Regulatory Guide 1.109: Difference between revisions

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{{Adams
{{Adams
| number = ML13350A285
| number = ML003740384
| issue date = 03/31/1976
| issue date = 10/31/1977
| title = 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.
| title = Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I
| author name =  
| author name =  
| author affiliation = NRC/OSD
| author affiliation = NRC/RES
| addressee name =  
| addressee name =  
| addressee affiliation =  
| addressee affiliation =  
| docket =  
| docket = WM-00011
| license number =  
| license number =  
| contact person =  
| contact person =  
| document report number = RG-1.109
| case reference number = -nr
| document report number = RG-1.109, Revision 1
| document type = Regulatory Guide
| document type = Regulatory Guide
| page count = 64
| page count = 86
}}
}}
{{#Wiki_filter:U.S. NUCLEAR REGULATORY COMMISSION                                                                                             March 1976 REGULATORY GUIDE
{{#Wiki_filter:Revision 1*
  OFFICE. OF STANDARDS DEVELOPMENT
                                    U.S. NUCLEAR REGULATORY COMMISSION                                                                               October 1977 REGULATORY GUIDE
                                                                                                                                      4,s.
                                    OFFICE OF STANDARDS DEVELOPMENT
                                                                    REGULATORY GUIDE 1. 09 CALCULATION OF ANNUAL DOSES TO MAN- FROM ROUTINE
      RELEASES OF REACTOR EFFLUENTS FOR TH


REGULATORY GUIDE 1.109                        "          "
==E. PURPOSE==
                            CALCULATION OF ANNUAL DOSES.,'TO MAN .fROM ROUTINE
OF EVALUATING COMPLIANCE WITH
RELEASES OF REACTOR EFFLUENTS FOR THE PU.!RPOSE OF EVALUATING COMPLIANCE WITH
                                                              10 CFR PART 50, APPENDIX I
                                                  10 CFR PART SO, APPENDIX I
                    ' USNRC REGULATORY GUIDES                                           Comments should be sent to the Secretary of the Commission. U.S. Nuclear Regu- Regulatoey Guides are issued to describe nd make available to th Public methods        latory Commission. Washington, D.C.       20555. Attention: Docketing and Service Branch.
                                                                              7.?
 
                                        \'~        *%~
acceptable to the NRC staff of implementing specific parts of the Commission's regulations, to delineate techniques used by the staff in evaluating specilic problems The guides are issued in the following ten broad divisions or postulated accidents, or to provide guidance to applicants. Regulatory Guides are not substitutes for regulations. and compliance with them is not required.        1. Power Reactors                           6. Products Methods and solutions different from those set out in the guides will be accept..      2. Research and Test Reactors                7. Transportation able if they provide a basis for the findings requisite to the issuance or continuance  3. Fuels and Materials Facilities            B. Occupational Health of a permit or license by the Conmission.                                              4. Environmental and Siting                 S.  Antitrust Review
                                              5- I
                                                                                        5. Materials and Plant Protection          10.  General Comments and suggestions for improvements in these guides are encouraged at all          Requests for single copies of issued guides (which may be reproducedl or for place times, and. guides will be revised, as appropriate, to accommodate comments and         ment on an automatic distribution list for single copies of future guides in specific to reflect new information or experience. This guide was revised as a result of         divisions should be made in writing to the U.S. Nuclear Regulatory Commission.
                  -~    ~
 
                      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
substantive comments received from the -public and additional staff review.              Washington. D.C.     20555, Attention: Director, Division of Document Control.
  ticularly useful in evaluating the need for an early revision                      206. Attention: Director. Office of Standards Development
 
*The      substantial number of.changes in this revision has made it impractical to indicate the changes with lines in the margin.
 
7


TABLE OF CONTENTS
TABLE OF CONTENTS
                                                                                                                                  Page  
                                                                                                                                            Page  


==A. INTRODUCTION==
==A. INTRODUCTION==
......................................................................                                        1.109-7
................................................................. 1.109-1


==B. DISCUSSION==
==B. DISCUSSION==
........................................................................                                       1.109-7
........................................................................                                             1.109-1


==C. REGULATORY POSITION==
==C. REGULATORY POSITION==
...............................................................                                      1.109-8
............                             .............................................. 1.109-2
    1.   Radiation Doses from Liquid Effluent Pathways.                                                 ..........................109-8 a.     Potable Water ...........................................................                                     1.109-8
        1.   Doses from Liquid Effluent Pathways ...........................................                                          1.109-2 a.   Potable Water ...........................................................                                           1.109-2 b.   Aquatic Foods.......................................................                                                 1.109-2 c.   Shoreline Deposits..................................................                                                 1.109-2 d.   Irrigated Foods .........................................................                                           1.109-3
          6.     Aquatic Foods ...........................................................                                    1.109-8 c.     Shoreline Deposits ....... ... ...........................................                                    1.109-8 d.     Irrigated Foods .........................................................                                     1.109-8
        2.   Gamma and Beta Doses from Noble Gases Discharged to the Atmosphere ...........                                           1.109-4 a.   Annual Gamma Air Dose from Noble Gas, Releases from Free-Standing Stacks More Than 80 Meters High.......................... ..................                                               1.109-4 b.   Annual Gamma Air Dose from All Other Gas Releases; Annual Beta Air Dose from All Noble Gas Releases .........................................                                                1.109-5 c.   Annual Total Body Dose from Noble Gas Releases from Free-Standing Stacks More Than 80 Meters High ................................................                                            1.109-5 d.   Annual Skin Dose from Noble Gas Releases from Free-Standing Stacks More Than 80 Meters High................                                                                     ........... 1.109-6 e.   Annual Total Body Dose from All Other Noble Gas Releases ................                                           1.109-6
    2.   Gamma and Beta Doses from Gaseous Effluents ..................................                                        1.109-10
              -f.   Annual Skin Dose from All Other Noble Gas Releases ......................                                           1.109-6
          a.      Gamma Air Dose Rates for Elevated Releases ..............................                                   1.109-10
        3.   Doses from Radioiodines and Other Radionuclides Released to the Atmosphere... .1.109-6.
          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
a.   Annual Organ Dose from. External Irradiation from Radionuclides Deposited onto the Ground Surface ................................................                                             1.109-7 b.   Annual Organ Dose from Inhalation of Radionuclides in Air ...............                                           1.109-7 c.   Annual Organ Dose from Ingestion of Atmospherically Released Radionuclides in Food ...................................................                                           1.109-7
    4.   Integrated Doses to the Population ...........................................                                       l.lO9-l1
        4.     Integrated Doses to the Population ...........................................                                           1.109-8
    5.   Summary of Staff Position..........................................1.109-14
        5.   Summary of Staff Position ....................................................                                            1.109-8


==D. IMPLEMENTATION==
==D. IMPLEMENTATION==
....................................................................                                       1.109-14 APPENDIX A, METHODS FOR CALCULATING DOSES TO MAN FROM RADIONUCLIDE DISCHARGES TO
....................................................................                                             1.109-8 APPENDIX A, METHODS FOR CALCULATING DOSES TO MAN FROM LIQUID EFFLUENT PATHWAYS .........                                             1.109-11
THE AQUATIC ENVIRONMENT ................................................................                                       1.109-17
        1.   Generalized Equation for Calculating Radiation Dose via Liquid Pathways ......                                           1.109-1.1 a.   Radionuclide Concentration in Environmental Media (Ci                                      ) .................     I..109-11 i              b.   Usage (U)                                 ..........................................                                 1.109-11 ap c.   Dose Factor (Daipj)               . .....................................................                           1.109-11
    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.     Equations for Liquid Pathways ................................................                                           1.109-12 a.   Potable Water.............................                                                                          1.109-12 b.  Aquatic Foods.......................................................                                                 1.109-12 c.   Dose from Shoreline Deposits .........................................                                               1.109-12 d.   Dose from Foods Grown on Land with Contaminated Water ...................                                           1.109-15 S REFERENCES FOR APPENDIX A......................................                                           ...................       1.109-18 iii
    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)
TABLE OF CONTENTS (Continued)
                                                                                                  Page
                                                                                                                              Page APPENDIX B, MODELS FOR CALCULATING DOSES FROM NOBLE GASES DISCHARGED TO THE
    1.   Annual Gamma Air Dose from Elevated Releases of Noble Gases ..................       1.109-39
ATMOSPHERE ..................................................                                 .........................   1.109-19
    2.   Annual Gamira Air Dose from Ground-Level Releases of Noble Gases and Annual Beta Air Dose ..............................................................      1 .109-40
      1.  Annual Gamma Air Dose from Noble Gas Releases from Free-Standing Stacks More Than 80 Meters High .....................................................                                   1.109-19-
    3.  Annual Dose to Tissue from Noble Gas Effluents ..............................         1.109-40
      2.   Annual Gamma Air Dose from All Other Noble Gas Releases and Annual Beta Air Dose from All Noble Gas Releases .........................................                                  1.109-20
          a.       Elevated Releases .......................................................   1.109-40
      3.  Annual Total Body and Skin Doses from Noble Gas Effluents ....................                                   1.109-20
          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
          a.        Releases from Free-Standing Stacks More Than 80 Meters High .............                              1.109-20
AND OTHER RADIONUCLIDES DISCHARGED TO THE ATMOSPHERE ...................................        1.109-45
          b.        All Other Releases ......................................................                             1.109-22 REFERENCES FOR APPENDIX B ...............................                                              .....................1.109-23 APPENDIX C, MODELS FOR CALCULATING DOSES VIA ADDITIONAL PATHWAYS FROM RADIOIODINES
    1.  Annual External Dose from Direct Exposure to Activity Deposited on the Ground Plane .................................................................        1.109-45
AND OTHER RADIONUCLIDES DISCHARGED TO THE ATMOSPHERE                                       ............................. 1.109-24
    2.  Annual Dose from Inhalation of Radionuclides in Air ..........................       1.109-46
      1.  Annual External Dose from Direct*Exposure to Activity Deposited on the                                                       ,
    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
          Ground Plane.                       ...................................................... 1.109-24
    4.
      2.  Annual Dose from Inhalation of Radionuclides in Air ..........................                                   1.109-25
 
      3.  Concentrations of Airborne Radionuclides in Foods........................1.109-25 a.         Parameters for Calculating Nuclide Concentrations in Forage, Produce, and Leafy Vegetables...............                                             ý ....................
c.       Parameters for Calculating Nuclide Concentration in Meat ................
                                                                                                                            1.109-25 b.         Parameters for Calculating Nuclide Concentrations in Milk ...............                              1.109-27 c.         Parameters for Calculating Nuclide Concentration in Meat ..............                               1.109-28
          Annual Dose from Atmospherically Released Radionuclides in Foods .............
      4.   Annual Dose from Atmospherically Released Radionuclides in Foods .............                                       1.109-28 REFERENCES FOR APPENDIX C.............................................................                                       1.109-29 APPENDIX D, MODELS FOR CALCULATING POPULATION DOSES FROM NUCLEAR POWER PLANT
                                                                                                1.109-59
EFFLUENTS ..............................................................................                                     1.109-30
                                                                                                1.109-59 I
       1.   General Expressions for Population Dose ......................................                                   1.109-30
REFERENCES FOR APPENDIX C..............................................................        1.109-60
      2..  Use of the Models ............................................................                                   1.109-33 a.        Population-Integrated Doses from Liquid Effluents .......................                             1.109-33 b.        Population-Integrated Doses from Airborne Effluents .................                                1.109-34 REFERENCE FOR APPENDIX D.......................................................                                            1.109-35 APPENDIX E, NUMERICAL DATA.FOR THE CALCULATION OF ANNUAL DOSES TO MAN FROM ROUTINE
APPENDIX D, MODELS FOR CALCULATING POPULATION DOSES FROM NUCLEAR POWER PLANT
RELEASES OF*REACTOR EFFLUENTS .........................................................                                    1.109-36
EFFLUENTS...............................................................................        1 .109-63
      1.    Environmental Data                                          .................................................  1.109-36
       1. General Expressions for Pý.pulation Dose ......................................       1.109-63
      2.    Human Data ..................................................................                                   1.109-36
    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
      3.    Dose Factors............................................................ 1.109-36
                                                                                        1.109-4
      4.  Other Parameters......................................................                                          1.109-43 REFERENCES FOR APPENDIX E                                      ....................................................        1.109-70
                                                                                      iv


TABLE OF CONTENTS (Continued)
TABLE OF CONTENTS (Continued)
                                                                                                                          Page
                                                                                                Page APPENDIX.F, METHODS FOR EVALUATING THE I FUNCTION ....................................... 1.109-72
    1.   Annual Gamma Air Dose from Elevated Releases of Noble Gases ..................                                1.109-39
        1.  Derivation of the I Function .................................................. 1.109-72
    2.  Annual Gamma Air Dose from Grjund-Level Releases of Noble.Gases and Annual Beta Air Dose ..............................................................                              1.109-40
        2.   Evaluation of the I Function .................................................. 1.109-75 REFERENCES FOR APPENDIX F................................................................. 1.109-80
    3.  Annual Dose to Tissue from Noble Gas Effluents ..............................                                1.109-40
     ,4      ;,v
          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
LIST OF TABLES
Table                                                                                                                       Page
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)
  1   Summary of Staff PosItion - Methods of Evaluating Compliance with Appendix I ............................................................                                                             ....   1.109-9 A-1   Bioaccumulation Factors To Be Used in the Absence of Site-Speciiic Data .......                                                               1.109-13 A-2  Shore-Width Factors for Use in Equations                                          (A-5),          (A-6), and (A-7) ..............             1.109-15 B-1  Dose Factors for Exposure to a Semi-Infinite Cloud of Noble Gases .............                                                               1.109-21 D-l   Recommended Values for the Transport Times in the Food Distribution System ....                                                                 1.109-32 E-1   Stable Element Transfer Data ..................................................                                                             . 1.109-37 E-2   Nuclide Transfer Parameters for Goat's Milk ...................................                                                               l.I09-38 E-3   Animal Consumption Rates .............................................                                                           ......     1.109-38 E-4-  Recommended Values for U a To Be Usedfor the Average Individual                                                      in lieu of Site-Specific Data .....                   .....................................................                                             1.109-39 E-5   Recommended Values for Uap To Be Used for the Maximum Exposed Individual                                                            in lieu of Site-Specific Data ...................................................                                                               1.109-40
        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                                            ..............................
E-6   External  Dose Factors for Standing on Contaminated Ground .....................                                                               1.109-41 E-7  Inhalation Dose Factors for Adults ............................................                                                               1.109-44 E-8  Inhalation Dose Factors for Teenagers ........................................                                                               1.109-47 E-9   Inhalation Dose Factors for Children .........................................                                                               1.109-50
                                                                                                                        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
E-l0  Inhalation Dose Factors for Infants .........................................                                                                 1.109-53 E-ll  Ingestion Dose Factors for Adults ............................................                                                               1.109-56 E-12  Ingestion Dose Factors for Teenagers ........................................                                                                 1.109-59 E-13  Ingestion Dose Factors for Children ..........................................                                                               1.109-62 E-14  Ingestion Dose Factors for Infants ...........................................                                                               1.109-65 E-15  Recommended Values for Other Parameters ......................................                                                               1.109-68 LIST OF FIGURES
0-1  Recommended Values to be Used for the Average Individual in Lieu of Site-Specific Data ..........................................................                                   1.109-64
Figure                                                                                                                                                  Page F-l      Staff-Written Computer.Listing .............................................                                                               1.109-76 F-2      Hamawi-Written Computer Listing .                                                                                                          1,109-78 vi
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.
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.


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


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,"
Portions of this guide supersede Regulatory Guide 1.42, Revision 1, "Interim Licensing Policy on as Low as Practicable for Gaseous Radioiodine Releases from Light-Water-Cooled Nuclear Power Reactors," which has been withdrawn.
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.
==B. DISCUSSION==
Appendix I to 10 CFR Part 50 provides guidance on the doses to members of the general public resulting from effluent releases that may be considered to be as low as is reasonably achievable. This guide describes basic features of the calculational models and assumptions in use by the NRC staff for the estimation of doses.


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.
Appendix A of this guide describes suggested models and assumptions for calculating the estimated doses to man from discharges to the hydrosphere. Appendix B of this guide describes suggested models and assumptions for calculating doses from noble gases discharged to the atmos- phere, and Appendix C.gives models and assumptions for estimating doses from radioiodines and other radionuclides released to the atmosphere. Appendix D describes the models and assumptions for calculating population doses (man-rem and man-thyroid-rem) from radionuclide releases to the atmosphere and hydrosphere. Appendix E presents tabular data pertaining to two or more of the other appendices.   Appendix F provides a discussion of, and derivation for, the I function used in computing gamma doses from elevated noble gas releases.


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.
In providing guidance for implementing Section II of Appendix I, the.NRC staff -has made use of the maximum exposed individual approach.       In this approach the numerical design objectives of Section II are compared to the calculated radiation exposures to maximum individuals in each of four age groups.


The 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.
The population is considered to be made up of infants (0 to 1 year), children (1 to 11 years),
teenagers (11 to 17 years), and adults (17 years and older).      For the purpose of evaluating dose commitment, the maximum infant is assumed to be newborn, the maximum child is taken to be 4 years old, the maximum teenager is taken to be 14 years old, and the maximum adult is-taken to be
17 years old.


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.
Maximum individuals are characterized as "maximum'" with -regard to food consumption, occupancy, and other usage of the region in the-vicinity of the plant site and as such represent individuals with habits representing reasonable deviations from the average for the population in general.


==B. DISCUSSION==
In all physiological and metabolic respects the maximum exposed individuals are assumed to have those characteristics that represent the averages for their corresponding age group in the general In this guide, the term "dose," when applied to individuals, is used instead of the more precise term "dose equivalent," as defined by the International Commission on Radiological Units and Measurements (ICRU).    When applied to the evaluation of internal'deposition of radioactivity, the term "dose," as used here, includes the prospective dose component arising from retention in the body beyond the period of environmental exposure, i.e., the dose commitment. The dose commitment is evaluated over a period of 50 years.
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).
11.109-I
                                                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.
population. Although specific individuals will almost certainly display dietary, recreational, and other living habits considerably different from those suggested here, and actual physiological and metabolic parameters may vary considerably, the NRC staff considers the maximum exposed individual to be a well-defined reference for implementation of Section II of Appendix I. The characterization of maximum exposed individuals is subject to continuing review by the NRC staff, and the applicant is encouraged to use information and data applicable to a specific region or site when possible. Where site-specific information and data is used, its justification should be documented for the NRC staff's review.


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.
Since the radiation dose commitment per unit intake of a given radionuclide usually varies as a function of-age, four sets.of internal dose conversion factors have been calculated. These dose factors are appropriate for the four different age groups defined above. Specifically, these dose factors are based on continuous intake over a one-year environmental exposure period and an associated dose commitment extending over a 50-year period from initiation of intake.


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


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.
As discussed in Section III.A.2 of Appendix I-to 10 CFR Part 50, the applicant may take intoaccount any real phenomena or actual exposure conditions.        Such conditions could include actual values for agricultural productivity, dietary habits, residence times, dose attenuation by'structures, measured environmental transport factors (such as bioaccumulation factors), or similar values actually determined for a specific site. The applicant should provide enough information on the measurements or other methods used to derive these substitute values to enable the NRC staff to evaluate their validity.


==C. REGULATORY POSITION==
==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.
Equations are provided below by which the NRC staff will estimate radiation exposure for maximum individuals and the population within 50 miles. These equations are appropriate for the exposure pathways that the staff routinely considers in its evaluations.        In addition, other exposure pathways that may arise due to unique conditions at a specific site should be considered if they are likely to provide a significant contribution to the total dose. A pathway is con- sidered significant if a conservative evaluation yields an additional dose increment equal to or more than 10 percent of the total from all pathways considered in this guide.
 
1.   Doses from Liquid Effluent Pathways The NRC staff will calculate radiation doses from potable water, aquatic food, shoreline deposits, and irrigated food pathways by using the following equations, which are described in detail in Appendix A of this guide.


a.     Potable Water MU1100
a.   Potable Water R   . : 1100 UapMp    Q 0ai pjexp(-Xitp)                                         (1)
                          M ,n R                         QiDaipjexp(-Xitp)                                       (1)
            apj            F      1ap b.   Aquatic Foods Ra      1100 UaFp  Q.B. 0D.exp(-it.)                               .          (2)
      b.   Aquatic Foods Raj'1100 UapM pn*                  -At2 I
            apj            F  1 1  p aipi          i p c.   Shoreline Deposits QiTiD        [exp(-Xitp)][l   exp(-t)                 (3)
            Rapi    1100    F      QiBipoaipjexp(-Aitp)                                     (2)
              apj == 110,000
      c.   Shoreline Deposits Wn 0
            Rap               Fp        1aipi          1pib
            Rapj = 110,000            I QiTiOai    [exp('Xitp)][l - exp(-'0t)]              (3)
                                                                  -
      d.    Irrigated Foods For all radionuclides except tritium:
                                                  1J09-2
               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;
d. Irrigated Foods For all radionuclides except tritium:                                  8 Frrr -    xp-I      )      fBv~      -  exp(-itb)]l R      = uveg    diexp(-thDaipj          --- Yv      Eite)]    +        '--  P    i    b api            .      .                        ev    rp("                      1r      b
        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;
                  + Uanimal      F ADaipj  Qd    p                  exp(AEite)]
       CiAw    is the concentration of radionuclide i in water consumed by animals, a:;sumed to be equal to Ciw (pCi/liter);
                    ap            IA aipjIQ F iexp    iXh)YvX
        Ciw    is the radionuclide concentration in water, in pCi/liter;
                  + fI Biv[  -  exp(-Aitb)]    +Ciaw                                                    (4)
      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);
        For tritium:
        di   is the deposition rate of nuclide i, in pCi/m2 per hr;
        R  .    vegC D          uanimalD    FA(CvQ  +  CQw)                                          (5)
          F   is the flow rate of the liquid effluent, in ft 3 /sec;
          apj      ap v apj + ap            api A VF        AwAw where B.        is the equilibrium bioaccumulation factor'for nuclide i in pathway p, expressed ip      as the ratio of the concentration in biota (in pCi/kg) to the radionuclide concentration in water (in pCi/liter),         in liters/kg;
          k  is the reciprocal of the body water volume (0.0041 liter-I for beef cattle and 0.0028 liter-I for dairy cattle);
            B.        is the concentration factor for uptake of radionuclide i from soil by edible v parts of crops, in pCi/kg (wet weight) per pCi/kg dry soil;
        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),
          CiAw       is the concentration of radionuclide.i in water consumed by animals,               in pCi/liter;
              dimensionless;
            Civ      is the concentration of radionuclide i in vegetation,             in pCi/kg;
          n  is the number of radionuclides that are to be considered;
        Daipj        is the dose factor, specific to a given age group a, radionuclide               i, pathway p, and organ j, which can be used to calculate the radiation dose from an intake of a radionuclide, in mrem/pCi, or-from exposure to a given concentra- tion of a radionuclide in sediment, expressed as a ratio of the dose rate (in mrem/hr) and the areal radionuclide concentration (in pCi/m 2 );
          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 ;
            di       is the deposition rate of nuclide i,       in pCi/m2 per hr;
        QAw   is the consumption rate of contaminated water by an animal, in liters/day;
              F     is the flow rate of the liquid effluent,         in ft 3 /sec;.
        QF   is the consumption rate of contaminated feed or forage by an animal,   in kg/day (net weight);
            fl      is the fraction of the year crops are irrigated, dimensionless;
          Qi is the release rate of nuclide i, in Ci/yr;
            FiA      is the stable element transfer coefficient that relates the daily intake rate by an animal to the concentration in an edible portion of animal product, in pCi/liter (milk) per pCi/day or pCi/kg (animal product) per pCi/day;
          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;
            M        is the mixing ratio (reciprocal of the dilution factor) at the point of exposure (or the point of withdrawal of drinking water or point of harvest of aquatic, food), dimensionless;',
      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;
                                                                                                  2
        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;
              P     is the effective 'surface density" for-sbil,. in kg(dry soil)/m QAw       is the consumption rate of contaminated water by an animal,               in liters/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;
            QF ,' is the consumption rate of contaminated feed or forage by an animal,                   in kg/day (wet weight);,
        tb    is the mid-point of the soil exposure time (15 years for a typical power reactor), in hours;
            /Qi     is the release rate of nuclide i,       in Ci/yr;
        te    Is the time period that crops are exposed to contamination during the growing season, in hours;
              r     is the fraction of deposited activity retained on-crops,               dimensionless;
                                        1.109-9
          Rap R         is the total annual dose to organ j of individuals of age group a from all of the nuclides i.in pathway p, in mrem/yr;
                                                  1.109-3


th      is a holdup time that represents the time interval between harvest and consumption of the food, in hours;
NU
              T      is the radioactive half life of nuclide i, in days;
                  tb      is the period of time for which sediment or soil is exposed to the contaminated water, in hours;
              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;
                  te      is the time period that crops are exposed to contamination during the growing season, 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);
                  th      is a holdup time that represents the time interval between harvest and consumption of the food, in hours;
                w    is the water intake rate via fresh forage (28 liters/day for beef cattle and
                  Ti      is the radioactive half life of nuclide i,     in days;
                      38 liters/day for dairy cattle);
                  t      is the average transit time required for nucli es to reach the point of exposure. For internal dose, tp is the total time elapsed between release of the nuclides and ingestion of food or water, in hours;
                W    is the shoreline width factor, dimensionless;
                Uap      is a usage factor that specifies the expos.,*oe time or intake rate for an individual of age group a associated with pathway p, in hr/yr, z/yr, or kg/yr;
              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"
                    W    is the shoreline width factor, dimer;sionless;
                      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);
                  Yv     is the agricultural productivity (yield),   in kg(wet weight)/m2 AEi     is the effective removal rate corn .]t for radionuclide i from crops, in hr where XEi= Xi + Xw , i is the rz-,)active decay constant, and Xw is the removal rate constant for physic,:      s by weathering (see Appendix E,
              Ai    is the radioactive decay constant of nuclide i,     in hr ,
                          Table E-15);
              AM    is the water elimination rate constant (0.32/day for beef cattle and 0.28/day for dairy cattle);
                          is the radioactive decay constant -:.r iuclide i, in hr-
            1100      is the factor to convert from (Ci/yr)/(ft 3 /sec)  to pCi/liter; and
                1100      is the factor to convert from (Ci/yr)i(ft 3 /sec)  to pCi/liter; and
        110,000      is the factor to convert from (Ci/yr)/(ft 3 /sec) to pCi/liter and to account for the proportionality constant used in the sediment radioactivity model.
            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.
These equ; ions yield the dose'rates to various organs of individuals from the exposure pathways mentio, ed above. Appendix I of 10 CFR Part 50 requires that the annual doses or dose commitments to the total body or any organ of any individual from the sum of the exposure path- ways from liquid effluents associated with each reactor should not exceed 3 mrem and 10 mrem, respectively.


2.    Gamma and Beta Doses from 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.
2.    Gamma and Beta Doses from Noble Gases Discharged to the Atmosphere The NRC staff will calculate radiation doses from noble gases using the following equations from Appendix B of this guide. Atmospheric dispersion models are found in Regulatory Guide 1.111,
  "Methods for Estimating Atmospheric Transport and Dispersion for Gaseous Effluents on Routine Releases from Light-Water-Cooled Reactors."
        a..    Annual Gamma Air Dose from Noble Gas Releases from Free-Standing Stacks More Than
                80 Meters High Dy(r,o)  r126          n  *U1n1 (Ek  Eki(H,u,S,az;Ek      QniAki6 n ns      k1 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,e)      is the annual gamma.air dose at a distance r (meters) in the sector at angle o, in mrad/yr;
                  Ek      is the energy of the kth photon energy group, in MeV/photon.


a.    Gamma Air Dose Rates for Elevated Releases
1.109-4
                        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;
fns      is the joint frequency of occurrence of stability class s and wind speed class n for sector O,_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.
I(H,u,s,az,Ek)         is the dimensionless numerical integration constant accounting for the distribution of radioactivity according to meteorological conditions of wind speed (u) and atmospheric stability (s) which in part determine the effective stack height (H) and the vertical plume standard deviation (az).ý In addition, I is a function of the photon energyEk and is T        Il + k12 as formulated in Slade (Appendix B, Reference 1);
              D
              Dni    is the release rate of radionuclide i, corrected for decay during transit to the distance r under wind speed un, in Ci/yr;
              un      is the mean wind speed of wind speed class n, in m/sec;
              60      is the sector width over which atmospheric conditionsare averaged,          in radians;
          Pa(Ek)      is the a.ir energy absorption coefficient for the kth photon energy group, in m-1; and
              260      is the conversion factor to obtain DY(r,e),    in mrad/yr, and has the units of mrad-radians-m3-disintegration/sec-MeV-Ci.


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);
b.   -Annual Gamma Air Dose from All Other Noble Gas Releases; Annual Beta Air Dose from All Noble Gas Releases DY(r,o) or DB(r,e) =.3.17 x 104-  Qi[x/Q]D(r,o)(DFi or. DFý)                 (7)
                'D
where DFý, DFý       are the gamma.and beta air dose factors for a uniform semi-infinite cloud of radionuclide i, in mrad-m 3/pCi-yr;
              Qn1      is the the releaser rate distance    under ofwind radionuclide i, corrected fnr decay during transit to speed un, in Ci/yr;
    DY(r,o) or D'(r,O)       are the annual gamma and beta air doses at the distance r in the sector at angle 0 from the discharge point, in mrad/yr;
                  r    is the distance from the release point to the receptor, in meters;
              Qi     is the release rate of the radionuclide i,     in Ci/yr;
                un      is the me;'n wind speed of wind speed class n, in m/sec;
   [x/Q]D (r,O)        is the annual average gaseous dispersion factor (corrected for radioactive decay) at the distance r in sector 0 in sec/m3 (see Regulatory Guide 1.111,
                AO      is the sector width over which atmospheric conditions are averaged, in radians;
                      "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-
                      and ua(Ek)      is the air energy absorption coefficient for the kth photon energy group, in m1 .
     3.17 x 104       is the number of pCi per Ci divided by the number of seconds per year.
      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)
c.    Annual Total Body Dose from Noble Gas Releases from Free-Standing Stacks More Than
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;
            80 Meters High T                      yT
         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;
            0 (r,o) = 1.11 SF   Dk(r,O)exp[-1Ja(Ek)td]                                     (8),
                                                    1.109-11
where DT (r,o)     is the annual total body dose at the distance r in sector 0, in mrem/yr;
         DY(r,0)      is the annual gamma air dose associated with the kth photon energy group at the distance r in sector E, in mrad/yr;
                                                  1.109-5


SF      is the attenuation factor that accounts for the dose reduction due to shielding provided by residential structures (0.7), dimensionless;
SF      is the attenuation factor that accounts for the dose reduction due to shielding provided by residential structures, dimensionless;
                  t      is the product of tissue density and depth used to determine a "whole-body"
              td      is the product of tissue density and depth used to determine a total body
                        exposure. This depth is 5 cm, which is equivalent to t = 5 g/cm2 ;
                                        2
            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.
                        dose, in g/cm
                                                                              2 VT(Ek)        is the tissue energy absorption coefficient, in cm /g; and
             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)
d.    Annual Skin Dose-from Noble Gas Releases from Free-Standing Stacks More Than 80 Meters Hig DS(rG)     1..11SFDY(r,G)   + 3.17 x 1044    Qi1 x/Q]D(r,e)DFSi                (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.
where DFSi        is the beta skin dose factor for a semi-infinite cloud of radionuclide i, which includes the attenuation by the outer "dead" layer of the skin, in mrem-m 3/pCi-yr; and DS(r,e)        is the annual skin dose at the distance r in sector e,   in mrem/yr.


All other parameters are as defined in preceding sections.
All other parameters are as defined in preceding paragraphs.


e.     Total Body Dose Rates from Ground-Level Releases D (r,e) = 1.11 SF
e.   Annual Total Body Dose from All Other Noble Gas Releases, DT(r,b) : SF
* xi(r,o)DFBi                                             (l0)
* xi(r,e)DFBi                                                       (10)
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);
where DFBi       is the total body dose factor for a semi-infinite cloud of the radionuclide i, which includes the attenuation of 5 g/cm2. of tissue, in mrem-m3 /pCi-yr;.
                                                                                                      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 .
          DT(r,o)'      is the annualtotal body dose due.to immersion in a semi-infinite cloud at.
All other parameters are as defined above.
 
the distance r in sector 0, in mrem/yr; and xi(r,e)        is.. the annual average ground-level concentration of.radionuclide i at'the distance r in sector e, in pCi/m3 All other parameters are as defined above.


f.     Skin Dose Rates from Ground-Level Releases D5 (r,0) = 1.11 SF *xi(r,e)DF     +  xi(rO)OFSi                            (1i)
f.   Annual Skin Dose from All Other Noble Gas Releases D5 (r,0) = 1.11 S      xi(r,O)DFI +     X1 (r,e)DFS                          (1 F1              1 where Ds(r,e)        is the annual skin dose due to immersion in a semi-infinite cloud at the distance r in sector 0, in mrem/yr.
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.
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.
3.     Doses from Radioiodines and Other Radionuclides* Released to the Atmosphere.
 
The NRC staff will calculate radiation doses from radioiodines and other radionuclides released to the atmosphere using the following equations from Appendix C of this guide.


i
Not including noble gases.
                                                  1.109-12


a.     External Irradiation from Activity Deposited onto the Ground Surface Dý(r,0) = 8760 SF      cG(r,o)DFG..
1.109-6
                                      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)
a.       Annual Organ Dose from External Irradiation from Radionuclides Deposited onto the Ground Surface DG(r,o)     8760 SF      C*(r,o)DFGi G                                                          (12)
where O (rO)          is the annual dose to organ      j of an individual in the age group a at location
where CG(r,e)           is the ground plane concentration of radionuclide i at distance r in sector e, in pCi/m2 DFG.         is  the open nuclide   i, infield mrem-mground
                *      CrO) due to inhalation of all radionuclides, in mrem/yr;
                                                       2      plane dose conversion factor for organ j from radio-
            DFA. ijaa    is  the inhalation dose factor for radionuclide i, organ j, and age group a, in mrem/pCi;
                                                        /pCi-hr;
                                                                                                3 Ra    is the annual air intake for individuals in the age group a, in m /yr; and
        DT(r,O)           is the annual dose to the organ j at location (r,e), in mrem/yr;
                                                                                                      3 xi(r,o)       is the concentration of radionuclide i in air at location (r,o), in pCi/m .
                  SF      is a shielding factor that accounts for the dose reduction due to shielding provided by residential structures during occupancy, dimensionless; and
      c.      Ingestion o   r    v            m          .FL            L    1)
              8760        is the number of hours in a year.
                  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
b.      Annual Organ Dose from Inhalation of Radionuclides in Air DA(r,e)    =  R                                                                      (3 ja            a = xi(r,O)DFAija a                  j                                                  (13)
where A(re)        is the annual dose to organ j of an individual in the age group a at location jar'              (r,e) due to inhalation, in mrem/yr;
            DFA..          is  the inhalation dose factor~for radionuclide i, organ j, and age group a, in mrem/pCi;
                  Ra      is the annual air intake for individuals in the age group a, in m3/yr; and..
        xi(r,e)            is the annual average concentration of radionuclide i in.air at location (r,e), in pCi/m 3 .
      c.-      Annual Organ Dose from Ingestion of Atmospherically Released Radionuclides in Food DDja (r,e) =    DFIaij[a91a f Cv(r,o) + UmCm(ro) + UFCF(rO) + ULf Ci(r,O              (14)
where Cv(r,D), CF(r,o),
CL(r,o),
1.


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.
C.(r,)
              1 are  the concentrations fruits,  and grains), milk,  of radionuclide  i in produce leafy vegetables,        (non-leafy-vegetables, and meat, respectively, at location (r, o), in pCi/kg or pCi/z;
            DD (r,o)      'isthe annual dose to the organ j of an individual in age group a from ja            ingestion of produce, milk, leafy vegetables, and meat at location (r,), in mrem/yr;
              DFlija      is the in       ingestion dose factor for radionuclide i, organ j, and age group a, mrem/pCi;
                f ,fz      are the respective fractions of the ingestion rates of produce and leafy vegetables that are produced in the garden of interest; and Uav  Umma'  Ua'F UaL    are the annual intake (usage) of produce, milk, meat, and leafy vegetables, respectively, for individuals in the age group a, in kg/yr or i/yr (equivalent to Uap).
                                                          1.109-7


5.  Summary of Staff Position A brief summary of the staff position on methods of evaluating compliance with Appendix I
4.    Inteqrated Doses to the Population The NRC staff will calculate integrated doses to the local population from all pathways discussed in Sections C.-l, 2, and 3. Because of the various conditions under which the equa- tions in Appendix D are used, they are not presented in this section. It is recommended that Appendix D be read for a detailed. discussion of the staff's models..
is presented in Table 1.
5.  Summary of Staff Position A brief summary of the staff position on methods of evaluating compliance with the numerical guides for design objectives of Appendix I is presented in Table 1. Methods of evaluating compliance with the cost-benefit provisions of Appendix I are addressed in Regulatory Guide 1.110,
'Cost-Benefit Analysis for Radwaste Systems for Light-Water-Cooled Nuclear Power Reactors."


==D. IMPLEMENTATION==
==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.
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.
This guide reflects current Nuclear Regulatory Commission practice. Therefore, except in those cases in which the license applicant or licensee proposes an acceptable alternative method, the method described herein for complying with specified portions of the Commission's regulations is being and will continue to be used in the evaluation of submittals for operating license or construction permit applications until the guide is revised as a result of suggestions from the.
 
public or additional staff review.
 
1.109-8


II
w
                                                                                                  I
                                                                                                                                                              -*~-<~
                                              1.109-14
                                                                            TABLE 1 SUMMARY OF STAFF POSITION -
                                                        METHODS OF EVALUATING COMPLIANCE WITH APPENDIX I
                                            APPENDIX I*                              RM-50-2              POINT OF DOSE                    EQUATIONS
  TYPE OF DOSE                          DESIGN OBJECTIVES                    DESIGN OBJECTIVES*          EVALUATION                      TO BE USED
  Liquid Effluents Dose to total body                  3 mrem/yr per unit                    5 mrem/yr per site        Location of the                  1, 2, 3, 4, & 5 from all  pathways                                                                                  highest dose offsite.**
            I
    Dose to any organ                  10 mrem/yr per unit                  5 mrem/yr per site        Same as above.                    1, 2, 3, 4, & 5 from all pathways Non-tritium releases                                                      5 Ci/yr per unit
0
  Gaseous Effluents***
'.
                                                                                                          Location of the                  6 or 7, as Gamma dose in air                  10 mrad/yr per unit                    10 mrad/yr per site highest dose offsite.&#xf7;            appropriate Beta dose in air                    20 mrad/yr per unit                  20 mrad/yr per site      Same as above.                    7 Dose to total body                  5 mrem/yr per unit                    5 mrem/yr per site        Location of the                  8 or 10, as of an individual                                                                                    highest dose                      appropriate offsite.**
    Dose to skin of an                  15 mrem/yr per unit                  15 mrem/yr per site      Same as above.                    9 or 11, as individual                                                                                                                            appropriate See footnotes at end of table, on following page.


TABLE 1 SUMMARY OF STAFF POSITION -
-v        --~*-.--~~ -- ---        --      --      ------ -
                        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.
TABLE 1 (Continued)
                                                    SUMMARY OF STAFF POSITION*-
                                        METHODS OF EVALUATING COMPLIANCE WITH APPENDIX I
                                APPENDIX I*                          RM-50-2                    POINT OF DOSE            EQUATIONS
TYPE OF DOSE                  DESIGN.OBJECTIVES                DESIGN OBJECTIVES*                EVALUATION              TO BE USED
Radioiodines and Particulates      Released tothe.Atmosphere Dose to any organ          15 mrem/yr per unit              15 mrem/yr per site              Location of the      12, 13, & 14 from all pathways                                                                              highest dose offsite...++
  1-131 releases                                              1 Ci/yr per unit                      - - - -                - - -  -
    Evaluated for a maximum individual,  as described in Section B of this guide.


Evaluated at a location that could be occupied during the term of plant operation.
Evaluated at a location that is anticipated to be occupied during plantlifetime or evaluated with respect to such potential land and water usage and food pathways as could actually exist during the term of plant operation Calculated only for noble gases.


Doses due to carbon-14 and tritium intake from terrestrial food chains are included in this category.
tEvaluated at a location that could be occupied during the term of plant operation.


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


1.109-15
tttEvaluated at.a location where an exposure pathway and dose receptor actually exist at the time of licensing. However, if the applicant determines design objectives with respect to radioactive iodineon the basis of existing conditions and if potential changes in land and water usage and food pathways could result in exposures in excess of the guideline values given above, the applicant should provide reasonable assurance that a monitoring and surveillance program will be performed to determine:
    (1) the quantities of radioactive iodine actually released to the atmosphere and deposited relative to those estimated in the determination of design objectives; (2) whether changes in land and water usage and food pathways which would result in individual.exposures greater than originally estimated have occurred; and (3) the content of radioactive iodine in foods involved in the changes,'if and when they occur.


APPENDIX A
APPENDIX A
                          METHODS FOR CALCULATING DOSES TO MAN FROM RADIONUCLIDE
                    METHODS FOR CALCULATING DOSES TO MAN FROM LIQUID EFFLUENT PATHWAYS
                                  DISCHARGES TO THE AQUATIC ENVIRONMENT
      The equations for estimating radiation exposureto man from four principal exposure path- ways in the aquatic environment (potable water, aquatic foods, shoreline-deposits, and irrigated foods) are listed in Section C, "Regulatory Position," of this guide.
      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.    Generalized Equation for Calculating Radiation Dose via Liquid Pathways.
 
Equation (A-l) is the generalized equation for calculating the radiation dose to man via liquid effluent pathways.
 
Raipj    Cip UapD aipj                                                            (A-1)
where C.        is the concentration    of nuclide i in the media of pathway p, in pCi/x, pCi/kg, or pCi/m 2 ;
                                                                                              pathway p, Daipj alp,        is and the dosej. factor, organ      It represents    to age specific the  dose group due toa, the intake of i, radionuclide a radionuclide, in mrem/pCi, or from exposure to a given concentration of a radionuclide in
                                                                2
                        'sediment, in mrem per hr/pCi per m R . .        is the annual dose to organ j of an individual of age group a from nuclide i alp,]      via pathway p, in mrem/yr; and is the  exposure  time or Z/yr intake                  associated with pathway p for Uaap      age  group  a, in hr/yr,        or rate kg/yr (usage)
                                                                    (as appropriate).
      The three factors, making up Equation (A-l) are discussed in the following sections, most of which were taken directly from the WASH-1258 report (Ref. 1). (An updated version of the portion of the WASH-1258 report describing models and computer programs is contained in the. BNWL-1754 report (Ref. 2).)
      a.    Radionuclide Concentrationin Environmental Media (Cip)
            The concentrations in environmental media of interest can be estimated from the mixing ratio Mp,  the discharge flow F, the radionuclide release rate Qi' and other terms presented in.
 
*the pathway equations that appear later in this discussion..
      b.    Usage (U      Y.
 
The second term of Equation.(A-l) is the usage term Ua.              Usage is expressed as a ap- consumption rate in kg/yr or liters/yr or as an exposure time in hr/yr, as appropriate for the pathway and age group under consideration.
 
The NRC staff encourages the use of site-specific data, whenever possible. Such data should be documented.        In the absence of site-specific data, however, the usage values (consumption rates and exposure times) presented in Appendix E, Table E-5, are recommended.
 
c.  Dose Factor (Daipj Dose factors for internal exposure via ingestion are provided in Appendix E, Tables E-ll,
  12, 13, and 14. Appendix E also provides further discussion of the data, models, and assumptions used.
 
Material deposited from sedimentation in an aquatic system represents a fairly large, nearly uniform thin sheet of contamination. The factors for converting surface contamination given in pCi/m2 to the dose rate at one meter above a uniformly contaminated plane have been described by Soldat and others (Refs. 3 and 4). Dose factors for exposure to soil sediment have units of mrem/hr per pCi/m2 and are presented in Appendix E, Table E-6.
 
1.109-11
 
2.    Equations for Liquid Pathways This section develops the equations required for the liquid pathway models. The principal difference between pathways is the manner in which the radionuclide concentrations are calculated.
 
The doses from the four pathways should be added to determine the total dose.
 
a.  Potable Water The annual dose from ingestion of water is calculated from Equation (A-2) below:
          Rapj  = 1100 MpF
                          Ua- aP* Qia pjeXp(-,t p)                                          (A-2)
Symbols for this equation were defined earlier, in Section C.l of this guide.
 
The summation process adds the dose contribution from each nuclide to yield the total dose for the pathway-organ combination selected. The expression (1100 QiM p/F)exp(-xit p) yields the concentration of nuclide i at the time the water is consumed, in pCi/X. This concentration is the term Cip in Equation (A-l). As a minimum, the transit time tp may be set equal to 12 hours to allow for radionuclide transport through the water purification plant and the water distribution system (Ref. 5).    The transit time should be increased as appropriate to: allow for travel from the point of effluent release to the water purification plant intake.      Credit may be taken for radionuclide removal by water purification processes using techniques such as those outlined in Reference 3.
 
It should be noted that, depending on the.hydrological dispersion model employed, the- mixing ratio, Mpor.dilution factor may not be explicitly defined.        In those instances (e.g.:,
buildup of activitykin a cooling pond), the relative concentration in the mixed stream (comparedc to the effluent co,6centration) may be supplied as a function of the radiological decay constant, with any potential' effl'uent recycling taken into account. Suggested hydrological dispersion models are presented in Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I."
      b.  Aquatic Foods The concentrations'of radionuclides in aquatic foods are assumed to be directly related to the concentrations of the nuclides in water.      Equilibrium ratios between the two concentrations, called bioaccumulation factors in this guide,.can be found in the literature (Ref. 6). The inclusion of the bioaccumulation factor Bip in Equation (A-2) yields Equation (A-3), which is suitable for calculating the internal dose from consumption of.aquatic foods.
 
U M
          Rapj  =1100    F  . QiBipD ai pjexp(-itp)                                .    (A-3)
Values of Bip are given in Table A-l; the other. parameters have been previously defined. The methodology presented in Reference 7 for the development of site-specific freshwater bioaccumula- tion factorsis considered to-be acceptable by the NRC staff.
 
The transit time tp may be set equal to 24 hours* to allow for radionuclide decay during transit through the food chain, as well as during food preparation.
 
c.    Dose from Shoreline Deposits The calculation of individual dose from shoreline deposits is complex since it involves estimation of sediment load, transport, and concentrations of radionuclides associated with Here, and in a number of other instances, the NRC staff has found it necessary to set forth guidance as to a parameter value in the absence ofempirical data.      In such instances judgments have been made after considering values assumed by others and model sensitivity to the parameter value in question. In this particular instance, the total body dose from fish ingestion, for a typical situation, was found to vary by less than a factor of two for a range of environmental transit times of from one to seven days.
 
1.109-12
 
TABLE A-1 BIOACCUMULATION FACTORS TO BE USED IN THE ABSENCE OF SITE-SPECIFIC DATA
                              (pCi/kg per pCi/liter)*
                            FRESHWATER                        SALTWATER
ELEMENT                FISH      INVERTEBRATE              FISH    INVERTEBRATE
H                    9.OE-01          9.OE-01          9.OE-OI          9.3E-C;
C                    4. 6E 03        9.1E 03          1.8E 03          1.4- 03 NA                      OE 02        2.OE 02          6.7E-02          1 9E-O1 P                      OE 05        2.OE 04          2.9E 04          3.OE .04 CR                  2.OE 02          2,OE 03          4.OE 02          2.OE 03 MN                  4. OE 02        9.OE 04          5.5E 02          4.OE 02 FE                  1.OE 02          3.2E 03          3.OE 03          2.OE 04 CO                  5. OE 01        2.OE 02          l.OE 02          1.OE 03 NI                  1.OE 02          1.OE 02          l.OE 02          2.5E 02 CU                  5. OE 01        4.OE 02          6.7E 02          1.7E 03 ZN                  2. OE 03    "    .OE 04          2.OE 03          5.OF,01 BR                  4. 2E 02    "\ 3.3E 02            1.5E-02          3.1E 00
RB                  2. OE 03i      *1.OE 03          8.3E 00          1.7E 01 SR                  3. OE 0i        l.OE 02          2.OE 00          2.OE 01 Y                    2. 5E 01        l.OE 03          2.5E 01          1.OE 03 ZR                  3.3E 00          6.7E 00          2.OE 02          8.OE 01 NB                  3. OE. 04        l.OE 02          3.OE 04          l.OE 02 MO                  4. OE 01        1.OE 01          l.OE 01          1.OE 01 TC                  1.5E 01          5.OE 00          l.OE 01          5.OE 01 RU                  2. OE 01        3.OE 02          3.OE 00          1.OE 03 RH                  1.OE 01          3.OE 02          l.OE 01          2.OE 03 TE**                4. OE 02        6.1E 03            1.OE 01          l.OE 02 I                    1.5E 01          5.OE 00.          l.OE 01          5.OE 01, CS                  2. OE 03        l.OE 03****      4.OE 01          2.5E 01 BA                  4. OE 00        2.OE 02          l.OE 01          1.OE 02 LA                  2. 5E 01        l.OE 03            2.5E 01.        l.OE 03 CE                  1.OE 00          1.OE 03            l.OE 01        6.OE 02 PR                  2. 5E 01        l.OE 03          2.5E 01          1.OE 03 ND                  2. 5E 01        l.OE 03            2.5E 01        1 .OE 03 W                    1.2E 03          l.OE 01            3. OE 01        3. OE 01 NP                  1.OE 01          4.OE 02          I. OE 01        1. OE 01 Values in Table A-1 are taken from Reference 6 unless otherwise indicated.
 
Data taken from Reference 8.
 
Data taken from Reference 7.
 
1 .109-13 Iii iiI
 
suspended and deposited materials. One method of approaching this problem was presented in the Year 2000 Study (Ref. 3).        Based on this model, an estimate of the radionuclide concentration in shoreline sediments can be obtained from the following expression:
            C.s  = Kc Ciw[l - exp(-Aitb)]                                                        (A-4)
            Cis =i where Cis        is.the concentration of nuclide i in sediment,      in pCi/kg;
              Ciw        is the concentration of nuclide i in water adjacent to the sediment,          in pCi/liter;
                K        is an assumed transfer constant from water to sediment,      in liters/kg per hr;
                tb        is the length of time the sediment is exposed to the contaminated Water, nominally 15 years (approximate midpoint of facility operating life), in hours; and A.        is the decay constant* of nuclide i, in hours-l.        In the original evaluation of the equation, xiwas chosen to be the radiological-decay constant. The true value should include an as yet unknown "environmental"      removal constant.
 
The value of Kc was derived for several radionuclides by using data from water and sediment samples collected over a period-of several years.in the Columbia River between Richland, Washington,..and the river mouth and in Tillamook Bay, Oregon, 75 km south of the river mouth (Refs. 9 and 10).      Since the primary use of the equation is to facilitate estimates of the exposure rate from gamma.iemitters one meter above the sediment, an effective surface contamina- tion was estimated. This surface contamination was assumed to be contained within the top 2.5 cm (1 in.) of sediment (with a mass of 40 kg/m 2 of surface).          The dose contribution from the radionuclides at depths below 2.5 cm was ignored. The resulting equation is Si  =  lOOTiCiwW[l  - exp(-xitb)]                                                    (A-5)
where Si        is the "effective" surface contamination,      in.pCi/m2 , that is used in subsequent calculations;
                Ti        is the radiological half-life of nuclide i,      in days;
                  W      is a shore-width factor that describes the geometry of the exposure; and
              100        is equal to [Kc (/kg-hr)*40(kg/m2)*    24(hr/day)/0.693],  in      -/m2-day.
 
Shore-width factors were derived from experimental data (Ref.. 11) and are summarized in Table A-2.    They represent the fraction of the dose from an infinite plane source that is estimated for these shoreline situations.
 
The combination of Equations (A-4) and (A-5) into the general Equation (A-l) leads to Equation (A-6) below for calculation of radiation dose from exposure to shoreline sediments.
 
Rapj    = Uap        aipj i.D    =  100 UapW    C Ti Daipj[l - exp(-xitb)]                  (A-6)
As in the development of Equation (A-2),           the expression (1100 Qi Mp/F)exp(-it p) may be substituted for C .    This results in the following relationship:
            Rap    = 110,000 ap p        QiTiDipj[exp(-xitp)]El - exp(_xitb)]                    (A-7)
            apj                  F    1    1aip                            tb)p If the presence of a radionuclide in water and sediment is controlled primarily by radioactive equilibrium with its parent nuclide, the water concentration and decay constant of the parent should be used in Equations (A-4) and (A-51.
 
1.109-14
 
TABLE A-2 SHORE-WIDTH FACTORS FOR USE IN EQUATIONS (A-5),    (A-6),  AND (A-7)
                    EXPOSURE SITUATION                      SHORE-WIDTH FACTOR, W
                  Discharge canal bank-                                0.1 River shoreline                                      0.2 Lake shore                                          0.3
                .Nominal  ocean site                                  0.5 Tidal basin                                          1.0
      d.  Dose from Foods Grown on Land with Contaminated Water The equations in the following paragraphs can be used to calculate doses from radio- nuclides released in liquid effluents but appearing in crops or animal products. Separate expressions are presented for tritium because of its unique environmental behavior.
 
(1)    Vegetation The concentration of radioactive material in vegetation results frol deposition onto the plant foliage and from uptake from the soil of activity deposited on the ground. The model, used for estimating the transfer of radionuclides from irrigation water to crops through water deposited on leaves and uptake from soil was derived for-a study of the potential doses to people from a nuclear power complex in the year 2000 (Ref. 3).
                  The equation for the model (for radionuclides except tritium) is presented below in slightly modified form. The. first term in brackets relates to the concentration derived from direct foliar deposition during the growing season. The second term relates to uptake from soil and reflects the long-term deposition during operation of the nuclear facility. Thus, for a uniform release rate, the concentration Civ of radionuclide i in the edible portion of crop species v, in units of pCi/kg,"is given by:.
          Civ  cidX
                  d [r[l    -  v exp(-xEite)] +f  I            ibv[I
                                                                iY  _ex (_ ith        -    Cexp(-x
                                                                                            ;(A-8)
                            L  YvAEi                    P1          J
where the terms are defined in Section C, "Regulatory'Position."        Appendix E, Table E-15, presents suggested values-for the parameters r, Yv' te' P, and th. Values for Biv are in Table E-l.
 
The deposition rate, di,  from irrigated water is defined by the relation di  = Ciw I (water deposition).                                              (A-9)
where Ciw      is the concentration of radionuclide i in water used for irrigation, in pCi/liter, and I      is the average irrigation rate, in liters/m2 /hr,    during the growing season.
 
For a cow grazing on fresh forage, te in Equation (A-8)    is set equal to 720 hours
(30 days), the typical time for a cow to return to a particular portion of the grazing site (Refs. 3 and 12).
                  For tritium, the equation for estimating Civ is (see Ref. 13):
                      Cv = Cw                                                              (A-10)
                                                  1.109-15
 
Jull
                      (2)    Animal Products The radionuclide concentration in an animal product such as meat or milk is dependent on the amount of contaminated feed or forage eaten by the animal and its intake of contaminated water.          The radionuclide concentration in animal products CiA in terms of pCi/liter or pCi/kg is proportional to the animal's intake of the radionuclide in feed or forage (sub- script F) and in water (subscript w):
                      CiA = F iA[CiFQF +              Q                                                                (A-ll)
                            The second set of terms in the brackets in Equation (A-1l)                    can be omitted if the animal does not drink contaminated water.                    Values for QF and QAw are presented in Appendix E,
        Table E-3.      Values for Biv and FiA are given in Appendix E, Table E-l.*
                      (3)    Total Dose from Food Grown on Land The total dose Rapj from irrigated foods and animal                  products (excluding tritium)
          is given by:
                              R UY~g    C D              Uanimal          D
                      Rapj = u~ p          iv aipj          ap      !    iA aipj                                      (A-12)
                            If values for Civ from Equation (A-8) and CiA from Equation (A-11)                    are substituted in Equation (A-12):
                                uveg      dFril                            - exp(-Ei te)]    flB[iv[  - exp(-Aitb)]1 Rapi        ap      d exp(ith)Daipj                    Yv XEi        +          PXi            .
                                    + u animal        FQ          Lxp-Ei d                rp -            e)
                                    +  ap        !  FiADaipj      Fd iexp(-ith          YvXEi fB    f [1 --exo(-x    t )
                                                        x{*t)_CiAwQAwj PXi[                                                              (A-13)
                                    +    I iv                *i b      CAAW
        where the terms are defined in Section C, "Regulatory Position."
                            It should be noted that the two components of Equation (A-12) imply that contribu- tions from the-individual vegetable and animal products have already been summed.                          In actual.
 
use, it will be necessary to compute separately the milk and meat portions of the dose due to animal products (also applicable to Equation (A-16)).
                            For tritium, the concentration                in animal products    (milk or meat)  is given by the following equation:
                    CA = Fa(CvQF + CAwQAw)                                                                            (A-14)
        where the terms are defined in Section C, "Regulatory Position."
                            Since by Equation (A-la)            Cv  =  C  ,  and since for all practical    purposes CAw = CW,
        Equation (A-14) can be restated as follows:
                    CA = FAC w(QF +QAw)                                                                              (A-15)
    S i *i Values for F.  iA appear as Fm and Fff in Table E-l.
 
1.109-16 IiIi
 
Similarly, the above equations for tritium concentration can be combined with the general Equation (A-1):
                                                                                    (A-16)
          R
          apj
                =vegCD
                  ap v apj
                            + uanimalc ap      ADapj
                                              1.109-17
 
REFERENCES FOR APPENDIX A
        1. "Final Environmental Statement Concerning Proposed Rule Making Action:- Numerical Guides for Design Objectives and Limiting Conditions for Operation to Meet the Criterion 'As Low As Practicable' for Radioactive Material in Light-Water-Cooled Power Reaictor Effluents,"
            USAEC Report WASH-1258, Washington, D.C., July 1973.
 
2.  J. K. Soldat et al., "Models and Computer Codes for Evaluating Environmental Radiation Doses," USAEC Report BNWL-1754, Pacific Northwest Laboratories, February 1974.


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


aipj   C ip Uap aipj                                                        (A--)
4.   J. K. Soldat, "Conversion of Survey Meter Readings to Concentration (iJCi/m 2 )," Item 04.3.4 in "Emergency Radiological Plans and Procedures," K. R. Heid (ed.), USAEC Report HW-70935, Hanford Laboratories, 1962.
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;&#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)
*5.   D. H. Denham and J. K. Soldat, "A Study of Selected Parameters Affecting the Radiation Dose from Radionuclides in Drinking Water Downstream of the Hanford Project," Health Physics, Vol. 28, pp. 139-144, February 1975.
            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.*
6.  S. E. Thompson et al., "Concentration Factors of Chemical Elements in Edible Aquatic Organisms," USAEC Report UCRL-50564, Rev. 1, Lawrence Radiation Laboratory, October 1972.
  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
7.   H. A. Vanderploeg et al., "Bioaccumulation Factors for Radionuclides in Freshwater Biota,"
            ORNL-5002, Oak Ridge, Tenn., November 1975.


TABLE A-I
8.  G. G' Kilaugh and L. R. McKay, "A Methodology for Calculating Radiation Doses from Radio-*
                                      DEFINITION OF POINTS AT WHICH CONCENTRATIONS IN ENVIRONMENTAL MEDIA (C ip)
             activity Released to the Environment," ORNL-4992, Oak Ridge National Laboratory, Oak Ridge, Tenn., March 1976.
                                                                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.
9... J. L Nelson, "Distribution of Sediments and Associated Radionuclides in the Columbia River below Hanford," p. 3.80 in "Hanford Radiological Sciences Research and Development Annual Report for 1964," D. W. Pearce and J. K. Green (eds.), USAEC Report BNWL-36, Pacific Northwest Laboratories, 1965.


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


TABLE A-2 RECOMMENDED VALUES FOR Uap TO BE U SED FOR THE MAXIMUM
11.   "Handbook of Radiological Protection, Part I: Data," prepared by a panelof the Radioactivity Advisory Committee.(H. J. Dunster, Chairman)., Department of Employment, Department of Health and Social Security, Ministry of Health and Social Services, Northern Ireland, Number SNB 11-360079-8, Her Majesty's Stationery Office, London, England, 1971.
                        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.
12.. J. J. Koranda, "Agricultural Factors Affecting the Daily Intake of Fresh Fallout by Dairy Cows," USAEC Report UCRL-12479, 1965.


CAn additional category of maximum individual (1-yr old) should be added for these pathways.
13.  L. R. Anspaugh et al., "The Dose to Man via Food-Chain Transfer Resulting from Exposure to Tritiated Water Vapor," in Tritium (A. A. Moghissi and M. W. Carter, eds.),
            CONF-710809, 1973.


Consumption rates are the same as the child's.
1.109-18 ti 1/4..
 
APPENDIX B
                                        MODELS FOR CALCULATING DOSES FROM
                                      NOBLE GASES DISCHARGED TO THE ATMOSPHERE
          The following analytical models are used for calculating doses from exposure to noble gases discharged to the atmosphere. Separate models are given for air and tissue doses due to gamma and beta rays.      Except for the case of noble gas doses resulting from elevated releases, all models assume immersion in a semi-infinite cloud.


dConsumption rate for adult obtained by averaging data from References 4, 6-9 and age-prorating using techniques contained in Reference 4.
1.    Annual Gamma Air Dose* from Noble Gas Releases from Free-Standing Stacks More Than 80 Meters Hih:
          Slade (Ref. 1) describes a derivation of equations for estimating annual air doses from photon emitters dispersed in the atmosphere.        The following expression can be used for calculating annual doses:
*i!                      ~260                                              D
                DY(r,e)    =  2--0    U-    fns
* 1*a(Ek)Ekl(HusozEk)      QniA                (B-l)
                                    n n s      k                          nk Symbols for this equation were defined earlier, in Regulatory Position C.2.a of this guide.


eData obtained directly from Reference 4.
A discussion of, and derivation for, the I function are presented in Appendix F of this guide.


fData obtained directly from Reference 15.
The photons are combined into energy groups, and each photon intensity within a group is weighted by its energy and energy absorption coefficient. Thus, the effective fraction of disintegrations of the nuclide i yielding photons corresponding to the photon energy group k, Aki, is determined to be Aki    = X [AmEma(Em)]/[Ekla(Ek)]                                              (B-2)
                        m where A        is the fraction of the disintegrations of nuclide i yielding photons m      .of energy Em;
                    Em      is the energy of the mth photon within the kth energy group, in MeV; and Wa (Em)        is the energy absorption coefficient in air associated with the photon energy Em, in m All other parameters are as previously defined. The summation is carried out over all photons-within.energy group k. Data for the photon energies and abundances for most of the noble gas nuclides were taken from Reference 2. For radionuclides not contained in Reference 2, data were obtained from Reference 3.


glnhalation rate for infant obtained by averaging data from References 10-14.
Decay during travel from the point of release to the receptor is Qni    Qi exp(-xir/un)
                        Q                                                                      (B-3)
    ., The term "gamma.air dose" refers to the components of the air dose associated with photons emitted during nuclear and atomic transformations, i.e., gamma and x-rays. Annihilation and bremsstrahlung photon radiations are possible contributors to this component of the air dose.


1.109-19
1.109-19


C.    Dose Factor (Daip.)
where Qi    is the initial release rate of nuclide i,  in Ci/yr;
            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.
                r    is the distance from the source to the receptor, in m; and is the decay constant of nuclide i,        -I
              Xi                                          in sec All other parameters are as previously defined.
 
2.    Annual Gamma Air Dose from All Other Noble Gas Releases and Annual Beta Air Dose* from All Noble Gas Releases Plumes of gaseous effluents are considered semi-infinite in the case of ground-level noble gas releases. The annual average ground-level concentration of radionuclide i at location (r,e)
is. determined from xi(r,e)  = 3.17 x 104 Q[x/Q] D(r,e)                                        (8-4)
where x.(r,e)     is the annual average ground-level concentration of nuclide i at the 3 distance r in the sector at angie e from the release point, in pCi/mi , and
      [x/Q]D(r,e)     is the annual average gaseous dispersion factor (corrected'for radioactive decay) in the sector at angle ,3it the distance r from the release point, in sec/m 3 . (See Regulatory Guide 1,111 for atmospheric dispersion models.)
      All other parameters are as previously defined.
 
The associated annual gamma or beta air dose is then D'(r,e) or D6 (r,e)   =
* xi(re)(DFi or DF)                                  (B-5)
where the terms are as~defined in Regulatory Position C.2.b.
 
Table B-1 presents a tabulation of the dose factors for the noble gases of interest.
 
3.    Annual Total Body and Skin Doses from Noble Gas Effluents It is also necessary to determine annual doses to real individuals in unrestricted areas.
 
The staff computes the total body dose from external radiation at a depth of 5 cm into the body and the skin dose at a depth of 7 mg/cm2 of tissue (Ref. 4).**
      a.  Releases from Free-Standing Stacks More Than 80 Meters High The annual total body dose is computed as follows:
          DT(r,e) =  1.11 x SF I DY(r,O)exp[-T(Ek)td1                                  (B-6)
  The term "beta air dose" refers to the component of the air dose associated with particle emissions during nuclear and atomic transformations, i.e., o+, B-, and conversion electrons.
 
See discussion in Appendix E, Section 3.


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.
1.109-20


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.
TABLE B-I
        DOSE FACTORS FOR    EXPOSURE TO A SEMI-INFINITE    CLOUD OF NOBLE GASES
Nucl ide      B-air*(DF )      B-Ski n* * (DFSi)    y-Air*(DFW)        y-Body**(DFBi)
Kr-83m      2. 88E-04                                  1 93E-05              7. 56E-08 Kr-85m      1. 97E-03            1 46E-03              I 23E-03              1.1 7E-03 Kr-85        1 .95E-03            1 34E-03              1 72E-05              1.61 E-05 Kr-87        1 .03E-02            9.73E-03              6.1 7E-03            5.. 92E-03 Kr-88        2. 93E-03            2. 37E-03              1. 52E-02            1 .47E-02 Kr-89        1 .06E-02            1 .OIE-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              9.1 5E-05 Xe-1 33m    1 . 48E-03          9. 94E-04              3.27E-04              2.551 E-04 Xe-1 33      1 . 05E-03            3.06E-04              3.53E-04              2.94E-04 Xe-1 35m    7. 39E-04            7.11 E-04            3.36E-03              3.12E-03 Xe-i 35.    2. 46E-03            1 86E-03              1 92E-03              1 .81E-03 Xe-i 37      1 . 27E-02            1 22E-02              1 51 E-03            1 .42E-03 Xe-i 38      4. 75E-03            4.13E-03              9.21 E -03            8.83E-03 Ar-41        3. 28E-53            2.69E-03              9. 30E-03            8.84E-03
  *        3 mrad-m pCi-yr
**        3 mrem-m pCi-yr
    2.88E-04  =  2.88 x 1O0
                                            I .109-21


A set of dose factors for 45 radionuclides was originally calculated for the year 2000
Symbols for this equation are defined in Regulatory Position C.2.c of this guide. The factor SF accounts for the dose reduction provided by the shielding effect of typical residential structures (see Appendix E, Section 4 and Table E-15).
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.
          The skin dose has two components, the gamma and beta contributions. The skin dose rate is computed by DS(r,e) : 1.11 x SFDY(ro) + 3.17.x 1 1 Qi[x/Q]D(rG)DFSi                    (B-7)
                                                  .i Symbols for this equation are defined in Regulatory Position C.2.d of this guide.


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.
The skin beta dose factors DFS were determined using the decay scheme source documents cited above and the methods used in References 5, 6, and 7. They are presented in Table B-i.


a.   Potable Water The annual dose from ingestion of water is calculated from Equation (A-2) below:
b.   All Other Releases The annual total body dose is computed as follows:
            Rapj = 1100    Uap  Qjexp(-x. .t )Daipj                                      (A-2)
          D(r,e) : SF ! xi(r,e)DFBi                                                  (B-8)
                apF            1            p aipj Symbols for this equation were defined earlier, in Section C.] of this guide.
          Symbols for this equation are defined in Regulatory Position C.2.e 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.
The annual skin dose is.computed as follows:
          D0(r,e)   1.11 x SF    xi(r,O)DFW + ! xi(r,e)DFSi                          (B-9)
          Symbols for this equation are defined in Regulatory Position C.2.f of this guide.


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.
1.109-22


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


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
2. M. J. Martin, "Radioactive Atoms,  Supplement I," USAEC Report ORNL-4923, November 1973.
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,
3. M. E. Meek and R. S. Gilbert, "Summary of Gamma and Beta Energy and Intensity Data," NEDO-
                                                  1.109-20
            12037, 1970.


TABLE A-3 ADULT INGESTION DOSE FACTORS
4.  J. K. Soldat et al., "The Dosimetry of the Radioactive Noble Gases," The Noble Gases (A. A. Moghissi and R. E. Stanley, eds.), ERDA-CONF 730 915, U.S. Energy Research and Development Administration, 1975.
                                              (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
5.  R. Loevinger et al., in Radiation Dosimetry (G. S. Hine and G. L. Brownell,  eds.),  Academic Press, New York, 1956.
  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          &#xfd;. 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 ..&#xfd;JF -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-n&#xfd;,                    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
6. M. J. Berger, "Improved Point Kernels for Electron and Beta-Ray Dosimetry," NBS Report NBSIR
            73-107, 1973.


TABLE A-3 (Continued)
7.' M. J. Berger, "Beta-Ray Dose in Tissue - Equivalent Material Immersed in a Radioactive Cloud," Health Physics, Vol. 26, pp. 1-12, January 1974.
  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)
al*
                BONE        LIVER      TOTAL RODY      THYROID  KIDNEY        LUNG        GI-LLI
'::i k!
  SUCLIDE
                                                      1.109-23
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)
APPENDIX C
  NUCL IDE  BONE          LIVER        TOTAL BODY    THYROID    KIDNEY    .LUNC  G[-I.'.'
                          MODELS FOR CALCULATING DOSES VIA ADDITIONAL PATHWAYS
B8RA      4.q8E-03      7.bbE-Ob                              2.17F-04    0.0
                                FROM RADIOIODINES AND OTHER RADIONUCLIDES*
       223                            9.95E-OU      0.0
                                      DISCHARGED TO THE ATMOSPHERE
88RA 224  1.b2E-03      3.90E-Ob                    0.0     1.11 E-oiU  0.0
1.    Annual External Dose from Direct Exposure to Activity Deposited on the Ground Plane The ground plane concentration of radionuclide i at the location (r,e) with respect to the release point may be determined by CG(r,O) =  [1.0 x 1012.1 [6i(re)  Qi]
                                      3.23E-04                                    3.2   E-Ou h.57E-03      7.79E-06       I .31E-01    0.0     2.21F-ou
            1       -                 1      1    [1 - exp(_xitb)].                   (C-l)
8BRA 225                                                                    .0
where CG(r,e)       is the ground plane concentration of the radionuclide i in the sector at I           angle 0 at the distancer from the release point, in pCi/m2 Q.      is the annual'release rate of nuclide i to the atmosphere, in Ci/yr;
          3.05F-01                    2.21E-01       0.0      1.b3E-04            S.,32E-Ou
              tb      is the time period over which the accumulation is evaluated, which is 15 years (mid-point of plant operating life). This is a simplified method of approximating the average deposition over the operating lifetime of the facility;
88RA 226                5.75E-06                                          0.0
        6i(r,e)      is the annual average relative deposition of effluent species i at location (r,e), considering depletion of the plume during transport, in m-2;
                        3.1?E-06      1.21E-01       0.0      8.84E-0s            5.64E-05 B8RA 228  1.12F-01                                                        0.0
              x       is the radiological decay constant for nuclide i, in yr-; and
B9AC 225                              2,QsE-07       0.0      6. 90F-6 7          4.07E-04
       1.0 x 1012       is the number of pCi per Ci.
          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
The annual dose resulting from direct exposure to the contaminated ground plane, from all radionuclides, is then DG(r,e) = 8760 SF
                                                                            0.0
* CG(r,e)DFGi                                            (C-2)
          1.37E-05      2.4BE-07                    0.0      tl    IE-Ob        5.JOE-Ou
where the terms-are defined in Regulatory Position C.3.a of this guide.
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
Values for the open field ground plane dose conversion factors for the skin and total body are given in Appendix E,'.Table E-6. The annual dose to all other organs is taken to be equivalent to the total body dose. The factor SF is assumed to have a value of 0.7, dimensionless.
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
Does not include noble gases.
                                          (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===
1.109-24
                                                                            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
2.    Annual Dose from Inhalation of Radionuclides in Air The annual average airborne concentration of radionuclide iat          the location (r,e) with res- K, i,, pect to the release point may be determined as xi(r,e)  =  3.17 x 104 Qi[x/Q] D(r,e)                                                  (C-3)
      where Qi      is the release rate of nuclide i to the atmosphere,      in Ci/yr;
                Xi(r,e)        is the annual average ground-level concentration, of nuclide i in air in sector e at distance r, in pCi/m3;
                                                                                                  3
          [x/Q]D(r,o)        is the annual average atmosphere dispersion factor, in sec/m (see Regulatory Guide 1.111). This includes depletion (for radioiodines and particulates)
                              and radioactive decay of the plume; and
            3.17 x l04        is the number of pCi/Ci divided by the number of sec/yr.


TABLE A-5 CHILD INGESTION DOSE FACTORS
The annual dose associated with inhalation of all radionuclides, to organ j of an individual in age group-a, is then
                                        (mrem/pCi ingested)
                  0.A
    NUCLIOE    BONE      LIVER      TOTAL B.11Y    TH~YRODI  K I)NEY    LUNr        G;I - LL I
                    ja (r,e) =  Ra Zx.(r,e)DFA.
  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
I             ja (C-4)
52TE 127      4A.50F-07  t .20E-07    9.65E-06      3. 1 OE-07          (.0          1 .'0?f-fl
            Values for DFAija are given in Appendix E, Tables E-7 through E-l0; values for Ra are given in Appendix E, Table E-5. All other symbols are as defined earlier in Regulatory Position C.3.b.
                          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
3.    Concentrations of Airborne Radionuclides in Foods The concentration of radioactive material in vegetation results from deposition onto the plant foliage and from uptake of activity initially deposited on the ground. The model used for estimating the transfer of radionuclides from the atmosphere to food products is similar to the model developed for estimating the transfer of radionuclides from irrigation water given in Appendix A of this guide.
                                              (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
a.    Parameters for.Calculating Nuclide Concentrations in Forage,        Produce, and Leafy Vegetables For all radioiodines and particulate radionuclides, except tritium and carbon-14,            the concentration of nuclide i in and on vegetation at the location (r,e) is estimated using
                                                                    [ -P exp(-xitb)]
                                                                Biv _2 Xi exp(-AEi te)]+                        exp (- i th )    (c-5)
                  Cv(r,e) =di (r,e) tr[l    -
                  See Regulatory Position C.1 of this guide for definitions of terms.            Values for the parameters r, te, Yv' P, and th are provided in Appendix E, Table E-15.             For the parameters te, Yv  and th' different values are given (in        Appendix E) to allow the use of Equation    (C-5) for different purposes:      estimating concentrations in produce consumed by man; in leafy vegetables consumed by man; in forage consumed directly as pasture grass by dairy cows, beef cattle, or goats; and in forage consumed as stored feed by dairy cows, beef cattle, or goats.


TABLE A-7 EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUJND*
1.109-25
                                              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
The deposition rate from the plume is defined by di(r,e)  = 1.1 x 1086i(r,e)Qi                                                (C-6)
              22      I ,66E-08    I. OE-08                                  97    4A*bOE-0q      i,4nE-Oq I TMA-
where d.(r,e)       is the deposition rate of radionuclide i onto ground at location (r,e), in pCi/m 2 -hr;
    11  NA          2.50E-0B      2.90E-08                                        2.29E-I I
          6i(r,e)       is th6 relative deposition of radionuclide i, considering depletion and
    1P       32    0,0)           0.0                              42MO    99      1 .qUF-0O          *20F-09
                            1                                     2 decay in transit to location (r,e), in m- (see Regulatory Guide 1.111); and
    20CA      U1      . nO -O
        1.1 x 1O8        is the number of pCi per Ci (10 2) divided by the number of hours per year
                    03.'JlE-09 U.01E-n9                        LJ3TC    9q4    Q.*,,E-10        I* OE-OQ
                           (8760).
    21 SC Ub          I*30F-08    1 .50E- -B                      43TC      04    0.0
       For radioiodines, the model considers only the elemental fraction of the effluent. The deposition should be computed only for that fraction of the effluent that is estimated to be elemental iodine. Measurements at operating facilities indicate that about half the radioiodine emissions may be considered nonelemental (Ref. 1). With this consideration included, Equation (C-6) for radioiodine becomes
    214CR                          2.b0E-1 0                      'i3TC            2.7WF-0O        I.OOF-Oq
                                      6.(C-7)
              51
            di(r,e) = 5.5 x 1076i(r,e)Qi where     is the total (elemental and nonelemental) radioiodine emission rate. The retention factor r for elemental radioiodine on vegetation should be taken as unity, since the experimental measurements (Refs. 1, 2, and 3) used to evaluate this transfer mechanism consisted of direct comparison of the gross radioiodine concentration on vegetation and the concentration in air (Refs. 4 and 5).
                                                                    44RU 101
        For radioiodines, the deposition model is based only on the dry deposition proces
                      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.
====s.  Wet====
.deposition, including "washout" of the organic and non-organic iodine fractions, should be con- sidered at some sites depending on the meteorological conditions (see Regulatory Guide 1.111).
        For particulates, the deposition model considers both wet and dry deposition. There is also a retention factor (r of Equation (C-5)) that accounts for the interception and capture of the deposited activity by the vegetative cover. A value of 0.2 is taken for this factor (Refs. 6 and 7). All nuclides except noble gases, tritium, carbon-14, and the iodines are treated as particulates.


1.109-28 E
Carbon-14 is assumed to be released in oxide form (CO or C02 ).    The concentration4of carbon,14 in vegetation is calculated by assuming that its ratio to the natural carbon in vegetation is the.


TABLE A-7 (Continued)
same as the ratio of carbon-14 to natural carbon in the atmosphere surrounding the vegetation (see Refs. 8 and 9). Also, in the case of intermittent releases, such as from gaseous waste decay tanks, the parameter p is employed to account for the fractional equilibrium ratio achieved. The parameter p is defined as the ratio of the total annual release time (for C-14 atmospheric releases)
            TOTAL BODY        SKIN                                TOTAL BODY        SKIN
to the total annual time during which photosynthesis occurs (taken to be 4400 hrs), under the condition'that the value of p should never exceed unity. For continuous C-14 releases, p is taken to be unity. These considerations yield the following relationship:
53!    13u    I.bOF-0      l.90t-o0i                    8RRA    2?3  1.50F-09    I.ROF-09
            C 4 (r,e) = 3.17 x 107 pQl 4 [x/Q](r,e) 0.11/0.16
531    13      1 .20EE-08  1uOE-O8                      8SRA    22u  3.9nE-0q    1.OOE-08
                        = 2.2 x 107 pQ1 4 [X/Q)(r,e)                                        (C-8)
                                                          88PA  P25  ;. 11F - I t I. 2()F -1A
where C 4 (r,e)     is the concentration of carbon-14 in vegetation grown at location (r,e), in pCi/kg;
55CS  134'1  b.P0E-10    7.Y0E-10
                  Q14     is the annual release rate of carbon-14, in Ci/yr;
55CS  134    1 .2F-08    IQOE-0p                      88AA    22b  b.41JF-oq    7.40E-O0
                      p     is the fractional equilibrium ratio, dimensionless;
55CS  135    0.0          D.0                            R.RA  228  I,?f'F-0    t.4OF-n8
                  0.11      is the fraction of total plant mass that is natural carbon, dimensionless;
                                                                                    1
                                                      1.109-26
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.
is.equal to the concentration of natural carbon in the atmosphere,           in g/m
                  0.16 and
                                                      1
          3.17 x 107        is equal to (1.0 x lO      2 pci/Ci)(l.0 x 103 g/kg)/(3.15 x 107 sec/yr).
      The concentration of tritium in vegetation is calculated from its concentration in the air surrounding the vegetation. Using the method described in Reference 10, the NRC staff derived the following equation:
            c'(r,).        3.17 x 107 QT[x/Q(rKe)(0.75)(0.5/H)
                          = 1.2 x 107 QT[x/Q](r,e)/H                                                  (C-9)
where C (r,e)        is the concentration of tritium in vegetation grown at location (r,e), in pCi/kg;
                        H  is the absolute humidity of the atmosphere at location (r,e), in g/m3 QT    is the annual release rate of tritium, in Ci/yr;
                    0.5    is the ratio of tritium concentration in plant water to tritium concentration in atmospheric water, dimensionless; and
                  0.75      is the fraction of total plant mass that is water, dimensionless.


Rap   = 1100 Uap      Q.B. D *exp(-Aitp                                      (A-3)
b.   Parameters for Calculating Nuclide Concentrations in Milk The radionuclide concentration in milk is dependent on the amount and contamination level of the feedconsumed by the animal.                The radionuclide concentration in milk is estimated as C'(re) =           vC(r,)Q   exp(-xitf)                                                  (C-10)
                                  i    aipj
where Cm(r,e)          is the concentration in milk of nuclide i,          in pCi/liter;
                                        ,          p Values of Bip are given in Table A-8; the other parameters have been previously defined.
          Cv(r, e)          is the concentration of radionuclide i in the animal's feed, in pCi/kg;
                  Fm        is the average fraction of the animal's daily intake of radionuclide i which appears in each liter of milk, in days/liter (see Appendix E, Tables E-l and TableE-2E-2,   cow the for use  and values goat data,  respectively;
                                                              in Table E-l);      for nuclides not listed in is the amount of feed consumed by the animal per day, in kg/day;
                  tf        is the average transport time of the activity from the feed into the milk and to the receptor (a value of 2 days is assumed); and i.      is  the radiological decay constant of nuclide i,          in days--1 The concentration of radionuclide i in the animal's~feed is estimated as C.(r,e) = fpfsC.(r,e) + (l - f )C*(r,e)            + fp(l    fs)CS(r,e)                (C-11)
                                    p s ip                i         p'                                (C-ll where C (r,e)          is the concentration of radionucl.ide i on pasture grass (calculated using Equation (C-5) with th=O), in pCi/kg;
            CS(r,e)          is the concentration of radionuclide i in stored feeds (calculated using Equation (C-5) with th=90 days), in pCi/kg;
                                                            1.109-27


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


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:
The values of the parameters tho te, Yv, and tf that will be employed in evaluating the milk pathway, unless site-specific data is supplied, are provided in Appendix E, Table E-15.
          C.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)
c.    Parameters for Calculating Nuclide Concentration in Meat As in the milk pathway, the radionuclide concentration in meat is dependent on the amount and contamination level of the feed consumed by the animal.      The radionuclide concentra- tion in meat is estimated as F(r,e)  FfCi(r,e)QF exp(-xits)                                           (C-12)
where Si     is the "effective" surface contamination, in pCi/m2, that is used in subsequent calculations;
  where CF(r,e)     is the concentration of nuclide i in animal flesh, in pCi/kg;
  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).
                    Ff  is the fraction of the animal's daily intake of nuclide i which appears in each kilogram of flesh, in days/kg (see Appendix E, Table E-l for values); and ts  is the average time from slaughter to consumption (see Appendix E, Table E-15)
  With a mass of 40 kg/m 2 of surface.
  All the other symbols are as previously defined.


1.109-30
Beef cattle will be assumed to be on open pasture for the grazing periods outlined for milk cattle.


TABLE A-8 BIOACCUMULATION FACTORS
4.    Annual Dose from Atmospherically Released Radionuclides in Foods The annual dose to organ j of an individual in age group a resulting from ingestion of all radionuclides in produce, milk, meat, and leafy vegetables is given by ia    vf v          c(Lo       FF          Lai       ]    (-3 DP (r,e)         ij[UafgC.(r,e)+
                            CpCilkg per pCi/liter)
                              DFI~                  UmC&#xb6;(,e) + U CFF(re) + UL f C(re)]      (C-13)
            FRESHNATER                              SALTMA17ER
                                      agi          a          a          aaXI
ELEMENT FISH    INVERTF3RATE      PLANT          PIS'    TIVERTE3RATE        PLANT
   where D a(r,-O)     is the annual dose to organ j of an individual in age group a from dietary intake of atmospherically released radionuclides, in mrem/yr;
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
              DFI..      is the dose conversion factor for the ingestion of nuclide i, organ j, and age group a, in mrem/pCi (from Tables E-ll through E-14 of Appendix E of this guide); and U UaV  ,     UF,    are the ingestion rates of produce (non-leafy vegetables, fruit, and grains),
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
       a   a a         a milk, meat, and leafy vegetables, respectively, for individuals in age group a (from Table E-5 of Appendix E of this guide).
C      U.    03
   All the other symbols are as previously defined.      Values of f  and fk to be assumed in the absence of site-specific information are given in Table E-15 of Appendix E as 0.76 and 1.0, respectively.
              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)
*i                                                  1.109-28
                      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===
REFERENCES FOR APPENDIX C
                    2,OE        I PoE 02      5.OE 02    0i 0OE        2.5f 01 BA           
1. B. H..Weiss et al., "Detailed Measurement of 1-131 in Air, Vegetation and Milk Around Three Operating Reactor Sites," NUREG-75/021, U.S. Nuclear Regulatory Commission, Washington, D.C., March 1975.
* 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).
2. D. F. Bunch (ed.), "Controlled Environmental Radioiodine Test, Progress Report Number Two,"
                                              1.109-32
    USAEC Report IDO-12063, January 1968.


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.
3.  J. D. Zimbrick and P. G. Voilleque, "Controlled Environmental Radioiodine Tests at the National Reactor Testing Station, Progress Report Number. Four," USAEC Report ID0-12065, December 1968.


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.
4.  F. 0. Hoffman, "Environmental Variables Involved with the Estimation of.the Amount of 1311
    -inMilk and the Subsequent Dose to the Thyroid," Institute fUr Reaktorsicherheit, Cologne, West Germany, IRS-W-6, June 1973.


The combination of Equations (A-4) and (A-5) into the general Equation (A-i) leads to
5.  F. 0. Hoffman, "A Reassessment of the Parameters Used To Predict the Environmental Transport of 1311 from Air to Milk,'" Institute fur Reaktorsicherheit, IRS-W-13, April-1975.
    ,*uation  (A-6) below for calculation of radiation dose from exposure to shoreline sediments.


Rapj      U
6. C. A. Pelletier and P. G. Voilleque, "The Behavior of 137Cs and Other Fallout Radionuclides on a Michigan Dairy Farm," Health Phys., Vol. 21, p. 777, 1971.
                            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).
7. P. G. Voilleque and C. A. Pelletier, "Comparison of External     Irradiation and Consumption
                        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:
                                              1 37    54 of Cow's Milk as Critical Pathways for       Cs,   Mn and 144Ce-144Pr Released to the Atmosphere," Health Phys., Vol. 27, p. 189, 1974.
                                                                                                              (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):
8.  Y. C. Ng et al., "Prediction of the Maximum Dosage to Man from the Fallout of Nuclear Devices, IV Handbook for Estimating the Maximum Internal Dose from Radionuclide
                              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
====s. Released====
    -to the Biosphere," USAEC Report UCRL-50163, Part IV, 1968.


TABLE A-9 SHORE-WIbTH FACTORS FOR USE IN EQUATIONS (A-5) and (A-6)
9. R. C. Weast (ed.),  "Handbook of Chemistry and Physics," CRC Press, Cleveland,     Ohio, 1970.
      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
10.  L. R. Anspaugh et al., "The Dose to Man via the Food-Chain Transfer Resulting from Exposure
    -to Tritiated Water Vapor," USAEC Report UCRL-73195, Rev. 1, 1972.


(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):
1.109-29
          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).*
APPENDIX D
                  The total dose Rapj from irrigated foods (excluding tritium) is given by:
                              MODELS FOR CALCULATING POPULATION DOSES FROM
          Ra          veg    CiD          + Uanimal ap            Y
                                      NUCLEAR POWER PLANT EFFLUENTS
                                                              *  iA Daipj                                            (A-12)
       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
            apj       ap        iv aipj If values for Civ from Equation (A-3) and CiA from Equation (A-11)                            are substituted in Equation (A-12):
of-Appendix I to 10 CFR Part 50.
                                            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
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.
                                                                  1.109-35


REFERENCES FOR APPENDIX A
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,
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,"
,the annual population-integrated dose is calculated as follows:
    USAEC Report WASH-1258, Washington, D.C., July 1973.
            D~j = O.Ol d*Pd Z Djdafda                                                      (D-l)-
                        d    a where Djda    is  the annual      to organ j (total body or.thyroid) of an average individual  of dose age group a in subregion d, in mrem/yr;
                SP    is the annual population-integrated dose to organ j (total body or thyroid),
                      in man-rems or thyroid man-rems;
              fda    is the fraction of the population in subregion d that is in.age group a;
                Pd    is the population associated with subregion d; and
            0.001      is the conversion factor from mrem to rem.


2. J. K. Soldat et al, "Models and Computer Codes for Evaluating Environvental Radiation Doses," USAEC Report BI3WL-1754, Pacific Northwest Laboratories, February 1974.
'The annual dose to the total body or thyroid of an average individual should be evaluated with the usage factors of Table E-4 of Appendix E. Models and equations for the detailed dose calculations are presented in Appendices A, B, and C of this guide. The annual population- integrated doses from ingestion of potable water, inhalation of airborne effluents, and external exposure to airborne or deposited radionuclides should be evaluated.       In addition to the pathways for which equations are presented in Appendices A, B, and C, other exposure pathways should be evaluated if conditions at a specific site indicate that they might provide a significant contri- bution to the total population dose from all pathways.      In this context, a significant contribu- tion is defined as 10 percent or more.


3. "Food Consumption, Prices, and Expenditures," AER-138, U.S.  Department of Agriculture, Washington, D.C., December 1974.
For pathways that involve food products produced in the subregion, the food products may be distributed to other areas for consumption.     For all the food that is produced within the 50-
mile radius, the radioactivity concentrations are averaged over the entire area by weighting the concentrations in each subregion by the amount produced in-each subregion.      This average concentra- tion is used in calculating the population doses. The 50-mile average concentration of.nuclide in food p is computed as ip = (1/Vp) exp(-x itp)
                                    P    Cdipvdp                                            (D-2)
   The population-integrated dose is the summation of the dose received by all individuals and has units of man-rem when applied to the total body dose and units of man-thyroid-rem when applied to the summation of thyroid dose.


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.
-1.109-30


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.
where is the average concentration over subregion d of the nuclide i in pathway p, in pCi/kg or pCi/liter (see Appendices A and C of this guide for models and equations for calculation of pathway concentrations);
              Cip        is the 50-mile average concentration of nuclide iin    pathway p, in
              *ip      pCi/kg or pCi/liter;
              t        is the transport time of the food medium p through the distribution system, p      in days (Table D-1 presents estimates of the transport times that may be used in lieu of site-specific data);
              Vdp        is the annual mass or volume of food medium p produced in subregion d, in kg or liters;
              V        is the mass or volume of the food medium p produced annually with the 50-mile radius about the site, in kg or liters; and
              *i        is the radiological decay constant for nuclide i,  in days- The population served by all the food produced within 50 miles of the site is estimated as Pp = V    /I U f                                                                (D-3)
                p .a ap a        r where fa        is the fraction of the population within the age group a;
                a P        is the estimated population that can be served by the quantity of food p P      likely to be produced within 50 miles of the site;
              Ua        is the use or consumption factor of food medium p for the average individual Uap      in age group a, in kg/yr or liters/yr (taken from Table E-4); and V        is the annual mass or volume of food medium p likely to be produced within P      a 50-mile radius about the site, in kg or liters.


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.
The annual population-integrated dose is then calculated as D    0.001  Y'Pp      a faC.i UapDF ai(D-4)
                    Sp where
                : P p if    P*p< P 5 Pp .,             p      50
                  P550]if  Pp > P5"50*
and DFai        is the ingestion dose factor for age group a and nuclide i,   in mrem/pCi (taken from Appendix E, Tables E-ll to E-14);
                                                      1.109-31


7. M. M. Miller and D. A. Nash, "Regional and Other Related Aspects of Shellfish Consumption -
TABLE D-1 RECOMMENDED VALUESFOR THE TRANSPORT TIMES IN THE FOOD
    Some Preliminary Findings of the 1969 Consumer Panel Survey," NIMFS Circular 361, USDC/NOfhA,
                            DISTRIBUTION SYST-...
    Seattle, Wash., June 1971.
    FOOD MEDIUM                            DISTRIBUTION TRANSPORT TIME (in days)
Fruits, grains, and vegetables                              14 Milk                                                          4 Meat and poultry                                            20
Sport fish                                                    7 Con*nercial fish                                            10
Drinking water                                                1 To be used in lieu of site-specific data on food distribution.


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.
1.109-32


9. "Draft Environmental Statement - Waste Management Operations, Hanford Reservation,  Richland, Washington," USAEC Report WASH-1538, Washington, D.C., September 1974.
0)
                  Djr      is the annual population-integrated dose to organ j (total body or thyroid),
                  !*      in man-rem/yr or thyroid man-rem/yr;
                  Pp      is the population consuming food medium p; and P50        is the total populationwithin 50 miles.


10. "Radiological  Health Handbook," USPHS,  Rockville, Md., January 1970.
All other factors are as defined above.


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.
Note that the above formulation limits theevaluation of the exposed population evaluation to the population residing within 50 miles as specified in paragraph D, Section II of Appendix I
to 10 CFR Part 50.        In calculating the annual population-integrated total body and thyroid doses, the age distribution of the population within 50 miles may be assumed to be the same as the age distribution of the U.S. population (Ref. 1). Reference 1 indicates the fractional breakdown to be as follows: children, 0.18; teenagers, 0.11; and adults, 0.71.          Infants (0-1 year in age) are not projected to exceed 2% of the population (Ref. 1), and their population fraction has been included in that given above for children.


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.
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.


13. P. M. Bryant, "Data for Assessments Concerning Controlled and Accidental Releases of 1I
(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.
    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.
The total body and thyroid dose of the individuals should be evaluated using
-Equation (A-2)      in Appendix A of this guide, together with the age-dependent usage factors U
                                                                                                    ap 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.


15. "Report of ICRP Committee II on Permissible Dose for Internal Radiation, International Commission on Radiological Protection," ICRP Publication 2, Pergamon Press, 1959.
If the population served by a particular water supply. system is not known, it can be estimated by the following:
              Pw e v/c                                                                        (D-5)
where c      is the average daily usage of individuals on the system, in gal/day per person;
                  Pw      is the estimated population served by the water system; and v      is the average daily intake of the water supply system, in gal/day.


16. J. K. Soldat, "Modeling of Environmental Pathways and Radiation Doses from fluclear Facilities," USAEC Report BNWL-SA-3939, Pacific Northwest Laboratory, 1971.
If the industrial usage from the water supply system is known, it can be sub- tracted from the average daily intake of the system before this value is entered into Equation (D-5).
                      The population served by a water supply system whose intake is within the 50-mile radius may include individuals who reside outside the circle. This population may be pro-rated to include only the population within the 50-mile radius. Conversely, a water supply system with an intake beyond the 50-mile radius may serve the population within the 50-mile radius, whose exposure via drinking water should be included in the 50-mile population dose evaluation.


17. C. M. Lederer et al,  Table of Isotopes,  6th Ed., John Wiley and Sons,  Inc., 1967.
1.109-33


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.
(2)  Doses from Aquatic Food Products The annual population-integrated total body and thyroid doses from consumption of aquatic food products are evaluated using the production of sport and commercial harvests in the various subregions. The mixing ratio (or dilution) should be evaluated for each subregion using an appropriate hydrological model.     For sport harvests, the entire edible harvest is a'ssumed to be ingested by the population within 50 miles. The formulation expressed by Equation.


1.109-36
(D-4) should be used with-the population Pp.given by the results of Equation (D-3).     The age- specific ingestion rates of Table E-4 may be used in lieu of site-specific data.
                                                                                                  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.
For commercial harvests, the production within 50 miles from the site is con- sidered as part of the total U.S. harvest. Equation (D-2) should be used to compute the average concentration, with V as the total estimated U.S. commercial harvest of the aquatic food p
medium p. The annual population--integrated dose is then computed using Equation (D-4) with Pp = P50. The age-specific factors of Table E-4 may be used in lieu of site-specific data.


20. J. F. Honstead, "Recreational Use of the Columbia River--Eval'ation of Environmental Exposure," USAEC Report BNWL-CC-2299, Pacific Northwest Laboratory, 1969.
(3)  Doses from Shoreline Deposits The annual population-integrated total body and thyroid doses from recreational activities on the shoreline of the receiving water body are evaluated by summiing the product of the individual doses in each subregion and the population exposed therein. All subregions within the 50-mile radius should be considered.where existing or designated recreational facili- ties exist. If available, actual recreational usage in the vicinity of each facility should be used. The formulation of Equation (D-l) is appropriate.


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.
(4)  Doses from Consumption of Terrestrial- Food Products Irrigated by Waters Receiving the Liquid Effluent The annual population-integrated total body and thyroid doses from consumption of food irrigated with water from the body receiving the liquid effluent are evaluated following the procedures outlined in the development of Equation (D-4).     Note that the term V of Equations (D-2) and (D-3) denotes the total production of food medium p within 50 miles, not just the total production of irrigated food medium p. The consumption rate data of Table D-l may be used in lieu of site-specific data in the evaluation of Equation (D-4).
      b.   Population-Integrated Doses from Airborne Effluents The annual total body and thyroid population-integrated doses should-be evaluated for the following principal exposure pathways: noble gas submersion, inhalation of airborne efflu- ents, ingestion of contaminated terrestrial foods (milk, meat, and produce), and external irradiation from activity deposited on the ground. Available state or county agricultural pro- duction data may be used for estimating the population-integrated doses from food consumption.


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.
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.


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


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.),
(2)  Doses due to Inhalation of Radioiodines and Particulates The annual  population-integrated total body and thyroid doses from inhalation of airborne effluents should  be evaluated by summing the products of the individual doses received in each subregion and the  population in each subregion.   Equation (D-1) may be used. The age- specific inhalation rates  of Table E-4 may be used with the data of Tables E-7 to E-l0.
    CONF-710809, 1973.


1.109-37
1.109-34


APPENDIX B
(3)  Doses due to Ingestion of Terrestrial Food Products The annual population-integrated total body and thyroid doses from. ingestion of terrestrial food products should be evaluated using the production data for each subregion. For milk, meat, and commercial vegetables, the formulation of Equation (D-2) should be used to calculate the average concentrations in the foods. These concentrations are then used in Equation (D-4), along with the data of Tables D-l, E-4, and E-ll to E-14, to calculate population doses.
                                    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.
(4)  Doses due to External Irradiation from Activity Deposited on the Ground The annual population-integrated total body and thyroid doses from external exposure to surface deposition of the effluent should be evaluated using Equation (D-l). A
household shielding and occupancy factor of 0.5 should be applied in conjunction with the dose factors of Table E-6.


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:
REFERENCE FOR APPENDIX D
                      D 260
1. "Current Population Reports," Bureau of the Census, Series P-25, No.   541, U.S. Dept. of Commerce, 1975.
                              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)
1.109-35
                    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)
APPENDIX E
  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.
                                NUMERICAL DATA FOR THE CALCULATION
                                OF ANNUAL DOSES TO MAN FROM ROUTINE
                                    RELEASES OF REACTOR EFFLUENTS
      This appendix contains data for use in the equations presented in the Regulatory Position and in Appendices A, B, C, and D of this guide. The numerical values presented in this appendix are those routinely used by the NRC staff. In instances where more appropriate information of a site-specific nature has been developed and documented, that information should be used.


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.")
In a number of instances the staff has found it necessary to provide guidance as to the value of a particular parameter in the absence of substantial empirical data. In such instances the staff has exercised judgment and has considered values used by others and the sensitivity of the results to the value assumed.
                                                1.109-30


where Qi    is the initial release rate of nuclide i, in Ci/yr, and
Information is provided below under four broad categories: environmental data, human data, dose factors, and other parameters.
                                                                  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.
1.    Environmental Data Table E-1 provides values for the following staDle element transfer coefficients:
      a.  Biv for the estimation of produce,  leafy vegetable, or pasture grass radioactivity from that in soil (pCi/kg in vegetation per pCi/kg in soil);
      b.    Fm for the estimation of cow milk activity from that in feed (pCi/i in milk per pCi/
day ingested by the animal); and c.    Ff for the estimation of meat activity from that in feed (pCi/kg in meat per pCi/day ingested by the animal).
The data are largely derived from Reference 1. The value of the cow milk transfer coefficient for radioiodine is based on the staff's review of the literature (Refs. 2-9).
      Values of transfer coefficients for goat milk are presented in Table E-2 for a limited number of nuclides. For nuclides not listed in Table E-2, the milk transfer coefficient from Table E-1 should be used.


The annual average ground-level concentration of gaseous effluent species i at location (r,o)
Various animal parameter values are presented in Table E-3 for use in estimating animal product activity levels as functions of the corresponding levels in feed and water supplies.
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
2.    Human Data Tables E-4 and E-5 present usage rates of various environmental media by average individuals and maximum individuals, respectively, according to age group.    "Seafood" is used to indicate intake of aquatic invertebrates such as lobster, crab, clams, and'oysters.     Ingestion of aquatic plant material is not normally assumed.
          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.    Dose Factors Dose factors for external irradiation from a uniformly contaminated ground plane are
                                                                          2 presented in Table E-6 (Refs. 10 and 11), in units of mrem/hr per pCi/m . These factors are applicable for surface contamination via deposition of liquid effluents on shoreline sediments or airborne effluents on ground surfaces.    Dose factors are provided for the total body and skin only. Doses to other organs are assumed equal to the total body dose.


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.
Dose factors provided in Table E-6 are derived from a consideration of the dose rate to air
1 meter above the ground plane and the penetration of the radiation into the body. The total body dose is computed at a penetration depth of 5 cm; the skin dose is computed at a depth of
7 mg/cm2 .  These tissue depths are indicated by Reference 12, where it is suggested that, for
                                              1.109-36


a.  Elevated Releases The annual total body dose is computed as follows:
TABLE E-1 STABLE ELEMENT TRANSFER DATA*
          DT(r,O) = 1.11 x SF I DI(re)exp[-i (Ek)t]                                  (B-6)
                            Biv                    Fm(Cow)              Ff Milk (d/z)
  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.)
    Element              Veg/Soil                                    Meat (d/kg)
  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.
    H**                  4.8E 00                1.OE-02            1.2E-02 C**                  5.5E 00                1.2E-02            3.1E-02 Na                  5.2E-02                4.0E-02***          3.OE-02 P                    l.IE 00                2.5E-02            4.6E-02 Cr                  2.5E-04                2.2E-03            2.4E-03 Mn                  2.9E-02                2.5E-04            8.OE-04 Fe                  6.6E-04                1 .2E-03            4.OE-02 Co                  9.4E-03                I .OE-03            1.3E-02 Ni                  1.9E-02                6.7E-03            5.3E-02 Cu                  1 .2E-01                1 .4E-02            8.OE-03 Zn                  4.OE-01                3.9E-02            3.0E-02 Rb                  1 .3E-01                3.OE-02            3.1E-02 Sr                  1.7E-02                8.0E-04***          6.OE-04
    'Y                  2.6E-03                1.OE-05            4.6E-03 Zr                  1 .7E-04                5.OE-06            3.4E-02 Nb                  9.4E-03                2.5E-03            2.8E-01 Mo                  1.2E-01                7.5E-03            8.OE-03 Tc                  2.5E-01                2.5E-02            4.OE-01 Ru                  5.0E-02                1 .OE-06            4.6E-01 Rh                  l.3E 01                1.OE-02            1.5E-03
'I'
    Ag                  I .5E-01                5.OE-02            1.7E-02 N, Te                  l.3E 00                1 .OE-03            7.7E-02 I                  2.OE-02                6.OE-03t            2.9E-03 Cs                  1 .OE-02                1 .2E-02***        4.OE-03 Ba,                 5.OE-03                .4.0E-04"***        3.2E-03 La                  2.5E-03                5.OE-06            2. OE-04 Ce                  2.5E-03                l.OE-04***          1 2E-03 Pr                  2.5E-03                5.OE-06            4.7E-03 Nd                  2.4E-03                5.OE-06            3. 3E-03 W                    1.8E-02                5.OE-04            1 .3E-03 Np                  2.5E-03                5.OE-06            2.OE-041t Data presented in this table is from Reference 1 unless otherwise indicated.


I
Meat
                                                1.109-40
          .    and milk coefficients are based on specific activity considerations.


TABLE B-i DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS
From Reference 15.
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.
tSee text.


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)
ttFroim Reference 13.
                                                        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.
1.109-37


b.    Ground-Level Releases The annual total body dose is computed as follows:
TABLE E-2 NUCLIDE TRANSFER PARAMETERS FOR GOAT'S MILK*
            DT(r,o) = 1.11 x SF &#xfd;xi(rO)DFBi                                              (B-8)
                                                  Fm (days/liter)
            Symbols for this equation were defined earlier in Regulatory Position C.2.e of this guide.
            Element H                                        0.17 C                                        0.10
              P                                        0.25 Fe                                        1.3E-04 Cu
                                                        0.014"*
              Sr I                                      0.06&*
              Cs                                      -0.30**
                Values in this table are from References 1 and 14 unless otherwise indicated.


The annual skin dose is computed as follows:
From Reference 15.
            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
TABLE E-3 ANIMAL CONSUMPTION RATES
I. "Meteorology and Atomic Energy 1968," D. H. Slade (ed.),  USAEC Report TID-24190, 1968.
                                                                QAw Feed or Forage                Water Animal                    (kg/day [wet weight])          (      R./day)
  Milk cow                      50 (Ref. 10)                  60 (Ref. 16)
  Beef cattle                  50 (Ref. 10)                  50 (Ref.  16)
  Goats                          6 (Ref. 17)                 8 (Ref . 18)
                                      1.109-38 IL


2. M. J. Martin, "Radioactive Atoms,  Supplement I," USAEC Report ORNL-4923,  November 1973.
TABLE E-4 RECOMMENDED VALUES FOR U    TO BE USED FOR THE AVERAGE INDIVIDUAL
                            ap IN LIEU OF SITE-SPECIFIC DATA
    Pathway                        Child        Teen        Adult Fruits, vegetables,  &
  grain (kg/yr)*                      200          240          190
Milk (z/yr)*                          170          200          110
Meat & poultry (kg/yr)*                            37          59            95 Fish (kg/yr)*                        2.2          5.2          6.9 Seafood (kg/yr)*                      0.33        0.75          1.0
Drinking water (L/yr)**              260          260          370
Shoreline recreation (hr/yr)**                          9.5          47            8.3 Inhalation (m3 /yr)                  3700***      8000***      8000t Consumption rate obtained from Reference 19 and age-prorated using techniques in Reference 10.


3. M. E. Meek and R. S. Gilbert, "Summary of Gamma and Beta Energy and Intensity Data," NEDO-
Data obtained directly from Reference 10.
  12037, 1970.


4. R. Loevinger et al, in Radiation Dosimetry (G. S. Hine and G. L. Brownell,    eds.), Academic Press, New York, 1956.
Inhalation rate derived from data provided in Reference 20.


5. M. J. Berger, "Improved Point Kernels for Electron and Beta-Ray Dosimetry," NBS Report NBSIR
tData obtained directly from Reference 20.
  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.
1.109-39


1.109-43
TABLE E-5 RECOMMENDED VALUES FOR Uap TO BE USED FOR THE MAXIMUM EXPOSED
                -  INfJVIDUAL IN LIEU OF SITE-SPECIFIC DATA
        Pathway            Infant          Child        Teen      Adult Fruits, vegetables &
  grain (kg/yr)*,**                          520        630      520
Leafy vegetables
  *(kg/yr)*                                  26          42        64 Milk (k/yr)*                330              330        400      310
Meat & poultry (kg/yr)*                                  41          65        110
Fish (fresh or salt)
    (kg/yr)***                                6.9        16        21 Other seafood (kg/yr)*                        1.7        3.8      5 Drinkingwater (Z/yr)t        330              510        510      730
Shoreline recreation (hr/yr)t                                  14          67 Inhalation (m3/yr)          1400tt          3700ttt    8000tt-t  8000tt Consumption rate obtained from Reference 19 for average individual and age-prorated and maximized using techniques contained in Reference 10.
 
Consists of the following (on a mass basis): 22% fruit, 54% vegetables (including leafy vegetables), and 24% grain.


APPENDIX C
Consumption rate for adult obtained by averaging data from References 10
                                MODELS FOR CALCULATING DOSES VIA ADDITIONAL PATHWAYS
     and 21-24 and age-prorated using techniques contained in Reference 10.
                                      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)
tData obtained directly from Reference 10.
                      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.
.Data obtained directly from Reference 20.


1.109-45
tttiInhalation rate derived from data provided in Reference 20.


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)
1.109-40
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)
TABLE E-6 EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND
      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.
                        (mrem/hr per pCi/m2)
Element                        Total Body              Skin
-H-3                              0.0                    0.0
C-14                              0.0                    0.0
NA-24                            2.50E-08              2.90E-08 P-32                              0.0                    0.0
Cr-51                            2.20E-10              2.60E-10
Mn-54                            5.80E-09              6.80E-09 Mn-56                            l.1OE-08                1.30E-08 Fe-55                            0.0                    0.0
.Fe-59                            8.OOE-09              9.40E-09 Co-58                            7.OOE-09              8.20E-09 Co-60                            1.70E-08                2.OOE-08 Ni-63                            0.0                    0.0
  Nr-65                            3.70E-09                4.30E-09 Cu-64                            1.51E-09                1.70E-09 Zn-65                            4.OOE-09                4.60E-09 Zn-69                            0.0                    0.0
  Br-83                            6.40E-11                9.30E-11 Br-84                            1.20E-08                1.40E-08 Br-85                            0.0                    0.0
  Rb-86                            6.30E-10                7.20E-10
  Rb-B8                            3.50E-09                4.O0E-09 Rb-89                            1.50E-08                1.80E-08 Sr-89                            5.60E-13                6.50E-13 Sr-91                            7.10E-09                8 30E-09 Sr-92                          .9.00E-09                IOOE-08 Y-90                            2.20E-12                2.60E-12 Y-91M                            3.80E-09                4.40E-09 Y-91                            2.40E-ll                2.70E-11 Y-92                            1.60E-09                1.90E-09 Y-93                            5.70E-1O                7.80E-10
  Zr-95                            5.ODE-09                5-80E-09 Zr-97                            5.50E-09                6.40E-09
*Nb-95                            5.10E-09                6.OOE-09 Mo-99                            1.90E-09                2.20E-09 Tc-99M                          9.60E-10                1.1OE-09 Tc-ll                            2.70E-09                3.OOE-09 Ru-103                            3.60E-09              4.2DE-09 Ru-105                          4.50E-09                5.1DE-09 Ru-106                            1.50E-09              1.80E-09 Ag-liOM                          1.80E-08              2.10E-08 Te-125M                        .3.50E-l1                4.80E-l1
  .Te-127M                        1.1OE-12                1.30E-12 Te-127                            1.OOE-l1              1.1OE-11 Te-129M                          7.70E-10              9.O0E-10
  Te-129                          7.10E-10                8.40E-10
  Te-131M                          8.40E-09                9.90E-09- Te-131                          2.20E-09              2.60E-06 Te-132                            1.70E-09              2.00E-09
  1-130                            1.40E-08              1.70E-08
  1-131                            2.80E-09              3.40E-09
  1-132                            1.70E-08              2.OOE-08
  1-133                          3.70E-09                4.50E-09
  1-134                            1.60E-08              1.90E-08
  1-135                          1.20E-08                1.40E-08
                                1.109-41


The annual dose to organ j in age group a from all nuclides in the effluent is:                  4 DA                                        (ra=R(C-6)
TABLE E-6 (Continued)
             Dja(r,o)    Ra zxi(re)DFAija
Element          Total Body  Skin Cs.-134            1.20E-08  1. 40E-08 Cs-136            1.50E-08  1 .70E-08 Cs-1 37            4.20E-09  4.90E-09 Cs-138            2. 1OE-08  2.40E-08 Ba-139            2.40E-09  2.70E-09 Ba-1 40            2. lOE-09  2.40E-09 Ba-141            4.30E-09  4.90E-09 Ba-142            7.90E-09  9.00E-09 La-I 40            1.50E-08  1. 70E-08 La-142            1.50E-08  I. 80E-08 Ce-141            5.50E-10  6.20E-10
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.
Ce-143            2.20E-09  2.50E-09 Ce-144            3.20E-10  3.70E-10
Pr-143            0.0        0.0
Pr-144             2.00E-10  2.30E-10
Nd-147            1. OOE-09  1.20E-09 W-187              3.10E-09  3.60E-09 Np-239            9.50E-10  1 .10E-09
              1.109-42


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)
calculational purposes, the average depth of the blood-forming organs may be assumed to be 5 cm.
                        '          '    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).
Reference 12 also identifies the cells of the basal layer of epidermis as the tissue of interest
                                                                                                        I
                                                                                        2 in the computation of skin dose and states an average depth for these cells of 7 mg/cm . This guidance is reflected in the dose factors presented in Table E-6 and also in those presented in Appendix B, Table B-l, for use in calculating external doses from noble gases.
                                                  1.109-46


TABLE C-1 ADULT INHALATION DOSE FACTORS
Dose factors for internal exposure are provided in Tables E-7 through E-14, in units of mrem per pCi intake (Ref. 25).    Tables E-7 through E-l0 are for inhalation (one table for each of the four age groups), while Tables E-ll through E-14 are for ingestion. Dose factors provided for the inhalation of H-3 include an increase of 50 percent to account for the additional amount of this isotope absorbed through the skin (Ref. 25).
                                          (mreni/pCi inhaled)
       As discussed in Section B, "Discussion," these dose factors are appropriate for continuous intake over a one-year period and include the dose commitment over a 50-year period. The cal- culational scheme by which these dose factors are derived includes elementary consideration of changing physical and metabolic characteristics during the period over which the dose commitment is evaluated. For example, environmental exposure of an infant over a one-year period is treated as follows: dose during the first year is computed based on infant physiological-and metabolic characteristics considering both the buildup and decay of the appropriate organ burden; dose during.years 1-10 is computed based on child physiological and metabolic data considering decay
    NUCLIDE      A0IE    LIVER    TfTAL 9')Y                  KI)NEY                  GI-LLI
.of the organ burden from its peak value at age 1; dose during years 11-16 is treated in a similar fashion using teenager characteristics; and dose during adulthood is computed based on the physiological and metabolic characteristics of an adult. Age-dependent parameters are changed in steps at the breaks between age groups.
  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
===4. Other Parameters===
      .Table E-15 has been provided as a central location for the recommended values of many of the miscellaneous parameters appearing in equations in this guide. In some instances, a parameter's value or units is a function of the equation it is used in. Additionally, for some parameters used in calculating activities in vegetation, the value is also a function of the exposure path- way. Table E-15 has been organized to note these complications.


TABLE C-1 (Continued)
Values of the parameter SF, a structural shielding and occupancy factor, are given in Table E-15 as 0.7 (for maximum individuals) and 0.5 (for the generalpopulation).   Using the general approach given in Reference 26, the staff estimates an average structural shielding factor of 0.5 for typical reactor effluents. Assuming the maximum individual spends about 50 percent of the time indoors, the overall shielding and occupancy factor is then approximately 0.7. The factor of 0.5 is used directly for population dose calculations. These factors are applicable for external gamma exposure from noble gases and for external exposure from contaminated ground surfaces.
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
1.109-43
  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


TABLE C-i (Continued)
TABLE E-7 PASE  I OF  3 INHALATION  DOSE FACTORS FOR AnULTS
  NUCLIDE       BONE        LI VER       TOTAL BODY      THYROID       KInNEY          LUNG           GI-LLI
                            (UREM  PER PCI INHALED)
                            I 56'F-Ob                                    3,*25E-O6
NUCLIDE     HONE    LIVER      T.ROCY       THYROID KIDNEY    LUNG     GI-LLI
531   133  I .0BE-O0                    5.h7E-07       3.hbE-OLA     3.2UE-07            0.0      I.09E-06
H    3  NO DATA    1.58E-07    1.58F-07    1.58E-C7 l.58E-07 1.58E-07  1.58E-07
531   134   5.ObE-08     2. 16E-07       7.70E- n        2.97E-05                    0.0
    1.4  2.27E-06  4.26E-07   4.26E-07    4.26E-07 4.26L-07 4.26E-07  4.26E-07 AA 24    1.28E-06  1.28E-06    1.28E-06     1.28E-06 1.28E-06 1.2RE-06  1.28E-06 p  32  1.65E-04  9.64E-06    6.26[-06    NO DATA   NC DATA  NO DATA  1.08E-05 CR 51    NO DATA    NO DATA    1.25E-08     7.44E-Oq 2.85E-09 1.80E-06  4.15F-07 MN 54    NO DATA    4.95E-0b    7.8rE-07    NO DATA  1.23L-06 1.75E-04  q.67E-06 MN 56    NO DATA    1.55E-10    2.29E-11    '0 DATA  1.63E-1O 1.18E-06  2.53E-06 FE 55    3.07E-06  2.12C-06    4.93E-07     NO DATA  NO DATA  9.C1E-06  7.54E-07 FE 59    1.47E-06   3.47E-0b    1.32E-06    NO DATA NO DATA  1.27E-04  2.35E-05 CO 58    ND DATA    1.98E-07    2.59E-07   NO DATA   NC DATA  1.16E-04  1.13E-05, CO 60    NO DATA    1.44E-06    1.85E-36    NO DATA  NO DATA  7.4bE-04  3.56E-05 NJ1 63  5.40E-05  3.13E-06    1.81E-06    NO DATA  NO DATA  2.23E-05  1.67E-06
                                                          I . 17 F -OU     .  1 F-Ob 0.0          bSbF-U7
4l 65    I.92E-10  2.o2C-II    1.14F-11     NO DATA  NC DATA  7.0OE-07  1.54E-06 CU 64    NO DATA    1.93E-10    7.63F-11    NO DATA  5.78E-1O 8.48E-07  6.12E-06 ZN 65    4.05E-06  1.29F-05   5.82E-06    NO DATA  R.62E-06 1.08E-04  6.68E-06 ZN 69    4.23E-12  8.14&#xfd;-12    5.65E-13     NO DATA  5.27L-12 1.15.E-07 2.04E-C9
531   135   3.30E-07      R. ?&#xa3;E-M7      3.?2E-07
&#xfd;AR 83   NO DATA    40 DATA    3.01E-08    NO DATA  NO DATA  NO DATA   2.90F-08
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
,R 84    NO DATA    NO DATA    3.91E-08     NO DATA  NO DATA  NO DATA  2.05E-13 diR 80  NO DATA    NO DATA    1.60E-09    NO DATA  NC DATA  NO DATA  LT E-24 RE! 8B  NO DATA    1.69E-D5    7.371E-06   NO DATA  NO DATA  NO DATA  2.08E-06 RB 88    NO DATA  .4.84E-08   2.41E-98    NO DATA  NO DATA NO DATA  4.iB-I1 RB 89    NO DATA    3.20E-O8    2.12E-08    NO DATA  NO DATA  NO DATA  1.16F-21 SR 89    3.80E-05   NO DATA    1.09E-06    NO DATA  NO DATA  1.75E-04  4.37E-05 SR 90    1.24E-02  NO DATA    7.62E-04    NO DATA  NC DATA  1.20E-03  9.02E-05 SR 91    7.74E-Oq  NO DATA    3.13E-1D    NO DATA  NO DATA  4.56E-06  2.39F-05 SR 92   8.43E-10  NO DATA    3.64E-11    NO DATA  NO DATA  2.06E-06  5.38E-06 Y 90    2.61E-07  NO DATA    7.01E-09     NO DATA  NO DATA  2.12E-05  6.32E-05 Y  9111 3.26E-11  NO DATA    1.27E-12    NO DATA  NC DATA  2.40E-07  1.66E-10
55CS                                                      0.0
Y  91  5.78E-05   NO OArA    1.55E-06    NO DATA  NO DATA  2.13E-04  4.81E-05 Y  92  1.29E-09   NO DATA    3.77E-11    NO DATA NO DATA  I.q6E-06  9.19E-06
55CS   135   1 ,UbF-05     I .29E-o5      6.AOE-lh                      I .07E-05      1.57E-06     2.11F-07
                                        1.109-44
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
TABLF    E-7,  CONT'D
5695  139   1.17F-I 0
                                                    PASF  2  OF  3 INHALATION DOCSE FACTORS FOR            ADULTS
S6BA I40                                  3.21F-07                      2.0QE-nq       1.5QE-nu    2.73L-05
                                          ,(REM PFR PCI INHALED)
            4.,86.F-0B          IE
    *.NUCL I ;L        BONE    LIVFR          T.-BODY        THYROID      KIDNEY      LUNG     GJ-LLI
                                  15FO
      'y  93    1.18E-Or  NO  DATA       3.26E-10        NO  DATA   NC  DAT.A  0.06E-06 5.27E-05 I      ZR   95    1.34E-05  4.3CE-06        2.91E-06       NO  DAT4    6.77E-06  2.21E-04 1.38E-05 ZR  97    1.2IF-O8  2.45E-09        1.13E-09      NO  DATA    3.71E-09  9.84E-C3 6.54E-05 NB  95    1.76E-06  9.77L-07        5.26E-07        NO  DATA    9.67E-07   6.31E-05 1.30F-05 MO  99.  AJO DATA  1.I5-1    8    2.87E-09        NO  DATA    3.64E-OB  1.14E-05 3.10E-05 TC   99M,' 1.29E-13   3.64F-13        4.63E-12        NO  DATA    5.52E-12  9.55E-08 5.20E-07 TC101     5."'2E-15  7.52E-15        1.36E-14       NO  DATA  -1.35E-13  4.99E-08 1.36F-21 RU*03      1.91E-07   NO DATA        8.23E-08       NO  DATA '7.29E-07    6.31E-05 1.38E-05 RUIC5      9.88E-11  NO DATA         3.89E-1i        NO  DATA    1.27E-10   1.37E-06 6.02E-06 RUI06      8.64E-C6  NO DATA          l.O)E-06      NO  DATA    1.67E-05  1.17E-03 1.14E-04 AG110     1.35C-,6  1..25.-06       7.43,--07      NO  DATA    2.46E-06  5.790-04 3.78E-05
5*A                        9,LIE-i5      !1.2nE-I 3                                   ?.112E-07    I.115F-17
                                                                               5 TC125M1    4.27E-07   1.Q9E-O7        5.84E-08        1.31E-07    1.5  E-06 3.92E-C5 8.83E-06 TE127r'    1.58F-06  7.21C-07       1.96E-07       4..1iE-07    5.72E-06  1.20E-04 1.87E-05 TE127      1.75[-10  8.OC'3-Il      3.87E-11        1.32E-10    6.37E-10  8.14E-07 7.1.7-06 IE129P    1.22E-06  5.84's-07      1.96E-O7        4.30E-07     4.57E-06  l.45E-O4  ,.79-05 TE129     6.220-12  2."9L-12       1.5'.)E-12     4.87E-12    2.34E-11  2.42E-07 I.96F-08 TEI3lM    8.14E-09  5.45E-09        3.63F-09        6.88E-09    3.86E-08  1.82E-05 6.95E-05 TF131      1.39E-12  7.44E-13        4.49E-13        1.17T-12    5.46E-12  1.74=-07 2.30E-09
                          63 38E- 15    A. 7E-1 3        0.0          2. 7E-IS
      1E132     3.25L-08   2.69E-08        2.0O?-08       2.37E-08    1.82E-07  3.60E-05 6.37F-05
SbBA                                                      0).0                        l.UqF-07     0.0
         1 1.30    5.72E-07  I.o8E-O6       6.6;C-07        1.42E-04     2.61E-06  NO DATA  9.61E-07
            9  I  F25
        1 131    3.15E-06  4.47E-io        2.56E-06        1.49E-03    7.66E-06  NO [ATA 7.85F-07
                      - 11                                              0l.0          1.70E-)5      5,.73E-nE
        1 132     1.45E-07  4.07E-07        1.45E-07       1.43E-05     6.48E-07   NO DATA  5.08F-08
57LA                      2. 1 7E-OA    5S.71E-LnQ        o.n
        1 133    1.08E-06  1.85E-06        5.65E-07        2.69E-04     3.23E-06  NO DATA  1.11F-06 I 134    ,.05-08    2.160-07        7.69E-08        3.73E-06    3.44E-07   NO DATA  1.26E-1O
        12                                                              0.0            1.SSE-Ob    7.31E-0e
        I 135    3.35E-C7  8.73E-07        3.21E-07        5.bOE-C5    1.39E-06  NO DATA  6.56E-07 CS134     4.66E-05  1.06E-04        9.10-05         NO DATA     3.59E-C5  1.22E-05 1.30E-06 CS136      4.88E-C6    1.F3Z0-05      1.33q-05        '40 DATA    I.,07E-05  1.50E-06 1.46E-06
57LA   1Ul   5 . 3 UF- 10  1 bhF    -In  2.7 1E-1 1
        --S137    5.98E-05  7.760-05        5.35[-05        NO  DATA    2.78E-q5  9.40E-06 1.052-06 CS13'i    4.14E-08  7.767-08        4.0jE-38        NO  ,ATA    6.OE-09    6.07E-09 2.33E-13 a139    1.17-.-10          -14    3.42-12        NO  DATA    7.78E-14  4.70E-07 1.120-07 A!!
57LA                        ,.88E-1 I    9.bSE-1 2                      0.0            7.02F-07      2.ULF-07 I ,bQE-Ob                      0.0
                                                      1.109-45
                                                          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)
TABLL E-7,    CONT'D
  NUCLIDE    BONE     LIVER     TOTAL BODY    THYROID     KIDNEY                     GI-I.1.1
                                  PAGE  3 OF  3 INHALATION DUSE FACTORS' FOR ADULTS
88RA 223  I .80F-0O  2.77E-07    3.bOE-05    n.0     7.8SE-nb      2.5SE-02   2.B4E-O0
                            (MREM PER PCI INHALED)
88RA 224  1.98F-O5    4.7BE-08   3.96E-06    0.0      1.35E-Ob      q,78-03      3.0 E-Ou
NUCLICE      BONE   LIVER     T.BcY        THYROID KIDNEY      LUNG   GI-LLI
68RA 225  3,00E-0O    3.56F-07    9.13E-02    0,0      I .OIE-05    2.92E-02    2.71E-Oa
sA140,  4.F8E-O6 b.13F-09   1.21E-07    NO DATA  2.O9E-09 1.59E-04  2.73F-05
88RA  22b 1.25E-01    2.39E-06                040      6.77E-05       1 .17E-01  2.94E-0O
-AI41   1.25E-11 9.41tz-15  4.2CE'-13  NO DATA  8.75E-15 2.42E-07 1.45E-17 RAI42   3.29E-12 3.38E-15   2.07E-1I   NO DATA   2.96E-15 I.49E-O  1.96E-26 LA140   4.30E-C8 2.171-08   5.73E-09    NU DATA  NO DATA .1.70E-0.5 5.73E-05 LA142    8.54E-1i 3.88E-11   9.65E-12   NO DATA  NO DATA   7.91F-07 2.64E-07 CE4I1    2.49E-O0 1.69;--06   1.91E-07   NO DATA   7.83E-07 4.52E-05  1.50E-05
8BRA  22A  4,41E-02   1.23E-Ob    4.76E-02    0.0      3.QSE-0O      1. 61E-01I 5.00&#xa3;-05
;E143   2.33E-08 1.72E-o0   1.91E-O9   NO DATA  7.60E-0   9 .97E-06 2.83E-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
-E144   4.29E-04 1.79E-04   2.30E-05   NO DATA  1.ObE-04  9.72E-04 1.02E-04 PR143   1.17E-06 4.69E-07   5.80E-O8   NO DATA  2.70E-07 3.51E-05  2.50E-05 PR144   3.76E-12 1.56E-12    1.91E-13   NO DATA 8.RIE-13 1.27E-07  2.69E-18 OD147 6.59E-07 7.62E-07   4.56E-08    NO DATA 4.45E-07 2.76E-05 2.16E-05 w 187   I.06E-09 B.85E-10   3.10E-IO   NO DATA NO DATA  3.63E-06  1.q4E-05 NP239  -2.87E-O8 2.S2E-09   1.55E-09   NO DATA  8.75E-09 4.70E-06 1.49E-05
9QTH  227  2. 17F-0O   3.92E-06    6.25E-06              2.22E-05      3. 78E-02    3. 3uE.-Oo
                                    1.109-46
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


TABLE C-2 TEENAGER INHALATION DOSE FACTORS
77
                                            (mrem/pCi inhaled)
  $                                      TABLE E-8 PAGE  1 OF 3 INHALATION DOSE FACTORS FOR TEENAGER
      NUCL IDE     A ONE     LIVER     TOlTAL 8B1)Y    THYROID   K I3NEY     LUNG       U 1-LI. I
                                  (NREM PER PCI INHALED)
     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
     14UCLICE    BONE     LIVER       T.BODY      THYROID KIDNEY     LUNG   GI-LLI
  11!INA  22    I*7bF-OS    1.76E-05     1.76E-05     i .7bE-05          I .76F-05    I .'J LE-Oh
     H    3  NO DATA  1.59E-07      1.59E-07    1.59E-07 1.59F-07 1.59E-07 1.59E-07 C   14  3.25E-06 6.C9E-07      6.09E-07    6.09E-07 6.09E-07 6.09E-07 6.09E-07
  27C0 55        0.0        2.20E-08 2.93E-OR          A,(                I .71E-OLI  1.1I F-05 bO    0).0                                  0.0
    1A 24    1.72E-06 1.72[-06     1.72E-06     1.72E-06 1.72E-06 1.72E-06 1.72E-06
  27CO                        1.55E-07 2.OhE-07                              I .07F-03    2.Q4lE-0'5
                          3 P- "32    2.36E-04 1. 7E-05      8.95E-06    NO DATA  NC DATA  NO DATA  1.16F-05 CR 51    NO DATA  NO DATA      1..69E-08    9.37E-09 3.842-09 2.62E-06 3,75E-07 MN 54   NO DATA  6.39F-06      1.OE-O6     NO DATA  1.59E-06 2.48E-04 8.35E-06 MN 56-    NO DATA  2.1 2 E-1O    3.15E-11     NO DATA  2.24E-10 1.90E-06 7.18E-06 FE-55     4.18E-06 2.98E-06      6.93E-07     NO DATA  NO DATA  1.55E-05 7.99E-07 FE 53    1.99E-06 4.62E-0.6    1.79E-06.   NO DATA  NO DATA L.91F-04 2.23E-05 CO 58.   NO DATA  2.59E-07     3.47E-07    NO DATA  NO DATA  1.68E-04 1.19E-05 CO 60    NO DATA  L.89E-06     2.48E-06   -NO DATA  NO DATA 1.09E-03 3.24E-.05 NI 63    7.25E-05 5.43E-06      2.47E-06     NO DATA  NO DATA  3.84E-05 1.77E-06
  38Sp B9        4,.84E-06  a3.0          1 .39E-07    0.0        (USE    3.13E-0LJ    4.4L2E -05
    'I 6&#xfd;5   2.73E-10 3.uo6-1l      1.59E-11    NO DATA  NO DATA 1.17E-06 4.59E-06 CU 64    NO DATA 2.54E-10     1.06E-10     NO DATA  8.01E-10 1392E-06 7.68E-06 LN 65   4.82E-06 1.67E-05     7.80E-06     NO DATA  1.08E-05 1.55E-04 5.83E-06
  38SR     90    I *.48E-03  0.0          9.01JE-05    0.0                ?.n7F-03
    *N 69    6.04E-12 1.15F-11     8.07E-13     NO DATA  7.53E-12 I.q8E-07 3.56F-08 HR 83   NO DATA  NO DATA      4.30E-00     NO DATA  NO DATA  NO DATA  LT E-24 L3R 84   NO DATA  NO DATA       5.41E-08     NO DATA  NO DATA  NO DATA  LT E-24 riR 85   NO DATA  NO DATA       2.29E-09 -NO DATA    NO DATA  NO DATA  LT E-24 RB 86   NO DATA  2.38E-05     1.05E-05- NO DATA    NO DATA  NO DATA  2.21E-06 R 8'3    NO DATA  6.82E-08      3.40E-08     NO DATA  NO DATA  NO DATA  3.65E-15 RB 89   NO DATA  4.402-08      2.9.1E-08    NO DATA  NO DATA  NO DATA  4.22E-17 SR 89    5.43E-05 NO DATA      1.56E-06     NO DATA  NO DATA  3.02E-04 4.64E-05 SR q3    1.35E-02 NO DATA      8.35E-04     NO DATA  NO DATA  2.06E-03 9.56E-05 SR 91    1.10E-08 NO DATA       4.39E-10    NO DATA  NO DATA  7.59E-06 3.24E-05 SR 92    1.19E-09 NO DATA       5.08EI-      NO DATA  NO DATA  3.43E-06 1.49E-05 Y 90    3.73E-07 NO DATA      1.OE-08      NO DATA  NO DATA  3.66E-05 6.99E-05 Y   91M  4.63E-11 NO DATA      1.77E-12     NO DATA  NO DATA  4.0OE-07 3.77E-09 Y   91   8.26E-05 NO DATA      2.21E-06    NO DATA  NO DATA  3.67E-04 5.11E-05 Y   92   1.84E-0q NO DATA      5.36E-11     NO DATA  NO DATA  3.35E-06 2.06E-05
                                                        0.n                            9.* bF-05
                                          1.109-47
  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.


1.109-51
TABLE  E-8,    CONTID
                                      PAGE 2 OF    3 lNHALtCTIOA DOSE FACTORS FOR TEFNAGFR
                            (MREM PER PCI INHALED)
IRJCLIDE    BONE    LIVFR        T.AODY        THYROID  KIDNEY      LUNG  GI-LLI
Y 93    1.69E-08 NO DATA      4.65E-10      NO DATA    NO DATA  1.04E-05 7.24E-05
!R 95    1.82E-05 5.73c-O      3.94E-06      NO DATA    8.42E-06  3.36E-04 1.86E-05 ZR 97    1.72E-08 3.40E-09      1.57E-09      NO DATA    5.15E-09  1.62E-05 7.88E-05 iDl 95  2.32E-06 1.29E--b      7.08E-07      NO DATA    1.25E-06  9.39E-05 1.21E-05 MO 99    AJ0 DATA 2.l1E-08    4.03E-09        40 CATA  5.14E-08  1.92E-05 3.36E-05 IC 99M  1.73E-13 4.83E-13      b.24E-12      NO DATA    7.20E-12 .1.44E-01 7.66E-07 TCIOI    7.40E-15 1.OE-14      1.03E-13      NO DATA    1.90E-13  F.34E-0O 1.09E-16 RU103    2.63E-07 NO CATA      1.12C-07      NO DATA    9.29E-07  9.79E-05 1.36F-05 RU1O5    1.40E-10 NO DATA      5.42E-11      NO DATA    1.76E-0O  2.27E-06 1.13E-05 RULOb    1.23F-05 NO DATA      1.55E-06      NO DATA    2.38E-05  2.01E-03 1.20E-04 AGtlOM  1.73E-06 1.64E-Ob      9.99E-0-7    NO DATA    3.13E-06  B.44E-04 3.41F-05 TE12SM  6.lOE-07 2.80E-07      8.34E-08      1.75E-07  NO DATA  6.70E-05 9.38E-06 TE127M  2.?5E-06 1.CF-0O      2.73E-07      5.48E-07  8.17E-06  2.07E-04 1.99E-05 TE127    2.51E-10 1.14F-1O      5.52E-11      1.77E-10  9.1OE-1O  1.40F-06 1.OIE-05 rE129m  1.74E-06 8. 2 3E-07  2.81E-07        5.72E-07  6.49E-06  2.47E-04 5.06E-05 TF129    8.87E-12 4.22E-12    2.29E-12      6.4RE-12  3.32E-11  4.12E-07 2.02E-07 rEl31    1.23E-08 7.51E-09      5.03E-09      '.3/406E-09  5.49E-08  2.97E-05 7.76E-05 TEl31    1.97E-12 1.04E-12      6.30E-13      I..55E-12 7.72E-12  2.92E-07 1.89E-09 TE132    4.50E-08 3.63E-08    2.74E-08      3.07E-08  2.44E-07  5.61E-05 5.79F-05 I 130    7.80E-07 2.247-06      8.9oE-07      1.86E-04  3.44E-06  NO DATA  1.14E-06
1 131    4.43E-06 6.14F-06      3.30E-06      I.83E-03  1.05E-05  NO DATA  8.11F-07 I 132    1.99E-07 5.47E-07      l.q7E-07      1.89E-05  8.65E-07  NO DATA  1.59E-07
1 133    1.52F-06 2.,bE-Cb      7.78E-97      3.b5E-04  4.49E-06  NO DATA  1.29E-06 I 134    1.1IE-07 2.90E-07      1.05E-07      4.94E-06  4.58E-07  NO DATA  2.55E-09
1 135    4.62E-07 1.18E-Ob      4.36E-07      7.76E-05  1.86E-06  NO DATA  9.69E-07 CS134    6.28E-05 1.41E-O      b.8oE-05      NO DATA    4.69E-05  1.83E-05 1.22E-06 CS136    6.44E-06 2.42C-05      1.71E-05      NO DATA    1.38E-05  2.22E-06 1.36E-06 CS137    8.38E-05 1.06E-04      3.89E-O5      NO DATA    3.80E-05  1.51F-05 1.06E-06 CS138    5.82E-08 1.07E-07      5.59E-08      NO DATA    8.28E-08  9.84E-09 3.38E-1l BA[39    1.67E-10 1.IE-13      4.87E-12      NO DATA    I.IIE-13  8.08E-07 8.06E-07
                                        1.109-48


TABLE C-3 CHILD INHALATION DOSE FACTORS.
'TAtLiLE  E-8,  CONT'IC
                                              PAGE  3 OF  3 INHALATION 00[SE F.ACTORS FOR TEENAGER
                                    (MREM PER PCT INHALED)
        NULO        DOE    LIL          T.3CCY          THYOC      KIDNEY    LUNG    GI-L
        ,3&140O 6.84E-06 A. 58F-09    4.40E-07        NIO DATA  2.85E-n9  2.54E-04  2.86E-05
        1dA41  1.78E-11 l..12F-1[4  5.93[-13        NO DATA    1.23E-14  4.11E-07  9.33E-14
        !AA2    4.62E-12 4.63E-15)    2.84F-13        NO DATA,  3.92E-15  2.39E-07  5.99E-20
        LA140  5.99E-08 2.951E-08    7.82--09        NO UATA    NO DATA  2.68E-05  6.09E-05 LA142  1.200-10 5.31E-11      1.32E-11        NO DATA    N' DATA  1.27E-06  1.50[-06 CE141  3.55E-06 2.37&#xfd;-Oh    2.71E-07        NO DAT4    1.11L-06  7.67E-05  1.58E-05 CE143  3.32E-08 2.4/2E-08    2.70E-09        NO DATA    I.08R-08  1.63E-0'5 3.19E-05 CE144  6.11E-04 2.53E-04      3.23E-05        NO DATA    1.51E-04  1.67E-03  1.08E-04
    .  PR143  1.67E-06 6.64E-07      3.2SE-O8        NO DATA    3.86E-07  6.04E-05  2.67E-05 PI,144  5.37E-12 2.20E-12    2.72E-13-- N'O DATA        1.26E-12 .2.19E-C7  2.94E-14 NIC4
          147  9.83E-07 1.07E-Ob    6.41E-08        NO DATA    b.2qE-07  4.65E-05  2.28F-05 W 187  1.50E-09 1.22c-O9    4.29E-IC        NO DATA    NO DATA  5.q2E-06  2.21F-05
      .. P239  4.23E-08 3.99E-09    2.21E-09        NU DATA    1.25E-08  8.11E-06  1.65E-05 i4 4
                                                1.109-49 O-.


(mrem/pCi inhaled)
TABLE E-9 PAGE  1 OF 3
     NUCLIDE      BONE      LIVER     TOTAL BODY     T-4YR310    KI )NFY        LJN.G        GI-LLI
                    -  INHALATION  DCSE FACTORS FOR CHILD
  IH      3  0.0        2.03E-07   2.03E-n7      ?.03E-07                 2.03E-07       2. 03R -07
                            (MREM  PER PCI INHALED)
   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
NUCLIUE     BONE      LIVER      T.BOCY      THYROID  KIDNEY    LUNG    GI-LLI
27C0 5a                  0.t1F-n8    7.?3E-08      0.0                      3.,O*E-OLi     9. 1,* -0o
11  3 NO DATA   3.04E-97    3.04E-07     3.04E-07  3.04E-07 3.04E-07   3.04E-07 C 14   9.70E-06 1.82E-06     1.82E-06     1.82E-06 1.82E-06 1.82E-06   1.82E-06 NA.24  4..35E-06 4.35:-06     4.35E-06    4.35E-06  4.35E-C6 4.35E-06  4.35E-06 P   32. 7.04E-04 3.CgE-05     2.671-05     NO DATA  NO DATA  Nn DATA    1.14E-05 CR 51. NO DATA  NO DATA      4.17E-08     2.31F-O8  6.57E-09 4.59E-06., 2.93E-07 MN 54   '4O DATA  1.16:-05     2.57E-Ob     NO DATA  2.71E-06 4.26F-04  6.19F-06 MN 56  NO DATA  4.48E-10     8.43E-11    NO DATA  4.52E-10 3.55E-06  3.33E-05 FE 55  1.28E-05  6.D0E-0o    2.10E-06    NO DATA   NO DATA  3.OOE-05   7.75E-07 FE 59   5.59E-06  9.C4E-06    4.51E-06    NO DATA  NO DATA  3.43E-04   1.91E-05 CO 58  NO DATA  4.79E-O7    8.55E-07    NO DATA  NO DATA  2.99E-04  9.29E-06 CO 60  NO DATA  3.55E-06    6.12E-06    Nil DATA  NO DATA  1.91E-03  2.60E-05 NI 63  2.22E-04  1.25E-05     7.56E-06     NO DATA  NO DATA  7.43E-05  I.71E-06
27C0    60    0.0        2.qOF-07    5.07E-n7      0.0          (USE        1.67E-03      2.H3F-0%
;4I 65  8.08E-10  7.99E-11    4.44E-11    Nfl DATA  NU DATA  2.21E-06  2.27E-05 CU 64  NO DATA  5.39E-10    2.90E-10    NO DATA  1.63E-09 2.59E-06  q.92E-06 ZN 65  1.15E-05 3.06E-05     1.90E-05    NO DATA  1.93E-05 2.69E-04  4.41E-06 ZN 69  1.81E-[1  2.61E-11    2.41E-12    NO DATA  1.58E-11 3.84E-07  2.75F-06 MR 83  NO DATA  NO DATA      1.28E-07    NO DATA   NO DATA  NO DATA    LT E-24 aR 84  NO DATA  NO DATA      1.48E-07   NO DATA  NO DATA  NO DATA    LT E-24
3ASR    89    I..45E-05   0.0        4.16E-07      0.0                _____  . 0E-Oa    I.56F -05
!R 85  NO DATA  NO DATA     6.84E-09      NO DATA. NO DATA  NO DATA    LT E-24 R( 86  NO DATA  5.36E-05      3.09E-O5    NO DATA  NO DATA  NO DATA   2.16E-06 RE' 88  NO DATA  1.52E-0T      9.90E-08    NO DATA  NO DATA  NO DATA    4.66E-09 RB 89  NO DATA   9.33E-08      7.8.E-O8    NO DATA  NO DATA- NO DATA    5.11E-1O
38SR    qO    4.A3F-03    0.0        2.70E-14      0.0                          *.OOE-n3 Q1     1
SR 89  1.62E-04  NO DATA       4.66E-06    NO DATA  NO DATA  5.83E-04   4.52E-05 SR 9O  2.73E-02  NO DATA      1.74E-03     NO DATA  NO DATA  3.99E-03   9.28E-05 SR  9L  3.28E-08  NO    DATA    1.24E-09    NO  DATA  NO  DATA 1.44E-05   4.701-05 SR  92  3.54E-09  NO   DATA   1.42E-10    NO DATA  NO  DATA 6.49[-06  6.55E-05 Y   90  1.1IE-06  NO    DATA    2.99E-08    NO DATA  NO  DATA 7.07E-05   7.24E-05 Y  91P  1.37E-1O NO    DATA    4.98E-12.   NO DATA  NO  DATA 7.60F-O0  4.64E-07 Y  91  2.47E-04  NO    DATA   6.59E-06     NO DATA  NO  DATA 7.10E-04  4.97E-05 Y  92  5.50E-09  NO DATA       1.57E-1O     NO DATA  NO DATA  6.46E-C6  6.46E-05
                                                                                                  ,EF-Ob
                                      1.109-50
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.


1.109-52
TABLL    E-9,  CONTOD
                                            PASE 2 OF 3 INHALATION DLSE FACTORS FOR CHILD
                                    (MRE&#xfd;M PER PCI INHALED)
            I DUCLIE BU.E    LIVER    T. LsOGY      THYROID  KIDNEY    LUNG    GI-LLI
    Y 93        5.04E-08  NO DATA    1.38E-09      NO DATA  NO DATA  2.0IE-05 1.05E-04 ZaR 95      5.13E-05  1.13E-05    1.OOE-05      NO DATA  1.61E-05 6.03E-04 1.65E-05 IR 97      5.07E-08  7.34E-09    4.32E-09      NO DATA  1.05E-08 3.06E-05 9.49E-05
    "NA 95      6.35E-06  2.48E-06    1.77E-06      NO DATA  2.33E-06 1.66E-04 l.OOE-05 IMO99      NO DATA  4.66E-08    1.15E-08      NO DATA  1.06E-07 3.66E-05 3.42E-05 TC 99'      4.81E-13  9.41E-.13  1.56E-11      NO DATA  1.37E-11 2.57E-C7 1..0E-06 TC10        2.19E-14  2.30E-14t  2.91E-13      NO DATA  3.92E-13 1.5RE-07 4.41F-09 PU103      7.55E-07  NO DATA    2.90E-07      NO DATA  1.90E-06 1.79E-04 1.21E-05 RUIO5      4.13E-1O  NO DATA    1.5OE-10      NO DATA  3.63E-10 4.30E-06 2.69E-05 RU106      3.68E-05  NO DATA    4.57E-06      NO DATA  4.97E-05 3.87E-03 1.16E-04 AGILOM      4.56E-06  3.08E-06    2.47E-06      NO DATA  5.74[-06 1.48E-03 2.TIE-05 TEI25M      1.82E-06  6.29E-07    2.47E-07      5.20E-07 NO DATA  1.29E-04 9.13E-06 TE127M      6.72E-06  2.31E-06    8.loE-07      1.64E-06 1.72E-05 4.OOE-04 1.93E-05 TE127      7.49E-10  2.57E-10    1.65E-10      5.30E-iO 1.91E-09 2.71F-06 1.52E-05
    1E129M      5.19E-C6  1.85E-06    8.22E-07      t.71E-06 1.36E-05 4.76E-04 4.91E-05 TE129      2.b4E-11  9.45E-12    6.44[-12      1.93E-11 6.94L-1i 7.94E-07 6.89E-06 TE131m      3.63E-08  1.60E-08    1.37E-08      2.64E-08 1.08E-07 5.56E-05 8.32F-05 rE131      5.87E-12  2.28E-12    1.78E-12      4.59E-12  1.59s-Il 5.55E-07 3.60E-07 TE132      1.30E-07  7.36E-08    7.12E-08      8.58E-08 4.79E-07 1.02E-04 3.72E-05
      1 .1.30    2.21E-06  4.43E-06    2.28E-06      4.99E-04  6.61L-06 NO DATA  1.38E-06
      1 131      1.30E-05  1.30E-05    7.37F-Ob      4.39E-03 2.13E-05 NO DATA  7.68E-07
      1 132      5.72E-07  1.10E-06    5.01E-07      5.23E-05 1.69E-06 NO DATA  8.65E-07
    1 133      4.48E-06  5.497-06    2-.08E-06      1.04E-03 9.13E-06 NO DATA  1.48E-06
      1 134      3.17E-07  5.84E-07    2.69E-07      1.37E-05 8.92E-07 NO DATA  2.58E-07
        [35    1.33E-06  2.36E-06    1.12E-06      2.14[-04  3.62E-06 NO DATA  1.20E-06 CS14        1. 76E-04 2.742-04    6.07E-05      AD DATA  8.93E-05 3.27E-05 1.04E-06 CS136      1.76E-05  4.62E-05    3.14E-05      NO DATA  2.58E-05 3.93E-06 1.13E-06 CS137      2.45E-04  2.23E-04    3.47F-05      NO DATA  7.63E-05 2.81E-05 9.78E-07 CS138      1.71E-07  2.27E-07    1.50E-07      NO DATA  1.68E-07 1.84E-08 7.29E-08
    , A139      4.98E-10  2.66F-13    1.45E-1i      NO DATA  2.33E-13 1.56E-06 1.56E-05 l0a,


TABLE C-4 INFANT INHALATION DOSE FACTORS
TABLE E-9,    CONTIC
                                            (irirem/pCi inhaled)
                                  PAGE 3 OF 3 INHALATION   DOSE FACTORS FOR CHILD
    NUCLIDE       S O:N F  LIVER        TDIAL 3J)Y                    KI NE Y   LU NC        GI-LLI
                          (MREM  PER PCI INHALED)
                0.0          3. 07E -n7    3.07E-07                            3.07E-07      3.07F-n7
NUCLIDE     BONE    LIVER     T.RODY       THYROID KIDNEY    LUNG   GI-LLI
                                                            3.07E-07 bC      1"                              3.bOE-06        3.SAE-06             3.bOE-Ob      3.OF-Oh
GA140  2.00E-05  1.75E-08    I.I7E-06     NO DATA  5.T7E-09 4.71E-O4 2.75E-05 BA[41  5.291E-11 2.95E-14    1.72F-12     NO DATA   2.56E-14 7.89E-07 7.44E-08 BA142  1.35E-11  9.73E-15   7.54E-13    NO DATA  7.87E-15 4.44E-07 7.41F-10
                3.6OE-O0      3.6OF-06
LAI40   I.74E-07  6.OBF-08  2.04E-08     NO DATA   NO DATA  4.94E-05 6.IOE-05 LAI42   3.50E-10  1.I1E-IO   3.49E-LI    Nfl DATA  NO DATA  2.35F-06 2.05E-05 CEI14   1.06E-05  5.28E-06   7.83E-07     NO DATA  2.31E-06 1.47E-04 1.53E-05 CE143  9.89E-o8  5.37L-08   7.77E-09     NO DATA  2.26E-OB 3.I2E-05 3.44E-05 CE144  I.B3E-03  5.72E-04   9.77E-05    NO DATA  3.17E-04 3.23E-03 1.05E-04 PR143  4.99E-06  1.50E-06  2.47E-0.7     NO DATA  8.1IE-07 1.17E-04 2.63E-05 PR144  1.b6E-11  4.99E-12   8.10E-13     NO DATA  2.64E-12 4.23E-07 5.32E-08 ND147  2.q211-06 2.36E-06   1.84F-07    NO DATA  1.30E-06 8.87L-05 2.22F-05 W 187   4.*dE-09  2.61[-09   1.17F-09     NO DATA  NC DATA 1.1LF-05 2.46E-05 NP239   1.26E-07 9.04-09    6.35E-09     NO DATA   2.63E-OB 1.5TE-05 1.73E-05
                                                                    0
                                    1.109-52
                                            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
TA13LE E-10
                                                      .
                                                              PAGE      1 OF 3 INHALATION DOSE FACTORS FOR              INFANT
                                                    (MREM PER PCI INHALED)
    NUCLIDE            BONE            LIVER            T.3ODY            THYROID  KIDNEY      LUNG    GI-LLI
    H      3      NO DATA            4.62E-07          4.62E-07          4.62F-67  4.62E-07  4.62E-07  4.62E-07 C    14        1.89E-05          3.79C-06          3.79E-06          3.79P-06  3.79E-06  3.79E-06  3.79E-06 NA  24        7.54E-06          7.54E-06          7.54E-06          7.54E-06  7.54E-06  7.54E-06  7.54E-06 P    32        1.45E-03          8.03E-05          5.53E-05          NO DATA  NO DATA  NO DATA    1.15E-05 CR 51          NO DATA          NO DATA            6.31E-08          4.11E-08  9.45E-09  9.17E-06  2.55E-07 MN 54          NO DATA          1.81E-05          3.56[-06          NO DATA  3.56E-06  7.14E-04  5.04E-06 MN 56          NO DATA          1.10E-09          1.58E-10          NO DATA  7.86E-10  P.95E-06  5.12E-05 FE 55          1.41E-05          8.39L-Ob          2.38E-06          NO DATA  NO DATA ' 6.21E-05  7.82E-07 FE 59          9.69E-06          1.b6E-05          6.77E-06          NO DATA  NO DATA  7.25E-04  1.77E-05 CO 58          NO DATA          8.71E-07          1.30E-06          NO DATA  NO DATA  5.55E-04  7.95F-06 CO 60          NO DATA          5.73E-06          8.41E-06          NO DATA  NO DATA  3.22E-03  2.28E-05 NI 61          2.42E-04          1.46E-05          8.29E-06          NO DATA-  NO DATA  1.49E-04  1.73E-06 NI 65          1.71E-09          2.303-10          8.79E-11          NO DATA  NO DATA  5.80E-06  3.58E-05 CU-64          NO DATA          1.34E-09          5.53E-10          NO DATA  2.84E-09  6.64E-06  1.07E-05 ZN 65          1.38E-05          4.,,7F-05          2.22E-05          NO DATA  2..32E-05 4.62E-04  3.67E-05
(01 7N 69          3.P5E-11          6.91g-ll          5.13E-12          NO DATA  2.87E-I1  1.05E-06  9.44E-06 RR 83'        NO DATA          NO DATA            2.72E-07          NO DATA  NO DATA  NO DATA    LT F-24 HR 84          NO DATA          NO DATA            2.86E-07          NO DATA  NO DATA  NO DATA    LT E-24 RR 8>        &#xfd;NO DATA          NO DATA            1.46E-08          NO DATA  NC DATA  NO DATA    LT E-24 IB 8b          NO DATA            1.36E-04          6.30E-05          NO DATA  NO DATA  NO DATA  - 2.17E-06
    '&#xfd;B 88        N(l UATA          3.98F-07          2.0DE-O7          NO DATA  NO DATA  NO DATA    2.42E-07 RB 89          NO DATA          2.29E-07          1.47E-07          NO DATA  NO DATA  NO DATA    4.87E-08 SR 89          2.84E-04          NO DATA            8.15E-06          NO DATA  NO DATA  1.45E-03  4.57E-05 SR 90          2.92E-02          NO DATA            1.85F-03          NO DATA  NC DATA  8.03E-03  9.3b6-05 SR 91          6.83E-O          NO DATA            2.47E-09          NO DATA  NO DATA  3.76E-05  5.24E-05 SR 92          7.50E-09          NO DATA            2.79E-10          NO DATA  NO DATA  1.70E-05  1.00E-04 Y 90          2.15L-06          NO DATA            6.30E-08          NO DATA  NO DATA  1.92F-04  7.43E-05
    ----------------------------------------------------------------------------
    Y    91,      2.AIE-10          NO DATA        ,  9.qOE-12          NO DATA  NO DATA  1.99E-06  1.68E-06 Y    91        '.?OE-04          NO DATA            1.12E-05          NO DATA  NO DATA  1.75E-03  5.02E-05 Y    92        1.L7E-08          NO DATA            3.29E-10          NO DATA  NO DATA  1.75E-05  9.04E-05
                                                                  1.109-53


This yields CV 4 (ro)    = 3.17 x 107 Q74 [x/Q'](r,) 0.11/0.16                                          U
TABLE E-1Ot    CONTID
                          = 2.2 x 107 Qi4 [x/Q'J(r,O)                                          (C-8)
                                    PAGE 2 OF 3 INHALATION DOSE FACTORS FOR      INFANT
where Cv 4 (r,O)          is the concentration of carbon-14 in vegetation grown at location (r,e), in pCi/kg;
                            (MREM PER PCI INHALED)
                  !Q14     is the annual release rate of carbon-14, in Ci/yr;
NUCLIDE    BONE    LIVER      T.BODY        THYROID  KIDNEY    LUNG    GI-LLI
              0.11         is the fraction of total plant mass that is natural carbon, dimensionless;
Y 93    1.07E-07  NO DATA    2.91E-09      NO DATA    NO DATA  5.46E-05 1.19E-04 ZR 95  8.24E-05  1.99E-05    1.45E-05    NO DATA    2.22E-05  1.25E-03 1.55E-05 ZR 97  1.07E-07  1.83E-08    8.36E-09    NO DATA    1.85E-08  7.88E-05 1.0OE-04&#xfd;
              0.16          is equal to the concentration of natural carbon in the atmosphere,     in g/M 3 and
NB 95  1.12E--05 4.59E-06    2.70E-06    NO DATA    3.37E-06  3.42E-04 9.05E-06 Mo 99  NO DATA  1.18-07      2.31E-08    NO DATA    I1R9E-07  9.63E-05 3.48E-05 TC 99M  9.98E-13  2.06E-12    2.66E-11    NO DATA    2.22E-11  5.79E-07 1.45E-06 TCIOI  4.65E-14  .5.98E-14    5.80E-13    NO DATA    6.99E-13  4.17E-07 6.03E-07
      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).
'RUI03  1.44E-06  NO DATA      4.85E-07    NO DATA    3.03E-06  3.94E-04 1.15E-05 RUI05  8.74E-10  NO'DATA    '2.93E-10     NO DATA    6.42E-10 1.12E-05 3.46E-05 RU106  6.20E-05  NO DATA      7.7.7E-06    NO DATA    7.61E-05  8.26E-03 1.17E-04 AGLIOM  7.13E-06. 5.16E-06    3.57E-06    NO DATA    7.80E-06' 2.62E-03 2.36E-05 TE125M  3.40E-06  1.42E-06    4.70E-07    1.16E-06  NO DATA  3.19E-04 9.22E-06 TE127M  1.19E-05  4.93E-06    I1.4BE-D6    3.48E-06  2.68E-05  9.37E-04 1.95E-05 TE12T  1.59E-09  6.81E-10    3.49E-10    1.32E-09  3.47E-09  7.39E-06 1.74E-05 TE129M  I.OIE-05  4.35E-06    1.59E-06    3.91E-06  2.27E-05  1.20E-03 4.93E-05 TE129  5.63E-11 2.48E-1I    1.34E-11     4.82E-11  1.25E-10  2.14E-06 1.88E-05 TE131M  7.62E-08  3.93E-08    2.59E-08    6.38E-08  1.89E-07  1.42E-04 8.51E-05 TE131  1.24E-11  5.87E-12    3.57E-12     1.13E-l  2.85E-11 1.47E-06 5.87E-06 TE132  2.66E-07  1.69E-07    1.26E-07      1.99E-07  7.39E-07  2.43E-04 3.15E-05
      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:
1 130  4.54E-06  9.91E-06     3.98E-06      1.14E-03  1.09E-05  NO DATA  1.42E-06
            CV(r,o) = 3.17 x 107 QT[X/QJ](r,O)(0.75)(0.5/H)
.1 131  2.71E-05  3.17E-05    1.40E-05      1.06E-02  3.70E-05  NO DATA  7.56E-07
                        = 1.2 x 10 7 Qi[X/Q'](re)/H                                            (c-9)
1 132  1.21E-06  2.53E-06    8.99E-07    1.21E-04  2.82E-06  NO DATA  1.36E-06
where Cv(r,o)            is the concentration of tritium in vegetation grown at location (r,e), pCi/kg;
1 133  9.46E-06  1.37E-05    4.OE-06      2.54E-03  1.60E-05  NO DATA  1.54E-06
                  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;
1 134  6.58E-07  1.34E-06    4.75E-07      3.18E-05  1.49E-06  NO DATA  9.21E-07 I 135  2.76E-06  5.43E-06    1.98E-06    4.97E-04  6.05E-06  NO DATA  1.31E-06 CS134  2.83E-04  5.02E-04    5.32E-05    NO DATA    1.36E-04  5.69E-05 9.53E-07 CS136  3.45E-05  9.61E-05    3.7BE-05    NO DATA    4.03E-05  8.40E-06 1.02E-06 CS137    3.92E-04 4.37F-04    3.25E-05    NO DATA    1.23E-04  5.09E-05 9,.53E-07 CS138  3.61E-07  5.58E-07    12.84E-OT    NO DATA    2.93E-07  4.67E-08 6.26E-07'
                0.5         is the ratio of tritium concentration in atmospheric water to tritium con--
BA139    1.06E-09 7.03E-13    3.07E-11    NO DATA    4.23E-13  4.25E-06 3.64E-05
                            centration in plant water, dimensionless; and
                                      1.109-54
              0.75          is the fraction of total plant mass that is water, dimensionless.


The deposition rate from the plume is defined by:
TABLE  E-1O,  CONT'D
            dC(r.o) = 1.1 x 108ai(r,e)Qj                                                        (C-10)
                                  PAGE 3 OF    3 INHALATION  DOSE FACTORS FOR    INFANT
where
                          (MREM  PER PCI INHALED)
        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
NuCLIOE    BONE    LIVER      F.BODY        THYROID  KIDNEY    LUNG  GI-LLI
      1.1 x 108            is the number of pCi per Ci (1012)   divided by the number of hours per year
BA140  4.OOE-05 4.OOE-08    2.07E-06      NO DATA    9.59E-09 1.14E-03 2.74E-05 BAl4L  L.12E-1O 7.70r-14    3.55E-12      NO DATA    4.64E-14 2.12E-06 3.39E-06 BA142  2.84E-11 2.36E-14    1.40E-12    NO DATA    1.36E-14 1.I1E-06 4.95E-07 LAI40  3.61E-07 1.43E-07    3.68E-08    NO DATA    NO DATA  1.20E-04 6.06E-05 LA142  7.36E-10 2.69E-1O    6.46E-II      NO DATA    NO DATA  5.87E-06 4.25E-05 CE141  1.98E-05 1.19E-05    1.42E-06    NO DATA    3.75E-06 3.69E-04 1.54E-05 CE143  2.09E-07 I.18E-07   I.58E-08      NO DATA   4.03E-08 8.30E-05 3.55E-05 CE144  2.28E-03 8.05E-04    1.26E-04    NO DATA    3.84E-04 7.03E-03 1.06E-04 PR143  1.OOE-05 3.74E-06    4.99E-07      NO DATA    1.41E-06 3.09E-04 2.66E-05 PR144   3.42E-1I 1.32E-11    1.72E-12    NO DATA    4.80E-12 1.15E-06 3.06E-06 NDI47  5.b7E-O6 5.81F-06    3.57E-07      NO DATA    2.25E-06 2.30E-04 2.23E-05 W 187   9.26E-Og 6.44E-09    2.23E-09     NO DATA    NO DATA 2.83E-05 2.54E-05 NP2.39 2.65E-07 2.37E-08    1.34E-08    NO DATA    4.73E-08 4.25E-05 1.78E-05
                            (8760).
                                    1.109-55
      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)
TABLE E-1i PAGE 1 OF 3 INGESTION DOUSE FACTORS FOR ADULTS
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).
                                    ( M REM PER PCI INGESTED)
      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).
NUCLILE    BONE      LIVER              T.BOGY                THYROID        KIDNEY            LUNG           GI-LLI
      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    3 NO DATA    I.05E-07            I.05E-07              1.05E-07        1.05E-07        1.05E-07      1.05E-0
11 and 12).   All nuclides except noble gases, tritium, carbon-14, and the iodines are treated as particulates.
C   14  2.84E-06  5.68E-07            5.68E-07              5.68E-07        5.68E-07        5.68E-07      5.68E-0
NA  24  1.70E-06  1.70E-06            l.TOE-06              1.70E-06        1.70E-06        1.70E-06      1.70E-O
P  32  .1.93E-04  1.20E-05            7.46E-06              NO DATA          NC DATA        NO DATA        2.17E-0!
CR  51  NO DATA    NO DATA            2.6bE-09              1.59E-09        5.86E-I0        3.53E-09.     6.69E-0          .
MN  54  NO UATA  4.57E-06            8.72E-07              NO DATA          1.36E-06        NO DATA        1.40E-0
MN 56  NO DATA    1.15r-07            2.04E-08              NO DATA          1.46E-07        NO DATA        3.67F-06 FE 55    2.75E-06  1.90F-O0            4.43E-07              NO DATA          NO DATA        1.06E-06      1.09E-06 FE 59    4.34E-06  1.02E-05            3.91E-06              NO DATA          NO DATA        2.85E-06      3.40E-05 CC 58    NO DATA  7.45E-07            1.67E-06              NO DATA          NO DATA        NO DATA        i.51F-05 CC 60   NO DATA  2.14F-06            4'.72 -0 6            NO DATA          NO DATA        NO DATA        4.02E-05 ilI 63  1.30E-C4  9.OIE-Ob            4.36E-06              NO DATA          NO DATA        NO DATA        I.88E-06 NI 65    5.28E-07  6.86E-08            3.13E-08              NO DATA          NO DATA        NO DATA        1.7lE-06 CU 64    NO DATA  8.33E-08            3.91E-08              NO DATA          2.10E-07        NO DATA        7.10E-06 ZN 65    4.847E-06 1649-65            0.gE-06                NO DATA          1.03E-05        NO DATA        9.70E-06 ZN 69    1.03E-08  1.97E-08            1.37E-09              NO DATA          1.28E-08        NO DATA        2.96E-09 BR 83    NO DATA  NO DATA            4.02E-08              NO DATA          NO DATA        NO DATA        5.79E-08 BR 84    NO DATA  NO DATA            5.2IE-08              NO DATA          NO DATA        NO DATA        4.09E-13 BR 85    NO DATA  NO DATA            2.14E-09              NO DATA          NC DATA        NO DATA        LT E-24
'R8 86    NO DATA  2.1E-05            9.83E-06              NO DATA          NO DATA         NO DATA        4.16E-06 RB 88    NO DATA  6.05E-08            3.21E-08              NO DATA          NO DATA        NO DATA        8.36E-1.9 RB 89    NO DATA  4.01E-08            2.82E-08              NO DATA          NO DATA        NO DATA        2.33E-21 SR 89    3.08E-04  NO DATA            8.84E-06              NO DATA          NO DATA        NO DATA       4.94E-05 SR 90    7.58E-03  NO DATA            .1.8bE-03              NO DATA          NO DATA        NO DATA        2.19E-04 SR 91    5.6TE-06  NO DATA            2.29E-07              NO DATA          NC DATA        NO DATA        2.70E-05 SR 92    2.15E-06  NO DATA            9.30E-08              NO DATA          NO DATA        NO DATA        4.26E-05 Y 90    9.62E-09  NO DATA            2.58E-1O              NO DATA          NO DATA        NO DATA        1.02E-04 Y  91M  9.09E-11 NO DATA            3.52E-12               NO DATA          NO DATA        NO DATA        2.67E-IO
Y  91  1.41E-07  NO DATA            3.77E-09              NO DATA          NO DATA        NO DATA        7.76E-05 Y  92  8.45E-10  NO DATA            2.47E-1I              NO DATA          NO DATA        NO DATA        1.48E-05
                        - - - - -- - - -- -- -- -- - -- -- - - - - - - - - - -  - - - - - - - - - - - - - - - -  - - - -- .5:
                                                      1.109-56


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:
TAB3LE E-11,  C(JNT'D
                        Parameter                                Value
                                        PArE  2 or 3 INGESFION DOSE FACTOOS FOR ADULIS
                                                                      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
                                (MREM PER PCI INGESTFD)
                                                            60 days for stored vegetables tb     (soil exposure time)                      15 years (midpoint of reactor operating lifetime)
      NUCLICE    BONE    LIVER      T.BODY      THYROIC    KIDNEY    LUNG      GI-LLI
          All other parameters in this equation are given in Regulatory Position C of this guide.
    Y    93  2.68E-C9 NO DATA      7.40E-11    NO DATA    NO DATA  NO DATA    8.50F-05 ZR 95  3.04E-OR 9.75E-09    6.60E-09    NO DATA    1.53E-08  NO DATA    3.09E-05 ZR 97  1.68E-09 3.39=-10    1.55E-10    NO DATA    5.12E-10  NO DATA    1.05E-04 N8 95  6.22E-09 3.46E-09    1.86E-09    NO DATA    3.42E-0q  NO DATA    2.10E-05 MO 99   NO DATA  4.31E-06    8.20E-07    NO DATA    9.76E-06  NO DATA    9.99E-06 TC 99PI 2.47E-10 6.98=-10    8.89E-09    NO DATA    1.06E-08  3.42E-10  4.13E-07 TCioi  2.54E-10 3.66E-IC    3.59E-09    NO DATA    6.59E-09  1.87E-10  1.10E-21 RUIO3  1.85E-07 NO DATA      7.97E-08    NO DATA    7.06E-07  NO DATA    2.16E-05 RUIO!I  1.54E-08 NU DATA      6.03L-09    NO DATA    1.99E-07  NO DATA    9.42E-06 WU106  2.75F-06 NO DATA      3.48E-07    JO DATA    5.31E-06  NO DATA    1.78E-04 AG11OM  1.60E-07 1.48F-07    8.79E-08    NO DATA    2.91C-07  NO DATA    6.04E-05 T2125M  2.69E-06 9.712-07    3.59E-07    8.06F-07    1.09E-05  NO DATA    1.07E-05 TE127M  6.77E-06 2.42C-06    8.25[-07    1.73E-06  2.75E-05  NO DATA    2.27E-05 TE127  1.IE-07  3.95E-08    2.38E-O8    8.15E-06    4.48E-07  NO DATA    8.68E-06
      1TE129M 1.15E-05 4.29c-0o    1.82E-06    3.95E-06    4.80E-05  NO DATA    5.792-05 rE129  3.14E-08 I.18E-O8    7.c*E-O9    2.41E-08    1.32E-07  NO DATA    2.37E-08 TE131t  1.73E-06 8.46'-07    7.05E-07    1.34E-06  8.57E-06  NO DATA    8.40E-05 T1131  1.97E-08 8.23E-09    6.22E-09    1.62E-08  .. 63L-08 NO DATA    2.79E-C9
  .. r2132    2.52E-06 1.b3E-O6i    1.5.-E-06    1.8E-C6    1.57E-05  NO DATA    T.7.12E-05
      1 130  7.56E-07 2.23E-06    8.80E-07    1.89f:-04  3.48E-06  NO DATA  ' 1.92E-06 I 131  4.16E-06 5.95c-06    3.41E-06    1.95F-C3    1.02E-05 NO DATA    1.57E-06
      1 132  2.03E-07 5.43F-07    1.90E-07    1.90E-05  8.65L-07  NO DATA    1.02E-07
      [ 133  1.42E-06 2.'t7E-06    7.53E-07    3.63E-04  4.31E-06  NO DATA    2.22E-06
      1 134  1.06E-07 2.881-07    1.03E-07    4.99E-06    4.58E-07  NO DATA    2.51E-10
      1 1-35  4.43E-07 1.16C-06    4.23C-07    7.65E-05  1.86E-C6  NO DATA    1.31E-06 CS134  6.22E-05 1.48E-04    1.21E-04    NO DATA    4.79L-05  1.59E-05  2.59E-06 v    CS136  6.51E-06 2.571-05     1.85E-05    NO DATA    1.43E-05  1.96E-06  2.92E-06 CS137  7.97E-05 1.G9E-04     7.14E-05    NO DATA     3.70L-05  1.23E-05  2.11E-06 CS138  5.52E-OR 1.C9E-07    5.40E-08    NO DATA    8.01E-08 7.91E-09  4.65E-13 BA139  9.70E-08 6.91E-I      2.84E-09    NO DATA     6.46E-11  i.92E-11  1.72E-07
                                          1.109-57


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)
IL
where C'(r,a)        is the concentration in milk of nuclide i,   in pCi/liter;
                                      TABLF E-,I,     CONT'D
        CY(r,O)        is the concentration of radionuclide i in the animal's feed,   in pCi/kg;
                                            PACE  3 OF  3 INGESTION DOSE FACTORS FOR ADULTS
              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);
                                  AMREM PLR PCI INGESTED)
                                                    1.109-55
    NUCL I CE    BONE     LIVER      T. (3DY      THYROID  KIDNEY    LUNG  GI-LLI
    -3A140    2.03[-05  2.55E-08    I.33E-06    NO DATA    8.67E-09 1.46E-08 4.18E-05 r.A141    4.TIE-08  3.56E-1I    1.59E-09    NO DATA    3.31E-l1 2.02E-11 2.22E-17 OA142    2.13E-08  2.19E-11    1.34E-09    .40 DATA  1.35E-1I 1.24E-11 3.OOE-26 LA140    2.5OE-09  1.26>-09      3.33E-10    NO DATA    NO DATA  NO DATA  9.25E-05 LA142    1.28E-10  5.B2E--1    1.45E-l1    NO DATA   NC DATA  NO DATA  4.25E-07
    0E141    9..36E-09 6.33E-09    7.1[E-lC    NO DATA   2.94E-09 NO DATA  2.42E-05
    .E143    1.65E-09  1.22F-06    1.35E-1O      NO DATA  5.37E-10 NO DATA  4.56E-05
  'CE144      4.A8E-07  2.04E-07    2.62E-08      NO DATA  1.21E-07 NO DATA  1.65E-04 PR143    9.20E-O  3.69-!09    4.56E-10      NO DATA  2.13E-09 NO DATA  4.03E-05 P1I44    3.OIE-11  1.25E-11    1.53E-12      NO DATA  7.05E-12 NO DATA  4.33E-18 N0147    6.29E-C9  7.Z7E-09    4.35E-I0      NO DATA  4.25E-09 NO DATA  3.49E-05 k 19.7    1.03E-07  8.61E-08    3.OE-08      NO DATA  NO DATA  Nn DATA  2.82E-05 NP239    1.19E-09  1.1,7E-1O    6.45E-1I      NO DATA  3.65E-10 NO DATA  2.40E-05
                                              1.109-58


TABLE C-5 STABLE ELEMENT TRANSFER DATA
TABLE E-12 PAGE 1 OF 3 INGESTION-DOSE  FACTORS FOR TEENASER
            Biv        Fm(Cow)            Ff                      8.av    Fm(Cow)          Ff VES/S3IL 41LK (1/L)    MEATT(D/KG)
                              (MREM PER  PCI INGESTED)
ELEM     VEG/SOIL  MILK(CD/L        MEAT(D/XG)          ELEM
NUCLICE     BONE        LIVER      T.HnUY      THYROID   KIDNEY     LUNG  GI-LLI
                                                            SB  I.IE-02   I oSE-03      POE-03 H      4,BE O0     I ,OE02** 2.2E-02
II    3 NO DATA   1.06E-07     1.OE-07     1.06[-07  1.06E-07  L.06E-07 1.06E-O7 C    14  4.06E-06  e.12E-07     8.12E-O7   8.12F-07  8.12E-07 H.12E-07 8.12F-07 NA 24    2.30E-06  2.30E-06      2.30E-06   2.30E-06  2.30E-06  2.30E-06 2.30E-06 P   32  2.76E-04  1.71E-05     1.07E-05    NO DATA  NO DATA  NO DATA 2.32E-05 CR 51    NU DATA    NO DATA      3.6OE-09    2.OOE-09  7.99E-10  5.14E-09 6.05E-07 MN 54    NO DATA    5.90E-Ob      1.17E-06   NO DATA   1.76E-06 NO DATA 1.21E-05 MN 56    NO DATA    1.58E-07      2.8LE-08    NO DATA  2..OE-07- NO DATA  1.04E-05 FE 55    3.7BE-06  2.68F-06      6.25E-07    NO DATA  NO DATA  1.70E-06 1.16E-06 FE 59    5.87E-06     .iJE-05    5.29E-06    NO DATA  NO DATA  4.32E-06 3.24E-05
                    2,0E-O;                                TE I'3E 00   I.0E-03        7, 7E-02 HE     5.OE-02                      2,nE-02
'O 58    NO DATA    9.72E-07     2.24E-06    ND DATA  NO DATA   NO DATA  1.34E-05 CO 60    NO DATA    2.81E-06    6.33E-06    NO DATA  NO.DATA  NO DATA  3.66E-05
        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
*&#xfd;4I63  1.77E-04  1.25C-05    b.OOE-06    NO DATA  NO DATA  NO DATA  1.99E-06
* 2E-02"      
14I 65 7.49E-07  .9.57E-08    4.36E-08    NO DATA  NO.DATA  NO DATA 5.19E-06 CU 64   NO DATA    1.15E-07     5.41E-08    NO DATA  2.91E-07  NO DATA  8.92E-06 ZN 65    5.76E-06  2.COE-C5.     9.33E-06   NO DATA    1.28E-05 NO DATA  8.47E-06 LN69    1.47E-08   2.6OE-08     1.96E-09    NO DATA   I.R3E-O8 NO DATA  5.16E-08
* OE-03 B      1.2E-01    2,7E-0"
*R 83    NO DATA    NO DATA      5.74E-08    NO DATA  NO DATA  NO DATA  LT E-24
                                                                b,OE-03                  3.2E-03 C      5*5E" O0   1,2E-02          3.1IF-n2                              . GOE-O1***
  .9R84 NO DATA   N. DATA      7.22E-08    NO DAT3  NO DATA  NO DATA  LT E-24 bR 85  NO DATA    NO DATA      3.05E-09    NO DATA  NO DATA  NO DATA LT E-24 RB 86    NO DATA   2.98E-05     1.40E-05   NO DATA  NO DATA  NO DATA 4.41E-06 RB 88    NO DATA   8.52E-08      4.54E-08    NO DATA  NO DATA  NO DATA 7.30E-15 RB 89  NO DATA   5.50E-08     3.89E-08   NO DATA  NO  DATA NO  DATA 8.43F-17 SR 89  4.40E-04   NO DATA      1.26E-05   NO DATA  NO  DATA NO  DATA 5.24E-O5 SR 90  8.30E-03   NO DATA      2.05E-03   NO DATA  NO  DATA NO DATA 2.33E-04 SR
N      7.5E 00    2,2E*O.             .OE-02            LA 2,SE-03                  2.OE-04 B.OE-n2              CE                            1.2E-03
---     8.-- E-O6  ND-DATA      3.21E-07    NO DATA  ND   DATA ND  DATA 3.-6E-05 SR 92  3.05E-06  NO DATA      3.30E-07    NO DATA  NO   DATA NO  DATA 7.77E-05 Y    90  1.37E-08  NO DATA       3.69E-1O    NO DATA  NO DATA  NO DATA 1.13E-04 Y    91M 1.29E-10  NO DATA      4.93E-12    NO DATA  NO DATA  NO DATA 6.09E-09 Y    91 2.0IE-07  NO DATA      5.31E-09    NO DATA  NO DATA  NO DATA  8.24E-05 Y    92  1.21E-09   NO DATA      3.50E-11    NO DATA  NO DATA  NO DATA  3.32E-05
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
                                      1.109-59
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.


Ref. 3.               +t Ref. 18.
TAtLF E-12,    CONTDO
                                            PASE  2 OF 3 INGESTION DOSE FACTORS FOR TEENAGER
                                    (MREM PFR PCI INGESTED)
  NUCLI'2E      BONE        LIVER      T.tODY      THYROID      KIDNEY        LUNG        GI-LLI
  Y 93      3.83E-C9    NO DATA      1.05E-10    NO DATA      NC DATA      NO DATA      1.17E-04 ZR 95      4.12E-08    1.302-08    8.91+E-09    NO DATA      1.91E-08    NO DATA      3.OOE-05
  7R 97    2.37E-09    4.69E-1O      2.16E-10    ND DATA      7.11E-10    NO DATA      1.27E-04
  14 P 95    8.22E-09    4.5bE-09      2.51E-09    NO DATA      4.42E-Oq    NO DATA      1.95F-05 MO 99      NO DATA      6.03E-06    1.15F-06    NO DATA      1.38E-05    NO DATA      1.08E-05 TC 99M    3.32E-10    9.26E-10      L.20E-08    NO DATA      1.38E-08    5.14E-1O    6.08E-07 TCIDI      3.60E-10    5.127-10    5.03E-09    NO DATA      q.26E-09    3.12E-10    8.75E-17 RU103      2.55E-07    NO DATA      1.09E-07    NO DATA      8.99E-07    NO DATA      2.13E-05 RU105      2.18E-08    NO UATA      8.46E-09    40 DATA      2.75E-07    NO DATA      1.76E-05 RI)0ob    3.92E-06    NO DATA      4.94E-07    NO DATA      7.56E-06    NO DATA      1.88E-04 AGIIOM    2.05E-07    1.94E-07    1.18E-O7    NO DATA      3.70E-07    NO DATA      5.45E-05 TE125m    3.33E-06    1.382-06    5.12E-07    1.07E-06    NO DATA      NO DATA      1.13E-05 TF127M    9.67E-06    3.4iE-Ob    1.15E-06    2.30E-06    3.92L-05    NO DATA      2.41E-05 FE127    1.58E-07    5.60E-08    3.40E-08    1.09F-O7    6.40E-07    NO DATOS    1.2ZE-05 TE129M    1.63E-05    6.C5-O6      2.58E-06    5.2bE-06    6.82E-05    Nn DATA      6.12E-05
  ---------------------------------------------------------------------------------------------------
  TEL29      4.48E-08    1.'b7F-08    I.,0)E-08    3.20E-08    1.88E-07    NO DATA      2.45F-07
! TEl31m    2.44E-06    1.17E-Ob    9.76E-07    1.76E-06    1.22E-05    NO DATA      9.39E-05 TF131      2.79E-08    I.L52-08    8.72E-09    2.15E-08    1.22E-07    NO DATA      2.29[-09
    2E132    3.49E-06    2.21F-06    2.08E-06    2.33E-06    2.12E-05    NO DATA      7.ODE-05
  1 130    1.03E-06    2.98E-06    1.19E-06    2.43E-04    4.59E-06    NO DATA      Z.29E-06
  1 131      5.85E-O      8.19C-06    4.40E-06    2.39E-03    1.41E-05    NO DATA      1.62E-06
  1 132      2.79E-07    7.30E-07    2.62E-07    2.46E-05    1.15E-06    NO DATA      3.18E-07
      133    2.01E-06    3.41L-06    1.04E-06    4.76E-04    5.98E-06    NO DATA      2.58E-06 I 134    1.46E-07    3.87E-07    1.39E-07    6.45E-06    6.10E-07    NO DATA      5.10E-09
  1 135      6.10E-07    1.57E-06    5.82E-07    1.OIE-04    2.48E-06    NO DATA      1.74E-06 CS134      8.37E-05    1.97F-04    9.14E-05    NO DATA      6.26E-05    2.39E-05    2.45E-06 CS136      8.59E-06    3.38E-05    2.27E-05    NO DATA      1.84E-05    2.90E-06    2.72E-06 CS137      1.12E-04    1.49E-04    5.19E-05    NO DATA      5.07E-05    1.97E-05    2.12E-06 CS138      7.76E-08    1.49C-07    7.45E-08    NO DATA      I.IOE-07    1.28F-08    6.76E-11
  3A139    1.39E-07    9.78L-11    4.05E-09    NO DATA      9.22E-1i    6.74E-11    1.24E-06
                                                1.109-60


Ref. 13.
TABLE E-12,      CONT'D
                                      PAGE    3 OF 3 I:AGESTION DOSE      FACTORS FOR TEFNAGER
                              (MREM PER    PCT INGESTED)
WUCLTLE    BONE    LIVER        T.60OY        THYROID  KIDNEY      LUNG    GI-LLI
64140    2.84E-05  3.48E-09      1.83E-06      NO DATA    1.18E-08  2.34E-08 4.38E-05 RAI41    6.71E.-OR 5.('1E-11      2.24E-09      NO DATA    4.65E-11  3.43E-11  1.43E-13
'A142    2.99E-08  2.39E-11      1.84E-09      40 DATA  2.53E-11  1.9qE-11 9.18E-20
LA140    3.48E-09  1.71C-09      4.55E-10      NO DATA    NC DATA  NO DATA  9.82E-05 LA142    1.79E-10  7.95E-11      1.98E-11      NO DATA    NO DATA  NO DATA  2.42E-06 CE141    1.33E-O8  8.88'-09      1.02E-09      NO DATA    4.18E-09  NO D4.TA  2.54E-05 CE143    2.35E-09  1. 7 1E-0 6    1.91E-1O      NO DATA    7.67E-10  NO DATA  .5.14E-05 CF144    6.96E-07  2.88E-07      3.74E-68      NO DATA    1.72E-07  NO DATA  1.755-04 PR143    1.31E-08  5.23C-09      6.52E-10      NO DATA    3.n4E-O9  NO DATA  4.31E-05 PR144    4.30E-11  1.762-11      2.18E-12      NO DATA    1.01E-11  NO DATA  4.74E-14
;qU147  9.38E-09  1.02F-08      6.11E-10      NO DATA    5.q99L-Oq Nn DATA  3.68E-05
  187  1.46E-07  1.19F-07      4.11E-38      NO DATA    NO DATA  NO DATA  3.22E-05
'JP239  1.76E-Oq  1.66E-10      9.22E-11      ,,n DATA  5.21L-10  NO DATA  2.67E-05
                                        1 .109-61


1.109-56 E1
TABLE E-13 PAGE  I OF    3 INGESTION  DOSE  FACTORS    FOR  CHILD
                                        (MREM  PER PCI    INGESTED)
          NUCLIDE      BONE    LIVER      T.oOUY      THYROID      KIDNEY    LUNG    GI-LL!
          II  3    NO DATA  2.03E-O7    2.01E-07    2.03E-07      2.03E-OT 2.03E-07 2.03E-07 C  14    1.21E-05  2.42E-06    2.42E-06    2.42E-06      2.42E-06 2.42E-06 2.42E-06 NA 24    5.80E-06  5.80E-06    5.80E-06    5.80E-06      5.BOE-06 5.80E-06 5.80E-06 P  32    8.25E-04  3.86C-05    3.IE--O5      40 DATA      NO DATA  NO DATA  2.28E-0.5 CR 51    NO DATA  NO DATA      8.90E-09    4.94E-09      1.35E-09 9.02E-09 4.72E-07
4        MN 54    NO DATA  1.07E-05    2.85E-06    NO DATA      3.OD0-06 NO DATA  8.98E-06 MN 56    NO DATA  3.34E-OT    7.54E.-08    NO DATA      4.04E-O7 NO DATA  4.84E-05 I!        FE-55    1.1SE-05  6.IOE-06    1.89E-06    NO DATA      NO DATA  3.45E-06 1.13E-06 FE 59    1.65E-05  2.67E-05    1.33E-05    NO DATA      NO DATA  7.74E-06 2.78E-05 CO 58    NO DATA  1.8OE-06    5.51E-06    NO DATA      NO.DATA  NO DATA  1.05E-05 CO 60    NO DATA  5.29E-06    1.56E-05    NO DATA      NO DATA  NO .DATA 2.93E-05 NI 63    5.38E-C4  2.88E-05    1.83E-05    NO DATA      NO DATA  NO DATA  1.94[-06 NI 65    2.22E-06  2.09F-07    1.22E-07    NO DATA      NO DATA  NO DATA  2.56E-05 CU 64    NO DATA  2.45E-07    1.48E-07    NO DATA      5.92E-07 NO DATA  1.15E-05 ZN 65      1.37E-05 3.o5E-0      2.27E-05    NO DATA      2.30E-05 NO DATA  6.41E-06 ZN  69    4.38E-O8  6.13E-08    5.85E-09    NO    DATA    3.84E-08 NO  DATA 3.99E-06 BR  83    NO DATA  NO DATA      1.71E-07    NO    DATA    NO DATA  NO  DATA LT E-24
        ...
          BR  84    NO DATA  NO DATA      1.97E-07    NO    DATA    NO DATA  NO  DATA LT E-24
  ,i!RR  -R 8-
              85  - NO
                    NO DATA-
                        DATA  NO - DATA
                              NO DATA  -- 9.12E-09    NO
                                                        NO    DATA
                                                              DATA-1-E-07 NO
                                                                      NO DATA
                                                                          DATA NO-
                                                                              NO. DATA
                                                                                  DATA LT E-24 LT  E-24 RB Bb"    NO DATA  6.70E-05    4.12E-05    NO DATA      NO DATA  NO DATA  4.31F-06 RB 88    NO DATA  1.90E-07      1.32E-07    NO DATA      NO DATA  NO DATA  9.32E-09 RB  89    NO  DATA  1.17E-07    1.04E-07    NO    DATA    NO  DATA NO DATA  1.02E-09 SR.89    .1.32E-03 NO DATA      3.77E-05    NO DATA      NO DATA  NO DATA  5.11E-05 SR  90    1.70E-02 NO DATA      4.31E-03    NO    DATA    NO  DATA NO  DATA 2.29E-04 SR 91      2.40E-05 NO DATA      9.06E-OT    NO DATA      NO DATA  NO DATA  5.30E-05 SR 92    9.03E-06  NO DATA      3.62E-07    NO DATA      NO DATA  NO DATA  1.TIE-04 Y 90      4.11E-08  NO DATA    *I.IOE-09    NO DATA      NO DATA  NO DATA  1.17E-04 Y  91M    3.82E-10 NO DATA      1.39E-1I    NO DATA      NO DATA  NO DATA  7.48E-07 Y  91    6.02E-07 NO DATA      1.61F-08    NO DATA      NO DATA  NO DATA  8.02E-05 Y  92    3.60E-09 NO  DATA    1.03E-1O    NO  DATA    NO DATA  NO  DATA 1.04E-04
                                                  1.109-62


TABLE C-6 NUCLIDE TRANSFER PARAMETERS FOR GOAT'S MILK
TABLE E-13, CONr'D
              ELEMENT                                  Fm (days/liter)
                                  PAGE 2 OF 3 INGESTION DOSE    FACTORS FOR CHILO
                H                                          0.17 B                                          0.012 C                                          0.10
                          (MREM PR    PC[ INGESTED)
                Mg                                        0.042 P.                                         0.25"
NUCLIDE    BONE    LIVER      T.3OOY      THYROID    KIDNEY      LUNG      GI-LLI
                Cl                                        0.5 K                                          0.057 Ca                                        0.47
Y 93    1.14C-CO NO DATA      3.13E-1O    NO DATA    NO DATA    NO DATA    1.70E-04 ZR 95  1.1bE-07 2.,5E-08    2.27E-08    NO DATA  '3.65E-O8  NO DATA    2.66E-05 ZR 97  6.99E-09 I.CIE-09    5.96E-1O    NO DATA    1.45E-09  NO DATA    1.53E-04 NR 95  2.25E-D8 8.76E-09    6.26E-09    NO DATA    8.23E-09  NO DATA    1.62E-05 mO 99  NO DATA  I.33F-05    3.29E-06    NO DATA    2.84E-05.  NO DATA    I.OE-O5 TC 99M  9.23E-1O 1.81E-09    3.00E-08    NO DATA    2.63E-08    &deg;.19E-10 1.03E-06 rClO1  1.07E-09 1.12E-09    1.42E-08    NO DATA    1.91E-08  5.92E-1O    3.56E-09 RUI03  7.31E-07 NO DATA      2.81E-07    NO DATA    1.84E-06. NO DATA    1.89E-05
                                                                  *
!'U1O5  6.45E-08 NO DATA      2.34E-08    NO DATA    5.67E-07  NO DATA    4.21E-05 RU106  1.17E-05 NO DATA      1.46E-06    NO DATA    1.58E-05  NO DATA    1.82E-04 AGIIOH  5.39E-07 3.64E-07    2.91E-07    NO DATA    6.78E-07  NO DATA    4.33E-05 TF125M  1.14E-05 3.09E-06    1.52E-06    3.20E-06  NO DATA    NO DATA    1.10F-05 FE127M  2.89E-05 7.78F-06    3.43E-06    6.91E-06  8.24E-05  NO DATA    2.34E-05 TF127  4.71E-07 1.27F-07    1.01E-07    3.26E-07  1.34E-06  NO DATA    1.84E-05 rE1291A 4.87E-05 1.36E-05    7.56E-06    1.57E-05  1.43E-04  NO DATA    5.94E-05
                Fe                                        1.3E-04 Cu                                        0.013 Sr                                        0.014 I                                          0.06 Cs                                        0.30
1E129  1.34E-07 3.74E-08    3.18E-08    9.56E-08  3.92E-07  NO DATA    8.34E-06 TE131M  7.20E-06 2.49E-06    2.65E-06    5.12E-06  2.41E-05  NO DATA    1.01E-04 TE131  8.30E-08 2.53E-08    2.47E-08    6.35E-08  2.51E-07  NO DATA    4.36E-07 tE132  1.01E-05 4.47E-0o    5.40E-06    6.51E-06  4.15E-05  NO DATA    4.50E-05
                Po                                        0.0018 Computed from the data of Refs.  I and 19.
1 130  2.92E-06 5.90E-06    3.04E-06    6.50E-04  8.82E-06  NO DATA    2.76E-06 I 131  1.72E-05 1.73C-05    9.83E-06    5.72E-03  2.84E-05  NO DATA    1.54E-06
1  132  8.00E-07 1.47E-06    6.76E-07    6.82E-05  2.25E-06  NO DATA    1.73E-06
1 133  5.92E-06 7.32E-06    2.77E-06    1.36E-03  1.22E-05  NO DATA    2.95E-06
1 134  4.19E-07 7.78E-07    3.58E-07    1.79E-05  1.19E-06  NO DATA    5.16E-07
1 135  1.75E-06 3.15E-06    1.49E-06    2.79E-04  4.83E-06  NO DATA    .2.40E-06 CS134  2.34E-04 3.84E-04    8.10E-0S    NO DATA    1.19E-04  4.27E-05    2.07E-06 CS136  2.35E-05 6.46E-05    4.18E-05    NO DATA    3.44E-05  5.13E-06    2.27E-06 CS137.  3.27E-04 3.13E-04    4.62E-05    NO DATA    1.02E-04  3.67E-05    1.96E-06 CS138  2.28E-07 3.17E-07    2.01E-07    NO DATA    2.23E-07  2.40E-08    1.46E-07
3A1,39  4.14E-07 2.21E-10    1.20E-08    NO DATA    1.93E-10 1.30E-10    2.39E-05
                                    1.109-63


**
TABLE  E-13,  CONT'D
   Ref. 13.
                                  PASE  3  OF .3 INGESTION DOSE FACTORS FOR CHILD
                          (MREP PER PCI INGESTED)
NUCLIUE    BONE    LIVER      T.BODY      THYROID    KIDNEY      LUNG    GI-LLI
RA140  8.31E-05 7.28E-08    4.85E-06    NO DATA    2.37L-08  4.34E-O8  4.21E-05
&#xfd;A!41  2.OOE-07 1.12C-1O    6.51E-09    NO DATA    9.69E-11  6.58E-1O  1.14E-O7
0A142  8.74E-08 6.29E-1i    4.88F-09    NO. DATA  5.09E-11  3.70E-11 1.14E-09 LA140  I.OIE-O8 3.53E-09    1.19E-09    AO.DATA    NO DATA    NO DATA  9.84E-05 LA142  5.24E-I0 1.67T-1O    5.23E-11    NO DATA    NO DATA    NO DATA  3.31E-05 CEI41  3.97E-08 1.98[-08    2.94E-09    NO DATA    8.68E-O0  NO DATA  2.47E-05 CE143  6.99E-09 3.79E-06    5.49E-1O    NO DATA    1.59E-09  NO DATA  5.55E-05 CE144  2.08E-06 6.52E-O      I.IIE-07    NO DATA    3.61E-07  NO DATA  1.70E-04 PR143  3.93E-08 1.18E-O8    1.95E-09    NO DATA   6.39E-09  NO DATA  4.24E-05 PR144  1.29E-10 3.99E-I1    6.49E-12    NO DATA    2.1lE-11  NO DATA  8.59E-08 N0147  2.79E-OR 2.26E-08    I.75E-09    'Nn DATA    1.24E-08  NO DATA  3.58E-05 W 187  4.29E-07 2.54F-07    1.14E-07    NO DATA    NO DATA .:NO DATA  3.57E-05 NP239  5.25E-09 3.77E-10    2.65E-10    NO DATA    1.09E-09  NO DATA  2.79E-05
                                    1.109-64


1.109-57
TABLE E-14 PAGE  I OF 3 INGESTION DOSE FACTORS FOR INFANT
                          (MREM PER -PCI INGESTED)
NUCLIDE    BONE    LIVER      T.BODY      THYROID  KIDNEY    LUNG  GI-LLI
H  3  NO DATA  3.08E-07    3.08E-O7    3.0RE-07  3.08E-07 3.OBE-O7 3.08E-07 C  14  2.37E-05 5.06E-06    5.06E-06    5.06E-06  5.06E-06 5.06F-06 5.06E-06 NA 24  1.O1E-05 1.OIE-05    1.01E-05    I.OIE-05  I.OIE-05 I.OIE-O5 1.O1E-05 P  32  1.70E-03 1.OOE-04    6.59E-05    NO DATA  NO DATA  NO DATA  2.30E-05 CR 51  NO DATA  NO DATA      1.41E-08    9.20E-09  2.OIE-09 1.79E-08 4.l1E-07 MN 54  NO DATA  1.99E-05    4.51E-06    NO DATA  4.41E-06 NO DATA  7.31E-06 MN 56  NO DATA  8.18E-07    1.41E-O7    ND DATA  7.03E-07 NO DATA  7.43E-05 FE 55  1.39E-05 8.98E-06    2.40E-06    NO DATA  NO DATA  4.39E-06 1.14E-06 FE 59  3.08E-05 5.38E-05    2.12E-05    NO DATA  NO DATA  1.59E-05 2.57E-05 CO 58  NO DATA  3.60E-06    8.93E-06    NO DATA  NO DATA  NO DATA  8.97E-06 CC 60  NO DATA  1.08E-05    2.55E-05    NO DATA  NO DATA  NO DATA  2.57E-05 NI 63  6.34E-04 3.92E-05    2.20E-05    NO DATA  NO DATA  NO DATA  1.95E-06 NI 65  4.70E-06 5.32E-07    2.42E-07    NO DATA  NO DATA  NO DATA  4.05E-05 CU 64  NO DATA  6.09E-07    2.82E-07    NO DATA  1.03E-06 NO DATA  1.25E-05 ZN 65  1.34E-05 6.31E-05    2.91E-05    NO DATA  3.06E-05 NO DATA  5.33E-05 ZN 69  9.33E-08 1.b8E-07    1.25E-08    NO DATA  6.98E-08 NO DATA  1.37F-05 BR 83  NO DATA  NO DATA      3.63E-07    NO DATA  NO DATA  NO DATA  LT E-24 bR 84  NO DATA  NO DATA      3.82E-07    NO DATA  NO DATA  NO DATA  LT E-24 OR 85  NO DATA  NO DATA      1.94E-08    NO DATA  NO DATA  NO DATA  LT E-24 RB B6  NO DATA  1.70,E-04    8.40E-05    NO DATA  NO DATA  NO DATA  4.35E-06 RB 88  NO DATA  4.98E-O7    2.73E-07    NO DATA  NO DATA  NO DATA  4.85F-07 RD 89  NO DATA  2.86E-07    1.97E-07    NO DATA  NO DATA  NO DATA  9.74E-08 SR 89  2.51E-03 NO DATA      7.20E-05    NO DATA  NO DATA  NO DATA  5.16E-05 SR 90  1.85E-02 NO DATA      4.71E-03    NO DATA  NO DATA  NO DATA  2.31E-04.


QF     is the amount of feed consumed by the animal per day,      in kg/day;
SR 91  5.OOE-05 NO DATA     1.81E-06    NO DATA  NO DATA  NO DATA  5.92E-05 SR 92  1.92C-05 NO DATA     7.13E-07    NO DATA  NO DATA  NO DATA  2.07E-04 Y 90    8.69E-08 NO DATA     2.3iE-09    NO DATA  NO DATA  NO DATA  1.20E-04 Y  91M  8.10E-I1 NO DATA     2.76E-11    NO DATA  NO DATA  NO DATA  2.70E-06 Y  91  1.13E-06 NO DATA      3.01E-08    NO DATA  NO DATA  NO DATA  8.10E-05 Y  92  7.65E-09 NO DATA      2.15E-10    NO DATA   NO DATA  NO DATA  1.46E-04
              t     is the average transport time of the activity from the feed into the mil:
                                    1.109-65
                      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
TABLE  E-14,  CONI'D
              ,        pfC(ro          -      i ,.p +      -  5  C~
                                        PAGE 2 OF 3 INGESTION DOSE FACTORS FOR INFANT
                                                                    I                       (-
                              (MREM PER PCI INGESTED)
where P
   NUCLIDE*    BONE      LIVER      T.DODY       THYROID  KIDNEY      LUNG      GI-LLI
        Ci(ra)      is the concentration of radionuclide i on pasture grass, in pCi/kg;
  Y 93    2.43E-08  NO DATA    6.62E-10      NO DATA    NO DATA  NO DATA    1.92E-04 ZR 95    2.06E-07  5.02E-08    3.56E-08      NO DATA    5.41E-O8  NO DATA    2.50E-05 IR 97    1.48E-08  2.54E-09    1.1&E-09      NO DATA    2.56E-09  NO DATA    1.62E-04 N8 95    4.20E-08  1.73E-08    I.ODE-08      NO DATA    1.74E-08  NO DATA    1.46E-05 MO 99    NO DATA  1.4CE-O5    6.63E-06      NO DATA    5.08E-05  NO DATA    1.12E-05 TC 99M  1.92E-09  3.96b-09    5.10E-08      NO DATA    4.26E-08  2.07E-09  1.15E-06 TC1O0    2.27E-09  2.86E-09    2.83E-08      -NO DATA    3.40E-08  1.56E-09  4.86E-07 RUED3    1.48E-06  NO DATA      4.95E-07      '4O DATA  3.08E-06  NO DATA    1.80E-05 RUI05    1.36E-07  NO DATA      4.58E-08      NO DATA    1.O0E-06  Nfl DATA  5.41E-05 RU106    2.41E-05  NO DATA      3.DIE-06      NO DATA    2.85E-05  NO  DATA - 1.83E-04 AGIOM    9.96E-07  7.27E-07.  4.81E-07       NO DATA    1.04E-06  NO  DATA  3.77E-05 TE125M  2.33E-05  7.79C-06    3.15E-O0      7.84E-06  NO DATA  NO  DATA, 1.1lE-05 TEI27M  5.85E-05  1.94E-05    7.08E-06      1.69E-05  1.44E-04  NO DATA    2.36E-05 TE127    1.00E-06  3.35E-07    2.15E-07      8.14E-07  2.44E-06  NO DATA    2.10E-05 TE129M  1.OOE-04  3.43E-05    1.54E-05      3.84E-05  2.50E-04  NO DATA    5.97E-05 TE129    2.84E-07  9.79OE-08      .63E-08    2.382-07  7.07E-07  NO DATA    2.27E-05 TEI131  1.52E-05  6.12E-06    5.05E-06      1.24E-05  4.21E-05  NO DATA    1.03E-04 TE131    1.76E-07  6.502E-08    4.94E-08      1.7E-07    4.50E-07  NO DATA    7.11E-06 TE132    2.08E-05  1.03E-05    9.612E-06    1.52E-05  6.44E-05  NO DATA    3.81E-05 I 130    6.OOE-06 1.32E-05    5.30E-06      1.48E-03   1 45E-05  NO DATA    2.83E-06
          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.
  1 131    3.59E-05  4.23E-05    1.86E-05      1.39E-02  4.94E-05  NO DATA    1.51E-06
    1132  1.66E-06  3.37E-06    1.20E-06      1.58E-04  3.76E-06  NO DATA    2.73E-06 I 133    1.25E-05  1.82[-05    5.33E-06      3.31E-03  2.14E-05  NO DATA    3.08E-06
    1134  8.69E-P7  1.78E-06    6.33E-07      4.15E-05  1..99E-06 NO DATA    1.84E-06
  1 135    3.64E-06  7.24E-06    2.64E-06      6.49E-04  9.07E-06  NO DATA    2.62E-06 CS134    3.77E-04  7.03E-04    7.10E-05      NO DATA    1.81E-04  7.42E-05  1.91E-06 CS136    4.59E-05  1.35E-04    5.04E-05      NO DATA    5.38L-05  1.10E-05  2.05E-06 CS137    5.22E.-04 b.IIE-04    4.33E-05      NO DATA    1.64E-04  6.64E-05    1.91E-06 CS138    4.81E-07  7.82E-07    3.79E-07      NO DATA    3.90E-07  6.09E-08    1.25E-06 BA139    8.81E-07. 5.84E-10    2.55E-08      NO DATA    3.51E-1O  3.54E-10  .5.58E-05
                                          1.109-66 m


The following parameters will be employed in evaluating the milk pathway, unless site-specific data is supplied.
TAt6LE E-14, CONT'D
                                  PA:,E 3 OF 3 INGESTION DOSE FACTORS FOR INFANT
                          (MREM PER PCI INGESTED)
NUCLIL;E    BONE    LIVER    T.3ODY      THYROID  KIDNEY    LUNG  GI-LLI
BA14u    1.7LE-04 1.71E-07    8.81E-06    NO DATA  4.06E-08 1.05E-07 4.20E-05 P,.A141  4.25E-O7 2.91E-1O    1.34E-08    NO DATA  1.75E-10 1.7TTE-O 5.19E-06 BA142    I.B4E-07 1.53E-1O    9.06E-09    NO DATA  8.8IE-11 9.26E-11 T.59E-07 LA140    2.11E-O8 8.32E-09    2.14E-09    NO DATA  NO DATA  NO DATA  9.77E-05 LA142    1.1OE-09 4.04E-10    9.61F-Il    NO DATA  NC DATA  NO DATA  6.86F-05 CEI4I    7.87E-08 4.8OE-08    5.65E-09    NO DATA  1.48E-08 NO DATA  2.48E-05 CE143    1.48E-08 9.82E-06    1.1?E-09    NO DATA  2.86E-09 NO DATA  5.73E-05 CE144    2.98E-06 1.22E-06    1.67E-07    NO DATA  4.93E-07 NO DATA  1.71E-04 PR143    8.13E-08 3.04E-08    4.03E-09    NO DATA  1.13E-08 NO DATA  4.29E-05 PR144    2.74L-I0 I.ObE-l0    1.38E-1I    NO DATA  3.84E-11 NO DATA  4.93E-06 ND147    5.53E-08 5.68E-08    3.48E-09    NO DATA  2.19E-O8 NO DATA  3.60E-05 w 187    9.03E-07 6.28E-07    2.17E-01    NO DATA  NO DATA  NO DATA  3.69E-05 NP239    1.1IE-08 9.93E-10    5.61E-16    NO DATA  1.98E-09 NO DATA  2.87E-05
                                    1.109-67


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
                                                                TABLE E-15 RECOMMENDED VALUES FOR OTHER PARAMETERS
                                                      90 days for stored feed te  (crop exposure time)           30 days Yv  (crop yield)                     0.75 kg/m 2 (wet weight) for pasture
    Parameter                                                                     Equation(s)
                                                      2.0 kg/m 2 (wet weight) for stored feed
    Symbol                                  Definition                            Where Used            Values              Reference(s)*
                                                  1.109-58
      fg          Fraction of produce ingested grown in garden of interest        14 & C-13            0.76 ft          Fraction of leafy vegetables grown in garden of interest        14 & C-13            1.0
                                                                                                    4
                                                                                                                  2 p           Effective surface density of soil (assumes a 15 cm plow          4, A-8, A-13, & C-5  240 kg/mi                10
                  layer, expressed in dry-weight)
                  Fraction of deposited activity retained on crops, leafy          4, A-8, & A-13        0.25                      27 vegetables, or pasture grass                                    C-5                  1.0 (for iodines)        2, 4, 13,
                                                                                                          0.2 (for other            28-31 particulates)
      SF          Attenuation factor accounting for shielding provided by          8, 9, 10, 11, 12,    0.7 (for maximum          26 residential structures                                          B-6, B-7, B-8, B-9,      individual)
Io
00                                                                                  & C-2                0.5 (for general          26
0QO
                                                                                                            population)
      tb          Period of long-term buildup for activity in sediment or          3, 4, A-4, A-5, A-6,  1.31 x 105 hr soil (nominally 15 yr)                                          A-7, A-8, A-13, & C-5 te         Period of crop, leafy vegetable, or pasture grass                4, A-8, A-13, & C-5   720 hrs (30 days,.        10 & 32 exposure during growing season                                                          for grass-cow-milk- man pathway)
                                                                                                          1440 hrs (60 days, for crop/vegetation- man pathway)
      tf          Transport time from animal feed-milk-man                        C-10                  2 days (for maximum individual)
                                                                                                          4 days (for general population)
    Parameter values given without references are based on staff judgments.


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
TABLE E-15 (Continued)
                                                                                                        (C-14)
  Parameter Equation(s)'
where C1&#xfd;(r~o)         is the concentration of nuclide i in animal flesh,          in pCi/kg;
  Symbol                                  Definition                              Where Used          Values                Reference(s)*
                    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
     th            Time delay between harvest of vegetation or crops and ingestion i)  For ingestion of forage by animals                        4, A-8,  A-13, & C-5 Zero (for pasture grass)
                            20 days.
                                                                                                      2160 hr (90 days for stored feed)
                ii)  For ingestion of crops by man                              4, A-8, A-13, & C-5  24 hr (1 day, for leafy vegetables &
                                                                                                          maximum individual)
                                                                                                      1440 hr (60 days, for produce & maximum individual)
                                                                                                      336 hr (14 days, for general population)
    t            Environmental transit time, release to receptor                1 & A-2              12 hr (for maximum p          (add time from release to exposure point to                                            individual)
                  minimums shown for distribution)                                                    24 hr (for general population)
0
                                                                                  2 & A-3              24 hr (for maximum individual)
                                                                                                      168 hr (7 days for population sport fish doses)
                                                                                                      240 hr (10 days for population com- mercial fish doses
                                                                                  3 & A-7              Zero tS          Average time from slaughter of meat animal to                   C-12                20 days consumption Y            Agricultural productivity by unit area (measured                4, A-8, A-13, & C-5 0.7 kg/mi2 (for grass-      33 V
                  in wet weight)                                                                        cow-milk-man pathway)
                                                                                                      2.0 kg/m 2 (for produce    34 or leafy vegetables ingested by man)
                                                                                                                  1 Rate constant for removal of activity on plant or leaf                              0.0021 hr- w
                  surfaces by weathering (corresponds to a 14-day half-life)
  Parameter values given without references are based on staff judgments.


All the other symbols are as previously defined.
REFERENCES FOR APPENDIX E
1. Y. C. Ng et al., "Prediction of the Maximum Dosage to Man from the Fallout of Nuclear Devices, Handbook for Estimating the Maximum Internal Dose from Radionuclides Released to the Biosphere," USAEC Report UCRL-50163, Part IV, 1968.


Beef cattle will be assumed to be on open pasture for the grazing periods outlined for milk cattle.
2. B. H. Weiss et al., "Detailed Measurement of 1-131 in Air, Vegetation and Milk around Three Operating Reactor Sites," Environmental Surveillance Around Nuclear Installations, Inter- national Atomic Energy Agency, IAEA/SM-180/44, Vienna, Austria, Vol. I: pp. 169-190, 1974.


4.     Annual Dose from Atmospherically Released Radionuclides in Foods The annual dose resulting from ingestion of radionuclide i in the diet is given by
3. F. 0. Hoffman, "Environmental Variables Involved with the Estimation of the Amount of 1-131 in Milk and the Subsequent Dose to the Thyroid," Institute fur Reaktorsicherheit, Cologne, West Germany, IRS-W-6, June 1973.
              0.


ija (r,,,) = DFIi4a i [Uvf
4. F. 0. Hoffman, "Parameters To Be Considered When Calculating the Age-Dependent 1-131 Dose to the Thyroid," Institute fir Reaktorsicherheit, Cologne, West Germany, IRS-W-5, April
                                        [aa gCv(r,.)
    1973.
                                                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)
5. F. 0. Hoffman, "A Reassessment of the Parameters Used To Predict the Environmental Transport of 1-131 from Air to Milk," Institute fur Reaktorsicherheit, Cologne, West Germany, IRS-W-13, April 1975.
                ja          ija    a g 1          a i          a i          a k I
                                                          1.l0-59


REFERENCES FOR APPENDIX C
6. F. W. Lengemann, "Radioiodine in the Milk of Cows and Goats After Oral Administration of Radioiodate and Radioiodide,'!' Health Phys., Vol. 17, pp. 565-9, 1969.
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-,
                                                                                                  &#x17d;,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.
7. R. J. Garner and R. S. Russel,  Radioactivity and Human Diet, R. Scott Russel    (ed.), Pergamon Press, Oxford, England, 1966.


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.
8. P. M. Bryant, "Data for Assessments Concerning Controlled and Accidental Releases of 1-131 and Cs-137 to the Stratosphere," Health Phys., Vol. 17, p. 51, 1969.


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.
9. J. D. Zimbrick and P. G. Voilleque (eds.),   "1967 CERT Progress Report," USAEC Report IDO-12067, p. 36, 1968.


5. D. F. Bunch (ed.), "Controlled Environmental Radioiodine Test, Progress R.eport Num!.,          To,"
10. J. F. Fletcher and W. L. Dotson (compilers), "HERMES - A Digital Computer Code for Estimating Regional Radiological Effects from the Nuclear Power Industry," USAEC Report HEDL-TME-71-168, Hanford Engineering Development Laboratory, 1971.
    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.
11. J. K. Soldat, "Conversion of Survey Meter Readings to Concentration (liCi/m 2 )," Item 04.3.4 in "Emergency Radiological Plans and Procedures," K. R. Heid (ed.), USAEC Report HW-70935, Hanford Laboratories, 1962.


December 1968.
12. "Permissible Dose from External Sources of Ionizing Radiation," Handbook 59,      U.S. Dept. of Commerce, 1954.


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


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


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.
15. R. J. Garner, "Transfer of Radioactive Materials from the Terrestrial    Environment to Animals and Man," CRC Press, Cleveland, Ohio, 1972.


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


11. C. A. Pelletier and P. G. Voilleque,   "The Behavior of 137Cs and Other Fallout RadiontucI'det.
17. A. L. Rogers, "Goat Keeping in the United States," International Dairy Goat Conference, London, July 1964.


on a Michigan Dairy Farm," Health Phys.,   Vol.  21, p.  777,   1971.
18. R. G. Bond and C. P. Straub (eds.), Handbook of Environmental Control,     Vol.  III, "Water      40
    Supply and Treatment," CRC Press, Cleveland, Ohio, 1975.


12. P. G. Voilleque and C. A. Pelletier, "Comparison of External Irradiation and Consutrption
1.109-70
                                                                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.
19. "Food Consumption, Prices, and Expenditures," AER-138, U.S.    Department of Agriculture, Washington, D.C., December 1974.


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.
20. "Report of the Task Group on Reference Man,"   ICRP Publication 23, Pergamon Press, Oxford, England, 1975.


15. R. J. Garner and R. S. Russell, Radioactivity and Human Diet, R. Scott Russell (ed.),
21. L. K. Bustad and J. L. Terry, "Basic Anatomical, Dietary, and Physiological Data for Radiological Calculations," HW-41638, General Electric Co., Richland, Wash., February 1956.
    Pergamon Press, Oxford, England, 1966.


16. P. M. Bryant, "Data for Assessments Concerning Controlled and Accidental Releases of
22. M. M. Miller and D. A. Nash, "Regional apd Other Related Aspects of Shellfish Consumption -
    1311 and 13 7 Cs to the Stratosphere," Health Phys., Vol. 17, p. 51, 1969.
    Some Preliminary Findings of the 1969 Consumer Panel Survey," NMFS Circular 361, USDC/NOAA,
    Seattle, Wash., June 1971.


E
23. "The Potential Radiological Implications of Nuclear Facilities in the Upper Mississippi River Basin in the Year 2000," USAEC Report WASH-1209, Washington, D.C., January 1973.
                                                I.109-60


REFERENCES (Continued)
24.  "Draft Environmental Statement - Waste Management Operations, Hanford Reservation, Richland, Washington," USAEC Report WASH-1528, Washington, D.C., September 1974.
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.
25.  G. R. Hoenes and J. K. Soldat, "Age-Specific Radiation Dose Commitment-Factors for a One Year Chronic Intake," USNRC Report NUREG-0172, to be issued in 1977. A draft is available in the Public Document Room.


19. D. S. Altman and P. L Altman (eds.), "Metabolism," Federation of American Societies for Experimental Biology, Bethesda, Md., 1968.
26. Z. G. Burson and A. E. Profio, "Structural Shielding from Cloud and Fallout Gamma Ray Sources for Assessing the Consequences of Reactor Accidents," EG&G-1183-1670, Las Vegas, Nev., 1975.


1.109-61
27. D. A. Baker et al., "FOOD - An Interactive Code to Calculate Internal Radiation Doses from Contaminated Food Products," BNWL-SA-5523, February 1976.


APPENDIX D
28.  D. F. Bunch (ed.), "Controlled Environmental Radioiodine Test, Progress Report Number Two,"
                              MODELS FOR CALCULATING POPULATION DOSES FROM
    USAEC Report IDO-12063, January 1968.
                                      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.
29.  J. D. Zimbrick and P. G. Voilleque, "Controlled Environmental Radioiodine Tests at the National Reactor Testing Station, Progress Report Number Four," USAEC Report IDO-12065, December 1968.


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:
30. C. A. Pelletier and P. G. Voilleque, "The Behavior of Cs-137 and Other Fallout Radionuclides
            D Dd0.001 Z Pd    Yd jad Djdafda f                                                    (D-l)
    -on a Michigan Dairy Farm," Health Phys., Vol. 21,p. 777, 1971.
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.
31.  P. G. Voilleque and C. A.. Pelletier, "Comparison of External Irradiation and Consumption of Cow's Milk as Critical Pathways for Cs-137, Mn-54 and Pr-144 Released to the Atmosphere,"
    Health Phys., Vol. 27, p. 189, 1974.


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
32. J. J. Koranda, "Agricultural Factors Affecting the Daily Intake of Fresh Fallout by Dairy Cows," USAEC Report UCRL-12479, 1965.
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
33.  M. E. Heath et al.,  Forages, the Iowa State University Press, Ames,  Iowa, 1973.


TABLE D-1 RECOMMENDED VALUES TO BE USED FOR THE AVERAGE INDIVIDUAL
34. "Statistical Abstract of the United States," U.S. Bureau of the Census,    93rd Edition, 1972.
                                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.
1.109-71


Data obtained directly from Reference 15 of Appendix A.
APPENDIX F
                                      METHODS FOR EVALUATING THE I FUNCTION
      The NRC staff calculates ground-level gamma radiation doses from elevated noble gas releases using Equation (6) in Regulatory Posifion C.2.a of this guide.                Equation (6) is based on the model presented in Slade (Ref. 1), which can be characterized as a vertically finite sector- averaged Gaussian plume model. Use of the model involves volume integration over a distributed source, resulting in certain integrals that define the I function, denoted by TT in Reference 1.


1.109-64 i
1.   Derivation of the I Function The derivation of the I function presented below is taken directly from Reference 1, which should be consulted for further details.


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);
The sector-average airborne radionuclide concentration resulting from a continuous release is given by the Gaussian plume model as (see Equation 7.60 of Ref. 1):
              C ip        is the 50-mile average concentration of nuclide i in pathway p,   in Cip        pCi/kg or pCi/liter;
                    :(Rz) Q          exp          h
                 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);
                                                - 2(z      +  exp                                  (F-i)
              vd          is the annual mass or volume of food medium p produced in subregion d, Vdp        in kg or liters;
                      2V~0 zURe              22L            2oL
                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
                        v~Taz uez where h    is the effective release height,           in meters;
                  *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)
                 QD      is the effective release rate, considering decay in transit, in Ci/sec;
where fa        is the fraction of the population within the age group a;
                  R    is the downwind distance, in meters;                                       (7 u    is the average wind speed,         in m/sec;
                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;
          x(R,z)       is the sector-average concentration at location (R,z),             in Ci/m3 z    is the vertical distance above the ground plane, in meters;
              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);
                  e    is the sector width, in radians; and o
                          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.
                a      is the vertical plume spread,         in meters.


The annual population-integrated dose is then calculated as
Equation (F-l) maybe restated, for simplicity, as:
           ?~O~
           7(R,z)    =           'DG(z)                                                            (F-2)
                  DiP= .Ol Z p
                                zRe where G(z)=        expF-     iz h)2 + exp                                                      (F-3)
                    0.001      P  1 *.*fa&#xfd;CipUapDai(-4
                                L  2a j                  L    zp z
                                          8 *U  ODF.                                          (0-4)
                                                                2a    J
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);
where the terms are as defined above.
                                                      1.109-65


TABLE D-2 RECOMMENDED VALUES FOR THE TRANSPORT TIMES IN THE FOOD
6.
                              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
1.109-72 M ME &#xfd;"-77-  ,  :E &#xfd; - ,
                                                                                      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),
The gamma dose rate to air at a distance of r meters from a point source of q curies is
                Pp      is the population consuming food medium p; and P5 0      is the total population within 50 miles.
                                                            1):
                            Equation 7.33 of Ref.


All other factors are as defined above.
expressed by (see Pa q(3.7xlOl10)E(l.6xlo -6)B(p,jia        r)exp(-or)
                                                2
                                            41r    (1293)(100)                                                (F-4)
  Where B(,va ,r)        is the buildup factor, dimensionless;
                      D'      is the dose rate to air, in rad/sec;
                        E      is the gamma ray energy per disintegration,            in MeV;
                        q      is the point source strength,            in curies;
                        r      is the distance,        in meters;
                        P      is the attenuation coefficient for air, in m-1l la      is the energy absorption coefficient for air, in m-I
                      100      is the number of ergs per gram-rad;
                    1293        is the density of air at standard temperature and pressure,              in g/m3
            1.6 x 10-6          is the number of ergs per MeV; and
            3.7 x 1010          is the number of disintegrations, per Ci-sec.


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
Equation (F-4) may be simplified as follows:
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.
                          SKiaqEB(P,'a,r)exp(-pr)                                                            (F-5)
                                        41Tr were M~
                                                                                                              (F-6)
                K        (3.7 x(1293)(100)=04
                                    10101(.6 x I0- 6          0.46 The next step is to incorporate Equation (F-2) into Equation (F-5) to arrive at an the ression for the differential dose rate dD' from                  the differential volume dV containing e... nuclide concentration X(R,z).                Consider a volume element of the plume located z meters above (see Figure 7.20
    r ga...d and at a horizontal distance L meters from-receptor location (R, 0)
    0the            All such volume elements located at the horizontal distance L are included in the
7,    ,g91shaped differential volumeelements                                          large that the concentration
                                                  21TLdLdz. If R is sufficiently -(R,z),
        r0aged over all such volume                        can be approximated by            the contribution of the Vershaped differential volume dV to the air dose rate at location (R,0) is given as K iaEB(  p' va'r)exp(-    tr) *(~    ~  V(F-7)
                                                                                                              F7
*              dD'    =
                                      4r  2                  (Rz)dV
                                                                  1.109-73


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 where q has been replaced by x(R,z)dV. Substituting (L2 + z2)I/2 for r and 2wLdLdz for dV in Equation (F-7), and integrating, the following expression is obtained:
:1                          KuIaEQD                B [vi'va&#xfd; (L2+ zI)j1      G(z) exp LuI(L 2+Z2   jLdd
                                                                                2
                          2 ,/2'R7                                        L2 + z
                                              00                                                      (F-8)
                                              T
        The I function, denoted by              T in Reference l, is defined as
              37-~            J
                            O00
                                    B_1__(_2_
                                    B )g;(2 Z2)l1/2]1 G(z)exp [w(L 2 L2 2 L
                                                                              + z2)1/2]
                                                                                      - LdLdz        (F-9)
  which, when substituted into Equation (F-8), yields Kv aEQD
        D'=                    I                                                                      (F-10)
        The constant K, equal to 0.46, when divided by /F yields the factor 0.260, which is the same as the factor of 260 in Equation (6) of Regulatory Position C.2.a, after multiplying by the number of mrad per rad.


(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 buildup factor given in Reference I is of the form B(p,var) : 1 + kpr                                                                            (F-11)
  where k        "a                                                                                  (F-12)
                  Ila Substituting the above expression for the buildup factor into Equation (F-9),              the I function is then given as I  =  '1 + k12                                                                (F-13)
  where the Il and 12 integrals can be written for this form of the buildup factor as I      2 3 /2zi        G(z)El(ljz)dz                                                  (F-14)
                                    0
I
    and an.         21       a        G(z)exp(-Pz)dz                                                  (F-15)
                                  z
                                    0
  where El(z) is the exponential integral defined by El(GZ)      =        f    exp(-r)r prz d(pr)                                          (F-16)
                                                                1.109-74


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.
2.    Evaluation of the I Function In Reference 1 the  I and 12 integrals have been evaluated. and the results presented graphically. Extraction of the data from these six-cycle log-log multicurve plots is a formidable task. A more satisfactory approach is to prepare a tabulation of the integrals as evaluated using numerical methods. These data can then be interpolated in implementing Equation (6) of Regulatory Position C.2.a.


If the population served by a particular water supply system is not known,      it can be estimated by the following:
The .NRC staff has developed a computer routine that evaluates the I function as formulated in Equation (F-g).  The I function as expressed in Equation (F-9) is independent of the buildup factor form. A listing of this routine is provided in Figure F-1.    Communication with the routine is through the COMMON statement, which also communicates with the function subprogram BULDUP, which defines the dose buildup factor B(p,p ar) desired by the user.
            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
Also, Yankee Atomic Electric Company has supplied a routine written by Dr. John N. Hamawi of that company (Ref. 2).  This routine evaluates the I, and 12 integrals as formulated in Equations (F-14) and (F-15), respectively.  A li.sting of the routine is provided in Figure F-2 (reproduced with the permission of Yankee Atomic Electric Company).   With the exceptions of changes in the title, the addition of the COMMON statement, the computing of I from IlIand 12V
(0-5).
and comment cards as to its authorship, the routine is reproduced as written by Dr. Hamawi.   The staff has compared the two routines and found their results to be in excellent agreement. The routine supplied by the Yankee Atomic Electric Company was found to be considerably faster than the staff's routine.
  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
1.109-75


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.
SUBROUTINE DINT
C**
        COMMONDATAIT/GMUZKHSSIGMZEBARDIM
    DOSE INTEGRAL SUBROUTINE -K.F.        ECKERMAN 11-24-74 r~r, C
C    SUBROUTINE EVALUATES THE DOSE INTEGRAL 'IT' AS DEFINED BY EON 7.61 C,   IN MET & AE-1968.      THE TWO DIMENSIONAL INTEGRATION IS EVALUATED
C .  USING GAUSSIAN-LEGENDRE QUADRATURE OF ORDER 48.


Such exposed population should be included in the 50-mile population dose evaluation.
C
C    COMMON INFO
C.          GMU-MASS ATTENUATION COEFFICIENT (I/METERS)
C            ZK-BUILDUP FACTOR ((U-MUA5/MUA      IF USED
C            HS-RELEASE POINT HEITH
C
Cw          RELEASE POINT HEIGHT (METERS)
C            SIGmZ-STANDARD DEVIATION OF PLUME (METERS)
C            EBAR-GAMMA RAY ENERGY (MEV)
C            DI-DOSE INTEGRAL
C            M-ENERGY GROUP INDEX IF NEEDED
      NOTE-ZKoEBAR,& M ARE USED BY BULDUP
        DIMENSION X(245),(24)
        DATA NN/48/,A/2.828427125/
        DATA X/
      10.0323801709, 0.0970046992o        0.1612223560,  0.2247637903,
      20.2873624873,    0.3487558862,    0,4086864819,  0.4669029047,
      30.5231609747, 0.5772247260,        0.6288673967,  0.6778723796,
      40.7240341309# 0.7671590325,        0.8070662040,  0.8435882616,
      50.8765720202,    0.9058791367,    0.9313866907,  0.9529877031,
      60.9705915925, 0.9841245837,        0,9935301722v  0.9987710072/
        DATA W/
      10.0647376968o 0,0644661644#      0.0639242385,  0.0631141922,
      20,0620394231, 0.0607044391,        0.0591148396,  0.0572772921,
      30.0551995036, 0.0528901894,        0.0503590355,    0,0076166584,
      40.0446745608p 0.0415450829#        0.0382413510,    0,0347772225,
      50,0311672278, 0.0274265097,        0.0235707608,    010196161604,
      60.0155793157,    0.0114772345,    0.0073275539,    0.0031533460/
        SUMUO.


(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).
Buo.5/(SIGMZ*SIGMZ)
The age-specific ingestion factors of Table D-I may be used in lieu of site-specific data.
        ZLB3HS-4.*SIGMZ
        ZUBBHS+4.*SIGMZ
        IFCZLB.LT.0.)ZLBuO.


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.
YUBUIS./GMU
        CZ0.5*(ZUB-ZLB)
        GcO.S*(ZUB+ZLB)
        E8O.5*YUB
        DO 7o II21PNN
        III-II1/2 Ful.


(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.
EX=O.


(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
IF(MOD(II,2).EQ.0)Fu-1.
(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
ZZUF*X(I)*C&#xf7;G
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.
        ARGUxB*(ZZ-HS),(ZZ-HS)
        IF(ARGU.GT.20.)GO TO 55 EXUEXP(-ARGU)
    55 ARGU=B*(ZZ&#xf7;HS)*(ZZeHS)
        IF(ARGU.GT.20.)GO TO 58 EXEEX+EXPC-ARGU)
    58 IFCEX.E..0.)GO TO 70
        DO 60 KK8I1NN
        KzKK-KK/2 Fpa.


1.109-68
IF(MOD(KK,2).EQ.0)Fu-I.


(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.
Figure F-I. Staff-Written Computer Listing
                                                                          /
                                      1.109-76


The age-specific inhalation rates of Table D-1 may be used with the data of Tables C-l to C-4.
YYzF*XCK)*E+E
  DI=YY*Yy&#xf7;ZZ*ZZ
  ARGUUGMU*SQRT(Dl)
  IF(ARGU.GT.2o.,)GO TO 60
  EXIEEX*EXP(-ARGU)*BULDUPCARGU)*YY/DI
  SUM-SUM&#xf7;W( I*W(K)*EXI
60 CONTINUE
70 CONTINUE
  DIxSUM*C*E/(A*SIGMZ)
  RETURN
  END
                            Figure F-I (continued)
                                  1 .109-77


(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.
SUBROUTINE      DINT
        REAL MU
        COMMON/DATAIT/MUZK*HoSIGZDIL
C    DOSE INTEGRAL ROUTINE WRITTEN BY
C                    DR, JOHN N. HAMAWI
C          YANKEE ATOMIC ELECTRIC COMPANY
C            NUCLEARSERVICES DIVISION
C                  20 TURNPIKE ROAD
C          WESTBOROUGH# MASSACHUSE-TTS 01581 C    YAEC REPORT No.        1105 C
C    COMMON INFO
C      MU-MASS ATTENUATION COEFFICIENT (1/METERS)
C      ZK-BUILDUP FACTOR (MU-MUA)/MUA
C      SIGZ-STANDARD DEVIATION OF PLUME (METERS)
C      DI-DOSE INTEGRAL -I TOTAL
C
C**    L- DETERMINES NUMBER OF INTERVALS USED IN            INTEGRATION
                                                                                      *
        DIMENSION CDATA(S),E(L9),B(49),P(9).
        DATA M/9/,CDATA/5.OD+3 1.OD+4o,2.0D+4#,5.0D+&#xf7;,1.OD&#xf7;S/5 DATA AOA1,A2,A3,A4,AS/ -0.57721566,            0.99999193, - 0,249910.55, C 0.05519968,-0.00976004,            0.00107857/
        DATA BO,BI,B2,B3/0.26777373M3,            8.6347608925, 18.0590169730,
      C 8.5733287401/
        DATA CO,CIPC2,C3/ 3.9584969228,          21.0996530827, 25.6329561486, C 9,5733223454/
        DATA DDID2oD3,DD4,D5,D6oD7,D8,D9/
      C 3543.75,989.,5888.,-928.,10496.,-4540.,1049b.,-928.,5888.,            98
                                                                                  9./
C****  COMPUTE LIMITS OF INTEGRATION ZMIN AND ZMAXs AND INTERVAL WIDTH
        IF(L.LT.2.OR.L.GT.6) L*          6 C S CDATA(L-I)
        N U L*(M-1) + 1 SIGZ2      SI.GZ*SIGZ
                  S
        ALFA    H - MU*SIGZ2 m
        BETA = SIGZ* SQRT(2.0*ALOG(C))
        IF(ALFA.GT.O.0)        GO TO 150
        ZMIN a 0.0
        ZMAX x ALFA +        SQRT(ALFA*ALFA + BETA*BETA)
      *GO.TO 200
  150  ZMIN 9 ALFA - BETA
        IF(ZMIN.LT.O.0)        ZMIN a 0.0
        ZMAX.8 ALFA + BETA
  2M    DZ 2 (ZMAX-ZMIN)/(N-1)
C****  COMPUTE EXPONENTIAL INTEGRAL TERMS EUl) (SPECIAL PROCED. FOR E(1))
        E(I) 2 2.1B907-ALOG(MU*DZ)
        DO 2s0 I 8 1, N
        Z 2 ZMIN + (I-i)*DZ
        X a MU*Z
        .IF(X.LE.0O) GO TO 250
        X2 9 X*X
        X3
* X*X2 X4 2 X*X3 X5 z X*X4 IF(X.LE.I.0) E(I) z -ALOG(X)          + AO&#xf7;AI*X+A2*X2+A3*X3+A4*X4+AS*X5 IF4X.GT.10O) E(VI) a (BO+BI*X+B2*X2&#xf7;B3*X3&#xf7;X4)/
      C                            (oCOI.C*X4C2*X2+C3*X3,X4)/(X*    EXP(X))
  250 CONTINUE
C**** COMPUTE INTEGRAND TERMS B(I1            AND P(I)
        DO 309 I        p1 N
        Z
* ZMIN + (I-1)*DZ
                      Figure F-2.  Hamawi-Written Computer Listing
                                        1.109-78


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.
Gu EXP(-(Z+H)*(Z+&#xf7;H/C2.0*SIGZ2))    +  EXP (-(Z-Hi*(Z-H)/C2.0*SIGZ2))
      B(I) a G*E(I)
  300 PCI) a G* EXP(-MU*Z)
C**** PERFORM NUMERICAL INTEGRATION USING 9-POINT NEWTON-COTES FORMULA
      SUMB v 0.0
      SUMP u 0.0
      MM 5 M - I
      KM x N - M + I
      DO 350 K 9 IpKMPMM
      8UMB x SUMB + DI*B(K)+D2*B(K&#xf7;I)&#xf7;D3*B(K&#xf7;2)e+D*BCK&#xf7;3)&#xf7;n5*B(K+S)
                                                                  9 C                      +D6*B(K+5)+D7*B(K4b&#xfd;+D8*B(K+7)+D       *BCK+8)
      SUMP a SUMP + DI*P(K)+D2*P(K+I)+D3*P(K+2&#xfd;&#xf7;D1*P(K+3)+DS*P(K+4)
    C                      +Db*P(K+S)+D7*P(K*bj+DS*P(K+7)+D9*PCK+8)
  350 CONTINUE
      DOmDZ*(SUMB+SUMP*ZK)/(D*2.828427*SIGZ)
      RETURN
      END
                          Figure F-2 (continued)
                                  1.109-79


(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
REFERENCES FOR APPENDIX F
household shielding and occupancy factor of 0.5 should be applied in conjunction with the dose factors of Tables A-3 to A-7.
1. "Meteorology and Atomic Energy 1968," D. H. Slade (ed.),  USAEC Report TID-241090,        1968.,
2. J. N. Hamawi, "A Method for Computing- the Gamma-Dose Integrals 1 and T2 for the Finite- Cloud Sector-Average Model," Yankee Atomic Electric Company Report YAEC-I105, 1976.


REFERENCE FOR APPENDIX D
A
"Current Population Reports," Bureau of the Census, Series P-25, No. 541, U.S. Dept. of Commerce,
                                          1.109-80
1975.
                                                          *U. S.GOVERNM~ENT PRINTING OFFICE. 1988-202-292:80014


1.109-69}}
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                                          USNRC
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Revision as of 10:11, 28 March 2020

Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I
ML003740384
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Site: WM-00011
Issue date: 10/31/1977
From:
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To:
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-nr RG-1.109, Revision 1
Download: ML003740384 (86)
v • d • e


Revision 1*

U.S. NUCLEAR REGULATORY COMMISSION October 1977 REGULATORY GUIDE

OFFICE OF STANDARDS DEVELOPMENT

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

RELEASES OF REACTOR EFFLUENTS FOR TH

E. PURPOSE

OF EVALUATING COMPLIANCE WITH

10 CFR PART 50, APPENDIX I

' USNRC REGULATORY GUIDES Comments should be sent to the Secretary of the Commission. U.S. Nuclear Regu- Regulatoey Guides are issued to describe nd make available to th Public methods latory Commission. Washington, D.C. 20555. Attention: Docketing and Service Branch.

acceptable to the NRC staff of implementing specific parts of the Commission's regulations, to delineate techniques used by the staff in evaluating specilic problems The guides are issued in the following ten broad divisions or postulated accidents, or to provide guidance to applicants. Regulatory Guides are not substitutes for regulations. and compliance with them is not required. 1. Power Reactors 6. Products Methods and solutions different from those set out in the guides will be accept.. 2. Research and Test Reactors 7. Transportation able if they provide a basis for the findings requisite to the issuance or continuance 3. Fuels and Materials Facilities B. Occupational Health of a permit or license by the Conmission. 4. Environmental and Siting S. Antitrust Review

5. Materials and Plant Protection 10. General Comments and suggestions for improvements in these guides are encouraged at all Requests for single copies of issued guides (which may be reproducedl or for place times, and. guides will be revised, as appropriate, to accommodate comments and ment on an automatic distribution list for single copies of future guides in specific to reflect new information or experience. This guide was revised as a result of divisions should be made in writing to the U.S. Nuclear Regulatory Commission.

substantive comments received from the -public and additional staff review. Washington. D.C. 20555, Attention: Director, Division of Document Control.

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

7

TABLE OF CONTENTS

Page

A. INTRODUCTION

................................................................. 1.109-1

B. DISCUSSION

........................................................................ 1.109-1

C. REGULATORY POSITION

............ .............................................. 1.109-2

1. Doses from Liquid Effluent Pathways ........................................... 1.109-2 a. Potable Water ........................................................... 1.109-2 b. Aquatic Foods....................................................... 1.109-2 c. Shoreline Deposits.................................................. 1.109-2 d. Irrigated Foods ......................................................... 1.109-3

2. Gamma and Beta Doses from Noble Gases Discharged to the Atmosphere ........... 1.109-4 a. Annual Gamma Air Dose from Noble Gas, Releases from Free-Standing Stacks More Than 80 Meters High.......................... .................. 1.109-4 b. Annual Gamma Air Dose from All Other Gas Releases; Annual Beta Air Dose from All Noble Gas Releases ......................................... 1.109-5 c. Annual Total Body Dose from Noble Gas Releases from Free-Standing Stacks More Than 80 Meters High ................................................ 1.109-5 d. Annual Skin Dose from Noble Gas Releases from Free-Standing Stacks More Than 80 Meters High................ ........... 1.109-6 e. Annual Total Body Dose from All Other Noble Gas Releases ................ 1.109-6

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

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

a. Annual Organ Dose from. External Irradiation from Radionuclides Deposited onto the Ground Surface ................................................ 1.109-7 b. Annual Organ Dose from Inhalation of Radionuclides in Air ............... 1.109-7 c. Annual Organ Dose from Ingestion of Atmospherically Released Radionuclides in Food ................................................... 1.109-7

4. Integrated Doses to the Population ........................................... 1.109-8

5. Summary of Staff Position .................................................... 1.109-8

D. IMPLEMENTATION

.................................................................... 1.109-8 APPENDIX A, METHODS FOR CALCULATING DOSES TO MAN FROM LIQUID EFFLUENT PATHWAYS ......... 1.109-11

1. Generalized Equation for Calculating Radiation Dose via Liquid Pathways ...... 1.109-1.1 a. Radionuclide Concentration in Environmental Media (Ci ) ................. I..109-11 i b. Usage (U) .......................................... 1.109-11 ap c. Dose Factor (Daipj) . ..................................................... 1.109-11

2. Equations for Liquid Pathways ................................................ 1.109-12 a. Potable Water............................. 1.109-12 b. Aquatic Foods....................................................... 1.109-12 c. Dose from Shoreline Deposits ......................................... 1.109-12 d. Dose from Foods Grown on Land with Contaminated Water ................... 1.109-15 S REFERENCES FOR APPENDIX A...................................... ................... 1.109-18 iii

TABLE OF CONTENTS (Continued)

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

ATMOSPHERE .................................................. ......................... 1.109-19

1. Annual Gamma Air Dose from Noble Gas Releases from Free-Standing Stacks More Than 80 Meters High ..................................................... 1.109-19-

2. Annual Gamma Air Dose from All Other Noble Gas Releases and Annual Beta Air Dose from All Noble Gas Releases ......................................... 1.109-20

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

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

b. All Other Releases ...................................................... 1.109-22 REFERENCES FOR APPENDIX B ............................... .....................1.109-23 APPENDIX C, MODELS FOR CALCULATING DOSES VIA ADDITIONAL PATHWAYS FROM RADIOIODINES

AND OTHER RADIONUCLIDES DISCHARGED TO THE ATMOSPHERE ............................. 1.109-24

1. Annual External Dose from Direct*Exposure to Activity Deposited on the ,

Ground Plane. ...................................................... 1.109-24

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

3. Concentrations of Airborne Radionuclides in Foods........................1.109-25 a. Parameters for Calculating Nuclide Concentrations in Forage, Produce, and Leafy Vegetables............... ý ....................

1.109-25 b. Parameters for Calculating Nuclide Concentrations in Milk ............... 1.109-27 c. Parameters for Calculating Nuclide Concentration in Meat .............. 1.109-28

4. Annual Dose from Atmospherically Released Radionuclides in Foods ............. 1.109-28 REFERENCES FOR APPENDIX C............................................................. 1.109-29 APPENDIX D, MODELS FOR CALCULATING POPULATION DOSES FROM NUCLEAR POWER PLANT

EFFLUENTS .............................................................................. 1.109-30

1. General Expressions for Population Dose ...................................... 1.109-30

2.. Use of the Models ............................................................ 1.109-33 a. Population-Integrated Doses from Liquid Effluents ....................... 1.109-33 b. Population-Integrated Doses from Airborne Effluents ................. 1.109-34 REFERENCE FOR APPENDIX D....................................................... 1.109-35 APPENDIX E, NUMERICAL DATA.FOR THE CALCULATION OF ANNUAL DOSES TO MAN FROM ROUTINE

RELEASES OF*REACTOR EFFLUENTS ......................................................... 1.109-36

1. Environmental Data ................................................. 1.109-36

2. Human Data .................................................................. 1.109-36

3. Dose Factors............................................................ 1.109-36

4. Other Parameters...................................................... 1.109-43 REFERENCES FOR APPENDIX E .................................................... 1.109-70

iv

TABLE OF CONTENTS (Continued)

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

1. Derivation of the I Function .................................................. 1.109-72

2. Evaluation of the I Function .................................................. 1.109-75 REFERENCES FOR APPENDIX F................................................................. 1.109-80

,4  ;,v

=..

LIST OF TABLES

Table Page

1 Summary of Staff PosItion - Methods of Evaluating Compliance with Appendix I ............................................................ .... 1.109-9 A-1 Bioaccumulation Factors To Be Used in the Absence of Site-Speciiic Data ....... 1.109-13 A-2 Shore-Width Factors for Use in Equations (A-5), (A-6), and (A-7) .............. 1.109-15 B-1 Dose Factors for Exposure to a Semi-Infinite Cloud of Noble Gases ............. 1.109-21 D-l Recommended Values for the Transport Times in the Food Distribution System .... 1.109-32 E-1 Stable Element Transfer Data .................................................. . 1.109-37 E-2 Nuclide Transfer Parameters for Goat's Milk ................................... l.I09-38 E-3 Animal Consumption Rates ............................................. ...... 1.109-38 E-4- Recommended Values for U a To Be Usedfor the Average Individual in lieu of Site-Specific Data ..... ..................................................... 1.109-39 E-5 Recommended Values for Uap To Be Used for the Maximum Exposed Individual in lieu of Site-Specific Data ................................................... 1.109-40

E-6 External Dose Factors for Standing on Contaminated Ground ..................... 1.109-41 E-7 Inhalation Dose Factors for Adults ............................................ 1.109-44 E-8 Inhalation Dose Factors for Teenagers ........................................ 1.109-47 E-9 Inhalation Dose Factors for Children ......................................... 1.109-50

E-l0 Inhalation Dose Factors for Infants ......................................... 1.109-53 E-ll Ingestion Dose Factors for Adults ............................................ 1.109-56 E-12 Ingestion Dose Factors for Teenagers ........................................ 1.109-59 E-13 Ingestion Dose Factors for Children .......................................... 1.109-62 E-14 Ingestion Dose Factors for Infants ........................................... 1.109-65 E-15 Recommended Values for Other Parameters ...................................... 1.109-68 LIST OF FIGURES

Figure Page F-l Staff-Written Computer.Listing ............................................. 1.109-76 F-2 Hamawi-Written Computer Listing . 1,109-78 vi

A. INTRODUCTION

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

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

acceptable to the staff for the calculation of preoperational estimates of effluent releases, dispersion of the effluent in the atmosphere and different water bodies, and estimation of the associated radiation doses* to man. This guide describes basic features of these calculational models and suggests parameters for the estimation of radiation doses to man from effluent releases.

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

Portions of this guide supersede Regulatory Guide 1.42, Revision 1, "Interim Licensing Policy on as Low as Practicable for Gaseous Radioiodine Releases from Light-Water-Cooled Nuclear Power Reactors," which has been withdrawn.

B. DISCUSSION

Appendix I to 10 CFR Part 50 provides guidance on the doses to members of the general public resulting from effluent releases that may be considered to be as low as is reasonably achievable. This guide describes basic features of the calculational models and assumptions in use by the NRC staff for the estimation of doses.

Appendix A of this guide describes suggested models and assumptions for calculating the estimated doses to man from discharges to the hydrosphere. Appendix B of this guide describes suggested models and assumptions for calculating doses from noble gases discharged to the atmos- phere, and Appendix C.gives models and assumptions for estimating doses from radioiodines and other radionuclides released to the atmosphere. Appendix D describes the models and assumptions for calculating population doses (man-rem and man-thyroid-rem) from radionuclide releases to the atmosphere and hydrosphere. Appendix E presents tabular data pertaining to two or more of the other appendices. Appendix F provides a discussion of, and derivation for, the I function used in computing gamma doses from elevated noble gas releases.

In providing guidance for implementing Section II of Appendix I, the.NRC staff -has made use of the maximum exposed individual approach. In this approach the numerical design objectives of Section II are compared to the calculated radiation exposures to maximum individuals in each of four age groups.

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

teenagers (11 to 17 years), and adults (17 years and older). For the purpose of evaluating dose commitment, the maximum infant is assumed to be newborn, the maximum child is taken to be 4 years old, the maximum teenager is taken to be 14 years old, and the maximum adult is-taken to be

17 years old.

Maximum individuals are characterized as "maximum'" with -regard to food consumption, occupancy, and other usage of the region in the-vicinity of the plant site and as such represent individuals with habits representing reasonable deviations from the average for the population in general.

In all physiological and metabolic respects the maximum exposed individuals are assumed to have those characteristics that represent the averages for their corresponding age group in the general In this guide, the term "dose," when applied to individuals, is used instead of the more precise term "dose equivalent," as defined by the International Commission on Radiological Units and Measurements (ICRU). When applied to the evaluation of internal'deposition of radioactivity, the term "dose," as used here, includes the prospective dose component arising from retention in the body beyond the period of environmental exposure, i.e., the dose commitment. The dose commitment is evaluated over a period of 50 years.

11.109-I

population. Although specific individuals will almost certainly display dietary, recreational, and other living habits considerably different from those suggested here, and actual physiological and metabolic parameters may vary considerably, the NRC staff considers the maximum exposed individual to be a well-defined reference for implementation of Section II of Appendix I. The characterization of maximum exposed individuals is subject to continuing review by the NRC staff, and the applicant is encouraged to use information and data applicable to a specific region or site when possible. Where site-specific information and data is used, its justification should be documented for the NRC staff's review.

Since the radiation dose commitment per unit intake of a given radionuclide usually varies as a function of-age, four sets.of internal dose conversion factors have been calculated. These dose factors are appropriate for the four different age groups defined above. Specifically, these dose factors are based on continuous intake over a one-year environmental exposure period and an associated dose commitment extending over a 50-year period from initiation of intake.

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

As discussed in Section III.A.2 of Appendix I-to 10 CFR Part 50, the applicant may take intoaccount any real phenomena or actual exposure conditions. Such conditions could include actual values for agricultural productivity, dietary habits, residence times, dose attenuation by'structures, measured environmental transport factors (such as bioaccumulation factors), or similar values actually determined for a specific site. The applicant should provide enough information on the measurements or other methods used to derive these substitute values to enable the NRC staff to evaluate their validity.

C. REGULATORY POSITION

Equations are provided below by which the NRC staff will estimate radiation exposure for maximum individuals and the population within 50 miles. These equations are appropriate for the exposure pathways that the staff routinely considers in its evaluations. In addition, other exposure pathways that may arise due to unique conditions at a specific site should be considered if they are likely to provide a significant contribution to the total dose. A pathway is con- sidered significant if a conservative evaluation yields an additional dose increment equal to or more than 10 percent of the total from all pathways considered in this guide.

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

a. Potable Water R . : 1100 UapMp Q 0ai pjexp(-Xitp) (1)

apj F 1ap b. Aquatic Foods Ra 1100 UaFp Q.B. 0D.exp(-it.) . (2)

apj F 1 1 p aipi i p c. Shoreline Deposits QiTiD [exp(-Xitp)][l exp(-t) (3)

apj == 110,000

Rap Fp 1aipi 1pib

-

1J09-2

d. Irrigated Foods For all radionuclides except tritium: 8 Frrr - xp-I ) fBv~ - exp(-itb)]l R = uveg diexp(-thDaipj --- Yv Eite)] + '-- P i b api . . ev rp(" 1r b

+ Uanimal F ADaipj Qd p exp(AEite)]

ap IA aipjIQ F iexp iXh)YvX

+ fI Biv[ - exp(-Aitb)] +Ciaw (4)

For tritium:

R . vegC D uanimalD FA(CvQ + CQw) (5)

apj ap v apj + ap api A VF AwAw where B. is the equilibrium bioaccumulation factor'for nuclide i in pathway p, expressed ip as the ratio of the concentration in biota (in pCi/kg) to the radionuclide concentration in water (in pCi/liter), in liters/kg;

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

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

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

Daipj is the dose factor, specific to a given age group a, radionuclide i, pathway p, and organ j, which can be used to calculate the radiation dose from an intake of a radionuclide, in mrem/pCi, or-from exposure to a given concentra- tion of a radionuclide in sediment, expressed as a ratio of the dose rate (in mrem/hr) and the areal radionuclide concentration (in pCi/m 2 );

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

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

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

FiA is the stable element transfer coefficient that relates the daily intake rate by an animal to the concentration in an edible portion of animal product, in pCi/liter (milk) per pCi/day or pCi/kg (animal product) per pCi/day;

M is the mixing ratio (reciprocal of the dilution factor) at the point of exposure (or the point of withdrawal of drinking water or point of harvest of aquatic, food), dimensionless;',

2

-;

P is the effective 'surface density" for-sbil,. in kg(dry soil)/m QAw is the consumption rate of contaminated water by an animal, in liters/day;

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

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

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

Rap R is the total annual dose to organ j of individuals of age group a from all of the nuclides i.in pathway p, in mrem/yr;

1.109-3

NU

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

te is the time period that crops are exposed to contamination during the growing season, in hours;

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

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

t is the average transit time required for nucli es to reach the point of exposure. For internal dose, tp is the total time elapsed between release of the nuclides and ingestion of food or water, in hours;

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

W is the shoreline width factor, dimer;sionless;

Yv is the agricultural productivity (yield), in kg(wet weight)/m2 AEi is the effective removal rate corn .]t for radionuclide i from crops, in hr where XEi= Xi + Xw , i is the rz-,)active decay constant, and Xw is the removal rate constant for physic,: s by weathering (see Appendix E,

Table E-15);

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

1100 is the factor to convert from (Ci/yr)i(ft 3 /sec) to pCi/liter; and

110,000 is the factor to convert from (Ci/yr)/(ft 3/sec) to pCi/liter and to account for the proportionality constant used in the sediment radioactivity model.

These equ; ions yield the dose'rates to various organs of individuals from the exposure pathways mentio, ed above. Appendix I of 10 CFR Part 50 requires that the annual doses or dose commitments to the total body or any organ of any individual from the sum of the exposure path- ways from liquid effluents associated with each reactor should not exceed 3 mrem and 10 mrem, respectively.

2. Gamma and Beta Doses from Noble Gases Discharged to the Atmosphere The NRC staff will calculate radiation doses from noble gases using the following equations from Appendix B of this guide. Atmospheric dispersion models are found in Regulatory Guide 1.111,

"Methods for Estimating Atmospheric Transport and Dispersion for Gaseous Effluents on Routine Releases from Light-Water-Cooled Reactors."

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

80 Meters High Dy(r,o) r126 n *U1n1 (Ek Eki(H,u,S,az;Ek QniAki6 n ns k1 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,e) is the annual gamma.air dose at a distance r (meters) in the sector at angle o, in mrad/yr;

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

1.109-4

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

I(H,u,s,az,Ek) is the dimensionless numerical integration constant accounting for the distribution of radioactivity according to meteorological conditions of wind speed (u) and atmospheric stability (s) which in part determine the effective stack height (H) and the vertical plume standard deviation (az).ý In addition, I is a function of the photon energyEk and is T Il + k12 as formulated in Slade (Appendix B, Reference 1);

D

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

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

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

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

260 is the conversion factor to obtain DY(r,e), in mrad/yr, and has the units of mrad-radians-m3-disintegration/sec-MeV-Ci.

b. -Annual Gamma Air Dose from All Other Noble Gas Releases; Annual Beta Air Dose from All Noble Gas Releases DY(r,o) or DB(r,e) =.3.17 x 104- Qi[x/Q]D(r,o)(DFi or. DFý) (7)

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

DY(r,o) or D'(r,O) are the annual gamma and beta air doses at the distance r in the sector at angle 0 from the discharge point, in mrad/yr;

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

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

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

3.17 x 104 is the number of pCi per Ci divided by the number of seconds per year.

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

80 Meters High T yT

0 (r,o) = 1.11 SF Dk(r,O)exp[-1Ja(Ek)td] (8),

where DT (r,o) is the annual total body dose at the distance r in sector 0, in mrem/yr;

DY(r,0) is the annual gamma air dose associated with the kth photon energy group at the distance r in sector E, in mrad/yr;

1.109-5

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

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

2

dose, in g/cm

2 VT(Ek) is the tissue energy absorption coefficient, in cm /g; and

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

d. Annual Skin Dose-from Noble Gas Releases from Free-Standing Stacks More Than 80 Meters Hig DS(rG) 1..11SFDY(r,G) + 3.17 x 1044 Qi1 x/Q]D(r,e)DFSi (9)

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

All other parameters are as defined in preceding paragraphs.

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

  • xi(r,e)DFBi (10)

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

DT(r,o)' is the annualtotal body dose due.to immersion in a semi-infinite cloud at.

the distance r in sector 0, in mrem/yr; and xi(r,e) is.. the annual average ground-level concentration of.radionuclide i at'the distance r in sector e, in pCi/m3 All other parameters are as defined above.

f. Annual Skin Dose from All Other Noble Gas Releases D5 (r,0) = 1.11 S xi(r,O)DFI + X1 (r,e)DFS (1 F1 1 where Ds(r,e) is the annual skin dose due to immersion in a semi-infinite cloud at the distance r in sector 0, in mrem/yr.

All other parameters are as defined above.

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

The NRC staff will calculate radiation doses from radioiodines and other radionuclides released to the atmosphere using the following equations from Appendix C of this guide.

Not including noble gases.

1.109-6

a. Annual Organ Dose from External Irradiation from Radionuclides Deposited onto the Ground Surface DG(r,o) 8760 SF C*(r,o)DFGi G (12)

where CG(r,e) is the ground plane concentration of radionuclide i at distance r in sector e, in pCi/m2 DFG. is the open nuclide i, infield mrem-mground

2 plane dose conversion factor for organ j from radio-

/pCi-hr;

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

SF is a shielding factor that accounts for the dose reduction due to shielding provided by residential structures during occupancy, dimensionless; and

8760 is the number of hours in a year.

b. Annual Organ Dose from Inhalation of Radionuclides in Air DA(r,e) = R (3 ja a = xi(r,O)DFAija a j (13)

where A(re) is the annual dose to organ j of an individual in the age group a at location jar' (r,e) due to inhalation, in mrem/yr;

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

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

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

c.- Annual Organ Dose from Ingestion of Atmospherically Released Radionuclides in Food DDja (r,e) = DFIaij[a91a f Cv(r,o) + UmCm(ro) + UFCF(rO) + ULf Ci(r,O (14)

where Cv(r,D), CF(r,o),

CL(r,o),

1.

C.(r,)

1 are the concentrations fruits, and grains), milk, of radionuclide i in produce leafy vegetables, (non-leafy-vegetables, and meat, respectively, at location (r, o), in pCi/kg or pCi/z;

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

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

f ,fz are the respective fractions of the ingestion rates of produce and leafy vegetables that are produced in the garden of interest; and Uav Umma' Ua'F UaL are the annual intake (usage) of produce, milk, meat, and leafy vegetables, respectively, for individuals in the age group a, in kg/yr or i/yr (equivalent to Uap).

1.109-7

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

5. Summary of Staff Position A brief summary of the staff position on methods of evaluating compliance with the numerical guides for design objectives of Appendix I is presented in Table 1. Methods of evaluating compliance with the cost-benefit provisions of Appendix I are addressed in Regulatory Guide 1.110,

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

D. IMPLEMENTATION

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

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

public or additional staff review.

1.109-8

w

-*~-<~

TABLE 1 SUMMARY OF STAFF POSITION -

METHODS OF EVALUATING COMPLIANCE WITH APPENDIX I

APPENDIX I* RM-50-2 POINT OF DOSE EQUATIONS

TYPE OF DOSE DESIGN OBJECTIVES DESIGN OBJECTIVES* EVALUATION TO BE USED

Liquid Effluents Dose to total body 3 mrem/yr per unit 5 mrem/yr per site Location of the 1, 2, 3, 4, & 5 from all pathways highest dose offsite.**

I

Dose to any organ 10 mrem/yr per unit 5 mrem/yr per site Same as above. 1, 2, 3, 4, & 5 from all pathways Non-tritium releases 5 Ci/yr per unit

0

Gaseous Effluents***

'.

Location of the 6 or 7, as Gamma dose in air 10 mrad/yr per unit 10 mrad/yr per site highest dose offsite.÷ appropriate Beta dose in air 20 mrad/yr per unit 20 mrad/yr per site Same as above. 7 Dose to total body 5 mrem/yr per unit 5 mrem/yr per site Location of the 8 or 10, as of an individual highest dose appropriate offsite.**

Dose to skin of an 15 mrem/yr per unit 15 mrem/yr per site Same as above. 9 or 11, as individual appropriate See footnotes at end of table, on following page.

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

___________________________________________

TABLE 1 (Continued)

SUMMARY OF STAFF POSITION*-

METHODS OF EVALUATING COMPLIANCE WITH APPENDIX I

APPENDIX I* RM-50-2 POINT OF DOSE EQUATIONS

TYPE OF DOSE DESIGN.OBJECTIVES DESIGN OBJECTIVES* EVALUATION TO BE USED

Radioiodines and Particulates Released tothe.Atmosphere Dose to any organ 15 mrem/yr per unit 15 mrem/yr per site Location of the 12, 13, & 14 from all pathways highest dose offsite...++

1-131 releases 1 Ci/yr per unit - - - - - - - -

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

Evaluated at a location that is anticipated to be occupied during plantlifetime or evaluated with respect to such potential land and water usage and food pathways as could actually exist during the term of plant operation Calculated only for noble gases.

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

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

tttEvaluated at.a location where an exposure pathway and dose receptor actually exist at the time of licensing. However, if the applicant determines design objectives with respect to radioactive iodineon the basis of existing conditions and if potential changes in land and water usage and food pathways could result in exposures in excess of the guideline values given above, the applicant should provide reasonable assurance that a monitoring and surveillance program will be performed to determine:

(1) the quantities of radioactive iodine actually released to the atmosphere and deposited relative to those estimated in the determination of design objectives; (2) whether changes in land and water usage and food pathways which would result in individual.exposures greater than originally estimated have occurred; and (3) the content of radioactive iodine in foods involved in the changes,'if and when they occur.

APPENDIX A

METHODS FOR CALCULATING DOSES TO MAN FROM LIQUID EFFLUENT PATHWAYS

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

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

Equation (A-l) is the generalized equation for calculating the radiation dose to man via liquid effluent pathways.

Raipj Cip UapD aipj (A-1)

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

pathway p, Daipj alp, is and the dosej. factor, organ It represents to age specific the dose group due toa, the intake of i, radionuclide a radionuclide, in mrem/pCi, or from exposure to a given concentration of a radionuclide in

2

'sediment, in mrem per hr/pCi per m R . . is the annual dose to organ j of an individual of age group a from nuclide i alp,] via pathway p, in mrem/yr; and is the exposure time or Z/yr intake associated with pathway p for Uaap age group a, in hr/yr, or rate kg/yr (usage)

(as appropriate).

The three factors, making up Equation (A-l) are discussed in the following sections, most of which were taken directly from the WASH-1258 report (Ref. 1). (An updated version of the portion of the WASH-1258 report describing models and computer programs is contained in the. BNWL-1754 report (Ref. 2).)

a. Radionuclide Concentrationin Environmental Media (Cip)

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

  • the pathway equations that appear later in this discussion..

b. Usage (U Y.

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

The NRC staff encourages the use of site-specific data, whenever possible. Such data should be documented. In the absence of site-specific data, however, the usage values (consumption rates and exposure times) presented in Appendix E, Table E-5, are recommended.

c. Dose Factor (Daipj Dose factors for internal exposure via ingestion are provided in Appendix E, Tables E-ll,

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

Material deposited from sedimentation in an aquatic system represents a fairly large, nearly uniform thin sheet of contamination. The factors for converting surface contamination given in pCi/m2 to the dose rate at one meter above a uniformly contaminated plane have been described by Soldat and others (Refs. 3 and 4). Dose factors for exposure to soil sediment have units of mrem/hr per pCi/m2 and are presented in Appendix E, Table E-6.

1.109-11

2. Equations for Liquid Pathways This section develops the equations required for the liquid pathway models. The principal difference between pathways is the manner in which the radionuclide concentrations are calculated.

The doses from the four pathways should be added to determine the total dose.

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

Rapj = 1100 MpF

Ua- aP* Qia pjeXp(-,t p) (A-2)

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

The summation process adds the dose contribution from each nuclide to yield the total dose for the pathway-organ combination selected. The expression (1100 QiM p/F)exp(-xit p) yields the concentration of nuclide i at the time the water is consumed, in pCi/X. This concentration is the term Cip in Equation (A-l). As a minimum, the transit time tp may be set equal to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to allow for radionuclide transport through the water purification plant and the water distribution system (Ref. 5). The transit time should be increased as appropriate to: allow for travel from the point of effluent release to the water purification plant intake. Credit may be taken for radionuclide removal by water purification processes using techniques such as those outlined in Reference 3.

It should be noted that, depending on the.hydrological dispersion model employed, the- mixing ratio, Mpor.dilution factor may not be explicitly defined. In those instances (e.g.:,

buildup of activitykin a cooling pond), the relative concentration in the mixed stream (comparedc to the effluent co,6centration) may be supplied as a function of the radiological decay constant, with any potential' effl'uent recycling taken into account. Suggested hydrological dispersion models are presented in Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I."

b. Aquatic Foods The concentrations'of radionuclides in aquatic foods are assumed to be directly related to the concentrations of the nuclides in water. Equilibrium ratios between the two concentrations, called bioaccumulation factors in this guide,.can be found in the literature (Ref. 6). The inclusion of the bioaccumulation factor Bip in Equation (A-2) yields Equation (A-3), which is suitable for calculating the internal dose from consumption of.aquatic foods.

U M

Rapj =1100 F . QiBipD ai pjexp(-itp) . (A-3)

Values of Bip are given in Table A-l; the other. parameters have been previously defined. The methodology presented in Reference 7 for the development of site-specific freshwater bioaccumula- tion factorsis considered to-be acceptable by the NRC staff.

The transit time tp may be set equal to 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s* to allow for radionuclide decay during transit through the food chain, as well as during food preparation.

c. Dose from Shoreline Deposits The calculation of individual dose from shoreline deposits is complex since it involves estimation of sediment load, transport, and concentrations of radionuclides associated with Here, and in a number of other instances, the NRC staff has found it necessary to set forth guidance as to a parameter value in the absence ofempirical data. In such instances judgments have been made after considering values assumed by others and model sensitivity to the parameter value in question. In this particular instance, the total body dose from fish ingestion, for a typical situation, was found to vary by less than a factor of two for a range of environmental transit times of from one to seven days.

1.109-12

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

(pCi/kg per pCi/liter)*

FRESHWATER SALTWATER

ELEMENT FISH INVERTEBRATE FISH INVERTEBRATE

H 9.OE-01 9.OE-01 9.OE-OI 9.3E-C;

C 4. 6E 03 9.1E 03 1.8E 03 1.4- 03 NA OE 02 2.OE 02 6.7E-02 1 9E-O1 P OE 05 2.OE 04 2.9E 04 3.OE .04 CR 2.OE 02 2,OE 03 4.OE 02 2.OE 03 MN 4. OE 02 9.OE 04 5.5E 02 4.OE 02 FE 1.OE 02 3.2E 03 3.OE 03 2.OE 04 CO 5. OE 01 2.OE 02 l.OE 02 1.OE 03 NI 1.OE 02 1.OE 02 l.OE 02 2.5E 02 CU 5. OE 01 4.OE 02 6.7E 02 1.7E 03 ZN 2. OE 03 " .OE 04 2.OE 03 5.OF,01 BR 4. 2E 02 "\ 3.3E 02 1.5E-02 3.1E 00

RB 2. OE 03i *1.OE 03 8.3E 00 1.7E 01 SR 3. OE 0i l.OE 02 2.OE 00 2.OE 01 Y 2. 5E 01 l.OE 03 2.5E 01 1.OE 03 ZR 3.3E 00 6.7E 00 2.OE 02 8.OE 01 NB 3. OE. 04 l.OE 02 3.OE 04 l.OE 02 MO 4. OE 01 1.OE 01 l.OE 01 1.OE 01 TC 1.5E 01 5.OE 00 l.OE 01 5.OE 01 RU 2. OE 01 3.OE 02 3.OE 00 1.OE 03 RH 1.OE 01 3.OE 02 l.OE 01 2.OE 03 TE** 4. OE 02 6.1E 03 1.OE 01 l.OE 02 I 1.5E 01 5.OE 00. l.OE 01 5.OE 01, CS 2. OE 03 l.OE 03**** 4.OE 01 2.5E 01 BA 4. OE 00 2.OE 02 l.OE 01 1.OE 02 LA 2. 5E 01 l.OE 03 2.5E 01. l.OE 03 CE 1.OE 00 1.OE 03 l.OE 01 6.OE 02 PR 2. 5E 01 l.OE 03 2.5E 01 1.OE 03 ND 2. 5E 01 l.OE 03 2.5E 01 1 .OE 03 W 1.2E 03 l.OE 01 3. OE 01 3. OE 01 NP 1.OE 01 4.OE 02 I. OE 01 1. OE 01 Values in Table A-1 are taken from Reference 6 unless otherwise indicated.

Data taken from Reference 8.

Data taken from Reference 7.

1 .109-13 Iii iiI

suspended and deposited materials. One method of approaching this problem was presented in the Year 2000 Study (Ref. 3). Based on this model, an estimate of the radionuclide concentration in shoreline sediments can be obtained from the following expression:

C.s = Kc Ciw[l - exp(-Aitb)] (A-4)

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

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

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

tb is the length of time the sediment is exposed to the contaminated Water, nominally 15 years (approximate midpoint of facility operating life), in hours; and A. is the decay constant* of nuclide i, in hours-l. In the original evaluation of the equation, xiwas chosen to be the radiological-decay constant. The true value should include an as yet unknown "environmental" removal constant.

The value of Kc was derived for several radionuclides by using data from water and sediment samples collected over a period-of several years.in the Columbia River between Richland, Washington,..and the river mouth and in Tillamook Bay, Oregon, 75 km south of the river mouth (Refs. 9 and 10). Since the primary use of the equation is to facilitate estimates of the exposure rate from gamma.iemitters one meter above the sediment, an effective surface contamina- tion was estimated. This surface contamination was assumed to be contained within the top 2.5 cm (1 in.) of sediment (with a mass of 40 kg/m 2 of surface). The dose contribution from the radionuclides at depths below 2.5 cm was ignored. The resulting equation is Si = lOOTiCiwW[l - exp(-xitb)] (A-5)

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

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

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

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

Shore-width factors were derived from experimental data (Ref.. 11) and are summarized in Table A-2. They represent the fraction of the dose from an infinite plane source that is estimated for these shoreline situations.

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

Rapj = Uap aipj i.D = 100 UapW C Ti Daipj[l - exp(-xitb)] (A-6)

As in the development of Equation (A-2), the expression (1100 Qi Mp/F)exp(-it p) may be substituted for C . This results in the following relationship:

Rap = 110,000 ap p QiTiDipj[exp(-xitp)]El - exp(_xitb)] (A-7)

apj F 1 1aip tb)p If the presence of a radionuclide in water and sediment is controlled primarily by radioactive equilibrium with its parent nuclide, the water concentration and decay constant of the parent should be used in Equations (A-4) and (A-51.

1.109-14

TABLE A-2 SHORE-WIDTH FACTORS FOR USE IN EQUATIONS (A-5), (A-6), AND (A-7)

EXPOSURE SITUATION SHORE-WIDTH FACTOR, W

Discharge canal bank- 0.1 River shoreline 0.2 Lake shore 0.3

.Nominal ocean site 0.5 Tidal basin 1.0

d. Dose from Foods Grown on Land with Contaminated Water The equations in the following paragraphs can be used to calculate doses from radio- nuclides released in liquid effluents but appearing in crops or animal products. Separate expressions are presented for tritium because of its unique environmental behavior.

(1) Vegetation The concentration of radioactive material in vegetation results frol deposition onto the plant foliage and from uptake from the soil of activity deposited on the ground. The model, used for estimating the transfer of radionuclides from irrigation water to crops through water deposited on leaves and uptake from soil was derived for-a study of the potential doses to people from a nuclear power complex in the year 2000 (Ref. 3).

The equation for the model (for radionuclides except tritium) is presented below in slightly modified form. The. first term in brackets relates to the concentration derived from direct foliar deposition during the growing season. The second term relates to uptake from soil and reflects the long-term deposition during operation of the nuclear facility. Thus, for a uniform release rate, the concentration Civ of radionuclide i in the edible portion of crop species v, in units of pCi/kg,"is given by:.

Civ cidX

d [r[l - v exp(-xEite)] +f I ibv[I

iY _ex (_ ith - Cexp(-x

(A-8)

L YvAEi P1 J

where the terms are defined in Section C, "Regulatory'Position." Appendix E, Table E-15, presents suggested values-for the parameters r, Yv' te' P, and th. Values for Biv are in Table E-l.

The deposition rate, di, from irrigated water is defined by the relation di = Ciw I (water deposition). (A-9)

where Ciw is the concentration of radionuclide i in water used for irrigation, in pCi/liter, and I is the average irrigation rate, in liters/m2 /hr, during the growing season.

For a cow grazing on fresh forage, te in Equation (A-8) is set equal to 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br />

(30 days), the typical time for a cow to return to a particular portion of the grazing site (Refs. 3 and 12).

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

Cv = Cw (A-10)

1.109-15

Jull

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

CiA = F iA[CiFQF + Q (A-ll)

The second set of terms in the brackets in Equation (A-1l) can be omitted if the animal does not drink contaminated water. Values for QF and QAw are presented in Appendix E,

Table E-3. Values for Biv and FiA are given in Appendix E, Table E-l.*

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

is given by:

R UY~g C D Uanimal D

Rapj = u~ p iv aipj ap  ! iA aipj (A-12)

If values for Civ from Equation (A-8) and CiA from Equation (A-11) are substituted in Equation (A-12):

uveg dFril - exp(-Ei te)] flB[iv[ - exp(-Aitb)]1 Rapi ap d exp(ith)Daipj Yv XEi + PXi .

+ u animal FQ Lxp-Ei d rp - e)

+ ap  ! FiADaipj Fd iexp(-ith YvXEi fB f [1 --exo(-x t )

x{*t)_CiAwQAwj PXi[ (A-13)

+ I iv *i b CAAW

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

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

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

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

CA = Fa(CvQF + CAwQAw) (A-14)

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

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

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

CA = FAC w(QF +QAw) (A-15)

S i *i Values for F. iA appear as Fm and Fff in Table E-l.

1.109-16 IiIi

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

(A-16)

R

apj

=vegCD

ap v apj

+ uanimalc ap ADapj

1.109-17

REFERENCES FOR APPENDIX A

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

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

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

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

4. J. K. Soldat, "Conversion of Survey Meter Readings to Concentration (iJCi/m 2 )," Item 04.3.4 in "Emergency Radiological Plans and Procedures," K. R. Heid (ed.), USAEC Report HW-70935, Hanford Laboratories, 1962.

  • 5. D. H. Denham and J. K. Soldat, "A Study of Selected Parameters Affecting the Radiation Dose from Radionuclides in Drinking Water Downstream of the Hanford Project," Health Physics, Vol. 28, pp. 139-144, February 1975.

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

7. H. A. Vanderploeg et al., "Bioaccumulation Factors for Radionuclides in Freshwater Biota,"

ORNL-5002, Oak Ridge, Tenn., November 1975.

8. G. G' Kilaugh and L. R. McKay, "A Methodology for Calculating Radiation Doses from Radio-*

activity Released to the Environment," ORNL-4992, Oak Ridge National Laboratory, Oak Ridge, Tenn., March 1976.

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

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

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

12.. J. J. Koranda, "Agricultural Factors Affecting the Daily Intake of Fresh Fallout by Dairy Cows," USAEC Report UCRL-12479, 1965.

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

CONF-710809, 1973.

1.109-18 ti 1/4..

APPENDIX B

MODELS FOR CALCULATING DOSES FROM

NOBLE GASES DISCHARGED TO THE ATMOSPHERE

The following analytical models are used for calculating doses from exposure to noble gases discharged to the atmosphere. Separate models are given for air and tissue doses due to gamma and beta rays. Except for the case of noble gas doses resulting from elevated releases, all models assume immersion in a semi-infinite cloud.

1. Annual Gamma Air Dose* from Noble Gas Releases from Free-Standing Stacks More Than 80 Meters Hih:

Slade (Ref. 1) describes a derivation of equations for estimating annual air doses from photon emitters dispersed in the atmosphere. The following expression can be used for calculating annual doses:

  • i! ~260 D

DY(r,e) = 2--0 U- fns

  • 1*a(Ek)Ekl(HusozEk) QniA (B-l)

n n s k nk Symbols for this equation were defined earlier, in Regulatory Position C.2.a of this guide.

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

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

m where A is the fraction of the disintegrations of nuclide i yielding photons m .of energy Em;

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

Decay during travel from the point of release to the receptor is Qni Qi exp(-xir/un)

Q (B-3)

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

1.109-19

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

r is the distance from the source to the receptor, in m; and is the decay constant of nuclide i, -I

Xi in sec All other parameters are as previously defined.

2. Annual Gamma Air Dose from All Other Noble Gas Releases and Annual Beta Air Dose* from All Noble Gas Releases Plumes of gaseous effluents are considered semi-infinite in the case of ground-level noble gas releases. The annual average ground-level concentration of radionuclide i at location (r,e)

is. determined from xi(r,e) = 3.17 x 104 Q[x/Q] D(r,e) (8-4)

where x.(r,e) is the annual average ground-level concentration of nuclide i at the 3 distance r in the sector at angie e from the release point, in pCi/mi , and

[x/Q]D(r,e) is the annual average gaseous dispersion factor (corrected'for radioactive decay) in the sector at angle ,3it the distance r from the release point, in sec/m 3 . (See Regulatory Guide 1,111 for atmospheric dispersion models.)

All other parameters are as previously defined.

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

  • xi(re)(DFi or DF) (B-5)

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

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

3. Annual Total Body and Skin Doses from Noble Gas Effluents It is also necessary to determine annual doses to real individuals in unrestricted areas.

The staff computes the total body dose from external radiation at a depth of 5 cm into the body and the skin dose at a depth of 7 mg/cm2 of tissue (Ref. 4).**

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

DT(r,e) = 1.11 x SF I DY(r,O)exp[-T(Ek)td1 (B-6)

The term "beta air dose" refers to the component of the air dose associated with particle emissions during nuclear and atomic transformations, i.e., o+, B-, and conversion electrons.

See discussion in Appendix E, Section 3.

1.109-20

TABLE B-I

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

Nucl ide B-air*(DF ) B-Ski n* * (DFSi) y-Air*(DFW) y-Body**(DFBi)

Kr-83m 2. 88E-04 1 93E-05 7. 56E-08 Kr-85m 1. 97E-03 1 46E-03 I 23E-03 1.1 7E-03 Kr-85 1 .95E-03 1 34E-03 1 72E-05 1.61 E-05 Kr-87 1 .03E-02 9.73E-03 6.1 7E-03 5.. 92E-03 Kr-88 2. 93E-03 2. 37E-03 1. 52E-02 1 .47E-02 Kr-89 1 .06E-02 1 .OIE-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 9.1 5E-05 Xe-1 33m 1 . 48E-03 9. 94E-04 3.27E-04 2.551 E-04 Xe-1 33 1 . 05E-03 3.06E-04 3.53E-04 2.94E-04 Xe-1 35m 7. 39E-04 7.11 E-04 3.36E-03 3.12E-03 Xe-i 35. 2. 46E-03 1 86E-03 1 92E-03 1 .81E-03 Xe-i 37 1 . 27E-02 1 22E-02 1 51 E-03 1 .42E-03 Xe-i 38 4. 75E-03 4.13E-03 9.21 E -03 8.83E-03 Ar-41 3. 28E-53 2.69E-03 9. 30E-03 8.84E-03

  • 3 mrad-m pCi-yr
    • 3 mrem-m pCi-yr

2.88E-04 = 2.88 x 1O0

I .109-21

Symbols for this equation are defined in Regulatory Position C.2.c of this guide. The factor SF accounts for the dose reduction provided by the shielding effect of typical residential structures (see Appendix E, Section 4 and Table E-15).

The skin dose has two components, the gamma and beta contributions. The skin dose rate is computed by DS(r,e) : 1.11 x SFDY(ro) + 3.17.x 1 1 Qi[x/Q]D(rG)DFSi (B-7)

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

The skin beta dose factors DFS were determined using the decay scheme source documents cited above and the methods used in References 5, 6, and 7. They are presented in Table B-i.

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

D(r,e) : SF ! xi(r,e)DFBi (B-8)

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

The annual skin dose is.computed as follows:

D0(r,e) 1.11 x SF xi(r,O)DFW + ! xi(r,e)DFSi (B-9)

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

1.109-22

REFERENCES FOR APPENDIX B

1. "Meteorology and Atomic Energy 1968," D. H. Slade (ed.), USAEC Report TID-24190, 1968.

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

3. M. E. Meek and R. S. Gilbert, "Summary of Gamma and Beta Energy and Intensity Data," NEDO- 12037, 1970.

4. J. K. Soldat et al., "The Dosimetry of the Radioactive Noble Gases," The Noble Gases (A. A. Moghissi and R. E. Stanley, eds.), ERDA-CONF 730 915, U.S. Energy Research and Development Administration, 1975.

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

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

73-107, 1973.

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

al*

'::i k!

1.109-23

APPENDIX C

MODELS FOR CALCULATING DOSES VIA ADDITIONAL PATHWAYS

FROM RADIOIODINES AND OTHER RADIONUCLIDES*

DISCHARGED TO THE ATMOSPHERE

1. Annual External Dose from Direct Exposure to Activity Deposited on the Ground Plane The ground plane concentration of radionuclide i at the location (r,e) with respect to the release point may be determined by CG(r,O) = [1.0 x 1012.1 [6i(re) Qi]

1 - 1 1 [1 - exp(_xitb)]. (C-l)

where CG(r,e) is the ground plane concentration of the radionuclide i in the sector at I angle 0 at the distancer from the release point, in pCi/m2 Q. is the annual'release rate of nuclide i to the atmosphere, in Ci/yr;

tb is the time period over which the accumulation is evaluated, which is 15 years (mid-point of plant operating life). This is a simplified method of approximating the average deposition over the operating lifetime of the facility;

6i(r,e) is the annual average relative deposition of effluent species i at location (r,e), considering depletion of the plume during transport, in m-2;

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

1.0 x 1012 is the number of pCi per Ci.

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

  • CG(r,e)DFGi (C-2)

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

Values for the open field ground plane dose conversion factors for the skin and total body are given in Appendix E,'.Table E-6. The annual dose to all other organs is taken to be equivalent to the total body dose. The factor SF is assumed to have a value of 0.7, dimensionless.

Does not include noble gases.

1.109-24

2. Annual Dose from Inhalation of Radionuclides in Air The annual average airborne concentration of radionuclide iat the location (r,e) with res- K, i,, pect to the release point may be determined as xi(r,e) = 3.17 x 104 Qi[x/Q] D(r,e) (C-3)

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

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

3

[x/Q]D(r,o) is the annual average atmosphere dispersion factor, in sec/m (see Regulatory Guide 1.111). This includes depletion (for radioiodines and particulates)

and radioactive decay of the plume; and

3.17 x l04 is the number of pCi/Ci divided by the number of sec/yr.

The annual dose associated with inhalation of all radionuclides, to organ j of an individual in age group-a, is then

0.A

ja (r,e) = Ra Zx.(r,e)DFA.

I ja (C-4)

Values for DFAija are given in Appendix E, Tables E-7 through E-l0; values for Ra are given in Appendix E, Table E-5. All other symbols are as defined earlier in Regulatory Position C.3.b.

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

a. Parameters for.Calculating Nuclide Concentrations in Forage, Produce, and Leafy Vegetables For all radioiodines and particulate radionuclides, except tritium and carbon-14, the concentration of nuclide i in and on vegetation at the location (r,e) is estimated using

[ -P exp(-xitb)]

Biv _2 Xi exp(-AEi te)]+ exp (- i th ) (c-5)

Cv(r,e) =di (r,e) tr[l -

See Regulatory Position C.1 of this guide for definitions of terms. Values for the parameters r, te, Yv' P, and th are provided in Appendix E, Table E-15. For the parameters te, Yv and th' different values are given (in Appendix E) to allow the use of Equation (C-5) for different purposes: estimating concentrations in produce consumed by man; in leafy vegetables consumed by man; in forage consumed directly as pasture grass by dairy cows, beef cattle, or goats; and in forage consumed as stored feed by dairy cows, beef cattle, or goats.

1.109-25

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

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

6i(r,e) is th6 relative deposition of radionuclide i, considering depletion and

1 2 decay in transit to location (r,e), in m- (see Regulatory Guide 1.111); and

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

(8760).

For radioiodines, the model considers only the elemental fraction of the effluent. The deposition should be computed only for that fraction of the effluent that is estimated to be elemental iodine. Measurements at operating facilities indicate that about half the radioiodine emissions may be considered nonelemental (Ref. 1). With this consideration included, Equation (C-6) for radioiodine becomes

6.(C-7)

di(r,e) = 5.5 x 1076i(r,e)Qi where is the total (elemental and nonelemental) radioiodine emission rate. The retention factor r for elemental radioiodine on vegetation should be taken as unity, since the experimental measurements (Refs. 1, 2, and 3) used to evaluate this transfer mechanism consisted of direct comparison of the gross radioiodine concentration on vegetation and the concentration in air (Refs. 4 and 5).

For radioiodines, the deposition model is based only on the dry deposition proces

s. Wet

.deposition, including "washout" of the organic and non-organic iodine fractions, should be con- sidered at some sites depending on the meteorological conditions (see Regulatory Guide 1.111).

For particulates, the deposition model considers both wet and dry deposition. There is also a retention factor (r of Equation (C-5)) that accounts for the interception and capture of the deposited activity by the vegetative cover. A value of 0.2 is taken for this factor (Refs. 6 and 7). All nuclides except noble gases, tritium, carbon-14, and the iodines are treated as particulates.

Carbon-14 is assumed to be released in oxide form (CO or C02 ). The concentration4of carbon,14 in vegetation is calculated by assuming that its ratio to the natural carbon in vegetation is the.

same as the ratio of carbon-14 to natural carbon in the atmosphere surrounding the vegetation (see Refs. 8 and 9). Also, in the case of intermittent releases, such as from gaseous waste decay tanks, the parameter p is employed to account for the fractional equilibrium ratio achieved. The parameter p is defined as the ratio of the total annual release time (for C-14 atmospheric releases)

to the total annual time during which photosynthesis occurs (taken to be 4400 hrs), under the condition'that the value of p should never exceed unity. For continuous C-14 releases, p is taken to be unity. These considerations yield the following relationship:

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

= 2.2 x 107 pQ1 4 [X/Q)(r,e) (C-8)

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

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

p is the fractional equilibrium ratio, dimensionless;

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

1.109-26

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

0.16 and

1

3.17 x 107 is equal to (1.0 x lO 2 pci/Ci)(l.0 x 103 g/kg)/(3.15 x 107 sec/yr).

The concentration of tritium in vegetation is calculated from its concentration in the air surrounding the vegetation. Using the method described in Reference 10, the NRC staff derived the following equation:

c'(r,). 3.17 x 107 QT[x/Q(rKe)(0.75)(0.5/H)

= 1.2 x 107 QT[x/Q](r,e)/H (C-9)

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

H is the absolute humidity of the atmosphere at location (r,e), in g/m3 QT is the annual release rate of tritium, in Ci/yr;

0.5 is the ratio of tritium concentration in plant water to tritium concentration in atmospheric water, dimensionless; and

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

b. Parameters for Calculating Nuclide Concentrations in Milk The radionuclide concentration in milk is dependent on the amount and contamination level of the feedconsumed by the animal. The radionuclide concentration in milk is estimated as C'(re) = vC(r,)Q exp(-xitf) (C-10)

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

Cv(r, e) is the concentration of radionuclide i in the animal's feed, in pCi/kg;

Fm is the average fraction of the animal's daily intake of radionuclide i which appears in each liter of milk, in days/liter (see Appendix E, Tables E-l and TableE-2E-2, cow the for use and values goat data, respectively;

in Table E-l); for nuclides not listed in is the amount of feed consumed by the animal per day, in kg/day;

tf is the average transport time of the activity from the feed into the milk and to the receptor (a value of 2 days is assumed); and i. is the radiological decay constant of nuclide i, in days--1 The concentration of radionuclide i in the animal's~feed is estimated as C.(r,e) = fpfsC.(r,e) + (l - f )C*(r,e) + fp(l fs)CS(r,e) (C-11)

p s ip i p' (C-ll where C (r,e) is the concentration of radionucl.ide i on pasture grass (calculated using Equation (C-5) with th=O), in pCi/kg;

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

1.109-27

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

The values of the parameters tho te, Yv, and tf that will be employed in evaluating the milk pathway, unless site-specific data is supplied, are provided in Appendix E, Table E-15.

c. Parameters for Calculating Nuclide Concentration in Meat As in the milk pathway, the radionuclide concentration in meat is dependent on the amount and contamination level of the feed consumed by the animal. The radionuclide concentra- tion in meat is estimated as F(r,e) FfCi(r,e)QF exp(-xits) (C-12)

where CF(r,e) is the concentration of nuclide i in animal flesh, in pCi/kg;

Ff is the fraction of the animal's daily intake of nuclide i which appears in each kilogram of flesh, in days/kg (see Appendix E, Table E-l for values); and ts is the average time from slaughter to consumption (see Appendix E, Table E-15)

All the other symbols are as previously defined.

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

4. Annual Dose from Atmospherically Released Radionuclides in Foods The annual dose to organ j of an individual in age group a resulting from ingestion of all radionuclides in produce, milk, meat, and leafy vegetables is given by ia vf v c(Lo FF Lai ] (-3 DP (r,e) ij[UafgC.(r,e)+

DFI~ UmC¶(,e) + U CFF(re) + UL f C(re)] (C-13)

agi a a aaXI

where D a(r,-O) is the annual dose to organ j of an individual in age group a from dietary intake of atmospherically released radionuclides, in mrem/yr;

DFI.. is the dose conversion factor for the ingestion of nuclide i, organ j, and age group a, in mrem/pCi (from Tables E-ll through E-14 of Appendix E of this guide); and U UaV , UF, are the ingestion rates of produce (non-leafy vegetables, fruit, and grains),

a a a a milk, meat, and leafy vegetables, respectively, for individuals in age group a (from Table E-5 of Appendix E of this guide).

All the other symbols are as previously defined. Values of f and fk to be assumed in the absence of site-specific information are given in Table E-15 of Appendix E as 0.76 and 1.0, respectively.

  • i 1.109-28

REFERENCES FOR APPENDIX C

1. B. H..Weiss et al., "Detailed Measurement of 1-131 in Air, Vegetation and Milk Around Three Operating Reactor Sites," NUREG-75/021, U.S. Nuclear Regulatory Commission, Washington, D.C., March 1975.

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

USAEC Report IDO-12063, January 1968.

3. J. D. Zimbrick and P. G. Voilleque, "Controlled Environmental Radioiodine Tests at the National Reactor Testing Station, Progress Report Number. Four," USAEC Report ID0-12065, December 1968.

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

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

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

6. C. A. Pelletier and P. G. Voilleque, "The Behavior of 137Cs and Other Fallout Radionuclides on a Michigan Dairy Farm," Health Phys., Vol. 21, p. 777, 1971.

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

1 37 54 of Cow's Milk as Critical Pathways for Cs, Mn and 144Ce-144Pr Released to the Atmosphere," Health Phys., Vol. 27, p. 189, 1974.

8. Y. C. Ng et al., "Prediction of the Maximum Dosage to Man from the Fallout of Nuclear Devices, IV Handbook for Estimating the Maximum Internal Dose from Radionuclide

s. Released

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

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

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

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

1.109-29

APPENDIX D

MODELS FOR CALCULATING POPULATION DOSES FROM

NUCLEAR POWER PLANT EFFLUENTS

Calculation of the annual population-integrated total body and thyroid doses* should be performed for the three effluent types identified in this guide. These doses should be evaluated for the population within a 50-mile radius of the site, as specified in paragraph D,Section II

of-Appendix I to 10 CFR Part 50.

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

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

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

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

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

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

in man-rems or thyroid man-rems;

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

Pd is the population associated with subregion d; and

0.001 is the conversion factor from mrem to rem.

'The annual dose to the total body or thyroid of an average individual should be evaluated with the usage factors of Table E-4 of Appendix E. Models and equations for the detailed dose calculations are presented in Appendices A, B, and C of this guide. The annual population- integrated doses from ingestion of potable water, inhalation of airborne effluents, and external exposure to airborne or deposited radionuclides should be evaluated. In addition to the pathways for which equations are presented in Appendices A, B, and C, other exposure pathways should be evaluated if conditions at a specific site indicate that they might provide a significant contri- bution to the total population dose from all pathways. In this context, a significant contribu- tion is defined as 10 percent or more.

For pathways that involve food products produced in the subregion, the food products may be distributed to other areas for consumption. For all the food that is produced within the 50-

mile radius, the radioactivity concentrations are averaged over the entire area by weighting the concentrations in each subregion by the amount produced in-each subregion. This average concentra- tion is used in calculating the population doses. The 50-mile average concentration of.nuclide in food p is computed as ip = (1/Vp) exp(-x itp)

P Cdipvdp (D-2)

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

-1.109-30

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

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

  • ip pCi/kg or pCi/liter;

t is the transport time of the food medium p through the distribution system, p in days (Table D-1 presents estimates of the transport times that may be used in lieu of site-specific data);

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

V is the mass or volume of the food medium p produced annually with the 50-mile radius about the site, in kg or liters; and

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

p .a ap a r where fa is the fraction of the population within the age group a;

a P is the estimated population that can be served by the quantity of food p P likely to be produced within 50 miles of the site;

Ua is the use or consumption factor of food medium p for the average individual Uap in age group a, in kg/yr or liters/yr (taken from Table E-4); and V is the annual mass or volume of food medium p likely to be produced within P a 50-mile radius about the site, in kg or liters.

The annual population-integrated dose is then calculated as D 0.001 Y'Pp a faC.i UapDF ai(D-4)

Sp where

P p if P*p< P 5 Pp., p 50

P550]if Pp > P5"50*

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

1.109-31

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

DISTRIBUTION SYST-...

FOOD MEDIUM DISTRIBUTION TRANSPORT TIME (in days)

Fruits, grains, and vegetables 14 Milk 4 Meat and poultry 20

Sport fish 7 Con*nercial fish 10

Drinking water 1 To be used in lieu of site-specific data on food distribution.

1.109-32

0)

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

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

Pp is the population consuming food medium p; and P50 is the total populationwithin 50 miles.

All other factors are as defined above.

Note that the above formulation limits theevaluation of the exposed population evaluation to the population residing within 50 miles as specified in paragraph D,Section II of Appendix I

to 10 CFR Part 50. In calculating the annual population-integrated total body and thyroid doses, the age distribution of the population within 50 miles may be assumed to be the same as the age distribution of the U.S. population (Ref. 1). Reference 1 indicates the fractional breakdown to be as follows: children, 0.18; teenagers, 0.11; and adults, 0.71. Infants (0-1 year in age) are not projected to exceed 2% of the population (Ref. 1), and their population fraction has been included in that given above for children.

2. Use of the Models a. Population-Integrated Doses from Liquid Effluents The annual total body and thyroid population-integrated doses due to exposure to liq- uid effluents should be evaluated for the following principal pathways: potable' water, aquatic food products, external irradiation from shoreline deposits, and terrestrial food products irri- gated with water that has received the liquid effluent.

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

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

-Equation (A-2) in Appendix A of this guide, together with the age-dependent usage factors U

ap obtained from Table D-1 The dilution from the discharge point to the usage point'should be evaluated using appropriate hydrological models for the various subregions.

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

Pw e v/c (D-5)

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

Pw is the estimated population served by the water system; and v is the average daily intake of the water supply system, in gal/day.

If the industrial usage from the water supply system is known, it can be sub- tracted from the average daily intake of the system before this value is entered into Equation (D-5).

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

1.109-33

(2) Doses from Aquatic Food Products The annual population-integrated total body and thyroid doses from consumption of aquatic food products are evaluated using the production of sport and commercial harvests in the various subregions. The mixing ratio (or dilution) should be evaluated for each subregion using an appropriate hydrological model. For sport harvests, the entire edible harvest is a'ssumed to be ingested by the population within 50 miles. The formulation expressed by Equation.

(D-4) should be used with-the population Pp.given by the results of Equation (D-3). The age- specific ingestion rates of Table E-4 may be used in lieu of site-specific data.

For commercial harvests, the production within 50 miles from the site is con- sidered as part of the total U.S. harvest. Equation (D-2) should be used to compute the average concentration, with V as the total estimated U.S. commercial harvest of the aquatic food p

medium p. The annual population--integrated dose is then computed using Equation (D-4) with Pp = P50. The age-specific factors of Table E-4 may be used in lieu of site-specific data.

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

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

b. Population-Integrated Doses from Airborne Effluents The annual total body and thyroid population-integrated doses should-be evaluated for the following principal exposure pathways: noble gas submersion, inhalation of airborne efflu- ents, ingestion of contaminated terrestrial foods (milk, meat, and produce), and external irradiation from activity deposited on the ground. Available state or county agricultural pro- duction data may be used for estimating the population-integrated doses from food consumption.

For the evaluation of exposures from atmospheric releases, the 50-mile region should be divided into 160 subregions formed by sectors centered on the 16 compass points (N, NNE, NE,

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

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

(2) Doses due to Inhalation of Radioiodines and Particulates The annual population-integrated total body and thyroid doses from inhalation of airborne effluents should be evaluated by summing the products of the individual doses received in each subregion and the population in each subregion. Equation (D-1) may be used. The age- specific inhalation rates of Table E-4 may be used with the data of Tables E-7 to E-l0.

1.109-34

(3) Doses due to Ingestion of Terrestrial Food Products The annual population-integrated total body and thyroid doses from. ingestion of terrestrial food products should be evaluated using the production data for each subregion. For milk, meat, and commercial vegetables, the formulation of Equation (D-2) should be used to calculate the average concentrations in the foods. These concentrations are then used in Equation (D-4), along with the data of Tables D-l, E-4, and E-ll to E-14, to calculate population doses.

(4) Doses due to External Irradiation from Activity Deposited on the Ground The annual population-integrated total body and thyroid doses from external exposure to surface deposition of the effluent should be evaluated using Equation (D-l). A

household shielding and occupancy factor of 0.5 should be applied in conjunction with the dose factors of Table E-6.

REFERENCE FOR APPENDIX D

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

1.109-35

APPENDIX E

NUMERICAL DATA FOR THE CALCULATION

OF ANNUAL DOSES TO MAN FROM ROUTINE

RELEASES OF REACTOR EFFLUENTS

This appendix contains data for use in the equations presented in the Regulatory Position and in Appendices A, B, C, and D of this guide. The numerical values presented in this appendix are those routinely used by the NRC staff. In instances where more appropriate information of a site-specific nature has been developed and documented, that information should be used.

In a number of instances the staff has found it necessary to provide guidance as to the value of a particular parameter in the absence of substantial empirical data. In such instances the staff has exercised judgment and has considered values used by others and the sensitivity of the results to the value assumed.

Information is provided below under four broad categories: environmental data, human data, dose factors, and other parameters.

1. Environmental Data Table E-1 provides values for the following staDle element transfer coefficients:

a. Biv for the estimation of produce, leafy vegetable, or pasture grass radioactivity from that in soil (pCi/kg in vegetation per pCi/kg in soil);

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

day ingested by the animal); and c. Ff for the estimation of meat activity from that in feed (pCi/kg in meat per pCi/day ingested by the animal).

The data are largely derived from Reference 1. The value of the cow milk transfer coefficient for radioiodine is based on the staff's review of the literature (Refs. 2-9).

Values of transfer coefficients for goat milk are presented in Table E-2 for a limited number of nuclides. For nuclides not listed in Table E-2, the milk transfer coefficient from Table E-1 should be used.

Various animal parameter values are presented in Table E-3 for use in estimating animal product activity levels as functions of the corresponding levels in feed and water supplies.

2. Human Data Tables E-4 and E-5 present usage rates of various environmental media by average individuals and maximum individuals, respectively, according to age group. "Seafood" is used to indicate intake of aquatic invertebrates such as lobster, crab, clams, and'oysters. Ingestion of aquatic plant material is not normally assumed.

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

2 presented in Table E-6 (Refs. 10 and 11), in units of mrem/hr per pCi/m . These factors are applicable for surface contamination via deposition of liquid effluents on shoreline sediments or airborne effluents on ground surfaces. Dose factors are provided for the total body and skin only. Doses to other organs are assumed equal to the total body dose.

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

1 meter above the ground plane and the penetration of the radiation into the body. The total body dose is computed at a penetration depth of 5 cm; the skin dose is computed at a depth of

7 mg/cm2 . These tissue depths are indicated by Reference 12, where it is suggested that, for

1.109-36

TABLE E-1 STABLE ELEMENT TRANSFER DATA*

Biv Fm(Cow) Ff Milk (d/z)

Element Veg/Soil Meat (d/kg)

H** 4.8E 00 1.OE-02 1.2E-02 C** 5.5E 00 1.2E-02 3.1E-02 Na 5.2E-02 4.0E-02*** 3.OE-02 P l.IE 00 2.5E-02 4.6E-02 Cr 2.5E-04 2.2E-03 2.4E-03 Mn 2.9E-02 2.5E-04 8.OE-04 Fe 6.6E-04 1 .2E-03 4.OE-02 Co 9.4E-03 I .OE-03 1.3E-02 Ni 1.9E-02 6.7E-03 5.3E-02 Cu 1 .2E-01 1 .4E-02 8.OE-03 Zn 4.OE-01 3.9E-02 3.0E-02 Rb 1 .3E-01 3.OE-02 3.1E-02 Sr 1.7E-02 8.0E-04*** 6.OE-04

'Y 2.6E-03 1.OE-05 4.6E-03 Zr 1 .7E-04 5.OE-06 3.4E-02 Nb 9.4E-03 2.5E-03 2.8E-01 Mo 1.2E-01 7.5E-03 8.OE-03 Tc 2.5E-01 2.5E-02 4.OE-01 Ru 5.0E-02 1 .OE-06 4.6E-01 Rh l.3E 01 1.OE-02 1.5E-03

'I'

Ag I .5E-01 5.OE-02 1.7E-02 N, Te l.3E 00 1 .OE-03 7.7E-02 I 2.OE-02 6.OE-03t 2.9E-03 Cs 1 .OE-02 1 .2E-02*** 4.OE-03 Ba, 5.OE-03 .4.0E-04"*** 3.2E-03 La 2.5E-03 5.OE-06 2. OE-04 Ce 2.5E-03 l.OE-04*** 1 2E-03 Pr 2.5E-03 5.OE-06 4.7E-03 Nd 2.4E-03 5.OE-06 3. 3E-03 W 1.8E-02 5.OE-04 1 .3E-03 Np 2.5E-03 5.OE-06 2.OE-041t Data presented in this table is from Reference 1 unless otherwise indicated.

Meat

. and milk coefficients are based on specific activity considerations.

From Reference 15.

tSee text.

ttFroim Reference 13.

1.109-37

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

Fm (days/liter)

Element H 0.17 C 0.10

P 0.25 Fe 1.3E-04 Cu

0.014"*

Sr I 0.06&*

Cs -0.30**

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

From Reference 15.

TABLE E-3 ANIMAL CONSUMPTION RATES

QAw Feed or Forage Water Animal (kg/day [wet weight]) ( R./day)

Milk cow 50 (Ref. 10) 60 (Ref. 16)

Beef cattle 50 (Ref. 10) 50 (Ref. 16)

Goats 6 (Ref. 17) 8 (Ref . 18)

1.109-38 IL

TABLE E-4 RECOMMENDED VALUES FOR U TO BE USED FOR THE AVERAGE INDIVIDUAL

ap IN LIEU OF SITE-SPECIFIC DATA

Pathway Child Teen Adult Fruits, vegetables, &

grain (kg/yr)* 200 240 190

Milk (z/yr)* 170 200 110

Meat & poultry (kg/yr)* 37 59 95 Fish (kg/yr)* 2.2 5.2 6.9 Seafood (kg/yr)* 0.33 0.75 1.0

Drinking water (L/yr)** 260 260 370

Shoreline recreation (hr/yr)** 9.5 47 8.3 Inhalation (m3 /yr) 3700*** 8000*** 8000t Consumption rate obtained from Reference 19 and age-prorated using techniques in Reference 10.

Data obtained directly from Reference 10.

Inhalation rate derived from data provided in Reference 20.

tData obtained directly from Reference 20.

1.109-39

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

- INfJVIDUAL IN LIEU OF SITE-SPECIFIC DATA

Pathway Infant Child Teen Adult Fruits, vegetables &

grain (kg/yr)*,** 520 630 520

Leafy vegetables

  • (kg/yr)* 26 42 64 Milk (k/yr)* 330 330 400 310

Meat & poultry (kg/yr)* 41 65 110

Fish (fresh or salt)

(kg/yr)*** 6.9 16 21 Other seafood (kg/yr)* 1.7 3.8 5 Drinkingwater (Z/yr)t 330 510 510 730

Shoreline recreation (hr/yr)t 14 67 Inhalation (m3/yr) 1400tt 3700ttt 8000tt-t 8000tt Consumption rate obtained from Reference 19 for average individual and age-prorated and maximized using techniques contained in Reference 10.

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

Consumption rate for adult obtained by averaging data from References 10

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

tData obtained directly from Reference 10.

.Data obtained directly from Reference 20.

tttiInhalation rate derived from data provided in Reference 20.

1.109-40

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

(mrem/hr per pCi/m2)

Element Total Body Skin

-H-3 0.0 0.0

C-14 0.0 0.0

NA-24 2.50E-08 2.90E-08 P-32 0.0 0.0

Cr-51 2.20E-10 2.60E-10

Mn-54 5.80E-09 6.80E-09 Mn-56 l.1OE-08 1.30E-08 Fe-55 0.0 0.0

.Fe-59 8.OOE-09 9.40E-09 Co-58 7.OOE-09 8.20E-09 Co-60 1.70E-08 2.OOE-08 Ni-63 0.0 0.0

Nr-65 3.70E-09 4.30E-09 Cu-64 1.51E-09 1.70E-09 Zn-65 4.OOE-09 4.60E-09 Zn-69 0.0 0.0

Br-83 6.40E-11 9.30E-11 Br-84 1.20E-08 1.40E-08 Br-85 0.0 0.0

Rb-86 6.30E-10 7.20E-10

Rb-B8 3.50E-09 4.O0E-09 Rb-89 1.50E-08 1.80E-08 Sr-89 5.60E-13 6.50E-13 Sr-91 7.10E-09 8 30E-09 Sr-92 .9.00E-09 IOOE-08 Y-90 2.20E-12 2.60E-12 Y-91M 3.80E-09 4.40E-09 Y-91 2.40E-ll 2.70E-11 Y-92 1.60E-09 1.90E-09 Y-93 5.70E-1O 7.80E-10

Zr-95 5.ODE-09 5-80E-09 Zr-97 5.50E-09 6.40E-09

  • Nb-95 5.10E-09 6.OOE-09 Mo-99 1.90E-09 2.20E-09 Tc-99M 9.60E-10 1.1OE-09 Tc-ll 2.70E-09 3.OOE-09 Ru-103 3.60E-09 4.2DE-09 Ru-105 4.50E-09 5.1DE-09 Ru-106 1.50E-09 1.80E-09 Ag-liOM 1.80E-08 2.10E-08 Te-125M .3.50E-l1 4.80E-l1

.Te-127M 1.1OE-12 1.30E-12 Te-127 1.OOE-l1 1.1OE-11 Te-129M 7.70E-10 9.O0E-10

Te-129 7.10E-10 8.40E-10

Te-131M 8.40E-09 9.90E-09- Te-131 2.20E-09 2.60E-06 Te-132 1.70E-09 2.00E-09

1-130 1.40E-08 1.70E-08

1-131 2.80E-09 3.40E-09

1-132 1.70E-08 2.OOE-08

1-133 3.70E-09 4.50E-09

1-134 1.60E-08 1.90E-08

1-135 1.20E-08 1.40E-08

1.109-41

TABLE E-6 (Continued)

Element Total Body Skin Cs.-134 1.20E-08 1. 40E-08 Cs-136 1.50E-08 1 .70E-08 Cs-1 37 4.20E-09 4.90E-09 Cs-138 2. 1OE-08 2.40E-08 Ba-139 2.40E-09 2.70E-09 Ba-1 40 2. lOE-09 2.40E-09 Ba-141 4.30E-09 4.90E-09 Ba-142 7.90E-09 9.00E-09 La-I 40 1.50E-08 1. 70E-08 La-142 1.50E-08 I. 80E-08 Ce-141 5.50E-10 6.20E-10

Ce-143 2.20E-09 2.50E-09 Ce-144 3.20E-10 3.70E-10

Pr-143 0.0 0.0

Pr-144 2.00E-10 2.30E-10

Nd-147 1. OOE-09 1.20E-09 W-187 3.10E-09 3.60E-09 Np-239 9.50E-10 1 .10E-09

1.109-42

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

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

2 in the computation of skin dose and states an average depth for these cells of 7 mg/cm . This guidance is reflected in the dose factors presented in Table E-6 and also in those presented in Appendix B, Table B-l, for use in calculating external doses from noble gases.

Dose factors for internal exposure are provided in Tables E-7 through E-14, in units of mrem per pCi intake (Ref. 25). Tables E-7 through E-l0 are for inhalation (one table for each of the four age groups), while Tables E-ll through E-14 are for ingestion. Dose factors provided for the inhalation of H-3 include an increase of 50 percent to account for the additional amount of this isotope absorbed through the skin (Ref. 25).

As discussed in Section B, "Discussion," these dose factors are appropriate for continuous intake over a one-year period and include the dose commitment over a 50-year period. The cal- culational scheme by which these dose factors are derived includes elementary consideration of changing physical and metabolic characteristics during the period over which the dose commitment is evaluated. For example, environmental exposure of an infant over a one-year period is treated as follows: dose during the first year is computed based on infant physiological-and metabolic characteristics considering both the buildup and decay of the appropriate organ burden; dose during.years 1-10 is computed based on child physiological and metabolic data considering decay

.of the organ burden from its peak value at age 1; dose during years 11-16 is treated in a similar fashion using teenager characteristics; and dose during adulthood is computed based on the physiological and metabolic characteristics of an adult. Age-dependent parameters are changed in steps at the breaks between age groups.

4. Other Parameters

.Table E-15 has been provided as a central location for the recommended values of many of the miscellaneous parameters appearing in equations in this guide. In some instances, a parameter's value or units is a function of the equation it is used in. Additionally, for some parameters used in calculating activities in vegetation, the value is also a function of the exposure path- way. Table E-15 has been organized to note these complications.

Values of the parameter SF, a structural shielding and occupancy factor, are given in Table E-15 as 0.7 (for maximum individuals) and 0.5 (for the generalpopulation). Using the general approach given in Reference 26, the staff estimates an average structural shielding factor of 0.5 for typical reactor effluents. Assuming the maximum individual spends about 50 percent of the time indoors, the overall shielding and occupancy factor is then approximately 0.7. The factor of 0.5 is used directly for population dose calculations. These factors are applicable for external gamma exposure from noble gases and for external exposure from contaminated ground surfaces.

1.109-43

TABLE E-7 PASE I OF 3 INHALATION DOSE FACTORS FOR AnULTS

(UREM PER PCI INHALED)

NUCLIDE HONE LIVER T.ROCY THYROID KIDNEY LUNG GI-LLI

H 3 NO DATA 1.58E-07 1.58F-07 1.58E-C7 l.58E-07 1.58E-07 1.58E-07

1.4 2.27E-06 4.26E-07 4.26E-07 4.26E-07 4.26L-07 4.26E-07 4.26E-07 AA 24 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.2RE-06 1.28E-06 p 32 1.65E-04 9.64E-06 6.26[-06 NO DATA NC DATA NO DATA 1.08E-05 CR 51 NO DATA NO DATA 1.25E-08 7.44E-Oq 2.85E-09 1.80E-06 4.15F-07 MN 54 NO DATA 4.95E-0b 7.8rE-07 NO DATA 1.23L-06 1.75E-04 q.67E-06 MN 56 NO DATA 1.55E-10 2.29E-11 '0 DATA 1.63E-1O 1.18E-06 2.53E-06 FE 55 3.07E-06 2.12C-06 4.93E-07 NO DATA NO DATA 9.C1E-06 7.54E-07 FE 59 1.47E-06 3.47E-0b 1.32E-06 NO DATA NO DATA 1.27E-04 2.35E-05 CO 58 ND DATA 1.98E-07 2.59E-07 NO DATA NC DATA 1.16E-04 1.13E-05, CO 60 NO DATA 1.44E-06 1.85E-36 NO DATA NO DATA 7.4bE-04 3.56E-05 NJ1 63 5.40E-05 3.13E-06 1.81E-06 NO DATA NO DATA 2.23E-05 1.67E-06

4l 65 I.92E-10 2.o2C-II 1.14F-11 NO DATA NC DATA 7.0OE-07 1.54E-06 CU 64 NO DATA 1.93E-10 7.63F-11 NO DATA 5.78E-1O 8.48E-07 6.12E-06 ZN 65 4.05E-06 1.29F-05 5.82E-06 NO DATA R.62E-06 1.08E-04 6.68E-06 ZN 69 4.23E-12 8.14ý-12 5.65E-13 NO DATA 5.27L-12 1.15.E-07 2.04E-C9

ýAR 83 NO DATA 40 DATA 3.01E-08 NO DATA NO DATA NO DATA 2.90F-08

,R 84 NO DATA NO DATA 3.91E-08 NO DATA NO DATA NO DATA 2.05E-13 diR 80 NO DATA NO DATA 1.60E-09 NO DATA NC DATA NO DATA LT E-24 RE! 8B NO DATA 1.69E-D5 7.371E-06 NO DATA NO DATA NO DATA 2.08E-06 RB 88 NO DATA .4.84E-08 2.41E-98 NO DATA NO DATA NO DATA 4.iB-I1 RB 89 NO DATA 3.20E-O8 2.12E-08 NO DATA NO DATA NO DATA 1.16F-21 SR 89 3.80E-05 NO DATA 1.09E-06 NO DATA NO DATA 1.75E-04 4.37E-05 SR 90 1.24E-02 NO DATA 7.62E-04 NO DATA NC DATA 1.20E-03 9.02E-05 SR 91 7.74E-Oq NO DATA 3.13E-1D NO DATA NO DATA 4.56E-06 2.39F-05 SR 92 8.43E-10 NO DATA 3.64E-11 NO DATA NO DATA 2.06E-06 5.38E-06 Y 90 2.61E-07 NO DATA 7.01E-09 NO DATA NO DATA 2.12E-05 6.32E-05 Y 9111 3.26E-11 NO DATA 1.27E-12 NO DATA NC DATA 2.40E-07 1.66E-10

Y 91 5.78E-05 NO OArA 1.55E-06 NO DATA NO DATA 2.13E-04 4.81E-05 Y 92 1.29E-09 NO DATA 3.77E-11 NO DATA NO DATA I.q6E-06 9.19E-06

1.109-44

TABLF E-7, CONT'D

PASF 2 OF 3 INHALATION DOCSE FACTORS FOR ADULTS

,(REM PFR PCI INHALED)

  • .NUCL I ;L BONE LIVFR T.-BODY THYROID KIDNEY LUNG GJ-LLI

'y 93 1.18E-Or NO DATA 3.26E-10 NO DATA NC DAT.A 0.06E-06 5.27E-05 I ZR 95 1.34E-05 4.3CE-06 2.91E-06 NO DAT4 6.77E-06 2.21E-04 1.38E-05 ZR 97 1.2IF-O8 2.45E-09 1.13E-09 NO DATA 3.71E-09 9.84E-C3 6.54E-05 NB 95 1.76E-06 9.77L-07 5.26E-07 NO DATA 9.67E-07 6.31E-05 1.30F-05 MO 99. AJO DATA 1.I5-1 8 2.87E-09 NO DATA 3.64E-OB 1.14E-05 3.10E-05 TC 99M,' 1.29E-13 3.64F-13 4.63E-12 NO DATA 5.52E-12 9.55E-08 5.20E-07 TC101 5."'2E-15 7.52E-15 1.36E-14 NO DATA -1.35E-13 4.99E-08 1.36F-21 RU*03 1.91E-07 NO DATA 8.23E-08 NO DATA '7.29E-07 6.31E-05 1.38E-05 RUIC5 9.88E-11 NO DATA 3.89E-1i NO DATA 1.27E-10 1.37E-06 6.02E-06 RUI06 8.64E-C6 NO DATA l.O)E-06 NO DATA 1.67E-05 1.17E-03 1.14E-04 AG110 1.35C-,6 1..25.-06 7.43,--07 NO DATA 2.46E-06 5.790-04 3.78E-05

5 TC125M1 4.27E-07 1.Q9E-O7 5.84E-08 1.31E-07 1.5 E-06 3.92E-C5 8.83E-06 TE127r' 1.58F-06 7.21C-07 1.96E-07 4..1iE-07 5.72E-06 1.20E-04 1.87E-05 TE127 1.75[-10 8.OC'3-Il 3.87E-11 1.32E-10 6.37E-10 8.14E-07 7.1.7-06 IE129P 1.22E-06 5.84's-07 1.96E-O7 4.30E-07 4.57E-06 l.45E-O4 ,.79-05 TE129 6.220-12 2."9L-12 1.5'.)E-12 4.87E-12 2.34E-11 2.42E-07 I.96F-08 TEI3lM 8.14E-09 5.45E-09 3.63F-09 6.88E-09 3.86E-08 1.82E-05 6.95E-05 TF131 1.39E-12 7.44E-13 4.49E-13 1.17T-12 5.46E-12 1.74=-07 2.30E-09

1E132 3.25L-08 2.69E-08 2.0O?-08 2.37E-08 1.82E-07 3.60E-05 6.37F-05

1 1.30 5.72E-07 I.o8E-O6 6.6;C-07 1.42E-04 2.61E-06 NO DATA 9.61E-07

1 131 3.15E-06 4.47E-io 2.56E-06 1.49E-03 7.66E-06 NO [ATA 7.85F-07

1 132 1.45E-07 4.07E-07 1.45E-07 1.43E-05 6.48E-07 NO DATA 5.08F-08

1 133 1.08E-06 1.85E-06 5.65E-07 2.69E-04 3.23E-06 NO DATA 1.11F-06 I 134 ,.05-08 2.160-07 7.69E-08 3.73E-06 3.44E-07 NO DATA 1.26E-1O

I 135 3.35E-C7 8.73E-07 3.21E-07 5.bOE-C5 1.39E-06 NO DATA 6.56E-07 CS134 4.66E-05 1.06E-04 9.10-05 NO DATA 3.59E-C5 1.22E-05 1.30E-06 CS136 4.88E-C6 1.F3Z0-05 1.33q-05 '40 DATA I.,07E-05 1.50E-06 1.46E-06

--S137 5.98E-05 7.760-05 5.35[-05 NO DATA 2.78E-q5 9.40E-06 1.052-06 CS13'i 4.14E-08 7.767-08 4.0jE-38 NO ,ATA 6.OE-09 6.07E-09 2.33E-13 a139 1.17-.-10 -14 3.42-12 NO DATA 7.78E-14 4.70E-07 1.120-07 A!!

1.109-45

TABLL E-7, CONT'D

PAGE 3 OF 3 INHALATION DUSE FACTORS' FOR ADULTS

(MREM PER PCI INHALED)

NUCLICE BONE LIVER T.BcY THYROID KIDNEY LUNG GI-LLI

sA140, 4.F8E-O6 b.13F-09 1.21E-07 NO DATA 2.O9E-09 1.59E-04 2.73F-05

-AI41 1.25E-11 9.41tz-15 4.2CE'-13 NO DATA 8.75E-15 2.42E-07 1.45E-17 RAI42 3.29E-12 3.38E-15 2.07E-1I NO DATA 2.96E-15 I.49E-O 1.96E-26 LA140 4.30E-C8 2.171-08 5.73E-09 NU DATA NO DATA .1.70E-0.5 5.73E-05 LA142 8.54E-1i 3.88E-11 9.65E-12 NO DATA NO DATA 7.91F-07 2.64E-07 CE4I1 2.49E-O0 1.69;--06 1.91E-07 NO DATA 7.83E-07 4.52E-05 1.50E-05

E143 2.33E-08 1.72E-o0 1.91E-O9 NO DATA 7.60E-0 9 .97E-06 2.83E-05

-E144 4.29E-04 1.79E-04 2.30E-05 NO DATA 1.ObE-04 9.72E-04 1.02E-04 PR143 1.17E-06 4.69E-07 5.80E-O8 NO DATA 2.70E-07 3.51E-05 2.50E-05 PR144 3.76E-12 1.56E-12 1.91E-13 NO DATA 8.RIE-13 1.27E-07 2.69E-18 OD147 6.59E-07 7.62E-07 4.56E-08 NO DATA 4.45E-07 2.76E-05 2.16E-05 w 187 I.06E-09 B.85E-10 3.10E-IO NO DATA NO DATA 3.63E-06 1.q4E-05 NP239 -2.87E-O8 2.S2E-09 1.55E-09 NO DATA 8.75E-09 4.70E-06 1.49E-05

1.109-46

77

$ TABLE E-8 PAGE 1 OF 3 INHALATION DOSE FACTORS FOR TEENAGER

(NREM PER PCI INHALED)

14UCLICE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI

H 3 NO DATA 1.59E-07 1.59E-07 1.59E-07 1.59F-07 1.59E-07 1.59E-07 C 14 3.25E-06 6.C9E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07

1A 24 1.72E-06 1.72[-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06

3 P- "32 2.36E-04 1. 7E-05 8.95E-06 NO DATA NC DATA NO DATA 1.16F-05 CR 51 NO DATA NO DATA 1..69E-08 9.37E-09 3.842-09 2.62E-06 3,75E-07 MN 54 NO DATA 6.39F-06 1.OE-O6 NO DATA 1.59E-06 2.48E-04 8.35E-06 MN 56- NO DATA 2.1 2 E-1O 3.15E-11 NO DATA 2.24E-10 1.90E-06 7.18E-06 FE-55 4.18E-06 2.98E-06 6.93E-07 NO DATA NO DATA 1.55E-05 7.99E-07 FE 53 1.99E-06 4.62E-0.6 1.79E-06. NO DATA NO DATA L.91F-04 2.23E-05 CO 58. NO DATA 2.59E-07 3.47E-07 NO DATA NO DATA 1.68E-04 1.19E-05 CO 60 NO DATA L.89E-06 2.48E-06 -NO DATA NO DATA 1.09E-03 3.24E-.05 NI 63 7.25E-05 5.43E-06 2.47E-06 NO DATA NO DATA 3.84E-05 1.77E-06

'I 6ý5 2.73E-10 3.uo6-1l 1.59E-11 NO DATA NO DATA 1.17E-06 4.59E-06 CU 64 NO DATA 2.54E-10 1.06E-10 NO DATA 8.01E-10 1392E-06 7.68E-06 LN 65 4.82E-06 1.67E-05 7.80E-06 NO DATA 1.08E-05 1.55E-04 5.83E-06

  • N 69 6.04E-12 1.15F-11 8.07E-13 NO DATA 7.53E-12 I.q8E-07 3.56F-08 HR 83 NO DATA NO DATA 4.30E-00 NO DATA NO DATA NO DATA LT E-24 L3R 84 NO DATA NO DATA 5.41E-08 NO DATA NO DATA NO DATA LT E-24 riR 85 NO DATA NO DATA 2.29E-09 -NO DATA NO DATA NO DATA LT E-24 RB 86 NO DATA 2.38E-05 1.05E-05- NO DATA NO DATA NO DATA 2.21E-06 R 8'3 NO DATA 6.82E-08 3.40E-08 NO DATA NO DATA NO DATA 3.65E-15 RB 89 NO DATA 4.402-08 2.9.1E-08 NO DATA NO DATA NO DATA 4.22E-17 SR 89 5.43E-05 NO DATA 1.56E-06 NO DATA NO DATA 3.02E-04 4.64E-05 SR q3 1.35E-02 NO DATA 8.35E-04 NO DATA NO DATA 2.06E-03 9.56E-05 SR 91 1.10E-08 NO DATA 4.39E-10 NO DATA NO DATA 7.59E-06 3.24E-05 SR 92 1.19E-09 NO DATA 5.08EI- NO DATA NO DATA 3.43E-06 1.49E-05 Y 90 3.73E-07 NO DATA 1.OE-08 NO DATA NO DATA 3.66E-05 6.99E-05 Y 91M 4.63E-11 NO DATA 1.77E-12 NO DATA NO DATA 4.0OE-07 3.77E-09 Y 91 8.26E-05 NO DATA 2.21E-06 NO DATA NO DATA 3.67E-04 5.11E-05 Y 92 1.84E-0q NO DATA 5.36E-11 NO DATA NO DATA 3.35E-06 2.06E-05

1.109-47

TABLE E-8, CONTID

PAGE 2 OF 3 lNHALtCTIOA DOSE FACTORS FOR TEFNAGFR

(MREM PER PCI INHALED)

IRJCLIDE BONE LIVFR T.AODY THYROID KIDNEY LUNG GI-LLI

Y 93 1.69E-08 NO DATA 4.65E-10 NO DATA NO DATA 1.04E-05 7.24E-05

!R 95 1.82E-05 5.73c-O 3.94E-06 NO DATA 8.42E-06 3.36E-04 1.86E-05 ZR 97 1.72E-08 3.40E-09 1.57E-09 NO DATA 5.15E-09 1.62E-05 7.88E-05 iDl 95 2.32E-06 1.29E--b 7.08E-07 NO DATA 1.25E-06 9.39E-05 1.21E-05 MO 99 AJ0 DATA 2.l1E-08 4.03E-09 40 CATA 5.14E-08 1.92E-05 3.36E-05 IC 99M 1.73E-13 4.83E-13 b.24E-12 NO DATA 7.20E-12 .1.44E-01 7.66E-07 TCIOI 7.40E-15 1.OE-14 1.03E-13 NO DATA 1.90E-13 F.34E-0O 1.09E-16 RU103 2.63E-07 NO CATA 1.12C-07 NO DATA 9.29E-07 9.79E-05 1.36F-05 RU1O5 1.40E-10 NO DATA 5.42E-11 NO DATA 1.76E-0O 2.27E-06 1.13E-05 RULOb 1.23F-05 NO DATA 1.55E-06 NO DATA 2.38E-05 2.01E-03 1.20E-04 AGtlOM 1.73E-06 1.64E-Ob 9.99E-0-7 NO DATA 3.13E-06 B.44E-04 3.41F-05 TE12SM 6.lOE-07 2.80E-07 8.34E-08 1.75E-07 NO DATA 6.70E-05 9.38E-06 TE127M 2.?5E-06 1.CF-0O 2.73E-07 5.48E-07 8.17E-06 2.07E-04 1.99E-05 TE127 2.51E-10 1.14F-1O 5.52E-11 1.77E-10 9.1OE-1O 1.40F-06 1.OIE-05 rE129m 1.74E-06 8. 2 3E-07 2.81E-07 5.72E-07 6.49E-06 2.47E-04 5.06E-05 TF129 8.87E-12 4.22E-12 2.29E-12 6.4RE-12 3.32E-11 4.12E-07 2.02E-07 rEl31 1.23E-08 7.51E-09 5.03E-09 '.3/406E-09 5.49E-08 2.97E-05 7.76E-05 TEl31 1.97E-12 1.04E-12 6.30E-13 I..55E-12 7.72E-12 2.92E-07 1.89E-09 TE132 4.50E-08 3.63E-08 2.74E-08 3.07E-08 2.44E-07 5.61E-05 5.79F-05 I 130 7.80E-07 2.247-06 8.9oE-07 1.86E-04 3.44E-06 NO DATA 1.14E-06

1 131 4.43E-06 6.14F-06 3.30E-06 I.83E-03 1.05E-05 NO DATA 8.11F-07 I 132 1.99E-07 5.47E-07 l.q7E-07 1.89E-05 8.65E-07 NO DATA 1.59E-07

1 133 1.52F-06 2.,bE-Cb 7.78E-97 3.b5E-04 4.49E-06 NO DATA 1.29E-06 I 134 1.1IE-07 2.90E-07 1.05E-07 4.94E-06 4.58E-07 NO DATA 2.55E-09

1 135 4.62E-07 1.18E-Ob 4.36E-07 7.76E-05 1.86E-06 NO DATA 9.69E-07 CS134 6.28E-05 1.41E-O b.8oE-05 NO DATA 4.69E-05 1.83E-05 1.22E-06 CS136 6.44E-06 2.42C-05 1.71E-05 NO DATA 1.38E-05 2.22E-06 1.36E-06 CS137 8.38E-05 1.06E-04 3.89E-O5 NO DATA 3.80E-05 1.51F-05 1.06E-06 CS138 5.82E-08 1.07E-07 5.59E-08 NO DATA 8.28E-08 9.84E-09 3.38E-1l BA[39 1.67E-10 1.IE-13 4.87E-12 NO DATA I.IIE-13 8.08E-07 8.06E-07

1.109-48

'TAtLiLE E-8, CONT'IC

PAGE 3 OF 3 INHALATION 00[SE F.ACTORS FOR TEENAGER

(MREM PER PCT INHALED)

NULO DOE LIL T.3CCY THYOC KIDNEY LUNG GI-L

,3&140O 6.84E-06 A. 58F-09 4.40E-07 NIO DATA 2.85E-n9 2.54E-04 2.86E-05

1dA41 1.78E-11 l..12F-1[4 5.93[-13 NO DATA 1.23E-14 4.11E-07 9.33E-14

!AA2 4.62E-12 4.63E-15) 2.84F-13 NO DATA, 3.92E-15 2.39E-07 5.99E-20

LA140 5.99E-08 2.951E-08 7.82--09 NO UATA NO DATA 2.68E-05 6.09E-05 LA142 1.200-10 5.31E-11 1.32E-11 NO DATA N' DATA 1.27E-06 1.50[-06 CE141 3.55E-06 2.37ý-Oh 2.71E-07 NO DAT4 1.11L-06 7.67E-05 1.58E-05 CE143 3.32E-08 2.4/2E-08 2.70E-09 NO DATA I.08R-08 1.63E-0'5 3.19E-05 CE144 6.11E-04 2.53E-04 3.23E-05 NO DATA 1.51E-04 1.67E-03 1.08E-04

. PR143 1.67E-06 6.64E-07 3.2SE-O8 NO DATA 3.86E-07 6.04E-05 2.67E-05 PI,144 5.37E-12 2.20E-12 2.72E-13-- N'O DATA 1.26E-12 .2.19E-C7 2.94E-14 NIC4

147 9.83E-07 1.07E-Ob 6.41E-08 NO DATA b.2qE-07 4.65E-05 2.28F-05 W 187 1.50E-09 1.22c-O9 4.29E-IC NO DATA NO DATA 5.q2E-06 2.21F-05

.. P239 4.23E-08 3.99E-09 2.21E-09 NU DATA 1.25E-08 8.11E-06 1.65E-05 i4 4

1.109-49 O-.

TABLE E-9 PAGE 1 OF 3

- INHALATION DCSE FACTORS FOR CHILD

(MREM PER PCI INHALED)

NUCLIUE BONE LIVER T.BOCY THYROID KIDNEY LUNG GI-LLI

11 3 NO DATA 3.04E-97 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 C 14 9.70E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 NA.24 4..35E-06 4.35:-06 4.35E-06 4.35E-06 4.35E-C6 4.35E-06 4.35E-06 P 32. 7.04E-04 3.CgE-05 2.671-05 NO DATA NO DATA Nn DATA 1.14E-05 CR 51. NO DATA NO DATA 4.17E-08 2.31F-O8 6.57E-09 4.59E-06., 2.93E-07 MN 54 '4O DATA 1.16:-05 2.57E-Ob NO DATA 2.71E-06 4.26F-04 6.19F-06 MN 56 NO DATA 4.48E-10 8.43E-11 NO DATA 4.52E-10 3.55E-06 3.33E-05 FE 55 1.28E-05 6.D0E-0o 2.10E-06 NO DATA NO DATA 3.OOE-05 7.75E-07 FE 59 5.59E-06 9.C4E-06 4.51E-06 NO DATA NO DATA 3.43E-04 1.91E-05 CO 58 NO DATA 4.79E-O7 8.55E-07 NO DATA NO DATA 2.99E-04 9.29E-06 CO 60 NO DATA 3.55E-06 6.12E-06 Nil DATA NO DATA 1.91E-03 2.60E-05 NI 63 2.22E-04 1.25E-05 7.56E-06 NO DATA NO DATA 7.43E-05 I.71E-06

4I 65 8.08E-10 7.99E-11 4.44E-11 Nfl DATA NU DATA 2.21E-06 2.27E-05 CU 64 NO DATA 5.39E-10 2.90E-10 NO DATA 1.63E-09 2.59E-06 q.92E-06 ZN 65 1.15E-05 3.06E-05 1.90E-05 NO DATA 1.93E-05 2.69E-04 4.41E-06 ZN 69 1.81E-[1 2.61E-11 2.41E-12 NO DATA 1.58E-11 3.84E-07 2.75F-06 MR 83 NO DATA NO DATA 1.28E-07 NO DATA NO DATA NO DATA LT E-24 aR 84 NO DATA NO DATA 1.48E-07 NO DATA NO DATA NO DATA LT E-24

!R 85 NO DATA NO DATA 6.84E-09 NO DATA. NO DATA NO DATA LT E-24 R( 86 NO DATA 5.36E-05 3.09E-O5 NO DATA NO DATA NO DATA 2.16E-06 RE' 88 NO DATA 1.52E-0T 9.90E-08 NO DATA NO DATA NO DATA 4.66E-09 RB 89 NO DATA 9.33E-08 7.8.E-O8 NO DATA NO DATA- NO DATA 5.11E-1O

SR 89 1.62E-04 NO DATA 4.66E-06 NO DATA NO DATA 5.83E-04 4.52E-05 SR 9O 2.73E-02 NO DATA 1.74E-03 NO DATA NO DATA 3.99E-03 9.28E-05 SR 9L 3.28E-08 NO DATA 1.24E-09 NO DATA NO DATA 1.44E-05 4.701-05 SR 92 3.54E-09 NO DATA 1.42E-10 NO DATA NO DATA 6.49[-06 6.55E-05 Y 90 1.1IE-06 NO DATA 2.99E-08 NO DATA NO DATA 7.07E-05 7.24E-05 Y 91P 1.37E-1O NO DATA 4.98E-12. NO DATA NO DATA 7.60F-O0 4.64E-07 Y 91 2.47E-04 NO DATA 6.59E-06 NO DATA NO DATA 7.10E-04 4.97E-05 Y 92 5.50E-09 NO DATA 1.57E-1O NO DATA NO DATA 6.46E-C6 6.46E-05

1.109-50

TABLL E-9, CONTOD

PASE 2 OF 3 INHALATION DLSE FACTORS FOR CHILD

(MREýM PER PCI INHALED)

I DUCLIE BU.E LIVER T. LsOGY THYROID KIDNEY LUNG GI-LLI

Y 93 5.04E-08 NO DATA 1.38E-09 NO DATA NO DATA 2.0IE-05 1.05E-04 ZaR 95 5.13E-05 1.13E-05 1.OOE-05 NO DATA 1.61E-05 6.03E-04 1.65E-05 IR 97 5.07E-08 7.34E-09 4.32E-09 NO DATA 1.05E-08 3.06E-05 9.49E-05

"NA 95 6.35E-06 2.48E-06 1.77E-06 NO DATA 2.33E-06 1.66E-04 l.OOE-05 IMO99 NO DATA 4.66E-08 1.15E-08 NO DATA 1.06E-07 3.66E-05 3.42E-05 TC 99' 4.81E-13 9.41E-.13 1.56E-11 NO DATA 1.37E-11 2.57E-C7 1..0E-06 TC10 2.19E-14 2.30E-14t 2.91E-13 NO DATA 3.92E-13 1.5RE-07 4.41F-09 PU103 7.55E-07 NO DATA 2.90E-07 NO DATA 1.90E-06 1.79E-04 1.21E-05 RUIO5 4.13E-1O NO DATA 1.5OE-10 NO DATA 3.63E-10 4.30E-06 2.69E-05 RU106 3.68E-05 NO DATA 4.57E-06 NO DATA 4.97E-05 3.87E-03 1.16E-04 AGILOM 4.56E-06 3.08E-06 2.47E-06 NO DATA 5.74[-06 1.48E-03 2.TIE-05 TEI25M 1.82E-06 6.29E-07 2.47E-07 5.20E-07 NO DATA 1.29E-04 9.13E-06 TE127M 6.72E-06 2.31E-06 8.loE-07 1.64E-06 1.72E-05 4.OOE-04 1.93E-05 TE127 7.49E-10 2.57E-10 1.65E-10 5.30E-iO 1.91E-09 2.71F-06 1.52E-05

1E129M 5.19E-C6 1.85E-06 8.22E-07 t.71E-06 1.36E-05 4.76E-04 4.91E-05 TE129 2.b4E-11 9.45E-12 6.44[-12 1.93E-11 6.94L-1i 7.94E-07 6.89E-06 TE131m 3.63E-08 1.60E-08 1.37E-08 2.64E-08 1.08E-07 5.56E-05 8.32F-05 rE131 5.87E-12 2.28E-12 1.78E-12 4.59E-12 1.59s-Il 5.55E-07 3.60E-07 TE132 1.30E-07 7.36E-08 7.12E-08 8.58E-08 4.79E-07 1.02E-04 3.72E-05

1 .1.30 2.21E-06 4.43E-06 2.28E-06 4.99E-04 6.61L-06 NO DATA 1.38E-06

1 131 1.30E-05 1.30E-05 7.37F-Ob 4.39E-03 2.13E-05 NO DATA 7.68E-07

1 132 5.72E-07 1.10E-06 5.01E-07 5.23E-05 1.69E-06 NO DATA 8.65E-07

1 133 4.48E-06 5.497-06 2-.08E-06 1.04E-03 9.13E-06 NO DATA 1.48E-06

1 134 3.17E-07 5.84E-07 2.69E-07 1.37E-05 8.92E-07 NO DATA 2.58E-07

[35 1.33E-06 2.36E-06 1.12E-06 2.14[-04 3.62E-06 NO DATA 1.20E-06 CS14 1. 76E-04 2.742-04 6.07E-05 AD DATA 8.93E-05 3.27E-05 1.04E-06 CS136 1.76E-05 4.62E-05 3.14E-05 NO DATA 2.58E-05 3.93E-06 1.13E-06 CS137 2.45E-04 2.23E-04 3.47F-05 NO DATA 7.63E-05 2.81E-05 9.78E-07 CS138 1.71E-07 2.27E-07 1.50E-07 NO DATA 1.68E-07 1.84E-08 7.29E-08

, A139 4.98E-10 2.66F-13 1.45E-1i NO DATA 2.33E-13 1.56E-06 1.56E-05 l0a,

TABLE E-9, CONTIC

PAGE 3 OF 3 INHALATION DOSE FACTORS FOR CHILD

(MREM PER PCI INHALED)

NUCLIDE BONE LIVER T.RODY THYROID KIDNEY LUNG GI-LLI

GA140 2.00E-05 1.75E-08 I.I7E-06 NO DATA 5.T7E-09 4.71E-O4 2.75E-05 BA[41 5.291E-11 2.95E-14 1.72F-12 NO DATA 2.56E-14 7.89E-07 7.44E-08 BA142 1.35E-11 9.73E-15 7.54E-13 NO DATA 7.87E-15 4.44E-07 7.41F-10

LAI40 I.74E-07 6.OBF-08 2.04E-08 NO DATA NO DATA 4.94E-05 6.IOE-05 LAI42 3.50E-10 1.I1E-IO 3.49E-LI Nfl DATA NO DATA 2.35F-06 2.05E-05 CEI14 1.06E-05 5.28E-06 7.83E-07 NO DATA 2.31E-06 1.47E-04 1.53E-05 CE143 9.89E-o8 5.37L-08 7.77E-09 NO DATA 2.26E-OB 3.I2E-05 3.44E-05 CE144 I.B3E-03 5.72E-04 9.77E-05 NO DATA 3.17E-04 3.23E-03 1.05E-04 PR143 4.99E-06 1.50E-06 2.47E-0.7 NO DATA 8.1IE-07 1.17E-04 2.63E-05 PR144 1.b6E-11 4.99E-12 8.10E-13 NO DATA 2.64E-12 4.23E-07 5.32E-08 ND147 2.q211-06 2.36E-06 1.84F-07 NO DATA 1.30E-06 8.87L-05 2.22F-05 W 187 4.*dE-09 2.61[-09 1.17F-09 NO DATA NC DATA 1.1LF-05 2.46E-05 NP239 1.26E-07 9.04-09 6.35E-09 NO DATA 2.63E-OB 1.5TE-05 1.73E-05

1.109-52

TA13LE E-10

PAGE 1 OF 3 INHALATION DOSE FACTORS FOR INFANT

(MREM PER PCI INHALED)

NUCLIDE BONE LIVER T.3ODY THYROID KIDNEY LUNG GI-LLI

H 3 NO DATA 4.62E-07 4.62E-07 4.62F-67 4.62E-07 4.62E-07 4.62E-07 C 14 1.89E-05 3.79C-06 3.79E-06 3.79P-06 3.79E-06 3.79E-06 3.79E-06 NA 24 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 P 32 1.45E-03 8.03E-05 5.53E-05 NO DATA NO DATA NO DATA 1.15E-05 CR 51 NO DATA NO DATA 6.31E-08 4.11E-08 9.45E-09 9.17E-06 2.55E-07 MN 54 NO DATA 1.81E-05 3.56[-06 NO DATA 3.56E-06 7.14E-04 5.04E-06 MN 56 NO DATA 1.10E-09 1.58E-10 NO DATA 7.86E-10 P.95E-06 5.12E-05 FE 55 1.41E-05 8.39L-Ob 2.38E-06 NO DATA NO DATA ' 6.21E-05 7.82E-07 FE 59 9.69E-06 1.b6E-05 6.77E-06 NO DATA NO DATA 7.25E-04 1.77E-05 CO 58 NO DATA 8.71E-07 1.30E-06 NO DATA NO DATA 5.55E-04 7.95F-06 CO 60 NO DATA 5.73E-06 8.41E-06 NO DATA NO DATA 3.22E-03 2.28E-05 NI 61 2.42E-04 1.46E-05 8.29E-06 NO DATA- NO DATA 1.49E-04 1.73E-06 NI 65 1.71E-09 2.303-10 8.79E-11 NO DATA NO DATA 5.80E-06 3.58E-05 CU-64 NO DATA 1.34E-09 5.53E-10 NO DATA 2.84E-09 6.64E-06 1.07E-05 ZN 65 1.38E-05 4.,,7F-05 2.22E-05 NO DATA 2..32E-05 4.62E-04 3.67E-05

(01 7N 69 3.P5E-11 6.91g-ll 5.13E-12 NO DATA 2.87E-I1 1.05E-06 9.44E-06 RR 83' NO DATA NO DATA 2.72E-07 NO DATA NO DATA NO DATA LT F-24 HR 84 NO DATA NO DATA 2.86E-07 NO DATA NO DATA NO DATA LT E-24 RR 8> ýNO DATA NO DATA 1.46E-08 NO DATA NC DATA NO DATA LT E-24 IB 8b NO DATA 1.36E-04 6.30E-05 NO DATA NO DATA NO DATA - 2.17E-06

'ýB 88 N(l UATA 3.98F-07 2.0DE-O7 NO DATA NO DATA NO DATA 2.42E-07 RB 89 NO DATA 2.29E-07 1.47E-07 NO DATA NO DATA NO DATA 4.87E-08 SR 89 2.84E-04 NO DATA 8.15E-06 NO DATA NO DATA 1.45E-03 4.57E-05 SR 90 2.92E-02 NO DATA 1.85F-03 NO DATA NC DATA 8.03E-03 9.3b6-05 SR 91 6.83E-O NO DATA 2.47E-09 NO DATA NO DATA 3.76E-05 5.24E-05 SR 92 7.50E-09 NO DATA 2.79E-10 NO DATA NO DATA 1.70E-05 1.00E-04 Y 90 2.15L-06 NO DATA 6.30E-08 NO DATA NO DATA 1.92F-04 7.43E-05

Y 91, 2.AIE-10 NO DATA , 9.qOE-12 NO DATA NO DATA 1.99E-06 1.68E-06 Y 91 '.?OE-04 NO DATA 1.12E-05 NO DATA NO DATA 1.75E-03 5.02E-05 Y 92 1.L7E-08 NO DATA 3.29E-10 NO DATA NO DATA 1.75E-05 9.04E-05

1.109-53

TABLE E-1Ot CONTID

PAGE 2 OF 3 INHALATION DOSE FACTORS FOR INFANT

(MREM PER PCI INHALED)

NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI

Y 93 1.07E-07 NO DATA 2.91E-09 NO DATA NO DATA 5.46E-05 1.19E-04 ZR 95 8.24E-05 1.99E-05 1.45E-05 NO DATA 2.22E-05 1.25E-03 1.55E-05 ZR 97 1.07E-07 1.83E-08 8.36E-09 NO DATA 1.85E-08 7.88E-05 1.0OE-04ý

NB 95 1.12E--05 4.59E-06 2.70E-06 NO DATA 3.37E-06 3.42E-04 9.05E-06 Mo 99 NO DATA 1.18-07 2.31E-08 NO DATA I1R9E-07 9.63E-05 3.48E-05 TC 99M 9.98E-13 2.06E-12 2.66E-11 NO DATA 2.22E-11 5.79E-07 1.45E-06 TCIOI 4.65E-14 .5.98E-14 5.80E-13 NO DATA 6.99E-13 4.17E-07 6.03E-07

'RUI03 1.44E-06 NO DATA 4.85E-07 NO DATA 3.03E-06 3.94E-04 1.15E-05 RUI05 8.74E-10 NO'DATA '2.93E-10 NO DATA 6.42E-10 1.12E-05 3.46E-05 RU106 6.20E-05 NO DATA 7.7.7E-06 NO DATA 7.61E-05 8.26E-03 1.17E-04 AGLIOM 7.13E-06. 5.16E-06 3.57E-06 NO DATA 7.80E-06' 2.62E-03 2.36E-05 TE125M 3.40E-06 1.42E-06 4.70E-07 1.16E-06 NO DATA 3.19E-04 9.22E-06 TE127M 1.19E-05 4.93E-06 I1.4BE-D6 3.48E-06 2.68E-05 9.37E-04 1.95E-05 TE12T 1.59E-09 6.81E-10 3.49E-10 1.32E-09 3.47E-09 7.39E-06 1.74E-05 TE129M I.OIE-05 4.35E-06 1.59E-06 3.91E-06 2.27E-05 1.20E-03 4.93E-05 TE129 5.63E-11 2.48E-1I 1.34E-11 4.82E-11 1.25E-10 2.14E-06 1.88E-05 TE131M 7.62E-08 3.93E-08 2.59E-08 6.38E-08 1.89E-07 1.42E-04 8.51E-05 TE131 1.24E-11 5.87E-12 3.57E-12 1.13E-l 2.85E-11 1.47E-06 5.87E-06 TE132 2.66E-07 1.69E-07 1.26E-07 1.99E-07 7.39E-07 2.43E-04 3.15E-05

1 130 4.54E-06 9.91E-06 3.98E-06 1.14E-03 1.09E-05 NO DATA 1.42E-06

.1 131 2.71E-05 3.17E-05 1.40E-05 1.06E-02 3.70E-05 NO DATA 7.56E-07

1 132 1.21E-06 2.53E-06 8.99E-07 1.21E-04 2.82E-06 NO DATA 1.36E-06

1 133 9.46E-06 1.37E-05 4.OE-06 2.54E-03 1.60E-05 NO DATA 1.54E-06

1 134 6.58E-07 1.34E-06 4.75E-07 3.18E-05 1.49E-06 NO DATA 9.21E-07 I 135 2.76E-06 5.43E-06 1.98E-06 4.97E-04 6.05E-06 NO DATA 1.31E-06 CS134 2.83E-04 5.02E-04 5.32E-05 NO DATA 1.36E-04 5.69E-05 9.53E-07 CS136 3.45E-05 9.61E-05 3.7BE-05 NO DATA 4.03E-05 8.40E-06 1.02E-06 CS137 3.92E-04 4.37F-04 3.25E-05 NO DATA 1.23E-04 5.09E-05 9,.53E-07 CS138 3.61E-07 5.58E-07 12.84E-OT NO DATA 2.93E-07 4.67E-08 6.26E-07'

BA139 1.06E-09 7.03E-13 3.07E-11 NO DATA 4.23E-13 4.25E-06 3.64E-05

1.109-54

TABLE E-1O, CONT'D

PAGE 3 OF 3 INHALATION DOSE FACTORS FOR INFANT

(MREM PER PCI INHALED)

NuCLIOE BONE LIVER F.BODY THYROID KIDNEY LUNG GI-LLI

BA140 4.OOE-05 4.OOE-08 2.07E-06 NO DATA 9.59E-09 1.14E-03 2.74E-05 BAl4L L.12E-1O 7.70r-14 3.55E-12 NO DATA 4.64E-14 2.12E-06 3.39E-06 BA142 2.84E-11 2.36E-14 1.40E-12 NO DATA 1.36E-14 1.I1E-06 4.95E-07 LAI40 3.61E-07 1.43E-07 3.68E-08 NO DATA NO DATA 1.20E-04 6.06E-05 LA142 7.36E-10 2.69E-1O 6.46E-II NO DATA NO DATA 5.87E-06 4.25E-05 CE141 1.98E-05 1.19E-05 1.42E-06 NO DATA 3.75E-06 3.69E-04 1.54E-05 CE143 2.09E-07 I.18E-07 I.58E-08 NO DATA 4.03E-08 8.30E-05 3.55E-05 CE144 2.28E-03 8.05E-04 1.26E-04 NO DATA 3.84E-04 7.03E-03 1.06E-04 PR143 1.OOE-05 3.74E-06 4.99E-07 NO DATA 1.41E-06 3.09E-04 2.66E-05 PR144 3.42E-1I 1.32E-11 1.72E-12 NO DATA 4.80E-12 1.15E-06 3.06E-06 NDI47 5.b7E-O6 5.81F-06 3.57E-07 NO DATA 2.25E-06 2.30E-04 2.23E-05 W 187 9.26E-Og 6.44E-09 2.23E-09 NO DATA NO DATA 2.83E-05 2.54E-05 NP2.39 2.65E-07 2.37E-08 1.34E-08 NO DATA 4.73E-08 4.25E-05 1.78E-05

1.109-55

TABLE E-1i PAGE 1 OF 3 INGESTION DOUSE FACTORS FOR ADULTS

( M REM PER PCI INGESTED)

NUCLILE BONE LIVER T.BOGY THYROID KIDNEY LUNG GI-LLI

-11 3 NO DATA I.05E-07 I.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-0

C 14 2.84E-06 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-0

NA 24 1.70E-06 1.70E-06 l.TOE-06 1.70E-06 1.70E-06 1.70E-06 1.70E-O

P 32 .1.93E-04 1.20E-05 7.46E-06 NO DATA NC DATA NO DATA 2.17E-0!

CR 51 NO DATA NO DATA 2.6bE-09 1.59E-09 5.86E-I0 3.53E-09. 6.69E-0 .

MN 54 NO UATA 4.57E-06 8.72E-07 NO DATA 1.36E-06 NO DATA 1.40E-0

MN 56 NO DATA 1.15r-07 2.04E-08 NO DATA 1.46E-07 NO DATA 3.67F-06 FE 55 2.75E-06 1.90F-O0 4.43E-07 NO DATA NO DATA 1.06E-06 1.09E-06 FE 59 4.34E-06 1.02E-05 3.91E-06 NO DATA NO DATA 2.85E-06 3.40E-05 CC 58 NO DATA 7.45E-07 1.67E-06 NO DATA NO DATA NO DATA i.51F-05 CC 60 NO DATA 2.14F-06 4'.72 -0 6 NO DATA NO DATA NO DATA 4.02E-05 ilI 63 1.30E-C4 9.OIE-Ob 4.36E-06 NO DATA NO DATA NO DATA I.88E-06 NI 65 5.28E-07 6.86E-08 3.13E-08 NO DATA NO DATA NO DATA 1.7lE-06 CU 64 NO DATA 8.33E-08 3.91E-08 NO DATA 2.10E-07 NO DATA 7.10E-06 ZN 65 4.847E-06 1649-65 0.gE-06 NO DATA 1.03E-05 NO DATA 9.70E-06 ZN 69 1.03E-08 1.97E-08 1.37E-09 NO DATA 1.28E-08 NO DATA 2.96E-09 BR 83 NO DATA NO DATA 4.02E-08 NO DATA NO DATA NO DATA 5.79E-08 BR 84 NO DATA NO DATA 5.2IE-08 NO DATA NO DATA NO DATA 4.09E-13 BR 85 NO DATA NO DATA 2.14E-09 NO DATA NC DATA NO DATA LT E-24

'R8 86 NO DATA 2.1E-05 9.83E-06 NO DATA NO DATA NO DATA 4.16E-06 RB 88 NO DATA 6.05E-08 3.21E-08 NO DATA NO DATA NO DATA 8.36E-1.9 RB 89 NO DATA 4.01E-08 2.82E-08 NO DATA NO DATA NO DATA 2.33E-21 SR 89 3.08E-04 NO DATA 8.84E-06 NO DATA NO DATA NO DATA 4.94E-05 SR 90 7.58E-03 NO DATA .1.8bE-03 NO DATA NO DATA NO DATA 2.19E-04 SR 91 5.6TE-06 NO DATA 2.29E-07 NO DATA NC DATA NO DATA 2.70E-05 SR 92 2.15E-06 NO DATA 9.30E-08 NO DATA NO DATA NO DATA 4.26E-05 Y 90 9.62E-09 NO DATA 2.58E-1O NO DATA NO DATA NO DATA 1.02E-04 Y 91M 9.09E-11 NO DATA 3.52E-12 NO DATA NO DATA NO DATA 2.67E-IO

Y 91 1.41E-07 NO DATA 3.77E-09 NO DATA NO DATA NO DATA 7.76E-05 Y 92 8.45E-10 NO DATA 2.47E-1I NO DATA NO DATA NO DATA 1.48E-05

- - - - -- - - -- -- -- -- - -- -- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -- .5:

1.109-56

TAB3LE E-11, C(JNT'D

PArE 2 or 3 INGESFION DOSE FACTOOS FOR ADULIS

(MREM PER PCI INGESTFD)

NUCLICE BONE LIVER T.BODY THYROIC KIDNEY LUNG GI-LLI

Y 93 2.68E-C9 NO DATA 7.40E-11 NO DATA NO DATA NO DATA 8.50F-05 ZR 95 3.04E-OR 9.75E-09 6.60E-09 NO DATA 1.53E-08 NO DATA 3.09E-05 ZR 97 1.68E-09 3.39=-10 1.55E-10 NO DATA 5.12E-10 NO DATA 1.05E-04 N8 95 6.22E-09 3.46E-09 1.86E-09 NO DATA 3.42E-0q NO DATA 2.10E-05 MO 99 NO DATA 4.31E-06 8.20E-07 NO DATA 9.76E-06 NO DATA 9.99E-06 TC 99PI 2.47E-10 6.98=-10 8.89E-09 NO DATA 1.06E-08 3.42E-10 4.13E-07 TCioi 2.54E-10 3.66E-IC 3.59E-09 NO DATA 6.59E-09 1.87E-10 1.10E-21 RUIO3 1.85E-07 NO DATA 7.97E-08 NO DATA 7.06E-07 NO DATA 2.16E-05 RUIO!I 1.54E-08 NU DATA 6.03L-09 NO DATA 1.99E-07 NO DATA 9.42E-06 WU106 2.75F-06 NO DATA 3.48E-07 JO DATA 5.31E-06 NO DATA 1.78E-04 AG11OM 1.60E-07 1.48F-07 8.79E-08 NO DATA 2.91C-07 NO DATA 6.04E-05 T2125M 2.69E-06 9.712-07 3.59E-07 8.06F-07 1.09E-05 NO DATA 1.07E-05 TE127M 6.77E-06 2.42C-06 8.25[-07 1.73E-06 2.75E-05 NO DATA 2.27E-05 TE127 1.IE-07 3.95E-08 2.38E-O8 8.15E-06 4.48E-07 NO DATA 8.68E-06

1TE129M 1.15E-05 4.29c-0o 1.82E-06 3.95E-06 4.80E-05 NO DATA 5.792-05 rE129 3.14E-08 I.18E-O8 7.c*E-O9 2.41E-08 1.32E-07 NO DATA 2.37E-08 TE131t 1.73E-06 8.46'-07 7.05E-07 1.34E-06 8.57E-06 NO DATA 8.40E-05 T1131 1.97E-08 8.23E-09 6.22E-09 1.62E-08 .. 63L-08 NO DATA 2.79E-C9

.. r2132 2.52E-06 1.b3E-O6i 1.5.-E-06 1.8E-C6 1.57E-05 NO DATA T.7.12E-05

1 130 7.56E-07 2.23E-06 8.80E-07 1.89f:-04 3.48E-06 NO DATA ' 1.92E-06 I 131 4.16E-06 5.95c-06 3.41E-06 1.95F-C3 1.02E-05 NO DATA 1.57E-06

1 132 2.03E-07 5.43F-07 1.90E-07 1.90E-05 8.65L-07 NO DATA 1.02E-07

[ 133 1.42E-06 2.'t7E-06 7.53E-07 3.63E-04 4.31E-06 NO DATA 2.22E-06

1 134 1.06E-07 2.881-07 1.03E-07 4.99E-06 4.58E-07 NO DATA 2.51E-10

1 1-35 4.43E-07 1.16C-06 4.23C-07 7.65E-05 1.86E-C6 NO DATA 1.31E-06 CS134 6.22E-05 1.48E-04 1.21E-04 NO DATA 4.79L-05 1.59E-05 2.59E-06 v CS136 6.51E-06 2.571-05 1.85E-05 NO DATA 1.43E-05 1.96E-06 2.92E-06 CS137 7.97E-05 1.G9E-04 7.14E-05 NO DATA 3.70L-05 1.23E-05 2.11E-06 CS138 5.52E-OR 1.C9E-07 5.40E-08 NO DATA 8.01E-08 7.91E-09 4.65E-13 BA139 9.70E-08 6.91E-I 2.84E-09 NO DATA 6.46E-11 i.92E-11 1.72E-07

1.109-57

IL

TABLF E-,I, CONT'D

PACE 3 OF 3 INGESTION DOSE FACTORS FOR ADULTS

AMREM PLR PCI INGESTED)

NUCL I CE BONE LIVER T. (3DY THYROID KIDNEY LUNG GI-LLI

-3A140 2.03[-05 2.55E-08 I.33E-06 NO DATA 8.67E-09 1.46E-08 4.18E-05 r.A141 4.TIE-08 3.56E-1I 1.59E-09 NO DATA 3.31E-l1 2.02E-11 2.22E-17 OA142 2.13E-08 2.19E-11 1.34E-09 .40 DATA 1.35E-1I 1.24E-11 3.OOE-26 LA140 2.5OE-09 1.26>-09 3.33E-10 NO DATA NO DATA NO DATA 9.25E-05 LA142 1.28E-10 5.B2E--1 1.45E-l1 NO DATA NC DATA NO DATA 4.25E-07

0E141 9..36E-09 6.33E-09 7.1[E-lC NO DATA 2.94E-09 NO DATA 2.42E-05

.E143 1.65E-09 1.22F-06 1.35E-1O NO DATA 5.37E-10 NO DATA 4.56E-05

'CE144 4.A8E-07 2.04E-07 2.62E-08 NO DATA 1.21E-07 NO DATA 1.65E-04 PR143 9.20E-O 3.69-!09 4.56E-10 NO DATA 2.13E-09 NO DATA 4.03E-05 P1I44 3.OIE-11 1.25E-11 1.53E-12 NO DATA 7.05E-12 NO DATA 4.33E-18 N0147 6.29E-C9 7.Z7E-09 4.35E-I0 NO DATA 4.25E-09 NO DATA 3.49E-05 k 19.7 1.03E-07 8.61E-08 3.OE-08 NO DATA NO DATA Nn DATA 2.82E-05 NP239 1.19E-09 1.1,7E-1O 6.45E-1I NO DATA 3.65E-10 NO DATA 2.40E-05

1.109-58

TABLE E-12 PAGE 1 OF 3 INGESTION-DOSE FACTORS FOR TEENASER

(MREM PER PCI INGESTED)

NUCLICE BONE LIVER T.HnUY THYROID KIDNEY LUNG GI-LLI

II 3 NO DATA 1.06E-07 1.OE-07 1.06[-07 1.06E-07 L.06E-07 1.06E-O7 C 14 4.06E-06 e.12E-07 8.12E-O7 8.12F-07 8.12E-07 H.12E-07 8.12F-07 NA 24 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 P 32 2.76E-04 1.71E-05 1.07E-05 NO DATA NO DATA NO DATA 2.32E-05 CR 51 NU DATA NO DATA 3.6OE-09 2.OOE-09 7.99E-10 5.14E-09 6.05E-07 MN 54 NO DATA 5.90E-Ob 1.17E-06 NO DATA 1.76E-06 NO DATA 1.21E-05 MN 56 NO DATA 1.58E-07 2.8LE-08 NO DATA 2..OE-07- NO DATA 1.04E-05 FE 55 3.7BE-06 2.68F-06 6.25E-07 NO DATA NO DATA 1.70E-06 1.16E-06 FE 59 5.87E-06 .iJE-05 5.29E-06 NO DATA NO DATA 4.32E-06 3.24E-05

'O 58 NO DATA 9.72E-07 2.24E-06 ND DATA NO DATA NO DATA 1.34E-05 CO 60 NO DATA 2.81E-06 6.33E-06 NO DATA NO.DATA NO DATA 3.66E-05

  • ý4I63 1.77E-04 1.25C-05 b.OOE-06 NO DATA NO DATA NO DATA 1.99E-06

14I 65 7.49E-07 .9.57E-08 4.36E-08 NO DATA NO.DATA NO DATA 5.19E-06 CU 64 NO DATA 1.15E-07 5.41E-08 NO DATA 2.91E-07 NO DATA 8.92E-06 ZN 65 5.76E-06 2.COE-C5. 9.33E-06 NO DATA 1.28E-05 NO DATA 8.47E-06 LN69 1.47E-08 2.6OE-08 1.96E-09 NO DATA I.R3E-O8 NO DATA 5.16E-08

  • R 83 NO DATA NO DATA 5.74E-08 NO DATA NO DATA NO DATA LT E-24

.9R84 NO DATA N. DATA 7.22E-08 NO DAT3 NO DATA NO DATA LT E-24 bR 85 NO DATA NO DATA 3.05E-09 NO DATA NO DATA NO DATA LT E-24 RB 86 NO DATA 2.98E-05 1.40E-05 NO DATA NO DATA NO DATA 4.41E-06 RB 88 NO DATA 8.52E-08 4.54E-08 NO DATA NO DATA NO DATA 7.30E-15 RB 89 NO DATA 5.50E-08 3.89E-08 NO DATA NO DATA NO DATA 8.43F-17 SR 89 4.40E-04 NO DATA 1.26E-05 NO DATA NO DATA NO DATA 5.24E-O5 SR 90 8.30E-03 NO DATA 2.05E-03 NO DATA NO DATA NO DATA 2.33E-04 SR

--- 8.-- E-O6 ND-DATA 3.21E-07 NO DATA ND DATA ND DATA 3.-6E-05 SR 92 3.05E-06 NO DATA 3.30E-07 NO DATA NO DATA NO DATA 7.77E-05 Y 90 1.37E-08 NO DATA 3.69E-1O NO DATA NO DATA NO DATA 1.13E-04 Y 91M 1.29E-10 NO DATA 4.93E-12 NO DATA NO DATA NO DATA 6.09E-09 Y 91 2.0IE-07 NO DATA 5.31E-09 NO DATA NO DATA NO DATA 8.24E-05 Y 92 1.21E-09 NO DATA 3.50E-11 NO DATA NO DATA NO DATA 3.32E-05

1.109-59

TAtLF E-12, CONTDO

PASE 2 OF 3 INGESTION DOSE FACTORS FOR TEENAGER

(MREM PFR PCI INGESTED)

NUCLI'2E BONE LIVER T.tODY THYROID KIDNEY LUNG GI-LLI

Y 93 3.83E-C9 NO DATA 1.05E-10 NO DATA NC DATA NO DATA 1.17E-04 ZR 95 4.12E-08 1.302-08 8.91+E-09 NO DATA 1.91E-08 NO DATA 3.OOE-05

7R 97 2.37E-09 4.69E-1O 2.16E-10 ND DATA 7.11E-10 NO DATA 1.27E-04

14 P 95 8.22E-09 4.5bE-09 2.51E-09 NO DATA 4.42E-Oq NO DATA 1.95F-05 MO 99 NO DATA 6.03E-06 1.15F-06 NO DATA 1.38E-05 NO DATA 1.08E-05 TC 99M 3.32E-10 9.26E-10 L.20E-08 NO DATA 1.38E-08 5.14E-1O 6.08E-07 TCIDI 3.60E-10 5.127-10 5.03E-09 NO DATA q.26E-09 3.12E-10 8.75E-17 RU103 2.55E-07 NO DATA 1.09E-07 NO DATA 8.99E-07 NO DATA 2.13E-05 RU105 2.18E-08 NO UATA 8.46E-09 40 DATA 2.75E-07 NO DATA 1.76E-05 RI)0ob 3.92E-06 NO DATA 4.94E-07 NO DATA 7.56E-06 NO DATA 1.88E-04 AGIIOM 2.05E-07 1.94E-07 1.18E-O7 NO DATA 3.70E-07 NO DATA 5.45E-05 TE125m 3.33E-06 1.382-06 5.12E-07 1.07E-06 NO DATA NO DATA 1.13E-05 TF127M 9.67E-06 3.4iE-Ob 1.15E-06 2.30E-06 3.92L-05 NO DATA 2.41E-05 FE127 1.58E-07 5.60E-08 3.40E-08 1.09F-O7 6.40E-07 NO DATOS 1.2ZE-05 TE129M 1.63E-05 6.C5-O6 2.58E-06 5.2bE-06 6.82E-05 Nn DATA 6.12E-05

TEL29 4.48E-08 1.'b7F-08 I.,0)E-08 3.20E-08 1.88E-07 NO DATA 2.45F-07

! TEl31m 2.44E-06 1.17E-Ob 9.76E-07 1.76E-06 1.22E-05 NO DATA 9.39E-05 TF131 2.79E-08 I.L52-08 8.72E-09 2.15E-08 1.22E-07 NO DATA 2.29[-09

2E132 3.49E-06 2.21F-06 2.08E-06 2.33E-06 2.12E-05 NO DATA 7.ODE-05

1 130 1.03E-06 2.98E-06 1.19E-06 2.43E-04 4.59E-06 NO DATA Z.29E-06

1 131 5.85E-O 8.19C-06 4.40E-06 2.39E-03 1.41E-05 NO DATA 1.62E-06

1 132 2.79E-07 7.30E-07 2.62E-07 2.46E-05 1.15E-06 NO DATA 3.18E-07

133 2.01E-06 3.41L-06 1.04E-06 4.76E-04 5.98E-06 NO DATA 2.58E-06 I 134 1.46E-07 3.87E-07 1.39E-07 6.45E-06 6.10E-07 NO DATA 5.10E-09

1 135 6.10E-07 1.57E-06 5.82E-07 1.OIE-04 2.48E-06 NO DATA 1.74E-06 CS134 8.37E-05 1.97F-04 9.14E-05 NO DATA 6.26E-05 2.39E-05 2.45E-06 CS136 8.59E-06 3.38E-05 2.27E-05 NO DATA 1.84E-05 2.90E-06 2.72E-06 CS137 1.12E-04 1.49E-04 5.19E-05 NO DATA 5.07E-05 1.97E-05 2.12E-06 CS138 7.76E-08 1.49C-07 7.45E-08 NO DATA I.IOE-07 1.28F-08 6.76E-11

3A139 1.39E-07 9.78L-11 4.05E-09 NO DATA 9.22E-1i 6.74E-11 1.24E-06

1.109-60

TABLE E-12, CONT'D

PAGE 3 OF 3 I:AGESTION DOSE FACTORS FOR TEFNAGER

(MREM PER PCT INGESTED)

WUCLTLE BONE LIVER T.60OY THYROID KIDNEY LUNG GI-LLI

64140 2.84E-05 3.48E-09 1.83E-06 NO DATA 1.18E-08 2.34E-08 4.38E-05 RAI41 6.71E.-OR 5.('1E-11 2.24E-09 NO DATA 4.65E-11 3.43E-11 1.43E-13

'A142 2.99E-08 2.39E-11 1.84E-09 40 DATA 2.53E-11 1.9qE-11 9.18E-20

LA140 3.48E-09 1.71C-09 4.55E-10 NO DATA NC DATA NO DATA 9.82E-05 LA142 1.79E-10 7.95E-11 1.98E-11 NO DATA NO DATA NO DATA 2.42E-06 CE141 1.33E-O8 8.88'-09 1.02E-09 NO DATA 4.18E-09 NO D4.TA 2.54E-05 CE143 2.35E-09 1. 7 1E-0 6 1.91E-1O NO DATA 7.67E-10 NO DATA .5.14E-05 CF144 6.96E-07 2.88E-07 3.74E-68 NO DATA 1.72E-07 NO DATA 1.755-04 PR143 1.31E-08 5.23C-09 6.52E-10 NO DATA 3.n4E-O9 NO DATA 4.31E-05 PR144 4.30E-11 1.762-11 2.18E-12 NO DATA 1.01E-11 NO DATA 4.74E-14

qU147 9.38E-09 1.02F-08 6.11E-10 NO DATA 5.q99L-Oq Nn DATA 3.68E-05

187 1.46E-07 1.19F-07 4.11E-38 NO DATA NO DATA NO DATA 3.22E-05

'JP239 1.76E-Oq 1.66E-10 9.22E-11 ,,n DATA 5.21L-10 NO DATA 2.67E-05

1 .109-61

TABLE E-13 PAGE I OF 3 INGESTION DOSE FACTORS FOR CHILD

(MREM PER PCI INGESTED)

NUCLIDE BONE LIVER T.oOUY THYROID KIDNEY LUNG GI-LL!

II 3 NO DATA 2.03E-O7 2.01E-07 2.03E-07 2.03E-OT 2.03E-07 2.03E-07 C 14 1.21E-05 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 NA 24 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.BOE-06 5.80E-06 5.80E-06 P 32 8.25E-04 3.86C-05 3.IE--O5 40 DATA NO DATA NO DATA 2.28E-0.5 CR 51 NO DATA NO DATA 8.90E-09 4.94E-09 1.35E-09 9.02E-09 4.72E-07

4 MN 54 NO DATA 1.07E-05 2.85E-06 NO DATA 3.OD0-06 NO DATA 8.98E-06 MN 56 NO DATA 3.34E-OT 7.54E.-08 NO DATA 4.04E-O7 NO DATA 4.84E-05 I! FE-55 1.1SE-05 6.IOE-06 1.89E-06 NO DATA NO DATA 3.45E-06 1.13E-06 FE 59 1.65E-05 2.67E-05 1.33E-05 NO DATA NO DATA 7.74E-06 2.78E-05 CO 58 NO DATA 1.8OE-06 5.51E-06 NO DATA NO.DATA NO DATA 1.05E-05 CO 60 NO DATA 5.29E-06 1.56E-05 NO DATA NO DATA NO .DATA 2.93E-05 NI 63 5.38E-C4 2.88E-05 1.83E-05 NO DATA NO DATA NO DATA 1.94[-06 NI 65 2.22E-06 2.09F-07 1.22E-07 NO DATA NO DATA NO DATA 2.56E-05 CU 64 NO DATA 2.45E-07 1.48E-07 NO DATA 5.92E-07 NO DATA 1.15E-05 ZN 65 1.37E-05 3.o5E-0 2.27E-05 NO DATA 2.30E-05 NO DATA 6.41E-06 ZN 69 4.38E-O8 6.13E-08 5.85E-09 NO DATA 3.84E-08 NO DATA 3.99E-06 BR 83 NO DATA NO DATA 1.71E-07 NO DATA NO DATA NO DATA LT E-24

...

BR 84 NO DATA NO DATA 1.97E-07 NO DATA NO DATA NO DATA LT E-24

,i!RR -R 8-

85 - NO

NO DATA-

DATA NO - DATA

NO DATA -- 9.12E-09 NO

NO DATA

DATA-1-E-07 NO

NO DATA

DATA NO-

NO. DATA

DATA LT E-24 LT E-24 RB Bb" NO DATA 6.70E-05 4.12E-05 NO DATA NO DATA NO DATA 4.31F-06 RB 88 NO DATA 1.90E-07 1.32E-07 NO DATA NO DATA NO DATA 9.32E-09 RB 89 NO DATA 1.17E-07 1.04E-07 NO DATA NO DATA NO DATA 1.02E-09 SR.89 .1.32E-03 NO DATA 3.77E-05 NO DATA NO DATA NO DATA 5.11E-05 SR 90 1.70E-02 NO DATA 4.31E-03 NO DATA NO DATA NO DATA 2.29E-04 SR 91 2.40E-05 NO DATA 9.06E-OT NO DATA NO DATA NO DATA 5.30E-05 SR 92 9.03E-06 NO DATA 3.62E-07 NO DATA NO DATA NO DATA 1.TIE-04 Y 90 4.11E-08 NO DATA *I.IOE-09 NO DATA NO DATA NO DATA 1.17E-04 Y 91M 3.82E-10 NO DATA 1.39E-1I NO DATA NO DATA NO DATA 7.48E-07 Y 91 6.02E-07 NO DATA 1.61F-08 NO DATA NO DATA NO DATA 8.02E-05 Y 92 3.60E-09 NO DATA 1.03E-1O NO DATA NO DATA NO DATA 1.04E-04

1.109-62

TABLE E-13, CONr'D

PAGE 2 OF 3 INGESTION DOSE FACTORS FOR CHILO

(MREM PR PC[ INGESTED)

NUCLIDE BONE LIVER T.3OOY THYROID KIDNEY LUNG GI-LLI

Y 93 1.14C-CO NO DATA 3.13E-1O NO DATA NO DATA NO DATA 1.70E-04 ZR 95 1.1bE-07 2.,5E-08 2.27E-08 NO DATA '3.65E-O8 NO DATA 2.66E-05 ZR 97 6.99E-09 I.CIE-09 5.96E-1O NO DATA 1.45E-09 NO DATA 1.53E-04 NR 95 2.25E-D8 8.76E-09 6.26E-09 NO DATA 8.23E-09 NO DATA 1.62E-05 mO 99 NO DATA I.33F-05 3.29E-06 NO DATA 2.84E-05. NO DATA I.OE-O5 TC 99M 9.23E-1O 1.81E-09 3.00E-08 NO DATA 2.63E-08 °.19E-10 1.03E-06 rClO1 1.07E-09 1.12E-09 1.42E-08 NO DATA 1.91E-08 5.92E-1O 3.56E-09 RUI03 7.31E-07 NO DATA 2.81E-07 NO DATA 1.84E-06. NO DATA 1.89E-05

!'U1O5 6.45E-08 NO DATA 2.34E-08 NO DATA 5.67E-07 NO DATA 4.21E-05 RU106 1.17E-05 NO DATA 1.46E-06 NO DATA 1.58E-05 NO DATA 1.82E-04 AGIIOH 5.39E-07 3.64E-07 2.91E-07 NO DATA 6.78E-07 NO DATA 4.33E-05 TF125M 1.14E-05 3.09E-06 1.52E-06 3.20E-06 NO DATA NO DATA 1.10F-05 FE127M 2.89E-05 7.78F-06 3.43E-06 6.91E-06 8.24E-05 NO DATA 2.34E-05 TF127 4.71E-07 1.27F-07 1.01E-07 3.26E-07 1.34E-06 NO DATA 1.84E-05 rE1291A 4.87E-05 1.36E-05 7.56E-06 1.57E-05 1.43E-04 NO DATA 5.94E-05

1E129 1.34E-07 3.74E-08 3.18E-08 9.56E-08 3.92E-07 NO DATA 8.34E-06 TE131M 7.20E-06 2.49E-06 2.65E-06 5.12E-06 2.41E-05 NO DATA 1.01E-04 TE131 8.30E-08 2.53E-08 2.47E-08 6.35E-08 2.51E-07 NO DATA 4.36E-07 tE132 1.01E-05 4.47E-0o 5.40E-06 6.51E-06 4.15E-05 NO DATA 4.50E-05

1 130 2.92E-06 5.90E-06 3.04E-06 6.50E-04 8.82E-06 NO DATA 2.76E-06 I 131 1.72E-05 1.73C-05 9.83E-06 5.72E-03 2.84E-05 NO DATA 1.54E-06

1 132 8.00E-07 1.47E-06 6.76E-07 6.82E-05 2.25E-06 NO DATA 1.73E-06

1 133 5.92E-06 7.32E-06 2.77E-06 1.36E-03 1.22E-05 NO DATA 2.95E-06

1 134 4.19E-07 7.78E-07 3.58E-07 1.79E-05 1.19E-06 NO DATA 5.16E-07

1 135 1.75E-06 3.15E-06 1.49E-06 2.79E-04 4.83E-06 NO DATA .2.40E-06 CS134 2.34E-04 3.84E-04 8.10E-0S NO DATA 1.19E-04 4.27E-05 2.07E-06 CS136 2.35E-05 6.46E-05 4.18E-05 NO DATA 3.44E-05 5.13E-06 2.27E-06 CS137. 3.27E-04 3.13E-04 4.62E-05 NO DATA 1.02E-04 3.67E-05 1.96E-06 CS138 2.28E-07 3.17E-07 2.01E-07 NO DATA 2.23E-07 2.40E-08 1.46E-07

3A1,39 4.14E-07 2.21E-10 1.20E-08 NO DATA 1.93E-10 1.30E-10 2.39E-05

1.109-63

TABLE E-13, CONT'D

PASE 3 OF .3 INGESTION DOSE FACTORS FOR CHILD

(MREP PER PCI INGESTED)

NUCLIUE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI

RA140 8.31E-05 7.28E-08 4.85E-06 NO DATA 2.37L-08 4.34E-O8 4.21E-05

ýA!41 2.OOE-07 1.12C-1O 6.51E-09 NO DATA 9.69E-11 6.58E-1O 1.14E-O7

0A142 8.74E-08 6.29E-1i 4.88F-09 NO. DATA 5.09E-11 3.70E-11 1.14E-09 LA140 I.OIE-O8 3.53E-09 1.19E-09 AO.DATA NO DATA NO DATA 9.84E-05 LA142 5.24E-I0 1.67T-1O 5.23E-11 NO DATA NO DATA NO DATA 3.31E-05 CEI41 3.97E-08 1.98[-08 2.94E-09 NO DATA 8.68E-O0 NO DATA 2.47E-05 CE143 6.99E-09 3.79E-06 5.49E-1O NO DATA 1.59E-09 NO DATA 5.55E-05 CE144 2.08E-06 6.52E-O I.IIE-07 NO DATA 3.61E-07 NO DATA 1.70E-04 PR143 3.93E-08 1.18E-O8 1.95E-09 NO DATA 6.39E-09 NO DATA 4.24E-05 PR144 1.29E-10 3.99E-I1 6.49E-12 NO DATA 2.1lE-11 NO DATA 8.59E-08 N0147 2.79E-OR 2.26E-08 I.75E-09 'Nn DATA 1.24E-08 NO DATA 3.58E-05 W 187 4.29E-07 2.54F-07 1.14E-07 NO DATA NO DATA .:NO DATA 3.57E-05 NP239 5.25E-09 3.77E-10 2.65E-10 NO DATA 1.09E-09 NO DATA 2.79E-05

1.109-64

TABLE E-14 PAGE I OF 3 INGESTION DOSE FACTORS FOR INFANT

(MREM PER -PCI INGESTED)

NUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI

H 3 NO DATA 3.08E-07 3.08E-O7 3.0RE-07 3.08E-07 3.OBE-O7 3.08E-07 C 14 2.37E-05 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06F-06 5.06E-06 NA 24 1.O1E-05 1.OIE-05 1.01E-05 I.OIE-05 I.OIE-05 I.OIE-O5 1.O1E-05 P 32 1.70E-03 1.OOE-04 6.59E-05 NO DATA NO DATA NO DATA 2.30E-05 CR 51 NO DATA NO DATA 1.41E-08 9.20E-09 2.OIE-09 1.79E-08 4.l1E-07 MN 54 NO DATA 1.99E-05 4.51E-06 NO DATA 4.41E-06 NO DATA 7.31E-06 MN 56 NO DATA 8.18E-07 1.41E-O7 ND DATA 7.03E-07 NO DATA 7.43E-05 FE 55 1.39E-05 8.98E-06 2.40E-06 NO DATA NO DATA 4.39E-06 1.14E-06 FE 59 3.08E-05 5.38E-05 2.12E-05 NO DATA NO DATA 1.59E-05 2.57E-05 CO 58 NO DATA 3.60E-06 8.93E-06 NO DATA NO DATA NO DATA 8.97E-06 CC 60 NO DATA 1.08E-05 2.55E-05 NO DATA NO DATA NO DATA 2.57E-05 NI 63 6.34E-04 3.92E-05 2.20E-05 NO DATA NO DATA NO DATA 1.95E-06 NI 65 4.70E-06 5.32E-07 2.42E-07 NO DATA NO DATA NO DATA 4.05E-05 CU 64 NO DATA 6.09E-07 2.82E-07 NO DATA 1.03E-06 NO DATA 1.25E-05 ZN 65 1.34E-05 6.31E-05 2.91E-05 NO DATA 3.06E-05 NO DATA 5.33E-05 ZN 69 9.33E-08 1.b8E-07 1.25E-08 NO DATA 6.98E-08 NO DATA 1.37F-05 BR 83 NO DATA NO DATA 3.63E-07 NO DATA NO DATA NO DATA LT E-24 bR 84 NO DATA NO DATA 3.82E-07 NO DATA NO DATA NO DATA LT E-24 OR 85 NO DATA NO DATA 1.94E-08 NO DATA NO DATA NO DATA LT E-24 RB B6 NO DATA 1.70,E-04 8.40E-05 NO DATA NO DATA NO DATA 4.35E-06 RB 88 NO DATA 4.98E-O7 2.73E-07 NO DATA NO DATA NO DATA 4.85F-07 RD 89 NO DATA 2.86E-07 1.97E-07 NO DATA NO DATA NO DATA 9.74E-08 SR 89 2.51E-03 NO DATA 7.20E-05 NO DATA NO DATA NO DATA 5.16E-05 SR 90 1.85E-02 NO DATA 4.71E-03 NO DATA NO DATA NO DATA 2.31E-04.

SR 91 5.OOE-05 NO DATA 1.81E-06 NO DATA NO DATA NO DATA 5.92E-05 SR 92 1.92C-05 NO DATA 7.13E-07 NO DATA NO DATA NO DATA 2.07E-04 Y 90 8.69E-08 NO DATA 2.3iE-09 NO DATA NO DATA NO DATA 1.20E-04 Y 91M 8.10E-I1 NO DATA 2.76E-11 NO DATA NO DATA NO DATA 2.70E-06 Y 91 1.13E-06 NO DATA 3.01E-08 NO DATA NO DATA NO DATA 8.10E-05 Y 92 7.65E-09 NO DATA 2.15E-10 NO DATA NO DATA NO DATA 1.46E-04

1.109-65

TABLE E-14, CONI'D

PAGE 2 OF 3 INGESTION DOSE FACTORS FOR INFANT

(MREM PER PCI INGESTED)

NUCLIDE* BONE LIVER T.DODY THYROID KIDNEY LUNG GI-LLI

Y 93 2.43E-08 NO DATA 6.62E-10 NO DATA NO DATA NO DATA 1.92E-04 ZR 95 2.06E-07 5.02E-08 3.56E-08 NO DATA 5.41E-O8 NO DATA 2.50E-05 IR 97 1.48E-08 2.54E-09 1.1&E-09 NO DATA 2.56E-09 NO DATA 1.62E-04 N8 95 4.20E-08 1.73E-08 I.ODE-08 NO DATA 1.74E-08 NO DATA 1.46E-05 MO 99 NO DATA 1.4CE-O5 6.63E-06 NO DATA 5.08E-05 NO DATA 1.12E-05 TC 99M 1.92E-09 3.96b-09 5.10E-08 NO DATA 4.26E-08 2.07E-09 1.15E-06 TC1O0 2.27E-09 2.86E-09 2.83E-08 -NO DATA 3.40E-08 1.56E-09 4.86E-07 RUED3 1.48E-06 NO DATA 4.95E-07 '4O DATA 3.08E-06 NO DATA 1.80E-05 RUI05 1.36E-07 NO DATA 4.58E-08 NO DATA 1.O0E-06 Nfl DATA 5.41E-05 RU106 2.41E-05 NO DATA 3.DIE-06 NO DATA 2.85E-05 NO DATA - 1.83E-04 AGIOM 9.96E-07 7.27E-07. 4.81E-07 NO DATA 1.04E-06 NO DATA 3.77E-05 TE125M 2.33E-05 7.79C-06 3.15E-O0 7.84E-06 NO DATA NO DATA, 1.1lE-05 TEI27M 5.85E-05 1.94E-05 7.08E-06 1.69E-05 1.44E-04 NO DATA 2.36E-05 TE127 1.00E-06 3.35E-07 2.15E-07 8.14E-07 2.44E-06 NO DATA 2.10E-05 TE129M 1.OOE-04 3.43E-05 1.54E-05 3.84E-05 2.50E-04 NO DATA 5.97E-05 TE129 2.84E-07 9.79OE-08 .63E-08 2.382-07 7.07E-07 NO DATA 2.27E-05 TEI131 1.52E-05 6.12E-06 5.05E-06 1.24E-05 4.21E-05 NO DATA 1.03E-04 TE131 1.76E-07 6.502E-08 4.94E-08 1.7E-07 4.50E-07 NO DATA 7.11E-06 TE132 2.08E-05 1.03E-05 9.612E-06 1.52E-05 6.44E-05 NO DATA 3.81E-05 I 130 6.OOE-06 1.32E-05 5.30E-06 1.48E-03 1 45E-05 NO DATA 2.83E-06

1 131 3.59E-05 4.23E-05 1.86E-05 1.39E-02 4.94E-05 NO DATA 1.51E-06

1132 1.66E-06 3.37E-06 1.20E-06 1.58E-04 3.76E-06 NO DATA 2.73E-06 I 133 1.25E-05 1.82[-05 5.33E-06 3.31E-03 2.14E-05 NO DATA 3.08E-06

1134 8.69E-P7 1.78E-06 6.33E-07 4.15E-05 1..99E-06 NO DATA 1.84E-06

1 135 3.64E-06 7.24E-06 2.64E-06 6.49E-04 9.07E-06 NO DATA 2.62E-06 CS134 3.77E-04 7.03E-04 7.10E-05 NO DATA 1.81E-04 7.42E-05 1.91E-06 CS136 4.59E-05 1.35E-04 5.04E-05 NO DATA 5.38L-05 1.10E-05 2.05E-06 CS137 5.22E.-04 b.IIE-04 4.33E-05 NO DATA 1.64E-04 6.64E-05 1.91E-06 CS138 4.81E-07 7.82E-07 3.79E-07 NO DATA 3.90E-07 6.09E-08 1.25E-06 BA139 8.81E-07. 5.84E-10 2.55E-08 NO DATA 3.51E-1O 3.54E-10 .5.58E-05

1.109-66 m

TAt6LE E-14, CONT'D

PA:,E 3 OF 3 INGESTION DOSE FACTORS FOR INFANT

(MREM PER PCI INGESTED)

NUCLIL;E BONE LIVER T.3ODY THYROID KIDNEY LUNG GI-LLI

BA14u 1.7LE-04 1.71E-07 8.81E-06 NO DATA 4.06E-08 1.05E-07 4.20E-05 P,.A141 4.25E-O7 2.91E-1O 1.34E-08 NO DATA 1.75E-10 1.7TTE-O 5.19E-06 BA142 I.B4E-07 1.53E-1O 9.06E-09 NO DATA 8.8IE-11 9.26E-11 T.59E-07 LA140 2.11E-O8 8.32E-09 2.14E-09 NO DATA NO DATA NO DATA 9.77E-05 LA142 1.1OE-09 4.04E-10 9.61F-Il NO DATA NC DATA NO DATA 6.86F-05 CEI4I 7.87E-08 4.8OE-08 5.65E-09 NO DATA 1.48E-08 NO DATA 2.48E-05 CE143 1.48E-08 9.82E-06 1.1?E-09 NO DATA 2.86E-09 NO DATA 5.73E-05 CE144 2.98E-06 1.22E-06 1.67E-07 NO DATA 4.93E-07 NO DATA 1.71E-04 PR143 8.13E-08 3.04E-08 4.03E-09 NO DATA 1.13E-08 NO DATA 4.29E-05 PR144 2.74L-I0 I.ObE-l0 1.38E-1I NO DATA 3.84E-11 NO DATA 4.93E-06 ND147 5.53E-08 5.68E-08 3.48E-09 NO DATA 2.19E-O8 NO DATA 3.60E-05 w 187 9.03E-07 6.28E-07 2.17E-01 NO DATA NO DATA NO DATA 3.69E-05 NP239 1.1IE-08 9.93E-10 5.61E-16 NO DATA 1.98E-09 NO DATA 2.87E-05

1.109-67

- ~

TABLE E-15 RECOMMENDED VALUES FOR OTHER PARAMETERS

Parameter Equation(s)

Symbol Definition Where Used Values Reference(s)*

fg Fraction of produce ingested grown in garden of interest 14 & C-13 0.76 ft Fraction of leafy vegetables grown in garden of interest 14 & C-13 1.0

2 p Effective surface density of soil (assumes a 15 cm plow 4, A-8, A-13, & C-5 240 kg/mi 10

layer, expressed in dry-weight)

Fraction of deposited activity retained on crops, leafy 4, A-8, & A-13 0.25 27 vegetables, or pasture grass C-5 1.0 (for iodines) 2, 4, 13,

0.2 (for other 28-31 particulates)

SF Attenuation factor accounting for shielding provided by 8, 9, 10, 11, 12, 0.7 (for maximum 26 residential structures B-6, B-7, B-8, B-9, individual)

Io

00 & C-2 0.5 (for general 26

0QO

population)

tb Period of long-term buildup for activity in sediment or 3, 4, A-4, A-5, A-6, 1.31 x 105 hr soil (nominally 15 yr) A-7, A-8, A-13, & C-5 te Period of crop, leafy vegetable, or pasture grass 4, A-8, A-13, & C-5 720 hrs (30 days,. 10 & 32 exposure during growing season for grass-cow-milk- man pathway)

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

tf Transport time from animal feed-milk-man C-10 2 days (for maximum individual)

4 days (for general population)

Parameter values given without references are based on staff judgments.

TABLE E-15 (Continued)

Parameter Equation(s)'

Symbol Definition Where Used Values Reference(s)*

th Time delay between harvest of vegetation or crops and ingestion i) For ingestion of forage by animals 4, A-8, A-13, & C-5 Zero (for pasture grass)

2160 hr (90 days for stored feed)

ii) For ingestion of crops by man 4, A-8, A-13, & C-5 24 hr (1 day, for leafy vegetables &

maximum individual)

1440 hr (60 days, for produce & maximum individual)

336 hr (14 days, for general population)

t Environmental transit time, release to receptor 1 & A-2 12 hr (for maximum p (add time from release to exposure point to individual)

minimums shown for distribution) 24 hr (for general population)

0

2 & A-3 24 hr (for maximum individual)

168 hr (7 days for population sport fish doses)

240 hr (10 days for population com- mercial fish doses

3 & A-7 Zero tS Average time from slaughter of meat animal to C-12 20 days consumption Y Agricultural productivity by unit area (measured 4, A-8, A-13, & C-5 0.7 kg/mi2 (for grass- 33 V

in wet weight) cow-milk-man pathway)

2.0 kg/m 2 (for produce 34 or leafy vegetables ingested by man)

1 Rate constant for removal of activity on plant or leaf 0.0021 hr- w

surfaces by weathering (corresponds to a 14-day half-life)

Parameter values given without references are based on staff judgments.

REFERENCES FOR APPENDIX E

1. Y. C. Ng et al., "Prediction of the Maximum Dosage to Man from the Fallout of Nuclear Devices, Handbook for Estimating the Maximum Internal Dose from Radionuclides Released to the Biosphere," USAEC Report UCRL-50163, Part IV, 1968.

2. B. H. Weiss et al., "Detailed Measurement of 1-131 in Air, Vegetation and Milk around Three Operating Reactor Sites," Environmental Surveillance Around Nuclear Installations, Inter- national Atomic Energy Agency, IAEA/SM-180/44, Vienna, Austria, Vol. I: pp. 169-190, 1974.

3. F. 0. Hoffman, "Environmental Variables Involved with the Estimation of the Amount of 1-131 in Milk and the Subsequent Dose to the Thyroid," Institute fur Reaktorsicherheit, Cologne, West Germany, IRS-W-6, June 1973.

4. F. 0. Hoffman, "Parameters To Be Considered When Calculating the Age-Dependent 1-131 Dose to the Thyroid," Institute fir Reaktorsicherheit, Cologne, West Germany, IRS-W-5, April

1973.

5. F. 0. Hoffman, "A Reassessment of the Parameters Used To Predict the Environmental Transport of 1-131 from Air to Milk," Institute fur Reaktorsicherheit, Cologne, West Germany, IRS-W-13, April 1975.

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

7. R. J. Garner and R. S. Russel, Radioactivity and Human Diet, R. Scott Russel (ed.), Pergamon Press, Oxford, England, 1966.

8. P. M. Bryant, "Data for Assessments Concerning Controlled and Accidental Releases of 1-131 and Cs-137 to the Stratosphere," Health Phys., Vol. 17, p. 51, 1969.

9. J. D. Zimbrick and P. G. Voilleque (eds.), "1967 CERT Progress Report," USAEC Report IDO-12067, p. 36, 1968.

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

11. J. K. Soldat, "Conversion of Survey Meter Readings to Concentration (liCi/m 2 )," Item 04.3.4 in "Emergency Radiological Plans and Procedures," K. R. Heid (ed.), USAEC Report HW-70935, Hanford Laboratories, 1962.

12. "Permissible Dose from External Sources of Ionizing Radiation," Handbook 59, U.S. Dept. of Commerce, 1954.

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

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

15. R. J. Garner, "Transfer of Radioactive Materials from the Terrestrial Environment to Animals and Man," CRC Press, Cleveland, Ohio, 1972.

16. J. K. Soldat et al., "Models and Computer Codes for Evaluating Radiation Doses," USAEC

Report BNWL-1754, Pacific Northwest Laboratories, February 1974.

17. A. L. Rogers, "Goat Keeping in the United States," International Dairy Goat Conference, London, July 1964.

18. R. G. Bond and C. P. Straub (eds.), Handbook of Environmental Control, Vol. III, "Water 40

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

1.109-70

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

20. "Report of the Task Group on Reference Man," ICRP Publication 23, Pergamon Press, Oxford, England, 1975.

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

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

Some Preliminary Findings of the 1969 Consumer Panel Survey," NMFS Circular 361, USDC/NOAA,

Seattle, Wash., June 1971.

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

24. "Draft Environmental Statement - Waste Management Operations, Hanford Reservation, Richland, Washington," USAEC Report WASH-1528, Washington, D.C., September 1974.

25. G. R. Hoenes and J. K. Soldat, "Age-Specific Radiation Dose Commitment-Factors for a One Year Chronic Intake," USNRC Report NUREG-0172, to be issued in 1977. A draft is available in the Public Document Room.

26. Z. G. Burson and A. E. Profio, "Structural Shielding from Cloud and Fallout Gamma Ray Sources for Assessing the Consequences of Reactor Accidents," EG&G-1183-1670, Las Vegas, Nev., 1975.

27. D. A. Baker et al., "FOOD - An Interactive Code to Calculate Internal Radiation Doses from Contaminated Food Products," BNWL-SA-5523, February 1976.

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

USAEC Report IDO-12063, January 1968.

29. J. D. Zimbrick and P. G. Voilleque, "Controlled Environmental Radioiodine Tests at the National Reactor Testing Station, Progress Report Number Four," USAEC Report IDO-12065, December 1968.

30. C. A. Pelletier and P. G. Voilleque, "The Behavior of Cs-137 and Other Fallout Radionuclides

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

31. P. G. Voilleque and C. A.. Pelletier, "Comparison of External Irradiation and Consumption of Cow's Milk as Critical Pathways for Cs-137, Mn-54 and Pr-144 Released to the Atmosphere,"

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

32. J. J. Koranda, "Agricultural Factors Affecting the Daily Intake of Fresh Fallout by Dairy Cows," USAEC Report UCRL-12479, 1965.

33. M. E. Heath et al., Forages, the Iowa State University Press, Ames, Iowa, 1973.

34. "Statistical Abstract of the United States," U.S. Bureau of the Census, 93rd Edition, 1972.

1.109-71

APPENDIX F

METHODS FOR EVALUATING THE I FUNCTION

The NRC staff calculates ground-level gamma radiation doses from elevated noble gas releases using Equation (6) in Regulatory Posifion C.2.a of this guide. Equation (6) is based on the model presented in Slade (Ref. 1), which can be characterized as a vertically finite sector- averaged Gaussian plume model. Use of the model involves volume integration over a distributed source, resulting in certain integrals that define the I function, denoted by TT in Reference 1.

1. Derivation of the I Function The derivation of the I function presented below is taken directly from Reference 1, which should be consulted for further details.

The sector-average airborne radionuclide concentration resulting from a continuous release is given by the Gaussian plume model as (see Equation 7.60 of Ref. 1):

(Rz) Q exp h

- 2(z + exp (F-i)

2V~0 zURe 22L 2oL

v~Taz uez where h is the effective release height, in meters;

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

R is the downwind distance, in meters; (7 u is the average wind speed, in m/sec;

x(R,z) is the sector-average concentration at location (R,z), in Ci/m3 z is the vertical distance above the ground plane, in meters;

e is the sector width, in radians; and o

a is the vertical plume spread, in meters.

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

7(R,z) = 'DG(z) (F-2)

zRe where G(z)= expF- iz h)2 + exp (F-3)

L 2a j L zp z

2a J

where the terms are as defined above.

6.

1.109-72 M ME ý"-77- , :E ý - ,

The gamma dose rate to air at a distance of r meters from a point source of q curies is

1):

Equation 7.33 of Ref.

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

2

41r (1293)(100) (F-4)

Where B(,va ,r) is the buildup factor, dimensionless;

D' is the dose rate to air, in rad/sec;

E is the gamma ray energy per disintegration, in MeV;

q is the point source strength, in curies;

r is the distance, in meters;

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

100 is the number of ergs per gram-rad;

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

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

3.7 x 1010 is the number of disintegrations, per Ci-sec.

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

SKiaqEB(P,'a,r)exp(-pr) (F-5)

41Tr were M~

(F-6)

K (3.7 x(1293)(100)=04

10101(.6 x I0- 6 0.46 The next step is to incorporate Equation (F-2) into Equation (F-5) to arrive at an the ression for the differential dose rate dD' from the differential volume dV containing e... nuclide concentration X(R,z). Consider a volume element of the plume located z meters above (see Figure 7.20

r ga...d and at a horizontal distance L meters from-receptor location (R, 0)

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

7, ,g91shaped differential volumeelements large that the concentration

21TLdLdz. If R is sufficiently -(R,z),

r0aged over all such volume can be approximated by the contribution of the Vershaped differential volume dV to the air dose rate at location (R,0) is given as K iaEB( p' va'r)exp(- tr) *(~ ~ V(F-7)

F7

  • dD' =

4r 2 (Rz)dV

1.109-73

  • 1 where q has been replaced by x(R,z)dV. Substituting (L2 + z2)I/2 for r and 2wLdLdz for dV in Equation (F-7), and integrating, the following expression is obtained:
1 KuIaEQD B [vi'vaý (L2+ zI)j1 G(z) exp LuI(L 2+Z2 jLdd

2

2 ,/2'R7 L2 + z

00 (F-8)

T

The I function, denoted by T in Reference l, is defined as

37-~ J

O00

B_1__(_2_

B )g;(2 Z2)l1/2]1 G(z)exp [w(L 2 L2 2 L

+ z2)1/2]

- LdLdz (F-9)

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

D'= I (F-10)

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

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

where k "a (F-12)

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

where the Il and 12 integrals can be written for this form of the buildup factor as I 2 3 /2zi G(z)El(ljz)dz (F-14)

0

I

and an. 21 a G(z)exp(-Pz)dz (F-15)

z

0

where El(z) is the exponential integral defined by El(GZ) = f exp(-r)r prz d(pr) (F-16)

1.109-74

2. Evaluation of the I Function In Reference 1 the I and 12 integrals have been evaluated. and the results presented graphically. Extraction of the data from these six-cycle log-log multicurve plots is a formidable task. A more satisfactory approach is to prepare a tabulation of the integrals as evaluated using numerical methods. These data can then be interpolated in implementing Equation (6) of Regulatory Position C.2.a.

The .NRC staff has developed a computer routine that evaluates the I function as formulated in Equation (F-g). The I function as expressed in Equation (F-9) is independent of the buildup factor form. A listing of this routine is provided in Figure F-1. Communication with the routine is through the COMMON statement, which also communicates with the function subprogram BULDUP, which defines the dose buildup factor B(p,p ar) desired by the user.

Also, Yankee Atomic Electric Company has supplied a routine written by Dr. John N. Hamawi of that company (Ref. 2). This routine evaluates the I, and 12 integrals as formulated in Equations (F-14) and (F-15), respectively. A li.sting of the routine is provided in Figure F-2 (reproduced with the permission of Yankee Atomic Electric Company). With the exceptions of changes in the title, the addition of the COMMON statement, the computing of I from IlIand 12V

and comment cards as to its authorship, the routine is reproduced as written by Dr. Hamawi. The staff has compared the two routines and found their results to be in excellent agreement. The routine supplied by the Yankee Atomic Electric Company was found to be considerably faster than the staff's routine.

1.109-75

SUBROUTINE DINT

C**

COMMONDATAIT/GMUZKHSSIGMZEBARDIM

DOSE INTEGRAL SUBROUTINE -K.F. ECKERMAN 11-24-74 r~r, C

C SUBROUTINE EVALUATES THE DOSE INTEGRAL 'IT' AS DEFINED BY EON 7.61 C, IN MET & AE-1968. THE TWO DIMENSIONAL INTEGRATION IS EVALUATED

C . USING GAUSSIAN-LEGENDRE QUADRATURE OF ORDER 48.

C

C COMMON INFO

C. GMU-MASS ATTENUATION COEFFICIENT (I/METERS)

C ZK-BUILDUP FACTOR ((U-MUA5/MUA IF USED

C HS-RELEASE POINT HEITH

C

Cw RELEASE POINT HEIGHT (METERS)

C SIGmZ-STANDARD DEVIATION OF PLUME (METERS)

C EBAR-GAMMA RAY ENERGY (MEV)

C DI-DOSE INTEGRAL

C M-ENERGY GROUP INDEX IF NEEDED

NOTE-ZKoEBAR,& M ARE USED BY BULDUP

DIMENSION X(245),(24)

DATA NN/48/,A/2.828427125/

DATA X/

10.0323801709, 0.0970046992o 0.1612223560, 0.2247637903,

20.2873624873, 0.3487558862, 0,4086864819, 0.4669029047,

30.5231609747, 0.5772247260, 0.6288673967, 0.6778723796,

40.7240341309# 0.7671590325, 0.8070662040, 0.8435882616,

50.8765720202, 0.9058791367, 0.9313866907, 0.9529877031,

60.9705915925, 0.9841245837, 0,9935301722v 0.9987710072/

DATA W/

10.0647376968o 0,0644661644# 0.0639242385, 0.0631141922,

20,0620394231, 0.0607044391, 0.0591148396, 0.0572772921,

30.0551995036, 0.0528901894, 0.0503590355, 0,0076166584,

40.0446745608p 0.0415450829# 0.0382413510, 0,0347772225,

50,0311672278, 0.0274265097, 0.0235707608, 010196161604,

60.0155793157, 0.0114772345, 0.0073275539, 0.0031533460/

SUMUO.

Buo.5/(SIGMZ*SIGMZ)

ZLB3HS-4.*SIGMZ

ZUBBHS+4.*SIGMZ

IFCZLB.LT.0.)ZLBuO.

YUBUIS./GMU

CZ0.5*(ZUB-ZLB)

GcO.S*(ZUB+ZLB)

E8O.5*YUB

DO 7o II21PNN

III-II1/2 Ful.

EX=O.

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

ZZUF*X(I)*C÷G

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

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

55 ARGU=B*(ZZ÷HS)*(ZZeHS)

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

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

DO 60 KK8I1NN

KzKK-KK/2 Fpa.

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

Figure F-I. Staff-Written Computer Listing

/

1.109-76

YYzF*XCK)*E+E

DI=YY*Yy÷ZZ*ZZ

ARGUUGMU*SQRT(Dl)

IF(ARGU.GT.2o.,)GO TO 60

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

SUM-SUM÷W( I*W(K)*EXI

60 CONTINUE

70 CONTINUE

DIxSUM*C*E/(A*SIGMZ)

RETURN

END

Figure F-I (continued)

1 .109-77

SUBROUTINE DINT

REAL MU

COMMON/DATAIT/MUZK*HoSIGZDIL

C DOSE INTEGRAL ROUTINE WRITTEN BY

C DR, JOHN N. HAMAWI

C YANKEE ATOMIC ELECTRIC COMPANY

C NUCLEARSERVICES DIVISION

C 20 TURNPIKE ROAD

C WESTBOROUGH# MASSACHUSE-TTS 01581 C YAEC REPORT No. 1105 C

C COMMON INFO

C MU-MASS ATTENUATION COEFFICIENT (1/METERS)

C ZK-BUILDUP FACTOR (MU-MUA)/MUA

C SIGZ-STANDARD DEVIATION OF PLUME (METERS)

C DI-DOSE INTEGRAL -I TOTAL

C

C** L- DETERMINES NUMBER OF INTERVALS USED IN INTEGRATION

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

DATA M/9/,CDATA/5.OD+3 1.OD+4o,2.0D+4#,5.0D+÷,1.OD÷S/5 DATA AOA1,A2,A3,A4,AS/ -0.57721566, 0.99999193, - 0,249910.55, C 0.05519968,-0.00976004, 0.00107857/

DATA BO,BI,B2,B3/0.26777373M3, 8.6347608925, 18.0590169730,

C 8.5733287401/

DATA CO,CIPC2,C3/ 3.9584969228, 21.0996530827, 25.6329561486, C 9,5733223454/

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

C 3543.75,989.,5888.,-928.,10496.,-4540.,1049b.,-928.,5888., 98

9./

C**** COMPUTE LIMITS OF INTEGRATION ZMIN AND ZMAXs AND INTERVAL WIDTH

IF(L.LT.2.OR.L.GT.6) L* 6 C S CDATA(L-I)

N U L*(M-1) + 1 SIGZ2 SI.GZ*SIGZ

S

ALFA H - MU*SIGZ2 m

BETA = SIGZ* SQRT(2.0*ALOG(C))

IF(ALFA.GT.O.0) GO TO 150

ZMIN a 0.0

ZMAX x ALFA + SQRT(ALFA*ALFA + BETA*BETA)

  • GO.TO 200

150 ZMIN 9 ALFA - BETA

IF(ZMIN.LT.O.0) ZMIN a 0.0

ZMAX.8 ALFA + BETA

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

C**** COMPUTE EXPONENTIAL INTEGRAL TERMS EUl) (SPECIAL PROCED. FOR E(1))

E(I) 2 2.1B907-ALOG(MU*DZ)

DO 2s0 I 8 1, N

Z 2 ZMIN + (I-i)*DZ

X a MU*Z

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

X2 9 X*X

X3

  • X*X2 X4 2 X*X3 X5 z X*X4 IF(X.LE.I.0) E(I) z -ALOG(X) + AO÷AI*X+A2*X2+A3*X3+A4*X4+AS*X5 IF4X.GT.10O) E(VI) a (BO+BI*X+B2*X2÷B3*X3÷X4)/

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

250 CONTINUE

C**** COMPUTE INTEGRAND TERMS B(I1 AND P(I)

DO 309 I p1 N

Z

  • ZMIN + (I-1)*DZ

Figure F-2. Hamawi-Written Computer Listing

1.109-78

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

B(I) a G*E(I)

300 PCI) a G* EXP(-MU*Z)

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

SUMB v 0.0

SUMP u 0.0

MM 5 M - I

KM x N - M + I

DO 350 K 9 IpKMPMM

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

9 C +D6*B(K+5)+D7*B(K4bý+D8*B(K+7)+D *BCK+8)

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

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

350 CONTINUE

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

RETURN

END

Figure F-2 (continued)

1.109-79

REFERENCES FOR APPENDIX F

1. "Meteorology and Atomic Energy 1968," D. H. Slade (ed.), USAEC Report TID-241090, 1968.,

2. J. N. Hamawi, "A Method for Computing- the Gamma-Dose Integrals 1 and T2 for the Finite- Cloud Sector-Average Model," Yankee Atomic Electric Company Report YAEC-I105, 1976.

A

1.109-80

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

UNITED STATES FIRST CLASS MAIL

NUCLEAR REGULATORY COMMISSION POSTAGE &t FEES PAID

USNRC

WASHINGTON, D.C. 20555 PERMIT No. G-67 OFFICIAL BUSINESS

PENALTY FOR PRIVATE USE, $300

S


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