Regulatory Guide 1.109: Difference between revisions

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{{Adams
{{Adams
| number = ML003740384
| number = ML13350A285
| issue date = 10/31/1977
| issue date = 03/31/1976
| 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
| 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
| author name =  
| author name =  
| author affiliation = NRC/RES
| author affiliation = NRC/OSD
| addressee name =  
| addressee name =  
| addressee affiliation =  
| addressee affiliation =  
| docket = WM-00011
| docket =  
| license number =  
| license number =  
| contact person =  
| contact person =  
| case reference number = -nr
| document report number = RG-1.109
| document report number = RG-1.109, Revision 1
| document type = Regulatory Guide
| document type = Regulatory Guide
| page count = 86
| page count = 64
}}
}}
{{#Wiki_filter:Revision 1*
{{#Wiki_filter:U.S. NUCLEAR REGULATORY COMMISSION
                                    U.S. NUCLEAR REGULATORY COMMISSION                                                                               October 1977 REGULATORY GUIDE
REGULATORY GUIDE
                                    OFFICE OF STANDARDS DEVELOPMENT
OFFICE. OF STANDARDS DEVELOPMENT
                                                                    REGULATORY GUIDE 1. 09 CALCULATION OF ANNUAL DOSES TO MAN- FROM ROUTINE
March 1976
      RELEASES OF REACTOR EFFLUENTS FOR TH
4,s.


==E. PURPOSE==
REGULATORY GUIDE 1.109
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.
CALCULATION OF ANNUAL DOSES.,'TO MAN .fROM ROUTINE
RELEASES OF REACTOR EFFLUENTS FOR THE PU.!RPOSE OF EVALUATING C
10 CFR PART SO, APPENDIX I
7.?
OMPLIANCE WITH
\\'~
*%~
5- I
-~
~
USNRC REGULATORY GUIDES  
Comments should be sent to the Secretary of the Commission. U.S. Nuclear Regulatory Guides are issued to describe and matte available to the publc Regultory Commission. Washingon D.C 20.


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


*The      substantial number of.changes in this revision has made it impractical to indicate the changes with lines in the margin.
TABLE OF CONTENTS
Page A.
 
INTRODUCTION ......................................................................
1.109-7 B.
 
DISCUSSION ........................................................................
1.109-7 C.


7
REGULATORY POSITION ...............................................................
1.109-8
1. Radiation Doses from Liquid Effluent Pathways.
 
..........................
109-8 a.
 
Potable Water ...........................................................
1.109-8
6. Aquatic Foods ...........................................................
1.109-8 c.
 
Shoreline Deposits .......
... ...........................................
1.109-8 d.
 
Irrigated Foods .........................................................
1.109-8
2.
 
Gamma and Beta Doses from Gaseous Effluents ..................................
1.109-10
a.
 
Gamma Air Dose Rates for Elevated Releases ..............................
1.109-10
b.
 
Ganma Air Dose Rates from Ground-Level Releases; Beta Air Dose Rates from Elevated and Ground-Level Releases
........................... 1.109-11 c.
 
Total Body Dose Rates from Elevated Releases ............................
1.109-11 d.
 
Skin Dose Rate from Elevated Releases ...................................
1.109-12 e. Total Body Dose Rates from Ground-Level Releases ........................
:.109-12 f.
 
Skin Dose Rates from Ground-Level Releases ..............................
1 109-12
3.
 
Doses from Radiuiodines and Other Radionuclides Released to the Atmosphere...
1.109-12 a.
 
External Irradiation from Activity Deposited onto the Ground Surface ....
1.109-13 b.
 
Inhalation ...............................................................
1.109-13 c.
 
Ingestion.
 
.................................................. 1.109-13
4.
 
Integrated Doses to the Population ...........................................
l.lO9-l1
5.
 
Summary of Staff Position..........................................1.109-14 D.
 
IMPLEMENTATION ....................................................................
1.109-14 APPENDIX A, METHODS FOR CALCULATING DOSES TO MAN FROM RADIONUCLIDE DISCHARGES TO
THE AQUATIC ENVIRONMENT ................................................................
1.109-17
1. Equation for Calculating Radiation Dose via Liquid Pathways ..................
1.109-17 a.
 
Concentration in Environmental Media (Cip) ..............................
1.109-17 b.
 
Usage (U ap) .............................................................
1.109-17 C.


TABLE OF CONTENTS
Dose Factor (Dp
                                                                                                                                            Page
"p ) .....................................................
1.109-20
2.


==A. INTRODUCTION==
Equation for Liquid Pathways ................................................  
................................................................. 1.109-1
l.l09-20
a.


==B. DISCUSSION==
Potable Water
........................................................................                                            1.109-1
...............................................  
1.109-20
b.


==C. REGULATORY POSITION==
Aquatic Foods..  
............                            .............................................. 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
1.109-20
        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
c.
              -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
Dose from Shoreline Deposits ............................................  
        4.    Integrated Doses to the Population ...........................................                                            1.109-8
1.109-30
        5.    Summary of Staff Position ....................................................                                            1.109-8
d.


==D. IMPLEMENTATION==
Dose from Foods Grown on Land Irrigated by Contaminated Water ...........  
....................................................................                                            1.109-8 APPENDIX A, METHODS FOR CALCULATING DOSES TO MAN FROM LIQUID EFFLUENT PATHWAYS .........                                             1.109-11
1.109-33 REFERENCES FOR APPENDIX A ..............................................................  
        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
1.109-36 APPENDIX B, MODELS FOR CALCULATING DOSES FROM NOBLE GASES DISCHARGED TO THE
        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
ATMOSPHERE ............................................................................  
1.109-39
1.109-3


TABLE OF CONTENTS (Continued)
TABLE OF CONTENTS (Continued)
                                                                                                                              Page APPENDIX B, MODELS FOR CALCULATING DOSES FROM NOBLE GASES DISCHARGED TO THE
Page
ATMOSPHERE ..................................................                                 .........................   1.109-19
1.
      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
Annual Gamma Air Dose from Elevated Releases of Noble Gases ..................  
      3.   Annual Total Body and Skin Doses from Noble Gas Effluents ....................                                  1.109-20
1.109-39
          a.       Releases from Free-Standing Stacks More Than 80 Meters High .............                              1.109-20
2.
          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
Annual Gamira Air Dose from Ground-Level Releases of Noble Gases and Annual Beta Air Dose ..............................................................  
      1.   Annual External Dose from Direct*Exposure to Activity Deposited on the                                                       ,
1 .109-40
          Ground Plane.                       ...................................................... 1.109-24
3.
      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 ....................
Annual Dose to Tissue from Noble Gas Effluents ..............................  
                                                                                                                            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
1.109-40
      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
a.
EFFLUENTS ..............................................................................                                     1.109-30
 
      1.   General Expressions for Population Dose ......................................                                   1.109-30
Elevated Releases .......................................................  
      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
1.109-40
RELEASES OF*REACTOR EFFLUENTS .........................................................                                     1.109-36
b.
      1.   Environmental Data                                          .................................................   1.109-36
 
      2.    Human Data ..................................................................                                    1.109-36
Ground-Level Releases ...................................................  
      3.    Dose Factors............................................................ 1.109-36
1.109-42 REFERENCES FOR APPENDIX B ..............................................................  
      4.  Other Parameters......................................................                                          1.109-43 REFERENCES FOR APPENDIX E                                      ....................................................        1.109-70
1.109-43 APPENDIX C, MODELS FOR CALCULATING DOSES VIA ADDITIONAL PATHWAYS FROM RADIOIODINES
                                                                                      iv
AND OTHER RADIONUCLIDES DISCHARGED TO THE ATMOSPHERE ...................................
1.109-45
1.
 
Annual External Dose from Direct Exposure to Activity Deposited on the Ground Plane .................................................................
1.109-45
2.
 
Annual Dose from Inhalation of Radionuclides in Air ..........................  
1.109-46
3.
 
Concentrations of Airborne Radionuclides in Foods ............................
1.109-46 a.
 
Parameters for Calculating Nuclide Concentrations in Vegetation Consumed by Man .............................................  
1.109-55 b.
 
Parameters for Calculating Nuclide Concentrations in Milk............  
1.109-55 c.
 
Parameters for Calculating Nuclide Concentration in Meat ................
1.109-59 I
4.
 
Annual Dose from Atmospherically Released Radionuclides in Foods .............  
1.109-59 REFERENCES FOR APPENDIX C ..............................................................
1.109-60
APPENDIX D, MODELS FOR CALCULATING POPULATION DOSES FROM NUCLEAR POWER PLANT
EFFLUENTS...............................................................................
1 .109-63
1. General Expressions for Pý.pulation Dose ......................................  
1.109-63
2.
 
Use of the Models .............................................................
1.109-67 a.
 
Population-Integrated Doses from Liquid Effluents .......................  
1.109-67 b.
 
Population-Integrated Doses from Airborne Effluents .....................  
1.109-68 REFERENCE FOR APPENDIX D ...............................................................  
1.109-69
1.109-4


TABLE OF CONTENTS (Continued)
TABLE OF CONTENTS (Continued)
                                                                                                Page APPENDIX.F, METHODS FOR EVALUATING THE I FUNCTION ....................................... 1.109-72
Page
        1.   Derivation of the I Function .................................................. 1.109-72
1.
        2.   Evaluation of the I Function .................................................. 1.109-75 REFERENCES FOR APPENDIX F................................................................. 1.109-80
 
    ,4      ;,v
Annual Gamma Air Dose from Elevated Releases of Noble Gases ..................
=..
1.109-39
2.
 
Annual Gamma Air Dose from Grjund-Level Releases of Noble.Gases and Annual Beta Air Dose ..............................................................
1.109-40
3.
 
Annual Dose to Tissue from Noble Gas Effluents ..............................
1.109-40
a..
Elevated Releases .......................................................
1.109-40
b.
 
Ground-Level Releases ...................................................
1.109-42 REFERENCES FOR APPENDIX B ..............................................................
1.109-43 APPENDIX C, MODELS FOR CALCULATING DOSES VIA ADDITIONAL PATHWAYS FROM RADIOIODINES
AND OTHER RADIONUCLIDES DISCHARGED TO THE ATMOSPHERE ...................................
1.109-45
1.
 
Annual External Dose from birect Exposure to Activity Deposited on the Ground Plane .................................................................
1.109-45
2.
 
Annual Dose from Inhalation of Radionuclides in Air ..........................  
1.109-46
3.
 
Concentrations of Airborne Radionuclides in Foods ............................
1.109-46 a.
 
Parameters for Calculating Nuclide Concentrations in Vegetation Consumed by Man .........................................................  
1 .109-55 b.
 
Parameters for Calculating Nuclide Concentrations in Milk ...............  
1.109-55 c.
 
Parameters for Calculating Nuclide Concentration in Meat ................  
1.109-59
4.
 
Annual Dose from Atmospherically Released Radionuclides in Foods .............
1.109-59 REFERENCES FOR APPENDIX C ..............................................................
1.109-60
APPENDIX D, MODELS FOR CALCULATING POPULATION DOSES FROM NUCLEAR POWER PLANT
EFFLUENTS...  
...........................................................................
1.109-63
1. GeneralExpressions for P p,,jlation Dose ......................................
1.109-63
2.
 
Use of the Models ...................................
........................
1.109-67 a.
 
Population-Integrated Doses from Liquid Effluents .......................
1.109-67 b.
 
Population-Integrated Doses from Airborne Effluents .....................
1.109-68 REFERENCE FOR APPENDIX D ...............................................................
1.109-69 E
1.109-4


LIST OF TABLES
LIST OF TABLES
Table                                                                                                                                                   Page
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
1 Summary of Staff Position - Methods of Evaluating Compliance with Appendix i ..................................................................  
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 .109-15 A-I
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
Definition of Points at Which Concentrations in Environmental Media (Clp)
Figure                                                                                                                                                  Page F-l      Staff-Written Computer.Listing .............................................                                                               1.109-76 F-2      Hamawi-Written Computer Listing .                                                                                                         1,109-78 vi
Should be Calculated ........................................................  
1.109-18 A-2 Recommended Values for Uap to be Used for the Maximum Exposed Individual in.Lieu of Site-Specific Data ...............................................  
1.109-19 A-3 Adult Ingestion Dose Factors ..................................................  
1.109-21 A-4 Teenager Ingestion Dose Factors ...............................................  
1.109-25 A-5 Child Ingesticn Dose Factors ..................................................  
1 .109-26 A-6 Infant Ingestion Dose Factors .................................................  
1.109-27 A-7 External Dose Factors for Standing on Contaminated Ground .....................  
1.109-28 A-8 Bioaccumulation Factors .......................................................  
1 .109-31 A-9 Shore Width Factors for Use in Equations (A-5) and (A-6) ......................  
1.109-34 A-10
Animal Consumption Rates ......................................................  
1.109-34 B-i Dose Factors for Noble Gases and Daughters
..............................
1.109-41 C-1 Adult Inhalation Dose Factors .................................................
1.109-47 C-2 Teenager Inhalation Dose Factors ..............................................
1.109-51 C-3 Child Inhalation Dose Factors .................................................
1.109-52 C-4 Infant Inhalation Dose Factors ................................................
1.109-53 C-5 Stable Element Transfer Data ..................................................  
1.109-56 C-6 Nuclide Transfer Parameters for Goat's Milk ...................................  
1.109-57
0-1 Recommended Values to be Used for the Average Individual in Lieu of Site-Specific Data ..........................................................  
1.109-64
0-2 Recommended Values for the Transport Times in the Food Distribution System ......................................................................  
1 .109-66
1.109-5
 
A.
 
INTRODUCTION
Section 20.106, "Radioactivity in Effluents to Unrestricted Areas," of the Nuclear Regulatory Commission's regulations in 10 CFR Part 20, "Standards for Protection Against Radiation," estab- lishes limits on concentrations of radioactive material in effluents to unrestricted areas.
 
Paragraph (c) of 5 20.1, "Purpose," of 10 CFR Part 20 states that licensees s;hould, in addition to complying with the limits set forth in that part, make every reasonable effort to maintain releases of radioactive materials in effluents to unrestricted areas as far below the limits specified as is reasonably achievable.
 
Sections 50.34a,
"Design Objectives for Equipment to Control Releases of Radioactive Material in Effluents -- Nuclear Power Reactors," and 50.36a, "Technical Specifications on Effluents from Nuclear Power Reactors," of 10 CFR Part 50, "Licensing of Production and Utilization Facilities,"
set forth design objectives and technical specifications to control releases of radioactive efflu- ents from light-water-cooled nuclear power reactors.
 
Section 50.36a of 10 CFR Fart 50 further provides that, in order to keep power reactor effluent releases as low as is reasonably achiev- able, each operating license will include technical specifications that (a) require compliance with the provisions of § 20.106 dealing with effluent discharge limits, (b)
require that operating procedures for the control of effluents be established and followed and that eqi ipment installed in the radioactive waste system be maintained and used, and (c) establish re( :,-ements for reporting measured releases of radionuclides to the environment.


==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.
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.
To implement Appendix I, the NRC staff has developed a series of guides that provide methods acceptable to the staff for the calculation of preoperational estimates of effluent releases, dispersion of the effluent in the atmosphere and different water bodies, and estimation of the associated radiation doses* to man.
 
This guide describes basic features of these calculational models and suggests parameters for the estimation of radiation doses to man from effluent releases.
 
The methods used herein are general approaches that the NRC staff has developed for application in lieu of specific parameters for individual sites.
 
The use of site-specific values by the applicant is encouraged.
 
However, the assumptions and methods used to obtain these parameters should be fully described and dncumented.


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 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.


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.
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.


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


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


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.
C.


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.
REGULATORY POSITION
1.


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


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.
Potable Water MU1100
M
,n R
QiDaipjexp(-Xitp)
(1)
b.


11.109-I
Aquatic Foods Raj'1100 U apM pn*
-At2 Rapi
1100
F
QiBipoaipjexp(-Aitp)
(2)
c.


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.
Shoreline Deposits I
W n 0
Rapj = 110,000
I QiTiOai
[exp('Xitp)][l - exp(-'0t)]
d.


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.
Irrigated Foods For all radionuclides except tritium:
(3)
ap veg p n dIexp( A t )D
.
[r[l - exp(-AEite)]
Biv[l - exp(-xitb)]]
Rapj Uap I
i ih alpj L
YvEi
*J
Uanimal n
{QFd exp(Xith)
r[ - exp(-Eite)]
+ Uap SiA aipj YvxEi BivDl - ep-lb]
+
pexp(-itb)]
+ CIAwQAw}
(4)
For tritium:
Rp
-
vegC D
animal api = ap v apj + Uap Dapj L A"(w +QAw)
(5)
4
1.109-8


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.
where Bip is the equilibrium bioaccumulation factor for nuclide i in pathway p, expressed as the ratio of the concentratio., in biota (in pCi/kg) to the radionuclide concentration in water (in pCi/lizer), in liters/kg;
Biv is the concentration factor for uptake of radionuclide i from soil by edible parts of crops, in pCi/kg (wet weight) per pCi/kg dry soil;
CiAw is the concentration of radionuclide i in water consumed by animals, a:;sumed to be equal to Ciw (pCi/liter);
Ciw is the radionuclide concentration in water, in pCi/liter;
D aipi is the dose factor, specific to a given radionuclide i, pathway p, organ j, and individual's age a, which can be used to calculate the radiation dose from an intake of a radionuclide, in mrem/pCi, or from exposure to a given concentration of a radionuclide in water, expressed as a ratio of the dose rate (in mrem/hr) and the radionuclide concentration in water (in pCi/liter);
di is the deposition rate of nuclide i, in pCi/m2 per hr;
F
is the flow rate of the liquid effluent, in ft 3/sec;
k is the reciprocal of the body water volume (0.0041 liter-I for beef cattle and 0.0028 liter-I for dairy cattle);
Mp is the mixing ratio (reciprocal of the dilution factor) at the point of exposure (or the point of withdrawal of drinking water or point of harvest of aquatic food) as described in Table A-1 (in Appendix A of this guide),
dimensionless;
n is the number of radionuclides that are to be considered;
2 P
is the effective "surface density" for soil, in kg(dry soil)/m .
Assuming a uniform mixing of all radionuclides in a plow layer of 15 cm (6 in.) depth, P has a value of approximately 240 kg/mi2 ;
QAw is the consumption rate of contaminated water by an animal, in liters/day;
QF
is the consumption rate of contaminated feed or forage by an animal, in kg/day (net weight);
Qi is the release rate of nuclide i, in Ci/yr;
r is the fraction of deposited activity retained on crops (which is 0.25 for sprinkler irrigation, 0.2 for particulates, and 1.0 for airborne deposition of radionuclides), dimensionless;
R
.i is the total annual dose to organ j of individuals of age a from all of the RaPj nuclides I in pathway p, in mrem/yr;
Si is the transfer coefficient for radionuclide i which relates the daily intake rate by an animal to the concentration in an edible portion of animal product, in pCi/liter (milk) per pCi/day or pCi/kg (animal product)
per pCi/day;
t is the period of time for which sediment is exposed to the contaminated water, nominally taken to be the mid-point of the operating lifetime of the facility, in hours;
tb is the mid-point of the soil exposure time (15 years for a typical power reactor), in hours;
te Is the time period that crops are exposed to contamination during the growing season, in hours;
1 .109-9


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.
th is a holdup time that represents the time interval between harvest and consumption of the food, in hours;
T
is the radioactive half life of nuclide i, in days;
tp is the average transit time required for nuclides to reach the point of exposure.


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


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.
These equations yield the dose rate to various organs of an individual from the exposure pathways mentioned above.


a.    Potable Water R  . : 1100 UapMp    Q 0ai pjexp(-Xitp)                                        (1)
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.
            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
2.
                  + 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
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.
                  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.
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,
a.
  "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
Gamma Air Dose Rates for Elevated Releases
260
I
DA
-7(o n~~ un ns I(Ek)IE(H,u,s,oz,Ek ik
(6)
where Aki is the photon yield for gamma-ray photons in energy group k from the decay of radionuclide i, in photons/disintegration;
DY(r,o)
is the annual total gamma air dose at a distance r in the sector at angle 0,
in mrad/yr;
Ek is the energy of the kth photon energy group, in MeV/photon;
1.109-10
 
fns is the fraction of the time that stability class s and wind speed n occur for sector 0, dimensionless;
I(H,utsoz,Ek)
Is the result of the numerical integration accounting for the distribution of radioactivity according to meteorological conditions of wind speed (u) and.
 
atmospheric stability (s) which in part determine the effective stack height (H) and the vertical plume standard deviation (o).
In addition, I is a function of the photon energy E,1 and is T = 1 4 kT2 as formulated in Slade (see Reference I fi:
Appendix B of this guide);
'D
Qn 1 is the release rate of radionuclide i, corrected fnr decay during transit to the distance r under wind speed un, in Ci/yr;
r is the distance from the release point to the receptor, in meters;
un is the me;'n wind speed of wind speed class n, in m/sec;
AO
is the sector width over which atmospheric conditions are averaged, in radians;
and ua(Ek)
is the air energy absorption coefficient for the kth photon energy group, in m1 .
b.
 
Gamma Air Dose Rates from Ground-Level Releases; Beta Air Dose Rates from Elevated and Ground-Level Releases o3 Q
'/
)D r
( or DF')
Dy(r,o) or DO(r,0) = 3.17 x 1O4 I[/Q ](r,o)(OFi or
(7)
where DF'Y OF8 I' I
Dy(r,O) or D'(r,o)
Qi
[x/Q']O(r,e)
3.17 x lO4 c.


fns      is the joint frequency of occurrence of stability class s and wind speed class n for sector O,_dimensionless;
Total are the gar,.na and beta air dose factors for radionuclide I, in mrad per yr/
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);
pCi per n3 ;
              D
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;
              Dni    is the release rate of radionuclide i, corrected for decay during transit to the distance r under wind speed un, in Ci/yr;
is the release rate of the radionuclide I, in Ci/yr;
              un      is the mean wind speed of wind speed class n, in m/sec;
is the annual average gaseous dispersion factor (corrected for radioactive decay) at the distance r in the sector at angle o from the ,-elease point, in sec/m3 (see Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light- Water-Cooled Reactors," for methods to estimate x/Q'); and is the number of pCi per Ci divided by the number of seconds per year.
              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)
Body Dose Rates from Elevated Releases DT(r,a) = 1.11 SF I DY(ro)exp[-'T(Ek)t]
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;
(8)
    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;
where oT(r,e)
              Qi      is the release rate of the radionuclide i,    in Ci/yr;
DY(r,o)
  [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,
k is the annual total body dose at the distance r in the sector at angle a from the discharge point, in mrem/yr;
                      "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," for methods to estimate x/Q); and-
is the annual gamma air dose associated with the kth photon energy group at the distance r in the sector at angle 0 from the discharge point, in mrad/yr;
    3.17 x 104        is the number of pCi per Ci divided by the number of seconds per year.
1.109-11


c.    Annual Total Body Dose from Noble Gas Releases from Free-Standing Stacks More Than
SF  
            80 Meters High T                      yT
is the attenuation factor that accounts for the dose reduction due to shielding provided by residential structures (0.7), dimensionless;
            0 (r,o) = 1.11 SF   Dk(r,O)exp[-1Ja(Ek)td]                                      (8),
t is the product of tissue density and depth used to determine a "whole-body"
where DT (r,o)      is the annual total body dose at the distance r in sector 0, in mrem/yr;
exposure.
        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;
This depth is 5 cm, which is equivalent to t = 5 g/cm2 ;
              td      is the product of tissue density and depth used to determine a total body
T(Ek)  
                                        2
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.    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)
d.
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.
Skin Dose Rate from Elevated Releases oS(r,O) = l.1ISFOY(r,O) + 3.17 x 10 ' Qi[x/QJ]D(rO)DFS
(9)
F
where DFSi is the beta skin dose factor for the radionuclide i which includes the attenuation by the outer "dead" layer of the skin, in mrem-m 3/pCi-yr.


e.   Annual Total Body Dose from All Other Noble Gas Releases, DT(r,b) : SF
This attenuation is for 70 micrometers or 7 mg/cm2
* xi(r,e)DFBi                                                        (10)
.f tissue; and DS(r,0)  
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;.
is the annual skin dose at the distance r in che sector at angle 0 from the discharge point, in mrem/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.
All other parameters are as defined in preceding sections.


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.
e.


Total Body Dose Rates from Ground-Level Releases D (r,e) = 1.11 SF
* xi(r,o)DFBi (l0)
where DFBi is the total body dose factor for the radionuclide i which includes the attenuation of 5 g/cmn2 of tissue, in mrem-m 3/pCi-yr (see Table B-l in
4 Appendix B of this guide);
DT(r,)
is the annual total body dose due to immersion in a semi-infinite cloud at the distance r in the sector at angle 0 from the discharge point, in mrem/yr; and xi(r,e)
is the annual average ground-level concentration of nuclide i at the distance r in the sector at angle 0 from the release point, in pCi/m 3 .
All other parameters are as defined above.
All other parameters are as defined above.


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


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


Not including noble gases.
All other parameters are as defined above.


1.109-6
3.


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)
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.
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)
i
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;
1.109-12
            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..
a.
        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)
External Irradiation from Activity Deposited onto the Ground Surface Dý(r,0) = 8760 SF
where Cv(r,D), CF(r,o),
G
CL(r,o),
cG(r,o)DFG..  
1.
(12)
where CG
is the ground plane concentration of radionuclide i, in pCi/m 2;
Ci DFGij is the open field ground plane dose conversion factor for organ J from radio- nuclide i, in mrem-m 2/pCi-hr;
DG(r,O)
is the annual dose to the organ j from the ground plane concentration of all radionuclides at location (r,o), in mrem/yr;
SF
is a shielding factor that accounts for the dose reduction afforded by the shielding provided by residential structures and by occupancy, dimensionless;
and
8760
is the number of hours in a year.
 
b.
 
Inhalation DA (r,o)  
R
R  
xi(r,o)DFAi
(13)
where O (rO)  
is the annual dose to organ j of an individual in the age group a at location
*
CrO) due to inhalation of all radionuclides, in mrem/yr;
DFA. a is the inhalation dose factor for radionuclide i, organ j, and age group a, ija in mrem/pCi;
3 Ra is the annual air intake for individuals in the age group a, in m /yr; and xi(r,o)  
is the concentration of radionuclide i in air at location (r,o), in pCi/m 3 .
c.
 
Ingestion o r v
m
.FL
L
1)
a (ro=  
2DFIi -
cV(r,+)  
+ UaCim(r,o) + U.i(r,o) + Uaf Ci(r,  
(14)
D. (ro)ja
[I a 9 i a
ai
+ a z
(4 where
,CF(r,O),
C.(r,o), C.(r,O)
are the concentrations of radionuclide i in produce (non-leafy-vegetables, fruits, and grains), milk, leafy vegetables, and meat, respectively, at location (r, o), in pCi/kg.
 
These variables are determined using Equation (C-7) from Appendix C of this guide;
D3 (r,o)  
is the annual dose to the organ j of an individual in age group a from inges- ja tion of all radlonuclides at location (r,o), in mrem/yr;
DFlija is the ingestion dose factor for radionuclide i, organ j, and age group a, from Tables A-3 through A-6 of Appendix A of this guide, in mrem/pCi;
f ft are the respective fractions of the ingestion rates of produce (vegetables, fruits, and grains) and leafy vegetables which are produced in the garden of interest (Note:
fg may be taken to be 0.76 in the absence of site-specific data which would indicate that the quantity of grain produced in the garden of interest would satisfy the intake values in Table A-2 of Appendix A of this guide); and U
Uvn, Um
, UF
are the annual intake (usage) of vegetables, milk, meat, and leafy vegetables a
Ua'
a a respectively, for individuals in the age group a, in kg/yr.
 
1.109-13
 
4.
 
Inteqrated Doses to the Population The NRC staff will calculate integrated doses to the local population from all pathways discussed in Sections C.1,
2, and 3.
 
Because of the various conditions under which the equa- tions in Appendix D are used, they are not presented in this section.
 
It is recommended that Appendix D be read for a detailed discussion of the staff's models.
 
5.


C.(r,)
Summary of Staff Position A brief summary of the staff position on methods of evaluating compliance with Appendix I
              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;
is presented in Table 1.
            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..
D.
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==
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.
This guide reflects current Nuclear Regulatory Commission practice.
 
Therefore, except in those cases in which the license applicant or licensee proposes an acceptable alternative method, the method described herein for complying with specified portions of the Commission's regulations is being and will continue to be used in the evaluation of submittals for operating license or construction permit applications until the guide is revised as a result of suggestions from the public or additional staff review.
 
II
I
1.109-14
 
TABLE 1 SUMMARY OF STAFF POSITION -
TYPE OF DOSE
Liquid Effluents Dose to total body from all pathways Dose to any organ from all pathways Gaseous Effluents**
Gamma dose in air Beta dose in air Dose to total body of an individual Dose to skin of an individual METHODS OF EVALUATING
APPENDIX I
DESIGN OBJECTIVE
3 mrem/yr per unit
10 mrem/yr per unit POINT OF DOSE
EVALUATION
COMPLIANCE WITH APPENDIX I
EQUATIONS
TO BE USED
Location of the highest dose offsite*
(see also Table A-I).
Same as above.


public or additional staff review.
1, 2, 3,
4,
& 5
1, 2,
3,
4,
& 5
10 mrad/yr per unit
20 mrad/yr per unit
5 mrem/yr per unit
15 mrem/yr per unit Location of the highest dose offsite.***
6 or 7, as appropriate Same as above.


1.109-8
7 Location of the highest dose offsite.*
Same as above.


w
8 or 10, as appropriate
                                                                                                                                                              -*~-<~
9 or 11, as appropriate Radioiodines and Particulatest Released to the Atmosphere Dose to any organ from all pathways
                                                                            TABLE 1 SUMMARY OF STAFF POSITION -
15 mrem/yr per unit Location of the highest dose offsite.,'
                                                        METHODS OF EVALUATING COMPLIANCE WITH APPENDIX I
12,
                                            APPENDIX I*                              RM-50-2              POINT OF DOSE                    EQUATIONS
13, & 14 Evaluated at a location that is anticipated to be occupied during plant lifetime or evaluated with respect to such potential land and water usage and food pathways as could actually exist during the term of plant operation.
  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.


-v        --~*-.--~~ -- ---        --      --      ------ -
Calculated only for noble gases.
                                                                                                            *
                    ___________________________________________


TABLE 1 (Continued)
Evaluated at a location that could be occupied during the term of plant operation.
                                                    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.
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.


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


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:
1.109-15
    (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 LIQUID EFFLUENT PATHWAYS
METHODS FOR CALCULATING DOSES TO MAN FROM RADIONUCLIDE
      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.
DISCHARGES TO THE AQUATIC ENVIRONMENT
The equations for estimating radiation exposure to man from four principal exposure path- ways in the aquatic environment (potable water, aquatic foods, shoreline deposits, and irrigated foods) are listed in Section C, "Regulatory Position," of this guide.
 
The equations can be used to calculate the annual doses to various organs of a child, 0 -
11 years; a teen,
12 -
18 years;
and an adult, 18+ years.
 
1.


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


Equation (A-l) is the generalized equation for calculating the radiation dose to man via liquid effluent pathways.
aipj C ip Uap aipj (A--)
where Cip is the concentration of nuclide i in the media of pathway p, in pCi/kg;
D ai is the dose factor which is specific to a given radionuclide. i, pathway p, organ j, and individual's age a.


Raipj    Cip UapD aipj                                                            (A-1)
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;
where C.        is the concentration    of nuclide i in the media of pathway p, in pCi/x, pCi/kg, or pCi/m 2 ;
Raip is the annual dose to organ j of an individual of age a from nuclide i via apip pathway p, in mrem/yr; and U ap is the exposure time or intake rate (usage) associated with pathway p for lap
                                                                                              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
.ge group a, in hr/yi or kg/yr (as appropriate).
                                                                2
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.
                        '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..
1).
      b.    Usage (U      Y.
(An updated version of the portion of the WASH-1258 report describing models and computer programs is contained in the BNWL-1754 report (Ref.


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.
2).)
a.


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.
Concentration in Environmental Media (Cip)
The points at which concentrations in environmental media of interest should be evaluated are shown in Table A-1.


c.  Dose Factor (Daipj Dose factors for internal exposure via ingestion are provided in Appendix E, Tables E-ll,
The concentrations can be estimated from the mixing ratio M p , the bio- accui;&#xfd;ulation factor Bip, the radionuclide release rate Qi, and other terms presented in the path- way equations that appear later in this discussion.
  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.
b.


1.109-11
Usage&#xfd; (Uap)
The second term of Equation (A-l)
is the usage term U ap.


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.
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 doses from the four pathways should be added to determine the total dose.
The NRC staff encourages the use of site-specific data, whenever possible, for param- eters such as those included in Table A-2.


a.  Potable Water The annual dose from ingestion of water is calculated from Equation (A-2) below:
Such data should be documented.
          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.
In the absence of site-specific data, however, the usage values (consumption rates and exposure times) presented in Table A-2 are reconmnended.*
In selecting usage values, not only the present land and water uses should be considered, but also changes in land and water uses made possible by such activities as chemical pollution abatement.


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.:,
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 --
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."
perhaps beyond the lifetime of the nuclear power station.
      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
1.109-17
          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.
TABLE A-I
DEFINITION OF POINTS AT WHICH CONCENTRATIONS IN ENVIRONMENTAL MEDIA (C ip)
SHOULD BE CALCULATED
SUBMERGED (single or multi- PATHWAY
SURFACE -
LOW VELOCITY
SURFACE -
HIGH VELOCITY
port) -
HIGH VELOCITY
Fish (fresh and salt water)
Invertebrates Shoreline Drinking water CO
Discharge canal Discharge canal Discharge canal Nearest anticipated downstream supply***
Nearest anticipated point of withdrawal for irrigation t Edge of initial mixing zone*
Edge of initial mixing zone*
Point of contact of diluted effluent with shoreline Nearest anticipated downstream supply,*
Nearest anticipated point of withdrawal for irrigation +
Edge of initial mixing zone**
Edge of initial mixing zone**
Point of contact of diluted effluent with shnreline Nearest anticipated downstream supply***
Nearest anticipated point of withdrawal for irrigation- Irrigated crops Point where effluent has Point where effluent has Fresh water sites only.


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.
over the plant lifetime, AFresh water sites only.


1.109-12
use projections over the or could exist.


TABLE A-1 BIOACCUMULATION FACTORS TO BE USED IN THE ABSENCE OF SITE-SPECIFIC DATA
undergone prompt dilution near the surface (about 5:1 for large receiving water bodies).
                              (pCi/kg per pCi/liter)*
undergone prompt dilution (about 10:1 in deep water and about 5:1 in shallow water).
                            FRESHWATER                        SALTWATER
The "nearest anticipated downstream supply" is that loc3tion which, based on land use projections is the closest point to the site where a drinking water supply exists or could exist.
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.
The "nearest anticipated point of withdrawal for irrigation" is that location which, based on land plant lifetime, is the closest point to the site where withdrawal for irrigation purposes exists
____


Data taken from Reference 7.
PATHWAY
Fruits & vegetables Leafy vegetablesa Milka,c Meat & poultrya Fish (fresh or salt)
Sea fooda Drinking waterc'e Shoreline recreation e
Boating Inhalation TABLE A-2 RECOMMENDED VALUES FOR Uap TO BE U
EXPOSED INDIVIDUAL IN LIEU OF S]
CHILD
& graina'b
520.0
26.0
330.0
41.0
d
6.9
1.7
510.0
5 e
14.0
29.0
2 7 00 . 0 e
51
190P.O(infant)g SED FOR THE MAXIMUM
ITE-SPECIFIC DATA
TEEN
ADULT
630.0
520
P?.0
64
100.0
310
65.0
110
16.0
21
3.8
5
510.0
730
67.0
12
52.0
52
,O0.,e
73 0 0 f UNITS
kg/yr kg/yr liters/yr kg/yr kg/yr kg/yr liters/yr hr/yr hr/yr m 3/yr aconsumption rate obtained from Reference 3 for average individual and age-prorated and maximized using techniques contained in Reference 4.


1 .109-13 Iii iiI
bconsists of the following (on a mass basis):
22% fruit, 54% vegetables (including leafy vegetables), and 24? grain.


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:
CAn additional category of maximum individual (1-yr old) should be added for these pathways.
            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)
Consumption rates are the same as the child's.
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.
dConsumption rate for adult obtained by averaging data from References 4, 6-9 and age-prorating using techniques contained in Reference 4.


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.
eData obtained directly from Reference 4.


Rapj    = Uap        aipj i.D    =  100 UapW    C Ti Daipj[l - exp(-xitb)]                  (A-6)
fData obtained directly from Reference 15.
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
glnhalation rate for infant obtained by averaging data from References 10-14.


TABLE A-2 SHORE-WIDTH FACTORS FOR USE IN EQUATIONS (A-5),    (A-6),  AND (A-7)
1.109-19
                    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).
C.
                  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)
Dose Factor (D aip.)
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.
Equations for calculating internal dose factors are derived from those given by the International Corninission on Radiological Protection (ICRP-Ref.


For a cow grazing on fresh forage, te in Equation (A-8)     is set equal to 720 hours
15) for body burden and ma):imur permissible concentration (r.IPC).  
(30 days), the typical time for a cow to return to a particular portion of the grazing site (Refs. 3 and 12).
Effective absorbed energies for the radionuclides are calcu- lated from the ICRP model.
                  For tritium, the equation for estimating Civ is (see Ref. 13):
                      Cv = Cw                                                              (A-10)
                                                  1.109-15


Jull
Appendix D of Reference 16 was used as a basic source of age-dependent dose factors for ingestion.
                      (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)).
Where data are lacking, metabolic parameters for the Standard M~an were used for other ages as well.
                            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
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.


Similarly, the above equations for tritium concentration can be combined with the general Equation (A-1):
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.
                                                                                    (A-16)
          R
          apj
                =vegCD
                  ap v apj
                            + uanimalc ap      ADapj
                                              1.109-17


REFERENCES FOR APPENDIX A
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.
        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.
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.


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.
A set of dose factors for 45 radionuclides was originally calculated for the year 2000
model (Ref.


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.
4).  
These factors have since been recalculated using recent decay scheme informia- tion (Ref. 18) and expanded to include additional radionuclides.


*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 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.


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.
2.


7.  H. A. Vanderploeg et al., "Bioaccumulation Factors for Radionuclides in Freshwater Biota,"
Equations for Liquid Pathways This section develops the set of equations required for the liquid pathway m:iodel.
            ORNL-5002, Oak Ridge, Tenn., November 1975.


8.  G. G' Kilaugh and L. R. McKay, "A Methodology for Calculating Radiation Doses from Radio-*
Tie principal difference betveen pathways is the manner in which the radionuclide concentrations are calculated.
            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.
The doses from the four pathways should be added to determine the total dose.


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.
a.


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.
Potable Water The annual dose from ingestion of water is calculated from Equation (A-2) below:
Rapj = 1100
U ap Qjexp(-x. .t )Daipj (A-2)
apF
1 p aipj Symbols for this equation were defined earlier, in Section C.] of this guide.


12.. J. J. Koranda, "Agricultural Factors Affecting the Daily Intake of Fresh Fallout by Dairy Cows," USAEC Report UCRL-12479, 1965.
The sunmation process adds the dose contribution from each nuclide to yield the total dose for the pathway-organ combination selected.


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.),
The Q!/F termis in Equation (A-2) define the concentration of nuclide i in the effluent at the point of discharge.
            CONF-710809, 1973.


1.109-18 ti 1/4..
The expression (QMM /F)exp(-A t ) yields the concentration of nuclide i at the time the water is consumed.


APPENDIX B
I p i p This concentration is the term Cip in Equation (A-1).
                                        MODELS FOR CALCULATING DOSES FROM
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.
                                      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:
The transit time should be increased as appropriate to allow for travel from the point of effluent release to the water purification plant intake.
          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.
Credit may be taken for radionuclide removal by water purification processes using techniques such as those outlined in Reference 4.


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)
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.
                        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)
In those instances (e.g.,
                        Q                                                                      (B-3)
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.
    ., 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
with any potential effluent recycling taken into account.


where Qi    is the initial release rate of nuclide i,   in Ci/yr;
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
                r    is the distance from the source to the receptor, in m; and is the decay constant of nuclide i,        -I
implementing Appendix 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)
b.
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)  =
Aquatic Foods The concentrations of radionuclides in aquatic foods are directly related to the concentrations of the nuclides in water.
* 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.
Equilibrium ratios between the two concentrations,
1.109-20


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.
TABLE A-3 ADULT INGESTION DOSE FACTORS
(mirem/pCi ingested)
'JUCLIDE
BO.E
I
3
0.0
4BE
10
3.l18-06 bC
14 P.BUE-06
7N
13 B.37E-09 QF
IS
b.2SF-07 IPJA
22
1.70F-05 IlIA
24
21,2OF-Ob
1 5P
32
1.Q3F-04
20CA
ul
1.87E-0'J
21SC
Ub.


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).**
5.SIF-OQ
      a.   Releases from Free-Standing Stacks More Than 80 Meters High The annual total body dose is computed as follows:
24CP
          DT(r,e) =  1.11 x SF I DY(r,O)exp[-T(Ek)td1                                  (B-6)
51 o.0
  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.
254.4 a  
n0
25mN
5b
0.0
2hFE
55 b.20E-0O
2bFE
59 U.3UE-0b
27Cf0
57
0.0
27C0
5B
0.0
27C0
60
0.0
28,NI
59
9.77E-06
28N1
63
1.30E-O0
284I
b5
5,20E-07
2qCU
b4
).0
30ZN
65 U.SE-06
30ZN
b94
1.70F-07
30ZN
b9
1.03E-08
34SE
79
0.0
35RP
A?
n.0
355P
93
0,0
35.P
84
0.0
35BR
85
0.0
37RB
0b
0.0
37BR
87
0.0
37RB
48
0.0
37RR
89 n.0
38SR
B9
3.09F-0'J
3BSR
QO
7.61F-03
3RSR
91
5.82F-Ob
38SR
92
2.IbE-Ob
39Y
go
9.63F-09
39Y
91M
9.10E-11
39Y
91
1.alE-07 LTVER
1.34E-n7
4.91E-n7
5.69E-07
9.37E-09
1.0
I .74E-05
2.?bE-0b
1. 21 E-05
0.0
I .nBE-08 S.57E-o6 I . I9E-07
2.79F-oS
1 .03E-09
.7 5 -07
/ . I, SE -{') 7
2. 15E-0b
3. 35E-O0
9.02E-O0
b.B7E-ng
5.3'JE-06
1 .54F-05 u .0, E-07
1 9SE-08
2. 6I-06
0.0
0.0
0.0
0.0
?.11 F-05 I .?3E-OS
6.06F-()8 U.0 1IE-O8
0.0
0.0
0.0
0.0
0.0
0.0
0.0
TnTAL 81)Y
1 .3UE-07
7.o5EF-0
ri.bqE-7
&#xfd;. 37E-09 b.93E-OR
I .74E-05
2.2hE-rib
7, *
7F.-t0h
2. olE-nS
3.11 E-OQ
2.bbE-19
.8 73E-.07
2. 0SE-OR
7.33E-06
3.9?E-06
2.JI1E-07 I .67E-1b U,72E-nb I .b3E-06
4.36F-Ob
3.1 3E-08
3.92E-OR
6.97E-08
3.731E0'
I .37E-0O
M.dOE-07
2.?PhE-n6
4 .
2E-n&#xfd;,
5.22E-O0
2.1 4E-O9
9.8UE-0b
4.28E-4b
3 . 21 E-04
2.93E-0.


See discussion in Appendix E, Section 3.
5.89F-06 I .86E-03 P.ShE-07
9.31E-08
2.5RE-10
3.53E-I?
3,7RE-09
1,i 3lI-O1 n n
5, qF -07
*l
3 7EF- 0 9 n.n I .711E-05
22.2SE-0b
0.n
1.S5QF-0*
0.0
n n
0.0
0.0
n.0
0.0
0,0
0.0
(
n
0,0
0.0
0.0
0.0
0,0
0.n
0.0
0.0
0.0
0.0
0,0
0.0
0.0
KT)NEY
I, S.


1.109-20
3 E-fl7
3. 71E-n7
5.69F-07
8. 37E-ng
0.0
I . 74E-nc
22.


TABLE B-I
?6F.-06
        DOSE FACTORS FOR    EXPOSURE TO A SEMI-INFINITE    CLOUD OF NOBLE GASES
0.0
Nucl ide      B-air*(DF )      B-Ski n* * (DFSi)    y-Air*(DFW)        y-Body**(DFBi)
0.0
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
I .OOF-0B
  *        3 mrad-m pCi-yr
36RIE-06 l,6bE-07
**        3 mrem-m pCi-yr
0.0
    2.88E-04  =  2.88 x 1O0
0.n
                                            I .109-21
0.0
0.0
0.0
0.0
0.0
? 1 n F - n
1 03E-nS
?. USE- n7 I ?O2F-OR
41, 5 6F. -n6 n00
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
LUNG
I .,OE-07
0.0
S.bqE-07
'. $7F-09
0.0
I . 74E-05
>. ?6*E-..0
0.0
,0.


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).
3. 53F-n9
          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)
0.0
                                                  .i Symbols for this equation are defined in Regulatory Position C.2.d of this guide.
0.0
1.23E-05
-nb
0.0
,00
n0.


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.
0.0
0*,0
0,0
0 . n
0,0
0.00
,00
0.0
0.0
0.0
n00
n,0
0,0
0.0
0.0
0.0
0.0
0.0
0.0)
0.0
GI-LL I
I . SiF-n7
2.bMF-0'i
5.bQE -07
6. 371F-09 I ASE-05 P. 26F-Uh
2.1I 7E -09 I ..&#xfd;JF -0i7
5.21F -05
1 . ttIE -07
3.h7F-O6 I . oW -05
5.4OF-06
1 .91F-05
,022F-OS
b790E-07 I1 .t i B F - O h
7 .i O-06 Q.70E-(6
2.49F-05
2. 9b-09
5, 38F-07
2.54F-Ob
.,79F-OR
u0nqF-13
0.0
4, 1bE-Oh
5. 7(E-07
8.3bF-19
0.0
MI,*4E-05 I .02E-nu
2.Q3E-05
4 , 2bf -05
1.02E-04
2,b7L-1 0
77bE7-05 Note;
0.0 means insufficient data or that the dose factor is <].OE-20.


b.   All Other Releases The annual total body dose is computed as follows:
1.109-21
          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:
TABLE A-3 (Continued)
          D0(r,e)   1.11 x SF    xi(r,O)DFW + ! xi(r,e)DFSi                          (B-9)
NUCLIDE
          Symbols for this equation are defined in Regulatory Position C.2.f of this guide.
39Y
92
39Y
93
4OZR
93
0OZR
95 a0ZR
97
14tN
q33
41.J
N
5 QLNB
q7 u2mO
q3
4240
9q
43TC
994
43TC
q9
43TC
101
44RIJ 103
40RU 105 LILRU 106
45RH 105
46PD 107
6bPD 109
47AG 1104 L7AG III
48CO 1134
48Co 1154
50SN 123
50SN
125
50SN
126 SISB 124 S1SB 125 SISH 12b SISB 127
'52TE
1254
52TE 127M
52TE
127
527E 12qM
52TE
129
.52TE 1314
52TE 131
52TE
132
52TE
1334
52TE 134
531
129
531
130
531
131
531
132 BONE
8.46F-10
2.6E-09
4 . IqF-08
3.0UE-OR
I.68F'-09
2.55E-08 b,2sF-09
5.23E-1 I
0.0
0.0
2.47F-10
I 2bE-07
2.54F- 10
1 .85E-07 I .S4E-08
2.75E-O0
1 .22E-07
0.0
0.0
1.6bOE'-07
5.82E-0R
0.0
0.0
3.1 IF-05
8. 3bE-06
8. U6E-05
2.81E-06
2.23F-Ob
1. 15F-Oh
2.5E-07
2.b8E-Ob
6.78E-06 I 1 IOE-07
1015E-05
3. ISE-08 S1,74E-06
1.97E-08
2.53E-05
4.63F-08
3.24F-08
3.27E-Ob
7,57E-07
4, tl6E-06
2.03E-07 LIVER
0.0
0.0
2.3uE-Oq
9.76E-09
3.39F-10
S. 33E-09
3.46RE-09
1.32E-1 I
7.52E-nb U,31E-0b
6.98E-I0
1 .8hF-07
3.67E-1 0
0.0
0.0
0.0
8.86E-08
1 .47E-07 I .77E-07
2!.'JRE-07
2.44LE-08
3. 1qF-Db I .84E-0b
5.16E-07
1 .6AF-n7
1.68E-Ob
5.30E-00
2.4nF-08
2,3'E-n8
5.bhE-09
9.73E-07
2.37F-Ob
3,95E-08
4L,30E-06
1. 19E-0FB
9, 47E-07
5.24E-09
1.6LAF-0b
2.80E-08
2, 13E.-08
2.8lE-Oh
2.2*iE-06 S. 96E'-06
5.43E-07 TOTAL BODv TH)ROID
2.07E-1I
0.0
7.40E-11 n.,
1.09E-09
0.0
6.61E-09 n.0
1.56E-10
0.0
2.05E-09 o0n
1.36E-nq n.n L.e2E-12
0.0
2.03E-07
010
8.20E-07 A.('
9.9nE-Aq n.0
5.OUE-08 o.n
3.60E-19 n.0
7.qgE-0R
0.0
6.ORE-Oq
0.0
3.48E-07
0,0
S.SIE-OR
0.0
9.UIE-Oq
0.0
U.OOE-08
0.0
4.80E-04
0.0
1.21E-0B
n.0
1.02E-07
0.0
5.AgE-OR
0.0
7,6OE-07 L.38F-07
3.79E-0 7 
1.39E-07
2.JIE-06
4,92E-07 I.IIE-0.b
6.79E-09
4.J8E-07
1.9BF-09 U.ISE-07
7.0SE-09
9,q2E-0M
3,IIE-09
3.59E-07
8.07E-07
9.26E-07
1.73E-06
2.3AE-OR
8.16E-0B
1.82E-06
3.qSF-06
7.66E-09
2.IE-0B
7.06E-07
1.34E-06 b.22E-O9
1.62E-OR
1.51E-06 I.BOE-06
4.06E-08
3.92E-03
1.3nE-0'
2.,3E-05
9.22E-0b
7.23E-03
8.R1E-07
2.85E-OIA
3.41E-06
1.95F-n3
1.93E-07
7.15E-05 KIDN EY
0.P
0.0
8.99E-O9 I .SUF-08
5 1 P .E - 10
5,58E-09
3. U 5 E-0q I .5AE-1 I
I O0hF-AR
2,34E-nb
().bOE-09
7.07E-n7
1 .'9E-07
5.32E-0b
3.76F-07
1 .. 32E-06 I .02E-O1
2. 91E-n7
7.8SF-nA
3.50F-nb I4.6F-06
0.0
0.0
0.0
0.0
0.0
0.0
I .09E-05
2.75E-05 LAI*,LRE-07 Li,.!lE-n5
1.3?E-n7
8.5E-06 R.b'E-nf
1,58E-05
2.57E-07
2.09E-n7
60 OSE-(b
3.UIE-Oh I. O.E -05
, bhE'-07 n.0
0,0
0.0,00
0.0
(0,0
0.0
0.0
0.0I
1 ,S2E-10
I .9SE-OP
0.0
*.0
(1.0
0.0
0.0
0.0
0,0
0.0
2.1 8E-Ob
2.33F-04
7,05E-n7 I .53E-n7
0.0
0,0
0.0}
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
Gl-I.Ll
9
* SO F -6C'5
2.U3f -Oh I O5E -na
3,RU*-no
2.1 OE -05 t.SiF-05 U *
7 F-OR
I .b??F -n,
,153F-n7 b.08F -('6
1bF-05
7 6
7E -('74
1,07Et-O5 b.


0Laf-it,
2.2bF-n5
7 . 7 a"E
- r* S
b. 33E-05
2.'3E-0S
7.95F-O5 I .97F-O0
9.40F-05 S QO2E-nh-
1,07E-05
?.27f -15
8. b8F -Ph
2. 37Fl-08
9.4
&#xa3;0E-05
7.*71 F-05 Li. I 7F -00
1
.92E-nt, I .57F-I~b
1 . n2E-07 I
1.109-22
1.109-22


REFERENCES FOR APPENDIX B
TABLE A-3 (Continued)
        1. "Meteorology and Atomic Energy 1968," D. H. Slade (ed.), USAEC Report TID-24190,   1968.
SUCLIDE
531
133
531
134
531
135
55CS
13U
5SCS 135
55CS 13b
55CS 137
55CS 135
55CS
139
569A
139
5654 1 a 0
5bBA
IUI
Sb8A
IUP
S7LA
1UO
57LA
I U1
57LA
IL2
58CE
I U
5CE 143
58CE
tUQ
S9Pq 143
59PR 10I4
6OND
lU7
6IPM &#xb6;LI7
61PM I aB7
6IPM
tuB
61Pm 151
62SM
151 b2SM 153
63EU 152
63EU 154
63EU 155 b3EU 156
65TB IbO
b740 16bM
74M~
191
740
185
744
187
52PH
P O
8381 210
84PO 210
BONE
1.43F-06
1 ObE-07
4.43F-07
2.1 3E-09
6.2?F-05 I q.F-05 b.51F-ob
7.98E-05
5. 5F-08
3.&#xa3;4 F-Os
0 . 7 1 F-O0S
2.03E-05
0.0
P. 13E-08
2.SOF-OQ
3.19E-10
1.28E-10
q,3 IE-Oq I.%5E-09 u.BQE-07
9.21E-09
3.02E-1 I
h.30E-oq
7.55E-08
3.07E-08
7, 1BF-09
1 .52E-09
.
l9
7F-I 0
6.91E-08
8.5RF-IO
I .q5E-O7
6. 1bE-07
5.61E-08 I . 37F -08
4.70E-08
2.70E-07
9.9?E-09
40.bE-07 I .03E-07 I .53F-02
0.b2E-07
3.57E-OU
LIVER
2.USF-06
2.SRE-07 I . I 7E-06
'J' (IQE -0B
1I USE -04.
 
I 80E-a5
2.57E-o5 I. .OE-0O
I. OoF-o 7
5.08F-08
5.92E-I I
2.55E-08
3.56E-i 1
2. 19E-1 I
I .26E-O9
9.91E-1l
5.82E-11
6, 3&#xa3;4E-09 I.22E-O0
2,uE-07
3 . 70aF.-O0
I .25E'-11I
7.28E-09
7 .10 E -09
7.96E-09 I . I9E-09
2. 1SE-I 0
1.1 7E-1 0
1.1I9E-0B
7.16E-1 0
U1 ,L"JE-OB
7o.7E-08
1 .22F -n8 I .ObE-0
0.0
13.44E-09
3.24E-09 I. 35E-07
8.62E-08 U.38E-03
3.19F-Ob
7.57E-o0
TOTAL RODY
THYROID
KIDNEY
7.57E-07
1.03E-n7
(429E-n7
?. 3nE-os
1.21E-OU
8.OOE-06 I .85E-05
7. 1SE-05 S.. iE-ns I .SE-08
2,84E-09 I .3E-06
1.59E-09 I .3UE-09
3.30E-10
I .62E-1 I
1 .&#xa3;4S5- 11
7 .18E-10
1.3SE-10
2.bE-08
4,57E-10
1.53E-12
4.35E-I0
2.P7E-Oq b.OSE-09
6.OOE-t0
S.7qE-1 I
5.92E-1 I
2.BbE-09
5.23E-1 I
3.9IE-O0
5.39E-08
7.88E-0Q
I .71E-ng
5.FbE-09 bAlE-08
3.46E-10
1.4?E-08
3,02E-08
5. &#xa3;E-Oa
3.97E-08
8.60E-n5
4.77E-04
3. 74E-05 I .5jE-n0
D.0
0.0
0.(I
0.0
0.()
0.0
0.0
0.0
0.0
0.0
0.0
0*.0
0I.0
0.0
0.0
0.0
0.()
0.0
0.0
0.0
0.0
0 .0
0.0
0.0
0.0
0.0
0.0
0.0
0&deg;0
0.0
0.0
(0.0
0 .0
0.0
0.0l
0.0
0.0
0.0
0.0
4. 33E-flb
'.*5 E-9
07
1. 86E-.nh
2. 4 E .. n
&#xa3;4. OE..0n I , 3E..n5
3. 71E'.-)5
8.02E.-n8
4.07E-08
6.&#xa3;7E-- I
R.6bE-09
3.3tIF-I
1.,SFE-II
I,.95E-1t
0.0
0.0
0.0
5.3.E-10
I .21E-07
2. 1 3E-09
7. 06E-1 2 I.25E-09
1I1 3UE-08
1 .2 1IF-O0S
2.25F-09
4.O7-1 0
2 . 0 9 F -1
1 . 33E-08
2.3?F-10
2.775E-07
3.621--07
5.,LIE-rib
7.09E-09 I.94E-08
1.26E-07
0.0
0,0
0.0
1.23E-n2
3. 84E-05
2.52E-03 LUNG
0.0
0.0
0.0
3.83E-
2,OSE-(
I .S9F-
I ,23E-
1 .Q2F-
3.70E-
3.92E-
I '46F-
2, 02E-
I .2UE-
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
*00
0.0
0.0
0.0
0.0
0.0
GI-LLI
2. 18EOb
2.51F-1 0
1.31E-06
09
1.58E-08
05
2.%9E-O0
06
4.. 21F-07
06
2.92E-0b OS
2.10E-06
09
4.65E-13
09
0.0
11
1.72E-07
08
&#xa3;*418E-05
11
2,22E-17
11
0.0
Q,25E-OS
4.25E-07
2,42E-05
4,S6E-05 I bSE-OS
4,03E-05
4.33E-18
3.49E-05
8.93E-06
6. 7E-05
9.34F-05
*,03E-05
3,22E-n5 S *25E-Ob
2,55E-05
2.56E-05
5.48E-05
9,60E-O0
7.26E-05
4.33E-05
0.0
*.bSE-07
1,56E-05
2,82E-05
5,42E-05
4.75E-05
6,36E-05
1.109-23


2. M. J. Martin, "Radioactive Atoms,  Supplement I," USAEC Report ORNL-4923, November 1973.
TABLE A-3 (Continued)
NUCL
B8RA
88RA
8BRA
88RA
B8RA
B9AC
89AC
90TH
90rH
90TH
90TH
90TH
90TH
91PA
91PA
92UL
92U
92U
92U
92U
92U
92U
93NP
93NP
93NP
9'PU
94PU
9UPU
9IJPU
guPU
9JPU
95AM
95AM
95AM
96CM
96CM
96CM
96CM
96CM
96CM
9bCM
98CF
IDE
BONE
223
4.q8E-03
224
1.b2E-03
225 h.57E-03
226
3.05F-01
228
1.12F-01
225
4.


3. M. E. Meek and R. S. Gilbert, "Summary of Gamma and Beta Energy and Intensity Data," NEDO-
-1F-06
            12037, 1970.
227
1.88E-03
227
1.37E-05
229
4.96F-OU
229 R.ObE-03
230
2.08E-03
232 l.SOE-03
23Q
.9.02F-08
231
4.I4F-03
233
5.26F-09
232 u.l4E-03
233
8.7?E-0O
234
8.37F-014
235
8.02E-04
23b
8.02E-O4
237 S.53F-08
238
7.67F-OU
237 l.38E-03
235
1.37E-08
239
1.20E-09
238
6.7SF-OU
239
7,60F-04
240
7.58E-04
2U1
1.5bE-05
242
7.22E-04
2L4L
9.60E-0O4
241
8.IOE-04
2Q2M
8.32E-0O
2i3
8.12E-0O
2U2
1.58E-05
243 b.43E-0O
244
4.851-04
24S.


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.
1.03F-03
2U6
1.02F-03
247
9.95E-04
2'8
8.27E-03
252
1.96E-O4 LIVER
7.bbE-Ob
3.90E-Ob
7.79E-06
5.75E-06
3.1?E-06
6,07F-06
2. *8E-OU
2.4BE-07
3.41E-06
1.21E-O04
1 I1 BE -O04 I .OIE-04
4.*72F-09 I.56E-0l I .0bE-09
0.0
0.0
G00
0.0
0.0
0.0
0.0
1.20E-O0
3i,6E-10
1.18E-1O
. 31E-05 I
OMiE-OQ
1,04iE-04S
9.4l7E-07
990E-05 I I 1BE-O4
2.79E-04i
2.78F-00
2.7 3E-O0i I .64E-&#xfd;05
2.QIE-0OJ
2.07E-04
2.B8E-O0
2. 88E-04
2. B3E-O0
2. 33E-03
0.0
9.95E-OU
3.23E-04 I .31E-01
2.21E-01
1.21E-01
2,QsE-07 I I II E-0Q
3.96E-07 I.b8E-AS
3.95E-O0
5.76E-05
.4,9?E-05
2.32E-09 I .61E-Ou Q,2AE-In
2.95E-04
5.29E-05
5. 1RE-05 A.86E-05
4.97E-05 I .47E-O0
4.55E-05
5.5qE-05
2.1 3E- 10
6.4AE-1 1
1 .67E-n5 I .88E-05 I.88E-05
3.33E-07 I .79E-05
2.13E-05
5.26E-05
5,47E-05
5.24E-05 I.OUE-Ob
3.77E-05
2.BRE-05
5.BIE-05
5,BOE-05
5.72E-05
4.71E-O4
4.95E-06
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
000
TOTAL BODY
THYROID
2.17F-04
1.11 E-oiU
2.21F-ou
1.b3E-04
8.84E-0s
6. 90F-6 7 R.03E-05 tl IE-Ob
4.67F-05
5.80E-OU
5.b9E-04 U.'3bE-ou
2.b7E-OR
1.0
3.99F-nq
4.47E-04
2.0TE-OQ
I 40E -no
2.27E-07 I,75E-0U
I
*7E-04 I .26E-n9
3.S5E-10
7. 1* E-o0
?.9bE-05
7.96E-05 I .53E-nS
7.SRE-n5
9.03E-05
3.QbE-OU
.. O8E-n4
3.95E-0O
4o.7E-0b SI
*7bE-0O
1. 3LE-04
2.71E-04
2.7,1E-n4
2.67E-O0
2.20E-03
0.0
KIDNEY
.LUNC
0.0
0.0
.0
0.0
0.0
,0.


5. R. Loevinger et al., in Radiation Dosimetry (G. S. Hine and G. L. Brownell, eds.),   Academic Press, New York, 1956.
0.0
0.0
,0.
 
0.0
0.0
n010
0.0
0.0
n100
0.0
0.0
0.0
0,0
0.0
0,0
0.0
0,0
0 0
0.0
0.0
0,0
0.0
0.0
0.0
0.0
0.0
0,0
0.0
0.0
11.0
0.0
0.0)
0.0
0.0
0.0
G[-I.'.'
3.2 E-Ou S.,32E-Ou
5.64E-05
4.07E-04
7.q'E-05
5.JOE-Ou
5.h3E-Ou
5,12E-Oa
6,O2E-OS
I *?'E-On
1.13E-Oa b.?T7-Ou I , 4F -0s b. 72E-0&#xfd;
b,27E-05 b. 1 UE-05
7,BIE-05
5. 7bE-OS
t.bbE-O0
7.94E-A5
7qUE-05
2.a0E-05
7.30E-05 h1b6F-05
6.78E-05 l.u0E-O0
6.5 SE-os q.,5SE-05
9,75SE-OS
7.02F-05
9. 34E-09
9. 73E-Oi
7.92E-05
7.8IE-09
7.55E-05
7.0F-05
6,9I1L-05 q. 09E-05
1.87E-O.3
2. 88E-04 I
4
1.109-24


6.  M. J. Berger, "Improved Point Kernels for Electron and Beta-Ray Dosimetry," NBS Report NBSIR
TABLE A-4 TEENAGER INGESTION DOSE FACTORS
            73-107, 1973.
(mrenm/pCi ingested)
NUCLIDE
BONE
LIVER
TOTAL
B:oY
I H
3
6C
1'J
IINA
22
27C0
513
27C0
bO
38SR
B9
38SR
9o
39Y
qo
39Y
91 unZR
95
41,NB
95
44RU
103 OULRU job
505N
123 SPTE 1254
52TE
127
52TE
129M
52 TE
13?
531
129
531
131
531
13
95cS
134
55CS
137
5b0A
1U n
57LA
140.


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.
5.1CE
I1i0
5RCE
I1aQ
b3EU) 154
92U
232
92U
234 gaPU 238
9UP I 23- QUPU 240
9'PU 2a!
95AM 241
9bCM ?42
96CM 24U
0.0
7.55E-07
2.36E-09
,00
0.0
1 .OE-02
3. 3OF-08
1 .9hE-07
3.72E-08
7.2JE-09
2,37F-07 U OOE-Ob U . 3AF -05
3.93E-06
1.51E-07 I bhF-05
3.55F-O0
L.bbF-O6
5.57E-0h
2. 03E-Ob
8.05E-05
1 .07F-O0
2.83E-05
3.43
*8F
-09
1 .2bE-08
7.22E-07
1 I5E-Ob
60.bE-03
1,22F-0,3
5,&#xa3;0E-0a
9.2bE-04
9,25F-04 u.03E-07
9,q3E-04
2.26E-05 b
* hL F-0 L
I ObE-07
7 .55E-07
2. 35E-35
9.92F-67
2. 76F-nb
0.0
0.0
0.0
I .2'JE-08
*.36E-0q
0.0
0.0
7,22E-o7 I . 37E -0h
5.3?E-OM
5.15F-Ob
2,22E-Ob
3.92F-O0
7.87E-06
3."UE-Oh
1 .9QE-01 I lUUE-0LJ
3.u4E-os I .72E-09
?.9bE-07 I .OnE-n7
0.0
0 0
I I* 1 E-O0
I . 29E -n4 I . 30F-oil
1.852E-o
(.1 7E-nU
2,33E-05
3. 33E-0O
I .06F-A7
7.SSF-07
2. 3SE-05 TqYq!10
1.n0E-07
7 . SSE-07
2.35F-05
2.26E-Ob
6. 30E-Ob I . 3E-15
2.57E-03 A.87F-ln0
5.?P3E-n9
8.6hE-nQ
?.u7E-OQ
1 OhE-07
5.03E-07
1 .0E-Ob
5.0AE-07
3.23F-08
2.61E-nb
2.1 nE-n6
1 .31F-05 U.6qE-nh I OhE-Ob nO
0.0
n o
0.0
0~o
0 . n
0,0
I5,13E-07
5.37E-07 I .03E0O7
5,30E-06
235SE-6 5
2.27E-03 b.?5F-0U
0.0
(USE
n 0
0.0
ADULT
3.75E-nS
0.0
0.0
T
0.0
DOSE'
0.0
0.0
FACTOR)
0 &deg; 0
0.0
0.0
0.0
0.0
I .3JF -05
. 31E-05
4.49F-n5
2.4? eo-O0
1 .O9F-O0
7.53E-05
2.68E-05 I . 78E-05
1 .6SEF-0s I .
IE-o0
6. 31F-05 I ,07F-05 I .22E-0O
5.R0E-05
8,00E-05
4.31E-07
1.49E-06
2,50E-06 OC
I -)NF Y
I .06F-07
7.55F-n7
2. 35F-05 GI-LLI
1.0h-07
7.55F-07
2.88-*-h
9. OhE-05
5.05E-05 I.fPE-06
4.59E-10
3,83E-O8 R.7qE-ng n,2tE-0
7.UnE-05
2.ORE-05
2.2QE-05
2.31E-05
1.02E-00
6.66E-05 I .50E-06 U.n3E-05
0.0
0.0
o.6
0).0
0,0
0.0
0.0
0.0
0.0
2.35E-05
2.24E-Oh
1.91F-05
1.q2F-06
?.33E-09
4.tUE-Oh
0.0
Q.8F.-0O
n.O
2.29L-05
0.0
1.70E-04
0.0
5.12E-05
0.0
6.72E-05
0.0
6,14E-05
0.0
7.30E-05 o.0
6bE6F-05
0.0
b.bbE-05
0.0
1.28f.-07
0.0
7.17E-05
0.0
7.80E-05
0.0
7.42E-05 Note:
0.0 means insufficient data or that the dose factor is <1.OE-20.


al*
1.109-25
'::i k!
                                                      1.109-23


APPENDIX C
TABLE A-5 CHILD INGESTION DOSE FACTORS
                          MODELS FOR CALCULATING DOSES VIA ADDITIONAL PATHWAYS
(mrem/pCi ingested)
                                FROM RADIOIODINES AND OTHER RADIONUCLIDES*
NUCLIOE
                                      DISCHARGED TO THE ATMOSPHERE
BONE
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]
LIVER
            1       -                 1     1   [1 - exp(_xitb)].                   (C-l)
TOTAL B.11Y
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;
I H
              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;
6C
        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;
I INA
              x      is the radiological decay constant for nuclide i,  in yr-; and
27C0
      1.0 x 1012      is the number of pCi per Ci.
27CO
38SR
39Y
39Y,
(J1NB
44 RU
44LRU
SO SN
S2TE
52TE
52TE
531
531
55c S
SscS
56BA
57LA
58CE
SOCE
b3EU
92U
9?U
911PU
94iPU
94PU
94 U
95AM
96CM
96CM
3
22
58 bO
89 qO
90
91
95
95
103 lob
123
1 25H
127
129M
132
129
131
133
137
110
1 a1 I a 1
154
232
234
238
239
2a0
2at
201
242
?' 11
0.0
2.26E-06
5. 89E-05
0.0
0.0
1.* 38F-03
1.*72E-02
4,1. E-08
5.65E-07
1 .04F-07
1 .95E-08
6,78E.-07 I*1.19E-05
1 .31E-0(1 t I 1'JF-05
4A.50F-07
41.95SO5 I .02F-O5
1 739-E -05
1 .63E-05
5,98E-06
2,24JE-041
3. 12E-04
8.26E-05 I .01E-08
3.76E-OR
2,14'E-06
2.58E-0b
1 .77E-02
3,57E-03 I .21F-03
1 .32E-03
1 .32F-03
7. 12E-07
1.4&#xa3;2E-03
6,74E-05
1. 12E-03
2.03E-07
2.26F-06
5,89F-05 I .8SE-nb
5. 17E-06
0.0
0.0
0.0
o,0
2,012E-08
8. 32E-09
0.0
0.0
1 .641E-06
3.09E-flb t .20E-07
1 .38E-05 UI.5OE -06
8.S(1F-06
1 .67E-DS
7.38E-06
3.77E-fl'
3.02E-04I
7.2SE-n8
3.52E-09 I BR8E-08
6. 70E-017
2.08F-07
0.0
0.0
1 .52E-04I
1 .62E-04i I .63E-noL
b.211E-n4
5.28E-nS
5.


The annual dose resulting from direct exposure to the contaminated ground plane, from all radionuclides, is then DG(r,e) = 8760 SF
L f -0 1
* CG(r,e)DFGi                                            (C-2)
5.58E-flb
where the terms-are defined in Regulatory Position C.3.a of this guide.
1 .55E-05
3.95E-05
41.36E-0 3 I
* I3E-oq I .56E08)
2.?OE-OA
6. I IE-09
2.71jE-07 I
USJE-06
3.22E-0b I .S2E-0b
9.65E-06
7.65E-06
5.'I2E-Ob
3.81EF-05 I 426E-05
2,90E-06~
2,03E-07
2. 26E-06 S.8QE-05 TH~YRODI
2.03E-07
2.26E-06
5.R~9E-05S
K I )NEY
0.0
0.0
o.0
0.0
0.0
0.0
0.0
I .73E-06
3.20E-06
3. 1 OE-07
1.58E-O5 b.62E -05b
2.79E-02
5,USE-03
1 .7F-0_
0.0
(USE
0.0
ADULT
0.0
0.11
,).0
DOSE
0.0
0.0l
0.0
FACTOR)  
0.0
(.0
0.0
0.0
0.0
0n0
JS. iSF-OS
&#x17d;.2 .8b
-051
7. 77E-05
2.50F-05
1 .J44E -05 I
* ThF -n03 I . k5F-va
1 , I OF -OS.


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.
1 .'0?f-fl S5.96EF-05
7 .89F-O5 LI *
9L .f7
1 .43E-06
?.Q9E-oh LUNr P . 0 3E -07 PQE-06S
G; I - LL I
2.0 3E-07
2. S7k-Ob
4
8. 02E-05
41.50F-05
&#xa3;1.SSE-0b
1 . I QE-09
2.80E-09 I.14 (E -07
2.03E-07
1 .26E-03
2.2 1 E-04J
3.09E-OS
3.27E-05
13flnE-05
1 .81E-08
9,9&E-05
'1.41hE-06
6.99E-95
0.0
0.0
0.00
0.0
0.0h
0.0
0.0
0.0
0.00
0.0
0.0
0.0
0.0
n , n n ,
u.19F-05
3.54E-05 u.32E-08
0.0
1.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
2.04FI-0(,
1 .8ar-06
0. *21 E-0b
1.noQE-011
2 .36E-05 I .711F-0'J
ai. /Ok -05 b.91L-OS
6. 3eF -0'3
7 . 50EF -V5
6
* PSE -0
6 1SL -05 I .32F -0 7
7 . 37 F - f'5
8.03E-05
7 . bUjE -OS
Im Note:
0.0 means insufficient data or that the dose factor is <I.OE-20.O
I
1.109-26


Does not include noble gases.
TABLE A-6 INFANT INGESTION DOSE FACTORS
(mrem/pCi ingested)
NI
b C
27C'
38S1
385
39y
4 1 P(
50S~
52TI
JCLTr)E
qti'*E
.3
0.0
14 U.81F-Ob A 22
1.OnF-OLI
LIVER
TflTAL ~VlDy
3.0 7F-o7
4.*81 F-ob I *00E-nd
3. 07E-07 U.BI E-06 I OO0E-04 T H4 Y 4 110
3. 07E-07 a0,
4 B I-n0b I.o 0F -04 K 1 3N F Y
LONG
3. 07F-07
6 1 E-Ob OO.0F-04~
GJ-LLI
3.07E-07
2
* 45E-Oh aJ Sa
0.0
3.78E-06
9.26E-06
0.0
0 .09.79E-
0
60n
0.0
1 .07 E- 05
2.56E-05
0.0
n0.


1.109-24
0
2bF
R
C
2,q3F-03
0.0
A.U2E-05
0.0
(USE
0.0
5."l8E-05 R
90
2.91F-02
0.0
6.U0E-03
6.0
0.0
2 F-04
40
BQIE-08
0.0
2.41E-!&#xfd;9
0 .n ADUL.T
.01.29
0
Q I
I. 2S9F -0h
0.0
3.33E-OR
.0
0
(.0
8.27E-05 R .
5
? .IIF -07
5.32E-nR
3.78E-08 n . n
0 .0
?.38E-05 Q
P95 I.g9E-nR
I. 75E-1)8
1 .0 3E - 1
0.0
DOSF
0 .0
1 .LJE-Oc J 103
1.OilE-0
0 ,0
U.BSE-07 n .0
1.0
1.7F0
J 1.06
2.5"&E-05
0.0
3.12E-16
0,0
0.0
19E0
N 123
2.7'9E-0Li Q.33F-oh h.96E-lb
4.33E-(16 FACTOR)
0.0
b.41E-05 E1254
2.'J3F-0'S
5.19E-nb
3,20E-flh R.OnE-OS
0.0
1.17E-05 b5
5 u
5
5
5
52TE
127
9.58F-07
52TE I?9M
1.05F-04
521E 132
2.t3F-05
531
129
2.95F-09
531
131
3.U2E-OS
531
133
1,2bF-05
55CS 130
U.SAE-04
55CS 13
6.53F-O0
56BA 1'&0
1,74E-00
57LA 100
2.12E-08 S8'E 141I
S.OOE-08
58CE lU4
0.49E-0b
63EU 154
4.30F-06
92U
232
3.66F-02
920J
234
7.u00F-n3 qAPO P38
1.71F-03
9'IPU ?39
1.70E-03 qqpU ?'40
1.78E-03
94PU P.01
11OhE-0b
95AM 241
1.93F-03
96CM
2U2
1.43E-nu
96CM 244
1.bdE-03
3. 1 9F-n7
3.61F-05 I n05E-05
2. IbE-OS
401
0F-05
1 BUE -05
9~ .2 4E-0 4
7 . 31
-4
1
'75-n7
5. 17E-ng
4:91F.08
1 .7 7E -0 h O .RUE-n7
0.0
0.0
2.1 BE-a04
2. 2bF-q0
22
8F?
E- fl I .37F-D7 I .01F-n3 I UOOE-04
1.6
7E -00
2. 06E-n7
1 .60E-05
0* 76E-Oh
7 .76E-05
2.3RE-05 S.'BE-06'
7.75E-0 7
3.q9E-05 I *99E-'n5 h.* 79 F-02 I .31E-62 u.*35E-0 S
..
0
0.0
n,0
0.0
0.0
,0o0
2.?27E-05
6. 33E-05 A, 08F.---05
4.46JE-07
1 .53E-06
3.*27E - 06
6.97E-05
0. *20E-05
8 qqF-0b
2
* I E-fO)
5.75E-IQ
2.0?E-n7
3.29E-07
2.68E-03
4.71EC-04
0 .25E-q5
0
* I
E-1)5
0 .45E-05
2.70E-OP
1 . IIE-nu
9 .Q9F-nb
1 .04E-04
0.0
0 5
0).0
0.0*
0.0*
0.0
0l,0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
9.42E-05 R.81E-05 I .07E-07
0.0
0.0
O.0
0.0
0.0
0.0
0.0
0l.0
0).0
0.0
0.0
(0.0
n0.0
I .OuF-04
2. 39E-05 I .85E-04
4.*7bE -05
7.*34E -05
6. 72F-05
7.98E -05
7.*29F -09
7.28E-05 I .40OF-07
7.8'4E-O5
13.b,3r-05
8. 12E-05 Note:
0.0 means insufficient data or that the dose factor is <1.OE-20.
 
1.109-27


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)
TABLE A-7 EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUJND*
      where Qi      is the release rate of nuclide i to the atmosphere,      in Ci/yr;
tmrem/hr per ptl/'.)
                Xi(r,e)        is the annual average ground-level concentration, of nuclide i in air in sector e at distance r, in pCi/m3;
TOTAL BODY
                                                                                                  3
SKIN
          [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)
TOTAL BODY
                              and radioactive decay of the plume; and
sKirt i H
            3.17 x l04        is the number of pCi/Ci divided by the number of sec/yr.
4BE
b C
74
9F
I TMA-
11 NA
1P
20CA
2 1 S C
214CR
.25MN
25MN
26FE
2bFE
27C0
27C0
27CO
28NI
28NI
28NI
29CU
30ZN
3nzN
3'JZN
34SE
35BR
358R
35BR
37RB
37RB
37RB
37R8
38SR
-38SR
38SR
3ASR
34Y
39Y
39Y
39Y
39Y
3
10
18
22
32 U 1 Ub
51
50
5b
55
59
57
58
6n
5q
63
65 ba b5
694
69
79
82
83
85
87
88
5Aq
59
90
92
90
914
91 q2
93
0'.0
0.0
7 60kE-0q b.


The annual dose associated with inhalation of all radionuclides, to organ j of an individual in age group-a, is then
0FO-09 I ,66E-08
                  0.A
2.50E-0B
                    ja (r,e)  =  Ra Zx.(r,e)DFA.
0,0)
3.'JlE-09
0 . nO
-O
I
*30F-08
2.20E-I0
9.60E-09
1 *BOE-ORq
0.0
9.


I             ja (C-4)
OE-t0
            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.
7.OOE-09
1, 70F-08
3. 70E-09 I .50E-09 UQ,00F-09
2.90E-09
0.0
0.0
I .90E-AA
6 . 9O0E - I
b.UOE-t 1 I .20F-08
0.0
6.30E-1O
3.50E-09 I .50E-08
5.60F-1 3
0.0
7.o I OE-Oq
9.OOE-09
2.20E-12
3.80E-0q
2. 4 OF-
II
I .6bOF-09
5.70E-I0
0,n
0.0
0 0
5.80E-09
8. OOE-09 I . OE-08
2.90E-08
0.0
U.01E-n9
1 .50E- -B
2.b0E-1 0
I IOE.-08
0.0
9,4OE-O9 I.OOE-OQ
R.20E-0Q
2. 00E-O0
0.0
0.0
1 .70E-09 I,70E-Oq
3.0OE-09
0.0
0.0
2.20F-ro8
9. 30E- II
.40E-08
0.0
7.20F-10
0.0
4.OOE-09
1.80E-08 b.5OE-13
0.0
. 3 0E-09 I .OOE-08
2,60E-12
4.40 E-09
2.70E-i I
17.90F-n
7 .80E-1 0
UOZR
4OZR
4OZR
41N8
42MO
LJ3TC
43TC
'i3TC
44RU
U &#xa3;4 P D
LA
RU
LA 9RH
46PD
47AG
47AG
4 A C r)
5""s
52TE
52TE
5128
515R
51TE
52TE
52TE
52TE
5?TE
52TE
521E
52TE
52TE
52TE
531
531
531
93
95
97
93*4
95
97
99
9q4
04
101
103
105
1 nb
105 i07
109 I I~
111
123
125
12b t 246
125 I ?b
127
12741
127
12 2'4
129 t31M
131
13 2 I 3M
129
130
131
13 2
133
6.0
5.00F-09
5. SOE -()q o0.


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.
5. 1OF -A9
4A*bOE-0q
2.29E-I I
1 .qUF-0O
Q. *,,E-10
0.0
2.7WF-0O
S.bOE-OO
4.5UF-Oq I .50F-09 b.6OE-10
0.0
3.50E-I I
I ,80F-08 I .80E-10
2.3nF-12
0,0
0.0
5. 7OF-t0
Q.DOF-09
1.30E-08
3. IOE-09
*
.9OF -') 9
5. 7OF-09
3.50F-12 I OOF-I I
7.70F-10
7. IOE-10
S.,
U OF -09
2,20F-09 I . 70F-0Q
1 .50E-08 I .OOF-09
4 .SOE-1 0
I *U0E-08
2.80F-09 I .7nE-0O
3.7UE-09
3.0
s . G010
5. O0)E -A9 i,4nE-Oq
*20F-09 I* OE-OQ
I.OOF-Oq
4 .20F-o9
5. 101-O
I jAnF-0q
7.7nE-10
S.0
14.001-I11
'. tOE-08
2. tOE-Io
2.60F-12
0.0
b,* bE-qR
b.bOE-10
I
DO0E-nm
1 .50F-09
3.50E-09 I .OOE-O8 b.hOF-*9 U*.AOE-1 I
1.


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
0E- II
                                                                    [ -P exp(-xitb)]
I .IOF-1 I
                                                                Biv _2 Xi exp(-AEi te)]+                        exp (- i th )    (c-5)
P *OOE-It0
                  Cv(r,e) =di (r,e) tr[l    -
g.uOE-I0
                  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.
4.90E-09
2,b0E-Ob
2.00F-09 I .70F-OA
1.20E-09
7,50F-I 0
1 .70E1-ri
1 7 0E - n9
5.40FO-DQ
2. O0E -08 U.5AE-09 I
*The same factors apply for adult, teen, child.


1.109-25
Note:
0.0 means insufficient data or that the dose factor is <l.OE-20.


The deposition rate from the plume is defined by di(r,e)  =  1.1 x 1086i(r,e)Qi                                                (C-6)
E
where d.(r,e)        is the deposition rate of radionuclide i onto ground at location (r,e), in pCi/m 2 -hr;
1.109-28
          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====
TABLE A-7 (Continued)
.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).
TOTAL BODY
        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.
SKIN
53!
13u I.bOF-0
l.90t-o0i
531
13
1 .20EE-08
1uOE-O8
55CS 134'1 b.P0E-10
7.Y0E-10
55CS 134
1 .2F-08 IQOE-0p
55CS 135
0.0
D.0
55CS
t36
1.5OF-'4
'.70E-08
55CS
137
4 .2OF
QJ
-. 90E-0Q
55CS 13A
2,tOE-05
2.uOE-OR
55CS t39 b.30E-ng
7.20F- nq
5b65
139
2.uOE-0Q
2.70E-0Q
5hBA
140
2.lOE-0q
2,unE-09
56BA
1UI
U.IOF-o9 qt90F-0Q
5b6A
1u2
7.9*E-09
9.00E-DO
57LA lU0
1.50E-0R
1.70E-08
57LA 141
2.5vE-10
2.5nE-t0
57LA
IQ2
1.50E-OR
t.ROE-05
58CE
]at  
5.50E-10
b.20E-t0
58CE 143
2.20E-0q
2.50E-0Q
58CE
Ua a
3.20F-10
3.70F- 10
59PR 143
0.0
0.0
59PR IOU
2.OOF-10
'.3nF-10
bOND 147
1.00E-0q
1.20E-09 blPM
I7
0.0
0.0
tIPM
4RM4
1.UtF-.F0
5 6.-01- bIP4 10B
u*hOF-09
5.3f5--*9 bIPM 14Q
2.50E-11
2.QoE-il biPH 151
2.2'F-OQ
2.30E-o9 b25
151 u.80E-11
2.10F-10
b2SM
53
2.70F-In
3.0OE-10
13EU 152
7.37E-09
3.53E-0O
63EU 15u
7.BUE-09
4.00F-19 b3EU 195 I.RIE-10
U.33E-10
b3EU 156
7.80F-09
3.70E-Mg
65TB 160
A.6(0E-A9
1.00E-0A
67H40 I664
5.90F-00
1.OOE-nS
7UA
181
2*10F-12
2,ROE-12
7Ui
185 n
0
.0
a
74"
187
3.1'E-AQ
3.bOE-09
82PH 210
1.30E-11
1.70E-11
381B 213
0.0
0.0
RaPO 210
5,10E-'1 b.2OE-tu TOTAL BODY
SKIN
8RRA 2?3
1.50F-09 I.ROF-09
8SRA 22u
3.9nE-0q
1.OOE-08
88PA P25
;. 11F -
t I
I. 2()F -1A
88AA 22b b.41JF-oq
7.40E-O0
R.RA 228 I,?f'F-0
1 t.4OF-n8
89AC
P2?
IrNF-OQ
1.80E-oQ
9A9C 227
2.OOE-09 2.40F-59
90TH 227
5.10F-10
b.30F-t0
90TH
22?
,.QOF-0Q
t.00E-0A
90TH 229
2.20F-0 0  
2.70E-09
90TH 230
h.S0E-nq
7.SOE-nq Q0TH ?32 S.OOF-OQ
U.nOE-Oq qOTH 23u
1.1OE-10
1.30F-10
91PA 231
2.20F-0Q
&#xfd;.70E-09 qtPA 233
1.30F-09
1.50F-99
92U
P32
2.5qF-12
2.b9E-11
92U
233
2.30E-09
2.rtOF-o9
92U
234 b.32F-13
1,59E-10
q2U
235 i.20F-Oq
4.OOF-ng
92L
P3b
2. IF-I
I .80E-11
92U
237 t.00F-09
1.30E-0q
92U
238
1.10F-10
1.50E-10
13NP 2;7
1.40F-09
1.bOE-Pq
93NP 238
2.8nF-09
3.20E-oq
93NP 23q
9.50F-10
1.10E-0q Q9PUJ 238
1.30E-12
1.80F-11
9LPU P39
7.90F-13
7.70E-12
94PU 240
1.30F-12 t.80E-11
9LPU 241
4.h0E-12 b.80E-12 QUPU 242
1.10F-12
1.60F-11
9qPki 2441
8.95E-10
1.62E-10
9SAM 241
1.801E-10
2.60F-10
95AM .4??4
2.h6F-11
1.80E-1l
95AM 24.3
1.30E-09
1.50E-09
96CM 2U2
5.50E-12
2.30E-11
96CM 243
2.30F-Oq
2.90E-0Q
96CM 2ila
2.qnE-12
1.8OE-11
96CM 245
9,50E-10
1,20E-09
96CM 246
1.00E-12
1S50E-11
96CH ?P7
2,20E-0Q
2.bOE-09
9bCM 2a8
6.8IE-0q
5.23E-09
98CF 252 b6b0F-0R
7.20E-08
1.109-29


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.
called bioaccumulation factors in this guide, can be found in the literature (Pnf.


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)
19).  
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:
The addition of the bioaccumulation factor Bip to Equation (A-2) yields Equation (A-3),  
            C 4 (r,e) = 3.17 x 107 pQl 4 [x/Q](r,e) 0.11/0.16
which is suitable for calculating the internal dose for consumption of aquatic foods.
                        = 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
Rap
                  0.16 and
= 1100 Uap Q.B. D *exp(-Aitp (A-3)
                                                      1
i aipj
          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:
p Values of Bip are given in Table A-8; the other parameters have been previously defined.
            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)
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.
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.
c.


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.
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.


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)
One method of approaching this problem was presented in the Year 2000 Study (Refs. 4, 17, 20, and 21).
  where CF(r,e)      is the concentration of nuclide i in animal flesh, in pCi/kg;
Based on these references, an estimate of the radio- nuclide concentration in shoreline sediments can be obtained from the following expressions:
                    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)
Ciw[l - exp(-.it)]
  All the other symbols are as previously defined.
C.s Kc
1w i
(A-4)
is c
where Cis is the concentration of nuclide i in sediment, in pCi/kg;
CiW
is the concentration of nuclide i in water adjacent to the sedinent, in pCi/liter;
Kc is an assumed transfer constant from water to sediment, in liters/kg per day;
t is the length of time the sediment is exposed to the contaminated water, nominally 15 years (approximate midpoint of facility operating life), in hours; and Ai is the decay constant* of nuclide i, in hours-l.


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


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)+
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).  
                              DFI~                  UmC&#xb6;(,e) + U CFF(re) + UL f C(re)]      (C-13)
Since the primary use of the equation is to facilitate estimates of the exposure rate from gamma emitters nn*w meter above the sediment, an effective surface contamina- tion was estimated.
                                      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
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.


REFERENCES FOR APPENDIX C
The resulting equation is Si MOT
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.
1 iCi WDl - exp(-Ait)]
(A-5)
where Si is the "effective" surface contamination, in pCi/m2, that is used in subsequent calculations;
If the presence of a radionuclide in water and sediment is controlled primarily by radioactive equilibrium with its parent nuclide, the water concentration and decay constant of the parent should be used in Equations (A-4) and (A-5).
With a mass of 40 kg/m 2 of surface.


2. D. F. Bunch (ed.), "Controlled Environmental Radioiodine Test, Progress Report Number Two,"
1.109-30
    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.
TABLE A-8 BIOACCUMULATION
FACTORS
CpCilkg per pCi/liter)
FRESHNATER
SALTMA17ER
ELEMENT
FISH
INVERTF3RATE
PLANT
PIS'
TIVERTE3RATE
PLANT
H
9,0E-Ol q.oE-01
9.OE-01
9.OE-ni
4.3E-01
9.3E-01 HE
1.0E 00
1.0f 00
10Elf
1.0ff O0
1.fOE 00


4. F. 0. Hoffman, "Environmental Variables Involved with the Estimation of.the Amount of 1311
====t. OE no LI ====
    -inMilk and the Subsequent Dose to the Thyroid," Institute fUr Reaktorsicherheit, Cologne, West Germany, IRS-W-6, June 1973.
5,0E-Ol C.oE: 01
3.0E 00
5.OE-01
50fE-Ol
3.0E 00
BE
2.OE 00
InE 01
2.0E 01
',OE
02 e.OE 02
1.OE 03 B
2.2E-01
5.OE 01
2.2E 00
2.2E-Ot QO.E-01
2.2E
oA
C
U.


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


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.
E 04
1T7E "04
1 .0f p
0
0
9.2E-O
9.?fE-01
9.2E-0l
9.bF-01
9.bE-01 Q.bE-O0
F
1.0E 01
1 .oE
02
2.0E 00
3.bF 00
3.6f on
1 .4E
00
NE
I.OE
O0
I.nE 00
1. r E 00
1.0E 00
1.0OE 00
1.OF 00
NA
I.OE 02
2.oE. 02
5.OE 02 b.7E-02
1.QE-01
9.SE-O1 MG
5.OE
01
1.oE 02
1.0OE 02
7.7Ff-01
7.7fE -01
7.7E -0 1 AL
ioE0f
01
6.;E 01 U.2E 02
1.0OF n1 b.OE O0
6.OE 02 SI
2.5E 00
2.';E 01
1.3E 02
1.0f 01
3.3E 01
6.7P 01 F
1.0oE 05
2.oE. OU
5.0E 0';
2.fE n4
3.0E O4
3.0E 03 T
7.5E 02 I.oE. 02
1.0E 02
1.7E 00
4,UE-01 U.4E-01 CL
5.0E 01
.ofE 02
5.OE 01
1.3E-02 I.QE-02
7.6E-02 AR
I.OE 00
1.nE 00
1,OE 00
1.0ffno I.OE 00
1.OE 00
K
I.OE 03
8.lE 02
6.7E 02
1.IE 01
.6fE 00
2.6E 01 CA
4,OE 01
3,3E 02
1.3E 02
5.0E-Ol
1.3E 01
5.OE 00
SC
2.0f 00
1.fE' 03 t0OE 0 Oi
2.0fE 00
1.fOE 0 Q
I.0 E 05 TI
t.OE 03
3.OE. 03
5.OE 02
1.OE o3
1.OE 03
2.0E 03 V
1.OE 01
3.E 03
1.0E 02
1.0E Ol


7. P. G. Voilleque and C. A. Pelletier, "Comparison of External      Irradiation and Consumption
===5. OE O ===
                                              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.
i.OE 02 CR
2.0E 02
2.nE 03 .
",OE 03
4.0E 02
2.0E 03
2.0E 03 m, ,40OE
02
9.oE 04
1.0fE 04
5.5E 02 *
4.OE 02
5.5E 03 FE
10OE 02
3.pE 03
1.0E 03
3.0E 03
2.OE O4
7.3E 02 c0
5fOE 01
2.nE 02
2,0E 02
.0OE 02 I.0E 03 I.OE 03 NI
1.OE 02
1.OE. 02
5.0E 01 I.OE 02
2.5E 02
2.5E 02 CU
5.OE 01
'i.nE, 02
2.0E 03
.7ffE
02
1.7f 03
1.0E 03 ZN
2.0E 03 i.nE 04
2.0E 04
2.0E 03
5.0E OU
1.0E 03 GA
.3E 02
6.7E 02
1.7fE 03
3.3fE 02 b.7E 02
1.7fE 03 GE
3.3E 03
3.fE- 01
3.3E 01
3.3E 03
1.7fE OU
3.3E 02 AS
1.OE 02 i.nE. 01
3.0E 03
3.3E 0R
3.3E 02
1.7E 03 SE
1.7E 02
1.7E 02
1.0E 03
4.0E 03
1.0E 03
1.0E 03 BR
4.2E 02
3.iE 02
5.OE 01
1.5E-02
3.1E
00
1.5E 00
KR
1.0E 00
1.nE:00
102
0:0
Ij 0E 0
.
f0E 00
.0fE 00
RB
2.0E 03 i.nE, 03 t.0E 03
8.3E 00
1.7E 01
1.7E 01 SR
3.0E 01 l.nE 02
5.0E 02
2.0E 00
20OF 01 I.OE 01 Y
2.5E 01
1.0E 03
5,OE 03
2.5E 01
.0OE 03
5.OE 03 ZR
3.3E 00
6.7fE 00
1.0E 03
2.OE 02 OE n1 I.OE 03 NB
3.0E Oi l.nE u2
8.OE 02
3.0E n4 I.OE 02
5.0E 02 Mo
1.0fE 01
1.nE' 01 I.OE 03 OE f0
1.0fE 0t
1.0fE 01 TC
I.5E 01
5.Off
00
U.0f1
1.0f
1O
5.0fE 01
4,OE 03 RU
10OE 01
3.0E 02
2.0E 03
.0OE 00
1.0E 03
2.OE 03 RH
1.fOE 01
3onE:02
2.OE 02
1.OE 01
2.0OE 03
2.0E 03 PD
1.0E 01
3.0E 02
2.OE 02 I.OE Ot
2.0E 03
2.0E 03 AG
2.3E 00
7.7Ef
02
2.OE 02
3.3E 03
3,3E 03
2.0E 02 CO
2.0E 02
2.nE. 03
1.0E 03
3.0E 03
2.5E 05
1.0E 03 IN
I.OE 05 l.nE 05
1.0E 05
1.0E 05 I.OE 05 I.OEf
05 SN
3.OE 03
1.0E 03
1.OE 02
3.0E 0
1.0fE 03 t.OE 02 sB
1.OE
00
1..ff,01
1.5E 03 1JQ,OE 01 S.0IE 00
1.5E 03 TE
4.OE 02*
1.0E. 05 I.OE 02*
I.OE 01**
I.OE 05 i.OE 03**
1
1.5E Ot
5.0E 00
4.OE Ol I1.0E 01
5.0F
O0
I.OE 03
1.109-31


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
TABLE A-8 (Continued)
FRESHWATER
ELEMENT
XE
CS
BA
LA
FISH
I .0E
2,OE
* 0E
2.SE
INVERYF3PATE
SALTWAE;&#xfd;
TrIH
T1JVEITE3RATE
PLA'NT
00
03
00
01 I . nE
I PoE
2.0E
I .nE
00
02
02
03 PLANT
I .OE
00
5.OE 02
5.OE 02 S.E 03
1
0 OE
0i 0OE
1 0 OE
2. 5E
00
oft
0!
01 I .O0E
2.5f
1 . 0OE
I if E
00
01
02
03 I5.


====s. Released====
nE
    -to the Biosphere," USAEC Report UCRL-50163, Part IV, 1968.
5. OE
00
Dl
02
03 CE
1.OE 00
1.nE 03
4*OE 03 t I.OE O
b.6OE 02 b.OE 02'
PR
2.5E 01 I.OE 03
5.OE 03
2.5E O
I.OE 03
5.OE 03 ND
2.5E 01 I.nE, 03 S.OE 01
2.5E 01
1.OE 03
5.6c 03 PM
2.5E 01 IoE' 03
5.OE 03
2.5E 01
1.0E 03
5.OE 03 Sm
2.5E 01 I.OE 03
5.OE 03
2.5E 01
1.OE 03 S.nE 03 EU
2.5E 01
1.nE 03 S.OE 03
2.SE n1
1.0E 03 S.OE 03 GD
2.5E 01
10oE. 03
5.hE 03
2.5E 01
1,OE 03
5.OE 03 TB
2.5E o0
1.oE 03
5.OE 03
?.SE 01
1.0E 03
5.0F 0.3 DY
2,SE 01 I.oE 03
5,OE 03
2.SE 01 I.OE 01
5.OE 03 HO
2.5E 01
1.OE 03
5.OE 03
2.SE o0
I.oE 03
5.Or n3 ER
2.5E 01 I.oE 03
5.OE n3
2,5E 01 I.OE 03
5.OE
03 TM
2.5E o0
1.hE 03 S.hE 03
2.SE 01 t.OE 03 S.OE 03 YB
2.5E
01
1.oE 03 S.OE 03
2.5E o1 I.OE 03
5.OE 03 LU
2.5E 01
1.nE 03
5.OE 03
2.SE O0
1.OE 03
5.OF 03 HF
3.3F 00
6,7E. 00
I.OE 03
2.OE 02
2.OE 01
2.OE 03 TA
3.OE 04 b.7E-02
8,OE 02


9. R. C. Weast (ed.), "Handbook of Chemistry and Physics," CRC Press, Cleveland,     Ohio, 1970.
===3. OE Ol ===
1.7E 04 I.OE 03 W
1o2E 03
1.oE 01
1.2E 03
3.0E 01
3.OE
01
3.OE 01 RE
1.2E 02
6.nE 01
2.UE 02 U.E 00
b.OF 01
2.uE 02
0S
1.OE 01
3.0E 02
2.OE 02
1.OE 01
2.OE 03
2.OE 03 rR
I.OE 01
3.E'
02
2.OE 02
1.OE (1
2.OE 03
2.E 03 PT
1.OE 02
3.nE 02
2.OE 02
1.OE 02
2.OE 03
2.0E 03 AU
3,3E 01
5oE 01
3.3E 01
3.3E 01
3.3E 01
3.3E 01 HG
I.OE 03
1.oE 05 I.OE 03
1.7E 01
3,3E 34 t.OE 03 TL
1,OE 04
1.;E 04 I.OE 05
1.0E 04
1,5E 04 I1.E 05 PB
1.OE 02
1.nE 02
2.OE 02
3.OE 02
1,E 03
5.OE 03 B
t.SE o0
2.aE 01"**2.E 01***tS
1.5E 01
2.UE 01"** 2. a
0 1 F**
PD
5.OE 02


10. L. R. Anspaugh et al., "The Dose to Man via the Food-Chain Transfer Resulting from Exposure
===2. nE Ou ===
    -to Tritiated Water Vapor," USAEC Report UCRL-73195, Rev. 1, 1972.
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.


1.109-29
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.


APPENDIX D
!.OF
                              MODELS FOR CALCULATING POPULATION DOSES FROM
01 b.6E 01 NP
                                      NUCLEAR POWER PLANT EFFLUENTS
I.OE 01
      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
4.nE. 02
of-Appendix I to 10 CFR Part 50.
3.OE 02 I.OE o1
1.OE 01 i. OE 00
PU
3,5E 00
I.oE 02
3.5F 02
3.OE
00
2.OE 02 I.OE 03 AM
2.5E 01
1.0E 03
5.OE 03
2.SE 01
1.OE 03
5.OE 03 CM
2.5E 01
1.nE. 03 S.OE 03
2.5E 01
1.OE 03
5.0E 03 BK
2.5E 01 I.nE; 03
5.0E f3
?.SE 01
1.OE 03
5.OE 03 CF
2.5E 01 I.oE'03
5.OE 03
2.SE 01
1.OE 03
5.OE 03 ES
I.OE 01
1.oE, 02 I.OE 03 I.OF 01 I.OE O0
b.OE 01 i
I.OE 01
1.E 02 I.OE 03 I.OE 01 I.OE 01 bOE 01
*ORNL - Private Communication
**Freke, A.M.,
"A Model for the Approximate Calculation of Safe Rates of Discharge into Marine Environments," Health Physics, Vol.


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.
13, p. 749, 1967.


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,
***Derived from data in Bowen, H.J.M.,  
,the annual population-integrated dose is calculated as follows:
Trace Elements in Biochemistry, New York, Academic Press (1966).
            D~j = O.Ol d*Pd Z Djdafda                                                      (D-l)-
1.109-32
                        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.
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.


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-
Shore-width factors were derived from experimental data (Ref.
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
24) and are sunanarized in Tdble A-9.


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);
They represent the fraction of the dose from an infinite plane source that is estimated for these shoreline situations.
              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)
The combination of Equations (A-4)  
                    Sp where
and (A-5) into the general Equation (A-i) leads to
                : P p if    P*p< P 5 Pp .,            p      50
,*uation (A-6) below for calculation of radiation dose from exposure to shoreline sediments.
                  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
Rapj U
                            DISTRIBUTION SYST-...
S*D  
    FOOD MEDIUM                            DISTRIBUTION TRANSPORT TIME (in days)
100 U W C T D
Fruits, grains, and vegetables                              14 Milk                                                          4 Meat and poultry                                            20
[
Sport fish                                                    7 Con*nercial fish                                            10
- exp(-- t)]
Drinking water                                                1 To be used in lieu of site-specific data on food distribution.
(A-6)
ap i
aipj Iap iw i aij U III W
110,000
--'--.  
QiT D
.[exp(-."\\t )][l - exp(-:i t)]
(A-7)
F
lli ipj iP
1 d.


1.109-32
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.


0)
Separate expressions are presented for tritium because of its unique environmental behavior.
                  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.
(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.


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
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).
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.
The equation for the model (for radionuclides except tritium) is presented below in slightly modified form.


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.
The first term in brackets relates to the concentration derived from direct foliar deposition during the growing season.


(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 second term relates to uptake from soil and reflects the long-term deposition during operation of the nuclear facility.


The total body and thyroid dose of the individuals should be evaluated using
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:
-Equation (A-2)       in Appendix A of this guide, together with the age-dependent usage factors U
iv i"
                                                                                                    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.
- exp(- '"U t e)]v Biv[I - ex 1(-'P 'itb)1]exp(-..it )  
(A-8 )
The de;,osition rate, di, from irrigated water is defined by the relation d'i = C iw (water deposition)
(A-9)
where Ciw is the concentration of radionuclide i in water used for irrigation, in pCi/liter, and I
is the irrigation rate, in liters/m2 /hr; i.e., volume of water (liters)
sprinkled on unit area of field in 1 hour.


If the population served by a particular water supply. system is not known, it can be estimated by the following:
For tritium, the equation for estimating Civ is (see Ref.
              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).
25):
                      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.
Cv M Ctl (A-10)
For a cow grazing on fresh forage, te in Equation (A--8)  
is set equal to 720 hours
(30 days), the typical time for a cow to return to a particular portion of the grazing site.


I
1.109-33
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.
TABLE A-9 SHORE-WIbTH FACTORS FOR USE IN EQUATIONS (A-5) and (A-6)
EXPOSURE SITUATION
SHORE-WIDTH FACTOR, W
Discharge canal bank
0.1 River shoreline
0.2 Lake shore
0.3 Nominal ocean site
0.5 Tidal basin
1.0
TABLE A-10
ANIMAL CONSUMPTION RATES
I
ANIMAL
Milk cow Beef cattle QF
FEED OR FORAGE
(kg/day [wet weight])
50 (pasture grass)
50 (stored feed grain)
QAw WATER
(;./day)
60
5o From Reference 4, Tables 111-B and -10.
 
P
1 .10g-34
 
(2)  
Animal Products The radionuclide concentration in an animal product such as meat or milk is dependent on the amount of contaminated feed or forage eaten by the animal and its intake of contaminated water.
 
The radionuclide concentration in animal products CiA in terms of pCi/liter or pCi/kg (Ref.
 
4)
is proportional to the animal's intake of the radionuclide in feed or forage (subscript F) and in water (subscript w):
CiA = F iAECiFQF + CiAwQAw]
(A-li)
The second set of terms in the brackets in Equation (A-1l)
can be omitted if the animal does not drink contaminated water.
 
Values for QF and QAw are presented in-Table A-i1.
 
Values for Biv and FiA are given in Table C-5 (see Appendix C).*
The total dose Rapj from irrigated foods (excluding tritium) is given by:
R a veg CiD
+ Uanimal Y
D
apj ap iv aipj ap
*
iA aipj (A-12)
If values for Civ from Equation (A-3) and CiA from Equation (A-11) are substituted in Equation (A-12):
veg i[)Da [
- exp(- Ei te)]
Biv[l - exp(-'it )]*
R
ve dix(,
hi ai iv
,
X
Lb apj ap v
ipJ
YvEi i
U panima
-r[l
- exp( '1Ei te)]
ap iA ai pj OFui Y-
/
~v Ei
+ Biv[l - exp(-,.,itb)]
(A-13)
+PN
i
)]+ CiAwQAwj It should be noted that the two components of Equation (A-12)
imply that contribu- tions from the individual vegetable and animal products have already been summed.
 
In actual use, it will be necessary to compute separately the milk and meat portions of the dose due to animal products (also applicable to Equation (A-17)).
For tritium, the concentration in animal products is given by the following equation (adapted from Reference 25):
kWCv +QAwCAw (A-14)
C A -
+kQCA
m in Since by Equation (A-IO) Cv = Cw, and since for all practical purposes CAw = Cw9 Equation (A-14) can be rearranged as follows:
kC
C A = 3 (w + QAw)
(A-15)
in Similarly, the above equations for tritium concentration can be combined with the general Equation (A-1):
Ra.
 
U ve C D
animal CAD apj (A-16)
Rapj : u~gvap vapj" + Uap Aaj(-6 Uve v ,,animal Da (w+
QAw)
(A-17)
V uea Daa apjs + Uap apj-inab Q(C--.
Valus fr FA appear as Fin and Ff in Table C-5.
 
1.109-35
 
REFERENCES FOR APPENDIX A
1. "Final Environmental Statement Concerning Proposed Rule Making Action:
Nlumierical Guides for Design Objectives and Limiting Conditions for Operation to Meet the Criterion 'As Low As Practicable' for Radioactive Material in Light-Water-Cooled Power Reactor Effluents,"
USAEC Report WASH-1258, Washington, D.C.,
July 1973.
 
2.
 
J. K. Soldat et al,
"Models and Computer Codes for Evaluating Environvental Radiation Doses," USAEC Report BI3WL-1754, Pacific Northwest Laboratories, February 1974.
 
3.
 
"Food Consumption, Prices, and Expenditures," AER-138, U.S. Department of Agriculture, Washington, D.C., December 1974.
 
4.
 
J.
 
F. Fletcher and W. L. Dotson (compilers),
"HERMES
- A Digital Computer Code for Estimating Regional Radiological Effects from the Nuclear Power Industry," USAEC Peport HEDL-TME-71-168, Hanford Engineering Development Laboratory, 1971.
 
5.
 
J.
 
K. Soldat, "Conversion of Survey Meter Readings to Concentration (;.Ci/m2),'
Itemi 04.3.4 in "Emergency Radiological Plans and Procedures," K. R. Heid (ed.), USAEC Report HW-70935, Hanford Laboratories, 1962.
 
6.
 
L. K. Bustad and J. L. Terry, "Basic Anatomical, Dietary, and Physiological Data for Radiological Calculations," HW-,41638, General Electric Co.,
Richland, W'ash.,
February 1956.
 
7.
 
M. M. Miller and D. A. Nash, "Regional and Other Related Aspects of Shellfish Consumption -
Some Preliminary Findings of the 1969 Consumer Panel Survey,"
NIMFS Circular 361, USDC/NOfhA,
Seattle, Wash., June 1971.
 
8.
 
"The Potential Radiological Implications of Nuclear Facilities in the Upper Mississippi River Basin in the Year 2000," USAEC Report WASH-1209, Washington, D.C., January 1973.
 
9.
 
"Draft Environmental Statement - Waste Management Operations, Hanford Reservation, Richland, Washington," USAEC Report WASH-1538, Washington, D.C., September 1974.
 
10. "Radiological Health Handbook," USPHS,
Rockville, Md.,
January 1970.
 
11.
 
F. 0. Hoffman, "Parameters To Be Considered When Calculating the Age-Dependent 1311 Dose to the Thyroid," IRS-W-5, Institute for Reactor Safety, Cologne, Germiany, April 1973.
 
12.
 
P. S. Rohwer and S. V. Kaye,
"Age-Dependent Models for Estimating Internal Dose in Feasibility Evaluations of Plowshare Events," ORNL-TM-2220,
Oak Ridge, Tenn.,
April 1968.


(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.
13.


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
P. M. Bryant, "Data for Assessments Concerning Controlled and Accidental Releases of 1I
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.
and 137Cs to the Atmosphere," Health Physics, Vol.


(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.
17, pp. 51-57, July 1969.


(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).
14.
      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,
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.
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.
15.


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


1.109-34
16.


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


(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
17.
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
C. M. Lederer et al, Table of Isotopes, 6th Ed.,  
1. "Current Population Reports," Bureau of the Census, Series P-25, No.   541, U.S. Dept. of Commerce, 1975.
John Wiley and Sons, Inc., 1967.
 
18.
 
S.
 
E. Thompson et al, "Concentration Factors of Chemical Elements in Edible Aquatic Organisms," USAEC Report UCRL-50564, Rev.


1.109-35
1, Lawrence Radiation Laboratory, October 1972.


APPENDIX E
1
                                NUMERICAL DATA FOR THE CALCULATION
1. 109-36
                                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.
19.


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


1.    Environmental Data Table E-1 provides values for the following staDle element transfer coefficients:
20.
      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.
J. F. Honstead, "Recreational Use of the Columbia River--Eval'ation of Environmental Exposure," USAEC Report BNWL-CC-2299, Pacific Northwest Laboratory, 1969.


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.
21.


3.   Dose Factors Dose factors for external irradiation from a uniformly contaminated ground plane are
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.),
                                                                          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.
USAEC Report BNWL-36, Pacific Northwest Laboratories,
1965.


Dose factors provided in Table E-6 are derived from a consideration of the dose rate to air
22.
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*
G. L. Toombs and P. B. Cutler (compilers),
                            Biv                    Fm(Cow)              Ff Milk (d/z)
"Comprehensive Final Report for the Lower Columbia River Environmental Survey in Oregon June 5,
    Element              Veg/Soil                                    Meat (d/kg)
1961 - July 31,  
    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
1967," Oregon State Board of Health, Div. of Sanitation and Engineering, 1968.
    '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
23.
          .    and milk coefficients are based on specific activity considerations.


From Reference 15.
"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.


tSee text.
24.


ttFroim Reference 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.


1.109-37
1.109-37


TABLE E-2 NUCLIDE TRANSFER PARAMETERS FOR GOAT'S MILK*
APPENDIX B
                                                  Fm (days/liter)
MODELS FOR CALCULATING DOSES FROM
            Element H                                        0.17 C                                        0.10
NOBLE GASES DISCHARGED TO THE ATMOSPHERE
              P                                        0.25 Fe                                        1.3E-04 Cu
The following analytical models are used for calculating doses from exposure to gaseous effluents.
                                                        0.014"*
 
              Sr I                                      0.06&*
Separate models are given for air and tissue doses due to gamma and beta rays.
              Cs                                      -0.30**
 
                Values in this table are from References 1 and 14 unless otherwise indicated.
Except for the case of noble gas doses resulting from elevated releases, all models assume submersion in an infinite cloud at the exposure point.


From Reference 15.
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.


TABLE E-3 ANIMAL CONSUMPTION RATES
The following expression can be used for calculating annual doses:
                                                                QAw Feed or Forage                Water Animal                    (kg/day [wet weight])          (      R./day)
D 260
  Milk cow                      50 (Ref. 10)                  60 (Ref. 16)
D
  Beef cattle                  50 (Ref. 10)                 50 (Ref.  16)
n un s I
  Goats                          6 (Ref. 17)                  8 (Ref . 18)
)1 ik Symbols for this equation were defined earlier, in Regulatory Position C.2.a of this guide.
                                      1.109-38 IL


TABLE E-4 RECOMMENDED VALUES FOR U    TO BE USED FOR THE AVERAGE INDIVIDUAL
The photons were combined into energy groups, and each photon intensity within a group was weighted by its energy and energy absorption coefficient.
                            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.
Thus, the effective fraction of disintegrations of the nuclide i yielding photons corresponding to the photon energy group k, Aki, was determined to be Aki I [AmEmpa(Em)]/[Ekwa(Ek)]
(B-2)
m where A
is the fraction of the disintegrations of nuclide i yielding photons m
of energy E
Em is the energy of the mth photon within the kth energy group, in MeV; and Ua (Em)
is the energy absorption coefficient in air associated with the photon energy Em, in m All other parameters are as previously defined.


Inhalation rate derived from data provided in Reference 20.
The summation is carried out over all photons within energy group k.


tData obtained directly from Reference 20.
Data for the photon energies and abundances for most of the noble gas nuclides were taken from Reference 2.


1.109-39
For radionuclides not contained in Reference 2, data were obtained from Reference 3.
 
Decay during travel from the point of release to the receptor is QD = Q* exp(-Xir/un)
(B-3)
The term "gamma air dose" refers to the components of the air dose associated with photons emitted during nuclear and atomic transformations, i.e., gamma and x-rays.
 
Annihilation and bremsstrahlung photon radiations are possible contributors to this compunent of the air dose.
 
Elevated release conditions are assumed to occur when the point of release is higher than twice the height of adjacent solid structures.
 
(See Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion for Gaseous Effluents in Routine Releases from Light- Water-Cooled Reactors.")
1.
 
109-30
 
where Qi is the initial release rate of nuclide i, in Ci/yr, and Ai is the decay constant of nuclide i, in sec"1 All other parameters are as previously defined.
 
2.
 
Annual Gamma Air Dose from Ground-Level Releases of Noble Gases and Annual Beta Air Dose Plumes of gaseous effluents are considered semi-infinite in the case of noble gases released from vents.
 
The concentration of the radionuclides in air at the receptor location may be determined from atmospheric dispersion model described in Regulatory Guide 1.111.
 
The annual average ground-level concentration of gaseous effluent species i at location (r,o)
from the release point is determined from xi(ra) = 3.17 x 104Q*[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,.
3 in sec/mi The constant 3.17 x lO4 represents the number of pCi per Ci divided by the number of seconds per year.
 
All other parameters are as previously defined.
 
The annual gamma or beta air dose associated with the airborne concentration of the effluent species is then I
DY(r,e) or DO(r,e) =
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.


TABLE E-5 RECOMMENDED VALUES FOR Uap TO BE USED FOR THE MAXIMUM EXPOSED
3.
                -  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.
Annual Dose to Tissue from Noble Gas Effluents It is also necessary to determine annual doses to real individuals in unrestricted areas.


Consumption rate for adult obtained by averaging data from References 10
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.
    and 21-24 and age-prorated using techniques contained in Reference 10.


tData obtained directly from Reference 10.
a.


.Data obtained directly from Reference 20.
Elevated Releases The annual total body dose is computed as follows:
DT(r,O) = 1.11 x SF I DI(re)exp[-i (Ek)t]
(B-6)
Ground-level release conditions are assumed to exist when the release point is less than or equal to twice the height of adjacent solid structures and the vertical exit velocity is less than five times the horizontal wind speed.


tttiInhalation rate derived from data provided in Reference 20.
(See Regulatory Guide 1.111.)
The term "beta air dose" refers to the component of the air dose associated with particle emissions during nuclear and atomic transformations, i.e., 0+, B-, and conversion electrons.


I
1.109-40
1.109-40


TABLE E-6 EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND
TABLE B-i DOSE FACTORS FOR NOBLE GASES
                        (mrem/hr per pCi/m2)
AND DAUGHTERS
Element                        Total Body              Skin
Nuci ide Kr-83m Kr-85m Kr-85 Kr-87 Kr-88 Kr-89 Kr-90
-H-3                              0.0                    0.0
Xe-1 31m Xe-1 33m Xe-i133 Xe-i 35m Xe-1 35 Xe-1 37 Xe-138 Ar-41 a-air* (DFB)
C-14                              0.0                    0.0
2.88E-04 I . 97E-03
NA-24                            2.50E-08              2.90E-08 P-32                              0.0                    0.0
1 .95E-03
Cr-51                            2.20E-10              2.60E-10
1 . 03E-02
Mn-54                            5.80E-09              6.80E-09 Mn-56                            l.1OE-08                1.30E-08 Fe-55                            0.0                    0.0
2. 93E-03
.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
1. 06E-02
  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
7. 83E-03
  Br-83                            6.40E-11                9.30E-11 Br-84                            1.20E-08                1.40E-08 Br-85                            0.0                    0.0
1.11 E-03 I .48E-03 i .05E-03
  Rb-86                            6.30E-10                7.20E-10
7. 39E-04
  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
2: 46E-03
  Zr-95                            5.ODE-09                5-80E-09 Zr-97                            5.50E-09                6.40E-09
1. 27E-02
*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
4. 75E-03
  .Te-127M                        1.1OE-12                1.30E-12 Te-127                            1.OOE-l1              1.1OE-11 Te-129M                          7.70E-10              9.O0E-10
3.28E-03
  Te-129                          7.10E-10                8.40E-10
1 .46E-03 I .34E-03
  Te-131M                          8.40E-09                9.90E-09- Te-131                          2.20E-09              2.60E-06 Te-132                            1.70E-09              2.00E-09
9. 73E-03
  1-130                            1.40E-08              1.70E-08
2. 37E-03
  1-131                            2.80E-09              3.40E-09
1
  1-132                            1.70E-08              2.OOE-08
. 01 E-02
  1-133                          3.70E-09                4.50E-09
7. 29E-03
  1-134                            1.60E-08              1.90E-08
4. 76E-04
  1-135                          1.20E-08                1.40E-08
9. 94E-04
                                1.109-41
3. 06E-04
7.11 E-04
1.86E-03
1. 22E-02
4.1 3E-03
2. 69E-03 y-Air* (DFB'')
1.93t-05
1.23-03
1. 72E-05
6. 17E-03
1.52E-02
1. 73E-02
1. 63E-02
1. 56E-04
3. 27E-04
3.53E-04
3. 36E-03
1. 92 E-0:3
1.51 E-0:3
9.21 E-03
9.30E-03 y-Body (DFBi)
7.56E-08
1 17E-03
1.61E-05
5 92E-03
1 .47E-02
1 .66E-02
1 56E-02
9. 5E-05
2.51 E-04
2.94E-04
3.12E-03
1.81E-03
1 .42E-03
8.83E-03
8.84E-03 mrad-m3 pCi -yr mrem-m3 pC i-yr
**'2.88E-04 = 2.88 x I0"4
1.109-41
 
Symbols for this equation were defined earlier in Regulatory Position C.2.c of this guide.
 
The constant 1.11 represents the ratio of the energy absorption coefficient for tissue to that for air.
 
The skin dose has two components, the ganmia and beta contributions.
 
The skin dose rate is computed by DS(r,o)
1.11 x SFD Y(r,o) + 3.17 x 104 1 Qi(x/Q']D (r,o)DFSi
(8-7)
1 Symbols for this equation were defined earlier in Regulatory Position C.2.d of this guide.
 
The skin beta dose factors OFS were determined using the decay scheme source docu- ments cited above and the methods used in References 4,
5, and 6.
 
b.
 
Ground-Level Releases The annual total body dose is computed as follows:
DT(r,o) = 1.11 x SF &#xfd;xi(rO)DFBi (B-8)
Symbols for this equation were defined earlier in Regulatory Position C.2.e of this guide.
 
The annual skin dose is computed as follows:
Ds(r,o) - 1.11 x SFF Zxi(r'e)DFi +
xii(ro)DFSi
(8-9)
where D5 (r,e)
is the annual skin dose due to immersion in a semi-infinite cloud in the sector at angle e, at the distance r from the release point, in mrem/yr, and xi(ra)
is the airborne concentration of radionuclide i at point (r,6), in pCi/m 3 . I1 I
1.109-42
 
REFERENCES FOR APPENU.X B
I.
 
"Meteorology and Atomic Energy 1968," D. H. Slade (ed.),
USAEC Report TID-24190, 1968.
 
2.
 
M. J. Martin, "Radioactive Atoms, Supplement I,"
USAEC Report ORNL-4923, November 1973.
 
3.
 
M. E. Meek and R. S. Gilbert, "Summary of Gamma and Beta Energy and Intensity Data," NEDO-
12037, 1970.
 
4.
 
R. Loevinger et al, in Radiation Dosimetry (G. S. Hine and G. L. Brownell, eds.), Academic Press, New York,
1956.


TABLE E-6 (Continued)
5.
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.
M. J. Berger, "Improved Point Kernels for Electron and Beta-Ray Dosimetry," NBS Report NBSIR
73-107, 1973.


Reference 12 also identifies the cells of the basal layer of epidermis as the tissue of interest
6.
                                                                                        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).
M. J. Berger, "Beta-Ray Dose in Tissue.- Equivalent Material Immersed in a Radioactive Cloud," Health Physics, Vol.
      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===
26, pp.
      .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.
1-12, January 1974.


1.109-43
1.109-43


TABLE E-7 PASE  I OF  3 INHALATION  DOSE FACTORS FOR AnULTS
APPENDIX C
                            (UREM  PER PCI INHALED)
MODELS FOR CALCULATING DOSES VIA ADDITIONAL PATHWAYS
NUCLIDE      HONE    LIVER      T.ROCY      THYROID  KIDNEY    LUNG    GI-LLI
FROM RADIOIODINES AND OTHER RADIONUCLIDES
H    3  NO DATA    1.58E-07    1.58F-07    1.58E-C7 l.58E-07 1.58E-07  1.58E-07
DISCHARGED TO THE ATMOSPHERE
    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.
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
 
&#xfd;AR 83  NO DATA    40 DATA    3.01E-08    NO DATA  NO DATA  NO DATA  2.90F-08
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
,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
1.1 x 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
(rc~ Q!
                                        1.109-44
C
i(r'c)
1 1-exp(-Xit)j (C&#xfd;-l)
;'-here C
.
is the ground plane concentration of the radionuclide i in the sector at angle - at the distance r from the release point, in pCi/m2;
Qi is the annual release rate of nuclide i to the atmosphere, J'i/yr;
t is the time period over which the accumulation is evaluated, which is 15 years (riid-point of plant operating life).  
This is a simplified method of approximating the average deposition over the operating lifetime of the facility;
is the annual average relative deposition of effluent species i at location (r,j), considering depletion of the plume during transport, in mn-2 ; and The annual plant is then is the radiological decay constant for nuclide i, in yr-1 .
dose from nuclide i resulting from direct exposure to the contaminated ground D
(r ,)
8760 SFCG(r,r.)DFG
(C-2)
where D. j(r,*)
ii and other terms The annual is the annual dose to organ j from the ground plane concentration of nuclide i at the location (r,r,), in mrem/yr;
are as defined previously in Regulatory Position C.3.a of this guide.
 
dose to organ j is therefore D (r,o) = 8760 S
C9(r,o)DFGi i
F
I 1 (C-3)
Values for the open field ground plane dose conversion factors for the skin and total body are given in Tables A-3 to A-7.
 
The annual dose to all other organs is taken to be equivalent to the total body dose.
 
Does not include noble gases or their shurt-lived daughters; see Appendix B.
 
1.109-45
 
2.


TABLF    E-7,   CONT'D
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)
                                                    PASF  2  OF  3 INHALATION DOCSE FACTORS FOR            ADULTS
3.17 x 104QQ[X/Q'] D(r,)
                                          ,(REM PFR PCI INHALED)
(C-4)
    *.NUCL I ;L        BONE    LIVFR          T.-BODY        THYROID      KIDNEY      LUNG    GJ-LLI
where is the release rate of nuclide i to the atmosphere, in Ci/yr;
      '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
xi(r,O)  
                                                                              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
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 ;
      1E132      3.25L-08  2.69E-08        2.0O?-08        2.37E-08    1.82E-07  3.60E-05 6.37F-05
[./Q']D(r,o)  
        1 1.30    5.72E-07  I.o8E-O6        6.6;C-07        1.42E-04    2.61E-06  NO DATA  9.61E-07
is the annual average atmosphere dispersion factor, in sec/m 3 (see Regulatory Guide 1.111).  
        1 131    3.15E-06  4.47E-io        2.56E-06        1.49E-03    7.66E-06  NO [ATA  7.85F-07
This includes depletion (for radiolodines and particulates)
        1 132    1.45E-07  4.07E-07        1.45E-07        1.43E-05    6.48E-07  NO DATA  5.08F-08
and radioactive decay of the plume; and
        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
4
        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
3.17 x 10  
        --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!!
is the product of the number of pCi/Ci and sec/yr.
                                                      1.109-45


TABLL E-7,   CONT'D
The annual dose associated with inhalation of nuclide i at the airborne concentration xi(r,O) is then DDA (rO) = xi(ro)RaDFAi (C-5)
                                  PAGE  3 OF  3 INHALATION DUSE FACTORS' FOR ADULTS
iiaa ija Values for DFAija are given in Tables C-1 to C-4, and all other symbols are as defined earlier in Regulatory Position C.3.b.
                            (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
The annual dose to organ j in age group a from all nuclides in the effluent is:
  $                                      TABLE E-8 PAGE  1 OF 3 INHALATION DOSE FACTORS FOR TEENAGER
4 DA
                                  (NREM PER PCI INHALED)
(ra=R(C-6)
    14UCLICE    BONE    LIVER      T.BODY      THYROID  KIDNEY    LUNG  GI-LLI
Dja(r,o)
    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
Ra zxi(re)DFAija
    1A 24    1.72E-06 1.72[-06      1.72E-06    1.72E-06 1.72E-06 1.72E-06 1.72E-06
3.
                          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 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
    *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
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.
                                      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
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.
                                              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-.


TABLE E-9 PAGE  1 OF 3
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)  
                    -   INHALATION  DCSE FACTORS FOR CHILD
di(r,o)
                            (MREM  PER PCI INHALED)
r[l
NUCLIUE    BONE      LIVER      T.BOCY      THYROID  KIDNEY    LUNG    GI-LLI
- exp('AEite)]
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
Biv[l - exp(-Y tb)]] exp(-1ith)
;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
Ax PXti (C-7)
See Regulatory Position C.l of tnis guide for definitions of terms.


TABLL    E-9,  CONTOD
Carbon-14 is assumed to be in oxide form (CO and C02).  
                                            PASE 2 OF 3 INHALATION DLSE FACTORS FOR CHILD
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.
                                    (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 E-9,    CONTIC
1 and 2).
                                  PAGE 3 OF 3 INHALATION  DOSE FACTORS FOR CHILD
I
                          (MREM  PER PCI INHALED)
1.109-46
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
TABLE C-1 ADULT INHALATION DOSE FACTORS
                                                              PAGE      1 OF 3 INHALATION DOSE FACTORS FOR              INFANT
(mreni/pCi inhaled)
                                                    (MREM PER PCI INHALED)
NUCLIDE
    NUCLIDE             BONE            LIVER            T.3ODY            THYROID  KIDNEY      LUNG    GI-LLI
I
    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
3 UBE
(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
10
    '&#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
bE
    ----------------------------------------------------------------------------
I*l
    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
7N
                                                                  1.109-53
13 QF
14
11NA
22
1 1 NA
2 a ISP
32
20CA
4L
215C
U b
24CR
51
25MIN
54
25 'N
5b
26FE
55
?6FE
59
?7CO
57
27C0
98
27CO
bo
28NI
59
28-1
65
29CU
b6
30ZN
65
30ZN
694
30
N
59
3uSE
79
359R
S2
35HR
93
353P
84
353R
85
374B
5h
37RB
87
37RR
58
37BR
Bq
3BSR
89
3ASR
90
38SP
91
3ASR
Q2
39Y
90
34Y
qO1
3QY
9 1U
39Y
91 A0IE
0.0
I .qSE-OU
2.28E-O0
6.27F-Oq
4.71E-07
1. 30F-05
1 .b9E-O6 I .b5E-0O4
3.83E-05
3.51E-05
0.0
0.0
0.0
7.b2E-06 I .a7E-Ob
0.0
A 0
0.0
",0OE-0b
5.40E-05
1 .92F-I0
0.0
L.0
hE-Oh
1 .02F-09
4.23F-12
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
3.8OE-05 I .2"E-02
7.9"E-09
8. 4 1E-1O
2,b6E-07
3.?2 E- II
5.78E-05 LIVER
TfTAL
9')Y
1.3QE-07 t.34E-07
3.OhE-05 U.QbE-Oh
4.27E-07 u.27E-17 b.27E-09 h.27E-01
0.0
S.20E-oS
1.30E-n5
1.30E-05 t.69E-Ob  
1.69E-0b
9.65E-Ob
6.27E-Oh
0.0
U.II3E-Ob
1.07E-04
3.11E-05
0.0
1.25E-0R
+/-.95E-0b
7.A7E-07
1.55E-10
2.29E-11
3,43E-05
9.O0E-0B
3.47E-03  
1.32E-06
5.bSE-08 B.39E-0O
I.QBE-07
2.SQE-07
1.u4E-nb
1.8SF-Ob
1.4bE-O
b.77F-07
3.92E-nh
1.PtE-06
?.62E-11 I.IaE-tl
1.83F-10  
7.b9E-1I
1.29E-05 S.PE-,)h
2.L5E-nq
2.2LE-I0
0.13E-12
5.61;E-13
3.83E-n7
6.0QE-O0
3.0
1.6hE-06
3.0
3.O0E-OR
0.0
3.91E-08
0.0
!.hAE-09
1.6QE-O5
7.3RE-Ob
;.87E-Ob
3.?IE-0h
3.85E-B8 P.4iE-08
3.21E-OB
2.12E-O0
0.0
1.09E-Ob
0*0
7.6?E-111
0.0
3.,qE-10
0.0
3.64E-11
0.0
7.01E-09
0.0
1.27E-12
0.0
1.55E-06
1 .34E-07 u.L?7E-07
8.27E-09
0.0
I 30E-05 I .69E-Ob
0.1
0.0
0.0
7.u"UE-09
0.0
0.0
0*.0
0.0
0.0
0.0
0o0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0}
0.0}
0.0
0).0
0.0
0.0
0.,0
0.0n
0.0
0.0
0.0
0.0
0.0
0.0A
0.0
KI)NEY
S.3LIE-07
0.0
4.27E-07
6.27F-OQ
0.0
1I 30E-05
1 ,bqE-06
0.0
0.0
I .OOE-0O
?. 5SE-09 I I23F-06 I .b3E-10
0.0
0.0
0.0)
00
0.0
0.0
5,7 8 F-10
8.b2E-0b I . Q48E-09
5.27E-12
5.bQE-07
0.0
0.0
0.0
0.0
0,0
0.0
0.0
6,0
0.0
0.0
0.0
0.0
0.0
1 I 34E-07
?.23E-Ou u.27F-07
6 *27E-O9 n.0
,1 I
E-n5
1 69F-Ob
0.0
0=0
S. OE-06
1 .75E-06
1 .18E-06
;o.RE-05
1 .27F-04
*.62F-05
1 .16bF-04i
7,L7E-04 A,21E-06
?.23E-05
7.01E-n7
*.L1E-07 I .OE-04
2,39E-Ob
1.15E-07 Li. LiE-OS
n100
0.O
0.0
0.0
0.0
0.0
0.0
0.0
I .75E-04 I .20E-03 u.92F-Ob
2.06E-Ob
2.12E-05
2.L1E-07
2.1 3E-0 4 GI-LLI
1 3LiE-0 7
1 .b7E-05 Li.*27E-07
*.27F-09
9.24E-09
1 , 30E -09
1 .bqE-Ob
1
* 08E-05
2.AbE-07
3.23E-05 uL
5 I E-07
9.b7E-Ob
2.53E-06
"7.SuF-Ob
2. 3SE-05
3.93E-06 I I ;3L-05 I. ,3E-OS
3 ,* .':6, -05 b. 1 IE-07
1 .67F-06 I , 5E -0O
h. 12E-06 b.bBF-06 I .71E-05
2,0* E-09
3.33E-Ob I . 30F-0b
2.qOE-08
2.05E-1 3
0.0
2.08E-O0
2.88E-07
4,i 11E-1I
0,0
4**37E-05
9.02E-05
2,59E-05
5.3RE-Ob
6.3PE-05
1 .6bE-I 0
4.81E-OS
Note:
0.0 means insufficient data or that the dose factor is <].OE-20.


TABLE E-1Ot    CONTID
1.109-47
                                    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-04&#xfd;
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
TABLE C-1 (Continued)
                                  PAGE 3 OF    3 INHALATION  DOSE FACTORS FOR    INFANT
NUCLIDE
                          (MREM  PER PCI INHALED)
BONE  
NuCLIOE    BONE   LIVER     F.BODY       THYROID   KIDNEY     LUNG  GI-LLI
LIVER  
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
TOTAL BODY  
                                    1.109-55
THYROID  
KIDNEY  
lltlN;
.I-i.LI
39Y
92
1.2qE-09  
0.0
3.77E-11  
0,0
0.0
1.bE-0h QIqE-ob
39Y
93
1.19E-08
0.0
3.26E-10  
n00
n.0
b.n7E-nh
5.,7f.-05
40ZR
q3
5,22E-05  
292E-o06
1,37E-O
0,0
.llF-0-5
'113E-05 I1.5F-06 UDZR
95 t.34F-05
4,30E-06
2.91E-0h m.0
b.77E-0h
2.22F-ou
1.4L-0c)
40ZR
97
1.21E-OB
2.U5E-09 I.13E-nQ
0,0
3.71E-09
4.SE-0b b.5UF-05
41NB
934
3  
3.lOE-05  
1.0IF-n5
2.AqE-n6 A.0
1.IE -0S
3.1IF-n
2,;BEE-0b.


TABLE E-1i PAGE 1 OF 3 INGESTION DOUSE FACTORS FOR ADULTS
UINB
                                    ( M REM PER PCI INGESTED)
95
NUCLILE    BONE      LIVER              T.BOGY                THYROID        KIDNEY            LUNG          GI-LLI
1,7kF-0  
-11    3 NO DATA    I.05E-07            I.05E-07              1.05E-07        1.05E-07        1.05E-07      1.05E-0
*.77E-n7
C  14  2.84E-06  5.68E-07           5.68E-07              5.68E-07        5.68E-07        5.68E-07      5.68E-0
5.2hE-07  
NA  24  1.70E-06  1.70E-06            l.TOE-06              1.70E-06        1.70E-06        1.70E-06      1.70E-O
0.0  
P  32  .1.93E-04  1.20E-05            7.46E-06              NO DATA          NC DATA        NO DATA        2.17E-0!
9.b7E-n7 b.12F-05 I.30E-65
CR  51  NO DATA    NO DATA            2.6bE-09              1.59E-09        5.86E-I0        3.53E-09.      6.69E-0          .
41N8
MN  54  NO UATA  4.57E-06            8.72E-07               NO DATA          1.36E-06        NO DATA        1.40E-0
97
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
2.783E-11
'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
7.03E-12 P.56E-I?
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
0.0  
                        - - - - -- - - -- -- -- -- - -- -- - - - - - - - - - -  - - - - - - - - - - - - - - - -  - - - -- .5:
5. 1E-12
                                                      1.109-56
.oO
F-07  
1.2F-0H
u24n
93
0.0  
1.17F-nb
3.17E-1;
q.n
.S55E-07  
5.11E-05
1.7qF--t U2MD
Q9
0.0
1.51E-0B
2.87E-19
0,n
;.&deg;UE-nB
1,1 AE-05 i.10-05
431C
994 0.n
3.64E-13
4 .h3E-1P
0.0
5.52E-12 P.SbE-n9 S.20F-n/
437C
9q
0.0
U.64F-0R
I.37E-04  
0.0
5.95E-07 l.nIE-04
7.SuEE-0b Q3TC
101
0.0
7.52E-15
7.38E-14 n0.0
1.35F-13 U.9qE-ns
0.0
44RU tn3 l.91E-07  
0.0.


TAB3LE E-11,  C(JNT'D
9.23E-fl
                                        PArE  2 or 3 INGESFION DOSE FACTOOS FOR ADULIS
0.0
                                (MREM PER PCI INGESTFD)
7.2qCE-07
      NUCLICE    BONE    LIVER      T.BODY      THYROIC    KIDNEY    LUNG      GI-LLI
6.32E-05  
    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
1.S
      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
-o..
  .. r2132    2.52E-06 1.b3E-O6i    1.5.-E-06    1.8E-C6    1.57E-05 NO DATA    T.7.12E-05
4uRU 105
      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
9,ASF-11
      1 132  2.03E-07 5.43F-07    1.90E-07    1.90E-05  8.65L-07  NO DATA    1.02E-07
0.0
      [ 133  1.42E-06 2.'t7E-06    7.53E-07    3.63E-04   4.31E-06  NO DATA    2.22E-06
3.RqE-l1
      1 134  1.06E-07 2.881-07    1.03E-07   4.99E-06    4.58E-07  NO DATA    2.51E-10
0.0
      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
1.27E-10  
                                          1.109-57
1.3AE-0b b.0?E-flb
'JLRU 106
8.64E-0b
0.0
I.0qE-06
0.0
1.67E-05  
1.16E-03
1.i
1 E-oll
45RH 105 q.24F-10
b.73F-10  
4.43E-10  
n.0
2.hE-nQ
2.'41E-ntb
1.01)E-05
46PD 107
0.0
q,27F-08 5,87E-09  
0.0
b.57E-07 Q.ugE-Ob
7.OhE-(,7
46PD 109
0.0
4.b3F-10
1.16E-itf n.0
?.35E-og
1.85E-Ob
1.52i-fS
47AG
1I104
1.335E-06 I.25E-06  
7.a3E-07 n.(
2.3bF6-06  
5.OE-04  
3..763 -05
47AG I1 I
,425E-08 I ./BE-08i A.8TE-Oq o,0
5. 7uE-P h
2. 34E-n)5 P.l79F-np I
URCO 113M
n.0
1.54E-0O
'.q7E-06  
0.0
1.71E-n4
2.06F-0U
1.99E-n5
48CO 115M
0.0
2.ab4-05
7.qSE-01
0.n
1.9RE-05  
1.7bE-Ou
.8OE-05
50SN 123
3.02E-05  
6.66E-07  
9.P2E-07  
5.6bE-07  
0.o P.89E-00
3 .92 -n5i
50SN 125
1 .IhF-0b
3.13E-08  
7.03E-06
2.59E-03
0.0
7,u2E-05  
.MIE-05
50SN 12b
1.58E-04 J.I BE-06  
6.OOE-06
1,P3E-0b
0.n I 17E-n 3  
1.59L-0P
SISB 124
3.QOF-06  
7.3bE-08
155E-06  
9.44E-09
0.0
3.1OF-0u
9.0OBF-nl9
51S5
125
8.2bE-06 B.91E-OR
I6bbE-06  
7.34F-09 P.0
?.75F-04 I.?bhf-05
51SB t2b
.O50F-07  
9.13E-09
1.62E-07  
2.75E-0
n 0.0
1.5RF-n5 b. OIE-0q
515
127
3.30E-08
7.22E-i0
1.?7E-09 3.q7E-10
0.0
?.nSE-05  
3.771F-05
52TE
12591
4.27E-07 I.98E-n7 S.84E-0A
I.31E-07
1.55F-nb
3.92F-05  
8.MSF-Ob
52TE i274
1.58E-06  
7.02E-07
1.9hE-07  
4.11F-07
5.72E-Ob
1.?OF-OQ
1.


7F-O0
52TE
127
1.75E-10
-.
03E-.11
3,87E-11
1.3.E-10
h.17F-j0
*.15E-07
7.17E-oh
52TE
129M 1.22F-0b
5.64E-o7
1.9RE-77
4.30E-07
: .S7,-0b
5E6
11SE-Oa u.7qE -01
52TE
129 b.22F-12
2.99E-12 t.5SE-12
4.87E-12
2.3L3E-11
.a2F-07 t.9bF-0 8
52TE 1314 B .74E-09
5.SE-0q
3,63E-09 BBF-01
3. bE-1A
1.82F--05 b, .9SF-0
52TE 131
1t39E-12
7.44E-13 u .'J9E-13
1.17E-1F
5.ubE-12
1.7 F-07
2. 4uE-0q
52TE
132
3.25F-07
2.b9E-Of
2.0?E-08
?.37E-0
I.S3E-n7
3,60F-05
6 .3 7E-f5
52TE
1I33M
7,24E-12
5.b0E-12
7.14E-12 6,27E-12
3.7TF-I1
5.51E-07
3.u5F-AQ
527E 134
3.84E-12
3.22E-12
1.57E-12
3.t)U E-12
2.1BE-11 Z.3UE-07
3.b9Emog
531
129
2.'49E-0b
2.1IE-O6
6.91E-O
5.55F-01
14.514E-0b o.l
2.2E-07 S31
130
5.73E-07
1.68E-Ob
6..hF-07
2.18F-04
2.blE-m6
0.0
q.hlF-07
531
131
3.ISE-O6
4.47E-06
2.56F-0b
1.0J9E-03
7.b7F-Oh
0.0
7.8hF-O7
531
132
1.45E-07 U.07E-07
1.45E-07
5.JBE-05 b.UqF-07
0.n
5.18F-0R
E
1.109-48
TABLE C-i (Continued)
NUCLIDE
531
531
531
55CS
55CS
55CS
55CS
55CS
55CS
5695 S6BA
5*A
SbBA
57LA
57LA
57LA
SRCE
5FCE
58CE
5QPP
51PR
bO lO
blPm b61 P.
blPM
b2SH
bSM
b*EU
b3EU
63EU
b3EU
6ST9 b7 1O
7LJ,
7iU
82PR
R391 BiPo
133
134
135
135 j36
137
139
139 I40
1Ul1 2
1UO
IL
IL
                                      TABLF E-,I,    CONT'D
I
                                            PACE  3 OF  3 INGESTION DOSE FACTORS FOR ADULTS
7
                                  AMREM PLR PCI INGESTED)
149
    NUCL I CE    BONE    LIVER      T. (3DY      THYROID  KIDNEY    LUNG  GI-LLI
151
    -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
151
    0E141    9..36E-09 6.33E-09    7.1[E-lC    NO DATA    2.94E-09 NO DATA  2.42E-05
153
    .E143    1.65E-09  1.22F-06    1.35E-1O      NO DATA  5.37E-10 NO DATA  4.56E-05
15?
  '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
151
                                              1.109-58
155
15h
160
Tk-T
155
917
210
210
210
BONE
I .0BE-O0
5.ObE-08
3.30E-07 I
* bOE-OR
U .hlF-05
1 ,UbF-05
4.8QE-06
5.08F-05 L4. IIE-0b
2.50F-08
1.17F-I 0
4.,86.F-0B
5 . 3 UF- 10
9 I
F25
- 11
2.49F-02
2. 3 5F -083 U3 2E -Ou I I.7E-06
3. 7bF- 1?
6.59E-07
8.37F-05
9.82gE-Ob
3.84E-07
3. 17F-O
,5* F-0q
.759F-05 I .70E-08
2. 3b8F-0d
7 IJOE-0U
I *OIF-05 I .79E-Ob
?. 21F-OS
3 . 3 7E -O0Q
6.2 IE-05 I .9SF-07 I , ObF-OQ
n.0
3.97F-O0
LI VER
I 56'F-Ob
2. 16E-07 R. ?&#xa3;E-M7 S.20E-D8
1 .06E-On I .29E-o5 I .83F-nS
7. 77F-05
7. 77E.-08
3.53F-n8
9. 32F -I a I E 15FO
63 3
8E- 15
9,LIE-i5
2. 1 7E-OA
1 bhF -In
,.88E-1 I
I ,bQE-Ob
1 .72E-n9
1.79F-04I
4.6QE-07 S.S96E-1 2
7.b2E-07
7.87E-nb
2.5UE-16 S. 37E-o8 U.87E-09 I.42F-09
1 U.RE-05
1. iF-08
5.UOE-05
9. IOE-O5 I u3SF-nS
I uSE-nb
0.0
I .OSE-n0i
2o0TE-ng
6. U7E-08
3,B5E-10
6.72E-03 I .59F-O0
9.bOE-01
5.h7E-07
7.70E- n
3.?2E-07 I .72E-0A
9.11IE-35
6.AOE-lh
1 .3 F-05
5. 36E-05 U . OE-31
3.LE-t
2
3.21F-07
!1.2nE-I 3 A. 7E-1 3
5S.


TABLE E-12 PAGE  1 OF 3 INGESTION-DOSE  FACTORS FOR TEENASER
71E-LnQ
                              (MREM PER  PCI INGESTED)
2.7 1E-1 1
NUCLICE    BONE        LIVER      T.HnUY      THYROID    KIDNEY    LUNG  GI-LLI
9.bSE-1 2
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
1 .QIE-07 I  
'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
I* E-IQ
*&#xfd;4I63  1.77E-04  1.25C-05    b.OOE-06    NO DATA  NO DATA  NO DATA  1.99E-06
2.30F-05
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
5. 7c)E-OR
*R 83    NO DATA    NO DATA      5.74E-08    NO DATA  NO DATA  NO DATA  LT E-24
I .I
  .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
E-1 3 Li.S6E-ag
---    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 * ~ I AE -0 L6 I.
                                      1.109-59


TAtLF E-12,    CONTDO
QfE-Oh
                                            PASE  2 OF 3 INGESTION DOSE FACTORS FOR TEENAGER
3.2nE-na I .'99F-00
                                    (MREM PFR PCI INGESTED)
7.21E-10
  NUCLI'2E      BONE        LIVER      T.tODY      THYROID      KIDNEY        LUNG        GI-LLI
1.SSE-Ob I O4E-09
  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
.1E7h-05
  7R 97    2.37E-09    4.69E-1O      2.16E-10    ND DATA      7.11E-10     NO DATA      1.27E-04
6. LRE-OS
  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
9,21E-Oh
  ---------------------------------------------------------------------------------------------------
2.UOE-n7
  TEL29      4.48E-08    1.'b7F-08    I.,0)E-08    3.20E-08    1.88E-07    NO DATA      2.45F-07
2. 75E-1b q.00F-05
! 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
?.1 7E-t 0
    2E132    3.49E-06    2.21F-06    2.08E-06    2.33E-06    2.12E-05    NO DATA      7.ODE-05
6.81E-09
  1 130    1.03E-06    2.98E-06    1.19E-06    2.43E-04    4.59E-06    NO DATA      Z.29E-06
3.1 OE-lO0
  1 131      5.85E-O      8.19C-06    4.40E-06    2.39E-03    1.41E-05    NO DATA      1.62E-06
8A.7E-Ou I .3?E-07 Q.58E-05 TOTAL BODY
  1 132      2.79E-07    7.30E-07    2.62E-07    2.46E-05    1.15E-06    NO DATA      3.18E-07
THYROID
      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
3.hbE-OLA
  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
2.97E-05 I . 1 7 F -OU
  3A139    1.39E-07    9.78L-11    4.05E-09    NO DATA      9.22E-1i    6.74E-11    1.24E-06
0.0
                                                1.109-60
0.0
0.0
0.0
0.0
0.


TABLE E-12,      CONT'D
0.0
                                      PAGE    3 OF 3 I:AGESTION DOSE      FACTORS FOR TEFNAGER
0).0
                              (MREM PER    PCT INGESTED)
o.n
WUCLTLE    BONE    LIVER        T.60OY        THYROID  KIDNEY      LUNG    GI-LLI
0.0
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
0,.0
'A142    2.99E-08  2.39E-11      1.84E-09      40 DATA  2.53E-11  1.9qE-11 9.18E-20
0,0
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
0,0
;qU147  9.38E-09  1.02F-08      6.11E-10      NO DATA    5.q99L-Oq Nn DATA  3.68E-05
0 . 0
  187  1.46E-07  1.19F-07       4.11E-38      NO DATA    NO DATA  NO DATA  3.22E-05
o~t
'JP239  1.76E-Oq  1.66E-10      9.22E-11      ,,n DATA  5.21L-10  NO DATA  2.67E-05
0.0
                                        1 .109-61
0.0
0,0
0.0
0(.0
,0O
0.0
0.0
0l,0
0.0
0.0
0.0
h,0
0.0
0.0
0.0
KInNEY
3,*25E-O6
3.2UE-07
.
1 F-Ob I .07E-05
2.'1IF-05 h.Olr-nR
3705F-05
7. li3F-Ili
2.0QE-nq
2. 7E-IS
0l.0
0.0
0.0
7 .*
7 .0 E-1A9
.570F-07 R.55F-l 3
1 .5AQE-0S
3.


TABLE E-13 PAGE  I OF    3 INGESTION  DOSE  FACTORS    FOR  CHILD
5F -0
                                        (MREM  PER PCI    INGESTED)
I . f6E-17
          NUCLIDE      BONE    LIVER      T.oOUY      THYROID      KIDNEY    LUNG    GI-LL!
9. IQE-O5
          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
?. 55F-nQ
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
I .56E-05
        ...
'4.* 9E-n9
          BR  84    NO DATA  NO DATA      1.97E-07    NO    DATA    NO DATA  NO  DATA LT E-24
3. 35E-04 La . 3bE-~IL
  ,i!RR  -R 8-
5. 59E-05
              85  - NO
9. 95F-07
                    NO DATA-
,I
                        DATA  NO - DATA
E-Oh t,57E-ou n,0
                              NO DATA  -- 9.12E-09    NO
0.0
                                                        NO    DATA
0,0
                                                              DATA-1-E-07 NO
2., 1 2E-02
                                                                      NO DATA
1 92F-05
                                                                          DATA NO-
2.-75E-03 LUNG
                                                                              NO. DATA
GI-LLI
                                                                                  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
0.0
                                                  1.109-62
I.09E-06
0.0
0.0
bSbF-U7
?.94F-OQ
7.,2E-o9 I.22E-05 I.30E-Otf
1.57E-06
2.11F-07
9. UE-Ob I.05b-0h S.07F-09  
2.33F-15
,;).9 E-09  
0.0
u.70E-07  
1.12E-07
1.5QE-nu
2.73L-05
?.112E-07 I.115F-17 l.UqF-07
0.0
1.70E-)5
5,.73E-nE
1.SSE-Ob
7.31E-0e
7.02F-07
2.ULF-07 u.52F-n5
1.SoE-05
9.LRF-=Ob
2.USE-05
4.73F-Au
1.02F-0O1 i.51F-3S
2.50F-05
1.27F-07
2.b6)-18
2.76F-05  
?.IhE-09
5.blE-n5
5.S4E-06
2.l tjF - nU i M. 18 F- 0
3.Q1E-05  
5.8OE-05
7.?2E-Ob
2.50E-05
3.Q4E-Ob
2.OOE-05 J.LbE-n5
3.25E-06 u.1SE-Ob .
.58F-0S
3.u3E-n4
1,59k-os
5.P.5E-0L
3,'IOE-05
1.47F-05  
5.95F-n6
9.57E-05 L.SOE-05
1.Q2E-04  
2.68E-05
3.q
-OL
1.59F-05
1.72F-06  
2.53E-07
5.57E-05
1.07F-05
3.b3E-Ob
1.94E-O5
;.63E-02
3.b6E-O5
1.11F-03
2,qSE-05
3,s1E-n2
4.19E-05
1.109-49


TABLE E-13, CONr'D
TABLE C-1 (Continued)
                                  PAGE 2 OF 3 INGESTION DOSE    FACTORS FOR CHILO
NUCLIDE
                          (MREM PR    PC[ INGESTED)
88RA 223
NUCLIDE    BONE   LIVER      T.3OOY      THYROID    KIDNEY      LUNG      GI-LLI
88RA 224
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
68RA 225
!'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
88RA 22b
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
8BRA
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
22A
1  132  8.00E-07 1.47E-06    6.76E-07    6.82E-05  2.25E-06  NO DATA    1.73E-06
89AC
1 133  5.92E-06 7.32E-06    2.77E-06    1.36E-03  1.22E-05  NO DATA    2.95E-06
225 BqAC 227
1 134  4.19E-07 7.78E-07    3.58E-07    1.79E-05  1.19E-06  NO DATA    5.16E-07
9QTH 227
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
90TH 228
3A1,39  4.14E-07 2.21E-10    1.20E-08    NO DATA    1.93E-10  1.30E-10    2.39E-05
90TH 229
                                    1.109-63
90TH 230
90TH 232
90TH 234
91PA
231
91PA
233
92U
232
92U
233
92U
23U
920
235 q2U
236
92U
237
92U
238
934P 237
93NP 23B
93NP 239 Q9PU 238
94PU 239
94PU 240
9PIJ 2ul
94tPU 242
94PU 240
95AM 201
95AM 2424
95AM 243
96CM P42
96CM 203
96CM 24,
9bCM 205
9bCM 246
96CM 247
96CM 208
98CF 252 BONE
I .80F-0O
1.98F-O5
3,00E-0O
1.25E-01
4,41E-02
4.23E-0a
2.30F 00
2. 1 7F-0O
2.00F-Ol
8.88E
00
2,2QE
00
I .99E  
00
I .63E-Ob S.n08
00
1.21F-06
5. I 0E-02 I .09&#xa3;-02
1. O* E-02 I. OOF -02
1 .OOE-02
3.67&#xa3;E-08
9.58E-03
1.69E 00
2.96E-07
2.87E-O0
?.69E 00
3,05E 00
3.04E 00
6.0SF-02
2.89&#xa3; 00
3.45E 00
9.93E-O0
1.02F n0
9.qUE-01 I , I UF-02
7.8SE-Ol
5.QOE-O1
1.?bE 00
1.25E
00
1.22E 00
I.01E 01
7.33E-01 LIVER
2.77E-07
4.7BE-08
3.56F-07
2.39E-06
1.23E-Ob
5.82E-nO
3.05E-0l
3.92E-06
3.39E-03 I .33E-01
1.31E-01
1.12E-01
9.56E-08 I .91E-01
2.4 2E-07
0.0
0.0
0.0
0.0
0.0
0.0
0.0
1,47E-01
7.99E-09
2.82E-09
3.73E-01
4,19&#xa3;-nl
4. 19E-01
3.28E-03
4.76E-01
3.46F-01
3.46E-01
3.40E-O0
I . 18F-02
2.97E-O0
2.5IE-01
3.59E-01
3,59QE-O
3.53E-at
2.91E 00
0.0
TOTAL BODY
3.bOE-05
3.96E-06
9.13E-02
4.76E-02
2. 8OE-O5
1 .36E-01
6.25E-06
6.77E-03
4.36E-O0
6.36E-2?
5.43E-O2
4.70E-08 I.9SE-OI
2.09E-07
3.66E-03
6.5QE-Ou
6,06E-Ou
6.07E-Ou
6.20E-00
9.77E-09
5.67E-O0
b.87E-OP
1.61E-n9
1.55E-09
6.6hE-&#xa3;O0
7,53E-0?
7.53E-0?
1.29E-03
7,1 7E--2 B,5'4E-02 b6,7E-02 B.73E-02 hf.uE-n2
7.50E-04
4.61E-02
3.51E-0?
7.1 &#xa3;E-f2
7.03E-a?
5.7qE-01 i .83E-02 THYROID
n.0
0.0
0,0
040
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
nO,
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0,0
0.0
0.0
0.0
0.0
0.0.


TABLE  E-13,  CONT'D
0.0
                                  PASE  3 OF .3 INGESTION DOSE FACTORS FOR CHILD
0.0
                          (MREP PER PCI INGESTED)
0.0
NUCLIUE    BONE    LIVER      T.BODY      THYROID    KIDNEY      LUNG    GI-LLI
0.0
RA140  8.31E-05 7.28E-08    4.85E-06    NO DATA    2.37L-08  4.34E-O8  4.21E-05
0.0
&#xfd;A!41  2.OOE-07 1.12C-1O    6.51E-09     NO DATA    9.69E-11  6.58E-1O  1.14E-O7
0.0
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
0).0
                                    1.109-64
0.0
KIDNEY
7.8SE-nb
1.35E-Ob I .OIE-05
6.77E-05
3.QSE-0O
b .
3&#xa3; -05
9,9 2E-02
2.22E-05 I. 89E-02 b .52E-
I-
6. (10E-0 1
5. *17E -01
5 *, L 1 E-0 7
0.0
9 . 1 SE -07
5.56E-03
2.5E-03
2 ,. -E
-03
2. 3E-n3
2, 3Sq-03
1.51&#xa3;-fl?
2. 1AF-03
5. 10E-O1
2. 7?&#xa3;-09
8. 75E -flQ
2,*,5E-01
3.?0F-01
3. 20&#xa3;-0 I
5.93E-03
3,OSE-nt
3.64E-01
5. OIE-OI
O.BbE-01
3.SOE-03
2.15E-01
1,64E-01
3.33E-ni
3.33E-01
3.28E-01
2.70E 00
0.0
2.5SE-02 q,78-03
2.92E-02
1 .17E-01
1. 61E-01I
2,21E-02
2.q F-0I
3. 78E-02
1.DIO E (in
3.50E 00
b.22E-01
5.31E-01 I.89E&#xa3;-O
5.75E-OP
3.52E-05
2..23E-01
5.33E-02 S.?2E-02
.QOF-02
5.01E-02 t.02F-0S
0.5FF-02
5.22F-02
1 .0E-05 u. 71F-Ob I .76F-01 I .b7E-0
I h7F-01 I .52F-O0
I sq9E-01 I .89F-01
5.86F-02
2.45E-02
5.bSE-n2
3.74E-02
6.32F-02
6.07F-02
5.86&#xa3;-n?
5.97E-02
5.86E-02
0.83E-al
1.56E-0l GI-I.1.1
2.B4E-O0
3.0 E-Ou
2.71E-Oa
2.94E-0O
5.00&#xa3;-05
2.52E-04 O.92E-05
3. 3uE.-Oo
3.17E-04
3. 1 7E-OU
3. 73E-05
7.9'jF-05
7.03F-05
7
* 0 3-OSi
1.02&#xa3;-05
0*lbE-05
3.89E-05 S.lf-05
0
* 80&#xa3;-05
3.57E-05 I, 2OE -nr I .ASE-O0
4.92E-O5
2.13F-05
0 . 52&#xa3;F -OIi
0.52F-Os
.20F -05
8. SE-07
.o
*05-OS
t.03E -05
.6bOE-09
5. 7qE-05 b.03E.-05
4.64E-05
'4 *. 6E -05
0. 36F-05
0.291-O',
5.b E-OS
S. 091-O0
I . 78&#xa3; -00
I
4
1.109-50


TABLE E-14 PAGE  I OF 3 INGESTION DOSE FACTORS FOR INFANT
TABLE C-2 TEENAGER INHALATION DOSE FACTORS
                          (MREM PER -PCI INGESTED)
(mrem/pCi inhaled)
NUCLIDE    BONE    LIVER      T.BODY      THYROID  KIDNEY    LUNG  GI-LLI
NUCL IDE
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.
I H  
3 bC
14l
11!INA
22
27C0
55
27CO
bO
38Sp B9
38SR
90
3c9Y
90
39Y
01
'jOZR
95 JJINB
95 U'JRU
103
44RJ;U 106 S0SN' 123
52TE 1254
52TE 127
52TE t294
52TE 132
531
129
531
131
531
133
55CS 13Ll SSCS t37
56BA 1Ji0
57LA ILJO
5ACE 1'J1
58CE I1U
U
b3EUI ISLI
QU 232
9?U
234I
9UPU 234~
QLIPU 239
9Lipu 2U0
9LJPU 24I1
95AM 24J1
96CM 24I2
9CM 244L
A ONE
0.0
5.66E-07 I
*7bF-OS
0.0
0).0
4,.84E-06 I *.48E-03 I .41E-.08 b. 72E06b
1.*3bE -Ob I . 70E-07
2.04OLE-08 I .05F-0b
5.09E-08 I b62E- II
I .49E-07
3. 75F -09
3.53E-06
4I.21IE-06 I 54~E-06
6
* LE-05
8. 02E-05
6,62E-07 I .79E-09
2.84IE-07
5. 2uF-05
9.195E-05
6. lL4E-03 I .25F-03
3.22F-01
3.67E-01I
3.66,E-0 1 I .29E-04I
I .20E-01 I .35E-03 b.99E-02 LIVER
TOlTAL 8B1)Y
1.06E-07
1.OhE-07
5.66E-07 S.bbE-07
1.76E-05
1.76E-05
2.20E-08
2.93E-OR
1.55E-07
2.OhE-07 a3.0
1 .39E-07
0.0
9.01JE-05
0.0
3.79E-10
0 .0
1.80E-07
!J.5LLE-07
3.17E-07
1.03E-07
9.7AIE-09
0.0
Q.ISF-flQ
0.0
1.3?E-07
7.6RE-08 I.1ISE-n7
2.32F-D8 b.QIE-09
7.30E-12
4I.02E-12
7.05F-08  
2.40OE-08
3.-OOE-09
2.2QE-09
2.9UE.06  
9.81E-06
5.90E-0b
3.SRE-06
2.58E-06
7.93E-n7
1.38F-04I
6.80E-05
1.03F-04I
3.79E-fl9
6.06E-10
LI.?7E-ng
4,.72E-10
l.b7E-10
1.90E-07
2.1RE-DA
2,17E-05
2,80E-06 I.02E-o5
&#xfd;.07E-06
0.0
LJ.37E-OLI
0.0
Z.72E-nS
3.4I3E-02
7.9FLE-03
5.OOF-02
9.06E-03
5.OLIF-n2 Q.13E-03 I.BLIE-0S
3.26E-Oh
4l.11F-02
7.79E-01
1.40OE-03
8,97E-0';
2.99E-02
4I.16E-03 THYROID
I .06F-01
5.bbE-07 i .7bE-05 A,(
0.0
0.0
0.0
0.n
0.0
0,0
0.0S.*
0
0.0
6.1 5E-OA
1 USE-OB
1.34E-1 1 i.FBE-05
2.54E-09
7.32E-03 I .7E-03
4.79E-04
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
0,0
0.0
0,0
0o0
K I 3NEY
LUNG
1 .O06F-07 S.b6E-07 I .76F-05 I .71E-OLI
I .07F-03 (USE
3.13E-0LJ
?.n7F-03
0.0
PMULT
3.57E-04I
3.*20E-04I
9.96E-05 DOSE
4.'I9E-05
?.05E-nS
LI 693E-0LI
FACTOR)
6.70E-05 I .33E-06
21.5LF-0LI
5.6b7E-05
0.0
0).0
0.0
I .ROE-05
1 .47F-05 P. 53F-OLI
2. 70E-05
7. 29E05 I . 72E-03
9.29E-04
3.84IE-01
9.00OE-02
3.1ILI-01
2.98E-01
3.01E-01 I
Q92E-04I
I .0 1E -0 1
6.LI7E02
1 OSE-01 U 1-LI. I
I .ObE -07
5.06eE-07 I .'J LE-Oh
1.1 I F-05
2.Q4lE-0'5
4.4 L2E -05
9.* bF-05 h. 79L-0'5 LI *
7F -05 I .6bE -05
1.1 IOE -05 I . IRF-05
1. 16L-04I
3.91E-05
8.95E-06 I . 01IE-09 LI.80E-05 b.b lE-OS
2. 16F-07
7.45FE-07
1 .25E-06 I . 12E-06
9.bOE-07
5.981E-05 I .4I2E-05
1 . OSE-04*
3.UIE-05
4,. IbE-OS
3.F81E-05
's.52E-05
'4. 13E-05
4,. 13E-05
7.94LE-08 LI.LJLE-05 LI.60E-05 N4ote: 0.0 means insufficient data or that the dose factor is <1.OE-20.


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
1.109-51
                                    1.109-65


TABLE   E-14,  CONI'D
TABLE C-3 CHILD INHALATION DOSE FACTORS.
                                        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
(mrem/pCi inhaled)
                                  PA:,E 3 OF 3 INGESTION DOSE FACTORS FOR INFANT
NUCLIDE
                          (MREM PER PCI INGESTED)
IH
NUCLIL;E    BONE   LIVER    T.3ODY      THYROID  KIDNEY    LUNG  GI-LLI
3
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
6C
                                    1.109-67
i1 IINA
?2
27C0
5a
27C0
60
3ASR
89
38SR
qO
39Y
90
39Y
QI
4OZR
95 LINR
q 5
44RU
103
44RU lOb
503N 123
52TE
125m
52TE
127
52TE
12QM
52TE 132
531
129
531
131
531
133
55CS 134
55CS 137 SbBA iaO
57LA I4O
S8CE
14l
58CE
144 b3EU IS1
92U
232
92U
234 qiPU 238
94PU 239
94PU 20
94PU 241
95AM 241
96CM 242
96CM 244 BONE
0.0
1 .69E-06
4,42F-05
0.0
I..45E-05
4.A3F-03
9.87E-08
2.01E-05
3.8IE-06
06,0E-07
5.AUE-08
3.12F-O0
I OUE-OS
I .52E-07
4.83E-I I
a.t4UE-07
1.. 08E-08 I, 05E -05 I .?3E-05
4.53E-Ob
1.68E-O0
2.34E-O4
1 ,93E-Ob
5.20F-09
8.47E-07
1.57E-0U
2.87E-04
1 .83F-02
3.73E'03
9,62E-0I
I.IOE 00
1 .09E 00
3.84E-o0
3.57E-01
4.,05F-03
2. 09E-0I
LIVER
TOTAL
BODY
2.03E-07
2.03E-n7
1.69E-06
1.69E-06
4.42E-05
4u2E-05
0.t1F-n8
7.?3E-08
2.qOF-07
5.07E-n7
0.0
4.16E-07
0.0
2.70E-14
0.0
2.65E-OQ
0.0
5.36E-07
9.86E-A7
8.05E-07
1.96E-07 t.dLE-07
0.0
2.36E-OB
0.0
3.89E-07
1.74E-07  
3.'3E-n7
5.25E-08  
2.0hE-08
1.bSF-11
1.20E-11
1.58E-07
7.03E-08
6.08E-0
.*
.91E-09
5.4OE-Ob
2.86E-fS
1&deg;25E-05 Q.a7E-0h
5,S3E-06
2T17E-06
2.b9E-O0
6,02E-05
2.16E-o'
3.38E-05 I,26E-nq
1.laE-07
9.63E-10
L.3uE-In
.24E-n7
6.30E-08
'I,9tE-oS
8,37E-06
2.IPE-05 2.OqE-n5
0.0
1.31E-n3
0.0
2.31E-04 I.OOE-01
2.38E-02
1.13E-01
2.71E-0?
I.I'4E-O.


-   ~
2,73E-0?
                                                                TABLE E-15 RECOMMENDED VALUES FOR OTHER PARAMETERS
.16E-n5
    Parameter                                                                      Equation(s)
9.73E-06
    Symbol                                  Definition                            Where Used            Values              Reference(s)*
9.31E-02
      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
2.33E-02
                                                                                                                  2 p          Effective surface density of soil (assumes a 15 cm plow          4, A-8, A-13, & C-5  240 kg/mi                10
3,17E-03
                  layer, expressed in dry-weight)
2.bRE-0O,
                  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,
b.77E-02
                                                                                                          0.2 (for other            28-31 particulates)
1.24E-02 T-4YR310
      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)
?.03E-07 I ,69E-06 a. a2E-05
Io
0.0
00                                                                                  & C-2                0.5 (for general          26
0.0
0QO
0.0
                                                                                                            population)
0.0
      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)
0.
                                                                                                          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
0
                                                                                  2 & A-3             24 hr (for maximum individual)
0.0
                                                                                                      168 hr (7 days for population sport fish doses)
0.0
                                                                                                      240 hr (10 days for population com- mercial fish doses
0.0
                                                                                  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
I .9RE-07
                  in wet weight)                                                                        cow-milk-man pathway)
4.35E-05 U.,IE-l 1
                                                                                                      2.0 kg/m 2 (for produce    34 or leafy vegetables ingested by man)
1 .4bE-07
                                                                                                                  1 Rate constant for removal of activity on plant or leaf                              0.0021 hr- w
7.24E-04
                  surfaces by weathering (corresponds to a 14-day half-life)
2.14E-02 u.t6E-03 I
  Parameter values given without references are based on staff judgments.
* 36F -03
0.0
&deg;00
0.0
0.0
0.0
0.0
0.0
0.n
0.0)
0.0r
0.0
0.0
0.0
K I )NFY
LJN.G
2.03E-07 I b69E-06
", '2E-05
3.,O*E-OLi (USE
1.67E-03
_____
. 0E-Oa
*.OOE-n3
7.26E-05 ADULT
6190E-OI
5. 72F-O0
DOSE
I 5AE-0*
1.71E-04i
3.93F-03 FACTOR)  
9.46E-04 I . 30F- 04
2.5E-Ob a.T7F-OU
I .03E-O0
0
.1.0
0.0
3.21E-n5
2.71F-05
0.69QE-0
U*Q2E-05 I. 39E-n4
3. 32F-n3 I .67F-03
7,"J3E-nl I .70F-01
5.87E-01
5.5bF-0I
5.61E-ni
3.6lE-0OJ
I .QSF-OI
.2 ? E_- n_1-_
?,02E-01 GI-LLI
2. 03R -07 I .bqE-06
9. 1,* -0o
2.H3F-0%
I.56F -05 Q1 1
,EF-Ob
..
23E-OS
LI .*
_-O
.I S2E -05 lI. 1 I- -05
7. 13 7-07
.10
3E-06 I. 53F -05 q.22E -OS)
b.52(- -05
2.168-07
7. I 7E-05 I .54E-O0
I .08E-Ob
, 22E-')7
2.. 28E-01 I.flE-05 I .07E-OP
/J. 57F -05
3.71F -05 a. V2E-is Li, &#x17d;LE -05
8. 1bE-OF
*J.S7F-05 a. 73r-05
6
0,0
Note:
0.0 means insufficient data or that the dose factor is <1.0E-20.


REFERENCES FOR APPENDIX E
1.109-52
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.
TABLE C-4 INFANT INHALATION DOSE FACTORS
(irirem/pCi inhaled)
NUCLIDE
bC
1"
IINA
22
27C0
58
27C0
b0
38SQ
Q.


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.
38SR
QO
39Y
00
39Y
91
4nZR
05
4INB
05
4JRUi
103
44RU
106
50SN
123
52TE 1254
52TE
i27
52TE
1294 S2TE 132
531
129
531
131
53!
133
55CS
13u
55CS 13 7
5b8.


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
!LAO
    1973.
57LA 1LO
5BCE 1l1
58CE
IlUq b3EU
154
92U
P32
92U
234 quPU 238
9gPU 239 gapu PLao
94PU
2U1
95AM 241
96CM 2u2 obC4 2U4 S O:N F
0.0
3.6OE-O0
7.53E-05
0.0
0.0
3.01E-05
9.4FE-03
2.lOF-07 UL27E-05
7.7uE-O6
9. I6E-07 I .21E-07
6.b5E-O6
2.22E-05
3.2uE-07
1.03E-I0
Q ,UuF-07
2,25E-08
2.23E-05
2.59F-05
9.5hE-06
3. 43E-OL
".90E-04
.0 7 7E-06
1 .09E-08 i .80E-Ob
3. 3IF-O4
5.99E-0O
3.q1E-02
7.94qE-03
2.05E 00
2.33E 00
2.33E 00
5. IBE--04
7.61E-01
9,62E-03
4.L45E-0 1 LIVER
3. 07E -n7
3.6OF-06
7.53E-05
8. 39E-OR
!. OOE-07
0.0
0.0
0,0
1 .9SE-06
4. 11E-07
0.0
0.0
U.6IE-n7 I .39E-07 w. 31E-t II
4i 1 UE-07 I. I2E-08 I .b2E-05
3.n5E-05 I .38E-05
5.8QE-O0
5.22E-04 S05E-09
2.29E-3q
1. IIE-0b I 30E-04
4.95E-n5
0.0
0.0
2.66E-01
3.O0E-01
3.02E-01 I. I OE--04
2.47E-l1
8.40E-03 I. 70F-01 TDIAL 3J)Y
3.07E-07
3.bOE-06
7.53E-05 I .2nE-07
8.38E-07
5,89E-07
5.7hE-0A
5.65E-09
191 LE-OB
1.*3QE-*6
2.ULiE-07
4 . ! 9E - n
8.16E-07
7.30E-07 u.UOE-08
2.56E-1 I
1.47E-07 I .*hE-nR
5.A2E-05 I .70E-35 LA.


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.
I QE-Oh
5.23E-05
3.15E-n5
2.11IE-07
7.*
E-1 0
1.2QE-17 I .7AE-05
3.72E-05
2.71E-03
0.91E-14 S.OSE-92
5.77E-02
5.81E-0?
2.07E-05 L.96E-02
5.71 F- 14
3.07E-07
3.SAE-06
7.53E- 0 5
0.0
0.0
0.0
0.0
0.0
0.0*
0.0
0,0
LA.


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.
IlE-07
0 .O
E-
1 .0 9F-0 7 I .OOE-10
3. 63F -0 7 I .70E-05
5.21E-02 I .OIE-02
3.


7. R. J. Garner and R. S. Russel,   Radioactivity and Human Diet, R. Scott Russel    (ed.), Pergamon Press, Oxford, England, 1966.
33E-03
0.0
0.0
0.0
0.0
n.0
0.0
0.0
0.0
0.0
0.0
0.0
0.0
K I
NE Y
LU N C
3.07E-07
3.bOE-Ob
7.S3F-05 h.28F-O0
(USE
3.QRE-03 I .h5F-n3 I .09E-02 AU. Q8E-04 ADULT'
, 88E-03 I .2QE-03 DOSE
3.JiF-OU
D. OE -04 I .07E-02
2.SBF-A3 FACTOR)  
3.54E-O4
7. 03F-00b I .31E-03
2.Q8E-04
0.0
0.0
0.0
7.22E-05
5.7%E-05
,I 17E-03
1 .21E-04l
3.7AE-O0
9.06E-03
3. 99E-03
2.02E 00
*.7LE-fl I .51E
00
I .43E
00
I .45E
00
q.9OE-nf S.32E-01
3,UIF-01
5.51E-01 GI-LLI
3.07F-n7
3.OF-Oh
1 .22L-06
8.67F-06
2. *3E-('0
4.6bE-
9.89F-
*
5.


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.
1 2E -05 I .01E-05
8. b7E-Ob
11.


9. J. D. Zimbrick and P. G. Voilleque (eds.),   "1967 CERT Progress Report," USAEC Report IDO-12067, p. 36, 1968.
I SE-05
1.2bE-04
4.28F-05
9.71F-Oh I .87E-05
5.23F-05
6. b8E-05
2M2E-07
7b6hE-07 I .S3E-0b
9.80E-07
9.45E-07
2.77E-06
6.43F-05
1 .4l F-05 I
15E-OLA
3.73E-05 L.SSE-05 A. 16E-05
4.qbE-05 U.51L-05 A.51E-05
8,.bE-08 U.86E-05
5.29E-05
5.03E-05
0.n
2.65E-02
0.0
Note:
0.0 means insufficient data or that the dose factor is <1.OE-20.


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.
1 . 109-53


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.
This yields C V4(ro) = 3.17 x 107 Q74[x/Q'](r,)
0.11/0.16 U
= 2.2 x 107 Qi4 [x/Q'J(r,O)
(C-8)
where C v4 (r,O)
is the concentration of carbon-14 in vegetation grown at location (r,e), in pCi/kg;
!Q14 is the annual release rate of carbon-14, in Ci/yr;
0.11 is the fraction of total plant mass that is natural carbon, dimensionless;
0.16 is equal to the concentration of natural carbon in the atmosphere, in g/M 3 and
3.17 x 107 is equal to (1.0 x 1012 pCi/Ci)(l.0 x 103 g/kg)/(3.15 x 107 sec/yr).
The concentration of tritium in vegetation is calculated from its concentration in the air surrounding the vegetation.


12. "Permissible Dose from External Sources of Ionizing Radiation," Handbook 59,     U.S. Dept. of Commerce, 1954.
Using the method described in Reference 3, the NRC staff derived the following equation:
CV(r,o) = 3.17 x 107 QT[X/QJ](r,O)(0.75)(0.5/H)
= 1.2 x 10 7 Qi[X/Q'](re)/H
(c-9)
where Cv(r,o)
is the concentration of tritium in vegetation grown at location (r,e), pCi/kg;
H
is the absolute humidity of the atmosphere at location (r,o) in g/m3 Q&#xfd;
is the annual release rate of tritium, Ci/yr;
0.5 is the ratio of tritium concentration in atmospheric water to tritium con--
centration in plant water, dimensionless; and
0.75 is the fraction of total plant mass that is water, dimensionless.


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


14. D. S. Altman and P. L. Altman (eds.), "Metabolism," Federation of American Societies for Experimental Biology, Bethesda, Md., 1968.
The deposition should be computed only for that fraction of the effluent that is estimated to be elemental iodine.


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


16. J. K. Soldat et al., "Models and Computer Codes for Evaluating Radiation Doses," USAEC
15.5 x
    Report BNWL-1754, Pacific Northwest Laboratories, February 1974.
107 Si(r,6)Q.


17. A. L. Rogers, "Goat Keeping in the United States," International Dairy Goat Conference, London, July 1964.
(C-1l)
and Q! is the total (elemental and nonelemental) radioiodine emission rate.


18. R. G. Bond and C. P. Straub (eds.), Handbook of Environmental Control,     Vol. III, "Water      40
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).
    Supply and Treatment," CRC Press, Cleveland, Ohio, 1975.
For radioiodines, the deposition model is based only on the dry deposition process.


1.109-70
Wlet deposition, including "washout" of the organic and non-organic iodine fractions, should be con- sidered at some sites depending on the meteorological conditions (see Regulatory Guide 1.111).
For particulates, the deposition model considers both wet and dry deposition.


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


20. "Report of the Task Group on Reference Man,"  ICRP Publication 23, Pergamon Press, Oxford, England, 1975.
A value of 0.2 is taken for this factor (References
11 and 12).  
All nuclides except noble gases, tritium, carbon-14, and the iodines are treated as particulates.


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.
a.


22. M. M. Miller and D. A. Nash, "Regional apd Other Related Aspects of Shellfish Consumption -
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),
    Some Preliminary Findings of the 1969 Consumer Panel Survey," NMFS Circular 361, USDC/NOAA,
the following parameters are used:
    Seattle, Wash., June 1971.
Parameter Value Yv (vegetation yield)
2.0 kg/mi2 te (exposure time to plume)
60 days th (holdup after harvest)
1 day for garden-fresh leafy vegetables
60 days for stored vegetables tb (soil exposure time)
15 years (midpoint of reactor operating lifetime)
All other parameters in this equation are given in Regulatory Position C of this guide.


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.
b.


24.  "Draft Environmental Statement - Waste Management Operations, Hanford Reservation, Richland, Washington," USAEC Report WASH-1528, Washington, D.C., September 1974.
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.


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.
The radionuclide concentration in milk is estimated a5 Cm(r,f): FmCiV(r,e)Q
exp(-xit)
(C-12)
where C'(r,a)
is the concentration in milk of nuclide i, in pCi/liter;
CY(r,O)
is the concentration of radionuclide i in the animal's feed, in pCi/kg;
Fm is the average fraction of the animal's daily intake of radionuclide i which appears in each liter of milk, in days/liter (see Tables C-5 and C-6 for cow and goat data, respectively; for nuclides not listed in Table C-6, use the values in Table C-5);
1.109-55


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.
TABLE C-5 STABLE ELEMENT TRANSFER DATA
ELEM
H
HE
Ll BE
B
C
N
0
F
NE
N A
4G
AL
al P
S
CL.


27.  D. A. Baker et al., "FOOD - An Interactive Code to Calculate Internal Radiation Doses from Contaminated Food Products," BNWL-SA-5523, February 1976.
AR
K
CA
sc TI
V
CR
MN
FE
CO
NJ
CU
ZN
GA
GE
A5 SE
BR
KR
Re SR
Y
ZR
NB
RU
RN
Po AG
CD
IN
SN
Biv VEG/SOIL
4,BE O0
5.OE-02
8,3E-OG
4, 2E-o4
1.2E-01
5*5E" O0
7.5E 00


28. D. F. Bunch (ed.), "Controlled Environmental Radioiodine Test, Progress Report Number Two,"
===1. bE GO===
    USAEC Report IDO-12063, January 1968.
6.5E-4O
iE-ol
5.2E-02
1.3E-ol I .BE-04
1.5E-OM


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. IE nO===
S19E-0!
S.OE 00
6oOE-01
3,7E-oi
.,,6E"O,?
I . IE-03 So"E-OS
i 3E-03
2.SEOu0
2.9E-io2
6,6E-Oq
9,a4E-03
1,9E-O2
1.2E-01 (S.OE-OI
2.SE-0O
i OE-ol I.OE-02
1.3E
O0
7#bE-01
3,OE
O0
1,3E-01
1.7E-02
2.bE"03
16.7E-04
9.4LE,-03
1.2E-01l
2,5E-01
5.OOZ02
1,3E 01
5,OE' 00
9.OE"01 t,;5E-Gt
2.5E-01
3, OE-O I
2,SE-01
2,5E'03 F
m(Cow)
MILK(CD/L
I ,OE02**
2,0E-O;
5,0E-O.


30.  C. A. Pelletier and P. G. Voilleque, "The Behavior of Cs-137 and Other Fallout Radionuclides
I,0E-Oa
    -on a Michigan Dairy Farm," Health Phys., Vol. 21,p. 777, 1971.
2,7E-0"
1,2E-02
2,2E*O.


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,"
2. OE*O2
    Health Phys., Vol. 27, p. 189, 1974.
1.,E-02
2. OE-O?
4 .OE-02*4**
IOE-02
5,OE-Ou I1OE-Oa
2,5E-OP
IBE-02
5,OE-02
2.0E-02 IOE'O*.
8 , OE-03***
5.0E'06**
5,OE-06 S. GE-Ge, lOE-03
2,2E*03
2,SE-Ou
1?2E-03 I.OE-03
6,7E-01 I# 4E-02
5,0E-05 S. OE04
6,OE"03
',SE-02 S.OE"O2
2, EOE.02
3#OE-O2 B OE-O4***
I I OE-05 S OE-06
2#5E"03
7,5E-03
2.SE-02 IOE"O6 I.OE-02 I,OEOG.


32. J. J. Koranda, "Agricultural Factors Affecting the Daily Intake of Fresh Fallout by Dairy Cows," USAEC Report UCRL-12479, 1965.
5,0E'02
5aOEw02
162E-Ou I.OE-0O
2.5E-03 Ff MEAT(D/XG)
2.2E-02
2,nE-02 i.oE-n3 B.OE-n2
3.


33. M. E. Heath et al., Forages, the Iowa State University Press, Ames,  Iowa, 1973.
1IF-n2
.OE-02 I .6F-02 I SF-ot
2. OF-n2
3.OE-02 SIOE-03 I ,E-o3 Q.OF-03 u.bFE-2
'J.6 -n2 I a.E-nI
8. nE-o2
1.2E-02 a.bE-02
3,IE-02
2a3E-n3
1.4E-03
4.OE-04
4.OE-n2
1.3E-02 S,3E-03
8. DE-03
3OBE-62 I &#xfd;3F on
?.fE 01
2.OE-03
1.5E-n3
2.OE-n2
3 a I E -0'
Is.6 E-03
3,OIE.02
2.


34. "Statistical Abstract of the United States," U.S. Bureau of the Census,     93rd Edition, 1972.
, BE -01
5,OE-o3
4. G E-ot t.SE-03 I .7E-02
8.OE-n3 R.MfE-02 ELEM
SB
TE
I
VE
CS
LA
CE
PR
,jD
PM
S4 EU
GD
TB
Dy ER
T
YB
LO
NF
TA
w RE
OS
I R
PT
A U
TL
PB
81 P3 AT
RN
FR
PA
A C
TH
PA
U
NP
PU
A 4
9K
CF
ES
F -
8.av VES/S3IL
I.IE-02 I'3E 00
2,OE-02 IOE 01 I OE-02 b,OE-03
2,SE-03
2*5E-03
2,SE-03
2 5E-03
2,SE-, 3
2.E-03
2.SE0 3
2,bE-03
2.bE-03
2,SE-03
2,#E-03
2. SE-03
2, 5E-03
2, SE-o33
2 bvE-03
1,7E-OP
6,3E-03


1.109-71
===1. SE Ot===
5,3E-01
2.SE-03
3 @3E-0I
2.5E-01 b, SE-02 I9SE-01
2oSE-01
2, SE-Ol
3,SE 00
I,
E-O2
3, IE-OQ
2.5E-03 Q,2E-03
2,SE-03
2,SEmO3
2, SE,,03
2, SE"-0
2, SE"04
2, SE,03
2,SEo.03
2 , SE"03
2,SE-03
2, SE-O3 Fm(Cow)
41 LK (1/L)
I oSE-03 I .0E-03 b. OE-3l3
2.OE-02 I
* 2E-02"
. GOE-O1***
5OE-Oh SOE-Ob S.OE-Ob
5.OE-Gb
5.0E-Ob S.OE-O6
5.OE-Gb SOE-Gb
5.OE-Ob SOE-Gb S.OE-Ob SoOE-06
5IOE-06
2.5E-02 S,OE-Ou
2*5E-02
5.OE-03
5,OE-03 S.OE'03
3.BE-02
2,2E-02 b.2E-O04 S5OE-O0
3,0E-O0
S.OE-02
2.oE-02
5GOE-02
.80"03**
5. GE-O6 S. GE-Oh SOEGOb S.OEGOU
5,GOE-b
2,OE-Oh
5.GE-Gb S.0E-Oh S.OE-Gb
5,0E-06
5,OE-Ob S.,OE-Gb
5,.OE - Oh Ff MEATT(D/KG)
POE-03
7, 7E-02 I2&#xfd;9E-03
2. E-02
* OE-03
3.2E-03
2.OE-04
1.2E-03
4,7E-03
3.3E-03
4.8E-03 S. E-03
4.BE-03
3, bE-03
~4, (E-03 S.3E-03 U,*E-03
.uOE-03 u.OE-03
4.OE-03
,Ci E-O1 I.bE
O0
1.3E-03
.,E-03 uOE-OI
1,SE-03
4.OE-03
.OE-03
2.bE-G1 u.OE-O?
2,9E-04 I SE-02 I 2E-02"
GOE O0
2,OE-02
2.OE-02
3,UE-02 be OE-02
2. GE -04I
B.OE 02
3,4E-O4-
2,0E-04
1.UE-05*.**
2,OE-Oci
2. OE-O
*i-
2,OE-G04-
2,0E-O*
20GE-OU
f II
Ref. 1.


APPENDIX F
Ref. 3.
                                      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.
Ref. 13.


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):
t Refs. 7, 8, 9, 10, 14, 15, 16, 17.
                    :(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:
+t Ref. 18.
          7(R,z)   =          'DG(z)                                                             (F-2)
 
                                zRe where G(z)=       expF-     iz h)2 + exp                                                      (F-3)
E
                                L 2a j                  L    zp z
1.109-56
                                                                2a    J
 
where the terms are as defined above.
TABLE C-6 NUCLIDE TRANSFER PARAMETERS FOR GOAT'S MILK
ELEMENT
Fm (days/liter)
H
0.17 B
0.012 C
0.10
Mg
0.042 P.
 
0.25"
Cl
0.5 K
0.057 Ca
0.47
*
Fe
1.3E-04 Cu
0.013 Sr
0.014 I
0.06 Cs
0.30
Po
0.0018 Computed from the data of Refs. I and 19.
 
** Ref.
 
13.
 
1.109-57
 
QF
is the amount of feed consumed by the animal per day, in kg/day;
t is the average transport time of the activity from the feed into the mil:
and to the receptor (a value of 2 days is assumed); and Ni is the radiological decay constant of nuclide i, in days- Milk-producing animals are assumed to be on open pasture for the following grazing periods:
Reg i Uon Southern U.S.
 
Northern U.S.
 
Pasture Period Whole year (fp
1)
May - Sept. (fp = 1/2)
where fp is the fraction of the year that animals graze on pasture.
 
These data may be supplemented by information on site-specific dairy practices.
 
The concentration of radionuclide i in the animal's feed is then cv(r, a)
f fCP(e)+ (I1 f )C5 (r,)
+f(1
(-3
,
pfC(ro
-
,.p i
+
-
I
5 C~
(-
where P
Ci(ra)
is the concentration of radionuclide i on pasture grass, in pCi/kg;
I(ro)
is the concentration of radionuclide i in stored feeds, in pCi/kg; and f s is the fraction of daily feed that is pasture grass when the animal grazes on pasture.
 
following parameters will be employed in evaluating the milk pathway, unless data is supplied.
 
The site-specific Parameter QF
(animal's daily feed)
th (storage time of animal's food)
te (crop exposure time)
Yv (crop yield)
Value
50 kg/day (wet weight) for cattle
6 kg/day (wet weight) for goats
0 for pasture
90 days for stored feed
30 days
0.75 kg/m 2 (wet weight) for pasture
2.0 kg/m 2 (wet weight) for stored feed
4
1.109-58
 
c.
 
Parameters for Calculating Nuclide Concentration in Meat As in the milk pathway, the radionuclide concentration in meat is dependent on the amount and contamination level of the feed consumed by the animal.
 
The radionuclide concentra- tion in meat is estimated as F
(C-14)
where C1&#xfd;(r~o)
is the concentration of nuclide i in animal flesh, in pCi/kg;
Ff is the fraction of the animal's daily intake of nuclide i which appears in each kiloaram of flesh, in days/kg (see Table C-5 for values); and t
is the average time from slaughter to consumption, which is assumed to be
20 days.
 
All the other symbols are as previously defined.
 
Beef cattle will be assumed to be on open pasture for the grazing periods outlined for milk cattle.
 
4.
 
Annual Dose from Atmospherically Released Radionuclides in Foods The annual dose resulting from ingestion of radionuclide i in the diet is given by
0 .
(r,,,) = DFIi4a [Uvf Cv(r,.) + UCr,) + U FC(,
+ ULf CL(r, e ija i
[a a g i a i -
Ua i a
U.
 
r (C-15)
where D . (r,e)
Dija is the annual dose to organ j of an individual in age group a for nuclide i, in mrem/yr;
DFIija is the dose conversion factor for the ingestion of nuclide i, organ j, and age group a, in mrem/pCi (from Tables A-3 through A-6 of Appendix A of this guide); and v
m F
L
Ua , Ua, Ua, Ua are the ingestion rates of produce (non-leafy vegetables, fruit, and grains),
milk, meat, and leafy vegetables, respectively, for individuals in age group a (from Table A-2 of Appendix A of this guide).
All the other symbols are as previously defined.
 
The annual dose to organ j of an individual in age group a from consumption of vegetables, milk, and meat is therefore DvD =
DF
.rvf
+ m
+ F F
L
L
ja ija a g 1 a i a i a k I
(C-16)
1.l0-59
 
REFERENCES FOR APPENDIX C
I.
 
Y. C. Ng et a), "Prediction of the Maximum Dosage to Man fro;m the rallout cif ucclar Devices, IV Handbook for Estimating the Maxi'ium Internal Dose tro, m RPdio!;uclide:;
&#x17d;,Pc
:d-,
to the Biosphere," USAEC Report UCRL-5D163, Part IV, 1968.
 
2.
 
R. C. Weast (ed.), "Handbook of Chemistry and Physics," CRC Press, Cle,',eland, Ohio,
1D70.
 
3.
 
L. R. Anspaugh et al,
"The Dose to Man via the Fooo-Chain Transfer EResultinq fro!:m Exposure to Tritiated Water Vapor,"
USAEC Report UCRL-73195, Rev.
 
1i,
1972.
 
4. B. H. Weiss et al, "Detailed Measurement of 1-13' in Air, Veqetation and
'i1[' ;.-ound Three Operating Reactor Sites," NUREG-75/021, U.S. N~uclear Regulatory Commission, Washington, D.C.,
March 1975.
 
5.
 
D. F. Bunch (ed.),
"Controlled Environmental Radioiodine Test, Progress R.eport Num!.,
To,"
USAEC Report ID0-12063, January 1968.


6.
6.


1.109-72 M ME &#xfd;"-77-   ,  :E &#xfd; - ,
J. D. Zimbrick and P. G. Voilleque, "Controlled Environmental Radioiodine Tests at le National Reactor Testing Station, Progress Report Number Four," USAEC Report iO--126E.


The gamma dose rate to air at a distance of r meters from a point source of q curies is
December 1968.
                                                            1):
                            Equation 7.33 of Ref.


expressed by (see Pa q(3.7xlOl10)E(l.6xlo -6)B(p,jia        r)exp(-or)
7.
                                                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:
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.
                          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:
!nter- national Atomic Energy Agency, IAEA/SM-180/44, Vienna, Austria, Vol.
: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.


The buildup factor given in Reference I is of the form B(p,var) : 1 + kpr                                                                            (F-11)
1: pp. 169-190,
  where k        "a                                                                                 (F-12)
1974.
                  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)
8.
                                    0
 
I
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.
    and an.         21        a        G(z)exp(-Pz)dz                                                  (F-15)
 
                                  z
9. F. 0. Hoffman,
                                    0
"Parameters To Be Considered When Calculating the Age-Dependent 131i Doe to the Thyroid," Institute fur Reaktorsicherheit, IRS-W-5, April 1973.
  where El(z) is the exponential integral defined by El(GZ)     =        f    exp(-r)r prz d(pr)                                           (F-16)
 
                                                                1.109-74
10.
 
F. 0. Hoffman,
"A Reassessment of the Parameters Used To Predict the Environmental Trans*ort of 1311 from Air to Milk," Institute fur Reaktorsicherheit, IRS-W-13, April 1975.
 
11.
 
C. A. Pelletier and P. G. Voilleque, "The Behavior of 137Cs and Other Fallout RadiontucI'det.
 
on a Michigan Dairy Farm," Health Phys.,
Vol.
 
21, p.
 
777,
1971.
 
12.
 
P. G. Voilleque and C. A. Pelletier, "Comparison of External Irradiation and Consutrption of Cow's Milk as Critical Pathways for 1 3 7Cs,
5 4Mn and
14 4 Ce- 14 4 Pr Released to the Atmosphere," Health Phys.,
Vol.
 
27, p. 189, 1974.
 
13. R. J. Garner, "Transfer of Radioactive Materials from the "i,T,'restrial Environ;nent to Animals and Man,"
CRC Press, Cleveland, Ohio, 1972.
 
14.
 
F. W. Lengemann,
"Radioiodine in the Milk of Cows and Goats After Oral Administration of Radioiodate and Radioiodide," Health Phys., Vol.
 
17, pp. 565-9,
1969.
 
15.
 
R. J. Garner and R. S. Russell, Radioactivity and Human Diet, R. Scott Russell (ed.),
Pergamon Press, Oxford, England,
1966.
 
16.
 
P. M. Bryant, "Data for Assessments Concerning Controlled and Accidental Releases of
1311 and 13 7 Cs to the Stratosphere," Health Phys.,
Vol.
 
17, p.
 
51,
1969.
 
E
I.109-60
 
REFERENCES (Continued)
17.
 
J. D. Zimbrick and P. G. Voilleqije (eds.), "1967 CERT Progress Report," USAEC Report
100-12067, p.
 
36, 1968.
 
18. R. S. Booth et al, "A Systems Analysis Methodology for Predicting Dose to Man from a Radioactivity Contaminated Terrestrial Environment," Proceedings of the Third National Symposium on Radioecology, USAEC Report CONF-710501, Oak Ridge, Tenn.,
pp. 877-893,  
1971.
 
19.
 
D. S. Altman and P. L Altman (eds.), "Metabolism," Federation of American Societies for Experimental Biology, Bethesda, Md.,
1968.
 
1.109-61
 
APPENDIX D
MODELS FOR CALCULATING POPULATION DOSES FROM
NUCLEAR POWER PLANT EFFLUENTS
Calculation of the annual population-integrated total body and thyroid doses should be performed for the three effluent types identified in this guide.
 
These doses should be evaluated for the population within a 50-mile radius of the site, as specified in paragraph D, Section II
of Appendix I to 10 CFR Part 50.
 
For the purpose of calculating the annual population-integrated dose, the 50-mile region should be divided into a number of subregions consistent with the nature of the region.
 
These subregions may represent, for example, the reaches of a river or land areas over which the appro- priate dispersion factor is averaged.
 
Dispersion factors, population data, and other information describing existing or planned uses of the subregions should be developed.
 
1.
 
General Expressions for Population Dose For pathways in which the permanent and transient population of the subregion can be con- sidered to be exposed to the average radionuclide concentrations estimated for the subregion, the annual population-integrated dose is calculated as follows:
D
0.001 Z Pd f
Djdafda (D-l)
Dd Yd jad where Djda is the annual dose to organ j (total body or thyroid) of an average individual of age group a in subregion d, in mrem/yr;
D
is the annual population-integrated dose to organ j (total body or thyroid),
i in man-rems or thyroid man-rems;
fda is the fraction of the population in subregion d that is in age group a;
P d is the population associated with subregion d; and
0.001 is the conversion factor from millirems to rems.
 
The annual dose to the total body or thyroid of an average individual should be evaluated with the usage factors of Table 0-1. Models and equations for the detailed dose calculations are presented In Appendices A, B, and C of this guide.
 
The annual population-integrated doses from ingestion of potable water, inhalation of airborne effluents, and external exposure to airborne or deposited radionuclides should be evaluated.
 
For pathways that involve food products produced in the subregion, the food products may be distributed to other areas for consumption.
 
For all the food that is produced within the
50-mile radius, the radioactivity concentrations are averaged over the entire area by weiqhting the concentrations in each subregion by the amount produced in each subregion.
 
This average concentration is used in calculating the population doses.
 
The 50-mile average concentration of nuclide i in food p is computed as C
= (/V
) exp(-Ait )
C
v
(0-2)
ip p
1 p d dip dp The population-integrated dose is the summation of the dose received by all individuals and has units of man-rem when applied to the total body dose and units of man-thyroid-rem when applied to the summation of thyroid dose.
 
1.109-63
 
TABLE D-1 RECOMMENDED VALUES TO BE USED FOR THE AVERAGE INDIVIDUAL
IN LIEU OF SITE-SPECIFIC DATA
PER CAPITA USAGE FACTORS (I
lAY
CHILD
TEEN
ADULT
Uap)
PATHW
JNITS
Fruits & Vegetables
& grain Milk Meat & Poultry Fish Seafood Drinking water Shoreline recreation Inhalation External Exposure from Deposited Airborne Radio- active Materials
200.00
170.00
37.00
2.20
0.33
260.00
9.50
2700.00
240.00
200.00
59.00
5.20
0.75
260.00
47.00
5100.00
190.0
110.0
95.0
6.9
1.0
370.0
8.3
7300.0
kg/yr
1/yr kg/yr kg/yr kg/yr
1/yr hr/yr m 3/yr
8760.00
8760.00
8760.0
hr/yr Consumption rate obtained from Reference 3 of Appendix A and in Reference 4 of Appendix A.
 
Data obtained directly from Reference 4 of Appendix A.
 
Data obtained directly from Reference 15 of Appendix A.
 
age-prorated using techniques i
1.109-64
 
where C d is the average concentration over subregion d of the nuclide i in pathway p, Cdip in pCi/kg or pCi/liter (see Appendices A and C of this guide for models and equations for calculation of pathway concentrations);
C ip is the 50-mile average concentration of nuclide i in pathway p, in Cip pCi/kg or pCi/liter;
t is the transport time of the food medium p through the distribution system, p
in days (Tahle D-2 presents estimates of the transport times that may be used in lieu of site-specific data);
v d is the annual mass or volume of food medium p produced in subregion d, Vdp in kg or liters;
V
is the mass or volume of the food medium p produced annually with the p'
50-mile radius about the site, in kg or liters; 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 P p = Vp/X Uapfa
(0-3)
where fa is the fraction of the population within the age group a;
P
is the estimated population that can be served by the quantity of food p p
likely to be produced within 50 miles of the site;
U a is the use or consumption factor of food medium p for the average Uap individual in age group a, in kg/yr or liters/yr (taken from Table 0-1);
and V
is the annual mass or volume of food medium p likely to be produced within a 50-mile radius about the site, in kg or liters.
 
The annual population-integrated dose is then calculated as
?~O~
0.001
1 P
8 *U ODF.
 
(0-4)
DiP=
.Ol Z p
*.*fa&#xfd;CipUapDai(-4 where P
if Pp < P
Pp p
5 P 50 if P p > Ps and DFai is the dose factor for age group a and nuclide i, in mrem/pCi (taken from Tables A-3 to A-7 and C-1 to C-4);
1.109-65
 
TABLE D-2 RECOMMENDED VALUES FOR THE TRANSPORT TIMES IN THE FOOD
T
DISTRIBUTION SYSTEM
FOOD MEDIUM
Fruits, grains, and vegetables Milk DISTRIBUTION TRANSPORT TIME (in days)
Meat and poultry Sport fish Commercial fish Drinking water
14
4
20
7
10
IO
To be used in lieu of site-specific data on food distribution.
 
4
1.109-66
 
D.
 
is the annual population-integrated dose to organ j (total body or thyroid),
Dj in man-rem/yr or thyroid man-rem/yr;
Pp is the population consuming food medium p; and P5 0
is the total population within 50 miles.
 
All other factors are as defined above.
 
Note that the above formulation limits the evaluation of the exposed population evaluation to the population residing within 50 miles as specified in paragraph D, Section II of Appendix I
to 10 CFR Part 50.
 
In calculating the annual population-integrated total body and thyroid doses, the current age distribution of the population within 50 miles may be assumed to be the same as the current age distribution of the U.S. population (see Reference for Appendix D).
Models and equations for the detailed dose calculations are presented in Appendices A, B, and C.
 
2.
 
Use of the Models a.
 
Population-Integrated Doses from Liquid Effluents The annual total body and thyroid population-integrated doses due to exposure to liq- uid effluents should be evaluated for the following principal pathways:
potable water, aquatic food products, external irradiation from shoreline deposits, and terrestrial food products irri- gated with water that has received the liquid effluent.
 
In addition to these pathways, other exposure pathways that arise from unique conditions at a specific site should be evaluated if they provide a significant* contribution to the annual dose received by an exposed population group.
 
(1) Doses from Potable Water The annual population-integrated total body and thyroid doses from water consump- tion are evaluated for all subregions that have water intakes existing or designated at the time of the license application.
 
The products of the individual doses and the population exposed in each such subregion within 50 miles from the site are summed to obtain the total dose.
 
The formulation expressed in Equation (D-1)  
may be used.
 
The total body and thyroid dose of the individuals should be evaluated using Ecuation (A-2) in Appendix A of this guide, together with the age-dependent usage factors Uap obtained from Table D-1.
 
The dilution from the discharge point to the usage point should be evaluated using appropriate hydrological models for the various subregions.
 
If the population served by a particular water supply system is not known, it can be estimated by the following:
Pw = v/c (D-5)
where c
is the average daily usage of individuals on the system, in gal/day per person;
P w is the estimated population served by the water system; and v
is the average'daily intake of the water supply system, in gal/day.
 
If the industrial usage from the water supply system is known, it can be sub- tracted from the average daily intake of the system before this value is entered into Equation
(0-5).
For the purpose of this guide, any additional pathway is deemed to be significant if a conservative evaluation of the pathway yields an additional dose contribution equal to or greater than 10% of the total from all the pathways described here.
 
Any pathway so identified should then be evaluated by a model similar to that used above.
 
1.109-67
 
The population served by a water supply system whose intake is within the 50-mile radius may include individuals who reside outside the circle.
 
This population may be pro-rated to include only the population within the 50-mile radius.
 
Conversely, a water supply system with an intake beyond the 50-mile radius may serve the population within the 50-mile radius.
 
Such exposed population should be included in the 50-mile population dose evaluation.
 
(2)
Doses from Food Products The annual population-integrated total body and thyroid doses from consumption of aquatic food products are evaluated using the production of sport and commercial harvests in the various subregions.
 
The mixing ratio (or dilution) should be evaluated for each sub- region using an appropriate hydrological model.
 
For sport harvests, the entire edible harvest is assumed to be ingested by the population within 50 miles.
 
The formulation expressed by Equation (D-4)  
should be used with the population Pp given by the results of Equation (D-3).
The age-specific ingestion factors of Table D-I may be used in lieu of site-specific data.
 
For commercial harvests, the production within 50 miles from the site is con- sidered as part of the total U.S. harvest.
 
Equation (D-2) should be used to compute the average concentration, with Vp as the total estimated U.S. commercial harvest of the aquatic food medium p.
 
The annual population-integrated dose is then computed using Equation (D-4) with Pp = PSO"
The age-specific factors of Table 0-1 may be used in lieu of site-specific data.
 
(3)
Doses from Shoreline Deposits The annual population-integrated total body and thyroid doses from recreational activities on the shoreline of the receiving water body are evaluated by sunmming the product of the individual doses in each subregion and the population exposed therein.
 
All subregions within the 50-mile radius should be considered where existing or designated recreational facili- ties exist.
 
If available, actual recreational usage in the vicinity of each facility should be used.
 
The formulation of Equation (D-1)
is appropriate.


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


The .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.
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.


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


1.109-75
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.


SUBROUTINE DINT
(See Regulatory Position C.1 of this guide.)
C**
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,  
        COMMONDATAIT/GMUZKHSSIGMZEBARDIM
NE, etc.)
    DOSE INTEGRAL SUBROUTINE -K.F.       ECKERMAN 11-24-74 r~r, C
and annuli at distances of 1, 2, 3, 4, 5,  
C    SUBROUTINE EVALUATES THE DOSE INTEGRAL 'IT' AS DEFINED BY EON 7.61 C,   IN MET & AE-1968.      THE TWO DIMENSIONAL INTEGRATION IS EVALUATED
10, 20, 30, 40, and 50 miles from the center of the facility.
C .  USING GAUSSIAN-LEGENDRE QUADRATURE OF ORDER 48.


C
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.
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)
(1)  
        ZLB3HS-4.*SIGMZ
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.
        ZUBBHS+4.*SIGMZ
        IFCZLB.LT.0.)ZLBuO.


YUBUIS./GMU
Equation (D-1)  
        CZ0.5*(ZUB-ZLB)
may be used.
        GcO.S*(ZUB+ZLB)
        E8O.5*YUB
        DO 7o II21PNN
        III-II1/2 Ful.


EX=O.
For external exposure, the model does not differentiate between age groups.


IF(MOD(II,2).EQ.0)Fu-1.
A structural shielding factor of 0.5,should be applied in conjunction with the dose factor data of Table B-1.


ZZUF*X(I)*C&#xf7;G
E
        ARGUxB*(ZZ-HS),(ZZ-HS)
1.109-68
        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.


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.


Figure F-I. Staff-Written Computer Listing
Equation (D-1)
                                                                          /
may be used.
                                      1.109-76


YYzF*XCK)*E+E
The age-specific inhalation rates of Table D-1 may be used with the data of Tables C-l to C-4.
  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


SUBROUTINE      DINT
(3)  
        REAL MU
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.
        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


Gu EXP(-(Z+H)*(Z+&#xf7;H/C2.0*SIGZ2))    +  EXP (-(Z-Hi*(Z-H)/C2.0*SIGZ2))
For milk, meat, and commercial vegetables, the formulation of Equation (0-2) should be used to calculate the average concentrations in the foods.
      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


REFERENCES FOR APPENDIX F
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.
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.


(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
A
                                          1.109-80
household shielding and occupancy factor of 0.5 should be applied in conjunction with the dose factors of Tables A-3 to A-7.
                                                          *U. S.GOVERNM~ENT PRINTING OFFICE. 1988-202-292:80014
 
REFERENCE FOR APPENDIX D
"Current Population Reports," Bureau of the Census, Series P-25, No.
 
541, U.S. Dept. of Commerce,
1975.


UNITED STATES              FIRST CLASS MAIL
1.109-69}}
NUCLEAR REGULATORY COMMISSION      POSTAGE &t FEES PAID
                                          USNRC
    WASHINGTON, D.C. 20555 PERMIT No. G-67 OFFICIAL BUSINESS
    PENALTY FOR PRIVATE USE, $300
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Revision as of 00:17, 11 January 2025

Calculation of Annual Does to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix 1
ML13350A285
Person / Time
Site: WM-00011
Issue date: 03/31/1976
From:
NRC/OSD
To:
References
RG-1.109
Download: ML13350A285 (64)
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{{#Wiki_filter:U.S. NUCLEAR REGULATORY COMMISSION REGULATORY GUIDE OFFICE. OF STANDARDS DEVELOPMENT March 1976 4,s.

REGULATORY GUIDE 1.109 " " CALCULATION OF ANNUAL DOSES.,'TO MAN .fROM ROUTINE RELEASES OF REACTOR EFFLUENTS FOR THE PU.!RPOSE OF EVALUATING C 10 CFR PART SO, APPENDIX I 7.? OMPLIANCE WITH \\'~

  • %~

5- I -~ ~ USNRC REGULATORY GUIDES Comments should be sent to the Secretary of the Commission. U.S. Nuclear Regulatory Guides are issued to describe and matte available to the publc Regultory Commission. Washingon D.C 20.

Attention. Doceing and methods acceptable to the NRC still of implementing specific parts of the Service Section Commission's regulations, to delineate techntiques used by the sltff in evolu The guides are issued in the foffowing tIn broad divisions sating specific problems or postulated accidents. or to provide guidance to eppli cants. RFegulatory Guides are not substitute% for regulatlon

s. end compliance

1. Power Reactors S. Products with them is not required. Methods end solution* different from those sot out in 2. Research and Test Roesctors 7 Transportation the guides will be acceptable It they provide a basis for the findings requistse to 3. Fuels and Materials facilitlee a Occupational Health the issuance or continuance of a permit or license by the Commission 4. Environmental and Siting 2 Antitrust Review Comments and suggestions for improvements in these guides are encouraged S. Meterials and Plant Protection 10 General at ail times, and guides will be revised. as appropriate, to accommodate corn mints and to reflect now information or aspetrience. However. cuminvets nn Copies of published guiides msa be obteined by written request indicating the this guidea. f received within about Iwo months alter its Issuance will h. por divisions desired to the U.S. Nuclear Regulatory Commrsrsun Washington. O.C ticularly useful in evaluating the need for an early revision 206. Attention: Director. Office of Standards Development

TABLE OF CONTENTS Page A.

INTRODUCTION ...................................................................... 1.109-7 B.

DISCUSSION ........................................................................ 1.109-7 C.

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

.......................... 109-8 a.

Potable Water ........................................................... 1.109-8 6. Aquatic Foods ........................................................... 1.109-8 c.

Shoreline Deposits ....... ... ........................................... 1.109-8 d.

Irrigated Foods ......................................................... 1.109-8 2.

Gamma and Beta Doses from Gaseous Effluents .................................. 1.109-10 a.

Gamma Air Dose Rates for Elevated Releases .............................. 1.109-10 b.

Ganma Air Dose Rates from Ground-Level Releases; Beta Air Dose Rates from Elevated and Ground-Level Releases ........................... 1.109-11 c.

Total Body Dose Rates from Elevated Releases ............................ 1.109-11 d.

Skin Dose Rate from Elevated Releases ................................... 1.109-12 e. Total Body Dose Rates from Ground-Level Releases ........................

.109-12 f.

Skin Dose Rates from Ground-Level Releases .............................. 1 109-12 3.

Doses from Radiuiodines and Other Radionuclides Released to the Atmosphere... 1.109-12 a.

External Irradiation from Activity Deposited onto the Ground Surface .... 1.109-13 b.

Inhalation ............................................................... 1.109-13 c.

Ingestion.

.................................................. 1.109-13 4.

Integrated Doses to the Population ........................................... l.lO9-l1 5.

Summary of Staff Position..........................................1.109-14 D.

IMPLEMENTATION .................................................................... 1.109-14 APPENDIX A, METHODS FOR CALCULATING DOSES TO MAN FROM RADIONUCLIDE DISCHARGES TO THE AQUATIC ENVIRONMENT ................................................................ 1.109-17 1. Equation for Calculating Radiation Dose via Liquid Pathways .................. 1.109-17 a.

Concentration in Environmental Media (Cip) .............................. 1.109-17 b.

Usage (U ap) ............................................................. 1.109-17 C.

Dose Factor (Dp "p ) ..................................................... 1.109-20 2.

Equation for Liquid Pathways ................................................ l.l09-20 a.

Potable Water ............................................... 1.109-20 b.

Aquatic Foods.. ............................ 1.109-20 c.

Dose from Shoreline Deposits ............................................ 1.109-30 d.

Dose from Foods Grown on Land Irrigated by Contaminated Water ........... 1.109-33 REFERENCES FOR APPENDIX A .............................................................. 1.109-36 APPENDIX B, MODELS FOR CALCULATING DOSES FROM NOBLE GASES DISCHARGED TO THE ATMOSPHERE ............................................................................ 1.109-39 1.109-3

TABLE OF CONTENTS (Continued) Page 1.

Annual Gamma Air Dose from Elevated Releases of Noble Gases .................. 1.109-39 2.

Annual Gamira Air Dose from Ground-Level Releases of Noble Gases and Annual Beta Air Dose .............................................................. 1 .109-40 3.

Annual Dose to Tissue from Noble Gas Effluents .............................. 1.109-40 a.

Elevated Releases ....................................................... 1.109-40 b.

Ground-Level Releases ................................................... 1.109-42 REFERENCES FOR APPENDIX B .............................................................. 1.109-43 APPENDIX C, MODELS FOR CALCULATING DOSES VIA ADDITIONAL PATHWAYS FROM RADIOIODINES AND OTHER RADIONUCLIDES DISCHARGED TO THE ATMOSPHERE ................................... 1.109-45 1.

Annual External Dose from Direct Exposure to Activity Deposited on the Ground Plane ................................................................. 1.109-45 2.

Annual Dose from Inhalation of Radionuclides in Air .......................... 1.109-46 3.

Concentrations of Airborne Radionuclides in Foods ............................ 1.109-46 a.

Parameters for Calculating Nuclide Concentrations in Vegetation Consumed by Man ............................................. 1.109-55 b.

Parameters for Calculating Nuclide Concentrations in Milk............ 1.109-55 c.

Parameters for Calculating Nuclide Concentration in Meat ................ 1.109-59 I 4.

Annual Dose from Atmospherically Released Radionuclides in Foods ............. 1.109-59 REFERENCES FOR APPENDIX C .............................................................. 1.109-60 APPENDIX D, MODELS FOR CALCULATING POPULATION DOSES FROM NUCLEAR POWER PLANT EFFLUENTS............................................................................... 1 .109-63 1. General Expressions for Pý.pulation Dose ...................................... 1.109-63 2.

Use of the Models ............................................................. 1.109-67 a.

Population-Integrated Doses from Liquid Effluents ....................... 1.109-67 b.

Population-Integrated Doses from Airborne Effluents ..................... 1.109-68 REFERENCE FOR APPENDIX D ............................................................... 1.109-69 1.109-4

TABLE OF CONTENTS (Continued) Page 1.

Annual Gamma Air Dose from Elevated Releases of Noble Gases .................. 1.109-39 2.

Annual Gamma Air Dose from Grjund-Level Releases of Noble.Gases and Annual Beta Air Dose .............................................................. 1.109-40 3.

Annual Dose to Tissue from Noble Gas Effluents .............................. 1.109-40 a.. Elevated Releases ....................................................... 1.109-40 b.

Ground-Level Releases ................................................... 1.109-42 REFERENCES FOR APPENDIX B .............................................................. 1.109-43 APPENDIX C, MODELS FOR CALCULATING DOSES VIA ADDITIONAL PATHWAYS FROM RADIOIODINES AND OTHER RADIONUCLIDES DISCHARGED TO THE ATMOSPHERE ................................... 1.109-45 1.

Annual External Dose from birect Exposure to Activity Deposited on the Ground Plane ................................................................. 1.109-45 2.

Annual Dose from Inhalation of Radionuclides in Air .......................... 1.109-46 3.

Concentrations of Airborne Radionuclides in Foods ............................ 1.109-46 a.

Parameters for Calculating Nuclide Concentrations in Vegetation Consumed by Man ......................................................... 1 .109-55 b.

Parameters for Calculating Nuclide Concentrations in Milk ............... 1.109-55 c.

Parameters for Calculating Nuclide Concentration in Meat ................ 1.109-59 4.

Annual Dose from Atmospherically Released Radionuclides in Foods ............. 1.109-59 REFERENCES FOR APPENDIX C .............................................................. 1.109-60 APPENDIX D, MODELS FOR CALCULATING POPULATION DOSES FROM NUCLEAR POWER PLANT EFFLUENTS... ........................................................................... 1.109-63 1. GeneralExpressions for P p,,jlation Dose ...................................... 1.109-63 2.

Use of the Models ................................... ........................ 1.109-67 a.

Population-Integrated Doses from Liquid Effluents ....................... 1.109-67 b.

Population-Integrated Doses from Airborne Effluents ..................... 1.109-68 REFERENCE FOR APPENDIX D ............................................................... 1.109-69 E 1.109-4

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

A.

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

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

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

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

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

To implement Appendix I, the NRC staff has developed a series of guides that provide methods acceptable to the staff for the calculation of preoperational estimates of effluent releases, dispersion of the effluent in the atmosphere and different water bodies, and estimation of the associated radiation doses* to man.

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

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

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

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

The procedures and models provided in this guide will be subject to continuing review by the-staff with the aim of providing greater flexibility to the applicant in meeting the require- ments of Appendix I.

As a result of such reviews, it is expected that alternative acceptable methods for calculation will be made available to applicants and that calculational procedures found to be unnecessary will be eliminated.

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

B. DISCUSSION

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

This guide describes basic features of the calculational models and assumptions in use by the NRC staff for the estimation of doses.

These estimates can be used to implement Appendix I in lieu of site-specific phenomena actually affecting the estimation of radiation exposure.

In this guide, the term "dose," when applied to individuals, is used instead of the more precise term "dose equivalent," as defined by the International Commission on Radiological Units and Measurements (ICRU). 1.109-7

Appendix A of this guide describes suggested methods for calculating the estimated doses to man from discharges to the hydrosphere.

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

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

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

If other models are selected, they should include the same exposure pathways and physical mechanisms as are used in the models described in this guide.

As discussed in Section III.A.2 of Appendix I to 10 CFR Part 50, the applicant may take into account any real phenomena or actual exposure conditions that affect or modify the estimate of radiation exposure.

Such conditions should include actual values for agricultural productiv- ity, residence times, dose attenuation by structures, measured environmental transport factors (suchas bioaccumulation factors), or similar values actually determined at a specific site.

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

C.

REGULATORY POSITION 1.

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

a.

Potable Water MU1100 M ,n R QiDaipjexp(-Xitp) (1) b.

Aquatic Foods Raj'1100 U apM pn* -At2 Rapi 1100 F QiBipoaipjexp(-Aitp) (2) c.

Shoreline Deposits I W n 0 Rapj = 110,000 I QiTiOai [exp('Xitp)][l - exp(-'0t)] d.

Irrigated Foods For all radionuclides except tritium: (3) ap veg p n dIexp( A t )D . [r[l - exp(-AEite)] Biv[l - exp(-xitb)]] Rapj Uap I i ih alpj L YvEi

  • J

Uanimal n {QFd exp(Xith) r[ - exp(-Eite)] + Uap SiA aipj YvxEi BivDl - ep-lb] + pexp(-itb)] + CIAwQAw} (4) For tritium: Rp - vegC D animal api = ap v apj + Uap Dapj L A"(w +QAw) (5) 4 1.109-8

where Bip is the equilibrium bioaccumulation factor for nuclide i in pathway p, expressed as the ratio of the concentratio., in biota (in pCi/kg) to the radionuclide concentration in water (in pCi/lizer), in liters/kg; Biv is the concentration factor for uptake of radionuclide i from soil by edible parts of crops, in pCi/kg (wet weight) per pCi/kg dry soil; CiAw is the concentration of radionuclide i in water consumed by animals, a:;sumed to be equal to Ciw (pCi/liter); Ciw is the radionuclide concentration in water, in pCi/liter; D aipi is the dose factor, specific to a given radionuclide i, pathway p, organ j, and individual's age a, which can be used to calculate the radiation dose from an intake of a radionuclide, in mrem/pCi, or from exposure to a given concentration of a radionuclide in water, expressed as a ratio of the dose rate (in mrem/hr) and the radionuclide concentration in water (in pCi/liter); di is the deposition rate of nuclide i, in pCi/m2 per hr; F is the flow rate of the liquid effluent, in ft 3/sec; k is the reciprocal of the body water volume (0.0041 liter-I for beef cattle and 0.0028 liter-I for dairy cattle); Mp is the mixing ratio (reciprocal of the dilution factor) at the point of exposure (or the point of withdrawal of drinking water or point of harvest of aquatic food) as described in Table A-1 (in Appendix A of this guide), dimensionless; n is the number of radionuclides that are to be considered; 2 P is the effective "surface density" for soil, in kg(dry soil)/m . Assuming a uniform mixing of all radionuclides in a plow layer of 15 cm (6 in.) depth, P has a value of approximately 240 kg/mi2 ; QAw is the consumption rate of contaminated water by an animal, in liters/day; QF is the consumption rate of contaminated feed or forage by an animal, in kg/day (net weight); Qi is the release rate of nuclide i, in Ci/yr; r is the fraction of deposited activity retained on crops (which is 0.25 for sprinkler irrigation, 0.2 for particulates, and 1.0 for airborne deposition of radionuclides), dimensionless; R .i is the total annual dose to organ j of individuals of age a from all of the RaPj nuclides I in pathway p, in mrem/yr; Si is the transfer coefficient for radionuclide i which relates the daily intake rate by an animal to the concentration in an edible portion of animal product, in pCi/liter (milk) per pCi/day or pCi/kg (animal product) per pCi/day; t is the period of time for which sediment is exposed to the contaminated water, nominally taken to be the mid-point of the operating lifetime of the facility, in hours; tb is the mid-point of the soil exposure time (15 years for a typical power reactor), in hours; te Is the time period that crops are exposed to contamination during the growing season, in hours; 1 .109-9

th is a holdup time that represents the time interval between harvest and consumption of the food, in hours; T is the radioactive half life of nuclide i, in days; tp is the average transit time required for nuclides to reach the point of exposure.

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

These equations yield the dose rate to various organs of an individual from the exposure pathways mentioned above.

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

2.

Gamma and Beta Doses from Gaseous Effluents The NRC staff will calculate radiation doses from gaseous effluents using the following equations from Appendix B of this guide.

The definitions of elevated and ground-level releases are found in Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion for Gaseous Effluents on Routine Releases from Light-Water-Cooled Reactors," and Appendix B to this guide.

a.

Gamma Air Dose Rates for Elevated Releases 260 I DA -7(o n~~ un ns I(Ek)IE(H,u,s,oz,Ek ik (6) where Aki is the photon yield for gamma-ray photons in energy group k from the decay of radionuclide i, in photons/disintegration; DY(r,o) is the annual total gamma air dose at a distance r in the sector at angle 0, in mrad/yr; Ek is the energy of the kth photon energy group, in MeV/photon; 1.109-10

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

atmospheric stability (s) which in part determine the effective stack height (H) and the vertical plume standard deviation (o). In addition, I is a function of the photon energy E,1 and is T = 1 4 kT2 as formulated in Slade (see Reference I fi: Appendix B of this guide); 'D Qn 1 is the release rate of radionuclide i, corrected fnr decay during transit to the distance r under wind speed un, in Ci/yr; r is the distance from the release point to the receptor, in meters; un is the me;'n wind speed of wind speed class n, in m/sec; AO is the sector width over which atmospheric conditions are averaged, in radians; and ua(Ek) is the air energy absorption coefficient for the kth photon energy group, in m1 . b.

Gamma Air Dose Rates from Ground-Level Releases; Beta Air Dose Rates from Elevated and Ground-Level Releases o3 Q '/ )D r ( or DF') Dy(r,o) or DO(r,0) = 3.17 x 1O4 I[/Q ](r,o)(OFi or (7) where DF'Y OF8 I' I Dy(r,O) or D'(r,o) Qi [x/Q']O(r,e) 3.17 x lO4 c.

Total are the gar,.na and beta air dose factors for radionuclide I, in mrad per yr/ pCi per n3 ; are the annual gamma and beta air doses at the distance r in the sector at angle 0 from the discharge point, in mrad/yr; is the release rate of the radionuclide I, in Ci/yr; is the annual average gaseous dispersion factor (corrected for radioactive decay) at the distance r in the sector at angle o from the ,-elease point, in sec/m3 (see Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light- Water-Cooled Reactors," for methods to estimate x/Q'); and is the number of pCi per Ci divided by the number of seconds per year.

Body Dose Rates from Elevated Releases DT(r,a) = 1.11 SF I DY(ro)exp[-'T(Ek)t] (8) where oT(r,e) DY(r,o) k is the annual total body dose at the distance r in the sector at angle a from the discharge point, in mrem/yr; is the annual gamma air dose associated with the kth photon energy group at the distance r in the sector at angle 0 from the discharge point, in mrad/yr; 1.109-11

SF is the attenuation factor that accounts for the dose reduction due to shielding provided by residential structures (0.7), dimensionless; t is the product of tissue density and depth used to determine a "whole-body" exposure.

This depth is 5 cm, which is equivalent to t = 5 g/cm2 ; T(Ek) is the tissue energy absorption coefficient, in cm2/g; and k) 1.11 is the average ratio of tissue to air energy absorption coefficients.

d.

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

This attenuation is for 70 micrometers or 7 mg/cm2 .f tissue; and DS(r,0) is the annual skin dose at the distance r in che sector at angle 0 from the discharge point, in mrem/yr.

All other parameters are as defined in preceding sections.

e.

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

  • xi(r,o)DFBi (l0)

where DFBi is the total body dose factor for the radionuclide i which includes the attenuation of 5 g/cmn2 of tissue, in mrem-m 3/pCi-yr (see Table B-l in 4 Appendix B of this guide); DT(r,) is the annual total body dose due to immersion in a semi-infinite cloud at the distance r in the sector at angle 0 from the discharge point, in mrem/yr; and xi(r,e) is the annual average ground-level concentration of nuclide i at the distance r in the sector at angle 0 from the release point, in pCi/m 3 . All other parameters are as defined above.

f.

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

All other parameters are as defined above.

3.

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

i 1.109-12

a.

External Irradiation from Activity Deposited onto the Ground Surface Dý(r,0) = 8760 SF G cG(r,o)DFG.. (12) where CG is the ground plane concentration of radionuclide i, in pCi/m 2; Ci DFGij is the open field ground plane dose conversion factor for organ J from radio- nuclide i, in mrem-m 2/pCi-hr; DG(r,O) is the annual dose to the organ j from the ground plane concentration of all radionuclides at location (r,o), in mrem/yr; SF is a shielding factor that accounts for the dose reduction afforded by the shielding provided by residential structures and by occupancy, dimensionless; and 8760 is the number of hours in a year.

b.

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

CrO) due to inhalation of all radionuclides, in mrem/yr; DFA. a is the inhalation dose factor for radionuclide i, organ j, and age group a, ija in mrem/pCi; 3 Ra is the annual air intake for individuals in the age group a, in m /yr; and xi(r,o) is the concentration of radionuclide i in air at location (r,o), in pCi/m 3 . c.

Ingestion o r v m .FL L 1) a (ro= 2DFIi - cV(r,+) + UaCim(r,o) + U.i(r,o) + Uaf Ci(r, (14) D. (ro)ja [I a 9 i a ai + a z (4 where ,CF(r,O), C.(r,o), C.(r,O) are the concentrations of radionuclide i in produce (non-leafy-vegetables, fruits, and grains), milk, leafy vegetables, and meat, respectively, at location (r, o), in pCi/kg.

These variables are determined using Equation (C-7) from Appendix C of this guide; D3 (r,o) is the annual dose to the organ j of an individual in age group a from inges- ja tion of all radlonuclides at location (r,o), in mrem/yr; DFlija is the ingestion dose factor for radionuclide i, organ j, and age group a, from Tables A-3 through A-6 of Appendix A of this guide, in mrem/pCi; f ft are the respective fractions of the ingestion rates of produce (vegetables, fruits, and grains) and leafy vegetables which are produced in the garden of interest (Note: fg may be taken to be 0.76 in the absence of site-specific data which would indicate that the quantity of grain produced in the garden of interest would satisfy the intake values in Table A-2 of Appendix A of this guide); and U Uvn, Um , UF are the annual intake (usage) of vegetables, milk, meat, and leafy vegetables a Ua' a a respectively, for individuals in the age group a, in kg/yr.

1.109-13

4.

Inteqrated Doses to the Population The NRC staff will calculate integrated doses to the local population from all pathways discussed in Sections C.1, 2, and 3.

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

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

5.

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

D.

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

This guide reflects current Nuclear Regulatory Commission practice.

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

II I 1.109-14

TABLE 1 SUMMARY OF STAFF POSITION - TYPE OF DOSE Liquid Effluents Dose to total body from all pathways Dose to any organ from all pathways Gaseous Effluents** Gamma dose in air Beta dose in air Dose to total body of an individual Dose to skin of an individual METHODS OF EVALUATING APPENDIX I DESIGN OBJECTIVE 3 mrem/yr per unit 10 mrem/yr per unit POINT OF DOSE EVALUATION COMPLIANCE WITH APPENDIX I EQUATIONS TO BE USED Location of the highest dose offsite* (see also Table A-I). Same as above.

1, 2, 3, 4, & 5 1, 2, 3, 4, & 5 10 mrad/yr per unit 20 mrad/yr per unit 5 mrem/yr per unit 15 mrem/yr per unit Location of the highest dose offsite.*** 6 or 7, as appropriate Same as above.

7 Location of the highest dose offsite.* Same as above.

8 or 10, as appropriate 9 or 11, as appropriate Radioiodines and Particulatest Released to the Atmosphere Dose to any organ from all pathways 15 mrem/yr per unit Location of the highest dose offsite.,' 12, 13, & 14 Evaluated at a location that is anticipated to be occupied during plant lifetime or evaluated with respect to such potential land and water usage and food pathways as could actually exist during the term of plant operation.

Calculated only for noble gases.

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

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

tt Evaluated at a location where an exposure pathway actually exists at time of licensing.

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

1.109-15

APPENDIX A METHODS FOR CALCULATING DOSES TO MAN FROM RADIONUCLIDE DISCHARGES TO THE AQUATIC ENVIRONMENT The equations for estimating radiation exposure to man from four principal exposure path- ways in the aquatic environment (potable water, aquatic foods, shoreline deposits, and irrigated foods) are listed in Section C, "Regulatory Position," of this guide.

The equations can be used to calculate the annual doses to various organs of a child, 0 - 11 years; a teen, 12 - 18 years; and an adult, 18+ years.

1.

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

aipj C ip Uap aipj (A--) where Cip is the concentration of nuclide i in the media of pathway p, in pCi/kg; D ai is the dose factor which is specific to a given radionuclide. i, pathway p, organ j, and individual's age a.

It represents Lhe annual dose due to the intake of a radionuJide, in mrem/pCi, or from exposure to a given concen- tration of a radionuclide in water, in mrem per hr/pCi per liter; Raip is the annual dose to organ j of an individual of age a from nuclide i via apip pathway p, in mrem/yr; and U ap is the exposure time or intake rate (usage) associated with pathway p for lap .ge group a, in hr/yi or kg/yr (as appropriate). The three factors making up Equation (A-1) are discussed in the following sections, most of which were taken directly from the WASA-1258 report (Ref.

1). (An updated version of the portion of the WASH-1258 report describing models and computer programs is contained in the BNWL-1754 report (Ref.

2).) a.

Concentration in Environmental Media (Cip) The points at which concentrations in environmental media of interest should be evaluated are shown in Table A-1.

The concentrations can be estimated from the mixing ratio M p , the bio- accui;ýulation factor Bip, the radionuclide release rate Qi, and other terms presented in the path- way equations that appear later in this discussion.

b.

Usageý (Uap) The second term of Equation (A-l) is the usage term U ap.

Usage is expressed as a consumption rate in kg/yr or liters/yr or as an exposure time in hr/yr, as appropriate for the pathway p and age group a under consideration.

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

Such data should be documented.

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

Radioactive material released into waterways may include long-lived radionuclides that have potential for accumulation in sediments and biota and may persist for many years -- perhaps beyond the lifetime of the nuclear power station.

1.109-17

TABLE A-I DEFINITION OF POINTS AT WHICH CONCENTRATIONS IN ENVIRONMENTAL MEDIA (C ip) SHOULD BE CALCULATED SUBMERGED (single or multi- PATHWAY SURFACE - LOW VELOCITY SURFACE - HIGH VELOCITY port) - HIGH VELOCITY Fish (fresh and salt water) Invertebrates Shoreline Drinking water CO Discharge canal Discharge canal Discharge canal Nearest anticipated downstream supply*** Nearest anticipated point of withdrawal for irrigation t Edge of initial mixing zone* Edge of initial mixing zone* Point of contact of diluted effluent with shoreline Nearest anticipated downstream supply,* Nearest anticipated point of withdrawal for irrigation + Edge of initial mixing zone** Edge of initial mixing zone** Point of contact of diluted effluent with shnreline Nearest anticipated downstream supply*** Nearest anticipated point of withdrawal for irrigation- Irrigated crops Point where effluent has Point where effluent has Fresh water sites only.

over the plant lifetime, AFresh water sites only.

use projections over the or could exist.

undergone prompt dilution near the surface (about 5:1 for large receiving water bodies). undergone prompt dilution (about 10:1 in deep water and about 5:1 in shallow water). The "nearest anticipated downstream supply" is that loc3tion which, based on land use projections is the closest point to the site where a drinking water supply exists or could exist.

The "nearest anticipated point of withdrawal for irrigation" is that location which, based on land plant lifetime, is the closest point to the site where withdrawal for irrigation purposes exists ____

PATHWAY Fruits & vegetables Leafy vegetablesa Milka,c Meat & poultrya Fish (fresh or salt) Sea fooda Drinking waterc'e Shoreline recreation e Boating Inhalation TABLE A-2 RECOMMENDED VALUES FOR Uap TO BE U EXPOSED INDIVIDUAL IN LIEU OF S] CHILD & graina'b 520.0 26.0 330.0 41.0 d 6.9 1.7 510.0 5 e 14.0 29.0 2 7 00 . 0 e 51 190P.O(infant)g SED FOR THE MAXIMUM ITE-SPECIFIC DATA TEEN ADULT 630.0 520 P?.0 64 100.0 310 65.0 110 16.0 21 3.8 5 510.0 730 67.0 12 52.0 52 ,O0.,e 73 0 0 f UNITS kg/yr kg/yr liters/yr kg/yr kg/yr kg/yr liters/yr hr/yr hr/yr m 3/yr aconsumption rate obtained from Reference 3 for average individual and age-prorated and maximized using techniques contained in Reference 4.

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

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

Consumption rates are the same as the child's.

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

eData obtained directly from Reference 4.

fData obtained directly from Reference 15.

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

1.109-19

C.

Dose Factor (D aip.) Equations for calculating internal dose factors are derived from those given by the International Corninission on Radiological Protection (ICRP-Ref.

15) for body burden and ma):imur permissible concentration (r.IPC). Effective absorbed energies for the radionuclides are calcu- lated from the ICRP model.

Appendix D of Reference 16 was used as a basic source of age-dependent dose factors for ingestion.

Where data are lacking, metabolic parameters for the Standard M~an were used for other ages as well.

The dose factors for external exposure were based on the assumption that the con- taminated medium is large enough to be considered an "infinite volume" relative to the range of the emitted radiations.

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

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

The factors for converting surface contamination given in pCi/m 2 to the annual gaisia dose at one meter above a uniformly contaminated plane have been described by Soldat and others (Refs. 4, 5, and 17). Dose factors for exposure to soil sediment have units of mnrern/hr per pCi/1n2 surface.

A set of dose factors for 45 radionuclides was originally calculated for the year 2000 model (Ref.

4). These factors have since been recalculated using recent decay scheme informia- tion (Ref. 18) and expanded to include additional radionuclides.

The revised list is given in Tables A-3 through A-7; it contains several radionuclides for which the daughter is not listed separately (e.g., Ru-Rh-106, Cs-137-Ba-137m, and Ce-Pr-144). In those instances, the daughter's decay energy has been included in the factor.

2.

Equations for Liquid Pathways This section develops the set of equations required for the liquid pathway m:iodel.

Tie principal difference betveen pathways is the manner in which the radionuclide concentrations are calculated.

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

a.

Potable Water The annual dose from ingestion of water is calculated from Equation (A-2) below: Rapj = 1100 U ap Qjexp(-x. .t )Daipj (A-2) apF 1 p aipj Symbols for this equation were defined earlier, in Section C.] of this guide.

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

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

The expression (QMM /F)exp(-A t ) yields the concentration of nuclide i at the time the water is consumed.

I p i p This concentration is the term Cip in Equation (A-1). As a minimum, the transit time tp may be set equal to 12 hours to allow for radionuclide transport through the water purification plant and the water distribution system.

The transit time should be increased as appropriate to allow for travel from the point of effluent release to the water purification plant intake.

Credit may be taken for radionuclide removal by water purification processes using techniques such as those outlined in Reference 4.

It should be noted that, depending on the hydrological dispersion model employed, the mixing ratio, M'Ip, or dilution factor may not be explicitly defined.

In those instances (e.g., buildup of activity in a cooling pond), the relative concentration in the mixed stream (compared to the effluent concentration) may be supplied as a function of the radiological decay constarnt.

with any potential effluent recycling taken into account.

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

b.

Aquatic Foods The concentrations of radionuclides in aquatic foods are directly related to the concentrations of the nuclides in water.

Equilibrium ratios between the two concentrations, 1.109-20

TABLE A-3 ADULT INGESTION DOSE FACTORS (mirem/pCi ingested) 'JUCLIDE BO.E I 3 0.0 4BE 10 3.l18-06 bC 14 P.BUE-06 7N 13 B.37E-09 QF IS b.2SF-07 IPJA 22 1.70F-05 IlIA 24 21,2OF-Ob 1 5P 32 1.Q3F-04 20CA ul 1.87E-0'J 21SC Ub.

5.SIF-OQ 24CP 51 o.0 254.4 a n0 25mN 5b 0.0 2hFE 55 b.20E-0O 2bFE 59 U.3UE-0b 27Cf0 57 0.0 27C0 5B 0.0 27C0 60 0.0 28,NI 59 9.77E-06 28N1 63 1.30E-O0 284I b5 5,20E-07 2qCU b4 ).0 30ZN 65 U.SE-06 30ZN b94 1.70F-07 30ZN b9 1.03E-08 34SE 79 0.0 35RP A? n.0 355P 93 0,0 35.P 84 0.0 35BR 85 0.0 37RB 0b 0.0 37BR 87 0.0 37RB 48 0.0 37RR 89 n.0 38SR B9 3.09F-0'J 3BSR QO 7.61F-03 3RSR 91 5.82F-Ob 38SR 92 2.IbE-Ob 39Y go 9.63F-09 39Y 91M 9.10E-11 39Y 91 1.alE-07 LTVER 1.34E-n7 4.91E-n7 5.69E-07 9.37E-09 1.0 I .74E-05 2.?bE-0b 1. 21 E-05 0.0 I .nBE-08 S.57E-o6 I . I9E-07 2.79F-oS 1 .03E-09 .7 5 -07 / . I, SE -{') 7 2. 15E-0b 3. 35E-O0 9.02E-O0 b.B7E-ng 5.3'JE-06 1 .54F-05 u .0, E-07 1 9SE-08 2. 6I-06 0.0 0.0 0.0 0.0 ?.11 F-05 I .?3E-OS 6.06F-()8 U.0 1IE-O8 0.0 0.0 0.0 0.0 0.0 0.0 0.0 TnTAL 81)Y 1 .3UE-07 7.o5EF-0 ri.bqE-7 ý. 37E-09 b.93E-OR I .74E-05 2.2hE-rib 7, * 7F.-t0h 2. olE-nS 3.11 E-OQ 2.bbE-19 .8 73E-.07 2. 0SE-OR 7.33E-06 3.9?E-06 2.JI1E-07 I .67E-1b U,72E-nb I .b3E-06 4.36F-Ob 3.1 3E-08 3.92E-OR 6.97E-08 3.731E0' I .37E-0O M.dOE-07 2.?PhE-n6 4 . 2E-ný, 5.22E-O0 2.1 4E-O9 9.8UE-0b 4.28E-4b 3 . 21 E-04 2.93E-0.

5.89F-06 I .86E-03 P.ShE-07 9.31E-08 2.5RE-10 3.53E-I? 3,7RE-09 1,i 3lI-O1 n n 5, qF -07

  • l

3 7EF- 0 9 n.n I .711E-05 22.2SE-0b 0.n 1.S5QF-0* 0.0 n n 0.0 0.0 n.0 0.0 0,0 0.0 ( n 0,0 0.0 0.0 0.0 0,0 0.n 0.0 0.0 0.0 0.0 0,0 0.0 0.0 KT)NEY I, S.

3 E-fl7 3. 71E-n7 5.69F-07 8. 37E-ng 0.0 I . 74E-nc 22.

?6F.-06 0.0 0.0 I .OOF-0B 36RIE-06 l,6bE-07 0.0 0.n 0.0 0.0 0.0 0.0 0.0 ? 1 n F - n 1 03E-nS ?. USE- n7 I ?O2F-OR 41, 5 6F. -n6 n00 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 LUNG I .,OE-07 0.0 S.bqE-07 '. $7F-09 0.0 I . 74E-05 >. ?6*E-..0 0.0 ,0.

3. 53F-n9 0.0 0.0 1.23E-05 -nb 0.0 ,00 n0.

0.0 0*,0 0,0 0 . n 0,0 0.00 ,00 0.0 0.0 0.0 n00 n,0 0,0 0.0 0.0 0.0 0.0 0.0 0.0) 0.0 GI-LL I I . SiF-n7 2.bMF-0'i 5.bQE -07 6. 371F-09 I ASE-05 P. 26F-Uh 2.1I 7E -09 I ..ýJF -0i7 5.21F -05 1 . ttIE -07 3.h7F-O6 I . oW -05 5.4OF-06 1 .91F-05 ,022F-OS b790E-07 I1 .t i B F - O h 7 .i O-06 Q.70E-(6 2.49F-05 2. 9b-09 5, 38F-07 2.54F-Ob .,79F-OR u0nqF-13 0.0 4, 1bE-Oh 5. 7(E-07 8.3bF-19 0.0 MI,*4E-05 I .02E-nu 2.Q3E-05 4 , 2bf -05 1.02E-04 2,b7L-1 0 77bE7-05 Note; 0.0 means insufficient data or that the dose factor is <].OE-20.

1.109-21

TABLE A-3 (Continued) NUCLIDE 39Y 92 39Y 93 4OZR 93 0OZR 95 a0ZR 97 14tN q33 41.J N 5 QLNB q7 u2mO q3 4240 9q 43TC 994 43TC q9 43TC 101 44RIJ 103 40RU 105 LILRU 106 45RH 105 46PD 107 6bPD 109 47AG 1104 L7AG III 48CO 1134 48Co 1154 50SN 123 50SN 125 50SN 126 SISB 124 S1SB 125 SISH 12b SISB 127 '52TE 1254 52TE 127M 52TE 127 527E 12qM 52TE 129 .52TE 1314 52TE 131 52TE 132 52TE 1334 52TE 134 531 129 531 130 531 131 531 132 BONE 8.46F-10 2.6E-09 4 . IqF-08 3.0UE-OR I.68F'-09 2.55E-08 b,2sF-09 5.23E-1 I 0.0 0.0 2.47F-10 I 2bE-07 2.54F- 10 1 .85E-07 I .S4E-08 2.75E-O0 1 .22E-07 0.0 0.0 1.6bOE'-07 5.82E-0R 0.0 0.0 3.1 IF-05 8. 3bE-06 8. U6E-05 2.81E-06 2.23F-Ob 1. 15F-Oh 2.5E-07 2.b8E-Ob 6.78E-06 I 1 IOE-07 1015E-05 3. ISE-08 S1,74E-06 1.97E-08 2.53E-05 4.63F-08 3.24F-08 3.27E-Ob 7,57E-07 4, tl6E-06 2.03E-07 LIVER 0.0 0.0 2.3uE-Oq 9.76E-09 3.39F-10 S. 33E-09 3.46RE-09 1.32E-1 I 7.52E-nb U,31E-0b 6.98E-I0 1 .8hF-07 3.67E-1 0 0.0 0.0 0.0 8.86E-08 1 .47E-07 I .77E-07 2!.'JRE-07 2.44LE-08 3. 1qF-Db I .84E-0b 5.16E-07 1 .6AF-n7 1.68E-Ob 5.30E-00 2.4nF-08 2,3'E-n8 5.bhE-09 9.73E-07 2.37F-Ob 3,95E-08 4L,30E-06 1. 19E-0FB 9, 47E-07 5.24E-09 1.6LAF-0b 2.80E-08 2, 13E.-08 2.8lE-Oh 2.2*iE-06 S. 96E'-06 5.43E-07 TOTAL BODv TH)ROID 2.07E-1I 0.0 7.40E-11 n., 1.09E-09 0.0 6.61E-09 n.0 1.56E-10 0.0 2.05E-09 o0n 1.36E-nq n.n L.e2E-12 0.0 2.03E-07 010 8.20E-07 A.(' 9.9nE-Aq n.0 5.OUE-08 o.n 3.60E-19 n.0 7.qgE-0R 0.0 6.ORE-Oq 0.0 3.48E-07 0,0 S.SIE-OR 0.0 9.UIE-Oq 0.0 U.OOE-08 0.0 4.80E-04 0.0 1.21E-0B n.0 1.02E-07 0.0 5.AgE-OR 0.0 7,6OE-07 L.38F-07 3.79E-0 7 1.39E-07 2.JIE-06 4,92E-07 I.IIE-0.b 6.79E-09 4.J8E-07 1.9BF-09 U.ISE-07 7.0SE-09 9,q2E-0M 3,IIE-09 3.59E-07 8.07E-07 9.26E-07 1.73E-06 2.3AE-OR 8.16E-0B 1.82E-06 3.qSF-06 7.66E-09 2.IE-0B 7.06E-07 1.34E-06 b.22E-O9 1.62E-OR 1.51E-06 I.BOE-06 4.06E-08 3.92E-03 1.3nE-0' 2.,3E-05 9.22E-0b 7.23E-03 8.R1E-07 2.85E-OIA 3.41E-06 1.95F-n3 1.93E-07 7.15E-05 KIDN EY 0.P 0.0 8.99E-O9 I .SUF-08 5 1 P .E - 10 5,58E-09 3. U 5 E-0q I .5AE-1 I I O0hF-AR 2,34E-nb ().bOE-09 7.07E-n7 1 .'9E-07 5.32E-0b 3.76F-07 1 .. 32E-06 I .02E-O1 2. 91E-n7 7.8SF-nA 3.50F-nb I4.6F-06 0.0 0.0 0.0 0.0 0.0 0.0 I .09E-05 2.75E-05 LAI*,LRE-07 Li,.!lE-n5 1.3?E-n7 8.5E-06 R.b'E-nf 1,58E-05 2.57E-07 2.09E-n7 60 OSE-(b 3.UIE-Oh I. O.E -05 , bhE'-07 n.0 0,0 0.0,00 0.0 (0,0 0.0 0.0 0.0I 1 ,S2E-10 I .9SE-OP 0.0

  • .0

(1.0 0.0 0.0 0.0 0,0 0.0 2.1 8E-Ob 2.33F-04 7,05E-n7 I .53E-n7 0.0 0,0 0.0} 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Gl-I.Ll 9

  • SO F -6C'5

2.U3f -Oh I O5E -na 3,RU*-no 2.1 OE -05 t.SiF-05 U * 7 F-OR I .b??F -n, ,153F-n7 b.08F -('6 1bF-05 7 6 7E -('74 1,07Et-O5 b.

0Laf-it, 2.2bF-n5 7 . 7 a"E - r* S b. 33E-05 2.'3E-0S 7.95F-O5 I .97F-O0 9.40F-05 S QO2E-nh- 1,07E-05 ?.27f -15 8. b8F -Ph 2. 37Fl-08 9.4 £0E-05 7.*71 F-05 Li. I 7F -00 1 .92E-nt, I .57F-I~b 1 . n2E-07 I 1.109-22

TABLE A-3 (Continued) SUCLIDE 531 133 531 134 531 135 55CS 13U 5SCS 135 55CS 13b 55CS 137 55CS 135 55CS 139 569A 139 5654 1 a 0 5bBA IUI Sb8A IUP S7LA 1UO 57LA I U1 57LA IL2 58CE I U 5CE 143 58CE tUQ S9Pq 143 59PR 10I4 6OND lU7 6IPM ¶LI7 61PM I aB7 6IPM tuB 61Pm 151 62SM 151 b2SM 153 63EU 152 63EU 154 63EU 155 b3EU 156 65TB IbO b740 16bM 74M~ 191 740 185 744 187 52PH P O 8381 210 84PO 210 BONE 1.43F-06 1 ObE-07 4.43F-07 2.1 3E-09 6.2?F-05 I q.F-05 b.51F-ob 7.98E-05 5. 5F-08 3.£4 F-Os 0 . 7 1 F-O0S 2.03E-05 0.0 P. 13E-08 2.SOF-OQ 3.19E-10 1.28E-10 q,3 IE-Oq I.%5E-09 u.BQE-07 9.21E-09 3.02E-1 I h.30E-oq 7.55E-08 3.07E-08 7, 1BF-09 1 .52E-09 . l9 7F-I 0 6.91E-08 8.5RF-IO I .q5E-O7 6. 1bE-07 5.61E-08 I . 37F -08 4.70E-08 2.70E-07 9.9?E-09 40.bE-07 I .03E-07 I .53F-02 0.b2E-07 3.57E-OU LIVER 2.USF-06 2.SRE-07 I . I 7E-06 'J' (IQE -0B 1I USE -04.

I 80E-a5 2.57E-o5 I. .OE-0O I. OoF-o 7 5.08F-08 5.92E-I I 2.55E-08 3.56E-i 1 2. 19E-1 I I .26E-O9 9.91E-1l 5.82E-11 6, 3£4E-09 I.22E-O0 2,uE-07 3 . 70aF.-O0 I .25E'-11I 7.28E-09 7 .10 E -09 7.96E-09 I . I9E-09 2. 1SE-I 0 1.1 7E-1 0 1.1I9E-0B 7.16E-1 0 U1 ,L"JE-OB 7o.7E-08 1 .22F -n8 I .ObE-0 0.0 13.44E-09 3.24E-09 I. 35E-07 8.62E-08 U.38E-03 3.19F-Ob 7.57E-o0 TOTAL RODY THYROID KIDNEY 7.57E-07 1.03E-n7 (429E-n7 ?. 3nE-os 1.21E-OU 8.OOE-06 I .85E-05 7. 1SE-05 S.. iE-ns I .SE-08 2,84E-09 I .3E-06 1.59E-09 I .3UE-09 3.30E-10 I .62E-1 I 1 .£4S5- 11 7 .18E-10 1.3SE-10 2.bE-08 4,57E-10 1.53E-12 4.35E-I0 2.P7E-Oq b.OSE-09 6.OOE-t0 S.7qE-1 I 5.92E-1 I 2.BbE-09 5.23E-1 I 3.9IE-O0 5.39E-08 7.88E-0Q I .71E-ng 5.FbE-09 bAlE-08 3.46E-10 1.4?E-08 3,02E-08 5. £E-Oa 3.97E-08 8.60E-n5 4.77E-04 3. 74E-05 I .5jE-n0 D.0 0.0 0.(I 0.0 0.() 0.0 0.0 0.0 0.0 0.0 0.0 0*.0 0I.0 0.0 0.0 0.0 0.() 0.0 0.0 0.0 0.0 0 .0 0.0 0.0 0.0 0.0 0.0 0.0 0°0 0.0 0.0 (0.0 0 .0 0.0 0.0l 0.0 0.0 0.0 0.0 4. 33E-flb '.*5 E-9 07 1. 86E-.nh 2. 4 E .. n £4. OE..0n I , 3E..n5 3. 71E'.-)5 8.02E.-n8 4.07E-08 6.£7E-- I R.6bE-09 3.3tIF-I 1.,SFE-II I,.95E-1t 0.0 0.0 0.0 5.3.E-10 I .21E-07 2. 1 3E-09 7. 06E-1 2 I.25E-09 1I1 3UE-08 1 .2 1IF-O0S 2.25F-09 4.O7-1 0 2 . 0 9 F -1 1 . 33E-08 2.3?F-10 2.775E-07 3.621--07 5.,LIE-rib 7.09E-09 I.94E-08 1.26E-07 0.0 0,0 0.0 1.23E-n2 3. 84E-05 2.52E-03 LUNG 0.0 0.0 0.0 3.83E- 2,OSE-( I .S9F- I ,23E- 1 .Q2F- 3.70E- 3.92E- I '46F- 2, 02E- I .2UE- 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0

  • 00

0.0 0.0 0.0 0.0 0.0 GI-LLI 2. 18EOb 2.51F-1 0 1.31E-06 09 1.58E-08 05 2.%9E-O0 06 4.. 21F-07 06 2.92E-0b OS 2.10E-06 09 4.65E-13 09 0.0 11 1.72E-07 08 £*418E-05 11 2,22E-17 11 0.0 Q,25E-OS 4.25E-07 2,42E-05 4,S6E-05 I bSE-OS 4,03E-05 4.33E-18 3.49E-05 8.93E-06 6. 7E-05 9.34F-05

  • ,03E-05

3,22E-n5 S *25E-Ob 2,55E-05 2.56E-05 5.48E-05 9,60E-O0 7.26E-05 4.33E-05 0.0

  • .bSE-07

1,56E-05 2,82E-05 5,42E-05 4.75E-05 6,36E-05 1.109-23

TABLE A-3 (Continued) NUCL B8RA 88RA 8BRA 88RA B8RA B9AC 89AC 90TH 90rH 90TH 90TH 90TH 90TH 91PA 91PA 92UL 92U 92U 92U 92U 92U 92U 93NP 93NP 93NP 9'PU 94PU 9UPU 9IJPU guPU 9JPU 95AM 95AM 95AM 96CM 96CM 96CM 96CM 96CM 96CM 9bCM 98CF IDE BONE 223 4.q8E-03 224 1.b2E-03 225 h.57E-03 226 3.05F-01 228 1.12F-01 225 4.

-1F-06 227 1.88E-03 227 1.37E-05 229 4.96F-OU 229 R.ObE-03 230 2.08E-03 232 l.SOE-03 23Q .9.02F-08 231 4.I4F-03 233 5.26F-09 232 u.l4E-03 233 8.7?E-0O 234 8.37F-014 235 8.02E-04 23b 8.02E-O4 237 S.53F-08 238 7.67F-OU 237 l.38E-03 235 1.37E-08 239 1.20E-09 238 6.7SF-OU 239 7,60F-04 240 7.58E-04 2U1 1.5bE-05 242 7.22E-04 2L4L 9.60E-0O4 241 8.IOE-04 2Q2M 8.32E-0O 2i3 8.12E-0O 2U2 1.58E-05 243 b.43E-0O 244 4.851-04 24S.

1.03F-03 2U6 1.02F-03 247 9.95E-04 2'8 8.27E-03 252 1.96E-O4 LIVER 7.bbE-Ob 3.90E-Ob 7.79E-06 5.75E-06 3.1?E-06 6,07F-06 2. *8E-OU 2.4BE-07 3.41E-06 1.21E-O04 1 I1 BE -O04 I .OIE-04 4.*72F-09 I.56E-0l I .0bE-09 0.0 0.0 G00 0.0 0.0 0.0 0.0 1.20E-O0 3i,6E-10 1.18E-1O . 31E-05 I OMiE-OQ 1,04iE-04S 9.4l7E-07 990E-05 I I 1BE-O4 2.79E-04i 2.78F-00 2.7 3E-O0i I .64E-ý05 2.QIE-0OJ 2.07E-04 2.B8E-O0 2. 88E-04 2. B3E-O0 2. 33E-03 0.0 9.95E-OU 3.23E-04 I .31E-01 2.21E-01 1.21E-01 2,QsE-07 I I II E-0Q 3.96E-07 I.b8E-AS 3.95E-O0 5.76E-05 .4,9?E-05 2.32E-09 I .61E-Ou Q,2AE-In 2.95E-04 5.29E-05 5. 1RE-05 A.86E-05 4.97E-05 I .47E-O0 4.55E-05 5.5qE-05 2.1 3E- 10 6.4AE-1 1 1 .67E-n5 I .88E-05 I.88E-05 3.33E-07 I .79E-05 2.13E-05 5.26E-05 5,47E-05 5.24E-05 I.OUE-Ob 3.77E-05 2.BRE-05 5.BIE-05 5,BOE-05 5.72E-05 4.71E-O4 4.95E-06 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 000 TOTAL BODY THYROID 2.17F-04 1.11 E-oiU 2.21F-ou 1.b3E-04 8.84E-0s 6. 90F-6 7 R.03E-05 tl IE-Ob 4.67F-05 5.80E-OU 5.b9E-04 U.'3bE-ou 2.b7E-OR 1.0 3.99F-nq 4.47E-04 2.0TE-OQ I 40E -no 2.27E-07 I,75E-0U I

  • 7E-04 I .26E-n9

3.S5E-10 7. 1* E-o0 ?.9bE-05 7.96E-05 I .53E-nS 7.SRE-n5 9.03E-05 3.QbE-OU .. O8E-n4 3.95E-0O 4o.7E-0b SI

  • 7bE-0O

1. 3LE-04 2.71E-04 2.7,1E-n4 2.67E-O0 2.20E-03 0.0 KIDNEY .LUNC 0.0 0.0 .0 0.0 0.0 ,0.

0.0 0.0 ,0.

0.0 0.0 n010 0.0 0.0 n100 0.0 0.0 0.0 0,0 0.0 0,0 0.0 0,0 0 0 0.0 0.0 0,0 0.0 0.0 0.0 0.0 0.0 0,0 0.0 0.0 11.0 0.0 0.0) 0.0 0.0 0.0 G[-I.'.' 3.2 E-Ou S.,32E-Ou 5.64E-05 4.07E-04 7.q'E-05 5.JOE-Ou 5.h3E-Ou 5,12E-Oa 6,O2E-OS I *?'E-On 1.13E-Oa b.?T7-Ou I , 4F -0s b. 72E-0ý b,27E-05 b. 1 UE-05 7,BIE-05 5. 7bE-OS t.bbE-O0 7.94E-A5 7qUE-05 2.a0E-05 7.30E-05 h1b6F-05 6.78E-05 l.u0E-O0 6.5 SE-os q.,5SE-05 9,75SE-OS 7.02F-05 9. 34E-09 9. 73E-Oi 7.92E-05 7.8IE-09 7.55E-05 7.0F-05 6,9I1L-05 q. 09E-05 1.87E-O.3 2. 88E-04 I 4 1.109-24

TABLE A-4 TEENAGER INGESTION DOSE FACTORS (mrenm/pCi ingested) NUCLIDE BONE LIVER TOTAL B:oY I H 3 6C 1'J IINA 22 27C0 513 27C0 bO 38SR B9 38SR 9o 39Y qo 39Y 91 unZR 95 41,NB 95 44RU 103 OULRU job 505N 123 SPTE 1254 52TE 127 52TE 129M 52 TE 13? 531 129 531 131 531 13 95cS 134 55CS 137 5b0A 1U n 57LA 140.

5.1CE I1i0 5RCE I1aQ b3EU) 154 92U 232 92U 234 gaPU 238 9UP I 23- QUPU 240 9'PU 2a! 95AM 241 9bCM ?42 96CM 24U 0.0 7.55E-07 2.36E-09 ,00 0.0 1 .OE-02 3. 3OF-08 1 .9hE-07 3.72E-08 7.2JE-09 2,37F-07 U OOE-Ob U . 3AF -05 3.93E-06 1.51E-07 I bhF-05 3.55F-O0 L.bbF-O6 5.57E-0h 2. 03E-Ob 8.05E-05 1 .07F-O0 2.83E-05 3.43

  • 8F

-09 1 .2bE-08 7.22E-07 1 I5E-Ob 60.bE-03 1,22F-0,3 5,£0E-0a 9.2bE-04 9,25F-04 u.03E-07 9,q3E-04 2.26E-05 b

  • hL F-0 L

I ObE-07 7 .55E-07 2. 35E-35 9.92F-67 2. 76F-nb 0.0 0.0 0.0 I .2'JE-08

  • .36E-0q

0.0 0.0 7,22E-o7 I . 37E -0h 5.3?E-OM 5.15F-Ob 2,22E-Ob 3.92F-O0 7.87E-06 3."UE-Oh 1 .9QE-01 I lUUE-0LJ 3.u4E-os I .72E-09 ?.9bE-07 I .OnE-n7 0.0 0 0 I I* 1 E-O0 I . 29E -n4 I . 30F-oil 1.852E-o (.1 7E-nU 2,33E-05 3. 33E-0O I .06F-A7 7.SSF-07 2. 3SE-05 TqYq!10 1.n0E-07 7 . SSE-07 2.35F-05 2.26E-Ob 6. 30E-Ob I . 3E-15 2.57E-03 A.87F-ln0 5.?P3E-n9 8.6hE-nQ ?.u7E-OQ 1 OhE-07 5.03E-07 1 .0E-Ob 5.0AE-07 3.23F-08 2.61E-nb 2.1 nE-n6 1 .31F-05 U.6qE-nh I OhE-Ob nO 0.0 n o 0.0 0~o 0 . n 0,0 I5,13E-07 5.37E-07 I .03E0O7 5,30E-06 235SE-6 5 2.27E-03 b.?5F-0U 0.0 (USE n 0 0.0 ADULT 3.75E-nS 0.0 0.0 T 0.0 DOSE' 0.0 0.0 FACTOR) 0 ° 0 0.0 0.0 0.0 0.0 I .3JF -05 . 31E-05 4.49F-n5 2.4? eo-O0 1 .O9F-O0 7.53E-05 2.68E-05 I . 78E-05 1 .6SEF-0s I . IE-o0 6. 31F-05 I ,07F-05 I .22E-0O 5.R0E-05 8,00E-05 4.31E-07 1.49E-06 2,50E-06 OC I -)NF Y I .06F-07 7.55F-n7 2. 35F-05 GI-LLI 1.0h-07 7.55F-07 2.88-*-h 9. OhE-05 5.05E-05 I.fPE-06 4.59E-10 3,83E-O8 R.7qE-ng n,2tE-0 7.UnE-05 2.ORE-05 2.2QE-05 2.31E-05 1.02E-00 6.66E-05 I .50E-06 U.n3E-05 0.0 0.0 o.6 0).0 0,0 0.0 0.0 0.0 0.0 2.35E-05 2.24E-Oh 1.91F-05 1.q2F-06 ?.33E-09 4.tUE-Oh 0.0 Q.8F.-0O n.O 2.29L-05 0.0 1.70E-04 0.0 5.12E-05 0.0 6.72E-05 0.0 6,14E-05 0.0 7.30E-05 o.0 6bE6F-05 0.0 b.bbE-05 0.0 1.28f.-07 0.0 7.17E-05 0.0 7.80E-05 0.0 7.42E-05 Note: 0.0 means insufficient data or that the dose factor is <1.OE-20.

1.109-25

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

L f -0 1 5.58E-flb 1 .55E-05 3.95E-05 41.36E-0 3 I

  • I3E-oq I .56E08)

2.?OE-OA 6. I IE-09 2.71jE-07 I USJE-06 3.22E-0b I .S2E-0b 9.65E-06 7.65E-06 5.'I2E-Ob 3.81EF-05 I 426E-05 2,90E-06~ 2,03E-07 2. 26E-06 S.8QE-05 TH~YRODI 2.03E-07 2.26E-06 5.R~9E-05S K I )NEY 0.0 0.0 o.0 0.0 0.0 0.0 0.0 I .73E-06 3.20E-06 3. 1 OE-07 1.58E-O5 b.62E -05b 2.79E-02 5,USE-03 1 .7F-0_ 0.0 (USE 0.0 ADULT 0.0 0.11 ,).0 DOSE 0.0 0.0l 0.0 FACTOR) 0.0 (.0 0.0 0.0 0.0 0n0 JS. iSF-OS Ž.2 .8b -051 7. 77E-05 2.50F-05 1 .J44E -05 I

  • ThF -n03 I . k5F-va

1 , I OF -OS.

1 .'0?f-fl S5.96EF-05 7 .89F-O5 LI * 9L .f7 1 .43E-06 ?.Q9E-oh LUNr P . 0 3E -07 PQE-06S G; I - LL I 2.0 3E-07 2. S7k-Ob 4 8. 02E-05 41.50F-05 £1.SSE-0b 1 . I QE-09 2.80E-09 I.14 (E -07 2.03E-07 1 .26E-03 2.2 1 E-04J 3.09E-OS 3.27E-05 13flnE-05 1 .81E-08 9,9&E-05 '1.41hE-06 6.99E-95 0.0 0.0 0.00 0.0 0.0h 0.0 0.0 0.0 0.00 0.0 0.0 0.0 0.0 n , n n , u.19F-05 3.54E-05 u.32E-08 0.0 1.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 2.04FI-0(, 1 .8ar-06 0. *21 E-0b 1.noQE-011 2 .36E-05 I .711F-0'J ai. /Ok -05 b.91L-OS 6. 3eF -0'3 7 . 50EF -V5 6

  • PSE -0

6 1SL -05 I .32F -0 7 7 . 37 F - f'5 8.03E-05 7 . bUjE -OS Im Note: 0.0 means insufficient data or that the dose factor is <I.OE-20.O I 1.109-26

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

  • 45E-Oh aJ Sa

0.0 3.78E-06 9.26E-06 0.0 0 .09.79E- 0 60n 0.0 1 .07 E- 05 2.56E-05 0.0 n0.

0 2bF R C 2,q3F-03 0.0 A.U2E-05 0.0 (USE 0.0 5."l8E-05 R 90 2.91F-02 0.0 6.U0E-03 6.0 0.0 2 F-04 40 BQIE-08 0.0 2.41E-!ý9 0 .n ADUL.T .01.29 0 Q I I. 2S9F -0h 0.0 3.33E-OR .0 0 (.0 8.27E-05 R . 5 ? .IIF -07 5.32E-nR 3.78E-08 n . n 0 .0 ?.38E-05 Q P95 I.g9E-nR I. 75E-1)8 1 .0 3E - 1 0.0 DOSF 0 .0 1 .LJE-Oc J 103 1.OilE-0 0 ,0 U.BSE-07 n .0 1.0 1.7F0 J 1.06 2.5"&E-05 0.0 3.12E-16 0,0 0.0 19E0 N 123 2.7'9E-0Li Q.33F-oh h.96E-lb 4.33E-(16 FACTOR) 0.0 b.41E-05 E1254 2.'J3F-0'S 5.19E-nb 3,20E-flh R.OnE-OS 0.0 1.17E-05 b5 5 u 5 5 5 52TE 127 9.58F-07 52TE I?9M 1.05F-04 521E 132 2.t3F-05 531 129 2.95F-09 531 131 3.U2E-OS 531 133 1,2bF-05 55CS 130 U.SAE-04 55CS 13 6.53F-O0 56BA 1'&0 1,74E-00 57LA 100 2.12E-08 S8'E 141I S.OOE-08 58CE lU4 0.49E-0b 63EU 154 4.30F-06 92U 232 3.66F-02 920J 234 7.u00F-n3 qAPO P38 1.71F-03 9'IPU ?39 1.70E-03 qqpU ?'40 1.78E-03 94PU P.01 11OhE-0b 95AM 241 1.93F-03 96CM 2U2 1.43E-nu 96CM 244 1.bdE-03 3. 1 9F-n7 3.61F-05 I n05E-05 2. IbE-OS 401 0F-05 1 BUE -05 9~ .2 4E-0 4 7 . 31 -4 1 '75-n7 5. 17E-ng 4:91F.08 1 .7 7E -0 h O .RUE-n7 0.0 0.0 2.1 BE-a04 2. 2bF-q0 22 8F? E- fl I .37F-D7 I .01F-n3 I UOOE-04 1.6 7E -00 2. 06E-n7 1 .60E-05 0* 76E-Oh 7 .76E-05 2.3RE-05 S.'BE-06' 7.75E-0 7 3.q9E-05 I *99E-'n5 h.* 79 F-02 I .31E-62 u.*35E-0 S .. 0 0.0 n,0 0.0 0.0 ,0o0 2.?27E-05 6. 33E-05 A, 08F.---05 4.46JE-07 1 .53E-06 3.*27E - 06 6.97E-05 0. *20E-05 8 qqF-0b 2

  • I E-fO)

5.75E-IQ 2.0?E-n7 3.29E-07 2.68E-03 4.71EC-04 0 .25E-q5 0

  • I

E-1)5 0 .45E-05 2.70E-OP 1 . IIE-nu 9 .Q9F-nb 1 .04E-04 0.0 0 5 0).0 0.0* 0.0* 0.0 0l,0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 9.42E-05 R.81E-05 I .07E-07 0.0 0.0 O.0 0.0 0.0 0.0 0.0 0l.0 0).0 0.0 0.0 (0.0 n0.0 I .OuF-04 2. 39E-05 I .85E-04 4.*7bE -05 7.*34E -05 6. 72F-05 7.98E -05 7.*29F -09 7.28E-05 I .40OF-07 7.8'4E-O5 13.b,3r-05 8. 12E-05 Note: 0.0 means insufficient data or that the dose factor is <1.OE-20.

1.109-27

TABLE A-7 EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUJND* tmrem/hr per ptl/'.) TOTAL BODY SKIN TOTAL BODY sKirt i H 4BE b C 74 9F I TMA- 11 NA 1P 20CA 2 1 S C 214CR .25MN 25MN 26FE 2bFE 27C0 27C0 27CO 28NI 28NI 28NI 29CU 30ZN 3nzN 3'JZN 34SE 35BR 358R 35BR 37RB 37RB 37RB 37R8 38SR -38SR 38SR 3ASR 34Y 39Y 39Y 39Y 39Y 3 10 18 22 32 U 1 Ub 51 50 5b 55 59 57 58 6n 5q 63 65 ba b5 694 69 79 82 83 85 87 88 5Aq 59 90 92 90 914 91 q2 93 0'.0 0.0 7 60kE-0q b.

0FO-09 I ,66E-08 2.50E-0B 0,0) 3.'JlE-09 0 . nO -O I

  • 30F-08

2.20E-I0 9.60E-09 1 *BOE-ORq 0.0 9.

OE-t0 7.OOE-09 1, 70F-08 3. 70E-09 I .50E-09 UQ,00F-09 2.90E-09 0.0 0.0 I .90E-AA 6 . 9O0E - I b.UOE-t 1 I .20F-08 0.0 6.30E-1O 3.50E-09 I .50E-08 5.60F-1 3 0.0 7.o I OE-Oq 9.OOE-09 2.20E-12 3.80E-0q 2. 4 OF- II I .6bOF-09 5.70E-I0 0,n 0.0 0 0 5.80E-09 8. OOE-09 I . OE-08 2.90E-08 0.0 U.01E-n9 1 .50E- -B 2.b0E-1 0 I IOE.-08 0.0 9,4OE-O9 I.OOE-OQ R.20E-0Q 2. 00E-O0 0.0 0.0 1 .70E-09 I,70E-Oq 3.0OE-09 0.0 0.0 2.20F-ro8 9. 30E- II .40E-08 0.0 7.20F-10 0.0 4.OOE-09 1.80E-08 b.5OE-13 0.0 . 3 0E-09 I .OOE-08 2,60E-12 4.40 E-09 2.70E-i I 17.90F-n 7 .80E-1 0 UOZR 4OZR 4OZR 41N8 42MO LJ3TC 43TC 'i3TC 44RU U £4 P D LA RU LA 9RH 46PD 47AG 47AG 4 A C r) 5""s 52TE 52TE 5128 515R 51TE 52TE 52TE 52TE 5?TE 52TE 521E 52TE 52TE 52TE 531 531 531 93 95 97 93*4 95 97 99 9q4 04 101 103 105 1 nb 105 i07 109 I I~ 111 123 125 12b t 246 125 I ?b 127 12741 127 12 2'4 129 t31M 131 13 2 I 3M 129 130 131 13 2 133 6.0 5.00F-09 5. SOE -()q o0.

5. 1OF -A9 4A*bOE-0q 2.29E-I I 1 .qUF-0O Q. *,,E-10 0.0 2.7WF-0O S.bOE-OO 4.5UF-Oq I .50F-09 b.6OE-10 0.0 3.50E-I I I ,80F-08 I .80E-10 2.3nF-12 0,0 0.0 5. 7OF-t0 Q.DOF-09 1.30E-08 3. IOE-09

.9OF -') 9 5. 7OF-09 3.50F-12 I OOF-I I 7.70F-10 7. IOE-10 S., U OF -09 2,20F-09 I . 70F-0Q 1 .50E-08 I .OOF-09 4 .SOE-1 0 I *U0E-08 2.80F-09 I .7nE-0O 3.7UE-09 3.0 s . G010 5. O0)E -A9 i,4nE-Oq

  • 20F-09 I* OE-OQ

I.OOF-Oq 4 .20F-o9 5. 101-O I jAnF-0q 7.7nE-10 S.0 14.001-I11 '. tOE-08 2. tOE-Io 2.60F-12 0.0 b,* bE-qR b.bOE-10 I DO0E-nm 1 .50F-09 3.50E-09 I .OOE-O8 b.hOF-*9 U*.AOE-1 I 1.

0E- II I .IOF-1 I P *OOE-It0 g.uOE-I0 4.90E-09 2,b0E-Ob 2.00F-09 I .70F-OA 1.20E-09 7,50F-I 0 1 .70E1-ri 1 7 0E - n9 5.40FO-DQ 2. O0E -08 U.5AE-09 I

  • The same factors apply for adult, teen, child.

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

E 1.109-28

TABLE A-7 (Continued) TOTAL BODY SKIN 53! 13u I.bOF-0 l.90t-o0i 531 13 1 .20EE-08 1uOE-O8 55CS 134'1 b.P0E-10 7.Y0E-10 55CS 134 1 .2F-08 IQOE-0p 55CS 135 0.0 D.0 55CS t36 1.5OF-'4 '.70E-08 55CS 137 4 .2OF QJ -. 90E-0Q 55CS 13A 2,tOE-05 2.uOE-OR 55CS t39 b.30E-ng 7.20F- nq 5b65 139 2.uOE-0Q 2.70E-0Q 5hBA 140 2.lOE-0q 2,unE-09 56BA 1UI U.IOF-o9 qt90F-0Q 5b6A 1u2 7.9*E-09 9.00E-DO 57LA lU0 1.50E-0R 1.70E-08 57LA 141 2.5vE-10 2.5nE-t0 57LA IQ2 1.50E-OR t.ROE-05 58CE ]at 5.50E-10 b.20E-t0 58CE 143 2.20E-0q 2.50E-0Q 58CE Ua a 3.20F-10 3.70F- 10 59PR 143 0.0 0.0 59PR IOU 2.OOF-10 '.3nF-10 bOND 147 1.00E-0q 1.20E-09 blPM I7 0.0 0.0 tIPM 4RM4 1.UtF-.F0 5 6.-01- bIP4 10B u*hOF-09 5.3f5--*9 bIPM 14Q 2.50E-11 2.QoE-il biPH 151 2.2'F-OQ 2.30E-o9 b25 151 u.80E-11 2.10F-10 b2SM 53 2.70F-In 3.0OE-10 13EU 152 7.37E-09 3.53E-0O 63EU 15u 7.BUE-09 4.00F-19 b3EU 195 I.RIE-10 U.33E-10 b3EU 156 7.80F-09 3.70E-Mg 65TB 160 A.6(0E-A9 1.00E-0A 67H40 I664 5.90F-00 1.OOE-nS 7UA 181 2*10F-12 2,ROE-12 7Ui 185 n 0 .0 a 74" 187 3.1'E-AQ 3.bOE-09 82PH 210 1.30E-11 1.70E-11 381B 213 0.0 0.0 RaPO 210 5,10E-'1 b.2OE-tu TOTAL BODY SKIN 8RRA 2?3 1.50F-09 I.ROF-09 8SRA 22u 3.9nE-0q 1.OOE-08 88PA P25

. 11F -

t I I. 2()F -1A 88AA 22b b.41JF-oq 7.40E-O0 R.RA 228 I,?f'F-0 1 t.4OF-n8 89AC P2? IrNF-OQ 1.80E-oQ 9A9C 227 2.OOE-09 2.40F-59 90TH 227 5.10F-10 b.30F-t0 90TH 22? ,.QOF-0Q t.00E-0A 90TH 229 2.20F-0 0 2.70E-09 90TH 230 h.S0E-nq 7.SOE-nq Q0TH ?32 S.OOF-OQ U.nOE-Oq qOTH 23u 1.1OE-10 1.30F-10 91PA 231 2.20F-0Q ý.70E-09 qtPA 233 1.30F-09 1.50F-99 92U P32 2.5qF-12 2.b9E-11 92U 233 2.30E-09 2.rtOF-o9 92U 234 b.32F-13 1,59E-10 q2U 235 i.20F-Oq 4.OOF-ng 92L P3b 2. IF-I I .80E-11 92U 237 t.00F-09 1.30E-0q 92U 238 1.10F-10 1.50E-10 13NP 2;7 1.40F-09 1.bOE-Pq 93NP 238 2.8nF-09 3.20E-oq 93NP 23q 9.50F-10 1.10E-0q Q9PUJ 238 1.30E-12 1.80F-11 9LPU P39 7.90F-13 7.70E-12 94PU 240 1.30F-12 t.80E-11 9LPU 241 4.h0E-12 b.80E-12 QUPU 242 1.10F-12 1.60F-11 9qPki 2441 8.95E-10 1.62E-10 9SAM 241 1.801E-10 2.60F-10 95AM .4??4 2.h6F-11 1.80E-1l 95AM 24.3 1.30E-09 1.50E-09 96CM 2U2 5.50E-12 2.30E-11 96CM 243 2.30F-Oq 2.90E-0Q 96CM 2ila 2.qnE-12 1.8OE-11 96CM 245 9,50E-10 1,20E-09 96CM 246 1.00E-12 1S50E-11 96CH ?P7 2,20E-0Q 2.bOE-09 9bCM 2a8 6.8IE-0q 5.23E-09 98CF 252 b6b0F-0R 7.20E-08 1.109-29

called bioaccumulation factors in this guide, can be found in the literature (Pnf.

19). The addition of the bioaccumulation factor Bip to Equation (A-2) yields Equation (A-3), which is suitable for calculating the internal dose for consumption of aquatic foods.

Rap = 1100 Uap Q.B. D *exp(-Aitp (A-3) i aipj , p Values of Bip are given in Table A-8; the other parameters have been previously defined.

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

c.

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

One method of approaching this problem was presented in the Year 2000 Study (Refs. 4, 17, 20, and 21). Based on these references, an estimate of the radio- nuclide concentration in shoreline sediments can be obtained from the following expressions: Ciw[l - exp(-.it)] C.s Kc 1w i (A-4) is c where Cis is the concentration of nuclide i in sediment, in pCi/kg; CiW is the concentration of nuclide i in water adjacent to the sedinent, in pCi/liter; Kc is an assumed transfer constant from water to sediment, in liters/kg per day; t is the length of time the sediment is exposed to the contaminated water, nominally 15 years (approximate midpoint of facility operating life), in hours; and Ai is the decay constant* of nuclide i, in hours-l.

In the original evaluation of the equation, Xi was chosen to be the radiological decay constant, but the true value should include an "environmental" removal constant.

The value of Kc was derived for several radionuclides by using data from water and sediment samples collected over a period of several years in the Columbia River between Richiand, Washington, and the river mouth and in Tillamook Bay, Oregon, 75 km south of the river mouth (Refs. 22 and 23). Since the primary use of the equation is to facilitate estimates of the exposure rate from gamma emitters nn*w meter above the sediment, an effective surface contamina- tion was estimated.

This surface contamination was assumed to be contained within the top 2.5 cm (I in.) of sediment.** The dose contribution from the radionuclides at depths below 2.5 cri was ignored.

The resulting equation is Si MOT 1 iCi WDl - exp(-Ait)] (A-5) where Si is the "effective" surface contamination, in pCi/m2, that is used in subsequent calculations; If the presence of a radionuclide in water and sediment is controlled primarily by radioactive equilibrium with its parent nuclide, the water concentration and decay constant of the parent should be used in Equations (A-4) and (A-5). With a mass of 40 kg/m 2 of surface.

1.109-30

TABLE A-8 BIOACCUMULATION FACTORS CpCilkg per pCi/liter) FRESHNATER SALTMA17ER ELEMENT FISH INVERTF3RATE PLANT PIS' TIVERTE3RATE PLANT H 9,0E-Ol q.oE-01 9.OE-01 9.OE-ni 4.3E-01 9.3E-01 HE 1.0E 00 1.0f 00 10Elf 1.0ff O0 1.fOE 00

t. OE no LI

5,0E-Ol C.oE: 01 3.0E 00 5.OE-01 50fE-Ol 3.0E 00 BE 2.OE 00 InE 01 2.0E 01 ',OE 02 e.OE 02 1.OE 03 B 2.2E-01 5.OE 01 2.2E 00 2.2E-Ot QO.E-01 2.2E oA C U.

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

E 04 1T7E "04 1 .0f p 0 0 9.2E-O 9.?fE-01 9.2E-0l 9.bF-01 9.bE-01 Q.bE-O0 F 1.0E 01 1 .oE 02 2.0E 00 3.bF 00 3.6f on 1 .4E 00 NE I.OE O0 I.nE 00 1. r E 00 1.0E 00 1.0OE 00 1.OF 00 NA I.OE 02 2.oE. 02 5.OE 02 b.7E-02 1.QE-01 9.SE-O1 MG 5.OE 01 1.oE 02 1.0OE 02 7.7Ff-01 7.7fE -01 7.7E -0 1 AL ioE0f 01 6.;E 01 U.2E 02 1.0OF n1 b.OE O0 6.OE 02 SI 2.5E 00 2.';E 01 1.3E 02 1.0f 01 3.3E 01 6.7P 01 F 1.0oE 05 2.oE. OU 5.0E 0'; 2.fE n4 3.0E O4 3.0E 03 T 7.5E 02 I.oE. 02 1.0E 02 1.7E 00 4,UE-01 U.4E-01 CL 5.0E 01 .ofE 02 5.OE 01 1.3E-02 I.QE-02 7.6E-02 AR I.OE 00 1.nE 00 1,OE 00 1.0ffno I.OE 00 1.OE 00 K I.OE 03 8.lE 02 6.7E 02 1.IE 01 .6fE 00 2.6E 01 CA 4,OE 01 3,3E 02 1.3E 02 5.0E-Ol 1.3E 01 5.OE 00 SC 2.0f 00 1.fE' 03 t0OE 0 Oi 2.0fE 00 1.fOE 0 Q I.0 E 05 TI t.OE 03 3.OE. 03 5.OE 02 1.OE o3 1.OE 03 2.0E 03 V 1.OE 01 3.E 03 1.0E 02 1.0E Ol

5. OE O

i.OE 02 CR 2.0E 02 2.nE 03 . ",OE 03 4.0E 02 2.0E 03 2.0E 03 m, ,40OE 02 9.oE 04 1.0fE 04 5.5E 02 * 4.OE 02 5.5E 03 FE 10OE 02 3.pE 03 1.0E 03 3.0E 03 2.OE O4 7.3E 02 c0 5fOE 01 2.nE 02 2,0E 02 .0OE 02 I.0E 03 I.OE 03 NI 1.OE 02 1.OE. 02 5.0E 01 I.OE 02 2.5E 02 2.5E 02 CU 5.OE 01 'i.nE, 02 2.0E 03 .7ffE 02 1.7f 03 1.0E 03 ZN 2.0E 03 i.nE 04 2.0E 04 2.0E 03 5.0E OU 1.0E 03 GA .3E 02 6.7E 02 1.7fE 03 3.3fE 02 b.7E 02 1.7fE 03 GE 3.3E 03 3.fE- 01 3.3E 01 3.3E 03 1.7fE OU 3.3E 02 AS 1.OE 02 i.nE. 01 3.0E 03 3.3E 0R 3.3E 02 1.7E 03 SE 1.7E 02 1.7E 02 1.0E 03 4.0E 03 1.0E 03 1.0E 03 BR 4.2E 02 3.iE 02 5.OE 01 1.5E-02 3.1E 00 1.5E 00 KR 1.0E 00 1.nE:00 102 0:0 Ij 0E 0 . f0E 00 .0fE 00 RB 2.0E 03 i.nE, 03 t.0E 03 8.3E 00 1.7E 01 1.7E 01 SR 3.0E 01 l.nE 02 5.0E 02 2.0E 00 20OF 01 I.OE 01 Y 2.5E 01 1.0E 03 5,OE 03 2.5E 01 .0OE 03 5.OE 03 ZR 3.3E 00 6.7fE 00 1.0E 03 2.OE 02 OE n1 I.OE 03 NB 3.0E Oi l.nE u2 8.OE 02 3.0E n4 I.OE 02 5.0E 02 Mo 1.0fE 01 1.nE' 01 I.OE 03 OE f0 1.0fE 0t 1.0fE 01 TC I.5E 01 5.Off 00 U.0f1 1.0f 1O 5.0fE 01 4,OE 03 RU 10OE 01 3.0E 02 2.0E 03 .0OE 00 1.0E 03 2.OE 03 RH 1.fOE 01 3onE:02 2.OE 02 1.OE 01 2.0OE 03 2.0E 03 PD 1.0E 01 3.0E 02 2.OE 02 I.OE Ot 2.0E 03 2.0E 03 AG 2.3E 00 7.7Ef 02 2.OE 02 3.3E 03 3,3E 03 2.0E 02 CO 2.0E 02 2.nE. 03 1.0E 03 3.0E 03 2.5E 05 1.0E 03 IN I.OE 05 l.nE 05 1.0E 05 1.0E 05 I.OE 05 I.OEf 05 SN 3.OE 03 1.0E 03 1.OE 02 3.0E 0 1.0fE 03 t.OE 02 sB 1.OE 00 1..ff,01 1.5E 03 1JQ,OE 01 S.0IE 00 1.5E 03 TE 4.OE 02* 1.0E. 05 I.OE 02* I.OE 01** I.OE 05 i.OE 03** 1 1.5E Ot 5.0E 00 4.OE Ol I1.0E 01 5.0F O0 I.OE 03 1.109-31

TABLE A-8 (Continued) FRESHWATER ELEMENT XE CS BA LA FISH I .0E 2,OE

  • 0E

2.SE INVERYF3PATE SALTWAE;ý TrIH T1JVEITE3RATE PLA'NT 00 03 00 01 I . nE I PoE 2.0E I .nE 00 02 02 03 PLANT I .OE 00 5.OE 02 5.OE 02 S.E 03 1 0 OE 0i 0OE 1 0 OE 2. 5E 00 oft 0! 01 I .O0E 2.5f 1 . 0OE I if E 00 01 02 03 I5.

nE 5. OE 00 Dl 02 03 CE 1.OE 00 1.nE 03 4*OE 03 t I.OE O b.6OE 02 b.OE 02' PR 2.5E 01 I.OE 03 5.OE 03 2.5E O I.OE 03 5.OE 03 ND 2.5E 01 I.nE, 03 S.OE 01 2.5E 01 1.OE 03 5.6c 03 PM 2.5E 01 IoE' 03 5.OE 03 2.5E 01 1.0E 03 5.OE 03 Sm 2.5E 01 I.OE 03 5.OE 03 2.5E 01 1.OE 03 S.nE 03 EU 2.5E 01 1.nE 03 S.OE 03 2.SE n1 1.0E 03 S.OE 03 GD 2.5E 01 10oE. 03 5.hE 03 2.5E 01 1,OE 03 5.OE 03 TB 2.5E o0 1.oE 03 5.OE 03 ?.SE 01 1.0E 03 5.0F 0.3 DY 2,SE 01 I.oE 03 5,OE 03 2.SE 01 I.OE 01 5.OE 03 HO 2.5E 01 1.OE 03 5.OE 03 2.SE o0 I.oE 03 5.Or n3 ER 2.5E 01 I.oE 03 5.OE n3 2,5E 01 I.OE 03 5.OE 03 TM 2.5E o0 1.hE 03 S.hE 03 2.SE 01 t.OE 03 S.OE 03 YB 2.5E 01 1.oE 03 S.OE 03 2.5E o1 I.OE 03 5.OE 03 LU 2.5E 01 1.nE 03 5.OE 03 2.SE O0 1.OE 03 5.OF 03 HF 3.3F 00 6,7E. 00 I.OE 03 2.OE 02 2.OE 01 2.OE 03 TA 3.OE 04 b.7E-02 8,OE 02

3. OE Ol

1.7E 04 I.OE 03 W 1o2E 03 1.oE 01 1.2E 03 3.0E 01 3.OE 01 3.OE 01 RE 1.2E 02 6.nE 01 2.UE 02 U.E 00 b.OF 01 2.uE 02 0S 1.OE 01 3.0E 02 2.OE 02 1.OE 01 2.OE 03 2.OE 03 rR I.OE 01 3.E' 02 2.OE 02 1.OE (1 2.OE 03 2.E 03 PT 1.OE 02 3.nE 02 2.OE 02 1.OE 02 2.OE 03 2.0E 03 AU 3,3E 01 5oE 01 3.3E 01 3.3E 01 3.3E 01 3.3E 01 HG I.OE 03 1.oE 05 I.OE 03 1.7E 01 3,3E 34 t.OE 03 TL 1,OE 04 1.;E 04 I.OE 05 1.0E 04 1,5E 04 I1.E 05 PB 1.OE 02 1.nE 02 2.OE 02 3.OE 02 1,E 03 5.OE 03 B t.SE o0 2.aE 01"**2.E 01***tS 1.5E 01 2.UE 01"** 2. a 0 1 F** PD 5.OE 02

2. nE Ou

2.OE 03 3.OE 02 51OE 03 2.OE 03 AT 1,5E 01 5,E' 00 .. OE 01 1.OE 4.0;7 03 RN 1.OE 00 I.oE 00 t.OE 00 1,OE 00 1,OE 00 I.OE 00 FR 4.OE 02 1,oE 02 8.OE 01 3,OE 01 2.OE 01 2.OE 0l RA 5.OE 01 2,'E 02 2.5E 03 S.OE 01 1,OE 02 I.OE 02 AC.

2.5E 01 1.oE 03 SOE 03 2.5E 01 I.OE 03 5.OE 0O TH 3.OE 01 5.nE 02 1.5E 03 t.OE 01 2,OE 03 3.OE 03 PA 1.IE 01 .iEE 02 1.IE 03 I.OE 01 I.OE 01 6.OE 00 U 2.OE 00 6,OE: O0 S.OE-0 1.OE 01.

!.OF 01 b.6E 01 NP I.OE 01 4.nE. 02 3.OE 02 I.OE o1 1.OE 01 i. OE 00 PU 3,5E 00 I.oE 02 3.5F 02 3.OE 00 2.OE 02 I.OE 03 AM 2.5E 01 1.0E 03 5.OE 03 2.SE 01 1.OE 03 5.OE 03 CM 2.5E 01 1.nE. 03 S.OE 03 2.5E 01 1.OE 03 5.0E 03 BK 2.5E 01 I.nE; 03 5.0E f3 ?.SE 01 1.OE 03 5.OE 03 CF 2.5E 01 I.oE'03 5.OE 03 2.SE 01 1.OE 03 5.OE 03 ES I.OE 01 1.oE, 02 I.OE 03 I.OF 01 I.OE O0 b.OE 01 i I.OE 01 1.E 02 I.OE 03 I.OE 01 I.OE 01 bOE 01

  • ORNL - Private Communication
    • Freke, A.M.,

"A Model for the Approximate Calculation of Safe Rates of Discharge into Marine Environments," Health Physics, Vol.

13, p. 749, 1967.

      • Derived from data in Bowen, H.J.M.,

Trace Elements in Biochemistry, New York, Academic Press (1966). 1.109-32

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

Shore-width factors were derived from experimental data (Ref.

24) and are sunanarized in Tdble A-9.

They represent the fraction of the dose from an infinite plane source that is estimated for these shoreline situations.

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

Rapj U S*D 100 U W C T D [ - exp(-- t)] (A-6) ap i aipj Iap iw i aij U III W 110,000 --'--. QiT D .[exp(-."\\t )][l - exp(-:i t)] (A-7) F lli ipj iP 1 d.

Dose from Foods Grown on Land Irrigated by Contaminated Water The equations in the following paragiaphs can be used to calculate doses from radio- nuclides in irrihjated crops.

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

(1) Vegetation The concentration of radioactive material in vegetation results from deposition onto the plant foliage and from uptake from the soil of activity deposited on the ground.

The rmodel used for estimating the transfer of radionuclides from irrigation water to crops through water deposited on leaves and uptake from soil was derived for a study of the potential doses to people from a nuclear power complex in the year 2000 (Ref. 4). The equation for the model (for radionuclides except tritium) is presented below in slightly modified form.

The first term in brackets relates to the concentration derived from direct foliar deposition during the growing season.

The second term relates to uptake from soil and reflects the long-term deposition during operation of the nuclear facility.

Thus for a uniform release rate, the concentration Civ of radionuclide i in the edible portion of crop species v, in units of pCi/kg, is given by: iv i" - exp(- '"U t e)]v Biv[I - ex 1(-'P 'itb)1]exp(-..it ) (A-8 ) The de;,osition rate, di, from irrigated water is defined by the relation d'i = C iw (water deposition) (A-9) where Ciw is the concentration of radionuclide i in water used for irrigation, in pCi/liter, and I is the irrigation rate, in liters/m2 /hr; i.e., volume of water (liters) sprinkled on unit area of field in 1 hour.

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

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

I 1.109-33

TABLE A-9 SHORE-WIbTH FACTORS FOR USE IN EQUATIONS (A-5) and (A-6) EXPOSURE SITUATION SHORE-WIDTH FACTOR, W Discharge canal bank 0.1 River shoreline 0.2 Lake shore 0.3 Nominal ocean site 0.5 Tidal basin 1.0 TABLE A-10 ANIMAL CONSUMPTION RATES I ANIMAL Milk cow Beef cattle QF FEED OR FORAGE (kg/day [wet weight]) 50 (pasture grass) 50 (stored feed grain) QAw WATER (;./day) 60 5o From Reference 4, Tables 111-B and -10.

P 1 .10g-34

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

The radionuclide concentration in animal products CiA in terms of pCi/liter or pCi/kg (Ref.

4) is proportional to the animal's intake of the radionuclide in feed or forage (subscript F) and in water (subscript w): CiA = F iAECiFQF + CiAwQAw] (A-li) The second set of terms in the brackets in Equation (A-1l) can be omitted if the animal does not drink contaminated water.

Values for QF and QAw are presented in-Table A-i1.

Values for Biv and FiA are given in Table C-5 (see Appendix C).* The total dose Rapj from irrigated foods (excluding tritium) is given by: R a veg CiD + Uanimal Y D apj ap iv aipj ap

iA aipj (A-12) If values for Civ from Equation (A-3) and CiA from Equation (A-11) are substituted in Equation (A-12): veg i[)Da [ - exp(- Ei te)] Biv[l - exp(-'it )]* R ve dix(, hi ai iv , X Lb apj ap v ipJ YvEi i U panima -r[l - exp( '1Ei te)] ap iA ai pj OFui Y- / ~v Ei + Biv[l - exp(-,.,itb)] (A-13) +PN i )]+ CiAwQAwj It should be noted that the two components of Equation (A-12) imply that contribu- tions from the individual vegetable and animal products have already been summed.

In actual use, it will be necessary to compute separately the milk and meat portions of the dose due to animal products (also applicable to Equation (A-17)). For tritium, the concentration in animal products is given by the following equation (adapted from Reference 25): kWCv +QAwCAw (A-14) C A - +kQCA m in Since by Equation (A-IO) Cv = Cw, and since for all practical purposes CAw = Cw9 Equation (A-14) can be rearranged as follows: kC C A = 3 (w + QAw) (A-15) in Similarly, the above equations for tritium concentration can be combined with the general Equation (A-1): Ra.

U ve C D animal CAD apj (A-16) Rapj : u~gvap vapj" + Uap Aaj(-6 Uve v ,,animal Da (w+ QAw) (A-17) V uea Daa apjs + Uap apj-inab Q(C--. Valus fr FA appear as Fin and Ff in Table C-5.

1.109-35

REFERENCES FOR APPENDIX A 1. "Final Environmental Statement Concerning Proposed Rule Making Action: Nlumierical Guides for Design Objectives and Limiting Conditions for Operation to Meet the Criterion 'As Low As Practicable' for Radioactive Material in Light-Water-Cooled Power Reactor Effluents," USAEC Report WASH-1258, Washington, D.C., July 1973.

2.

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

3.

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

4.

J.

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

5.

J.

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

6.

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

7.

M. M. Miller and D. A. Nash, "Regional and Other Related Aspects of Shellfish Consumption - Some Preliminary Findings of the 1969 Consumer Panel Survey," NIMFS Circular 361, USDC/NOfhA, Seattle, Wash., June 1971.

8.

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

9.

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

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

11.

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

12.

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

13.

P. M. Bryant, "Data for Assessments Concerning Controlled and Accidental Releases of 1I and 137Cs to the Atmosphere," Health Physics, Vol.

17, pp. 51-57, July 1969.

14.

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

15.

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

16.

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

17.

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

18.

S.

E. Thompson et al, "Concentration Factors of Chemical Elements in Edible Aquatic Organisms," USAEC Report UCRL-50564, Rev.

1, Lawrence Radiation Laboratory, October 1972.

1 1. 109-36

19.

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

20.

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

21.

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

22.

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

23.

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

24.

L. R.. Anspaugh et al, "The Dose to Man via Food-Chain Transfer Resulting from Exposure to Tritiated Water Vapor," in Tritium (A. A. Moghissi and M. W. Carter, eds.), CONF-710809, 1973.

1.109-37

APPENDIX B MODELS FOR CALCULATING DOSES FROM NOBLE GASES DISCHARGED TO THE ATMOSPHERE The following analytical models are used for calculating doses from exposure to gaseous effluents.

Separate models are given for air and tissue doses due to gamma and beta rays.

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

1. Annual Gamma Air Dose from Elevated Releases of Noble Gases Slade (Ref. 1) describes the derivation of the equations for estimating annual air doses from photon emitters dispersed in the atmosphere.

The following expression can be used for calculating annual doses: D 260 D n un s I )1 ik Symbols for this equation were defined earlier, in Regulatory Position C.2.a of this guide.

The photons were combined into energy groups, and each photon intensity within a group was weighted by its energy and energy absorption coefficient.

Thus, the effective fraction of disintegrations of the nuclide i yielding photons corresponding to the photon energy group k, Aki, was determined to be Aki I [AmEmpa(Em)]/[Ekwa(Ek)] (B-2) m where A is the fraction of the disintegrations of nuclide i yielding photons m of energy E Em is the energy of the mth photon within the kth energy group, in MeV; and Ua (Em) is the energy absorption coefficient in air associated with the photon energy Em, in m All other parameters are as previously defined.

The summation is carried out over all photons within energy group k.

Data for the photon energies and abundances for most of the noble gas nuclides were taken from Reference 2.

For radionuclides not contained in Reference 2, data were obtained from Reference 3.

Decay during travel from the point of release to the receptor is QD = Q* exp(-Xir/un) (B-3) The term "gamma air dose" refers to the components of the air dose associated with photons emitted during nuclear and atomic transformations, i.e., gamma and x-rays.

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

Elevated release conditions are assumed to occur when the point of release is higher than twice the height of adjacent solid structures.

(See Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion for Gaseous Effluents in Routine Releases from Light- Water-Cooled Reactors.") 1.

109-30

where Qi is the initial release rate of nuclide i, in Ci/yr, and Ai is the decay constant of nuclide i, in sec"1 All other parameters are as previously defined.

2.

Annual Gamma Air Dose from Ground-Level Releases of Noble Gases and Annual Beta Air Dose Plumes of gaseous effluents are considered semi-infinite in the case of noble gases released from vents.

The concentration of the radionuclides in air at the receptor location may be determined from atmospheric dispersion model described in Regulatory Guide 1.111.

The annual average ground-level concentration of gaseous effluent species i at location (r,o) from the release point is determined from xi(ra) = 3.17 x 104Q*[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,. 3 in sec/mi The constant 3.17 x lO4 represents the number of pCi per Ci divided by the number of seconds per year.

All other parameters are as previously defined.

The annual gamma or beta air dose associated with the airborne concentration of the effluent species is then I DY(r,e) or DO(r,e) = xi(re)(OF* or DFO) (B-a) where the terms are as defined in Regulatory Position C.2.b.

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

3.

Annual Dose to Tissue from Noble Gas Effluents It is also necessary to determine annual doses to real individuals in unrestricted areas.

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

a.

Elevated Releases The annual total body dose is computed as follows: DT(r,O) = 1.11 x SF I DI(re)exp[-i (Ek)t] (B-6) Ground-level release conditions are assumed to exist when the release point is less than or equal to twice the height of adjacent solid structures and the vertical exit velocity is less than five times the horizontal wind speed.

(See Regulatory Guide 1.111.) The term "beta air dose" refers to the component of the air dose associated with particle emissions during nuclear and atomic transformations, i.e., 0+, B-, and conversion electrons.

I 1.109-40

TABLE B-i DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS Nuci ide Kr-83m Kr-85m Kr-85 Kr-87 Kr-88 Kr-89 Kr-90 Xe-1 31m Xe-1 33m Xe-i133 Xe-i 35m Xe-1 35 Xe-1 37 Xe-138 Ar-41 a-air* (DFB) 2.88E-04 I . 97E-03 1 .95E-03 1 . 03E-02 2. 93E-03 1. 06E-02 7. 83E-03 1.11 E-03 I .48E-03 i .05E-03 7. 39E-04 2: 46E-03 1. 27E-02 4. 75E-03 3.28E-03 1 .46E-03 I .34E-03 9. 73E-03 2. 37E-03 1 . 01 E-02 7. 29E-03 4. 76E-04 9. 94E-04 3. 06E-04 7.11 E-04 1.86E-03 1. 22E-02 4.1 3E-03 2. 69E-03 y-Air* (DFB) 1.93t-05 1.23-03 1. 72E-05 6. 17E-03 1.52E-02 1. 73E-02 1. 63E-02 1. 56E-04 3. 27E-04 3.53E-04 3. 36E-03 1. 92 E-0:3 1.51 E-0:3 9.21 E-03 9.30E-03 y-Body (DFBi) 7.56E-08 1 17E-03 1.61E-05 5 92E-03 1 .47E-02 1 .66E-02 1 56E-02 9. 5E-05 2.51 E-04 2.94E-04 3.12E-03 1.81E-03 1 .42E-03 8.83E-03 8.84E-03 mrad-m3 pCi -yr mrem-m3 pC i-yr

    • '2.88E-04 = 2.88 x I0"4

1.109-41

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

The constant 1.11 represents the ratio of the energy absorption coefficient for tissue to that for air.

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

The skin dose rate is computed by DS(r,o) 1.11 x SFD Y(r,o) + 3.17 x 104 1 Qi(x/Q']D (r,o)DFSi (8-7) 1 Symbols for this equation were defined earlier in Regulatory Position C.2.d of this guide.

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

b.

Ground-Level Releases The annual total body dose is computed as follows: DT(r,o) = 1.11 x SF ýxi(rO)DFBi (B-8) Symbols for this equation were defined earlier in Regulatory Position C.2.e of this guide.

The annual skin dose is computed as follows: Ds(r,o) - 1.11 x SFF Zxi(r'e)DFi + xii(ro)DFSi (8-9) where D5 (r,e) is the annual skin dose due to immersion in a semi-infinite cloud in the sector at angle e, at the distance r from the release point, in mrem/yr, and xi(ra) is the airborne concentration of radionuclide i at point (r,6), in pCi/m 3 . I1 I 1.109-42

REFERENCES FOR APPENU.X B I.

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

2.

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

3.

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

4.

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

5.

M. J. Berger, "Improved Point Kernels for Electron and Beta-Ray Dosimetry," NBS Report NBSIR 73-107, 1973.

6.

M. J. Berger, "Beta-Ray Dose in Tissue.- Equivalent Material Immersed in a Radioactive Cloud," Health Physics, Vol.

26, pp.

1-12, January 1974.

1.109-43

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

Annual External Dose from Direct Exposure to Activitv Deposited on the Ground Plane The ground plane concentration of radionuclide i at the location (r,o) with respect to the release point may be determined by 1.1 x 10, (rc~ Q! C i(r'c) 1 1-exp(-Xit)j (Cý-l)

'-here C

. is the ground plane concentration of the radionuclide i in the sector at angle - at the distance r from the release point, in pCi/m2; Qi is the annual release rate of nuclide i to the atmosphere, J'i/yr; t is the time period over which the accumulation is evaluated, which is 15 years (riid-point of plant operating life). This is a simplified method of approximating the average deposition over the operating lifetime of the facility; is the annual average relative deposition of effluent species i at location (r,j), considering depletion of the plume during transport, in mn-2 ; and The annual plant is then is the radiological decay constant for nuclide i, in yr-1 . dose from nuclide i resulting from direct exposure to the contaminated ground D (r ,) 8760 SFCG(r,r.)DFG (C-2) where D. j(r,*) ii and other terms The annual is the annual dose to organ j from the ground plane concentration of nuclide i at the location (r,r,), in mrem/yr; are as defined previously in Regulatory Position C.3.a of this guide.

dose to organ j is therefore D (r,o) = 8760 S C9(r,o)DFGi i F I 1 (C-3) Values for the open field ground plane dose conversion factors for the skin and total body are given in Tables A-3 to A-7.

The annual dose to all other organs is taken to be equivalent to the total body dose.

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

1.109-45

2.

Annual Dose from Inhalation of Radionuclides in Air The annual average airborne concentration of radionuclide i at the location (r,t!) -ith res- pect to the release point may be determined as Xi(r,o) 3.17 x 104QQ[X/Q'] D(r,) (C-4) where is the release rate of nuclide i to the atmosphere, in Ci/yr; xi(r,O) is the annual average ground-level concentration of nuclide i in air in the sector at angle 6 at distance r from the, release point, in pCi/m 3 ; [./Q']D(r,o) is the annual average atmosphere dispersion factor, in sec/m 3 (see Regulatory Guide 1.111). This includes depletion (for radiolodines and particulates) and radioactive decay of the plume; and 4 3.17 x 10 is the product of the number of pCi/Ci and sec/yr.

The annual dose associated with inhalation of nuclide i at the airborne concentration xi(r,O) is then DDA (rO) = xi(ro)RaDFAi (C-5) iiaa ija Values for DFAija are given in Tables C-1 to C-4, and all other symbols are as defined earlier in Regulatory Position C.3.b.

The annual dose to organ j in age group a from all nuclides in the effluent is: 4 DA (ra=R(C-6) Dja(r,o) Ra zxi(re)DFAija 3.

Concentrations of Airborne Radionuclides in Foods The concentration of radioactive material in vegetation results from deposition onto the plant foliage and from uptake of activity initially deposited on the ground.

The model used for estimating the transfer of radionuclides from the atmosphere to food products is six:ilar to the model developed for estimating the transfer of radionuclides from irrigation water given in Appendix A of this guide.

For all radioiodines and particulate radionuclides, except tritium and carbon-14, the con- centrition of nuclide i in and on vegetation at the location (r,Q) is estimated using CV(rO) di(r,o) r[l - exp('AEite)] Biv[l - exp(-Y tb)]] exp(-1ith) ' ' + Ax PXti (C-7) See Regulatory Position C.l of tnis guide for definitions of terms.

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

1 and 2). I 1.109-46

TABLE C-1 ADULT INHALATION DOSE FACTORS (mreni/pCi inhaled) NUCLIDE I 3 UBE 10 bE I*l 7N 13 QF 14 11NA 22 1 1 NA 2 a ISP 32 20CA 4L 215C U b 24CR 51 25MIN 54 25 'N 5b 26FE 55 ?6FE 59 ?7CO 57 27C0 98 27CO bo 28NI 59 28-1 65 29CU b6 30ZN 65 30ZN 694 30 N 59 3uSE 79 359R S2 35HR 93 353P 84 353R 85 374B 5h 37RB 87 37RR 58 37BR Bq 3BSR 89 3ASR 90 38SP 91 3ASR Q2 39Y 90 34Y qO1 3QY 9 1U 39Y 91 A0IE 0.0 I .qSE-OU 2.28E-O0 6.27F-Oq 4.71E-07 1. 30F-05 1 .b9E-O6 I .b5E-0O4 3.83E-05 3.51E-05 0.0 0.0 0.0 7.b2E-06 I .a7E-Ob 0.0 A 0 0.0 ",0OE-0b 5.40E-05 1 .92F-I0 0.0 L.0 hE-Oh 1 .02F-09 4.23F-12 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 3.8OE-05 I .2"E-02 7.9"E-09 8. 4 1E-1O 2,b6E-07 3.?2 E- II 5.78E-05 LIVER TfTAL 9')Y 1.3QE-07 t.34E-07 3.OhE-05 U.QbE-Oh 4.27E-07 u.27E-17 b.27E-09 h.27E-01 0.0 S.20E-oS 1.30E-n5 1.30E-05 t.69E-Ob 1.69E-0b 9.65E-Ob 6.27E-Oh 0.0 U.II3E-Ob 1.07E-04 3.11E-05 0.0 1.25E-0R +/-.95E-0b 7.A7E-07 1.55E-10 2.29E-11 3,43E-05 9.O0E-0B 3.47E-03 1.32E-06 5.bSE-08 B.39E-0O I.QBE-07 2.SQE-07 1.u4E-nb 1.8SF-Ob 1.4bE-O b.77F-07 3.92E-nh 1.PtE-06 ?.62E-11 I.IaE-tl 1.83F-10 7.b9E-1I 1.29E-05 S.PE-,)h 2.L5E-nq 2.2LE-I0 0.13E-12 5.61;E-13 3.83E-n7 6.0QE-O0 3.0 1.6hE-06 3.0 3.O0E-OR 0.0 3.91E-08 0.0 !.hAE-09 1.6QE-O5 7.3RE-Ob

.87E-Ob

3.?IE-0h 3.85E-B8 P.4iE-08 3.21E-OB 2.12E-O0 0.0 1.09E-Ob 0*0 7.6?E-111 0.0 3.,qE-10 0.0 3.64E-11 0.0 7.01E-09 0.0 1.27E-12 0.0 1.55E-06 1 .34E-07 u.L?7E-07 8.27E-09 0.0 I 30E-05 I .69E-Ob 0.1 0.0 0.0 7.u"UE-09 0.0 0.0 0*.0 0.0 0.0 0.0 0o0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0} 0.0} 0.0 0).0 0.0 0.0 0.,0 0.0n 0.0 0.0 0.0 0.0 0.0 0.0A 0.0 KI)NEY S.3LIE-07 0.0 4.27E-07 6.27F-OQ 0.0 1I 30E-05 1 ,bqE-06 0.0 0.0 I .OOE-0O ?. 5SE-09 I I23F-06 I .b3E-10 0.0 0.0 0.0) 00 0.0 0.0 5,7 8 F-10 8.b2E-0b I . Q48E-09 5.27E-12 5.bQE-07 0.0 0.0 0.0 0.0 0,0 0.0 0.0 6,0 0.0 0.0 0.0 0.0 0.0 1 I 34E-07 ?.23E-Ou u.27F-07 6 *27E-O9 n.0 ,1 I E-n5 1 69F-Ob 0.0 0=0 S. OE-06 1 .75E-06 1 .18E-06

o.RE-05

1 .27F-04

  • .62F-05

1 .16bF-04i 7,L7E-04 A,21E-06 ?.23E-05 7.01E-n7

  • .L1E-07 I .OE-04

2,39E-Ob 1.15E-07 Li. LiE-OS n100 0.O 0.0 0.0 0.0 0.0 0.0 0.0 I .75E-04 I .20E-03 u.92F-Ob 2.06E-Ob 2.12E-05 2.L1E-07 2.1 3E-0 4 GI-LLI 1 3LiE-0 7 1 .b7E-05 Li.*27E-07

  • .27F-09

9.24E-09 1 , 30E -09 1 .bqE-Ob 1

  • 08E-05

2.AbE-07 3.23E-05 uL 5 I E-07 9.b7E-Ob 2.53E-06 "7.SuF-Ob 2. 3SE-05 3.93E-06 I I ;3L-05 I. ,3E-OS 3 ,* .':6, -05 b. 1 IE-07 1 .67F-06 I , 5E -0O h. 12E-06 b.bBF-06 I .71E-05 2,0* E-09 3.33E-Ob I . 30F-0b 2.qOE-08 2.05E-1 3 0.0 2.08E-O0 2.88E-07 4,i 11E-1I 0,0 4**37E-05 9.02E-05 2,59E-05 5.3RE-Ob 6.3PE-05 1 .6bE-I 0 4.81E-OS Note: 0.0 means insufficient data or that the dose factor is <].OE-20.

1.109-47

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

UINB 95 1,7kF-0

  • .77E-n7

5.2hE-07 0.0 9.b7E-n7 b.12F-05 I.30E-65 41N8 97 2.783E-11 7.03E-12 P.56E-I? 0.0 5. 1E-12 .oO F-07 1.2F-0H u24n 93 0.0 1.17F-nb 3.17E-1; q.n .S55E-07 5.11E-05 1.7qF--t U2MD Q9 0.0 1.51E-0B 2.87E-19 0,n

.°UE-nB

1,1 AE-05 i.10-05 431C 994 0.n 3.64E-13 4 .h3E-1P 0.0 5.52E-12 P.SbE-n9 S.20F-n/ 437C 9q 0.0 U.64F-0R I.37E-04 0.0 5.95E-07 l.nIE-04 7.SuEE-0b Q3TC 101 0.0 7.52E-15 7.38E-14 n0.0 1.35F-13 U.9qE-ns 0.0 44RU tn3 l.91E-07 0.0.

9.23E-fl 0.0 7.2qCE-07 6.32E-05 1.S -o.. 4uRU 105 9,ASF-11 0.0 3.RqE-l1 0.0 1.27E-10 1.3AE-0b b.0?E-flb 'JLRU 106 8.64E-0b 0.0 I.0qE-06 0.0 1.67E-05 1.16E-03 1.i 1 E-oll 45RH 105 q.24F-10 b.73F-10 4.43E-10 n.0 2.hE-nQ 2.'41E-ntb 1.01)E-05 46PD 107 0.0 q,27F-08 5,87E-09 0.0 b.57E-07 Q.ugE-Ob 7.OhE-(,7 46PD 109 0.0 4.b3F-10 1.16E-itf n.0 ?.35E-og 1.85E-Ob 1.52i-fS 47AG 1I104 1.335E-06 I.25E-06 7.a3E-07 n.( 2.3bF6-06 5.OE-04 3..763 -05 47AG I1 I ,425E-08 I ./BE-08i A.8TE-Oq o,0 5. 7uE-P h 2. 34E-n)5 P.l79F-np I URCO 113M n.0 1.54E-0O '.q7E-06 0.0 1.71E-n4 2.06F-0U 1.99E-n5 48CO 115M 0.0 2.ab4-05 7.qSE-01 0.n 1.9RE-05 1.7bE-Ou .8OE-05 50SN 123 3.02E-05 6.66E-07 9.P2E-07 5.6bE-07 0.o P.89E-00 3 .92 -n5i 50SN 125 1 .IhF-0b 3.13E-08 7.03E-06 2.59E-03 0.0 7,u2E-05 .MIE-05 50SN 12b 1.58E-04 J.I BE-06 6.OOE-06 1,P3E-0b 0.n I 17E-n 3 1.59L-0P SISB 124 3.QOF-06 7.3bE-08 155E-06 9.44E-09 0.0 3.1OF-0u 9.0OBF-nl9 51S5 125 8.2bE-06 B.91E-OR I6bbE-06 7.34F-09 P.0 ?.75F-04 I.?bhf-05 51SB t2b .O50F-07 9.13E-09 1.62E-07 2.75E-0 n 0.0 1.5RF-n5 b. OIE-0q 515 127 3.30E-08 7.22E-i0 1.?7E-09 3.q7E-10 0.0 ?.nSE-05 3.771F-05 52TE 12591 4.27E-07 I.98E-n7 S.84E-0A I.31E-07 1.55F-nb 3.92F-05 8.MSF-Ob 52TE i274 1.58E-06 7.02E-07 1.9hE-07 4.11F-07 5.72E-Ob 1.?OF-OQ 1.

7F-O0 52TE 127 1.75E-10 -. 03E-.11 3,87E-11 1.3.E-10 h.17F-j0

  • .15E-07

7.17E-oh 52TE 129M 1.22F-0b 5.64E-o7 1.9RE-77 4.30E-07

.S7,-0b

5E6 11SE-Oa u.7qE -01 52TE 129 b.22F-12 2.99E-12 t.5SE-12 4.87E-12 2.3L3E-11 .a2F-07 t.9bF-0 8 52TE 1314 B .74E-09 5.SE-0q 3,63E-09 BBF-01 3. bE-1A 1.82F--05 b, .9SF-0 52TE 131 1t39E-12 7.44E-13 u .'J9E-13 1.17E-1F 5.ubE-12 1.7 F-07 2. 4uE-0q 52TE 132 3.25F-07 2.b9E-Of 2.0?E-08 ?.37E-0 I.S3E-n7 3,60F-05 6 .3 7E-f5 52TE 1I33M 7,24E-12 5.b0E-12 7.14E-12 6,27E-12 3.7TF-I1 5.51E-07 3.u5F-AQ 527E 134 3.84E-12 3.22E-12 1.57E-12 3.t)U E-12 2.1BE-11 Z.3UE-07 3.b9Emog 531 129 2.'49E-0b 2.1IE-O6 6.91E-O 5.55F-01 14.514E-0b o.l 2.2E-07 S31 130 5.73E-07 1.68E-Ob 6..hF-07 2.18F-04 2.blE-m6 0.0 q.hlF-07 531 131 3.ISE-O6 4.47E-06 2.56F-0b 1.0J9E-03 7.b7F-Oh 0.0 7.8hF-O7 531 132 1.45E-07 U.07E-07 1.45E-07 5.JBE-05 b.UqF-07 0.n 5.18F-0R E 1.109-48

TABLE C-i (Continued) NUCLIDE 531 531 531 55CS 55CS 55CS 55CS 55CS 55CS 5695 S6BA 5*A SbBA 57LA 57LA 57LA SRCE 5FCE 58CE 5QPP 51PR bO lO blPm b61 P.

blPM b2SH bSM b*EU b3EU 63EU b3EU 6ST9 b7 1O 7LJ, 7iU 82PR R391 BiPo 133 134 135 135 j36 137 139 139 I40 1Ul1 2 1UO IL I 7 149 151 151 153 15? 151 155 15h 160 Tk-T 155 917 210 210 210 BONE I .0BE-O0 5.ObE-08 3.30E-07 I

  • bOE-OR

U .hlF-05 1 ,UbF-05 4.8QE-06 5.08F-05 L4. IIE-0b 2.50F-08 1.17F-I 0 4.,86.F-0B 5 . 3 UF- 10 9 I F25 - 11 2.49F-02 2. 3 5F -083 U3 2E -Ou I I.7E-06 3. 7bF- 1? 6.59E-07 8.37F-05 9.82gE-Ob 3.84E-07 3. 17F-O ,5* F-0q .759F-05 I .70E-08 2. 3b8F-0d 7 IJOE-0U I *OIF-05 I .79E-Ob ?. 21F-OS 3 . 3 7E -O0Q 6.2 IE-05 I .9SF-07 I , ObF-OQ n.0 3.97F-O0 LI VER I 56'F-Ob 2. 16E-07 R. ?£E-M7 S.20E-D8 1 .06E-On I .29E-o5 I .83F-nS 7. 77F-05 7. 77E.-08 3.53F-n8 9. 32F -I a I E 15FO 63 3 8E- 15 9,LIE-i5 2. 1 7E-OA 1 bhF -In ,.88E-1 I I ,bQE-Ob 1 .72E-n9 1.79F-04I 4.6QE-07 S.S96E-1 2 7.b2E-07 7.87E-nb 2.5UE-16 S. 37E-o8 U.87E-09 I.42F-09 1 U.RE-05 1. iF-08 5.UOE-05 9. IOE-O5 I u3SF-nS I uSE-nb 0.0 I .OSE-n0i 2o0TE-ng 6. U7E-08 3,B5E-10 6.72E-03 I .59F-O0 9.bOE-01 5.h7E-07 7.70E- n 3.?2E-07 I .72E-0A 9.11IE-35 6.AOE-lh 1 .3 F-05 5. 36E-05 U . OE-31 3.LE-t 2 3.21F-07 !1.2nE-I 3 A. 7E-1 3 5S.

71E-LnQ 2.7 1E-1 1 9.bSE-1 2 1 .QIE-07 I I* E-IQ 2.30F-05 5. 7c)E-OR I .I E-1 3 Li.S6E-ag 1 * ~ I AE -0 L6 I.

QfE-Oh 3.2nE-na I .'99F-00 7.21E-10 1.SSE-Ob I O4E-09 .1E7h-05 6. LRE-OS 9,21E-Oh 2.UOE-n7 2. 75E-1b q.00F-05 ?.1 7E-t 0 6.81E-09 3.1 OE-lO0 8A.7E-Ou I .3?E-07 Q.58E-05 TOTAL BODY THYROID 3.hbE-OLA 2.97E-05 I . 1 7 F -OU 0.0 0.0 0.0 0.0 0.0 0.

0.0 0).0 o.n 0.0 0,.0 0,0 0,0 0 . 0 o~t 0.0 0.0 0,0 0.0 0(.0 ,0O 0.0 0.0 0l,0 0.0 0.0 0.0 h,0 0.0 0.0 0.0 KInNEY 3,*25E-O6 3.2UE-07 . 1 F-Ob I .07E-05 2.'1IF-05 h.Olr-nR 3705F-05 7. li3F-Ili 2.0QE-nq 2. 7E-IS 0l.0 0.0 0.0 7 .* 7 .0 E-1A9 .570F-07 R.55F-l 3 1 .5AQE-0S 3.

5F -0 I . f6E-17 9. IQE-O5 ?. 55F-nQ I .56E-05 '4.* 9E-n9 3. 35E-04 La . 3bE-~IL 5. 59E-05 9. 95F-07 ,I E-Oh t,57E-ou n,0 0.0 0,0 2., 1 2E-02 1 92F-05 2.-75E-03 LUNG GI-LLI 0.0 I.09E-06 0.0 0.0 bSbF-U7 ?.94F-OQ 7.,2E-o9 I.22E-05 I.30E-Otf 1.57E-06 2.11F-07 9. UE-Ob I.05b-0h S.07F-09 2.33F-15 ,;).9 E-09 0.0 u.70E-07 1.12E-07 1.5QE-nu 2.73L-05 ?.112E-07 I.115F-17 l.UqF-07 0.0 1.70E-)5 5,.73E-nE 1.SSE-Ob 7.31E-0e 7.02F-07 2.ULF-07 u.52F-n5 1.SoE-05 9.LRF-=Ob 2.USE-05 4.73F-Au 1.02F-0O1 i.51F-3S 2.50F-05 1.27F-07 2.b6)-18 2.76F-05 ?.IhE-09 5.blE-n5 5.S4E-06 2.l tjF - nU i M. 18 F- 0 3.Q1E-05 5.8OE-05 7.?2E-Ob 2.50E-05 3.Q4E-Ob 2.OOE-05 J.LbE-n5 3.25E-06 u.1SE-Ob . .58F-0S 3.u3E-n4 1,59k-os 5.P.5E-0L 3,'IOE-05 1.47F-05 5.95F-n6 9.57E-05 L.SOE-05 1.Q2E-04 2.68E-05 3.q -OL 1.59F-05 1.72F-06 2.53E-07 5.57E-05 1.07F-05 3.b3E-Ob 1.94E-O5

.63E-02

3.b6E-O5 1.11F-03 2,qSE-05 3,s1E-n2 4.19E-05 1.109-49

TABLE C-1 (Continued) NUCLIDE 88RA 223 88RA 224 68RA 225 88RA 22b 8BRA 22A 89AC 225 BqAC 227 9QTH 227 90TH 228 90TH 229 90TH 230 90TH 232 90TH 234 91PA 231 91PA 233 92U 232 92U 233 92U 23U 920 235 q2U 236 92U 237 92U 238 934P 237 93NP 23B 93NP 239 Q9PU 238 94PU 239 94PU 240 9PIJ 2ul 94tPU 242 94PU 240 95AM 201 95AM 2424 95AM 243 96CM P42 96CM 203 96CM 24, 9bCM 205 9bCM 246 96CM 247 96CM 208 98CF 252 BONE I .80F-0O 1.98F-O5 3,00E-0O 1.25E-01 4,41E-02 4.23E-0a 2.30F 00 2. 1 7F-0O 2.00F-Ol 8.88E 00 2,2QE 00 I .99E 00 I .63E-Ob S.n08 00 1.21F-06 5. I 0E-02 I .09£-02 1. O* E-02 I. OOF -02 1 .OOE-02 3.67£E-08 9.58E-03 1.69E 00 2.96E-07 2.87E-O0 ?.69E 00 3,05E 00 3.04E 00 6.0SF-02 2.89£ 00 3.45E 00 9.93E-O0 1.02F n0 9.qUE-01 I , I UF-02 7.8SE-Ol 5.QOE-O1 1.?bE 00 1.25E 00 1.22E 00 I.01E 01 7.33E-01 LIVER 2.77E-07 4.7BE-08 3.56F-07 2.39E-06 1.23E-Ob 5.82E-nO 3.05E-0l 3.92E-06 3.39E-03 I .33E-01 1.31E-01 1.12E-01 9.56E-08 I .91E-01 2.4 2E-07 0.0 0.0 0.0 0.0 0.0 0.0 0.0 1,47E-01 7.99E-09 2.82E-09 3.73E-01 4,19£-nl 4. 19E-01 3.28E-03 4.76E-01 3.46F-01 3.46E-01 3.40E-O0 I . 18F-02 2.97E-O0 2.5IE-01 3.59E-01 3,59QE-O 3.53E-at 2.91E 00 0.0 TOTAL BODY 3.bOE-05 3.96E-06 9.13E-02 4.76E-02 2. 8OE-O5 1 .36E-01 6.25E-06 6.77E-03 4.36E-O0 6.36E-2? 5.43E-O2 4.70E-08 I.9SE-OI 2.09E-07 3.66E-03 6.5QE-Ou 6,06E-Ou 6.07E-Ou 6.20E-00 9.77E-09 5.67E-O0 b.87E-OP 1.61E-n9 1.55E-09 6.6hE-£O0 7,53E-0? 7.53E-0? 1.29E-03 7,1 7E--2 B,5'4E-02 b6,7E-02 B.73E-02 hf.uE-n2 7.50E-04 4.61E-02 3.51E-0? 7.1 £E-f2 7.03E-a? 5.7qE-01 i .83E-02 THYROID n.0 0.0 0,0 040 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 nO, 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0,0 0.0 0.0 0.0 0.0 0.0.

0.0 0.0 0.0 0.0 0.0 0.0 0).0 0.0 KIDNEY 7.8SE-nb 1.35E-Ob I .OIE-05 6.77E-05 3.QSE-0O b . 3£ -05 9,9 2E-02 2.22E-05 I. 89E-02 b .52E- I- 6. (10E-0 1 5. *17E -01 5 *, L 1 E-0 7 0.0 9 . 1 SE -07 5.56E-03 2.5E-03 2 ,. -E -03 2. 3E-n3 2, 3Sq-03 1.51£-fl? 2. 1AF-03 5. 10E-O1 2. 7?£-09 8. 75E -flQ 2,*,5E-01 3.?0F-01 3. 20£-0 I 5.93E-03 3,OSE-nt 3.64E-01 5. OIE-OI O.BbE-01 3.SOE-03 2.15E-01 1,64E-01 3.33E-ni 3.33E-01 3.28E-01 2.70E 00 0.0 2.5SE-02 q,78-03 2.92E-02 1 .17E-01 1. 61E-01I 2,21E-02 2.q F-0I 3. 78E-02 1.DIO E (in 3.50E 00 b.22E-01 5.31E-01 I.89E£-O 5.75E-OP 3.52E-05 2..23E-01 5.33E-02 S.?2E-02 .QOF-02 5.01E-02 t.02F-0S 0.5FF-02 5.22F-02 1 .0E-05 u. 71F-Ob I .76F-01 I .b7E-0 I h7F-01 I .52F-O0 I sq9E-01 I .89F-01 5.86F-02 2.45E-02 5.bSE-n2 3.74E-02 6.32F-02 6.07F-02 5.86£-n? 5.97E-02 5.86E-02 0.83E-al 1.56E-0l GI-I.1.1 2.B4E-O0 3.0 E-Ou 2.71E-Oa 2.94E-0O 5.00£-05 2.52E-04 O.92E-05 3. 3uE.-Oo 3.17E-04 3. 1 7E-OU 3. 73E-05 7.9'jF-05 7.03F-05 7

  • 0 3-OSi

1.02£-05 0*lbE-05 3.89E-05 S.lf-05 0

  • 80£-05

3.57E-05 I, 2OE -nr I .ASE-O0 4.92E-O5 2.13F-05 0 . 52£F -OIi 0.52F-Os .20F -05 8. SE-07 .o

  • 05-OS

t.03E -05 .6bOE-09 5. 7qE-05 b.03E.-05 4.64E-05 '4 *. 6E -05 0. 36F-05 0.291-O', 5.b E-OS S. 091-O0 I . 78£ -00 I 4 1.109-50

TABLE C-2 TEENAGER INHALATION DOSE FACTORS (mrem/pCi inhaled) NUCL IDE I H 3 bC 14l 11!INA 22 27C0 55 27CO bO 38Sp B9 38SR 90 3c9Y 90 39Y 01 'jOZR 95 JJINB 95 U'JRU 103 44RJ;U 106 S0SN' 123 52TE 1254 52TE 127 52TE t294 52TE 132 531 129 531 131 531 133 55CS 13Ll SSCS t37 56BA 1Ji0 57LA ILJO 5ACE 1'J1 58CE I1U U b3EUI ISLI QU 232 9?U 234I 9UPU 234~ QLIPU 239 9Lipu 2U0 9LJPU 24I1 95AM 24J1 96CM 24I2 9CM 244L A ONE 0.0 5.66E-07 I

  • 7bF-OS

0.0 0).0 4,.84E-06 I *.48E-03 I .41E-.08 b. 72E06b 1.*3bE -Ob I . 70E-07 2.04OLE-08 I .05F-0b 5.09E-08 I b62E- II I .49E-07 3. 75F -09 3.53E-06 4I.21IE-06 I 54~E-06 6

  • LE-05

8. 02E-05 6,62E-07 I .79E-09 2.84IE-07 5. 2uF-05 9.195E-05 6. lL4E-03 I .25F-03 3.22F-01 3.67E-01I 3.66,E-0 1 I .29E-04I I .20E-01 I .35E-03 b.99E-02 LIVER TOlTAL 8B1)Y 1.06E-07 1.OhE-07 5.66E-07 S.bbE-07 1.76E-05 1.76E-05 2.20E-08 2.93E-OR 1.55E-07 2.OhE-07 a3.0 1 .39E-07 0.0 9.01JE-05 0.0 3.79E-10 0 .0 1.80E-07 !J.5LLE-07 3.17E-07 1.03E-07 9.7AIE-09 0.0 Q.ISF-flQ 0.0 1.3?E-07 7.6RE-08 I.1ISE-n7 2.32F-D8 b.QIE-09 7.30E-12 4I.02E-12 7.05F-08 2.40OE-08 3.-OOE-09 2.2QE-09 2.9UE.06 9.81E-06 5.90E-0b 3.SRE-06 2.58E-06 7.93E-n7 1.38F-04I 6.80E-05 1.03F-04I 3.79E-fl9 6.06E-10 LI.?7E-ng 4,.72E-10 l.b7E-10 1.90E-07 2.1RE-DA 2,17E-05 2,80E-06 I.02E-o5 ý.07E-06 0.0 LJ.37E-OLI 0.0 Z.72E-nS 3.4I3E-02 7.9FLE-03 5.OOF-02 9.06E-03 5.OLIF-n2 Q.13E-03 I.BLIE-0S 3.26E-Oh 4l.11F-02 7.79E-01 1.40OE-03 8,97E-0'; 2.99E-02 4I.16E-03 THYROID I .06F-01 5.bbE-07 i .7bE-05 A,( 0.0 0.0 0.0 0.n 0.0 0,0 0.0S.* 0 0.0 6.1 5E-OA 1 USE-OB 1.34E-1 1 i.FBE-05 2.54E-09 7.32E-03 I .7E-03 4.79E-04 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0,0 0.0 0,0 0o0 K I 3NEY LUNG 1 .O06F-07 S.b6E-07 I .76F-05 I .71E-OLI I .07F-03 (USE 3.13E-0LJ ?.n7F-03 0.0 PMULT 3.57E-04I 3.*20E-04I 9.96E-05 DOSE 4.'I9E-05 ?.05E-nS LI 693E-0LI FACTOR) 6.70E-05 I .33E-06 21.5LF-0LI 5.6b7E-05 0.0 0).0 0.0 I .ROE-05 1 .47F-05 P. 53F-OLI 2. 70E-05 7. 29E05 I . 72E-03 9.29E-04 3.84IE-01 9.00OE-02 3.1ILI-01 2.98E-01 3.01E-01 I Q92E-04I I .0 1E -0 1 6.LI7E02 1 OSE-01 U 1-LI. I I .ObE -07 5.06eE-07 I .'J LE-Oh 1.1 I F-05 2.Q4lE-0'5 4.4 L2E -05 9.* bF-05 h. 79L-0'5 LI * 7F -05 I .6bE -05 1.1 IOE -05 I . IRF-05 1. 16L-04I 3.91E-05 8.95E-06 I . 01IE-09 LI.80E-05 b.b lE-OS 2. 16F-07 7.45FE-07 1 .25E-06 I . 12E-06 9.bOE-07 5.981E-05 I .4I2E-05 1 . OSE-04* 3.UIE-05 4,. IbE-OS 3.F81E-05 's.52E-05 '4. 13E-05 4,. 13E-05 7.94LE-08 LI.LJLE-05 LI.60E-05 N4ote: 0.0 means insufficient data or that the dose factor is <1.OE-20.

1.109-51

TABLE C-3 CHILD INHALATION DOSE FACTORS.

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

2,73E-0? .16E-n5 9.73E-06 9.31E-02 2.33E-02 3,17E-03 2.bRE-0O, b.77E-02 1.24E-02 T-4YR310 ?.03E-07 I ,69E-06 a. a2E-05 0.0 0.0 0.0 0.0 0.

000 0.0 0.0 0.0 I .9RE-07 4.35E-05 U.,IE-l 1 1 .4bE-07 7.24E-04 2.14E-02 u.t6E-03 I

  • 36F -03

0.0 °00 0.0 0.0 0.0 0.0 0.0 0.n 0.0) 0.0r 0.0 0.0 0.0 K I )NFY LJN.G 2.03E-07 I b69E-06 ", '2E-05 3.,O*E-OLi (USE 1.67E-03 _____ . 0E-Oa

  • .OOE-n3

7.26E-05 ADULT 6190E-OI 5. 72F-O0 DOSE I 5AE-0* 1.71E-04i 3.93F-03 FACTOR) 9.46E-04 I . 30F- 04 2.5E-Ob a.T7F-OU I .03E-O0 0 .1.0 0.0 3.21E-n5 2.71F-05 0.69QE-0 U*Q2E-05 I. 39E-n4 3. 32F-n3 I .67F-03 7,"J3E-nl I .70F-01 5.87E-01 5.5bF-0I 5.61E-ni 3.6lE-0OJ I .QSF-OI .2 ? E_- n_1-_ ?,02E-01 GI-LLI 2. 03R -07 I .bqE-06 9. 1,* -0o 2.H3F-0% I.56F -05 Q1 1 ,EF-Ob .. 23E-OS LI .* _-O .I S2E -05 lI. 1 I- -05 7. 13 7-07 .10 3E-06 I. 53F -05 q.22E -OS) b.52(- -05 2.168-07 7. I 7E-05 I .54E-O0 I .08E-Ob , 22E-')7 2.. 28E-01 I.flE-05 I .07E-OP /J. 57F -05 3.71F -05 a. V2E-is Li, ŽLE -05 8. 1bE-OF

  • J.S7F-05 a. 73r-05

6 0,0 Note: 0.0 means insufficient data or that the dose factor is <1.0E-20.

1.109-52

TABLE C-4 INFANT INHALATION DOSE FACTORS (irirem/pCi inhaled) NUCLIDE bC 1" IINA 22 27C0 58 27C0 b0 38SQ Q.

38SR QO 39Y 00 39Y 91 4nZR 05 4INB 05 4JRUi 103 44RU 106 50SN 123 52TE 1254 52TE i27 52TE 1294 S2TE 132 531 129 531 131 53! 133 55CS 13u 55CS 13 7 5b8.

!LAO 57LA 1LO 5BCE 1l1 58CE IlUq b3EU 154 92U P32 92U 234 quPU 238 9gPU 239 gapu PLao 94PU 2U1 95AM 241 96CM 2u2 obC4 2U4 S O:N F 0.0 3.6OE-O0 7.53E-05 0.0 0.0 3.01E-05 9.4FE-03 2.lOF-07 UL27E-05 7.7uE-O6 9. I6E-07 I .21E-07 6.b5E-O6 2.22E-05 3.2uE-07 1.03E-I0 Q ,UuF-07 2,25E-08 2.23E-05 2.59F-05 9.5hE-06 3. 43E-OL ".90E-04 .0 7 7E-06 1 .09E-08 i .80E-Ob 3. 3IF-O4 5.99E-0O 3.q1E-02 7.94qE-03 2.05E 00 2.33E 00 2.33E 00 5. IBE--04 7.61E-01 9,62E-03 4.L45E-0 1 LIVER 3. 07E -n7 3.6OF-06 7.53E-05 8. 39E-OR !. OOE-07 0.0 0.0 0,0 1 .9SE-06 4. 11E-07 0.0 0.0 U.6IE-n7 I .39E-07 w. 31E-t II 4i 1 UE-07 I. I2E-08 I .b2E-05 3.n5E-05 I .38E-05 5.8QE-O0 5.22E-04 S05E-09 2.29E-3q 1. IIE-0b I 30E-04 4.95E-n5 0.0 0.0 2.66E-01 3.O0E-01 3.02E-01 I. I OE--04 2.47E-l1 8.40E-03 I. 70F-01 TDIAL 3J)Y 3.07E-07 3.bOE-06 7.53E-05 I .2nE-07 8.38E-07 5,89E-07 5.7hE-0A 5.65E-09 191 LE-OB 1.*3QE-*6 2.ULiE-07 4 . ! 9E - n 8.16E-07 7.30E-07 u.UOE-08 2.56E-1 I 1.47E-07 I .*hE-nR 5.A2E-05 I .70E-35 LA.

I QE-Oh 5.23E-05 3.15E-n5 2.11IE-07 7.* E-1 0 1.2QE-17 I .7AE-05 3.72E-05 2.71E-03 0.91E-14 S.OSE-92 5.77E-02 5.81E-0? 2.07E-05 L.96E-02 5.71 F- 14 3.07E-07 3.SAE-06 7.53E- 0 5 0.0 0.0 0.0 0.0 0.0 0.0* 0.0 0,0 LA.

IlE-07 0 .O E- 1 .0 9F-0 7 I .OOE-10 3. 63F -0 7 I .70E-05 5.21E-02 I .OIE-02 3.

33E-03 0.0 0.0 0.0 0.0 n.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 K I NE Y LU N C 3.07E-07 3.bOE-Ob 7.S3F-05 h.28F-O0 (USE 3.QRE-03 I .h5F-n3 I .09E-02 AU. Q8E-04 ADULT' , 88E-03 I .2QE-03 DOSE 3.JiF-OU D. OE -04 I .07E-02 2.SBF-A3 FACTOR) 3.54E-O4 7. 03F-00b I .31E-03 2.Q8E-04 0.0 0.0 0.0 7.22E-05 5.7%E-05 ,I 17E-03 1 .21E-04l 3.7AE-O0 9.06E-03 3. 99E-03 2.02E 00

  • .7LE-fl I .51E

00 I .43E 00 I .45E 00 q.9OE-nf S.32E-01 3,UIF-01 5.51E-01 GI-LLI 3.07F-n7 3.OF-Oh 1 .22L-06 8.67F-06 2. *3E-('0 4.6bE- 9.89F-

5.

1 2E -05 I .01E-05 8. b7E-Ob 11.

I SE-05 1.2bE-04 4.28F-05 9.71F-Oh I .87E-05 5.23F-05 6. b8E-05 2M2E-07 7b6hE-07 I .S3E-0b 9.80E-07 9.45E-07 2.77E-06 6.43F-05 1 .4l F-05 I 15E-OLA 3.73E-05 L.SSE-05 A. 16E-05 4.qbE-05 U.51L-05 A.51E-05 8,.bE-08 U.86E-05 5.29E-05 5.03E-05 0.n 2.65E-02 0.0 Note: 0.0 means insufficient data or that the dose factor is <1.OE-20.

1 . 109-53

This yields C V4(ro) = 3.17 x 107 Q74[x/Q'](r,) 0.11/0.16 U = 2.2 x 107 Qi4 [x/Q'J(r,O) (C-8) where C v4 (r,O) is the concentration of carbon-14 in vegetation grown at location (r,e), in pCi/kg; !Q14 is the annual release rate of carbon-14, in Ci/yr; 0.11 is the fraction of total plant mass that is natural carbon, dimensionless; 0.16 is equal to the concentration of natural carbon in the atmosphere, in g/M 3 and 3.17 x 107 is equal to (1.0 x 1012 pCi/Ci)(l.0 x 103 g/kg)/(3.15 x 107 sec/yr). The concentration of tritium in vegetation is calculated from its concentration in the air surrounding the vegetation.

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

The deposition rate from the plume is defined by: dC(r.o) = 1.1 x 108ai(r,e)Qj (C-10) where 61 (r,O) is the relative deposition of nuclide i, considering depletion and decay in transit to location (r,O), in m"2 (see Regulatory Guide 1.111) and 1.1 x 108 is the number of pCi per Ci (1012) divided by the number of hours per year (8760). For radioiodines the model considers only the elemental fraction of the effluent.

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

Measurements at operating facilities indicate that about half the radioiodine emissions may be considered nonelemental (Reference 4). With this consideration included, Equation (C-l0) for radioiodine becumes: I 1.109-54

15.5 x 107 Si(r,6)Q.

(C-1l) and Q! is the total (elemental and nonelemental) radioiodine emission rate.

The retention ictor r for elemental radioiodine on vegetation should be taken as unity, since the experimental mea- surement (References 5, 6, and 7) techniques used to evaluate this transfer mechanism consisted of direct comparison of the gross radioiodine concentration on vegetation and the concentration in air (References 8, 9, and 10). For radioiodines, the deposition model is based only on the dry deposition process.

Wlet deposition, including "washout" of the organic and non-organic iodine fractions, should be con- sidered at some sites depending on the meteorological conditions (see Regulatory Guide 1.111). For particulates, the deposition model considers both wet and dry deposition.

There is also a retention factor (r of Equation (C-7)) that accounts for the interception and capture of the deposited activity by the vegetative cover.

A value of 0.2 is taken for this factor (References 11 and 12). All nuclides except noble gases, tritium, carbon-14, and the iodines are treated as particulates.

a.

Parameters for Calculating Nuclides Concentrations in Veqetation Consumed by Man When the radionuclide concentration in vegetation directly ingested by man is estimated using Equation (C-7), the following parameters are used: Parameter Value Yv (vegetation yield) 2.0 kg/mi2 te (exposure time to plume) 60 days th (holdup after harvest) 1 day for garden-fresh leafy vegetables 60 days for stored vegetables tb (soil exposure time) 15 years (midpoint of reactor operating lifetime) All other parameters in this equation are given in Regulatory Position C of this guide.

b.

Parameters for Calculating Nuclide Concentrations in Milk The radionuclide concentration in milk is dependent on the amount and contamination level of the feed consumed by the animal.

The radionuclide concentration in milk is estimated a5 Cm(r,f): FmCiV(r,e)Q exp(-xit) (C-12) where C'(r,a) is the concentration in milk of nuclide i, in pCi/liter; CY(r,O) is the concentration of radionuclide i in the animal's feed, in pCi/kg; Fm is the average fraction of the animal's daily intake of radionuclide i which appears in each liter of milk, in days/liter (see Tables C-5 and C-6 for cow and goat data, respectively; for nuclides not listed in Table C-6, use the values in Table C-5); 1.109-55

TABLE C-5 STABLE ELEMENT TRANSFER DATA ELEM H HE Ll BE B C N 0 F NE N A 4G AL al P S CL.

AR K CA sc TI V CR MN FE CO NJ CU ZN GA GE A5 SE BR KR Re SR Y ZR NB RU RN Po AG CD IN SN Biv VEG/SOIL 4,BE O0 5.OE-02 8,3E-OG 4, 2E-o4 1.2E-01 5*5E" O0 7.5E 00

1. bE GO

6.5E-4O iE-ol 5.2E-02 1.3E-ol I .BE-04 1.5E-OM

1. IE nO

S19E-0! S.OE 00 6oOE-01 3,7E-oi .,,6E"O,? I . IE-03 So"E-OS i 3E-03 2.SEOu0 2.9E-io2 6,6E-Oq 9,a4E-03 1,9E-O2 1.2E-01 (S.OE-OI 2.SE-0O i OE-ol I.OE-02 1.3E O0 7#bE-01 3,OE O0 1,3E-01 1.7E-02 2.bE"03 16.7E-04 9.4LE,-03 1.2E-01l 2,5E-01 5.OOZ02 1,3E 01 5,OE' 00 9.OE"01 t,;5E-Gt 2.5E-01 3, OE-O I 2,SE-01 2,5E'03 F m(Cow) MILK(CD/L I ,OE02** 2,0E-O; 5,0E-O.

I,0E-Oa 2,7E-0" 1,2E-02 2,2E*O.

2. OE*O2 1.,E-02 2. OE-O? 4 .OE-02*4** IOE-02 5,OE-Ou I1OE-Oa 2,5E-OP IBE-02 5,OE-02 2.0E-02 IOE'O*. 8 , OE-03*** 5.0E'06** 5,OE-06 S. GE-Ge, lOE-03 2,2E*03 2,SE-Ou 1?2E-03 I.OE-03 6,7E-01 I# 4E-02 5,0E-05 S. OE04 6,OE"03 ',SE-02 S.OE"O2 2, EOE.02 3#OE-O2 B OE-O4*** I I OE-05 S OE-06 2#5E"03 7,5E-03 2.SE-02 IOE"O6 I.OE-02 I,OEOG.

5,0E'02 5aOEw02 162E-Ou I.OE-0O 2.5E-03 Ff MEAT(D/XG) 2.2E-02 2,nE-02 i.oE-n3 B.OE-n2 3.

1IF-n2 .OE-02 I .6F-02 I SF-ot 2. OF-n2 3.OE-02 SIOE-03 I ,E-o3 Q.OF-03 u.bFE-2 'J.6 -n2 I a.E-nI 8. nE-o2 1.2E-02 a.bE-02 3,IE-02 2a3E-n3 1.4E-03 4.OE-04 4.OE-n2 1.3E-02 S,3E-03 8. DE-03 3OBE-62 I ý3F on ?.fE 01 2.OE-03 1.5E-n3 2.OE-n2 3 a I E -0' Is.6 E-03 3,OIE.02 2.

, BE -01 5,OE-o3 4. G E-ot t.SE-03 I .7E-02 8.OE-n3 R.MfE-02 ELEM SB TE I VE CS LA CE PR ,jD PM S4 EU GD TB Dy ER T YB LO NF TA w RE OS I R PT A U TL PB 81 P3 AT RN FR PA A C TH PA U NP PU A 4 9K CF ES F - 8.av VES/S3IL I.IE-02 I'3E 00 2,OE-02 IOE 01 I OE-02 b,OE-03 2,SE-03 2*5E-03 2,SE-03 2 5E-03 2,SE-, 3 2.E-03 2.SE0 3 2,bE-03 2.bE-03 2,SE-03 2,#E-03 2. SE-03 2, 5E-03 2, SE-o33 2 bvE-03 1,7E-OP 6,3E-03

1. SE Ot

5,3E-01 2.SE-03 3 @3E-0I 2.5E-01 b, SE-02 I9SE-01 2oSE-01 2, SE-Ol 3,SE 00 I, E-O2 3, IE-OQ 2.5E-03 Q,2E-03 2,SE-03 2,SEmO3 2, SE,,03 2, SE"-0 2, SE"04 2, SE,03 2,SEo.03 2 , SE"03 2,SE-03 2, SE-O3 Fm(Cow) 41 LK (1/L) I oSE-03 I .0E-03 b. OE-3l3 2.OE-02 I

  • 2E-02"

. GOE-O1*** 5OE-Oh SOE-Ob S.OE-Ob 5.OE-Gb 5.0E-Ob S.OE-O6 5.OE-Gb SOE-Gb 5.OE-Ob SOE-Gb S.OE-Ob SoOE-06 5IOE-06 2.5E-02 S,OE-Ou 2*5E-02 5.OE-03 5,OE-03 S.OE'03 3.BE-02 2,2E-02 b.2E-O04 S5OE-O0 3,0E-O0 S.OE-02 2.oE-02 5GOE-02 .80"03** 5. GE-O6 S. GE-Oh SOEGOb S.OEGOU 5,GOE-b 2,OE-Oh 5.GE-Gb S.0E-Oh S.OE-Gb 5,0E-06 5,OE-Ob S.,OE-Gb 5,.OE - Oh Ff MEATT(D/KG) POE-03 7, 7E-02 I2ý9E-03 2. E-02

  • OE-03

3.2E-03 2.OE-04 1.2E-03 4,7E-03 3.3E-03 4.8E-03 S. E-03 4.BE-03 3, bE-03 ~4, (E-03 S.3E-03 U,*E-03 .uOE-03 u.OE-03 4.OE-03 ,Ci E-O1 I.bE O0 1.3E-03 .,E-03 uOE-OI 1,SE-03 4.OE-03 .OE-03 2.bE-G1 u.OE-O? 2,9E-04 I SE-02 I 2E-02" GOE O0 2,OE-02 2.OE-02 3,UE-02 be OE-02 2. GE -04I B.OE 02 3,4E-O4- 2,0E-04 1.UE-05*.** 2,OE-Oci 2. OE-O

  • i-

2,OE-G04- 2,0E-O* 20GE-OU f II Ref. 1.

Ref. 3.

Ref. 13.

t Refs. 7, 8, 9, 10, 14, 15, 16, 17.

+t Ref. 18.

E 1.109-56

TABLE C-6 NUCLIDE TRANSFER PARAMETERS FOR GOAT'S MILK ELEMENT Fm (days/liter) H 0.17 B 0.012 C 0.10 Mg 0.042 P.

0.25" Cl 0.5 K 0.057 Ca 0.47

Fe 1.3E-04 Cu 0.013 Sr 0.014 I 0.06 Cs 0.30 Po 0.0018 Computed from the data of Refs. I and 19.

    • Ref.

13.

1.109-57

QF is the amount of feed consumed by the animal per day, in kg/day; t is the average transport time of the activity from the feed into the mil: and to the receptor (a value of 2 days is assumed); and Ni is the radiological decay constant of nuclide i, in days- Milk-producing animals are assumed to be on open pasture for the following grazing periods: Reg i Uon Southern U.S.

Northern U.S.

Pasture Period Whole year (fp 1) May - Sept. (fp = 1/2) where fp is the fraction of the year that animals graze on pasture.

These data may be supplemented by information on site-specific dairy practices.

The concentration of radionuclide i in the animal's feed is then cv(r, a) f fCP(e)+ (I1 f )C5 (r,) +f(1 (-3 , pfC(ro - ,.p i + - I 5 C~ (- where P Ci(ra) is the concentration of radionuclide i on pasture grass, in pCi/kg; I(ro) is the concentration of radionuclide i in stored feeds, in pCi/kg; and f s is the fraction of daily feed that is pasture grass when the animal grazes on pasture.

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

The site-specific Parameter QF (animal's daily feed) th (storage time of animal's food) te (crop exposure time) Yv (crop yield) Value 50 kg/day (wet weight) for cattle 6 kg/day (wet weight) for goats 0 for pasture 90 days for stored feed 30 days 0.75 kg/m 2 (wet weight) for pasture 2.0 kg/m 2 (wet weight) for stored feed 4 1.109-58

c.

Parameters for Calculating Nuclide Concentration in Meat As in the milk pathway, the radionuclide concentration in meat is dependent on the amount and contamination level of the feed consumed by the animal.

The radionuclide concentra- tion in meat is estimated as F (C-14) where C1ý(r~o) is the concentration of nuclide i in animal flesh, in pCi/kg; Ff is the fraction of the animal's daily intake of nuclide i which appears in each kiloaram of flesh, in days/kg (see Table C-5 for values); and t is the average time from slaughter to consumption, which is assumed to be 20 days.

All the other symbols are as previously defined.

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

4.

Annual Dose from Atmospherically Released Radionuclides in Foods The annual dose resulting from ingestion of radionuclide i in the diet is given by 0 . (r,,,) = DFIi4a [Uvf Cv(r,.) + UCr,) + U FC(, + ULf CL(r, e ija i [a a g i a i - Ua i a U.

r (C-15) where D . (r,e) Dija is the annual dose to organ j of an individual in age group a for nuclide i, in mrem/yr; DFIija is the dose conversion factor for the ingestion of nuclide i, organ j, and age group a, in mrem/pCi (from Tables A-3 through A-6 of Appendix A of this guide); and v m F L Ua , Ua, Ua, Ua are the ingestion rates of produce (non-leafy vegetables, fruit, and grains), milk, meat, and leafy vegetables, respectively, for individuals in age group a (from Table A-2 of Appendix A of this guide). All the other symbols are as previously defined.

The annual dose to organ j of an individual in age group a from consumption of vegetables, milk, and meat is therefore DvD = DF .rvf + m + F F L L ja ija a g 1 a i a i a k I (C-16) 1.l0-59

REFERENCES FOR APPENDIX C I.

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

d-,

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

2.

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

3.

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

1i, 1972.

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

5.

D. F. Bunch (ed.), "Controlled Environmental Radioiodine Test, Progress R.eport Num!., To," USAEC Report ID0-12063, January 1968.

6.

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

December 1968.

7.

B. H. Weiss et al, "Detailed Measurement of 1311 in Air, Vegetation and M.1ilk around Three Operating Reactor Sites," Environmental Surveillance around Nuclear Installatiorns.

!nter- national Atomic Energy Agency, IAEA/SM-180/44, Vienna, Austria, Vol.

1: pp. 169-190, 1974.

8.

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

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

10.

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

11.

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

on a Michigan Dairy Farm," Health Phys., Vol.

21, p.

777, 1971.

12.

P. G. Voilleque and C. A. Pelletier, "Comparison of External Irradiation and Consutrption of Cow's Milk as Critical Pathways for 1 3 7Cs, 5 4Mn and 14 4 Ce- 14 4 Pr Released to the Atmosphere," Health Phys., Vol.

27, p. 189, 1974.

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

14.

F. W. Lengemann, "Radioiodine in the Milk of Cows and Goats After Oral Administration of Radioiodate and Radioiodide," Health Phys., Vol.

17, pp. 565-9, 1969.

15.

R. J. Garner and R. S. Russell, Radioactivity and Human Diet, R. Scott Russell (ed.), Pergamon Press, Oxford, England, 1966.

16.

P. M. Bryant, "Data for Assessments Concerning Controlled and Accidental Releases of 1311 and 13 7 Cs to the Stratosphere," Health Phys., Vol.

17, p.

51, 1969.

E I.109-60

REFERENCES (Continued) 17.

J. D. Zimbrick and P. G. Voilleqije (eds.), "1967 CERT Progress Report," USAEC Report 100-12067, p.

36, 1968.

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

19.

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

1.109-61

APPENDIX D MODELS FOR CALCULATING POPULATION DOSES FROM NUCLEAR POWER PLANT EFFLUENTS Calculation of the annual population-integrated total body and thyroid doses should be performed for the three effluent types identified in this guide.

These doses should be evaluated for the population within a 50-mile radius of the site, as specified in paragraph D, Section II of Appendix I to 10 CFR Part 50.

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

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

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

1.

General Expressions for Population Dose For pathways in which the permanent and transient population of the subregion can be con- sidered to be exposed to the average radionuclide concentrations estimated for the subregion, the annual population-integrated dose is calculated as follows: D 0.001 Z Pd f Djdafda (D-l) Dd Yd jad where Djda is the annual dose to organ j (total body or thyroid) of an average individual of age group a in subregion d, in mrem/yr; D is the annual population-integrated dose to organ j (total body or thyroid), i in man-rems or thyroid man-rems; fda is the fraction of the population in subregion d that is in age group a; P d is the population associated with subregion d; and 0.001 is the conversion factor from millirems to rems.

The annual dose to the total body or thyroid of an average individual should be evaluated with the usage factors of Table 0-1. Models and equations for the detailed dose calculations are presented In Appendices A, B, and C of this guide.

The annual population-integrated doses from ingestion of potable water, inhalation of airborne effluents, and external exposure to airborne or deposited radionuclides should be evaluated.

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

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

This average concentration is used in calculating the population doses.

The 50-mile average concentration of nuclide i in food p is computed as C = (/V ) exp(-Ait ) C v (0-2) ip p 1 p d dip dp The population-integrated dose is the summation of the dose received by all individuals and has units of man-rem when applied to the total body dose and units of man-thyroid-rem when applied to the summation of thyroid dose.

1.109-63

TABLE D-1 RECOMMENDED VALUES TO BE USED FOR THE AVERAGE INDIVIDUAL IN LIEU OF SITE-SPECIFIC DATA PER CAPITA USAGE FACTORS (I lAY CHILD TEEN ADULT Uap) PATHW JNITS Fruits & Vegetables & grain Milk Meat & Poultry Fish Seafood Drinking water Shoreline recreation Inhalation External Exposure from Deposited Airborne Radio- active Materials 200.00 170.00 37.00 2.20 0.33 260.00 9.50 2700.00 240.00 200.00 59.00 5.20 0.75 260.00 47.00 5100.00 190.0 110.0 95.0 6.9 1.0 370.0 8.3 7300.0 kg/yr 1/yr kg/yr kg/yr kg/yr 1/yr hr/yr m 3/yr 8760.00 8760.00 8760.0 hr/yr Consumption rate obtained from Reference 3 of Appendix A and in Reference 4 of Appendix A.

Data obtained directly from Reference 4 of Appendix A.

Data obtained directly from Reference 15 of Appendix A.

age-prorated using techniques i 1.109-64

where C d is the average concentration over subregion d of the nuclide i in pathway p, Cdip in pCi/kg or pCi/liter (see Appendices A and C of this guide for models and equations for calculation of pathway concentrations); C ip is the 50-mile average concentration of nuclide i in pathway p, in Cip pCi/kg or pCi/liter; t is the transport time of the food medium p through the distribution system, p in days (Tahle D-2 presents estimates of the transport times that may be used in lieu of site-specific data); v d is the annual mass or volume of food medium p produced in subregion d, Vdp in kg or liters; V is the mass or volume of the food medium p produced annually with the p' 50-mile radius about the site, in kg or liters; 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 P p = Vp/X Uapfa

(0-3) where fa is the fraction of the population within the age group a; P is the estimated population that can be served by the quantity of food p p likely to be produced within 50 miles of the site; U a is the use or consumption factor of food medium p for the average Uap individual in age group a, in kg/yr or liters/yr (taken from Table 0-1); and V is the annual mass or volume of food medium p likely to be produced within a 50-mile radius about the site, in kg or liters.

The annual population-integrated dose is then calculated as ?~O~ 0.001 1 P 8 *U ODF.

(0-4) DiP= .Ol Z p

  • .*faýCipUapDai(-4 where P

if Pp < P Pp p 5 P 50 if P p > Ps and DFai is the dose factor for age group a and nuclide i, in mrem/pCi (taken from Tables A-3 to A-7 and C-1 to C-4); 1.109-65

TABLE D-2 RECOMMENDED VALUES FOR THE TRANSPORT TIMES IN THE FOOD T DISTRIBUTION SYSTEM FOOD MEDIUM Fruits, grains, and vegetables Milk DISTRIBUTION TRANSPORT TIME (in days) Meat and poultry Sport fish Commercial fish Drinking water 14 4 20 7 10 IO To be used in lieu of site-specific data on food distribution.

4 1.109-66

D.

is the annual population-integrated dose to organ j (total body or thyroid), Dj in man-rem/yr or thyroid man-rem/yr; Pp is the population consuming food medium p; and P5 0 is the total population within 50 miles.

All other factors are as defined above.

Note that the above formulation limits the evaluation of the exposed population evaluation to the population residing within 50 miles as specified in paragraph D, Section II of Appendix I to 10 CFR Part 50.

In calculating the annual population-integrated total body and thyroid doses, the current age distribution of the population within 50 miles may be assumed to be the same as the current age distribution of the U.S. population (see Reference for Appendix D). Models and equations for the detailed dose calculations are presented in Appendices A, B, and C.

2.

Use of the Models a.

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

In addition to these pathways, other exposure pathways that arise from unique conditions at a specific site should be evaluated if they provide a significant* contribution to the annual dose received by an exposed population group.

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

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

The formulation expressed in Equation (D-1) may be used.

The total body and thyroid dose of the individuals should be evaluated using Ecuation (A-2) in Appendix A of this guide, together with the age-dependent usage factors Uap obtained from Table D-1.

The dilution from the discharge point to the usage point should be evaluated using appropriate hydrological models for the various subregions.

If the population served by a particular water supply system is not known, it can be estimated by the following: Pw = v/c (D-5) where c is the average daily usage of individuals on the system, in gal/day per person; P w is the estimated population served by the water system; and v is the average'daily intake of the water supply system, in gal/day.

If the industrial usage from the water supply system is known, it can be sub- tracted from the average daily intake of the system before this value is entered into Equation (0-5). For the purpose of this guide, any additional pathway is deemed to be significant if a conservative evaluation of the pathway yields an additional dose contribution equal to or greater than 10% of the total from all the pathways described here.

Any pathway so identified should then be evaluated by a model similar to that used above.

1.109-67

The population served by a water supply system whose intake is within the 50-mile radius may include individuals who reside outside the circle.

This population may be pro-rated to include only the population within the 50-mile radius.

Conversely, a water supply system with an intake beyond the 50-mile radius may serve the population within the 50-mile radius.

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

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

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

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

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

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

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

The annual population-integrated dose is then computed using Equation (D-4) with Pp = PSO" The age-specific factors of Table 0-1 may be used in lieu of site-specific data.

(3) Doses from Shoreline Deposits The annual population-integrated total body and thyroid doses from recreational activities on the shoreline of the receiving water body are evaluated by sunmming the product of the individual doses in each subregion and the population exposed therein.

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

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

The formulation of Equation (D-1) is appropriate.

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

The consumption rate data of Table D-1 may be used in lieu of site-specific data in the evaluation of Equation (D-4). b.

Population-Integrated Doses from Airborne Effluents The annual total body and thyroid population-integrated doses should be evaluated for the following principal exposure pathways: noble gas submersion, inhalation of airborne efflu- ents, ingestion of contaminated terrestrial foods (milk, meat, and vegetation), and external irradiation from activity deposited on the ground.

In addition to these pathways, other exposure pathways that arise from unique conditions at a specific site should be evaluated if they provide a significant contribution to the annual dose received by an exposed population group.

(See Regulatory Position C.1 of this guide.) For the evaluation of exposures from atmospheric releases, the 50-mile region should be divided into 160 subregions formed by sectors centered on the 16 compass points (N, NNE, NE, etc.) and annuli at distances of 1, 2, 3, 4, 5, 10, 20, 30, 40, and 50 miles from the center of the facility.

The atmospheric dispersion factors (x/Q') or similar factors should be evaluated at the radial midpoint for each of the subregions using appropriate atmospheric dispersion models such as those described in Regulatory Guide 1.111.

(1) Doses due to Exposure to Noble Gases The annual population-integrated total body dose due to noble gas effluents should be evaluated by summing the products of the individual doses in each subregion and the population in each subregion.

Equation (D-1) may be used.

For external exposure, the model does not differentiate between age groups.

A structural shielding factor of 0.5,should be applied in conjunction with the dose factor data of Table B-1.

E 1.109-68

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

Equation (D-1) may be used.

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

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

For milk, meat, and commercial vegetables, the formulation of Equation (0-2) should be used to calculate the average concentrations in the foods.

These concentrations are then used in Equation (D-4), along with the data of Tables D-1, D-2, and A-l to calculate population doses.

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

REFERENCE FOR APPENDIX D "Current Population Reports," Bureau of the Census, Series P-25, No.

541, U.S. Dept. of Commerce, 1975.

1.109-69}}


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