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| issue date = 01/31/2007
| issue date = 01/31/2007
| title = Rev. 47 to Offsite Dose Calculation Manual (ODCM)
| title = Rev. 47 to Offsite Dose Calculation Manual (ODCM)
| author name = Ingram C D
| author name = Ingram C
| author affiliation = Duke Power Co
| author affiliation = Duke Power Co
| addressee name =  
| addressee name =  
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=Text=
=Text=
{{#Wiki_filter:Oconee Nuclear Station Units 1, 2 and 3 OFFSITE DOSE CALCULATION MANUAL (ODCM)    Prepared By:  C. D. Ingram General Office Radiation Protection Approved By:  L. E. Haynes Technical Manager, RP, Nuclear GO Reviewed By:  R. A. Bowser ONS Radiation Protection Reviewed By:  M. I. Sanders ONS Radwaste Chemistry
{{#Wiki_filter:Oconee Nuclear Station Units 1, 2 and 3 ODCM Offsite Dose Calculation Manual 2007


Approved By:   D. A. Baxter ONS Station Manager REVISION NUMBER 47 EFFECTIVE YEAR 2007    
Oconee Nuclear Station Units 1, 2 and 3 OFFSITE DOSE CALCULATION MANUAL (ODCM)
Prepared By: C. D. Ingram              Approved By: L. E. Haynes General Office Radiation Protection    Technical Manager, RP, Nuclear GO Reviewed By: R. A. Bowser ONS Radiation Protection Approved By: D. A. Baxter ONS Station Manager Reviewed By: M. I. Sanders ONS Radwaste Chemistry REVISION NUMBER                         EFFECTIVE YEAR 47                                    2007


Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 i TABLE OF CONTENTS Executive Summary
Oconee Nuclear Station                                                                     January, 2007 Offsite Dose Calculation Manual (ODCM)                                                       Revision 47 TABLE OF CONTENTS Executive Summary.         .   .   .   .     .   .   .   .   .   .     . Executive Summary-1 1.0 Radwaste Systems           .   .   .     .   .   .   .   .   .     .   .     .   . 1-1 1.0.1 Liquid Radwaste Processing .         .   .   .   .   .   .     .   .     .   . 1-1 1.0.2 Gaseous Radwaste Processing .       .   .   .   .   .   .     .   .     .   . 1-3 2.0 Release Rate Calculations       .   .     .   .   .   .   .   .     .   .     .   . 2-1 2.0.1 Liquid Release Rate Limit Calculations .       .   .   .   .     .   .     .   . 2-1 2.0.1.1 Liquid Radwaste Effluent Line Release Rate Limit Calculation   .     .   . 2-1 2.0.1.2 #3 Chemical Treatment Pond Effluent Line Discharge .       .   .     .   . 2-2 2.0.2 Gaseous Release Rate Limit Calculations .     .   .   .   .     .   .     .   . 2-5 2.0.2.1 Unit Vent Discharge Release Rate Limit Calculation   .     .   .     .   . 2-5 3.0 Setpoint Calculations       .   .   .     .   .   .   .   .   .     .   .     .   . 3-1 3.0.1 Liquid Radiation Monitor Setpoint Calculations     .   .   .     .   .     .   . 3-1 3.0.2 Gaseous Radiation Monitor Setpoint Calculations .       .   .     .   .     .   . 3-5 3.0.2.1 Unit Vents Setpoints (RIA-45 and RIA-46) .       .   .     .   .     .   . 3-7 3.0.2.2 Radwaste Facility Setpoints (4RIA-45) .     .   .   .     .   .     .   . 3-8 3.0.2.3 Interim Radwaste Building Setpoints (RIA-53)     .   .     .   .     .   . 3-9 3.0.2.4 Waste Gas Decay Tank Setpoints (RIA-37 and RIA-38)   .     .   .     .   . 3-9 4.0 Effluent Dose Models       .   .   .     .   .   .   .   .   .     .   .     .   . 4-1 4.0.1 Liquid Effluent Dose Model for the Maximum Exposed Individual       .   .     .   . 4-1 4.0.2 Gaseous Effluent Dose Model for the Maximum Exposed Individual     .   .     .   . 4-7 4.0.3 Direct Radiation     .   .   .     .   .   .   .   .   .     .   .     .   . 4-18 4.0.4 Effluent Apportionment .       .     .   .   .   .   .   .     .   .     .   . 4-18 5.0 Fuel Cycle Calculations .       .   .     .   .   .   .   .   .     .   .     .   . 5-1 5.0.1 Milling .       .   .   .   .     .   .   .   .   .   .     .   .     .   . 5-1 5.0.2 Conversion     .   .   .   .     .   .   .   .   .   .     .   .     .   . 5-1 5.0.3 Enrichment     .   .   .   .     .   .   .   .   .   .     .   .     .   . 5-1 5.0.4 Fuel Fabrication    .   .   .     .   .   .   .   .   .     .   .     .   . 5-1 5.0.5 Nuclear Power Production       .     .   .   .   .   .   .     .   .     .   . 5-2 5.0.6 Fuel Reprocessing .       .   .     .   .   .   .   .   .     .   .     .   . 5-2 5.0.7 40CFR190 Total Dose Determination       .   .   .   .   .     .   .     .   . 5-2 6.0 Environmental Locations         .   .     .   .   .   .   .   .     .   .     .   . 6-1 6.0.1 Site Description and Sample Locations .       .   .   .   .     .   .     .   . 6-1 6.0.2 Land Use Census Data .         .     .   .   .   .   .   .     .   .     .   . 6-1 6.0.3 Oconee Meteorology: Relative Air Concentrations and Deposition     .   .     .   . 6-8 6.0.3.1 XOQDOQ Methodology and Assumptions .             .   .     .   .     .   . 6-8 6.0.3.2 Meteorological Data .       .   .   .   .   .   .     .   .     .   . 6-9 6.0.3.3 Annual XOQDOQ Comparison to the ODCM             .   .     .   .     .   . 6-10 7.0 Licensee Initiated Changes       .   .     .   .   .   .   .   .     .   .     .   . 7-1 i
. . . . . . . . . . .   . Executive Summary-1   1.0 Radwaste Systems  
. . . . . . . . . . . . . 1-1 1.0.1   Li q uid Radwaste Processing
  . . . . . . . . . . . 1-1 1.0.2 Gaseous Radwaste Processing
. . . . . . . . . . . 1-3   2.0 Release Rate Calculations
. . . . . . . . . . . . 2-1 2.0.1 Li q uid Release Rate Limit Calculations
. . . . . . . . . 2-1   2.0.1.1 Li q uid Radwaste Effluent Line Release Rate Limit Calculation
  . . . 2-1   2.0.1.2 #3 Chemical Treatment Pond Effluent Line Discharge . . . .     . 2-2 2.0.2 Gaseous Release Rate Limit Calculations
. . . . . . . . . 2-5   2.0.2.1 Unit Vent Discharge Release Rate Limit Calculation
. . . . . 2-5   3.0 Setpoint Calculations  
. . . . . . . . . . . . . 3-1 3.0.1 Li q uid Radiation Monitor Setpoint Calculations
. . . . . . . 3-1   3.0.2   Gaseous Radiation Monitor Setpoint Calculations
. . . . . . . 3-5   3.0.2.1 Unit Vents Setpoints (RIA-4 5 and RIA-4 6) . . . . . . . 3-7   3.0.2.2 Radwaste Facility Setpoints (4RIA-4 5) . . . . . . . .       3-8   3.0.2.3 Interim Radwaste Building Setpoints (RIA-5 3) . . . . . . 3-9   3.0.2.4 Waste Gas Decay Tan k Setpoints (RIA-37 and RIA-3 8) . . . . . 3-9 4.0 Effluent Dose Models  
. . . . . . . . . . . . . 4-1 4.0.1 Li q uid Effluent Dose Model for the Maximum Exposed Individual
. . . . 4-1 4.0.2 Gaseous Effluent Dose Model for the Maximum Exposed Individual
. . . . 4-7 4.0.3 Direct Radiation . . . . . . . . . . . . . 4-1 8  4.0.4 Effluent Apportionment
. . . . . . . . . . . . 4-1 8  5.0 Fuel Cycle Calculations  
. . . . . . . . . . . . . 5-1 5.0.1 Milling . . . . . . . . . . . . . . . 5-1 5.0.2 Conversion
. . . . . . . . . . . . . . 5-1 5.0.3 Enrichment
. . . . . . . . . . . . . . 5-1 5.0.4 Fuel Fa brication . . . . . . . . . . . . . 5-1 5.0.5 Nuclear Power Production
. . . . . . . . . . . 5-2 5.0.6 Fuel Reprocessing
. . . . . . . . . . . . . 5-2         5.0.7 40CFR1 9 0 Total Dose Determination
. . . . . . . . . 5-2 6.0 Environmental Locations  
. . . . . . . . . . . . 6-1 6.0.1 Site Description and Sample Locations . . . . . . . . . 6-1 6.0.2 Land Use Census Data . . . . . . . . . . . . 6-1 6.0.3 Oconee Meteorology:
Relative Air Concentrations and Deposition
. . . . 6-8   6.0.3.1 X O Q DO Q Methodology and Assumptions
. . . . . . . 6-8   6.0.3.2 Meteorological Data . . . . . . . . . . . 6-9   6.0.3.3 Annual X O Q DO Q Comparison to the ODCM . . . . . . 6-10 7.0 Licensee Initiated Changes  
. . . . . . . . . . . . 7-1


Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47  ii Appendices
Oconee Nuclear Station                                                                 January, 2007 Offsite Dose Calculation Manual (ODCM)                                                   Revision 47 Appendices Appendix A: Dose Factors for Exposure to a Semi-Infinite Cloud of Noble Gases      . .    . A-1 Appendix B: Pi Dose Factors for use in the Gaseous Release Rate Limit Calculations . .    . B-1 Appendix C: Ai Adult Dose Factors for use in the Liquid Dose Calculations    .    . .    . C-1 Appendix D: Ai Teen Dose Factors for use in the Liquid Dose Calculations      .    . .    . D-1 Appendix E: Ai Child Dose Factors for use in the Liquid Dose Calculations    .    . .    . E-1 Appendix F: Ai Infant Dose Factors for use in the Liquid Dose Calculations    .    . .    . F-1 Appendix G: Ri Adult Dose Factors for use in the Gaseous Dose Calculations .      . .    . G-1 Appendix H: Ri Teen Dose Factors for use in the Gaseous Dose Calculations    .    . .    . H-1 Appendix I: Ri Child Dose Factors for use in the Gaseous Dose Calculations    .    . .    . I-1 Appendix J: Ri Infant Dose Factors for use in the Gaseous Dose Calculations .      . .    . J-1 LIST OF FIGURES 1.0-1  Liquid Radwaste System .    .    .    .    .  .    .    .    .  .    . .    . 1-2 1.0-2  Gaseous Radwaste System (4 pages)        .    .  .    .    .    .  .    . .    . 1-4 2.0-1  Liquid Radwaste Discharge Locations      .    .  .    .    .    .  .    . .    . 2-4 6.0-1  Sampling Locations Map (Site Boundary) .      .  .    .    .    .  .    . .    . 6-5 6.0-2  Sampling Locations Map (Ten Mile Radius)      .  .    .    .    .  .    . .    . 6-6 6.0-3 Land Use Census Map .        .    .    .    .  .    .    .    .  .    . .    . 6-7 LIST OF TABLES 3.0-1 RIA-33 Cs-137 Equivalents. .        .    .    .  .    .    .    .  .    . .    . 3-4 3.0-2 Xe-133 Equivalents .    .    .    .    .    .  .    .    .    .  .    . .    . 3-11 6.0-1 Sampling Locations .    .    .    .    .    .  .    .    .    .  .    . .    . 6-2 6.0-2 TLD Sites      .    .    .    .    .    .    .  .    .    .    .  .    . .    . 6-3 6.0-3 Land Use Census Results .    .    .    .    .  .    .    .    .  .    . .    . 6-4 6.0-4 Terrain Heights Above ONS Yard Grade Elevation (m) .          .    .  .    . .    . 6-9 6.0-5 ONS Atmospheric Stability Frequency (1988 - 1992)        .    .    .  .    . .    . 6-10 6.0-6 ONS Frequency of Wind Direction and Speed (1988 - 1992) .          .  .    . .    . 6-10 6.0-7 ONS Limiting /Q and D/Q Values (1988-1992)        .    .    .    .  .    . .    . 6-11 6.0-8 ONS Delta-T Ranges per Vertical Separation Distances .        .    .  .    . .    . 6-11 6.0-9 Oconee Semi-Elevated /Q and D/Q Average Values (1988-1992)        .  .    . .    . 6-12 6.0-10 Oconee Ground Level /Q and D/Q Average Values (1988-1992)        .  .    . .    . 6-14 ii


Appendix A:  Dose Factors for Exposure to a Semi-Infinite Cloud of No b le Gases . . . A-1 Appendix B:  P i Dose Factors for use in the Gaseous Release Rate Limit Calculations
Oconee Nuclear Station                                                      January, 2007 Offsite Dose Calculation Manual (ODCM)                                       Revision 47 EXECUTIVE
  . . . B-1 Appendix C:  A i Adult Dose Factors for use in the Li q uid Dose Calculations
  . . . . C-1 Appendix D:  A i Teen Dose Factors for use in the Li q uid Dose Calculations
  . . . . D-1 Appendix E:  A i Child Dose Factors for use in the Li q uid Dose Calculations
. . . . E-1 Appendix F:  A i Infant Dose Factors for use in the Li q uid Dose Calculations
. . . . F-1 Appendix G:  R i Adult Dose Factors for use in the Gaseous Dose Calculations
. . . . G-1 Appendix H:  R i Teen Dose Factors for use in the Gaseous Dose Calculations
. . . . H-1 Appendix I:  R i Child Dose Factors for use in the Gaseous Dose Calculations
. . . . I-1 Appendix J:  R i Infant Dose Factors for use in the Gaseous Dose Calculations
. . . . J-1  LIST OF FIGURES 1.0-1  Li q uid Radwaste System . . . . . . . . . . . . . 1-2 1.0-2  Gaseous Radwaste System (4 pages)  . . . . . . . . . . 1-4 2.0-1  Li q uid Radwaste Discharge Locations . . . . . . . . . . 2-4 6.0-1  Sampling Locations Map (Site Boundary) . . . . . . . . . . 6-5 6.0-2  Sampling Locations Map (Ten Mile Radius) . . . . . . . . . 6-6 6.0-3  Land Use Census Map . . . . . . . . . . . . . 6-7  LIST OF TABLES


3.0-1  RIA-33 Cs-137 E quivalents.
==SUMMARY==
. . . . . . . . . . . . 3-4 3.0-2  X e-133 E quivalents . . . . . . . . . . . . . . 3-11 6.0-1  Sampling Locations . . . . . . . . . . . . . . 6-2 6.0-2  TLD Sites . . . . . . . . . . . . . . . 6-3 6.0-3  Land Use Census Results . . . . . . . . . . . . . 6-4 6.0-4  Terrain Heights A bove ONS Yard Grade Elevation (m) .  . . . . . . 6-9 6.0-5  ONS Atmospheric Sta b ility Fre quency (1988 - 1 99 2) . . . . . . . 6-10 6.0-6  ONS Fre quency of W ind Direction and Speed (1988 - 1 99 2) . . . . . . 6-10 6.0-7  ONS Limiting /Q and D/Q Values (1 988-1 99 2) . . . . . . . . 6-11 6.0-8  ONS Delta-T Ranges per Vertical Separation Distances . . . . . . . 6-11 6.0-9  Oconee Semi-Elevated /Q and D/Q Average Values (1 988-1 99 2) . . . . . 6-12 6.0-10 Oconee Ground Level /Q and D/Q Average Values (1 988-1 99 2) . . . . . 6-14 Oconee Nuclear Station    January, 2007 Offsite Dose Calculation Manual (ODCM)    Revision 47  Executive Summary - Page 1  E XECUTIVE


==SUMMARY==
The Oconee Nuclear Station (ONS) Offsite Dose Calculation Manual (ODCM) provides the methodology and parameters to be used in the calculation of offsite doses due to normal operation radioactive liquid and gaseous effluents to assure compliance with the dose limitations of the Selected Licensee Commitments (SLCs, UFSAR Chapter 16) and Technical Specifications. These dose limitations assure that:
(1) the concentration of radioactive liquid effluents released from the site to the unrestricted area will be limited to 10 times the effluent concentration (EC) levels of 10CFR20, Appendix B, Table 2, and 2.0E-04 Ci/ml for dissolved and entrained noble gases; (2) the exposures to any individual member of the public from radioactive liquid effluents will not result in doses greater than the ALARA design objectives of 10CFR50, Appendix I or the 10CFR20 limits; (3) the dose rate at any time at the site boundary from radioactive gaseous effluents will be limited to: for noble gases; less than or equal to 500 mrem/yr to the whole body, and less than or equal to 3000 mrem/yr to the skin; and for iodine-131 and iodine-133, for tritium, and for all radioactive materials in particulate form with half-lives greater than 8 days; less than or equal to 1500 mrem/yr to any organ; (4) the exposure to any individual member of the public from radioactive gaseous effluents will not result in doses greater than the ALARA design objectives of 10CFR50, Appendix I or the 10CFR20 limits; and (5) the dose to any individual member of the public from the nuclear fuel cycle will not exceed the limits of 40CFR190.
The methodology and parameters used to assure compliance with the dose limitations described above shall be used to prepare the radioactive liquid and gaseous effluent reports required by the SLCs and Technical Specifications. Dose calculations      that    demonstrate compliance with 40CFR190 will be considered          to      demonstrate compliance with the 10CFR20 0.1-rem annual dose limit. The ODCM          also provides        the Executive Summary - Page 1


The Oconee Nuclear Station (ONS) Offsite Dose Calculation Manual (ODCM) provides the methodology and parameters to b e used in the calculation of offsite doses due to normal operation radioactive li q uid and gaseous effluents to assure compliance with the dose limitations of the Selected Licensee Commitments (SLCs, UFSAR Chapter 1 6) and Technical Specifications.
Oconee Nuclear Station                                                   January, 2007 Offsite Dose Calculation Manual (ODCM)                                   Revision 47 methodology and parameters to be used in the calculation of radioactive liquid and gaseous effluent monitoring instrumentation alarm /trip setpoints to assure compliance with the concentration and dose rate limitations of the SLCs and Technical Specifications. Normally RETDAS, a computer code that implements NUREG-0133 methodology, is used for the calculation of offsite doses, but the ODCM also provides a method for the calculation of offsite doses when RETDAS is not available.
These dose limitations assure that: 
The ODCM has been prepared as generically as possible in order to minimize the need for revisions. However, some changes to the ODCM such as land-use census data are expected on an annual basis. Any changes to the methodology and parameters to be used in this ODCM shall be reviewed by knowledgeable individual(s), and approved by the Station Manager and the General Office Radiation Protection Manager prior to implementation. Changes to the ODCM shall be submitted to the Nuclear Regulatory Commission in accordance with the SLCs and Technical Specifications.
(1) the concentration of radioactive li q uid effluents released from the site to the unrestricted area will b e limited to 10 times the effluent concentration (EC) levels of 10CFR20, Appendix B, Ta b le 2, and 2.0E-04 µCi/ml for dissolved and entrained no b le gases; (2) the exposures to any individual mem b er of the pu b lic from radioactive li quid effluents will not result in doses greater than the ALARA design o bjectives of 10CFR 5 0, Appendix I or the 10CFR20 limits; (3) the dose rate at any time at the site boundary from radioactive gaseous effluents will b e limited to: for no b le gases; less than or e q ual to 5 00 mrem/yr to the whole body, and less than or e qual to 3000 mrem/yr to the s k in;  and for iodine-131 and iodine-133, for tritium, and for all radioactive materials in particulate form with half-lives greater than 8 days; less than or e q ual to 1 5 00 mrem/yr to any organ; (4) the exposure to any individual mem b er of the pu b lic from radioactive gaseous effluents will not result in doses greater than the ALARA design o bjectives of 10CFR 5 0, Appendix I or the 10CFR20 limits; and (5) the dose to any individual mem b er of the pu b lic from the nuclear fuel cycle will not exceed the limits of 40CFR1 9 0. The methodology and parameters used to assure compliance with the dose limitations descri b ed a b ove shall b e used to prepare the radioactive li q uid and gaseous effluent reports re q uired b y the SLCs and Technical Specifications.
The ODCM does not replace any station implementing procedures. Programmatic controls for radioactive effluents and radiological environmental monitoring are contained in the Administrative Controls chapter of the Technical Specifications.
Dose calculations that demonstrate compliance with 40CFR1 9 0 will b e considered to demonstrate compliance with the 10CFR20    0.1-rem annual dose limit. The ODCM        also    provides        the Oconee Nuclear Station    January, 2007 Offsite Dose Calculation Manual (ODCM)     Revision 47   Executive Summary - Page 2 methodology and parameters to b e used in the calculation of radioactive li q uid and gaseous effluent monitoring instrumentation alarm /trip setpoints to assure compliance with the concentration and dose rate limitations of the SLCs and Technical Specifications.
Procedural details for radioactive effluents and radiological environmental monitoring consisting of licensee commitments, applicability, remedial actions, surveillance requirements, and the bases for these requirements are contained in Section 16.11 of the SLCs.
Normally RETDAS, a computer code that implements NUREG-0133 methodology, is used for the calculation of offsite doses, b ut the ODCM also provides a method for the calculation of offsite doses when RETDAS is not availa ble.
Executive Summary - Page 2
The ODCM has b een prepared as generically as possi b le in order to minimi z e the need for revisions.
However, some changes to the ODCM such as land-use census data are expected on an annual basis. Any changes to the methodology and parameters to b e used in this ODCM shall b e reviewed b y knowledgea b le individual(s), and approved b y the Station Manager and the General Office Radiation Protection Manager prior to implementation.
Changes to the ODCM shall b e su bmitted to the Nuclear Regulatory Commission in accordance with the SLCs and Technical Specifications.


The ODCM does not replace any station implementing procedures.
Oconee Nuclear Station                                                           January, 2007 Offsite Dose Calculation Manual (ODCM)                                           Revision 47 1.0 RADWASTE SYSTEMS 1.0.1 LIQUID RADWASTE PROCESSING The liquid radwaste system at Oconee Nuclear Station is used to collect and treat liquid chemical and radiochemical byproducts of unit operation. The system produces effluents that are discharged in small, dilute quantities to the environment. The means of treatment vary with waste type and desired product in the various systems:
Programmatic controls for radioactive effluents and radiological environmental monitoring are contained in the Administrative Controls chapter of the Technical Specifications.
Procedural details for radioactive effluents and radiological environmental monitoring consisting of licensee commitments, applica bility, remedial actions, surveillance re q uirements, and the bases for these re quirements are contained in Section 1 6.11 of the SLCs.
Oconee Nuclear Station     January, 2007 Offsite Dose Calculation Manual (ODCM)     Revision 47   Section 1 - Page 1  1.0 RAD WASTE SYSTEMS 1.0.1   LI QUID RAD WASTE PROCESSING The li q uid radwaste system at Oconee Nuclear Station is used to collect and treat li q uid chemical and radiochemical byproducts of unit operation.
The system produces effluents that are discharged in small, dilute quantities to the environment.
The means of treatment vary with waste type and desired product in the various systems:
(A) Filtration - Waste sources are filtered prior to processing as necessary.
(A) Filtration - Waste sources are filtered prior to processing as necessary.
(B) Ion Exchange - Ion exchange is used to remove radioactive ions from solution. Also, ion exchange is normally used in removing cations (cobalt, cesium, manganese) and anions (chloride, fluoride) from the filtrate in order to purify the filtrate for release.
(C) Gas Stripping - Removal of gaseous radioactive fission products is accomplished through venting of atmospheric holdup tanks.
Figure 1.0-1 is a schematic representation of the liquid radwaste system at Oconee.
Section 1 - Page 1
Oconee Nuclear Station                                    January, 2007 Offsite Dose Calculation Manual (ODCM)                    Revision 47 Figure 1.0-1 Oconee Nuclear Station Liquid Radwaste System Section 1 - Page 2
Oconee Nuclear Station                                                      January, 2007 Offsite Dose Calculation Manual (ODCM)                                      Revision 47 1.0.2 GASEOUS RADWASTE PROCESSING The purpose of the gaseous waste disposal system is to:
(1) Maintain a non-oxidizing cover gas of nitrogen in tanks and equipment that contain potentially radioactive gas; (2) Hold up radioactive gas for decay; and (3) Release gases (radioactive and non-radioactive) to the atmosphere under controlled conditions.
During power operation of the facilities, radioactive materials released to the atmosphere in gaseous effluents include low concentrations of fission product noble gases (krypton and xenon), halogens (mostly iodines), tritium contained in water vapor, and particulate material including both fission products and activated corrosion products.
The primary source of gaseous radioactive wastes is from the degassing of the primary coolant during letdown of the cooling water into various holding tanks. Additional sources of gaseous waste activity include the auxiliary building exhaust, spent fuel area exhaust, the discharge from the steam jet air ejectors, and purging and venting of the reactor containment building.
All components that can contain potentially radioactive gases are vented to a vent header.
The vent gases are subsequently drawn from this header by one of four waste gas compressors or a waste gas exhauster. The waste gas compressor discharges through a waste gas separator to one of seven waste gas tanks. The waste gas tanks and the waste gas exhauster discharge to the unit vent after passing through a filter bank consisting of a prefilter, an absolute filter, and a charcoal filter.
Radioactive gases may be released inside the reactor containment building when components of the primary system are opened to the building atmosphere for operational reasons or where minor leaks occur in the primary system. Prior to access, the reactor containment atmosphere will be monitored for radioactivity and, when necessary, purged through prefilters, high-efficiency particulate air (HEPA) filters, and charcoal filters, and released to the atmosphere through the unit vent. The purge equipment is sized for a flow rate of 50,000 cfm providing approximately 1.5 air changes per hour in the reactor building. Units 1, 2, and 3 have a separate vent stack which services each unit.
Figure 1.0-2 is a schematic representation of the gaseous radwaste system at Oconee.
Section 1 - Page 3
Oconee Nuclear Station                                      January, 2007 Offsite Dose Calculation Manual (ODCM)                      Revision 47 Figure 1.0-2 Oconee Nuclear Station Gaseous Radwaste System Page 1 of 4 Section 1 - Page 4
Oconee Nuclear Station                                      January, 2007 Offsite Dose Calculation Manual (ODCM)                      Revision 47 Figure 1.0-2 Oconee Nuclear Station Gaseous Radwaste System Page 2 of 4 Section 1 - Page 5
Oconee Nuclear Station                                      January, 2007 Offsite Dose Calculation Manual (ODCM)                      Revision 47 Figure 1.0-2 Oconee Nuclear Station Gaseous Radwaste System Page 3 of 4 Section 1 - Page 6


(B) Ion Exchange - Ion exchange is used to remove radioactive ions from solution. Also, ion exchange is normally used in removing cations (co balt, cesium, manganese) and anions (chloride, fluoride) from the filtrate in order to purify the filtrate for release. 
Oconee Nuclear Station                                     January, 2007 Offsite Dose Calculation Manual (ODCM)                     Revision 47 Figure 1.0-2 Oconee Nuclear Station Gaseous Radwaste System Page 4 of 4 Section 1 - Page 7
(C) Gas Stripping - Removal of gaseous radioactive fission products is accomplished through venting of atmospheric holdup tan k s.
Figure 1.0-1 is a schematic representation of the li q uid radwaste system at Oconee.
Oconee Nuclear Station     January, 2007 Offsite Dose Calculation Manual (ODCM)     Revision 47   Section 1 - Page 2  Figure 1.0
-1 Oconee Nuclear Station Li quid Radwaste System


Oconee Nuclear Station     January, 2007 Offsite Dose Calculation Manual (ODCM)     Revision 47   Section 1 - Page 3 1.0.2    GASEOUS RAD WASTE PROCESSING The purpose of the gaseous waste disposal system is to: 
Oconee Nuclear Station                                                       January, 2007 Offsite Dose Calculation Manual (ODCM)                                       Revision 47 2.0 RELEASE RATE CALCULATIONS 2.0.1 LIQUID RELEASE RATE LIMIT CALCULATIONS There are two liquid radwaste discharge points to the environment at Oconee; (1) the liquid radwaste effluent line to the Keowee Hydroelectric Unit Tailrace, and (2) the #3 Chemical Treatment Pond effluent line to the Keowee River (See Figure 2.0-1).
(1) Maintain a non-oxidi zing cover gas of nitrogen in tan k s and e q uipment that contain potentially radioactive gas; (2) Hold up radioactive gas for decay; and (3) Release gases (radioactive and non-radioactive) to the atmosphere under controlled conditions.
2.0.1.1 LIQUID RADWASTE EFFLUENT LINE RELEASE RATE LIMIT CALCULATION Liquid releases to the Keowee Hydroelectric Unit Tailrace normally contain the radioactive releases from the site including effluents from the Waste Monitor Tanks, Recycle Monitor Tanks, and Decant Monitor Tank. The Keowee Tailrace discharge point can also contain Turbine Building Sump Monitor Tank (TBSMT) releases, however TBSMT effluent normally contains very low (if any) activity, and, therefore is transferred to the #3 Chemical Treatment Pond prior to release. Dilution flow for the liquid radwaste effluent line is provided by the Keowee Hydroelectric Unit and the Keowee Hydro Fire Protection liquid waste release mixing line. For purposes of the release rate calculation, Keowee hydro dilution flow is assumed to be a minimum leakage flow of 38 cfs, and a maximum flow of 6600 cfs based on one hydro unit operating at 50% power. The Keowee Hydro Fire Protection liquid waste release mixing line provides an additional 38 cfs dilution flow. Since Keowee Hydro typically releases only a small percentage of time during the year, 76 cfs (38 cfs leakage + 38 cfs mixing line) is normally assumed for dilution flow when performing liquid release rate calculations.
To comply with Technical Specifications and Selected Licensee Commitments, and to assure that the concentration of radioactive liquid effluents released from the site to the unrestricted area is limited to 10 times the effluent concentrations (ECs) of 10CFR20, Appendix B, Table 2, Column 2, and 2.0E-04 PCi/ml for dissolved and entrained noble gases, the following release rate limit calculation shall be performed for liquid releases to the Keowee Hydro Tailrace via the liquid radwaste effluent line:
f d F y (DF  1 )      Condition: DF ! 1.0              Equation 2.1 where:
f    = the undiluted effluent flow, in gpm.
F    = the dilution flow available, in gpm.
      = normally 3.41E+04 gpm (76 cfs, based on a leakage rate of 38 cfs (19 cfs per Keowee Hydro unit), plus the Keowee Hydro Fire Protection liquid waste release Section 2 - Page 1


During power operation of the facilities, radioactive materials released to the atmosphere in gaseous effluents include low concentrations of fission product no b le gases (krypton and xenon), halogens (mostly iodines), tritium contained in water vapor, and particulate material including b oth fission products and activated corrosion products.
Oconee Nuclear Station                                                          January, 2007 Offsite Dose Calculation Manual (ODCM)                                          Revision 47 mixing line whose flow rate is 38 cfs. When Keowee Hydro enters an outage one of the two units is taken offline which temporarily reduces the amount of leakage by half. Therefore, during a Keowee Hydro outage the dilution flow is assumed to be 57 cfs (19 cfs leakage plus 38 cfs raw water, (2.56E+04 gpm)).
The primary source of gaseous radioactive wastes is from the degassing of the primary coolant during letdown of the cooling water into various holding tan k s. Additional sources of gaseous waste activity include the auxiliary b uilding exhaust, spent fuel area exhaust, the discharge from the steam j et air e j ectors, and purging and venting of the reactor containment building.
      = or 2.96E+06 gpm (6600 cfs, based on one hydro unit operating at 50% power).
All components that can contain potentially radioactive gases are vented to a vent header. The vent gases are su b se quently drawn from this header b y one of four waste gas compressors or a waste gas exhauster.
This value is only used if it is known that Keowee Hydro is discharging.
The waste gas compressor discharges through a waste gas separator to one of seven waste gas tan k s. The waste gas tan k s and the waste gas exhauster discharge to the unit vent after passing through a filter b an k consisting of a prefilter, an a b solute filter, and a charcoal filter.
DF = required dilution factor to be applied to the undiluted effluent flow, unitless.
Radioactive gases may b e released inside the reactor containment b uilding when components of the primary system are opened to the b uilding atmosphere for operational reasons or where minor lea k s occur in the primary system. Prior to access, the reactor containment atmosphere will b e monitored for radioactivity and, when necessary, purged through prefilters, high-efficiency particulate air (HEPA) filters, and charcoal filters, and released to the atmosphere through the unit vent. The purge e q uipment is si z ed for a flow rate of 5 0,000 cfm providing approximately 1.5 air changes per hour in the reactor building. Units 1, 2, and 3 have a separate vent stac k which services each unit.
Ci DF    V u    i  10 u ECi Equation 2.2 Note:
Figure 1.0-2 is a schematic representation of the gaseous radwaste system at Oconee.
If DF d 1.0 then no dilution is required and the release rate is unrestricted.
Oconee Nuclear Station    January, 2007 Offsite Dose Calculation Manual (ODCM)    Revision 47  Section 1 - Page 4  Figure 1.0
If DF ! 1.0 then dilution flow is required and the release rate is calculated using Equation 2.1. Equation 2.1 is used only when DF ! 1.0.
-2 Oconee Nuclear Station Gaseous Radwaste System  Page 1 of 4
V    = the most restrictive recirculation factor at equilibrium, (dimensionless). The recirculation factor accounts for the fraction of discharged water reused by the station. This value equals 1.0 since discharged liquid effluent is not reused at Oconee.
Ci    = the concentration of radionuclide, i, in the undiluted liquid effluent, in PCi/ml.
ECi = the concentration of radionuclide, i, from 10CFR20, Appendix B, Table 2, Column 2, in PCi/ml. Note: if radionuclide, i, is a dissolved noble gas, then ECi
          = 2.00E-05 PCi/ml.
Once the maximum release rate, f, is calculated the value is multiplied by 0.8 for additional conservatism.
2.0.1.2 #3 CHEMICAL TREATMENT POND EFFLUENT LINE DISCHARGE The #3 Chemical Treatment Pond (CTP) effluent line is the release point for station effluents that are normally considered to be non-radioactive; that is, the pond's effluent will not normally contain measurable activity above background with the exception of very low tritium activity. Tritium releases from the #3 CTP typically account for much less than 1% of the station total tritium release. It is assumed that no activity is present in the effluent until indicated by radiation monitoring measurements on the pond's inputs and/or by periodic analyses of the composite sample collected at the pond's discharge point. Inputs to this pond include the station's yard drain system, the decant water from the Powdex system, and the discharge from the Turbine Building Sump/TBSMT system whose contents have been determined to be below background. Inputs that have radiation Section 2 - Page 2


Oconee Nuclear Station     January, 2007 Offsite Dose Calculation Manual (ODCM)     Revision 47   Section 1 - Page 5 Figure 1.0
Oconee Nuclear Station                                                       January, 2007 Offsite Dose Calculation Manual (ODCM)                                       Revision 47 monitors associated with them will be set to assure that Selected Licensee Commitment 16.11-1 will not be exceeded. #3 CTP is a continuous release path that discharges to the Keowee River (see Figure 2.0-1).
-2 Oconee Nuclear Station Gaseous Radwaste System Page 2 of 4
The #3 CTP may also be the discharge path for large volumes of slightly contaminated water following a primary-to-secondary leak so long as administrative procedures are implemented to assure that release rate calculations similar to that used in Section 2.0.1.1 are performed, that all detectable radionuclides will be accounted for, and that no station limits will be exceeded.
Section 2 - Page 3


Oconee Nuclear Station     January, 2007 Offsite Dose Calculation Manual (ODCM)     Revision 47   Section 1 - Page 6 Figure 1.0
Oconee Nuclear Station                                   January, 2007 Offsite Dose Calculation Manual (ODCM)                     Revision 47 Figure 2.0-1 Liquid Radwaste Discharge Locations Section 2 - Page 4
-2 Oconee Nuclear Station Gaseous Radwaste System Page 3 of 4  


Oconee Nuclear Station     January, 2007 Offsite Dose Calculation Manual (ODCM)     Revision 47   Section 1 - Page 7 Figure 1.0
Oconee Nuclear Station                                                       January, 2007 Offsite Dose Calculation Manual (ODCM)                                         Revision 47 2.0.2        GASEOUS RELEASE RATE LIMIT CALCULATIONS The three unit vents are the primary gaseous radioactive release points at Oconee. The unit vents are the semi-elevated release points for waste gas decay tanks, containment building purges, auxiliary building ventilation, spent fuel pool ventilation, and the condenser air ejector (see Figure 1.0-2, pages 1, 2, and 3). Each unit vent contains multi-range radiation monitors (RIAs) and flow rate measuring instrumentation.
-2 Oconee Nuclear Station Gaseous Radwaste System Page 4 of 4  
There are three other separate gaseous effluent release points at Oconee; the Hot Machine Shop, Interim Radwaste Building and Radwaste Facility that are normally considered non-radioactive; that is, it is possible but unlikely that the effluent will contain measurable activity above background. Each of these release points are considered ground-level, and each has an effluent sampler and flow monitoring device (see Figure 1.0-2, page 4). In addition, the Interim Radwaste Building and Radwaste Facility have a RIA.
2.0.2.1 UNIT VENT DISCHARGE RELEASE RATE LIMIT CALCULATION In order to comply with Technical Specifications and Selected Licensee Commitments and to assure that the dose rate, at any time, at or beyond the site boundary due to radioactive materials released in gaseous effluents from the site is limited to: d 500 mrem/yr to the total body, and d 3000 mrem/yr to the skin for the noble gases, and is limited to d 1500 mrem/yr to any organ for radioiodine and for radioactive materials in particulate form, and radionuclides other than noble gases with half lives greater than 8 days, the following release rate and radiation monitor setpoint calculations shall be performed for releases from the waste gas decay tanks and the containment building. The release rate calculations when solved for the flow rate, f, are the release rates for noble gases and for radioiodines, particulates and other radionuclides with half-lives greater than 8 days. The most conservative release rate calculated shall control the flow rate. The following equations are based on the site dose rate limits. When applied to the individual release points the site dose rate values are apportioned 1/3 to each unit vent.
: a. Noble Gases Total Body:
    §        F      *
  ¨¨ K i  u Q
u Qi ¸¸  500 mrem/yr                      Equation 2.3 i ©                ¹ Skin:
    §                  F        *
  ¨¨ L  1.1M i      i  u Q
u Qi ¸¸  3000 mrem/yr            Equation 2.4 i ©                            ¹ Section 2 - Page 5


Oconee Nuclear Station     January, 2007 Offsite Dose Calculation Manual (ODCM)                                                                           Revision 47 Section 2 - Page 1
Oconee Nuclear Station                                                           January, 2007 Offsite Dose Calculation Manual (ODCM)                                           Revision 47
: b. Radioiodines, Particulates, and Others Inhalation, Ingestion and Ground Organ Pathways:


===2.0 RELEASE===
p    i Popi u W u Qi u Ei  1500 mrem/yr To include both the food and ground organ dose and the inhalation organ dose the equation can be expanded to:
RATE CALCULATIONS2.0.1  LIQUID RELEASE RATE LIMIT CALCULATIONSThere are two liquid radwaste discharge points to the environment at Oconee; (1) the liquid radwaste effluent line to the Keowee Hydroelectric Unit Tailrace, and (2) the #3 Chemical Treatment Pond effluent line to the Keowee River (See Figure 2.0-1).
  ^P p    i opi food/gr u WD / Q  Popi inhal u WF / Q` u Qi u Ei  1500 mrem/yr Equation 2.5 where:
2.0.1.1  LIQUID RADWASTE EFFLUENT LINE RELEASE RATE LIMIT CALCULATIONLiquid releases to the Keowee Hydroelectric Unit Tailrace normally contain the radioactive releases from the site including effluents from the Waste Monitor Tanks, Recycle Monitor Tanks, and Decant Monitor Tank. The Keowee Tailrace discharge point can also contain Turbine Building Sump Monitor Tank (TBSMT) releases, however TBSMT effluent normally contains very low (if any) activity, and, therefore is transferred to the #3 Chemical Treatment Pond prior to release. Dilution flow for the liquid radwaste effluent line is provided by the Keowee Hydroelectric Unit and the Keowee Hydro Fire Protection liquid waste release mixing line. For purposes of the release rate calculation, Keowee hydro dilution flow is assumed to be a minimum leakage flow of 38 cfs, and a maximum flow of 6600 cfs based on one hydro unit operating at 50% power. The Keowee Hydro Fire Protection liquid waste release mixing line provides an additional 38 cfs dilution flow. Since Keowee Hydro typically releases only a small percentage of time during the year, 76 cfs (38 cfs leakage + 38 cfs mixing line) is normally assumed for dilution flow when performing liquid release rate calculations. To comply with Technical Specifications and Selected Licensee Commitments, and to assure that the concentration of radioactive liquid effluents released from the site to the unrestricted area is limited to 10 times the effluent concentrations (ECs) of 10CFR20, Appendix B, Table 2, Column 2, and 2.0E-04 Ci/ml for dissolved and entrained noble gases, the following release rate limit calculation shall be performed for liquid releases to the Keowee Hydro Tailrace via the liquid radwaste effluent line:
Ki      = the total body dose factor due to gamma emissions for each identified noble gas radionuclide, i, in mrem/yr per PCi/m3 (See Appendix A).
)(DF F f 1    Condition:  DF  1.0Equation 2.1 where: f      =    the undiluted effluent flow, in gpm.
Li      = the skin dose factor due to beta emissions for each identified noble gas radionuclide, i, in mrem/yr per PCi/m3 (See Appendix A).
F      =    the dilution flow available, in gpm. =    normally 3.41E+04 gpm (76 cfs, based on a leakage rate of 38 cfs (19 cfs per Keowee Hydro unit), plus the Keowee Hydro Fire Protection liquid waste release Oconee Nuclear Station    January, 2007 Offsite Dose Calculation Manual (ODCM)                                                                           Revision 47 Section 2 - Page 2 mixing line whose flow rate is 38 cfs. When Keowee Hydro enters an outage one of the two units is taken offline which temporarily reduces the amount of leakage by half. Therefore, during a Keowee Hydro outage the dilution flow is assumed to be 57 cfs (19 cfs leakage plus 38 cfs raw water, (2.56E+04 gpm)).        =    or 2.96E+06 gpm (6600 cfs, based on one hydro unit operating at 50% power). This value is only used if it is known that Keowee Hydro is discharging.
Mi      = the air dose factor due to gamma emissions for each identified noble gas radionuclide, i, in mrad/yr per PCi/m3 (See Appendix A).
DF  =   required dilution factor to be applied to the undiluted effluent flow, unitless. i i i EC C DF 10      Equation 2.2 Note: If DF  1.0  then no dilution is required and the release rate is unrestricted.
Popi = the dose parameter for radionuclides other than noble gases for the inhalation pathway, in mrem/yr per PCi/m3 and for the food and ground plane pathways in (m2 u (mrem/yr per PCi/sec)) for organ, o, and radionuclide, i, (See Appendix B for the pathway specific dose commitment factors). Note: NUREG-1301, page 75, specifies use of the Child age group, Inhalation pathway, for the Popi values.
If DF  1.0  then dilution flow is required and the release rate is calculated using Equation 2.1. Equation 2.1 is used only when DF  1.0.      =  the most restrictive recirculation factor at equilibrium, (dimensionless). The recirculation factor accounts for the fraction of discharged water reused by the station. This value equals 1.0 since discharged liquid effluent is not reused at Oconee.
F/Q = the highest calculated annual average dispersion parameter for any area at or beyond the site boundary in sec/m3. For the Oconee Unit Vents this value is 1.672E-6 sec/m3. The location is the SW sector at 1.0 mile for semi-elevated releases. For the Hot Machine Shop, Interim Radwaste Building and Radwaste Facility this value is 7.308E-6 sec/m3. The location is the SE sector at 1.0 mile for ground-level releases. As discussed in Oconee UFSAR Section 2.1.1.3, the boundary for establishing gaseous effluent release limits is the exclusion area boundary (EAB). The EAB is defined as a 1 mile radius from the station center.
C i    =  the concentration of radionuclide, 'i', in the undiluted liquid effluent, in Ci/ml. EC i  =  the concentration of radionuclide, 'i', from 10CFR20, Appendix B, Table 2, Column 2, in Ci/ml. Note:  if radionuclide, 'i', is a dissolved noble gas, then EC i= 2.00E-05 Ci/ml. Once the maximum release rate, f, is calculated the value is multiplied by 0.8 for additional conservatism.
W    =    the highest calculated annual average dispersion or deposition parameter for estimating the maximum dose rate to an individual from the total inhalation, food, and ground plane pathways resulting from semi-elevated releases or ground-level releases:
2.0.1.2  #3 CHEMICAL TREATMENT POND EFFLUENT LINE DISCHARGEThe #3 Chemical Treatment Pond (CTP) effluent line is the release point for station effluents that are normally considered to be non-radioactive; that is, the pond's effluent will not normally contain measurable activity above background with the exception of very low tritium activity. Tritium releases from the #3 CTP typically account for much less than 1% of the station total tritium release. It is assumed that no activity is present in the effluent until indicated by radiation monitoring measurements on the pond's inputs and/or by periodic analyses of the composite sample collected at the pond's discharge point. Inputs to this pond include the station's yard drain system, the decant water from the Powdex system, and the discharge from the Turbine Building Sump/TBSMT system whose contents have been determined to be below background. Inputs that have radiation Oconee Nuclear Station    January, 2007 Offsite Dose Calculation Manual (ODCM)                                                                            Revision 47 Section 2 - Page 3 monitors associated with them will be set to assure that Selected Licensee Commitment 16.11-1 will not be exceeded.  #3 CTP is a continuous release path that discharges to the
Section 2 - Page 6


Keowee River (see Figure 2.0-1).The #3 CTP may also be the discharge path for large volumes of slightly contaminated water following a primary-to-secondary leak so long as administrative procedures are implemented to assure that release rate calculations similar to that used in Section 2.0.1.1 are performed, that all detectable radionuclides will be accounted for, and that no station limits will be exceeded.
Oconee Nuclear Station                                                           January, 2007 Offsite Dose Calculation Manual (ODCM)                                           Revision 47 WF/Qse = 1.672E-6 sec/m3, for the inhalation pathway and the airborne H-3 food pathway. The location is the SW sector at 1.0 mile for semi-elevated releases.
Oconee Nuclear Station     January, 2007 Offsite Dose Calculation Manual (ODCM)                                                                           Revision 47 Section 2 - Page 4 Figure 2.0-1 Liquid Radwaste Discharge Locations Oconee Nuclear Station    January, 2007 Offsite Dose Calculation Manual (ODCM)                                                                            Revision 47 Section 2 - Page 5 2.0.2   GASEOUS RELEASE RATE LIMIT CALCULATIONSThe three unit vents are the primary gaseous radioactive release points at Oconee. The unit vents are the semi-elevated release points for waste gas decay tanks, containment building purges, auxiliary building ventilation, spent fuel pool ventilation, and the condenser air ejector (see Figure 1.0-2, pages 1, 2, and 3). Each unit vent contains multi-range radiation monitors (RIAs) and flow rate measuring instrumentation. There are three other separate gaseous effluent release points at Oconee; the Hot Machine Shop, Interim Radwaste Building and Radwaste Facility that are normally considered non-radioactive; that is, it is possible but unlikely that the effluent will contain measurable activity above background. Each of these release points are considered ground-level, and each has an effluent sampler and flow monitoring device (see Figure 1.0-2, page 4). In
WD/Qse = 1.295E-8 m-2, for the food and ground plane pathways. The location is the NE sector at 1.0 mile for semi-elevated releases.
WF/Qgl = 7.308E-6 sec/m3, for the inhalation pathway and the airborne H-3 food pathway. The location is the SE sector at 1.0 mile for ground-level releases.
WD/Qgl = 2.259E-8 m-2, for the food and ground plane pathways. The location is the NE sector at 1.0 mile for ground-level releases.
Ei    = the filter removal factor for radionuclide, i, e.g., for 99% removal Ei = 0.01.
For iodine removal by charcoal adsorbers Ei = 0.1.
For particulate removal by HEPA filters Ei = 0.01.
Qi    = the release rate of radionuclide, i, in gaseous effluent from all release points at the site, in PCi/sec.
Qi      k 1Cif y k 2    4.72E  02 u Cif                      Equation 2.6 where:
Ci = the concentration of radionuclide, i, in undiluted gaseous effluent, in PCi/ml.
f    = the undiluted effluent flow, in ft3/min.
k1 = conversion factor, 2.83E+04 cc/ft3.
k2 = conversion factor, 6.0E+01 sec/min.
Substituting the expression for Qi in Equation 2.6 into Equations 2.3, 2.4, and 2.5, and solving for the flow rate, f, in each equation gives:
Noble Gases - Total Body Maximum Release Rate:
500 ftb 
4.72E  02 u FQ u        i Ki u Ci Section 2 - Page 7


addition, the Interim Radwaste Building and Radwaste Facility have a RIA.2.0.2.1  UNIT VENT DISCHARGE RELEASE RATE LIMIT CALCULATIONIn order to comply with Technical Specifications and Selected Licensee Commitments and to assure that the dose rate, at any time, at or beyond the site boundary due to radioactive materials released in gaseous effluents from the site is limited to:  500 mrem/yr to the total body, and  3000 mrem/yr to the skin for the noble gases, and is limited to  1500 mrem/yr to any organ for radioiodine and for radioactive materials in particulate form, and radionuclides other than noble gases with half lives greater than 8 days, the following release rate and radiation monitor setpoint calculations shall be performed for releases from the waste gas decay tanks and the containment building. The release rate calculations when solved for the flow rate, 'f', are the release rates for noble gases and for radioiodines, particulates and other radionuclides with half-lives greater than 8 days. The most conservative release rate calculated shall control the flow rate. The following equations are based on the site dose rate limits. When applied to the individual release points the site dose rate values are apportioned 1/3 to each unit vent.
Oconee Nuclear Station                                                               January, 2007 Offsite Dose Calculation Manual (ODCM)                                               Revision 47 Noble Gases - Skin Maximum Release Rate:
: a. Noble Gases Total Body:  i i i Q Q K mrem/yr 500 Equation 2.3 Skin:mrem/yr 3000 1.1i i i i Q Q M L Equation 2.4 Oconee Nuclear Station     January, 2007 Offsite Dose Calculation Manual (ODCM)                                                                           Revision 47 Section 2 - Page 6 b. Radioiodines, Particulates, and OthersInhalation, Ingestion and Ground Organ Pathways: i i i opi p E Q W P mrem/yr 1500To include both the food and ground organ dose and the inhalation organ dose the equation can be expanded to:  i i i Q opi Q D opi p E Q W P W P mrem/yr 1500/inhal/food/gr Equation 2.5 where: K i      =  the total body dose factor due to gamma emissions for each identified noble gas radionuclide, 'i', in mrem/yr per Ci/m 3 (See Appendix A).
3000 fsk 
L i      =  the skin dose factor due to beta emissions for each identified noble gas radionuclide, 'i', in mrem/yr per Ci/m 3 (See Appendix A).
4.72E  02 u FQ u  > Li  1.1Mi u Ci @
M i      =   the air dose factor due to gamma emissions for each identified noble gas radionuclide, 'i', in mrad/yr per Ci/m 3 (See Appendix A).
i Radioiodines, Particulates, and Others - Organ Maximum Release Rate:
P opi   =  the dose parameter for radionuclides other than noble gases for the inhalation pathway, in mrem/yr per Ci/m 3 and for the food and ground plane pathways in (m 2 (mrem/yr per Ci/sec)) for organ, 'o', and radionuclide, 'i', (See Appendix B for the pathway specific dose commitment factors). Note:  NUREG-1301, page 75, specifies use of the Child age group, Inhalation pathway, for the P opi values./Q  =  the highest calculated annual average dispersion parameter for any area at or beyond the site boundary in sec/m
1500 for 
: 3. For the Oconee Unit Vents this value is 1.672E-6 sec/m
4.72E  02 u    ^P p   i opi food/gr u WD / Q  Popi  inhal u WF / Q` u Ei u Ci ftb, fsk, and for, are calculated for each batch prior to release. The most limiting gaseous release rate is used to assure that no instantaneous dose rate limit is exceeded.
: 3. The location is the SW sector at 1.0 mile for semi-elevated releases. For the Hot Machine Shop, Interim Radwaste Building and Radwaste
Once the maximum release rate, f, is calculated the value is multiplied by 0.8 for additional conservatism.
Section 2 - Page 8


Facility this value is 7.308E-6 sec/m
Oconee Nuclear Station                                                      January, 2007 Offsite Dose Calculation Manual (ODCM)                                      Revision 47 Derivations of Iodine, Particulate, and H-3 Dose Commitment Factors (Popi)
: 3. The location is the SE sector at 1.0 mile for ground-level releases. As discussed in Oconee UFSAR Section 2.1.1.3, the boundary for establishing gaseous effluent release limits is the exclusion area boundary (EAB). The EAB is defined as a 1 mile radius from the station center.
Inhalation Pathway - Child Age Group P          K c ( BR )( DFA        )
W  =  the highest calculated annual average dispersion or deposition parameter for estimating the maximum dose rate to an individual from the total inhalation, food, and ground plane pathways resulting from semi-elevated releases or ground-level
opi                            oi Formula: from NUREG-0133, page 25.
Where:
Popi Dose commitment factor for Child age group, organ o, nuclide i, for the inhalation pathway (mrem/yr per PCi/m3). (See Appendix B for the pathway specific dose commitment factors).
K' Units conversion factor pCi/PCi (106).
BR Breathing rate for the Child age group (m3/yr, from Regulatory Guide 1.109):
Child - 3700 DFAoi Organ inhalation dose conversion factor for Child age group, organ o, nuclide i, (mrem/pCi), from Table E-9 of Regulatory Guide 1.109.
Section 2 - Page 9


releases:
Oconee Nuclear Station                                                       January, 2007 Offsite Dose Calculation Manual (ODCM)                                       Revision 47 3.0 SETPOINT CALCULATIONS 3.0.1 LIQUID RADIATION MONITOR SETPOINT CALCULATIONS As shown on Figure 1.0-1, RIA-33 is the controlling radiation monitor for liquid batch releases at Oconee. Once the liquid release rate parameters have been established radiation monitor setpoints shall be calculated to assure that the concentration of radioactive liquid effluents released from the site to the unrestricted area is limited to ten times the effluent concentrations (ECs) of 10CFR20, Appendix B, Table 2, Column 2, and 2.0E-04 Ci/ml for dissolved and entrained noble gases. By substituting the dilution factor (DF) from Equation 2.2 into Equation 2.1, solving for the undiluted liquid effluent concentration, Ci, and accounting for the monitor background reading, the liquid radiation monitor setpoint can be readily obtained by multiplying Ci by the radiation monitor correlation factor, CFi, as follows:
Oconee Nuclear Station     January, 2007 Offsite Dose Calculation Manual (ODCM)                                                                           Revision 47 Section 2 - Page 7 W/Qse  =   1.672E-6 sec/m 3, for the inhalation pathway and the airborne H-3 food pathway. The location is the SW sector at 1.0 mile for semi-elevated
Ci (F   + f ) x (10 x ECi )
Equation 3.1 x f SP      (C i
i x CFi ) + bkg                            Equation 3.2 where:
Ci    = the maximum allowable concentration of radionuclide, i, in the undiluted liquid effluent, in Ci/ml.
SP    = radiation monitor setpoint, in cpm.
CFi = radiation monitor correlation factor for radionuclide, i, in cpm/Ci/ml =
8.00E+07 cpm/Ci/ml for RIA-33.
bkg = background reading for the radiation monitor, in cpm.
All other parameters were previously defined.
Using conservative or "worst-case" parameters in Equation 3.1 and Equation 3.2 can provide a liquid radiation monitor setpoint that does not need to be revised for every release if activity is low enough to allow for this type of operation such as with continuous releases from the #3 CTP release point. However, for batch releases, e.g.,
waste monitor tanks, through the liquid radwaste effluent line to the Keowee hydro Section 3 - Page 1


releases.WD/Qse=   1.295E-8 m
Oconee Nuclear Station                                                      January, 2007 Offsite Dose Calculation Manual (ODCM)                                      Revision 47 tailrace the RIA-33 radiation monitor setpoints are calculated based on the actual expected activity in the release as follows:
-2, for the food and ground plane pathways. The location is the NE sector at 1.0 mile for semi-elevated releases.
First the "Correlation Concentration" (C CONC) is calculated:
W/Qgl    =  7.308E-6 sec/m 3, for the inhalation pathway and the airborne H-3 food pathway. The location is the SE sector at 1.0 mile for ground-level
C CONC =        (C i
i x EQi )
where:
Ci        = Undiluted liquid effluent concentration for each isotope, excluding tritium, Ci/ml.
EQi      = RIA-33 Cs-137 equivalence factor for each isotope, excluding tritium, to that of Cs-137 due to different gamma energies and abundance. This factor includes a 4-hour decay time due to the average time between sample and release. (See Table 3.0-1)
Next the RIA-33 setpoints are determined as follows:
If C CONC is > 9.0E-6 Ci/ml then three setpoint values are calculated. The actual "expected" count rate for the release is defined as the "Midpoint of Expected Range".
The Alert setpoint is defined as 1.5 times the expected counts from activity in the liquid effluent plus background. If the Alert setpoint is exceeded, but there is no upward trend, the release will be allowed to continue. If RIA-33 continues to trend upward then the release will be manually terminated. The "Upper Limit of Expected Range" is defined as 3 times the expected counts from activity in the liquid effluent plus background. The Upper Limit of Expected Range is called the "Trip" setpoint. If the Trip setpoint is exceeded the release will be automatically terminated. The "Lower Limit of Expected Range" is defined as 3 times lower than the expected counts from activity in the liquid effluent plus background. The Lower Limit of Expected Range provides assurance that the correct liquid effluent is being released. If the RIA-33 count rate does not increase to at least the Lower Limit of the Expected Range then the release will be terminated, and a new sample analysis will be performed. The four RIA-33 setpoints are calculated as follows:
Lower Limit of Expected Range = C CONC x (8.00E7/3) cpm/(Ci/ml) +
RIA-33 BKG Midpoint of Expected Range          = C CONC x 8.00E7 cpm/(Ci/ml) +
RIA-33 BKG Alert Setpoint                      = C CONC x (8.00E7x1.5) cpm/(Ci/ml) +
RIA-33 BKG Upper Limit of Expected Range = C CONC x (8.00E7x3) cpm/(Ci/ml) +
(Trip Setpoint)                      RIA-33 BKG Section 3 - Page 2


releases.WD/Qgl=  2.259E-8 m
Oconee Nuclear Station                                                 January, 2007 Offsite Dose Calculation Manual (ODCM)                                 Revision 47 If C CONC is  9.05E-6 Ci/ml then the RIA-33 setpoint is 2.16E3 cpm plus background (BKG) as the Upper Limit of Expected Range. This setpoint is used for low activity releases, and is based on limiting the concentration in the effluent to 10 times the 10CFR20 EC of Cs-134 which has the lowest effluent concentration value (9.0E-7 Ci/ml) for any detectable radionuclide in the effluent.
-2, for the food and ground plane pathways. The location is the NE sector at 1.0 mile for ground-level releases.
Section 3 - Page 3
E i    =    the filter removal factor for radionuclide, 'i', e.g., for 99% removal E i = 0.01.                For iodine removal by charcoal adsorbers E i = 0.1.                For particulate removal by HEPA filters E i = 0.01.
Q i    =  the release rate of radionuclide, 'i', in gaseous effluent from all release points at the site,  in  Ci/sec.f C k f C k Q i i i 02 4.72E 2 1          Equation 2.6 where: C i  =  the concentration of radionuclide, 'i', in undiluted gaseous effluent, in Ci/ml. f      =  the undiluted effluent flow, in ft 3/min. k 1    =  conversion factor, 2.83E+04 cc/ft 3.k 2    =  conversion factor, 6.0E+01 sec/min.
Substituting the expression for Q i in Equation 2.6 into Equations 2.3, 2.4, and 2.5, and solving for the flow rate, '
f', in each equation gives: Noble Gases - Total Body Maximum Release Rate: i 02 4.72E 500 i i tb C K Q f Oconee Nuclear Station     January, 2007 Offsite Dose Calculation Manual (ODCM)                                                                           Revision 47 Section 2 - Page 8 Noble Gases - Skin Maximum Release Rate: i 1.1 02 4.72E 3000 i i i sk C M L Q fRadioiodines, Particulates, and Others - Organ Maximum Release Rate: i i i Q inhal opi Q D food/gr opi p or C E W P W P f 02 4.72E 1500// f tb , f sk , and f or, are calculated for each batch prior to release. The most limiting gaseous release rate is used to assure that no instantaneous dose rate limit is exceeded. Once the maximum release rate, f, is calculated the value is multiplied by 0.8 for additional conservatism.
Oconee Nuclear Station    January, 2007 Offsite Dose Calculation Manual (ODCM)                                                                            Revision 47 Section 2 - Page 9 Derivations of Iodine, Particulate, and H-3 Dose Commitment Factors (P opi)Inhalation Pathway - Child Age Group
))((oi DFA BR K opi PFormula:  from NUREG-0133, page 25. Where:  P opi Dose commitment factor for Child age group, organ o, nuclide i, for the inhalation pathway (mrem/yr per  Ci/m 3).  (See Appendix B for the pathway specific dose commitment factors).
K'Units conversion factor pCi/ Ci (10 6).BR Breathing rate for the Child age group (m 3/yr, from Regulatory Guide 1.109):
Child - 3700 DFA oi Organ inhalation dose conversion factor for Child age group, organ o, nuclide i, (mrem/pCi), from Table E-9 of Regulatory Guide 1.109.
Oconee Nuclear Station    January, 2007 Offsite Dose Calculation Manual (ODCM)    Revision 47  Section 3 - Page 1  3.0 SETPOINT CALCULATIONS 3.0.1  LI QUID RADIATION MONITOR SETPOINT CALCULATIONS As shown on Figure 1.0-1, RIA-33 is the controlling radiation monitor for li q uid batch releases at Oconee. Once the li q uid release rate parameters have been esta blished radiation monitor setpoints shall b e calculated to assure that the concentration of radioactive li q uid effluents released from the site to the unrestricted area is limited to ten times the effluent concentrations (ECs) of 10CFR20, Appendix B, Ta b le 2, Column 2, and 2.0E-04 µCi/ml for dissolved and entrained no b le gases. By su b stituting the dilution factor (DF) from E quation 2.2 into E quation 2.1, solving for the undiluted li q uid effluent concentration, C i , and accounting for the monitor b ac kground reading, the li q uid radiation monitor setpoint can b e readily o btained b y multiplying C i b y the radiation monitor correlation factor, CF i , as follows: 
()()          10            f EC f F C i ixxx+
E q uat i on 3.1  ()bkg CF C SP i i i            +x E q uat i on 3.2  where:
C i    =  the max imum allowa b le concentrat i on o f rad i onucl i de, i, i n the und iluted l i q u i d e ffluent, i n µCi/ml. SP    =  rad i at i on mon i tor setpo i nt, i n cpm. CF i  =  rad i at i on mon i tor correlat i on factor f or rad i onucl i de, i, i n cpm/µCi/ml = 8.00 E+07 cpm/µCi/ml f or RIA-33. bkg  =  b ac k g round read i n g f or the rad i at i on mon itor, i n cpm.
All other parameters were prev iously de fi ned.
Us i n g conservat i ve or " worst-case" parameters i n E q uat i on 3.1 and E q uat i on 3.2 can prov i de a l i q u i d rad i at i on mon i tor setpo i nt that does not need to b e rev i sed f or every release if act i v i ty i s low enou g h to allow f or th i s type o f operat i on such as w i th cont i nuous releases from the #3 C T P release po i nt. However, f or batch releases, e.g., waste mon i tor tan k s, throu g h the l i q u i d radwaste e ffluent l i ne to the Keowee hydro Oconee Nuclear Stat i on    January, 2007 O ff s i te Dose Calculat i on Manual (OD C M)    Rev i s i on 47  Sect i on 3 - P a g e 2 ta ilrace the RIA-33 rad i at i on mon i tor setpo ints are calculated b ased on the actual expected act i v i ty i n the release as f ollows:
Fi rst the " Correlat i on Concentrat i on" (C C ON C) i s calculated:
  ()            x=i i i EQ C C ONC C where:
C i          =
Und iluted l i q u i d effluent concentrat i on for each i sotope, exclud i ng tr i t i um, µCi/ml. EQ i      = RIA-33 C s-137 e q u i valence factor for each i sotope, exclud i ng tr i t i um, to that of C s-137 due to d ifferent gamma energ i es and a bundance. Th i s factor i ncludes a 4-hour decay t i me due to the average t i me between sample and release. (See Ta b le 3.0-1)  Next the RIA-33 setpo ints are determ i ned as follows:  If C C ON C i s > 9.0 E-6 µCi/ml then three setpo i nt values are calculated.
The actual "expected" count rate for the release i s def i ned as the " M i dpo i nt of Expected Range". The Alert setpo i nt i s def i ned as 1.5 t imes the expected counts from act i v i ty i n the l i q u i d effluent plus b ac kground. If the Alert setpo i nt i s exceeded, b ut there i s no upward trend, the release w i ll b e allowed to cont i nue. If RIA-33 cont i nues to trend upward then the release w i ll b e manually term i nated. The " Upper L i m i t of Expected Range" i s def i ned as 3 t imes the expected counts from act i v i ty i n the l i q u i d effluent plus b ac kground. The Upper L i m i t of Expected Range i s called the " Tr i p" setpo i nt. If the Tr i p setpo i nt i s exceeded the release w i ll b e automat ically term inated. The "Lower L i m i t of Expected Range" i s def i ned as 3 t imes lower than the expected counts from act i v i ty i n the l i q u i d effluent plus b ac kground. The Lower L i m i t of Expected Range prov i des assurance that the correct l i q u i d effluent i s b e i ng released. If the RIA-33 count rate does not increase to at least the Lower L i m i t of the Expected Range then the release w i ll b e term inated, and a new sample analys i s w i ll b e performed.
The four RIA-33 setpo i nts are calculated as follows:  Lower L i m i t of Expected Range  =  C C ON C  x  (8.00 E 7/3) cpm/(µCi/ml)  +                                                              RIA-33 B K G  M i dpo i nt of Expected Range        =
C C ON C  x  8.00 E 7 cpm/(µCi/ml)  +                                                              RIA-33 B K G  Alert Setpo i nt                                =
C C ON C  x  (8.00 E 7x1.5) cpm/(µCi/ml)  +                                                            RIA-33 B K G  Upper L i m i t of Expected Range  =  C C ON C  x  (8.00 E 7x3) cpm/(µCi/ml)  +  (Tr i p Setpo i nt)                                  RIA-33 B K G Oconee Nuclear Stat i on    January, 2007 Offs i te Dose Calculat i on Manual (O D C M)    Rev i s i on 47  Sect i on 3 - Page 3  If C C ON C i s  9.0 5 E-6 µCi/ml then the RIA-33 setpo i nt i s 2.1 6 E 3 cpm plus b ac kground (B K G) as the Upper L i m i t of Expected Range. Th i s setpo i nt i s used for low act i v i ty releases, and i s b ased on l i m i t i ng the concentrat i on i n the effluent to 10 t imes the 10 CFR20 EC of C s-134 wh i ch has the lowest effluent concentrat i on value (9.0 E-7 µCi/ml) for any detecta b le rad i onucl i de i n the effluent.
Oconee Nuclear Stat i on    January, 2007 Offs i te Dose Calculat i on Manual (O D C M)    Rev i s i on 47  Sect i on 3 - Page 4 Ta ble 3.0-1  RIA-33 Cs-137 E q uivalents  Isotope E quivalence Factor Isotope E quivalence Factor Isotope E quivalence Factor Be-7 0.14 6 2 Mo-99 0.2 668 La-141 0.01 55 F-1 8 0.5 7 88 Tc-99 m 0.00 La-142 0.2 9 42 N a-24 0.85 1 9 Tc-101 0.00 C e-141 0.00 C l-3 8 0.00 9 0 Ru-103 1.33 68 C e-143 0.7 8 2 6 K-40  0.10 9 4 Ru-10 5 0.8 7 8 3 C e-144 0.0273 C r-5 1 0.143 8 Ru-10 6 0.442 9 I-130 3.30 95 Mn-5 4 1.0 6 17 Ag-10 8 m 3.4473 I-131 1.40 5 1 Mn-56 0.4 99 2 Ag-110m 3.5 17 9 I-132 1.02 59 Fe-59 1.0 556 C d-11 5 0.5 201 I-133 1.1 85 7 C o-5 7 0.0022 C d-11 5 m 0.023 5 I-134 0.13 88 C o-58 1.473 5 In-11 5 m 0.3 6 31 I-13 5 0.9 374 C o-6 0 2.04 95 S b-122 0.9 21 8 Ar-41 0.222 9 C u-6 4 0.3 95 4 S b-124 2.1 6 17 K r-85 0.00 59 N i-65 0.1 59 1 S b-12 5 1.130 8 K r-85 m  0.42 8 0 Z n-65 0.558 4 S b-12 6 5.17 6 2 K r-8 7 0.1213 Z n-69 m 1.13 9 1 Sn-113 0.99 71 K r-88 0.5 27 8 Se-7 5 1.30 9 2 Sn-123 0.00 66 K r-89 0.00 Br-8 0m 0.0 86 0 Sn-12 6 0.00 X e-131m 0.01 6 7 Br-8 2 3.4 69 1 Te-12 5 m 0.00 X e-133 0.000 6 Br-8 3 0.00 59 Te-127 0.0134 X e-133m 0.1172 Br-8 4 0.00 5 3 Te-127m 0.0001 X e-13 5 0.856 4 Br-85 0.00 Te-12 9 0.013 8 X e-13 5 m 0.00 R b-86 0.0 89 4 Te-12 9 m 0.0 5 07 X e-137 0.00 R b-88 0.00 Te-131 0.000 8 X e-13 8 0.00 R b-89 0.00 Te-131m 1.8 4 6 3 N d-147 0.2 6 1 9 Sr-89 0.0002 Te-132 0.9 7 66 Hf-1 8 1 1.420 9 Sr-9 1 0.6 4 6 0 Te-134 0.0408 W-1 8 7 0.8 027 Sr-9 2 0.3 9 00 C s-134 2.58 04 Tl-20 8 0.00 Y-9 1 0.0031 C s-13 6 3.1 9 1 6 B i-212 0.0144 Y-9 1m 0.043 9 C s-137 1.00 B i-214 0.0003 Y-9 2  0.1334 C s-13 8 0.0120 P b-212 0.44 9 7 Y-9 3 0.10 9 1 Ba-133 1.3 6 4 8 P b-214 0.0020 Z r-95 1.0 9 0 9 Ba-13 9 0.0203 Ra-22 6 0.0320 Z r-9 7 1.1210 Ba-140 0.5 307 Ac-22 8 0.8 2 6 1 N b-95 1.0 8 21 Ba-141 0.0002 Th-22 8 0.003 8 N b-95 m 0.2 9 1 9 Ba-142 0.00 N p-23 9 0.3 996 N b-9 7 0.11 6 4 La-140 2.3237 Oconee Nuclear Station    January, 2007 Offsite Dose Calculation Manual (ODCM)    Revision 47 Section 3 - Page 5 3.0.2    GASEOUS RADIATION MONITOR SETPOINT CALCULATIONSThe unit vent radiation monitor setpoints are established at the Oconee Nuclear Station to help ensure that gaseous release rate limits are not exceeded. For some release pathways in which a specific RIA exists, the setpoints also help to ensure that the effluent being released is the same concentration as indicated by manual samples, e.g. effluent from waste gas decay tanks, thereby reducing the likelihood of releasing the wrong tank. For instances in which the RIA which normally controls the release is not operable, or is "out of service", independent manual samples (IMS) are collected and the noble gas constituents from both samples are compared to help ensure that the intended "batch" is being released. For certain low potential release types, e.g. Integrated Leak Rate Tests, no RIA exists to ensure that release rate limits are not exceeded or to ensure that the effluent being released is the "expected" concentration. For such pathways, independent manual samples are required to be collected and noble gas constituents compared prior to release. The following list defines the controlling RIA for the various gaseous effluent release types at Oconee:
Pathway                                                            Controlling RIA Unit 1 "A" Waste Gas Decay Tank                  1&2 RIA 37/38 Unit 1 "B" Waste Gas Decay Tank                  1&2 RIA 37/38


Unit 1 "C" Waste Gas Decay Tank                  1&2 RIA 37/38
Oconee Nuclear Station                                                  January, 2007 Offsite Dose Calculation Manual (ODCM)                                  Revision 47 Table 3.0-1 RIA-33 Cs-137 Equivalents Isotope      Equivalence        Isotope      Equivalence  Isotope Equivalence Factor                            Factor              Factor Be-7              0.1462        Mo-99                0.2668 La-141      0.0155 F-18              0.5788        Tc-99m                0.00  La-142      0.2942 Na-24              0.8519        Tc-101                0.00  Ce-141        0.00 Cl-38              0.0090        Ru-103              1.3368 Ce-143      0.7826 K-40              0.1094        Ru-105              0.8783 Ce-144      0.0273 Cr-51              0.1438        Ru-106              0.4429 I-130        3.3095 Mn-54              1.0617        Ag-108m              3.4473 I-131        1.4051 Mn-56              0.4992        Ag-110m              3.5179 I-132        1.0259 Fe-59              1.0556        Cd-115              0.5201 I-133        1.1857 Co-57              0.0022        Cd-115m              0.0235 I-134        0.1388 Co-58              1.4735        In-115m              0.3631 I-135        0.9374 Co-60              2.0495        Sb-122              0.9218 Ar-41        0.2229 Cu-64              0.3954        Sb-124              2.1617 Kr-85        0.0059 Ni-65              0.1591        Sb-125              1.1308 Kr-85m      0.4280 Zn-65              0.5584        Sb-126              5.1762 Kr-87        0.1213 Zn-69m            1.1391        Sn-113              0.9971 Kr-88        0.5278 Se-75              1.3092        Sn-123              0.0066 Kr-89          0.00 Br-80m            0.0860        Sn-126                0.00  Xe-131m      0.0167 Br-82              3.4691        Te-125m              0.00  Xe-133      0.0006 Br-83              0.0059        Te-127              0.0134 Xe-133m      0.1172 Br-84              0.0053        Te-127m              0.0001 Xe-135      0.8564 Br-85                0.00        Te-129              0.0138 Xe-135m        0.00 Rb-86              0.0894        Te-129m              0.0507 Xe-137        0.00 Rb-88                0.00        Te-131              0.0008 Xe-138        0.00 Rb-89                0.00        Te-131m              1.8463 Nd-147      0.2619 Sr-89              0.0002        Te-132              0.9766 Hf-181      1.4209 Sr-91              0.6460        Te-134              0.0408 W-187        0.8027 Sr-92              0.3900        Cs-134              2.5804 Tl-208        0.00 Y-91              0.0031        Cs-136              3.1916 Bi-212      0.0144 Y-91m              0.0439        Cs-137                1.00  Bi-214      0.0003 Y-92              0.1334        Cs-138              0.0120 Pb-212      0.4497 Y-93              0.1091        Ba-133              1.3648 Pb-214      0.0020 Zr-95              1.0909        Ba-139              0.0203 Ra-226      0.0320 Zr-97              1.1210        Ba-140              0.5307 Ac-228      0.8261 Nb-95              1.0821        Ba-141              0.0002 Th-228      0.0038 Nb-95m            0.2919        Ba-142                0.00  Np-239      0.3996 Nb-97              0.1164        La-140              2.3237 Section 3 - Page 4


Unit 1 "D" Waste Gas Decay Tank                 1&2 RIA 37/38  
Oconee Nuclear Station                                                      January, 2007 Offsite Dose Calculation Manual (ODCM)                                      Revision 47 3.0.2    GASEOUS RADIATION MONITOR SETPOINT CALCULATIONS The unit vent radiation monitor setpoints are established at the Oconee Nuclear Station to help ensure that gaseous release rate limits are not exceeded. For some release pathways in which a specific RIA exists, the setpoints also help to ensure that the effluent being released is the same concentration as indicated by manual samples, e.g. effluent from waste gas decay tanks, thereby reducing the likelihood of releasing the wrong tank. For instances in which the RIA which normally controls the release is not operable, or is "out of service", independent manual samples (IMS) are collected and the noble gas constituents from both samples are compared to help ensure that the intended "batch" is being released. For certain low potential release types, e.g. Integrated Leak Rate Tests, no RIA exists to ensure that release rate limits are not exceeded or to ensure that the effluent being released is the "expected" concentration. For such pathways, independent manual samples are required to be collected and noble gas constituents compared prior to release. The following list defines the controlling RIA for the various gaseous effluent release types at Oconee:
Pathway                                            Controlling RIA Unit 1 "A" Waste Gas Decay Tank                    1&2 RIA 37/38 Unit 1 "B" Waste Gas Decay Tank                    1&2 RIA 37/38 Unit 1 "C" Waste Gas Decay Tank                    1&2 RIA 37/38 Unit 1 "D" Waste Gas Decay Tank                   1&2 RIA 37/38 Unit 3 "A" Waste Gas Decay Tank                    3 RIA 37/38 Unit 3 "B" Waste Gas Decay Tank                    3 RIA 37/38 Unit 3 "C" Waste Gas Decay Tank                    3 RIA 37/38 Unit 1 Reactor Building Purge                      1 RIA 45/46 Unit 2 Reactor Building Purge                      2 RIA 45/46 Unit 3 Reactor Building Purge                      3 RIA 45/46 Unit 1 Depressurization                            IMS 1 RIA 45/46 Alarm Only Unit 2 Depressurization                            IMS 2 RIA 45/46 Alarm Only Unit 3 Depressurization                            IMS 3 RIA 45/46 Alarm Only Unit 1 Hydrogen Recombiner                          IMS 1 RIA 45/46 Alarm Only Unit 2 Hydrogen Recombiner                          IMS 2 RIA 45/46 Alarm Only Unit 3 Hydrogen Recombiner                          IMS 3 RIA 45/46 Alarm Only Unit 1 Integrated Leak Rate Test                    IMS Unit 2 Integrated Leak Rate Test                    IMS Unit 3 Integrated Leak Rate Test                    IMS The following sections describe the methods by which setpoints are established. In general, gaseous radiation monitors are calibrated to Xe-133, and for continuous release points, e.g., the three unit vents, are preset at a maximum value based on the 500 mrem/year total body gaseous release rate limit according to the following methodology:
Section 3 - Page 5


Unit 3 "A" Waste Gas Decay Tank                  3 RIA 37/38
Oconee Nuclear Station                                                          January, 2007 Offsite Dose Calculation Manual (ODCM)                                          Revision 47 Note: when applied to the individual release points the 500 mrem/year site dose rate value is apportioned 30% to each Unit Vent (RIA-45 and RIA-46) semi-elevated release point.
The remaining 10% is allocated to the three ground-level release points, the Hot Machine Shop (no monitor), Interim Radwaste Building (RIA-53) and Radwaste Facility (4RIA-45) that are normally considered non-radioactive. Recall from Section 2.0.2.1 the following equation:
KXe  133 x  / Q x QXe  133 < 500 mrem/yr Solve for QXe-133:
500 QXe  133 <                                                      Equation 3.4 KXe  133 x  / Q From Equation 2.6:
QXe  133 = 4.72E + 02 x CXe  133 x f                          Equation 3.5 Substitute Equation 3.5 into Equation 3.4:
500 4.72E + 02 x CXe  133 x f <
KXe  133 x  / Q Solve for CXe-133:
500 CXe  133 <
4.72E + 02 x f x KXe  133 x  / Q CXe  133 SP =                + bkg                                      Equation 3.6 CF where:
KXe-133    =      2.94E+02, the total body dose factor due to gamma emissions for Xe-133, in mrem/year per Ci/m3 (See Appendix A).
/Q          =    the highest calculated semi-elevated annual average dispersion parameter for any area at or beyond the site boundary in sec/m3. For Oconee this value is 1.672E-6 sec/m3. The location is the SW sector at 1.0 mile.
QXe-133      = Xe-133 equivalent release rate limit for the noble gas total body dose pathway, in Ci/sec.
4.72E+02 = Conversion factor, (cc/ft3)/(sec/min).
Section 3 - Page 6


Unit 3 "B" Waste Gas Decay Tank                  3 RIA 37/38
Oconee Nuclear Station                                                        January, 2007 Offsite Dose Calculation Manual (ODCM)                                        Revision 47 CXe-133      = the maximum allowable Xe-133 equivalent concentration in the gaseous effluent, in Ci/cc.
f            = the gaseous effluent flow from the tank, building, or vent, in ft3/min.
SP            = radiation monitor setpoint, in cpm.
CF            = the Xe-133 equivalent monitor correlation factor, in Ci/cc/cpm.
bkg            = the radiation monitor background reading, in cpm.
Equation 3.6 provides the methodology to calculate the maximum setpoint for releases from the Unit Vents (RIA-45 and RIA-46), Radwaste Facility (4RIA-45), and Interim Radwaste Building (RIA-53).
3.0.2.1 UNIT VENTS SETPOINTS (RIA-45 and RIA-46)
Reactor Building purges from all 3 units are released via the applicable unit vent, either Unit 1, Unit 2, or Unit 3. Each of the 3 unit vents are monitored by a normal/low range RIA (RIA-45) and a high range RIA (RIA-46). In addition to Reactor Building purges, all other releases from the main plant, including the Auxiliary Building ventilation, Waste Gas Decay Tanks, and the Spent Fuel Pools are monitored by each unit's RIA-45 and RIA-46. However, RIA-45 and RIA-46 on each unit vent have release termination authority only for Reactor Building purge releases. Each unit's RIA-45 and RIA-46 will, when operable, activate Control Room alarms if the unit vent concentration exceeds the monitor's setpoint value. The setpoints for each unit's RIA-45 and RIA-46 are established on a "worst case" basis, with the upper bound normally set at 30 percent of the station release rate limit for noble gases in Xe-133 equivalent concentration as follows:
Recall Equation 3.6:
CXe  133 SP =              + bkg CF where:
500 CXe  133 <
4.72E + 02 x f x KXe  133 x  / Q 150 RIA  45unit vent =
4.72E + 02 x 6.5E + 04 x 2.94E + 02 x 1.672E  06 x 7.09E  08 RIA 45unit vent  1.40E + 05 cpm + bkg Section 3 - Page 7


Unit 3 "C" Waste Gas Decay Tank                  3 RIA 37/38 Unit 1 Reactor Building Purge                         1 RIA 45/46 Unit 2 Reactor Building Purge                        2 RIA 45/46 Unit 3 Reactor Building Purge                         3 RIA 45/46 Unit 1 Depressurization                                    IMS 1 RIA 45/46 Alarm Only Unit 2 Depressurization                                    IMS 2 RIA 45/46 Alarm Only Unit 3 Depressurization                                    IMS 3 RIA 45/46 Alarm Only Unit 1 Hydrogen Recombiner                          IMS 1 RIA 45/46 Alarm Only Unit 2 Hydrogen Recombiner                          IMS 2 RIA 45/46 Alarm Only Unit 3 Hydrogen Recombiner                          IMS 3 RIA 45/46 Alarm Only
Oconee Nuclear Station                                                    January, 2007 Offsite Dose Calculation Manual (ODCM)                                    Revision 47 where:
150          = 30% of the 500 mrem/yr total body release rate limit.
6.5E+04      = Unit Vent flow rate with Reactor Building Purge off, ft3/min.
1.672E-06 = Highest Semi-Elevated release point dispersion factor, sec/m3.
7.09E-08 = RIA-45 Correlation Factor, Ci/ml/cpm.
All other factors were previously defined.
150 RIA  46unit vent =
4.72E + 02 x 6.5E + 04 x 2.94E + 02 x 1.672E  06 x 3.17 E  04 RIA  46unit vent  31 cpm + bkg where:
3.17E-04    = RIA-46 Correlation Factor, Ci/ml/cpm.
All other factors were previously defined.
For instances in which the Reactor Building Purge is on, the setpoint is multiplied by 0.65 (65,000 cfm/ (65,000 cfm + 35,000 cfm purge flow)).
3.0.2.2 RADWASTE FACILITY SETPOINTS (4RIA-45) 25 4 RIA 45 =
4.72E + 02 x 1.297E + 05 x 2.94E + 02 x 7.308E  06 4 RIA 45 1.90E - 04 Ci/ml where:
25            = 5% of the 500 mrem/yr total body release rate limit.
1.297E+05 = Radwaste Facility Vent flow rate, ft3/min.
7.308E-06      = Highest Ground-Level release point dispersion factor, sec/m3.
All other factors were previously defined.
4RIA-45 reads in units of concentration, Ci/ml.
Section 3 - Page 8


Unit 1 Integrated Leak Rate Test                      IMS
Oconee Nuclear Station                                                      January, 2007 Offsite Dose Calculation Manual (ODCM)                                      Revision 47 3.0.2.3 INTERIM RADWASTE BUILDING SETPOINTS (RIA-53) 25 RIA  53 =
4.72E + 02 x 1.5E + 04 x 2.94E + 02 x 7.308E  06 x 3.4E  08 RIA  53  4.8E + 04 cpm + bkg where:
25              = 5% of the 500 mrem/yr total body release rate limit.
1.5E+04        = Interim Radwaste Building Vent flow rate, ft3/min.
7.308E-06      = Highest Ground-Level release point dispersion factor, sec/m3.
3.4E-08        = RIA-53 Correlation Factor, Ci/ml/cpm.
All other factors were previously defined.
In addition to the maximum setpoints discussed previously, Oconee uses "Alert" setpoints that are based on 10% of the reporting requirement from 10CFR50.73(a)(2)(viii)(A).
Each unit vent Alert setpoint is based on 60% of a Xe-133 Effluent Concentration (EC) value of 5.0E-07 Ci/ml at the site boundary. The Interim Radwaste Building and Radwaste Facility are each set at 10% of the Xe-133 EC. The method used to calculate the Alert setpoints is similar to that used to calculate the maximum setpoints except that the limit is based on concentration rather than dose rate. The Alert setpoints are approximately 42% of the maximum setpoints.
3.0.2.4 WASTE GAS DECAY TANK SETPOINTS (RIA-37 and RIA-38)
For batch releases where the effluent can contain activity significantly above background, e.g., Waste Gas Decay Tank (WGDT), two additional monitors, RIA-37 and RIA-38 are used to establish setpoints for each WGDT batch released. RIA-37 is the normal/low range noble gas monitor, and RIA-38 is the high range noble gas monitor. The following setpoint methodology is used:
CXe  133 =  (C i
i x Eqi )
CXe  133 Expected Cpm =                  + bkg CFXe  133 CXe  133 RIA - 37 and RIA - 38 Setpoint =                  x 1 .5      Equation 3.7 CFXe  133 Section 3 - Page 9


Unit 2 Integrated Leak Rate Test                      IMS Unit 3 Integrated Leak Rate Test                      IMS The following sections describe the methods by which setpoints are established. In general, gaseous radiation monitors are calibrated to Xe-133, and for continuous release points, e.g., the three unit vents, are preset at a maximum value based on the 500 mrem/year total body gaseous release rate limit according to the following methodology:
Oconee Nuclear Station                                                    January, 2007 Offsite Dose Calculation Manual (ODCM)                                     Revision 47 where:
Oconee Nuclear Stat i on    January, 2007 Offs i te Dose Calculat i on Manual (O D C M)     Rev i s i on 47  Sect i on 3 - Page 6 N ote: when appl i ed to the i nd i v idual release po ints the 5 00 mrem/year s i te dose rate value i s apport ioned 30% to each Un i t Vent (RIA-4 5 and RIA-4 6) sem i-elevated release po i nt. The rema i n i ng 10% i s allocated to the three ground-level release po i nts, the Hot Mach i ne Shop (no mon itor), Inter i m Radwaste Bu i ld i ng (RIA-5 3) and Radwaste Fac i l i ty (4RIA-4 5) that are normally cons idered non-rad ioact ive. Recall from Sect i on 2.0.2.1 the follow i ng e q uat i on:    mrem/yr 5 00        /    133 133<xxX e Xe Q Q K  Solv e for QXe-133:  /    5 00    133 133 Q K Q Xe Xex<
CXe-133   = Xe-133 equivalent concentration of the WGDT to be released, in Ci/ml.
E quation 3.4  From E quation 2.6:  f C Q Xe Xe        02 4.72E    133 133xx+=
Eqi        = Xe-133 equivalence factor for each noble gas isotope, excluding tritium, to that of Xe-133 due to different beta energies and abundance.
E quation 3.5  Su b stitut e E quation 3.5 into E quation 3.4:  Q K f C Xe Xe/    5 00            02 4.72E 133 133x<xx+  Solv e for CXe-133:  Q K f C Xe Xe/            02 E 72.4 5 00    133 133xxx+<  bkg    C F C    S P  Xe+=133 E quation 3.6  wh e r e:  KXe-133        =    2.9 4E+02, th e total body dos e factor du e to gamma e missions for X e-133 , in mr e m/y e ar p e r &#xb5;C i/m 3 (S ee App e ndix A). /Q          =
(See Table 3.0-2).
th e hi g h e st calculat e d s e mi-e l evat e d annual av e ra ge disp ersion param e t e r for any ar e a at or b eyond th e sit e boundary in s e c/m 3. For Ocon ee this valu e is 1.6 72E-6 s e c/m 3. Th e location is th e S W s ector at 1.0 mil e. QXe-133         
CFXe-133 = The expected RIA response to a given Xe-133 equivalent concentration, in Ci/ml/cpm. 1RIA-37 = 1.01E-08 Ci/ml/cpm, 3RIA-37 = 4.20E-08 Ci/ml/cpm, 1RIA-38 and 3RIA-38 = 1.34E-03 Ci/ml/cpm.
=   X e-133 e q uival e nt r e l e as e rat e limit for th e no b l e g as total b ody dos e pathway, in &#xb5;C i/s e c. 4.72E+02  =  C onv ersion factor, (cc/ft 3)/(s e c/min).
1.5        = An adjustment factor to account for expected minor variations in effluent concentration and RIA background.
Ocon ee Nucl e ar Station    January, 2007 Offsit e Dos e Calculation Manual (OD C M)    R evision 47  S ection 3 - P a ge 7  CXe-133         
bkg       = The radiation monitor background reading, in cpm.
= th e maximum allowa b l e X e-133 e q uival e nt conc entration in th e g as e ous efflu e nt, in &#xb5;C i/cc.
When the release pathway is from any Unit 1 WGDT (A-D), and the Xe-133 equivalent concentration is less than 2.8E-01 Ci/ml, the 1&2 RIA-38 setpoint is established at 313 cpm, and the 1&2 RIA-37 setpoint is calculated using Equation 3.7.
f                  =
When the release pathway is from any Unit 1 WGDT (A-D), and the Xe-133 equivalent concentration is greater than 2.8E-01 Ci/ml, the 1&2 RIA-37 setpoint is established as offscale high, and the 1&2 RIA-38 setpoint is calculated using Equation 3.7.
th e g as eous efflu e nt flow from th e tan k , b uildin g , or v e nt, in ft 3/min.
When the release pathway is from any Unit 3 WGDT (A-C), and the Xe-133 equivalent concentration is less than 2.8E-01 Ci/ml, the 3 RIA-38 setpoint is established at 313 cpm, and the 3 RIA-37 setpoint is calculated using Equation 3.7.
S P              =  radiation monitor s e tpoint, in cpm. C F              =
When the release pathway is from any Unit 3 WGDT (A-C), and the Xe-133 equivalent concentration is greater than 2.8E-01 Ci/ml, the 3 RIA-37 setpoint is established as offscale high, and the 3 RIA-38 setpoint is calculated using Equation 3.7.
th e X e-133 e q uival e nt monitor corr elation factor, in &#xb5;C i/cc/cpm. bkg             =
When there are no noble gases present in the WGDT sample, the RIA-37 setpoint is set to five times (5X) the RIA-37 background reading.
th e radiation monitor b ac k g round r eadin g , in cpm.
Section 3 - Page 10
E quation 3.6 provid e s th e m e thodolo g y to calculat e th e maximum s e tpoint for r e l e as e s from th e Unit V e nts (RIA-4 5 and RIA-4 6), Radwast e Facility (4RIA-4 5), and Int erim Radwast e Buildin g (RIA-5 3). 3.0.2.1  UNIT VENTS SETPOINTS (RIA
-4 5 and RIA-4 6)  R eactor Buildin g pur ge s from all 3 units ar e r e l e as e d via th e applica b l e unit v e nt, e ith e r Unit 1 , Unit 2, or Unit 3. Each of th e 3 unit v ents ar e monitor e d b y a normal/low ran ge RIA (RIA-4 5) and a hi g h ran ge RIA (RIA-4 6). In addition to R eactor Buildin g pur ge s, all oth e r r e l e as e s from th e main plant, includin g th e Auxiliary Buildin g v entilation, W ast e Gas D ecay Tan k s, and th e Sp e nt Fu e l P ools ar e monitor e d b y e ach unit's RIA-4 5 and RIA-4 6. How e v e r, RIA-4 5 and RIA-4 6 on e ach unit v e nt hav e r e l e as e t ermination authority only for R eactor Buildin g pur ge r e l e as e s. Each unit's RIA-4 5 and RIA-4 6 will, wh e n op e ra b l e , activat e C ontrol Room alarms if th e unit v e nt conc entration e xc ee ds th e monitor's s e tpoint valu e. Th e s e tpoints for e ach unit's RIA-4 5 and RIA-4 6 ar e e sta b lish e d on a " worst cas e" basis, with th e upp e r b ound normally s e t at 3 0 p e rc e nt of th e station r e l e as e rat e limit for no b l e g as e s in X e-133 e q uival e nt conc entration as follows:
R ecall E quation 3.6:  bkg    C F C    S P  Xe+=133    wh e r e:  Q K f C Xe Xe/            02 E 72.4 5 00    133 133xxx+<  0 8 7.0 9 E    0 6 1.6 72E    02 2.9 4E    04 6.5 E    02 4.72E 1 5 0    4 5 v e ntxx+x+x+=unit RIA  bk g    cpm 0 5 1.40E    4 5 ve nt++unit RIA Oco n ee N u clear S t a ti o n    J a nuary, 2007 Offs it e Dose Calc u la ti o n Ma nu al (ODCM)    R ev i s i o n 47  Sec ti o n 3 - Page 8 where:
1 5 0            =
30% of t he 5 00 mrem/yr t o t al body release ra t e l i m it.
6.5 E+04    =  U nit Ve nt flow ra t e w it h Reac t or B ui ld in g P u rge off, f t 3/m in.
1.6 72E-0 6  =  H ighes t Sem i-Eleva t ed release po int d i spers i o n fac t or, sec/m 3. 7.0 9 E-0 8    =  RIA-4 5 Correla ti o n Fac t or, &#xb5;C i/ml/cpm.
A ll o t her fac t ors were prev i o usly def in ed. 04 E 17.3    0 6 E 6 72.1    02 E 9 4.2   04 E 5.6    02 E 72.4 1 5 0    4 6 ve ntxx+x+x+=unit RIA  bk g  cpm 31    4 6 ve nt+unit RIA   where:  3.17E-04    =  RIA-4 6 Correla ti o n Fac t or, &#xb5;C i/ml/cpm.
A ll o t her fac t ors were prev i o usly def in ed.
For in s t a nces in wh i ch t he R eac t or B ui ld in g P urge i s o n , t he se t po int i s m u l ti pl i ed b y 0.65 (65 ,000 cfm/ (65,000 cfm + 3 5 ,000 cfm p urge flow)). 3.0.2.2  RAD WASTE FACILITY SETPOINTS (4RIA
-4 5)  0 6 7.30 8 E    02 2.9 4E    0 5 1.2 9 7E    02 4.72E 2 5    4 5 4x+x+x+=RIA &#xb5;C i/ml 04-1.9 0E    4 5 4RIA  where:
2 5                =  5%
of t he 5 00 mrem/yr t o t al body release ra t e l i m it.
1.2 9 7E+0 5  =  Radwas t e Fac i l it y Ve nt flow ra t e, f t 3/m in. 7.30 8 E-0 6    =  H ighes t Gro un d-Level release point d i spers i o n fac t or, sec/m 3.
A ll o t her fac t ors were prev i o usly def in ed. 4RIA-4 5 reads in unit s of co n ce nt ra ti o n , &#xb5;C i/ml.
Oco n ee N u clear S t a ti o n    J a nuary, 2007 Offs it e Dose Calc u la ti o n Ma nu al (ODCM)    R ev i s i o n 47  Sec ti o n 3 - Page 9 3.0.2.3  INTERIM RAD WASTE BUILDING SETPOINTS (RIA
-5 3)  0 8 3.4E    0 6 7.30 8 E    02 2.9 4E    04 1.5 E    02 4.72E 2 5    5 3xx+x+x+=RIA  bk g    cpm 04 4.8 E    5 3++RIA  where:
2 5                =  5%
of t he 5 00 mrem/yr t o t al body release ra t e l i m it.
1.5 E+04      =  Int er i m R adwas t e B ui ld in g Ve nt flow ra t e, f t 3/m in.
7.30 8 E-0 6    =  H ighes t Gro un d-Level release point d i spers i o n fac t or, sec/m 3. 3.4E-0 8        =  RIA-5 3 Correla ti o n Fac t or, &#xb5;C i/ml/cpm.
A ll o t her fac t ors were prev i o usly def in ed. In add iti o n t o t he max i m u m se t po int s d i sc u ssed prev i o usly, Oco n ee u ses " Aler t" se t po int s t ha t are b ased o n 10% of t he repor tin g re q ui reme nt from 10CF R 50.73(a)(2)(v iii)(A). Each unit ve nt Aler t se t po int i s b ased o n 6 0% of a X e-133 Effl u e nt Co n ce nt ra ti o n (EC) val u e of 5.0E-07 &#xb5;C i/ml a t t he s it e b o undary. The Int er i m R adwas t e B ui ld in g a n d R adwas t e Fac i l it y are each se t a t 10% of t he X e-133 EC. The me t hod used t o calc u la t e t he Aler t se t po int s i s s i m ilar t o t ha t u sed t o calc u la t e t he max i m u m se t point s excep t t ha t t he l i m it i s b ased o n co n ce nt ra ti o n ra t her t ha n dose ra t e. The A ler t se t po int s are approx i ma tely 42% of t he max i m u m se t po int s. 3.0.2.4  WASTE GAS DECAY TAN K SETPOINTS (RIA-37 and RIA
-3 8)  For b a t ch releases where t he effl u e nt ca n co nt a in ac ti v it y s i g ni f i ca nt ly a bove b ac kgro un d, e.g., W as t e Gas Decay Ta n k (W GDT), t wo add iti o n al mo nit ors, RIA-37 a n d RIA-3 8 are u sed t o es t a b l i sh se t po int s for each W GDT b a t ch released. RIA-37 i s t he n ormal/low ra n ge n o b le gas mo nit or, a n d RIA-3 8 i s t he h i gh ra n ge n o b le gas mo nit or. The follow in g se t po int me t hodology i s u sed:  ()          133x=i i i X e E q C C bk g    C F C    C pm  Expected Xe Xe+=133 133 5.1 133 133    CF C    Setpoint 3 8-RIA and 3 7 -RIA Xe Xex=
E q u a ti o n 3.7 O co n ee Nu c l ea r S t a ti o n    J a n u ary, 200 7 Offs it e D o s e Ca l c ul a ti o n M a n u a l (OD C M)    R e v i s i o n 4 7  Sec ti o n 3 - P a g e 10 wh e r e:  C Xe-133      =  X e-133 e q u i v a l e nt co n ce nt r a ti o n o f t h e W GDT t o b e r e l ea s ed , in &#xb5;C i/m l. Eq i          =  X e-133 e q u i v a l e n ce f ac t o r f o r eac h n o b l e g a s i s o t ope , exc lu d in g t r iti u m , t o t h a t o f X e-133 d u e t o d i ff e r e nt b e t a e n e rg i e s a n d a b u n da n ce.                     
(See T a b l e 3.0-2).
CF Xe-133  =  Th e expec t ed RIA r e s po n s e t o a g i v e n X e-133 e q u i v a l e nt co n ce nt r a ti o n , in &#xb5;C i/m l/cpm. 1RIA-3 7 = 1.01 E-0 8 &#xb5;C i/m l/cpm , 3RIA-3 7 =  4.20 E-0 8 &#xb5;C i/m l/cpm , 1RIA-3 8 a n d 3RIA-3 8  =  1.34 E-03 &#xb5;C i/m l/cpm.
1.5    =  An ad j us t me nt f ac t o r t o acco u nt f o r expec t ed m in o r v a r i a ti o n s in efflu e nt  co n ce nt r a ti o n a n d RIA b ac k gr o u n d.
bk g        =
Th e r ad i a ti o n mo nit o r b ac k gr o u n d r ead in g, in cpm. 


W h e n t h e r e l ea s e pa t hw a y i s fr om a n y U nit 1 W GDT (A-D), a n d t h e X e-133 e q u i v a l e nt co n ce nt r a ti o n i s l e ss t h a n 2.8 E-01 &#xb5;C i/m l, t h e 1&2 RIA-3 8 s e t po int i s e s t a b l i sh ed a t 313 cpm , a n d t h e 1&2 RIA-3 7 s e t po int i s ca l c ul a t ed us in g E q u a ti o n 3.7.
Oconee Nuclear Station                                            January, 2007 Offsite Dose Calculation Manual (ODCM)                            Revision 47 Table 3.0-2 Xe-133 Equivalents Isotope            Equivalence Factor Kr-83m                        0 Kr-85m                      2.48 Kr-85                        2.56 Kr-87                        2.93 Kr-88                        2.78 Kr-89                        2.93 Kr-90                        2.93 Xe-131m                      1.69 Xe-133m                      1.99 Xe-133                       1.0 Xe-135m                      0.83 Xe-135                      2.63 Xe-137                      2.93 Xe-138                      2.93 Ar-41                        2.82 C-11                         2.70 Section 3 - Page 11
W h e n t h e r e l ea s e pa t hw a y i s fr om a n y U nit 1 W GDT (A-D), a n d t h e X e-133 e q u i v a l e nt co n ce nt r a ti o n i s gr ea t e r t h a n 2.8 E-01 &#xb5;C i/m l, t h e 1&2 RIA-3 7 s e t po int i s e s t a b l i sh ed a s o ffs ca l e h igh, a n d t h e 1&2 RIA-3 8 s e t po int i s ca l c ul a t ed us in g E q u a ti o n 3.7.
W h e n t h e r e l ea s e pa t hw a y i s fr om a n y U nit 3 W GDT (A-C), a n d t h e X e-133 e q u i v a l e nt co n ce nt r a ti o n i s l e ss t h a n 2.8 E-01 &#xb5;C i/m l, t h e 3 RIA-3 8 s e t po int i s e s t a b l i sh ed a t 313 cpm , a n d t h e 3 RIA-3 7 s e t po int i s ca l c ul a t ed us in g E q u a ti o n 3.7.
W h e n t h e r e l ea s e pa t hw a y i s fr om a n y U nit 3 W GDT (A-C), a n d t h e X e-133 e q u i v a l e nt co n ce nt r a ti o n i s gr ea t e r t h a n 2.8 E-01 &#xb5;C i/m l, t h e 3 RIA-3 7 s e t po int i s e s t a b l i sh ed a s o ffs ca l e h igh, a n d t h e 3 RIA-3 8 s e t po int i s ca l c ul a t ed us in g E q u a ti o n 3.7.
W h e n t h e r e a r e n o n o b l e g a s e s p r e s e nt in t h e W GDT samp l e , t h e RIA-3 7 s e t po int i s s e t t o f i v e ti me s (5X) t h e RIA-3 7 b ac k gr o u n d r ead in g.
O co n ee Nu c l ea r S t a ti o n    J a n u ary, 200 7 Offs it e D o s e Ca l c ul a ti o n M a n u a l (OD C M)    R e v i s i o n 4 7  Sec ti o n 3 - P a g e 11 Ta ble 3.0-2  X e-133 E q uivalents


Isotope E quivalence Factor K r-8 3 m 0 K r-85 m 2.4 8 K r-85 2.56 K r-8 7 2.9 3 K r-88 2.7 8 K r-89 2.9 3 K r-9 0 2.9 3 X e-131 m 1.69 X e-133 m 1.99 X e-133 1.0 X e-13 5 m 0.8 3 X e-13 5 2.6 3 X e-13 7 2.9 3 X e-13 8 2.9 3 A r-41 2.8 2 C-11 2.7 0 O co n ee Nu c l ea r S t a ti o n    J a n u ary, 200 7 Offs it e D o s e Ca l c ul a ti o n M a n u a l (OD C M)
Oconee Nuclear Station                                                    January, 2007 Offsite Dose Calculation Manual (ODCM)                                      Revision 47 4.0 EFFLUENT DOSE MODELS The effluent dose models used to show compliance with 10CFR50, Appendix I ALARA design objectives, 40CFR190 fuel cycle dose limits, and the dose values given in station SLCs are based on the methodology given in NUREG-0133 and Regulatory Guide 1.109.
R e v i s i o n 4 7 Sec ti o n 4 - P a g e 1 4.0 EFFLUENT DOSE MODELS
Dose contributions to the maximum individual shall be calculated at least every 31 days, quarterly, and annually using the RETDAS computer code which implements the ODCM methodology. RETDAS, Radioactive Effluent Tracking and Dose Assessment Software, is a database application designed by Canberra Industries, Inc. to automate many of the tasks required in the administration of effluent releases at Oconee. RETDAS performs normal operation effluent dose assessment using NUREG-0133 and Regulatory Guide 1.109 methodology.
Station long-term historical and dose projection calculations are performed periodically to determine the station's status with respect to meeting annual ALARA goals specified in the Oconee SLCs. Such calculations are used to verify that adequate margin remains during a report period to allow normal station and radwaste system operation, including anticipated operational occurrences, for the remainder of the report period without exceeding applicable goals. Station 31-day dose projections that are used to assess the need to reduce effluent releases with the Gaseous Waste (GW) or Liquid Waste (LW) systems as required in the Oconee SLCs are estimated by the previous month's calculated dose results.
Fuel cycle dose calculations shall be performed annually or as required by special reports.
Dose contributions shall be calculated using the RETDAS computer program.
4.0.1 LIQUID EFFLUENT DOSE MODEL FOR THE MAXIMUM EXPOSED INDIVIDUAL Of the possible exposure pathways in the aquatic environment, only three contribute significantly to the total dose; these pathways are ingestion of potable water and aquatic foods, and direct exposure from radioactivity deposited on the shoreline. The dose contribution from these pathways for measured quantities of radioactive materials identified in liquid effluents released to unrestricted areas shall be calculated for the maximum exposed individual in each age group using the methodology provided in this section.
Liquid waste processed by the LW system can be released to the environment at Oconee from two liquid discharge points; (1) directly to the Keowee Tailrace through RIA-33 and (2) to the Chemical Treatment Pond #3 discharge point into the Keowee River (See Figure 2.0-1). Liquid dose calculations for the maximum exposed individual are performed and documented in the Annual Effluent Release Report for both locations using the applicable activity release and dilution data for each liquid effluent release point. The primary liquid effluent discharge point for Oconee is to the Keowee Tailrace Section 4 - Page 1


Th e efflu e nt do s e mode ls us ed t o sh o w comp l i a n ce w it h 10 CF R 5 0, A ppe n d i x I A LARA de s i g n o bj ec ti v e s, 40 CF R 1 9 0 fu e l c y c l e do s e l i m it s, a n d t h e do s e v a lu e s g i v e n in s t a ti o n S L C s a r e b a s ed o n t h e me t h odo l o gy g i v e n in NU R E G-0133 a n d R egul a t o ry Gu i de 1.10 9. D o s e co nt r i b u ti o n s t o t h e max i m u m in d i v i d u a l sh a ll b e ca l c ul a t ed a t l ea s t e v e ry 31 days, q u a r t erly, a n d a nn u ally us in g t h e R E TD A S comp u t e r code wh i c h i mp leme nt s t h e OD C M me t h odo l ogy. R E TD A S , R ad i oac ti v e Efflu e nt T r ac k in g a n d D o s e A ss e ss me nt S o f t w a r e , i s a da t a b a s e app l i ca ti o n de s i g n ed b y Ca n b e rr a In d us t r i e s, In c. t o a u t oma t e ma n y o f t h e t a s k s r e q u i r ed in t h e adm ini s t r a ti o n o f efflu e nt r e l ea s e s a t O co n ee. R E TD A S pe rf o r m s n o r ma l ope r a ti o n efflu e nt do s e a ss e ss me nt us in g NU R E G-0133 a n d R egul a t o ry Gu i de 1.10 9 me t h odo l ogy.
Oconee Nuclear Station                                                    January, 2007 Offsite Dose Calculation Manual (ODCM)                                     Revision 47 through RIA-33. In general, only low activity tritium releases (<1% station total) occur through the Chemical Treatment Pond #3 discharge point into the Keowee River. Dose calculations are performed for each of the two liquid discharge points for dose reporting purposes. The highest calculated dose from the two dose calculations is used to define the maximum individual dose from liquid releases at Oconee.
S t a ti o n l o n g-t e r m h i s t o r i ca l a n d do s e p r o j ec ti o n ca l c ul a ti o n s a r e pe rf o rmed pe r i od i cally t o de t e r m in e t h e s t a ti o n's s t a t us w it h r e spec t t o mee tin g a nn u a l A LARA g oa ls s pec i f i ed in t h e O co n ee S L C s. S u c h ca l c ul a ti o n s a r e us ed t o v e r i fy t h a t ade q u a t e ma rg in rema in s d ur in g a r epo r t pe r i od t o a ll o w n o r ma l s t a ti o n a n d r ad w a s t e sys t em ope r a ti o n , in c lu d in g a nti c i pa t ed ope r a ti o n a l occ urr e n ce s, f o r t h e r ema in de r o f t h e r epo r t pe r i od w it h o u t exceed in g app l i ca b l e g oa ls. S t a ti o n 31-da y do s e p r o j ec ti o n s t h a t a r e us ed t o a ss e ss t h e n eed t o r ed u ce efflu e nt r e l ea s e s w it h t h e G a s eo us W a s t e (G W) o r L i q u i d W a s t e (L W) sys t em s a s r e q u i r ed in t h e O co n ee S L C s a r e e s ti ma t ed b y t h e p r e v i o us mo nt h's ca l c ul a t ed do s e r e sul t s.
Section 4 - Page 2
F u e l c y c l e do s e ca l c ul a ti o n s sh a ll b e pe rf o rmed a nn u ally o r a s r e q u i r ed b y s pec i a l r epo r t s. D o s e co nt r i b u ti o n s sh a ll b e ca l c ul a t ed us in g t h e R E TD A S comp u t e r p r o gr am. 4.0.1  LI QUID EFFLUENT DOSE MODEL FOR THE MA XIMUM E XPOSED INDIVIDUAL Of t h e po ss i b l e expo sur e pa t hw a ys in t h e a q u a ti c e n v i r o n me nt , o n ly t hr ee co nt r i b u t e s i g ni f i ca nt ly t o t h e t o t a l do s e; t h e s e pa t hw a ys a r e in g e s ti o n o f po t a b l e w a t e r a n d a q u a ti c f ood s, a n d d i r ec t expo sur e fr om r ad ioac ti v it y depo s it ed o n t h e sh o r e l in e. Th e do s e co nt r i b u ti o n fr om t h e s e pa t hw a ys f o r mea sur ed q u a ntiti e s o f r ad i oac ti v e ma t e r i a ls i de nti f i ed in l i q u i d efflu e nt s r e l ea s ed t o u n r e s t r i c t ed a r ea s sh a ll b e ca l c ul a t ed f o r t h e max i m u m expo s ed in d i v i d u a l in eac h a g e gr o u p us in g t h e me t h odo l o gy p r o v i ded in t h i s s ec ti o n.
L i q u i d w a s t e p r oce ss ed b y t h e L W sys t em ca n b e r e l ea s ed t o t h e e n v i r o n me nt a t O co n ee fr om t w o l i q u i d d i s c h a rg e po int s; (1) d i r ec t ly t o t h e K eo w ee T a i lrace t hr ough RIA-33 a n d (2) t o t h e C h em i ca l Tr ea t me nt P o n d #3 d i s c h a rg e po int int o t h e K eo w ee Ri v e r (See F igur e 2.0-1). L i q u i d do s e ca l c ul a ti o n s f o r t h e max i m u m expo s ed in d i v i d u a l a r e pe rf o rmed a n d doc u me nt ed in t h e Ann u a l Efflu e nt R e l ea s e R epo r t f o r b o t h l oca ti o n s us in g t h e app l i ca b l e ac ti v it y r e l ea s e a n d d i lu ti o n da t a f o r eac h l i q u i d efflu e nt r e l ea s e po int. Th e p r i ma ry l i q u i d efflu e nt d i s c h a rg e point f o r O co n ee i s t o t h e K eo w ee T a i lrace O co n ee Nu c l ea r S t a ti o n    J a n u ary, 200 7 Offs it e D o s e Ca l c ul a ti o n M a n u a l (OD C M)
R e v i s i o n 4 7 Sec ti o n 4 - P a g e 2 t hr ough RIA-33. In g e n e r a l, o n ly l o w ac ti v it y t riti u m r e l ea s e s (<1% s t a ti o n t o t a l) occ ur t hr ough t h e C h em i ca l Tr ea t me nt P o n d #3 d i s c h a rg e po int int o t h e K eo w ee Ri v e r. D o s e ca l c ul a ti o n s a r e pe rf o rmed f o r eac h o f t h e t w o l i q u i d d i s c h a rg e po int s f o r do s e r epo r tin g p ur po s e s. Th e h i gh e s t ca l c ul a t ed do s e fr om t h e t w o do s e ca l c ul a ti o n s i s us ed t o de f in e t h e max i m u m in d i v i d u a l do s e fr om l i q u i d r e l ea s e s a t O co n ee.
Oconee Nuclear Station    January, 2007 Offsite Dose Calculation Manual (ODCM)                                                                            Revision 47 Section 4 - Page 3 Liquid Dose CalculationsThe following equation is used for calculating liquid dose to the maximum exposed individual at each of the two liquid effluent release points: 1 w n i i oapi p oa D F t C A Dose F f f F nFormula:  adapted from NUREG-0133, pages 15-17. Where:
Dose oa The cumulative dose commitment for organ o and age group a, from the liquid effluent for the total time period, t. (mrem)
A oapi Dose commitment factor for organ o, age group a, pathway p, and nuclide i (mrem/hr per Ci/ml).  (See Appendices C through F for age group and pathway specific dose commitment factors).
C i The average concentration of nuclide i, in undiluted liquid effluent during the time period, t. (Ci/ml) tThe length of time over which C i and F n are averaged for all liquid releases. (hr)
F n The near field average dilution factor for C i during the period of interest, t. Includes the recirculation factor. (dimensionless) fAverage liquid radwaste flow during the period of interest, t. (gpm) F Average dilution flow during the period of interest, t. (gpm) Normally 3.41E+04 gpm (76 cfs, based on a leakage rate of 38 cfs (19 cfs per Keowee Hydro unit, plus the Keowee Hydro Fire Protection liquid waste release mixing line whose flow rate is 38 cfs)). No dilution credit is taken for the relatively short period of time during the year that the Keowee Hydro units are running.Recirculation factor. (dimensionless)
* D w Dilution factor from the near field area to the potable water intake; 
= 30.0 for Oconee. This factor applies to the potable water pathway only. The nearest potable water intake to Oconee is located at the Andersen water intake approximately 31.5 miles from the site on a separate arm of Lake Hartwell. From a hydrology standpoint the Andersen water


intake should not be significantly affected by liquid effluent discharges from Oconee. 30.0 is a conservatively small dilution factor based on environmental sample data.  
Oconee Nuclear Station                                                        January, 2007 Offsite Dose Calculation Manual (ODCM)                                          Revision 47 Liquid Dose Calculations The following equation is used for calculating liquid dose to the maximum exposed individual at each of the two liquid effluent release points:
*The recirculation factor accounts for the fraction of discharged water reused by the station. Liquid effluent discharge cannot be recirculated back into the Oconee station.
1 Dose oa p    i Aoapi u Ci u 't u Fn u Dw f
Fn            uV f F Formula: adapted from NUREG-0133, pages 15-17. Where:
Doseoa The cumulative dose commitment for organ o and age group a, from the liquid effluent for the total time period, 't. (mrem)
Aoapi Dose commitment factor for organ o, age group a, pathway p, and nuclide i (mrem/hr per PCi/ml). (See Appendices C through F for age group and pathway specific dose commitment factors).
Ci The average concentration of nuclide i, in undiluted liquid effluent during the time period, 't. (PCi/ml)
          't The length of time over which Ci and Fn are averaged for all liquid releases. (hr)
Fn The near field average dilution factor for Ci during the period of interest,
                't. Includes the recirculation factor. (dimensionless) f Average liquid radwaste flow during the period of interest, 't. (gpm)
F Average dilution flow during the period of interest, 't. (gpm)
Normally 3.41E+04 gpm (76 cfs, based on a leakage rate of 38 cfs (19 cfs per Keowee Hydro unit, plus the Keowee Hydro Fire Protection liquid waste release mixing line whose flow rate is 38 cfs)). No dilution credit is taken for the relatively short period of time during the year that the Keowee Hydro units are running.
V Recirculation factor. (dimensionless)
* Dw Dilution factor from the near field area to the potable water intake;
                = 30.0 for Oconee. This factor applies to the potable water pathway only. The nearest potable water intake to Oconee is located at the Andersen water intake approximately 31.5 miles from the site on a separate arm of Lake Hartwell. From a hydrology standpoint the Andersen water intake should not be significantly affected by liquid effluent discharges from Oconee. 30.0 is a conservatively small dilution factor based on environmental sample data.
* The recirculation factor accounts for the fraction of discharged water reused by the station. Liquid effluent discharge cannot be recirculated back into the Oconee station.
Therefore, the recirculation factor is 1.0 at Oconee.
Therefore, the recirculation factor is 1.0 at Oconee.
O co n ee Nu c l ea r S t a ti o n    J a n u ary, 200 7 Offs it e D o s e Ca l c ul a ti o n M a n u a l (OD C M)
Section 4 - Page 3
R e v i s i o n 4 7 Sec ti o n
 
Oconee Nuclear Station                                                      January, 2007 Offsite Dose Calculation Manual (ODCM)                                      Revision 47 Derivation of Liquid Dose Commitment Factors (Aoapi)
Potable Water
                                                    - i t p Aoapi = 1.14 x105 x U aw x Daoi x e Formula: from NUREG-0133, page 16 and Regulatory Guide 1.109, page 1.109-12.
Where:
Aoapi Dose commitment factor for organ o, age group a, pathway p, and nuclide i, (mrem/hr per Ci/ml). (See Appendices C through F for age group and pathway specific dose commitment factors).
5 1.14x10 Units conversion factor (pCi-yr-ml)/(Ci-hr-kg).
Uaw Water consumption rate in liters per year for age group a. From Table E-5, Regulatory Guide 1.109.
Adult - 730 Teen - 510 Child - 510 Infant - 330 Daoi Dose factor for age group a, organ o, nuclide i, in mrem/pCi. From tables E-11 through E-14 of Regulatory Guide 1.109.
i      Decay constant for nuclide i, in sec-1.
tp      Environmental transit time from release to receptor. Default =
4.32E+04 sec (12 hours). From Regulatory Guide 1.109, Table E-15.


Oc o n ee Nucl e ar Stati o n    J a nu ar y, 2007 O ff s it e D o s e C alcul ati o n M a nu a l (O DCM)    R e vi s i o n 47  S e c ti o n 5 - P ag e 1  5.0 FUEL CYCLE CALCULATIONS In a cc o r d a nc e with th e r e q u ir e m e n t s o f 40C FR 1 9 0, th e a nnu a l d o s e c o mm it m e n t t o a ny m e m b e r o f th e g e n e ra l p u b l i c s ha ll b e c alcul at e d t o a ssu r e that d o s e s ar e l i m it e d t o 2 5 m i ll ir e ms t o th e t o ta l b o dy o r a ny orga n with th e e xc e pti o n o f th e th y r o i d whi c h i s l i m it e d t o 7 5 m i ll ir e ms. In a cc o r d a nc e with th e r e q u ir e m e n t s o f th e S e l e c t e d Li c e ns ee C o mm it m e n t s, th e a nnu a l d o s e c o mm it m e n t s ha ll a ls o b e c alcul at e d a ny ti m e that o n e o f th e q u art e r ly d o s e l i m it s o f th e S e l e c t e d Li c e ns ee C o mm it m e n t s i s e xc ee d e d; th e s e a nnu a l d o s e c o mm it m e n t s m a y n o t j us t b e c alcul at e d f o r th e c a l e nd ar y e ar.
Oconee Nuclear Station                                                       January, 2007 Offsite Dose Calculation Manual (ODCM)                                       Revision 47 6.0 ENVIRONMENTAL LOCATIONS 6.0.1 SITE DESCRIPTION AND SAMPLE LOCATIONS Oconee Nuclear Station (ONS) is located                 in Oconee County, South Carolina, approximately 8 miles northeast of Seneca, South Carolina, on the shore         of Lake Keowee. This lake was formed by damming the Keowee and Little Rivers in that location. Immediately to the south is the U.S. Government Hartwell Project. The Keowee Hydroelectric Plant near the station joins Lake Keowee and the upper reaches of Lake Hartwell.
T h e " Ura n i um f u e l cycl e" i s d e fi n e d i n 40C FR P art 1 9 0.02(b) a s: 
To the north, the Jocassee Hydroelectric Plant joins Lake Jocassee and Lake Keowee. Jocassee is a pumped storage plant. The ONS exclusion area boundary is 1 mile.
"Ura n i um f u e l cycl e m e a ns th e o p erati o ns o f m i ll i n g o r u ra n i um o r e , c h e m i c a l c o n v e r s i o n o f u ra n i um, i s o t o pi c e n ri c h m e n t o f u ra n i um, fa b ri cati o n o f u ra n i um f u e l, g e n erati o n o f e l e ctri c it y b y a light-wat e r-c oo l e d nucl e ar p o w e r p l a n t us i n g u ra n i um f u e l, a nd r e pr o c e ss i n g o f s p e n t u ra n i um f u e l, t o th e e x t e n t that th e s e d ir e c t ly su pp o rt th e pr o duc ti o n o f e l e ctri c a l p o w e r f o r p u b l i c us e u ti l i z i n g nucl e ar e n e rg y, b u t exclud e s m i n i n g o p erati o ns, o p erati o ns at wa s t e d i s p o s a l s it e s, tra ns p ortati o n o f a ny ra d i o a c tiv e m at eria l i n su pp o rt o f th e s e o p erati o ns, a nd th e r e us e o f r e c o v e r e d n o n-u ra n i um s p e c ia l nucl e ar a nd b y-pr o duc t m at eria ls fr o m th e cycl e."
Table 6.0-1 and Table 6.0-2 define the sampling and TLD locations for the Oconee Radiological Monitoring Program. Figure 6.0-1 and Figure 6.0-2 illustrate these locations as compared to Oconee Nuclear Station.
B a s e d o n thi s d e fi n iti o n o f th e f u e l cycl e a nd th e i n f o r mati o n i n 10C FR 5 1, T a b l e S-3, a nd W a s h-124 8 , th e ra d i o l o gi c a l i m pa c t o f th e f o ll o wi n g o p erati o ns ha s b ee n a ss e ss e d f o r Oc o n ee Nucl e ar Stati o n:  5.0.1  MILLING N o m i ll i n g o p erati o ns occu r withi n fift y m i l e s o f th e Oc o n ee Nucl e ar Stati o n. 5.0.2  CONVERSION N o u ra n i um h e x af lu o ri d e pr o duc ti o n occu r s withi n fift y m i l e s o f th e Oc o n ee Nucl e ar Stati o n. 5.0.3  ENRICHMENT N o u ra n i um e n ri c h m e n t o p erati o ns occu r withi n fift y m i l e s o f th e Oc o n ee Nucl e ar Stati o n. 5.0.4  FUEL FABRICATION N o f u e l fa b ri cati o n o p erati o ns o ccu r withi n fift y m i l e s o f th e Oc o n ee Nucl e ar Stati o n.
Air Sampling at Oconee Nuclear Station 6.0.2 LAND USE CENSUS DATA The Annual Land Use Census, required by Selected Licensee Commitments, is performed to ensure that changes in the use of areas at or beyond the site boundary are identified, and that modifications to the Radiological Environmental Monitoring Program are made if required by changes in land use. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10CFR50. Results are shown in Table 6.0-3 and Figure 6.0-3.
Oc o n ee Nucl e ar Stati o n    J a nu ar y, 2007 O ff s it e D o s e C alcul ati o n M a nu a l (O DCM)    R e vi s i o n 47  S e c ti o n 5 - P ag e 2 5.0.5  NUCLEAR PO WER PRODUCTION T h e pr o duc ti o n o f e l e ctri c it y f o r p u b l i c us e us i n g light-wat e r-c oo l e d nucl e ar p o w e r stati o ns r e sul t s i n i nc r e m e n t s o f d o s e t o i nd ivi du a ls withi n fift y m i l e s o f a ny stati o n du e t o l i q u i d a nd ga s e o us e ff lu e n t r e l e a s e s a nd d ir e c t ra diati o n o r s k ys hi n e. T h e i nc r e m e n t s o f d o s e r e sul ti n g fr o m l i q u i d a nd ga s e o us e ff lu e n t r e l e a s e s wi ll b e c alcul at e d us i n g th e O D CM m e th o d o l o g y i m p l e m e n t e d i n th e R ET D A S c o m p u t e r pr ogra m. T h e d o s e fr o m d ir e c t ra diati o n, s k ys hi n e , a nd ra diati o n fr o m th e stati o n s t o rag e fa c i l iti e s ha s b ee n e s ti m at e d us i n g c o ns ervativ e a ssum pti o ns (s ee S e c ti o n 4.0.3).
Section 6 - Page 1
In c ertai n s it uati o ns m o r e tha n o n e nucl e ar p o w e r stati o n s it e m a y c o ntri b u t e t o th e d o s e s t o b e c o ns i d e r e d i n m a k i n g f u e l cycl e d o s e a ss essm e n t s i n a cc o r d a nc e with 40C FR 1 9 0. H o w e v e r , s i nc e th e Oc o n ee nucl e ar stati o n i s l o c at e d o v e r 100 m i l e s fr o m th e Cataw b a a nd McGu ir e nucl e ar stati o ns, th e r e lativ e d o s e c o ntri b u ti o n fr o m e a c h s it e t o th e o th e r i s i ns ig nifi c a n t , a nd c a n b e ig n o r e d i n a ss e ss i n g c o m p l ia nc e with 40C FR 1 9 0. 5.0.6  FUEL REPROCESSING N o f u e l r e pr o c e ss i n g o p erati o ns o ccu r withi n fift y m i l e s o f th e Oc o n ee Nucl e ar Stati o n. 5.0.7  40CFR1 90 TOTAL DOSE DETERMINATION T o summ ari z e , only d o s e i nc r e m e n t s fr o m nucl e ar p o w e r pr o duc ti o n o p erati o ns (S e c ti o n 5.0.5) n ee d b e c o ns i d e r e d i n c alculati o ns t o d e m o nstrat e c o m p l ia nc e with th e r e q u ir e m e n t s o f 40C FR 1 9 0. T h e f u e l cycl e d o s e a ss e ssm e n t s f o r Oc o n ee Nucl e ar Stati o n only i nclud e l i q u i d a nd ga s e o us d o s e c o ntri b u ti o ns fr o m Oc o n ee a nd d o s e fr o m Oc o n ee's ISFS I s i nc e n o o th e r u ra n i um f u e l cycl e fa c i l it y c o ntri b u t e s s ig nifi c a n t ly t o Oc o n ee's m a x i mum e x p o s e d i ndivi du a l. F o r thi s d o s e a ss e ssm e n t , th e t o ta l b o dy a nd m a x imum o rga n d o s e c o ntri b u ti o ns t o th e m a x i mum e x p o s e d i nd ivi du a l fr o m Oc o n ee's l i q u i d a nd ga s e o us e ff lu e n t s ar e e s ti m at e d us i n g th e f o ll o wi n g c alculati o ns:  )(    )(    )(g D l D T D wb wb wb+=  )(    )(    )(g D l D T D mo mo mo+=  w here:  D wb(T)  =  T otal estimated fuel cycle whole b ody dose commitment resulting from the com bined li q uid and gaseous effluents of Oconee during the calendar year of interest, in mrem. D mo(T)  =  T otal estimated fuel cycle maximum organ dose commitment resulting from the com bined li q uid and gaseous effluents of Oconee during the calendar year of interest, in mrem.
Oconee Nuclear Station     January, 2007 Offsite Dose Calculation Manual (O D CM)     Revision 47   Section 6 - Page 1  6.0 ENVIRONMENTAL LOCATIONS 6.0.1 SITE DESCRIPTION AND SAMPLE LOCATIONS Oconee Nuclear Station (ONS) is located     in Oconee County, South Carolina, approximately 8 miles   northeast   of Seneca, South Carolina, on   the   shore   of La k e Keowee. T his la k e was formed b y damming the Keowee and Little Rivers in that location. Immediately to the south is the U.S. Government Hartwell Pro ject. T he Keowee Hydroelectric Plant near the station j oins La k e Keowee and the upper reaches of La k e Hartwell. T o the north, the J ocassee Hydroelectric Plant joins La k e Jocassee and La k e Keowee. Jocassee is a pumped storage plant. T he ONS exclusion area boundary is 1 mile.
T a b le 6.0-1 and T a b le 6.0-2 define the sampling and T L D locations for the Oconee Radiological Monitoring Program. Figure 6.0-1 and Figure 6.0-2 illustrate these locations as compared to Oconee Nuclear Station.    


6.0.2  LAND USE CENSUS DATA T he Annual Land Use Census, re q uired b y Selected Licensee Commitments, is performed to ensure that changes in the use of areas at or beyond the site boundary are identified, and that modifications to the Radiological Environmental Monitoring Program are made if re q uired b y changes in land use. This census satisfies the re q uirements of Section IV.B.3 of Appendix I to 10CFR 5 0. Results are shown in T a b le 6.0-3 and Figure 6.0-3. Air Sampling at Oconee Nuclear Station Oconee Nuclear Station    January, 2007 Offsite Dose Calculation Manual (O D CM)     Revision 47   Section 6 - Page 2 TABLE 6.0-1 OCONEE RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS
Oconee Nuclear Station                                                                       January, 2007 Offsite Dose Calculation Manual (ODCM)                                                       Revision 47 TABLE 6.0-1 OCONEE RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS Table 6.0-1 Codes W            Weekly        SM          Semimonthly BW            BiWeekly      Q            Quarterly M            Monthly        SA          Semiannually C            Control Site                                                          Air Rad. &  Surface Drinking Shoreline  Fish  Milk  Broadleaf Location Description*                  Particulate  Water  Water  Sediment                Vegetation 060          Greenville Water Intake Road (2.58 mi NNE)            W                                                  M 060          Greenville Water Intake Road (3.23 NE)                                    M 060 C **    Greenville Water Intake Road (2.28 NE)                                                    SA 062 C        Lake Keowee Hydro Intake (0.85 mi ENE)                          M Lake Hartwell Hwy 183 Bridge 063          (0.80 mi ESE) [000.7]                                                            SA      SA 063.1        Lake Hartwell Hwy 183 (0.79 mi E)                                M 064 C        Seneca (6.67 mi SSW) [004.1]                                            M 066          Anderson (18.9 mi SSE) [012]                                            M Lawrence Ramsey Bridge Hwy 27 067          (4.34 mi SSE) [005.2]                                                            SA      SA 068 C        High Falls County Park (1.82 mi W)                                                SA 071 C        Clemson Dairy (10.2 mi SSE) [006.3]                                                              SM 074          Keowee Key Resort (2.36 mi NNW)                        W 077          Skimmer Wall (1.00 mi SW)                              W                                                  M 078          Recreation Site (0.58 mi WSW)                          W 079          Keowee Dam (0.56 mi NE)                                W                                                  M 081 C        Clemson Operations Center (9.33 mi SE)                W                                                  M
* GPS data reflect approximate accuracy to within 2-5 meters. GPS field measurements were taken as close as possible to the item of interest.
        ** Control for Fish Only
[ ] Location Numbers prior to 1984 Section 6 - Page 2


T a b le 6.0-1 Codes W W ee k ly SM Semimonthly B W Bi W ee k ly Q Quarterly M Monthly SA Semiannually C Control Site # Location Description
Oconee Nuclear Station                                                                      January, 2007 Offsite Dose Calculation Manual (ODCM)                                                      Revision 47 TABLE 6.0-2 OCONEE RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS (TLD SITES)
* Air Rad. & Particulate  Surface Water Drin k ing Water Shoreline Sediment Fish Mil k Broadleaf Vegetation 0 6 0  Greenville Water Inta k e Road (2.58 mi NNE) W     M 0 6 0 Greenville Water Inta k e Road (3.23 NE)  M     0 6 0 C ** Greenville Water Inta k e Road (2.2 8 NE)     SA  0 6 2 C La k e Keowee Hydro Inta k e (0.85 mi ENE)  M       0 6 3 La k e Hartwell Hwy 1 8 3 Bridge  (0.8 0 mi ESE)  [000.7]     SA  SA   0 63.1 La k e Hartwell Hwy 1 8 3 (0.7 9 mi E) M     0 6 4 C Seneca (6.6 7 mi SS W) [004.1]   M     0 66 Anderson (1 8.9 mi SSE) [012]  M      0 6 7 Lawrence Ramsey Bridge Hwy 27 (4.34 mi SSE) [00 5.2]     SA  SA   068 C High Falls County Par k (1.8 2 mi W)   SA   071 C Clemson Dairy (10.2 mi SSE) [00 6.3]     SM  074 Keowee K ey Resort (2.3 6 mi NN W) W      077 S kimmer Wall (1.00 mi S W) W     M 07 8 Recreation Site (0.58 mi W S W) W       07 9 Keowee D am (0.56 mi NE) W     M 0 8 1 C Clemson Operations Center (9.33 mi SE) W      M
Site          Location*            Distance      Sector      Site               Location*     Distance    Sector MICROWAVE TOWER, 020      SITE BOUNDARY            0.16 miles      N          040                SIX MILE     4.74 miles     E 021      SITE BOUNDARY            0.25 miles      NNE        041          JCT HWY 101 & 133  4.25 miles    ESE LAWRENCE CHAPEL 022      SITE BOUNDARY            0.53 miles      NE         042          CHURCH, HWY 133    4.93 miles     SE HWY 291 AT 023      SITE BOUNDARY            0.93 miles      ENE         043          ISSAQUEENA PARK    4.09 miles    SSE HWY 130 AT LITTLE 024       SITE BOUNDARY            0.81 miles        E        044              RIVER DAM      3.96 miles      S TERMINUS OF HWY 588 025      SITE BOUNDARY            0.42 miles      ESE        045        AT CROOKED CREEK    4.78 miles    SSW HWY 188 AT 026      SITE BOUNDARY            0.34 miles      SE        046            CROOKED CREEK    4.61 miles    SW NEW HOPE CHURCH, 027      SITE BOUNDARY            0.49 miles     SSE        047                HWY 188      3.58 miles   WSW 028      SITE BOUNDARY            0.46 miles        S        048          JCT HWY 175 & 188 3.64 miles    W 029      SITE BOUNDARY            0.56 miles      SSW        049            JCT HWY 201 & 92 3.60 miles  WNW STAMP CREEK LANDING, 030      SITE BOUNDARY            0.42 miles     SW          050            END OF HWY 92    3.53 miles    NW HWY 128, 1 MILE N OF 031      SITE BOUNDARY            0.27 miles    WSW          051                HWY 130      4.64 miles  NNW DPC BRANCH OFFICE 076      SITE BOUNDARY            0.19 miles      W         052            SITE - PICKENS  12.4 miles    ENE DPC BRANCH OFFICE 032      SITE BOUNDARY            0.19 miles    WNW          053            SITE - LIBERTY   11.7 miles     E POST OFFICE - HWY 93 033      SITE BOUNDARY            0.21 miles    WNW          054                NORRIS      8.60 miles    ESE CLEMSON 034      SITE BOUNDARY            0.22 miles      NW          055        METEOROLOGY PLOT    9.27 miles    SSE 035      SITE BOUNDARY            0.17 miles     NNW          056      WATER TOWER - SENECA   7.30 miles   SSW OCONEE MEMORIAL 036   MILE CREEK LANDING          4.32 miles      N          057                HOSPITAL      8.42 miles    SW KEOWEE CHURCH,                                                        BRANCH RD 037          HWY 327              4.85 miles      NNE        058 C     SUBSTATION, WALHALLA  9.39 miles  WSW CONVENIENCE MART, 038     JCT HWY 183 & 133        4.24 miles      NE        059       TAMASSEE DAR SCHOOL    9.20 miles    NW HWY 133, 1 MILE EAST                                                      CLEMSON 039    OF JCT HWY 183 & 133        4.02 miles     ENE        081 C       OPERATIONS CENTER    9.33 miles    SE C = Control
* GPS data reflect approximate accuracy to within 2-5 meters. GPS field measurements were ta k en as     close as possi b le to the item of interest. **  Control for Fish Only [ ]  Location Num b ers prior to 1 98 4 Oconee Nuclear Station    January, 2007 Offsite Dose Calculation Manual (O D CM)    Revision 47  Section 6 - Page 3 TABLE 6.0-2  OCONEE RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS (TLD SITES)
* GPS data reflect approximate accuracy to within 2-5 meters. GPS field measurements were taken as close as possible to the item of interest.
Section 6 - Page 3


Site # Location* Distance Sector Site  # Location* Distance Sector  020  SI T E BOUN DARY  0.1 6 miles  N  040 MICRO W AVE T O W ER, SI X MILE  4.74 miles  E  021  SI T E BOUN DARY  0.2 5 miles  NNE  041  J C T H W Y 101 & 133  4.2 5 miles  ESE  022  SI T E BOUN DARY  0.5 3 miles  NE  042 LA WRENCE CHAPEL CHURCH, H W Y 133  4.9 3 miles  SE  023  SI T E BOUN DARY  0.9 3 miles  ENE  043 H W Y 2 9 1 A T  ISSA QUEENA PAR K  4.0 9 miles  SSE  024  SI T E BOUN DARY  0.8 1 miles  E  044 H W Y 130 A T LI TT LE RIVER D AM  3.96 miles  S  02 5  SI T E BOUN DARY  0.42 miles  ESE  04 5 TERMINUS OF H W Y 588  A T CROO K E D CREE K  4.7 8 miles  SS W  02 6  SI T E BOUN DARY  0.34 miles  SE  04 6 H W Y 1 88 A T  CROO K E D CREE K  4.6 1 miles  S W  027  SI T E BOUN DARY  0.4 9 miles  SSE  047 NE W HOPE CHURCH, H W Y 1 88  3.58 miles  W S W  02 8  SI T E BOUN DARY  0.4 6 miles  S  04 8  J C T H W Y 175 & 188  3.6 4 miles  W  02 9  SI T E BOUN DARY  0.56 miles  SS W  04 9  J C T H W Y 201 & 9 2  3.6 0 miles  W N W  030  SI T E BOUN DARY  0.42 miles  S W  0 5 0 S TAMP CREE K LAN DING,  EN D OF H W Y 9 2  3.5 3 miles  N W  031  SI T E BOUN DARY  0.27 miles  W S W  0 5 1 H W Y 12 8 , 1 MILE N OF H W Y 130  4.6 4 miles  NN W  07 6  SI T E BOUN DARY  0.1 9 miles  W  0 5 2 D PC BRANCH OFFICE SI T E - PIC KENS  12.4 miles  ENE  032  SI T E BOUN DARY  0.1 9 miles  W N W  0 5 3 D PC BRANCH OFFICE SI T E - LIBER T Y  11.7 miles  E  033  SI T E BOUN DARY  0.21 miles  W N W  0 5 4 POS T OFFICE - H W Y 9 3 NORRIS  8.6 0 miles  ESE  034  SI T E BOUN DARY  0.22 miles  N W  055 CLEMSON ME TEOROLOGY PLO T  9.27 miles  SSE  03 5  SI T E BOUN DARY  0.17 miles  NN W  056  W A T ER T O W ER - SENECA  7.30 miles  SS W  03 6  MILE CREE K LAN DING  4.32 miles  N  0 5 7  OCONEE MEMORIAL HOSPI T AL  8.42 miles  S W  037 K EO W EE CHURCH,  H W Y 327  4.85 miles  NNE  058 C BRANCH R D SUBS T A TION, WALHALLA  9.3 9 miles  W S W  03 8 CONVENIENCE MAR T ,  J C T H W Y 1 8 3 & 133  4.24 miles  NE  059  TAMASSEE D AR SCHOOL  9.20 miles  N W  03 9 H W Y 133, 1 MILE EAS T OF J C T H W Y 1 8 3 & 133  4.02 miles  ENE  0 8 1 C CLEMSON OPERA TIONS CEN T ER  9.33 miles  SE  C = Control
Oconee Nuclear Station                                                                   January, 2007 Offsite Dose Calculation Manual (ODCM)                                                   Revision 47 TABLE 6.0-3 Oconee 2006 Land Use Census Results*
* GPS data reflect approximate accuracy to within 2-5 meters. GPS field measurements were ta k en as      close as possi b le to the item of interest.
Land Use Census performed 6/19 - 6/20/2006 Sector                                      Distance        Sector                                 Distance (Miles)**                                               (Miles)**
Oconee Nuclear Station     January, 2007 Offsite Dose Calculation Manual (O D CM)     Revision 47   Section 6 - Page 4 TABLE 6.0-3 Oconee 200 6 Land Use Census Results
Nearest Residence                   2.98                 Nearest Residence                   1.96 N        Nearest Milk Animal                  -               S Nearest Milk Animal                  -
* Land Use Census performed 6/1 9 - 6/20/200 6  Sector   Distance (Miles)**   Sector  Distance (Miles)** N Nearest Residence Nearest Mil k Animal 2.98 -  S Nearest Residence Nearest Mil k Animal 1.96 -  NNE Nearest Residence Nearest Mil k Animal  1.85 -  SS W Nearest Residence Nearest Mil k Animal 1.3 6 -  NE Nearest Residence Nearest Mil k Animal 1.20 -  S W Nearest Residence Nearest Mil k Animal 1.3 9 -  ENE Nearest Residence Nearest Mil k Animal 1.34 -  W S W Nearest Residence Nearest Mil k Animal 1.8 1 -  E Nearest Residence Nearest Mil k Animal 1.14 -  W Nearest Residence Nearest Mil k Animal 1.7 6 -  ESE Nearest Residence Nearest Mil k Animal 1.5 7 -  W N W Nearest Residence Nearest Mil k Animal  1.3 5 -  SE Nearest Residence Nearest Mil k Animal 1.4 6 -  N W Nearest Residence Nearest Mil k Animal 1.00 -  SSE Nearest Residence Nearest Mil k Animal 1.5 4 - NN W Nearest Residence Nearest Mil k Animal 1.0 6 - - indicates no occurrences within the 5 mile radius
Nearest Residence                   1.85                 Nearest Residence                   1.36 NNE        Nearest Milk Animal                   -             SSW Nearest Milk Animal                  -
* T he land use census identifies nearest pathways to the exclusion area boundary (EAB, ~ 1.0 mile) for each of the 1 6 sectors. Locations beyond the nearest pathway for each sector are assumed to contain that pathway for dose calculation purposes. At Oconee, b road leaf vegetation samples are ta k en in lieu of a garden census. For dose calculation purposes, since a garden location cannot b e ruled out, a garden is assumed to exist at the site boundary and beyond for every sector. For the 4.5-5.0 mile sector all pathways, i.e., residence, garden, mil k animal (goat), and meat animal (cow), are assumed to exist for dose calculation purposes.
Nearest Residence                   1.20                 Nearest Residence                   1.39 NE        Nearest Milk Animal                   -             SW Nearest Milk Animal                  -
** GPS data reflect approximate accuracy to within 2-5 meters. GPS field measurements were ta k en as       close as possi b le to the item of interest.
Nearest Residence                   1.34                 Nearest Residence                   1.81 ENE        Nearest Milk Animal                  -            WSW  Nearest Milk Animal                   -
Oconee Nuclear Station          January, 2007 Offsite Dose Calculation Manual (O D CM)          Revision 47  Section 6 - Page 5 Figure 6.0-1 Sampling Locations Map (Site Boundary)
Nearest Residence                  1.14                Nearest Residence                  1.76 E        Nearest Milk Animal                  -               W Nearest Milk Animal                  -
Oconee Nuclear Station          January, 2007 Offsite Dose Calculation Manual (O D CM)          Revision 47  Section 6 - Page 6 Figure 6.0-2  Sampling Locations Map (Ten Mile Radius)
Nearest Residence                   1.57                Nearest Residence                   1.35 ESE       Nearest Milk Animal                  -          WNW    Nearest Milk Animal                   -
Nearest Residence                  1.46                Nearest Residence                   1.00 SE       Nearest Milk Animal                  -            NW  Nearest Milk Animal                   -
Nearest Residence                  1.54                Nearest Residence                   1.06 SSE       Nearest Milk Animal                   -           NNW  Nearest Milk Animal                   -
- indicates no occurrences within the 5 mile radius
* The land use census identifies nearest pathways to the exclusion area boundary (EAB, ~ 1.0 mile) for each of the 16 sectors. Locations beyond the nearest pathway for each sector are assumed to contain that pathway for dose calculation purposes. At Oconee, broad leaf vegetation samples are taken in lieu of a garden census. For dose calculation purposes, since a garden location cannot be ruled out, a garden is assumed to exist at the site boundary and beyond for every sector. For the 4.5-5.0 mile sector all pathways, i.e., residence, garden, milk animal (goat), and meat animal (cow), are assumed to exist for dose calculation purposes.
** GPS data reflect approximate accuracy to within 2-5 meters. GPS field measurements were taken as close as possible to the item of interest.
Section 6 - Page 4


Oconee Nuclear Station           January, 2007 Offsite Dose Calculation Manual (O D CM)           Revision 47   Section 6 - Page 7 Figure 6.0-3 ONS 200 6 Land Use Census Map
Oconee Nuclear Station                                                                     January, 2007 Offsite Dose Calculation Manual (ODCM)                                                     Revision 47 Figure 6.0-1 Sampling Locations Map (Site Boundary)
Section 6 - Page 5


Oconee Nuclear Station     January, 2007   Offsite Dose Calculation Manual (O D CM)     Revision 47     Section 6 - Page 8 6.0.3  OCONEE METEOROLOGY:  RELATIVE AIR CONCENTRATIONS AND DEPOSITION Calculations of annually averaged air concentrations and deposition values from routine releases provide the air dispersion and deposition factors needed for dose assessment.
Oconee Nuclear Station                                                                       January, 2007 Offsite Dose Calculation Manual (ODCM)                                                       Revision 47 Figure 6.0-2 Sampling Locations Map (Ten Mile Radius)
T he methodology is based upon Regulatory Guide 1.111, as implemented b y the NRC's computer model "X O Q D O Q: Computer Program for the Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations," NUREG/CR-2 9 1 9 , PNL-43 8 0, Septem b er 1 98 2.
Section 6 - Page 6
Five years of hourly meteorological data from the onsite instruments are processed into a representative j oint fre quency distri b ution of winds and atmospheric sta bility for input into the X O Q D O Q model (Version 2.0). T hus, the air dispersion and deposition factors (/Q and D/Q) output b y the model are b ased on a five-year climatology for the site. 6.0.3.1  X O Q DO Q METHODOLOGY AND ASSUMPTIONS A continuous, routine release (non-purge) is simulated from each unit vent. T he unit vent release type is categori z ed as semi-elevated, being elevated approximately 9 2% of the time and being at ground-level approximately 8% of the time. T his is based on RG 1.111 criteria, with the ratio (i.e. 3.6 4) of the average exit velocity (11.3 9 m/s) to the mean wind speed at the 6 0 m release height (3.13 m/s). T o account for all release pathways, Oconee is modeled as b oth a totally "ground-level" release and as a "mixed-mode" release, with two model runs of X O Q D O Q.
Surrounding terrain heights are not input for ground-level releases, b ut are used for the elevated portion of mixed-mode releases. T he locale consists of rolling terrain, so the default open terrain recirculation factor is applied in X O Q D OQ [K OP T (8)=1]. T his correction factor is recommended in RG 1.111 to ad j ust the straight-line airflow of the model for spatial and temporal variations that are produced b y large scale weather patterns.
In order for X O Q D O Q to treat the plume as a ground-level release, the exit velocity and the inside diameter of the unit vent must b e input as z ero. T he heat emission rate of each vent is also assumed to b e z ero, as recommended b y the model. A release height of 10 m is assumed for the ground-level release, with actual plant grade of 7 96 ft msl. Using the b uilding height (58 m) and minimum cross-sectional area of the containment b uilding (22 96 m 2), X O Q D O Q applies a b uilding wa k e correction to the relative air concentrations.


For the mixed-mode release, the exit velocities (11.1, 11.3, and 11.7 m/s for U1-U3, respectively
Oconee Nuclear Station                                                           January, 2007 Offsite Dose Calculation Manual (ODCM)                                           Revision 47 Figure 6.0-3 ONS 2006 Land Use Census Map Section 6 - Page 7
) and inside diameters (1.8 m) of the unit vents are input to the X O Q D O Q model for each vent. T he heat emission rate of each vent is still assumed to b e z ero, as in the ground-level release. Plant grade elevation is now input as z ero, however, to properly Oconee Nuclear Station     January, 2007   Offsite Dose Calculation Manual (O D CM)     Revision 47     Section 6 - Page 9 utili z e the input terrain heights a b ove yard grade elevation (T a b le 6.0-4). T he height of the vent  (6 0.7 m) a bove plant grade is used to determine the plume centerline height. Ta ble 6.0-4  Terrain Heights A bove ONS Yard Grade Elevation (m)
Distance:
0.5 mile 1 mile 1.5 miles 2.0 miles 2.5 miles 3.0 miles 3.5 miles 4.0 miles 4.5 miles 5.0 miles S 2 9 3 8 3 8 3 8 3 8 3 8 5 0 5 0 5 0 5 0 SS W 32 44 5 0 5 0 5 0 5 0 5 0 5 0 5 0 5 0 S W 3 8 44 44 44 5 0 5 0 5 0 5 0 5 0 5 0 W S W 44 44 44 44 44 44 44 4 8 4 8 5 7 W 4 8 4 8 4 8 4 8 48 55 58 73 73 73 W N W 2 9 2 9 2 9 38 65 65 71 71 77 8 0 N W 30 30 30 4 8 5 0 68 69 69 71 71 NN W 30 30 30 4 8 5 0 68 69 69 71 71 N 2 9 30 30 30 30 30 6 2 6 2 6 2 74 NNE 24 24 3 5 3 5 5 3 5 3 8 2 8 2 8 2 8 2 NE 7 13 3 5 44 44 5 0 78 88 99 100 ENE 4 23 3 5 3 8 5 3 6 2 74 8 0 99 100 E 1 24 24 24 5 7 68 68 74 8 4 8 4 ESE 1 1 13 3 5 6 2 6 2 6 2 65 71 71 SE 7 20 20 44 6 7 6 7 6 7 6 7 6 7 6 7 SSE 7 3 8 3 8 3 8 47 6 2 6 2 6 2 6 2 6 2  Calculations of relative air concentrations and deposition are made for gridded receptor distances per sector. T he model's default values for half-lives are used (i.e. no decay; 2.2 6 days for short-lived no b le gases; and 8 days with depletion factors for all iodines [DECAYS (I)= 101; 2.2 6; -8.0] ). 6.0.3.2  METEOROLOGICAL DATA Five years (1988-1 99 2) of hourly, onsite meteorological data are used to produce the j oint fre quency distri b utions of wind speed and direction per sta bility class. T he 10 m level winds are used. It is these j oint fre quency distri butions which are input to the X O Q D O Q model. X O Q D O Q extrapolates the 10 m wind speed to the release height during the elevated portion of mixed-mode releases. Hours of calm winds are distri b uted b y direction with the same fre quency as the lowest "noncalm" wind speed class [K OP T (1)=1]. T hus, wind speed classes are esta blished so that the lowest wind speed class is the starting threshold of the anemometer (i.e. the "calm" wind speed class). T he largest wind speed class has the upper b ound of (5 m/s + max hourly wind speed). Sta bility classes (A-G) are b ased on the vertical temperature gradient, measured b y the hourly averaged delta-T varia ble.
Oconee Nuclear Station    January, 2007    Offsite Dose Calculation Manual (O D CM)    Revision 47      Section 6 - Page 10 6.0.3.3  ANNUAL X O Q DO Q COMPARISON TO THE ODCM Each year, the prevailing winds and sta bility class fre quencies for ONS are compared to the 5-year period (1 988-1 99 2) upon which the /Q and D/Q calculations have b een made. T he 5-year climatology is summari z ed in T a b le 6.0-5 and T a b le 6.0-6 below. Since the comparison is being made to a 5-year climatology, significant differences should not occur in the meteorological varia bles of concern (i.e. winds and delta-T). T he meteorological comparison serves to verify this assumption.
Ta ble 6.0-5 ONS Atmospheric Sta bility Fre quency (1 988-1 99 2)  A B C D E F G Fre quency (%)  8.9  5.4  6.1  3 9.5  33.1  5.6  1.5  Ta ble 6.0-6 ONS Fre quency of Wind Direction (From) and Speed (1 988-1 99 2)  Sector Wind Direction Fre quency (%) Wind Speed Class (m/s) Wind Speed Fre quency (%) N 5.1 CALM 1.0 NNE 5.2 0.4 5 - 0.74 m/s 4.7 NE 9 0.7 5 - 0.99 m/s 9.4 ENE 8.3 1.00 - 1.24 m/s 10.0 E 5.2 1.2 5 - 1.4 9 m/s 12.3 ESE 3.1 1.5 0 - 1.99 m/s 1 6.8 SE 3 2.00 - 2.99 m/s 20.4 SSE 3.5 3.00 - 3.99 m/s 9.6 S 3.6 4.00 - 4.99 m/s 4.5 SS W 8.5 5.00 - 5.99 m/s 1.8 S W 11.7 6.00 - 7.99 m/s 1.3 W S W 7.4 8.00 - 9.99 m/s 0.3 W 5.1 > 9.99 m/s 8.9 W N W 6.9  N W 7.2  NN W 6.3   


T he j oint fre quency distri b utions of wind speed and direction versus atmospheric sta bility class are also determined from the annual data to provide input to the X O Q D O Q model. Modeled /Q and D/Q values for the 1.0 mile Exclusion Area Boundary at ONS are Oconee Nuclear Station     January, 2007   Offsite Dose Calculation Manual (O D CM)     Revision 47     Section 6 - Page 11 compared to the maximum of the (1 988-1 99 2) /Q and D/Q values from all sectors. If the newly calculated annual dispersion and deposition values do not result in a significant increase in the calculated offsite dose relative to the 10CFR 5 0, Appendix I dose o bjectives then the 5-yearQ and D/Q values used in the Annual Radiological Effluent Release Report (ARERR) are not revised. An increase in calculated offsite dose that is greater than five percent of the 10CFR 5 0, Appendix I dose o bjectives would b e considered significant enough to warrant a change in theQ and D/Q values used in the ARERR. If an increasing trend in the annualQ and D/Q values compared to the 5-year values is noted then a revised set of 5-yearQ and D/Q values will b e generated. These limiting values are listed in T a b le 6.0-7. T he entire /Q and D/Q list based on directional sector and distance is given in T a b le 6.0-9 and T a b le 6.0-10. Ta ble 6.0-7 ONS Limiting /Q and D/Q Values (1 988-1 99 2)  ( ,s/m 3) (D/Q ,1/m 2) Distance Sector Ground-level Release:  MaximumQ 7.30 8 E-0 6 1 mile EAB SE Ground-level Release:  Maximum D/Q 2.2 59 E-8 1 mile EAB NE Mixed-mode Release:  MaximumQ 1.6 72E-0 6 1 mile EAB S W Mixed-mode Release:  Maximum D/Q 1.2 95 E-0 8 1 mile EAB NE  Note: T he Oconee meteorological instruments were relocated from the 4 6 m microwave tower to a new 6 0 m onsite meteorological tower in April 1 988. T he 6 0 m tower became operational at 1700 hours on April 23, 1 988. Therefore, determination of atmospheric sta bility should use the 3 6 m separation criteria for the period Fe bruary 24, 1 9 77-April 22, 1 988 shown in T a b le 6.0-8. Data starting on April 23, 1 988 or later should use the 5 0 m separation criteria. Ta ble 6.0-8 ONS Delta-T Ranges per Vertical Separation Distances Sta bility Class 3 6m separation Delta
Oconee Nuclear Station                                                           January, 2007 Offsite Dose Calculation Manual (ODCM)                                           Revision 47 6.0.3 OCONEE METEOROLOGY: RELATIVE AIR CONCENTRATIONS AND DEPOSITION Calculations of annually averaged air concentrations and deposition values from routine releases provide the air dispersion and deposition factors needed for dose assessment.
-T (between 4 6 m-10m levels) FEB 24, 1 9 77 - APRIL 1 8 , 1 988 (4/1 8/88 ending hour 1430) 50m separation Delta
The methodology is based upon Regulatory Guide 1.111, as implemented by the NRC's computer model "XOQDOQ: Computer Program for the Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations," NUREG/CR-2919, PNL-4380, September 1982.
-T (between 6 0m-10m levels)
Five years of hourly meteorological data from the onsite instruments are processed into a representative joint frequency distribution of winds and atmospheric stability for input into the XOQDOQ model (Version 2.0). Thus, the air dispersion and deposition factors
Starting at hour 1700 on April 23, 1 988. A d T < -0.68 d T < -0.95 B -0.68 < d T < -0.6 1 -0.95 < d T < -0.85 C -0.6 1 < d T < -0.5 4 -0.85 < d T < -0.7 5 D -0.5 4 < d T < -0.1 8 -0.7 5 < d T < -0.2 5 E -0.1 8 < d T < 0.5 4 -0.2 5 < d T < 0.7 5 F 0.5 4 < d T < 1.44 0.7 5 < d T < 2.00 G 1.44 < D t 2.00 < d T Oconee Nuclear Station    January, 2007    Offsite Dose Calculation Manual (O D CM)     Revision 47      Section 6 - Page 12 Ta ble 6.0-9 (page 1 of 2)
(/Q and D/Q) output by the model are based on a five-year climatology for the site.
Oconee Semi
6.0.3.1 XOQDOQ METHODOLOGY AND ASSUMPTIONS A continuous, routine release (non-purge) is simulated from each unit vent. The unit vent release type is categorized as semi-elevated, being elevated approximately 92% of the time and being at ground-level approximately 8% of the time. This is based on RG 1.111 criteria, with the ratio (i.e. 3.64) of the average exit velocity (11.39 m/s) to the mean wind speed at the 60 m release height (3.13 m/s). To account for all release pathways, Oconee is modeled as both a totally "ground-level" release and as a "mixed-mode" release, with two model runs of XOQDOQ.
-Elevated /Q Average Values (1 988-1 99 2) (sec/m 3)                  Sector 1.0-1.5* 1.5-2.0 2.0-2.5 2.5-3.0 3.0-3.5 3.5-4.0 4.0-4.5 4.5-5.0 N 5.220E-07 2.65 0E-07 1.59 4E-07 1.0 69 E-07 7.71 9 E-0 8 7.321E-0 8 5.665 E-0 8 4.542E-0 8 NNE 8.37 9 E-07 4.734E-07 2.69 0E-07 2.003E-07 1.3 85 E-07 1.0 9 1E-07 8.37 9 E-0 8 6.6 7 6 E-0 8 NE 9.503E-07 6.3 5 0E-07 3.96 2E-07 2.5 3 5 E-07 1.847E-07 1.4 9 7E-07 1.1 5 7E-07 9.24 6 E-0 8 ENE 8.11 6 E-07 4.856 E-07 2.9 1 9 E-07 2.1 96 E-07 1.6 1 9 E-07 1.23 9 E-07 9.6 0 9 E-0 8 7.720E-0 8 E 5.95 0E-07 3.202E-07 2.01 5 E-07 2.270E-07 1.74 5 E-07 1.2 9 2E-07 1.024E-07 8.30 8 E-0 8 ESE 4.531E-07 3.300E-07 3.623E-07 4.020E-07 2.822E-07 2.10 9 E-07 1.688 E-07 1.40 5 E-07 SE 7.5 0 5 E-07 4.573E-07 5.4 9 0E-07 5.110E-07 3.56 0E-07 2.6 4 8 E-07 2.0 6 3E-07 1.665 E-07 SSE 1.41 9 E-0 6 7.42 8 E-07 4.527E-07 3.4 89 E-07 2.866 E-07 2.131E-07 1.659 E-07 1.337E-07 S 1.170E-0 6 6.0 99 E-07 3.701E-07 2.4 96 E-07 1.810E-07 1.55 2E-07 1.21 8 E-07 9.86 7E-0 8 SS W 1.214E-0 6 6.327E-07 3.56 4E-07 2.301E-07 1.621E-07 1.213E-07 9.4 8 1E-0 8 7.66 0E-0 8 S W 1.672E-0 6 7.2 85 E-07 4.0 5 7E-07 2.720E-07 1.89 1E-07 1.400E-07 1.0 85 E-07 8.70 8 E-0 8 W S W 1.558 E-0 6 6.820E-07 3.804E-07 2.43 8 E-07 1.70 8 E-07 1.271E-07 1.010E-07 8.114E-0 8 W 1.1 9 3E-0 6 5.214E-07 2.9 0 9 E-07 1.86 7E-07 1.372E-07 1.032E-07 8.32 6 E-0 8 6.65 4E-0 8 W N W 4.658 E-07 2.4 8 0E-07 1.7 6 0E-07 1.4 8 2E-07 1.024E-07 7.695 E-0 8 5.943E-0 8 4.7 96 E-0 8 N W 4.831E-07 2.524E-07 1.965 E-07 1.2 9 1E-07 9.959 E-0 8 7.3 56 E-0 8 5.68 2E-0 8 4.566 E-0 8 NN W 5.37 5 E-07 2.7 69 E-07 2.12 8 E-07 1.3 9 4E-07 1.072E-07 7.913E-0 8 6.110E-0 8 4.907E-0 8
Surrounding terrain heights are not input for ground-level releases, but are used for the elevated portion of mixed-mode releases. The locale consists of rolling terrain, so the default open terrain recirculation factor is applied in XOQDOQ [KOPT(8)=1]. This correction factor is recommended in RG 1.111 to adjust the straight-line airflow of the model for spatial and temporal variations that are produced by large scale weather patterns.
* Units are in miles from the station. As discussed in Oconee UFSAR Section 2.1.1.3, the boundary for esta blishing gaseous effluent release limits is the exclusion area boundary (EAB). T he EAB is at a radius of 1.0 mile from the station center. Each /Q value is calculated at the closest location for the sector, e.g., 1.6 72E-0 6 sec/m 3 is the /Q value at 1.0 mile (S W) from the station. 
In order for XOQDOQ to treat the plume as a ground-level release, the exit velocity and the inside diameter of the unit vent must be input as zero. The heat emission rate of each vent is also assumed to be zero, as recommended by the model. A release height of 10 m is assumed for the ground-level release, with actual plant grade of 796 ft msl. Using the building height (58 m) and minimum cross-sectional area of the containment building (2296 m2), XOQDOQ applies a building wake correction to the relative air concentrations.
For the mixed-mode release, the exit velocities (11.1, 11.3, and 11.7 m/s for U1-U3, respectively) and inside diameters (1.8 m) of the unit vents are input to the XOQDOQ model for each vent. The heat emission rate of each vent is still assumed to be zero, as in the ground-level release. Plant grade elevation is now input as zero, however, to properly Section 6 - Page 8


Oconee Nuclear Station     January, 2007   Offsite Dose Calculation Manual (O D CM)     Revision 47     Section 6 - Page 13 Ta ble 6.0-9 (page 2 of 2)
Oconee Nuclear Station                                                     January, 2007 Offsite Dose Calculation Manual (ODCM)                                     Revision 47 utilize the input terrain heights above yard grade elevation (Table 6.0-4). The height of the vent (60.7 m) above plant grade is used to determine the plume centerline height.
Oconee Semi
Table 6.0-4 Terrain Heights Above ONS Yard Grade Elevation (m)
-Elevated D
Distance:      0.5       1     1.5   2.0         2.5   3.0   3.5   4.0     4.5     5.0 mile     mile   miles  miles      miles  miles miles miles    miles    miles S               29        38      38      38          38    38    50    50      50      50 SSW            32        44      50      50          50    50    50    50      50      50 SW              38        44      44      44          50    50    50    50      50      50 WSW            44        44      44      44          44    44    44    48      48      57 W               48        48      48      48          48    55    58    73      73      73 WNW            29        29      29      38          65    65    71    71      77      80 NW              30        30      30      48          50    68    69    69      71      71 NNW            30        30      30      48          50     68   69     69      71     71 N               29        30      30      30          30    30    62    62      62      74 NNE             24        24      35      35          53    53    82    82      82      82 NE               7        13      35      44          44    50    78    88      99    100 ENE             4       23      35      38          53    62    74    80      99    100 E               1       24      24      24          57    68    68    74      84      84 ESE              1         1     13      35          62    62    62    65      71      71 SE               7       20      20      44          67    67    67    67      67      67 SSE             7       38      38      38          47    62    62    62      62      62 Calculations of relative air concentrations and deposition are made for gridded receptor distances per sector. The model's default values for half-lives are used (i.e. no decay; 2.26 days for short-lived noble gases; and 8 days with depletion factors for all iodines
/Q Average Values (1 988-1 99 2) (m-2)  Sector 1.0-1.5* 1.5-2.0 2.0-2.5 2.5-3.0 3.0-3.5 3.5-4.0 4.0-4.5 4.5-5.0 N 2.89 0E-0 9 1.1 8 4E-0 9 6.22 5 E-10 3.812E-10 2.586 E-10 3.3 8 0E-10 2.510E-10 1.943E-10 NNE 9.113E-0 9 3.989 E-0 9 2.013E-0 9 1.24 8 E-0 9 8.23 5 E-10 8.99 7E-10 6.66 7E-10 5.13 8 E-10 NE 1.2 95 E-0 8 5.666 E-0 9 2.9 1 9 E-0 9 1.72 9 E-0 9 1.14 5 E-0 9 1.224E-0 9 9.140E-10 7.0 6 7E-10 ENE 7.899 E-0 9 3.3 85 E-0 9 1.7 56 E-0 9 1.0 95 E-0 9 9.8 1 9 E-10 7.671E-10 5.74 9 E-10 4.4 66 E-10 E 4.4 5 4E-0 9 1.77 5 E-0 9 9.2 5 2E-10 7.1 6 4E-10 7.4 9 1E-10 5.2 6 7E-10 3.98 1E-10 3.12 5 E-10 ESE 4.3 6 1E-0 9 1.8 3 8 E-0 9 1.0 86 E-0 9 1.322E-0 9 8.696 E-10 6.1 6 1E-10 5.1 5 3E-10 4.13 9 E-10 SE 3.3 9 7E-0 9 1.3 85 E-0 9 8.341E-10 1.6 4 9 E-0 9 1.0 8 0E-0 9 7.595 E-10 5.6 2 9 E-10 4.340E-10 SSE 3.333E-0 9 1.323E-0 9 6.920E-10 4.404E-10 7.307E-10 5.202E-10 3.922E-10 3.0 9 1E-10 S 3.1 9 2E-0 9 1.2 56 E-0 9 6.530E-10 4.020E-10 2.7 88 E-10 2.177E-10 1.7 59 E-10 1.501E-10 SS W 5.1 9 0E-0 9 1.972E-0 9 9.899 E-10 5.895 E-10 3.9 2 8 E-10 2.842E-10 2.1 9 2E-10 1.77 8 E-10 S W 1.20 5 E-0 8 4.3 99 E-0 9 2.1 9 3E-0 9 1.2 99 E-0 9 8.521E-10 6.02 8 E-10 4.5 1 8 E-10 3.5 4 6 E-10 W S W 1.047E-0 8 3.824E-0 9 1.9 0 8 E-0 9 1.127E-0 9 7.422E-10 5.277E-10 3.98 0E-10 3.14 5 E-10 W 5.577E-0 9 2.044E-0 9 1.02 5 E-0 9 6.0 9 4E-10 4.134E-10 3.40 5 E-10 3.96 2E-10 3.0 5 2E-10 W N W 2.1 85 E-0 9 9.042E-10 5.220E-10 6.4 6 4E-10 4.227E-10 3.1 88 E-10 2.3 6 0E-10 1.868 E-10 N W 2.0 9 7E-0 9 8.7 59 E-10 5.22 5 E-10 3.1 96 E-10 4.521E-10 3.17 8 E-10 2.3 5 3E-10 1.812E-10 NN W 2.4 6 1E-0 9 1.02 8 E-0 9 6.21 9 E-10 3.7 65 E-10 5.12 8 E-10 3.604E-10 2.66 7E-10 2.0 5 4E-10
[DECAYS(I)= 101; 2.26; -8.0] ).
* Units are in miles from the station. As discussed in Oconee UFSAR Section 2.1.1.3, the boundary for esta blishing gaseous effluent release limits is the exclusion area boundary (EAB). T he EAB is defined as a 1 mile radius from the station center. Each D/Q value is calculated at the closest location for the sector, e.g., 1.20 5 E-0 8 m-2 is the D/Q value at 1.0 mile (S W) from the station.
6.0.3.2 METEOROLOGICAL DATA Five years (1988-1992) of hourly, onsite meteorological data are used to produce the joint frequency distributions of wind speed and direction per stability class. The 10 m level winds are used. It is these joint frequency distributions which are input to the XOQDOQ model. XOQDOQ extrapolates the 10 m wind speed to the release height during the elevated portion of mixed-mode releases. Hours of calm winds are distributed by direction with the same frequency as the lowest "noncalm" wind speed class
Oconee Nuclear Station     January, 2007   Offsite Dose Calculation Manual (O D CM)     Revision 47     Section 6 - Page 14 Ta ble 6.0-10 (page 1 of 2)
[KOPT(1)=1]. Thus, wind speed classes are established so that the lowest wind speed class is the starting threshold of the anemometer (i.e. the "calm" wind speed class). The largest wind speed class has the upper bound of (5 m/s + max hourly wind speed).
Oconee Ground Level /Q Average Values (1988-1 99 2) (sec/m 3)                  Sector 1.0-1.5* 1.5-2.0 2.0-2.5 2.5-3.0 3.0-3.5 3.5-4.0 4.0-4.5 4.5-5.0 N 2.11 5 E-0 6 8.3 89 E-07 4.4 95 E-07 2.822E-07 1.95 2E-07 1.443E-07 1.117E-07 8.96 1E-0 8 NNE 2.898 E-0 6 1.137E-0 6 6.047E-07 3.77 5 E-07 2.602E-07 1.9 1 6 E-07 1.4 8 0E-07 1.1 8 4E-07 NE 3.886 E-0 6 1.5 2 9 E-0 6 8.1 58 E-07 5.10 8 E-07 3.5 2 9 E-07 2.604E-07 2.01 5 E-07 1.6 1 6 E-07 ENE 3.22 6 E-0 6 1.277E-0 6 6.8 4 8 E-07 4.30 5 E-07 2.98 3E-07 2.207E-07 1.711E-07 1.374E-07 E 3.522E-0 6 1.410E-0 6 7.658 E-07 4.866 E-07 3.400E-07 2.534E-07 1.977E-07 1.596 E-07 ESE 5.96 4E-0 6 2.407E-0 6 1.321E-0 6 8.4 59 E-07 5.95 0E-07 4.4 5 7E-07 3.4 9 3E-07 2.832E-07 SE 7.30 8 E-0 6 2.972E-0 6 1.631E-0 6 1.044E-0 6 7.342E-07 5.4 9 7E-07 4.307E-07 3.4 9 0E-07 SSE 6.604E-0 6 2.65 7E-0 6 1.440E-0 6 9.117E-07 6.3 5 4E-07 4.723E-07 3.6 7 6 E-07 2.96 2E-07 S 5.27 8 E-0 6 2.121E-0 6 1.14 6 E-0 6 7.237E-07 5.032E-07 3.734E-07 2.901E-07 2.33 5 E-07 SS W 3.986 E-0 6 1.589 E-0 6 8.5 3 6 E-07 5.370E-07 3.721E-07 2.7 5 3E-07 2.13 5 E-07 1.714E-07 S W 4.10 8 E-0 6 1.620E-0 6 8.6 2 8 E-07 5.3 9 0E-07 3.71 5 E-07 2.73 5 E-07 2.112E-07 1.689 E-07 W S W 3.804E-0 6 1.503E-0 6 8.01 8 E-07 5.01 5 E-07 3.4 6 0E-07 2.5 4 9 E-07 1.970E-07 1.577E-07 W 2.9 7 8 E-0 6 1.1 86 E-0 6 6.3 6 1E-07 3.995 E-07 2.7 65 E-07 2.043E-07 1.58 3E-07 1.270E-07 W N W 2.201E-0 6 8.7 9 1E-07 4.72 6 E-07 2.974E-07 2.0 6 2E-07 1.5 2 6 E-07 1.1 8 3E-07 9.502E-0 8 N W 2.104E-0 6 8.3 85 E-07 4.4 99 E-07 2.8 2 6 E-07 1.95 7E-07 1.447E-07 1.121E-07 8.99 1E-0 8 NN W 2.221E-0 6 8.86 0E-07 4.7 55 E-07 2.988 E-07 2.0 69 E-07 1.5 2 9 E-07 1.1 85 E-07 9.5 0 8 E-0 8
Stability classes (A-G) are based on the vertical temperature gradient, measured by the hourly averaged delta-T variable.
* Units are in miles from the station. As discussed in Oconee UFSAR Section 2.1.1.3, the boundary for esta blishing gaseous effluent release limits is the exclusion area boundary (EAB). T he EAB is defined as a 1 mile radius from the station center. Each /Q value is calculated at the closest location for the sector, e.g., 4.10 8 E-0 6 sec/m 3 is the /Q value at 1.0 mile (S W) from the station.
Section 6 - Page 9
Oconee Nuclear Station    January, 2007    Offsite Dose Calculation Manual (O D CM)    Revision 47      Section 6 - Page 1 5 Ta ble 6.0-10 (page 2 of 2)
Oconee Ground Level D
/Q Average Values (1 988-1 99 2) (m-2)  Sector 1.0-1.5* 1.5-2.0 2.0-2.5 2.5-3.0 3.0-3.5 3.5-4.0 4.0-4.5 4.5-5.0 N 6.9 1 6 E-0 9 2.4 8 4E-0 9 1.232E-0 9 7.2 55 E-10 4.7 5 0E-10 3.342E-10 2.477E-10 1.9 0 9 E-10 NNE 1.642E-0 8 5.89 7E-0 9 2.924E-0 9 1.722E-0 9 1.12 8 E-0 9 7.934E-10 5.88 0E-10 4.531E-10 NE 2.2 59 E-0 8 8.114E-0 9 4.024E-0 9 2.3 69 E-0 9 1.55 1E-0 9 1.0 9 2E-0 9 8.0 9 0E-10 6.23 5 E-10 ENE 1.42 8 E-0 8 5.130E-0 9 2.544E-0 9 1.4 98 E-0 9 9.810E-10 6.902E-10 5.11 5 E-10 3.942E-10 E 9.899 E-0 9 3.556 E-0 9 1.7 6 3E-0 9 1.03 8 E-0 9 6.7 98 E-10 4.7 8 4E-10 3.5 4 5 E-10 2.732E-10 ESE 1.33 6 E-0 8 4.7 98 E-0 9 2.37 9 E-0 9 1.401E-0 9 9.174E-10 6.4 55 E-10 4.7 8 4E-10 3.686 E-10 SE 1.401E-0 8 5.034E-0 9 2.4 96 E-0 9 1.470E-0 9 9.6 2 5 E-10 6.772E-10 5.01 9 E-10 3.868 E-10 SSE 1.22 6 E-0 8 4.404E-0 9 2.1 8 4E-0 9 1.2 86 E-0 9 8.420E-10 5.9 2 5 E-10 4.3 9 1E-10 3.3 8 4E-10 S 1.00 8 E-0 8 3.620E-0 9 1.7 95 E-0 9 1.0 5 7E-0 9 6.922E-10 4.871E-10 3.610E-10 2.7 8 2E-10 SS W 9.941E-0 9 3.571E-0 9 1.771E-0 9 1.043E-0 9 6.8 2 8 E-10 4.804E-10 3.56 0E-10 2.744E-10 S W 1.717E-0 8 6.1 69 E-0 9 3.0 59 E-0 9 1.801E-0 9 1.1 8 0E-0 9 8.300E-10 6.1 5 1E-10 4.740E-10 W S W 1.574E-0 8 5.655 E-0 9 2.804E-0 9 1.65 1E-0 9 1.0 8 1E-0 9 7.6 0 8 E-10 5.6 3 8 E-10 4.34 5 E-10 W 9.988 E-0 9 3.588 E-0 9 1.77 9 E-0 9 1.04 8 E-0 9 6.86 0E-10 4.827E-10 3.577E-10 2.7 5 7E-10 W N W 5.95 3E-0 9 2.13 8 E-0 9 1.0 6 0E-0 9 6.244E-10 4.0 88 E-10 2.877E-10 2.132E-10 1.643E-10 N W 5.89 1E-0 9 2.11 6 E-0 9 1.04 9 E-0 9 6.17 9 E-10 4.04 6 E-10 2.847E-10 2.110E-10 1.6 2 6 E-10 NN W 6.672E-0 9 2.3 9 7E-0 9 1.1 88 E-0 9 6.998 E-10 4.58 2E-10 3.224E-10 2.3 9 0E-10 1.841E-10
* Units are in miles from the station. As discussed in Oconee UFSAR Section 2.1.1.3, the boundary for esta blishing gaseous effluent release limits is the exclusion area boundary (EAB). T he EAB is defined as a 1 mile radius from the station center. Each D/Q value is calculated at the closest location for the sector, e.g., 1.717E-0 8 m-2 is the D/Q value at 1.0 mile (S W) from the station.


Oconee Nuclear Station     January, 2007 Offsite Dose Calculation Manual (ODCM)     Revision 47 Section 7 - Page 1
Oconee Nuclear Station                                                       January, 2007 Offsite Dose Calculation Manual (ODCM)                                       Revision 47 6.0.3.3 ANNUAL XOQDOQ COMPARISON TO THE ODCM Each year, the prevailing winds and stability class frequencies for ONS are compared to the 5-year period (1988-1992) upon which the /Q and D/Q calculations have been made.
The 5-year climatology is summarized in Table 6.0-5 and Table 6.0-6 below. Since the comparison is being made to a 5-year climatology, significant differences should not occur in the meteorological variables of concern (i.e. winds and delta-T). The meteorological comparison serves to verify this assumption.
Table 6.0-5 ONS Atmospheric Stability Frequency (1988-1992)
A        B        C            D    E      F          G Frequency
(%)              8.9      5.4      6.1          39.5 33.1    5.6        1.5 Table 6.0-6 ONS Frequency of Wind Direction (From) and Speed (1988-1992)
Wind Direction      Wind Speed Class          Wind Speed Sector        Frequency (%)                (m/s)          Frequency (%)
N                      5.1                  CALM                  1.0 NNE                    5.2            0.45 - 0.74 m/s            4.7 NE                      9              0.75 - 0.99 m/s            9.4 ENE                    8.3            1.00 - 1.24 m/s            10.0 E                      5.2            1.25 - 1.49 m/s            12.3 ESE                    3.1            1.50 - 1.99 m/s            16.8 SE                      3              2.00 - 2.99 m/s            20.4 SSE                    3.5            3.00 - 3.99 m/s            9.6 S                      3.6            4.00 - 4.99 m/s            4.5 SSW                    8.5            5.00 - 5.99 m/s            1.8 SW                    11.7            6.00 - 7.99 m/s            1.3 WSW                    7.4            8.00 - 9.99 m/s            0.3 W                      5.1                > 9.99 m/s              8.9 WNW                    6.9 NW                      7.2 NNW                    6.3 The joint frequency distributions of wind speed and direction versus atmospheric stability class are also determined from the annual data to provide input to the XOQDOQ model.
Modeled /Q and D/Q values for the 1.0 mile Exclusion Area Boundary at ONS are Section 6 - Page 10


===7.0 LICENSEE===
Oconee Nuclear Station                                                            January, 2007 Offsite Dose Calculation Manual (ODCM)                                            Revision 47 compared to the maximum of the (1988-1992) /Q and D/Q values from all sectors. If the newly calculated annual dispersion and deposition values do not result in a significant increase in the calculated offsite dose relative to the 10CFR50, Appendix I dose objectives then the 5-year /Q and D/Q values used in the Annual Radiological Effluent Release Report (ARERR) are not revised. An increase in calculated offsite dose that is greater than five percent of the 10CFR50, Appendix I dose objectives would be considered significant enough to warrant a change in the /Q and D/Q values used in the ARERR. If an increasing trend in the annual /Q and D/Q values compared to the 5-year values is noted then a revised set of 5-year /Q and D/Q values will be generated. These limiting values are listed in Table 6.0-7. The entire /Q and D/Q list based on directional sector and distance is given in Table 6.0-9 and Table 6.0-10.
INITIATED CHANGESAll changes made to the Oconee ODCM are reviewed by knowledgeable individual(s), and approved by the Station Manager and the General Office Radiation Protection Manager prior to implementation. The following changes do not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.
Table 6.0-7 ONS Limiting /Q and D/Q Values (1988-1992)
Section 2 - Page 1Removed the "s" from Decant Monitor Tanks because there is only one Decant Monitor Tank.Section 2 - Page 2Added "TBSMT" to make clear that the Turbine Building Sump Monitor Tanks are an input source to #3 CTP. Removed "Radwaste Facility monitor tanks" because that source is not
(/Q,s/m3)    Distance            Sector (D/Q,1/m2)
Ground-level Release:      Maximum /Q        7.308E-06    1 mile EAB            SE Ground-level Release:      Maximum D/Q          2.259E-8    1 mile EAB            NE Mixed-mode Release:        Maximum /Q        1.672E-06    1 mile EAB            SW Mixed-mode Release:        Maximum D/Q          1.295E-08    1 mile EAB            NE Note:
The Oconee meteorological instruments were relocated from the 46 m microwave tower to a new 60 m onsite meteorological tower in April 1988. The 60 m tower became operational at 1700 hours on April 23, 1988. Therefore, determination of atmospheric stability should use the 36 m separation criteria for the period February 24, 1977-April 22, 1988 shown in Table 6.0-8. Data starting on April 23, 1988 or later should use the 50 m separation criteria.
Table 6.0-8 ONS Delta-T Ranges per Vertical Separation Distances Stability          36m separation Delta-T                  50m separation Delta-T Class            (between 46m-10m levels)                  (between 60m-10m levels)
FEB 24, 1977 - APRIL 18, 1988                  Starting at hour 1700 on (4/18/88 ending hour 1430)                        April 23, 1988.
A                      dT < -0.68                                dT < -0.95 B                  -0.68 < dT < -0.61                        -0.95 < dT < -0.85 C                  -0.61 < dT < -0.54                        -0.85 < dT < -0.75 D                  -0.54 < dT < -0.18                        -0.75 < dT < -0.25 E                  -0.18 < dT < 0.54                        -0.25 < dT < 0.75 F                  0.54 < dT < 1.44                          0.75 < dT < 2.00 G                      1.44 < Dt                                2.00 < dT Section 6 - Page 11


ever released to #3 CTP.
Oconee Nuclear Station                                                                January, 2007 Offsite Dose Calculation Manual (ODCM)                                                Revision 47 Table 6.0-9 (page 1 of 2)
Section 3 - Page 5Corrected typographical error for the Unit 2 Reactor Building Purge controlling RIA and the Unit 3 Reactor Building Purge controlling RIA.
Oconee Semi-Elevated /Q Average Values (1988-1992)
Section 4 - Page 3Provided detail on what value is assumed for the average dilution flow during the liquid release period of interest. Removed redundant information related to the recirculation factor.
(sec/m3)
Sector    1.0-1.5*    1.5-2.0    2.0-2.5      2.5-3.0        3.0-3.5  3.5-4.0  4.0-4.5    4.5-5.0 N          5.220E-07  2.650E-07  1.594E-07    1.069E-07      7.719E-08 7.321E-08 5.665E-08  4.542E-08 NNE        8.379E-07  4.734E-07  2.690E-07    2.003E-07      1.385E-07 1.091E-07 8.379E-08  6.676E-08 NE        9.503E-07  6.350E-07  3.962E-07    2.535E-07      1.847E-07 1.497E-07 1.157E-07  9.246E-08 ENE        8.116E-07  4.856E-07  2.919E-07    2.196E-07      1.619E-07 1.239E-07 9.609E-08  7.720E-08 E          5.950E-07  3.202E-07  2.015E-07    2.270E-07      1.745E-07 1.292E-07 1.024E-07  8.308E-08 ESE        4.531E-07  3.300E-07  3.623E-07    4.020E-07      2.822E-07 2.109E-07 1.688E-07  1.405E-07 SE        7.505E-07  4.573E-07  5.490E-07    5.110E-07      3.560E-07 2.648E-07 2.063E-07  1.665E-07 SSE        1.419E-06  7.428E-07  4.527E-07    3.489E-07      2.866E-07 2.131E-07 1.659E-07  1.337E-07 S          1.170E-06  6.099E-07  3.701E-07    2.496E-07      1.810E-07 1.552E-07 1.218E-07  9.867E-08 SSW        1.214E-06  6.327E-07  3.564E-07    2.301E-07      1.621E-07 1.213E-07 9.481E-08  7.660E-08 SW        1.672E-06  7.285E-07  4.057E-07    2.720E-07      1.891E-07 1.400E-07 1.085E-07  8.708E-08 WSW        1.558E-06  6.820E-07  3.804E-07    2.438E-07      1.708E-07 1.271E-07 1.010E-07  8.114E-08 W          1.193E-06  5.214E-07  2.909E-07    1.867E-07      1.372E-07 1.032E-07 8.326E-08  6.654E-08 WNW        4.658E-07  2.480E-07  1.760E-07    1.482E-07      1.024E-07 7.695E-08 5.943E-08  4.796E-08 NW        4.831E-07  2.524E-07  1.965E-07    1.291E-07      9.959E-08 7.356E-08 5.682E-08  4.566E-08 NNW        5.375E-07  2.769E-07  2.128E-07    1.394E-07      1.072E-07 7.913E-08 6.110E-08  4.907E-08
* Units are in miles from the station. As discussed in Oconee UFSAR Section 2.1.1.3, the boundary for establishing gaseous effluent release limits is the exclusion area boundary (EAB). The EAB is at a radius of 1.0 mile from the station center. Each /Q value is calculated at the closest location for the sector, e.g., 1.672E-06 sec/m3 is the /Q value at 1.0 mile (SW) from the station.
Section 6 - Page 12


Section 6 - Page 4Changed title of Table 6.0-3 to: "Oconee 2006 Land Use Census Results."
Oconee Nuclear Station                                                                  January, 2007 Offsite Dose Calculation Manual (ODCM)                                                  Revision 47 Table 6.0-9 (page 2 of 2)
Land use census dates were changed to reflect 2006 census dates.
Oconee Semi-Elevated D/Q Average Values (1988-1992)
(m-2)
Sector    1.0-1.5*    1.5-2.0    2.0-2.5    2.5-3.0        3.0-3.5  3.5-4.0  4.0-4.5    4.5-5.0 N          2.890E-09  1.184E-09  6.225E-10  3.812E-10      2.586E-10 3.380E-10 2.510E-10  1.943E-10 NNE        9.113E-09  3.989E-09  2.013E-09  1.248E-09      8.235E-10 8.997E-10 6.667E-10  5.138E-10 NE        1.295E-08  5.666E-09  2.919E-09  1.729E-09      1.145E-09 1.224E-09 9.140E-10  7.067E-10 ENE        7.899E-09  3.385E-09  1.756E-09  1.095E-09      9.819E-10 7.671E-10 5.749E-10  4.466E-10 E          4.454E-09  1.775E-09  9.252E-10  7.164E-10      7.491E-10 5.267E-10 3.981E-10  3.125E-10 ESE        4.361E-09  1.838E-09  1.086E-09  1.322E-09      8.696E-10 6.161E-10 5.153E-10  4.139E-10 SE        3.397E-09  1.385E-09  8.341E-10  1.649E-09      1.080E-09 7.595E-10 5.629E-10  4.340E-10 SSE        3.333E-09  1.323E-09  6.920E-10  4.404E-10      7.307E-10 5.202E-10 3.922E-10  3.091E-10 S          3.192E-09  1.256E-09  6.530E-10  4.020E-10      2.788E-10 2.177E-10 1.759E-10  1.501E-10 SSW        5.190E-09  1.972E-09  9.899E-10  5.895E-10      3.928E-10 2.842E-10 2.192E-10  1.778E-10 SW        1.205E-08  4.399E-09  2.193E-09  1.299E-09      8.521E-10 6.028E-10 4.518E-10  3.546E-10 WSW        1.047E-08  3.824E-09  1.908E-09  1.127E-09      7.422E-10 5.277E-10 3.980E-10  3.145E-10 W          5.577E-09  2.044E-09  1.025E-09  6.094E-10      4.134E-10 3.405E-10 3.962E-10  3.052E-10 WNW        2.185E-09  9.042E-10  5.220E-10  6.464E-10      4.227E-10 3.188E-10 2.360E-10  1.868E-10 NW        2.097E-09  8.759E-10  5.225E-10  3.196E-10      4.521E-10 3.178E-10 2.353E-10  1.812E-10 NNW        2.461E-09  1.028E-09  6.219E-10  3.765E-10      5.128E-10 3.604E-10 2.667E-10  2.054E-10
* Units are in miles from the station. As discussed in Oconee UFSAR Section 2.1.1.3, the boundary for establishing gaseous effluent release limits is the exclusion area boundary (EAB). The EAB is defined as a 1 mile radius from the station center. Each D/Q value is calculated at the closest location for the sector, e.g., 1.205E-08 m-2 is the D/Q value at 1.0 mile (SW) from the station.
Section 6 - Page 13


Section 6 - Page 6Location 036 symbol added to map in N sector.  
Oconee Nuclear Station                                                                  January, 2007 Offsite Dose Calculation Manual (ODCM)                                                  Revision 47 Table 6.0-10 (page 1 of 2)
Oconee Ground Level /Q Average Values (1988-1992)
(sec/m3)
Sector    1.0-1.5*    1.5-2.0    2.0-2.5    2.5-3.0        3.0-3.5  3.5-4.0  4.0-4.5    4.5-5.0 N          2.115E-06  8.389E-07  4.495E-07  2.822E-07      1.952E-07 1.443E-07 1.117E-07  8.961E-08 NNE        2.898E-06  1.137E-06  6.047E-07  3.775E-07      2.602E-07 1.916E-07 1.480E-07  1.184E-07 NE        3.886E-06  1.529E-06  8.158E-07  5.108E-07      3.529E-07 2.604E-07 2.015E-07  1.616E-07 ENE        3.226E-06  1.277E-06  6.848E-07  4.305E-07      2.983E-07 2.207E-07 1.711E-07  1.374E-07 E          3.522E-06  1.410E-06  7.658E-07  4.866E-07      3.400E-07 2.534E-07 1.977E-07  1.596E-07 ESE        5.964E-06  2.407E-06  1.321E-06  8.459E-07      5.950E-07 4.457E-07 3.493E-07  2.832E-07 SE        7.308E-06  2.972E-06  1.631E-06  1.044E-06      7.342E-07 5.497E-07 4.307E-07  3.490E-07 SSE        6.604E-06  2.657E-06  1.440E-06  9.117E-07      6.354E-07 4.723E-07 3.676E-07  2.962E-07 S          5.278E-06  2.121E-06  1.146E-06  7.237E-07      5.032E-07 3.734E-07 2.901E-07  2.335E-07 SSW        3.986E-06  1.589E-06  8.536E-07  5.370E-07      3.721E-07 2.753E-07 2.135E-07  1.714E-07 SW        4.108E-06  1.620E-06  8.628E-07  5.390E-07      3.715E-07 2.735E-07 2.112E-07  1.689E-07 WSW        3.804E-06  1.503E-06  8.018E-07  5.015E-07      3.460E-07 2.549E-07 1.970E-07  1.577E-07 W          2.978E-06  1.186E-06  6.361E-07  3.995E-07      2.765E-07 2.043E-07 1.583E-07  1.270E-07 WNW        2.201E-06  8.791E-07  4.726E-07  2.974E-07      2.062E-07 1.526E-07 1.183E-07  9.502E-08 NW        2.104E-06  8.385E-07  4.499E-07  2.826E-07      1.957E-07 1.447E-07 1.121E-07  8.991E-08 NNW        2.221E-06  8.860E-07  4.755E-07  2.988E-07      2.069E-07 1.529E-07 1.185E-07  9.508E-08
* Units are in miles from the station. As discussed in Oconee UFSAR Section 2.1.1.3, the boundary for establishing gaseous effluent release limits is the exclusion area boundary (EAB). The EAB is defined as a 1 mile radius from the station center. Each /Q value is calculated at the closest location for the sector, e.g., 4.108E-06 sec/m3 is the /Q value at 1.0 mile (SW) from the station.
Section 6 - Page 14


Section 6 - Page 7Changed title of Figure 6.0-3 to: "ONS 2006 Land Use Census Map."
Oconee Nuclear Station                                                                  January, 2007 Offsite Dose Calculation Manual (ODCM)                                                  Revision 47 Table 6.0-10 (page 2 of 2)
Oconee Ground Level D/Q Average Values (1988-1992)
(m-2)
Sector    1.0-1.5*    1.5-2.0    2.0-2.5    2.5-3.0        3.0-3.5  3.5-4.0  4.0-4.5    4.5-5.0 N          6.916E-09  2.484E-09  1.232E-09  7.255E-10      4.750E-10 3.342E-10 2.477E-10  1.909E-10 NNE        1.642E-08  5.897E-09  2.924E-09  1.722E-09      1.128E-09 7.934E-10 5.880E-10  4.531E-10 NE        2.259E-08  8.114E-09  4.024E-09  2.369E-09      1.551E-09 1.092E-09 8.090E-10  6.235E-10 ENE        1.428E-08  5.130E-09  2.544E-09  1.498E-09      9.810E-10 6.902E-10 5.115E-10  3.942E-10 E          9.899E-09  3.556E-09  1.763E-09  1.038E-09      6.798E-10 4.784E-10 3.545E-10  2.732E-10 ESE        1.336E-08  4.798E-09  2.379E-09  1.401E-09      9.174E-10 6.455E-10 4.784E-10  3.686E-10 SE        1.401E-08  5.034E-09  2.496E-09  1.470E-09      9.625E-10 6.772E-10 5.019E-10  3.868E-10 SSE        1.226E-08  4.404E-09  2.184E-09  1.286E-09      8.420E-10 5.925E-10 4.391E-10  3.384E-10 S          1.008E-08  3.620E-09  1.795E-09  1.057E-09      6.922E-10 4.871E-10 3.610E-10  2.782E-10 SSW        9.941E-09  3.571E-09  1.771E-09  1.043E-09      6.828E-10 4.804E-10 3.560E-10  2.744E-10 SW        1.717E-08  6.169E-09  3.059E-09  1.801E-09      1.180E-09 8.300E-10 6.151E-10  4.740E-10 WSW        1.574E-08  5.655E-09  2.804E-09  1.651E-09      1.081E-09 7.608E-10 5.638E-10  4.345E-10 W          9.988E-09  3.588E-09  1.779E-09  1.048E-09      6.860E-10 4.827E-10 3.577E-10  2.757E-10 WNW        5.953E-09  2.138E-09  1.060E-09  6.244E-10      4.088E-10 2.877E-10 2.132E-10  1.643E-10 NW        5.891E-09  2.116E-09  1.049E-09  6.179E-10      4.046E-10 2.847E-10 2.110E-10  1.626E-10 NNW        6.672E-09  2.397E-09  1.188E-09  6.998E-10      4.582E-10 3.224E-10 2.390E-10  1.841E-10
* Units are in miles from the station. As discussed in Oconee UFSAR Section 2.1.1.3, the boundary for establishing gaseous effluent release limits is the exclusion area boundary (EAB). The EAB is defined as a 1 mile radius from the station center. Each D/Q value is calculated at the closest location for the sector, e.g., 1.717E-08 m-2 is the D/Q value at 1.0 mile (SW) from the station.
Section 6 - Page 15


Oconee Nuclear Station                                                    January, 2007 Offsite Dose Calculation Manual (ODCM)                                    Revision 47 7.0 LICENSEE INITIATED CHANGES All changes made to the Oconee ODCM are reviewed by knowledgeable individual(s), and approved by the Station Manager and the General Office Radiation Protection Manager prior to implementation. The following changes do not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.
Section 2 - Page 1 Removed the "s" from Decant Monitor Tanks because there is only one Decant Monitor Tank.
Section 2 - Page 2 Added "TBSMT" to make clear that the Turbine Building Sump Monitor Tanks are an input source to #3 CTP. Removed "Radwaste Facility monitor tanks" because that source is not ever released to #3 CTP.
Section 3 - Page 5 Corrected typographical error for the Unit 2 Reactor Building Purge controlling RIA and the Unit 3 Reactor Building Purge controlling RIA.
Section 4 - Page 3 Provided detail on what value is assumed for the average dilution flow during the liquid release period of interest.
Removed redundant information related to the recirculation factor.
Section 6 - Page 4 Changed title of Table 6.0-3 to: "Oconee 2006 Land Use Census Results."
Land use census dates were changed to reflect 2006 census dates.
Section 6 - Page 6 Location 036 symbol added to map in N sector.
Section 6 - Page 7 Changed title of Figure 6.0-3 to: ONS 2006 Land Use Census Map.
Figure 6.0-3 regenerated to depict 2006 census data.
Figure 6.0-3 regenerated to depict 2006 census data.
Oconee Nuclear Station
Section 7 - Page 1
 
Oconee Nuclear Station                                                                                                                      January, 2007 Offsite Dose Calculation Manual (ODCM)                                                                                                      Revision 47 APPENDIX A Dose Factors for Exposure to a Semi-Infinite Cloud of Noble Gases*
Ki                            Li                            Mi                        Ni Total Body                        Skin                      Gamma Air                    Beta Air Nuclide mrem/yr/                      mrem/yr/                      mrad/yr/                  mrad/yr/
Ci/m3                      Ci/m3                          Ci/m3                    Ci/m3 AR-41                8.840E+03                    2.690E+03                      9.300E+03                3.280E+03 KR-83M                7.560E-02                    0.000E+00                      1.930E+01                2.880E+02 KR-85M                1.170E+03                    1.460E+03                      1.230E+03                1.970E+03 KR-85                1.610E+01                    1.340E+03                      1.720E+01                1.950E+03 KR-87                5.920E+03                    9.730E+03                      6.170E+03                1.030E+04 KR-88                1.470E+04                    2.370E+03                      1.


Oconee Nuclear Station                                                                                                January, 2007 Offsite Dose Calculation Manual (O D CM)                                                                                                                                                                      Revision 47    APPENDI X B  P i Dose Factors for use in the Gaseous Release Rate Limit Calculations Appendix B Pi Child Inhalation - Page 1 of 3 Agegroup:
Oconee
CHILD      Pathway: Inhalation (INHL) Units: mrem/yr / &#xb5;&#xb5;&#xb5;&#xb5;Ci/m 3 Nuclide Bone Liver Thyroid

Latest revision as of 15:16, 13 March 2020

Rev. 47 to Offsite Dose Calculation Manual (ODCM)
ML071581023
Person / Time
Site: Oconee  Duke Energy icon.png
Issue date: 01/31/2007
From: Ingram C
Duke Power Co
To:
Office of Nuclear Reactor Regulation
References
Download: ML071581023 (169)
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Text

Oconee Nuclear Station Units 1, 2 and 3 ODCM Offsite Dose Calculation Manual 2007

Oconee Nuclear Station Units 1, 2 and 3 OFFSITE DOSE CALCULATION MANUAL (ODCM)

Prepared By: C. D. Ingram Approved By: L. E. Haynes General Office Radiation Protection Technical Manager, RP, Nuclear GO Reviewed By: R. A. Bowser ONS Radiation Protection Approved By: D. A. Baxter ONS Station Manager Reviewed By: M. I. Sanders ONS Radwaste Chemistry REVISION NUMBER EFFECTIVE YEAR 47 2007

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 TABLE OF CONTENTS Executive Summary. . . . . . . . . . . . Executive Summary-1 1.0 Radwaste Systems . . . . . . . . . . . . . 1-1 1.0.1 Liquid Radwaste Processing . . . . . . . . . . . 1-1 1.0.2 Gaseous Radwaste Processing . . . . . . . . . . . 1-3 2.0 Release Rate Calculations . . . . . . . . . . . . 2-1 2.0.1 Liquid Release Rate Limit Calculations . . . . . . . . . 2-1 2.0.1.1 Liquid Radwaste Effluent Line Release Rate Limit Calculation . . . 2-1 2.0.1.2 #3 Chemical Treatment Pond Effluent Line Discharge . . . . . 2-2 2.0.2 Gaseous Release Rate Limit Calculations . . . . . . . . . 2-5 2.0.2.1 Unit Vent Discharge Release Rate Limit Calculation . . . . . 2-5 3.0 Setpoint Calculations . . . . . . . . . . . . . 3-1 3.0.1 Liquid Radiation Monitor Setpoint Calculations . . . . . . . 3-1 3.0.2 Gaseous Radiation Monitor Setpoint Calculations . . . . . . . 3-5 3.0.2.1 Unit Vents Setpoints (RIA-45 and RIA-46) . . . . . . . 3-7 3.0.2.2 Radwaste Facility Setpoints (4RIA-45) . . . . . . . . 3-8 3.0.2.3 Interim Radwaste Building Setpoints (RIA-53) . . . . . . 3-9 3.0.2.4 Waste Gas Decay Tank Setpoints (RIA-37 and RIA-38) . . . . . 3-9 4.0 Effluent Dose Models . . . . . . . . . . . . . 4-1 4.0.1 Liquid Effluent Dose Model for the Maximum Exposed Individual . . . . 4-1 4.0.2 Gaseous Effluent Dose Model for the Maximum Exposed Individual . . . . 4-7 4.0.3 Direct Radiation . . . . . . . . . . . . . 4-18 4.0.4 Effluent Apportionment . . . . . . . . . . . . 4-18 5.0 Fuel Cycle Calculations . . . . . . . . . . . . . 5-1 5.0.1 Milling . . . . . . . . . . . . . . . 5-1 5.0.2 Conversion . . . . . . . . . . . . . . 5-1 5.0.3 Enrichment . . . . . . . . . . . . . . 5-1 5.0.4 Fuel Fabrication . . . . . . . . . . . . . 5-1 5.0.5 Nuclear Power Production . . . . . . . . . . . 5-2 5.0.6 Fuel Reprocessing . . . . . . . . . . . . . 5-2 5.0.7 40CFR190 Total Dose Determination . . . . . . . . . 5-2 6.0 Environmental Locations . . . . . . . . . . . . 6-1 6.0.1 Site Description and Sample Locations . . . . . . . . . 6-1 6.0.2 Land Use Census Data . . . . . . . . . . . . 6-1 6.0.3 Oconee Meteorology: Relative Air Concentrations and Deposition . . . . 6-8 6.0.3.1 XOQDOQ Methodology and Assumptions . . . . . . . 6-8 6.0.3.2 Meteorological Data . . . . . . . . . . . 6-9 6.0.3.3 Annual XOQDOQ Comparison to the ODCM . . . . . . 6-10 7.0 Licensee Initiated Changes . . . . . . . . . . . . 7-1 i

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 Appendices Appendix A: Dose Factors for Exposure to a Semi-Infinite Cloud of Noble Gases . . . A-1 Appendix B: Pi Dose Factors for use in the Gaseous Release Rate Limit Calculations . . . B-1 Appendix C: Ai Adult Dose Factors for use in the Liquid Dose Calculations . . . . C-1 Appendix D: Ai Teen Dose Factors for use in the Liquid Dose Calculations . . . . D-1 Appendix E: Ai Child Dose Factors for use in the Liquid Dose Calculations . . . . E-1 Appendix F: Ai Infant Dose Factors for use in the Liquid Dose Calculations . . . . F-1 Appendix G: Ri Adult Dose Factors for use in the Gaseous Dose Calculations . . . . G-1 Appendix H: Ri Teen Dose Factors for use in the Gaseous Dose Calculations . . . . H-1 Appendix I: Ri Child Dose Factors for use in the Gaseous Dose Calculations . . . . I-1 Appendix J: Ri Infant Dose Factors for use in the Gaseous Dose Calculations . . . . J-1 LIST OF FIGURES 1.0-1 Liquid Radwaste System . . . . . . . . . . . . . 1-2 1.0-2 Gaseous Radwaste System (4 pages) . . . . . . . . . . 1-4 2.0-1 Liquid Radwaste Discharge Locations . . . . . . . . . . 2-4 6.0-1 Sampling Locations Map (Site Boundary) . . . . . . . . . . 6-5 6.0-2 Sampling Locations Map (Ten Mile Radius) . . . . . . . . . 6-6 6.0-3 Land Use Census Map . . . . . . . . . . . . . 6-7 LIST OF TABLES 3.0-1 RIA-33 Cs-137 Equivalents. . . . . . . . . . . . . 3-4 3.0-2 Xe-133 Equivalents . . . . . . . . . . . . . . 3-11 6.0-1 Sampling Locations . . . . . . . . . . . . . . 6-2 6.0-2 TLD Sites . . . . . . . . . . . . . . . 6-3 6.0-3 Land Use Census Results . . . . . . . . . . . . . 6-4 6.0-4 Terrain Heights Above ONS Yard Grade Elevation (m) . . . . . . . 6-9 6.0-5 ONS Atmospheric Stability Frequency (1988 - 1992) . . . . . . . 6-10 6.0-6 ONS Frequency of Wind Direction and Speed (1988 - 1992) . . . . . . 6-10 6.0-7 ONS Limiting /Q and D/Q Values (1988-1992) . . . . . . . . 6-11 6.0-8 ONS Delta-T Ranges per Vertical Separation Distances . . . . . . . 6-11 6.0-9 Oconee Semi-Elevated /Q and D/Q Average Values (1988-1992) . . . . . 6-12 6.0-10 Oconee Ground Level /Q and D/Q Average Values (1988-1992) . . . . . 6-14 ii

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 EXECUTIVE

SUMMARY

The Oconee Nuclear Station (ONS) Offsite Dose Calculation Manual (ODCM) provides the methodology and parameters to be used in the calculation of offsite doses due to normal operation radioactive liquid and gaseous effluents to assure compliance with the dose limitations of the Selected Licensee Commitments (SLCs, UFSAR Chapter 16) and Technical Specifications. These dose limitations assure that:

(1) the concentration of radioactive liquid effluents released from the site to the unrestricted area will be limited to 10 times the effluent concentration (EC) levels of 10CFR20, Appendix B, Table 2, and 2.0E-04 Ci/ml for dissolved and entrained noble gases; (2) the exposures to any individual member of the public from radioactive liquid effluents will not result in doses greater than the ALARA design objectives of 10CFR50, Appendix I or the 10CFR20 limits; (3) the dose rate at any time at the site boundary from radioactive gaseous effluents will be limited to: for noble gases; less than or equal to 500 mrem/yr to the whole body, and less than or equal to 3000 mrem/yr to the skin; and for iodine-131 and iodine-133, for tritium, and for all radioactive materials in particulate form with half-lives greater than 8 days; less than or equal to 1500 mrem/yr to any organ; (4) the exposure to any individual member of the public from radioactive gaseous effluents will not result in doses greater than the ALARA design objectives of 10CFR50, Appendix I or the 10CFR20 limits; and (5) the dose to any individual member of the public from the nuclear fuel cycle will not exceed the limits of 40CFR190.

The methodology and parameters used to assure compliance with the dose limitations described above shall be used to prepare the radioactive liquid and gaseous effluent reports required by the SLCs and Technical Specifications. Dose calculations that demonstrate compliance with 40CFR190 will be considered to demonstrate compliance with the 10CFR20 0.1-rem annual dose limit. The ODCM also provides the Executive Summary - Page 1

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 methodology and parameters to be used in the calculation of radioactive liquid and gaseous effluent monitoring instrumentation alarm /trip setpoints to assure compliance with the concentration and dose rate limitations of the SLCs and Technical Specifications. Normally RETDAS, a computer code that implements NUREG-0133 methodology, is used for the calculation of offsite doses, but the ODCM also provides a method for the calculation of offsite doses when RETDAS is not available.

The ODCM has been prepared as generically as possible in order to minimize the need for revisions. However, some changes to the ODCM such as land-use census data are expected on an annual basis. Any changes to the methodology and parameters to be used in this ODCM shall be reviewed by knowledgeable individual(s), and approved by the Station Manager and the General Office Radiation Protection Manager prior to implementation. Changes to the ODCM shall be submitted to the Nuclear Regulatory Commission in accordance with the SLCs and Technical Specifications.

The ODCM does not replace any station implementing procedures. Programmatic controls for radioactive effluents and radiological environmental monitoring are contained in the Administrative Controls chapter of the Technical Specifications.

Procedural details for radioactive effluents and radiological environmental monitoring consisting of licensee commitments, applicability, remedial actions, surveillance requirements, and the bases for these requirements are contained in Section 16.11 of the SLCs.

Executive Summary - Page 2

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 1.0 RADWASTE SYSTEMS 1.0.1 LIQUID RADWASTE PROCESSING The liquid radwaste system at Oconee Nuclear Station is used to collect and treat liquid chemical and radiochemical byproducts of unit operation. The system produces effluents that are discharged in small, dilute quantities to the environment. The means of treatment vary with waste type and desired product in the various systems:

(A) Filtration - Waste sources are filtered prior to processing as necessary.

(B) Ion Exchange - Ion exchange is used to remove radioactive ions from solution. Also, ion exchange is normally used in removing cations (cobalt, cesium, manganese) and anions (chloride, fluoride) from the filtrate in order to purify the filtrate for release.

(C) Gas Stripping - Removal of gaseous radioactive fission products is accomplished through venting of atmospheric holdup tanks.

Figure 1.0-1 is a schematic representation of the liquid radwaste system at Oconee.

Section 1 - Page 1

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 Figure 1.0-1 Oconee Nuclear Station Liquid Radwaste System Section 1 - Page 2

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 1.0.2 GASEOUS RADWASTE PROCESSING The purpose of the gaseous waste disposal system is to:

(1) Maintain a non-oxidizing cover gas of nitrogen in tanks and equipment that contain potentially radioactive gas; (2) Hold up radioactive gas for decay; and (3) Release gases (radioactive and non-radioactive) to the atmosphere under controlled conditions.

During power operation of the facilities, radioactive materials released to the atmosphere in gaseous effluents include low concentrations of fission product noble gases (krypton and xenon), halogens (mostly iodines), tritium contained in water vapor, and particulate material including both fission products and activated corrosion products.

The primary source of gaseous radioactive wastes is from the degassing of the primary coolant during letdown of the cooling water into various holding tanks. Additional sources of gaseous waste activity include the auxiliary building exhaust, spent fuel area exhaust, the discharge from the steam jet air ejectors, and purging and venting of the reactor containment building.

All components that can contain potentially radioactive gases are vented to a vent header.

The vent gases are subsequently drawn from this header by one of four waste gas compressors or a waste gas exhauster. The waste gas compressor discharges through a waste gas separator to one of seven waste gas tanks. The waste gas tanks and the waste gas exhauster discharge to the unit vent after passing through a filter bank consisting of a prefilter, an absolute filter, and a charcoal filter.

Radioactive gases may be released inside the reactor containment building when components of the primary system are opened to the building atmosphere for operational reasons or where minor leaks occur in the primary system. Prior to access, the reactor containment atmosphere will be monitored for radioactivity and, when necessary, purged through prefilters, high-efficiency particulate air (HEPA) filters, and charcoal filters, and released to the atmosphere through the unit vent. The purge equipment is sized for a flow rate of 50,000 cfm providing approximately 1.5 air changes per hour in the reactor building. Units 1, 2, and 3 have a separate vent stack which services each unit.

Figure 1.0-2 is a schematic representation of the gaseous radwaste system at Oconee.

Section 1 - Page 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 Figure 1.0-2 Oconee Nuclear Station Gaseous Radwaste System Page 1 of 4 Section 1 - Page 4

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 Figure 1.0-2 Oconee Nuclear Station Gaseous Radwaste System Page 2 of 4 Section 1 - Page 5

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 Figure 1.0-2 Oconee Nuclear Station Gaseous Radwaste System Page 3 of 4 Section 1 - Page 6

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 Figure 1.0-2 Oconee Nuclear Station Gaseous Radwaste System Page 4 of 4 Section 1 - Page 7

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 2.0 RELEASE RATE CALCULATIONS 2.0.1 LIQUID RELEASE RATE LIMIT CALCULATIONS There are two liquid radwaste discharge points to the environment at Oconee; (1) the liquid radwaste effluent line to the Keowee Hydroelectric Unit Tailrace, and (2) the #3 Chemical Treatment Pond effluent line to the Keowee River (See Figure 2.0-1).

2.0.1.1 LIQUID RADWASTE EFFLUENT LINE RELEASE RATE LIMIT CALCULATION Liquid releases to the Keowee Hydroelectric Unit Tailrace normally contain the radioactive releases from the site including effluents from the Waste Monitor Tanks, Recycle Monitor Tanks, and Decant Monitor Tank. The Keowee Tailrace discharge point can also contain Turbine Building Sump Monitor Tank (TBSMT) releases, however TBSMT effluent normally contains very low (if any) activity, and, therefore is transferred to the #3 Chemical Treatment Pond prior to release. Dilution flow for the liquid radwaste effluent line is provided by the Keowee Hydroelectric Unit and the Keowee Hydro Fire Protection liquid waste release mixing line. For purposes of the release rate calculation, Keowee hydro dilution flow is assumed to be a minimum leakage flow of 38 cfs, and a maximum flow of 6600 cfs based on one hydro unit operating at 50% power. The Keowee Hydro Fire Protection liquid waste release mixing line provides an additional 38 cfs dilution flow. Since Keowee Hydro typically releases only a small percentage of time during the year, 76 cfs (38 cfs leakage + 38 cfs mixing line) is normally assumed for dilution flow when performing liquid release rate calculations.

To comply with Technical Specifications and Selected Licensee Commitments, and to assure that the concentration of radioactive liquid effluents released from the site to the unrestricted area is limited to 10 times the effluent concentrations (ECs) of 10CFR20, Appendix B, Table 2, Column 2, and 2.0E-04 PCi/ml for dissolved and entrained noble gases, the following release rate limit calculation shall be performed for liquid releases to the Keowee Hydro Tailrace via the liquid radwaste effluent line:

f d F y (DF  1 ) Condition: DF ! 1.0 Equation 2.1 where:

f = the undiluted effluent flow, in gpm.

F = the dilution flow available, in gpm.

= normally 3.41E+04 gpm (76 cfs, based on a leakage rate of 38 cfs (19 cfs per Keowee Hydro unit), plus the Keowee Hydro Fire Protection liquid waste release Section 2 - Page 1

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 mixing line whose flow rate is 38 cfs. When Keowee Hydro enters an outage one of the two units is taken offline which temporarily reduces the amount of leakage by half. Therefore, during a Keowee Hydro outage the dilution flow is assumed to be 57 cfs (19 cfs leakage plus 38 cfs raw water, (2.56E+04 gpm)).

= or 2.96E+06 gpm (6600 cfs, based on one hydro unit operating at 50% power).

This value is only used if it is known that Keowee Hydro is discharging.

DF = required dilution factor to be applied to the undiluted effluent flow, unitless.

Ci DF V u i 10 u ECi Equation 2.2 Note:

If DF d 1.0 then no dilution is required and the release rate is unrestricted.

If DF ! 1.0 then dilution flow is required and the release rate is calculated using Equation 2.1. Equation 2.1 is used only when DF ! 1.0.

V = the most restrictive recirculation factor at equilibrium, (dimensionless). The recirculation factor accounts for the fraction of discharged water reused by the station. This value equals 1.0 since discharged liquid effluent is not reused at Oconee.

Ci = the concentration of radionuclide, i, in the undiluted liquid effluent, in PCi/ml.

ECi = the concentration of radionuclide, i, from 10CFR20, Appendix B, Table 2, Column 2, in PCi/ml. Note: if radionuclide, i, is a dissolved noble gas, then ECi

= 2.00E-05 PCi/ml.

Once the maximum release rate, f, is calculated the value is multiplied by 0.8 for additional conservatism.

2.0.1.2 #3 CHEMICAL TREATMENT POND EFFLUENT LINE DISCHARGE The #3 Chemical Treatment Pond (CTP) effluent line is the release point for station effluents that are normally considered to be non-radioactive; that is, the pond's effluent will not normally contain measurable activity above background with the exception of very low tritium activity. Tritium releases from the #3 CTP typically account for much less than 1% of the station total tritium release. It is assumed that no activity is present in the effluent until indicated by radiation monitoring measurements on the pond's inputs and/or by periodic analyses of the composite sample collected at the pond's discharge point. Inputs to this pond include the station's yard drain system, the decant water from the Powdex system, and the discharge from the Turbine Building Sump/TBSMT system whose contents have been determined to be below background. Inputs that have radiation Section 2 - Page 2

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 monitors associated with them will be set to assure that Selected Licensee Commitment 16.11-1 will not be exceeded. #3 CTP is a continuous release path that discharges to the Keowee River (see Figure 2.0-1).

The #3 CTP may also be the discharge path for large volumes of slightly contaminated water following a primary-to-secondary leak so long as administrative procedures are implemented to assure that release rate calculations similar to that used in Section 2.0.1.1 are performed, that all detectable radionuclides will be accounted for, and that no station limits will be exceeded.

Section 2 - Page 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 Figure 2.0-1 Liquid Radwaste Discharge Locations Section 2 - Page 4

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 2.0.2 GASEOUS RELEASE RATE LIMIT CALCULATIONS The three unit vents are the primary gaseous radioactive release points at Oconee. The unit vents are the semi-elevated release points for waste gas decay tanks, containment building purges, auxiliary building ventilation, spent fuel pool ventilation, and the condenser air ejector (see Figure 1.0-2, pages 1, 2, and 3). Each unit vent contains multi-range radiation monitors (RIAs) and flow rate measuring instrumentation.

There are three other separate gaseous effluent release points at Oconee; the Hot Machine Shop, Interim Radwaste Building and Radwaste Facility that are normally considered non-radioactive; that is, it is possible but unlikely that the effluent will contain measurable activity above background. Each of these release points are considered ground-level, and each has an effluent sampler and flow monitoring device (see Figure 1.0-2, page 4). In addition, the Interim Radwaste Building and Radwaste Facility have a RIA.

2.0.2.1 UNIT VENT DISCHARGE RELEASE RATE LIMIT CALCULATION In order to comply with Technical Specifications and Selected Licensee Commitments and to assure that the dose rate, at any time, at or beyond the site boundary due to radioactive materials released in gaseous effluents from the site is limited to: d 500 mrem/yr to the total body, and d 3000 mrem/yr to the skin for the noble gases, and is limited to d 1500 mrem/yr to any organ for radioiodine and for radioactive materials in particulate form, and radionuclides other than noble gases with half lives greater than 8 days, the following release rate and radiation monitor setpoint calculations shall be performed for releases from the waste gas decay tanks and the containment building. The release rate calculations when solved for the flow rate, f, are the release rates for noble gases and for radioiodines, particulates and other radionuclides with half-lives greater than 8 days. The most conservative release rate calculated shall control the flow rate. The following equations are based on the site dose rate limits. When applied to the individual release points the site dose rate values are apportioned 1/3 to each unit vent.

a. Noble Gases Total Body:

§ F *

¨¨ K i u Q

u Qi ¸¸  500 mrem/yr Equation 2.3 i © ¹ Skin:

§ F *

¨¨ L  1.1M i i u Q

u Qi ¸¸  3000 mrem/yr Equation 2.4 i © ¹ Section 2 - Page 5

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47

b. Radioiodines, Particulates, and Others Inhalation, Ingestion and Ground Organ Pathways:

p i Popi u W u Qi u Ei  1500 mrem/yr To include both the food and ground organ dose and the inhalation organ dose the equation can be expanded to:

^P p i opi food/gr u WD / Q  Popi inhal u WF / Q` u Qi u Ei  1500 mrem/yr Equation 2.5 where:

Ki = the total body dose factor due to gamma emissions for each identified noble gas radionuclide, i, in mrem/yr per PCi/m3 (See Appendix A).

Li = the skin dose factor due to beta emissions for each identified noble gas radionuclide, i, in mrem/yr per PCi/m3 (See Appendix A).

Mi = the air dose factor due to gamma emissions for each identified noble gas radionuclide, i, in mrad/yr per PCi/m3 (See Appendix A).

Popi = the dose parameter for radionuclides other than noble gases for the inhalation pathway, in mrem/yr per PCi/m3 and for the food and ground plane pathways in (m2 u (mrem/yr per PCi/sec)) for organ, o, and radionuclide, i, (See Appendix B for the pathway specific dose commitment factors). Note: NUREG-1301, page 75, specifies use of the Child age group, Inhalation pathway, for the Popi values.

F/Q = the highest calculated annual average dispersion parameter for any area at or beyond the site boundary in sec/m3. For the Oconee Unit Vents this value is 1.672E-6 sec/m3. The location is the SW sector at 1.0 mile for semi-elevated releases. For the Hot Machine Shop, Interim Radwaste Building and Radwaste Facility this value is 7.308E-6 sec/m3. The location is the SE sector at 1.0 mile for ground-level releases. As discussed in Oconee UFSAR Section 2.1.1.3, the boundary for establishing gaseous effluent release limits is the exclusion area boundary (EAB). The EAB is defined as a 1 mile radius from the station center.

W = the highest calculated annual average dispersion or deposition parameter for estimating the maximum dose rate to an individual from the total inhalation, food, and ground plane pathways resulting from semi-elevated releases or ground-level releases:

Section 2 - Page 6

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 WF/Qse = 1.672E-6 sec/m3, for the inhalation pathway and the airborne H-3 food pathway. The location is the SW sector at 1.0 mile for semi-elevated releases.

WD/Qse = 1.295E-8 m-2, for the food and ground plane pathways. The location is the NE sector at 1.0 mile for semi-elevated releases.

WF/Qgl = 7.308E-6 sec/m3, for the inhalation pathway and the airborne H-3 food pathway. The location is the SE sector at 1.0 mile for ground-level releases.

WD/Qgl = 2.259E-8 m-2, for the food and ground plane pathways. The location is the NE sector at 1.0 mile for ground-level releases.

Ei = the filter removal factor for radionuclide, i, e.g., for 99% removal Ei = 0.01.

For iodine removal by charcoal adsorbers Ei = 0.1.

For particulate removal by HEPA filters Ei = 0.01.

Qi = the release rate of radionuclide, i, in gaseous effluent from all release points at the site, in PCi/sec.

Qi k 1Cif y k 2 4.72E  02 u Cif Equation 2.6 where:

Ci = the concentration of radionuclide, i, in undiluted gaseous effluent, in PCi/ml.

f = the undiluted effluent flow, in ft3/min.

k1 = conversion factor, 2.83E+04 cc/ft3.

k2 = conversion factor, 6.0E+01 sec/min.

Substituting the expression for Qi in Equation 2.6 into Equations 2.3, 2.4, and 2.5, and solving for the flow rate, f, in each equation gives:

Noble Gases - Total Body Maximum Release Rate:

500 ftb 

4.72E  02 u FQ u i Ki u Ci Section 2 - Page 7

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 Noble Gases - Skin Maximum Release Rate:

3000 fsk 

4.72E  02 u FQ u > Li  1.1Mi u Ci @

i Radioiodines, Particulates, and Others - Organ Maximum Release Rate:

1500 for 

4.72E  02 u ^P p i opi food/gr u WD / Q  Popi inhal u WF / Q` u Ei u Ci ftb, fsk, and for, are calculated for each batch prior to release. The most limiting gaseous release rate is used to assure that no instantaneous dose rate limit is exceeded.

Once the maximum release rate, f, is calculated the value is multiplied by 0.8 for additional conservatism.

Section 2 - Page 8

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 Derivations of Iodine, Particulate, and H-3 Dose Commitment Factors (Popi)

Inhalation Pathway - Child Age Group P K c ( BR )( DFA )

opi oi Formula: from NUREG-0133, page 25.

Where:

Popi Dose commitment factor for Child age group, organ o, nuclide i, for the inhalation pathway (mrem/yr per PCi/m3). (See Appendix B for the pathway specific dose commitment factors).

K' Units conversion factor pCi/PCi (106).

BR Breathing rate for the Child age group (m3/yr, from Regulatory Guide 1.109):

Child - 3700 DFAoi Organ inhalation dose conversion factor for Child age group, organ o, nuclide i, (mrem/pCi), from Table E-9 of Regulatory Guide 1.109.

Section 2 - Page 9

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 3.0 SETPOINT CALCULATIONS 3.0.1 LIQUID RADIATION MONITOR SETPOINT CALCULATIONS As shown on Figure 1.0-1, RIA-33 is the controlling radiation monitor for liquid batch releases at Oconee. Once the liquid release rate parameters have been established radiation monitor setpoints shall be calculated to assure that the concentration of radioactive liquid effluents released from the site to the unrestricted area is limited to ten times the effluent concentrations (ECs) of 10CFR20, Appendix B, Table 2, Column 2, and 2.0E-04 Ci/ml for dissolved and entrained noble gases. By substituting the dilution factor (DF) from Equation 2.2 into Equation 2.1, solving for the undiluted liquid effluent concentration, Ci, and accounting for the monitor background reading, the liquid radiation monitor setpoint can be readily obtained by multiplying Ci by the radiation monitor correlation factor, CFi, as follows:

Ci (F + f ) x (10 x ECi )

Equation 3.1 x f SP (C i

i x CFi ) + bkg Equation 3.2 where:

Ci = the maximum allowable concentration of radionuclide, i, in the undiluted liquid effluent, in Ci/ml.

SP = radiation monitor setpoint, in cpm.

CFi = radiation monitor correlation factor for radionuclide, i, in cpm/Ci/ml =

8.00E+07 cpm/Ci/ml for RIA-33.

bkg = background reading for the radiation monitor, in cpm.

All other parameters were previously defined.

Using conservative or "worst-case" parameters in Equation 3.1 and Equation 3.2 can provide a liquid radiation monitor setpoint that does not need to be revised for every release if activity is low enough to allow for this type of operation such as with continuous releases from the #3 CTP release point. However, for batch releases, e.g.,

waste monitor tanks, through the liquid radwaste effluent line to the Keowee hydro Section 3 - Page 1

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 tailrace the RIA-33 radiation monitor setpoints are calculated based on the actual expected activity in the release as follows:

First the "Correlation Concentration" (C CONC) is calculated:

C CONC = (C i

i x EQi )

where:

Ci = Undiluted liquid effluent concentration for each isotope, excluding tritium, Ci/ml.

EQi = RIA-33 Cs-137 equivalence factor for each isotope, excluding tritium, to that of Cs-137 due to different gamma energies and abundance. This factor includes a 4-hour decay time due to the average time between sample and release. (See Table 3.0-1)

Next the RIA-33 setpoints are determined as follows:

If C CONC is > 9.0E-6 Ci/ml then three setpoint values are calculated. The actual "expected" count rate for the release is defined as the "Midpoint of Expected Range".

The Alert setpoint is defined as 1.5 times the expected counts from activity in the liquid effluent plus background. If the Alert setpoint is exceeded, but there is no upward trend, the release will be allowed to continue. If RIA-33 continues to trend upward then the release will be manually terminated. The "Upper Limit of Expected Range" is defined as 3 times the expected counts from activity in the liquid effluent plus background. The Upper Limit of Expected Range is called the "Trip" setpoint. If the Trip setpoint is exceeded the release will be automatically terminated. The "Lower Limit of Expected Range" is defined as 3 times lower than the expected counts from activity in the liquid effluent plus background. The Lower Limit of Expected Range provides assurance that the correct liquid effluent is being released. If the RIA-33 count rate does not increase to at least the Lower Limit of the Expected Range then the release will be terminated, and a new sample analysis will be performed. The four RIA-33 setpoints are calculated as follows:

Lower Limit of Expected Range = C CONC x (8.00E7/3) cpm/(Ci/ml) +

RIA-33 BKG Midpoint of Expected Range = C CONC x 8.00E7 cpm/(Ci/ml) +

RIA-33 BKG Alert Setpoint = C CONC x (8.00E7x1.5) cpm/(Ci/ml) +

RIA-33 BKG Upper Limit of Expected Range = C CONC x (8.00E7x3) cpm/(Ci/ml) +

(Trip Setpoint) RIA-33 BKG Section 3 - Page 2

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 If C CONC is 9.05E-6 Ci/ml then the RIA-33 setpoint is 2.16E3 cpm plus background (BKG) as the Upper Limit of Expected Range. This setpoint is used for low activity releases, and is based on limiting the concentration in the effluent to 10 times the 10CFR20 EC of Cs-134 which has the lowest effluent concentration value (9.0E-7 Ci/ml) for any detectable radionuclide in the effluent.

Section 3 - Page 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 Table 3.0-1 RIA-33 Cs-137 Equivalents Isotope Equivalence Isotope Equivalence Isotope Equivalence Factor Factor Factor Be-7 0.1462 Mo-99 0.2668 La-141 0.0155 F-18 0.5788 Tc-99m 0.00 La-142 0.2942 Na-24 0.8519 Tc-101 0.00 Ce-141 0.00 Cl-38 0.0090 Ru-103 1.3368 Ce-143 0.7826 K-40 0.1094 Ru-105 0.8783 Ce-144 0.0273 Cr-51 0.1438 Ru-106 0.4429 I-130 3.3095 Mn-54 1.0617 Ag-108m 3.4473 I-131 1.4051 Mn-56 0.4992 Ag-110m 3.5179 I-132 1.0259 Fe-59 1.0556 Cd-115 0.5201 I-133 1.1857 Co-57 0.0022 Cd-115m 0.0235 I-134 0.1388 Co-58 1.4735 In-115m 0.3631 I-135 0.9374 Co-60 2.0495 Sb-122 0.9218 Ar-41 0.2229 Cu-64 0.3954 Sb-124 2.1617 Kr-85 0.0059 Ni-65 0.1591 Sb-125 1.1308 Kr-85m 0.4280 Zn-65 0.5584 Sb-126 5.1762 Kr-87 0.1213 Zn-69m 1.1391 Sn-113 0.9971 Kr-88 0.5278 Se-75 1.3092 Sn-123 0.0066 Kr-89 0.00 Br-80m 0.0860 Sn-126 0.00 Xe-131m 0.0167 Br-82 3.4691 Te-125m 0.00 Xe-133 0.0006 Br-83 0.0059 Te-127 0.0134 Xe-133m 0.1172 Br-84 0.0053 Te-127m 0.0001 Xe-135 0.8564 Br-85 0.00 Te-129 0.0138 Xe-135m 0.00 Rb-86 0.0894 Te-129m 0.0507 Xe-137 0.00 Rb-88 0.00 Te-131 0.0008 Xe-138 0.00 Rb-89 0.00 Te-131m 1.8463 Nd-147 0.2619 Sr-89 0.0002 Te-132 0.9766 Hf-181 1.4209 Sr-91 0.6460 Te-134 0.0408 W-187 0.8027 Sr-92 0.3900 Cs-134 2.5804 Tl-208 0.00 Y-91 0.0031 Cs-136 3.1916 Bi-212 0.0144 Y-91m 0.0439 Cs-137 1.00 Bi-214 0.0003 Y-92 0.1334 Cs-138 0.0120 Pb-212 0.4497 Y-93 0.1091 Ba-133 1.3648 Pb-214 0.0020 Zr-95 1.0909 Ba-139 0.0203 Ra-226 0.0320 Zr-97 1.1210 Ba-140 0.5307 Ac-228 0.8261 Nb-95 1.0821 Ba-141 0.0002 Th-228 0.0038 Nb-95m 0.2919 Ba-142 0.00 Np-239 0.3996 Nb-97 0.1164 La-140 2.3237 Section 3 - Page 4

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 3.0.2 GASEOUS RADIATION MONITOR SETPOINT CALCULATIONS The unit vent radiation monitor setpoints are established at the Oconee Nuclear Station to help ensure that gaseous release rate limits are not exceeded. For some release pathways in which a specific RIA exists, the setpoints also help to ensure that the effluent being released is the same concentration as indicated by manual samples, e.g. effluent from waste gas decay tanks, thereby reducing the likelihood of releasing the wrong tank. For instances in which the RIA which normally controls the release is not operable, or is "out of service", independent manual samples (IMS) are collected and the noble gas constituents from both samples are compared to help ensure that the intended "batch" is being released. For certain low potential release types, e.g. Integrated Leak Rate Tests, no RIA exists to ensure that release rate limits are not exceeded or to ensure that the effluent being released is the "expected" concentration. For such pathways, independent manual samples are required to be collected and noble gas constituents compared prior to release. The following list defines the controlling RIA for the various gaseous effluent release types at Oconee:

Pathway Controlling RIA Unit 1 "A" Waste Gas Decay Tank 1&2 RIA 37/38 Unit 1 "B" Waste Gas Decay Tank 1&2 RIA 37/38 Unit 1 "C" Waste Gas Decay Tank 1&2 RIA 37/38 Unit 1 "D" Waste Gas Decay Tank 1&2 RIA 37/38 Unit 3 "A" Waste Gas Decay Tank 3 RIA 37/38 Unit 3 "B" Waste Gas Decay Tank 3 RIA 37/38 Unit 3 "C" Waste Gas Decay Tank 3 RIA 37/38 Unit 1 Reactor Building Purge 1 RIA 45/46 Unit 2 Reactor Building Purge 2 RIA 45/46 Unit 3 Reactor Building Purge 3 RIA 45/46 Unit 1 Depressurization IMS 1 RIA 45/46 Alarm Only Unit 2 Depressurization IMS 2 RIA 45/46 Alarm Only Unit 3 Depressurization IMS 3 RIA 45/46 Alarm Only Unit 1 Hydrogen Recombiner IMS 1 RIA 45/46 Alarm Only Unit 2 Hydrogen Recombiner IMS 2 RIA 45/46 Alarm Only Unit 3 Hydrogen Recombiner IMS 3 RIA 45/46 Alarm Only Unit 1 Integrated Leak Rate Test IMS Unit 2 Integrated Leak Rate Test IMS Unit 3 Integrated Leak Rate Test IMS The following sections describe the methods by which setpoints are established. In general, gaseous radiation monitors are calibrated to Xe-133, and for continuous release points, e.g., the three unit vents, are preset at a maximum value based on the 500 mrem/year total body gaseous release rate limit according to the following methodology:

Section 3 - Page 5

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 Note: when applied to the individual release points the 500 mrem/year site dose rate value is apportioned 30% to each Unit Vent (RIA-45 and RIA-46) semi-elevated release point.

The remaining 10% is allocated to the three ground-level release points, the Hot Machine Shop (no monitor), Interim Radwaste Building (RIA-53) and Radwaste Facility (4RIA-45) that are normally considered non-radioactive. Recall from Section 2.0.2.1 the following equation:

KXe 133 x / Q x QXe 133 < 500 mrem/yr Solve for QXe-133:

500 QXe 133 < Equation 3.4 KXe 133 x / Q From Equation 2.6:

QXe 133 = 4.72E + 02 x CXe 133 x f Equation 3.5 Substitute Equation 3.5 into Equation 3.4:

500 4.72E + 02 x CXe 133 x f <

KXe 133 x / Q Solve for CXe-133:

500 CXe 133 <

4.72E + 02 x f x KXe 133 x / Q CXe 133 SP = + bkg Equation 3.6 CF where:

KXe-133 = 2.94E+02, the total body dose factor due to gamma emissions for Xe-133, in mrem/year per Ci/m3 (See Appendix A).

/Q = the highest calculated semi-elevated annual average dispersion parameter for any area at or beyond the site boundary in sec/m3. For Oconee this value is 1.672E-6 sec/m3. The location is the SW sector at 1.0 mile.

QXe-133 = Xe-133 equivalent release rate limit for the noble gas total body dose pathway, in Ci/sec.

4.72E+02 = Conversion factor, (cc/ft3)/(sec/min).

Section 3 - Page 6

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 CXe-133 = the maximum allowable Xe-133 equivalent concentration in the gaseous effluent, in Ci/cc.

f = the gaseous effluent flow from the tank, building, or vent, in ft3/min.

SP = radiation monitor setpoint, in cpm.

CF = the Xe-133 equivalent monitor correlation factor, in Ci/cc/cpm.

bkg = the radiation monitor background reading, in cpm.

Equation 3.6 provides the methodology to calculate the maximum setpoint for releases from the Unit Vents (RIA-45 and RIA-46), Radwaste Facility (4RIA-45), and Interim Radwaste Building (RIA-53).

3.0.2.1 UNIT VENTS SETPOINTS (RIA-45 and RIA-46)

Reactor Building purges from all 3 units are released via the applicable unit vent, either Unit 1, Unit 2, or Unit 3. Each of the 3 unit vents are monitored by a normal/low range RIA (RIA-45) and a high range RIA (RIA-46). In addition to Reactor Building purges, all other releases from the main plant, including the Auxiliary Building ventilation, Waste Gas Decay Tanks, and the Spent Fuel Pools are monitored by each unit's RIA-45 and RIA-46. However, RIA-45 and RIA-46 on each unit vent have release termination authority only for Reactor Building purge releases. Each unit's RIA-45 and RIA-46 will, when operable, activate Control Room alarms if the unit vent concentration exceeds the monitor's setpoint value. The setpoints for each unit's RIA-45 and RIA-46 are established on a "worst case" basis, with the upper bound normally set at 30 percent of the station release rate limit for noble gases in Xe-133 equivalent concentration as follows:

Recall Equation 3.6:

CXe 133 SP = + bkg CF where:

500 CXe 133 <

4.72E + 02 x f x KXe 133 x / Q 150 RIA 45unit vent =

4.72E + 02 x 6.5E + 04 x 2.94E + 02 x 1.672E 06 x 7.09E 08 RIA 45unit vent 1.40E + 05 cpm + bkg Section 3 - Page 7

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 where:

150 = 30% of the 500 mrem/yr total body release rate limit.

6.5E+04 = Unit Vent flow rate with Reactor Building Purge off, ft3/min.

1.672E-06 = Highest Semi-Elevated release point dispersion factor, sec/m3.

7.09E-08 = RIA-45 Correlation Factor, Ci/ml/cpm.

All other factors were previously defined.

150 RIA 46unit vent =

4.72E + 02 x 6.5E + 04 x 2.94E + 02 x 1.672E 06 x 3.17 E 04 RIA 46unit vent 31 cpm + bkg where:

3.17E-04 = RIA-46 Correlation Factor, Ci/ml/cpm.

All other factors were previously defined.

For instances in which the Reactor Building Purge is on, the setpoint is multiplied by 0.65 (65,000 cfm/ (65,000 cfm + 35,000 cfm purge flow)).

3.0.2.2 RADWASTE FACILITY SETPOINTS (4RIA-45) 25 4 RIA 45 =

4.72E + 02 x 1.297E + 05 x 2.94E + 02 x 7.308E 06 4 RIA 45 1.90E - 04 Ci/ml where:

25 = 5% of the 500 mrem/yr total body release rate limit.

1.297E+05 = Radwaste Facility Vent flow rate, ft3/min.

7.308E-06 = Highest Ground-Level release point dispersion factor, sec/m3.

All other factors were previously defined.

4RIA-45 reads in units of concentration, Ci/ml.

Section 3 - Page 8

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 3.0.2.3 INTERIM RADWASTE BUILDING SETPOINTS (RIA-53) 25 RIA 53 =

4.72E + 02 x 1.5E + 04 x 2.94E + 02 x 7.308E 06 x 3.4E 08 RIA 53 4.8E + 04 cpm + bkg where:

25 = 5% of the 500 mrem/yr total body release rate limit.

1.5E+04 = Interim Radwaste Building Vent flow rate, ft3/min.

7.308E-06 = Highest Ground-Level release point dispersion factor, sec/m3.

3.4E-08 = RIA-53 Correlation Factor, Ci/ml/cpm.

All other factors were previously defined.

In addition to the maximum setpoints discussed previously, Oconee uses "Alert" setpoints that are based on 10% of the reporting requirement from 10CFR50.73(a)(2)(viii)(A).

Each unit vent Alert setpoint is based on 60% of a Xe-133 Effluent Concentration (EC) value of 5.0E-07 Ci/ml at the site boundary. The Interim Radwaste Building and Radwaste Facility are each set at 10% of the Xe-133 EC. The method used to calculate the Alert setpoints is similar to that used to calculate the maximum setpoints except that the limit is based on concentration rather than dose rate. The Alert setpoints are approximately 42% of the maximum setpoints.

3.0.2.4 WASTE GAS DECAY TANK SETPOINTS (RIA-37 and RIA-38)

For batch releases where the effluent can contain activity significantly above background, e.g., Waste Gas Decay Tank (WGDT), two additional monitors, RIA-37 and RIA-38 are used to establish setpoints for each WGDT batch released. RIA-37 is the normal/low range noble gas monitor, and RIA-38 is the high range noble gas monitor. The following setpoint methodology is used:

CXe 133 = (C i

i x Eqi )

CXe 133 Expected Cpm = + bkg CFXe 133 CXe 133 RIA - 37 and RIA - 38 Setpoint = x 1 .5 Equation 3.7 CFXe 133 Section 3 - Page 9

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 where:

CXe-133 = Xe-133 equivalent concentration of the WGDT to be released, in Ci/ml.

Eqi = Xe-133 equivalence factor for each noble gas isotope, excluding tritium, to that of Xe-133 due to different beta energies and abundance.

(See Table 3.0-2).

CFXe-133 = The expected RIA response to a given Xe-133 equivalent concentration, in Ci/ml/cpm. 1RIA-37 = 1.01E-08 Ci/ml/cpm, 3RIA-37 = 4.20E-08 Ci/ml/cpm, 1RIA-38 and 3RIA-38 = 1.34E-03 Ci/ml/cpm.

1.5 = An adjustment factor to account for expected minor variations in effluent concentration and RIA background.

bkg = The radiation monitor background reading, in cpm.

When the release pathway is from any Unit 1 WGDT (A-D), and the Xe-133 equivalent concentration is less than 2.8E-01 Ci/ml, the 1&2 RIA-38 setpoint is established at 313 cpm, and the 1&2 RIA-37 setpoint is calculated using Equation 3.7.

When the release pathway is from any Unit 1 WGDT (A-D), and the Xe-133 equivalent concentration is greater than 2.8E-01 Ci/ml, the 1&2 RIA-37 setpoint is established as offscale high, and the 1&2 RIA-38 setpoint is calculated using Equation 3.7.

When the release pathway is from any Unit 3 WGDT (A-C), and the Xe-133 equivalent concentration is less than 2.8E-01 Ci/ml, the 3 RIA-38 setpoint is established at 313 cpm, and the 3 RIA-37 setpoint is calculated using Equation 3.7.

When the release pathway is from any Unit 3 WGDT (A-C), and the Xe-133 equivalent concentration is greater than 2.8E-01 Ci/ml, the 3 RIA-37 setpoint is established as offscale high, and the 3 RIA-38 setpoint is calculated using Equation 3.7.

When there are no noble gases present in the WGDT sample, the RIA-37 setpoint is set to five times (5X) the RIA-37 background reading.

Section 3 - Page 10

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 Table 3.0-2 Xe-133 Equivalents Isotope Equivalence Factor Kr-83m 0 Kr-85m 2.48 Kr-85 2.56 Kr-87 2.93 Kr-88 2.78 Kr-89 2.93 Kr-90 2.93 Xe-131m 1.69 Xe-133m 1.99 Xe-133 1.0 Xe-135m 0.83 Xe-135 2.63 Xe-137 2.93 Xe-138 2.93 Ar-41 2.82 C-11 2.70 Section 3 - Page 11

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 4.0 EFFLUENT DOSE MODELS The effluent dose models used to show compliance with 10CFR50, Appendix I ALARA design objectives, 40CFR190 fuel cycle dose limits, and the dose values given in station SLCs are based on the methodology given in NUREG-0133 and Regulatory Guide 1.109.

Dose contributions to the maximum individual shall be calculated at least every 31 days, quarterly, and annually using the RETDAS computer code which implements the ODCM methodology. RETDAS, Radioactive Effluent Tracking and Dose Assessment Software, is a database application designed by Canberra Industries, Inc. to automate many of the tasks required in the administration of effluent releases at Oconee. RETDAS performs normal operation effluent dose assessment using NUREG-0133 and Regulatory Guide 1.109 methodology.

Station long-term historical and dose projection calculations are performed periodically to determine the station's status with respect to meeting annual ALARA goals specified in the Oconee SLCs. Such calculations are used to verify that adequate margin remains during a report period to allow normal station and radwaste system operation, including anticipated operational occurrences, for the remainder of the report period without exceeding applicable goals. Station 31-day dose projections that are used to assess the need to reduce effluent releases with the Gaseous Waste (GW) or Liquid Waste (LW) systems as required in the Oconee SLCs are estimated by the previous month's calculated dose results.

Fuel cycle dose calculations shall be performed annually or as required by special reports.

Dose contributions shall be calculated using the RETDAS computer program.

4.0.1 LIQUID EFFLUENT DOSE MODEL FOR THE MAXIMUM EXPOSED INDIVIDUAL Of the possible exposure pathways in the aquatic environment, only three contribute significantly to the total dose; these pathways are ingestion of potable water and aquatic foods, and direct exposure from radioactivity deposited on the shoreline. The dose contribution from these pathways for measured quantities of radioactive materials identified in liquid effluents released to unrestricted areas shall be calculated for the maximum exposed individual in each age group using the methodology provided in this section.

Liquid waste processed by the LW system can be released to the environment at Oconee from two liquid discharge points; (1) directly to the Keowee Tailrace through RIA-33 and (2) to the Chemical Treatment Pond #3 discharge point into the Keowee River (See Figure 2.0-1). Liquid dose calculations for the maximum exposed individual are performed and documented in the Annual Effluent Release Report for both locations using the applicable activity release and dilution data for each liquid effluent release point. The primary liquid effluent discharge point for Oconee is to the Keowee Tailrace Section 4 - Page 1

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 through RIA-33. In general, only low activity tritium releases (<1% station total) occur through the Chemical Treatment Pond #3 discharge point into the Keowee River. Dose calculations are performed for each of the two liquid discharge points for dose reporting purposes. The highest calculated dose from the two dose calculations is used to define the maximum individual dose from liquid releases at Oconee.

Section 4 - Page 2

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 Liquid Dose Calculations The following equation is used for calculating liquid dose to the maximum exposed individual at each of the two liquid effluent release points:

1 Dose oa p i Aoapi u Ci u 't u Fn u Dw f

Fn uV f F Formula: adapted from NUREG-0133, pages 15-17. Where:

Doseoa The cumulative dose commitment for organ o and age group a, from the liquid effluent for the total time period, 't. (mrem)

Aoapi Dose commitment factor for organ o, age group a, pathway p, and nuclide i (mrem/hr per PCi/ml). (See Appendices C through F for age group and pathway specific dose commitment factors).

Ci The average concentration of nuclide i, in undiluted liquid effluent during the time period, 't. (PCi/ml)

't The length of time over which Ci and Fn are averaged for all liquid releases. (hr)

Fn The near field average dilution factor for Ci during the period of interest,

't. Includes the recirculation factor. (dimensionless) f Average liquid radwaste flow during the period of interest, 't. (gpm)

F Average dilution flow during the period of interest, 't. (gpm)

Normally 3.41E+04 gpm (76 cfs, based on a leakage rate of 38 cfs (19 cfs per Keowee Hydro unit, plus the Keowee Hydro Fire Protection liquid waste release mixing line whose flow rate is 38 cfs)). No dilution credit is taken for the relatively short period of time during the year that the Keowee Hydro units are running.

V Recirculation factor. (dimensionless)

  • Dw Dilution factor from the near field area to the potable water intake;

= 30.0 for Oconee. This factor applies to the potable water pathway only. The nearest potable water intake to Oconee is located at the Andersen water intake approximately 31.5 miles from the site on a separate arm of Lake Hartwell. From a hydrology standpoint the Andersen water intake should not be significantly affected by liquid effluent discharges from Oconee. 30.0 is a conservatively small dilution factor based on environmental sample data.

  • The recirculation factor accounts for the fraction of discharged water reused by the station. Liquid effluent discharge cannot be recirculated back into the Oconee station.

Therefore, the recirculation factor is 1.0 at Oconee.

Section 4 - Page 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 Derivation of Liquid Dose Commitment Factors (Aoapi)

Potable Water

- i t p Aoapi = 1.14 x105 x U aw x Daoi x e Formula: from NUREG-0133, page 16 and Regulatory Guide 1.109, page 1.109-12.

Where:

Aoapi Dose commitment factor for organ o, age group a, pathway p, and nuclide i, (mrem/hr per Ci/ml). (See Appendices C through F for age group and pathway specific dose commitment factors).

5 1.14x10 Units conversion factor (pCi-yr-ml)/(Ci-hr-kg).

Uaw Water consumption rate in liters per year for age group a. From Table E-5, Regulatory Guide 1.109.

Adult - 730 Teen - 510 Child - 510 Infant - 330 Daoi Dose factor for age group a, organ o, nuclide i, in mrem/pCi. From tables E-11 through E-14 of Regulatory Guide 1.109.

i Decay constant for nuclide i, in sec-1.

tp Environmental transit time from release to receptor. Default =

4.32E+04 sec (12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />). From Regulatory Guide 1.109, Table E-15.

Section 4 - Page 4

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 Aquatic Foods

-it p Aoapi = 1.14 x105 xU af x BFi x Daoi x e Formula: from NUREG-0133, page 16 and Regulatory Guide 1.109, page 1.109-12.

Where:

Aoapi Dose commitment factor for organ o, age group a, pathway p, and nuclide i, (mrem/hr per Ci/ml). (See Appendices C through F for age group and pathway specific dose commitment factors).

5 1.14x10 Units conversion factor (pCi-yr-ml)/(Ci-hr-kg).

Uaf Fish consumption rate for age group a (kg/yr). From Table E-5, Regulatory Guide 1.109.

Adult - 21 Teen - 16 Child - 6.9 Infant - 0 BFi Bioaccumulation factor for nuclide i, in fish, in units of pCi/kg per pCi/liter. From Table A-1 of Regulatory Guide 1.109.

Daoi Dose factor for age group a, organ o, nuclide i, in mrem/pCi. From tables E-11 through E-14 of Regulatory Guide 1.109.

i Decay constant for nuclide i, in sec-1.

tp Environmental transit time from release to receptor. Default =

8.64E+04 sec (1 day). From Regulatory Guide 1.109, Table E-15.

Section 4 - Page 5

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 Shoreline Sediment 1

it p Aoapi = 1.14 x 10 x 100 x DFGoi x w x U as x Ti x e 5

2 x (1 e itb )

Formula: adapted from Regulatory Guide 1.109, page 1.109-14.

Where:

Aoapi Dose commitment factor for organ o, age group a, pathway p, and nuclide i, (mrem/hr per Ci/ml). (See Appendices C through F for age group and pathway specific dose commitment factors).

1.14x105 Units conversion factor (pCi-yr-ml)/(Ci-hr-kg).

100 Proportionality constant used in the sediment radioactivity model, (liters/(m2-day).

DFGoi Ground plane dose conversion factor for organ o, nuclide i (mrem/hr per pCi/m2), from Table E-6 of Regulatory Guide 1.109.

w Shoreline width factor. For Oconee = 0.2, from Table A-2, Regulatory Guide 1.109.

Uas Shoreline exposure rate for age group a (hr/yr), From Table E-5, Regulatory Guide 1.109.

Adult - 12 Teen - 67 Child - 14 Infant - 0 Ti1/2 Nuclide half life for nuclide i, in days.

i Nuclide decay constant for nuclide i.

tp Average transit time to point of exposure (0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />).

tb Sediment exposure time (15 years). Page 1.109-14.

Section 4 - Page 6

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 4.0.2 GASEOUS EFFLUENT DOSE MODEL FOR THE MAXIMUM EXPOSED INDIVIDUAL The dose contributions from measured quantities of radioactive materials identified in gaseous effluent released to unrestricted areas shall be calculated for the maximum gamma and beta air dose from noble gases, and for the maximum exposed individual from radioiodines, particulates, and others using the following equations:

Gaseous Dose Calculations Noble Gas Dose Calculations Gamma Air Dose Dose = 3.17 x10 8 x / Q x (M i x Qi )

i Formula: adapted from NUREG-0133, page 28.

Where:

Dose Gamma air dose for the time period of interest (mrad).

3.17x10-8 Inverse number of seconds in year (year/seconds).

Mi Gamma air dose factor due to gamma emissions for nuclide i (mrad/yr per Ci/m3). (See Appendix A).

/Q The highest calculated annual average relative concentration for any area at or beyond the site boundary (sec/m3)*. (See Table 6.0-9).

Qi Activity for nuclide i released during the time period of interest (Ci).

Beta Air Dose Dose = 3.17 x 10 8 x / Q x ( N i x Qi )

i Formula: adapted from NUREG-0133, page 28.

Where:

Dose Beta air dose for the time period of interest (mrad).

3.17x10-8 Inverse number of seconds in year (year/seconds).

Ni Beta air dose factor due to beta emissions for nuclide i (mrad/yr per Ci/m3). (See Appendix A).

/Q The highest calculated annual average relative concentration for any area at or beyond the site boundary (sec/m3)*. (See Table 6.0-9).

Qi Activity for nuclide i released during the time period of interest (Ci).

Section 4 - Page 7

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 Iodine, Particulates, and H-3 Dose Organ Dose Calculation Dose oa = 3 .17 x 10 8 x W x p

(R i

oapi x Qi )

Formula: adapted from NUREG-0133, pages 29 & 30.

Where:

Doseoa The cumulative dose commitment to the total body or any organ o, for an individual of age group a (mrem).

3.17x10-8 Inverse number of seconds in year (year/seconds).

Roapi Dose commitment factor for organ o, age group a, pathway p, and nuclide i. The units are based on whether a dispersion or deposition factor is used. When a /Q is used the units are mrem/yr per Ci/m3.

When a D/Q is used the units are (m2

  • mrem/yr) per Ci/sec. (See Appendices G through J for age group and pathway specific dose commitment factors).

W Dispersion (/Q) or deposition factor (D/Q)*. The factor used is based upon the pathway. Note: /Q is always used for tritium.

Pathway Factor Used Ground Plane Deposition D/Q (m-2)

Inhalation /Q (sec/m3)

Vegetation D/Q (m-2)

Grass/Cow/Milk D/Q (m-2)

Grass/Goat/Milk D/Q (m-2)

Grass/Cow/Meat D/Q (m-2)

Qi Activity for nuclide i, released during the time period of interest (Ci).

  • The dose from noble gases released from semi-elevated release points, e.g., unit vent, is calculated using the semi-elevated dispersion factors. The dose from noble gases released from ground level release points, e.g., Radwaste Facility vent, is calculated using the ground level dispersion factors. The total dose is the sum of the semi-elevated and ground level dose calculations. Maximum individual organ dose is determined by calculating the organ dose at each of the /Q and D/Q locations shown in Table 6.0-9 and Table 6.0-10 (128 locations) for both semi-elevated release points and ground level release points, summing the two at each location, and then choosing the dose from the maximum location. Dose is calculated only for those pathways (e.g., garden, milk animal, etc.) that actually exist at each location as determined by the land use census shown in Table 6.0-3. As discussed in Oconee UFSAR Section 2.1.1.3, the boundary for establishing gaseous effluent release limits is the exclusion area boundary (EAB). The EAB is defined as a 1 mile radius from the station center.

Section 4 - Page 8

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 Derivations of Iodine, Particulate, and H-3 Dose Commitment Factors (Roapi)

Ground Plane Deposition Pathway (1 e i t )

R oapi = K K ( SF ) DFG oi i

Formula: from NUREG-0133, page 32.

Where:

Roapi Dose commitment factor for organ o, age group a, nuclide i, for ground plane deposition pathway (m2*mrem/yr per Ci/sec). (See Appendices G through J for age group and pathway specific dose commitment factors).

K' Units conversion factor pCi/Ci (106).

K" Units conversion factor 8760 hr/year.

SF Shielding factor (dimensionless) (0.7, from Regulatory Guide 1.109).

DFGoi Ground plane dose conversion factor for organ o, nuclide i (mrem/hr per pCi/m2), from Table E-6 of Regulatory Guide 1.109.

-1 i Nuclide decay constant for nuclide i (sec ).

t Exposure time, 4.73x108 seconds (15 years).

Inhalation Pathway Roapi = K ( BRa )( DFAoi ) a Formula: from NUREG-0133, page 31.

Where:

Roapi Dose commitment factor for organ o, age group a, nuclide i, for inhalation pathway (mrem/yr per Ci/m3). (See Appendices G through J for age group and pathway specific dose commitment factors).

K' Units conversion factor pCi/Ci (106).

BRa Breathing rate for age group (m3/yr), from Regulatory Guide 1.109:

Adult - 8000 Teen - 8000 Child - 3700 Infant - 1400 (DFAoi)a Organ inhalation factor dose conversion factor for organ o, nuclide i, age group a (mrem/pCi), from Tables E-7 through E-10 of Regulatory Guide 1.109.

Section 4 - Page 9

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 Vegetation R oapi = K (r )

[

x ( DFL o i ) a x U a f L e L i t L

+ U aS f g e i t h ]

Yv ( i + w )

Formula: from NUREG-0133, page 35. Where:

Roapi Dose commitment factor for organ o, age group a, nuclide i, for vegetation pathway (m2*mrem/yr per Ci/sec). (See Appendices G through J for age group and pathway specific dose commitment factors).

K' Units conversion factor pCi/Ci (106).

r Fraction of deposited activity retained on vegetation, from Regulatory Guide 1.109.

1.0 for radioiodine.

0.2 for particulates.

Yv Vegetation areal density (kg/m2) (2.0, from Regulatory Guide 1.109).

-1 i Nuclide decay constant for nuclide i (sec ).

w Decay constant for removal of activity on leaf and plant surfaces by weathering (5.73x10-7 sec-1, from NUREG-0133).

(DFLoi)a Ingestion dose conversion factor for nuclide i, organ o, and age group a, from Tables E-11 through E-14 of Reg. Guide 1.109 (mrem/pCi).

L U a Consumption rate of fresh vegetation for age group a (kg/yr) (from Regulatory Guide 1.109).

Adult - 64 Teen - 42 Child - 26 Infant - 0 fL Fraction of annual intake of fresh leafy vegetation grown locally (1.0, from NUREG-0133).

tL Average time between harvest of leafy vegetation and consumption (8.6x104 seconds, (1 day), from Regulatory Guide 1.109).

USa Consumption rate of stored vegetation for age group a (kg/yr) (from Regulatory Guide 1.109).

Adult - 520 Teen - 630 Child - 520 Infant - 0 fg Fraction of annual intake of stored vegetation (0.76, from Regulatory Guide 1.109).

th Average time between harvest of stored vegetation and consumption (5.18x106 seconds, (60 days), from Regulatory Guide 1.109).

Section 4 - Page 10

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 Vegetation - Tritium

[ ]

R oapi = K' K' " U aL f L + U aS f g ( DFL oi ) a [0 . 75 ( 0 . 5 / H ) ]

Formula: from NUREG-0133, page 36.

Where:

Roapi Dose commitment factor for organ o, age group a, for vegetation pathway and tritium (mrem/yr per Ci/m3). (See Appendices G through J for age group and pathway specific dose commitment factors).

K' Units conversion factor pCi/Ci (106).

K'" Units conversion factor gm/kg (103).

ULa Consumption rate of fresh vegetation for age group a (kg/yr) (from Regulatory Guide 1.109).

Adult - 64 Teen - 42 Child - 26 Infant - 0 fL Fraction of annual intake of fresh leafy vegetation grown locally (1.0, from NUREG-0133).

USa Consumption rate of stored vegetation for age group a (kg/yr) (from Regulatory Guide 1.109).

Adult - 520 Teen - 630 Child - 520 Infant - 0 fg Fraction of annual intake of stored vegetation (0.76, from Regulatory Guide 1.109).

(DFLoi)a Ingestion dose conversion factor for nuclide i, organ o, and age group a, from Tables E-11 through E-14 of Regulatory Guide 1.109 (mrem/pCi).

0.75 Fraction of total feed that is water. (From NUREG-0133).

0.5 Ratio of specific activity of feed grass water to atmospheric water.

(From NUREG-0133).

H Absolute humidity of the atmosphere (8 gm/m3, from Regulatory Guide 1.109).

Section 4 - Page 11

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 Grass/Cow/Milk Q F (U ) f p fs (1 f p f s ) e i t h i t f R oapi = K ap F mi ( r )( DFL )a + e i + w oi Y p Ys Formula: from NUREG-0133, pages 32 & 33. Where:

Roapi Dose commitment factor for organ o, age group a, nuclide i, for grass/cow/milk pathway (m2*mrem/yr per Ci/sec). (See Appendices G through J for age group and pathway specific dose commitment factors).

K' Units conversion factor pCi/Ci (106).

QF Cow consumption rate (50 kg/day, from Regulatory Guide 1.109)

Uap Consumption rate of cow milk for age group a (liters/yr, from Regulatory Guide 1.109).

Adult - 310 Teen - 400 Child - 330 Infant - 300 r Fraction of deposited activity retained on cows feed grass, (from Regulatory Guide 1.109).

1.0 for radioiodine.

0.2 for particulates.

Yp Agricultural productivity by unit area of pasture feed grass (0.7 kg/m2, from Regulatory Guide 1.109).

Ys Agricultural productivity by unit area of stored feed (2.0 kg/m2, from Regulatory Guide 1.109).

-1 i Nuclide decay constant for nuclide i (sec ).

w Decay constant for removal of activity on leaf and plant surfaces by weathering (5.73x10-7 sec-1, from NUREG-0133).

(DFLoi)a Ingestion dose conversion factor for nuclide i, organ o, and age group a, from Tables E-11 through E-14 of Regulatory Guide 1.109 (mrem/pCi).

Fmi Stable element transfer coefficient for nuclide i, in days/liter, from Table E-1 of Regulatory Guide 1.109 for cow milk.

fp Fraction of year that the cow is on pasture (1.0, from RG 1.109).

fs Fraction of the cow feed that is pasture grass while the cow is on pasture (1.0, from Regulatory Guide 1.109).

tf Transport time for pasture to cow, to milk, to receptor (1.73E+05 seconds, from Regulatory Guide 1.109).

th Transport time from pasture, to harvest, to cow, to milk, to receptor (7.78e+06 seconds, from Regulatory Guide 1.109).

Section 4 - Page 12

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 Grass/Cow/Milk - Tritium Roapi = K K Fmi Q f U ap ( DFLio ) a [0.75(0.5 / H )]

Formula: from NUREG-0133, page 34.

Where:

Roapi Dose commitment factor for organ o, age group a, nuclide i, for grass/cow/milk pathway (mrem/yr per Ci/m3). (See Appendices G through J for age group and pathway specific dose commitment factors).

K' Units conversion factor pCi/Ci (106).

K'" Units conversion factor gm/kg (103).

QF Cow consumption rate (50 kg/day, from Regulatory Guide 1.109).

Uap Consumption rate of cow milk for age group a (liters/yr, from Regulatory Guide 1.109).

Adult - 310 Teen - 400 Child - 330 Infant - 300 (DFLoi)a Ingestion dose conversion factor for nuclide i, organ o, and age group a, from Tables E-11 through E-14 of Regulatory Guide 1.109 (mrem/pCi).

Fmi Stable element transfer coefficient for nuclide i, in days/liter, from Table E-1 of Regulatory Guide 1.109 for cow milk.

0.75 Fraction of total feed that is water (from NUREG-0133).

0.5 Ratio of specific activity of feed grass water to atmospheric water (from NUREG-0133).

H Absolute humidity of the atmosphere (8 gm/m3, from Regulatory Guide 1.109).

Section 4 - Page 13

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 Grass/Goat/Milk Q F (U ap ) f p f s (1 f p f s ) e i t h it f Roapi = K Fmi ( r )( DFL oi ) a + e i + w Y p Ys Formula: from NUREG-0133, pages 32 & 33. Where:

Roapi Dose commitment factor for organ o, age group a, nuclide i, for grass/goat/milk pathway (m2*mrem/yr per Ci/sec). (See Appendices G through J for age group and pathway specific dose commitment factors).

K' Units conversion factor pCi/Ci (106).

QF Goat consumption rate (6 kg/day, from Regulatory Guide 1.109).

Uap Consumption rate of goat milk for age group a (liters/yr, from Regulatory Guide 1.109).

Adult - 310 Teen - 400 Child - 330 Infant - 300 r Fraction of deposited activity retained on goats feed grass, from Regulatory Guide 1.109.

1.0 for radioiodine.

0.2 for particulates.

Yp Agricultural productivity by unit area of pasture feed grass (0.7 kg/m2, from Regulatory Guide 1.109).

Ys Agricultural productivity by unit area of stored feed (2.0 kg/m2, from Regulatory Guide 1.109).

-1 i Nuclide decay constant for nuclide i (sec ).

w Decay constant for removal of activity on leaf and plant surfaces by weathering (5.73x10-7 sec-1, from NUREG-0133).

(DFLoi)a Ingestion dose conversion factor for nuclide i, organ o, and age group a, from Tables E-11 through E-14 of Regulatory Guide 1.109 (mrem/pCi).

Fmi Stable element transfer coefficient for nuclide i, in days/liter, from Table E-2 of Regulatory Guide 1.109 for goat milk.

fp Fraction of year that the goat is on pasture (1.0, from RG 1.109).

fs Fraction of the goat feed that is pasture grass while the goat is on pasture (1.0, from Regulatory Guide 1.109).

tf Transport time for pasture to goat, to milk, to receptor (1.73E+05 seconds, from Regulatory Guide 1.109).

th Transport time from pasture, to harvest, to goat, to milk, to receptor (7.78e+06 seconds, from Regulatory Guide 1.109).

Section 4 - Page 14

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 Grass/Goat/Milk - Tritium Roapi = K K Fmi Q f U ap ( DFL oi ) a [0 .75 ( 0.5 / H ) ]

Formula: from NUREG-0133, page 34.

Where:

Roapi Dose commitment factor for organ o, age group a, nuclide i, for grass/goat/milk pathway (mrem/yr per Ci/m3). (See Appendices G through J for age group and pathway specific dose commitment factors).

K' Units conversion factor pCi/Ci (106).

K'" Units conversion factor gm/kg (103).

QF Goat consumption rate (6 kg/day, from Regulatory Guide 1.109).

Uap Consumption rate of goat milk for age group a (liters/yr, from Regulatory Guide 1.109).

Adult - 310 Teen - 400 Child - 330 Infant - 300 (DFLoi)a Ingestion dose conversion factor for nuclide i, organ o, and age group a, from Tables E-11 through E-14 of Regulatory Guide 1.109 (mrem/pCi).

Fmi Stable element transfer coefficient for nuclide i, in days/liter, from Table E-2 of Regulatory Guide 1.109 for goat milk.

0.75 Fraction of total feed that is water (from NUREG-0133).

0.5 Ratio of specific activity of feed grass water to atmospheric water (from NUREG-0133).

H Absolute humidity of the atmosphere (8 gm/m3, from Regulatory Guide 1.109).

Section 4 - Page 15

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 Grass/Cow/Meat Q F (U ap ) f p f s (1 f p f s ) e i t h it f R oapi = K F fi ( r )( DFL i ) a + e i + w Y p Ys Formula: from NUREG-0133, pages 34 & 35. Where:

Roapi Dose commitment factor for organ o, age group a, nuclide i, for grass/cow/meat pathway (m2*mrem/yr per Ci/sec). (See Appendices G through J for age group and pathway specific dose commitment factors).

K' Units conversion factor pCi/Ci (106).

QF Cow consumption rate (50 kg/day, from Regulatory Guide 1.109).

Uap Consumption rate of cow meat for age group a (kg/yr, from Regulatory Guide 1.109).

Adult - 110 Teen - 65 Child - 41 Infant - 0 r Fraction of deposited activity retained on cows feed grass (from Regulatory Guide 1.109).

1.0 for radioiodine.

0.2 for particulates.

Yp Agricultural productivity by unit area of pasture feed grass (0.7 kg/m2, from Regulatory Guide 1.109).

Ys Agricultural productivity by unit area of stored feed (2.0 kg/m2, from Regulatory Guide 1.109).

-1 i Nuclide decay constant for nuclide i (sec ).

w Decay constant for removal of activity on leaf and plant surfaces by weathering (5.73x10-7 sec-1, from NUREG-0133).

(DFLoi)a Ingestion dose conversion factor for nuclide i, organ o, and age group a, from Tables E-11 through E-14 of Regulatory Guide 1.109 (mrem/pCi).

Ffi Stable element transfer coefficient for nuclide i, in days/kg, from Table E-1 of Regulatory Guide 1.109 for cow meat.

fp Fraction of year that the cow is on pasture (1.0, from RG 1.109).

fs Fraction of the cow feed that is pasture grass while the cow is on pasture (1.0, from Regulatory Guide 1.109).

tf Transport time from pasture to receptor (1.73E+06 seconds, from Regulatory Guide 1.109).

th Transport time from crop field to receptor (7.78E+06 seconds, from Regulatory Guide 1.109).

Section 4 - Page 16

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 Grass/Cow/Meat - Tritium Roapi = K K F fi Q F U ap ( DFL oi ) a [0 .75 ( 0 .5 / H ) ]

Formula: from NUREG-0133, page 35.

Where:

Roapi Dose commitment factor for organ o, age group a, nuclide i, for grass/cow/meat pathway (mrem/yr per Ci/m3). (See Appendices G through J for age group and pathway specific dose commitment factors).

K' Units conversion factor pCi/Ci (106).

K'" Units conversion factor gm/kg (103).

QF Cow consumption rate (50 kg/day, from Regulatory Guide 1.109).

Uap Consumption rate of cow meat for age group a (kg/yr, from Regulatory Guide 1.109).

Adult - 110 Teen - 65 Child - 41 Infant - 0 (DFLoi)a Ingestion dose conversion factor for nuclide i, organ o, and age group a, from Tables E-11 through E-14 of Regulatory Guide 1.109 (mrem/pCi).

Ffi Stable element transfer coefficient for nuclide i, in days/liter, from Table E-1 of Regulatory Guide 1.109 for cow meat.

0.75 Fraction of total feed that is water (from NUREG-0133).

0.5 Ratio of specific activity of feed grass water to atmospheric water (from NUREG-0133).

H Absolute humidity of the atmosphere (8 gm/m3, from Regulatory Guide 1.109).

Section 4 - Page 17

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 4.0.3 DIRECT RADIATION Direct radiation is that radiation from confined sources, and does not include any external component from radioactive effluents. The point kernel method has been used to calculate offsite dose rates from radioactive materials stored in the refueling water storage tanks, reactor makeup water storage tanks, and temporary onsite radwaste storage tanks. Dose calculations using this method performed for Oconee Nuclear Station indicate direct radiation doses are much less than 0.01 mrem/yr and, therefore, make a negligible contribution to individual dose. Likewise, direct and air-scatter radiation dose contributions from the onsite Independent Spent Fuel Storage Installation (ISFSI) at Oconee have been calculated and documented in the "Oconee Nuclear Site 10CFR72.212 Written Evaluations" report. The maximum dose rate to the nearest potential resident from the Oconee ISFSI is calculated to be 0.0268 mrem/yr. Direct radiation doses will not be calculated routinely.

4.0.4 EFFLUENT APPORTIONMENT For the Oconee Nuclear Station the effluent releases are apportioned equally to each unit for each site as recommended by Section 3.1 of NUREG-0133, because the shared radwaste treatment systems at each site make it impractical to accurately ascribe releases to a specific reactor unit. For Annual Effluent Release Report purposes effluent releases are summed for each unit, and the maximum individual dose to the public is reported as a site total.

Section 4 - Page 18

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 5.0 FUEL CYCLE CALCULATIONS In accordance with the requirements of 40CFR190, the annual dose commitment to any member of the general public shall be calculated to assure that doses are limited to 25 millirems to the total body or any organ with the exception of the thyroid which is limited to 75 millirems. In accordance with the requirements of the Selected Licensee Commitments, the annual dose commitment shall also be calculated any time that one of the quarterly dose limits of the Selected Licensee Commitments is exceeded; these annual dose commitments may not just be calculated for the calendar year.

The "Uranium fuel cycle" is defined in 40CFR Part 190.02(b) as:

"Uranium fuel cycle means the operations of milling or uranium ore, chemical conversion of uranium, isotopic enrichment of uranium, fabrication of uranium fuel, generation of electricity by a light-water-cooled nuclear power plant using uranium fuel, and reprocessing of spent uranium fuel, to the extent that these directly support the production of electrical power for public use utilizing nuclear energy, but excludes mining operations, operations at waste disposal sites, transportation of any radioactive material in support of these operations, and the reuse of recovered non-uranium special nuclear and by-product materials from the cycle."

Based on this definition of the fuel cycle and the information in 10CFR51, Table S-3, and Wash-1248, the radiological impact of the following operations has been assessed for Oconee Nuclear Station:

5.0.1 MILLING No milling operations occur within fifty miles of the Oconee Nuclear Station.

5.0.2 CONVERSION No uranium hexafluoride production occurs within fifty miles of the Oconee Nuclear Station.

5.0.3 ENRICHMENT No uranium enrichment operations occur within fifty miles of the Oconee Nuclear Station.

5.0.4 FUEL FABRICATION No fuel fabrication operations occur within fifty miles of the Oconee Nuclear Station.

Section 5 - Page 1

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 5.0.5 NUCLEAR POWER PRODUCTION The production of electricity for public use using light-water-cooled nuclear power stations results in increments of dose to individuals within fifty miles of any station due to liquid and gaseous effluent releases and direct radiation or skyshine. The increments of dose resulting from liquid and gaseous effluent releases will be calculated using the ODCM methodology implemented in the RETDAS computer program. The dose from direct radiation, skyshine, and radiation from the station storage facilities has been estimated using conservative assumptions (see Section 4.0.3).

In certain situations more than one nuclear power station site may contribute to the doses to be considered in making fuel cycle dose assessments in accordance with 40CFR190.

However, since the Oconee nuclear station is located over 100 miles from the Catawba and McGuire nuclear stations, the relative dose contribution from each site to the other is insignificant, and can be ignored in assessing compliance with 40CFR190.

5.0.6 FUEL REPROCESSING No fuel reprocessing operations occur within fifty miles of the Oconee Nuclear Station.

5.0.7 40CFR190 TOTAL DOSE DETERMINATION To summarize, only dose increments from nuclear power production operations (Section 5.0.5) need be considered in calculations to demonstrate compliance with the requirements of 40CFR190. The fuel cycle dose assessments for Oconee Nuclear Station only include liquid and gaseous dose contributions from Oconee and dose from Oconee's ISFSI since no other uranium fuel cycle facility contributes significantly to Oconee's maximum exposed individual. For this dose assessment, the total body and maximum organ dose contributions to the maximum exposed individual from Oconee's liquid and gaseous effluents are estimated using the following calculations:

Dwb (T ) = Dwb (l ) + Dwb ( g )

Dmo (T ) = Dmo(l ) + Dmo ( g )

where:

Dwb(T) = Total estimated fuel cycle whole body dose commitment resulting from the combined liquid and gaseous effluents of Oconee during the calendar year of interest, in mrem.

Dmo(T) = Total estimated fuel cycle maximum organ dose commitment resulting from the combined liquid and gaseous effluents of Oconee during the calendar year of interest, in mrem.

Section 5 - Page 2

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 6.0 ENVIRONMENTAL LOCATIONS 6.0.1 SITE DESCRIPTION AND SAMPLE LOCATIONS Oconee Nuclear Station (ONS) is located in Oconee County, South Carolina, approximately 8 miles northeast of Seneca, South Carolina, on the shore of Lake Keowee. This lake was formed by damming the Keowee and Little Rivers in that location. Immediately to the south is the U.S. Government Hartwell Project. The Keowee Hydroelectric Plant near the station joins Lake Keowee and the upper reaches of Lake Hartwell.

To the north, the Jocassee Hydroelectric Plant joins Lake Jocassee and Lake Keowee. Jocassee is a pumped storage plant. The ONS exclusion area boundary is 1 mile.

Table 6.0-1 and Table 6.0-2 define the sampling and TLD locations for the Oconee Radiological Monitoring Program. Figure 6.0-1 and Figure 6.0-2 illustrate these locations as compared to Oconee Nuclear Station.

Air Sampling at Oconee Nuclear Station 6.0.2 LAND USE CENSUS DATA The Annual Land Use Census, required by Selected Licensee Commitments, is performed to ensure that changes in the use of areas at or beyond the site boundary are identified, and that modifications to the Radiological Environmental Monitoring Program are made if required by changes in land use. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10CFR50. Results are shown in Table 6.0-3 and Figure 6.0-3.

Section 6 - Page 1

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 TABLE 6.0-1 OCONEE RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS Table 6.0-1 Codes W Weekly SM Semimonthly BW BiWeekly Q Quarterly M Monthly SA Semiannually C Control Site Air Rad. & Surface Drinking Shoreline Fish Milk Broadleaf Location Description* Particulate Water Water Sediment Vegetation 060 Greenville Water Intake Road (2.58 mi NNE) W M 060 Greenville Water Intake Road (3.23 NE) M 060 C ** Greenville Water Intake Road (2.28 NE) SA 062 C Lake Keowee Hydro Intake (0.85 mi ENE) M Lake Hartwell Hwy 183 Bridge 063 (0.80 mi ESE) [000.7] SA SA 063.1 Lake Hartwell Hwy 183 (0.79 mi E) M 064 C Seneca (6.67 mi SSW) [004.1] M 066 Anderson (18.9 mi SSE) [012] M Lawrence Ramsey Bridge Hwy 27 067 (4.34 mi SSE) [005.2] SA SA 068 C High Falls County Park (1.82 mi W) SA 071 C Clemson Dairy (10.2 mi SSE) [006.3] SM 074 Keowee Key Resort (2.36 mi NNW) W 077 Skimmer Wall (1.00 mi SW) W M 078 Recreation Site (0.58 mi WSW) W 079 Keowee Dam (0.56 mi NE) W M 081 C Clemson Operations Center (9.33 mi SE) W M

  • GPS data reflect approximate accuracy to within 2-5 meters. GPS field measurements were taken as close as possible to the item of interest.
    • Control for Fish Only

[ ] Location Numbers prior to 1984 Section 6 - Page 2

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 TABLE 6.0-2 OCONEE RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS (TLD SITES)

Site Location* Distance Sector Site Location* Distance Sector MICROWAVE TOWER, 020 SITE BOUNDARY 0.16 miles N 040 SIX MILE 4.74 miles E 021 SITE BOUNDARY 0.25 miles NNE 041 JCT HWY 101 & 133 4.25 miles ESE LAWRENCE CHAPEL 022 SITE BOUNDARY 0.53 miles NE 042 CHURCH, HWY 133 4.93 miles SE HWY 291 AT 023 SITE BOUNDARY 0.93 miles ENE 043 ISSAQUEENA PARK 4.09 miles SSE HWY 130 AT LITTLE 024 SITE BOUNDARY 0.81 miles E 044 RIVER DAM 3.96 miles S TERMINUS OF HWY 588 025 SITE BOUNDARY 0.42 miles ESE 045 AT CROOKED CREEK 4.78 miles SSW HWY 188 AT 026 SITE BOUNDARY 0.34 miles SE 046 CROOKED CREEK 4.61 miles SW NEW HOPE CHURCH, 027 SITE BOUNDARY 0.49 miles SSE 047 HWY 188 3.58 miles WSW 028 SITE BOUNDARY 0.46 miles S 048 JCT HWY 175 & 188 3.64 miles W 029 SITE BOUNDARY 0.56 miles SSW 049 JCT HWY 201 & 92 3.60 miles WNW STAMP CREEK LANDING, 030 SITE BOUNDARY 0.42 miles SW 050 END OF HWY 92 3.53 miles NW HWY 128, 1 MILE N OF 031 SITE BOUNDARY 0.27 miles WSW 051 HWY 130 4.64 miles NNW DPC BRANCH OFFICE 076 SITE BOUNDARY 0.19 miles W 052 SITE - PICKENS 12.4 miles ENE DPC BRANCH OFFICE 032 SITE BOUNDARY 0.19 miles WNW 053 SITE - LIBERTY 11.7 miles E POST OFFICE - HWY 93 033 SITE BOUNDARY 0.21 miles WNW 054 NORRIS 8.60 miles ESE CLEMSON 034 SITE BOUNDARY 0.22 miles NW 055 METEOROLOGY PLOT 9.27 miles SSE 035 SITE BOUNDARY 0.17 miles NNW 056 WATER TOWER - SENECA 7.30 miles SSW OCONEE MEMORIAL 036 MILE CREEK LANDING 4.32 miles N 057 HOSPITAL 8.42 miles SW KEOWEE CHURCH, BRANCH RD 037 HWY 327 4.85 miles NNE 058 C SUBSTATION, WALHALLA 9.39 miles WSW CONVENIENCE MART, 038 JCT HWY 183 & 133 4.24 miles NE 059 TAMASSEE DAR SCHOOL 9.20 miles NW HWY 133, 1 MILE EAST CLEMSON 039 OF JCT HWY 183 & 133 4.02 miles ENE 081 C OPERATIONS CENTER 9.33 miles SE C = Control

  • GPS data reflect approximate accuracy to within 2-5 meters. GPS field measurements were taken as close as possible to the item of interest.

Section 6 - Page 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 TABLE 6.0-3 Oconee 2006 Land Use Census Results*

Land Use Census performed 6/19 - 6/20/2006 Sector Distance Sector Distance (Miles)** (Miles)**

Nearest Residence 2.98 Nearest Residence 1.96 N Nearest Milk Animal - S Nearest Milk Animal -

Nearest Residence 1.85 Nearest Residence 1.36 NNE Nearest Milk Animal - SSW Nearest Milk Animal -

Nearest Residence 1.20 Nearest Residence 1.39 NE Nearest Milk Animal - SW Nearest Milk Animal -

Nearest Residence 1.34 Nearest Residence 1.81 ENE Nearest Milk Animal - WSW Nearest Milk Animal -

Nearest Residence 1.14 Nearest Residence 1.76 E Nearest Milk Animal - W Nearest Milk Animal -

Nearest Residence 1.57 Nearest Residence 1.35 ESE Nearest Milk Animal - WNW Nearest Milk Animal -

Nearest Residence 1.46 Nearest Residence 1.00 SE Nearest Milk Animal - NW Nearest Milk Animal -

Nearest Residence 1.54 Nearest Residence 1.06 SSE Nearest Milk Animal - NNW Nearest Milk Animal -

- indicates no occurrences within the 5 mile radius

  • The land use census identifies nearest pathways to the exclusion area boundary (EAB, ~ 1.0 mile) for each of the 16 sectors. Locations beyond the nearest pathway for each sector are assumed to contain that pathway for dose calculation purposes. At Oconee, broad leaf vegetation samples are taken in lieu of a garden census. For dose calculation purposes, since a garden location cannot be ruled out, a garden is assumed to exist at the site boundary and beyond for every sector. For the 4.5-5.0 mile sector all pathways, i.e., residence, garden, milk animal (goat), and meat animal (cow), are assumed to exist for dose calculation purposes.
    • GPS data reflect approximate accuracy to within 2-5 meters. GPS field measurements were taken as close as possible to the item of interest.

Section 6 - Page 4

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 Figure 6.0-1 Sampling Locations Map (Site Boundary)

Section 6 - Page 5

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 Figure 6.0-2 Sampling Locations Map (Ten Mile Radius)

Section 6 - Page 6

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 Figure 6.0-3 ONS 2006 Land Use Census Map Section 6 - Page 7

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 6.0.3 OCONEE METEOROLOGY: RELATIVE AIR CONCENTRATIONS AND DEPOSITION Calculations of annually averaged air concentrations and deposition values from routine releases provide the air dispersion and deposition factors needed for dose assessment.

The methodology is based upon Regulatory Guide 1.111, as implemented by the NRC's computer model "XOQDOQ: Computer Program for the Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations," NUREG/CR-2919, PNL-4380, September 1982.

Five years of hourly meteorological data from the onsite instruments are processed into a representative joint frequency distribution of winds and atmospheric stability for input into the XOQDOQ model (Version 2.0). Thus, the air dispersion and deposition factors

(/Q and D/Q) output by the model are based on a five-year climatology for the site.

6.0.3.1 XOQDOQ METHODOLOGY AND ASSUMPTIONS A continuous, routine release (non-purge) is simulated from each unit vent. The unit vent release type is categorized as semi-elevated, being elevated approximately 92% of the time and being at ground-level approximately 8% of the time. This is based on RG 1.111 criteria, with the ratio (i.e. 3.64) of the average exit velocity (11.39 m/s) to the mean wind speed at the 60 m release height (3.13 m/s). To account for all release pathways, Oconee is modeled as both a totally "ground-level" release and as a "mixed-mode" release, with two model runs of XOQDOQ.

Surrounding terrain heights are not input for ground-level releases, but are used for the elevated portion of mixed-mode releases. The locale consists of rolling terrain, so the default open terrain recirculation factor is applied in XOQDOQ [KOPT(8)=1]. This correction factor is recommended in RG 1.111 to adjust the straight-line airflow of the model for spatial and temporal variations that are produced by large scale weather patterns.

In order for XOQDOQ to treat the plume as a ground-level release, the exit velocity and the inside diameter of the unit vent must be input as zero. The heat emission rate of each vent is also assumed to be zero, as recommended by the model. A release height of 10 m is assumed for the ground-level release, with actual plant grade of 796 ft msl. Using the building height (58 m) and minimum cross-sectional area of the containment building (2296 m2), XOQDOQ applies a building wake correction to the relative air concentrations.

For the mixed-mode release, the exit velocities (11.1, 11.3, and 11.7 m/s for U1-U3, respectively) and inside diameters (1.8 m) of the unit vents are input to the XOQDOQ model for each vent. The heat emission rate of each vent is still assumed to be zero, as in the ground-level release. Plant grade elevation is now input as zero, however, to properly Section 6 - Page 8

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 utilize the input terrain heights above yard grade elevation (Table 6.0-4). The height of the vent (60.7 m) above plant grade is used to determine the plume centerline height.

Table 6.0-4 Terrain Heights Above ONS Yard Grade Elevation (m)

Distance: 0.5 1 1.5 2.0 2.5 3.0 3.5 4.0 4.5 5.0 mile mile miles miles miles miles miles miles miles miles S 29 38 38 38 38 38 50 50 50 50 SSW 32 44 50 50 50 50 50 50 50 50 SW 38 44 44 44 50 50 50 50 50 50 WSW 44 44 44 44 44 44 44 48 48 57 W 48 48 48 48 48 55 58 73 73 73 WNW 29 29 29 38 65 65 71 71 77 80 NW 30 30 30 48 50 68 69 69 71 71 NNW 30 30 30 48 50 68 69 69 71 71 N 29 30 30 30 30 30 62 62 62 74 NNE 24 24 35 35 53 53 82 82 82 82 NE 7 13 35 44 44 50 78 88 99 100 ENE 4 23 35 38 53 62 74 80 99 100 E 1 24 24 24 57 68 68 74 84 84 ESE 1 1 13 35 62 62 62 65 71 71 SE 7 20 20 44 67 67 67 67 67 67 SSE 7 38 38 38 47 62 62 62 62 62 Calculations of relative air concentrations and deposition are made for gridded receptor distances per sector. The model's default values for half-lives are used (i.e. no decay; 2.26 days for short-lived noble gases; and 8 days with depletion factors for all iodines

[DECAYS(I)= 101; 2.26; -8.0] ).

6.0.3.2 METEOROLOGICAL DATA Five years (1988-1992) of hourly, onsite meteorological data are used to produce the joint frequency distributions of wind speed and direction per stability class. The 10 m level winds are used. It is these joint frequency distributions which are input to the XOQDOQ model. XOQDOQ extrapolates the 10 m wind speed to the release height during the elevated portion of mixed-mode releases. Hours of calm winds are distributed by direction with the same frequency as the lowest "noncalm" wind speed class

[KOPT(1)=1]. Thus, wind speed classes are established so that the lowest wind speed class is the starting threshold of the anemometer (i.e. the "calm" wind speed class). The largest wind speed class has the upper bound of (5 m/s + max hourly wind speed).

Stability classes (A-G) are based on the vertical temperature gradient, measured by the hourly averaged delta-T variable.

Section 6 - Page 9

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 6.0.3.3 ANNUAL XOQDOQ COMPARISON TO THE ODCM Each year, the prevailing winds and stability class frequencies for ONS are compared to the 5-year period (1988-1992) upon which the /Q and D/Q calculations have been made.

The 5-year climatology is summarized in Table 6.0-5 and Table 6.0-6 below. Since the comparison is being made to a 5-year climatology, significant differences should not occur in the meteorological variables of concern (i.e. winds and delta-T). The meteorological comparison serves to verify this assumption.

Table 6.0-5 ONS Atmospheric Stability Frequency (1988-1992)

A B C D E F G Frequency

(%) 8.9 5.4 6.1 39.5 33.1 5.6 1.5 Table 6.0-6 ONS Frequency of Wind Direction (From) and Speed (1988-1992)

Wind Direction Wind Speed Class Wind Speed Sector Frequency (%) (m/s) Frequency (%)

N 5.1 CALM 1.0 NNE 5.2 0.45 - 0.74 m/s 4.7 NE 9 0.75 - 0.99 m/s 9.4 ENE 8.3 1.00 - 1.24 m/s 10.0 E 5.2 1.25 - 1.49 m/s 12.3 ESE 3.1 1.50 - 1.99 m/s 16.8 SE 3 2.00 - 2.99 m/s 20.4 SSE 3.5 3.00 - 3.99 m/s 9.6 S 3.6 4.00 - 4.99 m/s 4.5 SSW 8.5 5.00 - 5.99 m/s 1.8 SW 11.7 6.00 - 7.99 m/s 1.3 WSW 7.4 8.00 - 9.99 m/s 0.3 W 5.1 > 9.99 m/s 8.9 WNW 6.9 NW 7.2 NNW 6.3 The joint frequency distributions of wind speed and direction versus atmospheric stability class are also determined from the annual data to provide input to the XOQDOQ model.

Modeled /Q and D/Q values for the 1.0 mile Exclusion Area Boundary at ONS are Section 6 - Page 10

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 compared to the maximum of the (1988-1992) /Q and D/Q values from all sectors. If the newly calculated annual dispersion and deposition values do not result in a significant increase in the calculated offsite dose relative to the 10CFR50, Appendix I dose objectives then the 5-year /Q and D/Q values used in the Annual Radiological Effluent Release Report (ARERR) are not revised. An increase in calculated offsite dose that is greater than five percent of the 10CFR50, Appendix I dose objectives would be considered significant enough to warrant a change in the /Q and D/Q values used in the ARERR. If an increasing trend in the annual /Q and D/Q values compared to the 5-year values is noted then a revised set of 5-year /Q and D/Q values will be generated. These limiting values are listed in Table 6.0-7. The entire /Q and D/Q list based on directional sector and distance is given in Table 6.0-9 and Table 6.0-10.

Table 6.0-7 ONS Limiting /Q and D/Q Values (1988-1992)

(/Q,s/m3) Distance Sector (D/Q,1/m2)

Ground-level Release: Maximum /Q 7.308E-06 1 mile EAB SE Ground-level Release: Maximum D/Q 2.259E-8 1 mile EAB NE Mixed-mode Release: Maximum /Q 1.672E-06 1 mile EAB SW Mixed-mode Release: Maximum D/Q 1.295E-08 1 mile EAB NE Note:

The Oconee meteorological instruments were relocated from the 46 m microwave tower to a new 60 m onsite meteorological tower in April 1988. The 60 m tower became operational at 1700 hours0.0197 days <br />0.472 hours <br />0.00281 weeks <br />6.4685e-4 months <br /> on April 23, 1988. Therefore, determination of atmospheric stability should use the 36 m separation criteria for the period February 24, 1977-April 22, 1988 shown in Table 6.0-8. Data starting on April 23, 1988 or later should use the 50 m separation criteria.

Table 6.0-8 ONS Delta-T Ranges per Vertical Separation Distances Stability 36m separation Delta-T 50m separation Delta-T Class (between 46m-10m levels) (between 60m-10m levels)

FEB 24, 1977 - APRIL 18, 1988 Starting at hour 1700 on (4/18/88 ending hour 1430) April 23, 1988.

A dT < -0.68 dT < -0.95 B -0.68 < dT < -0.61 -0.95 < dT < -0.85 C -0.61 < dT < -0.54 -0.85 < dT < -0.75 D -0.54 < dT < -0.18 -0.75 < dT < -0.25 E -0.18 < dT < 0.54 -0.25 < dT < 0.75 F 0.54 < dT < 1.44 0.75 < dT < 2.00 G 1.44 < Dt 2.00 < dT Section 6 - Page 11

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 Table 6.0-9 (page 1 of 2)

Oconee Semi-Elevated /Q Average Values (1988-1992)

(sec/m3)

Sector 1.0-1.5* 1.5-2.0 2.0-2.5 2.5-3.0 3.0-3.5 3.5-4.0 4.0-4.5 4.5-5.0 N 5.220E-07 2.650E-07 1.594E-07 1.069E-07 7.719E-08 7.321E-08 5.665E-08 4.542E-08 NNE 8.379E-07 4.734E-07 2.690E-07 2.003E-07 1.385E-07 1.091E-07 8.379E-08 6.676E-08 NE 9.503E-07 6.350E-07 3.962E-07 2.535E-07 1.847E-07 1.497E-07 1.157E-07 9.246E-08 ENE 8.116E-07 4.856E-07 2.919E-07 2.196E-07 1.619E-07 1.239E-07 9.609E-08 7.720E-08 E 5.950E-07 3.202E-07 2.015E-07 2.270E-07 1.745E-07 1.292E-07 1.024E-07 8.308E-08 ESE 4.531E-07 3.300E-07 3.623E-07 4.020E-07 2.822E-07 2.109E-07 1.688E-07 1.405E-07 SE 7.505E-07 4.573E-07 5.490E-07 5.110E-07 3.560E-07 2.648E-07 2.063E-07 1.665E-07 SSE 1.419E-06 7.428E-07 4.527E-07 3.489E-07 2.866E-07 2.131E-07 1.659E-07 1.337E-07 S 1.170E-06 6.099E-07 3.701E-07 2.496E-07 1.810E-07 1.552E-07 1.218E-07 9.867E-08 SSW 1.214E-06 6.327E-07 3.564E-07 2.301E-07 1.621E-07 1.213E-07 9.481E-08 7.660E-08 SW 1.672E-06 7.285E-07 4.057E-07 2.720E-07 1.891E-07 1.400E-07 1.085E-07 8.708E-08 WSW 1.558E-06 6.820E-07 3.804E-07 2.438E-07 1.708E-07 1.271E-07 1.010E-07 8.114E-08 W 1.193E-06 5.214E-07 2.909E-07 1.867E-07 1.372E-07 1.032E-07 8.326E-08 6.654E-08 WNW 4.658E-07 2.480E-07 1.760E-07 1.482E-07 1.024E-07 7.695E-08 5.943E-08 4.796E-08 NW 4.831E-07 2.524E-07 1.965E-07 1.291E-07 9.959E-08 7.356E-08 5.682E-08 4.566E-08 NNW 5.375E-07 2.769E-07 2.128E-07 1.394E-07 1.072E-07 7.913E-08 6.110E-08 4.907E-08

  • Units are in miles from the station. As discussed in Oconee UFSAR Section 2.1.1.3, the boundary for establishing gaseous effluent release limits is the exclusion area boundary (EAB). The EAB is at a radius of 1.0 mile from the station center. Each /Q value is calculated at the closest location for the sector, e.g., 1.672E-06 sec/m3 is the /Q value at 1.0 mile (SW) from the station.

Section 6 - Page 12

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 Table 6.0-9 (page 2 of 2)

Oconee Semi-Elevated D/Q Average Values (1988-1992)

(m-2)

Sector 1.0-1.5* 1.5-2.0 2.0-2.5 2.5-3.0 3.0-3.5 3.5-4.0 4.0-4.5 4.5-5.0 N 2.890E-09 1.184E-09 6.225E-10 3.812E-10 2.586E-10 3.380E-10 2.510E-10 1.943E-10 NNE 9.113E-09 3.989E-09 2.013E-09 1.248E-09 8.235E-10 8.997E-10 6.667E-10 5.138E-10 NE 1.295E-08 5.666E-09 2.919E-09 1.729E-09 1.145E-09 1.224E-09 9.140E-10 7.067E-10 ENE 7.899E-09 3.385E-09 1.756E-09 1.095E-09 9.819E-10 7.671E-10 5.749E-10 4.466E-10 E 4.454E-09 1.775E-09 9.252E-10 7.164E-10 7.491E-10 5.267E-10 3.981E-10 3.125E-10 ESE 4.361E-09 1.838E-09 1.086E-09 1.322E-09 8.696E-10 6.161E-10 5.153E-10 4.139E-10 SE 3.397E-09 1.385E-09 8.341E-10 1.649E-09 1.080E-09 7.595E-10 5.629E-10 4.340E-10 SSE 3.333E-09 1.323E-09 6.920E-10 4.404E-10 7.307E-10 5.202E-10 3.922E-10 3.091E-10 S 3.192E-09 1.256E-09 6.530E-10 4.020E-10 2.788E-10 2.177E-10 1.759E-10 1.501E-10 SSW 5.190E-09 1.972E-09 9.899E-10 5.895E-10 3.928E-10 2.842E-10 2.192E-10 1.778E-10 SW 1.205E-08 4.399E-09 2.193E-09 1.299E-09 8.521E-10 6.028E-10 4.518E-10 3.546E-10 WSW 1.047E-08 3.824E-09 1.908E-09 1.127E-09 7.422E-10 5.277E-10 3.980E-10 3.145E-10 W 5.577E-09 2.044E-09 1.025E-09 6.094E-10 4.134E-10 3.405E-10 3.962E-10 3.052E-10 WNW 2.185E-09 9.042E-10 5.220E-10 6.464E-10 4.227E-10 3.188E-10 2.360E-10 1.868E-10 NW 2.097E-09 8.759E-10 5.225E-10 3.196E-10 4.521E-10 3.178E-10 2.353E-10 1.812E-10 NNW 2.461E-09 1.028E-09 6.219E-10 3.765E-10 5.128E-10 3.604E-10 2.667E-10 2.054E-10

  • Units are in miles from the station. As discussed in Oconee UFSAR Section 2.1.1.3, the boundary for establishing gaseous effluent release limits is the exclusion area boundary (EAB). The EAB is defined as a 1 mile radius from the station center. Each D/Q value is calculated at the closest location for the sector, e.g., 1.205E-08 m-2 is the D/Q value at 1.0 mile (SW) from the station.

Section 6 - Page 13

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 Table 6.0-10 (page 1 of 2)

Oconee Ground Level /Q Average Values (1988-1992)

(sec/m3)

Sector 1.0-1.5* 1.5-2.0 2.0-2.5 2.5-3.0 3.0-3.5 3.5-4.0 4.0-4.5 4.5-5.0 N 2.115E-06 8.389E-07 4.495E-07 2.822E-07 1.952E-07 1.443E-07 1.117E-07 8.961E-08 NNE 2.898E-06 1.137E-06 6.047E-07 3.775E-07 2.602E-07 1.916E-07 1.480E-07 1.184E-07 NE 3.886E-06 1.529E-06 8.158E-07 5.108E-07 3.529E-07 2.604E-07 2.015E-07 1.616E-07 ENE 3.226E-06 1.277E-06 6.848E-07 4.305E-07 2.983E-07 2.207E-07 1.711E-07 1.374E-07 E 3.522E-06 1.410E-06 7.658E-07 4.866E-07 3.400E-07 2.534E-07 1.977E-07 1.596E-07 ESE 5.964E-06 2.407E-06 1.321E-06 8.459E-07 5.950E-07 4.457E-07 3.493E-07 2.832E-07 SE 7.308E-06 2.972E-06 1.631E-06 1.044E-06 7.342E-07 5.497E-07 4.307E-07 3.490E-07 SSE 6.604E-06 2.657E-06 1.440E-06 9.117E-07 6.354E-07 4.723E-07 3.676E-07 2.962E-07 S 5.278E-06 2.121E-06 1.146E-06 7.237E-07 5.032E-07 3.734E-07 2.901E-07 2.335E-07 SSW 3.986E-06 1.589E-06 8.536E-07 5.370E-07 3.721E-07 2.753E-07 2.135E-07 1.714E-07 SW 4.108E-06 1.620E-06 8.628E-07 5.390E-07 3.715E-07 2.735E-07 2.112E-07 1.689E-07 WSW 3.804E-06 1.503E-06 8.018E-07 5.015E-07 3.460E-07 2.549E-07 1.970E-07 1.577E-07 W 2.978E-06 1.186E-06 6.361E-07 3.995E-07 2.765E-07 2.043E-07 1.583E-07 1.270E-07 WNW 2.201E-06 8.791E-07 4.726E-07 2.974E-07 2.062E-07 1.526E-07 1.183E-07 9.502E-08 NW 2.104E-06 8.385E-07 4.499E-07 2.826E-07 1.957E-07 1.447E-07 1.121E-07 8.991E-08 NNW 2.221E-06 8.860E-07 4.755E-07 2.988E-07 2.069E-07 1.529E-07 1.185E-07 9.508E-08

  • Units are in miles from the station. As discussed in Oconee UFSAR Section 2.1.1.3, the boundary for establishing gaseous effluent release limits is the exclusion area boundary (EAB). The EAB is defined as a 1 mile radius from the station center. Each /Q value is calculated at the closest location for the sector, e.g., 4.108E-06 sec/m3 is the /Q value at 1.0 mile (SW) from the station.

Section 6 - Page 14

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 Table 6.0-10 (page 2 of 2)

Oconee Ground Level D/Q Average Values (1988-1992)

(m-2)

Sector 1.0-1.5* 1.5-2.0 2.0-2.5 2.5-3.0 3.0-3.5 3.5-4.0 4.0-4.5 4.5-5.0 N 6.916E-09 2.484E-09 1.232E-09 7.255E-10 4.750E-10 3.342E-10 2.477E-10 1.909E-10 NNE 1.642E-08 5.897E-09 2.924E-09 1.722E-09 1.128E-09 7.934E-10 5.880E-10 4.531E-10 NE 2.259E-08 8.114E-09 4.024E-09 2.369E-09 1.551E-09 1.092E-09 8.090E-10 6.235E-10 ENE 1.428E-08 5.130E-09 2.544E-09 1.498E-09 9.810E-10 6.902E-10 5.115E-10 3.942E-10 E 9.899E-09 3.556E-09 1.763E-09 1.038E-09 6.798E-10 4.784E-10 3.545E-10 2.732E-10 ESE 1.336E-08 4.798E-09 2.379E-09 1.401E-09 9.174E-10 6.455E-10 4.784E-10 3.686E-10 SE 1.401E-08 5.034E-09 2.496E-09 1.470E-09 9.625E-10 6.772E-10 5.019E-10 3.868E-10 SSE 1.226E-08 4.404E-09 2.184E-09 1.286E-09 8.420E-10 5.925E-10 4.391E-10 3.384E-10 S 1.008E-08 3.620E-09 1.795E-09 1.057E-09 6.922E-10 4.871E-10 3.610E-10 2.782E-10 SSW 9.941E-09 3.571E-09 1.771E-09 1.043E-09 6.828E-10 4.804E-10 3.560E-10 2.744E-10 SW 1.717E-08 6.169E-09 3.059E-09 1.801E-09 1.180E-09 8.300E-10 6.151E-10 4.740E-10 WSW 1.574E-08 5.655E-09 2.804E-09 1.651E-09 1.081E-09 7.608E-10 5.638E-10 4.345E-10 W 9.988E-09 3.588E-09 1.779E-09 1.048E-09 6.860E-10 4.827E-10 3.577E-10 2.757E-10 WNW 5.953E-09 2.138E-09 1.060E-09 6.244E-10 4.088E-10 2.877E-10 2.132E-10 1.643E-10 NW 5.891E-09 2.116E-09 1.049E-09 6.179E-10 4.046E-10 2.847E-10 2.110E-10 1.626E-10 NNW 6.672E-09 2.397E-09 1.188E-09 6.998E-10 4.582E-10 3.224E-10 2.390E-10 1.841E-10

  • Units are in miles from the station. As discussed in Oconee UFSAR Section 2.1.1.3, the boundary for establishing gaseous effluent release limits is the exclusion area boundary (EAB). The EAB is defined as a 1 mile radius from the station center. Each D/Q value is calculated at the closest location for the sector, e.g., 1.717E-08 m-2 is the D/Q value at 1.0 mile (SW) from the station.

Section 6 - Page 15

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 7.0 LICENSEE INITIATED CHANGES All changes made to the Oconee ODCM are reviewed by knowledgeable individual(s), and approved by the Station Manager and the General Office Radiation Protection Manager prior to implementation. The following changes do not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

Section 2 - Page 1 Removed the "s" from Decant Monitor Tanks because there is only one Decant Monitor Tank.

Section 2 - Page 2 Added "TBSMT" to make clear that the Turbine Building Sump Monitor Tanks are an input source to #3 CTP. Removed "Radwaste Facility monitor tanks" because that source is not ever released to #3 CTP.

Section 3 - Page 5 Corrected typographical error for the Unit 2 Reactor Building Purge controlling RIA and the Unit 3 Reactor Building Purge controlling RIA.

Section 4 - Page 3 Provided detail on what value is assumed for the average dilution flow during the liquid release period of interest.

Removed redundant information related to the recirculation factor.

Section 6 - Page 4 Changed title of Table 6.0-3 to: "Oconee 2006 Land Use Census Results."

Land use census dates were changed to reflect 2006 census dates.

Section 6 - Page 6 Location 036 symbol added to map in N sector.

Section 6 - Page 7 Changed title of Figure 6.0-3 to: ONS 2006 Land Use Census Map.

Figure 6.0-3 regenerated to depict 2006 census data.

Section 7 - Page 1

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX A Dose Factors for Exposure to a Semi-Infinite Cloud of Noble Gases*

Ki Li Mi Ni Total Body Skin Gamma Air Beta Air Nuclide mrem/yr/ mrem/yr/ mrad/yr/ mrad/yr/

Ci/m3 Ci/m3 Ci/m3 Ci/m3 AR-41 8.840E+03 2.690E+03 9.300E+03 3.280E+03 KR-83M 7.560E-02 0.000E+00 1.930E+01 2.880E+02 KR-85M 1.170E+03 1.460E+03 1.230E+03 1.970E+03 KR-85 1.610E+01 1.340E+03 1.720E+01 1.950E+03 KR-87 5.920E+03 9.730E+03 6.170E+03 1.030E+04 KR-88 1.470E+04 2.370E+03 1.520E+04 2.930E+03 KR-89 1.660E+04 1.010E+04 1.730E+04 1.060E+04 KR-90 1.560E+04 7.290E+03 1.630E+04 7.830E+03 XE-131M 9.150E+01 4.760E+02 1.560E+02 1.110E+03 XE-133M 2.510E+02 9.940E+02 3.270E+02 1.480E+03 XE-133 2.940E+02 3.060E+02 3.530E+02 1.050E+03 XE-135M 3.120E+03 7.110E+02 3.360E+03 7.390E+02 XE-135 1.810E+03 1.860E+03 1.920E+03 2.460E+03 XE-137 1.420E+03 1.220E+04 1.510E+03 1.270E+04 XE-138 8.830E+03 4.130E+03 9.210E+03 4.750E+03

  • Reference Regulatory Guide 1.109, Table B-1 Appendix A Dose Factors for Exposure to a Semi-Infinite Cloud of Noble Gases - Page 1 of 1

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX B Pi Dose Factors for use in the Gaseous Release Rate Limit Calculations Agegroup: CHILD Pathway: Inhalation (INHL) Units: mrem/yr / Ci/m3 Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body H-3 0.000E+00 1.120E+03 1.120E+03 1.120E+03 1.120E+03 1.120E+03 0.000E+00 1.120E+03 C-14 3.590E+04 6.730E+03 6.730E+03 6.730E+03 6.730E+03 6.730E+03 0.000E+00 6.730E+03 NA-24 1.610E+04 1.610E+04 1.610E+04 1.610E+04 1.610E+04 1.610E+04 0.000E+00 1.610E+04 P-32 2.600E+06 1.140E+05 0.000E+00 0.000E+00 0.000E+00 4.220E+04 0.000E+00 9.880E+04 CR-51 0.000E+00 0.000E+00 8.550E+01 2.430E+01 1.700E+04 1.080E+03 0.000E+00 1.540E+02 MN-54 0.000E+00 4.290E+04 0.000E+00 1.000E+04 1.580E+06 2.290E+04 0.000E+00 9.510E+03 MN-56 0.000E+00 1.660E+00 0.000E+00 1.670E+00 1.310E+04 1.230E+05 0.000E+00 3.120E-01 FE-55 4.740E+04 2.520E+04 0.000E+00 0.000E+00 1.110E+05 2.870E+03 0.000E+00 7.770E+03 FE-59 2.070E+04 3.340E+04 0.000E+00 0.000E+00 1.270E+06 7.070E+04 0.000E+00 1.670E+04 CO-58 0.000E+00 1.770E+03 0.000E+00 0.000E+00 1.110E+06 3.440E+04 0.000E+00 3.160E+03 CO-60 0.000E+00 1.310E+04 0.000E+00 0.000E+00 7.070E+06 9.620E+04 0.000E+00 2.260E+04 NI-63 8.210E+05 4.620E+04 0.000E+00 0.000E+00 2.750E+05 6.330E+03 0.000E+00 2.800E+04 NI-65 2.990E+00 2.960E-01 0.000E+00 0.000E+00 8.180E+03 8.400E+04 0.000E+00 1.640E-01 CU-64 0.000E+00 1.990E+00 0.000E+00 6.030E+00 9.580E+03 3.670E+04 0.000E+00 1.070E+00 ZN-65 4.260E+04 1.130E+05 0.000E+00 7.140E+04 9.950E+05 1.630E+04 0.000E+00 7.030E+04 ZN-69 6.700E-02 9.660E-02 0.000E+00 5.850E-02 1.420E+03 1.020E+04 0.000E+00 8.920E-03 BR-83 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4.740E+02 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.480E+02 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.530E+01 RB-86 0.000E+00 1.980E+05 0.000E+00 0.000E+00 0.000E+00 7.990E+03 0.000E+00 1.140E+05 RB-88 0.000E+00 5.620E+02 0.000E+00 0.000E+00 0.000E+00 1.720E+01 0.000E+00 3.660E+02 RB-89 0.000E+00 3.450E+02 0.000E+00 0.000E+00 0.000E+00 1.890E+00 0.000E+00 2.900E+02 SR-89 5.990E+05 0.000E+00 0.000E+00 0.000E+00 2.160E+06 1.670E+05 0.000E+00 1.720E+04 SR-90 1.010E+08 0.000E+00 0.000E+00 0.000E+00 1.480E+07 3.430E+05 0.000E+00 6.440E+06 SR-91 1.210E+02 0.000E+00 0.000E+00 0.000E+00 5.330E+04 1.740E+05 0.000E+00 4.590E+00 Appendix B Pi Child Inhalation - Page 1 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX B Pi Dose Factors for use in the Gaseous Release Rate Limit Calculations Agegroup: CHILD Pathway: Inhalation (INHL) Units: mrem/yr / Ci/m3 Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body SR-92 1.310E+01 0.000E+00 0.000E+00 0.000E+00 2.400E+04 2.420E+05 0.000E+00 5.250E-01 Y-90 4.110E+03 0.000E+00 0.000E+00 0.000E+00 2.620E+05 2.680E+05 0.000E+00 1.110E+02 Y-91 9.140E+05 0.000E+00 0.000E+00 0.000E+00 2.630E+06 1.840E+05 0.000E+00 2.440E+04 Y-91M 5.070E-01 0.000E+00 0.000E+00 0.000E+00 2.810E+03 1.720E+03 0.000E+00 1.840E-02 Y-92 2.030E+01 0.000E+00 0.000E+00 0.000E+00 2.390E+04 2.390E+05 0.000E+00 5.810E-01 Y-93 1.860E+02 0.000E+00 0.000E+00 0.000E+00 7.440E+04 3.880E+05 0.000E+00 5.110E+00 ZR-95 1.900E+05 4.180E+04 0.000E+00 5.960E+04 2.230E+06 6.110E+04 0.000E+00 3.700E+04 ZR-97 1.880E+02 2.720E+01 0.000E+00 3.880E+01 1.130E+05 3.510E+05 0.000E+00 1.600E+01 NB-95 2.350E+04 9.180E+03 0.000E+00 8.620E+03 6.140E+05 3.700E+04 0.000E+00 6.550E+03 MO-99 0.000E+00 1.720E+02 0.000E+00 3.920E+02 1.350E+05 1.270E+05 0.000E+00 4.260E+01 TC-99M 1.780E-03 3.480E-03 0.000E+00 5.070E-02 9.510E+02 4.810E+03 0.000E+00 5.770E-02 TC-101 8.100E-05 8.510E-05 0.000E+00 1.450E-03 5.850E+02 1.630E+01 0.000E+00 1.080E-03 RU-103 2.790E+03 0.000E+00 0.000E+00 7.030E+03 6.620E+05 4.480E+04 0.000E+00 1.070E+03 RU-105 1.530E+00 0.000E+00 0.000E+00 1.340E+00 1.590E+04 9.950E+04 0.000E+00 5.550E-01 RU-106 1.360E+05 0.000E+00 0.000E+00 1.840E+05 1.430E+07 4.290E+05 0.000E+00 1.690E+04 AG-110M 1.690E+04 1.140E+04 0.000E+00 2.120E+04 5.480E+06 1.000E+05 0.000E+00 9.140E+03 TE-125M 6.730E+03 2.330E+03 1.920E+03 0.000E+00 4.770E+05 3.380E+04 0.000E+00 9.140E+02 TE-127 2.770E+00 9.510E-01 1.960E+00 7.070E+00 1.000E+04 5.620E+04 0.000E+00 6.100E-01 TE-127M 2.490E+04 8.550E+03 6.070E+03 6.360E+04 1.480E+06 7.140E+04 0.000E+00 3.020E+03 TE-129 9.770E-02 3.500E-02 7.140E-02 2.570E-01 2.930E+03 2.550E+04 0.000E+00 2.380E-02 TE-129M 1.920E+04 6.840E+03 6.330E+03 5.030E+04 1.760E+06 1.820E+05 0.000E+00 3.040E+03 TE-131 2.170E-02 8.440E-03 1.700E-02 5.880E-02 2.050E+03 1.330E+03 0.000E+00 6.590E-03 TE-131M 1.340E+02 5.920E+01 9.770E+01 4.000E+02 2.060E+05 3.080E+05 0.000E+00 5.070E+01 TE-132 4.810E+02 2.720E+02 3.170E+02 1.770E+03 3.770E+05 1.380E+05 0.000E+00 2.630E+02 I-130 8.180E+03 1.640E+04 1.850E+06 2.450E+04 0.000E+00 5.110E+03 0.000E+00 8.440E+03 Appendix B Pi Child Inhalation - Page 2 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX B Pi Dose Factors for use in the Gaseous Release Rate Limit Calculations Agegroup: CHILD Pathway: Inhalation (INHL) Units: mrem/yr / Ci/m3 Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body I-131 4.810E+04 4.810E+04 1.620E+07 7.880E+04 0.000E+00 2.840E+03 0.000E+00 2.730E+04 I-132 2.120E+03 4.070E+03 1.940E+05 6.250E+03 0.000E+00 3.200E+03 0.000E+00 1.880E+03 I-133 1.660E+04 2.030E+04 3.850E+06 3.380E+04 0.000E+00 5.480E+03 0.000E+00 7.700E+03 I-134 1.170E+03 2.160E+03 5.070E+04 3.300E+03 0.000E+00 9.550E+02 0.000E+00 9.950E+02 I-135 4.920E+03 8.730E+03 7.920E+05 1.340E+04 0.000E+00 4.440E+03 0.000E+00 4.140E+03 CS-134 6.510E+05 1.010E+06 0.000E+00 3.300E+05 1.210E+05 3.850E+03 0.000E+00 2.250E+05 CS-136 6.510E+04 1.710E+05 0.000E+00 9.550E+04 1.450E+04 4.180E+03 0.000E+00 1.160E+05 CS-137 9.060E+05 8.250E+05 0.000E+00 2.820E+05 1.040E+05 3.620E+03 0.000E+00 1.280E+05 CS-138 6.330E+02 8.400E+02 0.000E+00 6.220E+02 6.810E+01 2.700E+02 0.000E+00 5.550E+02 BA-139 1.840E+00 9.840E-04 0.000E+00 8.620E-04 5.770E+03 5.770E+04 0.000E+00 5.360E-02 BA-140 7.400E+04 6.480E+01 0.000E+00 2.110E+01 1.740E+06 1.020E+05 0.000E+00 4.330E+03 BA-141 1.960E-01 1.090E-04 0.000E+00 9.470E-05 2.920E+03 2.750E+02 0.000E+00 6.360E-03 BA-142 5.000E-02 3.600E-05 0.000E+00 2.910E-05 1.640E+03 2.740E+00 0.000E+00 2.790E-03 LA-140 6.440E+02 2.250E+02 0.000E+00 0.000E+00 1.830E+05 2.260E+05 0.000E+00 7.550E+01 LA-142 1.300E+00 4.110E-01 0.000E+00 0.000E+00 8.700E+03 7.580E+04 0.000E+00 1.290E-01 CE-141 3.920E+04 1.950E+04 0.000E+00 8.550E+03 5.440E+05 5.660E+04 0.000E+00 2.900E+03 CE-143 3.660E+02 1.990E+02 0.000E+00 8.360E+01 1.150E+05 1.270E+05 0.000E+00 2.870E+01 CE-144 6.770E+06 2.120E+06 0.000E+00 1.170E+06 1.200E+07 3.880E+05 0.000E+00 3.610E+05 PR-143 1.850E+04 5.550E+03 0.000E+00 3.000E+03 4.330E+05 9.730E+04 0.000E+00 9.140E+02 PR-144 5.960E-02 1.850E-02 0.000E+00 9.770E-03 1.570E+03 1.970E+02 0.000E+00 3.000E-03 ND-147 1.080E+04 8.730E+03 0.000E+00 4.810E+03 3.280E+05 8.210E+04 0.000E+00 6.810E+02 W-187 1.630E+01 9.660E+00 0.000E+00 0.000E+00 4.110E+04 9.100E+04 0.000E+00 4.330E+00 NP-239 4.660E+02 3.340E+01 0.000E+00 9.730E+01 5.810E+04 6.400E+04 0.000E+00 2.350E+01 Appendix B Pi Child Inhalation - Page 3 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX C Ai Adult Dose Factors for use in the Liquid Dose Calculations Agegroup: ADULT Pathway: Potable Water (PWtr) Units: mrem/hr / Ci/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body H-3 0.000E+00 8.740E+00 8.740E+00 8.740E+00 8.740E+00 8.740E+00 0.000E+00 8.740E+00 C-14 2.360E+02 4.730E+01 4.730E+01 4.730E+01 4.730E+01 4.730E+01 0.000E+00 4.730E+01 NA-24 8.140E+01 8.140E+01 8.140E+01 8.140E+01 8.140E+01 8.140E+01 0.000E+00 8.140E+01 P-32 1.570E+04 9.750E+02 0.000E+00 0.000E+00 0.000E+00 1.760E+03 0.000E+00 6.060E+02 CR-51 0.000E+00 0.000E+00 1.310E-01 4.820E-02 2.900E-01 5.500E+01 0.000E+00 2.190E-01 MN-54 0.000E+00 3.800E+02 0.000E+00 1.130E+02 0.000E+00 1.160E+03 0.000E+00 7.250E+01 MN-56 0.000E+00 3.800E-01 0.000E+00 4.820E-01 0.000E+00 1.210E+01 0.000E+00 6.740E-02 FE-55 2.290E+02 1.580E+02 0.000E+00 0.000E+00 8.820E+01 9.070E+01 0.000E+00 3.690E+01 FE-59 3.580E+02 8.420E+02 0.000E+00 0.000E+00 2.350E+02 2.810E+03 0.000E+00 3.230E+02 CO-58 0.000E+00 6.170E+01 0.000E+00 0.000E+00 0.000E+00 1.250E+03 0.000E+00 1.380E+02 CO-60 0.000E+00 1.780E+02 0.000E+00 0.000E+00 0.000E+00 3.340E+03 0.000E+00 3.930E+02 NI-63 1.080E+04 7.500E+02 0.000E+00 0.000E+00 0.000E+00 1.560E+02 0.000E+00 3.630E+02 NI-65 1.620E+00 2.100E-01 0.000E+00 0.000E+00 0.000E+00 5.340E+00 0.000E+00 9.600E-02 CU-64 0.000E+00 3.590E+00 0.000E+00 9.060E+00 0.000E+00 3.060E+02 0.000E+00 1.690E+00 ZN-65 4.020E+02 1.280E+03 0.000E+00 8.560E+02 0.000E+00 8.060E+02 0.000E+00 5.780E+02 ZN-69 1.070E-04 2.050E-04 0.000E+00 1.330E-04 0.000E+00 3.080E-05 0.000E+00 1.430E-05 BR-83 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.480E-01 0.000E+00 1.030E-01 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.270E-12 0.000E+00 6.710E-07 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4.380E-77 RB-86 0.000E+00 1.720E+03 0.000E+00 0.000E+00 0.000E+00 3.400E+02 0.000E+00 8.030E+02 RB-88 0.000E+00 3.360E-12 0.000E+00 0.000E+00 0.000E+00 4.640E-23 0.000E+00 1.780E-12 RB-89 0.000E+00 3.090E-14 0.000E+00 0.000E+00 0.000E+00 1.790E-27 0.000E+00 2.170E-14 SR-89 2.550E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4.080E+03 0.000E+00 7.310E+02 SR-90 6.310E+05 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.820E+04 0.000E+00 1.550E+05 SR-91 1.960E+02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 9.350E+02 0.000E+00 7.930E+00 Appendix C Ai Adult Water - Page 1 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX C Ai Adult Dose Factors for use in the Liquid Dose Calculations Agegroup: ADULT Pathway: Potable Water (PWtr) Units: mrem/hr / Ci/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body SR-92 8.290E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.640E+02 0.000E+00 3.590E-01 Y-90 7.030E-01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 7.460E+03 0.000E+00 1.890E-02 Y-91 1.170E+01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 6.420E+03 0.000E+00 3.120E-01 Y-91M 3.360E-07 0.000E+00 0.000E+00 0.000E+00 0.000E+00 9.860E-07 0.000E+00 1.300E-08 Y-92 6.710E-03 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.170E+02 0.000E+00 1.960E-04 Y-93 9.770E-02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.100E+03 0.000E+00 2.700E-03 ZR-95 2.520E+00 8.070E-01 0.000E+00 1.270E+00 0.000E+00 2.560E+03 0.000E+00 5.460E-01 ZR-97 8.540E-02 1.720E-02 0.000E+00 2.600E-02 0.000E+00 5.340E+03 0.000E+00 7.880E-03 NB-95 5.130E-01 2.850E-01 0.000E+00 2.820E-01 0.000E+00 1.730E+03 0.000E+00 1.530E-01 MO-99 0.000E+00 3.160E+02 0.000E+00 7.160E+02 0.000E+00 7.330E+02 0.000E+00 6.020E+01 TC-99M 5.160E-03 1.460E-02 0.000E+00 2.210E-01 7.140E-03 8.630E+00 0.000E+00 1.860E-01 TC-101 1.130E-17 1.630E-17 0.000E+00 2.930E-16 8.320E-18 4.890E-29 0.000E+00 1.600E-16 RU-103 1.530E+01 0.000E+00 0.000E+00 5.820E+01 0.000E+00 1.780E+03 0.000E+00 6.570E+00 RU-105 1.970E-01 0.000E+00 0.000E+00 2.540E+00 0.000E+00 1.200E+02 0.000E+00 7.760E-02 RU-106 2.290E+02 0.000E+00 0.000E+00 4.410E+02 0.000E+00 1.480E+04 0.000E+00 2.890E+01 AG-110M 1.330E+01 1.230E+01 0.000E+00 2.420E+01 0.000E+00 5.020E+03 0.000E+00 7.300E+00 TE-125M 2.220E+02 8.030E+01 6.670E+01 9.020E+02 0.000E+00 8.850E+02 0.000E+00 2.970E+01 TE-127 3.780E+00 1.360E+00 2.800E+00 1.540E+01 0.000E+00 2.980E+02 0.000E+00 8.170E-01 TE-127M 5.620E+02 2.010E+02 1.440E+02 2.280E+03 0.000E+00 1.880E+03 0.000E+00 6.840E+01 TE-129 1.920E-03 7.230E-04 1.480E-03 8.080E-03 0.000E+00 1.450E-03 0.000E+00 4.690E-04 TE-129M 9.470E+02 3.530E+02 3.250E+02 3.950E+03 0.000E+00 4.770E+03 0.000E+00 1.500E+02 TE-131 3.520E-09 1.470E-09 2.900E-09 1.540E-08 0.000E+00 4.990E-10 0.000E+00 1.110E-09 TE-131M 1.090E+02 5.340E+01 8.450E+01 5.400E+02 0.000E+00 5.300E+03 0.000E+00 4.450E+01 TE-132 1.880E+02 1.220E+02 1.350E+02 1.170E+03 0.000E+00 5.770E+03 0.000E+00 1.140E+02 I-130 3.210E+01 9.460E+01 8.020E+03 1.480E+02 0.000E+00 8.140E+01 0.000E+00 3.730E+01 Appendix C Ai Adult Water - Page 2 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX C Ai Adult Dose Factors for use in the Liquid Dose Calculations Agegroup: ADULT Pathway: Potable Water (PWtr) Units: mrem/hr / Ci/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body I-131 3.320E+02 4.740E+02 1.550E+05 8.130E+02 0.000E+00 1.250E+02 0.000E+00 2.720E+02 I-132 4.540E-01 1.220E+00 4.250E+01 1.940E+00 0.000E+00 2.280E-01 0.000E+00 4.250E-01 I-133 7.920E+01 1.380E+02 2.020E+04 2.400E+02 0.000E+00 1.240E+02 0.000E+00 4.200E+01 I-134 6.580E-04 1.790E-03 3.100E-02 2.840E-03 0.000E+00 1.560E-06 0.000E+00 6.390E-04 I-135 1.050E+01 2.750E+01 1.810E+03 4.400E+01 0.000E+00 3.100E+01 0.000E+00 1.010E+01 CS-134 5.170E+03 1.230E+04 0.000E+00 3.980E+03 1.320E+03 2.150E+02 0.000E+00 1.010E+04 CS-136 5.280E+02 2.080E+03 0.000E+00 1.160E+03 1.590E+02 2.370E+02 0.000E+00 1.500E+03 CS-137 6.630E+03 9.070E+03 0.000E+00 3.080E+03 1.020E+03 1.760E+02 0.000E+00 5.940E+03 CS-138 8.450E-07 1.670E-06 0.000E+00 1.230E-06 1.210E-07 7.120E-12 0.000E+00 8.260E-07 BA-139 1.990E-02 1.420E-05 0.000E+00 1.330E-05 8.050E-06 3.530E-02 0.000E+00 5.830E-04 BA-140 1.640E+03 2.070E+00 0.000E+00 7.020E-01 1.180E+00 3.390E+03 0.000E+00 1.080E+02 BA-141 5.440E-12 4.120E-15 0.000E+00 3.830E-15 2.340E-15 2.570E-21 0.000E+00 1.840E-13 BA-142 6.290E-21 6.470E-24 0.000E+00 5.460E-24 3.660E-24 8.860E-39 0.000E+00 3.960E-22 LA-140 1.690E-01 8.530E-02 0.000E+00 0.000E+00 0.000E+00 6.260E+03 0.000E+00 2.250E-02 LA-142 5.720E-05 2.600E-05 0.000E+00 0.000E+00 0.000E+00 1.900E-01 0.000E+00 6.480E-06 CE-141 7.710E-01 5.210E-01 0.000E+00 2.420E-01 0.000E+00 1.990E+03 0.000E+00 5.910E-02 CE-143 1.070E-01 7.890E+01 0.000E+00 3.470E-02 0.000E+00 2.950E+03 0.000E+00 8.730E-03 CE-144 4.060E+01 1.700E+01 0.000E+00 1.010E+01 0.000E+00 1.370E+04 0.000E+00 2.180E+00 PR-143 7.460E-01 2.990E-01 0.000E+00 1.730E-01 0.000E+00 3.270E+03 0.000E+00 3.700E-02 PR-144 7.350E-16 3.050E-16 0.000E+00 1.720E-16 0.000E+00 1.060E-22 0.000E+00 3.730E-17 ND-147 5.070E-01 5.860E-01 0.000E+00 3.430E-01 0.000E+00 2.810E+03 0.000E+00 3.510E-02 W-187 6.050E+00 5.050E+00 0.000E+00 0.000E+00 0.000E+00 1.660E+03 0.000E+00 1.770E+00 NP-239 8.550E-02 8.400E-03 0.000E+00 2.620E-02 0.000E+00 1.720E+03 0.000E+00 4.630E-03 Appendix C Ai Adult Water - Page 3 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX C Ai Adult Dose Factors for use in the Liquid Dose Calculations Agegroup: ADULT Pathway: Fresh Water Fish - Sport (FFSP) Units: mrem/hr / Ci/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body H-3 0.000E+00 2.260E-01 2.260E-01 2.260E-01 2.260E-01 2.260E-01 0.000E+00 2.260E-01 C-14 3.130E+04 6.260E+03 6.260E+03 6.260E+03 6.260E+03 6.260E+03 0.000E+00 6.260E+03 NA-24 1.350E+02 1.350E+02 1.350E+02 1.350E+02 1.350E+02 1.350E+02 0.000E+00 1.350E+02 P-32 1.320E+06 8.210E+04 0.000E+00 0.000E+00 0.000E+00 1.480E+05 0.000E+00 5.100E+04 CR-51 0.000E+00 0.000E+00 7.420E-01 2.740E-01 1.650E+00 3.120E+02 0.000E+00 1.240E+00 MN-54 0.000E+00 4.370E+03 0.000E+00 1.300E+03 0.000E+00 1.340E+04 0.000E+00 8.330E+02 MN-56 0.000E+00 1.730E-01 0.000E+00 2.200E-01 0.000E+00 5.530E+00 0.000E+00 3.070E-02 FE-55 6.580E+02 4.550E+02 0.000E+00 0.000E+00 2.540E+02 2.610E+02 0.000E+00 1.060E+02 FE-59 1.020E+03 2.400E+03 0.000E+00 0.000E+00 6.720E+02 8.010E+03 0.000E+00 9.220E+02 CO-58 0.000E+00 8.830E+01 0.000E+00 0.000E+00 0.000E+00 1.790E+03 0.000E+00 1.980E+02 CO-60 0.000E+00 2.560E+02 0.000E+00 0.000E+00 0.000E+00 4.810E+03 0.000E+00 5.650E+02 NI-63 3.110E+04 2.160E+03 0.000E+00 0.000E+00 0.000E+00 4.500E+02 0.000E+00 1.040E+03 NI-65 1.720E-01 2.230E-02 0.000E+00 0.000E+00 0.000E+00 5.660E-01 0.000E+00 1.020E-02 CU-64 0.000E+00 2.680E+00 0.000E+00 6.760E+00 0.000E+00 2.290E+02 0.000E+00 1.260E+00 ZN-65 2.310E+04 7.350E+04 0.000E+00 4.920E+04 0.000E+00 4.630E+04 0.000E+00 3.320E+04 ZN-69 7.730E-07 1.480E-06 0.000E+00 9.610E-07 0.000E+00 2.220E-07 0.000E+00 1.030E-07 BR-83 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.500E-02 0.000E+00 3.820E-02 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 9.850E-18 0.000E+00 1.250E-12 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 0.000E+00 9.730E+04 0.000E+00 0.000E+00 0.000E+00 1.920E+04 0.000E+00 4.530E+04 RB-88 0.000E+00 1.290E-22 0.000E+00 0.000E+00 0.000E+00 1.780E-33 0.000E+00 6.830E-23 RB-89 0.000E+00 1.640E-26 0.000E+00 0.000E+00 0.000E+00 9.560E-40 0.000E+00 1.160E-26 SR-89 2.180E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.500E+03 0.000E+00 6.260E+02 SR-90 5.440E+05 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.570E+04 0.000E+00 1.340E+05 SR-91 7.050E+01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.360E+02 0.000E+00 2.850E+00 Appendix C Ai Adult Fish - Page 1 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX C Ai Adult Dose Factors for use in the Liquid Dose Calculations Agegroup: ADULT Pathway: Fresh Water Fish - Sport (FFSP) Units: mrem/hr / Ci/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body SR-92 3.320E-01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 6.570E+00 0.000E+00 1.430E-02 Y-90 4.440E-01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4.710E+03 0.000E+00 1.190E-02 Y-91 8.340E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4.590E+03 0.000E+00 2.230E-01 Y-91M 1.070E-11 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.150E-11 0.000E+00 4.150E-13 Y-92 4.600E-04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 8.060E+00 0.000E+00 1.340E-05 Y-93 3.080E-02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 9.770E+02 0.000E+00 8.500E-04 ZR-95 2.380E-01 7.620E-02 0.000E+00 1.200E-01 0.000E+00 2.410E+02 0.000E+00 5.160E-02 ZR-97 4.960E-03 1.000E-03 0.000E+00 1.510E-03 0.000E+00 3.100E+02 0.000E+00 4.570E-04 NB-95 4.380E+02 2.440E+02 0.000E+00 2.410E+02 0.000E+00 1.480E+06 0.000E+00 1.310E+02 MO-99 0.000E+00 8.020E+01 0.000E+00 1.820E+02 0.000E+00 1.860E+02 0.000E+00 1.530E+01 TC-99M 5.590E-04 1.580E-03 0.000E+00 2.400E-02 7.740E-04 9.340E-01 0.000E+00 2.010E-02 TC-101 2.610E-33 3.760E-33 0.000E+00 6.770E-32 1.920E-33 1.130E-44 0.000E+00 3.690E-32 RU-103 4.350E+00 0.000E+00 0.000E+00 1.660E+01 0.000E+00 5.080E+02 0.000E+00 1.870E+00 RU-105 8.670E-03 0.000E+00 0.000E+00 1.120E-01 0.000E+00 5.300E+00 0.000E+00 3.420E-03 RU-106 6.570E+01 0.000E+00 0.000E+00 1.270E+02 0.000E+00 4.250E+03 0.000E+00 8.320E+00 AG-110M 8.790E-01 8.130E-01 0.000E+00 1.600E+00 0.000E+00 3.320E+02 0.000E+00 4.830E-01 TE-125M 2.540E+03 9.190E+02 7.630E+02 1.030E+04 0.000E+00 1.010E+04 0.000E+00 3.400E+02 TE-127 1.790E+01 6.440E+00 1.330E+01 7.300E+01 0.000E+00 1.410E+03 0.000E+00 3.880E+00 TE-127M 6.440E+03 2.300E+03 1.650E+03 2.620E+04 0.000E+00 2.160E+04 0.000E+00 7.850E+02 TE-129 1.630E-05 6.120E-06 1.250E-05 6.850E-05 0.000E+00 1.230E-05 0.000E+00 3.970E-06 TE-129M 1.080E+04 4.020E+03 3.710E+03 4.500E+04 0.000E+00 5.430E+04 0.000E+00 1.710E+03 TE-131 8.710E-17 3.640E-17 7.160E-17 3.820E-16 0.000E+00 1.230E-17 0.000E+00 2.750E-17 TE-131M 9.510E+02 4.650E+02 7.370E+02 4.710E+03 0.000E+00 4.620E+04 0.000E+00 3.880E+02 TE-132 1.950E+03 1.260E+03 1.390E+03 1.210E+04 0.000E+00 5.960E+04 0.000E+00 1.180E+03 I-130 7.050E+00 2.080E+01 1.760E+03 3.250E+01 0.000E+00 1.790E+01 0.000E+00 8.210E+00 Appendix C Ai Adult Fish - Page 2 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX C Ai Adult Dose Factors for use in the Liquid Dose Calculations Agegroup: ADULT Pathway: Fresh Water Fish - Sport (FFSP) Units: mrem/hr / Ci/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body I-131 1.370E+02 1.960E+02 6.420E+04 3.360E+02 0.000E+00 5.170E+01 0.000E+00 1.120E+02 I-132 5.270E-03 1.410E-02 4.940E-01 2.250E-02 0.000E+00 2.650E-03 0.000E+00 4.940E-03 I-133 2.290E+01 3.990E+01 5.860E+03 6.950E+01 0.000E+00 3.580E+01 0.000E+00 1.210E+01 I-134 2.120E-08 5.750E-08 9.960E-07 9.140E-08 0.000E+00 5.010E-11 0.000E+00 2.060E-08 I-135 1.290E+00 3.370E+00 2.220E+02 5.410E+00 0.000E+00 3.810E+00 0.000E+00 1.240E+00 CS-134 2.980E+05 7.080E+05 0.000E+00 2.290E+05 7.610E+04 1.240E+04 0.000E+00 5.790E+05 CS-136 2.960E+04 1.170E+05 0.000E+00 6.500E+04 8.900E+03 1.330E+04 0.000E+00 8.400E+04 CS-137 3.820E+05 5.220E+05 0.000E+00 1.770E+05 5.890E+04 1.010E+04 0.000E+00 3.420E+05 CS-138 8.940E-12 1.770E-11 0.000E+00 1.300E-11 1.280E-12 7.530E-17 0.000E+00 8.750E-12 BA-139 5.650E-06 4.030E-09 0.000E+00 3.760E-09 2.280E-09 1.000E-05 0.000E+00 1.660E-07 BA-140 1.840E+02 2.310E-01 0.000E+00 7.860E-02 1.320E-01 3.790E+02 0.000E+00 1.210E+01 BA-141 8.700E-25 6.580E-28 0.000E+00 6.120E-28 3.730E-28 4.100E-34 0.000E+00 2.940E-26 BA-142 2.570E-42 2.640E-45 0.000E+00 2.230E-45 1.490E-45 3.620E-60 0.000E+00 1.610E-43 LA-140 9.900E-02 4.990E-02 0.000E+00 0.000E+00 0.000E+00 3.660E+03 0.000E+00 1.320E-02 LA-142 2.210E-07 1.000E-07 0.000E+00 0.000E+00 0.000E+00 7.330E-04 0.000E+00 2.500E-08 CE-141 2.190E-02 1.480E-02 0.000E+00 6.890E-03 0.000E+00 5.670E+01 0.000E+00 1.680E-03 CE-143 2.380E-03 1.760E+00 0.000E+00 7.760E-04 0.000E+00 6.590E+01 0.000E+00 1.950E-04 CE-144 1.170E+00 4.870E-01 0.000E+00 2.890E-01 0.000E+00 3.940E+02 0.000E+00 6.260E-02 PR-143 5.230E-01 2.100E-01 0.000E+00 1.210E-01 0.000E+00 2.290E+03 0.000E+00 2.590E-02 PR-144 1.550E-28 6.440E-29 0.000E+00 3.630E-29 0.000E+00 2.230E-35 0.000E+00 7.880E-30 ND-147 3.530E-01 4.080E-01 0.000E+00 2.390E-01 0.000E+00 1.960E+03 0.000E+00 2.440E-02 W-187 1.470E+02 1.230E+02 0.000E+00 0.000E+00 0.000E+00 4.030E+04 0.000E+00 4.300E+01 NP-239 2.120E-02 2.090E-03 0.000E+00 6.510E-03 0.000E+00 4.280E+02 0.000E+00 1.150E-03 Appendix C Ai Adult Fish - Page 3 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX C Ai Adult Dose Factors for use in the Liquid Dose Calculations Agegroup: ADULT Pathway: Shoreline Sediment (SHDp) Units: mrem/hr / Ci/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body H-3 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 C-14 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 NA-24 4.270E-01 4.270E-01 4.270E-01 4.270E-01 4.270E-01 4.270E-01 4.960E-01 4.270E-01 P-32 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 CR-51 1.670E-01 1.670E-01 1.670E-01 1.670E-01 1.670E-01 1.670E-01 1.970E-01 1.670E-01 MN-54 4.960E+01 4.960E+01 4.960E+01 4.960E+01 4.960E+01 4.960E+01 5.820E+01 4.960E+01 MN-56 3.230E-02 3.230E-02 3.230E-02 3.230E-02 3.230E-02 3.230E-02 3.820E-02 3.230E-02 FE-55 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 FE-59 9.770E+00 9.770E+00 9.770E+00 9.770E+00 9.770E+00 9.770E+00 1.150E+01 9.770E+00 CO-58 1.360E+01 1.360E+01 1.360E+01 1.360E+01 1.360E+01 1.360E+01 1.590E+01 1.360E+01 CO-60 7.690E+02 7.690E+02 7.690E+02 7.690E+02 7.690E+02 7.690E+02 9.050E+02 7.690E+02 NI-63 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 NI-65 1.060E-02 1.060E-02 1.060E-02 1.060E-02 1.060E-02 1.060E-02 1.240E-02 1.060E-02 CU-64 2.170E-02 2.170E-02 2.170E-02 2.170E-02 2.170E-02 2.170E-02 2.460E-02 2.170E-02 ZN-65 2.670E+01 2.670E+01 2.670E+01 2.670E+01 2.670E+01 2.670E+01 3.080E+01 2.670E+01 ZN-69 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-83 1.740E-04 1.740E-04 1.740E-04 1.740E-04 1.740E-04 1.740E-04 2.530E-04 1.740E-04 BR-84 7.250E-03 7.250E-03 7.250E-03 7.250E-03 7.250E-03 7.250E-03 8.460E-03 7.250E-03 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 3.220E-01 3.220E-01 3.220E-01 3.220E-01 3.220E-01 3.220E-01 3.680E-01 3.220E-01 RB-88 1.180E-03 1.180E-03 1.180E-03 1.180E-03 1.180E-03 1.180E-03 1.350E-03 1.180E-03 RB-89 4.400E-03 4.400E-03 4.400E-03 4.400E-03 4.400E-03 4.400E-03 5.280E-03 4.400E-03 SR-89 7.740E-04 7.740E-04 7.740E-04 7.740E-04 7.740E-04 7.740E-04 8.990E-04 7.740E-04 SR-90 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 SR-91 7.690E-02 7.690E-02 7.690E-02 7.690E-02 7.690E-02 7.690E-02 8.990E-02 7.690E-02 Appendix C Ai Adult Shoreline Sediment - Page 1 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX C Ai Adult Dose Factors for use in the Liquid Dose Calculations Agegroup: ADULT Pathway: Shoreline Sediment (SHDp) Units: mrem/hr / Ci/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body SR-92 2.780E-02 2.780E-02 2.780E-02 2.780E-02 2.780E-02 2.780E-02 3.090E-02 2.780E-02 Y-90 1.610E-04 1.610E-04 1.610E-04 1.610E-04 1.610E-04 1.610E-04 1.900E-04 1.610E-04 Y-91 3.840E-02 3.840E-02 3.840E-02 3.840E-02 3.840E-02 3.840E-02 4.320E-02 3.840E-02 Y-91M 3.590E-03 3.590E-03 3.590E-03 3.590E-03 3.590E-03 3.590E-03 4.150E-03 3.590E-03 Y-92 6.460E-03 6.460E-03 6.460E-03 6.460E-03 6.460E-03 6.460E-03 7.670E-03 6.460E-03 Y-93 6.560E-03 6.560E-03 6.560E-03 6.560E-03 6.560E-03 6.560E-03 8.980E-03 6.560E-03 ZR-95 8.760E+00 8.760E+00 8.760E+00 8.760E+00 8.760E+00 8.760E+00 1.020E+01 8.760E+00 ZR-97 1.060E-01 1.060E-01 1.060E-01 1.060E-01 1.060E-01 1.060E-01 1.230E-01 1.060E-01 NB-95 4.890E+00 4.890E+00 4.890E+00 4.890E+00 4.890E+00 4.890E+00 5.750E+00 4.890E+00 MO-99 1.430E-01 1.430E-01 1.430E-01 1.430E-01 1.430E-01 1.430E-01 1.660E-01 1.430E-01 TC-99M 6.590E-03 6.590E-03 6.590E-03 6.590E-03 6.590E-03 6.590E-03 7.550E-03 6.590E-03 TC-101 7.280E-04 7.280E-04 7.280E-04 7.280E-04 7.280E-04 7.280E-04 8.090E-04 7.280E-04 RU-103 3.870E+00 3.870E+00 3.870E+00 3.870E+00 3.870E+00 3.870E+00 4.520E+00 3.870E+00 RU-105 2.280E-02 2.280E-02 2.280E-02 2.280E-02 2.280E-02 2.280E-02 2.580E-02 2.280E-02 RU-106 1.510E+01 1.510E+01 1.510E+01 1.510E+01 1.510E+01 1.510E+01 1.810E+01 1.510E+01 AG-110M 1.230E+02 1.230E+02 1.230E+02 1.230E+02 1.230E+02 1.230E+02 1.440E+02 1.230E+02 TE-125M 5.550E-02 5.550E-02 5.550E-02 5.550E-02 5.550E-02 5.550E-02 7.620E-02 5.550E-02 TE-127 1.070E-04 1.070E-04 1.070E-04 1.070E-04 1.070E-04 1.070E-04 1.170E-04 1.070E-04 TE-127M 3.280E-03 3.280E-03 3.280E-03 3.280E-03 3.280E-03 3.280E-03 3.880E-03 3.280E-03 TE-129 9.390E-04 9.390E-04 9.390E-04 9.390E-04 9.390E-04 9.390E-04 1.110E-03 9.390E-04 TE-129M 7.080E-01 7.080E-01 7.080E-01 7.080E-01 7.080E-01 7.080E-01 8.270E-01 7.080E-01 TE-131 1.040E-03 1.040E-03 1.040E-03 1.040E-03 1.040E-03 1.040E-03 1.230E+00 1.040E-03 TE-131M 2.870E-01 2.870E-01 2.870E-01 2.870E-01 2.870E-01 2.870E-01 3.390E-01 2.870E-01 TE-132 1.520E-01 1.520E-01 1.520E-01 1.520E-01 1.520E-01 1.520E-01 1.780E-01 1.520E-01 I-130 1.970E-01 1.970E-01 1.970E-01 1.970E-01 1.970E-01 1.970E-01 2.390E-01 1.970E-01 Appendix C Ai Adult Shoreline Sediment - Page 2 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX C Ai Adult Dose Factors for use in the Liquid Dose Calculations Agegroup: ADULT Pathway: Shoreline Sediment (SHDp) Units: mrem/hr / Ci/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body I-131 6.160E-01 6.160E-01 6.160E-01 6.160E-01 6.160E-01 6.160E-01 7.480E-01 6.160E-01 I-132 4.460E-02 4.460E-02 4.460E-02 4.460E-02 4.460E-02 4.460E-02 5.240E-02 4.460E-02 I-133 8.770E-02 8.770E-02 8.770E-02 8.770E-02 8.770E-02 8.770E-02 1.070E-01 8.770E-02 I-134 1.600E-02 1.600E-02 1.600E-02 1.600E-02 1.600E-02 1.600E-02 1.900E-02 1.600E-02 I-135 9.040E-02 9.040E-02 9.040E-02 9.040E-02 9.040E-02 9.040E-02 1.050E-01 9.040E-02 CS-134 2.450E+02 2.450E+02 2.450E+02 2.450E+02 2.450E+02 2.450E+02 2.860E+02 2.450E+02 CS-136 5.400E+00 5.400E+00 5.400E+00 5.400E+00 5.400E+00 5.400E+00 6.120E+00 5.400E+00 CS-137 3.680E+02 3.680E+02 3.680E+02 3.680E+02 3.680E+02 3.680E+02 4.290E+02 3.680E+02 CS-138 1.280E-02 1.280E-02 1.280E-02 1.280E-02 1.280E-02 1.280E-02 1.470E-02 1.280E-02 BA-139 3.790E-03 3.790E-03 3.790E-03 3.790E-03 3.790E-03 3.790E-03 4.260E-03 3.790E-03 BA-140 7.350E-01 7.350E-01 7.350E-01 7.350E-01 7.350E-01 7.350E-01 8.400E-01 7.350E-01 BA-141 1.490E-03 1.490E-03 1.490E-03 1.490E-03 1.490E-03 1.490E-03 1.700E-03 1.490E-03 BA-142 1.610E-03 1.610E-03 1.610E-03 1.610E-03 1.610E-03 1.610E-03 1.830E-03 1.610E-03 LA-140 6.880E-01 6.880E-01 6.880E-01 6.880E-01 6.880E-01 6.880E-01 7.790E-01 6.880E-01 LA-142 2.720E-02 2.720E-02 2.720E-02 2.720E-02 2.720E-02 2.720E-02 3.260E-02 2.720E-02 CE-141 4.890E-01 4.890E-01 4.890E-01 4.890E-01 4.890E-01 4.890E-01 5.510E-01 4.890E-01 CE-143 8.270E-02 8.270E-02 8.270E-02 8.270E-02 8.270E-02 8.270E-02 9.400E-02 8.270E-02 CE-144 2.490E+00 2.490E+00 2.490E+00 2.490E+00 2.490E+00 2.490E+00 2.880E+00 2.490E+00 PR-143 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 PR-144 6.570E-05 6.570E-05 6.570E-05 6.570E-05 6.570E-05 6.570E-05 7.550E-05 6.570E-05 ND-147 3.000E-01 3.000E-01 3.000E-01 3.000E-01 3.000E-01 3.000E-01 3.600E-01 3.000E-01 W-187 8.420E-02 8.420E-02 8.420E-02 8.420E-02 8.420E-02 8.420E-02 9.780E-02 8.420E-02 NP-239 6.120E-02 6.120E-02 6.120E-02 6.120E-02 6.120E-02 6.120E-02 7.090E-02 6.120E-02 Appendix C Ai Adult Shoreline Sediment - Page 3 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX D Ai Teen Factors for use in the Liquid Dose Calculations Agegroup: TEEN Pathway: Potable Water (PWtr) Units: mrem/hr / Ci/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body H-3 0.000E+00 6.160E+00 6.160E+00 6.160E+00 6.160E+00 6.160E+00 0.000E+00 6.160E+00 C-14 2.360E+02 4.720E+01 4.720E+01 4.720E+01 4.720E+01 4.720E+01 0.000E+00 4.720E+01 NA-24 7.690E+01 7.690E+01 7.690E+01 7.690E+01 7.690E+01 7.690E+01 0.000E+00 7.690E+01 P-32 1.570E+04 9.700E+02 0.000E+00 0.000E+00 0.000E+00 1.320E+03 0.000E+00 6.070E+02 CR-51 0.000E+00 0.000E+00 1.150E-01 4.530E-02 2.950E-01 3.470E+01 0.000E+00 2.070E-01 MN-54 0.000E+00 3.430E+02 0.000E+00 1.020E+02 0.000E+00 7.030E+02 0.000E+00 6.790E+01 MN-56 0.000E+00 3.640E-01 0.000E+00 4.610E-01 0.000E+00 2.400E+01 0.000E+00 6.480E-02 FE-55 2.200E+02 1.560E+02 0.000E+00 0.000E+00 9.880E+01 6.740E+01 0.000E+00 3.630E+01 FE-59 3.390E+02 7.900E+02 0.000E+00 0.000E+00 2.490E+02 1.870E+03 0.000E+00 3.050E+02 CO-58 0.000E+00 5.620E+01 0.000E+00 0.000E+00 0.000E+00 7.750E+02 0.000E+00 1.300E+02 CO-60 0.000E+00 1.630E+02 0.000E+00 0.000E+00 0.000E+00 2.130E+03 0.000E+00 3.680E+02 NI-63 1.030E+04 7.270E+02 0.000E+00 0.000E+00 0.000E+00 1.160E+02 0.000E+00 3.490E+02 NI-65 1.610E+00 2.050E-01 0.000E+00 0.000E+00 0.000E+00 1.110E+01 0.000E+00 9.350E-02 CU-64 0.000E+00 3.470E+00 0.000E+00 8.770E+00 0.000E+00 2.690E+02 0.000E+00 1.630E+00 ZN-65 3.340E+02 1.160E+03 0.000E+00 7.430E+02 0.000E+00 4.920E+02 0.000E+00 5.420E+02 ZN-69 1.070E-04 2.040E-04 0.000E+00 1.330E-04 0.000E+00 3.760E-04 0.000E+00 1.430E-05 BR-83 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.030E-01 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 6.500E-07 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4.360E-77 RB-86 0.000E+00 1.700E+03 0.000E+00 0.000E+00 0.000E+00 2.520E+02 0.000E+00 7.990E+02 RB-88 0.000E+00 3.300E-12 0.000E+00 0.000E+00 0.000E+00 2.830E-19 0.000E+00 1.760E-12 RB-89 0.000E+00 2.960E-14 0.000E+00 0.000E+00 0.000E+00 4.540E-23 0.000E+00 2.090E-14 SR-89 2.540E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.030E+03 0.000E+00 7.280E+02 SR-90 4.830E+05 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.350E+04 0.000E+00 1.190E+05 SR-91 1.950E+02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 8.850E+02 0.000E+00 7.760E+00 Appendix D Ai Teen Water - Page 1 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX D Ai Teen Factors for use in the Liquid Dose Calculations Agegroup: TEEN Pathway: Potable Water (PWtr) Units: mrem/hr / Ci/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body SR-92 8.220E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.090E+02 0.000E+00 3.500E-01 Y-90 7.000E-01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.770E+03 0.000E+00 1.880E-02 Y-91 1.160E+01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4.760E+03 0.000E+00 3.120E-01 Y-91M 3.330E-07 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.570E-05 0.000E+00 1.270E-08 Y-92 6.710E-03 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.840E+02 0.000E+00 1.940E-04 Y-93 9.760E-02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.980E+03 0.000E+00 2.670E-03 ZR-95 2.380E+00 7.520E-01 0.000E+00 1.100E+00 0.000E+00 1.730E+03 0.000E+00 5.170E-01 ZR-97 8.420E-02 1.670E-02 0.000E+00 2.530E-02 0.000E+00 4.510E+03 0.000E+00 7.670E-03 NB-95 4.730E-01 2.630E-01 0.000E+00 2.540E-01 0.000E+00 1.120E+03 0.000E+00 1.440E-01 MO-99 0.000E+00 3.090E+02 0.000E+00 7.070E+02 0.000E+00 5.530E+02 0.000E+00 5.890E+01 TC-99M 4.840E-03 1.350E-02 0.000E+00 2.010E-01 7.500E-03 8.870E+00 0.000E+00 1.750E-01 TC-101 1.120E-17 1.590E-17 0.000E+00 2.880E-16 9.700E-18 2.720E-24 0.000E+00 1.560E-16 RU-103 1.470E+01 0.000E+00 0.000E+00 5.180E+01 0.000E+00 1.230E+03 0.000E+00 6.280E+00 RU-105 1.940E-01 0.000E+00 0.000E+00 2.450E+00 0.000E+00 1.570E+02 0.000E+00 7.540E-02 RU-106 2.280E+02 0.000E+00 0.000E+00 4.390E+02 0.000E+00 1.090E+04 0.000E+00 2.870E+01 AG-110M 1.190E+01 1.130E+01 0.000E+00 2.150E+01 0.000E+00 3.160E+03 0.000E+00 6.850E+00 TE-125M 2.210E+02 7.980E+01 6.180E+01 0.000E+00 0.000E+00 6.530E+02 0.000E+00 2.960E+01 TE-127 3.790E+00 1.340E+00 2.610E+00 1.530E+01 0.000E+00 2.930E+02 0.000E+00 8.150E-01 TE-127M 5.600E+02 1.990E+02 1.330E+02 2.270E+03 0.000E+00 1.400E+03 0.000E+00 6.660E+01 TE-129 1.920E-03 7.150E-04 1.370E-03 8.040E-03 0.000E+00 1.050E-02 0.000E+00 4.660E-04 TE-129M 9.380E+02 3.480E+02 3.030E+02 3.920E+03 0.000E+00 3.520E+03 0.000E+00 1.480E+02 TE-131 3.490E-09 1.440E-09 2.690E-09 1.520E-08 0.000E+00 2.860E-10 0.000E+00 1.090E-09 TE-131M 1.080E+02 5.150E+01 7.750E+01 5.380E+02 0.000E+00 4.140E+03 0.000E+00 4.300E+01 TE-132 1.820E+02 1.150E+02 1.220E+02 1.110E+03 0.000E+00 3.660E+03 0.000E+00 1.090E+02 I-130 3.050E+01 8.830E+01 7.200E+03 1.360E+02 0.000E+00 6.790E+01 0.000E+00 3.530E+01 Appendix D Ai Teen Water - Page 2 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX D Ai Teen Factors for use in the Liquid Dose Calculations Agegroup: TEEN Pathway: Potable Water (PWtr) Units: mrem/hr / Ci/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body I-131 3.260E+02 4.560E+02 1.330E+05 7.850E+02 0.000E+00 9.020E+01 0.000E+00 2.450E+02 I-132 4.360E-01 1.140E+00 3.850E+01 1.800E+00 0.000E+00 4.970E-01 0.000E+00 4.100E-01 I-133 7.830E+01 1.330E+02 1.860E+04 2.330E+02 0.000E+00 1.010E+02 0.000E+00 4.050E+01 I-134 6.330E-04 1.680E-03 2.800E-02 2.640E-03 0.000E+00 2.210E-05 0.000E+00 6.020E-04 I-135 1.010E+01 2.600E+01 1.670E+03 4.100E+01 0.000E+00 2.880E+01 0.000E+00 9.630E+00 CS-134 4.860E+03 1.140E+04 0.000E+00 3.640E+03 1.390E+03 1.420E+02 0.000E+00 5.310E+03 CS-136 4.860E+02 1.910E+03 0.000E+00 1.040E+03 1.640E+02 1.540E+02 0.000E+00 1.290E+03 CS-137 6.510E+03 8.660E+03 0.000E+00 2.950E+03 1.150E+03 1.230E+02 0.000E+00 3.020E+03 CS-138 8.300E-07 1.590E-06 0.000E+00 1.180E-06 1.370E-07 7.230E-10 0.000E+00 7.970E-07 BA-139 1.990E-02 1.400E-05 0.000E+00 1.320E-05 9.670E-06 1.780E-01 0.000E+00 5.810E-04 BA-140 1.610E+03 1.970E+00 0.000E+00 6.680E-01 1.320E+00 2.480E+03 0.000E+00 1.040E+02 BA-141 5.420E-12 4.050E-15 0.000E+00 3.760E-15 2.770E-15 1.150E-17 0.000E+00 1.810E-13 BA-142 6.170E-21 6.170E-24 0.000E+00 5.220E-24 4.100E-24 1.890E-32 0.000E+00 3.800E-22 LA-140 1.650E-01 8.090E-02 0.000E+00 0.000E+00 0.000E+00 4.640E+03 0.000E+00 2.150E-02 LA-142 5.590E-05 2.480E-05 0.000E+00 0.000E+00 0.000E+00 7.550E-01 0.000E+00 6.180E-06 CE-141 7.650E-01 5.110E-01 0.000E+00 2.400E-01 0.000E+00 1.460E+03 0.000E+00 5.870E-02 CE-143 1.060E-01 7.730E+01 0.000E+00 3.460E-02 0.000E+00 2.320E+03 0.000E+00 8.630E-03 CE-144 4.040E+01 1.670E+01 0.000E+00 9.990E+00 0.000E+00 1.020E+04 0.000E+00 2.170E+00 PR-143 7.420E-01 2.960E-01 0.000E+00 1.720E-01 0.000E+00 2.440E+03 0.000E+00 3.700E-02 PR-144 7.330E-16 3.000E-16 0.000E+00 1.720E-16 0.000E+00 8.080E-19 0.000E+00 3.720E-17 ND-147 5.280E-01 5.750E-01 0.000E+00 3.370E-01 0.000E+00 2.070E+03 0.000E+00 3.440E-02 W-187 5.990E+00 4.880E+00 0.000E+00 0.000E+00 0.000E+00 1.320E+03 0.000E+00 1.710E+00 NP-239 8.830E-02 8.330E-03 0.000E+00 2.610E-02 0.000E+00 1.340E+03 0.000E+00 4.630E-03 Appendix D Ai Teen Water - Page 3 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX D Ai Teen Dose Factors for use in the Liquid Dose Calculations Agegroup: TEEN Pathway: Fresh Water Fish - Sport (FFSP) Units: mrem/hr / Ci/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body H-3 0.000E+00 1.740E-01 1.740E-01 1.740E-01 1.740E-01 1.740E-01 0.000E+00 1.740E-01 C-14 3.410E+04 6.810E+03 6.810E+03 6.810E+03 6.810E+03 6.810E+03 0.000E+00 6.810E+03 NA-24 1.390E+02 1.390E+02 1.390E+02 1.390E+02 1.390E+02 1.390E+02 0.000E+00 1.390E+02 P-32 1.440E+06 8.910E+04 0.000E+00 0.000E+00 0.000E+00 1.210E+05 0.000E+00 5.580E+04 CR-51 0.000E+00 0.000E+00 7.120E-01 2.810E-01 1.830E+00 2.150E+02 0.000E+00 1.280E+00 MN-54 0.000E+00 4.300E+03 0.000E+00 1.280E+03 0.000E+00 8.810E+03 0.000E+00 8.520E+02 MN-56 0.000E+00 1.810E-01 0.000E+00 2.300E-01 0.000E+00 1.190E+01 0.000E+00 3.230E-02 FE-55 6.890E+02 4.880E+02 0.000E+00 0.000E+00 3.100E+02 2.110E+02 0.000E+00 1.140E+02 FE-59 1.050E+03 2.460E+03 0.000E+00 0.000E+00 7.760E+02 5.820E+03 0.000E+00 9.500E+02 CO-58 0.000E+00 8.780E+01 0.000E+00 0.000E+00 0.000E+00 1.210E+03 0.000E+00 2.020E+02 CO-60 0.000E+00 2.560E+02 0.000E+00 0.000E+00 0.000E+00 3.340E+03 0.000E+00 5.770E+02 NI-63 3.230E+04 2.280E+03 0.000E+00 0.000E+00 0.000E+00 3.630E+02 0.000E+00 1.090E+03 NI-65 1.860E-01 2.370E-02 0.000E+00 0.000E+00 0.000E+00 1.290E+00 0.000E+00 1.080E-02 CU-64 0.000E+00 2.820E+00 0.000E+00 7.140E+00 0.000E+00 2.190E+02 0.000E+00 1.330E+00 ZN-65 2.100E+04 7.280E+04 0.000E+00 4.660E+04 0.000E+00 3.080E+04 0.000E+00 3.390E+04 ZN-69 8.410E-07 1.600E-06 0.000E+00 1.050E-06 0.000E+00 2.950E-06 0.000E+00 1.120E-07 BR-83 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4.160E-02 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.320E-12 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 0.000E+00 1.050E+05 0.000E+00 0.000E+00 0.000E+00 1.550E+04 0.000E+00 4.920E+04 RB-88 0.000E+00 1.380E-22 0.000E+00 0.000E+00 0.000E+00 1.180E-29 0.000E+00 7.360E-23 RB-89 0.000E+00 1.720E-26 0.000E+00 0.000E+00 0.000E+00 2.630E-35 0.000E+00 1.220E-26 SR-89 2.370E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.830E+03 0.000E+00 6.800E+02 SR-90 4.540E+05 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.270E+04 0.000E+00 1.120E+05 SR-91 7.640E+01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.470E+02 0.000E+00 3.040E+00 Appendix D Ai Teen Fish - Page 1 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX D Ai Teen Dose Factors for use in the Liquid Dose Calculations Agegroup: TEEN Pathway: Fresh Water Fish - Sport (FFSP) Units: mrem/hr / Ci/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body SR-92 3.590E-01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 9.130E+00 0.000E+00 1.530E-02 Y-90 4.820E-01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.980E+03 0.000E+00 1.300E-02 Y-91 9.060E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.710E+03 0.000E+00 2.430E-01 Y-91M 1.160E-11 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.470E-10 0.000E+00 4.430E-13 Y-92 5.020E-04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.380E+01 0.000E+00 1.450E-05 Y-93 3.350E-02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.020E+03 0.000E+00 9.190E-04 ZR-95 2.450E-01 7.740E-02 0.000E+00 1.140E-01 0.000E+00 1.790E+02 0.000E+00 5.320E-02 ZR-97 5.330E-03 1.050E-03 0.000E+00 1.600E-03 0.000E+00 2.850E+02 0.000E+00 4.860E-04 NB-95 4.410E+02 2.450E+02 0.000E+00 2.370E+02 0.000E+00 1.050E+06 0.000E+00 1.350E+02 MO-99 0.000E+00 8.550E+01 0.000E+00 1.960E+02 0.000E+00 1.530E+02 0.000E+00 1.630E+01 TC-99M 5.720E-04 1.600E-03 0.000E+00 2.380E-02 8.860E-04 1.050E+00 0.000E+00 2.070E-02 TC-101 2.820E-33 4.010E-33 0.000E+00 7.240E-32 2.440E-33 6.840E-40 0.000E+00 3.930E-32 RU-103 4.570E+00 0.000E+00 0.000E+00 1.610E+01 0.000E+00 3.820E+02 0.000E+00 1.950E+00 RU-105 9.350E-03 0.000E+00 0.000E+00 1.180E-01 0.000E+00 7.550E+00 0.000E+00 3.630E-03 RU-106 7.140E+01 0.000E+00 0.000E+00 1.380E+02 0.000E+00 3.420E+03 0.000E+00 8.990E+00 AG-110M 8.580E-01 8.120E-01 0.000E+00 1.550E+00 0.000E+00 2.280E+02 0.000E+00 4.940E-01 TE-125M 2.760E+03 9.950E+02 7.710E+02 0.000E+00 0.000E+00 8.150E+03 0.000E+00 3.690E+02 TE-127 1.960E+01 6.950E+00 1.350E+01 7.940E+01 0.000E+00 1.510E+03 0.000E+00 4.220E+00 TE-127M 7.010E+03 2.490E+03 1.670E+03 2.840E+04 0.000E+00 1.750E+04 0.000E+00 8.340E+02 TE-129 1.770E-05 6.600E-06 1.260E-05 7.430E-05 0.000E+00 9.680E-05 0.000E+00 4.310E-06 TE-129M 1.160E+04 4.320E+03 3.760E+03 4.870E+04 0.000E+00 4.370E+04 0.000E+00 1.840E+03 TE-131 9.400E-17 3.870E-17 7.240E-17 4.110E-16 0.000E+00 7.710E-18 0.000E+00 2.940E-17 TE-131M 1.020E+03 4.900E+02 7.370E+02 5.110E+03 0.000E+00 3.930E+04 0.000E+00 4.090E+02 TE-132 2.060E+03 1.300E+03 1.370E+03 1.250E+04 0.000E+00 4.130E+04 0.000E+00 1.230E+03 I-130 7.320E+00 2.120E+01 1.730E+03 3.260E+01 0.000E+00 1.630E+01 0.000E+00 8.460E+00 Appendix D Ai Teen Fish - Page 2 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX D Ai Teen Dose Factors for use in the Liquid Dose Calculations Agegroup: TEEN Pathway: Fresh Water Fish - Sport (FFSP) Units: mrem/hr / Ci/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body I-131 1.470E+02 2.060E+02 6.000E+04 3.540E+02 0.000E+00 4.070E+01 0.000E+00 1.100E+02 I-132 5.520E-03 1.440E-02 4.870E-01 2.280E-02 0.000E+00 6.290E-03 0.000E+00 5.180E-03 I-133 2.470E+01 4.190E+01 5.850E+03 7.350E+01 0.000E+00 3.170E+01 0.000E+00 1.280E+01 I-134 2.220E-08 5.890E-08 9.810E-07 9.280E-08 0.000E+00 7.760E-10 0.000E+00 2.110E-08 I-135 1.350E+00 3.480E+00 2.240E+02 5.490E+00 0.000E+00 3.850E+00 0.000E+00 1.290E+00 CS-134 3.050E+05 7.180E+05 0.000E+00 2.280E+05 8.710E+04 8.930E+03 0.000E+00 3.330E+05 CS-136 2.970E+04 1.170E+05 0.000E+00 6.370E+04 1.000E+04 9.410E+03 0.000E+00 7.860E+04 CS-137 4.090E+05 5.440E+05 0.000E+00 1.850E+05 7.190E+04 7.730E+03 0.000E+00 1.890E+05 CS-138 9.580E-12 1.840E-11 0.000E+00 1.360E-11 1.580E-12 8.340E-15 0.000E+00 9.190E-12 BA-139 6.170E-06 4.340E-09 0.000E+00 4.090E-09 2.990E-09 5.510E-05 0.000E+00 1.800E-07 BA-140 1.960E+02 2.410E-01 0.000E+00 8.160E-02 1.620E-01 3.030E+02 0.000E+00 1.260E+01 BA-141 9.450E-25 7.050E-28 0.000E+00 6.550E-28 4.830E-28 2.010E-30 0.000E+00 3.150E-26 BA-142 2.750E-42 2.750E-45 0.000E+00 2.320E-45 1.830E-45 8.430E-54 0.000E+00 1.690E-43 LA-140 1.050E-01 5.160E-02 0.000E+00 0.000E+00 0.000E+00 2.960E+03 0.000E+00 1.370E-02 LA-142 2.350E-07 1.040E-07 0.000E+00 0.000E+00 0.000E+00 3.180E-03 0.000E+00 2.600E-08 CE-141 2.370E-02 1.590E-02 0.000E+00 7.460E-03 0.000E+00 4.540E+01 0.000E+00 1.820E-03 CE-143 2.590E-03 1.880E+00 0.000E+00 8.450E-04 0.000E+00 5.660E+01 0.000E+00 2.100E-04 CE-144 1.270E+00 5.240E-01 0.000E+00 3.130E-01 0.000E+00 3.180E+02 0.000E+00 6.810E-02 PR-143 5.680E-01 2.270E-01 0.000E+00 1.320E-01 0.000E+00 1.870E+03 0.000E+00 2.830E-02 PR-144 1.690E-28 6.900E-29 0.000E+00 3.960E-29 0.000E+00 1.860E-31 0.000E+00 8.550E-30 ND-147 4.020E-01 4.370E-01 0.000E+00 2.560E-01 0.000E+00 1.580E+03 0.000E+00 2.620E-02 W-187 1.590E+02 1.300E+02 0.000E+00 0.000E+00 0.000E+00 3.510E+04 0.000E+00 4.540E+01 NP-239 2.390E-02 2.260E-03 0.000E+00 7.080E-03 0.000E+00 3.630E+02 0.000E+00 1.250E-03 Appendix D Ai Teen Fish - Page 3 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX D Ai Teen Dose Factors for use in the Liquid Dose Calculations Agegroup: TEEN Pathway: Shoreline Sediment (SHDp) Units: mrem/hr / Ci/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body H-3 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 C-14 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 NA-24 2.390E+00 2.390E+00 2.390E+00 2.390E+00 2.390E+00 2.390E+00 2.770E+00 2.390E+00 P-32 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 CR-51 9.310E-01 9.310E-01 9.310E-01 9.310E-01 9.310E-01 9.310E-01 1.100E+00 9.310E-01 MN-54 2.770E+02 2.770E+02 2.770E+02 2.770E+02 2.770E+02 2.770E+02 3.250E+02 2.770E+02 MN-56 1.800E-01 1.800E-01 1.800E-01 1.800E-01 1.800E-01 1.800E-01 2.130E-01 1.800E-01 FE-55 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 FE-59 5.450E+01 5.450E+01 5.450E+01 5.450E+01 5.450E+01 5.450E+01 6.410E+01 5.450E+01 CO-58 7.570E+01 7.570E+01 7.570E+01 7.570E+01 7.570E+01 7.570E+01 8.870E+01 7.570E+01 CO-60 4.300E+03 4.300E+03 4.300E+03 4.300E+03 4.300E+03 4.300E+03 5.050E+03 4.300E+03 NI-63 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 NI-65 5.930E-02 5.930E-02 5.930E-02 5.930E-02 5.930E-02 5.930E-02 6.900E-02 5.930E-02 CU-64 1.210E-01 1.210E-01 1.210E-01 1.210E-01 1.210E-01 1.210E-01 1.370E-01 1.210E-01 ZN-65 1.490E+02 1.490E+02 1.490E+02 1.490E+02 1.490E+02 1.490E+02 1.720E+02 1.490E+02 ZN-69 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-83 9.730E-04 9.730E-04 9.730E-04 9.730E-04 9.730E-04 9.730E-04 1.410E-03 9.730E-04 BR-84 4.050E-02 4.050E-02 4.050E-02 4.050E-02 4.050E-02 4.050E-02 4.720E-02 4.050E-02 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 1.800E+00 1.800E+00 1.800E+00 1.800E+00 1.800E+00 1.800E+00 2.050E+00 1.800E+00 RB-88 6.610E-03 6.610E-03 6.610E-03 6.610E-03 6.610E-03 6.610E-03 7.550E-03 6.610E-03 RB-89 2.460E-02 2.460E-02 2.460E-02 2.460E-02 2.460E-02 2.460E-02 2.950E-02 2.460E-02 SR-89 4.320E-03 4.320E-03 4.320E-03 4.320E-03 4.320E-03 4.320E-03 5.020E-03 4.320E-03 SR-90 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 SR-91 4.290E-01 4.290E-01 4.290E-01 4.290E-01 4.290E-01 4.290E-01 5.020E-01 4.290E-01 Appendix D Ai Teen Shoreline Sediment - Page 1 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX D Ai Teen Dose Factors for use in the Liquid Dose Calculations Agegroup: TEEN Pathway: Shoreline Sediment (SHDp) Units: mrem/hr / Ci/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body SR-92 1.550E-01 1.550E-01 1.550E-01 1.550E-01 1.550E-01 1.550E-01 1.720E-01 1.550E-01 Y-90 8.970E-04 8.970E-04 8.970E-04 8.970E-04 8.970E-04 8.970E-04 1.060E-03 8.970E-04 Y-91 2.140E-01 2.140E-01 2.140E-01 2.140E-01 2.140E-01 2.140E-01 2.410E-01 2.140E-01 Y-91M 2.000E-02 2.000E-02 2.000E-02 2.000E-02 2.000E-02 2.000E-02 2.320E-02 2.000E-02 Y-92 3.600E-02 3.600E-02 3.600E-02 3.600E-02 3.600E-02 3.600E-02 4.280E-02 3.600E-02 Y-93 3.660E-02 3.660E-02 3.660E-02 3.660E-02 3.660E-02 3.660E-02 5.010E-02 3.660E-02 ZR-95 4.890E+01 4.890E+01 4.890E+01 4.890E+01 4.890E+01 4.890E+01 5.670E+01 4.890E+01 ZR-97 5.910E-01 5.910E-01 5.910E-01 5.910E-01 5.910E-01 5.910E-01 6.880E-01 5.910E-01 NB-95 2.730E+01 2.730E+01 2.730E+01 2.730E+01 2.730E+01 2.730E+01 3.210E+01 2.730E+01 MO-99 7.980E-01 7.980E-01 7.980E-01 7.980E-01 7.980E-01 7.980E-01 9.240E-01 7.980E-01 TC-99M 3.680E-02 3.680E-02 3.680E-02 3.680E-02 3.680E-02 3.680E-02 4.210E-02 3.680E-02 TC-101 4.070E-03 4.070E-03 4.070E-03 4.070E-03 4.070E-03 4.070E-03 4.520E-03 4.070E-03 RU-103 2.160E+01 2.160E+01 2.160E+01 2.160E+01 2.160E+01 2.160E+01 2.520E+01 2.160E+01 RU-105 1.270E-01 1.270E-01 1.270E-01 1.270E-01 1.270E-01 1.270E-01 1.440E-01 1.270E-01 RU-106 8.430E+01 8.430E+01 8.430E+01 8.430E+01 8.430E+01 8.430E+01 1.010E+02 8.430E+01 AG-110M 6.870E+02 6.870E+02 6.870E+02 6.870E+02 6.870E+02 6.870E+02 8.010E+02 6.870E+02 TE-125M 3.100E-01 3.100E-01 3.100E-01 3.100E-01 3.100E-01 3.100E-01 4.250E-01 3.100E-01 TE-127 5.950E-04 5.950E-04 5.950E-04 5.950E-04 5.950E-04 5.950E-04 6.540E-04 5.950E-04 TE-127M 1.830E-02 1.830E-02 1.830E-02 1.830E-02 1.830E-02 1.830E-02 2.160E-02 1.830E-02 TE-129 5.240E-03 5.240E-03 5.240E-03 5.240E-03 5.240E-03 5.240E-03 6.200E-03 5.240E-03 TE-129M 3.950E+00 3.950E+00 3.950E+00 3.950E+00 3.950E+00 3.950E+00 4.620E+00 3.950E+00 TE-131 5.830E-03 5.830E-03 5.830E-03 5.830E-03 5.830E-03 5.830E-03 6.890E+00 5.830E-03 TE-131M 1.600E+00 1.600E+00 1.600E+00 1.600E+00 1.600E+00 1.600E+00 1.890E+00 1.600E+00 TE-132 8.460E-01 8.460E-01 8.460E-01 8.460E-01 8.460E-01 8.460E-01 9.950E-01 8.460E-01 I-130 1.100E+00 1.100E+00 1.100E+00 1.100E+00 1.100E+00 1.100E+00 1.340E+00 1.100E+00 Appendix D Ai Teen Shoreline Sediment - Page 2 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX D Ai Teen Dose Factors for use in the Liquid Dose Calculations Agegroup: TEEN Pathway: Shoreline Sediment (SHDp) Units: mrem/hr / Ci/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body I-131 3.440E+00 3.440E+00 3.440E+00 3.440E+00 3.440E+00 3.440E+00 4.170E+00 3.440E+00 I-132 2.490E-01 2.490E-01 2.490E-01 2.490E-01 2.490E-01 2.490E-01 2.930E-01 2.490E-01 I-133 4.900E-01 4.900E-01 4.900E-01 4.900E-01 4.900E-01 4.900E-01 5.960E-01 4.900E-01 I-134 8.930E-02 8.930E-02 8.930E-02 8.930E-02 8.930E-02 8.930E-02 1.060E-01 8.930E-02 I-135 5.050E-01 5.050E-01 5.050E-01 5.050E-01 5.050E-01 5.050E-01 5.890E-01 5.050E-01 CS-134 1.370E+03 1.370E+03 1.370E+03 1.370E+03 1.370E+03 1.370E+03 1.600E+03 1.370E+03 CS-136 3.010E+01 3.010E+01 3.010E+01 3.010E+01 3.010E+01 3.010E+01 3.420E+01 3.010E+01 CS-137 2.050E+03 2.050E+03 2.050E+03 2.050E+03 2.050E+03 2.050E+03 2.400E+03 2.050E+03 CS-138 7.170E-02 7.170E-02 7.170E-02 7.170E-02 7.170E-02 7.170E-02 8.200E-02 7.170E-02 BA-139 2.120E-02 2.120E-02 2.120E-02 2.120E-02 2.120E-02 2.120E-02 2.380E-02 2.120E-02 BA-140 4.100E+00 4.100E+00 4.100E+00 4.100E+00 4.100E+00 4.100E+00 4.690E+00 4.100E+00 BA-141 8.330E-03 8.330E-03 8.330E-03 8.330E-03 8.330E-03 8.330E-03 9.490E-03 8.330E-03 BA-142 8.970E-03 8.970E-03 8.970E-03 8.970E-03 8.970E-03 8.970E-03 1.020E-02 8.970E-03 LA-140 3.840E+00 3.840E+00 3.840E+00 3.840E+00 3.840E+00 3.840E+00 4.350E+00 3.840E+00 LA-142 1.520E-01 1.520E-01 1.520E-01 1.520E-01 1.520E-01 1.520E-01 1.820E-01 1.520E-01 CE-141 2.730E+00 2.730E+00 2.730E+00 2.730E+00 2.730E+00 2.730E+00 3.080E+00 2.730E+00 CE-143 4.620E-01 4.620E-01 4.620E-01 4.620E-01 4.620E-01 4.620E-01 5.250E-01 4.620E-01 CE-144 1.390E+01 1.390E+01 1.390E+01 1.390E+01 1.390E+01 1.390E+01 1.610E+01 1.390E+01 PR-143 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 PR-144 3.670E-04 3.670E-04 3.670E-04 3.670E-04 3.670E-04 3.670E-04 4.220E-04 3.670E-04 ND-147 1.680E+00 1.680E+00 1.680E+00 1.680E+00 1.680E+00 1.680E+00 2.010E+00 1.680E+00 W-187 4.700E-01 4.700E-01 4.700E-01 4.700E-01 4.700E-01 4.700E-01 5.460E-01 4.700E-01 NP-239 3.420E-01 3.420E-01 3.420E-01 3.420E-01 3.420E-01 3.420E-01 3.960E-01 3.420E-01 Appendix D Ai Teen Shoreline Sediment - Page 3 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX E Ai Child Dose Factors for use in the Liquid Dose Calculations Agegroup: CHILD Pathway: Potable Water (PWtr) Units: mrem/hr / Ci/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body H-3 0.000E+00 1.180E+01 1.180E+01 1.180E+01 1.180E+01 1.180E+01 0.000E+00 1.180E+01 C-14 7.030E+02 1.410E+02 1.410E+02 1.410E+02 1.410E+02 1.410E+02 0.000E+00 1.410E+02 NA-24 1.940E+02 1.940E+02 1.940E+02 1.940E+02 1.940E+02 1.940E+02 0.000E+00 1.940E+02 P-32 4.680E+04 2.190E+03 0.000E+00 0.000E+00 0.000E+00 1.290E+03 0.000E+00 1.800E+03 CR-51 0.000E+00 0.000E+00 2.840E-01 7.750E-02 5.180E-01 2.710E+01 0.000E+00 5.110E-01 MN-54 0.000E+00 6.210E+02 0.000E+00 1.740E+02 0.000E+00 5.220E+02 0.000E+00 1.660E+02 MN-56 0.000E+00 7.700E-01 0.000E+00 9.320E-01 0.000E+00 1.120E+02 0.000E+00 1.740E-01 FE-55 6.680E+02 3.550E+02 0.000E+00 0.000E+00 2.010E+02 6.570E+01 0.000E+00 1.100E+02 FE-59 9.520E+02 1.540E+03 0.000E+00 0.000E+00 4.470E+02 1.600E+03 0.000E+00 7.670E+02 CO-58 0.000E+00 1.040E+02 0.000E+00 0.000E+00 0.000E+00 6.070E+02 0.000E+00 3.190E+02 CO-60 0.000E+00 3.080E+02 0.000E+00 0.000E+00 0.000E+00 1.700E+03 0.000E+00 9.070E+02 NI-63 3.130E+04 1.670E+03 0.000E+00 0.000E+00 0.000E+00 1.130E+02 0.000E+00 1.060E+03 NI-65 4.760E+00 4.480E-01 0.000E+00 0.000E+00 0.000E+00 5.490E+01 0.000E+00 2.610E-01 CU-64 0.000E+00 7.390E+00 0.000E+00 1.780E+01 0.000E+00 3.470E+02 0.000E+00 4.460E+00 ZN-65 7.950E+02 2.120E+03 0.000E+00 1.340E+03 0.000E+00 3.720E+02 0.000E+00 1.320E+03 ZN-69 3.190E-04 4.610E-04 0.000E+00 2.800E-04 0.000E+00 2.900E-02 0.000E+00 4.260E-05 BR-83 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.060E-01 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.780E-06 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.300E-76 RB-86 0.000E+00 3.820E+03 0.000E+00 0.000E+00 0.000E+00 2.460E+02 0.000E+00 2.350E+03 RB-88 0.000E+00 7.360E-12 0.000E+00 0.000E+00 0.000E+00 3.610E-13 0.000E+00 5.110E-12 RB-89 0.000E+00 6.300E-14 0.000E+00 0.000E+00 0.000E+00 5.490E-16 0.000E+00 5.600E-14 SR-89 7.620E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.950E+03 0.000E+00 2.180E+03 SR-90 9.880E+05 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.330E+04 0.000E+00 2.510E+05 SR-91 5.810E+02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.280E+03 0.000E+00 2.190E+01 Appendix E Ai Child Water - Page 1 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX E Ai Child Dose Factors for use in the Liquid Dose Calculations Agegroup: CHILD Pathway: Potable Water (PWtr) Units: mrem/hr / Ci/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body SR-92 2.430E+01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4.610E+02 0.000E+00 9.760E-01 Y-90 2.100E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.980E+03 0.000E+00 5.620E-02 Y-91 3.480E+01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4.640E+03 0.000E+00 9.310E-01 Y-91M 9.860E-07 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.930E-03 0.000E+00 3.590E-08 Y-92 2.000E-02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.770E+02 0.000E+00 5.710E-04 Y-93 2.900E-01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4.330E+03 0.000E+00 7.970E-03 ZR-95 6.710E+00 1.470E+00 0.000E+00 2.110E+00 0.000E+00 1.540E+03 0.000E+00 1.310E+00 ZR-97 2.480E-01 3.590E-02 0.000E+00 5.150E-02 0.000E+00 5.440E+03 0.000E+00 2.120E-02 NB-95 1.300E+00 5.040E-01 0.000E+00 4.740E-01 0.000E+00 9.330E+02 0.000E+00 3.600E-01 MO-99 0.000E+00 6.820E+02 0.000E+00 1.460E+03 0.000E+00 5.640E+02 0.000E+00 1.690E+02 TC-99M 1.350E-02 2.640E-02 0.000E+00 3.840E-01 1.340E-02 1.500E+01 0.000E+00 4.380E-01 TC-101 3.330E-17 3.480E-17 0.000E+00 5.940E-16 1.840E-17 1.110E-16 0.000E+00 4.410E-16 RU-103 4.210E+01 0.000E+00 0.000E+00 1.060E+02 0.000E+00 1.090E+03 0.000E+00 1.620E+01 RU-105 5.750E-01 0.000E+00 0.000E+00 5.060E+00 0.000E+00 3.750E+02 0.000E+00 2.090E-01 RU-106 6.800E+02 0.000E+00 0.000E+00 9.180E+02 0.000E+00 1.060E+04 0.000E+00 8.480E+01 AG-110M 3.130E+01 2.110E+01 0.000E+00 3.940E+01 0.000E+00 2.510E+03 0.000E+00 1.690E+01 TE-125M 6.590E+02 1.790E+02 1.850E+02 0.000E+00 0.000E+00 6.360E+02 0.000E+00 8.780E+01 TE-127 1.130E+01 3.050E+00 7.820E+00 3.210E+01 0.000E+00 4.410E+02 0.000E+00 2.420E+00 TE-127M 1.670E+03 4.510E+02 4.000E+02 4.780E+03 0.000E+00 1.360E+03 0.000E+00 1.990E+02 TE-129 5.730E-03 1.600E-03 4.090E-03 1.680E-02 0.000E+00 3.570E-01 0.000E+00 1.360E-03 TE-129M 2.800E+03 7.830E+02 9.030E+02 8.230E+03 0.000E+00 3.420E+03 0.000E+00 4.350E+02 TE-131 1.040E-08 3.160E-09 7.930E-09 3.140E-08 0.000E+00 5.450E-08 0.000E+00 3.090E-09 TE-131M 3.170E+02 1.100E+02 2.260E+02 1.060E+03 0.000E+00 4.450E+03 0.000E+00 1.170E+02 TE-132 5.280E+02 2.340E+02 3.400E+02 2.170E+03 0.000E+00 2.350E+03 0.000E+00 2.820E+02 I-130 8.650E+01 1.750E+02 1.930E+04 2.610E+02 0.000E+00 8.180E+01 0.000E+00 9.010E+01 Appendix E Ai Child Water - Page 2 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX E Ai Child Dose Factors for use in the Liquid Dose Calculations Agegroup: CHILD Pathway: Potable Water (PWtr) Units: mrem/hr / Ci/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body I-131 9.580E+02 9.630E+02 3.190E+05 1.580E+03 0.000E+00 8.580E+01 0.000E+00 5.470E+02 I-132 1.250E+00 2.300E+00 1.070E+02 3.520E+00 0.000E+00 2.710E+00 0.000E+00 1.060E+00 I-133 2.310E+02 2.850E+02 5.300E+04 4.750E+02 0.000E+00 1.150E+02 0.000E+00 1.080E+02 I-134 1.820E-03 3.370E-03 7.760E-02 5.160E-03 0.000E+00 2.240E-03 0.000E+00 1.550E-03 I-135 2.890E+01 5.210E+01 4.610E+03 7.990E+01 0.000E+00 3.970E+01 0.000E+00 2.460E+01 CS-134 1.360E+04 2.230E+04 0.000E+00 6.920E+03 2.480E+03 1.200E+02 0.000E+00 4.710E+03 CS-136 1.330E+03 3.660E+03 0.000E+00 1.950E+03 2.910E+02 1.290E+02 0.000E+00 2.370E+03 CS-137 1.900E+04 1.820E+04 0.000E+00 5.930E+03 2.130E+03 1.140E+02 0.000E+00 2.690E+03 CS-138 2.440E-06 3.390E-06 0.000E+00 2.380E-06 2.570E-07 1.560E-06 0.000E+00 2.150E-06 BA-139 5.940E-02 3.170E-05 0.000E+00 2.770E-05 1.860E-05 3.430E+00 0.000E+00 1.720E-03 BA-140 4.700E+03 4.120E+00 0.000E+00 1.340E+00 2.460E+00 2.380E+03 0.000E+00 2.740E+02 BA-141 1.620E-11 9.050E-15 0.000E+00 7.830E-15 5.310E-14 9.210E-12 0.000E+00 5.260E-13 BA-142 1.800E-20 1.300E-23 0.000E+00 1.050E-23 7.630E-24 2.350E-22 0.000E+00 1.010E-21 LA-140 4.780E-01 1.670E-01 0.000E+00 0.000E+00 0.000E+00 4.650E+03 0.000E+00 5.630E-02 LA-142 1.640E-04 5.210E-05 0.000E+00 0.000E+00 0.000E+00 1.030E+01 0.000E+00 1.630E-05 CE-141 2.280E+00 1.140E+00 0.000E+00 4.990E-01 0.000E+00 1.420E+03 0.000E+00 1.690E-01 CE-143 3.160E-01 1.710E+02 0.000E+00 7.180E-02 0.000E+00 2.510E+03 0.000E+00 2.480E-02 CE-144 1.210E+02 3.790E+01 0.000E+00 2.100E+01 0.000E+00 9.870E+03 0.000E+00 6.450E+00 PR-143 2.230E+00 6.690E-01 0.000E+00 3.620E-01 0.000E+00 2.400E+03 0.000E+00 1.110E-01 PR-144 2.200E-15 6.800E-16 0.000E+00 3.600E-16 0.000E+00 1.460E-12 0.000E+00 1.110E-16 ND-147 1.570E+00 1.270E+00 0.000E+00 6.990E-01 0.000E+00 2.020E+03 0.000E+00 9.860E-02 W-187 1.760E+01 1.040E+01 0.000E+00 0.000E+00 0.000E+00 1.460E+03 0.000E+00 4.680E+00 NP-239 2.630E-01 1.890E-02 0.000E+00 5.470E-02 0.000E+00 1.400E+03 0.000E+00 1.330E-02 Appendix E Ai Child Water - Page 3 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX E Ai Child Dose Factors for use in the Liquid Dose Calculations Agegroup: CHILD Pathway: Fresh Water Fish - Sport (FFSP) Units: mrem/hr / Ci/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body H-3 0.000E+00 1.440E-01 1.440E-01 1.440E-01 1.440E-01 1.440E-01 0.000E+00 1.440E-01 C-14 4.380E+04 8.760E+03 8.760E+03 8.760E+03 8.760E+03 8.760E+03 0.000E+00 8.760E+03 NA-24 1.510E+02 1.510E+02 1.510E+02 1.510E+02 1.510E+02 1.510E+02 0.000E+00 1.510E+02 P-32 1.850E+06 8.680E+04 0.000E+00 0.000E+00 0.000E+00 5.130E+04 0.000E+00 7.150E+04 CR-51 0.000E+00 0.000E+00 7.580E-01 2.070E-01 1.380E+00 7.240E+01 0.000E+00 1.370E+00 MN-54 0.000E+00 3.360E+03 0.000E+00 9.420E+02 0.000E+00 2.820E+03 0.000E+00 8.950E+02 MN-56 0.000E+00 1.650E-01 0.000E+00 2.000E-01 0.000E+00 2.400E+01 0.000E+00 3.730E-02 FE-55 9.040E+02 4.790E+02 0.000E+00 0.000E+00 2.710E+02 8.880E+01 0.000E+00 1.490E+02 FE-59 1.280E+03 2.070E+03 0.000E+00 0.000E+00 5.990E+02 2.150E+03 0.000E+00 1.030E+03 CO-58 0.000E+00 7.010E+01 0.000E+00 0.000E+00 0.000E+00 4.090E+02 0.000E+00 2.150E+02 CO-60 0.000E+00 2.080E+02 0.000E+00 0.000E+00 0.000E+00 1.150E+03 0.000E+00 6.130E+02 NI-63 4.230E+04 2.270E+03 0.000E+00 0.000E+00 0.000E+00 1.530E+02 0.000E+00 1.440E+03 NI-65 2.370E-01 2.230E-02 0.000E+00 0.000E+00 0.000E+00 2.740E+00 0.000E+00 1.300E-02 CU-64 0.000E+00 2.590E+00 0.000E+00 6.260E+00 0.000E+00 1.220E+02 0.000E+00 1.570E+00 ZN-65 2.150E+04 5.730E+04 0.000E+00 3.610E+04 0.000E+00 1.010E+04 0.000E+00 3.560E+04 ZN-69 1.080E-06 1.560E-06 0.000E+00 9.470E-07 0.000E+00 9.840E-05 0.000E+00 1.440E-07 BR-83 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.340E-02 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.570E-12 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 0.000E+00 1.020E+05 0.000E+00 0.000E+00 0.000E+00 6.530E+03 0.000E+00 6.250E+04 RB-88 0.000E+00 1.330E-22 0.000E+00 0.000E+00 0.000E+00 6.510E-24 0.000E+00 9.220E-23 RB-89 0.000E+00 1.580E-26 0.000E+00 0.000E+00 0.000E+00 1.370E-28 0.000E+00 1.400E-26 SR-89 3.070E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.190E+03 0.000E+00 8.780E+02 SR-90 4.010E+05 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.400E+03 0.000E+00 1.020E+05 SR-91 9.800E+01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.160E+02 0.000E+00 3.700E+00 Appendix E Ai Child Fish - Page 1 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX E Ai Child Dose Factors for use in the Liquid Dose Calculations Agegroup: CHILD Pathway: Fresh Water Fish - Sport (FFSP) Units: mrem/hr / Ci/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body SR-92 4.580E-01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 8.670E+00 0.000E+00 1.840E-02 Y-90 6.240E-01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.780E+03 0.000E+00 1.670E-02 Y-91 1.170E+01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.560E+03 0.000E+00 3.130E-01 Y-91M 1.480E-11 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.900E-08 0.000E+00 5.390E-13 Y-92 6.440E-04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.860E+01 0.000E+00 1.840E-05 Y-93 4.300E-02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 6.420E+02 0.000E+00 1.180E-03 ZR-95 2.980E-01 6.550E-02 0.000E+00 9.370E-02 0.000E+00 6.830E+01 0.000E+00 5.830E-02 ZR-97 6.780E-03 9.790E-04 0.000E+00 1.410E-03 0.000E+00 1.480E+02 0.000E+00 5.780E-04 NB-95 5.210E+02 2.030E+02 0.000E+00 1.900E+02 0.000E+00 3.750E+05 0.000E+00 1.450E+02 MO-99 0.000E+00 8.130E+01 0.000E+00 1.740E+02 0.000E+00 6.720E+01 0.000E+00 2.010E+01 TC-99M 6.860E-04 1.350E-03 0.000E+00 1.950E-02 6.830E-04 7.650E-01 0.000E+00 2.230E-02 TC-101 3.610E-33 3.780E-33 0.000E+00 6.440E-32 2.000E-33 1.200E-32 0.000E+00 4.790E-32 RU-103 5.650E+00 0.000E+00 0.000E+00 1.420E+01 0.000E+00 1.460E+02 0.000E+00 2.170E+00 RU-105 1.190E-02 0.000E+00 0.000E+00 1.050E-01 0.000E+00 7.790E+00 0.000E+00 4.330E-03 RU-106 9.190E+01 0.000E+00 0.000E+00 1.240E+02 0.000E+00 1.430E+03 0.000E+00 1.150E+01 AG-110M 9.720E-01 6.570E-01 0.000E+00 1.220E+00 0.000E+00 7.810E+01 0.000E+00 5.250E-01 TE-125M 3.540E+03 9.610E+02 9.950E+02 0.000E+00 0.000E+00 3.420E+03 0.000E+00 4.730E+02 TE-127 2.520E+01 6.800E+00 1.750E+01 7.170E+01 0.000E+00 9.850E+02 0.000E+00 5.410E+00 TE-127M 9.040E+03 2.430E+03 2.160E+03 2.580E+04 0.000E+00 7.320E+03 0.000E+00 1.070E+03 TE-129 2.280E-05 6.370E-06 1.630E-05 6.680E-05 0.000E+00 1.420E-03 0.000E+00 5.420E-06 TE-129M 1.500E+04 4.190E+03 4.840E+03 4.410E+04 0.000E+00 1.830E+04 0.000E+00 2.330E+03 TE-131 1.210E-16 3.680E-17 9.220E-17 3.650E-16 0.000E+00 6.330E-16 0.000E+00 3.590E-17 TE-131M 1.300E+03 4.500E+02 9.250E+02 4.350E+03 0.000E+00 1.820E+04 0.000E+00 4.790E+02 TE-132 2.570E+03 1.140E+03 1.650E+03 1.050E+04 0.000E+00 1.140E+04 0.000E+00 1.370E+03 I-130 8.950E+00 1.810E+01 1.990E+03 2.700E+01 0.000E+00 8.460E+00 0.000E+00 9.320E+00 Appendix E Ai Child Fish - Page 2 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX E Ai Child Dose Factors for use in the Liquid Dose Calculations Agegroup: CHILD Pathway: Fresh Water Fish - Sport (FFSP) Units: mrem/hr / Ci/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body I-131 1.860E+02 1.870E+02 6.190E+04 3.070E+02 0.000E+00 1.670E+01 0.000E+00 1.060E+02 I-132 6.830E-03 1.250E-02 5.820E-01 1.920E-02 0.000E+00 1.480E-02 0.000E+00 5.770E-03 I-133 3.140E+01 3.880E+01 7.210E+03 6.470E+01 0.000E+00 1.560E+01 0.000E+00 1.470E+01 I-134 2.750E-08 5.100E-08 1.170E-06 7.800E-08 0.000E+00 3.380E-08 0.000E+00 2.350E-08 I-135 1.670E+00 3.010E+00 2.660E+02 4.610E+00 0.000E+00 2.290E+00 0.000E+00 1.420E+00 CS-134 3.680E+05 6.040E+05 0.000E+00 1.870E+05 6.710E+04 3.250E+03 0.000E+00 1.270E+05 CS-136 3.510E+04 9.640E+04 0.000E+00 5.130E+04 7.660E+03 3.390E+03 0.000E+00 6.240E+04 CS-137 5.140E+05 4.920E+05 0.000E+00 1.600E+05 5.770E+04 3.080E+03 0.000E+00 7.270E+04 CS-138 1.210E-11 1.690E-11 0.000E+00 1.190E-11 1.280E-12 7.770E-12 0.000E+00 1.070E-11 BA-139 7.930E-06 4.230E-09 0.000E+00 3.700E-09 2.490E-09 4.580E-04 0.000E+00 2.300E-07 BA-140 2.480E+02 2.170E-01 0.000E+00 7.060E-02 1.290E-01 1.250E+02 0.000E+00 1.450E+01 BA-141 1.210E-24 6.800E-28 0.000E+00 5.880E-28 3.990E-27 6.920E-25 0.000E+00 3.950E-26 BA-142 3.460E-42 2.490E-45 0.000E+00 2.020E-45 1.470E-45 4.510E-44 0.000E+00 1.930E-43 LA-140 1.310E-01 4.590E-02 0.000E+00 0.000E+00 0.000E+00 1.280E+03 0.000E+00 1.550E-02 LA-142 2.970E-07 9.470E-08 0.000E+00 0.000E+00 0.000E+00 1.880E-02 0.000E+00 2.960E-08 CE-141 3.060E-02 1.520E-02 0.000E+00 6.680E-03 0.000E+00 1.900E+01 0.000E+00 2.260E-03 CE-143 3.320E-03 1.800E+00 0.000E+00 7.550E-04 0.000E+00 2.640E+01 0.000E+00 2.610E-04 CE-144 1.630E+00 5.120E-01 0.000E+00 2.830E-01 0.000E+00 1.330E+02 0.000E+00 8.710E-02 PR-143 7.340E-01 2.200E-01 0.000E+00 1.190E-01 0.000E+00 7.920E+02 0.000E+00 3.640E-02 PR-144 2.180E-28 6.750E-29 0.000E+00 3.570E-29 0.000E+00 1.450E-25 0.000E+00 1.100E-29 ND-147 5.150E-01 4.170E-01 0.000E+00 2.290E-01 0.000E+00 6.610E+02 0.000E+00 3.230E-02 W-187 2.010E+02 1.190E+02 0.000E+00 0.000E+00 0.000E+00 1.680E+04 0.000E+00 5.350E+01 NP-239 3.080E-02 2.210E-03 0.000E+00 6.390E-03 0.000E+00 1.630E+02 0.000E+00 1.550E-03 Appendix E Ai Child Fish - Page 3 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX E Ai Child Dose Factors for use in the Liquid Dose Calculations Agegroup: CHILD Pathway: Shoreline Sediment (SHDp) Units: mrem/hr / Ci/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body H-3 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 C-14 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 NA-24 4.990E-01 4.990E-01 4.990E-01 4.990E-01 4.990E-01 4.990E-01 5.780E-01 4.990E-01 P-32 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 CR-51 1.950E-01 1.950E-01 1.950E-01 1.950E-01 1.950E-01 1.950E-01 2.300E-01 1.950E-01 MN-54 5.790E+01 5.790E+01 5.790E+01 5.790E+01 5.790E+01 5.790E+01 6.790E+01 5.790E+01 MN-56 3.770E-02 3.770E-02 3.770E-02 3.770E-02 3.770E-02 3.770E-02 4.450E-02 3.770E-02 FE-55 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 FE-59 1.140E+01 1.140E+01 1.140E+01 1.140E+01 1.140E+01 1.140E+01 1.340E+01 1.140E+01 CO-58 1.580E+01 1.580E+01 1.580E+01 1.580E+01 1.580E+01 1.580E+01 1.850E+01 1.580E+01 CO-60 8.980E+02 8.980E+02 8.980E+02 8.980E+02 8.980E+02 8.980E+02 1.060E+03 8.980E+02 NI-63 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 NI-65 1.240E-02 1.240E-02 1.240E-02 1.240E-02 1.240E-02 1.240E-02 1.440E-02 1.240E-02 CU-64 2.530E-02 2.530E-02 2.530E-02 2.530E-02 2.530E-02 2.530E-02 2.870E-02 2.530E-02 ZN-65 3.120E+01 3.120E+01 3.120E+01 3.120E+01 3.120E+01 3.120E+01 3.590E+01 3.120E+01 ZN-69 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-83 2.030E-04 2.030E-04 2.030E-04 2.030E-04 2.030E-04 2.030E-04 2.960E-04 2.030E-04 BR-84 8.460E-03 8.460E-03 8.460E-03 8.460E-03 8.460E-03 8.460E-03 9.870E-03 8.460E-03 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 3.750E-01 3.750E-01 3.750E-01 3.750E-01 3.750E-01 3.750E-01 4.290E-01 3.750E-01 RB-88 1.380E-03 1.380E-03 1.380E-03 1.380E-03 1.380E-03 1.380E-03 1.580E-03 1.380E-03 RB-89 5.130E-03 5.130E-03 5.130E-03 5.130E-03 5.130E-03 5.130E-03 6.160E-03 5.130E-03 SR-89 9.030E-04 9.030E-04 9.030E-04 9.030E-04 9.030E-04 9.030E-04 1.050E-03 9.030E-04 SR-90 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 SR-91 8.970E-02 8.970E-02 8.970E-02 8.970E-02 8.970E-02 8.970E-02 1.050E-01 8.970E-02 Appendix E Ai Child Shoreline Sediment - Page 1 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX E Ai Child Dose Factors for use in the Liquid Dose Calculations Agegroup: CHILD Pathway: Shoreline Sediment (SHDp) Units: mrem/hr / Ci/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body SR-92 3.240E-02 3.240E-02 3.240E-02 3.240E-02 3.240E-02 3.240E-02 3.600E-02 3.240E-02 Y-90 1.880E-04 1.880E-04 1.880E-04 1.880E-04 1.880E-04 1.880E-04 2.220E-04 1.880E-04 Y-91 4.480E-02 4.480E-02 4.480E-02 4.480E-02 4.480E-02 4.480E-02 5.040E-02 4.480E-02 Y-91M 4.190E-03 4.190E-03 4.190E-03 4.190E-03 4.190E-03 4.190E-03 4.850E-03 4.190E-03 Y-92 7.530E-03 7.530E-03 7.530E-03 7.530E-03 7.530E-03 7.530E-03 8.940E-03 7.530E-03 Y-93 7.660E-03 7.660E-03 7.660E-03 7.660E-03 7.660E-03 7.660E-03 1.050E-02 7.660E-03 ZR-95 1.020E+01 1.020E+01 1.020E+01 1.020E+01 1.020E+01 1.020E+01 1.190E+01 1.020E+01 ZR-97 1.240E-01 1.240E-01 1.240E-01 1.240E-01 1.240E-01 1.240E-01 1.440E-01 1.240E-01 NB-95 5.710E+00 5.710E+00 5.710E+00 5.710E+00 5.710E+00 5.710E+00 6.710E+00 5.710E+00 MO-99 1.670E-01 1.670E-01 1.670E-01 1.670E-01 1.670E-01 1.670E-01 1.930E-01 1.670E-01 TC-99M 7.680E-03 7.680E-03 7.680E-03 7.680E-03 7.680E-03 7.680E-03 8.810E-03 7.680E-03 TC-101 8.500E-04 8.500E-04 8.500E-04 8.500E-04 8.500E-04 8.500E-04 9.440E-04 8.500E-04 RU-103 4.520E+00 4.520E+00 4.520E+00 4.520E+00 4.520E+00 4.520E+00 5.270E+00 4.520E+00 RU-105 2.660E-02 2.660E-02 2.660E-02 2.660E-02 2.660E-02 2.660E-02 3.010E-02 2.660E-02 RU-106 1.760E+01 1.760E+01 1.760E+01 1.760E+01 1.760E+01 1.760E+01 2.110E+01 1.760E+01 AG-110M 1.440E+02 1.440E+02 1.440E+02 1.440E+02 1.440E+02 1.440E+02 1.670E+02 1.440E+02 TE-125M 6.480E-02 6.480E-02 6.480E-02 6.480E-02 6.480E-02 6.480E-02 8.880E-02 6.480E-02 TE-127 1.240E-04 1.240E-04 1.240E-04 1.240E-04 1.240E-04 1.240E-04 1.370E-04 1.240E-04 TE-127M 3.830E-03 3.830E-03 3.830E-03 3.830E-03 3.830E-03 3.830E-03 4.520E-03 3.830E-03 TE-129 1.100E-03 1.100E-03 1.100E-03 1.100E-03 1.100E-03 1.100E-03 1.300E-03 1.100E-03 TE-129M 8.260E-01 8.260E-01 8.260E-01 8.260E-01 8.260E-01 8.260E-01 9.650E-01 8.260E-01 TE-131 1.220E-03 1.220E-03 1.220E-03 1.220E-03 1.220E-03 1.220E-03 1.440E+00 1.220E-03 TE-131M 3.350E-01 3.350E-01 3.350E-01 3.350E-01 3.350E-01 3.350E-01 3.950E-01 3.350E-01 TE-132 1.770E-01 1.770E-01 1.770E-01 1.770E-01 1.770E-01 1.770E-01 2.080E-01 1.770E-01 I-130 2.300E-01 2.300E-01 2.300E-01 2.300E-01 2.300E-01 2.300E-01 2.790E-01 2.300E-01 Appendix E Ai Child Shoreline Sediment - Page 2 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX E Ai Child Dose Factors for use in the Liquid Dose Calculations Agegroup: CHILD Pathway: Shoreline Sediment (SHDp) Units: mrem/hr / Ci/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body I-131 7.180E-01 7.180E-01 7.180E-01 7.180E-01 7.180E-01 7.180E-01 8.720E-01 7.180E-01 I-132 5.200E-02 5.200E-02 5.200E-02 5.200E-02 5.200E-02 5.200E-02 6.120E-02 5.200E-02 I-133 1.020E-01 1.020E-01 1.020E-01 1.020E-01 1.020E-01 1.020E-01 1.240E-01 1.020E-01 I-134 1.870E-02 1.870E-02 1.870E-02 1.870E-02 1.870E-02 1.870E-02 2.210E-02 1.870E-02 I-135 1.050E-01 1.050E-01 1.050E-01 1.050E-01 1.050E-01 1.050E-01 1.230E-01 1.050E-01 CS-134 2.860E+02 2.860E+02 2.860E+02 2.860E+02 2.860E+02 2.860E+02 3.340E+02 2.860E+02 CS-136 6.300E+00 6.300E+00 6.300E+00 6.300E+00 6.300E+00 6.300E+00 7.140E+00 6.300E+00 CS-137 4.290E+02 4.290E+02 4.290E+02 4.290E+02 4.290E+02 4.290E+02 5.010E+02 4.290E+02 CS-138 1.500E-02 1.500E-02 1.500E-02 1.500E-02 1.500E-02 1.500E-02 1.710E-02 1.500E-02 BA-139 4.420E-03 4.420E-03 4.420E-03 4.420E-03 4.420E-03 4.420E-03 4.970E-03 4.420E-03 BA-140 8.570E-01 8.570E-01 8.570E-01 8.570E-01 8.570E-01 8.570E-01 9.800E-01 8.570E-01 BA-141 1.740E-03 1.740E-03 1.740E-03 1.740E-03 1.740E-03 1.740E-03 1.980E-03 1.740E-03 BA-142 1.870E-03 1.870E-03 1.870E-03 1.870E-03 1.870E-03 1.870E-03 2.130E-03 1.870E-03 LA-140 8.020E-01 8.020E-01 8.020E-01 8.020E-01 8.020E-01 8.020E-01 9.090E-01 8.020E-01 LA-142 3.170E-02 3.170E-02 3.170E-02 3.170E-02 3.170E-02 3.170E-02 3.810E-02 3.170E-02 CE-141 5.700E-01 5.700E-01 5.700E-01 5.700E-01 5.700E-01 5.700E-01 6.430E-01 5.700E-01 CE-143 9.650E-02 9.650E-02 9.650E-02 9.650E-02 9.650E-02 9.650E-02 1.100E-01 9.650E-02 CE-144 2.900E+00 2.900E+00 2.900E+00 2.900E+00 2.900E+00 2.900E+00 3.360E+00 2.900E+00 PR-143 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 PR-144 7.660E-05 7.660E-05 7.660E-05 7.660E-05 7.660E-05 7.660E-05 8.810E-05 7.660E-05 ND-147 3.500E-01 3.500E-01 3.500E-01 3.500E-01 3.500E-01 3.500E-01 4.200E-01 3.500E-01 W-187 9.820E-02 9.820E-02 9.820E-02 9.820E-02 9.820E-02 9.820E-02 1.140E-01 9.820E-02 NP-239 7.140E-02 7.140E-02 7.140E-02 7.140E-02 7.140E-02 7.140E-02 8.270E-02 7.140E-02 Appendix E Ai Child Shoreline Sediment - Page 3 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX F Ai Infant Dose Factors for use in the Liquid Dose Calculations Agegroup: INFANT Pathway: Potable Water (PWtr) Units: mrem/hr / Ci/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body H-3 0.000E+00 1.160E+01 1.160E+01 1.160E+01 1.160E+01 1.160E+01 0.000E+00 1.160E+01 C-14 8.920E+02 1.900E+02 1.900E+02 1.900E+02 1.900E+02 1.900E+02 0.000E+00 1.900E+02 NA-24 2.190E+02 2.190E+02 2.190E+02 2.190E+02 2.190E+02 2.190E+02 0.000E+00 2.190E+02 P-32 6.240E+04 3.670E+03 0.000E+00 0.000E+00 0.000E+00 8.450E+02 0.000E+00 2.420E+03 CR-51 0.000E+00 0.000E+00 3.420E-01 7.470E-02 6.650E-01 1.530E+01 0.000E+00 5.240E-01 MN-54 0.000E+00 7.480E+02 0.000E+00 1.660E+02 0.000E+00 2.750E+02 0.000E+00 1.690E+02 MN-56 0.000E+00 1.220E+00 0.000E+00 1.050E+00 0.000E+00 1.110E+02 0.000E+00 2.100E-01 FE-55 5.230E+02 3.380E+02 0.000E+00 0.000E+00 1.650E+02 4.290E+01 0.000E+00 9.030E+01 FE-59 1.150E+03 2.010E+03 0.000E+00 0.000E+00 5.940E+02 9.590E+02 0.000E+00 7.910E+02 CO-58 0.000E+00 1.350E+02 0.000E+00 0.000E+00 0.000E+00 3.360E+02 0.000E+00 3.360E+02 CO-60 0.000E+00 4.060E+02 0.000E+00 0.000E+00 0.000E+00 9.670E+02 0.000E+00 9.590E+02 NI-63 2.390E+04 1.470E+03 0.000E+00 0.000E+00 0.000E+00 7.340E+01 0.000E+00 8.280E+02 NI-65 6.520E+00 7.380E-01 0.000E+00 0.000E+00 0.000E+00 5.620E+01 0.000E+00 3.360E-01 CU-64 0.000E+00 1.190E+01 0.000E+00 2.010E+01 0.000E+00 2.440E+02 0.000E+00 5.500E+00 ZN-65 6.910E+02 2.370E+03 0.000E+00 1.150E+03 0.000E+00 2.000E+03 0.000E+00 1.090E+03 ZN-69 4.390E-04 7.910E-04 0.000E+00 3.290E-04 0.000E+00 6.450E-02 0.000E+00 5.890E-05 BR-83 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4.200E-01 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.220E-06 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.800E-76 RB-86 0.000E+00 6.280E+03 0.000E+00 0.000E+00 0.000E+00 1.610E+02 0.000E+00 3.100E+03 RB-88 0.000E+00 1.250E-11 0.000E+00 0.000E+00 0.000E+00 1.220E-11 0.000E+00 6.840E-12 RB-89 0.000E+00 9.960E-14 0.000E+00 0.000E+00 0.000E+00 3.390E-14 0.000E+00 6.860E-14 SR-89 9.380E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.930E+03 0.000E+00 2.690E+03 SR-90 6.960E+05 0.000E+00 0.000E+00 0.000E+00 0.000E+00 8.690E+03 0.000E+00 1.770E+05 SR-91 7.830E+02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 9.270E+02 0.000E+00 2.830E+01 Appendix F Ai Infant Water - Page 1 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX F Ai Infant Dose Factors for use in the Liquid Dose Calculations Agegroup: INFANT Pathway: Potable Water (PWtr) Units: mrem/hr / Ci/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body SR-92 3.350E+01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.610E+02 0.000E+00 1.240E+00 Y-90 2.870E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.970E+03 0.000E+00 7.700E-02 Y-91 4.230E+01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.030E+03 0.000E+00 1.130E+00 Y-91M 1.350E-06 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4.510E-03 0.000E+00 4.610E-08 Y-92 2.740E-02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.240E+02 0.000E+00 7.710E-04 Y-93 4.010E-01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.170E+03 0.000E+00 1.090E-02 ZR-95 7.710E+00 1.880E+00 0.000E+00 2.020E+00 0.000E+00 9.350E+02 0.000E+00 1.330E+00 ZR-97 3.400E-01 5.840E-02 0.000E+00 5.890E-02 0.000E+00 3.720E+03 0.000E+00 2.670E-02 NB-95 1.560E+00 6.440E-01 0.000E+00 4.620E-01 0.000E+00 5.440E+02 0.000E+00 3.720E-01 MO-99 0.000E+00 1.130E+03 0.000E+00 1.680E+03 0.000E+00 3.710E+02 0.000E+00 2.200E+02 TC-99M 1.810E-02 3.740E-02 0.000E+00 4.020E-01 1.950E-02 1.090E+01 0.000E+00 4.820E-01 TC-101 4.570E-17 5.750E-17 0.000E+00 6.840E-16 3.140E-17 9.780E-15 0.000E+00 5.690E-16 RU-103 5.520E+01 0.000E+00 0.000E+00 1.150E+02 0.000E+00 6.710E+02 0.000E+00 1.850E+01 RU-105 7.850E-01 0.000E+00 0.000E+00 5.770E+00 0.000E+00 3.120E+02 0.000E+00 2.640E-01 RU-106 9.060E+02 0.000E+00 0.000E+00 1.070E+03 0.000E+00 6.880E+03 0.000E+00 1.130E+02 AG-110M 3.740E+01 2.730E+01 0.000E+00 3.910E+01 0.000E+00 1.420E+03 0.000E+00 1.810E+01 TE-125M 8.710E+02 2.910E+02 2.930E+02 0.000E+00 0.000E+00 4.150E+02 0.000E+00 1.180E+02 TE-127 1.550E+01 5.200E+00 1.260E+01 3.790E+01 0.000E+00 3.260E+02 0.000E+00 3.340E+00 TE-127M 2.190E+03 7.280E+02 6.340E+02 5.400E+03 0.000E+00 8.850E+02 0.000E+00 2.660E+02 TE-129 7.860E-03 2.710E-03 6.590E-03 1.960E-02 0.000E+00 6.280E-01 0.000E+00 1.840E-03 TE-129M 3.720E+03 1.280E+03 1.430E+03 9.310E+03 0.000E+00 2.220E+03 0.000E+00 5.730E+02 TE-131 1.420E-08 5.250E-09 1.270E-08 3.640E-08 0.000E+00 5.750E-07 0.000E+00 3.990E-09 TE-131M 4.330E+02 1.740E+02 3.540E+02 1.200E+03 0.000E+00 2.940E+03 0.000E+00 1.440E+02 TE-132 7.030E+02 3.480E+02 5.140E+02 2.180E+03 0.000E+00 1.290E+03 0.000E+00 3.250E+02 I-130 1.150E+02 2.530E+02 2.840E+04 2.780E+02 0.000E+00 5.430E+01 0.000E+00 1.020E+02 Appendix F Ai Infant Water - Page 2 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX F Ai Infant Dose Factors for use in the Liquid Dose Calculations Agegroup: INFANT Pathway: Potable Water (PWtr) Units: mrem/hr / Ci/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body I-131 1.290E+03 1.520E+03 5.010E+05 1.780E+03 0.000E+00 5.440E+01 0.000E+00 6.700E+02 I-132 1.680E+00 3.410E+00 1.600E+02 3.800E+00 0.000E+00 2.760E+00 0.000E+00 1.210E+00 I-133 3.150E+02 4.590E+02 8.350E+04 5.400E+02 0.000E+00 7.770E+01 0.000E+00 1.340E+02 I-134 2.440E-03 4.990E-03 1.160E-01 5.580E-03 0.000E+00 5.160E-03 0.000E+00 1.780E-03 I-135 3.900E+01 7.750E+01 6.950E+03 8.640E+01 0.000E+00 2.800E+01 0.000E+00 2.830E+01 CS-134 1.420E+04 2.640E+04 0.000E+00 6.810E+03 2.790E+03 7.180E+01 0.000E+00 2.670E+03 CS-136 1.680E+03 4.950E+03 0.000E+00 1.970E+03 4.030E+02 7.510E+01 0.000E+00 1.850E+03 CS-137 1.960E+04 2.300E+04 0.000E+00 6.170E+03 2.500E+03 7.190E+01 0.000E+00 1.630E+03 CS-138 3.330E-06 5.410E-06 0.000E+00 2.700E-06 4.210E-07 8.650E-06 0.000E+00 2.620E-06 BA-139 8.180E-02 5.420E-05 0.000E+00 3.260E-05 3.290E-05 5.180E+00 0.000E+00 2.370E-03 BA-140 6.260E+03 6.260E+00 0.000E+00 1.490E+00 3.840E+00 1.540E+03 0.000E+00 3.230E+02 BA-141 2.220E-11 1.520E-14 0.000E+00 9.140E-15 9.250E-15 2.710E-10 0.000E+00 7.000E-13 BA-142 2.460E-20 2.040E-23 0.000E+00 1.180E-23 1.240E-23 1.010E-19 0.000E+00 1.210E-21 LA-140 6.460E-01 2.550E-01 0.000E+00 0.000E+00 0.000E+00 2.990E+03 0.000E+00 6.550E-02 LA-142 2.220E-04 8.160E-05 0.000E+00 0.000E+00 0.000E+00 1.390E+01 0.000E+00 1.950E-05 CE-141 2.930E+00 1.790E+00 0.000E+00 5.510E-01 0.000E+00 9.230E+02 0.000E+00 2.100E-01 CE-143 4.330E-01 2.870E+02 0.000E+00 8.360E-02 0.000E+00 1.670E+03 0.000E+00 3.270E-02 CE-144 1.120E+02 4.580E+01 0.000E+00 1.850E+01 0.000E+00 6.430E+03 0.000E+00 6.270E+00 PR-143 2.980E+00 1.110E+00 0.000E+00 4.140E-01 0.000E+00 1.570E+03 0.000E+00 1.480E-01 PR-144 3.020E-15 1.170E-15 0.000E+00 4.240E-16 0.000E+00 5.440E-11 0.000E+00 1.520E-16 ND-147 2.020E+00 2.070E+00 0.000E+00 7.980E-01 0.000E+00 1.310E+03 0.000E+00 1.270E-01 W-187 2.400E+01 1.670E+01 0.000E+00 0.000E+00 0.000E+00 9.790E+02 0.000E+00 5.760E+00 NP-239 3.600E-01 3.220E-02 0.000E+00 6.430E-02 0.000E+00 9.320E+02 0.000E+00 1.820E-02 Appendix F Ai Infant Water - Page 3 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX G Ri Adult Dose Factors for use in the Gaseous Dose Calculations Agegroup: ADULT Pathway: Grs/Cow/Milk (CMILK) Units: m2*mrem/yr / Ci/sec; mrem/yr / Ci/m3 (H-3)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body H-3 0.000E+00 7.630E+02 7.630E+02 7.630E+02 7.630E+02 7.630E+02 0.000E+00 7.630E+02 C-14 2.630E+08 5.270E+07 5.270E+07 5.270E+07 5.270E+07 5.270E+07 0.000E+00 5.270E+07 NA-24 2.440E+06 2.440E+06 2.440E+06 2.440E+06 2.440E+06 2.440E+06 0.000E+00 2.440E+06 P-32 1.710E+10 1.060E+09 0.000E+00 0.000E+00 0.000E+00 1.920E+09 0.000E+00 6.610E+08 CR-51 0.000E+00 0.000E+00 1.710E+04 6.300E+03 3.790E+04 7.190E+06 0.000E+00 2.860E+04 MN-54 0.000E+00 8.410E+06 0.000E+00 2.500E+06 0.000E+00 2.580E+07 0.000E+00 1.610E+06 MN-56 0.000E+00 4.090E-03 0.000E+00 5.190E-03 0.000E+00 1.310E-01 0.000E+00 7.260E-04 FE-55 2.510E+07 1.740E+07 0.000E+00 0.000E+00 9.680E+06 9.950E+06 0.000E+00 4.050E+06 FE-59 2.970E+07 6.980E+07 0.000E+00 0.000E+00 1.950E+07 2.330E+08 0.000E+00 2.680E+07 CO-58 0.000E+00 4.710E+06 0.000E+00 0.000E+00 0.000E+00 9.550E+07 0.000E+00 1.060E+07 CO-60 0.000E+00 1.640E+07 0.000E+00 0.000E+00 0.000E+00 3.080E+08 0.000E+00 3.620E+07 NI-63 6.730E+09 4.660E+08 0.000E+00 0.000E+00 0.000E+00 9.730E+07 0.000E+00 2.260E+08 NI-65 3.700E-01 4.810E-02 0.000E+00 0.000E+00 0.000E+00 1.220E+00 0.000E+00 2.190E-02 CU-64 0.000E+00 2.380E+04 0.000E+00 6.010E+04 0.000E+00 2.030E+06 0.000E+00 1.120E+04 ZN-65 1.370E+09 4.370E+09 0.000E+00 2.920E+09 0.000E+00 2.750E+09 0.000E+00 1.970E+09 ZN-69 2.090E-12 4.000E-12 0.000E+00 2.600E-12 0.000E+00 6.010E-13 0.000E+00 2.780E-13 BR-83 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.400E-01 0.000E+00 9.720E-02 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.260E-28 0.000E+00 1.610E-23 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 0.000E+00 2.590E+09 0.000E+00 0.000E+00 0.000E+00 5.120E+08 0.000E+00 1.210E+09 RB-88 0.000E+00 2.140E-45 0.000E+00 0.000E+00 0.000E+00 2.960E-56 0.000E+00 1.140E-45 RB-89 0.000E+00 4.330E-53 0.000E+00 0.000E+00 0.000E+00 2.510E-66 0.000E+00 3.040E-53 SR-89 1.450E+09 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.330E+08 0.000E+00 4.160E+07 SR-90 4.680E+10 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.350E+09 0.000E+00 1.150E+10 SR-91 2.890E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.380E+05 0.000E+00 1.170E+03 Appendix G Ri Adult Cow Milk - Page 1 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX G Ri Adult Dose Factors for use in the Gaseous Dose Calculations Agegroup: ADULT Pathway: Grs/Cow/Milk (CMILK) Units: m2*mrem/yr / Ci/sec; mrem/yr / Ci/m3 (H-3)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body SR-92 4.880E-01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 9.680E+00 0.000E+00 2.110E-02 Y-90 7.080E+01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 7.510E+05 0.000E+00 1.900E+00 Y-91 8.590E+03 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4.730E+06 0.000E+00 2.300E+02 Y-91M 5.980E-20 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.760E-19 0.000E+00 2.320E-21 Y-92 5.580E-05 0.000E+00 0.000E+00 0.000E+00 0.000E+00 9.770E-01 0.000E+00 1.630E-06 Y-93 2.230E-01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 7.090E+03 0.000E+00 6.170E-03 ZR-95 9.430E+02 3.030E+02 0.000E+00 4.750E+02 0.000E+00 9.590E+05 0.000E+00 2.050E+02 ZR-97 4.330E-01 8.740E-02 0.000E+00 1.320E-01 0.000E+00 2.710E+04 0.000E+00 4.000E-02 NB-95 8.260E+04 4.590E+04 0.000E+00 4.540E+04 0.000E+00 2.790E+08 0.000E+00 2.470E+04 MO-99 0.000E+00 2.480E+07 0.000E+00 5.610E+07 0.000E+00 5.740E+07 0.000E+00 4.710E+06 TC-99M 3.320E+00 9.380E+00 0.000E+00 1.420E+02 4.600E+00 5.550E+03 0.000E+00 1.200E+02 TC-101 2.590E-60 3.740E-60 0.000E+00 6.730E-59 1.910E-60 1.120E-71 0.000E+00 3.670E-59 RU-103 1.020E+03 0.000E+00 0.000E+00 3.890E+03 0.000E+00 1.190E+05 0.000E+00 4.390E+02 RU-105 8.570E-04 0.000E+00 0.000E+00 1.110E-02 0.000E+00 5.240E-01 0.000E+00 3.380E-04 RU-106 2.040E+04 0.000E+00 0.000E+00 3.940E+04 0.000E+00 1.320E+06 0.000E+00 2.580E+03 AG-110M 5.820E+07 5.390E+07 0.000E+00 1.060E+08 0.000E+00 2.200E+10 0.000E+00 3.200E+07 TE-125M 1.630E+07 5.900E+06 4.900E+06 6.630E+07 0.000E+00 6.500E+07 0.000E+00 2.180E+06 TE-127 6.530E+02 2.340E+02 4.840E+02 2.660E+03 0.000E+00 5.150E+04 0.000E+00 1.410E+02 TE-127M 4.580E+07 1.640E+07 1.170E+07 1.860E+08 0.000E+00 1.540E+08 0.000E+00 5.580E+06 TE-129 2.830E-10 1.060E-10 2.170E-10 1.190E-09 0.000E+00 2.130E-10 0.000E+00 6.880E-11 TE-129M 6.020E+07 2.250E+07 2.070E+07 2.510E+08 0.000E+00 3.030E+08 0.000E+00 9.530E+06 TE-131 3.600E-33 1.500E-33 2.960E-33 1.580E-32 0.000E+00 5.100E-34 0.000E+00 1.140E-33 TE-131M 3.610E+05 1.770E+05 2.800E+05 1.790E+06 0.000E+00 1.750E+07 0.000E+00 1.470E+05 TE-132 2.400E+06 1.550E+06 1.720E+06 1.500E+07 0.000E+00 7.350E+07 0.000E+00 1.460E+06 I-130 4.200E+05 1.240E+06 1.050E+08 1.930E+06 0.000E+00 1.070E+06 0.000E+00 4.890E+05 Appendix G Ri Adult Cow Milk - Page 2 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX G Ri Adult Dose Factors for use in the Gaseous Dose Calculations Agegroup: ADULT Pathway: Grs/Cow/Milk (CMILK) Units: m2*mrem/yr / Ci/sec; mrem/yr / Ci/m3 (H-3)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body I-131 2.960E+08 4.230E+08 1.390E+11 7.260E+08 0.000E+00 1.120E+08 0.000E+00 2.430E+08 I-132 1.640E-01 4.390E-01 1.540E+01 7.000E-01 0.000E+00 8.250E-02 0.000E+00 1.540E-01 I-133 3.870E+06 6.730E+06 9.890E+08 1.170E+07 0.000E+00 6.050E+06 0.000E+00 2.050E+06 I-134 2.020E-12 5.480E-12 9.490E-11 8.710E-12 0.000E+00 4.770E-15 0.000E+00 1.960E-12 I-135 1.280E+04 3.360E+04 2.220E+06 5.390E+04 0.000E+00 3.800E+04 0.000E+00 1.240E+04 CS-134 5.650E+09 1.350E+10 0.000E+00 4.350E+09 1.450E+09 2.350E+08 0.000E+00 1.100E+10 CS-136 2.630E+08 1.040E+09 0.000E+00 5.780E+08 7.930E+07 1.180E+08 0.000E+00 7.480E+08 CS-137 7.380E+09 1.010E+10 0.000E+00 3.430E+09 1.140E+09 1.950E+08 0.000E+00 6.610E+09 CS-138 9.050E-24 1.790E-23 0.000E+00 1.310E-23 1.300E-24 7.620E-29 0.000E+00 8.850E-24 BA-139 4.420E-08 3.150E-11 0.000E+00 2.940E-11 1.790E-11 7.830E-08 0.000E+00 1.290E-09 BA-140 2.690E+07 3.380E+04 0.000E+00 1.150E+04 1.930E+04 5.530E+07 0.000E+00 1.760E+06 BA-141 4.090E-46 3.090E-49 0.000E+00 2.880E-49 1.760E-49 1.930E-55 0.000E+00 1.380E-47 BA-142 2.640E-80 2.720E-83 0.000E+00 2.300E-83 1.540E-83 3.720E-98 0.000E+00 1.660E-81 LA-140 4.510E+00 2.270E+00 0.000E+00 0.000E+00 0.000E+00 1.670E+05 0.000E+00 6.010E-01 LA-142 1.860E-11 8.460E-12 0.000E+00 0.000E+00 0.000E+00 6.170E-08 0.000E+00 2.110E-12 CE-141 4.840E+03 3.280E+03 0.000E+00 1.520E+03 0.000E+00 1.250E+07 0.000E+00 3.720E+02 CE-143 4.160E+01 3.070E+04 0.000E+00 1.350E+01 0.000E+00 1.150E+06 0.000E+00 3.400E+00 CE-144 3.580E+05 1.500E+05 0.000E+00 8.870E+04 0.000E+00 1.210E+08 0.000E+00 1.920E+04 PR-143 1.580E+02 6.330E+01 0.000E+00 3.660E+01 0.000E+00 6.920E+05 0.000E+00 7.830E+00 PR-144 5.870E-54 2.440E-54 0.000E+00 1.380E-54 0.000E+00 8.450E-61 0.000E+00 2.990E-55 ND-147 9.420E+01 1.090E+02 0.000E+00 6.360E+01 0.000E+00 5.220E+05 0.000E+00 6.510E+00 W-187 6.510E+03 5.450E+03 0.000E+00 0.000E+00 0.000E+00 1.780E+06 0.000E+00 1.900E+03 NP-239 3.670E+00 3.610E-01 0.000E+00 1.130E+00 0.000E+00 7.410E+04 0.000E+00 1.990E-01 Appendix G Ri Adult Cow Milk - Page 3 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX G Ri Adult Dose Factors for use in the Gaseous Dose Calculations Agegroup: ADULT Pathway: Grs/Goat/Milk (GMILK) Units: m2*mrem/yr / Ci/sec; mrem/yr / Ci/m3 (H-3)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body H-3 0.000E+00 1.560E+03 1.560E+03 1.560E+03 1.560E+03 1.560E+03 0.000E+00 1.560E+03 C-14 2.630E+08 5.270E+07 5.270E+07 5.270E+07 5.270E+07 5.270E+07 0.000E+00 5.270E+07 NA-24 2.930E+05 2.930E+05 2.930E+05 2.930E+05 2.930E+05 2.930E+05 0.000E+00 2.930E+05 P-32 2.050E+10 1.280E+09 0.000E+00 0.000E+00 0.000E+00 2.310E+09 0.000E+00 7.930E+08 CR-51 0.000E+00 0.000E+00 2.050E+03 7.550E+02 4.550E+03 8.620E+05 0.000E+00 3.430E+03 MN-54 0.000E+00 1.010E+06 0.000E+00 3.000E+05 0.000E+00 3.090E+06 0.000E+00 1.930E+05 MN-56 0.000E+00 4.910E-04 0.000E+00 6.230E-04 0.000E+00 1.570E-02 0.000E+00 8.710E-05 FE-55 3.260E+05 2.260E+05 0.000E+00 0.000E+00 1.260E+05 1.290E+05 0.000E+00 5.260E+04 FE-59 3.860E+05 9.070E+05 0.000E+00 0.000E+00 2.540E+05 3.020E+06 0.000E+00 3.480E+05 CO-58 0.000E+00 5.660E+05 0.000E+00 0.000E+00 0.000E+00 1.150E+07 0.000E+00 1.270E+06 CO-60 0.000E+00 1.970E+06 0.000E+00 0.000E+00 0.000E+00 3.700E+07 0.000E+00 4.340E+06 NI-63 8.070E+08 5.600E+07 0.000E+00 0.000E+00 0.000E+00 1.170E+07 0.000E+00 2.710E+07 NI-65 4.440E-02 5.770E-03 0.000E+00 0.000E+00 0.000E+00 1.460E-01 0.000E+00 2.630E-03 CU-64 0.000E+00 2.660E+03 0.000E+00 6.700E+03 0.000E+00 2.260E+05 0.000E+00 1.250E+03 ZN-65 1.650E+08 5.240E+08 0.000E+00 3.500E+08 0.000E+00 3.300E+08 0.000E+00 2.370E+08 ZN-69 2.510E-13 4.800E-13 0.000E+00 3.120E-13 0.000E+00 7.210E-14 0.000E+00 3.340E-14 BR-83 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.680E-02 0.000E+00 1.170E-02 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.520E-29 0.000E+00 1.930E-24 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 0.000E+00 3.110E+08 0.000E+00 0.000E+00 0.000E+00 6.140E+07 0.000E+00 1.450E+08 RB-88 0.000E+00 2.570E-46 0.000E+00 0.000E+00 0.000E+00 3.550E-57 0.000E+00 1.360E-46 RB-89 0.000E+00 5.190E-54 0.000E+00 0.000E+00 0.000E+00 3.020E-67 0.000E+00 3.650E-54 SR-89 3.050E+09 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4.890E+08 0.000E+00 8.750E+07 SR-90 9.830E+10 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.840E+09 0.000E+00 2.410E+10 SR-91 6.070E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.890E+05 0.000E+00 2.450E+03 Appendix G Ri Adult Goat Milk - Page 1 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX G Ri Adult Dose Factors for use in the Gaseous Dose Calculations Agegroup: ADULT Pathway: Grs/Goat/Milk (GMILK) Units: m2*mrem/yr / Ci/sec; mrem/yr / Ci/m3 (H-3)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body SR-92 1.030E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.030E+01 0.000E+00 4.440E-02 Y-90 8.500E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 9.010E+04 0.000E+00 2.280E-01 Y-91 1.030E+03 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.670E+05 0.000E+00 2.760E+01 Y-91M 7.170E-21 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.110E-20 0.000E+00 2.780E-22 Y-92 6.690E-06 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.170E-01 0.000E+00 1.960E-07 Y-93 2.680E-02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 8.500E+02 0.000E+00 7.400E-04 ZR-95 1.130E+02 3.630E+01 0.000E+00 5.700E+01 0.000E+00 1.150E+05 0.000E+00 2.460E+01 ZR-97 5.200E-02 1.050E-02 0.000E+00 1.580E-02 0.000E+00 3.250E+03 0.000E+00 4.800E-03 NB-95 9.910E+03 5.510E+03 0.000E+00 5.450E+03 0.000E+00 3.340E+07 0.000E+00 2.960E+03 MO-99 0.000E+00 2.970E+06 0.000E+00 6.730E+06 0.000E+00 6.890E+06 0.000E+00 5.660E+05 TC-99M 3.980E-01 1.130E+00 0.000E+00 1.710E+01 5.520E-01 6.660E+02 0.000E+00 1.430E+01 TC-101 3.110E-61 4.490E-61 0.000E+00 8.080E-60 2.290E-61 1.350E-72 0.000E+00 4.400E-60 RU-103 1.220E+02 0.000E+00 0.000E+00 4.660E+02 0.000E+00 1.430E+04 0.000E+00 5.260E+01 RU-105 1.030E-04 0.000E+00 0.000E+00 1.330E-03 0.000E+00 6.290E-02 0.000E+00 4.060E-05 RU-106 2.450E+03 0.000E+00 0.000E+00 4.730E+03 0.000E+00 1.580E+05 0.000E+00 3.100E+02 AG-110M 6.990E+06 6.460E+06 0.000E+00 1.270E+07 0.000E+00 2.640E+09 0.000E+00 3.840E+06 TE-125M 1.950E+06 7.080E+05 5.880E+05 7.950E+06 0.000E+00 7.800E+06 0.000E+00 2.620E+05 TE-127 7.830E+01 2.810E+01 5.800E+01 3.190E+02 0.000E+00 6.180E+03 0.000E+00 1.700E+01 TE-127M 5.490E+06 1.960E+06 1.400E+06 2.230E+07 0.000E+00 1.840E+07 0.000E+00 6.690E+05 TE-129 3.390E-11 1.270E-11 2.600E-11 1.430E-10 0.000E+00 2.560E-11 0.000E+00 8.260E-12 TE-129M 7.220E+06 2.690E+06 2.480E+06 3.020E+07 0.000E+00 3.640E+07 0.000E+00 1.140E+06 TE-131 4.320E-34 1.810E-34 3.550E-34 1.890E-33 0.000E+00 6.120E-35 0.000E+00 1.360E-34 TE-131M 4.330E+04 2.120E+04 3.360E+04 2.150E+05 0.000E+00 2.100E+06 0.000E+00 1.770E+04 TE-132 2.880E+05 1.860E+05 2.060E+05 1.800E+06 0.000E+00 8.820E+06 0.000E+00 1.750E+05 I-130 5.040E+05 1.490E+06 1.260E+08 2.320E+06 0.000E+00 1.280E+06 0.000E+00 5.870E+05 Appendix G Ri Adult Goat Milk - Page 2 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX G Ri Adult Dose Factors for use in the Gaseous Dose Calculations Agegroup: ADULT Pathway: Grs/Goat/Milk (GMILK) Units: m2*mrem/yr / Ci/sec; mrem/yr / Ci/m3 (H-3)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body I-131 3.550E+08 5.080E+08 1.670E+11 8.710E+08 0.000E+00 1.340E+08 0.000E+00 2.910E+08 I-132 1.970E-01 5.270E-01 1.840E+01 8.400E-01 0.000E+00 9.900E-02 0.000E+00 1.840E-01 I-133 4.640E+06 8.080E+06 1.190E+09 1.410E+07 0.000E+00 7.260E+06 0.000E+00 2.460E+06 I-134 2.420E-12 6.570E-12 1.140E-10 1.050E-11 0.000E+00 5.730E-15 0.000E+00 2.350E-12 I-135 1.540E+04 4.030E+04 2.660E+06 6.470E+04 0.000E+00 4.560E+04 0.000E+00 1.490E+04 CS-134 1.700E+10 4.040E+10 0.000E+00 1.310E+10 4.340E+09 7.060E+08 0.000E+00 3.300E+10 CS-136 7.900E+08 3.120E+09 0.000E+00 1.730E+09 2.380E+08 3.540E+08 0.000E+00 2.240E+09 CS-137 2.210E+10 3.030E+10 0.000E+00 1.030E+10 3.420E+09 5.860E+08 0.000E+00 1.980E+10 CS-138 2.710E-23 5.360E-23 0.000E+00 3.940E-23 3.890E-24 2.290E-28 0.000E+00 2.650E-23 BA-139 5.300E-09 3.780E-12 0.000E+00 3.530E-12 2.140E-12 9.400E-09 0.000E+00 1.550E-10 BA-140 3.230E+06 4.050E+03 0.000E+00 1.380E+03 2.320E+03 6.640E+06 0.000E+00 2.110E+05 BA-141 4.910E-47 3.710E-50 0.000E+00 3.450E-50 2.110E-50 2.310E-56 0.000E+00 1.660E-48 BA-142 3.170E-81 3.260E-84 0.000E+00 2.750E-84 1.850E-84 0.000E+00 0.000E+00 2.000E-82 LA-140 5.410E-01 2.730E-01 0.000E+00 0.000E+00 0.000E+00 2.000E+04 0.000E+00 7.210E-02 LA-142 2.230E-12 1.010E-12 0.000E+00 0.000E+00 0.000E+00 7.410E-09 0.000E+00 2.530E-13 CE-141 5.810E+02 3.930E+02 0.000E+00 1.830E+02 0.000E+00 1.500E+06 0.000E+00 4.460E+01 CE-143 4.990E+00 3.690E+03 0.000E+00 1.620E+00 0.000E+00 1.380E+05 0.000E+00 4.080E-01 CE-144 4.290E+04 1.790E+04 0.000E+00 1.060E+04 0.000E+00 1.450E+07 0.000E+00 2.300E+03 PR-143 1.890E+01 7.600E+00 0.000E+00 4.390E+00 0.000E+00 8.300E+04 0.000E+00 9.390E-01 PR-144 7.050E-55 2.930E-55 0.000E+00 1.650E-55 0.000E+00 1.010E-61 0.000E+00 3.580E-56 ND-147 1.130E+01 1.310E+01 0.000E+00 7.630E+00 0.000E+00 6.270E+04 0.000E+00 7.810E-01 W-187 7.820E+02 6.530E+02 0.000E+00 0.000E+00 0.000E+00 2.140E+05 0.000E+00 2.280E+02 NP-239 4.410E-01 4.330E-02 0.000E+00 1.350E-01 0.000E+00 8.890E+03 0.000E+00 2.390E-02 Appendix G Ri Adult Goat Milk - Page 3 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX G Ri Adult Dose Factors for use in the Gaseous Dose Calculations Agegroup: ADULT Pathway: Grs/Cow/Meat (CMEAT) Units: m2*mrem/yr / Ci/sec; mrem/yr / Ci/m3 (H-3)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body H-3 0.000E+00 3.250E+02 3.250E+02 3.250E+02 3.250E+02 3.250E+02 0.000E+00 3.250E+02 C-14 2.410E+08 4.830E+07 4.830E+07 4.830E+07 4.830E+07 4.830E+07 0.000E+00 4.830E+07 NA-24 1.360E-03 1.360E-03 1.360E-03 1.360E-03 1.360E-03 1.360E-03 0.000E+00 1.360E-03 P-32 4.660E+09 2.900E+08 0.000E+00 0.000E+00 0.000E+00 5.240E+08 0.000E+00 1.800E+08 CR-51 0.000E+00 0.000E+00 4.210E+03 1.550E+03 9.350E+03 1.770E+06 0.000E+00 7.050E+03 MN-54 0.000E+00 9.180E+06 0.000E+00 2.730E+06 0.000E+00 2.810E+07 0.000E+00 1.750E+06 MN-56 0.000E+00 1.320E-53 0.000E+00 1.680E-53 0.000E+00 4.220E-52 0.000E+00 2.350E-54 FE-55 2.930E+08 2.030E+08 0.000E+00 0.000E+00 1.130E+08 1.160E+08 0.000E+00 4.720E+07 FE-59 2.660E+08 6.240E+08 0.000E+00 0.000E+00 1.740E+08 2.080E+09 0.000E+00 2.390E+08 CO-58 0.000E+00 1.820E+07 0.000E+00 0.000E+00 0.000E+00 3.690E+08 0.000E+00 4.090E+07 CO-60 0.000E+00 7.520E+07 0.000E+00 0.000E+00 0.000E+00 1.410E+09 0.000E+00 1.660E+08 NI-63 1.890E+10 1.310E+09 0.000E+00 0.000E+00 0.000E+00 2.730E+08 0.000E+00 6.330E+08 NI-65 2.250E-52 2.920E-53 0.000E+00 0.000E+00 0.000E+00 7.400E-52 0.000E+00 1.330E-53 CU-64 0.000E+00 2.710E-07 0.000E+00 6.830E-07 0.000E+00 2.310E-05 0.000E+00 1.270E-07 ZN-65 3.560E+08 1.130E+09 0.000E+00 7.570E+08 0.000E+00 7.130E+08 0.000E+00 5.120E+08 ZN-69 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-83 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 8.650E-57 0.000E+00 6.000E-57 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 0.000E+00 4.870E+08 0.000E+00 0.000E+00 0.000E+00 9.600E+07 0.000E+00 2.270E+08 RB-88 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-89 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 SR-89 3.020E+08 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4.840E+07 0.000E+00 8.660E+06 SR-90 1.240E+10 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.590E+08 0.000E+00 3.050E+09 SR-91 1.520E-10 0.000E+00 0.000E+00 0.000E+00 0.000E+00 7.240E-10 0.000E+00 6.140E-12 Appendix G Ri Adult Cow Meat - Page 1 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX G Ri Adult Dose Factors for use in the Gaseous Dose Calculations Agegroup: ADULT Pathway: Grs/Cow/Meat (CMEAT) Units: m2*mrem/yr / Ci/sec; mrem/yr / Ci/m3 (H-3)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body SR-92 1.180E-49 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.340E-48 0.000E+00 5.100E-51 Y-90 1.080E+02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.140E+06 0.000E+00 2.890E+00 Y-91 1.130E+06 0.000E+00 0.000E+00 0.000E+00 0.000E+00 6.230E+08 0.000E+00 3.030E+04 Y-91M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Y-92 1.520E-39 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.660E-35 0.000E+00 4.430E-41 Y-93 4.690E-12 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.490E-07 0.000E+00 1.300E-13 ZR-95 1.870E+06 6.010E+05 0.000E+00 9.420E+05 0.000E+00 1.900E+09 0.000E+00 4.070E+05 ZR-97 2.070E-05 4.170E-06 0.000E+00 6.300E-06 0.000E+00 1.290E+00 0.000E+00 1.910E-06 NB-95 2.300E+06 1.280E+06 0.000E+00 1.260E+06 0.000E+00 7.760E+09 0.000E+00 6.870E+05 MO-99 0.000E+00 1.000E+05 0.000E+00 2.260E+05 0.000E+00 2.320E+05 0.000E+00 1.900E+04 TC-99M 4.450E-21 1.260E-20 0.000E+00 1.910E-19 6.150E-21 7.430E-18 0.000E+00 1.600E-19 TC-101 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RU-103 1.050E+08 0.000E+00 0.000E+00 4.010E+08 0.000E+00 1.230E+10 0.000E+00 4.530E+07 RU-105 5.780E-28 0.000E+00 0.000E+00 7.460E-27 0.000E+00 3.530E-25 0.000E+00 2.280E-28 RU-106 2.800E+09 0.000E+00 0.000E+00 5.400E+09 0.000E+00 1.810E+11 0.000E+00 3.540E+08 AG-110M 6.680E+06 6.180E+06 0.000E+00 1.220E+07 0.000E+00 2.520E+09 0.000E+00 3.670E+06 TE-125M 3.590E+08 1.300E+08 1.080E+08 1.460E+09 0.000E+00 1.430E+09 0.000E+00 4.810E+07 TE-127 2.120E-10 7.610E-11 1.570E-10 8.640E-10 0.000E+00 1.670E-08 0.000E+00 4.590E-11 TE-127M 1.120E+09 3.990E+08 2.850E+08 4.530E+09 0.000E+00 3.740E+09 0.000E+00 1.360E+08 TE-129 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 TE-129M 1.130E+09 4.230E+08 3.900E+08 4.730E+09 0.000E+00 5.710E+09 0.000E+00 1.790E+08 TE-131 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 TE-131M 4.510E+02 2.210E+02 3.490E+02 2.230E+03 0.000E+00 2.190E+04 0.000E+00 1.840E+02 TE-132 1.420E+06 9.180E+05 1.010E+06 8.840E+06 0.000E+00 4.340E+07 0.000E+00 8.620E+05 I-130 2.110E-06 6.220E-06 5.270E-04 9.700E-06 0.000E+00 5.350E-06 0.000E+00 2.450E-06 Appendix G Ri Adult Cow Meat - Page 2 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX G Ri Adult Dose Factors for use in the Gaseous Dose Calculations Agegroup: ADULT Pathway: Grs/Cow/Meat (CMEAT) Units: m2*mrem/yr / Ci/sec; mrem/yr / Ci/m3 (H-3)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body I-131 1.070E+07 1.540E+07 5.030E+09 2.630E+07 0.000E+00 4.050E+06 0.000E+00 8.800E+06 I-132 6.970E-59 1.860E-58 6.530E-57 2.970E-58 0.000E+00 3.500E-59 0.000E+00 6.530E-59 I-133 3.650E-01 6.350E-01 9.340E+01 1.110E+00 0.000E+00 5.710E-01 0.000E+00 1.940E-01 I-134 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 I-135 4.420E-17 1.160E-16 7.640E-15 1.860E-16 0.000E+00 1.310E-16 0.000E+00 4.270E-17 CS-134 6.580E+08 1.560E+09 0.000E+00 5.060E+08 1.680E+08 2.740E+07 0.000E+00 1.280E+09 CS-136 1.210E+07 4.760E+07 0.000E+00 2.650E+07 3.630E+06 5.410E+06 0.000E+00 3.420E+07 CS-137 8.720E+08 1.190E+09 0.000E+00 4.050E+08 1.350E+08 2.310E+07 0.000E+00 7.810E+08 CS-138 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BA-139 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BA-140 2.870E+07 3.610E+04 0.000E+00 1.230E+04 2.070E+04 5.920E+07 0.000E+00 1.880E+06 BA-141 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BA-142 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 LA-140 3.710E-02 1.870E-02 0.000E+00 0.000E+00 0.000E+00 1.370E+03 0.000E+00 4.940E-03 LA-142 3.470E-92 1.580E-92 0.000E+00 0.000E+00 0.000E+00 1.150E-88 0.000E+00 3.940E-93 CE-141 1.400E+04 9.500E+03 0.000E+00 4.410E+03 0.000E+00 3.630E+07 0.000E+00 1.080E+03 CE-143 2.010E-02 1.480E+01 0.000E+00 6.530E-03 0.000E+00 5.550E+02 0.000E+00 1.640E-03 CE-144 1.460E+06 6.090E+05 0.000E+00 3.610E+05 0.000E+00 4.930E+08 0.000E+00 7.830E+04 PR-143 2.100E+04 8.410E+03 0.000E+00 4.850E+03 0.000E+00 9.180E+07 0.000E+00 1.040E+03 PR-144 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 ND-147 7.070E+03 8.170E+03 0.000E+00 4.780E+03 0.000E+00 3.920E+07 0.000E+00 4.890E+02 W-187 2.070E-02 1.730E-02 0.000E+00 0.000E+00 0.000E+00 5.660E+00 0.000E+00 6.040E-03 NP-239 2.590E-01 2.550E-02 0.000E+00 7.950E-02 0.000E+00 5.230E+03 0.000E+00 1.400E-02 Appendix G Ri Adult Cow Meat - Page 3 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX G Ri Adult Dose Factors for use in the Gaseous Dose Calculations Agegroup: ADULT Pathway: Vegetation (VEG) Units: m2*mrem/yr / Ci/sec; mrem/yr / Ci/m3 (H-3)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body H-3 0.000E+00 2.260E+03 2.260E+03 2.260E+03 2.260E+03 2.260E+03 0.000E+00 2.260E+03 C-14 2.280E+08 4.550E+07 4.550E+07 4.550E+07 4.550E+07 4.550E+07 0.000E+00 4.550E+07 NA-24 2.690E+05 2.690E+05 2.690E+05 2.690E+05 2.690E+05 2.690E+05 0.000E+00 2.690E+05 P-32 1.400E+09 8.730E+07 0.000E+00 0.000E+00 0.000E+00 1.580E+08 0.000E+00 5.430E+07 CR-51 0.000E+00 0.000E+00 2.780E+04 1.020E+04 6.160E+04 1.170E+07 0.000E+00 4.640E+04 MN-54 0.000E+00 3.130E+08 0.000E+00 9.310E+07 0.000E+00 9.590E+08 0.000E+00 5.970E+07 MN-56 0.000E+00 1.580E+01 0.000E+00 2.000E+01 0.000E+00 5.040E+02 0.000E+00 2.800E+00 FE-55 2.100E+08 1.450E+08 0.000E+00 0.000E+00 8.080E+07 8.310E+07 0.000E+00 3.380E+07 FE-59 1.260E+08 2.960E+08 0.000E+00 0.000E+00 8.280E+07 9.880E+08 0.000E+00 1.140E+08 CO-58 0.000E+00 3.070E+07 0.000E+00 0.000E+00 0.000E+00 6.230E+08 0.000E+00 6.890E+07 CO-60 0.000E+00 1.670E+08 0.000E+00 0.000E+00 0.000E+00 3.140E+09 0.000E+00 3.690E+08 NI-63 1.040E+10 7.210E+08 0.000E+00 0.000E+00 0.000E+00 1.500E+08 0.000E+00 3.490E+08 NI-65 6.150E+01 7.990E+00 0.000E+00 0.000E+00 0.000E+00 2.030E+02 0.000E+00 3.640E+00 CU-64 0.000E+00 9.200E+03 0.000E+00 2.320E+04 0.000E+00 7.840E+05 0.000E+00 4.320E+03 ZN-65 3.170E+08 1.010E+09 0.000E+00 6.750E+08 0.000E+00 6.360E+08 0.000E+00 4.560E+08 ZN-69 5.490E-06 1.050E-05 0.000E+00 6.830E-06 0.000E+00 1.580E-06 0.000E+00 7.310E-07 BR-83 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4.470E+00 0.000E+00 3.110E+00 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.940E-16 0.000E+00 2.480E-11 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 0.000E+00 2.190E+08 0.000E+00 0.000E+00 0.000E+00 4.330E+07 0.000E+00 1.020E+08 RB-88 0.000E+00 3.430E-22 0.000E+00 0.000E+00 0.000E+00 4.740E-33 0.000E+00 1.820E-22 RB-89 0.000E+00 3.890E-26 0.000E+00 0.000E+00 0.000E+00 2.260E-39 0.000E+00 2.730E-26 SR-89 9.970E+09 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.600E+09 0.000E+00 2.860E+08 SR-90 6.050E+11 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.750E+10 0.000E+00 1.480E+11 SR-91 3.050E+05 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.450E+06 0.000E+00 1.230E+04 Appendix G Ri Adult Vegetation - Page 1 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX G Ri Adult Dose Factors for use in the Gaseous Dose Calculations Agegroup: ADULT Pathway: Vegetation (VEG) Units: m2*mrem/yr / Ci/sec; mrem/yr / Ci/m3 (H-3)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body SR-92 4.270E+02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 8.450E+03 0.000E+00 1.850E+01 Y-90 1.330E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.410E+08 0.000E+00 3.570E+02 Y-91 5.110E+06 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.810E+09 0.000E+00 1.370E+05 Y-91M 5.220E-09 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.530E-08 0.000E+00 2.020E-10 Y-92 9.150E-01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.600E+04 0.000E+00 2.680E-02 Y-93 1.700E+02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.380E+06 0.000E+00 4.680E+00 ZR-95 1.170E+06 3.770E+05 0.000E+00 5.910E+05 0.000E+00 1.190E+09 0.000E+00 2.550E+05 ZR-97 3.370E+02 6.810E+01 0.000E+00 1.030E+02 0.000E+00 2.110E+07 0.000E+00 3.110E+01 NB-95 1.420E+05 7.920E+04 0.000E+00 7.830E+04 0.000E+00 4.810E+08 0.000E+00 4.260E+04 MO-99 0.000E+00 6.150E+06 0.000E+00 1.390E+07 0.000E+00 1.430E+07 0.000E+00 1.170E+06 TC-99M 3.100E+00 8.770E+00 0.000E+00 1.330E+02 4.300E+00 5.190E+03 0.000E+00 1.120E+02 TC-101 8.220E-31 1.180E-30 0.000E+00 2.130E-29 6.050E-31 3.560E-42 0.000E+00 1.160E-29 RU-103 4.770E+06 0.000E+00 0.000E+00 1.820E+07 0.000E+00 5.570E+08 0.000E+00 2.060E+06 RU-105 5.390E+01 0.000E+00 0.000E+00 6.960E+02 0.000E+00 3.290E+04 0.000E+00 2.130E+01 RU-106 1.930E+08 0.000E+00 0.000E+00 3.720E+08 0.000E+00 1.250E+10 0.000E+00 2.440E+07 AG-110M 1.050E+07 9.750E+06 0.000E+00 1.920E+07 0.000E+00 3.980E+09 0.000E+00 5.790E+06 TE-125M 9.660E+07 3.500E+07 2.900E+07 3.930E+08 0.000E+00 3.860E+08 0.000E+00 1.290E+07 TE-127 5.660E+03 2.030E+03 4.190E+03 2.310E+04 0.000E+00 4.470E+05 0.000E+00 1.220E+03 TE-127M 3.490E+08 1.250E+08 8.920E+07 1.420E+09 0.000E+00 1.170E+09 0.000E+00 4.260E+07 TE-129 7.630E-04 2.870E-04 5.850E-04 3.210E-03 0.000E+00 5.760E-04 0.000E+00 1.860E-04 TE-129M 2.510E+08 9.380E+07 8.630E+07 1.050E+09 0.000E+00 1.270E+09 0.000E+00 3.980E+07 TE-131 1.500E-15 6.270E-16 1.230E-15 6.570E-15 0.000E+00 2.130E-16 0.000E+00 4.740E-16 TE-131M 9.120E+05 4.460E+05 7.060E+05 4.520E+06 0.000E+00 4.430E+07 0.000E+00 3.720E+05 TE-132 4.300E+06 2.780E+06 3.070E+06 2.680E+07 0.000E+00 1.320E+08 0.000E+00 2.610E+06 I-130 3.920E+05 1.160E+06 9.810E+07 1.810E+06 0.000E+00 9.960E+05 0.000E+00 4.570E+05 Appendix G Ri Adult Vegetation - Page 2 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX G Ri Adult Dose Factors for use in the Gaseous Dose Calculations Agegroup: ADULT Pathway: Vegetation (VEG) Units: m2*mrem/yr / Ci/sec; mrem/yr / Ci/m3 (H-3)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body I-131 8.080E+07 1.160E+08 3.790E+10 1.980E+08 0.000E+00 3.050E+07 0.000E+00 6.620E+07 I-132 5.760E+01 1.540E+02 5.390E+03 2.450E+02 0.000E+00 2.890E+01 0.000E+00 5.390E+01 I-133 2.090E+06 3.630E+06 5.330E+08 6.330E+06 0.000E+00 3.260E+06 0.000E+00 1.110E+06 I-134 9.650E-05 2.620E-04 4.540E-03 4.170E-04 0.000E+00 2.290E-07 0.000E+00 9.380E-05 I-135 3.900E+04 1.020E+05 6.730E+06 1.640E+05 0.000E+00 1.150E+05 0.000E+00 3.770E+04 CS-134 4.670E+09 1.110E+10 0.000E+00 3.590E+09 1.190E+09 1.940E+08 0.000E+00 9.080E+09 CS-136 4.270E+07 1.680E+08 0.000E+00 9.380E+07 1.290E+07 1.910E+07 0.000E+00 1.210E+08 CS-137 6.360E+09 8.700E+09 0.000E+00 2.950E+09 9.810E+08 1.680E+08 0.000E+00 5.700E+09 CS-138 3.920E-11 7.730E-11 0.000E+00 5.680E-11 5.610E-12 3.300E-16 0.000E+00 3.830E-11 BA-139 2.860E-02 2.030E-05 0.000E+00 1.900E-05 1.150E-05 5.060E-02 0.000E+00 8.360E-04 BA-140 1.280E+08 1.610E+05 0.000E+00 5.490E+04 9.240E+04 2.650E+08 0.000E+00 8.420E+06 BA-141 1.150E-21 8.700E-25 0.000E+00 8.090E-25 4.940E-25 5.430E-31 0.000E+00 3.890E-23 BA-142 5.960E-39 6.120E-42 0.000E+00 5.170E-42 3.470E-42 8.390E-57 0.000E+00 3.750E-40 LA-140 1.980E+03 9.970E+02 0.000E+00 0.000E+00 0.000E+00 7.320E+07 0.000E+00 2.630E+02 LA-142 2.020E-04 9.190E-05 0.000E+00 0.000E+00 0.000E+00 6.710E-01 0.000E+00 2.290E-05 CE-141 1.970E+05 1.330E+05 0.000E+00 6.190E+04 0.000E+00 5.100E+08 0.000E+00 1.510E+04 CE-143 9.980E+02 7.380E+05 0.000E+00 3.250E+02 0.000E+00 2.760E+07 0.000E+00 8.160E+01 CE-144 3.290E+07 1.380E+07 0.000E+00 8.160E+06 0.000E+00 1.110E+10 0.000E+00 1.770E+06 PR-143 6.260E+04 2.510E+04 0.000E+00 1.450E+04 0.000E+00 2.740E+08 0.000E+00 3.100E+03 PR-144 3.090E-26 1.280E-26 0.000E+00 7.230E-27 0.000E+00 4.440E-33 0.000E+00 1.570E-27 ND-147 3.330E+04 3.850E+04 0.000E+00 2.250E+04 0.000E+00 1.850E+08 0.000E+00 2.310E+03 W-187 3.800E+04 3.180E+04 0.000E+00 0.000E+00 0.000E+00 1.040E+07 0.000E+00 1.110E+04 NP-239 1.430E+03 1.400E+02 0.000E+00 4.380E+02 0.000E+00 2.880E+07 0.000E+00 7.740E+01 Appendix G Ri Adult Vegetation - Page 3 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX G Ri Adult Dose Factors for use in the Gaseous Dose Calculations Agegroup: ADULT Pathway: Inhalation (INHL) Units:

mrem/yr / Ci/m3 Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body H-3 0.000E+00 1.260E+03 1.260E+03 1.260E+03 1.260E+03 1.260E+03 0.000E+00 1.260E+03 C-14 1.820E+04 3.410E+03 3.410E+03 3.410E+03 3.410E+03 3.410E+03 0.000E+00 3.410E+03 NA-24 1.020E+04 1.020E+04 1.020E+04 1.020E+04 1.020E+04 1.020E+04 0.000E+00 1.020E+04 P-32 1.320E+06 7.710E+04 0.000E+00 0.000E+00 0.000E+00 8.640E+04 0.000E+00 5.010E+04 CR-51 0.000E+00 0.000E+00 5.950E+01 2.280E+01 1.440E+04 3.320E+03 0.000E+00 1.000E+02 MN-54 0.000E+00 3.960E+04 0.000E+00 9.840E+03 1.400E+06 7.740E+04 0.000E+00 6.300E+03 MN-56 0.000E+00 1.240E+00 0.000E+00 1.300E+00 9.440E+03 2.020E+04 0.000E+00 1.830E-01 FE-55 2.460E+04 1.700E+04 0.000E+00 0.000E+00 7.210E+04 6.030E+03 0.000E+00 3.940E+03 FE-59 1.180E+04 2.780E+04 0.000E+00 0.000E+00 1.020E+06 1.880E+05 0.000E+00 1.060E+04 CO-58 0.000E+00 1.580E+03 0.000E+00 0.000E+00 9.280E+05 1.060E+05 0.000E+00 2.070E+03 CO-60 0.000E+00 1.150E+04 0.000E+00 0.000E+00 5.970E+06 2.850E+05 0.000E+00 1.480E+04 NI-63 4.320E+05 3.140E+04 0.000E+00 0.000E+00 1.780E+05 1.340E+04 0.000E+00 1.450E+04 NI-65 1.540E+00 2.100E-01 0.000E+00 0.000E+00 5.600E+03 1.230E+04 0.000E+00 9.120E-02 CU-64 0.000E+00 1.460E+00 0.000E+00 4.620E+00 6.780E+03 4.900E+04 0.000E+00 6.150E-01 ZN-65 3.240E+04 1.030E+05 0.000E+00 6.900E+04 8.640E+05 5.340E+04 0.000E+00 4.660E+04 ZN-69 3.380E-02 6.510E-02 0.000E+00 4.220E-02 9.200E+02 1.630E+01 0.000E+00 4.520E-03 BR-83 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.320E+02 0.000E+00 2.410E+02 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.640E-03 0.000E+00 3.130E+02 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.280E+01 RB-86 0.000E+00 1.350E+05 0.000E+00 0.000E+00 0.000E+00 1.660E+04 0.000E+00 5.900E+04 RB-88 0.000E+00 3.870E+02 0.000E+00 0.000E+00 0.000E+00 3.340E-09 0.000E+00 1.930E+02 RB-89 0.000E+00 2.560E+02 0.000E+00 0.000E+00 0.000E+00 9.280E-12 0.000E+00 1.700E+02 SR-89 3.040E+05 0.000E+00 0.000E+00 0.000E+00 1.400E+06 3.500E+05 0.000E+00 8.720E+03 SR-90 9.920E+07 0.000E+00 0.000E+00 0.000E+00 9.600E+06 7.220E+05 0.000E+00 6.100E+06 SR-91 6.190E+01 0.000E+00 0.000E+00 0.000E+00 3.650E+04 1.910E+05 0.000E+00 2.500E+00 Appendix G Ri Adult Inhalation - Page 1 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX G Ri Adult Dose Factors for use in the Gaseous Dose Calculations Agegroup: ADULT Pathway: Inhalation (INHL) Units:

mrem/yr / Ci/m3 Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body SR-92 6.740E+00 0.000E+00 0.000E+00 0.000E+00 1.650E+04 4.300E+04 0.000E+00 2.910E-01 Y-90 2.090E+03 0.000E+00 0.000E+00 0.000E+00 1.700E+05 5.060E+05 0.000E+00 5.610E+01 Y-91 4.620E+05 0.000E+00 0.000E+00 0.000E+00 1.700E+06 3.850E+05 0.000E+00 1.240E+04 Y-91M 2.610E-01 0.000E+00 0.000E+00 0.000E+00 1.920E+03 1.330E+00 0.000E+00 1.020E-02 Y-92 1.030E+01 0.000E+00 0.000E+00 0.000E+00 1.570E+04 7.350E+04 0.000E+00 3.020E-01 Y-93 9.440E+01 0.000E+00 0.000E+00 0.000E+00 4.850E+04 4.220E+05 0.000E+00 2.610E+00 ZR-95 1.070E+05 3.440E+04 0.000E+00 5.420E+04 1.770E+06 1.500E+05 0.000E+00 2.330E+04 ZR-97 9.680E+01 1.960E+01 0.000E+00 2.970E+01 7.870E+04 5.230E+05 0.000E+00 9.040E+00 NB-95 1.410E+04 7.820E+03 0.000E+00 7.740E+03 5.050E+05 1.040E+05 0.000E+00 4.210E+03 MO-99 0.000E+00 1.210E+02 0.000E+00 2.910E+02 9.120E+04 2.480E+05 0.000E+00 2.300E+01 TC-99M 1.030E-03 2.910E-03 0.000E+00 4.420E-02 7.640E+02 4.160E+03 0.000E+00 3.700E-02 TC-101 4.180E-05 6.020E-05 0.000E+00 1.080E-03 3.990E+02 1.090E-11 0.000E+00 5.900E-04 RU-103 1.530E+03 0.000E+00 0.000E+00 5.830E+03 5.050E+05 1.100E+05 0.000E+00 6.580E+02 RU-105 7.900E-01 0.000E+00 0.000E+00 1.020E+00 1.100E+04 4.820E+04 0.000E+00 3.110E-01 RU-106 6.910E+04 0.000E+00 0.000E+00 1.340E+05 9.360E+06 9.120E+05 0.000E+00 8.720E+03 AG-110M 1.080E+04 1.000E+04 0.000E+00 1.970E+04 4.630E+06 3.020E+05 0.000E+00 5.940E+03 TE-125M 3.420E+03 1.580E+03 1.050E+03 1.240E+04 3.140E+05 7.060E+04 0.000E+00 4.670E+02 TE-127 1.400E+00 6.420E-01 1.060E+00 5.100E+00 6.510E+03 5.740E+04 0.000E+00 3.100E-01 TE-127M 1.260E+04 5.770E+03 3.290E+03 4.580E+04 9.600E+05 1.500E+05 0.000E+00 1.570E+03 TE-129 4.980E-02 2.390E-02 3.900E-02 1.870E-01 1.940E+03 1.570E+02 0.000E+00 1.240E-02 TE-129M 9.760E+03 4.670E+03 3.440E+03 3.660E+04 1.160E+06 3.830E+05 0.000E+00 1.580E+03 TE-131 1.110E-02 5.950E-03 9.360E-03 4.370E-02 1.390E+03 1.840E+01 0.000E+00 3.590E-03 TE-131M 6.990E+01 4.360E+01 5.500E+01 3.090E+02 1.460E+05 5.560E+05 0.000E+00 2.900E+01 TE-132 2.600E+02 2.150E+02 1.900E+02 1.460E+03 2.880E+05 5.100E+05 0.000E+00 1.620E+02 I-130 4.580E+03 1.340E+04 1.140E+06 2.090E+04 0.000E+00 7.690E+03 0.000E+00 5.280E+03 Appendix G Ri Adult Inhalation - Page 2 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX G Ri Adult Dose Factors for use in the Gaseous Dose Calculations Agegroup: ADULT Pathway: Inhalation (INHL) Units:

mrem/yr / Ci/m3 Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body I-131 2.520E+04 3.580E+04 1.190E+07 6.130E+04 0.000E+00 6.280E+03 0.000E+00 2.050E+04 I-132 1.160E+03 3.260E+03 1.140E+05 5.180E+03 0.000E+00 4.060E+02 0.000E+00 1.160E+03 I-133 8.640E+03 1.480E+04 2.150E+06 2.580E+04 0.000E+00 8.880E+03 0.000E+00 4.520E+03 I-134 6.440E+02 1.730E+03 2.980E+04 2.750E+03 0.000E+00 1.010E+00 0.000E+00 6.150E+02 I-135 2.680E+03 6.980E+03 4.480E+05 1.110E+04 0.000E+00 5.250E+03 0.000E+00 2.570E+03 CS-134 3.730E+05 8.480E+05 0.000E+00 2.870E+05 9.760E+04 1.040E+04 0.000E+00 7.280E+05 CS-136 3.900E+04 1.460E+05 0.000E+00 8.560E+04 1.200E+04 1.170E+04 0.000E+00 1.100E+05 CS-137 4.780E+05 6.210E+05 0.000E+00 2.220E+05 7.520E+04 8.400E+03 0.000E+00 4.280E+05 CS-138 3.310E+02 6.210E+02 0.000E+00 4.800E+02 4.860E+01 1.860E-03 0.000E+00 3.240E+02 BA-139 9.360E-01 6.660E-04 0.000E+00 6.220E-04 3.760E+03 8.960E+02 0.000E+00 2.740E-02 BA-140 3.900E+04 4.900E+01 0.000E+00 1.670E+01 1.270E+06 2.180E+05 0.000E+00 2.570E+03 BA-141 1.000E-01 7.530E-05 0.000E+00 7.000E-05 1.940E+03 1.160E-07 0.000E+00 3.360E-03 BA-142 2.630E-02 2.700E-05 0.000E+00 2.290E-05 1.190E+03 1.570E-16 0.000E+00 1.660E-03 LA-140 3.440E+02 1.740E+02 0.000E+00 0.000E+00 1.360E+05 4.580E+05 0.000E+00 4.580E+01 LA-142 6.830E-01 3.100E-01 0.000E+00 0.000E+00 6.330E+03 2.110E+03 0.000E+00 7.720E-02 CE-141 1.990E+04 1.350E+04 0.000E+00 6.260E+03 3.620E+05 1.200E+05 0.000E+00 1.530E+03 CE-143 1.860E+02 1.380E+02 0.000E+00 6.080E+01 7.980E+04 2.260E+05 0.000E+00 1.530E+01 CE-144 3.430E+06 1.430E+06 0.000E+00 8.480E+05 7.780E+06 8.160E+05 0.000E+00 1.840E+05 PR-143 9.360E+03 3.750E+03 0.000E+00 2.160E+03 2.810E+05 2.000E+05 0.000E+00 4.640E+02 PR-144 3.010E-02 1.250E-02 0.000E+00 7.050E-03 1.020E+03 2.150E-08 0.000E+00 1.530E-03 ND-147 5.270E+03 6.100E+03 0.000E+00 3.560E+03 2.210E+05 1.730E+05 0.000E+00 3.650E+02 W-187 8.480E+00 7.080E+00 0.000E+00 0.000E+00 2.900E+04 1.550E+05 0.000E+00 2.480E+00 NP-239 2.300E+02 2.260E+01 0.000E+00 7.000E+01 3.760E+04 1.190E+05 0.000E+00 1.240E+01 Appendix G Ri Adult Inhalation - Page 3 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX G Ri Adult Dose Factors for use in the Gaseous Dose Calculations Agegroup: ADULT Pathway: Ground Plane Deposition (GPD) Units: m2*mrem/yr / Ci/sec Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body H-3 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 C-14 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 NA-24 1.190E+07 1.190E+07 1.190E+07 1.190E+07 1.190E+07 1.190E+07 1.390E+07 1.190E+07 P-32 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 CR-51 4.660E+06 4.660E+06 4.660E+06 4.660E+06 4.660E+06 4.660E+06 5.510E+06 4.660E+06 MN-54 1.390E+09 1.390E+09 1.390E+09 1.390E+09 1.390E+09 1.390E+09 1.630E+09 1.390E+09 MN-56 9.020E+05 9.020E+05 9.020E+05 9.020E+05 9.020E+05 9.020E+05 1.070E+06 9.020E+05 FE-55 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 FE-59 2.730E+08 2.730E+08 2.730E+08 2.730E+08 2.730E+08 2.730E+08 3.210E+08 2.730E+08 CO-58 3.790E+08 3.790E+08 3.790E+08 3.790E+08 3.790E+08 3.790E+08 4.440E+08 3.790E+08 CO-60 2.150E+10 2.150E+10 2.150E+10 2.150E+10 2.150E+10 2.150E+10 2.530E+10 2.150E+10 NI-63 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 NI-65 2.970E+05 2.970E+05 2.970E+05 2.970E+05 2.970E+05 2.970E+05 3.450E+05 2.970E+05 CU-64 6.070E+05 6.070E+05 6.070E+05 6.070E+05 6.070E+05 6.070E+05 6.880E+05 6.070E+05 ZN-65 7.470E+08 7.470E+08 7.470E+08 7.470E+08 7.470E+08 7.470E+08 8.590E+08 7.470E+08 ZN-69 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-83 4.870E+03 4.870E+03 4.870E+03 4.870E+03 4.870E+03 4.870E+03 7.080E+03 4.870E+03 BR-84 2.030E+05 2.030E+05 2.030E+05 2.030E+05 2.030E+05 2.030E+05 2.360E+05 2.030E+05 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 8.990E+06 8.990E+06 8.990E+06 8.990E+06 8.990E+06 8.990E+06 1.030E+07 8.990E+06 RB-88 3.310E+04 3.310E+04 3.310E+04 3.310E+04 3.310E+04 3.310E+04 3.780E+04 3.310E+04 RB-89 1.230E+05 1.230E+05 1.230E+05 1.230E+05 1.230E+05 1.230E+05 1.480E+05 1.230E+05 SR-89 2.160E+04 2.160E+04 2.160E+04 2.160E+04 2.160E+04 2.160E+04 2.510E+04 2.160E+04 SR-90 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 SR-91 2.150E+06 2.150E+06 2.150E+06 2.150E+06 2.150E+06 2.150E+06 2.510E+06 2.150E+06 Appendix G Ri Adult Ground Plane Deposition - Page 1 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX G Ri Adult Dose Factors for use in the Gaseous Dose Calculations Agegroup: ADULT Pathway: Ground Plane Deposition (GPD) Units: m2*mrem/yr / Ci/sec Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body SR-92 7.770E+05 7.770E+05 7.770E+05 7.770E+05 7.770E+05 7.770E+05 8.630E+05 7.770E+05 Y-90 4.490E+03 4.490E+03 4.490E+03 4.490E+03 4.490E+03 4.490E+03 5.310E+03 4.490E+03 Y-91 1.070E+06 1.070E+06 1.070E+06 1.070E+06 1.070E+06 1.070E+06 1.210E+06 1.070E+06 Y-91M 1.000E+05 1.000E+05 1.000E+05 1.000E+05 1.000E+05 1.000E+05 1.160E+05 1.000E+05 Y-92 1.800E+05 1.800E+05 1.800E+05 1.800E+05 1.800E+05 1.800E+05 2.140E+05 1.800E+05 Y-93 1.830E+05 1.830E+05 1.830E+05 1.830E+05 1.830E+05 1.830E+05 2.510E+05 1.830E+05 ZR-95 2.450E+08 2.450E+08 2.450E+08 2.450E+08 2.450E+08 2.450E+08 2.840E+08 2.450E+08 ZR-97 2.960E+06 2.960E+06 2.960E+06 2.960E+06 2.960E+06 2.960E+06 3.440E+06 2.960E+06 NB-95 1.370E+08 1.370E+08 1.370E+08 1.370E+08 1.370E+08 1.370E+08 1.610E+08 1.370E+08 MO-99 3.990E+06 3.990E+06 3.990E+06 3.990E+06 3.990E+06 3.990E+06 4.630E+06 3.990E+06 TC-99M 1.840E+05 1.840E+05 1.840E+05 1.840E+05 1.840E+05 1.840E+05 2.110E+05 1.840E+05 TC-101 2.040E+04 2.040E+04 2.040E+04 2.040E+04 2.040E+04 2.040E+04 2.260E+04 2.040E+04 RU-103 1.080E+08 1.080E+08 1.080E+08 1.080E+08 1.080E+08 1.080E+08 1.260E+08 1.080E+08 RU-105 6.360E+05 6.360E+05 6.360E+05 6.360E+05 6.360E+05 6.360E+05 7.210E+05 6.360E+05 RU-106 4.220E+08 4.220E+08 4.220E+08 4.220E+08 4.220E+08 4.220E+08 5.070E+08 4.220E+08 AG-110M 3.440E+09 3.440E+09 3.440E+09 3.440E+09 3.440E+09 3.440E+09 4.010E+09 3.440E+09 TE-125M 1.550E+06 1.550E+06 1.550E+06 1.550E+06 1.550E+06 1.550E+06 2.130E+06 1.550E+06 TE-127 2.980E+03 2.980E+03 2.980E+03 2.980E+03 2.980E+03 2.980E+03 3.280E+03 2.980E+03 TE-127M 9.160E+04 9.160E+04 9.160E+04 9.160E+04 9.160E+04 9.160E+04 1.080E+05 9.160E+04 TE-129 2.620E+04 2.620E+04 2.620E+04 2.620E+04 2.620E+04 2.620E+04 3.100E+04 2.620E+04 TE-129M 1.980E+07 1.980E+07 1.980E+07 1.980E+07 1.980E+07 1.980E+07 2.310E+07 1.980E+07 TE-131 2.920E+04 2.920E+04 2.920E+04 2.920E+04 2.920E+04 2.920E+04 3.450E+07 2.920E+04 TE-131M 8.030E+06 8.030E+06 8.030E+06 8.030E+06 8.030E+06 8.030E+06 9.460E+06 8.030E+06 TE-132 4.230E+06 4.230E+06 4.230E+06 4.230E+06 4.230E+06 4.230E+06 4.980E+06 4.230E+06 I-130 5.510E+06 5.510E+06 5.510E+06 5.510E+06 5.510E+06 5.510E+06 6.690E+06 5.510E+06 Appendix G Ri Adult Ground Plane Deposition - Page 2 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX G Ri Adult Dose Factors for use in the Gaseous Dose Calculations Agegroup: ADULT Pathway: Ground Plane Deposition (GPD) Units: m2*mrem/yr / Ci/sec Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body I-131 1.720E+07 1.720E+07 1.720E+07 1.720E+07 1.720E+07 1.720E+07 2.090E+07 1.720E+07 I-132 1.250E+06 1.250E+06 1.250E+06 1.250E+06 1.250E+06 1.250E+06 1.470E+06 1.250E+06 I-133 2.450E+06 2.450E+06 2.450E+06 2.450E+06 2.450E+06 2.450E+06 2.980E+06 2.450E+06 I-134 4.470E+05 4.470E+05 4.470E+05 4.470E+05 4.470E+05 4.470E+05 5.300E+05 4.470E+05 I-135 2.530E+06 2.530E+06 2.530E+06 2.530E+06 2.530E+06 2.530E+06 2.950E+06 2.530E+06 CS-134 6.860E+09 6.860E+09 6.860E+09 6.860E+09 6.860E+09 6.860E+09 8.000E+09 6.860E+09 CS-136 1.510E+08 1.510E+08 1.510E+08 1.510E+08 1.510E+08 1.510E+08 1.710E+08 1.510E+08 CS-137 1.030E+10 1.030E+10 1.030E+10 1.030E+10 1.030E+10 1.030E+10 1.200E+10 1.030E+10 CS-138 3.590E+05 3.590E+05 3.590E+05 3.590E+05 3.590E+05 3.590E+05 4.100E+05 3.590E+05 BA-139 1.060E+05 1.060E+05 1.060E+05 1.060E+05 1.060E+05 1.060E+05 1.190E+05 1.060E+05 BA-140 2.050E+07 2.050E+07 2.050E+07 2.050E+07 2.050E+07 2.050E+07 2.350E+07 2.050E+07 BA-141 4.170E+04 4.170E+04 4.170E+04 4.170E+04 4.170E+04 4.170E+04 4.750E+04 4.170E+04 BA-142 4.490E+04 4.490E+04 4.490E+04 4.490E+04 4.490E+04 4.490E+04 5.110E+04 4.490E+04 LA-140 1.920E+07 1.920E+07 1.920E+07 1.920E+07 1.920E+07 1.920E+07 2.180E+07 1.920E+07 LA-142 7.600E+05 7.600E+05 7.600E+05 7.600E+05 7.600E+05 7.600E+05 9.120E+05 7.600E+05 CE-141 1.370E+07 1.370E+07 1.370E+07 1.370E+07 1.370E+07 1.370E+07 1.540E+07 1.370E+07 CE-143 2.310E+06 2.310E+06 2.310E+06 2.310E+06 2.310E+06 2.310E+06 2.630E+06 2.310E+06 CE-144 6.950E+07 6.950E+07 6.950E+07 6.950E+07 6.950E+07 6.950E+07 8.040E+07 6.950E+07 PR-143 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 PR-144 1.830E+03 1.830E+03 1.830E+03 1.830E+03 1.830E+03 1.830E+03 2.110E+03 1.830E+03 ND-147 8.390E+06 8.390E+06 8.390E+06 8.390E+06 8.390E+06 8.390E+06 1.010E+07 8.390E+06 W-187 2.350E+06 2.350E+06 2.350E+06 2.350E+06 2.350E+06 2.350E+06 2.730E+06 2.350E+06 NP-239 1.710E+06 1.710E+06 1.710E+06 1.710E+06 1.710E+06 1.710E+06 1.980E+06 1.710E+06 Appendix G Ri Adult Ground Plane Deposition - Page 3 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX H Ri Teen Dose Factors for use in the Gaseous Dose Calculations Agegroup: TEEN Pathway: Grs/Cow/Milk (CMILK) Units: m2*mrem/yr / Ci/sec; mrem/yr / Ci/m3 (H-3)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body H-3 0.000E+00 9.940E+02 9.940E+02 9.940E+02 9.940E+02 9.940E+02 0.000E+00 9.940E+02 C-14 4.860E+08 9.720E+07 9.720E+07 9.720E+07 9.720E+07 9.720E+07 0.000E+00 9.720E+07 NA-24 4.260E+06 4.260E+06 4.260E+06 4.260E+06 4.260E+06 4.260E+06 0.000E+00 4.260E+06 P-32 3.150E+10 1.950E+09 0.000E+00 0.000E+00 0.000E+00 2.650E+09 0.000E+00 1.220E+09 CR-51 0.000E+00 0.000E+00 2.770E+04 1.090E+04 7.130E+04 8.390E+06 0.000E+00 4.990E+04 MN-54 0.000E+00 1.400E+07 0.000E+00 4.180E+06 0.000E+00 2.870E+07 0.000E+00 2.780E+06 MN-56 0.000E+00 7.250E-03 0.000E+00 9.180E-03 0.000E+00 4.770E-01 0.000E+00 1.290E-03 FE-55 4.450E+07 3.160E+07 0.000E+00 0.000E+00 2.000E+07 1.370E+07 0.000E+00 7.360E+06 FE-59 5.180E+07 1.210E+08 0.000E+00 0.000E+00 3.810E+07 2.860E+08 0.000E+00 4.670E+07 CO-58 0.000E+00 7.940E+06 0.000E+00 0.000E+00 0.000E+00 1.090E+08 0.000E+00 1.830E+07 CO-60 0.000E+00 2.780E+07 0.000E+00 0.000E+00 0.000E+00 3.620E+08 0.000E+00 6.260E+07 NI-63 1.180E+10 8.350E+08 0.000E+00 0.000E+00 0.000E+00 1.330E+08 0.000E+00 4.010E+08 NI-65 6.770E-01 8.650E-02 0.000E+00 0.000E+00 0.000E+00 4.690E+00 0.000E+00 3.940E-02 CU-64 0.000E+00 4.250E+04 0.000E+00 1.070E+05 0.000E+00 3.290E+06 0.000E+00 2.000E+04 ZN-65 2.110E+09 7.320E+09 0.000E+00 4.680E+09 0.000E+00 3.100E+09 0.000E+00 3.410E+09 ZN-69 3.850E-12 7.330E-12 0.000E+00 4.790E-12 0.000E+00 1.350E-11 0.000E+00 5.130E-13 BR-83 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.790E-01 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.880E-23 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 0.000E+00 4.730E+09 0.000E+00 0.000E+00 0.000E+00 7.000E+08 0.000E+00 2.220E+09 RB-88 0.000E+00 3.890E-45 0.000E+00 0.000E+00 0.000E+00 3.330E-52 0.000E+00 2.070E-45 RB-89 0.000E+00 7.660E-53 0.000E+00 0.000E+00 0.000E+00 1.170E-61 0.000E+00 5.420E-53 SR-89 2.670E+09 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.190E+08 0.000E+00 7.660E+07 SR-90 6.610E+10 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.860E+09 0.000E+00 1.630E+10 SR-91 5.310E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.410E+05 0.000E+00 2.110E+03 Appendix H Ri Teen Cow Milk - Page 1 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX H Ri Teen Dose Factors for use in the Gaseous Dose Calculations Agegroup: TEEN Pathway: Grs/Cow/Milk (CMILK) Units: m2*mrem/yr / Ci/sec; mrem/yr / Ci/m3 (H-3)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body SR-92 8.940E-01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.280E+01 0.000E+00 3.810E-02 Y-90 1.300E+02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.070E+06 0.000E+00 3.510E+00 Y-91 1.580E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 6.480E+06 0.000E+00 4.240E+02 Y-91M 1.090E-19 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.170E-18 0.000E+00 4.180E-21 Y-92 1.030E-04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.830E+00 0.000E+00 2.980E-06 Y-93 4.120E-01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.260E+04 0.000E+00 1.130E-02 ZR-95 1.650E+03 5.200E+02 0.000E+00 7.650E+02 0.000E+00 1.200E+06 0.000E+00 3.580E+02 ZR-97 7.880E-01 1.560E-01 0.000E+00 2.370E-01 0.000E+00 4.220E+04 0.000E+00 7.190E-02 NB-95 1.410E+05 7.810E+04 0.000E+00 7.570E+04 0.000E+00 3.340E+08 0.000E+00 4.300E+04 MO-99 0.000E+00 4.470E+07 0.000E+00 1.020E+08 0.000E+00 8.010E+07 0.000E+00 8.530E+06 TC-99M 5.760E+00 1.610E+01 0.000E+00 2.390E+02 8.920E+00 1.050E+04 0.000E+00 2.080E+02 TC-101 4.740E-60 6.750E-60 0.000E+00 1.220E-58 4.110E-60 1.150E-66 0.000E+00 6.630E-59 RU-103 1.810E+03 0.000E+00 0.000E+00 6.380E+03 0.000E+00 1.510E+05 0.000E+00 7.740E+02 RU-105 1.560E-03 0.000E+00 0.000E+00 1.970E-02 0.000E+00 1.260E+00 0.000E+00 6.070E-04 RU-106 3.750E+04 0.000E+00 0.000E+00 7.240E+04 0.000E+00 1.800E+06 0.000E+00 4.730E+03 AG-110M 9.630E+07 9.110E+07 0.000E+00 1.740E+08 0.000E+00 2.560E+10 0.000E+00 5.540E+07 TE-125M 3.000E+07 1.080E+07 8.390E+06 0.000E+00 0.000E+00 8.860E+07 0.000E+00 4.020E+06 TE-127 1.210E+03 4.290E+02 8.350E+02 4.900E+03 0.000E+00 9.340E+04 0.000E+00 2.600E+02 TE-127M 8.440E+07 2.990E+07 2.010E+07 3.420E+08 0.000E+00 2.100E+08 0.000E+00 1.000E+07 TE-129 5.200E-10 1.940E-10 3.720E-10 2.180E-09 0.000E+00 2.840E-09 0.000E+00 1.270E-10 TE-129M 1.100E+08 4.090E+07 3.550E+07 4.610E+08 0.000E+00 4.130E+08 0.000E+00 1.740E+07 TE-131 6.580E-33 2.710E-33 5.070E-33 2.880E-32 0.000E+00 5.400E-34 0.000E+00 2.060E-33 TE-131M 6.570E+05 3.150E+05 4.740E+05 3.290E+06 0.000E+00 2.530E+07 0.000E+00 2.630E+05 TE-132 4.290E+06 2.720E+06 2.870E+06 2.610E+07 0.000E+00 8.610E+07 0.000E+00 2.560E+06 I-130 7.380E+05 2.140E+06 1.740E+08 3.290E+06 0.000E+00 1.640E+06 0.000E+00 8.530E+05 Appendix H Ri Teen Cow Milk - Page 2 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX H Ri Teen Dose Factors for use in the Gaseous Dose Calculations Agegroup: TEEN Pathway: Grs/Cow/Milk (CMILK) Units: m2*mrem/yr / Ci/sec; mrem/yr / Ci/m3 (H-3)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body I-131 5.370E+08 7.520E+08 2.190E+11 1.290E+09 0.000E+00 1.490E+08 0.000E+00 4.040E+08 I-132 2.910E-01 7.620E-01 2.570E+01 1.200E+00 0.000E+00 3.320E-01 0.000E+00 2.740E-01 I-133 7.070E+06 1.200E+07 1.670E+09 2.100E+07 0.000E+00 9.070E+06 0.000E+00 3.660E+06 I-134 3.580E-12 9.500E-12 1.580E-10 1.500E-11 0.000E+00 1.250E-13 0.000E+00 3.410E-12 I-135 2.280E+04 5.870E+04 3.780E+06 9.270E+04 0.000E+00 6.510E+04 0.000E+00 2.180E+04 CS-134 9.820E+09 2.310E+10 0.000E+00 7.340E+09 2.800E+09 2.870E+08 0.000E+00 1.070E+10 CS-136 4.480E+08 1.760E+09 0.000E+00 9.600E+08 1.510E+08 1.420E+08 0.000E+00 1.180E+09 CS-137 1.340E+10 1.780E+10 0.000E+00 6.060E+09 2.350E+09 2.530E+08 0.000E+00 6.200E+09 CS-138 1.640E-23 3.150E-23 0.000E+00 2.330E-23 2.710E-24 1.430E-26 0.000E+00 1.580E-23 BA-139 8.170E-08 5.750E-11 0.000E+00 5.420E-11 3.960E-11 7.290E-07 0.000E+00 2.380E-09 BA-140 4.850E+07 5.950E+04 0.000E+00 2.020E+04 4.000E+04 7.480E+07 0.000E+00 3.130E+06 BA-141 7.520E-46 5.620E-49 0.000E+00 5.210E-49 3.850E-49 1.600E-51 0.000E+00 2.510E-47 BA-142 4.790E-80 4.790E-83 0.000E+00 4.050E-83 3.190E-83 1.470E-91 0.000E+00 2.950E-81 LA-140 8.100E+00 3.980E+00 0.000E+00 0.000E+00 0.000E+00 2.290E+05 0.000E+00 1.060E+00 LA-142 3.360E-11 1.490E-11 0.000E+00 0.000E+00 0.000E+00 4.540E-07 0.000E+00 3.710E-12 CE-141 8.880E+03 5.930E+03 0.000E+00 2.790E+03 0.000E+00 1.700E+07 0.000E+00 6.810E+02 CE-143 7.640E+01 5.560E+04 0.000E+00 2.490E+01 0.000E+00 1.670E+06 0.000E+00 6.210E+00 CE-144 6.580E+05 2.720E+05 0.000E+00 1.630E+05 0.000E+00 1.660E+08 0.000E+00 3.540E+04 PR-143 2.900E+02 1.160E+02 0.000E+00 6.730E+01 0.000E+00 9.540E+05 0.000E+00 1.440E+01 PR-144 1.080E-53 4.430E-54 0.000E+00 2.540E-54 0.000E+00 1.190E-56 0.000E+00 5.490E-55 ND-147 1.810E+02 1.970E+02 0.000E+00 1.160E+02 0.000E+00 7.110E+05 0.000E+00 1.180E+01 W-187 1.190E+04 9.710E+03 0.000E+00 0.000E+00 0.000E+00 2.630E+06 0.000E+00 3.400E+03 NP-239 7.010E+00 6.610E-01 0.000E+00 2.070E+00 0.000E+00 1.060E+05 0.000E+00 3.670E-01 Appendix H Ri Teen Cow Milk - Page 3 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX H Ri Teen Dose Factors for use in the Gaseous Dose Calculations Agegroup: TEEN Pathway: Grs/Goat/Milk (GMILK) Units: m2*mrem/yr / Ci/sec; mrem/yr / Ci/m3 (H-3)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body H-3 0.000E+00 2.030E+03 2.030E+03 2.030E+03 2.030E+03 2.030E+03 0.000E+00 2.030E+03 C-14 4.860E+08 9.720E+07 9.720E+07 9.720E+07 9.720E+07 9.720E+07 0.000E+00 9.720E+07 NA-24 5.110E+05 5.110E+05 5.110E+05 5.110E+05 5.110E+05 5.110E+05 0.000E+00 5.110E+05 P-32 3.780E+10 2.340E+09 0.000E+00 0.000E+00 0.000E+00 3.180E+09 0.000E+00 1.470E+09 CR-51 0.000E+00 0.000E+00 3.330E+03 1.310E+03 8.550E+03 1.010E+06 0.000E+00 5.990E+03 MN-54 0.000E+00 1.680E+06 0.000E+00 5.020E+05 0.000E+00 3.450E+06 0.000E+00 3.340E+05 MN-56 0.000E+00 8.700E-04 0.000E+00 1.100E-03 0.000E+00 5.730E-02 0.000E+00 1.550E-04 FE-55 5.790E+05 4.110E+05 0.000E+00 0.000E+00 2.600E+05 1.780E+05 0.000E+00 9.570E+04 FE-59 6.740E+05 1.570E+06 0.000E+00 0.000E+00 4.960E+05 3.720E+06 0.000E+00 6.070E+05 CO-58 0.000E+00 9.520E+05 0.000E+00 0.000E+00 0.000E+00 1.310E+07 0.000E+00 2.190E+06 CO-60 0.000E+00 3.340E+06 0.000E+00 0.000E+00 0.000E+00 4.350E+07 0.000E+00 7.520E+06 NI-63 1.420E+09 1.000E+08 0.000E+00 0.000E+00 0.000E+00 1.590E+07 0.000E+00 4.810E+07 NI-65 8.120E-02 1.040E-02 0.000E+00 0.000E+00 0.000E+00 5.630E-01 0.000E+00 4.730E-03 CU-64 0.000E+00 4.730E+03 0.000E+00 1.200E+04 0.000E+00 3.670E+05 0.000E+00 2.230E+03 ZN-65 2.530E+08 8.780E+08 0.000E+00 5.620E+08 0.000E+00 3.720E+08 0.000E+00 4.100E+08 ZN-69 4.620E-13 8.800E-13 0.000E+00 5.750E-13 0.000E+00 1.620E-12 0.000E+00 6.160E-14 BR-83 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.150E-02 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.450E-24 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 0.000E+00 5.670E+08 0.000E+00 0.000E+00 0.000E+00 8.400E+07 0.000E+00 2.670E+08 RB-88 0.000E+00 4.670E-46 0.000E+00 0.000E+00 0.000E+00 4.000E-53 0.000E+00 2.490E-46 RB-89 0.000E+00 9.190E-54 0.000E+00 0.000E+00 0.000E+00 1.410E-62 0.000E+00 6.500E-54 SR-89 5.620E+09 0.000E+00 0.000E+00 0.000E+00 0.000E+00 6.690E+08 0.000E+00 1.610E+08 SR-90 1.390E+11 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.900E+09 0.000E+00 3.430E+10 SR-91 1.120E+05 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.060E+05 0.000E+00 4.440E+03 Appendix H Ri Teen Goat Milk - Page 1 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX H Ri Teen Dose Factors for use in the Gaseous Dose Calculations Agegroup: TEEN Pathway: Grs/Goat/Milk (GMILK) Units: m2*mrem/yr / Ci/sec; mrem/yr / Ci/m3 (H-3)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body SR-92 1.880E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4.780E+01 0.000E+00 8.000E-02 Y-90 1.560E+01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.290E+05 0.000E+00 4.210E-01 Y-91 1.900E+03 0.000E+00 0.000E+00 0.000E+00 0.000E+00 7.770E+05 0.000E+00 5.080E+01 Y-91M 1.310E-20 0.000E+00 0.000E+00 0.000E+00 0.000E+00 6.200E-19 0.000E+00 5.020E-22 Y-92 1.240E-05 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.390E-01 0.000E+00 3.580E-07 Y-93 4.940E-02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.510E+03 0.000E+00 1.360E-03 ZR-95 1.980E+02 6.250E+01 0.000E+00 9.180E+01 0.000E+00 1.440E+05 0.000E+00 4.300E+01 ZR-97 9.460E-02 1.870E-02 0.000E+00 2.840E-02 0.000E+00 5.070E+03 0.000E+00 8.620E-03 NB-95 1.690E+04 9.370E+03 0.000E+00 9.080E+03 0.000E+00 4.010E+07 0.000E+00 5.160E+03 MO-99 0.000E+00 5.370E+06 0.000E+00 1.230E+07 0.000E+00 9.610E+06 0.000E+00 1.020E+06 TC-99M 6.910E-01 1.930E+00 0.000E+00 2.870E+01 1.070E+00 1.270E+03 0.000E+00 2.500E+01 TC-101 5.690E-61 8.100E-61 0.000E+00 1.460E-59 4.930E-61 1.380E-67 0.000E+00 7.950E-60 RU-103 2.170E+02 0.000E+00 0.000E+00 7.660E+02 0.000E+00 1.810E+04 0.000E+00 9.290E+01 RU-105 1.880E-04 0.000E+00 0.000E+00 2.370E-03 0.000E+00 1.520E-01 0.000E+00 7.290E-05 RU-106 4.500E+03 0.000E+00 0.000E+00 8.680E+03 0.000E+00 2.160E+05 0.000E+00 5.670E+02 AG-110M 1.160E+07 1.090E+07 0.000E+00 2.080E+07 0.000E+00 3.070E+09 0.000E+00 6.650E+06 TE-125M 3.600E+06 1.300E+06 1.010E+06 0.000E+00 0.000E+00 1.060E+07 0.000E+00 4.820E+05 TE-127 1.450E+02 5.150E+01 1.000E+02 5.880E+02 0.000E+00 1.120E+04 0.000E+00 3.120E+01 TE-127M 1.010E+07 3.590E+06 2.410E+06 4.100E+07 0.000E+00 2.520E+07 0.000E+00 1.200E+06 TE-129 6.240E-11 2.330E-11 4.460E-11 2.620E-10 0.000E+00 3.410E-10 0.000E+00 1.520E-11 TE-129M 1.320E+07 4.900E+06 4.260E+06 5.530E+07 0.000E+00 4.960E+07 0.000E+00 2.090E+06 TE-131 7.900E-34 3.260E-34 6.090E-34 3.450E-33 0.000E+00 6.480E-35 0.000E+00 2.470E-34 TE-131M 7.880E+04 3.780E+04 5.690E+04 3.940E+05 0.000E+00 3.030E+06 0.000E+00 3.150E+04 TE-132 5.150E+05 3.260E+05 3.440E+05 3.130E+06 0.000E+00 1.030E+07 0.000E+00 3.070E+05 I-130 8.860E+05 2.560E+06 2.090E+08 3.950E+06 0.000E+00 1.970E+06 0.000E+00 1.020E+06 Appendix H Ri Teen Goat Milk - Page 2 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX H Ri Teen Dose Factors for use in the Gaseous Dose Calculations Agegroup: TEEN Pathway: Grs/Goat/Milk (GMILK) Units: m2*mrem/yr / Ci/sec; mrem/yr / Ci/m3 (H-3)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body I-131 6.450E+08 9.030E+08 2.630E+11 1.550E+09 0.000E+00 1.790E+08 0.000E+00 4.850E+08 I-132 3.500E-01 9.150E-01 3.080E+01 1.440E+00 0.000E+00 3.980E-01 0.000E+00 3.280E-01 I-133 8.480E+06 1.440E+07 2.010E+09 2.520E+07 0.000E+00 1.090E+07 0.000E+00 4.390E+06 I-134 4.300E-12 1.140E-11 1.900E-10 1.800E-11 0.000E+00 1.500E-13 0.000E+00 4.090E-12 I-135 2.740E+04 7.040E+04 4.530E+06 1.110E+05 0.000E+00 7.810E+04 0.000E+00 2.610E+04 CS-134 2.940E+10 6.930E+10 0.000E+00 2.200E+10 8.410E+09 8.620E+08 0.000E+00 3.220E+10 CS-136 1.340E+09 5.290E+09 0.000E+00 2.880E+09 4.540E+08 4.260E+08 0.000E+00 3.550E+09 CS-137 4.020E+10 5.340E+10 0.000E+00 1.820E+10 7.060E+09 7.600E+08 0.000E+00 1.860E+10 CS-138 4.920E-23 9.450E-23 0.000E+00 6.980E-23 8.120E-24 4.290E-26 0.000E+00 4.730E-23 BA-139 9.800E-09 6.900E-12 0.000E+00 6.500E-12 4.750E-12 8.750E-08 0.000E+00 2.860E-10 BA-140 5.820E+06 7.130E+03 0.000E+00 2.420E+03 4.800E+03 8.980E+06 0.000E+00 3.750E+05 BA-141 9.030E-47 6.740E-50 0.000E+00 6.260E-50 4.610E-50 1.920E-52 0.000E+00 3.010E-48 BA-142 5.750E-81 5.750E-84 0.000E+00 4.860E-84 3.820E-84 1.760E-92 0.000E+00 3.540E-82 LA-140 9.720E-01 4.780E-01 0.000E+00 0.000E+00 0.000E+00 2.740E+04 0.000E+00 1.270E-01 LA-142 4.030E-12 1.790E-12 0.000E+00 0.000E+00 0.000E+00 5.440E-08 0.000E+00 4.450E-13 CE-141 1.070E+03 7.120E+02 0.000E+00 3.350E+02 0.000E+00 2.040E+06 0.000E+00 8.170E+01 CE-143 9.170E+00 6.670E+03 0.000E+00 2.990E+00 0.000E+00 2.000E+05 0.000E+00 7.450E-01 CE-144 7.900E+04 3.270E+04 0.000E+00 1.950E+04 0.000E+00 1.990E+07 0.000E+00 4.240E+03 PR-143 3.480E+01 1.390E+01 0.000E+00 8.080E+00 0.000E+00 1.150E+05 0.000E+00 1.730E+00 PR-144 1.300E-54 5.320E-55 0.000E+00 3.050E-55 0.000E+00 1.430E-57 0.000E+00 6.590E-56 ND-147 2.170E+01 2.360E+01 0.000E+00 1.390E+01 0.000E+00 8.530E+04 0.000E+00 1.420E+00 W-187 1.430E+03 1.170E+03 0.000E+00 0.000E+00 0.000E+00 3.150E+05 0.000E+00 4.080E+02 NP-239 8.410E-01 7.930E-02 0.000E+00 2.490E-01 0.000E+00 1.280E+04 0.000E+00 4.410E-02 Appendix H Ri Teen Goat Milk - Page 3 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX H Ri Teen Dose Factors for use in the Gaseous Dose Calculations Agegroup: TEEN Pathway: Grs/Cow/Meat (CMEAT) Units: m2*mrem/yr / Ci/sec; mrem/yr / Ci/m3 (H-3)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body H-3 0.000E+00 1.940E+02 1.940E+02 1.940E+02 1.940E+02 1.940E+02 0.000E+00 1.940E+02 C-14 2.040E+08 4.080E+07 4.080E+07 4.080E+07 4.080E+07 4.080E+07 0.000E+00 4.080E+07 NA-24 1.080E-03 1.080E-03 1.080E-03 1.080E-03 1.080E-03 1.080E-03 0.000E+00 1.080E-03 P-32 3.930E+09 2.440E+08 0.000E+00 0.000E+00 0.000E+00 3.310E+08 0.000E+00 1.530E+08 CR-51 0.000E+00 0.000E+00 3.130E+03 1.240E+03 8.050E+03 9.470E+05 0.000E+00 5.640E+03 MN-54 0.000E+00 7.000E+06 0.000E+00 2.090E+06 0.000E+00 1.440E+07 0.000E+00 1.390E+06 MN-56 0.000E+00 1.070E-53 0.000E+00 1.360E-53 0.000E+00 7.070E-52 0.000E+00 1.910E-54 FE-55 2.380E+08 1.690E+08 0.000E+00 0.000E+00 1.070E+08 7.310E+07 0.000E+00 3.940E+07 FE-59 2.120E+08 4.950E+08 0.000E+00 0.000E+00 1.560E+08 1.170E+09 0.000E+00 1.910E+08 CO-58 0.000E+00 1.410E+07 0.000E+00 0.000E+00 0.000E+00 1.940E+08 0.000E+00 3.240E+07 CO-60 0.000E+00 5.830E+07 0.000E+00 0.000E+00 0.000E+00 7.600E+08 0.000E+00 1.310E+08 NI-63 1.520E+10 1.070E+09 0.000E+00 0.000E+00 0.000E+00 1.710E+08 0.000E+00 5.150E+08 NI-65 1.880E-52 2.410E-53 0.000E+00 0.000E+00 0.000E+00 1.300E-51 0.000E+00 1.100E-53 CU-64 0.000E+00 2.210E-07 0.000E+00 5.600E-07 0.000E+00 1.720E-05 0.000E+00 1.040E-07 ZN-65 2.500E+08 8.690E+08 0.000E+00 5.560E+08 0.000E+00 3.680E+08 0.000E+00 4.050E+08 ZN-69 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-83 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.070E-57 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 0.000E+00 4.070E+08 0.000E+00 0.000E+00 0.000E+00 6.020E+07 0.000E+00 1.910E+08 RB-88 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-89 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 SR-89 2.550E+08 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.030E+07 0.000E+00 7.290E+06 SR-90 8.050E+09 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.260E+08 0.000E+00 1.990E+09 SR-91 1.280E-10 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.800E-10 0.000E+00 5.090E-12 Appendix H Ri Teen Cow Meat - Page 1 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX H Ri Teen Dose Factors for use in the Gaseous Dose Calculations Agegroup: TEEN Pathway: Grs/Cow/Meat (CMEAT) Units: m2*mrem/yr / Ci/sec; mrem/yr / Ci/m3 (H-3)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body SR-92 9.880E-50 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.520E-48 0.000E+00 4.210E-51 Y-90 9.060E+01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 7.470E+05 0.000E+00 2.440E+00 Y-91 9.540E+05 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.910E+08 0.000E+00 2.560E+04 Y-91M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Y-92 1.280E-39 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.520E-35 0.000E+00 3.710E-41 Y-93 3.960E-12 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.210E-07 0.000E+00 1.090E-13 ZR-95 1.500E+06 4.730E+05 0.000E+00 6.950E+05 0.000E+00 1.090E+09 0.000E+00 3.250E+05 ZR-97 1.720E-05 3.410E-06 0.000E+00 5.170E-06 0.000E+00 9.230E-01 0.000E+00 1.570E-06 NB-95 1.790E+06 9.950E+05 0.000E+00 9.650E+05 0.000E+00 4.260E+09 0.000E+00 5.480E+05 MO-99 0.000E+00 8.270E+04 0.000E+00 1.890E+05 0.000E+00 1.480E+05 0.000E+00 1.580E+04 TC-99M 3.530E-21 9.850E-21 0.000E+00 1.470E-19 5.470E-21 6.470E-18 0.000E+00 1.280E-19 TC-101 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RU-103 8.570E+07 0.000E+00 0.000E+00 3.020E+08 0.000E+00 7.160E+09 0.000E+00 3.660E+07 RU-105 4.830E-28 0.000E+00 0.000E+00 6.090E-27 0.000E+00 3.900E-25 0.000E+00 1.880E-28 RU-106 2.360E+09 0.000E+00 0.000E+00 4.550E+09 0.000E+00 1.130E+11 0.000E+00 2.970E+08 AG-110M 5.060E+06 4.790E+06 0.000E+00 9.130E+06 0.000E+00 1.340E+09 0.000E+00 2.910E+06 TE-125M 3.030E+08 1.090E+08 8.470E+07 0.000E+00 0.000E+00 8.940E+08 0.000E+00 4.050E+07 TE-127 1.800E-10 6.380E-11 1.240E-10 7.290E-10 0.000E+00 1.390E-08 0.000E+00 3.870E-11 TE-127M 9.410E+08 3.340E+08 2.240E+08 3.820E+09 0.000E+00 2.350E+09 0.000E+00 1.120E+08 TE-129 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 TE-129M 9.500E+08 3.530E+08 3.070E+08 3.970E+09 0.000E+00 3.570E+09 0.000E+00 1.500E+08 TE-131 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 TE-131M 3.760E+02 1.800E+02 2.710E+02 1.880E+03 0.000E+00 1.450E+04 0.000E+00 1.500E+02 TE-132 1.160E+06 7.360E+05 7.750E+05 7.060E+06 0.000E+00 2.330E+07 0.000E+00 6.920E+05 I-130 1.700E-06 4.910E-06 4.000E-04 7.560E-06 0.000E+00 3.770E-06 0.000E+00 1.960E-06 Appendix H Ri Teen Cow Meat - Page 2 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX H Ri Teen Dose Factors for use in the Gaseous Dose Calculations Agegroup: TEEN Pathway: Grs/Cow/Meat (CMEAT) Units: m2*mrem/yr / Ci/sec; mrem/yr / Ci/m3 (H-3)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body I-131 8.920E+06 1.250E+07 3.650E+09 2.150E+07 0.000E+00 2.470E+06 0.000E+00 6.710E+06 I-132 5.660E-59 1.480E-58 4.990E-57 2.330E-58 0.000E+00 6.450E-59 0.000E+00 5.320E-59 I-133 3.050E-01 5.180E-01 7.230E+01 9.090E-01 0.000E+00 3.920E-01 0.000E+00 1.580E-01 I-134 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 I-135 3.600E-17 9.260E-17 5.960E-15 1.460E-16 0.000E+00 1.030E-16 0.000E+00 3.430E-17 CS-134 5.230E+08 1.230E+09 0.000E+00 3.910E+08 1.490E+08 1.530E+07 0.000E+00 5.710E+08 CS-136 9.400E+06 3.700E+07 0.000E+00 2.010E+07 3.170E+06 2.980E+06 0.000E+00 2.480E+07 CS-137 7.240E+08 9.630E+08 0.000E+00 3.280E+08 1.270E+08 1.370E+07 0.000E+00 3.360E+08 CS-138 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BA-139 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BA-140 2.380E+07 2.910E+04 0.000E+00 9.870E+03 1.960E+04 3.660E+07 0.000E+00 1.530E+06 BA-141 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BA-142 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 LA-140 3.050E-02 1.500E-02 0.000E+00 0.000E+00 0.000E+00 8.610E+02 0.000E+00 3.990E-03 LA-142 2.870E-92 1.280E-92 0.000E+00 0.000E+00 0.000E+00 3.880E-88 0.000E+00 3.180E-93 CE-141 1.180E+04 7.870E+03 0.000E+00 3.710E+03 0.000E+00 2.250E+07 0.000E+00 9.040E+02 CE-143 1.690E-02 1.230E+01 0.000E+00 5.510E-03 0.000E+00 3.690E+02 0.000E+00 1.370E-03 CE-144 1.230E+06 5.080E+05 0.000E+00 3.040E+05 0.000E+00 3.090E+08 0.000E+00 6.600E+04 PR-143 1.760E+04 7.040E+03 0.000E+00 4.090E+03 0.000E+00 5.800E+07 0.000E+00 8.780E+02 PR-144 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 ND-147 6.230E+03 6.770E+03 0.000E+00 3.980E+03 0.000E+00 2.440E+07 0.000E+00 4.060E+02 W-187 1.730E-02 1.410E-02 0.000E+00 0.000E+00 0.000E+00 3.820E+00 0.000E+00 4.940E-03 NP-239 2.260E-01 2.140E-02 0.000E+00 6.700E-02 0.000E+00 3.440E+03 0.000E+00 1.190E-02 Appendix H Ri Teen Cow Meat - Page 3 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX H Ri Teen Dose Factors for use in the Gaseous Dose Calculations Agegroup: TEEN Pathway: Vegetation (VEG) Units: m2*mrem/yr / Ci/sec; mrem/yr / Ci/m3 (H-3)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body H-3 0.000E+00 2.590E+03 2.590E+03 2.590E+03 2.590E+03 2.590E+03 0.000E+00 2.590E+03 C-14 3.690E+08 7.380E+07 7.380E+07 7.380E+07 7.380E+07 7.380E+07 0.000E+00 7.380E+07 NA-24 2.390E+05 2.390E+05 2.390E+05 2.390E+05 2.390E+05 2.390E+05 0.000E+00 2.390E+05 P-32 1.610E+09 9.970E+07 0.000E+00 0.000E+00 0.000E+00 1.350E+08 0.000E+00 6.240E+07 CR-51 0.000E+00 0.000E+00 3.430E+04 1.350E+04 8.810E+04 1.040E+07 0.000E+00 6.170E+04 MN-54 0.000E+00 4.540E+08 0.000E+00 1.360E+08 0.000E+00 9.320E+08 0.000E+00 9.010E+07 MN-56 0.000E+00 1.420E+01 0.000E+00 1.800E+01 0.000E+00 9.360E+02 0.000E+00 2.530E+00 FE-55 3.260E+08 2.310E+08 0.000E+00 0.000E+00 1.470E+08 1.000E+08 0.000E+00 5.390E+07 FE-59 1.790E+08 4.190E+08 0.000E+00 0.000E+00 1.320E+08 9.900E+08 0.000E+00 1.620E+08 CO-58 0.000E+00 4.360E+07 0.000E+00 0.000E+00 0.000E+00 6.010E+08 0.000E+00 1.000E+08 CO-60 0.000E+00 2.490E+08 0.000E+00 0.000E+00 0.000E+00 3.240E+09 0.000E+00 5.600E+08 NI-63 1.610E+10 1.130E+09 0.000E+00 0.000E+00 0.000E+00 1.810E+08 0.000E+00 5.450E+08 NI-65 5.720E+01 7.310E+00 0.000E+00 0.000E+00 0.000E+00 3.970E+02 0.000E+00 3.330E+00 CU-64 0.000E+00 8.340E+03 0.000E+00 2.110E+04 0.000E+00 6.470E+05 0.000E+00 3.920E+03 ZN-65 4.240E+08 1.470E+09 0.000E+00 9.420E+08 0.000E+00 6.230E+08 0.000E+00 6.870E+08 ZN-69 5.140E-06 9.800E-06 0.000E+00 6.400E-06 0.000E+00 1.810E-05 0.000E+00 6.860E-07 BR-83 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.910E+00 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.250E-11 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 0.000E+00 2.740E+08 0.000E+00 0.000E+00 0.000E+00 4.050E+07 0.000E+00 1.290E+08 RB-88 0.000E+00 3.170E-22 0.000E+00 0.000E+00 0.000E+00 2.720E-29 0.000E+00 1.690E-22 RB-89 0.000E+00 3.500E-26 0.000E+00 0.000E+00 0.000E+00 5.360E-35 0.000E+00 2.470E-26 SR-89 1.510E+10 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.800E+09 0.000E+00 4.340E+08 SR-90 7.510E+11 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.110E+10 0.000E+00 1.850E+11 SR-91 2.850E+05 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.290E+06 0.000E+00 1.130E+04 Appendix H Ri Teen Vegetation - Page 1 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX H Ri Teen Dose Factors for use in the Gaseous Dose Calculations Agegroup: TEEN Pathway: Vegetation (VEG) Units: m2*mrem/yr / Ci/sec; mrem/yr / Ci/m3 (H-3)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body SR-92 3.970E+02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.010E+04 0.000E+00 1.690E+01 Y-90 1.240E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.020E+08 0.000E+00 3.350E+02 Y-91 7.840E+06 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.210E+09 0.000E+00 2.100E+05 Y-91M 4.860E-09 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.290E-07 0.000E+00 1.860E-10 Y-92 8.600E-01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.360E+04 0.000E+00 2.490E-02 Y-93 1.590E+02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4.860E+06 0.000E+00 4.360E+00 ZR-95 1.720E+06 5.430E+05 0.000E+00 7.980E+05 0.000E+00 1.250E+09 0.000E+00 3.730E+05 ZR-97 3.120E+02 6.180E+01 0.000E+00 9.370E+01 0.000E+00 1.670E+07 0.000E+00 2.850E+01 NB-95 1.920E+05 1.070E+05 0.000E+00 1.030E+05 0.000E+00 4.560E+08 0.000E+00 5.870E+04 MO-99 0.000E+00 5.650E+06 0.000E+00 1.290E+07 0.000E+00 1.010E+07 0.000E+00 1.080E+06 TC-99M 2.740E+00 7.630E+00 0.000E+00 1.140E+02 4.240E+00 5.010E+03 0.000E+00 9.890E+01 TC-101 7.640E-31 1.090E-30 0.000E+00 1.970E-29 6.620E-31 1.860E-37 0.000E+00 1.070E-29 RU-103 6.820E+06 0.000E+00 0.000E+00 2.400E+07 0.000E+00 5.700E+08 0.000E+00 2.920E+06 RU-105 5.000E+01 0.000E+00 0.000E+00 6.310E+02 0.000E+00 4.040E+04 0.000E+00 1.940E+01 RU-106 3.100E+08 0.000E+00 0.000E+00 5.970E+08 0.000E+00 1.480E+10 0.000E+00 3.900E+07 AG-110M 1.520E+07 1.430E+07 0.000E+00 2.740E+07 0.000E+00 4.030E+09 0.000E+00 8.720E+06 TE-125M 1.480E+08 5.340E+07 4.140E+07 0.000E+00 0.000E+00 4.370E+08 0.000E+00 1.980E+07 TE-127 5.330E+03 1.890E+03 3.680E+03 2.160E+04 0.000E+00 4.120E+05 0.000E+00 1.150E+03 TE-127M 5.510E+08 1.960E+08 1.310E+08 2.240E+09 0.000E+00 1.370E+09 0.000E+00 6.560E+07 TE-129 7.140E-04 2.660E-04 5.100E-04 3.000E-03 0.000E+00 3.910E-03 0.000E+00 1.740E-04 TE-129M 3.620E+08 1.340E+08 1.170E+08 1.510E+09 0.000E+00 1.360E+09 0.000E+00 5.730E+07 TE-131 1.390E-15 5.750E-16 1.070E-15 6.100E-15 0.000E+00 1.140E-16 0.000E+00 4.360E-16 TE-131M 8.440E+05 4.050E+05 6.090E+05 4.220E+06 0.000E+00 3.250E+07 0.000E+00 3.380E+05 TE-132 3.910E+06 2.470E+06 2.610E+06 2.370E+07 0.000E+00 7.840E+07 0.000E+00 2.330E+06 I-130 3.510E+05 1.010E+06 8.280E+07 1.560E+06 0.000E+00 7.800E+05 0.000E+00 4.050E+05 Appendix H Ri Teen Vegetation - Page 2 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX H Ri Teen Dose Factors for use in the Gaseous Dose Calculations Agegroup: TEEN Pathway: Vegetation (VEG) Units: m2*mrem/yr / Ci/sec; mrem/yr / Ci/m3 (H-3)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body I-131 7.690E+07 1.080E+08 3.140E+10 1.850E+08 0.000E+00 2.130E+07 0.000E+00 5.780E+07 I-132 5.190E+01 1.360E+02 4.580E+03 2.140E+02 0.000E+00 5.920E+01 0.000E+00 4.880E+01 I-133 1.940E+06 3.290E+06 4.590E+08 5.760E+06 0.000E+00 2.490E+06 0.000E+00 1.000E+06 I-134 8.720E-05 2.310E-04 3.850E-03 3.640E-04 0.000E+00 3.050E-06 0.000E+00 8.310E-05 I-135 3.520E+04 9.070E+04 5.830E+06 1.430E+05 0.000E+00 1.000E+05 0.000E+00 3.360E+04 CS-134 7.100E+09 1.670E+10 0.000E+00 5.310E+09 2.030E+09 2.080E+08 0.000E+00 7.750E+09 CS-136 4.370E+07 1.720E+08 0.000E+00 9.370E+07 1.480E+07 1.380E+07 0.000E+00 1.160E+08 CS-137 1.010E+10 1.350E+10 0.000E+00 4.590E+09 1.780E+09 1.920E+08 0.000E+00 4.690E+09 CS-138 3.610E-11 6.940E-11 0.000E+00 5.120E-11 5.960E-12 3.150E-14 0.000E+00 3.470E-11 BA-139 2.690E-02 1.890E-05 0.000E+00 1.780E-05 1.300E-05 2.400E-01 0.000E+00 7.830E-04 BA-140 1.380E+08 1.690E+05 0.000E+00 5.740E+04 1.140E+05 2.130E+08 0.000E+00 8.900E+06 BA-141 1.080E-21 8.040E-25 0.000E+00 7.460E-25 5.500E-25 2.290E-27 0.000E+00 3.590E-23 BA-142 5.490E-39 5.490E-42 0.000E+00 4.640E-42 3.650E-42 1.680E-50 0.000E+00 3.380E-40 LA-140 1.810E+03 8.880E+02 0.000E+00 0.000E+00 0.000E+00 5.100E+07 0.000E+00 2.360E+02 LA-142 1.850E-04 8.240E-05 0.000E+00 0.000E+00 0.000E+00 2.510E+00 0.000E+00 2.050E-05 CE-141 2.830E+05 1.890E+05 0.000E+00 8.890E+04 0.000E+00 5.400E+08 0.000E+00 2.170E+04 CE-143 9.330E+02 6.790E+05 0.000E+00 3.040E+02 0.000E+00 2.040E+07 0.000E+00 7.580E+01 CE-144 5.270E+07 2.180E+07 0.000E+00 1.300E+07 0.000E+00 1.330E+10 0.000E+00 2.830E+06 PR-143 7.000E+04 2.800E+04 0.000E+00 1.630E+04 0.000E+00 2.300E+08 0.000E+00 3.490E+03 PR-144 2.900E-26 1.190E-26 0.000E+00 6.800E-27 0.000E+00 3.190E-29 0.000E+00 1.470E-27 ND-147 3.620E+04 3.940E+04 0.000E+00 2.310E+04 0.000E+00 1.420E+08 0.000E+00 2.360E+03 W-187 3.540E+04 2.880E+04 0.000E+00 0.000E+00 0.000E+00 7.800E+06 0.000E+00 1.010E+04 NP-239 1.390E+03 1.310E+02 0.000E+00 4.100E+02 0.000E+00 2.100E+07 0.000E+00 7.260E+01 Appendix H Ri Teen Vegetation - Page 3 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX H Ri Teen Dose Factors for use in the Gaseous Dose Calculations Agegroup: TEEN Pathway: Inhalation (INHL) Units: mrem/yr / Ci/m3 Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body H-3 0.000E+00 1.270E+03 1.270E+03 1.270E+03 1.270E+03 1.270E+03 0.000E+00 1.270E+03 C-14 2.600E+04 4.870E+03 4.870E+03 4.870E+03 4.870E+03 4.870E+03 0.000E+00 4.870E+03 NA-24 1.380E+04 1.380E+04 1.380E+04 1.380E+04 1.380E+04 1.380E+04 0.000E+00 1.380E+04 P-32 1.890E+06 1.100E+05 0.000E+00 0.000E+00 0.000E+00 9.280E+04 0.000E+00 7.160E+04 CR-51 0.000E+00 0.000E+00 7.500E+01 3.070E+01 2.100E+04 3.000E+03 0.000E+00 1.350E+02 MN-54 0.000E+00 5.110E+04 0.000E+00 1.270E+04 1.980E+06 6.680E+04 0.000E+00 8.400E+03 MN-56 0.000E+00 1.700E+00 0.000E+00 1.790E+00 1.520E+04 5.740E+04 0.000E+00 2.520E-01 FE-55 3.340E+04 2.380E+04 0.000E+00 0.000E+00 1.240E+05 6.390E+03 0.000E+00 5.540E+03 FE-59 1.590E+04 3.700E+04 0.000E+00 0.000E+00 1.530E+06 1.780E+05 0.000E+00 1.430E+04 CO-58 0.000E+00 2.070E+03 0.000E+00 0.000E+00 1.340E+06 9.520E+04 0.000E+00 2.780E+03 CO-60 0.000E+00 1.510E+04 0.000E+00 0.000E+00 8.720E+06 2.590E+05 0.000E+00 1.980E+04 NI-63 5.800E+05 4.340E+04 0.000E+00 0.000E+00 3.070E+05 1.420E+04 0.000E+00 1.980E+04 NI-65 2.180E+00 2.930E-01 0.000E+00 0.000E+00 9.360E+03 3.670E+04 0.000E+00 1.270E-01 CU-64 0.000E+00 2.030E+00 0.000E+00 6.410E+00 1.110E+04 6.140E+04 0.000E+00 8.480E-01 ZN-65 3.860E+04 1.340E+05 0.000E+00 8.640E+04 1.240E+06 4.660E+04 0.000E+00 6.240E+04 ZN-69 4.830E-02 9.200E-02 0.000E+00 6.020E-02 1.580E+03 2.850E+02 0.000E+00 6.460E-03 BR-83 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.440E+02 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4.330E+02 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.830E+01 RB-86 0.000E+00 1.900E+05 0.000E+00 0.000E+00 0.000E+00 1.770E+04 0.000E+00 8.400E+04 RB-88 0.000E+00 5.460E+02 0.000E+00 0.000E+00 0.000E+00 2.920E-05 0.000E+00 2.720E+02 RB-89 0.000E+00 3.520E+02 0.000E+00 0.000E+00 0.000E+00 3.380E-07 0.000E+00 2.330E+02 SR-89 4.340E+05 0.000E+00 0.000E+00 0.000E+00 2.420E+06 3.710E+05 0.000E+00 1.250E+04 SR-90 1.080E+08 0.000E+00 0.000E+00 0.000E+00 1.650E+07 7.650E+05 0.000E+00 6.680E+06 SR-91 8.800E+01 0.000E+00 0.000E+00 0.000E+00 6.070E+04 2.590E+05 0.000E+00 3.510E+00 Appendix H Ri Teen Inhalation - Page 1 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX H Ri Teen Dose Factors for use in the Gaseous Dose Calculations Agegroup: TEEN Pathway: Inhalation (INHL) Units: mrem/yr / Ci/m3 Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body SR-92 9.520E+00 0.000E+00 0.000E+00 0.000E+00 2.740E+04 1.190E+05 0.000E+00 4.060E-01 Y-90 2.980E+03 0.000E+00 0.000E+00 0.000E+00 2.930E+05 5.590E+05 0.000E+00 8.000E+01 Y-91 6.610E+05 0.000E+00 0.000E+00 0.000E+00 2.940E+06 4.090E+05 0.000E+00 1.770E+04 Y-91M 3.700E-01 0.000E+00 0.000E+00 0.000E+00 3.200E+03 3.020E+01 0.000E+00 1.420E-02 Y-92 1.470E+01 0.000E+00 0.000E+00 0.000E+00 2.680E+04 1.650E+05 0.000E+00 4.290E-01 Y-93 1.350E+02 0.000E+00 0.000E+00 0.000E+00 8.320E+04 5.790E+05 0.000E+00 3.720E+00 ZR-95 1.460E+05 4.580E+04 0.000E+00 6.740E+04 2.690E+06 1.490E+05 0.000E+00 3.150E+04 ZR-97 1.380E+02 2.720E+01 0.000E+00 4.120E+01 1.300E+05 6.300E+05 0.000E+00 1.260E+01 NB-95 1.860E+04 1.030E+04 0.000E+00 1.000E+04 7.510E+05 9.680E+04 0.000E+00 5.660E+03 MO-99 0.000E+00 1.690E+02 0.000E+00 4.110E+02 1.540E+05 2.690E+05 0.000E+00 3.220E+01 TC-99M 1.380E-03 3.860E-03 0.000E+00 5.760E-02 1.150E+03 6.130E+03 0.000E+00 4.990E-02 TC-101 5.920E-05 8.400E-05 0.000E+00 1.520E-03 6.670E+02 8.720E-07 0.000E+00 8.240E-04 RU-103 2.100E+03 0.000E+00 0.000E+00 7.430E+03 7.830E+05 1.090E+05 0.000E+00 8.960E+02 RU-105 1.120E+00 0.000E+00 0.000E+00 1.410E+00 1.820E+04 9.040E+04 0.000E+00 4.340E-01 RU-106 9.840E+04 0.000E+00 0.000E+00 1.900E+05 1.610E+07 9.600E+05 0.000E+00 1.240E+04 AG-110M 1.380E+04 1.310E+04 0.000E+00 2.500E+04 6.750E+06 2.730E+05 0.000E+00 7.990E+03 TE-125M 4.880E+03 2.240E+03 1.400E+03 0.000E+00 5.360E+05 7.500E+04 0.000E+00 6.670E+02 TE-127 2.010E+00 9.120E-01 1.420E+00 7.280E+00 1.120E+04 8.080E+04 0.000E+00 4.420E-01 TE-127M 1.800E+04 8.160E+03 4.380E+03 6.540E+04 1.660E+06 1.590E+05 0.000E+00 2.180E+03 TE-129 7.100E-02 3.380E-02 5.180E-02 2.660E-01 3.300E+03 1.620E+03 0.000E+00 1.760E-02 TE-129M 1.390E+04 6.580E+03 4.580E+03 5.190E+04 1.980E+06 4.050E+05 0.000E+00 2.250E+03 TE-131 1.580E-02 8.320E-03 1.240E-02 6.180E-02 2.340E+03 1.510E+01 0.000E+00 5.040E-03 TE-131M 9.840E+01 6.010E+01 7.250E+01 4.390E+02 2.380E+05 6.210E+05 0.000E+00 4.020E+01 TE-132 3.600E+02 2.900E+02 2.460E+02 1.950E+03 4.490E+05 4.630E+05 0.000E+00 2.190E+02 I-130 6.240E+03 1.790E+04 1.490E+06 2.750E+04 0.000E+00 9.120E+03 0.000E+00 7.170E+03 Appendix H Ri Teen Inhalation - Page 2 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX H Ri Teen Dose Factors for use in the Gaseous Dose Calculations Agegroup: TEEN Pathway: Inhalation (INHL) Units: mrem/yr / Ci/m3 Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body I-131 3.540E+04 4.910E+04 1.460E+07 8.400E+04 0.000E+00 6.490E+03 0.000E+00 2.640E+04 I-132 1.590E+03 4.380E+03 1.510E+05 6.920E+03 0.000E+00 1.270E+03 0.000E+00 1.580E+03 I-133 1.220E+04 2.050E+04 2.920E+06 3.590E+04 0.000E+00 1.030E+04 0.000E+00 6.220E+03 I-134 8.880E+02 2.320E+03 3.950E+04 3.660E+03 0.000E+00 2.040E+01 0.000E+00 8.400E+02 I-135 3.700E+03 9.440E+03 6.210E+05 1.490E+04 0.000E+00 6.950E+03 0.000E+00 3.490E+03 CS-134 5.020E+05 1.130E+06 0.000E+00 3.750E+05 1.460E+05 9.760E+03 0.000E+00 5.490E+05 CS-136 5.150E+04 1.940E+05 0.000E+00 1.100E+05 1.780E+04 1.090E+04 0.000E+00 1.370E+05 CS-137 6.700E+05 8.480E+05 0.000E+00 3.040E+05 1.210E+05 8.480E+03 0.000E+00 3.110E+05 CS-138 4.660E+02 8.560E+02 0.000E+00 6.620E+02 7.870E+01 2.700E-01 0.000E+00 4.460E+02 BA-139 1.340E+00 9.440E-04 0.000E+00 8.880E-04 6.460E+03 6.450E+03 0.000E+00 3.900E-02 BA-140 5.470E+04 6.700E+01 0.000E+00 2.280E+01 2.030E+06 2.290E+05 0.000E+00 3.520E+03 BA-141 1.420E-01 1.060E-04 0.000E+00 9.840E-05 3.290E+03 7.460E-04 0.000E+00 4.740E-03 BA-142 3.700E-02 3.700E-05 0.000E+00 3.140E-05 1.910E+03 4.790E-10 0.000E+00 2.270E-03 LA-140 4.790E+02 2.360E+02 0.000E+00 0.000E+00 2.140E+05 4.870E+05 0.000E+00 6.260E+01 LA-142 9.600E-01 4.250E-01 0.000E+00 0.000E+00 1.020E+04 1.200E+04 0.000E+00 1.060E-01 CE-141 2.840E+04 1.900E+04 0.000E+00 8.880E+03 6.140E+05 1.260E+05 0.000E+00 2.170E+03 CE-143 2.660E+02 1.940E+02 0.000E+00 8.640E+01 1.300E+05 2.550E+05 0.000E+00 2.160E+01 CE-144 4.890E+06 2.020E+06 0.000E+00 1.210E+06 1.340E+07 8.640E+05 0.000E+00 2.620E+05 PR-143 1.340E+04 5.310E+03 0.000E+00 3.090E+03 4.830E+05 2.140E+05 0.000E+00 6.620E+02 PR-144 4.300E-02 1.760E-02 0.000E+00 1.010E-02 1.750E+03 2.350E-04 0.000E+00 2.180E-03 ND-147 7.860E+03 8.560E+03 0.000E+00 5.020E+03 3.720E+05 1.820E+05 0.000E+00 5.130E+02 W-187 1.200E+01 9.760E+00 0.000E+00 0.000E+00 4.740E+04 1.770E+05 0.000E+00 3.430E+00 NP-239 3.380E+02 3.190E+01 0.000E+00 1.000E+02 6.490E+04 1.320E+05 0.000E+00 1.770E+01 Appendix H Ri Teen Inhalation - Page 3 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX H Ri Teen Dose Factors for use in the Gaseous Dose Calculations Agegroup: TEEN Pathway: Ground Plane Deposition (GPD) Units: m2*mrem/yr / Ci/sec Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body H-3 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 C-14 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 NA-24 1.190E+07 1.190E+07 1.190E+07 1.190E+07 1.190E+07 1.190E+07 1.390E+07 1.190E+07 P-32 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 CR-51 4.660E+06 4.660E+06 4.660E+06 4.660E+06 4.660E+06 4.660E+06 5.510E+06 4.660E+06 MN-54 1.390E+09 1.390E+09 1.390E+09 1.390E+09 1.390E+09 1.390E+09 1.630E+09 1.390E+09 MN-56 9.020E+05 9.020E+05 9.020E+05 9.020E+05 9.020E+05 9.020E+05 1.070E+06 9.020E+05 FE-55 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 FE-59 2.730E+08 2.730E+08 2.730E+08 2.730E+08 2.730E+08 2.730E+08 3.210E+08 2.730E+08 CO-58 3.790E+08 3.790E+08 3.790E+08 3.790E+08 3.790E+08 3.790E+08 4.440E+08 3.790E+08 CO-60 2.150E+10 2.150E+10 2.150E+10 2.150E+10 2.150E+10 2.150E+10 2.530E+10 2.150E+10 NI-63 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 NI-65 2.970E+05 2.970E+05 2.970E+05 2.970E+05 2.970E+05 2.970E+05 3.450E+05 2.970E+05 CU-64 6.070E+05 6.070E+05 6.070E+05 6.070E+05 6.070E+05 6.070E+05 6.880E+05 6.070E+05 ZN-65 7.470E+08 7.470E+08 7.470E+08 7.470E+08 7.470E+08 7.470E+08 8.590E+08 7.470E+08 ZN-69 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-83 4.870E+03 4.870E+03 4.870E+03 4.870E+03 4.870E+03 4.870E+03 7.080E+03 4.870E+03 BR-84 2.030E+05 2.030E+05 2.030E+05 2.030E+05 2.030E+05 2.030E+05 2.360E+05 2.030E+05 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 8.990E+06 8.990E+06 8.990E+06 8.990E+06 8.990E+06 8.990E+06 1.030E+07 8.990E+06 RB-88 3.310E+04 3.310E+04 3.310E+04 3.310E+04 3.310E+04 3.310E+04 3.780E+04 3.310E+04 RB-89 1.230E+05 1.230E+05 1.230E+05 1.230E+05 1.230E+05 1.230E+05 1.480E+05 1.230E+05 SR-89 2.160E+04 2.160E+04 2.160E+04 2.160E+04 2.160E+04 2.160E+04 2.510E+04 2.160E+04 SR-90 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 SR-91 2.150E+06 2.150E+06 2.150E+06 2.150E+06 2.150E+06 2.150E+06 2.510E+06 2.150E+06 Appendix H Ri Teen Ground Plane Deposition - Page 1 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX H Ri Teen Dose Factors for use in the Gaseous Dose Calculations Agegroup: TEEN Pathway: Ground Plane Deposition (GPD) Units: m2*mrem/yr / Ci/sec Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body SR-92 7.770E+05 7.770E+05 7.770E+05 7.770E+05 7.770E+05 7.770E+05 8.630E+05 7.770E+05 Y-90 4.490E+03 4.490E+03 4.490E+03 4.490E+03 4.490E+03 4.490E+03 5.310E+03 4.490E+03 Y-91 1.070E+06 1.070E+06 1.070E+06 1.070E+06 1.070E+06 1.070E+06 1.210E+06 1.070E+06 Y-91M 1.000E+05 1.000E+05 1.000E+05 1.000E+05 1.000E+05 1.000E+05 1.160E+05 1.000E+05 Y-92 1.800E+05 1.800E+05 1.800E+05 1.800E+05 1.800E+05 1.800E+05 2.140E+05 1.800E+05 Y-93 1.830E+05 1.830E+05 1.830E+05 1.830E+05 1.830E+05 1.830E+05 2.510E+05 1.830E+05 ZR-95 2.450E+08 2.450E+08 2.450E+08 2.450E+08 2.450E+08 2.450E+08 2.840E+08 2.450E+08 ZR-97 2.960E+06 2.960E+06 2.960E+06 2.960E+06 2.960E+06 2.960E+06 3.440E+06 2.960E+06 NB-95 1.370E+08 1.370E+08 1.370E+08 1.370E+08 1.370E+08 1.370E+08 1.610E+08 1.370E+08 MO-99 3.990E+06 3.990E+06 3.990E+06 3.990E+06 3.990E+06 3.990E+06 4.630E+06 3.990E+06 TC-99M 1.840E+05 1.840E+05 1.840E+05 1.840E+05 1.840E+05 1.840E+05 2.110E+05 1.840E+05 TC-101 2.040E+04 2.040E+04 2.040E+04 2.040E+04 2.040E+04 2.040E+04 2.260E+04 2.040E+04 RU-103 1.080E+08 1.080E+08 1.080E+08 1.080E+08 1.080E+08 1.080E+08 1.260E+08 1.080E+08 RU-105 6.360E+05 6.360E+05 6.360E+05 6.360E+05 6.360E+05 6.360E+05 7.210E+05 6.360E+05 RU-106 4.220E+08 4.220E+08 4.220E+08 4.220E+08 4.220E+08 4.220E+08 5.070E+08 4.220E+08 AG-110M 3.440E+09 3.440E+09 3.440E+09 3.440E+09 3.440E+09 3.440E+09 4.010E+09 3.440E+09 TE-125M 1.550E+06 1.550E+06 1.550E+06 1.550E+06 1.550E+06 1.550E+06 2.130E+06 1.550E+06 TE-127 2.980E+03 2.980E+03 2.980E+03 2.980E+03 2.980E+03 2.980E+03 3.280E+03 2.980E+03 TE-127M 9.160E+04 9.160E+04 9.160E+04 9.160E+04 9.160E+04 9.160E+04 1.080E+05 9.160E+04 TE-129 2.620E+04 2.620E+04 2.620E+04 2.620E+04 2.620E+04 2.620E+04 3.100E+04 2.620E+04 TE-129M 1.980E+07 1.980E+07 1.980E+07 1.980E+07 1.980E+07 1.980E+07 2.310E+07 1.980E+07 TE-131 2.920E+04 2.920E+04 2.920E+04 2.920E+04 2.920E+04 2.920E+04 3.450E+07 2.920E+04 TE-131M 8.030E+06 8.030E+06 8.030E+06 8.030E+06 8.030E+06 8.030E+06 9.460E+06 8.030E+06 TE-132 4.230E+06 4.230E+06 4.230E+06 4.230E+06 4.230E+06 4.230E+06 4.980E+06 4.230E+06 I-130 5.510E+06 5.510E+06 5.510E+06 5.510E+06 5.510E+06 5.510E+06 6.690E+06 5.510E+06 Appendix H Ri Teen Ground Plane Deposition - Page 2 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX H Ri Teen Dose Factors for use in the Gaseous Dose Calculations Agegroup: TEEN Pathway: Ground Plane Deposition (GPD) Units: m2*mrem/yr / Ci/sec Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body I-131 1.720E+07 1.720E+07 1.720E+07 1.720E+07 1.720E+07 1.720E+07 2.090E+07 1.720E+07 I-132 1.250E+06 1.250E+06 1.250E+06 1.250E+06 1.250E+06 1.250E+06 1.470E+06 1.250E+06 I-133 2.450E+06 2.450E+06 2.450E+06 2.450E+06 2.450E+06 2.450E+06 2.980E+06 2.450E+06 I-134 4.470E+05 4.470E+05 4.470E+05 4.470E+05 4.470E+05 4.470E+05 5.300E+05 4.470E+05 I-135 2.530E+06 2.530E+06 2.530E+06 2.530E+06 2.530E+06 2.530E+06 2.950E+06 2.530E+06 CS-134 6.860E+09 6.860E+09 6.860E+09 6.860E+09 6.860E+09 6.860E+09 8.000E+09 6.860E+09 CS-136 1.510E+08 1.510E+08 1.510E+08 1.510E+08 1.510E+08 1.510E+08 1.710E+08 1.510E+08 CS-137 1.030E+10 1.030E+10 1.030E+10 1.030E+10 1.030E+10 1.030E+10 1.200E+10 1.030E+10 CS-138 3.590E+05 3.590E+05 3.590E+05 3.590E+05 3.590E+05 3.590E+05 4.100E+05 3.590E+05 BA-139 1.060E+05 1.060E+05 1.060E+05 1.060E+05 1.060E+05 1.060E+05 1.190E+05 1.060E+05 BA-140 2.050E+07 2.050E+07 2.050E+07 2.050E+07 2.050E+07 2.050E+07 2.350E+07 2.050E+07 BA-141 4.170E+04 4.170E+04 4.170E+04 4.170E+04 4.170E+04 4.170E+04 4.750E+04 4.170E+04 BA-142 4.490E+04 4.490E+04 4.490E+04 4.490E+04 4.490E+04 4.490E+04 5.110E+04 4.490E+04 LA-140 1.920E+07 1.920E+07 1.920E+07 1.920E+07 1.920E+07 1.920E+07 2.180E+07 1.920E+07 LA-142 7.600E+05 7.600E+05 7.600E+05 7.600E+05 7.600E+05 7.600E+05 9.120E+05 7.600E+05 CE-141 1.370E+07 1.370E+07 1.370E+07 1.370E+07 1.370E+07 1.370E+07 1.540E+07 1.370E+07 CE-143 2.310E+06 2.310E+06 2.310E+06 2.310E+06 2.310E+06 2.310E+06 2.630E+06 2.310E+06 CE-144 6.950E+07 6.950E+07 6.950E+07 6.950E+07 6.950E+07 6.950E+07 8.040E+07 6.950E+07 PR-143 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 PR-144 1.830E+03 1.830E+03 1.830E+03 1.830E+03 1.830E+03 1.830E+03 2.110E+03 1.830E+03 ND-147 8.390E+06 8.390E+06 8.390E+06 8.390E+06 8.390E+06 8.390E+06 1.010E+07 8.390E+06 W-187 2.350E+06 2.350E+06 2.350E+06 2.350E+06 2.350E+06 2.350E+06 2.730E+06 2.350E+06 NP-239 1.710E+06 1.710E+06 1.710E+06 1.710E+06 1.710E+06 1.710E+06 1.980E+06 1.710E+06 Appendix H Ri Teen Ground Plane Deposition - Page 3 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX I Ri Child Dose Factors for use in the Gaseous Dose Calculations Agegroup: CHILD Pathway: Grs/Cow/Milk (CMILK) Units: m2*mrem/yr / Ci/sec; mrem/yr / Ci/m3 (H-3)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body H-3 0.000E+00 1.570E+03 1.570E+03 1.570E+03 1.570E+03 1.570E+03 0.000E+00 1.570E+03 C-14 1.190E+09 2.390E+08 2.390E+08 2.390E+08 2.390E+08 2.390E+08 0.000E+00 2.390E+08 NA-24 8.850E+06 8.850E+06 8.850E+06 8.850E+06 8.850E+06 8.850E+06 0.000E+00 8.850E+06 P-32 7.780E+10 3.640E+09 0.000E+00 0.000E+00 0.000E+00 2.150E+09 0.000E+00 3.000E+09 CR-51 0.000E+00 0.000E+00 5.650E+04 1.540E+04 1.030E+05 5.400E+06 0.000E+00 1.020E+05 MN-54 0.000E+00 2.100E+07 0.000E+00 5.880E+06 0.000E+00 1.760E+07 0.000E+00 5.590E+06 MN-56 0.000E+00 1.260E-02 0.000E+00 1.530E-02 0.000E+00 1.830E+00 0.000E+00 2.860E-03 FE-55 1.120E+08 5.930E+07 0.000E+00 0.000E+00 3.350E+07 1.100E+07 0.000E+00 1.840E+07 FE-59 1.200E+08 1.950E+08 0.000E+00 0.000E+00 5.640E+07 2.030E+08 0.000E+00 9.690E+07 CO-58 0.000E+00 1.210E+07 0.000E+00 0.000E+00 0.000E+00 7.070E+07 0.000E+00 3.710E+07 CO-60 0.000E+00 4.320E+07 0.000E+00 0.000E+00 0.000E+00 2.390E+08 0.000E+00 1.270E+08 NI-63 2.960E+10 1.590E+09 0.000E+00 0.000E+00 0.000E+00 1.070E+08 0.000E+00 1.010E+09 NI-65 1.660E+00 1.560E-01 0.000E+00 0.000E+00 0.000E+00 1.910E+01 0.000E+00 9.100E-02 CU-64 0.000E+00 7.460E+04 0.000E+00 1.800E+05 0.000E+00 3.500E+06 0.000E+00 4.510E+04 ZN-65 4.130E+09 1.100E+10 0.000E+00 6.940E+09 0.000E+00 1.930E+09 0.000E+00 6.850E+09 ZN-69 9.460E-12 1.370E-11 0.000E+00 8.300E-12 0.000E+00 8.620E-10 0.000E+00 1.260E-12 BR-83 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4.400E-01 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 6.510E-23 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 0.000E+00 8.770E+09 0.000E+00 0.000E+00 0.000E+00 5.640E+08 0.000E+00 5.390E+09 RB-88 0.000E+00 7.160E-45 0.000E+00 0.000E+00 0.000E+00 3.510E-46 0.000E+00 4.970E-45 RB-89 0.000E+00 1.340E-52 0.000E+00 0.000E+00 0.000E+00 1.170E-54 0.000E+00 1.190E-52 SR-89 6.620E+09 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.560E+08 0.000E+00 1.890E+08 SR-90 1.120E+11 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.510E+09 0.000E+00 2.830E+10 SR-91 1.300E+05 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.880E+05 0.000E+00 4.920E+03 Appendix I Ri Child Cow Milk - Page 1 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX I Ri Child Dose Factors for use in the Gaseous Dose Calculations Agegroup: CHILD Pathway: Grs/Cow/Milk (CMILK) Units: m2*mrem/yr / Ci/sec; mrem/yr / Ci/m3 (H-3)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body SR-92 2.180E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4.130E+01 0.000E+00 8.750E-02 Y-90 3.220E+02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 9.170E+05 0.000E+00 8.620E+00 Y-91 3.900E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.200E+06 0.000E+00 1.040E+03 Y-91M 2.670E-19 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.240E-16 0.000E+00 9.730E-21 Y-92 2.530E-04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 7.310E+00 0.000E+00 7.240E-06 Y-93 1.010E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.510E+04 0.000E+00 2.780E-02 ZR-95 3.830E+03 8.420E+02 0.000E+00 1.210E+03 0.000E+00 8.790E+05 0.000E+00 7.500E+02 ZR-97 1.920E+00 2.770E-01 0.000E+00 3.980E-01 0.000E+00 4.200E+04 0.000E+00 1.640E-01 NB-95 3.180E+05 1.240E+05 0.000E+00 1.160E+05 0.000E+00 2.290E+08 0.000E+00 8.840E+04 MO-99 0.000E+00 8.140E+07 0.000E+00 1.740E+08 0.000E+00 6.730E+07 0.000E+00 2.010E+07 TC-99M 1.320E+01 2.590E+01 0.000E+00 3.760E+02 1.320E+01 1.470E+04 0.000E+00 4.290E+02 TC-101 1.160E-59 1.220E-59 0.000E+00 2.080E-58 6.440E-60 3.870E-59 0.000E+00 1.540E-58 RU-103 4.280E+03 0.000E+00 0.000E+00 1.080E+04 0.000E+00 1.110E+05 0.000E+00 1.650E+03 RU-105 3.820E-03 0.000E+00 0.000E+00 3.360E-02 0.000E+00 2.490E+00 0.000E+00 1.390E-03 RU-106 9.240E+04 0.000E+00 0.000E+00 1.250E+05 0.000E+00 1.440E+06 0.000E+00 1.150E+04 AG-110M 2.090E+08 1.410E+08 0.000E+00 2.630E+08 0.000E+00 1.680E+10 0.000E+00 1.130E+08 TE-125M 7.380E+07 2.000E+07 2.070E+07 0.000E+00 0.000E+00 7.120E+07 0.000E+00 9.840E+06 TE-127 2.980E+03 8.020E+02 2.060E+03 8.470E+03 0.000E+00 1.160E+05 0.000E+00 6.380E+02 TE-127M 2.080E+08 5.600E+07 4.970E+07 5.930E+08 0.000E+00 1.680E+08 0.000E+00 2.470E+07 TE-129 1.280E-09 3.580E-10 9.160E-10 3.750E-09 0.000E+00 7.990E-08 0.000E+00 3.050E-10 TE-129M 2.710E+08 7.580E+07 8.750E+07 7.970E+08 0.000E+00 3.310E+08 0.000E+00 4.210E+07 TE-131 1.620E-32 4.920E-33 1.240E-32 4.890E-32 0.000E+00 8.490E-32 0.000E+00 4.810E-33 TE-131M 1.600E+06 5.530E+05 1.140E+06 5.350E+06 0.000E+00 2.240E+07 0.000E+00 5.890E+05 TE-132 1.020E+07 4.530E+06 6.600E+06 4.210E+07 0.000E+00 4.570E+07 0.000E+00 5.480E+06 I-130 1.730E+06 3.490E+06 3.840E+08 5.220E+06 0.000E+00 1.630E+06 0.000E+00 1.800E+06 Appendix I Ri Child Cow Milk - Page 2 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX I Ri Child Dose Factors for use in the Gaseous Dose Calculations Agegroup: CHILD Pathway: Grs/Cow/Milk (CMILK) Units: m2*mrem/yr / Ci/sec; mrem/yr / Ci/m3 (H-3)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body I-131 1.300E+09 1.310E+09 4.330E+11 2.150E+09 0.000E+00 1.170E+08 0.000E+00 7.450E+08 I-132 6.890E-01 1.270E+00 5.870E+01 1.940E+00 0.000E+00 1.490E+00 0.000E+00 5.820E-01 I-133 1.720E+07 2.120E+07 3.940E+09 3.540E+07 0.000E+00 8.560E+06 0.000E+00 8.030E+06 I-134 8.480E-12 1.570E-11 3.620E-10 2.410E-11 0.000E+00 1.040E-11 0.000E+00 7.250E-12 I-135 5.400E+04 9.720E+04 8.610E+06 1.490E+05 0.000E+00 7.400E+04 0.000E+00 4.600E+04 CS-134 2.260E+10 3.720E+10 0.000E+00 1.150E+10 4.130E+09 2.000E+08 0.000E+00 7.840E+09 CS-136 1.010E+09 2.780E+09 0.000E+00 1.480E+09 2.210E+08 9.770E+07 0.000E+00 1.800E+09 CS-137 3.220E+10 3.090E+10 0.000E+00 1.010E+10 3.620E+09 1.930E+08 0.000E+00 4.550E+09 CS-138 3.980E-23 5.530E-23 0.000E+00 3.890E-23 4.190E-24 2.550E-23 0.000E+00 3.510E-23 BA-139 2.010E-07 1.070E-10 0.000E+00 9.360E-11 6.300E-11 1.160E-05 0.000E+00 5.820E-09 BA-140 1.170E+08 1.030E+05 0.000E+00 3.340E+04 6.120E+04 5.930E+07 0.000E+00 6.840E+06 BA-141 1.850E-45 1.040E-48 0.000E+00 8.960E-49 6.090E-48 1.050E-45 0.000E+00 6.020E-47 BA-142 1.150E-79 8.310E-83 0.000E+00 6.720E-83 4.890E-83 1.510E-81 0.000E+00 6.450E-81 LA-140 1.940E+01 6.780E+00 0.000E+00 0.000E+00 0.000E+00 1.890E+05 0.000E+00 2.290E+00 LA-142 8.100E-11 2.580E-11 0.000E+00 0.000E+00 0.000E+00 5.120E-06 0.000E+00 8.090E-12 CE-141 2.190E+04 1.090E+04 0.000E+00 4.780E+03 0.000E+00 1.360E+07 0.000E+00 1.620E+03 CE-143 1.870E+02 1.020E+05 0.000E+00 4.260E+01 0.000E+00 1.490E+06 0.000E+00 1.470E+01 CE-144 1.620E+06 5.090E+05 0.000E+00 2.820E+05 0.000E+00 1.330E+08 0.000E+00 8.660E+04 PR-143 7.180E+02 2.160E+02 0.000E+00 1.170E+02 0.000E+00 7.750E+05 0.000E+00 3.560E+01 PR-144 2.680E-53 8.290E-54 0.000E+00 4.380E-54 0.000E+00 1.780E-50 0.000E+00 1.350E-54 ND-147 4.450E+02 3.600E+02 0.000E+00 1.980E+02 0.000E+00 5.700E+05 0.000E+00 2.790E+01 W-187 2.890E+04 1.710E+04 0.000E+00 0.000E+00 0.000E+00 2.400E+06 0.000E+00 7.670E+03 NP-239 1.720E+01 1.240E+00 0.000E+00 3.580E+00 0.000E+00 9.170E+04 0.000E+00 8.710E-01 Appendix I Ri Child Cow Milk - Page 3 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX I Ri Child Dose Factors for use in the Gaseous Dose Calculations Agegroup: CHILD Pathway: Grs/Goat/Milk (GMILK) Units: m2*mrem/yr / Ci/sec; mrem/yr / Ci/m3 (H-3)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body H-3 0.000E+00 3.200E+03 3.200E+03 3.200E+03 3.200E+03 3.200E+03 0.000E+00 3.200E+03 C-14 1.190E+09 2.390E+08 2.390E+08 2.390E+08 2.390E+08 2.390E+08 0.000E+00 2.390E+08 NA-24 1.060E+06 1.060E+06 1.060E+06 1.060E+06 1.060E+06 1.060E+06 0.000E+00 1.060E+06 P-32 9.330E+10 4.370E+09 0.000E+00 0.000E+00 0.000E+00 2.580E+09 0.000E+00 3.600E+09 CR-51 0.000E+00 0.000E+00 6.780E+03 1.850E+03 1.240E+04 6.480E+05 0.000E+00 1.220E+04 MN-54 0.000E+00 2.520E+06 0.000E+00 7.060E+05 0.000E+00 2.110E+06 0.000E+00 6.700E+05 MN-56 0.000E+00 1.520E-03 0.000E+00 1.840E-03 0.000E+00 2.200E-01 0.000E+00 3.430E-04 FE-55 1.450E+06 7.710E+05 0.000E+00 0.000E+00 4.360E+05 1.430E+05 0.000E+00 2.390E+05 FE-59 1.560E+06 2.530E+06 0.000E+00 0.000E+00 7.330E+05 2.630E+06 0.000E+00 1.260E+06 CO-58 0.000E+00 1.450E+06 0.000E+00 0.000E+00 0.000E+00 8.490E+06 0.000E+00 4.450E+06 CO-60 0.000E+00 5.180E+06 0.000E+00 0.000E+00 0.000E+00 2.870E+07 0.000E+00 1.530E+07 NI-63 3.560E+09 1.900E+08 0.000E+00 0.000E+00 0.000E+00 1.280E+07 0.000E+00 1.210E+08 NI-65 1.990E-01 1.870E-02 0.000E+00 0.000E+00 0.000E+00 2.290E+00 0.000E+00 1.090E-02 CU-64 0.000E+00 8.320E+03 0.000E+00 2.010E+04 0.000E+00 3.900E+05 0.000E+00 5.020E+03 ZN-65 4.960E+08 1.320E+09 0.000E+00 8.330E+08 0.000E+00 2.320E+08 0.000E+00 8.220E+08 ZN-69 1.140E-12 1.640E-12 0.000E+00 9.960E-13 0.000E+00 1.030E-10 0.000E+00 1.520E-13 BR-83 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.280E-02 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 7.820E-24 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 0.000E+00 1.050E+09 0.000E+00 0.000E+00 0.000E+00 6.770E+07 0.000E+00 6.470E+08 RB-88 0.000E+00 8.590E-46 0.000E+00 0.000E+00 0.000E+00 4.210E-47 0.000E+00 5.970E-46 RB-89 0.000E+00 1.610E-53 0.000E+00 0.000E+00 0.000E+00 1.410E-55 0.000E+00 1.430E-53 SR-89 1.390E+10 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.380E+08 0.000E+00 3.970E+08 SR-90 2.350E+11 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.160E+09 0.000E+00 5.950E+10 SR-91 2.740E+05 0.000E+00 0.000E+00 0.000E+00 0.000E+00 6.040E+05 0.000E+00 1.030E+04 Appendix I Ri Child Goat Milk - Page 1 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX I Ri Child Dose Factors for use in the Gaseous Dose Calculations Agegroup: CHILD Pathway: Grs/Goat/Milk (GMILK) Units: m2*mrem/yr / Ci/sec; mrem/yr / Ci/m3 (H-3)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body SR-92 4.580E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 8.680E+01 0.000E+00 1.840E-01 Y-90 3.870E+01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.100E+05 0.000E+00 1.030E+00 Y-91 4.680E+03 0.000E+00 0.000E+00 0.000E+00 0.000E+00 6.240E+05 0.000E+00 1.250E+02 Y-91M 3.210E-20 0.000E+00 0.000E+00 0.000E+00 0.000E+00 6.280E-17 0.000E+00 1.170E-21 Y-92 3.040E-05 0.000E+00 0.000E+00 0.000E+00 0.000E+00 8.770E-01 0.000E+00 8.690E-07 Y-93 1.210E-01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.810E+03 0.000E+00 3.330E-03 ZR-95 4.600E+02 1.010E+02 0.000E+00 1.450E+02 0.000E+00 1.050E+05 0.000E+00 9.000E+01 ZR-97 2.300E-01 3.330E-02 0.000E+00 4.780E-02 0.000E+00 5.040E+03 0.000E+00 1.960E-02 NB-95 3.810E+04 1.490E+04 0.000E+00 1.400E+04 0.000E+00 2.750E+07 0.000E+00 1.060E+04 MO-99 0.000E+00 9.760E+06 0.000E+00 2.090E+07 0.000E+00 8.080E+06 0.000E+00 2.420E+06 TC-99M 1.590E+00 3.110E+00 0.000E+00 4.520E+01 1.580E+00 1.770E+03 0.000E+00 5.150E+01 TC-101 1.400E-60 1.460E-60 0.000E+00 2.490E-59 7.720E-61 4.640E-60 0.000E+00 1.850E-59 RU-103 5.140E+02 0.000E+00 0.000E+00 1.290E+03 0.000E+00 1.330E+04 0.000E+00 1.980E+02 RU-105 4.580E-04 0.000E+00 0.000E+00 4.030E-03 0.000E+00 2.990E-01 0.000E+00 1.660E-04 RU-106 1.110E+04 0.000E+00 0.000E+00 1.500E+04 0.000E+00 1.720E+05 0.000E+00 1.380E+03 AG-110M 2.510E+07 1.690E+07 0.000E+00 3.150E+07 0.000E+00 2.010E+09 0.000E+00 1.350E+07 TE-125M 8.850E+06 2.400E+06 2.480E+06 0.000E+00 0.000E+00 8.540E+06 0.000E+00 1.180E+06 TE-127 3.570E+02 9.630E+01 2.470E+02 1.020E+03 0.000E+00 1.390E+04 0.000E+00 7.660E+01 TE-127M 2.500E+07 6.720E+06 5.970E+06 7.120E+07 0.000E+00 2.020E+07 0.000E+00 2.960E+06 TE-129 1.540E-10 4.300E-11 1.100E-10 4.510E-10 0.000E+00 9.590E-09 0.000E+00 3.660E-11 TE-129M 3.260E+07 9.090E+06 1.050E+07 9.560E+07 0.000E+00 3.970E+07 0.000E+00 5.060E+06 TE-131 1.940E-33 5.910E-34 1.480E-33 5.860E-33 0.000E+00 1.020E-32 0.000E+00 5.770E-34 TE-131M 1.920E+05 6.640E+04 1.360E+05 6.420E+05 0.000E+00 2.690E+06 0.000E+00 7.060E+04 TE-132 1.230E+06 5.440E+05 7.920E+05 5.050E+06 0.000E+00 5.480E+06 0.000E+00 6.570E+05 I-130 2.070E+06 4.190E+06 4.610E+08 6.260E+06 0.000E+00 1.960E+06 0.000E+00 2.160E+06 Appendix I Ri Child Goat Milk - Page 2 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX I Ri Child Dose Factors for use in the Gaseous Dose Calculations Agegroup: CHILD Pathway: Grs/Goat/Milk (GMILK) Units: m2*mrem/yr / Ci/sec; mrem/yr / Ci/m3 (H-3)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body I-131 1.560E+09 1.570E+09 5.200E+11 2.580E+09 0.000E+00 1.400E+08 0.000E+00 8.940E+08 I-132 8.270E-01 1.520E+00 7.050E+01 2.330E+00 0.000E+00 1.790E+00 0.000E+00 6.990E-01 I-133 2.060E+07 2.550E+07 4.730E+09 4.250E+07 0.000E+00 1.030E+07 0.000E+00 9.640E+06 I-134 1.020E-11 1.890E-11 4.350E-10 2.890E-11 0.000E+00 1.250E-11 0.000E+00 8.700E-12 I-135 6.480E+04 1.170E+05 1.030E+07 1.790E+05 0.000E+00 8.880E+04 0.000E+00 5.520E+04 CS-134 6.790E+10 1.110E+11 0.000E+00 3.450E+10 1.240E+10 6.010E+08 0.000E+00 2.350E+10 CS-136 3.030E+09 8.340E+09 0.000E+00 4.440E+09 6.630E+08 2.930E+08 0.000E+00 5.400E+09 CS-137 9.670E+10 9.260E+10 0.000E+00 3.020E+10 1.090E+10 5.800E+08 0.000E+00 1.370E+10 CS-138 1.190E-22 1.660E-22 0.000E+00 1.170E-22 1.260E-23 7.640E-23 0.000E+00 1.050E-22 BA-139 2.410E-08 1.290E-11 0.000E+00 1.120E-11 7.560E-12 1.390E-06 0.000E+00 6.980E-10 BA-140 1.410E+07 1.230E+04 0.000E+00 4.010E+03 7.340E+03 7.120E+06 0.000E+00 8.200E+05 BA-141 2.220E-46 1.240E-49 0.000E+00 1.080E-49 7.300E-49 1.270E-46 0.000E+00 7.230E-48 BA-142 1.390E-80 9.970E-84 0.000E+00 8.070E-84 5.870E-84 1.810E-82 0.000E+00 7.740E-82 LA-140 2.330E+00 8.140E-01 0.000E+00 0.000E+00 0.000E+00 2.270E+04 0.000E+00 2.740E-01 LA-142 9.730E-12 3.100E-12 0.000E+00 0.000E+00 0.000E+00 6.140E-07 0.000E+00 9.710E-13 CE-141 2.620E+03 1.310E+03 0.000E+00 5.740E+02 0.000E+00 1.630E+06 0.000E+00 1.940E+02 CE-143 2.250E+01 1.220E+04 0.000E+00 5.120E+00 0.000E+00 1.790E+05 0.000E+00 1.770E+00 CE-144 1.950E+05 6.110E+04 0.000E+00 3.380E+04 0.000E+00 1.590E+07 0.000E+00 1.040E+04 PR-143 8.620E+01 2.590E+01 0.000E+00 1.400E+01 0.000E+00 9.300E+04 0.000E+00 4.280E+00 PR-144 3.220E-54 9.950E-55 0.000E+00 5.260E-55 0.000E+00 2.140E-51 0.000E+00 1.620E-55 ND-147 5.330E+01 4.320E+01 0.000E+00 2.370E+01 0.000E+00 6.850E+04 0.000E+00 3.350E+00 W-187 3.470E+03 2.050E+03 0.000E+00 0.000E+00 0.000E+00 2.880E+05 0.000E+00 9.210E+02 NP-239 2.070E+00 1.490E-01 0.000E+00 4.300E-01 0.000E+00 1.100E+04 0.000E+00 1.040E-01 Appendix I Ri Child Goat Milk - Page 3 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX I Ri Child Dose Factors for use in the Gaseous Dose Calculations Agegroup: CHILD Pathway: Grs/Cow/Meat (CMEAT) Units: m2*mrem/yr / Ci/sec; mrem/yr / Ci/m3 (H-3)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body H-3 0.000E+00 2.340E+02 2.340E+02 2.340E+02 2.340E+02 2.340E+02 0.000E+00 2.340E+02 C-14 3.830E+08 7.670E+07 7.670E+07 7.670E+07 7.670E+07 7.670E+07 0.000E+00 7.670E+07 NA-24 1.720E-03 1.720E-03 1.720E-03 1.720E-03 1.720E-03 1.720E-03 0.000E+00 1.720E-03 P-32 7.420E+09 3.470E+08 0.000E+00 0.000E+00 0.000E+00 2.050E+08 0.000E+00 2.860E+08 CR-51 0.000E+00 0.000E+00 4.880E+03 1.330E+03 8.910E+03 4.660E+05 0.000E+00 8.790E+03 MN-54 0.000E+00 8.010E+06 0.000E+00 2.250E+06 0.000E+00 6.720E+06 0.000E+00 2.130E+06 MN-56 0.000E+00 1.430E-53 0.000E+00 1.730E-53 0.000E+00 2.070E-51 0.000E+00 3.230E-54 FE-55 4.570E+08 2.420E+08 0.000E+00 0.000E+00 1.370E+08 4.490E+07 0.000E+00 7.510E+07 FE-59 3.760E+08 6.090E+08 0.000E+00 0.000E+00 1.770E+08 6.340E+08 0.000E+00 3.030E+08 CO-58 0.000E+00 1.640E+07 0.000E+00 0.000E+00 0.000E+00 9.580E+07 0.000E+00 5.020E+07 CO-60 0.000E+00 6.930E+07 0.000E+00 0.000E+00 0.000E+00 3.840E+08 0.000E+00 2.040E+08 NI-63 2.910E+10 1.560E+09 0.000E+00 0.000E+00 0.000E+00 1.050E+08 0.000E+00 9.910E+08 NI-65 3.520E-52 3.310E-53 0.000E+00 0.000E+00 0.000E+00 4.060E-51 0.000E+00 1.930E-53 CU-64 0.000E+00 2.970E-07 0.000E+00 7.180E-07 0.000E+00 1.390E-05 0.000E+00 1.800E-07 ZN-65 3.750E+08 1.000E+09 0.000E+00 6.300E+08 0.000E+00 1.760E+08 0.000E+00 6.220E+08 ZN-69 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-83 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 9.520E-57 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 0.000E+00 5.770E+08 0.000E+00 0.000E+00 0.000E+00 3.710E+07 0.000E+00 3.550E+08 RB-88 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-89 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 SR-89 4.820E+08 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.870E+07 0.000E+00 1.380E+07 SR-90 1.040E+10 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.400E+08 0.000E+00 2.640E+09 SR-91 2.400E-10 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.300E-10 0.000E+00 9.050E-12 Appendix I Ri Child Cow Meat - Page 1 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX I Ri Child Dose Factors for use in the Gaseous Dose Calculations Agegroup: CHILD Pathway: Grs/Cow/Meat (CMEAT) Units: m2*mrem/yr / Ci/sec; mrem/yr / Ci/m3 (H-3)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body SR-92 1.850E-49 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.490E-48 0.000E+00 7.400E-51 Y-90 1.710E+02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4.880E+05 0.000E+00 4.590E+00 Y-91 1.800E+06 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.400E+08 0.000E+00 4.820E+04 Y-91M 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Y-92 2.410E-39 0.000E+00 0.000E+00 0.000E+00 0.000E+00 6.960E-35 0.000E+00 6.890E-41 Y-93 7.440E-12 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.110E-07 0.000E+00 2.040E-13 ZR-95 2.660E+06 5.850E+05 0.000E+00 8.380E+05 0.000E+00 6.110E+08 0.000E+00 5.210E+05 ZR-97 3.200E-05 4.630E-06 0.000E+00 6.650E-06 0.000E+00 7.010E-01 0.000E+00 2.730E-06 NB-95 3.100E+06 1.210E+06 0.000E+00 1.130E+06 0.000E+00 2.230E+09 0.000E+00 8.620E+05 MO-99 0.000E+00 1.150E+05 0.000E+00 2.460E+05 0.000E+00 9.510E+04 0.000E+00 2.840E+04 TC-99M 6.190E-21 1.210E-20 0.000E+00 1.760E-19 6.160E-21 6.910E-18 0.000E+00 2.010E-19 TC-101 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RU-103 1.550E+08 0.000E+00 0.000E+00 3.900E+08 0.000E+00 4.010E+09 0.000E+00 5.960E+07 RU-105 9.020E-28 0.000E+00 0.000E+00 7.930E-27 0.000E+00 5.890E-25 0.000E+00 3.270E-28 RU-106 4.440E+09 0.000E+00 0.000E+00 5.990E+09 0.000E+00 6.900E+10 0.000E+00 5.540E+08 AG-110M 8.390E+06 5.670E+06 0.000E+00 1.060E+07 0.000E+00 6.740E+08 0.000E+00 4.530E+06 TE-125M 5.690E+08 1.540E+08 1.600E+08 0.000E+00 0.000E+00 5.490E+08 0.000E+00 7.590E+07 TE-127 3.380E-10 9.120E-11 2.340E-10 9.630E-10 0.000E+00 1.320E-08 0.000E+00 7.260E-11 TE-127M 1.770E+09 4.780E+08 4.240E+08 5.060E+09 0.000E+00 1.440E+09 0.000E+00 2.110E+08 TE-129 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 TE-129M 1.790E+09 5.000E+08 5.770E+08 5.260E+09 0.000E+00 2.180E+09 0.000E+00 2.780E+08 TE-131 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 TE-131M 7.000E+02 2.420E+02 4.980E+02 2.340E+03 0.000E+00 9.820E+03 0.000E+00 2.580E+02 TE-132 2.120E+06 9.380E+05 1.370E+06 8.710E+06 0.000E+00 9.450E+06 0.000E+00 1.130E+06 I-130 3.030E-06 6.130E-06 6.750E-04 9.160E-06 0.000E+00 2.870E-06 0.000E+00 3.160E-06 Appendix I Ri Child Cow Meat - Page 2 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX I Ri Child Dose Factors for use in the Gaseous Dose Calculations Agegroup: CHILD Pathway: Grs/Cow/Meat (CMEAT) Units: m2*mrem/yr / Ci/sec; mrem/yr / Ci/m3 (H-3)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body I-131 1.650E+07 1.660E+07 5.500E+09 2.730E+07 0.000E+00 1.480E+06 0.000E+00 9.460E+06 I-132 1.020E-58 1.880E-58 8.730E-57 2.880E-58 0.000E+00 2.210E-58 0.000E+00 8.650E-59 I-133 5.670E-01 7.020E-01 1.300E+02 1.170E+00 0.000E+00 2.830E-01 0.000E+00 2.660E-01 I-134 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 I-135 6.510E-17 1.170E-16 1.040E-14 1.800E-16 0.000E+00 8.930E-17 0.000E+00 5.550E-17 CS-134 9.220E+08 1.510E+09 0.000E+00 4.690E+08 1.680E+08 8.160E+06 0.000E+00 3.190E+08 CS-136 1.620E+07 4.460E+07 0.000E+00 2.370E+07 3.540E+06 1.570E+06 0.000E+00 2.880E+07 CS-137 1.330E+09 1.280E+09 0.000E+00 4.160E+08 1.500E+08 7.990E+06 0.000E+00 1.880E+08 CS-138 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BA-139 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BA-140 4.380E+07 3.840E+04 0.000E+00 1.250E+04 2.290E+04 2.220E+07 0.000E+00 2.560E+06 BA-141 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BA-142 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 LA-140 5.590E-02 1.950E-02 0.000E+00 0.000E+00 0.000E+00 5.440E+02 0.000E+00 6.580E-03 LA-142 5.300E-92 1.690E-92 0.000E+00 0.000E+00 0.000E+00 3.350E-87 0.000E+00 5.290E-93 CE-141 2.220E+04 1.110E+04 0.000E+00 4.850E+03 0.000E+00 1.380E+07 0.000E+00 1.640E+03 CE-143 3.170E-02 1.720E+01 0.000E+00 7.210E-03 0.000E+00 2.520E+02 0.000E+00 2.490E-03 CE-144 2.320E+06 7.260E+05 0.000E+00 4.020E+05 0.000E+00 1.890E+08 0.000E+00 1.240E+05 PR-143 3.340E+04 1.000E+04 0.000E+00 5.430E+03 0.000E+00 3.600E+07 0.000E+00 1.660E+03 PR-144 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 ND-147 1.170E+04 9.470E+03 0.000E+00 5.190E+03 0.000E+00 1.500E+07 0.000E+00 7.330E+02 W-187 3.210E-02 1.900E-02 0.000E+00 0.000E+00 0.000E+00 2.670E+00 0.000E+00 8.530E-03 NP-239 4.260E-01 3.060E-02 0.000E+00 8.850E-02 0.000E+00 2.260E+03 0.000E+00 2.150E-02 Appendix I Ri Child Cow Meat - Page 3 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX I Ri Child Dose Factors for use in the Gaseous Dose Calculations Agegroup: CHILD Pathway: Vegetation (VEG) Units: m2*mrem/yr / Ci/sec; mrem/yr / Ci/m3 (H-3)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body H-3 0.000E+00 4.010E+03 4.010E+03 4.010E+03 4.010E+03 4.010E+03 0.000E+00 4.010E+03 C-14 8.890E+08 1.780E+08 1.780E+08 1.780E+08 1.780E+08 1.780E+08 0.000E+00 1.780E+08 NA-24 3.730E+05 3.730E+05 3.730E+05 3.730E+05 3.730E+05 3.730E+05 0.000E+00 3.730E+05 P-32 3.370E+09 1.580E+08 0.000E+00 0.000E+00 0.000E+00 9.310E+07 0.000E+00 1.300E+08 CR-51 0.000E+00 0.000E+00 6.500E+04 1.780E+04 1.190E+05 6.210E+06 0.000E+00 1.170E+05 MN-54 0.000E+00 6.650E+08 0.000E+00 1.860E+08 0.000E+00 5.580E+08 0.000E+00 1.770E+08 MN-56 0.000E+00 1.860E+01 0.000E+00 2.250E+01 0.000E+00 2.700E+03 0.000E+00 4.200E+00 FE-55 8.010E+08 4.250E+08 0.000E+00 0.000E+00 2.400E+08 7.870E+07 0.000E+00 1.320E+08 FE-59 3.980E+08 6.430E+08 0.000E+00 0.000E+00 1.860E+08 6.700E+08 0.000E+00 3.200E+08 CO-58 0.000E+00 6.440E+07 0.000E+00 0.000E+00 0.000E+00 3.760E+08 0.000E+00 1.970E+08 CO-60 0.000E+00 3.780E+08 0.000E+00 0.000E+00 0.000E+00 2.100E+09 0.000E+00 1.120E+09 NI-63 3.950E+10 2.110E+09 0.000E+00 0.000E+00 0.000E+00 1.420E+08 0.000E+00 1.340E+09 NI-65 1.050E+02 9.890E+00 0.000E+00 0.000E+00 0.000E+00 1.210E+03 0.000E+00 5.770E+00 CU-64 0.000E+00 1.100E+04 0.000E+00 2.660E+04 0.000E+00 5.160E+05 0.000E+00 6.640E+03 ZN-65 8.130E+08 2.160E+09 0.000E+00 1.360E+09 0.000E+00 3.800E+08 0.000E+00 1.350E+09 ZN-69 9.490E-06 1.370E-05 0.000E+00 8.320E-06 0.000E+00 8.640E-04 0.000E+00 1.270E-06 BR-83 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.370E+00 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.820E-11 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 0.000E+00 4.520E+08 0.000E+00 0.000E+00 0.000E+00 2.910E+07 0.000E+00 2.780E+08 RB-88 0.000E+00 4.380E-22 0.000E+00 0.000E+00 0.000E+00 2.150E-23 0.000E+00 3.040E-22 RB-89 0.000E+00 4.610E-26 0.000E+00 0.000E+00 0.000E+00 4.020E-28 0.000E+00 4.090E-26 SR-89 3.600E+10 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.390E+09 0.000E+00 1.030E+09 SR-90 1.240E+12 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.670E+10 0.000E+00 3.150E+11 SR-91 5.240E+05 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.160E+06 0.000E+00 1.980E+04 Appendix I Ri Child Vegetation - Page 1 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX I Ri Child Dose Factors for use in the Gaseous Dose Calculations Agegroup: CHILD Pathway: Vegetation (VEG) Units: m2*mrem/yr / Ci/sec; mrem/yr / Ci/m3 (H-3)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body SR-92 7.280E+02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.380E+04 0.000E+00 2.920E+01 Y-90 2.310E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 6.570E+07 0.000E+00 6.180E+02 Y-91 1.860E+07 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.480E+09 0.000E+00 4.990E+05 Y-91M 8.910E-09 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.740E-05 0.000E+00 3.240E-10 Y-92 1.580E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4.580E+04 0.000E+00 4.530E-02 Y-93 2.930E+02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4.370E+06 0.000E+00 8.040E+00 ZR-95 3.860E+06 8.480E+05 0.000E+00 1.210E+06 0.000E+00 8.850E+08 0.000E+00 7.550E+05 ZR-97 5.700E+02 8.240E+01 0.000E+00 1.180E+02 0.000E+00 1.250E+07 0.000E+00 4.860E+01 NB-95 4.110E+05 1.600E+05 0.000E+00 1.500E+05 0.000E+00 2.960E+08 0.000E+00 1.140E+05 MO-99 0.000E+00 7.710E+06 0.000E+00 1.650E+07 0.000E+00 6.380E+06 0.000E+00 1.910E+06 TC-99M 4.710E+00 9.230E+00 0.000E+00 1.340E+02 4.690E+00 5.260E+03 0.000E+00 1.530E+02 TC-101 1.410E-30 1.470E-30 0.000E+00 2.510E-29 7.780E-31 4.680E-30 0.000E+00 1.870E-29 RU-103 1.530E+07 0.000E+00 0.000E+00 3.860E+07 0.000E+00 3.970E+08 0.000E+00 5.900E+06 RU-105 9.160E+01 0.000E+00 0.000E+00 8.050E+02 0.000E+00 5.980E+04 0.000E+00 3.320E+01 RU-106 7.450E+08 0.000E+00 0.000E+00 1.010E+09 0.000E+00 1.160E+10 0.000E+00 9.300E+07 AG-110M 3.210E+07 2.170E+07 0.000E+00 4.040E+07 0.000E+00 2.580E+09 0.000E+00 1.730E+07 TE-125M 3.510E+08 9.500E+07 9.840E+07 0.000E+00 0.000E+00 3.380E+08 0.000E+00 4.670E+07 TE-127 9.850E+03 2.650E+03 6.810E+03 2.800E+04 0.000E+00 3.850E+05 0.000E+00 2.110E+03 TE-127M 1.320E+09 3.560E+08 3.160E+08 3.770E+09 0.000E+00 1.070E+09 0.000E+00 1.570E+08 TE-129 1.320E-03 3.690E-04 9.430E-04 3.870E-03 0.000E+00 8.230E-02 0.000E+00 3.140E-04 TE-129M 8.410E+08 2.350E+08 2.710E+08 2.470E+09 0.000E+00 1.030E+09 0.000E+00 1.310E+08 TE-131 2.570E-15 7.830E-16 1.960E-15 7.770E-15 0.000E+00 1.350E-14 0.000E+00 7.640E-16 TE-131M 1.540E+06 5.330E+05 1.100E+06 5.160E+06 0.000E+00 2.160E+07 0.000E+00 5.680E+05 TE-132 7.000E+06 3.100E+06 4.510E+06 2.880E+07 0.000E+00 3.120E+07 0.000E+00 3.740E+06 I-130 6.160E+05 1.240E+06 1.370E+08 1.860E+06 0.000E+00 5.820E+05 0.000E+00 6.410E+05 Appendix I Ri Child Vegetation - Page 2 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX I Ri Child Dose Factors for use in the Gaseous Dose Calculations Agegroup: CHILD Pathway: Vegetation (VEG) Units: m2*mrem/yr / Ci/sec; mrem/yr / Ci/m3 (H-3)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body I-131 1.430E+08 1.440E+08 4.750E+10 2.360E+08 0.000E+00 1.280E+07 0.000E+00 8.170E+07 I-132 9.220E+01 1.690E+02 7.860E+03 2.590E+02 0.000E+00 1.990E+02 0.000E+00 7.790E+01 I-133 3.530E+06 4.370E+06 8.110E+08 7.280E+06 0.000E+00 1.760E+06 0.000E+00 1.650E+06 I-134 1.550E-04 2.880E-04 6.620E-03 4.400E-04 0.000E+00 1.910E-04 0.000E+00 1.320E-04 I-135 6.260E+04 1.130E+05 9.970E+06 1.730E+05 0.000E+00 8.580E+04 0.000E+00 5.330E+04 CS-134 1.600E+10 2.630E+10 0.000E+00 8.150E+09 2.930E+09 1.420E+08 0.000E+00 5.550E+09 CS-136 8.240E+07 2.270E+08 0.000E+00 1.210E+08 1.800E+07 7.960E+06 0.000E+00 1.470E+08 CS-137 2.390E+10 2.290E+10 0.000E+00 7.460E+09 2.680E+09 1.430E+08 0.000E+00 3.380E+09 CS-138 6.570E-11 9.130E-11 0.000E+00 6.430E-11 6.920E-12 4.210E-11 0.000E+00 5.790E-11 BA-139 4.950E-02 2.640E-05 0.000E+00 2.310E-05 1.560E-05 2.860E+00 0.000E+00 1.440E-03 BA-140 2.770E+08 2.420E+05 0.000E+00 7.890E+04 1.450E+05 1.400E+08 0.000E+00 1.610E+07 BA-141 1.990E-21 1.110E-24 0.000E+00 9.620E-25 6.530E-24 1.130E-21 0.000E+00 6.460E-23 BA-142 9.930E-39 7.150E-42 0.000E+00 5.780E-42 4.200E-42 1.300E-40 0.000E+00 5.540E-40 LA-140 3.250E+03 1.130E+03 0.000E+00 0.000E+00 0.000E+00 3.160E+07 0.000E+00 3.820E+02 LA-142 3.360E-04 1.070E-04 0.000E+00 0.000E+00 0.000E+00 2.120E+01 0.000E+00 3.350E-05 CE-141 6.560E+05 3.270E+05 0.000E+00 1.430E+05 0.000E+00 4.080E+08 0.000E+00 4.860E+04 CE-143 1.720E+03 9.310E+05 0.000E+00 3.910E+02 0.000E+00 1.360E+07 0.000E+00 1.350E+02 CE-144 1.270E+08 3.980E+07 0.000E+00 2.210E+07 0.000E+00 1.040E+10 0.000E+00 6.780E+06 PR-143 1.460E+05 4.370E+04 0.000E+00 2.370E+04 0.000E+00 1.570E+08 0.000E+00 7.230E+03 PR-144 5.380E-26 1.660E-26 0.000E+00 8.800E-27 0.000E+00 3.580E-23 0.000E+00 2.710E-27 ND-147 7.150E+04 5.790E+04 0.000E+00 3.180E+04 0.000E+00 9.170E+07 0.000E+00 4.480E+03 W-187 6.430E+04 3.810E+04 0.000E+00 0.000E+00 0.000E+00 5.350E+06 0.000E+00 1.710E+04 NP-239 2.560E+03 1.840E+02 0.000E+00 5.310E+02 0.000E+00 1.360E+07 0.000E+00 1.290E+02 Appendix I Ri Child Vegetation - Page 3 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX I Ri Child Dose Factors for use in the Gaseous Dose Calculations Agegroup: CHILD Pathway: Inhalation (INHL) Units: mrem/yr / Ci/m3 Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body H-3 0.000E+00 1.120E+03 1.120E+03 1.120E+03 1.120E+03 1.120E+03 0.000E+00 1.120E+03 C-14 3.590E+04 6.730E+03 6.730E+03 6.730E+03 6.730E+03 6.730E+03 0.000E+00 6.730E+03 NA-24 1.610E+04 1.610E+04 1.610E+04 1.610E+04 1.610E+04 1.610E+04 0.000E+00 1.610E+04 P-32 2.600E+06 1.140E+05 0.000E+00 0.000E+00 0.000E+00 4.220E+04 0.000E+00 9.880E+04 CR-51 0.000E+00 0.000E+00 8.550E+01 2.430E+01 1.700E+04 1.080E+03 0.000E+00 1.540E+02 MN-54 0.000E+00 4.290E+04 0.000E+00 1.000E+04 1.580E+06 2.290E+04 0.000E+00 9.510E+03 MN-56 0.000E+00 1.660E+00 0.000E+00 1.670E+00 1.310E+04 1.230E+05 0.000E+00 3.120E-01 FE-55 4.740E+04 2.520E+04 0.000E+00 0.000E+00 1.110E+05 2.870E+03 0.000E+00 7.770E+03 FE-59 2.070E+04 3.340E+04 0.000E+00 0.000E+00 1.270E+06 7.070E+04 0.000E+00 1.670E+04 CO-58 0.000E+00 1.770E+03 0.000E+00 0.000E+00 1.110E+06 3.440E+04 0.000E+00 3.160E+03 CO-60 0.000E+00 1.310E+04 0.000E+00 0.000E+00 7.070E+06 9.620E+04 0.000E+00 2.260E+04 NI-63 8.210E+05 4.620E+04 0.000E+00 0.000E+00 2.750E+05 6.330E+03 0.000E+00 2.800E+04 NI-65 2.990E+00 2.960E-01 0.000E+00 0.000E+00 8.180E+03 8.400E+04 0.000E+00 1.640E-01 CU-64 0.000E+00 1.990E+00 0.000E+00 6.030E+00 9.580E+03 3.670E+04 0.000E+00 1.070E+00 ZN-65 4.260E+04 1.130E+05 0.000E+00 7.140E+04 9.950E+05 1.630E+04 0.000E+00 7.030E+04 ZN-69 6.700E-02 9.660E-02 0.000E+00 5.850E-02 1.420E+03 1.020E+04 0.000E+00 8.920E-03 BR-83 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4.740E+02 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.480E+02 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.530E+01 RB-86 0.000E+00 1.980E+05 0.000E+00 0.000E+00 0.000E+00 7.990E+03 0.000E+00 1.140E+05 RB-88 0.000E+00 5.620E+02 0.000E+00 0.000E+00 0.000E+00 1.720E+01 0.000E+00 3.660E+02 RB-89 0.000E+00 3.450E+02 0.000E+00 0.000E+00 0.000E+00 1.890E+00 0.000E+00 2.900E+02 SR-89 5.990E+05 0.000E+00 0.000E+00 0.000E+00 2.160E+06 1.670E+05 0.000E+00 1.720E+04 SR-90 1.010E+08 0.000E+00 0.000E+00 0.000E+00 1.480E+07 3.430E+05 0.000E+00 6.440E+06 SR-91 1.210E+02 0.000E+00 0.000E+00 0.000E+00 5.330E+04 1.740E+05 0.000E+00 4.590E+00 Appendix I Ri Child Inhalation - Page 1 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX I Ri Child Dose Factors for use in the Gaseous Dose Calculations Agegroup: CHILD Pathway: Inhalation (INHL) Units: mrem/yr / Ci/m3 Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body SR-92 1.310E+01 0.000E+00 0.000E+00 0.000E+00 2.400E+04 2.420E+05 0.000E+00 5.250E-01 Y-90 4.110E+03 0.000E+00 0.000E+00 0.000E+00 2.620E+05 2.680E+05 0.000E+00 1.110E+02 Y-91 9.140E+05 0.000E+00 0.000E+00 0.000E+00 2.630E+06 1.840E+05 0.000E+00 2.440E+04 Y-91M 5.070E-01 0.000E+00 0.000E+00 0.000E+00 2.810E+03 1.720E+03 0.000E+00 1.840E-02 Y-92 2.030E+01 0.000E+00 0.000E+00 0.000E+00 2.390E+04 2.390E+05 0.000E+00 5.810E-01 Y-93 1.860E+02 0.000E+00 0.000E+00 0.000E+00 7.440E+04 3.880E+05 0.000E+00 5.110E+00 ZR-95 1.900E+05 4.180E+04 0.000E+00 5.960E+04 2.230E+06 6.110E+04 0.000E+00 3.700E+04 ZR-97 1.880E+02 2.720E+01 0.000E+00 3.880E+01 1.130E+05 3.510E+05 0.000E+00 1.600E+01 NB-95 2.350E+04 9.180E+03 0.000E+00 8.620E+03 6.140E+05 3.700E+04 0.000E+00 6.550E+03 MO-99 0.000E+00 1.720E+02 0.000E+00 3.920E+02 1.350E+05 1.270E+05 0.000E+00 4.260E+01 TC-99M 1.780E-03 3.480E-03 0.000E+00 5.070E-02 9.510E+02 4.810E+03 0.000E+00 5.770E-02 TC-101 8.100E-05 8.510E-05 0.000E+00 1.450E-03 5.850E+02 1.630E+01 0.000E+00 1.080E-03 RU-103 2.790E+03 0.000E+00 0.000E+00 7.030E+03 6.620E+05 4.480E+04 0.000E+00 1.070E+03 RU-105 1.530E+00 0.000E+00 0.000E+00 1.340E+00 1.590E+04 9.950E+04 0.000E+00 5.550E-01 RU-106 1.360E+05 0.000E+00 0.000E+00 1.840E+05 1.430E+07 4.290E+05 0.000E+00 1.690E+04 AG-110M 1.690E+04 1.140E+04 0.000E+00 2.120E+04 5.480E+06 1.000E+05 0.000E+00 9.140E+03 TE-125M 6.730E+03 2.330E+03 1.920E+03 0.000E+00 4.770E+05 3.380E+04 0.000E+00 9.140E+02 TE-127 2.770E+00 9.510E-01 1.960E+00 7.070E+00 1.000E+04 5.620E+04 0.000E+00 6.100E-01 TE-127M 2.490E+04 8.550E+03 6.070E+03 6.360E+04 1.480E+06 7.140E+04 0.000E+00 3.020E+03 TE-129 9.770E-02 3.500E-02 7.140E-02 2.570E-01 2.930E+03 2.550E+04 0.000E+00 2.380E-02 TE-129M 1.920E+04 6.840E+03 6.330E+03 5.030E+04 1.760E+06 1.820E+05 0.000E+00 3.040E+03 TE-131 2.170E-02 8.440E-03 1.700E-02 5.880E-02 2.050E+03 1.330E+03 0.000E+00 6.590E-03 TE-131M 1.340E+02 5.920E+01 9.770E+01 4.000E+02 2.060E+05 3.080E+05 0.000E+00 5.070E+01 TE-132 4.810E+02 2.720E+02 3.170E+02 1.770E+03 3.770E+05 1.380E+05 0.000E+00 2.630E+02 I-130 8.180E+03 1.640E+04 1.850E+06 2.450E+04 0.000E+00 5.110E+03 0.000E+00 8.440E+03 Appendix I Ri Child Inhalation - Page 2 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX I Ri Child Dose Factors for use in the Gaseous Dose Calculations Agegroup: CHILD Pathway: Inhalation (INHL) Units: mrem/yr / Ci/m3 Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body I-131 4.810E+04 4.810E+04 1.620E+07 7.880E+04 0.000E+00 2.840E+03 0.000E+00 2.730E+04 I-132 2.120E+03 4.070E+03 1.940E+05 6.250E+03 0.000E+00 3.200E+03 0.000E+00 1.880E+03 I-133 1.660E+04 2.030E+04 3.850E+06 3.380E+04 0.000E+00 5.480E+03 0.000E+00 7.700E+03 I-134 1.170E+03 2.160E+03 5.070E+04 3.300E+03 0.000E+00 9.550E+02 0.000E+00 9.950E+02 I-135 4.920E+03 8.730E+03 7.920E+05 1.340E+04 0.000E+00 4.440E+03 0.000E+00 4.140E+03 CS-134 6.510E+05 1.010E+06 0.000E+00 3.300E+05 1.210E+05 3.850E+03 0.000E+00 2.250E+05 CS-136 6.510E+04 1.710E+05 0.000E+00 9.550E+04 1.450E+04 4.180E+03 0.000E+00 1.160E+05 CS-137 9.060E+05 8.250E+05 0.000E+00 2.820E+05 1.040E+05 3.620E+03 0.000E+00 1.280E+05 CS-138 6.330E+02 8.400E+02 0.000E+00 6.220E+02 6.810E+01 2.700E+02 0.000E+00 5.550E+02 BA-139 1.840E+00 9.840E-04 0.000E+00 8.620E-04 5.770E+03 5.770E+04 0.000E+00 5.360E-02 BA-140 7.400E+04 6.480E+01 0.000E+00 2.110E+01 1.740E+06 1.020E+05 0.000E+00 4.330E+03 BA-141 1.960E-01 1.090E-04 0.000E+00 9.470E-05 2.920E+03 2.750E+02 0.000E+00 6.360E-03 BA-142 5.000E-02 3.600E-05 0.000E+00 2.910E-05 1.640E+03 2.740E+00 0.000E+00 2.790E-03 LA-140 6.440E+02 2.250E+02 0.000E+00 0.000E+00 1.830E+05 2.260E+05 0.000E+00 7.550E+01 LA-142 1.300E+00 4.110E-01 0.000E+00 0.000E+00 8.700E+03 7.580E+04 0.000E+00 1.290E-01 CE-141 3.920E+04 1.950E+04 0.000E+00 8.550E+03 5.440E+05 5.660E+04 0.000E+00 2.900E+03 CE-143 3.660E+02 1.990E+02 0.000E+00 8.360E+01 1.150E+05 1.270E+05 0.000E+00 2.870E+01 CE-144 6.770E+06 2.120E+06 0.000E+00 1.170E+06 1.200E+07 3.880E+05 0.000E+00 3.610E+05 PR-143 1.850E+04 5.550E+03 0.000E+00 3.000E+03 4.330E+05 9.730E+04 0.000E+00 9.140E+02 PR-144 5.960E-02 1.850E-02 0.000E+00 9.770E-03 1.570E+03 1.970E+02 0.000E+00 3.000E-03 ND-147 1.080E+04 8.730E+03 0.000E+00 4.810E+03 3.280E+05 8.210E+04 0.000E+00 6.810E+02 W-187 1.630E+01 9.660E+00 0.000E+00 0.000E+00 4.110E+04 9.100E+04 0.000E+00 4.330E+00 NP-239 4.660E+02 3.340E+01 0.000E+00 9.730E+01 5.810E+04 6.400E+04 0.000E+00 2.350E+01 Appendix I Ri Child Inhalation - Page 3 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX I Ri Child Dose Factors for use in the Gaseous Dose Calculations Agegroup: CHILD Pathway: Ground Plane Deposition (GPD) Units: m2*mrem/yr / Ci/sec Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body H-3 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 C-14 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 NA-24 1.190E+07 1.190E+07 1.190E+07 1.190E+07 1.190E+07 1.190E+07 1.390E+07 1.190E+07 P-32 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 CR-51 4.660E+06 4.660E+06 4.660E+06 4.660E+06 4.660E+06 4.660E+06 5.510E+06 4.660E+06 MN-54 1.390E+09 1.390E+09 1.390E+09 1.390E+09 1.390E+09 1.390E+09 1.630E+09 1.390E+09 MN-56 9.020E+05 9.020E+05 9.020E+05 9.020E+05 9.020E+05 9.020E+05 1.070E+06 9.020E+05 FE-55 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 FE-59 2.730E+08 2.730E+08 2.730E+08 2.730E+08 2.730E+08 2.730E+08 3.210E+08 2.730E+08 CO-58 3.790E+08 3.790E+08 3.790E+08 3.790E+08 3.790E+08 3.790E+08 4.440E+08 3.790E+08 CO-60 2.150E+10 2.150E+10 2.150E+10 2.150E+10 2.150E+10 2.150E+10 2.530E+10 2.150E+10 NI-63 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 NI-65 2.970E+05 2.970E+05 2.970E+05 2.970E+05 2.970E+05 2.970E+05 3.450E+05 2.970E+05 CU-64 6.070E+05 6.070E+05 6.070E+05 6.070E+05 6.070E+05 6.070E+05 6.880E+05 6.070E+05 ZN-65 7.470E+08 7.470E+08 7.470E+08 7.470E+08 7.470E+08 7.470E+08 8.590E+08 7.470E+08 ZN-69 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-83 4.870E+03 4.870E+03 4.870E+03 4.870E+03 4.870E+03 4.870E+03 7.080E+03 4.870E+03 BR-84 2.030E+05 2.030E+05 2.030E+05 2.030E+05 2.030E+05 2.030E+05 2.360E+05 2.030E+05 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 8.990E+06 8.990E+06 8.990E+06 8.990E+06 8.990E+06 8.990E+06 1.030E+07 8.990E+06 RB-88 3.310E+04 3.310E+04 3.310E+04 3.310E+04 3.310E+04 3.310E+04 3.780E+04 3.310E+04 RB-89 1.230E+05 1.230E+05 1.230E+05 1.230E+05 1.230E+05 1.230E+05 1.480E+05 1.230E+05 SR-89 2.160E+04 2.160E+04 2.160E+04 2.160E+04 2.160E+04 2.160E+04 2.510E+04 2.160E+04 SR-90 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 SR-91 2.150E+06 2.150E+06 2.150E+06 2.150E+06 2.150E+06 2.150E+06 2.510E+06 2.150E+06 Appendix I Ri Child Ground Plane Deposition - Page 1 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX I Ri Child Dose Factors for use in the Gaseous Dose Calculations Agegroup: CHILD Pathway: Ground Plane Deposition (GPD) Units: m2*mrem/yr / Ci/sec Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body SR-92 7.770E+05 7.770E+05 7.770E+05 7.770E+05 7.770E+05 7.770E+05 8.630E+05 7.770E+05 Y-90 4.490E+03 4.490E+03 4.490E+03 4.490E+03 4.490E+03 4.490E+03 5.310E+03 4.490E+03 Y-91 1.070E+06 1.070E+06 1.070E+06 1.070E+06 1.070E+06 1.070E+06 1.210E+06 1.070E+06 Y-91M 1.000E+05 1.000E+05 1.000E+05 1.000E+05 1.000E+05 1.000E+05 1.160E+05 1.000E+05 Y-92 1.800E+05 1.800E+05 1.800E+05 1.800E+05 1.800E+05 1.800E+05 2.140E+05 1.800E+05 Y-93 1.830E+05 1.830E+05 1.830E+05 1.830E+05 1.830E+05 1.830E+05 2.510E+05 1.830E+05 ZR-95 2.450E+08 2.450E+08 2.450E+08 2.450E+08 2.450E+08 2.450E+08 2.840E+08 2.450E+08 ZR-97 2.960E+06 2.960E+06 2.960E+06 2.960E+06 2.960E+06 2.960E+06 3.440E+06 2.960E+06 NB-95 1.370E+08 1.370E+08 1.370E+08 1.370E+08 1.370E+08 1.370E+08 1.610E+08 1.370E+08 MO-99 3.990E+06 3.990E+06 3.990E+06 3.990E+06 3.990E+06 3.990E+06 4.630E+06 3.990E+06 TC-99M 1.840E+05 1.840E+05 1.840E+05 1.840E+05 1.840E+05 1.840E+05 2.110E+05 1.840E+05 TC-101 2.040E+04 2.040E+04 2.040E+04 2.040E+04 2.040E+04 2.040E+04 2.260E+04 2.040E+04 RU-103 1.080E+08 1.080E+08 1.080E+08 1.080E+08 1.080E+08 1.080E+08 1.260E+08 1.080E+08 RU-105 6.360E+05 6.360E+05 6.360E+05 6.360E+05 6.360E+05 6.360E+05 7.210E+05 6.360E+05 RU-106 4.220E+08 4.220E+08 4.220E+08 4.220E+08 4.220E+08 4.220E+08 5.070E+08 4.220E+08 AG-110M 3.440E+09 3.440E+09 3.440E+09 3.440E+09 3.440E+09 3.440E+09 4.010E+09 3.440E+09 TE-125M 1.550E+06 1.550E+06 1.550E+06 1.550E+06 1.550E+06 1.550E+06 2.130E+06 1.550E+06 TE-127 2.980E+03 2.980E+03 2.980E+03 2.980E+03 2.980E+03 2.980E+03 3.280E+03 2.980E+03 TE-127M 9.160E+04 9.160E+04 9.160E+04 9.160E+04 9.160E+04 9.160E+04 1.080E+05 9.160E+04 TE-129 2.620E+04 2.620E+04 2.620E+04 2.620E+04 2.620E+04 2.620E+04 3.100E+04 2.620E+04 TE-129M 1.980E+07 1.980E+07 1.980E+07 1.980E+07 1.980E+07 1.980E+07 2.310E+07 1.980E+07 TE-131 2.920E+04 2.920E+04 2.920E+04 2.920E+04 2.920E+04 2.920E+04 3.450E+07 2.920E+04 TE-131M 8.030E+06 8.030E+06 8.030E+06 8.030E+06 8.030E+06 8.030E+06 9.460E+06 8.030E+06 TE-132 4.230E+06 4.230E+06 4.230E+06 4.230E+06 4.230E+06 4.230E+06 4.980E+06 4.230E+06 I-130 5.510E+06 5.510E+06 5.510E+06 5.510E+06 5.510E+06 5.510E+06 6.690E+06 5.510E+06 Appendix I Ri Child Ground Plane Deposition - Page 2 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX I Ri Child Dose Factors for use in the Gaseous Dose Calculations Agegroup: CHILD Pathway: Ground Plane Deposition (GPD) Units: m2*mrem/yr / Ci/sec Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body I-131 1.720E+07 1.720E+07 1.720E+07 1.720E+07 1.720E+07 1.720E+07 2.090E+07 1.720E+07 I-132 1.250E+06 1.250E+06 1.250E+06 1.250E+06 1.250E+06 1.250E+06 1.470E+06 1.250E+06 I-133 2.450E+06 2.450E+06 2.450E+06 2.450E+06 2.450E+06 2.450E+06 2.980E+06 2.450E+06 I-134 4.470E+05 4.470E+05 4.470E+05 4.470E+05 4.470E+05 4.470E+05 5.300E+05 4.470E+05 I-135 2.530E+06 2.530E+06 2.530E+06 2.530E+06 2.530E+06 2.530E+06 2.950E+06 2.530E+06 CS-134 6.860E+09 6.860E+09 6.860E+09 6.860E+09 6.860E+09 6.860E+09 8.000E+09 6.860E+09 CS-136 1.510E+08 1.510E+08 1.510E+08 1.510E+08 1.510E+08 1.510E+08 1.710E+08 1.510E+08 CS-137 1.030E+10 1.030E+10 1.030E+10 1.030E+10 1.030E+10 1.030E+10 1.200E+10 1.030E+10 CS-138 3.590E+05 3.590E+05 3.590E+05 3.590E+05 3.590E+05 3.590E+05 4.100E+05 3.590E+05 BA-139 1.060E+05 1.060E+05 1.060E+05 1.060E+05 1.060E+05 1.060E+05 1.190E+05 1.060E+05 BA-140 2.050E+07 2.050E+07 2.050E+07 2.050E+07 2.050E+07 2.050E+07 2.350E+07 2.050E+07 BA-141 4.170E+04 4.170E+04 4.170E+04 4.170E+04 4.170E+04 4.170E+04 4.750E+04 4.170E+04 BA-142 4.490E+04 4.490E+04 4.490E+04 4.490E+04 4.490E+04 4.490E+04 5.110E+04 4.490E+04 LA-140 1.920E+07 1.920E+07 1.920E+07 1.920E+07 1.920E+07 1.920E+07 2.180E+07 1.920E+07 LA-142 7.600E+05 7.600E+05 7.600E+05 7.600E+05 7.600E+05 7.600E+05 9.120E+05 7.600E+05 CE-141 1.370E+07 1.370E+07 1.370E+07 1.370E+07 1.370E+07 1.370E+07 1.540E+07 1.370E+07 CE-143 2.310E+06 2.310E+06 2.310E+06 2.310E+06 2.310E+06 2.310E+06 2.630E+06 2.310E+06 CE-144 6.950E+07 6.950E+07 6.950E+07 6.950E+07 6.950E+07 6.950E+07 8.040E+07 6.950E+07 PR-143 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 PR-144 1.830E+03 1.830E+03 1.830E+03 1.830E+03 1.830E+03 1.830E+03 2.110E+03 1.830E+03 ND-147 8.390E+06 8.390E+06 8.390E+06 8.390E+06 8.390E+06 8.390E+06 1.010E+07 8.390E+06 W-187 2.350E+06 2.350E+06 2.350E+06 2.350E+06 2.350E+06 2.350E+06 2.730E+06 2.350E+06 NP-239 1.710E+06 1.710E+06 1.710E+06 1.710E+06 1.710E+06 1.710E+06 1.980E+06 1.710E+06 Appendix I Ri Child Ground Plane Deposition - Page 3 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX J Ri Infant Dose Factors for use in the Gaseous Dose Calculations Agegroup: INFANT Pathway: Grs/Cow/Milk (CMILK) Units: m2*mrem/yr / Ci/sec; mrem/yr / Ci/m3 (H-3)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body H-3 0.000E+00 2.380E+03 2.380E+03 2.380E+03 2.380E+03 2.380E+03 0.000E+00 2.380E+03 C-14 2.340E+09 5.000E+08 5.000E+08 5.000E+08 5.000E+08 5.000E+08 0.000E+00 5.000E+08 NA-24 1.540E+07 1.540E+07 1.540E+07 1.540E+07 1.540E+07 1.540E+07 0.000E+00 1.540E+07 P-32 1.600E+11 9.430E+09 0.000E+00 0.000E+00 0.000E+00 2.170E+09 0.000E+00 6.210E+09 CR-51 0.000E+00 0.000E+00 1.050E+05 2.300E+04 2.050E+05 4.700E+06 0.000E+00 1.610E+05 MN-54 0.000E+00 3.900E+07 0.000E+00 8.640E+06 0.000E+00 1.430E+07 0.000E+00 8.840E+06 MN-56 0.000E+00 3.100E-02 0.000E+00 2.660E-02 0.000E+00 2.810E+00 0.000E+00 5.340E-03 FE-55 1.350E+08 8.730E+07 0.000E+00 0.000E+00 4.270E+07 1.110E+07 0.000E+00 2.330E+07 FE-59 2.240E+08 3.920E+08 0.000E+00 0.000E+00 1.160E+08 1.870E+08 0.000E+00 1.540E+08 CO-58 0.000E+00 2.420E+07 0.000E+00 0.000E+00 0.000E+00 6.040E+07 0.000E+00 6.050E+07 CO-60 0.000E+00 8.820E+07 0.000E+00 0.000E+00 0.000E+00 2.100E+08 0.000E+00 2.080E+08 NI-63 3.490E+10 2.160E+09 0.000E+00 0.000E+00 0.000E+00 1.070E+08 0.000E+00 1.210E+09 NI-65 3.510E+00 3.970E-01 0.000E+00 0.000E+00 0.000E+00 3.020E+01 0.000E+00 1.800E-01 CU-64 0.000E+00 1.850E+05 0.000E+00 3.140E+05 0.000E+00 3.810E+06 0.000E+00 8.590E+04 ZN-65 5.550E+09 1.900E+10 0.000E+00 9.230E+09 0.000E+00 1.610E+10 0.000E+00 8.780E+09 ZN-69 2.020E-11 3.630E-11 0.000E+00 1.510E-11 0.000E+00 2.960E-09 0.000E+00 2.700E-12 BR-83 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 9.340E-01 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.260E-22 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 0.000E+00 2.230E+10 0.000E+00 0.000E+00 0.000E+00 5.690E+08 0.000E+00 1.100E+10 RB-88 0.000E+00 1.880E-44 0.000E+00 0.000E+00 0.000E+00 1.830E-44 0.000E+00 1.030E-44 RB-89 0.000E+00 3.290E-52 0.000E+00 0.000E+00 0.000E+00 1.120E-52 0.000E+00 2.260E-52 SR-89 1.260E+10 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.590E+08 0.000E+00 3.610E+08 SR-90 1.220E+11 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.520E+09 0.000E+00 3.100E+10 SR-91 2.720E+05 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.220E+05 0.000E+00 9.830E+03 Appendix J Ri Infant Cow Milk - Page 1 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX J Ri Infant Dose Factors for use in the Gaseous Dose Calculations Agegroup: INFANT Pathway: Grs/Cow/Milk (CMILK) Units: m2*mrem/yr / Ci/sec; mrem/yr / Ci/m3 (H-3)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body SR-92 4.640E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.000E+01 0.000E+00 1.720E-01 Y-90 6.810E+02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 9.410E+05 0.000E+00 1.830E+01 Y-91 7.330E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.250E+06 0.000E+00 1.950E+03 Y-91M 5.670E-19 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.890E-15 0.000E+00 1.930E-20 Y-92 5.380E-04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.030E+01 0.000E+00 1.510E-05 Y-93 2.160E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.700E+04 0.000E+00 5.870E-02 ZR-95 6.800E+03 1.660E+03 0.000E+00 1.790E+03 0.000E+00 8.260E+05 0.000E+00 1.180E+03 ZR-97 4.060E+00 6.970E-01 0.000E+00 7.030E-01 0.000E+00 4.450E+04 0.000E+00 3.180E-01 NB-95 5.930E+05 2.440E+05 0.000E+00 1.750E+05 0.000E+00 2.060E+08 0.000E+00 1.410E+05 MO-99 0.000E+00 2.080E+08 0.000E+00 3.110E+08 0.000E+00 6.850E+07 0.000E+00 4.060E+07 TC-99M 2.750E+01 5.670E+01 0.000E+00 6.100E+02 2.960E+01 1.650E+04 0.000E+00 7.300E+02 TC-101 2.470E-59 3.110E-59 0.000E+00 3.700E-58 1.700E-59 5.280E-57 0.000E+00 3.080E-58 RU-103 8.670E+03 0.000E+00 0.000E+00 1.800E+04 0.000E+00 1.050E+05 0.000E+00 2.900E+03 RU-105 8.050E-03 0.000E+00 0.000E+00 5.920E-02 0.000E+00 3.200E+00 0.000E+00 2.710E-03 RU-106 1.900E+05 0.000E+00 0.000E+00 2.250E+05 0.000E+00 1.440E+06 0.000E+00 2.380E+04 AG-110M 3.860E+08 2.820E+08 0.000E+00 4.030E+08 0.000E+00 1.460E+10 0.000E+00 1.860E+08 TE-125M 1.510E+08 5.040E+07 5.070E+07 0.000E+00 0.000E+00 7.180E+07 0.000E+00 2.040E+07 TE-127 6.320E+03 2.120E+03 5.140E+03 1.540E+04 0.000E+00 1.330E+05 0.000E+00 1.360E+03 TE-127M 4.210E+08 1.400E+08 1.220E+08 1.040E+09 0.000E+00 1.700E+08 0.000E+00 5.100E+07 TE-129 2.720E-09 9.380E-10 2.280E-09 6.770E-09 0.000E+00 2.170E-07 0.000E+00 6.350E-10 TE-129M 5.570E+08 1.910E+08 2.140E+08 1.390E+09 0.000E+00 3.330E+08 0.000E+00 8.580E+07 TE-131 3.430E-32 1.270E-32 3.060E-32 8.760E-32 0.000E+00 1.380E-30 0.000E+00 9.610E-33 TE-131M 3.380E+06 1.360E+06 2.750E+06 9.350E+06 0.000E+00 2.290E+07 0.000E+00 1.120E+06 TE-132 2.110E+07 1.040E+07 1.540E+07 6.530E+07 0.000E+00 3.870E+07 0.000E+00 9.750E+06 I-130 3.550E+06 7.810E+06 8.750E+08 8.580E+06 0.000E+00 1.670E+06 0.000E+00 3.130E+06 Appendix J Ri Infant Cow Milk - Page 2 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX J Ri Infant Dose Factors for use in the Gaseous Dose Calculations Agegroup: INFANT Pathway: Grs/Cow/Milk (CMILK) Units: m2*mrem/yr / Ci/sec; mrem/yr / Ci/m3 (H-3)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body I-131 2.720E+09 3.200E+09 1.050E+12 3.740E+09 0.000E+00 1.140E+08 0.000E+00 1.410E+09 I-132 1.430E+00 2.900E+00 1.360E+02 3.240E+00 0.000E+00 2.350E+00 0.000E+00 1.030E+00 I-133 3.630E+07 5.280E+07 9.600E+09 6.210E+07 0.000E+00 8.930E+06 0.000E+00 1.550E+07 I-134 1.760E-11 3.600E-11 8.400E-10 4.030E-11 0.000E+00 3.720E-11 0.000E+00 1.280E-11 I-135 1.120E+05 2.230E+05 2.000E+07 2.490E+05 0.000E+00 8.080E+04 0.000E+00 8.140E+04 CS-134 3.650E+10 6.800E+10 0.000E+00 1.750E+10 7.180E+09 1.850E+08 0.000E+00 6.870E+09 CS-136 1.980E+09 5.810E+09 0.000E+00 2.320E+09 4.740E+08 8.820E+07 0.000E+00 2.170E+09 CS-137 5.150E+10 6.020E+10 0.000E+00 1.620E+10 6.550E+09 1.880E+08 0.000E+00 4.270E+09 CS-138 8.390E-23 1.360E-22 0.000E+00 6.800E-23 1.060E-23 2.180E-22 0.000E+00 6.610E-23 BA-139 4.270E-07 2.830E-10 0.000E+00 1.700E-10 1.720E-10 2.710E-05 0.000E+00 1.240E-08 BA-140 2.410E+08 2.410E+05 0.000E+00 5.720E+04 1.480E+05 5.920E+07 0.000E+00 1.240E+07 BA-141 3.930E-45 2.690E-48 0.000E+00 1.620E-48 1.640E-48 4.800E-44 0.000E+00 1.240E-46 BA-142 2.430E-79 2.020E-82 0.000E+00 1.160E-82 1.220E-82 1.000E-78 0.000E+00 1.200E-80 LA-140 4.050E+01 1.600E+01 0.000E+00 0.000E+00 0.000E+00 1.880E+05 0.000E+00 4.110E+00 LA-142 1.700E-10 6.250E-11 0.000E+00 0.000E+00 0.000E+00 1.060E-05 0.000E+00 1.500E-11 CE-141 4.340E+04 2.640E+04 0.000E+00 8.150E+03 0.000E+00 1.370E+07 0.000E+00 3.110E+03 CE-143 3.970E+02 2.630E+05 0.000E+00 7.670E+01 0.000E+00 1.540E+06 0.000E+00 3.000E+01 CE-144 2.330E+06 9.520E+05 0.000E+00 3.850E+05 0.000E+00 1.330E+08 0.000E+00 1.300E+05 PR-143 1.490E+03 5.550E+02 0.000E+00 2.060E+02 0.000E+00 7.840E+05 0.000E+00 7.360E+01 PR-144 5.690E-53 2.200E-53 0.000E+00 7.980E-54 0.000E+00 1.020E-48 0.000E+00 2.870E-54 ND-147 8.810E+02 9.050E+02 0.000E+00 3.490E+02 0.000E+00 5.740E+05 0.000E+00 5.550E+01 W-187 6.080E+04 4.230E+04 0.000E+00 0.000E+00 0.000E+00 2.480E+06 0.000E+00 1.460E+04 NP-239 3.650E+01 3.260E+00 0.000E+00 6.510E+00 0.000E+00 9.430E+04 0.000E+00 1.840E+00 Appendix J Ri Infant Cow Milk - Page 3 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX J Ri Infant Dose Factors for use in the Gaseous Dose Calculations Agegroup: INFANT Pathway: Grs/Goat/Milk (GMILK) Units: m2*mrem/yr / Ci/sec; mrem/yr / Ci/m3 (H-3)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body H-3 0.000E+00 4.860E+03 4.860E+03 4.860E+03 4.860E+03 4.860E+03 0.000E+00 4.860E+03 C-14 2.340E+09 5.000E+08 5.000E+08 5.000E+08 5.000E+08 5.000E+08 0.000E+00 5.000E+08 NA-24 1.850E+06 1.850E+06 1.850E+06 1.850E+06 1.850E+06 1.850E+06 0.000E+00 1.850E+06 P-32 1.920E+11 1.130E+10 0.000E+00 0.000E+00 0.000E+00 2.600E+09 0.000E+00 7.460E+09 CR-51 0.000E+00 0.000E+00 1.260E+04 2.760E+03 2.460E+04 5.640E+05 0.000E+00 1.940E+04 MN-54 0.000E+00 4.680E+06 0.000E+00 1.040E+06 0.000E+00 1.720E+06 0.000E+00 1.060E+06 MN-56 0.000E+00 3.720E-03 0.000E+00 3.190E-03 0.000E+00 3.380E-01 0.000E+00 6.410E-04 FE-55 1.760E+06 1.130E+06 0.000E+00 0.000E+00 5.550E+05 1.440E+05 0.000E+00 3.030E+05 FE-59 2.920E+06 5.100E+06 0.000E+00 0.000E+00 1.510E+06 2.430E+06 0.000E+00 2.010E+06 CO-58 0.000E+00 2.910E+06 0.000E+00 0.000E+00 0.000E+00 7.250E+06 0.000E+00 7.260E+06 CO-60 0.000E+00 1.060E+07 0.000E+00 0.000E+00 0.000E+00 2.520E+07 0.000E+00 2.500E+07 NI-63 4.190E+09 2.590E+08 0.000E+00 0.000E+00 0.000E+00 1.290E+07 0.000E+00 1.450E+08 NI-65 4.210E-01 4.760E-02 0.000E+00 0.000E+00 0.000E+00 3.620E+00 0.000E+00 2.170E-02 CU-64 0.000E+00 2.070E+04 0.000E+00 3.500E+04 0.000E+00 4.240E+05 0.000E+00 9.570E+03 ZN-65 6.660E+08 2.280E+09 0.000E+00 1.110E+09 0.000E+00 1.930E+09 0.000E+00 1.050E+09 ZN-69 2.420E-12 4.360E-12 0.000E+00 1.810E-12 0.000E+00 3.550E-10 0.000E+00 3.240E-13 BR-83 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.120E-01 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.510E-23 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 0.000E+00 2.670E+09 0.000E+00 0.000E+00 0.000E+00 6.830E+07 0.000E+00 1.320E+09 RB-88 0.000E+00 2.250E-45 0.000E+00 0.000E+00 0.000E+00 2.190E-45 0.000E+00 1.230E-45 RB-89 0.000E+00 3.940E-53 0.000E+00 0.000E+00 0.000E+00 1.340E-53 0.000E+00 2.720E-53 SR-89 2.640E+10 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.430E+08 0.000E+00 7.580E+08 SR-90 2.550E+11 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.190E+09 0.000E+00 6.500E+10 SR-91 5.700E+05 0.000E+00 0.000E+00 0.000E+00 0.000E+00 6.750E+05 0.000E+00 2.060E+04 Appendix J Ri Infant Goat Milk - Page 1 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX J Ri Infant Dose Factors for use in the Gaseous Dose Calculations Agegroup: INFANT Pathway: Grs/Goat/Milk (GMILK) Units: m2*mrem/yr / Ci/sec; mrem/yr / Ci/m3 (H-3)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body SR-92 9.750E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.050E+02 0.000E+00 3.620E-01 Y-90 8.170E+01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.130E+05 0.000E+00 2.190E+00 Y-91 8.790E+03 0.000E+00 0.000E+00 0.000E+00 0.000E+00 6.300E+05 0.000E+00 2.340E+02 Y-91M 6.810E-20 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.270E-16 0.000E+00 2.320E-21 Y-92 6.450E-05 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.230E+00 0.000E+00 1.810E-06 Y-93 2.590E-01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.040E+03 0.000E+00 7.050E-03 ZR-95 8.170E+02 1.990E+02 0.000E+00 2.140E+02 0.000E+00 9.910E+04 0.000E+00 1.410E+02 ZR-97 4.870E-01 8.360E-02 0.000E+00 8.430E-02 0.000E+00 5.340E+03 0.000E+00 3.820E-02 NB-95 7.120E+04 2.930E+04 0.000E+00 2.100E+04 0.000E+00 2.480E+07 0.000E+00 1.700E+04 MO-99 0.000E+00 2.500E+07 0.000E+00 3.730E+07 0.000E+00 8.220E+06 0.000E+00 4.870E+06 TC-99M 3.300E+00 6.800E+00 0.000E+00 7.320E+01 3.550E+00 1.970E+03 0.000E+00 8.760E+01 TC-101 2.960E-60 3.730E-60 0.000E+00 4.440E-59 2.030E-60 6.340E-58 0.000E+00 3.690E-59 RU-103 1.040E+03 0.000E+00 0.000E+00 2.170E+03 0.000E+00 1.270E+04 0.000E+00 3.480E+02 RU-105 9.660E-04 0.000E+00 0.000E+00 7.110E-03 0.000E+00 3.840E-01 0.000E+00 3.250E-04 RU-106 2.280E+04 0.000E+00 0.000E+00 2.700E+04 0.000E+00 1.730E+05 0.000E+00 2.850E+03 AG-110M 4.630E+07 3.380E+07 0.000E+00 4.830E+07 0.000E+00 1.750E+09 0.000E+00 2.240E+07 TE-125M 1.810E+07 6.050E+06 6.090E+06 0.000E+00 0.000E+00 8.620E+06 0.000E+00 2.450E+06 TE-127 7.580E+02 2.540E+02 6.170E+02 1.850E+03 0.000E+00 1.590E+04 0.000E+00 1.630E+02 TE-127M 5.050E+07 1.680E+07 1.460E+07 1.240E+08 0.000E+00 2.040E+07 0.000E+00 6.120E+06 TE-129 3.260E-10 1.130E-10 2.740E-10 8.130E-10 0.000E+00 2.610E-08 0.000E+00 7.620E-11 TE-129M 6.690E+07 2.290E+07 2.570E+07 1.670E+08 0.000E+00 3.990E+07 0.000E+00 1.030E+07 TE-131 4.110E-33 1.520E-33 3.670E-33 1.050E-32 0.000E+00 1.660E-31 0.000E+00 1.150E-33 TE-131M 4.050E+05 1.630E+05 3.310E+05 1.120E+06 0.000E+00 2.750E+06 0.000E+00 1.350E+05 TE-132 2.530E+06 1.250E+06 1.850E+06 7.840E+06 0.000E+00 4.640E+06 0.000E+00 1.170E+06 I-130 4.260E+06 9.370E+06 1.050E+09 1.030E+07 0.000E+00 2.010E+06 0.000E+00 3.760E+06 Appendix J Ri Infant Goat Milk - Page 2 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX J Ri Infant Dose Factors for use in the Gaseous Dose Calculations Agegroup: INFANT Pathway: Grs/Goat/Milk (GMILK) Units: m2*mrem/yr / Ci/sec; mrem/yr / Ci/m3 (H-3)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body I-131 3.260E+09 3.850E+09 1.260E+12 4.490E+09 0.000E+00 1.370E+08 0.000E+00 1.690E+09 I-132 1.720E+00 3.480E+00 1.630E+02 3.890E+00 0.000E+00 2.820E+00 0.000E+00 1.240E+00 I-133 4.350E+07 6.340E+07 1.150E+10 7.450E+07 0.000E+00 1.070E+07 0.000E+00 1.860E+07 I-134 2.110E-11 4.320E-11 1.010E-09 4.830E-11 0.000E+00 4.470E-11 0.000E+00 1.540E-11 I-135 1.350E+05 2.680E+05 2.400E+07 2.990E+05 0.000E+00 9.700E+04 0.000E+00 9.770E+04 CS-134 1.090E+11 2.040E+11 0.000E+00 5.250E+10 2.150E+10 5.540E+08 0.000E+00 2.060E+10 CS-136 5.930E+09 1.740E+10 0.000E+00 6.950E+09 1.420E+09 2.650E+08 0.000E+00 6.510E+09 CS-137 1.540E+11 1.810E+11 0.000E+00 4.850E+10 1.960E+10 5.650E+08 0.000E+00 1.280E+10 CS-138 2.520E-22 4.090E-22 0.000E+00 2.040E-22 3.190E-23 6.540E-22 0.000E+00 1.980E-22 BA-139 5.130E-08 3.400E-11 0.000E+00 2.040E-11 2.060E-11 3.250E-06 0.000E+00 1.480E-09 BA-140 2.890E+07 2.890E+04 0.000E+00 6.870E+03 1.780E+04 7.100E+06 0.000E+00 1.490E+06 BA-141 4.720E-46 3.230E-49 0.000E+00 1.940E-49 1.960E-49 5.760E-45 0.000E+00 1.490E-47 BA-142 2.920E-80 2.430E-83 0.000E+00 1.400E-83 1.470E-83 1.200E-79 0.000E+00 1.440E-81 LA-140 4.860E+00 1.920E+00 0.000E+00 0.000E+00 0.000E+00 2.250E+04 0.000E+00 4.930E-01 LA-142 2.040E-11 7.500E-12 0.000E+00 0.000E+00 0.000E+00 1.270E-06 0.000E+00 1.790E-12 CE-141 5.200E+03 3.170E+03 0.000E+00 9.790E+02 0.000E+00 1.640E+06 0.000E+00 3.740E+02 CE-143 4.760E+01 3.160E+04 0.000E+00 9.200E+00 0.000E+00 1.840E+05 0.000E+00 3.600E+00 CE-144 2.790E+05 1.140E+05 0.000E+00 4.620E+04 0.000E+00 1.600E+07 0.000E+00 1.560E+04 PR-143 1.780E+02 6.670E+01 0.000E+00 2.480E+01 0.000E+00 9.410E+04 0.000E+00 8.840E+00 PR-144 6.830E-54 2.640E-54 0.000E+00 9.570E-55 0.000E+00 1.230E-49 0.000E+00 3.440E-55 ND-147 1.060E+02 1.090E+02 0.000E+00 4.190E+01 0.000E+00 6.880E+04 0.000E+00 6.650E+00 W-187 7.300E+03 5.070E+03 0.000E+00 0.000E+00 0.000E+00 2.980E+05 0.000E+00 1.750E+03 NP-239 4.380E+00 3.910E-01 0.000E+00 7.810E-01 0.000E+00 1.130E+04 0.000E+00 2.210E-01 Appendix J Ri Infant Goat Milk - Page 3 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX J Ri Infant Dose Factors for use in the Gaseous Dose Calculations Agegroup: INFANT Pathway: Inhalation (INHL) Units: mrem/yr / Ci/m3 Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body H-3 0.000E+00 6.470E+02 6.470E+02 6.470E+02 6.470E+02 6.470E+02 0.000E+00 6.470E+02 C-14 2.650E+04 5.310E+03 5.310E+03 5.310E+03 5.310E+03 5.310E+03 0.000E+00 5.310E+03 NA-24 1.060E+04 1.060E+04 1.060E+04 1.060E+04 1.060E+04 1.060E+04 0.000E+00 1.060E+04 P-32 2.030E+06 1.120E+05 0.000E+00 0.000E+00 0.000E+00 1.610E+04 0.000E+00 7.740E+04 CR-51 0.000E+00 0.000E+00 5.750E+01 1.320E+01 1.280E+04 3.570E+02 0.000E+00 8.950E+01 MN-54 0.000E+00 2.530E+04 0.000E+00 4.980E+03 1.000E+06 7.060E+03 0.000E+00 4.980E+03 MN-56 0.000E+00 1.540E+00 0.000E+00 1.100E+00 1.250E+04 7.170E+04 0.000E+00 2.210E-01 FE-55 1.970E+04 1.170E+04 0.000E+00 0.000E+00 8.690E+04 1.090E+03 0.000E+00 3.330E+03 FE-59 1.360E+04 2.350E+04 0.000E+00 0.000E+00 1.010E+06 2.480E+04 0.000E+00 9.480E+03 CO-58 0.000E+00 1.220E+03 0.000E+00 0.000E+00 7.770E+05 1.110E+04 0.000E+00 1.820E+03 CO-60 0.000E+00 8.020E+03 0.000E+00 0.000E+00 4.510E+06 3.190E+04 0.000E+00 1.180E+04 NI-63 3.390E+05 2.040E+04 0.000E+00 0.000E+00 2.090E+05 2.420E+03 0.000E+00 1.160E+04 NI-65 2.390E+00 2.840E-01 0.000E+00 0.000E+00 8.120E+03 5.010E+04 0.000E+00 1.230E-01 CU-64 0.000E+00 1.880E+00 0.000E+00 3.980E+00 9.300E+03 1.500E+04 0.000E+00 7.740E-01 ZN-65 1.930E+04 6.260E+04 0.000E+00 3.250E+04 6.470E+05 5.140E+04 0.000E+00 3.110E+04 ZN-69 5.390E-02 9.670E-02 0.000E+00 4.020E-02 1.470E+03 1.320E+04 0.000E+00 7.180E-03 BR-83 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.810E+02 BR-84 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4.000E+02 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.040E+01 RB-86 0.000E+00 1.900E+05 0.000E+00 0.000E+00 0.000E+00 3.040E+03 0.000E+00 8.820E+04 RB-88 0.000E+00 5.570E+02 0.000E+00 0.000E+00 0.000E+00 3.390E+02 0.000E+00 2.870E+02 RB-89 0.000E+00 3.210E+02 0.000E+00 0.000E+00 0.000E+00 6.820E+01 0.000E+00 2.060E+02 SR-89 3.980E+05 0.000E+00 0.000E+00 0.000E+00 2.030E+06 6.400E+04 0.000E+00 1.140E+04 SR-90 4.090E+07 0.000E+00 0.000E+00 0.000E+00 1.120E+07 1.310E+05 0.000E+00 2.590E+06 SR-91 9.560E+01 0.000E+00 0.000E+00 0.000E+00 5.260E+04 7.340E+04 0.000E+00 3.460E+00 Appendix J Ri Infant Inhalation - Page 1 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX J Ri Infant Dose Factors for use in the Gaseous Dose Calculations Agegroup: INFANT Pathway: Inhalation (INHL) Units: mrem/yr / Ci/m3 Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body SR-92 1.050E+01 0.000E+00 0.000E+00 0.000E+00 2.380E+04 1.400E+05 0.000E+00 3.910E-01 Y-90 3.290E+03 0.000E+00 0.000E+00 0.000E+00 2.690E+05 1.040E+05 0.000E+00 8.820E+01 Y-91 5.880E+05 0.000E+00 0.000E+00 0.000E+00 2.450E+06 7.030E+04 0.000E+00 1.570E+04 Y-91M 4.070E-01 0.000E+00 0.000E+00 0.000E+00 2.790E+03 2.350E+03 0.000E+00 1.390E-02 Y-92 1.640E+01 0.000E+00 0.000E+00 0.000E+00 2.450E+04 1.270E+05 0.000E+00 4.610E-01 Y-93 1.500E+02 0.000E+00 0.000E+00 0.000E+00 7.640E+04 1.670E+05 0.000E+00 4.070E+00 ZR-95 1.150E+05 2.790E+04 0.000E+00 3.110E+04 1.750E+06 2.170E+04 0.000E+00 2.030E+04 ZR-97 1.500E+02 2.560E+01 0.000E+00 2.590E+01 1.100E+05 1.400E+05 0.000E+00 1.170E+01 NB-95 1.570E+04 6.430E+03 0.000E+00 4.720E+03 4.790E+05 1.270E+04 0.000E+00 3.780E+03 MO-99 0.000E+00 1.650E+02 0.000E+00 2.650E+02 1.350E+05 4.870E+04 0.000E+00 3.230E+01 TC-99M 1.400E-03 2.880E-03 0.000E+00 3.110E-02 8.110E+02 2.030E+03 0.000E+00 3.720E-02 TC-101 6.510E-05 8.230E-05 0.000E+00 9.790E-04 5.840E+02 8.440E+02 0.000E+00 8.120E-04 RU-103 2.020E+03 0.000E+00 0.000E+00 4.240E+03 5.520E+05 1.610E+04 0.000E+00 6.790E+02 RU-105 1.220E+00 0.000E+00 0.000E+00 8.990E-01 1.570E+04 4.840E+04 0.000E+00 4.100E-01 RU-106 8.680E+04 0.000E+00 0.000E+00 1.070E+05 1.160E+07 1.640E+05 0.000E+00 1.090E+04 AG-110M 9.980E+03 7.220E+03 0.000E+00 1.090E+04 3.670E+06 3.300E+04 0.000E+00 5.000E+03 TE-125M 4.760E+03 1.990E+03 1.620E+03 0.000E+00 4.470E+05 1.290E+04 0.000E+00 6.580E+02 TE-127 2.230E+00 9.530E-01 1.850E+00 4.860E+00 1.030E+04 2.440E+04 0.000E+00 4.890E-01 TE-127M 1.670E+04 6.900E+03 4.870E+03 3.750E+04 1.310E+06 2.730E+04 0.000E+00 2.070E+03 TE-129 7.880E-02 3.470E-02 6.750E-02 1.750E-01 3.000E+03 2.630E+04 0.000E+00 1.880E-02 TE-129M 1.410E+04 6.090E+03 5.470E+03 3.180E+04 1.680E+06 6.900E+04 0.000E+00 2.230E+03 TE-131 1.740E-02 8.220E-03 1.580E-02 3.990E-02 2.060E+03 8.220E+03 0.000E+00 5.000E-03 TE-131M 1.070E+02 5.500E+01 8.930E+01 2.650E+02 1.990E+05 1.190E+05 0.000E+00 3.630E+01 TE-132 3.720E+02 2.370E+02 2.790E+02 1.030E+03 3.400E+05 4.410E+04 0.000E+00 1.760E+02 I-130 6.360E+03 1.390E+04 1.600E+06 1.530E+04 0.000E+00 1.990E+03 0.000E+00 5.570E+03 Appendix J Ri Infant Inhalation - Page 2 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX J Ri Infant Dose Factors for use in the Gaseous Dose Calculations Agegroup: INFANT Pathway: Inhalation (INHL) Units: mrem/yr / Ci/m3 Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body I-131 3.790E+04 4.440E+04 1.480E+07 5.180E+04 0.000E+00 1.060E+03 0.000E+00 1.960E+04 I-132 1.690E+03 3.540E+03 1.690E+05 3.950E+03 0.000E+00 1.900E+03 0.000E+00 1.260E+03 I-133 1.320E+04 1.920E+04 3.560E+06 2.240E+04 0.000E+00 2.160E+03 0.000E+00 5.600E+03 I-134 9.210E+02 1.880E+03 4.450E+04 2.090E+03 0.000E+00 1.290E+03 0.000E+00 6.650E+02 I-135 3.860E+03 7.600E+03 6.960E+05 8.470E+03 0.000E+00 1.830E+03 0.000E+00 2.770E+03 CS-134 3.960E+05 7.030E+05 0.000E+00 1.900E+05 7.970E+04 1.330E+03 0.000E+00 7.450E+04 CS-136 4.830E+04 1.350E+05 0.000E+00 5.640E+04 1.180E+04 1.430E+03 0.000E+00 5.290E+04 CS-137 5.490E+05 6.120E+05 0.000E+00 1.720E+05 7.130E+04 1.330E+03 0.000E+00 4.550E+04 CS-138 5.050E+02 7.810E+02 0.000E+00 4.100E+02 6.540E+01 8.760E+02 0.000E+00 3.980E+02 BA-139 1.480E+00 9.840E-04 0.000E+00 5.920E-04 5.950E+03 5.100E+04 0.000E+00 4.300E-02 BA-140 5.600E+04 5.600E+01 0.000E+00 1.340E+01 1.600E+06 3.840E+04 0.000E+00 2.900E+03 BA-141 1.570E-01 1.080E-04 0.000E+00 6.500E-05 2.970E+03 4.750E+03 0.000E+00 4.970E-03 BA-142 3.980E-02 3.300E-05 0.000E+00 1.900E-05 1.550E+03 6.930E+02 0.000E+00 1.960E-03 LA-140 5.050E+02 2.000E+02 0.000E+00 0.000E+00 1.680E+05 8.480E+04 0.000E+00 5.150E+01 LA-142 1.030E+00 3.770E-01 0.000E+00 0.000E+00 8.220E+03 5.950E+04 0.000E+00 9.040E-02 CE-141 2.770E+04 1.670E+04 0.000E+00 5.250E+03 5.170E+05 2.160E+04 0.000E+00 1.990E+03 CE-143 2.930E+02 1.930E+02 0.000E+00 5.640E+01 1.160E+05 4.970E+04 0.000E+00 2.210E+01 CE-144 3.190E+06 1.210E+06 0.000E+00 5.380E+05 9.840E+06 1.480E+05 0.000E+00 1.760E+05 PR-143 1.400E+04 5.240E+03 0.000E+00 1.970E+03 4.330E+05 3.720E+04 0.000E+00 6.990E+02 PR-144 4.790E-02 1.850E-02 0.000E+00 6.720E-03 1.610E+03 4.280E+03 0.000E+00 2.410E-03 ND-147 7.940E+03 8.130E+03 0.000E+00 3.150E+03 3.220E+05 3.120E+04 0.000E+00 5.000E+02 W-187 1.300E+01 9.020E+00 0.000E+00 0.000E+00 3.960E+04 3.560E+04 0.000E+00 3.120E+00 NP-239 3.710E+02 3.320E+01 0.000E+00 6.620E+01 5.950E+04 2.490E+04 0.000E+00 1.880E+01 Appendix J Ri Infant Inhalation - Page 3 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX J Ri Infant Dose Factors for use in the Gaseous Dose Calculations Agegroup: INFANT Pathway: Ground Plane Deposition (GPD) Units: m2*mrem/yr / Ci/sec Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body H-3 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 C-14 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 NA-24 1.190E+07 1.190E+07 1.190E+07 1.190E+07 1.190E+07 1.190E+07 1.390E+07 1.190E+07 P-32 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 CR-51 4.660E+06 4.660E+06 4.660E+06 4.660E+06 4.660E+06 4.660E+06 5.510E+06 4.660E+06 MN-54 1.390E+09 1.390E+09 1.390E+09 1.390E+09 1.390E+09 1.390E+09 1.630E+09 1.390E+09 MN-56 9.020E+05 9.020E+05 9.020E+05 9.020E+05 9.020E+05 9.020E+05 1.070E+06 9.020E+05 FE-55 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 FE-59 2.730E+08 2.730E+08 2.730E+08 2.730E+08 2.730E+08 2.730E+08 3.210E+08 2.730E+08 CO-58 3.790E+08 3.790E+08 3.790E+08 3.790E+08 3.790E+08 3.790E+08 4.440E+08 3.790E+08 CO-60 2.150E+10 2.150E+10 2.150E+10 2.150E+10 2.150E+10 2.150E+10 2.530E+10 2.150E+10 NI-63 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 NI-65 2.970E+05 2.970E+05 2.970E+05 2.970E+05 2.970E+05 2.970E+05 3.450E+05 2.970E+05 CU-64 6.070E+05 6.070E+05 6.070E+05 6.070E+05 6.070E+05 6.070E+05 6.880E+05 6.070E+05 ZN-65 7.470E+08 7.470E+08 7.470E+08 7.470E+08 7.470E+08 7.470E+08 8.590E+08 7.470E+08 ZN-69 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 BR-83 4.870E+03 4.870E+03 4.870E+03 4.870E+03 4.870E+03 4.870E+03 7.080E+03 4.870E+03 BR-84 2.030E+05 2.030E+05 2.030E+05 2.030E+05 2.030E+05 2.030E+05 2.360E+05 2.030E+05 BR-85 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 8.990E+06 8.990E+06 8.990E+06 8.990E+06 8.990E+06 8.990E+06 1.030E+07 8.990E+06 RB-88 3.310E+04 3.310E+04 3.310E+04 3.310E+04 3.310E+04 3.310E+04 3.780E+04 3.310E+04 RB-89 1.230E+05 1.230E+05 1.230E+05 1.230E+05 1.230E+05 1.230E+05 1.480E+05 1.230E+05 SR-89 2.160E+04 2.160E+04 2.160E+04 2.160E+04 2.160E+04 2.160E+04 2.510E+04 2.160E+04 SR-90 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 SR-91 2.150E+06 2.150E+06 2.150E+06 2.150E+06 2.150E+06 2.150E+06 2.510E+06 2.150E+06 Appendix J Ri Infant Ground Plane Deposition - Page 1 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX J Ri Infant Dose Factors for use in the Gaseous Dose Calculations Agegroup: INFANT Pathway: Ground Plane Deposition (GPD) Units: m2*mrem/yr / Ci/sec Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body SR-92 7.770E+05 7.770E+05 7.770E+05 7.770E+05 7.770E+05 7.770E+05 8.630E+05 7.770E+05 Y-90 4.490E+03 4.490E+03 4.490E+03 4.490E+03 4.490E+03 4.490E+03 5.310E+03 4.490E+03 Y-91 1.070E+06 1.070E+06 1.070E+06 1.070E+06 1.070E+06 1.070E+06 1.210E+06 1.070E+06 Y-91M 1.000E+05 1.000E+05 1.000E+05 1.000E+05 1.000E+05 1.000E+05 1.160E+05 1.000E+05 Y-92 1.800E+05 1.800E+05 1.800E+05 1.800E+05 1.800E+05 1.800E+05 2.140E+05 1.800E+05 Y-93 1.830E+05 1.830E+05 1.830E+05 1.830E+05 1.830E+05 1.830E+05 2.510E+05 1.830E+05 ZR-95 2.450E+08 2.450E+08 2.450E+08 2.450E+08 2.450E+08 2.450E+08 2.840E+08 2.450E+08 ZR-97 2.960E+06 2.960E+06 2.960E+06 2.960E+06 2.960E+06 2.960E+06 3.440E+06 2.960E+06 NB-95 1.370E+08 1.370E+08 1.370E+08 1.370E+08 1.370E+08 1.370E+08 1.610E+08 1.370E+08 MO-99 3.990E+06 3.990E+06 3.990E+06 3.990E+06 3.990E+06 3.990E+06 4.630E+06 3.990E+06 TC-99M 1.840E+05 1.840E+05 1.840E+05 1.840E+05 1.840E+05 1.840E+05 2.110E+05 1.840E+05 TC-101 2.040E+04 2.040E+04 2.040E+04 2.040E+04 2.040E+04 2.040E+04 2.260E+04 2.040E+04 RU-103 1.080E+08 1.080E+08 1.080E+08 1.080E+08 1.080E+08 1.080E+08 1.260E+08 1.080E+08 RU-105 6.360E+05 6.360E+05 6.360E+05 6.360E+05 6.360E+05 6.360E+05 7.210E+05 6.360E+05 RU-106 4.220E+08 4.220E+08 4.220E+08 4.220E+08 4.220E+08 4.220E+08 5.070E+08 4.220E+08 AG-110M 3.440E+09 3.440E+09 3.440E+09 3.440E+09 3.440E+09 3.440E+09 4.010E+09 3.440E+09 TE-125M 1.550E+06 1.550E+06 1.550E+06 1.550E+06 1.550E+06 1.550E+06 2.130E+06 1.550E+06 TE-127 2.980E+03 2.980E+03 2.980E+03 2.980E+03 2.980E+03 2.980E+03 3.280E+03 2.980E+03 TE-127M 9.160E+04 9.160E+04 9.160E+04 9.160E+04 9.160E+04 9.160E+04 1.080E+05 9.160E+04 TE-129 2.620E+04 2.620E+04 2.620E+04 2.620E+04 2.620E+04 2.620E+04 3.100E+04 2.620E+04 TE-129M 1.980E+07 1.980E+07 1.980E+07 1.980E+07 1.980E+07 1.980E+07 2.310E+07 1.980E+07 TE-131 2.920E+04 2.920E+04 2.920E+04 2.920E+04 2.920E+04 2.920E+04 3.450E+07 2.920E+04 TE-131M 8.030E+06 8.030E+06 8.030E+06 8.030E+06 8.030E+06 8.030E+06 9.460E+06 8.030E+06 TE-132 4.230E+06 4.230E+06 4.230E+06 4.230E+06 4.230E+06 4.230E+06 4.980E+06 4.230E+06 I-130 5.510E+06 5.510E+06 5.510E+06 5.510E+06 5.510E+06 5.510E+06 6.690E+06 5.510E+06 Appendix J Ri Infant Ground Plane Deposition - Page 2 of 3

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 APPENDIX J Ri Infant Dose Factors for use in the Gaseous Dose Calculations Agegroup: INFANT Pathway: Ground Plane Deposition (GPD) Units: m2*mrem/yr / Ci/sec Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body I-131 1.720E+07 1.720E+07 1.720E+07 1.720E+07 1.720E+07 1.720E+07 2.090E+07 1.720E+07 I-132 1.250E+06 1.250E+06 1.250E+06 1.250E+06 1.250E+06 1.250E+06 1.470E+06 1.250E+06 I-133 2.450E+06 2.450E+06 2.450E+06 2.450E+06 2.450E+06 2.450E+06 2.980E+06 2.450E+06 I-134 4.470E+05 4.470E+05 4.470E+05 4.470E+05 4.470E+05 4.470E+05 5.300E+05 4.470E+05 I-135 2.530E+06 2.530E+06 2.530E+06 2.530E+06 2.530E+06 2.530E+06 2.950E+06 2.530E+06 CS-134 6.860E+09 6.860E+09 6.860E+09 6.860E+09 6.860E+09 6.860E+09 8.000E+09 6.860E+09 CS-136 1.510E+08 1.510E+08 1.510E+08 1.510E+08 1.510E+08 1.510E+08 1.710E+08 1.510E+08 CS-137 1.030E+10 1.030E+10 1.030E+10 1.030E+10 1.030E+10 1.030E+10 1.200E+10 1.030E+10 CS-138 3.590E+05 3.590E+05 3.590E+05 3.590E+05 3.590E+05 3.590E+05 4.100E+05 3.590E+05 BA-139 1.060E+05 1.060E+05 1.060E+05 1.060E+05 1.060E+05 1.060E+05 1.190E+05 1.060E+05 BA-140 2.050E+07 2.050E+07 2.050E+07 2.050E+07 2.050E+07 2.050E+07 2.350E+07 2.050E+07 BA-141 4.170E+04 4.170E+04 4.170E+04 4.170E+04 4.170E+04 4.170E+04 4.750E+04 4.170E+04 BA-142 4.490E+04 4.490E+04 4.490E+04 4.490E+04 4.490E+04 4.490E+04 5.110E+04 4.490E+04 LA-140 1.920E+07 1.920E+07 1.920E+07 1.920E+07 1.920E+07 1.920E+07 2.180E+07 1.920E+07 LA-142 7.600E+05 7.600E+05 7.600E+05 7.600E+05 7.600E+05 7.600E+05 9.120E+05 7.600E+05 CE-141 1.370E+07 1.370E+07 1.370E+07 1.370E+07 1.370E+07 1.370E+07 1.540E+07 1.370E+07 CE-143 2.310E+06 2.310E+06 2.310E+06 2.310E+06 2.310E+06 2.310E+06 2.630E+06 2.310E+06 CE-144 6.950E+07 6.950E+07 6.950E+07 6.950E+07 6.950E+07 6.950E+07 8.040E+07 6.950E+07 PR-143 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 PR-144 1.830E+03 1.830E+03 1.830E+03 1.830E+03 1.830E+03 1.830E+03 2.110E+03 1.830E+03 ND-147 8.390E+06 8.390E+06 8.390E+06 8.390E+06 8.390E+06 8.390E+06 1.010E+07 8.390E+06 W-187 2.350E+06 2.350E+06 2.350E+06 2.350E+06 2.350E+06 2.350E+06 2.730E+06 2.350E+06 NP-239 1.710E+06 1.710E+06 1.710E+06 1.710E+06 1.710E+06 1.710E+06 1.980E+06 1.710E+06 Appendix J Ri Infant Ground Plane Deposition - Page 3 of 3

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