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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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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.
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.
These dose limitations assure that:
These dose limitations assure that:
(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.
(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.
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.
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.
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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.
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 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:
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 (co balt, cesium, manganese) and anions (chloride, fluoride) from the filtrate in order to purify the filtrate for release.  
(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.
(C) Gas Stripping - Removal of gaseous radioactive fission products is accomplished through venting of atmospheric holdup tan k s.
(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.
Figure 1.0-1 is a schematic representation of the li q uid radwaste system at Oconee.
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-1 Oconee Nuclear Station Li quid Radwaste System
-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  Section 1 - Page 3 1.0.2    GASEOUS RAD WASTE PROCESSING The purpose of the gaseous waste disposal system is to:
(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.
(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.


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-2 Oconee Nuclear Station Gaseous Radwaste System Page 4 of 4  
-2 Oconee Nuclear Station Gaseous Radwaste System Page 4 of 4  


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 Section 2 - Page 1 2.0 RELEASE 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).
 
===2.0 RELEASE===
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).
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:  
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:  
)(DF F f 1    Condition:  DF  1.0Equation 2.1 where: f      =    the undiluted effluent flow, in gpm.
)(DF F f 1    Condition:  DF  1.0Equation 2.1 where: f      =    the undiluted effluent flow, in gpm.
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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  
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  


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.  
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.
: 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).
: 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).
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).
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).
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K'Units conversion factor pCi/ Ci (10 6).BR Breathing rate for the Child age group (m 3/yr, from Regulatory Guide 1.109):
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.
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:
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+
()()          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:
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.
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.
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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:
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:
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:
()            x=i i i EQ C C ONC C where:
C i          =
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.
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.
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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 µC 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
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 µC 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=
-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 µC 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.                    
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 µC 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).
(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 µC i/m l/cpm. 1RIA-3 7 = 1.01 E-0 8 µC i/m l/cpm , 3RIA-3 7 =  4.20 E-0 8 µC i/m l/cpm , 1RIA-3 8 a n d 3RIA-3 8  =  1.34 E-03 µC i/m l/cpm.
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 µC i/m l/cpm. 1RIA-3 7 = 1.01 E-0 8 µC i/m l/cpm , 3RIA-3 7 =  4.20 E-0 8 µC i/m l/cpm , 1RIA-3 8 a n d 3RIA-3 8  =  1.34 E-03 µC i/m l/cpm.
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Oc o n ee Nucl e ar Stati o n    January, 2007 Off s it e D o se Calculati o n Manual (O D C M)
Oc o n ee Nucl e ar Stati o n    January, 2007 Off s it e D o se Calculati o n Manual (O D C M)
R e vi s i o n 47 S e cti o n 4 - Pag e 8 Iodine, Particulates, and H
R e vi s i o n 47 S e cti o n 4 - Pag e 8 Iodine, Particulates, and H
-3 Dose Organ Dose Calculation  
-3 Dose Organ Dose Calculation
()xxxx=i i o api p o a Q R W Dose    10 17.3 8    Formula:  adapted from NUREG
()xxxx=i i o api p o a Q R W Dose    10 17.3 8    Formula:  adapted from NUREG
-0133, pages 2 9 & 30. W h e r e: D o se o a Th e cumulativ e d o se c o mmitm e nt t o th e t otal b o dy o r any organ o , f o r an individual o f ag e gr o up a (mr em). 3.17x10-8 Inv e r se num b e r o f se c o nd s in y e ar (y e ar/se c o nd s). R oapi D o se c o mmitm e nt fact o r f o r organ o , ag e gr o up a, pathway p, and nuclid e i. Th e unit s ar e b a se d o n wh e th e r a di s p e r s i o n o r d e p o s iti o n fact o r i s u se d. W h e n a /Q i s u se d th e unit s ar e mr e m/yr p e r µCi/m 3. W h e n a D/Q i s u se d th e unit s ar e (m 2
-0133, pages 2 9 & 30. W h e r e: D o se o a Th e cumulativ e d o se c o mmitm e nt t o th e t otal b o dy o r any organ o , f o r an individual o f ag e gr o up a (mr em). 3.17x10-8 Inv e r se num b e r o f se c o nd s in y e ar (y e ar/se c o nd s). R oapi D o se c o mmitm e nt fact o r f o r organ o , ag e gr o up a, pathway p, and nuclid e i. Th e unit s ar e b a se d o n wh e th e r a di s p e r s i o n o r d e p o s iti o n fact o r i s u se d. W h e n a /Q i s u se d th e unit s ar e mr e m/yr p e r µCi/m 3. W h e n a D/Q i s u se d th e unit s ar e (m 2
* mr e m/yr) p e r µCi/se c.  (S ee App e ndic es G thr ough J f o r ag e gr o up and pathway s p ecific d o se c o mmitm e nt fact o r s). D i s p e r s i o n (/Q) o r d e p o s iti o n fact o r (D/Q)*. Th e fact o r u se d i s b a se d up o n th e pathway. N o t e: /Q i s alway s u se d f o r tritium. Pathway Fact o r U se d Gr o und Plan e D e p o s iti o n D/Q  (m-2) Inhalati o n /Q  (se c/m 3) V e g etati o n D/Q  (m-2) Gra ss/C o w/M il k D/Q  (m-2) Gra ss/G o at/M il k D/Q  (m-2) W Gra ss/C o w/M e at D/Q  (m-2) Q i Activity f o r nuclid e i, r e l e a se d during th e tim e p e ri o d o f int e r es t (µCi).
* mr e m/yr) p e r µCi/se c.  (S ee App e ndic es G thr ough J f o r ag e gr o up and pathway s p ecific d o se c o mmitm e nt fact o r s). D i s p e r s i o n (/Q) o r d e p o s iti o n fact o r (D/Q)*. Th e fact o r u se d i s b a se d up o n th e pathway. N o t e: /Q i s alway s u se d f o r tritium. Pathway Fact o r U se d Gr o und Plan e D e p o s iti o n D/Q  (m-2) Inhalati o n /Q  (se c/m 3) V e g etati o n D/Q  (m-2) Gra ss/C o w/M il k D/Q  (m-2) Gra ss/G o at/M il k D/Q  (m-2) W Gra ss/C o w/M e at D/Q  (m-2) Q i Activity f o r nuclid e i, r e l e a se d during th e tim e p e ri o d o f int e r es t (µCi).
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* 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.   
* 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 Section 7 - Page 1 7.0 LICENSEE 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.
 
===7.0 LICENSEE===
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.
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  
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  



Revision as of 00:12, 13 July 2019

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)


Text

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

Approved By: D. A. Baxter ONS Station Manager REVISION NUMBER 47 EFFECTIVE YEAR 2007

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 i TABLE OF CONTENTS Executive Summary

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

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

. . . 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.

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

These dose limitations assure that:

(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.

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.

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.

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.

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.

(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.

(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:

(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.

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.

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.

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.

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.

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.

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

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

-2 Oconee Nuclear Station Gaseous Radwaste System Page 1 of 4

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 Section 1 - Page 5 Figure 1.0

-2 Oconee Nuclear Station Gaseous Radwaste System Page 2 of 4

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 Section 1 - Page 6 Figure 1.0

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Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 Section 1 - Page 7 Figure 1.0

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Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (ODCM) Revision 47 Section 2 - Page 1 2.0 RELEASE 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).

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:

)(DF F f 1 Condition: DF 1.0Equation 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 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.

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.

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.

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.

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

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 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

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.

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).

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).

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).

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

3. For the Oconee Unit Vents this value is 1.672E-6 sec/m
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

Facility this value is 7.308E-6 sec/m

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.

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:

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

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.

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

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.

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

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:

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<

E quation 3.4 From E quation 2.6: f C Q Xe Xe 02 4.72E 133 133xx+=

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 µC i/m 3 (S ee App e ndix A). /Q =

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

= 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 µC i/s e c. 4.72E+02 = C onv ersion factor, (cc/ft 3)/(s e c/min).

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

= 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 µC i/cc.

f =

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.

S P = radiation monitor s e tpoint, in cpm. C F =

th e X e-133 e q uival e nt monitor corr elation factor, in µC i/cc/cpm. bkg =

th e radiation monitor b ac k g round r eadin g , in cpm.

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, µC 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, µC 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 µC 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 , µC 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, µC 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 µC 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 µC 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 µC i/m l/cpm. 1RIA-3 7 = 1.01 E-0 8 µC i/m l/cpm , 3RIA-3 7 = 4.20 E-0 8 µC i/m l/cpm , 1RIA-3 8 a n d 3RIA-3 8 = 1.34 E-03 µC 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 µC 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.

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 µC 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 µC 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 µC 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)

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

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.

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.

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.

  • 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.

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 4 Derivation of Li quid Dose Commitment Factors (Aoapi) P o t a b l e W a t e r p t aoi a w oapi D U A i-5 e 10 14.1xxxx= Formula: from NUREG

-0133, page 1 6 and Regulatory Guide 1.10 9 , page 1.10 9-12. Where: Aoap i D o se c o mm itment f a ct o r f o r o rg a n o , a ge gr o u p a , pa th w a y p , a nd nucl i de i , (mrem/hr p er µC i/ml). (See A pp end i ces C thr ough F f o r a ge gr o u p a nd pa th w a y s p ec i f i c d o se c o mm itment f a ct o rs). 1.14x10 5 U n i ts c o nvers i o n f a ct o r (p C i-yr-ml)/(µC i-hr-k g). U a w W ater c o nsum p t i o n r a te i n l iters p er ye a r f o r a ge gr o u p a. Fr o m T a b le E-5 , Regul a t o ry Gu i de 1.10 9. A dult - 730 Teen - 5 10 Ch i ld - 5 10 Inf a nt - 330 D ao i D o se f a ct o r f o r a ge gr o u p a , o rg a n o , nucl i de i , i n mrem/p C i. Fr o m t a bles E-11 thr ough E-14 o f Regul a t o ry Gu i de 1.10 9.

i D ec a y c o nst a nt f o r nucl i de i , i n sec-1.

t p Env i r o nment a l tr a ns i t t i me fr o m rele a se t o rece p t o r. D ef a ult = 4.32E+04 sec (12 h o urs). Fr o m Regul a t o ry Gu i de 1.10 9 , T a b le E-1 5.

Oc onee Nucle a r St a t i o n J a nu ary, 2007 Offs i te D o se C alcul a t i o n M a nu a l (O DCM) Rev i s i o n 47 Sect i o n 4 - P a ge 5 A q u a t i c F oo ds p t aoi i a f oapi D B F U A i- 5 e 10 14.1xxxxx= Formula: from NUREG

-0133, page 1 6 and Regulatory Guide 1.10 9 , page 1.10 9-12. Where: Aoap i D o se c o mm itment f a ct o r f o r o rg a n o , a ge gr o u p a , pa th w a y p , a nd nucl i de i , (mrem/hr p er µC i/ml). (See A pp end ices C thr ough F f o r a ge gr o u p a nd pa th w a y s p ec i f i c d o se c o mm itment f a ct o rs). 1.14x10 5 U n i ts c o nvers i o n f a ct o r (p C i-yr-ml)/(µC i-hr-k g). U a f F i sh c o nsum p t i o n r a te f o r a ge gr o u p a (k g/yr). Fr o m T a b le E-5 , Regul a t o ry Gu i de 1.10 9. A dult - 21 Teen - 1 6 Ch i ld - 6.9 Inf a nt - 0 B F i B i oaccumul a t i o n f a ct o r f o r nucl i de i , i n f i sh, i n un i ts o f p C i/k g p er p C i/l iter. Fr o m T a b le A-1 o f Regul a t o ry Gu i de 1.10 9. D ao i D o se f a ct o r f o r a ge gr o u p a , o rg a n o , nucl i de i , i n mrem/p C i. Fr o m t a bles E-11 thr ough E-14 o f Regul a t o ry Gu i de 1.10 9.

i D ec a y c o nst a nt f o r nucl i de i , i n sec-1.

t p Env i r o nment a l tr a ns i t t i me fr o m rele a se t o rece p t o r. D ef a ult = 8.6 4E+04 sec (1 d ay). Fr o m Regul a t o ry Gu i de 1.10 9 , T a b le E-1 5.

Oc onee Nucle a r St a t i o n J a nu ary, 2007 Offs i te D o se C alcul a t i o n M a nu a l (O DCM) Rev i s i o n 47 Sect i o n 4 - P a ge 6 Sh o rel i ne Sed iment )1 (100 10 14.1 2 1 5 b i p i t t i a s oi oapi e e T U w DFG Axxxxxxxx= Formula: adapted from Regulatory Guide 1.10 9 , page 1.10 9-14. W h e r e: Aoap i D o se c o mm i tm e nt f a ct o r f o r o rg a n o , a g e gr o u p a , pa th w a y p , a nd nucl i d e i , (mr e m/hr p e r µC i/ml). (S ee A pp e nd i c es C thr ough F f o r a g e gr o u p a nd pa th w a y s p e c i f i c d o se c o mm i tm e nt f a ct o r s). 1.14x10 5 U n i t s c o nv e r s i o n f a ct o r (p C i-yr-ml)/(µC i-hr-k g). 100 Pr opo rt i o n a l i ty c o n s t a nt u se d i n th e se d i m e nt r a d i oa ct i v i ty m o d e l, (l i t e r s/(m 2-d ay). D FG o i G r o und p l a n e d o se c o nv e r s i o n f a ct o r f o r o rg a n o , nucl i d e i (mr e m/hr p e r p C i/m 2), fr o m T a b l e E-6 o f R egul a t o ry G u i d e 1.10 9. w Sh o r e l i n e w i dth f a ct o r. F o r Oc o n ee = 0.2, fr o m T a b l e A-2, R egul a t o ry G u i d e 1.10 9. U a s Sh o r e l i n e e x po s ur e r a t e f o r a g e gr o u p a (hr/yr), F r o m T a b l e E-5 , R egul a t o ry G u i d e 1.10 9. A dult - 12 Tee n - 6 7 Ch i ld - 14 Inf a nt - 0 T i1/2 Nucl i d e h a lf l i f e f o r nucl i d e i , i n d a y s. i Nucl i d e d e c a y c o n s t a nt f o r nucl i d e i. t p A v e r a g e tr a n s i t t i m e t o po i nt o f e x po s ur e (0 h o ur s). t b S e d i m e nt e x po s ur e t i m e (1 5 y e a r s). P a g e 1.10 9-14.

Oc o n ee Nucl e a r St a t i o n J a nu ary, 2007 Off s i t e D o se C alcul a t i o n M a nu a l (O DCM)

R e v i s i o n 47 S e ct i o n 4 - P a g e 7 4.0.2 GASEOUS EFFLUENT DOSE MODEL FOR THE MA XIMUM E XPOSED INDIVIDUAL T h e d o se c o ntr i b ut i o n s fr o m m e a s ur e d q u a nt i t i es o f r a d i oa ct i v e m a t e r i a l s i d e nt i f i e d i n g a se o u s efflu e nt r e l e a se d t o unr es tr i ct e d a r e a s s h a ll b e c alcul a t e d f o r th e m a x imum g a mm a a nd b e t a a i r d o se fr o m n o b l e g a ses , a nd f o r th e m a x i mum e x po se d i nd i v i du a l fr o m r a d i o i o d i n es , pa rt icul a t es , a nd o th e r s u s i ng th e f o ll o w i ng e q u a t i o n s:

G a se o u s D o se C alcul a t i o n s No ble Gas Dose Calculations G a mm a Ai r D o se ()xxxx=i i i Q M Q Dose / 10 17.3 8 Formula: adapted from NUREG

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8. W h e r e: D o se Gamma air d o se f o r th e tim e p e ri o d o f int e r es t (mrad). 3.17x10-8 Inv e r se num b e r o f se c o nd s in y e ar (y e ar/se c o nd s). M i Gamma air d o se fact o r du e t o gamma e mi ss i o n s f o r nuclid e i (mrad/yr p e r µCi/m 3). (S ee App endix A). /Q Th e high es t calculat e d annual av e rag e r elativ e c o nc e ntrati o n f o r any ar e a at o r b e y o nd th e s it e b oundary (se c/m 3)*. (S ee Ta b l e 6.0-9). Q i Activity f o r nuclid e i r e l e a se d during th e tim e p e ri o d o f int e r es t (µCi). B e ta Air D o se ()xxxx=i i i Q N Q Dose / 10 17.3 8 Formula: adapted from NUREG

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8. W h e r e: D o se B e ta air d o se f o r th e tim e p e ri o d o f int e r es t (mrad). 3.17x10-8 Inv e r se num b e r o f se c o nd s in y e ar (y e ar/se c o nd s). N i B e ta air d o se fact o r du e t o b e ta e mi ss i o n s f o r nuclid e i (mrad/yr p e r µCi/m 3). (S ee App e ndix A). /Q Th e high es t calculat e d annual av e rag e r elativ e c o nc e ntrati o n f o r any ar e a at o r b e y o nd th e s it e b oundary (se c/m 3)*. (S ee Ta b l e 6.0-9). Q i Activity f o r nuclid e i r e l e a se d during th e tim e p e ri o d o f int e r es t (µCi).

Oc o n ee Nucl e ar Stati o n January, 2007 Off s it e D o se Calculati o n Manual (O D C M)

R e vi s i o n 47 S e cti o n 4 - Pag e 8 Iodine, Particulates, and H

-3 Dose Organ Dose Calculation

()xxxx=i i o api p o a Q R W Dose 10 17.3 8 Formula: adapted from NUREG

-0133, pages 2 9 & 30. W h e r e: D o se o a Th e cumulativ e d o se c o mmitm e nt t o th e t otal b o dy o r any organ o , f o r an individual o f ag e gr o up a (mr em). 3.17x10-8 Inv e r se num b e r o f se c o nd s in y e ar (y e ar/se c o nd s). R oapi D o se c o mmitm e nt fact o r f o r organ o , ag e gr o up a, pathway p, and nuclid e i. Th e unit s ar e b a se d o n wh e th e r a di s p e r s i o n o r d e p o s iti o n fact o r i s u se d. W h e n a /Q i s u se d th e unit s ar e mr e m/yr p e r µCi/m 3. W h e n a D/Q i s u se d th e unit s ar e (m 2

  • mr e m/yr) p e r µCi/se c. (S ee App e ndic es G thr ough J f o r ag e gr o up and pathway s p ecific d o se c o mmitm e nt fact o r s). D i s p e r s i o n (/Q) o r d e p o s iti o n fact o r (D/Q)*. Th e fact o r u se d i s b a se d up o n th e pathway. N o t e: /Q i s alway s u se d f o r tritium. Pathway Fact o r U se d Gr o und Plan e D e p o s iti o n D/Q (m-2) Inhalati o n /Q (se c/m 3) V e g etati o n D/Q (m-2) Gra ss/C o w/M il k D/Q (m-2) Gra ss/G o at/M il k D/Q (m-2) W Gra ss/C o w/M e at D/Q (m-2) Q i Activity f o r nuclid e i, r e l e a se d during th e tim e p e ri o d o f int e r es t (µCi).
  • Th e d o se fr o m n o b l e gases r e l e a se d fr o m se mi-e l e vat e d r e l e a se p o int s , e.g., unit v e nt, i s calculat e d u sing th e se mi-e l e vat e d di s p e r s i o n fact o r s. Th e d o se fr o m n o b l e ga ses r e l e a se d fr o m gr o und l e v e l r e l e a se p o int s , e.g., Radwa s t e Facility v e nt, i s calculat e d u sing th e gr o und l e v e l di s p e r s i o n fact o r s. Th e t otal d o se i s th e s um o f th e se mi-e l e vat e d and gr o und l e v e l d o se calculati o n s. Maximum individual o rgan d o se i s d e t ermin e d b y calculating th e organ d o se at each o f th e /Q and D/Q l ocati o n s s h o wn in Ta b l e 6.0-9 and Ta b l e 6.0-10 (12 8 l ocati o n s) f o r b o th se mi-e l e vat e d r e l e a se p o int s and gr o und l e v e l r e l e a se p o int s , s umming th e tw o at e ach l ocati o n, and th e n ch oo s ing th e d o se fr o m th e maximum l ocati o n. D o se i s calculat e d only f o r th o se pathway s (e.g., gard e n, mil k animal, etc.) that actually e xi s t at e ach l ocati o n a s d e t ermin e d b y th e land u se c e n s u s s h o wn in Ta b l e 6.0-3. A s di s cu sse d in Oc o n ee UFSAR S ecti o n 2.1.1.3, th e b oundary f o r es ta b li shing ga se o u s efflu e nt r e l e a se limit s i s th e exclu s i o n ar e a b oundary (EAB). Th e EAB i s d efin e d a s a 1 mil e radiu s fr o m th e stati o n c e nt e r.

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R e vi s i o n 47 S e cti o n 4 - Pag e 9 Derivations of Iodine, Particulate, and H

-3 Dose Commitment Factors (Roapi) Gr o und Plan e D e p o s iti o n Pathway =i t o i o api i e D FG S F K K R)1 ()( Formula: from NUREG

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W h e r e: R oapi D o se c o mmitm e nt fact o r f o r organ o , ag e gr o up a, nuclid e i, f o r gr o und plan e d e p o s iti o n pathway (m 2*mr e m/yr p e r µCi/se c). (S ee App e ndic es G thr ough J f o r ag e gr o up and pathway s p ecific d o se c o mmitm e nt fact o r s). K' Unit s c o nv e r s i o n fact o r pCi/µCi (10 6). K" Unit s c o nv e r s i o n fact o r 8 7 6 0 hr/y e ar. SF Shi e lding fact o r (dim e n s i o nl ess) (0.7, fr o m R egulat o ry Guid e 1.10 9). D FG o i Gr o und plan e d o se c o nv e r s i o n fact o r f o r organ o , nuclid e i (mr e m/hr p e r pCi/m 2), fr o m Ta b l e E-6 o f R egulat o ry Guid e 1.10 9. i Nuclid e d ecay c o n stant f o r nuclid e i (se c-1). t Exp o s ur e tim e , 4.73x10 8 se c o nd s (1 5 y e ar s). Inhalati o n Pathway a o i a o api D FA B R K R))((= Formula: from NUREG

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W h e r e: R oapi D o se c o mmitm e nt fact o r f o r organ o , ag e gr o up a, nuclid e i, f o r inhalati o n pathway (mr e m/yr p e r µCi/m 3). (S ee App e ndic es G thr ough J f o r ag e gr o up and pathway s p ecific d o se c o mmitm e nt fact o r s). K' Unit s c o nv e r s i o n fact o r pCi/µCi (10 6). BR a Br e athing rat e f o r ag e gr o up (m 3/yr), fr o m R egulat o ry Guid e 1.10 9: Adult - 8 000 T ee n - 8 000 Child - 3700 Infant - 1400 (D FA o i)a Organ inhalati o n fact o r d o se c o nv e r s i o n fact o r f o r o rgan o , nuclid e i, ag e gr o up a (mr e m/pCi), fr o m Ta b l es E-7 thr ough E-10 o f R egulat o ry Guid e 1.10 9.

Oc o n ee Nucl e ar Stati o n January, 2007 Off s it e D o se Calculati o n Manual (O D C M)

R e vi s i o n 47 S e cti o n 4 - Pag e 10 V e g etati o n []h i L i t g S a t L L a a i o w i v oapi e f U e f U DFL Y r K R+xx+=)()()( Formula: from NUREG

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5. Where: R oapi D o s e c o mm it m e n t fa c t o r f o r orga n o , ag e gr o u p a , nucl i d e i , f o r v e g etati o n pathwa y (m 2*m r e m/y r p e r µC i/s e c). (S ee A pp e nd i c e s G thr o u gh J f o r ag e gr o u p a nd pathwa y s p e cifi c d o s e c o mm it m e n t fa c t o r s). K' U n it s c o n v e r s i o n fa c t o r p C i/µC i (10 6). r Fra c ti o n o f d e p o s it e d a c tivit y r etai n e d o n v e g etati o n, fr o m R e g ul at o r y Gu i d e 1.10 9. 1.0 f o r ra d i o i o d i n e. 0.2 f o r parti cul at e s. Y v V e g etati o n ar e a l d e ns it y (k g/m 2) (2.0, fr o m R e g ul at o r y Gu i d e 1.10 9). i Nucl i d e d e c a y c o ns ta n t f o r nucl i d e i (s e c-1). w D e c a y c o ns ta n t f o r r e m o va l o f a c tivit y o n l e af a nd p l a n t su rfa c e s b y w eath e ri n g (5.73x10-7 s e c-1 , fr o m N UR EG-0133). (D FL o i)a In g e s ti o n d o s e c o n v e r s i o n fa c t o r f o r nucl i d e i , orga n o , a nd ag e gr o u p a , fr o m T a b l e s E-11 thr o u gh E-14 o f R e g. Gu i d e 1.10 9 (m r e m/p C i). U L a C o nsum pti o n rat e o f fr e s h v e g etati o n f o r ag e gr o u p a (k g/y r) (fr o m R e g ul at o r y Gu i d e 1.10 9). Adul t - 6 4 T ee n - 42 C hi ld - 2 6 In fa n t - 0 f L Fra c ti o n o f a nnu a l i n ta k e o f fr e s h l e af y v e g etati o n gr o w n l o c ally (1.0, fr o m N UR EG-0133). t L A v erag e ti m e b e tw ee n harv e s t o f l e af y v e g etati o n a nd c o nsum pti o n (8.6x10 4 s e c o nds, (1 d ay), fr o m R e g ul at o r y Gu i d e 1.10 9). U S a C o nsum pti o n rat e o f s t o r e d v e g etati o n f o r ag e gr o u p a (k g/y r) (fr o m R e g ul at o r y Gu i d e 1.10 9). Adul t - 5 20 T ee n - 6 30 C hi ld - 5 20 In fa n t - 0 f g Fra c ti o n o f a nnu a l i n ta k e o f s t o r e d v e g etati o n (0.7 6 , fr o m R e g ul at o r y Gu i d e 1.10 9). t h A v erag e ti m e b e tw ee n harv e s t o f s t o r e d v e g etati o n a nd c o nsum pti o n (5.1 8x10 6 s e c o nds, (6 0 d ays), fr o m R e g ul at o r y Gu i d e 1.10 9).

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R e vi s i o n 47 S e c ti o n 4 - P ag e 11 V e g etati o n - Triti um [][])/5.0 (7 5.0)(H DFL f U f U" K'K' R a oi g S a L L a oapi+= Formula: from NUREG

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6. W h e r e: R oapi D o s e c o mm it m e n t fa c t o r f o r orga n o , ag e gr o u p a , f o r v e g etati o n pathwa y a nd triti um (m r e m/y r p e r µC i/m 3). (S ee A pp e nd i c e s G thr o u gh J f o r ag e gr o u p a nd pathwa y s p e cifi c d o s e c o mm it m e n t fa c t o r s). K' U n it s c o n v e r s i o n fa c t o r p C i/µC i (10 6). K'" U n it s c o n v e r s i o n fa c t o r g m/k g (10 3). U L a C o nsum pti o n rat e o f fr e s h v e g etati o n f o r ag e gr o u p a (k g/y r) (fr o m R e g ul at o r y Gu i d e 1.10 9). Adul t - 6 4 T ee n - 42 C hi ld - 2 6 In fa n t - 0 f L Fra c ti o n o f a nnu a l i n ta k e o f fr e s h l e af y v e g etati o n gr o w n l o c ally (1.0, fr o m N UR EG-0133). U S a C o nsum pti o n rat e o f s t o r e d v e g etati o n f o r ag e gr o u p a (k g/y r) (fr o m R e g ul at o r y Gu i d e 1.10 9). Adul t - 5 20 T ee n - 6 30 C hi ld - 5 20 In fa n t - 0 f g Fra c ti o n o f a nnu a l i n ta k e o f s t o r e d v e g etati o n (0.7 6 , fr o m R e g ul at o r y Gu i d e 1.10 9). (D FL o i)a In g e s ti o n d o s e c o n v e r s i o n fa c t o r f o r nucl i d e i , orga n o , a nd ag e gr o u p a , fr o m T a b l e s E-11 thr o u gh E-14 o f R e g ul at o r y Gu i d e 1.10 9 (m r e m/p C i). 0.7 5 Fra c ti o n o f t o ta l f ee d that i s wat e r. (Fr o m N UR EG-0133). 0.5 Rati o o f s p e cifi c a c tivit y o f f ee d gra ss wat e r t o at m o s ph e ri c wat e r. (Fr o m N UR EG-0133). H A b s o lu t e h um i d it y o f th e at m o s ph e r e (8 g m/m 3 , fr o m R e g ul at o r y Gu i d e 1.10 9).

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R e vi s i o n 47 S e c ti o n 4 - P ag e 12 G ra ss/C o w/M i l k f i h i t s t s p p s p a oi m i w i ap F oapi e Y e f f Y f f DFL r F U Q K R++=)1 ())(()( Formula: from NUREG

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& 33. Where: R oapi D o s e c o mm it m e n t fa c t o r f o r orga n o , ag e gr o u p a , nucl i d e i , f o r gra ss/c o w/m i l k pathwa y (m 2*m r e m/y r p e r µC i/s ec). (S ee A pp e nd i c e s G thr o u gh J f o r ag e gr o u p a nd pathwa y s p e cifi c d o s e c o mm it m e n t fa c t o r s). K' U n it s c o n v e r s i o n fa c t o r p C i/µC i (10 6). Q F C o w c o nsum pti o n rat e (5 0 k g/d a y, fr o m R e g ul at o r y Gu i d e 1.10 9) U ap C o nsum pti o n rat e o f c o w m i l k f o r ag e gr o u p a (l it e r s/y r , fr o m R e g ul at o r y Gu i d e 1.10 9). Adul t - 310 T ee n - 400 C hi ld - 330 In fa n t - 300 r Fra c ti o n o f d e p o s it e d a c tivit y r etai n e d o n c o ws f ee d gra ss, (fr o m R e g ul at o r y Gu i d e 1.10 9). 1.0 f o r ra d i o i o d i n e. 0.2 f o r parti cul at e s. Y p A gri cul t u ra l pr o duc tivit y b y un it ar e a o f pa s t u r e f ee d gra ss (0.7 k g/m 2 , fr o m R e g ul at o r y Gu i d e 1.10 9). Y s A gri cul t u ra l pr o duc tivit y b y un it ar e a o f s t o r e d f ee d (2.0 k g/m 2 , fr o m R e g ul at o r y Gu i d e 1.10 9). i Nucl i d e d e c a y c o ns ta n t f o r nucl i d e i (s e c-1). w D e c a y c o ns ta n t f o r r e m o va l o f a c tivit y o n l e af a nd p l a n t su rfa c e s b y w eath e ri n g (5.73x10-7 s e c-1 , fr o m N UR EG-0133). (D FL o i)a In g e s ti o n d o s e c o n v e r s i o n fa c t o r f o r nucl i d e i , orga n o , a nd ag e gr o u p a , fr o m T a b l e s E-11 thr o u gh E-14 o f R e g ul at o r y Gu i d e 1.10 9 (m r e m/p C i). F m i Sta b l e e l e m e n t tra ns f e r c o e ffi c i e n t f o r nucl i d e i , i n d a ys/l it e r , fr o m T a b l e E-1 o f R e g ul at o r y Gu i d e 1.10 9 f o r c o w m i l k. f p Fra c ti o n o f y e ar that th e c o w i s o n pa s t u r e (1.0, fr o m R G 1.10 9). f s Fra c ti o n o f th e c o w f ee d that i s pa s t u r e gra ss whi l e th e c o w i s o n pa s t u r e (1.0, fr o m R e g ul at o r y Gu i d e 1.10 9). t f T ra ns p o rt ti m e f o r pa s t u r e t o c o w , t o m i l k , t o r e c e pt o r (1.73E+0 5 s e c o nds, fr o m R e g ul at o r y Gu i d e 1.10 9). t h T ra ns p o rt ti m e fr o m pa s t u r e , t o harv e s t , t o c o w , t o m i l k , t o r e c e pt o r (7.7 8 e+0 6 s e c o nds, fr o m R e g ul at o r y Gu i d e 1.10 9).

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R e vi s i o n 47 S e c ti o n 4 - P ag e 13 G ra ss/C o w/M i l k - Triti um [])/5.0 (7 5.0)(H DFL U Q F K K R a io ap f m i oapi= Formula: from NUREG

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W h e r e: R oapi D o s e c o mm it m e n t fa c t o r f o r orga n o , ag e gr o u p a , nucl i d e i , f o r gra ss/c o w/m i l k pathwa y (m r e m/y r p e r µC i/m 3). (S ee A pp e nd i c e s G thr o u gh J f o r ag e gr o u p a nd pathwa y s p e cifi c d o s e c o mm it m e n t fa c t o r s). K' U n it s c o n v e r s i o n fa c t o r p C i/µC i (10 6). K'" U n it s c o n v e r s i o n fa c t o r g m/k g (10 3). Q F C o w c o nsum pti o n rat e (5 0 k g/d a y, fr o m R e g ul at o r y Gu i d e 1.10 9). U ap C o nsum pti o n rat e o f c o w m i l k f o r ag e gr o u p a (l it e r s/y r , fr o m R e g ul at o r y Gu i d e 1.10 9). Adul t - 310 T ee n - 400 C hi ld - 330 In fa n t - 300 (D FL o i)a In g e s ti o n d o s e c o n v e r s i o n fa c t o r f o r nucl i d e i , orga n o , a nd ag e gr o u p a , fr o m T a b l e s E-11 thr o u gh E-14 o f R e g ul at o r y Gu i d e 1.10 9 (m r e m/p C i). F m i Sta b l e e l e m e n t tra ns f e r c o e ffi c i e n t f o r nucl i d e i , i n d a ys/l it e r , fr o m T a b l e E-1 o f R e g ul at o r y Gu i d e 1.10 9 f o r c o w m i l k. 0.7 5 Fra c ti o n o f t o ta l f ee d that i s wat e r (fr o m N UR EG-0133). 0.5 Rati o o f s p e cifi c a c tivit y o f f ee d gra ss wat e r t o at m o s ph e ri c wat e r (fr o m N UR EG-0133). H A b s o lu t e h um i d it y o f th e at m o s ph e r e (8 g m/m 3 , fr o m R e g ul at o r y Gu i d e 1.10 9).

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R e vi s i o n 47 S e c ti o n 4 - P ag e 14 G ra ss/G o at/M i l k f i h i t s t s p p s p a oi m i w i ap F oapi e Y e f f Y f f DFL r F U Q K R++=)1 ())(()( Formula: from NUREG

-0133, pages 32

& 33. Where: R oapi D o s e c o mm it m e n t fa c t o r f o r orga n o , ag e gr o u p a , nucl i d e i , f o r gra ss/g o at/m i l k pathwa y (m 2*m r e m/y r p e r µC i/s ec). (S ee A pp e nd i c e s G thr o u gh J f o r ag e gr o u p a nd pathwa y s p e cifi c d o s e c o mm it m e n t fa c t o r s). K' U n it s c o n v e r s i o n fa c t o r p C i/µC i (10 6). Q F G o at c o nsum pti o n rat e (6 k g/d a y, fr o m R e g ul at o r y Gu i d e 1.10 9). U ap C o nsum pti o n rat e o f g o at m i l k f o r ag e gr o u p a (l it e r s/y r , fr o m R e g ul at o r y Gu i d e 1.10 9). Adul t - 310 T ee n - 400 C hi ld - 330 In fa n t - 300 r Fra c ti o n o f d e p o s it e d a c tivit y r etai n e d o n g o ats f ee d gra ss, fr o m R e g ul at o r y Gu i d e 1.10 9. 1.0 f o r ra d i o i o d i n e. 0.2 f o r parti cul at e s. Y p A gri cul t u ra l pr o duc tivit y b y un it ar e a o f pa s t u r e f ee d gra ss (0.7 k g/m 2 , fr o m R e g ul at o r y Gu i d e 1.10 9). Y s A gri cul t u ra l pr o duc tivit y b y un it ar e a o f s t o r e d f ee d (2.0 k g/m 2 , fr o m R e g ul at o r y Gu i d e 1.10 9). i Nucl i d e d e c a y c o ns ta n t f o r nucl i d e i (s e c-1). w D e c a y c o ns ta n t f o r r e m o va l o f a c tivit y o n l e af a nd p l a n t su rfa c e s b y w eath e ri n g (5.73x10-7 s e c-1 , fr o m N UR EG-0133). (D FL o i)a In g e s ti o n d o s e c o n v e r s i o n fa c t o r f o r nucl i d e i , orga n o , a nd ag e gr o u p a , fr o m T a b l e s E-11 thr o u gh E-14 o f R e g ul at o r y Gu i d e 1.10 9 (m r e m/p C i). F m i Sta b l e e l e m e n t tra ns f e r c o e ffi c i e n t f o r nucl i d e i , i n d a ys/l it e r , fr o m T a b l e E-2 o f R e g ul at o r y Gu i d e 1.10 9 f o r g o at m i l k. f p Fra c ti o n o f y e ar that th e g o at i s o n pa s t u r e (1.0, fr o m R G 1.10 9). f s Fra c ti o n o f th e g o at f ee d that i s pa s t u r e gra ss whi l e th e g o at i s o n pa s t u r e (1.0, fr o m R e g ul at o r y Gu i d e 1.10 9). t f T ra ns p o rt ti m e f o r pa s t u r e t o g o at , t o m i l k , t o r e c e pt o r (1.73E+0 5 s e c o nds, fr o m R e g ul at o r y Gu i d e 1.10 9). t h T ra ns p o rt ti m e fr o m pa s t u r e , t o harv e s t , t o g o at , t o m i l k , t o r e c e pt o r (7.7 8 e+0 6 s e c o nds, fr o m R e g ul at o r y Gu i d e 1.10 9).

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 4 - P ag e 1 5 G ra ss/G o at/M i l k - Triti um [])/5.0 (7 5.0)(H DFL U Q F K K R a oi ap f m i oapi= Formula: from NUREG

-0133, page 34.

W h e r e: R oapi D o s e c o mm it m e n t fa c t o r f o r orga n o , ag e gr o u p a , nucl i d e i , f o r gra ss/g o at/m i l k pathwa y (m r e m/y r p e r µC i/m 3). (S ee A pp e nd i c e s G thr o u gh J f o r ag e gr o u p a nd pathwa y s p e cifi c d o s e c o mm it m e n t fa c t o r s). K' U n it s c o n v e r s i o n fa c t o r p C i/µC i (10 6). K'" U n it s c o n v e r s i o n fa c t o r g m/k g (10 3). Q F G o at c o nsum pti o n rat e (6 k g/d a y, fr o m R e g ul at o r y Gu i d e 1.10 9). U ap C o nsum pti o n rat e o f g o at m i l k f o r ag e gr o u p a (l it e r s/y r , fr o m R e g ul at o r y Gu i d e 1.10 9). Adul t - 310 T ee n - 400 C hi ld - 330 In fa n t - 300 (D FL o i)a In g e s ti o n d o s e c o n v e r s i o n fa c t o r f o r nucl i d e i , orga n o , a nd ag e gr o u p a , fr o m T a b l e s E-11 thr o u gh E-14 o f R e g ul at o r y Gu i d e 1.10 9 (m r e m/p C i). F m i Sta b l e e l e m e n t tra ns f e r c o e ffi c i e n t f o r nucl i d e i , i n d a ys/l it e r , fr o m T a b l e E-2 o f R e g ul at o r y Gu i d e 1.10 9 f o r g o at m i l k. 0.7 5 Fra c ti o n o f t o ta l f ee d that i s wat e r (fr o m N UR EG-0133). 0.5 Rati o o f s p e cifi c a c tivit y o f f ee d gra ss wat e r t o at m o s ph e ri c wat e r (fr o m N UR EG-0133). H A b s o lu t e h um i d it y o f th e at m o s ph e r e (8 g m/m 3 , fr o m R e g ul at o r y Gu i d e 1.10 9).

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 4 - P ag e 1 6 G ra ss/C o w/M e at f i h i t s t s p p s p a i fi w i ap F oapi e Y e f f Y f f DFL r F U Q K R++=)1 ())(()( Formula: from NUREG

-0133, pages 34

& 3 5. Where: R oapi D o s e c o mm it m e n t fa c t o r f o r orga n o , ag e gr o u p a , nucl i d e i , f o r gra ss/c o w/m e at pathwa y (m 2*m r e m/y r p e r µC i/s ec). (S ee A pp e nd i c e s G thr o u gh J f o r ag e gr o u p a nd pathwa y s p e cifi c d o s e c o mm it m e n t fa c t o r s). K' U n it s c o n v e r s i o n fa c t o r p C i/µC i (10 6). Q F C o w c o nsum pti o n rat e (5 0 k g/d a y, fr o m R e g ul at o r y Gu i d e 1.10 9). U ap C o nsum pti o n rat e o f c o w m e at f o r ag e gr o u p a (k g/y r , fr o m R e g ul at o r y Gu i d e 1.10 9). Adul t - 110 T ee n - 65 C hi ld - 41 In fa n t - 0 r Fra c ti o n o f d e p o s it e d a c tivit y r etai n e d o n c o ws f ee d gra ss (fr o m R e g ul at o r y Gu i d e 1.10 9). 1.0 f o r ra d i o i o d i n e. 0.2 f o r parti cul at e s. Y p A gri cul t u ra l pr o duc tivit y b y un it ar e a o f pa s t u r e f ee d gra ss (0.7 k g/m 2 , fr o m R e g ul at o r y Gu i d e 1.10 9). Y s A gri cul t u ra l pr o duc tivit y b y un it ar e a o f s t o r e d f ee d (2.0 k g/m 2 , fr o m R e g ul at o r y Gu i d e 1.10 9). i Nucl i d e d e c a y c o ns ta n t f o r nucl i d e i (s e c-1). w D e c a y c o ns ta n t f o r r e m o va l o f a c tivit y o n l e af a nd p l a n t su rfa c e s b y w eath e ri n g (5.73x10-7 s e c-1 , fr o m N UR EG-0133). (D FL o i)a In g e s ti o n d o s e c o n v e r s i o n fa c t o r f o r nucl i d e i , orga n o , a nd ag e gr o u p a , fr o m T a b l e s E-11 thr o u gh E-14 o f R e g ul at o r y Gu i d e 1.10 9 (m r e m/p C i). F fi Sta b l e e l e m e n t tra ns f e r c o e ffi c i e n t f o r nucl i d e i , i n d a ys/k g , fr o m T a b l e E-1 o f R e g ul at o r y Gu i d e 1.10 9 f o r c o w m e at. f p Fra c ti o n o f y e ar that th e c o w i s o n pa s t u r e (1.0, fr o m R G 1.10 9). f s Fra c ti o n o f th e c o w f ee d that i s pa s t u r e gra ss whi l e th e c o w i s o n pa s t u r e (1.0, fr o m R e g ul at o r y Gu i d e 1.10 9). t f T ra ns p o rt ti m e fr o m pa s t u r e t o r e c e pt o r (1.73E+0 6 s e c o nds, fr o m R e g ul at o r y Gu i d e 1.10 9). t h T ra ns p o rt ti m e fr o m c r o p fi e ld t o r e c e pt o r (7.7 8 E+0 6 s e c o nds, fr o m R e g ul at o r y Gu i d e 1.10 9).

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 4 - P ag e 17 G ra ss/C o w/M e at - Triti um [])/5.0 (7 5.0)(H DFL U Q F K K R a oi ap F fi oapi= Formula: from NUREG

-0133, page 3

5. W h e r e: R oapi D o s e c o mm it m e n t fa c t o r f o r orga n o , ag e gr o u p a , nucl i d e i , f o r gra ss/c o w/m e at pathwa y (m r e m/y r p e r µC i/m 3). (S ee A pp e nd i c e s G thr o u gh J f o r ag e gr o u p a nd pathwa y s p e cifi c d o s e c o mm it m e n t fa c t o r s). K' U n it s c o n v e r s i o n fa c t o r p C i/µC i (10 6). K'" U n it s c o n v e r s i o n fa c t o r g m/k g (10 3). Q F C o w c o nsum pti o n rat e (5 0 k g/d a y, fr o m R e g ul at o r y Gu i d e 1.10 9). U ap C o nsum pti o n rat e o f c o w m e at f o r ag e gr o u p a (k g/y r , fr o m R e g ul at o r y Gu i d e 1.10 9). Adul t - 110 T ee n - 65 C hi ld - 41 In fa n t - 0 (D FL o i)a In g e s ti o n d o s e c o n v e r s i o n fa c t o r f o r nucl i d e i , orga n o , a nd ag e gr o u p a , fr o m T a b l e s E-11 thr o u gh E-14 o f R e g ul at o r y Gu i d e 1.10 9 (m r e m/p C i). F fi Sta b l e e l e m e n t tra ns f e r c o e ffi c i e n t f o r nucl i d e i , i n d a ys/l it e r , fr o m T a b l e E-1 o f R e g ul at o r y Gu i d e 1.10 9 f o r c o w m e at. 0.7 5 Fra c ti o n o f t o ta l f ee d that i s wat e r (fr o m N UR EG-0133). 0.5 Rati o o f s p e cifi c a c tivit y o f f ee d gra ss wat e r t o at m o s ph e ri c wat e r (fr o m N UR EG-0133). H A b s o lu t e h um i d it y o f th e at m o s ph e r e (8 g m/m 3 , fr o m R e g ul at o r y Gu i d e 1.10 9).

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 4 - P ag e 1 8 4.0.3 DIRECT RADIATION D ir e c t ra diati o n i s that ra diati o n fr o m c o n fi n e d s o u r c e s, a nd d o e s n o t i nclud e a ny e x t e r n a l c o m p o n e n t fr o m ra d i o a c tiv e e ff lu e n t s. T h e p o i n t k e r n e l m e th o d ha s b ee n us e d t o c alcul at e o ff s it e d o s e rat e s fr o m ra d i o a c tiv e m at eria ls s t o r e d i n th e r e f u e l i n g wat e r s t o rag e ta n k s, r e a c t o r m a k e u p wat e r s t o rag e ta n k s, a nd t e m p o rar y o ns it e ra d wa s t e s t orag e ta n k s. D o s e c alculati o ns us i n g thi s m e th o d p e rf o r m e d f o r Oc o n ee Nucl e ar Stati o n i nd i c at e d ir e c t ra diati o n d o s e s ar e muc h l e ss tha n 0.01 m r e m/y r a nd, th e r e f o r e , m a k e a n e g ligi b l e c o ntri b u ti o n t o i nd ivi du a l d o s e. Li k e wi s e , d ir e c t a nd air-scatt e r ra diati o n d o s e c o ntri b u ti o ns fr o m th e o ns it e Ind e p e nd e n t Sp e n t F u e l St orag e Ins ta ll ati o n (ISFS I) at Oc o n ee hav e b ee n c alcul at e d a nd d o cum e n t e d i n th e " Oc o n ee Nucl e ar Sit e 10C FR 72.212 Writt e n E va luati o ns" r e p o rt. T h e m a x i mum d o s e rat e t o th e n e ar e s t p o t e n tia l r e s i d e n t fr o m th e Oc o n ee ISFS I i s c alcul at e d t o b e 0.0268 m r e m/y r. D ir e c t ra d iati o n d o s e s wi ll n o t b e c alcul at e d r o u ti n ely. 4.0.4 EFFLUENT APPORTIONMENT F o r th e Oc o n ee Nucl e ar Stati o n th e e ff lu e n t r e l e a s e s ar e app orti o n e d e q u ally t o e a c h un it f o r e a c h s it e a s r e c o mm e nd e d b y S e c ti o n 3.1 o f N UR EG-0133, b e c a us e th e s har e d ra d wa s t e tr e at m e n t sys t e ms at e a c h s it e m a k e it i m pra c ti c a l t o accu rat e ly a sc ri b e r e l e a s e s t o a s p e cifi c r e a c t o r un it. F o r Annu a l E ff lu e n t R e l e a s e R e p o rt p u rp o s e s e ff lu e n t r e l e a s e s ar e summ e d f o r e a c h un it , a nd th e m a x i mum i ndivi du a l d o s e t o th e p u b l i c i s r e p o rt e d a s a s it e t o ta l.

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.

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:

"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."

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.

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).

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

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

  • 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
  • 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)

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

  • 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.

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

  • 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
  • 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.
    • 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.

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)

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)

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 (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.

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.

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

) 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 hours0.0197 days <br />0.472 hours <br />0.00281 weeks <br />6.4685e-4 months <br /> 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

-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

-T (between 6 0m-10m levels)

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)

Oconee Semi

-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

  • 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.

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 Semi

-Elevated 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 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

  • 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.

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)

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

  • 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.

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 7.0 LICENSEE 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.

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

ever released to #3 CTP.

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

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.

Section 6 - Page 4Changed 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 6Location 036 symbol added to map in N sector.

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

Figure 6.0-3 regenerated to depict 2006 census data.

Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X A Dose Factors for Exposure to a Semi

-Infinite Cloud of No ble Gases* Appendix A Dose Factors for Exposure to a Semi-Infinite Cloud of No b le Gases - Page 1 of 1 Nuclide K i Total Body mrem/yr/ µµµµCi/m 3 L i S k in mrem/yr/ µµµµCi/m 3 M i Gamma Air mrad/yr/ µµµµCi/m 3 N i Beta Air mrad/yr/ µµµµCi/m 3 AR-41 8.840E+03 2.69 0E+03 9.300E+03 3.2 8 0E+03 K R-8 3M 7.56 0E-02 0.000E+00 1.930E+01 2.88 0E+02 K R-85 M 1.170E+03 1.4 6 0E+03 1.230E+03 1.970E+03 K R-85 1.610E+01 1.340E+03 1.720E+01 1.95 0E+03 K R-8 7 5.920E+03 9.730E+03 6.170E+03 1.030E+04 K R-88 1.470E+04 2.370E+03 1.520E+04 2.930E+03 K R-89 1.66 0E+04 1.010E+04 1.730E+04 1.0 6 0E+04 K R-9 0 1.56 0E+04 7.2 9 0E+03 1.630E+04 7.830E+03 X E-131M 9.1 5 0E+01 4.7 6 0E+02 1.56 0E+02 1.110E+03 X E-133M 2.510E+02 9.940E+02 3.270E+02 1.4 8 0E+03 X E-133 2.940E+02 3.0 6 0E+02 3.530E+02 1.0 5 0E+03 X E-13 5 M 3.120E+03 7.110E+02 3.3 6 0E+03 7.3 9 0E+02 X E-13 5 1.810E+03 1.86 0E+03 1.920E+03 2.4 6 0E+03 X E-137 1.420E+03 1.220E+04 1.510E+03 1.270E+04 X E-13 8 8.830E+03 4.130E+03 9.210E+03 4.7 5 0E+03

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:

CHILD Pathway: Inhalation (INHL) Units: mrem/yr / µµµµCi/m 3 Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in 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 3.59 0E+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+0 6 1.140E+0 5 0.000E+00 0.000E+00 0.000E+00 4.220E+04 0.000E+00 9.88 0E+04 CR-5 1 0.000E+00 0.000E+00 8.55 0E+01 2.430E+01 1.700E+04 1.0 8 0E+03 0.000E+00 1.540E+02 MN-5 4 0.000E+00 4.2 9 0E+04 0.000E+00 1.000E+04 1.58 0E+0 6 2.2 9 0E+04 0.000E+00 9.510E+03 MN-56 0.000E+00 1.66 0E+00 0.000E+00 1.670E+00 1.310E+04 1.230E+0 5 0.000E+00 3.120E-01 FE-55 4.740E+04 2.520E+04 0.000E+00 0.000E+00 1.110E+0 5 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+0 6 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+0 6 3.440E+04 0.000E+00 3.1 6 0E+03 CO-6 0 0.000E+00 1.310E+04 0.000E+00 0.000E+00 7.070E+0 6 9.620E+04 0.000E+00 2.2 6 0E+04 NI-6 3 8.210E+0 5 4.620E+04 0.000E+00 0.000E+00 2.7 5 0E+0 5 6.330E+03 0.000E+00 2.800E+04 NI-65 2.99 0E+00 2.96 0E-01 0.000E+00 0.000E+00 8.1 8 0E+03 8.400E+04 0.000E+00 1.640E-01 CU-6 4 0.000E+00 1.99 0E+00 0.000E+00 6.030E+00 9.58 0E+03 3.670E+04 0.000E+00 1.070E+00 Z N-65 4.2 6 0E+04 1.130E+0 5 0.000E+00 7.140E+04 9.95 0E+0 5 1.630E+04 0.000E+00 7.030E+04 Z N-69 6.700E-02 9.66 0E-02 0.000E+00 5.85 0E-02 1.420E+03 1.020E+04 0.000E+00 8.920E-03 BR-8 3 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-8 4 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.4 8 0E+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 1.98 0E+0 5 0.000E+00 0.000E+00 0.000E+00 7.99 0E+03 0.000E+00 1.140E+0 5 RB-88 0.000E+00 5.620E+02 0.000E+00 0.000E+00 0.000E+00 1.720E+01 0.000E+00 3.66 0E+02 RB-89 0.000E+00 3.4 5 0E+02 0.000E+00 0.000E+00 0.000E+00 1.89 0E+00 0.000E+00 2.900E+02 SR-89 5.99 0E+0 5 0.000E+00 0.000E+00 0.000E+00 2.1 6 0E+0 6 1.670E+0 5 0.000E+00 1.720E+04 SR-9 0 1.010E+0 8 0.000E+00 0.000E+00 0.000E+00 1.4 8 0E+07 3.430E+0 5 0.000E+00 6.440E+0 6 SR-9 1 1.210E+02 0.000E+00 0.000E+00 0.000E+00 5.330E+04 1.740E+0 5 0.000E+00 4.59 0E+00 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 2 of 3 Agegroup:

CHILD Pathway: Inhalation (INHL) Units: mrem/yr / µµµµCi/m 3 Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in Total Body SR-9 2 1.310E+01 0.000E+00 0.000E+00 0.000E+00 2.400E+04 2.420E+0 5 0.000E+00 5.2 5 0E-01 Y-9 0 4.110E+03 0.000E+00 0.000E+00 0.000E+00 2.620E+0 5 2.68 0E+0 5 0.000E+00 1.110E+02 Y-9 1 9.140E+0 5 0.000E+00 0.000E+00 0.000E+00 2.630E+0 6 1.840E+0 5 0.000E+00 2.440E+04 Y-9 1M 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-9 2 2.030E+01 0.000E+00 0.000E+00 0.000E+00 2.3 9 0E+04 2.3 9 0E+0 5 0.000E+00 5.810E-01 Y-9 3 1.86 0E+02 0.000E+00 0.000E+00 0.000E+00 7.440E+04 3.88 0E+0 5 0.000E+00 5.110E+00 Z R-95 1.900E+0 5 4.1 8 0E+04 0.000E+00 5.96 0E+04 2.230E+0 6 6.110E+04 0.000E+00 3.700E+04 Z R-9 7 1.88 0E+02 2.720E+01 0.000E+00 3.88 0E+01 1.130E+0 5 3.510E+0 5 0.000E+00 1.600E+01 NB-95 2.3 5 0E+04 9.1 8 0E+03 0.000E+00 8.620E+03 6.140E+0 5 3.700E+04 0.000E+00 6.55 0E+03 MO-99 0.000E+00 1.720E+02 0.000E+00 3.920E+02 1.3 5 0E+0 5 1.270E+0 5 0.000E+00 4.2 6 0E+01 T C-99 M 1.7 8 0E-03 3.4 8 0E-03 0.000E+00 5.070E-02 9.510E+02 4.810E+03 0.000E+00 5.770E-02 T C-101 8.100E-0 5 8.510E-0 5 0.000E+00 1.4 5 0E-03 5.85 0E+02 1.630E+01 0.000E+00 1.0 8 0E-03 RU-103 2.7 9 0E+03 0.000E+00 0.000E+00 7.030E+03 6.620E+0 5 4.4 8 0E+04 0.000E+00 1.070E+03 RU-10 5 1.530E+00 0.000E+00 0.000E+00 1.340E+00 1.59 0E+04 9.95 0E+04 0.000E+00 5.55 0E-01 RU-10 6 1.3 6 0E+0 5 0.000E+00 0.000E+00 1.840E+0 5 1.430E+07 4.2 9 0E+0 5 0.000E+00 1.69 0E+04 AG-110M 1.69 0E+04 1.140E+04 0.000E+00 2.120E+04 5.4 8 0E+0 6 1.000E+0 5 0.000E+00 9.140E+03 T E-12 5 M 6.730E+03 2.330E+03 1.920E+03 0.000E+00 4.770E+0 5 3.3 8 0E+04 0.000E+00 9.140E+02 T E-127 2.770E+00 9.510E-01 1.96 0E+00 7.070E+00 1.000E+04 5.620E+04 0.000E+00 6.100E-01 T E-127M 2.4 9 0E+04 8.55 0E+03 6.070E+03 6.3 6 0E+04 1.4 8 0E+0 6 7.140E+04 0.000E+00 3.020E+03 T E-12 9 9.770E-02 3.500E-02 7.140E-02 2.570E-01 2.930E+03 2.55 0E+04 0.000E+00 2.3 8 0E-02 T E-12 9 M 1.920E+04 6.840E+03 6.330E+03 5.030E+04 1.7 6 0E+0 6 1.820E+0 5 0.000E+00 3.040E+03 T E-131 2.170E-02 8.440E-03 1.700E-02 5.88 0E-02 2.0 5 0E+03 1.330E+03 0.000E+00 6.59 0E-03 T E-131M 1.340E+02 5.920E+01 9.770E+01 4.000E+02 2.0 6 0E+0 5 3.0 8 0E+0 5 0.000E+00 5.070E+01 T E-132 4.810E+02 2.720E+02 3.170E+02 1.770E+03 3.770E+0 5 1.3 8 0E+0 5 0.000E+00 2.630E+02 I-130 8.1 8 0E+03 1.640E+04 1.85 0E+0 6 2.4 5 0E+04 0.000E+00 5.110E+03 0.000E+00 8.440E+03 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 3 of 3 Agegroup:

CHILD Pathway: Inhalation (INHL) Units: mrem/yr / µµµµCi/m 3 Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in Total Body I-131 4.810E+04 4.810E+04 1.620E+07 7.88 0E+04 0.000E+00 2.840E+03 0.000E+00 2.730E+04 I-132 2.120E+03 4.070E+03 1.940E+0 5 6.2 5 0E+03 0.000E+00 3.200E+03 0.000E+00 1.88 0E+03 I-133 1.66 0E+04 2.030E+04 3.85 0E+0 6 3.3 8 0E+04 0.000E+00 5.4 8 0E+03 0.000E+00 7.700E+03 I-134 1.170E+03 2.1 6 0E+03 5.070E+04 3.300E+03 0.000E+00 9.55 0E+02 0.000E+00 9.95 0E+02 I-13 5 4.920E+03 8.730E+03 7.920E+0 5 1.340E+04 0.000E+00 4.440E+03 0.000E+00 4.140E+03 CS-134 6.510E+0 5 1.010E+0 6 0.000E+00 3.300E+0 5 1.210E+0 5 3.85 0E+03 0.000E+00 2.2 5 0E+0 5 CS-13 6 6.510E+04 1.710E+0 5 0.000E+00 9.55 0E+04 1.4 5 0E+04 4.1 8 0E+03 0.000E+00 1.1 6 0E+0 5 CS-137 9.0 6 0E+0 5 8.2 5 0E+0 5 0.000E+00 2.820E+0 5 1.040E+0 5 3.620E+03 0.000E+00 1.2 8 0E+0 5 CS-13 8 6.330E+02 8.400E+02 0.000E+00 6.220E+02 6.810E+01 2.700E+02 0.000E+00 5.55 0E+02 BA-13 9 1.840E+00 9.840E-04 0.000E+00 8.620E-04 5.770E+03 5.770E+04 0.000E+00 5.3 6 0E-02 BA-140 7.400E+04 6.4 8 0E+01 0.000E+00 2.110E+01 1.740E+0 6 1.020E+0 5 0.000E+00 4.330E+03 BA-141 1.96 0E-01 1.0 9 0E-04 0.000E+00 9.470E-0 5 2.920E+03 2.7 5 0E+02 0.000E+00 6.3 6 0E-03 BA-142 5.000E-02 3.600E-0 5 0.000E+00 2.910E-0 5 1.640E+03 2.740E+00 0.000E+00 2.7 9 0E-03 LA-140 6.440E+02 2.2 5 0E+02 0.000E+00 0.000E+00 1.830E+0 5 2.2 6 0E+0 5 0.000E+00 7.55 0E+01 LA-142 1.300E+00 4.110E-01 0.000E+00 0.000E+00 8.700E+03 7.58 0E+04 0.000E+00 1.2 9 0E-01 CE-141 3.920E+04 1.95 0E+04 0.000E+00 8.55 0E+03 5.440E+0 5 5.66 0E+04 0.000E+00 2.900E+03 CE-143 3.66 0E+02 1.99 0E+02 0.000E+00 8.3 6 0E+01 1.1 5 0E+0 5 1.270E+0 5 0.000E+00 2.870E+01 CE-144 6.770E+0 6 2.120E+0 6 0.000E+00 1.170E+0 6 1.200E+07 3.88 0E+0 5 0.000E+00 3.610E+0 5 PR-143 1.85 0E+04 5.55 0E+03 0.000E+00 3.000E+03 4.330E+0 5 9.730E+04 0.000E+00 9.140E+02 PR-144 5.96 0E-02 1.85 0E-02 0.000E+00 9.770E-03 1.570E+03 1.970E+02 0.000E+00 3.000E-03 N D-147 1.0 8 0E+04 8.730E+03 0.000E+00 4.810E+03 3.2 8 0E+0 5 8.210E+04 0.000E+00 6.810E+02 W-1 8 7 1.630E+01 9.66 0E+00 0.000E+00 0.000E+00 4.110E+04 9.100E+04 0.000E+00 4.330E+00 NP-23 9 4.66 0E+02 3.340E+01 0.000E+00 9.730E+01 5.810E+04 6.400E+04 0.000E+00 2.3 5 0E+01 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X C A i Adult Dose Factors for use in the Li quid Dose Calculations Appendix C Ai Adult Water - Page 1 of 3 Agegroup:

ADULT Pathway: Pota ble Water (P Wtr) Units: mrem/hr / µµµµCi/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in 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 2.3 6 0E+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 9.7 5 0E+02 0.000E+00 0.000E+00 0.000E+00 1.7 6 0E+03 0.000E+00 6.0 6 0E+02 CR-5 1 0.000E+00 0.000E+00 1.310E-01 4.820E-02 2.900E-01 5.500E+01 0.000E+00 2.1 9 0E-01 MN-5 4 0.000E+00 3.800E+02 0.000E+00 1.130E+02 0.000E+00 1.1 6 0E+03 0.000E+00 7.2 5 0E+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 2.2 9 0E+02 1.58 0E+02 0.000E+00 0.000E+00 8.820E+01 9.070E+01 0.000E+00 3.69 0E+01 FE-59 3.58 0E+02 8.420E+02 0.000E+00 0.000E+00 2.3 5 0E+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 1.2 5 0E+03 0.000E+00 1.3 8 0E+02 CO-6 0 0.000E+00 1.7 8 0E+02 0.000E+00 0.000E+00 0.000E+00 3.340E+03 0.000E+00 3.930E+02 NI-6 3 1.0 8 0E+04 7.500E+02 0.000E+00 0.000E+00 0.000E+00 1.56 0E+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-6 4 0.000E+00 3.59 0E+00 0.000E+00 9.0 6 0E+00 0.000E+00 3.0 6 0E+02 0.000E+00 1.69 0E+00 Z N-65 4.020E+02 1.2 8 0E+03 0.000E+00 8.56 0E+02 0.000E+00 8.0 6 0E+02 0.000E+00 5.7 8 0E+02 Z N-69 1.070E-04 2.0 5 0E-04 0.000E+00 1.330E-04 0.000E+00 3.0 8 0E-0 5 0.000E+00 1.430E-0 5 BR-8 3 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.4 8 0E-01 0.000E+00 1.030E-01 BR-8 4 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 4.3 8 0E-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 3.3 6 0E-12 0.000E+00 0.000E+00 0.000E+00 4.640E-23 0.000E+00 1.7 8 0E-12 RB-89 0.000E+00 3.0 9 0E-14 0.000E+00 0.000E+00 0.000E+00 1.7 9 0E-27 0.000E+00 2.170E-14 SR-89 2.55 0E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4.0 8 0E+03 0.000E+00 7.310E+02 SR-9 0 6.310E+0 5 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.820E+04 0.000E+00 1.55 0E+0 5 SR-9 1 1.96 0E+02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 9.3 5 0E+02 0.000E+00 7.930E+00 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X C A i Adult Dose Factors for use in the Li quid Dose Calculations Appendix C Ai Adult Water - Page 2 of 3 Agegroup:

ADULT Pathway: Pota ble Water (P Wtr) Units: mrem/hr / µµµµCi/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in Total Body SR-9 2 8.2 9 0E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.640E+02 0.000E+00 3.59 0E-01 Y-9 0 7.030E-01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 7.4 6 0E+03 0.000E+00 1.89 0E-02 Y-9 1 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-9 1M 3.3 6 0E-07 0.000E+00 0.000E+00 0.000E+00 0.000E+00 9.86 0E-07 0.000E+00 1.300E-0 8 Y-9 2 6.710E-03 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.170E+02 0.000E+00 1.96 0E-04 Y-9 3 9.770E-02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.100E+03 0.000E+00 2.700E-03 Z R-95 2.520E+00 8.070E-01 0.000E+00 1.270E+00 0.000E+00 2.56 0E+03 0.000E+00 5.4 6 0E-01 Z R-9 7 8.540E-02 1.720E-02 0.000E+00 2.600E-02 0.000E+00 5.340E+03 0.000E+00 7.88 0E-03 NB-95 5.130E-01 2.85 0E-01 0.000E+00 2.820E-01 0.000E+00 1.730E+03 0.000E+00 1.530E-01 MO-99 0.000E+00 3.1 6 0E+02 0.000E+00 7.1 6 0E+02 0.000E+00 7.330E+02 0.000E+00 6.020E+01 T C-99 M 5.1 6 0E-03 1.4 6 0E-02 0.000E+00 2.210E-01 7.140E-03 8.630E+00 0.000E+00 1.86 0E-01 T C-101 1.130E-17 1.630E-17 0.000E+00 2.930E-1 6 8.320E-1 8 4.89 0E-2 9 0.000E+00 1.600E-1 6 RU-103 1.530E+01 0.000E+00 0.000E+00 5.820E+01 0.000E+00 1.7 8 0E+03 0.000E+00 6.570E+00 RU-10 5 1.970E-01 0.000E+00 0.000E+00 2.540E+00 0.000E+00 1.200E+02 0.000E+00 7.7 6 0E-02 RU-10 6 2.2 9 0E+02 0.000E+00 0.000E+00 4.410E+02 0.000E+00 1.4 8 0E+04 0.000E+00 2.89 0E+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 T E-12 5 M 2.220E+02 8.030E+01 6.670E+01 9.020E+02 0.000E+00 8.85 0E+02 0.000E+00 2.970E+01 T E-127 3.7 8 0E+00 1.3 6 0E+00 2.800E+00 1.540E+01 0.000E+00 2.98 0E+02 0.000E+00 8.170E-01 T E-127M 5.620E+02 2.010E+02 1.440E+02 2.2 8 0E+03 0.000E+00 1.88 0E+03 0.000E+00 6.840E+01 T E-12 9 1.920E-03 7.230E-04 1.4 8 0E-03 8.0 8 0E-03 0.000E+00 1.4 5 0E-03 0.000E+00 4.69 0E-04 T E-12 9 M 9.470E+02 3.530E+02 3.2 5 0E+02 3.95 0E+03 0.000E+00 4.770E+03 0.000E+00 1.500E+02 T E-131 3.520E-0 9 1.470E-0 9 2.900E-0 9 1.540E-0 8 0.000E+00 4.99 0E-10 0.000E+00 1.110E-0 9 T E-131M 1.0 9 0E+02 5.340E+01 8.4 5 0E+01 5.400E+02 0.000E+00 5.300E+03 0.000E+00 4.4 5 0E+01 T E-132 1.88 0E+02 1.220E+02 1.3 5 0E+02 1.170E+03 0.000E+00 5.770E+03 0.000E+00 1.140E+02 I-130 3.210E+01 9.4 6 0E+01 8.020E+03 1.4 8 0E+02 0.000E+00 8.140E+01 0.000E+00 3.730E+01 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X C A i Adult Dose Factors for use in the Li quid Dose Calculations Appendix C Ai Adult Water - Page 3 of 3 Agegroup:

ADULT Pathway: Pota ble Water (P Wtr) Units: mrem/hr / µµµµCi/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in Total Body I-131 3.320E+02 4.740E+02 1.55 0E+0 5 8.130E+02 0.000E+00 1.2 5 0E+02 0.000E+00 2.720E+02 I-132 4.540E-01 1.220E+00 4.2 5 0E+01 1.940E+00 0.000E+00 2.2 8 0E-01 0.000E+00 4.2 5 0E-01 I-133 7.920E+01 1.3 8 0E+02 2.020E+04 2.400E+02 0.000E+00 1.240E+02 0.000E+00 4.200E+01 I-134 6.58 0E-04 1.7 9 0E-03 3.100E-02 2.840E-03 0.000E+00 1.56 0E-0 6 0.000E+00 6.3 9 0E-04 I-13 5 1.0 5 0E+01 2.7 5 0E+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 3.98 0E+03 1.320E+03 2.1 5 0E+02 0.000E+00 1.010E+04 CS-13 6 5.2 8 0E+02 2.0 8 0E+03 0.000E+00 1.1 6 0E+03 1.59 0E+02 2.370E+02 0.000E+00 1.500E+03 CS-137 6.630E+03 9.070E+03 0.000E+00 3.0 8 0E+03 1.020E+03 1.7 6 0E+02 0.000E+00 5.940E+03 CS-13 8 8.4 5 0E-07 1.670E-0 6 0.000E+00 1.230E-0 6 1.210E-07 7.120E-12 0.000E+00 8.2 6 0E-07 BA-13 9 1.99 0E-02 1.420E-0 5 0.000E+00 1.330E-0 5 8.0 5 0E-0 6 3.530E-02 0.000E+00 5.830E-04 BA-140 1.640E+03 2.070E+00 0.000E+00 7.020E-01 1.1 8 0E+00 3.3 9 0E+03 0.000E+00 1.0 8 0E+02 BA-141 5.440E-12 4.120E-1 5 0.000E+00 3.830E-1 5 2.340E-1 5 2.570E-21 0.000E+00 1.840E-13 BA-142 6.2 9 0E-21 6.470E-24 0.000E+00 5.4 6 0E-24 3.66 0E-24 8.86 0E-3 9 0.000E+00 3.96 0E-22 LA-140 1.69 0E-01 8.530E-02 0.000E+00 0.000E+00 0.000E+00 6.2 6 0E+03 0.000E+00 2.2 5 0E-02 LA-142 5.720E-0 5 2.600E-0 5 0.000E+00 0.000E+00 0.000E+00 1.900E-01 0.000E+00 6.4 8 0E-0 6 CE-141 7.710E-01 5.210E-01 0.000E+00 2.420E-01 0.000E+00 1.99 0E+03 0.000E+00 5.910E-02 CE-143 1.070E-01 7.89 0E+01 0.000E+00 3.470E-02 0.000E+00 2.95 0E+03 0.000E+00 8.730E-03 CE-144 4.0 6 0E+01 1.700E+01 0.000E+00 1.010E+01 0.000E+00 1.370E+04 0.000E+00 2.1 8 0E+00 PR-143 7.4 6 0E-01 2.99 0E-01 0.000E+00 1.730E-01 0.000E+00 3.270E+03 0.000E+00 3.700E-02 PR-144 7.3 5 0E-1 6 3.0 5 0E-1 6 0.000E+00 1.720E-1 6 0.000E+00 1.0 6 0E-22 0.000E+00 3.730E-17 N D-147 5.070E-01 5.86 0E-01 0.000E+00 3.430E-01 0.000E+00 2.810E+03 0.000E+00 3.510E-02 W-1 8 7 6.0 5 0E+00 5.0 5 0E+00 0.000E+00 0.000E+00 0.000E+00 1.66 0E+03 0.000E+00 1.770E+00 NP-23 9 8.55 0E-02 8.400E-03 0.000E+00 2.620E-02 0.000E+00 1.720E+03 0.000E+00 4.630E-03 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X C A i Adult Dose Factors for use in the Li quid Dose Calculations Appendix C Ai Adult Fish - Page 1 of 3 Agegroup:

ADULT Pathway: Fresh Water Fish

- Sport (FFSP) Units: mrem/hr / µµµµCi/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in Total Body H-3 0.000E+00 2.2 6 0E-01 2.2 6 0E-01 2.2 6 0E-01 2.2 6 0E-01 2.2 6 0E-01 0.000E+00 2.2 6 0E-01 C-14 3.130E+04 6.2 6 0E+03 6.2 6 0E+03 6.2 6 0E+03 6.2 6 0E+03 6.2 6 0E+03 0.000E+00 6.2 6 0E+03 NA-24 1.3 5 0E+02 1.3 5 0E+02 1.3 5 0E+02 1.3 5 0E+02 1.3 5 0E+02 1.3 5 0E+02 0.000E+00 1.3 5 0E+02 P-32 1.320E+0 6 8.210E+04 0.000E+00 0.000E+00 0.000E+00 1.4 8 0E+0 5 0.000E+00 5.100E+04 CR-5 1 0.000E+00 0.000E+00 7.420E-01 2.740E-01 1.65 0E+00 3.120E+02 0.000E+00 1.240E+00 MN-5 4 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 6.58 0E+02 4.55 0E+02 0.000E+00 0.000E+00 2.540E+02 2.610E+02 0.000E+00 1.0 6 0E+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 1.7 9 0E+03 0.000E+00 1.98 0E+02 CO-6 0 0.000E+00 2.56 0E+02 0.000E+00 0.000E+00 0.000E+00 4.810E+03 0.000E+00 5.65 0E+02 NI-6 3 3.110E+04 2.1 6 0E+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 5.66 0E-01 0.000E+00 1.020E-02 CU-6 4 0.000E+00 2.68 0E+00 0.000E+00 6.7 6 0E+00 0.000E+00 2.2 9 0E+02 0.000E+00 1.2 6 0E+00 Z N-65 2.310E+04 7.3 5 0E+04 0.000E+00 4.920E+04 0.000E+00 4.630E+04 0.000E+00 3.320E+04 Z N-69 7.730E-07 1.4 8 0E-0 6 0.000E+00 9.610E-07 0.000E+00 2.220E-07 0.000E+00 1.030E-07 BR-8 3 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-8 4 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 9.85 0E-1 8 0.000E+00 1.2 5 0E-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 1.2 9 0E-22 0.000E+00 0.000E+00 0.000E+00 1.7 8 0E-33 0.000E+00 6.830E-23 RB-89 0.000E+00 1.640E-2 6 0.000E+00 0.000E+00 0.000E+00 9.56 0E-40 0.000E+00 1.1 6 0E-2 6 SR-89 2.1 8 0E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.500E+03 0.000E+00 6.2 6 0E+02 SR-9 0 5.440E+0 5 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.570E+04 0.000E+00 1.340E+0 5 SR-9 1 7.0 5 0E+01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.3 6 0E+02 0.000E+00 2.85 0E+00 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X C A i Adult Dose Factors for use in the Li quid Dose Calculations Appendix C Ai Adult Fish - Page 2 of 3 Agegroup:

ADULT Pathway: Fresh Water Fish

- Sport (FFSP) Units: mrem/hr / µµµµCi/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in Total Body SR-9 2 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-9 0 4.440E-01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4.710E+03 0.000E+00 1.1 9 0E-02 Y-9 1 8.340E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4.59 0E+03 0.000E+00 2.230E-01 Y-9 1M 1.070E-11 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.1 5 0E-11 0.000E+00 4.1 5 0E-13 Y-9 2 4.600E-04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 8.0 6 0E+00 0.000E+00 1.340E-0 5 Y-9 3 3.0 8 0E-02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 9.770E+02 0.000E+00 8.500E-04 Z R-95 2.3 8 0E-01 7.620E-02 0.000E+00 1.200E-01 0.000E+00 2.410E+02 0.000E+00 5.1 6 0E-02 Z R-9 7 4.96 0E-03 1.000E-03 0.000E+00 1.510E-03 0.000E+00 3.100E+02 0.000E+00 4.570E-04 NB-95 4.3 8 0E+02 2.440E+02 0.000E+00 2.410E+02 0.000E+00 1.4 8 0E+0 6 0.000E+00 1.310E+02 MO-99 0.000E+00 8.020E+01 0.000E+00 1.820E+02 0.000E+00 1.86 0E+02 0.000E+00 1.530E+01 T C-99 M 5.59 0E-04 1.58 0E-03 0.000E+00 2.400E-02 7.740E-04 9.340E-01 0.000E+00 2.010E-02 T C-101 2.610E-33 3.7 6 0E-33 0.000E+00 6.770E-32 1.920E-33 1.130E-44 0.000E+00 3.69 0E-32 RU-103 4.3 5 0E+00 0.000E+00 0.000E+00 1.66 0E+01 0.000E+00 5.0 8 0E+02 0.000E+00 1.870E+00 RU-10 5 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-10 6 6.570E+01 0.000E+00 0.000E+00 1.270E+02 0.000E+00 4.2 5 0E+03 0.000E+00 8.320E+00 AG-110M 8.7 9 0E-01 8.130E-01 0.000E+00 1.600E+00 0.000E+00 3.320E+02 0.000E+00 4.830E-01 T E-12 5 M 2.540E+03 9.1 9 0E+02 7.630E+02 1.030E+04 0.000E+00 1.010E+04 0.000E+00 3.400E+02 T E-127 1.7 9 0E+01 6.440E+00 1.330E+01 7.300E+01 0.000E+00 1.410E+03 0.000E+00 3.88 0E+00 T E-127M 6.440E+03 2.300E+03 1.65 0E+03 2.620E+04 0.000E+00 2.1 6 0E+04 0.000E+00 7.85 0E+02 T E-12 9 1.630E-0 5 6.120E-0 6 1.2 5 0E-0 5 6.85 0E-0 5 0.000E+00 1.230E-0 5 0.000E+00 3.970E-0 6 T E-12 9 M 1.0 8 0E+04 4.020E+03 3.710E+03 4.500E+04 0.000E+00 5.430E+04 0.000E+00 1.710E+03 T E-131 8.710E-17 3.640E-17 7.1 6 0E-17 3.820E-1 6 0.000E+00 1.230E-17 0.000E+00 2.7 5 0E-17 T E-131M 9.510E+02 4.65 0E+02 7.370E+02 4.710E+03 0.000E+00 4.620E+04 0.000E+00 3.88 0E+02 T E-132 1.95 0E+03 1.2 6 0E+03 1.3 9 0E+03 1.210E+04 0.000E+00 5.96 0E+04 0.000E+00 1.1 8 0E+03 I-130 7.0 5 0E+00 2.0 8 0E+01 1.7 6 0E+03 3.2 5 0E+01 0.000E+00 1.7 9 0E+01 0.000E+00 8.210E+00 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X C A i Adult Dose Factors for use in the Li quid Dose Calculations Appendix C Ai Adult Fish - Page 3 of 3 Agegroup:

ADULT Pathway: Fresh Water Fish

- Sport (FFSP) Units: mrem/hr / µµµµCi/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in Total Body I-131 1.370E+02 1.96 0E+02 6.420E+04 3.3 6 0E+02 0.000E+00 5.170E+01 0.000E+00 1.120E+02 I-132 5.270E-03 1.410E-02 4.940E-01 2.2 5 0E-02 0.000E+00 2.65 0E-03 0.000E+00 4.940E-03 I-133 2.2 9 0E+01 3.99 0E+01 5.86 0E+03 6.95 0E+01 0.000E+00 3.58 0E+01 0.000E+00 1.210E+01 I-134 2.120E-0 8 5.7 5 0E-0 8 9.96 0E-07 9.140E-0 8 0.000E+00 5.010E-11 0.000E+00 2.0 6 0E-0 8 I-13 5 1.2 9 0E+00 3.370E+00 2.220E+02 5.410E+00 0.000E+00 3.810E+00 0.000E+00 1.240E+00 CS-134 2.98 0E+0 5 7.0 8 0E+0 5 0.000E+00 2.2 9 0E+0 5 7.610E+04 1.240E+04 0.000E+00 5.7 9 0E+0 5 CS-13 6 2.96 0E+04 1.170E+0 5 0.000E+00 6.500E+04 8.900E+03 1.330E+04 0.000E+00 8.400E+04 CS-137 3.820E+0 5 5.220E+0 5 0.000E+00 1.770E+0 5 5.89 0E+04 1.010E+04 0.000E+00 3.420E+0 5 CS-13 8 8.940E-12 1.770E-11 0.000E+00 1.300E-11 1.2 8 0E-12 7.530E-17 0.000E+00 8.7 5 0E-12 BA-13 9 5.65 0E-0 6 4.030E-0 9 0.000E+00 3.7 6 0E-0 9 2.2 8 0E-0 9 1.000E-0 5 0.000E+00 1.66 0E-07 BA-140 1.840E+02 2.310E-01 0.000E+00 7.86 0E-02 1.320E-01 3.7 9 0E+02 0.000E+00 1.210E+01 BA-141 8.700E-2 5 6.58 0E-2 8 0.000E+00 6.120E-2 8 3.730E-2 8 4.100E-34 0.000E+00 2.940E-2 6 BA-142 2.570E-42 2.640E-4 5 0.000E+00 2.230E-4 5 1.4 9 0E-4 5 3.620E-6 0 0.000E+00 1.610E-43 LA-140 9.900E-02 4.99 0E-02 0.000E+00 0.000E+00 0.000E+00 3.66 0E+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-0 8 CE-141 2.1 9 0E-02 1.4 8 0E-02 0.000E+00 6.89 0E-03 0.000E+00 5.670E+01 0.000E+00 1.68 0E-03 CE-143 2.3 8 0E-03 1.7 6 0E+00 0.000E+00 7.7 6 0E-04 0.000E+00 6.59 0E+01 0.000E+00 1.95 0E-04 CE-144 1.170E+00 4.870E-01 0.000E+00 2.89 0E-01 0.000E+00 3.940E+02 0.000E+00 6.2 6 0E-02 PR-143 5.230E-01 2.100E-01 0.000E+00 1.210E-01 0.000E+00 2.2 9 0E+03 0.000E+00 2.59 0E-02 PR-144 1.55 0E-2 8 6.440E-2 9 0.000E+00 3.630E-2 9 0.000E+00 2.230E-3 5 0.000E+00 7.88 0E-30 N D-147 3.530E-01 4.0 8 0E-01 0.000E+00 2.3 9 0E-01 0.000E+00 1.96 0E+03 0.000E+00 2.440E-02 W-1 8 7 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-23 9 2.120E-02 2.0 9 0E-03 0.000E+00 6.510E-03 0.000E+00 4.2 8 0E+02 0.000E+00 1.1 5 0E-03 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X C A i Adult Dose Factors for use in the Li quid Dose Calculations Appendix C Ai Adult Shoreline Sediment - Page 1 of 3 Agegroup:

ADULT Pathway: Shoreline Sediment (SHDp) Units: mrem/hr / µµµµCi/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in 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 4.96 0E-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-5 1 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-5 4 4.96 0E+01 4.96 0E+01 4.96 0E+01 4.96 0E+01 4.96 0E+01 4.96 0E+01 5.820E+01 4.96 0E+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 1.1 5 0E+01 9.770E+00 CO-58 1.3 6 0E+01 1.3 6 0E+01 1.3 6 0E+01 1.3 6 0E+01 1.3 6 0E+01 1.3 6 0E+01 1.59 0E+01 1.3 6 0E+01 CO-6 0 7.69 0E+02 7.69 0E+02 7.69 0E+02 7.69 0E+02 7.69 0E+02 7.69 0E+02 9.0 5 0E+02 7.69 0E+02 NI-6 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 NI-65 1.0 6 0E-02 1.0 6 0E-02 1.0 6 0E-02 1.0 6 0E-02 1.0 6 0E-02 1.0 6 0E-02 1.240E-02 1.0 6 0E-02 CU-6 4 2.170E-02 2.170E-02 2.170E-02 2.170E-02 2.170E-02 2.170E-02 2.4 6 0E-02 2.170E-02 Z N-65 2.670E+01 2.670E+01 2.670E+01 2.670E+01 2.670E+01 2.670E+01 3.0 8 0E+01 2.670E+01 Z N-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-8 3 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-8 4 7.2 5 0E-03 7.2 5 0E-03 7.2 5 0E-03 7.2 5 0E-03 7.2 5 0E-03 7.2 5 0E-03 8.4 6 0E-03 7.2 5 0E-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 3.68 0E-01 3.220E-01 RB-88 1.1 8 0E-03 1.1 8 0E-03 1.1 8 0E-03 1.1 8 0E-03 1.1 8 0E-03 1.1 8 0E-03 1.3 5 0E-03 1.1 8 0E-03 RB-89 4.400E-03 4.400E-03 4.400E-03 4.400E-03 4.400E-03 4.400E-03 5.2 8 0E-03 4.400E-03 SR-89 7.740E-04 7.740E-04 7.740E-04 7.740E-04 7.740E-04 7.740E-04 8.99 0E-04 7.740E-04 SR-9 0 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-9 1 7.69 0E-02 7.69 0E-02 7.69 0E-02 7.69 0E-02 7.69 0E-02 7.69 0E-02 8.99 0E-02 7.69 0E-02 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X C A i Adult Dose Factors for use in the Li quid Dose Calculations Appendix C Ai Adult Shoreline Sediment - Page 2 of 3 Agegroup:

ADULT Pathway: Shoreline Sediment (SHDp) Units: mrem/hr / µµµµCi/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in Total Body SR-9 2 2.7 8 0E-02 2.7 8 0E-02 2.7 8 0E-02 2.7 8 0E-02 2.7 8 0E-02 2.7 8 0E-02 3.0 9 0E-02 2.7 8 0E-02 Y-9 0 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-9 1 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-9 1M 3.59 0E-03 3.59 0E-03 3.59 0E-03 3.59 0E-03 3.59 0E-03 3.59 0E-03 4.1 5 0E-03 3.59 0E-03 Y-9 2 6.4 6 0E-03 6.4 6 0E-03 6.4 6 0E-03 6.4 6 0E-03 6.4 6 0E-03 6.4 6 0E-03 7.670E-03 6.4 6 0E-03 Y-9 3 6.56 0E-03 6.56 0E-03 6.56 0E-03 6.56 0E-03 6.56 0E-03 6.56 0E-03 8.98 0E-03 6.56 0E-03 Z R-95 8.7 6 0E+00 8.7 6 0E+00 8.7 6 0E+00 8.7 6 0E+00 8.7 6 0E+00 8.7 6 0E+00 1.020E+01 8.7 6 0E+00 Z R-9 7 1.0 6 0E-01 1.0 6 0E-01 1.0 6 0E-01 1.0 6 0E-01 1.0 6 0E-01 1.0 6 0E-01 1.230E-01 1.0 6 0E-01 NB-95 4.89 0E+00 4.89 0E+00 4.89 0E+00 4.89 0E+00 4.89 0E+00 4.89 0E+00 5.7 5 0E+00 4.89 0E+00 MO-99 1.430E-01 1.430E-01 1.430E-01 1.430E-01 1.430E-01 1.430E-01 1.66 0E-01 1.430E-01 T C-99 M 6.59 0E-03 6.59 0E-03 6.59 0E-03 6.59 0E-03 6.59 0E-03 6.59 0E-03 7.55 0E-03 6.59 0E-03 T C-101 7.2 8 0E-04 7.2 8 0E-04 7.2 8 0E-04 7.2 8 0E-04 7.2 8 0E-04 7.2 8 0E-04 8.0 9 0E-04 7.2 8 0E-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-10 5 2.2 8 0E-02 2.2 8 0E-02 2.2 8 0E-02 2.2 8 0E-02 2.2 8 0E-02 2.2 8 0E-02 2.58 0E-02 2.2 8 0E-02 RU-10 6 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 T E-12 5 M 5.55 0E-02 5.55 0E-02 5.55 0E-02 5.55 0E-02 5.55 0E-02 5.55 0E-02 7.620E-02 5.55 0E-02 T E-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 T E-127M 3.2 8 0E-03 3.2 8 0E-03 3.2 8 0E-03 3.2 8 0E-03 3.2 8 0E-03 3.2 8 0E-03 3.88 0E-03 3.2 8 0E-03 T E-12 9 9.3 9 0E-04 9.3 9 0E-04 9.3 9 0E-04 9.3 9 0E-04 9.3 9 0E-04 9.3 9 0E-04 1.110E-03 9.3 9 0E-04 T E-12 9 M 7.0 8 0E-01 7.0 8 0E-01 7.0 8 0E-01 7.0 8 0E-01 7.0 8 0E-01 7.0 8 0E-01 8.270E-01 7.0 8 0E-01 T E-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 T E-131M 2.870E-01 2.870E-01 2.870E-01 2.870E-01 2.870E-01 2.870E-01 3.3 9 0E-01 2.870E-01 T E-132 1.520E-01 1.520E-01 1.520E-01 1.520E-01 1.520E-01 1.520E-01 1.7 8 0E-01 1.520E-01 I-130 1.970E-01 1.970E-01 1.970E-01 1.970E-01 1.970E-01 1.970E-01 2.3 9 0E-01 1.970E-01 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X C A i Adult Dose Factors for use in the Li quid Dose Calculations Appendix C Ai Adult Shoreline Sediment - Page 3 of 3 Agegroup:

ADULT Pathway: Shoreline Sediment (SHDp) Units: mrem/hr / µµµµCi/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in Total Body I-131 6.1 6 0E-01 6.1 6 0E-01 6.1 6 0E-01 6.1 6 0E-01 6.1 6 0E-01 6.1 6 0E-01 7.4 8 0E-01 6.1 6 0E-01 I-132 4.4 6 0E-02 4.4 6 0E-02 4.4 6 0E-02 4.4 6 0E-02 4.4 6 0E-02 4.4 6 0E-02 5.240E-02 4.4 6 0E-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-13 5 9.040E-02 9.040E-02 9.040E-02 9.040E-02 9.040E-02 9.040E-02 1.0 5 0E-01 9.040E-02 CS-134 2.4 5 0E+02 2.4 5 0E+02 2.4 5 0E+02 2.4 5 0E+02 2.4 5 0E+02 2.4 5 0E+02 2.86 0E+02 2.4 5 0E+02 CS-13 6 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 3.68 0E+02 3.68 0E+02 3.68 0E+02 3.68 0E+02 3.68 0E+02 3.68 0E+02 4.2 9 0E+02 3.68 0E+02 CS-13 8 1.2 8 0E-02 1.2 8 0E-02 1.2 8 0E-02 1.2 8 0E-02 1.2 8 0E-02 1.2 8 0E-02 1.470E-02 1.2 8 0E-02 BA-13 9 3.7 9 0E-03 3.7 9 0E-03 3.7 9 0E-03 3.7 9 0E-03 3.7 9 0E-03 3.7 9 0E-03 4.2 6 0E-03 3.7 9 0E-03 BA-140 7.3 5 0E-01 7.3 5 0E-01 7.3 5 0E-01 7.3 5 0E-01 7.3 5 0E-01 7.3 5 0E-01 8.400E-01 7.3 5 0E-01 BA-141 1.4 9 0E-03 1.4 9 0E-03 1.4 9 0E-03 1.4 9 0E-03 1.4 9 0E-03 1.4 9 0E-03 1.700E-03 1.4 9 0E-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 6.88 0E-01 6.88 0E-01 6.88 0E-01 6.88 0E-01 6.88 0E-01 6.88 0E-01 7.7 9 0E-01 6.88 0E-01 LA-142 2.720E-02 2.720E-02 2.720E-02 2.720E-02 2.720E-02 2.720E-02 3.2 6 0E-02 2.720E-02 CE-141 4.89 0E-01 4.89 0E-01 4.89 0E-01 4.89 0E-01 4.89 0E-01 4.89 0E-01 5.510E-01 4.89 0E-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 2.4 9 0E+00 2.4 9 0E+00 2.4 9 0E+00 2.4 9 0E+00 2.4 9 0E+00 2.4 9 0E+00 2.88 0E+00 2.4 9 0E+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-0 5 6.570E-0 5 6.570E-0 5 6.570E-0 5 6.570E-0 5 6.570E-0 5 7.55 0E-0 5 6.570E-0 5 N D-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-1 8 7 8.420E-02 8.420E-02 8.420E-02 8.420E-02 8.420E-02 8.420E-02 9.7 8 0E-02 8.420E-02 NP-23 9 6.120E-02 6.120E-02 6.120E-02 6.120E-02 6.120E-02 6.120E-02 7.0 9 0E-02 6.120E-02 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X D A i Teen Factors for use in the Li quid Dose Calculations Appendix D Ai Teen Water - Page 1 of 3 Agegroup:

TEEN Pathway: Pota ble Water (P Wtr) Units: mrem/hr / µµµµCi/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in Total Body H-3 0.000E+00 6.1 6 0E+00 6.1 6 0E+00 6.1 6 0E+00 6.1 6 0E+00 6.1 6 0E+00 0.000E+00 6.1 6 0E+00 C-14 2.3 6 0E+02 4.720E+01 4.720E+01 4.720E+01 4.720E+01 4.720E+01 0.000E+00 4.720E+01 NA-24 7.69 0E+01 7.69 0E+01 7.69 0E+01 7.69 0E+01 7.69 0E+01 7.69 0E+01 0.000E+00 7.69 0E+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-5 1 0.000E+00 0.000E+00 1.1 5 0E-01 4.530E-02 2.95 0E-01 3.470E+01 0.000E+00 2.070E-01 MN-5 4 0.000E+00 3.430E+02 0.000E+00 1.020E+02 0.000E+00 7.030E+02 0.000E+00 6.7 9 0E+01 MN-56 0.000E+00 3.640E-01 0.000E+00 4.610E-01 0.000E+00 2.400E+01 0.000E+00 6.4 8 0E-02 FE-55 2.200E+02 1.56 0E+02 0.000E+00 0.000E+00 9.88 0E+01 6.740E+01 0.000E+00 3.630E+01 FE-59 3.3 9 0E+02 7.900E+02 0.000E+00 0.000E+00 2.4 9 0E+02 1.870E+03 0.000E+00 3.0 5 0E+02 CO-58 0.000E+00 5.620E+01 0.000E+00 0.000E+00 0.000E+00 7.7 5 0E+02 0.000E+00 1.300E+02 CO-6 0 0.000E+00 1.630E+02 0.000E+00 0.000E+00 0.000E+00 2.130E+03 0.000E+00 3.68 0E+02 NI-6 3 1.030E+04 7.270E+02 0.000E+00 0.000E+00 0.000E+00 1.1 6 0E+02 0.000E+00 3.4 9 0E+02 NI-65 1.610E+00 2.0 5 0E-01 0.000E+00 0.000E+00 0.000E+00 1.110E+01 0.000E+00 9.3 5 0E-02 CU-6 4 0.000E+00 3.470E+00 0.000E+00 8.770E+00 0.000E+00 2.69 0E+02 0.000E+00 1.630E+00 Z N-65 3.340E+02 1.1 6 0E+03 0.000E+00 7.430E+02 0.000E+00 4.920E+02 0.000E+00 5.420E+02 Z N-69 1.070E-04 2.040E-04 0.000E+00 1.330E-04 0.000E+00 3.7 6 0E-04 0.000E+00 1.430E-0 5 BR-8 3 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-8 4 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 4.3 6 0E-77 RB-86 0.000E+00 1.700E+03 0.000E+00 0.000E+00 0.000E+00 2.520E+02 0.000E+00 7.99 0E+02 RB-88 0.000E+00 3.300E-12 0.000E+00 0.000E+00 0.000E+00 2.830E-1 9 0.000E+00 1.7 6 0E-12 RB-89 0.000E+00 2.96 0E-14 0.000E+00 0.000E+00 0.000E+00 4.540E-23 0.000E+00 2.0 9 0E-14 SR-89 2.540E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.030E+03 0.000E+00 7.2 8 0E+02 SR-9 0 4.830E+0 5 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.3 5 0E+04 0.000E+00 1.1 9 0E+0 5 SR-9 1 1.95 0E+02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 8.85 0E+02 0.000E+00 7.7 6 0E+00 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X D A i Teen Factors for use in the Li quid Dose Calculations Appendix D Ai Teen Water - Page 2 of 3 Agegroup:

TEEN Pathway: Pota ble Water (P Wtr) Units: mrem/hr / µµµµCi/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in Total Body SR-9 2 8.220E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.0 9 0E+02 0.000E+00 3.500E-01 Y-9 0 7.000E-01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.770E+03 0.000E+00 1.88 0E-02 Y-9 1 1.1 6 0E+01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4.7 6 0E+03 0.000E+00 3.120E-01 Y-9 1M 3.330E-07 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.570E-0 5 0.000E+00 1.270E-0 8 Y-9 2 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-9 3 9.7 6 0E-02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.98 0E+03 0.000E+00 2.670E-03 Z R-95 2.3 8 0E+00 7.520E-01 0.000E+00 1.100E+00 0.000E+00 1.730E+03 0.000E+00 5.170E-01 Z R-9 7 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 3.0 9 0E+02 0.000E+00 7.070E+02 0.000E+00 5.530E+02 0.000E+00 5.89 0E+01 T C-99 M 4.840E-03 1.3 5 0E-02 0.000E+00 2.010E-01 7.500E-03 8.870E+00 0.000E+00 1.7 5 0E-01 T C-101 1.120E-17 1.59 0E-17 0.000E+00 2.88 0E-1 6 9.700E-1 8 2.720E-24 0.000E+00 1.56 0E-1 6 RU-103 1.470E+01 0.000E+00 0.000E+00 5.1 8 0E+01 0.000E+00 1.230E+03 0.000E+00 6.2 8 0E+00 RU-10 5 1.940E-01 0.000E+00 0.000E+00 2.4 5 0E+00 0.000E+00 1.570E+02 0.000E+00 7.540E-02 RU-10 6 2.2 8 0E+02 0.000E+00 0.000E+00 4.3 9 0E+02 0.000E+00 1.0 9 0E+04 0.000E+00 2.870E+01 AG-110M 1.1 9 0E+01 1.130E+01 0.000E+00 2.1 5 0E+01 0.000E+00 3.1 6 0E+03 0.000E+00 6.85 0E+00 T E-12 5 M 2.210E+02 7.98 0E+01 6.1 8 0E+01 0.000E+00 0.000E+00 6.530E+02 0.000E+00 2.96 0E+01 T E-127 3.7 9 0E+00 1.340E+00 2.610E+00 1.530E+01 0.000E+00 2.930E+02 0.000E+00 8.1 5 0E-01 T E-127M 5.600E+02 1.99 0E+02 1.330E+02 2.270E+03 0.000E+00 1.400E+03 0.000E+00 6.66 0E+01 T E-12 9 1.920E-03 7.1 5 0E-04 1.370E-03 8.040E-03 0.000E+00 1.0 5 0E-02 0.000E+00 4.66 0E-04 T E-12 9 M 9.3 8 0E+02 3.4 8 0E+02 3.030E+02 3.920E+03 0.000E+00 3.520E+03 0.000E+00 1.4 8 0E+02 T E-131 3.4 9 0E-0 9 1.440E-0 9 2.69 0E-0 9 1.520E-0 8 0.000E+00 2.86 0E-10 0.000E+00 1.0 9 0E-0 9 T E-131M 1.0 8 0E+02 5.1 5 0E+01 7.7 5 0E+01 5.3 8 0E+02 0.000E+00 4.140E+03 0.000E+00 4.300E+01 T E-132 1.820E+02 1.1 5 0E+02 1.220E+02 1.110E+03 0.000E+00 3.66 0E+03 0.000E+00 1.0 9 0E+02 I-130 3.0 5 0E+01 8.830E+01 7.200E+03 1.3 6 0E+02 0.000E+00 6.7 9 0E+01 0.000E+00 3.530E+01 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X D A i Teen Factors for use in the Li quid Dose Calculations Appendix D Ai Teen Water - Page 3 of 3 Agegroup:

TEEN Pathway: Pota ble Water (P Wtr) Units: mrem/hr / µµµµCi/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in Total Body I-131 3.2 6 0E+02 4.56 0E+02 1.330E+0 5 7.85 0E+02 0.000E+00 9.020E+01 0.000E+00 2.4 5 0E+02 I-132 4.3 6 0E-01 1.140E+00 3.85 0E+01 1.800E+00 0.000E+00 4.970E-01 0.000E+00 4.100E-01 I-133 7.830E+01 1.330E+02 1.86 0E+04 2.330E+02 0.000E+00 1.010E+02 0.000E+00 4.0 5 0E+01 I-134 6.330E-04 1.68 0E-03 2.800E-02 2.640E-03 0.000E+00 2.210E-0 5 0.000E+00 6.020E-04 I-13 5 1.010E+01 2.600E+01 1.670E+03 4.100E+01 0.000E+00 2.88 0E+01 0.000E+00 9.630E+00 CS-134 4.86 0E+03 1.140E+04 0.000E+00 3.640E+03 1.3 9 0E+03 1.420E+02 0.000E+00 5.310E+03 CS-13 6 4.86 0E+02 1.910E+03 0.000E+00 1.040E+03 1.640E+02 1.540E+02 0.000E+00 1.2 9 0E+03 CS-137 6.510E+03 8.66 0E+03 0.000E+00 2.95 0E+03 1.1 5 0E+03 1.230E+02 0.000E+00 3.020E+03 CS-13 8 8.300E-07 1.59 0E-0 6 0.000E+00 1.1 8 0E-0 6 1.370E-07 7.230E-10 0.000E+00 7.970E-07 BA-13 9 1.99 0E-02 1.400E-0 5 0.000E+00 1.320E-0 5 9.670E-0 6 1.7 8 0E-01 0.000E+00 5.810E-04 BA-140 1.610E+03 1.970E+00 0.000E+00 6.68 0E-01 1.320E+00 2.4 8 0E+03 0.000E+00 1.040E+02 BA-141 5.420E-12 4.0 5 0E-1 5 0.000E+00 3.7 6 0E-1 5 2.770E-1 5 1.1 5 0E-17 0.000E+00 1.810E-13 BA-142 6.170E-21 6.170E-24 0.000E+00 5.220E-24 4.100E-24 1.89 0E-32 0.000E+00 3.800E-22 LA-140 1.65 0E-01 8.0 9 0E-02 0.000E+00 0.000E+00 0.000E+00 4.640E+03 0.000E+00 2.1 5 0E-02 LA-142 5.59 0E-0 5 2.4 8 0E-0 5 0.000E+00 0.000E+00 0.000E+00 7.55 0E-01 0.000E+00 6.1 8 0E-0 6 CE-141 7.65 0E-01 5.110E-01 0.000E+00 2.400E-01 0.000E+00 1.4 6 0E+03 0.000E+00 5.870E-02 CE-143 1.0 6 0E-01 7.730E+01 0.000E+00 3.4 6 0E-02 0.000E+00 2.320E+03 0.000E+00 8.630E-03 CE-144 4.040E+01 1.670E+01 0.000E+00 9.99 0E+00 0.000E+00 1.020E+04 0.000E+00 2.170E+00 PR-143 7.420E-01 2.96 0E-01 0.000E+00 1.720E-01 0.000E+00 2.440E+03 0.000E+00 3.700E-02 PR-144 7.330E-1 6 3.000E-1 6 0.000E+00 1.720E-1 6 0.000E+00 8.0 8 0E-1 9 0.000E+00 3.720E-17 N D-147 5.2 8 0E-01 5.7 5 0E-01 0.000E+00 3.370E-01 0.000E+00 2.070E+03 0.000E+00 3.440E-02 W-1 8 7 5.99 0E+00 4.88 0E+00 0.000E+00 0.000E+00 0.000E+00 1.320E+03 0.000E+00 1.710E+00 NP-23 9 8.830E-02 8.330E-03 0.000E+00 2.610E-02 0.000E+00 1.340E+03 0.000E+00 4.630E-03 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X D A i Teen Dose Factors for use in the Li quid Dose Calculations Appendix D Ai Teen Fish - Page 1 of 3 Agegroup:

TEEN Pathway: Fresh Water Fish

- Sport (FFSP) Units: mrem/hr / µµµµCi/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in 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 1.3 9 0E+02 1.3 9 0E+02 1.3 9 0E+02 1.3 9 0E+02 1.3 9 0E+02 1.3 9 0E+02 0.000E+00 1.3 9 0E+02 P-32 1.440E+0 6 8.910E+04 0.000E+00 0.000E+00 0.000E+00 1.210E+0 5 0.000E+00 5.58 0E+04 CR-5 1 0.000E+00 0.000E+00 7.120E-01 2.810E-01 1.830E+00 2.1 5 0E+02 0.000E+00 1.2 8 0E+00 MN-5 4 0.000E+00 4.300E+03 0.000E+00 1.2 8 0E+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 1.1 9 0E+01 0.000E+00 3.230E-02 FE-55 6.89 0E+02 4.88 0E+02 0.000E+00 0.000E+00 3.100E+02 2.110E+02 0.000E+00 1.140E+02 FE-59 1.0 5 0E+03 2.4 6 0E+03 0.000E+00 0.000E+00 7.7 6 0E+02 5.820E+03 0.000E+00 9.500E+02 CO-58 0.000E+00 8.7 8 0E+01 0.000E+00 0.000E+00 0.000E+00 1.210E+03 0.000E+00 2.020E+02 CO-6 0 0.000E+00 2.56 0E+02 0.000E+00 0.000E+00 0.000E+00 3.340E+03 0.000E+00 5.770E+02 NI-6 3 3.230E+04 2.2 8 0E+03 0.000E+00 0.000E+00 0.000E+00 3.630E+02 0.000E+00 1.0 9 0E+03 NI-65 1.86 0E-01 2.370E-02 0.000E+00 0.000E+00 0.000E+00 1.2 9 0E+00 0.000E+00 1.0 8 0E-02 CU-6 4 0.000E+00 2.820E+00 0.000E+00 7.140E+00 0.000E+00 2.1 9 0E+02 0.000E+00 1.330E+00 Z N-65 2.100E+04 7.2 8 0E+04 0.000E+00 4.66 0E+04 0.000E+00 3.0 8 0E+04 0.000E+00 3.3 9 0E+04 Z N-69 8.410E-07 1.600E-0 6 0.000E+00 1.0 5 0E-0 6 0.000E+00 2.95 0E-0 6 0.000E+00 1.120E-07 BR-8 3 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4.1 6 0E-02 BR-8 4 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 1.0 5 0E+0 5 0.000E+00 0.000E+00 0.000E+00 1.55 0E+04 0.000E+00 4.920E+04 RB-88 0.000E+00 1.3 8 0E-22 0.000E+00 0.000E+00 0.000E+00 1.1 8 0E-2 9 0.000E+00 7.3 6 0E-23 RB-89 0.000E+00 1.720E-2 6 0.000E+00 0.000E+00 0.000E+00 2.630E-3 5 0.000E+00 1.220E-2 6 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-9 0 4.540E+0 5 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.270E+04 0.000E+00 1.120E+0 5 SR-9 1 7.640E+01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.470E+02 0.000E+00 3.040E+00 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X D A i Teen Dose Factors for use in the Li quid Dose Calculations Appendix D Ai Teen Fish - Page 2 of 3 Agegroup:

TEEN Pathway: Fresh Water Fish

- Sport (FFSP) Units: mrem/hr / µµµµCi/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in Total Body SR-9 2 3.59 0E-01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 9.130E+00 0.000E+00 1.530E-02 Y-9 0 4.820E-01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.98 0E+03 0.000E+00 1.300E-02 Y-9 1 9.0 6 0E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.710E+03 0.000E+00 2.430E-01 Y-9 1M 1.1 6 0E-11 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.470E-10 0.000E+00 4.430E-13 Y-9 2 5.020E-04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.3 8 0E+01 0.000E+00 1.4 5 0E-0 5 Y-9 3 3.3 5 0E-02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.020E+03 0.000E+00 9.1 9 0E-04 Z R-95 2.4 5 0E-01 7.740E-02 0.000E+00 1.140E-01 0.000E+00 1.7 9 0E+02 0.000E+00 5.320E-02 Z R-9 7 5.330E-03 1.0 5 0E-03 0.000E+00 1.600E-03 0.000E+00 2.85 0E+02 0.000E+00 4.86 0E-04 NB-95 4.410E+02 2.4 5 0E+02 0.000E+00 2.370E+02 0.000E+00 1.0 5 0E+0 6 0.000E+00 1.3 5 0E+02 MO-99 0.000E+00 8.55 0E+01 0.000E+00 1.96 0E+02 0.000E+00 1.530E+02 0.000E+00 1.630E+01 T C-99 M 5.720E-04 1.600E-03 0.000E+00 2.3 8 0E-02 8.86 0E-04 1.0 5 0E+00 0.000E+00 2.070E-02 T C-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 1.95 0E+00 RU-10 5 9.3 5 0E-03 0.000E+00 0.000E+00 1.1 8 0E-01 0.000E+00 7.55 0E+00 0.000E+00 3.630E-03 RU-10 6 7.140E+01 0.000E+00 0.000E+00 1.3 8 0E+02 0.000E+00 3.420E+03 0.000E+00 8.99 0E+00 AG-110M 8.58 0E-01 8.120E-01 0.000E+00 1.55 0E+00 0.000E+00 2.2 8 0E+02 0.000E+00 4.940E-01 T E-12 5 M 2.7 6 0E+03 9.95 0E+02 7.710E+02 0.000E+00 0.000E+00 8.1 5 0E+03 0.000E+00 3.69 0E+02 T E-127 1.96 0E+01 6.95 0E+00 1.3 5 0E+01 7.940E+01 0.000E+00 1.510E+03 0.000E+00 4.220E+00 T E-127M 7.010E+03 2.4 9 0E+03 1.670E+03 2.840E+04 0.000E+00 1.7 5 0E+04 0.000E+00 8.340E+02 T E-12 9 1.770E-0 5 6.600E-0 6 1.2 6 0E-0 5 7.430E-0 5 0.000E+00 9.68 0E-0 5 0.000E+00 4.310E-0 6 T E-12 9 M 1.1 6 0E+04 4.320E+03 3.7 6 0E+03 4.870E+04 0.000E+00 4.370E+04 0.000E+00 1.840E+03 T E-131 9.400E-17 3.870E-17 7.240E-17 4.110E-1 6 0.000E+00 7.710E-1 8 0.000E+00 2.940E-17 T E-131M 1.020E+03 4.900E+02 7.370E+02 5.110E+03 0.000E+00 3.930E+04 0.000E+00 4.0 9 0E+02 T E-132 2.0 6 0E+03 1.300E+03 1.370E+03 1.2 5 0E+04 0.000E+00 4.130E+04 0.000E+00 1.230E+03 I-130 7.320E+00 2.120E+01 1.730E+03 3.2 6 0E+01 0.000E+00 1.630E+01 0.000E+00 8.4 6 0E+00 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X D A i Teen Dose Factors for use in the Li quid Dose Calculations Appendix D Ai Teen Fish - Page 3 of 3 Agegroup:

TEEN Pathway: Fresh Water Fish

- Sport (FFSP) Units: mrem/hr / µµµµCi/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in Total Body I-131 1.470E+02 2.0 6 0E+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 2.2 8 0E-02 0.000E+00 6.2 9 0E-03 0.000E+00 5.1 8 0E-03 I-133 2.470E+01 4.1 9 0E+01 5.85 0E+03 7.3 5 0E+01 0.000E+00 3.170E+01 0.000E+00 1.2 8 0E+01 I-134 2.220E-0 8 5.89 0E-0 8 9.810E-07 9.2 8 0E-0 8 0.000E+00 7.7 6 0E-10 0.000E+00 2.110E-0 8 I-13 5 1.3 5 0E+00 3.4 8 0E+00 2.240E+02 5.4 9 0E+00 0.000E+00 3.85 0E+00 0.000E+00 1.2 9 0E+00 CS-134 3.0 5 0E+0 5 7.1 8 0E+0 5 0.000E+00 2.2 8 0E+0 5 8.710E+04 8.930E+03 0.000E+00 3.330E+0 5 CS-13 6 2.970E+04 1.170E+0 5 0.000E+00 6.370E+04 1.000E+04 9.410E+03 0.000E+00 7.86 0E+04 CS-137 4.0 9 0E+0 5 5.440E+0 5 0.000E+00 1.85 0E+0 5 7.1 9 0E+04 7.730E+03 0.000E+00 1.89 0E+0 5 CS-13 8 9.58 0E-12 1.840E-11 0.000E+00 1.3 6 0E-11 1.58 0E-12 8.340E-1 5 0.000E+00 9.1 9 0E-12 BA-13 9 6.170E-0 6 4.340E-0 9 0.000E+00 4.0 9 0E-0 9 2.99 0E-0 9 5.510E-0 5 0.000E+00 1.800E-07 BA-140 1.96 0E+02 2.410E-01 0.000E+00 8.1 6 0E-02 1.620E-01 3.030E+02 0.000E+00 1.2 6 0E+01 BA-141 9.4 5 0E-2 5 7.0 5 0E-2 8 0.000E+00 6.55 0E-2 8 4.830E-2 8 2.010E-30 0.000E+00 3.1 5 0E-2 6 BA-142 2.7 5 0E-42 2.7 5 0E-4 5 0.000E+00 2.320E-4 5 1.830E-4 5 8.430E-5 4 0.000E+00 1.69 0E-43 LA-140 1.0 5 0E-01 5.1 6 0E-02 0.000E+00 0.000E+00 0.000E+00 2.96 0E+03 0.000E+00 1.370E-02 LA-142 2.3 5 0E-07 1.040E-07 0.000E+00 0.000E+00 0.000E+00 3.1 8 0E-03 0.000E+00 2.600E-0 8 CE-141 2.370E-02 1.59 0E-02 0.000E+00 7.4 6 0E-03 0.000E+00 4.540E+01 0.000E+00 1.820E-03 CE-143 2.59 0E-03 1.88 0E+00 0.000E+00 8.4 5 0E-04 0.000E+00 5.66 0E+01 0.000E+00 2.100E-04 CE-144 1.270E+00 5.240E-01 0.000E+00 3.130E-01 0.000E+00 3.1 8 0E+02 0.000E+00 6.810E-02 PR-143 5.68 0E-01 2.270E-01 0.000E+00 1.320E-01 0.000E+00 1.870E+03 0.000E+00 2.830E-02 PR-144 1.69 0E-2 8 6.900E-2 9 0.000E+00 3.96 0E-2 9 0.000E+00 1.86 0E-31 0.000E+00 8.55 0E-30 N D-147 4.020E-01 4.370E-01 0.000E+00 2.56 0E-01 0.000E+00 1.58 0E+03 0.000E+00 2.620E-02 W-1 8 7 1.59 0E+02 1.300E+02 0.000E+00 0.000E+00 0.000E+00 3.510E+04 0.000E+00 4.540E+01 NP-23 9 2.3 9 0E-02 2.2 6 0E-03 0.000E+00 7.0 8 0E-03 0.000E+00 3.630E+02 0.000E+00 1.2 5 0E-03 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X D A i Teen Dose Factors for use in the Li quid Dose Calculations Appendix D Ai Teen Shoreline Sediment - Page 1 of 3 Agegroup:

TEEN Pathway: Shoreline Sediment (SHDp) Units: mrem/hr / µµµµCi/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in 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 2.3 9 0E+00 2.3 9 0E+00 2.3 9 0E+00 2.3 9 0E+00 2.3 9 0E+00 2.3 9 0E+00 2.770E+00 2.3 9 0E+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-5 1 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-5 4 2.770E+02 2.770E+02 2.770E+02 2.770E+02 2.770E+02 2.770E+02 3.2 5 0E+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 5.4 5 0E+01 5.4 5 0E+01 5.4 5 0E+01 5.4 5 0E+01 5.4 5 0E+01 5.4 5 0E+01 6.410E+01 5.4 5 0E+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-6 0 4.300E+03 4.300E+03 4.300E+03 4.300E+03 4.300E+03 4.300E+03 5.0 5 0E+03 4.300E+03 NI-6 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 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-6 4 1.210E-01 1.210E-01 1.210E-01 1.210E-01 1.210E-01 1.210E-01 1.370E-01 1.210E-01 Z N-65 1.4 9 0E+02 1.4 9 0E+02 1.4 9 0E+02 1.4 9 0E+02 1.4 9 0E+02 1.4 9 0E+02 1.720E+02 1.4 9 0E+02 Z N-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-8 3 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-8 4 4.0 5 0E-02 4.0 5 0E-02 4.0 5 0E-02 4.0 5 0E-02 4.0 5 0E-02 4.0 5 0E-02 4.720E-02 4.0 5 0E-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 2.0 5 0E+00 1.800E+00 RB-88 6.610E-03 6.610E-03 6.610E-03 6.610E-03 6.610E-03 6.610E-03 7.55 0E-03 6.610E-03 RB-89 2.4 6 0E-02 2.4 6 0E-02 2.4 6 0E-02 2.4 6 0E-02 2.4 6 0E-02 2.4 6 0E-02 2.95 0E-02 2.4 6 0E-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-9 0 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-9 1 4.2 9 0E-01 4.2 9 0E-01 4.2 9 0E-01 4.2 9 0E-01 4.2 9 0E-01 4.2 9 0E-01 5.020E-01 4.2 9 0E-01 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X D A i Teen Dose Factors for use in the Li quid Dose Calculations Appendix D Ai Teen Shoreline Sediment - Page 2 of 3 Agegroup:

TEEN Pathway: Shoreline Sediment (SHDp) Units: mrem/hr / µµµµCi/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in Total Body SR-9 2 1.55 0E-01 1.55 0E-01 1.55 0E-01 1.55 0E-01 1.55 0E-01 1.55 0E-01 1.720E-01 1.55 0E-01 Y-9 0 8.970E-04 8.970E-04 8.970E-04 8.970E-04 8.970E-04 8.970E-04 1.0 6 0E-03 8.970E-04 Y-9 1 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-9 1M 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-9 2 3.600E-02 3.600E-02 3.600E-02 3.600E-02 3.600E-02 3.600E-02 4.2 8 0E-02 3.600E-02 Y-9 3 3.66 0E-02 3.66 0E-02 3.66 0E-02 3.66 0E-02 3.66 0E-02 3.66 0E-02 5.010E-02 3.66 0E-02 Z R-95 4.89 0E+01 4.89 0E+01 4.89 0E+01 4.89 0E+01 4.89 0E+01 4.89 0E+01 5.670E+01 4.89 0E+01 Z R-9 7 5.910E-01 5.910E-01 5.910E-01 5.910E-01 5.910E-01 5.910E-01 6.88 0E-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 7.98 0E-01 7.98 0E-01 7.98 0E-01 7.98 0E-01 7.98 0E-01 7.98 0E-01 9.240E-01 7.98 0E-01 T C-99 M 3.68 0E-02 3.68 0E-02 3.68 0E-02 3.68 0E-02 3.68 0E-02 3.68 0E-02 4.210E-02 3.68 0E-02 T C-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 2.1 6 0E+01 2.1 6 0E+01 2.1 6 0E+01 2.1 6 0E+01 2.1 6 0E+01 2.1 6 0E+01 2.520E+01 2.1 6 0E+01 RU-10 5 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-10 6 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 T E-12 5 M 3.100E-01 3.100E-01 3.100E-01 3.100E-01 3.100E-01 3.100E-01 4.2 5 0E-01 3.100E-01 T E-127 5.95 0E-04 5.95 0E-04 5.95 0E-04 5.95 0E-04 5.95 0E-04 5.95 0E-04 6.540E-04 5.95 0E-04 T E-127M 1.830E-02 1.830E-02 1.830E-02 1.830E-02 1.830E-02 1.830E-02 2.1 6 0E-02 1.830E-02 T E-12 9 5.240E-03 5.240E-03 5.240E-03 5.240E-03 5.240E-03 5.240E-03 6.200E-03 5.240E-03 T E-12 9 M 3.95 0E+00 3.95 0E+00 3.95 0E+00 3.95 0E+00 3.95 0E+00 3.95 0E+00 4.620E+00 3.95 0E+00 T E-131 5.830E-03 5.830E-03 5.830E-03 5.830E-03 5.830E-03 5.830E-03 6.89 0E+00 5.830E-03 T E-131M 1.600E+00 1.600E+00 1.600E+00 1.600E+00 1.600E+00 1.600E+00 1.89 0E+00 1.600E+00 T E-132 8.4 6 0E-01 8.4 6 0E-01 8.4 6 0E-01 8.4 6 0E-01 8.4 6 0E-01 8.4 6 0E-01 9.95 0E-01 8.4 6 0E-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 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X D A i Teen Dose Factors for use in the Li quid Dose Calculations Appendix D Ai Teen Shoreline Sediment - Page 3 of 3 Agegroup:

TEEN Pathway: Shoreline Sediment (SHDp) Units: mrem/hr / µµµµCi/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in 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 2.4 9 0E-01 2.4 9 0E-01 2.4 9 0E-01 2.4 9 0E-01 2.4 9 0E-01 2.4 9 0E-01 2.930E-01 2.4 9 0E-01 I-133 4.900E-01 4.900E-01 4.900E-01 4.900E-01 4.900E-01 4.900E-01 5.96 0E-01 4.900E-01 I-134 8.930E-02 8.930E-02 8.930E-02 8.930E-02 8.930E-02 8.930E-02 1.0 6 0E-01 8.930E-02 I-13 5 5.0 5 0E-01 5.0 5 0E-01 5.0 5 0E-01 5.0 5 0E-01 5.0 5 0E-01 5.0 5 0E-01 5.89 0E-01 5.0 5 0E-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-13 6 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 2.0 5 0E+03 2.0 5 0E+03 2.0 5 0E+03 2.0 5 0E+03 2.0 5 0E+03 2.0 5 0E+03 2.400E+03 2.0 5 0E+03 CS-13 8 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-13 9 2.120E-02 2.120E-02 2.120E-02 2.120E-02 2.120E-02 2.120E-02 2.3 8 0E-02 2.120E-02 BA-140 4.100E+00 4.100E+00 4.100E+00 4.100E+00 4.100E+00 4.100E+00 4.69 0E+00 4.100E+00 BA-141 8.330E-03 8.330E-03 8.330E-03 8.330E-03 8.330E-03 8.330E-03 9.4 9 0E-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 4.3 5 0E+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 3.0 8 0E+00 2.730E+00 CE-143 4.620E-01 4.620E-01 4.620E-01 4.620E-01 4.620E-01 4.620E-01 5.2 5 0E-01 4.620E-01 CE-144 1.3 9 0E+01 1.3 9 0E+01 1.3 9 0E+01 1.3 9 0E+01 1.3 9 0E+01 1.3 9 0E+01 1.610E+01 1.3 9 0E+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 N D-147 1.68 0E+00 1.68 0E+00 1.68 0E+00 1.68 0E+00 1.68 0E+00 1.68 0E+00 2.010E+00 1.68 0E+00 W-1 8 7 4.700E-01 4.700E-01 4.700E-01 4.700E-01 4.700E-01 4.700E-01 5.4 6 0E-01 4.700E-01 NP-23 9 3.420E-01 3.420E-01 3.420E-01 3.420E-01 3.420E-01 3.420E-01 3.96 0E-01 3.420E-01 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X E A i Child Dose Factors for use in the Li quid Dose Calculations Appendix E Ai Child Water - Page 1 of 3 Agegroup:

CHILD Pathway: Pota ble Water (P Wtr) Units: mrem/hr / µµµµCi/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in Total Body H-3 0.000E+00 1.1 8 0E+01 1.1 8 0E+01 1.1 8 0E+01 1.1 8 0E+01 1.1 8 0E+01 0.000E+00 1.1 8 0E+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 4.68 0E+04 2.1 9 0E+03 0.000E+00 0.000E+00 0.000E+00 1.2 9 0E+03 0.000E+00 1.800E+03 CR-5 1 0.000E+00 0.000E+00 2.840E-01 7.7 5 0E-02 5.1 8 0E-01 2.710E+01 0.000E+00 5.110E-01 MN-5 4 0.000E+00 6.210E+02 0.000E+00 1.740E+02 0.000E+00 5.220E+02 0.000E+00 1.66 0E+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 6.68 0E+02 3.55 0E+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 3.1 9 0E+02 CO-6 0 0.000E+00 3.0 8 0E+02 0.000E+00 0.000E+00 0.000E+00 1.700E+03 0.000E+00 9.070E+02 NI-6 3 3.130E+04 1.670E+03 0.000E+00 0.000E+00 0.000E+00 1.130E+02 0.000E+00 1.0 6 0E+03 NI-65 4.7 6 0E+00 4.4 8 0E-01 0.000E+00 0.000E+00 0.000E+00 5.4 9 0E+01 0.000E+00 2.610E-01 CU-6 4 0.000E+00 7.3 9 0E+00 0.000E+00 1.7 8 0E+01 0.000E+00 3.470E+02 0.000E+00 4.4 6 0E+00 Z N-65 7.95 0E+02 2.120E+03 0.000E+00 1.340E+03 0.000E+00 3.720E+02 0.000E+00 1.320E+03 Z N-69 3.1 9 0E-04 4.610E-04 0.000E+00 2.800E-04 0.000E+00 2.900E-02 0.000E+00 4.2 6 0E-0 5 BR-8 3 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.0 6 0E-01 BR-8 4 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.7 8 0E-0 6 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-7 6 RB-86 0.000E+00 3.820E+03 0.000E+00 0.000E+00 0.000E+00 2.4 6 0E+02 0.000E+00 2.3 5 0E+03 RB-88 0.000E+00 7.3 6 0E-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 5.4 9 0E-1 6 0.000E+00 5.600E-14 SR-89 7.620E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.95 0E+03 0.000E+00 2.1 8 0E+03 SR-9 0 9.88 0E+0 5 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.330E+04 0.000E+00 2.510E+0 5 SR-9 1 5.810E+02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.2 8 0E+03 0.000E+00 2.1 9 0E+01 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X E A i Child Dose Factors for use in the Li quid Dose Calculations Appendix E Ai Child Water - Page 2 of 3 Agegroup:

CHILD Pathway: Pota ble Water (P Wtr) Units: mrem/hr / µµµµCi/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in Total Body SR-9 2 2.430E+01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4.610E+02 0.000E+00 9.7 6 0E-01 Y-9 0 2.100E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.98 0E+03 0.000E+00 5.620E-02 Y-9 1 3.4 8 0E+01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4.640E+03 0.000E+00 9.310E-01 Y-9 1M 9.86 0E-07 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.930E-03 0.000E+00 3.59 0E-0 8 Y-9 2 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-9 3 2.900E-01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4.330E+03 0.000E+00 7.970E-03 Z R-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 Z R-9 7 2.4 8 0E-01 3.59 0E-02 0.000E+00 5.1 5 0E-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 1.4 6 0E+03 0.000E+00 5.640E+02 0.000E+00 1.69 0E+02 T C-99 M 1.3 5 0E-02 2.640E-02 0.000E+00 3.840E-01 1.340E-02 1.500E+01 0.000E+00 4.3 8 0E-01 T C-101 3.330E-17 3.4 8 0E-17 0.000E+00 5.940E-1 6 1.840E-17 1.110E-1 6 0.000E+00 4.410E-1 6 RU-103 4.210E+01 0.000E+00 0.000E+00 1.0 6 0E+02 0.000E+00 1.0 9 0E+03 0.000E+00 1.620E+01 RU-10 5 5.7 5 0E-01 0.000E+00 0.000E+00 5.0 6 0E+00 0.000E+00 3.7 5 0E+02 0.000E+00 2.0 9 0E-01 RU-10 6 6.800E+02 0.000E+00 0.000E+00 9.1 8 0E+02 0.000E+00 1.0 6 0E+04 0.000E+00 8.4 8 0E+01 AG-110M 3.130E+01 2.110E+01 0.000E+00 3.940E+01 0.000E+00 2.510E+03 0.000E+00 1.69 0E+01 T E-12 5 M 6.59 0E+02 1.7 9 0E+02 1.85 0E+02 0.000E+00 0.000E+00 6.3 6 0E+02 0.000E+00 8.7 8 0E+01 T E-127 1.130E+01 3.0 5 0E+00 7.820E+00 3.210E+01 0.000E+00 4.410E+02 0.000E+00 2.420E+00 T E-127M 1.670E+03 4.510E+02 4.000E+02 4.7 8 0E+03 0.000E+00 1.3 6 0E+03 0.000E+00 1.99 0E+02 T E-12 9 5.730E-03 1.600E-03 4.0 9 0E-03 1.68 0E-02 0.000E+00 3.570E-01 0.000E+00 1.3 6 0E-03 T E-12 9 M 2.800E+03 7.830E+02 9.030E+02 8.230E+03 0.000E+00 3.420E+03 0.000E+00 4.3 5 0E+02 T E-131 1.040E-0 8 3.1 6 0E-0 9 7.930E-0 9 3.140E-0 8 0.000E+00 5.4 5 0E-0 8 0.000E+00 3.0 9 0E-0 9 T E-131M 3.170E+02 1.100E+02 2.2 6 0E+02 1.0 6 0E+03 0.000E+00 4.4 5 0E+03 0.000E+00 1.170E+02 T E-132 5.2 8 0E+02 2.340E+02 3.400E+02 2.170E+03 0.000E+00 2.3 5 0E+03 0.000E+00 2.820E+02 I-130 8.65 0E+01 1.7 5 0E+02 1.930E+04 2.610E+02 0.000E+00 8.1 8 0E+01 0.000E+00 9.010E+01 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X E A i Child Dose Factors for use in the Li quid Dose Calculations Appendix E Ai Child Water - Page 3 of 3 Agegroup:

CHILD Pathway: Pota ble Water (P Wtr) Units: mrem/hr / µµµµCi/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in Total Body I-131 9.58 0E+02 9.630E+02 3.1 9 0E+0 5 1.58 0E+03 0.000E+00 8.58 0E+01 0.000E+00 5.470E+02 I-132 1.2 5 0E+00 2.300E+00 1.070E+02 3.520E+00 0.000E+00 2.710E+00 0.000E+00 1.0 6 0E+00 I-133 2.310E+02 2.85 0E+02 5.300E+04 4.7 5 0E+02 0.000E+00 1.1 5 0E+02 0.000E+00 1.0 8 0E+02 I-134 1.820E-03 3.370E-03 7.7 6 0E-02 5.1 6 0E-03 0.000E+00 2.240E-03 0.000E+00 1.55 0E-03 I-13 5 2.89 0E+01 5.210E+01 4.610E+03 7.99 0E+01 0.000E+00 3.970E+01 0.000E+00 2.4 6 0E+01 CS-134 1.3 6 0E+04 2.230E+04 0.000E+00 6.920E+03 2.4 8 0E+03 1.200E+02 0.000E+00 4.710E+03 CS-13 6 1.330E+03 3.66 0E+03 0.000E+00 1.95 0E+03 2.910E+02 1.2 9 0E+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 2.69 0E+03 CS-13 8 2.440E-0 6 3.3 9 0E-0 6 0.000E+00 2.3 8 0E-0 6 2.570E-07 1.56 0E-0 6 0.000E+00 2.1 5 0E-0 6 BA-13 9 5.940E-02 3.170E-0 5 0.000E+00 2.770E-0 5 1.86 0E-0 5 3.430E+00 0.000E+00 1.720E-03 BA-140 4.700E+03 4.120E+00 0.000E+00 1.340E+00 2.4 6 0E+00 2.3 8 0E+03 0.000E+00 2.740E+02 BA-141 1.620E-11 9.0 5 0E-1 5 0.000E+00 7.830E-1 5 5.310E-14 9.210E-12 0.000E+00 5.2 6 0E-13 BA-142 1.800E-20 1.300E-23 0.000E+00 1.0 5 0E-23 7.630E-24 2.3 5 0E-22 0.000E+00 1.010E-21 LA-140 4.7 8 0E-01 1.670E-01 0.000E+00 0.000E+00 0.000E+00 4.65 0E+03 0.000E+00 5.630E-02 LA-142 1.640E-04 5.210E-0 5 0.000E+00 0.000E+00 0.000E+00 1.030E+01 0.000E+00 1.630E-0 5 CE-141 2.2 8 0E+00 1.140E+00 0.000E+00 4.99 0E-01 0.000E+00 1.420E+03 0.000E+00 1.69 0E-01 CE-143 3.1 6 0E-01 1.710E+02 0.000E+00 7.1 8 0E-02 0.000E+00 2.510E+03 0.000E+00 2.4 8 0E-02 CE-144 1.210E+02 3.7 9 0E+01 0.000E+00 2.100E+01 0.000E+00 9.870E+03 0.000E+00 6.4 5 0E+00 PR-143 2.230E+00 6.69 0E-01 0.000E+00 3.620E-01 0.000E+00 2.400E+03 0.000E+00 1.110E-01 PR-144 2.200E-1 5 6.800E-1 6 0.000E+00 3.600E-1 6 0.000E+00 1.4 6 0E-12 0.000E+00 1.110E-1 6 N D-147 1.570E+00 1.270E+00 0.000E+00 6.99 0E-01 0.000E+00 2.020E+03 0.000E+00 9.86 0E-02 W-1 8 7 1.7 6 0E+01 1.040E+01 0.000E+00 0.000E+00 0.000E+00 1.4 6 0E+03 0.000E+00 4.68 0E+00 NP-23 9 2.630E-01 1.89 0E-02 0.000E+00 5.470E-02 0.000E+00 1.400E+03 0.000E+00 1.330E-02 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X E A i Child Dose Factors for use in the Li quid Dose Calculations Appendix E Ai Child Fish - Page 1 of 3 Agegroup:

CHILD Pathway: Fresh Water Fish

- Sport (FFSP) Units: mrem/hr / µµµµCi/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in 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 4.3 8 0E+04 8.7 6 0E+03 8.7 6 0E+03 8.7 6 0E+03 8.7 6 0E+03 8.7 6 0E+03 0.000E+00 8.7 6 0E+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 1.85 0E+0 6 8.68 0E+04 0.000E+00 0.000E+00 0.000E+00 5.130E+04 0.000E+00 7.1 5 0E+04 CR-5 1 0.000E+00 0.000E+00 7.58 0E-01 2.070E-01 1.3 8 0E+00 7.240E+01 0.000E+00 1.370E+00 MN-5 4 0.000E+00 3.3 6 0E+03 0.000E+00 9.420E+02 0.000E+00 2.820E+03 0.000E+00 8.95 0E+02 MN-56 0.000E+00 1.65 0E-01 0.000E+00 2.000E-01 0.000E+00 2.400E+01 0.000E+00 3.730E-02 FE-55 9.040E+02 4.7 9 0E+02 0.000E+00 0.000E+00 2.710E+02 8.88 0E+01 0.000E+00 1.4 9 0E+02 FE-59 1.2 8 0E+03 2.070E+03 0.000E+00 0.000E+00 5.99 0E+02 2.1 5 0E+03 0.000E+00 1.030E+03 CO-58 0.000E+00 7.010E+01 0.000E+00 0.000E+00 0.000E+00 4.0 9 0E+02 0.000E+00 2.1 5 0E+02 CO-6 0 0.000E+00 2.0 8 0E+02 0.000E+00 0.000E+00 0.000E+00 1.1 5 0E+03 0.000E+00 6.130E+02 NI-6 3 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-6 4 0.000E+00 2.59 0E+00 0.000E+00 6.2 6 0E+00 0.000E+00 1.220E+02 0.000E+00 1.570E+00 Z N-65 2.1 5 0E+04 5.730E+04 0.000E+00 3.610E+04 0.000E+00 1.010E+04 0.000E+00 3.56 0E+04 Z N-69 1.0 8 0E-0 6 1.56 0E-0 6 0.000E+00 9.470E-07 0.000E+00 9.840E-0 5 0.000E+00 1.440E-07 BR-8 3 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-8 4 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+0 5 0.000E+00 0.000E+00 0.000E+00 6.530E+03 0.000E+00 6.2 5 0E+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 1.58 0E-2 6 0.000E+00 0.000E+00 0.000E+00 1.370E-2 8 0.000E+00 1.400E-2 6 SR-89 3.070E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.1 9 0E+03 0.000E+00 8.7 8 0E+02 SR-9 0 4.010E+0 5 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.400E+03 0.000E+00 1.020E+0 5 SR-9 1 9.800E+01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.1 6 0E+02 0.000E+00 3.700E+00 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X E A i Child Dose Factors for use in the Li quid Dose Calculations Appendix E Ai Child Fish - Page 2 of 3 Agegroup:

CHILD Pathway: Fresh Water Fish

- Sport (FFSP) Units: mrem/hr / µµµµCi/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in Total Body SR-9 2 4.58 0E-01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 8.670E+00 0.000E+00 1.840E-02 Y-9 0 6.240E-01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.7 8 0E+03 0.000E+00 1.670E-02 Y-9 1 1.170E+01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.56 0E+03 0.000E+00 3.130E-01 Y-9 1M 1.4 8 0E-11 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.900E-0 8 0.000E+00 5.3 9 0E-13 Y-9 2 6.440E-04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.86 0E+01 0.000E+00 1.840E-0 5 Y-9 3 4.300E-02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 6.420E+02 0.000E+00 1.1 8 0E-03 Z R-95 2.98 0E-01 6.55 0E-02 0.000E+00 9.370E-02 0.000E+00 6.830E+01 0.000E+00 5.830E-02 Z R-9 7 6.7 8 0E-03 9.7 9 0E-04 0.000E+00 1.410E-03 0.000E+00 1.4 8 0E+02 0.000E+00 5.7 8 0E-04 NB-95 5.210E+02 2.030E+02 0.000E+00 1.900E+02 0.000E+00 3.7 5 0E+0 5 0.000E+00 1.4 5 0E+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 T C-99 M 6.86 0E-04 1.3 5 0E-03 0.000E+00 1.95 0E-02 6.830E-04 7.65 0E-01 0.000E+00 2.230E-02 T C-101 3.610E-33 3.7 8 0E-33 0.000E+00 6.440E-32 2.000E-33 1.200E-32 0.000E+00 4.7 9 0E-32 RU-103 5.65 0E+00 0.000E+00 0.000E+00 1.420E+01 0.000E+00 1.4 6 0E+02 0.000E+00 2.170E+00 RU-10 5 1.1 9 0E-02 0.000E+00 0.000E+00 1.0 5 0E-01 0.000E+00 7.7 9 0E+00 0.000E+00 4.330E-03 RU-10 6 9.1 9 0E+01 0.000E+00 0.000E+00 1.240E+02 0.000E+00 1.430E+03 0.000E+00 1.1 5 0E+01 AG-110M 9.720E-01 6.570E-01 0.000E+00 1.220E+00 0.000E+00 7.810E+01 0.000E+00 5.2 5 0E-01 T E-12 5 M 3.540E+03 9.610E+02 9.95 0E+02 0.000E+00 0.000E+00 3.420E+03 0.000E+00 4.730E+02 T E-127 2.520E+01 6.800E+00 1.7 5 0E+01 7.170E+01 0.000E+00 9.85 0E+02 0.000E+00 5.410E+00 T E-127M 9.040E+03 2.430E+03 2.1 6 0E+03 2.58 0E+04 0.000E+00 7.320E+03 0.000E+00 1.070E+03 T E-12 9 2.2 8 0E-0 5 6.370E-0 6 1.630E-0 5 6.68 0E-0 5 0.000E+00 1.420E-03 0.000E+00 5.420E-0 6 T E-12 9 M 1.500E+04 4.1 9 0E+03 4.840E+03 4.410E+04 0.000E+00 1.830E+04 0.000E+00 2.330E+03 T E-131 1.210E-1 6 3.68 0E-17 9.220E-17 3.65 0E-1 6 0.000E+00 6.330E-1 6 0.000E+00 3.59 0E-17 T E-131M 1.300E+03 4.500E+02 9.2 5 0E+02 4.3 5 0E+03 0.000E+00 1.820E+04 0.000E+00 4.7 9 0E+02 T E-132 2.570E+03 1.140E+03 1.65 0E+03 1.0 5 0E+04 0.000E+00 1.140E+04 0.000E+00 1.370E+03 I-130 8.95 0E+00 1.810E+01 1.99 0E+03 2.700E+01 0.000E+00 8.4 6 0E+00 0.000E+00 9.320E+00 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X E A i Child Dose Factors for use in the Li quid Dose Calculations Appendix E Ai Child Fish - Page 3 of 3 Agegroup:

CHILD Pathway: Fresh Water Fish

- Sport (FFSP) Units: mrem/hr / µµµµCi/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in Total Body I-131 1.86 0E+02 1.870E+02 6.1 9 0E+04 3.070E+02 0.000E+00 1.670E+01 0.000E+00 1.0 6 0E+02 I-132 6.830E-03 1.2 5 0E-02 5.820E-01 1.920E-02 0.000E+00 1.4 8 0E-02 0.000E+00 5.770E-03 I-133 3.140E+01 3.88 0E+01 7.210E+03 6.470E+01 0.000E+00 1.56 0E+01 0.000E+00 1.470E+01 I-134 2.7 5 0E-0 8 5.100E-0 8 1.170E-0 6 7.800E-0 8 0.000E+00 3.3 8 0E-0 8 0.000E+00 2.3 5 0E-0 8 I-13 5 1.670E+00 3.010E+00 2.66 0E+02 4.610E+00 0.000E+00 2.2 9 0E+00 0.000E+00 1.420E+00 CS-134 3.68 0E+0 5 6.040E+0 5 0.000E+00 1.870E+0 5 6.710E+04 3.2 5 0E+03 0.000E+00 1.270E+0 5 CS-13 6 3.510E+04 9.640E+04 0.000E+00 5.130E+04 7.66 0E+03 3.3 9 0E+03 0.000E+00 6.240E+04 CS-137 5.140E+0 5 4.920E+0 5 0.000E+00 1.600E+0 5 5.770E+04 3.0 8 0E+03 0.000E+00 7.270E+04 CS-13 8 1.210E-11 1.69 0E-11 0.000E+00 1.1 9 0E-11 1.2 8 0E-12 7.770E-12 0.000E+00 1.070E-11 BA-13 9 7.930E-0 6 4.230E-0 9 0.000E+00 3.700E-0 9 2.4 9 0E-0 9 4.58 0E-04 0.000E+00 2.300E-07 BA-140 2.4 8 0E+02 2.170E-01 0.000E+00 7.0 6 0E-02 1.2 9 0E-01 1.2 5 0E+02 0.000E+00 1.4 5 0E+01 BA-141 1.210E-24 6.800E-2 8 0.000E+00 5.88 0E-2 8 3.99 0E-27 6.920E-2 5 0.000E+00 3.95 0E-2 6 BA-142 3.4 6 0E-42 2.4 9 0E-4 5 0.000E+00 2.020E-4 5 1.470E-4 5 4.510E-44 0.000E+00 1.930E-43 LA-140 1.310E-01 4.59 0E-02 0.000E+00 0.000E+00 0.000E+00 1.2 8 0E+03 0.000E+00 1.55 0E-02 LA-142 2.970E-07 9.470E-0 8 0.000E+00 0.000E+00 0.000E+00 1.88 0E-02 0.000E+00 2.96 0E-0 8 CE-141 3.0 6 0E-02 1.520E-02 0.000E+00 6.68 0E-03 0.000E+00 1.900E+01 0.000E+00 2.2 6 0E-03 CE-143 3.320E-03 1.800E+00 0.000E+00 7.55 0E-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 1.1 9 0E-01 0.000E+00 7.920E+02 0.000E+00 3.640E-02 PR-144 2.1 8 0E-2 8 6.7 5 0E-2 9 0.000E+00 3.570E-2 9 0.000E+00 1.4 5 0E-2 5 0.000E+00 1.100E-2 9 N D-147 5.1 5 0E-01 4.170E-01 0.000E+00 2.2 9 0E-01 0.000E+00 6.610E+02 0.000E+00 3.230E-02 W-1 8 7 2.010E+02 1.1 9 0E+02 0.000E+00 0.000E+00 0.000E+00 1.68 0E+04 0.000E+00 5.3 5 0E+01 NP-23 9 3.0 8 0E-02 2.210E-03 0.000E+00 6.3 9 0E-03 0.000E+00 1.630E+02 0.000E+00 1.55 0E-03 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X E A i Child Dose Factors for use in the Li quid Dose Calculations Appendix E Ai Child Shoreline Sediment - Page 1 of 3 Agegroup:

CHILD Pathway: Shoreline Sediment (SHDp) Units: mrem/hr / µµµµCi/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in 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 4.99 0E-01 4.99 0E-01 4.99 0E-01 4.99 0E-01 4.99 0E-01 4.99 0E-01 5.7 8 0E-01 4.99 0E-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-5 1 1.95 0E-01 1.95 0E-01 1.95 0E-01 1.95 0E-01 1.95 0E-01 1.95 0E-01 2.300E-01 1.95 0E-01 MN-5 4 5.7 9 0E+01 5.7 9 0E+01 5.7 9 0E+01 5.7 9 0E+01 5.7 9 0E+01 5.7 9 0E+01 6.7 9 0E+01 5.7 9 0E+01 MN-56 3.770E-02 3.770E-02 3.770E-02 3.770E-02 3.770E-02 3.770E-02 4.4 5 0E-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 1.58 0E+01 1.58 0E+01 1.58 0E+01 1.58 0E+01 1.58 0E+01 1.58 0E+01 1.85 0E+01 1.58 0E+01 CO-6 0 8.98 0E+02 8.98 0E+02 8.98 0E+02 8.98 0E+02 8.98 0E+02 8.98 0E+02 1.0 6 0E+03 8.98 0E+02 NI-6 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 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-6 4 2.530E-02 2.530E-02 2.530E-02 2.530E-02 2.530E-02 2.530E-02 2.870E-02 2.530E-02 Z N-65 3.120E+01 3.120E+01 3.120E+01 3.120E+01 3.120E+01 3.120E+01 3.59 0E+01 3.120E+01 Z N-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-8 3 2.030E-04 2.030E-04 2.030E-04 2.030E-04 2.030E-04 2.030E-04 2.96 0E-04 2.030E-04 BR-8 4 8.4 6 0E-03 8.4 6 0E-03 8.4 6 0E-03 8.4 6 0E-03 8.4 6 0E-03 8.4 6 0E-03 9.870E-03 8.4 6 0E-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 3.7 5 0E-01 3.7 5 0E-01 3.7 5 0E-01 3.7 5 0E-01 3.7 5 0E-01 3.7 5 0E-01 4.2 9 0E-01 3.7 5 0E-01 RB-88 1.3 8 0E-03 1.3 8 0E-03 1.3 8 0E-03 1.3 8 0E-03 1.3 8 0E-03 1.3 8 0E-03 1.58 0E-03 1.3 8 0E-03 RB-89 5.130E-03 5.130E-03 5.130E-03 5.130E-03 5.130E-03 5.130E-03 6.1 6 0E-03 5.130E-03 SR-89 9.030E-04 9.030E-04 9.030E-04 9.030E-04 9.030E-04 9.030E-04 1.0 5 0E-03 9.030E-04 SR-9 0 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-9 1 8.970E-02 8.970E-02 8.970E-02 8.970E-02 8.970E-02 8.970E-02 1.0 5 0E-01 8.970E-02 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X E A i Child Dose Factors for use in the Li quid Dose Calculations Appendix E Ai Child Shoreline Sediment - Page 2 of 3 Agegroup:

CHILD Pathway: Shoreline Sediment (SHDp) Units: mrem/hr / µµµµCi/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in Total Body SR-9 2 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-9 0 1.88 0E-04 1.88 0E-04 1.88 0E-04 1.88 0E-04 1.88 0E-04 1.88 0E-04 2.220E-04 1.88 0E-04 Y-9 1 4.4 8 0E-02 4.4 8 0E-02 4.4 8 0E-02 4.4 8 0E-02 4.4 8 0E-02 4.4 8 0E-02 5.040E-02 4.4 8 0E-02 Y-9 1M 4.1 9 0E-03 4.1 9 0E-03 4.1 9 0E-03 4.1 9 0E-03 4.1 9 0E-03 4.1 9 0E-03 4.85 0E-03 4.1 9 0E-03 Y-9 2 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-9 3 7.66 0E-03 7.66 0E-03 7.66 0E-03 7.66 0E-03 7.66 0E-03 7.66 0E-03 1.0 5 0E-02 7.66 0E-03 Z R-95 1.020E+01 1.020E+01 1.020E+01 1.020E+01 1.020E+01 1.020E+01 1.1 9 0E+01 1.020E+01 Z R-9 7 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 T C-99 M 7.68 0E-03 7.68 0E-03 7.68 0E-03 7.68 0E-03 7.68 0E-03 7.68 0E-03 8.810E-03 7.68 0E-03 T C-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-10 5 2.66 0E-02 2.66 0E-02 2.66 0E-02 2.66 0E-02 2.66 0E-02 2.66 0E-02 3.010E-02 2.66 0E-02 RU-10 6 1.7 6 0E+01 1.7 6 0E+01 1.7 6 0E+01 1.7 6 0E+01 1.7 6 0E+01 1.7 6 0E+01 2.110E+01 1.7 6 0E+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 T E-12 5 M 6.4 8 0E-02 6.4 8 0E-02 6.4 8 0E-02 6.4 8 0E-02 6.4 8 0E-02 6.4 8 0E-02 8.88 0E-02 6.4 8 0E-02 T E-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 T E-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 T E-12 9 1.100E-03 1.100E-03 1.100E-03 1.100E-03 1.100E-03 1.100E-03 1.300E-03 1.100E-03 T E-12 9 M 8.2 6 0E-01 8.2 6 0E-01 8.2 6 0E-01 8.2 6 0E-01 8.2 6 0E-01 8.2 6 0E-01 9.65 0E-01 8.2 6 0E-01 T E-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 T E-131M 3.3 5 0E-01 3.3 5 0E-01 3.3 5 0E-01 3.3 5 0E-01 3.3 5 0E-01 3.3 5 0E-01 3.95 0E-01 3.3 5 0E-01 T E-132 1.770E-01 1.770E-01 1.770E-01 1.770E-01 1.770E-01 1.770E-01 2.0 8 0E-01 1.770E-01 I-130 2.300E-01 2.300E-01 2.300E-01 2.300E-01 2.300E-01 2.300E-01 2.7 9 0E-01 2.300E-01 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X E A i Child Dose Factors for use in the Li quid Dose Calculations Appendix E Ai Child Shoreline Sediment - Page 3 of 3 Agegroup:

CHILD Pathway: Shoreline Sediment (SHDp) Units: mrem/hr / µµµµCi/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in Total Body I-131 7.1 8 0E-01 7.1 8 0E-01 7.1 8 0E-01 7.1 8 0E-01 7.1 8 0E-01 7.1 8 0E-01 8.720E-01 7.1 8 0E-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-13 5 1.0 5 0E-01 1.0 5 0E-01 1.0 5 0E-01 1.0 5 0E-01 1.0 5 0E-01 1.0 5 0E-01 1.230E-01 1.0 5 0E-01 CS-134 2.86 0E+02 2.86 0E+02 2.86 0E+02 2.86 0E+02 2.86 0E+02 2.86 0E+02 3.340E+02 2.86 0E+02 CS-13 6 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 4.2 9 0E+02 4.2 9 0E+02 4.2 9 0E+02 4.2 9 0E+02 4.2 9 0E+02 4.2 9 0E+02 5.010E+02 4.2 9 0E+02 CS-13 8 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-13 9 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 1.98 0E-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 9.0 9 0E-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 9.65 0E-02 9.65 0E-02 9.65 0E-02 9.65 0E-02 9.65 0E-02 9.65 0E-02 1.100E-01 9.65 0E-02 CE-144 2.900E+00 2.900E+00 2.900E+00 2.900E+00 2.900E+00 2.900E+00 3.3 6 0E+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 7.66 0E-0 5 7.66 0E-0 5 7.66 0E-0 5 7.66 0E-0 5 7.66 0E-0 5 7.66 0E-0 5 8.810E-0 5 7.66 0E-0 5 N D-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-1 8 7 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-23 9 7.140E-02 7.140E-02 7.140E-02 7.140E-02 7.140E-02 7.140E-02 8.270E-02 7.140E-02 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X F A i Infant Dose Factors for use in the Li quid Dose Calculations Appendix F Ai Infant Water - Page 1 of 3 Agegroup:

INFANT Pathway: Pota ble Water (P Wtr) Units: mrem/hr / µµµµCi/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in Total Body H-3 0.000E+00 1.1 6 0E+01 1.1 6 0E+01 1.1 6 0E+01 1.1 6 0E+01 1.1 6 0E+01 0.000E+00 1.1 6 0E+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 2.1 9 0E+02 2.1 9 0E+02 2.1 9 0E+02 2.1 9 0E+02 2.1 9 0E+02 2.1 9 0E+02 0.000E+00 2.1 9 0E+02 P-32 6.240E+04 3.670E+03 0.000E+00 0.000E+00 0.000E+00 8.4 5 0E+02 0.000E+00 2.420E+03 CR-5 1 0.000E+00 0.000E+00 3.420E-01 7.470E-02 6.65 0E-01 1.530E+01 0.000E+00 5.240E-01 MN-5 4 0.000E+00 7.4 8 0E+02 0.000E+00 1.66 0E+02 0.000E+00 2.7 5 0E+02 0.000E+00 1.69 0E+02 MN-56 0.000E+00 1.220E+00 0.000E+00 1.0 5 0E+00 0.000E+00 1.110E+02 0.000E+00 2.100E-01 FE-55 5.230E+02 3.3 8 0E+02 0.000E+00 0.000E+00 1.65 0E+02 4.2 9 0E+01 0.000E+00 9.030E+01 FE-59 1.1 5 0E+03 2.010E+03 0.000E+00 0.000E+00 5.940E+02 9.59 0E+02 0.000E+00 7.910E+02 CO-58 0.000E+00 1.3 5 0E+02 0.000E+00 0.000E+00 0.000E+00 3.3 6 0E+02 0.000E+00 3.3 6 0E+02 CO-6 0 0.000E+00 4.0 6 0E+02 0.000E+00 0.000E+00 0.000E+00 9.670E+02 0.000E+00 9.59 0E+02 NI-6 3 2.3 9 0E+04 1.470E+03 0.000E+00 0.000E+00 0.000E+00 7.340E+01 0.000E+00 8.2 8 0E+02 NI-65 6.520E+00 7.3 8 0E-01 0.000E+00 0.000E+00 0.000E+00 5.620E+01 0.000E+00 3.3 6 0E-01 CU-6 4 0.000E+00 1.1 9 0E+01 0.000E+00 2.010E+01 0.000E+00 2.440E+02 0.000E+00 5.500E+00 Z N-65 6.910E+02 2.370E+03 0.000E+00 1.1 5 0E+03 0.000E+00 2.000E+03 0.000E+00 1.0 9 0E+03 Z N-69 4.3 9 0E-04 7.910E-04 0.000E+00 3.2 9 0E-04 0.000E+00 6.4 5 0E-02 0.000E+00 5.89 0E-0 5 BR-8 3 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-8 4 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.220E-0 6 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-7 6 RB-86 0.000E+00 6.2 8 0E+03 0.000E+00 0.000E+00 0.000E+00 1.610E+02 0.000E+00 3.100E+03 RB-88 0.000E+00 1.2 5 0E-11 0.000E+00 0.000E+00 0.000E+00 1.220E-11 0.000E+00 6.840E-12 RB-89 0.000E+00 9.96 0E-14 0.000E+00 0.000E+00 0.000E+00 3.3 9 0E-14 0.000E+00 6.86 0E-14 SR-89 9.3 8 0E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.930E+03 0.000E+00 2.69 0E+03 SR-9 0 6.96 0E+0 5 0.000E+00 0.000E+00 0.000E+00 0.000E+00 8.69 0E+03 0.000E+00 1.770E+0 5 SR-9 1 7.830E+02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 9.270E+02 0.000E+00 2.830E+01 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X F A i Infant Dose Factors for use in the Li quid Dose Calculations Appendix F Ai Infant Water - Page 2 of 3 Agegroup:

INFANT Pathway: Pota ble Water (P Wtr) Units: mrem/hr / µµµµCi/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in Total Body SR-9 2 3.3 5 0E+01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.610E+02 0.000E+00 1.240E+00 Y-9 0 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-9 1 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-9 1M 1.3 5 0E-0 6 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4.510E-03 0.000E+00 4.610E-0 8 Y-9 2 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-9 3 4.010E-01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.170E+03 0.000E+00 1.0 9 0E-02 Z R-95 7.710E+00 1.88 0E+00 0.000E+00 2.020E+00 0.000E+00 9.3 5 0E+02 0.000E+00 1.330E+00 Z R-9 7 3.400E-01 5.840E-02 0.000E+00 5.89 0E-02 0.000E+00 3.720E+03 0.000E+00 2.670E-02 NB-95 1.56 0E+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 1.68 0E+03 0.000E+00 3.710E+02 0.000E+00 2.200E+02 T C-99 M 1.810E-02 3.740E-02 0.000E+00 4.020E-01 1.95 0E-02 1.0 9 0E+01 0.000E+00 4.820E-01 T C-101 4.570E-17 5.7 5 0E-17 0.000E+00 6.840E-1 6 3.140E-17 9.7 8 0E-1 5 0.000E+00 5.69 0E-1 6 RU-103 5.520E+01 0.000E+00 0.000E+00 1.1 5 0E+02 0.000E+00 6.710E+02 0.000E+00 1.85 0E+01 RU-10 5 7.85 0E-01 0.000E+00 0.000E+00 5.770E+00 0.000E+00 3.120E+02 0.000E+00 2.640E-01 RU-10 6 9.0 6 0E+02 0.000E+00 0.000E+00 1.070E+03 0.000E+00 6.88 0E+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 T E-12 5 M 8.710E+02 2.910E+02 2.930E+02 0.000E+00 0.000E+00 4.1 5 0E+02 0.000E+00 1.1 8 0E+02 T E-127 1.55 0E+01 5.200E+00 1.2 6 0E+01 3.7 9 0E+01 0.000E+00 3.2 6 0E+02 0.000E+00 3.340E+00 T E-127M 2.1 9 0E+03 7.2 8 0E+02 6.340E+02 5.400E+03 0.000E+00 8.85 0E+02 0.000E+00 2.66 0E+02 T E-12 9 7.86 0E-03 2.710E-03 6.59 0E-03 1.96 0E-02 0.000E+00 6.2 8 0E-01 0.000E+00 1.840E-03 T E-12 9 M 3.720E+03 1.2 8 0E+03 1.430E+03 9.310E+03 0.000E+00 2.220E+03 0.000E+00 5.730E+02 T E-131 1.420E-0 8 5.2 5 0E-0 9 1.270E-0 8 3.640E-0 8 0.000E+00 5.7 5 0E-07 0.000E+00 3.99 0E-0 9 T E-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 T E-132 7.030E+02 3.4 8 0E+02 5.140E+02 2.1 8 0E+03 0.000E+00 1.2 9 0E+03 0.000E+00 3.2 5 0E+02 I-130 1.1 5 0E+02 2.530E+02 2.840E+04 2.7 8 0E+02 0.000E+00 5.430E+01 0.000E+00 1.020E+02 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X F A i Infant Dose Factors for use in the Li quid Dose Calculations Appendix F Ai Infant Water - Page 3 of 3 Agegroup:

INFANT Pathway: Pota ble Water (P Wtr) Units: mrem/hr / µµµµCi/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in Total Body I-131 1.2 9 0E+03 1.520E+03 5.010E+0 5 1.7 8 0E+03 0.000E+00 5.440E+01 0.000E+00 6.700E+02 I-132 1.68 0E+00 3.410E+00 1.600E+02 3.800E+00 0.000E+00 2.7 6 0E+00 0.000E+00 1.210E+00 I-133 3.1 5 0E+02 4.59 0E+02 8.3 5 0E+04 5.400E+02 0.000E+00 7.770E+01 0.000E+00 1.340E+02 I-134 2.440E-03 4.99 0E-03 1.1 6 0E-01 5.58 0E-03 0.000E+00 5.1 6 0E-03 0.000E+00 1.7 8 0E-03 I-13 5 3.900E+01 7.7 5 0E+01 6.95 0E+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 2.7 9 0E+03 7.1 8 0E+01 0.000E+00 2.670E+03 CS-13 6 1.68 0E+03 4.95 0E+03 0.000E+00 1.970E+03 4.030E+02 7.510E+01 0.000E+00 1.85 0E+03 CS-137 1.96 0E+04 2.300E+04 0.000E+00 6.170E+03 2.500E+03 7.1 9 0E+01 0.000E+00 1.630E+03 CS-13 8 3.330E-0 6 5.410E-0 6 0.000E+00 2.700E-0 6 4.210E-07 8.65 0E-0 6 0.000E+00 2.620E-0 6 BA-13 9 8.1 8 0E-02 5.420E-0 5 0.000E+00 3.2 6 0E-0 5 3.2 9 0E-0 5 5.1 8 0E+00 0.000E+00 2.370E-03 BA-140 6.2 6 0E+03 6.2 6 0E+00 0.000E+00 1.4 9 0E+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-1 5 9.2 5 0E-1 5 2.710E-10 0.000E+00 7.000E-13 BA-142 2.4 6 0E-20 2.040E-23 0.000E+00 1.1 8 0E-23 1.240E-23 1.010E-1 9 0.000E+00 1.210E-21 LA-140 6.4 6 0E-01 2.55 0E-01 0.000E+00 0.000E+00 0.000E+00 2.99 0E+03 0.000E+00 6.55 0E-02 LA-142 2.220E-04 8.1 6 0E-0 5 0.000E+00 0.000E+00 0.000E+00 1.3 9 0E+01 0.000E+00 1.95 0E-0 5 CE-141 2.930E+00 1.7 9 0E+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 8.3 6 0E-02 0.000E+00 1.670E+03 0.000E+00 3.270E-02 CE-144 1.120E+02 4.58 0E+01 0.000E+00 1.85 0E+01 0.000E+00 6.430E+03 0.000E+00 6.270E+00 PR-143 2.98 0E+00 1.110E+00 0.000E+00 4.140E-01 0.000E+00 1.570E+03 0.000E+00 1.4 8 0E-01 PR-144 3.020E-1 5 1.170E-1 5 0.000E+00 4.240E-1 6 0.000E+00 5.440E-11 0.000E+00 1.520E-1 6 N D-147 2.020E+00 2.070E+00 0.000E+00 7.98 0E-01 0.000E+00 1.310E+03 0.000E+00 1.270E-01 W-1 8 7 2.400E+01 1.670E+01 0.000E+00 0.000E+00 0.000E+00 9.7 9 0E+02 0.000E+00 5.7 6 0E+00 NP-23 9 3.600E-01 3.220E-02 0.000E+00 6.430E-02 0.000E+00 9.320E+02 0.000E+00 1.820E-02 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X G R i Adult Dose Factors for use in the Gaseous Dose Calculations Appendix G Ri Adult Cow Milk - Page 1 of 3 Agegroup: ADULT Pathway: Grs

/Cow/Mil k (CMIL K) Units: m 2*mrem/yr / µµµµCi/sec; mrem/yr / µµµµCi/m 3 (H-3) Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in 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+0 8 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+0 6 2.440E+0 6 2.440E+0 6 2.440E+0 6 2.440E+0 6 2.440E+0 6 0.000E+00 2.440E+0 6 P-32 1.710E+10 1.0 6 0E+0 9 0.000E+00 0.000E+00 0.000E+00 1.920E+0 9 0.000E+00 6.610E+0 8 CR-5 1 0.000E+00 0.000E+00 1.710E+04 6.300E+03 3.7 9 0E+04 7.1 9 0E+0 6 0.000E+00 2.86 0E+04 MN-5 4 0.000E+00 8.410E+0 6 0.000E+00 2.500E+0 6 0.000E+00 2.58 0E+07 0.000E+00 1.610E+0 6 MN-56 0.000E+00 4.0 9 0E-03 0.000E+00 5.1 9 0E-03 0.000E+00 1.310E-01 0.000E+00 7.2 6 0E-04 FE-55 2.510E+07 1.740E+07 0.000E+00 0.000E+00 9.68 0E+0 6 9.95 0E+0 6 0.000E+00 4.0 5 0E+0 6 FE-59 2.970E+07 6.98 0E+07 0.000E+00 0.000E+00 1.95 0E+07 2.330E+0 8 0.000E+00 2.68 0E+07 CO-58 0.000E+00 4.710E+0 6 0.000E+00 0.000E+00 0.000E+00 9.55 0E+07 0.000E+00 1.0 6 0E+07 CO-6 0 0.000E+00 1.640E+07 0.000E+00 0.000E+00 0.000E+00 3.0 8 0E+0 8 0.000E+00 3.620E+07 NI-6 3 6.730E+0 9 4.66 0E+0 8 0.000E+00 0.000E+00 0.000E+00 9.730E+07 0.000E+00 2.2 6 0E+0 8 NI-65 3.700E-01 4.810E-02 0.000E+00 0.000E+00 0.000E+00 1.220E+00 0.000E+00 2.1 9 0E-02 CU-6 4 0.000E+00 2.3 8 0E+04 0.000E+00 6.010E+04 0.000E+00 2.030E+0 6 0.000E+00 1.120E+04 Z N-65 1.370E+0 9 4.370E+0 9 0.000E+00 2.920E+0 9 0.000E+00 2.7 5 0E+0 9 0.000E+00 1.970E+0 9 Z N-69 2.0 9 0E-12 4.000E-12 0.000E+00 2.600E-12 0.000E+00 6.010E-13 0.000E+00 2.7 8 0E-13 BR-8 3 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-8 4 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.2 6 0E-2 8 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 2.59 0E+0 9 0.000E+00 0.000E+00 0.000E+00 5.120E+0 8 0.000E+00 1.210E+0 9 RB-88 0.000E+00 2.140E-4 5 0.000E+00 0.000E+00 0.000E+00 2.96 0E-56 0.000E+00 1.140E-4 5 RB-89 0.000E+00 4.330E-5 3 0.000E+00 0.000E+00 0.000E+00 2.510E-66 0.000E+00 3.040E-5 3 SR-89 1.4 5 0E+0 9 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.330E+0 8 0.000E+00 4.1 6 0E+07 SR-9 0 4.68 0E+10 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.3 5 0E+0 9 0.000E+00 1.1 5 0E+10 SR-9 1 2.89 0E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.3 8 0E+0 5 0.000E+00 1.170E+03 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X G R i Adult Dose Factors for use in the Gaseous Dose Calculations Appendix G Ri Adult Cow Milk - Page 2 of 3 Agegroup: ADULT Pathway: Grs

/Cow/Mil k (CMIL K) Units: m 2*mrem/yr / µµµµCi/sec; mrem/yr / µµµµCi/m 3 (H-3) Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in Total Body SR-9 2 4.88 0E-01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 9.68 0E+00 0.000E+00 2.110E-02 Y-9 0 7.0 8 0E+01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 7.510E+0 5 0.000E+00 1.900E+00 Y-9 1 8.59 0E+03 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4.730E+0 6 0.000E+00 2.300E+02 Y-9 1M 5.98 0E-20 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.7 6 0E-1 9 0.000E+00 2.320E-21 Y-9 2 5.58 0E-0 5 0.000E+00 0.000E+00 0.000E+00 0.000E+00 9.770E-01 0.000E+00 1.630E-0 6 Y-9 3 2.230E-01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 7.0 9 0E+03 0.000E+00 6.170E-03 Z R-95 9.430E+02 3.030E+02 0.000E+00 4.7 5 0E+02 0.000E+00 9.59 0E+0 5 0.000E+00 2.0 5 0E+02 Z R-9 7 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 8.2 6 0E+04 4.59 0E+04 0.000E+00 4.540E+04 0.000E+00 2.7 9 0E+0 8 0.000E+00 2.470E+04 MO-99 0.000E+00 2.4 8 0E+07 0.000E+00 5.610E+07 0.000E+00 5.740E+07 0.000E+00 4.710E+0 6 T C-99 M 3.320E+00 9.3 8 0E+00 0.000E+00 1.420E+02 4.600E+00 5.55 0E+03 0.000E+00 1.200E+02 T C-101 2.59 0E-6 0 3.740E-6 0 0.000E+00 6.730E-59 1.910E-6 0 1.120E-71 0.000E+00 3.670E-59 RU-103 1.020E+03 0.000E+00 0.000E+00 3.89 0E+03 0.000E+00 1.1 9 0E+0 5 0.000E+00 4.3 9 0E+02 RU-10 5 8.570E-04 0.000E+00 0.000E+00 1.110E-02 0.000E+00 5.240E-01 0.000E+00 3.3 8 0E-04 RU-10 6 2.040E+04 0.000E+00 0.000E+00 3.940E+04 0.000E+00 1.320E+0 6 0.000E+00 2.58 0E+03 AG-110M 5.820E+07 5.3 9 0E+07 0.000E+00 1.0 6 0E+0 8 0.000E+00 2.200E+10 0.000E+00 3.200E+07 T E-12 5 M 1.630E+07 5.900E+0 6 4.900E+0 6 6.630E+07 0.000E+00 6.500E+07 0.000E+00 2.1 8 0E+0 6 T E-127 6.530E+02 2.340E+02 4.840E+02 2.66 0E+03 0.000E+00 5.1 5 0E+04 0.000E+00 1.410E+02 T E-127M 4.58 0E+07 1.640E+07 1.170E+07 1.86 0E+0 8 0.000E+00 1.540E+0 8 0.000E+00 5.58 0E+0 6 T E-12 9 2.830E-10 1.0 6 0E-10 2.170E-10 1.1 9 0E-0 9 0.000E+00 2.130E-10 0.000E+00 6.88 0E-11 T E-12 9 M 6.020E+07 2.2 5 0E+07 2.070E+07 2.510E+0 8 0.000E+00 3.030E+0 8 0.000E+00 9.530E+0 6 T E-131 3.600E-33 1.500E-33 2.96 0E-33 1.58 0E-32 0.000E+00 5.100E-34 0.000E+00 1.140E-33 T E-131M 3.610E+0 5 1.770E+0 5 2.800E+0 5 1.7 9 0E+0 6 0.000E+00 1.7 5 0E+07 0.000E+00 1.470E+0 5 T E-132 2.400E+0 6 1.55 0E+0 6 1.720E+0 6 1.500E+07 0.000E+00 7.3 5 0E+07 0.000E+00 1.4 6 0E+0 6 I-130 4.200E+0 5 1.240E+0 6 1.0 5 0E+0 8 1.930E+0 6 0.000E+00 1.070E+0 6 0.000E+00 4.89 0E+0 5 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X G R i Adult Dose Factors for use in the Gaseous Dose Calculations Appendix G Ri Adult Cow Milk - Page 3 of 3 Agegroup: ADULT Pathway: Grs

/Cow/Mil k (CMIL K) Units: m 2*mrem/yr / µµµµCi/sec; mrem/yr / µµµµCi/m 3 (H-3) Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in Total Body I-131 2.96 0E+0 8 4.230E+0 8 1.3 9 0E+11 7.2 6 0E+0 8 0.000E+00 1.120E+0 8 0.000E+00 2.430E+0 8 I-132 1.640E-01 4.3 9 0E-01 1.540E+01 7.000E-01 0.000E+00 8.2 5 0E-02 0.000E+00 1.540E-01 I-133 3.870E+0 6 6.730E+0 6 9.89 0E+0 8 1.170E+07 0.000E+00 6.0 5 0E+0 6 0.000E+00 2.0 5 0E+0 6 I-134 2.020E-12 5.4 8 0E-12 9.4 9 0E-11 8.710E-12 0.000E+00 4.770E-1 5 0.000E+00 1.96 0E-12 I-13 5 1.2 8 0E+04 3.3 6 0E+04 2.220E+0 6 5.3 9 0E+04 0.000E+00 3.800E+04 0.000E+00 1.240E+04 CS-134 5.65 0E+0 9 1.3 5 0E+10 0.000E+00 4.3 5 0E+0 9 1.4 5 0E+0 9 2.3 5 0E+0 8 0.000E+00 1.100E+10 CS-13 6 2.630E+0 8 1.040E+0 9 0.000E+00 5.7 8 0E+0 8 7.930E+07 1.1 8 0E+0 8 0.000E+00 7.4 8 0E+0 8 CS-137 7.3 8 0E+0 9 1.010E+10 0.000E+00 3.430E+0 9 1.140E+0 9 1.95 0E+0 8 0.000E+00 6.610E+0 9 CS-13 8 9.0 5 0E-24 1.7 9 0E-23 0.000E+00 1.310E-23 1.300E-24 7.620E-2 9 0.000E+00 8.85 0E-24 BA-13 9 4.420E-0 8 3.1 5 0E-11 0.000E+00 2.940E-11 1.7 9 0E-11 7.830E-0 8 0.000E+00 1.2 9 0E-0 9 BA-140 2.69 0E+07 3.3 8 0E+04 0.000E+00 1.1 5 0E+04 1.930E+04 5.530E+07 0.000E+00 1.7 6 0E+0 6 BA-141 4.0 9 0E-4 6 3.0 9 0E-4 9 0.000E+00 2.88 0E-4 9 1.7 6 0E-4 9 1.930E-55 0.000E+00 1.3 8 0E-47 BA-142 2.640E-8 0 2.720E-8 3 0.000E+00 2.300E-8 3 1.540E-8 3 3.720E-98 0.000E+00 1.66 0E-8 1 LA-140 4.510E+00 2.270E+00 0.000E+00 0.000E+00 0.000E+00 1.670E+0 5 0.000E+00 6.010E-01 LA-142 1.86 0E-11 8.4 6 0E-12 0.000E+00 0.000E+00 0.000E+00 6.170E-0 8 0.000E+00 2.110E-12 CE-141 4.840E+03 3.2 8 0E+03 0.000E+00 1.520E+03 0.000E+00 1.2 5 0E+07 0.000E+00 3.720E+02 CE-143 4.1 6 0E+01 3.070E+04 0.000E+00 1.3 5 0E+01 0.000E+00 1.1 5 0E+0 6 0.000E+00 3.400E+00 CE-144 3.58 0E+0 5 1.500E+0 5 0.000E+00 8.870E+04 0.000E+00 1.210E+0 8 0.000E+00 1.920E+04 PR-143 1.58 0E+02 6.330E+01 0.000E+00 3.66 0E+01 0.000E+00 6.920E+0 5 0.000E+00 7.830E+00 PR-144 5.870E-5 4 2.440E-5 4 0.000E+00 1.3 8 0E-5 4 0.000E+00 8.4 5 0E-6 1 0.000E+00 2.99 0E-55 N D-147 9.420E+01 1.0 9 0E+02 0.000E+00 6.3 6 0E+01 0.000E+00 5.220E+0 5 0.000E+00 6.510E+00 W-1 8 7 6.510E+03 5.4 5 0E+03 0.000E+00 0.000E+00 0.000E+00 1.7 8 0E+0 6 0.000E+00 1.900E+03 NP-23 9 3.670E+00 3.610E-01 0.000E+00 1.130E+00 0.000E+00 7.410E+04 0.000E+00 1.99 0E-01 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X G R i Adult Dose Factors for use in the Gaseous Dose Calculations Appendix G Ri Adult Goat Mil k - Page 1 of 3 Agegroup: ADULT Pathway: Grs

/Goat/Mil k (GMIL K) Units: m 2*mrem/yr / µµµµCi/sec; mrem/yr / µµµµCi/m 3 (H-3) Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in Total Body H-3 0.000E+00 1.56 0E+03 1.56 0E+03 1.56 0E+03 1.56 0E+03 1.56 0E+03 0.000E+00 1.56 0E+03 C-14 2.630E+0 8 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+0 5 2.930E+0 5 2.930E+0 5 2.930E+0 5 2.930E+0 5 2.930E+0 5 0.000E+00 2.930E+0 5 P-32 2.0 5 0E+10 1.2 8 0E+0 9 0.000E+00 0.000E+00 0.000E+00 2.310E+0 9 0.000E+00 7.930E+0 8 CR-5 1 0.000E+00 0.000E+00 2.0 5 0E+03 7.55 0E+02 4.55 0E+03 8.620E+0 5 0.000E+00 3.430E+03 MN-5 4 0.000E+00 1.010E+0 6 0.000E+00 3.000E+0 5 0.000E+00 3.0 9 0E+0 6 0.000E+00 1.930E+0 5 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-0 5 FE-55 3.2 6 0E+0 5 2.2 6 0E+0 5 0.000E+00 0.000E+00 1.2 6 0E+0 5 1.2 9 0E+0 5 0.000E+00 5.2 6 0E+04 FE-59 3.86 0E+0 5 9.070E+0 5 0.000E+00 0.000E+00 2.540E+0 5 3.020E+0 6 0.000E+00 3.4 8 0E+0 5 CO-58 0.000E+00 5.66 0E+0 5 0.000E+00 0.000E+00 0.000E+00 1.1 5 0E+07 0.000E+00 1.270E+0 6 CO-6 0 0.000E+00 1.970E+0 6 0.000E+00 0.000E+00 0.000E+00 3.700E+07 0.000E+00 4.340E+0 6 NI-6 3 8.070E+0 8 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 1.4 6 0E-01 0.000E+00 2.630E-03 CU-6 4 0.000E+00 2.66 0E+03 0.000E+00 6.700E+03 0.000E+00 2.2 6 0E+0 5 0.000E+00 1.2 5 0E+03 Z N-65 1.65 0E+0 8 5.240E+0 8 0.000E+00 3.500E+0 8 0.000E+00 3.300E+0 8 0.000E+00 2.370E+0 8 Z N-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-8 3 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.68 0E-02 0.000E+00 1.170E-02 BR-8 4 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.520E-2 9 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+0 8 0.000E+00 0.000E+00 0.000E+00 6.140E+07 0.000E+00 1.4 5 0E+0 8 RB-88 0.000E+00 2.570E-4 6 0.000E+00 0.000E+00 0.000E+00 3.55 0E-5 7 0.000E+00 1.3 6 0E-4 6 RB-89 0.000E+00 5.1 9 0E-5 4 0.000E+00 0.000E+00 0.000E+00 3.020E-6 7 0.000E+00 3.65 0E-5 4 SR-89 3.0 5 0E+0 9 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4.89 0E+0 8 0.000E+00 8.7 5 0E+07 SR-9 0 9.830E+10 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.840E+0 9 0.000E+00 2.410E+10 SR-9 1 6.070E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.89 0E+0 5 0.000E+00 2.4 5 0E+03 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X G R i Adult Dose Factors for use in the Gaseous Dose Calculations Appendix G Ri Adult Goat Mil k - Page 2 of 3 Agegroup: ADULT Pathway: Grs

/Goat/Mil k (GMIL K) Units: m 2*mrem/yr / µµµµCi/sec; mrem/yr / µµµµCi/m 3 (H-3) Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in Total Body SR-9 2 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-9 0 8.500E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 9.010E+04 0.000E+00 2.2 8 0E-01 Y-9 1 1.030E+03 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.670E+0 5 0.000E+00 2.7 6 0E+01 Y-9 1M 7.170E-21 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.110E-20 0.000E+00 2.7 8 0E-22 Y-9 2 6.69 0E-0 6 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.170E-01 0.000E+00 1.96 0E-07 Y-9 3 2.68 0E-02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 8.500E+02 0.000E+00 7.400E-04 Z R-95 1.130E+02 3.630E+01 0.000E+00 5.700E+01 0.000E+00 1.1 5 0E+0 5 0.000E+00 2.4 6 0E+01 Z R-9 7 5.200E-02 1.0 5 0E-02 0.000E+00 1.58 0E-02 0.000E+00 3.2 5 0E+03 0.000E+00 4.800E-03 NB-95 9.910E+03 5.510E+03 0.000E+00 5.4 5 0E+03 0.000E+00 3.340E+07 0.000E+00 2.96 0E+03 MO-99 0.000E+00 2.970E+0 6 0.000E+00 6.730E+0 6 0.000E+00 6.89 0E+0 6 0.000E+00 5.66 0E+0 5 T C-99 M 3.98 0E-01 1.130E+00 0.000E+00 1.710E+01 5.520E-01 6.66 0E+02 0.000E+00 1.430E+01 T C-101 3.110E-6 1 4.4 9 0E-6 1 0.000E+00 8.0 8 0E-6 0 2.2 9 0E-6 1 1.3 5 0E-72 0.000E+00 4.400E-6 0 RU-103 1.220E+02 0.000E+00 0.000E+00 4.66 0E+02 0.000E+00 1.430E+04 0.000E+00 5.2 6 0E+01 RU-10 5 1.030E-04 0.000E+00 0.000E+00 1.330E-03 0.000E+00 6.2 9 0E-02 0.000E+00 4.0 6 0E-0 5 RU-10 6 2.4 5 0E+03 0.000E+00 0.000E+00 4.730E+03 0.000E+00 1.58 0E+0 5 0.000E+00 3.100E+02 AG-110M 6.99 0E+0 6 6.4 6 0E+0 6 0.000E+00 1.270E+07 0.000E+00 2.640E+0 9 0.000E+00 3.840E+0 6 T E-12 5 M 1.95 0E+0 6 7.0 8 0E+0 5 5.88 0E+0 5 7.95 0E+0 6 0.000E+00 7.800E+0 6 0.000E+00 2.620E+0 5 T E-127 7.830E+01 2.810E+01 5.800E+01 3.1 9 0E+02 0.000E+00 6.1 8 0E+03 0.000E+00 1.700E+01 T E-127M 5.4 9 0E+0 6 1.96 0E+0 6 1.400E+0 6 2.230E+07 0.000E+00 1.840E+07 0.000E+00 6.69 0E+0 5 T E-12 9 3.3 9 0E-11 1.270E-11 2.600E-11 1.430E-10 0.000E+00 2.56 0E-11 0.000E+00 8.2 6 0E-12 T E-12 9 M 7.220E+0 6 2.69 0E+0 6 2.4 8 0E+0 6 3.020E+07 0.000E+00 3.640E+07 0.000E+00 1.140E+0 6 T E-131 4.320E-34 1.810E-34 3.55 0E-34 1.89 0E-33 0.000E+00 6.120E-3 5 0.000E+00 1.3 6 0E-34 T E-131M 4.330E+04 2.120E+04 3.3 6 0E+04 2.1 5 0E+0 5 0.000E+00 2.100E+0 6 0.000E+00 1.770E+04 T E-132 2.88 0E+0 5 1.86 0E+0 5 2.0 6 0E+0 5 1.800E+0 6 0.000E+00 8.820E+0 6 0.000E+00 1.7 5 0E+0 5 I-130 5.040E+0 5 1.4 9 0E+0 6 1.2 6 0E+0 8 2.320E+0 6 0.000E+00 1.2 8 0E+0 6 0.000E+00 5.870E+0 5 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X G R i Adult Dose Factors for use in the Gaseous Dose Calculations Appendix G Ri Adult Goat Mil k - Page 3 of 3 Agegroup: ADULT Pathway: Grs

/Goat/Mil k (GMIL K) Units: m 2*mrem/yr / µµµµCi/sec; mrem/yr / µµµµCi/m 3 (H-3) Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in Total Body I-131 3.55 0E+0 8 5.0 8 0E+0 8 1.670E+11 8.710E+0 8 0.000E+00 1.340E+0 8 0.000E+00 2.910E+0 8 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+0 6 8.0 8 0E+0 6 1.1 9 0E+0 9 1.410E+07 0.000E+00 7.2 6 0E+0 6 0.000E+00 2.4 6 0E+0 6 I-134 2.420E-12 6.570E-12 1.140E-10 1.0 5 0E-11 0.000E+00 5.730E-1 5 0.000E+00 2.3 5 0E-12 I-13 5 1.540E+04 4.030E+04 2.66 0E+0 6 6.470E+04 0.000E+00 4.56 0E+04 0.000E+00 1.4 9 0E+04 CS-134 1.700E+10 4.040E+10 0.000E+00 1.310E+10 4.340E+0 9 7.0 6 0E+0 8 0.000E+00 3.300E+10 CS-13 6 7.900E+0 8 3.120E+0 9 0.000E+00 1.730E+0 9 2.3 8 0E+0 8 3.540E+0 8 0.000E+00 2.240E+0 9 CS-137 2.210E+10 3.030E+10 0.000E+00 1.030E+10 3.420E+0 9 5.86 0E+0 8 0.000E+00 1.98 0E+10 CS-13 8 2.710E-23 5.3 6 0E-23 0.000E+00 3.940E-23 3.89 0E-24 2.2 9 0E-2 8 0.000E+00 2.65 0E-23 BA-13 9 5.300E-0 9 3.7 8 0E-12 0.000E+00 3.530E-12 2.140E-12 9.400E-0 9 0.000E+00 1.55 0E-10 BA-140 3.230E+0 6 4.0 5 0E+03 0.000E+00 1.3 8 0E+03 2.320E+03 6.640E+0 6 0.000E+00 2.110E+0 5 BA-141 4.910E-47 3.710E-5 0 0.000E+00 3.4 5 0E-5 0 2.110E-5 0 2.310E-56 0.000E+00 1.66 0E-4 8 BA-142 3.170E-8 1 3.2 6 0E-8 4 0.000E+00 2.7 5 0E-8 4 1.85 0E-8 4 0.000E+00 0.000E+00 2.000E-8 2 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-0 9 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+0 6 0.000E+00 4.4 6 0E+01 CE-143 4.99 0E+00 3.69 0E+03 0.000E+00 1.620E+00 0.000E+00 1.3 8 0E+0 5 0.000E+00 4.0 8 0E-01 CE-144 4.2 9 0E+04 1.7 9 0E+04 0.000E+00 1.0 6 0E+04 0.000E+00 1.4 5 0E+07 0.000E+00 2.300E+03 PR-143 1.89 0E+01 7.600E+00 0.000E+00 4.3 9 0E+00 0.000E+00 8.300E+04 0.000E+00 9.3 9 0E-01 PR-144 7.0 5 0E-55 2.930E-55 0.000E+00 1.65 0E-55 0.000E+00 1.010E-6 1 0.000E+00 3.58 0E-56 N D-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-1 8 7 7.820E+02 6.530E+02 0.000E+00 0.000E+00 0.000E+00 2.140E+0 5 0.000E+00 2.2 8 0E+02 NP-23 9 4.410E-01 4.330E-02 0.000E+00 1.3 5 0E-01 0.000E+00 8.89 0E+03 0.000E+00 2.3 9 0E-02 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X G R i Adult Dose Factors for use in the Gaseous Dose Calculations Appendix G Ri Adult Cow Meat - Page 1 of 3 Agegroup: ADULT Pathway: Grs

/Cow/Meat (CMEAT) Units: m 2*mrem/yr / µµµµCi/sec; mrem/yr / µµµµCi/m 3 (H-3) Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in Total Body H-3 0.000E+00 3.2 5 0E+02 3.2 5 0E+02 3.2 5 0E+02 3.2 5 0E+02 3.2 5 0E+02 0.000E+00 3.2 5 0E+02 C-14 2.410E+0 8 4.830E+07 4.830E+07 4.830E+07 4.830E+07 4.830E+07 0.000E+00 4.830E+07 NA-24 1.3 6 0E-03 1.3 6 0E-03 1.3 6 0E-03 1.3 6 0E-03 1.3 6 0E-03 1.3 6 0E-03 0.000E+00 1.3 6 0E-03 P-32 4.66 0E+0 9 2.900E+0 8 0.000E+00 0.000E+00 0.000E+00 5.240E+0 8 0.000E+00 1.800E+0 8 CR-5 1 0.000E+00 0.000E+00 4.210E+03 1.55 0E+03 9.3 5 0E+03 1.770E+0 6 0.000E+00 7.0 5 0E+03 MN-5 4 0.000E+00 9.1 8 0E+0 6 0.000E+00 2.730E+0 6 0.000E+00 2.810E+07 0.000E+00 1.7 5 0E+0 6 MN-56 0.000E+00 1.320E-5 3 0.000E+00 1.68 0E-5 3 0.000E+00 4.220E-5 2 0.000E+00 2.3 5 0E-5 4 FE-55 2.930E+0 8 2.030E+0 8 0.000E+00 0.000E+00 1.130E+0 8 1.1 6 0E+0 8 0.000E+00 4.720E+07 FE-59 2.66 0E+0 8 6.240E+0 8 0.000E+00 0.000E+00 1.740E+0 8 2.0 8 0E+0 9 0.000E+00 2.3 9 0E+0 8 CO-58 0.000E+00 1.820E+07 0.000E+00 0.000E+00 0.000E+00 3.69 0E+0 8 0.000E+00 4.0 9 0E+07 CO-6 0 0.000E+00 7.520E+07 0.000E+00 0.000E+00 0.000E+00 1.410E+0 9 0.000E+00 1.66 0E+0 8 NI-6 3 1.89 0E+10 1.310E+0 9 0.000E+00 0.000E+00 0.000E+00 2.730E+0 8 0.000E+00 6.330E+0 8 NI-65 2.2 5 0E-5 2 2.920E-5 3 0.000E+00 0.000E+00 0.000E+00 7.400E-5 2 0.000E+00 1.330E-5 3 CU-6 4 0.000E+00 2.710E-07 0.000E+00 6.830E-07 0.000E+00 2.310E-0 5 0.000E+00 1.270E-07 Z N-65 3.56 0E+0 8 1.130E+0 9 0.000E+00 7.570E+0 8 0.000E+00 7.130E+0 8 0.000E+00 5.120E+0 8 Z N-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-8 3 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 8.65 0E-5 7 0.000E+00 6.000E-5 7 BR-8 4 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+0 8 0.000E+00 0.000E+00 0.000E+00 9.600E+07 0.000E+00 2.270E+0 8 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+0 8 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4.840E+07 0.000E+00 8.66 0E+0 6 SR-9 0 1.240E+10 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.59 0E+0 8 0.000E+00 3.0 5 0E+0 9 SR-9 1 1.520E-10 0.000E+00 0.000E+00 0.000E+00 0.000E+00 7.240E-10 0.000E+00 6.140E-12 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X G R i Adult Dose Factors for use in the Gaseous Dose Calculations Appendix G Ri Adult Cow Meat - Page 2 of 3 Agegroup: ADULT Pathway: Grs

/Cow/Meat (CMEAT) Units: m 2*mrem/yr / µµµµCi/sec; mrem/yr / µµµµCi/m 3 (H-3) Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in Total Body SR-9 2 1.1 8 0E-4 9 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.340E-4 8 0.000E+00 5.100E-5 1 Y-9 0 1.0 8 0E+02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.140E+0 6 0.000E+00 2.89 0E+00 Y-9 1 1.130E+0 6 0.000E+00 0.000E+00 0.000E+00 0.000E+00 6.230E+0 8 0.000E+00 3.030E+04 Y-9 1M 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-9 2 1.520E-3 9 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.66 0E-3 5 0.000E+00 4.430E-41 Y-9 3 4.69 0E-12 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.4 9 0E-07 0.000E+00 1.300E-13 Z R-95 1.870E+0 6 6.010E+0 5 0.000E+00 9.420E+0 5 0.000E+00 1.900E+0 9 0.000E+00 4.070E+0 5 Z R-9 7 2.070E-0 5 4.170E-0 6 0.000E+00 6.300E-0 6 0.000E+00 1.2 9 0E+00 0.000E+00 1.910E-0 6 NB-95 2.300E+0 6 1.2 8 0E+0 6 0.000E+00 1.2 6 0E+0 6 0.000E+00 7.7 6 0E+0 9 0.000E+00 6.870E+0 5 MO-99 0.000E+00 1.000E+0 5 0.000E+00 2.2 6 0E+0 5 0.000E+00 2.320E+0 5 0.000E+00 1.900E+04 T C-99 M 4.4 5 0E-21 1.2 6 0E-20 0.000E+00 1.910E-1 9 6.1 5 0E-21 7.430E-1 8 0.000E+00 1.600E-1 9 T C-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 1.0 5 0E+0 8 0.000E+00 0.000E+00 4.010E+0 8 0.000E+00 1.230E+10 0.000E+00 4.530E+07 RU-10 5 5.7 8 0E-2 8 0.000E+00 0.000E+00 7.4 6 0E-27 0.000E+00 3.530E-2 5 0.000E+00 2.2 8 0E-2 8 RU-10 6 2.800E+0 9 0.000E+00 0.000E+00 5.400E+0 9 0.000E+00 1.810E+11 0.000E+00 3.540E+0 8 AG-110M 6.68 0E+0 6 6.1 8 0E+0 6 0.000E+00 1.220E+07 0.000E+00 2.520E+0 9 0.000E+00 3.670E+0 6 T E-12 5 M 3.59 0E+0 8 1.300E+0 8 1.0 8 0E+0 8 1.4 6 0E+0 9 0.000E+00 1.430E+0 9 0.000E+00 4.810E+07 T E-127 2.120E-10 7.610E-11 1.570E-10 8.640E-10 0.000E+00 1.670E-0 8 0.000E+00 4.59 0E-11 T E-127M 1.120E+0 9 3.99 0E+0 8 2.85 0E+0 8 4.530E+0 9 0.000E+00 3.740E+0 9 0.000E+00 1.3 6 0E+0 8 T E-12 9 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 T E-12 9 M 1.130E+0 9 4.230E+0 8 3.900E+0 8 4.730E+0 9 0.000E+00 5.710E+0 9 0.000E+00 1.7 9 0E+0 8 T E-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 T E-131M 4.510E+02 2.210E+02 3.4 9 0E+02 2.230E+03 0.000E+00 2.1 9 0E+04 0.000E+00 1.840E+02 T E-132 1.420E+0 6 9.1 8 0E+0 5 1.010E+0 6 8.840E+0 6 0.000E+00 4.340E+07 0.000E+00 8.620E+0 5 I-130 2.110E-0 6 6.220E-0 6 5.270E-04 9.700E-0 6 0.000E+00 5.3 5 0E-0 6 0.000E+00 2.4 5 0E-0 6 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X G R i Adult Dose Factors for use in the Gaseous Dose Calculations Appendix G Ri Adult Cow Meat - Page 3 of 3 Agegroup: ADULT Pathway: Grs

/Cow/Meat (CMEAT) Units: m 2*mrem/yr / µµµµCi/sec; mrem/yr / µµµµCi/m 3 (H-3) Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in Total Body I-131 1.070E+07 1.540E+07 5.030E+0 9 2.630E+07 0.000E+00 4.0 5 0E+0 6 0.000E+00 8.800E+0 6 I-132 6.970E-59 1.86 0E-58 6.530E-5 7 2.970E-58 0.000E+00 3.500E-59 0.000E+00 6.530E-59 I-133 3.65 0E-01 6.3 5 0E-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-13 5 4.420E-17 1.1 6 0E-1 6 7.640E-1 5 1.86 0E-1 6 0.000E+00 1.310E-1 6 0.000E+00 4.270E-17 CS-134 6.58 0E+0 8 1.56 0E+0 9 0.000E+00 5.0 6 0E+0 8 1.68 0E+0 8 2.740E+07 0.000E+00 1.2 8 0E+0 9 CS-13 6 1.210E+07 4.7 6 0E+07 0.000E+00 2.65 0E+07 3.630E+0 6 5.410E+0 6 0.000E+00 3.420E+07 CS-137 8.720E+0 8 1.1 9 0E+0 9 0.000E+00 4.0 5 0E+0 8 1.3 5 0E+0 8 2.310E+07 0.000E+00 7.810E+0 8 CS-13 8 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-13 9 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 1.88 0E+0 6 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-9 2 1.58 0E-9 2 0.000E+00 0.000E+00 0.000E+00 1.1 5 0E-88 0.000E+00 3.940E-9 3 CE-141 1.400E+04 9.500E+03 0.000E+00 4.410E+03 0.000E+00 3.630E+07 0.000E+00 1.0 8 0E+03 CE-143 2.010E-02 1.4 8 0E+01 0.000E+00 6.530E-03 0.000E+00 5.55 0E+02 0.000E+00 1.640E-03 CE-144 1.4 6 0E+0 6 6.0 9 0E+0 5 0.000E+00 3.610E+0 5 0.000E+00 4.930E+0 8 0.000E+00 7.830E+04 PR-143 2.100E+04 8.410E+03 0.000E+00 4.85 0E+03 0.000E+00 9.1 8 0E+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 N D-147 7.070E+03 8.170E+03 0.000E+00 4.7 8 0E+03 0.000E+00 3.920E+07 0.000E+00 4.89 0E+02 W-1 8 7 2.070E-02 1.730E-02 0.000E+00 0.000E+00 0.000E+00 5.66 0E+00 0.000E+00 6.040E-03 NP-23 9 2.59 0E-01 2.55 0E-02 0.000E+00 7.95 0E-02 0.000E+00 5.230E+03 0.000E+00 1.400E-02 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X G R i Adult Dose Factors for use in the Gaseous Dose Calculations Appendix G Ri Adult Vegetation - Page 1 of 3 Agegroup: ADULT Pathway: Vegetation (VEG) Units: m 2*mrem/yr / µµµµCi/sec; mrem/yr / µµµµCi/m 3 (H-3) Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in Total Body H-3 0.000E+00 2.2 6 0E+03 2.2 6 0E+03 2.2 6 0E+03 2.2 6 0E+03 2.2 6 0E+03 0.000E+00 2.2 6 0E+03 C-14 2.2 8 0E+0 8 4.55 0E+07 4.55 0E+07 4.55 0E+07 4.55 0E+07 4.55 0E+07 0.000E+00 4.55 0E+07 NA-24 2.69 0E+0 5 2.69 0E+0 5 2.69 0E+0 5 2.69 0E+0 5 2.69 0E+0 5 2.69 0E+0 5 0.000E+00 2.69 0E+0 5 P-32 1.400E+0 9 8.730E+07 0.000E+00 0.000E+00 0.000E+00 1.58 0E+0 8 0.000E+00 5.430E+07 CR-5 1 0.000E+00 0.000E+00 2.7 8 0E+04 1.020E+04 6.1 6 0E+04 1.170E+07 0.000E+00 4.640E+04 MN-5 4 0.000E+00 3.130E+0 8 0.000E+00 9.310E+07 0.000E+00 9.59 0E+0 8 0.000E+00 5.970E+07 MN-56 0.000E+00 1.58 0E+01 0.000E+00 2.000E+01 0.000E+00 5.040E+02 0.000E+00 2.800E+00 FE-55 2.100E+0 8 1.4 5 0E+0 8 0.000E+00 0.000E+00 8.0 8 0E+07 8.310E+07 0.000E+00 3.3 8 0E+07 FE-59 1.2 6 0E+0 8 2.96 0E+0 8 0.000E+00 0.000E+00 8.2 8 0E+07 9.88 0E+0 8 0.000E+00 1.140E+0 8 CO-58 0.000E+00 3.070E+07 0.000E+00 0.000E+00 0.000E+00 6.230E+0 8 0.000E+00 6.89 0E+07 CO-6 0 0.000E+00 1.670E+0 8 0.000E+00 0.000E+00 0.000E+00 3.140E+0 9 0.000E+00 3.69 0E+0 8 NI-6 3 1.040E+10 7.210E+0 8 0.000E+00 0.000E+00 0.000E+00 1.500E+0 8 0.000E+00 3.4 9 0E+0 8 NI-65 6.1 5 0E+01 7.99 0E+00 0.000E+00 0.000E+00 0.000E+00 2.030E+02 0.000E+00 3.640E+00 CU-6 4 0.000E+00 9.200E+03 0.000E+00 2.320E+04 0.000E+00 7.840E+0 5 0.000E+00 4.320E+03 Z N-65 3.170E+0 8 1.010E+0 9 0.000E+00 6.7 5 0E+0 8 0.000E+00 6.3 6 0E+0 8 0.000E+00 4.56 0E+0 8 Z N-69 5.4 9 0E-0 6 1.0 5 0E-0 5 0.000E+00 6.830E-0 6 0.000E+00 1.58 0E-0 6 0.000E+00 7.310E-07 BR-8 3 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-8 4 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.940E-1 6 0.000E+00 2.4 8 0E-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 2.1 9 0E+0 8 0.000E+00 0.000E+00 0.000E+00 4.330E+07 0.000E+00 1.020E+0 8 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 3.89 0E-2 6 0.000E+00 0.000E+00 0.000E+00 2.2 6 0E-3 9 0.000E+00 2.730E-2 6 SR-89 9.970E+0 9 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.600E+0 9 0.000E+00 2.86 0E+0 8 SR-9 0 6.0 5 0E+11 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.7 5 0E+10 0.000E+00 1.4 8 0E+11 SR-9 1 3.0 5 0E+0 5 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.4 5 0E+0 6 0.000E+00 1.230E+04 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X G R i Adult Dose Factors for use in the Gaseous Dose Calculations Appendix G Ri Adult Vegetation - Page 2 of 3 Agegroup: ADULT Pathway: Vegetation (VEG) Units: m 2*mrem/yr / µµµµCi/sec; mrem/yr / µµµµCi/m 3 (H-3) Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in Total Body SR-9 2 4.270E+02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 8.4 5 0E+03 0.000E+00 1.85 0E+01 Y-9 0 1.330E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.410E+0 8 0.000E+00 3.570E+02 Y-9 1 5.110E+0 6 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.810E+0 9 0.000E+00 1.370E+0 5 Y-9 1M 5.220E-0 9 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.530E-0 8 0.000E+00 2.020E-10 Y-9 2 9.1 5 0E-01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.600E+04 0.000E+00 2.68 0E-02 Y-9 3 1.700E+02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.3 8 0E+0 6 0.000E+00 4.68 0E+00 Z R-95 1.170E+0 6 3.770E+0 5 0.000E+00 5.910E+0 5 0.000E+00 1.1 9 0E+0 9 0.000E+00 2.55 0E+0 5 Z R-9 7 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+0 5 7.920E+04 0.000E+00 7.830E+04 0.000E+00 4.810E+0 8 0.000E+00 4.2 6 0E+04 MO-99 0.000E+00 6.1 5 0E+0 6 0.000E+00 1.3 9 0E+07 0.000E+00 1.430E+07 0.000E+00 1.170E+0 6 T C-99 M 3.100E+00 8.770E+00 0.000E+00 1.330E+02 4.300E+00 5.1 9 0E+03 0.000E+00 1.120E+02 T C-101 8.220E-31 1.1 8 0E-30 0.000E+00 2.130E-2 9 6.0 5 0E-31 3.56 0E-42 0.000E+00 1.1 6 0E-2 9 RU-103 4.770E+0 6 0.000E+00 0.000E+00 1.820E+07 0.000E+00 5.570E+0 8 0.000E+00 2.0 6 0E+0 6 RU-10 5 5.3 9 0E+01 0.000E+00 0.000E+00 6.96 0E+02 0.000E+00 3.2 9 0E+04 0.000E+00 2.130E+01 RU-10 6 1.930E+0 8 0.000E+00 0.000E+00 3.720E+0 8 0.000E+00 1.2 5 0E+10 0.000E+00 2.440E+07 AG-110M 1.0 5 0E+07 9.7 5 0E+0 6 0.000E+00 1.920E+07 0.000E+00 3.98 0E+0 9 0.000E+00 5.7 9 0E+0 6 T E-12 5 M 9.66 0E+07 3.500E+07 2.900E+07 3.930E+0 8 0.000E+00 3.86 0E+0 8 0.000E+00 1.2 9 0E+07 T E-127 5.66 0E+03 2.030E+03 4.1 9 0E+03 2.310E+04 0.000E+00 4.470E+0 5 0.000E+00 1.220E+03 T E-127M 3.4 9 0E+0 8 1.2 5 0E+0 8 8.920E+07 1.420E+0 9 0.000E+00 1.170E+0 9 0.000E+00 4.2 6 0E+07 T E-12 9 7.630E-04 2.870E-04 5.85 0E-04 3.210E-03 0.000E+00 5.7 6 0E-04 0.000E+00 1.86 0E-04 T E-12 9 M 2.510E+0 8 9.3 8 0E+07 8.630E+07 1.0 5 0E+0 9 0.000E+00 1.270E+0 9 0.000E+00 3.98 0E+07 T E-131 1.500E-1 5 6.270E-1 6 1.230E-1 5 6.570E-1 5 0.000E+00 2.130E-1 6 0.000E+00 4.740E-1 6 T E-131M 9.120E+0 5 4.4 6 0E+0 5 7.0 6 0E+0 5 4.520E+0 6 0.000E+00 4.430E+07 0.000E+00 3.720E+0 5 T E-132 4.300E+0 6 2.7 8 0E+0 6 3.070E+0 6 2.68 0E+07 0.000E+00 1.320E+0 8 0.000E+00 2.610E+0 6 I-130 3.920E+0 5 1.1 6 0E+0 6 9.810E+07 1.810E+0 6 0.000E+00 9.96 0E+0 5 0.000E+00 4.570E+0 5 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X G R i Adult Dose Factors for use in the Gaseous Dose Calculations Appendix G Ri Adult Vegetation - Page 3 of 3 Agegroup: ADULT Pathway: Vegetation (VEG) Units: m 2*mrem/yr / µµµµCi/sec; mrem/yr / µµµµCi/m 3 (H-3) Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in Total Body I-131 8.0 8 0E+07 1.1 6 0E+0 8 3.7 9 0E+10 1.98 0E+0 8 0.000E+00 3.0 5 0E+07 0.000E+00 6.620E+07 I-132 5.7 6 0E+01 1.540E+02 5.3 9 0E+03 2.4 5 0E+02 0.000E+00 2.89 0E+01 0.000E+00 5.3 9 0E+01 I-133 2.0 9 0E+0 6 3.630E+0 6 5.330E+0 8 6.330E+0 6 0.000E+00 3.2 6 0E+0 6 0.000E+00 1.110E+0 6 I-134 9.65 0E-0 5 2.620E-04 4.540E-03 4.170E-04 0.000E+00 2.2 9 0E-07 0.000E+00 9.3 8 0E-0 5 I-13 5 3.900E+04 1.020E+0 5 6.730E+0 6 1.640E+0 5 0.000E+00 1.1 5 0E+0 5 0.000E+00 3.770E+04 CS-134 4.670E+0 9 1.110E+10 0.000E+00 3.59 0E+0 9 1.1 9 0E+0 9 1.940E+0 8 0.000E+00 9.0 8 0E+0 9 CS-13 6 4.270E+07 1.68 0E+0 8 0.000E+00 9.3 8 0E+07 1.2 9 0E+07 1.910E+07 0.000E+00 1.210E+0 8 CS-137 6.3 6 0E+0 9 8.700E+0 9 0.000E+00 2.95 0E+0 9 9.810E+0 8 1.68 0E+0 8 0.000E+00 5.700E+0 9 CS-13 8 3.920E-11 7.730E-11 0.000E+00 5.68 0E-11 5.610E-12 3.300E-1 6 0.000E+00 3.830E-11 BA-13 9 2.86 0E-02 2.030E-0 5 0.000E+00 1.900E-0 5 1.1 5 0E-0 5 5.0 6 0E-02 0.000E+00 8.3 6 0E-04 BA-140 1.2 8 0E+0 8 1.610E+0 5 0.000E+00 5.4 9 0E+04 9.240E+04 2.65 0E+0 8 0.000E+00 8.420E+0 6 BA-141 1.1 5 0E-21 8.700E-2 5 0.000E+00 8.0 9 0E-2 5 4.940E-2 5 5.430E-31 0.000E+00 3.89 0E-23 BA-142 5.96 0E-3 9 6.120E-42 0.000E+00 5.170E-42 3.470E-42 8.3 9 0E-5 7 0.000E+00 3.7 5 0E-40 LA-140 1.98 0E+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 9.1 9 0E-0 5 0.000E+00 0.000E+00 0.000E+00 6.710E-01 0.000E+00 2.2 9 0E-0 5 CE-141 1.970E+0 5 1.330E+0 5 0.000E+00 6.1 9 0E+04 0.000E+00 5.100E+0 8 0.000E+00 1.510E+04 CE-143 9.98 0E+02 7.3 8 0E+0 5 0.000E+00 3.2 5 0E+02 0.000E+00 2.7 6 0E+07 0.000E+00 8.1 6 0E+01 CE-144 3.2 9 0E+07 1.3 8 0E+07 0.000E+00 8.1 6 0E+0 6 0.000E+00 1.110E+10 0.000E+00 1.770E+0 6 PR-143 6.2 6 0E+04 2.510E+04 0.000E+00 1.4 5 0E+04 0.000E+00 2.740E+0 8 0.000E+00 3.100E+03 PR-144 3.0 9 0E-2 6 1.2 8 0E-2 6 0.000E+00 7.230E-27 0.000E+00 4.440E-33 0.000E+00 1.570E-27 N D-147 3.330E+04 3.85 0E+04 0.000E+00 2.2 5 0E+04 0.000E+00 1.85 0E+0 8 0.000E+00 2.310E+03 W-1 8 7 3.800E+04 3.1 8 0E+04 0.000E+00 0.000E+00 0.000E+00 1.040E+07 0.000E+00 1.110E+04 NP-23 9 1.430E+03 1.400E+02 0.000E+00 4.3 8 0E+02 0.000E+00 2.88 0E+07 0.000E+00 7.740E+01 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X G R i Adult Dose Factors for use in the Gaseous Dose Calculations Appendix G Ri Adult Inhalation - Page 1 of 3 Agegroup:

ADULT Pathway: Inhalation (INHL) Units: mrem/yr / µµµµCi/m 3 Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in Total Body H-3 0.000E+00 1.2 6 0E+03 1.2 6 0E+03 1.2 6 0E+03 1.2 6 0E+03 1.2 6 0E+03 0.000E+00 1.2 6 0E+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+0 6 7.710E+04 0.000E+00 0.000E+00 0.000E+00 8.640E+04 0.000E+00 5.010E+04 CR-5 1 0.000E+00 0.000E+00 5.95 0E+01 2.2 8 0E+01 1.440E+04 3.320E+03 0.000E+00 1.000E+02 MN-5 4 0.000E+00 3.96 0E+04 0.000E+00 9.840E+03 1.400E+0 6 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 2.4 6 0E+04 1.700E+04 0.000E+00 0.000E+00 7.210E+04 6.030E+03 0.000E+00 3.940E+03 FE-59 1.1 8 0E+04 2.7 8 0E+04 0.000E+00 0.000E+00 1.020E+0 6 1.88 0E+0 5 0.000E+00 1.0 6 0E+04 CO-58 0.000E+00 1.58 0E+03 0.000E+00 0.000E+00 9.2 8 0E+0 5 1.0 6 0E+0 5 0.000E+00 2.070E+03 CO-6 0 0.000E+00 1.1 5 0E+04 0.000E+00 0.000E+00 5.970E+0 6 2.85 0E+0 5 0.000E+00 1.4 8 0E+04 NI-6 3 4.320E+0 5 3.140E+04 0.000E+00 0.000E+00 1.7 8 0E+0 5 1.340E+04 0.000E+00 1.4 5 0E+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-6 4 0.000E+00 1.4 6 0E+00 0.000E+00 4.620E+00 6.7 8 0E+03 4.900E+04 0.000E+00 6.1 5 0E-01 Z N-65 3.240E+04 1.030E+0 5 0.000E+00 6.900E+04 8.640E+0 5 5.340E+04 0.000E+00 4.66 0E+04 Z N-69 3.3 8 0E-02 6.510E-02 0.000E+00 4.220E-02 9.200E+02 1.630E+01 0.000E+00 4.520E-03 BR-8 3 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-8 4 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 1.2 8 0E+01 RB-86 0.000E+00 1.3 5 0E+0 5 0.000E+00 0.000E+00 0.000E+00 1.66 0E+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-0 9 0.000E+00 1.930E+02 RB-89 0.000E+00 2.56 0E+02 0.000E+00 0.000E+00 0.000E+00 9.2 8 0E-12 0.000E+00 1.700E+02 SR-89 3.040E+0 5 0.000E+00 0.000E+00 0.000E+00 1.400E+0 6 3.500E+0 5 0.000E+00 8.720E+03 SR-9 0 9.920E+07 0.000E+00 0.000E+00 0.000E+00 9.600E+0 6 7.220E+0 5 0.000E+00 6.100E+0 6 SR-9 1 6.1 9 0E+01 0.000E+00 0.000E+00 0.000E+00 3.65 0E+04 1.910E+0 5 0.000E+00 2.500E+00 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X G R i Adult Dose Factors for use in the Gaseous Dose Calculations Appendix G Ri Adult Inhalation - Page 2 of 3 Agegroup:

ADULT Pathway: Inhalation (INHL) Units: mrem/yr / µµµµCi/m 3 Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in Total Body SR-9 2 6.740E+00 0.000E+00 0.000E+00 0.000E+00 1.65 0E+04 4.300E+04 0.000E+00 2.910E-01 Y-9 0 2.0 9 0E+03 0.000E+00 0.000E+00 0.000E+00 1.700E+0 5 5.0 6 0E+0 5 0.000E+00 5.610E+01 Y-9 1 4.620E+0 5 0.000E+00 0.000E+00 0.000E+00 1.700E+0 6 3.85 0E+0 5 0.000E+00 1.240E+04 Y-9 1M 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-9 2 1.030E+01 0.000E+00 0.000E+00 0.000E+00 1.570E+04 7.3 5 0E+04 0.000E+00 3.020E-01 Y-9 3 9.440E+01 0.000E+00 0.000E+00 0.000E+00 4.85 0E+04 4.220E+0 5 0.000E+00 2.610E+00 Z R-95 1.070E+0 5 3.440E+04 0.000E+00 5.420E+04 1.770E+0 6 1.500E+0 5 0.000E+00 2.330E+04 Z R-9 7 9.68 0E+01 1.96 0E+01 0.000E+00 2.970E+01 7.870E+04 5.230E+0 5 0.000E+00 9.040E+00 NB-95 1.410E+04 7.820E+03 0.000E+00 7.740E+03 5.0 5 0E+0 5 1.040E+0 5 0.000E+00 4.210E+03 MO-99 0.000E+00 1.210E+02 0.000E+00 2.910E+02 9.120E+04 2.4 8 0E+0 5 0.000E+00 2.300E+01 T C-99 M 1.030E-03 2.910E-03 0.000E+00 4.420E-02 7.640E+02 4.1 6 0E+03 0.000E+00 3.700E-02 T C-101 4.1 8 0E-0 5 6.020E-0 5 0.000E+00 1.0 8 0E-03 3.99 0E+02 1.0 9 0E-11 0.000E+00 5.900E-04 RU-103 1.530E+03 0.000E+00 0.000E+00 5.830E+03 5.0 5 0E+0 5 1.100E+0 5 0.000E+00 6.58 0E+02 RU-10 5 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-10 6 6.910E+04 0.000E+00 0.000E+00 1.340E+0 5 9.3 6 0E+0 6 9.120E+0 5 0.000E+00 8.720E+03 AG-110M 1.0 8 0E+04 1.000E+04 0.000E+00 1.970E+04 4.630E+0 6 3.020E+0 5 0.000E+00 5.940E+03 T E-12 5 M 3.420E+03 1.58 0E+03 1.0 5 0E+03 1.240E+04 3.140E+0 5 7.0 6 0E+04 0.000E+00 4.670E+02 T E-127 1.400E+00 6.420E-01 1.0 6 0E+00 5.100E+00 6.510E+03 5.740E+04 0.000E+00 3.100E-01 T E-127M 1.2 6 0E+04 5.770E+03 3.2 9 0E+03 4.58 0E+04 9.600E+0 5 1.500E+0 5 0.000E+00 1.570E+03 T E-12 9 4.98 0E-02 2.3 9 0E-02 3.900E-02 1.870E-01 1.940E+03 1.570E+02 0.000E+00 1.240E-02 T E-12 9 M 9.7 6 0E+03 4.670E+03 3.440E+03 3.66 0E+04 1.1 6 0E+0 6 3.830E+0 5 0.000E+00 1.58 0E+03 T E-131 1.110E-02 5.95 0E-03 9.3 6 0E-03 4.370E-02 1.3 9 0E+03 1.840E+01 0.000E+00 3.59 0E-03 T E-131M 6.99 0E+01 4.3 6 0E+01 5.500E+01 3.0 9 0E+02 1.4 6 0E+0 5 5.56 0E+0 5 0.000E+00 2.900E+01 T E-132 2.600E+02 2.1 5 0E+02 1.900E+02 1.4 6 0E+03 2.88 0E+0 5 5.100E+0 5 0.000E+00 1.620E+02 I-130 4.58 0E+03 1.340E+04 1.140E+0 6 2.0 9 0E+04 0.000E+00 7.69 0E+03 0.000E+00 5.2 8 0E+03 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X G R i Adult Dose Factors for use in the Gaseous Dose Calculations Appendix G Ri Adult Inhalation - Page 3 of 3 Agegroup:

ADULT Pathway: Inhalation (INHL) Units: mrem/yr / µµµµCi/m 3 Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in Total Body I-131 2.520E+04 3.58 0E+04 1.1 9 0E+07 6.130E+04 0.000E+00 6.2 8 0E+03 0.000E+00 2.0 5 0E+04 I-132 1.1 6 0E+03 3.2 6 0E+03 1.140E+0 5 5.1 8 0E+03 0.000E+00 4.0 6 0E+02 0.000E+00 1.1 6 0E+03 I-133 8.640E+03 1.4 8 0E+04 2.1 5 0E+0 6 2.58 0E+04 0.000E+00 8.88 0E+03 0.000E+00 4.520E+03 I-134 6.440E+02 1.730E+03 2.98 0E+04 2.7 5 0E+03 0.000E+00 1.010E+00 0.000E+00 6.1 5 0E+02 I-13 5 2.68 0E+03 6.98 0E+03 4.4 8 0E+0 5 1.110E+04 0.000E+00 5.2 5 0E+03 0.000E+00 2.570E+03 CS-134 3.730E+0 5 8.4 8 0E+0 5 0.000E+00 2.870E+0 5 9.7 6 0E+04 1.040E+04 0.000E+00 7.2 8 0E+0 5 CS-13 6 3.900E+04 1.4 6 0E+0 5 0.000E+00 8.56 0E+04 1.200E+04 1.170E+04 0.000E+00 1.100E+0 5 CS-137 4.7 8 0E+0 5 6.210E+0 5 0.000E+00 2.220E+0 5 7.520E+04 8.400E+03 0.000E+00 4.2 8 0E+0 5 CS-13 8 3.310E+02 6.210E+02 0.000E+00 4.800E+02 4.86 0E+01 1.86 0E-03 0.000E+00 3.240E+02 BA-13 9 9.3 6 0E-01 6.66 0E-04 0.000E+00 6.220E-04 3.7 6 0E+03 8.96 0E+02 0.000E+00 2.740E-02 BA-140 3.900E+04 4.900E+01 0.000E+00 1.670E+01 1.270E+0 6 2.1 8 0E+0 5 0.000E+00 2.570E+03 BA-141 1.000E-01 7.530E-0 5 0.000E+00 7.000E-0 5 1.940E+03 1.1 6 0E-07 0.000E+00 3.3 6 0E-03 BA-142 2.630E-02 2.700E-0 5 0.000E+00 2.2 9 0E-0 5 1.1 9 0E+03 1.570E-1 6 0.000E+00 1.66 0E-03 LA-140 3.440E+02 1.740E+02 0.000E+00 0.000E+00 1.3 6 0E+0 5 4.58 0E+0 5 0.000E+00 4.58 0E+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 1.99 0E+04 1.3 5 0E+04 0.000E+00 6.2 6 0E+03 3.620E+0 5 1.200E+0 5 0.000E+00 1.530E+03 CE-143 1.86 0E+02 1.3 8 0E+02 0.000E+00 6.0 8 0E+01 7.98 0E+04 2.2 6 0E+0 5 0.000E+00 1.530E+01 CE-144 3.430E+0 6 1.430E+0 6 0.000E+00 8.4 8 0E+0 5 7.7 8 0E+0 6 8.1 6 0E+0 5 0.000E+00 1.840E+0 5 PR-143 9.3 6 0E+03 3.7 5 0E+03 0.000E+00 2.1 6 0E+03 2.810E+0 5 2.000E+0 5 0.000E+00 4.640E+02 PR-144 3.010E-02 1.2 5 0E-02 0.000E+00 7.0 5 0E-03 1.020E+03 2.1 5 0E-0 8 0.000E+00 1.530E-03 N D-147 5.270E+03 6.100E+03 0.000E+00 3.56 0E+03 2.210E+0 5 1.730E+0 5 0.000E+00 3.65 0E+02 W-1 8 7 8.4 8 0E+00 7.0 8 0E+00 0.000E+00 0.000E+00 2.900E+04 1.55 0E+0 5 0.000E+00 2.4 8 0E+00 NP-23 9 2.300E+02 2.2 6 0E+01 0.000E+00 7.000E+01 3.7 6 0E+04 1.1 9 0E+0 5 0.000E+00 1.240E+01 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X G R i Adult Dose Factors for use in the Gaseous Dose Calculations Appendix G Ri Adult Ground Plane Deposition - Page 1 of 3 Agegroup:

ADULT Pathway: Ground Plane Deposition (GPD) Units: m 2*mrem/yr / µµµµCi/sec Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in 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 1.1 9 0E+07 1.1 9 0E+07 1.1 9 0E+07 1.1 9 0E+07 1.1 9 0E+07 1.1 9 0E+07 1.3 9 0E+07 1.1 9 0E+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-5 1 4.66 0E+0 6 4.66 0E+0 6 4.66 0E+0 6 4.66 0E+0 6 4.66 0E+0 6 4.66 0E+0 6 5.510E+0 6 4.66 0E+0 6 MN-5 4 1.3 9 0E+0 9 1.3 9 0E+0 9 1.3 9 0E+0 9 1.3 9 0E+0 9 1.3 9 0E+0 9 1.3 9 0E+0 9 1.630E+0 9 1.3 9 0E+0 9 MN-56 9.020E+0 5 9.020E+0 5 9.020E+0 5 9.020E+0 5 9.020E+0 5 9.020E+0 5 1.070E+0 6 9.020E+0 5 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+0 8 2.730E+0 8 2.730E+0 8 2.730E+0 8 2.730E+0 8 2.730E+0 8 3.210E+0 8 2.730E+0 8 CO-58 3.7 9 0E+0 8 3.7 9 0E+0 8 3.7 9 0E+0 8 3.7 9 0E+0 8 3.7 9 0E+0 8 3.7 9 0E+0 8 4.440E+0 8 3.7 9 0E+0 8 CO-6 0 2.1 5 0E+10 2.1 5 0E+10 2.1 5 0E+10 2.1 5 0E+10 2.1 5 0E+10 2.1 5 0E+10 2.530E+10 2.1 5 0E+10 NI-6 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 NI-65 2.970E+0 5 2.970E+0 5 2.970E+0 5 2.970E+0 5 2.970E+0 5 2.970E+0 5 3.4 5 0E+0 5 2.970E+0 5 CU-6 4 6.070E+0 5 6.070E+0 5 6.070E+0 5 6.070E+0 5 6.070E+0 5 6.070E+0 5 6.88 0E+0 5 6.070E+0 5 Z N-65 7.470E+0 8 7.470E+0 8 7.470E+0 8 7.470E+0 8 7.470E+0 8 7.470E+0 8 8.59 0E+0 8 7.470E+0 8 Z N-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-8 3 4.870E+03 4.870E+03 4.870E+03 4.870E+03 4.870E+03 4.870E+03 7.0 8 0E+03 4.870E+03 BR-8 4 2.030E+0 5 2.030E+0 5 2.030E+0 5 2.030E+0 5 2.030E+0 5 2.030E+0 5 2.3 6 0E+0 5 2.030E+0 5 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 8.99 0E+0 6 8.99 0E+0 6 8.99 0E+0 6 8.99 0E+0 6 8.99 0E+0 6 8.99 0E+0 6 1.030E+07 8.99 0E+0 6 RB-88 3.310E+04 3.310E+04 3.310E+04 3.310E+04 3.310E+04 3.310E+04 3.7 8 0E+04 3.310E+04 RB-89 1.230E+0 5 1.230E+0 5 1.230E+0 5 1.230E+0 5 1.230E+0 5 1.230E+0 5 1.4 8 0E+0 5 1.230E+0 5 SR-89 2.1 6 0E+04 2.1 6 0E+04 2.1 6 0E+04 2.1 6 0E+04 2.1 6 0E+04 2.1 6 0E+04 2.510E+04 2.1 6 0E+04 SR-9 0 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-9 1 2.1 5 0E+0 6 2.1 5 0E+0 6 2.1 5 0E+0 6 2.1 5 0E+0 6 2.1 5 0E+0 6 2.1 5 0E+0 6 2.510E+0 6 2.1 5 0E+0 6 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X G R i Adult Dose Factors for use in the Gaseous Dose Calculations Appendix G Ri Adult Ground Plane Deposition - Page 2 of 3 Agegroup:

ADULT Pathway: Ground Plane Deposition (GPD) Units: m 2*mrem/yr / µµµµCi/sec Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in Total Body SR-9 2 7.770E+0 5 7.770E+0 5 7.770E+0 5 7.770E+0 5 7.770E+0 5 7.770E+0 5 8.630E+0 5 7.770E+0 5 Y-9 0 4.4 9 0E+03 4.4 9 0E+03 4.4 9 0E+03 4.4 9 0E+03 4.4 9 0E+03 4.4 9 0E+03 5.310E+03 4.4 9 0E+03 Y-9 1 1.070E+0 6 1.070E+0 6 1.070E+0 6 1.070E+0 6 1.070E+0 6 1.070E+0 6 1.210E+0 6 1.070E+0 6 Y-9 1M 1.000E+0 5 1.000E+0 5 1.000E+0 5 1.000E+0 5 1.000E+0 5 1.000E+0 5 1.1 6 0E+0 5 1.000E+0 5 Y-9 2 1.800E+0 5 1.800E+0 5 1.800E+0 5 1.800E+0 5 1.800E+0 5 1.800E+0 5 2.140E+0 5 1.800E+0 5 Y-9 3 1.830E+0 5 1.830E+0 5 1.830E+0 5 1.830E+0 5 1.830E+0 5 1.830E+0 5 2.510E+0 5 1.830E+0 5 Z R-95 2.4 5 0E+0 8 2.4 5 0E+0 8 2.4 5 0E+0 8 2.4 5 0E+0 8 2.4 5 0E+0 8 2.4 5 0E+0 8 2.840E+0 8 2.4 5 0E+0 8 Z R-9 7 2.96 0E+0 6 2.96 0E+0 6 2.96 0E+0 6 2.96 0E+0 6 2.96 0E+0 6 2.96 0E+0 6 3.440E+0 6 2.96 0E+0 6 NB-95 1.370E+0 8 1.370E+0 8 1.370E+0 8 1.370E+0 8 1.370E+0 8 1.370E+0 8 1.610E+0 8 1.370E+0 8 MO-99 3.99 0E+0 6 3.99 0E+0 6 3.99 0E+0 6 3.99 0E+0 6 3.99 0E+0 6 3.99 0E+0 6 4.630E+0 6 3.99 0E+0 6 T C-99 M 1.840E+0 5 1.840E+0 5 1.840E+0 5 1.840E+0 5 1.840E+0 5 1.840E+0 5 2.110E+0 5 1.840E+0 5 T C-101 2.040E+04 2.040E+04 2.040E+04 2.040E+04 2.040E+04 2.040E+04 2.2 6 0E+04 2.040E+04 RU-103 1.0 8 0E+0 8 1.0 8 0E+0 8 1.0 8 0E+0 8 1.0 8 0E+0 8 1.0 8 0E+0 8 1.0 8 0E+0 8 1.2 6 0E+0 8 1.0 8 0E+0 8 RU-10 5 6.3 6 0E+0 5 6.3 6 0E+0 5 6.3 6 0E+0 5 6.3 6 0E+0 5 6.3 6 0E+0 5 6.3 6 0E+0 5 7.210E+0 5 6.3 6 0E+0 5 RU-10 6 4.220E+0 8 4.220E+0 8 4.220E+0 8 4.220E+0 8 4.220E+0 8 4.220E+0 8 5.070E+0 8 4.220E+0 8 AG-110M 3.440E+0 9 3.440E+0 9 3.440E+0 9 3.440E+0 9 3.440E+0 9 3.440E+0 9 4.010E+0 9 3.440E+0 9 T E-12 5 M 1.55 0E+0 6 1.55 0E+0 6 1.55 0E+0 6 1.55 0E+0 6 1.55 0E+0 6 1.55 0E+0 6 2.130E+0 6 1.55 0E+0 6 T E-127 2.98 0E+03 2.98 0E+03 2.98 0E+03 2.98 0E+03 2.98 0E+03 2.98 0E+03 3.2 8 0E+03 2.98 0E+03 T E-127M 9.1 6 0E+04 9.1 6 0E+04 9.1 6 0E+04 9.1 6 0E+04 9.1 6 0E+04 9.1 6 0E+04 1.0 8 0E+0 5 9.1 6 0E+04 T E-12 9 2.620E+04 2.620E+04 2.620E+04 2.620E+04 2.620E+04 2.620E+04 3.100E+04 2.620E+04 T E-12 9 M 1.98 0E+07 1.98 0E+07 1.98 0E+07 1.98 0E+07 1.98 0E+07 1.98 0E+07 2.310E+07 1.98 0E+07 T E-131 2.920E+04 2.920E+04 2.920E+04 2.920E+04 2.920E+04 2.920E+04 3.4 5 0E+07 2.920E+04 T E-131M 8.030E+0 6 8.030E+0 6 8.030E+0 6 8.030E+0 6 8.030E+0 6 8.030E+0 6 9.4 6 0E+0 6 8.030E+0 6 T E-132 4.230E+0 6 4.230E+0 6 4.230E+0 6 4.230E+0 6 4.230E+0 6 4.230E+0 6 4.98 0E+0 6 4.230E+0 6 I-130 5.510E+0 6 5.510E+0 6 5.510E+0 6 5.510E+0 6 5.510E+0 6 5.510E+0 6 6.69 0E+0 6 5.510E+0 6 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X G R i Adult Dose Factors for use in the Gaseous Dose Calculations Appendix G Ri Adult Ground Plane Deposition - Page 3 of 3 Agegroup:

ADULT Pathway: Ground Plane Deposition (GPD) Units: m 2*mrem/yr / µµµµCi/sec Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in Total Body I-131 1.720E+07 1.720E+07 1.720E+07 1.720E+07 1.720E+07 1.720E+07 2.0 9 0E+07 1.720E+07 I-132 1.2 5 0E+0 6 1.2 5 0E+0 6 1.2 5 0E+0 6 1.2 5 0E+0 6 1.2 5 0E+0 6 1.2 5 0E+0 6 1.470E+0 6 1.2 5 0E+0 6 I-133 2.4 5 0E+0 6 2.4 5 0E+0 6 2.4 5 0E+0 6 2.4 5 0E+0 6 2.4 5 0E+0 6 2.4 5 0E+0 6 2.98 0E+0 6 2.4 5 0E+0 6 I-134 4.470E+0 5 4.470E+0 5 4.470E+0 5 4.470E+0 5 4.470E+0 5 4.470E+0 5 5.300E+0 5 4.470E+0 5 I-13 5 2.530E+0 6 2.530E+0 6 2.530E+0 6 2.530E+0 6 2.530E+0 6 2.530E+0 6 2.95 0E+0 6 2.530E+0 6 CS-134 6.86 0E+0 9 6.86 0E+0 9 6.86 0E+0 9 6.86 0E+0 9 6.86 0E+0 9 6.86 0E+0 9 8.000E+0 9 6.86 0E+0 9 CS-13 6 1.510E+0 8 1.510E+0 8 1.510E+0 8 1.510E+0 8 1.510E+0 8 1.510E+0 8 1.710E+0 8 1.510E+0 8 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-13 8 3.59 0E+0 5 3.59 0E+0 5 3.59 0E+0 5 3.59 0E+0 5 3.59 0E+0 5 3.59 0E+0 5 4.100E+0 5 3.59 0E+0 5 BA-13 9 1.0 6 0E+0 5 1.0 6 0E+0 5 1.0 6 0E+0 5 1.0 6 0E+0 5 1.0 6 0E+0 5 1.0 6 0E+0 5 1.1 9 0E+0 5 1.0 6 0E+0 5 BA-140 2.0 5 0E+07 2.0 5 0E+07 2.0 5 0E+07 2.0 5 0E+07 2.0 5 0E+07 2.0 5 0E+07 2.3 5 0E+07 2.0 5 0E+07 BA-141 4.170E+04 4.170E+04 4.170E+04 4.170E+04 4.170E+04 4.170E+04 4.7 5 0E+04 4.170E+04 BA-142 4.4 9 0E+04 4.4 9 0E+04 4.4 9 0E+04 4.4 9 0E+04 4.4 9 0E+04 4.4 9 0E+04 5.110E+04 4.4 9 0E+04 LA-140 1.920E+07 1.920E+07 1.920E+07 1.920E+07 1.920E+07 1.920E+07 2.1 8 0E+07 1.920E+07 LA-142 7.600E+0 5 7.600E+0 5 7.600E+0 5 7.600E+0 5 7.600E+0 5 7.600E+0 5 9.120E+0 5 7.600E+0 5 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+0 6 2.310E+0 6 2.310E+0 6 2.310E+0 6 2.310E+0 6 2.310E+0 6 2.630E+0 6 2.310E+0 6 CE-144 6.95 0E+07 6.95 0E+07 6.95 0E+07 6.95 0E+07 6.95 0E+07 6.95 0E+07 8.040E+07 6.95 0E+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 N D-147 8.3 9 0E+0 6 8.3 9 0E+0 6 8.3 9 0E+0 6 8.3 9 0E+0 6 8.3 9 0E+0 6 8.3 9 0E+0 6 1.010E+07 8.3 9 0E+0 6 W-1 8 7 2.3 5 0E+0 6 2.3 5 0E+0 6 2.3 5 0E+0 6 2.3 5 0E+0 6 2.3 5 0E+0 6 2.3 5 0E+0 6 2.730E+0 6 2.3 5 0E+0 6 NP-23 9 1.710E+0 6 1.710E+0 6 1.710E+0 6 1.710E+0 6 1.710E+0 6 1.710E+0 6 1.98 0E+0 6 1.710E+0 6 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X H R i Teen Dose Factors for use in the Gaseous Dose Calculations Appendix H Ri T een Cow Milk - Page 1 of 3 Agegroup: TEEN Pathway: Grs

/Cow/Mil k (CMIL K) Units: m 2*mrem/yr / µµµµCi/sec; mrem/yr / µµµµCi/m 3 (H-3) Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in 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 4.86 0E+0 8 9.720E+07 9.720E+07 9.720E+07 9.720E+07 9.720E+07 0.000E+00 9.720E+07 NA-24 4.2 6 0E+0 6 4.2 6 0E+0 6 4.2 6 0E+0 6 4.2 6 0E+0 6 4.2 6 0E+0 6 4.2 6 0E+0 6 0.000E+00 4.2 6 0E+0 6 P-32 3.1 5 0E+10 1.95 0E+0 9 0.000E+00 0.000E+00 0.000E+00 2.65 0E+0 9 0.000E+00 1.220E+0 9 CR-5 1 0.000E+00 0.000E+00 2.770E+04 1.0 9 0E+04 7.130E+04 8.3 9 0E+0 6 0.000E+00 4.99 0E+04 MN-5 4 0.000E+00 1.400E+07 0.000E+00 4.1 8 0E+0 6 0.000E+00 2.870E+07 0.000E+00 2.7 8 0E+0 6 MN-56 0.000E+00 7.2 5 0E-03 0.000E+00 9.1 8 0E-03 0.000E+00 4.770E-01 0.000E+00 1.2 9 0E-03 FE-55 4.4 5 0E+07 3.1 6 0E+07 0.000E+00 0.000E+00 2.000E+07 1.370E+07 0.000E+00 7.3 6 0E+0 6 FE-59 5.1 8 0E+07 1.210E+0 8 0.000E+00 0.000E+00 3.810E+07 2.86 0E+0 8 0.000E+00 4.670E+07 CO-58 0.000E+00 7.940E+0 6 0.000E+00 0.000E+00 0.000E+00 1.0 9 0E+0 8 0.000E+00 1.830E+07 CO-6 0 0.000E+00 2.7 8 0E+07 0.000E+00 0.000E+00 0.000E+00 3.620E+0 8 0.000E+00 6.2 6 0E+07 NI-6 3 1.1 8 0E+10 8.3 5 0E+0 8 0.000E+00 0.000E+00 0.000E+00 1.330E+0 8 0.000E+00 4.010E+0 8 NI-65 6.770E-01 8.65 0E-02 0.000E+00 0.000E+00 0.000E+00 4.69 0E+00 0.000E+00 3.940E-02 CU-6 4 0.000E+00 4.2 5 0E+04 0.000E+00 1.070E+0 5 0.000E+00 3.2 9 0E+0 6 0.000E+00 2.000E+04 Z N-65 2.110E+0 9 7.320E+0 9 0.000E+00 4.68 0E+0 9 0.000E+00 3.100E+0 9 0.000E+00 3.410E+0 9 Z N-69 3.85 0E-12 7.330E-12 0.000E+00 4.7 9 0E-12 0.000E+00 1.3 5 0E-11 0.000E+00 5.130E-13 BR-8 3 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.7 9 0E-01 BR-8 4 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.88 0E-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+0 9 0.000E+00 0.000E+00 0.000E+00 7.000E+0 8 0.000E+00 2.220E+0 9 RB-88 0.000E+00 3.89 0E-4 5 0.000E+00 0.000E+00 0.000E+00 3.330E-5 2 0.000E+00 2.070E-4 5 RB-89 0.000E+00 7.66 0E-5 3 0.000E+00 0.000E+00 0.000E+00 1.170E-6 1 0.000E+00 5.420E-5 3 SR-89 2.670E+0 9 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.1 9 0E+0 8 0.000E+00 7.66 0E+07 SR-9 0 6.610E+10 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.86 0E+0 9 0.000E+00 1.630E+10 SR-9 1 5.310E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.410E+0 5 0.000E+00 2.110E+03 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X H R i Teen Dose Factors for use in the Gaseous Dose Calculations Appendix H Ri T een Cow Milk - Page 2 of 3 Agegroup: TEEN Pathway: Grs

/Cow/Mil k (CMIL K) Units: m 2*mrem/yr / µµµµCi/sec; mrem/yr / µµµµCi/m 3 (H-3) Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in Total Body SR-9 2 8.940E-01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.2 8 0E+01 0.000E+00 3.810E-02 Y-9 0 1.300E+02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.070E+0 6 0.000E+00 3.510E+00 Y-9 1 1.58 0E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 6.4 8 0E+0 6 0.000E+00 4.240E+02 Y-9 1M 1.0 9 0E-1 9 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.170E-1 8 0.000E+00 4.1 8 0E-21 Y-9 2 1.030E-04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.830E+00 0.000E+00 2.98 0E-0 6 Y-9 3 4.120E-01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.2 6 0E+04 0.000E+00 1.130E-02 Z R-95 1.65 0E+03 5.200E+02 0.000E+00 7.65 0E+02 0.000E+00 1.200E+0 6 0.000E+00 3.58 0E+02 Z R-9 7 7.88 0E-01 1.56 0E-01 0.000E+00 2.370E-01 0.000E+00 4.220E+04 0.000E+00 7.1 9 0E-02 NB-95 1.410E+0 5 7.810E+04 0.000E+00 7.570E+04 0.000E+00 3.340E+0 8 0.000E+00 4.300E+04 MO-99 0.000E+00 4.470E+07 0.000E+00 1.020E+0 8 0.000E+00 8.010E+07 0.000E+00 8.530E+0 6 T C-99 M 5.7 6 0E+00 1.610E+01 0.000E+00 2.3 9 0E+02 8.920E+00 1.0 5 0E+04 0.000E+00 2.0 8 0E+02 T C-101 4.740E-6 0 6.7 5 0E-6 0 0.000E+00 1.220E-58 4.110E-6 0 1.1 5 0E-66 0.000E+00 6.630E-59 RU-103 1.810E+03 0.000E+00 0.000E+00 6.3 8 0E+03 0.000E+00 1.510E+0 5 0.000E+00 7.740E+02 RU-10 5 1.56 0E-03 0.000E+00 0.000E+00 1.970E-02 0.000E+00 1.2 6 0E+00 0.000E+00 6.070E-04 RU-10 6 3.7 5 0E+04 0.000E+00 0.000E+00 7.240E+04 0.000E+00 1.800E+0 6 0.000E+00 4.730E+03 AG-110M 9.630E+07 9.110E+07 0.000E+00 1.740E+0 8 0.000E+00 2.56 0E+10 0.000E+00 5.540E+07 T E-12 5 M 3.000E+07 1.0 8 0E+07 8.3 9 0E+0 6 0.000E+00 0.000E+00 8.86 0E+07 0.000E+00 4.020E+0 6 T E-127 1.210E+03 4.2 9 0E+02 8.3 5 0E+02 4.900E+03 0.000E+00 9.340E+04 0.000E+00 2.600E+02 T E-127M 8.440E+07 2.99 0E+07 2.010E+07 3.420E+0 8 0.000E+00 2.100E+0 8 0.000E+00 1.000E+07 T E-12 9 5.200E-10 1.940E-10 3.720E-10 2.1 8 0E-0 9 0.000E+00 2.840E-0 9 0.000E+00 1.270E-10 T E-12 9 M 1.100E+0 8 4.0 9 0E+07 3.55 0E+07 4.610E+0 8 0.000E+00 4.130E+0 8 0.000E+00 1.740E+07 T E-131 6.58 0E-33 2.710E-33 5.070E-33 2.88 0E-32 0.000E+00 5.400E-34 0.000E+00 2.0 6 0E-33 T E-131M 6.570E+0 5 3.1 5 0E+0 5 4.740E+0 5 3.2 9 0E+0 6 0.000E+00 2.530E+07 0.000E+00 2.630E+0 5 T E-132 4.2 9 0E+0 6 2.720E+0 6 2.870E+0 6 2.610E+07 0.000E+00 8.610E+07 0.000E+00 2.56 0E+0 6 I-130 7.3 8 0E+0 5 2.140E+0 6 1.740E+0 8 3.2 9 0E+0 6 0.000E+00 1.640E+0 6 0.000E+00 8.530E+0 5 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X H R i Teen Dose Factors for use in the Gaseous Dose Calculations Appendix H Ri T een Cow Milk - Page 3 of 3 Agegroup: TEEN Pathway: Grs

/Cow/Mil k (CMIL K) Units: m 2*mrem/yr / µµµµCi/sec; mrem/yr / µµµµCi/m 3 (H-3) Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in Total Body I-131 5.370E+0 8 7.520E+0 8 2.1 9 0E+11 1.2 9 0E+0 9 0.000E+00 1.4 9 0E+0 8 0.000E+00 4.040E+0 8 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+0 6 1.200E+07 1.670E+0 9 2.100E+07 0.000E+00 9.070E+0 6 0.000E+00 3.66 0E+0 6 I-134 3.58 0E-12 9.500E-12 1.58 0E-10 1.500E-11 0.000E+00 1.2 5 0E-13 0.000E+00 3.410E-12 I-13 5 2.2 8 0E+04 5.870E+04 3.7 8 0E+0 6 9.270E+04 0.000E+00 6.510E+04 0.000E+00 2.1 8 0E+04 CS-134 9.820E+0 9 2.310E+10 0.000E+00 7.340E+0 9 2.800E+0 9 2.870E+0 8 0.000E+00 1.070E+10 CS-13 6 4.4 8 0E+0 8 1.7 6 0E+0 9 0.000E+00 9.600E+0 8 1.510E+0 8 1.420E+0 8 0.000E+00 1.1 8 0E+0 9 CS-137 1.340E+10 1.7 8 0E+10 0.000E+00 6.0 6 0E+0 9 2.3 5 0E+0 9 2.530E+0 8 0.000E+00 6.200E+0 9 CS-13 8 1.640E-23 3.1 5 0E-23 0.000E+00 2.330E-23 2.710E-24 1.430E-2 6 0.000E+00 1.58 0E-23 BA-13 9 8.170E-0 8 5.7 5 0E-11 0.000E+00 5.420E-11 3.96 0E-11 7.2 9 0E-07 0.000E+00 2.3 8 0E-0 9 BA-140 4.85 0E+07 5.95 0E+04 0.000E+00 2.020E+04 4.000E+04 7.4 8 0E+07 0.000E+00 3.130E+0 6 BA-141 7.520E-4 6 5.620E-4 9 0.000E+00 5.210E-4 9 3.85 0E-4 9 1.600E-5 1 0.000E+00 2.510E-47 BA-142 4.7 9 0E-8 0 4.7 9 0E-8 3 0.000E+00 4.0 5 0E-8 3 3.1 9 0E-8 3 1.470E-9 1 0.000E+00 2.95 0E-8 1 LA-140 8.100E+00 3.98 0E+00 0.000E+00 0.000E+00 0.000E+00 2.2 9 0E+0 5 0.000E+00 1.0 6 0E+00 LA-142 3.3 6 0E-11 1.4 9 0E-11 0.000E+00 0.000E+00 0.000E+00 4.540E-07 0.000E+00 3.710E-12 CE-141 8.88 0E+03 5.930E+03 0.000E+00 2.7 9 0E+03 0.000E+00 1.700E+07 0.000E+00 6.810E+02 CE-143 7.640E+01 5.56 0E+04 0.000E+00 2.4 9 0E+01 0.000E+00 1.670E+0 6 0.000E+00 6.210E+00 CE-144 6.58 0E+0 5 2.720E+0 5 0.000E+00 1.630E+0 5 0.000E+00 1.66 0E+0 8 0.000E+00 3.540E+04 PR-143 2.900E+02 1.1 6 0E+02 0.000E+00 6.730E+01 0.000E+00 9.540E+0 5 0.000E+00 1.440E+01 PR-144 1.0 8 0E-5 3 4.430E-5 4 0.000E+00 2.540E-5 4 0.000E+00 1.1 9 0E-56 0.000E+00 5.4 9 0E-55 N D-147 1.810E+02 1.970E+02 0.000E+00 1.1 6 0E+02 0.000E+00 7.110E+0 5 0.000E+00 1.1 8 0E+01 W-1 8 7 1.1 9 0E+04 9.710E+03 0.000E+00 0.000E+00 0.000E+00 2.630E+0 6 0.000E+00 3.400E+03 NP-23 9 7.010E+00 6.610E-01 0.000E+00 2.070E+00 0.000E+00 1.0 6 0E+0 5 0.000E+00 3.670E-01 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X H R i Teen Dose Factors for use in the Gaseous Dose Calculations Appendix H Ri T een Goat Milk - Page 1 of 3 Agegroup: TEEN Pathway: Grs

/Goat/Mil k (GMIL K) Units: m 2*mrem/yr / µµµµCi/sec; mrem/yr / µµµµCi/m 3 (H-3) Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in 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 4.86 0E+0 8 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+0 5 5.110E+0 5 5.110E+0 5 5.110E+0 5 5.110E+0 5 5.110E+0 5 0.000E+00 5.110E+0 5 P-32 3.7 8 0E+10 2.340E+0 9 0.000E+00 0.000E+00 0.000E+00 3.1 8 0E+0 9 0.000E+00 1.470E+0 9 CR-5 1 0.000E+00 0.000E+00 3.330E+03 1.310E+03 8.55 0E+03 1.010E+0 6 0.000E+00 5.99 0E+03 MN-5 4 0.000E+00 1.68 0E+0 6 0.000E+00 5.020E+0 5 0.000E+00 3.4 5 0E+0 6 0.000E+00 3.340E+0 5 MN-56 0.000E+00 8.700E-04 0.000E+00 1.100E-03 0.000E+00 5.730E-02 0.000E+00 1.55 0E-04 FE-55 5.7 9 0E+0 5 4.110E+0 5 0.000E+00 0.000E+00 2.600E+0 5 1.7 8 0E+0 5 0.000E+00 9.570E+04 FE-59 6.740E+0 5 1.570E+0 6 0.000E+00 0.000E+00 4.96 0E+0 5 3.720E+0 6 0.000E+00 6.070E+0 5 CO-58 0.000E+00 9.520E+0 5 0.000E+00 0.000E+00 0.000E+00 1.310E+07 0.000E+00 2.1 9 0E+0 6 CO-6 0 0.000E+00 3.340E+0 6 0.000E+00 0.000E+00 0.000E+00 4.3 5 0E+07 0.000E+00 7.520E+0 6 NI-6 3 1.420E+0 9 1.000E+0 8 0.000E+00 0.000E+00 0.000E+00 1.59 0E+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-6 4 0.000E+00 4.730E+03 0.000E+00 1.200E+04 0.000E+00 3.670E+0 5 0.000E+00 2.230E+03 Z N-65 2.530E+0 8 8.7 8 0E+0 8 0.000E+00 5.620E+0 8 0.000E+00 3.720E+0 8 0.000E+00 4.100E+0 8 Z N-69 4.620E-13 8.800E-13 0.000E+00 5.7 5 0E-13 0.000E+00 1.620E-12 0.000E+00 6.1 6 0E-14 BR-8 3 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.1 5 0E-02 BR-8 4 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.4 5 0E-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+0 8 0.000E+00 0.000E+00 0.000E+00 8.400E+07 0.000E+00 2.670E+0 8 RB-88 0.000E+00 4.670E-4 6 0.000E+00 0.000E+00 0.000E+00 4.000E-5 3 0.000E+00 2.4 9 0E-4 6 RB-89 0.000E+00 9.1 9 0E-5 4 0.000E+00 0.000E+00 0.000E+00 1.410E-6 2 0.000E+00 6.500E-5 4 SR-89 5.620E+0 9 0.000E+00 0.000E+00 0.000E+00 0.000E+00 6.69 0E+0 8 0.000E+00 1.610E+0 8 SR-9 0 1.3 9 0E+11 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.900E+0 9 0.000E+00 3.430E+10 SR-9 1 1.120E+0 5 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.0 6 0E+0 5 0.000E+00 4.440E+03 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X H R i Teen Dose Factors for use in the Gaseous Dose Calculations Appendix H Ri T een Goat Milk - Page 2 of 3 Agegroup: TEEN Pathway: Grs

/Goat/Mil k (GMIL K) Units: m 2*mrem/yr / µµµµCi/sec; mrem/yr / µµµµCi/m 3 (H-3) Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in Total Body SR-9 2 1.88 0E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4.7 8 0E+01 0.000E+00 8.000E-02 Y-9 0 1.56 0E+01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.2 9 0E+0 5 0.000E+00 4.210E-01 Y-9 1 1.900E+03 0.000E+00 0.000E+00 0.000E+00 0.000E+00 7.770E+0 5 0.000E+00 5.0 8 0E+01 Y-9 1M 1.310E-20 0.000E+00 0.000E+00 0.000E+00 0.000E+00 6.200E-1 9 0.000E+00 5.020E-22 Y-9 2 1.240E-0 5 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.3 9 0E-01 0.000E+00 3.58 0E-07 Y-9 3 4.940E-02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.510E+03 0.000E+00 1.3 6 0E-03 Z R-95 1.98 0E+02 6.2 5 0E+01 0.000E+00 9.1 8 0E+01 0.000E+00 1.440E+0 5 0.000E+00 4.300E+01 Z R-9 7 9.4 6 0E-02 1.870E-02 0.000E+00 2.840E-02 0.000E+00 5.070E+03 0.000E+00 8.620E-03 NB-95 1.69 0E+04 9.370E+03 0.000E+00 9.0 8 0E+03 0.000E+00 4.010E+07 0.000E+00 5.1 6 0E+03 MO-99 0.000E+00 5.370E+0 6 0.000E+00 1.230E+07 0.000E+00 9.610E+0 6 0.000E+00 1.020E+0 6 T C-99 M 6.910E-01 1.930E+00 0.000E+00 2.870E+01 1.070E+00 1.270E+03 0.000E+00 2.500E+01 T C-101 5.69 0E-6 1 8.100E-6 1 0.000E+00 1.4 6 0E-59 4.930E-6 1 1.3 8 0E-6 7 0.000E+00 7.95 0E-6 0 RU-103 2.170E+02 0.000E+00 0.000E+00 7.66 0E+02 0.000E+00 1.810E+04 0.000E+00 9.2 9 0E+01 RU-10 5 1.88 0E-04 0.000E+00 0.000E+00 2.370E-03 0.000E+00 1.520E-01 0.000E+00 7.2 9 0E-0 5 RU-10 6 4.500E+03 0.000E+00 0.000E+00 8.68 0E+03 0.000E+00 2.1 6 0E+0 5 0.000E+00 5.670E+02 AG-110M 1.1 6 0E+07 1.0 9 0E+07 0.000E+00 2.0 8 0E+07 0.000E+00 3.070E+0 9 0.000E+00 6.65 0E+0 6 T E-12 5 M 3.600E+0 6 1.300E+0 6 1.010E+0 6 0.000E+00 0.000E+00 1.0 6 0E+07 0.000E+00 4.820E+0 5 T E-127 1.4 5 0E+02 5.1 5 0E+01 1.000E+02 5.88 0E+02 0.000E+00 1.120E+04 0.000E+00 3.120E+01 T E-127M 1.010E+07 3.59 0E+0 6 2.410E+0 6 4.100E+07 0.000E+00 2.520E+07 0.000E+00 1.200E+0 6 T E-12 9 6.240E-11 2.330E-11 4.4 6 0E-11 2.620E-10 0.000E+00 3.410E-10 0.000E+00 1.520E-11 T E-12 9 M 1.320E+07 4.900E+0 6 4.2 6 0E+0 6 5.530E+07 0.000E+00 4.96 0E+07 0.000E+00 2.0 9 0E+0 6 T E-131 7.900E-34 3.2 6 0E-34 6.0 9 0E-34 3.4 5 0E-33 0.000E+00 6.4 8 0E-3 5 0.000E+00 2.470E-34 T E-131M 7.88 0E+04 3.7 8 0E+04 5.69 0E+04 3.940E+0 5 0.000E+00 3.030E+0 6 0.000E+00 3.1 5 0E+04 T E-132 5.1 5 0E+0 5 3.2 6 0E+0 5 3.440E+0 5 3.130E+0 6 0.000E+00 1.030E+07 0.000E+00 3.070E+0 5 I-130 8.86 0E+0 5 2.56 0E+0 6 2.0 9 0E+0 8 3.95 0E+0 6 0.000E+00 1.970E+0 6 0.000E+00 1.020E+0 6 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X H R i Teen Dose Factors for use in the Gaseous Dose Calculations Appendix H Ri T een Goat Milk - Page 3 of 3 Agegroup: TEEN Pathway: Grs

/Goat/Mil k (GMIL K) Units: m 2*mrem/yr / µµµµCi/sec; mrem/yr / µµµµCi/m 3 (H-3) Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in Total Body I-131 6.4 5 0E+0 8 9.030E+0 8 2.630E+11 1.55 0E+0 9 0.000E+00 1.7 9 0E+0 8 0.000E+00 4.85 0E+0 8 I-132 3.500E-01 9.1 5 0E-01 3.0 8 0E+01 1.440E+00 0.000E+00 3.98 0E-01 0.000E+00 3.2 8 0E-01 I-133 8.4 8 0E+0 6 1.440E+07 2.010E+0 9 2.520E+07 0.000E+00 1.0 9 0E+07 0.000E+00 4.3 9 0E+0 6 I-134 4.300E-12 1.140E-11 1.900E-10 1.800E-11 0.000E+00 1.500E-13 0.000E+00 4.0 9 0E-12 I-13 5 2.740E+04 7.040E+04 4.530E+0 6 1.110E+0 5 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+0 9 8.620E+0 8 0.000E+00 3.220E+10 CS-13 6 1.340E+0 9 5.2 9 0E+0 9 0.000E+00 2.88 0E+0 9 4.540E+0 8 4.2 6 0E+0 8 0.000E+00 3.55 0E+0 9 CS-137 4.020E+10 5.340E+10 0.000E+00 1.820E+10 7.0 6 0E+0 9 7.600E+0 8 0.000E+00 1.86 0E+10 CS-13 8 4.920E-23 9.4 5 0E-23 0.000E+00 6.98 0E-23 8.120E-24 4.2 9 0E-2 6 0.000E+00 4.730E-23 BA-13 9 9.800E-0 9 6.900E-12 0.000E+00 6.500E-12 4.7 5 0E-12 8.7 5 0E-0 8 0.000E+00 2.86 0E-10 BA-140 5.820E+0 6 7.130E+03 0.000E+00 2.420E+03 4.800E+03 8.98 0E+0 6 0.000E+00 3.7 5 0E+0 5 BA-141 9.030E-47 6.740E-5 0 0.000E+00 6.2 6 0E-5 0 4.610E-5 0 1.920E-5 2 0.000E+00 3.010E-4 8 BA-142 5.7 5 0E-8 1 5.7 5 0E-8 4 0.000E+00 4.86 0E-8 4 3.820E-8 4 1.7 6 0E-9 2 0.000E+00 3.540E-8 2 LA-140 9.720E-01 4.7 8 0E-01 0.000E+00 0.000E+00 0.000E+00 2.740E+04 0.000E+00 1.270E-01 LA-142 4.030E-12 1.7 9 0E-12 0.000E+00 0.000E+00 0.000E+00 5.440E-0 8 0.000E+00 4.4 5 0E-13 CE-141 1.070E+03 7.120E+02 0.000E+00 3.3 5 0E+02 0.000E+00 2.040E+0 6 0.000E+00 8.170E+01 CE-143 9.170E+00 6.670E+03 0.000E+00 2.99 0E+00 0.000E+00 2.000E+0 5 0.000E+00 7.4 5 0E-01 CE-144 7.900E+04 3.270E+04 0.000E+00 1.95 0E+04 0.000E+00 1.99 0E+07 0.000E+00 4.240E+03 PR-143 3.4 8 0E+01 1.3 9 0E+01 0.000E+00 8.0 8 0E+00 0.000E+00 1.1 5 0E+0 5 0.000E+00 1.730E+00 PR-144 1.300E-5 4 5.320E-55 0.000E+00 3.0 5 0E-55 0.000E+00 1.430E-5 7 0.000E+00 6.59 0E-56 N D-147 2.170E+01 2.3 6 0E+01 0.000E+00 1.3 9 0E+01 0.000E+00 8.530E+04 0.000E+00 1.420E+00 W-1 8 7 1.430E+03 1.170E+03 0.000E+00 0.000E+00 0.000E+00 3.1 5 0E+0 5 0.000E+00 4.0 8 0E+02 NP-23 9 8.410E-01 7.930E-02 0.000E+00 2.4 9 0E-01 0.000E+00 1.2 8 0E+04 0.000E+00 4.410E-02 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X H R i Teen Dose Factors for use in the Gaseous Dose Calculations Appendix H Ri T een Cow Meat - Page 1 of 3 Agegroup: TEEN Pathway: Grs

/Cow/Meat (CMEAT) Units: m 2*mrem/yr / µµµµCi/sec; mrem/yr / µµµµCi/m 3 (H-3) Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in 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+0 8 4.0 8 0E+07 4.0 8 0E+07 4.0 8 0E+07 4.0 8 0E+07 4.0 8 0E+07 0.000E+00 4.0 8 0E+07 NA-24 1.0 8 0E-03 1.0 8 0E-03 1.0 8 0E-03 1.0 8 0E-03 1.0 8 0E-03 1.0 8 0E-03 0.000E+00 1.0 8 0E-03 P-32 3.930E+0 9 2.440E+0 8 0.000E+00 0.000E+00 0.000E+00 3.310E+0 8 0.000E+00 1.530E+0 8 CR-5 1 0.000E+00 0.000E+00 3.130E+03 1.240E+03 8.0 5 0E+03 9.470E+0 5 0.000E+00 5.640E+03 MN-5 4 0.000E+00 7.000E+0 6 0.000E+00 2.0 9 0E+0 6 0.000E+00 1.440E+07 0.000E+00 1.3 9 0E+0 6 MN-56 0.000E+00 1.070E-5 3 0.000E+00 1.3 6 0E-5 3 0.000E+00 7.070E-5 2 0.000E+00 1.910E-5 4 FE-55 2.3 8 0E+0 8 1.69 0E+0 8 0.000E+00 0.000E+00 1.070E+0 8 7.310E+07 0.000E+00 3.940E+07 FE-59 2.120E+0 8 4.95 0E+0 8 0.000E+00 0.000E+00 1.56 0E+0 8 1.170E+0 9 0.000E+00 1.910E+0 8 CO-58 0.000E+00 1.410E+07 0.000E+00 0.000E+00 0.000E+00 1.940E+0 8 0.000E+00 3.240E+07 CO-6 0 0.000E+00 5.830E+07 0.000E+00 0.000E+00 0.000E+00 7.600E+0 8 0.000E+00 1.310E+0 8 NI-6 3 1.520E+10 1.070E+0 9 0.000E+00 0.000E+00 0.000E+00 1.710E+0 8 0.000E+00 5.1 5 0E+0 8 NI-65 1.88 0E-5 2 2.410E-5 3 0.000E+00 0.000E+00 0.000E+00 1.300E-5 1 0.000E+00 1.100E-5 3 CU-6 4 0.000E+00 2.210E-07 0.000E+00 5.600E-07 0.000E+00 1.720E-0 5 0.000E+00 1.040E-07 Z N-65 2.500E+0 8 8.69 0E+0 8 0.000E+00 5.56 0E+0 8 0.000E+00 3.68 0E+0 8 0.000E+00 4.0 5 0E+0 8 Z N-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-8 3 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.070E-5 7 BR-8 4 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+0 8 0.000E+00 0.000E+00 0.000E+00 6.020E+07 0.000E+00 1.910E+0 8 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 2.55 0E+0 8 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.030E+07 0.000E+00 7.2 9 0E+0 6 SR-9 0 8.0 5 0E+0 9 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.2 6 0E+0 8 0.000E+00 1.99 0E+0 9 SR-9 1 1.2 8 0E-10 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.800E-10 0.000E+00 5.0 9 0E-12 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X H R i Teen Dose Factors for use in the Gaseous Dose Calculations Appendix H Ri T een Cow Meat - Page 2 of 3 Agegroup: TEEN Pathway: Grs

/Cow/Meat (CMEAT) Units: m 2*mrem/yr / µµµµCi/sec; mrem/yr / µµµµCi/m 3 (H-3) Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in Total Body SR-9 2 9.88 0E-5 0 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.520E-4 8 0.000E+00 4.210E-5 1 Y-9 0 9.0 6 0E+01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 7.470E+0 5 0.000E+00 2.440E+00 Y-9 1 9.540E+0 5 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.910E+0 8 0.000E+00 2.56 0E+04 Y-9 1M 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-9 2 1.2 8 0E-3 9 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.520E-3 5 0.000E+00 3.710E-41 Y-9 3 3.96 0E-12 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.210E-07 0.000E+00 1.0 9 0E-13 Z R-95 1.500E+0 6 4.730E+0 5 0.000E+00 6.95 0E+0 5 0.000E+00 1.0 9 0E+0 9 0.000E+00 3.2 5 0E+0 5 Z R-9 7 1.720E-0 5 3.410E-0 6 0.000E+00 5.170E-0 6 0.000E+00 9.230E-01 0.000E+00 1.570E-0 6 NB-95 1.7 9 0E+0 6 9.95 0E+0 5 0.000E+00 9.65 0E+0 5 0.000E+00 4.2 6 0E+0 9 0.000E+00 5.4 8 0E+0 5 MO-99 0.000E+00 8.270E+04 0.000E+00 1.89 0E+0 5 0.000E+00 1.4 8 0E+0 5 0.000E+00 1.58 0E+04 T C-99 M 3.530E-21 9.85 0E-21 0.000E+00 1.470E-1 9 5.470E-21 6.470E-1 8 0.000E+00 1.2 8 0E-1 9 T C-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+0 8 0.000E+00 7.1 6 0E+0 9 0.000E+00 3.66 0E+07 RU-10 5 4.830E-2 8 0.000E+00 0.000E+00 6.0 9 0E-27 0.000E+00 3.900E-2 5 0.000E+00 1.88 0E-2 8 RU-10 6 2.3 6 0E+0 9 0.000E+00 0.000E+00 4.55 0E+0 9 0.000E+00 1.130E+11 0.000E+00 2.970E+0 8 AG-110M 5.0 6 0E+0 6 4.7 9 0E+0 6 0.000E+00 9.130E+0 6 0.000E+00 1.340E+0 9 0.000E+00 2.910E+0 6 T E-12 5 M 3.030E+0 8 1.0 9 0E+0 8 8.470E+07 0.000E+00 0.000E+00 8.940E+0 8 0.000E+00 4.0 5 0E+07 T E-127 1.800E-10 6.3 8 0E-11 1.240E-10 7.2 9 0E-10 0.000E+00 1.3 9 0E-0 8 0.000E+00 3.870E-11 T E-127M 9.410E+0 8 3.340E+0 8 2.240E+0 8 3.820E+0 9 0.000E+00 2.3 5 0E+0 9 0.000E+00 1.120E+0 8 T E-12 9 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 T E-12 9 M 9.500E+0 8 3.530E+0 8 3.070E+0 8 3.970E+0 9 0.000E+00 3.570E+0 9 0.000E+00 1.500E+0 8 T E-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 T E-131M 3.7 6 0E+02 1.800E+02 2.710E+02 1.88 0E+03 0.000E+00 1.4 5 0E+04 0.000E+00 1.500E+02 T E-132 1.1 6 0E+0 6 7.3 6 0E+0 5 7.7 5 0E+0 5 7.0 6 0E+0 6 0.000E+00 2.330E+07 0.000E+00 6.920E+0 5 I-130 1.700E-0 6 4.910E-0 6 4.000E-04 7.56 0E-0 6 0.000E+00 3.770E-0 6 0.000E+00 1.96 0E-0 6 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X H R i Teen Dose Factors for use in the Gaseous Dose Calculations Appendix H Ri T een Cow Meat - Page 3 of 3 Agegroup: TEEN Pathway: Grs

/Cow/Meat (CMEAT) Units: m 2*mrem/yr / µµµµCi/sec; mrem/yr / µµµµCi/m 3 (H-3) Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in Total Body I-131 8.920E+0 6 1.2 5 0E+07 3.65 0E+0 9 2.1 5 0E+07 0.000E+00 2.470E+0 6 0.000E+00 6.710E+0 6 I-132 5.66 0E-59 1.4 8 0E-58 4.99 0E-5 7 2.330E-58 0.000E+00 6.4 5 0E-59 0.000E+00 5.320E-59 I-133 3.0 5 0E-01 5.1 8 0E-01 7.230E+01 9.0 9 0E-01 0.000E+00 3.920E-01 0.000E+00 1.58 0E-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-13 5 3.600E-17 9.2 6 0E-17 5.96 0E-1 5 1.4 6 0E-1 6 0.000E+00 1.030E-1 6 0.000E+00 3.430E-17 CS-134 5.230E+0 8 1.230E+0 9 0.000E+00 3.910E+0 8 1.4 9 0E+0 8 1.530E+07 0.000E+00 5.710E+0 8 CS-13 6 9.400E+0 6 3.700E+07 0.000E+00 2.010E+07 3.170E+0 6 2.98 0E+0 6 0.000E+00 2.4 8 0E+07 CS-137 7.240E+0 8 9.630E+0 8 0.000E+00 3.2 8 0E+0 8 1.270E+0 8 1.370E+07 0.000E+00 3.3 6 0E+0 8 CS-13 8 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-13 9 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 2.3 8 0E+07 2.910E+04 0.000E+00 9.870E+03 1.96 0E+04 3.66 0E+07 0.000E+00 1.530E+0 6 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 3.0 5 0E-02 1.500E-02 0.000E+00 0.000E+00 0.000E+00 8.610E+02 0.000E+00 3.99 0E-03 LA-142 2.870E-9 2 1.2 8 0E-9 2 0.000E+00 0.000E+00 0.000E+00 3.88 0E-88 0.000E+00 3.1 8 0E-9 3 CE-141 1.1 8 0E+04 7.870E+03 0.000E+00 3.710E+03 0.000E+00 2.2 5 0E+07 0.000E+00 9.040E+02 CE-143 1.69 0E-02 1.230E+01 0.000E+00 5.510E-03 0.000E+00 3.69 0E+02 0.000E+00 1.370E-03 CE-144 1.230E+0 6 5.0 8 0E+0 5 0.000E+00 3.040E+0 5 0.000E+00 3.0 9 0E+0 8 0.000E+00 6.600E+04 PR-143 1.7 6 0E+04 7.040E+03 0.000E+00 4.0 9 0E+03 0.000E+00 5.800E+07 0.000E+00 8.7 8 0E+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 N D-147 6.230E+03 6.770E+03 0.000E+00 3.98 0E+03 0.000E+00 2.440E+07 0.000E+00 4.0 6 0E+02 W-1 8 7 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-23 9 2.2 6 0E-01 2.140E-02 0.000E+00 6.700E-02 0.000E+00 3.440E+03 0.000E+00 1.1 9 0E-02 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X H R i Teen Dose Factors for use in the Gaseous Dose Calculations Appendix H Ri T een Vegetation - Page 1 of 3 Agegroup: TEEN Pathway: Vegetation (VEG) Units: m 2*mrem/yr / µµµµCi/sec; mrem/yr / µµµµCi/m 3 (H-3) Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in Total Body H-3 0.000E+00 2.59 0E+03 2.59 0E+03 2.59 0E+03 2.59 0E+03 2.59 0E+03 0.000E+00 2.59 0E+03 C-14 3.69 0E+0 8 7.3 8 0E+07 7.3 8 0E+07 7.3 8 0E+07 7.3 8 0E+07 7.3 8 0E+07 0.000E+00 7.3 8 0E+07 NA-24 2.3 9 0E+0 5 2.3 9 0E+0 5 2.3 9 0E+0 5 2.3 9 0E+0 5 2.3 9 0E+0 5 2.3 9 0E+0 5 0.000E+00 2.3 9 0E+0 5 P-32 1.610E+0 9 9.970E+07 0.000E+00 0.000E+00 0.000E+00 1.3 5 0E+0 8 0.000E+00 6.240E+07 CR-5 1 0.000E+00 0.000E+00 3.430E+04 1.3 5 0E+04 8.810E+04 1.040E+07 0.000E+00 6.170E+04 MN-5 4 0.000E+00 4.540E+0 8 0.000E+00 1.3 6 0E+0 8 0.000E+00 9.320E+0 8 0.000E+00 9.010E+07 MN-56 0.000E+00 1.420E+01 0.000E+00 1.800E+01 0.000E+00 9.3 6 0E+02 0.000E+00 2.530E+00 FE-55 3.2 6 0E+0 8 2.310E+0 8 0.000E+00 0.000E+00 1.470E+0 8 1.000E+0 8 0.000E+00 5.3 9 0E+07 FE-59 1.7 9 0E+0 8 4.1 9 0E+0 8 0.000E+00 0.000E+00 1.320E+0 8 9.900E+0 8 0.000E+00 1.620E+0 8 CO-58 0.000E+00 4.3 6 0E+07 0.000E+00 0.000E+00 0.000E+00 6.010E+0 8 0.000E+00 1.000E+0 8 CO-6 0 0.000E+00 2.4 9 0E+0 8 0.000E+00 0.000E+00 0.000E+00 3.240E+0 9 0.000E+00 5.600E+0 8 NI-6 3 1.610E+10 1.130E+0 9 0.000E+00 0.000E+00 0.000E+00 1.810E+0 8 0.000E+00 5.4 5 0E+0 8 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-6 4 0.000E+00 8.340E+03 0.000E+00 2.110E+04 0.000E+00 6.470E+0 5 0.000E+00 3.920E+03 Z N-65 4.240E+0 8 1.470E+0 9 0.000E+00 9.420E+0 8 0.000E+00 6.230E+0 8 0.000E+00 6.870E+0 8 Z N-69 5.140E-0 6 9.800E-0 6 0.000E+00 6.400E-0 6 0.000E+00 1.810E-0 5 0.000E+00 6.86 0E-07 BR-8 3 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-8 4 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.2 5 0E-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+0 8 0.000E+00 0.000E+00 0.000E+00 4.0 5 0E+07 0.000E+00 1.2 9 0E+0 8 RB-88 0.000E+00 3.170E-22 0.000E+00 0.000E+00 0.000E+00 2.720E-2 9 0.000E+00 1.69 0E-22 RB-89 0.000E+00 3.500E-2 6 0.000E+00 0.000E+00 0.000E+00 5.3 6 0E-3 5 0.000E+00 2.470E-2 6 SR-89 1.510E+10 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.800E+0 9 0.000E+00 4.340E+0 8 SR-9 0 7.510E+11 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.110E+10 0.000E+00 1.85 0E+11 SR-9 1 2.85 0E+0 5 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.2 9 0E+0 6 0.000E+00 1.130E+04 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X H R i Teen Dose Factors for use in the Gaseous Dose Calculations Appendix H Ri T een Vegetation - Page 2 of 3 Agegroup: TEEN Pathway: Vegetation (VEG) Units: m 2*mrem/yr / µµµµCi/sec; mrem/yr / µµµµCi/m 3 (H-3) Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in Total Body SR-9 2 3.970E+02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.010E+04 0.000E+00 1.69 0E+01 Y-9 0 1.240E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.020E+0 8 0.000E+00 3.3 5 0E+02 Y-9 1 7.840E+0 6 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.210E+0 9 0.000E+00 2.100E+0 5 Y-9 1M 4.86 0E-0 9 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.2 9 0E-07 0.000E+00 1.86 0E-10 Y-9 2 8.600E-01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.3 6 0E+04 0.000E+00 2.4 9 0E-02 Y-9 3 1.59 0E+02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4.86 0E+0 6 0.000E+00 4.3 6 0E+00 Z R-95 1.720E+0 6 5.430E+0 5 0.000E+00 7.98 0E+0 5 0.000E+00 1.2 5 0E+0 9 0.000E+00 3.730E+0 5 Z R-9 7 3.120E+02 6.1 8 0E+01 0.000E+00 9.370E+01 0.000E+00 1.670E+07 0.000E+00 2.85 0E+01 NB-95 1.920E+0 5 1.070E+0 5 0.000E+00 1.030E+0 5 0.000E+00 4.56 0E+0 8 0.000E+00 5.870E+04 MO-99 0.000E+00 5.65 0E+0 6 0.000E+00 1.2 9 0E+07 0.000E+00 1.010E+07 0.000E+00 1.0 8 0E+0 6 T C-99 M 2.740E+00 7.630E+00 0.000E+00 1.140E+02 4.240E+00 5.010E+03 0.000E+00 9.89 0E+01 T C-101 7.640E-31 1.0 9 0E-30 0.000E+00 1.970E-2 9 6.620E-31 1.86 0E-37 0.000E+00 1.070E-2 9 RU-103 6.820E+0 6 0.000E+00 0.000E+00 2.400E+07 0.000E+00 5.700E+0 8 0.000E+00 2.920E+0 6 RU-10 5 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-10 6 3.100E+0 8 0.000E+00 0.000E+00 5.970E+0 8 0.000E+00 1.4 8 0E+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+0 9 0.000E+00 8.720E+0 6 T E-12 5 M 1.4 8 0E+0 8 5.340E+07 4.140E+07 0.000E+00 0.000E+00 4.370E+0 8 0.000E+00 1.98 0E+07 T E-127 5.330E+03 1.89 0E+03 3.68 0E+03 2.1 6 0E+04 0.000E+00 4.120E+0 5 0.000E+00 1.1 5 0E+03 T E-127M 5.510E+0 8 1.96 0E+0 8 1.310E+0 8 2.240E+0 9 0.000E+00 1.370E+0 9 0.000E+00 6.56 0E+07 T E-12 9 7.140E-04 2.66 0E-04 5.100E-04 3.000E-03 0.000E+00 3.910E-03 0.000E+00 1.740E-04 T E-12 9 M 3.620E+0 8 1.340E+0 8 1.170E+0 8 1.510E+0 9 0.000E+00 1.3 6 0E+0 9 0.000E+00 5.730E+07 T E-131 1.3 9 0E-1 5 5.7 5 0E-1 6 1.070E-1 5 6.100E-1 5 0.000E+00 1.140E-1 6 0.000E+00 4.3 6 0E-1 6 T E-131M 8.440E+0 5 4.0 5 0E+0 5 6.0 9 0E+0 5 4.220E+0 6 0.000E+00 3.2 5 0E+07 0.000E+00 3.3 8 0E+0 5 T E-132 3.910E+0 6 2.470E+0 6 2.610E+0 6 2.370E+07 0.000E+00 7.840E+07 0.000E+00 2.330E+0 6 I-130 3.510E+0 5 1.010E+0 6 8.2 8 0E+07 1.56 0E+0 6 0.000E+00 7.800E+0 5 0.000E+00 4.0 5 0E+0 5 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X H R i Teen Dose Factors for use in the Gaseous Dose Calculations Appendix H Ri T een Vegetation - Page 3 of 3 Agegroup: TEEN Pathway: Vegetation (VEG) Units: m 2*mrem/yr / µµµµCi/sec; mrem/yr / µµµµCi/m 3 (H-3) Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in Total Body I-131 7.69 0E+07 1.0 8 0E+0 8 3.140E+10 1.85 0E+0 8 0.000E+00 2.130E+07 0.000E+00 5.7 8 0E+07 I-132 5.1 9 0E+01 1.3 6 0E+02 4.58 0E+03 2.140E+02 0.000E+00 5.920E+01 0.000E+00 4.88 0E+01 I-133 1.940E+0 6 3.2 9 0E+0 6 4.59 0E+0 8 5.7 6 0E+0 6 0.000E+00 2.4 9 0E+0 6 0.000E+00 1.000E+0 6 I-134 8.720E-0 5 2.310E-04 3.85 0E-03 3.640E-04 0.000E+00 3.0 5 0E-0 6 0.000E+00 8.310E-0 5 I-13 5 3.520E+04 9.070E+04 5.830E+0 6 1.430E+0 5 0.000E+00 1.000E+0 5 0.000E+00 3.3 6 0E+04 CS-134 7.100E+0 9 1.670E+10 0.000E+00 5.310E+0 9 2.030E+0 9 2.0 8 0E+0 8 0.000E+00 7.7 5 0E+0 9 CS-13 6 4.370E+07 1.720E+0 8 0.000E+00 9.370E+07 1.4 8 0E+07 1.3 8 0E+07 0.000E+00 1.1 6 0E+0 8 CS-137 1.010E+10 1.3 5 0E+10 0.000E+00 4.59 0E+0 9 1.7 8 0E+0 9 1.920E+0 8 0.000E+00 4.69 0E+0 9 CS-13 8 3.610E-11 6.940E-11 0.000E+00 5.120E-11 5.96 0E-12 3.1 5 0E-14 0.000E+00 3.470E-11 BA-13 9 2.69 0E-02 1.89 0E-0 5 0.000E+00 1.7 8 0E-0 5 1.300E-0 5 2.400E-01 0.000E+00 7.830E-04 BA-140 1.3 8 0E+0 8 1.69 0E+0 5 0.000E+00 5.740E+04 1.140E+0 5 2.130E+0 8 0.000E+00 8.900E+0 6 BA-141 1.0 8 0E-21 8.040E-2 5 0.000E+00 7.4 6 0E-2 5 5.500E-2 5 2.2 9 0E-27 0.000E+00 3.59 0E-23 BA-142 5.4 9 0E-3 9 5.4 9 0E-42 0.000E+00 4.640E-42 3.65 0E-42 1.68 0E-5 0 0.000E+00 3.3 8 0E-40 LA-140 1.810E+03 8.88 0E+02 0.000E+00 0.000E+00 0.000E+00 5.100E+07 0.000E+00 2.3 6 0E+02 LA-142 1.85 0E-04 8.240E-0 5 0.000E+00 0.000E+00 0.000E+00 2.510E+00 0.000E+00 2.0 5 0E-0 5 CE-141 2.830E+0 5 1.89 0E+0 5 0.000E+00 8.89 0E+04 0.000E+00 5.400E+0 8 0.000E+00 2.170E+04 CE-143 9.330E+02 6.7 9 0E+0 5 0.000E+00 3.040E+02 0.000E+00 2.040E+07 0.000E+00 7.58 0E+01 CE-144 5.270E+07 2.1 8 0E+07 0.000E+00 1.300E+07 0.000E+00 1.330E+10 0.000E+00 2.830E+0 6 PR-143 7.000E+04 2.800E+04 0.000E+00 1.630E+04 0.000E+00 2.300E+0 8 0.000E+00 3.4 9 0E+03 PR-144 2.900E-2 6 1.1 9 0E-2 6 0.000E+00 6.800E-27 0.000E+00 3.1 9 0E-2 9 0.000E+00 1.470E-27 N D-147 3.620E+04 3.940E+04 0.000E+00 2.310E+04 0.000E+00 1.420E+0 8 0.000E+00 2.3 6 0E+03 W-1 8 7 3.540E+04 2.88 0E+04 0.000E+00 0.000E+00 0.000E+00 7.800E+0 6 0.000E+00 1.010E+04 NP-23 9 1.3 9 0E+03 1.310E+02 0.000E+00 4.100E+02 0.000E+00 2.100E+07 0.000E+00 7.2 6 0E+01 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X H R i Teen Dose Factors for use in the Gaseous Dose Calculations Appendix H Ri T een Inhalation - Page 1 of 3 Agegroup:

TEEN Pathway: Inhalation (INHL) Units: mrem/yr / µµµµCi/m 3 Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in 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 1.3 8 0E+04 1.3 8 0E+04 1.3 8 0E+04 1.3 8 0E+04 1.3 8 0E+04 1.3 8 0E+04 0.000E+00 1.3 8 0E+04 P-32 1.89 0E+0 6 1.100E+0 5 0.000E+00 0.000E+00 0.000E+00 9.2 8 0E+04 0.000E+00 7.1 6 0E+04 CR-5 1 0.000E+00 0.000E+00 7.500E+01 3.070E+01 2.100E+04 3.000E+03 0.000E+00 1.3 5 0E+02 MN-5 4 0.000E+00 5.110E+04 0.000E+00 1.270E+04 1.98 0E+0 6 6.68 0E+04 0.000E+00 8.400E+03 MN-56 0.000E+00 1.700E+00 0.000E+00 1.7 9 0E+00 1.520E+04 5.740E+04 0.000E+00 2.520E-01 FE-55 3.340E+04 2.3 8 0E+04 0.000E+00 0.000E+00 1.240E+0 5 6.3 9 0E+03 0.000E+00 5.540E+03 FE-59 1.59 0E+04 3.700E+04 0.000E+00 0.000E+00 1.530E+0 6 1.7 8 0E+0 5 0.000E+00 1.430E+04 CO-58 0.000E+00 2.070E+03 0.000E+00 0.000E+00 1.340E+0 6 9.520E+04 0.000E+00 2.7 8 0E+03 CO-6 0 0.000E+00 1.510E+04 0.000E+00 0.000E+00 8.720E+0 6 2.59 0E+0 5 0.000E+00 1.98 0E+04 NI-6 3 5.800E+0 5 4.340E+04 0.000E+00 0.000E+00 3.070E+0 5 1.420E+04 0.000E+00 1.98 0E+04 NI-65 2.1 8 0E+00 2.930E-01 0.000E+00 0.000E+00 9.3 6 0E+03 3.670E+04 0.000E+00 1.270E-01 CU-6 4 0.000E+00 2.030E+00 0.000E+00 6.410E+00 1.110E+04 6.140E+04 0.000E+00 8.4 8 0E-01 Z N-65 3.86 0E+04 1.340E+0 5 0.000E+00 8.640E+04 1.240E+0 6 4.66 0E+04 0.000E+00 6.240E+04 Z N-69 4.830E-02 9.200E-02 0.000E+00 6.020E-02 1.58 0E+03 2.85 0E+02 0.000E+00 6.4 6 0E-03 BR-8 3 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-8 4 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+0 5 0.000E+00 0.000E+00 0.000E+00 1.770E+04 0.000E+00 8.400E+04 RB-88 0.000E+00 5.4 6 0E+02 0.000E+00 0.000E+00 0.000E+00 2.920E-0 5 0.000E+00 2.720E+02 RB-89 0.000E+00 3.520E+02 0.000E+00 0.000E+00 0.000E+00 3.3 8 0E-07 0.000E+00 2.330E+02 SR-89 4.340E+0 5 0.000E+00 0.000E+00 0.000E+00 2.420E+0 6 3.710E+0 5 0.000E+00 1.2 5 0E+04 SR-9 0 1.0 8 0E+0 8 0.000E+00 0.000E+00 0.000E+00 1.65 0E+07 7.65 0E+0 5 0.000E+00 6.68 0E+0 6 SR-9 1 8.800E+01 0.000E+00 0.000E+00 0.000E+00 6.070E+04 2.59 0E+0 5 0.000E+00 3.510E+00 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X H R i Teen Dose Factors for use in the Gaseous Dose Calculations Appendix H Ri T een Inhalation - Page 2 of 3 Agegroup:

TEEN Pathway: Inhalation (INHL) Units: mrem/yr / µµµµCi/m 3 Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in Total Body SR-9 2 9.520E+00 0.000E+00 0.000E+00 0.000E+00 2.740E+04 1.1 9 0E+0 5 0.000E+00 4.0 6 0E-01 Y-9 0 2.98 0E+03 0.000E+00 0.000E+00 0.000E+00 2.930E+0 5 5.59 0E+0 5 0.000E+00 8.000E+01 Y-9 1 6.610E+0 5 0.000E+00 0.000E+00 0.000E+00 2.940E+0 6 4.0 9 0E+0 5 0.000E+00 1.770E+04 Y-9 1M 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-9 2 1.470E+01 0.000E+00 0.000E+00 0.000E+00 2.68 0E+04 1.65 0E+0 5 0.000E+00 4.2 9 0E-01 Y-9 3 1.3 5 0E+02 0.000E+00 0.000E+00 0.000E+00 8.320E+04 5.7 9 0E+0 5 0.000E+00 3.720E+00 Z R-95 1.4 6 0E+0 5 4.58 0E+04 0.000E+00 6.740E+04 2.69 0E+0 6 1.4 9 0E+0 5 0.000E+00 3.1 5 0E+04 Z R-9 7 1.3 8 0E+02 2.720E+01 0.000E+00 4.120E+01 1.300E+0 5 6.300E+0 5 0.000E+00 1.2 6 0E+01 NB-95 1.86 0E+04 1.030E+04 0.000E+00 1.000E+04 7.510E+0 5 9.68 0E+04 0.000E+00 5.66 0E+03 MO-99 0.000E+00 1.69 0E+02 0.000E+00 4.110E+02 1.540E+0 5 2.69 0E+0 5 0.000E+00 3.220E+01 T C-99 M 1.3 8 0E-03 3.86 0E-03 0.000E+00 5.7 6 0E-02 1.1 5 0E+03 6.130E+03 0.000E+00 4.99 0E-02 T C-101 5.920E-0 5 8.400E-0 5 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+0 5 1.0 9 0E+0 5 0.000E+00 8.96 0E+02 RU-10 5 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-10 6 9.840E+04 0.000E+00 0.000E+00 1.900E+0 5 1.610E+07 9.600E+0 5 0.000E+00 1.240E+04 AG-110M 1.3 8 0E+04 1.310E+04 0.000E+00 2.500E+04 6.7 5 0E+0 6 2.730E+0 5 0.000E+00 7.99 0E+03 T E-12 5 M 4.88 0E+03 2.240E+03 1.400E+03 0.000E+00 5.3 6 0E+0 5 7.500E+04 0.000E+00 6.670E+02 T E-127 2.010E+00 9.120E-01 1.420E+00 7.2 8 0E+00 1.120E+04 8.0 8 0E+04 0.000E+00 4.420E-01 T E-127M 1.800E+04 8.1 6 0E+03 4.3 8 0E+03 6.540E+04 1.66 0E+0 6 1.59 0E+0 5 0.000E+00 2.1 8 0E+03 T E-12 9 7.100E-02 3.3 8 0E-02 5.1 8 0E-02 2.66 0E-01 3.300E+03 1.620E+03 0.000E+00 1.7 6 0E-02 T E-12 9 M 1.3 9 0E+04 6.58 0E+03 4.58 0E+03 5.1 9 0E+04 1.98 0E+0 6 4.0 5 0E+0 5 0.000E+00 2.2 5 0E+03 T E-131 1.58 0E-02 8.320E-03 1.240E-02 6.1 8 0E-02 2.340E+03 1.510E+01 0.000E+00 5.040E-03 T E-131M 9.840E+01 6.010E+01 7.2 5 0E+01 4.3 9 0E+02 2.3 8 0E+0 5 6.210E+0 5 0.000E+00 4.020E+01 T E-132 3.600E+02 2.900E+02 2.4 6 0E+02 1.95 0E+03 4.4 9 0E+0 5 4.630E+0 5 0.000E+00 2.1 9 0E+02 I-130 6.240E+03 1.7 9 0E+04 1.4 9 0E+0 6 2.7 5 0E+04 0.000E+00 9.120E+03 0.000E+00 7.170E+03 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X H R i Teen Dose Factors for use in the Gaseous Dose Calculations Appendix H Ri T een Inhalation - Page 3 of 3 Agegroup:

TEEN Pathway: Inhalation (INHL) Units: mrem/yr / µµµµCi/m 3 Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in Total Body I-131 3.540E+04 4.910E+04 1.4 6 0E+07 8.400E+04 0.000E+00 6.4 9 0E+03 0.000E+00 2.640E+04 I-132 1.59 0E+03 4.3 8 0E+03 1.510E+0 5 6.920E+03 0.000E+00 1.270E+03 0.000E+00 1.58 0E+03 I-133 1.220E+04 2.0 5 0E+04 2.920E+0 6 3.59 0E+04 0.000E+00 1.030E+04 0.000E+00 6.220E+03 I-134 8.88 0E+02 2.320E+03 3.95 0E+04 3.66 0E+03 0.000E+00 2.040E+01 0.000E+00 8.400E+02 I-13 5 3.700E+03 9.440E+03 6.210E+0 5 1.4 9 0E+04 0.000E+00 6.95 0E+03 0.000E+00 3.4 9 0E+03 CS-134 5.020E+0 5 1.130E+0 6 0.000E+00 3.7 5 0E+0 5 1.4 6 0E+0 5 9.7 6 0E+03 0.000E+00 5.4 9 0E+0 5 CS-13 6 5.1 5 0E+04 1.940E+0 5 0.000E+00 1.100E+0 5 1.7 8 0E+04 1.0 9 0E+04 0.000E+00 1.370E+0 5 CS-137 6.700E+0 5 8.4 8 0E+0 5 0.000E+00 3.040E+0 5 1.210E+0 5 8.4 8 0E+03 0.000E+00 3.110E+0 5 CS-13 8 4.66 0E+02 8.56 0E+02 0.000E+00 6.620E+02 7.870E+01 2.700E-01 0.000E+00 4.4 6 0E+02 BA-13 9 1.340E+00 9.440E-04 0.000E+00 8.88 0E-04 6.4 6 0E+03 6.4 5 0E+03 0.000E+00 3.900E-02 BA-140 5.470E+04 6.700E+01 0.000E+00 2.2 8 0E+01 2.030E+0 6 2.2 9 0E+0 5 0.000E+00 3.520E+03 BA-141 1.420E-01 1.0 6 0E-04 0.000E+00 9.840E-0 5 3.2 9 0E+03 7.4 6 0E-04 0.000E+00 4.740E-03 BA-142 3.700E-02 3.700E-0 5 0.000E+00 3.140E-0 5 1.910E+03 4.7 9 0E-10 0.000E+00 2.270E-03 LA-140 4.7 9 0E+02 2.3 6 0E+02 0.000E+00 0.000E+00 2.140E+0 5 4.870E+0 5 0.000E+00 6.2 6 0E+01 LA-142 9.600E-01 4.2 5 0E-01 0.000E+00 0.000E+00 1.020E+04 1.200E+04 0.000E+00 1.0 6 0E-01 CE-141 2.840E+04 1.900E+04 0.000E+00 8.88 0E+03 6.140E+0 5 1.2 6 0E+0 5 0.000E+00 2.170E+03 CE-143 2.66 0E+02 1.940E+02 0.000E+00 8.640E+01 1.300E+0 5 2.55 0E+0 5 0.000E+00 2.1 6 0E+01 CE-144 4.89 0E+0 6 2.020E+0 6 0.000E+00 1.210E+0 6 1.340E+07 8.640E+0 5 0.000E+00 2.620E+0 5 PR-143 1.340E+04 5.310E+03 0.000E+00 3.0 9 0E+03 4.830E+0 5 2.140E+0 5 0.000E+00 6.620E+02 PR-144 4.300E-02 1.7 6 0E-02 0.000E+00 1.010E-02 1.7 5 0E+03 2.3 5 0E-04 0.000E+00 2.1 8 0E-03 N D-147 7.86 0E+03 8.56 0E+03 0.000E+00 5.020E+03 3.720E+0 5 1.820E+0 5 0.000E+00 5.130E+02 W-1 8 7 1.200E+01 9.7 6 0E+00 0.000E+00 0.000E+00 4.740E+04 1.770E+0 5 0.000E+00 3.430E+00 NP-23 9 3.3 8 0E+02 3.1 9 0E+01 0.000E+00 1.000E+02 6.4 9 0E+04 1.320E+0 5 0.000E+00 1.770E+01 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X H R i Teen Dose Factors for use in the Gaseous Dose Calculations Appendix H Ri T een Ground Plane Deposition - Page 1 of 3 Agegroup:

TEEN Pathway: Ground Plane Deposition (GPD) Units: m 2*mrem/yr / µµµµCi/sec Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in 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 1.1 9 0E+07 1.1 9 0E+07 1.1 9 0E+07 1.1 9 0E+07 1.1 9 0E+07 1.1 9 0E+07 1.3 9 0E+07 1.1 9 0E+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-5 1 4.66 0E+0 6 4.66 0E+0 6 4.66 0E+0 6 4.66 0E+0 6 4.66 0E+0 6 4.66 0E+0 6 5.510E+0 6 4.66 0E+0 6 MN-5 4 1.3 9 0E+0 9 1.3 9 0E+0 9 1.3 9 0E+0 9 1.3 9 0E+0 9 1.3 9 0E+0 9 1.3 9 0E+0 9 1.630E+0 9 1.3 9 0E+0 9 MN-56 9.020E+0 5 9.020E+0 5 9.020E+0 5 9.020E+0 5 9.020E+0 5 9.020E+0 5 1.070E+0 6 9.020E+0 5 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+0 8 2.730E+0 8 2.730E+0 8 2.730E+0 8 2.730E+0 8 2.730E+0 8 3.210E+0 8 2.730E+0 8 CO-58 3.7 9 0E+0 8 3.7 9 0E+0 8 3.7 9 0E+0 8 3.7 9 0E+0 8 3.7 9 0E+0 8 3.7 9 0E+0 8 4.440E+0 8 3.7 9 0E+0 8 CO-6 0 2.1 5 0E+10 2.1 5 0E+10 2.1 5 0E+10 2.1 5 0E+10 2.1 5 0E+10 2.1 5 0E+10 2.530E+10 2.1 5 0E+10 NI-6 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 NI-65 2.970E+0 5 2.970E+0 5 2.970E+0 5 2.970E+0 5 2.970E+0 5 2.970E+0 5 3.4 5 0E+0 5 2.970E+0 5 CU-6 4 6.070E+0 5 6.070E+0 5 6.070E+0 5 6.070E+0 5 6.070E+0 5 6.070E+0 5 6.88 0E+0 5 6.070E+0 5 Z N-65 7.470E+0 8 7.470E+0 8 7.470E+0 8 7.470E+0 8 7.470E+0 8 7.470E+0 8 8.59 0E+0 8 7.470E+0 8 Z N-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-8 3 4.870E+03 4.870E+03 4.870E+03 4.870E+03 4.870E+03 4.870E+03 7.0 8 0E+03 4.870E+03 BR-8 4 2.030E+0 5 2.030E+0 5 2.030E+0 5 2.030E+0 5 2.030E+0 5 2.030E+0 5 2.3 6 0E+0 5 2.030E+0 5 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 8.99 0E+0 6 8.99 0E+0 6 8.99 0E+0 6 8.99 0E+0 6 8.99 0E+0 6 8.99 0E+0 6 1.030E+07 8.99 0E+0 6 RB-88 3.310E+04 3.310E+04 3.310E+04 3.310E+04 3.310E+04 3.310E+04 3.7 8 0E+04 3.310E+04 RB-89 1.230E+0 5 1.230E+0 5 1.230E+0 5 1.230E+0 5 1.230E+0 5 1.230E+0 5 1.4 8 0E+0 5 1.230E+0 5 SR-89 2.1 6 0E+04 2.1 6 0E+04 2.1 6 0E+04 2.1 6 0E+04 2.1 6 0E+04 2.1 6 0E+04 2.510E+04 2.1 6 0E+04 SR-9 0 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-9 1 2.1 5 0E+0 6 2.1 5 0E+0 6 2.1 5 0E+0 6 2.1 5 0E+0 6 2.1 5 0E+0 6 2.1 5 0E+0 6 2.510E+0 6 2.1 5 0E+0 6 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X H R i Teen Dose Factors for use in the Gaseous Dose Calculations Appendix H Ri T een Ground Plane Deposition - Page 2 of 3 Agegroup:

TEEN Pathway: Ground Plane Deposition (GPD) Units: m 2*mrem/yr / µµµµCi/sec Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in Total Body SR-9 2 7.770E+0 5 7.770E+0 5 7.770E+0 5 7.770E+0 5 7.770E+0 5 7.770E+0 5 8.630E+0 5 7.770E+0 5 Y-9 0 4.4 9 0E+03 4.4 9 0E+03 4.4 9 0E+03 4.4 9 0E+03 4.4 9 0E+03 4.4 9 0E+03 5.310E+03 4.4 9 0E+03 Y-9 1 1.070E+0 6 1.070E+0 6 1.070E+0 6 1.070E+0 6 1.070E+0 6 1.070E+0 6 1.210E+0 6 1.070E+0 6 Y-9 1M 1.000E+0 5 1.000E+0 5 1.000E+0 5 1.000E+0 5 1.000E+0 5 1.000E+0 5 1.1 6 0E+0 5 1.000E+0 5 Y-9 2 1.800E+0 5 1.800E+0 5 1.800E+0 5 1.800E+0 5 1.800E+0 5 1.800E+0 5 2.140E+0 5 1.800E+0 5 Y-9 3 1.830E+0 5 1.830E+0 5 1.830E+0 5 1.830E+0 5 1.830E+0 5 1.830E+0 5 2.510E+0 5 1.830E+0 5 Z R-95 2.4 5 0E+0 8 2.4 5 0E+0 8 2.4 5 0E+0 8 2.4 5 0E+0 8 2.4 5 0E+0 8 2.4 5 0E+0 8 2.840E+0 8 2.4 5 0E+0 8 Z R-9 7 2.96 0E+0 6 2.96 0E+0 6 2.96 0E+0 6 2.96 0E+0 6 2.96 0E+0 6 2.96 0E+0 6 3.440E+0 6 2.96 0E+0 6 NB-95 1.370E+0 8 1.370E+0 8 1.370E+0 8 1.370E+0 8 1.370E+0 8 1.370E+0 8 1.610E+0 8 1.370E+0 8 MO-99 3.99 0E+0 6 3.99 0E+0 6 3.99 0E+0 6 3.99 0E+0 6 3.99 0E+0 6 3.99 0E+0 6 4.630E+0 6 3.99 0E+0 6 T C-99 M 1.840E+0 5 1.840E+0 5 1.840E+0 5 1.840E+0 5 1.840E+0 5 1.840E+0 5 2.110E+0 5 1.840E+0 5 T C-101 2.040E+04 2.040E+04 2.040E+04 2.040E+04 2.040E+04 2.040E+04 2.2 6 0E+04 2.040E+04 RU-103 1.0 8 0E+0 8 1.0 8 0E+0 8 1.0 8 0E+0 8 1.0 8 0E+0 8 1.0 8 0E+0 8 1.0 8 0E+0 8 1.2 6 0E+0 8 1.0 8 0E+0 8 RU-10 5 6.3 6 0E+0 5 6.3 6 0E+0 5 6.3 6 0E+0 5 6.3 6 0E+0 5 6.3 6 0E+0 5 6.3 6 0E+0 5 7.210E+0 5 6.3 6 0E+0 5 RU-10 6 4.220E+0 8 4.220E+0 8 4.220E+0 8 4.220E+0 8 4.220E+0 8 4.220E+0 8 5.070E+0 8 4.220E+0 8 AG-110M 3.440E+0 9 3.440E+0 9 3.440E+0 9 3.440E+0 9 3.440E+0 9 3.440E+0 9 4.010E+0 9 3.440E+0 9 T E-12 5 M 1.55 0E+0 6 1.55 0E+0 6 1.55 0E+0 6 1.55 0E+0 6 1.55 0E+0 6 1.55 0E+0 6 2.130E+0 6 1.55 0E+0 6 T E-127 2.98 0E+03 2.98 0E+03 2.98 0E+03 2.98 0E+03 2.98 0E+03 2.98 0E+03 3.2 8 0E+03 2.98 0E+03 T E-127M 9.1 6 0E+04 9.1 6 0E+04 9.1 6 0E+04 9.1 6 0E+04 9.1 6 0E+04 9.1 6 0E+04 1.0 8 0E+0 5 9.1 6 0E+04 T E-12 9 2.620E+04 2.620E+04 2.620E+04 2.620E+04 2.620E+04 2.620E+04 3.100E+04 2.620E+04 T E-12 9 M 1.98 0E+07 1.98 0E+07 1.98 0E+07 1.98 0E+07 1.98 0E+07 1.98 0E+07 2.310E+07 1.98 0E+07 T E-131 2.920E+04 2.920E+04 2.920E+04 2.920E+04 2.920E+04 2.920E+04 3.4 5 0E+07 2.920E+04 T E-131M 8.030E+0 6 8.030E+0 6 8.030E+0 6 8.030E+0 6 8.030E+0 6 8.030E+0 6 9.4 6 0E+0 6 8.030E+0 6 T E-132 4.230E+0 6 4.230E+0 6 4.230E+0 6 4.230E+0 6 4.230E+0 6 4.230E+0 6 4.98 0E+0 6 4.230E+0 6 I-130 5.510E+0 6 5.510E+0 6 5.510E+0 6 5.510E+0 6 5.510E+0 6 5.510E+0 6 6.69 0E+0 6 5.510E+0 6 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X H R i Teen Dose Factors for use in the Gaseous Dose Calculations Appendix H Ri T een Ground Plane Deposition - Page 3 of 3 Agegroup:

TEEN Pathway: Ground Plane Deposition (GPD) Units: m 2*mrem/yr / µµµµCi/sec Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in Total Body I-131 1.720E+07 1.720E+07 1.720E+07 1.720E+07 1.720E+07 1.720E+07 2.0 9 0E+07 1.720E+07 I-132 1.2 5 0E+0 6 1.2 5 0E+0 6 1.2 5 0E+0 6 1.2 5 0E+0 6 1.2 5 0E+0 6 1.2 5 0E+0 6 1.470E+0 6 1.2 5 0E+0 6 I-133 2.4 5 0E+0 6 2.4 5 0E+0 6 2.4 5 0E+0 6 2.4 5 0E+0 6 2.4 5 0E+0 6 2.4 5 0E+0 6 2.98 0E+0 6 2.4 5 0E+0 6 I-134 4.470E+0 5 4.470E+0 5 4.470E+0 5 4.470E+0 5 4.470E+0 5 4.470E+0 5 5.300E+0 5 4.470E+0 5 I-13 5 2.530E+0 6 2.530E+0 6 2.530E+0 6 2.530E+0 6 2.530E+0 6 2.530E+0 6 2.95 0E+0 6 2.530E+0 6 CS-134 6.86 0E+0 9 6.86 0E+0 9 6.86 0E+0 9 6.86 0E+0 9 6.86 0E+0 9 6.86 0E+0 9 8.000E+0 9 6.86 0E+0 9 CS-13 6 1.510E+0 8 1.510E+0 8 1.510E+0 8 1.510E+0 8 1.510E+0 8 1.510E+0 8 1.710E+0 8 1.510E+0 8 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-13 8 3.59 0E+0 5 3.59 0E+0 5 3.59 0E+0 5 3.59 0E+0 5 3.59 0E+0 5 3.59 0E+0 5 4.100E+0 5 3.59 0E+0 5 BA-13 9 1.0 6 0E+0 5 1.0 6 0E+0 5 1.0 6 0E+0 5 1.0 6 0E+0 5 1.0 6 0E+0 5 1.0 6 0E+0 5 1.1 9 0E+0 5 1.0 6 0E+0 5 BA-140 2.0 5 0E+07 2.0 5 0E+07 2.0 5 0E+07 2.0 5 0E+07 2.0 5 0E+07 2.0 5 0E+07 2.3 5 0E+07 2.0 5 0E+07 BA-141 4.170E+04 4.170E+04 4.170E+04 4.170E+04 4.170E+04 4.170E+04 4.7 5 0E+04 4.170E+04 BA-142 4.4 9 0E+04 4.4 9 0E+04 4.4 9 0E+04 4.4 9 0E+04 4.4 9 0E+04 4.4 9 0E+04 5.110E+04 4.4 9 0E+04 LA-140 1.920E+07 1.920E+07 1.920E+07 1.920E+07 1.920E+07 1.920E+07 2.1 8 0E+07 1.920E+07 LA-142 7.600E+0 5 7.600E+0 5 7.600E+0 5 7.600E+0 5 7.600E+0 5 7.600E+0 5 9.120E+0 5 7.600E+0 5 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+0 6 2.310E+0 6 2.310E+0 6 2.310E+0 6 2.310E+0 6 2.310E+0 6 2.630E+0 6 2.310E+0 6 CE-144 6.95 0E+07 6.95 0E+07 6.95 0E+07 6.95 0E+07 6.95 0E+07 6.95 0E+07 8.040E+07 6.95 0E+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 N D-147 8.3 9 0E+0 6 8.3 9 0E+0 6 8.3 9 0E+0 6 8.3 9 0E+0 6 8.3 9 0E+0 6 8.3 9 0E+0 6 1.010E+07 8.3 9 0E+0 6 W-1 8 7 2.3 5 0E+0 6 2.3 5 0E+0 6 2.3 5 0E+0 6 2.3 5 0E+0 6 2.3 5 0E+0 6 2.3 5 0E+0 6 2.730E+0 6 2.3 5 0E+0 6 NP-23 9 1.710E+0 6 1.710E+0 6 1.710E+0 6 1.710E+0 6 1.710E+0 6 1.710E+0 6 1.98 0E+0 6 1.710E+0 6 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X I R i Child Dose Factors for use in the Gaseous Dose Calculations Appendix I Ri Child Cow Milk - Page 1 of 3 Agegroup: CHILD Pathway: Grs

/Cow/Mil k (CMIL K) Units: m 2*mrem/yr / µµµµCi/sec; mrem/yr / µµµµCi/m 3 (H-3) Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in 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 1.1 9 0E+0 9 2.3 9 0E+0 8 2.3 9 0E+0 8 2.3 9 0E+0 8 2.3 9 0E+0 8 2.3 9 0E+0 8 0.000E+00 2.3 9 0E+0 8 NA-24 8.85 0E+0 6 8.85 0E+0 6 8.85 0E+0 6 8.85 0E+0 6 8.85 0E+0 6 8.85 0E+0 6 0.000E+00 8.85 0E+0 6 P-32 7.7 8 0E+10 3.640E+0 9 0.000E+00 0.000E+00 0.000E+00 2.1 5 0E+0 9 0.000E+00 3.000E+0 9 CR-5 1 0.000E+00 0.000E+00 5.65 0E+04 1.540E+04 1.030E+0 5 5.400E+0 6 0.000E+00 1.020E+0 5 MN-5 4 0.000E+00 2.100E+07 0.000E+00 5.88 0E+0 6 0.000E+00 1.7 6 0E+07 0.000E+00 5.59 0E+0 6 MN-56 0.000E+00 1.2 6 0E-02 0.000E+00 1.530E-02 0.000E+00 1.830E+00 0.000E+00 2.86 0E-03 FE-55 1.120E+0 8 5.930E+07 0.000E+00 0.000E+00 3.3 5 0E+07 1.100E+07 0.000E+00 1.840E+07 FE-59 1.200E+0 8 1.95 0E+0 8 0.000E+00 0.000E+00 5.640E+07 2.030E+0 8 0.000E+00 9.69 0E+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-6 0 0.000E+00 4.320E+07 0.000E+00 0.000E+00 0.000E+00 2.3 9 0E+0 8 0.000E+00 1.270E+0 8 NI-6 3 2.96 0E+10 1.59 0E+0 9 0.000E+00 0.000E+00 0.000E+00 1.070E+0 8 0.000E+00 1.010E+0 9 NI-65 1.66 0E+00 1.56 0E-01 0.000E+00 0.000E+00 0.000E+00 1.910E+01 0.000E+00 9.100E-02 CU-6 4 0.000E+00 7.4 6 0E+04 0.000E+00 1.800E+0 5 0.000E+00 3.500E+0 6 0.000E+00 4.510E+04 Z N-65 4.130E+0 9 1.100E+10 0.000E+00 6.940E+0 9 0.000E+00 1.930E+0 9 0.000E+00 6.85 0E+0 9 Z N-69 9.4 6 0E-12 1.370E-11 0.000E+00 8.300E-12 0.000E+00 8.620E-10 0.000E+00 1.2 6 0E-12 BR-8 3 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-8 4 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+0 9 0.000E+00 0.000E+00 0.000E+00 5.640E+0 8 0.000E+00 5.3 9 0E+0 9 RB-88 0.000E+00 7.1 6 0E-4 5 0.000E+00 0.000E+00 0.000E+00 3.510E-4 6 0.000E+00 4.970E-4 5 RB-89 0.000E+00 1.340E-5 2 0.000E+00 0.000E+00 0.000E+00 1.170E-5 4 0.000E+00 1.1 9 0E-5 2 SR-89 6.620E+0 9 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.56 0E+0 8 0.000E+00 1.89 0E+0 8 SR-9 0 1.120E+11 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.510E+0 9 0.000E+00 2.830E+10 SR-9 1 1.300E+0 5 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.88 0E+0 5 0.000E+00 4.920E+03 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X I R i Child Dose Factors for use in the Gaseous Dose Calculations Appendix I Ri Child Cow Milk - Page 2 of 3 Agegroup: CHILD Pathway: Grs

/Cow/Mil k (CMIL K) Units: m 2*mrem/yr / µµµµCi/sec; mrem/yr / µµµµCi/m 3 (H-3) Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in Total Body SR-9 2 2.1 8 0E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4.130E+01 0.000E+00 8.7 5 0E-02 Y-9 0 3.220E+02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 9.170E+0 5 0.000E+00 8.620E+00 Y-9 1 3.900E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.200E+0 6 0.000E+00 1.040E+03 Y-9 1M 2.670E-1 9 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.240E-1 6 0.000E+00 9.730E-21 Y-9 2 2.530E-04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 7.310E+00 0.000E+00 7.240E-0 6 Y-9 3 1.010E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.510E+04 0.000E+00 2.7 8 0E-02 Z R-95 3.830E+03 8.420E+02 0.000E+00 1.210E+03 0.000E+00 8.7 9 0E+0 5 0.000E+00 7.500E+02 Z R-9 7 1.920E+00 2.770E-01 0.000E+00 3.98 0E-01 0.000E+00 4.200E+04 0.000E+00 1.640E-01 NB-95 3.1 8 0E+0 5 1.240E+0 5 0.000E+00 1.1 6 0E+0 5 0.000E+00 2.2 9 0E+0 8 0.000E+00 8.840E+04 MO-99 0.000E+00 8.140E+07 0.000E+00 1.740E+0 8 0.000E+00 6.730E+07 0.000E+00 2.010E+07 T C-99 M 1.320E+01 2.59 0E+01 0.000E+00 3.7 6 0E+02 1.320E+01 1.470E+04 0.000E+00 4.2 9 0E+02 T C-101 1.1 6 0E-59 1.220E-59 0.000E+00 2.0 8 0E-58 6.440E-6 0 3.870E-59 0.000E+00 1.540E-58 RU-103 4.2 8 0E+03 0.000E+00 0.000E+00 1.0 8 0E+04 0.000E+00 1.110E+0 5 0.000E+00 1.65 0E+03 RU-10 5 3.820E-03 0.000E+00 0.000E+00 3.3 6 0E-02 0.000E+00 2.4 9 0E+00 0.000E+00 1.3 9 0E-03 RU-10 6 9.240E+04 0.000E+00 0.000E+00 1.2 5 0E+0 5 0.000E+00 1.440E+0 6 0.000E+00 1.1 5 0E+04 AG-110M 2.0 9 0E+0 8 1.410E+0 8 0.000E+00 2.630E+0 8 0.000E+00 1.68 0E+10 0.000E+00 1.130E+0 8 T E-12 5 M 7.3 8 0E+07 2.000E+07 2.070E+07 0.000E+00 0.000E+00 7.120E+07 0.000E+00 9.840E+0 6 T E-127 2.98 0E+03 8.020E+02 2.0 6 0E+03 8.470E+03 0.000E+00 1.1 6 0E+0 5 0.000E+00 6.3 8 0E+02 T E-127M 2.0 8 0E+0 8 5.600E+07 4.970E+07 5.930E+0 8 0.000E+00 1.68 0E+0 8 0.000E+00 2.470E+07 T E-12 9 1.2 8 0E-0 9 3.58 0E-10 9.1 6 0E-10 3.7 5 0E-0 9 0.000E+00 7.99 0E-0 8 0.000E+00 3.0 5 0E-10 T E-12 9 M 2.710E+0 8 7.58 0E+07 8.7 5 0E+07 7.970E+0 8 0.000E+00 3.310E+0 8 0.000E+00 4.210E+07 T E-131 1.620E-32 4.920E-33 1.240E-32 4.89 0E-32 0.000E+00 8.4 9 0E-32 0.000E+00 4.810E-33 T E-131M 1.600E+0 6 5.530E+0 5 1.140E+0 6 5.3 5 0E+0 6 0.000E+00 2.240E+07 0.000E+00 5.89 0E+0 5 T E-132 1.020E+07 4.530E+0 6 6.600E+0 6 4.210E+07 0.000E+00 4.570E+07 0.000E+00 5.4 8 0E+0 6 I-130 1.730E+0 6 3.4 9 0E+0 6 3.840E+0 8 5.220E+0 6 0.000E+00 1.630E+0 6 0.000E+00 1.800E+0 6 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X I R i Child Dose Factors for use in the Gaseous Dose Calculations Appendix I Ri Child Cow Milk - Page 3 of 3 Agegroup: CHILD Pathway: Grs

/Cow/Mil k (CMIL K) Units: m 2*mrem/yr / µµµµCi/sec; mrem/yr / µµµµCi/m 3 (H-3) Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in Total Body I-131 1.300E+0 9 1.310E+0 9 4.330E+11 2.1 5 0E+0 9 0.000E+00 1.170E+0 8 0.000E+00 7.4 5 0E+0 8 I-132 6.89 0E-01 1.270E+00 5.870E+01 1.940E+00 0.000E+00 1.4 9 0E+00 0.000E+00 5.820E-01 I-133 1.720E+07 2.120E+07 3.940E+0 9 3.540E+07 0.000E+00 8.56 0E+0 6 0.000E+00 8.030E+0 6 I-134 8.4 8 0E-12 1.570E-11 3.620E-10 2.410E-11 0.000E+00 1.040E-11 0.000E+00 7.2 5 0E-12 I-13 5 5.400E+04 9.720E+04 8.610E+0 6 1.4 9 0E+0 5 0.000E+00 7.400E+04 0.000E+00 4.600E+04 CS-134 2.2 6 0E+10 3.720E+10 0.000E+00 1.1 5 0E+10 4.130E+0 9 2.000E+0 8 0.000E+00 7.840E+0 9 CS-13 6 1.010E+0 9 2.7 8 0E+0 9 0.000E+00 1.4 8 0E+0 9 2.210E+0 8 9.770E+07 0.000E+00 1.800E+0 9 CS-137 3.220E+10 3.0 9 0E+10 0.000E+00 1.010E+10 3.620E+0 9 1.930E+0 8 0.000E+00 4.55 0E+0 9 CS-13 8 3.98 0E-23 5.530E-23 0.000E+00 3.89 0E-23 4.1 9 0E-24 2.55 0E-23 0.000E+00 3.510E-23 BA-13 9 2.010E-07 1.070E-10 0.000E+00 9.3 6 0E-11 6.300E-11 1.1 6 0E-0 5 0.000E+00 5.820E-0 9 BA-140 1.170E+0 8 1.030E+0 5 0.000E+00 3.340E+04 6.120E+04 5.930E+07 0.000E+00 6.840E+0 6 BA-141 1.85 0E-4 5 1.040E-4 8 0.000E+00 8.96 0E-4 9 6.0 9 0E-4 8 1.0 5 0E-4 5 0.000E+00 6.020E-47 BA-142 1.1 5 0E-7 9 8.310E-8 3 0.000E+00 6.720E-8 3 4.89 0E-8 3 1.510E-8 1 0.000E+00 6.4 5 0E-8 1 LA-140 1.940E+01 6.7 8 0E+00 0.000E+00 0.000E+00 0.000E+00 1.89 0E+0 5 0.000E+00 2.2 9 0E+00 LA-142 8.100E-11 2.58 0E-11 0.000E+00 0.000E+00 0.000E+00 5.120E-0 6 0.000E+00 8.0 9 0E-12 CE-141 2.1 9 0E+04 1.0 9 0E+04 0.000E+00 4.7 8 0E+03 0.000E+00 1.3 6 0E+07 0.000E+00 1.620E+03 CE-143 1.870E+02 1.020E+0 5 0.000E+00 4.2 6 0E+01 0.000E+00 1.4 9 0E+0 6 0.000E+00 1.470E+01 CE-144 1.620E+0 6 5.0 9 0E+0 5 0.000E+00 2.820E+0 5 0.000E+00 1.330E+0 8 0.000E+00 8.66 0E+04 PR-143 7.1 8 0E+02 2.1 6 0E+02 0.000E+00 1.170E+02 0.000E+00 7.7 5 0E+0 5 0.000E+00 3.56 0E+01 PR-144 2.68 0E-5 3 8.2 9 0E-5 4 0.000E+00 4.3 8 0E-5 4 0.000E+00 1.7 8 0E-5 0 0.000E+00 1.3 5 0E-5 4 N D-147 4.4 5 0E+02 3.600E+02 0.000E+00 1.98 0E+02 0.000E+00 5.700E+0 5 0.000E+00 2.7 9 0E+01 W-1 8 7 2.89 0E+04 1.710E+04 0.000E+00 0.000E+00 0.000E+00 2.400E+0 6 0.000E+00 7.670E+03 NP-23 9 1.720E+01 1.240E+00 0.000E+00 3.58 0E+00 0.000E+00 9.170E+04 0.000E+00 8.710E-01 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X I R i Child Dose Factors for use in the Gaseous Dose Calculations Appendix I Ri Child Goat Milk - Page 1 of 3 Agegroup: CHILD Pathway: Grs

/Goat/Mil k (GMIL K) Units: m 2*mrem/yr / µµµµCi/sec; mrem/yr / µµµµCi/m 3 (H-3) Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in 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 1.1 9 0E+0 9 2.3 9 0E+0 8 2.3 9 0E+0 8 2.3 9 0E+0 8 2.3 9 0E+0 8 2.3 9 0E+0 8 0.000E+00 2.3 9 0E+0 8 NA-24 1.0 6 0E+0 6 1.0 6 0E+0 6 1.0 6 0E+0 6 1.0 6 0E+0 6 1.0 6 0E+0 6 1.0 6 0E+0 6 0.000E+00 1.0 6 0E+0 6 P-32 9.330E+10 4.370E+0 9 0.000E+00 0.000E+00 0.000E+00 2.58 0E+0 9 0.000E+00 3.600E+0 9 CR-5 1 0.000E+00 0.000E+00 6.7 8 0E+03 1.85 0E+03 1.240E+04 6.4 8 0E+0 5 0.000E+00 1.220E+04 MN-5 4 0.000E+00 2.520E+0 6 0.000E+00 7.0 6 0E+0 5 0.000E+00 2.110E+0 6 0.000E+00 6.700E+0 5 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 1.4 5 0E+0 6 7.710E+0 5 0.000E+00 0.000E+00 4.3 6 0E+0 5 1.430E+0 5 0.000E+00 2.3 9 0E+0 5 FE-59 1.56 0E+0 6 2.530E+0 6 0.000E+00 0.000E+00 7.330E+0 5 2.630E+0 6 0.000E+00 1.2 6 0E+0 6 CO-58 0.000E+00 1.4 5 0E+0 6 0.000E+00 0.000E+00 0.000E+00 8.4 9 0E+0 6 0.000E+00 4.4 5 0E+0 6 CO-6 0 0.000E+00 5.1 8 0E+0 6 0.000E+00 0.000E+00 0.000E+00 2.870E+07 0.000E+00 1.530E+07 NI-6 3 3.56 0E+0 9 1.900E+0 8 0.000E+00 0.000E+00 0.000E+00 1.2 8 0E+07 0.000E+00 1.210E+0 8 NI-65 1.99 0E-01 1.870E-02 0.000E+00 0.000E+00 0.000E+00 2.2 9 0E+00 0.000E+00 1.0 9 0E-02 CU-6 4 0.000E+00 8.320E+03 0.000E+00 2.010E+04 0.000E+00 3.900E+0 5 0.000E+00 5.020E+03 Z N-65 4.96 0E+0 8 1.320E+0 9 0.000E+00 8.330E+0 8 0.000E+00 2.320E+0 8 0.000E+00 8.220E+0 8 Z N-69 1.140E-12 1.640E-12 0.000E+00 9.96 0E-13 0.000E+00 1.030E-10 0.000E+00 1.520E-13 BR-8 3 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.2 8 0E-02 BR-8 4 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 1.0 5 0E+0 9 0.000E+00 0.000E+00 0.000E+00 6.770E+07 0.000E+00 6.470E+0 8 RB-88 0.000E+00 8.59 0E-4 6 0.000E+00 0.000E+00 0.000E+00 4.210E-47 0.000E+00 5.970E-4 6 RB-89 0.000E+00 1.610E-5 3 0.000E+00 0.000E+00 0.000E+00 1.410E-55 0.000E+00 1.430E-5 3 SR-89 1.3 9 0E+10 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.3 8 0E+0 8 0.000E+00 3.970E+0 8 SR-9 0 2.3 5 0E+11 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.1 6 0E+0 9 0.000E+00 5.95 0E+10 SR-9 1 2.740E+0 5 0.000E+00 0.000E+00 0.000E+00 0.000E+00 6.040E+0 5 0.000E+00 1.030E+04 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X I R i Child Dose Factors for use in the Gaseous Dose Calculations Appendix I Ri Child Goat Milk - Page 2 of 3 Agegroup: CHILD Pathway: Grs

/Goat/Mil k (GMIL K) Units: m 2*mrem/yr / µµµµCi/sec; mrem/yr / µµµµCi/m 3 (H-3) Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in Total Body SR-9 2 4.58 0E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 8.68 0E+01 0.000E+00 1.840E-01 Y-9 0 3.870E+01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.100E+0 5 0.000E+00 1.030E+00 Y-9 1 4.68 0E+03 0.000E+00 0.000E+00 0.000E+00 0.000E+00 6.240E+0 5 0.000E+00 1.2 5 0E+02 Y-9 1M 3.210E-20 0.000E+00 0.000E+00 0.000E+00 0.000E+00 6.2 8 0E-17 0.000E+00 1.170E-21 Y-9 2 3.040E-0 5 0.000E+00 0.000E+00 0.000E+00 0.000E+00 8.770E-01 0.000E+00 8.69 0E-07 Y-9 3 1.210E-01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.810E+03 0.000E+00 3.330E-03 Z R-95 4.600E+02 1.010E+02 0.000E+00 1.4 5 0E+02 0.000E+00 1.0 5 0E+0 5 0.000E+00 9.000E+01 Z R-9 7 2.300E-01 3.330E-02 0.000E+00 4.7 8 0E-02 0.000E+00 5.040E+03 0.000E+00 1.96 0E-02 NB-95 3.810E+04 1.4 9 0E+04 0.000E+00 1.400E+04 0.000E+00 2.7 5 0E+07 0.000E+00 1.0 6 0E+04 MO-99 0.000E+00 9.7 6 0E+0 6 0.000E+00 2.0 9 0E+07 0.000E+00 8.0 8 0E+0 6 0.000E+00 2.420E+0 6 T C-99 M 1.59 0E+00 3.110E+00 0.000E+00 4.520E+01 1.58 0E+00 1.770E+03 0.000E+00 5.1 5 0E+01 T C-101 1.400E-6 0 1.4 6 0E-6 0 0.000E+00 2.4 9 0E-59 7.720E-6 1 4.640E-6 0 0.000E+00 1.85 0E-59 RU-103 5.140E+02 0.000E+00 0.000E+00 1.2 9 0E+03 0.000E+00 1.330E+04 0.000E+00 1.98 0E+02 RU-10 5 4.58 0E-04 0.000E+00 0.000E+00 4.030E-03 0.000E+00 2.99 0E-01 0.000E+00 1.66 0E-04 RU-10 6 1.110E+04 0.000E+00 0.000E+00 1.500E+04 0.000E+00 1.720E+0 5 0.000E+00 1.3 8 0E+03 AG-110M 2.510E+07 1.69 0E+07 0.000E+00 3.1 5 0E+07 0.000E+00 2.010E+0 9 0.000E+00 1.3 5 0E+07 T E-12 5 M 8.85 0E+0 6 2.400E+0 6 2.4 8 0E+0 6 0.000E+00 0.000E+00 8.540E+0 6 0.000E+00 1.1 8 0E+0 6 T E-127 3.570E+02 9.630E+01 2.470E+02 1.020E+03 0.000E+00 1.3 9 0E+04 0.000E+00 7.66 0E+01 T E-127M 2.500E+07 6.720E+0 6 5.970E+0 6 7.120E+07 0.000E+00 2.020E+07 0.000E+00 2.96 0E+0 6 T E-12 9 1.540E-10 4.300E-11 1.100E-10 4.510E-10 0.000E+00 9.59 0E-0 9 0.000E+00 3.66 0E-11 T E-12 9 M 3.2 6 0E+07 9.0 9 0E+0 6 1.0 5 0E+07 9.56 0E+07 0.000E+00 3.970E+07 0.000E+00 5.0 6 0E+0 6 T E-131 1.940E-33 5.910E-34 1.4 8 0E-33 5.86 0E-33 0.000E+00 1.020E-32 0.000E+00 5.770E-34 T E-131M 1.920E+0 5 6.640E+04 1.3 6 0E+0 5 6.420E+0 5 0.000E+00 2.69 0E+0 6 0.000E+00 7.0 6 0E+04 T E-132 1.230E+0 6 5.440E+0 5 7.920E+0 5 5.0 5 0E+0 6 0.000E+00 5.4 8 0E+0 6 0.000E+00 6.570E+0 5 I-130 2.070E+0 6 4.1 9 0E+0 6 4.610E+0 8 6.2 6 0E+0 6 0.000E+00 1.96 0E+0 6 0.000E+00 2.1 6 0E+0 6 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X I R i Child Dose Factors for use in the Gaseous Dose Calculations Appendix I Ri Child Goat Milk - Page 3 of 3 Agegroup: CHILD Pathway: Grs

/Goat/Mil k (GMIL K) Units: m 2*mrem/yr / µµµµCi/sec; mrem/yr / µµµµCi/m 3 (H-3) Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in Total Body I-131 1.56 0E+0 9 1.570E+0 9 5.200E+11 2.58 0E+0 9 0.000E+00 1.400E+0 8 0.000E+00 8.940E+0 8 I-132 8.270E-01 1.520E+00 7.0 5 0E+01 2.330E+00 0.000E+00 1.7 9 0E+00 0.000E+00 6.99 0E-01 I-133 2.0 6 0E+07 2.55 0E+07 4.730E+0 9 4.2 5 0E+07 0.000E+00 1.030E+07 0.000E+00 9.640E+0 6 I-134 1.020E-11 1.89 0E-11 4.3 5 0E-10 2.89 0E-11 0.000E+00 1.2 5 0E-11 0.000E+00 8.700E-12 I-13 5 6.4 8 0E+04 1.170E+0 5 1.030E+07 1.7 9 0E+0 5 0.000E+00 8.88 0E+04 0.000E+00 5.520E+04 CS-134 6.7 9 0E+10 1.110E+11 0.000E+00 3.4 5 0E+10 1.240E+10 6.010E+0 8 0.000E+00 2.3 5 0E+10 CS-13 6 3.030E+0 9 8.340E+0 9 0.000E+00 4.440E+0 9 6.630E+0 8 2.930E+0 8 0.000E+00 5.400E+0 9 CS-137 9.670E+10 9.2 6 0E+10 0.000E+00 3.020E+10 1.0 9 0E+10 5.800E+0 8 0.000E+00 1.370E+10 CS-13 8 1.1 9 0E-22 1.66 0E-22 0.000E+00 1.170E-22 1.2 6 0E-23 7.640E-23 0.000E+00 1.0 5 0E-22 BA-13 9 2.410E-0 8 1.2 9 0E-11 0.000E+00 1.120E-11 7.56 0E-12 1.3 9 0E-0 6 0.000E+00 6.98 0E-10 BA-140 1.410E+07 1.230E+04 0.000E+00 4.010E+03 7.340E+03 7.120E+0 6 0.000E+00 8.200E+0 5 BA-141 2.220E-4 6 1.240E-4 9 0.000E+00 1.0 8 0E-4 9 7.300E-4 9 1.270E-4 6 0.000E+00 7.230E-4 8 BA-142 1.3 9 0E-8 0 9.970E-8 4 0.000E+00 8.070E-8 4 5.870E-8 4 1.810E-8 2 0.000E+00 7.740E-8 2 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+0 6 0.000E+00 1.940E+02 CE-143 2.2 5 0E+01 1.220E+04 0.000E+00 5.120E+00 0.000E+00 1.7 9 0E+0 5 0.000E+00 1.770E+00 CE-144 1.95 0E+0 5 6.110E+04 0.000E+00 3.3 8 0E+04 0.000E+00 1.59 0E+07 0.000E+00 1.040E+04 PR-143 8.620E+01 2.59 0E+01 0.000E+00 1.400E+01 0.000E+00 9.300E+04 0.000E+00 4.2 8 0E+00 PR-144 3.220E-5 4 9.95 0E-55 0.000E+00 5.2 6 0E-55 0.000E+00 2.140E-5 1 0.000E+00 1.620E-55 N D-147 5.330E+01 4.320E+01 0.000E+00 2.370E+01 0.000E+00 6.85 0E+04 0.000E+00 3.3 5 0E+00 W-1 8 7 3.470E+03 2.0 5 0E+03 0.000E+00 0.000E+00 0.000E+00 2.88 0E+0 5 0.000E+00 9.210E+02 NP-23 9 2.070E+00 1.4 9 0E-01 0.000E+00 4.300E-01 0.000E+00 1.100E+04 0.000E+00 1.040E-01 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X I R i Child Dose Factors for use in the Gaseous Dose Calculations Appendix I Ri Child Cow Meat - Page 1 of 3 Agegroup: CHILD Pathway: Grs

/Cow/Meat (CMEAT) Units: m 2*mrem/yr / µµµµCi/sec; mrem/yr / µµµµCi/m 3 (H-3) Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in 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+0 8 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+0 9 3.470E+0 8 0.000E+00 0.000E+00 0.000E+00 2.0 5 0E+0 8 0.000E+00 2.86 0E+0 8 CR-5 1 0.000E+00 0.000E+00 4.88 0E+03 1.330E+03 8.910E+03 4.66 0E+0 5 0.000E+00 8.7 9 0E+03 MN-5 4 0.000E+00 8.010E+0 6 0.000E+00 2.2 5 0E+0 6 0.000E+00 6.720E+0 6 0.000E+00 2.130E+0 6 MN-56 0.000E+00 1.430E-5 3 0.000E+00 1.730E-5 3 0.000E+00 2.070E-5 1 0.000E+00 3.230E-5 4 FE-55 4.570E+0 8 2.420E+0 8 0.000E+00 0.000E+00 1.370E+0 8 4.4 9 0E+07 0.000E+00 7.510E+07 FE-59 3.7 6 0E+0 8 6.0 9 0E+0 8 0.000E+00 0.000E+00 1.770E+0 8 6.340E+0 8 0.000E+00 3.030E+0 8 CO-58 0.000E+00 1.640E+07 0.000E+00 0.000E+00 0.000E+00 9.58 0E+07 0.000E+00 5.020E+07 CO-6 0 0.000E+00 6.930E+07 0.000E+00 0.000E+00 0.000E+00 3.840E+0 8 0.000E+00 2.040E+0 8 NI-6 3 2.910E+10 1.56 0E+0 9 0.000E+00 0.000E+00 0.000E+00 1.0 5 0E+0 8 0.000E+00 9.910E+0 8 NI-65 3.520E-5 2 3.310E-5 3 0.000E+00 0.000E+00 0.000E+00 4.0 6 0E-5 1 0.000E+00 1.930E-5 3 CU-6 4 0.000E+00 2.970E-07 0.000E+00 7.1 8 0E-07 0.000E+00 1.3 9 0E-0 5 0.000E+00 1.800E-07 Z N-65 3.7 5 0E+0 8 1.000E+0 9 0.000E+00 6.300E+0 8 0.000E+00 1.7 6 0E+0 8 0.000E+00 6.220E+0 8 Z N-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-8 3 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 9.520E-5 7 BR-8 4 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+0 8 0.000E+00 0.000E+00 0.000E+00 3.710E+07 0.000E+00 3.55 0E+0 8 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+0 8 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.870E+07 0.000E+00 1.3 8 0E+07 SR-9 0 1.040E+10 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.400E+0 8 0.000E+00 2.640E+0 9 SR-9 1 2.400E-10 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.300E-10 0.000E+00 9.0 5 0E-12 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X I R i Child Dose Factors for use in the Gaseous Dose Calculations Appendix I Ri Child Cow Meat - Page 2 of 3 Agegroup: CHILD Pathway: Grs

/Cow/Meat (CMEAT) Units: m 2*mrem/yr / µµµµCi/sec; mrem/yr / µµµµCi/m 3 (H-3) Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in Total Body SR-9 2 1.85 0E-4 9 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.4 9 0E-4 8 0.000E+00 7.400E-5 1 Y-9 0 1.710E+02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4.88 0E+0 5 0.000E+00 4.59 0E+00 Y-9 1 1.800E+0 6 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.400E+0 8 0.000E+00 4.820E+04 Y-9 1M 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-9 2 2.410E-3 9 0.000E+00 0.000E+00 0.000E+00 0.000E+00 6.96 0E-3 5 0.000E+00 6.89 0E-41 Y-9 3 7.440E-12 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.110E-07 0.000E+00 2.040E-13 Z R-95 2.66 0E+0 6 5.85 0E+0 5 0.000E+00 8.3 8 0E+0 5 0.000E+00 6.110E+0 8 0.000E+00 5.210E+0 5 Z R-9 7 3.200E-0 5 4.630E-0 6 0.000E+00 6.65 0E-0 6 0.000E+00 7.010E-01 0.000E+00 2.730E-0 6 NB-95 3.100E+0 6 1.210E+0 6 0.000E+00 1.130E+0 6 0.000E+00 2.230E+0 9 0.000E+00 8.620E+0 5 MO-99 0.000E+00 1.1 5 0E+0 5 0.000E+00 2.4 6 0E+0 5 0.000E+00 9.510E+04 0.000E+00 2.840E+04 T C-99 M 6.1 9 0E-21 1.210E-20 0.000E+00 1.7 6 0E-1 9 6.1 6 0E-21 6.910E-1 8 0.000E+00 2.010E-1 9 T C-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 1.55 0E+0 8 0.000E+00 0.000E+00 3.900E+0 8 0.000E+00 4.010E+0 9 0.000E+00 5.96 0E+07 RU-10 5 9.020E-2 8 0.000E+00 0.000E+00 7.930E-27 0.000E+00 5.89 0E-2 5 0.000E+00 3.270E-2 8 RU-10 6 4.440E+0 9 0.000E+00 0.000E+00 5.99 0E+0 9 0.000E+00 6.900E+10 0.000E+00 5.540E+0 8 AG-110M 8.3 9 0E+0 6 5.670E+0 6 0.000E+00 1.0 6 0E+07 0.000E+00 6.740E+0 8 0.000E+00 4.530E+0 6 T E-12 5 M 5.69 0E+0 8 1.540E+0 8 1.600E+0 8 0.000E+00 0.000E+00 5.4 9 0E+0 8 0.000E+00 7.59 0E+07 T E-127 3.3 8 0E-10 9.120E-11 2.340E-10 9.630E-10 0.000E+00 1.320E-0 8 0.000E+00 7.2 6 0E-11 T E-127M 1.770E+0 9 4.7 8 0E+0 8 4.240E+0 8 5.0 6 0E+0 9 0.000E+00 1.440E+0 9 0.000E+00 2.110E+0 8 T E-12 9 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 T E-12 9 M 1.7 9 0E+0 9 5.000E+0 8 5.770E+0 8 5.2 6 0E+0 9 0.000E+00 2.1 8 0E+0 9 0.000E+00 2.7 8 0E+0 8 T E-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 T E-131M 7.000E+02 2.420E+02 4.98 0E+02 2.340E+03 0.000E+00 9.820E+03 0.000E+00 2.58 0E+02 T E-132 2.120E+0 6 9.3 8 0E+0 5 1.370E+0 6 8.710E+0 6 0.000E+00 9.4 5 0E+0 6 0.000E+00 1.130E+0 6 I-130 3.030E-0 6 6.130E-0 6 6.7 5 0E-04 9.1 6 0E-0 6 0.000E+00 2.870E-0 6 0.000E+00 3.1 6 0E-0 6 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X I R i Child Dose Factors for use in the Gaseous Dose Calculations Appendix I Ri Child Cow Meat - Page 3 of 3 Agegroup: CHILD Pathway: Grs

/Cow/Meat (CMEAT) Units: m 2*mrem/yr / µµµµCi/sec; mrem/yr / µµµµCi/m 3 (H-3) Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in Total Body I-131 1.65 0E+07 1.66 0E+07 5.500E+0 9 2.730E+07 0.000E+00 1.4 8 0E+0 6 0.000E+00 9.4 6 0E+0 6 I-132 1.020E-58 1.88 0E-58 8.730E-5 7 2.88 0E-58 0.000E+00 2.210E-58 0.000E+00 8.65 0E-59 I-133 5.670E-01 7.020E-01 1.300E+02 1.170E+00 0.000E+00 2.830E-01 0.000E+00 2.66 0E-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-13 5 6.510E-17 1.170E-1 6 1.040E-14 1.800E-1 6 0.000E+00 8.930E-17 0.000E+00 5.55 0E-17 CS-134 9.220E+0 8 1.510E+0 9 0.000E+00 4.69 0E+0 8 1.68 0E+0 8 8.1 6 0E+0 6 0.000E+00 3.1 9 0E+0 8 CS-13 6 1.620E+07 4.4 6 0E+07 0.000E+00 2.370E+07 3.540E+0 6 1.570E+0 6 0.000E+00 2.88 0E+07 CS-137 1.330E+0 9 1.2 8 0E+0 9 0.000E+00 4.1 6 0E+0 8 1.500E+0 8 7.99 0E+0 6 0.000E+00 1.88 0E+0 8 CS-13 8 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-13 9 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 4.3 8 0E+07 3.840E+04 0.000E+00 1.2 5 0E+04 2.2 9 0E+04 2.220E+07 0.000E+00 2.56 0E+0 6 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 5.59 0E-02 1.95 0E-02 0.000E+00 0.000E+00 0.000E+00 5.440E+02 0.000E+00 6.58 0E-03 LA-142 5.300E-9 2 1.69 0E-9 2 0.000E+00 0.000E+00 0.000E+00 3.3 5 0E-8 7 0.000E+00 5.2 9 0E-9 3 CE-141 2.220E+04 1.110E+04 0.000E+00 4.85 0E+03 0.000E+00 1.3 8 0E+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 2.4 9 0E-03 CE-144 2.320E+0 6 7.2 6 0E+0 5 0.000E+00 4.020E+0 5 0.000E+00 1.89 0E+0 8 0.000E+00 1.240E+0 5 PR-143 3.340E+04 1.000E+04 0.000E+00 5.430E+03 0.000E+00 3.600E+07 0.000E+00 1.66 0E+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 N D-147 1.170E+04 9.470E+03 0.000E+00 5.1 9 0E+03 0.000E+00 1.500E+07 0.000E+00 7.330E+02 W-1 8 7 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-23 9 4.2 6 0E-01 3.0 6 0E-02 0.000E+00 8.85 0E-02 0.000E+00 2.2 6 0E+03 0.000E+00 2.1 5 0E-02 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X I R i Child Dose Factors for use in the Gaseous Dose Calculations Appendix I Ri Child Vegetation - Page 1 of 3 Agegroup: CHILD Pathway: Vegetation (VEG) Units: m 2*mrem/yr / µµµµCi/sec; mrem/yr / µµµµCi/m 3 (H-3) Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in 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 8.89 0E+0 8 1.7 8 0E+0 8 1.7 8 0E+0 8 1.7 8 0E+0 8 1.7 8 0E+0 8 1.7 8 0E+0 8 0.000E+00 1.7 8 0E+0 8 NA-24 3.730E+0 5 3.730E+0 5 3.730E+0 5 3.730E+0 5 3.730E+0 5 3.730E+0 5 0.000E+00 3.730E+0 5 P-32 3.370E+0 9 1.58 0E+0 8 0.000E+00 0.000E+00 0.000E+00 9.310E+07 0.000E+00 1.300E+0 8 CR-5 1 0.000E+00 0.000E+00 6.500E+04 1.7 8 0E+04 1.1 9 0E+0 5 6.210E+0 6 0.000E+00 1.170E+0 5 MN-5 4 0.000E+00 6.65 0E+0 8 0.000E+00 1.86 0E+0 8 0.000E+00 5.58 0E+0 8 0.000E+00 1.770E+0 8 MN-56 0.000E+00 1.86 0E+01 0.000E+00 2.2 5 0E+01 0.000E+00 2.700E+03 0.000E+00 4.200E+00 FE-55 8.010E+0 8 4.2 5 0E+0 8 0.000E+00 0.000E+00 2.400E+0 8 7.870E+07 0.000E+00 1.320E+0 8 FE-59 3.98 0E+0 8 6.430E+0 8 0.000E+00 0.000E+00 1.86 0E+0 8 6.700E+0 8 0.000E+00 3.200E+0 8 CO-58 0.000E+00 6.440E+07 0.000E+00 0.000E+00 0.000E+00 3.7 6 0E+0 8 0.000E+00 1.970E+0 8 CO-6 0 0.000E+00 3.7 8 0E+0 8 0.000E+00 0.000E+00 0.000E+00 2.100E+0 9 0.000E+00 1.120E+0 9 NI-6 3 3.95 0E+10 2.110E+0 9 0.000E+00 0.000E+00 0.000E+00 1.420E+0 8 0.000E+00 1.340E+0 9 NI-65 1.0 5 0E+02 9.89 0E+00 0.000E+00 0.000E+00 0.000E+00 1.210E+03 0.000E+00 5.770E+00 CU-6 4 0.000E+00 1.100E+04 0.000E+00 2.66 0E+04 0.000E+00 5.1 6 0E+0 5 0.000E+00 6.640E+03 Z N-65 8.130E+0 8 2.1 6 0E+0 9 0.000E+00 1.3 6 0E+0 9 0.000E+00 3.800E+0 8 0.000E+00 1.3 5 0E+0 9 Z N-69 9.4 9 0E-0 6 1.370E-0 5 0.000E+00 8.320E-0 6 0.000E+00 8.640E-04 0.000E+00 1.270E-0 6 BR-8 3 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-8 4 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+0 8 0.000E+00 0.000E+00 0.000E+00 2.910E+07 0.000E+00 2.7 8 0E+0 8 RB-88 0.000E+00 4.3 8 0E-22 0.000E+00 0.000E+00 0.000E+00 2.1 5 0E-23 0.000E+00 3.040E-22 RB-89 0.000E+00 4.610E-2 6 0.000E+00 0.000E+00 0.000E+00 4.020E-2 8 0.000E+00 4.0 9 0E-2 6 SR-89 3.600E+10 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.3 9 0E+0 9 0.000E+00 1.030E+0 9 SR-9 0 1.240E+12 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.670E+10 0.000E+00 3.1 5 0E+11 SR-9 1 5.240E+0 5 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.1 6 0E+0 6 0.000E+00 1.98 0E+04 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X I R i Child Dose Factors for use in the Gaseous Dose Calculations Appendix I Ri Child Vegetation - Page 2 of 3 Agegroup: CHILD Pathway: Vegetation (VEG) Units: m 2*mrem/yr / µµµµCi/sec; mrem/yr / µµµµCi/m 3 (H-3) Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in Total Body SR-9 2 7.2 8 0E+02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.3 8 0E+04 0.000E+00 2.920E+01 Y-9 0 2.310E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 6.570E+07 0.000E+00 6.1 8 0E+02 Y-9 1 1.86 0E+07 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.4 8 0E+0 9 0.000E+00 4.99 0E+0 5 Y-9 1M 8.910E-0 9 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.740E-0 5 0.000E+00 3.240E-10 Y-9 2 1.58 0E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4.58 0E+04 0.000E+00 4.530E-02 Y-9 3 2.930E+02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 4.370E+0 6 0.000E+00 8.040E+00 Z R-95 3.86 0E+0 6 8.4 8 0E+0 5 0.000E+00 1.210E+0 6 0.000E+00 8.85 0E+0 8 0.000E+00 7.55 0E+0 5 Z R-9 7 5.700E+02 8.240E+01 0.000E+00 1.1 8 0E+02 0.000E+00 1.2 5 0E+07 0.000E+00 4.86 0E+01 NB-95 4.110E+0 5 1.600E+0 5 0.000E+00 1.500E+0 5 0.000E+00 2.96 0E+0 8 0.000E+00 1.140E+0 5 MO-99 0.000E+00 7.710E+0 6 0.000E+00 1.65 0E+07 0.000E+00 6.3 8 0E+0 6 0.000E+00 1.910E+0 6 T C-99 M 4.710E+00 9.230E+00 0.000E+00 1.340E+02 4.69 0E+00 5.2 6 0E+03 0.000E+00 1.530E+02 T C-101 1.410E-30 1.470E-30 0.000E+00 2.510E-2 9 7.7 8 0E-31 4.68 0E-30 0.000E+00 1.870E-2 9 RU-103 1.530E+07 0.000E+00 0.000E+00 3.86 0E+07 0.000E+00 3.970E+0 8 0.000E+00 5.900E+0 6 RU-10 5 9.1 6 0E+01 0.000E+00 0.000E+00 8.0 5 0E+02 0.000E+00 5.98 0E+04 0.000E+00 3.320E+01 RU-10 6 7.4 5 0E+0 8 0.000E+00 0.000E+00 1.010E+0 9 0.000E+00 1.1 6 0E+10 0.000E+00 9.300E+07 AG-110M 3.210E+07 2.170E+07 0.000E+00 4.040E+07 0.000E+00 2.58 0E+0 9 0.000E+00 1.730E+07 T E-12 5 M 3.510E+0 8 9.500E+07 9.840E+07 0.000E+00 0.000E+00 3.3 8 0E+0 8 0.000E+00 4.670E+07 T E-127 9.85 0E+03 2.65 0E+03 6.810E+03 2.800E+04 0.000E+00 3.85 0E+0 5 0.000E+00 2.110E+03 T E-127M 1.320E+0 9 3.56 0E+0 8 3.1 6 0E+0 8 3.770E+0 9 0.000E+00 1.070E+0 9 0.000E+00 1.570E+0 8 T E-12 9 1.320E-03 3.69 0E-04 9.430E-04 3.870E-03 0.000E+00 8.230E-02 0.000E+00 3.140E-04 T E-12 9 M 8.410E+0 8 2.3 5 0E+0 8 2.710E+0 8 2.470E+0 9 0.000E+00 1.030E+0 9 0.000E+00 1.310E+0 8 T E-131 2.570E-1 5 7.830E-1 6 1.96 0E-1 5 7.770E-1 5 0.000E+00 1.3 5 0E-14 0.000E+00 7.640E-1 6 T E-131M 1.540E+0 6 5.330E+0 5 1.100E+0 6 5.1 6 0E+0 6 0.000E+00 2.1 6 0E+07 0.000E+00 5.68 0E+0 5 T E-132 7.000E+0 6 3.100E+0 6 4.510E+0 6 2.88 0E+07 0.000E+00 3.120E+07 0.000E+00 3.740E+0 6 I-130 6.1 6 0E+0 5 1.240E+0 6 1.370E+0 8 1.86 0E+0 6 0.000E+00 5.820E+0 5 0.000E+00 6.410E+0 5 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X I R i Child Dose Factors for use in the Gaseous Dose Calculations Appendix I Ri Child Vegetation - Page 3 of 3 Agegroup: CHILD Pathway: Vegetation (VEG) Units: m 2*mrem/yr / µµµµCi/sec; mrem/yr / µµµµCi/m 3 (H-3) Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in Total Body I-131 1.430E+0 8 1.440E+0 8 4.7 5 0E+10 2.3 6 0E+0 8 0.000E+00 1.2 8 0E+07 0.000E+00 8.170E+07 I-132 9.220E+01 1.69 0E+02 7.86 0E+03 2.59 0E+02 0.000E+00 1.99 0E+02 0.000E+00 7.7 9 0E+01 I-133 3.530E+0 6 4.370E+0 6 8.110E+0 8 7.2 8 0E+0 6 0.000E+00 1.7 6 0E+0 6 0.000E+00 1.65 0E+0 6 I-134 1.55 0E-04 2.88 0E-04 6.620E-03 4.400E-04 0.000E+00 1.910E-04 0.000E+00 1.320E-04 I-13 5 6.2 6 0E+04 1.130E+0 5 9.970E+0 6 1.730E+0 5 0.000E+00 8.58 0E+04 0.000E+00 5.330E+04 CS-134 1.600E+10 2.630E+10 0.000E+00 8.1 5 0E+0 9 2.930E+0 9 1.420E+0 8 0.000E+00 5.55 0E+0 9 CS-13 6 8.240E+07 2.270E+0 8 0.000E+00 1.210E+0 8 1.800E+07 7.96 0E+0 6 0.000E+00 1.470E+0 8 CS-137 2.3 9 0E+10 2.2 9 0E+10 0.000E+00 7.4 6 0E+0 9 2.68 0E+0 9 1.430E+0 8 0.000E+00 3.3 8 0E+0 9 CS-13 8 6.570E-11 9.130E-11 0.000E+00 6.430E-11 6.920E-12 4.210E-11 0.000E+00 5.7 9 0E-11 BA-13 9 4.95 0E-02 2.640E-0 5 0.000E+00 2.310E-0 5 1.56 0E-0 5 2.86 0E+00 0.000E+00 1.440E-03 BA-140 2.770E+0 8 2.420E+0 5 0.000E+00 7.89 0E+04 1.4 5 0E+0 5 1.400E+0 8 0.000E+00 1.610E+07 BA-141 1.99 0E-21 1.110E-24 0.000E+00 9.620E-2 5 6.530E-24 1.130E-21 0.000E+00 6.4 6 0E-23 BA-142 9.930E-3 9 7.1 5 0E-42 0.000E+00 5.7 8 0E-42 4.200E-42 1.300E-40 0.000E+00 5.540E-40 LA-140 3.2 5 0E+03 1.130E+03 0.000E+00 0.000E+00 0.000E+00 3.1 6 0E+07 0.000E+00 3.820E+02 LA-142 3.3 6 0E-04 1.070E-04 0.000E+00 0.000E+00 0.000E+00 2.120E+01 0.000E+00 3.3 5 0E-0 5 CE-141 6.56 0E+0 5 3.270E+0 5 0.000E+00 1.430E+0 5 0.000E+00 4.0 8 0E+0 8 0.000E+00 4.86 0E+04 CE-143 1.720E+03 9.310E+0 5 0.000E+00 3.910E+02 0.000E+00 1.3 6 0E+07 0.000E+00 1.3 5 0E+02 CE-144 1.270E+0 8 3.98 0E+07 0.000E+00 2.210E+07 0.000E+00 1.040E+10 0.000E+00 6.7 8 0E+0 6 PR-143 1.4 6 0E+0 5 4.370E+04 0.000E+00 2.370E+04 0.000E+00 1.570E+0 8 0.000E+00 7.230E+03 PR-144 5.3 8 0E-2 6 1.66 0E-2 6 0.000E+00 8.800E-27 0.000E+00 3.58 0E-23 0.000E+00 2.710E-27 N D-147 7.1 5 0E+04 5.7 9 0E+04 0.000E+00 3.1 8 0E+04 0.000E+00 9.170E+07 0.000E+00 4.4 8 0E+03 W-1 8 7 6.430E+04 3.810E+04 0.000E+00 0.000E+00 0.000E+00 5.3 5 0E+0 6 0.000E+00 1.710E+04 NP-23 9 2.56 0E+03 1.840E+02 0.000E+00 5.310E+02 0.000E+00 1.3 6 0E+07 0.000E+00 1.2 9 0E+02 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X I R i Child Dose Factors for use in the Gaseous Dose Calculations Appendix I Ri Child Inhalation - Page 1 of 3 Agegroup: CHILD Pathway: Inhalation (INHL) Units: mrem/yr / µµµµCi/m 3 Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in 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 3.59 0E+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+0 6 1.140E+0 5 0.000E+00 0.000E+00 0.000E+00 4.220E+04 0.000E+00 9.88 0E+04 CR-5 1 0.000E+00 0.000E+00 8.55 0E+01 2.430E+01 1.700E+04 1.0 8 0E+03 0.000E+00 1.540E+02 MN-5 4 0.000E+00 4.2 9 0E+04 0.000E+00 1.000E+04 1.58 0E+0 6 2.2 9 0E+04 0.000E+00 9.510E+03 MN-56 0.000E+00 1.66 0E+00 0.000E+00 1.670E+00 1.310E+04 1.230E+0 5 0.000E+00 3.120E-01 FE-55 4.740E+04 2.520E+04 0.000E+00 0.000E+00 1.110E+0 5 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+0 6 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+0 6 3.440E+04 0.000E+00 3.1 6 0E+03 CO-6 0 0.000E+00 1.310E+04 0.000E+00 0.000E+00 7.070E+0 6 9.620E+04 0.000E+00 2.2 6 0E+04 NI-6 3 8.210E+0 5 4.620E+04 0.000E+00 0.000E+00 2.7 5 0E+0 5 6.330E+03 0.000E+00 2.800E+04 NI-65 2.99 0E+00 2.96 0E-01 0.000E+00 0.000E+00 8.1 8 0E+03 8.400E+04 0.000E+00 1.640E-01 CU-6 4 0.000E+00 1.99 0E+00 0.000E+00 6.030E+00 9.58 0E+03 3.670E+04 0.000E+00 1.070E+00 Z N-65 4.2 6 0E+04 1.130E+0 5 0.000E+00 7.140E+04 9.95 0E+0 5 1.630E+04 0.000E+00 7.030E+04 Z N-69 6.700E-02 9.66 0E-02 0.000E+00 5.85 0E-02 1.420E+03 1.020E+04 0.000E+00 8.920E-03 BR-8 3 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-8 4 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.4 8 0E+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 1.98 0E+0 5 0.000E+00 0.000E+00 0.000E+00 7.99 0E+03 0.000E+00 1.140E+0 5 RB-88 0.000E+00 5.620E+02 0.000E+00 0.000E+00 0.000E+00 1.720E+01 0.000E+00 3.66 0E+02 RB-89 0.000E+00 3.4 5 0E+02 0.000E+00 0.000E+00 0.000E+00 1.89 0E+00 0.000E+00 2.900E+02 SR-89 5.99 0E+0 5 0.000E+00 0.000E+00 0.000E+00 2.1 6 0E+0 6 1.670E+0 5 0.000E+00 1.720E+04 SR-9 0 1.010E+0 8 0.000E+00 0.000E+00 0.000E+00 1.4 8 0E+07 3.430E+0 5 0.000E+00 6.440E+0 6 SR-9 1 1.210E+02 0.000E+00 0.000E+00 0.000E+00 5.330E+04 1.740E+0 5 0.000E+00 4.59 0E+00 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X I R i Child Dose Factors for use in the Gaseous Dose Calculations Appendix I Ri Child Inhalation - Page 2 of 3 Agegroup: CHILD Pathway: Inhalation (INHL) Units: mrem/yr / µµµµCi/m 3 Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in Total Body SR-9 2 1.310E+01 0.000E+00 0.000E+00 0.000E+00 2.400E+04 2.420E+0 5 0.000E+00 5.2 5 0E-01 Y-9 0 4.110E+03 0.000E+00 0.000E+00 0.000E+00 2.620E+0 5 2.68 0E+0 5 0.000E+00 1.110E+02 Y-9 1 9.140E+0 5 0.000E+00 0.000E+00 0.000E+00 2.630E+0 6 1.840E+0 5 0.000E+00 2.440E+04 Y-9 1M 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-9 2 2.030E+01 0.000E+00 0.000E+00 0.000E+00 2.3 9 0E+04 2.3 9 0E+0 5 0.000E+00 5.810E-01 Y-9 3 1.86 0E+02 0.000E+00 0.000E+00 0.000E+00 7.440E+04 3.88 0E+0 5 0.000E+00 5.110E+00 Z R-95 1.900E+0 5 4.1 8 0E+04 0.000E+00 5.96 0E+04 2.230E+0 6 6.110E+04 0.000E+00 3.700E+04 Z R-9 7 1.88 0E+02 2.720E+01 0.000E+00 3.88 0E+01 1.130E+0 5 3.510E+0 5 0.000E+00 1.600E+01 NB-95 2.3 5 0E+04 9.1 8 0E+03 0.000E+00 8.620E+03 6.140E+0 5 3.700E+04 0.000E+00 6.55 0E+03 MO-99 0.000E+00 1.720E+02 0.000E+00 3.920E+02 1.3 5 0E+0 5 1.270E+0 5 0.000E+00 4.2 6 0E+01 T C-99 M 1.7 8 0E-03 3.4 8 0E-03 0.000E+00 5.070E-02 9.510E+02 4.810E+03 0.000E+00 5.770E-02 T C-101 8.100E-0 5 8.510E-0 5 0.000E+00 1.4 5 0E-03 5.85 0E+02 1.630E+01 0.000E+00 1.0 8 0E-03 RU-103 2.7 9 0E+03 0.000E+00 0.000E+00 7.030E+03 6.620E+0 5 4.4 8 0E+04 0.000E+00 1.070E+03 RU-10 5 1.530E+00 0.000E+00 0.000E+00 1.340E+00 1.59 0E+04 9.95 0E+04 0.000E+00 5.55 0E-01 RU-10 6 1.3 6 0E+0 5 0.000E+00 0.000E+00 1.840E+0 5 1.430E+07 4.2 9 0E+0 5 0.000E+00 1.69 0E+04 AG-110M 1.69 0E+04 1.140E+04 0.000E+00 2.120E+04 5.4 8 0E+0 6 1.000E+0 5 0.000E+00 9.140E+03 T E-12 5 M 6.730E+03 2.330E+03 1.920E+03 0.000E+00 4.770E+0 5 3.3 8 0E+04 0.000E+00 9.140E+02 T E-127 2.770E+00 9.510E-01 1.96 0E+00 7.070E+00 1.000E+04 5.620E+04 0.000E+00 6.100E-01 T E-127M 2.4 9 0E+04 8.55 0E+03 6.070E+03 6.3 6 0E+04 1.4 8 0E+0 6 7.140E+04 0.000E+00 3.020E+03 T E-12 9 9.770E-02 3.500E-02 7.140E-02 2.570E-01 2.930E+03 2.55 0E+04 0.000E+00 2.3 8 0E-02 T E-12 9 M 1.920E+04 6.840E+03 6.330E+03 5.030E+04 1.7 6 0E+0 6 1.820E+0 5 0.000E+00 3.040E+03 T E-131 2.170E-02 8.440E-03 1.700E-02 5.88 0E-02 2.0 5 0E+03 1.330E+03 0.000E+00 6.59 0E-03 T E-131M 1.340E+02 5.920E+01 9.770E+01 4.000E+02 2.0 6 0E+0 5 3.0 8 0E+0 5 0.000E+00 5.070E+01 T E-132 4.810E+02 2.720E+02 3.170E+02 1.770E+03 3.770E+0 5 1.3 8 0E+0 5 0.000E+00 2.630E+02 I-130 8.1 8 0E+03 1.640E+04 1.85 0E+0 6 2.4 5 0E+04 0.000E+00 5.110E+03 0.000E+00 8.440E+03 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X I R i Child Dose Factors for use in the Gaseous Dose Calculations Appendix I Ri Child Inhalation - Page 3 of 3 Agegroup: CHILD Pathway: Inhalation (INHL) Units: mrem/yr / µµµµCi/m 3 Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in Total Body I-131 4.810E+04 4.810E+04 1.620E+07 7.88 0E+04 0.000E+00 2.840E+03 0.000E+00 2.730E+04 I-132 2.120E+03 4.070E+03 1.940E+0 5 6.2 5 0E+03 0.000E+00 3.200E+03 0.000E+00 1.88 0E+03 I-133 1.66 0E+04 2.030E+04 3.85 0E+0 6 3.3 8 0E+04 0.000E+00 5.4 8 0E+03 0.000E+00 7.700E+03 I-134 1.170E+03 2.1 6 0E+03 5.070E+04 3.300E+03 0.000E+00 9.55 0E+02 0.000E+00 9.95 0E+02 I-13 5 4.920E+03 8.730E+03 7.920E+0 5 1.340E+04 0.000E+00 4.440E+03 0.000E+00 4.140E+03 CS-134 6.510E+0 5 1.010E+0 6 0.000E+00 3.300E+0 5 1.210E+0 5 3.85 0E+03 0.000E+00 2.2 5 0E+0 5 CS-13 6 6.510E+04 1.710E+0 5 0.000E+00 9.55 0E+04 1.4 5 0E+04 4.1 8 0E+03 0.000E+00 1.1 6 0E+0 5 CS-137 9.0 6 0E+0 5 8.2 5 0E+0 5 0.000E+00 2.820E+0 5 1.040E+0 5 3.620E+03 0.000E+00 1.2 8 0E+0 5 CS-13 8 6.330E+02 8.400E+02 0.000E+00 6.220E+02 6.810E+01 2.700E+02 0.000E+00 5.55 0E+02 BA-13 9 1.840E+00 9.840E-04 0.000E+00 8.620E-04 5.770E+03 5.770E+04 0.000E+00 5.3 6 0E-02 BA-140 7.400E+04 6.4 8 0E+01 0.000E+00 2.110E+01 1.740E+0 6 1.020E+0 5 0.000E+00 4.330E+03 BA-141 1.96 0E-01 1.0 9 0E-04 0.000E+00 9.470E-0 5 2.920E+03 2.7 5 0E+02 0.000E+00 6.3 6 0E-03 BA-142 5.000E-02 3.600E-0 5 0.000E+00 2.910E-0 5 1.640E+03 2.740E+00 0.000E+00 2.7 9 0E-03 LA-140 6.440E+02 2.2 5 0E+02 0.000E+00 0.000E+00 1.830E+0 5 2.2 6 0E+0 5 0.000E+00 7.55 0E+01 LA-142 1.300E+00 4.110E-01 0.000E+00 0.000E+00 8.700E+03 7.58 0E+04 0.000E+00 1.2 9 0E-01 CE-141 3.920E+04 1.95 0E+04 0.000E+00 8.55 0E+03 5.440E+0 5 5.66 0E+04 0.000E+00 2.900E+03 CE-143 3.66 0E+02 1.99 0E+02 0.000E+00 8.3 6 0E+01 1.1 5 0E+0 5 1.270E+0 5 0.000E+00 2.870E+01 CE-144 6.770E+0 6 2.120E+0 6 0.000E+00 1.170E+0 6 1.200E+07 3.88 0E+0 5 0.000E+00 3.610E+0 5 PR-143 1.85 0E+04 5.55 0E+03 0.000E+00 3.000E+03 4.330E+0 5 9.730E+04 0.000E+00 9.140E+02 PR-144 5.96 0E-02 1.85 0E-02 0.000E+00 9.770E-03 1.570E+03 1.970E+02 0.000E+00 3.000E-03 N D-147 1.0 8 0E+04 8.730E+03 0.000E+00 4.810E+03 3.2 8 0E+0 5 8.210E+04 0.000E+00 6.810E+02 W-1 8 7 1.630E+01 9.66 0E+00 0.000E+00 0.000E+00 4.110E+04 9.100E+04 0.000E+00 4.330E+00 NP-23 9 4.66 0E+02 3.340E+01 0.000E+00 9.730E+01 5.810E+04 6.400E+04 0.000E+00 2.3 5 0E+01 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X I R i Child Dose Factors for use in the Gaseous Dose Calculations Appendix I Ri Child Ground Plane Deposition - Page 1 of 3 Agegroup: CHILD Pathway: Ground Plane Deposition (GPD) Units: m 2*mrem/yr / µµµµCi/sec Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in 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 1.1 9 0E+07 1.1 9 0E+07 1.1 9 0E+07 1.1 9 0E+07 1.1 9 0E+07 1.1 9 0E+07 1.3 9 0E+07 1.1 9 0E+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-5 1 4.66 0E+0 6 4.66 0E+0 6 4.66 0E+0 6 4.66 0E+0 6 4.66 0E+0 6 4.66 0E+0 6 5.510E+0 6 4.66 0E+0 6 MN-5 4 1.3 9 0E+0 9 1.3 9 0E+0 9 1.3 9 0E+0 9 1.3 9 0E+0 9 1.3 9 0E+0 9 1.3 9 0E+0 9 1.630E+0 9 1.3 9 0E+0 9 MN-56 9.020E+0 5 9.020E+0 5 9.020E+0 5 9.020E+0 5 9.020E+0 5 9.020E+0 5 1.070E+0 6 9.020E+0 5 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+0 8 2.730E+0 8 2.730E+0 8 2.730E+0 8 2.730E+0 8 2.730E+0 8 3.210E+0 8 2.730E+0 8 CO-58 3.7 9 0E+0 8 3.7 9 0E+0 8 3.7 9 0E+0 8 3.7 9 0E+0 8 3.7 9 0E+0 8 3.7 9 0E+0 8 4.440E+0 8 3.7 9 0E+0 8 CO-6 0 2.1 5 0E+10 2.1 5 0E+10 2.1 5 0E+10 2.1 5 0E+10 2.1 5 0E+10 2.1 5 0E+10 2.530E+10 2.1 5 0E+10 NI-6 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 NI-65 2.970E+0 5 2.970E+0 5 2.970E+0 5 2.970E+0 5 2.970E+0 5 2.970E+0 5 3.4 5 0E+0 5 2.970E+0 5 CU-6 4 6.070E+0 5 6.070E+0 5 6.070E+0 5 6.070E+0 5 6.070E+0 5 6.070E+0 5 6.88 0E+0 5 6.070E+0 5 Z N-65 7.470E+0 8 7.470E+0 8 7.470E+0 8 7.470E+0 8 7.470E+0 8 7.470E+0 8 8.59 0E+0 8 7.470E+0 8 Z N-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-8 3 4.870E+03 4.870E+03 4.870E+03 4.870E+03 4.870E+03 4.870E+03 7.0 8 0E+03 4.870E+03 BR-8 4 2.030E+0 5 2.030E+0 5 2.030E+0 5 2.030E+0 5 2.030E+0 5 2.030E+0 5 2.3 6 0E+0 5 2.030E+0 5 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 8.99 0E+0 6 8.99 0E+0 6 8.99 0E+0 6 8.99 0E+0 6 8.99 0E+0 6 8.99 0E+0 6 1.030E+07 8.99 0E+0 6 RB-88 3.310E+04 3.310E+04 3.310E+04 3.310E+04 3.310E+04 3.310E+04 3.7 8 0E+04 3.310E+04 RB-89 1.230E+0 5 1.230E+0 5 1.230E+0 5 1.230E+0 5 1.230E+0 5 1.230E+0 5 1.4 8 0E+0 5 1.230E+0 5 SR-89 2.1 6 0E+04 2.1 6 0E+04 2.1 6 0E+04 2.1 6 0E+04 2.1 6 0E+04 2.1 6 0E+04 2.510E+04 2.1 6 0E+04 SR-9 0 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-9 1 2.1 5 0E+0 6 2.1 5 0E+0 6 2.1 5 0E+0 6 2.1 5 0E+0 6 2.1 5 0E+0 6 2.1 5 0E+0 6 2.510E+0 6 2.1 5 0E+0 6 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X I R i Child Dose Factors for use in the Gaseous Dose Calculations Appendix I Ri Child Ground Plane Deposition - Page 2 of 3 Agegroup: CHILD Pathway: Ground Plane Deposition (GPD) Units: m 2*mrem/yr / µµµµCi/sec Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in Total Body SR-9 2 7.770E+0 5 7.770E+0 5 7.770E+0 5 7.770E+0 5 7.770E+0 5 7.770E+0 5 8.630E+0 5 7.770E+0 5 Y-9 0 4.4 9 0E+03 4.4 9 0E+03 4.4 9 0E+03 4.4 9 0E+03 4.4 9 0E+03 4.4 9 0E+03 5.310E+03 4.4 9 0E+03 Y-9 1 1.070E+0 6 1.070E+0 6 1.070E+0 6 1.070E+0 6 1.070E+0 6 1.070E+0 6 1.210E+0 6 1.070E+0 6 Y-9 1M 1.000E+0 5 1.000E+0 5 1.000E+0 5 1.000E+0 5 1.000E+0 5 1.000E+0 5 1.1 6 0E+0 5 1.000E+0 5 Y-9 2 1.800E+0 5 1.800E+0 5 1.800E+0 5 1.800E+0 5 1.800E+0 5 1.800E+0 5 2.140E+0 5 1.800E+0 5 Y-9 3 1.830E+0 5 1.830E+0 5 1.830E+0 5 1.830E+0 5 1.830E+0 5 1.830E+0 5 2.510E+0 5 1.830E+0 5 Z R-95 2.4 5 0E+0 8 2.4 5 0E+0 8 2.4 5 0E+0 8 2.4 5 0E+0 8 2.4 5 0E+0 8 2.4 5 0E+0 8 2.840E+0 8 2.4 5 0E+0 8 Z R-9 7 2.96 0E+0 6 2.96 0E+0 6 2.96 0E+0 6 2.96 0E+0 6 2.96 0E+0 6 2.96 0E+0 6 3.440E+0 6 2.96 0E+0 6 NB-95 1.370E+0 8 1.370E+0 8 1.370E+0 8 1.370E+0 8 1.370E+0 8 1.370E+0 8 1.610E+0 8 1.370E+0 8 MO-99 3.99 0E+0 6 3.99 0E+0 6 3.99 0E+0 6 3.99 0E+0 6 3.99 0E+0 6 3.99 0E+0 6 4.630E+0 6 3.99 0E+0 6 T C-99 M 1.840E+0 5 1.840E+0 5 1.840E+0 5 1.840E+0 5 1.840E+0 5 1.840E+0 5 2.110E+0 5 1.840E+0 5 T C-101 2.040E+04 2.040E+04 2.040E+04 2.040E+04 2.040E+04 2.040E+04 2.2 6 0E+04 2.040E+04 RU-103 1.0 8 0E+0 8 1.0 8 0E+0 8 1.0 8 0E+0 8 1.0 8 0E+0 8 1.0 8 0E+0 8 1.0 8 0E+0 8 1.2 6 0E+0 8 1.0 8 0E+0 8 RU-10 5 6.3 6 0E+0 5 6.3 6 0E+0 5 6.3 6 0E+0 5 6.3 6 0E+0 5 6.3 6 0E+0 5 6.3 6 0E+0 5 7.210E+0 5 6.3 6 0E+0 5 RU-10 6 4.220E+0 8 4.220E+0 8 4.220E+0 8 4.220E+0 8 4.220E+0 8 4.220E+0 8 5.070E+0 8 4.220E+0 8 AG-110M 3.440E+0 9 3.440E+0 9 3.440E+0 9 3.440E+0 9 3.440E+0 9 3.440E+0 9 4.010E+0 9 3.440E+0 9 T E-12 5 M 1.55 0E+0 6 1.55 0E+0 6 1.55 0E+0 6 1.55 0E+0 6 1.55 0E+0 6 1.55 0E+0 6 2.130E+0 6 1.55 0E+0 6 T E-127 2.98 0E+03 2.98 0E+03 2.98 0E+03 2.98 0E+03 2.98 0E+03 2.98 0E+03 3.2 8 0E+03 2.98 0E+03 T E-127M 9.1 6 0E+04 9.1 6 0E+04 9.1 6 0E+04 9.1 6 0E+04 9.1 6 0E+04 9.1 6 0E+04 1.0 8 0E+0 5 9.1 6 0E+04 T E-12 9 2.620E+04 2.620E+04 2.620E+04 2.620E+04 2.620E+04 2.620E+04 3.100E+04 2.620E+04 T E-12 9 M 1.98 0E+07 1.98 0E+07 1.98 0E+07 1.98 0E+07 1.98 0E+07 1.98 0E+07 2.310E+07 1.98 0E+07 T E-131 2.920E+04 2.920E+04 2.920E+04 2.920E+04 2.920E+04 2.920E+04 3.4 5 0E+07 2.920E+04 T E-131M 8.030E+0 6 8.030E+0 6 8.030E+0 6 8.030E+0 6 8.030E+0 6 8.030E+0 6 9.4 6 0E+0 6 8.030E+0 6 T E-132 4.230E+0 6 4.230E+0 6 4.230E+0 6 4.230E+0 6 4.230E+0 6 4.230E+0 6 4.98 0E+0 6 4.230E+0 6 I-130 5.510E+0 6 5.510E+0 6 5.510E+0 6 5.510E+0 6 5.510E+0 6 5.510E+0 6 6.69 0E+0 6 5.510E+0 6 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X I R i Child Dose Factors for use in the Gaseous Dose Calculations Appendix I Ri Child Ground Plane Deposition - Page 3 of 3 Agegroup: CHILD Pathway: Ground Plane Deposition (GPD) Units: m 2*mrem/yr / µµµµCi/sec Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in Total Body I-131 1.720E+07 1.720E+07 1.720E+07 1.720E+07 1.720E+07 1.720E+07 2.0 9 0E+07 1.720E+07 I-132 1.2 5 0E+0 6 1.2 5 0E+0 6 1.2 5 0E+0 6 1.2 5 0E+0 6 1.2 5 0E+0 6 1.2 5 0E+0 6 1.470E+0 6 1.2 5 0E+0 6 I-133 2.4 5 0E+0 6 2.4 5 0E+0 6 2.4 5 0E+0 6 2.4 5 0E+0 6 2.4 5 0E+0 6 2.4 5 0E+0 6 2.98 0E+0 6 2.4 5 0E+0 6 I-134 4.470E+0 5 4.470E+0 5 4.470E+0 5 4.470E+0 5 4.470E+0 5 4.470E+0 5 5.300E+0 5 4.470E+0 5 I-13 5 2.530E+0 6 2.530E+0 6 2.530E+0 6 2.530E+0 6 2.530E+0 6 2.530E+0 6 2.95 0E+0 6 2.530E+0 6 CS-134 6.86 0E+0 9 6.86 0E+0 9 6.86 0E+0 9 6.86 0E+0 9 6.86 0E+0 9 6.86 0E+0 9 8.000E+0 9 6.86 0E+0 9 CS-13 6 1.510E+0 8 1.510E+0 8 1.510E+0 8 1.510E+0 8 1.510E+0 8 1.510E+0 8 1.710E+0 8 1.510E+0 8 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-13 8 3.59 0E+0 5 3.59 0E+0 5 3.59 0E+0 5 3.59 0E+0 5 3.59 0E+0 5 3.59 0E+0 5 4.100E+0 5 3.59 0E+0 5 BA-13 9 1.0 6 0E+0 5 1.0 6 0E+0 5 1.0 6 0E+0 5 1.0 6 0E+0 5 1.0 6 0E+0 5 1.0 6 0E+0 5 1.1 9 0E+0 5 1.0 6 0E+0 5 BA-140 2.0 5 0E+07 2.0 5 0E+07 2.0 5 0E+07 2.0 5 0E+07 2.0 5 0E+07 2.0 5 0E+07 2.3 5 0E+07 2.0 5 0E+07 BA-141 4.170E+04 4.170E+04 4.170E+04 4.170E+04 4.170E+04 4.170E+04 4.7 5 0E+04 4.170E+04 BA-142 4.4 9 0E+04 4.4 9 0E+04 4.4 9 0E+04 4.4 9 0E+04 4.4 9 0E+04 4.4 9 0E+04 5.110E+04 4.4 9 0E+04 LA-140 1.920E+07 1.920E+07 1.920E+07 1.920E+07 1.920E+07 1.920E+07 2.1 8 0E+07 1.920E+07 LA-142 7.600E+0 5 7.600E+0 5 7.600E+0 5 7.600E+0 5 7.600E+0 5 7.600E+0 5 9.120E+0 5 7.600E+0 5 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+0 6 2.310E+0 6 2.310E+0 6 2.310E+0 6 2.310E+0 6 2.310E+0 6 2.630E+0 6 2.310E+0 6 CE-144 6.95 0E+07 6.95 0E+07 6.95 0E+07 6.95 0E+07 6.95 0E+07 6.95 0E+07 8.040E+07 6.95 0E+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 N D-147 8.3 9 0E+0 6 8.3 9 0E+0 6 8.3 9 0E+0 6 8.3 9 0E+0 6 8.3 9 0E+0 6 8.3 9 0E+0 6 1.010E+07 8.3 9 0E+0 6 W-1 8 7 2.3 5 0E+0 6 2.3 5 0E+0 6 2.3 5 0E+0 6 2.3 5 0E+0 6 2.3 5 0E+0 6 2.3 5 0E+0 6 2.730E+0 6 2.3 5 0E+0 6 NP-23 9 1.710E+0 6 1.710E+0 6 1.710E+0 6 1.710E+0 6 1.710E+0 6 1.710E+0 6 1.98 0E+0 6 1.710E+0 6 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X J R i Infant Dose Factors for use in the Gaseous Dose Calculations Appendix J Ri Infant Cow Milk - Page 1 of 3 Agegroup: INFANT Pathway: Grs

/Cow/Mil k (CMIL K) Units: m 2*mrem/yr / µµµµCi/sec; mrem/yr / µµµµCi/m 3 (H-3) Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in Total Body H-3 0.000E+00 2.3 8 0E+03 2.3 8 0E+03 2.3 8 0E+03 2.3 8 0E+03 2.3 8 0E+03 0.000E+00 2.3 8 0E+03 C-14 2.340E+0 9 5.000E+0 8 5.000E+0 8 5.000E+0 8 5.000E+0 8 5.000E+0 8 0.000E+00 5.000E+0 8 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+0 9 0.000E+00 0.000E+00 0.000E+00 2.170E+0 9 0.000E+00 6.210E+0 9 CR-5 1 0.000E+00 0.000E+00 1.0 5 0E+0 5 2.300E+04 2.0 5 0E+0 5 4.700E+0 6 0.000E+00 1.610E+0 5 MN-5 4 0.000E+00 3.900E+07 0.000E+00 8.640E+0 6 0.000E+00 1.430E+07 0.000E+00 8.840E+0 6 MN-56 0.000E+00 3.100E-02 0.000E+00 2.66 0E-02 0.000E+00 2.810E+00 0.000E+00 5.340E-03 FE-55 1.3 5 0E+0 8 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+0 8 3.920E+0 8 0.000E+00 0.000E+00 1.1 6 0E+0 8 1.870E+0 8 0.000E+00 1.540E+0 8 CO-58 0.000E+00 2.420E+07 0.000E+00 0.000E+00 0.000E+00 6.040E+07 0.000E+00 6.0 5 0E+07 CO-6 0 0.000E+00 8.820E+07 0.000E+00 0.000E+00 0.000E+00 2.100E+0 8 0.000E+00 2.0 8 0E+0 8 NI-6 3 3.4 9 0E+10 2.1 6 0E+0 9 0.000E+00 0.000E+00 0.000E+00 1.070E+0 8 0.000E+00 1.210E+0 9 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-6 4 0.000E+00 1.85 0E+0 5 0.000E+00 3.140E+0 5 0.000E+00 3.810E+0 6 0.000E+00 8.59 0E+04 Z N-65 5.55 0E+0 9 1.900E+10 0.000E+00 9.230E+0 9 0.000E+00 1.610E+10 0.000E+00 8.7 8 0E+0 9 Z N-69 2.020E-11 3.630E-11 0.000E+00 1.510E-11 0.000E+00 2.96 0E-0 9 0.000E+00 2.700E-12 BR-8 3 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-8 4 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.2 6 0E-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 5.69 0E+0 8 0.000E+00 1.100E+10 RB-88 0.000E+00 1.88 0E-44 0.000E+00 0.000E+00 0.000E+00 1.830E-44 0.000E+00 1.030E-44 RB-89 0.000E+00 3.2 9 0E-5 2 0.000E+00 0.000E+00 0.000E+00 1.120E-5 2 0.000E+00 2.2 6 0E-5 2 SR-89 1.2 6 0E+10 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.59 0E+0 8 0.000E+00 3.610E+0 8 SR-9 0 1.220E+11 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.520E+0 9 0.000E+00 3.100E+10 SR-9 1 2.720E+0 5 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.220E+0 5 0.000E+00 9.830E+03 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X J R i Infant Dose Factors for use in the Gaseous Dose Calculations Appendix J Ri Infant Cow Milk - Page 2 of 3 Agegroup: INFANT Pathway: Grs

/Cow/Mil k (CMIL K) Units: m 2*mrem/yr / µµµµCi/sec; mrem/yr / µµµµCi/m 3 (H-3) Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in Total Body SR-9 2 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-9 0 6.810E+02 0.000E+00 0.000E+00 0.000E+00 0.000E+00 9.410E+0 5 0.000E+00 1.830E+01 Y-9 1 7.330E+04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.2 5 0E+0 6 0.000E+00 1.95 0E+03 Y-9 1M 5.670E-1 9 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.89 0E-1 5 0.000E+00 1.930E-20 Y-9 2 5.3 8 0E-04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.030E+01 0.000E+00 1.510E-0 5 Y-9 3 2.1 6 0E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.700E+04 0.000E+00 5.870E-02 Z R-95 6.800E+03 1.66 0E+03 0.000E+00 1.7 9 0E+03 0.000E+00 8.2 6 0E+0 5 0.000E+00 1.1 8 0E+03 Z R-9 7 4.0 6 0E+00 6.970E-01 0.000E+00 7.030E-01 0.000E+00 4.4 5 0E+04 0.000E+00 3.1 8 0E-01 NB-95 5.930E+0 5 2.440E+0 5 0.000E+00 1.7 5 0E+0 5 0.000E+00 2.0 6 0E+0 8 0.000E+00 1.410E+0 5 MO-99 0.000E+00 2.0 8 0E+0 8 0.000E+00 3.110E+0 8 0.000E+00 6.85 0E+07 0.000E+00 4.0 6 0E+07 T C-99 M 2.7 5 0E+01 5.670E+01 0.000E+00 6.100E+02 2.96 0E+01 1.65 0E+04 0.000E+00 7.300E+02 T C-101 2.470E-59 3.110E-59 0.000E+00 3.700E-58 1.700E-59 5.2 8 0E-5 7 0.000E+00 3.0 8 0E-58 RU-103 8.670E+03 0.000E+00 0.000E+00 1.800E+04 0.000E+00 1.0 5 0E+0 5 0.000E+00 2.900E+03 RU-10 5 8.0 5 0E-03 0.000E+00 0.000E+00 5.920E-02 0.000E+00 3.200E+00 0.000E+00 2.710E-03 RU-10 6 1.900E+0 5 0.000E+00 0.000E+00 2.2 5 0E+0 5 0.000E+00 1.440E+0 6 0.000E+00 2.3 8 0E+04 AG-110M 3.86 0E+0 8 2.820E+0 8 0.000E+00 4.030E+0 8 0.000E+00 1.4 6 0E+10 0.000E+00 1.86 0E+0 8 T E-12 5 M 1.510E+0 8 5.040E+07 5.070E+07 0.000E+00 0.000E+00 7.1 8 0E+07 0.000E+00 2.040E+07 T E-127 6.320E+03 2.120E+03 5.140E+03 1.540E+04 0.000E+00 1.330E+0 5 0.000E+00 1.3 6 0E+03 T E-127M 4.210E+0 8 1.400E+0 8 1.220E+0 8 1.040E+0 9 0.000E+00 1.700E+0 8 0.000E+00 5.100E+07 T E-12 9 2.720E-0 9 9.3 8 0E-10 2.2 8 0E-0 9 6.770E-0 9 0.000E+00 2.170E-07 0.000E+00 6.3 5 0E-10 T E-12 9 M 5.570E+0 8 1.910E+0 8 2.140E+0 8 1.3 9 0E+0 9 0.000E+00 3.330E+0 8 0.000E+00 8.58 0E+07 T E-131 3.430E-32 1.270E-32 3.0 6 0E-32 8.7 6 0E-32 0.000E+00 1.3 8 0E-30 0.000E+00 9.610E-33 T E-131M 3.3 8 0E+0 6 1.3 6 0E+0 6 2.7 5 0E+0 6 9.3 5 0E+0 6 0.000E+00 2.2 9 0E+07 0.000E+00 1.120E+0 6 T E-132 2.110E+07 1.040E+07 1.540E+07 6.530E+07 0.000E+00 3.870E+07 0.000E+00 9.7 5 0E+0 6 I-130 3.55 0E+0 6 7.810E+0 6 8.7 5 0E+0 8 8.58 0E+0 6 0.000E+00 1.670E+0 6 0.000E+00 3.130E+0 6 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X J R i Infant Dose Factors for use in the Gaseous Dose Calculations Appendix J Ri Infant Cow Milk - Page 3 of 3 Agegroup: INFANT Pathway: Grs

/Cow/Mil k (CMIL K) Units: m 2*mrem/yr / µµµµCi/sec; mrem/yr / µµµµCi/m 3 (H-3) Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in Total Body I-131 2.720E+0 9 3.200E+0 9 1.0 5 0E+12 3.740E+0 9 0.000E+00 1.140E+0 8 0.000E+00 1.410E+0 9 I-132 1.430E+00 2.900E+00 1.3 6 0E+02 3.240E+00 0.000E+00 2.3 5 0E+00 0.000E+00 1.030E+00 I-133 3.630E+07 5.2 8 0E+07 9.600E+0 9 6.210E+07 0.000E+00 8.930E+0 6 0.000E+00 1.55 0E+07 I-134 1.7 6 0E-11 3.600E-11 8.400E-10 4.030E-11 0.000E+00 3.720E-11 0.000E+00 1.2 8 0E-11 I-13 5 1.120E+0 5 2.230E+0 5 2.000E+07 2.4 9 0E+0 5 0.000E+00 8.0 8 0E+04 0.000E+00 8.140E+04 CS-134 3.65 0E+10 6.800E+10 0.000E+00 1.7 5 0E+10 7.1 8 0E+0 9 1.85 0E+0 8 0.000E+00 6.870E+0 9 CS-13 6 1.98 0E+0 9 5.810E+0 9 0.000E+00 2.320E+0 9 4.740E+0 8 8.820E+07 0.000E+00 2.170E+0 9 CS-137 5.1 5 0E+10 6.020E+10 0.000E+00 1.620E+10 6.55 0E+0 9 1.88 0E+0 8 0.000E+00 4.270E+0 9 CS-13 8 8.3 9 0E-23 1.3 6 0E-22 0.000E+00 6.800E-23 1.0 6 0E-23 2.1 8 0E-22 0.000E+00 6.610E-23 BA-13 9 4.270E-07 2.830E-10 0.000E+00 1.700E-10 1.720E-10 2.710E-0 5 0.000E+00 1.240E-0 8 BA-140 2.410E+0 8 2.410E+0 5 0.000E+00 5.720E+04 1.4 8 0E+0 5 5.920E+07 0.000E+00 1.240E+07 BA-141 3.930E-4 5 2.69 0E-4 8 0.000E+00 1.620E-4 8 1.640E-4 8 4.800E-44 0.000E+00 1.240E-4 6 BA-142 2.430E-7 9 2.020E-8 2 0.000E+00 1.1 6 0E-8 2 1.220E-8 2 1.000E-7 8 0.000E+00 1.200E-8 0 LA-140 4.0 5 0E+01 1.600E+01 0.000E+00 0.000E+00 0.000E+00 1.88 0E+0 5 0.000E+00 4.110E+00 LA-142 1.700E-10 6.2 5 0E-11 0.000E+00 0.000E+00 0.000E+00 1.0 6 0E-0 5 0.000E+00 1.500E-11 CE-141 4.340E+04 2.640E+04 0.000E+00 8.1 5 0E+03 0.000E+00 1.370E+07 0.000E+00 3.110E+03 CE-143 3.970E+02 2.630E+0 5 0.000E+00 7.670E+01 0.000E+00 1.540E+0 6 0.000E+00 3.000E+01 CE-144 2.330E+0 6 9.520E+0 5 0.000E+00 3.85 0E+0 5 0.000E+00 1.330E+0 8 0.000E+00 1.300E+0 5 PR-143 1.4 9 0E+03 5.55 0E+02 0.000E+00 2.0 6 0E+02 0.000E+00 7.840E+0 5 0.000E+00 7.3 6 0E+01 PR-144 5.69 0E-5 3 2.200E-5 3 0.000E+00 7.98 0E-5 4 0.000E+00 1.020E-4 8 0.000E+00 2.870E-5 4 N D-147 8.810E+02 9.0 5 0E+02 0.000E+00 3.4 9 0E+02 0.000E+00 5.740E+0 5 0.000E+00 5.55 0E+01 W-1 8 7 6.0 8 0E+04 4.230E+04 0.000E+00 0.000E+00 0.000E+00 2.4 8 0E+0 6 0.000E+00 1.4 6 0E+04 NP-23 9 3.65 0E+01 3.2 6 0E+00 0.000E+00 6.510E+00 0.000E+00 9.430E+04 0.000E+00 1.840E+00 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X J R i Infant Dose Factors for use in the Gaseous Dose Calculations Appendix J Ri Infant Goat Mil k - Page 1 of 3 Agegroup: INFANT Pathway: Grs

/Goat/Mil k (GMIL K) Units: m 2*mrem/yr / µµµµCi/sec; mrem/yr / µµµµCi/m 3 (H-3) Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in Total Body H-3 0.000E+00 4.86 0E+03 4.86 0E+03 4.86 0E+03 4.86 0E+03 4.86 0E+03 0.000E+00 4.86 0E+03 C-14 2.340E+0 9 5.000E+0 8 5.000E+0 8 5.000E+0 8 5.000E+0 8 5.000E+0 8 0.000E+00 5.000E+0 8 NA-24 1.85 0E+0 6 1.85 0E+0 6 1.85 0E+0 6 1.85 0E+0 6 1.85 0E+0 6 1.85 0E+0 6 0.000E+00 1.85 0E+0 6 P-32 1.920E+11 1.130E+10 0.000E+00 0.000E+00 0.000E+00 2.600E+0 9 0.000E+00 7.4 6 0E+0 9 CR-5 1 0.000E+00 0.000E+00 1.2 6 0E+04 2.7 6 0E+03 2.4 6 0E+04 5.640E+0 5 0.000E+00 1.940E+04 MN-5 4 0.000E+00 4.68 0E+0 6 0.000E+00 1.040E+0 6 0.000E+00 1.720E+0 6 0.000E+00 1.0 6 0E+0 6 MN-56 0.000E+00 3.720E-03 0.000E+00 3.1 9 0E-03 0.000E+00 3.3 8 0E-01 0.000E+00 6.410E-04 FE-55 1.7 6 0E+0 6 1.130E+0 6 0.000E+00 0.000E+00 5.55 0E+0 5 1.440E+0 5 0.000E+00 3.030E+0 5 FE-59 2.920E+0 6 5.100E+0 6 0.000E+00 0.000E+00 1.510E+0 6 2.430E+0 6 0.000E+00 2.010E+0 6 CO-58 0.000E+00 2.910E+0 6 0.000E+00 0.000E+00 0.000E+00 7.2 5 0E+0 6 0.000E+00 7.2 6 0E+0 6 CO-6 0 0.000E+00 1.0 6 0E+07 0.000E+00 0.000E+00 0.000E+00 2.520E+07 0.000E+00 2.500E+07 NI-6 3 4.1 9 0E+0 9 2.59 0E+0 8 0.000E+00 0.000E+00 0.000E+00 1.2 9 0E+07 0.000E+00 1.4 5 0E+0 8 NI-65 4.210E-01 4.7 6 0E-02 0.000E+00 0.000E+00 0.000E+00 3.620E+00 0.000E+00 2.170E-02 CU-6 4 0.000E+00 2.070E+04 0.000E+00 3.500E+04 0.000E+00 4.240E+0 5 0.000E+00 9.570E+03 Z N-65 6.66 0E+0 8 2.2 8 0E+0 9 0.000E+00 1.110E+0 9 0.000E+00 1.930E+0 9 0.000E+00 1.0 5 0E+0 9 Z N-69 2.420E-12 4.3 6 0E-12 0.000E+00 1.810E-12 0.000E+00 3.55 0E-10 0.000E+00 3.240E-13 BR-8 3 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-8 4 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+0 9 0.000E+00 0.000E+00 0.000E+00 6.830E+07 0.000E+00 1.320E+0 9 RB-88 0.000E+00 2.2 5 0E-4 5 0.000E+00 0.000E+00 0.000E+00 2.1 9 0E-4 5 0.000E+00 1.230E-4 5 RB-89 0.000E+00 3.940E-5 3 0.000E+00 0.000E+00 0.000E+00 1.340E-5 3 0.000E+00 2.720E-5 3 SR-89 2.640E+10 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.430E+0 8 0.000E+00 7.58 0E+0 8 SR-9 0 2.55 0E+11 0.000E+00 0.000E+00 0.000E+00 0.000E+00 3.1 9 0E+0 9 0.000E+00 6.500E+10 SR-9 1 5.700E+0 5 0.000E+00 0.000E+00 0.000E+00 0.000E+00 6.7 5 0E+0 5 0.000E+00 2.0 6 0E+04 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X J R i Infant Dose Factors for use in the Gaseous Dose Calculations Appendix J Ri Infant Goat Mil k - Page 2 of 3 Agegroup: INFANT Pathway: Grs

/Goat/Mil k (GMIL K) Units: m 2*mrem/yr / µµµµCi/sec; mrem/yr / µµµµCi/m 3 (H-3) Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in Total Body SR-9 2 9.7 5 0E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.0 5 0E+02 0.000E+00 3.620E-01 Y-9 0 8.170E+01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.130E+0 5 0.000E+00 2.1 9 0E+00 Y-9 1 8.7 9 0E+03 0.000E+00 0.000E+00 0.000E+00 0.000E+00 6.300E+0 5 0.000E+00 2.340E+02 Y-9 1M 6.810E-20 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.270E-1 6 0.000E+00 2.320E-21 Y-9 2 6.4 5 0E-0 5 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.230E+00 0.000E+00 1.810E-0 6 Y-9 3 2.59 0E-01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.040E+03 0.000E+00 7.0 5 0E-03 Z R-95 8.170E+02 1.99 0E+02 0.000E+00 2.140E+02 0.000E+00 9.910E+04 0.000E+00 1.410E+02 Z R-9 7 4.870E-01 8.3 6 0E-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 2.4 8 0E+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+0 6 0.000E+00 4.870E+0 6 T C-99 M 3.300E+00 6.800E+00 0.000E+00 7.320E+01 3.55 0E+00 1.970E+03 0.000E+00 8.7 6 0E+01 T C-101 2.96 0E-6 0 3.730E-6 0 0.000E+00 4.440E-59 2.030E-6 0 6.340E-58 0.000E+00 3.69 0E-59 RU-103 1.040E+03 0.000E+00 0.000E+00 2.170E+03 0.000E+00 1.270E+04 0.000E+00 3.4 8 0E+02 RU-10 5 9.66 0E-04 0.000E+00 0.000E+00 7.110E-03 0.000E+00 3.840E-01 0.000E+00 3.2 5 0E-04 RU-10 6 2.2 8 0E+04 0.000E+00 0.000E+00 2.700E+04 0.000E+00 1.730E+0 5 0.000E+00 2.85 0E+03 AG-110M 4.630E+07 3.3 8 0E+07 0.000E+00 4.830E+07 0.000E+00 1.7 5 0E+0 9 0.000E+00 2.240E+07 T E-12 5 M 1.810E+07 6.0 5 0E+0 6 6.0 9 0E+0 6 0.000E+00 0.000E+00 8.620E+0 6 0.000E+00 2.4 5 0E+0 6 T E-127 7.58 0E+02 2.540E+02 6.170E+02 1.85 0E+03 0.000E+00 1.59 0E+04 0.000E+00 1.630E+02 T E-127M 5.0 5 0E+07 1.68 0E+07 1.4 6 0E+07 1.240E+0 8 0.000E+00 2.040E+07 0.000E+00 6.120E+0 6 T E-12 9 3.2 6 0E-10 1.130E-10 2.740E-10 8.130E-10 0.000E+00 2.610E-0 8 0.000E+00 7.620E-11 T E-12 9 M 6.69 0E+07 2.2 9 0E+07 2.570E+07 1.670E+0 8 0.000E+00 3.99 0E+07 0.000E+00 1.030E+07 T E-131 4.110E-33 1.520E-33 3.670E-33 1.0 5 0E-32 0.000E+00 1.66 0E-31 0.000E+00 1.1 5 0E-33 T E-131M 4.0 5 0E+0 5 1.630E+0 5 3.310E+0 5 1.120E+0 6 0.000E+00 2.7 5 0E+0 6 0.000E+00 1.3 5 0E+0 5 T E-132 2.530E+0 6 1.2 5 0E+0 6 1.85 0E+0 6 7.840E+0 6 0.000E+00 4.640E+0 6 0.000E+00 1.170E+0 6 I-130 4.2 6 0E+0 6 9.370E+0 6 1.0 5 0E+0 9 1.030E+07 0.000E+00 2.010E+0 6 0.000E+00 3.7 6 0E+0 6 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X J R i Infant Dose Factors for use in the Gaseous Dose Calculations Appendix J Ri Infant Goat Mil k - Page 3 of 3 Agegroup: INFANT Pathway: Grs

/Goat/Mil k (GMIL K) Units: m 2*mrem/yr / µµµµCi/sec; mrem/yr / µµµµCi/m 3 (H-3) Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in Total Body I-131 3.2 6 0E+0 9 3.85 0E+0 9 1.2 6 0E+12 4.4 9 0E+0 9 0.000E+00 1.370E+0 8 0.000E+00 1.69 0E+0 9 I-132 1.720E+00 3.4 8 0E+00 1.630E+02 3.89 0E+00 0.000E+00 2.820E+00 0.000E+00 1.240E+00 I-133 4.3 5 0E+07 6.340E+07 1.1 5 0E+10 7.4 5 0E+07 0.000E+00 1.070E+07 0.000E+00 1.86 0E+07 I-134 2.110E-11 4.320E-11 1.010E-0 9 4.830E-11 0.000E+00 4.470E-11 0.000E+00 1.540E-11 I-13 5 1.3 5 0E+0 5 2.68 0E+0 5 2.400E+07 2.99 0E+0 5 0.000E+00 9.700E+04 0.000E+00 9.770E+04 CS-134 1.0 9 0E+11 2.040E+11 0.000E+00 5.2 5 0E+10 2.1 5 0E+10 5.540E+0 8 0.000E+00 2.0 6 0E+10 CS-13 6 5.930E+0 9 1.740E+10 0.000E+00 6.95 0E+0 9 1.420E+0 9 2.65 0E+0 8 0.000E+00 6.510E+0 9 CS-137 1.540E+11 1.810E+11 0.000E+00 4.85 0E+10 1.96 0E+10 5.65 0E+0 8 0.000E+00 1.2 8 0E+10 CS-13 8 2.520E-22 4.0 9 0E-22 0.000E+00 2.040E-22 3.1 9 0E-23 6.540E-22 0.000E+00 1.98 0E-22 BA-13 9 5.130E-0 8 3.400E-11 0.000E+00 2.040E-11 2.0 6 0E-11 3.2 5 0E-0 6 0.000E+00 1.4 8 0E-0 9 BA-140 2.89 0E+07 2.89 0E+04 0.000E+00 6.870E+03 1.7 8 0E+04 7.100E+0 6 0.000E+00 1.4 9 0E+0 6 BA-141 4.720E-4 6 3.230E-4 9 0.000E+00 1.940E-4 9 1.96 0E-4 9 5.7 6 0E-4 5 0.000E+00 1.4 9 0E-47 BA-142 2.920E-8 0 2.430E-8 3 0.000E+00 1.400E-8 3 1.470E-8 3 1.200E-7 9 0.000E+00 1.440E-8 1 LA-140 4.86 0E+00 1.920E+00 0.000E+00 0.000E+00 0.000E+00 2.2 5 0E+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-0 6 0.000E+00 1.7 9 0E-12 CE-141 5.200E+03 3.170E+03 0.000E+00 9.7 9 0E+02 0.000E+00 1.640E+0 6 0.000E+00 3.740E+02 CE-143 4.7 6 0E+01 3.1 6 0E+04 0.000E+00 9.200E+00 0.000E+00 1.840E+0 5 0.000E+00 3.600E+00 CE-144 2.7 9 0E+0 5 1.140E+0 5 0.000E+00 4.620E+04 0.000E+00 1.600E+07 0.000E+00 1.56 0E+04 PR-143 1.7 8 0E+02 6.670E+01 0.000E+00 2.4 8 0E+01 0.000E+00 9.410E+04 0.000E+00 8.840E+00 PR-144 6.830E-5 4 2.640E-5 4 0.000E+00 9.570E-55 0.000E+00 1.230E-4 9 0.000E+00 3.440E-55 N D-147 1.0 6 0E+02 1.0 9 0E+02 0.000E+00 4.1 9 0E+01 0.000E+00 6.88 0E+04 0.000E+00 6.65 0E+00 W-1 8 7 7.300E+03 5.070E+03 0.000E+00 0.000E+00 0.000E+00 2.98 0E+0 5 0.000E+00 1.7 5 0E+03 NP-23 9 4.3 8 0E+00 3.910E-01 0.000E+00 7.810E-01 0.000E+00 1.130E+04 0.000E+00 2.210E-01 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X J R i Infant Dose Factors for use in the Gaseous Dose Calculations Appendix J Ri Infant Inhalation - Page 1 of 3 Agegroup: INFANT Pathway: Inhalation (INHL) Units: mrem/yr / µµµµCi/m 3 Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in 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 2.65 0E+04 5.310E+03 5.310E+03 5.310E+03 5.310E+03 5.310E+03 0.000E+00 5.310E+03 NA-24 1.0 6 0E+04 1.0 6 0E+04 1.0 6 0E+04 1.0 6 0E+04 1.0 6 0E+04 1.0 6 0E+04 0.000E+00 1.0 6 0E+04 P-32 2.030E+0 6 1.120E+0 5 0.000E+00 0.000E+00 0.000E+00 1.610E+04 0.000E+00 7.740E+04 CR-5 1 0.000E+00 0.000E+00 5.7 5 0E+01 1.320E+01 1.2 8 0E+04 3.570E+02 0.000E+00 8.95 0E+01 MN-5 4 0.000E+00 2.530E+04 0.000E+00 4.98 0E+03 1.000E+0 6 7.0 6 0E+03 0.000E+00 4.98 0E+03 MN-56 0.000E+00 1.540E+00 0.000E+00 1.100E+00 1.2 5 0E+04 7.170E+04 0.000E+00 2.210E-01 FE-55 1.970E+04 1.170E+04 0.000E+00 0.000E+00 8.69 0E+04 1.0 9 0E+03 0.000E+00 3.330E+03 FE-59 1.3 6 0E+04 2.3 5 0E+04 0.000E+00 0.000E+00 1.010E+0 6 2.4 8 0E+04 0.000E+00 9.4 8 0E+03 CO-58 0.000E+00 1.220E+03 0.000E+00 0.000E+00 7.770E+0 5 1.110E+04 0.000E+00 1.820E+03 CO-6 0 0.000E+00 8.020E+03 0.000E+00 0.000E+00 4.510E+0 6 3.1 9 0E+04 0.000E+00 1.1 8 0E+04 NI-6 3 3.3 9 0E+0 5 2.040E+04 0.000E+00 0.000E+00 2.0 9 0E+0 5 2.420E+03 0.000E+00 1.1 6 0E+04 NI-65 2.3 9 0E+00 2.840E-01 0.000E+00 0.000E+00 8.120E+03 5.010E+04 0.000E+00 1.230E-01 CU-6 4 0.000E+00 1.88 0E+00 0.000E+00 3.98 0E+00 9.300E+03 1.500E+04 0.000E+00 7.740E-01 Z N-65 1.930E+04 6.2 6 0E+04 0.000E+00 3.2 5 0E+04 6.470E+0 5 5.140E+04 0.000E+00 3.110E+04 Z N-69 5.3 9 0E-02 9.670E-02 0.000E+00 4.020E-02 1.470E+03 1.320E+04 0.000E+00 7.1 8 0E-03 BR-8 3 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-8 4 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+0 5 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 3.3 9 0E+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 2.0 6 0E+02 SR-89 3.98 0E+0 5 0.000E+00 0.000E+00 0.000E+00 2.030E+0 6 6.400E+04 0.000E+00 1.140E+04 SR-9 0 4.0 9 0E+07 0.000E+00 0.000E+00 0.000E+00 1.120E+07 1.310E+0 5 0.000E+00 2.59 0E+0 6 SR-9 1 9.56 0E+01 0.000E+00 0.000E+00 0.000E+00 5.2 6 0E+04 7.340E+04 0.000E+00 3.4 6 0E+00 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X J R i Infant Dose Factors for use in the Gaseous Dose Calculations Appendix J Ri Infant Inhalation - Page 2 of 3 Agegroup: INFANT Pathway: Inhalation (INHL) Units: mrem/yr / µµµµCi/m 3 Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in Total Body SR-9 2 1.0 5 0E+01 0.000E+00 0.000E+00 0.000E+00 2.3 8 0E+04 1.400E+0 5 0.000E+00 3.910E-01 Y-9 0 3.2 9 0E+03 0.000E+00 0.000E+00 0.000E+00 2.69 0E+0 5 1.040E+0 5 0.000E+00 8.820E+01 Y-9 1 5.88 0E+0 5 0.000E+00 0.000E+00 0.000E+00 2.4 5 0E+0 6 7.030E+04 0.000E+00 1.570E+04 Y-9 1M 4.070E-01 0.000E+00 0.000E+00 0.000E+00 2.7 9 0E+03 2.3 5 0E+03 0.000E+00 1.3 9 0E-02 Y-9 2 1.640E+01 0.000E+00 0.000E+00 0.000E+00 2.4 5 0E+04 1.270E+0 5 0.000E+00 4.610E-01 Y-9 3 1.500E+02 0.000E+00 0.000E+00 0.000E+00 7.640E+04 1.670E+0 5 0.000E+00 4.070E+00 Z R-95 1.1 5 0E+0 5 2.7 9 0E+04 0.000E+00 3.110E+04 1.7 5 0E+0 6 2.170E+04 0.000E+00 2.030E+04 Z R-9 7 1.500E+02 2.56 0E+01 0.000E+00 2.59 0E+01 1.100E+0 5 1.400E+0 5 0.000E+00 1.170E+01 NB-95 1.570E+04 6.430E+03 0.000E+00 4.720E+03 4.7 9 0E+0 5 1.270E+04 0.000E+00 3.7 8 0E+03 MO-99 0.000E+00 1.65 0E+02 0.000E+00 2.65 0E+02 1.3 5 0E+0 5 4.870E+04 0.000E+00 3.230E+01 T C-99 M 1.400E-03 2.88 0E-03 0.000E+00 3.110E-02 8.110E+02 2.030E+03 0.000E+00 3.720E-02 T C-101 6.510E-0 5 8.230E-0 5 0.000E+00 9.7 9 0E-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+0 5 1.610E+04 0.000E+00 6.7 9 0E+02 RU-10 5 1.220E+00 0.000E+00 0.000E+00 8.99 0E-01 1.570E+04 4.840E+04 0.000E+00 4.100E-01 RU-10 6 8.68 0E+04 0.000E+00 0.000E+00 1.070E+0 5 1.1 6 0E+07 1.640E+0 5 0.000E+00 1.0 9 0E+04 AG-110M 9.98 0E+03 7.220E+03 0.000E+00 1.0 9 0E+04 3.670E+0 6 3.300E+04 0.000E+00 5.000E+03 T E-12 5 M 4.7 6 0E+03 1.99 0E+03 1.620E+03 0.000E+00 4.470E+0 5 1.2 9 0E+04 0.000E+00 6.58 0E+02 T E-127 2.230E+00 9.530E-01 1.85 0E+00 4.86 0E+00 1.030E+04 2.440E+04 0.000E+00 4.89 0E-01 T E-127M 1.670E+04 6.900E+03 4.870E+03 3.7 5 0E+04 1.310E+0 6 2.730E+04 0.000E+00 2.070E+03 T E-12 9 7.88 0E-02 3.470E-02 6.7 5 0E-02 1.7 5 0E-01 3.000E+03 2.630E+04 0.000E+00 1.88 0E-02 T E-12 9 M 1.410E+04 6.0 9 0E+03 5.470E+03 3.1 8 0E+04 1.68 0E+0 6 6.900E+04 0.000E+00 2.230E+03 T E-131 1.740E-02 8.220E-03 1.58 0E-02 3.99 0E-02 2.0 6 0E+03 8.220E+03 0.000E+00 5.000E-03 T E-131M 1.070E+02 5.500E+01 8.930E+01 2.65 0E+02 1.99 0E+0 5 1.1 9 0E+0 5 0.000E+00 3.630E+01 T E-132 3.720E+02 2.370E+02 2.7 9 0E+02 1.030E+03 3.400E+0 5 4.410E+04 0.000E+00 1.7 6 0E+02 I-130 6.3 6 0E+03 1.3 9 0E+04 1.600E+0 6 1.530E+04 0.000E+00 1.99 0E+03 0.000E+00 5.570E+03 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X J R i Infant Dose Factors for use in the Gaseous Dose Calculations Appendix J Ri Infant Inhalation - Page 3 of 3 Agegroup: INFANT Pathway: Inhalation (INHL) Units: mrem/yr / µµµµCi/m 3 Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in Total Body I-131 3.7 9 0E+04 4.440E+04 1.4 8 0E+07 5.1 8 0E+04 0.000E+00 1.0 6 0E+03 0.000E+00 1.96 0E+04 I-132 1.69 0E+03 3.540E+03 1.69 0E+0 5 3.95 0E+03 0.000E+00 1.900E+03 0.000E+00 1.2 6 0E+03 I-133 1.320E+04 1.920E+04 3.56 0E+0 6 2.240E+04 0.000E+00 2.1 6 0E+03 0.000E+00 5.600E+03 I-134 9.210E+02 1.88 0E+03 4.4 5 0E+04 2.0 9 0E+03 0.000E+00 1.2 9 0E+03 0.000E+00 6.65 0E+02 I-13 5 3.86 0E+03 7.600E+03 6.96 0E+0 5 8.470E+03 0.000E+00 1.830E+03 0.000E+00 2.770E+03 CS-134 3.96 0E+0 5 7.030E+0 5 0.000E+00 1.900E+0 5 7.970E+04 1.330E+03 0.000E+00 7.4 5 0E+04 CS-13 6 4.830E+04 1.3 5 0E+0 5 0.000E+00 5.640E+04 1.1 8 0E+04 1.430E+03 0.000E+00 5.2 9 0E+04 CS-137 5.4 9 0E+0 5 6.120E+0 5 0.000E+00 1.720E+0 5 7.130E+04 1.330E+03 0.000E+00 4.55 0E+04 CS-13 8 5.0 5 0E+02 7.810E+02 0.000E+00 4.100E+02 6.540E+01 8.7 6 0E+02 0.000E+00 3.98 0E+02 BA-13 9 1.4 8 0E+00 9.840E-04 0.000E+00 5.920E-04 5.95 0E+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+0 6 3.840E+04 0.000E+00 2.900E+03 BA-141 1.570E-01 1.0 8 0E-04 0.000E+00 6.500E-0 5 2.970E+03 4.7 5 0E+03 0.000E+00 4.970E-03 BA-142 3.98 0E-02 3.300E-0 5 0.000E+00 1.900E-0 5 1.55 0E+03 6.930E+02 0.000E+00 1.96 0E-03 LA-140 5.0 5 0E+02 2.000E+02 0.000E+00 0.000E+00 1.68 0E+0 5 8.4 8 0E+04 0.000E+00 5.1 5 0E+01 LA-142 1.030E+00 3.770E-01 0.000E+00 0.000E+00 8.220E+03 5.95 0E+04 0.000E+00 9.040E-02 CE-141 2.770E+04 1.670E+04 0.000E+00 5.2 5 0E+03 5.170E+0 5 2.1 6 0E+04 0.000E+00 1.99 0E+03 CE-143 2.930E+02 1.930E+02 0.000E+00 5.640E+01 1.1 6 0E+0 5 4.970E+04 0.000E+00 2.210E+01 CE-144 3.1 9 0E+0 6 1.210E+0 6 0.000E+00 5.3 8 0E+0 5 9.840E+0 6 1.4 8 0E+0 5 0.000E+00 1.7 6 0E+0 5 PR-143 1.400E+04 5.240E+03 0.000E+00 1.970E+03 4.330E+0 5 3.720E+04 0.000E+00 6.99 0E+02 PR-144 4.7 9 0E-02 1.85 0E-02 0.000E+00 6.720E-03 1.610E+03 4.2 8 0E+03 0.000E+00 2.410E-03 N D-147 7.940E+03 8.130E+03 0.000E+00 3.1 5 0E+03 3.220E+0 5 3.120E+04 0.000E+00 5.000E+02 W-1 8 7 1.300E+01 9.020E+00 0.000E+00 0.000E+00 3.96 0E+04 3.56 0E+04 0.000E+00 3.120E+00 NP-23 9 3.710E+02 3.320E+01 0.000E+00 6.620E+01 5.95 0E+04 2.4 9 0E+04 0.000E+00 1.88 0E+01 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X J R i Infant Dose Factors for use in the Gaseous Dose Calculations Appendix J Ri Infant Ground Plane Deposition - Page 1 of 3 Agegroup: INFANT Pathway: Ground Plane Deposition (GPD) Units: m 2*mrem/yr / µµµµCi/sec Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in 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 1.1 9 0E+07 1.1 9 0E+07 1.1 9 0E+07 1.1 9 0E+07 1.1 9 0E+07 1.1 9 0E+07 1.3 9 0E+07 1.1 9 0E+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-5 1 4.66 0E+0 6 4.66 0E+0 6 4.66 0E+0 6 4.66 0E+0 6 4.66 0E+0 6 4.66 0E+0 6 5.510E+0 6 4.66 0E+0 6 MN-5 4 1.3 9 0E+0 9 1.3 9 0E+0 9 1.3 9 0E+0 9 1.3 9 0E+0 9 1.3 9 0E+0 9 1.3 9 0E+0 9 1.630E+0 9 1.3 9 0E+0 9 MN-56 9.020E+0 5 9.020E+0 5 9.020E+0 5 9.020E+0 5 9.020E+0 5 9.020E+0 5 1.070E+0 6 9.020E+0 5 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+0 8 2.730E+0 8 2.730E+0 8 2.730E+0 8 2.730E+0 8 2.730E+0 8 3.210E+0 8 2.730E+0 8 CO-58 3.7 9 0E+0 8 3.7 9 0E+0 8 3.7 9 0E+0 8 3.7 9 0E+0 8 3.7 9 0E+0 8 3.7 9 0E+0 8 4.440E+0 8 3.7 9 0E+0 8 CO-6 0 2.1 5 0E+10 2.1 5 0E+10 2.1 5 0E+10 2.1 5 0E+10 2.1 5 0E+10 2.1 5 0E+10 2.530E+10 2.1 5 0E+10 NI-6 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 NI-65 2.970E+0 5 2.970E+0 5 2.970E+0 5 2.970E+0 5 2.970E+0 5 2.970E+0 5 3.4 5 0E+0 5 2.970E+0 5 CU-6 4 6.070E+0 5 6.070E+0 5 6.070E+0 5 6.070E+0 5 6.070E+0 5 6.070E+0 5 6.88 0E+0 5 6.070E+0 5 Z N-65 7.470E+0 8 7.470E+0 8 7.470E+0 8 7.470E+0 8 7.470E+0 8 7.470E+0 8 8.59 0E+0 8 7.470E+0 8 Z N-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-8 3 4.870E+03 4.870E+03 4.870E+03 4.870E+03 4.870E+03 4.870E+03 7.0 8 0E+03 4.870E+03 BR-8 4 2.030E+0 5 2.030E+0 5 2.030E+0 5 2.030E+0 5 2.030E+0 5 2.030E+0 5 2.3 6 0E+0 5 2.030E+0 5 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 8.99 0E+0 6 8.99 0E+0 6 8.99 0E+0 6 8.99 0E+0 6 8.99 0E+0 6 8.99 0E+0 6 1.030E+07 8.99 0E+0 6 RB-88 3.310E+04 3.310E+04 3.310E+04 3.310E+04 3.310E+04 3.310E+04 3.7 8 0E+04 3.310E+04 RB-89 1.230E+0 5 1.230E+0 5 1.230E+0 5 1.230E+0 5 1.230E+0 5 1.230E+0 5 1.4 8 0E+0 5 1.230E+0 5 SR-89 2.1 6 0E+04 2.1 6 0E+04 2.1 6 0E+04 2.1 6 0E+04 2.1 6 0E+04 2.1 6 0E+04 2.510E+04 2.1 6 0E+04 SR-9 0 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-9 1 2.1 5 0E+0 6 2.1 5 0E+0 6 2.1 5 0E+0 6 2.1 5 0E+0 6 2.1 5 0E+0 6 2.1 5 0E+0 6 2.510E+0 6 2.1 5 0E+0 6 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X J R i Infant Dose Factors for use in the Gaseous Dose Calculations Appendix J Ri Infant Ground Plane Deposition - Page 2 of 3 Agegroup: INFANT Pathway: Ground Plane Deposition (GPD) Units: m 2*mrem/yr / µµµµCi/sec Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in Total Body SR-9 2 7.770E+0 5 7.770E+0 5 7.770E+0 5 7.770E+0 5 7.770E+0 5 7.770E+0 5 8.630E+0 5 7.770E+0 5 Y-9 0 4.4 9 0E+03 4.4 9 0E+03 4.4 9 0E+03 4.4 9 0E+03 4.4 9 0E+03 4.4 9 0E+03 5.310E+03 4.4 9 0E+03 Y-9 1 1.070E+0 6 1.070E+0 6 1.070E+0 6 1.070E+0 6 1.070E+0 6 1.070E+0 6 1.210E+0 6 1.070E+0 6 Y-9 1M 1.000E+0 5 1.000E+0 5 1.000E+0 5 1.000E+0 5 1.000E+0 5 1.000E+0 5 1.1 6 0E+0 5 1.000E+0 5 Y-9 2 1.800E+0 5 1.800E+0 5 1.800E+0 5 1.800E+0 5 1.800E+0 5 1.800E+0 5 2.140E+0 5 1.800E+0 5 Y-9 3 1.830E+0 5 1.830E+0 5 1.830E+0 5 1.830E+0 5 1.830E+0 5 1.830E+0 5 2.510E+0 5 1.830E+0 5 Z R-95 2.4 5 0E+0 8 2.4 5 0E+0 8 2.4 5 0E+0 8 2.4 5 0E+0 8 2.4 5 0E+0 8 2.4 5 0E+0 8 2.840E+0 8 2.4 5 0E+0 8 Z R-9 7 2.96 0E+0 6 2.96 0E+0 6 2.96 0E+0 6 2.96 0E+0 6 2.96 0E+0 6 2.96 0E+0 6 3.440E+0 6 2.96 0E+0 6 NB-95 1.370E+0 8 1.370E+0 8 1.370E+0 8 1.370E+0 8 1.370E+0 8 1.370E+0 8 1.610E+0 8 1.370E+0 8 MO-99 3.99 0E+0 6 3.99 0E+0 6 3.99 0E+0 6 3.99 0E+0 6 3.99 0E+0 6 3.99 0E+0 6 4.630E+0 6 3.99 0E+0 6 T C-99 M 1.840E+0 5 1.840E+0 5 1.840E+0 5 1.840E+0 5 1.840E+0 5 1.840E+0 5 2.110E+0 5 1.840E+0 5 T C-101 2.040E+04 2.040E+04 2.040E+04 2.040E+04 2.040E+04 2.040E+04 2.2 6 0E+04 2.040E+04 RU-103 1.0 8 0E+0 8 1.0 8 0E+0 8 1.0 8 0E+0 8 1.0 8 0E+0 8 1.0 8 0E+0 8 1.0 8 0E+0 8 1.2 6 0E+0 8 1.0 8 0E+0 8 RU-10 5 6.3 6 0E+0 5 6.3 6 0E+0 5 6.3 6 0E+0 5 6.3 6 0E+0 5 6.3 6 0E+0 5 6.3 6 0E+0 5 7.210E+0 5 6.3 6 0E+0 5 RU-10 6 4.220E+0 8 4.220E+0 8 4.220E+0 8 4.220E+0 8 4.220E+0 8 4.220E+0 8 5.070E+0 8 4.220E+0 8 AG-110M 3.440E+0 9 3.440E+0 9 3.440E+0 9 3.440E+0 9 3.440E+0 9 3.440E+0 9 4.010E+0 9 3.440E+0 9 T E-12 5 M 1.55 0E+0 6 1.55 0E+0 6 1.55 0E+0 6 1.55 0E+0 6 1.55 0E+0 6 1.55 0E+0 6 2.130E+0 6 1.55 0E+0 6 T E-127 2.98 0E+03 2.98 0E+03 2.98 0E+03 2.98 0E+03 2.98 0E+03 2.98 0E+03 3.2 8 0E+03 2.98 0E+03 T E-127M 9.1 6 0E+04 9.1 6 0E+04 9.1 6 0E+04 9.1 6 0E+04 9.1 6 0E+04 9.1 6 0E+04 1.0 8 0E+0 5 9.1 6 0E+04 T E-12 9 2.620E+04 2.620E+04 2.620E+04 2.620E+04 2.620E+04 2.620E+04 3.100E+04 2.620E+04 T E-12 9 M 1.98 0E+07 1.98 0E+07 1.98 0E+07 1.98 0E+07 1.98 0E+07 1.98 0E+07 2.310E+07 1.98 0E+07 T E-131 2.920E+04 2.920E+04 2.920E+04 2.920E+04 2.920E+04 2.920E+04 3.4 5 0E+07 2.920E+04 T E-131M 8.030E+0 6 8.030E+0 6 8.030E+0 6 8.030E+0 6 8.030E+0 6 8.030E+0 6 9.4 6 0E+0 6 8.030E+0 6 T E-132 4.230E+0 6 4.230E+0 6 4.230E+0 6 4.230E+0 6 4.230E+0 6 4.230E+0 6 4.98 0E+0 6 4.230E+0 6 I-130 5.510E+0 6 5.510E+0 6 5.510E+0 6 5.510E+0 6 5.510E+0 6 5.510E+0 6 6.69 0E+0 6 5.510E+0 6 Oconee Nuclear Station January, 2007 Offsite Dose Calculation Manual (O D CM) Revision 47 APPENDI X J R i Infant Dose Factors for use in the Gaseous Dose Calculations Appendix J Ri Infant Ground Plane Deposition - Page 3 of 3 Agegroup: INFANT Pathway: Ground Plane Deposition (GPD) Units: m 2*mrem/yr / µµµµCi/sec Nuclide Bone Liver Thyroid Kidney Lung Gilli S k in Total Body I-131 1.720E+07 1.720E+07 1.720E+07 1.720E+07 1.720E+07 1.720E+07 2.0 9 0E+07 1.720E+07 I-132 1.2 5 0E+0 6 1.2 5 0E+0 6 1.2 5 0E+0 6 1.2 5 0E+0 6 1.2 5 0E+0 6 1.2 5 0E+0 6 1.470E+0 6 1.2 5 0E+0 6 I-133 2.4 5 0E+0 6 2.4 5 0E+0 6 2.4 5 0E+0 6 2.4 5 0E+0 6 2.4 5 0E+0 6 2.4 5 0E+0 6 2.98 0E+0 6 2.4 5 0E+0 6 I-134 4.470E+0 5 4.470E+0 5 4.470E+0 5 4.470E+0 5 4.470E+0 5 4.470E+0 5 5.300E+0 5 4.470E+0 5 I-13 5 2.530E+0 6 2.530E+0 6 2.530E+0 6 2.530E+0 6 2.530E+0 6 2.530E+0 6 2.95 0E+0 6 2.530E+0 6 CS-134 6.86 0E+0 9 6.86 0E+0 9 6.86 0E+0 9 6.86 0E+0 9 6.86 0E+0 9 6.86 0E+0 9 8.000E+0 9 6.86 0E+0 9 CS-13 6 1.510E+0 8 1.510E+0 8 1.510E+0 8 1.510E+0 8 1.510E+0 8 1.510E+0 8 1.710E+0 8 1.510E+0 8 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-13 8 3.59 0E+0 5 3.59 0E+0 5 3.59 0E+0 5 3.59 0E+0 5 3.59 0E+0 5 3.59 0E+0 5 4.100E+0 5 3.59 0E+0 5 BA-13 9 1.0 6 0E+0 5 1.0 6 0E+0 5 1.0 6 0E+0 5 1.0 6 0E+0 5 1.0 6 0E+0 5 1.0 6 0E+0 5 1.1 9 0E+0 5 1.0 6 0E+0 5 BA-140 2.0 5 0E+07 2.0 5 0E+07 2.0 5 0E+07 2.0 5 0E+07 2.0 5 0E+07 2.0 5 0E+07 2.3 5 0E+07 2.0 5 0E+07 BA-141 4.170E+04 4.170E+04 4.170E+04 4.170E+04 4.170E+04 4.170E+04 4.7 5 0E+04 4.170E+04 BA-142 4.4 9 0E+04 4.4 9 0E+04 4.4 9 0E+04 4.4 9 0E+04 4.4 9 0E+04 4.4 9 0E+04 5.110E+04 4.4 9 0E+04 LA-140 1.920E+07 1.920E+07 1.920E+07 1.920E+07 1.920E+07 1.920E+07 2.1 8 0E+07 1.920E+07 LA-142 7.600E+0 5 7.600E+0 5 7.600E+0 5 7.600E+0 5 7.600E+0 5 7.600E+0 5 9.120E+0 5 7.600E+0 5 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+0 6 2.310E+0 6 2.310E+0 6 2.310E+0 6 2.310E+0 6 2.310E+0 6 2.630E+0 6 2.310E+0 6 CE-144 6.95 0E+07 6.95 0E+07 6.95 0E+07 6.95 0E+07 6.95 0E+07 6.95 0E+07 8.040E+07 6.95 0E+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 N D-147 8.3 9 0E+0 6 8.3 9 0E+0 6 8.3 9 0E+0 6 8.3 9 0E+0 6 8.3 9 0E+0 6 8.3 9 0E+0 6 1.010E+07 8.3 9 0E+0 6 W-1 8 7 2.3 5 0E+0 6 2.3 5 0E+0 6 2.3 5 0E+0 6 2.3 5 0E+0 6 2.3 5 0E+0 6 2.3 5 0E+0 6 2.730E+0 6 2.3 5 0E+0 6 NP-23 9 1.710E+0 6 1.710E+0 6 1.710E+0 6 1.710E+0 6 1.710E+0 6 1.710E+0 6 1.98 0E+0 6 1.710E+0 6