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| number = ML091280665
| number = ML091280665
| issue date = 01/31/2009
| issue date = 01/31/2009
| title = 2009 Offsite Dose Calculation Manual, Revision 49
| title = Offsite Dose Calculation Manual, Revision 49
| author name = Ingram C D
| author name = Ingram C
| author affiliation = Duke Energy Carolinas, LLC
| author affiliation = Duke Energy Carolinas, LLC
| addressee name =  
| addressee name =  
Line 15: Line 15:


=Text=
=Text=
{{#Wiki_filter:Duke i (tEnergy.Oconee Nuclear Station Units 1, 2 and 3 ODCM Offsite Dose Calculation Manual 2009 tDuke Power A Duke Energy Company Oconee Nuclear Station Units 1, 2 and 3 OFFSITE DOSE CALCULATION MANUAL (ODCM)Prepared By: C. D. Ingram Approved By: L. E. Haynes General Office Radiation Protection Corporate RP Manager, Nuclear GO Reviewed By: R. A. Bowser ONS Radiation Protection Approved By: T. P. Gillespie, Jr.ONS Station Manage.r Reviewed By: J. A. Cashin ONS Radwaste Chemistry REVISION NUMBER EFFECTIVE YEAR 49 2009 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)January, 2009 Revision 49 TABLE OF CONTENTS Executive Summary.Executive Summary- I 1.0 Radwaste Systems 1.0.1 Liquid Radwaste Processing
{{#Wiki_filter:Duke i (tEnergy.
Oconee Nuclear Station Units 1, 2 and 3 ODCM Offsite Dose Calculation Manual 2009


====1.0.2 Gaseous====
tDuke  Power A Duke Energy Company Oconee Nuclear Station Units 1, 2 and 3 OFFSITE DOSE CALCULATION MANUAL (ODCM)
Radwaste Processing
Prepared By: C. D. Ingram                Approved By: L. E. Haynes General Office Radiation Protection      Corporate RP Manager, Nuclear GO Reviewed By: R. A. Bowser ONS Radiation Protection Approved By: T. P. Gillespie, Jr.
..2.0 Release Rate Calculations
ONS Station Manage.r Reviewed By: J. A. Cashin ONS Radwaste Chemistry REVISION NUMBER                          EFFECTIVE YEAR 49                                    2009


====2.0.1 Liquid====
Oconee Nuclear Station                                                                    January, 2009 Offsite Dose Calculation Manual (ODCM)                                                      Revision 49 TABLE OF CONTENTS Executive Summary.                                                              Executive Summary- I 1.0 Radwaste Systems                                                                                1-1 1.0.1 Liquid Radwaste Processing                                                              1-1 1.0.2 Gaseous Radwaste Processing    .    .                                                  1-3 2.0 Release Rate Calculations                                                                      2-1 2.0.1 Liquid Release Rate Limit Calculations                                                 2-1 2.0.1.1 Liquid Radwaste Effluent Line Release Rate Limit Calculation                   2-1 2.0.1.2 #3 Chemical Treatment Pond Effluent Line Discharge                             2-2 2.0.2 Gaseous Release Rate Limit Calculations .                                               2-5 2.0.2.1 Unit Vent Discharge Release Rate Limit Calculation                             2-5 3.0  Setpoint Calculations                                                                        3-1 3.0.1 Liquid Radiation Monitor Setpoint Calculations    ..  .                                3-1 3.0.2 Gaseous Radiation Monitor Setpoint Calculations      .                                3-5 3.0.2.1 Unit Vents Setpoints (RIA-45 and RIA-46)                                        3-7 3.0.2.2 Radwaste Facility Setpoints (4RIA-45) .                                          3-8 3.0.2.3 interim Radwaste Building Setpoints (RIA-53)                                    3-9 3.0.2.4 Waste Gas Decay Tank Setpoints (RIA-37 and RIA-38).                            3-9 4.0  Effluent Dose Models                                                                          4-1 4.0.1 Liquid Effluent Dose Model for the Maximum Exposed Individual                          4-1 4.0.2 Gaseous Effluent Dose Model for the Maximum Exposed Individual.                        4-7 4.0.3 Direct Radiation                                                                        4-18 4.0.4 Effluent Apportionment ....                                                            4-18 5.0  Fuel Cycle Calculations .                                                                    5-1 5.0.1 Milling                                                                                5-1 5.0.2 Conversion                                                                              5-1 5.0.3 Enrichment                                                                              5-1 5.0.4 Fuel Fabrication                                                                        5-1 5.0.5 Nuclear Power Production                                                                5-2 5.0.6 Fuel Reprocessing                                                                      5-2 5.0.7 40CFR 190 Total Dose Determination                                                      5-2 6.0  Environmental Locations              .    .                                                  6-1 6.0.1 Site Description and Sample Locations                                                  6-1 6.0.2 Land Use Census Data                                                                    6-1 6.0.3 Oconee Meteorology: Relative Air Concentrations and Deposition                          6-8 6.0.3.1 XOQDOQ Methodology and Assumptions                                              6-8 6.0.3.2 Meteorological Data                    .                                        6-9 6.0.3.3 Annual XOQDOQ Comparison to the ODCM            .    .                        6-10 7.0 Licensee Initiated Changes                                                                      7-1 i
Release Rate Limit Calculations 2.0.1.1 Liquid Radwaste Effluent Line Release Rate Limit Calculation 2.0.1.2 #3 Chemical Treatment Pond Effluent Line Discharge 2.0.2 Gaseous Release Rate Limit Calculations  
.2.0.2.1 Unit Vent Discharge Release Rate Limit Calculation


===3.0 Setpoint===
Oconee Nuclear Station                                                              January, 2009 Offsite Dose Calculation Manual (ODCM)                                                Revision 49 Appendices Appendix  A: Dose Factors for Exposure to a Semi-Infinite Cloud of Noble Gases              A-I Appendix  B: Pi Dose Factors for use in the Gaseous Release Rate Limit Calculations        B-I Appendix  C: Ai Adult Dose Factors for use in the Liquid Dose Calculations                  C-I Appendix  D: Ai Teen Dose Factors for use in the Liquid Dose Calculations                  D-1 Appendix  E: Ai Child Dose Factors for use in the Liquid Dose Calculations                  E-I Appendix  F: Ai Infant Dose Factors for use in the Liquid Dose Calculations                F-1 Appendix  G: Ri Adult Dose Factors for use in the Gaseous.Dose Calculations                G-I Appendix  H: Ri Teen Dose Factors for use in the Gaseous Dose Calculations                  H-I Appendix  1: Ri Child Dose Factors for use in the Gaseous Dose Calculations                I-I Appendix  J: Ri Infant Dose Factors for use in the Gaseous Dose Calculations                J-I LIST OF FIGURES 1.0-1  Liquid Radwaste System.                                                              1-2 1.0-2  Gaseous Radwaste System (4 pages)                                                    1-4 2.0-1  Liquid Radwaste Discharge Locations                                                  2-4 6.0-1  Sampling Locations Map (Site Boundary).                                              6-5 6.0-2  Sampling Locations Map (Ten Mile Radius)                                            6-6 6.0-3  Land Use Census Map      .                  .                                      6-7 LIST OF TABLES 3.0-i RIA-33 Cs-137 Equivalents.                                                            3-4 3.0-2 Xe-133 Equivalents.                                                                  3-11 6.0-1 Sampling Locations.              .                                                  6-2 6.0-2 TLD Sites                                                                            6-3 6.0-3 Land Use Census Results.                                                              6-4 6.0-4 Terrain Heights Above ONS Yard Grade Elevation (m)                                    6-9 6.0-5 ONS Atmospheric Stability Frequency (1988 - 1992)                                    6-10 6.0-6 ONS Frequency of Wind Direction and Speed (1988 - 1992)                              6-10 6.0-7 ONS Limiting X/Q and D/Q Values (1988-1992)                                          6-11 6.0-8 ONS Delta-T Ranges per Vertical Separation Distances                                  6-11 6.0-9 Oconee Semi-Elevated x/Q and D/Q Average Values (1988-1992)                          6-12 6.0-10 Oconee Ground Level x/Q and D/Q Average Values (1988-1992)                            6-14 ii
Calculations


====3.0.1 Liquid====
Oconee Nuclear Station                                                      January, 2009 Offsite Dose Calculation Manual (ODCM)                                       Revision 49 EXECUTIVE
Radiation Monitor Setpoint Calculations
.. .3.0.2 Gaseous Radiation Monitor Setpoint Calculations
.3.0.2.1 Unit Vents Setpoints (RIA-45 and RIA-46)3.0.2.2 Radwaste Facility Setpoints (4RIA-45)
.3.0.2.3 interim Radwaste Building Setpoints (RIA-53)3.0.2.4 Waste Gas Decay Tank Setpoints (RIA-37 and RIA-38).4.0 Effluent Dose Models 4.0.1 Liquid Effluent Dose Model for the Maximum Exposed Individual


====4.0.2 Gaseous====
==SUMMARY==
Effluent Dose Model for the Maximum Exposed Individual.
 
The Oconee Nuclear Station (ONS) Offsite Dose Calculation Manual (ODCM) provides the methodology and parameters to be used in the calculation of offsite doses due to normal operation radioactive liquid and gaseous effluents to assure compliance with the dose limitations of the Selected Licensee Commitments (SLCs, UFSAR Chapter 16) and Technical Specifications. These dose limitations assure that:
(1) the concentration of radioactive liquid effluents released from the site to the unrestricted area will be limited to 10 times the effluent concentration (EC) levels of 10CFR20, Appendix B, Table 2, and 2.OE-04 ptCi/ml for dissolved and entrained noble gases; (2) the exposures to any individual member of the public from radioactive liquid effluents will not result in doses greater than the ALARA design objectives of IOCFR50, Appendix I or the 10CFR20 limits; (3) the dose rate at any time at the site boundary from radioactive gaseous effluents will be limited to: for noble gases; less than or equal to 500 mrem/yr to the whole body, and less than or equal to 3000 mrem/yr to the skin; and for iodine-131 and iodine-133, for tritium, and for all radioactive materials in particulate form with half-lives greater than 8 days; less than or equal to 1500 mrem/yr to any organ; (4) the exposure to any individual member of the public from radioactive gaseous effluents will not result in doses greater than the ALARA design objectives of IOCFR50, Appendix I or the 10CFR20 limits; and (5) the dose to any individual member of the public from the nuclear fuel cycle will not exceed the limits of 40CFR1 90.
The methodology and parameters F-used to assure compliance with the dose limitations described above shall be used to prepare the radioactive liquid and gaseous effluent reports required by the SLCs and Technical Specifications. Dose calculations      that    demonstrate compliance with 40CFR190 will be considered          to      demonstrate
* compliance with the 10CFR20 0.1-rem annual dose limit.          The ODCM          also provides        the Executive Summary - Page I
 
Oconee Nuclear Station                                                    January, 2009 Offsite Dose Calculation Manual (ODCM)                                    Revision 49 methodology and parameters to be used in the calculation of radioactive liquid and gaseous effluent monitoring instrumentation alarm /trip setpoints to assure compliance with the concentration and dose rate limitations of the SLCs and Technical Specifications. Normally RETDAS, a computer code that implements NUREG-0133 methodology, is used for the calculation of offsite doses, but the ODCM also provides a method for the calculation of offsite doses when RETDAS is not available.
The ODCM has been prepared as generically as possible in order to minimize the need for revisions. However, some changes to the ODCM such as land-use census data are expected on an annual basis. Any changes to the methodology and parameters to be used in this ODCM shall be reviewed by knowledgeable individual(s), and approved by the Station Manager and the General Office Radiation Protection Manager prior to implementation. Changes to the ODCM shall be submitted to the Nuclear Regulatory Commission in accordance with the SLCs and Technical Specifications.
The ODCM does not replace any station implementing procedures. Programmatic controls for radioactive effluents and radiological environmental monitoring are contained in the Administrative Controls chapter of the Technical Specifications.
Procedural details for radioactive effluents and radiological environmental monitoring consisting of licensee commitments, applicability, remedial actions, surveillance requirements, and the bases for these requirements are contained in Section 16.11 of the SLCs.
Executive Summary - Page 2
 
Oconee Nuclear Station                                                            January, 2009 Offsite Dose Calculation Manual (ODCM)                                            Revision 49 1.0 RADWASTE SYSTEMS 1.0.1    LIQUID RADWASTE PROCESSING The liquid radwaste system at Oconee Nuclear Station is used to collect and treat liquid chemical and radiochemical byproducts of unit operation. The system produces effluents that are discharged in small, dilute quantities to the environment. The means of treatment vary with waste type and desired product in the various systems:
(A) Filtration - Waste sources are filtered prior to processing as necessary.
(B) Ion Exchange - Ion exchange is used to remove radioactive ions from solution. Also, ion exchange is normally used in removing cations (cobalt, cesium, manganese) and anions (chloride, fluoride) from the filtrate in order to purify the filtrate for release.
(C) Gas Stripping - Removal of gaseous radioactive fission products is accomplished through venting of atmospheric holdup tanks.
Figure 1.0-1 is a schematic representation of the liquid radwaste system at Oconee.
Section I - Page I
 
Oconee Nuclear Station                                                                January, 2009 Offsite Dose Calculation Manual (ODCM)                                              Revision 49 Figure 1.0-10Oconee Nuclear Station Liquid Radwaste System E.
GA                                                                COOE.        ISCMARGE KEGW£E LAKE RAASýTE        SMIELDED FAGILITI        SWP -
AREA    YSE DRAINSFROM.                                                        %'EI            GE-lCEWATER
  . . RT-N SISTEM    -
MAlEAWASTEEEAPORAA-1.A"                                          SOAGR P-IFICATIOMGMI-RIZER SEMERGNSIM.*
FI -      ,.G' SPENTFUELSYSTEM
_,.ESAETESTAR*
FUEL T,**4EAF:_
20-4 S*LE      ANK1GE CrMC*LI.-                        / FNE. - I CE.TGALG Y~E C0NrEAAC-ATESTTANK1 SPENTFUEL COE-MR Section 1 - Page 2
 
Oconee Nuclear Station                                                      January, 2009 Offsite Dose Calculation Manual (ODCM)                                      Revision 49 1.0.2    GASEOUS RADWASTE PROCESSING The purpose of the gaseous waste disposal system is to:
(1) Maintain a non-oxidizing cover gas of nitrogen in tanks and equipment that contain potentially radioactive gas; (2) Hold up radioactive gas for decay; and (3) Release gases (radioactive and non-radioactive) to the atmosphere under controlled conditions.
During power operation of the facilities, radioactive materials released to the atmosphere in gaseous effluents include low concentrations of fission product noble gases (krypton and xenon), halogens (mostly iodines), tritium contained in water vapor, and particulate material including both fission products and activated corrosion products.
The primary source of gaseous radioactive wastes is from the degassing of the primary coolant during letdown of the cooling water into various holding tanks. Additional sources of gaseous waste activity include the auxiliary building exhaust, spent fuel area exhaust, the discharge from the steam jet air ejectors, and purging and venting of the reactor containment building.
All components that can contain potentially radioactive gases are vented to a vent header.
The vent gases are subsequently drawn from this header by one of four waste gas compressors or a waste gas exhauster. The waste gas compressor discharges through a waste gas separator to one of seven waste gas tanks. The waste gas tanks and the waste gas exhauster discharge to the unit vent after passing through a filter bank consisting of a prefilter, an absolute filter, and a charcoal filter.
Radioactive gases may be released inside the reactor containment building when components of the primary system are opened to the building atmosphere for operational, reasons or where minor leaks occur in the primary system. Prior to access, the reactor containment atmosphere will be monitored for radioactivity and, when necessary, purged through prefilters, high-efficiency particulate air (HEPA) filters, and charcoal filters, and released to the atmosphere through the unit vent. The purge equipment is sized for a flow rate of 50,000 cfm providing approximately 1.5 air changes per hour in the reactor building. Units 1, 2, and 3 have a separate vent stack which services each unit.
Figure 1.0-2 is a schematic representation of the gaseous radwaste system at Oconee.
Section I - Page 3
 
Oconee Nuclear Station                                        January, 2009 Offsite Dose Calculation Manual (ODCM)                        Revision 49 Figure 1.0-2 Oconee Nuclear Station Gaseous Radwaste System Page 1 of 4 VENT HT 200 FT Section 1 - Page 4
 
Oconee Nuclear Station                                                                                          January, 2009 Offsite Dose Calculation Manual (ODCM)                                                                          Revision 49 Figure 1.0-2 Oconee Nuclear Station Gaseous Radwaste System Page 2 of 4 UNIT VENT I2-RIASE UNIT 2 HEIGHT 200 FT PENETRATION ROOM VENTILATION SYSTEM                      ~A-32 UNIT 2 REACTOR BUILDING                      UNIT 2  E C O    UL  N  R F LT R    I T R      D O B R UNIT I & 2 SPENT FUEL -    POOL AREA                  RA CONDENSER FOR EJECTOR STEAM SYSTEM                                    GAS FROM STEAM GENERATOR TUBE LEAK      ,
AI R EJCO HOTWELL-*
DECONTAMINATION AND FUME HOODS AUXILIARY BUILDING VENT MULTIPLE AUXILIARY                                                                                STA-1 N GROUND STATIO BUILDING LOCATIONS                                                                                      L EVEL L
Section I- Page 5
 
Oconee Nuclear Station                                            January, 2009 Offsite Dose Calculation Manual (ODCM)                            Revision 49 Figure 1.0-2 Oconee Nuclear Station Gaseous Radwaste System Page 3 of 4 VENT IT 200 FT Section 1- Page 6
 
Oconee Nuclear Station                                                                                        January, 2009 Offsite Dose Calculation Manual (ODCM)                                                                        Revision 49 Figure 1.0-2 Oconee Nuclear Station Gaseous Radwaste System Page 4 of 4 HOT MACHINE SHOP VENTILATIONSYSTEM      PRFLE              EP                      OAIE            EXHAUST
                                                                      *                [ I~o*
PARTICULATEsAML&
WELDING HOOD      - RFITR              HP INTERIM RADWASTEFACILITY VENTILATION SYSTEM                                                                  EXAT RADWASTE BUILDING LOW            EXHAUST VENTILATION SYSTEM FLOW            EXHAUST TANK VENTS & LAB HOODS    HEPH HNO CARBONFILTEH HEPH HNO                      PRTICUOI TE &          4RIA-45 CARBON FILTER                  IODINE SMPLER VR SYSTEM OFF-GAS HEPH FIL0T CHRBON HLA ER              .EXHHUST VENTILATION SYSTEM                                                  FO Section 1.- Page 7
 
Oconee Nuclear Station                                                      January, 2009 Offsite Dose Calculation Manual (ODCM)                                        Revision 49 2.0 RELEASE RATE CALCULATIONS 2.0.1 LIQUID RELEASE RATE LIMIT CALCULATIONS There are two liquid radwaste discharge points to the environment at Oconee; (1) the liquid radwaste effluent line to the Keowee Hydroelectric Unit Tailrace, and (2) the #3 Chemical Treatment Pond effluent line to the Keowee River (See Figure 2.0-1).
2.0.1.1 LIQUID RADWASTE EFFLUENT LINE RELEASE RATE LIMIT CALCULATION Liquid releases to the Keowee Hydroelectric Unit Tailrace normally contain the radioactive releases from the site including effluents from the Waste Monitor Tanks, Recycle Monitor Tanks, and Decant Monitor Tank.. The Keowee Tailrace discharge point can also contain Turbine Building Sump Monitor Tank (TBSMT) releases, however TBSMT effluent normally contains very low (if any) activity, and, therefore is transferred to the #3 Chemical Treatment Pond prior to release. Dilution flow for the liquid radwaste effluent line is provided by the Keowee Hydroelectric Unit and the Keowee Hydro Fire Protection liquid waste release mixing line. For purposes of the release rate calculation, Keowee hydro dilution flow is assumed to be a minimum leakage flow of 38 cfs, and a maximum flow of 6600 cfs based on one hydro unit operating at 50% power. The Keowee Hydro Fire Protection liquid waste release mixing line provides an additional 38 cfs dilution flow. Since Keowee Hydro typically releases only a small percentage of time during the year, 76 cfs (38 cfs leakage + 38 cfs mixing line) is normally assumed for dilution flow when performing liquid release rate calculations.
To comply with Technical Specifications and Selected Licensee Commitments, and to assure that the concentration of radioactive liquid effluents released from the site to the unrestricted area is limited to 10 times the effluent concentrations (ECs) of 10CFR20, Appendix B, Table 2, Column 2, and 2.OE-04 [tCi/ml for dissolved and entrained noble gases, the following release rate limit calculation shall be performed for liquid releases to the Keowee Hydro Tailrace via the liquid radwaste effluent line:
f< F    -  (DF-1) Condition: DF> 1.0                        Equation 2.1 where:
f      = the undiluted effluent flow, in gpm.
F      = the dilution flow available, in gpm.
      = normally 3.41E+04 gpm (76 cfs, based on a leakage rate of 38 cfs (19 cfs per.
Keowee Hydro unit), plus the Keowee Hydro Fire Protection liquid waste release Section 2 - Page 1
 
Oconee Nuclear Station                                                          January, 2009 Offsite Dose Calculation Manual (ODCM)                                            Revision 49 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.
DF=(10                  x EC,)                                  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.
a        the most restrictive recirculation factor at equilibrium, (dimensionless). The recirculation factor accounts for the fraction of discharged water reused by the station. This value equals 1.0 since discharged liquid effluent is not reused at Oconee.
Ci    = the concentration of radionuclide, 'i', in the undiluted liquid effluent, in &#xfd;tCi/ml.
ECi = the concentration of radionuclide, 'i', from IOCFR20, Appendix B, Table 2, Column 2, in itCi/ml. Note: if radionuclide, 'i', is a dissolved noble gas, then ECi
          = 2.OOE-05 pCi/ml.
Once the maximum release rate, f, is calculated the value is multiplied by 0.8 for additional conservatism.
2.0.1.2 #3 CHEMICAL TREATMENT POND EFFLUENT LINE DISCHARGE The #3 Chemical Treatment Pond (CTP) effluent line is the release point for station effluents that are normally considered to be non-radioactive; that is, the pond's effluent will not normally contain measurable activity above background with the exception of very low tritium activity. Tritium releases from the #3 CTP typically account for much less than 1% of the station total tritium release. It is assumed that no activity is present in the effluent until indicated by radiation monitoring measurements on the pond's inputs and/or by periodic analyses of the composite sample collected at the pond's discharge point. Inputs to this pond include the station's yard drain system, the decant water from the Powdex system, and the discharge from the Turbine Building Sump/TBSMT system whose contents have been determined to be below background. Inputs that have radiation Section 2 - Page 2
 
Oconee Nuclear Station                                                      January, 2009 Offsite Dose Calculation Manual (ODCM)                                        Revision 49 monitors associated with them will be set to assure that Selected Licensee Commitment 16.11-1 will not be exceeded. #3 CTP is a continuous release path that discharges to the Keowee River (see Figure 2.0-1).
The #3 CTP may also be the discharge path for large volumes of slightly contaminated water following a primary-to-secondary leak so long as administrative procedures are implemented to assure that release rate calculations similar to that used in Section 2.0.1.1 are performed, that all detectable radionuclides will be accounted for, and that no station limits will be exceeded.
Section 2 - Page 3
 
Oconee Nuclear Station                                                                January, 2009 Offsite Dose Calculation Manual (ODCM)                                                  Revision 49 Figure 2.0-1 Liquid Radwaste Discharge Locations Lake Keowee Visitors ./.                                        Keowee /  n7 bente&'                                              Dam Discharge            . KeoweeTa*-*r\"
Release'Point Oconee Nuclear      -
(iU~
Section 2 - Page 4
 
Oconee Nuclear Station                                                        January, 2009 Offsite Dose Calculation Manual (ODCM)                                        Revision 49 2.0.2    GASEOUS RELEASE RATE LIMIT CALCULATIONS The three unit vents are the primary gaseous radioactive release points at Oconee. The unit vents are the semi-elevated release points for waste gas decay tanks, containment building purges, auxiliary building ventilation, spent fuel pool ventilation, and the condenser air ejector (see Figure 1.0-2, pages 1, 2, and 3). Each unit vent contains multi-range radiation monitors (RIAs) and flow rate measuring instrumentation.
There are three other separate gaseous effluent release points at Oconee; the Hot Machine Shop, Interim Radwaste Building and Radwaste Facility that are normally considered non-radioactive; that is, it is possible but unlikely that the effluent will contain measurable activity above background. Each of these release points are considered ground-level, and each has an effluent sampler and flow monitoring device (see Figure 1.0-2, page 4). In addition, the Interim Radwaste Building and Radwaste Facility have a RIA.
2.0.2.1 UNIT VENT DISCHARGE RELEASE RATE LIMIT CALCULATION In order to comply with Technical Specifications and Selected Licensee Commitments and to assure that the dose rate, at any time, at or beyond the site boundary due to radioactive materials released in gaseous effluents from the site is limited to: < 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:
X(KXZxQ        < 500mrem/yr                        Equation 2.3 Skin:
X((Li+,I .IM)xZ-I-xQi            < 3000 mrem/yr            Equation 2.4 Section 2 - Page 5
 
Oconee Nuclear Station                                                              January, 2009 Offsite Dose Calculation Manual (ODCM)                                              Revision 49
: b. Radioiodines, Particulates, and Others Inhalation, Ingestion and Ground Organ Pathways:
I  Z(P~pi x W x Qi x Ei) < 1500mrem/yr p    I To include both the food and ground organ dose and the inhalation organ dose the equation can be expanded to:
      -({(Pop:)foodgr Q            X  WD  0 + (Pop, ).hat X WX/0} x Q x Ei) < 1500mrem/yr
: p. i Equation 2.5 where:
Ki      = the total body dose factor due to gamma emissions for each identified noble gas radionuclide, 'i', in mrem/yr per ptCi/m 3 (See Appendix A).
L,      =    the skin dose factor due to beta emissions for each identified noble gas radionuclide, 'i', in mrem/yr per pCi/mn      3 (See Appendix A).
M        =    the air dose factor due to gamma emissions for each identified noble gas radionuclide, 'i', in mrad/yr per ptCi/m 3 (See Appendix A).
Pop,        the dose parameter for radionuclides other than noble gases for the inhalation pathway, in mrem/yr per p[Ci/mn3 and for the food and ground plane pathways in (i 2 x (mrem/yr per [tCi/sec)) for organ, 'o', and radionuclide, 'i', (See Appendix B for the pathway specific dose commitment factors). Note: NUREG-1301, page 75, specifies use of the Child age group, Inhalation pathway, for the Popi values.
X/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:
Section 2 - Page 6
 
Oconee Nuclear Station                                                            January, 2009 Offsite Dose Calculation Manual (ODCM)                                            Revision 49 Wz/Qse = 1.672E-6 sec/mr3, 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.
Wz/QgI  =  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    =  the filter removal factor for radionuclide, 'i', e.g., for 99% removal E, = 0.01.
For iodine removal by charcoal adsorbers E1 = 0.1.
For particulate removal by HEPA filters E, = 0.01.
Qj    =the release rate of radionuclide, 'i', in gaseous effluent from all release points at the site, in ptCi/sec.
Q= kiCf + k2 = 4.72E + 02 x Cf                                Equation 2.6 where:
Ci = the concentration of radionuclide, 'i', in undiluted gaseous effluent, in ptCi/ml.
f    =  the undiluted effluent flow, in ft3/min.
k1  =  conversion factor, 2.83E+04 cc/ft3 .
k    =  conversion factor, 6.OE+01 sec/min.
Substituting the expression for Q1 in Equation 2.6 into Equations 2.3, 2.4, and 2.5, and solving for the flow rate, 'f, in each equation'gives:
Noble Gases - Total Body Maximum Release Rate:
500 fib<
4.72E+02 x X/Q x          (Ki x Ct)
Section 2 - Page 7
 
Oconee Nuclear Station                                                                January, 2009 Offsite Dose Calculation Manual (ODCM)                                                Revision 49 Noble Gases - Skin Maximum Release Rate:
fk <3000 4.72E+02 x X                - [(L,+ 1.1M) x Ci]
Radioiodines, Particulates, and Others - Organ Maximum Release Rate:
1500 4.72E+02 x              "({(Pop,)foo-dg,  X'WD'Q      +  (Popi)imh.1 X Wx/Q Ix  x C,)
p    i fb, fik,  and for, are calculated for each batch prior to release. The most limiting gaseous release rate is used to assure that no instantaneous dose rate limit is exceeded.
Once the maximum release rate, f                is calculated the value is multiplied by 0.8 for additional conservatism.
Section 2 - Page 8
 
Oconee Nuclear Station                                                      January, 2009 Offsite Dose Calculation Manual (ODCM)                                      Revision 49 Derivations of Iodine, Particulate, and H-3 Dose Commitment Factors (Popi) 0 Inhalation Pathway - Child Age Group Pi      = K'(BR )(DFA o)
Formula: from NUREG-0133, page 25.
Where:
Popi  Dose commitment factor for Child age group, organ o, nuclide i, for the inhalation pathway (mrem/yr per *tCi/m 3). (See Appendix B for the pathway specific dose commitment factors).
K' Units conversion factor pCi/tCi (106).
BR Breathing rate for the Child age group (m3 /yr, from Regulatory Guide 1.109):
Child - 3700 DFAoi Organ inhalation dose conversion factor for Child age group, organ o, 1 nuclide i, (mrem/pCi), from Table E-9 of Regulatory Guide 1.109.
Section 2 - Page 9
 
Oconee Nuclear Station                                                        January, 2009 Offsite Dose Calculation Manual (ODCM)                                        Revision 49 3.0 SETPOINT CALCULATIONS 3.0.1 LIQUID RADIATION MONITOR SETPOINT CALCULATIONS As shown on Figure 1.0-1, RIA-33 is the controlling radiation monitor for liquid batch releases at Oconee. Once the liquid release rate parameters have been established radiation monitor setpoints shall be calculated to assure that the concentration of radioactive liquid effluents released from the site to the unrestricted area is limited to ten times the effluent concentrations (ECs) of 10CFR20, Appendix B, Table 2, Column 2, and 2.OE-04 p.Ci/ml for dissolved and entrained noble gases., By substituting the dilution factor (DF) from Equation 2.2 into Equation 2.1, solving for the undiluted liquid effluent concentration, Ci, and accounting for the monitor background reading, the liquid radiation monitor setpoint can be readily obtained by multiplying Ci by the radiation monitor correlation factor, CFi, as follows:
EC,)
Ci-< (F + f) x (10 x                                      Equation 3.1 (Cxf SP <- Z (c1 x CF,) + bkg Equation 3.2 where:
Ci    = the maximum allowable concentration of radionuclide, 'i', in the undiluted liquid effluent, in ltCi/ml.
SP    = radiation monitor setpoint, in cpm.
CF, = radiation monitor correlation factor for radionuclide, 'i', in cpm/tCi/ml, e.g.,
8.OOE+07 cpm/&#xfd;tCi/ml (Cs-137) for RIA-33.
bkg = background reading for the radiation monitor, in cpm.
All other parameters were previously defined.
Using conservative or "worst-case" parameters in Equation 3.1 and Equation 3.2 can provide a liquid radiation monitor setpoint that does not need to be revised for every release if activity is low enough to allow for this type of operation such as with continuous releases from the #3 CTP release point. However, for batch releases, e.g.,
waste monitor tanks, through the liquid radwaste effluent line to the Keowee hydro Section 3 - Page 1
 
Oconee Nuclear Station "                                                      January, 2009 Offsite Dose Calculation Manual (ODCM)                                        Revision 49 tailrace the RIA-33 radiation monitor setpoints are calculated based on the actual expected activity in the release as follows:
First the "Correlation Concentration" (C CONC) is calculated' C CONC      =      (CG x EQ,)
where:
C1        =    Undiluted liquid effluent concentration for each isotope, excluding tritium, ltCi/mnl.
EQj        =  RIA-33 Cs-137 equivalence factor for each isotope, excluding tritium, to that of Cs-137 due to different gamma energies and abundance. This factor includes a 4-hour decay time due to the average time between; sample and release. (See Table 3.0-1)
Next the RIA-33 setpoints are determined as follows:
If C CONC is > 9.OE-6 jtCi/ml then three setpoint values are calculated.!! The actual "expected" count rate for the release is defined as the "Midpoint of Expected Range".
The "Alert" setpoint is defined as 1.5 times the expected counts from activity in the liquid effluent plus background. If the "Alert" setpoint is exceeded, but there is no upward trend, the release will be allowed to continue. If RIA-33 continues to trend Iupward then the release will be manually terminated. The "Upper Limit of Expected Range" is defined as 3 times the expected counts from activity in the liquid effluent plus background. The "Upper Limit of Expected Range" is called the "Trip" setpoint. If the "Trip" setpoint is exceeded the release will be automatically terminated. The "Lower Limit of Expected Range" is defined as 3 times lower than the expected counts from activity in the liquid effluent plus background. The "Lower Limit of Expected Range" provides assurance that the correct liquid effluent is being released. If the RIA-33 count rate does not increase to at least the "Lower Limit of the Expected Range" then the release will be terminated, and a new sample analysis will be performed. The four RIA-33 setpoints are calculated as follows:
Lower Limit of Expected Range = C CONC x (8.00E7/3) 6pm/(QiCi/ml) +
RIA-33 BKG Midpoint of Expected Range            = C CONC x 8.00E7 cpm/(iCi/ml) +
RIA-33 BKG Alert Setpoint                        = C CONC x (8.OOE7x 1.5) cpm/(laCi/ml) +
RIA-33 BKG Upper Limit of Expected Range = C CONC x (8.00E7x3),cpm/(j.Ci/ml) +
(Trip Setpoint)                        RIA-33 BKG Section 3 - Page 2
 
Oconee Nuclear Station                                                      January, 2009 Offsite Dose Calculation Manual (ODCM)                                      Revision 49 If C CONC is _ 9.OE-6 jtCi/mi then the RIA-33 setpoint is 2.16E3 cpm (9.OE-6 x 8.00E7 x 3) plus background (BKG) as the "Upper Limit of Expected Range". This setpoint is used for low activity releases, and is based on limiting the concentration in the effluent to 10 times the IOCFR20 EC of Cs-134 which has the lowest effluent concentration value (9.OE-7 tCi/mi) for any detectable radionuclide in the effluent. Similarly, the RIA-33 "Alert" setpoint for low activity releases is 1.08E3 cpm (9.OE-6 x 8.00E7 x 1.5) plus background (BKG).
Section 3 - Page 3
 
Oconee Nuclear Station                                                    January, 2009 Offsite Dose Calculation Manual (ODCM)                                    Revision 49 Table 3.0-1 RIA-33 Cs-137 Equivalents isotope      Equivalence          Isotope        Equivalence    Isotope Equivalence Factor                              Factor                Factor Be-7              0.1462        Mo-99                  0.2668  La-141        0.0155 F-18              0.5788        Tc-99m                  0.00  La-142        0.2942 Na-24              0.8519        Tc-101                  0.00  Ce-141        0.00 CI-38              0.0090        Ru-103                1.3368  Ce-143        0.7826 K-40              0.1094        Ru-105                0.8783  Ce-144        0.0273 Cr-51              0.1438        Ru-106                0.4429  1-130        3.3095 Mn-54              1.0617      Ag-108m                3.4473  1-131        1.4051 Mn-56              0.4992        Ag-110m                3.5179  1-132        1.0259 Fe-59              1.0556      Cd-ll5                0.5201  1-133        1.1857 Co-57              0.0022        Cd-ll5m                0.0235  1-134        0.1388 Co-58              1.4735      In-115m                0.3631  1-135        0.9374 Co-60              2.0495        Sb-122                0.9218  Ar-41        0.2229 Cu-64              0.3954.      Sb-124                2.1617  Kr-85        0.0059 Ni-65              0.1591        Sb-125                1.1308  Kr-85m        0.4280 Zn-65              0.5584        Sb-126                5.1762  Kr-87        0.1213 Zn-69m              1.1391        Sn-113                0.9971  Kr-88        0.5278 Se-75              1.3092        Sn-123                0.0066  Kr-89          0.00 Br-80m            0.0860        Sn-126                0.00  Xe-131m      0.0167 Br-82              3.4691        Te-125m                0.00  X6-133        0.0006 Br-83              0.0059        Te-127                0.0134  Xe-133m      0.1172 Br-84              0.0053        Te-127m                0.0001  Xe-135        0.8564 Br-85                0.00        Te-129                0.0138  Xe-135m        0.00 Rb-86              0.0894        Te-129m                0.0507  Xe-137          0.00 Rb-88                0.00        Te-131                0.0008  Xe-138          0.00 Rb-89                0.00        Te-131m                1.8463  Nd-147        0.2619 Sr-89              0.0002        Te-132                0.9766  Hf-181        1.4209 Sr-91              0.6460        Te-134                0.0408  W-187        0.8027 Sr-92              0.3900        Cs-134                2.5804  TI-208          0.00 Y-91                0.0031        Cs-136                3.1916  Bi-212        0.0144 Y-91m              0.0439        Cs-137                  1.00  Bi-214        0.0003 Y-92                0.1334        Cs-138                0.0120  Pb-212        0.4497 Y-93                0.1091      Ba-133                1.3648  Pb-214        0.0020 Zr-95              1.0909        Ba-139                0.0203  Ra-226        0.0320 Zr-97              1.1210      Ba-140                0.5307  Ac-228        0.8261 Nb-95              1.0821        Ba-141                0.0002  Th-228        0.0038 Nb-95m              0.2919        Ba-142                  0.00  Np-239        0.3996 Nb-97              0.1164        La-140                2.3237 1_1__
Section 3 - Page 4
 
Oconee Nuclear Station                                                      January, 2009 Offsite Dose Calculation Manual (ODCM)                                      Revision 49 3.0.2      GASEOUS RADIATION MONITOR SETPOINT CALCULATIONS The unit vent radiation monitor setpoints are established at the Oconee Nuclear Station to help ensure that gaseous release rate limits are not exceeded. For some release pathways in which a specific RIA exists, the setpoints also help to ensure that the effluent being released is the same concentration as indicated by manual samples, e.g. effluent from waste gas decay tanks, thereby reducing the likelihood of releasing the wrong tank. For instances in which the RIA which normally controls the release is not operable, or is "out of service", independent manual samples (IMS) are collected and the noble gas constituents from both samples are compared to help ensure that the intended' "batch" is being released. For certain low potential release types, e.g. Integrated Leak Rate Tests, no RIA exists to ensure that release rate limits are not exceeded or to ensure that the effluent being released is the "expected" concentration. For such pathways, independent manual samples are required to be collected and noble gas constituents compared prior to release. The following list defines the controlling RIA for the various gaseous effluent release types at Oconee:
Pathway                                            Controlling RIA Unit  1 "A" Waste    Gas Decay  Tank            1&2 RIA 37/38 Unit  I "B" Waste    Gas Decay  Tank            l&2 RIA 37/38 Unit  1 "C" Waste    Gas Decay  Tank            1&2 RIA 37/38 Unit  I "D" Waste    Gas Decay  Tank            l&2 RIA 37/38 Unit  3 "A" Waste    Gas Decay  Tank            3 RIA 37/38 Unit  3 "B" Waste    Gas Decay  Tank            3 RIA 37/38 Unit  3 "C" Waste    Gas Decay  Tank            3 RIA 37/38 Unit 1 Reactor Building Purge                      1 RIA 45/46 Unit 2 Reactor Building Purge                      2 RIA 45/46 Unit 3 Reactor Building Purge                      3 RIA 45/46 Unit  1 Depressurization                          IMS 1 RIA 45/46 Alarm Only Unit  2 Depressurization                          IMS 2 RIA 45/46 Alarm Only Unit  3 Depressurization                          IMS 3 RIA 45/46 Alarm Only Unit  1 Hydrogen Recombiner                        IMS 1 RIA 45/46 Alarm Only Unit  2 Hydrogen Recombiner                        IMS 2 RIA 45/46 Alarm Only Unit  3 Hydrogen Recombiner                        IMS 3 RIA 45/46 Alarm Only Unit  1 Integrated Leak Rate Test                  IMS Unit  2 Integrated Leak Rate Test                  IMS Unit  3 Integrated Leak Rate Test                  IMS The following sections describe the methods by which setpoints are established. In general, gaseous radiation monitors are calibrated to Xe-133, and for continuous release points, e.g., the three unit vents, are preset at a maximum value based on the 500 mrem/year total body gaseous release rate limit according to the following methodology:
Section 3 - Page 5
 
Oconee Nuclear Station                                                            January, 2009 Offsite Dose Calculation Manual (ODCM)                                            Revision 49 Note: when applied to the individual release points the 500 mrem/year site dose rate value is apportioned 30% to each Unit Vent (RIA-45 and RIA-46) semi-elevated release point.
The remaining 10% is allocated to the three ground-level release points, the Hot Machine Shop (no monitor), Interim Radwaste Building (RIA-53) and Radwaste Facility (4RIA-45) that are normally considered non-radioactive. Recall from Section 2.0.2.1 the following equation:
KXe-133  X        Q  X Qxe-133 <  500 mrem/yr Solve for QXe-133:
S    500 Qxe - 133 <            50 Kx'e-133 )x,//
Equation 3.4 From Equation 2.6:
Qxe -133  =  4.72E + 02 x CXe - 133 x f                        Equation 3.5 Substitute Equation 3.5 into Equation 3.4:
4.72E + 02          Cx- 133 X f <          500 Kne-133    z/Q "X
Solve for CXe-133:
500 CXe - 133 <
4.72E+02 x f x Kxe-133            X /Q CXe - 133 SP = -                + bkg                                    Equation 3.6 CF where:
KXe-133      =    2.94E+02, the total body dose factor due to gamma emissions for Xe-133, in mrem/year per jtCi/m 3 (See Appendix A).
X/Q            =    the highest calculated semi-elevated annual average dispersion parameter for any area at or beyond the site boundary in sec/m 3. For Oconee this value is 1.672E-6 sec/m 3. The location is the SW sector at 1.0 mile.
Qxe-133              Xe-133 equivalent release rate limit for the noble gastotal body dose pathway, in /tCi/sec.
4.72E+02 = Conversion factor, (cc/ft3)/(sec/min).
Section 3 - Page 6
 
Oconee Nuclear Station                                                            January, 2009 Offsite Dose Calculation Manual (ODCM)                                            Revision 49 CXe-133        =  the maximum allowable Xe-133 equivalent concentration in the gaseous effluent,, in &#xfd;tCi/cc.
f                =  the gaseous effluent flow from the tank, building, or vent, in ft3/min.
SP                  radiation monitor setpoint, in cpm.
CF              =    the Xe-133 equivalent monitor correlation factor, in VtCi/cc/cpm.
bkg              =  the radiation monitor background reading, in cpm.
Equation 3.6 provides the methodology to calculate the maximum setpoint for releases from the Unit Vents (RIA-45 and RIA-46), Radwaste Facility (4RIA-45), and Interim Radwaste Building (RIA-53).
3.0.2.1 UNIT VENTS SETPOINTS (RIA-45 and RIA-46)
Reactor Building purges from all 3 units are released via the applicable unit vent, either Unit 1, Unit 2, or Unit 3. Each of the 3 unit vents are monitored by a normal/low range RIA (RIA-45) and a high range RIA (RIA-46). In addition to Reactor Building purges, all other releases from the main plant, including the Auxiliary Building ventilation, Waste Gas Decay Tanks, and the Spent Fuel 'Pools are monitored by each unit's RIA-45 and RIA-46. However, 'RIA-45 and RIA-46 on each, unit vent have release termination authority only for Reactor Building purge releases. Each unit's RIA-45 and RIA-46 will, when operable, activate Control Room alarms if the unit vent concentration exceeds the monitor's setpoint value. The setpoints for each unit's RIA-45 and RIA-46 are established on a "worst case" basis, With the upper bound' normally set at 30 percent of the station release rate limit for noblegases in Xe-133 equivalent concentration as follows:
Recall Equation 3.6:
CXe - 133 SP -                  + bkg CF where:
500 CXe - 133 <
4.72E+02 x f          x  KXe-133 X.X RA  -45ui    vent =                                          150 4.72E + 02 x 6.5E + 04 x 2.94E + 02 x 1.672E- 06 x 7.09E- 08 R/A - 45u,, vent        1.40E + 05 cpm + bkg Section 3 - Page 7
 
Oconee Nuclear Station                                                        January, 2009 OffsiteDose Calculation Manual (ODCM)                                        Revision 49 where:
150.        =    30% of the 500 mrem/yr total body release rate limit.
6.5E+04    =  Unit Vent flow rate with Reactor Building Purge off, ft3/min.
1.672E-06 = Highest Semi-Elevated release point dispersion; factor, sec/m3n 7.09E-08    =  RIA-45 Correlation Factor, &#xfd;tCi/ml/cpm.
All other factors were previously defined.
RIA -  6ui vent=
150            "
4.72E+02 x 6.5E+04 x 2.94E+02 x 1.672E-06 x 3.1'7E-04 RIA -46,tv._t        31 cpm + bkg where:
3.17E-04    =    RIA-46 Correlation Factor, laCi/ml/cpm.
All other factors were previously defined.
For instances in which the Reactor Building Purge is on, the setpoint is multiplied by 0.65 (65,000 cfm/ (65,000 cfm + 35,000 cfm purge flow)).
3.0.2.2 RADWASTE FACILITY SETPOINTS (4RIA-45) 4R/    45 =25    4-4.72E+02 x 1.297E+05 x 2.94E+02 x 7.308E-06 4R/A - 45        1.90E - 041 tCi/ml where:
25            =    5% of the 500 mrem/yr total body release rate limit.
1.297E+05    =    Radwaste Facility Vent flow rate, ft3/min.
3 7.308E-06    =    Highest Ground-Level release point dispersion factor, sec/r .
All other factors were previously defined.
4RIA-45 reads in units of concentration, iiCi/ml.          '
Section 3 - Page 8
 
Oconee Nuclear Station                                                      January, 2009 Offsite Dose Calculation Manual (ODCM)                                      Revision 49 3.0.2.3 INTERIM RADWASTE BUILDING SETPOINTS (RI*A-53) 25 RIA-53-=
4.72E + 02 x 1.5E + 04 x 2.94E + 02 x 7.308E - 06 x 3.4E - 08 RIA - 53    4.8E + 04 cpm + bkg where:
25            =  5% of the 500 mrem/yr total body release rate limit.
1.5E+04      =  Interim Radwaste Building Vent flow rate, ft3/min.
7.308E-06      = Highest Ground-Level release point dispersion factor, sec/m 3.
3.4E-08        = RIA-53 Correlation Factor, gICi/ml/cpm.
All other factors were previously defined.
In addition to the maximum setpoints discussed previously, Oconee.uses "Alert" setpoints that are based on 10% of the reporting requirement from 10CFR50.73(a)(2)(viii)(A).
Each unit vent Alert setpoint is based on 60% of a Xe-133 Effluent Concentration (EC) value of 5.OE-07 &#xfd;tCi/ml at the site boundary. The Interim Radwaste Building and Radwaste Facility are each set at 10% of the Xe-133 EC. The method usedto calculate the Alert setpoints is similar to that used to calculate the maximum setpoints except that the limit is based on concentration rather than. dose rate. The Alert setpoints are approximately 42% of the maximum setpoints.
3.0.2.4 WASTE GAS DECAY TANK SETPOINTS (RIA-37 and RIA-38)
For batch releases where the effluent can contain activity significantly above background, e.g., Waste Gas Decay Tank (WGDT),'two additional monitors, RIA-37 and RIA-38 are used to establish setpoints for each WGDT batch released. RIA-37 is the normal/low range noble gas monitor, and RIA-38 is the high range noble gas monitor. The following setpoint methodology is used:
CXe - 13 =    (c x Eq,)
CXe - 133 Expected Cpm =                  + bkg CFXe - 133 RIA - 37 and RIA - 38 Setpoint -      Cx&#xfd; - 133  x 1.5      Equation 3.7 SCFXe- 133 Section 3 - Page 9
 
Oconee Nuclear Station                                                      January, 2009 Offsite Dose Calculation Manual (ODCM)                                      Revision 49 where:
CXe-133  =  Xe-133 equivalent concentration of the WGDT to be released, in itCi/ml.
Eqi        =  Xe-133 equivalence factor for each noble gas isotope, excluding tritium, to that of Xe-133 due to different beta energies and abundance.
(See Table 3.0-2).
CFxe- 33 .= The expected RIA response to a given Xe-133 equivalent concentration, in
[tCi/ml/cpm. 1RIA-37.= 4.20E-08 &#xfd;tCi/ml/cpm, 3RIA-37 = 4.20E-08 ptCi/ml/cpm, 1RIA-38 and 3RIA-38 = 1.34E-03 ptCi/ml/cpm.
1.5        =  An adjustment factor to account for expected minor variations in effluent concentration and RIA background.
bkg        =  The radiation monitor background reading, in cpm.
When the release pathway is from any Unit I WGDT (A-D); and the Xe-13,3 equivalent concentration is less than 2.8E tCi/ml, the 1&2 RIA-38. setpoint is established at 313 cpm, and the 1&2 RIA-37 setpoint is calculated using Equation 3.7.
When the release pathway is from any Unit 1 WGDT (A-D), and the Xe-133 equivalent concentration is greater than 2.8E-01 j&#xfd;tCi/ml, the 1&2 RIA-37 setpoint is established as offscale high, and the 1&2 RIA-38 setpoint is calculated using Equation 3.7.
When the release pathway is from any. Unit 3 WGDT (A-C), and the Xe-133 equivalent concentration is less than 2.8E-01 jtCi/ml, the 3 RIA-38 setpoint is established at 313 cpm, and the 3 RIA-37 setpoint is calculated using Equation 3.7..
When the release pathway is from any Unit 3 WGDT (A-C), and the Xe-133 equivalent concentration is greater than 2.8E-01 lICi/ml, the 3 RIA-37 setpoint is established as offscale high, and the 3 RIA-38 setpoint is calculated using Equation 3.7.
When there are no noble gases present in the WGDT sample, the RIA-37 setpoint is set to five times (5X) the RIA-37 background reading.
Section 3 -Page 10
 
Oconee Nuclear Station                                              January, 2009 Offsite Dose Calculation Manual (ODCM)                              Revision 49 Table 3.0-2 Xe-133 Equivalents Isotope            Equivalence Factr" Kr-83m                          0 Kr-85m                        2.48 Kr-85                        2.56 Kr-87                        2.93 Kr-88                        2.78 Kr-89                        2.93 Kr-90                        2.93 Xe-131m                      1.69 Xe-133m                      1.99 Xe-133                        1.0 Xe-135m                      0.83 Xe-135                        2.63 Xe-137                        2.93 Xe-138                        2.93 Ar-41                        2.82 C-11                        2.70 Section 3 - Page 11
 
Oconee Nuclear Station                                                    January, 2009 Offsite Dose Calculation Manual (ODCM)                                      Revision 49 4.0 EFFLUENT DOSE MODELS The effluent dose models used to show compliance with I OCFR50, Appendix I ALARA design objectives, 40CFR190 fuel cycle dose limits, and the dose values given in station SLCs are based on the methodology given in NUREG-0 133 and Regulatory Guide 1.109.
Dose contributions to the maximum individual shall be calculated at least every 31 days, quarterly, and annually using the RETDAS computer code which implements the ODCM methodology. RETDAS, Radioactive Effluent Tracking and Dose Assessment Software, is a database application designed by Canberra Industries, Inc. to automate many of the tasks required in the administration of effluent releases at Oconee. RETDAS performs normal operation effluent dose assessment using NUREG-0133 and Regulatory Guide 1.109 methodology.
Station long-term historical and dose projection calculations are performed- periodically to determine the station's status with respect to meeting annual ALARA goals specified in the Oconee SLCs. Such calculations are used to verify that adequate margin remains during a report period to allow normal station and radwaste system operation, including anticipated operational occurrences, for the remainder of the report period without exceeding applicable goals. Station 31-day dose projections that are used to assess the need to reduce effluent releases with the Gaseous Waste (GW) or Liquid Waste (LW) systems as required in the Oconee SLCs are estimated by the previous month's calculated dose results.
Fuel cycle dose calculations shall be performed annually or as required by special reports.
Dose contributions shall be calculated using the RETDAS computer program.
4.0.1 LIQUID EFFLUENT DOSE MODEL FOR THE MAXIMUM EXPOSED INDIVIDUAL Of the possible exposure pathways in the aquatic environment, only three contribute significantly to the total dose; these pathways are ingestion of potable water and aquatic foods, and direct exposure from radioactivity deposited on the shoreline. The dose contribution from these pathways for measured quantities of radioactive materials identified in liquid effluents released to unrestricted areas. shall be calculated for the maximum exposed individual in each age group using the methodology provided in this section.
Liquid waste processed by the LW system can be released to the environment at Oconee from two liquid discharge points; (1) directly to the Keowee Tailrace through RIA-33 and (2) to the Chemical Treatment Pond #3 discharge point into the Keowee River (See Figure 2.0-1). Liquid dose calculations for the maximum exposed individual are performed and documented in the Annual Effluent Release Report for both locations using the applicable activity release and dilution data for each liquid effluent release point. The primary liquid effluent discharge point for Oconee is to the Keowee Tailrace Section 4 - Page 1


====4.0.3 Direct====
Oconee Nuclear Station                                                    January, 2009 Offsite Dose Calculation Manual (ODCM)                                      Revision 49 through RIA-33. In general, only low activity tritium releases (<1% station total) occur through the Chemical Treatment Pond #3 discharge point into the Keowee River. Dose calculations are performed for each of the two liquid discharge points for dose reporting purposes. The highest calculated dose from the two dose calculations is used to define the maximum individual dose from liquid releases at Oconee.
Radiation 4.0.4 Effluent Apportionment
Section 4 - Page 2
....1-1 1-1 1-3 2-1 2-1 2-1 2-2 2-5 2-5 3-1 3-1 3-5 3-7 3-8 3-9 3-9 4-1 4-1 4-7 4-18 4-18 5.0 Fuel Cycle Calculations
.5.0.1 Milling 5.0.2 Conversion


====5.0.3 Enrichment====
Oconee Nuclear Station                                                          January, 2009 Offsite Dose Calculation Manual (ODCM)                                          Revision 49 Liquid Dose Calculations The following equation is used for calculating liquid dose to the maximum exposed individual at each of the two liquid effluent release points:
5.0.4 Fuel Fabrication
A,    x      xC)XAtXFn X Ix Doseoa = I-I L.w p      i f
Ffxo    X f+F Formula: adapted from NUREG-0133; pages 15-17. Where:
Doseoa    The cumulative dose commitment for organ o and age group a, from the liquid effluent for the total time period, At. (mrem)
Aoapi Dose commitment factor for organ o, age group a, pathway p, and nuclide i (mrem/hr per jtCi/ml). (See Appendices C through F for age group and pathway specific dose commitment factors).
Ci The average concentration of nuclide i, in undiluted liquid effluent during the time period, At. (.tCi/ml)
At The length of time over which Ci and F, are averaged for all liquid releases. (hr)
F, The near field average dilution factor for Ci during the period of interest, At. Includes the recirculation factor. (dimensionless) f Average liquid radwaste flow during the period of interest, At. (gpm)
F Average dilution flow during the period of interest, At. (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.
a Recirculation factor. (dimensionless)
* Dw Dilution factor from the near field area to the potable water intake;
                = 30.0 for Oconee. This factor applies to the potable water pathway only. The nearest potable water intake to Oconee is located at the Andersen water intake approximately 31.5 miles from the site on a separate arm of Lake Hartwell. From a hydrology standpoint the Andersen water intake should not be significantly affected by liquid effluent discharges from Oconee. 30.0 is a conservatively small dilution factor based on environmental sample data.
* The recirculation factor accounts for the fraction of discharged water reused by the station. Liquid effluent discharge cannot be recirculated back into the Oconee station.
Therefore, the recirculation factor is 1.0 at Oconee.
Section 4 - Page 3


====5.0.5 Nuclear====
Oconee Nuclear Station                                                        January, 2009 Offsite Dose Calculation Manual (ODCM)                                          Revision 49 Derivation of Liquid Dose Commitment Factors                  (Aoapi)
Power Production 5.0.6 Fuel Reprocessing
Potable Water Aoapi =w1.        14x10' x          xDaoixe-&to Formula:. from NUREG-0133, page 16 and Regulatory Guide 1.109, page 1.109-12.
-Where:
Aoapi Dose commitment factor for organ o, age group a, pathway p, and nuclide i, (mrem/hr per ptCi/ml). (See Appendices C through F for age group and pathway specific dose commitment factors).
5 1.14x 10 Units conversion factor (pCi-yr-ml)/(utCi-hr-kg).
Uaw Water consumption rate in liters per year for age group a. From Table E-5, Regulatory Guide 1.109.
Adult - 730 Teen - 510 Child-510 Infant - 330 Daoi Dose factor for age group a, organ o, nuclide i, in mrem/pCi. From
_    _tables            E- I1through E- 14 of Regulatory Guide 1.109.
ki  Decay constant for nuclide i, in sec-.
tp  Environmental transit time from release to receptor. Default =
4.32E+04 sec (12 hours). From Regulatory Guide 1.109, Table E-15.
Section 4 - Page 4


====5.0.7 40CFR====
Oconee Nuclear Station                                                         January, 2009 Offsite Dose Calculation Manual (ODCM)                                         Revision 49 Aquatic Foods AAoapi -=1.14x10          5 xUa' xBFxDaoix et af Formula: from NUREG-0133, page 16 and Regulatory Guide 1.109, page 1.109 Where:
190 Total Dose Determination 5-1 5-1 5-1 5-1 5-1 5-2 5-2 5-2 6-1 6-1 6-1 6-8 6-8 6-9 6-10 6.0 Environmental Locations
Aoapi    Dose commitment factor for organ o, age group a, pathway p, and nuclide i, (mrem/hr per ltCi/ml). ' (See Appendices C through F for age group and pathway specific dose commitment factors).
..6.0.1 Site Description and Sample Locations 6.0.2 Land Use Census Data 6.0.3 Oconee Meteorology:
          .14xx 105 Units conversion factor (pCi-yr-ml)/(&#xfd;iCi-hr-kg).
Relative Air Concentrations and Deposition 6.0.3.1 XOQDOQ Methodology and Assumptions 6.0.3.2 Meteorological Data .6.0.3.3 Annual XOQDOQ Comparison to the ODCM ..7.0 Licensee Initiated Changes 7-1 i Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)January, 2009 Revision 49 Appendices Appendix A: Dose Factors for Exposure to a Semi-Infinite Cloud of Noble Gases Appendix B: Pi Dose Factors for use in the Gaseous Release Rate Limit Calculations Appendix C: Ai Adult Dose Factors for use in the Liquid Dose Calculations Appendix D: Ai Teen Dose Factors for use in the Liquid Dose Calculations Appendix E: Ai Child Dose Factors for use in the Liquid Dose Calculations Appendix F: Ai Infant Dose Factors for use in the Liquid Dose Calculations Appendix G: Ri Adult Dose Factors for use in the Gaseous. Dose Calculations Appendix H: Ri Teen Dose Factors for use in the Gaseous Dose Calculations Appendix 1: Ri Child Dose Factors for use in the Gaseous Dose Calculations Appendix J: Ri Infant Dose Factors for use in the Gaseous Dose Calculations A-I B-I C-I D-1 E-I F-1 G-I H-I I-I J-I LIST OF FIGURES 1.0-1 1.0-2 2.0-1 6.0-1 6.0-2 6.0-3 Liquid Radwaste System.Gaseous Radwaste System (4 pages)Liquid Radwaste Discharge Locations Sampling Locations Map (Site Boundary).
Uaf Fish consumption rate for age group a (kg/yr). From Table E-5, Regulatory Guide 1.109.
Sampling Locations Map (Ten Mile Radius)Land Use Census Map ..1-2 1-4 2-4 6-5 6-6 6-7 LIST OF TABLES 3.0-i RIA-33 Cs-137 Equivalents.
Adult - 21 Teen - 16 Child - 6.9 Infant - 0 BFi Bioaccumulation factor for nuclide i, in fish, in units of pCi/kg per pCi/liter. From Table A-I of Regulatory Guide 1.109.
3.0-2 Xe-133 Equivalents.
Daoi Dose factor for age group a, organ o, nuclide i, in mrem/pCi. From tables E- 11 through E-14 of Regulatory Guide 1.109.
6.0-1 Sampling Locations.  
Xi Decay constant for nuclide i, in sec-.
.6.0-2 TLD Sites 6.0-3 Land Use Census Results.6.0-4 Terrain Heights Above ONS Yard Grade Elevation (m)6.0-5 ONS Atmospheric Stability Frequency (1988 -1992)6.0-6 ONS Frequency of Wind Direction and Speed (1988 -1992)6.0-7 ONS Limiting X/Q and D/Q Values (1988-1992) 6.0-8 ONS Delta-T Ranges per Vertical Separation Distances 6.0-9 Oconee Semi-Elevated x/Q and D/Q Average Values (1988-1992) 6.0-10 Oconee Ground Level x/Q and D/Q Average Values (1988-1992) 3-4 3-11 6-2 6-3 6-4 6-9 6-10 6-10 6-11 6-11 6-12 6-14 ii Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 EXECUTIVE
tp Environmental transit time from release to receptor. Default =
8.64E+04 sec (1 day). From Regulatory Guide 1.109, Table E-15.
Section 4 - Page 5


==SUMMARY==
Oconee Nuclear Station                                                       January, 2009 Offsite Dose Calculation Manual (ODCM)                                         Revision 49 Shoreline Sediment Aoapi    =1.14x0        5  xlOOxDFGoiXWxUasxT xIe                        x(I  e-tb Formula:: adapted from Regulatory Guide 1.109, page 1.109-14.
The Oconee Nuclear Station (ONS) Offsite Dose Calculation Manual (ODCM) provides the methodology and parameters to be used in the calculation of offsite doses due to normal operation radioactive liquid and gaseous effluents to assure compliance with the dose limitations of the Selected Licensee Commitments (SLCs, UFSAR Chapter 16) and Technical Specifications.
Where:
These dose limitations assure that: (1) the concentration of radioactive liquid effluents released from the site to the unrestricted area will be limited to 10 times the effluent concentration (EC) levels of 10CFR20, Appendix B, Table 2, and 2.OE-04 ptCi/ml for dissolved and entrained noble gases;(2) the exposures to any individual member of the public from radioactive liquid effluents will not result in doses greater than the ALARA design objectives of IOCFR50, Appendix I or the 1OCFR20 limits;(3) the dose rate at any time at the site boundary from radioactive gaseous effluents will be limited to: for noble gases; less than or equal to 500 mrem/yr to the whole body, and less than or equal to 3000 mrem/yr to the skin; and for iodine-131 and iodine-133, for tritium, and for all radioactive materials in particulate form with half-lives greater than 8 days; less than or equal to 1500 mrem/yr to any organ;(4) the exposure to any individual member of the public from radioactive gaseous effluents will not result in doses greater than the ALARA design objectives of IOCFR50, Appendix I or the 1OCFR20 limits; and (5) the dose to any individual member of the public from the nuclear fuel cycle will not exceed the limits of 40CFR1 90.The methodology and parameters F-used to assure compliance with the dose limitations described above shall be used to prepare the radioactive liquid and gaseous effluent reports required by the SLCs and Technical Specifications.
Aoapi    Dose commitment factor for organ o, age group a, pathway p, and nuclide i, (mrem/hr per pCi/ml). (See Appendices C through F for age group and pathway specific dose commitment factors).
Dose calculations that demonstrate compliance with 40CFR190 will be considered to demonstrate
1.14x 105 Units conversion factor (pCi-yr-ml)/(ptCi-hr-kg).
* compliance with the 1OCFR20 0.1-rem annual dose limit. The ODCM also provides the Executive Summary -Page I Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 methodology and parameters to be used in the calculation of radioactive liquid and gaseous effluent monitoring instrumentation alarm /trip setpoints to assure compliance with the concentration and dose rate limitations of the SLCs and Technical Specifications.
100 Proportionality constant used in the sediment radioactivity model, (liters/(m 2-day).
Normally RETDAS, a computer code that implements NUREG-0133 methodology, is used for the calculation of offsite doses, but the ODCM also provides a method for the calculation of offsite doses when RETDAS is not available.
DFGoi      Ground plane dose conversion factor for organ o, nuclide i (mrem/hr per pCi/mi2), from Table E-6 of Regulatory Guide 1.109.
The ODCM has been prepared as generically as possible in order to minimize the need for revisions.
w    Shoreline width factor. For Oconee = 0.2, from Table A-2, Regulatory Guide 1.109.
However, some changes to the ODCM such as land-use census data are expected on an annual basis. Any changes to the methodology and parameters to be used in this ODCM shall be reviewed by knowledgeable individual(s), and approved by the Station Manager and the General Office Radiation Protection Manager prior to implementation.
U. Shoreline exposure rate for age group a (hr/yr), From Table E-5, Regulatory Guide 1.109.
Changes to the ODCM shall be submitted to the Nuclear Regulatory Commission in accordance with the SLCs and Technical Specifications.
Adult - 12 Teen -67 Child- 14 Infant - 0 Ti'/  Nuclide half life for nuclide i, in days.
The ODCM does not replace any station implementing procedures.
                  ,i  Nuclide decay constant for nuclide i.
Programmatic controls for radioactive effluents and radiological environmental monitoring are contained in the Administrative Controls chapter of the Technical Specifications.
tp  Average transit time to point of exposure (0 hours).
Procedural details for radioactive effluents and radiological environmental monitoring consisting of licensee commitments, applicability, remedial actions, surveillance requirements, and the bases for these requirements are contained in Section 16.11 of the SLCs.Executive Summary -Page 2 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)January, 2009 Revision 49 1.0 RADWASTE SYSTEMS 1.0.1 LIQUID RADWASTE PROCESSING The liquid radwaste system at Oconee Nuclear Station is used to collect and treat liquid chemical and radiochemical byproducts of unit operation.
tb  Sediment exposure time (15 years). Page 1.109-14.
The system produces effluents that are discharged in small, dilute quantities to the environment.
Section 4 - Page 6
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.
Oconee Nuclear Station                                                                 January, 2009 Offsite Dose Calculation Manual (ODCM)                                                 Revision 49 4.0.2 GASEOUS EFFLUENT DOSE MODEL FOR THE MAXIMUM EXPOSED INDIVIDUAL The dose contributions from measured quantities of radioactive materials identified in gaseous effluent released to unrestricted areas shall be calculated for the maximum gamma and beta air dose from noble gases, and for the maximum exposed individual from radioiodines, particulates, and others using the following equations:
Also, ion exchange is normally used in removing cations (cobalt, cesium, manganese) and anions (chloride, fluoride) from the filtrate in order to purify the filtrate for release.(C) Gas Stripping
Gaseous Dose Calculations Noble Gas Dose Calculations Gamma Air Dose Dose, =3.17x10-8 xz/QX                      -(MixQ        i)
-Removal of gaseous radioactive fission products is accomplished through venting of atmospheric holdup tanks.Figure 1.0-1 is a schematic representation of the liquid radwaste system at Oconee.Section I -Page I Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)January, 2009 Revision 49 Figure 1.0-10Oconee Nuclear Station Liquid Radwaste System GA E. COOE. ISCMARGE LAKE KEGW&#xa3;E RAAS&#xfd;TE FAGILITI SMIELDED AREA SWP -YSE DRAINS FROM. %'EI GE-lCE WATER..RT-N SISTEM -MAlEA WASTE EEAPORAA-1.A" SOAGR P-IFICATIOM GMI-RIZER SEMERGN " SPENT FUEL SYSTEM ,.G' FI -_,.ESAE TEST FUEL A F:_20-4 ANK1GEI.- FNE. / -I CE.TGA LG Y~E C0NrEAAC-A TEST TANK1 SPENT FUEL COE-MR Section 1 -Page 2 Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 1.0.2 GASEOUS RADWASTE PROCESSING The purpose of the gaseous waste disposal system is to: (1) Maintain a non-oxidizing cover gas of nitrogen in tanks and equipment that contain potentially radioactive gas;(2) Hold up radioactive gas for decay; and (3) Release gases (radioactive and non-radioactive) to the atmosphere under controlled conditions.
Formula: adapted from:NUREG-0133, page 28.
During power operation of the facilities, radioactive materials released to the atmosphere in gaseous effluents include low concentrations of fission product noble gases (krypton and xenon), halogens (mostly iodines), tritium contained in water vapor, and particulate material including both fission products and activated corrosion products.The primary source of gaseous radioactive wastes is from the degassing of the primary coolant during letdown of the cooling water into various holding tanks. Additional sources of gaseous waste activity include the auxiliary building exhaust, spent fuel area exhaust, the discharge from the steam jet air ejectors, and purging and venting of the reactor containment building.All components that can contain potentially radioactive gases are vented to a vent header.The vent gases are subsequently drawn from this header by one of four waste gas compressors or a waste gas exhauster.
Where:
The waste gas compressor discharges through a waste gas separator to one of seven waste gas tanks. The waste gas tanks and the waste gas exhauster discharge to the unit vent after passing through a filter bank consisting of a prefilter, an absolute filter, and a charcoal filter.Radioactive gases may be released inside the reactor containment building when components of the primary system are opened to the building atmosphere for operational, reasons or where minor leaks occur in the primary system. Prior to access, the reactor containment atmosphere will be monitored for radioactivity and, when necessary, purged through prefilters, high-efficiency particulate air (HEPA) filters, and charcoal filters, and released to the atmosphere through the unit vent. The purge equipment is sized for a flow rate of 50,000 cfm providing approximately 1.5 air changes per hour in the reactor building.
Dosey Gamma air dose for the time period of interest (mrad).
Units 1, 2, and 3 have a separate vent stack which services each unit.Figure 1.0-2 is a schematic representation of the gaseous radwaste system at Oconee.Section I -Page 3 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)January, 2009 Revision 49 Figure 1.0-2 Oconee Nuclear Station Gaseous Radwaste System Page 1 of 4 VENT HT 200 FT Section 1 -Page 4 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)January, 2009 Revision 49 Figure 1.0-2 Oconee Nuclear Station Gaseous Radwaste System Page 2 of 4 I2-RIASE UNIT VENT UNIT 2 PENETRATION ROOM VENTILATION SYSTEM~A-32 UNIT 2 REACTOR BUILDING UNIT 2 E C O U L N R F LT R I T R D O B R UNIT I & 2 SPENT FUEL -POOL AREA RA CONDENSER FOR EJECTOR STEAM SYSTEM GAS FROM STEAM GENERATOR TUBE LEAK , AI R EJCO HOTWELL-*HEIGHT 200 FT N GROUND EVEL DECONTAMINATION AND FUME HOODS STATIO L AUXILIARY BUILDING VENT MULTIPLE AUXILIARY STA-1 BUILDING LOCATIONS L Section I- Page 5 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)January, 2009 Revision 49 Figure 1.0-2 Oconee Nuclear Station Gaseous Radwaste System Page 3 of 4 VENT IT 200 FT Section 1 -Page 6 Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 Figure 1.0-2 Oconee Nuclear Station Gaseous Radwaste System Page 4 of 4 HOT MACHINE SHOP VENTILATION SYSTEM PRFLE EP OAIE EXHAUST* [ PARTICULATEsAML&
3.17x 10-8 Inverse number of seconds in year (year/seconds).
WELDING HOOD -RFITR HP INTERIM RADWASTE FACILITY VENTILATION SYSTEM EXAT RADWASTE BUILDING VENTILATION SYSTEM LOW EXHAUST FLOW EXHAUST TANK VENTS & LAB HOODS HEPH HNO CARBON FILTEH HEPH HNO PRTICUOI TE & 4RIA-45 VR SYSTEM OFF-GAS CARBON FILTER IODINE SMPLER HEPH HLA CHRBON FIL0T ER .EXHHUST VENTILATION SYSTEM FO Section 1.- Page 7 Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 2.0 RELEASE RATE CALCULATIONS
Mi Gamma air dose factor due to gamma emissions for nuclide i (mrad/yr per  &#xfd;LCi/m3). (See Appendix A).
z/Q .Iarea The highest    calculated at or beyond          annual the site        average boundary      relative (sec/m      concentration 3)*. (See            for any Table 6.0-9).     I Qi    Activity for nuclide i released during the time period of interest (UtCi).
Beta Air Dose Dosef =3.17x10- 8 x /Qxj(Nx Q,)
Formula: adapted from NUREG-0133, page 28.
Where:
Doser3    Beta air dose for the time period of interest (mrad).
3.17x 10-8    Inverse number of seconds in year (year/seconds).
Ni    Beta air dose factor due to beta emissions for nuclide i (mrad/yr per
                      &#xfd;LCi/m 3). (See Appendix A).
x/Q    The highest calculated annual average relative concentration for any area at or beyond the site boundary (sec/m 3)*. (See Table 6.0-9).
Qi    Activity for nuclide i released during the time period of interest (&#xfd;tCi).
0 Section 4 - Page 7
 
Oconee Nuclear Station                                                         January, 2009 Offsite Dose Calculation Manual (ODCM)                                           Revision 49 Iodine, Particulates, and H-3 Dose Organ Dose Calculation Dose oa = 3.17 x lO-8 x W x            Y            (Roapi X QJ) p      i Formula: adapted from NUREG-0133, pages 29`& 30.
Where:
Doseoa    The cumulative dose commitment to the total body or any organ o, for an individual of age group a (mrem).
3.17x 10- 8  Inverse number of seconds in year (year/seconds).
Roapi    Dose commitment factor for organ o, age group a, pathway p, and nuclide i. The units are based on whether a dispersion or deposition factor is used. When a x,/Q is used the units are.mrem/yr per ltCi/m 3.
When a D/Q is used the units are (M2 mrem/yr) per &#xfd;tCi/sec. (See Appendices G through J for age group and pathway specific dose commitment factors).
W    Dispersion (x/Q) or deposition factor (D/Q)*. The factor used is based upon the pathway. Note: X/Q is always used for tritium.
Pathway                                  Factor Used Ground Plane Deposition                  D/Q (m 2 )
Inhalation                              X/Q (sec/m 3 )
Vegetation                              D/Q (m-2)
Grass/Cow/Milk                          D/Q (m-2)
Grass/Goat/Milk                          D/Q (m2 )
Grass/Cow/Meat                          D/Q (m-2)
Qi    Activity for nuclide i, released during the time period of interest (ltCi).
* The dose from noble gases released from semi-elevated release points, e.g., unit vent, is calculated using the semi-elevated dispersion factors. The dose from noble gases released from ground level release points, e.g., Radwaste Facility vent, is calculated using the ground level dispersion factors. The total dose is the sum of the semi-elevated and ground level dose calculations. Maximum individual organ dose is determined by calculating the organ dose at each of the x/Q and D/Q locations shown in Table 6.0-9 and' Table 6.0-10 (128 locations) for both semi-elevated release points and ground level release points, summing the two at each location, and then choosing the dose from the maximum location. Dose is calculated only for those pathways (e.g., garden, milk animal, etc.) that actually exist at each location as determined by the land use census shown in Table 6.0-3. As discussed in Oconee UFSAR Section 2.1.1.3, the boundary for establishing gaseous effluent release limits is the exclusion area boundary (EAB). The EAB is defined as a I mile radius from the station center.
Section 4 - Page 8


====2.0.1 LIQUID====
Oconee Nuclear Station                                                               January, 2009 Offsite Dose Calculation Manual (ODCM)                                               Revision 49 Derivations of Iodine, Particulate, and H-3 Dose Commitment Factors (Roapi)
RELEASE RATE LIMIT CALCULATIONS There are two liquid radwaste discharge points to the environment at Oconee; (1) the liquid radwaste effluent line to the Keowee Hydroelectric Unit Tailrace, and (2) the #3 Chemical Treatment Pond effluent line to the Keowee River (See Figure 2.0-1).2.0.1.1 LIQUID RADWASTE EFFLUENT LINE RELEASE RATE LIMIT CALCULATION Liquid releases to the Keowee Hydroelectric Unit Tailrace normally contain the radioactive releases from the site including effluents from the Waste Monitor Tanks, Recycle Monitor Tanks, and Decant Monitor Tank.. The Keowee Tailrace discharge point can also contain Turbine Building Sump Monitor Tank (TBSMT) releases, however TBSMT effluent normally contains very low (if any) activity, and, therefore is transferred to the #3 Chemical Treatment Pond prior to release. Dilution flow for the liquid radwaste effluent line is provided by the Keowee Hydroelectric Unit and the Keowee Hydro Fire Protection liquid waste release mixing line. For purposes of the release rate calculation, Keowee hydro dilution flow is assumed to be a minimum leakage flow of 38 cfs, and a maximum flow of 6600 cfs based on one hydro unit operating at 50% power. The Keowee Hydro Fire Protection liquid waste release mixing line provides an additional 38 cfs dilution flow. Since Keowee Hydro typically releases only a small percentage of time during the year, 76 cfs (38 cfs leakage + 38 cfs mixing line) is normally assumed for dilution flow when performing liquid release rate calculations.
Ground Plane Denosition Pathway Roapi  =K'K"(SF)DFGOI          i       A Formula: from NUREG-0133, page 32.
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.OE-04 [tCi/ml for dissolved and entrained noble gases, the following release rate limit calculation shall be performed for liquid releases to the Keowee Hydro Tailrace via the liquid radwaste effluent line: f< F -(DF-1) Condition:
Where:
DF> 1.0 Equation 2.1 where: f = the undiluted effluent flow, in gpm.F = the dilution flow available, in gpm.= normally 3.41E+04 gpm (76 cfs, based on a leakage rate of 38 cfs (19 cfs per.Keowee Hydro unit), plus the Keowee Hydro Fire Protection liquid waste release Section 2 -Page 1 Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 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.
Roapi  Dose commitment factor for organ o, age group a, nuclide i, for ground plane deposition pathway (m2 mrem/yr per jtCi/sec). (See Appendices G through J for age group and pathway specific dose commitment factors).
DF = required dilution factor to be applied to the undiluted effluent flow, unitless.DF=(10 x EC,) Equation 2.2 Note: If DF < 1.0 then no dilution is required and the release rate is unrestricted.
K'    Units conversion factor pCi/&#xfd;tCi (1.06).
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.a the most restrictive recirculation factor at equilibrium, (dimensionless).
K"    Units conversion, factor 8760 hr/year.
The recirculation factor accounts for the fraction of discharged water reused by the station. This value equals 1.0 since discharged liquid effluent is not reused at Oconee.Ci = the concentration of radionuclide, 'i', in the undiluted liquid effluent, in &#xfd;tCi/ml.ECi = the concentration of radionuclide, 'i', from IOCFR20, Appendix B, Table 2, Column 2, in itCi/ml. Note: if radionuclide, 'i', is a dissolved noble gas, then ECi= 2.OOE-05 pCi/ml.Once the maximum release rate, f, is calculated the value is multiplied by 0.8 for additional conservatism.
SF    Shielding factor (dimensionless) (0:7, from Regulatory Guide 1.109).
2.0.1.2 #3 CHEMICAL TREATMENT POND EFFLUENT LINE DISCHARGE The #3 Chemical Treatment Pond (CTP) effluent line is the release point for station effluents that are normally considered to be non-radioactive; that is, the pond's effluent will not normally contain measurable activity above background with the exception of very low tritium activity.
DFGoi    Ground plane dose conversion factor for organ o, nuclide i (mrem/hr per pCi/mr2), from Table E-6 of Regulator: Guide 1.109.
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.
X*  Nuclide decay constant for nuclide i (sec-).
Inputs that have radiation Section 2 -Page 2 Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 monitors associated with them will be set to assure that Selected Licensee Commitment 16.11-1 will not be exceeded.
t  Exposure time, 4.73xx108 seconds (15 years).
#3 CTP is a continuous release path that discharges to the Keowee River (see Figure 2.0-1).The #3 CTP may also be the discharge path for large volumes of slightly contaminated water following a primary-to-secondary leak so long as administrative procedures are implemented to assure that release rate calculations similar to that used in Section 2.0.1.1 are performed, that all detectable radionuclides will be accounted for, and that no station limits will be exceeded.Section 2 -Page 3 Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 Figure 2.0-1 Liquid Radwaste Discharge Locations Lake Keowee Visitors ./. Keowee / n 7 bente&' Dam Discharge
Inhalation Pathway Roapi: K'(BRa )(DFAoi )a Formula: from NUREG-0133, page 31.
. Release'Point Oconee Nuclear -(i U~Section 2 -Page 4 Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 2.0.2 GASEOUS RELEASE RATE LIMIT CALCULATIONS The three unit vents are the primary gaseous radioactive release points at Oconee. The unit vents are the semi-elevated release points for waste gas decay tanks, containment building purges, auxiliary building ventilation, spent fuel pool ventilation, and the condenser air ejector (see Figure 1.0-2, pages 1, 2, and 3). Each unit vent contains multi-range radiation monitors (RIAs) and flow rate measuring instrumentation.
Where:
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.
Roapi  Dose commitment factor for organ o, age group a, nuclide i, for inhalation pathway (mrem/yr per       uiCi/m 3).. (See Appendices G through J for age group and pathway specific dose commitment factors).
Each of these release points are considered ground-level, and each has an effluent sampler and flow monitoring device (see Figure 1.0-2, page 4). In addition, the Interim Radwaste Building and Radwaste Facility have a RIA.2.0.2.1 UNIT VENT DISCHARGE RELEASE RATE LIMIT CALCULATION In order to comply with Technical Specifications and Selected Licensee Commitments and to assure that the dose rate, at any time, at or beyond the site boundary due to radioactive materials released in gaseous effluents from the site is limited to: < 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.
K' Units conversion factor pCi/pCi (106).
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: X(KXZ xQ < 500mrem/yr Equation 2.3 Skin: X((Li+,I .IM)xZ-I-xQi
BRa Breathing rate for age group (m3/yr), from Regulatory Guide 1.109:
< 3000 mrem/yr Equation 2.4 Section 2 -Page 5 Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 b. Radioiodines, Particulates, and Others Inhalation, Ingestion and Ground Organ Pathways: I Z(P~pi x W x Qi x Ei) < 1500mrem/yr p I To include both the food and ground organ dose and the inhalation organ dose the equation can be expanded to: Q -({(Pop:)foodgr X WD 0 + (Pop, ).hat X WX/0} x Q x Ei) < 1500mrem/yr
Adult - 8000 Teen - 8000 Child - 3700 Infant - 1400 (DFAoi)a Organ inhalation factor dose conversion factor for.organ o, nuclide i, age group a (mrem/pCi), from Tables E-7 through E-10 of Regulatory Guide 1.109.
: p. i Equation 2.5 where: Ki = the total body dose factor due to gamma emissions for each identified noble gas radionuclide, 'i', in mrem/yr per ptCi/m 3 (See Appendix A).L, = the skin dose factor due to beta emissions for each identified noble gas radionuclide, 'i', in mrem/yr per pCi/mn 3 (See Appendix A).M = the air dose factor due to gamma emissions for each identified noble gas radionuclide, 'i', in mrad/yr per ptCi/m 3 (See Appendix A).Pop, the dose parameter for radionuclides other than noble gases for the inhalation pathway, in mrem/yr per p[Ci/mn 3 and for the food and ground plane pathways in (i 2 x (mrem/yr per [tCi/sec))
Section 4 - Page 9
for organ, 'o', and radionuclide, 'i', (See Appendix B for the pathway specific dose commitment factors).
Note: NUREG-1301, page 75, specifies use of the Child age group, Inhalation pathway, for the Popi values.X/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: Section 2 -Page 6 Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 Wz/Qse = 1.672E-6 sec/mr 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.Wz/QgI = 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 = the filter removal factor for radionuclide, 'i', e.g., for 99% removal E, = 0.01.For iodine removal by charcoal adsorbers E 1 = 0.1.For particulate removal by HEPA filters E, = 0.01.Qj =the release rate of radionuclide, 'i', in gaseous effluent from all release points at the site, in ptCi/sec.Q= kiCf + k2 = 4.72E + 02 x Cf Equation 2.6 where: Ci = the concentration of radionuclide, 'i', in undiluted gaseous effluent, in ptCi/ml.f = the undiluted effluent flow, in ft 3/min.k 1 = conversion factor, 2.83E+04 cc/ft 3.k = conversion factor, 6.OE+01 sec/min.Substituting the expression for Q 1 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: fib< 500 4.72E+02 x X/Q x (Ki x C t)Section 2 -Page 7 Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 Noble Gases -Skin Maximum Release Rate: fk <3000 4.72E+02 x X -[(L,+ 1.1M) x Ci]Radioiodines, Particulates, and Others -Organ Maximum Release Rate: 1500 4.72E+02 x "({(Pop,)foo-dg, X'WD'Q + (Popi)imh.1 X Wx/Q Ix x C,)p i fb, fik, and for, are calculated for each batch prior to release. The most limiting gaseous release rate is used to assure that no instantaneous dose rate limit is exceeded.Once the maximum release rate, f is calculated the value is multiplied by 0.8 for additional conservatism.
Section 2 -Page 8 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)January, 2009 Revision 49 Derivations of Iodine, Particulate, and H-3 Dose Commitment Factors (Popi)Inhalation Pathway -Child Age Group 0 Pi = K'(BR )(DFA o)Formula: from NUREG-0133, page 25.Where: Popi Dose commitment factor for Child age group, organ o, nuclide i, for the inhalation pathway (mrem/yr per 3). (See Appendix B for the pathway specific dose commitment factors).K' Units conversion factor pCi/tCi (106).BR Breathing rate for the Child age group (m 3/yr, from Regulatory Guide 1.109): Child -3700 DFAoi Organ inhalation dose conversion factor for Child age group, organ o, 1 nuclide i, (mrem/pCi), from Table E-9 of Regulatory Guide 1.109.Section 2 -Page 9 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)January, 2009 Revision 49 3.0 SETPOINT CALCULATIONS


====3.0.1 LIQUID====
Oconee Nuclear Station                                                           January, 2009 Offsite Dose Calculation Manual (ODCM)                                           Revision 49 Vegetation Roap=       K1L         (r)         x(DFL oJ)a x [ULfLeAAtL + U fge~2At/ ]
RADIATION MONITOR SETPOINT CALCULATIONS As shown on Figure 1.0-1, RIA-33 is the controlling radiation monitor for liquid batch releases at Oconee. Once the liquid release rate parameters have been established radiation monitor setpoints shall be calculated to assure that the concentration of radioactive liquid effluents released from the site to the unrestricted area is limited to ten times the effluent concentrations (ECs) of 10CFR20, Appendix B, Table 2, Column 2, and 2.OE-04 p.Ci/ml for dissolved and entrained noble gases., By substituting the dilution factor (DF) from Equation 2.2 into Equation 2.1, solving for the undiluted liquid effluent concentration, Ci, and accounting for the monitor background reading, the liquid radiation monitor setpoint can be readily obtained by multiplying Ci by the radiation monitor correlation factor, CFi, as follows: Ci-< (F + f) x (10 x EC,)(Cxf SP <- Z (c 1 x CF,) + bkg Equation 3.1 Equation 3.2 where: Ci = the maximum allowable concentration of radionuclide, 'i', in the undiluted liquid effluent, in ltCi/ml.SP = radiation monitor setpoint, in cpm.CF, = radiation monitor correlation factor for radionuclide, 'i', in cpm/tCi/ml, e.g., 8.OOE+07 cpm/&#xfd;tCi/ml (Cs-137) for RIA-33.bkg = background reading for the radiation monitor, in cpm.All other parameters were previously defined.Using conservative or "worst-case" parameters in Equation 3.1 and Equation 3.2 can provide a liquid radiation monitor setpoint that does not need to be revised for every release if activity is low enough to allow for this type of operation such as with continuous releases from the #3 CTP release point. However, for batch releases, e.g., waste monitor tanks, through the liquid radwaste effluent line to the Keowee hydro Section 3 -Page 1 Oconee Nuclear Station " January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 tailrace the RIA-33 radiation monitor setpoints are calculated based on the actual expected activity in the release as follows: First the "Correlation Concentration" (C CONC) is calculated' C CONC = (CG x EQ,)where: C 1  = Undiluted liquid effluent concentration for each isotope, excluding tritium, ltCi/mnl.EQj = RIA-33 Cs-137 equivalence factor for each isotope, excluding tritium, to that of Cs-137 due to different gamma energies and abundance.
Yv+,+A)
This factor includes a 4-hour decay time due to the average time between; sample and release. (See Table 3.0-1)Next the RIA-33 setpoints are determined as follows: If C CONC is > 9.OE-6 jtCi/ml then three setpoint values are calculated.!!
Formula: from NUREG-0133, page 35. .Where:
The actual"expected" count rate for the release is defined as the "Midpoint of Expected Range".The "Alert" setpoint is defined as 1.5 times the expected counts from activity in the liquid effluent plus background.
Roapi   Dose commitment factor for organ o, age group a, nuclide i, for vegetation pathway (m2 .mrem/yr per pCi/sec). (See Appendices G through J for age group and pathway specific' dose commitment factors).
If the "Alert" setpoint is exceeded, but there is no upward trend, the release will be allowed to continue.
K'   Units conversion factor pCi/pCi (106).
If RIA-33 continues to trend Iupward then the release will be manually terminated.
r Fraction of deposited activity retained on vegetation, from Regulatory Guide 1.109.
The "Upper Limit of Expected Range" is defined as 3 times the expected counts from activity in the liquid effluent plus background.
1.0 for radioiodine.
The "Upper Limit of Expected Range" is called the "Trip" setpoint.
If the"Trip" setpoint is exceeded the release will be automatically terminated.
The "Lower Limit of Expected Range" is defined as 3 times lower than the expected counts from activity in the liquid effluent plus background.
The "Lower Limit of Expected Range" provides assurance that the correct liquid effluent is being released.
If the RIA-33 count rate does not increase to at least the "Lower Limit of the Expected Range" then the release will be terminated, and a new sample analysis will be performed.
The four RIA-33 setpoints are calculated as follows: Lower Limit of Expected Range = C CONC x (8.00E7/3) 6pm/(QiCi/ml)
+RIA-33 BKG Midpoint of Expected Range = C CONC x 8.00E7 cpm/(iCi/ml)
+RIA-33 BKG Alert Setpoint = C CONC x (8.OOE7x 1.5) cpm/(laCi/ml)
+RIA-33 BKG Upper Limit of Expected Range = C CONC x (8.00E7x3),cpm/(j.Ci/ml)
+(Trip Setpoint)
RIA-33 BKG Section 3 -Page 2 Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 If C CONC is _ 9.OE-6 jtCi/mi then the RIA-33 setpoint is 2.16E3 cpm (9.OE-6 x 8.00E7 x 3) plus background (BKG) as the "Upper Limit of Expected Range". This setpoint is used for low activity releases, and is based on limiting the concentration in the effluent to 10 times the IOCFR20 EC of Cs-134 which has the lowest effluent concentration value (9.OE-7 tCi/mi) for any detectable radionuclide in the effluent.
Similarly, the RIA-33"Alert" setpoint for low activity releases is 1.08E3 cpm (9.OE-6 x 8.00E7 x 1.5) plus background (BKG).Section 3 -Page 3 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)January, 2009 Revision 49 Table 3.0-1 RIA-33 Cs-137 Equivalents isotope Equivalence Isotope Equivalence Isotope Equivalence Factor Factor Factor Be-7 0.1462 Mo-99 0.2668 La-141 0.0155 F-18 0.5788 Tc-99m 0.00 La-142 0.2942 Na-24 0.8519 Tc-101 0.00 Ce-141 0.00 CI-38 0.0090 Ru-103 1.3368 Ce-143 0.7826 K-40 0.1094 Ru-105 0.8783 Ce-144 0.0273 Cr-51 0.1438 Ru-106 0.4429 1-130 3.3095 Mn-54 1.0617 Ag-108m 3.4473 1-131 1.4051 Mn-56 0.4992 Ag-110m 3.5179 1-132 1.0259 Fe-59 1.0556 Cd-ll5 0.5201 1-133 1.1857 Co-57 0.0022 Cd-ll5m 0.0235 1-134 0.1388 Co-58 1.4735 In-115m 0.3631 1-135 0.9374 Co-60 2.0495 Sb-122 0.9218 Ar-41 0.2229 Cu-64 0.3954. Sb-124 2.1617 Kr-85 0.0059 Ni-65 0.1591 Sb-125 1.1308 Kr-85m 0.4280 Zn-65 0.5584 Sb-126 5.1762 Kr-87 0.1213 Zn-69m 1.1391 Sn-113 0.9971 Kr-88 0.5278 Se-75 1.3092 Sn-123 0.0066 Kr-89 0.00 Br-80m 0.0860 Sn-126 0.00 Xe-131m 0.0167 Br-82 3.4691 Te-125m 0.00 X6-133 0.0006 Br-83 0.0059 Te-127 0.0134 Xe-133m 0.1172 Br-84 0.0053 Te-127m 0.0001 Xe-135 0.8564 Br-85 0.00 Te-129 0.0138 Xe-135m 0.00 Rb-86 0.0894 Te-129m 0.0507 Xe-137 0.00 Rb-88 0.00 Te-131 0.0008 Xe-138 0.00 Rb-89 0.00 Te-131m 1.8463 Nd-147 0.2619 Sr-89 0.0002 Te-132 0.9766 Hf-181 1.4209 Sr-91 0.6460 Te-134 0.0408 W-187 0.8027 Sr-92 0.3900 Cs-134 2.5804 TI-208 0.00 Y-91 0.0031 Cs-136 3.1916 Bi-212 0.0144 Y-91m 0.0439 Cs-137 1.00 Bi-214 0.0003 Y-92 0.1334 Cs-138 0.0120 Pb-212 0.4497 Y-93 0.1091 Ba-133 1.3648 Pb-214 0.0020 Zr-95 1.0909 Ba-139 0.0203 Ra-226 0.0320 Zr-97 1.1210 Ba-140 0.5307 Ac-228 0.8261 Nb-95 1.0821 Ba-141 0.0002 Th-228 0.0038 Nb-95m 0.2919 Ba-142 0.00 Np-239 0.3996 Nb-97 0.1164 La-140 2.3237 1_1__Section 3 -Page 4 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)January, 2009 Revision 49 3.0.2 GASEOUS RADIATION MONITOR SETPOINT CALCULATIONS The unit vent radiation monitor setpoints are established at the Oconee Nuclear Station to help ensure that gaseous release rate limits are not exceeded.
For some release pathways in which a specific RIA exists, the setpoints also help to ensure that the effluent being released is the same concentration as indicated by manual samples, e.g. effluent from waste gas decay tanks, thereby reducing the likelihood of releasing the wrong tank. For instances in which the RIA which normally controls the release is not operable, or is "out of service", independent manual samples (IMS) are collected and the noble gas constituents from both samples are compared to help ensure that the intended' "batch" is being released.
For certain low potential release types, e.g. Integrated Leak Rate Tests, no RIA exists to ensure that release rate limits are not exceeded or to ensure that the effluent being released is the "expected" concentration.
For such pathways, independent manual samples are required to be collected and noble gas constituents compared prior to release. The following list defines the controlling RIA for the various gaseous effluent release types at Oconee: Pathway Controlling RIA Unit 1 "A" Waste Gas Decay Tank Unit I "B" Waste Gas Decay Tank Unit 1 "C" Waste Gas Decay Tank Unit I "D" Waste Gas Decay Tank Unit 3 "A" Waste Gas Decay Tank Unit 3 "B" Waste Gas Decay Tank Unit 3 "C" Waste Gas Decay Tank Unit 1 Reactor Building Purge Unit 2 Reactor Building Purge Unit 3 Reactor Building Purge Unit 1 Depressurization Unit 2 Depressurization Unit 3 Depressurization Unit 1 Hydrogen Recombiner Unit 2 Hydrogen Recombiner Unit 3 Hydrogen Recombiner Unit 1 Integrated Leak Rate Test Unit 2 Integrated Leak Rate Test Unit 3 Integrated Leak Rate Test 1&2 RIA 37/38 l&2 RIA 37/38 1&2 RIA 37/38 l&2 RIA 37/38 3 RIA 37/38 3 RIA 37/38 3 RIA 37/38 1 RIA 45/46 2 RIA 45/46 3 RIA 45/46 IMS 1 RIA 45/46 Alarm Only IMS 2 RIA 45/46 Alarm Only IMS 3 RIA 45/46 Alarm Only IMS 1 RIA 45/46 Alarm Only IMS 2 RIA 45/46 Alarm Only IMS 3 RIA 45/46 Alarm Only IMS IMS IMS The following sections describe the methods by which setpoints are established.
In general, gaseous radiation monitors are calibrated to Xe-133, and for continuous release points, e.g., the three unit vents, are preset at a maximum value based on the 500 mrem/year total body gaseous release rate limit according to the following methodology:
Section 3 -Page 5 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)January, 2009 Revision 49 Note: when applied to the individual release points the 500 mrem/year site dose rate value is apportioned 30% to each Unit Vent (RIA-45 and RIA-46) semi-elevated release point.The remaining 10% is allocated to the three ground-level release points, the Hot Machine Shop (no monitor), Interim Radwaste Building (RIA-53) and Radwaste Facility (4RIA-45)that are normally considered non-radioactive.
Recall from Section 2.0.2.1 the following equation: KXe-133 X Q X Qxe-133 < 500 mrem/yr Solve for QXe-133: S 500 Qxe -133 < 50 Kx'e-133 )x,//Equation 3.4 From Equation 2.6: Qxe -133 = 4.72E + 02 x CXe -133 x f Substitute Equation 3.5 into Equation 3.4: 4.72E + 02 Cx- 133 X f < 500 Kne-133 "X z/Q Solve for CXe-133: Equation 3.5 CXe -133 <500 4.72E+02 x f x Kxe-133 X /Q CXe -133 SP = -+ bkg CF Equation 3.6 where: KXe-133 = 2.94E+02, the total body dose factor due to gamma emissions for Xe-133, in mrem/year per jtCi/m 3 (See Appendix A).X/Q = the highest calculated semi-elevated annual average dispersion parameter for any area at or beyond the site boundary in sec/m 3.For Oconee this value is 1.672E-6 sec/m 3.The location is the SW sector at 1.0 mile.Qxe-133 Xe-133 equivalent release rate limit for the noble gastotal body dose pathway, in /tCi/sec.4.72E+02 = Conversion factor, (cc/ft 3)/(sec/min).
Section 3 -Page 6 Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 CXe-133 = the maximum allowable Xe-133 equivalent concentration in the gaseous effluent,, in &#xfd;tCi/cc.f = the gaseous effluent flow from the tank, building, or vent, in ft 3/min.SP radiation monitor setpoint, in cpm.CF = the Xe-133 equivalent monitor correlation factor, in VtCi/cc/cpm.
bkg = the radiation monitor background reading, in cpm.Equation 3.6 provides the methodology to calculate the maximum setpoint for releases from the Unit Vents (RIA-45 and RIA-46), Radwaste Facility (4RIA-45), and Interim Radwaste Building (RIA-53).3.0.2.1 UNIT VENTS SETPOINTS (RIA-45 and RIA-46)Reactor Building purges from all 3 units are released via the applicable unit vent, either Unit 1, Unit 2, or Unit 3. Each of the 3 unit vents are monitored by a normal/low range RIA (RIA-45) and a high range RIA (RIA-46).
In addition to Reactor Building purges, all other releases from the main plant, including the Auxiliary Building ventilation, Waste Gas Decay Tanks, and the Spent Fuel 'Pools are monitored by each unit's RIA-45 and RIA-46. However, 'RIA-45 and RIA-46 on each, unit vent have release termination authority only for Reactor Building purge releases.
Each unit's RIA-45 and RIA-46 will, when operable, activate Control Room alarms if the unit vent concentration exceeds the monitor's setpoint value. The setpoints for each unit's RIA-45 and RIA-46 are established on a "worst case" basis, With the upper bound' normally set at 30 percent of the station release rate limit for noblegases in Xe-133 equivalent concentration as follows: Recall Equation 3.6: CXe -133 SP -+ bkg CF where: CXe -133 < 500 4.72E+02 x f x KXe-133 X.X RA -45ui vent = 150 4.72E + 02 x 6.5E + 04 x 2.94E + 02 x 1.672E- 06 x 7.09E- 08 R/A -45u,, vent 1.40E + 05 cpm + bkg Section 3 -Page 7 Oconee Nuclear Station January, 2009 OffsiteDose Calculation Manual (ODCM) Revision 49 where: 150. = 30% of the 500 mrem/yr total body release rate limit.6.5E+04 = Unit Vent flow rate with Reactor Building Purge off, ft 3/min.1.672E-06
= Highest Semi-Elevated release point dispersion; factor, sec/m3n 7.09E-08 = RIA-45 Correlation Factor, &#xfd;tCi/ml/cpm.
All other factors were previously defined.150 " RIA -6ui vent=4.72E+02 x 6.5E+04 x 2.94E+02 x 1.672E-06 x 3.1'7E-04 RIA -46,tv._t 31 cpm + bkg where: 3.17E-04 = RIA-46 Correlation Factor, laCi/ml/cpm.
All other factors were previously defined.For instances in which the Reactor Building Purge is on, the setpoint is multiplied by 0.65 (65,000 cfm/ (65,000 cfm + 35,000 cfm purge flow)).3.0.2.2 RADWASTE FACILITY SETPOINTS (4RIA-45)4R/ 4- 45 =25 4.72E+02 x 1.297E+05 x 2.94E+02 x 7.308E-06 4R/A -45 1.90E -04 1 tCi/ml where: 25 = 5% of the 500 mrem/yr total body release rate limit.1.297E+05
= Radwaste Facility Vent flow rate, ft 3/min.7.308E-06
= Highest Ground-Level release point dispersion factor, sec/r 3.All other factors were previously defined.4RIA-45 reads in units of concentration, iiCi/ml. 'Section 3 -Page 8 Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 3.0.2.3 INTERIM RADWASTE BUILDING SETPOINTS RIA-53-= 25 4.72E + 02 x 1.5E + 04 x 2.94E + 02 x 7.308E -06 x 3.4E -08 RIA -53 4.8E + 04 cpm + bkg where: 25 = 5% of the 500 mrem/yr total body release rate limit.1.5E+04 = Interim Radwaste Building Vent flow rate, ft 3/min.7.308E-06
= Highest Ground-Level release point dispersion factor, sec/m 3.3.4E-08 = RIA-53 Correlation Factor, gICi/ml/cpm.
All other factors were previously defined.In addition to the maximum setpoints discussed previously, Oconee.uses "Alert" setpoints that are based on 10% of the reporting requirement from 1OCFR50.73(a)(2)(viii)(A).
Each unit vent Alert setpoint is based on 60% of a Xe-133 Effluent Concentration (EC)value of 5.OE-07 &#xfd;tCi/ml at the site boundary.
The Interim Radwaste Building and Radwaste Facility are each set at 10% of the Xe-133 EC. The method usedto calculate the Alert setpoints is similar to that used to calculate the maximum setpoints except that the limit is based on concentration rather than. dose rate. The Alert setpoints are approximately 42% of the maximum setpoints.
3.0.2.4 WASTE GAS DECAY TANK SETPOINTS (RIA-37 and RIA-38)For batch releases where the effluent can contain activity significantly above background, e.g., Waste Gas Decay Tank (WGDT),'two additional monitors, RIA-37 and RIA-38 are used to establish setpoints for each WGDT batch released.
RIA-37 is the normal/low range noble gas monitor, and RIA-38 is the high range noble gas monitor. The following setpoint methodology is used: CXe -3 = 1 (c x Eq,)CXe -133 Expected Cpm = + bkg CFXe -133 RIA -37 and RIA -38 Setpoint -Cx&#xfd; -133 x 1.5 Equation 3.7 SCFXe- 133 Section 3 -Page 9 Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 where: CXe-133 = Xe-133 equivalent concentration of the WGDT to be released, in itCi/ml.Eqi = Xe-133 equivalence factor for each noble gas isotope, excluding tritium, to that of Xe-133 due to different beta energies and abundance.(See Table 3.0-2).CFxe-3 3.= The expected RIA response to a given Xe-133 equivalent concentration, in[tCi/ml/cpm.
1RIA-37.=
4.20E-08 &#xfd;tCi/ml/cpm, 3RIA-37 = 4.20E-08 ptCi/ml/cpm, 1RIA-38 and 3RIA-38 = 1.34E-03 ptCi/ml/cpm.
1.5 = An adjustment factor to account for expected minor variations in effluent concentration and RIA background.
bkg = The radiation monitor background reading, in cpm.When the release pathway is from any Unit I WGDT (A-D); and the Xe-13,3 equivalent concentration is less than 2.8E tCi/ml, the 1&2 RIA-38. setpoint is established at 313 cpm, and the 1&2 RIA-37 setpoint is calculated using Equation 3.7.When the release pathway is from any Unit 1 WGDT (A-D), and the Xe-133 equivalent concentration is greater than 2.8E-01 j&#xfd;tCi/ml, the 1&2 RIA-37 setpoint is established as offscale high, and the 1 &2 RIA-38 setpoint is calculated using Equation 3.7.When the release pathway is from any. Unit 3 WGDT (A-C), and the Xe-133 equivalent concentration is less than 2.8E-01 jtCi/ml, the 3 RIA-38 setpoint is established at 313 cpm, and the 3 RIA-37 setpoint is calculated using Equation 3.7..When the release pathway is from any Unit 3 WGDT (A-C), and the Xe-133 equivalent concentration is greater than 2.8E-01 lICi/ml, the 3 RIA-37 setpoint is established as offscale high, and the 3 RIA-38 setpoint is calculated using Equation 3.7.When there are no noble gases present in the WGDT sample, the RIA-37 setpoint is set to five times (5X) the RIA-37 background reading.Section 3 -Page 10 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)January, 2009 Revision 49 Table 3.0-2 Xe-133 Equivalents Isotope Equivalence Factr" Kr-83m 0 Kr-85m 2.48 Kr-85 2.56 Kr-87 2.93 Kr-88 2.78 Kr-89 2.93 Kr-90 2.93 Xe-131m 1.69 Xe-133m 1.99 Xe-133 1.0 Xe-135m 0.83 Xe-135 2.63 Xe-137 2.93 Xe-138 2.93 Ar-41 2.82 C-11 2.70 Section 3 -Page 11 Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 4.0 EFFLUENT DOSE MODELS The effluent dose models used to show compliance with I OCFR50, Appendix I ALARA design objectives, 40CFR190 fuel cycle dose limits, and the dose values given in station SLCs are based on the methodology given in NUREG-0 133 and Regulatory Guide 1.109.Dose contributions to the maximum individual shall be calculated at least every 31 days, quarterly, and annually using the RETDAS computer code which implements the ODCM methodology.
RETDAS, Radioactive Effluent Tracking and Dose Assessment Software, is a database application designed by Canberra Industries, Inc. to automate many of the tasks required in the administration of effluent releases at Oconee. RETDAS performs normal operation effluent dose assessment using NUREG-0133 and Regulatory Guide 1.109 methodology.
Station long-term historical and dose projection calculations are performed-periodically to determine the station's status with respect to meeting annual ALARA goals specified in the Oconee SLCs. Such calculations are used to verify that adequate margin remains during a report period to allow normal station and radwaste system operation, including anticipated operational occurrences, for the remainder of the report period without exceeding applicable goals. Station 31-day dose projections that are used to assess the need to reduce effluent releases with the Gaseous Waste (GW) or Liquid Waste (LW)systems as required in the Oconee SLCs are estimated by the previous month's calculated dose results.Fuel cycle dose calculations shall be performed annually or as required by special reports.Dose contributions shall be calculated using the RETDAS computer program.4.0.1 LIQUID EFFLUENT DOSE MODEL FOR THE MAXIMUM EXPOSED INDIVIDUAL Of the possible exposure pathways in the aquatic environment, only three contribute significantly to the total dose; these pathways are ingestion of potable water and aquatic foods, and direct exposure from radioactivity deposited on the shoreline.
The dose contribution from these pathways for measured quantities of radioactive materials identified in liquid effluents released to unrestricted areas. shall be calculated for the maximum exposed individual in each age group using the methodology provided in this section.Liquid waste processed by the LW system can be released to the environment at Oconee from two liquid discharge points; (1) directly to the Keowee Tailrace through RIA-33 and (2) to the Chemical Treatment Pond #3 discharge point into the Keowee River (See Figure 2.0-1). Liquid dose calculations for the maximum exposed individual are performed and documented in the Annual Effluent Release Report for both locations using the applicable activity release and dilution data for each liquid effluent release point. The primary liquid effluent discharge point for Oconee is to the Keowee Tailrace Section 4 -Page 1 Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 through RIA-33. In general, only low activity tritium releases (<1% station total) occur through the Chemical Treatment Pond #3 discharge point into the Keowee River. Dose calculations are performed for each of the two liquid discharge points for dose reporting purposes.
The highest calculated dose from the two dose calculations is used to define the maximum individual dose from liquid releases at Oconee.Section 4 -Page 2 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)January, 2009 Revision 49 Liquid Dose Calculations The following equation is used for calculating liquid dose to the maximum exposed individual at each of the two liquid effluent release points: Doseoa = I-I A, x xC)XAtXFn X Ix p i f X Ffxo f+F L.w Formula: adapted from NUREG-0133; pages 15-17. Where: Doseoa The cumulative dose commitment for organ o and age group a, from the liquid effluent for the total time period, At. (mrem)Aoapi Dose commitment factor for organ o, age group a, pathway p, and nuclide i (mrem/hr per jtCi/ml). (See Appendices C through F for age group and pathway specific dose commitment factors).Ci The average concentration of nuclide i, in undiluted liquid effluent during the time period, At. (.tCi/ml)At The length of time over which Ci and F, are averaged for all liquid releases. (hr)F, The near field average dilution factor for Ci during the period of interest, At. Includes the recirculation factor. (dimensionless) f Average liquid radwaste flow during the period of interest, At. (gpm)F Average dilution flow during the period of interest, At. (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.a Recirculation factor. (dimensionless)
*Dw Dilution factor from the near field area to the potable water intake;= 30.0 for Oconee. This factor applies to the potable water pathway only. The nearest potable water intake to Oconee is located at the Andersen water intake approximately 31.5 miles from the site on a separate arm of Lake Hartwell.
From a hydrology standpoint the Andersen water intake should not be significantly affected by liquid effluent discharges from Oconee. 30.0 is a conservatively small dilution factor based on environmental sample data.* The recirculation factor accounts for the fraction of discharged water reused by the station. Liquid effluent discharge cannot be recirculated back into the Oconee station.Therefore, the recirculation factor is 1.0 at Oconee.Section 4 -Page 3 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)January, 2009 Revision 49 Derivation of Liquid Dose Commitment Factors (Aoapi)Potable Water Aoapi =w1. 14x10' x xDaoixe-&to Formula:.
from NUREG-0133, page 16 and Regulatory Guide 1.109, page 1.109-12.-Where: Aoapi Dose commitment factor for organ o, age group a, pathway p, and nuclide i, (mrem/hr per ptCi/ml). (See Appendices C through F for age group and pathway specific dose commitment factors).1.14x 10 5 Units conversion factor (pCi-yr-ml)/(utCi-hr-kg).
Uaw Water consumption rate in liters per year for age group a. From Table E-5, Regulatory Guide 1.109.Adult -730 Teen -510 Child-510 Infant -330 Daoi Dose factor for age group a, organ o, nuclide i, in mrem/pCi.
From_ _tables E- I1 through E- 14 of Regulatory Guide 1.109.ki Decay constant for nuclide i, in sec-.tp Environmental transit time from release to receptor.
Default =4.32E+04 sec (12 hours). From Regulatory Guide 1.109, Table E-15.Section 4 -Page 4 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)January, 2009 Revision 49 Aquatic Foods A -=1.14x10 5 xUa' xBFxDaoix et Aoapi af Formula: from NUREG-0133, page 16 and Regulatory Guide 1.109, page 1.109-12-Where: Aoapi Dose commitment factor for organ o, age group a, pathway p, and nuclide i, (mrem/hr per ltCi/ml).
' (See Appendices C through F for age group and pathway specific dose commitment factors)..1 4xx 105 Units conversion factor (pCi-yr-ml)/(&#xfd;iCi-hr-kg).
Uaf Fish consumption rate for age group a (kg/yr). From Table E-5, Regulatory Guide 1.109.Adult -21 Teen -16 Child -6.9 Infant -0 BFi Bioaccumulation factor for nuclide i, in fish, in units of pCi/kg per pCi/liter.
From Table A-I of Regulatory Guide 1.109.Daoi Dose factor for age group a, organ o, nuclide i, in mrem/pCi.
From tables E- 11 through E-14 of Regulatory Guide 1.109.Xi Decay constant for nuclide i, in sec-.tp Environmental transit time from release to receptor.
Default =8.64E+04 sec (1 day). From Regulatory Guide 1.109, Table E-15.Section 4 -Page 5 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)January, 2009 Revision 49 Shoreline Sediment Aoapi =1.14x0 5 xlOOxDFGoiXWxUasxT xI e x(I e-tb Formula::
adapted from Regulatory Guide 1.109, page 1.109-14.Where: Aoapi Dose commitment factor for organ o, age group a, pathway p, and nuclide i, (mrem/hr per pCi/ml). (See Appendices C through F for age group and pathway specific dose commitment factors).1.14x 105 Units conversion factor (pCi-yr-ml)/(ptCi-hr-kg).
100 Proportionality constant used in the sediment radioactivity model, (liters/(m 2-day).DFGoi Ground plane dose conversion factor for organ o, nuclide i (mrem/hr per pCi/mi 2), from Table E-6 of Regulatory Guide 1.109.w Shoreline width factor. For Oconee = 0.2, from Table A-2, Regulatory Guide 1.109.U. Shoreline exposure rate for age group a (hr/yr), From Table E-5, Regulatory Guide 1.109.Adult -12 Teen -67 Child- 14 Infant -0 Ti'/ Nuclide half life for nuclide i, in days.,i Nuclide decay constant for nuclide i.tp Average transit time to point of exposure (0 hours).tb Sediment exposure time (15 years). Page 1.109-14.Section 4 -Page 6 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)January, 2009 Revision 49 4.0.2 GASEOUS EFFLUENT DOSE MODEL FOR THE MAXIMUM EXPOSED INDIVIDUAL The dose contributions from measured quantities of radioactive materials identified in gaseous effluent released to unrestricted areas shall be calculated for the maximum gamma and beta air dose from noble gases, and for the maximum exposed individual from radioiodines, particulates, and others using the following equations:
Gaseous Dose Calculations Noble Gas Dose Calculations Gamma Air Dose Dose, =3.17x10-8 xz/QX -(MixQ i)Formula: adapted from:NUREG-0133, page 28.Where: Dosey Gamma air dose for the time period of interest (mrad).3.17x 10-8 Inverse number of seconds in year (year/seconds).
Mi Gamma air dose factor due to gamma emissions for nuclide i (mrad/yr per &#xfd;LCi/m3). (See Appendix A).z/Q The highest calculated annual average relative concentration for any.Iarea at or beyond the site boundary (sec/m 3)*. (See Table 6.0-9). I Qi Activity for nuclide i released during the time period of interest (UtCi).Beta Air Dose Dosef =3.17x10-8 x /Qxj(Nx Q,)Formula: adapted from NUREG-0133, page 28.Where: Doser3 Beta air dose for the time period of interest (mrad).3.17x 10-8 Inverse number of seconds in year (year/seconds).
Ni Beta air dose factor due to beta emissions for nuclide i (mrad/yr per&#xfd;LCi/m 3). (See Appendix A).x/Q The highest calculated annual average relative concentration for any area at or beyond the site boundary (sec/m 3)*. (See Table 6.0-9).Qi Activity for nuclide i released during the time period of interest (&#xfd;tCi).0 Section 4 -Page 7 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)Iodine, Particulates, and H-3 Dose Organ Dose Calculation Dose oa = 3.17 x lO-8 x W x Y (Roapi X QJ)p i January, 2009 Revision 49 Formula: adapted from NUREG-0133, pages 29`& 30.Where: Doseoa The cumulative dose commitment to the total body or any organ o, for an individual of age group a (mrem).3.17x 10-8 Inverse number of seconds in year (year/seconds).
Roapi Dose commitment factor for organ o, age group a, pathway p, and nuclide i. The units are based on whether a dispersion or deposition factor is used. When a x,/Q is used the units are.mrem/yr per ltCi/m 3.When a D/Q is used the units are (M 2 mrem/yr) per &#xfd;tCi/sec. (See Appendices G through J for age group and pathway specific dose commitment factors).W Dispersion (x/Q) or deposition factor (D/Q)*. The factor used is based upon the pathway. Note: X/Q is always used for tritium.Pathway Factor Used Ground Plane Deposition D/Q (m 2)Inhalation X/Q (sec/m 3)Vegetation D/Q (m-2)Grass/Cow/Milk D/Q (m-2)Grass/Goat/Milk D/Q (m 2)Grass/Cow/Meat D/Q (m-2)Qi Activity for nuclide i, released during the time period of interest (ltCi).* The dose from noble gases released from semi-elevated release points, e.g., unit vent, is calculated using the semi-elevated dispersion factors. The dose from noble gases released from ground level release points, e.g., Radwaste Facility vent, is calculated using the ground level dispersion factors. The total dose is the sum of the semi-elevated and ground level dose calculations.
Maximum individual organ dose is determined by calculating the organ dose at each of the x/Q and D/Q locations shown in Table 6.0-9 and'Table 6.0-10 (128 locations) for both semi-elevated release points and ground level release points, summing the two at each location, and then choosing the dose from the maximum location.
Dose is calculated only for those pathways (e.g., garden, milk animal, etc.) that actually exist at each location as determined by the land use census shown in Table 6.0-3. As discussed in Oconee UFSAR Section 2.1.1.3, the boundary for establishing gaseous effluent release limits is the exclusion area boundary (EAB). The EAB is defined as a I mile radius from the station center.Section 4 -Page 8 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)January, 2009 Revision 49 Derivations of Iodine, Particulate, and H-3 Dose Commitment Factors (Roapi)Ground Plane Denosition Pathway Roapi =K'K"(SF)DFGOI i A Formula: from NUREG-0133, page 32.Where: Roapi Dose commitment factor for organ o, age group a, nuclide i, for ground plane deposition pathway (m 2 mrem/yr per jtCi/sec). (See Appendices G through J for age group and pathway specific dose commitment factors).K' Units conversion factor pCi/&#xfd;tCi (1.06).K" Units conversion, factor 8760 hr/year.SF Shielding factor (dimensionless)
(0:7, from Regulatory Guide 1.109).DFGoi Ground plane dose conversion factor for organ o, nuclide i (mrem/hr per pCi/mr 2), from Table E-6 of Regulator:
Guide 1.109.Nuclide decay constant for nuclide i (sec-).t Exposure time, 4.73xx108 seconds (15 years).Inhalation Pathway Roapi: K'(BRa )(DFAoi )a Formula: from NUREG-0133, page 31.Where: Roapi Dose commitment factor for organ o, age group a, nuclide i, for inhalation pathway (mrem/yr per uiCi/m 3).. (See Appendices G through J for age group and pathway specific dose commitment factors).K' Units conversion factor pCi/pCi (106).BRa Breathing rate for age group (m 3/yr), from Regulatory Guide 1.109: Adult -8000 Teen -8000 Child -3700 Infant -1400 (DFAoi)a Organ inhalation factor dose conversion factor for. organ o, nuclide i, age group a (mrem/pCi), from Tables E-7 through E-10 of Regulatory Guide 1.109.Section 4 -Page 9 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)January, 2009 Revision 49 Vegetation Roap= K1L (r) x(DFL oJ)a x [ULfLeAAtL  
+ U fge~2At/ ]Yv+, +A)Formula: from NUREG-0133, page 35. .Where: Roapi Dose commitment factor for organ o, age group a, nuclide i, for vegetation pathway (m 2.mrem/yr per pCi/sec). (See Appendices G through J for age group and pathway specific' dose commitment factors).K' Units conversion factor pCi/pCi (106).r Fraction of deposited activity retained on vegetation, from Regulatory Guide 1.109.1.0 for radioiodine.
0.2 for particulates.
0.2 for particulates.
Yv Vegetation areal density (kg/m 2) (2.0, from Regulatory Guide 1.109).'Xi Nuclide decay constant for nuclide i (secl).kw. Decay constant for removal of activity on leaf and plant surfaces by weathering (5.73 x 107 set-', from NUREG-0 133).(DFLoi)a Ingestion dose conversion factor for nuclide i, organ o, and age group a, from' Tables E- 11 through E- 14 of Reg. Guide 1.109 (mrem/pCi).
Yv   Vegetation areal density (kg/m 2) (2.0, from Regulatory Guide 1.109).
ULa Consumption rate of fresh vegetation for age group a (kg/yr) (from Regulatory Guide 1.109).Adult -64 Teen -42 Child- 26 Infant -0 fL Fraction of annual~intake of fresh leafy vegetation grown locally (1.0, fromNUREG-0133).'
                'Xi   Nuclide decay constant for nuclide i (secl).
tL Average time between harvest of leafy vegetation and consumption 1 (8.6x 104 seconds, (1 day), from Regulatory Guide 1.109).USa Consumption rate of stored vegetation for age group a (kg/yr) (from Regulatory Guide 1.109).Adult -'520 Teen -630 Child -520 Infant- 0 fg Fraction of annual intake of stored vegetation (0.76, from Regulatory Guide 1.109).th Average time between harvest of stored vegetation and consumption (5.18x 106 seconds, (60 days), from Regulatory Guide 1. 109).Section 4 -Page 10 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)January, 2009 Revision 49 Vegetation  
kw. Decay constant for removal of activity on leaf and plant surfaces by weathering (5.73 x 107 set-', from NUREG-0 133).
-Tritium Roapi --' K'"[ LU U +U fg](DFLo 0[0.75(O.5  
(DFLoi)a     Ingestion dose conversion factor for nuclide i, organ o, and age group a, from' Tables E- 11 through E- 14 of Reg. Guide 1.109 (mrem/pCi).
/ H)]Formula: from NUREG-0133, page 36.Where: Roapi Dose commitment factor for organ o, age group a, for vegetation pathway and tritium (mrem/yr per &#xfd;tCi/m 3(See Appendices G through J for age group and pathway specific dose commitment factors).K' Units conversion factor pCi/!tCi (106).K.' Units conversion factor gm/kg (103).ULa Consumption rate of fresh vegetation for age group a (kg/yr) (from Regulatory Guide 1.109).Adult -64 Teen -42 Child -26 Infant -0 fL Fraction of annual intake of fresh leafy vegetation grown locally (1.0, from NUREG-0133).
ULa     Consumption rate of fresh vegetation for age group a (kg/yr) (from Regulatory Guide 1.109).
Usa Consumption rate of stored vegetation for age group a (kg/yr) (from RegulatoryGuide 1.109).Adult -520 Teen -630 Child -520 Infant -0 fg Fraction of annual intake of stored vegetation (0.76, from Regulatory Guide 1.109).(DFLoi)a Ingestion dose conversion factor for nuclide i, organ o, and age group a, from Tables E-11 through E-14 of Regulatory Guide 1.109 (mrem/pCi).
Adult - 64 Teen - 42 Child- 26 Infant - 0 fL   Fraction of annual~intake of fresh leafy vegetation grown locally (1.0, fromNUREG-0133).'
0.75 "Fraction of total feed that is water, (From NUREG-0 133).0.5 Ratio of specific activity of feed grass water to atmospheric water.(From NUREG-0 133).H Absolute humidity of the atmosphere (8 gm/m 3 , from Reghlatory Guide 1.109).Section 4 -Page 11 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)Grass/Cow/Milk January, 2009 Revision 49 RoUp, = K ' Q F (U p ) F4, (r)( DFL j ) , f 1 +Ai + A2 F Yp 7fpf,)e- A'&#xfd;~ ]e -Formula: from NUREG-0133, pages 32 & 33. Where: Roapi Dose commitment factor for organ o, age group a, nuclide i, for grass/cow/milk pathway (mEmrem/yr per tCi/sec). (See Appendices G through J for age group and pathway specific dose commitment factors).K' Units conversion factor pCi/[Ci (106).QF Cow consumption rate (50 kg/day, from Regulatory Guide 1.109)Uap Consumption rate of cow milk for age group a (liters/yr, from Regulatory Guide 1.109).Adult -310 Teen- 400 Child -330 Infant -300 r Fraction of deposited activity retained on cow's feed grass, (from Regulatory Guide 1.109).1.0 for radioiodine.
tL   Average time between harvest of leafy vegetation and consumption 1 (8.6x 104 seconds, (1 day), from Regulatory Guide 1.109).
USa     Consumption rate of stored vegetation for age group a (kg/yr) (from Regulatory Guide 1.109).
Adult -'520 Teen -630 Child - 520 Infant- 0 fg   Fraction of annual intake of stored vegetation (0.76, from Regulatory Guide 1.109).
th Average time between harvest of stored vegetation and consumption (5.18x 106 seconds, (60 days), from Regulatory Guide 1. 109).
Section 4 - Page 10
 
Oconee Nuclear Station                                                         January, 2009 Offsite Dose Calculation Manual (ODCM)                                           Revision 49 Vegetation - Tritium Roapi -- ' K'"[ LU               +UU fg](DFLo0[0.75(O.5 / H)]
Formula: from NUREG-0133, page 36.
Where:
Roapi   Dose commitment factor for organ o, age group a, for vegetation pathway and tritium (mrem/yr per &#xfd;tCi/m 3)* (See Appendices G through J for age group and pathway specific dose commitment factors).
K'   Units conversion factor pCi/!tCi (106).
K.'     Units conversion factor gm/kg (103).
ULa     Consumption rate of fresh vegetation for age group a (kg/yr) (from Regulatory Guide 1.109).
Adult - 64 Teen - 42 Child - 26 Infant - 0 fL   Fraction of annual intake of fresh leafy vegetation grown locally (1.0, from NUREG-0133).
Usa     Consumption rate of stored vegetation for age group a (kg/yr) (from RegulatoryGuide 1.109).
Adult - 520 Teen - 630 Child - 520 Infant - 0 fg   Fraction of annual intake of stored vegetation (0.76, from Regulatory Guide 1.109).
(DFLoi)a     Ingestion dose conversion factor for nuclide i, organ o, and age group a, from Tables E-11 through E-14 of Regulatory Guide 1.109 (mrem/pCi).
0.75   "Fraction of total feed that is water, (From NUREG-0 133).
0.5   Ratio of specific activity of feed grass water to atmospheric water.
(From NUREG-0 133).
H     Absolute humidity of the atmosphere (8 gm/m3 , from Reghlatory Guide 1.109).
Section 4 - Page 11
 
Oconee Nuclear Station                                                             January, 2009 Offsite Dose Calculation Manual (ODCM)                                             Revision 49 Grass/Cow/Milk RoUp,   = K ' QAiF (U+ A2p ) F4, F    (r)( DFL     j)       f
                                                        , Yp  + 1 7fpf,)e-   A'&#xfd;~ ]e -
Formula: from NUREG-0133, pages 32 & 33. Where:
Roapi   Dose commitment factor for organ o, age group a, nuclide i, for grass/cow/milk pathway (mEmrem/yr per tCi/sec). (See Appendices G through J for age group and pathway specific dose commitment factors).
K'   Units conversion factor pCi/[Ci (106).
QF     Cow consumption rate (50 kg/day, from Regulatory Guide 1.109)
Uap     Consumption rate of cow milk for age group a (liters/yr, from Regulatory Guide 1.109).
Adult - 310 Teen- 400 Child - 330 Infant - 300 r   Fraction of deposited activity retained on cow's feed grass, (from Regulatory Guide 1.109).
1.0 for radioiodine.
0.2 for particulates.
0.2 for particulates.
Yp Agricultural productivity by unit area of pasture feed grass (0.7 kg/m 2 , from Regulatory Guide 1.109).Ys Agricultural productivity by unit area of stored feed (2.0 kg/m 2 , from Regulatory Guide 1.109).Nuclide decay constant for nuclide i (sec-1).Decay constant for removal of activity on leaf and plant surfaces by weathering (5.73x 1 0-7 sec-1 , from NUREG-0 133).(DFLoi)a Ingestion dose conversion factor for nuclide i, organ o, and age group a, from Tables E-1 1 through E-14 of Regulatory Guide 1.109 (mrem/pCi).
Yp     Agricultural productivity by unit area of pasture feed grass (0.7 kg/m2 , from Regulatory Guide 1.109).
Fmi Stable element transfer coefficient for nuclide i, in days/liter, from Table E- I of Regulatory Guide 1.109 for cow milk.fp Fraction of year that the cow is on pasture (1.0, from RG 1.109).fs Fraction of the cow feed that is pasture grass while the cow is on pasture (1.0, from Regulatory Guide 1.109).tf Transport time for pasture to cow, to milk, to receptor (1.73E+05 seconds, from Regulatory Guide 1.109).th Transport time from pasture, to harvest, to cow, to milk, to receptor (7.78e+06 seconds, from Regulatory Guide 1.109).Section 4 -Page 12 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)January, 2009 Revision 49 Grass/Cow/Milk
Ys   Agricultural productivity by unit area of stored feed (2.0 kg/m2 , from Regulatory Guide 1.109).
-Tritium Roapi K' K' FmiQfUap (DFLio)a [0.75(0.5
X*    Nuclide decay constant for nuclide i (sec-1).
/ H)]Formula: from NUREG-0133, page 34.Where: Roapi Dose commitment factor for organ o, age group a, nuclide i, for grass/cow/milk pathway (mrem/yr per &#xfd;tCi/m 3). (See Appendices G through J for age group and pathway specific dose commitment factors).K' Units conversion factor pCi/pCi (106).K"' Units conversion factor im/kg (10 3).QI Cow consumption rate (50 kg/day, from Regulatory Guide 1.109).Uap Consumption rate of cow milk for age group a (liters/yr, from Regulatory Guide 1.109).Adult -310 Teen- 400 Child -330 Infant -300 (DFLoi)a Ingestion dose conversion factor for nuclide i, organ o, and age group a, from Tables E- I1 through E-14 of Regulatory Guide 1.109 (mrem/pCi).
X*    Decay constant for removal of activity on leaf and plant surfaces by weathering (5.73x 10-7 sec- 1, from NUREG-0 133).
Fmi Stable element transfer coefficient for nuclide i, in days/liter, from Table E-1 of Regulatory Guide 1.109 for cow milk.0.75 Fraction of total feed that is water (from NUREG-0133).
(DFLoi)a     Ingestion dose conversion factor for nuclide i, organ o, and age group a, from Tables E-1 1 through E-14 of Regulatory Guide 1.109 (mrem/pCi).
Fmi     Stable element transfer coefficient for nuclide i, in days/liter, from Table E- I of Regulatory Guide 1.109 for cow milk.
fp   Fraction of year that the cow is on pasture (1.0, from RG 1.109).
fs   Fraction of the cow feed that is pasture grass while the cow is on pasture (1.0, from Regulatory Guide 1.109).
tf Transport time for pasture to cow, to milk, to receptor (1.73E+05 seconds, from Regulatory Guide 1.109).
th   Transport time from pasture, to harvest, to cow, to milk, to receptor (7.78e+06 seconds, from Regulatory Guide 1.109).
Section 4 -Page 12


===0.5 Ratio===
Oconee Nuclear Station                                                            January, 2009 Offsite Dose Calculation Manual (ODCM)                                            Revision 49 Grass/Cow/Milk - Tritium Roapi      K' K' FmiQfUap(DFLio)a[0.75(0.5 / H)]
of specific activity of feed grass water to atmospheric water (from NUREG-0133).
Formula: from NUREG-0133, page 34.
H Absolute humidity of the atmosphere (8 gm/mi 3 , from Regulatory I Guide 1.109).Section 4 -Page 13 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)January, 2009 Revision 49 Grass/Goat/Milk Roapi = K F Fmi(r)(DFLoi)a.fpI  
Where:
+ (I- f)e e ,t Formula: from NUREG-0133, pages 32 & 33. Where: Roapi Dose commitment factor for organ o, age group a, nuclide i, for grass/goat/milk pathway (mnimrem/yr per (See Appendices G through J for age group and pathway specific dose commitment factors), K' Units conversion factor pCi/&#xfd;tCi (106).QF Goat consumption rate (6 kg/day, from Regulatory Guide 1.109).Uap Consumption rate of goat milk for age group a (liters/yr, from Regulatory Guide 1.109).Adult -310 Teen- 400 Child -330 Infant- 300 r Fraction of deposited activity retained on goat's feed grass, from Regulatory Guide 1.109.1.0 for radioiodine.
Roapi    Dose commitment factor for organ o, age group a, nuclide i, for grass/cow/milk pathway (mrem/yr per &#xfd;tCi/m 3). (See Appendices G through J for age group and pathway specific dose commitment factors).
K' Units conversion factor pCi/pCi (106).
K"' Units conversion factor im/kg (103 ).
QI Cow consumption rate (50 kg/day, from Regulatory Guide 1.109).
Uap Consumption rate of cow milk for age group a (liters/yr, from Regulatory Guide 1.109).
Adult - 310 Teen- 400 Child - 330 Infant - 300 (DFLoi)a Ingestion dose conversion factor for nuclide i, organ o, and age group a, from Tables E- I1through E-14 of Regulatory Guide 1.109 (mrem/pCi).
Fmi    Stable element transfer coefficient for nuclide i, in days/liter, from Table E-1 of Regulatory Guide 1.109 for cow milk.
0.75 Fraction of total feed that is water (from NUREG-0133).
0.5 Ratio of specific activity of feed grass water to atmospheric water (from NUREG-0133).
H Absolute humidity of the atmosphere (8 gm/mi3, from Regulatory I Guide 1.109).
Section 4 - Page 13
 
Oconee Nuclear Station                                                         January, 2009 Offsite Dose Calculation Manual (ODCM)                                         Revision 49 Grass/Goat/Milk Roapi   =K     F             Fmi(r)(DFLoi)a.fpI + (I-             f)e       e   ,t Formula: from NUREG-0133, pages 32 & 33. Where:
Roapi   Dose commitment factor for organ o, age group a, nuclide i, for grass/goat/milk pathway (mnimrem/yr per *tCi/sec). (See Appendices G through J for age group and pathway specific dose commitment factors),
K' Units conversion factor pCi/&#xfd;tCi (106).
QF Goat consumption rate (6 kg/day, from Regulatory Guide 1.109).
Uap     Consumption rate of goat milk for age group a (liters/yr, from Regulatory Guide 1.109).
Adult - 310 Teen- 400 Child - 330 Infant- 300 r Fraction of deposited activity retained on goat's feed grass, from Regulatory Guide 1.109.
1.0 for radioiodine.
0.2 f6r particulates.
0.2 f6r particulates.
Yp Agricultural productivity by unit area of pasture feed grass (0.7 kg/m 2 , from Regulatory Guide 1.109).Y, Agricultural productivity by unit-area of stored feed (2.0 kg/m 2 , from Regulatory Guide 1.109).Nuclide decay constant for nuclide i (sec-).Decay constant for removal of activity on leaf and plant surfaces by weathering (5.73x 10-7 sec-1 , from NUREG-0 133).(DFLoi)a Ingestion dose conversion factor for nuclide i, organ o, and age group a, from Tables E-Il through E-14 of Regulatory Guide 1.109 (mrem/pCi).
Yp Agricultural productivity by unit area of pasture feed grass (0.7 kg/m2 , from Regulatory Guide 1.109).
Fmi Stable element transfer coefficient for nuclide i, in days/liter, from Table E-2 of Regulatory Guide 1.109 for goat milk.f 0 Fraction of year that the goat is on pasture (1.0, from RG 1.109).f, Fraction of the goat feed that is pasture grass while the goat is on pasture (1.0, from Regulatory Guide 1.109).tf Transport time for pasture to goat, to milk, to receptor (1.73E+05' seconds, from Regulatory Guide 1.109).th Transport time from pasture, to harvest, to goat, to milk, to receptor I (7.78e+06 seconds, from Regulatory Guide 1.109).Section 4 -Page 14 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)January, 2009 Revision 49 Grass/Goat/Milk  
Y, Agricultural productivity by unit-area of stored feed (2.0 kg/m 2, from Regulatory Guide 1.109).
-Tritium Roapi =K'K"'FmiQfUap(DFLoi)a[0.75(0.&#xfd;51/H)]
X* Nuclide decay constant for nuclide i (sec-).
Formula: from NUREG-0133, page 34.!Where: Roapi Dose commitment factor for organ o, age group a, nuclide'i, for grass/goat/milk pathway (mrem/yr per &#xfd;tCi/m 3): (See Appendices G through J for age group and pathway specific dose commitment factors).K'. Units conversion factor pCi/[LCi (106).K"' Units conversion factor gm/kg (103).QF Goat consumption rate (6 kg/day, from Regulatory Guide 1.109).Uap Consumption rate of goat milk for age group a (liters/yr, from Regulatory Guide 1.109).Adult -310 Teen- 400 Child -330 Infant -300 (DFLoi)a Ingestion dose conversion factor for nuclide i, organ o, and age group a, from Tables E- 11 through E- 14 of Regulatory Guide 1.109 (mrem/pCi).
X* Decay constant for removal of activity on leaf and plant surfaces by weathering (5.73x 10-7 sec-1 , from NUREG-0 133).
Fmi Stable element transfer coefficient for nuclide i, in days/liter, from Table E-2 of Regulatory Guide 1.109 for goat milk.0.75 Fraction of total feed that is water (from NUREG-0 133).0.5 Ratio of specific activity of feed grass water to atmospheric water (from NUREG-0133).
(DFLoi)a Ingestion dose conversion factor for nuclide i, organ o, and age group a, from Tables E-Il through E-14 of Regulatory Guide 1.109 (mrem/pCi).
H Absolute humidity of the atmosphere (8 gm/m 3 , from Regulatory I Guide 1.109).Section 4 -Page 15 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)January, 2009 Revision 49 Grass/Cow/Meat K' QF(Uap) [ff (1 -fpf-)e,-Ath eAt Fapi K (r)(DFLIL f) f Formula: from NUREG-0133,:pages-34  
Fmi Stable element transfer coefficient for nuclide i, in days/liter, from Table E-2 of Regulatory Guide 1.109 for goat milk.
& 35. Where: Roapi Dose commitment factor for organ o, age group a, nuclide i, for grass/cow/meat pathway (m 2"mrem/yr per &#xfd;tCi/sec). (See Appendices G through J for age group and pathway specific dose commitment factors).K' Units conversion factor pCi/&#xfd;tCi (106).QF Cow consumption rate (50 kg/day, from Regulatory Guide 1.109).Uap Consumption rate of cow meat for age group a (kg/yr, from Regulatory Guide 1.109).Adult.- 110 Teen- 65 Child -41 Infant -0 r Fraction of deposited activity retained on cow's feed grass (from Regulatory Guide 1.109).1.0 for radioiodine.
f0 Fraction of year that the goat is on pasture (1.0, from RG 1.109).
f, Fraction of the goat feed that is pasture grass while the goat is on pasture (1.0, from Regulatory Guide 1.109).
tf Transport time for pasture to goat, to milk, to receptor (1.73E+05' seconds, from Regulatory Guide 1.109).
th   Transport time from pasture, to harvest, to goat, to milk, to receptor I (7.78e+06 seconds, from Regulatory Guide 1.109).
Section 4 -Page 14
 
Oconee Nuclear Station                                                       January, 2009 Offsite Dose Calculation Manual (ODCM)                                       Revision 49 Grass/Goat/Milk - Tritium Roapi =K'K"'FmiQfUap(DFLoi)a[0.75(0.&#xfd;51/H)]
Formula: from NUREG-0133, page 34.!
Where:
Roapi   Dose commitment factor for organ o, age group a, nuclide'i, for grass/goat/milk pathway (mrem/yr per &#xfd;tCi/m 3): (See Appendices G through J for age group and pathway specific dose commitment factors).
K'. Units conversion factor pCi/[LCi (106).
K"' Units conversion factor gm/kg (103).
QF Goat consumption rate (6 kg/day, from Regulatory Guide 1.109).
Uap Consumption rate of goat milk for age group a (liters/yr, from Regulatory Guide 1.109).
Adult - 310 Teen- 400 Child - 330 Infant - 300 (DFLoi)a Ingestion dose conversion factor for nuclide i, organ o, and age group a, from Tables E- 11 through E- 14 of Regulatory Guide 1.109 (mrem/pCi).
Fmi Stable element transfer coefficient for nuclide i, in days/liter, from Table E-2 of Regulatory Guide 1.109 for goat milk.
0.75 Fraction of total feed that is water (from NUREG-0 133).
0.5 Ratio of specific activity of feed grass water to atmospheric water (from NUREG-0133).
H Absolute humidity of the atmosphere (8 gm/m3 , from Regulatory I Guide 1.109).
Section 4 -Page 15
 
Oconee Nuclear Station                                                             January, 2009 Offsite Dose Calculation Manual (ODCM)                                               Revision 49 Grass/Cow/Meat K' QF(Uap)
K                Fapi(r)(DFLIL        [fff          (1 - fpf-)e,-Ath eAt f)
Formula: from NUREG-0133,:pages-34 & 35. Where:
Roapi   Dose commitment factor for organ o, age group a, nuclide i, for grass/cow/meat pathway (m2"mrem/yr per &#xfd;tCi/sec). (See Appendices G through J for age group and pathway specific dose commitment factors).
K'   Units conversion factor pCi/&#xfd;tCi (106).
QF     Cow consumption rate (50 kg/day, from Regulatory Guide 1.109).
Uap     Consumption rate of cow meat for age group a (kg/yr, from Regulatory Guide 1.109).
Adult.- 110 Teen- 65 Child - 41 Infant - 0 r   Fraction of deposited activity retained on cow's feed grass (from Regulatory Guide 1.109).
1.0 for radioiodine.
0.2 for particulates.
0.2 for particulates.
Yp Agricultural productivity by unit area of pasture feed grass (0.7 kg/m 2 , from Regulatory Guide 1.109).Y, Agricultural productivity by unit area of stored feed (2.0 kg/m 2 , from Regulatory Guide 1.109).Nuclide decay constant for nuclide i (sec-1).Xw Decay constant for removal of activity on leaf and plant surfaces by weathering (5.73x 10-7 sec', from NUREG-0133).(DFLoi)a Ingestion dose conversion factor for nuclide i, organ o, and age group a, from Tables E- i l through E- 14 of Regulatory Guide 1.109 (mrem/pCi).  
Yp     Agricultural productivity by unit area of pasture feed grass (0.7 kg/m 2 , from Regulatory Guide 1.109).
-Ffi Stable element transfer coefficient for nuclide i, in days/kg, from Table E-I of Regulatory Guide 1.109 for cow meat.fp Fraction of year that the cow is on pasture (1.0, from RG 1.109).fs Fraction of the cow feed that is pasture grass while the cow is on pasture (1.0, from Regulatory Guide 1.109).tf Transport time from pasture to receptor (1.73E+06 seconds, from Regulatory Guide 1.109).th Transport time from crop field to receptor (7.78E+06 seconds, from Regulatory Guide 1.109).Section 4 -Page 16 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)January, 2009 Revision 49 Grass/Cow/Meat
Y, Agricultural productivity by unit area of stored feed (2.0 kg/m2 , from Regulatory Guide 1.109).
-Tritium Roapi = K' KF "'FfQFUap (FLoi)a[0.75(0.5
X* Nuclide decay constant for nuclide i (sec-1).
/ H)]Formula: from NUREG-0133, page 35.Where: Roapi Dose commitment factor for organ o, age group a; nuclide &#xfd;i, for grass/cow/meat pathway (mrem/yr per jiCi/m 3). (See Appendices G through J for age group and pathway specific dose commitment factors).K' Units conversion factor pCi/jtCi (106).K"' Units conversion factor gm/kg (103).QF Cow consumption rate (50 kg/day, from Regulatory Guide 1.109).Uap Consumption rate of cow meat for age group a (kg/yr, from Regulatory Guide 1.109).'Adult -110 Teen -65 Child -41 Infant -0 (DFLoi)a Ingestion dose conversion factor for nuclide i, organ o, and age group a, from Tables E- 11 through E- 14 of Regulatory Guide 1.109 (mrem/pCi)..
Xw Decay constant for removal of activity on leaf and plant surfaces by weathering (5.73x 10-7 sec', from NUREG-0133).
Ffi Stable element transfer coefficient for nUclide i, in dayS/liter, from Table E- 1 of Regulatory Guide 1.109 for cow meat.0.75 Fraction of total feed that is water (from NUREG-0 133).0.5 Ratio of specific activity of feed grass water to atmospheric water (from NUREG-0133).
(DFLoi)a Ingestion dose conversion factor for nuclide i, organ o, and age group a, from Tables E- i l through E- 14 of Regulatory Guide 1.109 (mrem/pCi).                                                             -
H Absolute humidity of the atmosphere (8 gm/m 3 , from Regulatory Guide 1.109).Section 4 -Page 17 Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 4.0.3 DIRECT RADIATION Direct radiation is that radiation from confined sources, and does not include any external component from radioactive effluents.
Ffi Stable element transfer coefficient for nuclide i, in days/kg, from Table E-I of Regulatory Guide 1.109 for cow meat.
The point kernel method has been used to calculate offsite dose rates from radioactive materials stored in the refueling water storage tanks, reactor makeup water storage tanks, and temporary onsite radwaste storage tanks. Dose calculations using this method performed for Oconee Nuclear Station indicate direct radiation doses are much less than 0.01 mrem/yr and, therefore, make a negligible contribution to individual dose.Likewise, direct and air-scatter radiation dose contributions from the onsite Independent Spent Fuel Storage Installation (ISFSI) at Oconee have been calculated and documented in the "Oconee Nuclear Site 1OCFR72.212 Written Evaluations" report The results of-the calculation demonstrate that conservatively assuming 2000 hours of occupancy per year the annual dose at the nearest controlled area boundary (approximately, 300 meters)is below the 1OCFR72.104(a) and 40CFRI90.10(a) limit of 25 mrem from direct and skyshine radiation.
fp Fraction of year that the cow is on pasture (1.0, from RG 1.109).
Since it is demonstrated, that with a conservative occupancy assumption the doses at the controlled area boundary are within limits, it can easily be concluded that the dose to a "real individual" is Within the same limits. The closest residence to the ISFSI is in the SW-SSW direction approximately 1 mile (-1600 meters)from the ISFSI, or 1.36 miles from the centerline of the site. The maximum dose rate dose to the nearest resident from the Oconee ISFSi' assuming 100% occupancy time is estimated to be much less than 1 mrem/yr.Direct radiation doses will not be calculated routinely.
fs Fraction of the cow feed that is pasture grass while the cow is on pasture (1.0, from Regulatory Guide 1.109).
tf Transport time from pasture to receptor (1.73E+06 seconds, from Regulatory Guide 1.109).
th Transport time from crop field to receptor (7.78E+06 seconds, from Regulatory Guide 1.109).
Section 4 - Page 16


====4.0.4 EFFLUENT====
Oconee Nuclear Station                                                          January, 2009 Offsite Dose Calculation Manual (ODCM)                                            Revision 49 Grass/Cow/Meat - Tritium Roapi    = K' KF    "'FfQFUap(FLoi)a[0.75(0.5                        / H)]
APPORTIONMENT For the Oconee Nuclear Station the effluent releases are apportioned equally to each unit for each site as recommended by Section 3.1 of NUREG-0133, because the shared radwaste treatment systems at each site make it impractical to accurately ascribe releases to a specific reactor unit. For Annual Effluent Release Report purposes effluent releases are summed for each unit, and the maximum individual dose to the public is reported as a site total.Section 4 -Page 18 Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 5.0 FUEL CYCLE CALCULATIONS In accordance with the requirements of 40CFR190, the annuIal dose commitment to any member of the general public shall be calculated to assure that doses are limited to 25 millirems to the total body or any organ with the exception of the thyroid which is limited to 75 millirems.
Formula: from NUREG-0133, page 35.
In accordance with the requirements of the Selected Licensee Commitments, the annual dose commitment shall also be calculated any time that one of the quarterly dose limits of the Selected Licensee Commitments is exceeded; these annual'dose commitments may not just be calculated for the calendar year.The "Uranium fuel cycle" is defined in 40CFR Part 190.02(b):as: "Uranium fuel'cycle means the operations of milling ,or Uranium ore, chemical conversion of uranium, isotopic enrichment of uranium, fabrication of uranium fuel, generation of electricity by a light-water-cooled nuclear power plant using uranium fuel, and reprocessing of spent uranium fuel, to. the extent that these directly support the production of electrical power for public use utilizing nuclear energy, but excludes mining operations, operations atwaste disposal sites, transportation of any radioactive material in support of these operations, and the reuse of recovered non-uranium special nuclear and by-product materials from the cycle." Based on this definition of the fuel cycle and the' information in 1OCFR51, Table S-3, and Wash-1248, the radiological impact of the following operations has been assessed for Oconee Nuclear Station: 5.0.1 MILLING No milling operations occur within fifty- miles of the Oconee Nuclear Station: 5.0.2 CONVERSION No uranium hexafluoride production occurs within fifty miles of the Oconee Nuclear Station.5.0.3 ENRICHMENT No uranium enrichment operations occur within fifty miles of the Oconee Nuclear Station.5.0.4 FUEL FABRICATION No fuel fabrication operations occur within fifty miles of the Oconee Nuclear Station.Section 5 -Page 1 Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 5.0.5 NUCLEAR POWER PRODUCTION The production of electricity for public use using light-water-cooled nuclear power stations results in increments of dose to individuals within fifty miles of any station due to liquid and gaseous effluent releases and direct radiation or skyshine.
Where:
The increments of dose resulting from liquid and gaseous effluent releases will be calculated using the ODCM methodology implemented in the RETDAS computer program. The dose from direct radiation, skyshine, and radiation from the station storage facilities has been estimated using conservative assumptions (see Section 4.0.3).In. certain situations more than one nuclear power station site may contribute to the doses to be considered in making fuel cycle dose assessments in accordance with 40CFR190.However, since the Oconee nuclear station is located over 100 miles from the Catawba and McGuire nuclea" stations, the relative dose contribution from each site to the other is insignificant, and can be ignored in assessing compliance with 40CFR190.5.0.6 FUEL REPROCESSING No fuel reprocessing operations occur within fifty miles of the Oconee Nuclear Station.5.0.7 40CFR190 TOTAL DOSE DETERMINATION To summarize, only dose increments from nuclear power production operations (Section 5.0.5) need be considered in calculations to demonstrate compliance with the requirements of 40CFRI 90. The fuel cycle dose assessments for Oconee Nuclear Station only include liquid and gaseous dose contributions from Oconee and dose from Oconee's ISFSI since no other uranium fuel cycle facility contributes significantly to Oconee's maximum exlposed individual.
Roapi    Dose commitment factor for organ o, age group a; nuclide &#xfd;i,for grass/cow/meat pathway (mrem/yr per jiCi/m 3). (See Appendices G through J for age group and pathway specific dose commitment factors).
For this dose assessment, the total body and maximum organ dose contributions to the maximum exposed individual from Oconee's liquid and gaseous effluents are estimated using the following calculations:
K'    Units conversion factor pCi/jtCi (106).
Dwb(T) = Dwb(l) + Dwb(g)DOo(T) = DO,(l) + Dmo(g)where: Db(T) = Total estimated fuel cycle whole body dose commitment resulting from the combined liquid and gaseous effluents of Oconee during the calendar year of interest, in mrem.Dmo(T) = Total estimated fuel cycle maximum organ dose commitment resulting from the combined liquid and gaseous effluents of Oconee during the calendar year of interest, in mrem.Section 5 -Page 2 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)January, 2009 Revision 49 6.0 ENVIRONMENTAL LOCATIONS 6.0.1 SITE DESCRIPTION AND SAMPLE LOCATIONS Oconee Nuclear Station (ONS) is located in Oconee County, South Carolina, approximately 8 miles northeast of- Seneca, South Carolina, on the shore of Lake Keowee. This lake was formed by, damming the Keowee and Little Rivers in that location.
K"'    Units conversion factor gm/kg (103).
Immediately to the south is the U.S. Government Hartwell Project. The Keowee Hydroelectric Plant near the station joins Lake Keowee and the upper reaches of Lake Hartwell.
QF    Cow consumption rate (50 kg/day, from Regulatory Guide 1.109).
To the north, the Jocassee Hydroelectric Plant joins Lake Jocassee and Lake Keowee. Jocassee is a pumped storage plant. The ONS exclusion area boundary is 1 mile.Table 6.0-1 and Table 6.0-2 define the sampling and TLD locations for the Oconee Radiological Monitoring Program. Figure 6.0-1 'and Figure 6.0-2 illustrate these locations as compared to Oconee Nuclear Station.Air Sampling at Oconee Nuclear Station 6.0.2 LAND USE CENSUS DATA The Annual Land Use Census, required by Selected Licensee Commitments, is performed to ensure that changes' in the use of areas at or beyond the site boundary are identified, and that modifications to the Radiological Environmental Monitoring Program are made if required by changes in land use. This census satisfies the requirements of Section IV.B.3 of Appendix I to 1 OCFR50. Results are shown in Table 6.0-3 and Figure 6.0-3.'Section 6 -Page 1 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)January, 2009 Revision 49 TABLE 6.0-1 OCONEE RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS Table 6.0-1 Codes 'W Weekly SM Semimonthly BW BiWeekly Q _ Quarterly M Monthly SA Semiannually C Control:Site ocation Description*
Uap    Consumption rate of cow meat for age group a (kg/yr, from Regulatory Guide 1.109).
Air Rad. & .Suface Diinking Shoreline
                      'Adult - 110 Teen - 65 Child - 41 Infant - 0 (DFLoi)a      Ingestion dose conversion factor for nuclide i, organ o, and age group a, from Tables E- 11 through E- 14 of Regulatory Guide 1.109 (mrem/pCi)..
-. Fish -Milk Broadleaf Le Partseulate W ater Water Sediment.  
Ffi    Stable element transfer coefficient for nUclide i, in dayS/liter, from Table E- 1 of Regulatory Guide 1.109 for cow meat.
-Vegetation 060 Greenville Water Intake Road (3.23 NE) M 060 C ** Greenville Water Intake Road (2.28 NE) SA 062 C Lake Keowee Hydro Intake (0.85 mi ENE) M Lake Hartwell Hwy 183 Bridge 063 (0.80 mi ESE) [000.7] SA SA 063.1 Lake Hartwell Hwy 183 (0.79 mi E) M 064 C Seneca (6.67 mi SSW) [004.1] M 066 Anderson (18.9 mi SSE) [012] M Lawrence Ramsey Bridge Hwy 27 067 (4.34 mi SSE) [005.2] SA SA 068 C High Falls County Park (1.82 mi W) SA 071 C Clemson Dairy (10.2 mi SSE) [006.3] SM 074 Keowee Key Resort (2.36 mi NNW). W 077 Skimmer Wall (1.00 mi SW) W M 078 Recreation Site (0.58 mi WSW) W 079 Keowee Dam (0.56 mi NE) W _ M 081 C Clemson Operations Center (9.33 mi SE) W -M 084 Sue Craig Road (2.58 mi NNE) W M* GPS data reflect approximate accuracy to within 2-5 meters. GPS field measurements were taken as close as possible to the item of interest.** Control for Fish Only[ Location Numbers prior to 1984 " Section 6 -Page 2 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)January, 2009 Revision 49 TABLE 6.0-2 OCONEE RADIOLOGICAL MONITORING PROGRAM, SAMPLING LOCATIONS (TLD SITES)Site Location*
0.75    Fraction of total feed that is water (from NUREG-0 133).
'Disitance Sector Site Lo-cation*
0.5    Ratio of specific activity of feed grass water to atmospheric water (from NUREG-0133).
Distance6 Sector.MICROWAVE TOWER, 020 SITE BOUNDARY 0. 16 miles N 040 SIX MILE 4.74,miles E 021 SITE BOUNDARY 0.25 miles NNE 041 JCT HWY 101 & 133 4.25'.miles ESE LAWRENCE CHAPEL 022 SITE BOUNDARY 0.53 miles NE 042 CHURCH, HWY 133 4.93,miles SE HWY 291 AT 023 SITE BOUNDARY 0.93 miles ENE 043. ISSAQUEENA PARK 4.09 miles SSE HWY 130 AT LITTLE i: 024 SITE BOUNDARY 0.81 miles E 044 RIVER DAM, 3.96,miles S TERMINUS OF HWY 588 025 SITE BOUNDARY 0.42 miles ESE 045 AT CROOKED CREEK 4.78,miles SSW HWY 188 AT 026 SITE BOUNDARY 0.34 miles SE 046 CROOKED CREEK 4.61 miles SW NEW HOPE CHURCH, 027 SITE BOUNDARY 0.49 miles SSE 047 HWY .188 3.58,miles WSW 028, SITE BOUNDARY 0.46 miles S 048 JCT HWY 175 & 188 3.64 ,miles W 029 SITE BOUNDARY 0.56 miles SSW 049 JCT HWY 201 & 92 3.601miles WNW STAMP CREEK LANDING, 030 SITE BOUNDARY 0.42 miles SW 050 END OF HWY 92' 3.53 miles NW HWY 128,1 MILENOF 031 SITE BOUNDARY 0.27 miles WSW 051 HWY{130 4.64 miles NNW DPC BRANCH OFFICE 076 SITE BOUNDARY 0.19 miles W 052 SITE -PICKENS 12.4'miles, ENE DPC BRANCH OFFICE 032 SITE BOUNDARY 0.19 miles WNW 053 SITE -LIBERTY 11.7 miles E" POST OFFICE -HWY 93 033 SITE BOUNDARY 0.21 miles WNW 054 NORRIS 8.60 miles ESE CLEMSON 034 SITE BOUNDARY 0.22 miles
H    Absolute humidity of the atmosphere (8 gm/m 3 , from Regulatory Guide 1.109).
* NW 055 METEOROLOGY PLOT 9.27 miles SSE 035 SITE BOUNDARY 0.17 miles NNW 056 WATER TOWER -SENECA 7.30 miles SSW OCONEE MEMORIAL 1 036 MILE CREEK LANDING 4.32 miles N 057 HOSPITAL "x .8.42 miles SW KEOWEE CHURCH, BRANCH RD 037 HWY 327 4.85 miles NNE 058 C SUBSTATION, WALHALLA 9.39 miles WSW CONVENIENCE MART, 038 JCT HWY 183 & 133 4.24 miles NE 059 TAMASSEE DAR SCHOOL 9.20 miles. NW HWY 133, 1 MILE EAST CLEMSON 039 OF JCT HWY 183 & 133 4.02 miles ENE 081 C OPERATIONS CENTER 9.33'miles SE C = Control* GPS data reflect approximate accuracy to within 2-5 meters. GPS field measurements were taken as close as possible to the item of interest.Section 6 -Page 3 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)January, 2009 Revision 49 TABLE 6.0-3 Oconee 2008 Land Use Census Results*Land Use Census performed 6/4 -6/5/2008 Sector Distahce Sector Distance'(Miles)** (Miles)**Nearest Residence 2.98 Nearest Residence 1.96 N Nearest Milk Animal -S Nearest Milk Animal -Nearest Residence 1.84 -Nearest Residence 1.36 NNE Nearest Milk Animal SSW Nearest Milk Animal Nearest Residence 1.20 Nearest Residence 1.31 NE Nearest Milk Animal -SW Nearest Milk Animal -Nearest Residence 1.34: Nearest Residence 1.81 ENE Nearest Milk Animal -WSW Nearest Milk Animal -Nearest Residence L14, Nearest Residence 1.76 E Nearest Milk Animal -Nearest Milk Animal Nearest Residence 1.57 Nearest Residence 1.35 ESE Nearest Milk Animal -WNW Nearest Milk Animal Nearest Residence 1.46 Nearest Residence 1.04 SE Nearest Milk Animal -NW Nearest Milk Animal " Nearest Residence 1.54 Nearest Residence' 1.06 SSE Nearest Milk Animal -NNW Nearest Milk Animal -"-" indicates no occurrences within the 5 mile radius The land use census identifies nearest pathways to the exclusion area boundary (EAB, -1.0 mile) for each of the 16 sectors..
Section 4 - Page 17
Locations beyond the nearest pathway for each sector are assumed to contain that pathway for dose calculation purposes.
 
At Oconee, broad leaf vegetation samples are taken in lieu of a garden census.. For dose calculation purposes, since a garden location cannot be ruled out, a garden is assumed to- exist at the site boundary and beyond for every sector. For the 4.5-5.0 mile sector all pathways, i.e., residence, garden, milk animal (goat), and meat animal (cow), are assumed to exist for dose calculation purposes.** GPS data reflect approximate accuracy to within 2-5 meters. GPS field measurements were taken as close as possible to the item of interest.Section 6 -Page 4 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)January, 2009 Revision 49 Figure 6.0-1 Sampling Locations Map (Site Boundary)Oconee Nuclear Station Sampling Locations Map (One Mile Radius)Legend o TLD Locations A& All Other LocationsPublic Roads/XV* County Boundary Water Approndmate focaion 6f featkures shovn-0 0.25 0.tiles Projecbon NCSP NAD27 Section 6 -Page 5 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)January, 2009 Revision 49 Figure 6.0-2 Sampling Locations Map (Ten Mile Radius)I.Oconee Nuclear Station Sampling Locations Map (Ten Mile Radius)Legend a TLD Locations A All Other Locations/'v' Public Roads yPj Rail Roads 7v, County Boundary Incorporated Areas Water Approximate location of features  0 1 2 3Miles Projedion NCSP NAD27 Section 6 -Page 6 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)January, 2009 Revision 49 Figure 6.0-3 ONS 2008 Land Use Census Map Oconee Nuclear Station 2008 Land Use Census Map Legend* ResidencePublic Roads\ Rail Road/"../, County Boundary Water approximate location of features shown 0 0.5 1 2 Miles Projection NCSP NAD27 June 2008 (Section 6 -Page 7 Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 6.0.3 OCONEE METEOROLOGY:
Oconee Nuclear Station                                                     January, 2009 Offsite Dose Calculation Manual (ODCM)                                      Revision 49 4.0.3 DIRECT RADIATION Direct radiation is that radiation from confined sources, and does not include any external component from radioactive effluents. The point kernel method has been used to calculate offsite dose rates from radioactive materials stored in the refueling water storage tanks, reactor makeup water storage tanks, and temporary onsite radwaste storage tanks. Dose calculations using this method performed for Oconee Nuclear Station indicate negligibledirect  radiation doses are much less than 0.01 mrem/yr and, therefore, make a contribution to individual dose.
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.
Likewise, direct and air-scatter radiation dose contributions from the onsite Independent Spent Fuel Storage Installation (ISFSI) at Oconee have been calculated and documented in the "Oconee Nuclear Site 10CFR72.212 Written Evaluations" report The results of
The methodology is based upon Regulatory Guide 1.111, as implemented by the NRC's computer model "XOQDOQ: Computer Program for the Meteorological Evaluation of Routine Effluent' Releases at Nuclear Power Stations," NUREG/CR-2919, PNL-4380, September 1982.Five years of hourly meteorological data from the onsite instruments are processed into a representative joint frequency distribution of winds and atmospheric stability for input into the XOQDOQ model (Version 2.0). Thus, the air dispersion and deposition factors (x/Q and D/Q) output by the model are based on' a five-year climatology for the site.6.0.3.1 XOODOQ METHODOLOGY AND ASSUMPTIONS A continuous, routine release (non-purge) is simulated from each unit vent. The unit vent release type is categorized as semi-elevated, being elevated approximately 92% of the time and being at ground-level approximately 8% of the time. This is based on RG 1.111 criteria, with the ratio (i.e. 3.64) of the average exit velocity (11.39 m/s) to the mean wind speed at the 60 m release height (3.13 m/s). To account for all release pathways, Oconee is modeled as both a totally "ground-level" release and as a "mixed-mode" release, with two model runs of XOQDOQ.Surrounding terrain heights are not, input for ground-level releases, but are used for the elevated portion of mixed-mode releases.
-the calculation demonstrate that conservatively assuming 2000 hours of occupancy per year the annual dose at the nearest controlled area boundary (approximately, 300 meters) is below the 10CFR72.104(a) and 40CFRI90.10(a) limit of 25 mrem from direct and skyshine radiation. Since it is demonstrated, that with a conservative occupancy assumption the doses at the controlled area boundary are within limits, it can easily be concluded that the dose to a "real individual" is Within the same limits. The closest residence to the ISFSI is in the SW-SSW direction approximately 1 mile (-1600 meters) from the ISFSI, or 1.36 miles from the centerline of the site. The maximum dose rate dose to the nearest resident from the Oconee ISFSi' assuming 100% occupancy time is estimated to be much less than 1 mrem/yr.
The locale consists of rolling terrain, so the default open terrain recirculation factor is applied in XOQDOQ [KOPT(8)=I].
Direct radiation doses will not be calculated routinely.
This correction factor is recommended in RG 1.111 to adjust the straight-line airflow of the model for spatial and temporal variations are produced by large scale weather patterns.In order for XOQDOQ to treat the plume as a ground-level release, the' exit velocity and the inside diameter of the unit vent must be input as zero. The heat emission rate of each vent is also assumed to be zero, as recommended by the model. A release height of 10 m is assumed for the ground-level release, with actual plant grade of 796 ft msl. Using the building height (58 m) and minimum cross-sectional area of the containment building (2296 M 2), XOQDOQ applies a building wake correction to the relative air concentrations.
4.0.4 EFFLUENT APPORTIONMENT For the Oconee Nuclear Station the effluent releases are apportioned equally to each unit for each site as recommended by Section 3.1 of NUREG-0133, because the shared radwaste treatment systems at each site make it impractical to accurately ascribe releases to a specific reactor unit. For Annual Effluent Release Report purposes effluent releases are summed for each unit, and the maximum individual dose to the public is reported as a site total.
For the mixed-mode release, the exit velocities (11.1, 11.3, and 11.7 m/s for U1-U3, respectively) and inside diameters (1.8 m) of the unit vents are input to the XOQDOQ model for each vent. The heat emission rate of each vent is still assumed to be zero, as in the ground-level release. Plant grade elevation is now input as zero, however, to properly Section 6 -Page 8 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)January, 2009 Revision 49 utilize the input terrain heights above yard grade elevation (Table 6.0-4). The height of the vent (60.7 m) above plant grade is used to determine the plume centerline height.Table 6.0-4 Terrain Heights Above ONS Yard Grade Elevation (m)Distance:
Section 4 - Page 18
0.5 1 1.5 2.0 2.5 3.0 3.5 .4.0' 4.5 5.0 mile mile miles miles miles miles miles .miles,: miles miles S 29 38 38 38 38 38 50 50 50 50 SSW 32 44 50 50 50 50 50 50 50 50 SW 38 44 44 44 50 50 50 50 50 50 WSW 44 44 44 44 44 44 44 48 48 57 W 48 48 48 48 48 55 58 73 73 73 WNW 29 29 29 38 65 '65 71 71 77 80 NW 30 30 30 48 50 68 69 69 71 71 NNW 30 30 30 48 50 68 69 69 71 71 N 29 30 30 30 30 30' 62 62 62 74 NNE 24 24 35 35 53 53 82 82 82 82 NE 7 13 35 44 44 50 78 88 99 100 ENE 4 23 35 38 53 62 74 80 99 100 E 1 24 24 24 57 68 68 74 84 84 ESE 1 1 13 35 62 62 .62 65 71 71 SE 7 20 20 44 67 67 67 67 67 67 SSE 7 38 38 38 47 62 62 62 62 62 Calculations of relative air concentrations and deposition are made for gridded receptor distances per sector. The model's default values for half-lives are used (i.e. no decay;2.26 days for short-lived noble gases; and 8 days with depletion factors for all- iodines[DECAYS(I)=
 
101; 2.26; -8.0]).6.0.3.2 METEOROLOGICAL DATA Five years (1988-1992) of hourly, onsite meteorological data are used to produce the joint frequency distributions of wind speed and direction per stability class. The 10 m level winds are used. It is these joint frequency distributions which are input to the XOQDOQ model. XOQDOQ extrapolates the 10 m wind speed to the release height during the elevated portion of mixed-mode releases.
Oconee Nuclear Station                                                      January, 2009 Offsite Dose Calculation Manual (ODCM)                                      Revision 49 5.0 FUEL CYCLE CALCULATIONS In accordance with the requirements of 40CFR190, the annuIal dose commitment to any member of the general public shall be calculated to assure that doses are limited to 25 millirems to the total body or any organ with the exception of the thyroid which is limited to 75 millirems. In accordance with the requirements of the Selected Licensee Commitments, the annual dose commitment shall also be calculated any time that one of the quarterly dose limits of the Selected Licensee Commitments is exceeded; these annual' dose commitments may not just be calculated for the calendar year.
Hours of calm winds are distributed by direction with the same frequency as the lowest "noncalm" wind speed class[KOPT(1)=I].
The "Uranium fuel cycle" is defined in 40CFR Part 190.02(b):as:
Thus, wind speed classes are established so that the lowest wind speed class is the starting threshold of the anemometer (i.e. the "calm" wind speed class). The largest wind speed class has the upper bound of (5 m/s + max hourly wind speed).Stability classes (A-G) are based on the vertical temperature gradient, measured by the hourly averaged delta-T variable.Section 6 -Page 9 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)January, 2009 Revision 49 6.0.3.3 ANNUAL XOQDOQ COMPARISON TO THE ODCM Each year, the prevailing winds and stability class frequencies for ONS are compared to the 5-year period (1988-1992) upon which the X/Q and D/Q calculations have been made.The 5-year climatology is summarized in Table 6.0-5 and Table 6.0-6 below. Since the comparison is being made to a 5-year climatology, significant differences should not occur in the meteorological variables of concern (i.e. winds and delta-T).
"Uranium fuel'cycle means the operations of milling ,or Uranium ore, chemical conversion of uranium, isotopic enrichment of uranium, fabrication of uranium fuel, generation of electricity by a light-water-cooled nuclear power plant using uranium fuel, and reprocessing of spent uranium fuel, to.the extent that these directly support the production of electrical power for public use utilizing nuclear energy, but excludes mining operations, operations atwaste disposal sites, transportation of any radioactive material in support of these operations, and the reuse of recovered non-uranium special nuclear and by-product materials from the cycle."
The meteorological comparison serves to verify this assumption.
Based on this definition of the fuel cycle and the' information in 10CFR51, Table S-3, and Wash-1248, the radiological impact of the following operations has been assessed for Oconee Nuclear Station:
5.0.1 MILLING No milling operations occur within fifty- miles of the Oconee Nuclear Station:
5.0.2 CONVERSION No uranium hexafluoride production occurs within fifty miles of the Oconee Nuclear Station.
5.0.3 ENRICHMENT No uranium enrichment operations occur within fifty miles of the Oconee Nuclear Station.
5.0.4 FUEL FABRICATION No fuel fabrication operations occur within fifty miles of the Oconee Nuclear Station.
Section 5 - Page 1
 
Oconee Nuclear Station                                                     January, 2009 Offsite Dose Calculation Manual (ODCM)                                     Revision 49 5.0.5 NUCLEAR POWER PRODUCTION The production of electricity for public use using light-water-cooled nuclear power stations results in increments of dose to individuals within fifty miles of any station due to liquid and gaseous effluent releases and direct radiation or skyshine. The increments of dose resulting from liquid and gaseous effluent releases will be calculated using the ODCM methodology implemented in the RETDAS computer program. The dose from direct radiation, skyshine, and radiation from the station storage facilities has been estimated using conservative assumptions (see Section 4.0.3).
In. certain situations more than one nuclear power station site may contribute to the doses to be considered in making fuel cycle dose assessments in accordance with 40CFR190.
However, since the Oconee nuclear station is located over 100 miles from the Catawba and McGuire nuclea" stations, the relative dose contribution from each site to the other is insignificant, and can be ignored in assessing compliance with 40CFR190.
5.0.6 FUEL REPROCESSING No fuel reprocessing operations occur within fifty miles of the Oconee Nuclear Station.
5.0.7 40CFR190 TOTAL DOSE DETERMINATION To summarize, only dose increments from nuclear power production operations (Section 5.0.5) need be considered in calculations to demonstrate compliance with the requirements of 40CFRI 90. The fuel cycle dose assessments for Oconee Nuclear Station only include liquid and gaseous dose contributions from Oconee and dose from Oconee's ISFSI since no other uranium fuel cycle facility contributes significantly to Oconee's maximum exlposed individual. For this dose assessment, the total body and maximum organ dose contributions to the maximum exposed individual from Oconee's liquid and gaseous effluents are estimated using the following calculations:
Dwb(T) = Dwb(l) + Dwb(g)
DOo(T) = DO,(l) + Dmo(g) where:
Db(T) = Total estimated fuel cycle whole body dose commitment resulting from the combined liquid and gaseous effluents of Oconee during the calendar year of interest, in mrem.
Dmo(T) = Total estimated fuel cycle maximum organ dose commitment resulting from the combined liquid and gaseous effluents of Oconee during the calendar year of interest, in mrem.
Section 5 - Page 2
 
Oconee Nuclear Station                                                    January, 2009 Offsite Dose Calculation Manual (ODCM)                                   Revision 49 6.0 ENVIRONMENTAL LOCATIONS 6.0.1 SITE DESCRIPTION AND SAMPLE LOCATIONS Oconee Nuclear Station (ONS) is located in Oconee County, South Carolina, approximately 8 miles northeast of- Seneca, South Carolina, on the shore                of Lake Keowee. This lake was formed by, damming the Keowee and Little Rivers in that location. Immediately to the south is the U.S. Government Hartwell Project. The Keowee Hydroelectric Plant near the station joins Lake Keowee and the upper reaches of Lake Hartwell. To the north, the Jocassee Hydroelectric Plant joins Lake Jocassee and Lake Keowee. Jocassee is a pumped storage plant. The ONS exclusion area boundary is 1 mile.
Table 6.0-1 and Table 6.0-2 define the sampling and TLD locations for the Oconee Radiological Monitoring Program. Figure 6.0-1 'and Figure 6.0-2 illustrate these locations as compared to Oconee Nuclear Station.
Air Sampling at Oconee Nuclear Station 6.0.2 LAND USE CENSUS DATA The Annual Land Use Census, required by Selected Licensee Commitments, is performed to ensure that changes' in the use of areas at or beyond the site boundary are identified, and that modifications to the Radiological Environmental Monitoring Program are made if required by changes in land use. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10CFR50. Results are shown in Table 6.0-3 and Figure 6.0-3.'
Section 6 - Page 1
 
Oconee Nuclear Station                                                                          January, 2009 Offsite Dose Calculation Manual (ODCM)                                                          Revision 49 TABLE 6.0-1 OCONEE RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS Table 6.0-1 Codes        '
W           Weekly        SM          Semimonthly BW          BiWeekly      Q      _    Quarterly M            Monthly      SA          Semiannually C            Control
:Site                  ocation  Description*          Le Air Rad. &
Partseulate
                                                                          .Suface W ater Diinking Shoreline -. Fish  -Milk Broadleaf Water  Sediment.           -    Vegetation 060        Greenville Water Intake Road (3.23 NE)                                      M 060 C **   Greenville Water Intake Road (2.28 NE)                                                          SA 062 C      Lake Keowee Hydro Intake (0.85 mi ENE)                            M Lake Hartwell Hwy 183 Bridge 063        (0.80 mi ESE) [000.7]                                                                SA        SA 063.1     Lake Hartwell Hwy 183 (0.79 mi E)                                M 064 C      Seneca (6.67 mi SSW) [004.1]                                                M 066        Anderson (18.9 mi SSE) [012]                                                M Lawrence Ramsey Bridge Hwy 27 067        (4.34 mi SSE) [005.2]                                                                SA        SA 068 C      High Falls County Park (1.82 mi W)                                                  SA 071 C     Clemson Dairy (10.2 mi SSE) [006.3]                                                                    SM 074        Keowee Key Resort (2.36 mi NNW).                       W 077        Skimmer Wall (1.00 mi SW)                             W                                                      M 078        Recreation Site (0.58 mi WSW)                         W 079        Keowee Dam (0.56 mi NE)                                W                _                                      M 081 C      Clemson Operations Center (9.33 mi SE)                W                        -                             M 084        Sue Craig Road (2.58 mi NNE)                          W                                                      M
* GPS data reflect approximate accuracy to within 2-5 meters. GPS field measurements were taken as close as possible to the item of interest.
        ** Control for Fish Only
[ Location Numbers prior to 1984                                                            "
Section 6 - Page 2
 
Oconee Nuclear Station                                                                            January, 2009 Offsite Dose Calculation Manual (ODCM)                                                            Revision 49 TABLE 6.0-2 OCONEE RADIOLOGICAL MONITORING PROGRAM, SAMPLING LOCATIONS (TLD SITES)
Site          Location*          'Disitance      Sector        Site              Lo-cation*        Distance6  Sector
                                                        .                     MICROWAVE TOWER, 020      SITE BOUNDARY            0. 16 miles      N            040                SIX MILE          4.74,miles      E 021      SITE BOUNDARY            0.25 miles      NNE          041          JCT HWY 101 & 133      4.25'.miles    ESE LAWRENCE CHAPEL 022      SITE BOUNDARY            0.53 miles      NE            042          CHURCH, HWY 133        4.93,miles      SE HWY 291 AT 023      SITE BOUNDARY            0.93 miles      ENE          043.        ISSAQUEENA PARK        4.09 miles    SSE HWY 130 AT LITTLE            i:
024      SITE BOUNDARY            0.81 miles        E          044              RIVER DAM,          3.96,miles      S TERMINUS OF HWY 588 025      SITE BOUNDARY            0.42 miles      ESE          045        AT CROOKED CREEK        4.78,miles    SSW HWY 188 AT 026      SITE BOUNDARY            0.34 miles      SE          046          CROOKED CREEK          4.61 miles    SW NEW HOPE CHURCH, 027      SITE BOUNDARY            0.49 miles      SSE          047                HWY .188          3.58,miles    WSW 028,      SITE BOUNDARY            0.46 miles        S          048          JCT HWY 175 & 188      3.64 ,miles    W 029      SITE BOUNDARY            0.56 miles      SSW          049            JCT HWY 201 & 92      3.601miles  WNW STAMP CREEK LANDING, 030      SITE BOUNDARY            0.42 miles      SW          050            END OF HWY 92'      3.53 miles    NW HWY 128,1 MILENOF 031      SITE BOUNDARY            0.27 miles    WSW            051                HWY{130          4.64 miles    NNW DPC BRANCH OFFICE 076      SITE BOUNDARY            0.19 miles      W            052            SITE - PICKENS        12.4'miles,   ENE DPC BRANCH OFFICE 032      SITE BOUNDARY            0.19 miles    WNW            053            SITE - LIBERTY        11.7 miles      E" POST OFFICE - HWY 93 033      SITE BOUNDARY            0.21 miles    WNW            054                NORRIS          8.60 miles    ESE CLEMSON 034      SITE BOUNDARY            0.22 miles
* NW            055        METEOROLOGY PLOT        9.27 miles    SSE 035      SITE BOUNDARY            0.17 miles    NNW            056      WATER TOWER - SENECA      7.30 miles    SSW OCONEE MEMORIAL                1 036    MILE CREEK LANDING          4.32 miles        N            057              HOSPITAL      "x . 8.42 miles      SW KEOWEE CHURCH,                                                            BRANCH RD 037          HWY 327              4.85 miles      NNE          058 C      SUBSTATION, WALHALLA      9.39 miles    WSW CONVENIENCE MART, 038      JCT HWY 183 & 133          4.24 miles      NE            059      TAMASSEE DAR SCHOOL        9.20 miles. NW HWY 133, 1 MILE EAST                                                          CLEMSON 039    OF JCT HWY 183 & 133        4.02 miles      ENE          081 C        OPERATIONS CENTER        9.33'miles      SE C = Control
* GPS data reflect approximate accuracy to within 2-5 meters. GPS field measurements were taken as close as possible to the item of interest.
Section 6 - Page 3
 
Oconee Nuclear Station                                                                    January, 2009 Offsite Dose Calculation Manual (ODCM)                                                    Revision 49 TABLE 6.0-3 Oconee 2008 Land Use Census Results*
Land Use Census performed 6/4 - 6/5/2008 Sector                                        Distahce          Sector                                Distance' (Miles)**                                                (Miles)**
Nearest Residence                  2.98                  Nearest Residence                  1.96 N      Nearest Milk Animal                  -              S  Nearest Milk Animal                    -
Nearest Residence                  1.84                - Nearest Residence                  1.36 NNE        Nearest Milk Animal                                SSW  Nearest Milk Animal Nearest Residence                  1.20                  Nearest Residence                  1.31 NE        Nearest Milk Animal                  -              SW  Nearest Milk Animal                    -
Nearest Residence                  1.34:                Nearest Residence                  1.81 ENE        Nearest Milk Animal                  -            WSW    Nearest Milk Animal                    -
Nearest Residence                  L14,                  Nearest Residence                  1.76 E        Nearest Milk Animal                  -                  Nearest Milk Animal Nearest Residence                  1.57                  Nearest Residence                  1.35 ESE        Nearest Milk Animal                  -           WNW    Nearest Milk Animal Nearest Residence                  1.46                  Nearest Residence                  1.04 SE        Nearest Milk Animal                  -             NW  Nearest Milk Animal "
Nearest Residence                  1.54                  Nearest Residence'                  1.06 SSE        Nearest Milk Animal                  -           NNW    Nearest Milk Animal                  -
"-"  indicates no occurrences within the 5 mile radius The land use census identifies nearest pathways to the exclusion area boundary (EAB, - 1.0 mile) for each of the 16 sectors.. Locations beyond the nearest pathway for each sector are assumed to contain that pathway for dose calculation purposes. At Oconee, broad leaf vegetation samples are taken in lieu of a garden census.. For dose calculation purposes, since a garden location cannot be ruled out, a garden is assumed to- exist at the site boundary and beyond for every sector. For the 4.5-5.0 mile sector all pathways, i.e., residence, garden, milk animal (goat), and meat animal (cow), are assumed to exist for dose calculation purposes.
** GPS data reflect approximate accuracy to within 2-5 meters. GPS field measurements were taken as close as possible to the item of interest.
Section 6 - Page 4
 
Oconee Nuclear Station                                                                                                  January, 2009 Offsite Dose Calculation Manual (ODCM)                                                                                Revision 49 Figure 6.0-1 Sampling Locations Map (Site Boundary)
Oconee Nuclear Station Sampling Locations Map (One Mile Radius)
Legend o    TLD Locations A& All Other Locations
                                                                                            /t*      Public Roads
                                                                                            /XV      County Boundary Water Approndmate focaion 6f featkures shovn-0 0            0.25                .tiles Projecbon NCSP NAD27 Section 6 - Page 5
 
Oconee Nuclear Station                                                                                                     January, 2009 Offsite Dose Calculation Manual (ODCM)                                                                                     Revision 49 Figure 6.0-2 Sampling Locations Map (Ten Mile Radius)
I.
Oconee Nuclear Station Sampling Locations Map (Ten Mile Radius)
Legend a    TLD Locations A    All Other Locations
                                                                                                /'v'    Public Roads yPj Rail Roads 7v, County Boundary Incorporated Areas Water Approximate location of features show*"
0     1     2     3Miles Projedion NCSP NAD27 Section 6 - Page 6
 
Oconee Nuclear Station                                                                                          January, 2009 Offsite Dose Calculation Manual (ODCM)                                                                          Revision 49 Figure 6.0-3 ONS 2008 Land Use Census Map Oconee Nuclear Station 2008 Land Use Census Map Legend
* Residence
* Public Roads
                                                                                      \        Rail Road
                                                                                  /"../,      County Boundary Water approximate location of features shown
(
0      0.5    1          2 Miles Projection NCSP NAD27 June 2008 Section 6 - Page 7
 
Oconee Nuclear Station                                                          January, 2009 Offsite Dose Calculation Manual (ODCM)                                          Revision 49 6.0.3 OCONEE METEOROLOGY: RELATIVE AIR CONCENTRATIONS AND DEPOSITION Calculations of annually averaged air concentrations and deposition values from routine releases provide the air dispersion and deposition factors needed for dose assessment.
The methodology is based upon Regulatory Guide 1.111, as implemented by the NRC's computer model "XOQDOQ: Computer Program for the Meteorological Evaluation of Routine Effluent' Releases at Nuclear Power Stations," NUREG/CR-2919, PNL-4380, September 1982.
Five years of hourly meteorological data from the onsite instruments are processed into a representative joint frequency distribution of winds and atmospheric stability for input into the XOQDOQ model (Version 2.0). Thus, the air dispersion and deposition factors (x/Q and D/Q) output by the model are based on' a five-year climatology for the site.
6.0.3.1 XOODOQ METHODOLOGY AND ASSUMPTIONS A continuous, routine release (non-purge) is simulated from each unit vent. The unit vent release type is categorized as semi-elevated, being elevated approximately 92% of the time and being at ground-level approximately 8% of the time. This is based on RG 1.111 criteria, with the ratio (i.e. 3.64) of the average exit velocity (11.39 m/s) to the mean wind speed at the 60 m release height (3.13 m/s). To account for all release pathways, Oconee is modeled as both a totally "ground-level" release and as a "mixed-mode" release, with two model runs of XOQDOQ.
Surrounding terrain heights are not, input for ground-level releases, but are used for the elevated portion of mixed-mode releases. The locale consists of rolling terrain, so the default open terrain recirculation factor is applied in XOQDOQ [KOPT(8)=I]. This correction factor is recommended in RG 1.111 to adjust the straight-line airflow of the model for spatial and temporal variations *that are produced by large scale weather patterns.
In order for XOQDOQ to treat the plume as a ground-level release, the' exit velocity and the inside diameter of the unit vent must be input as zero. The heat emission rate of each vent is also assumed to be zero, as recommended by the model. A release height of 10 m is assumed for the ground-level release, with actual plant grade of 796 ft msl. Using the building height (58 m) and minimum cross-sectional area of the containment building (2296 M2 ), XOQDOQ applies a building wake correction to the relative air concentrations.
For the mixed-mode release, the exit velocities (11.1, 11.3, and 11.7 m/s for U1-U3, respectively) and inside diameters (1.8 m) of the unit vents are input to the XOQDOQ model for each vent. The heat emission rate of each vent is still assumed to be zero, as in the ground-level release. Plant grade elevation is now input as zero, however, to properly Section 6 - Page 8
 
Oconee Nuclear Station                                                          January, 2009 Offsite Dose Calculation Manual (ODCM)                                          Revision 49 utilize the input terrain heights above yard grade elevation (Table 6.0-4). The height of the vent (60.7 m) above plant grade is used to determine the plume centerline height.
Table 6.0-4 Terrain Heights Above ONS Yard Grade Elevation (m)
Distance:      0.5        1      1.5  2.0          2.5    3.0  3.5    . 4.0'      4.5    5.0 mile      mile    miles miles        miles miles    miles . miles,:    miles  miles S              29        38      38    38          38      38    50        50      50      50 SSW              32      44      50    50          50      50  50        50      50      50 SW              38      44      44    44          50      50  50        50        50    50 WSW            44        44      44    44          44      44    44      48        48      57 W              48        48      48    48          48        55  58        73      73      73 WNW            29        29      29    38          65  '65      71        71      77      80 NW              30        30      30    48          50      68    69        69      71      71 NNW            30        30      30    48          50      68    69        69      71      71 N              29        30      30    30          30      30'  62        62      62      74 NNE            24        24      35    35          53      53  82        82        82    82 NE              7        13      35    44          44      50  78        88        99    100 ENE              4        23      35    38          53      62    74        80      99      100 E                1      24      24    24          57      68    68        74        84    84 ESE              1        1      13    35          62      62  .62        65      71      71 SE              7        20      20    44          67      67    67        67      67      67 SSE              7        38      38    38          47      62    62        62        62    62 Calculations of relative air concentrations and deposition are made for gridded receptor distances per sector. The model's default values for half-lives are used (i.e. no decay; 2.26 days for short-lived noble gases; and 8 days with depletion factors for all- iodines
[DECAYS(I)= 101; 2.26; -8.0]).
6.0.3.2 METEOROLOGICAL DATA Five years (1988-1992) of hourly, onsite meteorological data are used to produce the joint frequency distributions of wind speed and direction per stability class. The 10 m level winds are used. It is these joint frequency distributions which are input to the XOQDOQ model. XOQDOQ extrapolates the 10 m wind speed to the release height during the elevated portion of mixed-mode releases. Hours of calm winds are distributed by direction with the same frequency as the lowest "noncalm" wind speed class
[KOPT(1)=I]. Thus, wind speed classes are established so that the lowest wind speed class is the starting threshold of the anemometer (i.e. the "calm" wind speed class). The largest wind speed class has the upper bound of (5 m/s + max hourly wind speed).
Stability classes (A-G) are based on the vertical temperature gradient, measured by the hourly averaged delta-T variable.
Section 6 - Page 9
 
Oconee Nuclear Station                                                        January, 2009 Offsite Dose Calculation Manual (ODCM)                                        Revision 49 6.0.3.3 ANNUAL XOQDOQ COMPARISON TO THE ODCM Each year, the prevailing winds and stability class frequencies for ONS are compared to the 5-year period (1988-1992) upon which the X/Q and D/Q calculations have been made.
The 5-year climatology is summarized in Table 6.0-5 and Table 6.0-6 below. Since the comparison is being made to a 5-year climatology, significant differences should not occur in the meteorological variables of concern (i.e. winds and delta-T). The meteorological comparison serves to verify this assumption.
Table 6.0-5 ONS Atmospheric Stability Frequency (1988-1992)
Table 6.0-5 ONS Atmospheric Stability Frequency (1988-1992)
Table 6.0-6 ONS Frequency of Wind Direction (From) and Speed (1988-1992)
Table 6.0-6 ONS Frequency of Wind Direction (From) and Speed (1988-1992)
Wind Direction Wind Speed Class Wind Speed Sector Frequency
Wind Direction      Wind Speed Class            Wind Speed Sector        Frequency (%)                  (m/s)          Frequency(%)
(%) (m/s) Frequency(%)
N                      5.1                    CALM                  1.0 NNE                    5.2            0.45 - 0.74 m/s              4.7 NE                      9              0.75 - 0.99 m/s              9.4 ENE                    8.3              1.00 - 1.24 m/s            10.0 E                      5.2            1.25 - 1.49 m/s              12.3 ESE                    3.1            1.50 - 1.99 m/s              16.8 SE                      3              2.00 - 2.99 m/s              20.4 SSE                    3.5            3.00 - 3.99 m/s              9.6 S                      3.6            4.00 - 4.99 m/s              4.5 SSW                    8.5            5.00 - 5.99 m/s              1.8 SW                      11.7            6.00 - 7.99 m/s              1.3 WSW                    7.4            8.00 - 9.99 m/s              0.3 W                      5.1                > 9.99 m/s                8.9 WNW                    6.9 NW                      7.2 NNW                    6.3        _      __. __  _... . _______.___________
N 5.1 CALM 1.0 NNE 5.2 0.45 -0.74 m/s 4.7 NE 9 0.75 -0.99 m/s 9.4 ENE 8.3 1.00 -1.24 m/s 10.0 E 5.2 1.25 -1.49 m/s 12.3 ESE 3.1 1.50 -1.99 m/s 16.8 SE 3 2.00 -2.99 m/s 20.4 SSE 3.5 3.00 -3.99 m/s 9.6 S 3.6 4.00 -4.99 m/s 4.5 SSW 8.5 5.00 -5.99 m/s 1.8 SW 11.7 6.00 -7.99 m/s 1.3 WSW 7.4 8.00 -9.99 m/s 0.3 W 5.1 > 9.99 m/s 8.9 WNW 6.9 NW 7.2 NNW 6.3 _ .__ __ _... ._______.___________
The joint frequency distributions of wind speed and direction versus atmospheric stability class are also determined from the annual data to provide input to the XOQDOQ model.
The joint frequency distributions of wind speed and direction versus atmospheric stability class are also determined from the annual data to provide input to the XOQDOQ model.Modeled X/Q and D/Q values for the 1.0 mile Exclusion Area Boundary at ONS are Section 6 -Page .10 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM)January, 2009 Revision 49 compared to the maximum of the (1988-1992)
Modeled X/Q and D/Q values for the 1.0 mile Exclusion Area Boundary at ONS are Section 6 - Page .10
X/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 IOCFR50, Appendix I dose objectives then the 5-year X/Q and D/Q values used in the Annual Radiological Effluent Release Report (ARERR) are not revised. An increase in calculated offsite dose that is greater than five percent of the 1OCFR50, Appendix I dose objectives would be considered significant enough to warrant a change in the X/Q and D/Q values used in the ARERR. If an increasing trend in the annual X/Q and D/Q values compared to the 5-year values is noted then a revised set of 5-year X/Q and D/Q values will be generated.
 
These limiting values are listed in Table 6.0
Oconee Nuclear Station                                                            January, 2009 Offsite Dose Calculation Manual (ODCM)                                            Revision 49 compared to the maximum of the (1988-1992) X/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 IOCFR50, Appendix I dose objectives then the 5-year X/Q and D/Q values

Latest revision as of 12:50, 12 March 2020

Offsite Dose Calculation Manual, Revision 49
ML091280665
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Site: Oconee  Duke Energy icon.png
Issue date: 01/31/2009
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Duke i (tEnergy.

Oconee Nuclear Station Units 1, 2 and 3 ODCM Offsite Dose Calculation Manual 2009

tDuke Power A Duke Energy Company Oconee Nuclear Station Units 1, 2 and 3 OFFSITE DOSE CALCULATION MANUAL (ODCM)

Prepared By: C. D. Ingram Approved By: L. E. Haynes General Office Radiation Protection Corporate RP Manager, Nuclear GO Reviewed By: R. A. Bowser ONS Radiation Protection Approved By: T. P. Gillespie, Jr.

ONS Station Manage.r Reviewed By: J. A. Cashin ONS Radwaste Chemistry REVISION NUMBER EFFECTIVE YEAR 49 2009

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 TABLE OF CONTENTS Executive Summary. Executive Summary- I 1.0 Radwaste Systems 1-1 1.0.1 Liquid Radwaste Processing 1-1 1.0.2 Gaseous Radwaste Processing . . 1-3 2.0 Release Rate Calculations 2-1 2.0.1 Liquid Release Rate Limit Calculations 2-1 2.0.1.1 Liquid Radwaste Effluent Line Release Rate Limit Calculation 2-1 2.0.1.2 #3 Chemical Treatment Pond Effluent Line Discharge 2-2 2.0.2 Gaseous Release Rate Limit Calculations . 2-5 2.0.2.1 Unit Vent Discharge Release Rate Limit Calculation 2-5 3.0 Setpoint Calculations 3-1 3.0.1 Liquid Radiation Monitor Setpoint Calculations .. . 3-1 3.0.2 Gaseous Radiation Monitor Setpoint Calculations . 3-5 3.0.2.1 Unit Vents Setpoints (RIA-45 and RIA-46) 3-7 3.0.2.2 Radwaste Facility Setpoints (4RIA-45) . 3-8 3.0.2.3 interim Radwaste Building Setpoints (RIA-53) 3-9 3.0.2.4 Waste Gas Decay Tank Setpoints (RIA-37 and RIA-38). 3-9 4.0 Effluent Dose Models 4-1 4.0.1 Liquid Effluent Dose Model for the Maximum Exposed Individual 4-1 4.0.2 Gaseous Effluent Dose Model for the Maximum Exposed Individual. 4-7 4.0.3 Direct Radiation 4-18 4.0.4 Effluent Apportionment .... 4-18 5.0 Fuel Cycle Calculations . 5-1 5.0.1 Milling 5-1 5.0.2 Conversion 5-1 5.0.3 Enrichment 5-1 5.0.4 Fuel Fabrication 5-1 5.0.5 Nuclear Power Production 5-2 5.0.6 Fuel Reprocessing 5-2 5.0.7 40CFR 190 Total Dose Determination 5-2 6.0 Environmental Locations . . 6-1 6.0.1 Site Description and Sample Locations 6-1 6.0.2 Land Use Census Data 6-1 6.0.3 Oconee Meteorology: Relative Air Concentrations and Deposition 6-8 6.0.3.1 XOQDOQ Methodology and Assumptions 6-8 6.0.3.2 Meteorological Data . 6-9 6.0.3.3 Annual XOQDOQ Comparison to the ODCM . . 6-10 7.0 Licensee Initiated Changes 7-1 i

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 Appendices Appendix A: Dose Factors for Exposure to a Semi-Infinite Cloud of Noble Gases A-I Appendix B: Pi Dose Factors for use in the Gaseous Release Rate Limit Calculations B-I Appendix C: Ai Adult Dose Factors for use in the Liquid Dose Calculations C-I Appendix D: Ai Teen Dose Factors for use in the Liquid Dose Calculations D-1 Appendix E: Ai Child Dose Factors for use in the Liquid Dose Calculations E-I Appendix F: Ai Infant Dose Factors for use in the Liquid Dose Calculations F-1 Appendix G: Ri Adult Dose Factors for use in the Gaseous.Dose Calculations G-I Appendix H: Ri Teen Dose Factors for use in the Gaseous Dose Calculations H-I Appendix 1: Ri Child Dose Factors for use in the Gaseous Dose Calculations I-I Appendix J: Ri Infant Dose Factors for use in the Gaseous Dose Calculations J-I LIST OF FIGURES 1.0-1 Liquid Radwaste System. 1-2 1.0-2 Gaseous Radwaste System (4 pages) 1-4 2.0-1 Liquid Radwaste Discharge Locations 2-4 6.0-1 Sampling Locations Map (Site Boundary). 6-5 6.0-2 Sampling Locations Map (Ten Mile Radius) 6-6 6.0-3 Land Use Census Map . . 6-7 LIST OF TABLES 3.0-i RIA-33 Cs-137 Equivalents. 3-4 3.0-2 Xe-133 Equivalents. 3-11 6.0-1 Sampling Locations. . 6-2 6.0-2 TLD Sites 6-3 6.0-3 Land Use Census Results. 6-4 6.0-4 Terrain Heights Above ONS Yard Grade Elevation (m) 6-9 6.0-5 ONS Atmospheric Stability Frequency (1988 - 1992) 6-10 6.0-6 ONS Frequency of Wind Direction and Speed (1988 - 1992) 6-10 6.0-7 ONS Limiting X/Q and D/Q Values (1988-1992) 6-11 6.0-8 ONS Delta-T Ranges per Vertical Separation Distances 6-11 6.0-9 Oconee Semi-Elevated x/Q and D/Q Average Values (1988-1992) 6-12 6.0-10 Oconee Ground Level x/Q and D/Q Average Values (1988-1992) 6-14 ii

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 EXECUTIVE

SUMMARY

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

(1) the concentration of radioactive liquid effluents released from the site to the unrestricted area will be limited to 10 times the effluent concentration (EC) levels of 10CFR20, Appendix B, Table 2, and 2.OE-04 ptCi/ml for dissolved and entrained noble gases; (2) the exposures to any individual member of the public from radioactive liquid effluents will not result in doses greater than the ALARA design objectives of IOCFR50, Appendix I or the 10CFR20 limits; (3) the dose rate at any time at the site boundary from radioactive gaseous effluents will be limited to: for noble gases; less than or equal to 500 mrem/yr to the whole body, and less than or equal to 3000 mrem/yr to the skin; and for iodine-131 and iodine-133, for tritium, and for all radioactive materials in particulate form with half-lives greater than 8 days; less than or equal to 1500 mrem/yr to any organ; (4) the exposure to any individual member of the public from radioactive gaseous effluents will not result in doses greater than the ALARA design objectives of IOCFR50, Appendix I or the 10CFR20 limits; and (5) the dose to any individual member of the public from the nuclear fuel cycle will not exceed the limits of 40CFR1 90.

The methodology and parameters F-used to assure compliance with the dose limitations described above shall be used to prepare the radioactive liquid and gaseous effluent reports required by the SLCs and Technical Specifications. Dose calculations that demonstrate compliance with 40CFR190 will be considered to demonstrate

  • compliance with the 10CFR20 0.1-rem annual dose limit. The ODCM also provides the Executive Summary - Page I

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 methodology and parameters to be used in the calculation of radioactive liquid and gaseous effluent monitoring instrumentation alarm /trip setpoints to assure compliance with the concentration and dose rate limitations of the SLCs and Technical Specifications. Normally RETDAS, a computer code that implements NUREG-0133 methodology, is used for the calculation of offsite doses, but the ODCM also provides a method for the calculation of offsite doses when RETDAS is not available.

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

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

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

Executive Summary - Page 2

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 1.0 RADWASTE SYSTEMS 1.0.1 LIQUID RADWASTE PROCESSING The liquid radwaste system at Oconee Nuclear Station is used to collect and treat liquid chemical and radiochemical byproducts of unit operation. The system produces effluents that are discharged in small, dilute quantities to the environment. The means of treatment vary with waste type and desired product in the various systems:

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

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

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

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

Section I - Page I

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 Figure 1.0-10Oconee Nuclear Station Liquid Radwaste System E.

GA COOE. ISCMARGE KEGW£E LAKE RAASýTE SMIELDED FAGILITI SWP -

AREA YSE DRAINSFROM.  %'EI GE-lCEWATER

. . RT-N SISTEM -

MAlEAWASTEEEAPORAA-1.A" SOAGR P-IFICATIOMGMI-RIZER SEMERGNSIM.*

FI - ,.G' SPENTFUELSYSTEM

_,.ESAETESTAR*

FUEL T,**4EAF:_

20-4 S*LE ANK1GE CrMC*LI.- / FNE. - I CE.TGALG Y~E C0NrEAAC-ATESTTANK1 SPENTFUEL COE-MR Section 1 - Page 2

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 1.0.2 GASEOUS RADWASTE PROCESSING The purpose of the gaseous waste disposal system is to:

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

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

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

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

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

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

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

Section I - Page 3

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 Figure 1.0-2 Oconee Nuclear Station Gaseous Radwaste System Page 1 of 4 VENT HT 200 FT Section 1 - Page 4

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 Figure 1.0-2 Oconee Nuclear Station Gaseous Radwaste System Page 2 of 4 UNIT VENT I2-RIASE UNIT 2 HEIGHT 200 FT PENETRATION ROOM VENTILATION SYSTEM ~A-32 UNIT 2 REACTOR BUILDING UNIT 2 E C O UL N R F LT R I T R D O B R UNIT I & 2 SPENT FUEL - POOL AREA RA CONDENSER FOR EJECTOR STEAM SYSTEM GAS FROM STEAM GENERATOR TUBE LEAK ,

AI R EJCO HOTWELL-*

DECONTAMINATION AND FUME HOODS AUXILIARY BUILDING VENT MULTIPLE AUXILIARY STA-1 N GROUND STATIO BUILDING LOCATIONS L EVEL L

Section I- Page 5

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 Figure 1.0-2 Oconee Nuclear Station Gaseous Radwaste System Page 3 of 4 VENT IT 200 FT Section 1- Page 6

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 Figure 1.0-2 Oconee Nuclear Station Gaseous Radwaste System Page 4 of 4 HOT MACHINE SHOP VENTILATIONSYSTEM PRFLE EP OAIE EXHAUST

  • [ I~o*

PARTICULATEsAML&

WELDING HOOD - RFITR HP INTERIM RADWASTEFACILITY VENTILATION SYSTEM EXAT RADWASTE BUILDING LOW EXHAUST VENTILATION SYSTEM FLOW EXHAUST TANK VENTS & LAB HOODS HEPH HNO CARBONFILTEH HEPH HNO PRTICUOI TE & 4RIA-45 CARBON FILTER IODINE SMPLER VR SYSTEM OFF-GAS HEPH FIL0T CHRBON HLA ER .EXHHUST VENTILATION SYSTEM FO Section 1.- Page 7

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 2.0 RELEASE RATE CALCULATIONS 2.0.1 LIQUID RELEASE RATE LIMIT CALCULATIONS There are two liquid radwaste discharge points to the environment at Oconee; (1) the liquid radwaste effluent line to the Keowee Hydroelectric Unit Tailrace, and (2) the #3 Chemical Treatment Pond effluent line to the Keowee River (See Figure 2.0-1).

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

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

f< F - (DF-1) Condition: DF> 1.0 Equation 2.1 where:

f = the undiluted effluent flow, in gpm.

F = the dilution flow available, in gpm.

= normally 3.41E+04 gpm (76 cfs, based on a leakage rate of 38 cfs (19 cfs per.

Keowee Hydro unit), plus the Keowee Hydro Fire Protection liquid waste release Section 2 - Page 1

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 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.

DF=(10 x EC,) 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.

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

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

ECi = the concentration of radionuclide, 'i', from IOCFR20, Appendix B, Table 2, Column 2, in itCi/ml. Note: if radionuclide, 'i', is a dissolved noble gas, then ECi

= 2.OOE-05 pCi/ml.

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

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

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 monitors associated with them will be set to assure that Selected Licensee Commitment 16.11-1 will not be exceeded. #3 CTP is a continuous release path that discharges to the Keowee River (see Figure 2.0-1).

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

Section 2 - Page 3

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 Figure 2.0-1 Liquid Radwaste Discharge Locations Lake Keowee Visitors ./. Keowee / n7 bente&' Dam Discharge . KeoweeTa*-*r\"

Release'Point Oconee Nuclear -

(iU~

Section 2 - Page 4

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 2.0.2 GASEOUS RELEASE RATE LIMIT CALCULATIONS The three unit vents are the primary gaseous radioactive release points at Oconee. The unit vents are the semi-elevated release points for waste gas decay tanks, containment building purges, auxiliary building ventilation, spent fuel pool ventilation, and the condenser air ejector (see Figure 1.0-2, pages 1, 2, and 3). Each unit vent contains multi-range radiation monitors (RIAs) and flow rate measuring instrumentation.

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

2.0.2.1 UNIT VENT DISCHARGE RELEASE RATE LIMIT CALCULATION In order to comply with Technical Specifications and Selected Licensee Commitments and to assure that the dose rate, at any time, at or beyond the site boundary due to radioactive materials released in gaseous effluents from the site is limited to: < 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:

X(KXZxQ < 500mrem/yr Equation 2.3 Skin:

X((Li+,I .IM)xZ-I-xQi < 3000 mrem/yr Equation 2.4 Section 2 - Page 5

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49

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

I Z(P~pi x W x Qi x Ei) < 1500mrem/yr p I To include both the food and ground organ dose and the inhalation organ dose the equation can be expanded to:

-({(Pop:)foodgr Q X WD 0 + (Pop, ).hat X WX/0} x Q x Ei) < 1500mrem/yr

p. i Equation 2.5 where:

Ki = the total body dose factor due to gamma emissions for each identified noble gas radionuclide, 'i', in mrem/yr per ptCi/m 3 (See Appendix A).

L, = the skin dose factor due to beta emissions for each identified noble gas radionuclide, 'i', in mrem/yr per pCi/mn 3 (See Appendix A).

M = the air dose factor due to gamma emissions for each identified noble gas radionuclide, 'i', in mrad/yr per ptCi/m 3 (See Appendix A).

Pop, the dose parameter for radionuclides other than noble gases for the inhalation pathway, in mrem/yr per p[Ci/mn3 and for the food and ground plane pathways in (i 2 x (mrem/yr per [tCi/sec)) for organ, 'o', and radionuclide, 'i', (See Appendix B for the pathway specific dose commitment factors). Note: NUREG-1301, page 75, specifies use of the Child age group, Inhalation pathway, for the Popi values.

X/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:

Section 2 - Page 6

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 Wz/Qse = 1.672E-6 sec/mr3, 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.

Wz/QgI = 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 = the filter removal factor for radionuclide, 'i', e.g., for 99% removal E, = 0.01.

For iodine removal by charcoal adsorbers E1 = 0.1.

For particulate removal by HEPA filters E, = 0.01.

Qj =the release rate of radionuclide, 'i', in gaseous effluent from all release points at the site, in ptCi/sec.

Q= kiCf + k2 = 4.72E + 02 x Cf Equation 2.6 where:

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

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

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

k = conversion factor, 6.OE+01 sec/min.

Substituting the expression for Q1 in Equation 2.6 into Equations 2.3, 2.4, and 2.5, and solving for the flow rate, 'f, in each equation'gives:

Noble Gases - Total Body Maximum Release Rate:

500 fib<

4.72E+02 x X/Q x (Ki x Ct)

Section 2 - Page 7

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 Noble Gases - Skin Maximum Release Rate:

fk <3000 4.72E+02 x X - [(L,+ 1.1M) x Ci]

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

1500 4.72E+02 x "({(Pop,)foo-dg, X'WD'Q + (Popi)imh.1 X Wx/Q Ix x C,)

p i fb, fik, and for, are calculated for each batch prior to release. The most limiting gaseous release rate is used to assure that no instantaneous dose rate limit is exceeded.

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

Section 2 - Page 8

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 Derivations of Iodine, Particulate, and H-3 Dose Commitment Factors (Popi) 0 Inhalation Pathway - Child Age Group Pi = K'(BR )(DFA o)

Formula: from NUREG-0133, page 25.

Where:

Popi Dose commitment factor for Child age group, organ o, nuclide i, for the inhalation pathway (mrem/yr per *tCi/m 3). (See Appendix B for the pathway specific dose commitment factors).

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

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

Child - 3700 DFAoi Organ inhalation dose conversion factor for Child age group, organ o, 1 nuclide i, (mrem/pCi), from Table E-9 of Regulatory Guide 1.109.

Section 2 - Page 9

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 3.0 SETPOINT CALCULATIONS 3.0.1 LIQUID RADIATION MONITOR SETPOINT CALCULATIONS As shown on Figure 1.0-1, RIA-33 is the controlling radiation monitor for liquid batch releases at Oconee. Once the liquid release rate parameters have been established radiation monitor setpoints shall be calculated to assure that the concentration of radioactive liquid effluents released from the site to the unrestricted area is limited to ten times the effluent concentrations (ECs) of 10CFR20, Appendix B, Table 2, Column 2, and 2.OE-04 p.Ci/ml for dissolved and entrained noble gases., By substituting the dilution factor (DF) from Equation 2.2 into Equation 2.1, solving for the undiluted liquid effluent concentration, Ci, and accounting for the monitor background reading, the liquid radiation monitor setpoint can be readily obtained by multiplying Ci by the radiation monitor correlation factor, CFi, as follows:

EC,)

Ci-< (F + f) x (10 x Equation 3.1 (Cxf SP <- Z (c1 x CF,) + bkg Equation 3.2 where:

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

SP = radiation monitor setpoint, in cpm.

CF, = radiation monitor correlation factor for radionuclide, 'i', in cpm/tCi/ml, e.g.,

8.OOE+07 cpm/ýtCi/ml (Cs-137) for RIA-33.

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

All other parameters were previously defined.

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

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

Oconee Nuclear Station " January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 tailrace the RIA-33 radiation monitor setpoints are calculated based on the actual expected activity in the release as follows:

First the "Correlation Concentration" (C CONC) is calculated' C CONC = (CG x EQ,)

where:

C1 = Undiluted liquid effluent concentration for each isotope, excluding tritium, ltCi/mnl.

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

Next the RIA-33 setpoints are determined as follows:

If C CONC is > 9.OE-6 jtCi/ml then three setpoint values are calculated.!! The actual "expected" count rate for the release is defined as the "Midpoint of Expected Range".

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

Lower Limit of Expected Range = C CONC x (8.00E7/3) 6pm/(QiCi/ml) +

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

RIA-33 BKG Alert Setpoint = C CONC x (8.OOE7x 1.5) cpm/(laCi/ml) +

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

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

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 If C CONC is _ 9.OE-6 jtCi/mi then the RIA-33 setpoint is 2.16E3 cpm (9.OE-6 x 8.00E7 x 3) plus background (BKG) as the "Upper Limit of Expected Range". This setpoint is used for low activity releases, and is based on limiting the concentration in the effluent to 10 times the IOCFR20 EC of Cs-134 which has the lowest effluent concentration value (9.OE-7 tCi/mi) for any detectable radionuclide in the effluent. Similarly, the RIA-33 "Alert" setpoint for low activity releases is 1.08E3 cpm (9.OE-6 x 8.00E7 x 1.5) plus background (BKG).

Section 3 - Page 3

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 Table 3.0-1 RIA-33 Cs-137 Equivalents isotope Equivalence Isotope Equivalence Isotope Equivalence Factor Factor Factor Be-7 0.1462 Mo-99 0.2668 La-141 0.0155 F-18 0.5788 Tc-99m 0.00 La-142 0.2942 Na-24 0.8519 Tc-101 0.00 Ce-141 0.00 CI-38 0.0090 Ru-103 1.3368 Ce-143 0.7826 K-40 0.1094 Ru-105 0.8783 Ce-144 0.0273 Cr-51 0.1438 Ru-106 0.4429 1-130 3.3095 Mn-54 1.0617 Ag-108m 3.4473 1-131 1.4051 Mn-56 0.4992 Ag-110m 3.5179 1-132 1.0259 Fe-59 1.0556 Cd-ll5 0.5201 1-133 1.1857 Co-57 0.0022 Cd-ll5m 0.0235 1-134 0.1388 Co-58 1.4735 In-115m 0.3631 1-135 0.9374 Co-60 2.0495 Sb-122 0.9218 Ar-41 0.2229 Cu-64 0.3954. Sb-124 2.1617 Kr-85 0.0059 Ni-65 0.1591 Sb-125 1.1308 Kr-85m 0.4280 Zn-65 0.5584 Sb-126 5.1762 Kr-87 0.1213 Zn-69m 1.1391 Sn-113 0.9971 Kr-88 0.5278 Se-75 1.3092 Sn-123 0.0066 Kr-89 0.00 Br-80m 0.0860 Sn-126 0.00 Xe-131m 0.0167 Br-82 3.4691 Te-125m 0.00 X6-133 0.0006 Br-83 0.0059 Te-127 0.0134 Xe-133m 0.1172 Br-84 0.0053 Te-127m 0.0001 Xe-135 0.8564 Br-85 0.00 Te-129 0.0138 Xe-135m 0.00 Rb-86 0.0894 Te-129m 0.0507 Xe-137 0.00 Rb-88 0.00 Te-131 0.0008 Xe-138 0.00 Rb-89 0.00 Te-131m 1.8463 Nd-147 0.2619 Sr-89 0.0002 Te-132 0.9766 Hf-181 1.4209 Sr-91 0.6460 Te-134 0.0408 W-187 0.8027 Sr-92 0.3900 Cs-134 2.5804 TI-208 0.00 Y-91 0.0031 Cs-136 3.1916 Bi-212 0.0144 Y-91m 0.0439 Cs-137 1.00 Bi-214 0.0003 Y-92 0.1334 Cs-138 0.0120 Pb-212 0.4497 Y-93 0.1091 Ba-133 1.3648 Pb-214 0.0020 Zr-95 1.0909 Ba-139 0.0203 Ra-226 0.0320 Zr-97 1.1210 Ba-140 0.5307 Ac-228 0.8261 Nb-95 1.0821 Ba-141 0.0002 Th-228 0.0038 Nb-95m 0.2919 Ba-142 0.00 Np-239 0.3996 Nb-97 0.1164 La-140 2.3237 1_1__

Section 3 - Page 4

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 3.0.2 GASEOUS RADIATION MONITOR SETPOINT CALCULATIONS The unit vent radiation monitor setpoints are established at the Oconee Nuclear Station to help ensure that gaseous release rate limits are not exceeded. For some release pathways in which a specific RIA exists, the setpoints also help to ensure that the effluent being released is the same concentration as indicated by manual samples, e.g. effluent from waste gas decay tanks, thereby reducing the likelihood of releasing the wrong tank. For instances in which the RIA which normally controls the release is not operable, or is "out of service", independent manual samples (IMS) are collected and the noble gas constituents from both samples are compared to help ensure that the intended' "batch" is being released. For certain low potential release types, e.g. Integrated Leak Rate Tests, no RIA exists to ensure that release rate limits are not exceeded or to ensure that the effluent being released is the "expected" concentration. For such pathways, independent manual samples are required to be collected and noble gas constituents compared prior to release. The following list defines the controlling RIA for the various gaseous effluent release types at Oconee:

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

Section 3 - Page 5

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 Note: when applied to the individual release points the 500 mrem/year site dose rate value is apportioned 30% to each Unit Vent (RIA-45 and RIA-46) semi-elevated release point.

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

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

S 500 Qxe - 133 < 50 Kx'e-133 )x,//

Equation 3.4 From Equation 2.6:

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

4.72E + 02 Cx- 133 X f < 500 Kne-133 z/Q "X

Solve for CXe-133:

500 CXe - 133 <

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

KXe-133 = 2.94E+02, the total body dose factor due to gamma emissions for Xe-133, in mrem/year per jtCi/m 3 (See Appendix A).

X/Q = the highest calculated semi-elevated annual average dispersion parameter for any area at or beyond the site boundary in sec/m 3. For Oconee this value is 1.672E-6 sec/m 3. The location is the SW sector at 1.0 mile.

Qxe-133 Xe-133 equivalent release rate limit for the noble gastotal body dose pathway, in /tCi/sec.

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

Section 3 - Page 6

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 CXe-133 = the maximum allowable Xe-133 equivalent concentration in the gaseous effluent,, in ýtCi/cc.

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

SP radiation monitor setpoint, in cpm.

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

bkg = the radiation monitor background reading, in cpm.

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

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

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

Recall Equation 3.6:

CXe - 133 SP - + bkg CF where:

500 CXe - 133 <

4.72E+02 x f x KXe-133 X.X RA -45ui vent = 150 4.72E + 02 x 6.5E + 04 x 2.94E + 02 x 1.672E- 06 x 7.09E- 08 R/A - 45u,, vent 1.40E + 05 cpm + bkg Section 3 - Page 7

Oconee Nuclear Station January, 2009 OffsiteDose Calculation Manual (ODCM) Revision 49 where:

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

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

1.672E-06 = Highest Semi-Elevated release point dispersion; factor, sec/m3n 7.09E-08 = RIA-45 Correlation Factor, ýtCi/ml/cpm.

All other factors were previously defined.

RIA - 6ui vent=

150 "

4.72E+02 x 6.5E+04 x 2.94E+02 x 1.672E-06 x 3.1'7E-04 RIA -46,tv._t 31 cpm + bkg where:

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

All other factors were previously defined.

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

3.0.2.2 RADWASTE FACILITY SETPOINTS (4RIA-45) 4R/ 45 =25 4-4.72E+02 x 1.297E+05 x 2.94E+02 x 7.308E-06 4R/A - 45 1.90E - 041 tCi/ml where:

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

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

3 7.308E-06 = Highest Ground-Level release point dispersion factor, sec/r .

All other factors were previously defined.

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

Section 3 - Page 8

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 3.0.2.3 INTERIM RADWASTE BUILDING SETPOINTS (RI*A-53) 25 RIA-53-=

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

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

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

7.308E-06 = Highest Ground-Level release point dispersion factor, sec/m 3.

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

All other factors were previously defined.

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

Each unit vent Alert setpoint is based on 60% of a Xe-133 Effluent Concentration (EC) value of 5.OE-07 ýtCi/ml at the site boundary. The Interim Radwaste Building and Radwaste Facility are each set at 10% of the Xe-133 EC. The method usedto calculate the Alert setpoints is similar to that used to calculate the maximum setpoints except that the limit is based on concentration rather than. dose rate. The Alert setpoints are approximately 42% of the maximum setpoints.

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

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

CXe - 13 = (c x Eq,)

CXe - 133 Expected Cpm = + bkg CFXe - 133 RIA - 37 and RIA - 38 Setpoint - Cxý - 133 x 1.5 Equation 3.7 SCFXe- 133 Section 3 - Page 9

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 where:

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

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

(See Table 3.0-2).

CFxe- 33 .= The expected RIA response to a given Xe-133 equivalent concentration, in

[tCi/ml/cpm. 1RIA-37.= 4.20E-08 ýtCi/ml/cpm, 3RIA-37 = 4.20E-08 ptCi/ml/cpm, 1RIA-38 and 3RIA-38 = 1.34E-03 ptCi/ml/cpm.

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

bkg = The radiation monitor background reading, in cpm.

When the release pathway is from any Unit I WGDT (A-D); and the Xe-13,3 equivalent concentration is less than 2.8E tCi/ml, the 1&2 RIA-38. setpoint is established at 313 cpm, and the 1&2 RIA-37 setpoint is calculated using Equation 3.7.

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

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

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

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

Section 3 -Page 10

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 Table 3.0-2 Xe-133 Equivalents Isotope Equivalence Factr" Kr-83m 0 Kr-85m 2.48 Kr-85 2.56 Kr-87 2.93 Kr-88 2.78 Kr-89 2.93 Kr-90 2.93 Xe-131m 1.69 Xe-133m 1.99 Xe-133 1.0 Xe-135m 0.83 Xe-135 2.63 Xe-137 2.93 Xe-138 2.93 Ar-41 2.82 C-11 2.70 Section 3 - Page 11

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 4.0 EFFLUENT DOSE MODELS The effluent dose models used to show compliance with I OCFR50, Appendix I ALARA design objectives, 40CFR190 fuel cycle dose limits, and the dose values given in station SLCs are based on the methodology given in NUREG-0 133 and Regulatory Guide 1.109.

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

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

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

Dose contributions shall be calculated using the RETDAS computer program.

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

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

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 through RIA-33. In general, only low activity tritium releases (<1% station total) occur through the Chemical Treatment Pond #3 discharge point into the Keowee River. Dose calculations are performed for each of the two liquid discharge points for dose reporting purposes. The highest calculated dose from the two dose calculations is used to define the maximum individual dose from liquid releases at Oconee.

Section 4 - Page 2

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 Liquid Dose Calculations The following equation is used for calculating liquid dose to the maximum exposed individual at each of the two liquid effluent release points:

A, x xC)XAtXFn X Ix Doseoa = I-I L.w p i f

Ffxo X f+F Formula: adapted from NUREG-0133; pages 15-17. Where:

Doseoa The cumulative dose commitment for organ o and age group a, from the liquid effluent for the total time period, At. (mrem)

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

Ci The average concentration of nuclide i, in undiluted liquid effluent during the time period, At. (.tCi/ml)

At The length of time over which Ci and F, are averaged for all liquid releases. (hr)

F, The near field average dilution factor for Ci during the period of interest, At. Includes the recirculation factor. (dimensionless) f Average liquid radwaste flow during the period of interest, At. (gpm)

F Average dilution flow during the period of interest, At. (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.

a Recirculation factor. (dimensionless)

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

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

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

Therefore, the recirculation factor is 1.0 at Oconee.

Section 4 - Page 3

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 Derivation of Liquid Dose Commitment Factors (Aoapi)

Potable Water Aoapi =w1. 14x10' x xDaoixe-&to Formula:. from NUREG-0133, page 16 and Regulatory Guide 1.109, page 1.109-12.

-Where:

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

5 1.14x 10 Units conversion factor (pCi-yr-ml)/(utCi-hr-kg).

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

Adult - 730 Teen - 510 Child-510 Infant - 330 Daoi Dose factor for age group a, organ o, nuclide i, in mrem/pCi. From

_ _tables E- I1through E- 14 of Regulatory Guide 1.109.

ki Decay constant for nuclide i, in sec-.

tp Environmental transit time from release to receptor. Default =

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

Section 4 - Page 4

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 Aquatic Foods AAoapi -=1.14x10 5 xUa' xBFxDaoix et af Formula: from NUREG-0133, page 16 and Regulatory Guide 1.109, page 1.109 Where:

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

.14xx 105 Units conversion factor (pCi-yr-ml)/(ýiCi-hr-kg).

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

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

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

Xi Decay constant for nuclide i, in sec-.

tp Environmental transit time from release to receptor. Default =

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

Section 4 - Page 5

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 Shoreline Sediment Aoapi =1.14x0 5 xlOOxDFGoiXWxUasxT xIe x(I e-tb Formula:: adapted from Regulatory Guide 1.109, page 1.109-14.

Where:

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

1.14x 105 Units conversion factor (pCi-yr-ml)/(ptCi-hr-kg).

100 Proportionality constant used in the sediment radioactivity model, (liters/(m 2-day).

DFGoi Ground plane dose conversion factor for organ o, nuclide i (mrem/hr per pCi/mi2), from Table E-6 of Regulatory Guide 1.109.

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

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

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

,i Nuclide decay constant for nuclide i.

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

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

Section 4 - Page 6

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 4.0.2 GASEOUS EFFLUENT DOSE MODEL FOR THE MAXIMUM EXPOSED INDIVIDUAL The dose contributions from measured quantities of radioactive materials identified in gaseous effluent released to unrestricted areas shall be calculated for the maximum gamma and beta air dose from noble gases, and for the maximum exposed individual from radioiodines, particulates, and others using the following equations:

Gaseous Dose Calculations Noble Gas Dose Calculations Gamma Air Dose Dose, =3.17x10-8 xz/QX -(MixQ i)

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

Where:

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

3.17x 10-8 Inverse number of seconds in year (year/seconds).

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

z/Q .Iarea The highest calculated at or beyond annual the site average boundary relative (sec/m concentration 3)*. (See for any Table 6.0-9). I Qi Activity for nuclide i released during the time period of interest (UtCi).

Beta Air Dose Dosef =3.17x10- 8 x /Qxj(Nx Q,)

Formula: adapted from NUREG-0133, page 28.

Where:

Doser3 Beta air dose for the time period of interest (mrad).

3.17x 10-8 Inverse number of seconds in year (year/seconds).

Ni Beta air dose factor due to beta emissions for nuclide i (mrad/yr per

ýLCi/m 3). (See Appendix A).

x/Q The highest calculated annual average relative concentration for any area at or beyond the site boundary (sec/m 3)*. (See Table 6.0-9).

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

0 Section 4 - Page 7

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 Iodine, Particulates, and H-3 Dose Organ Dose Calculation Dose oa = 3.17 x lO-8 x W x Y (Roapi X QJ) p i Formula: adapted from NUREG-0133, pages 29`& 30.

Where:

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

3.17x 10- 8 Inverse number of seconds in year (year/seconds).

Roapi Dose commitment factor for organ o, age group a, pathway p, and nuclide i. The units are based on whether a dispersion or deposition factor is used. When a x,/Q is used the units are.mrem/yr per ltCi/m 3.

When a D/Q is used the units are (M2 mrem/yr) per ýtCi/sec. (See Appendices G through J for age group and pathway specific dose commitment factors).

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

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

Inhalation X/Q (sec/m 3 )

Vegetation D/Q (m-2)

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

Grass/Goat/Milk D/Q (m2 )

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

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

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

Section 4 - Page 8

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 Derivations of Iodine, Particulate, and H-3 Dose Commitment Factors (Roapi)

Ground Plane Denosition Pathway Roapi =K'K"(SF)DFGOI i A Formula: from NUREG-0133, page 32.

Where:

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

K' Units conversion factor pCi/ýtCi (1.06).

K" Units conversion, factor 8760 hr/year.

SF Shielding factor (dimensionless) (0:7, from Regulatory Guide 1.109).

DFGoi Ground plane dose conversion factor for organ o, nuclide i (mrem/hr per pCi/mr2), from Table E-6 of Regulator: Guide 1.109.

X* Nuclide decay constant for nuclide i (sec-).

t Exposure time, 4.73xx108 seconds (15 years).

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

Where:

Roapi Dose commitment factor for organ o, age group a, nuclide i, for inhalation pathway (mrem/yr per uiCi/m 3).. (See Appendices G through J for age group and pathway specific dose commitment factors).

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

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

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

Section 4 - Page 9

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 Vegetation Roap= K1L (r) x(DFL oJ)a x [ULfLeAAtL + U fge~2At/ ]

Yv+,+A)

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

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

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

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

1.0 for radioiodine.

0.2 for particulates.

Yv Vegetation areal density (kg/m 2) (2.0, from Regulatory Guide 1.109).

'Xi Nuclide decay constant for nuclide i (secl).

kw. Decay constant for removal of activity on leaf and plant surfaces by weathering (5.73 x 107 set-', from NUREG-0 133).

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

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

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

tL Average time between harvest of leafy vegetation and consumption 1 (8.6x 104 seconds, (1 day), from Regulatory Guide 1.109).

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

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

th Average time between harvest of stored vegetation and consumption (5.18x 106 seconds, (60 days), from Regulatory Guide 1. 109).

Section 4 - Page 10

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 Vegetation - Tritium Roapi -- ' K'"[ LU +UU fg](DFLo0[0.75(O.5 / H)]

Formula: from NUREG-0133, page 36.

Where:

Roapi Dose commitment factor for organ o, age group a, for vegetation pathway and tritium (mrem/yr per ýtCi/m 3)* (See Appendices G through J for age group and pathway specific dose commitment factors).

K' Units conversion factor pCi/!tCi (106).

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

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

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

Usa Consumption rate of stored vegetation for age group a (kg/yr) (from RegulatoryGuide 1.109).

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

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

0.75 "Fraction of total feed that is water, (From NUREG-0 133).

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

(From NUREG-0 133).

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

Section 4 - Page 11

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 Grass/Cow/Milk RoUp, = K ' QAiF (U+ A2p ) F4, F (r)( DFL j) f

, Yp + 1 7fpf,)e- A'ý~ ]e -

Formula: from NUREG-0133, pages 32 & 33. Where:

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

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

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

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

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

1.0 for radioiodine.

0.2 for particulates.

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

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

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

X* Decay constant for removal of activity on leaf and plant surfaces by weathering (5.73x 10-7 sec- 1, from NUREG-0 133).

(DFLoi)a Ingestion dose conversion factor for nuclide i, organ o, and age group a, from Tables E-1 1 through E-14 of Regulatory Guide 1.109 (mrem/pCi).

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

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

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

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

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

Section 4 -Page 12

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 Grass/Cow/Milk - Tritium Roapi K' K' FmiQfUap(DFLio)a[0.75(0.5 / H)]

Formula: from NUREG-0133, page 34.

Where:

Roapi Dose commitment factor for organ o, age group a, nuclide i, for grass/cow/milk pathway (mrem/yr per ýtCi/m 3). (See Appendices G through J for age group and pathway specific dose commitment factors).

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

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

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

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

Adult - 310 Teen- 400 Child - 330 Infant - 300 (DFLoi)a Ingestion dose conversion factor for nuclide i, organ o, and age group a, from Tables E- I1through E-14 of Regulatory Guide 1.109 (mrem/pCi).

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

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

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

H Absolute humidity of the atmosphere (8 gm/mi3, from Regulatory I Guide 1.109).

Section 4 - Page 13

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 Grass/Goat/Milk Roapi =K F Fmi(r)(DFLoi)a.fpI + (I- f)e e ,t Formula: from NUREG-0133, pages 32 & 33. Where:

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

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

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

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

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

1.0 for radioiodine.

0.2 f6r particulates.

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

Y, Agricultural productivity by unit-area of stored feed (2.0 kg/m 2, from Regulatory Guide 1.109).

X* Nuclide decay constant for nuclide i (sec-).

X* Decay constant for removal of activity on leaf and plant surfaces by weathering (5.73x 10-7 sec-1 , from NUREG-0 133).

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

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

f0 Fraction of year that the goat is on pasture (1.0, from RG 1.109).

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

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

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

Section 4 -Page 14

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 Grass/Goat/Milk - Tritium Roapi =K'K"'FmiQfUap(DFLoi)a[0.75(0.ý51/H)]

Formula: from NUREG-0133, page 34.!

Where:

Roapi Dose commitment factor for organ o, age group a, nuclide'i, for grass/goat/milk pathway (mrem/yr per ýtCi/m 3): (See Appendices G through J for age group and pathway specific dose commitment factors).

K'. Units conversion factor pCi/[LCi (106).

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

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

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

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

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

0.75 Fraction of total feed that is water (from NUREG-0 133).

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

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

Section 4 -Page 15

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 Grass/Cow/Meat K' QF(Uap)

K Fapi(r)(DFLIL [fff (1 - fpf-)e,-Ath eAt f)

Formula: from NUREG-0133,:pages-34 & 35. Where:

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

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

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

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

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

1.0 for radioiodine.

0.2 for particulates.

Yp Agricultural productivity by unit area of pasture feed grass (0.7 kg/m 2 , from Regulatory Guide 1.109).

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

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

Xw Decay constant for removal of activity on leaf and plant surfaces by weathering (5.73x 10-7 sec', from NUREG-0133).

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

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

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

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

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

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

Section 4 - Page 16

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 Grass/Cow/Meat - Tritium Roapi = K' KF "'FfQFUap(FLoi)a[0.75(0.5 / H)]

Formula: from NUREG-0133, page 35.

Where:

Roapi Dose commitment factor for organ o, age group a; nuclide ýi,for grass/cow/meat pathway (mrem/yr per jiCi/m 3). (See Appendices G through J for age group and pathway specific dose commitment factors).

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

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

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

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

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

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

0.75 Fraction of total feed that is water (from NUREG-0 133).

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

H Absolute humidity of the atmosphere (8 gm/m 3 , from Regulatory Guide 1.109).

Section 4 - Page 17

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 4.0.3 DIRECT RADIATION Direct radiation is that radiation from confined sources, and does not include any external component from radioactive effluents. The point kernel method has been used to calculate offsite dose rates from radioactive materials stored in the refueling water storage tanks, reactor makeup water storage tanks, and temporary onsite radwaste storage tanks. Dose calculations using this method performed for Oconee Nuclear Station indicate negligibledirect radiation doses are much less than 0.01 mrem/yr and, therefore, make a contribution to individual dose.

Likewise, direct and air-scatter radiation dose contributions from the onsite Independent Spent Fuel Storage Installation (ISFSI) at Oconee have been calculated and documented in the "Oconee Nuclear Site 10CFR72.212 Written Evaluations" report The results of

-the calculation demonstrate that conservatively assuming 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> of occupancy per year the annual dose at the nearest controlled area boundary (approximately, 300 meters) is below the 10CFR72.104(a) and 40CFRI90.10(a) limit of 25 mrem from direct and skyshine radiation. Since it is demonstrated, that with a conservative occupancy assumption the doses at the controlled area boundary are within limits, it can easily be concluded that the dose to a "real individual" is Within the same limits. The closest residence to the ISFSI is in the SW-SSW direction approximately 1 mile (-1600 meters) from the ISFSI, or 1.36 miles from the centerline of the site. The maximum dose rate dose to the nearest resident from the Oconee ISFSi' assuming 100% occupancy time is estimated to be much less than 1 mrem/yr.

Direct radiation doses will not be calculated routinely.

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

Section 4 - Page 18

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 5.0 FUEL CYCLE CALCULATIONS In accordance with the requirements of 40CFR190, the annuIal dose commitment to any member of the general public shall be calculated to assure that doses are limited to 25 millirems to the total body or any organ with the exception of the thyroid which is limited to 75 millirems. In accordance with the requirements of the Selected Licensee Commitments, the annual dose commitment shall also be calculated any time that one of the quarterly dose limits of the Selected Licensee Commitments is exceeded; these annual' dose commitments may not just be calculated for the calendar year.

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

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

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

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

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

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

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

Section 5 - Page 1

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 5.0.5 NUCLEAR POWER PRODUCTION The production of electricity for public use using light-water-cooled nuclear power stations results in increments of dose to individuals within fifty miles of any station due to liquid and gaseous effluent releases and direct radiation or skyshine. The increments of dose resulting from liquid and gaseous effluent releases will be calculated using the ODCM methodology implemented in the RETDAS computer program. The dose from direct radiation, skyshine, and radiation from the station storage facilities has been estimated using conservative assumptions (see Section 4.0.3).

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

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

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

5.0.7 40CFR190 TOTAL DOSE DETERMINATION To summarize, only dose increments from nuclear power production operations (Section 5.0.5) need be considered in calculations to demonstrate compliance with the requirements of 40CFRI 90. The fuel cycle dose assessments for Oconee Nuclear Station only include liquid and gaseous dose contributions from Oconee and dose from Oconee's ISFSI since no other uranium fuel cycle facility contributes significantly to Oconee's maximum exlposed individual. For this dose assessment, the total body and maximum organ dose contributions to the maximum exposed individual from Oconee's liquid and gaseous effluents are estimated using the following calculations:

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

DOo(T) = DO,(l) + Dmo(g) where:

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

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

Section 5 - Page 2

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 6.0 ENVIRONMENTAL LOCATIONS 6.0.1 SITE DESCRIPTION AND SAMPLE LOCATIONS Oconee Nuclear Station (ONS) is located in Oconee County, South Carolina, approximately 8 miles northeast of- Seneca, South Carolina, on the shore of Lake Keowee. This lake was formed by, damming the Keowee and Little Rivers in that location. Immediately to the south is the U.S. Government Hartwell Project. The Keowee Hydroelectric Plant near the station joins Lake Keowee and the upper reaches of Lake Hartwell. To the north, the Jocassee Hydroelectric Plant joins Lake Jocassee and Lake Keowee. Jocassee is a pumped storage plant. The ONS exclusion area boundary is 1 mile.

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

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

Section 6 - Page 1

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 TABLE 6.0-1 OCONEE RADIOLOGICAL MONITORING PROGRAM SAMPLING LOCATIONS Table 6.0-1 Codes '

W Weekly SM Semimonthly BW BiWeekly Q _ Quarterly M Monthly SA Semiannually C Control

Site ocation Description* Le Air Rad. &

Partseulate

.Suface W ater Diinking Shoreline -. Fish -Milk Broadleaf Water Sediment. - Vegetation 060 Greenville Water Intake Road (3.23 NE) M 060 C ** Greenville Water Intake Road (2.28 NE) SA 062 C Lake Keowee Hydro Intake (0.85 mi ENE) M Lake Hartwell Hwy 183 Bridge 063 (0.80 mi ESE) [000.7] SA SA 063.1 Lake Hartwell Hwy 183 (0.79 mi E) M 064 C Seneca (6.67 mi SSW) [004.1] M 066 Anderson (18.9 mi SSE) [012] M Lawrence Ramsey Bridge Hwy 27 067 (4.34 mi SSE) [005.2] SA SA 068 C High Falls County Park (1.82 mi W) SA 071 C Clemson Dairy (10.2 mi SSE) [006.3] SM 074 Keowee Key Resort (2.36 mi NNW). W 077 Skimmer Wall (1.00 mi SW) W M 078 Recreation Site (0.58 mi WSW) W 079 Keowee Dam (0.56 mi NE) W _ M 081 C Clemson Operations Center (9.33 mi SE) W - M 084 Sue Craig Road (2.58 mi NNE) W M

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

[ Location Numbers prior to 1984 "

Section 6 - Page 2

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 TABLE 6.0-2 OCONEE RADIOLOGICAL MONITORING PROGRAM, SAMPLING LOCATIONS (TLD SITES)

Site Location* 'Disitance Sector Site Lo-cation* Distance6 Sector

. MICROWAVE TOWER, 020 SITE BOUNDARY 0. 16 miles N 040 SIX MILE 4.74,miles E 021 SITE BOUNDARY 0.25 miles NNE 041 JCT HWY 101 & 133 4.25'.miles ESE LAWRENCE CHAPEL 022 SITE BOUNDARY 0.53 miles NE 042 CHURCH, HWY 133 4.93,miles SE HWY 291 AT 023 SITE BOUNDARY 0.93 miles ENE 043. ISSAQUEENA PARK 4.09 miles SSE HWY 130 AT LITTLE i:

024 SITE BOUNDARY 0.81 miles E 044 RIVER DAM, 3.96,miles S TERMINUS OF HWY 588 025 SITE BOUNDARY 0.42 miles ESE 045 AT CROOKED CREEK 4.78,miles SSW HWY 188 AT 026 SITE BOUNDARY 0.34 miles SE 046 CROOKED CREEK 4.61 miles SW NEW HOPE CHURCH, 027 SITE BOUNDARY 0.49 miles SSE 047 HWY .188 3.58,miles WSW 028, SITE BOUNDARY 0.46 miles S 048 JCT HWY 175 & 188 3.64 ,miles W 029 SITE BOUNDARY 0.56 miles SSW 049 JCT HWY 201 & 92 3.601miles WNW STAMP CREEK LANDING, 030 SITE BOUNDARY 0.42 miles SW 050 END OF HWY 92' 3.53 miles NW HWY 128,1 MILENOF 031 SITE BOUNDARY 0.27 miles WSW 051 HWY{130 4.64 miles NNW DPC BRANCH OFFICE 076 SITE BOUNDARY 0.19 miles W 052 SITE - PICKENS 12.4'miles, ENE DPC BRANCH OFFICE 032 SITE BOUNDARY 0.19 miles WNW 053 SITE - LIBERTY 11.7 miles E" POST OFFICE - HWY 93 033 SITE BOUNDARY 0.21 miles WNW 054 NORRIS 8.60 miles ESE CLEMSON 034 SITE BOUNDARY 0.22 miles

  • NW 055 METEOROLOGY PLOT 9.27 miles SSE 035 SITE BOUNDARY 0.17 miles NNW 056 WATER TOWER - SENECA 7.30 miles SSW OCONEE MEMORIAL 1 036 MILE CREEK LANDING 4.32 miles N 057 HOSPITAL "x . 8.42 miles SW KEOWEE CHURCH, BRANCH RD 037 HWY 327 4.85 miles NNE 058 C SUBSTATION, WALHALLA 9.39 miles WSW CONVENIENCE MART, 038 JCT HWY 183 & 133 4.24 miles NE 059 TAMASSEE DAR SCHOOL 9.20 miles. NW HWY 133, 1 MILE EAST CLEMSON 039 OF JCT HWY 183 & 133 4.02 miles ENE 081 C OPERATIONS CENTER 9.33'miles SE C = Control
  • GPS data reflect approximate accuracy to within 2-5 meters. GPS field measurements were taken as close as possible to the item of interest.

Section 6 - Page 3

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 TABLE 6.0-3 Oconee 2008 Land Use Census Results*

Land Use Census performed 6/4 - 6/5/2008 Sector Distahce Sector Distance' (Miles)** (Miles)**

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

Nearest Residence 1.84 - Nearest Residence 1.36 NNE Nearest Milk Animal SSW Nearest Milk Animal Nearest Residence 1.20 Nearest Residence 1.31 NE Nearest Milk Animal - SW Nearest Milk Animal -

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

Nearest Residence L14, Nearest Residence 1.76 E Nearest Milk Animal - Nearest Milk Animal Nearest Residence 1.57 Nearest Residence 1.35 ESE Nearest Milk Animal - WNW Nearest Milk Animal Nearest Residence 1.46 Nearest Residence 1.04 SE Nearest Milk Animal - NW Nearest Milk Animal "

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

"-" indicates no occurrences within the 5 mile radius The land use census identifies nearest pathways to the exclusion area boundary (EAB, - 1.0 mile) for each of the 16 sectors.. Locations beyond the nearest pathway for each sector are assumed to contain that pathway for dose calculation purposes. At Oconee, broad leaf vegetation samples are taken in lieu of a garden census.. For dose calculation purposes, since a garden location cannot be ruled out, a garden is assumed to- exist at the site boundary and beyond for every sector. For the 4.5-5.0 mile sector all pathways, i.e., residence, garden, milk animal (goat), and meat animal (cow), are assumed to exist for dose calculation purposes.

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

Section 6 - Page 4

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 Figure 6.0-1 Sampling Locations Map (Site Boundary)

Oconee Nuclear Station Sampling Locations Map (One Mile Radius)

Legend o TLD Locations A& All Other Locations

/t* Public Roads

/XV County Boundary Water Approndmate focaion 6f featkures shovn-0 0 0.25 .tiles Projecbon NCSP NAD27 Section 6 - Page 5

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 Figure 6.0-2 Sampling Locations Map (Ten Mile Radius)

I.

Oconee Nuclear Station Sampling Locations Map (Ten Mile Radius)

Legend a TLD Locations A All Other Locations

/'v' Public Roads yPj Rail Roads 7v, County Boundary Incorporated Areas Water Approximate location of features show*"

0 1 2 3Miles Projedion NCSP NAD27 Section 6 - Page 6

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 Figure 6.0-3 ONS 2008 Land Use Census Map Oconee Nuclear Station 2008 Land Use Census Map Legend

  • Residence
  • Public Roads

\ Rail Road

/"../, County Boundary Water approximate location of features shown

(

0 0.5 1 2 Miles Projection NCSP NAD27 June 2008 Section 6 - Page 7

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 6.0.3 OCONEE METEOROLOGY: RELATIVE AIR CONCENTRATIONS AND DEPOSITION Calculations of annually averaged air concentrations and deposition values from routine releases provide the air dispersion and deposition factors needed for dose assessment.

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

Five years of hourly meteorological data from the onsite instruments are processed into a representative joint frequency distribution of winds and atmospheric stability for input into the XOQDOQ model (Version 2.0). Thus, the air dispersion and deposition factors (x/Q and D/Q) output by the model are based on' a five-year climatology for the site.

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

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

In order for XOQDOQ to treat the plume as a ground-level release, the' exit velocity and the inside diameter of the unit vent must be input as zero. The heat emission rate of each vent is also assumed to be zero, as recommended by the model. A release height of 10 m is assumed for the ground-level release, with actual plant grade of 796 ft msl. Using the building height (58 m) and minimum cross-sectional area of the containment building (2296 M2 ), XOQDOQ applies a building wake correction to the relative air concentrations.

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

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 utilize the input terrain heights above yard grade elevation (Table 6.0-4). The height of the vent (60.7 m) above plant grade is used to determine the plume centerline height.

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

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

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

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

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

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

Section 6 - Page 9

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 6.0.3.3 ANNUAL XOQDOQ COMPARISON TO THE ODCM Each year, the prevailing winds and stability class frequencies for ONS are compared to the 5-year period (1988-1992) upon which the X/Q and D/Q calculations have been made.

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

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

Table 6.0-6 ONS Frequency of Wind Direction (From) and Speed (1988-1992)

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

N 5.1 CALM 1.0 NNE 5.2 0.45 - 0.74 m/s 4.7 NE 9 0.75 - 0.99 m/s 9.4 ENE 8.3 1.00 - 1.24 m/s 10.0 E 5.2 1.25 - 1.49 m/s 12.3 ESE 3.1 1.50 - 1.99 m/s 16.8 SE 3 2.00 - 2.99 m/s 20.4 SSE 3.5 3.00 - 3.99 m/s 9.6 S 3.6 4.00 - 4.99 m/s 4.5 SSW 8.5 5.00 - 5.99 m/s 1.8 SW 11.7 6.00 - 7.99 m/s 1.3 WSW 7.4 8.00 - 9.99 m/s 0.3 W 5.1 > 9.99 m/s 8.9 WNW 6.9 NW 7.2 NNW 6.3 _ __. __ _... . _______.___________

The joint frequency distributions of wind speed and direction versus atmospheric stability class are also determined from the annual data to provide input to the XOQDOQ model.

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

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 compared to the maximum of the (1988-1992) X/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 IOCFR50, Appendix I dose objectives then the 5-year X/Q and D/Q values used in the Annual Radiological Effluent Release Report (ARERR) are not revised. An increase in calculated offsite dose that is greater than five percent of the 10CFR50, Appendix I dose objectives would be considered significant enough to warrant a change in the X/Q and D/Q values used in the ARERR. If an increasing trend in the annual X/Q and D/Q values compared to the 5-year values is noted then a revised set of 5-year X/Q and D/Q values will be generated. These limiting values are listed in Table 6.0-7. The entire X/Q and D/Q list based on directional sector and distance is given in Table 6.0-9 and Table 6.0-10.

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

(X/Q,s/m 3) Distance Sector (D/Q,1/m)

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

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

Table 6.0-8 ONS Delta-T Ranges per Vertical Separation Distances Stability 36m separation Delta-T 50m separation Delta-T Class (between 46m-10m levels) (between 60m-l0m'nlevels)

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

A dT < -0.68 dT < -0.95 B -0.68 < dT < -0.61 -0.95 < dT < -0.85 C -0.61 < dT < -0.54 -0.85 < dT < -0.75 D -0.54 < dT < -0.18 -0.75 < dT < -0.25 E -0.18 < dT < 0.54 -0.25 < dT < 0.75 F 0.54 < dT < 1.44 0.75 < dT < 2.00 G 1.44 < Dt 2.00 < dT Section 6 - Page 1 .

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 '

Table 6.0-9 (page 1 of2)

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

(sec/m 3)

Sector 1.0*l.5* 1.5-2.0 _2.0-2.5 2.5-3.0 3.0-3.5' 3.5--0. 4.04;"5 45-5ý0 ::

N 5.220E-07 2,650E-07 1.594E-07 1.069E-07 7.719E-08 7.321E-08 5.665E-08 4.542E-08 NNE 8.379E-07 4.734E-07 2.69"0E-07 2.003E-07 1.385E-07 1.091E-07 , 8.379E-08 6.676E-08 NE 9.503E-07 6.350E-07 3.962E-07 2.535E-07 1.847E-07 1.497E-07 1.157E-07 9.246E-08 ENE 8.116E-07 4.856E-07 2.919E-07 .2.196E-07 1.619E-07 1.239E-07 9.609E-08 7.720E-08 E 5.950E-07 3.202E-07 2.015E-07 2.270E-07 1.745E-07 1.292E-07 1.024E-07 8.308E-08 ESE 4.531E-07 3.300E-07 3.623E-07 4.020E-07 2.822E-07 2.109E-07 1.688E-07 1.405E-07 SE 7.505E-07 4.573E-07 5.490E-07 5.11 OE-07 3.560E-07 2.648E-07 2.063E-07 1.665E-07 SSE 1.419E-06 7.428k-07 4.527E-07. 3.489E-07 2.866E-07 2.131E-07 1.659E-07 1.337E-07 S 1. 170E-06 6.099E-07 3.701E-07 2.496E-07 1.810E-07 1.552E-07 1.218E-07 9.867E-08 SSW 1.214E-06 6.327E-07 3.564E-07 2.301E-07 1.621E-07 1.213E-07 9.481E-08 7.660E-08 SW 1.672E-06 7.285E-07 4.057E-07 2.720E-07 1.891E-07 1.400E-07 1.085E-07 8.708E-08 WSW 1.558E-06 6.820E-07 3.804E-07 2.438E-07 1.708E-07 1.271E-07 1.010E-07 8.114E-08 W 1. 193E-06 5.214E-07 2.909E-07 1.867E-07 1.372E-07 1.032E-07 8.326E-08 6.654E-08 WNW 4.658E-07 2.480E-07 I 1.760E-07 1.482E-07 1.024E-07 7.695E-08 5.943E-08 4.796E-08 NW 4.831E-07 2.524E-07 1.965E-07 1.291E-07 9.959E-08 7.356E-08 5.682E-08 4.566E-08 NNW 5.375E-07 2.769E-07 2.128E-07 1.394E-07 1.072E-07 .7.913E-08 6.11 OE-08 4.907E-08

  • Units are in miles from the station. As discussed in Oconee UFSAR Section 2.1.1.3, the boundary for establishing gaseous effluent release limits is the exclusion area boundary (EAB). The EAB is at a radius of 1.0 mile from the station center. Each X/Q value is calculated at the closest location for' the sector, e.g., 1.672E-06 sec/mi3 is the X/Q value at 1.0' mile (SW) from the station.

Section 6 -Page 12

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 Table 6.0-9 (page 2 of 2)

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

(m-2)

Sector 1.*i1.5* 1.5-2.0 210 2.5' 2.5-310 3.0-3.5 3 3-4.0 4.0-4 4.5-5.0 N 2.890E-09 1 184E-09 6.225E-10 3.812E-10 2.586E-10 3.380E-10 2.510E-10 1.943E- 10 NNE 9.113E-09 3.989E-09 2.013E-09 1.248E-09 8.235E-10 8.997E-10 6.667E-10 5 138E-10 NE 1.295E-08 5.666E-09 2.919E-09 1.729E-09 1.145E-09 1.224E-09 9.140E-10 7.067E-10 ENE 7.899E-09 3.385E-09 1.756E-09 1.095E-09 9.819E-10 7.671E-10 5.749E-0 4.466E-10 E 4.454E-09 1.775E-09 9.252E-10 7.164E-10 7.491E-10 5.267E-10 3.981E-10 3.125E-10 ESE 4.361E-09 1.838E-09 1.086E-09 .1.322E-09 8.696E-10 6.161E-10 5.153E-10 4.139E-10 SE, 3.397E-09 1.385E-09 8.341E-10 1.649E-09 1.080E-09 7.595E-10 5.629E-10 4.340E-10 SSE 3.333E-09 1.323E-09 6.920E-10 4.404E-10 7.307E-10 5.202E-10 3.922E-10 3.091E-10 S 3.192E-09 1.256E-09 6.530E-10 4.020E-10 2.788E-10 2.177E-10 1.759E-10 1.501E-10 SSW 5.190E-09 1972E-09 9.899E-10 5.895E-10 3.928E-10 2.842E-10 2.192E-10 1.778E-10 SW 1.205E-08 4.399E-09 2.193E-09 1.299E-09 8.521E-10 6.028E-10 4.518E-10 ,' 3.546E-10 WSW 1.047E-08 3824E-09 1.908E-09 1.127E-09 7.422E-10 5.277E-10 .3.980E-10 3.145E-10 W 5.577E-09 2044E-09 1.025E-09 6.094E-10 4.134E-10 3.405E-10 3.962E-10 3.052E-10

,WNVW 2.185E-09 9.042E-10 5.220E- 10 6.464E- 10 4.227E- 10 3.188E-10 2360E-10'! 1.868E-10

'NW 2.097E-09 8,759E-10 5 225E-10 3.196E-10 4.521E-10 3 178E- 10 2.353E-10 , 1.812E-10 NNW 2.461E-09 1.028E-09 6.219E-10 3.765E- 10 5.128E-10 3.604E- 10 2.667E- 10 2.054E- 10

  • Units are in miles from the station. As discussed in Oconee, UFSAR Section 2.1.1.3, the boundary for establishing gaseous effluent release limits is the exclusion area boundary (EAB). The EAB is defined as a 1 mile radius from the-statioh center. Each D/Q value is calculated at the closest location for the sector, e.g., 1.205E-08 m2 is the D/Q value'at 1.0 mile (SW) from the station.

Section 6 - Page 13

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 Table 6.0-10 (page 1 of2)

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

(sec/mr3 )

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 4.04.5 4.515;0 N 2.115E-06 8.389E-07 4.495E-07 2.822E-07 1.952E-07 1.443E-07 1.117E-07 8.961E-08 NNE 2.898E-06 1.137E-06 6.047E-07 3.775E-07 2.602E-07 1.916E-07 1.480E-07 1.184E-07 NE 3.886E-06 1.529E-06 8.158E-07 5.108E-07 3.529E-07 2.604E-07 2.015E-07 1.616E-07 ENE 3.226E-06 1.277E-06 6.848E-07 4.305E-07 2.983E-07 2.207E-07 1.711 E-07 1.374E-07 E 3.522E-06 1.410E-06 7.658E-07 4.866E-07 3.400E-07 2.534E-07 1.977E-07 1.596E-07 ESE 5.964E-06 2.407E-06 1.321E-06 8.459E-07 5.950E-07 4.457E-07 3.493E-07 2.832E-07 SE 7.308E-06 2.972E-06 1.631E-06 1.044E-06 7.342E-07 5.497E-07 4.307E-07 3.490E-07 SSE 6.604E-06 2.657E-06 1.440E-06 9.117E-07 6.354E-07 4.723E-07 3.676E-07 2.962E-07 S 5.278E-06 2.121E-06 1.146E-06 7.237E-07 5.032E-07 3.734E-07 2.901E-07 2.335E-07 SSW. 3.986E-06 1.589E-06 8.536E-07 5.310E-07 3.721E-07 2.753E-07 2.135E-07 1.714E-07 SW 4.108E-06 1.620E-06 8.628E-07 5.390E-07 3.715E-07 2.735E-07 2.112E-07 1.689E-07 WSW\ 3.804E-06 1.503E-06 8.018E-07 5.015E-07 3.460E-07 .2.549E-07 1.970E-07 1.577E-07 W 2.978E-06 1.186E-06 6.361E-07 3.995E-07 2.765E-07 2.043E-07 1.583E-07 1.270E-07

'"NW 2.201E-06 8.791E-07 4.726E-07 2.974E-07 2.062E-07 1.526E-07 1.183E-07 9.502E-08 NW 2.104E-06 8.385E-07 4.499E-07 2.826E-07 1.957E-07 1.447E-07 1.121E-07 8.991E-08 NNW 2.221E-06 8.860E-07 4.755E-07 2.988E-07 2.069E-07 1.529E-07 1.185E-07. 9.508E-08

  • Units are in miles from the station. As discussed in Oconee UFSAR Section 2.1.1.3, the boundary for establishing gaseous effluent release limits is the exclusion area boundary (EAB). The EAB is defined as a 1 mile radius from the station center. Each x/Q value is calculated at the closest location for the sector, e.g., 4.108E-06 sec/mr3 is the X/Q value at 1.0 mile (SW) from the station.

Section 6 -Page 14

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 Table 6.0-10 (page 2 of 2)

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

(M-2)

Sector 1.0-1.5* 1.-5-2.0 2.0-2.5 2.5-3.0 3.0-3.5 335-4.0 40- 4 .5-5.0 N 6.916E-09 2.484E-09 1.232E-09 7.255E-10 4.750E-10 3.342E-10 2.477E-10 1.909E-10 NINE 1.642E-08 5.897E-09 2.924E-09 1.722E-09 1.128E-09 7.934E-10 5.880E-10 4.531E-10 NE 2.259E-08 8.114E-09 4.024E-09 2.369E-09 1.551E-09 1.092E-09 8.090E-10 6.235E-10 ENE 1.428E-08 5.130E-09 2.544E-09 1.498E-09 9.810E-10 6.902E-10 5.115E-10 3.942E-10 E 9.899E-09 3.556E-09 1.763E-09 1.038E-09 6.798E-10 4.784E-10 3.545E-10 2.732E-10 ESE 1.336E-08 4.798E-09 2.379E-09 1.401E-09 9.174E-10 6.455E-10 4.784E-10 3.686E-10 SE 1.401E-08 5.034E-09 2.496E-09 1.470E-09 9.625E-10 6.772E-10 5.019E-10 3.868E-10 SSE 1.226E-08 4.404E-.09 2.184E-09 1.286E-09 8.420E-10 5.925E-10 4.391E-10 3.384E-10 S 1.008E-08 3.620E-09 1.795E-09 1.057E-09 6.922E-10 4.871E-10 3.610E-10 2.782E-10 SSW 9.941E-09 3.571E-09 1.771E-09 1.043E-09 6.828E-10 4.804E-10 3.560E-10 2.744E-10 SW 1.717E-08 6.169E-09 3.059E-09 1.801E-09 . 1.180E-09 8.300E-10 6.151E-10 4.740E-10 WSW 1.574E-08 5.655E-09 2.804E-09 1.651 E-09 1.081E-09 7.608E-10 5.638E-10 4.345E-10 W 9.988E-09 3.588E-09 1.779E-09 1.048E-09 6.860E-10 4.827E-10 3.577E-10 2.757E-10 "NW 5.953E-09 2.138E-09 1.060E-09 6.244E-10 4.088E-10 2.877E- 10 2.132E-10 1.643E.10 NW 5.891E-09 2.116E-09 1.049E-09 6.179E-10 4.046E- 10 2.847E- 10 2.11 E-10 1.626E-10 NNW 6.672E-09 2.397E-09 '.I88E-09 6.998E-10 4.582E-10 3.224E-10 2.390E-10 1.841E-10

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

Section 6 -Page 15

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 7.0 LICENSEE INITIATED CHANGES All changes made to the Oconee ODCM are reviewed by knowledgeable individual(s), and approved by the: Station Manager and the General Office Radiation Protection Manager prior to implementation. The following changes do not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

Section 3 - Page 1 Added "(Cs-I137)" to clarify which isotope the 8.00E+07 cpm/*Ci/ml correlation value applied to.

Section 3 - Page 3 Added a description of the methodology used for the RIA-33 "Alert" setpoint for low activity tanks (< 9.OE-06 ltCi/ml). (Reference PIP 0-08-06705, CA #1)

Section 3 - Page 10 Changed the correlation value for 1RIA-37 from 1.01E-08 [tCi/ml/cpm to 4.20E-08 gCi/ml/cpm to be consistent with Oconee procedure HP/0/B/1000/060A.

(Reference PIP 0-08-06451)

Section 6 - Page 4 Changed title of Table 6.0-3 to: "Oconee 2008 Land Use Census Results."

Land use census dates were changed to reflect 2008 census dates. The 2008 land use census was performed June 4-5, 2008, and the results were certified and made available for use on November 4, 2008.

The distance (miles) for the SW sector residence was changed from 1.32 to 1.31.

The distance (miles) for the NNE sector residence was changed from 1.85 to 1.84.

Section 6 - Page 7 Changed title of Figure 6.0-3 to: "ONS 2008 Land Use Census Map."

Figure 6.0-3 regenerated to depict 2008 census data.

Section 7 -Page 1

Oconee Nuclear Station January, 2009 Revision 49 Offsite Dose Calculation Manual (ODCM)

APPENDIX A Dose Factors for Exposure to a Semi-Infinite Cloud of Noble Gases*

Ki Li Mi Ni Total Body Skin Gamma Air Beta Air mrem/yr/ mrem/yr/,: mrad/yr/ mrad/yr/.

___i/m*___ _., Lei/m 3

/m 3 JLCi/m 3 1 jtCi/m3 AR-41 8.840E+03 2.690E+03 9.300E+03 3.280E+03 KR-83M 7.560E-02 0.OOOE+00 1.930E+01 2.880E+02 KR-85M 1.1 70E+03 1.460E+03 1.230E+03 1.970E+03 KR-85 1.610E+01 1.340E+03 1.720E+01 1.950E+03 KR-87 5.920E+03 9.730E+03 6.170E+03 1.030E+04 KR-88 1.470E+04 2.370E+03 1.520E+04 2.930E+03 KR-89 1.660E+04 1.010E+04 1.730E+04 1.060E+04 KR-90 1.560E+04 7.290E+03 1.630E+04 7.830E+03 XE-131M 9.150E+01 4.760E+02 1.560E+02 1.110E+03 XE-133M 2.5 10E+02 9.940E+02 3.270E+02 1.480Et03 XE-133 2.940E+02 3.060E+02 3.530E+02 1.050E+03 XE-135M 3.120E+03 7.11OE+02 3.360E+03 7.390E+02 XE-135 1.810E+03 1.860E+03 1.920E+03 2.460E+03 XE- 137 1.420E+03 1.220E+04 1.510E+03 1.270E+04 XE-138 8.830E+03 4.130E+03 9.210E+03 4.750E+03

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

Oconee Nuclear Station 0

January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX B P, Dose Factors for use in the Gaseous Release Rate Limit Calculations Agegroup: CHILD Pathway: Inhalation (INHL) Units: mrem/yr / pCi/mr3 Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body H-3 0.OOOE+00 1.120E+03 1.120E+03 1.120E+03 1.120E+03 1.120E+03 0.OOOE+00 1.120E+03 C-14 3.590E+04 6.730E+03 6.730E+03 6.730E+03 6.730E+03 6.730E+03 0.OOOE+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.OOOE+00 1.610E+04 P-32 2.600E+06 1.140E+05 0.OOOE+00 0.OOOE+00 0.OOOE+00 4.220E+04 0.000E+00 9.880E+04 CR-51 0.OOOE+00 0.600E+00 8.550E+01 2.430E+01 1.700E+04 1.080E+03 0.OOOE+00 1.540E+02 MN-54 0.OOOE+00 4.290E+04 0.OOOE+00 1.000E+04 1.580E+06 2.290E+04 0.OOOE+00 9.510E+03 I MN-56 0.OOOE+00 1.660E+00 0.OOOE+00 1.670E+00 1.310E+04 1.230E+05 0.OOOE+00 3.120E-01 FE-55 4.740E+04 2.520E+04 0.OOOE+00 0.OOOE+00 1.11OE+05 2.870E+03 0.OOOE+00 7.770E+03 FE-59 2.070E+04 3.340E+04 0.OOOE+00 0.000E+00 1.270E+06 7.070E+04 0.OOOE+00 1.670E+04 CO-58 0.000E+00 1.770E+03 0.OOOE+00 0.000E+00 1.11OE+06 3.440E+04 0.OOOE+00 3.160E+03 CO-60 0.OOOE+00 1.310E+04 0.OOOE+00 0.OOOE+00 7.070E+06 9.620E+04 0.OOOE+00 2.260E+04 NI-63 8.210E+05 4.620E+04 0.OOOE+00 0.OOOE+00 2.750E+05 6.330E+03 0.OOOE+00 2.800E+04 NI-65 2.990E+00 2.960E-01 0.OOOE+00 0.OOOE+00 8.180E+03 8.400E+04 0.OOOE+00 1.640E-01 CU-64 0.OOOE+00 1.990E+00 0.000E+00 6.030E+00 9.580E+03 3.670E+04 0.OOOE+00 1.070E+00 ZN-65 4.260E+04 1.130E+05 0.OOOE+00 7.140E+04 9.950E+05 1.630E+04 0.OOOE+00 7.030E+04 ZN-69 6.700E-02 9.660E-02 0.OOOE+00 5.850E-02 1.420E+03 1.020E+04 0.OOOE+00 8.920E-03 BR-83 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.000E+00 4.740E+02 BR-84 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 5.480E+02 BR-85 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.000E+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 2.530E+01 RB-86 0.OOOE+00 1.980E+05 0.OOOE+00 0.OOOE+00 0.OOOE+00 7.990E+03 0.OOOE+00 1.140E+05 RB-88 0.OOOE+00 5.620E+02 0.OOOE+00 0.000E+00 0.OOOE+00 1.720E+01 0.OOOE+00 3.660E+02 RB-89 0.OOOE+00 3.450E+02 0.OOOE+00 0.000E+00 0.OOOE+00 1.890E+00 0.OOOE+00 2.900E+02 SR-89 5.990E+05 0.OOOE+00 0.OOOE+00 0.OOOE+00 2.160E+06 1.670E+05 0.OOOE+00 1.720E+04 SR-90 1.010E+08 0.OOOE+00 0.000E+00 0.OOOE+00 1.480E+07 3.430E+05 0.OOOE+00 6.440E+06 SR-91 1.210E+02 0.OOOE+00 0.OOOE+00 0.OOOE+00 5.330E+04 1.740E+05 0.OOOE+00 4.590E+00 Appendix B Pi Child Inhalation - Page I of 3

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX B Pi Dose Factors for use in the Gaseous Release Rate Limit Calculations Agegroup: CHILD Pathway: Inhalation (INHL) Units: mrem/yr / p.Ci/m 3 Nuclide Bone Liver Thyroid Kidney" Lung., Gilli, .- Skin,.y Total Bod*y SR-92 1.310E+01 0.OOOE+00 0.OOOE+00 0.OOOE+00 2.400E+04 2.420E+05 0.OOOE+00 5.250E-01 Y-90 4.11OE+03 0.OOOE+00 0.000E+00 0.OOOE+00 2.620E+05 2.680E+05 0.OOOE+00 1.11OE+02 Y-91 9.140E+05 0.OOOE+00 0.000E+00 0.OOOE+00 2.630E+06 1.840E+05 0.OOOE+00 2.440E+04 Y-91M 5.070E-01 0.OOOE+00 0.OOOE+00 0.OOOE+00 2.810E+03 1.720E+03 0.OOOE+00 1.840E-02 Y-92 2.030E+01 0.OOOE+00 0.000E+00 0.OOOE+00 2.390E+04 2.390E+05 0.OOOE+00 5.810E-01 Y-93 1.860E+02 0.OOOE+00 0.OOOE+00 0.OOOE+00 7.440E-04 3.880E+05 0.OOOE+00 5.11OE+00 ZR-95 1.900E+05 4.180E+04 0.OOOE+00 5.960E+04 2.230E+06 6.11 OE+04 0.OOOE+00 3.700E+04 ZR-97 1.880E+02 2.720E+01 0.OOOE+00 3.880E+01 1.130E+05 3.510E+05 0.OOOE+00 1.600E+01 NB-95 2.350E+04 9.180E+03 0.000E+00 8.620E+03 6.140E+05 3.700E+04 0.OOOE+00 6.550E+03 MO-99 0.OOOE+00 1.720E+02 0.OOOE+00 3.920E+02 1.350E+05 1.270E+05 0.OOOE+00 4.260E+01 TC-99M 1.780E-03 3.480E-03 0.OOOE+00 5.070E-02 9.510E+02 4.81 OE+03 0.OOOE+00 5.770E-02 TC-101 8.100E-05 8.510E-05 0.OOOE+00 1.450E-03 5.850E+02 1.630E+01 0.OOOE+00 1.080E-03 RU-103 2.790E+03 0.000E+00 0.OOOE+00 7.030E+03 6.620E+05 4.480E+04 0.OOOE+00 1.070E+03 RU-105 1.530E+00 0.000E+00 0.OOOE+00 1.340E+00 1.590E+04 9.950E+04 0.OOOE+00 5.550E-01 RU- 106 1.360E+05 0.OOOE+00 0.000E+00 1.840E+05 1.430E+07 4.290E+05 0.OOOE+00 1.690E+04 AG- 110M 1.690E+04 1.140E+04 0.OOOE+00 2.120E+04 5.480E+06 1.000E+05 0.OOOE+00 9.140E+03 TE-125M 6.730E+03 2.330E+03 1.920E+03 0.OOOE+00 4.770E+05 3.380E+04 0.OOOE+00 9.140E+02 TE-127 2.770E+00 9.510E-01 1.960E+00 7.070E+00 1.000E+04 5.620E+04 0.OOOE+00 6.100E-01 TE-127M 2.490E+04 8.550E+03 6.070E+03 6.360E+04 1.480E+06 7.140E+04 0.000E+00 3.020E+03 TE-129 9.770E-02 3.500E-02 7.140E-02 2.570E-01 2.930E+03 2.550E+04 0.OOOE+00 2.380E-02 TE-129M 1.920E+04 6.840E+03 6.330E+03 5.030E+04 1.760E+06 1.820E+05 0.OOOE+00 3.040E+03 TE-131 2.170E-02 8.440E-03 1.700E-02 5.880E-02 2.050E+03 1.330E+03 0.000E+00 6.590E-03 TE-131M 1.340E+02 5.920E+01 9.770E+01 4.OOOE+02 2.060E+05 3.080E+05 0.OOOE+00 5.070E+01 TE-132 4.810E+02 2.720E+02 3.170E+02 1.770E+03 3.770E+05 1.380E+05 0.OOOE+00 2.630E+02 1-130 8.180E+03 1.640E+04 1.850E+06 2.450E+04 0.OOOE+00 5.110E+03 0.OOOE+00 8.440E+03

.0 Appendix B Pi Child Inhalation - Page 2 of 3 0

Oconee Nuclear Station 0

January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX B Pi Dose Factors for use in the Gaseous Release Rate Limit Calculations Agegroup: CHILD Pathway: Inhalation (INHL) Units: mrem/yr / ptCi/m 3 Nuclide Bone. Liver Thyroid Kidney Lung Gilli 'Skin TotalBod 1-131 4.810E+04 4.810E+04 1.620E+07 7.880E+04 0.OOOE+00 2.840E+03 0.OOOE+00 2.730E+04 1-132 2.120E+03 4.070E+03 1.940E+05 6.250E+03 0.OOOE+00 3.200E+03 0.OOOE+00 1.880E+03 1-133 1.660E+04 2.030E+04 3.850E+06 3.380E+04 0.OOOE+00 5.480E+03 0.OOOE+00 7.700E+03 1-134 1.170E+03 2.160E+03 5.070E+04 3.300E+03 0.OOOE+00 9.550E+02 0.OOOE+00 9.950E+02 1-135 4.920E+03 8.730E+03 7.920E+05 1.340E+04- 0.OOOE+00 4.440E+03 0.OOOE+00 4.140E+03 CS-134 6.510E+05 1.010E+06 0.OOOE÷00 3.300E+05 1.210E+05 3.850E+03 0.OOOE+00 2.250E+05 CS-136 6;5.10E+04 1.710E+05 0.000E+00- 9.550E+04 1.450E+04 4.180E+03 O.000E+60 1.160E+05 CS-137 9.060E+05 8.250E+05 0.000E+00 2.820E+05 1.040E+05 3.620E+03 0.OOOE+00 1.280E+05 CS-138 6.330E+02 8.400E+02 0.OOOE+00 6.220E+02 6.810E+01 2.700E+02 0.OOOE+00 5.550E+02 BA-139 1.840E+00 9.840E-04 0.OOOE+00 8.620E-04 5.770E+03 5.770E+04 0.OOOE+00 5.360E-02 BA-140 7.400E+04 6.480E+01 0.OOOE+00 2.11OE+01 1.740E+06 1.020E+05 0.OOOE+00 4.330E+03 BA-141 1.960E-01 1.090E-04 0.OOOE+00 9.470E-05 2.920E+03 2.750E+02 0.OOOE+00 6.360E-03 BA-142 5.OOOE-02 3.600E-05 0.OOOE+00 2.910E-05 1.640E+03 2.740E+00 0.OOOE÷00 2.790E-03 LA-140 6.440E+02 2.250E+02 0.OOOE+00 0.OOOE+00 1.830E+05 2.260E+05 0.OOOE+00 7.550E+01 LA-142 1.300E+00 4.11OE-01 0.OOOE+00 0.OOOE+00 8.700E+03 7.580E+04 0.OOOE+00 1.290E-01 CE-141 3.920E+04 1.950E+04- O.OOOE+00 8.550E+03 5.440E+05 5.660E+04 0.OOOE+00 2.900E+03 CE- 143 3.660E+02 1.990Et02 0.OOOE+00 8.360E+01 1.150E+05 1.270E+05 0.OOOE+00 2.870E+01 CE-144 6.770E+06 2.120E+06 0.OOOE+00 1.170E+06 1.200E+07 3.880E+05 0.OOOE+00 3.610E+05 PR-143 1.850E+04 5.550E+03 0.OOOE+00 3.OOOE+03 4.330E+05 9.730E+04 0.OOOE+00 9.140E+02 PR-144 5.960E-02 1.850E-02 0.OOOE+00 9.770E-03 1.570E+03 1.970E+02 0.OOOE+00. 3,000E-03 ND-147 1.080E+04 8.730E+03 0.OOOE+00 4.810E+03 3.280E+05 8.210E+04 0.OOOE+00 6.810E+02 W-187 1.630E+01 9.660E+00 0.OOOE+00 0.OOOE+00 4.11OE+04 9.100E+04 0.OOOE+00 4.330E+00 NP-239 4.660E+02 3.340E+01 0.000E+00 9.730E+01 5.810E+04 6.400E+04 0.OOE+00 2.350E+01 Appendix B Pi Child Inhalation - Page 3 of 3

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX C Ai Adult Dose Factors for use in the Liquid Dose Calculations Agegroup: ADULT Pathway: Potable Water (PWtr) Units: mrem/hr /XCi/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body H-3 0.OOOE+00 8.740E+00 8.740E+00 8.740E+00 8.740E+00 8.740E+00 0.000E+00 8.740E+00 C-14 2.360E+02 4.730E+01 4.730E+01 4.730E+01 4.730E+01 4.730E+01 0.000E+00 4.730E+01 NA-24 8.140E+O1 8.140E+01 8.140E+01 8.140E+01 8.140E+01 8.140E+01 0.OOOE+00 8.140E+01 P-32 1.570E+04 9.750E+02 0.OOOE+00 O.OOOE+00 0.OOOE+00 1;760E+03 0.OOOE+00 6.060E+02 CR-51 0.OOOE+00 0.OOOE+00 1.310E-01 4.820E-02 2.900E-01 5.500E+01 0.OOOE+00 2.190E-01 MN-54 0.OOOE+00 3.800E+02 0.OOOE+00 1.130E+02 0.OOOE+00 1.160E+03 0.OOOE+00 7.250E+01 MN-56 0.OOOE+00 3.800E-01 0.OOOE+00 4.820E-01 0.OOOE+00 1.210E+01 0.OOOE+00 6.740E-02 FE-55 2.290E+02 1.580E+02 0.OOOE+00 0.OOE+00 -8.820E+01 9.070E+01 0.OOOE+00 3.690E+01 FE-59 3.580E+02 8.420E+02 0.OOOE+00 0.OOOE+00 2.350E+02 2.810E+03 0.OOOE+00 3.230E+02 CO-58 0.OOOE+00 6.170E+01 0.OOOE+00 0.OOOE+00 0.OOOE+00 1.250E+03 0.OOOE+00 1.380E+02 CO-60 0.000E+00 1.780E+02 0.OOOE+00 0.OOOE+00 0.OOOE+00 3,340E+03' 0.OOOE+00 3.930E+02 NI-63 1:080E+04 7.500E+02 0.OOOE+00 0.OOOEt00 0.OOOE+00 1.560E+02 0.OOOE+00 3.630E+02 NI-65 1.620E+00 2.100E-01 0.OOOE+00 o0.OOOE+00 0.OOOE+00 5.340E+00 O.OOOE+00 9.600E-02 CU-64 0.OOOE+00 3.590E+00 0.00OE+00 9.060E+00 0.OOOE+00 3.060E+02 0.OOOE+00 1.690E+00 ZN-65 4.020E+02 1.280E+03 0.OOOE+00 8.560E+02 0.OOOE+00* 8.060E+02 0.OOOE+00 5.780E+02 ZN-69 1.070E-04* 2.050E-04 0.OOOE+00 1.330E-04 0.OOOE+00 3.080E-05 0.000E+00 1.430E-05 BR-83 0.OOOE+00 0.OOOE+00 0.OOOE+00 - 0.OOOE+00 0.OOOE+00 1.480E-01 0.OOOE+00 1.030E-01 BR-84 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 5.270E-12 0.OOOE+00 6.710E-07 BR-85 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 4.380E-77 RB-86, 0.OOOE+00 1.720E+03 0.OOOE+00 0.600E+00 0.OOOE+00 - 3.400E+02 0.0O6E+00 8.030E+02 RB-88 0.OOOE+00 3.360E-12 O.OOOE+00 0.OOOE+00 0.OOOE+00 4.640E-23 0.OOOE+00 1.780E-12.

RB-89 0.OOOE+00 3.090E-14 0.000E+00 0.OOOE+00 0.000+E00 1.790E-27 0.OOOE+00 2.170E-14 SR-89 2.550E+04 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 4.080E+03 0.OOOE+00 7.3 10E+02 SR-90 6.310E+05 0.OOOE+00 0.00OE+00 0.OOOE+00 0.OOOE+00 1.820E+04 0.000E+00 1.550E+05 SR-91 1.960E+02 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 9.350E+02 0.000E+00 7.930E+00 Appendix C Ai Adult Water - Page 1 of 3

Oconee Nuclear Station 0

January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX C Ai Adult Dose Factors for use in the Liquid Dose Calculations Agegroup: ADULT Pathway:. Potable Water (PWtr) Units: mrem/hr / pCi/ml Nuclide Bone Liver,. Thyroid Kidney. Lung iGilli Skin Total.Body SR-92 8.290E+00 0.000E+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 1.640E+02 0.OOOE+00 3.590E-01 Y-90 7.030E-01 0.000E+00 0.OOOE+00 0.OOOE+00 0.000E+00 7.460E+03 0.000E+00 1.890E-02 Y-91 1.170E+01 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 6.420E+03 0.OOOE+00 3.120E-01 Y-91M 3.360E-07 0.000E+00 0.000E+00 0.OOOE+00 0.OOOE+00 9.860E-07 0.OOOE+00 1.300E-08 Y-92 6.710E-03 0.00.OE+00 0.OOOE+00 0.000E+00 0.OOOE+00 1.170E+02 0.000E+00 1.960E-04 Y-93 9.770E-02 0.OOOE+00 0.OOOE+00 0.000E+00 0.OOOE+00 3.100E+03 0.OOOE+00 2.700E-03 ZR-95 2.520E+00 8.070E-01 0.OOOE+00 1.270E+00 0.000E+00 2.560E+03. 0.OOOE+00 5.460E-01 ZR-97 8.540E-02 1.720E-02 0.OOOE+00 2.600E-02. 0.OOOE+00 5.340E+03 0.OOOE+00 '7.880E-03 NB-95 5.130E-01 2.850E-01 0.OOOE+00 2.820E-01 0.OOOE+00 1.730E+03 0.OOOE+00 1.530E-01 MO-99 0.OOOE+00 3.160E+02 0.OOOE+00 7.160E+02 0.OOOE+00 7.330E+02 0.OOOE+00 6.020E+0.1 TC-99M 5.160E-03 1.460E-02 0.OOOE+00 2.210E-01 7.140E-03 8.630E+00 0.OOOE+00 1.860E-01 TC-101 1.130E-17 1.630E-17 0.OOOE+00 2.930E-16 8.320E-18 4.890E-29 0.OOOE+00 1.600E-16 RU-103 1.530E+01 0.OOOE+00 0.OOOE+00 5.820E+01 0.OOOE+00 1.780E+03 0.000E+00 6.570E+00 RU-105 1.970E-01 0.OOOE+00 0.OOOE+00 2.540E+00 0.000E+00 1.200E+02 0.OOOE+00 7.760E-02 RU-106 2.290E+02 0.OOOE+00 0.000E+00 4.410E+02 0.OOOE+00 1.480E+04 0.OOOE+00 2.890E+01 AG-1 10M 1.330E+01 1.230E+01 0.000E+00 2.420E+01 0.OOOE+00 5.020E+03 0.OOOE+00 7.300E+00 TE-125M 2.220E+02 8.030E+01 6.670E+01 9.020E+02 0.000E+00 8.850E+02 0.OOOE+00 2.970E+01 TE-127 3.780E+00 1.360E+00 2.800E+00 1.540E+01 0.OOOE+00 2.980E+02 0.OOOE+00 8.170E-0I TE-127M 5.620E+02 2.010E+02 1.440E+02 2.280E+03 0.OOOE+00 1.880E+03 0.OOOE+00 6.840E+01 TE-129 1.920E-03 7.230E-04 1.480E-03 8.080E-03 0.OOOE+00 1.450E-03 0.OOOE+00 4;690E-04 TE-129M 9.470E+02 3.530E+02 3.250E+02 3.950E+03 0.OOOE+00 4.770E+03 0.000E+00 1.500E+02 TE- 131 3.520E-09 1.470E-09 2.900E-09 1.540E-08 0.OOOE+00 4.990E-10 0.OOOE+00 1.11OE-09 TE-131M 1.090E+02 5.340E+01 8.450E+01 5.400E+02 0.OOOE+00 5.300E+03 0.OOOE+00 4.450E+01 TE-132 1.880E+02 1.220E+02 1.350E+02 1.170E+03 0.OOOE+00 5.770E+03 0.OOOE+00 1.140E+02 11-130 3.21 OE+0 1 9.460E+01 8.020E+03 1.480E+02 0.OOOE+00 8.140E+01 0.OOOE+00 3.730E+01 Appendix C Ai Adult Water - Page 2 of 3

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX C A; Adult Dose Factors for use in the Liquid Dose Calculations Agegroup: ADULT Pathway: Potable Water (PWtr) Units: mrem/hr / p.Ci/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body 1-131 3.320E+02 4.740E+02 1.550E+05 8.130E+02 0.OOOE+00 1.250E+02 0.OOOE+00 2.720E+02 1-132 4.540E-01 1.220E+00 4.250E+01 1.940E+00 0.OOOE+00 2.280E-01 0.OOOE+00 4.250E-01 1-133 7.920E+01 1.380E+02 2.020E+04 2.400E+02 0.000E+00 1.240E+02 0.OOOE+00 4.200E+01 1-134 6.580E-04 1.790E-03 3.100E-02 2.840E-03 0.OOOE+00 1.560E-06 0.OOOE+00 6.390E-04 1-135 1.050E+01 2.750E+01 1.810E+03 4.400E+01 0.OOOE+00 3.100E+01 0.OOOE+00 1.010E+01 CS-134 5.170E+03 1.230E+04 0.0OOOE+00 3.980E+03 1.320E+03 2.150E+02 0.OOOE+00 1.01OE+04 CS-136 5.280E+02 2.080E+03. 0.OOOE+00 1.160E+03 1.590E+02 2.370E+02 0.OOOE+00 1.500E+03 CS-137 6.630E+03 9.070E+03 0.OOOE+00 3.080E+03 1.020E+03 1.760E+02 0.000E+00 5.940E+03 CS-138 8.450E-07 1.670E-06 0.OOOE+00 1.230E-06 1.210E-07 7.120E-12 0.OOOE+00 8.260E-07 BA-139 1.990E-02 1.420E-05 0.OOOE+00 1.330E-05 8.050E-06 3.530E-02 0.000E+00 5.830E-04 BA- 140 1.640E+03 2.070E+00 0.OOOE+00 7.020E-01 1.180E+00 3.390E+03 0.OOOE+00 1.080E+02 BA-141 5.440E-12 4.120E-15 0.OOOE+00 3.830E-15 2.340E-15 2.570E-21 0.OOOE+00 1.840E-13 BA-142 6.290E-21 6.470E-24 0:OOOE+00 5.460E-24 3.660E-24 8.860E-39 0.OOOE+00 3.960E-22 LA-140 .1.690E-01 8.530E-02 0.OOOE+00 0.OOOE+00 0.OOOE+00 6.260E+03 0.OOOE+00 2.250E-02 LA-142 5.720E-05 2.600E-05'. 0.000E+06 O.OOOE+00 0.OOOE+00 1.900E-01 0.OOOE+/-00 6.480E-06 CE-141 7.710E-01 5.210E-01 0.OOOE+00 2.420E-01 0.OOOE+00 1.990E+03 0.OOOE+00 5.910E-02 CE-143 1.070E-01 7.890E+01 0.OOOE+00 3.470E-02 0.OOOE+00 2.950E+03 0.000E+00 8.730E-03 CE-144 4.060E+01 1.700E+01 0.OOOE+00 1.010E+01 0.OOOE+00 1.370E+04 0.OOOE+00 2.180E+00 PR-143 7.460E-01 2.990E-01 0.000E+00 1.730E-01 0.OOOE+00 3.270E+03 0.OOOE+00 3.700E-02 PR-144 7.350E-16 3.050E-16 0.000E+00 1.720E-16 0.OOOE+00 1.060E-22 0.OOOE+00 3.730E-17 ND-147 5.070E-01 5.860E-01 0.OOOE+00 3.430E-01 0.OOOE+00 2.810E+03 0.OOOE+00 3.5 1OE-02 W-187 6.050E+00 5.050E+00 0.OOOE+00 O.OOOE+00 0.OOOE+00 1.660E+03 0.OOOE+00 1.770E+00 NP-239 8.550E-02 8.400E-03 0.OOOE+00 2.620E-02 0.OOOE+00 1.720E+03 0.OOOE+00 4.630E-03 0

Appendix C Ai Adult Water - Page 3 of 3

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX C Ai Adult Dose Factors for use in the Liquid Dose Calculations Agegroup::` ADULT  :,Pathway: Fresh Water Fish - Sport (FFSP) Units: mrem/hr / p.Ci/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin TotalBody H-3 0.OOOE+00 2.260E-01 2.260E-0I 2.260E-01 2.260E-01 2.260E-01 0.OOOE+00 2.260E-01 C-14 3.130E+04 6.260E+03 6.260E+03 6.260E+03 6.260E+03 6.260E+03 -0.000E+00 6.260E+03 NA-24 1.350E+02 1.350E+02 1.350E+02 1.350E+02 1.350E+02 1.350E+02 0.OOOE+00 1.350E+02 P-32 1.320E+06 8.210E+04 0.OOOE+00 0.OOOE+00 0.OOOE+00 1.480E+05 0.OOOE+00 5.100E+04 CR-51 0.OOOE+00 0.000E+00 "7420E-01 2.740E-01 1.650E+00 3.120E+02 0.OOOE+00 1.240E+00 MN-54 0.OOOE+00 4.370E+03 0.OOOE+00 1.300E+03 0.OOOE+00 - 1.340E+04 0.OOOE+00 8.330E+02 MN-56 0.000E+00 1.730E-01 0.OOOE+00 2.200E-01 0.000E+00 5.530E+00 0.OOOE+00 3.070E-02 FE-55 6.580E+02 4.550E+02 0.000E+00 0.OOOE+00 2.540E+02 2.61 OE+02 0.000E+00 1.060E+02 FE-59 1.020E+03 2.400E+03 0.OOOE+00 0.OOOE+00 6.720E+02 8.010E+03 0.OOOE+00 9.220E+02 CO-58 0.OOOE+00 8.830E+01 O.OOOE+00 0.OOOE+00 0.OOOE+00 1;790E+03 0.000E+00 1.980E+02 CO-60 0.000E+00 2.560E+02 0.OOOE+00 0.OOOE+00 O.OOOE+00 4.810E+03 0.OOOE+00 5.650E+02 NI-63 3.11OE+04 2.160E+03 0.OOOE+00 0.000E+00 0.OOOE+00 4.500E+02 0.000E+00 1.040E+03 NI-65 1.720E-01 2.230E-02 0.OOOE+00 .0.OOOE+00 0.OOOE+00 5.660E-01 0.000E+00 1.020E-02 CU-64 0.000E+00 2.680E+00 0.000E+00 6.760E+00 0.OOOE+00 2.290E+02 0.000E+00 1.260E+00 ZN-65 2.3 1OE+04 7.350E+04 0.OOOE+00 4.920E+04 O.OOOE+00 4.630E+04 0.OOOE+00 3.320E+04 ZN-69 .7.730E-07 1.480E-06 0.OOOE+00 9.610E-07 0.OOOE+00 2.220E-07 0.OOOE+00 1.030E-07 BR-83 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 5.500E-02 0.000E+00 3.820E-02 BR-84 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 9.850E-18 0.OOOE+00 1.250E-12 BR-85 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 RB-86 0.OOOE+00 9.730E+04 0.OOOE+00 0.OOOE+00 0.OOOE+00 1.920E+04 0.000E+00 4.530E+04 RB-88 0.OOOE+00 1.290E-22 0.000E+00 0.OOOE+00 0.000E+00 1.780E-33 0.000E+00 6.830E-23 RB-89 0.000E+00 1.640E-26 0.OOOE+00 0.000E+00 0.OOOE+00 9.560E-40 O.OOOE+00 1.160E-26 SR-89 2.180E+04 0.OOOE+00 0.OOOE+00 0.000E+00 0.OOOE+00 3.500E+03 0.000E+00 6.260E+02 SR-90 5.440E+05 0.600E+00 0.000E+00 0.000E+00 0.OOOE+00 1.570E+04 0.OOOE+00. 1.340E+05 SR-91 7.050E+01 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 3.360E+02 0.OOOE+00 2.850E+00 Appendix C Al Adult Fish - Page 1 of 3

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX C Ai Adult Dose Factors for use in the Liquid Dose Calculations Agegroup: ADULT :Pathway:- Fresh Water Fish - Sport (FFSP) Units: mrem/hr / pCi/ml Nuclide: Bone Livr Thyroid, Kidne Lung Gilli Skin Total.Body SR-92 3.320E-01 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 6.570E+00 0.OOOE+00 1.430E-02 Y-90 4.440E-01 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 4.710E+03 0.OOOE+00 1.190E-02 Y-91 8.340E+00 0.OOOE+00 0.OOOE+00 0.000E+00 0.OOOE+00 4.590E+03 0.OOOE+00 2.230E-01 Y-91M 1.070E-11 0.OOOE+00 0.OOOE+00 O.OOOE+00 0.OOOE+00 3.150E-11 0.0OOE+00 4.150E-13 Y-92 4.600E-04 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 8.060E+00 0.000E+00 1..340E-05 Y-93 3.080E-02 0.OOOE+00 0.OOOE+00 0.OOOE+00 O.OOOE+00 9.770E+02 0.OOOE+00 8.500E-04 ZR-95 2.380E-01 7.620E-02 0.000E+00 1.200E-01 0.OOOE+00 2.410E+02 0.OOOE+00 5.160E-02 ZR-97 4.960E-03 1.000E-03 0.OOOE+00 1.510E-03 0.OOOE+00 3.100E+02 0.OOOE+00 4.570E-04 NB-95 4.380E+02 2.440E+02 0.OOOE+00 2.410E+02 0.OOOE+00 1.480E+06 0.OOOE+00 1.310E+02 MO-99 0.OOOE+00 8.020E+01 0.OOOE+00 1.820E+02 0.OOOE+00 1.860E+02 0.OOOE+00 1.530E+01 TC-99M 5.590E-04 1.580E-03 0.OOOE+00 2.400E-02 7.740E-04 9.340E-01 0.OOOE+00 2.010E-02 TC-101 2.610E-33 3.760E-33 0.OOOE+00 6.770E-32 1.920E-33 1.130E-44 0.OOOE+00 3.690E-32 RU-103 4.350E+00 0.OOOE+00 0.OOOE+00 1.660E+01 0.000E+00 5.080E+02 0.OOOE+00 1.870E+00 RU-105 8.670E-03 0.OOOE+00 0.000E+00 1.120E-01 0.000E+00 5.300E+00 0.OOOE+00 3.420E-03 RU- 106 6.570E+01 0.000E+00 0.OOOE+00 1.270E+02 0.OOOE+00 4.250E+03 0.000E+00 8.320E+00 AG-110M 8.790E-01 8.130E-01 0.OOOE+00 1.600E+00 0.OOOE+00 3.320E+02 0.OOOE+00 4.830E-01 TE-125M 2.540E+03 9.190E+02 7.630E+02 1.030E+04 0.OOOE+00 1.010E+04 0.OOOE+00 3.400E+02 TE-127 1.790E+01 6.440E+00 1.330E+01 7.300E+01 0.OOOE+00 1.410E+03 0.OOOE+00 3.880E+00 TE-127M 6.440E+03 2.300E+03 1.650E+03 2.620E+04 0.OOOE+00 2.160E+04 0.OOOE+00 7.850E+02 TE-129 1.630E-05 6.120E-06 1.250E-05 6.850E-05 0.000E+00 1.230E-05 . .OOOE.0O - 3.970E-.06 TE- 129M 1.080E+04 4.020E+03 3.710E+03 4.500E+04 0.OOOE+00 5.430E+04 0.OOOE+00 1.710E+03 TE-131 8.710E-17 3.640E-17 7.160E-17 3.820E-16 0.OOOE+00 1.230E-17 0.OOOE+00 2.750E-17 TE- 131M 9.51 OE+02 4.650E+02 7.370E+02 4.710E+03 0.OOOE+00 4.620E+04 0.OOOE+00 3.880E+02 TE-132 1.950E+03 1.260E+03 1.390E+03 1.210E+04 0.OOOE+00 5.960E+04 0.OOOE+00 1.1 80E+03 11-130 7.050E+00 2.080E+01 1.760E+03 3.250E+01 0.OOOE+00 1.790E+01 0.OOOE+00 8.210E+00 0

Appendix C Ai Adult Fish - Page 2 of 3

Oconee Nuclear Station 0

January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX C A, Adult Dose Factors for use in the Liquid Dose Calculations Agegroup: ADULT Pathway: Fresh Water Fish - Sport (FFSP) Units:. mrem/hr / pLCi/ml Nuclide Bone Liver Thyroid Kidney LUng Gilli Skin Total Body 1-131 1.370E+02 1.960E+02 6.420E+04 3.360E+02 0.000E+00. 5.170E+01 0.000E+00 1. 120E+02 1-132 5.270E-03 1.410E-02 4.940E-01 2.250E-02 0.OOOE+00 2.650E-03 0.OOOE+00 4.940E-03 1-133 2.290E+01 3.990E+01 5.860E+03 6.950E+01 0.OOOE+00 3.580E+01 0.OOOE+00 1.210E+01 1-134 2.120E-08 5.750E-08 9.960E-07 9.140E-08 0.OOOE+0'0 5.0.1OE-11 0.OOOE+00 2.060E-08 1-135 1.290E+00 3.370E+00 2.220E+02 5.410E+00 0.OOOE+00 3.810E+00 0.OOOE+00 1.240E+00 CS-134 2.980E+05 7.080E+05 0.OOOE+00. 2.290E+05 7.610E+04 1.240E+04 0.OOOE+00 5.790E+05 CS-136 2.960E+04 1.170E+05 0.OOOE+00 6.500E+04 8.900E+03 1.330E+04 0.OOOE+/-00 8.400E+04 CS-137 .3.820E+05 5.220E+05 0.000E+00 1.770E+05 5.890E+04 1.0lO0E+04 0.000E+00 3.420E+05 CS-138 8.940E-12 1.770E-1 1 0.060E+00 1.300E-1 1 1.280E-12 7.530E-17 0.000E+00 8.750E-12 BA-139 5.650E-06 4.030E-09 0.OOOE+00 3.760E-09 2.280E-09 1.000E-05 0.OOOE+00 1.660E-07 BA-140 1.840E+02 2.310E-01 0.OOOE+00 7.860E-02 1.320E-01 3.790E+02 0.OOOE+00 1.210E+01 BA- 141 8.700E-25 6.580E-28 0.OOOE+00 6.120E-28 3.730E-28 4.100E-34 0.OOOE+00 2.940E-26 BA-142 2.570E-42 2.640E-45 0.OOOE-00 2.230E-45 1.490E-45 3.620E-60 0.OOOE+/-00 1.610E-43 LA-140 9.900E-02 4.990E-02 0.OOOE+00 0.000E+00 0.OOOE+00 3.660E+03 0.OOOE+00 1.320E-02 LA-142 2.210E-07 1.000E-07 0.OOOE+00 0.OOOE+00 0.000E+00 7.330E-04 0.OOOE+00 2.500E-08 CE-141 2.190E-02 1.480E-02 0.OOOE+00 6.890E-03 0.000E+00 5.670E+01 0.OOOE+00 1.680E-03 CE-143 2.3 80E-03 1.760E+00 0.OOOE+00 7.760E-04 0.000E+00 6.590E+01 0.OOOE+00 1.950E-04 CE- 144 1.170E+00 4.870E-01 0.000E+00 2.890E-01 0.OOOE+00 3.940E+02 0.OOOE+00 6.260E-02 PR-143 5.230E-01 2.100E-01 0.OOOE+00 1.210E-01 0.OOOE+00 2.290E+03 0.OOOE+00 2.590E-02 PR-144 1.550E-28 6.440E-29 0.OOOE+00 3.630E-29 0.OOOE+00 2.230E-35 0.OOOE+00 7.880E-30 ND-147 3.530E-01 4.080E-01 0.OOOE+00 2.390E-01 0.OOOE+00 1.960E+03 0.OOOE+00 2.440E-02 W-187 1.470E+02 1.230E+02 0.OOOE+00 0.OOOE+00 0.OOOE+00 4.030E+04 0.OOOE+00 4.300E+01 NP-239 2.120E-02 2.090E-03 0.OOOE+00 6.510E-03 0.OOOE+00 4.280E+02 0.OOOE+00 1.150E-03 Appendix C Ai Adult Fish - Page 3 of 3

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX C Ai Adult Dose Factors for use in the Liquid Dose Calculations Agegroup: ADULT Pathway: Shoreline Sediment (SHDp) Units: mrem/hr / pCi/ml

  • Nuclide* Bone. Liver Thyroid Kidney Lung Gilli Skin, Total Body H-3 0.000E+00 0.OOOE+00 0.000E+00 0.OOOE+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 C-14 0.OOOE+00 0.OOOE+00 0.000E+00 0.OOOE+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 NA-24 4.270E-01 4.270E-01 4.270E-01 4.270E-01 4.270E-01 4.270E-01 4.960E-01 4.270E-01 P-32 0.000E+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.000E+00 0.000E+00 0.OOOE+00 CR-51 1.670E-01 1.670E-01 1.670E-01 1.670E-01 1.670E-01 1.670E-01 1.970E-01 1.670E-01 MN-54 4.960E+01 4.960E+0I 4.960E+01 4.960E+01 4.960E+01 4.960E+01 5.820E+01 4.960E+01 MN-56 3.230E-02 3.230E-02 3.230E-02 3.230E-02 3.230E-02 3.230E-02 3.820E-02 3.230E-02 FE-55 0.000E+00 0.OOOE+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.OOOE+00 0.000E+00 FE-59 9.770E+00 9.770E+00 9.770E+00 9.770E+00 9.770E+00 9.770E+00 1.150E+01 9.770E+00 CO-58 1.360E+01 1.360E+01 1.360E+01 1.360E+01 1.360E+01 1.360E+01 1.590E+01 1.360E+01 CO-60 7.690E+02 7.690E+02 7.690E+02 7.690E+02 7.690E+02 7.690E+02 9.050E+02 7.690E+02 NI-63 0.OOOE+00 0.OOOE+00 0.000E+00 0.OOOE+00 0.000E+00 0.000E+00 0.OOOE+00 0.OOOE+00 NI-65 1.060E-02 1.060E-02 1.060E-02 1.060E-02 1.060E-02 1.060E-02 1.240E-02 1.060E-02 CU-64 2.170E-02 2.170E-02 2.170E-02 2.170E-02 2.170E-02 2.170E-02 2.460E-02 2.170E-02 ZN-65 2.670E+01 2.670E+01 2.670E+01 2.670E+01 2.670E+01 2.670E+01 3.080E+01 2.670E+01 ZN-69 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.OOOE+00 BR-83 1.740E-04 1.740E-04 1.740E-04 1.740E-04 1.740E-04 - 1.740E-04 2.530E-04 1.740E-04 BR-84 7.250E-03 7.250E-03 7.250E-03 7.250E-03 7.250E-03 7.250E-03 8.460E-03 7.250E-03 BR-85 0.000E+00 0.OOOE+00 0.000E+00 0.OOOE+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-0f 3.680E-0i 3.220E-01 RB-88 1.180E-03 1.180E-03 1.180E-03 1.180E-03 1.180E-03 1.180E-03 1.350E-03 1.180E-03 RB-89 4.400E-03 4.400E-03 4.400E-03 4.400E-03 4.400E-03 4.400E-03 5.280E-03 4.400E-03 SR-89 7.740E-04 7.740E-04 7.740E-04 7.740E-04 7.740E-04 7.740E-04 8.990E-04 7.740E-04 SR-90 0.000E+00 0.OOOE+00 0.000E+00 0.OOOE+00 0.000E+00 0.000E+00 0.OOOE+00 0.000E+00 SR-91 7.690E-02 7.690E-02 7.690E-02 7.690E-02 7.690E-02 7.690E-02 8.990E-02 7.690E-02 Appendix C Ai Adult Shoreline Sediment - Page 1 of 3 0

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January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX C A. Adult Dose Factors for use in the Liquid Dose Calculations Agegroup: ADULT Pathway: Shoreline Sediment (SHDp) Units: mrem/hr / ptCi/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin -Total Body SR-92 2.780E-02 2.780E-02 2.780E-02 2.780E-02 2.780E-02 2.780E-02 3.090E-02 2.780E-02 Y-90 1.610E-04 1.610E-04 1.610E-04 1.610E-04 1.610E-04 1.610E-04 1.900E-04 1.610E-04 Y-91 3.840E-02 3.840E-02 3.840E-02 3.840E-02 3.840E-02 3.840E-02 4.320E-02 3.840E-02 Y-91M 3.590E-03 3.590E-03 3.590E-03 3.590E-03 3.590E-03 3.590E-03 4.150E-03 3.590E-03 Y-92 6.460E-03 6.460E-03 6.460E-03 6.460E-03 6.460E-03 6.460E-03 7.670E-03 6.460E-03 Y-93 6.560E-03 6.560E-03 6.560E-03 6.560E-03 6.560E-03 6.560E-03 8.980E-03 6.560E-03 ZR-95 8.760E+00 8.760E+00 8.760E+00 8.760E+00 8.760E+00 8.760E+00 1.020E+01 8.760E+00 ZR-97 1.060E-01 1.060E-01 1.060E-01 1.060E-01 1.060E-01 1.060E-01 1.230E-01 1.060E-01 NB-95 4.890E+00 4.890E+00 4.890E+00 4.890E+00 4.890E+00 4.890E+00 5.750E+00 4.890E+00 MO-99 1.430E-01 1.430E-01 1.430E-01 1.430E-01 - 1.430E-01 1.430E-01 1.660E-01 1.430E-01 TC-99M 6.590E-03 6.590E-03 6.590E-03 6.590E-03 6.590E-03 6.590E-03 7.550E-03 6.590E-03 TC-101 7.280E-04 7.280E-04 7.280E-04 7.280E-04 7.280E-04 7.280E-04 8.090E-04 7.280E-04 RU-103 3.870E+00 3.870E-00 3.870E+00 3.870E+00 3.870E+00 3.870E+00 4.520E+00 3.870E+00 RU-105 2.280E-02 2.280E-02 -2.280E-02 2.280E-02 2.280E-02 2.280E-02 2.580E-02 2.280E-02 RU-106 1.510E+01 1.510E+01 1.510E+01 1.510E+01 1.510E+01, 1.510E+01 1.810E+01 1.510E+01 AG-110M 1.230E+02 1.230E+02 1.230E+02 1.230E+02 1.230E+02 1.230E+02 1.440E+02 1.230E+02 TE-125M 5.550E-02 5.550E-02 5.550E-02 5.550E-02 5.550E-02 5.550E-02 7.620E-02 5.550E-02 TE- 127 1.070E-04 1.070E-04 1.070E-04 1.070E-04 1.070E-04 1.070E-04 1.170E-04 1.070E-04 TE-127M 3.280E-03 3.280E-03 3.280E-03 3.280E-03 3.280E-03 3.280E-03 3.880E-03 3.280E-03 TE-129 9.390E-04 9.390E-04 9.390E-04 9.390E-04 9.390E-04 9.390E-04 1.11OE-03 9.390E-04 TE-129M 7.080E-01 7.080E-01 7.080E-01 7.080E-01 7.080E-01 7.080E-01 8.270E-01 7.080E-01 TE- 131 1.040E-03 1.040E-03 1.040E-03 1.040E-03 1.040E-03 1.040E-03 1.230E+00 1.040E-03 TE-131M 2.870E-01 2.870E-01 2.870E-01 2.870E-01 2.870E-01 2.870E-01 3.390E-01 2.870E-01 TE- 132 1.520E-01. 1.520E-01 1.520E-01 1.520E-01 1.520E-01 1.520E-01 1.780E-01 1.520E-01 11-130 1.970E-01 1.970E-01 1.970E-01 1.970E-01 1.970E-01 1.970E-01 2.390E-01 1.970E-01 Appendix C Ai Adult Shoreline Sediment - Page 2 of 3

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX C Ai Adult Dose Factors for use in the Liquid Dose Calculations Agegroup: ADULT Pathway:: Shoreline Sediment (SHDp) Units: mrem/hr / iCi/ml Nuclide Bone Liver Thyroid Kidney, Lung Gilli Skin TotalBody 1-131 6.160E-01 6.160E-01 6.160E-01 6.160E-01 6.160E-01 6.160E-01 7.480E-01 6.160E-01 1-132 4.460E-02 4.460E-02 4.460E-02 4.460E-02 4.460E-02 4.460E-02 5.240E-02 4.460E-02 1-133 8.770E-02 8.770E-02 8.770E-02 8.770E-02 8.770E-02 8.770E-02 1.070E-01 8.770E-02 1-134 1.600E-02 1.600E-02 1.600E-02 1.600E-02 1.600E-02 1.600E-02 1.900E-02 1.600E-02 1-135 9.040E-02 9.040E-02 9.040E-02 9.040E-02 9.040E-02 9.040E-02 1.050E-01 9.040E-02 CS-134 2.450E+02 2.450E+02 2.450E+02 2.450E+02 2.450E+02 2.450E+02 2.860E+02 2.450E+02 CS-136 5.400E+00 5.400E+00 5.400E+00 5.400E+00 5.400E+00 5.400E+00 6.120E+00 5.400E+00 CS-137 3.680E+02 3.680E+02 3.680E+02 3.680E+02 3.680E+02 3.680E+02 4.290E+02 3.680E+02 CS-138 1.280E-02 1.280E-02 1.280E-02 1.280E-02 1.280E-02 1.280E-02 1.470E-02 1.280E-02 BA-139 3.790E-03 3.790E-03 3.790E-03 3.790E-03 3.790E-03 3.790E-03 4.260E-03 3.790E-03 BA- 140 7.350E-01 7.350E-01 7.350E-01 7.350E-01 7.350E-01 7.350E-01 8.400E-0 1 7.350E-01 BA- 141 1.490E-03 1.490E-03 1.490E-03 .1.490E-03 1.490E-03 1.490E-03 1.700E-03 1.490E-03 BA- 142 1.610E-03 1.61 OE-03 1.61 OE-03 1.610E-03 1.61 OE-03 1.61 OE-03 1.830E-03 1.610E-03 LA- 140 6.880E-01 6.880E-01 6.880E-01 6.880E-01 6.880E-01 6.880E-01 7.790E-01 6.880E-01 LA-142 2.720E-02 2.720E-02 2.720E-02 2.720E-02 2.720E-02 2.720E-02 3.260E-02 2.720E-02 CE-141 4.890E-01 4.890E-01 4.890E-01 4.890E-01 4.890E-01 4.890E-01 5.510E-01 4.890E-01 CE- 143 8.270E-02 8.270E-02 8.270E-02 - 8.270E-02 8.270E-02 .8.270E-02 9.400E-02 8.270E-02 CE-144 2.490E+00 2.490E+00 2.490E+00 2.490E+00 2.490E+00 2.490E+00 2.880E+00 2.490E+00 PR-143 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 PR-144 6.570E-05 6.570E 6.570E 6.570E-05 6.570E-05 6.570E-05 7.550E-05 6.570E-05 ND-147 3.OOOE-01 3.OOOE-01 3.000E-01 3.OOOE-01 3.OOOE-01 3.000E-01 3.600E-01 3.000E-01 W-187 8.420E-02 8.420E-02 8.420E-02 8.420E-02 8.420E-02 8.420E-02 9.780E-02 8.420E-02 NP-239 6.120E-02 6.120E-02 6.120E-02 6.120E-02 6.120E-02 6.120E-02 7.090E-02 6.120E-02 Appendix C Ai Adult Shoreline Sediment - Page 3 of 3

0Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX D Ai Teen Factors for use in the Liquid Dose Calculations Agegroup: TEEN Pathway: Potable Water (PWtr) Units: mrem/hr / gCi/ml Nuclide .. Bone. Liver Thyroid g**

..... L uKidey Gilli Skin' - "Total Body H-3 0.OOOE+00 6.160E+00 6.160E+00 6.160E+00 6.160E+00 6.160E+00 0.000E+00 6.160E+00 C- 14 2.360E+02 4.720E+01 4.720E+01 4.720E+01I 4.720E+01 4.720E+01 0.OOOE+00 4.720E+01 NA-24 7.690E+01 7.690E+01 7.690E+01 7.690E+01 7.690E+01 7.690E+01 0.OOOE+00 7.690E+01 P-32 1.570E+04 9.700E+02 0.000E+00 0.OOOE+00 0.OOOE+00 1.320E+03 0.OOOE+00 6.070E+02 CR-51 0.000E+00 0.000E+00 1.150E-01 4.530E-02 2.950E-01 3.470E+01 0.OOOE+00 2.070E-01 MN-54 0.OOOE+00 3.430E+02 0.OOOE+00 1.020E+02 0.OOOE+00 7.030E+02 0.OOOE+00 6.790E+01 MN-56 0.OOOE+00 3.640E-01 0.OOOE+00 4.610E-01 0.000E+00 2.400E+01 0.OOOE+00 6.480E-02 FE-55 2.200E+02 1.560E+02 0.000E+00 O.OOOE+00 9.880E+01 6.740Et01 0.000E+00 3.630E+01 FE-59 3.390E+02 7.900E+02 O.OOOE+00 0.OOOE+00 2.490E+02 1.870E+03 0.OOOE+00 3.050E+02 CO-58 0.OOOE+00 5.620E+01 0.OOOE+00 0.OOOE+00 0.OOOE+00 7.750E+02 0.000E+00 1.300E+02.

CO-60 0.OOOE+00 1.630E+02 0.OOOE+00 0.OOOE+00 0.000E+00 2.130E+03 0.000E+00 3.680E+02 NI-63 1.030E4-04 7.270E+02 0.OOOE+00 0.000E+00 0.000t+00 1.160E+02 0.OOOE+00 3.490E+02 NI-65 1.610E+00 2.050E-01 0.OOOE+00 0.OOOE+00 0.000E+00 1.11OE+01 0.OOOE+00 9.350E-02 CU-64 0.OOOE+00 3.470E+00 0.000E+00 8.770E+00 0.000E+00 2.690E+02 0.000E+00 1.630E+00 ZN-65 3.340E+02 1.1 60E+03 0.OOOE+00 7.430E+02 0.OOOE+00 4.920E+02 0.000E+00 5.420E+02 ZN-69 1.070E-04 2.040E-04 0.OOOE+00 1.330E-04 0.OOOE+00 3.760E-04 0.OOOE+00 1.430E-05 BR-83 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.030E-01 BR-84 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.000E+00 0.000E+00 0.OOOE+00 0.OOOE+00 6.500E-07 BR-85 . 0.OOOE+00 0.OOOE+00 0.OOOE+00 O.OOOE+00 0.OOOE+00 0.000E+00 0.000E+00 4.360E-77 RB-86 0.OOOE+00 1.700E+03 0.000E+00 O.OOOE+00 0.000E+00 2.520E+02 0.OOOE+00 7.990E+02 RB-88 0.OOOE+00 3.300E-12 0.OOOE+00 0.OOOE+00 0.OOOE+00 2.830E-19 0.OOOE+00 1.760E-12 RB-89 0.OOOE+00 2.960E-14 0.OOOE+00 0.OOOE+00 " 0.OOOE+00 4.540E-23 0.OOOE+00 2.090E-14 SR-89 2.540E+04 0.000E+00 0.OOOE+00 0.000E+00 0.000E+00 3.030E+03 0.OOOE+00 7.280E+02 SR-90 4.830E+05 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 1.350E+04 0.OOOE+00 1.190E+05 SR-91 1.950E+02 0.OOOE+00 0.000E+00 0.OOOE+00 0.OOOE+00 8.850E+02 0.000E+00 7.760E+00 Appendix D Ai Teen Water - Page 1of 3

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX D A, Teen Factors for use in the Liquid Dose Calculations Agegroup: TEEN Pathway: Potable Water (PWtr) Units: mrem/hr / pCi/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body SR-92 8.220E+00 0.000E+00 0.OOOE+00 0.000E+00 0.OOOE+00 2.090E+02 0.OOOE+00 3.500E-01 Y-90 7.OOOE-01 0.000E+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 5.770E+03 0.OOOE+00 1.880E-02 Y-91 1.160E+01 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 4.760E+03 0.OOOE+00 3.120E-01 Y-91M 3.330E-07 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 1.570E-05 0.OOOE+00 1.270E-08 Y-92 6.710E-03 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 1.840E+02 0.OOOE+00 1.940E-04 Y-93 9.760E-02 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 2.980E+03 0.OOOE+00 2.670E-03 ZR-95 2.380E+00 7.520E-01 0.OOOE+00 1.100E+00 0.OOOE+00 1.730E+03 0.OOOE+00 5.170E-01 ZR-97 8.420E-02 1.670E-02 0.OOOE+00 2.530E-02 0.OOOE+00 4.510E+03 0.OOOE+00 7.670E-03 NB-95 4.730E-01 2.630E-01 0.OOOE+00 2.540E-01 0.OOOE+00 1.120E+03 0.OOOE+00 1.440E-01 MO-99 0.00OE+00 3.090E+02 0.OOOE+00 7.070E+02 0.OOOE+00 5.530E+02 0.OOOE+00 5.890E+01 TC-99M 4.840E-03 1.350E-02 O.OOOE+00 2.010E-01 7.500E-03 8.870E+00 0.OOOE+00 1.750E-01 TC-101 1.120E-17 1.590E-17 0.OOOE+00 2.880E-16 9.700E-18 2.720E-24 0.OOOE+00 1.560E-16 RU-103 1.470E+01 0.OOOE+00 0.OOOE+00 5.180E+01 0.OOOE+00 1.230E+03 0.OOOE+00 6.280E+00 RU-105 1.940E-01 0.OOOE+00 0.OOOE+-00 2.450E+00 0.OOOE+00 1.570E+02 0.OOOE+00 7.540E-02 RU-106 2.280E+02 0.OOOE+00 0.000E+00 4.390E+02 0.OOOE+00 1.090E+04 0.OOOE+00 2.870E+01 AG-1 10M 1.190E+01 1.130E+01 0.OOOE+00 2.150E+01 0.OOOE+00 3.160E+03 0.OOOE+00 6.850E+00 TE-125M 2.210E+02 7.980E+01 6,180E+01 0.OOOE+00 0.OOOE+00 6.530E+02 0.OOOE+00 2.960E+01 TE-127 3.790E+00 L340E+00 2.610E+00 1.530E+01 0.OOOE+00 2.930E+02 0.OOOE+00 8.150E-01 TE-127M 5.600E+02 1.990E+02 1.330E+02 2.270E+03 0.000t+00 1.400E+03 0.OOOE+00 6.660E+01 TE-129 1.920E-03 7.150E-04 1.370E-03 8.040E-03 O.OOOE+00

  • 1.050E-02 0.OOOE+00 4.660E-04 TE-129M 9.380E+02 3.480E+02 3.030E+02 3.920E+03 0.OOOE+00 3.520E+03 0.OOOE+00 1.480E+02 TE-131 3.490E-09 1.440E-09 2.690E-09 1.520E-08 0.OOOE+00 2.860E-10 0.OOOE+00 1.090E-09 TE-131M 1.080E+02 5.150E+01 7.750E+01 5.380E+02 0.OOOE+00 4.140E+03 O.OOOE+00 4.300E+01 TE-132 1.820E+02 1.150E+02 1.220E+02 1.11OE+03 0.OOOE+00 3.660E+03 0.OOOE+00 1.090E+02 1-130 3.050E+01 8.830E+01 7.200E+03 1.360E+02 0.OOOE+00 6.790E+01 0.000E+00 3.530E+01 0

Appendix D Ai Teen Water - Page 2 of 3

Oconee Nuclear Station 0

January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX D A. Teen Factors for use in the Liquid Dose Calculations Agegroup. TEEN Pathway: Potable Water (PWtr) Units: mrem/hr / ýWCi/ml Nuclide fBoe'Livr Thyroid Kidney,"= :Lungf .. Gilli. - . Skin Total Body 1-131 3.260E+02 4.560E+02 1.330E+05 7.850E+02 0.OOOE+00 9.020E-01 0.OOOE+00 2.450E+02 1-132 4.360E-01 1.140E+00 -3.850E+01 1.800E+00 0.OOOE+00 4.970E-01 0.OOOE+00 4.100E-01 1-133 7.830E+01 1.330E+02 1.860E+04 2.330E+02 0.OOOE+00 1.010E+02 0.OOOE+00 4.050E+01 1-134 6.330E-04 1,.680E-03 2.800E-02 2.640E-03 0.OOOE+00 2.210E-05 0.OOOE+00 6.020E-04 1-135 1.01OE+01 2.600E+01 1.670E+03 4.100E+01 0.OOOE+00 2.880E+01 0.OOOE+00 9.630E+00 CS-134 4.860E+03 1.140E+04 0.OOOE+00 3.640E+03 1.390E+03 1.420E+02 O.000E+00 5.31 OE+03 CS-136 4.860E+02 1.910E+03 0.OOOE+00 1.040E+03 1.640E+02 1.540E+02 0.OOOE+00 1.290E+03 CS-137 6.510E+03 8.660E+03 0.OOOE+00 2.950E+03 1.150E+03 1.230E+02 0.OOOE+00 3.020E+03 CS-138 8.300E-07 1.590E-06 0.000E+00 1.180E-06 1.370E-07 7.230E-10 0.OOOE+00 7.970E-07 BA-139 1.990E-02 1.400E-05 0.OOOE+00 1.320E-05 9.670E-06 1.780E-01 0.OOOE+00 5.810E-04 BA-140 1.610E+03 1.970E+00 0.OOOE+00 6.680E-01 1.320E+00 2.480E+03 0.OOOE+00 1.040E+02 BA- 141 5.420E-12 4.050E-15 0.OOOE+00 3.760E- 15 2.770E-15 1.150E-17 0.OOOE+00 1.810E-13 BA-142 6.170E-21 6.170E-24 O.OOOE+00 5.220E-24 4.100E-24 1.890E-32 0.OOOE+00 3.800E-22 LA-140 1.650E-01 8.090E-02 0.OOOE+00 0.OOOE+00 0.OOOE+00 4.640E+03 0.OOOE+00 2.150E-02 LA-142 5.590E-05 2.480E-05 0.OOOE+00 0.OOOE+00 0.OOOEt00 7.550E-01 0.OOOE+00 6.180E-06 CE- 141 7.650E-01 5.11OE-01 0.OOOE+00 2.400E 0.OOOE+00 1.460E+03 0.000E+00 - 5.870E-02 CE-143 1.060E-01 7.730E+01 0.OOOE+00 3.460E-02 0.OOOE+00 2.320E+03 0.OOOE+00 8.630E-03 CE-144 4.040E+01 1.670E+01 0.OOOE+00 9.990E+00 0.OOOE+00 1.020E+04 0.OOOE+00 2.170E+00 PR-143 7.420E-01 2.960E-01 0.OOOE+00 1.720E-01 0.OOOE+00 2.440E+03 0.000E+00 3.700E-02 PR-144 7.330E-16 3.OOOE-16 0.OOOE+00 1.720E-16 0.OOOE+00 8.080E-19 0.000E+00 3.720E-17 ND-147 5.280E-01 5.750E-01 0.000E+00 3.370E-01 0.OOOE+00 2.070E+03 0.OOOE+00 3.440E-02 W-187 5.990E+00 4.880E+00 O.OOOE+00 0.OOOE+00 0.OOOE+00 1.320E+03 0.OOOE+00 1.710E+00 NP-239 8.830E-02 8.330E-03 0.OOOE+00 2.610E-02 0.OOOE+00 1.340E+03 0.OOOE+00 4.630E-03 Appendix D Ai Teen Water - Page 3 of 3

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX D Ai Teen Dose Factors for use in the Liquid Dose Calculations Agegroup: TEEN PathWay: Fresh Water Fish - Sport (FFSP) Units': 'mrem/hr / Ciiml Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body H-3 0.OOOE+00 1.740E-01 1.740E-0 1 1.740E-01 1.740E-01 1.740E-01 0.000E+00 1.740E-0 I C-14 3.410E+04 6.810E-i+03 6.810E+03 6.810E+03 6.810E+03 6.810E+03 0.OOOE+00 6.810E+03 NA-24 1.390E+02 1.390E+02 1.390E+02 1.390E+02 1.390E+02 1.390E+02 0.OOOE+00 1.390E+02 P-32 1.440E+06 8.910E+04. 0.000E+00 0.OOOE+00 0.OOOE+00 1.210E+05 0.OOOE+00 - 5.580E+04 CR-51 0.OOOE+00 0.OOOE+00 7.120E-01 2.810E-01 1.830E+00 2.150E+02 0.OOOE+00 1.280E+00 MN-54 0.OOOE+00 4.300E+03 O.OOOE+00 4.280E+03 0.OOOE+00 8.810E+03 0.OOOE+00 8.520E+02 MN-56 O.OOOE+00 1.810E-01 0.OOOE+00 2.300E-01 0.OOOE+00 1.190E+01 0.000E+00 3.230E-02 FE-55 6.890E+02 4.880E+02 0.OOOE+00 0.000E+00 3.100E+02 2.110E+02 0.000E+00 1.140E+02 FE-59 1.050E+03 2.460E+03 0.OOOE+00 0.OOOE+00 7.760E+02 5.820E+03 0.OOOE+00 9.500E+02 CO-58 0.OOOE+00 8.780E+01 0.OOOE+00 0.OOOE+00 0.OOOE+00 1.210E+03 0.000E+00 2.020E+02 CO-60 0.OOOE+00 2.560E+02 0.OOOE+00 0.OOOE+f00 0.OOOE+00 3.340E+03 0.OOOE+00 5.770E+02 NI-63 3.230E+04 2.280E+03 0.OOOE+00 0.OOOE+00 0.000OE+00 - 3.630E+02 0:OOOE+00 1.090E+03 NI-65 1.860E-01 2.370E-02 0.OOOE+00 0.OOOE+00 0.000E+00 1.290E+00 0.000E+00 1.080E-02 CU-64 0.OOOE+00 2.820E+00 0.000E+00 7.140E+00 0.OOOE+00 2.190E+02 O.OOOE+00 1.330E+00 ZN-65 2.100E+04 7.280E+04 0.OOOE+00 4.660E+04 0.OOOE+00 3.080E+04 0.OOOE+00 3.390E+04 ZN-69 8.410E-07 1.600E-06 0.OOOE+00 1.050E-06 0.000E+00 2.950E-06 0.OOOE+00 1.120E-07 BR-83 0.OOOE+00 0.OOOE+00 0.OOOE+00 O.000E+00 0.000E+00 0.OOOE+00 0.OOOE+00 4.160E-02 BR-84 0.000E+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OO0E+00 0.000E+00 0.OOOE+00 1.320E-12 BR-85 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00

-RB-86 0.000E+06 1'.050E+05. O.OOOE+00 O.OOOE+ .. O.OOOE+00 .. 1.550E+04 0.600E+00 -. 4.920E+04 RB-88 0.OOOE+00 1.380E-22 0.OOOE+00 0.OOOE+00 0.000E+00 1.1 80E-29 0.OOOE+00 7.360E-23 RB-89 0.000E+00 1.720E-26 0.000E+00 0.OOOE+00 0.000E+00 2.630E-35 0.000E+00 1.220E-26 SR-89 2.370E+04 0.OOOE+00 0.OOOE+00 0.000E+00 0.000E+00 2.830E+03 0.000E+00 6.800E+02 SR-90 4.540E+05 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.000E+00 1.270E+04 0.000E+00 1.120E+05 SR-91 7.640E+01 0.000E+00 0.OOOE+00 0.OOOE+00 0.000E+00 3.470E+02 0.OOOE+00 3.040E+00 Appendix D Ai Teen Fish - Page 1 of 3

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX D Ai Teen Dose Factors for use in the Liquid Dose Calculations "Agegroup: TEEN Pathway: Fresh Water Fish - Sport (FFSP) Units: mrem/hr/IXCi/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin g Total Bodyo SR-92 3.590E-01 0.OOOE+00 0.000E+00 0.060E+00 0.OOOE+00 9.130E+00 0.OOOE+00 1.530E-02 Y-90 4.820E-01 0.000E+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 3.980E+03 00003E+00 1.300E-02 Y-91 9.060E+00 0.OOOE+00 0.000E+00 0.OOOE+00 0.OOOE+00 3.710E+03 0.000E+00 2.430E-01 Y-91M 1.160E-11 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.000E+00 5.470E-10 0.OOOE+00 4.430E-13 Y-92 5.020E-04 .0003E+00 0.OOOE+00 0.OOOE+00 0.OOOEt00 1.380E+01 0.000E+00 1.450E-05 Y-93 3.350E-02 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 1.020E+03 0.OOOE+00 9.190E-04 ZR-95 2.450E-01 7.740E-02 0.OOOE+00 1.140E-01 0.OOOE+00 1.790E+02 0.OOOE+00 5.320E-02 ZR-97 5.330E-03 1.050E-03 0.OOOE+00 1.600E-03 0.OOOE+00 2.850E+02 0.000E+00 4.860E-04 NB-95 4.410E+02 2.450E+02 0.OOOE+00 2.370E+02 0.OOOE+00 1.050E+06 0.OOOE+00 1.350E+02 MO-99 0.OOOE+00 8.550E+01 0.OOOE+00 - 1.960E+02 0.OOOE+00- 1.530E+02 0.000E+00 1.630E+01 TC-99M 5.720E-04 1.600E-03 0.OOOE+00 2.380E-02 8.860E-04 1.050E+00 0.OOOE+00 2.070E-02 TC-101 2.820E-33 4.010E-33 00003E+00 7.240E-32 2.440E-33 6.840E-40 0.OOOE+00 3.930E-32 RU-103 4.570E+00 0.OOOE+00 0.OOOE+00 1.610E+01 0.OOOE+00 3.820E+02 0.OOOE+00 1.950E+00 RU-105 9.350E-03 0.OOOE+00 0.OOOE+00 1.180E-01 0.OOOE+00 7.550E+00 0.OOOE+00 3.630E-03 RU-106 7.140E+01- 0.000E+00 0.000t+00 1.380E+02 0.000E+00 3.420E+03 0.000E+00 8.990E+00 AG-I OM 8.580E-01 8.120E-01 0.OOOE+00 1.550E+00 0.OOOE+00 2.280E1+02 0.000E+00 4.940E-01 TE-125M 2.760E+03 9.950E+02 7.710E+02 0.OOOE+00 0.OOOE+00 8.150E+03 0.000E+00 3.690E+02 TE-127 1.960E+01 6.950E+00 1.350E+01 7.940E+01 0.OOOE+00 1.510E+03 0.OOOE+00 4.220E+00 TE-127M 7.010E+03 2.490E+03 1.670E+03 2.840E+04 0.OOOE+00 1.750E+04 0.000E+00 8.340E+02 TE-129 1.770E-05 6.600E-06 1.260E-05 7.430E-05 0.OOOE+00 9.680E-05 0.OOOE+00 4.310E-06 TE-129M 1.160E+04 4.320E+03 3.760E+03 4.870E+04 0.OOOE+00 4.370E+04 0.OOOE+00 1.840E+03 TE-131 9.400E-17 3.870E-17 7.240E-17 4.110E-16 0.OOOE+00 7.710E-18 0.000E+00 2.940E-17 TE-131M 1.020E+03 4.900E+02 7.370E+02 5.11OE+03 0.OOOE+00 3.930E+04 0.OOOE+00 4.090E+02 TE-132 2.060E+03 1.300E+03 1.370E+03 1.250E+04 0.OOOE+00 4.130E+04 0.OOOE+00 1.230E+03 1-130 7.320E+00 2.120E+01 1.730E+03 3.260E+01 0.OOOE+00 1.630E+01 0.OOOE+00 8.460E+00 Appendix D Ai Teen Fish - Page 2 of 3

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX D Ai Teen Dose Factors for use in the Liquid Dose Calculations Agegroup: TEEN Pathway: Fresh Water Fish - Sport (FFSP) Units: mrem/hr / tCi/ml Nucdide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body 1-131 1.470E+02 2.060E+02 6.OOOE+04 3.540E+02 0.OOOE+00 4.070E+01 0.OOOE+00 1.100E+02 1-132 5.520E-03 1.440E-02 4.870E-01 2.280E-02 0.OOOE+00 6.290E-03 0.OOOE+00 5.180E-03 1-133 2.470E+01 4.190E+01 5.850E+03 7.350E+01 0.OOOE+00 3.170E+01 0.000E+00 1.280E+01 1-134 2.220E-08 5.890E-08 9.810E-07 9.280E-08 0.OOOE+00 7.760E-10 0.OOOE+00 2.11OE-08 1-135 1.350E+00 3.480E+00 2.240E+02 5.490E+00 0.OOOE+00 3.850E+00 0.OOOE+00 1.290E+00 CS-134 3.050E+05 7.180E+05 0.OOOE+00 2.280E+05 8.710E+04 8.930E+03 0.OOOE+00 3.330E+05 CS-136 2.970E+04 1.170E+05 0.OOOE+00 6.370E+04 1.000E+04 9.410E+03 0.OOOE+00 7.860E+04 CS-137 4.090E+05 5.440E+05 0.OOOE+00 1.850E+05 7.190E+04 7.730E+03 0.OOOE+00 1.890E+05 CS-138 9.580E-12 1.840E-11 0.OOOE+00 1.360E-11 1.580E-12 8.340E-15 0.000E+00 9.190E-12 BA-139 6.170E-06 4.340E-09 0.000E+00 4.090E-09 2.990E-09 5.510E-05 0.000E+00 1.800E-07 BA-140 1.960E+02 2.410E-01 0.000E+00- 8.160E-02 1.620E-01 3.030E+02 0.OOOE+00 1.260E+01 BA-141 9.450E-25 7.050E-28 0.OOOE+00 6.550E-28 4.830E-28 2.010E-30 0.OOOE+00 3.150E-26 BA-142 2.750E-42 2.750E-45 0.OOOE+00 2.320E-45 1.830E-45 8.430E-54 0.OOOE+00 1.690E-43 LA-140 1.050E-01 5.160E-02 0.OOOE+00 0.OOOE+00 0.OOOE+00 2.960E+03 0.OOOE+00 1.370E-02 LA-142 2.350E-07 1.040E-07 0.000E+00 0.OOOE+00 0.OOOE+00 3.180E-03 0.OOOE+00 2.600E-08 CE-141 2.370E-02 1.590E-02 0.OOOE+00 7.460E-03 0.OOOE+00 4.540E+01 0.OOOE+00 1.820E-03 CE-143 2.590E-03 1.880E+00 0.OOOE+00 8.450E-04 0.OOOE+00 5.660E+01 0.OOOE+00 2.100E-04 CE-144 1.270E+00 5.240E-01 0.OOOE+00 3.130E-01 0.OOOE+00 3.180E+02 0.OOOE+00 6.810E-02 PR-143 5.680E-01* 2.270E-01 0.OOOE+00 1.320E-01 0.OOOE+00 1.870E+03 0.OOOE+00 2.830E-02 PR-144 - .1.690E-28 6.900E,29 0.OOOE+00 -3.960E-29 O.OOOE+00 1.860E-31 .0.000E+00 . 8.550E-30 ND-147 4.020E-01 4.370E-01 0.OOOE+00 2.560E-01 0.OOOE+00 1.580E+03 0.OOOE+00 2.620E-02 W-187 1.590E+02 1.300E+02 0.OOOE-00 0.OOOE+00 0.OOOE+00 3.5 1OE+04 0.OOOE+00 4.540E+01 NP-239 2.390E-02 2.260E-03 0.OOOE+00 7.080E-03 0.OOOE+00 3.630E+02 0.000E+00 1.250E-03 Appendix D Ai Teen Fish - Page 3 of 3

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX D Ai Teen Dose Factors for use in the Liquid Dose Calculations Agegroup: TEEN Pathway: Shoreline Sediment (SHDp) Units: mrem/hr / i.Ci/ml Nuclide Bone Liver Thyroid Kidney Lung Gili' Skin TotalBody H-3 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 C- 14 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 NA-24 2.390E+00 2.390E+00 2.390E+00 2.390E+00 2.390E+00 2.390E+00 2.770E+00 2.390E+00 P-32 0.OOOE+00 0.OOOE+00 0.OOOE+00 O.OOOE+00 0.000E+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 CR-51 9.310E-01 9.310E-01 9.310E-01 9.310E-01 9.310E-01 9.310E-01 1.100E+00 9.310E-01 MN-54 2.770E+02 2.770E+02 2.770E+02 2.770E+02 2.770E+-02 2.770E+02 3.250E+02 2.770E+02 MiN-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.OOOE+00 O.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOEtOO O.OOOE+00 0.OOOE+00 FE-59 5.450E+01 5.450E+01 5.450E+01 5.450E+01 5.450E+01 5.450E+01 6.410E+01 5.450E+01 CO-58 7.570E+01 7.570E+01 7.570E+01 7.570E+01 7.570E+01 7.570E+01 8.870E+01 7.570E+01 CO-60 4.300E+03 4.300E+03 4.300E+03 4.300E+03 4.300E+03 4.300E+/-03 5.050E+03 4.300E+03 NI-63 0.000E+00 0.OOOE+00 0.OOOE+00 O.OOOE+00 0.0O0E+00 0.000E+00 0.OOOE+00 0.OOOE+00 NI-65 5.930E-02 5.930E-02 5.930E-02 .5.930E-02 5.930E-02 5.930E-02 6.900E-02 5.930E-02 CU-64 1.210E-01 1.210E-01 1.210E-01 1.210E-01 1.210E-01 1.210E-01 1.370E-01 1.210E-01 ZN-65. 1.490E+02 1.490E+02 1.490E+02 1.490E+02 1.490E+02 1.490E+02 1.720E+02 1.490E+02 ZN-69 0.OOOE+00 0.OOOE+00 0.000E+00 0,OOOE+00 0.000E+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 BR-83 9.730E-04 9.730E-04 9.730E-04 9.730E-04 9.730E-04 *9.730E-04 1.410E-03 9.730E-04, BR-84 4.050E-02 4.050E-02 4.050E-02 4.050E-02 4.050E-02 4.050E-02 4.720E-02 4.050E-02 BR-85 0.000E+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 RB-86 1.800E+00 1.800E+00 1.800E+00 1.800E+00 1.800E+00 1.800E+00 .2.050E+00 1.800E+00 RB-88 6.610E-03 6.610E-03 6.610E-03 6.610E-03 6.610E-03 6.610E-03 7.550E-03 6.610E-03 RB-89 2.460E-02 2.460E-02 2.460E-02 2.460E-02 2.460E-02 2.460E-02 2.950E-02 2.460E-02 SR-89 4.320E-03 4.320E-03 4.320E-03 4.320E-03 4.320E-03 4.320E-03 5.020E-03 4.320E-03 SR-90 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.000E+00 SR-91 4.290E-01 4.290E-01 4.290E-01 4.290E-01 4.290E-01 4.290E-01 5.020E-01 4.290E-01 Appendix D Ai Teen Shoreline Sediment - Page 1 of 3

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX D Ai Teen Dose Factors for use in the Liquid Dose Calculations A gegroup:

I TEEN Pathway: Shoreline Sediment (SHDp) Units: mrem/hr / gCi/ml Nuclide. Bone . Liver Thyroid LuKidneng*, Gilli Skin TotalrBody

-SR-92 1.550E-01 1.550E-01 1.550E-01 1.550E-01 1.550E-01 1.550E-01 1.720E-01 1.550E-01 Y-90 8.970E-04 8.970E-04 8.970E-04 . 8.970E-04 8.970E-04 8.970E-04 1.060E-03 8.970E-04 Y-91 2.140E-01 2.140E-01 2.140E-01 2.140E-01 2.140E-01 2.140E-01 2.410E-01 2.140E-01 Y-91M 2.000E-02 2.OOOE-02 2.000E-02 2.000E-02 2.000E-02 2.000E-02 2.320E-02 2.OOOE-02 Y-92 3.600E-02 3.600E-02 3.600E-02 -3.600E-02 3.600E-02 3.600E-02 4.280E-02 3.600E-02 Y-93 3.660E-02 3.660E-02 3.660E-02 3.660E-02 3.660E-02 3.660E-02 5.010E-02 3.660E-02 ZR-95 4.890E+01 4 .890E+01 4.890E+01 4.890E+01 4.890E+01 4.890E+01 5.670E+01 4.890E+01 ZR-97 5.910E-01 5.910E-01 5.910E-01 5.910E-01 5.910E-01 5.910E-01 6.880E-01 5.910E-01 NB-95 2.730E+01 2.730E+01 2.730E+01 2.730E+01 2.730E+01 2.730E+01 3.210E+01 2.730E+01 MQ-99 7.980E-01 7.980E-01 7.980E-01 7.980E-01 7.980E-01 7.980E-01 9.240E-01 7.980E-01 T.C-99M 3.680E-02 3.680E-02 3.680E-02 3.680E-02 3.680E-02 3.680E-02 4.210E-02 3.680E-02 TC-101 4.070E-03 4.070E-03 4.070E-03 4.070E-03 4.070E-03 4.070E-03 4.520E-03 4.070E-03 RU-103 2.160E+01 2.160E+01 2.160E+01 2.160E+01 2.160E+01 2.160E+01 2.520E+01 2.160E+01 RU-105 1.270E&01 1.270E-01 1.270E-01 1.270E-01 1.270E-01 1.270E-01 1.440E-01 1.270E-01 RU-106 8.430E+01 8.430E+01 8.430E+01 8.430E+01 8.430E+01 8.430E+01 1.016E+02 8.430E+01 AG-1 OM 6.870E+02 6.870E+02 6.870E+02 6.870E+02 6.870E+02 6.870E+02 8.010E+02 6.870E+02 TE-125M 3.100E-01 3.100E-01 3.100E-01 3.100E-01 3.100E-01 .3.100E-01 4.250E-01 3.100E-01 TE-127 5.950E-04 5.950E-04 5.950E-04 5.950E-04 5.950E-04 5.950E-04 6.540E-04 5.950E-04 TE-127M 1.830E-02 1.830E-02 1.830E-02 1.830E-02 1.830E-02 1.830E-02 2.160E-02 1.830E-02 TE-129 5.240E-0-3 5.240E-03 5.240E-03 5.240E-03 5.240E-03 5.240E-03 6.200E-03 5.240E-03 TE-129M 3.950E+00 3.950E+00 3.950E+00 3.950E+00 3.950E+00 3.950E+00 4.620E+00 3.950E+00 TE-131 5.830E-03 5.830E-03 5.830E-03 5.830E-03 - 5.830E-03 5:830E-03 6.890E+00 5.830E-03 TE-131M 1.600E+00 1.600E+00 1.600E+00 1.600E+00 1.600E+00 1.600E+00 1.890E+00 1.600E+00 TE-132 8.460E-01 8.460E-01 8.460E-01 8.460E-01 8.460E-01 8.460E-01 9.950E-01 8.460E-01 1-130 1.100E+00 1.100E+00 -1.100E+00 1.100E+00 1.100E+00 1.100E+00 1.340E+00 1.100E+00 Appendix D Ai Teen Shoreline' Sediment - Page 2 of 3 0

Oconee Nuclear Station 0 9 January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX D Ai Teen Dose Factors for use in the Liuuid Dose Calculations Agegroup: TEEN Pathway: Shoreline, Sediment (SHDp) Units: mrem/hr / piCi/ml Nuclide Bone Liver Thyroid Kidney Lung .. Gilli Skin Total Body 1-131 3.440E+00 3.440E+00 3.440E+00 3.440E+00 3.440E+00 3.440E+00 4.170E+00 3.440E+00 1-132 2.490E-01 2.490E-01 2.490E-01 2.490E-01 2.490E-01 2.490E-01 2.930E-01 2.490E-01 1-133 4.900E-01 4.900E-O1 4.900E-01 4.900E-01 4.900E-01 4.900E-01 5.960E-01 4.900E-01 1-134 8.930E-02 8.930E-02 8.930E-02 8.930E-02 8.930E-02 8.930E-02 1.060E-01 8.930E-02 1-135 5.050E-01 5.050E-01 5.050E-01 5.050E-01 5.050E-01 5.050E-01 5.890E-01 5.050E-01 CS-134 1.370E+03 1.370E+03 1.370E+03 1.370E+03 1.370E+03 1.370E+03 1.600E+03 1.370E+03 CS-136 3.010E+01 3.010E+01 3.010E+01 3.010E+01 3.010E+01 3.010E+01 3.420E+01 3.010E+01 CS-137 2.050E+03 2.050E+03 2.050E+03 2.050E+03 2.050E+03 2.050E+03 2.400E+03 2.050E+03 CS-138 7.170E-02 7.170E-02 7.170E-02 7.170E-02 7.170E-02 7.170E-02 8.200E-02 7.170E-02

.BA-139 2.120E-02 2.120E-02 2.120E-02 2.120E-02 2.120E-02 2.120E-02 2.380E-02 2.120E-02 BA-140 4.100E+00 4.100E+00 4.100E+00 4.100E+00 4.100E+00 4.100E+00 4.690E+00 4.1OOE+00 BA-141 8.330E-03 8.330E-03 8.330E-03 8.330E-03 8.330E-03 8.330E-03 9.490E-03 8.330E-03 BA-142 8.970E-03 8.970E-03 8.970E-03 8.970E-03 8.970E-03 8.970E-03 1.020E-02 8.970E-03 LA-140 3.840E+00 3.840E+00 3.840E+00 3.840E+00 3.840E+00 3.840E+00 4.350E+00 3.840E+00 LA-142 1.520E-01 1.520E-01 1.520E-01 1.520E-01 1.520E-01 1.520E-01 1.820E-01 1.520E-01 CE-141 2.730E+00 2.730E+00 2.730E+00 2.730E+00 2.730E+00 2.730E+00 3.080E+00 2.730E+00 CE-143 4.620E-01 4.620E-01 4.620E-61 4.620E-01 4.620E-01 4.620E-01 5.250E-01 4.620E-01 CE-144 1.390E+01 1.390E+01 1.390E+01 -1.390E+01 1.390E+01 1.390E+01 1.610E+01 1.390E+01 PR-143 0.000E+00 O.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 PR-144 3.670E-04 3.670E-04 3.670E-04 3.670E-04 3.670E-04 3.670E-04 4.220E-04 3.670E-04 ND-147 1.680E+00 1.680E+00 1.680E+00 1.680E+00 1.680E+00 1.680E+00 2.010E+00 1.680E+00 W-187 4.700E-01 4.700E-01 4.700E-01 4.700E-01 4.700E-01 4.700E-01 5.460E-01 4.700E-01 NP-239 3.420E-0 1 3.420E-0 1 3.420E-0 1 3.420E-0 1 3.420E-0 1 3.420E-01 3.960E-01 3.420E-0 1 Appendix D Ai Teen Shoreline Sediment - Page 3 of 3

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX E A_Child Dose Factors for use in the Liquid Dose Calculations Agegroup: CHILD Pathway: Potable Water (PWtr) Units: mrem/hr / XCi/ml Nuclide Bone Liver Thyroid Kidney 2 Lung Gilli Skin Total Body H-3 0.OOOE+00 1.180E+01 1.180E+01 1.180E+01 1.180E+01 1.180E+01 0.OOOE+00 1.*180E+01 C- 14 7.030E+02 1.410E+02 1.410E+02 1.410E+02 1.410E+02 1.410E+02 0.000E+00 1.410E+02 NA-24 1.940E+02 1.940E+02 1.940E+02 1.940E+02 1.940E+02 1.940E+02 0.OOOE+00 1.940E+02 P-32 4.680E+04 2.190E+03 0.OOOE+00 0.OOOE+00 0.OOOE+00 1.290E+03 0.OOOE+00 1.800E+03 CR-51 0.OOOE+00 0.OOOE+00 2.840E-01 7.750E-02 5.180E-01 2.710E+01 0.OOOE+00 5.11OE-01 MN-54 0.OOOE+00 6.21 OE+02 0.OOOE+00 1.740E+02 0.OOOE+00 5.220E+02 0.0OOE+00 1.660E+02 MN-56 0.OOOE+00 7.700E-01 0.OOOE+00 9.320E-01 0.OOOE+00 1.120E+02 0.OOOE+00 1.740E-01 FE-55 6.680E+02 3.550E+02 0.OOOE+00 0.OOOE+00 2.010E+02 6.570E+01 0.OOOE+00 1.100E+02 FE-59 9.520E+02 1.540E+03 0.OOOE+00 0.OOOE+00 4.470E+02 1.600E+03 0.OOOE+00 7.670E+02 CO,58 0.OOOE+00 1.040E+02 0.OOE+00 0.OOOE+00 0.OOOE+00 6.070E+02 0.OOOE+00 3.190E+02 CO-60 0.OOOE+00 3.080E+02 0.OOOE+00 0.OOOE+00 0.OOOE+00 1.700E+03 0.OOOE+00 9.070E+02 NI-63 3.130E+04 1.670E+03 0.OOOE+00 0.OOOE+00 0.000E+00 1.130E+02 0.000E+00 1.060E+03 NI-65 4.760E+00 4.480E-01 0.OOOE+00 0.OOOE+00 0.OOOE+00 5.490E+01 0.OOOE+00 2.610E-01 CU-64 0.OOOE+00 7.390E+00 0.OOOE+00 1.780E+01 0.OOOE+00 3.470E+02 0.000E+00 4.460E+00 ZN-65 7.950E+02 2.120E+03 0.OOOE+00 1.340E+03 0.OOOE+00 3.720E+02 0.OOOE+00 1.320E+03 ZN-69 3.190E-04 4.610E-04 0.OOOE+00. 2.800E-04 0.OOOE+00 2.900E-02 0.OOOE+00 4.260E-05 BR-83 0.OOOE+00 0.OOOE+O0 0.OOOE+00- 0.OOOE+00 0.OOOE+00 0.000E+00 0.OOOE+00 3.060E-01 BR-84 0.000E+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 1.780E-06 BR-85 0.000E+00- 0.O00E+/ .O.OOE+00 0.OOOE+00 0.0OOE+00 0.OOOE+00 0.OOOE+00 1.300E-76 RB-86 0.OOOE+00 3.820E+03 0.OOOE+00 0.OOOE+00 0.OOOE+00 2.460E+02 0.OOOE+00 2.350E+03 RB-88 0.OOOE+00 7.360E-12 0.000E+00 0.OOOE+00 0.OOOE+00 3.610E-13 0.OOOE+00 5.11OE-12 RB-89 0.OOOE+00 6.300E-14 0.OOOE+00 0.OOOE+00 0.OOOE+00 5.490E-16 0.000E+00 5.600E-14 SR-89 7.620E+04 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 2.950E+03 0.000E+00 2.180E+03 SR-90 9.880E+05 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 1.330E+04 0.OOOE+00 2.510E+05 SR-91 5.810E+02 0.OOOE+00 0.OOOE+00 O.OOOE+00 0.OOOE+00 1.280E+03 0.OOOE+00 2.190E+01 Appendix E Ai Child Water - Page 1of 3 0

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX E Ai Child Dose Factors for use in the Liquid Dose Calculations Agegroup: CHILD Pathway: Potable Water (PWtr) Units: mrem/hr / .tCi/ml Nuclide Bone Liver., Thyroid Kidney. Lung Gilli Skin- TotalBody SR-92 2.430E+01 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 4.610E+02 0.OOOE+00 9.760E-01 Y-90 2.100E+00 0.OOOE+00 0.OOOE+00 0.000E+00 0.OOOE+00 5.980E+03 0.OOOE+00 5.620E-02 Y-91 3.480E+01 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 4.640E+03 0.OOOE+00 9.310E-01 Y-91M 9.860E-07 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.000E+00 1.930E-03 0.000E+00 3.590E-08 Y-92 2.OOOE-02 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 5.770E+02 0.OOOE+00 5.710E-04 Y-93 2.900E-01 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 4.330E+03 0.000E+00 7.970E-03 ZR-95 6.710E+00 1.470E+00 0.OOOE+00 2.110E+00 0.000E+00 1.540E+03 0.OOOE+00 1.3 1OE+00 ZR-97 2.480E-01 3.590E-02 0.OOOE+00 5.150E-02 0.OOOE+00 5.440E+03 0.OOOE+00 2.120E-02 NB-95 1.300E+00 5.040E-01 0.OOOE+00 4.740E-01 0.OOOE+00 9.330E+02 0.OOOE+00 3.600E-01 MO-99 0.OOOE+00 6.820E+02 0.OOOE+00 1.460E+03 0.OOOE+00 5.640E+02 0.000E+00 1.690E+0'T TC-99M 1.350E-02 2.640E-02 0.OOOE+00 3.840E-01 1.340E-02 1.500E+01 0.OOOE+00 4.380E-01 TC-101 3.330E-17 3.480E-17 0.OOOE+00 5.940E- 16 1.840E-17 1.110E-16 0.OOOE+00 4.410E- 16 RU-103 4.210E+01 0.000E+00 0.OOOE+00 1.060E+02 0.OOOE+00 1.090E+03 0.OOOE+00 1.620E+01 RU-105 5.750E-01 0.OOOE+00. 0.OOOE+00 5.060E+00 0.OOOE+00 3.750E+02 0.OOOE+00 2.090E-01 RU-106 6.800E+02 O.OOOE+00 0.OOOE+00 9.180E+02 0.OOOE+00 1.060E+04 O.OOE+÷00 8.480E+01 AG-110M 3.130E+01 2.11OE+01 0.OOOE+00 3.940E+01 0.OOOE+00 2.510E+03 0.OOOE+00 1.690E+01 TE-125M 6.590E+02 1.790E+02 1.850E+02 0.OOOE+00 0.OOOE+00 6.360E+02 0.OOOE+00 8.780E+01 TE-127 1.130E+01 3.050E+00 7.820E+00 3.210E+01 0.OOOE+00 4.410E+02 0.OOOE+00 2.420E+00 TE-127M 1.670E+03 4.510E+02 4.OOOE+02 4.780E+03 0.OOOE+00 1.360E+03 0.OOOE+00 1.990E+02 TE-129 5.730E-03 1.600E-03 4.090E-03 1.680E-02 0.OOOE+00 3.570E-01 0.OOOE+00 1.360E-03 TE-129M 2.800E+03 7.830E+02 9.030E+02 8.230E+03 0.OOOE+00 3.420E+03 0.OOOE+00 4.350E+02 TE- 131 1.040E-08 3.160E-09 7.930E-09 3.140E-08 0.OOOE+00 5.450E-08 0.OOOE+00 3.090E-09 TE-131M 3.170E+02 1.1 OOE+02 2.260E+02 1.060E+03 0.OOOE+00 4.450E+03 0.OOOE+00 1.170E+02 TE-132 5.280E+02 2.340E+02 3.400E+02 2.170E+03 0.OOOE+00 2.350E+03 0.OOOE+00 2.820E+02 1-130 8.650E+01 1.750E+02 1.930E+04 2.610E+02 0.OOOE+00 8.180E+01 0.OOOE+00 9.010E+01 Appendix E Ai Child Water - Page 2 of 3

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX E Ai Child Dose Factorsfor use in the Liquid Dose Calculations

.Agegroup: CHILD Pathway: Potable Water(PWtr) Units: mrem/hr / j.Ci/ml Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body 1-131 9.580E+02 9.630E+02 3.190E+05 1.580E+03 0.000E+00 8.580E+01 0.OOOE+00 5.470E+02 1-132 1.250E+00 2.300E+00 1.070E+02 3.520E+00 0.000E+00 2.710E+00 0.OOOE+00 1.060E+00 1-133 2.310E+02 2.850E+02 5.300E+04 4.750E+02 0.000E+00 1.150E+02 0.000E+00 1.080E+02 1-134 1.820E-03 3.370E-03 7.760E-02 5.160E-03 0.OOOE+00 2.240E-03 0.000E+00 1.550E-03 1-135 2.890E+01 5.210E+01 4.610E+03 7.990E+011 0.000E+00 3.970E+01 0.000E+00 2.460E+01 CS-134 1.360E+04 2.230E+04 0.OOOE+00 6.920E+03 2.480E+03 1.200E+02 0.OOOE+00 4.710E+03 CS-136 1.330E+03 3.660E+03 0.000E+00 1.950E+03 2.910E+02 1.290E+02 0.OOOE+00 2.370E+03 CS-137 1.900E+04 1.820E+04 0.000E+00 5.930E+03 2.130E+03, 1.140E+02 0.000E+00 2.690E+03 CS-138 2.440E-06 3.390E-06 0.000E+00 2.380E-06 2.570E-07 1.560E-06 0.OOOE+00 2.150E-06 BA-139 5.940E-02 3.170E-05 0.000E+00 2.770E-05 1.860E-05 3.430E+00 0.000E+00 1.720E-03 BA-140 4.700E+03 4.120E+00 0.OOOE+00. 1.340E+00 2.460E+00 2.380E+03 0.OOOE+00 2.740E+02 BA-141 1.620E-1 1 9.050E-15 0.OOOE+00 7.830E-15 5.310E-14 9.210E-12 0.000E+00 5.260E-13 BA-142 1.800E-20 1.300E-23 0.OOOE+00 '1.050E-23 7.630E-24 2.350E-22 0.OOOE+00 1.01 OE-21 LA- 140 4.780E-01 1.670E-01 0.OOOE+00 0.OOOE+00 0.OOOE+00 4.650E+03 0.OOOE+00 5.630E-02 LA-142 1.640E-04 5.210E-05 0.OOOE+00 0.OOOE+00 0.OOOE+00 1.030E+01 0.OOOE+00 1.630E-05 CE- 141 2.280E+00 1.140E+00 0.OOOE+00 4.990E-01 0.OOOE+00 1.420E+03 0.OOOE+00 1.690E-01 CE-143 3.160E-01 1.710E+02 0.OOOE+00 7.180E-02 0.000E+00 2.510E+03 0.000E+00 2.480E-02 CE-144 1.210E+02 3.790E+01 0.OOOE+00 2.1OOE+01 0.OOOE+00 9.870E+03 0.000E+00 6.450E+00 PR-143 2.230E+00 6.690E-01 0.OOOE+00 3.620E-01 0.OOOE+00 2.400E+03 0.000E+00 1.! 10QE-01 PR-144 2.200E- 15 6.800E-16 0.OOOE+00 3.600E-16 0.OOOE+00 1.460E-12 0.000E+00 1.11OE- 16 ND-147 1.570E+00 1.270E+00 0.OOOE+00 6.990E-01 0.OOOE+00 2.020E+03 0.OOOE+00 9.860E-02 W-187 1.760E+01 1.040E+01 0.OOOE+00 O.OOOE+00 0.000E+00 1.460E+03 0.OOOE+00 4.680E+00 NP-239 2.630E-01 1.890E-02 0.000E+00 5.470E-02 0.OOOE+00 1.400E+03 0.OOOE+00 1.330E-02 Appendix E Ai Child Water - Page 3 of 3

.9

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX E A. Child Dose Factors for use in the Liouid Dose Calculations Agegroup: CHILD Pathway: Fresh Water Fish - Sport (FFSP) Units: mrem/hr / *iCi/ml Nuclide Bone *Liver Thyroid Kidney. Lung. Gilli Skin Total Body H-3 0.OOOE+00 1.440E-01 1.440E-01 1.440E-01 1.440E-01 1.440E-01 0.OOOE+00 1.440E-01 C-14 4.380E+04 8.760E+03 8.760E+03 8.760E+03 8.760E+03 8.760E+03 0.OOOE+00 8.760E+03 NA-24 1.51 OE+02 1.51 OE+02 1.51 OE+02 1.510E+02 1.51 OE+02 1.510E+02 0.000E+00 1.51 OE+02 P-32 1.850E+06 8.680E+04 0.OOOE+00 0.OOOE+00 0.OOOE+00 5.130E+04 0.OOOE+00 7.150E+04 CR-51 0.OOOE+00 0.OOOE+00 7.580E-01 2.070E-01 1.380E+00 7.240E+01 0.OOOE+00 1.370E+00 MN-54 0.OOOE+00 3.360E+03 0.OOOE+00 9.420E+02 0.OOOE+00 2.820E+03 0.000E+00 8.950E+02 MN-56 0.OOOE+00 1.650E-01 0.OOOE+00 2.OOOE-01 0.000E+00 2.400E+01 0.OOOE+00 3.730E-02 FE-55 9.040E+02 4.790E+02 0.OOOE+00 0.OOOE+00 2.710E+02 8.880E+01 0.OOOE+00 1.490E+02 FE-59 1.280E+03 2.070E+03 0.OOOE+00 0.OOOE+00 5.990E+02 2.150E+03 0.OOOE+00 1.030E+03 CO-58 0.OOOE+00 7.010E+01 0.OOOE+00 0.OOOE+00 0.OOOE+00 4.090E+02 0.OOOE+00 2.150E+02 CO-60 0.OOOE+00 2.080E+02 0.OOOE+00 0.OOOE+00 0.OOOE+00 1.150E+03 0.OOOE+00 6.130E+02 NI-63 4.230E+04 2.270E+03 0.OOOE+00 0.OOOE+00 0.OOOE+00 1.530E+02 0;OOOE+00 1.440E+03 NI-65 2.370E-01 2.230E-02 0.OOOE+00 0.OOOE+00 0.OOOE+00 2-740E+00 0.OOOE+00 1.300E-02 CU-64 0.OOOE+00 2.590E+00 0.OOOE+00 6.260E+00 0.OOOE+00 1.220E+02 0.000E+00 1.570E+00 ZN-65 2.150E+04 5.730E+04 0.OOOE+00 3.610E+04 0.OOOE+00 1.010E+04 0.OOOE+00 3.560E+04 ZN-69 1.080E-06 1.560E-06 0.OOOE+00 9.470E-07 0.OOOE+00 9.840E-05 0.OOOE+00 1.440E-07 BR-83 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 5.340E-02 BR-84 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.0001+00 0.OOOE+00 1.570E-12 BR-85 O.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 -O.OOOE+00 0.OOOE+00 RB-86 0.OOOE+00 1.020E+05 0.OOOE+00 0.OOOE+00 0.OOOE+00 6.530E+03 0.OOOE+00 6.250E+04 RB-88 0.OOOE+00 1.330E-22 0.OOOE+00 0.OOOE+00 0.OOOE+00 6.5 1OE-24 0.OOOE+00 9.220E-23 RB-89 0.OOOE+00 1.580E-26 0.OOOE+00 0.OOOE+00 0.OOOE+00 1.370E-28 0.OOOE+00 1.400E-26 SR-89 3.070E+04 0.OOOE+00 0.OOOE+00 0.060E+00 0.OOOE'+00 1.190E+03 0.OOOE+00 8.780E+02 SR-90 4.01OE+05 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 5.400E+03 0.OOOE+00 1.020E+05 SR-91 9.800E+0 1 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.000E+00 2.160E+02 0.OOOE+00 3.700E+00 Appendix E Ai Child Fish - Page 1 of 3 ,

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX E A. Child Dose Factors for use in the Liuuid Dose Calculations Agegroup: CHILD Pathway: Fresh Water Fish - Sport (FFSP) Units:ý mrem/hr / pCi/ml Nuclide Bone Liver Thyroid Kidn.ey Lung Gilli, Skin Total Body SR-92 4.580E-01 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 8.670E+00 0.OOOE+00 1.840E-02 Y-90 6.240E-01 0.000E+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 1.780E+03 0.OOOE+00 1.670E-02 Y-91 1.170E+01 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 1.560E+03 0.OOOE+00 3.130E-01 Y-91M 1.480E-11 0.OOOE+00 0.OOOE+00 O.OOOE+00 0.OOOE+00 2.900E-08 0.OOOE+00 5.390E-13 Y-92 6.440E-04 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 1.860E+01 0.000E+00 1.840E-05 Y-93 4.300E-02 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 6.420E+02 0.000E+00 1.180E-03 ZR-95 2.980E-01 6.550E-02 0.OOOE+00 9.370E-02 0.OOOE+00 6.830E+01 0.000E+00 5.830E-02 ZR-97 6.780E-03 9.790E-04 0.OOOE+00 1.410E-03 0.OOOE+00 1.480E+02 0.000E+00 5.780E-04 NB-95 5.210E+02 2.030E+02 0.OOOE+00 1.900E+02 0.OOOE+00 3.750E+05 O.000E+00 1.450E+02 MO-99 0.OOOE+00 8.130E+01 0.OOOE+00 1.740E+02 0.OOOE+00 6.720E+01 0.OOOE+00 2.010E+01 TC-99M 6.860E-04 1.350E-03 0.OOOE+00 1.950E-02 6.830E-04 7.650E-01 0.OOOE+00 2.230E-02 TC-101 3.610E-33 3.780E-33 0.000E+00 6.440E-32 2.OOOE-33 1.200E-32 0.OOOE+00 4.790E-32 RU-103 5.650E+00 0.OOOE+00 0.OOOE+00 1.420E+01 0.OOOE+00 1.460E+02 0.OOOE+00 2.170E+00 RU-105 1.190E-02 0.OOOE+00 0.OOOE+00 1.050E-01 0.OOOE+00 7.790E+00 0.OOOE+00 4.330E-03 RU-106 9.190E+01 0.OOOE+00 0.OOOE+00 1.240E+02 0.OOOE+00 1.430E+03 0.OOOE+00 1.150E+01 AG- 110M 9.720E-01 6.570E-01 0.OOOE+00 1.220E+00 0.OOOE+00 7.810E+01 0.OOOE+00 5.250E-01 TE-125M 3.540E+03 9.610E+02 9.950E+02 0.OOOE+00 0.OOOE+00 3.420E+03 0.OOOE+00 4.730E+02 TE-127 2.520E+01' 6.800E+00 1.750E+01 7.170E+01 0.OOOE+00 9.850E+02 0.OOOE+00 5.410E+00 TE-127M - 9.040E+03 2.430E+03 2.160E+03 2.580E+04 0.OOOE+/-00 7.320E+03 0.000E+00 1.070E+03 TE- 129 2.280E-05 6.370E-06 1.630E-05 6.680E-05 0.OOOE+00 1.420E-03 0.OOOE+00 5.420E-06 TE-129M 1.500E+04 4.190E+03 4.840E+03 4.410E+04 0.000E+00 1.830E+04 0.000E+00 2.330E+03 TE-131 1.210E-16 3.680E-17 9.220E-17 3.650E-16 O.OOOE+00 6.330E-16 0.OOOE+00 3.590E-17 TE-131M 1.300E+03 4.500E+02 9.250E+02 4.350E+03 0.OOOE+00 1.820E+04 0.OOOE+00 4.790E+02 TE-132 2.570E+03 1.140E+03 1.650E+03 1.050E+04 0.OOOE+00 1.140E+04 0.OOOE+00 1.370E+03 1-130 8.950E+00 1.810E+01 1.990E+03 2.700E+01 0.OOOE+00 8.460E+00 0.OOOE+00 9.320E+00 Appendix E Ai Child Fish - Page 2 of 3

Oconee Nuclear Station 0

January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX E Ai Child Dose Factors for use- in the Liquid Dose Calculations Agegroup: CHILD -Pathway: Fresh Water Fish - Sport (FFSP) Units: mrem/hr / jiCi/ml Nuclide Bone Liver Thyroid .Kidney Lung., Gilli Skin Total Body 1-131 1.860E+02 1.870E+02 6.190E+04 3.070E+02 0.OOOE+00 1.670E+01 0.OOOE+00 1.060E+02 1-132 6.830E-03 1.250E-02 5.820E-01 1.920E-02 0.OOOE+00 1.480E-02 0.000E+00 5.770E-03 1-133 3.140E+01 3.880E+01 7.210E+03 6.470E+01 0.OOOE+00 1.560E+01 0:OOOE+00 1.470E+01 1-134 2.750E-08 5.100E-08 1.170E-06 7.800E-08 0.OOOE+00 3.380E-08 0.OOOE+00 2.350E-08 1-135 1.670E+00 3.0101E+00 2.660E+02 4.61 OE+00 0.000E+00 2.290E+00 O.OOOE+00 1.420E+00 CS-134 3.680E+05 6.040E+05 0.OOOE+00 1.870E+05 6.710E+04 3.250E+03 0.OOOE+00 1.270E+05 CS-136 3.510E+04 9.640E+04 0.OOOE+00 5.130E+04 7.660E+03 3.390E+03 O.OOOE+00 6.240E+04 CS-137 5.140E+05 4.920E+05 0.OOOE+00 1.600E+05 5.770E+04 3.080E+03 0.OOOE+00 7.270E+04 CS-138 1.210E-1 1 1.690E- 1 0.OOOE+00 1.190E- 1I 1.280E-12 7.770E-12 O.OOOE+00 1.070E- 1I BA-139 7.930E-06 4.230E-09 0.OOOE+00 3.700E-09 2.490E-09 4.580E-04 0.000E+00 2.300E-07 BA-140 2.480E+02 2.170E-01 0.OOOE+00 7.060E-02 1.290E-01 1.250E+02 0.OOOE+00 1.450E+01 BA-141 1.21 OE-24 6.800E-28 0.OOOE+00 5.880E-28 3.990E-27 6.920E-25 0.OOOE+00 3.950E-26 BA-142 3.460E-42 2.490E-45 0.OOOE+00 2.020E-45 1.470E-45 4.51OE-44 0.OOOE+00 1.930E-43 LA-140 1.310E-01 4.590E-02 0.OOOE+00 O.000E+00 0.OOOE+00 1.280E+03 0.OOOE+00 1.550E-02 LA-142 .2.970E-07 9.470E-08 0.OOOE+00 0.OOOE+00 0.OOOE+00 1.880E-02 0.OOOE+00 2.960E-08 CE-141 3.060E-02 1.520E-02 0.OOOE+00 6.680E-03 0.OOOE+00 1.900E+01 0.OOOE+00 2.260E-03 CE-143 3.320E-03 1.800E+00 0.000E+00 7.550E-04 0.OOOE+00 2.640E+01 0.OOOE+00 2.610E-04 CE-144 1.630E+00 5.120E-01 0.000E+00 2.830E-01 0.OOOE+00 1.330E+02 0.OOOE+00 8.710E-02 PR- 143 7.340E-01 2.200E-01 0.OOOE+00 1.190E-01 0.OOOE+00 7.920E+02 0.OOOE+00 3.640E-02 PR- 144 2.180E-28 6.750E-29 0.000E+00 3.570E-29 0.000E+00 1.450E-25 0.OOOE+00 1.100E-29 ND-147 5.150E-01 4.170E-01 0.OOOE+00 2.290E-01 0.OOOE+00 6.610E+02 0.OOOE+00 3.230E-02 W-187 2.010E+02 1.190E+02 0.OOOE+00 O.OOOE+00 0.000E+00 1.680E+/-04 0.OOOE+00 5.350E+01 NP-239 3.080E-02 2.210E-03 0.OOOE+00 6.390E-03 0.OOOE+00 1.630E+02 0.OOOE+00 1.550E-03 Appendix E Ai Child Fish . Page 3 of 3

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX E A_ Child Dose Factors for use in the Liquid Dose Calculations Agegroup: CHILD Pathway:., Shoreline Sediment (SHDp) Units: mrem/hr / iCi/ml Nuclide Bone Liver Thyroid. Kidney Lung Gilli Skin.. Total Body H-3 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 C-14 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.000E+00 0.OOOE+00 0.OOOE+00 0.000E+00 0.OOOE+00 NA-24 4.990E-01 4.990E-01 4.990E-01 4.990E-01 4.990E-01 4.990E-01 5.780E-01 4.990E-01

P-32 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 CR-51 1.950E-01 1.950E-01 1.950E-01 1.950E-01 1.950E-01 1.950E-01 2.300E-01 1.950E-01 MN-54 5.790E+01 5.790E+01 5.790E+01 5.790E+01 5.790E+01 5.790E+01 6.790E+01 5.790E+01 MN-56 3.770E-02 3.770E-02 3.770E-02 3.770E-02 3.770E-02 3.770E-02 4.450E-02 3.770E-02 FE-55 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 FE-59 1.140E+01 1.140E+01 1.140E+01 1.140E+01 1.140E+01 1.140E+01 1.340E+01 1.140E+01 CO-58 1.580E+01 1.580Et01 1.580E+01 1.580E+01 1.580E+01 1.580E+01 1.850E+01 1.580E+01 CO-60 8.980E+02 8.980E+02 8.980E+02 8.980E+02 8.980E+02 8.980E+02 1.060E+03 8.980E+02 NI-63 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 NI-65 1.240E-02 1.240E-02 1.240E-02 1.240E-02 1.240E-02 1.240E-02 1.440E-02 1.240E-02
  • CU-64 2.530E-02 2.530E-02 2.530E-02 2.530E-02 2.530E-02 2.530E-02 2.870E-02 2.530E-02 ZN-65 3.120E+01 3.120E+01 3.120E+01 3.120E+01 3.1l20E+01 3.120E+01 3.590E+01 3.120E+01 ZN-69 0.OOOE+00. 0.OOOE+00 0.OOOE+00 0.000E+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 BR-83 2.030E-04 2.030E-04 2.030E-04 2.030E-04 2.030E-04 2.030E-04 2.960E-04 2.030E-04 BR-84 8.460E-03 8.460E-03 8.460E-03 8.460E-03 8.460E-03 8.460E-03 9.870E-03 8.460E-03 BR-85 0.OOOE+00, 0.000E+00_ 0.00OE+00- O.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 RB-86 3.750E-01 3.750E-01 3.750E-01 3.750E-01 3.750E-01 3.750E-01 4.290E-01 3.750E-01 RB-88 1.380E-03 1.380E-03 1.380E-03 1.380E-03 1.380E-03 1.380E-03 1.580E-03 1.380E-03 RB-89 5.130E-03 5.130E-03 5.130E-03 5. 130E-03 5.130E-03 5.130E-03 6.160E-03 5.130E-03 SR-89 9.030E-04 9.030E-04 9.030E-04 9.030E-04 9.030E-04 9.030E-04 1.050E-03 9.030E-04 SR-90 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 SR-91 8.970E-02 8.970E-02 8.970E-02 8.970E-02 8.970E-02 8.970E-02 1.050E-01 8.970E-02 Appendix E Ai Child Shoreline Sediment - Page 1 of 3

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX E Ai Child Dose Factors for use in the Liquid Dose Calculations Agegroup: CHILD Pathway:. Shoreline Sediment (SHDp) Units: mrem/hr / pCi/ml Nuclide Bone'. Ler Thyroid Kidney Lung Gilli Skin. Total Body SR-92 3.240E-02 3.240E-02 3.240E-02 3.240E-02 3.240E-02 3.240E-02 3.600E-02 3.240E-02 Y-90 1.880E-04 1.880E-04 1.880E-04 1.880E-04 1.880E-04 1.880E-04 2.220E-04 1.880E-04 Y-91 4.480E-02 4.480E-02 4.480E-02 4.480E-02 4.480E-02 4.480E-02 5.040E-02 4.480E-02 Y-91M 4.190E-03 4.190E-03 4.190E-03 4.190E-03 4.190E-03 4.190E-03 4.850E-03 4.190E-03 Y-92 '7.530E-03 7.530E-03 7.530E-03 7.530E-03 7.530E-03 7.530E-03 8.940E-03 7.530E-03 Y-93 7.660E-03 7.660E-03 7.660E-03 7.660E-03 7.660E-03 7.660E-03 1.050E-02 7,660E-03 ZR-95 1.020E+01 1.020E+01 1.020E+0 1 1.020E+01 t1.020E+01 1.020E+01 1.190E+0 1 1.020E+0 1 ZR-97 1.240E-01 1.240E-01 1.240E-01 1.240E-01 1.240E-01 1.240E-01 1.440E-01 1.240E-01 NB-95 5.710E+00 5.710E+00 5.710E+00 5.710E+00 5.710E+00 5.710E+00 6.710E+00 5.710E+00 MO-99 1.670E-01 1.670E-01 1.670E-01 1.670E-01 1.670E-01 1.670E-01 1.930E-01 1.670E-01' TC-99M 7.680E-03 7.680E-03 7.680E-03 7.680E-03 7.680E-03 7.680E-03 8.810E-03 7.680E-03 TC-101 8.500E-04 8.500E-04 .8.500E-04 8.500E-04 8.500E-04 8.500E-04 9.440E-04 8.50OE-04 RU- 103 4.520E+00 4.520E+00 4.520E+00 4.520E+00 4.520E+00 4.520E+00 5.270E+00 4.520E+00 RU-105 2.660E-02 2.660E-02 2.660E-02 2.660E-02 2.660E-02 2.660E-02 3.010E-02 2.660E-02 RU-106 1.760E+01 1.760E+01 i.760E+01 1.760E+01 .1.760E+01 1.760E+01 2.11OE+01 1.760E+01 AG-1 10M 1.440E+02 1.440E+02 1.440E+02 1.440E+02 1.440E+02 1.440E+02 1.670E+02 1.440E+02

.TE-125M 6.480E-02 6.480E-02 6.480E-02 6.480E-02 6.480E-02 6.480E-02 8.880E-02 6.480E-02 TE- 127 1.240E-04 1.240E-04 1..240E-04 1.240E-04 1.240E-04 1.240E-04 1.370E-04 1.240E-04 TE-127M 3.830E-03 3.830E-03 3.830E-03 3.830E-03 3.830E-03 3.830E-03 4.520E-03 3,830E-03 TE-129 1.100E-03 1.100E-03 1.100E-03 1.100E-03 1.100E-03 1.100E-03 1.300E-03 1.100E-03 TE-129M 8.260E-01 8.260E-01 8.260E-01 8.260E-01 8.260E-01 8.260E-01 9.650E-01 8.260E-01 TE- 131 1.220E-03 1.220E-03 1.220E-03 1.220E-03 1.220E-03 1.220E-03 1.440E+00 1.220E-03 TE-131M 3.350E-01 3.350E-01 3.350E-01 3.350E-01 3.350E-01 3.350E-01 3.950E-01 3.350E-01 TE-132 1.770E-01 1.770E-01 1.770E-01 1.770E-01 1.770E-01 1.770E-01 2.080E-01 1.770E-01 1-130 2.300E-01 2.300E-01 2.300E-01 2.300E-01 2.300E-01 2.300E-01 2.790E-01 2.300E-01 Appendix E Ai Child Shoreline Sediment - Page 2 of 3

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX E Ai Child Dose Factors for use in the Liquid Dose Calculations Agegroup: CHILD Pathway: Shoreline Sediment (SHDp) Units: mrem/hr / XCi/ml

<Nucide BLiver i Kidney Lung Gilli .,Skin Total Bod 1-131 7.180E-0 1 7.180E-01 7.180E-01 7.180E-01 7.180E-01 7.180E-01 8.720E-01 7.180E-01 1-132 5.200E-02 5.200E-02 5.200E-02 5.200E-02 5.200E-02 5.200E-02 6.120E-02 5.200E-02 1-133. 1.020E-01 1.020E-01 1.020E-01 1.020E-01 1.020E-01 1.020E-01 1.240E-01 1.020E-01 1-134 1.870E-02 1.870E-02 1.870E-02 1.870E-02 1.870E-02 1.870E-02 2.210E-02 1.870E-02 1-135 1.050E-01 1.050E-01 1.050E-01 1.050E-01 1.050E-01 1.050E-01 1.230E-01 1.050E-01 CS-134 2.860E+02 2.860E+02 2.860E+02 2.860E+02 2.860E+02 2.860E+02 3.340E+02 2.860E+02 CS-136 ý6.300E+00 6.300E+00 6.300E+00 6.300E+00 6.300E+00 6.360E+00 7.140E+00 6.300E+00 CS-137 4.290E+02 4.290E+02 4.290E+02 4.290E+02 4.290E+02 4.290E+02 5.010E+02 4.290E+02 CS-138 1.500E-02 1.500E-02 1.500E-02 - 1.500E-02 1.500E-02 41.500E-02 1.710E-02 1.500E-02 BA-139 4.420E-03 4.420E-03 4.420E-03 4.420E-03 4.420E-03 4.420E-03 4.970E-03 4.420E-03 BA-140 8.570E-01 8.570E-01 8.570E-01 8.570E-01 8.570E-01 8.570E-01 9.800E-01 8.570E-01 BA-141 1.740E-03 1.740E-03 1.740E-03 1.740E-03 1.740E-03 1.740E-03 1.980E-03 1.740E-03 BA-142 1.870E-03 1.870E-03 1.870E-03 1.870E-03 1.870E-03 1.870E-03 2.130E-03 1.870E-03 LA-140 8.020E-01 8.020E-01 8.020E-01 8.020E-01 8.020E-01 8.020E-01 9.090E-01 8.020E-01 LA-142 3.170E-02 3.170E-02 3.170E-02 3.170E-02 3.170E-02 3.170E-02 3.810E-02 3.170E-02 CE-141 5.700E-01-, 5.700E-01 5.700E-01 5.700E-01 5.700E-01 5.700E-01 6.430E-01 5.700E-01 CE-143 9.650E-02 9.650E-02, 9.650E-02 9.650E&02 9.650E-02 9.650E-02 1.100E-01 9.650E-02 CE- 144 2.900E+00 2.900E+00 2.900E+00 2.900E+00 2.900E+00 2.900E+00 3.360E+00 2.900E+00

ýPR-143 . .0.OOOE+00t - 0.0..E.00 0.000E+/-00

_0E.. 0E+O0 . 0.-OOOE+00 . .OOOE+00 . .OOOE+00 0.OOOE+00 PR-144 7.660E-05 7.660E-05 7.660E-05 7.660E-05 7.660E-05 7.660E-05 8.810E-05 7.660E-05 ND-147- 3.500E-01 3.500E-01 3.500E-01 3.500E-01 3.500E-01 3.500E-01 4.200E-01 3.500E-01 W-187 9.820E-02 9.820E-02 9.820E-02 9.820E-02 9.820E-02 9.820E-02 1.140E-01 9.820E-02 NP-239 7.140E-02 7.140E-02 7.140E-02 7.140E-02 7.140E-02 7.140E-02 8.270E-02 7.140E-02 Appendix E Ai Child Shoreline Sediment - Page 3 of 3 0

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX F A.i Infant Dose Factors for use in the Liquid Dose Calculations Agegroup: INFANT pathway: Potable Water (PWtr) Units: . mrem/hr / jxCi/ml

Nulide . Bone
  • Liver- Thyroid Kidney Lung Gilli.:,- S"m. i Total Body H-3 0.OOOE+00 1.160E+01 1.160E+01 1.160E+01 1.160E+01 1.160E+01 0.OOOE+00 1.160E+01 C-14 8.920E+02 1.900E+02 1.900E+02 1.900E+02 1.900E+02 1.900E+02 0.OOOE+00 1.900E+02 NA-24 2.190E+02 2.190E+02 2.190E+02 2.190E+02 2.190E+02 2.190E+02 O.OOOE+00 2.190E+02 P-32 6.240E+04 3.670E+03 0.OOOE+00 0.OOOE+00 0.OOOE+00 8.450E+02 0.OOOE+00 2.420E+03 CR-51 0.OOOE+00 0.OOOE+00 3.420E-01 7.470E-02 6.650E-01 1.530E+01 0.OOOE+00 5.240E-01 MN-54 0.OOOE+00 7.480E+02 0.OOOE+00 1.660Et02 0.OOOE+00 2.750E+02 0.OOOE+00 1.690E+02 MN-56 0.OOOE+00 1.220E+00 0.000E+00 1.050E+00 0.OOOE+00 1.11OE+02 0.OOOE+00 2.100E-01 FE-55 5.230E+02 3.380E+02 0.OOOE+00 0.OOOE+00 1.650E+02 4.290E+01 0.OOOE+00 9.030E+01 FE-59 1.150E+03 2.010E+03 0.OOOE+00 0.OOOE+00 5.940E+02 9.590E+02 0.000E+00 7.910E+02 CO-58 0.OOOE+00 1.350E+02 0.OOOE+00 0.OOOE+00 0.OOOE+00 3.360E+02 0.000E+00 3.360E+02 CO-60 0.OOOE+00 4.060E+02 0.000E+00 0.OOOE+00 0.OOOE+00 9.670E+02 0.OOOE+00 9.590E+02 NI-63 2.390E+04 1.470E+03 0.OOOE+00 0.OOOE+00 0.OOOE+00 7.340E+01 0.000E+00 8.280E+02 NI-65 6.520E+00 7.380E-01 0.OOOE+00 0.OOOE+00 0.OOOE+00 5.620E+01 0.OOOE+00 3.360E-01 CU-64 0.OOOE+00 1.190E+01 0.OOOE+00 2.010E+01 0.OOOE+00 2.440E+02 0.OOOE+00 5.500E+00 ZN-65 6.910E+02 2.370E+03 0.OOOE+00 1.150E+03 0.OOOE+00 2.OOOE+03 0.OOOE+00 1.090E+03 ZN-69 4.390E-04 7.91 OE-04 6.000E+00 3.290E-04 0.OOOE+00 6.450E-02 0.OOOE+00 5.890E-05 BR-83 0.OOOE+00 0.OOOE+00 6.000E+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 4.200E-01 BR-84 0.OOOE+00 O.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 2.220E-06 BR-85 0.OOOE+00 0.OOOE+00 0.OOOE+00 O.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 1.800E-76 RB-86 0.OOOE+00 6.280E+03 0.OOOE+00 0.OOOE+00 0.OOOE+00 1.610E+02 0.OOOE+00 3.100E+03 RB-88 0.OOOE+00 1.250E- 11 0.OOOE+00 O.OOOE+00 0.OOOE+00 1.220E- 11 0.000E+00 6.840E-12 RB-89 0.OOOE+00 9.960E-14 0.OOOE+00 0.OOOE+00 0.OOOE+00 3.390E-14 0.OOOE+00 6.860E-14 SR-89 9.380E+04 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 1.930E+03 0.OOOE+00 2.690E+03 SR-90 6.960E+05 0.OOOE+00 0.OOOE+00 O.OOOE+00. 0.OOOE+00 8.690E+03 0.OOOE+00 1.770E+05 SR-91 7.830E+02 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 9.270E+02 0.OOOE+00 2.830E+01 Appendix F Ai Infant Water - Page 1 of 3

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX F Ai Infant Dose Factors for use in the Liquid Dose Calculations Agegroup: INFANT Pathway: Potable Water (PWtr) Units: mrem/hr / ptCi/ml Nuclide . Bone Liver Thyroil Kidne l ung kGilii TotalBody Sin SR-92 3.350E+01 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 3.610E+02 0.OOOE+00 1.240E+00 Y-90 2.870E+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 3.970E+03 0.OOOE+00 7.700E-02 Y-91 4.230E+01 0.000E+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 3.030E+03 0.OOOE+00 1.130E+00 Y-91M 1.350E-06 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 4.510E-03 0.OOOE+00 4.610E-08 Y-92 2.740E-02 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 5.240E+02 0.OOOE+00 7.710E-04 Y-93 4.010E-01 0.OOOE+00 0.OOOE+00 0.000E+00 0.OOOE+00 3.170E+03 0.000E+00 1.090E-02 ZR-95 7.710E+00 1.880E+00 0.OOOE+00 2.020E+00 0.OOOE+00 9.350E+02 0.OOOE+00 1.330E+00 ZR-97 3.400E-0 1 5.840E-02 0.OOOE+00 5.890E-02 0.OOOE+00 3.720E+03 0.OOOE+00 2.670E-02 NB-95 1.560E+00 6.440E-01 0.OOOE+00 4.620E-01 0.OOOE+00 5.440E+02 0.OOOE+00 3.720E-01 MO-99 0.000E+00 1.130E+03 0.OOOE+00 1.680E+03 0.OOOE+00 3.710E+02 0.OOOE+00 2.200E+02 TC-99M 1.810E-02 3.740E-02 0.000E+00 4.020E-01 1.950E-02 1.090E+01 0.000E+00 4.820E-01 TC-101 4.570E-17 5.750E-17 0.000E+00 6.840E- 16 3.140E-17 9.780E-15 0.OOOE+00 5.690E-16 RU-103 5.520E+01 0.000E+00 0.OOOE+00 1.150E+02 0.OOOE+00 6.710E+02 0.OOOE+00 1.850E+01 RU-105 7.850E-01 0.000E+00 0.OOOE+00 5.770E+00 0.OOOE+00 3.120E+02 0.OOOE+00 2.640E-01 RU-106 9.060E+02 0.000E+00 0.OOOE+00 1.070E+03 0.OOOE+00 6.880E+03 0.OOOE+00 1.130E+02 AG- 110M 3.740E+01 2.730E+01 0.OOOE+00 3.910E+01 0.OOOE+00 1.420E+03 0.OOOE+00 1.810E+01 TE-125M 8.710E+02 2.910E+02 2.930E+02 0.OOOE+00 0.OOOE+00 4.150E+02 0.OOOE+00 1.180E+02 TE-127 1.550E+01 5.200E+00 1.260E+01 3.790E+01 0.OOOE+00 3.260E+02 0.OOOE+00 3.340E+00 TE-127M 2.190E+03 7.280E+02 6.340E+02 5.400E+03 0.OOOE+00 8.850E+02 0.OOOE+00 2.660E+02 TE-129 7.860E-03 2.710E-03 6.590E-03 1.960E-02 - 0.OOOE+00 6.280E-01o 0.000E+00 1.840E-03 TE-129M 3.720E+03 1.280E+03 1.430E+03 9.310E+03 0.OOOE+00 2.220E+03 0.OOOE+00 5.730E+02 TE-131 1.420E-08 5.250E-09 1.270E-08 3.640E-08 0.OOOE+00 5.750E-07 0.000E+00 3.990E-09 TE-131M 4.330E+02 1.740E+02 3.540E+02 1.200E+03 0.OOOE+00 2.940E+03 0.OOOE+00 1.440E+02 TE- 132 7.030E+02 3.480E+02 5.140E+02 2.180E+03 0.OOOE+00 1.290E+03 0.OOOE+00 3.250E+02 1-130 1.150E+02 2.530E+02 2.840E+04 2.780E+02 0.OOOE+00 5.430E+01 0.OOOE+00 1.020E+02 Appendix F Ai Infant Water - Page 2 of 3

Oconee Nuclear Station 0

January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX F Ai Infant Dose Factors for use in the Liquid Dose Calculations Agegroup: INFANT Pathway:. Potable Water (PWtr) Units: mrem/hr / pCi/ml Nuclide , Bone Liver Thyroid Kidney Lung iGi!i Skin Total Body 1-131 1.290E+03 1.520E+03 5.010E+05 1.780E+03 0.OOOE+00 5.440E+01 0.OOOE+00 6.700E+02 1-132 1.680E+00 3.410E+00 1.600E+02 3.800E+00 0.OOOE+00 2.760E+00 0.OOOE+00 1.210E+00 1-133 3.150E+02 4.590E+02 8.350E+04 5.400E+02 0.OOOE+00 7.770E+01 0.OOOE+00 1.340E+02 1-134 2.440E-03 4.990E-03 1.160E-01 5.580E-03 0.OOOE+-00 5.160E-03 0.OOOE+00 1.780E-03 1-135 3.900E+01 7.750E+01 6.950E+03 8.640E+01 0.OOOE+00 2.800E+01 0.OOOE+00 2.830E+01 CS-134 1.420E+04 2.640E+04 0.OOOE+00 6.810E+03 2.790E+03 7.180E+01 0.OOOE+00 2.670E+03 CS-136 1.680E+03 4.950E+03 0.OOOE+00 1.970E+03 4.030E+02 7.510E+01 0.OOOE+00 1.850E+03 CS-137 1.960E+04 2.300E+04 0.OOOE+00 6.170E+03 2.500E+03 7.190E+01 0.OOOE+00 1.630E+03 CS-138 3.330E-06 5.410E-06 0.OOOE+00 2.700E-06 4.210E-07 8.650E-06 0.OOOE+00 2.620E-06 BA- 139 8.180E-02 5.420E-05 0.OOOE+00 3.260E-05 3.290E-05 5.180E+00 0.OOOE+00 2.370E-03.

BA-140 6.260E+03 6.260E+00 0.OOOE+00 1.490E+00 3.840E+00 1.540E+03 0.OOOE+00 3.230E+02 BA-141 2.220E-11 1.520E-14 0.000E+00 9.140E-15 9.250E-15 2.710E-10 0.OOOE+00 7.00OE-13 BA-142 2.460E-20 2.040E-23 0.OOOE+00 1.180E-23 1.240E-23 1.010E-19 0.OOOE+00 1.210E-21 LA-140 6.460E-01 2.550E-01 0.OOOE+00 0.OOOE+00 0.OOOE+00 2.990E+03 0.OOOE+00 6.550E-02 LA-142 2.220E-04 8.160E-05 0.OOOE+00 0*000E+00 0.OOOE+00 1.390E+01 0.OOOE+00 1.950E-05 CE- 141 2.930E+00 1.790E+00 0.OOOE+00 5.510E-01 0.OOOE+00 9.230E+02 0.OOOE+00 2.1OOE-01 CE-143 4.330E-01 2.870E+02 0.OOOE+00 8.360E-02 0.OOOE+00 1.670E+03 0.OOOE+00 3.270E-02 CE-144 1.120E+02 4.580E+01 0.000E+00 1.850E+01 0.OOOE+00 6.430E+03 0.OOOE+00 6.270E+00 PR-143 2.980E+00 1.11OE+00 0.OOOE+00 4.140E-01 0.OOOE+00 1.570E+03 0.OOOE+00 1.480E-01 PR-144 3.020E-15 1.170E- 15 0.000E+00 4.240E-16 0.OOOE+00 5.440E- 11 0.000E+00 1.520E-16 ND- 147 2.020E+00 2.070E+00 0.OOOE+00 7.980E-01 0.OOOE+00 1.310E+03 0.000E+00 1.270E-0 1 W-187 2.400E+01 1.670E+01 0.OOOE+00 0.OOOE+00 0.OOOE+00 9.790E+02 0.OOOE+00 5.760E+00 NP-239 3.600E-01 3.220E-02 0.OOOE+00 6.430E-02 0.OOOE+00 9.320E+02 0.OOOE+00 1.820E-02 Appendix F Ai Infant Water - Page 3 of 3

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX G Ri Adult Dose Factors for use in the Gaseous Dose Calculations Agegroup: ADULT Pathway:, Grs/Cow/Milk (CMILK) Units:: m2 mrem/yr / p.Ci/sec;

_____ mrem/yr / Ci/m 3 (H-3)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body H-3 0.OOOE+00 7.630E+02 7.630E+02 7.630E+02 7.630E+02 7.630E+02 0.OOOE+00 7.630E+02 C-14 2.630E+08 5.270E+07 5.270E+07 5.270E+07 5.270E+07 5.270E+07 0.OOOE+00 5.270E+07 NA-24 2.440E+06 2.440E+06 2.440E+06 2.440E+06 2.440E+06 2.440E+06 0.OOOE+00 2.440E+06 P-32 1.710E+10 1.060E+09 0.OOOE+00 0.OOOE+00 0.OOOE+00 1.920E+09 0.OOOE+00 6.610E+08 CR-51 0.OOOE+00 0.OOOE+00 1.710E+04 6.300E+03 3.790E+04 7.190E+06 0.OOOE+00 2.860E+04 MN-54 0.OOOE+00 8.41 OE+06 0.OOOE+00 2.500E+06 0.OOOE+00 2.580E+07 0.OOOE+00 1.610E+06 MN-56 0.OOOE+00 4.090E-03 0.OOOE+00 5.190E-03 0.OOOE+00 1.310E-01 0.OOOE+00 7.260E-04 FE-55 2.510E+07 1.740E+07 0.OOOE+00 0.OOOE+00 9.680E+06 .9.950E+06 0.OOOE+00 4.050E+06 FE-59 2.970E+07 6.980E+07 0.OOOE+00 0.OOOE+00 1.950E+07 2.330E+08 0.OOOE+00 2.680E+07 CO-58 0.OOOE+00 4.710E+06 0.OOOE+00 0.OOOE+00 0.OOOE+00 9.550E+07 0.OOOE+00 1.060E+07 CO-60 0.OOOE+00 1.640E+07 0.OOOE+00 0.OOOE+00 0.OOOE+00 3.080E+08 0.OOOE+00 3.620E+07 NI-63 6.730E+09 4.660E+08 0.OOOE+00 0.OOOE+00 0.OOOE+00 9.730E+07 0.OOOE+00 2.260E+08 NI-65 3.700E-01 4.810E-02 0.OOOE+00 0.OOOE+00 0.OOOE+00 1.220E+00 0.OOOE+00 2.190E-02 CU-64 0.OOOE+00 2.380E+04 0.OOOE+00 6.01OE+04 0.OOOE+00 2.030E+06 0.OOOE+00 1.120E+04 ZN-65 1.370E+09 4.370E+09 0.OOOE+00 2.920E+09 0.OOOE+00 2.750E+09 0.000E+00 1.970E+09 ZN-69 2.090E-12 4.OOOE-12 0.OOOE+00 2.600E-12 0.OOOE+00 6.010E-13 0.OOOE+00 2.780E-13 BR-83 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 1.400E-01 0.OOOE+00 9.720E-02 BR-84 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 1.260E-28 0.OOOE+00 1.610E-23 BR-85 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 RB:86 . .0.000E+00 2.590E+09 0.OOOE+00 0.OOOE+00 0_000E+00 5.120E+-08 0.OOOE+00 1.210E+09 RB-88 0.OOOE+00 2.140E-45 0.OOOE+00 0.OOOE+00 O.OOOE+00 2.960E-56 0.OOOE+00 1.140E-45 RB-89 0.OOOE+00 4.330E-53 0.OOOE+00 0.OOOE+00 0.OOOE+00 2.510E-66 0.000E+00 3.040E-53 SR-89 1.450E+09 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 2.330E+08 0.OOOE+00 4.160E+07 SR-90 4.680E+10 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.000E+00 1.350E+09 0.OOOE+00 1.150E+10 SR-91 2.890E+04 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 1.380E+05 0.OOOE+00 1.170E+03 Appendix G Ri Adult Cow Milk - Page I of 3

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX G R1 Adult Dose Factors for use in the Gaseous Dose Calculations Agegroup: ADULT Pathway:, Grs/Cow/Milk (CMILK)l Units:, m2 .mrem/yr / ýCi/sec; mrem/yr I iCi/m 3 (H-3) ir Thyoi Kidney Lung Gilli Skin, Total Body SR-92 4.880E-01 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 9.680E+00 0.OOOE+00 2.11OE-02 Y-90 7.080E+01 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 7.5 10E+05 0.OOOE+00 1.900E+00 Y-91 8.590E+03 0.OOOE+00 0.OOOE+00 0.OOOE+00 O.OOOE+00 4.730E+06 O.OOOE+00 2.300E+02 Y-91M 5.980E-20 0.006E+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 1.760E-19 0.OOOE+00 2.320E-21 Y-92 5.580E-05 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.0100E00 9.770E-01 0.OOOE+00 1.630E-06 Y-93 2.230E-01 0.000E+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 7.090E+03 0.OOOE+00 6.170E-03 ZR-95 9.430E+02 3.030E+02 0.OOOE+00 4.750E+02 0.000E+00 9.590E+05 0.OOOE+00 2.050E+02 ZR-97 4.330E-01 8.740E-02 0.OOOE+00 1.320E-01. 0.OOOE+00 2.710E+04 0.OOOE+00 4.000E-02 NB-95 8.260E+04. 4.590E+04 O.OOOE+00 4.540E+04 0.OOOE+00 2.790E+08 0.OOOE+00 2.470E+04 MO-99 0.OOOE+00 2.480E+07 0.OOOE+00 5.610E+07 0.OOOE+00 5.740E+07 0.OOOE+00 4.710E+06 TC-99M 3.320E+00 9.380E+00 0.OOOE+00 1.420E+02 4.600E+00 5.550E+03 0.OOOE+00 1.200E+02 TC-101 2.590E-60 3.740E-60 0.OOOE+00 6.730E-59 1.910E-60 1.120E-71 0.OOOE+00 3.670E-59 RU-103 1.020E+03 0.OOOE+00 0.OOOE+00 3.890E+03 0.000E+00 1.190E+05 0.OOOE+00 4.390E+02 RU-105 8.570E-04 0.OOOE+00 0.000E+00 1.110E-02 0.OOOE+00 5.240E-01 0.OOOE+00 3.380E-04 RU- 106 2.040E+04 0.OOOE+00 0.OOOE+00 3.940E+04 0.OOOE+00 1.320E+06 0.OOOE+00 2.580E+03 AG-110M 5.820E+07 5.390E+07 0.000E+00 1.060E+08 0.OOOE+00 .2.200E+10 0.OOOE+00 3.200E+07 TE-125M 1.630E+07 5.900E+06 4.900E+06 6.630E+07 0.OOOE+00 6.500E+07 0.OOOE+00 2.180E+06 0.OOOE+00 5.150E+04 0.000E+00 1.410E+02 2.340E+02 4.840E+02 2.660E+03 TE-127 6.530E+02 TE-127M 4.580E+07 1.640E+07 1.170E+07 1.860E+08 0.OOOE+00 1.540E+08 0.OOOE+00 5.580E+06 TE-129 2.830E-10 1.060E-10 2.170E-10, 1.190E-09 0.OOOE+00 2.130E-10 0.OOOE+00 6.880E-11 TE-129M 6.020E+07 2.250E+07 2.070E+07 2.5 1OE+08 0.OOOE+00 3.030E+08 0.OOOE+00 9.530E+06 TE-131 3.600E-33 1.500E-33 2.960E-33 1.580E-32 0.OOOE+00 5.100E-34 0.OOOE+00 1.140E-33 TE-131M 3.610E+05 1.770E+05 2.800E+05 1.790E+06" 0.OOOE+00 1.750E+07 0.OOOE+00 1.470E+05 TE- 132 2.400E+06 1.550E+06 1.720E+06 1.500E+07 0.OOOE+00 7.350E+07 0.OOOE+00 1.460E+06 1-130 4.200E+05 1.240E+06 1.050E+08 1.930E+06 0.OOOE+00 1.070E+06 0.OOOE+00 4.890E+05 Appendix G Ri Adult Cow Milk - Page 2 of 3

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX G Ri Adult Dose Factors for use in the Gaseous Dose Calculations Agegroup:. ADULT Pathway: Grs/Cow/Milk (CMILK) Uni.:tUits: m~ mrem/yr /

2Ci/sec;

______-__:__ .'mrem/yr /gCi/m 3 (H-3)

Nuclide Bone Liver Thyroid ' Kidney Lung, Gillii .. ,Skin TotaIBody 1-131 2.960E+08 4.230E+08 1.390E+11 7.260E+08 0.OOOE+00 1.120E+08 0.OOOE+00 2.430E+08 1-132 1.640E-01 4.390E-01 1.540E+01 7.OOOE-01 0.OOOE+00 8.250E-02 0.OOOE+00 1.540E-01 1-133 3.870E+06 6.730E+06 9.890E+08 1.170E+07 0.OOOE+00 6.050E+06 0.OOOE+00 2.050E1+06 1-134 2.020E-12 5.480E-12 9.490E- 11 8.710E- 12 0.000E+00 4.770E-15 0.000E+00 1.960E-12 1-135 1.280E+04 3.360E+04 2.220E+06 5.390E+04 0.OOOE+00 3.800E+04 0.OOOE+00 1.240E+04 CS-134 5.650E+09 1.350E+10 0.OOOE+00 4.350E+09 1.450E+09 2.350E+08 0.000E+00 1.100E+10 CS-136 2.630E+08 1.040E+09 0.OOOE+00 5.780E+08 7.930E+07 1.180E+08 0.OOOE+00 7.480E+08 CS-137 7.380E+09 1.010E+10 0.OOOE+00 3.430E+09 1.140E+09 1.950E+08 0.OOOE+00 6.610E+09 CS-138 9.050E-24 1.790E-23 0.OOOE+00 1.310E-23 1.300E-24 7.620E-29 0.OOOE+00 8.850E-24 BA-139 4.420E-08 3.150E-1i 0.OOOE+00 2.940E-11 1.790E-11 7.830E-08 0.OOOE+00 1.290E-09 BA-140 2.690E+07 3.380E+04 0.OOOE+00 1.150E+04 1.930E+04 5.530E+07 0.OOOE+00 1.760E+06 BA-141 4.090E-46 3.090E-49 0.OOOE+00 2.880E-49 1.760E-49 1.930E-55 0.OOOE+00 1.380E-47 BA- 142 2.640E-80 2.720E-83 0.000E+00 2.300E-83 1.540E-83 3.720E-98 0.OOOE+00 1.660E-81 LA-140 4.510E+00 2.270E+00 0.OOOE+00 0.OOOE-+/-00 0.000E+00 1.670E+05 0.OOOE+00 6.010E-01 LA-142 1.860E- 11 8.460E-12 0.000E4O0 0.OOOE+00 0.OOOE+00 6.170E-08 0.OOOE+00 2.11OE- 12 CE-141 4.840E+03 3.280E+03 0.OOOE+00 1.520E+03 0.OOOE+00 1.250E+07 0.OOOE+00 3.720E+02 CE-143 4.160E+01 3.070E+04 0.OOOE+00 1.350E+01 0.000E+00 1.150E+06 0.OOOE+00 3.400E+00 CE-144 3.580E+05 1.500E+05 0.OOOE+00 8.870E+04 0.OOOE+00 1.210E+08 0.600E+00 1.920E+04 PR-143 1.580E+02 6.330E+01 0.OOOE+00 3.660E+01 0.OOOE+00 6.920E+05 0.000E+00 7.830E+00

. .870E-54 5PR-844 . 2.440E-54 .. 0.O00EE0- O-380E-54-, 0.OOOE+00 . 8450E '0:000E+/-00V 2:990E&55 ND-147 9.420E+01 1.090E+02 0.000E+00 6.360E+01 0.OOOE+00 5.220E+05 0.OOOE+00 6.510E+00 W-187 6.510E+03 5.450E+03 0.OOOE+00 0.OOOE+00 0.OOOE+00 1.780E+06 0.OOOE+00 1.900E+03 NP-239 3.670E+00 3.610E-01 0.OOOE+00 1.130E+00 O.OOOE+00 7.410E+04 0.000E+00 1.990E-01 Appendix G Ri Adult Cow Milk - Page 3 of 3

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX G R1 Adult Dose Factors for use in the Gaseous Dose Calculations Age-group: ADULT PathWay: Grs/Goat/Milk (GMILK) Units:. m2.mrem/yr / p.Cilsec;

_______________________________________________ ________ _________ mrem/yr /pCi/m' (H-3)

Nuclide. ..'Boie ~ Liver Thyroid Kidney Lung Gilli Skin.,: Total Body H-3 0.OOOE+00 1.56013+03 1.560E+03 1.560E+03 1.560E+03 1.560E+03 0.OOOE+00 1.560E+03 C-14 - 2.630E+08 5.270E+07 5.270E+07 5.270E+/-07 5.270E+07 5.270E+07 0.OOOE+ý00 5.270E+07 NA-24 2.930E+05 2.430E+05 2.930E+05 2.930E+05 2.930E+05 2.930E+i05 0.OOOE+00 2.930E+05 P-32 2.050E+10 1.280E+09 0.OOOE+00 0.OOOE+00 0.OOOE+00 2.3 10E+09 0.OOOE+00 7.930E+/-08 CR-51 0.OOOE+00 0.OOOE+00 2.050E+03 7.550E+/-02 4.550E+03 8.620E+05 0.OOOE+00 3.430E+03 MIN-54 0.OOOE+00 1.010E+06 0.OOOE+00 3.OOOE+05 0.OOOE+00 3.090E+06 0.OOOE+00 1.930E+05 MTN-56 0.OOOE+00 4.91013-04 0.OOOE+100 6.230E-04 0.OOOE+00 l.570&-02 0.OOOE+00 8.710h-05 FE-55 3.260E+05 2.2670E'+05 - .OOOE+00 0.OOOE+00 1.260E+05 1.290E+05 0.000E+00. 5.260E+04 FE-59 3.860E+05 9.070E+05 0.OOOE+00 0.OOOE+/-00 2.540E+05 3.020E+06 0.000,E+00 31.480E+05 CO-58 0.OOOE+00 5.660E+05 0.OOOE+-00 0.00O13+00 .0.000E+00 1.150E+07 0.00O13+00 1.270E+06 CO-60 0.OOOE+00 1.970E+06 0.OOOE+00 0.OOOE+00 O.OOOE+00 3.700E+07 0.00013+00 4.340E+06 NI-63 8.070E+08 5.600E+07 0.00013+00' 0.OOOE+00 0.OOOEtOO 1.170E+07 0.OOOE+00 2.710E+/-07 N1-;65 4.440E-02 5.770E-03 0.OOOE+00 0.OOOE+00 0.OOOE+00 1.460E-01I 0.OOOE+00 2..630E-03 CU-64 0.00013+00 2.660E+03 0.OOOE+/-00 6.700E+03 O.OOOE+00 2.260E+05 0.OOOE+/-00 1.250E+03 ZN-65 1.650E+08 5.24013+08 0.OOOE+00 3.500E+08 0.00013+00 3.300E+08 0.00O13+00 2.370E#-08 ZN-69 2.510E-13 4.800E-13 0.OOOE+00 3.120E- 13 0;OOOE+00 7.210E-14 0.OOOE+/-00 3.340E-14 BR-83 0.00013+00 0.OOOE+00 0.00013+00 0,000E+00 0.OOOE+00 1.680E-02 0.OOOE+00 1.170E-02 BR-84 0.OOOE+00 0.000E+00 0.OOOE+00 0.000E+00 0.OOOE+00 1.520E-29 0.OOOE+/-00 1.930E-24.

BR-85 0.OOOE+00 - .OOOE+00 0.OOOE-'00 0.OOOE+00 0.000E+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 RB-86 0.OOOE+00 3.11 OE+08 0.OOOE+00 0.OOOE+00 0.OOOE+0O 6.140E+07 0.OOOE+00 1.450E+08 RB-88 0.006E+00 2.570E-46 0.OOOE+00 0.OOOE+00 0.OOOE+00 3.550E-57 0.OOOE+/-00 1.360E-46 RB-89 0.OOOE+00 5.190&-54 0.OOOE+00 0.OOOE+00 0.OOOE+00 3.020E-67 0.OOOE+00 3.650E-54 SR-89 3.050E+09 0.OOOE0 6.0E+00 O.OOOE+60 O.OOOE+O.000+0 4.890E+08 0.OOOE+00 8.750E+07 SR-90 9.830E+10 0.OOOE+00 0.OOOE+00 0.00013+00 0.OOOE+00 2.840E+09 0.000E+00 2.410E+10 SR-91 6.07013+04 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 2.890E+I05 0.000E+00 2.450E+03 Appendix G Ri Adult Goat Milk - Page 1of 3

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 .

APPENDIX G R; Adult Dose Factors for use in the.Gaseous Dose Calculations Agegroup: ADULT Pathway: Grs/Goat/Milk (GMILK) Units: m 22.Ci/sec;

.mrem/yr /

_ _ _ _ _ _ _ _ _ _ _ _ _ _ __  : mrem/yr / jtCi/m3 (H-3)

Nuclide Bone. Liver, 'Thyroid Kidney Lung Gilli Skin 'Total Bodyýý SR-92 1.030E+00 0.OOOE+00 0.000E+00- 0.000E+00 0.OOOE+00 2.030E+01 0.OOOE+00 4.440E-02 Y-90 8.500E+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 9.010E+04 0.OOOE+00 2.280E-01 Y-91 .1.030E+03 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 5.670E+05 0.OOOE+00 2.760E+01 Y-91M 7.170E-21 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 2.11 OE-20 0.OOOE+00 2.780E-22 Y-92 6.690E-06 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 1.170E-01 0.OOOE+00 1.960E-07 Y-93 2.680E-02 0.000E+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 8.500E+02 0.OOOE+00 7.400E-04 ZR-95 1.130E+02 3.630E+01 0.OOOE+00 5.700E+01 0.000E+00 - 1.150E+05 0.000E+00 2.460E+/-01 ZR-97 5.200E-02 1.050E-02 0.OOOE+00 1.580E-02 0.OOOE+00 3.250E+03 0.OOOE+00 4.800E-03 NB-95 9.910E+03 -5.5i OE+03 0.OOOE+00 5.450E+03 0.OOOE+00 3.340E+07 0.000E+00 2.960E+03 MO-99 0.OOOE+00 2.970E+06 0.OOOE+00 6.730E+06 0.OOOE+00 6.890E+06 0.OOOE+00 5.660E+05 TC-99M 3.980E-01 1.130E+00 0.OOOE+00 1.710E+01 5.520E-01 6.660E+02 0.OOOE+00 1.430E+01 TC-101 3.11OE-61 4.490E-61 0.OOOE+06 8.080E-60 2.290E-61 1.350E-72 0.000E+00 4.400E-60 -

RU- 103 1.220E+02 0.005+00E 0.OOOE+00 4.660E+02 0.OOOE+00 1.430E+04 0.OOOE+00 5.260E+01 RU- 105 1.030E-04 0.OOOE+00 0.OOOE+00 1.330E-03 0.OOOE+00 6.290E-02 0.OOOE+00 4.060E-05 RU-106 2.450E+03 0.OOOE+00 0.OOOE+00 4.730E+03 0.OOOE+00 1.580E+05 0.OOOE+00- 3.100E+02 AG-I OM 6.990E+06 6.460E+06 0.000E+00 1.270E+07 0.OOOE+00 2.640E+09 0.OOOE+00 3.840E+06 TE-125M 1.950E+06 7.080E+05 5.880E+05 7.950E+06 0.OOOE+00 7.800E+06 O.000E+00 2.620E+05 TE-127 7.830E+01 2.810E+01 5.800E+01 3.190E+02 0.OOOE+00 6.180E+03 0.000E+00 1.700E+01 TE-127M 5.490E+'06 1.960E+06 1.400E+06 2.230E+07 0.OOOE+00 1.840E+07 0.OOOE+00 6.690E+05

-TE-129 - 3.390E-11--. .270E-11l-- 2.600E-1-1 .. .1.430E - -0.000+E00 - *2.560E-11 0.OOOE+00 8.260E412 TE-129M 7.220E+06 2.690E+06 2.480E+06 3.020E+07 0.OOOE+00 3.640E+07 0.OOOE+00 1.140E+06 TE-131 4.320E-34 1.810E-34 3.550E-34 1.890E-33 0.OOOE+00 6.120E-35 0.OOOE+00 1.360E-34 TE-131M 4.330E+04 2.120E+04 3.360E+04 2.150E+05 0.OOOE+00 2.100E+06 0.OOOE+00 1.770E+04 TE-132 2.880E+05 1.860E+05 2.060E+05 1.800E+06 0.000E+00 8.820E+06 0.OOOE+00 1.750E+05 1-130 5.040E+05 1.490E+06 1.260E+08 2.320E+06 0,OOOE+00 1.280E+/-06 0.OOOE+00 5.870E+05 Appendix G Ri Adult Goat Milk - Page 2 of 3 9.

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX G Ri Adult Dose Factors for use in the Gaseous Dose Calculations Agegroup:. ADULT Pathway: Grs/Goat/Milk (GMILK) Units: m 2 mrem/yr / J4Ci/sec;

___-_______ ___________ :___________ __________ _______ .mrem/yr / J4Ci/m 3 (H-3)

Nuc!!ide Bone Liver Thyroid Kidney Lung Gi  :[ Skin TotalBody 1-131 3.550E+08 5.080E+08 1.670E+i 1 8.710E+08 0.000E+00 1.340E+08 0.OOOE+00 2.910E+08 1-132 1.970E-01 5.270E-01 1.840E+01 8.400E-01 0.OOOE00 9.900E-02 0.OOOE+00 1.840E-01 1-133 4.640E+06 8.080E+06 1.190E+09 1.410E+07 .0.000E+00 7.260E+06 0.OOOE+00 2.460E+06 1-134 2.420E-12 6.570E-12 1.140E-10 1.050E-11 0.OOOE+00 5.730E-15 0.OOOE+00 2.350E-12 1-135 1.540E+04 4.030E+04 2.660E+06 6.470E+04 0.OOOE+00 4.560E+04 0.OOOE+00 1.490E+04 CS-134 1.700E+10 4.040E+10 0.OOOE+00 1.310Et10 4.340E+09 7.060E+08 0.OOOE+00 3.300E+10 CS-136 7.900E+08 3.120E+09 0.000E+00 1.730E-+09 2.380E+08 3.540E+08 0.OOOE+00 2.240E+09 CS-137 2.210E+10 3.030E+10 0.OOOE+00 1.030E+10 3.420E+09 5.860E+08 0.OOOE+00 1.980E+10 CS-138 2.710E-23 5.360E-23 0.OOOE+00 3.940E-23 3.890E-24 2.290E-28 O.OOOE+00 2.650E-23 BA-139 5.300E-09 3.780E-12 .0.000E+00 3.530E-12 2.140E-12 9.400E-09 0.OOOE+00 1.550E-10 BA-140 3.230E+06 4.050E+03 0.OOOE+00 i.380E+03 2.320E+03 6.640E+06 0.OOOE+00 2.11OE+05 BA-141 4.910E-47 3.710E-50 0.OOOE+00 3.450E-50 2.11OE-50 2.310E-56 0.00OE+00 1.660E-48 BA-142 3.170E-81 3.260E-84 0.OOOE+00 2.750E-84 1.850E-84 0.OOOE+00 0.OOOE+00 2.000E-82 LA-140 5.410E-01 2.730E-01 0.000E+00 O.OOOE+00 0.OOOE+00 2.OOOE+04 0.OOOE+00 7.210E-02 LA-142 2.230E-12 1.010E-12 0.OOOE+00 0.OOOE+00 0.OOOE+00 7.410E-09 0.OOOEt00 2.530E-13 CE-141 5.810E+02 3.930E+02 - 0.OOOE+00 1.830E+02 0.OOOE+00 1.500E+06 0.OOOE+00 4.460E+01 CE-143 4.990E+00 3.690E+03 0.OOOE+00 1.620E+00 0.000E+00 1.380E+05 O.OOOE+00 4.080E-01 CE-144 4.290E+04 1.790E+04 0.OOOE+00 1.060E+04 0.OOOE+00 1.450E+07 O.OOOE+00 2.300E+03 PR-143 1.890E+01 7.600E+00 0.OOOE+00 4.390E+00 0.OOOE+00 8.300E+04 0.OOOE+00 9.390E-01 PR-144 7.050E-55 2.930E-55 0.OOOE+00- 1.650E-55 0.OOOE+00 1.010E-61 0.OOOE+00 3.580E-56 ND-147 1.130E+01 1.3i0E+01 O.OOOE+00 7.630E+00 0.000E+00 6.270E+04 0.000E+00 7.810E-01 W-187 7.820E+02 6.530E+02 0.006E+00 O.OOOE+00 0.OOOE+00 2.140E+05 0.OOOE+00 2.280E+02 NP-239 4.410E-01 4.330E-02 0.OOOE+00 1.350E-01 0.OOOE+00 8.890E+03 0.OOOE+00 2.390E-02 Appendix G Ri Adult Goat Milk - Page 3 of 3-

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX G Ri Adult Dose Factors for use in the Gaseous Dose Calculations Agegroup: ADULT Pathway: Grs/Cow/Meat (CMEAT) Units: m 2.mrem/yr / Ci/sec;

_________ ___________________ mrem/yr/ JCi/m3 (H1-3)

Nuclide Bone LiVer Thyrid .Kidney Lung Gilli, Skin Total Body, H-3 0.OOOE+00 3.250E+02 3.250E+02 3.250E+02 3.250E+02 3.250E+02 0.OOOE+00 3.250E+02 C-14 2.410E+08 4.830E+07 4.830E+07 4.830E+07 4.830E+07 4.830E+07 0.OOOE+00 4.830E+07 NA-24 1.360E-03 1.360E-03 1.360E-03 1.360E-03 1.360E-03 1.360E-03 0.OOOE+00 1.360E-03 P-32 4.660E+09 2.900E+08 0.000E+00 0.OOOE+00 0.000E+00 5.240E+08 0.OOOE+00 1.800E+08 CR-51 0.000E+00 0.OOOE+00. 4.210E+03 1.550E+03 9.350E+03 -. 770E+06 0.OOOE+00 7.050E+03 MN-54 0.OOOE+00 9.180E+06 0.OOOE+00 2.730E+06 0.000E+00 2.810E+07 0.OOOE+00 1.750E+06 MN-56 0.OOOE+00 1.320E-53 0.OOOE+00 1.680E-53 0.000E+00 4.220E-52 0.OOOE+00 2.350E-54 FE-55 2.930E+08 2.030E+08 0.OOOE+00 0.OOOE+00 1.130E+08 1.160E+08 0.OOOE+00 4.720E+07 FE-59 2.660E+08 6.240E+08 0.OOOE+00 0.060E+00 1.740E+08 2.080E+09 0.OOOE+00 2.390E+08 CO-58 0.OOOE+00

  • 1.820E+07 0.OOOE+00 0.OOOE+00 0.OOOE+00 3.690E+08 0.000E+00 4.090E+07 CO-60 0.OOOE+00 7.520E+07 0.OOOE+00 0.060E+00 0.OOOE+00 1.410E+09 0.000E+00 1.660E+08 NI-63 1.890E+10 1.310E+09 0.OOOE+00 0.OOOE+00 0.OOOE+00 2.730E+08 0.OOOE+00 6.330E+08 NI-65 2.250E-52 2.920E-53 0.000E+00 0.OOOE+00 0.OOOE+00 7.400E-52 0.OOOE+00 1.330E-53 CU-64 0.OOOE+00 2.710E-07 0.OOOE+00 6.830E-07 0.OOOE+00 2.310E-05 0.OOOE+00 1.270E-07 ZN-65 3.560E+08 1.130E+09 0.OOOE+00 7.570E+08' 0.000E+00 7.130E+08 0.OOOE+00 5.120E+08 ZN-69 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.000E+00 0.000E+00 0.000E+00 0.OOOE+00 BR-83 Q.OOOE+00 0.OOE+00 0.OOOE+00 0.000E+00 0.000E+00 8.650E-57 0.OOOE+00 6.OOOE-57 BR-84 0.OOOE+00 O.OOOE+00 0.OOOE+00 O.OOOE+00 0.OOOE+00 0.000E+00 0.000E+00 0.OOOE+00 BR-85 O.OOOE+00_ ,O.OOOE+00 0.OOOE+00 . .OOOE+00 . .OOOE+00 0.000E+00 0.OOOE+00 ._00OE+00 RB-86 0.OOOE+00 4.870E+08 0.OOOE+00 0.OOOE+00 0.OOOE+00 9.600E+07 0.OOOE+00 2.270E+08 RB-88 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.000E+00 0:000E+00 0.000E+00 0.000E+00 0.OOOE+00 RB-89 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.000E+00 0.OOOE+00 0.000E+00 0.OOOE+00 0.OOOE+00 SR-89 3.020E+08 0.OOOE+00 0.000E+00 0.OOOE+00 0.OOOE+00 4.840E+07 0.000E+00 8.660E+06 SR-90 1.240E+10 0.OOOE+00 0.000E+00 0.000E+00 0.OOOE+00 3.590E+08 0.OOOE+00 3.050E+09 SR-91 1.520E-10 0.OOOE+00 0.OOOE+00 0.000E+00 0.000E+00 7.240E-10 0.OOOE+00 6.140E- 12 Appendix G Ri Adult Cow Meat - Page 1 of 3

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX G Ri Adult Dose Factors for use in the Gaseous Dose Calculations 2

Agegroup: ADULT Pathway: Grs/Cow/Meat (CMEAT) Units: m mrem/yr / PCi/sec;

_______ __mrem/yr / jiCi/m 3 (H-3)

Nuciide Bone Liver Thyroid . Kidney Lung, Gilli Skin Total Body SR-92 1.180E-49 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.000E+00 2.340E-48 0.OOOE+00 5.100E-51 Y-90 1.080E+02 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.000E+00 1.140E+06 0.OOOE+00 2.890E+00 Y-91 1.130E+06 0.000E+00 0.OOOE+00 0.000E+00 0.000E+00 6.230E+08 0.OOOE+00 3.030E+04 Y-91M 0.OOOE+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E600 0.000E+00 0.000E+00 Y-92 1.520E-39 0.000E+00 0.OOOE+00 0.000E+00 0.000E+00 2.660E-35 0.000E+00 4.430E-41 Y-93 4.690E-12 0.000E+00 0.000E+00 0.000E+00 0.000E+00 1.490E-07 0.000E+00 1.300E-13 ZR-95 1.870E+06 6.010E+05 0.OOOE+00 9.420E+05 0.000E+00 1.900E+09 0.OOOE+00 4.070E+05 ZR-97 2.070E-05 4.170E-06 0.000E+00 6.300E-06 0.000E+00 1.290E+00 0.000E+00 1.910E-06 NB-95 2.300E+06 1.280E+06 O.000E+00 1.260E+06 0.000E+00 7.760E+09 0.000E+00 6.870E+05 MO-99 0.OOOE+00 1.000E+05 0.OOOE+00 2.260E+05 0.000E+00 2.320E+05 0.OOOE+00 1.900E+04 TC-99M 4.450E-21 1.260E-20 0.006E+00 .1.910E-19 6.150E-21 7.430E- 18 0.OOOE+00 1.600E-19 TC-101 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.000E+00 0.OOOE+00 0.000E+00 0.000E+00 RU-103 1.050E+08 0.OOOE+00 0.000E+00 4.010E+08 0.000E+00 1.230E+10 0.000E+00 4.530E+07 RU-105 5.780E-28 0.OOOE+00 0.OOOE+00 7.460E-27 0.000E+00 3.530E-25 0.000E+00 2.280E-28 RU-106 2.800E+09 0.OOOE+00 0.OOOE+00 5.400E+09 0.OOOE+00 1.810E+1l 0.000E+00 3.540E+08 AG- 110M 6.680E+06 6.180E+06 0.OOOE+00 1.220E+07 0.OOOE+00 2.520E+09 0.000E+00 3.670E+06 TE-125M 3.590E+08 1.300E+08 1.080E+08 1.460E+09 O.OOOE+00 1.430E+09 0.OOOE+00 4.810E+07 TE-127 2.120E-10 7.6 1E- 11 1.570E-10 8.640E- 10 0.000E+00 1.670E-08 0.000E+00 4.590E- 11 TE-127M 1.120E+09 3.990E+08 2.850E+08 4.530E+09 0.000E+00 3.740E+09 0.000E+00 1.360E+08 TE-129 0.OOOE+00 0.OOOE+00 0.000E+00 0.OOOE+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 TE-129M 1.130E+09 4.230E+08 3.900E+08 4.730E+09 0.000E+00 5.71 0E+09 0.000E+00 1.790E+08 TE- 131 0.OOOE+00 0.OOOE+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 TE- 131M 4.51 OE+02 2.21 OE+02 3.490E+02 2.230E+03 0.OOOE+00 2.190E+04 0.000E+00 1.840E+02 TE-132 1.420E+06 9.180E+05 1.010E+06 8.840E+06 0.000E+00 4.340E+07 0.OOOE+00 8.620E+05 11-130 2.11OE-06 6.220E-06 5.270E-04 9.700E-06 0.OOOE+00 5.350E-06 0.000E+00 2.450E-06 Appendix G Ri Adult Cow Meat - Page 2 of 3

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX G R_Adult Dose Factors for use in the Gaseous Dose Calculations 2

Agegroup: ADULT Pathway: Grs/Cow/Meat (CMEAT) Units: m mrem/yr / jiCi/sec;

___________ ___.__ __ "__ mrem/yr/ ICi/m(H-3) 3 Nuclide Bone Liver Thyroid Kidney Lung - Gilli Skin Total Body 1-131 1.070E+07 1.540E+07 5.030E+09 2.630E+07 0.OOOE+00 4.050E+06 0.OOOE+00 8.800E+06 1-132 6.970E-59 1.860E-58 6.530E-57 2.970E-58 0.OOOE+00 3.500E-59 0.OOOE+00 6.530E-59 1-133 3.650E-01 6.350E-01 9.340E+01 1.11OE+00 0.OOOE+00 5.710E-01 0.OOOE+00 1.940E-01 1-134 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE÷00 0.OOOE+00 0.000E+00 1-135 4.420E-17 1.160E-16 7.640E-15 1.860E-16 0.OOOE+00 1.310E-16 0.000E+00 4.270E-17 CS-134 6.580E+08 1.560E+09 0.OOOE+00 5.060E+08 1.680E+08 2.740E+07 0.000E+00 1.280E+09 CS-136 1.210E+07 4.760E+07 0.OOOE+00 2.650E+07 3.630E+06 5.410E+06 0.OOOE+00 3.420E+07 CS-137 8.720E+08 1.190E+09 0.OOOE+00 4.050E+08 1.350E+08 2.310E+07 0.OOOE+00 7.810E+08 CS-138 0.OOOE+00 0.OOOE+00 0.OOOE+00 O.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 BA-139 0.OOOE+00 0.000E+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.000E+00 0.OOOE+00 BA-140 2.870E+07 3.61 OE+04 0.OOOE+00 1.230E+04 2.070E+04 5.920E+07 0.OOOE+00 1.880E+06 BA-141 0.OOOE+00 0.OOOE+00 0.000E+00 0.0010E+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 BA-142 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 LA-140 3.710E-02 1.870E-02 0.OOOE+00 0.OOOE+00 0.OOOE+00 1.370E+03 0.OOOE+00 4.940E-03 LA-142 3.470E-92 1.580E-92 0.OOOE+00 0.000E+00 0.OOOE+00 1.150E-88 0.000E+00 3.940E-93 CE-141 1.400E+04 9.500E+03 0.OOOE+00 4.410E+03 0.OOOE+00. 3.630E+07 0.OOOE+00 1.080E+03 CE-143 2.010E-02 1.480E+01 0.OOOE+00 6.530E-03 0.OOOE+00 *5.550E+02 0.OOOE+00 1.640E-03 CE-144 1.460E+06 6.090E+05 0.OOOE+00 3.610E+05 0.000E+00 4.930E+08 0.OOOE+00 7.830E+04 PR-143 2.100E+04 8.410E+03 0.000E+00 4.850E-+03 0.OOOE+00 9.180E+07 0.OOOE+00 1.040E+03 PR-144 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 ND-147 7.070E+03 8.170E+03 0.OOOE+00 4.780E+03 0.OOOE+00 3.920E+07 0.OOOE+00 4.890E+02 W-187 2.070E-02 1.730E-02 0.OOOE+00 0.000E+00 0.OOOE+00 5.660E+00 0.000E+00 6.040E-03 NP-239 2.590E-01 2.550E-02 0.OOOE+00 7.950E-02 0.000E+00 5.230E+03 0.000E+00 1.400E-02 9

Appendix G Ri Adult Cow Meat - Page 3 of 3

Oconee Nuclear Station 0

January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX G Ri Adult Dose Factors for use in the Gaseous Dose Calculations Agegroup.:ý ADULT Pathway: Vegetation (VEG) Units: m 2.mrem/yr / jiCi/sec;

__________ _________ ___________ ______mrem/yr / jtCi/m 3 (H-3)

Nuclide Bone Liver Thyroid Kidne Lung Gilli Skin Total Body H-3 0.090E+00 2.260E+03 2.260E+03 2.260E+03 2.260E+03 2.260E+03 0.OOOE+00 2.260E+03 C-14 2.280E+08 4.550E+07 4.550E+07 4.550E+07 4.550E+07 4.550E+07 0.OOOE+00 4.550E+07 NA-24 2.690E+05 2.690E+05 2.690E+05 2.690E+05 2.690E+05 2.690E+05 0.OOOE+00 2.690E+05 P-32 1.400E+09 8.730E+07 0.OOOE+00 0.OOOE+00 0.OOOE+00 1.580E+08 0.OOOE+00 5.430E+07 CR-51 0.OOOE+00 0.OOOE+00 2.780E+04 1.020E+04 6.160E+04 1.170E+07 0.OOOE+00 4.640E+04 MN-54 0.OOOE+00 3.130E+08 0.00OE+00 9.310E+07 0.OOOE+00 9.590E+08 0.OOOE+00 5.970E+07 MN-56 0.OOOE+00 1.580E+01 0.OOOE+00 2.000E+01 0.OOOE+00 5.040E+02 0.OOOE+00 2.800E+00 FE-55 2.100E+08 1.450E+08 0.OOOE+00 0.OOOE+00 8.080E+07 8.310E+07 0.OOOE+00 3.380E+07 FE-59 1.260E+08 2.960E+08 O.OOOE+00 0.OOOE+00 8.280E+07 9.880E+08 0.OOOE+00 1.140E+08 CO-58 0.OOOE+00 3.070E+07 0.OOOE+00 0.OOOE+00 0.OOOE+00 6.230E+08 0.OOOE+00 6.890E+07 CO-60 0.OOOE+00 1.670E+08 0.OOOE+00 0.OOOE+00 6.000E+00 3.140E+09 0.OOOE+00 3.690E+08 NI-63 1.040E+10 7.210E+08 0.OOOE+00 0.OOOE+00 0.OOOE+00 1.500E+08 0.OOOE+00 3.490E+08 NI-65 6.150E+01 7.990E+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 2.030E+02 0.OOOE+00 3.640E+00 CU-64 0.OOOE+00 9.200E+03 0.000E+00 2.320E+04 6.000E+00 7.840E+05 0.OOOE+00 4.320E+03 ZN-65 3.170E+08 1.01OE+09 0.OOOE+00 6.750E+08 0.000E+00 6.360E+08 0.OOOE+00 4.560E+08 ZN-69 5.490E-06 1.050E-05 0.OOOE+00 6.830E-06 0.OOOE+00 1.580E-06 0.000E+00 7.310E-07 BR-83 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.000E+00 0.000E+00 4.470E+00 0.OOOE+00 3.11OE+00 BR-84 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.000E+00 1.940E-16 0.OOOE+00 2.480E-1 1 BR-85 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.000E+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.000E+00 RB-86 0.OOOE+00 2.190E+08 0.OOOE+00 0.OOOE+00 0.OOOE+00 4.330E+07 0.OOOE+00 1.020E+08 RB-88 0.OOOE+00 3.430E-22 0.OOOE+00 0.OOOE+00 0.OOOE+00 4.740E-33 0.OOOE+00 1.820E-22 RB-89 0.OOOE+00 3.890E-26 0.OOOE+00 0.OOOE+00 0.OOOE+00 2.260E-39 0.OOOE+00 2.730E-26 SR-89 9.970E+09 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 1.600E+09 0.OOOE+00 2.860E+08 SR-90 6.050E+11 0.OOOE+00 0.OOOE+00 0.000E+00 0.OOOE+00 1.750E+10 0.OOOE+00 1.480E+11 SR-91 3.050E+05 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 1.450E+06 0.OOOE+00 1.230E+04 Appendix G Ri Adult Vegetation - Page 1of 3

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX G Ri Adult Dose Factors for use in the Gaseous Dose Calculations 2

Agegroutp: ADULT Pathiway::ý Vegetation (VEG) 'U.nits:, m mrem/yr / pCilsec;

'"  ;" * * * :*:*i
  • mrem/y'r/ Ci/m3 (H--3)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body SR-92 4.270E+02 0.000E+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 8.450E+03 0.OOOE+00 1.850E+01 Y-90 1.330E+04 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 1.410E+08 0.OOOE+00 3.570E+02 Y-91 5.11OE+06 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 2.810E+09 0.OOOE+00 1.370E+05 Y-91M 5.220E-09 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.000E+00 1.530E-08 0.OOOE+00 2.020E-10 Y-92 9.150E-01 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 1.600E+04 0.OOOE+00 2.680E-02 Y-93 1.700E+02 0.OOOE+00 0.OOOE+00 0.000E+06 0.OOOE+00 5.380E+06 0.OOOE+00 4.680E+00 ZR-95 1.170E+06 3.770E+05 0.OOOE+00 5.910E+05 0.000E+00 1.190E+09 0.OOOE+00 2.550E+05 ZR-97 3.370E+02 6.810E+01 0.OOOE+00 1.030E+02 0.OOOE+00 2.11OE+07 0.000E+00 3.11OE+01 NB-95 1.420E+05 7.920E+04 0.OOOE+00 7.830E+04 0.OOOE+00 4.810E+08 0.OOOE+00 4.260E+04 MO-99 0.000E+00 6.150E+06 0.OOOE+00 1.390E+07 0.OOOE+00 1.430E+07 0.OOOE+00 1.170E+06 TC-99M 3.100E+00 8.770E+00 0.OOOE+00 1.330E+02 4.300E+00 5.190E+03 0.OOOE+00 1.120E+02 TC-101 8.220E-31 1.180E-30 0.000E+00 2.130E-29 6.050E-31 3.560E-42 0.OOOE+00 1.160E-29 RU-103 4.770E+06 0.000E+00 0.OOOE+00 1.820E+07 0.OOOE+00 5.570E+08 0.000E+00 2.060E+06 RU-105 5.390E+01 0.OOOE+00 0.OOOE+00 6.960E+02 0.OOOE+00 3.290E+04 0.OOOE+00 2.130E+01 RU-106 1.930E+08 0.OOOE+00 0.OOOE+00 3.720E+08 0.OOOE+00 1.250E+10 0.OOOE+00 2.440E+07 AG-1 10M 1.050E+07 9.750E+06 0.OOOE+00 1.920E+07 0.OOOE+00 3.980E+09 0.OOOE+00 5.790E+06 TE-125M 9.660E+07 3.500E+07 2.900E+07 3.930E+08 0.OOOE+00 3.860E+08 0.OOOE+00 1.290E+07 TE- 127 5.660E+03 2.030E+03 4.190E+03 2.310E+04 0.OOOE+00 4.470E+05 0.000E+00 1.220E+03 TE-127M 3.490E+08 1.250E+08 8.920E+07 1.420E+09 0.OOOE+00 1.170E+09 0.000E+00 4.260E+07

-TE-129 - 7.630E-04 2.870E-04 .. 5.850E-04-- - 3.210E-03--... 0.OOOE+00 5.760E-04 0.OOOE+00 1.860E-04 TE-129M 2.5-10E+08 9.380E+07 8.630E+07 1.050E+09 0.OOOE+00 1.270E+09 0.OOOE+00 3.980E+07 TE-131 1.500E-15 6.270E-16 1,230E-15 6.570E-15 0.OOOE+00 2.130E-16 0.000E+00 4.740E-16 TE-131M 9.120E+05 4.460E+05 7.060E+05 4.520E+06 0.OOOE+00 4.430E+07 0.000E+00 3.720E+05 TE-132 4.300E+06 2.780E+06 3.070E+06 2.680E+07 O.OOOE+00 1.320E+08 0.000E+00 2.610E+06 1-130 3.920E+05 1.160E+06 9.810E+07 1.810E+06 0.OOOE+00 9.960E+05 0.OOOE+00 4.570E+05 Appendix G Ri Adult Vegetation - Page 2 of 3 0 0

Oconee Nuclear Station 0 January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX G Ri Adult Dose Factors for use in the Gaseous Dose Calculations Agegroup: ADULT Pathway: Vegetation (VEG) Units:. m 2.mrem/yr / p.Ci/sec;

.- , .. mrem/yr / tCi/m3 (H-3)

Nuclide .'Bone . Liver Thyroid, Kidney Lung Gilli Skin Total Body 1-131 8.080E+07 1.160E+08 3.790E+10 1.980E+08 0.OOOE+00 3.050E+07 0.000E+00 6.620E+07 1-132 5.760E+01 1.540E+02 5.390E+03 2.450E+02 0.OOOE+00 2.890E+01 0.000E+00 5.390E+01 1-133 2.090E+06 3.630E+06 5.330E+08 6.330E+06 0.OOOE+00 3.260E+06 0.OOOE+00 1.11OE+06 1-134. 9.650E-05 2.620E-04 4.540E-03 4.170E-04 0.OOOE+00 2.290E-07 O.000E+00 9.380E-05 1-135 3.900E+04 1.020E+05 6.730E+06 1.640E+05 0,0O0E+00 1.150E+05 0.000E+00 3.770E+04 CS-134 - 4.670E+09 1.110E+I0 0.OOOE+00 3.590E+09 1.190E+09 1.940E+08 0.OOOE+00 9.080E+09 CS-136 4.270E+07 1.680E+08 0.OOOE+00 9.380E+07 11290E+07 1.910E+07 0.OOOE+00 1.210E+08 CS-137 6.360E+09 8.700E+09 0.OOOE+00 2.950E+09 9.810E+08. 1.680E+08 0.OOOE+00 5.700E+09 CS-138 3.920E-11 7.730E-11 0.000E+00 5.680E-11 5.610E-12 3.300E-16 0.OOOE+00 3.830E-11 BA-139- 2.860E-02 2.030E-05 0.OOOE+00 1.900E-05 1.150E-05 5.060E-02 0.OOOE+00 8.360E-04 BA-140 1.280E+08 1.610E+05 0.OOOE+00 5.490E+04 9.240E+04 2.650E+08 0.OOOE+00 8.420E+06 BA-141 1.150E-21 8.700E-25 0.OOOE+00 8.090E-25 4.940E-25 .5.430E-31 0.OOOE+00 3.890E-23 BA-142 5.960E-39 6.120E-42 0.OOOE+00 5.170E-42 -3.470E-42 8.390E6-57 0.OOOE+00 3.750E-40 LA-140 1.980E+03 9.970E+02 0.000E+60 0.OOOE+00 0.OOOE+00 7.320E+07 0.OOOE+00 2.630E+02 LA-142 2.020E-04 9.190E-05 0.OOOE+00 0.OOOE+00 0.OOOE+00 6.710E-01 0.000E+00 2.290E-05 CE-141 1.970E+05 1.330E+05 0.OOOE+00 6.190E+04 0.00OE+00 5.100E+08 0.OOOE+00 1.5 1OE+04 CE-143 -9.980E+/-02 7.380E+05 . 0.OOOE+00 3.250E+02 0.OOOE+00 2.760E+07 0.OOOE+00 8.160E+01 CE-144 3.290E+07 1.380E+07 0.OOOE+00 8.160E+06 0.OOOE+00 1.110E+10 0.OOOE+00 1.770E+06 PR- 143 6.260E+04 2.5 1OE+04 0.OOOE+00 1.450E+04 0.006E+00 2.740E+08 0.OOOE+00 3.100E+03 PR-144 3.090E-26 1.280E-26 0.060E+00 7.230E-27 0.OOOE+00 4.440E-33 0.OOOE+00 1.570E-27 ND-147 3.330E+04 3.850E+04 0.OOOE+00 2.250E+04 0.OOOE+00 1.850E+08 0.OOOE+00 - 2.310E+03 W- 187 3.800E+04 3.180E+04 0.OOOE+00 0.OOOE+00 0.OOOE+00 1.040E+07 0.OOOE+00 1.11 OE+04 NP-239 1.430E+03 1.400E+02 0.OOOE+00 4.380E+02 0.OOOE+00 2.880E+07 0.OOOE+00 7.740E+01 Appendix G Ri Adult Vegetation - Page 3 of 3

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX G Ri Adult Dose Factors for use in the Gaseous Dose Calculations

'-Agegroup: ADULT Pathway:-. Inhalation (INHL) Units:

... ...* '  : , ...: ' m rem /y r/tCi/m3 Nuclide. Bone Liver Thyroid Kidney Lung Gilli Skin Total Body H-3 0.OOOE+00 1.260E+03 1.260E+03 1.260E+03 1.260E+03 1.260E+03 0.000E+00 1.260E+03 C-14 1.820E+04 3.410E+03 3.410E+03 3.410E+03 3.410E+03 3.410E+03 0.000E+00 3.410E+03 NA-24 1.020E+04 1.020E+04 1.020E+04 I1.020E+04 1.020E+04 1.020E+04 0.000E+00 1.020E+04 P-32 1.320E+06 7.710E+04 0.OOOE+00 0.OOOE+00 0.000E+00 8.640E+04 0.000E+00 5.010E+04 CR-51 0.OOOE+00 0.OOOE+00 5.950E+01 2.280E+01 1.440E+04 3.320E+03 0.000E+00 1.000E+02 MN-54 0.OOOE+00 3.960E+04 0.OOOE+00.. 9.840E+03 1.400E+06 7.740E+04 0.000E+00 6.300E+03 MN-56 O.OOOE+00 1.240E+00 0.000E+00 1.300E+00 9.440E+03 2.020E+04 0.OOOE+00 1.830E-01 FE-55 2.460E+04 1.700E+04 0.OOOE+00 0.OOOE+00 7.210E+04 6.030E+03 0.OOOE+00 3.940E+03 FE-59 1.180E+04 2.780E+04 0.OOOE+00 0.OOOE+00 1.020E+06 1.880E+/-05 0.000E+00 1.060E+04 CO-58 0.000Et00 1.580E+03 0.OOOE+00 0.000E+00 9.280E+05 1.060E+05 0.000E+00 2.070E+03 CO-60 0.OOOE+00 1.150E+04 0.OOOE+00 0.OOOE+00 5.970E+06 2.850E+05 0.000E+00 1.480E+04 NI-63* 4.320E+05 3.140E+04 0.OOOE+00 0.OOOE+00 1.780E+05 1.340E+04 0.000E+00 1.450E+04 NI-65 1.540E+00 .2.100E-01 0.000E+00 0.OOOE+00 5.600Et03 1.230E+04 0.000E+00 9.120E-02 CU-64 0.OOOE+00 1.460E+00 0.OOOE+00 4.620E+00 6.780E+03 4.900E+04 0.000E+00 6.150E-01 ZN-65 3.240E+04 1.030E+05 0.OOOE+00 6.900E+04 8:640E+05 5.340E+04 0.O0OE+00 4.660E+04 ZN-69 3.380E-02 6.510E-02 0.OOOE+00 4.220E-02 9.200E+02 1.630E+01 0.000E+00 4.520E-03 BR-83 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+0O 0.000E+00 2.320E+02 0.OOOE+00 2.410E+02 BR-84. 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 -1.640E-03 0.000E+00 3.130E+02 BR-85 0.OOOE+00 0.OOOE+00 0:000E+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.000E+00 1.280E+01

-RB-86-. . 0.000E+00 - 1.350E&05 . - 00 .

.OOOE+......00 .000E+00 0 1.660E+0-4 .0OOOE+/ 5.900E+04 RB-88 0.OOOE+00 3.870E+02 0.OOOE+00 0.OOOE+00 0.OOOE+00 3.340E-09 0.000E+00 1.930E+02 RB-89 0.OOOE+00 2.560E+02 0.000E+00 0.OOOE+00 0.OOOE+00 9.280E-12 0.OOOE+00 1.700E+02 SR-89 3.040E+05 0.000E+00 0.000E+00 0.OOOE+00 1.400E+06 3.500E+05 0.OOOE+00 8.720E+03 SR-90 9.920E+07 0.OOOE+00 0.000E+00 0.OOOE+00 9.600E+06 7.220E+05 0.000E+00 6.100E+06 SR-91 6.190E+01 0.OOOE+00 0.000E+00 0.000E+00 3.650E+04 1.910E+05 0.OOOE+00 2.500E+00 Appendix G Ri Adult Inhalation - Page 1 of 3

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX G R1 Adult Dose Factorsfor use in the Gaseous Dose Calculations Agegroup: ADULT Pathway: Inhalation (INHL) Units:

3 Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body SR-92 6.740E+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 1.650E+04 4.300E+04 0.OOOE+00 2.910E-01 Y-90 2.090E+03 0.OOOE+00 0.000E+00 0.OOOE+00 1.700E+05 5.060E+05 0.OOOE+00 5.610E+01 Y-91 4.620E+05 0.OOOE+00 0.OOOE+00 0.OOOE+00 1.700E+06 3.850E+05 0.OOOE+00 1.240E+04 Y-91M 2.610E-01 0.OOOE+00 0.OOOE+00 0.OOOE+00 1.920E+03 1.330E+00 0.OOOE+00 1.020E-02 Y-92 1.030E+01 0.OOOE+00 O.OOOE+00 0.OOOE+00 1.570E+04 7.350E+04 0.OOOE+00 3.020E-01 Y-93 9.440E+01 0.OOOE+00 O.OOOE+00 0.OOOE+00 4.850E+04 4.220E+05 0.OOOE+00 2.6 1OE+00 ZR-95 1.070E+05 3.440E+04 O.OOOE+00 5.420E+04 1.770E+06 1.500E+05 0.OOOE+00 2.330E+04 ZR-97 9.680E+01 1.960E+01 0.OOOE+00 2.970E+01 7.870E+04 5.230E+05 0.OOOE+00 9.040E+00 NB-95 1.410E+04 7.820E+03 0.OOOE+00 7.740E+03 5.050E+05 1.040E+05 0.000E+00 4.210E+03 MO-99 0.OOOE+00 1.210E+02 0.OOOE+00 2.910E+02 9.120E+04 2.480E+05 0.OOOE+00 2.300E+01 TC-99M 1.030E-03 2.910E-03 0.OOOE+00 4.420E-02 7.640E+02 4.160E+03 0.OOOE+00 3.700E-02 TC-101 4.180E-05 6.020E-05 0.000E+00 1.080E-03 3.990E+02 1.090E-11 0.OOOE+00 5.900E-04 RU-103 1.530E+03 0.OOOE+00 0.000E+60 5.830E+03 5.050E+05 1.100E+05 O.OOOE+00 6.580E+02 RU-105 7.900E-01 0.000E+00 O.OOOE-00 1.020E+00 1.100E+04 4.820E+04 0.OOOE+00 3.11OE-01 RU-106 6.910E+04 0.OOOE+00 0.OOOE+00 1.340E+05 9.360E+06 9.120E+05 0.OOOE+00 8.720E+03 AG-1 10M 1.080E+04 1.000E+04 0.OOOE+00 1.970E+04 4.630E+06 3.020E+05 O.OOOE+00 5.940E+03 TE-125M 3.420E+03 1.580E+03 1.050E+03 1.240E+04 3.140E+05 7.060E+04 0.000E+00 4.670E+02 TE-127 1.400E+00 6.420E-01. 1.060E+00 5.100E+00 6.5 1OE+03 5.740E+04 0OOOE+00 3.100E-01 TE-127M 1.260E+04 5.770E+03 3.290E4-03 4.580E+04 9.600E+05 1.500E+05 0.OOOE+00 1.570E+03 TE-129 4.980E-02 2.390E-02 3.900E-02 1.870E-01 1.940E+03 1.570E+02 0.OOOE+00 1.240E-02 TE-129M 9.760E+03 4.670E+03 3.440E+03 3.660E+04 1.160E+06 3.830E+05 0.OOOE+00 1.580E+03 TE- 131 1.11OE-02 5.950E-03 9.360E-03 4.370E-02 1.390E+03 1.840E+01 0.OOOE+00 3.590E-03 TE-131M 6.990E+01 4.360E+01 5.500E+01 3.090E+02 1.460E+05 5.560E+05 0.OOOE+00 2.900E+01 TE-132 2.600E+02 2.150E+02 1.900E+02 1.460E+03 2.880E+05 5.100E+05 0.OOOE+00 1.620E+02 1-130 4.580E+03 1.340E+04 1.140E+06 2.090E+04 0.OOOE+00 7.690E+03 0.000E+00 5.280E+03 Appendix G Ri Adult Inhalation - Page 2 of 3

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX G R. Adult Dose Factors for use in the Gaseous Dose Calculations

.Agegroup: ADULT 'Pathway: Inhalation (INHL) tiUnits:

. -:i*i ::' ': , .mrem/Y '/ýtCi/m33 Nuclide Bone Liver Thyroid, Kidney Lung Gilli Skin Total Body 1-131 2.520E+04 3.580E+04 1.190E+07 6.130E+04 0.OOOE+00 6.280E+03 0.OOOE+00 2.050E+04 1-132 1.160E+03 3.260E+03 1.140E+05 5.180E+03 0.OOOE+00 4.060E+02 0.OOOE+00 1.160E+03 1-433 8.640E+03 1.480E+04 2.150E+06 2.580E+04 0.OOOE+00 8.880E+03 0.OOOE+00 4.520E+03 1-134 6.440E+02 1.730E+03 2.980E+04 2.750E+03 0.OOOE+00 1.010E+00 0.OOOE+00 6.150E+02 1-135 2.680E+03 6.980E+03 4.480E+05 1.110E+04 0.OOOE+00 5.250E+03 0.OOOE+00 2.570E+03 CS-134 3.730E+05 8.480E+05 0.OOOE+00 2.870E+05 9.760E+04 1.040E+04 0.OOOE+00 7.280E+05 CS-136 3.900E+04 1.460E+05 0.000E+00 8.560E+04 1.200E+04 1.170E+04 0.OOOE+00 1.100E+05 CS-137 4.780E+05 6.210E+05 0.OOOE+00 2.220E+05 7.520E+04 8.400E+03 0.OOOE+00 4.280E+05 CS-138 3.3 1OE+02 6.210E+02 0.OOOE+00 4.800E+02 4.860E+01 1.860E-03 0.OOOE+00 3.240E+02 BA-139 9.360E-01 6.660E-04 0.OOOE+00. 6.220E-04 3.760E+03 8.960E+02 0.OOOE+00 2.740E-02 BA-140 3.900E+04 4.900E+01 0.000E+00 1.670E+01 1.270E+06 2.180E+05 0.000E+00 2.570E+03 BA-141 1.000E-01 7.530E-05 0.OOOE+00 7.OOOE-05 1.940E+03 1.160E-07 0.OOOE+00 3.360E-03 BA-142 2.630E-02 2.700E-05 0.OOOE+00 2.290E-05 1.190E+03 1.570E-16 0.000E+00 1.660E-03 LA-140 3.440E+02 1.740E+02 0.OOOE+00 0.OOOE+00 1.360E+05 4.580E+05 0.OOOE+00 4.580E+01 LA-142 6.830E-01 3.100E-01 0.000E+00 0.OOOE+00 6.330E+03 2.11OE+03 0.OOOE+00 7.720E-02 CE-141 1.990E+04 1.350E+04 0.OOOE+00 6.260E+03 3.620E+05 1.200E+05 0.OOOE+00 1.530E+03 CE-143 1.860E+02 1.380E+02 0.OOOE+00 6.080E+01 7.980E+04 2.260E+05 0.OOOE+00 1.530E+01 CE-144 3.430E+06 1.430E+06 0.OOOE+00 8.480E+05 7.780E+06 8.160E+05 0.OOOE+00 1.840E+05 PR-143 9.360E+03 3.750E+03 0.OOOE+00 2.160E+03 2.810E+05 2.OOOE+05 0.OOOE+00 4.640E+02 PR-144 3.010E-02 1.250E-02 0.0O00E+00 7.050E-03 1.020E+03 2.150E-08 0.OOOE+00 1.530E-03 ND-147 5.270E+03 6.100E+03 0.OOOE+00 3.560E+03 2.210E+05 1.730E+05 0.OOOE+00 3.650E+02 W-187 8.480E+00 7.080E+00 0.000E+00 0.OOOE+00 2.900E+04 1.550E+05 0.OOOE+00 2.480E+00 NP-239 2.300E+02 2.260E+01 0.OOOE+00 7.OOOE+01 3.760E+04 1.190E+05 0.OOOE+00 1.240E+01 Appendix G Ri Adult Inhalation - Page 3 of 3'

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX G RK Adult Dose Factors for use in the Gaseous Dose Calculations Agegroup: ADULT Pathway: Ground Plane Deposition (GPD) Units: m 2.mrem/yr / XCi/sec Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin TotalBody H-3 0.OOOE+00 0.OOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 C-14 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 NA-24 1.190E+07 1.190E+07 1.190E+07 1.190E+07 1.190E+07 1.190E+07 1.390E+07 1.190E+07 P-32 0.000E+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 O.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 CR-51 4.660E+06 4.660E+06 4.660E+06 4.660E+06 4.660E+06 4.660E+06 5.5 1OE+06 4.660E+06 MN-54 1.390E+09 1.390E+09 1.390E+09 1.390E+09 1.390E+09 1.390E+09 1.630E+09 1.390E+09 MN-56 9.020E+05 9.020E+05 9.020E+05 9.020E+05 9.020E+05 9.020E+05 1.070E+06 9.020E+05 FE-55 O.OOOE+00 0.OOOE+00 0.OOOE+00 0.000E+00 0.OOOE+00 0.O0OE+00 0.000E+00 0.OOOE+00 FE-59 2.730E+08 2.730E+08 2.730E+08 2.730E+08 2.730E+08 2.730E+08 3.210E+08 2.730E+08 CO-58 3.790E+08 3.790E+08 3.790E+08 3.790E+08 *3.790E+08 3.790E+08 4.440E+08 3.790E+08 CO-60 2.150E+10 2.150E+10 2.150E+10 2.150E+10 2.150E+10 2.150E+10 2.530E+10 2.150E+10 NI-63 0.000E+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.000E+00 0.OOOE+00 0.000E+00 0.OOOE+00 NI-65 2.970E+05 2.970E+05 2.970E+05 2.970E+05 2.970E+05 2.970E+05 3.450E+05 2.970E+05 CU-64 6.070E+05 6.070E+05 6.070E+05 6.070E+05 6.070E+05 6.070E+05 6.880E+05 6.070E+05 ZN-65 7.470E+08 7.470E+08 7.470E+08 7.470E+08 7.470E+08 7.470E3+08 8.590E+08 7.470E+08 ZN-69 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.000E+00 0.OOOE+00 0.OOOE+00 0.000E+00 0.OOOE+00 BR-83 4.870E+03 4.870E+03 4.870E+03 4.870E+03 4.870E+03 4.870E+03 7.080E+03 4.870E+03 BR-84 2.030E+05 2.030E+05 2.030E+05 2.030E+05 2.030E+05 2.030E+05 2.360E+05 2.030E+05 BR-85 0.OOOE+00 0.OOOE+00 0.OOOE+00 O.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 RB-86 8.990E+06 8.990E+06 8.990E+06 8.990E+06 8.990E+06 8.990E+06 1.030E+07 8.990E+06 RB-88 3.3 10E+04 3.31 OE+04 3.31 OE+04 3.31 OE+04 3.31 OE+04 3.31 OE+04 3.780E+04 3.3101E+04 RB-89 1.230E+05 1.230E+05 1.230E+05 1.230E+05 1.230E+05 1.230E+05 1.480E+05 1.230E+05 SR-89 2.160E+04 2.160E+04 2.160E+04 2.160E+04 2.160E+04 2.160E+04 2.510E+04 2.160E+04 SR-90 0.OOOE+00 0.OOOE+00 0.000E+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.000E+00 0.OOOE+00 SR-91 2.150E+06 2.150E+06 2.150E+06 2.150E+06 2.150E+06 2.150E+06 2.5 1OE+06 2.150E+06 Appendix G Ri Adult Ground Plane Deposition - Page 1 of 3

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX G Ri Adult Dose Factors for use in the Gaseous Dose Calculations Agegroup: ADULT Pathway: Ground Plane Deposition (GPD) Units: m mrem/yr / p.Ci/sec Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body SR-92 7.770E+05 7.770E+05 7.770E+05 7.770E+05 7.770E+05 7.770E+05 8.630E+05 7.770E+05 Y-90 4.490E+03 4.490E+03 4.490E+03 4.490E+03 4.490E+03 4.490E+03 5.310E+03 4.490E+03 Y-91 1.070E+06 1.070E+06 1.070E+06 1.070E+06 1.070E+06 1.070E+06 1.210E+06 1.070E+06 Y-91M 1.000E+05 1.000E+05 1.000E+05 1.000E+05 1.000E+05 1.000E+05 1.160E+05 1.000E+05

-Y-92 1.800E+05 1.800E+05 1.800E+05 1.800E+05. 1.800E+05 1.800E+05 2.140E+05 1.800E+05 Y-93 1.830E+05 1.830E+05 1.830E+05 1.830E+05 1.830E+05 1.830E+05 2.510E+05 1.830E+05 ZR-95 2.450E+08 2.450E+08 2.450E+08 2.450E+08 2.450E+08 2.450E+08 2.840E+08 2.450E+08 ZR-97 2.960E+06 2.960E+06 2.960E+06 2.960E+06 2.960E+06 2.960E+06 3.440E+06 2.960E+06 NB-95 1.370E+08 1.370E+08 1.370E+08 1.370E+08 1.370E+08 1.370E+08 1.610E+08 1.370E+08 MO-99 3.990E+06 3.990E+06 3.990E+06 3.990E+06 3.990E+06 3.990E+06 4.630E+06 3.990E+06 TC-99M 1.840E+05 1.840E+05 1.840E+05 1.840E+05 1.840E+05 1.840E+05 2.11OE+05 1.840E+05

.TC-101 2.040E+04 2.040E+04 2.040E+04 2.040E+04 2.040E+04 2.040E+04 2.260E+04 2.040E+04 RU-103 1.080E+08 1.080E+08 1.080E+08 1.080E+08 1.080E+08 1.080E+08 1.260E+08 1.080E+08 RU-105 6.360E+05 6.360E+05 6.360E+05 6.360E+05 6.360E+05 6.360E+05 7.210E+05 6.360E+05 RU-106 4.220E+08 4.221)E+08 4.220E+08 4.220E+08 4.220E+08 4.220E+08 5.070E+08 4.220E+08 AG-i IOM 3.440E+09 3.440E+09 3.440E+09 3.440E+09 3.440E+09 3.440E+09 4.010E+09 3.440E+09 TE-125M 1.550E+06 1.550E+06 1.550E+06 1.550E+06 1.550E+06 1.550E+06 2.130E+06 1.550E+06 STE- 127 2.980E+03 2.980E+03 2.980E+03 2.980E+03 2.980E+03 2.980E+03 3.280E+03 2.980E+03 TE-127M 9.160E+04 9.160E+04 9.160E+04 9.160E+04 9.160E+04 9.160E+04 1.080E+05 9.160E+04 TE-129 2.620E+04 2.620E+04 2.620E+04 2.620E+04 2.620E+04 2.620E+04 3.100E+04 2.620E+04 TE-129M 1.980E+07 1.980E+07 1.980E+07. 1.980E+07 1.980E+07 1.980E+07 2.310E+07 1.980E+07 TE- 131 2.920E+04 2.920E+04 2.920E+04 2.920E+04 2.920E+04 2.920E+04 3.450E+07 2.920E+04 TE- 131M 8.030E+06 8.030E+06 8.030E+06 8.030E+06 8.030E+06 8.030E+06 9.460E+06 8.030E+06 TE-132 4.230E+06 4.230E+06 4.230E+06 4.230E+06 4.230E+06 4.230E+06 4.980E+06 4.230E+06 1-130 5.510E+06 5.510E+06 5.510E+06 5.510E+06 5.510E+06 5.510E+06 6.690E+06 5.510E+06 Appendix G Ri Adult Ground Plane Deposition - Page 2 of 3 0

Oconee Nuclear Station 0

January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX G Ri Adult Dose Factors for use in the Gaseous Dose Calculations Agegroup: ADULT Pathway: . Ground Plane Deposition (GPD) Units: m 2.mrem/yr./ItCi/sec Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body 1-131 1.720E+07 1.720E+07 1.720E+07 1.720E+07 1.720E+07 1.720E+07 2.090E+07 1.720E+07 1-132 1.250E+06 1.250E+06 1.250E+06 1.250E+06 1.250E+06 1.250E+06 1.470E+06 1.250E+06 1-133 2.450E+06 2.450E+06 2.450E+06 2.450E+06 2.450E+06 2.450E+06 2.980E+06 2.450E+06 1-134 4.470E+05 4.470E+05 4.470E+05 4.470E+05 4.470E+05 4.470E+05 5.300E+05 4.470E+05 1-135 2.530E+06 2.530E+06 2.530E+06 2.530E+06 2.530E+06 2.530E+06 2.950E+06 2.530E+06 CS- 134 6.860E+09 6.860E+09 6.860E+09 6.860E+09 6.860E+09 6.860E+09 8.OOOE+09 6.860E+09 CS-136 1.510E+08 1.510E+08 1.510E+08 1.510E+08 1.510E+08 1.510E+08 1.710E+08 1.510E+08 CS-137 1.030E+10 1.030E+10 1.030E+10 1.030E+10 1.030E+10 1.030E+10 1.200E+10 1.030E+10 CS-138 3.590E+05 3.590E+05 3.590E+05 3.590E+05 3.590E+05 -3.590E+05 4.100E+05 3.590E+05 BA-139 1.060E+05 1.060E+05 1.060E+05 1.060E+05 1.060E+05 1.060E+05 1.190E+05 1.060E+05 BA-140 2.050E+07. 2.050E+07 2.050E+07 2.050E+07 2.050E+07 2.050E+07 2.350E+07 2.050E+07 BA- 141 4.170E+04 4.170E+04 4.170E+04 4.170E+04 4.170E+04 4.170E+04 4.750E+04 4.170E+04 BA-142 4.490E+04 4.490E+04 4.490E+04 4.490E+04 4.490E+04 4.490E+04 5.11 OE+04 4.490E+04 LA- 140 1.920E+07 1.920E+07 1.920E+07 1.920E+07 1.920E+07 1.920E+07 2.180E+07 1.920E+07 LA-142 7.600E+05 7.600E+05 7.600E+05 7.600E+05 7.600E+05 7.600E+05 9.120E+05 7.600E+05 CE-141 1.370E+07 1.370E+07 1.370E+07 1.370E+07 1.370E+07 1.370E+07 1.540E+07 1.370E+07 CE-143 2.310E+06 2.310E+06 2.310E+06 2.310E+06 2.310E+06 2.310E+06 2.630E+06 2.310E+06 CE-144 6.950E+07 6.950E+07 6.950E+07 6.950E+07 6.950E+07 6.950E+07 8.040E+07 6.950E+07 PR-143 0.000E+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00* 0.OOOE+00 0.OOOE+00 PR-144 1.830E+03 1.830E+03 1.830E+03 1.830E+03 ' 1.830E+03 1.830E+03 2.1 fOE+03 1.830E+03 ND-147 8.390E+06 8.390E+06 8.390E+06 8.390E+06 8.390E+06 8.390E+06 1.010E+07 8.390E+06 W-187 2.350E+06 2.350E+06 2.350E+06 2.350E+06 2.350E+06 2.350E+06 2.730E+06 2.350E+06 NP-239 1.710E+06 1.710E+06 1.710E+06 1.710E+06 1.71 OE+06 1.710E+06 1.980E+06 1.710E+06 Appendix G Ri Adult Ground Plane Deposition - Page 3 of 3

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX H R1 Teen Dose Factors for use in'the Gaseous Dose Calculations Agegroup: TEEN Pathway: Grs/Cow/Milk (CMILK) Units: m 2 mrem/yr / jiCi/sec;

________- _ _mrem/yr / pCi/m 3 (H-3)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body H-3 0.000E+00 9.940E+02 9.940E+02 9.940E+02 9.940E+02 9.940E+02 0.000E+00 9.940E+02 C-14 4.860E+08 9.720E+07 9.720E+07 9.720E+07 9.720E+07 9.720E+07 0.OOOE+00 9.720E+07 NA-24 4.260E+06 4.260E+06 4.260E+06 4.260E+06 4.260E+06 4.260E+06 0.OOOE+00 4.260E+06 P-32 3.150E+10 1.950E+09 0.000E+00 0.OOOE+00 0.000E+00 2.650E+09 0.OOOE+00 1.220E+09 CR-51 0.OOOE+00 0.OOOE4-00 2.770E+04 1.090E+04 7.130E+04 8.390E+06 0.000E+00 4.990E+04 MN-54 0.OOOE+00 1.400E+07 0.000E+00 4;180E+06 0.000E+00 2.870E+07 0.000E+00 2.780E+06 MN-56 0.000E+00 7.250E-03 0.000E+00 9.180E-03 0.000E+00 4.770E-01 0.000E+00 1.290E-03 FE-55 4.450E+07 3.160E+07 0.000E+00 0.OOOE+00 2.000E+07 1.370E+07 0.OOOE+00 7.360E+06 FE-59 5.180E+07 1.210E+08 0.000E+00 0.000E+00 3.810E+07 2.860E+08 0.OOOE+00 4.670E+07 CO-58 0.OOOE+00 7.940E+06 0.OOOE+00 0.000E+00 0.OOOE+00 1.090E+08 0.OOOE+00 1.830E+07 CO-60 0.OOOE+00 2.780E+07 0.000E+00 0.OOOE+00 0.000E+00 3.620E+08 0.000E+00 6.260E+07 NI-63 1.180E+10 8.350E+08 0.OOOE+00 0.OOOE+00 0.000E+00 1.330E+08 0.OOOE+00 4.010E+08 NI-65 6.770E-01 8.650E-02 0.OOOE+00 0.OOOE+00 0.000E+00 4.690E+00 0.000E+00 3.940E-02 CU-64 0.OOOE+00 4.250E+04 0.OOOE+00 1.070E+05 0.000E+00 3.290E+06 0.000E+00 2.000E+04 ZN-65 2.11OE+09 7.320E+09 0.OOOE+00 4.680E+09 0.OOOE+00 3.100E+09 0.OOOE+00 3.410E+09 ZN-69 3.850E-12 7.330E-12 0.000E-00 4.790E-12 0.000E+00 1.350E- 11 0.000E+00 5.030E-13 BR-83 0.OOOE+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 O.OOOE+00 1.790E-01 BR-84 0.OOOE+00 0.000E+00 0.OOOE+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.880E-23 BR-85 0.000E+00 o.OOOE+00 0.000E+00 o.OOOE+OO 0.000E+00 0.000E+00 0.000E+00 0.OOOE+00 RB 0.OOOE+00 4;730E+09 0.000E+00 0.OOOE+00 0.000E+00 7.000E+08 0.000E+00 .2.220E+09 RB-88 0.000E+00 3.890E-45 0.000E+00 0.000E+00 0.000E+00 3.330E-52 0.000E+00 2.070E-45 RB-89 0.000E+00 7.660E-53 0.000E+00 0.OOOE+00 0.000E+00 1.1 70E-61 0.000E+00 5.420E-53 SR-89 2.670E+09 0.OOOE+00 0.000E+00 O.OOOE+00 0.000E+00 3.190E+08 0.OOOE+00 7.660E+07 SR-90 6.610E+10 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.000E+00 1.860E+09 0.000E+00 1.630E+10 SR-91 5.310E+04 0.000E+00 0.000E+00 0.OOOE+00 0.OOOE+00 2.410E+05 0.000E+00 2.110E+03 Appendix H Ri Teen Cow Milk - Page 1 of 3

0Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX H Ri Teen Dose Factors for use in the Gaseous Dose Calculations

.Agegroup: TEEN Pathway: Grs/Cow/Milk (CMILK) Units: m2 .mrem/yr / lCi/sec;

____-______ _.________. ___________ ___________ ___________ ____________ mrem/yr / itCi/m3 (H-3)

Nuc.ide Bone Liver Thyro.id Kidney LungGii S kin-  : Tota .Body SR-92 8.940E-01 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.280E+01 0.OOOE+00 3.810E-02 Y-90 1.300E+02 0.OOOE+00 0.000E+00 0.OOOE+00 0.000E+00 1.070E+06 0.000E+00 3.510E+00 Y-91 1.580E+04 0.OOOE+00 0.000E+00 0.000E+00 0.000E+00 6.480E+06 0.OOOE+00 4.240E+02 Y-91M 1.090E-19 0.000E+00 0.000E+00 0.000E+00 0.000E+00 5.170E-18 0.000E+00 4.180E-21 Y-92 1.030E-04 0.000E+00 0.000E+00 0.000E+00 0.000E+00 2.830E+00 0.000E+00 2.980E-06 Y-93 4.120E-01 0.OOOE+00 0.000E+00 0.000E+00 0.000E+00 1.260E+04 0.000E+00 I. 130E-02 ZR-95 1.650E+03 5.200E+02 0.000E+00 7.650E+02 0.000E+00 1.200E,+06 0.000E+00 3.580E+02 ZR-97 7.880E-01 1.560E-01 0.000E+00 2.370E-01 0.000E+00 4.220E+04 0.000t+00 7.190E-02 NB-95 1.410E+05 7.81 OE+04 0.OOOE+00 7.570E+04 0.OOOE+00 3.340E+08 0.OOOE+00 4.300E+04 MO-99 0.OOOE+00 4.470E+07 0.000E+00 1.020E+08 0.OOOE+00 8.010E+07 0.OOOE+00 8.530E+06 TC-99M 5.760E+00 1.610E+01 0.OOOE+00 2.390E+02 8.920E+00 1.050E+04 0.000E+00 2.080E+02 TC-101 4.740E-60 6.750E-60 0.OOOE+00 1.220E-58 4.1 1OE-60 1.150E-66 A0.000E+00 6.630E-59 RU-103 1.810E+03 0.OOOE+00 0.OOOE+00 61380E+03 O.OOOE+00 1.510E+05 0.000E+/-00 7.740E+02 RU-105 1.560E-03 0.OOOE+00 0.OOOE+00 1.970E-02 O.OOOE+00 1.260E+00 O.000E+00 6.070E-04 RU-106 3.750E+04 0.000E+00 0.000E+00 7.240E+04 0.000E+00 1.800E+06 0.000E+00 4.730E+03 AG-1 10M 9.630E+07 9.11OE+07 0.OOOE+00 1.740E+08 0.000E+00 2.560E+10 0.000E+00 5.540E+07 TE-125M 3.OOOE+07 1.080E+07 8.390E+06 0.OOOE+00 0.000E+00 8.860E+07 0.000E+00 4.020E+06 TE-127 1.210E+03 4.290E+02 8.350E+02 4.900E+03 0.000E+00 9.340E+04 0.000E+00 2.600E+02 TE- 127M 8.440E+07 2.990E+07 2.010E+07 3.420E+08 0.000E+00 2.100E+08 0.000E+00 1.000E+07 TE-129 5.200E-10 1.940E-10 3.720E-10 2.180E-09 0.OOOE+00 2.840E-09 0.OOOE+00 1.270E-10 TE-129M 1.100E+08 4.090E+07 3.550E+07 4.610E+08 0.OOOE+00 4.130E+08 0.000E+00 1.740E+07 TE-131 6.580E-33 2.710E-33 5.070E-33 2.880E-32 0.000E+00 5.400E-34 0.000E+00 2.060E-33 TE-131M 6.570E+05 _3.150E+05 4.740E+05 3.290E+06 0.OOOE+00 2.530E+07 0.OOOE+00 2.630E+05 TE-132 4.290E+06 2.720E+06 2.870E+06 2.610E+07 0.OOOE+00 8.610E+07 0.OOOE+00 2.560E+06 1-130 7.380E+05 2.140E+06 1.740E+08 3.290E+06 0.OOOE+00 1.640E+06 0.OOOE+00 8.530E+05 Appendix H Ri Teen Cow Milk - Page 2 of 3

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX H Ri Teen Dose Factors for use in the Gaseous Dose Calculations Agegroup: TEEN Pathway: Grs/Cow/Milk (CMILK) Units: m 2 mrem/yr / ptCi/sec; mrem/yr / JtCi/m3 (H-3)

Nuclide Bone Liver Thyroid. Kidney Lung Gilli -Skin TotalBod, 1-131' 5.370E+08 7.520E+08 2.190E+1I 1.290E+09 0.OOOE+00 1.490E+08 O.OOOE+00 4.040E+08 1-132 2.910E-01 7.620E-01 2.570E+01 1.200E+00 0.OOOE+00 3.320E-01 0.OOOE+00 2.740E-01 1-133' 7.070E+06 1.200E+07 1.670E+09 2.100E+07 0.OOOE+00 9.070E+06 0.000E+00 3.660E+06 1-134 3.580E-12 9.500E-12 1.580E-10 1.500E-11 0.OOOE+00 1.250E-13 0.OOOE+00 3.410E-12 1-135 2.280E+04 5.870E+04 3.780E+06 9.270E+04 0.OOOE+00 6.510E+04 0.OOOE+00 2.180E+04 CS-134 9.820E+09 2.310E+10 0.OOOE+00 7.340E+09 2.800E+09 2.870E+08 0.000E+00 1.070E+10 CS-136 4.480E+08 1.760E+09 0.OOOE+00 9.600E+08 1.510E+08 1.420E+08 0.OOOE+00 1.180E+09 CS-137 1.340E+10 1.780E+10 0.OOOE+00 6.060E+09 2.350E+09 2.530E+08 O.OOOE+00 6.200E+09 CS,-138 1.640E-23 3.150E-23 0.000E+00 2.330E-23 2.710E-24 1.430E-26 0.OOOE+00 1.580E-23 BA-139 8.170E-08 5.750E- I1 0.OOOE+00 5.420E- 11 3.960E-11 7.290E-07 0.000E+00 2.380E-09 BA-140 4.850E+07 5.950E+04 O.OOOE+00 2.020E+04 4.OOOE+04 7.480E+07 0.000E+00 3.130E+06 BA-141 7.520E-46 5.620E-49 0.OOOE+00 5.210E-49 3.850E-49 1.600E-51 0.OOOE+00 2.5 1OE-47 BA-142 4.790E-80 4.790E-83 0.OOOE+00 4.050E-83 3.190E-83 1.470E-91 0.000E+00 2.950E-81 LA-140 8.100E+00 3.980E+00 0.000E+60 O.OOOE+00 0.OOOE+00 2.290E+05 0.OOOE+00 1.060E+00 LA-142 3.360E-11 1.490E-11 0.OOOE+00 O.OOOE+00 0.OOOE+00 4.540E-07 O.OOOE+00 - 3.710E-12 CE-141 8.880E+03 5.930E+03 0.OOOE+00 2.790E+03 0.OOOE+00 1.700E+07 0.OOOE+00 6.810E+02 CE-143 7.640E+01 5.560E+04 0.OOOE+00 2.490E+01 0.OOOE+00 1.670E+06 0.OOOE+00 6.210E+00 CE-144 6.580E+05 2.720E+05 0.OOOE+00 1.630E+05 0.OOOE+00 1.660E+08 0.OOOE+00 3.540E+04 PR-143 2.900E+02 1.160E+02 0,OOOE+00 6.730E+01 0.OOOE+00 9.540E+05 O.OOOE+00 . 1.440E+O1 PR-144 1.080E-53 4.430E-54 0.OOOE+00 2.540E-54 0.OOOE+00 1.190E-56 0.OOOE+00 5.490E-55 ND-147 1.810E+02 1.970E+02 0.OOOE+00 1.160E+02 0.OOOE+00 7.11OE+05 0.OOOE+00 1.180E+01 W-187 1.190E+04 9.710E+03 0.OOOE+00 0.OOOE+00 0.OOOE+00 2.630E+06 0.OOOE+00 3.400E+03 NP-239 7.010E+00 6.610E-01 O.OOOE+00 2.070E+00 0.OOOE+00 1.060E+05 0.OOOE+00 3.670E-01 Appendix H Ri Teen Cow Milk - Page 3 of 3

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX H Ri Teen Dose Factors for use in the Gaseous Dose Calculations Agegro'up:, TEEN Pathway: Grs/Goat/Milk (GMILK) Units:, m 2*mrem/yr / gCi/see;

________ __________________mremlyr /JCi/m3 (H1-3)

- ucide - .Bone, Liver' Thyroid Kidneyý Lung Vil _Skin Totl H-3 0.OOOE+00 2.030E+03 2.030E+03 2.030E+03 2.030E+03 2.030E+03 0.OOOE+00 2.030E+03 C-14 4.860E+08 9.720E+07 9.720E+07 9.720E+07 9.720E+07 9.720E+07 0.OOOE+00 9.720E+07 NA-24 5.11 OE+05 5.11 OE+05 5.1-10E+05 5.110E+05 5.1 10E+/ 5.11OE+05 0.OOOE+00 5. 11OE+05 P-32 3.780E+10 2.34013+09 0.OOOE+00 0.OOOE+00 0.OOOE+00 31 8M+09 0.OOOE+00 1.470E+09 CR-51 0.OOOE+00 0.OOOE+00 3.330E+03 1.31013+03 8.550E+03 1.010E+06 0.000E+/-00 5.990E+03 MN-54 0.OOOE+00 1.680E+06 0.OOOE+00 5.020E+05 0.OOOE+00 3.450E+06 0.OOOE+00 3.340E+05 MIN-56 0.OOOE+00 8.700E-04 0.000E+00 1.100E-03 0.OOOE+00 5.73013-02 0.000E+00 1.550E-04 FE-55 5.790E+05 4.11 OE+05 0.00013+00 0.OOOE+00 2.600E+05 1.780E+05 0.OOOE+00 9.570E+04 FE-59 6.740E+05 1.57013+06 0.OOOE+00 0.OOOE+00 4.960E-ý05 33720E+06 0.OOOE+00 6.070E+05 CO-58 0.OOOE+00 9.52E+05 - 0.000E'+00 0.OOO13+00 0,00O.OE+00 1.310E+07 0.000E+00 2.190E+06 CO-60 0.OOOE+00 3.340E+i06 0.OOOE+00 0.OOOE+00 0.OOOE+00 4.350E+07 0.OOOE+/-00 7.520Et06 NI-63 1.420E+09 1:OOOE+08 0.OOOE+00 0.00013+00 0.OOOE+00 1.590E+07 O.000E+00 4.810E+07 NI-65 8.120E-02 L.04013-02 0.OOOE+00 0.OOOE+00 0.OOOE+00 5.630E-01 0.OOOE+00 4.730E-03 CU-64 0.OOOE+00 4.730E+03 0.OOOE+00 1.200E+04 0.OOOE+00 3.670E+05 0.OOOE+0O 2.230E+03 ZN-65 2.530E+08 8.780E+08 0.OOOE+00 5.620E+08 0.OOOE+00 3.2E0 .OOOE+00 4.100E+/-08 ZN-69 4.620E-13 8.800E-13 0.OOOE+00 5.750E-13 0.000E+00 .1.620E-12 0.OOOE+00 6.160E-14 BR-83 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.000E+00 0.OOOE+00 0.OOOE+00 0.OOOE+/-00 2.150E-02 BR-84 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 - .OOOE+00 0.OOOE+00 3..50E-24 BR-85 0.OOOE+00 0.OOOE+00 0,000E+00 0.OOOE+00 0.OOOE+00 0.000E+00 0.OOOE+00 0.OOOE-i00 RB-86 O-OOOE+00 5.670E+08 0.OOOE+00 0.OOOE+00 0.OOOE+00 8.400E+07 0.OOOE+00 2.670E+08 RB-88 0.OOOE+00 4.670E-46 0.OOOE+00 0.OOOE+00 0.OOOE+00 4.OOOE-53 0.OOOE+00 2.490E-46 RB-89 0.OOOE+00 9.190E-54 0.OOOE+00 0.OOOE+00 0.OOOE+/-00 1.410E-62 0.OOOE+00 6.500E-54 SR-89 5.62013+09 0.00O13+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 6.690E+08 0.OOOE+00 1.610E+08 SR-90 1.390E+11I 0.OOOE+00 0.OOOE+00 O.OOOE+00 0.000E+00 3.900E+/-09 0.OOOE+00 3.430E+10 SR-91 1.120E+05 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.000E+00 5.060E+05 0.OOOE+00 4.440E+03 Appendix H Ri Teen Goat Milk - Page 1 of 3

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX H Ri Teen Dose Factors for use in the Gaseous Dose Calculations Agegroup: TEEN Paithway: Grs/Goat/Milk (GMILK) Units: m 2.mrem/yr / pCi/sec;

, ___________  :::: ___________*: __ mrem/yr / tCi/m 3 (H-3)

Nucide -.- Bone Lier Thrid Kidney - L'un' Gilli Skin Tot-l-Body SR-92 1.880E+00 0.OOOE+00 0.OOOE+00 0.000E+00 0.OOOE+00 4.780E+01 0.OOOE+00 8.OOOE-02 Y-90 1.560E+01 0.OOOE+00 0.OOOE+00 0.000E+00 0.OOOE+00 1.290E+05 0.OOOE+00 4.210E-01 Y-91 1.900E+03 0.000E+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 7.770E+05 0.OOOE+00 5.080E+01 Y-91M 1.310E-20 0.OOOE+00 0.000E+00 0.OOOE+00 0.000E+00 6.200E-19 0.OOOE+00 5.020E-22 Y-92 1.240E-05 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 3.390E,01 0.OOOE+00 3.580E-07 Y-93 4.940E-02. 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 1.510E+03 0.OOOE+00 -1.360E-03 ZR-95 1.980E+02 6.250E+01 0.OOOE+00 9.180E+01 0.000E+00 1.440E+05 0.OOOE+00 4.300E+01 ZR-97 9.460E-02 1.870E-02 0.OOOE+00 2.840E-02 0.OOOE+00- 5.070E4-03 0.OOOE+00 8.620E-03 NB-95, 1.690E+04 9.370E+03 0.OOOE+00 9.080E+03 0.OOOE+00 4.010E+07 0.OOOE+00 5.160E+03.

MO-99 0.OOOE+00 5.370E÷06 0.OOOE+00 1.230E+07 0.OOOE+00 9.610E+06 0.OOOE#00 1.020E+06 TC-99M 6.910E-01 1.930E+00 0.OOOE+00 2.870E+01 1.070E+00 1.270E+03 0.OOOE+00 2.500E+01 TC-101 5.690E-61 8.100E-61 0.OOOE+00 1.460E-59. 4.930E-61 1.380E-67 0.OOOE+00 7.950E-60 RU-103 2.170E+02 0.000E+00 0.OOOE+00 7.660E+02 0.OOOE+00 1.810E+04 0.OOOE+00 9.290E+01 RU-105 1.880E-04 0.OOOE+00 0.OOOE+00 2.370E-03 0.000E+00 1.520E-01 0.OOOE+00 7.290E-05 RU-106 4.500E+03 0.OOOE+00 0.OOOE+00 8.680E+03 0.000E+00 2.160E+05 0.OOOE+00 5.670E+02 AG-110M 1.160E+07 1.090E+07 0.OOOE+00 2.080E+07 0.OOOE+00 3.070E+09 0.OOOE+00 6.650E+06 TE-125M 3.600E+06 1.300E+06 1.010E+06 0.OOOE+00 0.000E+00 1.060E+07 0.OOOE+00 4.820E+05 TE-i27 1.450E+02 5.150E+01 1.000E+02 5.880E+02 0.OOOE+00 1.120E+04 0.000E+00 3.120E+01 TE-127M .. 1.01E+07 3.590E+06 2.410E+06 . 4.100E+07 _. 0.OOOE+00 2.520E+07 0.OOOE+00 1.200E+06 TE-129 6.240E-11 2.330E-11 4.460E-11 2:620E- 10 0.OOOE+00 3.410E-10 0.OOOE+00 1.520E-11 TE-129M 1.320E+07 4.900E+06 4.260E+06 5.530E+07 0.OOOE+00 4.960E+07 0.OOOE+00 2.090E+06 TE-131 7.900E-34 3.260E-34 6.090E-34 3.450E-33 0.OOOE+00 6.480E-35 0.OOOE+00 2.470E-34 TE-131M 7.880E+04 3.780E+04 5.690E+04 3.940E+05 0.OOOE+00 3.030E+06 O.OOOE+00 3.150E+04 TE-132 5.150E+05 3.260E+05 3.440E+05 3.130E+06 0.OOOE+00 1.030E+07 0.OOOE+00 3.070E+05 11-130 8.860E+05 2.560E+06 2.090E+08 3.950E+06 0.OOOE+00 1.970E+06 0.OOOE+00 1.020E+06 Appendix H Ri Teen Goat Milk - Page 2 of 3

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX H R. Teen Dose Factors for use in the Gaseous Dose Calculations 2 mrem/yr / WtCi/sec; nm Agegroup: TEEN Pathway: Grs/Goat/Milk (GMILK) Units:

________ __________________mrem/yr I ~Ci/m3 (H-3)

Nudide BoBne Liver. Thyroid <Kidney Lung Gi!!iS Total Body 1-131 6.450E+08 9.030E+08 2.630E+11 1.550E+09 0.OOOE+00 1.790E+08 0.OOOE+00 4.850E+08 1-132 3.500E-01 9.150E-01 3.080E+01 1.440E+00 0.OOOE+00 3.980E-01 0.OOOE+00 3.280E-01 1-133 8;480E+06 1.440E+07 2.010E+09 2.520E+07 0.OOOE+00 1.090E+07 0.OOOE+00 4.390E+06 1-134 4.300E-12 1.140E-11 1.900E-10 1.800E-11 0.OOOE+00 1.500E-13 0.OOOE+00 4.090E-12 1-135 2.740E+04 7.040E+04 4.530E+06 1.11OE+05 0.OOOE+00 7.810E+04 0.OOOE+00 2.610E+04 CS-134 2.940E+10 6.930E+10 0.OOOE+00 2.200E+10 8.410E+09 8.620E+08 O.OOOE+00 3.220E+10 CS-136 1.340E+09 5.290E+09 0.OOOE+00 2.880E+09 4.540E+08 4.260E+08 0.OOOE+00 3.550E+09 CS-137 4.020E+10 5.340E+10 0.OOOE+00 1.820E+10 7.060E+09 7.600E+08 0.OOOE+00 1.860E+10 CS-138 4.920E-23 9.450E-23 0.OOOE+00 6.980E-23 8.120E-24 4.290E-26 0.OOOE+00 4.730E-23 BA-139 9.800E-09 6.900E-12 0.OOOE+00 6.500E-12 4.750E-12 8.750E-08 0.OOOE+00 2.860E-10 BA-140 5.820E+06 7.130E+03 0.OOOE+00 2.420E+03 4.800E+03 8.980E+06 0.OOOE+00 3.750E+05 BA-141 9.030E-47 6.740E-50 0.OOOE+00 6.260E-50 4.610E-50 1.920E-52 0.OOOE+00 3.010E-48 BA-142 5.750E-81 5.750E-84 0.000E+00 4.860E-84 3.820E-84 1.760E-92 *0.000E+00 3.540E-82 LA-140 9.720E-01 4.780E-01 0.OOOE+00 0.OOOE+00 0.000E+00 2.740E+04 0.OOOE+00 1.270E-01 LA-142 4.030E-12 1.790E-12 0.OOOE+00 O.000E+00 0.000E+00 5.440E-08 0.OOOE+00 4.450E-13 CE-141 1.070E+03 7.120E+02 0.000E+00 3.350E+02 0.OOOE+00 2.040E+06 0.000E+00 8.170E+01 CE-143 9.170E+00 6.670E+03 0.OOOE+00 2.990E+00 0.OOOE+00 2.OOOE+05 0.000E+00 7.450E-01 CE-144 7.900E+04 3.270E+04 0.OOOE+00 1.950E+04 0.OOOE+00 1.990E+07 0.OOOE+00 4.240E+03 PR-143 3.480E+01 1.390E+01 0.OOOE+00 8.080E+00 0.OOOE+00 i.150E+05 0.000E+00 1.730E+00 PR-144 1.300E-54 5.320E-55 0.OOOE+00 3.050E-55 0.OOOE+00 1.430E-57 0.OOOE+00 6.590E-56 ND-147 2.170E+01 2.360E+01 0.OOOE+00 1.390E+01 0.OOOE+00 8.530E+04 0.OOOE+00 1.420E+00 W-187 1.430E+03 1.170E+03 0.000E+00 0.OOOE+00 0.OOOE+00 3.150E+05 0.000E+00 4.080E+02 NP-239 8.410E-01 7.930E-02 0.OOOE+00 2.490E-01 0.000E+00 1.280E+04 0.OOOE+00 4.410E-02 Appendix H Ri Teen Goat Milk - Page 3 of 3

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 "

APPENDIX H Ri Teen Dose Factors for use in the Gaseous Dose Calculations Agegroup: TEEN Pathwvay: GrslCow/Meat (CMEAT) ..Unitls:. m 2 mrem/yr / pWilsec;

_________ _________mrem/yr IjCi/m' (H1-3)

Nu-clide, Bone :_Liver Thyroid Kidney Lung Gilli Skin Total Bdy H-3 0.OOOE+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+081 4.080E+07 4.080E+07 4.080E+07 4.080E+074.8E0 .000E+/-00 4.080E+07 NA'-24 1.080E-03 1.080E-03 1.080E-03 1.080E.-03 1.080E-03 1.080E-03 0.OOOE+00 1.080E-03 P-32 3.930E+09 2.440E+08 0.000E+00 0.OOOE+00 0.OOOE+00 3.3 10E+0 8 0.OOOE+00 1.530E+i08 CR-51 0.000E+00 0.OOOE+00 3.130E+03 1.240E+03 9.050E+03 9.470E+/-05 0.OOOE+00 5.640E+03 MvN-54 0.000E+/-00 7.OOOE+06 0.OOOE+00 2.090E+/-06 0.OOOE+00 1.440E+07,. 0.OOOE+00 1.390E+06 M~N-561 0.OOOE+00 1.070E-53 0.OOOE+00 1.360E-53 0.OOOE+00 7.070E-52 0.OOOE+00 1.910E-54 FE-55 2.380E+08 1.690E+08 0.OOOE-i00 0..OOOE+00 1.070E+08 7.3 10E+07 0.OOOE+00 3.940E+07 FE-59 2.120E+08 4.950E+08 0.OOOE+00 0.OOOE+00 1.560E+08 1.170E+09 0.000E+00 1.910E+08 CO-58 0.OOOE+00 1.410E+/-07 0.000E+00 0.OOOE+00 0.OOOE+00 1.940E+08 0.000E+00 3.240E+07 CO-60 0.OOOE+00 5.830E+07 0.OOOE+00 0.OOOE+00 0.000E+00 7.600E+08. 0.OOOE+00 1.3 10E+08 N1-63' 1.520E+10 1.076E+09 0.000E+00 O.OOOE+00 0.OOOE+00 1.710E+/-08 0.OOOE+00 5.150E+08 NI-65 1.880E-52 2.4 10E-53 0.000E+00 0.OOOE+00 0.000E+00 1.300E-5 1 0.OOOE+00 1.1 OOE-53 CU-64 0.OOOE+00 2.21 OE-07 0.OOOE+00 5.600E-07 0.000E+00 1.720E-05 0.OOOE+00 1.040E-07 ZN-65 2.50. E+08 8.690E+08 0.OOOE+00 5,560E+08 0.000E+00 3.680E+08 0.OOOE-'00 4.050E+08 ZN-69 0.000E+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 BR-83 0.OOOE+00 0.00013+00 0.OOOE+00 0.000E+00 0.OOOE+00 - 0.OOOE+00 0.OOOE+00 5.07013-57 BR-84 0.0m0 .OOOE+000.000 E+00 0.000 0.0E0 13+00 .OOOE+00 0.OOOE+00 0.000E+00 0.OOOE+00

ýBR-85 0OO+0 000+0 _ .0E0 0.00QE0 000+0- .0E+00 0.000E+000 _ 0000E+00 RB-86 0.OOOE+00 4.070E+08 0.OOOE+00 0.OOOE+00 0.000E+00 6.020E+07 0.000E+00 1.910E+08 RB-88 0.OOOE+00 0.OOOE+00 0.00013+00 0.OOOE+00 0.OOOE+00 0.000E+00 0.000E+00 0.OOOE+/-00 RB-89 0.OOO13+00 0.OOOE+00 0.OOOE+/-00 0.OOOE+00 0.000E+00 0.000E+00 0.OOOE+00 0.OOOE+00 SR-89 2.550E+08 0.OOOE+00 0.000E+00 0.OOOE+00 0.OOOE+00 3.030E+/-07 0.OOOE+00 7.290E+06 SR-W0 8.050E+09 .000E+00 0.OOOE+00 0.000E+00 0-000E+00 2.260E+08 0.OOOE+0O 1.990E+09 SR-9 1 1.280E-160 .000E+00 0.000E+00 0.OOOE+00 0.000E+00 5.800E- 10 0.000E+00 5.090E- 12

-0 AppendixH Ri Teen Cow Meat- Page 1 of 3

0Oconee Nuclear Station 0

January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX H R, Teen Dose Factors for use in the Gaseous Dose Calculations Agegroup: TEEN Pathway:.* Grs/Cow/Meat-(CMEAT) Unnits.: m 2.mrem/yr / p.Ci/sec;

_____ _* __:_ _ _ _..........._ _ mrem/yr / Ci/m 3 (H-3).

Nuclide Bone Liver Thyroid Kidney Lung Gili. Skin Total Body SR-92 9.880E-50 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 2.520E-48 0.OOOE+00 4.210E-51 Y-90 9.060E+01 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 7.470E+05 0.OOOE+00 2.440E+00 Y-91 9.540E+05 0.OOOE+00 0.OOOE+00 0.000E+00 0.OOOE+00 3.910E+08 0.OOOE+00 2.560E+04 Y-91M 0.OOOE+00 0.000E+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 Y-92 1.280E-39 0.OOOE+00 0.OOOE+00 O.OOOE+00 0.OOOE+00 3.520E-35 0.OOOE+00 3.710E-41 Y-93 3.960E-12 0.OOOE+00 0.OOOE+00 O.OOOE+00 0.OOOE+00 1.210E-07 0.OOOE+00 1.090E-13 ZR-95 1.500E+06 4.730E+05 O.OOOE+00 6.950E+05 0.OOOE+00 1.090E+09 0.OOOE+00 3.250E+05 ZR-97 1.720E-05 3.410E-06 O.OOOE+00 5.170E-06 0.OOOE+00 9.230E-01 0.OOOE+00 1.570E-06 NB-95 1.790E+06 9.950E+05 0.OOOE+00 9.650E+05 0.OOOE+00 4.260E+09 0.OOOE+00 5.480E+05 MO-99 0.OOOE+00 8.270E+04 0.OOOE+00 1.890E+05 0.OOOE+00 1.480E+05 0.OOOE+00 1.580E+04 TC-99M 3.530E-21 9.850E-21 0.OOOE+00 1.470E-19 5.470E-21 6.470E-18 0.000E+00 1.280E-19 TC-101 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.000E+06 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 RU-103 8.570E+07 0.OOOE+00 0.OOOE+00 3.020E+08 0.OOOE+00 7. 1 60E+09 .0.OOOE+00 3.660E+07 RU-105 4.830E-28 0.OOOE+00 0.OOOE+00 6.090E-27 0.OOOE+00 3.900E-25 0.OOOE+00 1.880E-28 RU-106 2.360E+09 0.OOOE+00 0.OOOE+00 4.550E+09 0.OOOE+00 1.130E+11 0.OOOE+00 2.970E+08 AG- 1OM 5.060E+06 4.790E+06 0.OOOE+00 9.130E+06 0.OOOE+00 1.340E+09 0.OOOE+00 2.910E+06 TE-125M 3.030E+08 1.090E+08 8.470E+07 O.OOOE+00 0.OOOE+00 8.940E+08 0.000E+00 4.050E+07 TE-127 1.800E-10 6.380E-11 1.240E-10 7.290E-10 0.OOOE+00 1.390E-08 0.OOOE+00 3.870E-11 TE-127M 9.410E+08 3.340E+08 2.240E+08 3.820E+09 0.000E+00 2.350E+09 0.OOOE+00 1.120E+08 TE- 129 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.000E+00 0.OOOE+00 TE-129M 9.500E+08 3.530E+08 3.070E+08 3.970E+09 0.000E+00 3.570E+09 0.OOOE+00 1.500E+08 TE-131 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.000E+00 TE-131M 3.760E+02 1.800E+02 2.710E+02 1.880E+03 0.000E+00 1.450E+04 0.OOOE+00 1.500E+02 TE-132 1.160E+06 7.360E+05 7.750E+05 7.060E+06 0.OOOE+00 2.330E+07 0.OOOE+00 6.920E+05 1-130 1.700E-06 4.910E-06 4.OOOE-04 7.560E-06 0.OOOE+00 3.770E-06 0.OOOE+00 1.960E-06 Appendix H Ri Teen Cow Meat - Page 2 of 3

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX H R, Teen Dose Factors for use in the Gaseous Dose Calculations Agegroup: TEEN Pathway: Grs/Cow/Meat (CMEAT) Units: m 2.mrem/yr / gCi/sec;

.... mrem/yr / tCi/m 3 (H-3)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body 1-131 8.920E+06 1.250E+07 3.650E+09 2.150E+07 0.OOOE+00 2.470E+06 0.OOE+00 6.710E+06 1-132 5.660E-59 1.480E-58 4.990E-57 2.330E-58 0.OOOE+00 6.450E-59 0.OOOE+00 5.320E-59 1-133 3.050E-01 5.180E-01 7.230E+01 9.090E-01 0.OOOE+00 3.920E-01 0.OOOE+00 1.580E-01 1-134 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 1-135 3.600E-17 9.260E-17 5.960E-15 1.460E-16 0.OOOE+00 1.030E-16 0.OOOE+00 3.430E-17 CS-134 5.230E+08 1.230E+09 0.OOOE+00 3.910E+08 1.490E+08 1.530E+07 0.OOOE+00 5.710E+08 CS-136 9.400E+06 3.700E+07 0.OOOE+00 2.010E+07 3.170E+06 2.980E+06 0.OOOE+00 2.480E+07 CS-137 7.240E+08 9.630E+08 0.OOOE+00 3.280E+08 1.270E+08 1.370E+07 0.OOOE+00 3.360E+08 CS-138 0.OOOE+00 0.OOOE+00 0.OOOE+00 O.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 BA-139 0.OOOE+00 0.OOOE+00 0.000E+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.000E+00 0.OOOE+00 BA-140 2.380E+07 2.910E+04 0.OOOE+00 9.870E+03 1.960E+04 3.660E+07 0.OOOE+00 1.530E+06 BA- 141 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.000E+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 BA-142 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 LA-140 3.050E-02 1.500E-02 0.OOOE+00 0.OOOE+00 0.OOOE+00 8.610E+02 0.OOOE+00 3.990E-03 LA-142 2.870E-92. 1.:280E-92 0.OOOE+00 0.OOOE+00 0.OOOE+00 3.880E-88 0.OOOE+00 3.180E-93 CE-141 1.180E+04 7.870E+03 0.OOOE+00 3.710E+03 0.OOOE+00 2.250E+07 0.000E+00 9.040E+02 C*-143 1.690E-02 1.230E+01 0.000E+00 5.510E-03 0.000E+00 3.690E+02. 0.000E+00 1.370E-03 CEI144 1.230E+06 5.080E+05 0.000E+00. 3.040E+05 0.OOOE+00 3.090E+08 0.OOOE+00 6.600E+04 PR-143 1.760E+04 7.040E+03 0.OOOE+00 .090E+03 0.000E+00 5.800E+07 . .OOOE+00 8.780E+02 PR-144 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.000E+00 0.OOOE+00 0.OOOE+00 ND- 147 6.230E+03 6.770E+03 0.OOOE+00 3.980E+03 0.00013+00 2.440E+07 0.OOOE+00 4.060E+02 W-187 1.730E-02 1.410E-02 0.000E+00 0.OOOE+00 0.OOOE+00 3.820E+00 0.000E+00 4.940E-03 NP-239 2.260E-01 2.140E-02 0.OOOE+00 6.700E-02 0.OOOE+00 3.440E+03 0.OOOE+00 1.190E-02 Appendix H Ri Teen Cow Meat - Page 3 of 3

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX H Ri Teen Dose Factors for use in the Gaseous Dose Calculations Agegroup: TEEN Pathway: Vegetation (VEG) Units:InmZmrem/yr / tCi/sec;

_-_______ ___________________ ___-__ __ mrem/yr / ui/mr (H-3) 3 Nuclide Bone Liver Thyroid kidney Lung - Gilli Skin I TotlBody, H-3 0.OOOE+00 2.590E+03 2.590E+03 2.590E+03 2.590E+03 2.590E+03 0.OOOE+00 2.590E+03 C-14 3.690E+08 7.380E+07 7.380E+07 7.380E+07 7.380E+07 7.380E+07 0.OOOE+00 7.380E+07 NA-24 2.390E+05 2.390E+05 2.390E+05 2.390E+05 2.390E+05 2.390E+05 0.OOOE+00 2.390E+05 P-32 1.610E+09 9.970E+07 0.000E+00 0.OOOE+00 0.000E+00 *1.350E+08 0.OOOE+00 6.240E+07 CR-51 0.OOOE+00 0.OOOE+00 3.430E+04 1;350E+04 8.810E+04 1.040E+07 0.OOOE+00 6.170E+04 MN-54 0.OOOE+00 4.540E+08 0.000E+00 1.360E+08': 0.000E+00 9.320E+08 0.00OE-O00 9.010E+07 MN-56 0.OOOE+00 1.420E+01 0.OOOE+00 1.800E+01 0.OOOE+00 9.360E+/-02 0.OOOE+00 2.530E+00 FE-55 3.260E+08 2.310E+08 0.OOOE+00 O.OOOE+00. 1.470E+08  !.000E+08 0.OOOE+00 5.390E+07 FE-59 1;790E+08 4.190E+08 0.OOOE+00 0.OOOE+00 1.320E+08 9.900E+08 0.OOOE+00 1.620E+08 CO-58 0.OOOE+00 4.360E+07 0.OOOE+00 O.OOOE+00 0.000E+00 6.010E+08 0.OOOE+00 1.000E+08 CO-60 0.OOOE+00 2.490E+08 0.OOOE+00 0.OOOE+00 0.000E+00 3.240E+09 0.000E+00 5.600E+08 NI-63 1.610E+10 1.130E+09 O.OOOE+00 0.OOOE+00 0.OOOE+00 1.810E+08 0.OOOE+00 5.450E+/-08 NI-65 5.720E+01 7.310E+/-00 0.000E+00 0.OOOE+00 0.000E+00 3.970E+02 0.OOOE+00 3.330E+00 CU-64 0.000E+00 8.340E+03 0.OOOE+00 2.11OE+04 0.000E+00 6.470E+05 0.OOOE+00 3.920E+-03 ZN-65 4.240E+08 1.470E+09 0.OOOE+00 9.420E+08 O.000E+00 6.230E+08 0.OOOE+/-00 6.870E+08 ZN-69 5.140E-06 9.800E-06 0.OOOE+00 6.400E-06 0.000E-00 1.810E-05 0.OOOE+00 6.860E-07 BR-83 0.000E+00 0.000E+00 0.OOOE+00 O.OOOE+00 0.000E+00 0.OOOE+00 0.000E+00 2.910E+/-00.

BR-84 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 . 0 0.00E+00 0.000E+00 2.250E-11 BR-85 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 RB-86 0.OOOE+00 2.740E-08 0.OOOE+00 0.000E+00 0.OOOE+/-00 4.050E+07 0.OOOE+00 1.290E+08 RB-88 0.OOOE+00 3.170E-22 0.OOOE+00 0.OOOE+00 0.000E+00 2.720E-29 0.OOOE+00 1.690E-22 RB-89 0.OOOE+00 3.500E-26 0.000E+00 0.OOOE+00 - 0.000E+00 5.360E-35 0.000E+00 2.470E-26 SR-89 1.510E+10 0.000E+00 0.000E+00 0.OOOE+00 0.000E+00 1.800E+09 0.OOOE+00 4.340E+08 SR-90 7.510E+11 O.OOOE+00 0.OOOE+00 0.OOOE+00 0.000E+00 2.110E+10 0.OOOE+00 1.850E+11 SR-91 2.850E+05 0.OOOE+00 0.000E+00 O.OOOE+00 0.000E+00 1.290E+06 0.OOOE+00 1.130E+04 Appendix H Ri Teen Vegetation - Page 1 of 3

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX H R

ml Teen fln~e Factors for use in the Gaseous Dose Calculations Teen.....

R.1 Agegrupi: TEEN Pathway: Vegetation (VEG) - Units:! m2 "mrem/yr / gCi/sec;

____ _mrem/yr / lCi/m3 (H-3)

-NUclide :' Bone Liver Thyroid Kidney Lung Gilli. Skin Total Body:

SR-92 3.970E+02 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 1.010E+04 0.OOOE+00 1.690E+01 Y-90 1.240E+04 0.000E+00 0.OOOE+00 O.OOOE+00 0.OOOE+00 1.020E+08 0.OOOE+00 3.350E+02 Y-91 7.840E+06 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 3.210E+09 0.OOOE+00 2.100E+05 Y-91M 4.860E-09 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 2.290E-07 0.OOOE+00 1.860E-10 Y-92 8.600E-01 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00' 2.360E+04 0.000E+00 2.490E-02 Y-93 1.590E+02 O.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 4.860E+06 0.OOOE+00 4.360E+00 ZR-95 1.720E+06 5.430E+05 0.OOOE+00 7.980E+05 0.OOOE+00 1.250E+09 0.OOOE+00 3.730E+05 ZR-97 3.120E+02 6.180E+01 0.OOOE+00 9.370E+01 0.OOOE+00 1.670E+07 0.OOOE+00 2.850E-01 NB-95 1.920E+05 1.070E+05 0.OOOE+00 1.030E+05 0.OOOE+00 4.560E+08 0.OOOE+00 5.870E+04 MO99 0.OOOE+00 5.650E+06 0.OOOE+00. 1.290E+07 0.OOOE+00 1.010E+07 0.OOOE+00 1.080E+06 TC-99M 2.740E+00 7.630E+00 0.OOOE+00 1.140E+02 4.240E+00 5.010E+03 0.000E+00 9.890E+01 TC-101 7.640E-31 1.090E-30 0.OOOE+00 1.970E-29 6.620E-31 1.860E-37 0.OOOE+00 1.070E-29 RU-103 6.820E+06. 0.OOOE+00 0.OOOE+00 2.400E+07 0.OOOE+00 5.700E+08 0.OOOE+00 2.920E+06 RU-105 5.OOOE+01 0.OOOE+00 0.OOOE+00 6.310E+02 0.000E+00 4.040E+04 0.OOOE+00 1.940E+01 RU-106 3.100E+08 0.OOOE+/-00 0.OOOE+00 5.970E+08 0.OOOE+00 1.480E+10 0.000E+00 3.900E+07 AG-110M 1.520E+07 1.430E+07 0.OOOE+00 2.740E+07 0.000E+00 4.030E+09 0.000E+60 8.720E+06 TE-125M 1.480E+08 5.340E+07 4.140E+07 0.OOOE+00 O.OOOE+00 4.370E+08 0.000E+00 1.980E+07 TE-127 5.330E+03 1.890E+03 3.6°80E+03 2.160E+04 0.000E+00 4.120E+05 0.000E+00 1.150E+03 JTE-127M -.- 5.510E+/-08 1.960E+08 I 1.310E+/-08 2.240E+09 - .OOOE+00 1.370E+09 0.OOOE+00 6.560E+07 TE-129 7.140E-04 2.660E-04 5.100E-04 3.OOOE-03 0.OOOE+00 3.910E-03 0.OOOE+00 1.740E-04 TE-129M 3.620E+08 1.340E+08 1.170E+08 1.510E+09 0.OOOE+00 1.360E+09 0.OOOE+00 5.730E+07 TE-131 1.390E-15 5.750E416 1.070E-15 6.100E-15 0.OOOE+00 1.140E-16' 0.OOOE+00 4.360E-16 TE-131M 8.440E+05 4.050E+05 6.090E+05 4.220E+06 0.OOOE+00 3.250E+07 0.OOOE+00 3.380E+05 TE-132 3.910E+06 2.470E+06 2.610E+06 2.370E+07 0.OOOE+00 7.840E+07 0.OOOE+00 2.330E+06 1-130 3.510E+05 1.010E+06 8.280E+07 1.560E+06 0.0OOE+00 7.800E+05 0.OOOE+00 4.050E+05 Appendix H Ri Teen Vegetation - Page 2 of 3

Oconee Nuclear Station 9

January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX H R. Teen Dose Factors for use in the Gaseous Dose Calculations Agegroup: TEEN Pathway: Vegetation (VEG) Units: m2 mrem/yr / WxCi/sec;

_________________ ________ ________ ________ _________mrem/yr / jii/m 3 (1-3)-

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total!Body 1-131 7.690E+07 1.080E+08 3.140E+10 1.850E+08 0.OOOE+00 2.130E+07 0.OOOE+00 5.780E+07 1-132 5.190E+01 1.360E+02 4.580E+03 2.140E+02 0.000E+00 5.920E+01 0.000E+00 4.880E+01 1-133 1.940E+06 3.290E+06 4.590E+08 5.760E+06 0.OOOE+00 2.490E+06 0.OOOE+00 1.000E+06 1-134 8.720E-05 2.310E-04 3.850E-03 3.640E-04 0.000E+00 3.050E-06 0.OOOE+00 8.310E-05 1-135 3.520E+04 9.070E+04 5.830E+06 1.430E+05 0.000E+00 1.000E+05 0.OOOE+00 3.360E+04 CS-134 7.1OOE+09 1.670E+10 0.OOOE+00 5.310E+09 2.030E+09 2.080E+08 0.OOOE+00 7.750E+09 CS-136 4.370E+07 1.720E+08 0.OOOE+00 9.370E+07 1.480E+07 1.380E+07 0.006E+00 1.160E+08 CS-137 1.010E+10 1.350E4-10 0.OOOE+00 4.590E+09 1.780E+09 1.920E+08 0.OOOE+00 4.690E+09 CS-138 3.610E-1 1 6.940E-1 1 0.000E+00 5.120E-1 1 5.960E-12 3.150E-14 0.OOOE+00 3.470E-1 1 BA-139 2.690E-02 1.890E-05 0.OOOE+00 1.780E-05 1.300E-05 2.400E-01 0.OOOE+00 7.830E-04 BA-140 1.380E+08 1.690E+05 0.OOOE+00 5.740E+04 1.140E+05 2.130E+08 0.OOOE+00 8.900E+06 BA-141 1.080E-21 8.040E-25 0.OOOE+00 7.460E-25 5.500E-25 2.290E-27 0.000E+00 3.590E-23 BA-142 5.490E-39 5.490E-42 0.OOOE+00 4.640E-42 .3.650E-42 1.680E-50 0.OOOE+00 3.380E-40 LA-140 1.810E+03 8.880E+02

  • 0.000E+00 0.OOOE+00 0.OOOE+00 5.100E+07 0.OOOE+00 2.360E+02 LA-142 1.850E-04 8.240E-05 0.OOOE+00 0.OOOE+00 0.000E+00 2.510E+00 0.OOOE+00 2.050E-05 CE-141 2.830E+05 1.890E+05 0.OOOE+00 8.890E+04 0.OOOE+00 5.400E+08 0.OOOE+00 2.170E+04 CE-143 9.330E+02 6.790E+05 0.OOOE+00 3.040E+02 0.OOOE+00 2.040E+07 6.000E+00 7.580E+/-01 CE-144 5.270E+07 2.180E-+07 0.OOOE+00 1.300E+07 0.000E+00 1.330E+10 0.OOOE+00 2.830E+06 PR-143 7.OOOE+04 2.800E+04 0.OOOE+00 1.630E+04 0.000E+00 2.300E+08 0.OOOE+00 3.490E+03 PR-144 2.900E-26 1.190E-26 0.OOOE+00 6.800E-27 0.OOOE+00 3.190E-29 0.OOOE+00 1.470E-27 ND-147 3.620E+04 3.940E+04 0.OOOE+00 2.3 1OE+04 0.OOOE+00 1.420E+08 0.OOOE+00 2.360E+03 W-187 3.540E+04 2.880E+04 0.OOOE+00 0.OOOE+00 0.OOOE+00 7.800E+06 0.000E+00 1.010E+04 NP-239 1.390E+03 1.310E+02 0.OOOE+00 4.100E+02 0.OOOE+00 2.100E+07 0.OOOE+00 7.260E+01 Appendix H Ri Teen Vegetation - Page 3 of 3

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) .Revision 49 APPENDIX H Rj Teen Dose Factors for use in the Gaseous Dose Calculations Agegroup: TEEN Pathwayi.:, Inhalation (INHL) Units: mrem/yr / tiCi/m3 Nuclide Bone Liver. Thyroid Kidney Lung Gilli Skin TotalBody H 0.OOOE+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.OOOE+00 4.870E+03 NA-24 1.380E+04 1.380E+04 1.380E+04 1.380E+04 1.380E+04 1.380E+04 0.OOOE+00 1.380E+04 P-32 1.890E+06 1.100E+05 0.OOOE+00 0.000E+00 0.000E+00 9.280E+04 0.000E+00- 7.160E+04 CR-51 0.OOOE+00 0.OOOE+00 7.500E+01 3.070E+01 2.100E+04 3.OOOE+03 0.OOOE+00 1.350E+02 MN-54 0.OOOE+00 5.11OE+04 0.OOOE+00 1.270E+04 1.980E+06 6.680E+04 0.OOOE+00 8.400E+03 MN-56. 0.OOOE+00 1.700E+00 0.OOOE+00 1.790E+00 1.520E+04 5.740E+04 0.OOOE+00 2.520E-01 FE-55 3.340E+04 2.380E+04 0.OOOE+00 O.OOOE+00 1.240E+05 6.390E+03 0.OOOE+00 5.540E+03.

TE-59 1.590E+04 3.700E+04 0.OOOE+00 O.OOOE+00 1.530E+06 1.780E+05 6.000E+00 1.430E+04

'CO-58ý 0.OOOE+00 2.070E+03 0.OOOE+00 0.OOOE+00 1.340E+06 9.520E+04 0.OOOE+00 2.780E+03 CO-60 0.OOOE+00 1.510E+04 0.OOOE+00 0.OOOE+00 8.720E+06. 2.590E+05. 0.OOOE+00 1.980E+04 NI-63 5.800E+05 4.340E+04 0.OOOE+00 0.OOOE+00 3.070E+05 1.420E+04 0.OOOE+00 1.980E+04 NI-65 2.180E+00 2.930E-01 0.OOOE+00 0.OOOE+00 9.360E+03 3.670E+04 0.OOOE+00 1.270E-01 CU-64 0.OOOE+00 2.030E+00 0.OOOE+00 6.410E+00 1.11OE+04 6.140E+04 0.OOOE+00 8.480E-01 ZN-65 3.860E+04 1.340E+05. 0.OOOE+00 8.640E+04 1.240E+06. 4.660E+04 0.OOOE+00 6.240E+04 ZN-69 4.830E-02 9.200E-02 0.OOOE+00 6.020E-02 1.580E+03 2.850E+02 0.600E+00 6.460E-03 BR-83 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 3.440E+02 "BR-84 0.OOOE+00 0.OOOE+00 0.OOOE+00 O.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 4.330E+02 BR-85 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 1.830E+01 RB-86 0.000E+00 1.900+05 O.OOOE+00 0.OO0E+00 0.OOOE+00 1.770E;04 0.000 -00 8.400E 0-04' RB-88 0.00OE+00 5.460E+02 0,OOOE+00 0.OOOE+00 0.OOOE+00 2.920E-05 0.000E+00 2.720E+02 RB-89 0.OOOE+00 3.520E+02 0.000E+00 0.OOOE+00 0.OOOE+00 3.380E-07 0.OOOE+00 2.330E+02 SR-89 4.340E+05 0.OOOE+00 0.OOOE+00 0.OOOE+00 2.420E+06 3.710E+05 0.000E+00 1.250E+04 SR-90 1.080E+08 O.OOOE+00 0.OOOE+00 0.OOOE+00 1.650E+07 7.650E+05 0.OOOE+00 6.680E+06 SR-91 8.800E+01 0.OOOE+00 0.000E+00 0.OOOE+00 6.070E+04 2.590E+05 0.OOOE+00 3.510E+00 Appendix H Ri Teen Inhalation - Page 1 of 3

Oconee Nuclear Station 9

January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX H Ri Teen Dose Factors for use in the Gaseous Dose Calculations Agegroup: TEEN .,Pathway:, Inhalation (INHL) Units: mrem/yr / tCi/m3 Nuclide Bone Liver Thyroid Kidney_ .',:Lunfig 0Gili Skin Total Body SR-92 9.520E+00 0.000E+00 0.OOOE+00 0.000E+00 2.740E+04 1.190E+05 0.OOOE+00 4.060E-01 Y-90 2.980E+03 0.OOOE+00 0.000E+00 0.OOOE+00 2.930E+05 5.590E+05 0.OOOE+00 8.OOOE+01 Y-91 6.610E+05 0.OOOE+00 0.OOOE+00 0.OOOE+00 2.940E+06 4.090E+05 0.OOOE+00 1.770E+04 Y-91M 3.700E-01 0.OOOE+00 0.000E+00 0.OOOE+00 3.200E+03 3.020E+01 0.OOOE+00 1.420E-02 Y-92 1.470E+01 0.OOOE+00 0.OOOE+00 0.OOOE+00 2.680E+04 1.650E+05 0.000E+00 4.290E-01 Y-93 1.350E+02 0.OOOE+00 0.000E+00 0.OOOE+00 8.320E+04 5.790E+05 0.OOOE+00 3.720E+00 ZR-95 1.460E+05 -4.580E+04 - 0.OOOE+00 6.740E+04 2.690E+06 1.490E+05 0.OOOE+00 3.150E+04 ZR-97 1.380E+02 2.720E+01 0.OOOE+00 4.120E+01 1.300E+05 6.300E+05 0.OOOE+00 1.260E+01 NB-95 1.860E+04 1.030E+04 0.OOOE+00 1.000E+04 7.510E+05 9.680E+04 0.OOOE+00 5.660E+03 MO-99 0.OOOE+00 1.690E+02 0.OOOE+00 4.11OE+02 1.540E+05 2.690E+05 0.OOOE+00 3.220Et01 TC-99M 1.380E-03 3.860E-03 0.OOOE+00 5.760E-02 1.150E+03 6.130E+03 0.OOOE+00 4.990E-02 TC-101 5.920E-05 8.400E-05 0.OOOE+00 1.520E-03 6.670E+02 8.720E-07 0.OOOE+00 8.240E-04 RU-103 2.100E+03 0.OOOE+00 0.000E+00 7.430E+03 7.830E+05 1.090E+05 0.OOOE+00 8.960E+02 RU-105 1.120E+00 0.OOOE+00 0.OOOE+00 1.410E+00 1.820E+04 9.040E+04 0.OOOE+00 4.340E-01 RU- 106 9.840E+04 0.OOOE+00 0.OOOE+00 1.900E+05 1.610E+07 9.600E+05 0.OOOE+00 1.240E+04 AG-110M 1.380E+04 1.310E+04 0.OOOE+00 2.500E+04 6.750E+06 2.730E+05 0.OOOE+00 7.990E+03 TE-125M 4.880E+03 2.240E+03 1.400E+03 0.000E+00 5.360E+05 7.500E+04 0.000E+00 6.670E+02 TE- 127 2.010E+00 9.120E-0I 1.420E+00 7.280E+00 1.120E+04 8.080E+04 0.OOOE+00 4.420E-01 TE-127M 1.800E+04 8.160E+03 4.380E+03 6.540E+04 1.660E+06 1.590E+05 0.000E+00 2.180E+03 TE-129 7.100E-02 3.380E-02 5.180E-02 2.660E-01 3.300E+03 1.620E+03 0.OOOE+00 1.760E-02 TE-129M 1.390E+04 6.580E+03 4.580E+03 5.190E+04 1.980E+06 4.050E+05 0.OOOE+00 2.250E+03 TE- 131 1.580E-02 8.320E-03 1.240E-02 6.180E-02 2.340E+03 1.510E+01 0.OOOE+00 5.040E-03 TE-131M 9.840E+01 6.010E+01 7.250E+01 4.390E+02 2.380E+05 6.210E+05 0.OOOE+00 4.020E+01 TE-132 3.600E+02 2.900E+02 2.460E+02 1.950E+03 4.490E+05 4.630E+05 0.OOOE+00 2.190E+02 11-130 6.240E+03 1.790E+04 1.490E+06 2.750E+04 0.OOOE+00 9.120E+03 0.OOOE+00 7.170E+03 Appendix H Ri Teen Inhalation - Page 2 of 3

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX H R; Teen Dose Factors for use in the Gaseous Dose Calculations

- Agegroup: TEEN Pathway: Inhalation (INHL) Units: mrem/yr / tCi/m 3 Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body 1-131 3.540E+04 4.91 OE+04 1.460E+07 8.400E+04 0.OOOE+00 6.490E+03 0.OOOE+00 2.640E+04 1-132 1.590E+03 4.380E+03 1.510E+05 6.920E+03 0.OOOE+00 1.270E+03 0.OOOE+00 1.580E+03 1-133 1.220E+04 2.050E+04 2.920E+06 3.590E+04 0.OOOE+00 1.030E+04 0.OOOE+00 6.220E+03 1-134 8.880E+02 2.320E+03 3.950E+04 3.660E+03 0.OOOE+00 2.040E+01 0.OOOE+00 8.400E+02 1-135 3.700E+03 9.440E+03 6.210E+05 1.490E+04 0.OOOE+00 6.950E+03 0.OOOE+00 3.490E+03 CS-134 5.020E+05 1.130E+06 0.OOOE+00 3.750E+05 1.460E+05 9.760E+03 0.OOOE+00 5.490E+05 CS-136 5.150E+04 1.940E+05 0.OOOE+00 1.100E+05 1.780E+04 1.090E+04 0.OOOE+00 1.370E+05 CS-137 6.700E+05 8.480E+05 0.OOOE+00 3.040E+05 1.210E+05 8.480E+03 0.OOOE+00 3.110E+05 CS-138 4.660E+02 8.560E+02 0.OOOE+00 6.620E+02 7.870E+01 2.700E-01 0.OOOE+00 4.460E+02 BA-139 1.340E+00 9.440E-04 0.000E+00 8.880E-04 6.460E+03 6.450E+03 0.OOOE+00 3.900E-02 BA-140 5.470E+04 6.700E+01 0.OOOE+00 2.280E+01 2.030E+06 2.290E+05 0.OOOE+00 3.520E+03 BA-141 1.420E-01 1.060E-04 0.OOOE+00 9.840E-05 3.290E+03 7.460E-04 0.OOOE+00 4.740E-03 BA-142 3.700E-02 3.700E-05 0.OOOE+00 3.140E-05 1.910E+03 4.790E-10 0.OOOE+00 2.270E-03 LA-140 4.790E+02 2.360E+02 0.OOOE+00 0.OOOE+00 - 2.140E+05 4.870E+05 0.OOOE+00 6.260E+O1 LA-142 9.600E-01 4.250E-01 0.OOOE+00 0.OOOE+00 1.020E+04 1.200E+04 0.000E+00 1.060E-01 CE-141 2.840E+04 1.900E+04 0.OOOE+00 8.880E+03 6.140E+05 1.260E+05 0.060E+60 2.170E+03 CE-143 2.660E+02 1.940E+02 0.OOOE+00 8.640E+01 1.300E+05 2.550E+05 0.OOOE+00 2.160E+01 CE- 144 4.890E+06 2.020E+06 0.000E+00 1.210E+06 1.340E+07 8.640E+05 0.OOOE+00 2.620E+05 PR-143 1.340E+04 5.310E+03 0.OOOE+00 3.090E+03 4.830E+05 2.140E+05 0.000E+00 6.620E+02 PR-144 " 4.300E 1.760E-02 0.OOOE+00 - 1.010E-02 1.750E+03 2.350E-04 0.OOOE+00 2.180E-03 ND-147 7.860E+03 8.560E+03 0.OOOE+00 5.020E+03 3.720E+05 1.820E+05 0.OOOE+00 5.130E+02 W-187 1.200E+01 9.760E+00 0.OOOE+00 0.OOOE+00 - 4.740E+04 1.770E+05 0.OOOE+00 3.430E+00 NP-239 3.380E+02 3.190E+01 0.000E+00 1.000E+02 6.490E+04 1.320E+05 0.OOOE+00 1.770E+01 Appendix H Ri Teen Inhalation - Page 3 of 3

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX H R, Teen Dose Factors for use in the Gaseous Dose Calculations Agegroup: TEEN Pathway: Ground Plane Deposition (GPD) Units: m 2 mrem/yr / ýCi/sec Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body H-3 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.000E+00 0.OOOE+00 0.000E+00 C-14 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.000E+00 0.OOOE+00 0.OOOE+00 NA-24 1.190E+07 1.190E+07 1.190E+07 1.190E+07 .1.190E+07 1.190E+07 1.390E+07 1.190E+07 P-32 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 CR-51 4.660E+06 4.660E+06 4.660E+06 4.660E+06 4.660E+06 4.660E+06 5.510E+06 4.660E+06 MN-54 1.390E+09 1.390E+09 1.390E+09 1.390E+09 1.390E+09 1.390E+09 1.630E+09 1.390E+09 MN-56 9.020E+05 9.020E+05 9.020E+05 9.020E+05 9.020E+05 9.020E+05 1.070E+06 9.020E+05 FE-55 0.OOOE+00 0.OOOE+00 0.000E+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 FE-59 2.730E+08 2.730E+08 2.730E+08 2.730E+08 2.730E+08 2.730E+08 3.210E+08 2.730E+08 CO-58 3.790E+08 3.790E+08 3.790E+08 3.790E+08 3.790E+08 3.790E+08 4.440E+08 3.790E+08 CO-60 2.150E+10 2.150E+10 2.150E+10 2.150E+10 2.150E+10 2.150E+10 2.530E+10 2.150E+10 NI-63 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.000E+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 NI-65 2.970E+05 2.970E+05 2.970E--05 2.970E+05 2.970E+05 2.970E+05 3.450E+05 2.970E+05 CU-64 6.070E+05 6.070E+05 6.070E+05 6.070E+05 6.070E+05 6.070E+05 6.880E+05 6.070E+05 ZN-65 7.470E+08 7.470E+08 7.470E+08 7.470E+08 7.470E+08 7.470E+08 8.590E+08 7.470E+08 ZN-69 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 BR-83 4.870E+03 4.870E+03 4.870E+03 4.870E+03 4.870E+03 4.870E+03 7.080E+03 4.870E+03 BR-84 2.030E+05 2.030E+05 2.030E+05 2.030E+05 2.030E+05 2.030E+05 2.360E+05 2.030E+05 BR-85 0.OOOE+00 0.000E+00 0.OOOE+00 O.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 RB-86 8.990E+06 8.990E+06 8.990E+06 8.990E+06 8.990E+06 8.990E+06 1.030E+07 8.990E+06 RB-88 3.310E+04 3.310E+04 3.310E+04 3.310E+04 3.310E+04 3.310E+04 3.780E+04 3.310E+04 RB-89 1.230E+05 1.230E+05 1.230E+05 1.230E+05 1.230E+05 1.230E+05 1.480E+05 1.230E+05 SR-89 2.160E+04 2.160E+04 2.160E+04 2.160E+04 2.160E+04 2.160E+04 2.510E+04 2.160E+04 SR-90 0.OOOE+00 0.OOOE+00 0.OOOE+00 O.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.000E+00 SR-91 2.150E+06 2.150E+06 2.150E+06 2.150E+06 2.150E+06 2.150E+06 2.510E+06 2.150E+06 Appendix H Ri Teen Ground Plane Deposition - Page 1 of 3

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX H R. Teen Dose Factors for use in the Gaseous Dose Calculations Agegroup: TEEN Pathway: Ground Plane Deposition (GPD) Units: m mrem/yr / p.Ci/sec Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body SR-92 7.770E+05 7.770E+05 7.770E+05 7.770E+05 7.770E+05 7.770E+05 8.630E+05 7.770E+05 Y-90 4.490E+03 4.490E+03 4.490E+03 4.490E+03 4.490E+03 4.490E+03 5.3 1OE+03 4.490E+03 Y-91 1.070E+06 1.070E+06 1.070E+06 1.070E+06 1.070E+06 1.070E+06 1.210E+06 1.070E+06 Y-91M 1.000E+05 1.000E+05 1.000E+05 1.000E+05 1.000E+05 1.000E+05 1.160E+05 1.000E+05 Y-92 1.800E+05 1.800E+05 1.800E+05 1.800E+05 1.800E-05 1.800E+05 2.140E+05 1.800E+05 Y-93 1.830E+05 1.830E+05 1.830E+05 1.830E+05 1.830E+05 1.830E+05 2.510E+05 1.830E+05 ZR-95 2.450E+08 2.450E+08 2.450E+08 2.450E+08 2.450E+08 2.450E+08 2.840E+08 2.450E+08 ZR-97 2.960E+06 2.960E+06 2.960E+06 2.960E+06 2.960E+06 2.960E+06 3.440E+06 2.960E+06 NB-95 1.370E+08 1.370E+08 1.370E+08 1,370E+08 1.370E+08 1.370E+08 1.610E+08 1.370E+08 MO-99 3.990E+06 3.990E+06 3.990E+06 3.990E+06 3.990E+06 3.990E+06 4.630E+06 3.990E+06 TC-99M 1.840E+05 1.840E+05 1.840E+05 1.840E+05 1.840E+05 1.840E+05 2.11OE+05 1.840E+05 TC-101 2.040E+04 2.040E+04 2.040E+04 2.040E+04 2.040E+04 2.040E+04 2.260E+04 2.040E+04 RU-103 1.080E+08 1.080E+08 1.080E+08 1.080E+08 1.080E+08 1.080E+08 1.260E+08 1.080E+08 RU-105 6.360E+05 6.360E+05 6.360E+05 6.360E+05 6.360E+05 6.360E+05 7.210E+05 6.360E+05 RU-106 4.220E+08 4.220E+08 4.220E+08 4.220E+08 4.220E+08 4.220E+08 5.070E+08 4.220E+08 AG-1 10M 3.440E+09 3.440E+09 3.440E+09 3.440E+09 3.440E+09 3.440E+09 4.010E+09 3.440E+09 TE-125M 1.550E+06 1.550E+06 1.550E+06 1.550E+06 1.550E+06 1.550E+06 2.130E+06 1.550E+06 TE-127 2.980E+03 2.980E+03 2.980E+03 2.980E+03 2.980E+03 2.980E+03 3.280E+03 2.980E+03 TE-127M 9.160E+04 9.160E+04 9.160E+04 9.160E+04 9.160E+04 9.160E+04 1.080E+05 9.160E+04 TE-129 2.620E+0 4 2.620E+04 2.620E+04 2.620E+04 2.620E+04 2.620E+04 3.100E+04 2.620E+04-TE-129M 1.980E+07 1.980E+07 1.980E+07 1.980E+07 1.980E+07 1.980E+07 2.310E+07 1.980E+07 TE- 131 2.920E+04 2.920E+04 2.920E+04 2.920E+04 2.920E+04 2.920E+04 3.450E+07 2.920E+04 TE-131M 8.030E+06 8.030E+06 8.030E+06 8.030E+06 8.030E+06 8.030E+06 9.460E+06 8.030E+06 TE-132 4.230E+06 4.230E+06 4.230E+06 4.230E+06 4.230E+06 4.230E+06 4.980E+06 4.230E+06 1-130 5.510E+06 5.5 1OE+06 5.510E+06 5.5 1OE+06 5.51OE+06 5.5 1OE+06 6.690E+06 5.5 1OE+06 Appendix H Ri Teen Ground Plane Deposition - Page 2 of 3 0

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX H R, Teen Dose Factors for use in the Gaseous Dose Calculations Agegroup: TEEN Pathway: Ground Plane Deposition (GPD) Units: m 2-mrem/yr /pCi/sec Nuclide Bone Liver- Thyroid Kidney Long, Gilli Skin Total Body 1-131 1.720E+07 1.720E+07 1.720E+07 1.720E+07 1.720E+07 1.720E+07 2.090E+07 1.720E+07 1-132 1.250E+06 1.250E+06 1.250E+06 1.250E+06 1.250E+06 1.250E+06 1.470E+06 1.250E+06 J-133 2.450E+06 2.450E+06 2.450E+06 2.450E+06 2.450E+06 2.450E+06 2.980E+06 2:450E+06 1- 134 4.470E+05 4.470E+05 4.470E+05 4.470E+05 4.470E+05 4.470E+05 5.300E+05 4.470E+05 1-135 2.530E+06 2.530E+06 2.530E+06 2.530E+06 2.530E+06 2.530E+06 2.950E+06 2.530E+06 CS-134 6.860E+09 6.860E+09 6.860E+09 6.860E+09 6.860E+09 6.860E+09 8.OOOE+09 6.860E+09 CS-136 1.510E+08 1.510E+08 1.510E+08 .1.510E+08 1.510E+08 1.510E+08 1.71OE4-08 1.510E+08 CS-137 1.030E+10 1.030E+10 1.030E+10 1.030E+10 1.030E+10 1.030E+10 1.200E+10 1.030E+10 CS-138 3.590E+05 3.590E+05 3.590E+05 3.590E+05 3.590E+05 3.590E+05 4.100E+05 3.590E+05 BA- 139 1.060E+05 1.060E+05 1.060E+05 1.060E+05 1 .060E+05 1.060E+05 1.190E+05 1.060E+05 BA-140 2.050E+07 2.050E+07 2.050E+07 2.050E+07 2.050E+07 2.050E+07 2.350E+07 2.050E+07 BA-141 4.170E+04 4.170E+04 4.170E+04 4.170E+04 4.170E+04 4.170E+04 4.750E+04 4.170E+04 BA-142 4.490E+04 4.490E+04 4.490E+04 4.490E+04 4.490E+04 4.490E+04 5.11OE+04 4.490E+04 LA-140 1.920E+07 1.920E+07 1.920E+07 1.920E+07 1.920E+07 1.920E+07 2.180E+07 1.920E+07 LA-142 7.600E+05 7.600E+05 7.600E+05 7.600E+05 7.600E+05 7.600E+05 9.120E+05 7.600E+05 CE-141 1.370E+07 1.370E+07 1.370E+07 1.370E+07 1.370E+07 1.370E+07 1.540E+07 1.370E+07 CE-143 2.310E+06 2.310E-I+06 2.310E +06 2.310E+06 2.310E 06 2.310E+06 2.630E+06 2.310E+06 CE-144 6.950E+07 6.950E+07 6.950E+07 6.950E+07 6.950E+07 6.950E+07 8.040E+07 6.950E+07 PR-143 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.000E+00 0.OOOE+00 0.OOOE+00 PR-144 1.830E+03 1.830E+03 1.830E+03 1.830E+03 1.830E+03 1.830E+03 2.11OE+03 1.830E+03 ND-147 8.390E+06 8.390E+06 8.390E+06 8.390E+06 8.390E+06 8.390E+06 1.010E-407 8.390E+06 W-187 2.350E+06 2.350E+06 2.350E+06 2.350E+06 2.350E+06 2.350E+06 2.730E+06 2.350E+06 NP-239 1.710E+06 1.710E+06 1.710E+06 1.710E+06 1.710E+06 1.710E+06 1.980E+06 1.710E+06 Appendix H Ri Teen Ground Plane Deposition - Page 3 of 3

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX I Ri Child Dose Factors for use in the Gaseous Dose Calculations Agegroup: CHILD Pathway: Grs/Cow/Milk (CMILK) Units: m mrem/yr / jtCi/sec;

_____mrem/yr/ tCi/m3 (H-3)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body H-3 0.OOOE+00 1.570E+03 1.570E+03 1.570E+03 1.570E+03 1.570E+03 0.000E+00 1.570E+03 C-14 1.190E+09 2.390E+08 2.390E+08 2.390E+08 2.390E+08 2.390E+08 0.OOOE+00 2.390E+08 NA-24 8.850E+06 8.850E+06 8.850E+06 8.850E+06 8.850E+06 8.850E+06 0.OOOE+00 8.850E+06 P-32 7.780E+10 3.640E+09 0.OOOE+00 0.OOOE+00 0.OOOE+00 2.150E+09 0.OOOE+00 3.OOOE+09 CR-51 0.OOOE+00 0.OOOE+00 5.650E+04 1.540E+04 1.030E+05 5.400E+06 0.OOOE+00 1.020E+05 MN-54 0.OOOE+00 2.100E+07 0.OOOE+00 5.880E+06 0.OOOE+00 1.760E+07 0.OOOE+00 5.590E+06 MN-56 0.OOOE+00 1.260E-02 0.OOOE+00 1.530E-02 0.OOOE+00 1.830E+00 0.000E+00 2.860E-03 FE-55 1.120E+08 5.930E+07 0.OOOE+00 0.OOOE+00 3.350E+07 1.1OOE+07 0.OOOE+00 1.840E+07 FE-59 1.200E+08 1.950E+08 0.000E+00 0.OOOE+00 5.640E+07 2.030E+08 0.OOOE+00 9.690E+07 CO-58 0.OOOE+00 1.210E+07 0.OOOE+00 0.OOOE+00 0.OOOE+00 7.070E+07 0.OOOE+00 3.710E+07 CO-60 0.OOOE+00 4.320E+07 0.OOOE+00 0.OOOE+00 0.OOOE+00 2.390E+08 0.OOOE+00 1.270E+08 NI-63 2.960E+10 1.590E+09 0.OOOE+00 0.OOOE+00 0.OOOE+00 1.070E+08 0.OOOE+00 1.010E+09 NI-65 1.660E+00 1.560E-01 0.OOOE+00 0.OOOE+00 0.OOOE+00 1.910E+01 0.OOOE+00 9.100E-02 CU-64 0.OOOE+00 7.460E+04 0.OOOE+00 1.800E+05 0.000E+00 3.500E+06 0.OOOE+00 4.510E+04 ZN-65 4.130E+09 1.100E+10 0.OOOE+00. 6.940E+09 0.OOOE+00 1.930E+09 0.OOOE+00 6.850E+09 ZN-69 9.460E-12 1.370E-11 0.OOOE+00 8.300E-12 0.000E+00 8.620E-10 0.OOOE+00 1.260E-12 BR-83 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.000E+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 4.400E-01 BR-'84 0.OOOE+00 0.000E+00 0.OOOE+00 0.000E+00 0.OOOE+00 0.OOOE+00 0.000E+00 6.5 1OE-23 BR-85 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 RB-86 - 0.000E+00 8.770E÷09 0.000E+00. 0.000E+00 -0.OOOE+00 5.640E+08 0.000E+00 5.390E+/-09 RB-88 0.OOOE+00 7.160E-45 0.OOOE+00 O.OOOE+00 0.OOOE+00 3.5 1OE-46 0.OOOE+00 4.970E-45 RB-89 0.OOOE+00 1.340E-52 0.OOOE+00 0.OOOE+00 0.000E+00 1.170E-54 0.OOOE+00 1.190E-52 SR-89 6.620E+09 0.OOOE+00 0.OOOE+00 - 0.OOOE+00 .0003E+00 2.560E+08 0.OOOE+00 1.890E+08 SR-90 1.120E+l 1 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 1.510E+09 0.OOOE+00 2.830E+10 SR-91 1.300E+05 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 2.880E+05 0.OOOE+00 4.920E+03 0

Appendix I Ri Child Cow Milk - Page 1 of 3 0

Oconee Nuclear Station 9

January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX I Ri Child Dose Factors for use in the Gaseous Dose Calculations "Agegroup: CHILD Pathway: Grs/Cow/Milk (CMILK) iUnits:. m2'mrem/yr lCi/sec;

/

________mrem/yr / jCi/m3 (H-3)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body SR-92 2.180E+00 0.OOOE+00 0.000E+00 0.000E+00 0.000E+00 4.130E+01 0.OOOE+00 8.750E-02 Y-90 3.220E+02 0.OOOE+00 0.000E+00 0.000E+00 0.000E+00 9.170E+05 0.OOOE+00 8.620E+00 Y-91 3.900E+04 0.OOOE+00 0.000E+00 0.000E+00 0.OOOE+00 5.200E+06 0.OOOE+00 1.040E+03 Y-91M 2.670E-19 0.OOOE+00 0.OOOE+00 0.000E+00 0.000E+-00 5.240E-16 0.060E+00 9. 730E-21 Y-92 2.530E-04 0.OOOE+00 0.OOOE+00 0.000E+00 0.000E+00 7.310E+00 0.000E+00 7.240E-06 Y-93 1.010E+00 0.OOOE+00 0.OOOE+00 0.000E+00 0.003E+00 1.510E+04 0.OOOE+00 2.780E-02 ZR-95 3.830E+03 8.420E+02 0.OOOE+00 1.210E+03 0.006E+06 8.790E+05 0.000E+00 7.500E+02 ZR-97 1.920E+00 2.770E-01 0.000E+00 3.980E-01 0.OOOE+00 4.200E+04 0.000E+00 1.640E-01 NB-95 3.180E+05 1.240E+05 0.OOOE+00 1.160E+05 0.000E+00 2.290E+08 0.000E+00 8.840E+04 MO-99 0.OOOE+00 8.140E+07 0.OOOE+00 1.740E+08 0.000E+00 6.730E+07 0.000E+00 2.010E+07 TC-99M 1.320E+01 2.590E+01 0.OOOE+00 3.760E+02 1.320E+01 1.470E+04 0.OOOE+00 4.290E+02 TC-101 1.160E-59 1.220E-59 0.OOOE+00 2.080E-58 6.440E-60 3.870E-59 0.OOOE+00 1.540E-58 RU-103 4.280E+03 0.OOOE+00 0.OOOE+00 1.080E+04 0.OOOE+00 1.libE+05 0.OOOE+00 1.650E+03 RU-105 3.820E-03 0.000E+00 0.OOOE+00 3.360E-02 0.060E+00 2.490E+06 0.OOOE+00 1.390E-03 RU-106 9.240E+04 0.OOOE+00 0.OOOE+00 1.250E+05 0.OOOE+00 1.440E+06 0.OOOE+00 1.150E+04 AG- lOM 2.090E+08 1.410E+08 0.OOOE+00 2.630E+08 0.OOOE+00 1.680E+10 0.006E+00 i.130E+08 TE-125M 7.380E+07 2.OOOE+07 2.070E+07 0.OOOE+00 0.OOOE+00 7.120E+07 0.OOOE+00 9.840E+06 TE-127 2.980E+03 8.020E+02 2.060E+03 8.470E+03 0.000E+00 1.160E+05 0.OOOE+00 6.380E+02 TE-127M 2.080E+08 5.600E+07 4.970E+07 5.930E+08 0.OOOE+00 1.680E+08 0.OOOE+00 2.470E+07 TE-129 1.280E-09 3.580E-10 9.160E-10 3.750E-09 0.OOOE+00 7.990E-08 0.OOOE+00 3.050E-10 TE-129M 2.710E+08 7.580E+07 8.750E+07 7.970E+08 0.OOOE+00 3.310E+08 0.OOOE+00 4.210E+07 TE-131 1.620E-32 4.920E-33 1.240E-32 .'4.890E-32 0.OOOE+00 8.490E-32 0.OOOE+00 4.810E-33 TE-131M 1.600E+06 5.530E+05 1.140E+06 5.350E+06 0.OOOE+00 2.240E+07 0.OOOE+00 5.890E+05 TE-132 1.020E+07 4.530E+06 6.600E+06 4.210E+07 0.OOOE+00 4.570E+07 0.OOOE+00 5.480E+06 1-130 1.730E+06 3.490E+06 3.840E+08 5.220E+06 0.OOOE+00 1.630E+06 0.OOOE+00 1.800E+06 Appendix I Ri Child Cow Milk - Page 2 of 3

Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX I Ri Child Dose Factors for use in the Gaseous Dose Calculations Agegroup: CHILD Pathway: Grs/Cow/Milk (CMILK) Units: m2-mrem/yr / jiCi/sec;

___. ...... __ __ _mrem/yr / pCi/mr (H-3)

Nuclide Bone Liver Thyroid' Kidney,:, Lung Gilli Skint Total Body 1-131 1.300E+09 1.310E+09 4.330E+11 2.150E+09 O.OOOE+00 1.170E+08 O.OOOE+00 7.450E+08 1-132 6.890E-01 1.270E+00 5.870E+01 1.940E+00 O.OOOE+00 1.490E+00 O.OOOE+00 5.820E-01 1-133 1.720E+07 2.120E+07 3.940E+09 3.540E+07 O.OOOE+00 8.560E+06 O.OOOE+00 8.030E+06 1-134 8.480E-12 1.570E-11 3.620E-10 2.41OE-11 O.OOOE+00 1.040E-11 O.OOOE+00 7.250E-12 1-135 5.400E+04 9.720E+04 8.610E+06 1.490E+05 O.OOOE+00 7.400E+04 O.OOOE+00 4.600E+04 CS-134 2.260E+10 3.720E+10 O.OOOE+00 1.150E+10 4.130E+09 2.OOOE+08 O.OOOE+00 7.840E+09 CS-136- 1.010E+09 2.780E+09 O.OOOE+00 1.480E+09 2.210E+08 9.770E+07 O.OOOE+00 1.800E+09 CS-137 3.220E+10 3.090E+10 O.OOOE+00 1.010E+10 3.620E+09 1.930E+08 O.OOOE+00 4.550E+09 CS-138 3.980E-23 5.530E-23 O.OOOE+00 3.890E-23 4.190E-24 2.550E-23 O.OOOE+00 3.510E-23 BA-139 2.010E-07 1.070E-10 O.OOOE+00 '9.360E-11 6.300E-11 1.160E-05 O.OOOE+00 5.820E-09 BA-140 1.170E+08 1.030E+05 O.OOOE+00 3.340E+04 6.120E+04 5.930E+07 O.OOOE+00 6.840E+06 BA-141 1.850E-45 1.040E-48 O.OOOE+00 8.960E-49 6.090E-48 1.050E-45 O.OOOE+00 6.020E-47 BA-142 1.150E-79 8.310E-83 O.OOOE+00 6.720E-83 4.890E-83 1.510E-81 O.OOOE+00 6.450E-81 LA-140 1.940E+01 6.780E+00 O.OOOE+00 O.OOOE+00 0.000E+00 1.890E+05 O.OOOE+00 2.290E+00 LA-142 8.100E-11 2.580E-11 O.OOOE+00 O.OOOE+00. O.OOOE+00 5.120E-06 O.OOOE+00 8.090E-12 CE- 141 2.190E+04 1.090E+04 O.OOOE+00 4.780E+03 0,000E+00 1.360E+07 O.OOOE+00 1.620E+03 CE-143 1.870E+02 1.020E+05 O.OOOE+00 4.260E+O1 O.OOOE+00 1.490E+06 O.OOOE+00 1.470E+O1 CE-144 1.620E+06 5.090E+05 O.OOOE+00 2.820E+05 O.OOOE+00 1.330E+08 O.OOOE+00 8.660E+04 PR-143 7.180E+02 2.160E+02 O.OOOE+00 1.170E+02 O.OOOE+00 7.750E+05 O.OOOE+00- 3.560E+01 PR-144 2.680E-53 8.290E-54 O.OOOE+00 4.380E-54 O.OOOE+00 1.780E-50 O.OOOE+00 1.350E-54 ND-147 4.450E+02 3.600E+02 O.OOOE+00 1.980E+02 O.OOOE+00 5.700E+05 O.OOOE+00 2.790E+O1 W-1* 87 2.890E+04 1.710E+04 O.OOOE+00 O.OOOE+00 O.OOOE+00 2.400E+06 O.OOOE+00 7.670E+03 NP-239 1.720E+01 1.240E+00 O.OOOE+00 3.580E+00 O.OOOE+00 9.170E+04 O.OOOE+00 8.710E-01 Appendix I Ri Child Cow Milk - Page 3 of 3

Oconee Nuclear Station 0

January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX I Re Child Dose Factors for use in the Gaseous Dose Calculations Age'group;: CHILD Patihway: Grs/Goat/Milk (GMILK) Uniits: m 2.mrem/yr / tCi/sec;

___________ ___________ __________ ___________ ___________ _____ mrem/yr / tCi/m3 (H-3)

Nuclide Bone'- Liver Thyroid Kidney Lung Gilli Skin Total Bod!y H-3 0.OOOE+00 3.200E+03 3.200E+03 3.200E+03 3.200E+03 3.200E+03 0.OOOE+00 3.200E+03 C-14 1.190E+09 2.390E+08 2.390E+08 2.390E+08 2.390E+08 2.390E+08 0.OOOE+00 2.390E+08 NA-24 1.060E+06 1.060E+06 1.060E+06 1.060E+06 1.060E+06 1.060E+06 0.OOOE+00 1.060E+06 P-32 9.330E+10. 4.370E+09 0.000E+00 0.OOOE+00 0.OOOE+00 2.580E+09 0.OOOE+00 3.600E+09 CR-51 0.OOOE+00 0.060E+00 6.780E+03 1.850E+03 1.240E+04 6.480E+05 0.OOOE+00 1.220E+04 MN-54 0.OOOE+00 2.520E+06 0.OOOE+00 7.060E+05 0.OOOE+00 2.110E+06 0.OOOE+00 6.700E+05 MN-56 0.OOOE+00 1.520E-03 0.OOOE+00 1.840E-03 0.OOOE+00 2.200E-01 0.OOOE+00 3.430E-04 FE-55 1.450E+06 7.710E+05 O.OOOE+00 O.OOOE+00 4.360E+05 1.430E+05 0.OOOE+00 2.390E+05 FE-59 1.560E+06 2.530E+06 0.OOOE+00 0.OOOE+00 7.330E+05 2.630E+06 0.OOOE+00 1.260E+06 CO-58 0.OOOE+00 1.450E+06 0.000E+00 0.OOOE+00 0.OOOE+00 8.490E+06 0.OOOE+00 4.450E+06 CO-60 0.OOOE+00 5.180E+06 0.060E+00 0.OOOE+00 0.OOOE+00 2.870E+07 0.OOOE+00 1.530E+07 NI-63 3.560E+09 1.900E+08 0.OOOE+00 0.0OOE+00 0.OOOE+00 1.280E+07 0.OOOE+00 1.210E+08 NI-65 1.990E-01 1.870E-02 0.OOOE+00 0.OOOE+00 0.OOOE+00 2.290E+-00 0.OOOE+00 1.090E-02 CU-64 0.000E+00 8.320E+03 0.OOOE+00 2.010E+04 0.OOOE+00 3.900E+05 0.OOOE+00 5.020E+03 ZN-65 4.960E+08 1.320E+09 0.013E+00 8.330E+08 0.OOOE+00 2.320E+08 0.OOOE+00 8.220E+08 ZN-69 1.140E-12 1.640E-12 0.OOOE+00 9.960E-13 0.OOOE+00 1.030E-10 0.OOOE+00 1.520E-13 BR-83 0.OOOE+00 0.OOOE+00 0.000E+00 0.000E+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 5.280E-02 BR-84 0.OOOE+00 0.060E+00 0.OOOE+00 O.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 7.820E-24 BR-85 0.OOOE+00 0.OOOE+00 0.OOOE+00 O.OOOE+00 0.000E+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 RB-86 0.OOOE+00 1.050E+09 0.000E+00 O.OOOE+00 0.OOOE+00 6.770E+07 0.OOOE+00 6.470E+08 RB-88 0.OOOE+00 8.590E-46 0.000E+00 0.OOOE+00 0.OOOE+00* 4.210E-47 0.OOOE+00 5.970E-46 RB-89 0.OOOE+00 1.610E-53 0.OOOE+00 0.OOOE+00 0.OOOE+00 1.410E-55 0.000E+00 1.430E-53 SR-89 1.390E+10 0.OOOE+00 0.000E+00 0.OOOE+00 0.OOOE+00 5.380E+08 0.OOOE+00 3.970E+08 SR-90 2.350E+11 0.000E+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 3.160E+09 0.OOOE+00 5.950E+10 SR-91 2.740E+05 0.000E+00 0.OOOE+00 0.000tE00 0.000E+00 6.040E+05 0.000E+00 1.030E+04 Appendix I Ri Child Goat Milk - Page 1 of 3

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX I R. Child Dose Factors for use in the Gaseous Dose Calculations Agegroup: CHILD Pathway: Grs/Goat/IVilk (GMILK) Units: m 2 mrem/yr / p.Ci/sec;.

Nuclide_-

_mrem/yr Bone Liver Thyroid Kidney Lung _ Gilli . *Skin_

I *tCi/m 3 (H-3)

TotalBody SR-92 4.580E+00 0.OOOE+00 0,OOOE+00 0.OOOE+00 0.000E+00 8.680E+01 0.OOOE+00 1.840E-01 Y-90 3.870E+01 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 1.100E+05 0.000E+00 1.030E+00 Y-91 4.680E+03 O.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 6.240E+05 0.000E+00 1.250E+02 Y-91M 3.210E-20 0.OOOE+00 0.OOOE+00 O.OOOE+00 0.OOOE+00 6.280E-17 0.OOOE+00 1.170E-21 Y-92 3.040E-05 0.OOOE+00 0.000E+00 0.OOOE+00 0.OOOE+00 8.770E-01 .0.OOOE+00 8.690E-07 Y-93 1.210E-01 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 1.810E+03 0.OOOE+00 3.330E-03 ZR-95 4.600E+02 1.010E+02 0.OOOE+00 1.450E+02 0.OOOE+00 1.050E+05 0.OOOE+00 9.OOOE+01 ZR-97 2.300E-01. 3.330E-02 0.OOOE+00 4.780E-02 0.OOOE+00 5.040E+03 0.OOOE+00 1.960E-02 NB-95 3.810E +04 1.490E+04 0.OOOE+00 1.400E+04 0.OOOE+00 2.750E+07 0.0003E+00 1.060E+04 MO-99 0.OOOE+00 9.760E+06 0.OOOE+00 2.090E+07 0.OOOE+00 8.080E+06 0.OOOE+00 2.420E+06 TC-99M 1.590E+00 3.110E+00 0.OOOE+00 4.520E+01 1.580E+00 1.770E+03 0.OOOE+00 5.150E+01 TC-101 1.400E-60 1.460E-60 0.000E+00 2.490E-59 7.720E-61 4.640E-60 0.OOOE+-00 -1.850E-59 RU- 103 5.140E+02 0.006E+00 o.OOOE+00 1.290E+03 0.OOOE+00 1.330E+04 0.000E+00 1.980E+02 RU-105 4.580E-04 0.OOOE+00 *0.000E+00 4.030E-03 0.OOOE+00 2.990E-01 0.OOOE+00 1.660E-04 kU-106 1.110E+04 0.OOOE+00 0.OOOE+00 1.500E+04 0.OOOE+00 1.720E+05 0.OOOE+00 1.380E+03 AG- 110M 2.510E+07 1.690E+07 0.oooE+00. 3.150E+07 o.oooE+00 2.010E+09 0.OOOE+00 1.350E+07 TE-125M 8.850E+06 2. 400E+06 2.480E+06 0.OOOE+00 0.000E+00 8.540E+06 0.OOOE+00 1.180E+06 TE- 127 3.570E+02 9.630E+01 2.470E+02 1Q020E+03 0.OOOE+00 1.390E+04 O.OOOE+00- 7.660E+01 TE-127M 2.500E+07 6.720E+06 5.970E+06 7.120E+07 0.000E+00 2.020E+07 0.000E+00 2.960E+06 TE-129 41540E-10 4=300E-1-l -1.1OOE 4.510E-10 .. 0.OOOE+00--- -. 9,590E-09.. -.-..0.000E+00 1-3.660E11L TE-129M 3.260E+07 9.090E+06 1.050E+07 9.560E+07 0.OOOE+00 3.970E+07 0.OOOE+00 5.060E+06 TE- 131 1.940E-33 5.910E-34 1.480E-33 5.860E-33 0.OOOE+00 1.020E-32 0.OOOE+00 5.770E-34 TE-131M 1.920E+05 6.640E+04 1.360E+05 6.420E+05 0.OOOE+00 2.690E+06 0.OOOE+00 7.060E+04 TE-132 1.230E+06 5.440E+05 7.920E+05 5.050E+06 0.OOOE+00 5.480E+06 0.OOOE+00 6.570E+05 11-130 2.070E+06 4.190E+06 4.610E+08 6.260E+06 0.OOOE+00 1.960E+06 0.000E+00 2.160E+06 Appendix I Ri Child Goat Milk - Page 2 of 3

Oconee Nuclear Station 0

January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX I Ri Child Dose Factors for use in the Gaseous Dose Calculations Agegroup:... CHILD Pathway: Grs/Goat/Milk (GMILK) -Units:.- m2.mrem/yr / liCi/sec;

______.___ ___________ ______.... ___________ mrem/yr / pCi/m 3 (H-3)

Nuclide Bone Liver Thyroid -.'Kidney. Lungn Gilli. Skin' 'Total Body 1-131 1.560E+09 1.570E+09 5.200E+11 2.580E+09 0.000E+00 1.400E+08 0.OOOE+00 8.940E+08 1-132 8.270E-01 1.520E+00 7.050E+0I 2.330E+00 0.OOOE+00 1.790E+00 0.OOOE+00 6.990E-01I 1-133 2.060E+07 2.550E+07 4.730E+09 4.250E+07 0.OOOE+00 1.030E+07 0.000E+00 9.640E+06 1-134 1.020E-11 1.890E- 11 4.350E-10 2.890E- 11 0.000E+00 1.250E-11 0.000E+00 8.700E-12 1-135 6.480E+04 1.170E+05 1.030E+07 1.790E+05 0.000E+00 8.880E+04 0.000E+00 5.520E+04 CS-134 6.790E+10 1.11 OE+ll 0.000E+00 3.450E+10 1.240E+10 6.010E+08 0.000E4-00 2.350E+10 CS-136 3.030E+09 8.340E+09 0.OOOE+00 4.440E+09 6.630E+08 2.930E+08 0.OOOE+00 5.400E+09 CS-137 9.670E+10 9.260E+10 0.OOOE+00 3.020E+10 1.090E+10 5.800E+08 0.000E+00 1.370E+10 CS-138 1.190E-22 1.660E-22 0.000E+00 1.170E-22 1.260E-23 7.640E-23 0.OOOE+00 1.050E-22 BA-139 2.410E-08 1.290E-11 0.OOOE+00 1.120E-11 7.560E-12 1.390E-06 0.OOOE+00 6.980E-10 BA-140 1.410E+07 1.230E+04 0.000E+00 4.o01E+03 7.340E+03 7.120E+06 0.OOOE+00 8.200E+05 BA-141 2.220E-46 1.240E-49 0.OOOE+00 1.080E-49 7.300E-49 1.270E-46 0.OOOE+00 7.230E-48 BA-142 1.390E-80 9.970E-84 0.000E+00 8.070E-84 5.870E-84 1.810E 0.OOOE+00 7.740E-82 LA-140 2.330E+00 8.140E-01 0.OOOE+00 0.OOOE+00 0.000E+00 2.270E+04 0.OOOE+00 2.740E-01 LA-142 9.730E-12 3.100E-12 0.OOOE+00 0.000E+00 0.OOOE+00 6.140E-07 0.OOOE+00 9.710E-13 CE- 141 2.620E+03 1.310E+03 0.OOOE+00 5.740E+02 0.000E+00 1.630E+06 0.OOOE+00 1.940E+02 CE-143 2.250E+01 1.220E+04 0.OOOE+00 5.120E+00 0.000E+00 1.790t+05 0.OOOE+00 1.770E+00 CE-144 1.950E+05 6.11OE+04 0.OOOE+00 3.380E+04 0.000E+00 1.590E+07 0.OOOE+00 1.040E+04 PR-143 8.620E+0I 2.590E+01 ..0.00E+00 1.400E+01 0.000E+00 9.300E+04 0.OOOE+00 4.280E+00 PR-144 3.220E-54 9.950E-55 0.OOOE+00 5.260E-55 0.OOOE+00 2.140E-51 0.000E+00 1.620E-55 ND-147 5.330E+01 4.320E+01 0.OOOE+00 2.370E+01 0.000E+00 6.850E+04 0.OOOE+00 3.350E+00 W-187 3.470E+03 2.050E+03 0.000E+00 O.OOOE+00 0.000E+00 2.880E+05 0.000E+00 9.210E+02 NP-239 2.070E+00 .1.490E-01 0.OOOE+00 4.300E-01 0.000E+00 1.100E+04 0.000E+00 1.040E-01 Appendix I Ri Child Goat Milk - Page 3 of 3

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX I Ri Child Dose Factors for use in the Gaseous Dose Calculations Agegroup: CHILD Pathway: Grs/Cow/Meat (CMEAT) Units: m2.mrem/yr / XCi/sec;

_ _ _ __ __ _ _mrem/yr / jtCi/m 3 (H-3)

Nuclide Bone . Liver Thyroid. Kidney Lung Gilli. Skin Total Body H-3 0.OOOE+00 2.340E+02 2.340E+02 2.340E+02 2.340E+02 2.340E+02 0.OOOE+00 2.340E+02 C-14 3.830E+08 7.670E+07 7.670E+07 7.670E+07 7.670E+07 7.670E+07 0.000E+00 7.670E+07 NA-24 1.720E-03 1.720E-03 1.720E-03 1.720E-03 1.720E-03 1.720E-03 0.000E+00 1.720E-03 P-32 7.420E+09 3.470E+08 0.OOOE+00 0.OOOE+00 0.OOOE+00 2.050E+08 0.OOOE+00 2.860E+08 CR-51 0.OOOE+00 0.OOOE+00 4.880E+03 *1.330E+03 8.910E+03 4.660E+05 0.000E+00 8.790E+03 MN-54 0.OOOE+00 8.010E+06 0.000E+00 2.250E+06 0.OOOE+00 6.720E+06 0.OOOE+00 2.130E+06 MN-56 0.OOOE+00 1.430E-53 0.000E+00 1.730E-53 0.OOOE+00 2.070E-51 0.OOOE+00 3.230E-54 FE-55 4.570E+08 2.420E+08 0.000E+00 0.OOOE+00 1.70E+08 4.490E+07 0.000E+00 7.510E+07 FE-59 3.760E+08 6.090E+08 0.OOOE+00 0.OOOE+00 1.770E+08 6.340E+08 0.000E+00 3.030E+08 CO-58 0.OOOE+00 1.640E+07 0.OOOE+00 0.OOOE+00 0.000E+00 9.580E+07 0.OOOE+00 5.020E+07 CO-60 0.OOOE+00 6.930E+07 0.000E+00 0.000E+00 0.OOOE+00 3.840E+08 0.OOOE+00 2.040E+08 NI-63 2.910E+10 1.560E+09 0.OOOE+00 0.000E+00 0.000E+00 1.050E+08 0.000E+00 9.910E+08 NI-65 3.520E-52 3.3 1OE-53 0.OOOE+00 0.000E+00 0.OOOE+00 4.060E-51 0.OOOE+00 1.930E-53 CU-64 0.OOOE+00 2.970E-07 0.000E+00 7.180E-07 0.000E+00 1.390E-05 0.000E+00 1.800E-07 ZN-65 3.750E+08 1.OOOE+09 0.000E+00 6.300E+08 0.OOOE+00 1.760E+08 0.OOOE+00 6.220E+08 ZN-69 0.000E+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.000E+00 0.000E+00 0.OOOE+00 BR-83 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.000E+00 0.OOOE+00 0.OOOE+00 9.520E-57 BR-84 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0OOOE+00 BR-85 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.000E+00 RB-86 0.000E+00 5.770E+08 - 0.OOOE-00 0.OOOE+00 0.OOOE+00 3.710E+/-07 0.OOOE+00 3.550E+08 RB-88 0.OOOE+00 0.OOOE+00 0.000E+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 RB-89 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.000E+00 0.OOOE+00 0.000E+00 0.OOOE+00 SR-89 4.820E+08 0.OOOE+00 0.000E+00 0.OOOE+00 0.OOOE+00 1.870E+07 0.OOOE+00 1.380E+07 SR-90 1.040E+10 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 1.400E+08 0.OOOE+00 2.640E+09 SR-91 2.400E-10 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 5.300E-10 0.000E+00 9.050E-12 Appendix I Ri Child Cow Meat - Page 1 of 3

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX I Ri Child Dose Factors for use in the Gaseous Dose Calculations Agegroup: CHILD Pathway: Grs/Cow/Meat (CMEAT) 'Units: m2 mrem/yr / ptCi/sec;

_ __ __mrem/yr ,CUM 3 (H-3)

Nuciide BoneI Liver: Thyroid . Kid.ey Lung Gilli Skin Tota Body SR-92 1.850E-49 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.000E+00 3.490E-48 0.000E+00 7.400E-51 Y-90 1.710E+02 0.OOOE+00 0.000E+00 0.OOOE+00 0.000E+00 4.880E+05 0.000E+00 4.590E+00 Y-91 1.800E+06 0.OOOE+00 0.000E+00 0.000E+00 0.000E+00 2.400E+08 0.000E+00 4.820E+04 Y-91M 0.OOOE+00 0.OOOE+00 0.000E+00 0.OOOE+00 0.000E+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 Y-92 2.410E-39 0.OOOE+00 0.000E+00 0.OOOE+00 0.OOOE+00 6.960E-35 0.OOOE+00 6.890E-41 Y-93 7.440E-12 0.OOOE+00 0.OOOE+00 0.000E+00 0.000E+00 1.11 0E-07 0.OOOE+00 2.040E-13 ZR-95 2.660E+06 5.850E+05 0.000E+00 8.380E+05 0.000E+00 6.11OE+08 0.000E+00 5.210E+05 ZR-97 3.200E-05 4.630E-06 0.OOOE+00 6.650E-06 0.OOOE+00 7.010E-01 0.000E+00 2.730E-06 NB-95 3.100E+06 1.210E+06 0.000E+00 1.130E+06 0.OOOE+00 2.230E+09 0.000E+00 8.620E+05 MO-99 0.000E+00 1.150E+05 0.OOOE+00 2.460E+05 0.OOOE+00 9.510E+04 0.OOOE+00 2.840E+04 TC-99M 6.190E-21 1.210E-20 0.OOOE+00 1.760E-19 6.160E-21 6.910E-18 0.000E-00 2.010E-19 TC-101 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.000E+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 RU-103 1.550E+08 0.OOOE+00 0.OOOE+00 3.900E+08 0.000E+00 4.010E+09 0.OOOE+00 5.960E+07 RU-105 9.020E-28 0.OOOE+00 0.OOOE+00 7.930E-27 0.000E+00 5.890E-25 0.OOOE+00 3.270E-28 RU-106 4.440E+09 0.OOOE+00 0.OOOE+00 5.990E+09 0.OOOE+00 6.900E+10 0.000E+00 5.540E+08 AG-110M 8.390E+06 5.670E+06 0.OOOE+00 1.060E+07 0.OOOE+00 6.740E+08 0.OOOE+00 4.530E+06 TE-125M 5.690E+08 1.540E+08 1.600E+08 0.OOOE+00 0.OOOE+00 5.490E+08 0.OOOE+00 7.590E+07 TE-127 3.380E-10 9.120E-11 2.340E-10 9.630E-10 0.OOOE+00 1.320E-68 0.600E+00 7.260E-11 TE-127M 1.770E+09 4.780E+08 4.240E+08 5.060E+09 0.OOOE+00 1.440E+09 0.OOOE+00 2.110E+08 TE-129 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.000E+00 0.OOOE+00 0.OOOE+00 TE-129M 1.790E+09 5.OOOE+08 5.770E+08 5.260E+09 0.000E+00 2.180E+09 6.000E+00 2.780E+08 TE-131 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE +00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 TE-131M 7.OOOE+02 2.420E+02 4.980E+02 2.340E+03 0.000E+00 9.820E+03 0.OOOE+00 2.580E+02 TE-132 2.120E+06 9.380E+05 1.370E+06 8.710E+06 0.000E+00 9.450E+06 0.OOOE+00 1.130E+06 1-130 3.030E-06 6.130E-06 6.750E-04 9.160E-06 0.OOOE+00 2.870E-06 0.OOOE+00 3.160E-06 Appendix I Ri Child Cow Meat - Page 2 of 3

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX I Ri Child Dose Factors for use in the Gaseous Dose Calculations

'Agegroup: CHILD Pathway:' Grs/Cow/Meat (CMEAT) Units:. m2.mrem/yr / pXCi/sec;

._mrem/yr / tCi/m 3 (H-3)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body 1-131 1.650E+07 1.660E+07 5.500E+09 2.730E+07 0.OOOE+00 1.480E+06 0.OOOE+00 9.460E+06 1-132 1.020E-58 1.880E-58 8.730E-57 2.880E-58 0.OOOE+00 2.210E-58 0.OOOE+00 8.650E-59 1-133 5.670E-01 7.020E-01 1.300E+02 1.170E+00 0.OOOE+00 2.830E-01 0.OOOE+00 2.660E-01 1-134 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.000E+00 0.OOOE+00 0.000E+00 1-135 6.510E-17 1.170E-16 1.040E-14 1.800E-16 0.OOOE+00 8.930E-17 0.OOOE+00 5.550E-17 CS-134 9.220E+08 1.510E+09 0.OOOE+00 4.690E+08 1.680E+08 8.160E+06 0.OOOE+00 3.190E+08 CS- 136 1.620E+07 4.460E+07 0.OOOE+00 2.370E+07 3.540E+06 1.570E+06 0.OOOE+00 2.880E+07 CS-137 1.330E+09 1.280E+09 0.OOOE+00 4.160E+08 1.500E+08 7.990E+06 0.OOOE+00 1.880E+08 CS-138 0.OOOE+00 0.OOOE+00, 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.000E+00 BA- 139 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.000E+00 0.OOOE+00 BA-140 4.380E+07 3.840E+04 0.OOOE+00 1.250E+04 2.290E+04 2.220E+07 0.000E+00 2.560E+06 BA-141 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.000E+00 BA-142 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.000E+00 0.OOOE+00 LA-140 5.590E-02 1.950E-02 0.OOOE+00 0.OOOE+00 0.000E+00 5.440E+02 0.OOOE+00 6.580E-03 LA-142 5.300E-92 1.690E-92 0.OOOE+00 0.OOOE+00 0.OOOE+00 3.350E-87 0.OOOE+00 5.290E-93 CE-141 2.220E+04 1.11OE+04 0.OOOE+00 4.850E+03 0.OOOE+00 1.380E+07 0.OOOE+00 1.640E+03 CE-143 3.170E-02 1.720E+01 0.OOOE+00 7.210E-03 0.OOOE+00 2.520E+02 0.000E+00 2.490E-03 CE-144 2.320E+06 7.260E+05 0.OOOE+00 4.020E+05 0.OOOE+00 1.890E+08 0.OOOE+00 1.240E+05 PR-143 3.340E+04 1.000E+04 0.OOOE+00 5.430E+03 0.OOOE+00 3.600E+07 0.OOOE+00 1.660E+03 PR-144 .-.. 0.OOOE+00 0.OOOE+00- 0.OOOE+00-- 0.OOOE+00 A0.000E 0.OOOE+00 0.OOOE+00 -0.000E+00 ND-147 1.170E+04 9.470E+03 0.OOOE+00 5.190E+03 0.OOOE+00 1.500E+07 0.OOOE+00 7.330E+02 W-187 3.210E-02 1.900E-02 0.OOOE+00 0.OOOE+00 0.OOOE+00 2.670E+00 0.OOOE+00 8.530E-03 NP-239 4.260E-01 3.060E-02 0.OOOE+00 8.850E-02 0.OOOE+00 2.260E+03 0.000E+00 2.150E-02 Appendix I Ri Child Cow Meat - Page 3 of 3

Oconee Nuclear Station 0

January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX I R1 Child Dose Factors for use in the Gaseous Dose Calculations Agegroup: CHILD Pathway: Vegetation (VEG) Units: m 2 -mrem/yr / jiCi/sec; mrem/yr / jtCi/m 3 (H-3)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body H-3 0.OOOE+00 4.010E+03 4.010E+03 4.01OE+03 4.010E+03 4.01OE+03 0.OOOE+00 4.010E+03 C-14 8.890E+08 1.780E+08 1.780E+08 1.780E+08 1,780E+08 1.780E+08 0.OOOE+00 1.780E+08 NA-24 3.730E+05 3.730E+05 3.730E+05 3.730E+05 3.730E+05 3.730E+05 0.OOOE+00 3.730E+05 P-32 3.370E+09 1.580E+08 0.OOOE+00 0.OOOE+00 0.OOOE+00 9.310E+07 0.000E+00 1.300E+08 CR-51 0.OOOE+00 0.OOOE+00 6.500E+04 1.780E+04 1.190E+05 6.210E+06 0.0OOE+00 1.170E+05 MN-54 0.OOOE+00 6.650E+08 0.OOOE+00 1.860E+08 0.OOOE+00 5.580E+08 0.000E+00 1.770E+08 MN-56 0.OOOE+00 1.860E+01 0.OOOE+00 2.250E+01 0.OOOE+00 2.700E+03 0.OOOEt00 4.200E+00 FE-55 8.010E+08 4.250E+08 0.OOOE+00 0.OOOE+00 2.400E+08 7.870E+07 0.OOOE+00 1.320E+08 FE-59 3.980E+08 6.430E+08 0.OOOE+00 0.OOOE+00 1.860E+08 6.700E+08 0.OOOE+00 3.200E+08 CO-58 0.OOOE+00 6.440E+07 0.OOOE+00 0.OOOE+00 0.OOOE+00 3.760E+08 0.OOOE+00 1.970E+08 CO-60 0.000E+00 3.780E+08 0.000E+00 0.OOOE+00 0.OOOE+00 2.100E+09 0.OOOE+00 1.120E+09 NI-63 3.950E+10 2.11OE+09 0.OOOE+00 0.OOOE+00 0.OOOE+00 1.420E+08 0.OOOE+00 1.340E+09 NI-65 1.050E+02 9.890E+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 1.210E+03 0.OOOE+00 5.770E+00 CU-64 0.OOOE+00 1.100E+04 0.OOOE+00 2.660E+04 0.OOOE+00 5.160E+05 0.OOOE+00 6.640E+03 ZN-65 8.130E+08 2.160E+09 0.OOOE+00 1.360E+09 0.OOOE+00 3.800E+08 0.OOOE+00 1.350E+09 ZN-69 9.490E-06 1.370E-05 0.OOOE+00 8.320E-06 0.OOOE+00 8.640E-04 0.OOOE+00 1.270E-06 BR-83 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 5.370E+00 BR-84 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 3.820E- I1 BR-85 0.OOOE+00 0.OOOE+00. 0.OOOE+00 0.000E+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 RB-86 0.OOOE+00 4.520E+08 0.OOOE+00 0.OOOE+00 0.OOOE+00 2.910E+07 0.OOOE+00 2.780E+08 RB-88 0.OOOE+00 4.380E-22 0.OOOE+00 0.OOOE+00 0.OOOE+00 2.150E-23 0.OOOE+00 3.040E-22 RB-89 0.OOOE+00 4.610E-26 0.OOOE+00 0.OOOE+00 0.OOOE+00 4.020E-28 0.000E+00 4.090E-26 SR-89 3.600E+10 0.OOOE+00 0.OOOE+00 0.000E+00 0.OOOE+00 1.390E+09 0.OOOE+00 1.030E+09 SR-90 1.240E+12 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 1.670E+10 0.OOOE+00 3.150E+ I1 SR-91 5.240E+05 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 1.160E+06 0.OOOE+00 1.980E+04 Appendix I Ri Child Vegetation - Page 1 of 3

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX I R1 Child Dose Factors for use in the Gaseous Dose Calculations Agegroup: CHILD Pathway: Vegetation (VEG) Units: m mrem/yr / jiCi/sec;

_ __ _ _ _mrem/yr / .Ci/m 3 (H-3)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body SR-92 7.280E+02 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 1.380E+04 0.000E+00 2.920E+01 Y-90 2.3 10E +04 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 6.570E+07 0.000E+00 6.180E+02 Y-91 1.860E+07 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 2.480E+09 0.OOOE+00 4.990E+05 Y-91M 8.910E-09 0.OOOE+00 O.OOOE+00 O.OOOE+00 0.OOOE+00 1.740E-05 0.000E+00 3.240E-I0 Y-92 1.580E+00 0.OOOE+00 0.OOOE+00 O.OOOE+00 0.OOOE+00 4.580E+04 0.OOOE+00 4.530E-02 Y-93 2.930E+02 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 4.370E+06 0.OOOE+00 8.040E+00 ZR-95 3.860E+06 8.480E+05 0.OOOE+00 i.210E+06 0.OOOE+00 8.850E+08 0.000E+00 7.550E+05 ZR-97 5.700E+02 8.240E+01 0.OOOE+00 1.180E+02 0.OOOE+00 1.250E+07 0.OOOE+00 4.860E+01 NB-95 4.11OE+05 1.600E+05 0.OOOE+00 1.500E+05 0.OOOE+00 2.960E+08 0.OOOE+00 1.140E+05 MO-99 0.OOOE+00 7.710E+06 0.OOOE+00 1.650E+07 0.OOOE+00 6.380E+06 0.OOOE+00 1.910E+06 TC-99M 4.710E+00 9.230E+00 0.OOOE+00 1.340E+02 4.690E+00 5.260E+03 0.000E+00 1.530E+02 TC-101 1.410E-30 1.470E-30 0.OOOE+00 2.51OE-29 7.780E-31 4.680E-30 0.000E+00 1.870E-29 RU- 103 1.530E+07 0.OOOE+00 0.OOOE+00 3.860E+07 0.OOOE+00 3.970E+08 0.000E+00 5.900E+06 RU-105 9.160E+01 0.OOOE+00 0.OOOE+00 8.050E+02 0.OOOE+00 5.980E+04 0.OOOE+00 3.320E+01 RU-106 7.450E+08 O.OOOE+00 0.OOOE+00 1.010E+09 0.OOOE+00 1.160E+10 0.000E+00 9.300E+07 AG-1 10M 3.210E+07 2.170E+07 0.OOOE+00 4.040E+07 0.OOOE+00 2.580E+09 0.OOOE+00 1.730E+07 TE-125M 3.51 OE+08 9.500E+07 9.840E+07 0.OOOE+00 0.000E+00 3.380E+08 0.000E+00 4.670E+07 TE-127 9.850E+03 2.650E+03 6.810E+03 2.800E+04 0.OOOE+00 3.850E+05 0.000E-00 2.11OE+03 TE-127M 1.320E+09 3.560E+08 3.160E+08 3.770E+09 0.OOOE+00 1.070E+09 0.OOOE+00 1.570E+08 TE-129 1.320E-03 3;690E-04--- 9-.430E-04 3,870E-03 0.OOOE+00 8.230E-02 0.000E+00 3.140E-04 TE-129M 8.410E+08 2.350E+08 2.710E+08 2.470E+09 0.OOOE+00 1.030E+09 0.000E+00 1.310E+08 TE-131 2.570E-15 7.830E-16 1.960E-15 7.770E-15 0.OOOE+00 1.350E-14 0.000E+00 7.640E-16 TE-131M 1.540E+06 5.330E+05 1.100E+06 5.160E+06 0.000E+00 2.160E+07 0.000E+00 5.680E+05 TE-132 7.OOOE+06 3.100E+06 4.510E+06 2.880E+07 0.OOOE+00 3.120E+07 0.000E+00 3.740E+06 1-130 6.160E+05 1.240E+06 1.370E+08 1.860E+06 0.OOOE+00 5.820E+05 0.000E+00 6.410E+05 Appendix I Ri Child Vegetation - Page 2 of 3

Oconee Nuclear Station 0

January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX I Ri Child Dose Factors for use in the Gaseous Dose Calculations Agegroup: CHILD Pathway: Vegetation (VEG) Units: m 2 mrem/yr / jCi/sec; mrem/yr / *Ci/m 3 (H-3)

Nuclide Bone Liver Thyroid. Kidney Lung Gilli Skin Total Body 1-131 1.430E+08 1.440E+08 4.750E+10 2.360E+08 0.OOOE+00 1.280E+07 0.OOOE+00 8.170E+07 1-132 9.220E+0 1 1.690E+02 7.860E+03 2.590E+02 0.OOOE+00 1.990E+02 0.OOOE+00 7.790E+0 1 1-133 3.530E+06 4.370E+06 8.11OE+08 7.280E+06 0.000E+00 1.760E+06 0.OOOE+00 1.650E+06 1-134 1.550E-04 2.880E-04 6.620E-03 4.400E-04 0.000E+00 1.910E-04 0.OOOE+00 1.320E-04 1-135 6.260E+04 1.130E+05 9.970E+06 1.730E+05 0.OOOE+00 8.580E+04 0.OOOE+00 5.330E+04 CS-134 1.600E+10 2.630E+10 0.OOOE+00 8.150E+09 2.930E+09 1.420E+08 0.OOOE+00 5.550E+09 CS-136 8.240E+07 2.270E+08 0.OOOE+00 1.210E+08 1.800E+07 7.960E+06 0.OOOE+00 1.470E+08 CS-137 2.390E+10 2.290E+10 0.OOOE+00 7.460E+09 2.680E+09 1.430E+08 0.OOOE+00 3.380E+09 CS-138 6.570E-11 9.130E-11 0.OOOE+00 6.430E-11 6.920E-12 4.210E-11 0.OOOE+00 5.790E-I1 BA-139 4.950E-02 2.640E-05 0.OOOE+00 2.310E-05 1.560E-05 2.860E+00 0.OOOE+00 1.440E-03 BA-140 2.770E+08 2.420E+05 0.OOOE+00 7.890E+04 1.450E+05 1.400E+08 0.OOOE+00 1.610E+07 BA-141 1.990E-21 1.11OE-24 0.OOOE+00 9.620E-25 6.530E-24 1.130E-21 0.OOOE+00 6.460E-23 BA-142 9.930E-39 7.150E-42 0.OOOE+00 5.780E-42 4.200E-42 1.300E-40 0.OOOE+00 5.540E-40 LA-140 3.250E+03 1.130E+03 0.OOOE+00 0.OOOE+00 0.OOOE+00 3.160E+07 0.OOOE+00 3.820E+02 LA-142 3.360E-04 1.070E-04 0.OOOE+00 0.000E+00 0.OOOE+00 2.120E+01 0.000E+00 3.350E-05 CE-141 6.560E+05 3.270E+05 0.000E+00 1.430E+05 0.OOOE+00 4.080E+08 0.OOOE+00 4.860E+04 CE-143 .1.720Et03 9.310E+05 0.OOOE+00 3.910E+02 0.OOOE+00 1.360E+07 0.000E+00 1.350E+02 CE-144 1.270E+08 3.980E+07 0.OOOE+00 2.210E+07 0.OOOE+00 1.040E+10 0.OOOE+00 6.780E+06 PR-143 1.460E+05 4.370E+04 0.OOOE+00 2.370E+04 0.OOOE+00 1.570E+08 0.000E+00 7.230E+03 PR-144 5.380E-26 1.660E-26 0.OOOE+00 8.800E-27 0.OOOE+00 3.580E-23 0.OOOE+00 2.710E-27 ND-147 7.150E+04 5.790E+04 0.OOOE+00 3.180E+04 0.OOOE+00 9.170E+07 0.OOOE+00 4.480E+03 W-187 6.430E+04 3.810E+04 0.OOOE+00 0.OOOE+00 0.OOOE+00 5.350E+06 0.OOOE+00 1.710E+04 NP-239 2.560E+03 1.840E+02 0.OOOE+00 5.310E+02 0.000E+00 1.360E+07 0.OOOE+00 1.290E+02 Appendix I Ri Child Vegetation - Page 3 of 3

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX I Ri Child Dose Factors for use in the Gaseous Dose Calculations Agegr6up: CHILD Pathway: Inhalation (INHL) Units: mrem/yr / ptCi/m 3 Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body H-3 0.OOOE+00 1.120E+03 1.120E+03 1.120E+03 1.120E+03 1.120E+03 0.OOOE+00 1.120E+03 C-14 3.590E+04 6.730E+03 6.730E+03 6.730E+03 6.730E+03 6.730E+03 0.OOOE+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.OOOE+00 1.610E+/-04 P-32. 2.600E+06 1.140E+05 0.OOOE+00 0.OOOE+00 0.OOOE+00 4.220E+04 0.OOOE+00 9.880E+04 CR-51 0.000E+00 0.OOOE+00 8.550E+01 2.430E+01 1.700E+04 1.080E+03 0.OOOE+00 1.540E+02 MN-54 0.OOOE+00 4.290E+04 O.OOOE+00 1.000E+04 1.580E+06 2.290E+04 0.OOOE+00 9.510E+03 MN-56 0.OOOE+00 1.660E+/-00 0.OOOE+00 1.670E+00 1.310E+04 1.230E+05 0.OOOE+00 3.120E-01 FE-55 4.740E+04 2.520E+04 0.OOOE+00 0.OOOE+00 1.11OE+05 2.870E+03 0.OOOE+00 7.770E+03 FE-59 2.070E+04 3.340E+04 0.OOOE+00 O.OOOE+00 1.270E+06 7.070E+04 0.OOOE+00 1.670E+04 CO-58 O.OOOE+00 1.770E+03 O.OOOE+00 0.OOOE+00 1.11OE+06 3.440E+04 0.OOOE+00 3.160E+03 CO-60 0.OOOE+00 1.3 1OE+04 O.OOOE+00 0.OOOE+00. 7.070E+06 9.620E+04 0.OOOE+00 2.260E+04 NI-63 8.210E+05 4.620E+04 O.OOOE+00 0.OOOE+00 2.750E+05 6.330E+03 0.OOOE+00 2.800E+04 NI-65 2.990E+00 2.960E-01 0.OOOE+00 0.OOOE+00 8.180E+03 8:400E+04 0.000E+00 1.640E-01 CU-64 0.OOOE+00 1.990E+00 O.OOOE+00 6.030E+00 9.580E+03 3.670E+04 0.OOOE+00 1.070E+00 ZN-65 4.260E+04 1.130E+05 O.OOOE+00 7.140E+04 9.950E+05 1.630E+04 0.OOOE+00 7.030E+04 ZN-69 6.700E-02 9.660E-02 0.OOOE+00 5.850E-02 1.420E+03 1.020E+04 0.OOOE+00 8.920E-03 BR-83 O.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 4.740E+02 BR-84 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00. O.000E+00 5.480E+02 BR-85 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.060E+00 0.OOOE+00 0.OOOE+00 0.000E+00 2.530E+01

-RB-86 0.OOOE+00 1.980E+05-.--. 0.OOOE+/-00 0.OOOE+00 0.OOOE+00 7.990Et+03- 0.OOOE+00 ,1.140E+05 RB-88 0.OOOE+00 5.620E+02 0.OOOE+00 0.OOOE+00 0.OOOE+00 1.720E+01 0.OOOE+/-00 3.660E+02 RB-89 0.OOOE+00 3.450E+02 0.OOOE+00 0.OOOE+00 0.OOOE+00 1.890E+00 0.OOOE+00 2.900E+02 SR-89 5.990E+05 0.OOOE+00 0.OOOE+00 O.OOOE+00 2.160E+06 1.670E+05 0.OOOE+00 1.720E+04 SR-90 1.010E+08 0.OOOE+00 0.OOOE+00 O.OOOE+00 1.480E+07 3.430E+05 0.OOOE+00 6.440E+06 SR-91 1.210E+02 0.OOOE+00 0.OOOE+00 0.OOOE+00 5.330E+04 1.740E+05 0.OOOE+00 4.590E+00 Appendix I Ri Child Inhalation - Page 1 of 3 0

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX I R. Child Dose Factors for use in the Gaseous Dose Calculations Agegroup: CHILD Pathway: Inhalation (INHL) Units: mrem/yr / ptCi/m 3 Nuclide Bone Liver Thyroid Kidney, Lung Gilli Skinft Total Body_

SR-92 1.310E+01 0.OOOE+00 0.OOOE+00 0.OOOE+00 2.400E+04 2.420E+05 0.OOOE+00 5.250E-01 Y-90 4.11OE+03 0.000E+00 0.OOOE+00 0.OOOE+00 2.620E+05 2.680E+05 0.OOOE+00 1.11OE+02 Y-91 9.140E+05 0.OOOE+00 0.OOOE+00 0.OOOE+00 2.630E+06 1.840E-+05 0.OOOE+00 2.440E+04 Y-91M 5.070E-01 0.OOOE+00 0.OOOE+00 0.OOOE+00 2.810E+03 1.720E+03 0.OOOE+00 1.840E-02 Y-92 2.030E+01 0.OOOE+00 0.OOOE+00 0.OOOE+00 2.390E+04 2.390E+05 0.OOOE+00 5.810E-01 Y-93 1.860E+02 0.OOOE+00 0.OOOE+00 0.OOOE+00 7.440E+04 3.880E+05 0.OOOE+00 5.11 OE+00 ZR-95 1.900E+05 4.180E+04 0.OOOE+00 5.960E+04 2.230E+06 6.11OE+04 0.OOOE+00 3.700E+04 ZR-97 1.880E+02 2.720E+01 0.OOOE+00 3.880E+01 1.130E+05 3.510E+05 0.OOOE+00 1.600E+01 NB-95 2.350E+04 9.180E+03 0.OOOE+00 8.620E+03 6.140E+05 3.700E+04 0.OOOE+00 6.550E+03 MO-99 0.OOOE+00 1.720E+02 0.OOOE+00 3.920E+02 1.350E+05 1.270E+05 0.OOOE+00 4.260E+01 TC-99M 1.780E-03 3.480E-03 0.OOOE+00 5.070E-02 9.510E+02 4.8 1OE÷03 0.OOOE+00 5.770E-02 TC-101 8.100E-05 8.510E-05 0.OOOE+00 1.450E-03 5.850E+02 1.630E+01 0.000E+00 1.080E-03 RU-103 2.790E+03 0.OOOE+00 0.OOOE+00 7.030E+03 6.620E+05 4.480E+04 0.000E+00 1.070E+03 RU-105 1.530E+00 0.OOOE+00 0.OOOE+00 1.340E+00 1.590E+04 9.950E+04 0.OOOE+00 5.550E-01 RU-106 1.360E+05 0.OOOE+00 0.OOOE+00 1.840E+05 1.430E+07 4.290E+05 0.OOOE-00 1.690E+04 AG- 110M 1.690E+04 1.140E+04 0.OOOE+00 2.120E+04 5.480E+06 1.000E+05 0.OOOE+00 9.140E+03 TE-125M 6.730E+03 2.330E+03 1.920E+03 0.OOOE+00 4.770E+05 3.380Ef-04 0.OOOE+00 9.140E+02 TE- 127 2.770E+00 9.510E-01 1.960E+00 7.070E+00 1.000E+04 5.620E+04 0.OOOE+00 6.1OOE-01 TE-127M 2.490E+04 8.550E+03 6.070E+03 6.360E+04 1.480E+06 7.140E+04 0.OOOE+00 3.020E+03 TE-129 9.770E-02 3.500E-02 7.140E-02 /2.570E-01 2.930E+03 2.550E+04 0.OOOE+00 2.380E-02 TE-129M 1.920E+04 6.840E+03 6.330E+03 5.030E+04 1.760E+06 1.820E+05 0.OOOE+00 3.040E+03 TE- 131 2.170E-02 8.440E-03 1.700E-02 5.880E-02 2.050E+03 1.330E+03 0.OOOE+00 6.590E-03 TE-131M 1.340E+02 5.920E+01 9.770E+01 4.OOOE+02 2.060E+05 3.080E+05 0.OOOE+00 5.070E+01 TE-132 4.810E+02 2.720E+02 3.170E+02 1.770E+03 3.770E+05 1.380E+05 0.OOOE+00 2.630E+02 1-130 8.180E+03 1.640E+04 1.850E+06 2.450E+04 0.OOOE+00 5.11OE+03 0.OOOE+00 8.440E+03 Appendix I Ri Child Inhalation - Page 2 of 3

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX I R. Child Dose Factors for use in the Gaseous Dose Calculations Agegroup: CHILD Pathway: Inhalation (INHL) Units: mrem/yr / pCi/m3 Nuclide  : Bone ,Liver Thyroid Kidfiey, ]I Lu: Gilli "" Ski' , TotalBody 1-131 4.810E+04 4.810E+04 1.620E+07 7.880E+04 0.OOOE+00 2.840E+03 0.OOOE+00 2.730E+04

.1-132 2.120E+03 4.070E+03 1.940E+05 6.250E+03 0.OOOE+00 3.200E+03 0.000E+00 1.880E+03 1-133 1.660E+04 2.030E+04 3.850E+06 3.380E+04 0.OOOE+00 5.480E+03 0.OOOE+00 7.700E+03 1-134 1.170E+03 2.160E+03 5.070E+04 3.300E+03 0.OOOE+00 9.550E+02 0.OOOE+00 9.950E+02 1-135 4.920E+03 8.730E+03 7.920E+05 1.340E+04 0.000E+00 4.440E+03 0.OOOE+00 4.140E+03 CS-134 6.510E+05 1.01OE+06 0.OOOE+00 3.300E+05 1.210E+05 3.850E+03 0.OOOE+00 2.250E+05 CS-136 6.510E+04 1.710E+05 0.OOOE+00 9.550E+04 1.450E+04 4.180E+03 0.OOOE+00 1.160E+05 CS-137 9.060E+05 8.250E+05 0.OOOE+00 2.820E+05 1.040E+05 3.620E+03 0.OOOE+00 1.280E+05 CS-138 6.330E+02 8.400E+02 0.000E+00 6.220E+02 6.810E+01 2.700E+02 0.000E+00 5.550E+02 BA-139 1.840E+00 9.840E-04 0.OOOE+00 8.620E-04 5.770E+03 5.770E+04 0.OOOE+00 5.360E-02 BA-140 7.400E+04 6.480E+01 0.OOOE+00 2.110E+01 1.740E+06 1.020E+05 0.OOOE+00 4.330E+03 BA-141 1.960E-01 1.090E-04 0.OOOE+00 9.470E-05 2.920E+03 2.750E+02 0.OOOE+00 6.360E-03 BA-142 5.OOOE-02 3.600E-05 0.000E+00 2.910E-05 1.640E+03 2.740E+00 0.OOOE+00 2.790E-03 LA-140 6.440E+02 2.250E+02 0.000E+00 0.000E+00 1.830E+05 2.260E+05 0.OOOE+00 7.550E+01 LA-142 1.300E+00 4.11OE-01 0.OOOE+00 0.OOOE+00 8.700E+03 7.580E+04 0.OOOE+00 1.290E-01 CE-141 3.920E+04 1.950E+04 0.000E+00 8.550E+03 5.440E+05 5.660E+04 0.OOOE+00 2.900E+03 CE-143 3.660E+02 1.990E+02 0.OOOE+00 8.360E4-01 1.150E+05 1.270E+05 0.OOOE+00 2.870E+01 CE-144 6.770E+06 2.120E+06 0.OOOE+00 1.170E+06 1.200E+07 3.880E+05 0.000E+00 3.610E+05 PR-143 1.850E+04 5.550E+03 0.OOOE+00 3.006E+03 4.330E+05 9.730E+04 0.OOOE+00 9.140E+02 PR-144 - 5.960E-02 - 1.850E-02 . 0.000E+00 - 9.770E-03 1.570E+03 1.970E+02 0.OOOE+00 .3.OOOE-03 _

ND-147 1.080E+04 8.730E+03 0.OOOE+00 4.810E+03 3.280E+05 8.210E+04 0.OOOE+00 6.810E+02 W-187 1.630E+01 9.660E+00 0.OOOE+00 0.OOOE+00 4.11OE+04 9.100E+04 0.OOOE+00 4.330E+00 NP-239 4.660E+02 3.340E+01 0.000E+00 9.730E+01 5.810E+04 6.400E+04 0.OOOE+00 2.350E+01 Appendix I Ri Child Inhalation - Page 3 of 3 0

0 January, 2009 Oconee Nuclear Station Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX I Ri Child Dose Factors for use in the Gaseous Dose Calculations

'Aegrup:CHILD PathWay: Ground Plane Deposition (GPD) Units:
UnWS
,- iinim re/r/ /

m2"mrem/yr is Wxi/sec Nuclide,, Bone Liver Thyroid Kidney* Lung Gitii' Skin, Total Boddy H-3 0.OOOE+00 0.OOOE+00 0.O00E+00 0.OOOE+00. 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.000E+00 C-14 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.000E+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.000E÷00 NA-24 1.190E+07 1.190E+07 1.190E+07 1.190E+07 1.190E+07 1.190E+07 1.390E+07 1.190E+07 P-32 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 CR-51 4.660E+06 4.660E+06 4.660E+06 4.660E+06 4.660E+06 4.660E+06 5.510E+06 4.660E+06 MN-54 1.390E+09 1.390E+09 1.390E+09 1.390E+09 1.390E+09 1.390E+09 1.630E+09 1.390E+09 MN-56 9.020E+05 - 9.020E+05 9.020E+05 9.020E+05 9.020E+05 9.020E+05 1.070E+06 9.020E+05 FE-55 O.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.000E+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 FE-59 2.730E+08 2.730E+08 2.730E+08 2.730E+08 2.730E+08 2.730E+08 3.210E+08 2.730E+08 CO-58 3.790E+08 3.790E+08 3.790E+08 3.790E+08 3.790E+08 3.790E+08 4.440E+08 3.790E+08 CO-60 2.150E+10 2.150E+10 2.150E+10 2.150E+10 2.150E+10 2.150E+10 2.530Eq+10 2.150E+10 NI-63 0.OOOE+00 0.000-E00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00. 0.OOOE+00 NI-65 2.970E+05 2.970E+05 2.970E+05 '2.970E+05 2.970E+05 2.970E+05 3.450E+05 2.970E+05 CU-64 6.070E+05 6.070E+05 6.070E+05 6.070E+05 6.070E+05 6.070E+05 6.880E+05 6.070E+05 ZN-65 7.470E+08 7.470E+08 7.470E+08 7.470E+08 7.470E+08 7.470E+08 8.590E+08 7.470E+08 ZN-69 0.OOOE+00 0.OOOE+00 0.600E+00 O.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 BR-83 4.870E+03 4.870E+03 4.870E+03 4.870E+03 4.870E+03. 4.870E+03 7.080E+03 4.870E+03 BR-84 2.030E+05 2.030E+05 2.030E+05 2.030E+05 2.030E+05 2.030E+05 .2.360E+05 2.030E+05 BR-85 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.600E+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 RB-86 8.990E+06 8.990E+06 8.990E+06 8.990E+06 8.990E+06 8.990E+06 1.030E+07 8.990E+06 RB-88 3.310E+04 3.310E+04 3.310E+04 3.310E+04 3.310E+04 3.310E+04 3.780E+04 3.310E+04 RB-89 1.230E+05 1.230E+05 1.230E+05 1.230E+05 1.230E+05 1.230E+05 1.480E+05 1.230E+05 SR-89 2.160E+04 2.160E+04 2.160E+04 2.160E+04 2.160E+04 2.160E+04 2.510E+04 2.160E+04 SR-90 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.000E+00 SR-91 2.150E+06 2.150E+06 2.150E+06 2.150E+06 2.150E+06 2.150E+06 2.510E+06 2.150E+06 Appendix I Ri Child Ground Plane Deposition - Page 1 of 3

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX I Ri Child Dose Factors for use in the Gaseous-Dose Calculations Agegroup: CHILD Pathway: Ground Plane Deposition (GPD) Units: m2.mrem/yr / pti/sec "Nuciide  ! Bone Live'r

  • Thyroid ,,-'Kidney Lung Gilli, . Skin Total.Body SR-92 7.770E+05 7.770E+05 7.770E+05 7.770E+05 7.770E+05 7.770E+05 8.630E+05 7.770E+05 Y-90 4.490E+03 4.490E+03 4.490E+03 4.490E+03 4.490E+03 4.490E+03 5.3 1OE+03 4.490E+03 Y-91 1.070E+06 1.070E+06 1.070E+06 1.070E+06 1.070E+06 1.070E+06 1.210E+06 1.070E+06 Y-91M 1.000E+05 1.000E+05 1.000E+05 1.000E+05 1.000E+05 1.000E+05 1.160E+05 1.000E+05

-Y-92 1.800E+05 1.800E+05 1.800E+05 1.800E+05 1.800E+05 1.800E+05 2.140E+05 1.800E+05 Y-93 1.830E+05 1.830E+05 1.830E+05 1.830E+05 1.830E+05 1.830E+05 2.510E+05 1.830E+05 ZR-95 2.450E+08 2.450E+08 2.450E+08 2.450E+08 2.450E+08 2.450E+08 2.840E+08 2.450E+08 ZR-97. 2.960E+06 2.960E+06 2.960E+06 2.960E+06 2.960E+06 2.960E+06 3.440E+06 2.960E+06 NB-95 1.370E+08 1.370E+08 1.370E+08 1.370E+08 1.370E+08 1.370E+08 1.610E+08 1.370E+08 MO-99 3.990E+06 3.990E+06 3.990E+06 3.990E+06 3.990E+06 3.990E+06 4.630E+06 3.990E+06 TC-99M 1.840E+05 1.840E+05 1.840E+05 1.840E+05 1.840E+05 1.840E+05 2.11OE+05 1.840E+05 TC-101 2.040E+04 2.040E+04 2.040E+04 2.040E+04 2.040E+04 2.040E+04 2.260E+04 2.040E+04 RU-103 1.080E+08 1.080E+08 1.080E+08 1.080E+08 1.080E+08 1.080E+08 1.260E+08 1.080E+08 RU-105 6.360E+05 6.360E+05 6.360E+05 6.360E+05 6.360E+05 6.360E+05 7.210E+05 6.360E+05 RU-106 4.220E+08 4.220E+08 4.220E+08 4.220E+08 4.220E+08 4.220E+08 5.070E+08 4.220E+08 AG- 110M 3.440E+09 3.440E+09 3.440E+09 3.440E+09 3.440E+09 3.440E+09 4.0 1OE+09 3.440E+09 TE-125M 1.550E+06 1.550E+06 1.550E+06 1.550E+06 1.550E+06 1.550E+06 2.130E+06 1.550E+06 TE- 127 2.980E+03 2.980E+03 2:980E+03 2.980E+03 2.980E+/-03 2.980E+03 3.280E+03 2.980E+03 TE-127M 9.160E+04 9.160E+04 9.160E+04 9.160E+04 9.160E+04 9.160E+04 1.080E+05 9.160E+04

-TE-129, 2.620E+04 2.620E+04 2.620E+04 2.620E+04 - 2.620E+04 2.620E+/-04 3.100E+04 2.620E+04 TE-l129M 1.980E-07 1.980E+07 1.980E+07 1.980E+07 1.980E+07 1.980E+07 2.310E+07 1.980E+07 TE- 131 2.920E+04 2.920E+04 2.920E+04 2.920E+04 2.920E+04 2.920E+04 3.450E+07 2.920E+04 TE-131M 8.030E+06 8.030E+06 8.030E+06 8.030E+06 8.030E+06 8.030E+06 9.460E+06 8.030E+06 TE-132 4.230E+06 4.230E+06 4.230E+06 4.230E+06 4.230E+06 4.230E+06 4.980E+06 4.230E+06 1-130 5.510E+06 5.510E+06 5.510E+06 5.510E+06 5.510E+06 5.510E+06 6.690E+06 5.510E+06 Appendix I Ri Child Ground Plane Deposition - Page 2 of 3 0 0

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January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX I K Child Dose Factors for use in the Gaseous Dose Calculations Agegroup: CHILD Pathway,:i Ground Plane Deposition (GPD) Units: m2 mrem/yr / pCi/sec Nuclide .. Bone- Liver.- Thyroid Kidney Lung -GilhivTtalBody Skin 1-131 1.720E+07 1.720E+07 1.720E+07 1.720E+07 1.720E+/-07 1.720E+07 2.090E+07 1.720E+07 1-132 1.250E+06 1.250E+06 1.250E+06 1.250E+06 1.250E+06 1.250E+06 1.470E+06 1.250E+06 1-133 2.450E+06 2.450E+06 2.450E+06 2.450E+06 2.450E+06 2.450E+06 2.980E+06 2.450E+06 1-134 4.470E+05 4.470E+05 4.470E+05 4.470E+05 4.470E+05 4.470E+05 5.300E+05 4.470E+05 1-135 2.530E+06 2.530E+06 2.530E+06 2.530E+06 2.530E+06 2.530E+06 2.950E+06 2.530E+06 CS-134 6.860E+09 6.860E+09 6.860E+09 6.860E+09 6.860E+09 6.860E+09 8.OOOE+09 6.860E+09 CS-136 1.510E+08 1.510E+08 1.510E+08 1.510E+08 1.510E+08 1.510E+08 1.710E+08 1.5iOE+08 CS-137 1.030E+10 1.030E+10 1.030E+i0 1.030E+10 1.030E+10 1.030E+10 1.200E+10 1.030E+10 CS-138 3.590E+05 3.590E+05 3.590E+05 3.590E+05 3.590E+05 3.590E+05 4.100E+05 3.590E+05 BA-139 1.060E+05 1.060E+05 1.060E+05 1.060E+05 1.060E+05 1.060E+05 1.190E+05 1.060E+05 BA-140 2.050E+07 2.050E+07 2.050E1+07 2.050E+07 2.050E+07 2.050E+07 2.350E+07 2.050E+07 BA-141 4.170E+04 4.170E+04 4.170E+04 4.170E+04 4.170E+04 4.170E+04 4.750E+04 4.170E+04 BA-142 4.490E+04 4.490E+04 4.490E+04 4.490E+04 4.490E+04 4.490E+04 5.11OE+04 4.490E+04 LA-140 1.920E+07 1.920E+07 1.920E+07 1.920E+07 1.920E+07 1.920E+07 2.180E+07 1.920E+07 LA-142 7.600E+05 7.600E+05 7.600E+05 7.600E+05 7.600E+05 7.600E+05 9.120E+05 7.600E+05 CE-141 1.370E+07  !.370E+07 1.370E+07 1.370E+07 1.370E+07 1.370E+07 1.540E+07 1.370E+07 CE-143 2.310E+06 2.310E+06 2.310E+06 2.310E+06 2.310E+06 2.310E+06 2.630E+06 2.310E+06 CE-144 6.950E+07 6.950E+07 6.950E+07 6.950E+07 6.950E+07 6.950E+07 8.040E+07 6.950E+07 PR-143 0.OOOE+00 0.000E+00 0.000E+00 0.OOOE+00 0.000E+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 PR-144 1.830E+03 1.830E+03 1.830E+03 1.830E+03 1.830E+03 1.830E+03 2.11OE+03 1.830E+03 ND-147 8.390E+06 8.390E+06 8.390E+06 8.390E+06 8.390E+06 8.390E+06 1.010E+07 8.390E+06 W-187 2.350E+06 2.350E+06 2.350E+06 2.350E+06 2.350E+06 2.350E+06 2.730E+06 2.350E+06 NP-239 1.710E+06 1.710E+06 1.710E+06 1.710E+06 1.710E+06 1.710E+06 1.980E+06 1.710E+06 Appendix I Ri Child Ground Plane Deposition - Page 3 of 3

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX J R. Infant Dose Factors for -use in the Gaseous Dose Calculations Agegroup: NAT Pah y:Grs/CowIMilk (CMILK) Unts mmrem/yr / ýCi/sec;

_______________ _______ ________ mremlyr / .Ci~m 3 (H-3)

Nuclide Bonhe Liver Thyroid Kidne ~ Ln il kn TtlBd H-3 0.OOOE+00 2.380E+03 2.380E+03 2.380E+03 2.380E+03 2.380E+03 0.OOOE+00 2.380E+03 C-14 2.340E+09 5.OOOE+08 5.OOOE+08 5.OOOE+08 5.00013+08 5.000E+09 0.OOOE+00 5.OOOE+08 NA-24 1.540E+07 1,540E+07 1.540E+07 1.540E+07 1.540E+07 1.540E+07 0.OOOE+00 1.540E+07 P-32 1.600E+1 I 9.430E+09 0.OOOE+00 0.OOOE+00 0.OOOE+00 2.170E+09 0.OOOE+00 6.210E+/-09 CR-51 0.OOOE+00 0.OOOE+00 1.050E+05 2.300E+04 2.050E+05 4.700E+06 0.OOOE+00 1.610E+05 MN-54 0.00013+00 3.900E+07 0.00013+00 8.640E+/-06 0.000E+00 1.430E+07 0.OOOE+00 8.840E+06 Iv[N-56 0.OOOE+00 3.100E-02 0.OOOE+00 2.660E-02 0.OOOE+00 2.8 10E+00 0.OOOE+/-00 5.340E-03 FE-55 1.350E+08 8.730E+07 0.OOOEtOO 0.OOOE+00 4.270E+07 1.110OE+07 0.0008+00 2.330E+07 FE-59 2.240E+08 3.920E+08 0.OOOE+00 0.OOOE+00 1.160E+08 1.870E+/-08 0.OOOE+00 1.540E+08

ýCO-5,8 0.OOOE+00 2.420E+07 0.OOOE+00 0.OOOE+00 0.OOOE+00 6.040E+/-07 0.OOOE+00 6.050E+07 CO-60. 0.OOOE+00- 8.820E+07 0.OOOE+00 0.OOOE+00 0.OOOE+00 2.100OE+08 0.OOOE+O0 2.080E+08 NI-63 3.490E+10 2.160E+09 0.OOOE+00 0.OOOE+00 0.OOOE+00 1.070E+08 0.OOOE+00 1.210E+09 NI-65 3.510OE+00 3.970E-0 I 0.OOOE+00 0.000E+00 0.OOOE+00 3.020E+0 1 0.OOOE+/-00 .1.800E-0 1 CU-64 0.OOOE+00. 1.850E+05 0.OOOE+00 3.14013+05 0.OOOE+/-00 3.8 1OE06 0.OOOE+00 8.590E+04 ZN-65 5.550E+09 1.900E+10 0.OOOE+00 9.230E+09 0.000E+00 1.610E+10 0.OOOE+00 8.780E+09 ZN-69 2.020E-1I1 3.630E-1I 0.OOOE+00 1.51 OE-1I 0.OOOE+00 2.960E-09 0.OOOE+0O 2.700E- 12 BR-83 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.000E+00 0.OOOE+00 9.340E-0 1 BR-84 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.00013t00 0.OOOE+00 0.OOOE+00 1.260E-22 BR-85 0.00013+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.00013+00 O.OOOE+00 0.OOOE+/-00 0.OOOE+00

~RB 0.OOOE+00 ~=- 2.230E+ 10 0.OOOE+00=. -O=.000E+O0 0.OOOE+00 ~=5.690E+08 0.OOOE+00 1.IOOE+10 RB-88 0.OOOE-I00 1.886E-44 0.OOOE+00 0.OOOE+00 0.OOOE+00 1.830E-44 0.OOOE+/-00 1.030E-44 RB-89 0.OOOE+00 3.290E-52 0.OOOE+/-00 0.OOOE+00 0.OOOE+00 1.120E-52 0.OOOE+00 2.260E-52 SR-89 1.260E+10 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 2.590E+08 0.000E+00 3.6 10E+0 8 SR-90 1.220E+1 1 0.00013+00 0.OOOE+00 0.OOOE+00 0.000E+00 1.520E+09 0.OOO13+00 3.100E+10 SR-91 2.720E+05 0.OOOE+00 0.000E+00 0.OOOE+00 0.OOOE+00 3.220E+05 0.00O13+00 9.8 3 E+3 Appendix J Ri Infant Cow Milk - Page 1 of 3

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January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX J R1 Infant Dose Factors for use in the Gaseous Dose Calculations Agegroup: INFANT -Pathway: Grs/Cow/Milk (CMILK) Units::. m 2.mrem/yr / piCi/sec;

_______ ________ mrem/yr C/,jCm 3 (H-3)

Nuclide Bone Liver Thyoid Kidney Lung Gi!ii Skin, . Total Body SR-92 4.640E+00 0.OOOE+00 6.oooE+00 0.OOOE+00 0.OOOE+00 5.OOOE+01 0.OOOE+00 1.720E-01 Y-90 6.810E+02 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 9.410E+05 0.OOOE+00 1.830E+01 Y-91 7.330E+04 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 5.250E+06 0.OOOE+00 1.950E+03 Y-91M 5.670E-19 0.OOOE+00. 0.OOOE+00 0.OOOE+00 0.OOOE+00 1.890E-15 0.OOOE+00 1.930E-20 Y-92 5.380E-04 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 1.030E+01 0.OOOE+00 1.5 1E-05 Y-93 2.160E+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.000E+00 1.700E+04 0.OOOE+00 5.870E-02 ZR-95. 6.800E+03 1.660E+03 0.000E+00 1.790E+03 0.OOOE+00 8.260E+05 0.OOOE+00 1.180E+03 ZR-97 4.060E+00 6.970E-01 0.OOOE+00 7.030E-01 0.000E+00 4.450E+04 0.600E+00 3.180E-01 NB-95 5.930E+05 2.440E+05 0.000E+00 1.750E+05 0.OOOE+00 2.060E+08 0.OOOE+00 1.410E+05 MO-99 0.OOOE+00 2.080E+08 0.OOOE+00 3.11 OE+08 0.000E+00 6.850E+07 0.OOOE+00 4.060E+07 TC-99M 2.750E+01 5.670E+01 0.OOOE+00 6.100E+02 2.960E+01 1.650E+04 0.OOOE+00 7.300E+02 TC-101 2.470E-59 3.11OE-59 0.OOOE+00 3.700E-58 1.700E-59 5.280E-57 0.OOOE+00 3.080E-58 RU-103 8.670E+03 0.OOOE+00 0.OOOE+00 1.800E+04 0.OOOE+00 1.050E+05 0.OOOE+00 2.900E+03 RU-105 8.050E-03 0.OOOE+00 0.OOOE+00 5.920E-02 0.OOOE+00 3.200E+00 0.OOOE+00 2.710E-03 RU-106 1.900E+05 0.OOOE+00 0.OOOE+00 2.250E+05 0.OOOE+00 1.440E+06 0.OOOE+00 2.380E+04 AG-1 10M 3.860E+08 2.820E+08 0.OOOE+00 4.030E+08 0.OOOE+00 1.460E+10 0.OOOE+00 1.860E+08 TE-125M 1.510E+08 5.040E+07 5.070E+07 0.OOOE+00 0.OOOE+00 7.180E+07 0.OOOE+00 2.040E+07 TE-127 6.320E+03 2.120E+03 5.140E+03 1.540E+04 0.OOOE+00 1.330E+05 0.OOOE+00 1.360E+03 TE-127M 4.210E+08 1.400E+08 1.220E+08 1.040E+09 0.000E+00 1.700E+08 0.OOOE+00 5.100E+07 TE-129 2.720E-09 9.380E-10 2.280E-09 6.770E-09 0.OOOE+00 2.170E-07 0.OOOE+00 6.350E-10 TE-129M 5.570E+08 1.910E+08 2.140E+08 1.390E+09 0.OOOE+00 3.330E+08 0.OOOE+00 8.580E+07 TE-131 3.430E-32 1.270E-32 3.060E-32 8.760E-32 0.OOOE+00 1.380E-30 0.OOOE+00 9.610E-33 TE-131M 3.380E+06 1.360E+06 2.750E+06 9.350E+06 0.OOOE+00 2.290E+07. 0.OOOE+00 1.120E+06 TE-132 2.11OE+07 1.040E+07 1.540E+07 6.530E+07 0.OOOE+00 3.870E+07 0.OOOE+00 9.750E+06 1-130 3.550E+06 7.810E+06 8.750E+08 8.580E+06 0.OOOE+00 1.670E+06 0.OOOE+00 3.130E+06 Appendix J Ri Infant Cow Milk - Page 2 of 3

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX J Ri Infant Dose Factors for use in the Gaseous Dose Calculations Agegroup: INFANT Pathway:, Grs/Cow/Milk (CMILK) Units: m 2 -mrem/yr / pCi/sec; Cim 3 (H-3) immrem/yr Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin. Total Body 1-131. 2.720E+09 3.200E+09 1.050E+12 3.740E+09 0.OOOE+00 1.140E+08 0.OOOE+00 1.410E+09 1-132 1.430E+00 2.900E+00 l.360E+02 3.240E+00 0.000E+00 2.350E+00 0.OOOE+00 1.030E+00 1-133 3.630E+07 5.280E+07 9.600E+09 6.210E+07 0.000E+00 8.930E+06 0.OOOE+00 1.550E+07 1-134 1.760E- 11 3.600E- 11 8.400E-10 4.030E- I1 0.OOOE+00 3.720E-11 0.OOOE+00 1.280E-11 1-135 1.120E+05 2.230E+05 2.060E+07 2.490E+05 0.OOOE+00 8.080E+04 0.OOOE+00 8.140E+04 CS-134 3.650E+10 6.800E+10 0.OOOE+00 1.750E+10 7.180E+09 1.850E+08 0.OOOE+00 6.870E+09 CS-136 1.980E+09 5.810E+09 0.000E+00 2.320E+09 4.740E+08 8.820E+07 0.OOOE+00 2.170E+09 CS-137 5.150E+10 6.020E+10 0.OOOE+00 1.620E+10 6.550E+09 1.880E+08 0.0OOE+00 4.270E+09 CS-138 8.390E-23 1.360E-22 0.OOOE+00 6.800E-23 1.060E-23 2.180E-22 0.000E+00 6.610E-23 BA-139 4.270E-07 2.830E-10 0.OOOE+00 1.700E-10 1.720E-10 2.710E-05 0.OOOE+00 1.240E-08 BA-140 2.410E+08 2.410E+05 0.OOOE+00 5.720E+04 1.480E+05 5.920E+07 0.000E+00 1.240E+07 BA-141 3.930E-45 2.690E-48 0.OOOE+00 1.620E-48 1.640E-48 4.800E-44 0.OOOE+00 1.240E-46 BA-142 2.430E-79 2.020E-82 0.OOOE+00 1.160E-82 1.220E-82 1.000E-78 0.OOOE+00 1.200E-80 LA-140 4.050E+01 1.600E+01 0.OOOE+00 0.OOOE+00 0.OOOE+00 1.880E+05 0.OOOE+00 4.11OE+00 LA-142 1.700E-10 6.250E-11 0.OOOE+00 0.OOOE+00 0.OOOE+00 1.060E-05 0.OOOE+00 1.500E-11 CE-141 4.340E+04 2.640E+04 0.OOOE+00 8.150E+03 0.OOOE+00 1.370E+07 0.OOOE+00 3.11OE+03 CE-143 3.970E+02 2.630E+05 0.OOOE+00 7.670E+01 0.OOOE+00 1.540E+06 0.OOOE+00 3.OOOE+01 CE-144 2.330E+06 9.520E+05 0.000E+00 3.850E+05 0.OOOE+00 1.330E+08 0.OOOE+00 1.300E+05 PR-143 1.490E+03 5.550E+02 0.OOOE+00 2.060E+02 0.000E+00 7.840E+05 0.OOOE+00 7.360E+01 PR-144 5.690E-53 2.200E-53 O 0.OOOE+00 7.980E-54-- 0.000E+00- 1.020E-48 0.000E+00- --- 2.870E-54 ND-147 8.810E+02 9.050E+02 0.OOOE+00 3.490E+02 0.OOOE+00 5.740E+05 0.000E+00 5.550E+01 W-187 6.080E+04 4.230E+04 0.OOOE+00 0.OOOE+00 0.OOOE+00 2.480E+06 0.OOOE+00 1.460E+04 NP-239 3.650E+01 3.260E+00 0.OOOE+00 6.510E+00 0.OOOE+00 9.430E+04 0.OOOE+00 1.840E+00 Appendix J Ri Infant Cow Milk - Page 3 of 3

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX J Ri Infant Dose Factors for use in-the Gaseous Dose Calculations Agegroup: INFANT Pathway: Grs/Goat/Milk (GMILK) Units: m 2 mrem/yr / gtCi/sec;

________mrem/yr / jtCi/m 3 (H-3)

-Nuclide Bone Liver ... ,Thyroid , Kidney Lun Gilli Ttal:,Body TSkin H-3 0.OOOE+00 4.860E+03 4.860E+03 4.860E+03 4.860E+03 4.860E+03 0.000E+00 4.860E+03 C-14 2.340E+09 5.000E+08 5.000E+08 5.OOOE+08 5.OOOE+08 5.000E+08 0.OOOE+00 5.OOOE+08 NA-24 1.850E+06. 1.850E+06 1.850E+06 1.850E+06 1.850E+06 1.850E+06 0:OOOE+00 1.850E+06 P-32 1.920E+I1 1.130E+10 0.000E+00 0.OOOE+00 0.000E+00 2.600E+09 0.000E+00 7.460E+09 CR-51 0.OOOE+00 0.000E+00 1.260E+04 2.760E+03 2.460E+04 5.640E+05 0.000E+00 1.940E+04 MIN-54 0.OOOE+00 4.680E+06 0.000E+00 1.040E+06 0.OOOE+00 1.720E+06 0.000E+00 1.060E+06 MN-56 0.000E+00 3.720E-03 0.OOOE+00 3.190E-03 0.000E+00 3.380E-01 0.000E+00 6.410E&04 FE-55 1.760E+06 1.130E+06 0.000E+00 0.OOOE+00 5.550E+05 1.440E+05 0.000E+00 3.030E+05 FE-59 2.920E+06 5.100E+06 0.OOOE+00 0.000E+00 1.510E+06 2.430E+06 0.OOOE+00 2.010E+06 CO-58 0.OOOE+00 2.91 OE+06 0.OOOE+00 0.OOOE+00 0.OOOE+00 7.250E+06 0.000E+00 7.260E+06 CO-60 0.000E+00 1.060E+07 0.OOOE+00 0.OOOE+00 0.OOOE+00 2.520E+07 0.OOOE+00 2.500E+07 NI-63 4.190E+09 2.590E+08 0.000E+00 0.OOOE+00 0.OOOE+00 1.290E+07 0.OOOE+00 1.450E+08 NI-65 4.210E-01 4.760E-02 0.000E+00 0.OOOE+00 0.000E+00 3.620E+00 0.OOOE+00 2.170E-02 CU-64 0.OOOE+00 2.070E+04 0.OOOE+00 3.500E+04 0.000E+00 4.240E+05 0.OOOE+00 9.570E+03 ZN-65 6.660E+08 2.280E+09 0.OOOE+00 1.I 1OE+09 0.OOOE+00 1.930E+09 0.OOOE+00 1.050E+09 ZN-69 2.420E-12 4.360E-12 0.OOOE+00 1.810E-12 O.OOOE+00 3.550E-10 0.OOOE+00 3.240E-13 BR-83 0.OOOE+00 0.OOOE+00 0.000E+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.000E+00 1.120E-01 BR-84 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.000E+00 0.OOOE+00 0.OOOE+00 O.OOOE+00 1.5 1OE-23 BR-85 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.000E+00 0.000E+00 0.OOOE+00 0.OOOE+00 RB-86 0.OOOE+00 2.670E+09 0.OOOE+00 0.OOOE+00 0.OOOE+00 6.830E+07 0.OOOE+00 1.320E+09 RB-88 0.OOOE+00 2.250E-45 O.OOOE+00 0.OOOE+00 0.OOOE+00 2.190E-45 0.OOOE+00 1.230E-45 RB-89 0.OOOE+00 3.940E-53 0.OOOE+00 0.OOOE+00 0.OOOE+00 1.340E-53 0.OOOE+00 2.720E-53 SR-89 2.640E+10 0.OOOE+00 0.OOOE+00 O.OOOE+00 0.OOOE+00 5.430E+08 0.OOOE+00 7.580E+08 SR-90 2.550E+11 0.OOOE+00 0.000E+00 0.000E+00 0.OOOE+00 3.190E+09 0.000E+00 6.500E+10 SR-91 5.700E+05 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 6.750E+05 0.000E+00 2.060E+04 Appendix J Ri Infant Goat Milk - Page 1 of 3

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX J R. Infant Dose Factors for use in the Gaseous Dose Calculations Agegroup: INFANT Pathway:,; Grs/Goat/Milk (GMILK) Units: m 2.mrem/yr / p Ci/sec;

....... mrem/yr / jtCi/m 3 (H-3)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body SR-92 9.750E+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.000E+00 1.050E+02 0.OOOE+00 3.620E-01 Y-90 8.170E+01 0.OOOE+00 0.OOOE+00 0.000E+00 0.000E+00 1.130E+05 0.OOOE+00 2.190E+-00 Y-9 1. 8.790E+03 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.000E+00 6.300E+05 0.OOOE+00 2.340E+02 Y-91M 6.810E-20 0.OOOE+00 0.000E+00 0.000E+00 0.OOOE+00 2.270E-16 0.OOOE+00 2.320E-21 Y-92 6.450E-05 0.OOOE+00 0.OOOE+00 0.000E+00 0.000E+00 1.230E+00 0.OOOE+00 1.810E-06 Y-93 2.590E-01 0.OOOE+00 0.000E+00 0.000E+00 0.OOOE+00 2.040E+03 0.OOOE+00 7.050E-03 ZR-95 8.170E+02 1.990E+02 0.000E+00 2.140E+02 0.OOOE+00 9.910E+04 0.OOOE+00 1.410E+02 ZR-97 4.870E-01 8.360E-02 0.OOOE+00 8.430E-02 0.OOOE+00 5.340E+03 0.OOOE+00 3.820E-02 NB-95 7.120E+04 2.930E+04 0.OOOE+00 2.100E+04 0.OOOE+00 2.480E+07 0.OOOE+00 1.700E+04 MO-99 0.OOOE+00 2.500E+07 0.OOOE+00 3.730E+07 0.OOOE+00 8.220E+06 0.OOOE+00 4.870E+06 TC-99M 3.300E+00 6.800E+00 0.OOOE+00 7.320E+01 3.550E+00 1.970E+03 0.000E+00 8.760E+01 TC-101 2.960E-60 3.730E-60 0.OOOE+00 4.440E-59 2.030E-60 6.340E-58 0.OOOE+00 3.690E-59 RU-103 1.040E+03 0.OOOE+00 0.OOOE+00 2.170E+03 0.OOOE+00 1.270E+04 0.OOOE+00 3.480E+02 RU-105 9.660E-04 0.OOOE+00 0.OOOE+00 7.11OE-03 0.OOOE+00 3.840E-01 0.OOOE+00 3.250E-04 RU-106 2.280E+04 0.OOOE+00 0.OOOE+00 2.700E+04 0.OOOE+00 1.730E+05 0.OOOE+00 2.850E+03 AG-1 10M 4.630E+07 ( 3.380E+07 0.OOOE+00 4.830E+07 0.OOOE+00 1.750E+09 0.OOOE+00 2.240E+07 TE-125M 1.810E+07 6.050E+06 6.090E+06 0.OOOE+00 0.000E+00 8.620E+06 0.OOOE+00 2.450E+06 TE-127 7.580E+02 2.540E+02 6.170E+02 1.850E+03 0.OOOE+00 1.590E+04 0.OOOE+00 1.630E+02

.TE-127M 5.050E+07 1.680E+07 1.460E+07 1.240E+08 0.000E+00 2.040E+07 0.OOOE+00 6.120E+06 TE-129 3.260E-10-= 1.130E-10 -23740E-10 8.130E-10

  • 0.000E00E--- 2.610E-08 - 0.000E+00 7.620E-11 TE-129M 6.690E+07 2.290E+07 2.570E+07 1.670E+08 0.OOOE+00 3.990E+07 0.OOOE+00 1.030E+07 TE-131 4.11OE-33 1.520E-33 3.670E-33 1.050E-32 0.000E+00 1.660E-31 0.OOOE+00 1.150E-33 TE-131M 4.050E+05 1.630E+05 3.310E+05 1.120E+06 0.OOOE+00 2.750E+06 0.OOOE+00 1.350E+05 TE-132 2.530E+06 1.250E+06 1.850E+06 7.840E+06 0.OOOE+00 4.640E+06 0.OOOE+00 1.170E+06 1-130 4.260E+06 9.370E+06 1.050E+09 1.030E+07 0.OOOE+00 2.01OE+06 0.OOOE+00 3.760E+06 Appendix J Ri Infant Goat Milk - Page 2 of 3

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX J R. Infant Dose Factors for use in the Gaseous Dose Calculations Dose.. ..

R:Infn Agegroup: INFANT Pathway: Grs/Goat/Milk (GMILK) Units: m 2 mrem/yr / .Ci/sec; mrem/yr / ptCi/m 3 (H1-3)

Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body 1-131 3.260E+09 3.850E+09 1.260E+12 4.490E+09 0.OOOE+00 1.370E+08 0.OOOE+00 1.690E+09 1-132 1.720E+00 3.480E+00 1.630E+02 3.890E+00 0.OOOE+00 2.820E+00 0.OOOE+00 1.240E+00 1-133 4.350E+07 6.340E+07 1.150E+10 7.450E+07 0.OOOE+00 1.070E+07 0.OOOE+00 1.860E+07 1-134 2.11OE-11 4.320E-11 1.010E-09 4.830E- I 0.OOOE+00 4.470E- I1 0.OOOE+00 1.540E- 11 1-135 1.350E+05 2.680E+05 2.400E+07 2.990E+05 0.OOOE+00 9.700E+04 0.OOOE+00 9.770E+04 CS-1 34 1.090E+1I 2.040E+11 0.OOOE+00 5.250E+10 2.150E+10 5.540E+08 0.OOOE+00 2.060E+10 CS-136 5.930E+09 1.740E+10 0.OOOE+00 6.950E+09 1.420E+09 2.650E+08 0.OOOE+00 6.510E+09 CS-137 1.540E+11 1.810E+1 0.OOOE+00 4.850E+10 1.960E+10 5.650E+08 0.OOOE+00 1.280E+10 CS-138 2.520E-22 4.090E-22 0.OOOE+00 2.040E-22 3.190E-23 6.540E-22 0.OOOE+00 1.980E-22 BA-139 5.130E-08 3.400E-11 0.OOOE+00 2.040E-11 2.060E-11 3.250E-06 0.OOOE+00 1.480E-09 BA-140 2.890E+07 2.890E+04 0.OOOE+00 6.870E+03 1.780E+04 7.1OOE+06 0.OOOE+00 1.490E+06 BA-141 43720E-46 3.230E-49 0.OOOE+00 1.940E-49 1.960E-49 5.760E-45 0.OOOE+00 1.490E-47 BA-142 2.920E-80 2.430E-83 0.OOOE+00 1.400E-83 1.470E-83 1.200E-79 0.OOOE+00 1.440E-81 LA-140 4.860E+00 1.920E+00 0.OOOE÷00 0.OOOE+00 0:000E-00 2.250E+04 0.OOOE+00 4.930E-01 LA-142 2.040E- 11 7.500E-12 0.OOOE+00 0.OOOE+00 0.OOOE+00 1.270E-06 0.OOOE+00 1.790E-12 CE-141 5.200E103 3.170E+03 0.OOOE+00. 9.790E+02 0.OOOE+00 1.640E+06 0.OOOE+00 3.740E+02 CE-143 4.760E+0 1 3.160E+04 0.OOOE+00 9.200E+00 0.000E+00 1.840E+05 0.OOOE+00 3.600E+00 CE-144 2.790E+05 1.140E+05 0.OOOE+00 4.620E+04 0.000E+00 1.600E+07 0.OOOE+00 1.560E+04 PR- 143 1.780E+02 6.670E+01 0.OOOE+00 2.480E+01 0.OOOE+00 9.4 10E+04 0.OOOE+00 8.840E+00 PR-144 6.830E-54 2.640E-54 0.OOOE+00 9.570E-55 0.OOOE+00 1.230E-49 0.OOOE+00 3.440E-55 ND-147 1.060E+02 1.090E+02 0.OOOE+00 4.190E+01 0.OOOE+00 6.880E+04 0.OOOE+00 6.650E+00 W-187 7.3 00E+ 03 5.070E+03 0.OOOE+00 0.OOOE+00 0.OOOE+00 2.980E+05 0.OOOE+00 1.750E+03 NP-239 4.380E+00 3.910E-01 0.OOOE+00 7.810E-01 0.OOOE+00 1.130E+04 0.OOOE+00 2.210E-01 Appendix J Ri Infant Goat Milk - Page 3 of 3

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX J Ri Infant Dose Factors for use in the Gaseous Dose Calculations

.Agegroup: INFANT Pathway: Inhalation (INHL) Units: mrem/yr / Ci/m3 Nuclide 6 Bonie :Liver,:; Thyroid _Kidney: l Lung " Gilli Skin Total Body H-3 0.OOOE+00 6.470E+02 6.470E+02 6.470E+02 6.470E+02 6.470E+02 0.OOOE+00 6.470E+02 C-14 2.650E+04 5.310E+03 5.310E-4+03 5.310E+03 5.310E+03 5.310E+03 0.000E+00 5.310E+03 NA-24 1.060E+04 1.060E+04 1.060E+04 1.060E+04 1.060E+04 1.060E+04 0.OOOE+00 1.060E+04 P-32 ' 2.030E+06 1.120E+05 0.000E+00 0.OOOE+00 0.OOOE+00 1.610E+04 0.OOOE+00 7.740E+04

  • CR-51 0.OOOE+00 0.OOOE+00 5.750E+01 1.320E+01 1.280E+04 3.570E+02 0.OOOE+00 8.950E+01 MN-54 0.000E+00 2.530E+04 0.000E+00 4.980E+03 1.000E+06 7.060E+03 0.OOOE+00, 4.980E+03 MN-56 0.OOOE+00 1.540E+00 0.OOOE+00 1.100E+00 1.250E+04 7.170E+04 0.000E+00 2.210E-01 FE-55 1.970E+04 1.170E+04 0.OOOE+00 0.000E+00 8.690E+04 1.090E+03 0.OOOE+00 3.330E+03 FE-59 1.360E+04 2.350E+04 0.OOOE+00 O.OOOE+00 1.010E+06 2.480E+04 0.OOOE+00 9.480E+03 CO-58 0.OOOE+00 1.220E+03 0.OOOE+00 0.OOOE+00 7.770E+05 1.11OE+04 O.OOOE+00 1.820E+03 CO-60 0.OOOE+00 8.020E+03 0.OOOE+00 0.OOOE+00 4.510E+06 3.190E+04 0.000E+00 1.180E+04 NI-63 3.390E+/-05 2.040E+04 0.OOOE+00 0.OOOE+00 2.090E+05 2.420E+03 0.OOOE+00 1.160E+04

-NI-65 2.390E+00 2.840E-01 0.OOOE+00 0.000E+00 8.120E+03 5.010E+04 0.OOOE+00 1.230E-01 CU-64 0.000E+00 1.880E+00 0.000E+00 3.980E+00 9.300E+03 1.500E+04 0.000E+00 7.740E-01I ZN-65 1.930E+04 6.260E+04 0.OOOE+00 3.250E+04 6.470E+05 5.140E+04 0.000E+00 3.11OE+04 ZN-69 5.390E-02 9.670E-02 0.000E+00 4.020E-02 1.470E+03 1.320E+04 0.OOOE+00 7.180E-03 BR-83 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 O.OOOE+00 0.OOOE+00 0.OOOE+00 3.810E+02 BR-84. 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 4.OOOE+02 BR-85 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 2.040E+01 RB-86 0.OOOE+00 1.900E+05 0.OOOE+00 0.OOOE+00 OOOE+/-00 .. 3.040E+03 0.OOOE+00 8.820E+-04 RB-88 0.OOOE+00 5.570E+02 0.OOOE+00 0.OOOE+00 0.000E+00 3.390E+02 0.OOOE+00 2.870E+02 RB-89 0.OOOE+00 3.210E+02 0.OOOE+00 0.OOOE+00 0.OOOE+00 6.820E+01 0.060E+00 2.060E+02 SR-89 3.980E+05 0.OOOE+00 0.OOOE+00 0.OOOE+00 2.030E+06 6.400E+04 O.OOOE+00 1.140E+04 SR-90 4.090E+07 0.000E+00 0.OOOE+00 0.OOOE+00 1.120E+07 1.310E+05 0.OOOE+00 2.590E+06 SR-91 9.560E+01 0.OOOE+00 0.OOOE+00 0.OOOE+00 5.260E+04 7.340E+04 0.OOOE+00 3.460E+00 Appendix J Ri Infant Inhalation - Page 1 of 3

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX J Ri Infant Dose Factors for use in the Gaseous Dose Calculations Agegroup: INFANT Pathway: Inhalation (INHL) Units: mrem/yr /p.Ci/m 3 Nuclide - Bone Liver. Thyroid Kidney,. - Lung Gilli Skin Total Body SR-92 1.050E+01 0.OOOE+00 0.OOOE+00 0.OOOE+00 2.380E+04 1.400E+05 0.OOOE+00 3.910E-01 Y-90 3.290E+03 0.OOOE+00 0.OOOE+00 0.OOOE+00 2.690E+05 1.040E+05 0.OOOE+00 8.820E+01 Y-91 5.880E+05 0.OOOE+00 0.OOOE+00 0.OOOE+00 2.450E+06 7.030E+04 0.OOOE+00 1.570E+04 Y-91M 4.070E-01 0.OOOE+00 0.OOOE+00 0.OOOE+00 2.790E+03 2.350E+03 0.OOOE+00 1.390E-02 Y-92 1.640E+01 0.OOOE+00 0.000E+00 0.OOOE+00 2.450E+04 1.270E+05 0.000E+00 4.610E-01 Y-93 1.500E+02 0.OOOE+00 0.OOOE+00 O.OOOE+00 7.640E+04 1.670E+05 0.OOOE+00 4.070E+00 ZR-95 1.150E+05 2.790E+04 .0.000E+00 3.11 OE+04 1.750E+06 2.170E+04 0.OOOE+00 2.030E+04 ZR-97 1.500E+02 2.560E+01 0.OOOE+00 2.590E+01 1.100E+05 1.400E+05 0.OOOE+00 1.170E+01 NB-95 1.570E+04 6.430E+03 0.OOOE+00 4.720E+03 4.790E+05 1.270E+04 0.OOOE+00 3.780E+03 MO-99 0.OOOE+00 1.650E+02 0.OOOE+00 2.650E+02 1.350E+05 4.870E+04 0.OOOE+00 3.230E+01 TC-99M 1.400E-03 2.880E-03 0.OOOE+00 3.11OE-02 8.11OE+02 2.030E+03 0.060E+00 3.720E-02 TC-101 6.510E-05 8.230E-05 0.OOOE+00 9.790E-04 5.840E+02 8.440E+02 0.000E+00 8.120E-04 RU-103 2.020E+03 0.OOOE+00 0.OOOE+00 4.240E+03 5.520E+05 1.610E+04 0.06OE+00 6.790E+02 RU-105 1.220E+00 0.OOOE+00 0.OOOE+00 8.990E-01 1.570E+04 4.840E+04 0.000E+00 4.100E-01 RU-106 8.680E+04 0.OOOE+00 0.OOOE+00 1.070E+05 1.160E+07 1.640E+05 0.060E+00 1.090E+04 AG- 110M 9.980E+03 7.220E+03 0.OOOE+00 1.090E+04 3.670E+06 3.300E+04 0.OOOE+00 5.OOOE+03 TE-125M 4.760E+03 1.990E+03 1.620E+03 0.OOOE+00 4.470E+05 1.290E+04 0.OOOE+00 6.580E+02 TE-127 2.230E+00 9.530E-01 1.850E+00 4.860E+00 1.030E+04 2.440E+04 0.OOOE+00 4.890E-01 TE-127M 1.670E+04 6.900E+03 4.870E+03 3.750E+04 1.310E+06 2.730E+04 0.OOOE+00 2.070E+03 TE-129 7.880E-02 3.470E-02 6.750E-02 1.750E-01 3.OOOE+03 2.630E+04 0.OOOE+00 1.880E-02 TE-129M 1.410E+04 6.090E+03 5.470E+03 3.180E+04 1.680E+06 6.900E+04 0.OOOE+00 2.230E+03 TE- 131 1.740E-02 8.220E-03 1.580E-02 3.990E-02 2.060E+03 8.220E+03 0.OOOE+00 5.OOOE-03 TE-131M 1.070E+02 5.500E+01 .8.930E+01 2.650E+02 1.990E+05 1.190E+05 0.OOOE+00 3.630E+01 TE-132 3.720E+02 2.370E+02 2.790Eq+02 1.030E+03 3.400E+05 4.410E+04 0.OOOE+00 1.760E+02 11-130 6.360E+03 1.390E+04 1.600E+06 1.530E+04 0.OOOE+00 1.990E+03 0.OOOE+00 5.570E+03 Appendix J Ri Infant Inhalation - Page 2 of 3

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX J Ri Infant Dose Factors for use in the Gaseous Dose Calculations Agegroup: INFANT Pathway: Inhalation (INHL) Units: mrem/yr / pCi/m3 Nuclide Bone Liver Thyroid Kidney Lung Gilli: Skin Total Body 1-131 3.790E+04 4.440E+04 1.480E+07 5.180E+04 0.OOOE+00 1.060E+03 0.OOOE+00 1.960E+04 1-132 1.690E+03 3.540E+03 1.690E+05 3.950E+03 0.OOOE+00 1.900E+03 0.OOOE+00 1.260E+03 1-133 1.320E+04 1.920E+04 3.560E+06 2.240E+04 0.OOOE+00 2.160E+03 0.OOOE+00 5.600E+03 1-134 9.210E+02 1.880E+03 4.450E+04 2.090E+03 0.OOOE+00 1.290E+03 0.000E+00 6.650E+02 1-135 3.860E+03 7.600E+03 6.960E+05 8.470E+03 0.OOOE+00 1.830E+03 0.OOOE+00 2.770E+03 CS-134 3.960E+05 7.030E+05 0.OOOE+00 1.900E+05 7.970E+04 1.330E+03 0.000E+00 7.450E+04 CS-136 4.830E+04 1.350E+05 0.OOOE+00 5.640E+04 1.180E+04 1.430E+03 0.000E+00 5.290E+04 CS-137 5.490E+05 6.120E+05 0.OOOE+00 1.720E+05 7.130E+04 1.330E+03 0.OOOE+00 4.550E+04 CS-138 5.050E+02 7.810E+02 0.OOOE+00 4.1OOE+02 6.540E+01 8.760E+02 0.000E+00 3.980E+02 BA-139 1.480E+00 9.840E-04 0.OOOE+00 5.920E-04 5.950E+03 5.100E+04 0.OOOE+00 4.300E-02 BA-140 5.600E+04 5.600E+01 0.OOOE+00 1.340E+01 1.600E+06 3.840E+04 0.OOOE+00 2.900E+03 BA-141 1.570E-01 1.080E-04 0.OOOE+00 6.500E-05 2.970E+03 4.750E+03 0.OOOE+00 4.970E-03 BA-142 3.980E-02 3.300E-05 0.OOOE+00 1.900E-05 1.550E+03 6.930E+02 0.000E+00 1.960E-03 LA-140 5.050E+02 2.OOOE+02 0.OOOE+00 O.OOOE+00 1.680E+05 8.480E+04 0.OOOE+00 5.150E+01 LA-142 1.030E+00 3.776E-01 0.OOOE+00 0.OOOE+00 8.220E+03 5.950E+04 0.OOOE+00 9.040E-02 CE- 141 2.770E+04 1.670E+04 0.OOOE+00 5.250E+03 5.170E+05 2.160E+04 0.OOOE+00 1.990E+03 CE- 143 2.930E+02 1.930E+02 0.OOOE+00 5.640E+01 1.160E+05 4.970E+04 0.OOOE+00 2.210E+01 CE-144 3.190E406 1.210E-I+06 0.000E+00 5.380E+05 9.840E+06 1.480E+05 0.OOOE+00 1.760E+05 PR-143 1.400E+04 5.240E+03 0.OOOE+00 1.970E+03 4.330E+05 3.720E+04 0.000E+00 6.990E+02 PR-144 . 4.790E-02 .1.850E-02 - 0.000E+00 6.720E-03 . 1.6.10E+03 4.280E++/-03 0.OOOE+00 2.410E-03 ND-147 7.940E+03 8.130E+03 0.OOOE+00 3.150E+03 3.220E+05 3.120E+04 0.OOOE+00 5.OOOE+02 W-187 1.300E+01 9.020E+00 0.OOOE+00 0.OOOE+00 3.960E+04 3.560E+04 0.OOOE+00 3.120E+00 NP-239 3.710E+02 3.320E+01 0.OOOE+00 6.620E+01 5.950E+04 2.490E+04 0.OOOE+00 1.880E+01 Appendix J Ri Infant Inhalation - Page 3 of 3

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January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX J R; Infant Dose Factors for use in the Gaseous Dose Calculations Agegroup: INFANT Pathway: Ground Plane Deposition (GPD) Units: m2.mrem/yr / j4Ci/sec Nuclide Bone Liver Thyroid Kidney, Lung Gilli. Skin Total Body H-3 0.OOOE+00 0.OOOE+00. 0.OOOE+00 O.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 C-14 0.OOOE+00 0.OOOE+00. 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.000E+00 0.OOOE+00 NA-24 1.190E+07 1.190E+07 1.190E+07 1.190E+07 1.190E+07 1.190E+07 1.390E+07 .1.190E+07 P-32 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.000E+00 0.OOOE+00 0.000E-O0 CR-51 4.660E+06 4.660E+06 4.660E+06 4.660E+06 4.660E+06 4.660E+06 5.510E+06 4.660E+06 MN-54 1.390E+09 1.390E+09 1.390E+09 1.390E+09 1.390E+09 1.390E+09 1.630E+09 1.390E+09 MN-56 9.020E+05 9.020E+05 9.020E+05 9.020E+05 9.020E+05 9.020E+05 1.070E+06 9.020E+05 FE-55 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 FE-59 2.730E+08 2.730E+08 2.730E+08 2.730E+08 2.730E+08 2.730E+08 3.210E+08 2.730E+08 CO-58 3.790E+08 3.790E+08 3.790E+08 3.790E+08 3.790E+08 3.790E+08 4.440E+08 3.790E+08 CO-60 2.150E+10 2.150E+10 2.150E+10 2.150E+10 2.150E+10 2.150E+10 2.530E+10 2.150E+10 NI-63 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 NI-65 2.970E+05 2.970E+05 2.970E+05 2.970E+05 2.970E+05 2.970E+05 3.450E+05 2.970E+05 CU-64 6.070E+05 6.070E+05 6.070E+05 6.070E+05 6.070E+05 6.070E+05 6.880E+05 6.070E+05 ZN-65 7.470E+08 7.470E+08 7.470E+08 7.470E+08 7.470E+08 7.470E+08 8.590E+08 7.470E+08 ZN-69 0.OOOE+00 0.000E+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 BR-83 4.870E+03-§ 4.870E+03 4.870E+03 4.870E+03 4.870E+03 4.870E+03 7.080E+03 4.870E+03 BR-84 2.030E+05 2.030E+05 2.030E+05 2.030E+05 2.030E+05 2.030E+05 2.360E+05 2.030E+05 BR-85 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.000E+00 RB-86 8.990E+06 8.990E+06 8.990E+06 8.990E+06 8.990E+06 8.990E+06 1.030E+07 8.990E+06 RB-88 3.31OE+04 3.310E+04 3.310E+04 3.310E+04 3.310E+04 3.310E+04 3.780E+04 3.310E+04 RB-89 1.230E+05 1.230E+05 1.230E+05 1.230E+05 1.230E+05 1.230E+05 1.480E+05 1.230E+05 SR-89 2.160E+04 2.160E+04 2.160E+04 2.160E+04 2.160E+04 2.160E+04 2.510E+04 2.160E+04 SR-90 0.OOOE+00 0.OOOE+00 *0.000E+00 O.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 SR-91 2.150E+06 2.150E+06 2.150E+06 2.150E+06 2.150E+06 2.150E+06 2.510E+06 2.150E+06 Appendix J Ri Infant Ground Plane Deposition - Page I of 3

Oconee Nuclear Station January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX J Ri Infant Dose Factors for use in the Gaseous Dose Calculations Agegroup: INFANT Pathway:. Ground Plane Deposition (GPD) Units: m2.mrem/yr / jaCi/sec Nuclide Bone Liver Thyroid Kidney.'.. Lung Gilli ý'$ki'n Total Body SR-92 7.770E+05 7.770E+05 7.770E+05 7.770E+05 7.770E+05 7.770E+05 8.630E+05 7.770E+05 Y-90 4.490E+03 4.490E+03 4.490E+03 4.490E+03 4.490E+03 4.490E+03 5.310E+03 4.490E+03 Y-91 1.070E+06 1.070E+06 1.070E+06 1.070E+06 1 .070E+06 1.070E+06 1.210E+06 1.070E+06 Y-91M 1.000E+05 1.000E+05 1.000E+05 1.000E+05 1.000E+05 1.000E+05 1.160E+05 1.000E+05 Y-92 1.800E+05 1.800E+05 1.800E+05 1.800E+05 1.800E+05 1.800E+05 2.140E+05 1.800E+05 Y-93 1.830E+05 1.830E+05 1.830E+05 1.830E+05 1.830E+05 1.830E+05 2.510E+05 1.830E+05 ZR-95 2.450E+08 2.450E+08 2.450E+08 2.450E+08 2.450E+08 2.450E+08 2.840E+08 2.450E+08 ZR-97 2.960E+06 2.960E+06 2.960E+06 2.960E+06 2.960E+06 2.960E+06 3.440E+06 2.960E+06 NB-95 1.370E+08 1.370E+08 1.370E+08 1.370E+08 1.370E+08 1.370E+08 1.610E+08 1.370E+08 MO-99 3.990E+06 3.990E+06 3.990E+06 3.990E+06 3.990E+06 3.990E+06 4.630E+06 3.990E+06 TC-99M 1.840E+05 1.840E+05 1.840E+05 1.840E+05 1.840E+05 1.840E+05 2.110E+05 1.840E+05 TC-101 2.040E+04 2.040E+04 2.040E+04 2.040E+04 2.040E+04 2.040E+04 2.260E+04 2.040E+04 RU-103 1.080E+08 1.080E+08 1.080E+08 1.080E+08 1.080E+08 1.080E+08 1.260E+08 1.080E+08 RU-105 6.360E+05 6.360E+05 6.360E+05 6.360E+05 6.360E+05 6.360E+05 7.210E+05 6.360E+05 RU-106 4.220E+08 4.220E+08 4.220E+08 4.220E+08 4.220E+08 4.220E+08 5.070E+08 4.220E+08 AG- 110M 3.440E+09 3.440E+09 3.440E+09 3.440E+09 3.440E+09 3.440E+09 4.010E+09 3.440E+09 TE-125M 1.550E+06 1.550E+06 1.550E+06 1.550E+06 1.550E+06 1.550E+06 2.130E+06 1.550E+06 TE-127 2.980E+03 2.980E+03 2.980E,+03 2.980E+03 2.980E+03 2.980E+03 3.280E+03 2.980E+03 TE-127M 9.160E+04 9.160E+04 9.160E+04 9.160E+04 9.160E+04 9.160E+04 1.080E+05 9.160E+04 TE-129 2.620E+04 2.620E+04 2.620E+04- 2.620E+04 - 2.620E+04 2.620E+04 -- 3.100E+04 2.620E+04 TE-129M 1.980E+07 1.980E+07 1.980E+07 1.980E+07 1.980E+07 1.980E+07 2.310E+07 1.980E+07 TE- 131 2.920E+04 2.920E+04 2.920E+04 2.920E+04 2.920E+04 2.920E+04 3.450E+07 2.920E+04 TE- 131M 8.030E+06 8.030E+06 8.030E+06 8.030E+06 8.030E+06 8.030E+06 9.460E+06 8.030E+06 TE-132 4.230E+06 4.230E+06 4.230E+06 4.230E+06 4.230E+06 4.230E+06 4.980E+06 4.230E+06 1-130 5.510E+06 5.510E+06 5.510E+06 5.510E+06 5.510E+06 5.510E+06 6.690E+06 5.510E+06 Appendix J Ri Infant Ground Plane Deposition - Page 2 of 3

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January, 2009 Offsite Dose Calculation Manual (ODCM) Revision 49 APPENDIX J Ri Infant Dose Factors for use in the Gaseous Dose Calculations Agegroup: INFANT Pathway: Ground Plane Deposition (GPD) Units: m 2. mrem/yr / tCi/sec Nuclide Bone Liver Thyroid Kidney Lung Gilli Skin Total Body 1-131 1.720E+07 1.720E+07 1.720E+07 1.720E+07 1.720E+07 1.720E+07 2.090E+07 1.720E+07 1-132 1.250E+06 1.250E+06 1.250E+06 1.250E+06 1.250E+06 1.250E+06 1.470E+06 1.250E+06 1-133 2.450E+06 2.450E+06 2.450E+06 2.450E+06 2.450E+06 2.450E+06 2.980E+06 2.450E+06 1-134 4.470E+05 4.470E+05 4.470E+05 4.470E+05 4.470E+05 4.470E+05 5.300E+05 4.470E+05 1-135 2.530E+06 2.530E+06 2.530E+06 2.530E+06 2.530E+06 2.530E+06 2.950E+06 2.530E+06 CS-134 6.860E+09 6.860E+09 6.860E+09 6.860E+09 6.860E+09 6.860E+09 8.OOOE+09 6.860E+09 CS-136 1.510E+08 1.510E+08 1.510E+08 1.510E+08 1.510E+08 1.510E+08 1.710E+08 1.510E+08 CS-137 1.030E+10 1.030E+10 1.030E+10 1.030E+10 1.030E+10 1.030E+10 1.200E+10 1.030E+10 CS-138 3.590E+05 3.590E+05 3.590E+05 3.590E+05 3.590E+05 3.590E+05 4.100E+05 3.590E+05 BA-139 1.060E+05 1.060E+05 1.060E+05 1.060E+05 1.060E+05 1.060E+05 1.190E+05 1.060E+05 BA-140 2.050E+07 2.050E+07 2.050E+07 2.050E+07 2.050E+07 2.050E+07 2.350E+07 2.050E+07 BA-141 4.170E+04 4.170E+04 4.170E+04 4.170E+04 4.170E+04 4.170E+04 4.750E+04 4.170E+04 BA-142 4.490E+04 4.490E+04 4.490E+04 4.490E+04 4.490E+04 4.490E+04 5.11OE+04 4.490E+04 LA- 140 1.920E+07 1.920E+07 1.920E+07 1.920E+07 1.920E+07 1.920E+07 2.180E+07 1.920E+07 LA-142 7.600E+05 7.600E+05 7.600E+05 7.600E+05 7.600E+05 7.600E+05 9.120E+05 7.600E+05 CE-141 1.370E+07 1.370E+07 1.370E+07 1.370E+07 1.370E+07 1.370E+07 1.540E+07 1.370E+07 CE-143 2.310E+06 2.310E+06 2.310E+06 2.310E+06 2.310E+06 2.310E+06 2.630E+06 2.310E+06 CE-144 6.950E+07 6.950E+07 6.950E+07 6.950E+07 6.950E+07 6.950E+07 8.040E+07 6.950E+07 PR-143 0.600E+00 0.000E+00 0.OOOE+00 0.000E+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.000E+00 PR-144 1.830E+03 1.830E+03 1.830E+03 1.830E+03 1.830E+03 1.830E+03 2.11 OE+03 1.830E+03 ND-147 8.390E+06 8.390E+06 8.390E+06 8.390E+06 8.390E+06 8.390E+06 1.010E+07 8.390E+06 W-187 2.350E+06 2.350E+06 2.350E+06 2.350E+06 2.350E+06 2.350E+06 2.730E+06 2.350E+06 NP-239 1.710E+06 1.710E+06 1.710E+06 1.71 OE+06 1.710E+06 1.71 OE+06 1.980E+06 1.710E+06 Appendix J Ri Infant Ground Plane Deposition - Page 3 of 3