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* .. LICENSING MANAGER CROSS DISCIPLINE REVIEW Approved By I Date: Print Signature  
* .. LICENSING MANAGER CROSS DISCIPLINE REVIEW Approved By I Date: Print Signature  
.** EP MANAGER CROSS DISCIPLINE REVIEW Approved By I Date: Print Signature  
.** EP MANAGER CROSS DISCIPLINE REVIEW Approved By I Date: Print Signature  
*. .. CHEMSITRY MANAGER PROCEDURE APPROVAL  
*. .. CHEMSITRY MANAGER PROCEDURE APPROVAL *.*. ** Approved By I Date: Print Signature ORG REVIEW Approved By I Date: Print Signature SITE DIRECTOR APPROVAL Approved By I Date: Print Signature  
*.*. ** Approved By I Date: Print Signature ORG REVIEW Approved By I Date: Print Signature SITE DIRECTOR APPROVAL Approved By I Date: Print Signature  
.* DAECODAM Page 1of280 Rev. 37 TABLE OF CONTENTS Section Title 1.0 2.0 3.0 2.1 2.2 2.3 2.4 2.5 2.6 2.7  
.* DAECODAM Page 1of280 Rev. 37 TABLE OF CONTENTS Section Title 1.0 2.0 3.0 2.1 2.2 2.3 2.4 2.5 2.6 2.7  


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==1.0 INTRODUCTION==
==1.0 INTRODUCTION==


This manual provides a description of the facility's Offsite Dose Assessment  
This manual provides a description of the facility's Offsite Dose Assessment Program, the Radiological Effluents Controls Program and the Radiological Environmental Monitoring Program. EFFLUENTS CONTROLS PROGRAM This program, conforming to 10 CFR 50.36a, provides for the control of radioactive effluents and for maintaining the doses to members of the public from radioactive effluents as low as reasonably achievable.
: Program, the Radiological Effluents Controls Program and the Radiological Environmental Monitoring Program.
EFFLUENTS CONTROLS PROGRAM This program, conforming to 10 CFR 50.36a, provides for the control of radioactive effluents and for maintaining the doses to members of the public from radioactive effluents as low as reasonably achievable.
The program is contained in sections six and seven of the ODAM, is implemented by procedures, and includes remedial actions to be taken whenever the program limits are exceeded.
The program is contained in sections six and seven of the ODAM, is implemented by procedures, and includes remedial actions to be taken whenever the program limits are exceeded.
Section eight of the ODAM includes the requirement for the Annual Radioactive Material Release Report. The Radioactive Material Release Report covers the operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year in accordance with 10 CFR 50.36a. The report includes a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided in the report is consistent with the objectives outlined in the ODAM and Process Control Program and in conformance with 10 CFR 50.36a and 10 CFR Part 50, Appendix I, Section IV.B.1. RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM The Radiological Environmental Monitoring Program (REMP) provides for representative measurements of radioactivity in the highest potential exposure  
Section eight of the ODAM includes the requirement for the Annual Radioactive Material Release Report. The Radioactive Material Release Report covers the operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year in accordance with 10 CFR 50.36a. The report includes a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided in the report is consistent with the objectives outlined in the ODAM and Process Control Program and in conformance with 10 CFR 50.36a and 10 CFR Part 50, Appendix I, Section IV.B.1. RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM The Radiological Environmental Monitoring Program (REMP) provides for representative measurements of radioactivity in the highest potential exposure pathways, verification of the accuracy of the effluent monitoring program and modeling of environmental exposure pathways.
: pathways, verification of the accuracy of the effluent monitoring program and modeling of environmental exposure pathways.
Additionally, the REMP is designed to demonstrate that radioactive effluents from DAEC are ALARA. GROUNDWATER PROTECTION PROGRAM The Groundwater Protection Program (GWPP) provides representative measurements of radioactivity in the highest potentially exposed aquifer, verification of the accuracy of the GWPP monitoring efforts and modeling of the subsurface.
Additionally, the REMP is designed to demonstrate that radioactive effluents from DAEC are ALARA. GROUNDWATER PROTECTION PROGRAM The Groundwater Protection Program (GWPP) provides representative measurements of radioactivity in the highest potentially exposed aquifer, verification of the accuracy of the GWPP monitoring efforts and modeling of the subsurface.
Additionally, the GWPP is designed to protect and mitigate radiological contaminates to groundwater.
Additionally, the GWPP is designed to protect and mitigate radiological contaminates to groundwater.
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Calculations of dose committed from radioactive releases over extended time (3 and 12 months) are also made for the purpose of verifying compliance with regulatory limits on offsite dose. For these calculations the receptor is selected on the basis of the combination of applicable exposure pathways identified in the land use census and the maximum ground level ,VQ at a residence, or on the basis of more conservative conditions such that the dose to any resident near the Station is unlikely to be underestimated.
Calculations of dose committed from radioactive releases over extended time (3 and 12 months) are also made for the purpose of verifying compliance with regulatory limits on offsite dose. For these calculations the receptor is selected on the basis of the combination of applicable exposure pathways identified in the land use census and the maximum ground level ,VQ at a residence, or on the basis of more conservative conditions such that the dose to any resident near the Station is unlikely to be underestimated.
2.0 LIQUID EFFLUENT 2.1 Radioactivity In Liquid Waste The concentration of radionuclides in liquid waste is determined by sampling and analysis in accord with the surveillance requirements of Section 7.1.2, Table 7.1-2. When a radionuclide is identified, it is reported as being present in the sample even if the concentration is below the required LLD for the analysis.
2.0 LIQUID EFFLUENT 2.1 Radioactivity In Liquid Waste The concentration of radionuclides in liquid waste is determined by sampling and analysis in accord with the surveillance requirements of Section 7.1.2, Table 7.1-2. When a radionuclide is identified, it is reported as being present in the sample even if the concentration is below the required LLD for the analysis.
2.2 Aqueous Concentration Radioactive material in liquid effluent is diluted successively by water flowing in the discharge pipe and in the River. The diluted concentration of radionuclide i in a receiving stream is estimated with the equation where F1 Cz; = C; C = concentration of radionuclide i in liquid radwaste released  
2.2 Aqueous Concentration Radioactive material in liquid effluent is diluted successively by water flowing in the discharge pipe and in the River. The diluted concentration of radionuclide i in a receiving stream is estimated with the equation where F1 Cz; = C; C = concentration of radionuclide i in liquid radwaste released (µCi/ml) C,; = concentration of radionuclide i in the receiving stream (µCi/ml) F1 = release rate of liquid radwaste (mUsec)d F2 = dilution flow of receiving stream of water (mUsec)d For the purpose of calculating the radioactivity concentration in water at the restricted area boundary (section 2.5), the flow in the discharge pipe, Fe, is assigned to F 2. The b The Duane Arnold Energy Center, also referred to henceforth as the Station, is defined as including BOTH the Nuclear Reactor Facility and the Independent Spent Fuel Storage Installation (ISFSI). c Reference meteorological conditions are 1971, 1974 and 1975 data composited as discussed in "Duane Arnold Energy Center, Evaluation of Liquid and Gaseous Effluent Releases in Accordance With 10 CFR 50 Appendix I," submitted to the NRC June 3, 1976. ct F 1 , F 2 , and Fe may have any convenient units of flow (i.e., volume/time) provided the units of all are identical.
(µCi/ml)
DAEC ODAM Page 6 of 280 Rev. 37 water flow in the discharge pipe may include the liquid waste effluent flow, the liquid radwaste dilution water flow, the cooling tower blowdown flow and other streams such as RHR and emergency service water discharged via the dilution structure and discharge pipe. These streams are illustrated in Figure 2-1. In the River immediately beyond the discharge pipe and the restricted area boundary, the effective dilution is Where Fe =discharge pipe flow M = factor of additional mixing in the River A near field mixing ratio from the pipe into the near field of the River, M = 5, is assigned when estimating maximum potential individual doses involving exposure by eating fish or from consuming irrigated foods. In the event water is drawn from the River downstream of the Station for drinking water or another exposure pathway, F 2 represents the portion of the River flow into which the liquid effluent from the Station is effectively mixed. 2.3 Basis of Mixing Ratios Downstream dilution of aqueous discharge from the DAEC has been estimated based on thermal plume studies conducted in 197 4 at the DAEC. e Measurements of the discharge temperature and river temperature indicated that the 1°F excess temperature isotherm was about 350 feet downstream of the discharge.
C,; = concentration of radionuclide i in the receiving stream (µCi/ml)
F1 = release rate of liquid radwaste (mUsec)d F2 = dilution flow of receiving stream of water (mUsec)d For the purpose of calculating the radioactivity concentration in water at the restricted area boundary (section 2.5), the flow in the discharge pipe, Fe, is assigned to F2. The b The Duane Arnold Energy Center, also referred to henceforth as the Station, is defined as including BOTH the Nuclear Reactor Facility and the Independent Spent Fuel Storage Installation (ISFSI).
c Reference meteorological conditions are 1971, 1974 and 1975 data composited as discussed in "Duane Arnold Energy Center, Evaluation of Liquid and Gaseous Effluent Releases in Accordance With 10 CFR 50 Appendix I," submitted to the NRC June 3, 1976. ct F1, F2, and Fe may have any convenient units of flow (i.e., volume/time) provided the units of all are identical.
DAEC ODAM Page 6 of 280 Rev. 37 water flow in the discharge pipe may include the liquid waste effluent flow, the liquid radwaste dilution water flow, the cooling tower blowdown flow and other streams such as RHR and emergency service water discharged via the dilution structure and discharge pipe. These streams are illustrated in Figure 2-1. In the River immediately beyond the discharge pipe and the restricted area boundary, the effective dilution is Where Fe =discharge pipe flow M = factor of additional mixing in the River A near field mixing ratio from the pipe into the near field of the River, M = 5, is assigned when estimating maximum potential individual doses involving exposure by eating fish or from consuming irrigated foods. In the event water is drawn from the River downstream of the Station for drinking water or another exposure  
: pathway, F2 represents the portion of the River flow into which the liquid effluent from the Station is effectively mixed. 2.3 Basis of Mixing Ratios Downstream dilution of aqueous discharge from the DAEC has been estimated based on thermal plume studies conducted in 197 4 at the DAEC. e Measurements of the discharge temperature and river temperature indicated that the 1°F excess temperature isotherm was about 350 feet downstream of the discharge.
This 1°F isotherm represented a dilution of the discharge by the Cedar River of about a factor of 12. In determining additional dilution within the receiving water for evaluating doses from a plant with cooling towers, the NRC guideline*t is that the factor should be limited to a number such that the product of the number and the average blowdown flow to the receiving water body is 1000 cfs or less. At the DAEC, the discharge rate can be conservatively approximated by a cooling tower blowdown rate of 4000 gpm, or about 9 cfs. Using the NRC guideline, an additional dilution of 100 in the Cedar River could be assumed for evaluating doses due to liquid effluent.
This 1°F isotherm represented a dilution of the discharge by the Cedar River of about a factor of 12. In determining additional dilution within the receiving water for evaluating doses from a plant with cooling towers, the NRC guideline*t is that the factor should be limited to a number such that the product of the number and the average blowdown flow to the receiving water body is 1000 cfs or less. At the DAEC, the discharge rate can be conservatively approximated by a cooling tower blowdown rate of 4000 gpm, or about 9 cfs. Using the NRC guideline, an additional dilution of 100 in the Cedar River could be assumed for evaluating doses due to liquid effluent.
Since the average flow in the Cedar River is about 3,775 cfs, the additional dilution in the River is achievable.
Since the average flow in the Cedar River is about 3,775 cfs, the additional dilution in the River is achievable.
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Land Use Censuses have shown that the nearest use of river water for irrigation is 2.3 miles downstream and the nearest use of river water (from alluvial wells) is 2.2 miles downstream for the City of Palo and more than 8 miles downstream for the City of Cedar Rapids. For the sake of simplification and conservatism in routine liquid dose calculations, a dilution factor of 5 is assumed for fish and irrigation pathways and a dilution factor of 10 is assumed for drinking water for the evaluation of doses during DAEC operation.
Land Use Censuses have shown that the nearest use of river water for irrigation is 2.3 miles downstream and the nearest use of river water (from alluvial wells) is 2.2 miles downstream for the City of Palo and more than 8 miles downstream for the City of Cedar Rapids. For the sake of simplification and conservatism in routine liquid dose calculations, a dilution factor of 5 is assumed for fish and irrigation pathways and a dilution factor of 10 is assumed for drinking water for the evaluation of doses during DAEC operation.
2.4 Method of Establishing Alarm Setpoints e IELP, Cedar River Baseline Ecological Study, DAEC, annual report, Jan. 1974-Jan.1975.
2.4 Method of Establishing Alarm Setpoints e IELP, Cedar River Baseline Ecological Study, DAEC, annual report, Jan. 1974-Jan.1975.
f Boegli, J.S., et. al., Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants, NUREG-0133,  
f Boegli, J.S., et. al., Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants, NUREG-0133, p. 16, October, 1978 DAEC ODAM Page 7 of 280 Rev. 37 The liquid radwaste effluent line has a monitor which provides automatic isolation when 10 times the water effluent concentration listed in 10 CFR 20 Appendix B, Table 2, is being exceeded in the unrestricted area. The other liquid effluent pathways have monitors which provide alarms when 10 times the 10 CFR 20 water effluent concentration is being exceeded in the unrestricted area. Given the nature and frequency of discharges, prompt action to reduce radioactive releases following an alarm, will assure the requirements of 10 CFR Part 20. 1301; 10 CFR Part 50 Appendix I, Section IV; and 40 CFR Part 190 are not exceeded.
: p. 16, October, 1978 DAEC ODAM Page 7 of 280 Rev. 37 The liquid radwaste effluent line has a monitor which provides automatic isolation when 10 times the water effluent concentration listed in 10 CFR 20 Appendix B, Table 2, is being exceeded in the unrestricted area. The other liquid effluent pathways have monitors which provide alarms when 10 times the 10 CFR 20 water effluent concentration is being exceeded in the unrestricted area. Given the nature and frequency of discharges, prompt action to reduce radioactive releases following an alarm, will assure the requirements of 10 CFR Part 20. 1301; 10 CFR Part 50 Appendix I, Section IV; and 40 CFR Part 190 are not exceeded.
The alarm setpoint for the liquid effluent radiation monitor is derived from the concentration limit provided in 10 CFR Part 20.1001-20.2402 Appendix B Table 2 Column 2 applied at the unrestricted area boundary where the discharge pipe flows into the river. The alarm setpoint does not consider dilution, dispersion, or decay of radioactive material beyond the site boundary.
The alarm setpoint for the liquid effluent radiation monitor is derived from the concentration limit provided in 10 CFR Part 20.1001-20.2402 Appendix B Table 2 Column 2 applied at the unrestricted area boundary where the discharge pipe flows into the river. The alarm setpoint does not consider  
That is, the alarm setpoint is based on a concentration limit at the end of the discharge pipe. The radiation monitoring and isolation points are located in each line through which radioactive waste effluent is eventually discharged into the discharge pipe. The alarm setpoint for effluent monitors on batch releases is based on measurements, according to Table 7.1-2. For liquids released in continuous aqueous discharge which are normally radioactively clean, the setpoint is based on the effective Water Effluent Concentration (WEC) for the most likely contaminating source, i.e., the primary coolant water. A measured spectrum from the primary coolant water is used to determine the effective WEC based on WEC fractions according to 10 CFR 20 Appendix B. 2.4.1 Setpoint for a Batch Release A sample of each batch of liquid radwaste is analyzed for 1-131 and other principal gamma emitters, or for total activity concentration prior to release. The ratio, FWECb, of the activity concentration in the tank to the unrestricted area WEC (10 CFR Part 20, Appendix B, Table 2, Column 2) is calculated with the equation DAEC ODAM Page 8 of280 Rev. 37 where fraction of unrestricted area WEC in batch derived from activity measured prior to release. concentration of radionuclide i (including 1-131 and principal gamma emitters) in batch sample taken prior to release (µCi/ml) Whether radioiodine and primary gamma emitters are identified prior to a batch release or not, the liquid radwaste effluent line radiation monitor alarm setpoint is determined with the equation where s = 10 = A= g= S=JOx *-*g +Bkg l A Fs2 J FWECb Fs1 radiation monitor alarm setpoint (cpm) factor to account for fact that DAEC's instantaneous release limit is ten times the listed WECs counting rate (cpm/ml) or activity concentration  
: dilution, dispersion, or decay of radioactive material beyond the site boundary.
That is, the alarm setpoint is based on a concentration limit at the end of the discharge pipe. The radiation monitoring and isolation points are located in each line through which radioactive waste effluent is eventually discharged into the discharge pipe. The alarm setpoint for effluent monitors on batch releases is based on measurements, according to Table 7.1-2. For liquids released in continuous aqueous discharge which are normally radioactively clean, the setpoint is based on the effective Water Effluent Concentration (WEC) for the most likely contaminating source, i.e., the primary coolant water. A measured spectrum from the primary coolant water is used to determine the effective WEC based on WEC fractions according to 10 CFR 20 Appendix B. 2.4.1 Setpoint for a Batch Release A sample of each batch of liquid radwaste is analyzed for 1-131 and other principal gamma emitters, or for total activity concentration prior to release.
The ratio, FWECb, of the activity concentration in the tank to the unrestricted area WEC (10 CFR Part 20, Appendix B, Table 2, Column 2) is calculated with the equation DAEC ODAM Page 8 of280 Rev. 37 where fraction of unrestricted area WEC in batch derived from activity measured prior to release.
concentration of radionuclide i (including 1-131 and principal gamma emitters) in batch sample taken prior to release (µCi/ml)
Whether radioiodine and primary gamma emitters are identified prior to a batch release or not, the liquid radwaste effluent line radiation monitor alarm setpoint is determined with the equation where s = 10 = A= g= S=JOx *-*g +Bkg l A Fs2 J FWECb Fs1 radiation monitor alarm setpoint (cpm) factor to account for fact that DAEC's instantaneous release limit is ten times the listed WECs counting rate (cpm/ml) or activity concentration  
(µCi/ml) of sample in :Lcbi laboratory analysis.
(µCi/ml) of sample in :Lcbi laboratory analysis.
A equals ; if an isotopic analysis were performed or Cb if a gross activity analysis was performed.
A equals ; if an isotopic analysis were performed or Cb if a gross activity analysis was performed.
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9 Value not less than the discharge pipe flow alarm minimum setpoint.
9 Value not less than the discharge pipe flow alarm minimum setpoint.
g Any suitable but identical units of flow (volume/time)
g Any suitable but identical units of flow (volume/time)
DAEC ODAM Page 9 of 280 Rev. 37 Note that A/FWECb represents the counting rate of a solution having the same radionuclide distribution as the sample and having the water effluent concentration of that mixture.
DAEC ODAM Page 9 of 280 Rev. 37 Note that A/FWECb represents the counting rate of a solution having the same radionuclide distribution as the sample and having the water effluent concentration of that mixture. 2.4.2 Setpoint for a Continuous Release Continuous aqueous discharges are sampled and analyzed according to the schedule in Table 7.1-2. The ratio, FWECc, of the activity concentration in each of the continuous release streams to the unrestricted area WEC is calculated with the equations where FWECc = Cc;= FWECc = ; WEC; fraction of unrestricted area WEC in continuous release based upon activity measured in primary coolant sample(s) concentration of radionuclide i in sample(s)  
2.4.2 Setpoint for a Continuous Release Continuous aqueous discharges are sampled and analyzed according to the schedule in Table 7.1-2. The ratio, FWECc, of the activity concentration in each of the continuous release streams to the unrestricted area WEC is calculated with the equations where FWECc = Cc;= FWECc = ; WEC; fraction of unrestricted area WEC in continuous release based upon activity measured in primary coolant sample(s) concentration of radionuclide i in sample(s)  
(µCi/ml) The alarm setpoint of the radiation monitor on a continuous radioactive discharge line is determined with the equation S=JOx *-*g +Bkg l A Fs2 J FWECc Fs1 where I 0 = factor to account for fact that DAE C's instantaneous release limit is ten times the listed WECs A = activity concentration  
(µCi/ml)
The alarm setpoint of the radiation monitor on a continuous radioactive discharge line is determined with the equation S=JOx *-*g +Bkg l A Fs2 J FWECc Fs1 where I 0 = factor to account for fact that DAE C's instantaneous release limit is ten times the listed WECs A = activity concentration  
(µCi/ml) or counting rate (cpm/ml) in laboratory of monthly reactor primary coolant sample. Fs, = Flow in the liquid discharge line (mUsec).h Value not greater than off discharge line flow alarm maximum setpoint.
(µCi/ml) or counting rate (cpm/ml) in laboratory of monthly reactor primary coolant sample. Fs, = Flow in the liquid discharge line (mUsec).h Value not greater than off discharge line flow alarm maximum setpoint.
Fs2 = flow in the discharge pipe (mUsec).h Value not less than discharge pipe flow alarm minimum setpoint.
Fs2 = flow in the discharge pipe (mUsec).h Value not less than discharge pipe flow alarm minimum setpoint.
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DAEC ODAM Page 10 of 280 Rev. 37 The radioactivity concentration in continuous aqueous effluent is usually so low that measurement of a representative radionuclide in a sample of the water is uncertain.
DAEC ODAM Page 10 of 280 Rev. 37 The radioactivity concentration in continuous aqueous effluent is usually so low that measurement of a representative radionuclide in a sample of the water is uncertain.
Thus, the ratio, A/FWECc, which represents the WEC of a given spectrum of radionuclides, is usually derived from reactor primary coolant analysis(es).
Thus, the ratio, A/FWECc, which represents the WEC of a given spectrum of radionuclides, is usually derived from reactor primary coolant analysis(es).
Alternatively, it may be determined from analyses of the continuous effluent itself. In the event the concentration of radioactive material in the sample from the continuous release is below measurable levels (i.e., less than the lower limit of detection),
Alternatively, it may be determined from analyses of the continuous effluent itself. In the event the concentration of radioactive material in the sample from the continuous release is below measurable levels (i.e., less than the lower limit of detection), the value of 1 x 1 o-s µCi/ml or the equivalent counting rate (cpm/ml) may be substituted for the factor A A ---(i.e., -1*10-8). FWECc FWECc 2.5 Radioactivity Concentration in Water at the Restricted Area Boundary Section 6.1.2 provides limits on instantaneous radioactivity concentration in the unrestricted area due to aqueous effluents from DAEC. Compliance is assessed by monitoring, sampling, analyzing and establishing setpoints according to Section 7.1.2. As long as a liquid effluent monitor named in Table 6.1-1 does not exceed an alarm or trip setpoint, determined in accordance with section 2.3, or as long as the total or gross activity concentration, measured as required in Section 7.1.2, does not exceed 1 x 10-7 µCi/ml after dilution in the discharge pipe, Section 6.1.2 is satisfied.
the value of 1 x 1 o-s µCi/ml or the equivalent counting rate (cpm/ml) may be substituted for the factor A A ---(i.e., -1*10-8). FWECc FWECc 2.5 Radioactivity Concentration in Water at the Restricted Area Boundary Section 6.1.2 provides limits on instantaneous radioactivity concentration in the unrestricted area due to aqueous effluents from DAEC. Compliance is assessed by monitoring,  
: sampling, analyzing and establishing setpoints according to Section 7.1.2. As long as a liquid effluent monitor named in Table 6.1-1 does not exceed an alarm or trip setpoint, determined in accordance with section 2.3, or as long as the total or gross activity concentration, measured as required in Section 7.1.2, does not exceed 1 x 10-7 µCi/ml after dilution in the discharge pipe, Section 6.1.2 is satisfied.
In the event of an alarm, indicating concentrations in the unrestricted area in excess of section 6.1.2 limits, the release shall be terminated and dose calculations will be performed to assure the limits specified in sections 6.1.3 and 6.3.1 are not exceeded.
In the event of an alarm, indicating concentrations in the unrestricted area in excess of section 6.1.2 limits, the release shall be terminated and dose calculations will be performed to assure the limits specified in sections 6.1.3 and 6.3.1 are not exceeded.
Compliance with 10 CFR 20.1301 shall not be demonstrated on the basis of determining the average annual liquid effluent concentration.
Compliance with 10 CFR 20.1301 shall not be demonstrated on the basis of determining the average annual liquid effluent concentration.
But rather by demonstrating compliance with 40 CFR 190 (i.e., section 6.3.1). Such a practice was deemed acceptable by the NRG in their preamble to the revised 10 CFR 20.i 2.6 Accumulated Personal Maximum Dose Section 7.1.3 requires an assessment to be performed at least once every 30 days in any quarter in which radioactive effluent is discharged which determines whether the dose or dose commitment to a person offsite due to radioactive material released in liquid effluent calculated on a cumulative basis exceeds the limits of Section 6.1.3. The requirement is satisfied by computing the accumulated dose commitment to the most exposed organ and to the whole body of a hypothetical person exposed by eating fish or consuming irrigated strawberries and drinking water taken from the river offsite downstream of the discharge pipe. The pathway(s) and or age group(s) selected may vary by season. For instance, fishing near the DAEC is practically non-existent during the winter; thus, a dose evaluation of the fish pathway is not required for aqueous effluent discharged during the winter months of January,  
But rather by demonstrating compliance with 40 CFR 190 (i.e., section 6.3.1). Such a practice was deemed acceptable by the NRG in their preamble to the revised 10 CFR 20.i 2.6 Accumulated Personal Maximum Dose Section 7.1.3 requires an assessment to be performed at least once every 30 days in any quarter in which radioactive effluent is discharged which determines whether the dose or dose commitment to a person offsite due to radioactive material released in liquid effluent calculated on a cumulative basis exceeds the limits of Section 6.1.3. The requirement is satisfied by computing the accumulated dose commitment to the most exposed organ and to the whole body of a hypothetical person exposed by eating fish or consuming irrigated strawberries and drinking water taken from the river offsite downstream of the discharge pipe. The pathway(s) and or age group(s) selected may vary by season. For instance, fishing near the DAEC is practically non-existent during the winter; thus, a dose evaluation of the fish pathway is not required for aqueous effluent discharged during the winter months of January, February, or March. The accumulated dose commitment is computed at least once every 30 days but may be computed as analyses become available.
: February, or March. The accumulated dose commitment is computed at least once every 30 days but may be computed as analyses become available.  
Normally, DAEC employs the MIDAS computer program to calculate dose to a member of the public from aqueous effluent that uses the equations in Reg Guide 1.1 ogi and ; Federal Register Volume 56, #98, Tuesday, May 21, 1991, p. 23360 i USNRC, Regulatory Guide 1.109, revision 1, Position C.1, pp. 1.109-2 thru 1.109-4, Oct. 1977 DAEC ODAM Page 11 of 280 Rev. 37 standard values therein for maximally exposed people. The amount of strawberries a person may eat is estimated to be one-half the amount of fresh leafy vegetable consumption.
: Normally, DAEC employs the MIDAS computer program to calculate dose to a member of the public from aqueous effluent that uses the equations in Reg Guide 1.1 ogi and ; Federal Register Volume 56, #98, Tuesday, May 21, 1991, p. 23360 i USNRC, Regulatory Guide 1.109, revision 1, Position C.1, pp. 1.109-2 thru 1.109-4, Oct. 1977 DAEC ODAM Page 11 of 280 Rev. 37 standard values therein for maximally exposed people. The amount of strawberries a person may eat is estimated to be one-half the amount of fresh leafy vegetable consumption.
Alternatively, the amount of strawberries eaten may be assumed to equal the amount of fresh leafy vegetables eaten. Alternatively, the dose may be calculated in the following way, for instance, in the event calculations by hand were necessary.
Alternatively, the amount of strawberries eaten may be assumed to equal the amount of fresh leafy vegetables eaten. Alternatively, the dose may be calculated in the following way, for instance, in the event calculations by hand were necessary.
where  
where  
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(µCi/ml) t k = duration of radioactive release represented by sample k which occurs within time boundaries TB and TE and during which concentration Cik and flows F1k and F2k exist. (min.) 3. 785* 10-3 = conversion constant (3785 mUgal
(µCi/ml) t k = duration of radioactive release represented by sample k which occurs within time boundaries TB and TE and during which concentration Cik and flows F1k and F2k exist. (min.) 3. 785* 10-3 = conversion constant (3785 mUgal
* 10-e Ci/µCi) F h = flow in the radioactive waste release line (gal/minf represented by sample k. F 2ke = flow into which radioactive release represented by sample k is mixed in the river at the point of exposure or withdrawal of water for use (same units as F1k)* DAECODAM Page 12 of 280 Rev. 37   
* 10-e Ci/µCi) F h = flow in the radioactive waste release line (gal/minf represented by sample k. F 2ke = flow into which radioactive release represented by sample k is mixed in the river at the point of exposure or withdrawal of water for use (same units as F1k)* DAECODAM Page 12 of 280 Rev. 37   
= M x Fck where Fck = discharge pipe flow (gal/min)k during release represented by sample k M = factor of additional mixing in the river Pathway-to-dose transfer  
= M x Fck where Fck = discharge pipe flow (gal/min)k during release represented by sample k M = factor of additional mixing in the river Pathway-to-dose transfer factors, Aeani. for use in calculating the dose commitment arising from radioactive material released in aqueous effluents are tabulated in Appendix C. These dose transfer factors were derived using LADT AP II and standard values from Regulatory Guide 1.109, revision 1, except where corrections have been incorporated in LADTAP II. Appropriate tables representing applicable environmental pathways of exposure and most exposed age group(s) are selected and used in calculating the dose commitment.
: factors, Aeani. for use in calculating the dose commitment arising from radioactive material released in aqueous effluents are tabulated in Appendix C. These dose transfer factors were derived using LADT AP II and standard values from Regulatory Guide 1.109, revision 1, except where corrections have been incorporated in LADTAP II. Appropriate tables representing applicable environmental pathways of exposure and most exposed age group(s) are selected and used in calculating the dose commitment.
The pathway(s) and/or age group(s) selected may vary by season. Pathways of Maximum Exposure to a Member of the Public:
The pathway(s) and/or age group(s) selected may vary by season. Pathways of Maximum Exposure to a Member of the Public:
* Ingestion of Fish taken from the river near the discharge pipe o Age Group: Adult o Dilution:
* Ingestion of Fish taken from the river near the discharge pipe o Age Group: Adult o Dilution:
F2 = 5Fc o Food: Sport Fish
F 2 = 5Fc o Food: Sport Fish
* Irrigated Food Pathway o Age Group: Teen o Dilution:
* Irrigated Food Pathway o Age Group: Teen o Dilution:
F2 = 5Fc o Food: Strawberries
F 2 = 5Fc o Food: Strawberries
* Drinking Water Pathway o Age Group: Infant o Dilution:
* Drinking Water Pathway o Age Group: Infant o Dilution:
F2 = 10Fc o Dilution:
F 2 = 10Fc o Dilution:
F2 = 5F c only when Land Use Census identifies this pathway within 3 miles of the plant Variables F1, F2, and Fe are also defined in section 2.2. 2.7 Projected Maximum Dose to a Person Offsite The dose commitment to a person offsite due to radioactive material released in liquid effluent may be projected by calculating the extrapolated whole body and most exposed organ dose commitments to a hypothetical person exposed via the same pathways evaluated in section 2.6. The potential dose commitments to organs and to the whole body are computed separately.
F 2 = 5F c only when Land Use Census identifies this pathway within 3 miles of the plant Variables F 1 , F 2 , and Fe are also defined in section 2.2. 2.7 Projected Maximum Dose to a Person Offsite The dose commitment to a person offsite due to radioactive material released in liquid effluent may be projected by calculating the extrapolated whole body and most exposed organ dose commitments to a hypothetical person exposed via the same pathways evaluated in section 2.6. The potential dose commitments to organs and to the whole body are computed separately.
The dose commitment to a maximally exposed hypothetical person will be projected by calculating the doses accumulated during the most recent three months (according to the method described in section 2.6) and by assuming the result represents the projected doses during the current quarter.
The dose commitment to a maximally exposed hypothetical person will be projected by calculating the doses accumulated during the most recent three months (according to the method described in section 2.6) and by assuming the result represents the projected doses during the current quarter. Alternatively, the quarterly dose commitment may be projected by using the equation:
Alternatively, the quarterly dose commitment may be projected by using the equation:
Pan = where k Any suitable, identical units of flow (volume/time) 92 Dan x DAEC ODAM Page 13 of 280 Rev. 37 Pan = 92 = X= Dan = projected dose commitment (mrem) to organ n (including whole body) of age group a for the current quarter number of days in a quarter number of days to date in current quarter dose commitment to organ n, including whole body, of the maximally exposed person in age group a based on available aqueous effluent measurements during the quarter to date (mrem) 2.8 Groundwater Pathway Low levels of radioactive contamination have been identified in sub-surface water on site. There is the possibility that this water could represent potential exposure to the public. Hydrogeology studies indicate that this water will migrate towards the river in sectors ranging from East-North-East to the South-South-West.
Pan = where k Any suitable, identical units of flow (volume/time) 92 Dan x DAEC ODAM Page 13 of 280 Rev. 37 Pan = 92 = X= Dan = projected dose commitment (mrem) to organ n (including whole body) of age group a for the current quarter number of days in a quarter number of days to date in current quarter dose commitment to organ n, including whole body, of the maximally exposed person in age group a based on available aqueous effluent measurements during the quarter to date (mrem) 2.8 Groundwater Pathway Low levels of radioactive contamination have been identified in sub-surface water on site. There is the possibility that this water could represent potential exposure to the public. Hydrogeology studies indicate that this water will migrate towards the river in sectors ranging from East-North-East to the South-South-West.
The only potential exposure pathways are described in Section 2.6 To monitor for the migration of any radioactive contamination beyond the owner controlled area, sampling of on-site ground water, river water, and down gradient drinking water is performed as a function of the Radiological Environmental Monitoring Program (REMP) and the Ground Water Protection Program (GWPP). These programs are described in Section 5.0. In February 2016, the GWPP routine sampling identified a contaminate plume in the shallow aquifer (less than 25 feet deep). Release standards are set forth in Section 6.0, Radiological Liquid Effluent Release 0.6.1.2, Table 7.1-2. In accordance with GWPP Administrative Control Procedure (ACP) 1411.35 and Environmental Protection Agency (EPA) drinking water standards for tritium, 20,000 pCi/L, groundwater batch and continuous releases are expected less than(<) 20,000 pCi/L. Groundwater samples are analyzed on-site and validated by off-site secondary laboratory.
The only potential exposure pathways are described in Section 2.6 To monitor for the migration of any radioactive contamination beyond the owner controlled area, sampling of on-site ground water, river water, and down gradient drinking water is performed as a function of the Radiological Environmental Monitoring Program (REMP) and the Ground Water Protection Program (GWPP). These programs are described in Section 5.0. In February 2016, the GWPP routine sampling identified a contaminate plume in the shallow aquifer (less than 25 feet deep). Release standards are set forth in Section 6.0, Radiological Liquid Effluent Release 0.6.1.2, Table 7.1-2. In accordance with GWPP Administrative Control Procedure (ACP) 1411.35 and Environmental Protection Agency (EPA) drinking water standards for tritium, 20,000 pCi/L, groundwater batch and continuous releases are expected less than(<) 20,000 pCi/L. Groundwater samples are analyzed on-site and validated by off-site secondary laboratory.
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GEl'ERAL SERVICE WA TE.R SYSTEM Coolers Turbine Cooler Feild Pump Cooler EHC Unit Cooler Rellctor Bldg CW Heat Exchangers RHR and EMERGENCY SERVICE WATER SYSTEMS Water Pump RHR Heat Emerscncy Service I Chillers and Wa!<!r Pump "' l Coolers SBDG Coolers I RADIOACTIVE WASTE SYSTEMS River Water for Dilution Equipment Radwasie Radwaste Treaunent System HP I LP Cond. Cond. Deter gem Waste Floor Drain Waste Floor Drain Trealmcnt System Chemical Was11:: Chi:mleal Was11::Tanks a:  
GEl'ERAL SERVICE WA TE.R SYSTEM Coolers Turbine Cooler Feild Pump Cooler EHC Unit Cooler Rellctor Bldg CW Heat Exchangers RHR and EMERGENCY SERVICE WATER SYSTEMS Water Pump RHR Heat Emerscncy Service I Chillers and Wa!<!r Pump "' l Coolers SBDG Coolers I RADIOACTIVE WASTE SYSTEMS River Water for Dilution Equipment Radwasie Radwaste Treaunent System HP I LP Cond. Cond. Deter gem Waste Floor Drain Waste Floor Drain Trealmcnt System Chemical Was11:: Chi:mleal Was11::Tanks a:  
::0 Ol 9: 0 0 c Ol Ol  
::0 Ol 9: 0 0 c Ol Ol  
-*co C6 )> ::!1 Ol Q. cc ro ..., m CD m:::i N =ll CD I --. ....>. ccc CD '< ;:?. () 0 CD -* ::J Ol ...... :0 CD ..., ..., Ol 3 3.0 GASEOUS EFFLUENT 3.1 Introduction The Station discharges gaseous effluent through a stack and discharges ventilation air from the reactor and radwaste building through the reactor building vents. Ventilation air from the Turbine Building is discharged through the Turbine Building vent and through the Reactor Building vent. Ventilation from the LLRPSF is discharged through the LLRPSF vent. These gaseous effluent  
-*co C6 )> ::!1 Ol Q. cc ro ..., m CD m:::i N =ll CD I --. ....>. ccc CD '< ;:?. () 0 CD -* ::J Ol ...... :0 CD ..., ..., Ol 3 3.0 GASEOUS EFFLUENT 3.1 Introduction The Station discharges gaseous effluent through a stack and discharges ventilation air from the reactor and radwaste building through the reactor building vents. Ventilation air from the Turbine Building is discharged through the Turbine Building vent and through the Reactor Building vent. Ventilation from the LLRPSF is discharged through the LLRPSF vent. These gaseous effluent streams, radioactivity monitoring points, and effluent discharge points are shown schematically in Figure 3-1. Gaseous release point locations and elevations at the Station are described in Table 3-1. Gaseous discharges from the stack are treated as an elevated release while discharges via the building vents are assumed to be ground-level, building wake, or split wake releases.
: streams, radioactivity monitoring points, and effluent discharge points are shown schematically in Figure 3-1. Gaseous release point locations and elevations at the Station are described in Table 3-1. Gaseous discharges from the stack are treated as an elevated release while discharges via the building vents are assumed to be ground-level, building wake, or split wake releases.
3.2 Radioactivity in Gaseous Effluent For the purpose of estimating offsite radionuclide concentrations and radiation doses, measured radionuclide concentrations in gaseous effluent and in ventilation air exhausted from the Station are relied upon. The gross radioactivity of noble gases discharged is measured by the radioactive noble gas effluent monitors according to Tables 6.2-1 and 7.2-2. Radionuclides other than noble gases in gaseous effluents are measured by sampling and analyses in accordance with Table 7.2-2. Each radionuclide measured in an effluent may be assumed to be discharged uniformly during the sampling period. When radioactivity is identified at a concentration below the LLD for the analysis, that concentration is reported.
3.2 Radioactivity in Gaseous Effluent For the purpose of estimating offsite radionuclide concentrations and radiation doses, measured radionuclide concentrations in gaseous effluent and in ventilation air exhausted from the Station are relied upon. The gross radioactivity of noble gases discharged is measured by the radioactive noble gas effluent monitors according to Tables 6.2-1 and 7.2-2. Radionuclides other than noble gases in gaseous effluents are measured by sampling and analyses in accordance with Table 7.2-2. Each radionuclide measured in an effluent may be assumed to be discharged uniformly during the sampling period. When radioactivity is identified at a concentration below the LLD for the analysis, that concentration is reported.
When radioactivity is not identified in a sample, it is not reported as being present in that sample. The quantity of radioactive noble gas discharged via the offgas stack or a vent during an interval of time is determined by integrating the release rate measurement of each effluent noble gas monitor.
When radioactivity is not identified in a sample, it is not reported as being present in that sample. The quantity of radioactive noble gas discharged via the offgas stack or a vent during an interval of time is determined by integrating the release rate measurement of each effluent noble gas monitor. An hourly interval is normally used for dose rate assessments and a daily or longer interval is used for dose assessments.
An hourly interval is normally used for dose rate assessments and a daily or longer interval is used for dose assessments.
If represents the gross activity of noble gas discharged via the offgas stack or a vent and gi represents the fraction of radionuclide i in the distribution of radioactive gases in that effluent stream, then the quantity of radionuclide i released in the gaseous effluent stream during counting interval j is estimated by the relation:
If represents the gross activity of noble gas discharged via the offgas stack or a vent and gi represents the fraction of radionuclide i in the distribution of radioactive gases in that effluent stream, then the quantity of radionuclide i released in the gaseous effluent stream during counting interval j is estimated by the relation:
The distribution of radioactive noble gases in gaseous effluent streams is determined by gamma spectrum analysis of gaseous effluent samples in accordance with Table 7.2-2. Results of one or more previous analyses may be averaged to obtain a representative spectrum.
The distribution of radioactive noble gases in gaseous effluent streams is determined by gamma spectrum analysis of gaseous effluent samples in accordance with Table 7.2-2. Results of one or more previous analyses may be averaged to obtain a representative spectrum.
In the event a representative distribution is not available or is unobtainable from sample(s) of an effluent stream taken during the current quarter, it will be derived from past measurements, e.g., earlier sample results or annual radioactive material release reports.
In the event a representative distribution is not available or is unobtainable from sample(s) of an effluent stream taken during the current quarter, it will be derived from past measurements, e.g., earlier sample results or annual radioactive material release reports. Alternatively, a noble gas spectrum for a given effluent stream in Table 3-2 herein, may be assumed. DAECODAM Page 16 of 280 Rev. 37 An airborne discharge of radionuclides other than noble gases may be represented by multiple samples with each sample providing a measure of the concentration of specific radionuclides, Ci, in gaseous effluent discharged at flow, Fa, during a time increment At. Thus, each release is quantified according to the relation:
Alternatively, a noble gas spectrum for a given effluent stream in Table 3-2 herein, may be assumed.
where Fa1 = Qik = 2: Ck FaJ l'!..tJ j the quantity of radionuclide i released in a given effluent stream based on analysis k (Ci) concentration of radionuclide i in gaseous effluent identified by analysis k (&#xb5;Ci/ML or Ci/m 3) effluent stream discharge rate during the increment Dti (m 3/sec) time increment during which radionuclide i at concentration Cik is being discharged (sec) The analysis index k may represent either a grab sample, integrated sample, or a composite sample required by the effluent sampling and analysis program specified in Table 7.2-2. 3.3 Main Condenser Offgas Pretreatment Monitor Alarm Setpoint A noble gas activity monitor is provided to measure gross gamma activity in gases from the main condenser air ejector. The pretreatment monitor includes an alarm that is set to report when the gamma radiation level in gas discharged by the main condenser air ejector indicates the gross radioactivity discharge rate, after 30 minutes delay and decay, exceeds 1 Ci/sec. The main condenser Offgas gross gamma activity rate is an initial condition of the Steam-Line Break Accident (Roof Top Release).
DAECODAM Page 16 of 280 Rev. 37 An airborne discharge of radionuclides other than noble gases may be represented by multiple samples with each sample providing a measure of the concentration of specific radionuclides, Ci, in gaseous effluent discharged at flow, Fa, during a time increment At. Thus, each release is quantified according to the relation:
where Fa1 = Qik = 2: Ck FaJ l'!..tJ j the quantity of radionuclide i released in a given effluent stream based on analysis k (Ci) concentration of radionuclide i in gaseous effluent identified by analysis k (&#xb5;Ci/ML or Ci/m3) effluent stream discharge rate during the increment Dti (m3/sec) time increment during which radionuclide i at concentration Cik is being discharged (sec) The analysis index k may represent either a grab sample, integrated sample, or a composite sample required by the effluent sampling and analysis program specified in Table 7.2-2. 3.3 Main Condenser Offgas Pretreatment Monitor Alarm Setpoint A noble gas activity monitor is provided to measure gross gamma activity in gases from the main condenser air ejector.
The pretreatment monitor includes an alarm that is set to report when the gamma radiation level in gas discharged by the main condenser air ejector indicates the gross radioactivity discharge rate, after 30 minutes delay and decay, exceeds 1 Ci/sec. The main condenser Offgas gross gamma activity rate is an initial condition of the Steam-Line Break Accident (Roof Top Release).
Restricting the gross radioactivity rate of noble gasses from the main condenser to a rate of 1 Ci/sec provides reasonable assurance that the total body exposure to an individual at the exclusion area boundary will not exceed a small fraction of the limits of 10 CFR Part 50.67 in the event this effluent is inadvertently discharged directly to the environment without treatment.
Restricting the gross radioactivity rate of noble gasses from the main condenser to a rate of 1 Ci/sec provides reasonable assurance that the total body exposure to an individual at the exclusion area boundary will not exceed a small fraction of the limits of 10 CFR Part 50.67 in the event this effluent is inadvertently discharged directly to the environment without treatment.
DAECODAM Page 17 of 280 Rev. 37 where The alarm setpoint is determined with the relation:
DAECODAM Page 17 of 280 Rev. 37 where The alarm setpoint is determined with the relation:
S= 2120 = F= g= main condenser air ejector noble gas monitor alarm setpoint (cpm) or (MR/hr) [(1.0 E6 &#xb5;Ci/sec)  
S= 2120 = F= g= main condenser air ejector noble gas monitor alarm setpoint (cpm) or (MR/hr) [(1.0 E6 &#xb5;Ci/sec) * (1 ft3/28317 cm 3)]
* (1 ft3/28317 cm3)]
* 60 sec/min air ejector discharge rate (ft3/min) noble gas monitor calibration or counting rate response for gamma radiation l cpm J l mR I hr J &#xb5;Ci I cm 3 or &#xb5;Ci I cm 3 f; = fraction of noble gas gross activity due to noble gas radionuclide i in a representative spectrum of noble gases at the main condenser offgas detector A; = radioactive decay constant of noble gas nuclide i (min-1) t = 30 min; decay time in delay line DAEC ODAM Page 18 of 280 Rev. 37 3.4 Effluent Noble Gas Monitor Alarm Setpoint Section 6.2.2 provides limits on dose equivalent rates associated with airborne radioactive materials concentrations in the unrestricted area due to airborne effluents from the Station. Instrumentation is provided to monitor gamma radiation in the airborne effluents according to Table 6.2-1. Each effluent noble gas monitor includes an alarm that can be set to activate when the dose rate off site or the noble gas concentration at ground level offsite is expected (calculated) to exceed a specified level. Compliance with the limits on dose rate from noble gases is demonstrated by setting each gaseous effluent monitor alarm setpoint so that an alarm will occur at or before the dose rate limit for noble gases is reached. If an alarm occurs with the setpoint at the limit, compliance with Section 6.2.2.a is assessed as described in section 3.5. On the basis of effluent noble gases from the DAEC during recent years, the gamma dose rate to a person's whole body is expected to be a larger fraction of the limit, 500 mrem/yr, than is the beta plus gamma dose rate to skin is to its limit, 3000 mrem/yr. As a result, a gaseous effluent monitor setpoint may be derived on the basis of the gamma dose rate to a person's whole body alone such that an alarm is set to occur at or before the whole body dose rate offsite exceeds 500 mrem/yr. A noble gas monitor may be set to activate an alarm at a lower setting than the derived setpoint corresponding to the dose rate limit (or corresponding concentration limit). In the event an alarm occurs at the lower setting, the monitor record is compared with the derived setpoint.
* 60 sec/min air ejector discharge rate (ft3/min) noble gas monitor calibration or counting rate response for gamma radiation l cpm J l mR I hr J &#xb5;Ci I cm3 or &#xb5;Ci I cm3 f; = fraction of noble gas gross activity due to noble gas radionuclide i in a representative spectrum of noble gases at the main condenser offgas detector A; = radioactive decay constant of noble gas nuclide i (min-1) t = 30 min; decay time in delay line DAEC ODAM Page 18 of 280 Rev. 37 3.4 Effluent Noble Gas Monitor Alarm Setpoint Section 6.2.2 provides limits on dose equivalent rates associated with airborne radioactive materials concentrations in the unrestricted area due to airborne effluents from the Station.
Instrumentation is provided to monitor gamma radiation in the airborne effluents according to Table 6.2-1. Each effluent noble gas monitor includes an alarm that can be set to activate when the dose rate off site or the noble gas concentration at ground level offsite is expected (calculated) to exceed a specified level. Compliance with the limits on dose rate from noble gases is demonstrated by setting each gaseous effluent monitor alarm setpoint so that an alarm will occur at or before the dose rate limit for noble gases is reached.
If an alarm occurs with the setpoint at the limit, compliance with Section 6.2.2.a is assessed as described in section 3.5. On the basis of effluent noble gases from the DAEC during recent years, the gamma dose rate to a person's whole body is expected to be a larger fraction of the limit, 500 mrem/yr, than is the beta plus gamma dose rate to skin is to its limit, 3000 mrem/yr.
As a result, a gaseous effluent monitor setpoint may be derived on the basis of the gamma dose rate to a person's whole body alone such that an alarm is set to occur at or before the whole body dose rate offsite exceeds 500 mrem/yr.
A noble gas monitor may be set to activate an alarm at a lower setting than the derived setpoint corresponding to the dose rate limit (or corresponding concentration limit). In the event an alarm occurs at the lower setting, the monitor record is compared with the derived setpoint.
If the derived setpoint is exceeded, compliance with Section 6.2.2.a is assessed as described in section 3.5. Each radioactive noble gas effluent monitor setpoint is derived on the basis of whole body dose equivalent rate in the unrestricted area. Setpoints for gaseous effluent monitors may be set independently because excessive effluent release via the turbine building vent is unlikely.
If the derived setpoint is exceeded, compliance with Section 6.2.2.a is assessed as described in section 3.5. Each radioactive noble gas effluent monitor setpoint is derived on the basis of whole body dose equivalent rate in the unrestricted area. Setpoints for gaseous effluent monitors may be set independently because excessive effluent release via the turbine building vent is unlikely.
Other releases are likely to be initiated independently and released from different levels, i.e., vent and stack releases with points of maximum concentration offsite not likely to coincide.
Other releases are likely to be initiated independently and released from different levels, i.e., vent and stack releases with points of maximum concentration offsite not likely to coincide.
For the purpose of deriving a setpoint, the distribution of radioactive noble gases in an effluent stream is determined as described in section 3.2. Setpoint Determination The alarm setpoint of a radioactive noble gas effluent monitor may be calculated on the basis of whole body dose equivalent rate offsite, 500 mrem/yr.
For the purpose of deriving a setpoint, the distribution of radioactive noble gases in an effluent stream is determined as described in section 3.2. Setpoint Determination The alarm setpoint of a radioactive noble gas effluent monitor may be calculated on the basis of whole body dose equivalent rate offsite, 500 mrem/yr. A setpoint of a monitor of an elevated release, e.g., from the stack, may be calculated with the equation:
A setpoint of a monitor of an elevated  
r :Le; j S = 1. 06 * .!!_ * ; + Bkg f LC;XDFf i DAEC ODAM Page 19 of 280 Rev. 37 The setpoint of a monitor of a ground-level or building release, e.g., from the turbine building vent or 3 reactor building vents or LLRPSF vent may be calculated with the equation:
: release, e.g., from the stack, may be calculated with the equation:
l :Le; j S= 1.06*-(h J L i v +Bkg f X C;*DF; Q i where s = the alarm setpoint (cpm) or (MR/hr) h = monitor response to activity concentration of effluent being monitored, C= DF[ = Bkg = DAECODAM l cpm J l mR I hr J &#xb5;Ci I cm 3 or &#xb5;Ci I cm 3 relative concentration of noble gas radionuclide i in effluent at the point of monitoring  
r :Le; j S = 1. 06 * .!!_ * ; + Bkg f LC;XDFf i DAEC ODAM Page 19 of 280 Rev. 37 The setpoint of a monitor of a ground-level or building  
(&#xb5;Ci/cm 3) atmospheric dispersion from point of ground-level or building wake release to the location of potential exposure (sec/m 3) factor converting elevated release rate of radionuclide i to whole body dose equivalent rate at the location of potential exposure l mremCiJ yr
: release, e.g., from the turbine building vent or 3 reactor building vents or LLRPSF vent may be calculated with the equation:
l :Le; j S= 1.06*-(h J L i v +Bkg f X C;*DF; Q i where s = the alarm setpoint (cpm) or (MR/hr) h = monitor response to activity concentration of effluent being monitored, C= DF[ = Bkg = DAECODAM l cpm J l mR I hr J &#xb5;Ci I cm3 or &#xb5;Ci I cm3 relative concentration of noble gas radionuclide i in effluent at the point of monitoring  
(&#xb5;Ci/cm3) atmospheric dispersion from point of ground-level or building wake release to the location of potential exposure (sec/m3) factor converting elevated release rate of radionuclide i to whole body dose equivalent rate at the location of potential exposure l mremCiJ yr
* 1!__ sec factor converting ground-level of split-wake release of radionuclide i to the whole body dose equivalent rate at the location of potential exposure l mremCij yr* &#xb5; 3 m flow of gaseous effluent stream, i.e., flow past the monitor (ft3/min) monitoring instrument background (cpm) or (MR/hr) Page 20 of 280 Rev. 37 Each monitoring channel has a unique response, h, which is determined by the instrument calibration.
* 1!__ sec factor converting ground-level of split-wake release of radionuclide i to the whole body dose equivalent rate at the location of potential exposure l mremCij yr* &#xb5; 3 m flow of gaseous effluent stream, i.e., flow past the monitor (ft3/min) monitoring instrument background (cpm) or (MR/hr) Page 20 of 280 Rev. 37 Each monitoring channel has a unique response, h, which is determined by the instrument calibration.
The concentration of each noble gas radionuclide, Cj, in a gaseous effluent is determined as discussed earlier in this section.
The concentration of each noble gas radionuclide, Cj, in a gaseous effluent is determined as discussed earlier in this section. Since the dose rate limits for airborne effluents apply everywhere offsite, alarm setpoints are determined and compliance is assessed at the site boundary where the minimum atmospheric dispersion (maximum XI Q) occurs. The atmospheric dispersion factor and the dose conversion factor DFt depend on local conditions.
Since the dose rate limits for airborne effluents apply everywhere  
The value of XI Q adopted in a setpoint calculation will be based either on prevailing meteorological conditions or on reference meteorological conditions at the DAEC. The minimum atmospheric dispersion offsite from a ground-level or building wake release derived from reference meteorological conditions is at the site boundary 1260 meters NNW of the Station where: (x) =4.3* 10-6 sec/ m 3 Q vent The dose conversion factors, DFt , used in setpoint calculations for gaseous effluent monitors are in Table 3-4. In the event DFt is derived on the basis of prevailing meteorology, it will be calculated in accordance with Regulatory Guide 1.109, Appendix B. DAECODAM Page 21 of 280 Rev. 37 3.5 Dose Equivalent Rate Offsite Section 6.2.2 provides limits on dose equivalent rates associated with airborne radioactive materials concentrations in the unrestricted area due to airborne effluents from the Station. Compliance is assessed on the basis of measurements specified in Table 7.2-2. 3.5.1 Noble Gas Limits on radioactive noble gas in the unrestricted area are provided in Section 6.2.2.a. Each radioactive noble gas effluent monitor is set to alarm when, or below when, the noble gas in airborne effluent from a monitored stack or vent is expected to cause either dose rate limit in Section 6.2.2.a to be exceeded.
: offsite, alarm setpoints are determined and compliance is assessed at the site boundary where the minimum atmospheric dispersion (maximum XI Q) occurs. The atmospheric dispersion factor and the dose conversion factor DFt depend on local conditions.
In the event an airborne effluent release from the Station exceeds the derived setpoint (limit) for an effluent noble gas monitor (except when caused by the performance of a Surveillance Test Procedure), an assessment of compliance is performed as described herein. The quantity of radioactive noble gas released in a increment of time is measured by the radioactive noble gas effluent monitors and the distribution of radioactive noble gases in a gaseous effluent stream is determined as described in section 3.2 herein. Compliance with Section 6.2.2.a may be assessed by calculating the dose equivalent rate as described hereafter and by comparing it with the limiting dose rate in the Specification.
The value of XI Q adopted in a setpoint calculation will be based either on prevailing meteorological conditions or on reference meteorological conditions at the DAEC. The minimum atmospheric dispersion offsite from a ground-level or building wake release derived from reference meteorological conditions is at the site boundary 1260 meters NNW of the Station where: (x) =4.3* 10-6 sec/ m3 Q vent The dose conversion  
3.5.1.1 Total Body Dose Rate For evaluating compliance with Effluent Control, Section 6.2.2.a, the total body dose equivalent rate due to noble gas gamma radiation is calculated with the equation:
: factors, DFt , used in setpoint calculations for gaseous effluent monitors are in Table 3-4. In the event DFt is derived on the basis of prevailing meteorology, it will be calculated in accordance with Regulatory Guide 1.109, Appendix B. DAECODAM Page 21 of 280 Rev. 37 3.5 Dose Equivalent Rate Offsite Section 6.2.2 provides limits on dose equivalent rates associated with airborne radioactive materials concentrations in the unrestricted area due to airborne effluents from the Station.
where Dr= DFf = DAECODAM -1 [ (Qgi sJ (Qg; (XJ vJ] Dy=----*DFi --* -*DF; 3600 l t s v l t Q v noble gas gamma dose rate to total body (mrem/yr) quantity of noble gas radionuclide i discharged  
Compliance is assessed on the basis of measurements specified in Table 7.2-2. 3.5.1 Noble Gas Limits on radioactive noble gas in the unrestricted area are provided in Section 6.2.2.a.
(&#xb5;Ci) during time increment t (yr) factor converting unit noble gas nuclide i stack release to total body dose at ground level received from the overhead plume [ mrem ] (&#xb5;Ci yr) I sec Page 22 of 280 Rev. 37 factor converting time integrated, ground level concentration of noble gas nuclide i to total body dose from gamma dose from gamma radiation 1 3600 = ( mrem ) &#xb5;Ci yr I m 3 conversion (hr/sec) Dose factor DF!, for exposure to noble gases released from an elevated stack are calculated by a finite plume model implemented in the MIDAS program.1 a It assumes decay of short-lived nuclides, an air dose-to-tissue dose conversion of 1.11, and that the dose to internal organs is equivalent to the tissue dose. In this model, meteorological data concurrent with the period of release are used to evaluate the dose rate. The dose from noble gases released from a vent (near ground level) or to skin from an elevated release is derived from a semi-infinite cloud model. Noble gas semi-infinite cloud gamma-to-total body dose factors, DFr, are listed in Table 3-4. When the total body and organ doses from noble gases are computed as required by Section 7.3.1, the nearby resident exposed to the maximal ground-level noble gas concentration (maximum ,VQ) is selected as the receptor.
Each radioactive noble gas effluent monitor is set to alarm when, or below when, the noble gas in airborne effluent from a monitored stack or vent is expected to cause either dose rate limit in Section 6.2.2.a to be exceeded.
Alternatively, the dose from noble gases may be computed at 1260 meters NNW of the reactor, a location identified in Figure 3-2, where the nearby resident who may be exposed to maximal ground-level noble gas concentrations (maximum ,VQ) is selected as the receptor.c In that case, values of the dose factors DF! and DFr in Table 3-4 are employed.m Total body dose factors for exposure from a plume from an elevated, stack release, DF!, in Table 3-4 were computed with the aid of an NRC code, RABFIN. In those computations, reference meteorology was assumed as the basis of atmospheric dispersion.
In the event an airborne effluent release from the Station exceeds the derived setpoint (limit) for an effluent noble gas monitor (except when caused by the performance of a Surveillance Test Procedure),
For discharge from a vent, reference meteorological dispersion at the 1260 m NNW, ( x!Q Jv, is 4.3 x 1 o-6 sec/m 3. 3.5.1.2 Skin Dose Rate The skin dose equivalent rate due to radioactive noble gas is calculated with the equation:  
an assessment of compliance is performed as described herein. The quantity of radioactive noble gas released in a increment of time is measured by the radioactive noble gas effluent monitors and the distribution of radioactive noble gases in a gaseous effluent stream is determined as described in section 3.2 herein. Compliance with Section 6.2.2.a may be assessed by calculating the dose equivalent rate as described hereafter and by comparing it with the limiting dose rate in the Specification.
3.5.1.1 Total Body Dose Rate For evaluating compliance with Effluent  
: Control, Section 6.2.2.a, the total body dose equivalent rate due to noble gas gamma radiation is calculated with the equation:
where Dr= DFf = DAECODAM  
-1 [ (Qgi sJ (Qg; (XJ vJ] Dy=----*DFi --* -*DF; 3600 l t s v l t Q v noble gas gamma dose rate to total body (mrem/yr) quantity of noble gas radionuclide i discharged  
(&#xb5;Ci) during time increment t (yr) factor converting unit noble gas nuclide i stack release to total body dose at ground level received from the overhead plume [ mrem ] (&#xb5;Ci yr) I sec Page 22 of 280 Rev. 37 factor converting time integrated, ground level concentration of noble gas nuclide i to total body dose from gamma dose from gamma radiation 1 3600 = ( mrem ) &#xb5;Ci yr I m3 conversion (hr/sec)
Dose factor DF!, for exposure to noble gases released from an elevated stack are calculated by a finite plume model implemented in the MIDAS program.1a It assumes decay of short-lived  
: nuclides, an air dose-to-tissue dose conversion of 1.11, and that the dose to internal organs is equivalent to the tissue dose. In this model, meteorological data concurrent with the period of release are used to evaluate the dose rate. The dose from noble gases released from a vent (near ground level) or to skin from an elevated release is derived from a semi-infinite cloud model. Noble gas semi-infinite cloud gamma-to-total body dose factors, DFr, are listed in Table 3-4. When the total body and organ doses from noble gases are computed as required by Section 7.3.1, the nearby resident exposed to the maximal ground-level noble gas concentration (maximum  
,VQ) is selected as the receptor.
Alternatively, the dose from noble gases may be computed at 1260 meters NNW of the reactor, a location identified in Figure 3-2, where the nearby resident who may be exposed to maximal ground-level noble gas concentrations (maximum  
,VQ) is selected as the receptor.c In that case, values of the dose factors DF! and DFr in Table 3-4 are employed.m Total body dose factors for exposure from a plume from an elevated, stack release, DF!, in Table 3-4 were computed with the aid of an NRC code, RABFIN. In those computations, reference meteorology was assumed as the basis of atmospheric dispersion.
For discharge from a vent, reference meteorological dispersion at the 1260 m NNW, ( x!Q Jv, is 4.3 x 1 o-6 sec/m3. 3.5.1.2 Skin Dose Rate The skin dose equivalent rate due to radioactive noble gas is calculated with the equation:  
;;/3=-1 [J;,Spi(Q;  
;;/3=-1 [J;,Spi(Q;  
*(%)} +z:J;, Spi(Q; *(%)} l 3600 l t Q s v l t Q v where a David Slade, ed., Meteorology and Atomic Energy 1968, TID-24190,pp.
*(%)} +z:J;, Spi(Q; *(%)} l 3600 l t Q s v l t Q v where a David Slade, ed., Meteorology and Atomic Energy 1968, TID-24190,pp.
350-355.
350-355. m Dose transfer factors DF;&deg; in Table 3.4 are a units conversion of values in Regulatory Guide 1.109, Table B-1, column 5. cDue to limitations of the Midas&#xa9; software used to perform these calculations, a conservative higher calculated dose may be reported.
m Dose transfer factors DF;&deg; in Table 3.4 are a units conversion of values in Regulatory Guide 1.109, Table B-1, column 5. cDue to limitations of the Midas&#xa9; software used to perform these calculations, a conservative higher calculated dose may be reported.
When using Annualized Average Meteorological data, the Midas system uses known X/Q values from the 1 mile radius to extrcpolate X/Q values at the site boundary.
When using Annualized Average Meteorological data, the Midas system uses known X/Q values from the 1 mile radius to extrcpolate X/Q values at the site boundary.
The resulting maximum site boundary X/Q value is greater than 4.3 x 10 sec/m3 and is located on the site boundary toward the SSE. DAECODAM Page 23 of 280 Rev. 37 Dp Qi t = = noble gas beta dose rate to skin (mrem/yr) quantity of noble gas radionuclide i (&#xb5;Ci) discharged during time increment t (hr) S /Ji = factor converting time integrated ground level concentration of noble gas to skin dose from beta radiation mJ] &#xb5;Ciyr 1 3600 = conversion (hr/sec)
The resulting maximum site boundary X/Q value is greater than 4.3 x 10 sec/m 3 and is located on the site boundary toward the SSE. DAECODAM Page 23 of 280 Rev. 37 Dp Qi t = = noble gas beta dose rate to skin (mrem/yr) quantity of noble gas radionuclide i (&#xb5;Ci) discharged during time increment t (hr) S /Ji = factor converting time integrated ground level concentration of noble gas to skin dose from beta radiation mJ] &#xb5;Ciyr 1 3600 = conversion (hr/sec) Compliance with Section 6.2.2.a dose rate to skin is evaluated by calculating the noble gas beta dose equivalent rate offsite at a location 1260 meters NNW of the Station, which is also identified in Figure 3-2.ct At that location, the reference atmospheric dispersion factors to be used in the calculations are: =4.3* J0-6 sec/ m 3 and =2.8* 10-7 sec/ m 3 Alternatively, averaged meteorological dispersion data coincident with the period of release may be used to evaluate the dose rate. The semi-infinite noble gas skin dose equivalent factors are in Table 3-4. They are also derived from Regulatory Guide 1.109, Table 8-1. d Due to limitations of the Midas&#xa9; software used to perform these calculations, a conservative higher calculated dose may be reported.
Compliance with Section 6.2.2.a dose rate to skin is evaluated by calculating the noble gas beta dose equivalent rate offsite at a location 1260 meters NNW of the Station, which is also identified in Figure 3-2.ct At that location, the reference atmospheric dispersion factors to be used in the calculations are: =4.3* J0-6 sec/ m3 and =2.8* 10-7 sec/ m3 Alternatively, averaged meteorological dispersion data coincident with the period of release may be used to evaluate the dose rate. The semi-infinite noble gas skin dose equivalent factors are in Table 3-4. They are also derived from Regulatory Guide 1.109, Table 8-1. d Due to limitations of the Midas&#xa9; software used to perform these calculations, a conservative higher calculated dose may be reported.
When using Annualized Average Meteorological data, the Midas system uses known X/Q values from the 1 mile radius to extrapolate X/Q values at the site boundary.
When using Annualized Average Meteorological data, the Midas system uses known X/Q values from the 1 mile radius to extrapolate X/Q values at the site boundary.
The resulting maximum site boundary X/Q value is greater than 4.3 x 10-e sec/m3 and is located on the site boundary toward the SSE. DAECODAM Page 24 of 280 Rev. 37 3.5.2 Iodine, Tritium, and Particulates Section 6.2.2.b provides a limit on iodine-131, iodine-133, H-3, and on radioactive particulates having 8 day or longer half-lives in air in the unrestricted area around the Station.
The resulting maximum site boundary X/Q value is greater than 4.3 x 10-e sec/m 3 and is located on the site boundary toward the SSE. DAECODAM Page 24 of 280 Rev. 37 3.5.2 Iodine, Tritium, and Particulates Section 6.2.2.b provides a limit on iodine-131, iodine-133, H-3, and on radioactive particulates having 8 day or longer half-lives in air in the unrestricted area around the Station. In the event airborne effluent from the Station causes a radioactive noble gas effluent monitor to alarm (except when alarm is due to the performance of a Surveillance Test Procedure) or if the assessment required by Section 7.2.4 shows Section 6.2.4 to have been exceeded, an assessment of compliance with Section 6.2.2.b will be performed using a method described in this section. 3.5.2.1 Organ Dose Ratee Compliance with Section 6.2.2.b is assessed by calculating the dose rate* to the most exposed organ of an assumed adult member of the public inhaling airborne 1-131, 1-133, H-3, and inhaling radioactive particulates having half-lives of 8 days or longer at the location in the unrestricted area having the maximum potential concentration of the effluents (i.e., the location at which reference meteorological data indicates minimum atmospheric dispersion from the Station (max XI Q). The organ dose rate is calculated with the following equations:
In the event airborne effluent from the Station causes a radioactive noble gas effluent monitor to alarm (except when alarm is due to the performance of a Surveillance Test Procedure) or if the assessment required by Section 7.2.4 shows Section 6.2.4 to have been exceeded, an assessment of compliance with Section 6.2.2.b will be performed using a method described in this section.
3.5.2.1 Organ Dose Ratee Compliance with Section 6.2.2.b is assessed by calculating the dose rate* to the most exposed organ of an assumed adult member of the public inhaling airborne 1-131, 1-133, H-3, and inhaling radioactive particulates having half-lives of 8 days or longer at the location in the unrestricted area having the maximum potential concentration of the effluents (i.e., the location at which reference meteorological data indicates minimum atmospheric dispersion from the Station (max XI Q). The organ dose rate is calculated with the following equations:
For a vent discharge:
For a vent discharge:
Danv 8. 7 66E -3 "'""' "'""' L., L., Qikv TAani TE-TB k For an offgas stack discharge:
Danv 8. 7 66E -3 "'""' "'""' L., L., Qikv TAani TE-TB k For an offgas stack discharge:
Line 185: Line 135:
Dans = dose equivalent rate from a stack discharge (mrem/yr)
Dans = dose equivalent rate from a stack discharge (mrem/yr)
Danv = dose equivalent rate from a vent discharge (mrem/yr)
Danv = dose equivalent rate from a vent discharge (mrem/yr)
Qks, Q"" = quantity of radionuclide i released in a given effluent stream based on analysis k (&#xb5;Ci) during discharged time increment TB to TE (hr) of interest Qiks' Qih* = quantity of radionuclide i released in a given effluent stream based on analysis k (&#xb5;Ci) during discharged time increment TB to TE (hr) of interest  
Qks, Q"" = quantity of radionuclide i released in a given effluent stream based on analysis k (&#xb5;Ci) during discharged time increment TB to TE (hr) of interest Qiks' Qih* = quantity of radionuclide i released in a given effluent stream based on analysis k (&#xb5;Ci) during discharged time increment TB to TE (hr) of interest &deg;For inhaled or ingested radioactive material, the consequent "dose" means the committed dose equivalent.
&deg;For inhaled or ingested radioactive  
: material, the consequent "dose" means the committed dose equivalent.
The "dose rate" is the committed dose equivalent per unit of time of exposure to the radioactive material in the environment.
The "dose rate" is the committed dose equivalent per unit of time of exposure to the radioactive material in the environment.
DAECODAM Page 25 of 280 Rev. 37 TAani = factor converting airborne concentration of radionuclide i to dose commitment to organ n of a person in age group a where exposure is directly to airborne material  
DAECODAM Page 25 of 280 Rev. 37 TAani = factor converting airborne concentration of radionuclide i to dose commitment to organ n of a person in age group a where exposure is directly to airborne material ((c;::J/J l XQiJs *lXQiJv = atmospheric dispersion from stack and vent, respectively, to ground level at location of interest (sec/m 3) 8. 766E-3 = Conversion (1 Ci/1 E6 &#xb5;Ci)(8766 hr/yr) Radionuclides other than noble gases airborne effluent are measured and quantified as described in section 3.2. Normally, radioactive material measured in effluent is assumed to be discharged uniformly over the period represented by the sample. The averaging time of the measured releases used to evaluate compliance will not exceed 92 days for Sr-89 and Sr-90 and will not exceed 31 days for the other radionuclides.
((c;::J/J lXQiJs *lXQiJv = atmospheric dispersion from stack and vent, respectively, to ground level at location of interest (sec/m3) 8. 766E-3 = Conversion (1 Ci/1E6 &#xb5;Ci)(8766 hr/yr) Radionuclides other than noble gases airborne effluent are measured and quantified as described in section 3.2. Normally, radioactive material measured in effluent is assumed to be discharged uniformly over the period represented by the sample. The averaging time of the measured releases used to evaluate compliance will not exceed 92 days for Sr-89 and Sr-90 and will not exceed 31 days for the other radionuclides.
The maximum offsite exposure potential is expected to occur at 1260 meters NNW of the Station where the reference atmospheric dispersion, to be used in the calculation is 4.3
The maximum offsite exposure potential is expected to occur at 1260 meters NNW of the Station where the reference atmospheric dispersion, to be used in the calculation is 4.3
* 10-6 sec/m3 and 2.8
* 10-6 sec/m 3 and 2.8
* 10-7 sec/m3 Currently, compliance with Section 6.2.2.b is evaluated by calculating an adult inhalation dose rate at 1260 meters NNW of the Stationt.
* 10-7 sec/m 3 Currently, compliance with Section 6.2.2.b is evaluated by calculating an adult inhalation dose rate at 1260 meters NNW of the Stationt.
The dose transfer  
The dose transfer factors, TAani. used in the computation are tabulated in Appendix A. bue to limitations of the Midas&#xa9; software used to perform these calculations, a conservative higher calculated dose may be reported.
: factors, TAani. used in the computation are tabulated in Appendix A. bue to limitations of the Midas&#xa9; software used to perform these calculations, a conservative higher calculated dose may be reported.
When using Annualized Average Meteorological data, the Midas system uses known X/Q values from the 1 mile radius to extrapolate XJQ values at the site boundary.
When using Annualized Average Meteorological data, the Midas system uses known X/Q values from the 1 mile radius to extrapolate XJQ values at the site boundary.
The resulting maximum site boundary XJQ value is greater than 4.3 x 1 O.s sec/m3 and is located on the site boundary toward the SSE. DAEC ODAM Page 26 of 280 Rev. 37 805.1.1.1 Rainwater Recapture of Tritium The phenomenon of rainwater recapture of the tritium present in gaseous effluents has been observed on site. A liquid pathway analysis of the activity present in the rainwater runoff has been performed.
The resulting maximum site boundary XJQ value is greater than 4.3 x 1 O.s sec/m 3 and is located on the site boundary toward the SSE. DAEC ODAM Page 26 of 280 Rev. 37 805.1.1.1 Rainwater Recapture of Tritium The phenomenon of rainwater recapture of the tritium present in gaseous effluents has been observed on site. A liquid pathway analysis of the activity present in the rainwater runoff has been performed.
The maximum dose to a member of the public from this liquid has been conservatively estimated to be less than 0.01 mrem per year. 3.6 Noble Gas Gamma Radiation Dose Accumulated in Air Section 6.2.3 requires that the offsite air dose during any calendar quarter not exceed 5 mrad and the annual air dose not exceed 10 mrad from noble gas gamma radiation.
The maximum dose to a member of the public from this liquid has been conservatively estimated to be less than 0.01 mrem per year. 3.6 Noble Gas Gamma Radiation Dose Accumulated in Air Section 6.2.3 requires that the offsite air dose during any calendar quarter not exceed 5 mrad and the annual air dose not exceed 10 mrad from noble gas gamma radiation.
Section 7.2.3.1 requires a monthly calculation assessment to verify that the cumulative air dose due to gamma radiation from radioactive noble gas released in gaseous effluents during the quarter and year do not exceed Section 6.2.3. The distribution of radioactive noble gases in gaseous releases and the quantity of radioactive noble gas discharged during an interval of time are determined as described in section 3.2 herein. The gamma radiation dose to air offsite as a consequence of noble gas discharge from DAEC is calculated with the where Dr= =
Section 7.2.3.1 requires a monthly calculation assessment to verify that the cumulative air dose due to gamma radiation from radioactive noble gas released in gaseous effluents during the quarter and year do not exceed Section 6.2.3. The distribution of radioactive noble gases in gaseous releases and the quantity of radioactive noble gas discharged during an interval of time are determined as described in section 3.2 herein. The gamma radiation dose to air offsite as a consequence of noble gas discharge from DAEC is calculated with the where Dr= =
Line 203: Line 149:
: i. factor converting unit release of noble gas radionuclide i from the stack to air dose at ground-level received from gamma radiation from the overhead plume (mrad/&#xb5;Ci) factor converting time integrated, ground-level concentration of noble gas to air dose from gamma radiation  
: i. factor converting unit release of noble gas radionuclide i from the stack to air dose at ground-level received from gamma radiation from the overhead plume (mrad/&#xb5;Ci) factor converting time integrated, ground-level concentration of noble gas to air dose from gamma radiation  
((,a:::)/
((,a:::)/
m3 J atmospheric dispersion factor for a vent (ground-level or building wake) discharge (sec/m3) Section 7.2.3.1 is satisfied by calculating the noble gas gamma radiation dose to air at the offsite location identified in Figure 3-2. At that location, 1260 meters NNW of the Stationh, the reference*
m3 J atmospheric dispersion factor for a vent (ground-level or building wake) discharge (sec/m 3) Section 7.2.3.1 is satisfied by calculating the noble gas gamma radiation dose to air at the offsite location identified in Figure 3-2. At that location, 1260 meters NNW of the Stationh, the reference*
9 atmospheric dispersion factor to be used is 9 Due to limitations of the Midas&#xa9; software used to perform these calculations, a conservative higher calculated dose may be reported.
9 atmospheric dispersion factor to be used is 9 Due to limitations of the Midas&#xa9; software used to perform these calculations, a conservative higher calculated dose may be reported.
When using Annualized Average Meteorological data, the Midas system uses known X/Q values from the 1 mile radius to extr<polate X/Q values at the site boundary.
When using Annualized Average Meteorological data, the Midas system uses known X/Q values from the 1 mile radius to extr<polate X/Q values at the site boundary.
The resulting maximum site boundary X/Q value is greater than 4.3 x 10 sec/m3 and is located on the site boundary toward the SSE. DAECODAM Page 27 of 280 Rev. 37   
The resulting maximum site boundary X/Q value is greater than 4.3 x 10 sec/m 3 and is located on the site boundary toward the SSE. DAECODAM Page 27 of 280 Rev. 37   
=4.3* Jo-6 sec/ m3 Values of Ays and Ayv appropriate for use at that location, assuming reference meteorological conditions, are listed in Table 3-3. An NRG code, RABFIN, modified for sector width averaged meteorology was used to calculate the air dose transfer  
=4.3* Jo-6 sec/ m 3 Values of Ays and Ayv appropriate for use at that location, assuming reference meteorological conditions, are listed in Table 3-3. An NRG code, RABFIN, modified for sector width averaged meteorology was used to calculate the air dose transfer factors, Ar; for a stack discharge, in ODAM Table 3-3. They represent air dose at ground level 1260 meters NNW of the station from a unit release of each radionuclide i from the stack. Dose transfer factors for vent discharges, Ar;, are equivalent to factors in Regulatory Guide 1.109, Table B-1, g-air expressed in different units. 3.6.1 Alternate Method of Evaluating Compliance with Gamma Air Dose Limits Alternatively, the gamma radiation dose to air offsite may be calculated with the equation where Ar,,Jf = Arwff = 0.8 = an effective dose conversion factor based on the typical radionuclide distribution in stack releases converting unit release of radioactive noble gases from the stack to air dose at ground level at a specific location (mrad/&#xb5;Ci).
: factors, Ar; for a stack discharge, in ODAM Table 3-3. They represent air dose at ground level 1260 meters NNW of the station from a unit release of each radionuclide i from the stack. Dose transfer factors for vent discharges, Ar;, are equivalent to factors in Regulatory Guide 1.109, Table B-1, g-air expressed in different units. 3.6.1 Alternate Method of Evaluating Compliance with Gamma Air Dose Limits Alternatively, the gamma radiation dose to air offsite may be calculated with the equation where Ar,,Jf = Arwff = 0.8 = an effective dose conversion factor based on the typical radionuclide distribution in stack releases converting unit release of radioactive noble gases from the stack to air dose at ground level at a specific location (mrad/&#xb5;Ci).
an effective dose conversion factor based on the typical radioactive distribution in vent releases converting a time integrated, ground level concentration of noble gases to air dose from gamma radiation l mrad J (&#xb5;Ci sec/ m 3) a factor of conservatism which compensates for variability in radionuclide distribution The derivation and basis of the effective gamma air dose conversion factor are provided in Appendix B. Values of the effective factors are tabulated in Table 3-3. By inserting the appropriate values for Dy (5 mrad/quarter y-air dose) and for AYseff (1.6 x 10-11 mrad/&#xb5;Ci) or Agveff (6.4 x 10-5 mrad/(&#xb5;Ci sec/m 3)) into the equation above and solving for either (AQi)s or (AQi)v, respectively, release quantities of noble gases from either the stack or vent corresponding to the technical specification limit of 5 mrad/quarter (total for all release points) may be determined.
an effective dose conversion factor based on the typical radioactive distribution in vent releases converting a time integrated, ground level concentration of noble gases to air dose from gamma radiation l mrad J (&#xb5;Ci sec/ m3) a factor of conservatism which compensates for variability in radionuclide distribution The derivation and basis of the effective gamma air dose conversion factor are provided in Appendix B. Values of the effective factors are tabulated in Table 3-3. By inserting the appropriate values for Dy (5 mrad/quarter y-air dose) and for AYseff (1.6 x 10-11 mrad/&#xb5;Ci) or Agveff (6.4 x 10-5 mrad/(&#xb5;Ci sec/m3)) into the equation above and solving for either (AQi)s or (AQi)v, respectively, release quantities of noble gases from either the stack or vent corresponding to the technical specification limit of 5 mrad/quarter (total for all release points) may be determined.
The limit of 5 mrad/quarter is described in section 6.2.3 and is for the total of all release points. At the location, 1260 meters NNW h Reference atmospheric conditions are summarized and discussed in "Duane Arnold Energy Center, Evaluation of Liquid and Gaseous Effluent Releases in Accordance with 10 CFR 50 Appendix I," submitted to NRC June 3, 1976, Reference atmospheric dispersion factors tabulated therein, also appear in Appendix B herein. DAECODAM Page 28 of 280 Rev. 37 of the station, (which is the controlling location based on reference meteorology) the release limits are individually Release Quarterly Limit (Ci) Annual Limit Point (Ci) Stack 2.5 x 10 5 5.0 x 10 5 Vent 1.25x10 4 2.5 x 10 4 The following equations may be used to assess both the stack and vent discharges for compliance with the quarterly release limits on noble gas gamma dose to air. j + j 250,000 12,500 or, on a monthly rate basis (although not a requirement) j + j 250,000 12,500 :::; 1 1 3 The equations which may be used to assess both the stack and vent discharges for compliance with the annual air dose limits from noble gas are: j + v j 500,000 25,000 or, on a monthly rate basis (although not a requirement) j + v j 500,000 25,000 :::; 1 1 12 As long as these relations are satisfied for both stack and vent releases of noble gases, no additional calculations are needed to verify compliance with the gamma-air dose limits of Section 6.2.3. Calculations of beta air doses per Section 3.6 may be omitted as discussed in Appendix B. DAECODAM Page 29 of 280 Rev. 37   
The limit of 5 mrad/quarter is described in section 6.2.3 and is for the total of all release points. At the location, 1260 meters NNW h Reference atmospheric conditions are summarized and discussed in "Duane Arnold Energy Center, Evaluation of Liquid and Gaseous Effluent Releases in Accordance with 10 CFR 50 Appendix I," submitted to NRC June 3, 1976, Reference atmospheric dispersion factors tabulated  
: therein, also appear in Appendix B herein. DAECODAM Page 28 of 280 Rev. 37 of the station, (which is the controlling location based on reference meteorology) the release limits are individually Release Quarterly Limit (Ci) Annual Limit Point (Ci) Stack 2.5 x 105 5.0 x 105 Vent 1.25x104 2.5 x 104 The following equations may be used to assess both the stack and vent discharges for compliance with the quarterly release limits on noble gas gamma dose to air. j + j 250,000 12,500 or, on a monthly rate basis (although not a requirement) j + j 250,000 12,500 :::; 1 1 3 The equations which may be used to assess both the stack and vent discharges for compliance with the annual air dose limits from noble gas are: j + v j 500,000 25,000 or, on a monthly rate basis (although not a requirement) j + v j 500,000 25,000 :::; 1 1 12 As long as these relations are satisfied for both stack and vent releases of noble gases, no additional calculations are needed to verify compliance with the gamma-air dose limits of Section 6.2.3. Calculations of beta air doses per Section 3.6 may be omitted as discussed in Appendix B. DAECODAM Page 29 of 280 Rev. 37   
: 3. 7 Noble Gas Beta Radiation Dose Accumulated in Air Section 6.2.3 requires that the offsite air dose during any calendar quarter not exceed 10 mrad from noble gas beta radiation and not exceed 20 mrad during any calendar year. Section 7.2.3.1 requires a monthly assessment to verify that the cumulative air dose due to beta radiation from radioactive noble gas released in gaseous effluents not exceed either limit of Section 6.2.3. The radioactive noble gas distribution and activity discharged are determined as described in paragraph 3.6 herein. The beta radiation dose to air offsite as a consequence of noble gas released from the Station is calculated with the equation:
: 3. 7 Noble Gas Beta Radiation Dose Accumulated in Air Section 6.2.3 requires that the offsite air dose during any calendar quarter not exceed 10 mrad from noble gas beta radiation and not exceed 20 mrad during any calendar year. Section 7.2.3.1 requires a monthly assessment to verify that the cumulative air dose due to beta radiation from radioactive noble gas released in gaseous effluents not exceed either limit of Section 6.2.3. The radioactive noble gas distribution and activity discharged are determined as described in paragraph 3.6 herein. The beta radiation dose to air offsite as a consequence of noble gas released from the Station is calculated with the equation:
where D/J = = = noble gas beta dose to air due to stack and vent releases (mrad) factor converting time-integrated, ground-level concentration of noble gas radionuclide ito air dose from beta radiation  
where D/J = = = noble gas beta dose to air due to stack and vent releases (mrad) factor converting time-integrated, ground-level concentration of noble gas radionuclide ito air dose from beta radiation  
-m3J &#xb5;C1 -sec atmospheric dispersion factor for a discharge via the stack (sec/m3) atmospheric dispersion factor for a vent (ground level or building wake) discharge (sec/m3). Specification 7.2.3.1 is satisfied by calculating the noble gas beta radiation dose to air at the location identified on Figure 3-2. At that location, 1260 meters NNW of the reactori, the reference atmospheric dispersion factors to be used are = = 2.8 x 10-7 4.3 x 10-s Beta radiation-to-air dose conversion  
-m 3 J &#xb5;C1 -sec atmospheric dispersion factor for a discharge via the stack (sec/m 3) atmospheric dispersion factor for a vent (ground level or building wake) discharge (sec/m 3). Specification 7.2.3.1 is satisfied by calculating the noble gas beta radiation dose to air at the location identified on Figure 3-2. At that location, 1260 meters NNW of the reactori, the reference atmospheric dispersion factors to be used are = = 2.8 x 10-7 4.3 x 10-s Beta radiation-to-air dose conversion  
: factors, for noble gas radionuclides are listed in Table 3-3. ;Due to limitations of the Midas&#xa9; software used to perform these calculations, a conservative higher calculated dose may be reported.
: factors, for noble gas radionuclides are listed in Table 3-3. ;Due to limitations of the Midas&#xa9; software used to perform these calculations, a conservative higher calculated dose may be reported.
When using Annualized Average Meteorological data, the Midas system uses known X/Q values from the 1 mile radius to extrapolate XJQ values at the site boundary.
When using Annualized Average Meteorological data, the Midas system uses known X/Q values from the 1 mile radius to extrapolate XJQ values at the site boundary.
The resulting maximum site boundary X/Q value is greater than 4.3 x 1 O.s sec/m3 and is located on the site boundary toward the SSE. DAECODAM Page 30 of 280 Rev. 37 3.8 Dose Due to Iodine and Particulates in Gaseous Effluentsi Section 6.2.4 requires that 1-131, 1-133, H-3, and radioactive material in particulate form having half-lives greater than 8 days in gaseous effluents released to the area offsite cause no more than 7.5 mrem to any organ of a member of the public during a calendar quarter and no more than 15 mrem during any calendar year. Section 7.2.4 requires an assessment at least once every month to verify that the cumulative dose commitment does not exceed either limit of Section 6.2.4. Airborne releases are discharged either via the offgas stack as an elevated release or via building vents and treated as a ground-level, building wake, or split wake release.
The resulting maximum site boundary X/Q value is greater than 4.3 x 1 O.s sec/m 3 and is located on the site boundary toward the SSE. DAECODAM Page 30 of 280 Rev. 37 3.8 Dose Due to Iodine and Particulates in Gaseous Effluentsi Section 6.2.4 requires that 1-131, 1-133, H-3, and radioactive material in particulate form having half-lives greater than 8 days in gaseous effluents released to the area offsite cause no more than 7.5 mrem to any organ of a member of the public during a calendar quarter and no more than 15 mrem during any calendar year. Section 7.2.4 requires an assessment at least once every month to verify that the cumulative dose commitment does not exceed either limit of Section 6.2.4. Airborne releases are discharged either via the offgas stack as an elevated release or via building vents and treated as a ground-level, building wake, or split wake release. Radionuclides mentioned above in airborne effluents that are measured by the sampling and analysis schedule in Table 7.2-2 are included in the release term used to calculate doses. Section 3.2 describes the quantification of these radionuclides other than noble gases. A person may be exposed directly to an airborne concentration of radioactive material discharged in effluent and indirectly via pathways involving deposition of radioactive material onto the ground. Dose estimates account for the separate exposure pathways.
Radionuclides mentioned above in airborne effluents that are measured by the sampling and analysis schedule in Table 7.2-2 are included in the release term used to calculate doses. Section 3.2 describes the quantification of these radionuclides other than noble gases. A person may be exposed directly to an airborne concentration of radioactive material discharged in effluent and indirectly via pathways involving deposition of radioactive material onto the ground. Dose estimates account for the separate exposure pathways.
The dose commitment to a person offsite associated with a gaseous release, Qik* of radioactive material other than noble gas is calculated with the appropriate one(s) of the following equations for a stack release: for a vent release: iThe dose to any organ of a person arising from radioactive iodine-131, iodine-133, tritium, and radioactive material in particulate form having half-lives greater than 8 days. Noble gases not considered.
The dose commitment to a person offsite associated with a gaseous release, Qik* of radioactive material other than noble gas is calculated with the appropriate one(s) of the following equations for a stack release:
DAECODAM Page 31 of 280 Rev. 37 where Danske = TAanie = TGanie = the dose commitment (mrem) to organ n of a person in age group a via exposure pathway e due to radionuclides identified in analysis k of a stack release where the analysis is required by Table 7.2-2. the dose commitment via pathway e from a vent release (mrem) factor converting airborne concentration of radionuclide i to dose commitment to organ n of a person in any group a where exposure is directly to airborne material via exposure pathway e. l mrem J (Ci sec)/ m 3 factor converting ground deposition of radionuclide i to dose commitment organ n of a person in age group a where exposure is directly or indirectly to radioactive material that has been deposited on the ground via exposure ( mrem) pathway e. Ci 1 m 2 quantity of radionuclide i released in a given effluent stream based on analysis k (Ci) relative deposition factor, i.e., factor converting airborne effluent discharge from stack or vent respectively, to a real deposition on land (m-2). The analysis index k may represent either an analysis of a grab sample, a weekly composite analysis, a monthly composite analysis, or a quarterly composite analysis.
for a vent release:
iThe dose to any organ of a person arising from radioactive iodine-131, iodine-133,  
: tritium, and radioactive material in particulate form having half-lives greater than 8 days. Noble gases not considered.
DAECODAM Page 31 of 280 Rev. 37 where Danske = TAanie = TGanie = the dose commitment (mrem) to organ n of a person in age group a via exposure pathway e due to radionuclides identified in analysis k of a stack release where the analysis is required by Table 7.2-2. the dose commitment via pathway e from a vent release (mrem) factor converting airborne concentration of radionuclide i to dose commitment to organ n of a person in any group a where exposure is directly to airborne material via exposure pathway e. l mrem J (Ci sec)/ m3 factor converting ground deposition of radionuclide i to dose commitment organ n of a person in age group a where exposure is directly or indirectly to radioactive material that has been deposited on the ground via exposure  
( mrem) pathway e. Ci 1 m2 quantity of radionuclide i released in a given effluent stream based on analysis k (Ci) relative deposition factor, i.e., factor converting airborne effluent discharge from stack or vent respectively, to a real deposition on land (m-2). The analysis index k may represent either an analysis of a grab sample, a weekly composite  
: analysis, a monthly composite  
: analysis, or a quarterly composite analysis.
Since tritium in water vapor is absorbed directly by vegetation, the tritium concentration in growing vegetation is proportional to the airborne concentration rather than to relative deposition as in the case of particulates.
Since tritium in water vapor is absorbed directly by vegetation, the tritium concentration in growing vegetation is proportional to the airborne concentration rather than to relative deposition as in the case of particulates.
Thus the dose commitment from airborne tritium via vegetation (fruit and vegetables),
Thus the dose commitment from airborne tritium via vegetation (fruit and vegetables), air-grass-cow-milk, or air-grass-cow-meat pathways is calculated with the appropriate one(s) of the equations:
air-grass-cow-milk, or air-grass-cow-meat pathways is calculated with the appropriate one(s) of the equations:
for a stack release Danse for a vent release DAEC ODAM Page 32 of 280 Rev. 37 Dame = lXJ " " Q TA Q v ikv 1.rl.anie The dose commitment accumulated by a person offsite is computed at least every 30 days to satisfy Section 7.2.4.1 but may be calculated as analytical results of effluent measurements, performed as specified in Table 7.2-2, become available.
for a stack release Danse for a vent release DAEC ODAM Page 32 of 280 Rev. 37 Dame = lXJ " " Q TA Q v ikv 1.rl.anie The dose commitment accumulated by a person offsite is computed at least every 30 days to satisfy Section 7.2.4.1 but may be calculated as analytical results of effluent measurements, performed as specified in Table 7.2-2, become available.
The dose accumulated as a result of stack discharge is computed with Dans = L Danse and the dose accumulated as a result of vent discharge is computed with Danv = L Danve Doses committed during the same time period due to discharges from the stack and vents are additive, thus where Dan= + ", Dan Dans L...J Dam> v the dose commitment accumulated during the quarter to date as a result of all measured radioactive gaseous discharges except noble gases to any organ n, including total body, of a person offsite in age group a (mrem). When the dose to a person from iodine and particulates discharged in gaseous effluents is calculated as required by Section 7.2.4, appropriate environmental pathways (from among those for which dose transfer factors are provided in Appendix A) will be evaluated.
The dose accumulated as a result of stack discharge is computed with Dans = L Danse and the dose accumulated as a result of vent discharge is computed with Danv = L Danve Doses committed during the same time period due to discharges from the stack and vents are additive, thus where Dan= + ", Dan Dans L...J Dam> v the dose commitment accumulated during the quarter to date as a result of all measured radioactive gaseous discharges except noble gases to any organ n, including total body, of a person offsite in age group a (mrem). When the dose to a person from iodine and particulates discharged in gaseous effluents is calculated as required by Section 7.2.4, appropriate environmental pathways (from among those for which dose transfer factors are provided in Appendix A) will be evaluated.
Line 236: Line 172:
Seasonal appropriateness of pathways is considered.
Seasonal appropriateness of pathways is considered.
The air-grass (fresh or man pathway is evaluated**
The air-grass (fresh or man pathway is evaluated**
where a cow is located, 2650 meters WNW of DAEC, reference atmospheric deposition factors are: DAECODAM Page 33 of 280 Rev. 37 lDJ =2.l*10-9m-2 lDJ =4.28*10-9m-2 Q s Q v **This receptor is historical in nature. See the current land use census to verify this point as the most conservative receptor location for the pathway.
where a cow is located, 2650 meters WNW of DAEC, reference atmospheric deposition factors are: DAECODAM Page 33 of 280 Rev. 37 l DJ =2.l*10-9 m-2 lDJ =4.28*10-9 m-2 Q s Q v **This receptor is historical in nature. See the current land use census to verify this point as the most conservative receptor location for the pathway. 3.8.1 Alternate Method of Evaluating Doses Due to Iodine and Particulates in Gaseous Effluents Alternatively, the dose commitment to a maximally exposed, hypothetical individual may be calculated by the equation where: D;nf-111y  
3.8.1 Alternate Method of Evaluating Doses Due to Iodine and Particulates in Gaseous Effluents Alternatively, the dose commitment to a maximally  
: exposed, hypothetical individual may be calculated by the equation where: D;nf-111y  
= Dinf-thy=
= Dinf-thy=
* L[Q;*TG;nj-thy-I-13J*(D!Q)].
* L[Q;*TG;nj-thy-I-13J*(D!Q)].
1 =
1 =
* L[Q;*TG;nf-thy-J-J31*(D!Q)l, 1 the dose commitment accumulated during the quarter to date to a hypothetical infant's thyroid as a result of the releases of 1-131 (mrem) the measured quantity of 1-131 released in a given effluent stream, stack or vent (Ci) TG;nf-thy-1-131 = the dose transfer factor for the infant thyroid from the cow-milk pathway for 1-131 measured in the effluent stream 1 0.8 = ( mrem) Cilm2 a factor of conservatism which accounts for the dose contribution for releases of particulate radioactive material other than 1-131 When the maximum organ dose is evaluated by using the equation above, analyses of other organ doses via other pathways are not needed to demonstrate compliance within the dose limits of Section 6.2.4. The rationale for only evaluating the dose contribution of 1-131 is derived from an evaluation of the radioactive material releases and the environmental pathways.
* L[Q;*TG;nf-thy-J-J31*(D!Q)l, 1 the dose commitment accumulated during the quarter to date to a hypothetical infant's thyroid as a result of the releases of 1-131 (mrem) the measured quantity of 1-131 released in a given effluent stream, stack or vent (Ci) TG;nf-thy-1-131 = the dose transfer factor for the infant thyroid from the cow-milk pathway for 1-131 measured in the effluent stream 1 0.8 = ( mrem) Cilm 2 a factor of conservatism which accounts for the dose contribution for releases of particulate radioactive material other than 1-131 When the maximum organ dose is evaluated by using the equation above, analyses of other organ doses via other pathways are not needed to demonstrate compliance within the dose limits of Section 6.2.4. The rationale for only evaluating the dose contribution of 1-131 is derived from an evaluation of the radioactive material releases and the environmental pathways.
The air-grass-cow-milk-man pathway is by far the controlling pathway and the infant's thyroid is the limiting organ. This pathway typically contributes greater than 90% of the total calculated dose to the infant's thyroid and 1-131 contributes essentially all of the dose (-95%). Therefore, it is possible to demonstrate compliance with the dose limits of Section 6.2.4 by the conservative calculation method presented above. DAEC ODAM Page 34 of 280 Rev. 37 3.9 Dose to a Person from Noble Gases Section 7.3.1 requires the calculation of the dose or dose commitment to a person offsite exposed to 12 consecutive months of radioactive liquid and gaseous effluents from the Station.
The air-grass-cow-milk-man pathway is by far the controlling pathway and the infant's thyroid is the limiting organ. This pathway typically contributes greater than 90% of the total calculated dose to the infant's thyroid and 1-131 contributes essentially all of the dose (-95%). Therefore, it is possible to demonstrate compliance with the dose limits of Section 6.2.4 by the conservative calculation method presented above. DAEC ODAM Page 34 of 280 Rev. 37 3.9 Dose to a Person from Noble Gases Section 7.3.1 requires the calculation of the dose or dose commitment to a person offsite exposed to 12 consecutive months of radioactive liquid and gaseous effluents from the Station. One component of personal dose is total body irradiation by gamma rays from noble gases. Another is irradiation of skin by beta and gamma radiation from noble gases. The methods of calculating these doses are presented in sections 3.9.1 and 3.9.2. The amount of radioactive noble gas discharged is determined in the manner described in section 3.2. 3.9.1 Gamma Dose to Total Body The gamma radiation dose to the whole body of a member of the public as a consequence of noble gas released from the Station is calculated with the equation:
One component of personal dose is total body irradiation by gamma rays from noble gases. Another is irradiation of skin by beta and gamma radiation from noble gases. The methods of calculating these doses are presented in sections 3.9.1 and 3.9.2. The amount of radioactive noble gas discharged is determined in the manner described in section 3.2. 3.9.1 Gamma Dose to Total Body The gamma radiation dose to the whole body of a member of the public as a consequence of noble gas released from the Station is calculated with the equation:
where: Dr= P v Y1 = noble gas gamma dose to total body (mrem) quantity of noble gas nuclide i released via stack or vent (Ci) factor converting unit noble gas nuclide i stack release to total body dose at ground level received from the overhead plume (mrem/Ci) factor converting time integrated, ground level concentration of noble gas nuclide i to total body dose from gamma radiation ( mrem ) Ci sec/ m 3 The dose to total body and organs other than skin from noble gases released from an elevated stack are calculated by a finite plume model.k It assumes decay of short-lived nuclides, a residential shielding factor of 0.7, an air dose-to-tissue dose conversion of 1.11, and that the dose to internal organs is equivalent to the tissue dose. Dose factors for exposure to noble gas plume gamma radiation, pr:, are computed by the MIDAS program. kDavid Slade, ed., Meteorology and Atomic Energy 1968, TID-24190, pp. 350-355. DAECODAM Page 35 of 280 Rev. 37 The dose from noble gases released from a vent (near ground level) or to skin from an elevated release is derived from a semi-infinite cloud model. Noble gas semi-infinite cloud gamma-to-total body dose factors, pr;', are listed in Appendix A under the plume pathway. When the total body and organ doses from noble gases are computed as required by Section 7.3.1, the nearby resident exposed to the maximal ground-level noble gas concentration (minimum X 1 Q) is selected as the receptor.
where: Dr= P v Y1 = noble gas gamma dose to total body (mrem) quantity of noble gas nuclide i released via stack or vent (Ci) factor converting unit noble gas nuclide i stack release to total body dose at ground level received from the overhead plume (mrem/Ci) factor converting time integrated, ground level concentration of noble gas nuclide i to total body dose from gamma radiation  
( mrem ) Ci sec/ m3 The dose to total body and organs other than skin from noble gases released from an elevated stack are calculated by a finite plume model.k It assumes decay of short-lived  
: nuclides, a residential shielding factor of 0.7, an air dose-to-tissue dose conversion of 1.11, and that the dose to internal organs is equivalent to the tissue dose. Dose factors for exposure to noble gas plume gamma radiation, pr:, are computed by the MIDAS program.
kDavid Slade, ed., Meteorology and Atomic Energy 1968, TID-24190, pp. 350-355.
DAECODAM Page 35 of 280 Rev. 37 The dose from noble gases released from a vent (near ground level) or to skin from an elevated release is derived from a semi-infinite cloud model. Noble gas semi-infinite cloud gamma-to-total body dose  
: factors, pr;', are listed in Appendix A under the plume pathway.
When the total body and organ doses from noble gases are computed as required by Section 7.3.1, the nearby resident exposed to the maximal ground-level noble gas concentration (minimum X 1 Q) is selected as the receptor.
Alternatively, the dose from noble gases may be computed at 1260 meters NNW of the reactor where the nearby resident who may be exposed to maximal ground-level noble gas concentrations (minimum X 1 Q) is selected as the receptor.
Alternatively, the dose from noble gases may be computed at 1260 meters NNW of the reactor where the nearby resident who may be exposed to maximal ground-level noble gas concentrations (minimum X 1 Q) is selected as the receptor.
In that case, values of p s p v . the dose factors Y; and Y; in Table 3-5 are employed.
In that case, values of p s p v . the dose factors Y; and Y; in Table 3-5 are employed.1 Reference meteorological  
1 Reference meteorological  
: d.
: d.
* f t d. h t th t I t* (XI Q) is 4. 3 x 1 o-6 sec/ m3 1spers1on or ven 1sc arges a a oca ion, "' 3.9.2 Dose to Skin The beta radiation dose to the skin of a member of the public due to beta radiation from noble gas released from the Station may be calculated with the equation where Dp = noble as dose to skin (mrem) sfJi = factor converting time integrated ground level concentration of noble gas to skin dose from beta radiation  
* f t d. h t th t I t* (XI Q) is 4. 3 x 1 o-6 sec/ m 3 1spers1on or ven 1sc arges a a oca ion, "' 3.9.2 Dose to Skin The beta radiation dose to the skin of a member of the public due to beta radiation from noble gas released from the Station may be calculated with the equation where Dp = noble as dose to skin (mrem) sfJi = factor converting time integrated ground level concentration of noble gas to skin dose from beta radiation ( mrem ) Ci sec/ m 3 Semi-infinite cloud noble gas beta-to-skin dose factors, Spi appear in Table 3-5. The total dose to the skin from noble gases is approximately equal to the beta radiation dose to the skin plus the gamma radiation dose to the total body. When the skin dose due to noble gas beta radiation is computed as required by Section 7.3.1, the receptor selected is the nearby resident exposed to maximal ground-level concentrations (maximum XI Q). Alternatively, the skin dose to a postulated receptor (resident) at 1260 meters NNW of the reactor may be calculated.
( mrem ) Ci sec/ m3 Semi-infinite cloud noble gas beta-to-skin dose factors, Spi appear in Table 3-5. The total dose to the skin from noble gases is approximately equal to the beta radiation dose to the skin plus the gamma radiation dose to the total body. When the skin dose due to noble gas beta radiation is computed as required by Section 7.3.1, the receptor selected is the nearby resident exposed to maximal ground-level concentrations (maximum XI Q). Alternatively, the skin dose to a postulated receptor (resident) at 1260 meters NNW of the reactor may be calculated.
1 Dose transfer factors in Table 3.5 and in Appendix A under the plume pathway are the same. DAECODAM Page 36 of 280 Rev. 37 Figure 3.1 Gaseous Radioactive Waste Flow Diagram r------------------
1Dose transfer factors in Table 3.5 and in Appendix A under the plume pathway are the same. DAECODAM Page 36 of 280 Rev. 37 Figure 3.1 Gaseous Radioactive Waste Flow Diagram r------------------
Offgas System t !JantondQ:n;ab!e I
Offgas System t !JantondQ:n;ab!e I
Condenser I I I I I i Otfgo:.ijJfitl Compre-:;.sor tS1l1 orrgas Condenser Calalytk Reton-blner ......._
Condenser I I I I I i Otfgo:.ijJfitl Compre-:;.sor tS1l1 orrgas Condenser Calalytk Reton-blner ......._ ceio1er 30mtn Le Delay Condenser Llne ' I Prefiler L. ___ !:aU!!_ ____ : L-i-------------------------------i-
ceio1er 30mtn Le Delay Condenser Llne ' I Prefiler L. ___ !:aU!!_ ____ : L-i-------------------------------i-
------I Arter FiltBr l j 7000: ,...FIA I 1.73 MinUtl} Holdup Piping I ' 0**************"'*"''***-*-**-*****.---...;..;;.=="'"'=:;..;...='------t-----, .. _,;
------I Arter FiltBr l j 7000: ,...FIA I 1.73 MinUtl} Holdup Piping I ' 0**************"'*"''***-*-**-*****.---...;..;;.=="'"'=:;..;...='------t-----, .. _,;
vact.1umPurrip 1 ____________
vact.1umPurrip 1 ____________
Line 271: Line 195:
! Refuel Floor Pool Exhaust--------<
! Refuel Floor Pool Exhaust--------<
r-*-------*-*--
r-*-------*-*--
r; ain Exhaust Plenum Potarrti.;i!ly Co11-1arrinei:te4 r' > 1V-EF-?1Af61C l300 CFM 32500CFM Exheios1 Plenum R3 Rf*H 176 Actident RIA-4175 RPcactor Bldg. Normal RM*7645 RM-7647 RM-7649 At:tident RM-i'M' RM-7E4& RM-764S Venn: rt. 7$25 CFH Adrnin Sida. HotL<ib$-
r; ain Exhaust Plenum Potarrti.;i!ly Co11-1arrinei:te4 r' > 1V-EF-?1Af61C l300 CFM 32500CFM Exheios1 Plenum R3 Rf*H 176 Actident RIA-4175 RPcactor Bldg. Normal RM*7645 RM-7647 RM-7649 At:tident RM-i'M' RM-7E4& RM-764S Venn: rt. 7$25 CFH Adrnin Sida. HotL<ib$-DAECODAM Page 37 of 280 Rev. 37 Figure 3-1 (Continued)
DAECODAM Page 37 of 280 Rev. 37 Figure 3-1 (Continued)
R1 Main Condenser SJAE Offgas Post-treatment Noble Gas Activity Monitor R2 Main Condenser SJAE Offgas Hydrogen Monitor R3 Offgas Stack Radiation Monitoring System R4 Reactor Building Exhaust Vent Monitoring System R5 Turbine Building Exhaust Vent Monitoring System R6 Main Condenser SJAE Offgas Pretreatment Noble Gas Activity Monitor R? LLRPSF Exhaust Vent Monitoring System DAEC ODAM Page 38 of 280 Rev. 37 Figure 3-2 Dose Calculation Sites Site Description Distance from Plant A Noble gas gamma air dose: 936 meters Northwest B Noble gas beta air dose: 1, 176 meters North c Goat milk: 2,470 meters East-Northeast I D Aquatic pathways:
R1 Main Condenser SJAE Offgas Post-treatment Noble Gas Activity Monitor R2 Main Condenser SJAE Offgas Hydrogen Monitor R3 Offgas Stack Radiation Monitoring System R4 Reactor Building Exhaust Vent Monitoring System R5 Turbine Building Exhaust Vent Monitoring System R6 Main Condenser SJAE Offgas Pretreatment Noble Gas Activity Monitor R? LLRPSF Exhaust Vent Monitoring System DAEC ODAM Page 38 of 280 Rev. 37 Figure 3-2 Dose Calculation Sites Site Description Distance from Plant A Noble gas gamma air dose: 936 meters Northwest B Noble gas beta air dose: 1, 176 meters North c Goat milk: 2,470 meters East-Northeast I D Aquatic pathways:
Cedar River I E Most Exposed resident:
Cedar River I E Most Exposed resident:
805 meters West I DAEC ODAM Page 39 of 280 Rev. 37 Parameter Release Height Release Mode Effluent Source DAEC ODAM Off gas Stack 328 feet Elevated Waste Gas System Table 3-1 Atmospheric Gaseous Release Points at the Duane Arnold Energy Center RELEASE POINT Reactor Turbine Building Vent Building Vent 156 feet 90 feet Wake-split Wake-split Reactor Building Upper Turbine Gas Treatment Radwaste Building Buildi'rilg System Lower Turbine Building Page 40 of 280 Rev. 37 LLRPSF Building Vent 65 feet Wake-split LLRPSF Building.
805 meters West I DAEC ODAM Page 39 of 280 Rev. 37 Parameter Release Height Release Mode Effluent Source DAEC ODAM Off gas Stack 328 feet Elevated Waste Gas System Table 3-1 Atmospheric Gaseous Release Points at the Duane Arnold Energy Center RELEASE POINT Reactor Turbine Building Vent Building Vent 156 feet 90 feet Wake-split Wake-split Reactor Building Upper Turbine Gas Treatment Radwaste Building Buildi'rilg System Lower Turbine Building Page 40 of 280 Rev. 37 LLRPSF Building Vent 65 feet Wake-split LLRPSF Building.
and Storage Facility c d Rel Nuclide Kr-83m Kr-85m Kr-85 Kr-87 Kr-88 Kr-89 Xe-131 m Xe-133m Xe-133 Xe-135m Xe-135 Xe-137 Xe-138 TABLE NOTATION Table 3-2 f Radioactive Noble Gases in G STACK RELEASE (Ci/vr)"
and Storage Facility c d Rel Nuclide Kr-83m Kr-85m Kr-85 Kr-87 Kr-88 Kr-89 Xe-131 m Xe-133m Xe-133 Xe-135m Xe-135 Xe-137 Xe-138 TABLE NOTATION Table 3-2 f Radioactive Noble Gases in G STACK RELEASE (Ci/vr)" Fractionb 4.90E+01 2.53E-03 2.34E+03 1.21E-01 1.40E+02 7.23E-03 1.56E+02 8.06E-03 1.65E+03 8.52E-02 6.40E+02 3.31E-02 4.80E+01 2.48E-03 3.50E+01 1.81 E-03 1.24E+04 6.41 E-01 1.80E+01 9.30E-04 5.10E+02 2.63E-02 7.80E+02 4.03E-02 5.90E+02 3.05E-02 19356 1.0 Effl t f D Arnold E Cent PLANT VENTS RELEASE (Ci/yr)" Fractionb 0 0 7.40E+01 1.98E-02 0 0 1.36E+02 3.64E-02 2.36E+02 6.32E-02 0 0 0 0 0 0 3.92E+02 1.05E-01 7.42E+02 1.99E-01 7.43E+02 1.99E-01 0 0 1.41E+03 3.78E-01 3733. 1.0 a Releases computed by BWR-GALE for DAEC Base Case gaseous radwaste treatment.
Fractionb 4.90E+01 2.53E-03 2.34E+03 1.21E-01 1.40E+02 7.23E-03 1.56E+02 8.06E-03 1.65E+03 8.52E-02 6.40E+02 3.31E-02 4.80E+01 2.48E-03 3.50E+01 1.81 E-03 1.24E+04 6.41 E-01 1.80E+01 9.30E-04 5.10E+02 2.63E-02 7.80E+02 4.03E-02 5.90E+02 3.05E-02 19356 1.0 Effl t f D Arnold E Cent PLANT VENTS RELEASE (Ci/yr)"
Fractionb 0 0 7.40E+01 1.98E-02 0 0 1.36E+02 3.64E-02 2.36E+02 6.32E-02 0 0 0 0 0 0 3.92E+02 1.05E-01 7.42E+02 1.99E-01 7.43E+02 1.99E-01 0 0 1.41E+03 3.78E-01 3733. 1.0 a Releases computed by BWR-GALE for DAEC Base Case gaseous radwaste treatment.
Computed releases are included only to show the basis of the radionuclide distribution.
Computed releases are included only to show the basis of the radionuclide distribution.
b This is the calculated distribution of radionuclides in gaseous effluents in each release pathway.
b This is the calculated distribution of radionuclides in gaseous effluents in each release pathway. To estimate radionuclide concentrations in a sample in which only the total activity concentration has been measured, multiply the total activity concentration by the fraction of respective radionuclides listed above. DAEC ODAM Page 41 of 280 Rev. 37 Table 3-3 Transfer Factors for Maximum Offsite Air Dose Radionuclide Air Dose Transfer Factors a b Ar; A " Y; A/3; (  
To estimate radionuclide concentrations in a sample in which only the total activity concentration has been measured, multiply the total activity concentration by the fraction of respective radionuclides listed above. DAEC ODAM Page 41 of 280 Rev. 37 Table 3-3 Transfer Factors for Maximum Offsite Air Dose Radionuclide Air Dose Transfer Factors a b Ar; A " Y; A/3; (  
&#xb5;Ci ( mrad ) &#xb5;Ci sec/ m 3 ( mrad ) &#xb5;Ci sec/ m 3 Kr-83m 4.3E-14 6.1E-7 9.1 E-6 Kr-85m 6.0E-12 3.9E-5 6.2E-5 Kr-85 8.4E-14 5.4E-7 6.2E-5 Kr-87 2.3E-11 2.0E-4 3.3E-4 Kr-88 6.4E-11 4.8E-4 9.3E-5 Kr-89 3.0E-11 5.5E-4 3.4E-4 Kr-90 ---5.2E-4 2.5E-4 Xe-131m 1.8E-12 4.9E-6 3.5E-5 Xe-133m 1.4E-12 1.0E-5 4.7E-5 Xe-133 1.5E-12 1.1 E-5 3.3E-5 Xe-135m 1.1 E-11 1.1E-4 2.3E-5 Xe-135 9.5E-12 6.1E-5 7.8E-5 Xe-137 2.6E-12 4.8E-5 4.0E-4 Xe-138 3.6E-11 2.9E-4 1.5E-4 Ar-41 4.4E-11 2.9E-4 1.0E-4 TABLE NOTATIONS a b An NRG code, RABFIN, modified for sector width averaged meteorology, was used to calculate the air dose transfer factors, Ar: for a stack discharge.
&#xb5;Ci ( mrad ) &#xb5;Ci sec/ m3 ( mrad ) &#xb5;Ci sec/ m3 Kr-83m 4.3E-14 6.1E-7 9.1 E-6 Kr-85m 6.0E-12 3.9E-5 6.2E-5 Kr-85 8.4E-14 5.4E-7 6.2E-5 Kr-87 2.3E-11 2.0E-4 3.3E-4 Kr-88 6.4E-11 4.8E-4 9.3E-5 Kr-89 3.0E-11 5.5E-4 3.4E-4 Kr-90 ---5.2E-4 2.5E-4 Xe-131m 1.8E-12 4.9E-6 3.5E-5 Xe-133m 1.4E-12 1.0E-5 4.7E-5 Xe-133 1.5E-12 1.1 E-5 3.3E-5 Xe-135m 1.1 E-11 1.1E-4 2.3E-5 Xe-135 9.5E-12 6.1E-5 7.8E-5 Xe-137 2.6E-12 4.8E-5 4.0E-4 Xe-138 3.6E-11 2.9E-4 1.5E-4 Ar-41 4.4E-11 2.9E-4 1.0E-4 TABLE NOTATIONS a b An NRG code, RABFIN, modified for sector width averaged meteorology, was used to calculate the air dose transfer  
They represent air dose at ground level 1260 meters NNW of the station from a unit release of each radionuclide i from the stack and dispersed by reference meteorology at the DAEC. Dose transfer factors for vent discharges, A Y ;* and AfJ; are equivalent to factors in Regulatory Guide 1.109, Table B-1, g-air and b-air, expressed in different units. DAECODAM Page 42 of 280 Rev. 37 b Radionuclide Kr-83m Kr-85m Kr-85 Kr-87 Kr-88 Kr-89 Kr-90 Xe-131m Xe-133m Xe-133 Xe-135m Xe-135 Xe-137 Xe-138 Ar-41 Table 3-4 Transfer Factors for Dose Equivalent Rate to A Person Offsite Due to Radioactive Noble Gases Dose Transfer Factors a, b, c DFt [ mrem ] (&#xb5;Ci yr) I sec [ mrem l (&#xb5;Ci yr)/m 3 6.27E-9 7.56E-2 1.81E-4 1.17E+3 2.51 E-6 1.61 E+1 6.97E-4 5.92E+3 1.91E-3 1.47E+4 9.14E-4 1.66E+4 ---1.56E+4 4.83E-5 9.15E+1 3.61 E-5 2.51E+2 4.09E-5 2.94E+2 3.39E-4 3.12E+3 2.84E-4 1.81E+3 7.90E-5 1.42E+3 1.08E-3 8.83E+3 1.32E-3 8.84E+3 TABLE NOTATIONS a Receptor located 1260 meters NNW of Station b Based on reference meteorology at DAEC d Sp; [ mrem ] (&#xb5;Ci yr)/m 3 0 1.46E+3 9.73E+3 9.73E+3 2.37E+3 1.01E+4 7.29E+3 4.76E+2 9.94E+2 3.06E+2 7.11E+2 1.86E+3 1.22E+4 4.13E+3 2.69E+3 c Factors DFf computed by computer code RABFIN, modified for sector width averaged meteorology d Factors from Regulatory Guide 1.109, revision 1, Table B-1, column 5 DAECODAM Page 43 of 280 Rev. 37 Radionuclide Kr-83m Kr-85m Kr-85 Kr-87 Kr-88 Kr-89 Kr-90 Xe-131m Xe-133m Xe-133 Xe-135m Xe-135 Xe-137 Xe-138 Ar-41 Table 3-5 Transfer Factors for Dose Equivalent Rate to A Person Offsite Due to Radioactive Noble Gases Dose Transfer Factors a, b, c c, d Py; p v Y; [mzmJ [ mrem ] (Ci sec)/m 3 1.39E-10 1.68E-3 4.03E-6 2.60E+1 5.58E-8 3.58E-1 1.55E-5 1.31 E+2 4.25E-5 3.26E+2 2.03E-5 3.68E+2 ---3.46E+2 1.07E-6 2.03 8.05E-7 5.57 9.03E-7 6.52 7.49E-6 6.92E+1 6.31E-6 4.01E+1 1.75E-6 3.15E+1 2.39E-5 1.96E+2 2.92E-5 1.96E+2 s /3i [ mrem l (Cisec)/m 3 ---4.63E+1 4.25E+1 3.08E+2 7.51 E+1 3.20E+2 2.31E+2 1.51 E+1 3.15E+1 9.70 2.25E+1 5.89E+1 3.87E+2 1.31 E+2 8.52E+1 4.0 DOSE COMMITMENT FROM RELEASE OVER EXTENDED TIME TABLE NOTATIONS a Receptor located 1260 meters NNW of Station b Based on reference meteorology at DAEC s p v p s c Factors PY; and Y; already account for a 0.7 residential shielding factor. Factors Y; were computed by computer code RABFIN, modified for sector width averaged meteorology P v d Factors Y; and from Regulatory Guide 1.109, revision 1, Table B-1 DAEC ODAM Page 44 of 280 Rev. 37 d 4.0 DOSE COMMITMENT FROM RELEASE OVER EXTENDED TIME 4.1 Dose Assessment for 10 CFR Part 50, Appendix I a Sections 7.1.3, 7.2.3, and 7.2.4 require quarterly and annual assessments to demonstrate compliance with Appendix I dose limits. The assessment includes the following calculations of dose as described by equations for: 1. total body and maximally exposed organ doses due to liquid effluent via drinking water and eating fish from the River and from consuming food irrigated with river water as in paragraph 2.5. 2. total body and maximally exposed organ doses due to gaseous effluentsa other than noble gases as in paragraph 3.8. 3. doses to air offsite due to noble gas g as in paragraph 3.6 and due to noble gas as in paragraph 3.7. The dose calculations are based on liquid and gaseous effluents from the Station during each calendar quarter and for a calendar year, determined in accord with Tables 7 .1-2 and 7.2-2. Environmental concentrations depend on dispersion and dilution of the effluent.
: factors, Ar: for a stack discharge.
They represent air dose at ground level 1260 meters NNW of the station from a unit release of each radionuclide i from the stack and dispersed by reference meteorology at the DAEC. Dose transfer factors for vent discharges, A Y ;* and AfJ; are equivalent to factors in Regulatory Guide 1.109, Table B-1, g-air and b-air, expressed in different units. DAECODAM Page 42 of 280 Rev. 37 b Radionuclide Kr-83m Kr-85m Kr-85 Kr-87 Kr-88 Kr-89 Kr-90 Xe-131m Xe-133m Xe-133 Xe-135m Xe-135 Xe-137 Xe-138 Ar-41 Table 3-4 Transfer Factors for Dose Equivalent Rate to A Person Offsite Due to Radioactive Noble Gases Dose Transfer Factors a, b, c DFt [ mrem ] (&#xb5;Ci yr) I sec [ mrem l (&#xb5;Ci yr)/m3 6.27E-9 7.56E-2 1.81E-4 1.17E+3 2.51 E-6 1.61 E+1 6.97E-4 5.92E+3 1.91E-3 1.47E+4 9.14E-4 1.66E+4 ---1.56E+4 4.83E-5 9.15E+1 3.61 E-5 2.51E+2 4.09E-5 2.94E+2 3.39E-4 3.12E+3 2.84E-4 1.81E+3 7.90E-5 1.42E+3 1.08E-3 8.83E+3 1.32E-3 8.84E+3 TABLE NOTATIONS a Receptor located 1260 meters NNW of Station b Based on reference meteorology at DAEC d Sp; [ mrem ] (&#xb5;Ci yr)/m3 0 1.46E+3 9.73E+3 9.73E+3 2.37E+3 1.01E+4 7.29E+3 4.76E+2 9.94E+2 3.06E+2 7.11E+2 1.86E+3 1.22E+4 4.13E+3 2.69E+3 c Factors DFf computed by computer code RABFIN, modified for sector width averaged meteorology d Factors from Regulatory Guide 1.109, revision 1, Table B-1, column 5 DAECODAM Page 43 of 280 Rev. 37 Radionuclide Kr-83m Kr-85m Kr-85 Kr-87 Kr-88 Kr-89 Kr-90 Xe-131m Xe-133m Xe-133 Xe-135m Xe-135 Xe-137 Xe-138 Ar-41 Table 3-5 Transfer Factors for Dose Equivalent Rate to A Person Offsite Due to Radioactive Noble Gases Dose Transfer Factors a, b, c c, d Py; p v Y; [mzmJ [ mrem ] (Ci sec)/m3 1.39E-10 1.68E-3 4.03E-6 2.60E+1 5.58E-8 3.58E-1 1.55E-5 1.31 E+2 4.25E-5 3.26E+2 2.03E-5 3.68E+2 ---3.46E+2 1.07E-6 2.03 8.05E-7 5.57 9.03E-7 6.52 7.49E-6 6.92E+1 6.31E-6 4.01E+1 1.75E-6 3.15E+1 2.39E-5 1.96E+2 2.92E-5 1.96E+2 s /3i [ mrem l (Cisec)/m 3 ---4.63E+1 4.25E+1 3.08E+2 7.51 E+1 3.20E+2 2.31E+2 1.51 E+1 3.15E+1 9.70 2.25E+1 5.89E+1 3.87E+2 1.31 E+2 8.52E+1 4.0 DOSE COMMITMENT FROM RELEASE OVER EXTENDED TIME TABLE NOTATIONS a Receptor located 1260 meters NNW of Station b Based on reference meteorology at DAEC s p v p s c Factors PY; and Y; already account for a 0.7 residential shielding factor. Factors Y; were computed by computer code RABFIN, modified for sector width averaged meteorology P v d Factors Y; and from Regulatory Guide 1.109, revision 1, Table B-1 DAEC ODAM Page 44 of 280 Rev. 37 d 4.0 DOSE COMMITMENT FROM RELEASE OVER EXTENDED TIME 4.1 Dose Assessment for 10 CFR Part 50, Appendix I a Sections 7.1.3, 7.2.3, and 7.2.4 require quarterly and annual assessments to demonstrate compliance with Appendix I dose limits. The assessment includes the following calculations of dose as described by equations for: 1. total body and maximally exposed organ doses due to liquid effluent via drinking water and eating fish from the River and from consuming food irrigated with river water as in paragraph 2.5. 2. total body and maximally exposed organ doses due to gaseous effluentsa other than noble gases as in paragraph 3.8. 3. doses to air offsite due to noble gas g as in paragraph 3.6 and due to noble gas as in paragraph 3.7. The dose calculations are based on liquid and gaseous effluents from the Station during each calendar quarter and for a calendar year, determined in accord with Tables 7 .1-2 and 7.2-2. Environmental concentrations depend on dispersion and dilution of the effluent.
For aqueous effluents over extended time, the aquatic concentration is estimated according to section 2.2. Atmospheric dispersion and deposition factors used to estimate the dose commitment due to gaseous effluents are ordinarily derived from reference meteorological data. Otherwise, quarterly averaged or annual averaged meteorological conditions concurrent with the gaseous release being evaluated will be used to estimate atmospheric dispersion and deposition.
For aqueous effluents over extended time, the aquatic concentration is estimated according to section 2.2. Atmospheric dispersion and deposition factors used to estimate the dose commitment due to gaseous effluents are ordinarily derived from reference meteorological data. Otherwise, quarterly averaged or annual averaged meteorological conditions concurrent with the gaseous release being evaluated will be used to estimate atmospheric dispersion and deposition.
The receptor of the dose is described such that the dose to any resident near the Station is unlikely to be underestimated.
The receptor of the dose is described such that the dose to any resident near the Station is unlikely to be underestimated.
That is, the receptor is selected on the basis of the combination of applicable pathways of exposure to gaseous effluent identified in the annual land use census and maximum ground level X 1 Q at the residence.
That is, the receptor is selected on the basis of the combination of applicable pathways of exposure to gaseous effluent identified in the annual land use census and maximum ground level X 1 Q at the residence.
Conditions (i.e., location, X 1 Q, and/or pathways) more conservative (i.e., expected to yield higher calculated doses) than appropriate for the maximally exposed individual may be assumed in the dose assessment.
Conditions (i.e., location, X 1 Q, and/or pathways) more conservative (i.e., expected to yield higher calculated doses) than appropriate for the maximally exposed individual may be assumed in the dose assessment.
Radioactive iodine-131, iodine-133,  
Radioactive iodine-131, iodine-133, tritium, and radioactive material in particulate form having half-lives greater than 8 days. DAECODAM Page 45 of 280 Rev. 37 Seasonal appropriateness of exposure pathways may be considered.
: tritium, and radioactive material in particulate form having half-lives greater than 8 days. DAECODAM Page 45 of 280 Rev. 37 Seasonal appropriateness of exposure pathways may be considered.
Exposure by eating fresh vegetation or drinking milk from cows or goats fed fresh forage is an inappropriate assumption during the first or fourth calendar quarter; rather consumption of stored vegetation and stored forage is assumed during those quarters.
Exposure by eating fresh vegetation or drinking milk from cows or goats fed fresh forage is an inappropriate assumption during the first or fourth calendar quarter; rather consumption of stored vegetation and stored forage is assumed during those quarters.
Otherwise, during the second and third calendar  
Otherwise, during the second and third calendar quarters, exposure by eating fresh vegetation and/or drinking milk from cows or goats fed fresh forage is assumed where those pathways exist. Similarly, the liquid effluent-river-fish-man pathway is not assumed during the winter quarter. Factors converting stack-released noble gas to gamma radiation dose from the overhead plume are calculated on the basis of reference meteorological data for the receptor location or alternatively, by the MIDAS program for a residential location offsite where maximum X 1 Q at ground level occurs. Other environmental pathway-to-dose transfer factors used in the dose calculations are provided in Appendix A. 4.2 Dose Assessment for 40 CFR Part 190 and 10 CFR 72.104 The regulations governing the maximum allowable dose or dose commitment to a member of the public from all uranium fuel cycle-sources of radiation and radioactive material in the environment is stated in 40 CFR Part 190 and 1 O CFR 72.104. It requires that the dose or dose commitment to a member of the public from all sources not exceed 25 mrem/yr to the whole body or 25 mrem/yr to any organ or 75 mrem/yr to the thyroid. Section 7.3.1 requires calculation of the dose at least once every year to assess compliance with the regulation.
: quarters, exposure by eating fresh vegetation and/or drinking milk from cows or goats fed fresh forage is assumed where those pathways exist. Similarly, the liquid effluent-river-fish-man pathway is not assumed during the winter quarter.
Factors converting stack-released noble gas to gamma radiation dose from the overhead plume are calculated on the basis of reference meteorological data for the receptor location or alternatively, by the MIDAS program for a residential location offsite where maximum X 1 Q at ground level occurs. Other environmental pathway-to-dose transfer factors used in the dose calculations are provided in Appendix A. 4.2 Dose Assessment for 40 CFR Part 190 and 10 CFR 72.104 The regulations governing the maximum allowable dose or dose commitment to a member of the public from all uranium fuel cycle-sources of radiation and radioactive material in the environment is stated in 40 CFR Part 190 and 1 O CFR 72.104. It requires that the dose or dose commitment to a member of the public from all sources not exceed 25 mrem/yr to the whole body or 25 mrem/yr to any organ or 75 mrem/yr to the thyroid.
Section 7.3.1 requires calculation of the dose at least once every year to assess compliance with the regulation.
More frequent calculations may be performed if higher than normal releases are experienced (twice the design objective rates in a single quarter).
More frequent calculations may be performed if higher than normal releases are experienced (twice the design objective rates in a single quarter).
Fuel cycle sources or nuclear power reactors other than the Stationb itself do not measurably or significantly increase the radioactivity concentration in the vicinity of the Station; therefore, only radiation and radioactivity in the environment attributable to the Station itself are considered in the assessment of compliance with 40 CFR Part 190 and 10 CFR 72.104. Contributions to the dose due to liquid and gaseous effluent are calculated as described by the equations for: 1. total body and maximally exposed organ doses due to liquid effluent via drinking water, consuming irrigated food and from eating fish from the River as in paragraph 2.5 2. total body dose due to noble gas y as in paragraph 3.9.1 3. skin dose due to noble gas 13 as in paragraph 3.9.2 b The Station is defined as BOTH the Nuclear Reactor Facility and the Independent Spent Fuel Storage Installation (ISFSI).
Fuel cycle sources or nuclear power reactors other than the Stationb itself do not measurably or significantly increase the radioactivity concentration in the vicinity of the Station; therefore, only radiation and radioactivity in the environment attributable to the Station itself are considered in the assessment of compliance with 40 CFR Part 190 and 10 CFR 72.104. Contributions to the dose due to liquid and gaseous effluent are calculated as described by the equations for: 1. total body and maximally exposed organ doses due to liquid effluent via drinking water, consuming irrigated food and from eating fish from the River as in paragraph 2.5 2. total body dose due to noble gas y as in paragraph 3.9.1 3. skin dose due to noble gas 13 as in paragraph 3.9.2 b The Station is defined as BOTH the Nuclear Reactor Facility and the Independent Spent Fuel Storage Installation (ISFSI). DAECODAM Page 46 of 280 Rev. 37   
DAECODAM Page 46 of 280 Rev. 37   
: 4. total body and maximally exposed organ doses due to gaseous effluentsc other than noble gases as in Paragraph 3.8. Additionally, the contribution to total dose from direct radiation is assessed annually by using environmental TLDs. The doses are calculated on the basis of liquid and gaseous effluents from the Station during 12 consecutive months, determined in accord with Tables 7.1-2 and 7.2-2. For the purpose of the Annual Radiological Environmental Report, doses are based upon release during a calendar year. Aqueous radioactive material concentrations are estimated according to paragraph 2.2 on the basis of annual averaged stream flow. Annual averaged meteorological conditions concurrent with gaseous releases being evaluated are used to estimate atmospheric dispersion, deposition, and elevated plume gamma exposure.
: 4. total body and maximally exposed organ doses due to gaseous effluentsc other than noble gases as in Paragraph 3.8. Additionally, the contribution to total dose from direct radiation is assessed annually by using environmental TLDs. The doses are calculated on the basis of liquid and gaseous effluents from the Station during 12 consecutive months, determined in accord with Tables 7.1-2 and 7.2-2. For the purpose of the Annual Radiological Environmental Report, doses are based upon release during a calendar year. Aqueous radioactive material concentrations are estimated according to paragraph 2.2 on the basis of annual averaged stream flow. Annual averaged meteorological conditions concurrent with gaseous releases being evaluated are used to estimate atmospheric dispersion, deposition, and elevated plume gamma exposure.
The receptor of the dose is described such that the dose to any resident near the Station is not likely to be underestimated, although conditions more conservative than appropriate for the maximally exposed person may be assumed in the dose assessment.
The receptor of the dose is described such that the dose to any resident near the Station is not likely to be underestimated, although conditions more conservative than appropriate for the maximally exposed person may be assumed in the dose assessment.
Ordinarily, the receptor is selected on the basis of the applicable combination of existing pathways of exposure to gaseous effluent identified in the annual land use census and the maximum ground level XI Q at the residence.
Ordinarily, the receptor is selected on the basis of the applicable combination of existing pathways of exposure to gaseous effluent identified in the annual land use census and the maximum ground level XI Q at the residence.
When assessing compliance with 40 CFR 190, Radiological Environmental Monitoring Program results may be used to indicate actual radioactivity levels in the environment attributable to the DAEC. These measured levels may be used to supplement the evaluation of doses to members of the public for assessing compliance with 40 CFR 190. Factors converting stack-released noble gas to gamma radiation dose from the overhead plume are calculated on the basis of annual averaged meteorological data for the receptor location.
When assessing compliance with 40 CFR 190, Radiological Environmental Monitoring Program results may be used to indicate actual radioactivity levels in the environment attributable to the DAEC. These measured levels may be used to supplement the evaluation of doses to members of the public for assessing compliance with 40 CFR 190. Factors converting stack-released noble gas to gamma radiation dose from the overhead plume are calculated on the basis of annual averaged meteorological data for the receptor location.
Other environmental pathway-to-dose transfer factors are listed in Appendices A, B and C. c Radioactive iodine-131, iodine-133,  
Other environmental pathway-to-dose transfer factors are listed in Appendices A, B and C. c Radioactive iodine-131, iodine-133, tritium, and radioactive material in particulate form having half-lives greater than 8 days. DAECODAM Page 47 of 280 Rev. 37 5.0 ENVIRONMENTAL MONITORING PROGRAMS Section 5.0 of the ODAM provides a description of the Radiological Environmental Monitoring Program (REMP) and the Ground Water Protection Program (GWPP). This section also contains descriptions of the Environmental Sampling Program Station Locations.
: tritium, and radioactive material in particulate form having half-lives greater than 8 days. DAECODAM Page 47 of 280 Rev. 37 5.0 ENVIRONMENTAL MONITORING PROGRAMS Section 5.0 of the ODAM provides a description of the Radiological Environmental Monitoring Program (REMP) and the Ground Water Protection Program (GWPP). This section also contains descriptions of the Environmental Sampling Program Station Locations.
5.1 Radiological Environmental Monitoring Program A program shall be provided to monitor the radiation and radionuclides in the environs of the station. The program shall provide: (1) representative measurements of radioactivity in the highest potential exposure pathways, (2) verification of the accuracy of the effluent monitoring program and modeling of environmental exposure pathways.
5.1 Radiological Environmental Monitoring Program A program shall be provided to monitor the radiation and radionuclides in the environs of the station.
The program shall: (1) be contained in the ODAM, (2) conform to the guidance of Appendix I to 10 CFR Part 50 and 10 CFR 72, (3) include the following: (a) Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the ODAM. (b) A Land Use Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the monitoring program are made if required by the results of this census. (c) Participation in an lnterlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring.
The program shall provide:  
5.2 Ground Water Protection Program (GWPP) A program shall be provided to prevent, detect and respond to inadvertent and radiological releases with the potential to reach ground water. The program shall provide: (1) for the prevention of inadvertent/unplanned radiological releases from plant systems, structures and components (SSCs) or during plant evolutions or work practices that represent an elevated risk of experiencing a release of licensed radiological material into the environment.
(1) representative measurements of radioactivity in the highest potential exposure  
: pathways, (2) verification of the accuracy of the effluent monitoring program and modeling of environmental exposure pathways.
The program shall: (1) be contained in the ODAM, (2) conform to the guidance of Appendix I to 10 CFR Part 50 and 10 CFR 72, (3) include the following:  
(a) Monitoring,  
: sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the ODAM. (b) A Land Use Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the monitoring program are made if required by the results of this census. (c) Participation in an lnterlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring.
5.2 Ground Water Protection Program (GWPP) A program shall be provided to prevent, detect and respond to inadvertent and radiological releases with the potential to reach ground water. The program shall provide:  
(1) for the prevention of inadvertent/unplanned radiological releases from plant systems, structures and components (SSCs) or during plant evolutions or work practices that represent an elevated risk of experiencing a release of licensed radiological material into the environment.
DAECODAM Page 48 of 280 Rev. 37 (2) aspects for monitoring, detecting and responding to unplanned/unmonitored releases of licensed radioactive material to the environment and a communications/notification plan that addresses internal notifications to management and communications/reporting to State and local stakeholders and regulators for specified events or conditions.
DAECODAM Page 48 of 280 Rev. 37 (2) aspects for monitoring, detecting and responding to unplanned/unmonitored releases of licensed radioactive material to the environment and a communications/notification plan that addresses internal notifications to management and communications/reporting to State and local stakeholders and regulators for specified events or conditions.
The program shall: (1) be contained in the site administrative control procedure ACP 1411.35,  
The program shall: (1) be contained in the site administrative control procedure ACP 1411.35, ''The DAEC Groundwater Protection Program".  
''The DAEC Groundwater Protection Program".  
(2) implement the Ground Water Protection Initiative Final Guidance Document, NEl-07 -07[Final].
(2) implement the Ground Water Protection Initiative Final Guidance  
5.3 Sampling Station Locations ODAM Table 5-1 "ENVIRONMENTAL SAMPLE STATIONS" is a list of locations where samples may be collected and does not represent a list of required samples. Environmental monitoring locations are shown on Figures 5-1 and 5-2. DAEC may conduct additional environmental monitoring exclusive of the requirements of Specifications 6.3.2 and ACP 1411.35. DAEC ODAM Page 49 of 280 Rev. 37 t N I 57 DAEC ODAM Figure 5-1 Environmental Monitoring Programs Sampling Near the Duane Arnold Energy Center .. ----*91 -15 I 32 I I I I I 31 I l I I 30 I I I I I 29 I I l 2s I L-----86 GATE 2000feet 55 113 107 DAEC 130 106 133 122 131 73 114 111 Page 50 of 280 107* 68 132 69 N 94 173 169 168 Rev. 37 DAECODAM Figure 5-2 Radiological Environmental Monitoring Program Sampling Stations Outside 0.5 Miles from DAEC __ .... ,..... ..... :;:;:,  
: Document, NEl-07 -07[Final].
5.3 Sampling Station Locations ODAM Table 5-1 "ENVIRONMENTAL SAMPLE STATIONS" is a list of locations where samples may be collected and does not represent a list of required samples.
Environmental monitoring locations are shown on Figures 5-1 and 5-2. DAEC may conduct additional environmental monitoring exclusive of the requirements of Specifications 6.3.2 and ACP 1411.35.
DAEC ODAM Page 49 of 280 Rev. 37 t N I 57 DAEC ODAM Figure 5-1 Environmental Monitoring Programs Sampling Near the Duane Arnold Energy Center .. ----*91 -15 I 32 I I I I I 31 I l I I 30 I I I I I 29 I I l 2s I L-----86 GATE 2000feet 55 113 107 DAEC 130 106 133 122 131 73 114 111 Page 50 of 280 107* 68 132 69 N 94 173 169 168 Rev. 37 DAECODAM Figure 5-2 Radiological Environmental Monitoring Program Sampling Stations Outside 0.5 Miles from DAEC __ .... ,..... ..... :;:;:,  
----*---*-*****--**-*** *--110 ATKINS *10 99 10 MILE RADIUS CENTER POINT eos 109 05a' PALO* 05 37 TODDVILLE 38 *11 39 Page 51 of 280 ALBURNETT 13* Rev. 37 Station Program Number 1 REMP 2 REMP 3 REMP 4 5 REMP 5a REMP 6 REMP 7 REMP 8 REMP 9 10 REMP 11 REMP 12 13 REMP 14 15 REMP 15a GWPP 16 REMP 16a GWPP 17 REMP 18 REMP DAECODAM Table 5-1 ENVIRONMENTAL SAMPLE STATIONS Station Location and Sample Type Location:
----*---*-*****--**-*** *--110 ATKINS *10 99 10 MILE RADIUS CENTER POINT eos 109 05a' PALO* 05 37 TODDVILLE 38 *11 39 Page 51 of 280 ALBURNETT 13* Rev. 37 Station Program Number 1 REMP 2 REMP 3 REMP 4 5 REMP 5a REMP 6 REMP 7 REMP 8 REMP 9 10 REMP 11 REMP 12 13 REMP 14 15 REMP 15a GWPP 16 REMP 16a GWPP 17 REMP 18 REMP DAECODAM Table 5-1 ENVIRONMENTAL SAMPLE STATIONS Station Location and Sample Type Location:
Cedar Rapids, 20,800 meters SE Type: TLD Control Airborne Particulate and Iodine Control -Not Currently Active Location:
Cedar Rapids, 20,800 meters SE Type: TLD Control Airborne Particulate and Iodine Control -Not Currently Active Location:
Marion, 16,900 meters ESE Type: TLD Control Airborne Particulate and Iodine Control -Not Currently Active Location:  
Marion, 16,900 meters ESE Type: TLD Control Airborne Particulate and Iodine Control -Not Currently Active Location:
: Hiawatha, 10,800 meters SE Type: TLD Control Airborne Particulate and Iodine Not used Location:
Hiawatha, 10,800 meters SE Type: TLD Control Airborne Particulate and Iodine Not used Location:
Palo, 4,500 meters SSW Type: TLD Control Location:
Palo, 4,500 meters SSW Type: TLD Control Location:
Palo, 3,470 meters SSW Type: TLD Control Airborne Particulate and Iodine Location:
Palo, 3,470 meters SSW Type: TLD Control Airborne Particulate and Iodine Location:
Line 416: Line 319:
MH201 electrical vault, South of Turbine Building Type: Surface Water Location:
MH201 electrical vault, South of Turbine Building Type: Surface Water Location:
DAEC Sewage Plant Effluent Type: Surface Water Location:
DAEC Sewage Plant Effluent Type: Surface Water Location:
On-Site:
On-Site: North Drainage Ditch Type: Bottom Sediments Not used Location:
North Drainage Ditch Type: Bottom Sediments Not used Location:
5,890 meters SW Type: Vegetation Location:
5,890 meters SW Type: Vegetation Location:
12, 700 meters SW Type: Milk Location:
12, 700 meters SW Type: Milk Location:
Line 462: Line 364:
A channel is an arrangement of a sensor and associated components used to evaluate plant variables and produce discrete outputs used in logic. A channel terminates and loses its identity where individual channel outputs are combined in logic. A CHANNEL CHECK shall be the qualitative assessment, by observation, of channel behavior during operation.
A channel is an arrangement of a sensor and associated components used to evaluate plant variables and produce discrete outputs used in logic. A channel terminates and loses its identity where individual channel outputs are combined in logic. A CHANNEL CHECK shall be the qualitative assessment, by observation, of channel behavior during operation.
This determination shall include, where possible, comparison of the channel indication and status to other indications or status derived from independent instrument channels measuring the same parameter.
This determination shall include, where possible, comparison of the channel indication and status to other indications or status derived from independent instrument channels measuring the same parameter.
A CHANNEL FUNCTIONAL TEST shall be the injection of a simulated or actual signal into the channel as close to the sensor as practicable to verify OPERABILITY, including required alarm, interlock,  
A CHANNEL FUNCTIONAL TEST shall be the injection of a simulated or actual signal into the channel as close to the sensor as practicable to verify OPERABILITY, including required alarm, interlock, display, and trip functions , and channel failure trips. The CHANNEL FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total channel steps. (continued)
: display, and trip functions  
, and channel failure trips. The CHANNEL FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total channel steps. (continued)
Page 59 of 280 Rev. 37 GASEOUS RADWASTE TREATMENT SYSTEM MEMBER(S)
Page 59 of 280 Rev. 37 GASEOUS RADWASTE TREATMENT SYSTEM MEMBER(S)
OF THE PUBLIC MODE OPERABLE-OPERABILITY SITE BOUNDARY SOURCE CHECK UNRESTRICTED AREA DAEC ODAM Definitions 0 6.0.1.1 6.0.1.1 Definitions (continued)
OF THE PUBLIC MODE OPERABLE-OPERABILITY SITE BOUNDARY SOURCE CHECK UNRESTRICTED AREA DAEC ODAM Definitions 0 6.0.1.1 6.0.1.1 Definitions (continued)
A GASEOUS RADWASTE TREATMENT SYSTEM is any system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system offgases from the primary system and providing delay or holdup for the purpose of reducing radioactivity prior to release to the environment.
A GASEOUS RADWASTE TREATMENT SYSTEM is any system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system offgases from the primary system and providing delay or holdup for the purpose of reducing radioactivity prior to release to the environment.
MEMBER(S)
MEMBER(S)
OF THE PUBLIC are persons who are not occupationally associated with the Company and who do not normally frequent the DAEC site. The category does not include contractors, contractor employees,  
OF THE PUBLIC are persons who are not occupationally associated with the Company and who do not normally frequent the DAEC site. The category does not include contractors, contractor employees, vendors, or persons who enter the site to make deliveries or to service equipment.
: vendors, or persons who enter the site to make deliveries or to service equipment.
A MODE shall correspond to any on inclusive combination of mode switch position, average reactor coolant temperature, and reactor vessel head closure bolt tensioning specified in Technical Specifications Table 1.1-1 with fuel in the reactor vessel. A system, subsystem, division, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, division, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s).
A MODE shall correspond to any on inclusive combination of mode switch position, average reactor coolant temperature, and reactor vessel head closure bolt tensioning specified in Technical Specifications Table 1.1-1 with fuel in the reactor vessel. A system, subsystem,  
The SITE BOUNDARY is that line beyond which the land is neither owned, nor leased, nor otherwise controlled by the Company. UFSAR Figure 1.2-1 identifies the DAEC SITE BOUNDARY.
: division, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety function(s) and when all necessary attendant instrumentation,  
: controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem,  
: division, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s).
The SITE BOUNDARY is that line beyond which the land is neither owned, nor leased, nor otherwise controlled by the Company.
UFSAR Figure 1.2-1 identifies the DAEC SITE BOUNDARY.
A SOURCE CHECK is the assessment of channel response when the channel sensor is exposed to a source of radiation.
A SOURCE CHECK is the assessment of channel response when the channel sensor is exposed to a source of radiation.
The UNRESTRICTED AREA is that land (offsite) beyond the SITE BOUNDARY.
The UNRESTRICTED AREA is that land (offsite) beyond the SITE BOUNDARY.
Page 60 of 280 Rev. 37 Definitions 0 6.0.1.1 0 6.0.1 USE AND APPLICATION 0 6.0.1.2 Logical Connectors PURPOSE BACKGROUND EXAMPLES DAECODAM The purpose of this section is to explain the meaning of logical connectors.
Page 60 of 280 Rev. 37 Definitions 0 6.0.1.1 0 6.0.1 USE AND APPLICATION 0 6.0.1.2 Logical Connectors PURPOSE BACKGROUND EXAMPLES DAECODAM The purpose of this section is to explain the meaning of logical connectors.
Logical connectors are used in offsite Dose Assessment Manual (ODAM) to discriminate  
Logical connectors are used in offsite Dose Assessment Manual (ODAM) to discriminate between, and yet connect, discrete Conditions, Required Actions, Completion Times, Surveillances, and Frequencies.
: between, and yet connect, discrete Conditions, Required  
: Actions, Completion Times, Surveillances, and Frequencies.
The only logical connectors that appear in the ODAM are AND and OR. The physical arrangement of these connectors constitutes logical conventions with specific meanings.
The only logical connectors that appear in the ODAM are AND and OR. The physical arrangement of these connectors constitutes logical conventions with specific meanings.
Several levels of logic may be used to state Required Actions.
Several levels of logic may be used to state Required Actions. These levels are identified by the placement (or nesting) of the logical connectors and by the number assigned to each Required Action. The first level of logic is identified by the first digit of the number assigned to a Required Action and the placement of the logical connector in the first level of nesting (i.e., left justified with the number of the Required Action). The successive levels of logic are identified by additional digits of the Required Action number and by successive indentions of the logical connectors.
These levels are identified by the placement (or nesting) of the logical connectors and by the number assigned to each Required Action. The first level of logic is identified by the first digit of the number assigned to a Required Action and the placement of the logical connector in the first level of nesting (i.e., left justified with the number of the Required Action).
The successive levels of logic are identified by additional digits of the Required Action number and by successive indentions of the logical connectors.
When logical connectors are used to state a Condition, Completion Time, Surveillance, or Frequency, only the first level of logic is used, and the logical connector is left justified with the statement of the Condition, Completion Time, Surveillance, or Frequency.
When logical connectors are used to state a Condition, Completion Time, Surveillance, or Frequency, only the first level of logic is used, and the logical connector is left justified with the statement of the Condition, Completion Time, Surveillance, or Frequency.
The ODAM uses Logical Connectors in precisely the same manner they are used in the Technical Requirements Manual (TRM) and the Technical Specifications (TS). Examples illustrating the use of logical connectors are found in TS 1.2 and in the TRM T1 .2 Page 61 of 280 Rev. 37 Completion Times 0 6.0.1.3 0 6.0.1 USE AND APPLICATION 0 6.0.1.3 Completion Times PURPOSE BACKGROUND DESCRIPTION DAEC ODAM The purpose of this section is to establish the Completion Time convention and to provide guidance for its use. OLCOs specify minimum requirements for ensuring safe operation of the unit. The ACTIONS associated with a OLCO state Conditions that typically describe the ways in which the requirements of the OLCO can fail to be met. Specified with each stated Condition are Required Action(s) and Completion Times(s).
The ODAM uses Logical Connectors in precisely the same manner they are used in the Technical Requirements Manual (TRM) and the Technical Specifications (TS). Examples illustrating the use of logical connectors are found in TS 1.2 and in the TRM T1 .2 Page 61 of 280 Rev. 37 Completion Times 0 6.0.1.3 0 6.0.1 USE AND APPLICATION 0 6.0.1.3 Completion Times PURPOSE BACKGROUND DESCRIPTION DAEC ODAM The purpose of this section is to establish the Completion Time convention and to provide guidance for its use. OLCOs specify minimum requirements for ensuring safe operation of the unit. The ACTIONS associated with a OLCO state Conditions that typically describe the ways in which the requirements of the OLCO can fail to be met. Specified with each stated Condition are Required Action(s) and Completion Times(s).
The Completion Time is the amount of time allowed for completing a Required Action. It is referenced to the time of discovery of a situation (e.g., inoperable equipment or variable not within limits) that requires entering an ACTIONS Condition unless otherwise specified, providing the unit is in a MODE or specified condition stated in the Applicability of the OLCO. Required Actions must be completed prior to the expiration of the specified Completion Time. An ACTIONS Condition remains in effect and the Required Actions apply until the Condition no longer exists or the unit is not within the OLCO Applicability.
The Completion Time is the amount of time allowed for completing a Required Action. It is referenced to the time of discovery of a situation (e.g., inoperable equipment or variable not within limits) that requires entering an ACTIONS Condition unless otherwise specified, providing the unit is in a MODE or specified condition stated in the Applicability of the OLCO. Required Actions must be completed prior to the expiration of the specified Completion Time. An ACTIONS Condition remains in effect and the Required Actions apply until the Condition no longer exists or the unit is not within the OLCO Applicability.
If situations are discovered that require entry into more than one Condition at a time within a single OLCO (multiple Conditions),
If situations are discovered that require entry into more than one Condition at a time within a single OLCO (multiple Conditions), the Required Actions for each Condition must be performed within the associated Completion Time. When in multiple Conditions, separate Completion Times are tracked for each Condition starting from the time of discovery of the situation that required entry into the Condition.
the Required Actions for each Condition must be performed within the associated Completion Time. When in multiple Conditions, separate Completion Times are tracked for each Condition starting from the time of discovery of the situation that required entry into the Condition.
Once a Condition has been entered, subsequent divisions, subsystems, components, or variables expressed in the Condition, discovered to be inoperable or not within limits, will not result in separate entry into the Condition unless specifically stated. The Required Actions of the Condition continue to apply to each additional failure, with Completion Times based on initial entry into the Condition. (continued)
Once a Condition has been entered, subsequent divisions, subsystems, components, or variables expressed in the Condition, discovered to be inoperable or not within limits, will not result in separate entry into the Condition unless specifically stated. The Required Actions of the Condition continue to apply to each additional  
Page 62 of 280 Rev. 37 DAEC ODAM Completion Times 0 6.0.1.3 0 6.0.1.3 Completion Times (continued)
: failure, with Completion Times based on initial entry into the Condition.  
However, when a subsequent division, subsystem, component, or variable expressed in the Condition is discovered to be inoperable or not within limits, the Completion Time(s) may be extended.
(continued)
Page 62 of 280 Rev. 37 DAEC ODAM Completion Times 0 6.0.1.3 0 6.0.1.3 Completion Times (continued)  
: However, when a subsequent  
: division, subsystem, component, or variable expressed in the Condition is discovered to be inoperable or not within limits, the Completion Time(s) may be extended.
To apply this Completion Time extension, two criteria must first be met. The subsequent inoperability:  
To apply this Completion Time extension, two criteria must first be met. The subsequent inoperability:  
: a. Must exist concurrent with the first inoperability; and b. Must remain inoperable or not within limits after the first inoperability is resolved.
: a. Must exist concurrent with the first inoperability; and b. Must remain inoperable or not within limits after the first inoperability is resolved.
Line 507: Line 394:
The "specified Frequency" consists of the requirements of the Frequency column of each OSR, as well as certain Notes in the Surveillance column that modify performance requirements.
The "specified Frequency" consists of the requirements of the Frequency column of each OSR, as well as certain Notes in the Surveillance column that modify performance requirements.
Sometimes special situations dictate when the requirements of a Surveillance are to be met. They are "otherwise stated" conditions allowed by OSR 7.0.3.0.1.
Sometimes special situations dictate when the requirements of a Surveillance are to be met. They are "otherwise stated" conditions allowed by OSR 7.0.3.0.1.
They may be stated as clarifying Notes in the Surveillance, as part of the Surveillance or both. Situations where a Surveillance could be required (i.e., its Frequency could expire),
They may be stated as clarifying Notes in the Surveillance, as part of the Surveillance or both. Situations where a Surveillance could be required (i.e., its Frequency could expire), but where it is not possible or not desired that it be performed until sometime after the associated OLCO is within its Applicability, represent potential OSR 7.0.3.0.4 conflicts.
but where it is not possible or not desired that it be performed until sometime after the associated OLCO is within its Applicability, represent potential OSR 7.0.3.0.4 conflicts.
To avoid these conflicts, the OSR (i.e., the Surveillance or the Frequency) is stated such that it is only "required" when it can be and should be performed.
To avoid these conflicts, the OSR (i.e., the Surveillance or the Frequency) is stated such that it is only "required" when it can be and should be performed.
With an OSR satisfied, OSR 6.0.3.0.4 imposes no restriction.
With an OSR satisfied, OSR 6.0.3.0.4 imposes no restriction.
Line 514: Line 400:
A Surveillance is "met" only when the acceptance criteria are satisfied.
A Surveillance is "met" only when the acceptance criteria are satisfied.
Known failure of the requirements of a Surveillance.
Known failure of the requirements of a Surveillance.
even without a Surveillance specifically being "performed,"
even without a Surveillance specifically being "performed," constitutes a Surveillance not "met." "Performance" refers only to the requirement to specifically determine the ability to meet the acceptance criteria.
constitutes a Surveillance not "met." "Performance" refers only to the requirement to specifically determine the ability to meet the acceptance criteria.
OSR 7.0.3.04 restrictions would not apply if both the following conditions are satisfied:  
OSR 7.0.3.04 restrictions would not apply if both the following conditions are satisfied:  
: a. The surveillance is not required to be performed; and b. The Surveillance is not required to be met or, even if required to be met, is not known to be failed. The ODAM implements Frequency in precisely the same manner they as it is employed in the Technical Requirements Manual (TRM) and the Technical Specifications (TS). Examples illustrating the use of logical connectors are found in TS 1.4 and in the TRM T1 .4. Page 64 of 280 Rev. 36 1/16 LCO Applicability 0 6.0.3.0 6.0.3 Limiting Conditions for Operation (OLCO) Applicability OLCO 6.0.3.0.1 OLCOs shall be met during the MODES or other specified conditions in the Applicability, except as provided in OLCO 6.0.3.0.2.
: a. The surveillance is not required to be performed; and b. The Surveillance is not required to be met or, even if required to be met, is not known to be failed. The ODAM implements Frequency in precisely the same manner they as it is employed in the Technical Requirements Manual (TRM) and the Technical Specifications (TS). Examples illustrating the use of logical connectors are found in TS 1.4 and in the TRM T1 .4. Page 64 of 280 Rev. 36 1/16 LCO Applicability 0 6.0.3.0 6.0.3 Limiting Conditions for Operation (OLCO) Applicability OLCO 6.0.3.0.1 OLCOs shall be met during the MODES or other specified conditions in the Applicability, except as provided in OLCO 6.0.3.0.2.
OLCO 6.0.3.0.2 Upon discovery of a failure to meet an OLCO, the Required Actions of the associated Conditions shall be met, except as provided in OLCO 6.0.3.0.5.
OLCO 6.0.3.0.2 Upon discovery of a failure to meet an OLCO, the Required Actions of the associated Conditions shall be met, except as provided in OLCO 6.0.3.0.5.
If the OLCO is met or is no longer applicable prior to expiration of the specified Completion Time(s),
If the OLCO is met or is no longer applicable prior to expiration of the specified Completion Time(s), completion of the Required Action(s) is not required, unless otherwise stated. OLCO 6.0.3.0.3 Not Used. OLCO 6.0 3.0.4 When an OLCO is not met, entry into a MODE or other specified condition in the Applicability shall not be made except when the associated ACTIONS to be entered permit continued operation in the MODE or other specified condition in the Applicability for an unlimited period of time. This OLCO shall not prevent changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit. OLCO 6.0 3.0.4 Exceptions to this OLCO are stated in the individual OLCOs. These exceptions allow entry into MODES or other specified conditions in the Applicability when the associated ACTIONS to be entered allow unit operation in the MODE or other specified condition in the Applicability only for a limited period of time. OLCO 6.0.3.0.4 is only applicable for entry into a MODE or other specified condition in the Applicability in MODES 1 2, and 3. OLCO 6.0.3.0.5 Equipment removed from service or declared inoperable to comply with ACTIONS may be returned to service under administrative control solely to perform testing required to demonstrate its OPERABILITY or the OPERABILITY of other equipment.
completion of the Required Action(s) is not required, unless otherwise stated. OLCO 6.0.3.0.3 Not Used. OLCO 6.0 3.0.4 When an OLCO is not met, entry into a MODE or other specified condition in the Applicability shall not be made except when the associated ACTIONS to be entered permit continued operation in the MODE or other specified condition in the Applicability for an unlimited period of time. This OLCO shall not prevent changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit. OLCO 6.0 3.0.4 Exceptions to this OLCO are stated in the individual OLCOs. These exceptions allow entry into MODES or other specified conditions in the Applicability when the associated ACTIONS to be entered allow unit operation in the MODE or other specified condition in the Applicability only for a limited period of time. OLCO 6.0.3.0.4 is only applicable for entry into a MODE or other specified condition in the Applicability in MODES 1 2, and 3. OLCO 6.0.3.0.5 Equipment removed from service or declared inoperable to comply with ACTIONS may be returned to service under administrative control solely to perform testing required to demonstrate its OPERABILITY or the OPERABILITY of other equipment.
This is an exception to OLCO 6.0.3.0.2 for the system returned to service under administrative control to perform the testing required to demonstrate OPERABILITY. (continued)
This is an exception to OLCO 6.0.3.0.2 for the system returned to service under administrative control to perform the testing required to demonstrate OPERABILITY.  
(continued)
DAECODAM Page 65 of 280 Rev. 36 1/16 OLCO 6.0.3.0.6 DAECODAM LCO Applicability (continued) 0 6.0.1.3 6.0.3 Limiting Conditions for Operation (OLCO) Applicability (continued)
DAECODAM Page 65 of 280 Rev. 36 1/16 OLCO 6.0.3.0.6 DAECODAM LCO Applicability (continued) 0 6.0.1.3 6.0.3 Limiting Conditions for Operation (OLCO) Applicability (continued)
When An ODAM supported system OLCO is not met solely due to a TS support system OLCO not being met, the ODAM Conditions and Required Actions associated with this supported system are not required to be entered.
When An ODAM supported system OLCO is not met solely due to a TS support system OLCO not being met, the ODAM Conditions and Required Actions associated with this supported system are not required to be entered. Only the TS support system OLCO ACTIONS are required to be entered. This is an exception to OLCO 6.0.3.0.2 for the ODAM supported system. When a support system's Required Action (either TS or ODAM) directs a supported system in the ODAM to be declared inoperable or directs entry into Conditions and Required Actions for a ODAM supported system, the applicable ODAM Conditions and Required Actions shall be entered in accordance with ODAM 6.0.3.0.2 When a TS supported system OLCO is not met solely due to a ODAM support system OLCO not being met, the TS supported system Conditions and Required Actions are required to be entered Immediately, under the definition of OPERABILITY, as neither TS LCO 3.0.6 or ODAM OLCO 6.0.3.0.6 apply. When an inoperable Technical Specification support system, structure, or component, (SSC) provides support to a ODAM SSC, which, in turn, supports a supported SSC addressed in the Technical Specifications, Technical Specification LCO 3.0.6 remains applicable.
Only the TS support system OLCO ACTIONS are required to be entered.
This is an exception to OLCO 6.0.3.0.2 for the ODAM supported system. When a support system's Required Action (either TS or ODAM) directs a supported system in the ODAM to be declared inoperable or directs entry into Conditions and Required Actions for a ODAM supported system, the applicable ODAM Conditions and Required Actions shall be entered in accordance with ODAM 6.0.3.0.2 When a TS supported system OLCO is not met solely due to a ODAM support system OLCO not being met, the TS supported system Conditions and Required Actions are required to be entered Immediately, under the definition of OPERABILITY, as neither TS LCO 3.0.6 or ODAM OLCO 6.0.3.0.6 apply. When an inoperable Technical Specification support system, structure, or component, (SSC) provides support to a ODAM SSC, which, in turn, supports a supported SSC addressed in the Technical Specifications, Technical Specification LCO 3.0.6 remains applicable.
Page 66 of 280 Rev. 37 OSR Applicability 0 7.0.3.0 0 7.0.3 SURVEILLANCE REQUIREMENT (OSR) APPLICABILITY OSR 7.0.3.0.1 OSR 7.0.3.0.2 OSR 7.0.3.0.3 OSR 7.0.3.0.4 DAECODAM OSRs shall be met during the MODES or other specified conditions in the Applicability for individual OLCOS, unless otherwise stated in the OSR. Failure to meet a Surveillance, whether such failure is experienced during the performance of the Surveillance or between performances of the Surveillance, shall be failure to meet the OLCO. Failure to perform a Surveillance within the specified Frequency shall be failure to meet the OLCO except as provided in OSR 7.0.3.0.3.
Page 66 of 280 Rev. 37 OSR Applicability 0 7.0.3.0 0 7.0.3 SURVEILLANCE REQUIREMENT (OSR) APPLICABILITY OSR 7.0.3.0.1 OSR 7.0.3.0.2 OSR 7.0.3.0.3 OSR 7.0.3.0.4 DAECODAM OSRs shall be met during the MODES or other specified conditions in the Applicability for individual OLCOS, unless otherwise stated in the OSR. Failure to meet a Surveillance, whether such failure is experienced during the performance of the Surveillance or between performances of the Surveillance, shall be failure to meet the OLCO. Failure to perform a Surveillance within the specified Frequency shall be failure to meet the OLCO except as provided in OSR 7.0.3.0.3.
Surveillances do not have to be performed on inoperable equipment or variables outside specified limits. The specified Frequency for each OSR is met if the Surveillance is performed within 1.25 times the interval specified in the Frequency, as measured from the previous performance or as measured from the time a specified condition of the Frequency is met. For Frequencies specified as "once," the above interval extension does not apply. If a Completion Time requires periodic performance on a "once per ... " basis, the above Frequency extension applies to each performance after the initial performance.
Surveillances do not have to be performed on inoperable equipment or variables outside specified limits. The specified Frequency for each OSR is met if the Surveillance is performed within 1.25 times the interval specified in the Frequency, as measured from the previous performance or as measured from the time a specified condition of the Frequency is met. For Frequencies specified as "once," the above interval extension does not apply. If a Completion Time requires periodic performance on a "once per ... " basis, the above Frequency extension applies to each performance after the initial performance.
Exceptions to this OSR are stated in the individual OLCOs. If it is discovered that a Surveillance was not performed within its specified Frequency, then compliance with the requirement to declare the OLCO not met may be delayed, from the time of discovery, up to 24 hours or up to the limit of the specified Frequency, whichever is more. This delay period is permitted to allow performance of the Surveillance.
Exceptions to this OSR are stated in the individual OLCOs. If it is discovered that a Surveillance was not performed within its specified Frequency, then compliance with the requirement to declare the OLCO not met may be delayed, from the time of discovery, up to 24 hours or up to the limit of the specified Frequency, whichever is more. This delay period is permitted to allow performance of the Surveillance.
If the Surveillance is not performed within the delay period, the OLCO must immediately be declared not met, and the applicable Condition(s) must be entered.
If the Surveillance is not performed within the delay period, the OLCO must immediately be declared not met, and the applicable Condition(s) must be entered. When the Surveillance is performed within the delay period and the Surveillance is not met, the OLCO must immediately be declared not met, and the applicable Condition(s) must be entered. Entry into a MODE or other specified condition in the Applicability of an OLCO shall not be made unless the OLCO's Surveillances have been met within their specified Frequency.
When the Surveillance is performed within the delay period and the Surveillance is not met, the OLCO must immediately be declared not met, and the applicable Condition(s) must be entered.
Entry into a MODE or other specified condition in the Applicability of an OLCO shall not be made unless the OLCO's Surveillances have been met within their specified Frequency.
This provision shall not prevent entry into MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit. OSR 7.0.3.0.4 is only applicable for entry into a MODE or other specified condition in the Applicability in MODES 1, 2, and 3. Page 67 of 280 Rev. 36 1/16 0 6.1 0 6.1.1 OLCO 6.1.1 APPLICABILITY:
This provision shall not prevent entry into MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit. OSR 7.0.3.0.4 is only applicable for entry into a MODE or other specified condition in the Applicability in MODES 1, 2, and 3. Page 67 of 280 Rev. 36 1/16 0 6.1 0 6.1.1 OLCO 6.1.1 APPLICABILITY:
ACTIONS CONDITION A. One or more channels inoperable B. As required by Required Action A.1 and referenced in Table 6.1-1 C. As required by Required Action A.1 and referenced in Table 6.1-1 D. Less than the minimum required channels OPERABLE.
ACTIONS CONDITION A. One or more channels inoperable B. As required by Required Action A.1 and referenced in Table 6.1-1 C. As required by Required Action A.1 and referenced in Table 6.1-1 D. Less than the minimum required channels OPERABLE.
Line 545: Line 424:
SURVEILLANCE FREQUENCY OSR 7.1.1.1 Perform CHANNEL CHECK 24 Hours OSR 7.1.1.2 Perform SOURCE CHECK 24 Hours OSR 7.1.1.3 Perform SOURCE CHECK 30 Days OSR 7.1.1.4 Perform CHANNEL FUNCTIONAL TEST 92 Days OSR 7.1.1.5 Perform CHANNEL CALIBRATION 18 Months OSR 7.1.1.6 Perform Monitor Setpoint Calculation.
SURVEILLANCE FREQUENCY OSR 7.1.1.1 Perform CHANNEL CHECK 24 Hours OSR 7.1.1.2 Perform SOURCE CHECK 24 Hours OSR 7.1.1.3 Perform SOURCE CHECK 30 Days OSR 7.1.1.4 Perform CHANNEL FUNCTIONAL TEST 92 Days OSR 7.1.1.5 Perform CHANNEL CALIBRATION 18 Months OSR 7.1.1.6 Perform Monitor Setpoint Calculation.
18 Months OSR 7.1.1.7 Perform CHANNEL FUNCTIONAL TEST Prior to release OSR 7.1.1.8 Perform CHANNEL CALIBRATION Prior to release OSR 7.1.1.9 Perform Monitor Setpoint Calculation.
18 Months OSR 7.1.1.7 Perform CHANNEL FUNCTIONAL TEST Prior to release OSR 7.1.1.8 Perform CHANNEL CALIBRATION Prior to release OSR 7.1.1.9 Perform Monitor Setpoint Calculation.
Prior to release DAEC ODAM Page 70 of 280 Rev. 37 TABLE 6.1-1 /7.1-1 Radioactive Liquid Instrumentation 0 6.1.1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION Minimum Conditions Instrument Applicability Channels Referenced from Surveillance Required Action Requirements Operable A.1 1. Gross Radioactive Monitors Providing Automatic Termination of Release OSR 7.1.1.1 <al OSR 7.1.1.2 (bl During 1 B OSR 7.1.1.7 (dl a. Liquid Radwaste Effluent Line Releases (e) OSR 7.1.1.8 <cl OSR 7.1.1.9 2. Gross Radioactive Monitors Not Providing Automatic Termination of Release a. RHR Service Water System During 1 OSR 7 .1.1.1 <al Releases OSR 7.1.1.3 b. General Service Water During 1 c OSR 7.1.1.4 <el System Releases OSR 7.1.1.5<cJ RHRSW/ESW Rupture Disc During OSR 7.1.1.6 c. 1 Effluent Line Releases  
Prior to release DAEC ODAM Page 70 of 280 Rev. 37 TABLE 6.1-1 /7.1-1 Radioactive Liquid Instrumentation 0 6.1.1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION Minimum Conditions Instrument Applicability Channels Referenced from Surveillance Required Action Requirements Operable A.1 1. Gross Radioactive Monitors Providing Automatic Termination of Release OSR 7.1.1.1 <al OSR 7.1.1.2 (bl During 1 B OSR 7.1.1.7 (dl a. Liquid Radwaste Effluent Line Releases (e) OSR 7.1.1.8 <cl OSR 7.1.1.9 2. Gross Radioactive Monitors Not Providing Automatic Termination of Release a. RHR Service Water System During 1 OSR 7 .1.1.1 <al Releases OSR 7.1.1.3 b. General Service Water During 1 c OSR 7.1.1.4 <el System Releases OSR 7.1.1.5<cJ RHRSW/ESW Rupture Disc During OSR 7.1.1.6 c. 1 Effluent Line Releases 3. Flow Rate Measurement Devices a. Liquid Radwaste Effluent Line During 1 OSR 7.1.1.1 <a> Releases D (f) During OSR 7.1.1.7 b. Liquid Radwaste Dilution Line Releases 1 OSR 7.1.1.8 TABLE NOTATIONS (a) During releases via this pathway. (b) On any day on which a release is made, a SOURCE CHECK shall be made at least once, prior to the first release. ( c) The CHANNEL CALIBRATION shall include the use of a known radioactive source (traceable to the NIST radiation measurement system or acceptable non-NIST standards) positioned in a reproducible geometry with respect to the sensor and emitting beta or gamma radiation in the range measured by the channel. CHANNEL CALIBRATION may normally be done during refueling outages. (d) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway if the following condition exists: 1. Instrument indicates measured levels above the alarm/trip setpoint. (e) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exist: 1. Instrument indicates measured levels above the alarm/trip setpoint.  
: 3. Flow Rate Measurement Devices a. Liquid Radwaste Effluent Line During 1 OSR 7.1.1.1 <a> Releases D (f) During OSR 7.1.1.7 b. Liquid Radwaste Dilution Line Releases 1 OSR 7.1.1.8 TABLE NOTATIONS (a) During releases via this pathway.  
: 2. Circuit failure. 3. Instrument indicates a downscale failure. 4. Instrument controls not set in operate mode. (!J CHANNEL CHECK shall consist of verifying indication of flow during periods of release. CHANNEL CHECK shall be made at least once daily on any day on which continuous, periodic, or batch releases are made. DAECODAM Page 71 of 280 Rev. 37 0 6.1 Radioactive Liquid Instrumentation 0 6.1.1 RADIOACTIVE LIQUID EFFLUENT CONTROLS 0 6.1.2 Liquid Effluent Concentration OLCO 6.1.2 The concentration of radioactive material in liquid effluent released from the site to the UNRESTRICTED AREA shall not exceed ten times the concentrations specified in 10 CFR 20, Appendix B, Table 2, Column 2 to 1 O CFR 20.1001 -20.2402. APPLICABILITY:
(b) On any day on which a release is made, a SOURCE CHECK shall be made at least once, prior to the first release.  
( c) The CHANNEL CALIBRATION shall include the use of a known radioactive source (traceable to the NIST radiation measurement system or acceptable non-NIST standards) positioned in a reproducible geometry with respect to the sensor and emitting beta or gamma radiation in the range measured by the channel.
CHANNEL CALIBRATION may normally be done during refueling outages.  
(d) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway if the following condition exists: 1. Instrument indicates measured levels above the alarm/trip setpoint.  
(e) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exist: 1. Instrument indicates measured levels above the alarm/trip setpoint.  
: 2. Circuit failure.  
: 3. Instrument indicates a downscale failure.  
: 4. Instrument controls not set in operate mode. (!J CHANNEL CHECK shall consist of verifying indication of flow during periods of release.
CHANNEL CHECK shall be made at least once daily on any day on which continuous,  
: periodic, or batch releases are made. DAECODAM Page 71 of 280 Rev. 37 0 6.1 Radioactive Liquid Instrumentation 0 6.1.1 RADIOACTIVE LIQUID EFFLUENT CONTROLS 0 6.1.2 Liquid Effluent Concentration OLCO 6.1.2 The concentration of radioactive material in liquid effluent released from the site to the UNRESTRICTED AREA shall not exceed ten times the concentrations specified in 10 CFR 20, Appendix B, Table 2, Column 2 to 1 O CFR 20.1001 -20.2402.
APPLICABILITY:
At all times. ACTIONS A. CONDITION Concentration of radioactive material released from site to UNRESTRICTED AREAS not within the limit. DAECODAM REQUIRED ACTION COMPLETION TIME A.1 Restore concentration Immediately to within limits. Page 72 of 280 Rev. 37 Radioactive Liquid Effluent Concentration 0 7.1.2 SURVEILLANCE REQUIREMENTS  
At all times. ACTIONS A. CONDITION Concentration of radioactive material released from site to UNRESTRICTED AREAS not within the limit. DAECODAM REQUIRED ACTION COMPLETION TIME A.1 Restore concentration Immediately to within limits. Page 72 of 280 Rev. 37 Radioactive Liquid Effluent Concentration 0 7.1.2 SURVEILLANCE REQUIREMENTS  
------------------------------------------NOTE------------------------------------------
------------------------------------------NOTE------------------------------------------
Line 563: Line 431:
--------------------------
--------------------------
N 0 TE--------------------------
N 0 TE--------------------------
P o rti on s of each sample are "split out" and added to the Monthly and Quarterly Composite sample. Sample the Batch Release.
P o rti on s of each sample are "split out" and added to the Monthly and Quarterly Composite sample. Sample the Batch Release. The results of pre-release analyses shall be used with the calculation methods in the ODAM to establish trip setpoints for batch releases to assure that the concentration at the UNRESTRICTED AREA boundary does not exceed the limit in OLCO 6.1.2. ----------------------------N 0 TE--------------------------
The results of pre-release analyses shall be used with the calculation methods in the ODAM to establish trip setpoints for batch releases to assure that the concentration at the UNRESTRICTED AREA boundary does not exceed the limit in OLCO 6.1.2. ----------------------------N 0 TE--------------------------
P o rtio ns of each sample are split out and added to the Monthly and Quarterly Composite sample. -----------------------------N 0 TE--------------------------
P o rtio ns of each sample are split out and added to the Monthly and Quarterly Composite sample. -----------------------------N 0 TE--------------------------
1 n the event of a positive identification of reactor by-product radioactivity in the service water, additional sampling and analysis shall be performed as specified in Table 7.1-2, Table Items B.2 through B.5. Sample the Continuous Release during releases to the environment via this pathway.
1 n the event of a positive identification of reactor by-product radioactivity in the service water, additional sampling and analysis shall be performed as specified in Table 7.1-2, Table Items B.2 through B.5. Sample the Continuous Release during releases to the environment via this pathway. AND Analyze the sample from the release for Gross Beta/Gamma.
AND Analyze the sample from the release for Gross Beta/Gamma.
Analyze the sample from the release for Principal Gamma Emitters and 1-131. Page 73 of 280 FREQUENCY PRIOR TO EACH RELEASE PRIOR TO EACH RELEASE 7 Days (continued)
Analyze the sample from the release for Principal Gamma Emitters and 1-131. Page 73 of 280 FREQUENCY PRIOR TO EACH RELEASE PRIOR TO EACH RELEASE 7 Days (continued)
Rev. 37 OSR 7.1.2.4 OSR 7.1.2.5 OSR 7.1.2.6 OSR 7.1.2.7 DAECODAM Radioactive Liquid Effluent Concentration 0 7.1.2 Analyze the sample from the release for Principal Gamma Emitters and 1-131. Analyze the "Monthly" Composite sample for Tritium.  
Rev. 37 OSR 7.1.2.4 OSR 7.1.2.5 OSR 7.1.2.6 OSR 7.1.2.7 DAECODAM Radioactive Liquid Effluent Concentration 0 7.1.2 Analyze the sample from the release for Principal Gamma Emitters and 1-131. Analyze the "Monthly" Composite sample for Tritium. --------------------------N 0 TE--------------------------
--------------------------N 0 TE--------------------------
F or Service Water, this OSR is only required following a positive identification of reactor product radioactivity in the sample as determined during OSR 7.1.2.3 or OSR 7.1.2.5. -------------------------
F or Service Water, this OSR is only required following a positive identification of reactor product radioactivity in the sample as determined during OSR 7.1.2.3 or OSR 7.1.2.5.  
-------------------------
N 0 TE----------------------------
N 0 TE----------------------------
F or "clean" water systems, this OSR is only required following a positive identification of reactor by-product radioactivity in the sample as determined during OSR 7 .1.2.4. -------------------------N 0 TE----------------------------
F or "clean" water systems, this OSR is only required following a positive identification of reactor by-product radioactivity in the sample as determined during OSR 7 .1.2.4. -------------------------N 0 TE----------------------------
F or GWPP Mitigation system, this OSR is only required following a positive identification of a radioactive reactor by-product in the sample as determined during OSR 7.1.2.3.
F or GWPP Mitigation system, this OSR is only required following a positive identification of a radioactive reactor by-product in the sample as determined during OSR 7.1.2.3. Analyze the Quarterly Composite sample for Sr-89, Sr-90, Fe-55 PRIOR TO EACH RELEASE 30 Days 92 Days Analyze the "Monthly" Composite sample for Gross 30 Days Alpha. Page 7 4 of 280 Rev. 37 Radioactive Liquid Effluent Concentration 0 6.1.2 TABLE 7.1-2 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Liquid Release Type Surveillance Table Type of Activity Requirements item/note Analysis A. Radwaste Tanks OSR 7.1.2.1 A.1: Each Principal Gamma Batch Release Batch Emmittersc OSR 7.1.2.4 OSR 7.1.2.2 l-131c OSR 7.1.2.1 A.2: (d) (b) H-3 OSR 7.1.2.5 OSR 7.1.2.7 Gross alpha OSR 7.1.2.1 A.3: (d)(b) Sr-89, Sr-90 OSR 7.1.2.6 Fe-55 8. Continuous Service OSR 7.1.2.3 8.1: (d) Gross beta/gamma Water Release OSR 7.1.2.3 8.2: (d) Principal Gamma Sample Points: Emitters
Analyze the Quarterly Composite sample for Sr-89, Sr-90, Fe-55 PRIOR TO EACH RELEASE 30 Days 92 Days Analyze the "Monthly" Composite sample for Gross 30 Days Alpha. Page 7 4 of 280 Rev. 37 Radioactive Liquid Effluent Concentration 0 6.1.2 TABLE 7.1-2 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Liquid Release Type Surveillance Table Type of Activity Requirements item/note Analysis A. Radwaste Tanks OSR 7.1.2.1 A.1: Each Principal Gamma Batch Release Batch Emmittersc OSR 7.1.2.4 OSR 7.1.2.2 l-131c OSR 7.1.2.1 A.2: (d) (b) H-3 OSR 7.1.2.5 OSR 7.1.2.7 Gross alpha OSR 7.1.2.1 A.3: (d)(b) Sr-89, Sr-90 OSR 7.1.2.6 Fe-55 8. Continuous Service OSR 7.1.2.3 8.1: (d) Gross beta/gamma Water Release OSR 7.1.2.3 8.2: (d) Principal Gamma Sample Points: Emitters
* General Services Water 1-131
* General Services Water 1-131
* RHR Service Water System A
* RHR Service Water System A
* RHR Service Water System B 8.4: (b),(d) OSR 7.1.2.5 H-3 OSR 7.1.2.7 Gross alpha OSR 7.1.2.6 8.5: (b),(d) Sr-89, Sr-90 Fe-55 C. "Clean" Systems OSR 7.1.2.1 C.1: Principal Gamma Batch Release OSR 7.1.2.4 Emitters(!)
* RHR Service Water System B 8.4: (b),(d) OSR 7.1.2.5 H-3 OSR 7.1.2.7 Gross alpha OSR 7.1.2.6 8.5: (b),(d) Sr-89, Sr-90 Fe-55 C. "Clean" Systems OSR 7.1.2.1 C.1: Principal Gamma Batch Release OSR 7.1.2.4 Emitters(!)
1-131(1)
1-131(1) Sample Points: OSR 7.1.2.5 C.2: (b) (d) (e)
Sample Points: OSR 7.1.2.5 C.2: (b) (d) (e)
H-3(1)
H-3(1)
* CST Pit Rain Water
* CST Pit Rain Water
Line 587: Line 449:
* Neutralizing Tank 1T022
* Neutralizing Tank 1T022
* FRAC tanks Fe-55 D. GWPP Mitigation System OSR 7.1.2.3 D.1: Principal Gamma Emitters Continuous Release 1-131 (c) OSR 7.1.2.5 D.2: (b)(d)(e)
* FRAC tanks Fe-55 D. GWPP Mitigation System OSR 7.1.2.3 D.1: Principal Gamma Emitters Continuous Release 1-131 (c) OSR 7.1.2.5 D.2: (b)(d)(e)
H-3(fl OSR 7.1.2.7 Gross Alpha OSR 7.1.2.6 D.3: (b)(dl Sr-89, Sr-90 Fe-55 DAEC ODAM Page 75 of 280 Lower Limit of Detection (LLD)(a)  
H-3(fl OSR 7.1.2.7 Gross Alpha OSR 7.1.2.6 D.3: (b)(dl Sr-89, Sr-90 Fe-55 DAEC ODAM Page 75 of 280 Lower Limit of Detection (LLD)(a) (&#xb5;Ci/ml) 5x10-7 1x10-5 1 x 10-5 1x10-7 5 x 10-8 1x10-5 1x10-7 5 x 10-7 1x10-5 1x10-5 1x10-7 5 x 10-8 1 x 10-6 5 x 10-7 1x10-5 1 x 10-5 5 x 10-8 1 x 10-6 5.0X 10-7 1.0 x 10-6 1.0X 10-5 1.0 x 10-7 5.0 x 10-8 1.0X10-6 Rev. 37 TABLE NOTATIONS Radioactive Liquid Effluent Concentration 0 6.1.2 <alThe LLD is defined, for purposes of these controls, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal. DAEC ODAM Page 76 of 280 Rev. 37 Radioactive Liquid Effluent Concentration 0 6.1.2 For a particular measurement, which may include radiochemical separation:
(&#xb5;Ci/ml) 5x10-7 1x10-5 1 x 10-5 1x10-7 5 x 10-8 1x10-5 1x10-7 5 x 10-7 1x10-5 1x10-5 1x10-7 5 x 10-8 1 x 10-6 5 x 10-7 1x10-5 1 x 10-5 5 x 10-8 1 x 10-6 5.0X 10-7 1.0 x 10-6 1.0X 10-5 1.0 x 10-7 5.0 x 10-8 1.0X10-6 Rev. 37 TABLE NOTATIONS Radioactive Liquid Effluent Concentration 0 6.1.2 <alThe LLD is defined, for purposes of these controls, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal. DAEC ODAM Page 76 of 280 Rev. 37 Radioactive Liquid Effluent Concentration 0 6.1.2 For a particular measurement, which may include radiochemical separation:
4.66 Sb LLD Ex Vx 2.22E6x e-w where: LLD is the "a priori" lower limit of detection as defined above (microcuries per unit mass or volume) and where: Sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute) Eis the counting efficiency (counts per disintegration)
4.66 Sb LLD Ex Vx 2.22E6x e-w where: LLD is the "a priori" lower limit of detection as defined above (microcuries per unit mass or volume) and where: Sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute) Eis the counting efficiency (counts per disintegration)
Vis the sample size (units of mass or volume) 2.22E6 is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield, when applicable, "A is the radioactive decay constant for the particular radionuclide (sec-\ and f.. t for effluents is the elapsed time between the midpoint of sample collection and the time of counting (sec-1)_
Vis the sample size (units of mass or volume) 2.22E6 is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield, when applicable, "A is the radioactive decay constant for the particular radionuclide (sec-\ and f.. t for effluents is the elapsed time between the midpoint of sample collection and the time of counting (sec-1)_ Alternatively, exp may be replaced by At e-212 1 e. e-212 J -e-211 Where: t 1 is the total sampling time or sample compositing time t 2 is the elapsed time between the end of sample collection and the time of counting.
Alternatively, exp may be replaced by At e-212 1 e. e-212 J -e-211 Where: t1 is the total sampling time or sample compositing time t2 is the elapsed time between the end of sample collection and the time of counting.
It should be recognized that the LLD is defined as an .9. priori (before the fact) limit representing the capability of a measurement system and not as an &#xa3;!.posteriori (after the fact) limit for a particular measurement.
It should be recognized that the LLD is defined as an .9. priori (before the fact) limit representing the capability of a measurement system and not as an &#xa3;!.posteriori (after the fact) limit for a particular measurement.
Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions with typical values of E, V, Y, and Dt for the radionuclides Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144. Occasionally background fluctuations, unavoidably small sample sizes, interfering radionuclides, or other uncontrollable circumstances may render these LLDs unachievable.
Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions with typical values of E, V, Y, and Dt for the radionuclides Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144. Occasionally background fluctuations, unavoidably small sample sizes, interfering radionuclides, or other uncontrollable circumstances may render these LLDs unachievable.
When calculating the LLD for a radionuclide determined by gamma ray spectrometry, the background may include the typical contributions of other radionuclides normally present in the samples.
When calculating the LLD for a radionuclide determined by gamma ray spectrometry, the background may include the typical contributions of other radionuclides normally present in the samples. The background count rate of a Ge(Li) detector is determined from background counts that are determined to be within the full width of the specific energy band used for the quantitative analysis for that radionuclide.
The background count rate of a Ge(Li) detector is determined from background counts that are determined to be within the full width of the specific energy band used for the quantitative analysis for that radionuclide.
The principal gamma emitters for which the LLD specification will apply are exclusively the following radionuclides:
The principal gamma emitters for which the LLD specification will apply are exclusively the following radionuclides:
Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137 and Ce-141. Ce-144 shall be measured, but with an LLD of 5E-6. This list does not mean that only these nuclides are to be detected and reported.
Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137 and Ce-141. Ce-144 shall be measured, but with an LLD of 5E-6. This list does not mean that only these nuclides are to be detected and reported.
Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported.
Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported.
Nuclides which are below the LLD for the analyses should not be reported as being present at the LLD level. When unusual circumstances result in LLDs higher than required, the reasons shall be documented in the Annual Radioactive Material Release Report. (b) A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquids released.  
Nuclides which are below the LLD for the analyses should not be reported as being present at the LLD level. When unusual circumstances result in LLDs higher than required, the reasons shall be documented in the Annual Radioactive Material Release Report. (b) A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquids released. ( c) In the event a gross or y analysis is performed in lieu of an isotopic analysis before a batch is discharged, a sample shall be analyzed for principal gamma emitters afterward. (d) Analysis may be performed after release. (e) Analysis at a frequency of less than 30 days is allowed. (I) If liquids from these systems are released from the site via a pathway that is NOT directly to the Cedar River, the required LLDs of Table 6.3.2 are applicable.
( c) In the event a gross or y analysis is performed in lieu of an isotopic analysis before a batch is discharged, a sample shall be analyzed for principal gamma emitters afterward.  
(d) Analysis may be performed after release.  
(e) Analysis at a frequency of less than 30 days is allowed.  
(I) If liquids from these systems are released from the site via a pathway that is NOT directly to the Cedar River, the required LLDs of Table 6.3.2 are applicable.
DAECODAM Page 77 of 280 Rev. 37 Dose Due to Liquid Radioactive Effluents 0 6.1.3 0 6.1 RADIOACTIVE LIQUID EFFLUENT CONTROLS 0 6.1.3 Dose Due to Liquid Radioactive Effluents OLCO 6.1.3 The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released to the UNRESTRICTED AREA shall not exceed: APPLICABILITY:
DAECODAM Page 77 of 280 Rev. 37 Dose Due to Liquid Radioactive Effluents 0 6.1.3 0 6.1 RADIOACTIVE LIQUID EFFLUENT CONTROLS 0 6.1.3 Dose Due to Liquid Radioactive Effluents OLCO 6.1.3 The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released to the UNRESTRICTED AREA shall not exceed: APPLICABILITY:
ACTIONS 1.5 mrem to the total body during any calendar  
ACTIONS 1.5 mrem to the total body during any calendar quarter, 5.0 mrem to any organ during any calendar quarter, 3.0 mrem to the total body during any calendar year, or 10.0 mrem to any organ during any calendar year. At All Times CONDITION REQUIRED ACTION COMPLETION TIME A. Calculated dose from the A.1 Prepare and submit a Special 30 days release of radioactive Report to the Commission materials in liquid which identifies the cause(s) effluents exceeds limits. for exceeding the limit and defines the action to be taken. DAEC ODAM Page 78 of 280 Rev. 37 Dose Due to Liquid Radioactive Effluents 0 7.1.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY OSR 7.1.3.1 In any quarter in which radioactive liquid effluent is 30 Days discharged, an assessment shall be performed in accordance with the ODAM in order to verify that the cumulative dose commitment does not exceed the limits in OLCO 6.1.3. DAEC ODAM Page 79 of 280 Rev. 37 Liquid Waste Treatment 0 6.1.4 0 6.1 0 6.1.4 OLCO 6.1.4 APPLICABILITY:
: quarter, 5.0 mrem to any organ during any calendar  
: quarter, 3.0 mrem to the total body during any calendar year, or 10.0 mrem to any organ during any calendar year. At All Times CONDITION REQUIRED ACTION COMPLETION TIME A. Calculated dose from the A.1 Prepare and submit a Special 30 days release of radioactive Report to the Commission materials in liquid which identifies the cause(s) effluents exceeds limits. for exceeding the limit and defines the action to be taken. DAEC ODAM Page 78 of 280 Rev. 37 Dose Due to Liquid Radioactive Effluents 0 7.1.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY OSR 7.1.3.1 In any quarter in which radioactive liquid effluent is 30 Days discharged, an assessment shall be performed in accordance with the ODAM in order to verify that the cumulative dose commitment does not exceed the limits in OLCO 6.1.3. DAEC ODAM Page 79 of 280 Rev. 37 Liquid Waste Treatment 0 6.1.4 0 6.1 0 6.1.4 OLCO 6.1.4 APPLICABILITY:
ACTIONS A. CONDITION Radioactive liquid waste being discharge without treatment and in excess of limits. DAEC ODAM RADIOACTIVE LIQUID EFFLUENT CONTROLS Liquid Waste Treatment Appropriate liquid radwaste equipment shall be used to treat any untreated batch of liquid waste prior to discharge when a released analysis indicates a radioactivity concentration (exclusive of tritium and dissolved gases) of 0.01 &#xb5;Ci/ml or higher. At all times. REQUIRED ACTION COMPLETION TIME A.1 Prepare and submit a Special 30 days Report to the Commission which includes identification of inoperable equipment or subsystems and the reason, actions taken to restore the inoperable equipment, and description of action(s) taken to prevent recurrence.
ACTIONS A. CONDITION Radioactive liquid waste being discharge without treatment and in excess of limits. DAEC ODAM RADIOACTIVE LIQUID EFFLUENT CONTROLS Liquid Waste Treatment Appropriate liquid radwaste equipment shall be used to treat any untreated batch of liquid waste prior to discharge when a released analysis indicates a radioactivity concentration (exclusive of tritium and dissolved gases) of 0.01 &#xb5;Ci/ml or higher. At all times. REQUIRED ACTION COMPLETION TIME A.1 Prepare and submit a Special 30 days Report to the Commission which includes identification of inoperable equipment or subsystems and the reason, actions taken to restore the inoperable equipment, and description of action(s) taken to prevent recurrence.
Page 80 of 280 Rev. 37 Liquid Waste Treatment 0 7.1.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY OSR 7.1.4.1 Each radioactive liquid waste batch shall be PRIOR TO EACH sampled and analyzed in accordance with Section RELEASE 7.1.2 and Table 7.1-2. DAECODAM Page 81 of 280 Rev. 37 Liquid Holdup Tanks 0 6.1.5 0 6.1 0 6.1.5 OLCO 6.1.5 APPLICABILITY:
Page 80 of 280 Rev. 37 Liquid Waste Treatment 0 7.1.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY OSR 7.1.4.1 Each radioactive liquid waste batch shall be PRIOR TO EACH sampled and analyzed in accordance with Section RELEASE 7.1.2 and Table 7.1-2. DAECODAM Page 81 of 280 Rev. 37 Liquid Holdup Tanks 0 6.1.5 0 6.1 0 6.1.5 OLCO 6.1.5 APPLICABILITY:
Line 616: Line 469:
DAECODAM Page 83 of 280 Rev. 37 Radioactive Gaseous Effluent Instrumentation 0 6.2.1.1 06.2 0 6.2.1.1 OLCO 6.2.1.1 APPLICABILITY:
DAECODAM Page 83 of 280 Rev. 37 Radioactive Gaseous Effluent Instrumentation 0 6.2.1.1 06.2 0 6.2.1.1 OLCO 6.2.1.1 APPLICABILITY:
ACTIONS CONDITION A. One or more channels inoperable.
ACTIONS CONDITION A. One or more channels inoperable.
B. As required by Required Action A.1 and referenced in Table 6.2-1 C. As required by Required Action A.1 and referenced in Table 6.2-1 DAEC ODAM RADIOACTIVE GASEOUS EFFLUENT CONTROLS Radioactive Gaseous Effluent Instrumentation The Radioactive Gaseous Effluent Instrumentation for each function in Table 6.2-1 shall be OPERABLE During releases via this pathway.
B. As required by Required Action A.1 and referenced in Table 6.2-1 C. As required by Required Action A.1 and referenced in Table 6.2-1 DAEC ODAM RADIOACTIVE GASEOUS EFFLUENT CONTROLS Radioactive Gaseous Effluent Instrumentation The Radioactive Gaseous Effluent Instrumentation for each function in Table 6.2-1 shall be OPERABLE During releases via this pathway. REQUIRED ACTION COMPLETION TIME A.1 Enter the condition referenced Immediately in Table 6.2-1 for the channel. AND A.2 Restore required channel(s) to 30 days OPERABLE status. B.1 Collect gaseous grab sample. once per 8 hours AND B.2 Analyze sample for radioactivity.
REQUIRED ACTION COMPLETION TIME A.1 Enter the condition referenced Immediately in Table 6.2-1 for the channel.
AND A.2 Restore required channel(s) to 30 days OPERABLE status. B.1 Collect gaseous grab sample. once per 8 hours AND B.2 Analyze sample for radioactivity.
Within 24 hours of sample collection C. 1 Establish preplanned alternate 8 hours monitoring method. OR C.2.1 Collect gaseous grab sample. once per 8 hours AND C.2.2 Analyze sample for radioactivity.
Within 24 hours of sample collection C. 1 Establish preplanned alternate 8 hours monitoring method. OR C.2.1 Collect gaseous grab sample. once per 8 hours AND C.2.2 Analyze sample for radioactivity.
Within 24 hours of sample collection (continued)
Within 24 hours of sample collection (continued)
Line 630: Line 481:
1 nstrumentation shall be OPERABLE and in service except that channels out of service are permitted for the purpose of required tests, checks and calibrations without declaring the channel to be inoperable.
1 nstrumentation shall be OPERABLE and in service except that channels out of service are permitted for the purpose of required tests, checks and calibrations without declaring the channel to be inoperable.
SURVEILLANCE FREQUENCY OSR 7.2.1.1.1 Perform CHANNEL CHECK 24 Hours --------------------------N 0 TE-----------------------------
SURVEILLANCE FREQUENCY OSR 7.2.1.1.1 Perform CHANNEL CHECK 24 Hours --------------------------N 0 TE-----------------------------
During releases via this pathway.  
During releases via this pathway. ----------------------------------------------------------------
----------------------------------------------------------------
OSR 7.2.1.1.2 Perform CHANNEL CHECK 7 Days OSR 7.2.1.1.3 Perform SOURCE CHECK 30 Days OSR 7.2.1.1.4 Determine the monitor setpoints in accordance with 92 Days the method described in the ODAM. OSR 7.2.1.1.5 Perform CHANNEL FUNCTIONAL TEST 92 Days OSR 7.2.1.1.6 Determine the monitor setpoints in accordance with 18 Months the method described in the ODAM. OSR 7.2.1.1.7 Perform CHANNEL CALIBRATION 18 Months DAECODAM Page 86 of 280 Rev. 37 Radioactive Gaseous Effluent Instrumentation 0 6.2.1.1 I TABLE 6.2-1 I TABLE 7.2-1 NORMAL RANGE RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Instrument 1.0ffgas Stack Monitoring System a. Noble Gas Activity Monitor b ...  
OSR 7.2.1.1.2 Perform CHANNEL CHECK 7 Days OSR 7.2.1.1.3 Perform SOURCE CHECK 30 Days OSR 7.2.1.1.4 Determine the monitor setpoints in accordance with 92 Days the method described in the ODAM. OSR 7.2.1.1.5 Perform CHANNEL FUNCTIONAL TEST 92 Days OSR 7.2.1.1.6 Determine the monitor setpoints in accordance with 18 Months the method described in the ODAM. OSR 7.2.1.1.7 Perform CHANNEL CALIBRATION 18 Months DAECODAM Page 86 of 280 Rev. 37 Radioactive Gaseous Effluent Instrumentation 0 6.2.1.1 I TABLE 6.2-1 I TABLE 7.2-1 NORMAL RANGE RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Instrument 1.0ffgas Stack Monitoring System a. Noble Gas Activity Monitor b ...  
..  
..  
Line 664: Line 514:
.. --.......................................  
.. --.......................................  
-...............  
-...............  
-*******-
-*******-OSR 7.2.1.1.1, OSR 7.2.1.1.5, OSR 7.2.1.1.7 continued Rev. 37 Radioactive Gaseous Effluent Instrumentation 0 6.2.1.1 TABLE 6.2-1 NOTATIONS*  
OSR 7.2.1.1.1, OSR 7.2.1.1.5, OSR 7.2.1.1.7 continued Rev. 37 Radioactive Gaseous Effluent Instrumentation 0 6.2.1.1 TABLE 6.2-1 NOTATIONS*  
<alouring releases via this pathway. (bl Instrumentation shall be OPERABLE and in service except that channels out of service are permitted for the purpose of required tests, checks and calibrations without declaring the channel to be inoperable.
<alouring releases via this pathway.  
(bl Instrumentation shall be OPERABLE and in service except that channels out of service are permitted for the purpose of required tests, checks and calibrations without declaring the channel to be inoperable.
TABLE 7.2-1 NOTATIONS (c) The CHANNEL CALIBRATION shall include the use of a known radioactive source (traceable to the NIST radiation measurement system or other acceptable non-NIST standards) positioned in a reproducible geometry with respect to the sensor and emitting beta and/or gamma radiation in the range measured by the channel in accord with established station calibration procedures.
TABLE 7.2-1 NOTATIONS (c) The CHANNEL CALIBRATION shall include the use of a known radioactive source (traceable to the NIST radiation measurement system or other acceptable non-NIST standards) positioned in a reproducible geometry with respect to the sensor and emitting beta and/or gamma radiation in the range measured by the channel in accord with established station calibration procedures.
Alternatively, after the initial calibration, noble gas activity monitors maybe calibrated by laboratory analyzed gas samples collected and analyzed per Table 7.2-2, item A. (d) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exist: 1.0 Instrument indicates measured levels above the alarm setpoint.
Alternatively, after the initial calibration, noble gas activity monitors maybe calibrated by laboratory analyzed gas samples collected and analyzed per Table 7.2-2, item A. (d) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exist: 1.0 Instrument indicates measured levels above the alarm setpoint.
2.0 Circuit failure.
2.0 Circuit failure. 3.0 Instrument indicates a downscale failure. 4.0 Deleted. DAEC ODAM Page 88 of 280 Rev. 37 Offgas Radioactive Gaseous Effluent Instrumentation 0 6.2.1.2 06.2 0 6.2.1.2 OLCO 6.2.1.2 APPLICABILITY:
3.0 Instrument indicates a downscale failure.
4.0 Deleted.
DAEC ODAM Page 88 of 280 Rev. 37 Offgas Radioactive Gaseous Effluent Instrumentation 0 6.2.1.2 06.2 0 6.2.1.2 OLCO 6.2.1.2 APPLICABILITY:
ACTIONS CONDITION A. One or more channels inoperable.
ACTIONS CONDITION A. One or more channels inoperable.
B. As required by Required Action A.1 and referenced in Table 6.2-2 DAEC ODAM RADIOACTIVE GASEOUS EFFLUENT CONTROLS Offgas Radioactive Gaseous Effluent Instrumentation The Offgas Radioactive Gaseous Effluent Instrumentation for each Function in Table 6.2-2 shall be OPERABLE When the Offgas system is operating.
B. As required by Required Action A.1 and referenced in Table 6.2-2 DAEC ODAM RADIOACTIVE GASEOUS EFFLUENT CONTROLS Offgas Radioactive Gaseous Effluent Instrumentation The Offgas Radioactive Gaseous Effluent Instrumentation for each Function in Table 6.2-2 shall be OPERABLE When the Offgas system is operating.
REQUIRED ACTION COMPLETION TIME A.1 Enter the Condition referenced Immediately in table 6.2-2 for the channel.
REQUIRED ACTION COMPLETION TIME A.1 Enter the Condition referenced Immediately in table 6.2-2 for the channel. B.1 Verify the charcoal bed of the Immediately offgas system is not bypassed.
B.1 Verify the charcoal bed of the Immediately offgas system is not bypassed.
AND B.2 Verify offgas stack noble gas Immediately activity monitor is operable.
AND B.2 Verify offgas stack noble gas Immediately activity monitor is operable.
AND B.3 Restore channel(s) to 30 Days OPERABLE status. (continued)
AND B.3 Restore channel(s) to 30 Days OPERABLE status. (continued)
Line 688: Line 532:
N 0 TE--------------------------------------------
N 0 TE--------------------------------------------
1 n strum en ta ti on shall be OPERABLE and in service except that channels out of service are permitted for the purpose of required tests, checks and calibrations without declaring the channel to be inoperable.
1 n strum en ta ti on shall be OPERABLE and in service except that channels out of service are permitted for the purpose of required tests, checks and calibrations without declaring the channel to be inoperable.
SURVEILLANCE FREQUENCY OSR 7.2.1.2.1 Perform CHANNEL CHECK 24 Hours OSR 7 .2.1.2.2 Perform SOURCE CHECK 30 Days OSR 7.2.1.2.3 Perform CHANNEL FUNCTIONAL TEST 92 Days OSR 7.2.1.2.4 Determine the monitor setpoints in accordance with 92 Days the method described in the ODAM. OSR 7.2.1.2.5 Perform CHANNEL CALIBRATION 18 Months OSR 7.2.1.2.6 Perform FUNCTIONAL TEST of the CHARCOAL 48 Months BED BYPASS VALVE LOGIC SYSTEM DAECODAM Page 91 of 280 Rev. 37 Offgas Radioactive Gaseous Effluent Instrumentation 0 6.2.1.2 TABLE 6.2-2 RADIATION MONITORING INSTRUMENTATION Instrumentation Minimu Conditions Surveillance Requirements m Referenced Channel from s Required Opera bl Action A.1 e Offgas Post-Treatment 1 B OSR 7.2.1.2.1, OSR 7.2.1.2.2, Radiation Monitors (a) OSR 7.2.1.2.3(e>,
SURVEILLANCE FREQUENCY OSR 7.2.1.2.1 Perform CHANNEL CHECK 24 Hours OSR 7 .2.1.2.2 Perform SOURCE CHECK 30 Days OSR 7.2.1.2.3 Perform CHANNEL FUNCTIONAL TEST 92 Days OSR 7.2.1.2.4 Determine the monitor setpoints in accordance with 92 Days the method described in the ODAM. OSR 7.2.1.2.5 Perform CHANNEL CALIBRATION 18 Months OSR 7.2.1.2.6 Perform FUNCTIONAL TEST of the CHARCOAL 48 Months BED BYPASS VALVE LOGIC SYSTEM DAECODAM Page 91 of 280 Rev. 37 Offgas Radioactive Gaseous Effluent Instrumentation 0 6.2.1.2 TABLE 6.2-2 RADIATION MONITORING INSTRUMENTATION Instrumentation Minimu Conditions Surveillance Requirements m Referenced Channel from s Required Opera bl Action A.1 e Offgas Post-Treatment 1 B OSR 7.2.1.2.1, OSR 7.2.1.2.2, Radiation Monitors (a) OSR 7.2.1.2.3(e>, OSR 7.2.1.2.4, OSR 7 .2.1.2.5, OSR 7.2.1.2.6 Offgas Pre-Treatment 1 c OSR 7.2.1.2.1, OSR 7.2.1.2.2, Radiation Monitors (b) OSR 7.2.1.2.3(e), OSR 7.2.1.2.4, OSR 7.2.1.2.5 TABLE 6.2.2 NOTATIONS (a) The monitors shall be set to initiate immediate closure of the charcoal bed bypass valve at a setting equivalent to or below the dose rate limits in ODAM Section 6.2.2. {b) The monitors shall be set to initiate an alarm if the monitor exceeds a trip setting equivalent to 1.0 Ci/sec of noble gases after 30 minutes delay in the offgas holdup line. (e) The CHANNEL FUNCTIONAL TEST for this instrument shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exist: a. Instrument indicates measured levels above the alarm/trip setpoint.  
OSR 7.2.1.2.4, OSR 7 .2.1.2.5, OSR 7.2.1.2.6 Offgas Pre-Treatment 1 c OSR 7.2.1.2.1, OSR 7.2.1.2.2, Radiation Monitors (b) OSR 7.2.1.2.3(e),
: b. Instrument indicates a downscale failure. c. Instrument controls not set in operate mode. DAEC ODAM Page 92 of 280 Rev. 37 Gaseous Effluent Dose Rate 06.2.2 06.2 06.2.2 OLCO 6.2.2 APPLICABILITY:
OSR 7.2.1.2.4, OSR 7.2.1.2.5 TABLE 6.2.2 NOTATIONS (a) The monitors shall be set to initiate immediate closure of the charcoal bed bypass valve at a setting equivalent to or below the dose rate limits in ODAM Section 6.2.2. {b) The monitors shall be set to initiate an alarm if the monitor exceeds a trip setting equivalent to 1.0 Ci/sec of noble gases after 30 minutes delay in the offgas holdup line. (e) The CHANNEL FUNCTIONAL TEST for this instrument shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exist: a. Instrument indicates measured levels above the alarm/trip setpoint.  
: b. Instrument indicates a downscale failure.  
: c. Instrument controls not set in operate mode. DAEC ODAM Page 92 of 280 Rev. 37 Gaseous Effluent Dose Rate 06.2.2 06.2 06.2.2 OLCO 6.2.2 APPLICABILITY:
ACTIONS CONDITION RADIOACTIVE GASEOUS EFFLUENT DOSE RATE Gaseous Effluent Dose Rate The dose rate in the UNRESTRICTED AREA due to the release of gaseous effluents shall not exceed: a. 500 mrem/year to the total body or 3000 mrem/year to skin due to radioactive noble gas; and b. 1500 mrem/year to any organ due to 1-131, 1-133, H-3, and to radioactive particulates having half-lives of 8 days or more. During Releases.
ACTIONS CONDITION RADIOACTIVE GASEOUS EFFLUENT DOSE RATE Gaseous Effluent Dose Rate The dose rate in the UNRESTRICTED AREA due to the release of gaseous effluents shall not exceed: a. 500 mrem/year to the total body or 3000 mrem/year to skin due to radioactive noble gas; and b. 1500 mrem/year to any organ due to 1-131, 1-133, H-3, and to radioactive particulates having half-lives of 8 days or more. During Releases.
REQUIRED ACTION COMPLETION TIME A. Dose rate not within A.1 Reduce the release rate Immediately limits. within limit. DAEC ODAM Page 93 of 280 Rev. 37 Gaseous Effluent Release Concentration 07.2.2 SURVEILLANCE REQUIRMENTS  
REQUIRED ACTION COMPLETION TIME A. Dose rate not within A.1 Reduce the release rate Immediately limits. within limit. DAEC ODAM Page 93 of 280 Rev. 37 Gaseous Effluent Release Concentration 07.2.2 SURVEILLANCE REQUIRMENTS  
Line 698: Line 539:
*Refer to ODAM Table 7.2-2 for details concerning Sampling and Analysis OSR 7.2.2.1 OSR 7.2.2.2 OSR 7.2.2.3 OSR 7.2.2.4 OSR 7.2.2.5 DAEC ODAM SURVEILLANCE Monitor for Radioactive Noble Gas gamma activity.
*Refer to ODAM Table 7.2-2 for details concerning Sampling and Analysis OSR 7.2.2.1 OSR 7.2.2.2 OSR 7.2.2.3 OSR 7.2.2.4 OSR 7.2.2.5 DAEC ODAM SURVEILLANCE Monitor for Radioactive Noble Gas gamma activity.
Sample the Effluent Stream for 1-131. Analyze for 1-131within48 hours of sample pull.
Sample the Effluent Stream for 1-131. Analyze for 1-131within48 hours of sample pull.
Retain samples for Quarterly Composite analysis.  
Retain samples for Quarterly Composite analysis. (OSR 7.2.2.8) Sample the Effluent Stream for particulates.
(OSR 7.2.2.8)
Analyze for principal gamma emitters from particulates within 48 hours of sample pull*. FREQUENCY Continuously Continuously 7 Days Following an increase of more than 50% as indicated by the Treat rad. monitor* Continuously 7 Days Following an increase of more than 50% as indicated by the Treat rad. monitor* Perform gas grab sample of the effluent stream 30 Days and analyze for principal gamma emitters.  
Sample the Effluent Stream for particulates.
Analyze for principal gamma emitters from particulates within 48 hours of sample pull*. FREQUENCY Continuously Continuously 7 Days Following an increase of more than 50% as indicated by the Treat rad. monitor*
Continuously 7 Days Following an increase of more than 50% as indicated by the Treat rad. monitor*
Perform gas grab sample of the effluent stream 30 Days and analyze for principal gamma emitters.  
--------------------------NOTE----------------------
--------------------------NOTE----------------------
Applies only for the Reactor Building and Off gas Stack effluent streams.
Applies only for the Reactor Building and Off gas Stack effluent streams. Perform gas grab sample of the effluent stream and analyze for principal gamma emitters.
Perform gas grab sample of the effluent stream and analyze for principal gamma emitters.
Page 94 of 280 Following an increase of more than 50% as indicated by the Treat rad. monitor (continued)
Page 94 of 280 Following an increase of more than 50% as indicated by the Treat rad. monitor (continued)
Rev. 37 Gaseous Effluent Concentration 07.2.2 SURVEILLANCES (continued)
Rev. 37 Gaseous Effluent Concentration 07.2.2 SURVEILLANCES (continued)
SURVEILLANCE FREQUENCY OSR 7.2.2.6 Perform grab sample of the effluent stream and 92 Days analyze for Tritium.  
SURVEILLANCE FREQUENCY OSR 7.2.2.6 Perform grab sample of the effluent stream and 92 Days analyze for Tritium. ----------------------------
----------------------------
N 0 TE--------------------
N 0 TE--------------------
OSR 7.2.2.7 Applies only for the Reactor Building and Off When the Reactor Head gas Stack effluent streams.
OSR 7.2.2.7 Applies only for the Reactor Building and Off When the Reactor Head gas Stack effluent streams. is removed ---------------------------------------------------------
is removed ---------------------------------------------------------
Perform grab sample of the effluent stream and analyze for Tritium. OSR 7.2.2.8 Analyze Particulate Composite sample for 92 Days Sr-89, Sr-90, Gross Alpha *Refer to ODAM Table 7.2-2 for details concerning Sampling and Analysis DAEC ODAM Page 95 of 280 Rev. 37 Gaseous Effluent Release Concentration 0 7.2.2 TABLE 7.2-2 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Gaseous Release Type Surveillance Frequency Type of Activity Lower Limit of Requirements Analysis Detection (LLD)<al A. Offgas Stack, and Elevated Gas Grab Sample Reactor Building Vent OSR 7.2.2.5 (bl Post-Treat Principal Gamma 1 x 1 o-4<d) Readings (bl Emitters OSR 7.2.2.7 <cl Reactor Head Tritium Grab 1 x 10-5 Removed (c) Sample (H-3) B. Offgas Stack, Reactor Routine OR Building Vent, Turbine OSR 7.2.2.2 <el elevated Charcoal Sample 1 x 10-12 Building Vent, and Post-Treat 1-131 Low-Level Radwaste Readings (fl Processing Storage Routine OR Particulate Sample Facility Vent OSR 7.2.2.3 (el elevated Principal Gamma 1 x 10-11(d) Post-Treat Emitters (1-131, Readings <fl Others) Gas Grab Sample OSR 7.2.2.4 Routine Principal Gamma 1 x 10-4(d) Emitters OSR 7.2.2.6 Routine Tritium Grab 1 x 10-5 Sample (H-3) Composite Particulate Sample 1 x 10-11 OSR 7.2.2.8 <el Routine <9 l Sr-89, Sr-90 Gross Alpha 1 x 10-11 Fe-55 1 x 10-11 C. Offgas Stack, Reactor Building Vent, Turbine Monitor Building Vent, and OSR 7.2.2.1 Continuous Radioactive Noble 1 x 10-5 Low-Level Radwaste Gas gamma Processing and activity Storage Facility TABLE NOTATIONS  
Perform grab sample of the effluent stream and analyze for Tritium.
<al Units for the listed values are &#xb5;Ci/cc. See Table 7.1-2 for a definition of the lower limit of detection (LLD). (bl Monthly analyses shall be performed following an increase of more than 50% in the steady state releases as indicated by the post-treat noble gas activity monitor, after factoring out the effect due to a change in reactor power, or other minor temporary fluctuations not related to fuel integrity such as line up changes for condensate de-mineralizers or reactor water cleanup. (c) A H-3 grab sample will also be taken from the Offgas Stack or Reactor Building Vent when the reactor head is removed. DAECODAM Page 96 of 280 Rev. 37 Gaseous Effluent Concentration 0 7.2.2 (dJ The principal gamma emitters for which the LLD will apply are exclusively the following radionuclides:
OSR 7.2.2.8 Analyze Particulate Composite sample for 92 Days Sr-89, Sr-90, Gross Alpha *Refer to ODAM Table 7.2-2 for details concerning Sampling and Analysis DAEC ODAM Page 95 of 280 Rev. 37 Gaseous Effluent Release Concentration 0 7.2.2 TABLE 7.2-2 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Gaseous Release Type Surveillance Frequency Type of Activity Lower Limit of Requirements Analysis Detection (LLD)<al A. Offgas Stack, and Elevated Gas Grab Sample Reactor Building Vent OSR 7.2.2.5 (bl Post-Treat Principal Gamma 1 x 1 o-4<d) Readings (bl Emitters OSR 7.2.2.7 <cl Reactor Head Tritium Grab 1 x 10-5 Removed (c) Sample (H-3) B. Offgas Stack, Reactor Routine OR Building Vent, Turbine OSR 7.2.2.2 <el elevated Charcoal Sample 1 x 10-12 Building Vent, and Post-Treat 1-131 Low-Level Radwaste Readings (fl Processing Storage Routine OR Particulate Sample Facility Vent OSR 7.2.2.3 (el elevated Principal Gamma 1 x 10-11(d)
Post-Treat Emitters (1-131, Readings  
<fl Others) Gas Grab Sample OSR 7.2.2.4 Routine Principal Gamma 1 x 10-4(d) Emitters OSR 7.2.2.6 Routine Tritium Grab 1 x 10-5 Sample (H-3) Composite Particulate Sample 1 x 10-11 OSR 7.2.2.8 <el Routine <9l Sr-89, Sr-90 Gross Alpha 1 x 10-11 Fe-55 1 x 10-11 C. Offgas Stack, Reactor Building Vent, Turbine Monitor Building Vent, and OSR 7.2.2.1 Continuous Radioactive Noble 1 x 10-5 Low-Level Radwaste Gas gamma Processing and activity Storage Facility TABLE NOTATIONS  
<al Units for the listed values are &#xb5;Ci/cc. See Table 7.1-2 for a definition of the lower limit of detection (LLD). (bl Monthly analyses shall be performed following an increase of more than 50% in the steady state releases as indicated by the post-treat noble gas activity  
: monitor, after factoring out the effect due to a change in reactor power, or other minor temporary fluctuations not related to fuel integrity such as line up changes for condensate de-mineralizers or reactor water cleanup.  
(c) A H-3 grab sample will also be taken from the Offgas Stack or Reactor Building Vent when the reactor head is removed.
DAECODAM Page 96 of 280 Rev. 37 Gaseous Effluent Concentration 0 7.2.2 (dJ The principal gamma emitters for which the LLD will apply are exclusively the following radionuclides:
Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99,Cs--134, Cs-137, Ce-141 and Ce-144 for particulate emissions.
Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99,Cs--134, Cs-137, Ce-141 and Ce-144 for particulate emissions.
This list does not mean that only these nuclides are to be detected and reported.
This list does not mean that only these nuclides are to be detected and reported.
Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported.
Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported.
Nuclides which are below the LLD may be reported as "less than" their respective LLD and should not be reported as being present at the LLD of the nuclide.
Nuclides which are below the LLD may be reported as "less than" their respective LLD and should not be reported as being present at the LLD of the nuclide. Each measured radionuclide concentration is used in a required concentration or dose calculation only if it is detected at or above the LLD. When unusual circumstances persist more than 30 days and cause LLD higher than required, the reasons shall be documented in the Annual Radioactive Material Release Report. (e) The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculations made in accordance with Sections 6.2.2, 6.2.3, and 6.2.4. <IJ Sample media shall be changed at least once per seven days and the analysis completed within 48 hours after changing (or after removal from the sampler).
Each measured radionuclide concentration is used in a required concentration or dose calculation only if it is detected at or above the LLD. When unusual circumstances persist more than 30 days and cause LLD higher than required, the reasons shall be documented in the Annual Radioactive Material Release Report. (e) The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculations made in accordance with Sections 6.2.2, 6.2.3, and 6.2.4. <IJ Sample media shall be changed at least once per seven days and the analysis completed within 48 hours after changing (or after removal from the sampler).
Analyses shall also be performed within 48 hours following an increase of more than 50% in the steady state release as indicated by the post-treat noble gas activity monitor, after factoring out the effect due to a change in reactor power. When samples collected for 24 hours or less are analyzed, the corresponding LLD may be increased by a factor of 10. <9 l A quarterly composite sample shall include an equal fraction of each weekly particulate sample collected during the quarter. DAECODAM Page 97 of 280 Rev. 37 Doses Due to Noble Gases 0 6.2.3 0 6.2 RADIOACTIVE GASEOUS EFFLUENT CONTROLS 06.2.3 Doses Due to Noble Gases OLCO 6.2.3 The Air Dose in the UNRESTRICTED AREA due to noble gases released in gaseous effluents shall not exceed: APPLICABILITY:
Analyses shall also be performed within 48 hours following an increase of more than 50% in the steady state release as indicated by the post-treat noble gas activity  
: monitor, after factoring out the effect due to a change in reactor power. When samples collected for 24 hours or less are analyzed, the corresponding LLD may be increased by a factor of 10. <9l A quarterly composite sample shall include an equal fraction of each weekly particulate sample collected during the quarter.
DAECODAM Page 97 of 280 Rev. 37 Doses Due to Noble Gases 0 6.2.3 0 6.2 RADIOACTIVE GASEOUS EFFLUENT CONTROLS 06.2.3 Doses Due to Noble Gases OLCO 6.2.3 The Air Dose in the UNRESTRICTED AREA due to noble gases released in gaseous effluents shall not exceed: APPLICABILITY:
ACTIONS 5.0 mrad from gamma radiation during any calendar quarter; 10.0 mrad from beta radiation during any calendar quarter; 10.0 mrad from gamma radiation during any calendar year; or 20.0 mrad from beta radiation during any calendar year. During Releases CONDITION REQUIRED ACTION COMPLETION TIME A. Calculated air dose not within limits. DAEC ODAM A.1 Submit a Special Report to 30 days the NRC identifying the cause(s) for exceeding the limit and define the corrective actions taken. Page 98 of 280 Rev. 37 Doses Due to Noble Gases 0 7.2.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY OSR 7.2.3.1 An assessment shall be performed in accordance 30 Days with the ODAM to verify that the cumulative air dose during the quarter and year due to noble gases does not exceed the limits in ODAM section 6.2.3. DAEC ODAM Page 99 of 280 Rev. 37 Doses Due to Iodine and Particulates in Air 0 6.2.4 0 6.2 0 6.2.4 OLCO 6.2.4 APPLICABILITY:
ACTIONS 5.0 mrad from gamma radiation during any calendar quarter; 10.0 mrad from beta radiation during any calendar quarter; 10.0 mrad from gamma radiation during any calendar year; or 20.0 mrad from beta radiation during any calendar year. During Releases CONDITION REQUIRED ACTION COMPLETION TIME A. Calculated air dose not within limits. DAEC ODAM A.1 Submit a Special Report to 30 days the NRC identifying the cause(s) for exceeding the limit and define the corrective actions taken. Page 98 of 280 Rev. 37 Doses Due to Noble Gases 0 7.2.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY OSR 7.2.3.1 An assessment shall be performed in accordance 30 Days with the ODAM to verify that the cumulative air dose during the quarter and year due to noble gases does not exceed the limits in ODAM section 6.2.3. DAEC ODAM Page 99 of 280 Rev. 37 Doses Due to Iodine and Particulates in Air 0 6.2.4 0 6.2 0 6.2.4 OLCO 6.2.4 APPLICABILITY:
ACTIONS CONDITION RADIOACTIVE GASEOUS EFFLUENT CONTROLS Doses Due to Iodine and Particulates in Air The dose to a MEMBER OF THE PUBLIC from lodine-131, 1-133, H-3, and from radionuclides in particulate form having half-lives greater than eight days in gaseous effluents released from the site to the UNRESTRICTED AREA shall not exceed: 7.5 mrem to any organ during any calendar quarter; or 15.0 mrem to any organ during any calendar year. During Releases.
ACTIONS CONDITION RADIOACTIVE GASEOUS EFFLUENT CONTROLS Doses Due to Iodine and Particulates in Air The dose to a MEMBER OF THE PUBLIC from lodine-131, 1-133, H-3, and from radionuclides in particulate form having half-lives greater than eight days in gaseous effluents released from the site to the UNRESTRICTED AREA shall not exceed: 7.5 mrem to any organ during any calendar quarter; or 15.0 mrem to any organ during any calendar year. During Releases.
Line 735: Line 560:
APPLICABILITY:
APPLICABILITY:
During Offgas System operation.
During Offgas System operation.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. No Offgas System A.1 Restore Offgas System 7 days charcoal beds in charcoal bed to service.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. No Offgas System A.1 Restore Offgas System 7 days charcoal beds in charcoal bed to service. service. ----------NOTE---------
service.  
Not applicable until after 4 hours of commencing operation of the main condenser air ejector. --------------------------
----------NOTE---------
Not applicable until after 4 hours of commencing operation of the main condenser air ejector.  
--------------------------
B. Required Action and B.1 Submit a Special Report to 30 days associated Completion the NRC identifying the Time not met. inoperable equipment or subsystem and reason for inoperability, actions taken to prevent a recurrence.
B. Required Action and B.1 Submit a Special Report to 30 days associated Completion the NRC identifying the Time not met. inoperable equipment or subsystem and reason for inoperability, actions taken to prevent a recurrence.
DAECODAM Page 102 of 280 Rev. 37 Gaseous Radwaste Treatment 0 7.2.5 SURVEILLANCE REQUIREMENTS OSR 7.2.5.1 SURVEILLANCE The gaseous effluent monitoring systems of ODAM N/A Sections 6.2.1 and 7.2.1 shall be used to verify the operation of the Offgas system. FREQUENCY DAECODAM Page 103 of 280 Rev. 37 Mechanical Vacuum Pump Radiation Release Rate 06.2.6 06.2 06.2.6 OLCO 6.2.6 APPLICABILITY:
DAECODAM Page 102 of 280 Rev. 37 Gaseous Radwaste Treatment 0 7.2.5 SURVEILLANCE REQUIREMENTS OSR 7.2.5.1 SURVEILLANCE The gaseous effluent monitoring systems of ODAM N/A Sections 6.2.1 and 7.2.1 shall be used to verify the operation of the Offgas system. FREQUENCY DAECODAM Page 103 of 280 Rev. 37 Mechanical Vacuum Pump Radiation Release Rate 06.2.6 06.2 06.2.6 OLCO 6.2.6 APPLICABILITY:
Line 745: Line 567:
During mechanical vacuum pump operation.
During mechanical vacuum pump operation.
REQUIRED ACTION COMPLETION TIME A. Radioactive release rate not within limit. A.1 Restore radioactive release rate to within limits. Immediately DAEC ODAM Page 104 of 280 Rev. 37 Dose 0 6.3.1 SURVEILLANCE REQUIREMENTS OSR 7.2.6.1 DAEC ODAM SURVEILLANCE The gaseous effluent monitoring systems of ODAM Sections 6.2.1 and 7.2.1 shall be used to verify the operation of the Offgas system. Page 105 of 280 FREQUENCY N/A Rev. 37 Dose 0 6.3.1 06.3 0 6.3.1 OLCO 6.3.1 APPLICABILITY:
REQUIRED ACTION COMPLETION TIME A. Radioactive release rate not within limit. A.1 Restore radioactive release rate to within limits. Immediately DAEC ODAM Page 104 of 280 Rev. 37 Dose 0 6.3.1 SURVEILLANCE REQUIREMENTS OSR 7.2.6.1 DAEC ODAM SURVEILLANCE The gaseous effluent monitoring systems of ODAM Sections 6.2.1 and 7.2.1 shall be used to verify the operation of the Offgas system. Page 105 of 280 FREQUENCY N/A Rev. 37 Dose 0 6.3.1 06.3 0 6.3.1 OLCO 6.3.1 APPLICABILITY:
ACTIONS CONDITION A. Calculated dose from radioactive OFFSITE DOSE ASSESSMENT CONTROLS Dose The annual dose or dose commitment to any MEMBER OF THE PUBLIC due to radiation and radioactive material in effluents from DAEC shall not exceed 75 mrem to the thyroid or 25 mrem to the total body or any other organ. At all times. REQUIRED ACTION COMPLETION TIME A.1 Perform an assessment of compliance 7 days with 40 CFR 190 and material released in 10 CFR 72.104 and limit subsequent liquid or gaseous releases such that the dose or dose effluents exceeds commitment to a MEMBER OF THE twice the limits of PUBLIC is ::;,75 mrem to his thyroid Sections 6.1.3, 6.2.3 and ::;,25 mrem to his total body or any or 6.2.4 other organ over 12 consecutive months including the period of elevated release.
ACTIONS CONDITION A. Calculated dose from radioactive OFFSITE DOSE ASSESSMENT CONTROLS Dose The annual dose or dose commitment to any MEMBER OF THE PUBLIC due to radiation and radioactive material in effluents from DAEC shall not exceed 75 mrem to the thyroid or 25 mrem to the total body or any other organ. At all times. REQUIRED ACTION COMPLETION TIME A.1 Perform an assessment of compliance 7 days with 40 CFR 190 and material released in 10 CFR 72.104 and limit subsequent liquid or gaseous releases such that the dose or dose effluents exceeds commitment to a MEMBER OF THE twice the limits of PUBLIC is ::;,75 mrem to his thyroid Sections 6.1.3, 6.2.3 and ::;,25 mrem to his total body or any or 6.2.4 other organ over 12 consecutive months including the period of elevated release. B. The estimated dose B.1 Prepare and submit a Special Report 30 days exceeds either limit to the NRC in lieu of any other report; in Section 6.3.1. it shall include the cause of the release of exposure, an estimate of the dose to the likely most exposed MEMBER(s)
B. The estimated dose B.1 Prepare and submit a Special Report 30 days exceeds either limit to the NRC in lieu of any other report; in Section 6.3.1. it shall include the cause of the release of exposure, an estimate of the dose to the likely most exposed MEMBER(s)
OF THE PUBLIC, corrective actions taken or planned to prevent a recurrence, and a schedule for achieving compliance.
OF THE PUBLIC, corrective actions taken or planned to prevent a recurrence, and a schedule for achieving compliance.
If the condition causing the limit(s) to be exceeded has not been corrected, the Special Report may also state a request for a variance in accordance with the provisions of 40 CFR Part 190. In that event, the request is timely and a variance is granted until NRC action on the request is complete.
If the condition causing the limit(s) to be exceeded has not been corrected, the Special Report may also state a request for a variance in accordance with the provisions of 40 CFR Part 190. In that event, the request is timely and a variance is granted until NRC action on the request is complete.
DAEC ODAM Page 106 of 280 Rev. 37 Dose 0 7.3.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY OSR 7.3.1.1 Cumulative dose contributions from liquid and 12 Months gaseous effluents to a MEMBER OF THE PUBLIC offsite shall be evaluated as described in the ODAM. DAEC ODAM Page 107 of 280 Rev. 37 Radiological Environmental Monitoring Program 06.3.2 06.3 OFFSITE DOSE ASSESSMENT CONTROLS 0 6.3.2 Radiological Environmental Monitoring Program (REMP) Ground Water Protection Program (GWPP) OLCO 6.3.2 A radiological environmental monitoring program shall be conducted as specified in Table 6.3-1. APPLICABILITY:
DAEC ODAM Page 106 of 280 Rev. 37 Dose 0 7.3.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY OSR 7.3.1.1 Cumulative dose contributions from liquid and 12 Months gaseous effluents to a MEMBER OF THE PUBLIC offsite shall be evaluated as described in the ODAM. DAEC ODAM Page 107 of 280 Rev. 37 Radiological Environmental Monitoring Program 06.3.2 06.3 OFFSITE DOSE ASSESSMENT CONTROLS 0 6.3.2 Radiological Environmental Monitoring Program (REMP) Ground Water Protection Program (GWPP) OLCO 6.3.2 A radiological environmental monitoring program shall be conducted as specified in Table 6.3-1. APPLICABILITY:
At all times. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Deviation from Table A.1 Deviations are permitted from Table Once per year 6.3-1 6.3-1 if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment and other legitimate reasons.
At all times. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Deviation from Table A.1 Deviations are permitted from Table Once per year 6.3-1 6.3-1 if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment and other legitimate reasons. If specimens are unobtainable due to sampling equipment malfunction, every effort shall be made to complete corrective action prior to the end of the next sampling period. All deviations from Table 6.3-1 shall be documented in the Annual Radiological Environmental Report. B. In the event B.1 Prepare and submit to the Commission 30 Days radioactivity in a within 30 days after discovery a Special sampled Report which includes an evaluation of environmental any release conditions, environmental medium, averaged factors or other conditions which over a calendar caused the value(s) of Table 6.3-3 or quarter, is two times the quarterly dose limit to be attributable to DAEC exceeded and which defines the and exceeds an corrective actions to be taken. If the appropriate value radioactivity in environmental sample(s) listed in Table 6.3-3 is not attributable to releases from the or, if not listed, Station, the Special Report is not causes a potential required.
If specimens are unobtainable due to sampling equipment malfunction, every effort shall be made to complete corrective action prior to the end of the next sampling period. All deviations from Table 6.3-1 shall be documented in the Annual Radiological Environmental Report. B. In the event B.1 Prepare and submit to the Commission 30 Days radioactivity in a within 30 days after discovery a Special sampled Report which includes an evaluation of environmental any release conditions, environmental medium, averaged factors or other conditions which over a calendar caused the value(s) of Table 6.3-3 or quarter, is two times the quarterly dose limit to be attributable to DAEC exceeded and which defines the and exceeds an corrective actions to be taken. If the appropriate value radioactivity in environmental sample(s) listed in Table 6.3-3 is not attributable to releases from the or, if not listed, Station, the Special Report is not causes a potential required.  
Instead, the sample(s) annual dose result(s) shall be reported and exceeding two times explained in the Annual Radiological the quarterly dose Environmental Report. limit in Section 6.1.3 or 6.2.4 (continued)
: Instead, the sample(s) annual dose result(s) shall be reported and exceeding two times explained in the Annual Radiological the quarterly dose Environmental Report. limit in Section 6.1.3 or 6.2.4 (continued)
DAEC ODAM Page 108 of 280 Rev. 37 ACTIONS (continued)
DAEC ODAM Page 108 of 280 Rev. 37 ACTIONS (continued)
CONDITION C. When C.1 environmental sampling medium is not available from a sampling location or the location is no longer appropriate.
CONDITION C. When C.1 environmental sampling medium is not available from a sampling location or the location is no longer appropriate.
D. A location is D.1 identified at which the calculated personal dose associated with one or more exposure pathways exceeds by 20% the maximum calculated dose associated with like pathway(
D. A location is D.1 identified at which the calculated personal dose associated with one or more exposure pathways exceeds by 20% the maximum calculated dose associated with like pathway( s) at a location where sampling is conducted as specified by Table 6.3-1 DAECODAM Radiological Environmental Monitoring Program 0 6.3.2 REQUIRED ACTION COMPLETION TIME The cause and the location where Once per year replacement samples were obtained and/or will be obtained shall be reported in the Annual Radiological Environmental Report. The pathway(s) having maximum Once per year exposure potential at the newly identified location will be added to the radiological monitoring program at a subsequent Operations Committee meeting, if samples are reasonably attainable at the new location.
s) at a location where sampling is conducted as specified by Table 6.3-1 DAECODAM Radiological Environmental Monitoring Program 0 6.3.2 REQUIRED ACTION COMPLETION TIME The cause and the location where Once per year replacement samples were obtained and/or will be obtained shall be reported in the Annual Radiological Environmental Report. The pathway(s) having maximum Once per year exposure potential at the newly identified location will be added to the radiological monitoring program at a subsequent Operations Committee  
Like pathway(s) monitored (sampled) at a location, excluding the control station location(s), having a lesser associated calculated personal dose may be deleted from the program at the time the new pathway(s) and location are added. Page 109 of 280 Rev. 37 Radiological Environmental Monitoring Program 0 7.3.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY OSR 7.3.2.1 Sampling and analyses required in Table 6.3-1 12 Months shall be performed such that the detection capabilities specified in Table 6.3-2 are achieved under routine conditions.
: meeting, if samples are reasonably attainable at the new location.
If a sample analysis does not meet the LLD specified, report the reason attributed in the next Annual Radiological Environmental Report. OSR 7.3.2.2 DAEC shall conduct annually a land use census 12 Months within three miles of the Station to identify radiologically important changes in land use. DAEC ODAM Page 110 of 280 Rev. 37 Radiological Environmental Monitoring Program 0 6.3.2 TABLE 6.3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Minimum Sampling and Type and Frequency of Analysis Pathway and/or Number of Collection Schedule (a) Sample Type Sampling Stations Airborne Five Continuous operation of sampler with Analyze for gross beta activity 2 72 hours Particulates sample collection WEEKLY or as required after filter change. by dust loading Perform gamma isotopic analysis on each sample having gross beta activity > 10 times the yearly mean of control samples. Perform gamma isotopic analysis on composite (by sampling location) of samples collected during each quarter Airborne Iodine Five Continuous operation of sampler with Analyze each cartridge for 1-131 within sample collection WEEKLY 8 days of collection.
Like pathway(s) monitored (sampled) at a location, excluding the control station location(s),
having a lesser associated calculated personal dose may be deleted from the program at the time the new pathway(s) and location are added. Page 109 of 280 Rev. 37 Radiological Environmental Monitoring Program 0 7.3.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY OSR 7.3.2.1 Sampling and analyses required in Table 6.3-1 12 Months shall be performed such that the detection capabilities specified in Table 6.3-2 are achieved under routine conditions.
If a sample analysis does not meet the LLD specified, report the reason attributed in the next Annual Radiological Environmental Report. OSR 7.3.2.2 DAEC shall conduct annually a land use census 12 Months within three miles of the Station to identify radiologically important changes in land use. DAEC ODAM Page 110 of 280 Rev. 37 Radiological Environmental Monitoring Program 0 6.3.2 TABLE 6.3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Minimum Sampling and Type and Frequency of Analysis Pathway and/or Number of Collection Schedule (a) Sample Type Sampling Stations Airborne Five Continuous operation of sampler with Analyze for gross beta activity 2 72 hours Particulates sample collection WEEKLY or as required after filter change. by dust loading Perform gamma isotopic analysis on each sample having gross beta activity  
> 10 times the yearly mean of control samples.
Perform gamma isotopic analysis on composite (by sampling location) of samples collected during each quarter Airborne Iodine Five Continuous operation of sampler with Analyze each cartridge for 1-131 within sample collection WEEKLY 8 days of collection.
Ambient Forty two QUARTERLY Read gamma radiation dose quarterly.
Ambient Forty two QUARTERLY Read gamma radiation dose quarterly.
Radiation Surface Water Three MONTHLY Tritium and Gamma isotopic analysis of each sample. Drinking Water Three MONTHLY Tritium and Gamma isotopic analysis of each sample. If reactor by-product gamma emitters are identified, OR tritium concentration is >MDA, then analyze, Sr-89, Sr-90, Fe-55 and alpha emitters.
Radiation Surface Water Three MONTHLY Tritium and Gamma isotopic analysis of each sample. Drinking Water Three MONTHLY Tritium and Gamma isotopic analysis of each sample. If reactor by-product gamma emitters are identified, OR tritium concentration is >MDA, then analyze, Sr-89, Sr-90, Fe-55 and alpha emitters.
Ground Water Six QUARTERLY Tritium and Gamma isotopic analysis of each sample. If reactor by-product gamma emitters are identified, OR tritium concentration is > MDA, then analyze for Sr-89, Sr-90, Fe-55 and alpha emitters.
Ground Water Six QUARTERLY Tritium and Gamma isotopic analysis of each sample. If reactor by-product gamma emitters are identified, OR tritium concentration is > MDA, then analyze for Sr-89, Sr-90, Fe-55 and alpha emitters.
River Sediment One SEMIANNUALLY Gamma isotopic analysis of each sample. Milk Two MONTHLY for dairy cattle and when Gamma isotopic and 1-131 analysis of each available for goat milk. sample. Fish Two SEMIANNUALLY Gamma isotopic analysis on edible portion.
River Sediment One SEMIANNUALLY Gamma isotopic analysis of each sample. Milk Two MONTHLY for dairy cattle and when Gamma isotopic and 1-131 analysis of each available for goat milk. sample. Fish Two SEMIANNUALLY Gamma isotopic analysis on edible portion. Vegetation Six ANNUALLY at harvest time. At least two Gamma isotopic and 1-131 analysis of each samples of each: sample. grain green leafy vegetation foraqe. \8) .. -The following definitions of schedule timing shall apply to Table 6.3 1 only. WEEKLY -Not less than once per calendar week. A maximum interval of 11 days is allowed between the collection of any two consecutive samples. BIWEEKLY -Not less than once every two calendar weeks. A maximum interval of 18 days is allowed between the collection of any two consecutive samples. MONTHLY -Not less than once per calendar month. An interval of not less than 10 days will be provided between collection of any two consecutive samples. QUARTERLY  
Vegetation Six ANNUALLY at harvest time. At least two Gamma isotopic and 1-131 analysis of each samples of each: sample. grain green leafy vegetation foraqe. \8) .. -The following definitions of schedule timing shall apply to Table 6.3 1 only. WEEKLY -Not less than once per calendar week. A maximum interval of 11 days is allowed between the collection of any two consecutive samples.
-Not less than once per calendar quarter. An interval of not less than 30 days will be provided between collection of any two consecutive samples. SEMIANNUALLY  
BIWEEKLY  
-One sample each between calendar dates (January 1 -June 30) and (July 1 -December 31). An interval of not less than 60 days will be provided between collection of any two consecutive samples. ANNUALLY -Not less than once per calendar year with an interval of not less than 120 days between collection of any two consecutive samples. DAECODAM Page 111 of 280 Rev. 37 TABLE 6.3-2 Radiological Environmental Monitoring Program 06.3.2 GROUNDWATER PROTECTION PROGRAM Exposure Pathway Minimum Sampling and !rype and Frequency of Analysis and/or Sample Number of Collection Schedule (a) Type Sampling Stations Groundwater Forty (b) QUARTERLY Tritium and Gamma isotopic analysis of each sample. If reactor by-product gamma emitters are identified, OR tritium concentration is >MDA, then analyze for Sr-89, Sr-90, Fe-55 and alpha emitters.
-Not less than once every two calendar weeks. A maximum interval of 18 days is allowed between the collection of any two consecutive samples.
MONTHLY -Not less than once per calendar month. An interval of not less than 10 days will be provided between collection of any two consecutive samples.
QUARTERLY  
-Not less than once per calendar quarter.
An interval of not less than 30 days will be provided between collection of any two consecutive samples.
SEMIANNUALLY  
-One sample each between calendar dates (January 1 -June 30) and (July 1 -December 31). An interval of not less than 60 days will be provided between collection of any two consecutive samples.
ANNUALLY  
-Not less than once per calendar year with an interval of not less than 120 days between collection of any two consecutive samples.
DAECODAM Page 111 of 280 Rev. 37 TABLE 6.3-2 Radiological Environmental Monitoring Program 06.3.2 GROUNDWATER PROTECTION PROGRAM Exposure Pathway Minimum Sampling and !rype and Frequency of Analysis and/or Sample Number of Collection Schedule (a) Type Sampling Stations Groundwater Forty (b) QUARTERLY Tritium and Gamma isotopic analysis of each sample. If reactor by-product gamma emitters are identified, OR tritium concentration is >MDA, then analyze for Sr-89, Sr-90, Fe-55 and alpha emitters.
Groundwater One (c) MONTHLY Tritium and Gamma isotopic analysis of Conditional each sample. If reactor by-product gamma emitters are identified, OR tritium concentration is >MDA, then analyze for Sr-89, Sr-90, Fe-55 and alpha emitters.
Groundwater One (c) MONTHLY Tritium and Gamma isotopic analysis of Conditional each sample. If reactor by-product gamma emitters are identified, OR tritium concentration is >MDA, then analyze for Sr-89, Sr-90, Fe-55 and alpha emitters.
Soil Two ANNUALLY  
Soil Two ANNUALLY Tritium, Gamma isotopic and Strontium-90 Precipitation Four MONTHLY Tritium and Gamma isotopic analysis of each samole. Electrical Vaults One SEMIANNUALLY Tritium and Gamma isotopic analysis of each sample. DAEC Sewage One BIWEEKLY Tritium and Gamma isotopic analysis of Plant Effluent each sample. (a)The following definitions of schedule timing shall apply to Table 6.3-2 only: WEEKLY -At least once per calendar week. BIWEEKLY -Not less than once every two calendar weeks. A maximum interval of 18 days is allowed between the collection of any two consecutive samples. MONTHLY -Not less than once per calendar month. An interval of not less than 10 days will be provided between collection of any two consecutive samples. QUARTERLY  
: Tritium, Gamma isotopic and Strontium-90 Precipitation Four MONTHLY Tritium and Gamma isotopic analysis of each samole. Electrical Vaults One SEMIANNUALLY Tritium and Gamma isotopic analysis of each sample. DAEC Sewage One BIWEEKLY Tritium and Gamma isotopic analysis of Plant Effluent each sample. (a)The following definitions of schedule timing shall apply to Table 6.3-2 only: WEEKLY -At least once per calendar week. BIWEEKLY  
-Not less than once per calendar quarter. An interval of not less than 30 days will be provided between collection of any two consecutive samples. SEMIANNUALLY  
-Not less than once every two calendar weeks. A maximum interval of 18 days is allowed between the collection of any two consecutive samples.
-One sample each between calendar dates (January 1 -June 30) and (July 1 -December 31). An interval of not less than 60 days will be provided between collection of any two consecutive samples. ANNUALLY -Not less than once per calendar year with an interval of not less than 120 days between collection of any two consecutive samples. (b)As of January 1, 2017, fifty-six groundwater wells are operational.  
MONTHLY -Not less than once per calendar month. An interval of not less than 10 days will be provided between collection of any two consecutive samples.
<0>The number of conditional wells sampled in a calendar month depends upon identified isotope, concentration of isotope, targeted aquifer, and extraction well operations.
QUARTERLY  
DAEC ODAM Page 112 of 280 Rev. 37 Radiological Environmental Monitoring Program 06.3.2 TABLE 6.3-3 MAXIMUM VALUES OF THE LOWER LIMIT OF DETECTION FOR ENVIRONMENTAL SAMPLE ANALYSIS <a> Analysis Medium Water Airborne Fish Milk (pCi/L) Food Sediment (pCi/L) Particulate or (pCi/kg, Products (pCi/kg, dry) Gas (pCi/m 3) wet) (pCi/kg, wet) Gross beta 4 1 x 10-2 H-3 2000 (DJ 3000 (c) Mn-54 15 130 Fe-59 30 260 Co-58, Co-15 130 60 Zn-65 30 260 Zr-95 30 Nb-95 15 1-131 1 (d) 7 x 10-2 1 60 Cs-134 15 5 x 10-2 130 15 60 150 Cs-137 18 6x10-2 150 18 80 180 Ba-140 60 60 La-140 15 15 TABLE NOTATIONS Table 6.3-2 (a) The LLD is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a new count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal. For a particular measurement, which may include radiochemical separation LLD= (4.66Sb)/(E
-Not less than once per calendar quarter.
An interval of not less than 30 days will be provided between collection of any two consecutive samples.
SEMIANNUALLY  
-One sample each between calendar dates (January 1 -June 30) and (July 1 -December 31). An interval of not less than 60 days will be provided between collection of any two consecutive samples.
ANNUALLY  
-Not less than once per calendar year with an interval of not less than 120 days between collection of any two consecutive samples.  
(b)As of January 1, 2017, fifty-six groundwater wells are operational.  
<0>The number of conditional wells sampled in a calendar month depends upon identified  
: isotope, concentration of isotope, targeted  
: aquifer, and extraction well operations.
DAEC ODAM Page 112 of 280 Rev. 37 Radiological Environmental Monitoring Program 06.3.2 TABLE 6.3-3 MAXIMUM VALUES OF THE LOWER LIMIT OF DETECTION FOR ENVIRONMENTAL SAMPLE ANALYSIS  
<a> Analysis Medium Water Airborne Fish Milk (pCi/L) Food Sediment (pCi/L) Particulate or (pCi/kg, Products (pCi/kg, dry) Gas (pCi/m3) wet) (pCi/kg, wet) Gross beta 4 1 x 10-2 H-3 2000 (DJ 3000 (c) Mn-54 15 130 Fe-59 30 260 Co-58, Co-15 130 60 Zn-65 30 260 Zr-95 30 Nb-95 15 1-131 1 (d) 7 x 10-2 1 60 Cs-134 15 5 x 10-2 130 15 60 150 Cs-137 18 6x10-2 150 18 80 180 Ba-140 60 60 La-140 15 15 TABLE NOTATIONS Table 6.3-2 (a) The LLD is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a new count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal. For a particular measurement, which may include radiochemical separation LLD= (4.66Sb)/(E
* V
* V
* 2.22
* 2.22
* Y
* Y
* e -i."1) where:
* e -i." 1) where:
* LLD is the lower limit of detection as defined above (picocuries per unit mass or volume)
* LLD is the lower limit of detection as defined above (picocuries per unit mass or volume)
* Sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute)
* Sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute)
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* A is the radioactive decay constant for the particular radionuclide, and D
* A is the radioactive decay constant for the particular radionuclide, and D
* t for environmental samples is the elapsed time between sample collection, or end of the sample collection period, and time of counting Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions.
* t for environmental samples is the elapsed time between sample collection, or end of the sample collection period, and time of counting Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions.
With typical values of E, V, Y, and Llt for the radionuclides named in the Table. Occasionally background fluctuations, unavoidably small sample sizes, the presence of interfering  
With typical values of E, V, Y, and Llt for the radionuclides named in the Table. Occasionally background fluctuations, unavoidably small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable.
: nuclides, or other uncontrollable circumstances may render these LLDs unachievable.
In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Report. continued DAEC ODAM Page 113 of 280 Rev. 37 Radiological Environmental Monitoring Program 0 6.3.2 When a radionuclide attributable to DAEC but not listed in this table is measured it shall be reported. (b) For Drinking Water. (c) For samples of water not used as a source of drinking water. (d) If no drinking water pathway exists, a value of 15 pCi/I may be used. DAEC ODAM Page 114 of 280 Rev. 37 Radiological Environmental Monitoring Program 0 6.3.2 TABLE 6.3-4 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Reporting Levels<a>
In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Report. continued DAEC ODAM Page 113 of 280 Rev. 37 Radiological Environmental Monitoring Program 0 6.3.2 When a radionuclide attributable to DAEC but not listed in this table is measured it shall be reported.  
(b) For Drinking Water. (c) For samples of water not used as a source of drinking water. (d) If no drinking water pathway exists, a value of 15 pCi/I may be used. DAEC ODAM Page 114 of 280 Rev. 37 Radiological Environmental Monitoring Program 0 6.3.2 TABLE 6.3-4 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Reporting Levels<a>
Analysi Water Airborne Fish Milk Food Products s (pCi/liter)
Analysi Water Airborne Fish Milk Food Products s (pCi/liter)
Particulate (pCi/Kg, wet) (pCi/liter)  
Particulate (pCi/Kg, wet) (pCi/liter) (pCi/Kg, wet) or Gases (pCi/m 3) H-3 2 x 10 4 (b) 3 X 10 4 (c) Mn-54 1 x 10 3 3 x 10 4 Fe-59 4 x 10 2 1 x 10 4 Co-58 1 x 10 3 3 x 10 4 Co-60 3x10 2 1 x 10 4 Zn-65 3x10 2 2x10 4 Zr-4 X 10 2 (c) Nb95 1-131 2d 0.9 3 1 x 10 2 Cs-134 30 10 1 x 10 3 60 1 x 10 3 Cs-137 50 20 2 x 10 3 70 2 x 10 3 Ba-2 X 10 2 (e) 3 X 10 2 (e) La140 TABLE NOTATIONS Table 6.3-3 <a>The reporting level is exceeded when one or more radionuclides are detected in a sample and l:[(concentration)/(reporting level)] :=:: 1. (b)For drinking water samples. This is 40 CFR Part 141 value. <c>For samples of water not used as a source of drinking water. (dllf no drinking water pathway exists, a value of 20 pCi/I may be used. <e>concentration of parent or daughter.
(pCi/Kg, wet) or Gases (pCi/m3) H-3 2 x 104(b) 3 X 104(c) Mn-54 1 x 103 3 x 104 Fe-59 4 x 102 1 x 104 Co-58 1 x 103 3 x 104 Co-60 3x102 1 x 104 Zn-65 3x102 2x104 Zr-4 X 102(c) Nb95 1-131 2d 0.9 3 1 x 102 Cs-134 30 10 1 x 103 60 1 x 103 Cs-137 50 20 2 x 103 70 2 x 103 Ba-2 X 102(e) 3 X 102(e) La140 TABLE NOTATIONS Table 6.3-3 <a>The reporting level is exceeded when one or more radionuclides are detected in a sample and l:[(concentration)/(reporting level)] :=:: 1. (b)For drinking water samples.
This is 40 CFR Part 141 value. <c>For samples of water not used as a source of drinking water. (dllf no drinking water pathway exists, a value of 20 pCi/I may be used. <e>concentration of parent or daughter.
DAEC ODAM Page 115 of 280 Rev. 37 BASES BASES SECTION 6.1 / 7.1 6.1.1 Radioactive Liquid Effluent Instrumentation  
DAEC ODAM Page 115 of 280 Rev. 37 BASES BASES SECTION 6.1 / 7.1 6.1.1 Radioactive Liquid Effluent Instrumentation  
/7.1.1 DAEC ODAM The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the release of radioactive material in liquid effluents.
/7.1.1 DAEC ODAM The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the release of radioactive material in liquid effluents.
Line 822: Line 611:
Instrumentation is expected to be OPERABLE and in service when required by controls.
Instrumentation is expected to be OPERABLE and in service when required by controls.
An instrument may be removed from service voluntarily for the purpose of tests, checks, or calibration, without declaring the channel inoperable.
An instrument may be removed from service voluntarily for the purpose of tests, checks, or calibration, without declaring the channel inoperable.
The radwaste effluent line radiation monitor recorder RR3972 is not required in order to comply with the controls stated in the ODAM. It is provided for recording trends during a release and need not be maintained OPERABLE  
The radwaste effluent line radiation monitor recorder RR3972 is not required in order to comply with the controls stated in the ODAM. It is provided for recording trends during a release and need not be maintained OPERABLE -i.e. calibrated and functionally tested -other than during a release. Page 116 of 280 Rev. 37 BASES BASES SECTION 6.1 / 7.1 6.1.2 / 7.1.2 Liquid Effluent Concentration DAECODAM The basic requirements concerning effluents from nuclear power are stated in 10 CFR 50.36a. These requirements indicate that compliance with Technical Specifications will keep average annual releases of radioactive material in effluents to a small percentage of the limits specified in 10 CFR 20.106. These (new 10 CFR 20.1301) requirements further indicate that operational flexibility is allowed, compatible with considerations of health and safety, which may temporarily result in releases higher than such small percentages, but still within the limits specified in the old 10 CFR 20.106. These referenced concentrations are specific values which relate to an annual average dose of 500 millirems.
-i.e. calibrated and functionally tested -other than during a release.
Page 116 of 280 Rev. 37 BASES BASES SECTION 6.1 / 7.1 6.1.2 / 7.1.2 Liquid Effluent Concentration DAECODAM The basic requirements concerning effluents from nuclear power are stated in 10 CFR 50.36a. These requirements indicate that compliance with Technical Specifications will keep average annual releases of radioactive material in effluents to a small percentage of the limits specified in 10 CFR 20.106. These (new 10 CFR 20.1301) requirements further indicate that operational flexibility is allowed, compatible with considerations of health and safety, which may temporarily result in releases higher than such small percentages, but still within the limits specified in the old 10 CFR 20.106. These referenced concentrations are specific values which relate to an annual average dose of 500 millirems.
As stated in the Introduction to Appendix B of the new 10 CFR 20, the liquid effluent concentrations limits, given in the appendix, are based on an annual dose of 50 millirem.
As stated in the Introduction to Appendix B of the new 10 CFR 20, the liquid effluent concentrations limits, given in the appendix, are based on an annual dose of 50 millirem.
Prior to the issuance of the revision to Part 20, a release concentration corresponding to a limiting dose of 500 millirem had been acceptable as a TS limit for liquid effluents.
Prior to the issuance of the revision to Part 20, a release concentration corresponding to a limiting dose of 500 millirem had been acceptable as a TS limit for liquid effluents.
The limit was applicable at all times and has been used to provide assurance that the limits of 10 CFR 50 Appendix I were not likely to be exceeded.
The limit was applicable at all times and has been used to provide assurance that the limits of 10 CFR 50 Appendix I were not likely to be exceeded.
Since the limits of 10 CFR 50 are the ultimate value to which a license must adhere, and since the old concentration limits adequately provide such assurance, it should not be necessary to reduce this limit by a factor of 10. Conformance with the dose limits in section 6.1.3 will necessitate average annual I liquid effluent concentrations being below those specified in 10 CFR 20.1001 -20.2402 Appendix B to&sect;&sect; 20.1001-20.2402.
Since the limits of 10 CFR 50 are the ultimate value to which a license must adhere, and since the old concentration limits adequately provide such assurance, it should not be necessary to reduce this limit by a factor of 10. Conformance with the dose limits in section 6.1.3 will necessitate average annual I liquid effluent concentrations being below those specified in 10 CFR 20.1001 -20.2402 Appendix B to&sect;&sect; 20.1001-20.2402.
Demonstrating compliance with section 6.1.3 will result in a de facto demonstration of compliance with 10 CFR 20 limits. The continuous service water sample points noted in Table 7.1-2 are adequate to I ensure sampling of potential liquid radioactive effluents from the service water systems.
Demonstrating compliance with section 6.1.3 will result in a de facto demonstration of compliance with 10 CFR 20 limits. The continuous service water sample points noted in Table 7.1-2 are adequate to I ensure sampling of potential liquid radioactive effluents from the service water systems. The sample points include the General Service Water System and the RHR Service Water Systems A and B. The sample point for the RHR Service Water Systems is at a location downstream of the point where Emergency Service Water discharge joins with the RHR Service Water System, and upstream of the point where the RHRSW/ESW Rupture Disc Line branches off of the RHR Service Water System. This sample point will therefore provide for sampling effluents from the RHR Service Water System, Emergency Service Water System and/or RHRSW/ESW Rupture Disc Line. The "clean" system water sample points noted in Table 7.1-2 are adequate to ensure sampling of potential liquid radioactive effluents from systems believed to NOT contain principal gamma emitters and iodine. The sample points include I the Transformer Pit, the CST Pit, FRAC tanks, and the Neut. Tank (1T022). Page 117 of 280 Rev. 37 6.1.2 / 7.1.2 (cont'd) 6.1.3 / 7.1.3 6.1.4 / 7.1.4 1. BASES The GWPP mitigation system sample points noted in Table 7.1-2 are adequate to ensure sampling of potential liquid radioactive effluents in the shallow groundwater.
The sample points include the General Service Water System and the RHR Service Water Systems A and B. The sample point for the RHR Service Water Systems is at a location downstream of the point where Emergency Service Water discharge joins with the RHR Service Water System, and upstream of the point where the RHRSW/ESW Rupture Disc Line branches off of the RHR Service Water System. This sample point will therefore provide for sampling effluents from the RHR Service Water System, Emergency Service Water System and/or RHRSW/ESW Rupture Disc Line. The "clean" system water sample points noted in Table 7.1-2 are adequate to ensure sampling of potential liquid radioactive effluents from systems believed to NOT contain principal gamma emitters and iodine. The sample points include I the Transformer Pit, the CST Pit, FRAC tanks, and the Neut. Tank (1T022).
Further, the GWPP mitigation plan support a reduction in contaminate concentration such that releases are expected below Administrative Control Procedure (ACP) 1411.35 and Environmental Protection Agency (EPA) drinking water limit of 20,000 pCi/L. Dose Due to Radioactive Effluents Section 6.1.3, 6.2.3 and 6.2.4 implement the requirements of 10 CFR Part 50.36a and of 10 CFR Part 50, Appendix I, Section IV. These sections keep levels of radioactive materials in LWR effluents as low as is reasonably achievable.
Page 117 of 280 Rev. 37 6.1.2 / 7.1.2 (cont'd) 6.1.3 / 7.1.3 6.1.4 / 7.1.4 1. BASES The GWPP mitigation system sample points noted in Table 7.1-2 are adequate to ensure sampling of potential liquid radioactive effluents in the shallow groundwater.  
: Further, the GWPP mitigation plan support a reduction in contaminate concentration such that releases are expected below Administrative Control Procedure (ACP) 1411.35 and Environmental Protection Agency (EPA) drinking water limit of 20,000 pCi/L. Dose Due to Radioactive Effluents Section 6.1.3, 6.2.3 and 6.2.4 implement the requirements of 10 CFR Part 50.36a and of 10 CFR Part 50, Appendix I, Section IV. These sections keep levels of radioactive materials in LWR effluents as low as is reasonably achievable.
Compliance with these sections will also keep average releases of radioactive material to effluent at small percentages of the limits specified in 10 CFR Part 20.106. Surveillance requirements provide for the measurement of releases and calculation of doses to verify compliance with the controls.
Compliance with these sections will also keep average releases of radioactive material to effluent at small percentages of the limits specified in 10 CFR Part 20.106. Surveillance requirements provide for the measurement of releases and calculation of doses to verify compliance with the controls.
Action statements in these sections implement the requirements of 10 CFR Part 50.36(c)(2) and 10 CFR Part 50, Appendix I, Section IV.A in the event a control is not met. 2. Liquid Effluents With the implementation of Section 6.1.3, there is reasonable assurance that Station operation will not cause a radionuclide concentration in public drinking water taken from the Cedar River that exceeds the standard for anthropogenic radioactivity in community drinking water. The equations in the ODAM for calculating doses due to measured releases of radioactive material in liquid effluent are consistent with the methodology in Regulatory Guide 1.109 and 1.113. The assessment of personal doses will examine potential exposure pathways including, as appropriate, consumption of fish and water taken from the Cedar River I downstream of the discharge pipe. Liquid Waste Treatment This section implements the requirements of 10 CFR Part 50.36a (a)(1) that operating procedures be established and followed and that equipment be maintained and used to keep releases to the environment as low as is reasonably achievable.
Action statements in these sections implement the requirements of 10 CFR Part 50.36(c)(2) and 10 CFR Part 50, Appendix I, Section IV.A in the event a control is not met. 2. Liquid Effluents With the implementation of Section 6.1.3, there is reasonable assurance that Station operation will not cause a radionuclide concentration in public drinking water taken from the Cedar River that exceeds the standard for anthropogenic radioactivity in community drinking water. The equations in the ODAM for calculating doses due to measured releases of radioactive material in liquid effluent are consistent with the methodology in Regulatory Guide 1.109 and 1.113. The assessment of personal doses will examine potential exposure pathways including, as appropriate, consumption of fish and water taken from the Cedar River I downstream of the discharge pipe. Liquid Waste Treatment This section implements the requirements of 10 CFR Part 50.36a (a)(1) that operating procedures be established and followed and that equipment be maintained and used to keep releases to the environment as low as is reasonably achievable.
The section intends that appropriate portions of the system which were used to establish compliance with the design objectives in 10 CFR Part 50, Appendix I, Section II be used when specified to provide reasonable assurance that releases of radioactive material in liquid effluent will be kept as low as is reasonably achievable.
The section intends that appropriate portions of the system which were used to establish compliance with the design objectives in 10 CFR Part 50, Appendix I, Section II be used when specified to provide reasonable assurance that releases of radioactive material in liquid effluent will be kept as low as is reasonably achievable.
The components in the liquid radwaste system which are appropriate to process liquid waste in order to satisfy Section 7.1.4 are the floor drain demineralizer and the radwaste demineralizer.
The components in the liquid radwaste system which are appropriate to process liquid waste in order to satisfy Section 7.1.4 are the floor drain demineralizer and the radwaste demineralizer.
The activity concentration,  
The activity concentration, &#xb5;Ci/ml, below which liquid radwaste treatment would not be cost-beneficial, and therefore not required, is demonstrated below. The quantity of radioactive material in liquid effluent released annually from the DAEC has been calculated to be: total iodines 0.11 curie total others (less H3) 0.25 Total 0.36 curie DAEC ODAM Page 118 of 280 Rev. 37 DAECODAM BASES The population dose commitment resulting from the radioactive material in liquid effluent released annually has been calculated to be* thyroid total body Total 0.164 man rem 0.114 0.278 man rem Therefore, population doses are about 1.5 man rem per curie of iodine released and about 0.5 man rem per curie of other radionuclides (less H3) released in liquids. On the basis of gross activity, the population dose is about one man rem per curie released in liquids. The volume of liquid waste processed and intended for discharge is estimated to be: Low Purity Waste Chemical Waste 5700 gal/day = 1.8 x 106 gal/yr 600 gal/day = 1. 9 x 105 gal/yr Since the same DAEC equipment is used to process both streams, the total volume to be processed is about 2 x 106 gal/yr. The annual cost to operate the radwaste processing equipment, based on Dirty Waste Ion Exchange operation, has been estimated* (neglecting credit for capital recovery) to be $88,000 per year. Thus the unit volume operating cost is about:
&#xb5;Ci/ml, below which liquid radwaste treatment would not be cost-beneficial, and therefore not required, is demonstrated below. The quantity of radioactive material in liquid effluent released annually from the DAEC has been calculated to be: total iodines 0.11 curie total others (less H3) 0.25 Total 0.36 curie DAEC ODAM Page 118 of 280 Rev. 37 DAECODAM BASES The population dose commitment resulting from the radioactive material in liquid effluent released annually has been calculated to be* thyroid total body Total 0.164 man rem 0.114 0.278 man rem Therefore, population doses are about 1.5 man rem per curie of iodine released and about 0.5 man rem per curie of other radionuclides (less H3) released in liquids.
I yr = $0.05 I gal 2 x 10 gal I yr Thus the operating cost to treat a 4000 gallon batch of chemical waste by ion exchange would be about $200. The operating cost to treat a 10000 gallon batch of floor drain waste by ion exchange would be about $500. Assuming the cost-benefit balance is $1000 expenditure per man rem reduced and assuming treatment removes all radioactivity from the liquid, then (1) the activity concentration in a Chemical Waste batch below which treatment is not cost-beneficial is C $200 1 curie 10 6 &#xb5;Ci 1 man rem = x x x---4000 gal x 3785 .!!!!.___
On the basis of gross activity, the population dose is about one man rem per curie released in liquids.
The volume of liquid waste processed and intended for discharge is estimated to be: Low Purity Waste Chemical Waste 5700 gal/day = 1.8 x 106 gal/yr 600 gal/day = 1. 9 x 105 gal/yr Since the same DAEC equipment is used to process both streams, the total volume to be processed is about 2 x 106 gal/yr. The annual cost to operate the radwaste processing equipment, based on Dirty Waste Ion Exchange operation, has been estimated*  
(neglecting credit for capital recovery) to be $88,000 per year. Thus the unit volume operating cost is about:
I yr = $0.05 I gal 2 x 10 gal I yr Thus the operating cost to treat a 4000 gallon batch of chemical waste by ion exchange would be about $200. The operating cost to treat a 10000 gallon batch of floor drain waste by ion exchange would be about $500. Assuming the cost-benefit balance is $1000 expenditure per man rem reduced and assuming treatment removes all radioactivity from the liquid, then (1) the activity concentration in a Chemical Waste batch below which treatment is not cost-beneficial is C $200 1 curie 106 &#xb5;Ci 1 man rem = x x x---4000 gal x 3785 .!!!!.___
man rem curie $1000 gal C=0.013 &#xb5;Ci/ml (continued)
man rem curie $1000 gal C=0.013 &#xb5;Ci/ml (continued)
Page 119 of 280 Rev. 37 6.1.4 / 7.1.4 BASES (2) the activity concentration in a batch of Floor Drain Waste below which treatment is not cost-beneficial is $500 1 curie 106 &#xb5;Ci 1 man rem C= x JOOOOgalx3785.!!!!_
Page 119 of 280 Rev. 37 6.1.4 / 7.1.4 BASES (2) the activity concentration in a batch of Floor Drain Waste below which treatment is not cost-beneficial is $500 1 curie 10 6 &#xb5;Ci 1 man rem C= x JOOOOgalx3785.!!!!_
manrem curie $1000 gal c = 0. 013 &#xb5;Ci/ml, Liquid waste treatment with the evaporator at DAEC has been shown to be neither cost-beneficial nor necessary to comply with 10 CFR 50 Appendix I, Section II. Consequently, liquid radwaste treatment to achieve an activity concentration below 0.01 &#xb5;Ci/ml in liquid effluent is not justified.
manrem curie $1000 gal c = 0. 013 &#xb5;Ci/ml, Liquid waste treatment with the evaporator at DAEC has been shown to be neither cost-beneficial nor necessary to comply with 10 CFR 50 Appendix I, Section II. Consequently, liquid radwaste treatment to achieve an activity concentration below 0.01 &#xb5;Ci/ml in liquid effluent is not justified.
6.1.5 / 7.1.5 Liquid Holdup Tanks DAEC ODAM The tanks listed in the specification include all liquid radwaste tanks (1T-88 and 1T-269) located in the Low-Level Radwaste Processing Facility (LLRPSF).
6.1.5 / 7.1.5 Liquid Holdup Tanks DAEC ODAM The tanks listed in the specification include all liquid radwaste tanks (1T-88 and 1T-269) located in the Low-Level Radwaste Processing Facility (LLRPSF).
Because the LLRPSF is not seismically  
Because the LLRPSF is not seismically designed, these tanks are considered as outdoor tanks that are not surrounded by liners, dikes, or walls capable of holding the tanks' contents.
: designed, these tanks are considered as outdoor tanks that are not surrounded by liners, dikes, or walls capable of holding the tanks' contents.
Restricting the quantity of radioactive material contained in the specified tanks provides assurance that in the event of an uncontrolled release of the tanks' contents, the resulting concentrations would be less than the limits of 10 CFR 20, Appendix B to 20.1001 -20.2402, Table 2, Column 2, at the nearest potable water supply in an UNRESTRICTED AREA. Page 120 of 280 Rev. 37 BASES BASES SECTION 6.2 / 7.2 6.2.1 /7.2.1 DAEC ODAM Radioactive Gaseous Effluent Instrumentation The radioactive gaseous effluent instrumentation is provided to monitor the release of radioactive materials in gaseous effluents and, as appropriate, to control potential releases.
Restricting the quantity of radioactive material contained in the specified tanks provides assurance that in the event of an uncontrolled release of the tanks' contents, the resulting concentrations would be less than the limits of 10 CFR 20, Appendix B to 20.1001 -20.2402, Table 2, Column 2, at the nearest potable water supply in an UNRESTRICTED AREA. Page 120 of 280 Rev. 37 BASES BASES SECTION 6.2 / 7.2 6.2.1 /7.2.1 DAEC ODAM Radioactive Gaseous Effluent Instrumentation The radioactive gaseous effluent instrumentation is provided to monitor the release of radioactive materials in gaseous effluents and, as appropriate, to control potential releases.
The presence of instruments for monitoring radioactive effluents is depicted in ODAM Figure 3-1. The OPERABILITY and use of these instruments implements the requirements of 10 CFR Part 50, Appendix A, General Design Criteria 60, 63, and 64. Reactor building exhaust ventilation shaft radiation monitors initiate isolation of the reactor building normal ventilation and start standby gas treatment when a high trip point is reached.
The presence of instruments for monitoring radioactive effluents is depicted in ODAM Figure 3-1. The OPERABILITY and use of these instruments implements the requirements of 10 CFR Part 50, Appendix A, General Design Criteria 60, 63, and 64. Reactor building exhaust ventilation shaft radiation monitors initiate isolation of the reactor building normal ventilation and start standby gas treatment when a high trip point is reached. DAEC is equipped with a radioactive gaseous effluent monitoring system which includes detectors at the offgas stack (R3), the reactor building vent (R4), the turbine building vent (R5), and the LLRPSF vent (R7). A remote indication and control unit located near each detector displays the detector reading and, whenever the setpoint is exceeded, an indicator light. The data are also routed to a control computer and a control room display, but do not cause a trip to isolate the ventilated area. In the event the control computer and/or control room display fail to function or are voluntarily taken out of service, each remote indication and control unit is designed to acquire data for up to 30 hours. It is intended that each affected remote indication and control unit display be observed at least once per 24 hours (in which case the affected channel remains OPERABLE).
DAEC is equipped with a radioactive gaseous effluent monitoring system which includes detectors at the offgas stack (R3), the reactor building vent (R4), the turbine building vent (R5), and the LLRPSF vent (R7). A remote indication and control unit located near each detector displays the detector reading and, whenever the setpoint is exceeded, an indicator light. The data are also routed to a control computer and a control room display, but do not cause a trip to isolate the ventilated area. In the event the control computer and/or control room display fail to function or are voluntarily taken out of service, each remote indication and control unit is designed to acquire data for up to 30 hours. It is intended that each affected remote indication and control unit display be observed at least once per 24 hours (in which case the affected channel remains OPERABLE).
If an alarm trip setpoint is exceeded at the same time the control computer and/or control room display are neither functioning nor in service, alarm annunciation will still occur in the control room. In the event the detector reading and the indication of exceeding the monitor setpoint are not provided at either the control room or the remote indication and control unit, then the affected channel is not OPERABLE and DAEC will either perform the appropriate ACTION or will provide an alternate monitoring system. This permits DAEC to retain the GE gaseous monitoring system as an alternate system for normal effluent monitoring when the Kaman system is temporarily inoperable.
If an alarm trip setpoint is exceeded at the same time the control computer and/or control room display are neither functioning nor in service, alarm annunciation will still occur in the control room. In the event the detector reading and the indication of exceeding the monitor setpoint are not provided at either the control room or the remote indication and control unit, then the affected channel is not OPERABLE and DAEC will either perform the appropriate ACTION or will provide an alternate monitoring system. This permits DAEC to retain the GE gaseous monitoring system as an alternate system for normal effluent monitoring when the Kaman system is temporarily inoperable.
When used as an alternate monitoring system, the GE system is subject to the requirements stated in Sections 6.2.1 and 7.2.1 and to LLD requirements stated in Table 7.2-2, Note (d). Two air ejector offgas post-treatment monitors are provided.
When used as an alternate monitoring system, the GE system is subject to the requirements stated in Sections 6.2.1 and 7.2.1 and to LLD requirements stated in Table 7.2-2, Note (d). Two air ejector offgas post-treatment monitors are provided.
They are designed so that an instrument failure gives a downscale trip or an inoperative trip. When both instruments reach an upscale trip point, or when one reaches an upscale and the other reaches a downscale trip point or inoperative, a trip is actuated.
They are designed so that an instrument failure gives a downscale trip or an inoperative trip. When both instruments reach an upscale trip point, or when one reaches an upscale and the other reaches a downscale trip point or inoperative, a trip is actuated.
The post-treatment monitors have three upscale trip setpoints. The lower level upscale trip (high) will initiate charcoal bed valve closure.  
The post-treatment monitors have three upscale trip setpoints. The lower level upscale trip (high) will initiate charcoal bed valve closure. (CV-4134A opening and CV-4134B closing to route offgas through the charcoal.)
(CV-4134A opening and CV-4134B closing to route offgas through the charcoal.)
The intermediate and upper trip points (high-high and high-high-high) are for alarm only. Page 121 of 280 Rev. 37 BASES BASES SECTION 6.2 17.2 2. Not used 3. Gaseous Effluents Assessments of dose required by Sections 7.2.3 and 7.2.4 to verify compliance with Appendix I, Section IV are based on measured radioactivity in gaseous effluent and on calculation methods stated in the ODAM. Pathways of exposure and location of individuals are selected such that the dose to a nearby resident is unlikely to be underestimated.
The intermediate and upper trip points (high-high and high-high-high) are for alarm only. Page 121 of 280 Rev. 37 BASES BASES SECTION 6.2 17.2 2. Not used 3. Gaseous Effluents Assessments of dose required by Sections 7.2.3 and 7.2.4 to verify compliance with Appendix I, Section IV are based on measured radioactivity in gaseous effluent and on calculation methods stated in the ODAM. Pathways of exposure and location of individuals are selected such that the dose to a nearby resident is unlikely to be underestimated.
Dose assessment methodology described in the ODAM for gaseous effluent will be consistent with the methodology in Regulatory Guides 1.109 and 1.111. Cumulative and projected assessments of dose made during a quarter are based on historical average meteorological conditions measured at DAEC. Assessment made for the annual radiological environmental report will be based on annual averages of atmospheric conditions during the period of release.
Dose assessment methodology described in the ODAM for gaseous effluent will be consistent with the methodology in Regulatory Guides 1.109 and 1.111. Cumulative and projected assessments of dose made during a quarter are based on historical average meteorological conditions measured at DAEC. Assessment made for the annual radiological environmental report will be based on annual averages of atmospheric conditions during the period of release. 6.2.2 / 7.2.2 Gaseous Effluent Concentration DAECODAM The basic requirements concerning effluents from nuclear power are stated in 10 CFR 50.36a. These requirements indicate that compliance with Technical Specifications will keep average annual releases of radioactive material in effluents to a small percentage of the limits specified in 10 CFR 20. These (new 10 CFR 20.1301) requirements further indicate that operational flexibility is allowed, compatible with considerations of health and safety, which may temporarily result in releases higher than such small percentages, but still within the limits specified in the old 10 CFR 20.106. These referenced concentrations are specific values which relate to an annual average dose of 500 millirems.
6.2.2 / 7.2.2 Gaseous Effluent Concentration DAECODAM The basic requirements concerning effluents from nuclear power are stated in 10 CFR 50.36a. These requirements indicate that compliance with Technical Specifications will keep average annual releases of radioactive material in effluents to a small percentage of the limits specified in 10 CFR 20. These (new 10 CFR 20.1301) requirements further indicate that operational flexibility is allowed, compatible with considerations of health and safety, which may temporarily result in releases higher than such small percentages, but still within the limits specified in the old 10 CFR 20.106. These referenced concentrations are specific values which relate to an annual average dose of 500 millirems.
As stated in the Introduction to Appendix B of the new 10 CFR 20, the gaseous effluent concentration limits given in the appendix are based on an annual dose of 50 millirem for isotopes for which inhalation or ingestion is limiting or 100 millirem for isotopes for which submersion (noble gases) is limiting.
As stated in the Introduction to Appendix B of the new 10 CFR 20, the gaseous effluent concentration limits given in the appendix are based on an annual dose of 50 millirem for isotopes for which inhalation or ingestion is limiting or 100 millirem for isotopes for which submersion (noble gases) is limiting.
Prior to the issuance of the revision to Part 20 a release concentration corresponding to limiting dose rates less than or equal to 500 mrem/yr to the whole body, 3000 mrem/yr to the skin from noble gases, and 1500 mrem/yr to any organ from iodine, and tritium, had been acceptable as a TS limit for airborne effluents.
Prior to the issuance of the revision to Part 20 a release concentration corresponding to limiting dose rates less than or equal to 500 mrem/yr to the whole body, 3000 mrem/yr to the skin from noble gases, and 1500 mrem/yr to any organ from iodine, and tritium, had been acceptable as a TS limit for airborne effluents.
This limit was applicable at all times and had been used to provide assurance that the limits of 10 CFR 50 Appendix I and 40 CFR 190 were not likely to be exceeded.
This limit was applicable at all times and had been used to provide assurance that the limits of 10 CFR 50 Appendix I and 40 CFR 190 were not likely to be exceeded.
Since the limits of 10 CFR 50 Appendix I and 40 CFR 90 are more restrictive than 10 CFR 20, and because the dose limits specified have been successfully used to assure compliance with these regulations, it should not be necessary to reduce the dose rate basis to 50 or 100 millirem.
Since the limits of 10 CFR 50 Appendix I and 40 CFR 90 are more restrictive than 10 CFR 20, and because the dose limits specified have been successfully used to assure compliance with these regulations, it should not be necessary to reduce the dose rate basis to 50 or 100 millirem.
Conformance with the dose limits of 7.3.1 will necessitate the average annual airborne effluent concentrations being below those specified in 10 CFR 20 Appendix B. Demonstrating compliance with section 6.3.1 will result in a de facto demonstration of compliance with 10 CFR 20 limits. Assessment of compliance is based upon an effluents measurement program defined in Table 7.2-2 and methodology stated in the ODAM. The resolving time of the measurements, i.e., the sample integration time, bounds the minimum averaging time of the effluent measurements waste streams.
Conformance with the dose limits of 7.3.1 will necessitate the average annual airborne effluent concentrations being below those specified in 10 CFR 20 Appendix B. Demonstrating compliance with section 6.3.1 will result in a de facto demonstration of compliance with 10 CFR 20 limits. Assessment of compliance is based upon an effluents measurement program defined in Table 7.2-2 and methodology stated in the ODAM. The resolving time of the measurements, i.e., the sample integration time, bounds the minimum averaging time of the effluent measurements waste streams. The Standby Gas Treatment System is considered an Engineered Safety Feature and not an exhaust ventilation treatment system. Page 122 of 280 Rev. 37 BASES BASES SECTION 6.2 / 7.2 Thus the exhaust ventilation system discharges via the reactor building vent. 6.2.3 / 7.2.3 Doses due to Noble Gases These specifications implement the requirements of 10 CFR Part 50, Appendix I. 6.2.4 / 7.2.4 Doses due to Iodine and Particulates in Air These specifications implement 10 CFR Part 50, Appendix I. The dose calculation methods in the ODAM depend on existing pathways of exposure to a member of the public or more conservative conditions assumed (yielding a higher calculated dose). Calculations and methods are such that an estimate of the dose to a member of the public is not likely to be underestimated substantially.
The Standby Gas Treatment System is considered an Engineered Safety Feature and not an exhaust ventilation treatment system. Page 122 of 280 Rev. 37 BASES BASES SECTION 6.2 / 7.2 Thus the exhaust ventilation system discharges via the reactor building vent. 6.2.3 / 7.2.3 Doses due to Noble Gases These specifications implement the requirements of 10 CFR Part 50, Appendix I. 6.2.4 / 7.2.4 Doses due to Iodine and Particulates in Air These specifications implement 10 CFR Part 50, Appendix I. The dose calculation methods in the ODAM depend on existing pathways of exposure to a member of the public or more conservative conditions assumed (yielding a higher calculated dose). Calculations and methods are such that an estimate of the dose to a member of the public is not likely to be underestimated substantially.
6.2.5 / 7.2.5 Gaseous Radwaste Treatment DAECODAM This specification implements the requirement of 10 CFR Part 50.36a(a)(1) that operating procedures be established and followed and that equipment be maintained and used to keep releases to the environment as low as is reasonably achievable.
6.2.5 / 7.2.5 Gaseous Radwaste Treatment DAECODAM This specification implements the requirement of 10 CFR Part 50.36a(a)(1) that operating procedures be established and followed and that equipment be maintained and used to keep releases to the environment as low as is reasonably achievable.
In order to satisfy Section 6.2.5, every reasonable effort shall be made to maintain and operate at least one train of the Offgas System charcoal absorbers with pre-and aft-particulate filters to process radioactive gaseous effluent prior to release.
In order to satisfy Section 6.2.5, every reasonable effort shall be made to maintain and operate at least one train of the Offgas System charcoal absorbers with pre-and aft-particulate filters to process radioactive gaseous effluent prior to release. The specification that the Offgas System which was used to establish compliance with the design objectives in 10 CFR Part 50, Appendix I, Section II be used when specified provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept as low as is reasonably achievable.
The specification that the Offgas System which was used to establish compliance with the design objectives in 10 CFR Part 50, Appendix I, Section II be used when specified provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept as low as is reasonably achievable.
ODAM Figure 3-1 is a flow diagram depicting gaseous radioactive waste streams. The Standby Gas Treatment System is considered an Engineered Safety Feature and not an exhaust ventilation treatment system. Page 123 of 280 Rev. 37 BASES SECTION 6.3 17.3 6.3.1 /7.3.1 Dose BASES Section 6.3.1 is provided to comply with the dose limitation requirement of 40 CFR 190. This section requires the assessment of dose to demonstrate that a person (a nearby resident) has not received a radiation dose exceeding that specified in 40 CFR 190 including doses from direct radiation.
ODAM Figure 3-1 is a flow diagram depicting gaseous radioactive waste streams.
The Standby Gas Treatment System is considered an Engineered Safety Feature and not an exhaust ventilation treatment system. Page 123 of 280 Rev. 37 BASES SECTION 6.3 17.3 6.3.1 /7.3.1 Dose BASES Section 6.3.1 is provided to comply with the dose limitation requirement of 40 CFR 190. This section requires the assessment of dose to demonstrate that a person (a nearby resident) has not received a radiation dose exceeding that specified in 40 CFR 190 including doses from direct radiation.
There is no other licensed nuclear fuel cycle facility within 50 miles of DAEC, thus it is assumed that the dose from other uranium fuel cycle facilities is negligible.
There is no other licensed nuclear fuel cycle facility within 50 miles of DAEC, thus it is assumed that the dose from other uranium fuel cycle facilities is negligible.
In the event a report is required to satisfy Action b, it shall be deemed adequate to satisfy the reporting requirement in Section 8.2.2. By demonstrating compliance with 40 CFR 190, DAEC will be, de facto, in compliance with the dose limits specified in 10 CFR 20.1301 and 10 CFR 72.104. Such a position is in keeping with that stated by the NRG in the preamble to the revised 10 CFR 20 (56 CFR 23360). 6.3.2 I 7.3.2 Radiological Environmental Monitoring DAEC ODAM The radiological environmental monitoring  
In the event a report is required to satisfy Action b, it shall be deemed adequate to satisfy the reporting requirement in Section 8.2.2. By demonstrating compliance with 40 CFR 190, DAEC will be, de facto, in compliance with the dose limits specified in 10 CFR 20.1301 and 10 CFR 72.104. Such a position is in keeping with that stated by the NRG in the preamble to the revised 10 CFR 20 (56 CFR 23360). 6.3.2 I 7.3.2 Radiological Environmental Monitoring DAEC ODAM The radiological environmental monitoring program, including the land use census, is conducted to satisfy the requirements of 10 CFR Part 50, Appendix I, Section IV.B.2 and .3. The minimum radiological monitoring program required by this specification provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides which lead to the highest potential radiation exposures of individuals resulting from the station operation.
: program, including the land use census, is conducted to satisfy the requirements of 10 CFR Part 50, Appendix I, Section IV.B.2 and .3. The minimum radiological monitoring program required by this specification provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides which lead to the highest potential radiation exposures of individuals resulting from the station operation.
This monitoring program thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways.
This monitoring program thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways.
The land use census is conducted annually to identify changes in use of the UNRESTRICTED AREA in order to recommend modifications in monitoring programs for evaluating individual doses from principal exposure pathways.
The land use census is conducted annually to identify changes in use of the UNRESTRICTED AREA in order to recommend modifications in monitoring programs for evaluating individual doses from principal exposure pathways.
Line 880: Line 653:
The program shall be contained in the ODAM, shall be implemented by procedures, and shall include remedial actions to be taken whenever the program limits are exceeded.
The program shall be contained in the ODAM, shall be implemented by procedures, and shall include remedial actions to be taken whenever the program limits are exceeded.
The program shall include the following elements.  
The program shall include the following elements.  
: a. Limitations on the functional capacity of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODAM; b. Limitations on the concentrations of radioactive material released in liquid effluents from the site to UNRESTRICTED AREAs, conforming to ten times (10x) the concentrations listed in Appendix B, Table 2, Column 2 to 10 CFR 20.1001 -20.2402;  
: a. Limitations on the functional capacity of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODAM; b. Limitations on the concentrations of radioactive material released in liquid effluents from the site to UNRESTRICTED AREAs, conforming to ten times (10x) the concentrations listed in Appendix B, Table 2, Column 2 to 10 CFR 20.1001 -20.2402; c. Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents pursuant to 10 CFR 20.1302 and with the methodology and parameters in the ODAM conforming to 10CFR50, Appendix I; d. Limitations on the annual and quarterly doses or dose commitment to a member of the public from radioactive materials in liquid effluents released to UNRESTRICTED AREAs; e. Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODAM at least every 30 days; f. Limitations on the functional capability and use of the liquid and gaseous effluent treatment systems to ensure that the appropriate portions of these systems which were used to establish compliance with the design objectives in 10 CFR 50, Appendix I, Section II be used when specified to provide reasonable assurance that releases of radioactive material in liquid and gaseous effluents be kept as low as reasonably achievable;  
: c. Monitoring,  
: sampling, and analysis of radioactive liquid and gaseous effluents pursuant to 10 CFR 20.1302 and with the methodology and parameters in the ODAM conforming to 10CFR50, Appendix I; d. Limitations on the annual and quarterly doses or dose commitment to a member of the public from radioactive materials in liquid effluents released to UNRESTRICTED AREAs; e. Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODAM at least every 30 days; f. Limitations on the functional capability and use of the liquid and gaseous effluent treatment systems to ensure that the appropriate portions of these systems which were used to establish compliance with the design objectives in 10 CFR 50, Appendix I, Section II be used when specified to provide reasonable assurance that releases of radioactive material in liquid and gaseous effluents be kept as low as reasonably achievable;  
: g. Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas at or beyond the site boundary shall be limited to the following:  
: g. Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas at or beyond the site boundary shall be limited to the following:  
: 1. For noble gases: less than or equal to a dose rate of 500 mrem/yr to the whole body and less than or equal to a dose rate of 3000 mrem/yr to the skin, and 2. For iodine-131, iodine-133,  
: 1. For noble gases: less than or equal to a dose rate of 500 mrem/yr to the whole body and less than or equal to a dose rate of 3000 mrem/yr to the skin, and 2. For iodine-131, iodine-133, tritium, and for all radionuclides in particulate form with half-lives>
: tritium, and for all radionuclides in particulate form with half-lives>
8 days:; less than or equal to a dose rate of 1500 mrem/yr to any organ; h. Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I; I. Limitations on the annual and quarterly doses to a member of the public from iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives>
8 days:; less than or equal to a dose rate of 1500 mrem/yr to any organ; h. Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I; I. Limitations on the annual and quarterly doses to a member of the public from iodine-131, iodine-133,  
8 days in gaseous effluents released to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I; and j. Limitations on the annual dose or dose commitment to any member of the public due to releases of radioactivity and to radiation from uranium fuel cycle sources, conforming to 40 CFR 190 and 10 CFR 72.104. DAECODAM Page 125 of 280 Rev. 37 REPORTING REQUIREMENTS (continued) 8.2 8.1.2 THE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM The Radiological Environmental Monitoring Program is described in section 5 of the ODAM. Specifications for implementation are located in section 6.3.2 8.1.3 INTERLABORATORY COMPARISON PROGRAM Analyses shall be performed on radioactive materials supplied in an lnterlaboratory Comparison Program. In the event analyses were not performed as required in Section 8.1.3, report the corrective actions taken to prevent a recurrence in the Annual Radiological Environmental Report. The requirement for participation in an lnterlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid. DAEC ODAM Page 126 of 280 Rev. 37 8.2 REPORTING REQUIREMENTS 8.2.1 ANNUAL RADIOACTIVE MATERIAL RELEASE REPORT REPORTING REQUIREMENTS 8.2 (1) A report of radioactive materials released from the Station shall be submitted to the NRC on or before May 1 of each year in accordance with 10 CFR 50.36a. Each report shall include the information specified in item (2) below covering the preceding twelve months. (2) An Annual Radioactive Material Release Report shall include a summary by calendar quarter of the quantities of radioactive liquid and gaseous effluents and radioactive solid waste released from the Station. The data on radioactive liquid and gaseous effluents should be reported in the format in Tables 8.2-1 and 8.2-2. The data on radioactive solid waste should include: 1. classification of the waste (per 10 CFR Part 61) 2. total volume shipped 3. total radioactive material shipped (curies) 4. identification of principal radionuclides  
: tritium, and all radionuclides in particulate form with half-lives>
: 5. solidification agent 6. physical description of the waste (3) A summary description of any changes to the ODAM. (4) A summary of meteorological data collected during the year will be submitted in the annual report following January 1. Alternatively, summary meteorological data may be retained by DAEC and made available to the NRC upon request. (5) Include all onsite ground water sample results, for samples that are being taken in support of the Industry Ground Water Protection Initiative, but are from onsite sample locations that have not been incorporated into the Radiological Environmental Monitoring Program. (6) Include a description for all sample analyses/conditions for which communications were made to State and Local officials due to exceeding the applicable ODAM reporting levels for environmental samples for locations that have not been added to the plant's Radiological Environmental Monitoring Program. (7) Include a description of all spills or leaks (of radioactive material) that were communicated to State/Local Stakeholders. (continued)
8 days in gaseous effluents released to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I; and j. Limitations on the annual dose or dose commitment to any member of the public due to releases of radioactivity and to radiation from uranium fuel cycle sources, conforming to 40 CFR 190 and 10 CFR 72.104. DAECODAM Page 125 of 280 Rev. 37 REPORTING REQUIREMENTS (continued) 8.2 8.1.2 THE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM The Radiological Environmental Monitoring Program is described in section 5 of the ODAM. Specifications for implementation are located in section 6.3.2 8.1.3 INTERLABORATORY COMPARISON PROGRAM Analyses shall be performed on radioactive materials supplied in an lnterlaboratory Comparison Program.
In the event analyses were not performed as required in Section 8.1.3, report the corrective actions taken to prevent a recurrence in the Annual Radiological Environmental Report. The requirement for participation in an lnterlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid. DAEC ODAM Page 126 of 280 Rev. 37 8.2 REPORTING REQUIREMENTS 8.2.1 ANNUAL RADIOACTIVE MATERIAL RELEASE REPORT REPORTING REQUIREMENTS 8.2 (1) A report of radioactive materials released from the Station shall be submitted to the NRC on or before May 1 of each year in accordance with 10 CFR 50.36a. Each report shall include the information specified in item (2) below covering the preceding twelve months. (2) An Annual Radioactive Material Release Report shall include a summary by calendar quarter of the quantities of radioactive liquid and gaseous effluents and radioactive solid waste released from the Station.
The data on radioactive liquid and gaseous effluents should be reported in the format in Tables 8.2-1 and 8.2-2. The data on radioactive solid waste should include:
: 1. classification of the waste (per 10 CFR Part 61) 2. total volume shipped 3. total radioactive material shipped (curies)  
: 4. identification of principal radionuclides  
: 5. solidification agent 6. physical description of the waste (3) A summary description of any changes to the ODAM. (4) A summary of meteorological data collected during the year will be submitted in the annual report following January 1. Alternatively, summary meteorological data may be retained by DAEC and made available to the NRC upon request.  
(5) Include all onsite ground water sample results, for samples that are being taken in support of the Industry Ground Water Protection Initiative, but are from onsite sample locations that have not been incorporated into the Radiological Environmental Monitoring Program.  
(6) Include a description for all sample analyses/conditions for which communications were made to State and Local officials due to exceeding the applicable ODAM reporting levels for environmental samples for locations that have not been added to the plant's Radiological Environmental Monitoring Program.  
(7) Include a description of all spills or leaks (of radioactive material) that were communicated to State/Local Stakeholders.  
(continued)
DAECODAM Page 127 of 280 Rev. 37 TABLE 8.2-1 REPORTING REQUIREMENTS (continued) 8.2 ANNUAL RADIOACTIVE MATERIAL RELEASE REPORT (YEAR) LIQUID EFFLUENTS Nuclides Released Unit Quarter Quarter strontium-89 Ci E E strontium-90 Ci E E cesium-134 Ci E E cesium-137 Ci E E iodine-131 Ci E E cobalt-58 Ci E E cobalt-60 Ci E E iron-55 Ci E E iron-59 Ci E E zinc-65 Ci E E manganese-54 Ci E E chromium-51 Ci E E zirconium-niobium-95 Ci E E molybdenum-99 Ci E E technetium-99m Ci E E barium-lanthanum-140 Ci E E cerium-141 Ci E E Other (specify)
DAECODAM Page 127 of 280 Rev. 37 TABLE 8.2-1 REPORTING REQUIREMENTS (continued) 8.2 ANNUAL RADIOACTIVE MATERIAL RELEASE REPORT (YEAR) LIQUID EFFLUENTS Nuclides Released Unit Quarter Quarter strontium-89 Ci E E strontium-90 Ci E E cesium-134 Ci E E cesium-137 Ci E E iodine-131 Ci E E cobalt-58 Ci E E cobalt-60 Ci E E iron-55 Ci E E iron-59 Ci E E zinc-65 Ci E E manganese-54 Ci E E chromium-51 Ci E E zirconium-niobium-95 Ci E E molybdenum-99 Ci E E technetium-99m Ci E E barium-lanthanum-140 Ci E E cerium-141 Ci E E Other (specify)
Ci E E Ci E E Ci E E Ci E E Ci E E Total for period (above) Ci E E xenon-133 Ci E E xenon-135 Ci E E DAEC ODAM Page 128 of 280 Rev. 37 TABLE 8.2-2 REPORTING REQUIREMENTS (continued) 8.2 ANNUAL RADIOACTIVE MATERIAL RELEASE REPORT (YEAR) GASEOUS EFFLUENTS Nuclides Released Unit Quarter Quarter 1. Fission gases krypton-85 Ci E E krypton-85m Ci E E krypton-87 Ci E E krypton-88 Ci E E xenon-133 Ci E E xenon-135 Ci E E xenon-135m Ci E E xenon-138 Ci E E Others (specify)
Ci E E Ci E E Ci E E Ci E E Ci E E Total for period (above) Ci E E xenon-133 Ci E E xenon-135 Ci E E DAEC ODAM Page 128 of 280 Rev. 37 TABLE 8.2-2 REPORTING REQUIREMENTS (continued) 8.2 ANNUAL RADIOACTIVE MATERIAL RELEASE REPORT (YEAR) GASEOUS EFFLUENTS Nuclides Released Unit Quarter Quarter 1. Fission gases krypton-85 Ci E E krypton-85m Ci E E krypton-87 Ci E E krypton-88 Ci E E xenon-133 Ci E E xenon-135 Ci E E xenon-135m Ci E E xenon-138 Ci E E Others (specify)
Line 903: Line 664:
Total for period Ci .E .E 3. Particulates strontium-89 Ci E E strontium-90 Ci E E cesium-134 Ci E E cesium-137 Ci E E barium-lanthanum-140 Ci E E Others (specify)
Total for period Ci .E .E 3. Particulates strontium-89 Ci E E strontium-90 Ci E E cesium-134 Ci E E cesium-137 Ci E E barium-lanthanum-140 Ci E E Others (specify)
Ci E E Ci E E DAECODAM Page 129 of 280 Rev. 37 REPORTING REQUIREMENTS (continued) 8.2 8.2.2 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT An annual report of radiological environmental surveillance activities required by Section 6.3.2 shall be submitted to the NRC by May 15th of each year. Each report shall be consistent with the objectives outlined in the ODAM, and with 10 CFR 50, Appendix I, Sections IV.B.2, IV.B.3, and IV.C. The report shall include the following information:  
Ci E E Ci E E DAECODAM Page 129 of 280 Rev. 37 REPORTING REQUIREMENTS (continued) 8.2 8.2.2 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT An annual report of radiological environmental surveillance activities required by Section 6.3.2 shall be submitted to the NRC by May 15th of each year. Each report shall be consistent with the objectives outlined in the ODAM, and with 10 CFR 50, Appendix I, Sections IV.B.2, IV.B.3, and IV.C. The report shall include the following information:  
(1) A summary description of the radiological environmental monitoring program required by Section 6.3.2. (2) A map and a table of distances and directions of locations of sampling stations required in Table 6.3-1. (3) A summary of the land use census required in Section 7.3.2.2.  
(1) A summary description of the radiological environmental monitoring program required by Section 6.3.2. (2) A map and a table of distances and directions of locations of sampling stations required in Table 6.3-1. (3) A summary of the land use census required in Section 7.3.2.2. (4) Results of analyses of samples required by the radiological environmental monitoring program, Table 6.3-1. In the event some results are not available, the reasons shall be explained in the report. In the event the missing results are obtained, they shall be submitted in a supplementary report as soon as is reasonable.  
(4) Results of analyses of samples required by the radiological environmental monitoring  
(5) An assessment of radiation doses to a MEMBER OF THE PUBLIC likely to be the most exposed due to radioactive liquid and gaseous effluents released from DAEC during the year. The assessment shall be performed as described in the ODAM. (6) Deleted. (7) Results of participation in the lnterlaboratory Comparison Program. (8) Deviation from environmental sampling schedule.  
: program, Table 6.3-1. In the event some results are not available, the reasons shall be explained in the report. In the event the missing results are obtained, they shall be submitted in a supplementary report as soon as is reasonable.  
(5) An assessment of radiation doses to a MEMBER OF THE PUBLIC likely to be the most exposed due to radioactive liquid and gaseous effluents released from DAEC during the year. The assessment shall be performed as described in the ODAM. (6) Deleted.  
(7) Results of participation in the lnterlaboratory Comparison Program.  
(8) Deviation from environmental sampling schedule.  
(9) A report of all analyses in which the LLD, required by Table 6.3-2, was not achieved.  
(9) A report of all analyses in which the LLD, required by Table 6.3-2, was not achieved.  
(10) A report of any changes in sample locations.  
(10) A report of any changes in sample locations.  
(11) Include a description for all sample analyses/conditions for which communications were made to State and Local Stakeholders due to exceeding the REMP reporting levels provided in the plant's OCDM/ODAM for locations that are described in the plant's REMP or GWPP programs.
(11) Include a description for all sample analyses/conditions for which communications were made to State and Local Stakeholders due to exceeding the REMP reporting levels provided in the plant's OCDM/ODAM for locations that are described in the plant's REMP or GWPP programs.
DAECODAM Page 130 of 280 Rev. 37 8.2.3 SPECIAL REPORTS REPORTING REQUIREMENTS (continued) 8.2 Special reports shall be submitted to the Director of Inspection and Enforcement Regional Office within the time period specified for each report. These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference specification.  
DAECODAM Page 130 of 280 Rev. 37 8.2.3 SPECIAL REPORTS REPORTING REQUIREMENTS (continued) 8.2 Special reports shall be submitted to the Director of Inspection and Enforcement Regional Office within the time period specified for each report. These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference specification.  
: 1. Radioactive Liquid or Gaseous Effluent  
: 1. Radioactive Liquid or Gaseous Effluent -calculated dose exceeding specified limit (ODAM Sections 6.1.3, 6.2.3, and 6.2.4). 2. Off-Gas System inoperable (ODAM Section 6.2.5). 3. Measured levels of radioactivity in an environmental sampling medium determined to exceed the reporting level values of ODAM Table 6.3-3 when averaged over any calendar quarter sampling period (ODAM Section 6.3.2). Report to State and Local authorities in accordance with Administrative Control Procedure (ACP) 1402.3. 4. Annual dose to a MEMBER OF THE PUBLIC determined to exceed 40 CFR Part 190 dose limit (ODAM Section 6.3.1.1).  
-calculated dose exceeding specified limit (ODAM Sections 6.1.3, 6.2.3, and 6.2.4). 2. Off-Gas System inoperable (ODAM Section 6.2.5). 3. Measured levels of radioactivity in an environmental sampling medium determined to exceed the reporting level values of ODAM Table 6.3-3 when averaged over any calendar quarter sampling period (ODAM Section 6.3.2). Report to State and Local authorities in accordance with Administrative Control Procedure (ACP) 1402.3. 4. Annual dose to a MEMBER OF THE PUBLIC determined to exceed 40 CFR Part 190 dose limit (ODAM Section 6.3.1.1).  
: 5. Radioactive liquid waste release without treatment when activity concentration is equal to or greater than 0.01 &#xb5;Ci\mL (ODAM Section 6.1.4). 6. Liquid Holdup Tank Instrumentation Inoperable (ODAM Section 6.1.6). DAEC ODAM Page 131 of 280 Rev. 37 8.3.1 CHANGES TO THE ODAM REPORTING REQUIREMENTS (continued) 8.2 a. Shall be documented and records of reviews performed shall be retained for the duration of the facility operating license. This documentation shall contain: 1) Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change(s) and: 2) A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 72.104, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent dose or setpoint calculations.  
: 5. Radioactive liquid waste release without treatment when activity concentration is equal to or greater than 0.01 &#xb5;Ci\mL (ODAM Section 6.1.4). 6. Liquid Holdup Tank Instrumentation Inoperable (ODAM Section 6.1.6). DAEC ODAM Page 131 of 280 Rev. 37 8.3.1 CHANGES TO THE ODAM REPORTING REQUIREMENTS (continued) 8.2 a. Shall be documented and records of reviews performed shall be retained for the duration of the facility operating license.
This documentation shall contain:
: 1) Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change(s) and: 2) A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 72.104, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent dose or setpoint calculations.  
: b. Shall become effective after review and acceptance by the Onsite Review Group and approval by the DAEC Site Director.  
: b. Shall become effective after review and acceptance by the Onsite Review Group and approval by the DAEC Site Director.  
: c. Shall be submitted to the commission in the form of a complete, legible copy of the entire ODAM as a part of or concurrent with the Annual Radioactive Material Release Report for the period of the report in which any change to the ODAM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date the change was implemented.
: c. Shall be submitted to the commission in the form of a complete, legible copy of the entire ODAM as a part of or concurrent with the Annual Radioactive Material Release Report for the period of the report in which any change to the ODAM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date the change was implemented.
DAEC ODAM Page 132 of 280 Rev.37 Appendix A APPENDIX A: DOSE TRANSFER FACTORS FOR AIRBORNE PATHWAYS Environmental pathway models have been solved on the bases of unit radionuclide release in effluent (1 Ci/yr) and unit atmospheric dispersion (1 sec/m3} or deposition (1/m2) to derive dose transfer factors for airborne effluent.
DAEC ODAM Page 132 of 280 Rev.37 Appendix A APPENDIX A: DOSE TRANSFER FACTORS FOR AIRBORNE PATHWAYS Environmental pathway models have been solved on the bases of unit radionuclide release in effluent (1 Ci/yr) and unit atmospheric dispersion (1 sec/m 3} or deposition (1/m 2) to derive dose transfer factors for airborne effluent.
The dose transfer factors in this appendix were computed with the GASPAR II computer  
The dose transfer factors in this appendix were computed with the GASPAR II computer programa, using default values of parameters applicable to the most exposed members of the public as recommended in Regulatory Guide 1.109, revision 1, with the following exceptions.
: programa, using default values of parameters applicable to the most exposed members of the public as recommended in Regulatory Guide 1.109, revision 1, with the following exceptions.
Significant revisions of data since publication of the Regulatory Guide 1.109, revision 1 and incorporated into GASPAR II were employed.
Significant revisions of data since publication of the Regulatory Guide 1.109, revision 1 and incorporated into GASPAR II were employed.
Data differing from those in the Regulatory Guide 1.109 are identified in GASPAR II documentation.b After publishing Reg. Guide 1.109, the NRC recommended that soil-to
Data differing from those
Determination of Effective Dose Factors The effective dose transfer factors are based on past operating data. The radioactive effluent distribution for the past years can be used to derive single effective factors by the following equations:
Determination of Effective Dose Factors The effective dose transfer factors are based on past operating data. The radioactive effluent distribution for the past years can be used to derive single effective factors by the following equations:
where Arseff = f = i where Ay -v e.ff -Arv;= DAEC ODAM A Yse.ff the effective gamma-air dose factor due to stack releases of noble gases (mrad/&#xb5;Ci) the gamma-air dose factor due to stack releases of each noble gas radionuclide i (mrad/&#xb5;Ci) the fraction of noble gas radioactivity constituted by radionuclide i A Yvejf the effective gamma-air dose factor due to vent releases of all noble gases ( mrad ) &#xb5;Ci sec/ m3 the gamma-air dose factor due to vent releases of each noble gas ( mrad ) radionuclide i . 3 &#xb5;Ci sec/ m A f3v e.ff Page 163 of 280 Rev. 37 Appendix B where A/Jeff = the effective beta-air dose factor due to either vent or stack releases of all noble gases ( mrad ) &#xb5;Ci sec/ m3 the beta air dose factor due to either vent or stack releases of each noble gas . . . ( mrad ) radionuclide  
where Arseff = f = i where Ay -v e.ff -Arv;= DAEC ODAM A Yse.ff the effective gamma-air dose factor due to stack releases of noble gases (mrad/&#xb5;Ci) the gamma-air dose factor due to stack releases of each noble gas radionuclide i (mrad/&#xb5;Ci) the fraction of noble gas radioactivity constituted by radionuclide i A Yvejf the effective gamma-air dose factor due to vent releases of all noble gases ( mrad ) &#xb5;Ci sec/ m 3 the gamma-air dose factor due to vent releases of each noble gas ( mrad ) radionuclide i . 3 &#xb5;Ci sec/ m A f3v e.ff Page 163 of 280 Rev. 37 Appendix B where A/Jeff = the effective beta-air dose factor due to either vent or stack releases of all noble gases ( mrad ) &#xb5;Ci sec/ m 3 the beta air dose factor due to either vent or stack releases of each noble gas . . . ( mrad ) radionuclide  
/ . 3 &#xb5;Ci sec/ m To determine the appropriate effective factors to be used and to evaluate the degree of variability, the atmospheric radioactive effluents for the past 3 years have been evaluated.
/ . 3 &#xb5;Ci sec/ m To determine the appropriate effective factors to be used and to evaluate the degree of variability, the atmospheric radioactive effluents for the past 3 years have been evaluated.
Table B-1 presents the radionuclide distribution for stack and vent releases as measured by isotopic analysis of periodic grab samples from the respective effluent release points. Table B-2 presents the effective dose factors (gamma-air and beta-air) derived on the basis of the radionuclide distribution.
Table B-1 presents the radionuclide distribution for stack and vent releases as measured by isotopic analysis of periodic grab samples from the respective effluent release points. Table B-2 presents the effective dose factors (gamma-air and beta-air) derived on the basis of the radionuclide distribution.
Except for the year 1981, the variability of the effective factors is minor. For 1981, Xe-138 contributes significantly to the derivation of the effective factors for stack releases.
Except for the year 1981, the variability of the effective factors is minor. For 1981, Xe-138 contributes significantly to the derivation of the effective factors for stack releases.
The Xe-138 contribution for the years 1979 and 1980 is not so significant.
The Xe-138 contribution for the years 1979 and 1980 is not so significant.
This increase in Xe-138 from 1981 results in a larger variability of the yearly values from the average than what is considered typical.
This increase in Xe-138 from 1981 results in a larger variability of the yearly values from the average than what is considered typical. Therefore, in order to assure adequate conservatism, the effective dose factors for stack releases will be based on the radionuclide distribution for the year 1981. Because this is considered an atypical distribution resulting in higher doses, use of the data will provide dose estimates which are conservative.
Therefore, in order to assure adequate conservatism, the effective dose factors for stack releases will be based on the radionuclide distribution for the year 1981. Because this is considered an atypical distribution resulting in higher doses, use of the data will provide dose estimates which are conservative.
As more data become available to further establish a typical radionuclide distribution, the effective dose factors for stack releases may be reevaluated.
As more data become available to further establish a typical radionuclide distribution, the effective dose factors for stack releases may be reevaluated.
To provide an additional degree of conservatism, a factor of 0.8 is introduced into the dose calculational process when the effective dose transfer factor is used. This added conservatism provides additional assurance that the evaluation of doses by the use of a single effective factor will not significantly underestimate any actual doses in the environment.
To provide an additional degree of conservatism, a factor of 0.8 is introduced into the dose calculational process when the effective dose transfer factor is used. This added conservatism provides additional assurance that the evaluation of doses by the use of a single effective factor will not significantly underestimate any actual doses in the environment.
Line 972: Line 693:
As discussed in Section 3.6.1, the maximum allowable releases based on the gamma-air effective dose factor have been determined to be 250,000 Ci/quarter for stack releases and 12,700 Ci/quarter for vent releases.
As discussed in Section 3.6.1, the maximum allowable releases based on the gamma-air effective dose factor have been determined to be 250,000 Ci/quarter for stack releases and 12,700 Ci/quarter for vent releases.
For the beta air effective dose factors, the releases of noble gases corresponding to the quarterly limit of 10 mrads corresponds to 307,000 Ci/quarter for stack releases and 29,600 Ci/quarter for vent releases.
For the beta air effective dose factors, the releases of noble gases corresponding to the quarterly limit of 10 mrads corresponds to 307,000 Ci/quarter for stack releases and 29,600 Ci/quarter for vent releases.
Comparing these values for allowable releases with the values based on the gamma-air effective dose factors, it is demonstrated that the gamma-air doses are more restrictive than the air doses. In other words, the doses calculated by using the gamma-air effective dose factors represent a larger fraction of the allowable dose than does the dose calculated by using the beta-air effective dose factors.
Comparing these values for allowable releases with the values based on the gamma-air effective dose factors, it is demonstrated that the gamma-air doses are more restrictive than the air doses. In other words, the doses calculated by using the gamma-air effective dose factors represent a larger fraction of the allowable dose than does the dose calculated by using the beta-air effective dose factors. Therefore, when using the effective dose factors for evaluating compliance with the quarterly dose limits of Section 6.2.3, only the gamma-air dose need be evaluated; compliance with the gamma-air dose limit represents a de facto compliance with the beta-air dose limit. DAECODAM Page 164 of 280 Rev.37 Appendix B Reevaluation The doses due to the gaseous effluents are evaluated by the more detailed calculational methods (i.e., use of nuclide specific dose factors) on a yearly basis. At that time, a comparison can be made between the simplified method and the detailed method to assure the overall reasonableness of this limited analysis approach.
Therefore, when using the effective dose factors for evaluating compliance with the quarterly dose limits of Section 6.2.3, only the gamma-air dose need be evaluated; compliance with the gamma-air dose limit represents a de facto compliance with the beta-air dose limit. DAECODAM Page 164 of 280 Rev.37 Appendix B Reevaluation The doses due to the gaseous effluents are evaluated by the more detailed calculational methods (i.e., use of nuclide specific dose factors) on a yearly basis. At that time, a comparison can be made between the simplified method and the detailed method to assure the overall reasonableness of this limited analysis approach.
If the comparison indicates that the radionuclide distribution has changed significantly, thereby causing the simplified method to underestimate the doses, the value of the effective factors will need to be reexamined to assure the overall acceptability of this approach.
If the comparison indicates that the radionuclide distribution has changed significantly, thereby causing the simplified method to underestimate the doses, the value of the effective factors will need to be reexamined to assure the overall acceptability of this approach.  
However, this reexamination will only be needed if the doses as calculated by the detailed analysis exceed 50% of the design bases doses (i.e., greater than 50% of the 10 mrad gamma air dose or 20 mrad beta air dose). DAECODAM Page 165 of 280 Rev. 37 Appendix B Table B-1 RADIONUCLIDE DISTRIBUTION OF STACK AND VENT RELEASES Radionuclide Fraction of Total Releases Stack Vent 1979 1980 1981 1979 1980 1981 Kr-85m .11 .05 .09 .02 ------Kr-87 .01 ---.02 ---.01 ---Kr-88 .07 .04 .08 ---------Xe-133 .76 .82 .45 .24 .24 .14 Xe-135 .01 .02 .03 .72 .50 .59 Xe-135m ---.02 .08 .02 .22 .21 Xe-138 .02 .06 .25 ---.03 .05 Table B-2 EFFECTIVE DOSE FACTORS NOBLE GASES -AIR DOSES Year Stack Releases Vent Releases Gamma-Air Beta-Air Gamma-Air Beta-Air Effective Dose Effective Dose Effective Dose Effective Dose Factor Factor Factor Factor Arseff AfJseff Arveff AfJveff ( ( mrad ) ( mrad ) &#xb5;Ci sec/ m 3 ( mrad ) &#xb5;Cz &#xb5;Ci sec/ m 3 &#xb5;Ci sec/ m 3 1979 7.0x10-12 5.9x10-5 5.0x10-5 6.5x10-5 1980 6.7x10-12 5.3x10-5 6.7x10-5 6.0x10-5 1981 1.6x10-11 9.3x10-12 6.4x10-5 6.3x10-5 Average 9.9x10-12 6.8x10-5 6.4x10-5 6.3x10-5 DAECODAM Page 166 of 280 Rev. 37 Appendix C APPENDIX C: DOSE TRANSFER FACTORS FOR WATERBORNE PATHWAYS Dose transfer factors for waterborne effluent have been derived by solving environmental pathway models on the bases of unit radionuclide release in effluent (1 Ci/yr) discharged in 1 gallon/minute of water. The dose transfer factors in this appendix were computed with the LADT AP II computer program, using default values of parameters applicable to the most exposed members of the public as recommended in Regulatory 1.109, revision 1, with the following exceptions:
: However, this reexamination will only be needed if the doses as calculated by the detailed analysis exceed 50% of the design bases doses (i.e., greater than 50% of the 10 mrad gamma air dose or 20 mrad beta air dose). DAECODAM Page 165 of 280 Rev. 37 Appendix B Table B-1 RADIONUCLIDE DISTRIBUTION OF STACK AND VENT RELEASES Radionuclide Fraction of Total Releases Stack Vent 1979 1980 1981 1979 1980 1981 Kr-85m .11 .05 .09 .02 ------Kr-87 .01 ---.02 ---.01 ---Kr-88 .07 .04 .08 ---------Xe-133 .76 .82 .45 .24 .24 .14 Xe-135 .01 .02 .03 .72 .50 .59 Xe-135m ---.02 .08 .02 .22 .21 Xe-138 .02 .06 .25 ---.03 .05 Table B-2 EFFECTIVE DOSE FACTORS NOBLE GASES -AIR DOSES Year Stack Releases Vent Releases Gamma-Air Beta-Air Gamma-Air Beta-Air Effective Dose Effective Dose Effective Dose Effective Dose Factor Factor Factor Factor Arseff AfJseff Arveff AfJveff (  
( mrad ) ( mrad ) &#xb5;Ci sec/ m3 ( mrad ) &#xb5;Cz &#xb5;Ci sec/ m3 &#xb5;Ci sec/ m3 1979 7.0x10-12 5.9x10-5 5.0x10-5 6.5x10-5 1980 6.7x10-12 5.3x10-5 6.7x10-5 6.0x10-5 1981 1.6x10-11 9.3x10-12 6.4x10-5 6.3x10-5 Average 9.9x10-12 6.8x10-5 6.4x10-5 6.3x10-5 DAECODAM Page 166 of 280 Rev. 37 Appendix C APPENDIX C: DOSE TRANSFER FACTORS FOR WATERBORNE PATHWAYS Dose transfer factors for waterborne effluent have been derived by solving environmental pathway models on the bases of unit radionuclide release in effluent (1 Ci/yr) discharged in 1 gallon/minute of water. The dose transfer factors in this appendix were computed with the LADT AP II computer  
: program, using default values of parameters applicable to the most exposed members of the public as recommended in Regulatory 1.109, revision 1, with the following exceptions:
In order to account for significant revisions of data since publication of the Regulatory Guide, data differing from those in Regulatory Guide 1.109, revision 1 are identified in LADTAP II documentation.
In order to account for significant revisions of data since publication of the Regulatory Guide, data differing from those in Regulatory Guide 1.109, revision 1 are identified in LADTAP II documentation.
14 After publishing Reg. Guide 1.109, the NRC recommended that soil-to-plant bioaccumulation  
14 After publishing Reg. Guide 1.109, the NRC recommended that soil-to-plant bioaccumulation factors, Biv. of cesium and strontium be changed.15 The revised values were used to derive dose transfer factors tabulated for Sr89, Sr90, and Cs137 in irrigated vegetation.
: factors, Biv. of cesium and strontium be changed.15 The revised values were used to derive dose transfer factors tabulated for Sr89, Sr90, and Cs137 in irrigated vegetation.
Values of environmental transit time recommended in Reg. Guide 1.109 16 , namely 1440 hr from harvest of stored vegetables to ingestion, were retained.
Values of environmental transit time recommended in Reg. Guide 1.10916, namely 1440 hr from harvest of stored vegetables to ingestion, were retained.
LADT AP II divergence from Reg. Guide 1.109 is reflected in tritium dose transfer factors that are typically 43% lower than those described in the Reg. Guide. Dose transfer factors are included hereafter for the following parameters.
LADT AP II divergence from Reg. Guide 1.109 is reflected in tritium dose transfer factors that are typically 43% lower than those described in the Reg. Guide. Dose transfer factors are included hereafter for the following parameters.
Only those pathways applicable at the time of a radioactive liquid effluent release will be used for dose calculations.
Only those pathways applicable at the time of a radioactive liquid effluent release will be used for dose calculations.
Likely pathways would include potable water, freshwater fish and irrigated fresh leafy vegetables (including strawberries).
Likely pathways would include potable water, freshwater fish and irrigated fresh leafy vegetables (including strawberries).
14 15 16 Strenge, D.L., et. al., LADTAP II -Technical Reference and User guide, NUREG/CR-4013, April 1986. NRC, SECY-79-653A, January 30, 1980. Regulatory Guide 1.109, rev. 1, Table E-15. DAECODAM Page 167 of 280 Rev. 37 A d. C ppen IX Pathway Age Group Organ Potable water Adult Total Body Freshwater fish Teenager GI tract Freshwater invertebrates Child Bone Irrigated fresh leafy vegetables Infant Liver Irrigated stored vegetables, fruit, and grain Kidney Irrigated grass-cow-milk Thyroid Irrigated grass-cow
14 15 16 Strenge, D.

Revision as of 22:33, 7 July 2018

Duane Arnold, Offsite Dose Assessment Manual (Odam), Revision 37
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Enclosure 2 to NG-17-0092 Duane Arnold Energy Center Offsite Dose Assessment Manual (ODAM), Revision 37 280 pages follow OFFSITE DOSE ASSESSMENT MANUAL GASEOUS AND LIQUID EFFLUENTS Duane Arnold Energy Center Record the following:

Date!Time:

______ I ____ Initials:

__ _ NOTE: User shall perform and document a Temp Issue I Rev. Check to ensure revision is current, in accordance with procedure use and adherence requirements.

Prepared By: I Date: Print Signature

  • .. LICENSING MANAGER CROSS DISCIPLINE REVIEW Approved By I Date: Print Signature

.** EP MANAGER CROSS DISCIPLINE REVIEW Approved By I Date: Print Signature

  • . .. CHEMSITRY MANAGER PROCEDURE APPROVAL *.*. ** Approved By I Date: Print Signature ORG REVIEW Approved By I Date: Print Signature SITE DIRECTOR APPROVAL Approved By I Date: Print Signature

.* DAECODAM Page 1of280 Rev. 37 TABLE OF CONTENTS Section Title 1.0 2.0 3.0 2.1 2.2 2.3 2.4 2.5 2.6 2.7

2.8 INTRODUCTION

LIQUID EFFLUENT Radioactivity In Liquid Waste Aqueous Concentration Basis of Mixing Ratios Method of Establishing Alarm Setpoints 2.4.1 Setpoint for a Batch Release 2.4.2 Setpoint for a Continuous Release Radioactivity Concentration in Water at the Restricted Area Boundary Accumulated Personal Maximum Dose Projected Dose to a Person Offsite Groundwater Pathway GASEOUS EFFLUENT 3.1 Introduction 3.2 Radioactivity in Gaseous Effluent 3.3 Main Condenser Offgas Pretreatment Monitor Alarm Setpoint 3.4 Effluent Noble Gas Monitor Alarm Setpoint 3.5 Dose Equivalent Rate Offsite 3.5.1 Noble Gas 3.5.1.1 Total Body Dose Rate 3.5.1.2 Skin Dose Rate 3.5.2 Iodine, Tritium, and Particulates 3.5.2.1 Organ Dose Rate 3.5.2.2 Rainwater Recapture of Tritium 3.6 Noble Gas Gamma Radiation Dose Accumulated in Air 3.6.1 Alternate Method of Evaluating Compliance with Gamma Air Dose Limits 3. 7 Noble Gas Beta Radiation Dose Accumulated in Air 3.8 Dose Due to Iodine and Particulates in Gaseous Effluents 3.8.1 Alternate Method of Evaluating Doses Due to Iodine and Particulates in Gaseous Effluents 3.9 Dose to a Person from Noble Gases 3.9.1 Gamma Dose to Total Body 3.9.2 Dose to Skin 4.0 DOSE COMMITMENT FROM RELEASE OVER EXTENDED TIME 4.1 Dose Assessment for 10 CFR Part 50, Appendix I 4.2 Dose Assessment for 40 CFR Part 190 5.0 ENVIRONMENTAL MONITORING PROGRAMS 5.1 Radiological Environmental Monitoring Program (REMP) 5.2 Ground Water Protection Program (GWPP) 5.3 Sampling Station Locations continued DAEC ODAM Page 2 of 280 Page 5 6 6 6 7 7 8 10 11 11 13 14 16 16 16 17 19 22 22 22 23 25 25 27 27 28 30 30 34 35 35 36 45 45 46 48 48 48 49 Rev. 37 TABLE OF CONTENTS Section Title 6.0 RADIOLOGICAL EFFLUENT CONTROLS AND SURVEILLANCE REQUIREMENTS 6.0.1 Use and Application 6.0.1.1 Definitions 6.0.1.2 Logical Connectors 6.0.1.3 Completion Times 6.0.1.4 Frequency (not used) 6.0.2 6.0.3 7.0.3 Limiting Conditions for Operation Applicability Surveillance Requirement Applicability 6/7.1 Radioactive Liquid Effluent Controls and Surveillance Requirements 6.1.1 Radioactive Liquid Effluent Instrumentation 6.1.2 Liquid Effluent Concentration 6.1.3 Dose Due to Radioactive Effluents 6.1.4 Liquid Waste Treatment 6.1.5 Liquid Holdup Tanks 6/7.2 Radioactive Gaseous Effluent Controls and Surveillance Requirements 6.2.1.1 6.2.1.2 6.2.2 6.2.3 6.2.4 6.2.5 6.2.6 Radioactive Gaseous Effluent Instrumentation Offgas Radioactive Gaseous Effluent Instrumentation Gaseous Effluent Dose Rate Doses Due to Noble Gases Doses Due to Iodine and Particulates in Air Gaseous Radwaste Treatment Mechanical Vacuum Pump Radiation Release Rate 6/7.3 6.3.1 6.3.2 Offsite Dose Assessment Controls and Surveillance Requirements Dose Radiological Environmental Monitoring Program BASES 6.1.1and7.1.1 BASES 6.1.2 and 7.1.2 BASES 6.1.3 and 7.1.3 BASES 6.1.4 and 7.1.4 BASES 6.1.5 and 7.1.5 BASES 6.2.1 and 7.2.1 BASES 6.2.2 and 7.2.2 BASES 6.2.3 and 7.2.3 BASES 6.2.4 and 7.2.4 BASES 6.2.5 and 7.2.5 BASES 6.3.1 and 7.3.1 BASES 6.3.2 and 7.3.2 BASES continued DAEC ODAM Page 3 of 280 Page 58 58 58 60 61 63 64 66 67 67 77 76 78 80 82 84 87 91 96 98 100 102 104 104 106 113 114 115 115 117 118 119 120 120 120 121 121 Rev. 37 TABLE OF CONTENTS Section 8.0 8.1 8.2 8.1.1 8.1.2 8.1.3 8.2.1 8.2.2 8.2.3 Title ADMINISTRATIVE CONTROLS Programs and Manuals Radioactive Effluent Controls Program The Radiological Environmental Monitoring Program lnterlaboratory Comparison Program Reporting Requirements Annual Radioactive Material Release Report Annual Radiological Environmental Report Special Reports Page 122 122 122 123 123 124 124 127 128 APPENDIX A: DOSE TRANSFER FACTORS FOR AIRBORNE PATHWAYS A-1 APPENDIX B: TECHNICAL BASES FOR EFFECTIVE DOSE FACTORS B-1 APPENDIX C: DOSE TRANSFER FOR WATERBORNE PATHWAYS C-1 DAEC ODAM Page4 of 280 Rev. 37 OFFSITE DOSE ASSESSMENT MANUAL FOR GASEOUS AND LIQUID EFFLUENTS

1.0 INTRODUCTION

This manual provides a description of the facility's Offsite Dose Assessment Program, the Radiological Effluents Controls Program and the Radiological Environmental Monitoring Program. EFFLUENTS CONTROLS PROGRAM This program, conforming to 10 CFR 50.36a, provides for the control of radioactive effluents and for maintaining the doses to members of the public from radioactive effluents as low as reasonably achievable.

The program is contained in sections six and seven of the ODAM, is implemented by procedures, and includes remedial actions to be taken whenever the program limits are exceeded.

Section eight of the ODAM includes the requirement for the Annual Radioactive Material Release Report. The Radioactive Material Release Report covers the operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year in accordance with 10 CFR 50.36a. The report includes a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided in the report is consistent with the objectives outlined in the ODAM and Process Control Program and in conformance with 10 CFR 50.36a and 10 CFR Part 50, Appendix I, Section IV.B.1. RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM The Radiological Environmental Monitoring Program (REMP) provides for representative measurements of radioactivity in the highest potential exposure pathways, verification of the accuracy of the effluent monitoring program and modeling of environmental exposure pathways.

Additionally, the REMP is designed to demonstrate that radioactive effluents from DAEC are ALARA. GROUNDWATER PROTECTION PROGRAM The Groundwater Protection Program (GWPP) provides representative measurements of radioactivity in the highest potentially exposed aquifer, verification of the accuracy of the GWPP monitoring efforts and modeling of the subsurface.

Additionally, the GWPP is designed to protect and mitigate radiological contaminates to groundwater.

The REMP and GWPP programs are described in sections five, six and seven of the ODAM and conforms to the guidance of Appendix I to 10 CFR Part 50 and 10 CFR 72, Section eight of the ODAM includes the requirement for the Annual Radiological Environmental Operating Report. The Annual Radiological Environmental Operating Report covers the operation of the unit during the previous calendar year and is submitted by May 15 of each year. The report includes summaries, interpretations, and analyses of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided is consistent with the objectives outlined in the Offsite Dose Assessment Manual (ODAM), and in 10 CFR 50, Appendix I, Sections IV.B.2, IV.B.3, and IV.C. OFFSITEDOSEASSESSMENTPROGRAM The methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents are included in sections two, three and four of the ODAM. These chapters describe acceptable methods of calculating radioactivity concentrations in the environment and the potentially resultant committed doses to a member of the public in the unrestricted areaa that are associated with LWR liquid and gaseous effluents.

a Unrestricted area means outside of the boundary of property owned, leased, or controlled by the Company on which DAEC is sited. The DAEC site boundary is identified by UFSAR Figure 1.2-1. DAEC ODAM Page 5 of 280 Rev. 37 The methodology stated in this Manual is acceptable for use in demonstrating operational compliance with 1 O CFR 20.1301, 10 CFR 50 Appendix I, 10 CFR 72.104, and 40 CFR 190. Only the dose attributable to the Duane Arnold Energy Centerb is considered in demonstrating compliance with 40 CFR 190 since no other nuclear facility exists within 50 miles of the Center. Calculations are made monthly to assess the potential air doses offsite and to a nearby resident in order to guide the management of station effluents.

The receptor is described such that the dose to any resident near the Station is unlikely to be underestimated.

Calculations made to assess the radioactive noble gas dose to air are based on the location offsite that could be occupied by a person where the maximum air dose is expected.

For these accumulated dose calculations, atmospheric dispersion and deposition of gaseous effluents may be based on reference meteorological conditions.c More conservative conditions (i.e., location and/or exposure pathways expected to yield higher computed doses) than appropriate for the maximally exposed person may be assumed in the dose estimated.

Calculations of dose committed from radioactive releases over extended time (3 and 12 months) are also made for the purpose of verifying compliance with regulatory limits on offsite dose. For these calculations the receptor is selected on the basis of the combination of applicable exposure pathways identified in the land use census and the maximum ground level ,VQ at a residence, or on the basis of more conservative conditions such that the dose to any resident near the Station is unlikely to be underestimated.

2.0 LIQUID EFFLUENT 2.1 Radioactivity In Liquid Waste The concentration of radionuclides in liquid waste is determined by sampling and analysis in accord with the surveillance requirements of Section 7.1.2, Table 7.1-2. When a radionuclide is identified, it is reported as being present in the sample even if the concentration is below the required LLD for the analysis.

2.2 Aqueous Concentration Radioactive material in liquid effluent is diluted successively by water flowing in the discharge pipe and in the River. The diluted concentration of radionuclide i in a receiving stream is estimated with the equation where F1 Cz; = C; C = concentration of radionuclide i in liquid radwaste released (µCi/ml) C,; = concentration of radionuclide i in the receiving stream (µCi/ml) F1 = release rate of liquid radwaste (mUsec)d F2 = dilution flow of receiving stream of water (mUsec)d For the purpose of calculating the radioactivity concentration in water at the restricted area boundary (section 2.5), the flow in the discharge pipe, Fe, is assigned to F 2. The b The Duane Arnold Energy Center, also referred to henceforth as the Station, is defined as including BOTH the Nuclear Reactor Facility and the Independent Spent Fuel Storage Installation (ISFSI). c Reference meteorological conditions are 1971, 1974 and 1975 data composited as discussed in "Duane Arnold Energy Center, Evaluation of Liquid and Gaseous Effluent Releases in Accordance With 10 CFR 50 Appendix I," submitted to the NRC June 3, 1976. ct F 1 , F 2 , and Fe may have any convenient units of flow (i.e., volume/time) provided the units of all are identical.

DAEC ODAM Page 6 of 280 Rev. 37 water flow in the discharge pipe may include the liquid waste effluent flow, the liquid radwaste dilution water flow, the cooling tower blowdown flow and other streams such as RHR and emergency service water discharged via the dilution structure and discharge pipe. These streams are illustrated in Figure 2-1. In the River immediately beyond the discharge pipe and the restricted area boundary, the effective dilution is Where Fe =discharge pipe flow M = factor of additional mixing in the River A near field mixing ratio from the pipe into the near field of the River, M = 5, is assigned when estimating maximum potential individual doses involving exposure by eating fish or from consuming irrigated foods. In the event water is drawn from the River downstream of the Station for drinking water or another exposure pathway, F 2 represents the portion of the River flow into which the liquid effluent from the Station is effectively mixed. 2.3 Basis of Mixing Ratios Downstream dilution of aqueous discharge from the DAEC has been estimated based on thermal plume studies conducted in 197 4 at the DAEC. e Measurements of the discharge temperature and river temperature indicated that the 1°F excess temperature isotherm was about 350 feet downstream of the discharge.

This 1°F isotherm represented a dilution of the discharge by the Cedar River of about a factor of 12. In determining additional dilution within the receiving water for evaluating doses from a plant with cooling towers, the NRC guideline*t is that the factor should be limited to a number such that the product of the number and the average blowdown flow to the receiving water body is 1000 cfs or less. At the DAEC, the discharge rate can be conservatively approximated by a cooling tower blowdown rate of 4000 gpm, or about 9 cfs. Using the NRC guideline, an additional dilution of 100 in the Cedar River could be assumed for evaluating doses due to liquid effluent.

Since the average flow in the Cedar River is about 3,775 cfs, the additional dilution in the River is achievable.

These results indicate both a dilution factor of 12 at a downstream distance of 350 feet and conformance to the NRC guideline.

Land Use Censuses have shown that the nearest use of river water for irrigation is 2.3 miles downstream and the nearest use of river water (from alluvial wells) is 2.2 miles downstream for the City of Palo and more than 8 miles downstream for the City of Cedar Rapids. For the sake of simplification and conservatism in routine liquid dose calculations, a dilution factor of 5 is assumed for fish and irrigation pathways and a dilution factor of 10 is assumed for drinking water for the evaluation of doses during DAEC operation.

2.4 Method of Establishing Alarm Setpoints e IELP, Cedar River Baseline Ecological Study, DAEC, annual report, Jan. 1974-Jan.1975.

f Boegli, J.S., et. al., Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants, NUREG-0133, p. 16, October, 1978 DAEC ODAM Page 7 of 280 Rev. 37 The liquid radwaste effluent line has a monitor which provides automatic isolation when 10 times the water effluent concentration listed in 10 CFR 20 Appendix B, Table 2, is being exceeded in the unrestricted area. The other liquid effluent pathways have monitors which provide alarms when 10 times the 10 CFR 20 water effluent concentration is being exceeded in the unrestricted area. Given the nature and frequency of discharges, prompt action to reduce radioactive releases following an alarm, will assure the requirements of 10 CFR Part 20. 1301; 10 CFR Part 50 Appendix I, Section IV; and 40 CFR Part 190 are not exceeded.

The alarm setpoint for the liquid effluent radiation monitor is derived from the concentration limit provided in 10 CFR Part 20.1001-20.2402 Appendix B Table 2 Column 2 applied at the unrestricted area boundary where the discharge pipe flows into the river. The alarm setpoint does not consider dilution, dispersion, or decay of radioactive material beyond the site boundary.

That is, the alarm setpoint is based on a concentration limit at the end of the discharge pipe. The radiation monitoring and isolation points are located in each line through which radioactive waste effluent is eventually discharged into the discharge pipe. The alarm setpoint for effluent monitors on batch releases is based on measurements, according to Table 7.1-2. For liquids released in continuous aqueous discharge which are normally radioactively clean, the setpoint is based on the effective Water Effluent Concentration (WEC) for the most likely contaminating source, i.e., the primary coolant water. A measured spectrum from the primary coolant water is used to determine the effective WEC based on WEC fractions according to 10 CFR 20 Appendix B. 2.4.1 Setpoint for a Batch Release A sample of each batch of liquid radwaste is analyzed for 1-131 and other principal gamma emitters, or for total activity concentration prior to release. The ratio, FWECb, of the activity concentration in the tank to the unrestricted area WEC (10 CFR Part 20, Appendix B, Table 2, Column 2) is calculated with the equation DAEC ODAM Page 8 of280 Rev. 37 where fraction of unrestricted area WEC in batch derived from activity measured prior to release. concentration of radionuclide i (including 1-131 and principal gamma emitters) in batch sample taken prior to release (µCi/ml) Whether radioiodine and primary gamma emitters are identified prior to a batch release or not, the liquid radwaste effluent line radiation monitor alarm setpoint is determined with the equation where s = 10 = A= g= S=JOx *-*g +Bkg l A Fs2 J FWECb Fs1 radiation monitor alarm setpoint (cpm) factor to account for fact that DAEC's instantaneous release limit is ten times the listed WECs counting rate (cpm/ml) or activity concentration

(µCi/ml) of sample in :Lcbi laboratory analysis.

A equals ; if an isotopic analysis were performed or Cb if a gross activity analysis was performed.

ratio of effluent radiation monitor counting rate to laboratory counting rate or activity concentration in a given batch of liquid (cpm per cpm/ml or cpm per µCi/ml) monitoring instrument background (cpm) flow in the batch release line (gal/min).*

Value not greater than the discharge line flow alarm maximum setpoint.

minimum flow in the discharge pipe (gal/min).

9 Value not less than the discharge pipe flow alarm minimum setpoint.

g Any suitable but identical units of flow (volume/time)

DAEC ODAM Page 9 of 280 Rev. 37 Note that A/FWECb represents the counting rate of a solution having the same radionuclide distribution as the sample and having the water effluent concentration of that mixture. 2.4.2 Setpoint for a Continuous Release Continuous aqueous discharges are sampled and analyzed according to the schedule in Table 7.1-2. The ratio, FWECc, of the activity concentration in each of the continuous release streams to the unrestricted area WEC is calculated with the equations where FWECc = Cc;= FWECc = ; WEC; fraction of unrestricted area WEC in continuous release based upon activity measured in primary coolant sample(s) concentration of radionuclide i in sample(s)

(µCi/ml) The alarm setpoint of the radiation monitor on a continuous radioactive discharge line is determined with the equation S=JOx *-*g +Bkg l A Fs2 J FWECc Fs1 where I 0 = factor to account for fact that DAE C's instantaneous release limit is ten times the listed WECs A = activity concentration

(µCi/ml) or counting rate (cpm/ml) in laboratory of monthly reactor primary coolant sample. Fs, = Flow in the liquid discharge line (mUsec).h Value not greater than off discharge line flow alarm maximum setpoint.

Fs2 = flow in the discharge pipe (mUsec).h Value not less than discharge pipe flow alarm minimum setpoint.

g = ratio of effluent radiation monitor counting rate to laboratory counting rate or activity concentration in a given batch of liquid (cpm per cpm/ml or cpm per µCi/ml) h Any suitable but identical units of flow (volume/time)

DAEC ODAM Page 10 of 280 Rev. 37 The radioactivity concentration in continuous aqueous effluent is usually so low that measurement of a representative radionuclide in a sample of the water is uncertain.

Thus, the ratio, A/FWECc, which represents the WEC of a given spectrum of radionuclides, is usually derived from reactor primary coolant analysis(es).

Alternatively, it may be determined from analyses of the continuous effluent itself. In the event the concentration of radioactive material in the sample from the continuous release is below measurable levels (i.e., less than the lower limit of detection), the value of 1 x 1 o-s µCi/ml or the equivalent counting rate (cpm/ml) may be substituted for the factor A A ---(i.e., -1*10-8). FWECc FWECc 2.5 Radioactivity Concentration in Water at the Restricted Area Boundary Section 6.1.2 provides limits on instantaneous radioactivity concentration in the unrestricted area due to aqueous effluents from DAEC. Compliance is assessed by monitoring, sampling, analyzing and establishing setpoints according to Section 7.1.2. As long as a liquid effluent monitor named in Table 6.1-1 does not exceed an alarm or trip setpoint, determined in accordance with section 2.3, or as long as the total or gross activity concentration, measured as required in Section 7.1.2, does not exceed 1 x 10-7 µCi/ml after dilution in the discharge pipe, Section 6.1.2 is satisfied.

In the event of an alarm, indicating concentrations in the unrestricted area in excess of section 6.1.2 limits, the release shall be terminated and dose calculations will be performed to assure the limits specified in sections 6.1.3 and 6.3.1 are not exceeded.

Compliance with 10 CFR 20.1301 shall not be demonstrated on the basis of determining the average annual liquid effluent concentration.

But rather by demonstrating compliance with 40 CFR 190 (i.e., section 6.3.1). Such a practice was deemed acceptable by the NRG in their preamble to the revised 10 CFR 20.i 2.6 Accumulated Personal Maximum Dose Section 7.1.3 requires an assessment to be performed at least once every 30 days in any quarter in which radioactive effluent is discharged which determines whether the dose or dose commitment to a person offsite due to radioactive material released in liquid effluent calculated on a cumulative basis exceeds the limits of Section 6.1.3. The requirement is satisfied by computing the accumulated dose commitment to the most exposed organ and to the whole body of a hypothetical person exposed by eating fish or consuming irrigated strawberries and drinking water taken from the river offsite downstream of the discharge pipe. The pathway(s) and or age group(s) selected may vary by season. For instance, fishing near the DAEC is practically non-existent during the winter; thus, a dose evaluation of the fish pathway is not required for aqueous effluent discharged during the winter months of January, February, or March. The accumulated dose commitment is computed at least once every 30 days but may be computed as analyses become available.

Normally, DAEC employs the MIDAS computer program to calculate dose to a member of the public from aqueous effluent that uses the equations in Reg Guide 1.1 ogi and ; Federal Register Volume 56, #98, Tuesday, May 21, 1991, p. 23360 i USNRC, Regulatory Guide 1.109, revision 1, Position C.1, pp. 1.109-2 thru 1.109-4, Oct. 1977 DAEC ODAM Page 11 of 280 Rev. 37 standard values therein for maximally exposed people. The amount of strawberries a person may eat is estimated to be one-half the amount of fresh leafy vegetable consumption.

Alternatively, the amount of strawberries eaten may be assumed to equal the amount of fresh leafy vegetables eaten. Alternatively, the dose may be calculated in the following way, for instance, in the event calculations by hand were necessary.

where

= Dan = -3" A f:..Dank=3.785*xJO L.JCik

  • ilTk L.Jp *Aeani 1 e 2ek Dan = L Ll Dank k the dose commitment (mrem) to organ n of age group a due to the isotopes identified in analysis k, where the analyses are those required by Table 7.1-2. Thus the contribution to the dose from gamma emitters become available on a batch basis for batch releases and on a weekly basis for continuous releases.

Similarly the contributions from H-3 is available on a monthly basis and the contributions from Fe-55, Sr-89, and Sr-90 become available on a quarterly basis. the dose commitment during the quarter-to-date to organ n, including whole body, of the maximally exposed person in age group a (mrem) Aeani =transfer factor relating a unit release of radionuclide i (Ci) in a unit stream flow (gal/min) to dose commitment to organ n, or whole body, of an exposed person in [mrem gal] age group a Ci min via environmental pathway e. Ck = the concentration of radionuclide i in the undiluted liquid waste represented by sample k to be discharged

(µCi/ml) t k = duration of radioactive release represented by sample k which occurs within time boundaries TB and TE and during which concentration Cik and flows F1k and F2k exist. (min.) 3. 785* 10-3 = conversion constant (3785 mUgal

  • 10-e Ci/µCi) F h = flow in the radioactive waste release line (gal/minf represented by sample k. F 2ke = flow into which radioactive release represented by sample k is mixed in the river at the point of exposure or withdrawal of water for use (same units as F1k)* DAECODAM Page 12 of 280 Rev. 37

= M x Fck where Fck = discharge pipe flow (gal/min)k during release represented by sample k M = factor of additional mixing in the river Pathway-to-dose transfer factors, Aeani. for use in calculating the dose commitment arising from radioactive material released in aqueous effluents are tabulated in Appendix C. These dose transfer factors were derived using LADT AP II and standard values from Regulatory Guide 1.109, revision 1, except where corrections have been incorporated in LADTAP II. Appropriate tables representing applicable environmental pathways of exposure and most exposed age group(s) are selected and used in calculating the dose commitment.

The pathway(s) and/or age group(s) selected may vary by season. Pathways of Maximum Exposure to a Member of the Public:

  • Ingestion of Fish taken from the river near the discharge pipe o Age Group: Adult o Dilution:

F 2 = 5Fc o Food: Sport Fish

  • Irrigated Food Pathway o Age Group: Teen o Dilution:

F 2 = 5Fc o Food: Strawberries

  • Drinking Water Pathway o Age Group: Infant o Dilution:

F 2 = 10Fc o Dilution:

F 2 = 5F c only when Land Use Census identifies this pathway within 3 miles of the plant Variables F 1 , F 2 , and Fe are also defined in section 2.2. 2.7 Projected Maximum Dose to a Person Offsite The dose commitment to a person offsite due to radioactive material released in liquid effluent may be projected by calculating the extrapolated whole body and most exposed organ dose commitments to a hypothetical person exposed via the same pathways evaluated in section 2.6. The potential dose commitments to organs and to the whole body are computed separately.

The dose commitment to a maximally exposed hypothetical person will be projected by calculating the doses accumulated during the most recent three months (according to the method described in section 2.6) and by assuming the result represents the projected doses during the current quarter. Alternatively, the quarterly dose commitment may be projected by using the equation:

Pan = where k Any suitable, identical units of flow (volume/time) 92 Dan x DAEC ODAM Page 13 of 280 Rev. 37 Pan = 92 = X= Dan = projected dose commitment (mrem) to organ n (including whole body) of age group a for the current quarter number of days in a quarter number of days to date in current quarter dose commitment to organ n, including whole body, of the maximally exposed person in age group a based on available aqueous effluent measurements during the quarter to date (mrem) 2.8 Groundwater Pathway Low levels of radioactive contamination have been identified in sub-surface water on site. There is the possibility that this water could represent potential exposure to the public. Hydrogeology studies indicate that this water will migrate towards the river in sectors ranging from East-North-East to the South-South-West.

The only potential exposure pathways are described in Section 2.6 To monitor for the migration of any radioactive contamination beyond the owner controlled area, sampling of on-site ground water, river water, and down gradient drinking water is performed as a function of the Radiological Environmental Monitoring Program (REMP) and the Ground Water Protection Program (GWPP). These programs are described in Section 5.0. In February 2016, the GWPP routine sampling identified a contaminate plume in the shallow aquifer (less than 25 feet deep). Release standards are set forth in Section 6.0, Radiological Liquid Effluent Release 0.6.1.2, Table 7.1-2. In accordance with GWPP Administrative Control Procedure (ACP) 1411.35 and Environmental Protection Agency (EPA) drinking water standards for tritium, 20,000 pCi/L, groundwater batch and continuous releases are expected less than(<) 20,000 pCi/L. Groundwater samples are analyzed on-site and validated by off-site secondary laboratory.

Off-site laboratory results are published in Annual Radiological Material Release Report and Annual Radiological Environmental Report. DAEC ODAM Page 14 of 280 Rev. 37

§; m () 0 §; s: '"O Ol cc CD ....>. (.Tl 0 -N CXl 0 ::0 (J,) -..-J Geocl'lll Service Wall::rf'ump Reactor Building Closed Cooling Wa11::rLooJ)

GEl'ERAL SERVICE WA TE.R SYSTEM Coolers Turbine Cooler Feild Pump Cooler EHC Unit Cooler Rellctor Bldg CW Heat Exchangers RHR and EMERGENCY SERVICE WATER SYSTEMS Water Pump RHR Heat Emerscncy Service I Chillers and Wa!<!r Pump "' l Coolers SBDG Coolers I RADIOACTIVE WASTE SYSTEMS River Water for Dilution Equipment Radwasie Radwaste Treaunent System HP I LP Cond. Cond. Deter gem Waste Floor Drain Waste Floor Drain Trealmcnt System Chemical Was11:: Chi:mleal Was11::Tanks a:

0 Ol 9: 0 0 c Ol Ol

-*co C6 )> ::!1 Ol Q. cc ro ..., m CD m:::i N =ll CD I --. ....>. ccc CD '< ;:?. () 0 CD -* ::J Ol ...... :0 CD ..., ..., Ol 3 3.0 GASEOUS EFFLUENT 3.1 Introduction The Station discharges gaseous effluent through a stack and discharges ventilation air from the reactor and radwaste building through the reactor building vents. Ventilation air from the Turbine Building is discharged through the Turbine Building vent and through the Reactor Building vent. Ventilation from the LLRPSF is discharged through the LLRPSF vent. These gaseous effluent streams, radioactivity monitoring points, and effluent discharge points are shown schematically in Figure 3-1. Gaseous release point locations and elevations at the Station are described in Table 3-1. Gaseous discharges from the stack are treated as an elevated release while discharges via the building vents are assumed to be ground-level, building wake, or split wake releases.

3.2 Radioactivity in Gaseous Effluent For the purpose of estimating offsite radionuclide concentrations and radiation doses, measured radionuclide concentrations in gaseous effluent and in ventilation air exhausted from the Station are relied upon. The gross radioactivity of noble gases discharged is measured by the radioactive noble gas effluent monitors according to Tables 6.2-1 and 7.2-2. Radionuclides other than noble gases in gaseous effluents are measured by sampling and analyses in accordance with Table 7.2-2. Each radionuclide measured in an effluent may be assumed to be discharged uniformly during the sampling period. When radioactivity is identified at a concentration below the LLD for the analysis, that concentration is reported.

When radioactivity is not identified in a sample, it is not reported as being present in that sample. The quantity of radioactive noble gas discharged via the offgas stack or a vent during an interval of time is determined by integrating the release rate measurement of each effluent noble gas monitor. An hourly interval is normally used for dose rate assessments and a daily or longer interval is used for dose assessments.

If represents the gross activity of noble gas discharged via the offgas stack or a vent and gi represents the fraction of radionuclide i in the distribution of radioactive gases in that effluent stream, then the quantity of radionuclide i released in the gaseous effluent stream during counting interval j is estimated by the relation:

The distribution of radioactive noble gases in gaseous effluent streams is determined by gamma spectrum analysis of gaseous effluent samples in accordance with Table 7.2-2. Results of one or more previous analyses may be averaged to obtain a representative spectrum.

In the event a representative distribution is not available or is unobtainable from sample(s) of an effluent stream taken during the current quarter, it will be derived from past measurements, e.g., earlier sample results or annual radioactive material release reports. Alternatively, a noble gas spectrum for a given effluent stream in Table 3-2 herein, may be assumed. DAECODAM Page 16 of 280 Rev. 37 An airborne discharge of radionuclides other than noble gases may be represented by multiple samples with each sample providing a measure of the concentration of specific radionuclides, Ci, in gaseous effluent discharged at flow, Fa, during a time increment At. Thus, each release is quantified according to the relation:

where Fa1 = Qik = 2: Ck FaJ l'!..tJ j the quantity of radionuclide i released in a given effluent stream based on analysis k (Ci) concentration of radionuclide i in gaseous effluent identified by analysis k (µCi/ML or Ci/m 3) effluent stream discharge rate during the increment Dti (m 3/sec) time increment during which radionuclide i at concentration Cik is being discharged (sec) The analysis index k may represent either a grab sample, integrated sample, or a composite sample required by the effluent sampling and analysis program specified in Table 7.2-2. 3.3 Main Condenser Offgas Pretreatment Monitor Alarm Setpoint A noble gas activity monitor is provided to measure gross gamma activity in gases from the main condenser air ejector. The pretreatment monitor includes an alarm that is set to report when the gamma radiation level in gas discharged by the main condenser air ejector indicates the gross radioactivity discharge rate, after 30 minutes delay and decay, exceeds 1 Ci/sec. The main condenser Offgas gross gamma activity rate is an initial condition of the Steam-Line Break Accident (Roof Top Release).

Restricting the gross radioactivity rate of noble gasses from the main condenser to a rate of 1 Ci/sec provides reasonable assurance that the total body exposure to an individual at the exclusion area boundary will not exceed a small fraction of the limits of 10 CFR Part 50.67 in the event this effluent is inadvertently discharged directly to the environment without treatment.

DAECODAM Page 17 of 280 Rev. 37 where The alarm setpoint is determined with the relation:

S= 2120 = F= g= main condenser air ejector noble gas monitor alarm setpoint (cpm) or (MR/hr) [(1.0 E6 µCi/sec) * (1 ft3/28317 cm 3)]

  • 60 sec/min air ejector discharge rate (ft3/min) noble gas monitor calibration or counting rate response for gamma radiation l cpm J l mR I hr J µCi I cm 3 or µCi I cm 3 f; = fraction of noble gas gross activity due to noble gas radionuclide i in a representative spectrum of noble gases at the main condenser offgas detector A; = radioactive decay constant of noble gas nuclide i (min-1) t = 30 min; decay time in delay line DAEC ODAM Page 18 of 280 Rev. 37 3.4 Effluent Noble Gas Monitor Alarm Setpoint Section 6.2.2 provides limits on dose equivalent rates associated with airborne radioactive materials concentrations in the unrestricted area due to airborne effluents from the Station. Instrumentation is provided to monitor gamma radiation in the airborne effluents according to Table 6.2-1. Each effluent noble gas monitor includes an alarm that can be set to activate when the dose rate off site or the noble gas concentration at ground level offsite is expected (calculated) to exceed a specified level. Compliance with the limits on dose rate from noble gases is demonstrated by setting each gaseous effluent monitor alarm setpoint so that an alarm will occur at or before the dose rate limit for noble gases is reached. If an alarm occurs with the setpoint at the limit, compliance with Section 6.2.2.a is assessed as described in section 3.5. On the basis of effluent noble gases from the DAEC during recent years, the gamma dose rate to a person's whole body is expected to be a larger fraction of the limit, 500 mrem/yr, than is the beta plus gamma dose rate to skin is to its limit, 3000 mrem/yr. As a result, a gaseous effluent monitor setpoint may be derived on the basis of the gamma dose rate to a person's whole body alone such that an alarm is set to occur at or before the whole body dose rate offsite exceeds 500 mrem/yr. A noble gas monitor may be set to activate an alarm at a lower setting than the derived setpoint corresponding to the dose rate limit (or corresponding concentration limit). In the event an alarm occurs at the lower setting, the monitor record is compared with the derived setpoint.

If the derived setpoint is exceeded, compliance with Section 6.2.2.a is assessed as described in section 3.5. Each radioactive noble gas effluent monitor setpoint is derived on the basis of whole body dose equivalent rate in the unrestricted area. Setpoints for gaseous effluent monitors may be set independently because excessive effluent release via the turbine building vent is unlikely.

Other releases are likely to be initiated independently and released from different levels, i.e., vent and stack releases with points of maximum concentration offsite not likely to coincide.

For the purpose of deriving a setpoint, the distribution of radioactive noble gases in an effluent stream is determined as described in section 3.2. Setpoint Determination The alarm setpoint of a radioactive noble gas effluent monitor may be calculated on the basis of whole body dose equivalent rate offsite, 500 mrem/yr. A setpoint of a monitor of an elevated release, e.g., from the stack, may be calculated with the equation:

r :Le; j S = 1. 06 * .!!_ * ; + Bkg f LC;XDFf i DAEC ODAM Page 19 of 280 Rev. 37 The setpoint of a monitor of a ground-level or building release, e.g., from the turbine building vent or 3 reactor building vents or LLRPSF vent may be calculated with the equation:

l :Le; j S= 1.06*-(h J L i v +Bkg f X C;*DF; Q i where s = the alarm setpoint (cpm) or (MR/hr) h = monitor response to activity concentration of effluent being monitored, C= DF[ = Bkg = DAECODAM l cpm J l mR I hr J µCi I cm 3 or µCi I cm 3 relative concentration of noble gas radionuclide i in effluent at the point of monitoring

(µCi/cm 3) atmospheric dispersion from point of ground-level or building wake release to the location of potential exposure (sec/m 3) factor converting elevated release rate of radionuclide i to whole body dose equivalent rate at the location of potential exposure l mremCiJ yr

  • 1!__ sec factor converting ground-level of split-wake release of radionuclide i to the whole body dose equivalent rate at the location of potential exposure l mremCij yr* µ 3 m flow of gaseous effluent stream, i.e., flow past the monitor (ft3/min) monitoring instrument background (cpm) or (MR/hr) Page 20 of 280 Rev. 37 Each monitoring channel has a unique response, h, which is determined by the instrument calibration.

The concentration of each noble gas radionuclide, Cj, in a gaseous effluent is determined as discussed earlier in this section. Since the dose rate limits for airborne effluents apply everywhere offsite, alarm setpoints are determined and compliance is assessed at the site boundary where the minimum atmospheric dispersion (maximum XI Q) occurs. The atmospheric dispersion factor and the dose conversion factor DFt depend on local conditions.

The value of XI Q adopted in a setpoint calculation will be based either on prevailing meteorological conditions or on reference meteorological conditions at the DAEC. The minimum atmospheric dispersion offsite from a ground-level or building wake release derived from reference meteorological conditions is at the site boundary 1260 meters NNW of the Station where: (x) =4.3* 10-6 sec/ m 3 Q vent The dose conversion factors, DFt , used in setpoint calculations for gaseous effluent monitors are in Table 3-4. In the event DFt is derived on the basis of prevailing meteorology, it will be calculated in accordance with Regulatory Guide 1.109, Appendix B. DAECODAM Page 21 of 280 Rev. 37 3.5 Dose Equivalent Rate Offsite Section 6.2.2 provides limits on dose equivalent rates associated with airborne radioactive materials concentrations in the unrestricted area due to airborne effluents from the Station. Compliance is assessed on the basis of measurements specified in Table 7.2-2. 3.5.1 Noble Gas Limits on radioactive noble gas in the unrestricted area are provided in Section 6.2.2.a. Each radioactive noble gas effluent monitor is set to alarm when, or below when, the noble gas in airborne effluent from a monitored stack or vent is expected to cause either dose rate limit in Section 6.2.2.a to be exceeded.

In the event an airborne effluent release from the Station exceeds the derived setpoint (limit) for an effluent noble gas monitor (except when caused by the performance of a Surveillance Test Procedure), an assessment of compliance is performed as described herein. The quantity of radioactive noble gas released in a increment of time is measured by the radioactive noble gas effluent monitors and the distribution of radioactive noble gases in a gaseous effluent stream is determined as described in section 3.2 herein. Compliance with Section 6.2.2.a may be assessed by calculating the dose equivalent rate as described hereafter and by comparing it with the limiting dose rate in the Specification.

3.5.1.1 Total Body Dose Rate For evaluating compliance with Effluent Control, Section 6.2.2.a, the total body dose equivalent rate due to noble gas gamma radiation is calculated with the equation:

where Dr= DFf = DAECODAM -1 [ (Qgi sJ (Qg; (XJ vJ] Dy=----*DFi --* -*DF; 3600 l t s v l t Q v noble gas gamma dose rate to total body (mrem/yr) quantity of noble gas radionuclide i discharged

(µCi) during time increment t (yr) factor converting unit noble gas nuclide i stack release to total body dose at ground level received from the overhead plume [ mrem ] (µCi yr) I sec Page 22 of 280 Rev. 37 factor converting time integrated, ground level concentration of noble gas nuclide i to total body dose from gamma dose from gamma radiation 1 3600 = ( mrem ) µCi yr I m 3 conversion (hr/sec) Dose factor DF!, for exposure to noble gases released from an elevated stack are calculated by a finite plume model implemented in the MIDAS program.1 a It assumes decay of short-lived nuclides, an air dose-to-tissue dose conversion of 1.11, and that the dose to internal organs is equivalent to the tissue dose. In this model, meteorological data concurrent with the period of release are used to evaluate the dose rate. The dose from noble gases released from a vent (near ground level) or to skin from an elevated release is derived from a semi-infinite cloud model. Noble gas semi-infinite cloud gamma-to-total body dose factors, DFr, are listed in Table 3-4. When the total body and organ doses from noble gases are computed as required by Section 7.3.1, the nearby resident exposed to the maximal ground-level noble gas concentration (maximum ,VQ) is selected as the receptor.

Alternatively, the dose from noble gases may be computed at 1260 meters NNW of the reactor, a location identified in Figure 3-2, where the nearby resident who may be exposed to maximal ground-level noble gas concentrations (maximum ,VQ) is selected as the receptor.c In that case, values of the dose factors DF! and DFr in Table 3-4 are employed.m Total body dose factors for exposure from a plume from an elevated, stack release, DF!, in Table 3-4 were computed with the aid of an NRC code, RABFIN. In those computations, reference meteorology was assumed as the basis of atmospheric dispersion.

For discharge from a vent, reference meteorological dispersion at the 1260 m NNW, ( x!Q Jv, is 4.3 x 1 o-6 sec/m 3. 3.5.1.2 Skin Dose Rate The skin dose equivalent rate due to radioactive noble gas is calculated with the equation:

/3=-1 [J;,Spi(Q;
  • (%)} +z:J;, Spi(Q; *(%)} l 3600 l t Q s v l t Q v where a David Slade, ed., Meteorology and Atomic Energy 1968, TID-24190,pp.

350-355. m Dose transfer factors DF;° in Table 3.4 are a units conversion of values in Regulatory Guide 1.109, Table B-1, column 5. cDue to limitations of the Midas© software used to perform these calculations, a conservative higher calculated dose may be reported.

When using Annualized Average Meteorological data, the Midas system uses known X/Q values from the 1 mile radius to extrcpolate X/Q values at the site boundary.

The resulting maximum site boundary X/Q value is greater than 4.3 x 10 sec/m 3 and is located on the site boundary toward the SSE. DAECODAM Page 23 of 280 Rev. 37 Dp Qi t = = noble gas beta dose rate to skin (mrem/yr) quantity of noble gas radionuclide i (µCi) discharged during time increment t (hr) S /Ji = factor converting time integrated ground level concentration of noble gas to skin dose from beta radiation mJ] µCiyr 1 3600 = conversion (hr/sec) Compliance with Section 6.2.2.a dose rate to skin is evaluated by calculating the noble gas beta dose equivalent rate offsite at a location 1260 meters NNW of the Station, which is also identified in Figure 3-2.ct At that location, the reference atmospheric dispersion factors to be used in the calculations are: =4.3* J0-6 sec/ m 3 and =2.8* 10-7 sec/ m 3 Alternatively, averaged meteorological dispersion data coincident with the period of release may be used to evaluate the dose rate. The semi-infinite noble gas skin dose equivalent factors are in Table 3-4. They are also derived from Regulatory Guide 1.109, Table 8-1. d Due to limitations of the Midas© software used to perform these calculations, a conservative higher calculated dose may be reported.

When using Annualized Average Meteorological data, the Midas system uses known X/Q values from the 1 mile radius to extrapolate X/Q values at the site boundary.

The resulting maximum site boundary X/Q value is greater than 4.3 x 10-e sec/m 3 and is located on the site boundary toward the SSE. DAECODAM Page 24 of 280 Rev. 37 3.5.2 Iodine, Tritium, and Particulates Section 6.2.2.b provides a limit on iodine-131, iodine-133, H-3, and on radioactive particulates having 8 day or longer half-lives in air in the unrestricted area around the Station. In the event airborne effluent from the Station causes a radioactive noble gas effluent monitor to alarm (except when alarm is due to the performance of a Surveillance Test Procedure) or if the assessment required by Section 7.2.4 shows Section 6.2.4 to have been exceeded, an assessment of compliance with Section 6.2.2.b will be performed using a method described in this section. 3.5.2.1 Organ Dose Ratee Compliance with Section 6.2.2.b is assessed by calculating the dose rate* to the most exposed organ of an assumed adult member of the public inhaling airborne 1-131, 1-133, H-3, and inhaling radioactive particulates having half-lives of 8 days or longer at the location in the unrestricted area having the maximum potential concentration of the effluents (i.e., the location at which reference meteorological data indicates minimum atmospheric dispersion from the Station (max XI Q). The organ dose rate is calculated with the following equations:

For a vent discharge:

Danv 8. 7 66E -3 "'""' "'""' L., L., Qikv TAani TE-TB k For an offgas stack discharge:

8.766E-3 lXJ Dans TE -TB Qiks TAani Q s Combining separate release points gives Dan = Dans + L Danv v where Dan= the dose equivalent rate to organ n of a person in age group a due to radionuclides discharged in airborne effluents during time interval TB to TE (mrem/yr)

Dans = dose equivalent rate from a stack discharge (mrem/yr)

Danv = dose equivalent rate from a vent discharge (mrem/yr)

Qks, Q"" = quantity of radionuclide i released in a given effluent stream based on analysis k (µCi) during discharged time increment TB to TE (hr) of interest Qiks' Qih* = quantity of radionuclide i released in a given effluent stream based on analysis k (µCi) during discharged time increment TB to TE (hr) of interest °For inhaled or ingested radioactive material, the consequent "dose" means the committed dose equivalent.

The "dose rate" is the committed dose equivalent per unit of time of exposure to the radioactive material in the environment.

DAECODAM Page 25 of 280 Rev. 37 TAani = factor converting airborne concentration of radionuclide i to dose commitment to organ n of a person in age group a where exposure is directly to airborne material ((c;::J/J l XQiJs *lXQiJv = atmospheric dispersion from stack and vent, respectively, to ground level at location of interest (sec/m 3) 8. 766E-3 = Conversion (1 Ci/1 E6 µCi)(8766 hr/yr) Radionuclides other than noble gases airborne effluent are measured and quantified as described in section 3.2. Normally, radioactive material measured in effluent is assumed to be discharged uniformly over the period represented by the sample. The averaging time of the measured releases used to evaluate compliance will not exceed 92 days for Sr-89 and Sr-90 and will not exceed 31 days for the other radionuclides.

The maximum offsite exposure potential is expected to occur at 1260 meters NNW of the Station where the reference atmospheric dispersion, to be used in the calculation is 4.3

  • 10-6 sec/m 3 and 2.8
  • 10-7 sec/m 3 Currently, compliance with Section 6.2.2.b is evaluated by calculating an adult inhalation dose rate at 1260 meters NNW of the Stationt.

The dose transfer factors, TAani. used in the computation are tabulated in Appendix A. bue to limitations of the Midas© software used to perform these calculations, a conservative higher calculated dose may be reported.

When using Annualized Average Meteorological data, the Midas system uses known X/Q values from the 1 mile radius to extrapolate XJQ values at the site boundary.

The resulting maximum site boundary XJQ value is greater than 4.3 x 1 O.s sec/m 3 and is located on the site boundary toward the SSE. DAEC ODAM Page 26 of 280 Rev. 37 805.1.1.1 Rainwater Recapture of Tritium The phenomenon of rainwater recapture of the tritium present in gaseous effluents has been observed on site. A liquid pathway analysis of the activity present in the rainwater runoff has been performed.

The maximum dose to a member of the public from this liquid has been conservatively estimated to be less than 0.01 mrem per year. 3.6 Noble Gas Gamma Radiation Dose Accumulated in Air Section 6.2.3 requires that the offsite air dose during any calendar quarter not exceed 5 mrad and the annual air dose not exceed 10 mrad from noble gas gamma radiation.

Section 7.2.3.1 requires a monthly calculation assessment to verify that the cumulative air dose due to gamma radiation from radioactive noble gas released in gaseous effluents during the quarter and year do not exceed Section 6.2.3. The distribution of radioactive noble gases in gaseous releases and the quantity of radioactive noble gas discharged during an interval of time are determined as described in section 3.2 herein. The gamma radiation dose to air offsite as a consequence of noble gas discharge from DAEC is calculated with the where Dr= =

gi* Arf Ari gi*(XJ l lj VI ] QV noble gas gamma dose to air due to effluent from stack and vent (mrad) total measured radioactivity release via stack or vent measured by noble gas effluent monitor during counting interval j (µCi) the fraction of radioactive gas in a given effluent stream attributable to noble gas radionuclide

i. factor converting unit release of noble gas radionuclide i from the stack to air dose at ground-level received from gamma radiation from the overhead plume (mrad/µCi) factor converting time integrated, ground-level concentration of noble gas to air dose from gamma radiation

((,a:::)/

m3 J atmospheric dispersion factor for a vent (ground-level or building wake) discharge (sec/m 3) Section 7.2.3.1 is satisfied by calculating the noble gas gamma radiation dose to air at the offsite location identified in Figure 3-2. At that location, 1260 meters NNW of the Stationh, the reference*

9 atmospheric dispersion factor to be used is 9 Due to limitations of the Midas© software used to perform these calculations, a conservative higher calculated dose may be reported.

When using Annualized Average Meteorological data, the Midas system uses known X/Q values from the 1 mile radius to extr<polate X/Q values at the site boundary.

The resulting maximum site boundary X/Q value is greater than 4.3 x 10 sec/m 3 and is located on the site boundary toward the SSE. DAECODAM Page 27 of 280 Rev. 37

=4.3* Jo-6 sec/ m 3 Values of Ays and Ayv appropriate for use at that location, assuming reference meteorological conditions, are listed in Table 3-3. An NRG code, RABFIN, modified for sector width averaged meteorology was used to calculate the air dose transfer factors, Ar; for a stack discharge, in ODAM Table 3-3. They represent air dose at ground level 1260 meters NNW of the station from a unit release of each radionuclide i from the stack. Dose transfer factors for vent discharges, Ar;, are equivalent to factors in Regulatory Guide 1.109, Table B-1, g-air expressed in different units. 3.6.1 Alternate Method of Evaluating Compliance with Gamma Air Dose Limits Alternatively, the gamma radiation dose to air offsite may be calculated with the equation where Ar,,Jf = Arwff = 0.8 = an effective dose conversion factor based on the typical radionuclide distribution in stack releases converting unit release of radioactive noble gases from the stack to air dose at ground level at a specific location (mrad/µCi).

an effective dose conversion factor based on the typical radioactive distribution in vent releases converting a time integrated, ground level concentration of noble gases to air dose from gamma radiation l mrad J (µCi sec/ m 3) a factor of conservatism which compensates for variability in radionuclide distribution The derivation and basis of the effective gamma air dose conversion factor are provided in Appendix B. Values of the effective factors are tabulated in Table 3-3. By inserting the appropriate values for Dy (5 mrad/quarter y-air dose) and for AYseff (1.6 x 10-11 mrad/µCi) or Agveff (6.4 x 10-5 mrad/(µCi sec/m 3)) into the equation above and solving for either (AQi)s or (AQi)v, respectively, release quantities of noble gases from either the stack or vent corresponding to the technical specification limit of 5 mrad/quarter (total for all release points) may be determined.

The limit of 5 mrad/quarter is described in section 6.2.3 and is for the total of all release points. At the location, 1260 meters NNW h Reference atmospheric conditions are summarized and discussed in "Duane Arnold Energy Center, Evaluation of Liquid and Gaseous Effluent Releases in Accordance with 10 CFR 50 Appendix I," submitted to NRC June 3, 1976, Reference atmospheric dispersion factors tabulated therein, also appear in Appendix B herein. DAECODAM Page 28 of 280 Rev. 37 of the station, (which is the controlling location based on reference meteorology) the release limits are individually Release Quarterly Limit (Ci) Annual Limit Point (Ci) Stack 2.5 x 10 5 5.0 x 10 5 Vent 1.25x10 4 2.5 x 10 4 The following equations may be used to assess both the stack and vent discharges for compliance with the quarterly release limits on noble gas gamma dose to air. j + j 250,000 12,500 or, on a monthly rate basis (although not a requirement) j + j 250,000 12,500 :::; 1 1 3 The equations which may be used to assess both the stack and vent discharges for compliance with the annual air dose limits from noble gas are: j + v j 500,000 25,000 or, on a monthly rate basis (although not a requirement) j + v j 500,000 25,000 :::; 1 1 12 As long as these relations are satisfied for both stack and vent releases of noble gases, no additional calculations are needed to verify compliance with the gamma-air dose limits of Section 6.2.3. Calculations of beta air doses per Section 3.6 may be omitted as discussed in Appendix B. DAECODAM Page 29 of 280 Rev. 37

3. 7 Noble Gas Beta Radiation Dose Accumulated in Air Section 6.2.3 requires that the offsite air dose during any calendar quarter not exceed 10 mrad from noble gas beta radiation and not exceed 20 mrad during any calendar year. Section 7.2.3.1 requires a monthly assessment to verify that the cumulative air dose due to beta radiation from radioactive noble gas released in gaseous effluents not exceed either limit of Section 6.2.3. The radioactive noble gas distribution and activity discharged are determined as described in paragraph 3.6 herein. The beta radiation dose to air offsite as a consequence of noble gas released from the Station is calculated with the equation:

where D/J = = = noble gas beta dose to air due to stack and vent releases (mrad) factor converting time-integrated, ground-level concentration of noble gas radionuclide ito air dose from beta radiation

-m 3 J µC1 -sec atmospheric dispersion factor for a discharge via the stack (sec/m 3) atmospheric dispersion factor for a vent (ground level or building wake) discharge (sec/m 3). Specification 7.2.3.1 is satisfied by calculating the noble gas beta radiation dose to air at the location identified on Figure 3-2. At that location, 1260 meters NNW of the reactori, the reference atmospheric dispersion factors to be used are = = 2.8 x 10-7 4.3 x 10-s Beta radiation-to-air dose conversion

factors, for noble gas radionuclides are listed in Table 3-3. ;Due to limitations of the Midas© software used to perform these calculations, a conservative higher calculated dose may be reported.

When using Annualized Average Meteorological data, the Midas system uses known X/Q values from the 1 mile radius to extrapolate XJQ values at the site boundary.

The resulting maximum site boundary X/Q value is greater than 4.3 x 1 O.s sec/m 3 and is located on the site boundary toward the SSE. DAECODAM Page 30 of 280 Rev. 37 3.8 Dose Due to Iodine and Particulates in Gaseous Effluentsi Section 6.2.4 requires that 1-131, 1-133, H-3, and radioactive material in particulate form having half-lives greater than 8 days in gaseous effluents released to the area offsite cause no more than 7.5 mrem to any organ of a member of the public during a calendar quarter and no more than 15 mrem during any calendar year. Section 7.2.4 requires an assessment at least once every month to verify that the cumulative dose commitment does not exceed either limit of Section 6.2.4. Airborne releases are discharged either via the offgas stack as an elevated release or via building vents and treated as a ground-level, building wake, or split wake release. Radionuclides mentioned above in airborne effluents that are measured by the sampling and analysis schedule in Table 7.2-2 are included in the release term used to calculate doses. Section 3.2 describes the quantification of these radionuclides other than noble gases. A person may be exposed directly to an airborne concentration of radioactive material discharged in effluent and indirectly via pathways involving deposition of radioactive material onto the ground. Dose estimates account for the separate exposure pathways.

The dose commitment to a person offsite associated with a gaseous release, Qik* of radioactive material other than noble gas is calculated with the appropriate one(s) of the following equations for a stack release: for a vent release: iThe dose to any organ of a person arising from radioactive iodine-131, iodine-133, tritium, and radioactive material in particulate form having half-lives greater than 8 days. Noble gases not considered.

DAECODAM Page 31 of 280 Rev. 37 where Danske = TAanie = TGanie = the dose commitment (mrem) to organ n of a person in age group a via exposure pathway e due to radionuclides identified in analysis k of a stack release where the analysis is required by Table 7.2-2. the dose commitment via pathway e from a vent release (mrem) factor converting airborne concentration of radionuclide i to dose commitment to organ n of a person in any group a where exposure is directly to airborne material via exposure pathway e. l mrem J (Ci sec)/ m 3 factor converting ground deposition of radionuclide i to dose commitment organ n of a person in age group a where exposure is directly or indirectly to radioactive material that has been deposited on the ground via exposure ( mrem) pathway e. Ci 1 m 2 quantity of radionuclide i released in a given effluent stream based on analysis k (Ci) relative deposition factor, i.e., factor converting airborne effluent discharge from stack or vent respectively, to a real deposition on land (m-2). The analysis index k may represent either an analysis of a grab sample, a weekly composite analysis, a monthly composite analysis, or a quarterly composite analysis.

Since tritium in water vapor is absorbed directly by vegetation, the tritium concentration in growing vegetation is proportional to the airborne concentration rather than to relative deposition as in the case of particulates.

Thus the dose commitment from airborne tritium via vegetation (fruit and vegetables), air-grass-cow-milk, or air-grass-cow-meat pathways is calculated with the appropriate one(s) of the equations:

for a stack release Danse for a vent release DAEC ODAM Page 32 of 280 Rev. 37 Dame = lXJ " " Q TA Q v ikv 1.rl.anie The dose commitment accumulated by a person offsite is computed at least every 30 days to satisfy Section 7.2.4.1 but may be calculated as analytical results of effluent measurements, performed as specified in Table 7.2-2, become available.

The dose accumulated as a result of stack discharge is computed with Dans = L Danse and the dose accumulated as a result of vent discharge is computed with Danv = L Danve Doses committed during the same time period due to discharges from the stack and vents are additive, thus where Dan= + ", Dan Dans L...J Dam> v the dose commitment accumulated during the quarter to date as a result of all measured radioactive gaseous discharges except noble gases to any organ n, including total body, of a person offsite in age group a (mrem). When the dose to a person from iodine and particulates discharged in gaseous effluents is calculated as required by Section 7.2.4, appropriate environmental pathways (from among those for which dose transfer factors are provided in Appendix A) will be evaluated.

The dose calculated is to a receptor at the location of the nearby residence experiencing the minimum atmospheric dispersion at ground-level from the station, i.e., maximum X , concurrent with the effluent discharge.

Alternatively, the dose may be Q calculated to a receptor at the location identified in Figure 3-2 where reference atmospheric dispersion and deposition factors are: Food pathways are evaluated at the location of food production based on minimum atmospheric dispersion at ground-level concurrent with the effluent discharge or, alternatively, with reference meteorology applicable at that location.

Seasonal appropriateness of pathways is considered.

The air-grass (fresh or man pathway is evaluated**

where a cow is located, 2650 meters WNW of DAEC, reference atmospheric deposition factors are: DAECODAM Page 33 of 280 Rev. 37 l DJ =2.l*10-9 m-2 lDJ =4.28*10-9 m-2 Q s Q v **This receptor is historical in nature. See the current land use census to verify this point as the most conservative receptor location for the pathway. 3.8.1 Alternate Method of Evaluating Doses Due to Iodine and Particulates in Gaseous Effluents Alternatively, the dose commitment to a maximally exposed, hypothetical individual may be calculated by the equation where: D;nf-111y

Dinf-thy

  • L[Q;*TG;nj-thy-I-13J*(D!Q)].

1 =

  • L[Q;*TG;nf-thy-J-J31*(D!Q)l, 1 the dose commitment accumulated during the quarter to date to a hypothetical infant's thyroid as a result of the releases of 1-131 (mrem) the measured quantity of 1-131 released in a given effluent stream, stack or vent (Ci) TG;nf-thy-1-131 = the dose transfer factor for the infant thyroid from the cow-milk pathway for 1-131 measured in the effluent stream 1 0.8 = ( mrem) Cilm 2 a factor of conservatism which accounts for the dose contribution for releases of particulate radioactive material other than 1-131 When the maximum organ dose is evaluated by using the equation above, analyses of other organ doses via other pathways are not needed to demonstrate compliance within the dose limits of Section 6.2.4. The rationale for only evaluating the dose contribution of 1-131 is derived from an evaluation of the radioactive material releases and the environmental pathways.

The air-grass-cow-milk-man pathway is by far the controlling pathway and the infant's thyroid is the limiting organ. This pathway typically contributes greater than 90% of the total calculated dose to the infant's thyroid and 1-131 contributes essentially all of the dose (-95%). Therefore, it is possible to demonstrate compliance with the dose limits of Section 6.2.4 by the conservative calculation method presented above. DAEC ODAM Page 34 of 280 Rev. 37 3.9 Dose to a Person from Noble Gases Section 7.3.1 requires the calculation of the dose or dose commitment to a person offsite exposed to 12 consecutive months of radioactive liquid and gaseous effluents from the Station. One component of personal dose is total body irradiation by gamma rays from noble gases. Another is irradiation of skin by beta and gamma radiation from noble gases. The methods of calculating these doses are presented in sections 3.9.1 and 3.9.2. The amount of radioactive noble gas discharged is determined in the manner described in section 3.2. 3.9.1 Gamma Dose to Total Body The gamma radiation dose to the whole body of a member of the public as a consequence of noble gas released from the Station is calculated with the equation:

where: Dr= P v Y1 = noble gas gamma dose to total body (mrem) quantity of noble gas nuclide i released via stack or vent (Ci) factor converting unit noble gas nuclide i stack release to total body dose at ground level received from the overhead plume (mrem/Ci) factor converting time integrated, ground level concentration of noble gas nuclide i to total body dose from gamma radiation ( mrem ) Ci sec/ m 3 The dose to total body and organs other than skin from noble gases released from an elevated stack are calculated by a finite plume model.k It assumes decay of short-lived nuclides, a residential shielding factor of 0.7, an air dose-to-tissue dose conversion of 1.11, and that the dose to internal organs is equivalent to the tissue dose. Dose factors for exposure to noble gas plume gamma radiation, pr:, are computed by the MIDAS program. kDavid Slade, ed., Meteorology and Atomic Energy 1968, TID-24190, pp. 350-355. DAECODAM Page 35 of 280 Rev. 37 The dose from noble gases released from a vent (near ground level) or to skin from an elevated release is derived from a semi-infinite cloud model. Noble gas semi-infinite cloud gamma-to-total body dose factors, pr;', are listed in Appendix A under the plume pathway. When the total body and organ doses from noble gases are computed as required by Section 7.3.1, the nearby resident exposed to the maximal ground-level noble gas concentration (minimum X 1 Q) is selected as the receptor.

Alternatively, the dose from noble gases may be computed at 1260 meters NNW of the reactor where the nearby resident who may be exposed to maximal ground-level noble gas concentrations (minimum X 1 Q) is selected as the receptor.

In that case, values of p s p v . the dose factors Y; and Y; in Table 3-5 are employed.1 Reference meteorological

d.
  • f t d. h t th t I t* (XI Q) is 4. 3 x 1 o-6 sec/ m 3 1spers1on or ven 1sc arges a a oca ion, "' 3.9.2 Dose to Skin The beta radiation dose to the skin of a member of the public due to beta radiation from noble gas released from the Station may be calculated with the equation where Dp = noble as dose to skin (mrem) sfJi = factor converting time integrated ground level concentration of noble gas to skin dose from beta radiation ( mrem ) Ci sec/ m 3 Semi-infinite cloud noble gas beta-to-skin dose factors, Spi appear in Table 3-5. The total dose to the skin from noble gases is approximately equal to the beta radiation dose to the skin plus the gamma radiation dose to the total body. When the skin dose due to noble gas beta radiation is computed as required by Section 7.3.1, the receptor selected is the nearby resident exposed to maximal ground-level concentrations (maximum XI Q). Alternatively, the skin dose to a postulated receptor (resident) at 1260 meters NNW of the reactor may be calculated.

1 Dose transfer factors in Table 3.5 and in Appendix A under the plume pathway are the same. DAECODAM Page 36 of 280 Rev. 37 Figure 3.1 Gaseous Radioactive Waste Flow Diagram r------------------

Offgas System t !JantondQ:n;ab!e I

Condenser I I I I I i Otfgo:.ijJfitl Compre-:;.sor tS1l1 orrgas Condenser Calalytk Reton-blner ......._ ceio1er 30mtn Le Delay Condenser Llne ' I Prefiler L. ___ !:aU!!_ ____ : L-i-------------------------------i-

I Arter FiltBr l j 7000: ,...FIA I 1.73 MinUtl} Holdup Piping I ' 0**************"'*"***-*-**-*****.---...;..;;.=="'"'=:;..;...='------t-----, .. _,;

vact.1umPurrip 1 ____________

J I--------------------; Turbine Gland Seal I HPCI Gland Seal V*ruumPump

1 RCIC Gland Seal Vacuum Pump------;

RWBldg. &aporator

1

_______

! Refuel Floor Pool Exhaust--------<

r-*-------*-*--

r; ain Exhaust Plenum Potarrti.;i!ly Co11-1arrinei:te4 r' > 1V-EF-?1Af61C l300 CFM 32500CFM Exheios1 Plenum R3 Rf*H 176 Actident RIA-4175 RPcactor Bldg. Normal RM*7645 RM-7647 RM-7649 At:tident RM-i'M' RM-7E4& RM-764S Venn: rt. 7$25 CFH Adrnin Sida. HotL<ib$-DAECODAM Page 37 of 280 Rev. 37 Figure 3-1 (Continued)

R1 Main Condenser SJAE Offgas Post-treatment Noble Gas Activity Monitor R2 Main Condenser SJAE Offgas Hydrogen Monitor R3 Offgas Stack Radiation Monitoring System R4 Reactor Building Exhaust Vent Monitoring System R5 Turbine Building Exhaust Vent Monitoring System R6 Main Condenser SJAE Offgas Pretreatment Noble Gas Activity Monitor R? LLRPSF Exhaust Vent Monitoring System DAEC ODAM Page 38 of 280 Rev. 37 Figure 3-2 Dose Calculation Sites Site Description Distance from Plant A Noble gas gamma air dose: 936 meters Northwest B Noble gas beta air dose: 1, 176 meters North c Goat milk: 2,470 meters East-Northeast I D Aquatic pathways:

Cedar River I E Most Exposed resident:

805 meters West I DAEC ODAM Page 39 of 280 Rev. 37 Parameter Release Height Release Mode Effluent Source DAEC ODAM Off gas Stack 328 feet Elevated Waste Gas System Table 3-1 Atmospheric Gaseous Release Points at the Duane Arnold Energy Center RELEASE POINT Reactor Turbine Building Vent Building Vent 156 feet 90 feet Wake-split Wake-split Reactor Building Upper Turbine Gas Treatment Radwaste Building Buildi'rilg System Lower Turbine Building Page 40 of 280 Rev. 37 LLRPSF Building Vent 65 feet Wake-split LLRPSF Building.

and Storage Facility c d Rel Nuclide Kr-83m Kr-85m Kr-85 Kr-87 Kr-88 Kr-89 Xe-131 m Xe-133m Xe-133 Xe-135m Xe-135 Xe-137 Xe-138 TABLE NOTATION Table 3-2 f Radioactive Noble Gases in G STACK RELEASE (Ci/vr)" Fractionb 4.90E+01 2.53E-03 2.34E+03 1.21E-01 1.40E+02 7.23E-03 1.56E+02 8.06E-03 1.65E+03 8.52E-02 6.40E+02 3.31E-02 4.80E+01 2.48E-03 3.50E+01 1.81 E-03 1.24E+04 6.41 E-01 1.80E+01 9.30E-04 5.10E+02 2.63E-02 7.80E+02 4.03E-02 5.90E+02 3.05E-02 19356 1.0 Effl t f D Arnold E Cent PLANT VENTS RELEASE (Ci/yr)" Fractionb 0 0 7.40E+01 1.98E-02 0 0 1.36E+02 3.64E-02 2.36E+02 6.32E-02 0 0 0 0 0 0 3.92E+02 1.05E-01 7.42E+02 1.99E-01 7.43E+02 1.99E-01 0 0 1.41E+03 3.78E-01 3733. 1.0 a Releases computed by BWR-GALE for DAEC Base Case gaseous radwaste treatment.

Computed releases are included only to show the basis of the radionuclide distribution.

b This is the calculated distribution of radionuclides in gaseous effluents in each release pathway. To estimate radionuclide concentrations in a sample in which only the total activity concentration has been measured, multiply the total activity concentration by the fraction of respective radionuclides listed above. DAEC ODAM Page 41 of 280 Rev. 37 Table 3-3 Transfer Factors for Maximum Offsite Air Dose Radionuclide Air Dose Transfer Factors a b Ar; A " Y; A/3; (

µCi ( mrad ) µCi sec/ m 3 ( mrad ) µCi sec/ m 3 Kr-83m 4.3E-14 6.1E-7 9.1 E-6 Kr-85m 6.0E-12 3.9E-5 6.2E-5 Kr-85 8.4E-14 5.4E-7 6.2E-5 Kr-87 2.3E-11 2.0E-4 3.3E-4 Kr-88 6.4E-11 4.8E-4 9.3E-5 Kr-89 3.0E-11 5.5E-4 3.4E-4 Kr-90 ---5.2E-4 2.5E-4 Xe-131m 1.8E-12 4.9E-6 3.5E-5 Xe-133m 1.4E-12 1.0E-5 4.7E-5 Xe-133 1.5E-12 1.1 E-5 3.3E-5 Xe-135m 1.1 E-11 1.1E-4 2.3E-5 Xe-135 9.5E-12 6.1E-5 7.8E-5 Xe-137 2.6E-12 4.8E-5 4.0E-4 Xe-138 3.6E-11 2.9E-4 1.5E-4 Ar-41 4.4E-11 2.9E-4 1.0E-4 TABLE NOTATIONS a b An NRG code, RABFIN, modified for sector width averaged meteorology, was used to calculate the air dose transfer factors, Ar: for a stack discharge.

They represent air dose at ground level 1260 meters NNW of the station from a unit release of each radionuclide i from the stack and dispersed by reference meteorology at the DAEC. Dose transfer factors for vent discharges, A Y ;* and AfJ; are equivalent to factors in Regulatory Guide 1.109, Table B-1, g-air and b-air, expressed in different units. DAECODAM Page 42 of 280 Rev. 37 b Radionuclide Kr-83m Kr-85m Kr-85 Kr-87 Kr-88 Kr-89 Kr-90 Xe-131m Xe-133m Xe-133 Xe-135m Xe-135 Xe-137 Xe-138 Ar-41 Table 3-4 Transfer Factors for Dose Equivalent Rate to A Person Offsite Due to Radioactive Noble Gases Dose Transfer Factors a, b, c DFt [ mrem ] (µCi yr) I sec [ mrem l (µCi yr)/m 3 6.27E-9 7.56E-2 1.81E-4 1.17E+3 2.51 E-6 1.61 E+1 6.97E-4 5.92E+3 1.91E-3 1.47E+4 9.14E-4 1.66E+4 ---1.56E+4 4.83E-5 9.15E+1 3.61 E-5 2.51E+2 4.09E-5 2.94E+2 3.39E-4 3.12E+3 2.84E-4 1.81E+3 7.90E-5 1.42E+3 1.08E-3 8.83E+3 1.32E-3 8.84E+3 TABLE NOTATIONS a Receptor located 1260 meters NNW of Station b Based on reference meteorology at DAEC d Sp; [ mrem ] (µCi yr)/m 3 0 1.46E+3 9.73E+3 9.73E+3 2.37E+3 1.01E+4 7.29E+3 4.76E+2 9.94E+2 3.06E+2 7.11E+2 1.86E+3 1.22E+4 4.13E+3 2.69E+3 c Factors DFf computed by computer code RABFIN, modified for sector width averaged meteorology d Factors from Regulatory Guide 1.109, revision 1, Table B-1, column 5 DAECODAM Page 43 of 280 Rev. 37 Radionuclide Kr-83m Kr-85m Kr-85 Kr-87 Kr-88 Kr-89 Kr-90 Xe-131m Xe-133m Xe-133 Xe-135m Xe-135 Xe-137 Xe-138 Ar-41 Table 3-5 Transfer Factors for Dose Equivalent Rate to A Person Offsite Due to Radioactive Noble Gases Dose Transfer Factors a, b, c c, d Py; p v Y; [mzmJ [ mrem ] (Ci sec)/m 3 1.39E-10 1.68E-3 4.03E-6 2.60E+1 5.58E-8 3.58E-1 1.55E-5 1.31 E+2 4.25E-5 3.26E+2 2.03E-5 3.68E+2 ---3.46E+2 1.07E-6 2.03 8.05E-7 5.57 9.03E-7 6.52 7.49E-6 6.92E+1 6.31E-6 4.01E+1 1.75E-6 3.15E+1 2.39E-5 1.96E+2 2.92E-5 1.96E+2 s /3i [ mrem l (Cisec)/m 3 ---4.63E+1 4.25E+1 3.08E+2 7.51 E+1 3.20E+2 2.31E+2 1.51 E+1 3.15E+1 9.70 2.25E+1 5.89E+1 3.87E+2 1.31 E+2 8.52E+1 4.0 DOSE COMMITMENT FROM RELEASE OVER EXTENDED TIME TABLE NOTATIONS a Receptor located 1260 meters NNW of Station b Based on reference meteorology at DAEC s p v p s c Factors PY; and Y; already account for a 0.7 residential shielding factor. Factors Y; were computed by computer code RABFIN, modified for sector width averaged meteorology P v d Factors Y; and from Regulatory Guide 1.109, revision 1, Table B-1 DAEC ODAM Page 44 of 280 Rev. 37 d 4.0 DOSE COMMITMENT FROM RELEASE OVER EXTENDED TIME 4.1 Dose Assessment for 10 CFR Part 50, Appendix I a Sections 7.1.3, 7.2.3, and 7.2.4 require quarterly and annual assessments to demonstrate compliance with Appendix I dose limits. The assessment includes the following calculations of dose as described by equations for: 1. total body and maximally exposed organ doses due to liquid effluent via drinking water and eating fish from the River and from consuming food irrigated with river water as in paragraph 2.5. 2. total body and maximally exposed organ doses due to gaseous effluentsa other than noble gases as in paragraph 3.8. 3. doses to air offsite due to noble gas g as in paragraph 3.6 and due to noble gas as in paragraph 3.7. The dose calculations are based on liquid and gaseous effluents from the Station during each calendar quarter and for a calendar year, determined in accord with Tables 7 .1-2 and 7.2-2. Environmental concentrations depend on dispersion and dilution of the effluent.

For aqueous effluents over extended time, the aquatic concentration is estimated according to section 2.2. Atmospheric dispersion and deposition factors used to estimate the dose commitment due to gaseous effluents are ordinarily derived from reference meteorological data. Otherwise, quarterly averaged or annual averaged meteorological conditions concurrent with the gaseous release being evaluated will be used to estimate atmospheric dispersion and deposition.

The receptor of the dose is described such that the dose to any resident near the Station is unlikely to be underestimated.

That is, the receptor is selected on the basis of the combination of applicable pathways of exposure to gaseous effluent identified in the annual land use census and maximum ground level X 1 Q at the residence.

Conditions (i.e., location, X 1 Q, and/or pathways) more conservative (i.e., expected to yield higher calculated doses) than appropriate for the maximally exposed individual may be assumed in the dose assessment.

Radioactive iodine-131, iodine-133, tritium, and radioactive material in particulate form having half-lives greater than 8 days. DAECODAM Page 45 of 280 Rev. 37 Seasonal appropriateness of exposure pathways may be considered.

Exposure by eating fresh vegetation or drinking milk from cows or goats fed fresh forage is an inappropriate assumption during the first or fourth calendar quarter; rather consumption of stored vegetation and stored forage is assumed during those quarters.

Otherwise, during the second and third calendar quarters, exposure by eating fresh vegetation and/or drinking milk from cows or goats fed fresh forage is assumed where those pathways exist. Similarly, the liquid effluent-river-fish-man pathway is not assumed during the winter quarter. Factors converting stack-released noble gas to gamma radiation dose from the overhead plume are calculated on the basis of reference meteorological data for the receptor location or alternatively, by the MIDAS program for a residential location offsite where maximum X 1 Q at ground level occurs. Other environmental pathway-to-dose transfer factors used in the dose calculations are provided in Appendix A. 4.2 Dose Assessment for 40 CFR Part 190 and 10 CFR 72.104 The regulations governing the maximum allowable dose or dose commitment to a member of the public from all uranium fuel cycle-sources of radiation and radioactive material in the environment is stated in 40 CFR Part 190 and 1 O CFR 72.104. It requires that the dose or dose commitment to a member of the public from all sources not exceed 25 mrem/yr to the whole body or 25 mrem/yr to any organ or 75 mrem/yr to the thyroid. Section 7.3.1 requires calculation of the dose at least once every year to assess compliance with the regulation.

More frequent calculations may be performed if higher than normal releases are experienced (twice the design objective rates in a single quarter).

Fuel cycle sources or nuclear power reactors other than the Stationb itself do not measurably or significantly increase the radioactivity concentration in the vicinity of the Station; therefore, only radiation and radioactivity in the environment attributable to the Station itself are considered in the assessment of compliance with 40 CFR Part 190 and 10 CFR 72.104. Contributions to the dose due to liquid and gaseous effluent are calculated as described by the equations for: 1. total body and maximally exposed organ doses due to liquid effluent via drinking water, consuming irrigated food and from eating fish from the River as in paragraph 2.5 2. total body dose due to noble gas y as in paragraph 3.9.1 3. skin dose due to noble gas 13 as in paragraph 3.9.2 b The Station is defined as BOTH the Nuclear Reactor Facility and the Independent Spent Fuel Storage Installation (ISFSI). DAECODAM Page 46 of 280 Rev. 37

4. total body and maximally exposed organ doses due to gaseous effluentsc other than noble gases as in Paragraph 3.8. Additionally, the contribution to total dose from direct radiation is assessed annually by using environmental TLDs. The doses are calculated on the basis of liquid and gaseous effluents from the Station during 12 consecutive months, determined in accord with Tables 7.1-2 and 7.2-2. For the purpose of the Annual Radiological Environmental Report, doses are based upon release during a calendar year. Aqueous radioactive material concentrations are estimated according to paragraph 2.2 on the basis of annual averaged stream flow. Annual averaged meteorological conditions concurrent with gaseous releases being evaluated are used to estimate atmospheric dispersion, deposition, and elevated plume gamma exposure.

The receptor of the dose is described such that the dose to any resident near the Station is not likely to be underestimated, although conditions more conservative than appropriate for the maximally exposed person may be assumed in the dose assessment.

Ordinarily, the receptor is selected on the basis of the applicable combination of existing pathways of exposure to gaseous effluent identified in the annual land use census and the maximum ground level XI Q at the residence.

When assessing compliance with 40 CFR 190, Radiological Environmental Monitoring Program results may be used to indicate actual radioactivity levels in the environment attributable to the DAEC. These measured levels may be used to supplement the evaluation of doses to members of the public for assessing compliance with 40 CFR 190. Factors converting stack-released noble gas to gamma radiation dose from the overhead plume are calculated on the basis of annual averaged meteorological data for the receptor location.

Other environmental pathway-to-dose transfer factors are listed in Appendices A, B and C. c Radioactive iodine-131, iodine-133, tritium, and radioactive material in particulate form having half-lives greater than 8 days. DAECODAM Page 47 of 280 Rev. 37 5.0 ENVIRONMENTAL MONITORING PROGRAMS Section 5.0 of the ODAM provides a description of the Radiological Environmental Monitoring Program (REMP) and the Ground Water Protection Program (GWPP). This section also contains descriptions of the Environmental Sampling Program Station Locations.

5.1 Radiological Environmental Monitoring Program A program shall be provided to monitor the radiation and radionuclides in the environs of the station. The program shall provide: (1) representative measurements of radioactivity in the highest potential exposure pathways, (2) verification of the accuracy of the effluent monitoring program and modeling of environmental exposure pathways.

The program shall: (1) be contained in the ODAM, (2) conform to the guidance of Appendix I to 10 CFR Part 50 and 10 CFR 72, (3) include the following: (a) Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the ODAM. (b) A Land Use Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the monitoring program are made if required by the results of this census. (c) Participation in an lnterlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring.

5.2 Ground Water Protection Program (GWPP) A program shall be provided to prevent, detect and respond to inadvertent and radiological releases with the potential to reach ground water. The program shall provide: (1) for the prevention of inadvertent/unplanned radiological releases from plant systems, structures and components (SSCs) or during plant evolutions or work practices that represent an elevated risk of experiencing a release of licensed radiological material into the environment.

DAECODAM Page 48 of 280 Rev. 37 (2) aspects for monitoring, detecting and responding to unplanned/unmonitored releases of licensed radioactive material to the environment and a communications/notification plan that addresses internal notifications to management and communications/reporting to State and local stakeholders and regulators for specified events or conditions.

The program shall: (1) be contained in the site administrative control procedure ACP 1411.35, The DAEC Groundwater Protection Program".

(2) implement the Ground Water Protection Initiative Final Guidance Document, NEl-07 -07[Final].

5.3 Sampling Station Locations ODAM Table 5-1 "ENVIRONMENTAL SAMPLE STATIONS" is a list of locations where samples may be collected and does not represent a list of required samples. Environmental monitoring locations are shown on Figures 5-1 and 5-2. DAEC may conduct additional environmental monitoring exclusive of the requirements of Specifications 6.3.2 and ACP 1411.35. DAEC ODAM Page 49 of 280 Rev. 37 t N I 57 DAEC ODAM Figure 5-1 Environmental Monitoring Programs Sampling Near the Duane Arnold Energy Center .. ----*91 -15 I 32 I I I I I 31 I l I I 30 I I I I I 29 I I l 2s I L-----86 GATE 2000feet 55 113 107 DAEC 130 106 133 122 131 73 114 111 Page 50 of 280 107* 68 132 69 N 94 173 169 168 Rev. 37 DAECODAM Figure 5-2 Radiological Environmental Monitoring Program Sampling Stations Outside 0.5 Miles from DAEC __ .... ,..... ..... :;:;:,

*---*-*****--**-*** *--110 ATKINS *10 99 10 MILE RADIUS CENTER POINT eos 109 05a' PALO* 05 37 TODDVILLE 38 *11 39 Page 51 of 280 ALBURNETT 13* Rev. 37 Station Program Number 1 REMP 2 REMP 3 REMP 4 5 REMP 5a REMP 6 REMP 7 REMP 8 REMP 9 10 REMP 11 REMP 12 13 REMP 14 15 REMP 15a GWPP 16 REMP 16a GWPP 17 REMP 18 REMP DAECODAM Table 5-1 ENVIRONMENTAL SAMPLE STATIONS Station Location and Sample Type Location:

Cedar Rapids, 20,800 meters SE Type: TLD Control Airborne Particulate and Iodine Control -Not Currently Active Location:

Marion, 16,900 meters ESE Type: TLD Control Airborne Particulate and Iodine Control -Not Currently Active Location:

Hiawatha, 10,800 meters SE Type: TLD Control Airborne Particulate and Iodine Not used Location:

Palo, 4,500 meters SSW Type: TLD Control Location:

Palo, 3,470 meters SSW Type: TLD Control Airborne Particulate and Iodine Location:

Center Point, 9,660 meters N Type: TLD Control Airborne Particulate and Iodine Location:

Shellsburg, 7,950 meters W Type: TLD Control Airborne Particulate and Iodine Location:

Urbana, 15,000 meters NNW Type: TLD Control Airborne Particulate and Iodine Control -Not Currently Active Not Used Location:

Atkins, 13,600 meters SSW Type: TLD Control Airborne Particulate and Iodine Control -Not Currently Active Location:

Toddville, 4,980 meters E Type: TLD Control Airborne Particulate and Iodine Not Used Location:

Alburnett, 14,500 meters ENE Type: TLD Control Airborne Particulate and Iodine Control Not Used Location:

On-site, 1,050 meters NNW Type: TLD Airborne Particulate and Iodine Location:

On-site, 505 meters NNW Type: Soil Location:

On-site, 520 meters SSE Type: TLD Airborne Particulate and Iodine Vegetation Meteorology Tower Location:

On-site, 520 meters SSE Type: Soil Precipitation Location:

On-site, 1,050 meters N Type: TLD Location:

630 meters NNE Type: TLD Page 52 of 280 Rev. 37 Station Program Number 19 REMP 20 REMP 21 REMP 22 REMP 23 REMP 24 25 26 27 28 REMP 29 REMP 30 REMP 31 REMP 32 REMP 33 REMP 34 REMP 35 REMP 36 REMP 37 REMP 38 REMP 39 REMP 40 REMP 41 REMP 42 REMP 43 REMP 44 REMP 45 REMP DAEC ODAM Table 5-1 ENVIRONMENTAL SAMPLE STATIONS Station Location and Sample Type Location:

On-site, 590 meters NE Type: TLD Location:

On-site, 550 meters ENE Type: TLD Location:

On-site, 515 meters ENE Type: TLD Location:

On-site,=535 meters ESE Type: TLD Location:

On-site,=490 meters SE Type: TLD Not Used Not Used Not Used Not Used Location:

On-site, 730 meters WSW Type: TLD Location:

On-site, 630 meters W Type: TLD Location:

On-site, 640 meters WNW Type TLD Location:

On-site, 1,020 meters NW Type: TLD Location:

On-site, 1, 110 meters NNW Type: TLD Location:

4,340 meters N Type: TLD Location:

3,930 meters NNE Type: TLD Location:

2,800 meters NE Type: TLD Location:

3,500 meters ENE Type: TLD Location:

2,960 meters E Type: TLD Location:

3, 180 meters ESE Type: TLD Location:

2,510 meters SE Type: TLD Location:

Wickiup Hill Learning Center 2,430 meters SSE Type: TLD Airborne Particulate and Iodine Location:

5,680 meters S Type: TLD Location:

4,380 meters SSE Type: TLD Location:

1,590 meters SSW Type: TLD Location:

1,580 meters WSW Type: TLD Location:

1,420 meters W Type: TLD Page 53 of 280 Rev. 37 Station Program Number 46 REMP 47 REMP 48 REMP 49 REMP 50 REMP 51 REMP 52 REMP 53 REMP 54 REMP 55 REMP 56 REMP GWPP 57 REMP 58 REMP 59 60 61 REMP 62 GWPP 63 GWPP 64 GWPP 65 GWPP 66 GWPP 67 GWPP 68 GWPP DAEC ODAM Table 5-1 ENVIRONMENTAL SAMPLE STATIONS Station Location and Sample Type Location:

1,580 meters WNW Type: TLD Location:

1, 760 meters NW Type: TLD Location:

1,680 meters NNW Type: TLD Location:

Lewis Access, upstream of DAEC 6,750 meters NNW Type: Fish Control Surface Water Control Bottom Sediment Control Location:

Plant Intake, 560 meters SE Type: Bottom Sediment Control Surface Water Location:

Plant Discharge, 600 meters SE Type: Bottom Sediment Surface Water Location:

Plant potable water supply Type: Drinking Water Location:

Treated Municipal Water, 13,900 meters SE Type: Ground Water Drinking Water Location:

Inlet to Municipal Water Treatment System, 13,900 meters SE Type: Ground Water Drinking Water Location:

On-site, Production Wells Type: Ground Water Location:

Generic control sample for sampling quality assurance Type: Water, soil, vegetation, milk, sediment, fish, special samples Location:

Farm, 805 meters W Type: Ground Water Vegetation Location:

Farm, 974 meters WSW-SW Type: Ground Water Not Used Not Used Location:

Cedar River, 670 meters SSE Type: Fish Surface Water Location:

Onsite Monitoring Well MW-18A near SE corner of the turbine building Type: Ground Water Location:

Onsite Monitoring Well MW-19A near S wall of the turbine building Type: Ground Water Location:

Onsite Monitoring Well MW-20A near S wall of the turbine building Type: Ground Water Location:

Onsite Monitoring Well MW-21A near S wall of the turbine building Type: Ground Water Location:

Onsite Monitoring Well MW-22A S turbine building wall and W of MW-OBA Type: Ground Water Location:

Onsite Monitoring Well MW-23A S of MW-22A and NW of MW-14A Type: Ground Water Location:

Extraction Well EW-01 A SE of MW-23A and W of MW-14A Type: Ground Water Page 54 of 280 Rev. 37 Station Program Number 69 GWPP 70 71 72 REMP 73 GWPP 74 GWPP 75 GWPP 76 REMP 77 78 79 80 81 82 REMP 83 REMP 84 REMP 85 REMP 86 REMP 87 GWPP 88 GWPP 89 GWPP 90 GWPP 91 REMP 92 GWPP 93 GWPP 94 GWPP 95 GWPP 96 REMP 97 GWPP DAEC ODAM Table 5-1 ENVIRONMENTAL SAMPLE STATIONS Station Location and Sample Type Location:

Extraction Well EW-02A SSE of MW-12A in the Owner Controlled Area Type: Ground Water Not Used Not Used Location:

Farm, 3,200 meters SSW Type: Ground Water Location:

2MH216/1 MH117 electrical vault, West of the Offgas Stack Type: Surface Water Location:

2MH215/1MH116 electrical vault, E. of RB RR, W. of Condensate Storage Tanks Type: Surface Water Location:

2MH207 electrical vault, East of South End of Pump House Type: Surface Water Location:

Farm, 2,888 meters East Northeast Type: Milk Not Used Not Used Not Used Not Used Not Used Location:

On-site, 660 meters SSE Type: TLD Location:

On-site, 620 meters SSE Type: TLD Location:

On-site, 610 meters S Type: TLD Location:

On-site, 660 meters SSW Type: TLD Location:

On-site, 850 meters SW Type: TLD Location:

MH218 electrical vault, East of the Turbine Building Type: Surface Water Location:

MH219 electrical vault, North of Air Compressor Building Type: Surface Water Location:

MH221 electrical vault, Between Air Compressor Building and H2 Skid Type: Surface Water Location:

MH222 electrical vault, North of "B" Well Type: Surface Water Location:

On-site, 1,090 meters NNW Type: TLD Location:

MH202 electrical vault, West of XR1/XR2 Transformers Type: Surface Water Location:

MH213 electrical vault, East of the Pump House Type: Surface Water Location:

MH214 electrical vault, South of "B" Cooling Tower Type: Surface Water Location:

MH217 electrical vault, Southwest of Intake Building Type: Surface Water Location:

Farm, 11,400 meters SSW Type: Vegetation Location:

MH 102 electrical vault, "A" Well Road North of the Substation Type: Vegetation Page 55 of 280 Rev. 37 Station Program Number 98 GWPP 99 REMP 100 GWPP 101 GWPP 102 GWPP 103 GWPP 104 GWPP 105 GWPP 106 GWPP 107 GWPP 107 a REMP 108 109 REMP 110 REMP 111 GWPP 112 GWPP 113 GWPP 114 GWPP 115 GWPP 116 GWPP 117 118 REMP 119 GWPP 120 GWPP DAECODAM Table 5-1 ENVIRONMENTAL SAMPLE STATIONS Station Location and Sample Type Location:

MH103 electrical vault, "A" Well Road West of the Substation Type: Surface Water Location:

Pleasant Creek Lake, 3,880 meters WNW Type: Surface Water Location:

MH206 electrical vault, West of Pump House Type: Surface Water Location:

1 MH109 electrical vault, East of the North End of the Pump House Type: Surface Water Location:

2MH208/1 MH110 electrical vault, Road to Intake Building Type: Surface Water Location:

MH101 electrical vault, North of PAB, East of Security Fence Type: Surface Water Location:

MH 115 electrical vault, South of "A" Cooling Tower Type: Surface Water Location:

MH 114 electrical vault, South of "A" Cooling Tower Type: Surface Water Location:

MH201 electrical vault, South of Turbine Building Type: Surface Water Location:

DAEC Sewage Plant Effluent Type: Surface Water Location:

On-Site: North Drainage Ditch Type: Bottom Sediments Not used Location:

5,890 meters SW Type: Vegetation Location:

12, 700 meters SW Type: Milk Location:

Onsite Monitoring Wells MW01A and MW01 B (SSE) Type: Ground Water Precipitation Location:

Onsite Monitoring Wells MW02A and MW02B (ESE) Type: Ground Water Precipitation Location:

Onsite Monitoring Wells MW03A and MW03B (ESE) Type: Ground Water Location:

Onsite Monitoring Wells MW04A and MW04B (South) Type: Ground Water Precipitation Location:

Onsite Monitoring Wells MW05A and MW05B (SSW) Type: Ground Water Precipitation Location:

Onsite Monitoring Wells MW06A and MW06B (NE) Type: Ground Water Precipitation Not Used Location:

2,230 meters NW Type: Vegetation Location:

2MH209/1 MH111 electrical vault, Road to Intake Building Type: Surface Water Location:

2MH210/1MH112 electrical vault, Road to Intake Building Type: Surface Water Page 56 of 280 Rev. 37 Station Program Number 121 GWPP 122 GWPP 123 GWPP 124 GWPP 125 GWPP 127 GWPP 128 GWPP 129 GWPP 130 GWPP 131 GWPP 132 GWPP 133 GWPP 134 GWPP 135 GWPP 136 GWPP 137 GWPP 138 REMP 161 REMP 162 REMP 163 REMP 164 REMP 165 GWPP 166 GWPP 167 GWPP DAECODAM Table 5-1 ENVIRONMENTAL SAMPLE STATIONS Station Location and Sample Type Location:

2MH211/1MH113 electrical vault, Road to Intake Building Type: Surface Water Location:

Onsite Sluice Pond, in OCA Type: Surface Water Location:

Onsite South Drainage Ditch Type: Surface Water Location:

Onsite North Drainage Ditch Type: Surface Water Location:

Onsite South Storm Drain Outfall Type: Surface Water Location:

Protected Area, North of CST Pit, Monitoring Wells MW07A and MW07B Type: Ground Water Precipitation Location:

Protected Area, CAD Shack, Monitoring Wells MW08A and MW08B Type: Ground Water Precipitation Location:

Protected Area, SE Corner of CST Pit, Monitoring Wells MW09A and MW09B Type: Ground Water Location:

Protected Area, SW Corner of CST Pit, Monitoring Wells MW10A and MW10B Type: Ground Water Location:

On-site Monitoring Wells MW11A and 11 B SE in Owner Controlled Area Type: Ground Water Location:

On-site Monitoring Wells MW12A and MW128 SE in Owner Controlled Area Type: Ground Water Location:

On-site Monitoring Wells MW13A and MW138 SW in Owner Controlled Area Type: Ground Water Location:

On-site Monitoring Wells MW14A and MW14B SSE in Protected Area Type: Ground Water Location:

On-site Monitoring Wells MW1 SA and MW158 SE in Owner Controlled Area Type: Ground Water Location:

On-site Monitoring Wells MW16A and MW16B ENE in Protected Area Type: Ground Water Location:

On-site Monitoring Well MW17C NE in Protected Area Type: Ground Water Location:

21,600 meters WSW Type: Milk Control Vegetation Control Location:

On-site, ISFSI, East Fence Line Type: TLD Location:

On-site, ISFSI, South Fence Line Type: TLD Location:

On-site, ISFSI, West Fence Line Type: TLD Location:

On-site, ISFSI, North Fence Line Type: TLD Location:

On-site Monitoring Wells MW24A ESE in Owner Controlled Area Type: Ground Water Location:

On-site Monitoring Wells MW25A ESE in Owner Controlled Area Type: Ground Water Location:

On-site Monitoring Wells MW26A ESE in Owner Controlled Area Type: Ground Water Page 57 of 280 Rev. 37 Station Program Number 168 GWPP 169 GWPP 170 GWPP 171 GWPP 172 GWPP 173 GWPP DAEC ODAM Table 5-1 ENVIRONMENTAL SAMPLE STATIONS Station Location and Sample Type Location:

On-site Monitoring Wells MW27A and MW27B SE in Owner Controlled Area Type: Ground Water Location:

On-site Monitoring Wells MW28A and MW28B SE in Owner Controlled Area Type: Ground Water Location:

On-site Monitoring Wells MW29A and MW29B SE in Owner Controlled Area Type: Ground Water Location:

On-site Monitoring Wells MW30A and MW30B SE in Owner Controlled Area Type: Ground Water Location:

On-site Monitoring Wells MW31A and MW31 B SE in Owner Controlled Area Type: Ground Water Location:

On-site Monitoring Wells MW32A and MW32B SE in Owner Controlled Area Type: Ground Water Page 58 of 280 Rev. 37 Definitions 0 6.0.1.1 0 6.0.1 USE AND APPLICATION 0 6.0.1.1 Definitions NOTE The defined terms of this section appear in capitalized type and are applicable throughout these OLCOs and Bases ACTIONS CHANNEL CALIBRATION CHANNEL CHANNEL CHECK CHANNEL FUNCTIONAL TEST DAECODAM Definition ACTIONS shall be that part of a ODAM Specification that prescribes Required Actions to be taken under designated Conditions within specified Completion Times. A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds within the necessary range and accuracy to known values of the parameter that the channel monitors.

The CHANNEL CALIBRATION shall encompass the entire channel, including the required sensor, alarm, display, and trip functions, and shall include the CHANNEL FUNCTIONAL TEST. The CHANNEL CALIBRATION may be performed by means of any series of sequential, overlapping, or total channel steps so that the entire channel is calibrated.

A channel is an arrangement of a sensor and associated components used to evaluate plant variables and produce discrete outputs used in logic. A channel terminates and loses its identity where individual channel outputs are combined in logic. A CHANNEL CHECK shall be the qualitative assessment, by observation, of channel behavior during operation.

This determination shall include, where possible, comparison of the channel indication and status to other indications or status derived from independent instrument channels measuring the same parameter.

A CHANNEL FUNCTIONAL TEST shall be the injection of a simulated or actual signal into the channel as close to the sensor as practicable to verify OPERABILITY, including required alarm, interlock, display, and trip functions , and channel failure trips. The CHANNEL FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total channel steps. (continued)

Page 59 of 280 Rev. 37 GASEOUS RADWASTE TREATMENT SYSTEM MEMBER(S)

OF THE PUBLIC MODE OPERABLE-OPERABILITY SITE BOUNDARY SOURCE CHECK UNRESTRICTED AREA DAEC ODAM Definitions 0 6.0.1.1 6.0.1.1 Definitions (continued)

A GASEOUS RADWASTE TREATMENT SYSTEM is any system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system offgases from the primary system and providing delay or holdup for the purpose of reducing radioactivity prior to release to the environment.

MEMBER(S)

OF THE PUBLIC are persons who are not occupationally associated with the Company and who do not normally frequent the DAEC site. The category does not include contractors, contractor employees, vendors, or persons who enter the site to make deliveries or to service equipment.

A MODE shall correspond to any on inclusive combination of mode switch position, average reactor coolant temperature, and reactor vessel head closure bolt tensioning specified in Technical Specifications Table 1.1-1 with fuel in the reactor vessel. A system, subsystem, division, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, division, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s).

The SITE BOUNDARY is that line beyond which the land is neither owned, nor leased, nor otherwise controlled by the Company. UFSAR Figure 1.2-1 identifies the DAEC SITE BOUNDARY.

A SOURCE CHECK is the assessment of channel response when the channel sensor is exposed to a source of radiation.

The UNRESTRICTED AREA is that land (offsite) beyond the SITE BOUNDARY.

Page 60 of 280 Rev. 37 Definitions 0 6.0.1.1 0 6.0.1 USE AND APPLICATION 0 6.0.1.2 Logical Connectors PURPOSE BACKGROUND EXAMPLES DAECODAM The purpose of this section is to explain the meaning of logical connectors.

Logical connectors are used in offsite Dose Assessment Manual (ODAM) to discriminate between, and yet connect, discrete Conditions, Required Actions, Completion Times, Surveillances, and Frequencies.

The only logical connectors that appear in the ODAM are AND and OR. The physical arrangement of these connectors constitutes logical conventions with specific meanings.

Several levels of logic may be used to state Required Actions. These levels are identified by the placement (or nesting) of the logical connectors and by the number assigned to each Required Action. The first level of logic is identified by the first digit of the number assigned to a Required Action and the placement of the logical connector in the first level of nesting (i.e., left justified with the number of the Required Action). The successive levels of logic are identified by additional digits of the Required Action number and by successive indentions of the logical connectors.

When logical connectors are used to state a Condition, Completion Time, Surveillance, or Frequency, only the first level of logic is used, and the logical connector is left justified with the statement of the Condition, Completion Time, Surveillance, or Frequency.

The ODAM uses Logical Connectors in precisely the same manner they are used in the Technical Requirements Manual (TRM) and the Technical Specifications (TS). Examples illustrating the use of logical connectors are found in TS 1.2 and in the TRM T1 .2 Page 61 of 280 Rev. 37 Completion Times 0 6.0.1.3 0 6.0.1 USE AND APPLICATION 0 6.0.1.3 Completion Times PURPOSE BACKGROUND DESCRIPTION DAEC ODAM The purpose of this section is to establish the Completion Time convention and to provide guidance for its use. OLCOs specify minimum requirements for ensuring safe operation of the unit. The ACTIONS associated with a OLCO state Conditions that typically describe the ways in which the requirements of the OLCO can fail to be met. Specified with each stated Condition are Required Action(s) and Completion Times(s).

The Completion Time is the amount of time allowed for completing a Required Action. It is referenced to the time of discovery of a situation (e.g., inoperable equipment or variable not within limits) that requires entering an ACTIONS Condition unless otherwise specified, providing the unit is in a MODE or specified condition stated in the Applicability of the OLCO. Required Actions must be completed prior to the expiration of the specified Completion Time. An ACTIONS Condition remains in effect and the Required Actions apply until the Condition no longer exists or the unit is not within the OLCO Applicability.

If situations are discovered that require entry into more than one Condition at a time within a single OLCO (multiple Conditions), the Required Actions for each Condition must be performed within the associated Completion Time. When in multiple Conditions, separate Completion Times are tracked for each Condition starting from the time of discovery of the situation that required entry into the Condition.

Once a Condition has been entered, subsequent divisions, subsystems, components, or variables expressed in the Condition, discovered to be inoperable or not within limits, will not result in separate entry into the Condition unless specifically stated. The Required Actions of the Condition continue to apply to each additional failure, with Completion Times based on initial entry into the Condition. (continued)

Page 62 of 280 Rev. 37 DAEC ODAM Completion Times 0 6.0.1.3 0 6.0.1.3 Completion Times (continued)

However, when a subsequent division, subsystem, component, or variable expressed in the Condition is discovered to be inoperable or not within limits, the Completion Time(s) may be extended.

To apply this Completion Time extension, two criteria must first be met. The subsequent inoperability:

a. Must exist concurrent with the first inoperability; and b. Must remain inoperable or not within limits after the first inoperability is resolved.

The total Completion Time, as measured from discovery of the subsequent inoperability.

The above Completion Time extensions do not apply to those OLCOs that have exceptions that allow completely separate re-entry into the Condition (for each division, subsystem, component or variable expressed in the Condition) and separate tracking of Completion Times based on this re-entry.

These exceptions are stated in individual OLCOs. The above Completion Time extension does not apply to a Completion Time with a modified "time zero." This modified "time zero" may be expressed as a repetitive time (i.e., .. once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />." where the Completion Time is referenced from a previous completion of the Required Action versus the time of Condition entry) or as a time modified by the phrase "from discovery

... " When "Immediately" is used as a Completion Time, the Required Action should be pursued without delay and in a controlled manner. The ODAM implements Completion Times in precisely the same manner they are applied in the Technical Requirements Manual (TRM) and the Technical Specifications (TS). Examples illustrating the implementation of Completion Times are found in TS 1.3 and in the TRM T1 .3. Page 63 of 280 Rev. 37 Frequency 0 6.0.1.4 0 6.0.1 USE AND APPLICATION 0 6.0.1.4 Frequency PURPOSE The purpose of this section is to define the proper use and application of Frequency Requirements.

DESCRIPTION EXAMPLES DAEC ODAM Each ODAM Surveillance Requirement (OSR) has a specified Frequency in which the Surveillance must be met in order to meet the associated OLCO. An understanding of the correct application of the specified Frequency is necessary for compliance with the OSR. The "specified Frequency" is referred to throughout this section and each of the Specifications of Section 6.0.3.0, Surveillance Requirement (SR) Applicability.

The "specified Frequency" consists of the requirements of the Frequency column of each OSR, as well as certain Notes in the Surveillance column that modify performance requirements.

Sometimes special situations dictate when the requirements of a Surveillance are to be met. They are "otherwise stated" conditions allowed by OSR 7.0.3.0.1.

They may be stated as clarifying Notes in the Surveillance, as part of the Surveillance or both. Situations where a Surveillance could be required (i.e., its Frequency could expire), but where it is not possible or not desired that it be performed until sometime after the associated OLCO is within its Applicability, represent potential OSR 7.0.3.0.4 conflicts.

To avoid these conflicts, the OSR (i.e., the Surveillance or the Frequency) is stated such that it is only "required" when it can be and should be performed.

With an OSR satisfied, OSR 6.0.3.0.4 imposes no restriction.

The use of "met" or "performed" in these instances conveys specific meanings.

A Surveillance is "met" only when the acceptance criteria are satisfied.

Known failure of the requirements of a Surveillance.

even without a Surveillance specifically being "performed," constitutes a Surveillance not "met." "Performance" refers only to the requirement to specifically determine the ability to meet the acceptance criteria.

OSR 7.0.3.04 restrictions would not apply if both the following conditions are satisfied:

a. The surveillance is not required to be performed; and b. The Surveillance is not required to be met or, even if required to be met, is not known to be failed. The ODAM implements Frequency in precisely the same manner they as it is employed in the Technical Requirements Manual (TRM) and the Technical Specifications (TS). Examples illustrating the use of logical connectors are found in TS 1.4 and in the TRM T1 .4. Page 64 of 280 Rev. 36 1/16 LCO Applicability 0 6.0.3.0 6.0.3 Limiting Conditions for Operation (OLCO) Applicability OLCO 6.0.3.0.1 OLCOs shall be met during the MODES or other specified conditions in the Applicability, except as provided in OLCO 6.0.3.0.2.

OLCO 6.0.3.0.2 Upon discovery of a failure to meet an OLCO, the Required Actions of the associated Conditions shall be met, except as provided in OLCO 6.0.3.0.5.

If the OLCO is met or is no longer applicable prior to expiration of the specified Completion Time(s), completion of the Required Action(s) is not required, unless otherwise stated. OLCO 6.0.3.0.3 Not Used. OLCO 6.0 3.0.4 When an OLCO is not met, entry into a MODE or other specified condition in the Applicability shall not be made except when the associated ACTIONS to be entered permit continued operation in the MODE or other specified condition in the Applicability for an unlimited period of time. This OLCO shall not prevent changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit. OLCO 6.0 3.0.4 Exceptions to this OLCO are stated in the individual OLCOs. These exceptions allow entry into MODES or other specified conditions in the Applicability when the associated ACTIONS to be entered allow unit operation in the MODE or other specified condition in the Applicability only for a limited period of time. OLCO 6.0.3.0.4 is only applicable for entry into a MODE or other specified condition in the Applicability in MODES 1 2, and 3. OLCO 6.0.3.0.5 Equipment removed from service or declared inoperable to comply with ACTIONS may be returned to service under administrative control solely to perform testing required to demonstrate its OPERABILITY or the OPERABILITY of other equipment.

This is an exception to OLCO 6.0.3.0.2 for the system returned to service under administrative control to perform the testing required to demonstrate OPERABILITY. (continued)

DAECODAM Page 65 of 280 Rev. 36 1/16 OLCO 6.0.3.0.6 DAECODAM LCO Applicability (continued) 0 6.0.1.3 6.0.3 Limiting Conditions for Operation (OLCO) Applicability (continued)

When An ODAM supported system OLCO is not met solely due to a TS support system OLCO not being met, the ODAM Conditions and Required Actions associated with this supported system are not required to be entered. Only the TS support system OLCO ACTIONS are required to be entered. This is an exception to OLCO 6.0.3.0.2 for the ODAM supported system. When a support system's Required Action (either TS or ODAM) directs a supported system in the ODAM to be declared inoperable or directs entry into Conditions and Required Actions for a ODAM supported system, the applicable ODAM Conditions and Required Actions shall be entered in accordance with ODAM 6.0.3.0.2 When a TS supported system OLCO is not met solely due to a ODAM support system OLCO not being met, the TS supported system Conditions and Required Actions are required to be entered Immediately, under the definition of OPERABILITY, as neither TS LCO 3.0.6 or ODAM OLCO 6.0.3.0.6 apply. When an inoperable Technical Specification support system, structure, or component, (SSC) provides support to a ODAM SSC, which, in turn, supports a supported SSC addressed in the Technical Specifications, Technical Specification LCO 3.0.6 remains applicable.

Page 66 of 280 Rev. 37 OSR Applicability 0 7.0.3.0 0 7.0.3 SURVEILLANCE REQUIREMENT (OSR) APPLICABILITY OSR 7.0.3.0.1 OSR 7.0.3.0.2 OSR 7.0.3.0.3 OSR 7.0.3.0.4 DAECODAM OSRs shall be met during the MODES or other specified conditions in the Applicability for individual OLCOS, unless otherwise stated in the OSR. Failure to meet a Surveillance, whether such failure is experienced during the performance of the Surveillance or between performances of the Surveillance, shall be failure to meet the OLCO. Failure to perform a Surveillance within the specified Frequency shall be failure to meet the OLCO except as provided in OSR 7.0.3.0.3.

Surveillances do not have to be performed on inoperable equipment or variables outside specified limits. The specified Frequency for each OSR is met if the Surveillance is performed within 1.25 times the interval specified in the Frequency, as measured from the previous performance or as measured from the time a specified condition of the Frequency is met. For Frequencies specified as "once," the above interval extension does not apply. If a Completion Time requires periodic performance on a "once per ... " basis, the above Frequency extension applies to each performance after the initial performance.

Exceptions to this OSR are stated in the individual OLCOs. If it is discovered that a Surveillance was not performed within its specified Frequency, then compliance with the requirement to declare the OLCO not met may be delayed, from the time of discovery, up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or up to the limit of the specified Frequency, whichever is more. This delay period is permitted to allow performance of the Surveillance.

If the Surveillance is not performed within the delay period, the OLCO must immediately be declared not met, and the applicable Condition(s) must be entered. When the Surveillance is performed within the delay period and the Surveillance is not met, the OLCO must immediately be declared not met, and the applicable Condition(s) must be entered. Entry into a MODE or other specified condition in the Applicability of an OLCO shall not be made unless the OLCO's Surveillances have been met within their specified Frequency.

This provision shall not prevent entry into MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit. OSR 7.0.3.0.4 is only applicable for entry into a MODE or other specified condition in the Applicability in MODES 1, 2, and 3. Page 67 of 280 Rev. 36 1/16 0 6.1 0 6.1.1 OLCO 6.1.1 APPLICABILITY:

ACTIONS CONDITION A. One or more channels inoperable B. As required by Required Action A.1 and referenced in Table 6.1-1 C. As required by Required Action A.1 and referenced in Table 6.1-1 D. Less than the minimum required channels OPERABLE.

DAEC ODAM Radioactive Liquid Instrumentation 0 6.1.1 RADIOACTIVE LIQUID EFFLUENT CONTROLS Radioactive Liquid Instrumentation The Radioactive Liquid Instrumentation for each function in Table 6.1-1 shall be OPERABLE with their alarm and trip setpoints set to ensure that the limits of Section 6.1.2 are not exceeded.

As shown in Table 6.1-1 REQUIRED ACTION COMPLETION TIME A.1 Enter the condition(s)

Immediately referenced in Table 6.1-1 for the channel(s).

AND A.2 Restore required channel(s) to 30 days OPERABLE status. B.1 Obtain at least two samples and Prior to release analyze in accordance with Section 6.1.2 and Table 7.1-2 AND B.1 Independently verify release Prior to release rate calculations and discharge valving by technically qualified Facility Staff member. C. 1 Obtain sample and analyze for Once per 8 Hours either gross beta/gamma or gamma radioactivity.

D.1 Estimate flow rate at least once Immediately per batch. (continued)

Page 68 of 280 Rev. 37 Radioactive Liquid Instrumentation 0 6.1.1 0 6.1.1 Radioactive Liquid Instrumentation (continued CONDITION REQUIRED ACTION COMPLETION TIME E. Required Action E.1 Explain in next Annual Next submittal of the and associated Radioactive Material Release Annual Radioactive Completion Time of Report why the instrument was Material Release Condition A not not made operable in a timely Report met. manner. DAECODAM Page 69 of 280 Rev. 37 SURVEILLANCE REQUIREMENTS Radioactive Liquid Instrumentation 0 6.1.1 ------------------------------------------------------

N 0 TE-----------------------------------------------

1 n strum entati on shall be OPERABLE and in service except that channels out of service are permitted for the purpose of required tests, checks, and calibrations without declaring the channel to be inoperable.

SURVEILLANCE FREQUENCY OSR 7.1.1.1 Perform CHANNEL CHECK 24 Hours OSR 7.1.1.2 Perform SOURCE CHECK 24 Hours OSR 7.1.1.3 Perform SOURCE CHECK 30 Days OSR 7.1.1.4 Perform CHANNEL FUNCTIONAL TEST 92 Days OSR 7.1.1.5 Perform CHANNEL CALIBRATION 18 Months OSR 7.1.1.6 Perform Monitor Setpoint Calculation.

18 Months OSR 7.1.1.7 Perform CHANNEL FUNCTIONAL TEST Prior to release OSR 7.1.1.8 Perform CHANNEL CALIBRATION Prior to release OSR 7.1.1.9 Perform Monitor Setpoint Calculation.

Prior to release DAEC ODAM Page 70 of 280 Rev. 37 TABLE 6.1-1 /7.1-1 Radioactive Liquid Instrumentation 0 6.1.1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION Minimum Conditions Instrument Applicability Channels Referenced from Surveillance Required Action Requirements Operable A.1 1. Gross Radioactive Monitors Providing Automatic Termination of Release OSR 7.1.1.1 <al OSR 7.1.1.2 (bl During 1 B OSR 7.1.1.7 (dl a. Liquid Radwaste Effluent Line Releases (e) OSR 7.1.1.8 <cl OSR 7.1.1.9 2. Gross Radioactive Monitors Not Providing Automatic Termination of Release a. RHR Service Water System During 1 OSR 7 .1.1.1 <al Releases OSR 7.1.1.3 b. General Service Water During 1 c OSR 7.1.1.4 <el System Releases OSR 7.1.1.5<cJ RHRSW/ESW Rupture Disc During OSR 7.1.1.6 c. 1 Effluent Line Releases 3. Flow Rate Measurement Devices a. Liquid Radwaste Effluent Line During 1 OSR 7.1.1.1 <a> Releases D (f) During OSR 7.1.1.7 b. Liquid Radwaste Dilution Line Releases 1 OSR 7.1.1.8 TABLE NOTATIONS (a) During releases via this pathway. (b) On any day on which a release is made, a SOURCE CHECK shall be made at least once, prior to the first release. ( c) The CHANNEL CALIBRATION shall include the use of a known radioactive source (traceable to the NIST radiation measurement system or acceptable non-NIST standards) positioned in a reproducible geometry with respect to the sensor and emitting beta or gamma radiation in the range measured by the channel. CHANNEL CALIBRATION may normally be done during refueling outages. (d) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway if the following condition exists: 1. Instrument indicates measured levels above the alarm/trip setpoint. (e) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exist: 1. Instrument indicates measured levels above the alarm/trip setpoint.

2. Circuit failure. 3. Instrument indicates a downscale failure. 4. Instrument controls not set in operate mode. (!J CHANNEL CHECK shall consist of verifying indication of flow during periods of release. CHANNEL CHECK shall be made at least once daily on any day on which continuous, periodic, or batch releases are made. DAECODAM Page 71 of 280 Rev. 37 0 6.1 Radioactive Liquid Instrumentation 0 6.1.1 RADIOACTIVE LIQUID EFFLUENT CONTROLS 0 6.1.2 Liquid Effluent Concentration OLCO 6.1.2 The concentration of radioactive material in liquid effluent released from the site to the UNRESTRICTED AREA shall not exceed ten times the concentrations specified in 10 CFR 20, Appendix B, Table 2, Column 2 to 1 O CFR 20.1001 -20.2402. APPLICABILITY:

At all times. ACTIONS A. CONDITION Concentration of radioactive material released from site to UNRESTRICTED AREAS not within the limit. DAECODAM REQUIRED ACTION COMPLETION TIME A.1 Restore concentration Immediately to within limits. Page 72 of 280 Rev. 37 Radioactive Liquid Effluent Concentration 0 7.1.2 SURVEILLANCE REQUIREMENTS

NOTE------------------------------------------

Refer to ODAM Table 7.1-2 for details concerning Sampling and Analysis OSR 7.1.2.1 OSR 7.1.2.2 OSR 7.1.2.3 DAEC ODAM SURVEILLANCE

N 0 TE--------------------------

P o rti on s of each sample are "split out" and added to the Monthly and Quarterly Composite sample. Sample the Batch Release. The results of pre-release analyses shall be used with the calculation methods in the ODAM to establish trip setpoints for batch releases to assure that the concentration at the UNRESTRICTED AREA boundary does not exceed the limit in OLCO 6.1.2. ----------------------------N 0 TE--------------------------

P o rtio ns of each sample are split out and added to the Monthly and Quarterly Composite sample. -----------------------------N 0 TE--------------------------

1 n the event of a positive identification of reactor by-product radioactivity in the service water, additional sampling and analysis shall be performed as specified in Table 7.1-2, Table Items B.2 through B.5. Sample the Continuous Release during releases to the environment via this pathway. AND Analyze the sample from the release for Gross Beta/Gamma.

Analyze the sample from the release for Principal Gamma Emitters and 1-131. Page 73 of 280 FREQUENCY PRIOR TO EACH RELEASE PRIOR TO EACH RELEASE 7 Days (continued)

Rev. 37 OSR 7.1.2.4 OSR 7.1.2.5 OSR 7.1.2.6 OSR 7.1.2.7 DAECODAM Radioactive Liquid Effluent Concentration 0 7.1.2 Analyze the sample from the release for Principal Gamma Emitters and 1-131. Analyze the "Monthly" Composite sample for Tritium. --------------------------N 0 TE--------------------------

F or Service Water, this OSR is only required following a positive identification of reactor product radioactivity in the sample as determined during OSR 7.1.2.3 or OSR 7.1.2.5. -------------------------

N 0 TE----------------------------

F or "clean" water systems, this OSR is only required following a positive identification of reactor by-product radioactivity in the sample as determined during OSR 7 .1.2.4. -------------------------N 0 TE----------------------------

F or GWPP Mitigation system, this OSR is only required following a positive identification of a radioactive reactor by-product in the sample as determined during OSR 7.1.2.3. Analyze the Quarterly Composite sample for Sr-89, Sr-90, Fe-55 PRIOR TO EACH RELEASE 30 Days 92 Days Analyze the "Monthly" Composite sample for Gross 30 Days Alpha. Page 7 4 of 280 Rev. 37 Radioactive Liquid Effluent Concentration 0 6.1.2 TABLE 7.1-2 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Liquid Release Type Surveillance Table Type of Activity Requirements item/note Analysis A. Radwaste Tanks OSR 7.1.2.1 A.1: Each Principal Gamma Batch Release Batch Emmittersc OSR 7.1.2.4 OSR 7.1.2.2 l-131c OSR 7.1.2.1 A.2: (d) (b) H-3 OSR 7.1.2.5 OSR 7.1.2.7 Gross alpha OSR 7.1.2.1 A.3: (d)(b) Sr-89, Sr-90 OSR 7.1.2.6 Fe-55 8. Continuous Service OSR 7.1.2.3 8.1: (d) Gross beta/gamma Water Release OSR 7.1.2.3 8.2: (d) Principal Gamma Sample Points: Emitters

  • General Services Water 1-131
  • RHR Service Water System B 8.4: (b),(d) OSR 7.1.2.5 H-3 OSR 7.1.2.7 Gross alpha OSR 7.1.2.6 8.5: (b),(d) Sr-89, Sr-90 Fe-55 C. "Clean" Systems OSR 7.1.2.1 C.1: Principal Gamma Batch Release OSR 7.1.2.4 Emitters(!)

1-131(1) Sample Points: OSR 7.1.2.5 C.2: (b) (d) (e)

H-3(1)

  • CST Pit Rain Water
  • Transformer Pit OSR 7.1.2.6 C.3: (b)(d) Sr-89, Sr-90
  • Neutralizing Tank 1T022
  • FRAC tanks Fe-55 D. GWPP Mitigation System OSR 7.1.2.3 D.1: Principal Gamma Emitters Continuous Release 1-131 (c) OSR 7.1.2.5 D.2: (b)(d)(e)

H-3(fl OSR 7.1.2.7 Gross Alpha OSR 7.1.2.6 D.3: (b)(dl Sr-89, Sr-90 Fe-55 DAEC ODAM Page 75 of 280 Lower Limit of Detection (LLD)(a) (µCi/ml) 5x10-7 1x10-5 1 x 10-5 1x10-7 5 x 10-8 1x10-5 1x10-7 5 x 10-7 1x10-5 1x10-5 1x10-7 5 x 10-8 1 x 10-6 5 x 10-7 1x10-5 1 x 10-5 5 x 10-8 1 x 10-6 5.0X 10-7 1.0 x 10-6 1.0X 10-5 1.0 x 10-7 5.0 x 10-8 1.0X10-6 Rev. 37 TABLE NOTATIONS Radioactive Liquid Effluent Concentration 0 6.1.2 <alThe LLD is defined, for purposes of these controls, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal. DAEC ODAM Page 76 of 280 Rev. 37 Radioactive Liquid Effluent Concentration 0 6.1.2 For a particular measurement, which may include radiochemical separation:

4.66 Sb LLD Ex Vx 2.22E6x e-w where: LLD is the "a priori" lower limit of detection as defined above (microcuries per unit mass or volume) and where: Sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute) Eis the counting efficiency (counts per disintegration)

Vis the sample size (units of mass or volume) 2.22E6 is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield, when applicable, "A is the radioactive decay constant for the particular radionuclide (sec-\ and f.. t for effluents is the elapsed time between the midpoint of sample collection and the time of counting (sec-1)_ Alternatively, exp may be replaced by At e-212 1 e. e-212 J -e-211 Where: t 1 is the total sampling time or sample compositing time t 2 is the elapsed time between the end of sample collection and the time of counting.

It should be recognized that the LLD is defined as an .9. priori (before the fact) limit representing the capability of a measurement system and not as an £!.posteriori (after the fact) limit for a particular measurement.

Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions with typical values of E, V, Y, and Dt for the radionuclides Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144. Occasionally background fluctuations, unavoidably small sample sizes, interfering radionuclides, or other uncontrollable circumstances may render these LLDs unachievable.

When calculating the LLD for a radionuclide determined by gamma ray spectrometry, the background may include the typical contributions of other radionuclides normally present in the samples. The background count rate of a Ge(Li) detector is determined from background counts that are determined to be within the full width of the specific energy band used for the quantitative analysis for that radionuclide.

The principal gamma emitters for which the LLD specification will apply are exclusively the following radionuclides:

Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137 and Ce-141. Ce-144 shall be measured, but with an LLD of 5E-6. This list does not mean that only these nuclides are to be detected and reported.

Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported.

Nuclides which are below the LLD for the analyses should not be reported as being present at the LLD level. When unusual circumstances result in LLDs higher than required, the reasons shall be documented in the Annual Radioactive Material Release Report. (b) A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquids released. ( c) In the event a gross or y analysis is performed in lieu of an isotopic analysis before a batch is discharged, a sample shall be analyzed for principal gamma emitters afterward. (d) Analysis may be performed after release. (e) Analysis at a frequency of less than 30 days is allowed. (I) If liquids from these systems are released from the site via a pathway that is NOT directly to the Cedar River, the required LLDs of Table 6.3.2 are applicable.

DAECODAM Page 77 of 280 Rev. 37 Dose Due to Liquid Radioactive Effluents 0 6.1.3 0 6.1 RADIOACTIVE LIQUID EFFLUENT CONTROLS 0 6.1.3 Dose Due to Liquid Radioactive Effluents OLCO 6.1.3 The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released to the UNRESTRICTED AREA shall not exceed: APPLICABILITY:

ACTIONS 1.5 mrem to the total body during any calendar quarter, 5.0 mrem to any organ during any calendar quarter, 3.0 mrem to the total body during any calendar year, or 10.0 mrem to any organ during any calendar year. At All Times CONDITION REQUIRED ACTION COMPLETION TIME A. Calculated dose from the A.1 Prepare and submit a Special 30 days release of radioactive Report to the Commission materials in liquid which identifies the cause(s) effluents exceeds limits. for exceeding the limit and defines the action to be taken. DAEC ODAM Page 78 of 280 Rev. 37 Dose Due to Liquid Radioactive Effluents 0 7.1.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY OSR 7.1.3.1 In any quarter in which radioactive liquid effluent is 30 Days discharged, an assessment shall be performed in accordance with the ODAM in order to verify that the cumulative dose commitment does not exceed the limits in OLCO 6.1.3. DAEC ODAM Page 79 of 280 Rev. 37 Liquid Waste Treatment 0 6.1.4 0 6.1 0 6.1.4 OLCO 6.1.4 APPLICABILITY:

ACTIONS A. CONDITION Radioactive liquid waste being discharge without treatment and in excess of limits. DAEC ODAM RADIOACTIVE LIQUID EFFLUENT CONTROLS Liquid Waste Treatment Appropriate liquid radwaste equipment shall be used to treat any untreated batch of liquid waste prior to discharge when a released analysis indicates a radioactivity concentration (exclusive of tritium and dissolved gases) of 0.01 µCi/ml or higher. At all times. REQUIRED ACTION COMPLETION TIME A.1 Prepare and submit a Special 30 days Report to the Commission which includes identification of inoperable equipment or subsystems and the reason, actions taken to restore the inoperable equipment, and description of action(s) taken to prevent recurrence.

Page 80 of 280 Rev. 37 Liquid Waste Treatment 0 7.1.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY OSR 7.1.4.1 Each radioactive liquid waste batch shall be PRIOR TO EACH sampled and analyzed in accordance with Section RELEASE 7.1.2 and Table 7.1-2. DAECODAM Page 81 of 280 Rev. 37 Liquid Holdup Tanks 0 6.1.5 0 6.1 0 6.1.5 OLCO 6.1.5 APPLICABILITY:

ACTIONS RADIOACTIVE EFFLUENT CONTROLS Liquid Holdup Tanks The quantity of radioactive material contained in the unprotected outdoor tanks shall be limited to less than or equal to 50 Curies, excluding tritium and dissolved or entrained noble gases. At all times. ----------------------------------------------------NOTE-------------------------------------------------------

Tanks included in this specification are those outdoor tanks that are not surrounded by liners, dikes, or walls capable of holding the tanks' contents and that do not have tank overflows and surrounding area drains connected to the liquid radwaste treatment system. (The liquid radwaste storage tanks (1T-88 and 1T-269) located in the Low-Level Radwaste Processing and Storage Facility are considered unprotected outdoor tanks.) CONDITION A. Quantity of radioactive material in the tanks exceeding the limit. REQUIRED ACTION A.1 Suspend all additions of the radioactive material to the tanks. AND A.2 Reduce tank contents to within the limit. A.3 Describe in next Annual Radioactive Effluent Release Report the events leading to this condition.

COMPLETION TIME Immediately 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> 1 year A.4 Prepare and submit a 30 Days Special Report to the Commission which identifies the cause(s) for exceeding the limit and defines the action to be taken. (10CFR20.2203)

DAEC ODAM Page 82 of 280 Rev. 37 Liquid Holdup Tanks 0 7.1.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY OSR 7.1.5.1 When radioactive materials are being added to a 7 Days tank, the quantity of radioactive material contained in all tanks shall be determined to be within the 50 curie limit by analyzing a representative sample of the tanks' contents.

DAECODAM Page 83 of 280 Rev. 37 Radioactive Gaseous Effluent Instrumentation 0 6.2.1.1 06.2 0 6.2.1.1 OLCO 6.2.1.1 APPLICABILITY:

ACTIONS CONDITION A. One or more channels inoperable.

B. As required by Required Action A.1 and referenced in Table 6.2-1 C. As required by Required Action A.1 and referenced in Table 6.2-1 DAEC ODAM RADIOACTIVE GASEOUS EFFLUENT CONTROLS Radioactive Gaseous Effluent Instrumentation The Radioactive Gaseous Effluent Instrumentation for each function in Table 6.2-1 shall be OPERABLE During releases via this pathway. REQUIRED ACTION COMPLETION TIME A.1 Enter the condition referenced Immediately in Table 6.2-1 for the channel. AND A.2 Restore required channel(s) to 30 days OPERABLE status. B.1 Collect gaseous grab sample. once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> AND B.2 Analyze sample for radioactivity.

Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of sample collection C. 1 Establish preplanned alternate 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> monitoring method. OR C.2.1 Collect gaseous grab sample. once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> AND C.2.2 Analyze sample for radioactivity.

Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of sample collection (continued)

Page 84 of 280 Rev. 37 ACTIONS (continued)

D. As required by D.1 Required Action A.1 and referenced in Table 6.2-1 AND D.2 AND D.3 E. As required by E.1 Required Action A. 1 and referenced in Table 6.2-1 F. As required by F.1 Required Action A.1 and referenced AND in Table 6.2-1 F.2 G. Minimum required G.1 instrumentation not returned to OPERABLE status within 30 days. DAECODAM Radioactive Gaseous Effluent Instrumentation 0 6.2.1.1 Establish continuous sampling 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> with auxiliary equipment.

Collect sample(s)

Once per 7 days Analyze sample(s) for Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of radioactivity.

sample collection Estimate flow rate initially and 8 Hours whenever operation of a main exhaust fan combination is changed in the system. Collect gaseous grab sample. once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Analyze sample for radioactivity.

Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of sample collection Explain in next Annual Radioactive Material Release Report why the instrument was not made operable in a timely manner. Page 85 of 280 Rev. 37 Radioactive Gaseous Effluent Instrumentation 0 7.2.1.1 SURVEILLANCE REQUIREMENTS

NOTE-----------------------------------------------

1 nstrumentation shall be OPERABLE and in service except that channels out of service are permitted for the purpose of required tests, checks and calibrations without declaring the channel to be inoperable.

SURVEILLANCE FREQUENCY OSR 7.2.1.1.1 Perform CHANNEL CHECK 24 Hours --------------------------N 0 TE-----------------------------

During releases via this pathway. ----------------------------------------------------------------

OSR 7.2.1.1.2 Perform CHANNEL CHECK 7 Days OSR 7.2.1.1.3 Perform SOURCE CHECK 30 Days OSR 7.2.1.1.4 Determine the monitor setpoints in accordance with 92 Days the method described in the ODAM. OSR 7.2.1.1.5 Perform CHANNEL FUNCTIONAL TEST 92 Days OSR 7.2.1.1.6 Determine the monitor setpoints in accordance with 18 Months the method described in the ODAM. OSR 7.2.1.1.7 Perform CHANNEL CALIBRATION 18 Months DAECODAM Page 86 of 280 Rev. 37 Radioactive Gaseous Effluent Instrumentation 0 6.2.1.1 I TABLE 6.2-1 I TABLE 7.2-1 NORMAL RANGE RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Instrument 1.0ffgas Stack Monitoring System a. Noble Gas Activity Monitor b ...

..

c.

..... d. Effluent Flow Measuring Device e. Sample Flow Measuring Device 2. Reactor Building Exhaust Vent . . .

a. Noble Gas Activity Monitor .. *****-******-*?..:

___

..

.... Minimum Channels Ooerable ab

            • . ..... --. d. Effluent Flow Measuring
e. Sample Flow Measuring Device 3. Turbine Building Exhaust Vent Monitoring System a. Noble Gas Activity Monitor b .... .. .. . C.:
d. Effluent Flow Measuring Device e. Sample Flow Measuring Device 4. Low-Level Radwaste Processing and Storage Facility Exhaust Vent --
a. Noble Gas Activity Monitor b.
c.

..... d. Effluent Flow Measuring Device e. Sample Flow Measuring Device DAECODAM Conditions Referenced from Required Action A.1 c D D E Surveillance Requirements OSR 7.2.1.1.1, OSR 7.2.1.1.3 OSR 7.2.1.1.4, OSR 7.2.1.1.5(dJ, OSR 7.2.1.1.7(cJ OSR 7.2.1.1.2 OSR 7.2.1.1.2 OSR 7.2.1.1.1, OSR 7.2.1.1.5, OSR 7.2.1.1.7 E ......................

-..................

1, OSR 1.5, B D D E E B D D E E F D D E E Page 87 of 280 OSR 7.2.1.1.7

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

-.... -.............

.. OSR 7.2.1.1.1, OSR 7.2.1.1.3, OSR 7.2.1.1.5(dl, OSR 7.2.1.1.6, OSR 7.2.1.1.7(cJ OSR 7.2.1.1.2 OSR 7.2.1.1.2 OSR 7.2.1.1.1, OSR 7.2.1.1.5, OSR 7.2.1.1.7

                • -**-*-*--*--*-****-****** . . .. ******-***************-

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

.. OSR 7.2.1.1.1, OSR 7.2.1.1.5, OSR 7.2.1.1.7 OSR 7.2.1.1.1, OSR 7.2.1.1.3, OSR 7.2.1.1.5(dl, OSR 7.2.1.1.6, OSR 7.2.1.1.?(cl OSR 7.2.1.1.2 OSR 7.2.1.1.2 OSR 7.2.1.1.1, OSR 7.2.1.1.5, OSR 7.2.1.1.7

                    • -*-*********

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

---**** .. ******************--*

.. *-*-*--OSR 7.2.1.1.1, OSR 7.2.1.1.5, OSR 7.2.1.1.7

                                • -

OSR 7.2.1.1.1, OSR 7.2.1.1.3 OSR 7.2.1.1.5(dl, OSR 7.2.1.1.6 OSR 7.2.1.1.?(c)

OSR 7.2.1.1.2 OSR 7.2.1.1.2 OSR 7.2.1.1.1, OSR 7.2.1.1.5, OSR 7.2.1.1.7

                                                                                                • -*********************

.. --.......................................

-...............

-*******-OSR 7.2.1.1.1, OSR 7.2.1.1.5, OSR 7.2.1.1.7 continued Rev. 37 Radioactive Gaseous Effluent Instrumentation 0 6.2.1.1 TABLE 6.2-1 NOTATIONS*

<alouring releases via this pathway. (bl Instrumentation shall be OPERABLE and in service except that channels out of service are permitted for the purpose of required tests, checks and calibrations without declaring the channel to be inoperable.

TABLE 7.2-1 NOTATIONS (c) The CHANNEL CALIBRATION shall include the use of a known radioactive source (traceable to the NIST radiation measurement system or other acceptable non-NIST standards) positioned in a reproducible geometry with respect to the sensor and emitting beta and/or gamma radiation in the range measured by the channel in accord with established station calibration procedures.

Alternatively, after the initial calibration, noble gas activity monitors maybe calibrated by laboratory analyzed gas samples collected and analyzed per Table 7.2-2, item A. (d) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exist: 1.0 Instrument indicates measured levels above the alarm setpoint.

2.0 Circuit failure. 3.0 Instrument indicates a downscale failure. 4.0 Deleted. DAEC ODAM Page 88 of 280 Rev. 37 Offgas Radioactive Gaseous Effluent Instrumentation 0 6.2.1.2 06.2 0 6.2.1.2 OLCO 6.2.1.2 APPLICABILITY:

ACTIONS CONDITION A. One or more channels inoperable.

B. As required by Required Action A.1 and referenced in Table 6.2-2 DAEC ODAM RADIOACTIVE GASEOUS EFFLUENT CONTROLS Offgas Radioactive Gaseous Effluent Instrumentation The Offgas Radioactive Gaseous Effluent Instrumentation for each Function in Table 6.2-2 shall be OPERABLE When the Offgas system is operating.

REQUIRED ACTION COMPLETION TIME A.1 Enter the Condition referenced Immediately in table 6.2-2 for the channel. B.1 Verify the charcoal bed of the Immediately offgas system is not bypassed.

AND B.2 Verify offgas stack noble gas Immediately activity monitor is operable.

AND B.3 Restore channel(s) to 30 Days OPERABLE status. (continued)

Page 89 of 280 Rev. 37 ACTIONS (continued)

CONDITION C. As required by C.1 Required Action A.1 and referenced in Table 6.2-2 AND C.2.1 AND C.2.2 AND C.3.1 OR C.3.2 AND C.4 D. Required Action D.1 and associated Completion Time of Condition B or C not met. DAEC ODAM Radioactive Gaseous Effluent Instrumentation 0 6.2.1.2 REQUIRED ACTION COMPLETION TIME Verify the charcoal bed of the Immediately offgas system is not bypassed.

Obtain a gas grab sample. Once per 7 Days Analyze the grab sample. 24 Hours Verify offgas stack noble gas Immediately activity monitor is operable.

Verify one post-treatment Immediately monitor is OPERABLE.

Restore channel(s) to 30 Days OPERABLE status. Submit a Special Report to the 30 Days NRC identifying the cause(s) for exceeding the limit and define the corrective actions taken. Page 90 of 280 Rev. 37 Offgas Radioactive Gaseous Effluent Instrumentation 0 7.2.1.2 SURVEILLANCE REQUIREMENTS

N 0 TE--------------------------------------------

1 n strum en ta ti on shall be OPERABLE and in service except that channels out of service are permitted for the purpose of required tests, checks and calibrations without declaring the channel to be inoperable.

SURVEILLANCE FREQUENCY OSR 7.2.1.2.1 Perform CHANNEL CHECK 24 Hours OSR 7 .2.1.2.2 Perform SOURCE CHECK 30 Days OSR 7.2.1.2.3 Perform CHANNEL FUNCTIONAL TEST 92 Days OSR 7.2.1.2.4 Determine the monitor setpoints in accordance with 92 Days the method described in the ODAM. OSR 7.2.1.2.5 Perform CHANNEL CALIBRATION 18 Months OSR 7.2.1.2.6 Perform FUNCTIONAL TEST of the CHARCOAL 48 Months BED BYPASS VALVE LOGIC SYSTEM DAECODAM Page 91 of 280 Rev. 37 Offgas Radioactive Gaseous Effluent Instrumentation 0 6.2.1.2 TABLE 6.2-2 RADIATION MONITORING INSTRUMENTATION Instrumentation Minimu Conditions Surveillance Requirements m Referenced Channel from s Required Opera bl Action A.1 e Offgas Post-Treatment 1 B OSR 7.2.1.2.1, OSR 7.2.1.2.2, Radiation Monitors (a) OSR 7.2.1.2.3(e>, OSR 7.2.1.2.4, OSR 7 .2.1.2.5, OSR 7.2.1.2.6 Offgas Pre-Treatment 1 c OSR 7.2.1.2.1, OSR 7.2.1.2.2, Radiation Monitors (b) OSR 7.2.1.2.3(e), OSR 7.2.1.2.4, OSR 7.2.1.2.5 TABLE 6.2.2 NOTATIONS (a) The monitors shall be set to initiate immediate closure of the charcoal bed bypass valve at a setting equivalent to or below the dose rate limits in ODAM Section 6.2.2. {b) The monitors shall be set to initiate an alarm if the monitor exceeds a trip setting equivalent to 1.0 Ci/sec of noble gases after 30 minutes delay in the offgas holdup line. (e) The CHANNEL FUNCTIONAL TEST for this instrument shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exist: a. Instrument indicates measured levels above the alarm/trip setpoint.

b. Instrument indicates a downscale failure. c. Instrument controls not set in operate mode. DAEC ODAM Page 92 of 280 Rev. 37 Gaseous Effluent Dose Rate 06.2.2 06.2 06.2.2 OLCO 6.2.2 APPLICABILITY:

ACTIONS CONDITION RADIOACTIVE GASEOUS EFFLUENT DOSE RATE Gaseous Effluent Dose Rate The dose rate in the UNRESTRICTED AREA due to the release of gaseous effluents shall not exceed: a. 500 mrem/year to the total body or 3000 mrem/year to skin due to radioactive noble gas; and b. 1500 mrem/year to any organ due to 1-131, 1-133, H-3, and to radioactive particulates having half-lives of 8 days or more. During Releases.

REQUIRED ACTION COMPLETION TIME A. Dose rate not within A.1 Reduce the release rate Immediately limits. within limit. DAEC ODAM Page 93 of 280 Rev. 37 Gaseous Effluent Release Concentration 07.2.2 SURVEILLANCE REQUIRMENTS

NOTE------------------------------------------

  • Refer to ODAM Table 7.2-2 for details concerning Sampling and Analysis OSR 7.2.2.1 OSR 7.2.2.2 OSR 7.2.2.3 OSR 7.2.2.4 OSR 7.2.2.5 DAEC ODAM SURVEILLANCE Monitor for Radioactive Noble Gas gamma activity.

Sample the Effluent Stream for 1-131. Analyze for 1-131within48 hours of sample pull.

Retain samples for Quarterly Composite analysis. (OSR 7.2.2.8) Sample the Effluent Stream for particulates.

Analyze for principal gamma emitters from particulates within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of sample pull*. FREQUENCY Continuously Continuously 7 Days Following an increase of more than 50% as indicated by the Treat rad. monitor* Continuously 7 Days Following an increase of more than 50% as indicated by the Treat rad. monitor* Perform gas grab sample of the effluent stream 30 Days and analyze for principal gamma emitters.

NOTE----------------------

Applies only for the Reactor Building and Off gas Stack effluent streams. Perform gas grab sample of the effluent stream and analyze for principal gamma emitters.

Page 94 of 280 Following an increase of more than 50% as indicated by the Treat rad. monitor (continued)

Rev. 37 Gaseous Effluent Concentration 07.2.2 SURVEILLANCES (continued)

SURVEILLANCE FREQUENCY OSR 7.2.2.6 Perform grab sample of the effluent stream and 92 Days analyze for Tritium. ----------------------------

N 0 TE--------------------

OSR 7.2.2.7 Applies only for the Reactor Building and Off When the Reactor Head gas Stack effluent streams. is removed ---------------------------------------------------------

Perform grab sample of the effluent stream and analyze for Tritium. OSR 7.2.2.8 Analyze Particulate Composite sample for 92 Days Sr-89, Sr-90, Gross Alpha *Refer to ODAM Table 7.2-2 for details concerning Sampling and Analysis DAEC ODAM Page 95 of 280 Rev. 37 Gaseous Effluent Release Concentration 0 7.2.2 TABLE 7.2-2 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Gaseous Release Type Surveillance Frequency Type of Activity Lower Limit of Requirements Analysis Detection (LLD)<al A. Offgas Stack, and Elevated Gas Grab Sample Reactor Building Vent OSR 7.2.2.5 (bl Post-Treat Principal Gamma 1 x 1 o-4<d) Readings (bl Emitters OSR 7.2.2.7 <cl Reactor Head Tritium Grab 1 x 10-5 Removed (c) Sample (H-3) B. Offgas Stack, Reactor Routine OR Building Vent, Turbine OSR 7.2.2.2 <el elevated Charcoal Sample 1 x 10-12 Building Vent, and Post-Treat 1-131 Low-Level Radwaste Readings (fl Processing Storage Routine OR Particulate Sample Facility Vent OSR 7.2.2.3 (el elevated Principal Gamma 1 x 10-11(d) Post-Treat Emitters (1-131, Readings <fl Others) Gas Grab Sample OSR 7.2.2.4 Routine Principal Gamma 1 x 10-4(d) Emitters OSR 7.2.2.6 Routine Tritium Grab 1 x 10-5 Sample (H-3) Composite Particulate Sample 1 x 10-11 OSR 7.2.2.8 <el Routine <9 l Sr-89, Sr-90 Gross Alpha 1 x 10-11 Fe-55 1 x 10-11 C. Offgas Stack, Reactor Building Vent, Turbine Monitor Building Vent, and OSR 7.2.2.1 Continuous Radioactive Noble 1 x 10-5 Low-Level Radwaste Gas gamma Processing and activity Storage Facility TABLE NOTATIONS

<al Units for the listed values are µCi/cc. See Table 7.1-2 for a definition of the lower limit of detection (LLD). (bl Monthly analyses shall be performed following an increase of more than 50% in the steady state releases as indicated by the post-treat noble gas activity monitor, after factoring out the effect due to a change in reactor power, or other minor temporary fluctuations not related to fuel integrity such as line up changes for condensate de-mineralizers or reactor water cleanup. (c) A H-3 grab sample will also be taken from the Offgas Stack or Reactor Building Vent when the reactor head is removed. DAECODAM Page 96 of 280 Rev. 37 Gaseous Effluent Concentration 0 7.2.2 (dJ The principal gamma emitters for which the LLD will apply are exclusively the following radionuclides:

Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99,Cs--134, Cs-137, Ce-141 and Ce-144 for particulate emissions.

This list does not mean that only these nuclides are to be detected and reported.

Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported.

Nuclides which are below the LLD may be reported as "less than" their respective LLD and should not be reported as being present at the LLD of the nuclide. Each measured radionuclide concentration is used in a required concentration or dose calculation only if it is detected at or above the LLD. When unusual circumstances persist more than 30 days and cause LLD higher than required, the reasons shall be documented in the Annual Radioactive Material Release Report. (e) The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculations made in accordance with Sections 6.2.2, 6.2.3, and 6.2.4. <IJ Sample media shall be changed at least once per seven days and the analysis completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing (or after removal from the sampler).

Analyses shall also be performed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> following an increase of more than 50% in the steady state release as indicated by the post-treat noble gas activity monitor, after factoring out the effect due to a change in reactor power. When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or less are analyzed, the corresponding LLD may be increased by a factor of 10. <9 l A quarterly composite sample shall include an equal fraction of each weekly particulate sample collected during the quarter. DAECODAM Page 97 of 280 Rev. 37 Doses Due to Noble Gases 0 6.2.3 0 6.2 RADIOACTIVE GASEOUS EFFLUENT CONTROLS 06.2.3 Doses Due to Noble Gases OLCO 6.2.3 The Air Dose in the UNRESTRICTED AREA due to noble gases released in gaseous effluents shall not exceed: APPLICABILITY:

ACTIONS 5.0 mrad from gamma radiation during any calendar quarter; 10.0 mrad from beta radiation during any calendar quarter; 10.0 mrad from gamma radiation during any calendar year; or 20.0 mrad from beta radiation during any calendar year. During Releases CONDITION REQUIRED ACTION COMPLETION TIME A. Calculated air dose not within limits. DAEC ODAM A.1 Submit a Special Report to 30 days the NRC identifying the cause(s) for exceeding the limit and define the corrective actions taken. Page 98 of 280 Rev. 37 Doses Due to Noble Gases 0 7.2.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY OSR 7.2.3.1 An assessment shall be performed in accordance 30 Days with the ODAM to verify that the cumulative air dose during the quarter and year due to noble gases does not exceed the limits in ODAM section 6.2.3. DAEC ODAM Page 99 of 280 Rev. 37 Doses Due to Iodine and Particulates in Air 0 6.2.4 0 6.2 0 6.2.4 OLCO 6.2.4 APPLICABILITY:

ACTIONS CONDITION RADIOACTIVE GASEOUS EFFLUENT CONTROLS Doses Due to Iodine and Particulates in Air The dose to a MEMBER OF THE PUBLIC from lodine-131, 1-133, H-3, and from radionuclides in particulate form having half-lives greater than eight days in gaseous effluents released from the site to the UNRESTRICTED AREA shall not exceed: 7.5 mrem to any organ during any calendar quarter; or 15.0 mrem to any organ during any calendar year. During Releases.

REQUIRED ACTION COMPLETION TIME A. Calculated dose not within limits. A.1 Submit a Special Report to 30 days the NRC identifying the cause(s) for exceeding the limit and define the corrective actions taken. DAEC ODAM Page 100 of 280 Rev. 37 Doses Due to Iodine and Particulates in Air 0 7.2.4 SURVEILLANCE REQUIREMENTS OSR 7.2.4.1 DAEC ODAM SURVEILLANCE An assessment shall be performed in accordance with the ODAM to verify that the cumulative dose commitment due to 1-131, 1-133, H-3, and radioactive particulates having half-lives greater than eight days in gaseous effluents does not exceed the limits in ODAM Section 6.2.4. Page 101 of 280 FREQUENCY 30 Days Rev. 37 Gaseous Radwaste Treatment 06.2.5 06.2 RADIOACTIVE GASEOUS EFFLUENT CONTROLS 0 6.2.5 Gaseous Radwaste Treatment OLCO 6.2.5 At least one train of charcoal beds in the Offgas System shall be placed in operation to treat radioactive gases from the main condenser.

APPLICABILITY:

During Offgas System operation.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. No Offgas System A.1 Restore Offgas System 7 days charcoal beds in charcoal bed to service. service. ----------NOTE---------

Not applicable until after 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of commencing operation of the main condenser air ejector. --------------------------

B. Required Action and B.1 Submit a Special Report to 30 days associated Completion the NRC identifying the Time not met. inoperable equipment or subsystem and reason for inoperability, actions taken to prevent a recurrence.

DAECODAM Page 102 of 280 Rev. 37 Gaseous Radwaste Treatment 0 7.2.5 SURVEILLANCE REQUIREMENTS OSR 7.2.5.1 SURVEILLANCE The gaseous effluent monitoring systems of ODAM N/A Sections 6.2.1 and 7.2.1 shall be used to verify the operation of the Offgas system. FREQUENCY DAECODAM Page 103 of 280 Rev. 37 Mechanical Vacuum Pump Radiation Release Rate 06.2.6 06.2 06.2.6 OLCO 6.2.6 APPLICABILITY:

ACTIONS CONDITION RADIOACTIVE GASEOUS EFFLUENT CONTROLS Mechanical Vacuum Pump Radiation Release Rate During mechanical vacuum pump operation the release rate of gross activity except for halogens and particulates with half-lives longer than eight days shall not exceed 1 curie/sec.

During mechanical vacuum pump operation.

REQUIRED ACTION COMPLETION TIME A. Radioactive release rate not within limit. A.1 Restore radioactive release rate to within limits. Immediately DAEC ODAM Page 104 of 280 Rev. 37 Dose 0 6.3.1 SURVEILLANCE REQUIREMENTS OSR 7.2.6.1 DAEC ODAM SURVEILLANCE The gaseous effluent monitoring systems of ODAM Sections 6.2.1 and 7.2.1 shall be used to verify the operation of the Offgas system. Page 105 of 280 FREQUENCY N/A Rev. 37 Dose 0 6.3.1 06.3 0 6.3.1 OLCO 6.3.1 APPLICABILITY:

ACTIONS CONDITION A. Calculated dose from radioactive OFFSITE DOSE ASSESSMENT CONTROLS Dose The annual dose or dose commitment to any MEMBER OF THE PUBLIC due to radiation and radioactive material in effluents from DAEC shall not exceed 75 mrem to the thyroid or 25 mrem to the total body or any other organ. At all times. REQUIRED ACTION COMPLETION TIME A.1 Perform an assessment of compliance 7 days with 40 CFR 190 and material released in 10 CFR 72.104 and limit subsequent liquid or gaseous releases such that the dose or dose effluents exceeds commitment to a MEMBER OF THE twice the limits of PUBLIC is ::;,75 mrem to his thyroid Sections 6.1.3, 6.2.3 and ::;,25 mrem to his total body or any or 6.2.4 other organ over 12 consecutive months including the period of elevated release. B. The estimated dose B.1 Prepare and submit a Special Report 30 days exceeds either limit to the NRC in lieu of any other report; in Section 6.3.1. it shall include the cause of the release of exposure, an estimate of the dose to the likely most exposed MEMBER(s)

OF THE PUBLIC, corrective actions taken or planned to prevent a recurrence, and a schedule for achieving compliance.

If the condition causing the limit(s) to be exceeded has not been corrected, the Special Report may also state a request for a variance in accordance with the provisions of 40 CFR Part 190. In that event, the request is timely and a variance is granted until NRC action on the request is complete.

DAEC ODAM Page 106 of 280 Rev. 37 Dose 0 7.3.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY OSR 7.3.1.1 Cumulative dose contributions from liquid and 12 Months gaseous effluents to a MEMBER OF THE PUBLIC offsite shall be evaluated as described in the ODAM. DAEC ODAM Page 107 of 280 Rev. 37 Radiological Environmental Monitoring Program 06.3.2 06.3 OFFSITE DOSE ASSESSMENT CONTROLS 0 6.3.2 Radiological Environmental Monitoring Program (REMP) Ground Water Protection Program (GWPP) OLCO 6.3.2 A radiological environmental monitoring program shall be conducted as specified in Table 6.3-1. APPLICABILITY:

At all times. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Deviation from Table A.1 Deviations are permitted from Table Once per year 6.3-1 6.3-1 if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment and other legitimate reasons. If specimens are unobtainable due to sampling equipment malfunction, every effort shall be made to complete corrective action prior to the end of the next sampling period. All deviations from Table 6.3-1 shall be documented in the Annual Radiological Environmental Report. B. In the event B.1 Prepare and submit to the Commission 30 Days radioactivity in a within 30 days after discovery a Special sampled Report which includes an evaluation of environmental any release conditions, environmental medium, averaged factors or other conditions which over a calendar caused the value(s) of Table 6.3-3 or quarter, is two times the quarterly dose limit to be attributable to DAEC exceeded and which defines the and exceeds an corrective actions to be taken. If the appropriate value radioactivity in environmental sample(s) listed in Table 6.3-3 is not attributable to releases from the or, if not listed, Station, the Special Report is not causes a potential required.

Instead, the sample(s) annual dose result(s) shall be reported and exceeding two times explained in the Annual Radiological the quarterly dose Environmental Report. limit in Section 6.1.3 or 6.2.4 (continued)

DAEC ODAM Page 108 of 280 Rev. 37 ACTIONS (continued)

CONDITION C. When C.1 environmental sampling medium is not available from a sampling location or the location is no longer appropriate.

D. A location is D.1 identified at which the calculated personal dose associated with one or more exposure pathways exceeds by 20% the maximum calculated dose associated with like pathway( s) at a location where sampling is conducted as specified by Table 6.3-1 DAECODAM Radiological Environmental Monitoring Program 0 6.3.2 REQUIRED ACTION COMPLETION TIME The cause and the location where Once per year replacement samples were obtained and/or will be obtained shall be reported in the Annual Radiological Environmental Report. The pathway(s) having maximum Once per year exposure potential at the newly identified location will be added to the radiological monitoring program at a subsequent Operations Committee meeting, if samples are reasonably attainable at the new location.

Like pathway(s) monitored (sampled) at a location, excluding the control station location(s), having a lesser associated calculated personal dose may be deleted from the program at the time the new pathway(s) and location are added. Page 109 of 280 Rev. 37 Radiological Environmental Monitoring Program 0 7.3.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY OSR 7.3.2.1 Sampling and analyses required in Table 6.3-1 12 Months shall be performed such that the detection capabilities specified in Table 6.3-2 are achieved under routine conditions.

If a sample analysis does not meet the LLD specified, report the reason attributed in the next Annual Radiological Environmental Report. OSR 7.3.2.2 DAEC shall conduct annually a land use census 12 Months within three miles of the Station to identify radiologically important changes in land use. DAEC ODAM Page 110 of 280 Rev. 37 Radiological Environmental Monitoring Program 0 6.3.2 TABLE 6.3-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Minimum Sampling and Type and Frequency of Analysis Pathway and/or Number of Collection Schedule (a) Sample Type Sampling Stations Airborne Five Continuous operation of sampler with Analyze for gross beta activity 2 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Particulates sample collection WEEKLY or as required after filter change. by dust loading Perform gamma isotopic analysis on each sample having gross beta activity > 10 times the yearly mean of control samples. Perform gamma isotopic analysis on composite (by sampling location) of samples collected during each quarter Airborne Iodine Five Continuous operation of sampler with Analyze each cartridge for 1-131 within sample collection WEEKLY 8 days of collection.

Ambient Forty two QUARTERLY Read gamma radiation dose quarterly.

Radiation Surface Water Three MONTHLY Tritium and Gamma isotopic analysis of each sample. Drinking Water Three MONTHLY Tritium and Gamma isotopic analysis of each sample. If reactor by-product gamma emitters are identified, OR tritium concentration is >MDA, then analyze, Sr-89, Sr-90, Fe-55 and alpha emitters.

Ground Water Six QUARTERLY Tritium and Gamma isotopic analysis of each sample. If reactor by-product gamma emitters are identified, OR tritium concentration is > MDA, then analyze for Sr-89, Sr-90, Fe-55 and alpha emitters.

River Sediment One SEMIANNUALLY Gamma isotopic analysis of each sample. Milk Two MONTHLY for dairy cattle and when Gamma isotopic and 1-131 analysis of each available for goat milk. sample. Fish Two SEMIANNUALLY Gamma isotopic analysis on edible portion. Vegetation Six ANNUALLY at harvest time. At least two Gamma isotopic and 1-131 analysis of each samples of each: sample. grain green leafy vegetation foraqe. \8) .. -The following definitions of schedule timing shall apply to Table 6.3 1 only. WEEKLY -Not less than once per calendar week. A maximum interval of 11 days is allowed between the collection of any two consecutive samples. BIWEEKLY -Not less than once every two calendar weeks. A maximum interval of 18 days is allowed between the collection of any two consecutive samples. MONTHLY -Not less than once per calendar month. An interval of not less than 10 days will be provided between collection of any two consecutive samples. QUARTERLY

-Not less than once per calendar quarter. An interval of not less than 30 days will be provided between collection of any two consecutive samples. SEMIANNUALLY

-One sample each between calendar dates (January 1 -June 30) and (July 1 -December 31). An interval of not less than 60 days will be provided between collection of any two consecutive samples. ANNUALLY -Not less than once per calendar year with an interval of not less than 120 days between collection of any two consecutive samples. DAECODAM Page 111 of 280 Rev. 37 TABLE 6.3-2 Radiological Environmental Monitoring Program 06.3.2 GROUNDWATER PROTECTION PROGRAM Exposure Pathway Minimum Sampling and !rype and Frequency of Analysis and/or Sample Number of Collection Schedule (a) Type Sampling Stations Groundwater Forty (b) QUARTERLY Tritium and Gamma isotopic analysis of each sample. If reactor by-product gamma emitters are identified, OR tritium concentration is >MDA, then analyze for Sr-89, Sr-90, Fe-55 and alpha emitters.

Groundwater One (c) MONTHLY Tritium and Gamma isotopic analysis of Conditional each sample. If reactor by-product gamma emitters are identified, OR tritium concentration is >MDA, then analyze for Sr-89, Sr-90, Fe-55 and alpha emitters.

Soil Two ANNUALLY Tritium, Gamma isotopic and Strontium-90 Precipitation Four MONTHLY Tritium and Gamma isotopic analysis of each samole. Electrical Vaults One SEMIANNUALLY Tritium and Gamma isotopic analysis of each sample. DAEC Sewage One BIWEEKLY Tritium and Gamma isotopic analysis of Plant Effluent each sample. (a)The following definitions of schedule timing shall apply to Table 6.3-2 only: WEEKLY -At least once per calendar week. BIWEEKLY -Not less than once every two calendar weeks. A maximum interval of 18 days is allowed between the collection of any two consecutive samples. MONTHLY -Not less than once per calendar month. An interval of not less than 10 days will be provided between collection of any two consecutive samples. QUARTERLY

-Not less than once per calendar quarter. An interval of not less than 30 days will be provided between collection of any two consecutive samples. SEMIANNUALLY

-One sample each between calendar dates (January 1 -June 30) and (July 1 -December 31). An interval of not less than 60 days will be provided between collection of any two consecutive samples. ANNUALLY -Not less than once per calendar year with an interval of not less than 120 days between collection of any two consecutive samples. (b)As of January 1, 2017, fifty-six groundwater wells are operational.

<0>The number of conditional wells sampled in a calendar month depends upon identified isotope, concentration of isotope, targeted aquifer, and extraction well operations.

DAEC ODAM Page 112 of 280 Rev. 37 Radiological Environmental Monitoring Program 06.3.2 TABLE 6.3-3 MAXIMUM VALUES OF THE LOWER LIMIT OF DETECTION FOR ENVIRONMENTAL SAMPLE ANALYSIS <a> Analysis Medium Water Airborne Fish Milk (pCi/L) Food Sediment (pCi/L) Particulate or (pCi/kg, Products (pCi/kg, dry) Gas (pCi/m 3) wet) (pCi/kg, wet) Gross beta 4 1 x 10-2 H-3 2000 (DJ 3000 (c) Mn-54 15 130 Fe-59 30 260 Co-58, Co-15 130 60 Zn-65 30 260 Zr-95 30 Nb-95 15 1-131 1 (d) 7 x 10-2 1 60 Cs-134 15 5 x 10-2 130 15 60 150 Cs-137 18 6x10-2 150 18 80 180 Ba-140 60 60 La-140 15 15 TABLE NOTATIONS Table 6.3-2 (a) The LLD is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a new count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal. For a particular measurement, which may include radiochemical separation LLD= (4.66Sb)/(E

  • V
  • 2.22
  • Y
  • e -i." 1) where:
  • LLD is the lower limit of detection as defined above (picocuries per unit mass or volume)
  • Sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute)
  • E is the counting efficiency (counts per disintegration)
  • Vis the sample size (units of mass or volume)
  • 2.22 is the number of disintegrations per minute per picocurie,
  • Y is the fractional radiochemical yield, when applicable,
  • A is the radioactive decay constant for the particular radionuclide, and D
  • t for environmental samples is the elapsed time between sample collection, or end of the sample collection period, and time of counting Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions.

With typical values of E, V, Y, and Llt for the radionuclides named in the Table. Occasionally background fluctuations, unavoidably small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable.

In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Report. continued DAEC ODAM Page 113 of 280 Rev. 37 Radiological Environmental Monitoring Program 0 6.3.2 When a radionuclide attributable to DAEC but not listed in this table is measured it shall be reported. (b) For Drinking Water. (c) For samples of water not used as a source of drinking water. (d) If no drinking water pathway exists, a value of 15 pCi/I may be used. DAEC ODAM Page 114 of 280 Rev. 37 Radiological Environmental Monitoring Program 0 6.3.2 TABLE 6.3-4 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Reporting Levels<a>

Analysi Water Airborne Fish Milk Food Products s (pCi/liter)

Particulate (pCi/Kg, wet) (pCi/liter) (pCi/Kg, wet) or Gases (pCi/m 3) H-3 2 x 10 4 (b) 3 X 10 4 (c) Mn-54 1 x 10 3 3 x 10 4 Fe-59 4 x 10 2 1 x 10 4 Co-58 1 x 10 3 3 x 10 4 Co-60 3x10 2 1 x 10 4 Zn-65 3x10 2 2x10 4 Zr-4 X 10 2 (c) Nb95 1-131 2d 0.9 3 1 x 10 2 Cs-134 30 10 1 x 10 3 60 1 x 10 3 Cs-137 50 20 2 x 10 3 70 2 x 10 3 Ba-2 X 10 2 (e) 3 X 10 2 (e) La140 TABLE NOTATIONS Table 6.3-3 <a>The reporting level is exceeded when one or more radionuclides are detected in a sample and l:[(concentration)/(reporting level)] :=:: 1. (b)For drinking water samples. This is 40 CFR Part 141 value. <c>For samples of water not used as a source of drinking water. (dllf no drinking water pathway exists, a value of 20 pCi/I may be used. <e>concentration of parent or daughter.

DAEC ODAM Page 115 of 280 Rev. 37 BASES BASES SECTION 6.1 / 7.1 6.1.1 Radioactive Liquid Effluent Instrumentation

/7.1.1 DAEC ODAM The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the release of radioactive material in liquid effluents.

The OPERABILITY and use of these instruments implements the requirements of 10 CFR Part 50, Appendix A, General Design Criteria 60, 63, and 64. The alarm and/or trip setpoints for these instruments are calculated in the manner described in the ODAM to assure that the alarm and/or trip will occur before ten times the values specified in 10 CFR Part 20.2001 -20.2402, Appendix Bare exceeded.

Instrumentation is expected to be OPERABLE and in service when required by controls.

An instrument may be removed from service voluntarily for the purpose of tests, checks, or calibration, without declaring the channel inoperable.

The radwaste effluent line radiation monitor recorder RR3972 is not required in order to comply with the controls stated in the ODAM. It is provided for recording trends during a release and need not be maintained OPERABLE -i.e. calibrated and functionally tested -other than during a release. Page 116 of 280 Rev. 37 BASES BASES SECTION 6.1 / 7.1 6.1.2 / 7.1.2 Liquid Effluent Concentration DAECODAM The basic requirements concerning effluents from nuclear power are stated in 10 CFR 50.36a. These requirements indicate that compliance with Technical Specifications will keep average annual releases of radioactive material in effluents to a small percentage of the limits specified in 10 CFR 20.106. These (new 10 CFR 20.1301) requirements further indicate that operational flexibility is allowed, compatible with considerations of health and safety, which may temporarily result in releases higher than such small percentages, but still within the limits specified in the old 10 CFR 20.106. These referenced concentrations are specific values which relate to an annual average dose of 500 millirems.

As stated in the Introduction to Appendix B of the new 10 CFR 20, the liquid effluent concentrations limits, given in the appendix, are based on an annual dose of 50 millirem.

Prior to the issuance of the revision to Part 20, a release concentration corresponding to a limiting dose of 500 millirem had been acceptable as a TS limit for liquid effluents.

The limit was applicable at all times and has been used to provide assurance that the limits of 10 CFR 50 Appendix I were not likely to be exceeded.

Since the limits of 10 CFR 50 are the ultimate value to which a license must adhere, and since the old concentration limits adequately provide such assurance, it should not be necessary to reduce this limit by a factor of 10. Conformance with the dose limits in section 6.1.3 will necessitate average annual I liquid effluent concentrations being below those specified in 10 CFR 20.1001 -20.2402 Appendix B to§§ 20.1001-20.2402.

Demonstrating compliance with section 6.1.3 will result in a de facto demonstration of compliance with 10 CFR 20 limits. The continuous service water sample points noted in Table 7.1-2 are adequate to I ensure sampling of potential liquid radioactive effluents from the service water systems. The sample points include the General Service Water System and the RHR Service Water Systems A and B. The sample point for the RHR Service Water Systems is at a location downstream of the point where Emergency Service Water discharge joins with the RHR Service Water System, and upstream of the point where the RHRSW/ESW Rupture Disc Line branches off of the RHR Service Water System. This sample point will therefore provide for sampling effluents from the RHR Service Water System, Emergency Service Water System and/or RHRSW/ESW Rupture Disc Line. The "clean" system water sample points noted in Table 7.1-2 are adequate to ensure sampling of potential liquid radioactive effluents from systems believed to NOT contain principal gamma emitters and iodine. The sample points include I the Transformer Pit, the CST Pit, FRAC tanks, and the Neut. Tank (1T022). Page 117 of 280 Rev. 37 6.1.2 / 7.1.2 (cont'd) 6.1.3 / 7.1.3 6.1.4 / 7.1.4 1. BASES The GWPP mitigation system sample points noted in Table 7.1-2 are adequate to ensure sampling of potential liquid radioactive effluents in the shallow groundwater.

Further, the GWPP mitigation plan support a reduction in contaminate concentration such that releases are expected below Administrative Control Procedure (ACP) 1411.35 and Environmental Protection Agency (EPA) drinking water limit of 20,000 pCi/L. Dose Due to Radioactive Effluents Section 6.1.3, 6.2.3 and 6.2.4 implement the requirements of 10 CFR Part 50.36a and of 10 CFR Part 50, Appendix I, Section IV. These sections keep levels of radioactive materials in LWR effluents as low as is reasonably achievable.

Compliance with these sections will also keep average releases of radioactive material to effluent at small percentages of the limits specified in 10 CFR Part 20.106. Surveillance requirements provide for the measurement of releases and calculation of doses to verify compliance with the controls.

Action statements in these sections implement the requirements of 10 CFR Part 50.36(c)(2) and 10 CFR Part 50, Appendix I, Section IV.A in the event a control is not met. 2. Liquid Effluents With the implementation of Section 6.1.3, there is reasonable assurance that Station operation will not cause a radionuclide concentration in public drinking water taken from the Cedar River that exceeds the standard for anthropogenic radioactivity in community drinking water. The equations in the ODAM for calculating doses due to measured releases of radioactive material in liquid effluent are consistent with the methodology in Regulatory Guide 1.109 and 1.113. The assessment of personal doses will examine potential exposure pathways including, as appropriate, consumption of fish and water taken from the Cedar River I downstream of the discharge pipe. Liquid Waste Treatment This section implements the requirements of 10 CFR Part 50.36a (a)(1) that operating procedures be established and followed and that equipment be maintained and used to keep releases to the environment as low as is reasonably achievable.

The section intends that appropriate portions of the system which were used to establish compliance with the design objectives in 10 CFR Part 50, Appendix I, Section II be used when specified to provide reasonable assurance that releases of radioactive material in liquid effluent will be kept as low as is reasonably achievable.

The components in the liquid radwaste system which are appropriate to process liquid waste in order to satisfy Section 7.1.4 are the floor drain demineralizer and the radwaste demineralizer.

The activity concentration, µCi/ml, below which liquid radwaste treatment would not be cost-beneficial, and therefore not required, is demonstrated below. The quantity of radioactive material in liquid effluent released annually from the DAEC has been calculated to be: total iodines 0.11 curie total others (less H3) 0.25 Total 0.36 curie DAEC ODAM Page 118 of 280 Rev. 37 DAECODAM BASES The population dose commitment resulting from the radioactive material in liquid effluent released annually has been calculated to be* thyroid total body Total 0.164 man rem 0.114 0.278 man rem Therefore, population doses are about 1.5 man rem per curie of iodine released and about 0.5 man rem per curie of other radionuclides (less H3) released in liquids. On the basis of gross activity, the population dose is about one man rem per curie released in liquids. The volume of liquid waste processed and intended for discharge is estimated to be: Low Purity Waste Chemical Waste 5700 gal/day = 1.8 x 106 gal/yr 600 gal/day = 1. 9 x 105 gal/yr Since the same DAEC equipment is used to process both streams, the total volume to be processed is about 2 x 106 gal/yr. The annual cost to operate the radwaste processing equipment, based on Dirty Waste Ion Exchange operation, has been estimated* (neglecting credit for capital recovery) to be $88,000 per year. Thus the unit volume operating cost is about:

I yr = $0.05 I gal 2 x 10 gal I yr Thus the operating cost to treat a 4000 gallon batch of chemical waste by ion exchange would be about $200. The operating cost to treat a 10000 gallon batch of floor drain waste by ion exchange would be about $500. Assuming the cost-benefit balance is $1000 expenditure per man rem reduced and assuming treatment removes all radioactivity from the liquid, then (1) the activity concentration in a Chemical Waste batch below which treatment is not cost-beneficial is C $200 1 curie 10 6 µCi 1 man rem = x x x---4000 gal x 3785 .!!!!.___

man rem curie $1000 gal C=0.013 µCi/ml (continued)

Page 119 of 280 Rev. 37 6.1.4 / 7.1.4 BASES (2) the activity concentration in a batch of Floor Drain Waste below which treatment is not cost-beneficial is $500 1 curie 10 6 µCi 1 man rem C= x JOOOOgalx3785.!!!!_

manrem curie $1000 gal c = 0. 013 µCi/ml, Liquid waste treatment with the evaporator at DAEC has been shown to be neither cost-beneficial nor necessary to comply with 10 CFR 50 Appendix I, Section II. Consequently, liquid radwaste treatment to achieve an activity concentration below 0.01 µCi/ml in liquid effluent is not justified.

6.1.5 / 7.1.5 Liquid Holdup Tanks DAEC ODAM The tanks listed in the specification include all liquid radwaste tanks (1T-88 and 1T-269) located in the Low-Level Radwaste Processing Facility (LLRPSF).

Because the LLRPSF is not seismically designed, these tanks are considered as outdoor tanks that are not surrounded by liners, dikes, or walls capable of holding the tanks' contents.

Restricting the quantity of radioactive material contained in the specified tanks provides assurance that in the event of an uncontrolled release of the tanks' contents, the resulting concentrations would be less than the limits of 10 CFR 20, Appendix B to 20.1001 -20.2402, Table 2, Column 2, at the nearest potable water supply in an UNRESTRICTED AREA. Page 120 of 280 Rev. 37 BASES BASES SECTION 6.2 / 7.2 6.2.1 /7.2.1 DAEC ODAM Radioactive Gaseous Effluent Instrumentation The radioactive gaseous effluent instrumentation is provided to monitor the release of radioactive materials in gaseous effluents and, as appropriate, to control potential releases.

The presence of instruments for monitoring radioactive effluents is depicted in ODAM Figure 3-1. The OPERABILITY and use of these instruments implements the requirements of 10 CFR Part 50, Appendix A, General Design Criteria 60, 63, and 64. Reactor building exhaust ventilation shaft radiation monitors initiate isolation of the reactor building normal ventilation and start standby gas treatment when a high trip point is reached. DAEC is equipped with a radioactive gaseous effluent monitoring system which includes detectors at the offgas stack (R3), the reactor building vent (R4), the turbine building vent (R5), and the LLRPSF vent (R7). A remote indication and control unit located near each detector displays the detector reading and, whenever the setpoint is exceeded, an indicator light. The data are also routed to a control computer and a control room display, but do not cause a trip to isolate the ventilated area. In the event the control computer and/or control room display fail to function or are voluntarily taken out of service, each remote indication and control unit is designed to acquire data for up to 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. It is intended that each affected remote indication and control unit display be observed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (in which case the affected channel remains OPERABLE).

If an alarm trip setpoint is exceeded at the same time the control computer and/or control room display are neither functioning nor in service, alarm annunciation will still occur in the control room. In the event the detector reading and the indication of exceeding the monitor setpoint are not provided at either the control room or the remote indication and control unit, then the affected channel is not OPERABLE and DAEC will either perform the appropriate ACTION or will provide an alternate monitoring system. This permits DAEC to retain the GE gaseous monitoring system as an alternate system for normal effluent monitoring when the Kaman system is temporarily inoperable.

When used as an alternate monitoring system, the GE system is subject to the requirements stated in Sections 6.2.1 and 7.2.1 and to LLD requirements stated in Table 7.2-2, Note (d). Two air ejector offgas post-treatment monitors are provided.

They are designed so that an instrument failure gives a downscale trip or an inoperative trip. When both instruments reach an upscale trip point, or when one reaches an upscale and the other reaches a downscale trip point or inoperative, a trip is actuated.

The post-treatment monitors have three upscale trip setpoints. The lower level upscale trip (high) will initiate charcoal bed valve closure. (CV-4134A opening and CV-4134B closing to route offgas through the charcoal.)

The intermediate and upper trip points (high-high and high-high-high) are for alarm only. Page 121 of 280 Rev. 37 BASES BASES SECTION 6.2 17.2 2. Not used 3. Gaseous Effluents Assessments of dose required by Sections 7.2.3 and 7.2.4 to verify compliance with Appendix I,Section IV are based on measured radioactivity in gaseous effluent and on calculation methods stated in the ODAM. Pathways of exposure and location of individuals are selected such that the dose to a nearby resident is unlikely to be underestimated.

Dose assessment methodology described in the ODAM for gaseous effluent will be consistent with the methodology in Regulatory Guides 1.109 and 1.111. Cumulative and projected assessments of dose made during a quarter are based on historical average meteorological conditions measured at DAEC. Assessment made for the annual radiological environmental report will be based on annual averages of atmospheric conditions during the period of release. 6.2.2 / 7.2.2 Gaseous Effluent Concentration DAECODAM The basic requirements concerning effluents from nuclear power are stated in 10 CFR 50.36a. These requirements indicate that compliance with Technical Specifications will keep average annual releases of radioactive material in effluents to a small percentage of the limits specified in 10 CFR 20. These (new 10 CFR 20.1301) requirements further indicate that operational flexibility is allowed, compatible with considerations of health and safety, which may temporarily result in releases higher than such small percentages, but still within the limits specified in the old 10 CFR 20.106. These referenced concentrations are specific values which relate to an annual average dose of 500 millirems.

As stated in the Introduction to Appendix B of the new 10 CFR 20, the gaseous effluent concentration limits given in the appendix are based on an annual dose of 50 millirem for isotopes for which inhalation or ingestion is limiting or 100 millirem for isotopes for which submersion (noble gases) is limiting.

Prior to the issuance of the revision to Part 20 a release concentration corresponding to limiting dose rates less than or equal to 500 mrem/yr to the whole body, 3000 mrem/yr to the skin from noble gases, and 1500 mrem/yr to any organ from iodine, and tritium, had been acceptable as a TS limit for airborne effluents.

This limit was applicable at all times and had been used to provide assurance that the limits of 10 CFR 50 Appendix I and 40 CFR 190 were not likely to be exceeded.

Since the limits of 10 CFR 50 Appendix I and 40 CFR 90 are more restrictive than 10 CFR 20, and because the dose limits specified have been successfully used to assure compliance with these regulations, it should not be necessary to reduce the dose rate basis to 50 or 100 millirem.

Conformance with the dose limits of 7.3.1 will necessitate the average annual airborne effluent concentrations being below those specified in 10 CFR 20 Appendix B. Demonstrating compliance with section 6.3.1 will result in a de facto demonstration of compliance with 10 CFR 20 limits. Assessment of compliance is based upon an effluents measurement program defined in Table 7.2-2 and methodology stated in the ODAM. The resolving time of the measurements, i.e., the sample integration time, bounds the minimum averaging time of the effluent measurements waste streams. The Standby Gas Treatment System is considered an Engineered Safety Feature and not an exhaust ventilation treatment system. Page 122 of 280 Rev. 37 BASES BASES SECTION 6.2 / 7.2 Thus the exhaust ventilation system discharges via the reactor building vent. 6.2.3 / 7.2.3 Doses due to Noble Gases These specifications implement the requirements of 10 CFR Part 50, Appendix I. 6.2.4 / 7.2.4 Doses due to Iodine and Particulates in Air These specifications implement 10 CFR Part 50, Appendix I. The dose calculation methods in the ODAM depend on existing pathways of exposure to a member of the public or more conservative conditions assumed (yielding a higher calculated dose). Calculations and methods are such that an estimate of the dose to a member of the public is not likely to be underestimated substantially.

6.2.5 / 7.2.5 Gaseous Radwaste Treatment DAECODAM This specification implements the requirement of 10 CFR Part 50.36a(a)(1) that operating procedures be established and followed and that equipment be maintained and used to keep releases to the environment as low as is reasonably achievable.

In order to satisfy Section 6.2.5, every reasonable effort shall be made to maintain and operate at least one train of the Offgas System charcoal absorbers with pre-and aft-particulate filters to process radioactive gaseous effluent prior to release. The specification that the Offgas System which was used to establish compliance with the design objectives in 10 CFR Part 50, Appendix I, Section II be used when specified provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept as low as is reasonably achievable.

ODAM Figure 3-1 is a flow diagram depicting gaseous radioactive waste streams. The Standby Gas Treatment System is considered an Engineered Safety Feature and not an exhaust ventilation treatment system. Page 123 of 280 Rev. 37 BASES SECTION 6.3 17.3 6.3.1 /7.3.1 Dose BASES Section 6.3.1 is provided to comply with the dose limitation requirement of 40 CFR 190. This section requires the assessment of dose to demonstrate that a person (a nearby resident) has not received a radiation dose exceeding that specified in 40 CFR 190 including doses from direct radiation.

There is no other licensed nuclear fuel cycle facility within 50 miles of DAEC, thus it is assumed that the dose from other uranium fuel cycle facilities is negligible.

In the event a report is required to satisfy Action b, it shall be deemed adequate to satisfy the reporting requirement in Section 8.2.2. By demonstrating compliance with 40 CFR 190, DAEC will be, de facto, in compliance with the dose limits specified in 10 CFR 20.1301 and 10 CFR 72.104. Such a position is in keeping with that stated by the NRG in the preamble to the revised 10 CFR 20 (56 CFR 23360). 6.3.2 I 7.3.2 Radiological Environmental Monitoring DAEC ODAM The radiological environmental monitoring program, including the land use census, is conducted to satisfy the requirements of 10 CFR Part 50, Appendix I, Section IV.B.2 and .3. The minimum radiological monitoring program required by this specification provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides which lead to the highest potential radiation exposures of individuals resulting from the station operation.

This monitoring program thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways.

The land use census is conducted annually to identify changes in use of the UNRESTRICTED AREA in order to recommend modifications in monitoring programs for evaluating individual doses from principal exposure pathways.

It may be conducted by door-to-door survey, by aerial survey, or by consulting with local agricultural or governmental authorities.

In order that radiological environmental monitoring stations may be relocated to reflect current conditions, the locations of stations required by Table 6.3-1 are described in the Offsite Dose Assessment Manual. Revisions thereto are administered in accordance with TS 5.5.1 and ODAM 8.3.1. DAEC may conduct additional environmental monitoring exclusive of the requirements of Sections 6.3.2. Page 124 of 280 Rev. 37 8.0 ADMINISTRATIVE CONTROLS 8.1 PROGRAMS AND MANUALS 8.1.1 RADIOACTIVE EFFLUENT CONTROLS PROGRAM PROGRAMS AND MANUALS 8.1 This program, conforming to 10 CFR 50.36a, provides for the control of radioactive effluents and for maintaining the doses to members of the public from radioactive effluents as low as reasonably achievable.

The program shall be contained in the ODAM, shall be implemented by procedures, and shall include remedial actions to be taken whenever the program limits are exceeded.

The program shall include the following elements.

a. Limitations on the functional capacity of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODAM; b. Limitations on the concentrations of radioactive material released in liquid effluents from the site to UNRESTRICTED AREAs, conforming to ten times (10x) the concentrations listed in Appendix B, Table 2, Column 2 to 10 CFR 20.1001 -20.2402; c. Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents pursuant to 10 CFR 20.1302 and with the methodology and parameters in the ODAM conforming to 10CFR50, Appendix I; d. Limitations on the annual and quarterly doses or dose commitment to a member of the public from radioactive materials in liquid effluents released to UNRESTRICTED AREAs; e. Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODAM at least every 30 days; f. Limitations on the functional capability and use of the liquid and gaseous effluent treatment systems to ensure that the appropriate portions of these systems which were used to establish compliance with the design objectives in 10 CFR 50, Appendix I, Section II be used when specified to provide reasonable assurance that releases of radioactive material in liquid and gaseous effluents be kept as low as reasonably achievable;
g. Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas at or beyond the site boundary shall be limited to the following:
1. For noble gases: less than or equal to a dose rate of 500 mrem/yr to the whole body and less than or equal to a dose rate of 3000 mrem/yr to the skin, and 2. For iodine-131, iodine-133, tritium, and for all radionuclides in particulate form with half-lives>

8 days:; less than or equal to a dose rate of 1500 mrem/yr to any organ; h. Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I; I. Limitations on the annual and quarterly doses to a member of the public from iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives>

8 days in gaseous effluents released to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I; and j. Limitations on the annual dose or dose commitment to any member of the public due to releases of radioactivity and to radiation from uranium fuel cycle sources, conforming to 40 CFR 190 and 10 CFR 72.104. DAECODAM Page 125 of 280 Rev. 37 REPORTING REQUIREMENTS (continued) 8.2 8.1.2 THE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM The Radiological Environmental Monitoring Program is described in section 5 of the ODAM. Specifications for implementation are located in section 6.3.2 8.1.3 INTERLABORATORY COMPARISON PROGRAM Analyses shall be performed on radioactive materials supplied in an lnterlaboratory Comparison Program. In the event analyses were not performed as required in Section 8.1.3, report the corrective actions taken to prevent a recurrence in the Annual Radiological Environmental Report. The requirement for participation in an lnterlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid. DAEC ODAM Page 126 of 280 Rev. 37 8.2 REPORTING REQUIREMENTS 8.2.1 ANNUAL RADIOACTIVE MATERIAL RELEASE REPORT REPORTING REQUIREMENTS 8.2 (1) A report of radioactive materials released from the Station shall be submitted to the NRC on or before May 1 of each year in accordance with 10 CFR 50.36a. Each report shall include the information specified in item (2) below covering the preceding twelve months. (2) An Annual Radioactive Material Release Report shall include a summary by calendar quarter of the quantities of radioactive liquid and gaseous effluents and radioactive solid waste released from the Station. The data on radioactive liquid and gaseous effluents should be reported in the format in Tables 8.2-1 and 8.2-2. The data on radioactive solid waste should include: 1. classification of the waste (per 10 CFR Part 61) 2. total volume shipped 3. total radioactive material shipped (curies) 4. identification of principal radionuclides

5. solidification agent 6. physical description of the waste (3) A summary description of any changes to the ODAM. (4) A summary of meteorological data collected during the year will be submitted in the annual report following January 1. Alternatively, summary meteorological data may be retained by DAEC and made available to the NRC upon request. (5) Include all onsite ground water sample results, for samples that are being taken in support of the Industry Ground Water Protection Initiative, but are from onsite sample locations that have not been incorporated into the Radiological Environmental Monitoring Program. (6) Include a description for all sample analyses/conditions for which communications were made to State and Local officials due to exceeding the applicable ODAM reporting levels for environmental samples for locations that have not been added to the plant's Radiological Environmental Monitoring Program. (7) Include a description of all spills or leaks (of radioactive material) that were communicated to State/Local Stakeholders. (continued)

DAECODAM Page 127 of 280 Rev. 37 TABLE 8.2-1 REPORTING REQUIREMENTS (continued) 8.2 ANNUAL RADIOACTIVE MATERIAL RELEASE REPORT (YEAR) LIQUID EFFLUENTS Nuclides Released Unit Quarter Quarter strontium-89 Ci E E strontium-90 Ci E E cesium-134 Ci E E cesium-137 Ci E E iodine-131 Ci E E cobalt-58 Ci E E cobalt-60 Ci E E iron-55 Ci E E iron-59 Ci E E zinc-65 Ci E E manganese-54 Ci E E chromium-51 Ci E E zirconium-niobium-95 Ci E E molybdenum-99 Ci E E technetium-99m Ci E E barium-lanthanum-140 Ci E E cerium-141 Ci E E Other (specify)

Ci E E Ci E E Ci E E Ci E E Ci E E Total for period (above) Ci E E xenon-133 Ci E E xenon-135 Ci E E DAEC ODAM Page 128 of 280 Rev. 37 TABLE 8.2-2 REPORTING REQUIREMENTS (continued) 8.2 ANNUAL RADIOACTIVE MATERIAL RELEASE REPORT (YEAR) GASEOUS EFFLUENTS Nuclides Released Unit Quarter Quarter 1. Fission gases krypton-85 Ci E E krypton-85m Ci E E krypton-87 Ci E E krypton-88 Ci E E xenon-133 Ci E E xenon-135 Ci E E xenon-135m Ci E E xenon-138 Ci E E Others (specify)

Ci E E Ci E E Ci E E Total for period Ci E E 2. Iodines iodine-131 Ci E E iodine-133 Ci E E iodine-135 Ci E E Others (specify)

Total for period Ci .E .E 3. Particulates strontium-89 Ci E E strontium-90 Ci E E cesium-134 Ci E E cesium-137 Ci E E barium-lanthanum-140 Ci E E Others (specify)

Ci E E Ci E E DAECODAM Page 129 of 280 Rev. 37 REPORTING REQUIREMENTS (continued) 8.2 8.2.2 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT An annual report of radiological environmental surveillance activities required by Section 6.3.2 shall be submitted to the NRC by May 15th of each year. Each report shall be consistent with the objectives outlined in the ODAM, and with 10 CFR 50, Appendix I, Sections IV.B.2, IV.B.3, and IV.C. The report shall include the following information:

(1) A summary description of the radiological environmental monitoring program required by Section 6.3.2. (2) A map and a table of distances and directions of locations of sampling stations required in Table 6.3-1. (3) A summary of the land use census required in Section 7.3.2.2. (4) Results of analyses of samples required by the radiological environmental monitoring program, Table 6.3-1. In the event some results are not available, the reasons shall be explained in the report. In the event the missing results are obtained, they shall be submitted in a supplementary report as soon as is reasonable.

(5) An assessment of radiation doses to a MEMBER OF THE PUBLIC likely to be the most exposed due to radioactive liquid and gaseous effluents released from DAEC during the year. The assessment shall be performed as described in the ODAM. (6) Deleted. (7) Results of participation in the lnterlaboratory Comparison Program. (8) Deviation from environmental sampling schedule.

(9) A report of all analyses in which the LLD, required by Table 6.3-2, was not achieved.

(10) A report of any changes in sample locations.

(11) Include a description for all sample analyses/conditions for which communications were made to State and Local Stakeholders due to exceeding the REMP reporting levels provided in the plant's OCDM/ODAM for locations that are described in the plant's REMP or GWPP programs.

DAECODAM Page 130 of 280 Rev. 37 8.2.3 SPECIAL REPORTS REPORTING REQUIREMENTS (continued) 8.2 Special reports shall be submitted to the Director of Inspection and Enforcement Regional Office within the time period specified for each report. These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference specification.

1. Radioactive Liquid or Gaseous Effluent -calculated dose exceeding specified limit (ODAM Sections 6.1.3, 6.2.3, and 6.2.4). 2. Off-Gas System inoperable (ODAM Section 6.2.5). 3. Measured levels of radioactivity in an environmental sampling medium determined to exceed the reporting level values of ODAM Table 6.3-3 when averaged over any calendar quarter sampling period (ODAM Section 6.3.2). Report to State and Local authorities in accordance with Administrative Control Procedure (ACP) 1402.3. 4. Annual dose to a MEMBER OF THE PUBLIC determined to exceed 40 CFR Part 190 dose limit (ODAM Section 6.3.1.1).
5. Radioactive liquid waste release without treatment when activity concentration is equal to or greater than 0.01 µCi\mL (ODAM Section 6.1.4). 6. Liquid Holdup Tank Instrumentation Inoperable (ODAM Section 6.1.6). DAEC ODAM Page 131 of 280 Rev. 37 8.3.1 CHANGES TO THE ODAM REPORTING REQUIREMENTS (continued) 8.2 a. Shall be documented and records of reviews performed shall be retained for the duration of the facility operating license. This documentation shall contain: 1) Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change(s) and: 2) A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 72.104, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent dose or setpoint calculations.
b. Shall become effective after review and acceptance by the Onsite Review Group and approval by the DAEC Site Director.
c. Shall be submitted to the commission in the form of a complete, legible copy of the entire ODAM as a part of or concurrent with the Annual Radioactive Material Release Report for the period of the report in which any change to the ODAM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date the change was implemented.

DAEC ODAM Page 132 of 280 Rev.37 Appendix A APPENDIX A: DOSE TRANSFER FACTORS FOR AIRBORNE PATHWAYS Environmental pathway models have been solved on the bases of unit radionuclide release in effluent (1 Ci/yr) and unit atmospheric dispersion (1 sec/m 3} or deposition (1/m 2) to derive dose transfer factors for airborne effluent.

The dose transfer factors in this appendix were computed with the GASPAR II computer programa, using default values of parameters applicable to the most exposed members of the public as recommended in Regulatory Guide 1.109, revision 1, with the following exceptions.

Significant revisions of data since publication of the Regulatory Guide 1.109, revision 1 and incorporated into GASPAR II were employed.

Data differing from those in the Regulatory Guide 1.109 are identified in GASPAR II documentation.b After publishing Reg. Guide 1.109, the NRC recommended that soil-to-plant bioaccumulation factors, Biv. of cesium and strontium be changed.c The revised values were used to derive dose transfer factors tabulated for Sr89, Sr90, and Cs137. Values of environmental transit time recommended in Reg. Guide 1.109,d namely 1440 hr from harvest of stored vegetables to ingestion, were retained in lieu of default values in GASPAR 11.e These factors affected dose transfer factors more than 10% only for H3, Sr89, Sr90, Cs137, Ce141, and Ce144. Dose transfer factors from C14 via inhalation and from Kr90 via irradiation by an airborne cloud are the same as in the previous MIDAS library since GASPAR II does not produce them. Skin dose transfer factors are assumed to be the same as total body dose transfer factors for H3 and C14 in exposure pathways involving inhalation or ingestion also because GASPAR II does not calculate them. a b c d e Strenge, D.L., et. al., GASPAR II -Technical Reference and User Guide, NUREG/CR-4653, March 1987 Ibid. I 3. 3. 1. 1, 3. 3. 2. 3 USNRC, SECY-79-653A, January 30, 1980. Regulatory Guide 1.109, rev. 1, Table E-15 Strenge, et. al., p. C.3. DAECODAM Page 133 of 280 Rev. 37 Appendix A Dose transfer factors are included hereafter for the following parameters.

Pathway Age Group Organ Inhalation Adult Total Body Ground irradiation Teenager GI tract Grass-cow-milk Child Bone Grass-goat-milk Infant Liver Grass-cow-meat Kidney Vegetables, leafy + produce Thyroid Plume irradiation Lung Skin DAEC ODAM Page 134 of 280 Rev. 37 Appendix A DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT AIR Computed by GASPAR II AGE =ADULT PATHWAY= INHALATION TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN (mrem m 2)/Ci H 3 2.28E+01 2.28E+01 O.OOE-01 2.28E+01 2.28E+01 2.28E+01 2.28E+01 2.28E+01 c 14 1.08E+02 1.08E+02 5.76E+02 1.08E+02 1.08E+02 1.08E+02 1.08E+02 0.00E-01 AR41 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR83m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR85m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 85 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 87 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 88 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 89 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 90 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE131m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE133m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE133 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE135m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE135 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE137 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE138 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CR 51 3.17E+OO 1.05E+02 O.OOE-01 O.OOE-01 7.23E-01 1.89E+OO 4.56E+02 O.OOE-01 MN 54 2.00E+02 2.45E+03 O.OOE-01 1.25E+03 3.12E+02 O.OOE-01 4.44E+04 O.OOE-01 FE 55 1.25E+02 1.91 E+02 7.81E+02 5.38E+02 O.OOE-01 O.OOE-01 2.29E+03 O.OOE-01 FE 59 3.36E+02 5.96E+03 3.74E+02 8.81 E+02 O.OOE-01 O.OOE-01 3.23E+04 O.OOE-01 co 58 6.56E+01 3.36E+03 O.OOE-01 5.01E+01 O.OOE-01 O.OOE-01 2.94E+04 O.OOE-01 C060 4.69E+02 9.03E+03 O.OOE-01 3.64E+02 O.OOE-01 O.OOE-01 1.89E+05 O.OOE-01 ZN 65 1.48E+03 1.70E+03 1.03E+03 3.26E+03 2.19E+03 O.OOE-01 2.74E+04 O.OOE-01 SR 89 2.76E+02 1.11E+04 9.63E+03 O.OOE-01 O.OOE-01 O.OOE-01 4.44E+04 O.OOE-01 SR 90 1.83E+04 2.29E+04 9.10E+05 0.00E-01 O.OOE-01 O.OOE-01 3.04E+05 O.OOE-01 ZR 95 7.38E+02 4.75E+03 3.39E+03 1.09E+03 1.72E+03 O.OOE-01 5.61E+04 O.OOE-01 SB124 3.93E+02 1.29E+04 9.89E+02 1.87E+01 O.OOE-01 2.40E+OO 7.86E+04 O.OOE-01 CS134 2.31 E+04 3.30E+02 1.18E+04 2.69E+04 9.10E+03 O.OOE-01 3.09E+03 O.OOE-01 CS136 3.49E+03 3.71E+02 1.24E+03 4.63E+03 2.71 E+03 O.OOE-01 3.80E+02 O.OOE-01 CS137 1.36E+04 2.66E+02 1.52E+04 1.97E+04 7.07E+03 O.OOE-01 2.38E+03 O.OOE-01 BA140 8.14E+01 6.91 E+03 1.24E+03 1.56E+OO 5.29E-01 O.OOE-01 4.02E+04 O.OOE-01 CE141 4.85E+01 3.80E+03 6.31E+02 4.28E+02 1.99E+02 O.OOE-01 1.15E+04 O.OOE-01 CE144 5.83E+03 2.59E+04 1.09E+05 4.53E+04 2.69E+04 O.OOE-01 2.47E+05 O.OOE-01 I 131 6.50E+02 1.99E+02 7.99E+02 1.13E+03 1.94E+03 3.77E+05 O.OOE-01 O.OOE-01 1133 1.43E+02 2.81 E+02 2.74E+02 4.69E+02 8.21E+02 6.81 E+04 O.OOE-01 O.OOE-01 DAEC ODAM Page 135 of 280 Rev.37 Appendix A DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT AIR Computed by GASPAR II AGE =ADULT PATHWAY= GROUND PLANE TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN {mrem m 2)/Ci H 3 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 c 14 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 AR41 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR83m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR85m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 85 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 87 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 88 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 89 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 90 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE131m O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE133m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE133 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE135m O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE135 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE137 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE138 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CR 51 1.47E+05 1.47E+05 1.47E+05 1.47E+05 1.47E+05 1.47E+05 1.47E+05 1.74E+05 MN 54 4.37E+07 4.37E+07 4.37E+07 4.37E+07 4.37E+07 4.37E+07 4.37E+07 5.13E+07 FE 55 9.80E+05 2.77E+05 5.48E+06 1.61E+06 O.OOE-01 O.OOE-01 3.22E+06 O.OOE-01 FE 59 8.65E+06 8.65E+06 8.65E+06 8.65E+06 8.65E+06 8.65E+06 8.65E+06 1.01E+07 co 58 1.20E+07 1.20E+07 1.20E+07 1.20E+07 1.20E+07 1.20E+07 1.20E+07 1.41E+07 co 60 6.81 E+08 6.81 E+08 6.81 E+08 6.81 E+08 6.81 E+08 6.81 E+08 6.81 E+08 8.02E+08 ZN 65 2.36E+07 2.36E+07 2.36E+07 2.36E+07 2.36E+07 2.36E+07 2.36E+07 2.72E+07 SR 89 6.85E+02 6.85E+02 6.85E+02 6.85E+02 6.85E+02 6.85E+02 6.85E+02 7.95E+02 SR 90 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 ZR 95 7.76E+06 7.76E+06 7.76E+06 7.76E+06 7.76E+06 7.76E+06 7.76E+06 9.03E+06 SB124 1.90E+07 1.90E+07 1.90E+07 1.90E+07 1.90E+07 1.90E+07 1.90E+07 2.19E+07 CS134 2.17E+08 2.17E+08 2.17E+08 2.17E+08 2.17E+08 2.17E+08 2.17E+08 2.53E+08 CS136 4.75E+06 4.75E+06 4.75E+06 4.75E+06 4.75E+06 4.75E+06 4.75E+06 5.39E+06 CS137 3.26E+08 3.26E+08 3.26E+08 3.26E+08 3.26E+08 3.26E+08 3.26E+08 3.80E+08 BA140 6.SOE+OS 6.SOE+OS 6.SOE+OS 6.SOE+OS 6.SOE+OS 6.SOE+OS 6.50E+05 7.45E+05 CE141 4.34E+05 4.34E+05 4.34E+05 4.34E+05 4.34E+05 4.34E+05 4.34E+05 4.88E+05 CE144 2.21 E+06 2.21 E+06 2.21 E+06 2.21 E+06 2.21 E+06 2.21 E+06 2.21E+06 2.55E+06 I 131 2.73E+05 2.73E+05 2.73E+05 2.73E+05 2.73E+05 2.73E+05 2.73E+05 3.33E+05 1133 3.90E+04 3.90E+04 3.90E+04 3.90E+04 3.90E+04 3.90E+04 3.90E+04 4.72E+04 DAEC ODAM Page 136 of 280 Rev.37 Appendix A DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT AIR Computed by GASPAR II AGE =ADULT PATHWAY= COW-MILK TOTAL BODY GI-LU BONE LIVER KIDNEY THYROID LUNG SKIN (mrem m 2)/Ci H 3 1.39E+01 1.39E+01 O.OOE-01 1.39E+01 1.39E+01 1.39E+01 1.39E+01 1.39E+01 c 14 2.33E+03 2.33E+03 1.16E+04 2.33E+03 2.33E+03 2.33E+03 2.33E+03 2.33E+03 AR41 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR83m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR85m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 85 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 87 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 88 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 89 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 90 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE131m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE133m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE133 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE135m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE135 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE137 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE138 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CR 51 8.08E+02 2.03E+05 O.OOE-01 O.OOE-01 1.78E+02 4.85E+02 1.07E+03 O.OOE-01 MN 54 4.06E+04 6.53E+05 O.OOE-01 2.13E+05 6.34E+04 O.OOE-01 O.OOE-01 O.OOE-01 FE 55 8.26E+04 2.03E+05 5.12E+05 3.54E+05 O.OOE-01 O.OOE-01 1.97E+05 O.OOE-01 FE 59 7.29E+05 6.34E+06 8.08E+05 1.90E+06 O.OOE-01 O.OOE-01 5.29E+05 O.OOE-01 co 58 2.79E+05 2.52E+06 O.OOE-01 1.24E+05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 C060 9.10E+05 7.73E+06 O.OOE-01 4.12E+05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZN 65 5.61E+07 7.83E+07 3.90E+07 1.25E+08 8.33E+07 O.OOE-01 O.OOE-01 O.OOE-01 SR 89 1.21E+06 6.75E+06 4.21 E+07 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 90 1.40E+08 1.76E+08 6.97E+09 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 95 5.42E+OO 2.54E+04 2.50E+01 8.02E+OO 1.26E+01 O.OOE-01 O.OOE-01 O.OOE-01 SB124 2.72E+05 1.95E+07 6.85E+05 1.30E+04 O.OOE-01 1.66E+03 5.32E+05 O.OOE-01 CS134 2.77E+08 5.93E+06 1.43E+08 3.39E+08 1.10E+08 O.OOE-01 3.64E+07 O.OOE-01 CS136 2.26E+07 3.55E+06 7.95E+06 3.14E+07 1.75E+07 O.OOE-01 2.39E+06 O.OOE-01 CS137 1.76E+08 5.20E+06 1.97E+08 2.69E+08 9.13E+07 O.OOE-01 3.04E+07 O.OOE-01 BA140 5.32E+04 1.68E+06 8.14E+05 1.02E+03 3.49E+02 O.OOE-01 5.86E+02 O.OOE-01 CE141 1.04E+01 3.49E+05 1.35E+02 9.16E+01 4.25E+01 O.OOE-01 O.OOE-01 O.OOE-01 CE144 4.82E+02 3.03E+06 8.97E+03 3.74E+03 2.22E+03 O.OOE-01 O.OOE-01 O.OOE-01 1131 3.77E+06 1.74E+06 4.63E+06 6.59E+06 1.13E+07 2.16E+09 O.OOE-01 O.OOE-01 1133 3.26E+04 9.60E+04 6.15E+04 1.07E+05 1.87E+05 1.57E+07 O.OOE-01 O.OOE-01 DAEC ODAM Page 137 of 280 Rev. 37 Appendix A DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT AIR Computed by GASPAR II AGE =ADULT PATHWAY= GOAT-MILK TOTAL BODY GI-LU BONE LIVER KIDNEY THYROID LUNG SKIN (mrem m 2)/Ci H 3 2.84E+01 2.84E+01 O.OOE-01 2.84E+01 2.84E+01 2.84E+01 2.84E+01 2.84E+01 c 14 2.33E+03 2.33E+03 1.16E+04 2.33E+03 2.33E+03 2.33E+03 2.33E+03 2.33E+03 AR41 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR83m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR85m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 85 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 87 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 88 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 89 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 90 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE131m O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE133m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE133 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE135m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE135 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE137 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE138 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CR 51 9.70E+01 2.44E+04 O.OOE-01 O.OOE-01 2.14E+01 5.80E+01 1.29E+02 O.OOE-01 MN 54 4.88E+03 7.83E+04 O.OOE-01 2.55E+04 7.61 E+03 O.OOE-01 O.OOE-01 O.OOE-01 FE 55 1.07E+04 2.63E+04 6.65E+04 4.60E+04 O.OOE-01 O.OOE-01 2.57E+04 O.OOE-01 FE 59 9.44E+04 8.21 E+05 1.05E+05 2.47E+05 O.OOE-01 O.OOE-01 6.91 E+04 O.OOE-01 C058 3.36E+04 3.02E+05 O.OOE-01 1.49E+04 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 C060 1.09E+05 9.29E+05 O.OOE-01 4.94E+04 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZN 65 6.75E+06 9.41E+06 4.69E+06 1.49E+07 9.98E+06 O.OOE-01 O.OOE-01 O.OOE-01 SR 89 2.54E+06 1.42E+07 8.84E+07 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 90 2.94E+08 3.68E+08 1.46E+10 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 95 6.53E-01 3.05E+03 3.00E+OO 9.63E-01 1.51E+OO O.OOE-01 O.OOE-01 O.OOE-01 SB124 3.26E+04 2.34E+06 8.24E+04 1.56E+03 O.OOE-01 2.00E+02 6.40E+04 O.OOE-01 CS134 8.30E+08 1.78E+07 4.28E+08 1.02E+09 3.30E+08 O.OOE-01 1.09E+08 O.OOE-01 CS136 6.78E+07 1.07E+07 2.38E+07 9.41E+07 5.23E+07 O.OOE-01 7.16E+06 O.OOE-01 CS137 5.29E+08 1.56E+07 5.89E+08 8.08E+08 2.74E+08 O.OOE-01 9.10E+07 O.OOE-01 BA140 6.40E+03 2.01E+05 9.76E+04 1.23E+02 4.18E+01 O.OOE-01 7.04E+01 O.OOE-01 CE141 1.25E+OO 4.18E+04 1.62E+01 1.10E+01 5.10E+OO O.OOE-01 O.OOE-01 O.OOE-01 CE144 5.77E+01 3.64E+05 1.07E+03 4.50E+02 2.67E+02 O.OOE-01 O.OOE-01 O.OOE-01 I 131 4.53E+06 2.09E+06 5.55E+06 7.92E+06 1.36E+07 2.60E+09 O.OOE-01 O.OOE-01 1133 3.90E+04 1.15E+05 7.38E+04 1.28E+05 2.24E+05 1.89E+07 O.OOE-01 O.OOE-01 DAEC ODAM Page 138 of 280 Rev.37 Appendix A DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT AIR Computed by GASPAR II AGE =ADULT PATHWAY= ANIMAL-MEAT TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN m 2}/Ci H 3 5.93E+OO 5.93E+OO O.OOE-01 5.93E+OO 5.93E+OO 5.93E+OO 5.93E+OO 5.93E+OO c 14 2.13E+03 2.13E+03 1.06E+04 2.13E+03 2.13E+03 2.13E+03 2.13E+03 2.13E+03 AR41 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 83m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 85m O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 85 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 87 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 88 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 89 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 90 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE131m 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE133m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE133 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE135m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE135 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE137 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE138 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CR 51 1.99E+02 5.01 E+04 O.OOE-01 O.OOE-01 4.40E+01 1.19E+02 2.65E+02 O.OOE-01 MN 54 4.44E+04 7.10E+05 0.00E-01 2.32E+05 6.91 E+04 O.OOE-01 O.OOE-01 O.OOE-01 FE 55 7.36E+05 1.81 E+06 4.58E+06 3.17E+06 O.OOE-01 O.OOE-01 1.77E+06 O.OOE-01 FE 59 6.50E+06 5.64E+07 7.23E+06 1.70E+07 O.OOE-01 O.OOE-01 4.75E+06 O.OOE-01 co 58 1.08E+06 9.76E+06 O.OOE-01 4.82E+05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 C060 4.15E+06 3.55E+07 O.OOE-01 1.89E+06 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZN 65 1.46E+07 2.03E+07 1.01E+07 3.23E+07 2.16E+07 O.OOE-01 O.OOE-01 O.OOE-01 SR 89 2.51 E+05 1.40E+06 8.75E+06 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 90 3.74E+07 4.66E+07 1.85E+09 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 95 1.08E+04 5.04E+07 4.98E+04 1.59E+04 2.50E+04 O.OOE-01 O.OOE-01 O.OOE-01 SB124 2.09E+05 1.50E+07 5.26E+05 9.98E+03 O.OOE-01 1.28E+03 4.12E+05 O.OOE-01 CS134 3.23E+07 6.91 E+05 1.66E+07 3.93E+07 1.28E+07 O.OOE-01 4.25E+06 O.OOE-01 CS136 1.03E+06 1.63E+05 3.61 E+05 1.43E+06 7.95E+05 O.OOE-01 1.09E+05 O.OOE-01 CS137 2.08E+07 6.15E+05 2.33E+07 3.17E+07 1.08E+07 O.OOE-01 3.58E+06 O.OOE-01 BA140 5.70E+04 1.79E+06 8.71E+05 1.09E+03 3.71E+02 O.OOE-01 6.27E+02 O.OOE-01 CE141 3.01E+01 1.01E+06 3.93E+02 2.65E+02 1.23E+02 O.OOE-01 O.OOE-01 O.OOE-01 CE144 1.96E+03 1.24E+07 3.64E+04 1.53E+04 9.06E+03 O.OOE-01 O.OOE-01 O.OOE-01 I 131 1.37E+05 6.31E+04 1.67E+05 2.39E+05 4.09E+05 7.83E+07 O.OOE-01 O.OOE-01 1133 3.11 E-03 9.16E-03 5.86E-03 1.02E-02 1.78E-02 1.50E+OO O.OOE-01 O.OOE-01 DAEC ODAM Page 139 of 280 Rev. 37 Appendix A DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT AIR Computed by GASPAR II AGE =ADULT PATHWAY= VEGETABLES TOTAL BODY GI-LU BONE LIVER KIDNEY THYROID LUNG SKIN (mrem m 2)/Ci H 3 4.12E+01 4.12E+01 O.OOE-01 4.12E+01 4.12E+01 4.12E+01 4.12E+01 4.12E+01 c 14 5.74E+03 5.74E+03 2.87E+04 5.74E+03 5.74E+03 5.74E+03 5.74E+03 5.74E+03 AR41 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR83m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR85m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 85 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 87 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 88 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 89 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 90 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE131m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE133m 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE133 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE135m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 XE135 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE137 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE138 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CR 51 1.45E+03 3.64E+05 O.OOE-01 O.OOE-01 3.20E+02 8.68E+02 1.93E+03 O.OOE-01 MN 54 1.86E+06 2.99E+07 O.OOE-01 9.76E+06 2.90E+06 O.OOE-01 O.OOE-01 O.OOE-01 FE 55 3.99E+05 9.84E+05 2.49E+06 1.71E+06 O.OOE-01 O.OOE-01 9.56E+05 O.OOE-01 FE 59 3.52E+06 3.07E+07 3.93E+06 9.19E+06 O.OOE-01 O.OOE-01 2.57E+06 O.OOE-01 co 58 2.13E+06 1.93E+07 O.OOE-01 9.51 E+05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 co 60 1.16E+07 9.92E+07 O.OOE-01 5.29E+06 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZN 65 1.83E+07 2.55E+07 1.27E+07 4.06E+07 2.70E+07 O.OOE-01 O.OOE-01 O.OOE-01 SR 89 9.19E+06 5.13E+07 3.20E+08 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 90 1.26E+09 1.57E+09 6.27E+10 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 95 7.89E+03 3.68E+07 3.64E+04 1.16E+04 1.83E+04 0.00E-01 O.OOE-01 O.OOE-01 SB124 1.27E+06 9.13E+07 3.20E+06 6.08E+04 O.OOE-01 7.80E+03 2.50E+06 O.OOE-01 CS134 2.87E+08 6.15E+06 1.47E+08 3.52E+08 1.13E+08 O.OOE-01 3.77E+07 O.OOE-01 CS136 3.83E+06 6.02E+05 1.35E+06 5.32E+06 2.96E+06 O.OOE-01 4.06E+05 O.OOE-01 CS137 2.06E+08 6.08E+06 2.30E+08 3.14E+08 1.07E+08 O.OOE-01 3.55E+07 O.OOE-01 BA140 2.67E+05 8.37E+06 4.06E+06 5.10E+03 1.74E+03 O.OOE-01 2.92E+03 O.OOE-01 CE141 4.72E+02 1.59E+07 6.15E+03 4.15E+03 1.93E+03 O.OOE-01 O.OOE-01 O.OOE-01 CE144 5.36E+04 3.39E+08 9.98E+05 4.18E+05 2.48E+05 O.OOE-01 O.OOE-01 O.OOE-01 I 131 1.05E+06 4.82E+05 1.28E+06 1.83E+06 3.14E+06 5.99E+08 O.OOE-01 O.OOE-01 I 133 1.75E+04 5.17E+04 3.30E+04 5.74E+04 1.00E+05 8.43E+06 O.OOE-01 O.OOE-01 DAEC ODAM Page 140 of 280 Rev.37 Appendix A DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT AIR Computed by GASPAR II AGE =ADULT PATHWAY= PLUME TOTAL BODY GI-LU BONE LIVER KIDNEY THYROID LUNG SKIN {mrem m 3}/{Ci sec} H 3 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 c 14 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 AR41 1.96E+02 1.96E+02 1.96E+02 1.96E+02 1.96E+02 1.96E+02 1.96E+02 3.14E+02 KR83m 1.68E-03 1.68E-03 1.68E-03 1.68E-03 1.68E-03 1.68E-03 9.38E-02 4.75E-01 KR85m 2.60E+01 2.60E+01 2.60E+01 2.60E+01 2.60E+01 2.60E+01 2.66E+01 7.67E+01 KR 85 3.58E-01 3.58E-01 3.58E-01 3.58E-01 3.58E-01 3.58E-01 9.51 E-01 4.28E+01 KR 87 1.32E+02 1.32E+02 1.32E+02 1.32E+02 1.32E+02 1.32E+02 1.35E+02 4.60E+02 KR 88 3.26E+02 3.26E+02 3.26E+02 3.26E+02 3.26E+02 3.26E+02 3.26E+02 4.50E+02 KR 89 3.68E+02 3.68E+02 3.68E+02 3.68E+02 3.68E+02 3.68E+02 3.71E+02 7.48E+02 KR 90 3.46E+02 3.46E+02 3.46E+02 3.46E+02 3.46E+02 3.46E+02 3.49E+02 6.33E+02 XE131m 2.03E+OO 2.03E+OO 2.03E+OO 2.03E+OO 2.03E+OO 2.03E+OO 2.38E+OO 1.89E+01 XE133m 5.58E+OO 5.58E+OO 5.58E+OO 5.58E+OO 5.58E+OO 5.58E+OO 6.02E+OO 3.96E+01 XE133 6.53E+OO 6.53E+OO 6.53E+OO 6.53E+OO 6.53E+OO 6.53E+OO 6.85E+OO 1.84E+01 XE135m 6.91E+01 6.91 E+01 6.91E+01 6.91E+01 6.91E+01 6.91E+01 6.94E+01 1.05E+02 XE135 4.02E+01 4.02E+01 4.02E+01 4.02E+01 4.02E+01 4.02E+01 4.09E+01 1.06E+02 XE137 3.15E+01 3.15E+01 3.15E+01 3.15E+01 3.15E+01 3.15E+01 3.55E+01 4.25E+02 XE138 1.96E+02 1.96E+02 1.96E+02 1.96E+02 1.96E+02 1.96E+02 1.97E+02 3.58E+02 CR 51 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 MN 54 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 FE 55 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 FE 59 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 co 58 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 C060 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZN 65 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 0.00E-01 SR 89 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 90 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 ZR 95 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SB124 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CS134 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 CS136 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CS137 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 BA140 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 CE141 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CE144 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 I 131 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 1133 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 DAEC ODAM Page 141 of 280 Rev. 37 Appendix A DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT AIR Computed by GASPAR II AGE =TEENAGER PATHWAY= INHALATION TOTAL BODY GI-LU BONE LIVER KIDNEY THYROID LUNG SKIN {mrem m 3}/{Ci sec} H 3 2.30E+01 2.30E+01 O.OOE-01 2.30E+01 2.30E+01 2.30E+01 2.30E+01 2.30E+01 c 14 1.54E+02 1.54E+02 8.24E+02 1.54E+02 1.54E+02 1.54E+02 1.54E+02 O.OOE-01 AR41 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR83m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR85m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 85 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 KR 87 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 88 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 89 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 90 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE131m O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE133m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE133 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE135m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE135 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE137 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE138 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CR51 4.28E+OO 9.51E+01 O.OOE-01 O.OOE-01 9.73E-01 2.38E+OO 6.65E+02 O.OOE-01 MN 54 2.66E+02 2.12E+03 O.OOE-01 1.62E+03 4.02E+02 O.OOE-01 6.27E+04 O.OOE-01 FE 55 1.75E+02 2.02E+02 1.06E+03 7.55E+02 O.OOE-01 O.OOE-01 3.94E+03 O.OOE-01 FE 59 4.53E+02 5.64E+03 5.04E+02 1.17E+03 O.OOE-01 O.OOE-01 4.85E+04 O.OOE-01 C058 8.81 E+01 3.02E+03 O.OOE-01 6.56E+01 O.OOE-01 O.OOE-01 4.25E+04 O.OOE-01 C060 6.27E+02 8.21 E+03 O.OOE-01 4.79E+02 O.OOE-01 O.OOE-01 2.76E+05 O.OOE-01 ZN 65 1.98E+03 1.48E+03 1.22E+03 4.25E+03 2.74E+03 O.OOE-01 3.93E+04 O.OOE-01 SR 89 3.96E+02 1.18E+04 1.38E+04 O.OOE-01 O.OOE-01 O.OOE-01 7.67E+04 O.OOE-01 SR 90 2.11E+04 2.42E+04 1.05E+06 O.OOE-01 O.OOE-01 O.OOE-01 5.23E+05 O.OOE-01 ZR 95 9.98E+02 4.72E+03 4.63E+03 1.45E+03 2.14E+03 O.OOE-01 8.52E+04 O.OOE-01 SB124 5.32E+02 1.26E+04 1.37E+03 2.52E+01 O.OOE-01 3.09E+OO 1.22E+05 O.OOE-01 CS134 1.74E+04 3.09E+02 1.59E+04 3.58E+04 1.19E+04 O.OOE-01 4.63E+03 O.OOE-01 CS136 4.34E+03 3.45E+02 1.63E+03 6.15E+03 3.49E+03 O.OOE-01 5.64E+02 O.OOE-01 CS137 9.86E+03 2.69E+02 2.13E+04 2.69E+04 9.63E+03 O.OOE-01 3.83E+03 O.OOE-01 BA140 1.12E+02 7.26E+03 1.73E+03 2.13E+OO 7.23E-01 O.OOE-01 6.43E+04 O.OOE-01 CE141 6.88E+01 3.99E+03 9.00E+02 6.02E+02 2.81 E+02 O.OOE-01 1.95E+04 O.OOE-01 CE144 8.33E+03 2.74E+04 1.55E+05 6.40E+04 3.83E+04 O.OOE-01 4.25E+05 O.OOE-01 I 131 8.37E+02 2.06E+02 1.12E+03 1.56E+03 2.66E+03 4.63E+05 O.OOE-01 O.OOE-01 1133 1.97E+02 3.26E+02 3.87E+02 6.50E+02 1.14E+03 9.25E+04 O.OOE-01 O.OOE-01 DAEC ODAM Page 142 of 280 Rev. 37 Appendix A DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT AIR Computed by GASPAR II AGE =TEENAGER PATHWAY= GROUND PLANE TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN mrem m 2 /Ci H 3 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 c 14 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 AR41 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 83m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR85m O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 85 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 87 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 88 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 89 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 90 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE131m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE133m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE133 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE135m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 XE135 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE137 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE138 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 CR 51 1.47E+05 1.47E+05 1.47E+05 1.47E+05 1.47E+05 1.47E+05 1.47E+05 1.74E+05 MN 54 4.37E+07 4.37E+07 4.37E+07 4.37E+07 4.37E+07 4.37E+07 4.37E+07 5.13E+07 FE 55 1.06E+06 3.10E+05 5.57E+06 1.69E+06 O.OOE-01 O.OOE-01 O.OOE-01 3.22E+06 FE 59 8.65E+06 8.65E+06 8.65E+06 8.65E+06 8.65E+06 8.65E+06 8.65E+06 1.01E+07 co 58 1.20E+07 1.20E+07 1.20E+07 1.20E+07 1.20E+07 1.20E+07 1.20E+07 1.41E+07 co 60 6.81 E+08 6.81 E+08 6.81E+08 6.81E+08 6.81E+08 6.81E+08 6.81 E+08 8.02E+08 ZN 65 2.36E+07 2.36E+07 2.36E+07 2.36E+07 2.36E+07 2.36E+07 2.36E+07 2.72E+07 SR 89 6.85E+02 6.85E+02 6.85E+02 6.85E+02 6.85E+02 6.85E+02 6.85E+02 7.95E+02 SR 90 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 95 7.76E+06 7.76E+06 7.76E+06 7.76E+06 7.76E+06 7.76E+06 7.76E+06 9.03E+06 SB124 1.90E+07 1.90E+07 1.90E+07 1.90E+07 1.90E+07 1.90E+07 1.90E+07 2.19E+07 CS134 2.17E+08 2.17E+08 2.17E+08 2.17E+08 2.17E+08 2.17E+08 2.17E+08 2.53E+08 CS136 4.75E+06 4.75E+06 4.75E+06 4.75E+06 4.75E+06 4.75E+06 4.75E+06 5.39E+06 CS137 3.26E+08 3.26E+08 3.26E+08 3.26E+08 3.26E+08 3.26E+08 3.26E+08 3.80E+08 BA140 6.50E+05 6.50E+05 6.50E+05 6.50E+05 6.50E+05 6.50E+05 6.50E+05 7.45E+05 CE141 4.34E+05 4.34E+05 4.34E+05 4.34E+05 4.34E+05 4.34E+05 4.34E+05 4.88E+05 CE144 2.21 E+06 2.21 E+06 2.21 E+06 2.21 E+06 2.21E+06 2.21 E+06 2.21E+06 2.55E+06 I 131 2.73E+05 2.73E+05 2.73E+05 2.73E+05 2.73E+05 2.73E+05 2.73E+05 3.33E+05 1133 3.90E+04 3.90E+04 3.90E+04 3.90E+04 3.90E+04 3.90E+04 3.90E+04 4.72E+04 DAEC ODAM Page 143 of 280 Rev. 37 Appendix A DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT AIR Computed by GASPAR II AGE =TEENAGER PATHWAY= COW-MILK TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN mrem m 2 /Ci H 3 1.81 E+01 1.81E+01 O.OOE-01 1.81 E+01 1.81E+01 1.81 E+01 1.81 E+01 1.81E+01 c 14 4.28E+03 4.28E+03 2.15E+04 4.28E+03 4.28E+03 4.28E+03 4.28E+03 4.28E+03 AR41 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR83m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR85m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 85 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 87 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 88 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 89 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 90 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE131m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE133m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE133 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE135m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE135 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE137 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE138 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CR 51 1.41E+03 2.37E+05 O.OOE-01 O.OOE-01 3.10E+02 7.86E+02 2.02E+03 O.OOE-01 MN 54 7.04E+04 7.26E+05 O.OOE-01 3.55E+05 1.06E+05 O.OOE-01 O.OOE-01 O.OOE-01 FE 55 1.50E+05 2.78E+05 9.08E+05 6.46E+05 O.OOE-01 O.OOE-01 4.09E+05 O.OOE-01 FE 59 1.27E+06 7.76E+06 1.41E+06 3.30E+06 O.OOE-01 O.OOE-01 1.04E+06 O.OOE-01 co 58 4.82E+05 2.89E+06 O.OOE-01 2.09E+05 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 C060 1.57E+06 9.10E+06 O.OOE-01 6.97E+05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZN 65 9.73E+07 8.84E+07 6.02E+07 2.09E+08 1.33E+08 O.OOE-01 O.OOE-01 O.OOE-01 SR 89 2.22E+06 9.25E+06 7.76E+07 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 90 2.11E+08 2.41E+08 1.06E+10 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 95 9.51 E+OO 3.20E+04 4.37E+01 1.38E+01 2.03E+01 O.OOE-01 O.OOE-01 O.OOE-01 88124 4.79E+05 2.47E+07 1.22E+06 2.25E+04 O.OOE-01 2.78E+03 1.07E+06 O.OOE-01 CS134 2.70E+08 7.26E+06 2.47E+08 5.83E+08 1.85E+08 O.OOE-01 7.07E+07 O.OOE-01 CS136 3.58E+07 4.28E+06 1.35E+07 5.32E+07 2.90E+07 O.OOE-01 4.56E+06 O.OOE-01 CS137 1.65E+08 6.75E+06 3.58E+08 4.75E+08 1.62E+08 O.OOE-01 6.27E+07 O.OOE-01 BA140 9.48E+04 2.27E+06 1.47E+06 1.80E+03 6.12E+02 O.OOE-01 1.21E+03 O.OOE-01 CE141 1.90E+01 4.72E+05 2.48E+02 1.65E+02 7.80E+01 O.OOE-01 O.OOE-01 O.OOE-01 CE144 8.87E+02 4.15E+06 1.65E+04 6.81 E+03 4.09E+03 O.OOE-01 O.OOE-01 0.00E-01 I 131 6.31 E+06 2.32E+06 8.37E+06 1.17E+07 2.02E+07 3.42E+09 O.OOE-01 O.OOE-01 1133 5.80E+04 1.44E+05 1.12E+05 1.90E+05 3.33E+05 2.66E+07 O.OOE-01 O.OOE-01 DAEC ODAM Page 144 of 280 Rev. 37 Appendix A DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT AIR Computed by GASPAR II AGE =TEENAGER PATHWAY= GOAT-MILK TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN mrem m 2 /Ci H 3 3.71E+01 3.71 E+01 O.OOE-01 3.71E+01 3.71E+01 3.71E+01 3.71E+01 3.71E+01 c 14 4.28E+03 4.28E+03 2.15E+04 4.28E+03 4.28E+03 4.28E+03 4.28E+03 4.28E+03 AR41 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR83m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 85m 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 85 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 87 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 88 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 89 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 90 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE131m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE133m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE133 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE135m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE135 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE137 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE138 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CR 51 1.70E+02 2.85E+04 O.OOE-01 O.OOE-01 3.71E+01 9.41 E+01 2.42E+02 O.OOE-01 MN 54 8.43E+03 8.71E+04 O.OOE-01 4.25E+04 1.27E+04 O.OOE-01 O.OOE-01 O.OOE-01 FE 55 1.95E+04 3.62E+04 1.18E+05 8.37E+04 O.OOE-01 O.OOE-01 5.31E+04 O.OOE-01 FE 59 1.65E+05 1.01 E+06 1.83E+05 4.28E+05 O.OOE-01 O.OOE-01 1.35E+05 O.OOE-01 co 58 5.80E+04 3.45E+05 O.OOE-01 2.51 E+04 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 C060 1.89E+05 1.09E+06 O.OOE-01 8.37E+04 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZN 65 1.17E+07 1.06E+07 7.19E+06 2.50E+07 1.60E+07 O.OOE-01 O.OOE-01 O.OOE-01 SR 89 4.66E+06 1.94E+07 1.63E+08 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 90 4.44E+08 5.07E+08 2.22E+10 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 95 1.14E+OO 3.83E+03 5.26E+OO 1.66E+OO 2.43E+OO O.OOE-01 O.OOE-01 O.OOE-01 SB124 5.74E+04 2.96E+06 1.47E+05 2.70E+03 O.OOE-01 3.33E+02 1.28E+05 O.OOE-01 CS134 8.11E+08 2.17E+07 7.42E+08 1.75E+09 5.55E+08 O.OOE-01 2.12E+08 O.OOE-01 CS136 1.07E+08 1.28E+07 4.06E+07 1.60E+08 8.68E+07 O.OOE-01 1.37E+07 O.OOE-01 CS137 4.94E+08 2.02E+07 1.07E+09 1.42E+09 4.85E+08 O.OOE-01 1.88E+08 O.OOE-01 BA140 1.14E+04 2.72E+05 1.77E+05 2.16E+02 7.32E+01 O.OOE-01 1.45E+02 O.OOE-01 CE141 2.28E+OO 5.67E+04 2.98E+01 1.99E+01 9.35E+OO O.OOE-01 O.OOE-01 O.OOE-01 CE144 1.06E+02 4.98E+05 1.98E+03 8.18E+02 4.88E+02 O.OOE-01 O.OOE-01 O.OOE-01 1131 7.54E+06 2.78E+06 1.00E+07 1.41E+07 2.42E+07 4.09E+09 O.OOE-01 O.OOE-01 1133 6.97E+04 1.73E+05 1.35E+05 2.28E+05 3.99E+05 3.20E+07 O.OOE-01 O.OOE-01 DAEC ODAM Page 145 of 280 Rev. 37 Appendix A DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT AIR Computed by GASPAR II AGE =TEENAGER PATHWAY= ANIMAL-MEAT TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN {mrem m 2}/Ci H 3 3.55E+OO 3.55E+OO O.OOE-01 3.55E+OO 3.55E+OO 3.55E+OO 3.55E+OO 3.55E+OO c 14 1.80E+03 1.80E+03 9.00E+03 1.80E+03 1.80E+03 1.80E+03 1.80E+03 1.80E+03 AR41 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR83m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR85m 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 85 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 87 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 88 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 89 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 90 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE131m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE133m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE133 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE135m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE135 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE137 0.00E-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 XE138 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 CR 51 1.59E+02 2.68E+04 O.OOE-01 O.OOE-01 3.49E+01 8.84E+01 2.28E+02 O.OOE-01 MN 54 3.52E+04 3.64E+05 O.OOE-01 1.77E+05 5.29E+04 O.OOE-01 O.OOE-01 O.OOE-01 FE 55 6.14E+05 1.13E+06 3.72E+06 2.64E+06 O.OOE-01 0.00E-01 1.67E+06 O.OOE-01 FE 59 5.20E+06 3.17E+07 5.77E+06 1.35E+07 O.OOE-01 0.00E-01 4.25E+06 O.OOE-01 co 58 8.56E+05 5.10E+06 O.OOE-01 3.71 E+05 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 C060 3.30E+06 1.91E+07 O.OOE-01 1.46E+06 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZN 65 1.16E+07 1.05E+07 7.13E+06 2.47E+07 1.58E+07 0.00E-01 O.OOE-01 O.OOE-01 SR 89 2.12E+05 8.81 E+05 7.38E+06 O.OOE-01 0.00E-01 0.00E-01 O.OOE-01 O.OOE-01 SR 90 2.57E+07 2.93E+07 1.28E+09 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 ZR 95 8.62E+03 2.90E+07 3.99E+04 1.25E+04 1.84E+04 0.00E-01 O.OOE-01 O.OOE-01 SB124 1.68E+05 8.68E+06 4.31E+05 7.95E+03 O.OOE-01 9.76E+02 3.77E+05 O.OOE-01 CS134 1.44E+07 3.87E+05 1.32E+07 3.10E+07 9.86E+06 0.00E-01 3.77E+06 O.OOE-01 CS136 7.48E+05 8.94E+04 2.83E+05 1.11 E+06 6.05E+05 0.00E-01 9.54E+04 O.OOE-01 CS137 8.94E+06 3.64E+05 1.93E+07 2.57E+07 8.75E+06 O.OOE-01 3.39E+06 O.OOE-01 BA140 4.63E+04 1.11E+06 7.19E+05 8.81E+02 2.99E+02 0.00E-01 5.93E+02 O.OOE-01 CE141 2.52E+01 6.27E+05 3.30E+02 2.20E+02 1.03E+02 O.OOE-01 O.OOE-01 O.OOE-01 CE144 1.65E+03 7.73E+06 3.08E+04 1.27E+04 7.61 E+03 O.OOE-01 O.OOE-01 O.OOE-01 I 131 1.05E+05 3.83E+04 1.39E+05 1.95E+05 3.36E+05 5.67E+07 O.OOE-01 O.OOE-01 1133 2.54E-03 6.31 E-03 4.91E-03 8.30E-03 1.46E-02 1.16E+OO O.OOE-01 O.OOE-01 DAEC ODAM Page 146 of 280 Rev.37 Appendix A DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT AIR Computed by GASPAR II AGE =TEENAGER PATHWAY= VEGETABLES TOTAL BODY GI-LU BONE LIVER KIDNEY THYROID LUNG SKIN mrem m 2 /Ci H 3 4.72E+01 4.72E+01 O.OOE-01 4.72E+01 4.72E+01 4.72E+01 4.72E+01 4.72E+01 c 14 9.32E+03 9.32E+03 4.66E+04 9.32E+03 9.32E+03 9.32E+03 9.32E+03 9.32E+03 AR41 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR83m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 85m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 85 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 87 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 88 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 89 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 90 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE131m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE133m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE133 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE135m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 XE135 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE137 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE138 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CR 51 1.93E+03 3.23E+05 O.OOE-01 O.OOE-01 4.21E+02 1.07E+03 2.75E+03 O.OOE-01 MN 54 2.81 E+06 2.91 E+07 O.OOE-01 1.42E+07 4.21E+06 O.OOE-01 O.OOE-01 O.OOE-01 FE 55 5.92+05 1.10E+06 3.59E+06 2.54E+06 O.OOE-01 O.OOE-01 1.61E+06 O.OOE-01 FE 59 5.01E+06 3.07E+07 5.58E+06 1.30E+07 O.OOE-01 O.OOE-01 4.09E+06 O.OOE-01 co 58 3.11 E+06 1.86E+07 O.OOE-01 1.35E+06 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 C060 1.77E+07 1.02E+08 O.OOE-01 7.86E+06 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZN 65 2.75E+07 2.50E+07 1.70E+07 5.89E+07 3.77E+07 O.OOE-01 O.OOE-01 O.OOE-01 SR 89 1.39E+07 5.80E+07 4.88E+08 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 90 1.66E+09 1.90E+09 8.33E+10 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 95 1.15E+04 3.87E+07 5.32E+04 1.68E+04 2.47E+04 O.OOE-01 O.OOE-01 O.OOE-01 SB124 1.87E+06 9.63E+07 4.79E+06 8.81 E+04 O.OOE-01 1.09E+04 4.18E+06 O.OOE-01 CS134 2.45E+08 6.56E+06 2.24E+08 5.29E+08 1.68E+08 O.OOE-01 6.40E+07 O.OOE-01 CS136 3.64E+06 4.37E+05 1.38E+06 5.42E+06 2.95E+06 O.OOE-01 4.66E+05 O.OOE-01 CS137 1.70E+08 6.94E+06 3.68E+08 4.88E+08 1.66E+08 O.OOE-01 6.43E+07 O.OOE-01 BA140 2.82E+05 6.75E+06 4.37E+06 5.36E+03 1.82E+03 O.OOE-01 3.61 E+03 O.OOE-01 CE141 6.78E+02 1.69E+07 8.84E+03 5.89E+03 2.78E+03 O.OOE-01 O.OOE-01 O.OOE-01 CE144 8.62E+04 4.02E+08 1.60E+06 6.62E+05 3.96E+05 O.OOE-01 O.OOE-01 O.OOE-01 I 131 9.16E+05 3.36E+05 1.22E+06 1.70E+06 2.93E+06 4.98E+08 O.OOE-01 O.OOE-01 1133 1.58E+04 3.93E+04 3.06E+04 5.20E+04 9.13E+04 7.26E+06 O.OOE-01 O.OOE-01 DAEC ODAM Page 147 of 280 Rev. 37 Appendix A DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT AIR Computed by GASPAR II AGE =TEENAGER PATHWAY= PLUME TOTAL BODY GI-LU BONE LIVER KIDNEY THYROID LUNG SKIN {mrem m 3}/{Ci sec} H 3 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 c 14 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 AR41 1.96E+02 1.96E+02 1.96E+02 1.96E+02 1.96E+02 1.96E+02 1.96E+02 3.14E+02 KR 83m 1.68E-03 1.68E-03 1.68E-03 1.68E-03 1.68E-03 1.68E-03 9.38E-02 4.75E-01 KR85m 2.60E+01 2.60E+01 2.60E+01 2.60E+01 2.60E+01 2.60E+01 2.66E+01 7.67E+01 KR 85 3.58E-01 3.58E-01 3.58E-01 3.58E-01 3.58E-01 3.58E-01 9.51 E-01 4.28E+01 KR 87 1.32E+02 1.32E+02 1.32E+02 1.32E+02 1.32E+02 1.32E+02 1.35E+02 4.60E+02 KR 88 3.26E+02 3.26E+02 3.26E+02 3.26E+02 3.26E+02 3.26E+02 3.26E+02 4.50E+02 KR 89 3.68E+02 3.68E+02 3.68E+02 3.68E+02 3.68E+02 3.68E+02 3.71 E+02 7.48E+02 KR 90 3.46E+02 3.46E+02 3.46E+02 3.46E+02 3.46E+02 3.46E+02 3.49E+02 6.33E+02 XE131m 2.03E+OO 2.03E+OO 2.03E+OO 2.03E+OO 2.03E+OO 2.03E+OO 2.38E+OO 1.89E+01 XE133m 5.58E+OO 5.58E+OO 5.58E+OO 5.58E+OO 5.58E+OO 5.58E+OO 6.02E+OO 3.96E+01 XE133 6.53E+OO 6.53E+OO 6.53E+OO 6.53E+OO 6.53E+OO 6.53E+OO 6.85E+OO 1.84E+01 XE135m 6.91E+01 6.91E+01 6.91E+01 6.91E+01 6.91E+01 6.91E+01 6.94E+01 1.05E+02 XE135 4.02E+01 4.02E+01 4.02E+01 4.02E+01 4.02E+01 4.02E+01 4.09E+01 1.06E+02 XE137 3.15E+01 3.15E+01 3.15E+01 3.15E+01 3.15E+01 3.15E+01 3.55E+01 4.25E+02 XE138 1.96E+02 1.96E+02 1.96E+02 1.96E+02 1.96E+02 1.96E+02 1.97E+02 3.58E+02 CR 51 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 MN 54 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 FE 55 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 FE 59 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 co 58 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 C060 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZN 65 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 89 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 SR 90 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 95 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SB124 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CS134 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CS136 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CS137 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BA140 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CE141 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CE144 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 1131 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 1133 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 DAEC ODAM Page 148 of 280 Rev. 37 Appendix A DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT AIR Computed by GASPAR II AGE =CHILD PATHWAY= INHALATION TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN {mrem m 3}/{Ci sec} H 3 2.03E+01 2.03E+01 O.OOE-01 2.03E+01 2.03E+01 2.03E+01 2.03E+01 2.03E+01 c 14 2.13E+02 2.13E+02 1.14E+03 2.13E+02 2.13E+02 2.13E+02 2.13E+02 O.OOE-01 AR41 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR83m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR85m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 85 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 87 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 88 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 89 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 90 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE131m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE133m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE133 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE135m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE135 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE137 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE138 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CR 51 4.88E+OO 3.42E+01 O.OOE-01 O.OOE-01 7.70E-01 2.71E+OO 5.39E+02 O.OOE-01 MN 54 3.01E+02 7.26E+02 O.OOE-01 1.36E+03 3.17E+02 O.OOE-01 5.01 E+04 O.OOE-01 FE55 2.46E+02 9.09E+02 1.50E+03 7.97E+02 O.OOE-01 O.OOE-01 3.52E+03 O.OOE-01 FE59 5.29E+02 2.24E+03 6.56E+02 1.06E+03 O.OOE-01 O.OOE-01 4.02E+04 O.OOE-01 co 58 1.00E+02 1.09E+03 O.OOE-01 5.61E+01 O.OOE-01 O.OOE-01 3.52E+04 O.OOE-01 co 60 7.19E+02 3.05E+03 O.OOE-01 4.15E+02 O.OOE-01 O.OOE-01 2.24E+05 O.OOE-01 ZN 65 2.23E+03 5.17E+02 1.35E+03 3.58E+03 2.26E+03 O.OOE-01 3.16E+04 O.OOE-01 SR 89 5.45E+02 5.29E+03 1.90E+04 O.OOE-01 O.OOE-01 O.OOE-01 6.85E+04 O.OOE-01 SR 90 2.43E+04 1.09E+04 1.22E+06 O.OOE-01 O.OOE-01 O.OOE-01 4.69E+05 O.OOE-01 ZR 95 1.17E+03 1.94E+03 6.02E+03 1.32E+03 1.89E+03 O.OOE-01 7.07E+04 O.OOE-01 SB124 6.34E+02 5.20E+03 1.82E+03 2.35E+01 O.OOE-01 3.99E+OO 1.03E+05 O.OOE-01 CS134 7.13E+03 1.22E+02 2.06E+04 3.20E+04 1.05E+04 O.OOE-01 3.83E+03 O.OOE-01 CS136 3.68E+03 1.32E+02 2.06E+03 5.42E+03 3.03E+03 O.OOE-01 4.60E+02 O.OOE-01 CS137 4.06E+03 1.15E+02 2.87E+04 2.61E+04 8.94E+03 O.OOE-01 3.30E+03 O.OOE-01 BA140 1.37E+02 3.23E+03 2.35E+03 2.05E+OO 6.69E-01 O.OOE-01 5.51E+04 O.OOE-01 CE141 9.19E+01 1.79E+03 1.24E+03 6.18E+02 2.71 E+02 O.OOE-01 1.72E+04 O.OOE-01 CE144 1.15E+04 1.23E+04 2.15E+05 6.72E+04 3.71E+04 O.OOE-01 3.80E+05 O.OOE-01 I 131 8.65E+02 9.00E+01 1.52E+03 1.52E+03 2.50E+03 5.17E+05 O.OOE-01 O.OOE-01 I 133 2.44E+02 1.74E+02 5.26E+02 6.43E+02 1.07E+03 1.22E+05 O.OOE-01 O.OOE-01 DAEC ODAM Page 149 of 280 Rev. 37 Appendix A DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT AIR Computed by GASPAR II AGE =CHILD PATHWAY= GROUND PLANE TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN {mrem m 2}/Ci H 3 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 c 14 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 AR41 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR83m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 85m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 85 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 87 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 88 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 0.00E-01 KR 89 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 90 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE131m O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE133m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE133 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE135m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE135 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE137 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE138 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CR51 1.47E+05 1.47E+05 1.47E+05 1.47E+05 1.47E+05 1.47E+05 1.47E+05 1.74E+05 MN 54 4.37E+07 4.37E+07 4.37E+07 4.37E+07 4.37E+07 4.37E+07 4.37E+07 5.13E+07 FE 55 1.23E+06 3.52E+05 6.03E+06 1.98E+06 O.OOE-01 O.OOE-01 3.86E+06 O.OOE-01 FE 59 8.65E+06 8.65E+06 8.65E+06 8.65E+06 8.65E+06 8.65E+06 8.65E+06 1.01E+07 co 58 1.20E+07 1.20E+07 1.20E+07 1.20E+07 1.20E+07 1.20E+07 1.20E+07 1.41E+07 C060 6.81E+08 6.81 E+08 6.81 E+08 6.81E+08 6.81E+08 6.81 E+08 6.81 E+08 8.02E+08 ZN 65 2.36E+07 2.36E+07 2.36E+07 2.36E+07 2.36E+07 2.36E+07 2.36E+07 2.72E+07 SR 89 6.85E+02 6.85E+02 6.85E+02 6.85E+02 6.85E+02 6.85E+02 6.85E+02 7.95E+02 SR 90 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 ZR 95 7.76E+06 7.76E+06 7.76E+06 7.76E+06 7.76E+06 7.76E+06 7.76E+06 9.03E+06 SB124 1.90E+07 1.90E+07 1.90E+07 1.90E+07 1.90E+07 1.90E+07 1.90E+07 2.19E+07 CS134 2.17E+08 2.17E+08 2.17E+08 2.17E+08 2.17E+08 2.17E+08 2.17E+08 2.53E+08 CS136 4.75E+06 4.75E+06 4.75E+06 4.75E+06 4.75E+06 4.75E+06 4.75E+06 5.39E+06 CS137 3.26E+08 3.26E+08 3.26E+08 3.26E+08 3.26E+08 3.26E+08 3.26E+08 3.80E+08 BA140 6.50E+05 6.50E+05 6.50E+05 6.50E+05 6.50E+05 6.50E+05 6.50E+05 7.45E+05 CE141 4.34E+05 4.34E+05 4.34E+05 4.34E+05 4.34E+05 4.34E+05 4.34E+05 4.88E+05 CE144 2.21E+06 2.21E+06 2.21 E+06 2.21E+06 2.21E+06 2.21E+06 2.21 E+06 2.55E+06 I 131 2.73E+05 2.73E+05 2.73E+05 2.73E+05 2.73E+05 2.73E+05 2.73E+05 3.33E+05 1133 3.90E+04 3.90E+04 3.90E+04 3.90E+04 3.90E+04 3.90E+04 3.90E+04 4.72E+04 DAEC ODAM Page 150 of 280 Rev.37 Appendix A DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT AIR Computed by GASPAR II AGE =CHILD PATHWAY= COW-MILK TOTAL BODY GI-LU BONE LIVER KIDNEY THYROID LUNG SKIN {mrem m 2}/Ci H 3 2.87E+01 2.87E+01 O.OOE-01 2.87E+01 2.87E+01 2.87E+01 2.87E+01 2.87E+01 c 14 1.06E+04 1.06E+04 5.26E+04 1.06E+04 1.06E+04 1.06E+04 1.06E+04 1.06E+04 AR41 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 83m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 85m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 85 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 87 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 88 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 89 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 90 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE131m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE133m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE133 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE135m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE135 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE137 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE138 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CR 51 2.88E+03 1.53E+05 O.OOE-01 O.OOE-01 4.37E+02 1.60E+03 2.92E+03 O.OOE-01 MN 54 1.41E+05 4.44E+05 O.OOE-01 5.29E+05 1.49E+05 O.OOE-01 O.OOE-01 O.OOE-01 FE 55 3.74E+05 2.24E+05 2.27E+06 1.21E+06 O.OOE-01 O.OOE-01 6.82E+05 O.OOE-01 FE 59 2.63E+06 5.51 E+06 3.26E+06 5.29E+06 O.OOE-01 O.OOE-01 1.53E+06 O.OOE-01 co 58 9.79E+05 1.87E+06 O.OOE-01 3.20E+05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 C060 3.20E+06 5.99E+06 O.OOE-01 1.08E+06 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZN 65 1.95E+08 5.51 E+07 1.18E+08 3.14E+08 1.98E+08 O.OOE-01 O.OOE-01 O.OOE-01 SR 89 5.48E+06 7.45E+06 1.92E+08 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 90 4.40E+08 1.95E+08 2.18E+10 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 95 1.99E+01 2.33E+04 1.02E+02 2.23E+01 3.20E+01 O.OOE-01 O.OOE-01 O.OOE-01 SB124 1.01E+06 1.81 E+07 2.89E+06 3.74E+04 O.OOE-01 6.40E+03 1.61E+06 O.OOE-01 CS134 1.97E+08 5.04E+06 5.70E+08 9.38E+08 2.90E+08 O.OOE-01 1.04E+08 O.OOE-01 CS136 5.42E+07 2.95E+06 3.05E+07 8.40E+07 4.47E+07 O.OOE-01 6.65E+06 O.OOE-01 CS137 1.21E+08 5.17E+06 8.59E+08 8.24E+08 2.68E+08 O.OOE-01 9.63E+07 O.OOE-01 BA140 2.07E+05 1.80E+06 3.55E+06 3.11E+03 1.01E+03 O.OOE-01 1.85E+03 O.OOE-01 CE141 4.53E+01 3.80E+05 6.12E+02 3.05E+02 1.33E+02 O.OOE-01 O.OOE-01 O.OOE-01 CE144 2.17E+03 3.33E+06 4.06E+04 1.27E+04 7.07E+03 O.OOE-01 O.OOE-01 O.OOE-01 I 131 1.16E+07 1.82E+06 2.03E+07 2.04E+07 3.36E+07 6.75E+09 O.OOE-01 O.OOE-01 1133 1.28E+05 1.36E+05 2.73E+05 3.36E+05 5.61 E+05 6.27E+07 O.OOE-01 O.OOE-01 DAEC ODAM Page 151 of 280 Rev. 37 '<;.

Appendix A DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT AIR Computed by GASPAR II AGE =CHILD PATHWAY= GOAT-MILK TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN {mrem m 2}/Ci H 3 5.86E+01 5.86E+01 O.OOE-01 5.86E+01 5.86E+01 5.86E+01 5.86E+01 5.86E+01 c 14 1.06E+04 1.06E+04 5.26E+04 1.06E+04 1.06E+04 1.06E+04 1.06E+04 1.06E+04 AR41 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 83m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR85m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 85 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 87 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 88 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 89 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 90 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE131m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 XE133m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE133 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 XE135m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE135 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE137 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE138 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CR 51 3.45E+02 1.83E+04 O.OOE-01 O.OOE-01 5.23E+01 1.92E+02 3.52E+02 O.OOE-01 MN 54 1.70E+04 5.36E+04 O.OOE-01 6.37E+04 1.78E+04 O.OOE-01 O.OOE-01 O.OOE-01 FE 55 4.86E+04 2.91 E+04 2.96E+04 1.57E+05 O.OOE-01 0.00E-01 8.87E+04 O.OOE-01 FE 59 3.42E+05 7.16E+05 4.25E+05 6.88E+05 O.OOE-01 O.OOE-01 1.99E+05 O.OOE-01 co 58 1.18E+05 2.24E+05 O.OOE-01 3.83E+04 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 co 60 3.83E+05 7.19E+05 O.OOE-01 1.30E+05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZN 65 2.34E+07 6.62E+06 1.41E+07 3.77E+07 2.37E+07 O.OOE-01 O.OOE-01 O.OOE-01 SR 89 1.15E+07 1.56E+07 4.02E+08 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 90 9.22E+08 4.09E+08 4.60E+10 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 95 2.39E+OO 2.80E+03 1.22E+01 2.68E+OO 3.83E+OO O.OOE-01 O.OOE-01 O.OOE-01 SB124 1.22E+05 2.17E+06 3.49E+05 4.50E+03 O.OOE-01 7.67E+02 1.93E+05 O.OOE-01 CS134 5.93E+08 1.51E+07 1.71E+09 2.81E+09 8.71E+08 O.OOE-01 3.12E+08 O.OOE-01 CS136 1.63E+08 8.84E+06 9.16E+07 2.52E+08 1.34E+08 O.OOE-01 2.00E+07 O.OOE-01 CS137 3.64E+08 1.55E+07 2.58E+09 2.47E+09 8.05E+08 O.OOE-01 2.89E+08 O.OOE-01 BA140 2.48E+04 2.16E+05 4.25E+05 3.74E+02 1.21E+02 O.OOE-01 2.22E+02 O.OOE-01 CE141 5.42E+OO 4.56E+04 7.32E+01 3.64E+01 1.60E+01 O.OOE-01 O.OOE-01 O.OOE-01 CE144 2.60E+02 3.99E+05 4.88E+03 1.53E+03 8.46E+02 O.OOE-01 O.OOE-01 O.OOE-01 I 131 1.39E+07 2.18E+06 2.44E+07 2.45E+07 4.02E+07 8.11E+09 O.OOE-01 O.OOE-01 1133 1.53E+05 1.63E+05 3.26E+05 4.06E+05 6.75E+05 7.51 E+07 O.OOE-01 O.OOE-01 DAEC ODAM Page 152 of 280 Rev. 37 Appendix A DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT AIR Computed by GASPAR II AGE =CHILD PATHWAY= ANIMAL-MEAT TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN {mrem m 2}/Ci H 3 4.28E+OO 4.28E+OO O.OOE-01 4.28E+OO 4.28E+OO 4.28E+OO 4.28E+OO 4.28E+OO c 14 3.39E+03 3.39E+03 1.69E+04 3.39E+03 3.39E+03 3.39E+03 3.39E+03 3.39E+03 AR41 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR83m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR85m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 85 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 87 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR88 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 89 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 90 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE131m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE133m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE133 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE135m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE135 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE137 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE138 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CR 51 2.48E+02 1.32E+04 O.OOE-01 O.OOE-01 3.77E+01 1.38E+02 2.52E+02 O.OOE-01 MN 54 5.39E+04 1.70E+05 O.OOE-01 2.02E+05 5.67E+04 O.OOE-01 O.OOE-01 O.OOE-01 FE 55 1.17E+06 6.99E+05 7.11E+06 3.77E+06 O.OOE-01 O.OOE-01 2.14E+06 O.OOE-01 FE 59 8.24E+06 1.72E+07 1.02E+07 1.65E+07 O.OOE-01 O.OOE-01 4.79E+06 -O.OOE-01 co 58 1.32E+06 2.53E+06 O.OOE-01 4.34E+05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 C060 5.13E+06 9.63E+06 O.OOE-01 1.74E+06 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZN 65 1.77E+07 5.01 E+06 1.07E+07 2.85E+07 1.80E+07 O.OOE-01 O.OOE-01 O.OOE-01 SR 89 3.99E+05 5.42E+05 1.40E+07 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 90 4.09E+07 1.82E+07 2.03E+09 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 95 1.38E+04 1.62E+07 7.07E+04 1.55E+04 2.22E+04 O.OOE-01 O.OOE-01 O.OOE-01 SB124 2.73E+05 4.88E+06 7.80E+05 1.01E+04 O.OOE-01 1.72E+03 4.34E+05 O.OOE-01 CS134 8.05E+06 2.06E+05 2.33E+07 3.80E+07 1.18E+07 O.OOE-01 4.25E+06 O.OOE-01 CS136 8.68E+05 4.72E+04 4.88E+05 1.34E+06 7.13E+05 O.OOE-01 1.06E+05 O.OOE-01 CS137 5.01 E+06 2.13E+05 3.55E+07 3.39E+07 1.11E+07 O.OOE-01 3.99E+06 O.OOE-01 BA140 7.76E+04 6.72E+05 1.33E+06 1.16E+03 3.80E+02 O.OOE-01 6.94E+02 O.OOE-01 CE141 4.60E+01 3.87E+05 6.21E+02 3.09E+02 1.36E+02 O.OOE-01 O.OOE-01 O.OOE-01 CE144 3.10E+03 4.75E+06 5.80E+04 1.82E+04 1.01E+04 O.OOE-01 O.OOE-01 O.OOE-01 I 131 1.47E+05 2.31 E+04 2.58E+05 2.59E+05 4.25E+05 8.56E+07 O.OOE-01 O.OOE-01 1133 4.25E-03 4.53E-03 9.10E-03 1.12E-02 1.88E-02 2.09E+OO O.OOE-01 O.OOE-01 DAEC ODAM Page 153 of 280 Rev. 37 Appendix A DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT AIR Computed by GASPAR II AGE =CHILD PATHWAY= VEGETABLES TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN mrem m 2 /Ci H 3 7.32E+01 7.32E+01 O.OOE-01 7.32E+01 7.32E+01 7.32E+01 7.32E+01 7.32E+01 c 14 2.24E+04 2.24E+04 1.12E+05 2.24E+04 2.24E+04 2.24E+04 2.24E+04 2.24E+04 AR41 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR83m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR85m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 85 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 87 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 88 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 89 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 90 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE131m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE133m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE133 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE135m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE135 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE137 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE138 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CR51 3.68E+03 1.94E+05 O.OOE-01 O.OOE-01 5.55E+02 2.03E+03 3.71 E+03 O.OOE-01 MN 54 5.51 E+06 1.74E+07 O.OOE-01 2.07E+07 5.80E+06 O.OOE-01 O.OOE-01 O.OOE-01 FE 55 1.41E+06 8.45E+05 8.57E+06 4.57E+06 O.OOE-01 O.OOE-01 2.59E+06 O.OOE-01 FE 59 9.95E+06 2.08E+07 1.23E+07 2.00E+07 O.OOE-01 O.OOE-01 5.80E+06 O.OOE-01 C058 6.08E+06 1.16E+07 O.OOE-01 1.99E+06 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 C060 3.52E+07 6.62E+07 O.OOE-01 1.19E+07 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZN 65 5.39E+07 1.52E+07 3.26E+07 8.68E+07 5.45E+07 O.OOE-01 O.OOE-01 0.00E-01 SR 89 3.30E+07 4.47E+07 1.16E+09 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 90 3.39E+09 1.51E+09 1.69E+11 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 95 2.33E+04 2.73E+07 1.19E+05 2.62E+04 3.74E+04 O.OOE-01 O.OOE-01 O.OOE-01 SB124 3.83E+06 6.81 E+07 1.09E+07 1.42E+05 O.OOE-01 2.41E+04 6.05E+06 0.00E-01 CS134 1.75E+08 4.47E+06 5.07E+08 8.30E+08 2.58E+08 O.OOE-01 9.25E+07 O.OOE-01 CS136 4.63E+06 2.50E+05 2.59E+06 7.13E+06 3.80E+06 O.OOE-01 5.67E+05 O.OOE-01 CS137 1.22E+08 5.20E+06 8.65E+08 8.27E+08 2.70E+08 O.OOE-01 9.70E+07 O.OOE-01 BA140 5.10E+05 4.44E+06 8.78E+06 7.67E+03 2.50E+03 O.OOE-01 4.56E+03 O.OOE-01 CE141 1.52E+03 1.27E+07 2.05E+04 1.02E+04 4.47E+03 O.OOE-01 O.OOE-01 O.OOE-01 CE144 2.06E+05 3.16E+08 3.87E+06 1.21E+06 6.69E+05 O.OOE-01 O.OOE-01 O.OOE-01 I 131 1.29E+06 2.03E+05 2.27E+06 2.28E+06 3.74E+06 7.54E+08 O.OOE-01 0.00E-01 1133 2.61 E+04 2.78E+04 5.58E+04 6.91 E+04 1.15E+05 1.28E+07 O.OOE-01 O.OOE-01 DAEC ODAM Page 154 of 280 Rev. 37 Appendix A DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT AIR Computed by GASPAR II AGE =CHILD PATHWAY= PLUME TOTAL BODY GI-LU BONE LIVER KIDNEY THYROID LUNG SKIN {mrem m 3}/{Ci sec} H 3 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 c 14 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 AR41 1.96E+02 1.96E+02 1.96E+02 1.96E+02 1.96E+02 1.96E+02 1.96E+02 3.14E+02 KR83m 1.68E-03 1.68E-03 1.68E-03 1.68E-03 1.68E-03 1.68E-03 9.38E-02 4.75E-01 KR85m 2.60E+01 2.60E+01 2.60E+01 2.60E+01 2.60E+01 2.60E+01 2.66E+01 7.67E+01 KR 85 3.58E-01 3.58E-01 3.58E-01 3.58E-01 3.58E-01 3.58E-01 9.51 E-01 4.28E+01 KR 87 1.32E+02 1.32E+02 1.32E+02 1.32E+02 1.32E+02 1.32E+02 1.35E+02 4.60E+02 KR 88 3.26E+02 3.26E+02 3.26E+02 3.26E+02 3.26E+02 3.26E+02 3.26E+02 4.50E+02 KR 89 3.68E+02 3.68E+02 3.68E+02 3.68E+02 3.68E+02 3.68E+02 3.71 E+02 7.48E+02 KR 90 3.46E+02 3.46E+02 3.46E+02 3.46E+02 3.46E+02 3.46E+02 3.49E+02 6.33E+02 XE131m 2.03E+OO 2.03E+OO 2.03E+OO 2.03E+OO 2.03E+OO 2.03E+OO 2.38E+OO 1.89E+01 XE133m 5.58E+OO 5.58E+OO 5.58E+OO 5.58E+OO 5.58E+OO 5.58E+OO 6.02E+OO 3.96E+01 XE133 6.53E+OO 6.53E+OO 6.53E+OO 6.53E+OO 6.53E+OO 6.53E+OO 6.85E+OO 1.84E+01 XE135m 6.91E+01 6.91E+01 6.91E+01 6.91E+01 6.91E+01 6.91E+01 6.94E+01 1.05E+02 XE135 4.02E+01 4.02E+01 4.02E+01 4.02E+01 4.02E+01 4.02E+01 4.09E+01 1.06E+02 XE137 3.15E+01 3.15E+01 3.15E+01 3.15E+01 3.15E+01 3.15E+01 3.55E+01 4.25E+02 XE138 1.96E+02 1.96E+02 1.96E+02 1.96E+02 1.96E+02 1.96E+02 1.97E+02 3.58E+02 CR 51 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 MN 54 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 FE 55 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 FE 59 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 co 58 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 C060 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZN 65 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 89 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 90 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 95 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SB124 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CS134 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CS136 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CS137 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BA140 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CE141 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CE144 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 I 131 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 1133 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 DAEC ODAM Page 155 of 280 Rev. 37 Appendix A DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT AIR Computed by GASPAR II AGE =INFANT PATHWAY= INHALATION TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN {mrem m 3}/{Ci sec} H 3 1.17E+01 1.17E+01 O.OOE-01 1.17E+01 1.17E+01 1.17E+01 1.17E+01 1.17E+01 c 14 1.68E+02 1.68E+02 8.39E+02 1.68E+02 1.68E+02 1.68E+02 1.68E+02 O.OOE-01 AR41 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR83m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 85m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 85 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 87 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 88 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 89 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 90 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE131m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE133m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE133 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE135m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE135 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE137 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE138 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CR 51 2.84E+OO 1.13E+01 O.OOE-01 O.OOE-01 4.18E-01 1.83E+OO 4.06E+02 O.OOE-01 MN 54 1.58E+02 2.24E+02 O.OOE-01 8.05E+02 1.58E+02 O.OOE-01 3.17E+04 O.OOE-01 FE 55 1.05E+02 3.47E+01 6.27E+02 3.72E+02 O.OOE-01 O.OOE-01 2.77E+03 O.OOE-01 FE 59 3.00E+02 7.86E+02 4.31E+02 7.45E+02 O.OOE-01 O.OOE-01 3.23E+04 O.OOE-01 C058 5.77E+01 3.52E+02 O.OOE-01 3.87E+01 O.OOE-01 O.OOE-01 2.46E+04 O.OOE-01 co 60 3.74E+02 1.01E+03 O.OOE-01 2.54E+02 O.OOE-01 O.OOE-01 1.43E+05 O.OOE-01 ZN 65 9.86E+02 1.63E+03 6.12E+02 1.98E+03 1.03E+03 O.OOE-01 2.05E+04 O.OOE-01 SR 89 3.61 E+02 2.03E+03 1.26E+04 O.OOE-01 O.OOE-01 O.OOE-01 6.43E+04 O.OOE-01 SR 90 9.89E+03 4.15E+03 4.91E+05 O.OOE-01 O.OOE-01 O.OOE-01 3.55E+05 O.OOE-01 ZR 95 6.43E+02 6.88E+02 3.64E+03 8.84E+02 9.86E+02 O.OOE-01 5.55E+04 O.OOE-01 SB124 3.80E+02 1.87E+03 1.20E+03 1.76E+01 O.OOE-01 3.20E+OO 8.40E+04 O.OOE-01 CS134 2.36E+03 4.21 E+01 1.25E+04 2.23E+04 6.02E+03 O.OOE-01 2.53E+03 O.OOE-01 CS136 1.68E+03 4.53E+01 1.53E+03 4.28E+03 1.79E+03 O.OOE-01 3.74E+02 O.OOE-01 CS137 1.44E+03 4.21 E+01 1.74E+04 1.94E+04 5.45E+03 O.OOE-01 2.26E+03 O.OOE-01 BA140 9.19E+01 1.22E+03 1.77E+03 1.77E+OO 4.25E-01 O.OOE-01 5.07E+04 O.OOE-01 CE141 6.31E+01 6.85E+02 8.78E+02 5.29E+02 1.66E+02 O.OOE-01 1.64E+04 O.OOE-01 CE144 5.58E+03 4.69E+03 1.01E+05 3.83E+04 1.70E+04 O.OOE-01 3.12E+05 O.OOE-01 I 131 6.21E+02 3.36E+01 1.20E+03 1.41E+03 1.64E+03 4.69E+05 O.OOE-01 O.OOE-01 1133 1.77E+02 6.85E+01 4.18E+02 6.08E+02 7.10E+02 1.13E+05 O.OOE-01 O.OOE-01 DAEC ODAM Page 156 of 280 Rev. 37 Appendix A DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT AIR Computed by GASPAR II AGE =INFANT PATHWAY= GROUND PLANE TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN {mrem m 2}/Ci H 3 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 c 14 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 AR41 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 83m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR85m 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 85 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 87 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 88 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 89 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 90 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE131m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE133m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE133 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE135m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE135 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE137 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 XE138 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CR 51 1.47E+05 1.47E+05 1.47E+05 1.47E+05 1.47E+05 1.47E+05 1.47E+05 1.74E+05 MN 54 4.37E+07 4.37E+07 4.37E+07 4.37E+07 4.37E+07 4.37E+07 4.37E+07 5.13E+07 FE 55 9.79E+05 3.84E+05 3.90E+06 1.44E+06 O.OOE-01 O.OOE-01 2.39E+06 O.OOE-01 FE 59 8.65E+06 8.65E+06 8.65E+06 8.65E+06 8.65E+06 8.65E+06 8.65E+06 1.01E+07 co 58 1.20E+07 1.20E+07 1.20E+07 1.20E+07 1.20E+07 1.20E+07 1.20E+07 1.41E+07 C060 6.81E+08 6.81 E+08 6.81E+08 6.81 E+08 6.81 E+08 6.81 E+08 6.81 E+08 8.02E+08 ZN 65 2.36E+07 2.36E+07 2.36E+07 2.36E+07 2.36E+07 2.36E+07 2.36E+07 2.72E+07 SR 89 6.85E+02 6.85E+02 6.85E+02 6.85E+02 6.85E+02 6.85E+02 6.85E+02 7.95E+02 SR 90 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 95 7.76E+06 7.76E+06 7.76E+06 7.76E+06 7.76E+06 7.76E+06 7.76E+06 9.03E+06 SB124 1.90E+07 1.90E+07 1.90E+07 1.90E+07 1.90E+07 1.90E+07 1.90E+07 2.19E+07 CS134 2.17E+08 2.17E+08 2.17E+08 2.17E+08 2.17E+08 2.17E+08 2.17E+08 2.53E+08 CS136 4.75E+06 4.75E+06 4.75E+06 4.75E+06 4.75E+06 4.75E+06 4.75E+06 5.39E+06 CS137 3.26E+08 3.26E+08 3.26E+08 3.26E+08 3.26E+08 3.26E+08 3.26E+08 3.80E+08 BA140 6.50E+05 6.50E+05 6.50E+05 6.50E+05 6.50E+05 6.50E+05 6.50E+05 7.45E+05 CE141 4.34E+05 4.34E+05 4.34E+05 4.34E+05 4.34E+05 4.34E+05 4.34E+05 4.88E+05 CE144 2.21 E+06 2.21E+06 2.21E+06 2.21E+06 2.21E+06 2.21 E+06 2.21 E+06 2.55E+06 I 131 2.73E+05 2.73E+05 2.73E+05 2.73E+05 2.73E+05 2.73E+05 2.73E+05 3.33E+05 1133 3.90E+04 3.90E+04 3.90E+04 3.90E+04 3.90E+04 3.90E+04 3.90E+04 4.72E+04 DAEC ODAM Page 157 of 280 Rev. 37 Appendix A DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT AIR Computed by GASPAR II AGE =INFANT PATHWAY= COW-MILK TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN {mrem m 2}/Ci H 3 4.34E+01 4.34E+01 O.OOE-01 4.34E+01 4.34E+01 4.34E+01 4.34E+01 4.34E+01 c 14 2.21 E+04 2.21E+04 1.03E+05 2.21E+04 2.21E+04 2.21E+04 2.21 E+04 2.21E+04 AR41 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 83m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR85m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 85 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 87 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 88 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 89 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 90 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE131m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE133m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE133 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE135m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE135 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE137 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE138 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CR 51 4.56E+03 1.33E+05 O.OOE-01 O.OOE-01 6.50E+02 2.98E+03 5.80E+03 O.OOE-01 MN 54 2.23E+05 3.61 E+05 O.OOE-01 9.86E+05 2.19E+05 O.OOE-01 O.OOE-01 O.OOE-01 FE 55 4.73E+05 2.26E+05 2.74E+06 1.77E+06 O.OOE-01 O.OOE-01 8.70E+05 O.OOE-01 FE 59 4.18E+06 5.10E+06 6.08E+06 1.06E+07 O.OOE-01 O.OOE-01 3.15E+06 O.OOE-01 C058 1.60E+06 1.59E+06 O.OOE-01 6.40E+05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 C060 5.23E+06 5.26E+06 O.OOE-01 2.21E+06 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZN 65 2.50E+08 4.60E+08 1.58E+08 5.42E+08 2.63E+08 O.OOE-01 O.OOE-01 O.OOE-01 SR 89 1.05E+07 7.51 E+06 3.64E+08 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 90 4.88E+08 1.97E+08 2.41E+10 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 95 3.12E+01 2.19E+04 1.80E+02 4.40E+01 4.75E+01 O.OOE-01 O.OOE-01 O.OOE-01 SB124 1.73E+06 1.72E+07 5.58E+06 8.21 E+04 O.OOE-01 1.48E+04 3.49E+06 O.OOE-01 CS134 1.73E+08 4.66E+06 9.19E+08 1.71E+09 4.40E+08 O.OOE-01 1.81E+08 O.OOE-01 CS136 6.56E+07 2.66E+06 5.96E+07 1.75E+08 7.00E+07 O.OOE-01 1.43E+07 O.OOE-01 CS137 1.14E+08 5.01E+06 1.37E+09 1.61E+09 4.31 E+08 O.OOE-01 1.75E+08 O.OOE-01 BA140 3.77E+05 1.79E+06 7.29E+06 7.29E+03 1.73E+03 O.OOE-01 4.50E+03 O.OOE-01 CE141 8.68E+01 3.80E+05 1.21E+03 7.38E+02 2.28E+02 O.OOE-01 O.OOE-01 O.OOE-01 CE144 3.26E+03 3.33E+06 5.83E+04 2.38E+04 9.63E+03 O.OOE-01 O.OOE-01 O.OOE-01 I 131 2.20E+07 1.78E+06 4.25E+07 5.01 E+07 5.83E+07 1.64E+10 O.OOE-01 O.OOE-01 1133 2.46E+05 1.42E+05 5.77E+05 8.40E+05 9.86E+05 1.52E+08 O.OOE-01 O.OOE-01 DAEC ODAM Page 158 of 280 Rev.37 Appendix A DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT AIR Computed by GASPAR II AGE =INFANT PATHWAY= GOAT-MILK TOTAL BODY GI-LU BONE LIVER KIDNEY THYROID LUNG SKIN {mrem m 2}/Ci H 3 8.87E+01 8.87E+01 O.OOE-01 8.87E+01 8.87E+01 8.87E+01 8.87E+01 8.87E+01 c 14 2.21 E+04 2.21 E+04 1.03E+05 2.21E+04 2.21E+04 2.21 E+04 2.21E+04 2.21E+04 AR41 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR83m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR85m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 85 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 87 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 88 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 89 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 90 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE131m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 XE133m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE133 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE135m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE135 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE137 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE138 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CR 51 5.48E+02 1.60E+04 O.OOE-01 O.OOE-01 7.80E+01 3.58E+02 6.94E+02 O.OOE-01 MN 54 2.68E+04 4.34E+04 O.OOE-01 1.19E+05 2.62E+04 O.OOE-01 O.OOE-01 O.OOE-01 FE 55 6.17E+04 2.94E+04 3.57E+05 2.30E+05 O.OOE-01 O.OOE-01 1.13E+05 O.OOE-01 FE 59 5.45E+05 6.62E+05 7.92E+05 1.38E+06 O.OOE-01 O.OOE-01 4.09E+05 O.OOE-01 co 58 1.91E+05 1.91E+05 O.OOE-01 7.67E+04 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 C060 6.27E+05 6.31 E+05 O.OOE-01 2.66E+05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZN 65 3.00E+07 5.51 E+07 1.90E+07 6.53E+07 3.16E+07 O.OOE-01 0.00E-01 O.OOE-01 SR 89 2.20E+07 1.58E+07 7.67E+08 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 90 1.03E+09 4.15E+08 5.07E+10 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 95 3.74E+OO 2.63E+03 2.16E+01 5.29E+OO 5.67E+OO O.OOE-01 O.OOE-01 O.OOE-01 SB124 2.08E+05 2.07E+06 6.69E+05 9.86E+03 O.OOE-01 1.78E+03 4.18E+05 O.OOE-01 CS134 5.20E+08 1.40E+07 2.76E+09 5.13E+09 1.32E+09 O.OOE-01 5.42E+08 O.OOE-01 CS136 1.96E+08 7.99E+06 1.79E+08 5.26E+08 2.10E+08 O.OOE-01 4.28E+07 O.OOE-01 CS137 3.42E+08 1.51 E+07 4.12E+09 4.82E+09 1.29E+09 O.OOE-01 5.23E+08 O.OOE-01 BA140 4.50E+04 2.15E+05 8.78E+05 8.78E+02 2.08E+02 O.OOE-01 5.39E+02 O.OOE-01 CE141 1.04E+01 4.56E+04 1.45E+02 8.87E+01 2.73E+01 O.OOE-01 O.OOE-01 O.OOE-01 CE144 3.93E+02 4.02E+05 7.00E+03 2.86E+03 1.16E+03 O.OOE-01 O.OOE-01 O.OOE-01 I 131 2.63E+07 2.14E+06 5.07E+07 5.99E+07 7.00E+07 1.97E+10 O.OOE-01 O.OOE-01 1133 2.95E+05 1.70E+05 6.91E+05 1.01E+06 1.18E+06 1.83E+08 O.OOE-01 O.OOE-01 DAEC ODAM Page 159 of 280 Rev. 37 Appendix A DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT AIR Computed by GASPAR II AGE =INFANT PATHWAY= ANIMAL-MEAT TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN {mrem m 2}/Ci H 3 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 c 14 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 AR41 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR83m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR85m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 85 0.00E-01 O.OOE-01 O.OOE-01 0.00E-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 87 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 88 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 89 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 90 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE131m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE133m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE133 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE135m O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE135 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE137 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE138 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CR 51 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 MN 54 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 FE 55 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 FE 59 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 co 58 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 C060 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZN 65 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 0.00E-01 SR 89 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 90 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 95 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SB124 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CS134 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CS136 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CS137 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BA140 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CE141 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CE144 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 I 131 0.00E-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 1133 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 DAEC ODAM Page 160 of 280 Rev.37 Appendix A DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT AIR Computed by GASPAR II AGE =INFANT PATHWAY= VEGETABLES TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN {mrem m 2}/Ci H 3 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 c 14 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 AR41 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR83m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR85m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 85 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 KR 87 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 88 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 89 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR 90 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE131m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE133m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE133 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE135m O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE135 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE137 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE138 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CR 51 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 MN 54 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 FE 55 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 FE 59 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 co 58 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 C060 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZN 65 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 89 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 90 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 95 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SB124 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CS134 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CS136 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CS137 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BA140 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CE141 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CE144 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 I 131 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 1133 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 DAEC ODAM Page 161 of 280 Rev. 37 Appendix A DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT AIR Computed by GASPAR II AGE =INFANT PATHWAY= PLUME TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN {mrem m 3}/{Ci sec} H 3 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 c 14 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 AR41 1.96E+02 1.96E+02 1.96E+02 1.96E+02 1.96E+02 1.96E+02 1.96E+02 3.14E+02 KR83m 1.68E-03 1.68E-03 1.68E-03 1.68E-03 1.68E-03 1.68E-03 9.38E-02 4.75E-01 KR85m 2.60E+01 2.60E+01 2.60E+01 2.60E+01 2.60E+01 2.60E+01 2.66E+01 7.67E+01 KR 85 3.58E-01 3.58E-01 3.58E-01 3.58E-01 3.58E-01 3.58E-01 9.51 E-01 4.28E+01 KR 87 1.32E+02 1.32E+02 1.32E+02 1.32E+02 1.32E+02 1.32E+02 1.35E+02 4.60E+02 KR 88 3.26E+02 3.26E+02 3.26E+02 3.26E+02 3.26E+02 3.26E+02 3.26E+02 4.50E+02 KR 89 3.68E+02 3.68E+02 3.68E+02 3.68E+02 3.68E+02 3.68E+02 3.71 E+02 7.48E+02 KR 90 3.46E+02 3.46E+02 3.46E+02 3.46E+02 3.46E+02 3.46E+02 3.49E+02 6.33E+02 XE131m 2.03E+OO 2.03E+OO 2.03E+OO 2.03E+OO 2.03E+OO 2.03E+OO 2.38E+OO 1.89E+01 XE133m 5.58E+OO 5.58E+OO 5.58E+OO 5.58E+OO 5.58E+OO 5.58E+OO 6.02E+OO 3.96E+01 XE133 6.53E+OO 6.53E+OO 6.53E+OO 6.53E+OO 6.53E+OO 6.53E+OO 6.85E+OO 1.84E+01 XE135m 6.91E+01 6.91 E+01 6.91E+01 6.91E+01 6.91E+01 6.91E+01 6.94E+01 1.05E+02 XE135 4.02E+01 4.02E+01 4.02E+01 4.02E+01 4.02E+01 4.02E+01 4.09E+01 1.06E+02 XE137 3.15E+01 3.15E+01 3.15E+01 3.15E+01 3.15E+01 3.15E+01 3.55E+01 4.25E+02 XE138 1.96E+02 1.96E+02 1.96E+02 1.96E+02 1.96E+02 1.96E+02 1.97E+02 3.58E+02 CR 51 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 MN 54 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 FE 55 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 FE 59 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 C058 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 C060 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 ZN 65 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 89 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 90 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 95 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SB124 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CS134 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CS136 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CS137 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BA140 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CE141 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CE144 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 I 131 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 I 133 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 DAEC ODAM Page 162 of 280 Rev.37 Appendix B APPENDIX B: TECHNICAL BASES FOR EFFECTIVE DOSE FACTORS Overview The evaluation of doses due to releases of radioactive material to the atmosphere can be simplified by the use of effective dose transfer factors instead of using dose factors which are radionuclide specific.

These effective factors, which are based on the total radioactivity released to approximate the dose in the environment, i.e., instead of having to sum the isotopic distribution multiplied by the isotope specific dose factor only a single multiplication times the total quantity of radioactive material released would be needed. This approach provides a reasonable estimate of the actual dose while eliminating the need for a detailed calculational technique.

Determination of Effective Dose Factors The effective dose transfer factors are based on past operating data. The radioactive effluent distribution for the past years can be used to derive single effective factors by the following equations:

where Arseff = f = i where Ay -v e.ff -Arv;= DAEC ODAM A Yse.ff the effective gamma-air dose factor due to stack releases of noble gases (mrad/µCi) the gamma-air dose factor due to stack releases of each noble gas radionuclide i (mrad/µCi) the fraction of noble gas radioactivity constituted by radionuclide i A Yvejf the effective gamma-air dose factor due to vent releases of all noble gases ( mrad ) µCi sec/ m 3 the gamma-air dose factor due to vent releases of each noble gas ( mrad ) radionuclide i . 3 µCi sec/ m A f3v e.ff Page 163 of 280 Rev. 37 Appendix B where A/Jeff = the effective beta-air dose factor due to either vent or stack releases of all noble gases ( mrad ) µCi sec/ m 3 the beta air dose factor due to either vent or stack releases of each noble gas . . . ( mrad ) radionuclide

/ . 3 µCi sec/ m To determine the appropriate effective factors to be used and to evaluate the degree of variability, the atmospheric radioactive effluents for the past 3 years have been evaluated.

Table B-1 presents the radionuclide distribution for stack and vent releases as measured by isotopic analysis of periodic grab samples from the respective effluent release points. Table B-2 presents the effective dose factors (gamma-air and beta-air) derived on the basis of the radionuclide distribution.

Except for the year 1981, the variability of the effective factors is minor. For 1981, Xe-138 contributes significantly to the derivation of the effective factors for stack releases.

The Xe-138 contribution for the years 1979 and 1980 is not so significant.

This increase in Xe-138 from 1981 results in a larger variability of the yearly values from the average than what is considered typical. Therefore, in order to assure adequate conservatism, the effective dose factors for stack releases will be based on the radionuclide distribution for the year 1981. Because this is considered an atypical distribution resulting in higher doses, use of the data will provide dose estimates which are conservative.

As more data become available to further establish a typical radionuclide distribution, the effective dose factors for stack releases may be reevaluated.

To provide an additional degree of conservatism, a factor of 0.8 is introduced into the dose calculational process when the effective dose transfer factor is used. This added conservatism provides additional assurance that the evaluation of doses by the use of a single effective factor will not significantly underestimate any actual doses in the environment.

By evaluating doses using these effective dose factors, maximum allowable releases of noble gases for any calendar quarter may be determined.

As discussed in Section 3.6.1, the maximum allowable releases based on the gamma-air effective dose factor have been determined to be 250,000 Ci/quarter for stack releases and 12,700 Ci/quarter for vent releases.

For the beta air effective dose factors, the releases of noble gases corresponding to the quarterly limit of 10 mrads corresponds to 307,000 Ci/quarter for stack releases and 29,600 Ci/quarter for vent releases.

Comparing these values for allowable releases with the values based on the gamma-air effective dose factors, it is demonstrated that the gamma-air doses are more restrictive than the air doses. In other words, the doses calculated by using the gamma-air effective dose factors represent a larger fraction of the allowable dose than does the dose calculated by using the beta-air effective dose factors. Therefore, when using the effective dose factors for evaluating compliance with the quarterly dose limits of Section 6.2.3, only the gamma-air dose need be evaluated; compliance with the gamma-air dose limit represents a de facto compliance with the beta-air dose limit. DAECODAM Page 164 of 280 Rev.37 Appendix B Reevaluation The doses due to the gaseous effluents are evaluated by the more detailed calculational methods (i.e., use of nuclide specific dose factors) on a yearly basis. At that time, a comparison can be made between the simplified method and the detailed method to assure the overall reasonableness of this limited analysis approach.

If the comparison indicates that the radionuclide distribution has changed significantly, thereby causing the simplified method to underestimate the doses, the value of the effective factors will need to be reexamined to assure the overall acceptability of this approach.

However, this reexamination will only be needed if the doses as calculated by the detailed analysis exceed 50% of the design bases doses (i.e., greater than 50% of the 10 mrad gamma air dose or 20 mrad beta air dose). DAECODAM Page 165 of 280 Rev. 37 Appendix B Table B-1 RADIONUCLIDE DISTRIBUTION OF STACK AND VENT RELEASES Radionuclide Fraction of Total Releases Stack Vent 1979 1980 1981 1979 1980 1981 Kr-85m .11 .05 .09 .02 ------Kr-87 .01 ---.02 ---.01 ---Kr-88 .07 .04 .08 ---------Xe-133 .76 .82 .45 .24 .24 .14 Xe-135 .01 .02 .03 .72 .50 .59 Xe-135m ---.02 .08 .02 .22 .21 Xe-138 .02 .06 .25 ---.03 .05 Table B-2 EFFECTIVE DOSE FACTORS NOBLE GASES -AIR DOSES Year Stack Releases Vent Releases Gamma-Air Beta-Air Gamma-Air Beta-Air Effective Dose Effective Dose Effective Dose Effective Dose Factor Factor Factor Factor Arseff AfJseff Arveff AfJveff ( ( mrad ) ( mrad ) µCi sec/ m 3 ( mrad ) µCz µCi sec/ m 3 µCi sec/ m 3 1979 7.0x10-12 5.9x10-5 5.0x10-5 6.5x10-5 1980 6.7x10-12 5.3x10-5 6.7x10-5 6.0x10-5 1981 1.6x10-11 9.3x10-12 6.4x10-5 6.3x10-5 Average 9.9x10-12 6.8x10-5 6.4x10-5 6.3x10-5 DAECODAM Page 166 of 280 Rev. 37 Appendix C APPENDIX C: DOSE TRANSFER FACTORS FOR WATERBORNE PATHWAYS Dose transfer factors for waterborne effluent have been derived by solving environmental pathway models on the bases of unit radionuclide release in effluent (1 Ci/yr) discharged in 1 gallon/minute of water. The dose transfer factors in this appendix were computed with the LADT AP II computer program, using default values of parameters applicable to the most exposed members of the public as recommended in Regulatory 1.109, revision 1, with the following exceptions:

In order to account for significant revisions of data since publication of the Regulatory Guide, data differing from those in Regulatory Guide 1.109, revision 1 are identified in LADTAP II documentation.

14 After publishing Reg. Guide 1.109, the NRC recommended that soil-to-plant bioaccumulation factors, Biv. of cesium and strontium be changed.15 The revised values were used to derive dose transfer factors tabulated for Sr89, Sr90, and Cs137 in irrigated vegetation.

Values of environmental transit time recommended in Reg. Guide 1.109 16 , namely 1440 hr from harvest of stored vegetables to ingestion, were retained.

LADT AP II divergence from Reg. Guide 1.109 is reflected in tritium dose transfer factors that are typically 43% lower than those described in the Reg. Guide. Dose transfer factors are included hereafter for the following parameters.

Only those pathways applicable at the time of a radioactive liquid effluent release will be used for dose calculations.

Likely pathways would include potable water, freshwater fish and irrigated fresh leafy vegetables (including strawberries).

14 15 16 Strenge, D.L., et. al., LADTAP II -Technical Reference and User guide, NUREG/CR-4013, April 1986. NRC, SECY-79-653A, January 30, 1980. Regulatory Guide 1.109, rev. 1, Table E-15. DAECODAM Page 167 of 280 Rev. 37 A d. C ppen IX Pathway Age Group Organ Potable water Adult Total Body Freshwater fish Teenager GI tract Freshwater invertebrates Child Bone Irrigated fresh leafy vegetables Infant Liver Irrigated stored vegetables, fruit, and grain Kidney Irrigated grass-cow-milk Thyroid Irrigated grass-cow-meat Lung Irrigated stored forage-cow-milk Skin Irrigated stored forage-cow-meat Animal drinks river water-milk Animal drinks river water-meat River shoreline deposits-irradiation Swimming Boating DAEC ODAM Page 168 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =ADULT PATHWAY= POTABLE WATER TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN (mrem gal}/(Ci min} H 3 2.19E+01 2.19E+01 O.OOE-01 2.19E+01 2.19E+01 2.19E+01 2.19E+01 O.OOE-01 c 14 2.08E+02 2.08E+02 1.04E+03 2.08E+02 2.08E+02 2.08E+02 2.08E+02 O.OOE-01 NA24 2.06E+02 2.06E+02 2.06E+02 2.06E+02 2.06E+02 2.06E+02 2.06E+02 0.00E-01 p 32 2.60E+03 7.57E+03 6.73E+04 4.19E+03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CR 51 9.50E-01 2.39E+02 O.OOE-01 O.OOE-01 2.09E-01 5.68E-01 1.26E+OO O.OOE-01 MN 54 3.19E+02 5.12E+03 O.OOE-01 1.67E+03 4.97E+02 O.OOE-01 O.OOE-01 O.OOE-01 MN 56 1.15E-02 2.06E+OO O.OOE-01 6.46E-02 8.20E-02 O.OOE-01 O.OOE-01 O.OOE-01 FE 55 1.62E+02 3.99E+02 1.01 E+03 6.95E+02 O.OOE-01 O.OOE-01 3.88E+02 O.OOE-01 FE 59 1.41E+03 1.23E+04 1.56E+03 3.68E+03 O.OOE-01 O.OOE-01 1.03E+03 O.OOE-01 C058 6.06E+02 5.48E+03 O.OOE-01 2.70E+02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 C060 1.73E+03 1.47E+04 O.OOE-01 7.84E+02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl63 1.60E+03 6.89E+02 4.76E+04 3.30E+03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl65 1.56E-02 8.66E-01 2.63E-01 3.42E-02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 cu 64 3.85E+OO 6.99E+02 O.OOE-01 8.21 E+OO 2.07E+01 O.OOE-01 O.OOE-01 O.OOE-01 ZN 65 2.54E+03 3.54E+03 1.77E+03 5.62E+03 3.76E+03 O.OOE-01 O.OOE-01 O.OOE-01 ZN 69 1.21 E-08 2.62E-08 9.11E-08 1.74E-07 1.13E-07 O.OOE-01 O.OOE-01 O.OOE-01 BR 83 1.40E-02 2.02E-02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 84 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 85 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 86 3.47E+03 1.47E+03 O.OOE-01 7.45E+03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 88 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 89 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 89 3.19E+03 1.78E+04 1.11E+05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 90 6.41E+04 8.02E+04 3.19E+06 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 91 1.45E+01 1.71E+03 3.59E+02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 92 7.38E-02 3.38E+01 1.71E+OO O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 90 7.29E-02 2.88E+04 2.72E+OO O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Y91M O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 91 1.37E+OO 2.81 E+04 5.10E+01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 92 8.37E-05 5.02E+01 2.86E-03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 93 5.20E-03 5.98E+03 1.89E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 95 2.39E+OO 1.12E+04 1.10E+01 3.53E+OO 5.54E+OO O.OOE-01 O.OOE-01 O.OOE-01 ZR 97 2.12E-02 1.44E+04 2.30E-01 4.64E-02 7.00E-02 O.OOE-01 O.OOE-01 O.OOE-01 NB 95 6.68E-01 7.54E+03 2.23E+OO 1.24E+OO 1.23E+OO O.OOE-01 O.OOE-01 O.OOE-01 M099 2.33E+02 2.84E+03 O.OOE-01 1.23E+03 2.78E+03 O.OOE-01 O.OOE-01 O.OOE-01 TC 99M 2.05E-01 9.53E+OO 5.70E-03 1.61E-02 2.45E-01 O.OOE-01 7.89E-03 O.OOE-01 TC101 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 DAEC ODAM Page 169 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =ADULT PATHWAY= POTABLE WATER TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN (mrem gal)/(Ci min) RU103 2.87E+01 7.77E+03 6.66E+01 O.OOE-01 2.54E+02 O.OOE-01 O.OOE-01 O.OOE-01 RU105 5.24E-02 8.12E+01 1.33E-01 O.OOE-01 1.72E+OO O.OOE-01 O.OOE-01 O.OOE-01 RU106 1.27E+02 6.51E+04 1.00E+03 O.OOE-01 1.94E+03 O.OOE-01 O.OOE-01 O.OOE-01 AG110M 3.21E+01 2.21 E+04 5.85E+01 5.41E+01 1.06E+02 O.OOE-01 O.OOE-01 O.OOE-01 TE125M 1.30E+02 3.87E+03 9.70E+02 3.51 E+02 3.94E+03 2.92E+02 O.OOE-01 O.OOE-01 TE127M 3.00E+02 8.26E+03 2.46E+03 8.81E+02 1.00E+04 6.30E+02 O.OOE-01 O.OOE-01 TE127 1.47E+OO 5.36E+02 6.80E+OO 2.44E+OO 2.77E+01 5.03E+OO O.OOE-01 O.OOE-01 TE129M 6.53E+02 2.08E+04 4.13E+03 1.54E+03 1.72E+04 1.42E+03 O.OOE-01 O.OOE-01 TE129 1.66E-06 5.13E-06 6.79E-06 2.55E-06 2.85E-05 5.21E-06 O.OOE-01 O.OOE-01 TE131M 1.48E+02 1.77E+04 3.64E+02 1.78E+02 1.80E+03 2.82E+02 O.OOE-01 O.OOE-01 TE131 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE132 4.53E+02 2.28E+04 7.46E+02 4.83E+02 4.65E+03 5.33E+02 O.OOE-01 O.OOE-01 1130 8.37E+01 1.83E+02 7.19E+01 2.12E+02 3.31 E+02 1.80E+04 O.OOE-01 O.OOE-01 I 131 1.15E+03 5.28E+02 1.40E+03 2.00E+03 3.43E+03 6.55E+05 O.OOE-01 O.OOE-01 1132 5.03E-02 2.?0E-02 5.38E-02 1.44E-01 2.29E-01 5.03E+OO O.OOE-01 O.OOE-01 1133 1.24E+02 3.66E+02 2.34E+02 4.07E+02 7.10E+02 5.98E+04 O.OOE-01 O.OOE-01 I 134 2.10E-07 5.11E-10 2.16E-07 5.86E-07 9.32E-07 1.02E-05 O.OOE-01 O.OOE-01 1135 1.26E+01 3.85E+01 1.30E+01 3.41 E+01 5.47E+01 2.25E+03 O.OOE-01 O.OOE-01 CS134 4.43E+04 9.48E+02 2.28E+04 5.42E+04 1.75E+04 O.OOE-01 5.82E+03 O.OOE-01 CS136 6.43E+03 1.01E+03 2.26E+03 8.93E+03 4.97E+03 O.OOE-01 6.81 E+02 O.OOE-01 CS137 2.61 E+04 7.73E+02 2.92E+04 3.99E+04 1.35E+04 O.OOE-01 4.50E+03 O.OOE-01 CS138 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BA139 5.81E-06 3.52E-04 1.98E-04 1.41 E-07 1.32E-07 O.OOE-01 8.02E-08 O.OOE-01 BA140 4.61 E+02 1.45E+04 7.04E+03 8.85E+OO 3.01 E+OO O.OOE-01 5.0?E+OO O.OOE-01 BA141 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BA142 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 LA140 8.0?E-02 2.24E+04 6.06E-01 3.05E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 LA142 1.08E-07 3.18E-03 9.57E-07 4.35E-07 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CE141 2.57E-01 8.68E+03 3.36E+OO 2.27E+OO 1.05E+OO O.OOE-01 O.OOE-01 O.OOE-01 CE143 2.99E-02 1.01E+04 3.66E-01 2.70E+02 1.19E-01 O.OOE-01 O.OOE-01 O.OOE-01 CE144 9.57E+OO 6.03E+04 1.78E+02 7.46E+01 4.42E+01 O.OOE-01 O.OOE-01 O.OOE-01 PR143 1.59E-01 1.40E+04 3.20E+OO 1.28E+OO 7.42E-01 O.OOE-01 O.OOE-01 O.OOE-01 PR144 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ND147 1.50E-01 1.20E+04 2.16E+OO 2.50E+OO 1.46E+OO O.OOE-01 O.OOE-01 O.OOE-01 W187 5.50E+OO 5.15E+03 1.88E+01 1.57E+01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 NP239 1.76E-02 6.55E+03 3.25E-01 3.20E-02 9.97E-02 O.OOE-01 O.OOE-01 O.OOE-01 DAEC ODAM Page 170 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =ADULT PATHWAY= FRESH WATER FISH TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN {mrem gaQ/{Ci min) H 3 5.68E-01 5.68E-01 O.OOE-01 5.68E-01 5.68E-01 5.68E-01 5.68E-01 O.OOE-01 c 14 2.75E+04 2.75E+04 1.38E+05 2.75E+04 2.75E+04 2.75E+04 2.75E+04 O.OOE-01 NA24 5.90E+02 5.90E+02 5.90E+02 5.90E+02 5.90E+02 5.90E+02 5.90E+02 O.OOE-01 p 32 7.49E+06 2.18E+07 1.94E+08 1.20E+07 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CR 51 5.47E+OO 1.37E+03 O.OOE-01 O.OOE-01 1.20E+OO 3.27E+OO 7.26E+OO O.OOE-01 MN 54 3.67E+03 5.89E+04 O.OOE-01 1.92E+04 5.72E+03 O.OOE-01 O.OOE-01 O.OOE-01 MN 56 1.28E-01 2.31E+01 O.OOE-01 7.24E-01 9.19E-01 O.OOE-01 O.OOE-01 O.OOE-01 FE 55 4.66E+02 1.15E+03 2.90E+03 2.00E+03 O.OOE-01 O.OOE-01 1.12E+03 O.OOE-01 FE 59 4.06E+03 3.53E+04 4.50E+03 1.06E+04 O.OOE-01 O.OOE-01 2.96E+03 O.OOE-01 C058 8.71E+02 7.88E+03 O.OOE-01 3.89E+02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 C060 2.49E+03 2.12E+04 O.OOE-01 1.13E+03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl63 4.59E+03 1.98E+03 1.37E+05 9.49E+03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl65 4.36E-02 2.42E+OO 7.36E-01 9.56E-02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 cu 64 5.51 E+OO 1.00E+03 O.OOE-01 1.17E+01 2.96E+01 O.OOE-01 O.OOE-01 O.OOE-01 ZN 65 1.46E+05 2.04E+05 1.02E+05 3.24E+05 2.16E+05 O.OOE-01 O.OOE-01 O.OOE-01 ZN 69 6.48E-07 1.40E-06 4.87E-06 9.32E-06 6.05E-06 O.OOE-01 O.OOE-01 O.OOE-01 BR 83 1.65E-01 2.37E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 84 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 85 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 86 2.00E+05 8.45E+04 O.OOE-01 4.28E+05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 88 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 89 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 89 2.76E+03 1.54E+04 9.60E+04 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 90 5.53E+04 6.92E+04 2.75E+06 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 91 1.24E+01 1.47E+03 3.08E+02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 92 6.21E-02 2.85E+01 1.44E+OO O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 90 5.24E-02 2.07E+04 1.95E+OO O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Y 91M O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 91 9.81 E-01 2.02E+04 3.67E+01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 92 5.90E-05 3.54E+01 2.02E-03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 93 3.72E-03 4.27E+03 1.35E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 95 2.27E-01 1.06E+03 1.05E+OO 3.35E-01 5.26E-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 97 2.00E-03 1.36E+03 2.17E-02 4.38E-03 6.62E-03 O.OOE-01 O.OOE-01 O.OOE-01 NB 95 5.76E+02 6.51 E+06 1.93E+03 1.07E+03 1.06E+03 O.OOE-01 O.OOE-01 O.OOE-01 M099 6.71E+01 8.17E+02 O.OOE-01 3.52E+02 7.98E+02 O.OOE-01 O.OOE-01 O.OOE-01 TC 99M 8.75E-02 4.07E+OO 2.43E-03 6.87E-03 1.04E-01 O.OOE-01 3.37E-03 O.OOE-01 TC101 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 DAEC ODAM Page 171 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =ADULT PATHWAY= FRESH WATER FISH TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN {mrem gall/{Ci minl RU103 8.25E+OO 2.24E+03 1.91E+01 O.OOE-01 7.31E+01 O.OOE-01 O.OOE-01 O.OOE-01 RU105 1.48E-02 2.30E+01 3.76E-02 O.OOE-01 4.86E-01 O.OOE-01 O.OOE-01 O.OOE-01 RU106 3.66E+01 1.87E+04 2.89E+02 O.OOE-01 5.58E+02 O.OOE-01 O.OOE-01 O.OOE-01 AG110M 2.12E+OO 1.46E+03 3.87E+OO 3.58E+OO 7.03E+OO O.OOE-01 O.OOE-01 O.OOE-01 TE125M 1.49E+03 4.46E+04 1.12E+04 4.04E+03 4.54E+04 3.36E+03 O.OOE-01 O.OOE-01 TE127M 3.45E+03 9.51 E+04 2.83E+04 1.01E+04 1.15E+05 7.25E+03 O.OOE-01 O.OOE-01 TE127 1.68E+01 6.12E+03 7.76E+01 2.79E+01 3.16E+02 5.75E+01 O.OOE-01 O.OOE-01 TE129M 7.51 E+03 2.39E+05 4.75E+04 1.77E+04 1.98E+05 1.63E+04 O.OOE-01 O.OOE-01 TE129 1.79E-05 5.56E-05 7.36E-05 2.??E-05 3.09E-04 5.65E-05 O.OOE-01 O.OOE-01 TE131M 1.70E+03 2.03E+05 4.18E+03 2.04E+03 2.07E+04 3.24E+03 O.OOE-01 O.OOE-01 TE131 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE132 5.21 E+03 2.62E+05 8.58E+03 5.55E+03 5.35E+04 6.13E+03 O.OOE-01 O.OOE-01 I 130 3.59E+01 7.84E+01 3.09E+01 9.11 E+01 1.42E+02 7.72E+03 O.OOE-01 O.OOE-01 I 131 4.94E+02 2.28E+02 6.03E+02 8.62E+02 1.48E+03 2.83E+05 O.OOE-01 O.OOE-01 1132 2.11 E-02 1.13E-02 2.25E-02 6.02E-02 9.60E-02 2.11E+OO O.OOE-01 O.OOE-01 1133 5.33E+01 1.57E+02 1.01 E+02 1.75E+02 3.05E+02 2.57E+04 O.OOE-01 O.OOE-01 I 134 8.36E-08 2.04E-10 8.60E-08 2.34E-07 3.72E-07 4.05E-06 O.OOE-01 O.OOE-01 1135 5.37E+OO 1.64E+01 5.56E+OO 1.46E+01 2.33E+01 9.60E+02 O.OOE-01 O.OOE-01 CS134 2.55E+06 5.45E+04 1.31E+06 3.12E+06 1.01E+06 O.OOE-01 3.35E+05 O.OOE-01 CS136 3.70E+05 5.84E+04 1.30E+05 5.14E+05 2.86E+05 O.OOE-01 3.92E+04 O.OOE-01 CS137 1.50E+06 4.45E+04 1.68E+06 2.30E+06 7.80E+05 O.OOE-01 2.59E+05 O.OOE-01 CS138 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BA139 6.35E-07 3.85E-05 2.17E-05 1.55E-08 1.45E-08 O.OOE-01 8.??E-09 O.OOE-01 BA140 5.31E+01 1.67E+03 8.10E+02 1.02E+OO 3.46E-01 O.OOE-01 5.83E-01 O.OOE-01 BA141 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BA142 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 LA140 5.80E-02 1.61E+04 4.35E-01 2.19E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 LA142 7.45E-08 2.18E-03 6.58E-07 2.99E-07 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CE141 7.41E-03 2.50E+02 9.65E-02 6.53E-02 3.03E-02 O.OOE-01 O.OOE-01 O.OOE-01 CE143 8.59E-04 2.90E+02 1.05E-02 7.77E+OO 3.42E-03 O.OOE-01 O.OOE-01 O.OOE-01 CE144 2.75E-01 1.73E+03 5.13E+OO 2.14E+OO 1.27E+OO O.OOE-01 O.OOE-01 O.OOE-01 PR143 1.14E-01 1.01 E+04 2.30E+OO 9.24E-01 5.33E-01 O.OOE-01 O.OOE-01 O.OOE-01 PR144 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ND147 1.08E-01 8.63E+03 1.56E+OO 1.80E+OO 1.05E+OO O.OOE-01 O.OOE-01 O.OOE-01 W187 1.89E+02 1.77E+05 6.48E+02 5.41E+02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 NP239 5.06E-03 1.88E+03 9.34E-02 9.18E-03 2.86E-02 O.OOE-01 O.OOE-01 O.OOE-01 DAEC ODAM Page 172 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =ADULT PATHWAY= FRESH WATER INVERTEBRATES TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN {mrem gaQ/{Ci min} H 3 1.35E-01 1.35E-01 O.OOE-01 1.35E-01 1.35E-01 1.35E-01 1.35E-01 O.OOE-01 c 14 1.30E+04 1.30E+04 6.48E+04 1.30E+04 1.30E+04 1.30E+04 1.30E+04 O.OOE-01 NA24 2.81 E+02 2.81 E+02 2.81E+02 2.81 E+02 2.81E+02 2.81 E+02 2.81 E+02 O.OOE-01 p 32 3.57E+05 1.04E+06 9.22E+06 5.73E+05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CR 51 1.30E+01 3.27E+03 O.OOE-01 O.OOE-01 2.87E+OO 7.78E+OO 1.73E+01 O.OOE-01 MN 54 1.96E+05 3.15E+06 O.OOE-01 1.03E+06 3.06E+05 O.OOE-01 O.OOE-01 O.OOE-01 MN 56 6.88E+OO 1.24E+03 O.OOE-01 3.88E+01 4.92E+01 O.OOE-01 O.OOE-01 O.OOE-01 FE 55 3.55E+03 8.74E+03 2.21E+04 1.52E+04 O.OOE-01 O.OOE-01 8.50E+03 O.OOE-01 FE 59 3.09E+04 2.69E+05 3.43E+04 8.06E+04 O.OOE-01 O.OOE-01 2.25E+04 O.OOE-01 C058 8.30E+02 7.50E+03 O.OOE-01 3.70E+02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 co 60 2.37E+03 2.02E+04 O.OOE-01 1.07E+03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl63 1.09E+03 4.72E+02 3.26E+04 2.26E+03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl65 1.04E-02 5.77E-01 1.75E-01 2.28E-02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 cu 64 1.05E+01 1.91E+03 O.OOE-01 2.24E+01 5.64E+01 O.OOE-01 O.OOE-01 O.OOE-01 ZN 65 1.74E+05 2.43E+05 1.21E+05 3.85E+05 2.58E+05 O.OOE-01 O.OOE-01 O.OOE-01 ZN 69 7.71E-07 1.67E-06 5.80E-06 1.11 E-05 7.21E-06 O.OOE-01 O.OOE-01 O.OOE-01 BR 83 3.08E-02 4.44E-02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 84 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 85 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 86 2.38E+04 1.01E+04 O.OOE-01 5.10E+04 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 88 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 89 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 89 2.19E+03 1.22E+04 7.62E+04 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 90 4.39E+04 5.49E+04 2.18E+06 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 91 9.87E+OO 1.16E+03 2.44E+02 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 92 4.93E-02 2.26E+01 1.14E+OO O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 90 4.99E-01 1.97E+05 1.86E+01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Y 91M O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 91 9.35E+OO 1.92E+05 3.50E+02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 92 5.62E-04 3.37E+02 1.92E-02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 93 3.54E-02 4.07E+04 1.28E+OO O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 95 1.1 OE-01 5.14E+02 5.06E-01 1.62E-01 2.54E-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 97 9.69E-04 6.56E+02 1.05E-02 2.12E-03 3.20E-03 O.OOE-01 O.OOE-01 O.OOE-01 NB 95 4.58E-01 5.17E+03 1.53E+OO 8.51 E-01 8.41 E-01 O.OOE-01 O.OOE-01 O.OOE-01 MO 99 1.60E+01 1.95E+02 O.OOE-01 8.39E+01 1.90E+02 O.OOE-01 O.OOE-01 O.OOE-01 TC 99M 6.94E-03 3.23E-01 1.93E-04 5.45E-04 8.28E-03 O.OOE-01 2.67E-04 O.OOE-01 TC101 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 DAEC ODAM Page 173 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =ADULT PATHWAY= FRESH WATER INVERTEBRATES TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN {mrem gaQ!{Ci min} RU103 5.89E+01 1.60E+04 1.37E+02 O.OOE-01 5.22E+02 O.OOE-01 O.OOE-01 O.OOE-01 RU105 1.06E-01 1.64E+02 2.68E-01 O.OOE-01 3.47E+OO O.OOE-01 O.OOE-01 O.OOE-01 RU106 2.61 E+02 1.34E+05 2.07E+03 O.OOE-01 3.99E+03 O.OOE-01 O.OOE-01 O.OOE-01 AG110M 1.69E+02 1.16E+05 3.08E+02 2.85E+02 5.61 E+02 O.OOE-01 O.OOE-01 O.OOE-01 TE125M 5.43E+03 1.62E+05 4.05E+04 1.47E+04 1.65E+05 1.22E+04 O.OOE-01 O.OOE-01 TE127M 1.25E+04 3.45E+05 1.03E+05 3.68E+04 4.18E+05 2.63E+04 O.OOE-01 O.OOE-01 TE127 6.10E+01 2.22E+04 2.82E+02 1.01E+02 1.15E+03 2.09E+02 O.OOE-01 O.OOE-01 TE129M 2.73E+04 8.68E+05 1.72E+05 6.43E+04 7.19E+05 5.92E+04 O.OOE-01 O.OOE-01 TE129 6.51E-05 2.02E-04 2.67E-04 1.00E-04 1.12E-03 2.05E-04 O.OOE-01 O.OOE-01 TE131M 6.18E+03 7.37E+05 1.52E+04 7.42E+03 7.51 E+04 1.17E+04 O.OOE-01 O.OOE-01 TE131 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE132 1.89E+04 9.53E+05 3.12E+04 2.01 E+04 1.94E+05 2.22E+04 O.OOE-01 O.OOE-01 1130 2.85E+OO 6.22E+OO 2.45E+OO 7.23E+OO 1.13E+01 6.12E+02 O.OOE-01 O.OOE-01 I 131 3.92E+01 1.81E+01 4.79E+01 6.84E+01 1.17E+02 2.24E+04 O.OOE-01 O.OOE-01 1132 1.67E-03 8.98E-04 1.79E-03 4.78E-03 7.62E-03 1.67E-01 O.OOE-01 O.OOE-01 1133 4.23E+OO 1.25E+01 7.98E+OO 1.39E+01 2.42E+01 2.04E+03 O.OOE-01 O.OOE-01 1134 6.64E-09 1.62E-11 6.83E-09 1.86E-08 2.95E-08 3.21E-07 O.OOE-01 O.OOE-01 1135 4.26E-01 1.30E+OO 4.41 E-01 1.15E+OO 1.85E+OO 7.62E+01 O.OOE-01 O.OOE-01 CS134 3.03E+05 6.49E+03 1.56E+05 3.71E+05 1.20E+05 O.OOE-01 3.99E+04 O.OOE-01 CS136 4.40E+04 6.95E+03 1.55E+04 6.11E+04 3.40E+04 O.OOE-01 4.66E+03 O.OOE-01 CS137 1.79E+05 5.29E+03 2.00E+05 2.73E+05 9.28E+04 O.OOE-01 3.09E+04 O.OOE-01 CS138 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BA139 7.56E-06 4.58E-04 2.58E-04 1.84E-07 1.72E-07 O.OOE-01 1.04E-07 O.OOE-01 BA140 6.32E+02 1.99E+04 9.65E+03 1.21E+01 4.12E+OO O.OOE-01 6.94E+OO O.OOE-01 BA141 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BA142 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 LA140 5.52E-01 1.53E+05 4.14E+OO 2.09E+OO O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 LA142 7.10E-07 2.08E-02 6.26E-06 2.85E-06 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CE141 1.76E+OO 5.94E+04 2.30E+01 1.56E+01 7.22E+OO O.OOE-01 O.OOE-01 O.OOE-01 CE143 2.05E-01 6.91 E+04 2.50E+OO 1.85E+03 8.14E-01 O.OOE-01 O.OOE-01 O.OOE-01 CE144 6.56E+01 4.13E+05 1.22E+03 5.11E+02 3.03E+02 O.OOE-01 O.OOE-01 O.OOE-01 PR143 1.09E+OO 9.61E+04 2.19E+01 8.80E+OO 5.08E+OO O.OOE-01 O.OOE-01 O.OOE-01 PR144 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ND147 1.02E+OO 8.22E+04 1.48E+01 1.71 E+01 1.00E+01 O.OOE-01 O.OOE-01 O.OOE-01 W187 3.76E-01 3.52E+02 1.28E+OO 1.07E+OO O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 NP239 4.82E-02 1.79E+04 8.89E-01 8.74E-02 2.73E-01 O.OOE-01 O.OOE-01 O.OOE-01 DAEC ODAM Page 174 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE ==ADULT PATHWAY==

IRRIGATED FRESH LEAFY VEGETABLES TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN (mrem gaQ/(Ci minl H 3 1.92E+OO 1.92E+OO O.OOE-01 1.92E+OO 1.92E+OO 1.92E+OO 1.92E+OO O.OOE-01 c 14 2.03E+03 2.03E+03 1.01E+04 2.03E+03 2.03E+03 2.03E+03 2.03E+03 O.OOE-01 NA24 6.22E+OO 6.22E+OO 6.22E+OO 6.22E+OO 6.22E+OO 6.22E+OO 6.22E+OO O.OOE-01 p 32 9.84E+02 2.86E+03 2.54E+04 1.58E+03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CR 51 4.60E-01 1.16E+02 O.OOE-01 O.OOE-01 1.01 E-01 2.75E-01 6.10E-01 O.OOE-01 MN 54 2.16E+02 3.47E+03 O.OOE-01 1.13E+03 3.37E+02 O.OOE-01 O.OOE-01 O.OOE-01 MN 56 4.90E-05 8.81E-03 O.OOE-01 2.76E-04 3.50E-04 O.OOE-01 O.OOE-01 O.OOE-01 FE 55 1.12E+02 2.76E+02 6.97E+02 4.81 E+02 O.OOE-01 O.OOE-01 2.68E+02 O.OOE-01 FE 59 7.75E+02 6.74E+03 8.61E+02 2.02E+03 O.OOE-01 O.OOE-01 5.65E+02 O.OOE-01 C058 3.63E+02 3.28E+03 O.OOE-01 1.62E+02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 C060 1.21 E+03 1.03E+04 O.OOE-01 5.50E+02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl63 1.16E+03 5.02E+02 3.47E+04 2.41E+03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl65 6.50E-05 3.62E-03 1.10E-03 1.42E-04 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 cu 64 9.79E-02 1.78E+01 O.OOE-01 2.08E-01 5.26E-01 O.OOE-01 O.OOE-01 O.OOE-01 ZN 65 1.80E+03 2.51 E+03 1.25E+03 3.99E+03 2.67E+03 O.OOE-01 O.OOE-01 O.OOE-01 ZN 69 1.22E-11 2.63E-11 9.14E-11 1.75E-10 1.14E-10 O.OOE-01 O.OOE-01 O.OOE-01 BR 83 5.52E-05 7.94E-05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 84 1.45E-16 1.14E-21 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 85 3.62E-37 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 86 1.46E+03 6.17E+02 O.OOE-01 3.13E+03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 88 3.95E-28 1.03E-38 O.OOE-01 7.45E-28 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 89 3.31E-30 2.73E-43 O.OOE-01 4.71E-30 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 89 1.82E+03 1.01E+04 6.33E+04 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 90 6.25E+04 7.82E+04 3.11 E+06 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 91 2.74E-01 3.23E+01 6.78E+OO O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 92 3.38E-04 1.55E-01 7.82E-03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 90 8.54E-03 3.37E+03 3.18E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Y 91M 1.82E-15 1.38E-13 4.71 E-14 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 91 7.92E-01 1.63E+04 2.96E+01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 92 5.32E-07 3.19E-01 1.82E-05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 93 1.04E-04 1.20E+02 3.78E-03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 95 1.41E+OO 6.60E+03 6.49E+OO 2.08E+OO 3.27E+OO O.OOE-01 O.OOE-01 O.OOE-01 ZR 97 7.19E-04 4.87E+02 7.79E-03 1.57E-03 2.37E-03 O.OOE-01 O.OOE-01 O.OOE-01 NB 95 3.47E-01 3.92E+03 1.16E+OO 6.45E-01 6.38E-01 O.OOE-01 O.OOE-01 O.OOE-01 MO 99 2.80E+01 3.41E+02 O.OOE-01 1.47E+02 3.33E+02 O.OOE-01 O.OOE-01 O.OOE-01 TC 99M 2.38E-03 1.11E-01 6.61E-05 1.87E-04 2.83E-03 O.OOE-01 9.15E-05 O.OOE-01 TC101 3.20E-31 9.81 E-44 2.26E-32 3.26E-32 5.87E-31 O.OOE-01 1.67E-32 O.OOE-01 DAEC ODAM Page 175 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =ADULT PATHWAY= IRRIGATED FRESH LEAFY VEGETABLES TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN mrem al I Ci min RU103 1.54E+01 4.16E+03 3.56E+01 O.OOE-01 1.36E+02 O.OOE-01 O.OOE-01 O.OOE-01 RU105 4.31 E-04 6.68E-01 1.09E-03 O.OOE-01 1.41 E-02 O.OOE-01 O.OOE-01 O.OOE-01 RU106 8.73E+01 4.47E+04 6.90E+02 O.OOE-01 1.33E+03 O.OOE-01 O.OOE-01 O.OOE-01 AG110M 2.20E+01 1.51E+04 4.00E+01 3.70E+01 7.28E+01 O.OOE-01 O.OOE-01 O.OOE-01 TE125M 7.96E+01 2.37E+03 5.94E+02 2.15E+02 2.42E+03 1.79E+02 O.OOE-01 O.OOE-01 TE127M 2.08E+02 5.72E+03 1.71E+03 6.10E+02 6.93E+03 4.36E+02 O.OOE-01 O.OOE-01 TE127 2.76E-02 1.01 E+01 1.27E-01 4.57E-02 5.19E-01 9.44E-02 O.OOE-01 O.OOE-01 TE129M 3.47E+02 1.10E+04 2.19E+03 8.18E+02 9.15E+03 7.53E+02 O.OOE-01 O.OOE-01 TE129 2.33E-09 7.23E-09 9.59E-09 3.60E-09 4.03E-08 7.36E-09 O.OOE-01 O.OOE-01 TE131M 8.86E+OO 1.06E+03 2.17E+01 1.06E+01 1.08E+02 1.69E+01 O.OOE-01 O.OOE-01 TE131 2.02E-21 9.06E-22 6.40E-21 2.67E-21 2.80E-20 5.26E-21 O.OOE-01 O.OOE-01 TE132 6.34E+01 3.20E+03 1.04E+02 6.76E+01 6.51 E+02 7.46E+01 O.OOE-01 O.OOE-01 1130 2.07E+OO 4.52E+OO 1.78E+OO 5.25E+OO 8.19E+OO 4.45E+02 O.OOE-01 O.OOE-01 I 131 3.07E+02 1.41E+02 3.75E+02 5.36E+02 9.19E+02 1.76E+05 O.OOE-01 O.OOE-01 I 132 1.87E-04 1.00E-04 2.00E-04 5.34E-04 8.51E-04 1.87E-02 O.OOE-01 O.OOE-01 1133 5.16E+OO 1.52E+01 9.74E+OO 1.69E+01 2.96E+01 2.49E+03 O.OOE-01 O.OOE-01 1134 1.82E-10 4.44E-13 1.87E-10 5.09E-10 8.10E-10 8.82E-09 O.OOE-01 O.OOE-01 1135 1.61 E-01 4.92E-01 1.67E-01 4.36E-01 6.99E-01 2.87E+01 O.OOE-01 O.OOE-01 CS134 3.07E+04 6.56E+02 1.58E+04 3.75E+04 1.21 E+04 O.OOE-01 4.03E+03 O.OOE-01 CS136 2.28E+03 3.60E+02 8.04E+02 3.17E+03 1.76E+03 O.OOE-01 2.42E+02 O.OOE-01 CS137 1.86E+04 5.51 E+02 2.08E+04 2.85E+04 9.67E+03 O.OOE-01 3.21 E+03 O.OOE-01 CS138 2.37E-16 2.04E-21 2.42E-16 4.78E-16 3.52E-16 O.OOE-01 3.47E-17 O.OOE-01 BA139 1.05E-08 6.39E-07 3.60E-07 2.57E-10 2.40E-10 O.OOE-01 1.46E-10 O.OOE-01 BA140 1.62E+02 5.09E+03 2.47E+03 3.11E+OO 1.06E+OO O.OOE-01 1.78E+OO O.OOE-01 BA141 7.72E-29 1.08E-36 2.29E-27 1.73E-30 1.61E-30 O.OOE-01 9.81 E-31 O.OOE-01 BA142 3.45E-32 O.OOE-01 5.48E-31 5.63E-34 4.76E-34 O.OOE-01 3.19E-34 O.OOE-01 LA140 6.27E-03 1.74E+03 4.70E-02 2.37E-02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 LA142 2.33E-10 6.82E-06 2.05E-09 9.34E-10 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CE141 1.31E-01 4.41E+03 1.71E+OO 1.15E+OO 5.35E-01 O.OOE-01 O.OOE-01 O.OOE-01 CE143 1.94E-03 6.56E+02 2.37E-02 1.75E+01 7.72E-03 O.OOE-01 O.OOE-01 O.OOE-01 CE144 6.44E+OO 4.05E+04 1.20E+02 5.01E+01 2.97E+01 O.OOE-01 O.OOE-01 O.OOE-01 PR143 5.75E-02 5.08E+03 1.16E+OO 4.65E-01 2.68E-01 O.OOE-01 O.OOE-01 O.OOE-01 PR144 2.51E-33 7.11 E-39 4.94E-32 2.05E-32 1.16E-32 O.OOE-01 O.OOE-01 O.OOE-01 ND147 4.87E-02 3.90E+03 7.03E-01 8.13E-01 4.75E-01 O.OOE-01 O.OOE-01 O.OOE-01 w 187 2.62E-01 2.45E+02 8.97E-01 7.49E-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 NP239 1.85E-03 6.89E+02 3.42E-02 3.36E-03 1.05E-02 O.OOE-01 O.OOE-01 O.OOE-01 DAEC ODAM Page 176 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =ADULT PATHWAY= IRRIGATED STORED FRUIT, VEGETABLES, GRAIN TOTAL BODY GI-LU BONE LIVER KIDNEY THYROID LUNG SKIN (mrem gal)/(Ci min) H 3 1.55E+01 1.55E+01 O.OOE-01 1.55E+01 1.55E+01 1.55E+01 1.55E+01 O.OOE-01 c 14 1.65E+04 1.65E+04 8.23E+04 1.65E+04 1.65E+04 1.65E+04 1.65E+04 O.OOE-01 NA24 1.34E-24 1.34E-24 1.34E-24 1.34E-24 1.34E-24 1.34E-24 1.34E-24 O.OOE-01 p 32 4.58E+02 1.33E+03 1.18E+04 7.36E+02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CR 51 8.52E-01 2.14E+02 O.OOE-01 O.OOE-01 1.88E-01 5.09E-01 1.13E+OO O.OOE-01 MN 54 1.54E+03 2.47E+04 O.OOE-01 8.08E+03 2.40E+03 O.OOE-01 O.OOE-01 O.OOE-01 MN 56 2.27E-27 4.09E-25 O.OOE-01 1.28E-26 1.63E-26 O.OOE-01 O.OOE-01 O.OOE-01 FE 55 8.75E+02 2.15E+03 5.43E+03 3.75E+03 O.OOE-01 O.OOE-01 2.09E+03 O.OOE-01 FE 59 2.52E+03 2.19E+04 2.79E+03 6.57E+03 O.OOE-01 O.OOE-01 1.83E+03 O.OOE-01 co 58 1.66E+03 1.50E+04 O.OOE-01 7.39E+02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 C060 9.66E+03 8.23E+04 O.OOE-01 4.38E+03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl63 9.45E+03 4.08E+03 2.82E+05 1.95E+04 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl65 3.40E-27 1.89E-25 5.74E-26 7.46E-27 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 cu 64 2.59E-26 4.?0E-24 O.OOE-01 5.51E-26 1.39E-25 O.OOE-01 O.OOE-01 O.OOE-01 ZN 65 1.24E+04 1.73E+04 8.62E+03 2.74E+04 1.83E+04 O.OOE-01 O.OOE-01 O.OOE-01 ZN 69 3.58E-29 7.74E-29 2.69E-28 5.15E-28 3.35E-28 O.OOE-01 O.OOE-01 O.OOE-01 BR 83 4.12E-27 5.93E-27 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 84 4.30E-28 3.38E-33 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 85 2.95E-36 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 86 1.33E+03 5.63E+02 O.OOE-01 2.85E+03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 88 5.32E-29 1.39E-39 O.OOE-01 1.00E-28 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 89 2.69E-29 2.22E-42 O.OOE-01 3.83E-29 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 89 6.56E+03 3.67E+04 2.29E+05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 90 5.06E+05 6.33E+05 2.52E+07 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 91 1.13E-25 1.33E-23 2.79E-24 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 92 1.11 E-26 5.09E-24 2.57E-25 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 90 1.58E-08 6.26E-03 5.90E-07 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Y 91M 7.18E-32 5.44E-30 1.85E-30 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 91 3.20E+OO 6.59E+04 1.20E+02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 92 4.09E-30 2.45E-24 1.40E-28 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 93 3.87E-29 4.44E-23 1.40E-27 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 95 6.05E+OO 2.83E+04 2.79E+01 8.94E+OO 1.40E+01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 97 3.38E-28 2.29E-22 3.66E-27 7.38E-28 1.12E-27 O.OOE-01 O.OOE-01 O.OOE-01 NB 95 8.82E-01 9.95E+03 2.95E+OO 1.64E+OO 1.62E+OO O.OOE-01 O.OOE-01 O.OOE-01 M099 7.80E-05 9.51 E-04 O.OOE-01 4.10E-04 9.29E-04 O.OOE-01 O.OOE-01 O.OOE-01 TC 99M 2.69E-27 1.25E-25 7.46E-29 2.11 E-28 3.20E-27 O.OOE-01 1.03E-28 O.OOE-01 TC101 2.60E-30 7.96E-43 1.84E-31 2.65E-31 4.77E-30 O.OOE-01 1.35E-31 O.OOE-01 DAEC ODAM Page 177 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =ADULT PATHWAY= IRRIGATED STORED FRUIT, VEGETABLES, GRAIN TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN mrem al I Ci min RU103 4.41 E+01 1.19E+04 1.02E+02 O.OOE-01 3.90E+02 O.OOE-01 O.OOE-01 O.OOE-01 RU105 1.30E-27 2.02E-24 3.30E-27 O.OOE-01 4.27E-26 O.OOE-01 O.OOE-01 O.OOE-01 RU106 6.35E+02 3.25E+05 5.02E+03 O.OOE-01 9.69E+03 O.OOE-01 O.OOE-01 O.OOE-01 AG110M 1.52E+02 1.04E+05 2.76E+02 2.55E+02 5.02E+02 O.OOE-01 O.OOE-01 O.OOE-01 TE125M 3.20E+02 9.53E+03 2.39E+03 8.65E+02 9.71E+03 7.18E+02 O.OOE-01 O.OOE-01 TE127M 1.16E+03 3.19E+04 9.52E+03 3.40E+03 3.87E+04 2.43E+03 O.OOE-01 O.OOE-01 TE127 1.16E-26 4.24E-24 5.37E-26 1.93E-26 2.19E-25 3.98E-26 O.OOE-01 O.OOE-01 TE129M 8.34E+02 2.65E+04 5.27E+03 1.97E+03 2.20E+04 1.81E+03 O.OOE-01 O.OOE-01 TE129 2.81E-28 8.72E-28 1.16E-27 4.34E-28 4.86E-27 8.86E-28 O.OOE-01 O.OOE-01 TE131M 4.41 E-13 5.25E-11 1.08E-12 5.29E-13 5.36E-12 8.38E-13 O.OOE-01 O.OOE-01 TE131 2.86E-29 1.28E-29 9.04E-29 3.78E-29 3.96E-28 7.44E-29 O.OOE-01 O.OOE-01 TE132 1.84E-03 9.30E-02 3.04E-03 1.97E-03 1.89E-02 2.17E-03 O.OOE-01 O.OOE-01 1130 5.67E-25 1.24E-24 4.87E-25 1.44E-24 2.24E-24 1.22E-22 O.OOE-01 O.OOE-01 I 131 1.54E+01 7.10E+OO 1.88E+01 2.69E+01 4.61E+01 8.81 E+03 O.OOE-01 O.OOE-01 1132 1.84E-26 9.87E-27 1.96E-26 5.25E-26 8.37E-26 1.84E-24 O.OOE-01 O.OOE-01 1133 1.40E-19 4.11E-19 2.63E-19 4.58E-19 7.99E-19 6.73E-17 0.00E-01 O.OOE-01 I 134 2.33E-27 5.68E-30 2.40E-27 6.52E-27 1.04E-26 1.13E-25 O.OOE-01 O.OOE-01 1135 1.43E-25 4.37E-25 1.48E-25 3.87E-25 6.20E-25 2.55E-23 O.OOE-01 O.OOE-01 CS134 2.36E+05 5.05E+03 1.21 E+05 2.89E+05 9.34E+04 O.OOE-01 3.10E+04 O.OOE-01 CS136 8.20E+02 1.29E+02 2.88E+02 1.14E+03 6.34E+02 O.OOE-01 8.68E+01 O.OOE-01 CS137 1.51E+05 4.46E+03 1.69E+05 2.30E+05 7.82E+04 O.OOE-01 2.60E+04 O.OOE-01 CS138 4.57E-28 3.94E-33 4.67E-28 9.23E-28 6.78E-28 O.OOE-01 6.70E-29 O.OOE-01 BA139 1.35E-28 8.14E-27 4.59E-27 3.27E-30 3.06E-30 O.OOE-01 1.86E-30 O.OOE-01 BA140 5.38E+01 1.69E+03 8.22E+02 1.03E+OO 3.51 E-01 O.OOE-01 5.91 E-01 O.OOE-01 BA141 2.85E-30 3.98E-38 8.43E-29 6.37E-32 5.93E-32 O.OOE-01 3.62E-32 O.OOE-01 BA142 2.80E-31 O.OOE-01 4.45E-30 4.58E-33 3.87E-33 O.OOE-01 2.59E-33 O.OOE-01 LA140 1.33E-12 3.70E-07 1.00E-11 5.04E-12 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 LA142 8.11 E-31 2.38E-26 7.16E-30 3.26E-30 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CE141 3.02E-01 1.02E+04 3.93E+OO 2.66E+OO 1.24E+OO O.OOE-01 O.OOE-01 O.OOE-01 CE143 2.16E-15 7.31E-10 2.65E-14 1.96E-11 8.61E-15 O.OOE-01 O.OOE-01 O.OOE-01 CE144 4.53E+01 2.85E+05 8.44E+02 3.53E+02 2.09E+02 O.OOE-01 O.OOE-01 O.OOE-01 PR143 2.31E-02 2.04E+03 4.65E-01 1.87E-01 1.08E-01 O.OOE-01 O.OOE-01 O.OOE-01 PR144 2.27E-33 6.41 E-39 4.46E-32 1.85E-32 1.04E-32 O.OOE-01 O.OOE-01 O.OOE-01 ND147 9.92E-03 7.95E+02 1.43E-01 1.66E-01 9.69E-02 O.OOE-01 O.OOE-01 O.OOE-01 w 187 3.21 E-18 3.01E-15 1.10E-17 9.18E-18 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 NP239 4.47E-10 1.66E-04 8.25E-09 8.11E-10 2.53E-09 O.OOE-01 O.OOE-01 O.OOE-01 DAEC ODAM Page 178 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =ADULT PATHWAY= IRRIGATED FRESH FORAGE--MILK TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN {mrem gaQ/{Ci min) H 3 4.24E+OO 4.24E+OO O.OOE-01 4.24E+OO 4.24E+OO 4.24E+OO 4.24E+OO O.OOE-01 c 14 6.45E+03 6.45E+03 3.23E+04 6.45E+03 6.45E+03 6.45E+03 6.45E+03 O.OOE-01 NA24 5.70E+01 5.70E+01 5.70E+01 5.70E+01 5.70E+01 5.70E+01 5.70E+01 O.OOE-01 p 32 1.52E+04 4.43E+04 3.94E+05 2.45E+04 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CR 51 6.17E-01 1.55E+02 O.OOE-01 O.OOE-01 1.36E-01 3.69E-01 8.18E-01 O.OOE-01 MN 54 3.07E+01 4.93E+02 O.OOE-01 1.61E+02 4.79E+01 O.OOE-01 O.OOE-01 O.OOE-01 MN 56 1.30E-08 2.34E-06 O.OOE-01 7.32E-08 9.30E-08 O.OOE-01 O.OOE-01 O.OOE-01 FE 55 7.62E+01 1.87E+02 4.73E+02 3.27E+02 O.OOE-01 O.OOE-01 1.82E+02 O.OOE-01 FE 59 5.55E+02 4.83E+03 6.16E+02 1.45E+03 O.OOE-01 O.OOE-01 4.05E+02 O.OOE-01 C058 2.13E+02 1.92E+03 O.OOE-01 9.48E+01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 C060 6.82E+02 5.81 E+03 O.OOE-01 3.09E+02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl63 4.30E+03 1.85E+03 1.28E+05 8.89E+03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl65 4.10E-07 2.28E-05 6.91 E-06 8.98E-07 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 cu 64 2.55E-01 4.63E+01 O.OOE-01 5.43E-01 1.37E+OO O.OOE-01 O.OOE-01 0.00E-01 ZN 65 3.88E+04 5.41E+04 2.70E+04 8.59E+04 5.74E+04 O.OOE-01 O.OOE-01 O.OOE-01 ZN 69 7.91E-18 1.71E-17 5.94E-17 1.14E-16 7.39E-17 O.OOE-01 O.OOE-01 O.OOE-01 BR 83 1.81 E-06 2.61E-06 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 84 1.82E-27 1.43E-32 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 85 1.25E-35 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 86 2.71E+04 1.15E+04 O.OOE-01 5.81E+04 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 88 1.36E-28 3.54E-39 O.OOE-01 2.56E-28 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 89 6.87E-29 5.68E-42 O.OOE-01 9.77E-29 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 89 8.69E+02 4.86E+03 3.03E+04 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 90 3.73E+04 4.67E+04 1.86E+06 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 91 2.63E-02 3.10E+OO 6.50E-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 92 4.06E-07 1.86E-04 9.39E-06 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 90 4.56E-05 1.80E+01 1.?0E-03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Y91M 2.28E-26 1.73E-24 5.89E-25 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 91 4.67E-03 9.62E+01 1.75E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 92 3.40E-11 2.04E-05 1.16E-09 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 93 1.39E-07 1.59E-01 5.02E-06 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 95 4.15E-03 1.94E+01 1.91 E-02 6.12E-03 9.61E-03 O.OOE-01 O.OOE-01 O.OOE-01 ZR 97 9.29E-07 6.29E-01 1.01E-05 2.03E-06 3.0?E-06 O.OOE-01 O.OOE-01 O.OOE-01 NB 95 5.23E-01 5.90E+03 1.75E+OO 9.72E-01 9.61 E-01 O.OOE-01 O.OOE-01 O.OOE-01 MO 99 1.13E+02 1.37E+03 O.OOE-01 5.93E+02 1.34E+03 O.OOE-01 O.OOE-01 O.OOE-01 TC 99M 2.59E-03 1.20E-01 7.19E-05 2.03E-04 3.08E-03 O.OOE-01 9.95E-05 O.OOE-01 TC101 5.52E-30 1.69E-42 3.91 E-31 5.63E-31 1.01 E-29 O.OOE-01 2.88E-31 O.OOE-01 DAEC ODAM Page 179 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =ADULT PATHWAY= IRRIGATED FRESH FORAGE--MILK TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN {mrem gaQ/{Ci min} RU103 9.19E-03 2.49E+OO 2.13E-02 O.OOE-01 8.15E-02 O.OOE-01 O.OOE-01 0.00E-01 RU105 7.01E-09 1.09E-05 1.78E-08 O.OOE-01 2.30E-07 O.OOE-01 O.OOE-01 O.OOE-01 RU106 4.93E-02 2.52E+01 3.90E-01 O.OOE-01 7.53E-01 O.OOE-01 O.OOE-01 O.OOE-01 AG110M 6.19E+02 4.25E+05 1.13E+03 1.04E+03 2.05E+03 O.OOE-01 O.OOE-01 O.OOE-01 TE125M 4.55E+01 1.35E+03 3.39E+02 1.23E+02 1.38E+03 1.02E+02 O.OOE-01 O.OOE-01 TE127M 1.14E+02 3.14E+03 9.37E+02 3.35E+02 3.80E+03 2.39E+02 O.OOE-01 O.OOE-01 TE127 3.19E-03 1.16E+OO 1.48E-02 5.30E-03 6.01E-02 1.09E-02 O.OOE-01 O.OOE-01 TE129M 2.05E+02 6.53E+03 1.30E+03 4.84E+02 5.41E+03 4.45E+02 O.OOE-01 O.OOE-01 TE129 9.47E-16 2.94E-15 3.89E-15 1.46E-15 1.63E-14 2.99E-15 O.OOE-01 O.OOE-01 TE131M 3.50E+OO 4.16E+02 8.58E+OO 4.20E+OO 4.25E+01 6.64E+OO O.OOE-01 O.OOE-01 TE131 2.41E-30 1.08E-30 7.65E-30 3.20E-30 3.35E-29 6.29E-30 O.OOE-01 O.OOE-01 TE132 3.52E+01 1.77E+03 5.79E+01 3.75E+01 3.61 E+02 4.14E+01 O.OOE-01 O.OOE-01 1130 2.23E+OO 4.87E+OO 1.92E+OO 5.66E+OO 8.83E+OO 4.79E+02 O.OOE-01 O.OOE-01 I 131 1.15E+03 5.30E+02 1.40E+03 2.01 E+03 3.44E+03 6.58E+05 O.OOE-01 O.OOE-01 1132 5.61E-07 3.01E-07 6.00E-07 1.60E-06 2.56E-06 5.61E-05 O.OOE-01 O.OOE-01 1133 9.64E+OO 2.84E+01 1.82E+01 3.16E+01 5.52E+01 4.65E+03 O.OOE-01 O.OOE-01 I 134 4.20E-18 1.02E-20 4.32E-18 1.17E-17 1.87E-17 2.04E-16 O.OOE-01 O.OOE-01 I 135 5.36E-02 1.64E-01 5.54E-02 1.45E-01 2.33E-01 9.57E+OO O.OOE-01 O.OOE-01 CS134 2.08E+05 4.45E+03 1.07E+05 2.54E+05 8.23E+04 O.OOE-01 2.73E+04 O.OOE-01 CS136 1.72E+04 2.71E+03 6.05E+03 2.39E+04 1.33E+04 O.OOE-01 1.82E+03 O.OOE-01 CS137 1.25E+05 3.69E+03 1.39E+05 1.91E+05 6.47E+04 O.OOE-01 2.15E+04 O.OOE-01 CS138 4.67E-28 4.02E-33 4.78E-28 9.43E-28 6.93E-28 O.OOE-01 6.85E-29 O.OOE-01 BA139 1.63E-14 9.87E-13 5.57E-13 3.97E-16 3.71E-16 O.OOE-01 2.25E-16 O.OOE-01 BA140 4.06E+01 1.28E+03 6.20E+02 7.79E-01 2.65E-01 O.OOE-01 4.46E-01 O.OOE-01 BA141 9.?0E-32 1.35E-39 2.87E-30 2.17E-33 2.02E-33 O.OOE-01 1.23E-33 O.OOE-01 BA142 9.54E-33 O.OOE-01 1.52E-31 1.56E-34 1.32E-34 O.OOE-01 8.82E-35 O.OOE-01 LA140 1.43E-05 3.98E+OO 1.08E-04 5.43E-05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 LA142 1.64E-17 4.81E-13 1.45E-16 6.59E-17 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CE141 7.91E-03 2.67E+02 1.03E-01 6.98E-02 3.24E-02 O.OOE-01 O.OOE-01 O.OOE-01 CE143 8.13E-05 2.75E+01 9.94E-04 7.35E-01 3.23E-04 O.OOE-01 O.OOE-01 O.OOE-01 CE144 3.67E-01 2.31 E+03 6.84E+OO 2.86E+OO 1.70E+OO O.OOE-01 O.OOE-01 0.00E-01 PR143 1.80E-04 1.59E+01 3.63E-03 1.46E-03 8.41E-04 O.OOE-01 O.OOE-01 O.OOE-01 PR144 9.64E-37 2.73E-42 1.90E-35 7.88E-36 4.44E-36 O.OOE-01 O.OOE-01 O.OOE-01 ND147 1.53E-04 1.23E+01 2.21E-03 2.55E-03 1.49E-03 O.OOE-01 O.OOE-01 O.OOE-01 W187 4.52E-02 4.24E+01 1.55E-01 1.29E-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 NP239 4.77E-06 1.78E+OO 8.81 E-05 8.66E-06 2.?0E-05 O.OOE-01 O.OOE-01 O.OOE-01 DAEC ODAM Page 180 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =ADULT PATHWAY= IRRIGATED FRESH FORAGE--MEAT TOTAL BODY GI-LU BONE LIVER KIDNEY THYROID LUNG SKIN (mrem gal)/(Ci min) H 3 1.65E+OO 1.65E+OO O.OOE-01 1.65E+OO 1.65E+OO 1.65E+OO 1.65E+OO O.OOE-01 c 14 5.91 E+03 5.91E+03 2.96E+04 5.91E+03 5.91E+03 5.91 E+03 5.91E+03 O.OOE-01 NA24 3.43E-08 3.43E-08 3.43E-08 3.43E-08 3.43E-08 3.43E-08 3.43E-08 O.OOE-01 p 32 4.15E+03 1.21E+04 1.07E+05 6.68E+03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CR 51 1.52E-01 3.82E+01 O.OOE-01 O.OOE-01 3.35E-02 9.09E-02 2.02E-01 O.OOE-01 MN 54 3.35E+01 5.38E+02 O.OOE-01 1.75E+02 5.22E+01 O.OOE-01 O.OOE-01 O.OOE-01 MN 56 5.49E-29 9.88E-27 O.OOE-01 3.09E-28 3.93E-28 O.OOE-01 O.OOE-01 O.OOE-01 FE 55 8.90E+02 2.19E+03 5.52E+03 3.82E+03 O.OOE-01 O.OOE-01 2.13E+03 O.OOE-01 FE 59 4.96E+03 4.31 E+04 5.51 E+03 1.29E+04 O.OOE-01 O.OOE-01 3.62E+03 O.OOE-01 co 58 8.23E+02 7.44E+03 O.OOE-01 3.67E+02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 C060 3.13E+03 2.66E+04 O.OOE-01 1.42E+03 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 Nl63 1.21E+04 5.20E+03 3.60E+05 2.49E+04 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl65 5.45E-27 3.03E-25 9.20E-26 1.20E-26 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 cu 64 2.80E-12 5.08E-10 O.OOE-01 5.96E-12 1.50E-11 O.OOE-01 O.OOE-01 O.OOE-01 ZN 65 1.01 E+04 1.40E+04 7.00E+03 2.23E+04 1.49E+04 O.OOE-01 O.OOE-01 O.OOE-01 ZN 69 3.24E-29 7.00E-29 2.44E-28 4.66E-28 3.03E-28 O.OOE-01 O.OOE-01 O.OOE-01 BR 83 3.22E-27 4.64E-27 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 84 3.37E-28 2.64E-33 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 85 2.30E-36 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 86 5.10E+03 2.16E+03 O.OOE-01 1.09E+04 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 88 4.98E-29 1.30E-39 O.OOE-01 9.39E-29 O.OOE-01 O.OOE-01 O.OCJE-01 O.OOE-01 RB 89 2.52E-29 2.08E-42 O.OOE-01 3.58E-29 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 89 1.81E+02 1.01E+03 6.29E+03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 90 9.93E+03 1.24E+04 4.94E+05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 91 1.36E-16 1.60E-14 3.37E-15 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 92 2.02E-28 9.24E-26 4.66E-27 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 90 7.00E-05 2.77E+01 2.61E-03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Y 91M 9.98E-33 7.57E-31 2.58E-31 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 91 6.16E-01 1.27E+04 2.30E+01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 92 5.68E-31 3.41 E-25 1.94E-29 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 93 2.85E-18 3.27E-12 1.03E-16 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 95 8.23E+OO 3.85E+04 3.79E+01 1.22E+01 1.91 E+01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 97 4.47E-11 3.03E-05 4.85E-10 9.78E-11 1.48E-10 O.OOE-01 O.OOE-01 O.OOE-01 NB 95 1.46E+01 1.64E+05 4.87E+01 2.71E+01 2.68E+01 O.OOE-01 O.OOE-01 O.OOE-01 MO 99 4.55E-01 5.54E+OO O.OOE-01 2.39E+OO 5.42E+OO O.OOE-01 O.OOE-01 O.OOE-01 TC 99M 3.58E-24 1.66E-22 9.94E-26 2.81E-25 4.27E-24 O.OOE-01 1.38E-25 O.OOE-01 TC101 3.13E-29 9.61E-42 2.22E-30 3.20E-30 5.76E-29 O.OOE-01 1.63E-30 O.OOE-01 DAEC ODAM Page 181 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =ADULT PATHWAY= IRRIGATED FRESH FORAGE--MEAT TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN mrem al I Ci min RU103 9.50E+02 2.58E+05 2.21E+03 O.OOE-01 8.42E+03 O.OOE-01 O.OOE-01 O.OOE-01 RU105 1.57E-26 2.44E-23 3.99E-26 O.OOE-01 5.16E-25 O.OOE-01 O.OOE-01 O.OOE-01 RU106 6.77E+03 3.46E+06 5.35E+04 O.OOE-01 1.03E+05 O.OOE-01 O.OOE-01 O.OOE-01 AG110M 7.11E+01 4.88E+04 1.29E+02 1.20E+02 2.35E+02 O.OOE-01 O.OOE-01 O.OOE-01 TE125M 1.00E+03 2.99E+04 7.48E+03 2.71 E+03 3.04E+04 2.25E+03 O.OOE-01 O.OOE-01 TE127M 2.78E+03 7.65E+04 2.28E+04 8.16E+03 9.27E+04 5.83E+03 O.OOE-01 O.OOE-01 TE127 1.07E-15 3.88E-13 4.92E-15 1.77E-15 2.01 E-14 3.65E-15 O.OOE-01 O.OOE-01 TE129M 3.86E+03 1.23E+05 2.44E+04 9.11E+03 1.02E+05 8.39E+03 O.OOE-01 O.OOE-01 TE129 6.50E-28 2.01E-27 2.67E-27 1.00E-27 1.12E-26 2.05E-27 O.OOE-01 O.OOE-01 TE131M 4.40E-03 5.25E-01 1.08E-02 5.28E-03 5.35E-02 8.37E-03 O.OOE-01 O.OOE-01 TE131 6.60E-29 2.96E-29 2.09E-28 8.73E-29 9.15E-28 1.72E-28 O.OOE-01 O.OOE-01 TE132 2.10E+01 1.06E+03 3.45E+01 2.23E+01 2.15E+02 2.46E+01 O.OOE-01 O.OOE-01 1130 1.11E-11 2.43E-11 9.56E-12 2.82E-11 4.40E-11 2.39E-09 O.OOE-01 O.OOE-01 I 131 4.18E+01 1.92E+01 5.10E+01 7.29E+01 1.25E+02 2.39E+04 O.OOE-01 O.OOE-01 1132 1.61 E-27 8.65E-28 1.72E-27 4.60E-27 7.33E-27 1.61 E-25 O.OOE-01 O.OOE-01 1133 9.35E-07 2.76E-06 1.76E-06 3.07E-06 5.35E-06 4.51 E-04 O.OOE-01 O.OOE-01 I 134 2.04E-28 4.98E-31 2.10E-28 5.71E-28 9.08E-28 9.89E-27 O.OOE-01 O.OOE-01 1135 1.74E-22 5.33E-22 1.80E-22 4.72E-22 7.57E-22 3.11 E-20 O.OOE-01 O.OOE-01 CS134 2.42E+04 5.18E+02 1.24E+04 2.96E+04 9.57E+03 O.OOE-01 3.18E+03 O.OOE-01 CS136 7.85E+02 1.24E+02 2.76E+02 1.09E+03 6.07E+02 O.OOE-01 8.32E+01 O.OOE-01 CS137 1.48E+04 4.36E+02 1.65E+04 2.25E+04 7.65E+03 O.OOE-01 2.54E+03 O.OOE-01 CS138 5.53E-29 4.76E-34 5.65E-29 1.12E-28 8.20E-29 O.OOE-01 8.10E-30 O.OOE-01 BA139 1.30E-29 7.88E-28 4.44E-28 3.16E-31 2.96E-31 1.79E-31 O.OOE-01 BA140 4.35E+01 1.37E+03 6.64E+02 8.34E-01 2.84E-01 O.OOE-01 4.78E-01 O.OOE-01 BA141 2.75E-31 3.84E-39 8.15E-30 6.16E-33 5.73E-33 O.OOE-01 3.50E-33 O.OOE-01 BA142 2.71E-32 O.OOE-01 4.30E-31 4.42E-34 3.74E-34 O.OOE-01 2.51 E-34 O.OOE-01 LA140 1.20E-07 3.34E-02 9.03E-07 4.55E-07 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 LA142 4.90E-33 1.44E-28 4.33E-32 1.97E-32 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CE141 2.29E-02 7.73E+02 2.99E-01 2.02E-01 9.40E-02 O.OOE-01 O.OOE-01 O.OOE-01 CE143 4.12E-08 1.39E-02 5.04E-07 3.73E-04 1.64E-07 O.OOE-01 O.OOE-01 O.OOE-01 CE144 1.50E+OO 9.42E+03 2.79E+01 1.16E+01 6.91 E+OO O.OOE-01 O.OOE-01 O.OOE-01 PR143 2.40E-02 2.12E+03 4.84E-01 1.94E-01 1.12E-01 O.OOE-01 O.OOE-01 O.OOE-01 PR144 3.22E-34 9.11 E-40 6.33E-33 2.63E-33 1.48E-33 O.OOE-01 O.OOE-01 O.OOE-01 ND147 1.16E-02 9.33E+02 1.68E-01 1.94E-01 1.14E-01 O.OOE-01 O.OOE-01 O.OOE-01 w 187 1.52E-07 1.43E-04 5.22E-07 4.36E-07 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 NP239 3.42E-07 1.27E-01 6.32E-06 6.21E-07 1.94E-06 O.OOE-01 O.OOE-01 O.OOE-01 DAEC ODAM Page 182 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =ADULT PATHWAY= IRRIGATED STORED FEED--MILK TOTAL BODY GI-LU BONE LIVER KIDNEY THYROID LUNG SKIN (mrem gaQ/(Ci min) H 3 4.24E+OO 4.24E+OO O.OOE-01 4.24E+OO 4.24E+OO 4.24E+OO 4.24E+OO O.OOE-01 c 14 6.67E+03 6.67E+03 3.34E+04 6.67E+03 6.67E+03 6.67E+03 6.67E+03 O.OOE-01 NA24 5.70E+01 5.70E+01 5.70E+01 5.70E+01 5.70E+01 5.70E+01 5.70E+01 O.OOE-01 p 32 1.60E+04 4.66E+04 4.14E+05 2.58E+04 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CR 51 6.83E-01 1.72E+02 O.OOE-01 O.OOE-01 1.50E-01 4.08E-01 9.06E-01 O.OOE-01 MN 54 3.72E+01 5.97E+02 O.OOE-01 1.95E+02 5.80E+01 O.OOE-01 O.OOE-01 O.OOE-01 MN 56 1.30E-08 2.34E-06 O.OOE-01 7.32E-08 9.30E-08 O.OOE-01 O.OOE-01 O.OOE-01 FE 55 9.31E+01 2.29E+02 5.78E+02 3.99E+02 O.OOE-01 O.OOE-01 2.23E+02 O.OOE-01 FE 59 6.34E+02 5.51 E+03 7.04E+02 1.65E+03 O.OOE-01 O.OOE-01 4.62E+02 O.OOE-01 co 58 2.48E+02 2.25E+03 O.OOE-01 1.11E+02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 C060 8.35E+02 7.11E+03 O.OOE-01 3.78E+02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl63 5.26E+03 2.27E+03 1.57E+05 1.09E+04 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl65 4.10E-07 2.28E-05 6.91E-06 8.98E-07 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 cu 64 2.55E-01 4.63E+01 O.OOE-01 5.43E-01 1.37E+OO O.OOE-01 O.OOE-01 O.OOE-01 ZN 65 4.67E+04 6.51 E+04 3.25E+04 1.03E+05 6.91 E+04 O.OOE-01 O.OOE-01 O.OOE-01 ZN 69 7.91E-18 1.71E-17 5.94E-17 1.14E-16 7.39E-17 O.OOE-01 O.OOE-01 O.OOE-01 BR 83 1.81 E-06 2.61E-06 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 84 1.82E-27 1.43E-32 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 85 1.25E-35 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 86 2.91E+04 1.23E+04 O.OOE-01 6.25E+04 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 88 1.36E-28 3.54E-39 O.OOE-01 2.56E-28 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 89 6.87E-29 5.68E-42 O.OOE-01 9.77E-29 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 89 9.97E+02 5.57E+03 3.48E+04 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 90 4.19E+04 5.25E+04 2.09E+06 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 91 2.63E-02 3.10E+OO 6.50E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 92 4.06E-07 1.86E-04 9.39E-06 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 90 4.56E-05 1.80E+01 1.?0E-03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Y 91M 2.28E-26 1.73E-24 5.89E-25 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 91 5.42E-03 1.11E+02 2.03E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 92 3.40E-11 2.04E-05 1.16E-09 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 93 1.39E-07 1.59E-01 5.02E-06 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 95 4.82E-03 2.26E+01 2.22E-02 7.13E-03 1.12E-02 O.OOE-01 O.OOE-01 O.OOE-01 ZR 97 9.29E-07 6.29E-01 1.01 E-05 2.03E-06 3.0?E-06 O.OOE-01 O.OOE-01 O.OOE-01 NB 95 5.88E-01 6.64E+03 1.97E+OO 1.09E+OO 1.08E+OO O.OOE-01 O.OOE-01 O.OOE-01 MO 99 1.13E+02 1.37E+03 O.OOE-01 5.93E+02 1.34E+03 O.OOE-01 O.OOE-01 O.OOE-01 TC 99M 2.59E-03 1.20E-01 7.19E-05 2.03E-04 3.08E-03 O.OOE-01 9.95E-05 O.OOE-01 TC101 5.52E-30 1.69E-42 3.91 E-31 5.63E-31 1.01 E-29 O.OOE-01 2.88E-31 O.OOE-01 DAEC ODAM Page 183 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =ADULT PATHWAY= IRRIGATED STORED FEED--MILK TOTAL BODY GI-LU BONE LIVER KIDNEY THYROID LUNG SKIN {mrem gaQ/{Ci min} RU103 1.04E-02 2.83E+OO 2.42E-02 0.00E-01 9.23E-02 O.OOE-01 O.OOE-01 O.OOE-01 RU105 7.01E-09 1.09E-05 1.78E-08 O.OOE-01 2.30E-07 O.OOE-01 O.OOE-01 O.OOE-01 RU106 5.98E-02 3.06E+01 4.73E-01 O.OOE-01 9.13E-01 O.OOE-01 O.OOE-01 O.OOE-01 AG110M 7.47E+02 5.13E+05 1.36E+03 1.26E+03 2.47E+03 O.OOE-01 O.OOE-01 O.OOE-01 TE125M 5.25E+01 1.56E+03 3.92E+02 1.42E+02 1.59E+03 1.18E+02 O.OOE-01 O.OOE-01 TE127M 1.35E+02 3.71E+03 1.10E+03 3.95E+02 4.49E+03 2.82E+02 O.OOE-01 O.OOE-01 TE127 3.19E-03 1.16E+OO 1.48E-02 5.30E-03 6.01E-02 1.09E-02 O.OOE-01 O.OOE-01 TE129M 2.30E+02 7.31 E+03 1.45E+03 5.42E+02 6.06E+03 4.99E+02 O.OOE-01 0.00E-01 TE129 9.47E-16 2.94E-15 3.89E-15 1.46E-15 1.63E-14 2.99E-15 O.OOE-01 O.OOE-01 TE131M 3.50E+OO 4.16E+02 8.58E+OO 4.20E+OO 4.25E+01 6.64E+OO O.OOE-01 O.OOE-01 TE131 2.41E-30 1.08E-30 7.65E-30 3.20E-30 3.35E-29 6.29E-30 0.00E-01 O.OOE-01 TE132 3.52E+01 1.77E+03 5.80E+01 3.75E+01 3.61 E+02 4.14E+01 O.OOE-01 O.OOE-01 1130 2.23E+OO 4.87E+OO 1.92E+OO 5.66E+OO 8.83E+OO 4.79E+02 O.OOE-01 O.OOE-01 I 131 1.17E+03 5.39E+02 1.43E+03 2.04E+03 3.50E+03 6.69E+05 O.OOE-01 O.OOE-01 1132 5.61E-07 3.01E-07 6.00E-07 1.60E-06 2.56E-06 5.61E-05 O.OOE-01 O.OOE-01 1133 9.64E+OO 2.84E+01 1.82E+01 3.16E+01 5.52E+01 4.65E+03 O.OOE-01 O.OOE-01 I 134 4.20E-18 1.02E-20 4.32E-18 1.17E-17 1.87E-17 2.04E-16 O.OOE-01 O.OOE-01 1135 5.36E-02 1.64E-01 5.54E-02 1.45E-01 2.33E-01 9.57E+OO O.OOE-01 O.OOE-01 CS134 2.54E+05 5.43E+03 1.30E+05 3.10E+05 1.00E+05 O.OOE-01 3.33E+04 O.OOE-01 CS136 1.80E+04 2.84E+03 6.33E+03 2.50E+04 1.39E+04 O.OOE-01 1.91E+03 O.OOE-01 CS137 1.53E+05 4.52E+03 1.71E+05 2.33E+05 7.92E+04 O.OOE-01 2.63E+04 O.OOE-01 CS138 4.67E-28 4.02E-33 4.78E-28 9.43E-28 6.93E-28 O.OOE-01 6.85E-29 O.OOE-01 BA139 1.63E-14 9.87E-13 5.57E-13 3.97E-16 3.71E-16 O.OOE-01 2.25E-16 O.OOE-01 BA140 4.25E+01 1.33E+03 6.48E+02 8.14E-01 2.77E-01 O.OOE-01 4.66E-01 O.OOE-01 BA141 9.70E-32 1.35E-39 2.87E-30 2.17E-33 2.02E-33 O.OOE-01 1.23E-33 O.OOE-01 BA142 9.54E-33 O.OOE-01 1.52E-31 1.56E-34 1.32E-34 O.OOE-01 8.82E-35 O.OOE-01 LA140 1.43E-05 3.98E+OO 1.08E-04 5.43E-05 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 LA142 1.64E-17 4.81E-13 1.45E-16 6.59E-17 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CE141 8.86E-03 2.98E+02 1.16E-01 7.81E-02 3.63E-02 O.OOE-01 O.OOE-01 O.OOE-01 CE143 8.13E-05 2.75E+01 9.94E-04 7.35E-01 3.23E-04 O.OOE-01 O.OOE-01 O.OOE-01 CE144 4.44E-01 2.80E+03 8.27E+OO 3.46E+OO 2.05E+OO O.OOE-01 O.OOE-01 O.OOE-01 PR143 1.89E-04 1.67E+01 3.81E-03 1.53E-03 8.82E-04 O.OOE-01 O.OOE-01 O.OOE-01 PR144 9.64E-37 2.73E-42 1.90E-35 7.88E-36 4.44E-36 O.OOE-01 O.OOE-01 O.OOE-01 ND147 1.58E-04 1.27E+01 2.29E-03 2.64E-03 1.55E-03 O.OOE-01 O.OOE-01 0.00E-01 w 187 4.52E-02 4.24E+01 1.55E-01 1.29E-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 NP239 4.77E-06 1.78E+OO 8.81 E-05 8.66E-06 2.70E-05 O.OOE-01 O.OOE-01 O.OOE-01 DAEC ODAM Page 184 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =ADULT PATHWAY= IRRIGATED STORED FEED--MEAT TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN (mrem gaQ/(Ci min} H 3 1.65E+OO 1.65E+OO O.OOE-01 1.65E+OO 1.65E+OO 1.65E+OO 1.65E+OO O.OOE-01 c 14 6.12E+03 6.12E+03 3.06E+04 6.12E+03 6.12E+03 6.12E+03 6.12E+03 O.OOE-01 NA24 3.43E-08 3.43E-08 3.43E-08 3.43E-08 3.43E-08 3.43E-08 3.43E-08 O.OOE-01 p 32 4.37E+03 1.27E+04 1.13E+05 7.03E+03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CR 51 1.68E-01 4.23E+01 O.OOE-01 O.OOE-01 3.71E-02 1.01 E-01 2.23E-01 O.OOE-01 MN 54 4.06E+01 6.51 E+02 O.OOE-01 2.13E+02 6.33E+01 O.OOE-01 O.OOE-01 O.OOE-01 MN 56 5.49E-29 9.88E-27 O.OOE-01 3.09E-28 3.93E-28 O.OOE-01 O.OOE-01 O.OOE-01 FE 55 1.09E+03 2.67E+03 6.75E+03 4.66E+03 O.OOE-01 O.OOE-01 2.60E+03 O.OOE-01 FE 59 5.67E+03 4.93E+04 6.29E+03 1.48E+04 O.OOE-01 O.OOE-01 4.13E+03 O.OOE-01 C058 9.62E+02 8.69E+03 O.OOE-01 4.29E+02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 C060 3.82E+03 3.26E+04 O.OOE-01 1.73E+03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl63 1.48E+04 6.36E+03 4.40E+05 3.05E+04 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 N165 5.45E-27 3.03E-25 9.20E-26 1.20E-26 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 cu 64 2.80E-12 5.08E-10 O.OOE-01 5.96E-12 1.50E-11 O.OOE-01 O.OOE-01 O.OOE-01 ZN 65 1.21E+04 1.69E+04 8.42E+03 2.68E+04 1.79E+04 O.OOE-01 O.OOE-01 O.OOE-01 ZN 69 3.24E-29 7.00E-29 2.44E-28 4.66E-28 3.03E-28 O.OOE-01 O.OOE-01 O.OOE-01 BR 83 3.22E-27 4.64E-27 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 84 3.37E-28 2.64E-33 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 85 2.30E-36 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 86 5.48E+03 2.32E+03 O.OOE-01 1.18E+04 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 88 4.98E-29 1.30E-39 O.OOE-01 9.39E-29 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 89 2.52E-29 2.08E-42 O.OOE-01 3.58E-29 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 SR 89 2.07E+02 1.16E+03 7.22E+03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 90 1.11E+04 1.39E+04 5.55E+05 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 91 1.36E-16 1.60E-14 3.37E-15 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 92 2.02E-28 9.24E-26 4.66E-27 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 90 7.01E-05 2.77E+01 2.61E-03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Y 91M 9.98E-33 7.57E-31 2.58E-31 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 91 7.14E-01 1.47E+04 2.67E+01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 92 5.68E-31 3.41 E-25 1.94E-29 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 93 2.85E-18 3.27E-12 1.03E-16 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 95 9.58E+OO 4.49E+04 4.41E+01 1.42E+01 2.22E+01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 97 4.47E-11 3.03E-05 4.85E-10 9.78E-11 1.48E-10 O.OOE-01 O.OOE-01 O.OOE-01 NB 95 1.64E+01 1.85E+05 5.48E+01 3.05E+01 3.02E+01 O.OOE-01 O.OOE-01 O.OOE-01 M099 4.55E-01 5.54E+OO O.OOE-01 2.39E+OO 5.42E+OO O.OOE-01 O.OOE-01 O.OOE-01 TC 99M 3.58E-24 1.66E-22 9.94E-26 2.81E-25 4.27E-24 O.OOE-01 1.38E-25 O.OOE-01 TC101 3.13E-29 9.61E-42 2.22E-30 3.20E-30 5.76E-29 O.OOE-01 1.63E-30 O.OOE-01 DAEC ODAM Page 185 of 280 Rev.37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =ADULT PATHWAY= IRRIGATED STORED FEED--MEAT TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN mrem al I Ci min RU103 1.08E+03 2.92E+05 2.50E+03 O.OOE-01 9.54E+03 O.OOE-01 O.OOE-01 O.OOE-01 RU105 1.57E-26 2.44E-23 3.99E-26 O.OOE-01 5.16E-25 O.OOE-01 O.OOE-01 O.OOE-01 RU106 8.21 E+03 4.20E+06 6.49E+04 O.OOE-01 1.25E+05 O.OOE-01 O.OOE-01 O.OOE-01 AG110M 8.57E+01 5.89E+04 1.56E+02 1.44E+02 2.84E+02 O.OOE-01 O.OOE-01 O.OOE-01 TE125M 1.16E+03 3.45E+04 8.64E+03 3.13E+03 3.51 E+04 2.60E+03 O.OOE-01 O.OOE-01 TE127M 3.28E+03 9.03E+04 2.69E+04 9.63E+03 1.09E+05 6.88E+03 O.OOE-01 O.OOE-01 TE127 1.0?E-15 3.88E-13 4.92E-15 1.77E-15 2.01E-14 3.65E-15 O.OOE-01 O.OOE-01 TE129M 4.33E+03 1.38E+05 2.74E+04 1.02E+04 1.14E+05 9.40E+03 O.OOE-01 O.OOE-01 TE129 6.50E-28 2.01E-27 2.67E-27 1.00E-27 1.12E-26 2.05E-27 O.OOE-01 O.OOE-01 TE131M 4.40E-03 5.25E-01 1.08E-02 5.28E-03 5.35E-02 8.37E-03 O.OOE-01 O.OOE-01 TE131 6.60E-29 2.96E-29 2.09E-28 8.73E-29 9.15E-28 1.72E-28 O.OOE-01 O.OOE-01 TE132 2.10E+01 1.06E+03 3.45E+01 2.23E+01 2.15E+02 2.47E+01 O.OOE-01 O.OOE-01 1130 1.11E-11 2.43E-11 9.56E-12 2.82E-11 4.40E-11 2.39E-09 O.OOE-01 O.OOE-01 I 131 4.25E+01 1.96E+01 5.19E+01 7.42E+01 1.27E+02 2.43E+04 O.OOE-01 O.OOE-01 1132 1.61E-27 8.65E-28 1.72E-27 4.60E-27 7.33E-27 1.61E-25 O.OOE-01 O.OOE-01 1133 9.35E-07 2.76E-06 1.76E-06 3.0?E-06 5.35E-06 4.51 E-04 O.OOE-01 O.OOE-01 1134 2.04E-28 4.98E-31 2.10E-28 5.71E-28 9.08E-28 9.89E-27 O.OOE-01 O.OOE-01 1135 1.74E-22 5.33E-22 1.80E-22 4.72E-22 7.57E-22 3.11 E-20 O.OOE-01 O.OOE-01 CS134 2.95E+04 6.31 E+02 1.52E+04 3.61 E+04 1.17E+04 O.OOE-01 3.88E+03 O.OOE-01 CS136 8.21E+02 1.30E+02 2.89E+02 1.14E+03 6.35E+02 O.OOE-01 8.70E+01 O.OOE-01 CS137 1.81E+04 5.34E+02 2.02E+04 2.76E+04 9.36E+03 O.OOE-01 3.11E+03 O.OOE-01 CS138 5.53E-29 4.76E-34 5.65E-29 1.12E-28 8.20E-29 O.OOE-01 8.10E-30 O.OOE-01 BA139 1.30E-29 7.88E-28 4.44E-28 3.16E-31 2.96E-31 O.OOE-01 1.79E-31 O.OOE-01 BA140 4.55E+01 1.43E+03 6.94E+02 8.72E-01 2.96E-01 O.OOE-01 4.99E-01 O.OOE-01 BA141 2.75E-31 3.84E-39 8.15E-30 6.16E-33 5.73E-33 O.OOE-01 3.50E-33 O.OOE-01 BA142 2.71E-32 O.OOE-01 4.30E-31 4.42E-34 3.74E-34 O.OOE-01 2.51 E-34 O.OOE-01 LA140 1.20E-07 3.34E-02 9.03E-07 4.55E-07 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 LA142 4.90E-33 1.44E-28 4.33E-32 1.97E-32 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CE141 2.57E-02 8.66E+02 3.35E-01 2.26E-01 1.05E-01 O.OOE-01 O.OOE-01 O.OOE-01 CE143 4.12E-08 1.39E-02 5.04E-07 3.73E-04 1.64E-07 O.OOE-01 O.OOE-01 O.OOE-01 CE144 1.81E+OO 1.14E+04 3.37E+01 1.41E+01 8.36E+OO O.OOE-01 O.OOE-01 O.OOE-01 PR143 2.52E-02 2.22E+03 5.08E-01 2.04E-01 1.18E-01 O.OOE-01 O.OOE-01 O.OOE-01 PR144 3.22E-34 9.11 E-40 6.33E-33 2.63E-33 1.48E-33 O.OOE-01 O.OOE-01 O.OOE-01 ND147 1.20E-02 9.65E+02 1.74E-01 2.01 E-01 1.1 ?E-01 O.OOE-01 O.OOE-01 O.OOE-01 W187 1.52E-07 1.43E-04 5.22E-07 4.36E-07 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 NP239 3.42E-07 1.27E-01 6.32E-06 6.21E-07 1.94E-06 O.OOE-01 O.OOE-01 O.OOE-01 DAEC ODAM Page 186 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =ADULT PATHWAY= ANIMAL DRINKING WATER--MILK TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN (mrem gal)/(Ci min) H 3 5.08E+OO 5.08E+OO O.OOE-01 5.08E+OO 5.08E+OO 5.08E+OO 5.08E+OO O.OOE-01 c 14 6.36E+01 6.36E+01 3.18E+02 6.36E+01 6.36E+01 6.36E+01 6.36E+01 O.OOE-01 NA24 6.64E+01 6.64E+01 6.64E+01 6.64E+01 6.64E+01 6.64E+01 6.64E+01 O.OOE-01 p 32 1.58E+03 4.59E+03 4.08E+04 2.54E+03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CR 51 5.19E-02 1.31 E+01 O.OOE-01 O.OOE-01 1.14E-02 3.10E-02 6.89E-02 O.OOE-01 MN 54 2.03E+OO 3.25E+01 O.OOE-01 1.06E+01 3.16E+OO O.OOE-01 O.OOE-01 O.OOE-01 MN 56 8.55E-08 1.54E-05 O.OOE-01 4.82E-07 6.12E-07 O.OOE-01 O.OOE-01 O.OOE-01 FE 55 4.95E+OO 1.22E+01 3.08E+01 2.12E+01 O.OOE-01 O.OOE-01 1.19E+01 O.OOE-01 FE 59 4.24E+01 3.69E+02 4.71 E+01 1.11 E+02 O.OOE-01 O.OOE-01 3.09E+01 O.OOE-01 co 58 1.53E+01 1.38E+02 O.OOE-01 6.82E+OO O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 C060 4.40E+01 3.75E+02 O.OOE-01 2.00E+01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl63 2.73E+02 1.18E+02 8.13E+03 5.63E+02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl65 2.75E-06 1.53E-04 4.63E-05 6.02E-06 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 cu 64 3.50E-01 6.35E+01 O.OOE-01 7.45E-01 1.88E+OO O.OOE-01 O.OOE-01 O.OOE-01 ZN 65 2.52E+03 3.51 E+03 1.75E+03 5.57E+03 3.73E+03 O.OOE-01 O.OOE-01 O.OOE-01 ZN 69 1.40E-16 3.03E-16 1.05E-15 2.01E-15 1.31E-15 O.OOE-01 O.OOE-01 O.OOE-01 BR 83 1.28E-05 1.84E-05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 84 5.76E-26 4.52E-31 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 85 4.38E-33 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 86 2.55E+03 1.08E+03 O.OOE-01 5.48E+03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 88 7.66E-27 2.00E-37 O.OOE-01 1.44E-26 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 89 4.53E-27 3.74E-40 O.OOE-01 6.44E-27 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 89 6.42E+01 3.59E+02 2.24E+03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 90 1.31E+03 1.63E+03 6.50E+04 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 91 4.76E-02 5.61 E+OO 1.18E+OO O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 92 2.52E-06 1.16E-03 5.84E-05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 90 1.42E-05 5.61 E+OO 5.29E-04 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Y 91M 4.64E-25 3.52E-23 1.20E-23 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 91 3.43E-04 7.07E+OO 1.28E-02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 92 1.62E-10 9.73E-05 5.56E-09 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 93 2.38E-07 2.73E-01 8.61 E-06 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 95 3.01E-04 1.41E+OO 1.39E-03 4.45E-04 6.98E-04 O.OOE-01 O.OOE-01 O.OOE-01 ZR 97 9.68E-07 6.56E-01 1.05E-05 2.12E-06 3.20E-06 O.OOE-01 O.OOE-01 O.OOE-01 NB 95 4.17E-02 4.71E+02 1.39E-01 7.76E-02 7.67E-02 O.OOE-01 O.OOE-01 O.OOE-01 M099 3.43E+01 4.18E+02 O.OOE-01 1.80E+02 4.08E+02 O.OOE-01 O.OOE-01 O.OOE-01 TC 99M 7.34E-03 3.41 E-01 2.04E-04 5.76E-04 8.74E-03 O.OOE-01 2.82E-04 O.OOE-01 TC101 3.92E-28 1.20E-40 2.77E-29 3.99E-29 7.19E-28 O.OOE-01 2.04E-29 O.OOE-01 DAEC ODAM Page 187 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =ADULT PATHWAY= ANIMAL DRINKING WATER--MILK TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN mrem al I Ci min RU103 7.18E-04 1.94E-01 1.67E-03 O.OOE-01 6.36E-03 O.OOE-01 O.OOE-01 O.OOE-01 RU105 2.69E-08 4.16E-05 6.80E-08 O.OOE-01 8.79E-07 O.OOE-01 O.OOE-01 O.OOE-01 RU106 3.24E-03 1.65E+OO 2.56E-02 O.OOE-01 4.94E-02 O.OOE-01 0.00E-01 O.OOE-01 AG110M 4.08E+01 2.80E+04 7.42E+01 6.87E+01 1.35E+02 O.OOE-01 O.OOE-01 O.OOE-01 TE125M 3.27E+OO 9.75E+01 2.44E+01 8.85E+OO 9.93E+01 7.34E+OO O.OOE-01 O.OOE-01 TE127M 7.60E+OO 2.09E+02 6.24E+01 2.23E+01 2.53E+02 1.59E+01 O.OOE-01 O.OOE-01 TE127 5.87E-03 2.14E+OO 2.71 E-02 9.74E-03 1.10E-01 2.01E-02 O.OOE-01 O.OOE-01 TE129M 1.63E+01 5.18E+02 1.03E+02 3.84E+01 4.29E+02 3.53E+01 O.OOE-01 O.OOE-01 TE129 1.37E-14 4.24E-14 5.62E-14 2.11E-14 2.36E-13 4.31E-14 O.OOE-01 O.OOE-01 TE131M 2.12E+OO 2.53E+02 5.20E+OO 2.54E+OO 2.58E+01 4.03E+OO O.OOE-01 0.00E-01 TE131 9.67E-29 4.34E-29 3.06E-28 1.28E-28 1.34E-27 2.52E-28 O.OOE-01 O.OOE-01 TE132 9.25E+OO 4.66E+02 1.52E+01 9.86E+OO 9.49E+01 1.09E+01 O.OOE-01 O.OOE-01 I 130 3.14E+OO 6.86E+OO 2.70E+OO 7.97E+OO 1.24E+01 6.75E+02 O.OOE-01 O.OOE-01 I 131 1.60E+02 7.37E+01 1.95E+02 2.79E+02 4.79E+02 9.16E+04 O.OOE-01 O.OOE-01 I 132 4.12E-06 2.21 E-06 4.40E-06 1.18E-05 1.88E-05 4.12E-04 O.OOE-01 O.OOE-01 1133 8.25E+OO 2.43E+01 1.56E+01 2.71E+01 4.72E+01 3.98E+03 O.OOE-01 O.OOE-01 1134 8.07E-17 1.97E-19 8.31E-17 2.26E-16 3.59E-16 3.91E-15 O.OOE-01 O.OOE-01 1135 1.39E-01 4.25E-01 1.44E-01 3.76E-01 6.04E-01 2.48E+01 O.OOE-01 O.OOE-01 CS134 1.35E+04 2.89E+02 6.95E+03 1.65E+04 5.35E+03 O.OOE-01 1.78E+03 0.00E-01 CS136 1.86E+03 2.94E+02 6.54E+02 2.58E+03 1.44E+03 O.OOE-01 1.97E+02 O.OOE-01 CS137 8.00E+03 2.36E+02 8.92E+03 1.22E+04 4.14E+03 O.OOE-01 1.38E+03 O.OOE-01 CS138 1.46E-26 1.26E-31 1.49E-26 2.95E-26 2.16E-26 O.OOE-01 2.14E-27 O.OOE-01 BA139 2.00E-13 1.21E-11 6.82E-12 4.86E-15 4.54E-15 O.OOE-01 2.76E-15 O.OOE-01 BA140 4.45E+OO 1.40E+02 6.78E+01 8.52E-02 2.90E-02 O.OOE-01 4.88E-02 O.OOE-01 BA141 5.34E-30 7.46E-38 1.58E-28 1.20E-31 1.11E-31 O.OOE-01 6.79E-32 O.OOE-01 BA142 8.97E-31 O.OOE-01 1.43E-29 1.47E-32 1.24E-32 O.OOE-01 8.30E-33 O.OOE-01 LA140 6.69E-06 1.86E+OO 5.02E-05 2.53E-05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 LA142 1.80E-16 5.26E-12 1.59E-15 7.21E-16 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CE141 6.42E-04 2.16E+01 8.36E-03 5.66E-03 2.63E-03 O.OOE-01 O.OOE-01 O.OOE-01 CE143 4.52E-05 1.53E+01 5.53E-04 4.09E-01 1.80E-04 O.OOE-01 O.OOE-01 O.OOE-01 CE144 2.43E-02 1.53E+02 4.53E-01 1.90E-01 1.12E-01 O.OOE-01 O.OOE-01 O.OOE-01 PR143 1.92E-05 1.70E+OO 3.87E-04 1.55E-04 8.96E-05 O.OOE-01 O.OOE-01 O.OOE-01 PR144 5.62E-35 1.59E-40 1.11 E-33 4.60E-34 2.59E-34 O.OOE-01 O.OOE-01 O.OOE-01 ND147 1.79E-05 1.43E+OO 2.58E-04 2.99E-04 1.75E-04 O.OOE-01 O.OOE-01 O.OOE-01 w 187 3.40E-02 3.18E+01 1.16E-01 9.71E-02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 NP239 1.65E-06 6.15E-01 3.05E-05 3.00E-06 9.35E-06 O.OOE-01 O.OOE-01 O.OOE-01 DAEC ODAM Page 188 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =ADULT PATHWAY= ANIMAL DRINKING WATER--MEAT TOTAL BODY GI-LU BONE LIVER KIDNEY THYROID LUNG SKIN (mrem gal)/(Ci min) H 3 1.65E+OO 1.65E+OO O.OOE-01 1.65E+OO 1.65E+OO 1.65E+OO 1.65E+OO O.OOE-01 c 14 4.86E+01 4.86E+01 2.43E+02 4.86E+01 4.86E+01 4.86E+01 4.86E+01 O.OOE-01 NA24 3.33E-08 3.33E-08 3.33E-08 3.33E-08 3.33E-08 3.33E-08 3.33E-08 O.OOE-01 p 32 3.58E+02 1.04E+03 9.27E+03 5.77E+02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CR 51 1.07E-02 2.68E+OO O.OOE-01 O.OOE-01 2.35E-03 6.37E-03 1.42E-02 O.OOE-01 MN 54 1.84E+OO 2.96E+01 O.OOE-01 9.65E+OO 2.87E+OO O.OOE-01 O.OOE-01 O.OOE-01 MN 56 3.01E-28 5.42E-26 O.OOE-01 1.70E-27 2.16E-27 O.OOE-01 O.OOE-01 O.OOE-01 FE 55 4.82E+01 1.19E+02 2.99E+02 2.07E+02 O.OOE-01 O.OOE-01 1.15E+02 O.OOE-01 FE 59 3.16E+02 2.75E+03.

3.51E+02 8.24E+02 O.OOE-01 O.OOE-01 2.30E+02 O.OOE-01 co 58 4.93E+01 4.45E+02 O.OOE-01 2.20E+01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 C060 1.68E+02 1.43E+03 O.OOE-01 7.62E+01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl63 6.37E+02 2.75E+02 1.90E+04 1.32E+03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl65 3.05E-26 1.69E-24 5.14E-25 6.67E-26 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 cu 64 3.20E-12 5.81E-10 O.OOE-01 6.82E-12 1.72E-11 O.OOE-01 O.OOE-01 O.OOE-01 ZN 65 5.44E+02 7.59E+02 3.78E+02 1.20E+03 8.06E+02 O.OOE-01 O.OOE-01 O.OOE-01 ZN 69 4.78E-28 1.03E-27 3.60E-27 6.88E-27 4.47E-27 O.OOE-01 O.OOE-01 O.OOE-01 BR 83 1.89E-26 2.72E-26 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 84 8.86E-27 6.96E-32 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 85 6.73E-34 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 86 4.00E+02 1.69E+02 O.OOE-01 8.59E+02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 88 2.34E-27 6.10E-38 O.OOE-01 4.41 E-27 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 89 1.38E-27 1.14E-40 O.OOE-01 1.97E-27 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 89 1.11E+01 6.21E+01 3.87E+02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 90 2.89E+02 3.62E+02 1.44E+04 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 91 2.06E-16 2.42E-14 5.09E-15 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 92 1.04E-27 4.78E-25 2.41 E-26 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 90 1.82E-05 7.18E+OO 6.77E-04 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Y 91M 1.69E-31 1.28E-29 4.37E-30 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 91 3.77E-02 7.77E+02 1.41E+OO O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 92 2.26E-30 1.35E-24 7.73E-29 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 93 4.07E-18 4.67E-12 1.47E-16 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 95 4.99E-01 2.33E+03 2.30E+OO 7.37E-01 1.16E+OO O.OOE-01 O.OOE-01 O.OOE-01 ZR 97 3.89E-11 2.63E-05 4.21E-10 8.50E-11 1.28E-10 O.OOE-01 O.OOE-01 O.OOE-01 NB 95 9.69E-01 1.09E+04 3.24E+OO 1.80E+OO 1.78E+OO O.OOE-01 O.OOE-01 O.OOE-01 M099 1.15E-01 1.40E+OO O.OOE-01 6.06E-01 1.37E+OO O.OOE-01 O.OOE-01 O.OOE-01 TC 99M 8.45E-24 3.93E-22 2.35E-25 6.64E-25 1.01 E-23 O.OOE-01 3.25E-25 O.OOE-01 TC101 1.85E-27 5.68E-40 1.31E-28 1.89E-28 3.40E-27 O.OOE-01 9.65E-29 O.OOE-01 DAEC ODAM Page 189 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =ADULT PATHWAY= ANIMAL DRINKING WATER--MEAT TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN mrem al I Ci min RU103 6.18E+01 1.67E+04 1.43E+02 O.OOE-01 5.47E+02 O.OOE-01 O.OOE-01 O.OOE-01 RU105 5.03E-26 7.79E-23 1.27E-25 O.OOE-01 1.65E-24 O.OOE-01 O.OOE-01 O.OOE-01 RU106 3.70E+02 1.89E+05 2.92E+03 O.OOE-01 5.64E+03 O.OOE-01 O.OOE-01 O.OOE-01 AG110M 3.90E+OO 2.68E+03 7.10E+OO 6.57E+OO 1.29E+01 O.OOE-01 O.OOE-01 O.OOE-01 TE125M 6.01E+01 1.79E+03 4.48E+02 1.62E+02 1.82E+03 1.35E+02 O.OOE-01 O.OOE-01 TE127M 1.54E+02 4.25E+03 1.27E+03 4.53E+02 5.14E+03 3.24E+02 O.OOE-01 O.OOE-01 TE127 1.63E-15 5.95E-13 7.54E-15 2.71 E-15 3.07E-14 5.58E-15 O.OOE-01 O.OOE-01 TE129M 2.56E+02 8.13E+03 1.62E+03 6.03E+02 6.74E+03 5.55E+02 O.OOE-01 O.OOE-01 TE129 7.83E-27 2.43E-26 3.21E-26 1.21 E-26 1.35E-25 2.47E-26 O.OOE-01 O.OOE-01 TE131M 2.23E-03 2.65E-01 5.46E-03 2.67E-03 2.71E-02 4.23E-03 O.OOE-01 O.OOE-01 TE131 2.20E-27 9.87E-28 6.97E-27 2.91E-27 3.06E-26 5.73E-27 O.OOE-01 O.OOE-01 TE132 4.59E+OO 2.31E+02 7.57E+OO 4.89E+OO 4.71E+01 5.40E+OO O.OOE-01 O.OOE-01 1130 1.31E-11 2.85E-11 1.12E-11 3.31 E-11 5.17E-11 2.81E-09 O.OOE-01 O.OOE-01 I 131 4.85E+OO 2.23E+OO 5.91 E+OO 8.46E+OO 1.45E+01 2.77E+03 O.OOE-01 O.OOE-01 1132 9.85E-27 5.29E-27 1.05E-26 2.81E-26 4.48E-26 9.85E-25 O.OOE-01 O.OOE-01 1133 6.67E-07 1.96E-06 1.26E-06 2.19E-06 3.82E-06 3.21 E-04 O.OOE-01 O.OOE-01 1134 3.27E-27 7.97E-30 3.36E-27 9.14E-27 1.45E-26 1.58E-25 O.OOE-01 O.OOE-01 1135 3.76E-22 1.15E-21 3.90E-22 1.02E-21 1.64E-21 6.73E-20 O.OOE-01 O.OOE-01 CS134 1.31E+03 2.81E+01 6.74E+02 1.60E+03 5.19E+02 O.OOE-01 1.72E+02 O.OOE-01 CS136 7.08E+01 1.12E+01 2.49E+01 9.83E+01 5.47E+01 O.OOE-01 7.50E+OO O.OOE-01 CS137 7.87E+02 2.33E+01 8.79E+02 1.20E+03 4.08E+02 O.OOE-01 1.36E+02 O.OOE-01 CS138 1.44E-27 1.24E-32 1.47E-27 2.90E-27 2.13E-27 O.OOE-01 2.11 E-28 O.OOE-01 BA139 1.33E-28 8.04E-27 4.53E-27 3.23E-30 3.02E-30 O.OOE-01 1.83E-30 O.OOE-01 BA140 3.97E+OO 1.25E+02 6.05E+01 7.60E-02 2.58E-02 O.OOE-01 4.35E-02 O.OOE-01 BA141 1.26E-29 1.76E-37 3.74E-28 2.83E-31 2.63E-31 O.OOE-01 1.61 E-31 O.OOE-01 BA142 2.12E-30 O.OOE-01 3.37E-29 3.47E-32 2.93E-32 O.OOE-01 1.96E-32 O.OOE-01 LA140 4.67E-08 1.30E-02 3.51 E-07 1.77E-07 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 LA142 4.47E-32 1.31 E-27 3.94E-31 1.79E-31 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CE141 1.55E-03 5.23E+01 2.02E-02 1.37E-02 6.35E-03 O.OOE-01 O.OOE-01 O.OOE-01 CE143 1.91 E-08 6.45E-03 2.34E-07 1.73E-04 7.60E-08 O.OOE-01 O.OOE-01 O.OOE-01 CE144 8.26E-02 5.20E+02 1.54E+OO 6.43E-01 3.82E-01 O.OOE-01 O.OOE-01 O.OOE-01 PR143 2.13E-03 1.88E+02 4.30E-02 1.72E-02 9.95E-03 O.OOE-01 O.OOE-01 O.OOE-01 PR144 1.56E-32 4.42E-38 3.08E-31 1.28E-31 7.20E-32 O.OOE-01 O.OOE-01 O.OOE-01 ND147 1.13E-03 9.09E+01 1.64E-02 1.89E-02 1.11 E-02 O.OOE-01 O.OOE-01 O.OOE-01 w 187 9.54E-08 8.94E-05 3.26E-07 2.73E-07 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 NP239 9.88E-08 3.67E-02 1.82E-06 1.79E-07 5.59E-07 O.OOE-01 O.OOE-01 O.OOE-01 DAEC ODAM Page 190 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =ADULT PATHWAY= RIVER SHORELINE DEPOSITS TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN (mrem gaQ!(Ci min} H 3 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 c 14 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 NA24 1.88E+OO 1.88E+OO 1.88E+OO 1.88E+OO 1.88E+OO 1.88E+OO 1.88E+OO 2.18E+OO p 32 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CR 51 7.33E-01 7.33E-01 7.33E-01 7.33E-01 7.33E-01 7.33E-01 7.33E"01 8.66E-01 MN 54 2.18E+02 2.18E+02 2.18E+02 2.18E+02 2.18E+02 2.18E+02 2.18E+02 2.56E+02 MN 56 1.38E-01 1.38E-01 1.38E-01 1.38E-01 1.38E-01 1.38E-01 1.38E-01 1.63E-01 FE 55 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 FE 59 4.29E+01 4.29E+01 4.29E+01 4.29E+01 4.29E+01 4.29E+01 4.29E+01 5.04E+01 C058 5.98E+01 5.98E+01 5.98E+01 5.98E+01 5.98E+01 5.98E+01 5.98E+01 7.01E+01 C060 3.38E+03 3.38E+03 3.38E+03 3.38E+03 3.38E+03 3.38E+03 3.38E+03 3.98E+03 Nl63 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl65 4.55E-02 4.55E-02 4.55E-02 4.55E-02 4.55E-02 4.55E-02 4.55E-02 5.29E-02 cu 64 9.48E-02 9.48E-02 9.48E-02 9.48E-02 9.48E-02 9.48E-02 9.48E-02 1.0?E-01 ZN 65 1.17E+02 1.17E+02 1.17E+02 1.17E+02 1.17E+02 1.17E+02 1.17E+02 1.35E+02 ZN 69 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 83 7.46E-04 7.46E-04 7.46E-04 7.46E-04 7.46E-04 7.46E-04 7.46E-04 1.08E-03 BR 84 2.80E-02 2.80E-02 2.80E-02 2.80E-02 2.80E-02 2.80E-02 2.80E-02 3.27E-02 BR 85 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 86 1.42E+OO 1.42E+OO 1.42E+OO 1.42E+OO 1.42E+OO 1.42E+OO 1.42E+OO 1.62E+OO RB 88 4.14E-03 4.14E-03 4.14E-03 4.14E-03 4.14E-03 4.14E-03 4.14E-03 4.73E-03 RB 89 1.46E-02 1.46E-02 1.46E-02 1.46E-02 1.46E-02 1.46E-02 1.46E-02 1.75E-02 SR 89 3.40E-03 3.40E-03 3.40E-03 3.40E-03 3.40E-03 3.40E-03 3.40E-03 3.95E-03 SR 90 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 SR 91 3.35E-01 3.35E-01 3.35E-01 3.35E-01 3.35E-01 3.35E-01 3.35E-01 3.92E-01 SR 92 1.19E-01 1.19E-01 1.19E-01 1.19E-01 1.19E-01 1.19E-01 1.19E-01 1.33E-01 y 90 7.08E-04 7.08E-04 7.08E-04 7.08E-04 7.08E-04 7.08E-04 7.08E-04 8.36E-04 Y 91M 1.45E-02 1.45E-02 1.45E-02 1.45E-02 1.45E-02 1.45E-02 1.45E-02 1.68E-02 y 91 1.69E-01 1.69E-01 1.69E-01 1.69E-01 1.69E-01 1.69E-01 1.69E-01 1.90E-01 y 92 2.80E-02 2.80E-02 2.80E-02 2.80E-02 2.80E-02 2.80E-02 2.80E-02 3.32E-02 y 93 2.86E-02 2.86E-02 2.86E-02 2.86E-02 2.86E-02 2.86E-02 2.86E-02 3.92E-02 ZR 95 3.86E+01 3.86E+01 3.86E+01 3.86E+01 3.86E+01 3.86E+01 3.86E+01 4.48E+01 ZR 97 4.64E-01 4.64E-01 4.64E-01 4.64E-01 4.64E-01 4.64E-01 4.64E-01 5.40E-01 NB 95 2.16E+01 2.16E+01 2.16E+01 2.16E+01 2.16E+01 2.16E+01 2.16E+01 2.54E+01 MO 99 6.28E-01 6.28E-01 6.28E-01 6.28E-01 6.28E-01 6.28E-01 6.28E-01 7.27E-01 TC 99M 2.87E-02 2.87E-02 2.87E-02 2.87E-02 2.87E-02 2.87E-02 2.87E-02 3.28E-02 TC101 2.39E-03 2.39E-03 2.39E-03 2.39E-03 2.39E-03 2.39E-03 2.39E-03 2.66E-03 DAEC ODAM Page 191 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =ADULT PATHWAY= RIVER SHORELINE DEPOSITS TOTAL BODY GI-LU BONE LIVER KIDNEY THYROID LUNG SKIN (mrem gal)/(Ci min) RU103 1.70E+01 1.70E+01 1.70E+01 1.70E+01 1.70E+01 1.70E+01 1.70E+01 1.99E+01 RU105 9.86E-02 9.86E-02 9.86E-02 9.86E-02 9.86E-02 9.86E-02 9.86E-02 1.12E-01 RU106 6.65E+01 6.65E+01 6.65E+01 6.65E+01 6.65E+01 6.65E+01 6.65E+01 7.97E+01 AG110M 5.43E+02 5.43E+02 5.43E+02 5.43E+02 5.43E+02 5.43E+02 5.43E+02 6.34E+02 TE125M 2.45E-01 2.45E-01 2.45E-01 2.45E-01 2.45E-01 2.45E-01 2.45E-01 3.36E-01 TE127M 1.44E-02 1.44E-02 1.44E-02 1.44E-02 1.44E-02 1.44E-02 1.44E-02 1.71E-02 TE127 4.65E-04 4.65E-04 4.65E-04 4.65E-04 4.65E-04 4.65E-04 4.65E-04 5.12E-04 TE129M 3.11E+OO 3.11E+OO 3.11E+OO 3.11E+OO 3.11E+OO 3.11E+OO 3.11E+OO 3.64E+OO TE129 3.89E-03 3.89E-03 3.89E-03 3.89E-03 3.89E-03 3.89E-03 3.89E-03 4.60E-03 TE131M 1.26E+OO 1.26E+OO 1.26E+OO 1.26E+OO 1.26E+OO 1.26E+OO 1.26E+OO 1.49E+OO TE131 3.90E-03 3.90E-03 3.90E-03 3.90E-03 3.90E-03 3.90E-03 3.90E-03 4.61 E+OO TE132 6.67E-01 6.67E-01 6.67E-01 6.67E-01 6.67E-01 6.67E-01 6.67E-01 7.85E-01 I 130 8.62E-01 8.62E-01 8.62E-01 8.62E-01 8.62E-01 8.62E-01 8.62E-01 1.05E+OO I 131 2.71 E+OO 2.71 E+OO 2.71 E+OO 2.71E+OO 2.71 E+OO 2.71 E+OO 2.71E+OO 3.29E+OO 1132 1.90E-01 1.90E-01 1.90E-01 1.90E-01 1.90E-01 1.90E-01 1.90E-01 2.24E-01 I 133 3.85E-01 3.85E-01 3.85E-01 3.85E-01 3.85E-01 3.85E-01 3.85E-01 4.68E-01 1134 6.49E-02 6.49E-02 6.49E-02 6.49E-02 6.49E-02 6.49E-02 6.49E-02 7.71E-02 1135 3.93E-01 3.93E-01 3.93E-01 3.93E-01 3.93E-01 3.93E-01 3.93E-01 4.58E-01 CS134 1.08E+03 1.08E+03 1.08E+03 1.08E+03 1.08E+03 1.08E+03 1.08E+03 1.26E+03 CS136 2.37E+01 2.37E+01 2.37E+01 2.37E+01 2.37E+01 2.37E+01 2.37E+01 2.68E+01 CS137 1.62E+03 1.62E+03 1.62E+03 1.62E+03 1.62E+03 1.62E+03 1.62E+03 1.89E+03 CS138 4.98E-02 4.98E-02 4.98E-02 4.98E-02 4.98E-02 4.98E-02 4.98E-02 5.69E-02 BA139 1.58E-02 1.58E-02 1.58E-02 1.58E-02 1.58E-02 1.58E-02 1.58E-02 1.77E-02 BA140 3.23E+OO 3.23E+OO 3.23E+OO 3.23E+OO 3.23E+OO 3.23E+OO 3.23E+OO 3.70E+OO BA141 5.24E-03 5.24E-03 5.24E-03 5.24E-03 5.24E-03 5.24E-03 5.24E-03 5.97E-03 BA142 4.79E-03 4.79E-03 4.79E-03 4.79E-03 4.79E-03 4.79E-03 4.79E-03 5.46E-03 LA140 3.03E+OO 3.03E+OO 3.03E+OO 3.03E+OO 3.03E+OO 3.03E+OO 3.03E+OO 3.43E+OO LA142 1.11E-01 1.11E-01 1.11E-01 1.11E-01 1.11E-01 1.11E-01 1.11E-01 1.33E-01 CE141 2.15E+OO 2.15E+OO 2.15E+OO 2.15E+OO 2.15E+OO 2.15E+OO 2.15E+OO 2.42E+OO CE143 3.65E-01 3.65E-01 3.65E-01 3.65E-01 3.65E-01 3.65E-01 3.65E-01 4.15E-01 CE144 1.10E+01 1.10E+01 1.10E+01 1.10E+01 1.10E+01 1.10E+01 1.10E+01 1.27E+01 PR143 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 PR144 2.27E-04 2.27E-04 2.27E-04 2.27E-04 2.27E-04 2.27E-04 2.27E-04 2.61 E-04 ND147 1.34E+OO 1.34E+OO 1.34E+OO 1.34E+OO 1.34E+OO 1.34E+OO 1.34E+OO 1.60E+OO W187 3.71E-01 3.71 E-01 3.71 E-01 3.71 E-01 3.71 E-01 3.71E-01 3.71 E-01 4.31 E-01 NP239 2.70E-01 2.70E-01 2.70E-01 2.70E-01 2.70E-01 2.70E-01 2.70E-01 3.12E-01 DAEC ODAM Page 192 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =ADULT PATHWAY= SWIMMING TOTAL BODY GI-LU BONE LIVER KIDNEY THYROID LUNG SKIN (mrem gaQ/(Ci min) H 3 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 c 14 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 NA24 3.12E+01 3.12E+01 3.12E+01 3.12E+01 3.12E+01 3.12E+01 3.12E+01 O.OOE-01 p 32 2.57E-02 2.57E-02 2.57E-02 2.57E-02 2.57E-02 2.57E-02 2.57E-02 O.OOE-01 CR 51 2.09E-01 2.09E-01 2.09E-01 2.09E-01 2.09E-01 2.09E-01 2.09E-01 O.OOE-01 MN 54 6.02E+OO 6.02E+OO 6.02E+OO 6.02E+OO 6.02E+OO 6.02E+OO 6.02E+OO O.OOE-01 MN 56 1.25E+01 1.25E+01 1.25E+01 1.25E+01 1.25E+01 1.25E+01 1.25E+01 O.OOE-01 FE 55 2.57E-04 2.57E-04 2.57E-04 2.57E-04 2.57E-04 2.57E-04 2.57E-04 O.OOE-01 FE 59 8.83E+OO 8.83E+OO 8.83E+OO 8.83E+OO 8.83E+OO 8.83E+OO 8.83E+OO O.OOE-01 co 58 7.23E+OO 7.23E+OO 7.23E+OO 7.23E+OO 7.23E+OO 7.23E+OO 7.23E+OO O.OOE-01 C060 1.85E+01 1.85E+01 1.85E+01 1.85E+01 1.85E+01 1.85E+01 1.85E+01 O.OOE-01 Nl63 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl65 3.90E+OO 3.90E+OO 3.90E+OO 3.90E+OO 3.90E+OO 3.90E+OO 3.90E+OO O.OOE-01 cu 64 1.48E+OO 1.48E+OO 1.48E+OO 1.48E+OO 1.48E+OO 1.48E+OO 1.48E+OO O.OOE-01 ZN 65 4.42E+OO 4.42E+OO 4.42E+OO 4.42E+OO 4.42E+OO 4.42E+OO 4.42E+OO O.OOE-01 ZN 69 5.97E-03 5.97E-03 5.97E-03 5.97E-03 5.97E-03 5.97E-03 5.97E-03 O.OOE-01 BR 83 6.63E-02 6.63E-02 6.63E-02 6.63E-02 6.63E-02 6.63E-02 6.63E-02 O.OOE-01 BR 84 1.23E+01 1.23E+01 1.23E+01 1.23E+01 1.23E+01 1.23E+01 1.23E+01 O.OOE-01 BR 85 1.32E-02 1.32E-02 1.32E-02 1.32E-02 1.32E-02 1.32E-02 1.32E-02 O.OOE-01 RB 86 6.82E-01 6.82E-01 6.82E-01 6.82E-01 6.82E-01 6.82E-01 6.82E-01 O.OOE-01 RB 88 3.82E+OO 3.82E+OO 3.82E+OO 3.82E+OO 3.82E+OO 3.82E+OO 3.82E+OO O.OOE-01 RB 89 1.38E+01 1.38E+01 1.38E+01 1.38E+01 1.38E+01 1.38E+01 1.38E+01 O.OOE-01 SR 89 1.85E-02 1.85E-02 1.85E-02 1.85E-02 1.85E-02 1.85E-02 1.85E-02 O.OOE-01 SR 90 2.17E-03 2.17E-03 2.17E-03 2.17E-03 2.17E-03 2.17E-03 2.17E-03 O.OOE-01 SR 91 7.57E+OO 7.57E+OO 7.57E+OO 7.57E+OO 7.57E+OO 7.57E+OO 7.57E+OO O.OOE-01 SR 92 1.02E+01 1.02E+01 1.02E+01 1.02E+01 1.02E+01 1.02E+01 1.02E+01 O.OOE-01 y 90 5.21E-02 5.21E-02 5.21 E-02 5.21E-02 5.21E-02 5.21 E-02 5.21E-02 O.OOE-01 Y 91M 3.69E+OO 3.69E+OO 3.69E+OO 3.69E+OO 3.69E+OO 3.69E+OO 3.69E+OO O.OOE-01 y 91 2.69E-02 2.69E-02 2.69E-02 2.69E-02 2.69E-02 2.69E-02 2.69E-02 O.OOE-01 y 92 1.81E+OO 1.81E+OO 1.81E+OO 1.81E+OO 1.81E+OO 1.81E+OO 1.81E+OO O.OOE-01 y 93 7.57E-01 7.57E-01 7.57E-01 7.57E-01 7.57E-01 7.57E-01 7.57E-01 O.OOE-01 ZR 95 6.02E+OO 6.02E+OO 6.02E+OO 6.02E+OO 6.02E+OO 6.02E+OO 6.02E+OO O.OOE-01 ZR 97 6.00E+OO 6.00E+OO 6.00E+OO 6.00E+OO 6.00E+OO 6.00E+OO 6.00E+OO O.OOE-01 NB 95 5.62E+OO 5.62E+OO 5.62E+OO 5.62E+OO 5.62E+OO 5.62E+OO 5.62E+OO O.OOE-01 MO 99 1.88E+OO 1.88E+OO 1.88E+OO 1.88E+OO 1.88E+OO 1.88E+OO 1.88E+OO O.OOE-01 TC 99M 9.52E-01 9.52E-01 9.52E-01 9.52E-01 9.52E-01 9.52E-01 9.52E-01 O.OOE-01 TC101 2.04E+OO 2.04E+OO 2.04E+OO 2.04E+OO 2.04E+OO 2.04E+OO 2.04E+OO O.OOE-01 DAEC ODAM Page 193 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =ADULT PATHWAY= SWIMMING TOTAL BODY GI-LU BONE LIVER KIDNEY THYROID LUNG SKIN {mrem gal}/{Ci min) RU103 3.57E+OO 3.57E+OO 3.57E+OO 3.57E+OO 3.57E+OO 3.57E+OO 3.57E+OO O.OOE-01 RU105 4.74E+OO 4.74E+OO 4.74E+OO 4.74E+OO 4.74E+OO 4.74E+OO 4.74E+OO O.OOE-01 RU106 1.52E+OO 1.52E+OO 1.52E+OO 1.52E+OO 1.52E+OO 1.52E+OO 1.52E+OO O.OOE-01 AG110M 1.97E+01 1.97E+01 1.97E+01 1.97E+01 1.97E+01 1.97E+01 1.97E+01 O.OOE-01 TE125M 1.48E-02 1.48E-02 1.48E-02 1.48E-02 1.48E-02 1.48E-02 1.48E-02 O.OOE-01 TE127M 1.04E-03 1.04E-03 1.04E-03 1.04E-03 1.04E-03 1.04E-03 1.04E-03 O.OOE-01 TE127 1.12E-02 1.12E-02 1.12E-02 1.12E-02 1.12E-02 1.12E-02 1.12E-02 O.OOE-01 TE129M 8.43E-01 8.43E-01 8.43E-01 8.43E-01 8.43E-01 8.43E-01 8.43E-01 O.OOE-01 TE129 7.19E-01 7.19E-01 7.19E-01 7.19E-01 7.19E-01 7.19E-01 7.19E-01 O.OOE-01 TE131M 8.81 E+OO 8.81 E+OO 8.81 E+OO 8.81E+OO 8.81E+OO 8.81E+OO 8.81 E+OO O.OOE-01 TE131 2.52E+OO 2.52E+OO 2.52E+OO 2.52E+OO 2.52E+OO 2.52E+OO 2.52E+OO O.OOE-01 TE132 1.60E+OO 1.60E+OO 1.60E+OO 1.60E+OO 1.60E+OO 1.60E+OO 1.60E+OO O.OOE-01 I 130 1.56E+01 1.56E+01 1.56E+01 1.56E+01 1.56E+01 1.56E+01 1.56E+01 O.OOE-01 I 131 3.13E+OO 3.13E+OO 3.13E+OO 3.13E+OO 3.13E+OO 3.13E+OO 3.13E+OO O.OOE-01 1132 1.71E+01 1.71E+01 1.71E+01 1.71E+01 1.71E+01 1.71E+01 1.71E+01 O.OOE-01 1133 3.84E+OO 3.84E+OO 3.84E+OO 3.84E+OO 3.84E+OO 3.84E+OO 3.84E+OO O.OOE-01 I 134 1.56E+01 1.56E+01 1.56E+01 1.56E+01 1.56E+01 1.56E+01 1.56E+01 O.OOE-01 I 135 1.31 E+01 1.31 E+01 1.31 E+01 1.31E+01 1.31E+01 1.31 E+01 1.31 E+01 O.OOE-01 CS134 1.16E+01 1.16E+01 1.16E+01 1.16E+01 1.16E+01 1.16E+01 1.16E+01 O.OOE-01 CS136 1.65E+01 1.65E+01 1.65E+01 1.65E+01 1.65E+01 1.65E+01 1.65E+01 O.OOE-01 CS137 4.01E+OO 4.01 E+OO 4.01 E+OO 4.01 E+OO 4.01E+OO 4.01E+OO 4.01E+OO O.OOE-01 CS138 1.41E+01 1.41 E+01 1.41E+01 1.41E+01 1.41E+01 1.41E+01 1.41E+01 O.OOE-01 BA139 2.94E-01 2.94E-01 2.94E-01 2.94E-01 2.94E-01 2.94E-01 2.94E-01 O.OOE-01 BA140 1.97E+OO 1.97E+OO 1.97E+OO 1.97E+OO 1.97E+OO 1.97E+OO 1.97E+OO O.OOE-01 BA141 3.52E+OO 3.52E+OO 3.52E+OO 3.52E+OO 3.52E+OO 3.52E+OO 3.52E+OO O.OOE-01 BA142 5.99E+OO 5.99E+OO 5.99E+OO 5.99E+OO 5.99E+OO 5.99E+OO 5.99E+OO O.OOE-01 LA140 1.64E+01 1.64E+01 1.64E+01 1.64E+01 1.64E+01 1.64E+01 1.64E+01 O.OOE-01 LA142 1.73E+01 1.73E+01 1.73E+01 1.73E+01 1.73E+01 1.73E+01 1.73E+01 O.OOE-01 CE141 5.22E-01 5.22E-01 5.22E-01 5.22E-01 5.22E-01 5.22E-01 5.22E-01 O.OOE-01 CE143 2.28E+OO 2.28E+OO 2.28E+OO 2.28E+OO 2.28E+OO 2.28E+OO 2.28E+OO O.OOE-01 CE144 3.45E-01 3.45E-01 3.45E-01 3.45E-01 3.45E-01 3.45E-01 3.45E-01 O.OOE-01 PR143 6.42E-03 6.42E-03 6.42E-03 6.42E-03 6.42E-03 6.42E-03 6.42E-03 O.OOE-01 PR144 1.??E-01 1.??E-01 1.??E-01 1.??E-01 1.??E-01 1.??E-01 1.??E-01 O.OOE-01 ND147 1.12E+OO 1.12E+OO 1.12E+OO 1.12E+OO 1.12E+OO 1.12E+OO 1.12E+OO O.OOE-01 W187 3.32E+OO 3.32E+OO 3.32E+OO 3.32E+OO 3.32E+OO 3.32E+OO 3.32E+OO O.OOE-01 NP239 9.62E-01 9.62E-01 9.62E-01 9.62E-01 9.62E-01 9.62E-01 9.62E-01 O.OOE-01 DAEC ODAM Page 194 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDE$

IN EFFLUENT WATER AGE =ADULT PATHWAY= BOATING TOTAL BODY GI-LU BONE LIVER KIDNEY THYROID LUNG SKIN {mrem gaQ/{Ci min} H 3 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 c 14 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 NA24 5.65E+01 5.65E+01 5.65E+01 5.65E+01 5.65E+01 5.65E+01 5.65E+01 O.OOE-01 p 32 4.66E-02 4.66E-02 4.66E-02 4.66E-02 4.66E-02 4.66E-02 4.66E-02 O.OOE-01 CR 51 3.78E-01 3.78E-01 3.78E-01 3.78E-01 3.78E-01 3.78E-01 3.78E-01 O.OOE-01 MN 54 1.09E+01 1.09E+01 1.09E+01 1.09E+01 1.09E+01 1.09E+01 1.09E+01 O.OOE-01 MN 56 2.27E+01 2.27E+01 2.27E+01 2.27E+01 2.27E+01 2.27E+01 2.27E+01 O.OOE-01 FE 55 4.66E-04 4.66E-04 4.66E-04 4.66E-04 4.66E-04 4.66E-04 4.66E-04 O.OOE-01 FE 59 1.60E+01 1.60E+01 1.60E+01 1.60E+01 1.60E+01 1.60E+01 1.60E+01 O.OOE-01 C058 1.31 E+01 1.31E+01 1.31E+01 1.31 E+01 1.31E+01 1.31 E+01 1.31E+01 O.OOE-01 co 60 3.35E+01 3.35E+01 3.35E+01 3.35E+01 3.35E+01 3.35E+01 3.35E+01 O.OOE-01 Nl63 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl65 7.08E+OO 7.08E+OO 7.08E+OO 7.08E+OO 7.08E+OO 7.08E+OO 7.08E+OO O.OOE-01 cu 64 2.68E+OO 2.68E+OO 2.68E+OO 2.68E+OO 2.68E+OO 2.68E+OO 2.68E+OO O.OOE-01 ZN 65 8.00E+OO 8.00E+OO 8.00E+OO 8.00E+OO 8.00E+OO 8.00E+OO 8.00E+OO O.OOE-01 ZN 69 1.08E-02 1.08E-02 1.08E-02 1.08E-02 1.08E-02 1.08E-02 1.08E-02 O.OOE-01 BR 83 1.20E-01 1.20E-01 1.20E-01 1.20E-01 1.20E-01 1.20E-01 1.20E-01 O.OOE-01 BR 84 2.24E+01 2.24E+01 2.24E+01 2.24E+01 2.24E+01 2.24E+01 2.24E+01 O.OOE-01 BR 85 2.39E-02 2.39E-02 2.39E-02 2.39E-02 2.39E-02 2.39E-02 2.39E-02 O.OOE-01 RB 86 1.24E+OO 1.24E+OO 1.24E+OO 1.24E+OO 1.24E+OO 1.24E+OO 1.24E+OO O.OOE-01 RB 88 6.92E+OO 6.92E+OO 6.92E+OO 6.92E+OO 6.92E+OO 6.92E+OO 6.92E+OO O.OOE-01 RB 89 2.49E+01 2.49E+01 2.49E+01 2.49E+01 2.49E+01 2.49E+01 2.49E+01 O.OOE-01 SR 89 3.35E-02 3.35E-02 3.35E-02 3.35E-02 3.35E-02 3.35E-02 3.35E-02 O.OOE-01 SR 90 3.93E-03 3.93E-03 3.93E-03 3.93E-03 3.93E-03 3.93E-03 3.93E-03 O.OOE-01 SR 91 1.37E+01 1.37E+01 1.37E+01 1.37E+01 1.37E+01 1.37E+01 1.37E+01 O.OOE-01 SR 92 1.84E+01 1.84E+01 1.84E+01 1.84E+01 1.84E+01 1.84E+01 1.84E+01 O.OOE-01 y 90 9.45E-02 9.45E-02 9.45E-02 9.45E-02 9.45E-02 9.45E-02 9.45E-02 O.OOE-01 Y 91M 6.69E+OO 6.69E+OO 6.69E+OO 6.69E+OO 6.69E+OO 6.69E+OO 6.69E+OO O.OOE-01 y 91 4.87E-02 4.87E-02 4.87E-02 4.87E-02 4.87E-02 4.87E-02 4.87E-02 O.OOE-01 y 92 3.28E+OO 3.28E+OO 3.28E+OO 3.28E+OO 3.28E+OO 3.28E+OO 3.28E+OO O.OOE-01 y 93 1.37E+OO 1.37E+OO 1.37E+OO 1.37E+OO 1.37E+OO 1.37E+OO 1.37E+OO O.OOE-01 ZR 95 1.09E+01 1.09E+01 1.09E+01 1.09E+01 1.09E+01 1.09E+01 1.09E+01 O.OOE-01 ZR 97 1.09E+01 1.09E+01 1.09E+01 1.09E+01 1.09E+01 1.09E+01 1.09E+01 O.OOE-01 NB 95 1.02E+01 1.02E+01 1.02E+01 1.02E+01 1.02E+01 1.02E+01 1.02E+01 O.OOE-01 M099 3.42E+OO 3.42E+OO 3.42E+OO 3.42E+OO 3.42E+OO 3.42E+OO 3.42E+OO O.OOE-01 TC 99M 1.73E+OO 1.73E+OO 1.73E+OO 1.73E+OO 1.73E+OO 1.73E+OO 1.73E+OO O.OOE-01 TC101 3.69E+OO 3.69E+OO 3.69E+OO 3.69E+OO 3.69E+OO 3.69E+OO 3.69E+OO O.OOE-01 DAEC ODAM Page 195 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =ADULT PATHWAY= BOATING TOTAL BODY GI-LU BONE LIVER KIDNEY THYROID LUNG SKIN (mrem gal)/(Ci min) RU103 6.47E+OO 6.47E+OO 6.47E+OO 6.47E+OO 6.47E+OO 6.47E+OO 6.47E+OO O.OOE-01 RU105 8.60E+OO 8.60E+OO 8.60E+OO 8.60E+OO 8.60E+OO 8.60E+OO 8.60E+OO O.OOE-01 RU106 2.77E+OO 2.77E+OO 2.77E+OO 2.77E+OO 2.77E+OO 2.77E+OO 2.77E+OO O.OOE-01 AG110M 3.57E+01 3.57E+01 3.57E+01 3.57E+01 3.57E+01 3.57E+01 3.57E+01 O.OOE-01 TE125M 2.69E-02 2.69E-02 2.69E-02 2.69E-02 2.69E-02 2.69E-02 2.69E-02 O.OOE-01 TE127M 1.89E-03 1.89E-03 1.89E-03 1.89E-03 1.89E-03 1.89E-03 1.89E-03 O.OOE-01 TE127 2.02E-02 2.02E-02 2.02E-02 2.02E-02 2.02E-02 2.02E-02 2.02E-02 O.OOE-01 TE129M 1.53E+OO 1.53E+OO 1.53E+OO 1.53E+OO 1.53E+OO 1.53E+OO 1.53E+OO O.OOE-01 TE129 1.30E+OO 1.30E+OO 1.30E+OO 1.30E+OO 1.30E+OO 1.30E+OO 1.30E+OO O.OOE-01 TE131M 1.60E+01 1.60E+01 1.60E+01 1.60E+01 1.60E+01 1.60E+01 1.60E+01 O.OOE-01 TE131 4.56E+OO 4.56E+OO 4.56E+OO 4.56E+OO 4.56E+OO 4.56E+OO 4.56E+OO O.OOE-01 TE132 2.91 E+OO 2.91E+OO 2.91 E+OO 2.91 E+OO 2.91 E+OO 2.91 E+OO 2.91E+OO O.OOE-01 1130 2.82E+01 2.82E+01 2.82E+01 2.82E+01 2.82E+01 2.82E+01 2.82E+01 O.OOE-01 I 131 5.67E+OO 5.67E+OO 5.67E+OO 5.67E+OO 5.67E+OO 5.67E+OO 5.67E+OO O.OOE-01 1132 3.11 E+01 3.11 E+01 3.11 E+01 3.11E+01 3.11E+01 3.11 E+01 3.11 E+01 O.OOE-01 1133 6.96E+OO 6.96E+OO 6.96E+OO 6.96E+OO 6.96E+OO 6.96E+OO 6.96E+OO O.OOE-01 I 134 2.82E+01 2.82E+01 2.82E+01 2.82E+01 2.82E+01 2.82E+01 2.82E+01 O.OOE-01 1135 2.38E+01 2.38E+01 2.38E+01 2.38E+01 2.38E+01 2.38E+01 2.38E+01 O.OOE-01 CS134 2.11 E+01 2.11E+01 2.11 E+01 2.11 E+01 2.11E+01 2.11 E+01 2.11 E+01 O.OOE-01 CS136 2.98E+01 2.98E+01 2.98E+01 2.98E+01 2.98E+01 2.98E+01 2.98E+01 O.OOE-01 CS137 7.28E+OO 7.28E+OO 7.28E+OO 7.28E+OO 7.28E+OO 7.28E+OO 7.28E+OO O.OOE-01 CS138 2.56E+01 2.56E+01 2.56E+01 2.56E+01 2.56E+01 2.56E+01 2.56E+01 O.OOE-01 BA139 5.33E-01 5.33E-01 5.33E-01 5.33E-01 5.33E-01 5.33E-01 5.33E-01 O.OOE-01 BA140 3.56E+OO 3.56E+OO 3.56E+OO 3.56E+OO 3.56E+OO 3.56E+OO 3.56E+OO O.OOE-01 BA141 6.37E+OO 6.37E+OO 6.37E+OO 6.37E+OO 6.37E+OO 6.37E+OO 6.37E+OO O.OOE-01 BA142 1.09E+01 1.09E+01 1.09E+01 1.09E+01 1.09E+01 1.09E+01 1.09E+01 O.OOE-01 LA140 2.98E+01 2.98E+01 2.98E+01 2.98E+01 2.98E+01 2.98E+01 2.98E+01 O.OOE-01 LA142 3.13E+01 3.13E+01 3.13E+01 3.13E+01 3.13E+01 3.13E+01 3.13E+01 O.OOE-01 CE141 9.46E-01 9.46E-01 9.46E-01 9.46E-01 9.46E-01 9.46E-01 9.46E-01 O.OOE-01 CE143 4.14E+OO 4.14E+OO 4.14E+OO 4.14E+OO 4.14E+OO 4.14E+OO 4.14E+OO O.OOE-01 CE144 6.26E-01 6.26E-01 6.26E-01 6.26E-01 6.26E-01 6.26E-01 6.26E-01 O.OOE-01 PR143 1.16E-02 1.16E-02 1.16E-02 1.16E-02 1.16E-02 1.16E-02 1.16E-02 O.OOE-01 PR144 3.20E-01 3.20E-01 3.20E-01 3.20E-01 3.20E-01 3.20E-01 3.20E-01 O.OOE-01 ND147 2.04E+OO 2.04E+OO 2.04E+OO 2.04E+OO 2.04E+OO 2.04E+OO 2.04E+OO O.OOE-01 w 187 6.02E+OO 6.02E+OO 6.02E+OO 6.02E+OO 6.02E+OO 6.02E+OO 6.02E+OO 0.00E-01 NP239 1.74E+OO 1.74E+OO 1.74E+OO 1.74E+OO 1.74E+OO 1.74E+OO 1.74E+OO O.OOE-01 DAEC ODAM Page 196 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =TEENAGER PATHWAY= POTABLE WATER TOTAL BODY GI-LU BONE LIVER KIDNEY THYROID LUNG SKIN {mrem gaQ/{Ci min} H 3 1.54E+01 1.54E+01 O.OOE-01 1.54E+01 1.54E+01 1.54E+01 1.54E+01 O.OOE-01 c 14 2.08E+02 2.08E+02 1.04E+03 2.08E+02 2.08E+02 2.08E+02 2.08E+02 O.OOE-01 NA24 1.95E+02 1.95E+02 1.95E+02 1.95E+02 1.95E+02 1.95E+02 1.95E+02 O.OOE-01 p 32 2.61 E+03 5.66E+03 6.73E+04 4.17E+03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CR 51 8.99E-01 1.51E+02 O.OOE-01 O.OOE-01 1.97E-01 4.99E-01 1.28E+OO O.OOE-01 MN 54 2.99E+02 3.09E+03 O.OOE-01 1.51E+03 4.49E+02 O.OOE-01 O.OOE-01 O.OOE-01 MN 56 1.10E-02 4.08E+OO O.OOE-01 6.20E-02 7.85E-02 O.OOE-01 O.OOE-01 O.OOE-01 FE 55 1.60E+02 2.97E+02 9.67E+02 6.85E+02 O.OOE-01 O.OOE-01 4.35E+02 O.OOE-01 FE 59 1.33E+03 8.16E+03 1.48E+03 3.45E+03 O.OOE-01 O.OOE-01 1.09E+03 O.OOE-01 C058 5.68E+02 3.40E+03 O.OOE-01 2.46E+02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 C060 1.62E+03 9.36E+03 O.OOE-01 7.19E+02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl63 1.53E+03 5.09E+02 4.53E+04 3.20E+03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 N165 1.52E-02 1.80E+OO 2.61 E-01 3.33E-02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 cu 64 3.72E+OO 6.14E+02 O.OOE-01 7.91 E+OO 2.00E+01 O.OOE-01 O.OOE-01 O.OOE-01 ZN 65 2.38E+03 2.16E+03 1.47E+03 5.10E+03 3.27E+03 O.OOE-01 O.OOE"01 O.OOE-01 ZN 69 1.21 E-08 3.19E-07 9.08E-08 1.73E-07 1.13E-07 O.OOE-01 O.OOE-01 O.OOE-01 BR 83 1.40E-02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 84 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 85 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 86 3.45E+03 1.09E+03 O.OOE-01 7.35E+03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 88 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 89 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 89 3.18E+03 1.32E+04 1.11E+05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 90 5.22E+04 5.96E+04 2.61 E+06 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 91 1.42E+01 1.62E+03 3.57E+02 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 92 7.21E-02 4.31E+01 1.69E+OO O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 90 7.29E-02 2.23E+04 2.70E+OO O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Y 91M O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 91 1.36E+OO 2.08E+04 5.08E+01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 92 8.29E-05 7.86E+01 2.86E-03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 93 5.16E-03 5.75E+03 1.88E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 95 2.26E+OO 7.59E+03 1.04E+01 3.29E+OO 4.84E+OO O.OOE-01 O.OOE-01 O.OOE-01 ZR 97 2.06E-02 1.21E+04 2.27E-01 4.48E-02 6.80E-02 O.OOE-01 O.OOE-01 O.OOE-01 NB 95 6.30E-01 4.89E+03 2.06E+OO 1.14E+OO 1.11E+OO O.OOE-01 O.OOE-01 O.OOE-01 M099 2.29E+02 2.15E+03 O.OOE-01 1.20E+03 2.74E+03 O.OOE-01 O.OOE-01 O.OOE-01 TC99M 1.93E-01 9.80E+OO 5.35E-03 1.49E-02 2.22E-01 O.OOE-01 8.29E-03 O.OOE-01 TC101 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 DAEC ODAM Page 197 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =TEENAGER PATHWAY= POTABLE WATER TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN mrem al I Ci min RU103 2.74E+01 5.36E+03 6.41E+01 O.OOE-01 2.26E+02 O.OOE-01 O.OOE-01 O.OOE-01 RU105 5.09E-02 1.06E+02 1.31 E-01 O.OOE-01 1.65E+OO O.OOE-01 O.OOE-01 O.OOE-01 RU106 1.26E+02 4.80E+04 1.00E+03 O.OOE-01 1.93E+03 O.OOE-01 O.OOE-01 O.OOE-01 AG110M 3.01E+01 1.39E+04 5.23E+01 4.95E+01 9.44E+01 O.OOE-01 O.OOE-01 O.OOE-01 TE125M 1.29E+02 2.86E+03 9.68E+02 3.49E+02 O.OOE-01 2.71E+02 O.OOE-01 O.OOE-01 TE127M 2.92E+02 6.13E+03 2.46E+03 8.72E+02 9.97E+03 5.85E+02 O.OOE-01 O.OOE-01 TE127 1.47E+OO 5.27E+02 6.82E+OO 2.42E+OO 2.76E+01 4.70E+OO O.OOE-01 O.OOE-01 TE129M 6.47E+02 1.53E+04 4.09E+03 1.52E+03 1.71E+04 1.32E+03 O.OOE-01 O.OOE-01 TE129 1.65E-06 3.70E-05 6.77E-06 2.52E-06 2.84E-05 4.83E-06 O.OOE-01 O.OOE-01 TE131M 1.43E+02 1.38E+04 3.59E+02 1.72E+02 1.79E+03 2.59E+02 O.OOE-01 O.OOE-01 TE131 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 TE132 4.30E+02 1.45E+04 7.22E+02 4.57E+02 4.39E+03 4.82E+02 O.OOE-01 O.OOE-01 1130 7.91E+01 1.52E+02 6.85E+01 1.98E+02 3.05E+02 1.62E+04 O.OOE-01 O.OOE-01 I 131 1.03E+03 3.80E+02 1.37E+03 1.92E+03 3.31 E+03 5.61 E+05 O.OOE-01 O.OOE-01 1132 4.85E-02 5.89E-02 5.16E-02 1.35E-01 2.13E-01 4.55E+OO O.OOE-01 O.OOE-01 1133 1.20E+02 2.97E+02 2.31 E+02 3.92E+02 6.88E+02 5.48E+04 O.OOE-01 O.OOE-01 I 134 1.98E-07 7.25E-09 2.0BE-07 5.50E-07 8.68E-07 9.17E-06 O.OOE-01 O.OOE-01 I 135 1.19E+01 3.57E+01 1.25E+01 3.22E+01 5.09E+01 2.07E+03 O.OOE-01 O.OOE-01 CS134 2.34E+04 6.26E+02 2.14E+04 5.04E+04 1.60E+04 O.OOE-01 6.11 E+03 O.OOE-01 CS136 5.51 E+03 6.60E+02 2.08E+03 8.20E+03 4.47E+03 O.OOE-01 7.04E+02 O.OOE-01 CS137 1.33E+04 5.42E+02 2.87E+04 3.81E+04 1.30E+04 O.OOE-01 5.04E+03 O.OOE-01 CS138 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BA139 5.79E-06 1.77E-03 1.99E-04 1.40E-07 1.32E-07 O.OOE-01 9.63E-08 O.OOE-01 BA140 4.44E+02 1.06E+04 6.88E+03 8.44E+OO 2.86E+OO 0.00E-01 5.67E+OO O.OOE-01 BA141 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BA142 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 LA140 7.71E-02 1.66E+04 5.89E-01 2.90E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 LA142 1.03E-07 1.26E-02 9.35E-07 4.15E-07 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CE141 2.55E-01 6.36E+03 3.33E+OO 2.22E+OO 1.05E+OO O.OOE-01 O.OOE-01 O.OOE-01 CE143 2.96E-02 7.96E+03 3.64E-01 2.65E+02 1.19E-01 O.OOE-01 O.OOE-01 O.OOE-01 CE144 9.55E+OO 4.47E+04 1.78E+02 7.35E+01 4.39E+01 O.OOE-01 O.OOE-01 O.OOE-01 PR143 1.59E-01 1.05E+04 3.19E+OO 1.27E+OO 7.39E-01 O.OOE-01 O.OOE-01 O.OOE-01 PR144 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ND147 1.47E-01 8.85E+03 2.26E+OO 2.45E+OO 1.44E+OO O.OOE-01 O.OOE-01 O.OOE-01 W187 5.32E+OO 4.11E+03 1.86E+01 1.52E+01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 NP239 1.76E-02 5.09E+03 3.36E-01 3.17E-02 9.94E-02 O.OOE-01 O.OOE-01 O.OOE-01 DAEC ODAM Page 198 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =TEENAGER PATHWAY= FRESH WATER FISH TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN {mrem gaQ/{Ci min} H 3 4.36E-01 4.36E-01 O.OOE-01 4.36E-01 4.36E-01 4.36E-01 4.36E-01 O.OOE-01 c 14 3.00E+04 3.00E+04 1.50E+05 3.00E+04 3.00E+04 3.00E+04 3.00E+04 O.OOE-01 NA24 6.08E+02 6.08E+02 6.08E+02 6.08E+02 6.08E+02 6.08E+02 6.08E+02 O.OOE-01 p 32 8.18E+06 1.77E+07 2.11E+08 1.31E+07 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CR 51 5.64E+OO 9.47E+02 O.OOE-01 O.OOE-01 1.24E+OO 3.13E+OO 8.05E+OO O.OOE-01 MN 54 3.75E+03 3.88E+04 O.OOE-01 1.89E+04 5.64E+03 O.OOE-01 O.OOE-01 O.OOE-01 MN 56 1.35E-01 4.99E+01 O.OOE-01 7.57E-01 9.59E-01 O.OOE-01 O.OOE-01 O.OOE-01 FE 55 5.01 E+02 9.31E+02 3.03E+03 2.15E+03 O.OOE-01 O.OOE-01 1.36E+03 O.OOE-01 FE 59 4.18E+03 2.56E+04 4.64E+03 1.08E+04 O.OOE-01 O.OOE-01 3.41E+03 O.OOE-01 co 58 8.90E+02 5.33E+03 O.OOE-01 3.86E+02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 C060 2.54E+03 1.47E+04 O.OOE-01 1.13E+03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl63 4.82E+03 1.60E+03 1.42E+05 1.00E+04 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl65 4.63E-02 5.51 E+OO 7.95E-01 1.02E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 cu 64 5.81 E+OO 9.58E+02 O.OOE-01 1.24E+01 3.12E+01 O.OOE-01 O.OOE-01 O.OOE-01 ZN 65 1.49E+05 1.36E+05 9.22E+04 3.20E+05 2.05E+05 O.OOE-01 O.OOE-01 O.OOE-01 ZN 69 7.06E-07 1.86E-05 5.30E-06 1.01 E-05 6.59E-06 O.OOE-01 0.00E-01 O.OOE-01 BR 83 1.79E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 84 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 85 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 86 2.17E+05 6.82E+04 O.OOE-01 4.61E+05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 88 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 89 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 89 2.99E+03 1.24E+04 1.04E+05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 90 4.91E+04 5.61 E+04 2.46E+06 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 91 1.33E+01 1.51E+03 3.34E+02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 92 6.61E-02 3.95E+01 1.55E+OO O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 90 5.71E-02 1.75E+04 2.12E+OO O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Y 91M O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 91 1.0?E+OO 1.63E+04 3.99E+01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 92 6.37E-05 6.05E+01 2.20E-03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 93 4.02E-03 4.48E+03 1.47E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 95 2.34E-01 7.86E+02 1.08E+OO 3.41 E-01 5.01 E-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 97 2.13E-03 1.25E+03 2.34E-02 4.62E-03 7.01E-03 O.OOE-01 O.OOE-01 O.OOE-01 NB 95 5.93E+02 4.60E+06 1.94E+03 1.08E+03 1.04E+03 O.OOE-01 O.OOE-01 O.OOE-01 MO 99 7.17E+01 6.73E+02 O.OOE-01 3.76E+02 8.60E+02 O.OOE-01 O.OOE-01 O.OOE-01 TC 99M 9.00E-02 4.56E+OO 2.49E-03 6.94E-03 1.04E-01 O.OOE-01 3.85E-03 O.OOE-01 TC101 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 DAEC ODAM Page 199 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =TEENAGER PATHWAY= FRESH WATER FISH TOTAL BODY GI-LU BONE LIVER KIDNEY THYROID LUNG SKIN (mrem gal)/(Ci min) RU103 8.60E+OO 1.68E+03 2.01 E+01 O.OOE-01 7.09E+01 O.OOE-01 O.OOE-01 O.OOE-01 RU105 1.57E-02 3.27E+01 4.05E-02 O.OOE-01 5.11E-01 O.OOE-01 O.OOE-01 O.OOE-01 RU106 3.96E+01 1.51E+04 3.14E+02 O.OOE-01 6.06E+02 O.OOE-01 O.OOE-01 O.OOE-01 AG110M 2.17E+OO 1.00E+03 3.78E+OO 3.57E+OO 6.81E+OO O.OOE-01 O.OOE-01 O.OOE-01 TE125M 1.62E+03 3.59E+04 1.21E+04 4.38E+03 O.OOE-01 3.39E+03 O.OOE-01 O.OOE-01 TE127M 3.67E+03 7.69E+04 3.09E+04 1.09E+04 1.25E+05 7.34E+03 O.OOE-01 O.OOE-01 TE127 1.83E+01 6.56E+03 8.49E+01 3.01E+01 3.44E+02 5.86E+01 O.OOE-01 O.OOE-01 TE129M 8.12E+03 1.92E+05 5.13E+04 1.90E+04 2.14E+05 1.65E+04 O.OOE-01 O.OOE-01 TE129 1.95E-05 4.38E-04 8.00E-05 2.98E-05 3.36E-04 5.72E-05 O.OOE-01 O.OOE-01 TE131M 1.80E+03 1.73E+05 4.49E+03 2.15E+03 2.24E+04 3.24E+03 O.OOE-01 O.OOE-01 TE131 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE132 5.40E+03 1.82E+05 9.05E+03 5.73E+03 5.50E+04 6.04E+03 O.OOE-01 O.OOE-01 1130 3.70E+01 7.12E+01 3.20E+01 9.27E+01 1.43E+02 7.56E+03 O.OOE-01 O.OOE-01 I 131 4.86E+02 1.79E+02 6.46E+02 9.04E+02 1.56E+03 2.64E+05 O.OOE-01 O.OOE-01 1132 2.21E-02 2.69E-02 2.36E-02 6.17E-02 9.72E-02 2.0BE+OO O.OOE-01 O.OOE-01 1133 5.61 E+01 1.39E+02 1.08E+02 1.84E+02 3.23E+02 2.57E+04 O.OOE-01 O.OOE-01 I 134 8.60E-08 3.15E-09 9.03E-08 2.39E-07 3.77E-07 3.99E-06 O.OOE-01 O.OOE-01 I 135 5.56E+OO 1.66E+01 5.83E+OO 1.50E+01 2.37E+01 9.66E+02 O.OOE-01 O.OOE-01 CS134 1.47E+06 3.93E+04 1.34E+06 3.16E+06 1.00E+06 O.OOE-01 3.83E+05 O.OOE-01 CS136 3.46E+05 4.14E+04 1.31E+05 5.15E+05 2.80E+05 O.OOE-01 4.42E+04 O.OOE-01 CS137 8.33E+05 3.40E+04 1.80E+06 2.39E+06 8.14E+05 O.OOE-01 3.16E+05 O.OOE-01 CS138 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BA139 6.90E-07 2.11 E-04 2.37E-05 1.67E-08 1.57E-08 O.OOE-01 1.15E-08 O.OOE-01 BA140 5.57E+01 1.33E+03 8.64E+02 1.06E+OO 3.59E-01 O.OOE-01 7.12E-01 O.OOE-01 BA141 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BA142 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 LA140 6.03E-02 1.30E+04 4.61 E-01 2.27E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 LA142 7.75E-08 9.47E-03 7.01 E-07 3.11 E-07 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CE141 8.02E-03 2.00E+02 1.05E-01 6.98E-02 3.29E-02 O.OOE-01 O.OOE-01 O.OOE-01 CE143 9.26E-04 2.49E+02 1.14E-02 8.29E+OO 3.72E-03 0.00E-01 O.OOE-01 O.OOE-01 CE144 2.99E-01 1.40E+03 5.57E+OO 2.31E+OO 1.38E+OO O.OOE-01 O.OOE-01 O.OOE-01 PR143 1.24E-01 8.22E+03 2.50E+OO 9.97E-01 5.BOE-01 O.OOE-01 O.OOE-01 O.OOE-01 PR144 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ND147 1.15E-01 6.94E+03 1.77E+OO 1.92E+OO 1.13E+OO O.OOE-01 O.OOE-01 O.OOE-01 W187 2.00E+02 1.54E+05 7.00E+02 5.70E+02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 NP239 5.51E-03 1.60E+03 1.05E-01 9.92E-03 3.11 E-02 O.OOE-01 O.OOE-01 O.OOE-01 DAEC ODAM Page 200 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =TEENAGER PATHWAY= FRESH WATER INVERTEBRATES TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN (mrem gaQ/(Ci min} H 3 1.04E-01 1.04E-01 O.OOE-01 1.04E-01 1.04E-01 1.04E-01 1.04E-01 O.OOE-01 c 14 1.41E+04 1.41E+04 7.04E+04 1.41E+04 1.41 E+04 1.41E+04 1.41 E+04 O.OOE-01 NA24 2.89E+02 2.89E+02 2.89E+02 2.89E+02 2.89E+02 2.89E+02 2.89E+02 O.OOE-01 p 32 3.89E+05 8.43E+05 1.00E+O? 6.21 E+05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CR 51 1.34E+01 2.25E+03 O.OOE-01 O.OOE-01 2.93E+OO 7.44E+OO 1.91 E+01 O.OOE-01 MN 54 2.00E+05 2.07E+06 O.OOE-01 1.01E+06 3.01E+05 O.OOE-01 O.OOE-01 O.OOE-01 MN 56 7.20E+OO 2.66E+03 O.OOE-01 4.05E+01 5.12E+01 O.OOE-01 O.OOE-01 O.OOE-01 FE 55 3.81 E+03 7.07E+03 2.30E+04 1.63E+04 O.OOE-01 O.OOE-01 1.04E+04 O.OOE-01 FE 59 3.18E+04 1.95E+05 3.53E+04 8.23E+04 O.OOE-01 O.OOE-01 2.59E+04 O.OOE-01 C058 8.46E+02 5.06E+03 O.OOE-01 3.67E+02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 co 60 2.41E+03 1.39E+04 O.OOE-01 1.07E+03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl63 1.14E+03 3.79E+02 3.37E+04 2.38E+03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl65 1.10E-02 1.31E+OO 1.89E-01 2.41 E-02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 cu 64 1.10E+01 1.82E+03 O.OOE-01 2.35E+01 5.94E+01 O.OOE-01 O.OOE-01 O.OOE-01 ZN 65 1.77E+05 1.61E+05 1.09E+05 3.80E+05 2.43E+05 0.00E-01 O.OOE-01 O.OOE-01 ZN 69 8.39E-07 2.21E-05 6.29E-06 1.20E-05 7.83E-06 O.OOE-01 O.OOE-01 O.OOE-01 BR 83 3.35E-02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 84 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 85 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 86 2.57E+04 8.10E+03 O.OOE-01 5.47E+04 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 88 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 89 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 89 2.37E+03 9.85E+03 8.27E+04 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 90 3.89E+04 4.44E+04 1.94E+06 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 91 1.05E+01 1.20E+03 2.64E+02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 92 5.24E-02 3.13E+01 1.23E+OO O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 90 5.42E-01 1.66E+05 2.01E+01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Y 91M O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 91 1.02E+01 1.55E+05 3.79E+02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 92 6.06E-04 5.74E+02 2.09E-02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 93 3.82E-02 4.25E+04 1.39E+OO O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 95 1.13E-01 3.79E+02 5.21 E-01 1.64E-01 2.41 E-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 97 1.03E-03 6.03E+02 1.13E-02 2.23E-03 3.38E-03 O.OOE-01 O.OOE-01 O.OOE-01 NB 95 4.69E-01 3.64E+03 1.54E+OO 8.53E-01 8.26E-01 O.OOE-01 O.OOE-01 O.OOE-01 M099 1.70E+01 1.60E+02 O.OOE-01 8.92E+01 2.04E+02 O.OOE-01 O.OOE-01 O.OOE-01 TC 99M 7.12E-03 3.61 E-01 1.97E-04 5.50E-04 8.19E-03 O.OOE-01 3.05E-04 O.OOE-01 TC101 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 DAEC ODAM Page 201 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =TEENAGER PATHWAY= FRESH WATER INVERTEBRATES TOTAL BODY GI-LU BONE LIVER KIDNEY THYROID LUNG SKIN (mrem gal)/(Ci min) RU103 6.13E+01 1.20E+04 1.43E+02 O.OOE-01 5.05E+02 O.OOE-01 O.OOE-01 O.OOE-01 RU105 1.12E-01 2.33E+02 2.89E-01 O.OOE-01 3.64E+OO O.OOE-01 O.OOE-01 O.OOE-01 RU106 2.82E+02 1.07E+05 2.24E+03 O.OOE-01 4.32E+03 O.OOE-01 O.OOE-01 O.OOE-01 AG110M 1.73E+02 7.98E+04 3.00E+02 2.84E+02 5.42E+02 O.OOE-01 O.OOE-01 O.OOE-01 TE125M 5.88E+03 1.30E+05 4.40E+04 1.59E+04 O.OOE-01 1.23E+04 O.OOE-01 O.OOE-01 TE127M 1.33E+04 2.78E+05 1.12E+05 3.96E+04 4.53E+05 2.66E+04 O.OOE-01 O.OOE-01 TE127 6.62E+01 2.38E+04 3.08E+02 1.09E+02 1.25E+03 2.12E+02 O.OOE-01 O.OOE-01 TE129M 2.94E+04 6.97E+05 1.86E+05 6.89E+04 7.77E+05 5.99E+04 O.OOE-01 O.OOE-01 TE129 7.05E-05 1.58E-03 2.90E-04 1.08E-04 1.22E-03 2.07E-04 O.OOE-01 O.OOE-01 TE131M 6.50E+03 6.26E+05 1.63E+04 7.80E+03 8.13E+04 1.17E+04 O.OOE-01 O.OOE-01 TE131 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE132 1.95E+04 6.58E+05 3.28E+04 2.08E+04 1.99E+05 2.19E+04 O.OOE-01 O.OOE-01 1130 2.93E+OO 5.64E+OO 2.54E+OO 7.34E+OO 1.13E+01 5.98E+02 O.OOE-01 O.OOE-01 1131 3.85E+01 1.42E+01 5.12E+01 7.16E+01 1.23E+02 2.09E+04 O.OOE-01 O.OOE-01 1132 1.75E-03 2.13E-03 1.87E-03 4.89E-03 7.70E-03 1.65E-01 O.OOE-01 O.OOE-01 1133 4.44E+OO 1.10E+01 8.59E+OO 1.46E+01 2.55E+01 2.03E+03 O.OOE-01 O.OOE-01 I 134 6.81E-09 2.50E-10 7.15E-09 1.90E-08 2.99E-08 3.16E-07 O.OOE-01 O.OOE-01 1135 4.40E-01 1.32E+OO 4.62E-01 1.19E+OO 1.88E+OO 7.64E+01 O.OOE-01 O.OOE-01 CS134 1.74E+05 4.67E+03 1.59E+05 3.75E+05 1.19E+05 O.OOE-01 4.55E+04 O.OOE-01 CS136 4.10E+04 4.92E+03 1.55E+04 6.11E+04 3.33E+04 O.OOE-01 5.24E+03 O.OOE-01 CS137 9.90E+04 4.04E+03 2.13E+05 2.84E+05 9.67E+04 O.OOE-01 3.76E+04 O.OOE-01 CS138 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BA139 8.20E-06 2.51E-03 2.81E-04 1.98E-07 1.87E-07 O.OOE-01 1.36E-07 O.OOE-01 BA140 6.61 E+02 1.58E+04 1.03E+04 1.26E+01 4.26E+OO O.OOE-01 8.45E+OO O.OOE-01 BA141 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BA142 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 LA140 5.73E-01 1.24E+05 4.38E+OO 2.15E+OO O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 LA142 7.36E-07 9.00E-02 6.66E-06 2.96E-06 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CE141 1.90E+OO 4.74E+04 2.48E+01 1.66E+01 7.80E+OO O.OOE-01 O.OOE-01 O.OOE-01 CE143 2.20E-01 5.92E+04 2.71 E+OO 1.97E+03 8.83E-01 O.OOE-01 O.OOE-01 O.OOE-01 CE144 7.11E+01 3.33E+05 1.32E+03 5.48E+02 3.27E+02 O.OOE-01 O.OOE-01 O.OOE-01 PR143 1.18E+OO 7.81E+04 2.37E+01 9.48E+OO 5.51 E+OO O.OOE-01 O.OOE-01 O.OOE-01 PR144 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ND147 1.09E+OO 6.59E+04 1.68E+01 1.83E+01 1.07E+01 O.OOE-01 O.OOE-01 O.OOE-01 w 187 3.96E-01 3.05E+02 1.38E+OO 1.13E+OO O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 NP239 5.24E-02 1.52E+04 9.99E-01 9.43E-02 2.96E-01 O.OOE-01 O.OOE-01 O.OOE-01 DAEC ODAM Page 202 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =TEENAGER PATHWAY= IRRIGATED FRESH LEAFY VEGETABLES TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN (mrem gaQ!(Ci min} H 3 1.27E+OO 1.27E+OO O.OOE-01 1.27E+OO 1.27E+OO 1.27E+OO 1.27E+OO O.OOE-01 c 14 1.90E+03 1.90E+03 9.50E+03 1.90E+03 1.90E+03 1.90E+03 1.90E+03 O.OOE-01 NA24 5.53E+OO 5.53E+OO 5.53E+OO 5.53E+OO 5.53E+OO 5.53E+OO 5.53E+OO O.OOE-01 p 32 9.26E+02 2.01 E+03 2.39E+04 1.48E+03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CR 51 4.08E-01 6.86E+01 O.OOE-01 O.OOE-01 8.95E-02 2.27E-01 5.83E-01 O.OOE-01 MN 54 1.90E+02 1.97E+03 O.OOE-01 9.60E+02 2.86E+02 O.OOE-01 O.OOE-01 O.OOE-01 MN 56 4.43E-05 1.64E-02 O.OOE-01 2.49E-04 3.15E-04 O.OOE-01 O.OOE-01 O.OOE-01 FE 55 1.04E+02 1.93E+02 6.28E+02 4.46E+02 O.OOE-01 O.OOE-01 2.83E+02 O.OOE-01 FE 59 6.88E+02 4.22E+03 7.64E+02 1.78E+03 O.OOE-01 O.OOE-01 5.62E+02 O.OOE-01 C058 3.19E+02 1.91E+03 O.OOE-01 1.39E+02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 C060 1.07E+03 6.18E+03 O.OOE-01 4.74E+02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl63 1.05E+03 3.49E+02 3.10E+04 2.19E+03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl65 5.94E-05 7.08E-03 1.02E-03 1.31 E-04 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 cu 64 8.88E-02 1.46E+01 O.OOE-01 1.89E-01 4.78E-01 O.OOE-01 O.OOE-01 O.OOE-01 ZN 65 1.59E+03 1.44E+03 9.80E+02 3.40E+03 2.18E+03 O.OOE-01 O.OOE-01 O.OOE-01 ZN 69 1.14E-11 3.01E-10 8.56E-11 1.63E-10 1.07E-10 O.OOE-01 O.OOE-01 O.OOE-01 BR 83 5.17E-05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 84 1.32E-16 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 85 3.39E-37 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 86 1.36E+03 4.29E+02 O.OOE-01 2.90E+03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 88 3.67E-28 5.90E-35 O.OOE-01 6.88E-28 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 89 3.00E-30 6.50E-39 O.OOE-01 4.24E-30 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 89 1.70E+03 7.07E+03 5.93E+04 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 90 4.78E+04 5.46E+04 2.39E+06 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 91 2.52E-01 2.87E+01 6.33E+OO O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 92 3.10E-04 1.85E-01 7.28E-03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 90 8.01E-03 2.45E+03 2.98E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Y 91M 1.68E-15 2.07E-12 4.39E-14 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 91 7.43E-01 1.14E+04 2.77E+01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 92 4.94E-07 4.69E-01 1.71 E-05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 93 9.72E-05 1.08E+02 3.55E-03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 95 1.25E+OO 4.20E+03 5.77E+OO 1.82E+OO 2.68E+OO O.OOE-01 O.OOE-01 O.OOE-01 ZR 97 6.57E-04 3.86E+02 7.21 E-03 1.43E-03 2.16E-03 O.OOE-01 O.OOE-01 O.OOE-01 NB 95 3.07E-01 2.39E+03 1.01E+OO 5.58E-01 5.41 E-01 O.OOE-01 O.OOE-01 O.OOE-01 MO 99 2.58E+01 2.42E+02 O.OOE-01 1.35E+02 3.09E+02 O.OOE-01 O.OOE-01 O.OOE-01 TC 99M 2.11E-03 1.07E-01 5.83E-05 1.63E-04 2.42E-03 O.OOE-01 9.02E-05 O.OOE-01 TC101 2.94E-31 5.11 E-39 2.10E-32 2.99E-32 5.41 E-31 O.OOE-01 1.82E-32 O.OOE-01 DAEC ODAM Page 203 of 280 Rev.37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =TEENAGER PATHWAY= IRRIGATED FRESH LEAFY VEGETABLES TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN {mrem gaQ/{Ci min} RU103 1.38E+01 2.69E+03 3.22E+01 O.OOE-01 1.14E+02 O.OOE-01 O.OOE-01 O.OOE-01 RU105 3.94E-04 8.19E-01 1.01 E-03 O.OOE-01 1.28E-02 O.OOE-01 O.OOE-01 O.OOE-01 RU106 8.13E+01 3.10E+04 6.45E+02 O.OOE-01 1.24E+03 O.OOE-01 O.OOE-01 O.OOE-01 AG110M 1.94E+01 8.95E+03 3.37E+01 3.19E+01 6.07E+01 O.OOE-01 O.OOE-01 O.OOE-01 TE125M 7.45E+01 1.64E+03 5.57E+02 2.01E+02 O.OOE-01 1.56E+02 O.OOE-01 O.OOE-01 TE127M 1.90E+02 3.98E+03 1.60E+03 5.67E+02 6.48E+03 3.80E+02 O.OOE-01 O.OOE-01 TE127 2.58E-02 9.27E+OO 1.20E-01 4.26E-02 4.86E-01 8.28E-02 O.OOE-01 O.OOE-01 TE129M 3.23E+02 7.66E+03 2.04E+03 7.57E+02 8.53E+03 6.58E+02 O.OOE-01 O.OOE-01 TE129 2.18E-09 4.91 E-08 8.97E-09 3.35E-09 3.77E-08 6.41 E-09 O.OOE-01 O.OOE-01 TE131M 8.05E+OO 7.75E+02 2.01 E+01 9.65E+OO 1.01E+02 1.45E+01 O.OOE-01 O.OOE-01 TE131 1.86E-21 4.88E-22 5.94E-21 2.45E-21 2.60E-20 4.58E-21 O.OOE-01 O.OOE-01 TE132 5.66E+01 1.90E+03 9.50E+01 6.01E+01 5.77E+02 6.34E+01 O.OOE-01 O.OOE-01 1130 1.84E+OO 3.54E+OO 1.59E+OO 4.60E+OO 7.09E+OO 3.75E+02 O.OOE-01 O.OOE-01 I 131 2.60E+02 9.58E+01 3.46E+02 4.84E+02 8.34E+02 1.41E+05 O.OOE-01 O.OOE-01 1132 1.69E-04 2.0SE-04 1.SOE-04 4.71E-04 7.42E-04 1.59E-02 O.OOE-01 O.OOE-01 1133 4.68E+OO 1.16E+01 9.05E+OO 1.54E+01 2.69E+01 2.14E+03 O.OOE-01 O.OOE-01 I 134 1.61E-10 5.92E-12 1.69E-10 4.49E-10 7.0SE-10 7.48E-09 O.OOE-01 O.OOE-01 1135 1.44E-01 4.29E-01 1.50E-01 3.87E-01 6.12E-01 2.49E+01 O.OOE-01 O.OOE-01 CS134 1.52E+04 4.07E+02 1.39E+04 3.28E+04 1.04E+04 O.OOE-01 3.97E+03 O.OOE-01 CS136 1.84E+03 2.20E+02 6.96E+02 2.74E+03 1.49E+03 O.OOE-01 2.35E+02 O.OOE-01 CS137 8.90E+03 3.63E+02 1.92E+04 2.55E+04 8.69E+03 O.OOE-01 3.38E+03 O.OOE-01 CS138 2.15E-16 1.95E-19 2.24E-16 4.29E-16 3.17E-16 O.OOE-01 3.69E-17 O.OOE-01 BA139 9.87E-09 3.02E-06 3.39E-07 2.38E-10 2.25E-10 O.OOE-01 1.64E-10 O.OOE-01 BA140 1.46E+02 3.50E+03 2.27E+03 2.78E+OO 9.43E-01 O.OOE-01 1.87E+OO O.OOE-01 BA141 7.14E-29 4.56E-33 2.14E-27 1.60E-30 1.48E-30 O.OOE-01 1.09E-30 O.OOE-01 BA142 3.10E-32 1.55E-42 5.04E-31 5.04E-34 4.27E-34 O.OOE-01 3.36E-34 O.OOE-01 LA140 5.62E-03 1.21E+03 4.30E-02 2.11 E-02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 LA142 2.0SE-10 2.55E-05 1.88E-09 8.37E-10 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CE141 1.22E-01 3.04E+03 1.59E+OO 1.06E+OO 5.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 CE143 1.SOE-03 4.85E+02 2.22E-02 1.61 E+01 7.24E-03 O.OOE-01 O.OOE-01 O.OOE-01 CE144 6.03E+OO 2.82E+04 1.12E+02 4.64E+01 2.77E+01 O.OOE-01 O.OOE-01 O.OOE-01 PR143 5.39E-02 3.56E+03 1.08E+OO 4.32E-01 2.51 E-01 O.OOE-01 O.OOE-01 O.OOE-01 PR144 2.35E-33 5.11 E-35 4.63E-32 1.90E-32 1.09E-32 O.OOE-01 O.OOE-01 O.OOE-01 ND147 4.48E-02 2.70E+03 6.88E-01 7.49E-01 4.40E-01 O.OOE-01 O.OOE-01 O.OOE-01 W187 2.38E-01 1.84E+02 8.34E-01 6.SOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 NP239 1.74E-03 5.03E+02 3.32E-02 3.13E-03 9.81E-03 O.OOE-01 O.OOE-01 O.OOE-01 DAEC ODAM Page 204 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE ::: TEENAGER PATHWAY= IRRIGATED STORED FRUIT VEGETABLES, GRAIN TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN (mrem gaQ/(Ci min} H 3 1.89E+01 1.89E+01 O.OOE-01 1.89E+01 1.89E+01 1.89E+01 1.89E+01 O.OOE-01 c 14 2.85E+04 2.85E+04 1.43E+05 2.85E+04 2.85E+04 2.85E+04 2.85E+04 O.OOE-01 NA24 2.19E-24 2.19E-24 2.19E-24 2.19E-24 2.19E-24 2.19E-24 2.19E-24 O.OOE-01 p 32 7.96E+02 1.72E+03 2.05E+04 1.27E+03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CR 51 1.40E+OO 2.35E+02 O.OOE-01 O.OOE-01 3.06E-01 7.76E-01 1.99E+OO O.OOE-01 MN 54 2.50E+03 2.59E+04 O.OOE-01 1.26E+04 3.77E+03 O.OOE-01 O.OOE-01 O.OOE-01 MN 56 3.79E-27 1.40E-24 O.OOE-01 2.13E-26 2.70E-26 O.OOE-01 O.OOE-01 O.OOE-01 FE55 1.49E+03 2.77E+03 9.04E+03 6.41E+03 O.OOE-01 O.OOE-01 4.07E+03 O.OOE-01 FE 59 4.12E+03 2.53E+04 4.58E+03 1.07E+04 O.OOE-01 O.OOE-01 3.37E+03 O.OOE-01 co 58 2.69E+03 1.61E+04 O.OOE-01 1.17E+03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 C060 1.57E+04 9.07E+04 O.OOE-01 6.97E+03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl63 1.58E+04 5.23E+03 4.65E+05 3.28E+04 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl65 5.74E-27 6.84E-25 9.87E-26 1.26E-26 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 cu 64 4.34E-26 7.15E-24 O.OOE-01 9.22E-26 2.33E-25 O.OOE-01 O.OOE-01 O.OOE-01 ZN 65 2.01 E+04 1.83E+04 1.24E+04 4.32E+04 2.76E+04 O.OOE-01 O.OOE-01 O.OOE-01 ZN 69 6.21E-29 1.63E-27 4.66E-28 8.87E-28 5.80E-28 O.OOE-01 O.OOE-01 O.OOE-01 BR 83 7.12E-27 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 84 7.22E-28 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 85 5.09E-36 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 86 2.29E+03 7.23E+02 O.OOE-01 4.88E+03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 88 9.12E-29 1.47E-35 O.OOE-01 1.71 E-28 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 89 4.50E-29 9.74E-38 O.OOE-01 6.36E-29 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 89 1.13E+04 4.71E+04 3.96E+05 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 90 7.14E+05 8.16E+05 3.57E+07 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 91 1.91 E-25 2.18E-23 4.81 E-24 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 92 1.88E-26 1.12E-23 4.41E-25 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 90 2.74E-08 8.40E-03 1.02E-06 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Y 91M 1.22E-31 1.50E-28 3.19E-30 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 91 5.54E+OO 8.47E+04 2.07E+02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 92 7.02E-30 6.66E-24 2.43E-28 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 93 6.65E-29 7.41 E-23 2.43E-27 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 95 9.94E+OO 3.33E+04 4.58E+01 1.44E+01 2.12E+01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 97 5.70E-28 3.35E-22 6.25E-27 1.24E-27 1.88E-27 O.OOE-01 O.OOE-01 O.OOE-01 NB 95 1.44E+OO 1.12E+04 4.72E+OO 2.62E+OO 2.54E+OO O.OOE-01 O.OOE-01 O.OOE-01 MO 99 1.33E-04 1.25E-03 O.OOE-01 6.95E-04 1.59E-03 O.OOE-01 O.OOE-01 O.OOE-01 TC 99M 4.39E-27 2.22E-25 1.21 E-28 3.39E-28 5.05E-27 O.OOE-01 1.88E-28 O.OOE-01 TC101 4.41 E-30 7.67E-38 3.16E-31 4.49E-31 8.12E-30 O.OOE-01 2.73E-31 O.OOE-01 DAEC ODAM Page 205 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =TEENAGER PATHWAY= IRRIGATED STORED FRUIT VEGETABLES, GRAIN TOTAL BODY GI-LU BONE LIVER KIDNEY THYROID LUNG SKIN (mrem gal)/(Ci min) RU103 7.30E+01 1.43E+04 1.71 E+02 O.OOE-01 6.02E+02 O.OOE-01 O.OOE-01 O.OOE-01 RU105 2.20E-27 4.57E-24 5.66E-27 O.OOE-01 7.14E-26 O.OOE-01 O.OOE-01 O.OOE-01 RU106 1.09E+03 4.15E+05 8.66E+03 O.OOE-01 1.67E+04 O.OOE-01 O.OOE-01 O.OOE-01 AG110M 2.47E+02 1.14E+05 4.29E+02 4.06E+02 7.74E+02 O.OOE-01 O.OOE-01 O.OOE-01 TE125M 5.53E+02 1.22E+04 4.13E+03 1.49E+03 O.OOE-01 1.15E+03 O.OOE-01 O.OOE-01 TE127M 1.96E+03 4.11E+04 1.65E+04 5.85E+03 6.68E+04 3.92E+03 O.OOE-01 O.OOE-01 TE127 2.01E-26 7.22E-24 9.35E-26 3.31E-26 3.79E-25 6.45E-26 O.OOE-01 O.OOE-01 TE129M 1.43E+03 3.40E+04 9.05E+03 3.36E+03 3.79E+04 2.92E+03 O.OOE-01 O.OOE-01 TE129 4.86E-28 1.09E-26 2.00E-27 7.44E-28 8.38E-27 1.43E-27 O.OOE-01 O.OOE-01 TE131M 7.40E-13 7.12E-11 1.85E-12 8.87E-13 9.25E-12 1.33E-12 O.OOE-01 O.OOE-01 TE131 4.85E-29 1.27E-29 1.55E-28 6.39E-29 6.78E-28 1.20E-28 O.OOE-01 O.OOE-01 TE132 3.04E-03 1.02E-01 5.10E-03 3.23E-03 3.10E-02 3.41 E-03 O.OOE-01 O.OOE-01 1130 9.29E-25 1.79E-24 8.04E-25 2.33E-24 3.58E-24 1.90E-22 O.OOE-01 O.OOE-01 I 131 2.41E+01 8.87E+OO 3.20E+01 4.49E+01 7.72E+01 1.31E+04 O.OOE-01 O.OOE-01 1132 3.07E-26 3.73E-26 3.27E-26 8.56E-26 1.35E-25 2.88E-'24 0.00E-01 O.OOE-01 1133 2.34E-19 5.79E-19 4.51 E-19 7.66E-19 1.34E-18 1.07E-16 O.OOE-01 O.OOE-01 I 134 3.81E-27 1.40E-28 4.00E-27 1.06E-26 1.67E-26 1.77E-25 O.OOE-01 O.OOE-01 I 135 2.35E-25 7.03E-25 2.46E-25 6.34E-25 1.00E-24 4.08E-23 O.OOE-01 O.OOE-01 CS134 2.16E+05 5.79E+03 1.98E+05 4.65E+05 1.48E+05 O.OOE-01 5.65E+04 O.OOE-01 CS136 1.22E+03 1.46E+02 4.61E+02 1.81E+03 9.88E+02 O.OOE-01 1.56E+02 O.OOE-01 CS137 1.33E+05 5.43E+03 2.87E+05 3.82E+05 1.30E+05 O.OOE-01 5.05E+04 O.OOE-01 CS138 7.65E-28 6.94E-31 7.96E-28 1.53E-27 1.13E-27 O.OOE-01 1.31 E-28 O.OOE-01 BA139 2.32E-28 7.11 E-26 7.98E-27 5.61E-30 5.29E-30 O.OOE-01 3.87E-30 O.OOE-01 BA140 8.97E+01 2.15E+03 1.39E+03 1.71 E+OO 5.79E-01 O.OOE-01 1.15E+OO O.OOE-01 BA141 4.86E-30 3.10E-34 1.45E-28 1.09E-31 1.01 E-31 O.OOE-01 7.44E-32 O.OOE-01 BA142 4.66E-31 2.32E-41 7.57E-30 7.57E-33 6.40E-33 O.OOE-01 5.04E-33 O.OOE-01 LA140 2.21 E-12 4.76E-07 1.69E-11 8.29E-12 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 LA142 1.34E-30 1.64E-25 1.21 E-29 5.39E-30 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CE141 5.19E-01 1.29E+04 6.77E+OO 4.52E+OO 2.13E+OO O.OOE-01 O.OOE-01 O.OOE-01 CE143 3.71E-15 9.99E-10 4.57E-14 3.32E-11 1.49E-14 O.OOE-01 O.OOE-01 O.OOE-01 CE144 7.83E+01 3.67E+05 1.46E+03 6.03E+02 3.60E+02 O.OOE-01 O.OOE-01 O.OOE-01 PR143 4.00E-02 2.64E+03 8.03E-01 3.20E-01 1.86E-01 O.OOE-01 O.OOE-01 O.OOE-01 PR144 3.91E-33 8.50E-35 7.71E-32 3.16E-32 1.81 E-32 O.OOE-01 O.OOE-01 O.OOE-01 ND147 1.69E-02 1.02E+03 2.59E-01 2.82E-01 1.65E-01 O.OOE-01 O.OOE-01 O.OOE-01 W187 5.39E-18 4.16E-15 1.89E-17 1.54E-17 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 NP239 7.74E-10 2.24E-04 1.48E-08 1.39E-09 4.37E-09 O.OOE-01 O.OOE-01 O.OOE-01 DAEC ODAM Page 206 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =TEENAGER PATHWAY= IRRIGATED FRESH FORAGE--MILK TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN (mrem gaQ/(Ci min} H 3 5.51 E+OO 5.51 E+OO O.OOE-01 5.51 E+OO 5.51 E+OO 5.51 E+OO 5.51 E+OO O.OOE-01 c 14 1.19E+04 1.19E+04 5.95E+04 1.19E+04 1.19E+04 1.19E+04 1.19E+04 O.OOE-01 NA24 9.95E+01 9.95E+01 9.95E+01 9.95E+01 9.95E+01 9.95E+01 9.95E+01 O.OOE-01 p 32 2.82E+04 6.11E+04 7.27E+05 4.50E+04 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CR 51 1.08E+OO 1.81E+02 O.OOE-01 O.OOE-01 2.36E-01 5.98E-01 1.54E+OO O.OOE-01 MN 54 5.31E+01 5.50E+02 O.OOE-01 2.68E+02 7.99E+01 O.OOE-01 O.OOE-01 O.OOE-01 MN 56 2.31E-08 8.55E-06 O.OOE-01 1.30E-07 1.64E-07 O.OOE-01 O.OOE-01 O.OOE-01 FE55 1.39E+02 2.57E+02 8.39E+02 5.95E+02 O.OOE-01 O.OOE-01 3.77E+02 O.OOE-01 FE 59 9.69E+02 5.93E+03 1.07E+03 2.51 E+03 O.OOE-01 O.OOE-01 7.91 E+02 O.OOE-01 co 58 3.68E+02 2.20E+03 O.OOE-01 1.60E+02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 C060 1.18E+03 6.83E+03 O.OOE-01 5.24E+02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl63 7.64E+03 2.53E+03 2.25E+05 1.59E+04 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl65 7.36E-07 8.76E-05 1.26E-05 1.62E-06 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 cu 64 4.55E-01 7.50E+01 O.OOE-01 9.67E-01 2.45E+OO O.OOE-01 O.OOE-01 O.OOE-01 ZN 65 6.71E+04 6.10E+04 4.15E+04 1.44E+05 9.21E+04 O.OOE-01 O.OOE-01 O.OOE-01 ZN 69 1.46E-17 3.84E-16 1.09E-16 2.09E-16 1.36E-16 O.OOE-01 O.OOE-01 O.OOE-01 BR 83 3.34E-06 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 84 3.26E-27 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 85 2.30E-35 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 86 4.98E+04 1.57E+04 O.OOE-01 1.06E+05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 88 2.48E-28 3.99E-35 O.OOE-01 4.66E-28 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 89 1.22E-28 2.65E-37 O.OOE-01 1.73E-28 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 89 1.60E+03 6.65E+03 5.58E+04 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 90 5.62E+04 6.42E+04 2.81 E+06 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 91 4.75E-02 5.42E+OO 1.20E+OO O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 92 7.33E-07 4.38E-04 1.72E-05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 90 8.41 E-05 2.58E+01 3.12E-03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 Y 91M 4.12E-26 5.09E-23 1.08E-24 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 91 8.62E-03 1.32E+02 3.22E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 92 6.22E-11 5.90E-05 2.15E-09 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 93 2.54E-07 2.83E-01 9.26E-06 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 95 7.24E-03 2.43E+01 3.34E-02 1.05E-02 1.55E-02 O.OOE-01 O.OOE-01 O.OOE-01 ZR 97 1.67E-06 9.82E-01 1.83E-05 3.63E-06 5.50E-06 O.OOE-01 O.OOE-01 O.OOE-01 NB 95 9.10E-01 7.07E+03 2.98E+OO 1.65E+OO 1.60E+OO O.OOE-01 O.OOE-01 O.OOE-01 MO 99 2.04E+02 1.92E+03 O.OOE-01 1.07E+03 2.45E+03 O.OOE-01 O.OOE-01 O.OOE-01 TC 99M 4.51E-03 2.28E-01 1.25E-04 3.48E-04 5.18E-03 O.OOE-01 1.93E-04 O.OOE-01 TC101 9.99E-30 1.74E-37 7.15E-31 1.02E-30 1.84E-29 O.OOE-01 6.19E-31 O.OOE-01 DAEC ODAM Page 207 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =TEENAGER PATHWAY= IRRIGATED FRESH FORAGE--MILK TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN (mrem gal)/(Ci min) RU103 1.62E-02 3.17E+OO 3.80E-02 O.OOE-01 1.34E-01 O.OOE-01 O.OOE-01 O.OOE-01 RU105 1.26E-08 2.62E-05 3.25E-08 O.OOE-01 4.09E-07 O.OOE-01 O.OOE-01 O.OOE-01 RU106 9.04E-02 3.44E+01 7.17E-01 O.OOE-01 1.38E+OO O.OOE-01 O.OOE-01 O.OOE-01 AG110M 1.07E+03 4.95E+05 1.86E+03 1.76E+03 3.36E+03 O.OOE-01 O.OOE-01 O.OOE-01 TE125M 8.37E+01 1.85E+03 6.26E+02 2.25E+02 O.OOE-01 1.75E+02 O.OOE-01 O.OOE-01 TE127M 2.05E+02 4.30E+03 1.73E+03 6.12E+02 7.00E+03 4.11E+02 O.OOE-01 O.OOE-01 TE127 5.89E-03 2.11E+OO 2.74E-02 9.?0E-03 1.11E-01 1.89E-02 0.00E-01 O.OOE-01 TE129M 3.75E+02 8.90E+03 2.37E+03 8.80E+02 9.92E+03 7.65E+02 O.OOE-01 O.OOE-01 TE129 1.74E-15 3.91 E-14 7.16E-15 2.67E-15 3.00E-14 5.11E-15 O.OOE-01 O.OOE-01 TE131M 6.24E+OO 6.01 E+02 1.56E+01 7.49E+OO 7.81E+01 1.13E+01 O.OOE-01 O.OOE-01 TE131 4.37E-30 1.15E-30 1.40E-29 5.76E-30 6.11E-29 1.08E-29 O.OOE-01 O.OOE-01 TE132 6.17E+01 2.08E+03 1.03E+02 6.56E+01 6.29E+02 6.91E+01 O.OOE-01 O.OOE-01 1130 3.90E+OO 7.50E+OO 3.37E+OO 9.76E+OO 1.50E+01 7.95E+02

  • O.OOE-01 O.OOE-01 I 131 1.92E+03 7.05E+02 2.55E+03 3.57E+03 6.14E+03 1.04E+06 O.OOE-01 O.OOE-01 1132 9.99E-07 1.21 E-06 1.06E-06 2.78E-06 4.38E-06 9.38E-05 O.OOE-01 O.OOE-01 1133 1.72E+01 4.26E+01 3.32E+01 5.63E+01 9.88E+01 7.86E+03 O.OOE-01 O.OOE-01 I 134 7.32E-18 2.68E-19 7.69E-18 2.04E-17 3.21E-17 3.39E-16 O.OOE-01 O.OOE-01 1135 9.40E-02 2.81 E-01 9.85E-02 2.54E-01 4.00E-01 1.63E+01 O.OOE-01 O.OOE-01 CS134 2.03E+05 5.43E+03 1.86E+05 4.37E+05 1.39E+05 O.OOE-01 5.30E+04 O.OOE-01 CS136 2.72E+04 3.26E+03 1.03E+04 4.05E+04 2.21E+04 O.OOE-01 3.48E+03 O.OOE-01 CS137 1.17E+05 4.79E+03 2.53E+05 3.36E+05 1.14E+05 O.OOE-01 4.45E+04 O.OOE-01 CS138 8.32E-28 7.55E-31 8.67E-28 1.66E-27 1.23E-27 O.OOE-01 1.43E-28 O.OOE-01 BA139 3.00E-14 9.18E-12 1.03E-12 7.24E-16 6.83E-16 O.OOE-01 4.99E-16 O.OOE-01 BA140 7.22E+01 1.73E+03 1.12E+03 1.37E+OO 4.65E-01 O.OOE-01 9.23E-01 O.OOE-01 BA141 1.76E-31 1.12E-35 5.28E-30 3.94E-33 3.66E-33 O.OOE-01 2.?0E-33 O.OOE-01 BA142 1.69E-32 8.44E-43 2.75E-31 2.75E-34 2.32E-34 O.OOE-01 1.83E-34 O.OOE-01 LA140 2.53E-05 5.46E+OO 1.93E-04 9.51E-05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 LA142 2.89E-17 3.54E-12 2.62E-16 1.16E-16 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CE141 1.45E-02 3.61 E+02 1.89E-01 1.26E-01 5.94E-02 O.OOE-01 O.OOE-01 O.OOE-01 CE143 1.48E-04 4.00E+01 1.83E-03 1.33E+OO 5.96E-04 O.OOE-01 O.OOE-01 O.OOE-01 CE144 6.76E-01 3.16E+03 1.26E+01 5.20E+OO 3.11E+OO O.OOE-01 O.OOE-01 O.OOE-01 PR143 3.32E-04 2.20E+01 6.67E-03 2.67E-03 1.55E-03 O.OOE-01 O.OOE-01 O.OOE-01 PR144 1.77E-36 3.86E-38 3.50E-35 1.43E-35 8.22E-36 O.OOE-01 O.OOE-01 O.OOE-01 ND147 2.77E-04 1.67E+01 4.25E-03 4.62E-03 2.71E-03 O.OOE-01 O.OOE-01 O.OOE-01 W187 8.08E-02 6.24E+01 2.83E-01 2.31 E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 NP239 8.81E-06 2.55E+OO 1.68E-04 1.59E-05 4.98E-05 O.OOE-01 O.OOE-01 O.OOE-01 DAEC ODAM Page 208 of 280 Rev.37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =TEENAGER PATHWAY= IRRIGATED FRESH FORAGE--MEAT TOTAL BODY GI-LU BONE LIVER KIDNEY THYROID LUNG SKIN {mrem gaQ/(Ci min) H 3 9.85E-01 9.85E-01 O.OOE-01 9.85E-01 9.85E-01 9.85E-01 9.85E-01 O.OOE-01 c 14 5.00E+03 5.00E+03 2.50E+04 5.00E+03 5.00E+03 5.00E+03 5.00E+03 O.OOE-01 NA24 2.74E-08 2.74E-08 2.74E-08 2.74E-08 2.74E-08 2.74E-08 2.74E-08 O.OOE-01 p 32 3.52E+03 7.63E+03 9.08E+04 5.63E+03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CR 51 1.22E-01 2.04E+01 O.OOE-01 O.OOE-01 2.67E-02 6.76E-02 1.74E-01 O.OOE-01 MN 54 2.65E+01 2.75E+02 O.OOE-01 1.34E+02 3.99E+01 O.OOE-01 O.OOE-01 O.OOE-01 MN 56 4.47E-29 1.65E-26 O.OOE-01 2.51E-28 3.18E-28 O.OOE-01 O.OOE-01 O.OOE-01 FE 55 7.42E+02 1.38E+03 4.49E+03 3.18E+03 O.OOE-01 O.OOE-01 2.02E+03 O.OOE-01 FE 59 3.97E+03 2.43E+04 4.40E+03 1.03E+04 O.OOE-01 O.OOE-01 3.24E+03 O.OOE-01 C058 6.52E+02 3.90E+03 O.OOE-01 2.83E+02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 C060 2.48E+03 1.43E+04 O.OOE-01 1.10E+03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl63 9.82E+03 3.26E+03 2.90E+05 2.04E+04 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl65 4.49E-27 5.34E-25 7.71 E-26 9.85E-27 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 cu 64 2.29E-12 3.77E-10 O.OOE-01 4.86E-12 1.23E-11 O.OOE-01 O.OOE-01 O.OOE-01 ZN 65 7.97E+03 7.24E+03 4.92E+03 1.71E+04 1.09E+04 O.OOE-01 O.OOE-01 O.OOE-01 ZN 69 2.74E-29 7.21E-28 2.05E-28 3.91E-28 2.56E-28 O.OOE-01 O.OOE-01 O.OOE-01 BR 83 2.72E-27 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 84 2.76E-28 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 85 1.94E-36 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 86 4.29E+03 1.35E+03 O.OOE-01 9.13E+03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 88 4.17E-29 6.70E-36 O.OOE-01 7.82E-29 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 89 2.05E-29 4.45E-38 O.OOE-01 2.90E-29 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 89 1.52E+02 6.33E+02 5.31 E+03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 90 6.84E+03 7.81 E+03 3.42E+05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 91 1.13E-16 1.28E-14 2.83E-15 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 92 1.67E-28 9.95E-26 3.91E-27 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 90 5.92E-05 1.81 E+01 2.20E-03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Y 91M 8.26E-33 1.02E-29 2.16E-31 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 91 5.21E-01 7.96E+03 1.94E+01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 92 4.76E-31 4.51 E-25 1.64E-29 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 93 2.39E-18 2.66E-12 8.71E-17 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 95 6.59E+OO 2.21 E+04 3.04E+01 9.58E+OO 1.41E+01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 97 3.68E-11 2.17E-05 4.04E-10 8.00E-11 1.21E-10 O.OOE-01 O.OOE-01 O.OOE-01 NB 95 1.16E+01 9.03E+04 3.81 E+01 2.11 E+01 2.05E+01 O.OOE-01 O.OOE-01 O.OOE-01 MO 99 3.77E-01 3.54E+OO O.OOE-01 1.98E+OO 4.53E+OO O.OOE-01 O.OOE-01 O.OOE-01 TC 99M 2.86E-24 1.45E-22 7.90E-26 2.20E-25 3.28E-24 O.OOE-01 1.22E-25 O.OOE-01 TC101 2.60E-29 4.52E-37 1.86E-30 2.64E-30 4.78E-29 O.OOE-01 1.61 E-30 O.OOE-01 DAEC ODAM Page 209 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =TEENAGER PATHWAY= IRRIGATED FRESH FORAGE--MEAT TOTAL BODY GI-LU BONE LIVER KIDNEY THYROID LUNG SKIN (mrem gal)/(Ci min) RU103 7.68E+02 1.50E+05 1.80E+03 O.OOE-01 6.33E+03 O.OOE-01 O.OOE-01 O.OOE-01 RU105 1.30E-26 2.70E-23 3.34E-26 O.OOE-01 4.21 E-25 O.OOE-01 O.OOE-01 O.OOE-01 RU106 5.68E+03 2.16E+06 4.51 E+04 O.OOE-01 8.69E+04 O.OOE-01 O.OOE-01 O.OOE-01 AG110M 5.64E+01 2.60E+04 9.79E+01 9.27E+01 1.77E+02 O.OOE-01 O.OOE-01 O.OOE-01 TE125M 8.45E+02 1.86E+04 6.32E+03 2.28E+03 O.OOE-01 1.76E+03 O.OOE-01 O.OOE-01 TE127M 2.29E+03 4.80E+04 1.93E+04 6.83E+03 7.81E+04 4.58E+03 O.OOE-01 O.OOE-01 TE127 8.99E-16 3.23E-13 4.18E-15 1.48E-15 1.69E-14 2.88E-15 O.OOE-01 O.OOE-01 TE129M 3.24E+03 7.68E+04 2.05E+04 7.59E+03 8.56E+04 6.60E+03 O.OOE-01 O.OOE-01 TE129 5.47E-28 1.23E-26 2.25E-27 8.39E-28 9.44E-27 1.61 E-27 O.OOE-01 O.OOE-01 TE131M 3.60E-03 3.47E-01 9.01E-03 4.32E-03 4.50E-02 6.50E-03 O.OOE-01 O.OOE-01 TE131 5.47E-29 1.44E-29 1.75E-28 7.21 E-29 7.65E-28 1.35E-28 O.OOE-01 O.OOE-01 TE132 1.68E+01 5.66E+02 2.82E+01 1.79E+01 1.72E+02 1.89E+01 O.OOE-01 O.OOE-01 1130 8.90E-12 1.71E-11 7.70E-12 2.23E-11 3.43E-11 1.82E-09 O.OOE-01 O.OOE-01 I 131 3.19E+01 1.17E+01 4.24E+01 5.93E+01 1.02E+02 1.73E+04 O.OOE-01 O.OOE-01 1132 1.31E-27 1.59E-27 1.40E-27 3.66E-27 5.76E-27 1.23E-25 O.OOE-01 O.OOE-01 1133 7.63E-07 1.89E-06 1.47E-06 2.50E-06 4.39E-06 3.49E-04 O.OOE-01 O.OOE-01 1134 1.63E-28 5.98E-30 1.71E-28 4.54E-28 7.15E-28 7.56E-27 O.OOE-01 O.OOE-01 1135 1.40E-22 4.18E-22 1.47E-22 3.78E-22 5.96E-22 2.43E-20 O.OOE-01 O.OOE-01 CS134 1.08E+04 2.89E+02 9.89E+03 2.33E+04 7.39E+03 O.OOE-01 2.82E+03 O.OOE-01 CS136 5.69E+02 6.82E+01 2.15E+02 8.47E+02 4.61 E+02 O.OOE-01 7.27E+01 O.OOE-01 CS137 6.34E+03 2.59E+02 1.37E+04 1.82E+04 6.19E+03 O.OOE-01 2.41E+03 O.OOE-01 CS138 4.51E-29 4.09E-32 4.69E-29 9.01E-29 6.65E-29 O.OOE-01 7.74E-30 O.OOE-01 BA139 1.10E-29 3.36E-27 3.76E-28 2.65E-31 2.49E-31 O.OOE-01 1.82E-31 O.OOE-01 BA140 3.54E+01 8.47E+02 5.49E+02 6.73E-01 2.28E-01 O.OOE-01 4.52E-01 O.OOE-01 BA141 2.29E-31 1.46E-35 6.86E-30 5.12E-33 4.76E-33 O.OOE-01 3.51E-33 0.00E-01 BA142 2.20E-32 1.10E-42 3.57E-31 3.57E-34 3.02E-34 O.OOE-01 2.38E-34 O.OOE-01 LA140 9.71E-08 2.10E-02 7.43E-07 3.65E-07 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 LA142 3.96E-33 4.84E-28 3.58E-32 1.59E-32 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CE141 1.93E-02 4.80E+02 2.51 E-01 1.68E-01 7.89E-02 O.OOE-01 O.OOE-01 O.OOE-01 CE143 3.45E-08 9.28E-03 4.24E-07 3.09E-04 1.38E-07 O.OOE-01 O.OOE-01 O.OOE-01 CE144 1.26E+OO 5.90E+03 2.35E+01 9.72E+OO 5.80E+OO O.OOE-01 O.OOE-01 O.OOE-01 PR143 2.03E-02 1.34E+03 4.07E-01 1.63E-01 9.45E-02 O.OOE-01 O.OOE-01 O.OOE-01 PR144 2.71E-34 5.89E-36 5.34E-33 2.19E-33 1.26E-33 O.OOE-01 O.OOE-01 O.OOE-01 ND147 9.65E-03 5.81 E+02 1.48E-01 1.61 E-01 9.46E-02 O.OOE-01 O.OOE-01 O.OOE-01 W187 1.25E-07 9.64E-05 4.37E-07 3.56E-07 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 NP239 2.89E-07 8.38E-02 5.52E-06 5.21E-07 1.63E-06 O.OOE-01 O.OOE-01 O.OOE-01 DAEC ODAM Page 210 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =TEENAGER PATHWAY= IRRIGATED STORED FEED--MILK TOTAL BODY GI-LU BONE LIVER KIDNEY THYROID LUNG SKIN {mrem gaQ/{Ci min) H 3 5.51 E+OO 5.51 E+OO O.OOE-01 5.51 E+OO 5.51 E+OO 5.51 E+OO 5.51 E+OO O.OOE-01 c 14 1.23E+04 1.23E+04 6.16E+04 1.23E+04 1.23E+04 1.23E+04 1.23E+04 O.OOE-01 NA24 9.95E+01 9.95E+01 9.95E+01 9.95E+01 9.95E+01 9.95E+01 9.95E+01 O.OOE-01 p 32 2.96E+04 6.43E+04 7.65E+05 4.74E+04 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CR 51 1.19E+OO 2.00E+02 O.OOE-01 O.OOE-01 2.61 E-01 6.62E-01 1.70E+OO O.OOE-01 MN 54 6.44E+01 6.66E+02 O.OOE-01 3.25E+02 9.68E+01 O.OOE-01 O.OOE-01 O.OOE-01 MN 56 2.31E-08 8.55E-06 O.OOE-01 1.30E-07 1.64E-07 O.OOE-01 O.OOE-01 O.OOE-01 FE 55 1.69E+02 3.15E+02 1.02E+03 7.27E+02 O.OOE-01 O.OOE-01 4.61E+02 O.OOE-01 FE 59 1.11E+03 6.78E+03 1.23E+03 2.87E+03 O.OOE-01 O.OOE-01 9.04E+02 O.OOE-01 C058 4.30E+02 2.57E+03 O.OOE-01 1.87E+02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 co 60 1.44E+03 8.35E+03 O.OOE-01 6.41E+02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl63 9.34E+03 3.10E+03 2.75E+05 1.94E+04 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl65 7.36E-07 8.76E-05 1.26E-05 1.62E-06 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 cu 64 4.55E-01 7.50E+01 O.OOE-01 9.67E-01 2.45E+OO O.OOE-01 O.OOE-01 O.OOE-01 ZN 65 8.07E+04 7.33E+04 4.98E+04 1.73E+05 1.11 E+05 O.OOE-01 O.OOE-01 O.OOE-01 ZN 69 1.46E-17 3.84E-16 1.09E-16 2.09E-16 1.36E-16 O.OOE-01 O.OOE-01 O.OOE-01 BR 83 3.34E-06 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 84 3.26E-27 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 85 2.30E-35 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 86 5.35E+04 1.68E+04 O.OOE-01 1.14E+05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 88 2.48E-28 3.99E-35 O.OOE-01 4.66E-28 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 89 1.22E-28 2.65E-37 O.OOE-01 1.73E-28 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 89 1.83E+03 7.63E+03 6.41 E+04 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 90 6.31 E+04 7.20E+04 3.15E+06 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 91 4.75E-02 5.42E+OO 1.20E+OO O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 92 7.33E-07 4.38E-04 1.72E-05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 90 8.41 E-05 2.58E+01 3.12E-03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Y 91M 4.12E-26 5.09E-23 1.08E-24 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 91 9.99E-03 1.53E+02 3.73E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 92 6.22E-11 5.90E-05 2.15E-09 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 93 2.54E-07 2.83E-01 9.26E-06 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 95 8.43E-03 2.83E+01 3.88E-02 1.23E-02 1.80E-02 O.OOE-01 O.OOE-01 O.OOE-01 ZR 97 1.67E-06 9.82E-01 1.83E-05 3.63E-06 5.50E-06 O.OOE-01 O.OOE-01 O.OOE-01 NB 95 1.02E+OO 7.96E+03 3.36E+OO 1.86E+OO 1.80E+OO O.OOE-01 O.OOE-01 O.OOE-01 M099 2.04E+02 1.92E+03 O.OOE-01 1.07E+03 2.45E+03 O.OOE-01 O.OOE-01 O.OOE-01 TC 99M 4.51E-03 2.28E-01 1.25E-04 3.48E-04 5.18E-03 O.OOE-01 1.93E-04 O.OOE-01 TC101 9.99E-30 1.74E-37 7.15E-31 1.02E-30 1.84E-29 O.OOE-01 6.19E-31 O.OOE-01 DAEC ODAM Page 211 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =TEENAGER PATHWAY= IRRIGATED STORED FEED--MILK TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN {mrem gal)/{Ci min} RU103 1.84E-02 3.59E+OO 4.30E-02 O.OOE-01 1.52E-01 O.OOE-01 O.OOE-01 O.OOE-01 RU105 1.26E-08 2.62E-05 3.25E-08 O.OOE-01 4.09E-07 O.OOE-01 0.00E-01 O.OOE-01 RU106 1.1 OE-01 4.17E+01 8.?0E-01 O.OOE-01 1.68E+OO O.OOE-01 O.OOE-01 O.OOE-01 AG110M 1.29E+03 5.97E+05 2.25E+03 2.13E+03 4.06E+03 O.OOE-01 O.OOE-01 O.OOE-01 TE125M 9.66E+01 2.13E+03 7.23E+02 2.60E+02 O.OOE-01 2.02E+02 O.OOE-01 O.OOE-01 TE127M 2.42E+02 5.08E+03 2.04E+03 7.23E+02 8.26E+03 4.84E+02 0.00E-01 O.OOE-01 TE127 5.89E-03 2.11E+OO 2.74E-02 9.?0E-03 1.11E-01 1.89E-02 O.OOE-01 O.OOE-01 TE129M 4.20E+02 9.97E+03 2.66E+03 9.86E+02 1.11E+04 8.57E+02 0.00E-01 O.OOE-01 TE129 1.74E-15 3.91 E-14 7.16E-15 2.67E-15 3.00E-14 5.11 E-15 0.00E-01 O.OOE-01 TE131M 6.24E+OO 6.01 E+02 1.56E+01 7.49E+OO 7.81E+01 1.13E+01 O.OOE-01 O.OOE-01 TE131 4.37E-30 1.15E-30 1.40E-29 5.76E-30 6.11E-29 1.08E-29 O.OOE-01 O.OOE-01 TE132 6.17E+01 2.08E+03 1.04E+02 6.56E+01 6.29E+02 6.92E+01 O.OOE-01 O.OOE-01 1130 3.90E+OO 7.50E+OO 3.37E+OO 9.76E+OO 1.50E+01 7.95E+02 0.00E-01 O.OOE-01 I 131 1.95E+03 7.17E+02 2.59E+03 3.63E+03 6.24E+03 1.06E+06 0.00E-01 O.OOE-01 1132 9.99E-07 1.21 E-06 1.06E-06 2.78E-06 4.38E-06 9.38E-05 O.OOE-01 O.OOE-01 1133 1.72E+01 4.26E+01 3.32E+01 5.63E+01 9.88E+01 7.86E+03 0.00E-01 O.OOE-01 1134 7.32E-18 2.68E-19 7.69E-18 2.04E-17 3.21E-17 3.39E-16 O.OOE-01 O.OOE-01 1135 9.40E-02 2.81 E-01 9.85E-02 2.54E-01 4.00E-01 1.63E+01 O.OOE-01 O.OOE-01 CS134 2.47E+05 6.63E+03 2.26E+05 5.33E+05 1.69E+05 O.OOE-01 6.46E+04 O.OOE-01 CS136 2.85E+04 3.41E+03 1.08E+04 4.24E+04 2.31 E+04 O.OOE-01 3.64E+03 O.OOE-01 CS137 1.43E+05 5.86E+03 3.09E+05 4.12E+05 1.40E+05 O.OOE-01 5.44E+04 O.OOE-01 CS138 8.32E-28 7.55E-31 8.67E-28 1.66E-27 1.23E-27 O.OOE-01 1.43E-28 O.OOE-01 BA139 3.00E-14 9.18E-12 1.03E-12 7.24E-16 6.83E-16 O.OOE-01 4.99E-16 O.OOE-01 BA140 7.54E+01 1.80E+03 1.17E+03 1.43E+OO 4.86E-01 0.00E-01 9.64E-01 O.OOE-01 BA141 1.76E-31 1.12E-35 5.28E-30 3.94E-33 3.66E-33 O.OOE-01 2.?0E-33 O.OOE-01 BA142 1.69E-32 8.44E-43 2.75E-31 2.75E-34 2.32E-34 O.OOE-01 1.83E-34 O.OOE-01 LA140 2.53E-05 5.46E+OO 1.93E-04 9.51E-05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 LA142 2.89E-17 3.54E-12 2.62E-16 1.16E-16 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CE141 1.62E-02 4.04E+02 2.12E-01 1.41 E-01 6.65E-02 O.OOE-01 O.OOE-01 O.OOE-01 CE143 1.48E-04 4.00E+01 1.83E-03 1.33E+OO 5.96E-04 O.OOE-01 0.00E-01 O.OOE-01 CE144 8.18E-01 3.83E+03 1.52E+01 6.30E+OO 3.76E+OO O.OOE-01 0.00E-01 O.OOE-01 PR143 3.49E-04 2.30E+01 7.00E-03 2.80E-03 1.63E-03 O.OOE-01 O.OOE-01 O.OOE-01 PR144 1.77E-36 3.86E-38 3.50E-35 1.43E-35 8.22E-36 O.OOE-01 0.00E-01 O.OOE-01 ND147 2.87E-04 1.73E+01 4.40E-03 4.78E-03 2.81E-03 O.OOE-01 0.00E-01 0.00E-01 W187 8.08E-02 6.24E+01 2.83E-01 2.31 E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 NP239 8.81E-06 2.55E+OO 1.68E-04 1.59E-05 4.98E-05 O.OOE-01 O.OOE-01 O.OOE-01 DAEC ODAM Page 212 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =TEENAGER PATHWAY= IRRIGATED STORED FEED--MEAT TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN {mrem gaQ!{Ci min) H 3 9.85E-01 9.85E-01 O.OOE-01 9.85E-01 9.85E-01 9.85E-01 9.85E-01 O.OOE-01 c 14 5.17E+03 5.17E+03 2.58E+04 5.17E+03 5.17E+03 5.17E+03 5.17E+03 O.OOE-01 NA24 2.74E-08 2.74E-08 2.74E-08 2.74E-08 2.74E-08 2.74E-08 2.74E-08 O.OOE-01 p 32 3.71E+03 8.03E+03 9.56E+04 5.92E+03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CR 51 1.35E-01 2.26E+01 O.OOE-01 O.OOE-01 2.95E-02 7.48E-02 1.92E-01 O.OOE-01 MN 54 3.22E+01 3.33E+02 O.OOE-01 1.62E+02 4.84E+01 O.OOE-01 O.OOE-01 O.OOE-01 MN 56 4.47E-29 1.65E-26 O.OOE-01 2.51 E-28 3.18E-28 O.OOE-01 O.OOE-01 O.OOE-01 FE 55 9.06E+02 1.68E+03 5.48E+03 3.89E+03 O.OOE-01 O.OOE-01 2.47E+03 O.OOE-01 FE 59 4.53E+03 2.77E+04 5.03E+03 1.17E+04 O.OOE-01 O.OOE-01 3.70E+03 O.OOE-01 C058 7.62E+02 4.56E+03 O.OOE-01 3.31E+02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 C060 3.03E+03 1.75E+04 O.OOE-01 1.35E+03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl63 1.20E+04 3.98E+03 3.54E+05 2.50E+04 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl65 4.49E-27 5.34E-25 7.71 E-26 9.85E-27 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 cu 64 2.29E-12 3.??E-10 O.OOE-01 4.86E-12 1.23E-11 O.OOE-01 O.OOE-01 O.OOE-01 ZN 65 9.59E+03 8.71E+03 5.92E+03 2.06E+04 1.32E+04 O.OOE-01 O.OOE-01 O.OOE-01 ZN 69 2.74E-29 7.21 E-28 2.05E-28 3.91E-28 2.56E-28 O.OOE-01 O.OOE-01 O.OOE-01 BR 83 2.72E-27 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 84 2.76E-28 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 85 1.94E-36 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 86 4.61E+03 1.45E+03 O.OOE-01 9.81 E+03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 88 4.17E-29 6.70E-36 O.OOE-01 7.82E-29 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 89 2.05E-29 4.45E-38 O.OOE-01 2.90E-29 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 SR 89 1.75E+02 7.26E+02 6.10E+03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 90 7.68E+03 8.77E+03 3.84E+05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 91 1.13E-16 1.28E-14 2.83E-15 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 92 1.67E-28 9.95E-26 3.91E-27 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 90 5.92E-05 1.81 E+01 2.20E-03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Y 91M 8.26E-33 1.02E-29 2.16E-31 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 91 6.04E-01 9.23E+03 2.25E+01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 92 4.76E-31 4.51E-25 1.64E-29 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 93 2.39E-18 2.66E-12 8.71 E-17 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 95 7.67E+OO 2.57E+04 3.53E+01 1.11E+01 1.64E+01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 97 3.68E-11 2.17E-05 4.04E-10 8.00E-11 1.21 E-10 O.OOE-01 O.OOE-01 O.OOE-01 NB 95 1.31E+01 1.02E+05 4.28E+01 2.38E+01 2.30E+01 O.OOE-01 O.OOE-01 O.OOE-01 M099 3.??E-01 3.54E+OO O.OOE-01 1.98E+OO 4.53E+OO O.OOE-01 O.OOE-01 O.OOE-01 TC 99M 2.86E-24 1.45E-22 7.90E-26 2.20E-25 3.28E-24 O.OOE-01 1.22E-25 O.OOE-01 TC101 2.60E-29 4.52E-37 1.86E-30 2.64E-30 4.78E-29 O.OOE-01 1.61 E-30 O.OOE-01 DAEC ODAM Page 213 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =TEENAGER PATHWAY= IRRIGATED STORED FEED--MEAT TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN (mrem gaQ/(Ci min} RU103 8.70E+02 1.70E+05 2.04E+03 O.OOE-01 7.18E+03 O.OOE-01 O.OOE-01 O.OOE-01 RU105 1.30E-26 2.70E-23 3.34E-26 O.OOE-01 4.21E-25 O.OOE-01 O.OOE-01 O.OOE-01 RU106 6.89E+03 2.62E+06 5.47E+04 O.OOE-01 1.05E+05 O.OOE-01 O.OOE-01 O.OOE-01 AG110M 6.80E+01 3.14E+04 1.18E+02 1.12E+02 2.13E+02 O.OOE-01 O.OOE-01 O.OOE-01 TE125M 9.75E+02 2.15E+04 7.30E+03 2.63E+03 O.OOE-01 2.04E+03 O.OOE-01 O.OOE-01 TE127M 2.70E+03 5.67E+04 2.27E+04 8.06E+03 9.21E+04 5.41E+03 0.00E-01 O.OOE-01 TE127 8.99E-16 3.23E-13 4.18E-15 1.48E-15 1.69E-14 2.88E-15 O.OOE-01 O.OOE-01 TE129M 3.63E+03 8.60E+04 2.29E+04 8.50E+03 9.59E+04 7.39E+03 O.OOE-01 O.OOE-01 TE129 5.47E-28 1.23E-26 2.25E-27 8.39E-28 9.44E-27 1.61 E-27 O.OOE-01 O.OOE-01 TE131M 3.60E-03 3.47E-01 9.01 E-03 4.32E-03 4.50E-02 6.50E-03 O.OOE-01 O.OOE-01 TE131 5.47E-29 1.44E-29 1.75E-28 7.21 E-29 7.65E-28 1.35E-28 O.OOE-01 O.OOE-01 TE132 1.68E+01 5.67E+02 2.82E+01 1.79E+01 1.72E+02 1.89E+01 0.00E-01 O.OOE-01 1130 8.90E-12 1.71E-11 7.70E-12 2.23E-11 3.43E-11 1.82E-09 O.OOE-01 O.OOE-01 I 131 3.24E+01 1.19E+01 4.31 E+01 6.03E+01 1.04E+02 1.76E+04 0.00E-01 O.OOE-01 1132 1.31 E-27 1.59E-27 1.40E-27 3.66E-27 5.76E-27 1.23E-25 O.OOE-01 O.OOE-01 1133 7.63E-07 1.89E-06 1.47E-06 2.50E-06 4.39E-06 3.49E-04 0.00E-01 O.OOE-01 I 134 1.63E-28 5.98E-30 1.71 E-28 4.54E-28 7.15E-28 7.56E-27 O.OOE-01 O.OOE-01 1135 1.40E-22 4.18E-22 1.47E-22 3.78E-22 5.96E-22 2.43E-20 O.OOE-01 O.OOE-01 CS134 1.32E+04 3.53E+02 1.21E+04 2.84E+04 9.02E+03 O.OOE-01 3.44E+03 O.OOE-01 CS136 5.95E+02 7.13E+01 2.25E+02 8.87E+02 4.83E+02 O.OOE-01 7.61E+01 O.OOE-01 CS137 7.76E+03 3.17E+02 1.67E+04 2.23E+04 7.58E+03 O.OOE-01 2.95E+03 O.OOE-01 CS138 4.51E-29 4.09E-32 4.69E-29 9.01E-29 6.65E-29 O.OOE-01 7.74E-30 O.OOE-01 BA139 1.10E-29 3.36E-27 3.76E-28 2.65E-31 2.49E-31 O.OOE-01 1.82E-31 O.OOE-01 BA140 3.70E+01 8.84E+02 5.73E+02 7.03E-01 2.38E-01 O.OOE-01 4.73E-01 O.OOE-01 BA141 2.29E-31 1.46E-35 6.86E-30 5.12E-33 4.76E-33 O.OOE-01 3.51E-33 O.OOE-01 BA142 2.20E-32 1.10E-42 3.57E-31 3.57E-34 3.02E-34 O.OOE-01 2.38E-34 O.OOE-01 LA140 9.71E-08 2.10E-02 7.43E-07 3.65E-07 O.OOE-01 0.00E-01 0.00E-01 O.OOE-01 LA142 3.96E-33 4.84E-28 3.58E-32 1.59E-32 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CE141 2.16E-02 5.37E+02 2.81 E-01 1.88E-01 8.83E-02 O.OOE-01 O.OOE-01 O.OOE-01 CE143 3.45E-08 9.28E-03 4.24E-07 3.09E-04 1.38E-07 0.00E-01 O.OOE-01 O.OOE-01 CE144 1.53E+OO 7.15E+03 2.84E+01 1.18E+01 7.02E+OO O.OOE-01 O.OOE-01 O.OOE-01 PR143 2.13E-02 1.41E+03 4.27E-01 1.71E-01 9.92E-02 O.OOE-01 O.OOE-01 O.OOE-01 PR144 2.71E-34 5.89E-36 5.34E-33 2.19E-33 1.26E-33 O.OOE-01 O.OOE-01 O.OOE-01 ND147 9.98E-03 6.01 E+02 1.53E-01 1.67E-01 9.79E-02 O.OOE-01 O.OOE-01 O.OOE-01 W187 1.25E-07 9.64E-05 4.37E-07 3.56E-07 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 NP239 2.89E-07 8.38E-02 5.52E-06 5.21 E-07 1.63E-06 O.OOE-01 O.OOE-01 O.OOE-01 DAEC ODAM Page 214 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =TEENAGER PATHWAY= ANIMAL DRINKING WATER--MILK TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN (mrem gal)/(Ci min) H 3 6.61 E+OO 6.61 E+OO O.OOE-01 6.61 E+OO 6.61 E+OO 6.61 E+OO 6.61 E+OO O.OOE-01 c 14 1.17E+02 1.17E+02 5.87E+02 1.17E+02 1.17E+02 1.17E+02 1.17E+02 O.OOE-01 NA24 1.16E+02 1.16E+02 1.16E+02 1.16E+02 1.16E+02 1.16E+02 1.16E+02 O.OOE-01 p 32 2.92E+03 6.33E+03 7.53E+04 4.66E+03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CR 51 9.06E-02 1.52E+01 O.OOE-01 O.OOE-01 1.99E-02 5.03E-02 1.29E-01 O.OOE-01 MN 54 3.51E+OO 3.63E+01 O.OOE-01 1.77E+01 5.28E+OO O.OOE-01 O.OOE-01 O.OOE-01 MN 56 1.52E-07 5.62E-05 O.OOE-01 8.54E-07 1.08E-06 O.OOE-01 O.OOE-01 O.OOE-01 FE 55 9.02E+OO 1.67E+01 5.45E+01 3.87E+01 O.OOE-01 O.OOE-01 2.45E+01 O.OOE-01 FE59 7.41E+01 4.54E+02 8.22E+01 1.92E+02 O.OOE-01 O.OOE-01 6.05E+01 O.OOE-01 C058 2.64E+01 1.58E+02 O.OOE-01 1.15E+01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 co 60 7.62E+01 4.40E+02 O.OOE-01 3.38E+01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl63 4.84E+02 1.61E+02 1.43E+04 1.01E+03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl65 4.94E-06 5.87E-04 8.48E-05 1.08E-05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 cu 64 6.25E-01 1.03E+02 O.OOE-01 1.33E+OO 3.36E+OO O.OOE-01 O.OOE-01 O.OOE-01 ZN 65 4.36E+03 3.95E+03 2.69E+03 9.34E+03 5.98E+03 O.OOE-01 O.OOE-01 O.OOE-01 ZN 69 2.58E-16 6.80E-15 1.94E-15 3.69E-15 2.41E-15 O.OOE-01 O.OOE-01 O.OOE-01 BR 83 2.35E-05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 84 1.03E-25 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 85 8.05E-33 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 86 4.69E+03 1.48E+03 O.OOE-01 9.98E+03 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 RB 88 1.40E-26 2.25E-33 O.OOE-01 2.62E-26 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 89 8.07E-27 1.75E-35 O.OOE-01 1.14E-26 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 89 1.18E+02 4.91E+02 4.12E+03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 90 1.96E+03 2.24E+03 9.83E+04 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 91 8.61E-02 9.82E+OO 2.16E+OO O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 92 4.56E-06 2.72E-03 1.07E-04 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 y 90 2.62E-05 8.02E+OO 9.72E-04 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Y 91M 8.39E-25 1.04E-21 2.19E-23 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 91 6.34E-04 9.69E+OO 2.36E-02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 92 2.97E-10 2.82E-04 1.03E-08 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 y 93 4.35E-07 4.85E-01 1.59E-05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 95 5.27E-04 1.77E+OO 2.43E-03 7.66E-04 1.12E-03 O.OOE-01 O.OOE-01 O.OOE-01 ZR 97 1.74E-06 1.02E+OO 1.91 E-05 3.78E-06 5.73E-06 O.OOE-01 O.OOE-01 O.OOE-01 NB 95 7.26E-02 5.64E+02 2.38E-01 1.32E-01 1.28E-01 O.OOE-01 O.OOE-01 O.OOE-01 MO 99 6.21E+01 5.83E+02 O.OOE-01 3.25E+02 7.45E+02 O.OOE-01 O.OOE-01 O.OOE-01 TC 99M 1.28E-02 6.47E-01 3.53E-04 9.86E-04 1.47E-02 O.OOE-01 5.47E-04 O.OOE-01 TC101 7.08E-28 1.23E-35 5.07E-29 7.21E-29 1.30E-27 O.OOE-01 4.39E-29 O.OOE-01 DAEC ODAM Page 215 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =TEENAGER PATHWAY= ANIMAL DRINKING WATER--MILK TOTAL BODY GI-LU BONE LIVER KIDNEY THYROID LUNG SKIN mrem al I Ci min RU103 1.27E-03 2.48E-01 2.96E-03 O.OOE-01 1.04E-02 O.OOE-01 O.OOE-01 O.OOE-01 RU105 4.82E-08 1.00E-04 1.24E-07 O.OOE-01 1.57E-06 O.OOE-01 O.OOE-01 O.OOE-01 RU106 5.93E-03 2.26E+OO 4.70E-02 O.OOE-01 9.07E-02 O.OOE-01 O.OOE-01 O.OOE-01 AG110M 7.07E+01 3.26E+04 1.23E+02 1.16E+02 2.21E+02 O.OOE-01 O.OOE-01 O.OOE-01 TE125M 6.02E+OO 1.33E+02 4.50E+01 1.62E+01 O.OOE-01 1.26E+01 O.OOE-01 O.OOE-01 TE127M 1.37E+01 2.86E+02 1.15E+02 4.08E+01 4.66E+02 2.73E+01 0.00E-01 O.OOE-01 TE127 1.08E-02 3.88E+OO 5.03E-02 1.78E-02 2.04E-01 3.47E-02 O.OOE-01 O.OOE-01 TE129M 2.98E+01 7.07E+02 1.88E+02 6.98E+01 7.87E+02 6.07E+01 O.OOE-01 O.OOE-01 TE129 2.52E-14 5.66E-13 1.03E-13 3.86E-14 4.34E-13 7.39E-14 O.OOE-01 O.OOE-01 TE131M 3.79E+OO 3.64E+02 9.47E+OO 4.54E+OO 4.73E+01 6.83E+OO O.OOE-01 O.OOE-01 TE131 1.75E-28 4.59E-29 5.60E-28 2.31E-28 2.45E-27 4.31E-28 O.OOE-01 O.OOE-01 TE132 1.62E+01 5.46E+02 2.72E+01 1.72E+01 1.65E+02 1.82E+01 O.OOE-01 O.OOE-01 1130 5.49E+OO 1.06E+01 4.75E+OO 1.37E+01 2.12E+01 1.12E+03 O.OOE-01 O.OOE-01 I 131 2.67E+02 9.82E+01 3.54E+02 4.96E+02 8.54E+02 1.45E+05 O.OOE-01 O.OOE-01 1132 7.33E-06 8.89E-06 7.80E-06 2.04E-05 3.22E-05 6.88E-04 O.OOE-01 O.OOE-01 I 133 1.47E+01 3.65E+01 2.84E+01 4.82E+01 8.45E+01 6.73E+03 O.OOE-01 O.OOE-01 I 134 1.41E-16 5.16E-18 1.48E-16 3.91 E-16 6.17E-16 6.52E-15 O.OOE-01 O.OOE-01 1135 2.44E-01 7.29E-01 2.SSE-01 6.57E-01 1.04E+OO 4.23E+01 O.OOE-01 O.OOE-01 CS134 1.32E+04 3.53E+02 1.21E+04 2.84E+04 9.03E+03 O.OOE-01 3.45E+03 O.OOE-01 CS136 2.94E+03 3.53E+02 1.11E+03 4.38E+03 2.39E+03 O.OOE-01 3.76E+02 O.OOE-01 CS137 7.50E+03 3.06E+02 1.62E+04 2.15E+04 7.33E+03 O.OOE-01 2.85E+03 O.OOE-01 CS138 2.60E-26 2.36E-29 2.71 E-26 5.20E-26 3.84E-26 O.OOE-01 4.46E-27 O.OOE-01 BA139 3.67E-13 1.12E-10 1.26E-11 8.87E-15 8.36E-15 O.OOE-01 6.11E-15 O.OOE-01 BA140 7.89E+OO 1.89E+02 1.22E+02 1.SOE-01 5.09E-02 O.OOE-01 1.01 E-01 O.OOE-01 BA141 9.71E-30 6.20E-34 2.91E-28 2.17E-31 2.02E-31 O.OOE-01 1.49E-31 O.OOE-01 BA142 1.59E-30 7.93E-41 2.58E-29 2.58E-32 2.19E-32 O.OOE-01 1.72E-32 O.OOE-01 LA140 1.18E-05 2.55E+OO 9.02E-05 4.43E-05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 LA142 3.16E-16 3.87E-11 2.86E-15 1.27E-15 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CE141 1.18E-03 2.93E+01 1.53E-02 1.02E-02 4.82E-03 O.OOE-01 O.OOE-01 O.OOE-01 CE143 8.25E-05 2.22E+01 1.02E-03 7.39E-01 3.31E-04 O.OOE-01 O.OOE-01 O.OOE-01 CE144 4.48E-02 2.10E+02 8.34E-01 3.45E-01 2.06E-01 O.OOE-01 O.OOE-01 O.OOE-01 PR143 3.54E-05 2.34E+OO 7.11 E-04 2.84E-04 1.65E-04 O.OOE-01 O.OOE-01 O.OOE-01 PR144 1.03E-34 2.25E-36 2.04E-33 8.35E-34 4.79E-34 O.OOE-01 O.OOE-01 O.OOE-01 ND147 3.24E-05 1.95E+OO 4.97E-04 5.41E-04 3.18E-04 O.OOE-01 O.OOE-01 O.OOE-01 W187 6.07E-02 4.69E+01 2.13E-01 1.73E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 NP239 3.0SE-06 8.83E-01 5.82E-05 5.49E-06 1.72E-05 O.OOE-01 O.OOE-01 O.OOE-01 DAEC ODAM Page 216 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =TEENAGER PATHWAY= ANIMAL DRINKING WATER--MEAT TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN (mrem gaQ/(Ci min} H 3 9.85E-01 9.85E-01 O.OOE-01 9.85E-01 9.85E-01 9.85E-01 9.85E-01 O.OOE-01 c 14 4.10E+01 4.10E+01 2.05E+02 4.10E+01 4.10E+01 4.10E+01 4.10E+01 O.OOE-01 NA24 2.66E-08 2.66E-08 2.66E-08 2.66E-08 2.66E-08 2.66E-08 2.66E-08 O.OOE-01 p 32 3.04E+02 6.59E+02 7.84E+03 4.86E+02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CR 51 8.53E-03 1.43E+OO O.OOE-01 O.OOE-01 1.87E-03 4.74E-03 1.22E-02 O.OOE-01 MN 54 1.46E+OO 1.51 E+01 O.OOE-01 7.36E+OO 2.20E+OO O.OOE-01 O.OOE-01 O.OOE-01 MN 56 2.45E-28 9.07E-26 O.OOE-01 1.38E-27 1.74E-27 O.OOE-01 O.OOE-01 O.OOE-01 FE 55 4.02E+01 7.46E+01 2.43E+02 1.72E+02 O.OOE-01 O.OOE-01 1.09E+02 O.OOE-01 FE 59 2.53E+02 1.55E+03 2.80E+02 6.54E+02 O.OOE-01 O.OOE-01 2.06E+02 O.OOE-01 C058 3.90E+01 2.34E+02 O.OOE-01 1.69E+01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 C060 1.33E+02 7.70E+02 O.OOE-01 5.91E+01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl63 5.18E+02 1.72E+02 1.53E+04 1.08E+03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl65 2.51E-26 2.98E-24 4.31 E-25 5.50E-26 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 cu 64 2.62E-12 4.32E-10 O.OOE-01 5.56E-12 1.41E-11 O.OOE-01 O.OOE-01 O.OOE-01 ZN 65 4.31E+02 3.91E+02 2.66E+02 9.24E+02 5.92E+02 O.OOE-01 O.OOE-01 O.OOE-01 ZN 69 4.04E-28 1.06E-26 3.03E-27 5.78E-27 3.77E-27 O.OOE-01 O.OOE-01 O.OOE-01 BR 83 1.60E-26 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 84 7.26E-27 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 85 5.67E-34 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 86 3.37E+02 1.06E+02 O.OOE-01 7.17E+02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 88 1.96E-27 3.15E-34 O.OOE-01 3.67E-27 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 89 1.13E-27 2.45E-36 O.OOE-01 1.60E-27 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 89 9.36E+OO 3.89E+01 3.27E+02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 90 1.99E+02 2.28E+02 9.97E+03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 91 1.70E-16 1.94E-14 4.28E-15 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 92 8.63E-28 5.16E-25 2.02E-26 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 90 1.54E-05 4.70E+OO 5.70E-04 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Y 91M 1.40E-31 1.73E-28 3.66E-30 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 91 3.19E-02 4.88E+02 1.19E+OO O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 92 1.89E-30 1.79E-24 6.54E-29 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 93 3.41 E-18 3.80E-12 1.24E-16 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 95 3.99E-01 1.34E+03 1.84E+OO 5.81E-01 8.53E-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 97 3.20E-11 1.88E-05 3.51E-10 6.95E-11 1.05E-10 O.OOE-01 O.OOE-01 O.OOE-01 NB 95 7.72E-01 6.00E+03 2.53E+OO 1.40E+OO 1.36E+OO O.OOE-01 O.OOE-01 O.OOE-01 M099 9.56E-02 8.97E-01 O.OOE-01 5.01 E-01 1.15E+OO O.OOE-01 O.OOE-01 O.OOE-01 TC 99M 6.74E-24 3.42E-22 1.87E-25 5.20E-25 7.75E-24 O.OOE-01 2.89E-25 O.OOE-01 TC101 1.53E-27 2.67E-35 1.10E-28 1.56E-28 2.82E-27 O.OOE-01 9.51E-29 O.OOE-01 DAEC ODAM Page 217 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =TEENAGER PATHWAY= ANIMAL DRINKING WATER--MEAT TOTAL BODY GI-LU .BONE LIVER KIDNEY THYROID LUNG SKIN mrem al I Ci min RU103 4.99E+01 9.76E+03 1.17E+02 O.OOE-01 4.12E+02 O.OOE-01 O.OOE-01 O.OOE-01 RU105 4.13E-26 8.60E-23 1.06E-25 O.OOE-01 1.34E-24 O.OOE-01 O.OOE-01 O.OOE-01 RU106 3.10E+02 1.18E+05 2.46E+03 O.OOE-01 4.75E+03 O.OOE-01 O.OOE-01 O.OOE-01 AG110M 3.10E+OO 1.43E+03 5.38E+OO 5.09E+OO 9.70E+OO O.OOE-01 O.OOE-01 O.OOE-01 TE125M 5.06E+01 1.12E+03 3.79E+02 1.36E+02 O.OOE-01 1.06E+02 O.OOE-01 O.OOE-01 TE127M 1.27E+02 2.66E+03 1.07E+03 3.79E+02 4.33E+03 2.54E+02 O.OOE-01 0.00E-01 TE127 1.38E-15 4.94E-13 6.40E-15 2.27E-15 2.59E-14 4.41 E-15 O.OOE-01 O.OOE-01 TE129M 2.14E+02 5.08E+03 1.35E+03 5.02E+02 5.66E+03 4.37E+02 O.OOE-01 O.OOE-01 TE129 6.59E-27 1.48E-25 2.71 E-26 1.01E-26 1.14E-25 1.94E-26 O.OOE-01 O.OOE-01 TE131M 1.82E-03 1.75E-01 4.55E-03 2.18E-03 2.28E-02 3.28E-03 O.OOE-01 O.OOE-01 TE131 1.82E-27 4.79E-28 5.84E-27 2.41E-27 2.55E-26 4.50E-27 O.OOE-01 O.OOE-01 TE132 3.69E+OO 1.24E+02 6.19E+OO 3.92E+OO 3.76E+01 4.13E+OO O.OOE-01 O.OOE-01 I 130 1.04E-11 2.01 E-11 9.04E-12 2.62E-11 4.03E-11 2.13E-09 O.OOE-01 O.OOE-01 1131 3.70E+OO 1.36E+OO 4.91 E+OO 6.88E+OO 1.18E+01 2.01E+03 O.OOE-01 O.OOE-01 I 132 8.03E-27 9.74E-27 8.55E-27 2.24E-26 3.52E-26 7.54E-25 O.OOE-01 O.OOE-01 1133 5.44E-07 1.35E-06 1.05E-06 1.78E-06 3.13E-06 2.49E-04 O.OOE-01 O.OOE-01 1134 2.61E-27 9.57E-29 2.74E-27 7.26E-27 1.14E-26 1.21 E-25 O.OOE-01 O.OOE-01 1135 3.02E-22 9.04E-22 3.17E-22 8.16E-22 1.29E-21 5.25E-20 O.OOE-01 O.OOE-01 CS134 5.85E+02 1.57E+01 5.36E+02 1.26E+03 4.01 E+02 O.OOE-01 1.53E+02 0.00E-01 CS136 5.13E+01 6.15E+OO 1.94E+01 7.64E+01 4.16E+01 O.OOE-01 6.56E+OO O.OOE-01 CS137 3.38E+02 1.38E+01 7.30E+02 9.71E+02 3.30E+02 O.OOE-01 1.28E+02 O.OOE-01 CS138 1.17E-27 1.06E-30 1.22E-27 2.35E-27 1.73E-27 O.OOE-01 2.01E-28 O.OOE-01 BA139 1.12E-28 3.42E-26 3.84E-27 2.70E-30 2.55E-30 O.OOE-01 1.86E-30 O.OOE-01 BA140 3.22E+OO 7.72E+01 5.00E+01 6.13E-02 2.0BE-02 O.OOE-01 4.12E-02 O.OOE-01 BA141 1.05E-29 6.72E-34 3.15E-28 2.35E-31 2.1 BE-31 O.OOE-01 1.61 E-31 O.OOE-01 BA142 1.72E-30 8.59E-41 2.BOE-29 2.BOE-32 2.37E-32 O.OOE-01 1.86E-32 O.OOE-01 LA140 3.77E-08 8.14E-03 2.89E-07 1.42E-07 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 LA142 3.61E-32 4.41E-27 3.26E-31 1.45E-31 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CE141 1.30E-03 3.24E+01 1.70E-02 1.13E-02 5.33E-03 O.OOE-01 O.OOE-01 O.OOE-01 CE143 1.60E-08 4.30E-03 1.96E-07 1.43E-04 6.41E-08 O.OOE-01 O.OOE-01 O.OOE-01 CE144 6.97E-02 3.26E+02 1.30E+OO 5.37E-01 3.21E-01 O.OOE-01 O.OOE-01 O.OOE-01 PR143 1.BOE-03 1.19E+02 3.62E-02 1.44E-02 8.39E-03 O.OOE-01 O.OOE-01 O.OOE-01 PR144 1.32E-32 2.86E-34 2.60E-31 1.06E-31 6.10E-32 O.OOE-01 O.OOE-01 0.00E-01 ND147 9.40E-04 5.66E+01 1.44E-02 1.57E-02 9.22E-03 O.OOE-01 O.OOE-01 O.OOE-01 w 187 7.81E-08 6.03E-05 2.74E-07 2.23E-07 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 NP239 8.34E-08 2.42E-02 1.59E-06 1.50E-07 4.71 E-07 O.OOE-01 O.OOE-01 O.OOE-01 DAEC ODAM Page 218 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =TEENAGER PATHWAY= RIVER SHORELINE DEPOSITS TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN (mrem gaQ/(Ci min} H 3 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 c 14 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 NA24 1.05E+01 1.05E+01 1.05E+01 1.05E+01 1.05E+01 1.05E+01 1.05E+01 1.22E+01 p 32 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CR 51 4.09E+OO 4.09E+OO 4.09E+OO 4.09E+OO 4.09E+OO 4.09E+OO 4.09E+OO 4.84E+OO MN 54 1.22E+03 1.22E+03 1.22E+03 1.22E+03 1.22E+03 1.22E+03 1.22E+03 1.43E+03 MN 56 7.70E-01 7.70E-01 7.70E-01 7.70E-01 7.70E-01 7.70E-01 7.70E-01 9.10E-01 FE 55 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 FE 59 2.40E+02 2.40E+02 2.40E+02 2.40E+02 2.40E+02 2.40E+02 2.40E+02 2.82E+02 C058 3.34E+02 3.34E+02 3.34E+02 3.34E+02 3.34E+02 3.34E+02 3.34E+02 3.91 E+02 co 60 1.89E+04 1.89E+04 1.89E+04 1.89E+04 1.89E+04 1.89E+04 1.89E+04 2.22E+04 Nl63 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl65 2.54E-01 2.54E-01 2.54E-01 2.54E-01 2.54E-01 2.54E-01 2.54E-01 2.95E-01 cu 64 5.29E-01 5.29E-01 5.29E-01 5.29E-01 5.29E-01 5.29E-01 5.29E-01 6.00E-01 ZN 65 6.56E+02 6.56E+02 6.56E+02 6.56E+02 6.56E+02 6.56E+02 6.56E+02 7.54E+02 ZN 69 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 83 4.16E-03 4.16E-03 4.16E-03 4.16E-03 4.16E-03 4.16E-03 4.16E-03 6.05E-03 BR 84 1.56E-01 1.56E-01 1.56E-01 1.56E-01 1.56E-01 1.56E-01 1.56E-01 1.83E-01 BR 85 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 86 7.92E+OO 7.92E+OO 7.92E+OO 7.92E+OO 7.92E+OO 7.92E+OO 7.92E+OO 9.05E+OO RB 88 2.31E-02 2.31E-02 2.31E-02 2.31E-02 2.31E-02 2.31E-02 2.31E-02 2.64E-02 RB 89 8.14E-02 8.14E-02 8.14E-02 8.14E-02 8.14E-02 8.14E-02 8.14E-02 9.76E-02 SR 89 1.90E-02 1.90E-02 1.90E-02 1.90E-02 1.90E-02 1.90E-02 1.90E-02 2.21E-02 SR 90 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 91 1.87E+OO 1.87E+OO 1.87E+OO 1.87E+OO 1.87E+OO 1.87E+OO 1.87E+OO 2.19E+OO SR 92 6.66E-01 6.66E-01 6.66E-01 6.66E-01 6.66E-01 6.66E-01 6.66E-01 7.40E-01 y 90 3.95E-03 3.95E-03 3.95E-03 3.95E-03 3.95E-03 3.95E-03 3.95E-03 4.67E-03 Y 91M 8.09E-02 8.09E-02 8.09E-02 8.09E-02 8.09E-02 8.09E-02 8.09E-02 9.36E-02 y 91 9.45E-01 9.45E-01 9.45E-01 9.45E-01 9.45E-01 9.45E-01 9.45E-01 1.06E+OO y 92 1.56E-01 1.56E-01 1.56E-01 1.56E-01 1.56E-01 1.56E-01 1.56E-01 1.85E-01 y 93 1.60E-01 1.60E-01 1.60E-01 1.60E-01 1.60E-01 1.60E-01 1.60E-01 2.19E-01 ZR 95 2.16E+02 2.16E+02 2.16E+02 2.16E+02 2.16E+02 2.16E+02 2.16E+02 2.50E+02 ZR 97 2.59E+OO 2.59E+OO 2.59E+OO 2.59E+OO 2.59E+OO 2.59E+OO 2.59E+OO 3.02E+OO NB 95 1.21E+02 1.21E+02 1.21E+02 1.21E+02 1.21E+02 1.21E+02 1.21E+02 1.42E+02 M099 3.51 E+OO 3.51 E+OO 3.51 E+OO 3.51 E+OO 3.51 E+OO 3.51 E+OO 3.51 E+OO 4.06E+OO TC 99M 1.60E-01 1.60E-01 1.60E-01 1.60E-01 1.60E-01 1.60E-01 1.60E-01 1.83E-01 TC101 1.33E-02 1.33E-02 1.33E-02 1.33E-02 1.33E-02 1.33E-02 1.33E-02 1.48E-02 DAEC ODAM Page 219 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =TEENAGER PATHWAY= RIVER SHORELINE DEPOSITS TOTAL BODY GI-LU BONE LIVER KIDNEY THYROID LUNG SKIN (mrem gaQ/(Ci min} RU103 9.52E+01 9.52E+01 9.52E+01 9.52E+01 9.52E+01 9.52E+01 9.52E+01 1.11E+02 RU105 5.50E-01 5.50E-01 5.50E-01 5.50E-01 5.50E-01 5.50E-01 5.50E-01 6.24E-01 RU106 3.71E+02 3.71 E+02 3.71E+02 3.71 E+02 3.71E+02 3.71E+02 3.71E+02 4.45E+02 AG110M 3.03E+03 3.03E+03 3.03E+03 3.03E+03 3.03E+03 3.03E+03 3.03E+03 3.54E+03 TE125M 1.37E+OO 1.37E+OO 1.37E+OO 1.37E+OO 1.37E+OO 1.37E+OO 1.37E+OO 1.88E+OO TE127M 8.06E-02 8.06E-02 8.06E-02 8.06E-02 8.06E-02 8.06E-02 8.06E-02 9.53E-02 TE127 2.60E-03 2.60E-03 2.60E-03 2.60E-03 2.60E-03 2.60E-03 2.60E-03 2.86E-03 TE129M 1.74E+01 1.74E+01 1.74E+01 1.74E+01 1.74E+01 1.74E+01 1.74E+01 2.03E+01 TE129 2.17E-02 2.17E-02 2.17E-02 2.17E-02 2.17E-02 2.17E-02 2.17E-02 2.57E-02 TE131M 7.04E+OO 7.04E+OO 7.04E+OO 7.04E+OO 7.04E+OO 7.04E+OO 7.04E+OO 8.30E+OO TE131 2.18E-02 2.18E-02 2.18E-02 2.18E-02 2.18E-02 2.18E-02 2.18E-02 2.58E+01 TE132 3.72E+OO 3.72E+OO 3.72E+OO 3.72E+OO 3.72E+OO 3.72E+OO 3.72E+OO 4.38E+OO I 130 4.81 E+OO 4.81 E+OO 4.81 E+OO 4.81 E+OO 4.81 E+OO 4.81 E+OO 4.81 E+OO 5.84E+OO I 131 1.51 E+01 1.51 E+01 1.51E+01 1.51 E+01 1.51 E+01 1.51 E+01 1.51 E+01 1.84E+01 1132 1.06E+OO 1.06E+OO 1.06E+OO 1.06E+OO 1.06E+OO 1.06E+OO 1.06E+OO 1.25E+OO 1133 2.15E+OO 2.15E+OO 2.15E+OO 2.15E+OO 2.15E+OO 2.15E+OO 2.15E+OO 2.62E+OO 1134 3.62E-01 3.62E-01 3.62E-01 3.62E-01 3.62E-01 3.62E-01 3.62E-01 4.30E-01 1135 2.19E+OO 2.19E+OO 2.19E+OO 2.19E+OO 2.19E+OO 2.19E+OO 2.19E+OO 2.56E+OO CS134 6.01 E+03 6.01 E+03 6.01 E+03 6.01 E+03 6.01E+03 6.01 E+03 6.01E+03 7.01 E+03 CS136 1.32E+02 1.32E+02 1.32E+02 1.32E+02 1.32E+02 1.32E+02 1.32E+02 1.50E+02 CS137 9.06E+03 9.06E+03 9.06E+03 9.06E+03 9.06E+03 9.06E+03 9.06E+03 1.06E+04 CS138 2.78E-01 2.78E-01 2.78E-01 2.78E-01 2.78E-01 2.78E-01 2.78E-01 3.18E-01 BA139 8.79E-02 8.79E-02 8.79E-02 8.79E-02 8.79E-02 8.79E-02 8.79E-02 9.89E-02 BA140 1.81 E+01 1.81E+01 1.81 E+01 1.81E+01 1.81 E+01 1.81 E+01 1.81E+01 2.06E+01 BA141 2.92E-02 2.92E-02 2.92E-02 2.92E-02 2.92E-02 2.92E-02 2.92E-02 3.33E-02 BA142 2.67E-02 2.67E-02 2.67E-02 2.67E-02 2.67E-02 2.67E-02 2.67E-02 3.05E-02 LA140 1.69E+01 1.69E+01 1.69E+01 1.69E+01 1.69E+01 1.69E+01 1.69E+01 1.91 E+01 LA142 6.19E-01 6.19E-01 6.19E-01 6.19E-01 6.19E-01 6.19E-01 6.19E-01 7.43E-01 CE141 1.20E+01 1.20E+01 1.20E+01 1.20E+01 1.20E+01 1.20E+01 1.20E+01 1.35E+01 CE143 2.04E+OO 2.04E+OO 2.04E+OO 2.04E+OO 2.04E+OO 2.04E+OO 2.04E+OO 2.32E+OO CE144 6.12E+01 6.12E+01 6.12E+01 6.12E+01 6.12E+01 6.12E+01 6.12E+01 7.08E+01 PR143 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 PR144 1.27E-03 1.27E-03 1.27E-03 1.27E-03 1.27E-03 1.27E-03 1.27E-03 1.46E-03 ND147 7.46E+OO 7.46E+OO 7.46E+OO 7.46E+OO 7.46E+OO 7.46E+OO 7.46E+OO 8.95E+OO w 187 2.07E+OO 2.07E+OO 2.07E+OO 2.07E+OO 2.07E+OO 2.07E+OO 2.07E+OO 2.40E+OO NP239 1.50E+OO 1.50E+OO 1.50E+OO 1.50E+OO 1.50E+OO 1.50E+OO 1.50E+OO 1.74E+OO DAEC ODAM Page 220 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =TEENAGER PATHWAY= SWIMMING TOTAL BODY GI-LU BONE LIVER KIDNEY THYROID LUNG SKIN (mrem gaQ/(Ci min} H 3 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 c 14 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 NA24 1.75E+02 1.75E+02 1.75E+02 1.75E+02 1.75E+02 1.75E+02 1.75E+02 O.OOE-01 p 32 1.45E-01 1.45E-01 1.45E-01 1.45E-01 1.45E-01 1.45E-01 1.45E-01 O.OOE-01 CR 51 1.17E+OO 1.17E+OO 1.17E+OO 1.17E+OO 1.17E+OO 1.17E+OO 1.17E+OO O.OOE-01 MN 54 3.39E+01 3.39E+01 3.39E+01 3.39E+01 3.39E+01 3.39E+01 3.39E+01 O.OOE-01 MN 56 7.03E+01 7.03E+01 7.03E+01 7.03E+01 7.03E+01 7.03E+01 7.03E+01 O.OOE-01 FE 55 1.44E-03 1.44E-03 1.44E-03 1.44E-03 1.44E-03 1.44E-03 1.44E-03 O.OOE-01 FE 59 4.97E+01 4.97E+01 4.97E+01 4.97E+01 4.97E+01 4.97E+01 4.97E+01 O.OOE-01 C058 4.06E+01 4.06E+01 4.06E+01 4.06E+01 4.06E+01 4.06E+01 4.06E+01 O.OOE-01 C060 1.04E+02 1.04E+02 1.04E+02 1.04E+02 1.04E+02 1.04E+02 1.04E+02 O.OOE-01 Nl63 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl65 2.20E+01 2.20E+01 2.20E+01 2.20E+01 2.20E+01 2.20E+01 2.20E+01 O.OOE-01 cu 64 8.31 E+OO 8.31 E+OO 8.31 E+OO 8.31 E+OO 8.31E+OO 8.31 E+OO 8.31 E+OO O.OOE-01 ZN 65 2.48E+01 2.48E+01 2.48E+01 2.48E+01 2.48E+01 2.48E+01 2.48E+01 O.OOE-01 ZN 69 3.36E-02 3.36E-02 3.36E-02 3.36E-02 3.36E-02 3.36E-02 3.36E-02 O.OOE-01 BR 83 3.73E-01 3.73E-01 3.73E-01 3.73E-01 3.73E-01 3.73E-01 3.73E-01 O.OOE-01 BR 84 6.93E+01 6.93E+01 6.93E+01 6.93E+01 6.93E+01 6.93E+01 6.93E+01 O.OOE-01 BR 85 7.41 E-02 7.41 E-02 7.41 E-02 7.41E-02 7.41E-02 7.41 E-02 7.41E-02 O.OOE-01 RB 86 3.84E+OO 3.84E+OO 3.84E+OO 3.84E+OO 3.84E+OO 3.84E+OO 3.84E+OO O.OOE-01 RB 88 2.15E+01 2.15E+01 2.15E+01 2.15E+01 2.15E+01 2.15E+01 2.15E+01 O.OOE-01 RB 89 7.74E+01 7.74E+01 7.74E+01 7.74E+01 7.74E+01 7.74E+01 7.74E+01 O.OOE-01 SR 89 1.04E-01 1.04E-01 1.04E-01 1.04E-01 1.04E-01 1.04E-01 1.04E-01 O.OOE-01 SR 90 1.22E-02 1.22E-02 1.22E-02 1.22E-02 1.22E-02 1.22E-02 1.22E-02 O.OOE-01 SR 91 4.26E+01 4.26E+01 4.26E+01 4.26E+01 4.26E+01 4.26E+01 4.26E+01 O.OOE-01 SR 92 5.72E+01 5.72E+01 5.72E+01 5.72E+01 5.72E+01 5.72E+01 5.72E+01 O.OOE-01 y 90 2.93E-01 2.93E-01 2.93E-01 2.93E-01 2.93E-01 2.93E-01 2.93E-01 O.OOE-01 Y 91M 2.08E+01 2.08E+01 2.08E+01 2.08E+01 2.08E+01 2.08E+01 2.08E+01 O.OOE-01 y 91 1.51 E-01 1.51 E-01 1.51E-01 1.51 E-01 1.51 E-01 1.51 E-01 1.51 E-01 O.OOE-01 y 92 1.02E+01 1.02E+01 1.02E+01 1.02E+01 1.02E+01 1.02E+01 1.02E+01 O.OOE-01 y 93 4.26E+OO 4.26E+OO 4.26E+OO 4.26E+OO 4.26E+OO 4.26E+OO 4.26E+OO O.OOE-01 ZR 95 3.39E+01 3.39E+01 3.39E+01 3.39E+01 3.39E+01 3.39E+01 3.39E+01 O.OOE-01 ZR 97 3.37E+01 3.37E+01 3.37E+01 3.37E+01 3.37E+01 3.37E+01 3.37E+01 O.OOE-01 NB 95 3.16E+01 3.16E+01 3.16E+01 3.16E+01 3.16E+01 3.16E+01 3.16E+01 O.OOE-01 M099 1.06E+01 1.06E+01 1.06E+01 1.06E+01 1.06E+01 1.06E+01 1.06E+01 O.OOE-01 TC 99M 5.36E+OO 5.36E+OO 5.36E+OO 5.36E+OO 5.36E+OO 5.36E+OO 5.36E+OO O.OOE-01 TC101 1.14E+01 1.14E+01 1.14E+01 1.14E+01 1.14E+01 1.14E+01 1.14E+01 O.OOE-01 DAEC ODAM Page 221 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =TEENAGER PATHWAY= SWIMMING TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN {mrem gaQ/{Ci min} RU103 2.01E+01 2.01E+01 2.01E+01 2.01E+01 2.01E+01 2.01E+01 2.01E+01 O.OOE-01 RU105 2.67E+01 2.67E+01 2.67E+01 2.67E+01 2.67E+01 2.67E+01 2.67E+01 O.OOE-01 RU106 8.58E+OO 8.58E+OO 8.58E+OO 8.58E+OO 8.58E+OO 8.58E+OO 8.58E+OO O.OOE-01 AG110M 1.11E+02 1.11E+02 1.11E+02 1.11E+02 1.11E+02 1.11E+02 1.11E+02 O.OOE-01 TE125M 8.33E-02 8.33E-02 8.33E-02 8.33E-02 8.33E-02 8.33E-02 8.33E-02 O.OOE-01 TE127M 5.87E-03 5.87E-03 5.87E-03 5.87E-03 5.87E-03 5.87E-03 5.87E-03 O.OOE-01 TE127 6.28E-02 6.28E-02 6.28E-02 6.28E-02 6.28E-02 6.28E-02 6.28E-02 O.OOE-01 TE129M 4.74E+OO 4.74E+OO 4.74E+OO 4.74E+OO 4.74E+OO 4.74E+OO 4.74E+OO O.OOE-01 TE129 4.04E+OO 4.04E+OO 4.04E+OO 4.04E+OO 4.04E+OO 4.04E+OO 4.04E+OO O.OOE-01 TE131M 4.96E+01 4.96E+01 4.96E+01 4.96E+01 4.96E+01 4.96E+01 4.96E+01 O.OOE-01 TE131 1.41E+01 1.41E+01 1.41E-t-01 1.41E+01 1.41E+01 1.41E+01 1.41E+01 O.OOE-01 TE132 9.02E+OO 9.02E+OO 9.02E+OO 9.02E+OO 9.02E+OO 9.02E+OO 9.02E+OO O.OOE-01 1130 8.76E+01 8.76E+01 8.76E+01 8.76E+01 8.76E+01 8.76E+01 8.76E+01 O.OOE-01 I 131 1.76E+01 1.76E+01 1.76E+01 1.76E+01 1.76E+01 1.76E+01 1.76E+01 O.OOE-01 1132 9.64E+01 9.64E+01 9.64E+01 9.64E+01 9.64E+01 9.64E+01 9.64E+01 O.OOE-01 1133 2.16E+01 2.16E+01 2.16E+01 2.16E+01 2.16E+01 2.16E+01 2.16E+01 O.OOE-01 1134 8.76E+01 8.76E+01 8.76E+01 8.76E+01 8.76E+01 8.76E+01 8.76E+01 O.OOE-01 1135 7.37E+01 7.37E+01 7.37E+01 7.37E+01 7.37E+01 7.37E+01 7.37E+01 O.OOE-01 CS134 6.55E+01 6.55E+01 6.55E+01 6.55E+01 6.55E+01 6.55E+01 6.55E+01 O.OOE-01 CS136 9.26E+01 9.26E+01 9.26E+01 9.26E+01 9.26E+01 9.26E+01 9.26E+01 O.OOE-01 CS137 2.26E+01 2.26E+01 2.26E+01 2.26E+01 2.26E+01 2.26E+01 2.26E+01 O.OOE-01 CS138 7.94E+01 7.94E+01 7.94E+01 7.94E+01 7.94E+01 7.94E+01 7.94E+01 O.OOE-01 BA139 1.65E+OO 1.65E+OO 1.65E+OO 1.65E+OO 1.65E+OO 1.65E+OO 1.65E+OO O.OOE-01 BA140 1.11E+01 1.11E+01 1.11 E+01 1.11E+01 1.11E+01 1.11E+01 1.11E+01 O.OOE-01 BA141 1.98E+01 1.98E+01 1.98E+01 1.98E+01 1.98E+01 1.98E+01 1.98E+01 O.OOE-01 BA142 3.37E+01 3.37E+01 3.37E+01 3.37E+01 3.37E+01 3.37E+01 3.37E+01 O.OOE-01 LA140 9.24E+01 9.24E+01 9.24E+01 9.24E+01 9.24E+01 9.24E+01 9.24E+01 O.OOE-01 LA142 9.71E+01 9.71E+01 9.71E+01 9.71E+01 9.71E+01 9.71E+01 9.71E+01 O.OOE-01 CE141 2.93E+OO 2.93E+OO 2.93E+OO 2.93E+OO 2.93E+OO 2.93E+OO 2.93E+OO O.OOE-01 CE143 1.28E+01 1.28E+01 1.28E+01 1.28E+01 1.28E+01 1.28E+01 1.28E+01 O.OOE-01 CE144 1.94E+OO 1.94E+OO 1.94E+OO 1.94E+OO 1.94E+OO 1.94E+OO 1.94E+OO O.OOE-01 PR143 3.61E-02 3.61E-02 3.61 E-02 3.61E-02 3.61E-02 3.61E-02 3.61E-02 O.OOE-01 PR144 9.94E-01 9.94E-01 9.94E-01 9.94E-01 9.94E-01 9.94E-01 9.94E-01 O.OOE-01 ND147 6.32E+OO 6.32E+OO 6.32E+OO 6.32E+OO 6.32E+OO 6.32E+OO 6.32E+OO O.OOE-01 W187 1.87E+01 1.87E+01 1.87E+01 1.87E+01 1.87E+01 1.87E+01 1.87E+01 O.OOE-01 NP239 5.41E+OO 5.41E+OO 5.41 E+OO 5.41E+OO 5.41E+OO 5.41E+OO 5.41E+OO O.OOE-01 DAEC ODAM Page 222 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =TEENAGER PATHWAY= BOATING TOTAL BODY GI-LU BONE LIVER KIDNEY THYROID LUNG SKIN (mrem gaQ/(Ci min} H 3 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 c 14 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 NA24 1.01E+02 1.01E+02 1.01E+02 1.01E+02 1.01E+02 1.01E+02 1.01E+02 O.OOE-01 p 32 8.35E-02 8.35E-02 8.35E-02 8.35E-02 8.35E-02 8.35E-02 8.35E-02 O.OOE-01 CR 51 6.78E-01 6.78E-01 6.78E-01 6.78E-01 6.78E-01 6.78E-01 6.78E-01 O.OOE-01 MN 54 1.96E+01 1.96E+01 1.96E+01 1.96E+01 1.96E+01 1.96E+01 1.96E+01 O.OOE-01 MN 56 4.06E+01 4.06E+01 4.06E+01 4.06E+01 4.06E+01 4.06E+01 4.06E+01 O.OOE-01 FE 55 8.35E-04 8.35E-04 8.35E-04 8.35E-04 8.35E-04 8.35E-04 8.35E-04 O.OOE-01 FE 59 2.87E+01 2.87E+01 2.87E+01 2.87E+01 2.87E+01 2.87E+01 2.87E+01 O.OOE-01 co 58 2.35E+01 2.35E+01 2.35E+01 2.35E+01 2.35E+01 2.35E+01 2.35E+01 O.OOE-01 C060 6.00E+01 6.00E+01 6.00E+01 6.00E+01 6.00E+01 6.00E+01 6.00E+01 O.OOE-01 Nl63 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl65 1.27E+01 1.27E+01 1.27E+01 1.27E+01 1.27E+01 1.27E+01 1.27E+01 O.OOE-01 cu 64 4.80E+OO 4.80E+OO 4.80E+OO 4.80E+OO 4.80E+OO 4.80E+OO 4.80E+OO O.OOE-01 ZN 65 1.44E+01 1.44E+01 1.44E+01 1.44E+01 1.44E+01 1.44E+01 1.44E+01 O.OOE-01 ZN 69 1.94E-02 1.94E-02 1.94E-02 1.94E-02 1.94E-02 1.94E-02 1.94E-02 O.OOE-01 BR 83 2.15E-01 2.15E-01 2.15E-01 2.15E-01 2.15E-01 2.15E-01 2.15E-01 O.OOE-01 BR 84 4.01E+01 4.01E+01 4.01 E+01 4.01E+01 4.01E+01 4.01E+01 4.01E+01 O.OOE-01 BR 85 4.28E-02 4.28E-02 4.28E-02 4.28E-02 4.28E-02 4.28E-02 4.28E-02 O.OOE-01 RB 86 2.22E+OO 2.22E+OO 2.22E+OO 2.22E+OO 2.22E+OO 2.22E+OO 2.22E+OO O.OOE-01 RB 88 1.24E+01 1.24E+01 1.24E+01 1.24E+01 1.24E+01 1.24E+01 1.24E+01 O.OOE-01 RB 89 4.47E+01 4.47E+01 4.47E+01 4.47E+01 4.47E+01 4.47E+01 4.47E+01 O.OOE-01 SR 89 6.00E-02 6.00E-02 6.00E-02 6.00E-02 6.00E-02 6.00E-02 6.00E-02 O.OOE-01 SR 90 7.04E-03 7.04E-03 7.04E-03 7.04E-03 7.04E-03 7.04E-03 7.04E-03 O.OOE-01 SR 91 2.46E+01 2.46E+01 2.46E+01 2.46E+01 2.46E+01 2.46E+01 2.46E+01 0.00E-01 SR 92 3.31E+01 3.31 E+01 3.31 E+01 3.31E+01 3.31E+01 3.31E+01 3.31E+01 O.OOE-01 y 90 1.69E-01 1.69E-01 1.69E-01 1.69E-01 1.69E-01 1.69E-01 1.69E-01 O.OOE-01 Y 91M 1.20E+01 1.20E+01 1.20E+01 1.20E+01 1.20E+01 1.20E+01 1.20E+01 O.OOE-01 y 91 8.74E-02 8.74E-02 8.74E-02 8.74E-02 8.74E-02 8.74E-02 8.74E-02 O.OOE-01 y 92 5.89E+OO 5.89E+OO 5.89E+OO 5.89E+OO 5.89E+OO 5.89E+OO 5.89E+OO O.OOE-01 y 93 2.46E+OO 2.46E+OO 2.46E+OO 2.46E+OO 2.46E+OO 2.46E+OO 2.46E+OO O.OOE-01 ZR 95 1.96E+01 1.96E+01 1.96E+01 1.96E+01 1.96E+01 1.96E+01 1.96E+01 O.OOE-01 ZR 97 1.95E+01 1.95E+01 1.95E+01 1.95E+01 1.95E+01 1.95E+01 1.95E+01 O.OOE-01 NB 95 1.83E+01 1.83E+01 1.83E+01 1.83E+01 1.83E+01 1.83E+01 1.83E+01 O.OOE-01 M099 6.12E+OO 6.12E+OO 6.12E+OO 6.12E+OO 6.12E+OO 6.12E+OO 6.12E+OO O.OOE-01 TC99M 3.10E+OO 3.10E+OO 3.10E+OO 3.10E+OO 3.10E+OO 3.10E+OO 3.10E+OO O.OOE-01 TC101 6.62E+OO 6.62E+OO 6.62E+OO 6.62E+OO 6.62E+OO 6.62E+OO 6.62E+OO O.OOE-01 DAEC ODAM Page 223 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =TEENAGER PATHWAY= BOATING TOTAL BODY GI-LU BONE LIVER KIDNEY THYROID LUNG SKIN {mrem gaQ/{Ci min} -----RU103 1.16E+01 1.16E+01 1.16E+01 1.16E+01 1.16E+01 1.16E+01 1.16E+01 O.OOE-01 RU105 1.54E+01 1.54E+01 1.54E+01 1.54E+01 1.54E+01 1.54E+01 1.54E+01 O.OOE-01 RU106 4.96E+OO 4.96E+OO 4.96E+OO 4.96E+OO 4.96E+OO 4.96E+OO 4.96E+OO O.OOE-01 AG110M 6.39E+01 6.39E+01 6.39E+01 6.39E+01 6.39E+01 6.39E+01 6.39E+01 O.OOE-01 TE125M 4.81E-02 4.81E-02 4.81E-02 4.81 E-02 4.81E-02 4.81E-02 4.81E-02 O.OOE-01 TE127M 3.39E-03 3.39E-03 3.39E-03 3.39E-03 3.39E-03 3.39E-03 3.39E-03 O.OOE-01 TE127 3.63E-02 3.63E-02 3.63E-02 3.63E-02 3.63E-02 3.63E-02 3.63E-02 O.OOE-01 TE129M 2.74E+OO 2.74E+OO 2.74E+OO 2.74E+OO 2.74E+OO 2.74E+OO 2.74E+OO O.OOE-01 TE129 2.34E+OO 2.34E+OO 2.34E+OO 2.34E+OO 2.34E+OO 2.34E+OO 2.34E+OO O.OOE-01 TE131M 2.86E+01 2.86E+01 2.86E+01 2.86E+01 2.86E+01 2.86E+01 2.86E+01 O.OOE-01 TE131 8.18E+OO 8.18E+OO 8.18E+OO 8.18E+OO 8.18E+OO 8.18E+OO 8.18E+OO O.OOE-01 TE132 5.21 E+OO 5.21E+OO 5.21E+OO 5.21E+OO 5.21E+OO 5.21 E+OO 5.21 E+OO O.OOE-01 1130 5.06E+01 5.06E+01 5.06E+01 5.06E+01 5.06E+01 5.06E+01 5.06E+01 O.OOE-01 I 131 1.02E+01 1.02E+01 1.02E+01 1.02E+01 1.02E+01 1.02E+01 1.02E+01 O.OOE-01 1132 5.57E+01 5.57E+01 5.57E+01 5.57E+01 5.57E+01 5.57E+01 5.57E+01 O.OOE-01 1133 1.25E+01 1.25E+01 1.25E+01 1.25E+01 1.25E+01 1.25E+01 1.25E+01 O.OOE-01 I 134 5.06E+01 5.06E+01 5.06E+01 5.06E+01 5.06E+01 5.06E+01 5.06E+01 O.OOE-01 1135 4.26E+01 4.26E+01 4.26E+01 4.26E+01 4.26E+01 4.26E+01 4.26E+01 O.OOE-01 CS134 3.78E+01 3.78E+01 3.78E+01 3.78E+01 3.78E+01 3.78E+01 3.78E+01 O.OOE-01 CS136 5.35E+01 5.35E+01 5.35E+01 5.35E+01 5.35E+01 5.35E+01 5.35E+01 O.OOE-01 CS137 1.31 E+01 1.31 E+01 1.31E+01 1.31E+01 1.31E+01 1.31 E+01 1.31 E+01 O.OOE-01 CS138 4.59E+01 4.59E+01 4.59E+01 4.59E+01 4.59E+01 4.59E+01 4.59E+01 O.OOE-01 BA139 9.55E-01 9.55E-01 9.55E-01 9.55E-01 9.55E-01 9.55E-01 9.55E-01 O.OOE-01 BA140 6.39E+OO 6.39E+OO 6.39E+OO 6.39E+OO 6.39E+OO 6.39E+OO 6.39E+OO O.OOE-01 BA141 1.14E+01 1.14E+01 1.14E+01 1.14E+01 1.14E+01 1.14E+01 1.14E+01 O.OOE-01 BA142 1.95E+01 1.95E+01 1.95E+01 1.95E+01 1.95E+01 1.95E+01 1.95E+01 O.OOE-01 LA140 5.34E+01 5.34E+01 5.34E+01 5.34E+01 5.34E+01 5.34E+01 5.34E+01 O.OOE-01 LA142 5.61E+01 5.61E+01 5.61E+01 5.61E+01 5.61E+01 5.61E+01 5.61E+01 O.OOE-01 CE141 1.70E+OO 1.70E+OO 1.70E+OO 1.70E+OO 1.70E+OO 1.70E+OO 1.70E+OO O.OOE-01 CE143 7.42E+OO 7.42E+OO 7.42E+OO 7.42E+OO 7.42E+OO 7.42E+OO 7.42E+OO O.OOE-01 CE144 1.12E+OO 1.12E+OO 1.12E+OO 1.12E+OO 1.12E+OO 1.12E+OO 1.12E+OO O.OOE-01 PR143 2.09E-02 2.09E-02 2.09E-02 2.09E-02 2.09E-02 2.09E-02 2.09E-02 O.OOE-01 PR144 5.74E-01 5.74E-01 5.74E-01 5.74E-01 5.74E-01 5.74E-01 5.74E-01 O.OOE-01 ND147 3.65E+OO 3.65E+OO 3.65E+OO 3.65E+OO 3.65E+OO 3.65E+OO 3.65E+OO O.OOE-01 W187 1.08E+01 1.08E+01 1.08E+01 1.08E+01 1.08E+01 1.08E+01 1.08E+01 O.OOE-01 NP239 3.13E+OO 3.13E+OO 3.13E+OO 3.13E+OO 3.13E+OO 3.13E+OO 3.13E+OO O.OOE-01 DAEC ODAM Page 224 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =CHILD PATHWAY= POTABLE WATER TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN (mrem gal}/(Ci min} H 3 2.97E+01 2.97E+01 O.OOE-01 2.97E+01 2.97E+01 2.97E+01 2.97E+01 O.OOE-01 c 14 6.19E+02 6.19E+02 3.10E+03 6.19E+02 6.19E+02 6.19E+02 6.19E+02 O.OOE-01 NA24 4.91 E+02 4.91 E+02 4.91 E+02 4.91E+02 4.91E+02 4.91 E+02 4.91E+02 O.OOE-01 p 32 7.75E+03 5.56E+03 2.01 E+05 9.41E+03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CR 51 2.22E+OO 1.18E+02 O.OOE-01 O.OOE-01 3.37E-01 1.23E+OO 2.25E+OO O.OOE-01 MN 54 7.28E+02 2.29E+03 O.OOE-01 2.73E+03 7.66E+02 O.OOE-01 O.OOE-01 O.OOE-01 MN 56 2.96E-02 1.90E+01 O.OOE-01 1.31 E-01 1.59E-01 O.OOE-01 O.OOE-01 O.OOE-01 FE 55 4.83E+02 2.89E+02 2.94E+03 1.56E+03 O.OOE-01 O.OOE-01 8.82E+02 O.OOE-01 FE 59 3.35E+03 7.00E+03 4.16E+03 6.73E+03 O.OOE-01 O.OOE-01 1.95E+03 O.OOE-01 co 58 1.40E+03 2.66E+03 O.OOE-01 4.56E+02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 C060 3.99E+03 7.50E+03 O.OOE-01 1.35E+03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl63 4.68E+03 4.96E+02 1.38E+05 7.37E+03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl65 4.24E-02 8.90E+OO 7.72E-01 7.27E-02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 cu 64 1.02E+01 7.91E+02 O.OOE-01 1.69E+01 4.07E+01 O.OOE-01 O.OOE-01 O.OOE-01 ZN 65 5.79E+03 1.64E+03 3.50E+03 9.31E+03 5.87E+03 O.OOE-01 O.OOE-01 O.OOE-01 ZN 69 3.61E-08 2.47E-05 2.71E-07 3.91E-07 2.37E-07 O.OOE-01 O.OOE-01 O.OOE-01 BR 83 4.17E-02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 84 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 85 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 86 1.02E+04 1.06E+03 O.OOE-01 1.65E+04 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 88 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 89 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 SR 89 9.52E+03 1.29E+04 3.33E+05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 90 1.32E+05 5.86E+04 6.55E+06 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 91 4.01E+01 2.35E+03 1.06E+03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 92 2.01 E-01 9.48E+01 5.01 E+OO O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 90 2.17E-01 2.31 E+04 8.12E+OO O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Y 91M O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 91 4.07E+OO 2.03E+04 1.52E+02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 92 2.44E-04 2.46E+02 8.52E-03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 93 1.54E-02 8.35E+03 5.60E-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 95 5.75E+OO 6.73E+03 2.94E+01 6.46E+OO 9.24E+OO O.OOE-01 O.OOE-01 O.OOE-01 ZR 97 5.70E-02 1.46E+04 6.68E-01 9.65E-02 1.39E-01 O.OOE-01 O.OOE-01 O.OOE-01 NB 95 1.57E+OO 4.06E+03 5.65E+OO 2.20E+OO 2.07E+OO O.OOE-01 O.OOE-01 O.OOE-01 M099 6.54E+02 2.19E+03 O.OOE-01 2.64E+03 5.65E+03 O.OOE-01 O.OOE-01 O.OOE-01 TC 99M 4.84E-01 1.66E+01 1.49E-02 2.92E-02 4.24E-01 O.OOE-01 1.48E-02 O.OOE-01 TC101 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 DAEC ODAM Page 225 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =CHILD PATHWAY= POTABLE WATER TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN (mrem gal)/(Ci min) RU103 7.07E+01 4.75E+03 1.84E+02 O.OOE-01 4.63E+02 O.OOE-01 O.OOE-01 O.OOE-01 RU105 1.41E-01 2.53E+02 3.88E-01 O.OOE-01 3.41E+OO O.OOE-01 O.OOE-01 O.OOE-01 RU106 3.73E+02 4.65E+04 2.99E+03 O.OOE-01 4.04E+03 O.OOE-01 O.OOE-01 O.OOE-01 AG110M 7.43E+01 1.10E+04 1.38E+02 9.29E+01 1.73E+02 O.OOE-01 O.OOE-01 O.OOE-01 TE125M 3.84E+02 2.78E+03 2.88E+03 7.81E+02 O.OOE-01 8.09E+02 O.OOE-01 O.OOE-01 TE127M 8.72E+02 5.95E+03 7.35E+03 1.98E+03 2.09E+04 1.76E+03 O.OOE-01 O.OOE-01 TE127 4.36E+OO 7.94E+02 2.03E+01 5.48E+OO 5.78E+01 1.41E+01 O.OOE-01 O.OOE-01 TE129M 1.89E+03 1.49E+04 1.22E+04 3.41E+03 3.58E+04 3.94E+03 O.OOE-01 O.OOE-01 TE129 4.81E-06 1.26E-03 2.02E-05 5.65E-06 5.92E-05 1.44E-05 O.OOE-01 O.OOE-01 TE131M 3.89E+02 1.48E+04 1.06E+03 3.66E+02 3.54E+03 7.52E+02 O.OOE-01 O.OOE-01 TE131 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE132 1.12E+03 9.31 E+03 2.09E+03 9.25E+02 8.59E+03 1.35E+03 O.OOE-01 O.OOE-01 1130 2.02E+02 1.83E+02 1.94E+02 3.92E+02 5.86E+02 4.32E+04 O.OOE-01 O.OOE-01 I 131 2.31 E+03 3.61 E+02 4.04E+03 4.06E+03 6.67E+03 1.34E+06 O.OOE-01 O.OOE-01 1132 1.25E-01 3.20E-01 1.48E-01 2.72E-01 4.17E-01 1.26E+01 O.OOE-01 O.OOE-01 1133 3.19E+02 3.39E+02 6.81 E+02 8.42E+02 1.40E+03 1.56E+05 O.OOE-01 O.OOE-01 1134 5.09E-07 7.34E-07 5.96E-07 1.11 E-06 1.69E-06 2.55E-05 O.OOE-01 O.OOE-01 1135 3.06E+01 4.93E+01 3.59E+01 6.47E+01 9.92E+01 5.73E+03 O.OOE-01 O.OOE-01 CS134 2.07E+04 5.29E+02 5.98E+04 9.82E+04 3.04E+04 O.OOE-01 1.09E+04 O.OOE-01 CS136 1.01E+04 5.51 E+02 5.70E+03 1.57E+04 8.35E+03 O.OOE-01 1.24E+03 O.OOE-01 CS137 1.18E+04 5.02E+02 8.37E+04 8.01E+04 2.61 E+04 O.OOE-01 9.39E+03 O.OOE-01 CS138 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BA139 1.71E-05 3.41 E-02 5.91E-04 3.16E-07 2.76E-07 O.OOE-01 1.86E-07 O.OOE-01 BA140 1.18E+03 1.02E+04 2.01 E+04 1.76E+01 5.74E+OO O.OOE-01 1.05E+01 O.OOE-01 BA141 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BA142 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 LA140 2.01 E-01 1.67E+04 1.71E+OO 5.98E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 LA142 2.73E-07 1.73E-01 2.74E-06 8.72E-07 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CE141 7.37E-01 6.19E+03 9.94E+OO 4.96E+OO 2.17E+OO O.OOE-01 O.OOE-01 O.OOE-01 CE143 8.51E-02 8.60E+03 1.08E+OO 5.87E+02 2.46E-01 O.OOE-01 O.OOE-01 O.OOE-01 CE144 2.83E+01 4.34E+04 5.31 E+02 1.66E+02 9.22E+01 O.OOE-01 O.OOE-01 O.OOE-01 PR143 4.74E-01 1.03E+04 9.56E+OO 2.87E+OO 1.55E+OO O.OOE-01 O.OOE-01 O.OOE-01 PR144 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ND147 4.21E-01 8.61 E+03 6.71 E+OO 5.43E+OO 2.98E+OO O.OOE-01 O.OOE-01 O.OOE-01 w 187 1.46E+01 4.56E+03 5.48E+01 3.24E+01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 NP239 5.05E-02 5.32E+03 1.00E+OO 7.19E-02 2.08E-01 O.OOE-01 O.OOE-01 O.OOE-01 DAEC ODAM Page 226 of 280 Rev.37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =CHILD PATHWAY= FRESH WATER FISH TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN (mrem gaQ/(Ci min} H 3 3.61 E-01 3.61 E-01 O.OOE-01 3.61 E-01 3.61 E-01 3.61 E-01 3.61 E-01 O.OOE-01 c 14 3.85E+04 3.85E+04 1.93E+05 3.85E+04 3.85E+04 3.85E+04 3.85E+04 O.OOE-01 NA24 6.61 E+02 6.61 E+02 6.61 E+02 6.61 E+02 6.61 E+02 6.61E+02 6.61 E+02 O.OOE-01 p 32 1.05E+07 7.52E+06 2.72E+08 1.27E+07 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CR 51 6.01 E+OO 3.19E+02 O.OOE-01 O.OOE-01 9.12E-01 3.34E+OO 6.09E+OO O.OOE-01 MN 54 3.94E+03 1.24E+04 O.OOE-01 1.48E+04 4.15E+03 O.OOE-01 O.OOE-01 O.OOE-01 MN 56 1.56E-01 1.00E+02 O.OOE-01 6.91 E-01 8.35E-01 O.OOE-01 O.OOE-01 O.OOE-01 FE55 6.54E+02 3.91E+02 3.98E+03 2.11E+03 O.OOE-01 O.OOE-01 1.19E+03 O.OOE-01 FE 59 4.53E+03 9.48E+03 5.62E+03 9.10E+03 O.OOE-01 O.OOE-01 2.64E+03 O.OOE-01 co 58 9.45E+02 1.80E+03 O.OOE-01 3.09E+02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 C060 2.70E+03 5.07E+03 O.OOE-01 9.15E+02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl63 6.34E+03 6.72E+02 1.86E+05 9.97E+03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl65 5.58E-02 1.17E+01 1.02E+OO 9.57E-02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 cu 64 6.85E+OO 5.32E+02 O.OOE-01 1.13E+01 2.74E+01 O.OOE-01 O.OOE-01 O.OOE-01 ZN 65 1.57E+05 4.43E+04 9.46E+04 2.52E+05 1.59E+05 O.OOE-01 O.OOE-01 O.OOE-01 ZN 69 9.09E-07 6.20E-04 6.81 E-06 9.84E-06 5.97E-06 O.OOE-01 O.OOE-01 O.OOE-01 BR 83 2.30E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 84 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 85 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 86 2.75E+05 2.88E+04 O.OOE-01 4.47E+05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 88 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 89 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 89 3.86E+03 5.23E+03 1.35E+05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 90 5.35E+04 2.38E+04 2.66E+06 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 SR 91 1.62E+01 9.46E+02 4.28E+02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 92 7.94E-02 3.75E+01 1.98E+OO O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 90 7.34E-02 7.81E+03 2.74E+OO O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Y 91M O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 91 1.38E+OO 6.86E+03 5.15E+01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 92 8.09E-05 8.17E+01 2.83E-03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 93 5.17E-03 2.81 E+03 1.88E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 95 2.57E-01 3.01 E+02 1.31E+OO 2.88E-01 4.12E-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 97 2.53E-03 6.50E+02 2.97E-02 4.29E-03 6.16E-03 O.OOE-01 O.OOE-01 O.OOE-01 NB 95 6.37E+02 1.65E+06 2.29E+03 8.92E+02 8.38E+02 O.OOE-01 O.OOE-01 O.OOE-01 M099 8.84E+01 2.96E+02 O.OOE-01 3.57E+02 7.63E+02 O.OOE-01 O.OOE-01 O.OOE-01 TC 99M 9.?0E-02 3.33E+OO 2.98E-03 5.85E-03 8.51E-02 O.OOE-01 2.97E-03 O.OOE-01 TC101 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 DAEC ODAM Page 227 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =CHILD PATHWAY= FRESH WATER FISH TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN (mrem gal)/(Ci min) RU103 9.56E+OO 6.43E+02 2.49E+01 O.OOE-01 6.26E+01 O.OOE-01 O.OOE-01 O.OOE-01 RU105 1.BBE-02 3.38E+01 5.17E-02 O.OOE-01 4.55E-01 O.OOE-01 O.OOE-01 O.OOE-01 RU106 5.05E+01 6.29E+03 4.04E+02 O.OOE-01 5.46E+02 O.OOE-01 O.OOE-01 O.OOE-01 AG110M 2.31 E+OO 3.44E+02 4.28E+OO 2.89E+OO 5.38E+OO O.OOE-01 O.OOE-01 O.OOE-01 TE125M 2.08E+03 1.50E+04 1.56E+04 4.23E+03 O.OOE-01 4.38E+03 O.OOE-01 O.OOE-01 TE127M 4.72E+03 3.22E+04 3.98E+04 1.07E+04 1.13E+05 9.51 E+03 O.OOE-01 O.OOE-01 TE127 2.34E+01 4.27E+03 1.09E+02 2.95E+01 3.11E+02 7.56E+01 O.OOE-01 O.OOE-01 TE129M 1.03E+04 8.06E+04 6.61 E+04 1.84E+04 1.94E+05 2.13E+04 O.OOE-01 O.OOE-01 TE129 2.45E-05 6.42E-03 1.03E-04 2.88E-05 3.02E-04 7.36E-05 O.OOE-01 O.OOE-01 TE131M 2.10E+03 8.01E+04 5.71E+03 1.98E+03 1.91E+04 4.06E+03 O.OOE-01 O.OOE-01 TE131 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE132 6.04E+03 5.03E+04 1.13E+04 5.00E+03 4.64E+04 7.28E+03 O.OOE-01 O.OOE-01 I 130 4.08E+01 3.70E+01 3.92E+01 7.92E+01 1.18E+02 8.72E+03 O.OOE-01 O.OOE-01 I 131 4.68E+02 7.33E+01 8.19E+02 8.24E+02 1.35E+03 2.72E+05 O.OOE-01 O.OOE-01 1132 2.46E-02 6.31E-02 2.92E-02 5.36E-02 8.20E-02 2.49E+OO O.OOE-01 O.OOE-01 1133 6.45E+01 6.87E+01 1.38E+02 1.70E+02 2.84E+02 3.17E+04 O.OOE-01 0.00E-01 I 134 9.55E-08 1.38E-07 1.12E-07 2.0?E-07 3.17E-07 4.77E-06 O.OOE-01 O.OOE-01 1135 6.14E+OO 9.90E+OO 7.22E+OO 1.30E+01 1.99E+01 1.15E+03 O.OOE-01 O.OOE-01 CS134 5.60E+05 1.43E+04 1.62E+06 2.66E+06 8.23E+05 0.00E-01 2.95E+05 O.OOE-01 CS136 2.74E+05 1.49E+04 1.54E+05 4.24E+05 2.26E+05 O.OOE-01 3.37E+04 O.OOE-01 CS137 3.20E+05 1.36E+04 2.26E+06 2.17E+06 7.06E+05 O.OOE-01 2.54E+05 O.OOE-01 CS138 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 BA139 8.82E-07 1.76E-03 3.04E-05 1.62E-08 1.42E-08 O.OOE-01 9.56E-09 O.OOE-01 BA140 6.36E+01 5.52E+02 1.09E+03 9.55E-01 3.11 E-01 O.OOE-01 5.69E-01 O.OOE-01 BA141 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BA142 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 LA140 6.BOE-02 5.63E+03 5.77E-01 2.02E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 LA142 8.83E-08 5.59E-02 8.85E-07 2.82E-07 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CE141 9.96E-03 8.37E+01 1.34E-01 6.71E-02 2.94E-02 O.OOE-01 O.OOE-01 O.OOE-01 CE143 1.15E-03 1.16E+02 1.46E-02 7.93E+OO 3.32E-03 O.OOE-01 O.OOE-01 O.OOE-01 CE144 3.83E-01 5.87E+02 7.18E+OO 2.25E+OO 1.25E+OO O.OOE-01 O.OOE-01 O.OOE-01 PR143 1.60E-01 3.49E+03 3.23E+OO 9.?0E-01 5.25E-01 O.OOE-01 O.OOE-01 O.OOE-01 PR144 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ND147 1.42E-01 2.91 E+03 2.27E+OO 1.84E+OO 1.01E+OO O.OOE-01 O.OOE-01 O.OOE-01 W187 2.36E+02 7.38E+04 8.86E+02 5.25E+02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 NP239 6.83E-03 7.19E+02 1.35E-01 9.72E-03 2.81E-02 O.OOE-01 O.OOE-01 O.OOE-01 DAEC ODAM Page 228 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =CHILD PATHWAY= FRESH WATER INVERTEBRATES TOTAL BODY GI-LU BONE LIVER KIDNEY THYROID LUNG SKIN (mrem 9al)/(Ci min) H 3 8.90E-02 8.90E-02 O.OOE-01 8.90E-02 8.90E-02 8.90E-02 8.90E-02 O.OOE-01 c 14 1.88E+04 1.88E+04 9.39E+04 1.88E+04 1.88E+04 1.88E+04 1.88E+04 O.OOE-01 NA24 3.26E+02 3.26E+02 3.26E+02 3.26E+02 3.26E+02 3.26E+02 3.26E+02 O.OOE-01 p 32 5.17E+05 3.70E+05 1.34E+07 6.27E+05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CR 51 1.48E+01 7.85E+02 O.OOE-01 O.OOE-01 2.25E+OO 8.22E+OO 1.50E+01 O.OOE-01 MN 54 2.18E+05 6.88E+05 O.OOE-01 8.20E+05 2.30E+05 O.OOE-01 O.OOE-01 O.OOE-01 MN 56 8.64E+OO 5.55E+03 O.OOE-01 3.83E+01 4.63E+01 O.OOE-01 O.OOE-01 O.OOE-01 FE 55 5.16E+03 3.08E+03 3.14E+04 1.66E+04 O.OOE-01 O.OOE-01 9.41E+03 O.OOE-01 FE 59 3.57E+04 7.47E+04 4.43E+04 7.18E+04 O.OOE-01 O.OOE-01 2.08E+04 O.OOE-01 C058 9.31 E+02 1.77E+03 O.OOE-01 3.04E+02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 co 60 2.66E+03 5.00E+03 O.OOE-01 9.02E+02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl63 1.56E+03 1.65E+02 4.59E+04 2.46E+03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl65 1.38E-02 2.89E+OO 2.50E-01 2.36E-02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 cu 64 1.35E+01 1.05E+03 O.OOE-01 2.24E+01 5.40E+01 O.OOE-01 O.OOE-01 O.OOE-01 ZN 65 1.93E+05 5.45E+04 1.16E+05 3.10E+05 1.96E+05 O.OOE-01 O.OOE-01 O.OOE-01 ZN 69 1.12E-06 7.64E-04 8.39E-06 1.21 E-05 7.35E-06 O.OOE-01 O.OOE-01 O.OOE-01 BR 83 4.46E-02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 84 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 85 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 86 3.39E+04 3.54E+03 O.OOE-01 5.51E+04 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 88 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 89 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 89 3.17E+03 4.30E+03 1.11 E+05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 90 4.39E+04 1.95E+04 2.18E+06 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 91 1.33E+01 7.77E+02 3.52E+02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 92 6.52E-02 3.08E+01 1.63E+OO O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 90 7.23E-01 7.69E+04 2.70E+01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Y 91M O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 91 1.36E+01 6.76E+04 5.07E+02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 92 7.97E-04 8.05E+02 2.79E-02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 93 5.09E-02 2.76E+04 1.85E+OO O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 95 1.28E-01 1.50E+02 6.56E-01 1.44E-01 2.06E-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 97 1.27E-03 3.25E+02 1.49E-02 2.15E-03 3.08E-03 O.OOE-01 O.OOE-01 O.OOE-01 NB 95 5.24E-01 1.35E+03 1.88E+OO 7.33E-01 6.88E-01 0.00E-01 O.OOE-01 O.OOE-01 MO 99 2.18E+01 7.28E+01 O.OOE-01 8.81E+01 1.88E+02 O.OOE-01 O.OOE-01 O.OOE-01 TC 99M 7.97E-03 2.74E-01 2.45E-04 4.81E-04 6.98E-03 O.OOE-01 2.44E-04 O.OOE-01 TC101 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 DAEC ODAM Page 229 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =CHILD PATHWAY= FRESH WATER INVERTEBRATES TOTAL BODY GI-LU BONE LIVER KIDNEY THYROID LUNG SKIN (mrem gal)/(Ci min) RU103 7.07E+01 4.75E+03 1.84E+02 O.OOE-01 4.63E+02 O.OOE-01 O.OOE-01 O.OOE-01 RU105 1.39E-01 2.49E+02 3.82E-01 O.OOE-01 3.36E+OO O.OOE-01 O.OOE-01 O.OOE-01 RU106 3.73E+02 4.65E+04 2.99E+03 O.OOE-01 4.04E+03 O.OOE-01 O.OOE-01 O.OOE-01 AG110M 1.91E+02 2.84E+04 3.53E+02 2.38E+02 4.44E+02 0.00E-01 O.OOE-01 O.OOE-01 TE125M 7.81E+03 5.66E+04 5.86E+04 1.59E+04 O.OOE-01 1.64E+04 O.OOE-01 O.OOE-01 TE127M 1.77E+04 1.21E+05 1.49E+05 4.02E+04 4.26E+05 3.57E+04 O.OOE-01 O.OOE-01 TE127 8.80E+01 1.60E+04 4.10E+02 1.11 E+02 1.17E+03 2.84E+02 O.OOE-01 O.OOE-01 TE129M 3.85E+04 3.03E+05 2.48E+05 6.93E+04 7.29E+05 8.00E+04 O.OOE-01 O.OOE-01 TE129 9.20E-05 2.41E-02 3.BBE-04 1.0BE-04 1.14E-03 2.77E-04 O.OOE-01 O.OOE-01 TE131M 7.90E+03 3.01E+05 2.15E+04 7.42E+03 7.18E+04 1.53E+04 O.OOE-01 O.OOE-01 TE131 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 TE132 2.27E+04 1.89E+05 4.25E+04 1.88E+04 1.74E+05 2.74E+04 O.OOE-01 O.OOE-01 1130 3.35E+OO 3.04E+OO 3.22E+OO 6.50E+OO 9.72E+OO 7.16E+02 O.OOE-01 O.OOE-01 I 131 3.85E+01 6.02E+OO 6.73E+01 6.77E+01 1.11 E+02 2.24E+04 O.OOE-01 O.OOE-01 1132 2.02E-03 5.18E-03 2.40E-03 4.40E-03 6.73E-03 2.04E-01 O.OOE-01 O.OOE-01 1133 5.30E+OO 5.64E+OO 1.13E+01 1.40E+01 2.33E+01 2.60E+03 O.OOE-01 O.OOE-01 1134 7.84E-09 1.13E-08 9.18E-09 1.70E-08 2.61E-08 3.92E-07 O.OOE-01 O.OOE-01 1135 5.04E-01 8.13E-01 5.93E-01 1.07E+OO 1.64E+OO 9.45E+01 O.OOE-01 O.OOE-01 CS134 6.90E+04 1.76E+03 1.99E+05 3.27E+05 1.01E+05 O.OOE-01 3.64E+04 O.OOE-01 CS136 3.38E+04 1.84E+03 1.90E+04 5.23E+04 2.78E+04 O.OOE-01 4.15E+03 O.OOE-01 CS137 3.94E+04 1.67E+03 2.79E+05 2.67E+05 8.70E+04 O.OOE-01 3.13E+04 O.OOE-01 CS138 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BA139 1.09E-05 2.16E-02 3.75E-04 2.00E-07 1.75E-07 O.OOE-01 1.18E-07 O.OOE-01 BA140 7.84E+02 6.80E+03 1.34E+04 1.18E+01 3.83E+OO O.OOE-01 7.01 E+OO O.OOE-01 BA141 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 BA142 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 LA140 6.70E-01 5.54E+04 5.69E+OO 1.99E+OO O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 LA142 8.70E-07 5.51 E-01 8.72E-06 2.78E-06 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CE141 2.45E+OO 2.06E+04 3.32E+01 1.65E+01 7.25E+OO O.OOE-01 O.OOE-01 O.OOE-01 CE143 2.83E-01 2.86E+04 3.60E+OO 1.95E+03.

8.19E-01 O.OOE-01 O.OOE-01 O.OOE-01 CE144 9.45E+01 1.45E+05 1.77E+03 5.55E+02 3.07E+02 O.OOE-01 O.OOE-01 O.OOE-01 PR143 1.58E+OO 3.44E+04 3.19E+01 9.56E+OO 5.18E+OO O.OOE-01 O.OOE-01 O.OOE-01 PR144 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ND147 1.40E+OO 2.87E+04 2.24E+01 1.81E+01 9.94E+OO O.OOE-01 O.OOE-01 O.OOE-01 W187 4.84E-01 1.51E+02 1.82E+OO 1.08E+OO O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 NP239 6.73E-02 7.09E+03 1.33E+OO 9.58E-02 2.77E-01 O.OOE-01 O.OOE-01 O.OOE-01 DAEC ODAM Page 230 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =CHILD PATHWAY= IRRIGATED FRESH LEAFY VEGETABLES TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN (mrem gal)/(Ci min) H 3 1.51E+OO 1.51E+OO O.OOE-01 1.51E+OO 1.51E+OO 1.51E+OO 1.51E+OO O.OOE-01 c 14 3.51 E+03 3.51 E+03 1.75E+04 3.51E+03 3.51 E+03 3.51 E+03 3.51 E+03 O.OOE-01 NA24 8.63E+OO 8.63E+OO 8.63E+OO 8.63E+OO 8.63E+OO 8.63E+OO 8.63E+OO O.OOE-01 p 32 1.70E+03 1.22E+03 4.42E+04 2.07E+03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CR 51 6.25E-01 3.32E+01 O.OOE-01 O.OOE-01 9.48E-02 3.47E-01 6.33E-01 O.OOE-01 MN 54 2.87E+02 9.05E+02 O.OOE-01 1.08E+03 3.02E+02 O.OOE-01 O.OOE-01 O.OOE-01 MN 56 7.35E-05 4.72E-02 O.OOE-01 3.26E-04 3.94E-04 O.OOE-01 O.OOE-01 O.OOE-01 FE 55 1.94E+02 1.16E+02 1.18E+03 6.28E+02 O.OOE-01 O.OOE-01 3.55E+02 O.OOE-01 FE 59 1.07E+03 2.24E+03 1.33E+03 2.15E+03 O.OOE-01 O.OOE-01 6.24E+02 O.OOE-01 co 58 4.86E+02 9.27E+02 O.OOE-01 1.59E+02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 C060 1.63E+03 3.06E+03 O.OOE-01 5.53E+02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl63 1.99E+03 2.11E+02 5.84E+04 3.13E+03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl65 1.03E-04 2.16E-02 1.87E-03 1.76E-04 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 cu 64 1.50E-01 1.17E+01 O.OOE-01 2.49E-01 6.02E-01 O.OOE-01 O.OOE-01 O.OOE-01 ZN 65 2.39E+03 6.75E+02 1.44E+03 3.84E+03 2.42E+03 O.OOE-01 O.OOE-01 O.OOE-01 ZN 69 2.11 E-11 1.44E-08 1.58E-10 2.28E-10 1.38E-10 O.OOE-01 O.OOE-01 O.OOE-01 BR 83 9.53E-05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 84 2.23E-16 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 85 6.28E-37 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 86 2.48E+03 2.60E+02 O.OOE-01 4.04E+03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 88 6.60E-28 4.66E-29 O.OOE-01 9.50E-28 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 89 4.96E-30 4.87E-32 O.OOE-01 5.58E-30 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 89 3.15E+03 4.27E+03 1.10E+05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 90 7.47E+04 3.32E+04 3.71 E+06 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 91 4.40E-01 2.57E+01 1.17E+01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 92 5.35E-04 2.53E-01 1.33E-02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 90 1.48E-02 1.57E+03 5.53E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Y 91M 2.93E-15 1.57E-10 8.04E-14 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 91 1.37E+OO 6.84E+03 5.14E+01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 92 9.01E-07 9.09E-01 3.15E-05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 93 1.79E-04 9.75E+01 6.54E-03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 95 1.97E+OO 2.31 E+03 1.01E+01 2.21E+OO 3.17E+OO O.OOE-01 O.OOE-01 O.OOE-01 ZR 97 1.12E-03 2.88E+02 1.32E-02 1.90E-03 2.73E-03 O.OOE-01 O.OOE-01 O.OOE-01 NB 95 4.74E-01 1.23E+03 1.71E+OO 6.64E-01 6.24E-01 O.OOE-01 O.OOE-01 O.OOE-01 M099 4.56E+01 1.52E+02 O.OOE-01 1.84E+02 3.94E+02 O.OOE-01 O.OOE-01 O.OOE-01 TC 99M 3.26E-03 1.12E-01 1.00E-04 1.97E-04 2.86E-03 O.OOE-01 9.99E-05 O.OOE-01 TC101 5.14E-31 1.29E-31 3.87E-32 4.05E-32 6.91 E-31 O.OOE-01 2.14E-32 O.OOE-01 DAEC ODAM Page 231 of 280 Rev.37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =CHILD PATHWAY= IRRIGATED FRESH LEAFY VEGETABLES TOTAL BODY GI-LU BONE LIVER KIDNEY THYROID LUNG SKIN (mrem gal)/(Ci min) RU103 2.20E+01 1.48E+03 5.72E+01 O.OOE-01 1.44E+02 O.OOE-01 O.OOE-01 O.OOE-01 RU105 6.74E-04 1.21E+OO 1.86E-03 O.OOE-01 1.63E-02 O.OOE-01 O.OOE-01 O.OOE-01 RU106 1.49E+02 1.85E+04 1.19E+03 O.OOE-01 1.61 E+03 O.OOE-01 O.OOE-01 O.OOE-01 AG110M 2.96E+01 4.40E+03 5.48E+01 3.70E+01 6.89E+01 O.OOE-01 O.OOE-01 O.OOE-01 TE125M 1.37E+02 9.90E+02 1.03E+03 2.78E+02 O.OOE-01 2.88E+02 O.OOE-01 O.OOE-01 TE127M 3.51 E+02 2.39E+03 2.96E+03 7.96E+02 8.43E+03 7.07E+02 O.OOE-01 O.OOE-01 TE127 4.75E-02 8.66E+OO 2.22E-01 5.97E-02 6.31E-01 1.53E-01 O.OOE-01 O.OOE-01 TE129M 5.86E+02 4.60E+03 3.77E+03 1.05E+03 1.11E+04 1.22E+03 O.OOE-01 O.OOE-01 TE129 3.94E-09 1.03E-06 1.66E-08 4.64E-09 4.86E-08 1.19E-08 O.OOE-01 O.OOE-01 TE131M 1.35E+01 5.16E+02 3.68E+01 1.27E+01 1.23E+02 2.61E+01 O.OOE-01 O.OOE-01 TE131 3.26E-21 5.75E-20 1.09E-20 3.34E-21 3.31E-20 8.38E-21 O.OOE-01 O.OOE-01 TE132 9.10E+01 7.58E+02 1.70E+02 7.53E+01 6.99E+02 1.10E+02 O.OOE-01 O.OOE-01 1130 2.90E+OO 2.64E+OO 2.79E+OO 5.64E+OO 8.43E+OO 6.21 E+02 O.OOE-01 O.OOE-01 I 131 3.60E+02 5.64E+01 6.30E+02 6.33E+02 1.04E+03 2.09E+05 O.OOE-01 O.OOE-01 I 132 2.?0E-04 6.91E-04 3.20E-04 5.87E-04 8.99E-04 2.72E-02 O.OOE-01 O.OOE-01 1133 7.72E+OO 8.22E+OO 1.65E+01 2.04E+01 3.40E+01 3.79E+03 O.OOE-01 O.OOE-01 1134 2.57E-10 3.71E-10 3.01E-10 5.59E-10 8.55E-10 1.29E-08 O.OOE-01 O.OOE-01 1135 2.27E-01 3.66E-01 2.67E-01 4.81E-01 7.37E-01 4.26E+01 O.OOE-01 O.OOE-01 CS134 8.34E+03 2.13E+02 2.41E+04 3.95E+04 1.22E+04 O.OOE-01 4.40E+03 O.OOE-01 CS136 2.10E+03 1.14E+02 1.18E+03 3.24E+03 1.72E+03 O.OOE-01 2.57E+02 O.OOE-01 CS137 4.90E+03 2.08E+02 3.47E+04 3.32E+04 1.08E+04 O.OOE-01 3.89E+03 O.OOE-01 CS138 3.58E-16 2.60E-16 4.0?E-16 5.65E-16 3.98E-16 O.OOE-01 4.28E-17 O.OOE-01 BA139 1.81 E-08 3.61E-05 6.25E-07 3.34E-10 2.91E-10 O.OOE-01 1.96E-10 O.OOE-01 BA140 2.40E+02 2.08E+03 4.11E+03 3.60E+OO 1.17E+OO O.OOE-01 2.15E+OO O.OOE-01 BA141 1.28E-28 2.25E-27 3.95E-27 2.21E-30 1.91 E-30 O.OOE-01 1.30E-29 O.OOE-01 BA142 5.10E-32 1.19E-32 9.13E-31 6.57E-34 5.32E-34 O.OOE-01 3.87E-34 O.OOE-01 LA140 9.10E-03 7.52E+02 7.72E-02 2.?0E-02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 LA142 3.41 E-10 2.16E-04 3.42E-09 1.09E-09 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CE141 2.18E-01 1.83E+03 2.94E+OO 1.47E+OO 6.42E-01 O.OOE-01 O.OOE-01 O.OOE-01 CE143 3.21E-03 3.24E+02 4.08E-02 2.21E+01 9.29E-03 O.OOE-01 O.OOE-01 O.OOE-01 CE144 1.11E+01 1.70E+04 2.08E+02 6.51E+01 3.60E+01 O.OOE-01 O.OOE-01 O.OOE-01 PR143 9.98E-02 2.17E+03 2.01 E+OO 6.04E-01 3.27E-01 O.OOE-01 O.OOE-01 O.OOE-01 PR144 4.33E-33 5.73E-29 8.60E-32 2.66E-32 1.41E-32 O.OOE-01 O.OOE-01 O.OOE-01 ND147 7.95E-02 1.63E+03 1.27E+OO 1.03E+OO 5.63E-01 O.OOE-01 O.OOE-01 O.OOE-01 W187 4.03E-01 1.26E+02 1.52E+OO 8.98E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 NP239 3.09E-03 3.25E+02 6.12E-02 4.40E-03 1.27E-02 O.OOE-01 O.OOE-01 O.OOE-01 DAEC ODAM Page 232 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =CHILD PATHWAY= IRRIGATED STORED FRUIT, VEGETABLES, GRAIN TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN {mrem gaQ/{Ci min) H 3 3.00E+01 3.00E+01 O.OOE-01 3.00E+01 3.00E+01 3.00E+01 3.00E+01 O.OOE-01 c 14 7.01 E+04 7.01 E+04 3.51 E+05 7.01 E+04 7.01E+04 7.01 E+04 7.01 E+04 O.OOE-01 NA24 4.57E-24 4.57E-24 4.57E-24 4.57E-24 4.57E-24 4.57E-24 4.57E-24 O.OOE-01 p 32 1.95E+03 1.40E+03 5.06E+04 2.37E+03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CR 51 2.85E+OO 1.51E+02 O.OOE-01 O.OOE-01 4.32E-01 1.58E+OO 2.89E+OO O.OOE-01 MN 54 5.04E+03 1.59E+04 O.OOE-01 1.89E+04 5.30E+03 O.OOE-01 O.OOE-01 O.OOE-01 MN 56 8.39E-27 5.39E-24 O.OOE-01 3.72E-26 4.50E-26 O.OOE-01 O.OOE-01 O.OOE-01 FE 55 3.73E+03 2.23E+03 2.27E+04 1.20E+04 O.OOE-01 O.OOE-01 6.81 E+03 O.OOE-01 FE 59 8.56E+03 1.79E+04 1.06E+04 1.72E+04 O.OOE-01 O.OOE-01 4.98E+03 O.OOE-01 C058 5.47E+03 1.04E+04 O.OOE-01 1.79E+03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 C060 3.19E+04 5.99E+04 O.OOE-01 1.08E+04 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl63 3.97E+04 4.21 E+03 1.17E+06 6.25E+04 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl65 1.33E-26 2.78E-24 2.41 E-25 2.27E-26 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 cu 64 9.80E-26 7.61 E-24 O.OOE-01 1.62E-25 3.92E-25 O.OOE-01 O.OOE-01 O.OOE-01 ZN 65 4.04E+04 1.14E+04 2.44E+04 6.50E+04 4.10E+04 O.OOE-01 O.OOE-01 O.OOE-01 ZN 69 1.53E-28 1.04E-25 1.15E-27 1.65E-27 1.00E-27 O.OOE-01 O.OOE-01 O.OOE-01 BR 83 1.75E-26 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 84 1.63E-27 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 85 1.26E-35 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 86 5.57E+03 5.83E+02 O.OOE-01 9.06E+03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 88 2.19E-28 1.55E-29 O.OOE-01 3.15E-28 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 89 9.92E-29 9.73E-31 O.OOE-01 1.12E-28 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 89 2.80E+04 3.79E+04 9.80E+05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 90 1.49E+06 6.62E+05 7.40E+07 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 91 4.45E-25 2.60E-23 1.18E-23 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 92 4.32E-26 2.04E-23 1.08E-24 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 90 6.75E-08 7.18E-03 2.52E-06 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Y 91M 2.83E-31 1.53E-26 7.79E-30 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 91 1.37E+01 6.81 E+04 5.11E+02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 92 1.71E-29 1.72E-23 5.96E-28 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 93 1.64E-28 8.89E-23 5.96E-27 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 95 2.08E+01 2.44E+04 1.06E+02 2.34E+01 3.35E+01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 97 1.30E-27 3.33E-22 1.52E-26 2.20E-27 3.16E-27 O.OOE-01 O.OOE-01 O.OOE-01 NB 95 2.97E+OO 7.68E+03 1.07E+01 4.15E+OO 3.90E+OO O.OOE-01 O.OOE-01 O.OOE-01 MO 99 3.13E-04 1.05E-03 O.OOE-01 1.27E-03 2.70E-03 O.OOE-01 O.OOE-01 O.OOE-01 TC 99M 9.06E-27 3.11 E-25 2.79E-28 5.47E-28 7.95E-27 O.OOE-01 2.78E-28 O.OOE-01 TC101 1.03E-29 2.58E-30 7.74E-31 8.10E-31 1.38E-29 O.OOE-01 4.28E-31 O.OOE-01 DAEC ODAM Page 233 of 280 Rev. 37 <::

Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =CHILD PATHWAY= IRRIGATED STORED FRUIT, VEGETABLES, GRAIN TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN (mrem gal)/(Ci min) RU103 1.55E+02 1.04E+04 4.04E+02 O.OOE-01 1.02E+03 O.OOE-01 O.OOE-01 O.OOE-01 RU105 5.02E-27 9.03E-24 1.38E-26 O.OOE-01 1.22E-25 O.OOE-01 O.OOE-01 O.OOE-01 RU106 2.66E+03 3.32E+05 2.13E+04 O.OOE-01 2.88E+04 O.OOE-01 O.OOE-01 O.OOE-01 AG110M 5.02E+02 7.48E+04 9.31 E+02 6.28E+02 1.17E+03 O.OOE-01 O.OOE-01 O.OOE-01 TE125M 1.35E+03 9.80E+03 1.02E+04 2.75E+03 O.OOE-01 2.85E+03 O.OOE-01 O.OOE-01 TE127M 4.82E+03 3.29E+04 4.07E+04 1.09E+04 1.16E+05 9.72E+03 O.OOE-01 O.OOE-01 TE127 4.93E-26 8.99E-24 2.30E-25 6.20E-26 6.55E-25 1.59E-25 O.OOE-01 O.OOE-01 TE129M 3.46E+03 2.72E+04 2.23E+04 6.23E+03 6.55E+04 7.19E+03 O.OOE-01 O.OOE-01 TE129 1.17E-27 3.07E-25 4.93E-27 1.38E-27 1.44E-26 3.52E-27 O.OOE-01 O.OOE-01 TE131M 1.66E-12 6.32E-11 4.50E-12 1.56E-12 1.51E-11 3.20E-12 O.OOE-01 O.OOE-01 TE131 1.13E-28 2.00E-27 3.81E-28 1.16E-28 1.15E-27 2.91 E-28 O.OOE-01 O.OOE-01 TE132 6.51E-03 5.43E-02 1.22E-02 5.39E-03 5.01E-02 7.85E-03 O.OOE-01 O.OOE-01 1130 1.96E-24 1.78E-24 1.88E-24 3.80E-24 5.68E-24 4.19E-22 O.OOE-01 O.OOE-01 I 131 4.44E+01 6.96E+OO 7.77E+01 7.82E+01 1.28E+02 2.59E+04 O.OOE-01 O.OOE-01 1132 6.54E-26 1.67E-25 7.74E-26 1.42E-25 2.18E-25 6.60E-24 O.OOE-01 O.OOE-01 I 133 5.13E-19 5.47E-19 1.10E-18 1.36E-18 2.26E-18 2.52E-16 O.OOE-01 O.OOE-01 1134 8.10E-27 1.17E-26 9.48E-27 1.76E-26 2.69E-26 4.05E-25 O.OOE-01 O.OOE-01 1135 4.96E-25 8.00E-25 5.83E-25 1.05E-24 1.61 E-24 9.30E-23 O.OOE-01 O.OOE-01 CS134 1.58E+05 4.04E+03 4.56E+05 7.49E+05 2.32E+05 O.OOE-01 8.33E+04 O.OOE-01 CS136 1.85E+03 1.01E+02 1.04E+03 2.86E+03 1.52E+03 O.OOE-01 2.27E+02 O.OOE-01 CS137 9.77E+04 4.14E+03 6.92E+05 6.62E+05 2.16E+05 O.OOE-01 7.76E+04 O.OOE-01 CS138 1.70E-27 1.24E-27 1.93E-27 2.68E-27 1.89E-27 O.OOE-01 2.03E-28 O.OOE-01 BA139 5.68E-28 1.13E-24 1.96E-26 1.05E-29 9.14E-30 O.OOE-01 6.16E-30 O.OOE-01 BA140 1.96E+02 1.70E+03 3.36E+03 2.95E+OO 9.59E-01 O.OOE-01 1.76E+OO O.OOE-01 BA141 1.17E-29 2.04E-28 3.58E-28 2.01 E-31 1.74E-31 O.OOE-01 1.18E-30 O.OOE-01 BA142 1.02E-30 2.38E-31 1.83E-29 1.31 E-32 1.06E-32 O.OOE-01 7.73E-33 O.OOE-01 LA140 4.76E-12 3.94E-07 4.04E-11 1.41E-11 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 LA142 2.93E-30 1.85E-24 2.93E-29 9.34E-30 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CE141 1.24E+OO 1.04E+04 1.67E+01 8.32E+OO 3.65E+OO O.OOE-01 O.OOE-01 O.OOE-01 CE143 8.80E-15 8.90E-10 1.12E-13 6.08E-11 2.55E-14 O.OOE-01 O.OOE-01 O.OOE-01 CE144 1.92E+02 2.94E+05 3.60E+03 1.13E+03 6.24E+02 O.OOE-01 O.OOE-01 O.OOE-01 PR143 9.86E-02 2.14E+03 1.99E+OO 5.97E-01 3.23E-01 O.OOE-01 O.OOE-01 O.OOE-01 PR144 9.61E-33 1.27E-28 1.91 E-31 5.91E-32 3.12E-32 O.OOE-01 O.OOE-01 O.OOE-01 ND147 3.99E-02 8.16E+02 6.36E-01 5.15E-01 2.83E-01 O.OOE-01 O.OOE-01 O.OOE-01 W187 1.22E-17 3.81E-15 4.58E-17 2.71E-17 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 NP239 1.84E-09 1.93E-04 3.64E-08 2.61E-09 7.55E-09 O.OOE-01 O.OOE-01 O.OOE-01 DAEC ODAM Page 234 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =CHILD PATHWAY= IRRIGATED FRESH FORAGE--MILK TOTAL BODY GI-LU BONE LIVER KIDNEY THYROID LUNG SKIN (mrem gaQ/(Ci minl H 3 8.73E+OO 8.73E+OO O.OOE-01 8.73E+OO 8.73E+OO 8.73E+OO 8.73E+OO O.OOE-01 c 14 2.93E+04 2.93E+04 1.46E+05 2.93E+04 2.93E+04 2.93E+04 2.93E+04 O.OOE-01 NA24 2.07E+02 2.07E+02 2.07E+02 2.07E+02 2.07E+02 2.07E+02 2.07E+02 O.OOE-01 p 32 6.91 E+04 4.95E+04 1.79E+06 8.38E+04 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CR 51 2.20E+OO 1.16E+02 O.OOE-01 O.OOE-01 3.33E-01 1.22E+OO 2.23E+OO O.OOE-01 MN 54 1.07E+02 3.36E+02 O.OOE-01 4.01 E+02 1.12E+02 O.OOE-01 O.OOE-01 O.OOE-01 MN 56 5.11E-08 3.28E-05 O.OOE-01 2.26E-07 2.74E-07 O.OOE-01 O.OOE-01 O.OOE-01 FE 55 3.46E+02 2.07E+02 2.11E+03 1.12E+03 O.OOE-01 O.OOE-01 6.32E+02 O.OOE-01 FE 59 2.01 E+03 4.20E+03 2.49E+03 4.03E+03 O.OOE-01 O.OOE-01 1.17E+03 O.OOE-01 co 58 7.47E+02 1.42E+03 O.OOE-01 2.44E+02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 C060 2.40E+03 4.51 E+03 O.OOE-01 8.14E+02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl63 1.92E+04 2.04E+03 5.65E+05 3.02E+04 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl65 1.70E-06 3.57E-04 3.09E-05 2.91E-06 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 cu 64 1.03E+OO 7.98E+01 O.OOE-01 1.70E+OO 4.11E+OO O.OOE-01 O.OOE-01 O.OOE-01 ZN 65 1.35E+05 3.81 E+04 8.13E+04 2.17E+05 1.37E+05 O.OOE-01 O.OOE-01 O.OOE-01 ZN 69 3.59E-17 2.45E-14 2.69E-16 3.89E-16 2.36E-16 O.OOE-01 O.OOE-01 O.OOE-01 BR 83 8.21E-06 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 84 7.38E-27 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 85 5.67E-35 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 86 1.21E+05 1.26E+04 O.OOE-01 1.97E+05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 88 5.95E-28 4.20E-29 O.OOE-01 8.57E-28 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 89 2.70E-28 2.64E-30 O.OOE-01 3.03E-28 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 89 3.95E+03 5.35E+03 1.38E+05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 90 1.17E+05 5.20E+04 5.82E+06 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 91 1.11E-01 6.47E+OO 2.93E+OO O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 92 1.68E-06 7.95E-04 4.20E-05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 90 2.07E-04 2.20E+01 7.73E-03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Y 91M 9.59E-26 5.16E-21 2.63E-24 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 91 2.13E-02 1.06E+02 7.94E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 92 1.51E-10 1.53E-04 5.28E-09 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 93 6.25E-07 3.39E-01 2.28E-05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 95 1.52E-02 1.78E+01 7.76E-02 1.70E-02 2.44E-02 O.OOE-01 O.OOE-01 O.OOE-01 ZR 97 3.80E-06 9.76E-01 4.46E-05 6.44E-06 9.25E-06 O.OOE-01 O.OOE-01 O.OOE-01 NB 95 1.87E+OO 4.85E+03 6.73E+OO 2.62E+OO 2.46E+OO O.OOE-01 O.OOE-01 O.OOE-01 M099 4.82E+02 1.61E+03 O.OOE-01 1.95E+03 4.16E+03 O.OOE-01 O.OOE-01 O.OOE-01 TC 99M 9.29E-03 3.19E-01 2.86E-04 5.61E-04 8.15E-03 O.OOE-01 2.85E-04 O.OOE-01 TC101 2.32E-29 5.83E-30 1.75E-30 1.83E-30 3.13E-29 O.OOE-01 9.69E-31 O.OOE-01 DAEC ODAM Page 235 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =CHILD PATHWAY= IRRIGATED FRESH FORAGE--MILK TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN {mrem 9aQ/{Ci min} RU103 3.45E-02 2.32E+OO 8.98E-02 O.OOE-01 2.26E-01 O.OOE-01 O.OOE-01 O.OOE-01 RU105 2.87E-08 5.17E-05 7.92E-08 O.OOE-01 6.96E-07 O.OOE-01 0.00E-01 O.OOE-01 RU106 2.20E-01 2.75E+01 1.77E+OO O.OOE-01 2.38E+OO O.OOE-01 0.00E-01 O.OOE-01 AG110M 2.18E+03 3.25E+05 4.04E+03 2.73E+03 5.08E+03 O.OOE-01 O.OOE-01 O.OOE-01 TE125M 2.05E+02 1.48E+03 1.54E+03 4.17E+02 O.OOE-01 4.31E+02 O.OOE-01 O.OOE-01 TE127M 5.05E+02 3.45E+03 4.26E+03 1.15E+03 1.21E+04 1.02E+03 O.OOE-01 O.OOE-01 TE127 1.44E-02 2.63E+OO 6.73E-02 1.81 E-02 1.91 E-01 4.66E-02 O.OOE-01 O.OOE-01 TE129M 9.07E+02 7.13E+03 5.84E+03 1.63E+03 1.72E+04 1.88E+03 O.OOE-01 O.OOE-01 TE129 4.19E-15 1.10E-12 1.77E-14 4.93E-15 5.17E-14 1.26E-14 O.OOE-01 O.OOE-01 TE131M 1.40E+01 5.33E+02 3.80E+01 1.31 E+01 1.27E+02 2.70E+01 O.OOE-01 O.OOE-01 TE131 1.02E-29 1.80E-28 3.43E-29 1.05E-29 1.04E-28 2.62E-29 0.00E-01 O.OOE-01 TE132 1.32E+02 1.10E+03 2.47E+02 1.09E+02 1.02E+03 1.59E+02 0.00E-01 O.OOE-01 1130 8.21 E+OO 7.45E+OO 7.89E+OO 1.59E+01 2.38E+01 1.76E+03 O.OOE-01 O.OOE-01 I 131 3.53E+03 5.53E+02 6.18E+03 6.21 E+03 1.02E+04 2.05E+06 0.00E-01 O.OOE-01 1132 2.13E-06 5.44E-06 2.52E-06 4.62E-06 7.07E-06 2.14E-04 O.OOE-01 O.OOE-01 1133 3.78E+01 4.02E+01 8.07E+01 9.98E+01 1.66E+02 1.85E+04 0.00E-01 O.OOE-01 I 134 1.55E-17 2.24E-17 1.82E-17 3.38E-17 5.17E-17 7.77E-16 O.OOE-01 O.OOE-01 1135 1.99E-01 3.20E-01 2.33E-01 4.20E-01 6.43E-01 3.72E+01 O.OOE-01 O.OOE-01 CS134 1.48E+05 3.79E+03 4.28E+05 7.02E+05 2.18E+05 O.OOE-01 7.81E+04 O.OOE-01 CS136 4.13E+04 2.24E+03 2.32E+04 6.39E+04 3.40E+04 O.OOE-01 5.07E+03 O.OOE-01 CS137 8.60E+04 3.65E+03 6.09E+05 5.83E+05 1.90E+05 O.OOE-01 6.83E+04 O.OOE-01 CS138 1.85E-27 1.35E-27 2.10E-27 2.92E-27 2.05E-27 O.OOE-01 2.21E-28 O.OOE-01 BA139 7.33E-14 1.46E-10 2.53E-12 1.35E-15 1.18E-15 O.OOE-01 7.94E-16 O.OOE-01 BA140 1.58E+02 1.37E+03 2.70E+03 2.37E+OO 7.71E-01 0.00E-01 1.41E+OO O.OOE-01 BA141 4.23E-31 7.40E-30 1.30E-29 7.27E-33 6.29E-33 O.OOE-01 4.27E-32 O.OOE-01 BA142 3.70E-32 8.64E-33 6.62E-31 4.76E-34 3.86E-34 O.OOE-01 2.80E-34 O.OOE-01 LA140 5.46E-05 4.51 E+OO 4.63E-04 1.62E-04 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 LA142 6.30E-17 3.99E-11 6.32E-16 2.01E-16 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CE141 3.45E-02 2.90E+02 4.66E-01 2.32E-01 1.02E-01 O.OOE-01 O.OOE-01 O.OOE-01 CE143 3.52E-04 3.56E+01 4.48E-03 2.43E+OO 1.02E-03 O.OOE-01 O.OOE-01 O.OOE-01 CE144 1.65E+OO 2.53E+03 3.10E+01 9.72E+OO 5.38E+OO O.OOE-01 O.OOE-01 O.OOE-01 PR143 8.20E-04 1.78E+01 1.65E-02 4.96E-03 2.69E-03 O.OOE-01 O.OOE-01 O.OOE-01 PR144 4.35E-36 5.76E-32 8.66E-35 2.68E-35 1.42E-35 O.OOE-01 O.OOE-01 O.OOE-01 ND147 6.54E-04 1.34E+01 1.04E-02 8.45E-03 4.64E-03 O.OOE-01 O.OOE-01 O.OOE-01 W187 1.82E-01 5.71E+01 6.86E-01 4.06E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 NP239 2.09E-05 2.20E+OO 4.14E-04 2.97E-05 8.59E-05 O.OOE-01 O.OOE-01 O.OOE-01 DAEC ODAM Page 236 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =CHILD PATHWAY= IRRIGATED FRESH FORAGE--MEAT TOTAL BODY GI-LU BONE LIVER KIDNEY THYROID LUNG SKIN (mrem gal)/(Ci min) H 3 1.19E+OO 1.19E+OO O.OOE-01 1.19E+OO 1.19E+OO 1.19E+OO 1.19E+OO O.OOE-01 c 14 9.39E+03 9.39E+03 4.70E+04 9.39E+03 9.39E+03 9.39E+03 9.39E+03 O.OOE-01 NA24 4.37E-08 4.37E-08 4.37E-08 4.37E-08 4.37E-08 4.37E-08 4.37E-08 O.OOE-01 p 32 6.60E+03 4.73E+03 1.71 E+05 8.01E+03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CR 51 1.90E-01 1.01 E+01 O.OOE-01 O.OOE-01 2.88E-02 1.05E-01 1.92E-01 O.OOE-01 MN 54 4.08E+01 1.28E+02 O.OOE-01 1.53E+02 4.29E+01 O.OOE-01 O.OOE-01 O.OOE-01 MN 56 7.56E-29 4.86E-26 O.OOE-01 3.35E-28 4.05E-28 O.OOE-01 O.OOE-01 O.OOE-01 FE 55 1.41E+03 8.46E+02 8.61 E+03 4.57E+03 O.OOE-01 O.OOE-01 2.58E+03 O.OOE-01 FE 59 6.29E+03 1.31E+04 7.80E+03 1.26E+04 O.OOE-01 O.OOE-01 3.66E+03 O.OOE-01 C058 1.01E+03 1.93E+03 O.OOE-01 3.30E+02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 C060 3.85E+03 7.24E+03 O.OOE-01 1.31E+03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl63 1.89E+04 2.00E+03 5.55E+05 2.97E+04 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl65 7.92E-27 1.66E-24 1.44E-25 1.36E-26 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 cu 64 3.95E-12 3.07E-10 O.OOE-01 6.53E-12 1.58E-11 O.OOE-01 O.OOE-01 O.OOE-01 ZN 65 1.22E+04 3.46E+03 7.39E+03 1.97E+04 1.24E+04 O.OOE-01 O.OOE-01 O.OOE-01 ZN 69 5.16E-29 3.52E-26 3.86E-28 5.58E-28 3.39E-28 O.OOE-01 O.OOE-01 O.OOE-01 BR 83 5.11 E-27 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 BR 84 4.77E-28 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 BR 85 3.66E-36 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 86 7.96E+03 8.33E+02 O.OOE-01 1.29E+04 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 88 7.64E-29 5.39E-30 O.OOE-01 1.10E-28 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 89 3.46E-29 3.40E-31 O.OOE-01 3.90E-29 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 89 2.87E+02 3.89E+02 1.00E+04 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 90 1.09E+04 4.84E+03 5.41 E+05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 91 2.01E-16 1.17E-14 5.31E-15 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 92 2.93E-28 1.38E-25 7.30E-27 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 90 1.11 E-04 1.18E+01 4.16E-03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Y 91M 1.47E-32 7.90E-28 4.04E-31 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 91 9.81 E-01 4.89E+03 3.67E+01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 92 8.83E-31 8.92E-25 3.09E-29 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 93 4.49E-18 2.44E-12 1.64E-16 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 95 1.06E+01 1.24E+04 5.39E+01 1.19E+01 1.70E+01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 97 6.41 E-11 1.65E-05 7.52E-10 1.09E-10 1.56E-10 O.OOE-01 O.OOE-01 O.OOE-01 NB 95 1.83E+01 4.73E+04 6.57E+01 2.56E+01 2.40E+01 O.OOE-01 O.OOE-01 O.OOE-01 MO 99 6.80E-01 2.28E+OO O.OOE-01 2.75E+OO 5.87E+OO O.OOE-01 O.OOE-01 O.OOE-01 TC 99M 4.50E-24 1.54E-22 1.39E-25 2.72E-25 3.95E-24 O.OOE-01 1.38E-25 O.OOE-01 TC101 4.62E-29 1.16E-29 3.48E-30 3.65E-30 6.22E-29 O.OOE-01 1.93E-30 O.OOE-01 DAEC ODAM Page 237 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =CHILD PATHWAY= IRRIGATED FRESH FORAGE--MEAT TOTAL BODY GI-LU BONE LIVER KIDNEY THYROID LUNG SKIN {mrem gaQ/{Ci min} RU103 1.25E+03 8.40E+04 3.25E+03 O.OOE-01 8.18E+03 O.OOE-01 O.OOE-01 O.OOE-01 RU105 2.26E-26 4.07E-23 6.23E-26 O.OOE-01 5.48E-25 O.OOE-01 O.OOE-01 O.OOE-01 RU106 1.06E+04 1.32E+06 8.48E+04 O.OOE-01 1.15E+05 O.OOE-01 O.OOE-01 O.OOE-01 AG110M 8.77E+01 1.30E+04 1.62E+02 1.10E+02 2.04E+02 O.OOE-01 O.OOE-01 O.OOE-01 TE125M 1.58E+03 1.14E+04 1.19E+04 3.22E+03 O.OOE-01 3.33E+03 O.OOE-01 O.OOE-01 TE127M 4.31E+03 2.94E+04 3.63E+04 9.78E+03 1.04E+05 8.68E+03 O.OOE-01 O.OOE-01 TE127 1.68E-15 3.07E-13 7.86E-15 2.12E-15 2.23E-14 5.44E-15 O.OOE-01 O.OOE-01 TE129M 5.98E+03 4.70E+04 3.85E+04 1.08E+04 1.13E+05 1.24E+04 O.OOE-01 O.OOE-01 TE129 1.01 E-27 2.64E-25 4.24E-27 1.19E-27 1.24E-26 3.03E-27 O.OOE-01 O.OOE-01 TE131M 6.17E-03 2.35E-01 1.68E-02 5.80E-03 5.61E-02 1.19E-02 O.OOE-01 O.OOE-01 TE131 9.76E-29 1.72E-27 3.28E-28 1.00E-28 9.92E-28 2.51E-28 O.OOE-01 O.OOE-01 TE132 2.76E+01 2.30E+02 5.16E+01 2.28E+01 2.12E+02 3.32E+01 O.OOE-01 O.OOE-01 1130 1.43E-11 1.30E-11 1.38E-11 2.78E-11 4.16E-11 3.07E-09 O.OOE-01 O.OOE-01 I 131 4.49E+01 7.04E+OO 7.86E+01 7.90E+01 1.30E+02 2.61 E+04 O.OOE-01 O.OOE-01 1132 2.14E-27 5.47E-27 2.53E-27 4.64E-27 7.11E-27 2.16E-25 O.OOE-01 O.OOE-01 1133 1.28E-06 1.37E-06 2.74E-06 3.39E-06 5.65E-06 6.30E-04 O.OOE-01 O.OOE-01 I 134 2.65E-28 3.81E-28 3.10E-28 5.75E-28 8.80E-28 1.32E-26 O.OOE-01 O.OOE-01 1135 2.26E-22 3.64E-22 2.66E-22 4.78E-22 7.33E-22 4.23E-20 O.OOE-01 O.OOE-01 CS134 6.03E+03 1.54E+02 1.74E+04 2.86E+04 8.87E+03 O.OOE-01 3.18E+03 O.OOE-01 CS136 6.61 E+02 3.59E+01 3.72E+02 1.02E+03 5.44E+02 O.OOE-01 8.11 E+01 O.OOE-01 CS137 3.56E+03 1.51E+02 2.52E+04 2.41E+04 7.86E+03 O.OOE-01 2.83E+03 O.OOE-01 CS138 7.67E-29 5.57E-29 8.70E-29 1.21 E-28 8.51E-29 O.OOE-01 9.16E-30 O.OOE-01 BA139 2.0SE-29 4.08E-26 7.07E-28 3.??E-31 3.29E-31 O.OOE-01 2.22E-31 O.OOE-01 BA140 5.91E+01 5.13E+02 1.01E+03 8.88E-01 2.89E-01 O.OOE-01 5.29E-01 O.OOE-01 BA141 4.20E-31 7.36E-30 1.29E-29 7.23E-33 6.25E-33 O.OOE-01 4.25E-32 O.OOE-01 BA142 3.68E-32 8.58E-33 6.58E-31 4.74E-34 3.83E-34 O.OOE-01 2.79E-34 O.OOE-01 LA140 1.60E-07 1.32E-02 1.36E-06 4.75E-07 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 LA142 6.59E-33 4.17E-27 6.60E-32 2.11 E-32 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CE141 3.SOE-02 2.94E+02 4.73E-01 2.36E-01 1.03E-01 O.OOE-01 O.OOE-01 O.OOE-01 CE143 6.25E-08 6.32E-03 7.96E-07 4.31E-04 1.81E-07 O.OOE-01 O.OOE-01 O.OOE-01 CE144 2.36E+OO 3.62E+03 4.43E+01 1.39E+01 7.68E+OO O.OOE-01 O.OOE-01 O.OOE-01 PR143 3.82E-02 8.31 E+02 7.71 E-01 2.31 E-01 1.25E-01 O.OOE-01 O.OOE-01 O.OOE-01 PR144 5.09E-34 6.73E-30 1.01 E-32 3.13E-33 1.65E-33 O.OOE-01 O.OOE-01 O.OOE-01 ND147 1.74E-02 3.57E+02 2.78E-01 2.25E-01 1.23E-01 O.OOE-01 O.OOE-01 O.OOE-01 w 187 2.15E-07 6.74E-05 8.10E-07 4.80E-07 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 NP239 5.25E-07 5.52E-02 1.04E-05 7.46E-07 2.16E-06 O.OOE-01 O.OOE-01 O.OOE-01 DAEC ODAM Page 238 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =CHILD PATHWAY= IRRIGATED STORED FEED--MILK TOTAL BODY GI-LU BONE LIVER KIDNEY THYROID LUNG SKIN (mrem gaQ/(Ci min2 H 3 8.73E+OO 8.73E+OO O.OOE-01 8.73E+OO 8.73E+OO 8.73E+OO 8.73E+OO O.OOE-01 c 14 3.03E+04 3.03E+04 1.51E+05 3.03E+04 3.03E+04 3.03E+04 3.03E+04 O.OOE-01 NA24 2.07E+02 2.07E+02 2.07E+02 2.07E+02 2.07E+02 2.07E+02 2.07E+02 O.OOE-01 p 32 7.27E+04 5.21 E+04 1.89E+06 8.83E+04 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CR 51 2.43E+OO 1.29E+02 O.OOE-01 O.OOE-01 3.69E-01 1.35E+OO 2.46E+OO O.OOE-01 MN 54 1.29E+02 4.08E+02 O.OOE-01 4.86E+02 1.36E+02 O.OOE-01 O.OOE-01 O.OOE-01 MN 56 5.11 E-08 3.28E-05 O.OOE-01 2.26E-07 2.74E-07 O.OOE-01 O.OOE-01 O.OOE-01 FE 55 4.23E+02 2.53E+02 2.57E+03 1.36E+03 O.OOE-01 O.OOE-01 7.72E+02 O.OOE-01 FE 59 2.29E+03 4.80E+03 2.85E+03 4.61E+03 O.OOE-01 O.OOE-01 1.34E+03 O.OOE-01 C058 8.73E+02 1.66E+03 O.OOE-01 2.85E+02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 C060 2.94E+03 5.52E+03 O.OOE-01 9.96E+02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl63 2.35E+04 2.49E+03 6.91 E+05 3.70E+04 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl65 1.?0E-06 3.57E-04 3.09E-05 2.91E-06 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 cu 64 1.03E+OO 7.98E+01 O.OOE-01 1.?0E+OO 4.11E+OO O.OOE-01 O.OOE-01 O.OOE-01 ZN 65 1.62E+05 4.58E+04 9.78E+04 2.61 E+05 1.64E+05 O.OOE-01 O.OOE-01 O.OOE-01 ZN 69 3.59E-17 2.45E-14 2.69E-16 3.89E-16 2.36E-16 O.OOE-01 O.OOE-01 O.OOE-01 BR 83 8.21E-06 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 84 7.38E-27 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 85 5.67E-35 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 86 1.30E+05 1.36E+04 O.OOE-01 2.11E+05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 88 5.95E-28 4.20E-29 O.OOE-01 8.57E-28 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 89 2.70E-28 2.64E-30 O.OOE-01 3.03E-28 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 89 4.53E+03 6.14E+03 1.59E+05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 90 1.31E+05 5.84E+04 6.53E+06 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 91 1.11E-01 6.47E+OO 2.93E+OO O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 92 1.68E-06 7.95E-04 4.20E-05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 90 2.07E-04 2.20E+01 7.73E-03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Y 91M 9.59E-26 5.16E-21 2.63E-24 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 91 2.46E-02 1.23E+02 9.20E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 92 1.51E-10 1.53E-04 5.28E-09 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 93 6.25E-07 3.39E-01 2.28E-05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 95 1.77E-02 2.07E+01 9.03E-02 1.98E-02 2.84E-02 O.OOE-01 O.OOE-01 O.OOE-01 ZR 97 3.80E-06 9.76E-01 4.46E-05 6.44E-06 9.25E-06 O.OOE-01 O.OOE-01 O.OOE-01 NB 95 2.11E+OO 5.45E+03 7.58E+OO 2.95E+OO 2.77E+OO O.OOE-01 O.OOE-01 O.OOE-01 MO 99 4.82E+02 1.61E+03 O.OOE-01 1.95E+03 4.16E+03 O.OOE-01 O.OOE-01 O.OOE-01 TC 99M 9.29E-03 3.19E-01 2.86E-04 5.61E-04 8.15E-03 O.OOE-01 2.85E-04 O.OOE-01 TC101 2.32E-29 5.83E-30 1.75E-30 1.83E-30 3.13E-29 O.OOE-01 9.69E-31 O.OOE-01 DAEC ODAM Page 239 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =CHILD PATHWAY= IRRIGATED STORED FEED--MILK TOTAL BODY GI-LU BONE LIVER KIDNEY THYROID LUNG SKIN (mrem gal)/(Ci min) RU103 3.91E-02 2.63E+OO 1.02E-01 O.OOE-01 2.56E-01 O.OOE-01 O.OOE-01 O.OOE-01 RU105 2.87E-08 5.17E-05 7.92E-08 O.OOE-01 6.96E-07 O.OOE-01 O.OOE-01 O.OOE-01 RU106 2.67E-01 3.33E+01 2.14E+OO O.OOE-01 2.89E+OO O.OOE-01 O.OOE-01 O.OOE-01 AG110M 2.63E+03 3.92E+05 4.87E+03 3.29E+03 6.13E+03 O.OOE-01 O.OOE-01 O.OOE-01 TE125M 2.37E+02 1.71E+03 1.77E+03 4.81 E+02 O.OOE-01 4.98E+02 O.OOE-01 O.OOE-01 TE127M 5.96E+02 4.07E+03 5.02E+03 1.35E+03 1.43E+04 1.20E+03 O.OOE-01 O.OOE-01 TE127 1.44E-02 2.63E+OO 6.73E-02 1.81 E-02 1.91 E-01 4.66E-02 O.OOE-01 O.OOE-01 TE129M 1.02E+03 7.98E+03 6.55E+03 1.83E+03 1.92E+04 2.11E+03 O.OOE-01 O.OOE-01 TE129 4.19E-15 1.10E-12 1.77E-14 4.93E-15 5.17E-14 1.26E-14 O.OOE-01 O.OOE-01 TE131M 1.40E+01 5.33E+02 3.80E+01 1.31E+01 1.27E+02 2.70E+01 O.OOE-01 O.OOE-01 TE131 1.02E-29 1.80E-28 3.43E-29 1.05E-29 1.04E-28 2.62E-29 O.OOE-01 O.OOE-01 TE132 1.32E+02 1.10E+03 2.47E+02 1.09E+02 1.02E+03 1.59E+02 O.OOE-01 O.OOE-01 1130 8.21 E+OO 7.45E+OO 7.89E+OO 1.59E+01 2.38E+01 1.76E+03 O.OOE-01 O.OOE-01 I 131 3.59E+03 5.63E+02 6.28E+03 6.32E+03 1.04E+04 2.09E+06 O.OOE-01 O.OOE-01 1132 2.13E-06 5.44E-06 2.52E-06 4.62E-06 7.07E-06 2.14E-04 O.OOE-01 O.OOE-01 1133 3.78E+01 4.02E+01 8.07E+01 9.98E+01 1.66E+02 1.85E+04 O.OOE-01 O.OOE-01 1134 1.55E-17 2.24E-17 1.82E-17 3.38E-17 5.17E-17 7.77E-16 O.OOE-01 O.OOE-01 1135 1.99E-01 3.20E-01 2.33E-01 4.20E-01 6.43E-01 3.72E+01 O.OOE-01 O.OOE-01 CS134 1.81E+05 4.62E+03 5.22E+05 8.57E+05 2.65E+05 O.OOE-01 9.53E+04 O.OOE-01 CS136 4.33E+04 2.35E+03 2.43E+04 6.69E+04 3.56E+04 O.OOE-01 5.31E+03 O.OOE-01 CS137 1.05E+05 4.47E+03 7.45E+05 7.14E+05 2.33E+05 O.OOE-01 8.37E+04 O.OOE-01 CS138 1.85E-27 1.35E-27 2.10E-27 2.92E-27 2.05E-27 O.OOE-01 2.21E-28 O.OOE-01 BA139 7.33E-14 1.46E-10 2.53E-12 1.35E-15 1.18E-15 O.OOE-01 7.94E-16 O.OOE-01 BA140 1.65E+02 1.43E+03 2.82E+03 2.47E+OO 8.05E-01 O.OOE-01 1.48E+OO O.OOE-01 BA141 4.23E-31 7.40E-30 1.30E-29 7.27E-33 6.29E-33 O.OOE-01 4.27E-32 O.OOE-01 BA142 3.70E-32 8.64E-33 6.62E-31 4.76E-34 3.86E-34 O.OOE-01 2.80E-34 O.OOE-01 LA140 5.46E-05 4.51 E+OO 4.63E-04 1.62E-04 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 LA142 6.30E-17 3.99E-11 6.32E-16 2.01E-16 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CE141 3.86E-02 3.24E+02 5.21E-01 2.60E-01 1.14E-01 O.OOE-01 O.OOE-01 O.OOE-01 CE143 3.52E-04 3.56E+01 4.48E-03 2.43E+OO 1.02E-03 O.OOE-01 O.OOE-01 O.OOE-01 CE144 2.00E+OO 3.07E+03 3.75E+01 1.18E+01 6.52E+OO O.OOE-01 O.OOE-01 O.OOE-01 PR143 8.60E-04 1.87E+01 1.73E-02 5.20E-03 2.82E-03 O.OOE-01 O.OOE-01 O.OOE-01 PR144 4.35E-36 5.76E-32 8.66E-35 2.68E-35 1.42E-35 O.OOE-01 O.OOE-01 O.OOE-01 ND147 6.77E-04 1.39E+01 1.08E-02 8.75E-03 4.80E-03 O.OOE-01 O.OOE-01 O.OOE-01 w 187 1.82E-01 5.71E+01 6.86E-01 4.06E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 NP239 2.09E-05 2.20E+OO 4.14E-04 2.97E-05 8.59E-05 O.OOE-01 O.OOE-01 O.OOE-01 DAEC ODAM Page 240 of 280 Rev.37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =CHILD PATHWAY= IRRIGATED STORED FEED--MEAT TOTAL BODY GI-LU BONE LIVER KIDNEY THYROID LUNG SKIN {mrem gaQ!{Ci min) H 3 1.19E+OO 1.19E+OO O.OOE-01 1.19E+OO 1.19E+OO 1.19E+OO 1.19E+OO O.OOE-01 c 14 9.72E+03 9.72E+03 4.86E+04 9.72E+03 9.72E+03 9.72E+03 9.72E+03 O.OOE-01 NA24 4.37E-08 4.37E-08 4.37E-08 4.37E-08 4.37E-08 4.37E-08 4.37E-08 O.OOE-01 p 32 6.95E+03 4.98E+03 1.80E+05 8.43E+03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CR 51 2.10E-01 1.11E+01 O.OOE-01 O.OOE-01 3.18E-02 1.16E-01 2.13E-01 O.OOE-01 MN 54 4.94E+01 1.56E+02 O.OOE-01 1.85E+02 5.20E+01 O.OOE-01 O.OOE-01 O.OOE-01 MN 56 7.56E-29 4.86E-26 O.OOE-01 3.35E-28 4.05E-28 O.OOE-01 O.OOE-01 O.OOE-01 FE 55 1.73E+03 1.03E+03 1.05E+04 5.58E+03 O.OOE-01 O.OOE-01 3.16E+03 O.OOE-01 FE 59 7.18E+03 1.50E+04 8.91 E+03 1.44E+04 O.OOE-01 O.OOE-01 4.18E+03 O.OOE-01 co 58 1.18E+03 2.25E+03 O.OOE-01 3.86E+02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 co 60 4.71E+03 8.85E+03 O.OOE-01 1.60E+03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl63 2.31 E+04 2.45E+03 6.79E+05 3.63E+04 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl65 7.92E-27 1.66E-24 1.44E-25 1.36E-26 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 cu 64 3.95E-12 3.07E-10 O.OOE-01 6.53E-12 1.58E-11 O.OOE-01 O.OOE-01 O.OOE-01 ZN 65 1.47E+04 4.16E+03 8.88E+03 2.37E+04 1.49E+04 O.OOE-01 O.OOE-01 O.OOE-01 ZN 69 5.16E-29 3.52E-26 3.86E-28 5.58E-28 3.39E-28 O.OOE-01 O.OOE-01 O.OOE-01 BR 83 5.11 E-27 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 84 4.77E-28 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 BR 85 3.66E-36 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 86 8.56E+03 8.95E+02 O.OOE-01 1.39E+04 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 88 7.64E-29 5.39E-30 O.OOE-01 1.10E-28 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 89 3.46E-29 3.40E-31 O.OOE-01 3.90E-29 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 89 3.29E+02 4.47E+02 1.15E+04 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 90 1.22E+04 5.44E+03 6.08E+05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 91 2.01E-16 1.17E-14 5.31E-15 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 92 2.93E-28 1.38E-25 7.30E-27 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 90 1.11 E-04 1.18E+01 4.16E-03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Y 91M 1.47E-32 7.90E-28 4.04E-31 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 91 1.14E+OO 5.66E+03 4.25E+01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 92 8.83E-31 8.92E-25 3.09E-29 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 93 4.49E-18 2.44E-12 1.64E-16 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 95 1.23E+01 1.44E+04 6.28E+01 1.38E+01 1.97E+01 O.OOE-01 0.00E-01 O.OOE-01 ZR 97 6.41E-11 1.65E-05 7.52E-10 1.09E-10 1.56E-10 O.OOE-01 O.OOE-01 O.OOE-01 NB 95 2.06E+01 5.32E+04 7.39E+01 2.88E+01 2.70E+01 O.OOE-01 O.OOE-01 O.OOE-01 M099 6.80E-01 2.28E+OO O.OOE-01 2.75E+OO 5.87E+OO O.OOE-01 O.OOE-01 O.OOE-01 TC99M 4.50E-24 1.54E-22 1.39E-25 2.72E-25 3.95E-24 O.OOE-01 1.38E-25 O.OOE-01 TC101 4.62E-29 1.16E-29 3.48E-30 3.65E-30 6.22E-29 O.OOE-01 1.93E-30 O.OOE-01 DAEC ODAM Page 241 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =CHILD PATHWAY= IRRIGATED STORED FEED--MEAT TOTAL BODY GI-LU BONE LIVER KIDNEY THYROID LUNG SKIN (mrem gal}/(Ci min} RU103 1.41E+03 9.52E+04 3.68E+03 O.OOE-01 9.27E+03 O.OOE-01 O.OOE-01 O.OOE-01 RU105 2.26E-26 4.07E-23 6.23E-26 O.OOE-01 5.48E-25 O.OOE-01 O.OOE-01 O.OOE-01 RU106 1.28E+04 1.60E+06 1.03E+05 O.OOE-01 1.39E+05 O.OOE-01 O.OOE-01 O.OOE-01 AG110M 1.06E+02 1.57E+04 1.96E+02 1.32E+02 2.46E+02 O.OOE-01 O.OOE-01 O.OOE-01 TE125M 1.83E+03 1.32E+04 1.37E+04 3.71E+03 O.OOE-01 3.85E+03 O.OOE-01 O.OOE-01 TE127M 5.09E+03 3.47E+04 4.28E+04 1.15E+04 1.22E+05 1.02E+04 O.OOE-01 O.OOE-01 TE127 1.68E-15 3.07E-13 7.86E-15 2.12E-15 2.23E-14 5.44E-15 O.OOE-01 O.OOE-01 TE129M 6.70E+03 5.27E+04 4.32E+04 1.21 E+04 1.27E+05 1.39E+04 O.OOE-01 O.OOE-01 TE129 1.01 E-27 2.64E-25 4.24E-27 1.19E-27 1.24E-26 3.03E-27 O.OOE-01 O.OOE-01 TE131M 6.17E-03 2.35E-01 1.68E-02 5.80E-03 5.61E-02 1.19E-02 O.OOE-01 O.OOE-01 TE131 9.76E-29 1.72E-27 3.28E-28 1.00E-28 9.92E-28 2.51E-28 O.OOE-01 O.OOE-01 TE132 2.76E+01 2.30E+02 5.16E+01 2.28E+01 2.12E+02 3.32E+01 O.OOE-01 O.OOE-01 1130 1.43E-11 1.30E-11 1.38E-11 2.78E-11 4.16E-11 3.07E-09 O.OOE-01 O.OOE-01 I 131 4.57E+01 7.16E+OO 7.99E+01 8.04E+01 1.32E+02 2.66E+04 O.OOE-01 O.OOE-01 1132 2.14E-27 5.47E-27 2.53E-27 4.64E-27 7.11E-27 2.16E-25 O.OOE-01 O.OOE-01 1133 1.28E-06 1.37E-06 2.74E-06 3.39E-06 5.65E-06 6.30E-04 O.OOE-01 O.OOE-01 I 134 2.65E-28 3.81 E-28 3.10E-28 5.75E-28 8.80E-28 1.32E-26 O.OOE-01 O.OOE-01 1135 2.26E-22 3.64E-22 2.66E-22 4.78E-22 7.33E-22 4.23E-20 O.OOE-01 O.OOE-01 CS134 7.36E+03 1.88E+02 2.13E+04 3.49E+04 1.08E+04 O.OOE-01 3.88E+03 O.OOE-01 CS136 6.92E+02 3.76E+01 3.89E+02 1.07E+03 5.69E+02 O.OOE-01 8.49E+01 O.OOE-01 CS137 4.36E+03 1.85E+02 3.08E+04 2.95E+04 9.62E+03 O.OOE-01 3.46E+03 O.OOE-01 CS138 7.67E-29 5.57E-29 8.70E-29 1.21 E-28 8.51E-29 O.OOE-01 9.16E-30 O.OOE-01 BA139 2.05E-29 4.08E-26 7.07E-28 3.77E-31 3.29E-31 O.OOE-01 2.22E-31 O.OOE-01 BA140 6.18E+01 5.36E+02 1.06E+03 9.27E-01 3.02E-01 O.OOE-01 5.53E-01 O.OOE-01 BA141 4.20E-31 7.36E-30 1.29E-29 7.23E-33 6.25E-33 O.OOE-01 4.25E-32 O.OOE-01 BA142 3.68E-32 8.58E-33 6.58E-31 4.74E-34 3.83E-34 O.OOE-01 2.79E-34 O.OOE-01 LA140 1.60E-07 1.32E-02 1.36E-06 4.75E-07 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 LA142 6.59E-33 4.17E-27 6.60E-32 2.11E-32 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CE141 3.92E-02 3.29E+02 5.29E-01 2.64E-01 1.16E-01 O.OOE-01 O.OOE-01 O.OOE-01 CE143 6.25E-08 6.32E-03 7.96E-07 4.31E-04 1.81 E-07 O.OOE-01 O.OOE-01 O.OOE-01 CE144 2.86E+OO 4.38E+03 5.36E+01 1.68E+01 9.30E+OO O.OOE-01 O.OOE-01 O.OOE-01 PR143 4.01E-02 8.72E+02 8.08E-01 2.43E-01 1.32E-01 O.OOE-01 O.OOE-01 O.OOE-01 PR144 5.09E-34 6.73E-30 1.01 E-32 3.13E-33 1.65E-33 O.OOE-01 O.OOE-01 O.OOE-01 ND147 1.80E-02 3.69E+02 2.88E-01 2.33E-01 1.28E-01 O.OOE-01 O.OOE-01 O.OOE-01 W187 2.15E-07 6.74E-05 8.10E-07 4.80E-07 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 NP239 5.25E-07 5.52E-02 1.04E-05 7.46E-07 2.16E-06 O.OOE-01 O.OOE-01 O.OOE-01 DAEC ODAM Page 242 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =CHILD PATHWAY= ANIMAL DRINKING WATER--MILK TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN (mrem gal)/(Ci min) H 3 1.05E+01 1.05E+01 O.OOE-01 1.05E+01 1.05E+01 1.05E+01 1.05E+01 O.OOE-01 c 14 2.88E+02 2.88E+02 1.44E+03 2.88E+02 2.88E+02 2.88E+02 2.88E+02 O.OOE-01 NA24 2.41E+02 2.41 E+02 2.41 E+02 2.41E+02 2.41E+02 2.41E+02 2.41E+02 O.OOE-01 p 32 7.15E+03 5.13E+03 1.86E+05 8.68E+03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CR 51 1.85E-01 9.80E+OO O.OOE-01 O.OOE-01 2.80E-02 1.03E-01 1.87E-01 O.OOE-01 MN 54 7.05E+OO 2.22E+01 O.OOE-01 2.65E+01 7.42E+OO O.OOE-01 O.OOE-01 O.OOE-01 MN 56 3.36E-07 2.16E-04 O.OOE-01 1.49E-06 1.80E-06 O.OOE-01 O.OOE-01 O.OOE-01 FE 55 2.25E+01 1.34E+01 1.37E+02 7.26E+01 O.OOE-01 O.OOE-01 4.11 E+01 O.OOE-01 FE 59 1.54E+02 3.21E+02 1.91 E+02 3.08E+02 O.OOE-01 O.OOE-01 8.94E+01 O.OOE-01 C058 5.37E+01 1.02E+02 O.OOE-01 1.75E+01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 C060 1.55E+02 2.91E+02 O.OOE-01 5.25E+01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 Nl63 1.22E+03 1.29E+02 3.58E+04 1.92E+03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl65 1.14E-05 2.39E-03 2.0?E-04 1.95E-05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 cu 64 1.41E+OO 1.09E+02 O.OOE-01 2.33E+OO 5.64E+OO O.OOE-01 O.OOE-01 O.OOE-01 ZN 65 8.74E+03 2.47E+03 5.28E+03 1.41E+04 8.86E+03 O.OOE-01 O.OOE-01 O.OOE-01 ZN 69 6.36E-16 4.34E-13 4.76E-15 6.89E-15 4.18E-15 O.OOE-01 O.OOE-01 O.OOE-01 BR 83 5.78E-05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 84 2.33E-25 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 85 1.99E-32 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 86 1.14E+04 1.19E+03 O.OOE-01 1.85E+04 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 88 3.35E-26 2.37E-27 O.OOE-01 4.83E-26 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 89 1.78E-26 1.75E-28 O.OOE-01 2.00E-26 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 89 2.91E+02 3.95E+02 1.02E+04 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 90 4.09E+03 1.82E+03 2.03E+05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 91 2.01 E-01 1.17E+01 5.31 E+OO 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 92 1.05E-05 4.94E-03 2.61 E-04 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 90 6.44E-05 6.85E+OO 2.40E-03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Y 91M 1.95E-24 1.05E-19 5.36E-23 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 91 1.56E-03 7.78E+OO 5.84E-02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 92 7.21E-10 7.28E-04 2.52E-08 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 93 1.0?E-06 5.81 E-01 3.90E-05 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 ZR 95 1.10E-03 1.29E+OO 5.64E-03 1.24E-03 1.??E-03 O.OOE-01 O.OOE-01 O.OOE-01 ZR 97 3.96E-06 1.02E+OO 4.65E-05 6.72E-06 9.64E-06 O.OOE-01 O.OOE-01 O.OOE-01 NB 95 1.49E-01 3.86E+02 5.37E-01 2.09E-01 1.96E-01 O.OOE-01 O.OOE-01 O.OOE-01 M099 1.46E+02 4.90E+02 O.OOE-01 5.92E+02 1.26E+03 O.OOE-01 O.OOE-01 O.OOE-01 TC 99M 2.64E-02 9.05E-01 8.11 E-04 1.59E-03 2.31E-02 O.OOE-01 8.0?E-04 O.OOE-01 TC101 1.65E-27 4.13E-28 1.24E-28 1.30E-28 2.22E-27 O.OOE-01 6.87E-29 O.OOE-01 DAEC ODAM Page 243 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =CHILD PATHWAY= ANIMAL DRINKING WATER--MILK TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN mrem al I Ci min RU103 2.69E-03 1.81E-01 7.01E-03 O.OOE-01 1.76E-02 O.OOE-01 O.OOE-01 O.OOE-01 RU105 1.10E-07 1.98E-04 3.03E-07 O.OOE-01 2.67E-06 O.OOE-01 O.OOE-01 O.OOE-01 RU106 1.44E-02 1.BOE+OO 1.16E-01 O.OOE-01 1.56E-01 O.OOE-01 O.OOE-01 O.OOE-01 AG110M 1.44E+02 2.14E+04 2.66E+02 1.80E+02 3.35E+02 O.OOE-01 O.OOE-01 O.OOE-01 TE125M 1.47E+01 1.07E+02 1.10E+02 3.00E+01 O.OOE-01 3.10E+01 O.OOE-01 O.OOE-01 TE127M 3.36E+01 2.29E+02 2.83E+02 7.63E+01 8.08E+02 6.78E+01 O.OOE-01 O.OOE-01 TE127 2.65E-02 4.83E+OO 1.24E-01 3.33E-02 3.52E-01 8.56E-02 O.OOE-01 O.OOE-01 TE129M 7.20E+01 5.66E+02 4.64E+02 1.29E+02 1.36E+03 1.49E+02 O.OOE-01 O.OOE-01 TE129 6.06E-14 1.59E-11 2.55E-13 7.13E-14 7.47E-13 1.82E-13 O.OOE-01 O.OOE-01 TE131M 8.48E+OO 3.23E+02 2.30E+01 7.97E+OO 7.72E+01 1.64E+01 O.OOE-01 O.OOE-01 TE131 4.09E-28 7.21E-27 1.37E-27 4.19E-28 4.15E-27 1.05E-27 O.OOE-01 O.OOE-01 TE132 3.48E+01 2.90E+02 6.50E+01 2.88E+01 2.67E+02 4.19E+01 O.OOE-01 O.OOE-01 I 130 1.16E+01 1.05E+01 1.11E+01 2.24E+01 3.35E+01 2.47E+03 O.OOE-01 O.OOE-01 I 131 4.91 E+02 7.70E+01 8.60E+02 8.65E+02 1.42E+03 2.86E+05 O.OOE-01 O.OOE-01 I 132 1.56E-05 3.99E-05 1.85E-05 3.39E-05 5.19E-05 1.57E-03 O.OOE-01 O.OOE-01 1133 3.23E+01 3.44E+01 6.90E+01 8.53E+01 1.42E+02 1.59E+04 O.OOE-01 O.OOE-01 1134 2.99E-16 4.30E-16 3.50E-16 6.49E-16 9.93E-16 1.49E-14 O.OOE-01 O.OOE-01 1135 5.15E-01 8.29E-01 6.04E-01 1.09E+OO 1.67E+OO 9.64E+01 O.OOE-01 O.OOE-01 CS134 9.64E+03 2.46E+02 2.78E+04 4.57E+04 1.42E+04 O.OOE-01 5.08E+03 O.OOE-01 CS136 4.47E+03 2.43E+02 2.51 E+03 6.91 E+03 3.68E+03 O.OOE-01 5.49E+02 O.OOE-01 CS137 5.51 E+03 2.34E+02 3.90E+04 3.73E+04 1.22E+04 O.OOE-01 4.37E+03 O.OOE-01 CS138 5.78E-26 4.20E-26 6.56E-26 9.12E-26 6.42E-26 O.OOE-01 6.91E-27 O.OOE-01 BA139 8.98E-13 1.79E-09 3.10E-11 1.65E-14 1.44E-14 O.OOE-01 9.72E-15 O.OOE-01 BA140 1.73E+01 1.50E+02 2.96E+02 2.59E-01 8.43E-02 O.OOE-01 1.54E-01 O.OOE-01 BA141 2.33E-29 4.0SE-28 7.15E-28 4.01 E-31 3.47E-31 O.OOE-01 2.35E-30 O.OOE-01 BA142 3.48E-30 8.13E-31 6.23E-29 4.48E-32 3.63E-32 O.OOE-01 2.64E-32 O.OOE-01 LA140 2.54E-05 2.10E+OO 2.16E-04 7.55E-05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 LA142 6.89E-16 4.36E-10 6.91 E-15 2.20E-15 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CE141 2.BOE-03 2.35E+01 3.78E-02 1.BBE-02 8.26E-03 O.OOE-01 O.OOE-01 O.OOE-01 CE143 1.96E-04 1.98E+01 2.49E-03 1.35E+OO 5.67E-04 O.OOE-01 O.OOE-01 O.OOE-01 CE144 1.10E-01 1.68E+02 2.06E+OO 6.45E-01 3.57E-01 O.OOE-01 O.OOE-01 O.OOE-01 PR143 8.73E-05 1.90E+OO 1.76E-03 5.28E-04 2.86E-04 O.OOE-01 O.OOE-01 O.OOE-01 PR144 2.54E-34 3.36E-30 5.05E-33 1.56E-33 8.26E-34 O.OOE-01 O.OOE-01 O.OOE-01 ND147 7.65E-05 1.57E+OO 1.22E-03 9.BBE-04 5.42E-04 O.OOE-01 O.OOE-01 O.OOE-01 w 187 1.37E-01 4.29E+01 5.15E-01 3.05E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 NP239 7.23E-06 7.61 E-01 1.43E-04 1.03E-05 2.97E-05 O.OOE-01 O.OOE-01 O.OOE-01 DAEC ODAM Page 244 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =CHILD PATHWAY= ANIMAL DRINKING WATER--MEAT TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN (mrem gaQ/(Ci min} H 3 1.19E+OO 1.19E+OO O.OOE-01 1.19E+OO 1.19E+OO 1.19E+OO 1.19E+OO O.OOE-01 c 14 7.72E+01 7.72E+01 3.86E+02 7.72E+01 7.72E+01 7.72E+01 7.72E+01 O.OOE-01 NA24 4.24E-08 4.24E-08 4.24E-08 4.24E-08 4.24E-08 4.24E-08 4.24E-08 O.OOE-01 p 32 5.70E+02 4.08E+02 1.48E+04 6.91E+02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CR 51 1.33E-02 7.05E-01 O.OOE-01 O.OOE-01 2.02E-03 7.38E-03 1.35E-02 O.OOE-01 MN 54 2.24E+OO 7.07E+OO O.OOE-01 8.42E+OO 2.36E+OO O.OOE-01 O.OOE-01 O.OOE-01 MN 56 4.15E-28 2.66E-25 O.OOE-01 1.84E-27 2.22E-27 O.OOE-01 O.OOE-01 O.OOE-01 FE 55 7.67E+01 4.58E+01 4.67E+02 2.47E+02 O.OOE-01 O.OOE-01 1.40E+02 O.OOE-01 FE 59 4.01 E+02 8.38E+02 4.97E+02 8.04E+02 O.OOE-01 O.OOE-01 2.33E+02 O.OOE-01 co 58 6.06E+01 1.15E+02 O.OOE-01 1.98E+01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 C060 2.07E+02 3.89E+02 O.OOE-01 7.02E+01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl63 9.97E+02 1.06E+02 2.93E+04 1.57E+03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl65 4.42E-26 9.28E-24 8.05E-25 7.58E-26 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 cu 64 4.52E-12 3.51E-10 O.OOE-01 7.48E-12 1.81E-11 O.OOE-01 O.OOE-01 O.OOE-01 ZN 65 6.62E+02 1.87E+02 3.99E+02 1.06E+03 6.70E+02 O.OOE-01 O.OOE-01 O.OOE-01 ZN 69 7.61E-28 5.19E-25 5.70E-27 8.24E-27 5.00E-27 O.OOE-01 O.OOE-01 O.OOE-01 BR 83 3.00E-26 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 84 1.25E-26 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 85 1.07E-33 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 86 6.25E+02 6.54E+01 O.OOE-01 1.02E+03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 88 3.59E-27 2.53E-28 O.OOE-01 5.17E-27 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 89 1.90E-27 1.87E-29 O.OOE-01 2.14E-27 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 89 1.77E+01 2.40E+01 6.19E+02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 90 3.17E+02 1.41E+02 1.58E+04 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 91 3.03E-16 1.77E-14 8.03E-15 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 92 1.51 E-27 7.16E-25 3.78E-26 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 90 2.89E-05 3.07E+OO 1.08E-03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Y 91M 2.49E-31 1.34E-26 6.84E-30 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 91 6.01E-02 2.99E+02 2.25E+OO O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 92 3.51E-30 3.55E-24 1.23E-28 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 93 6.41E-18 3.48E-12 2.34E-16 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 95 6.39E-01 7.49E+02 3.27E+OO 7.18E-01 1.03E+OO O.OOE-01 O.OOE-01 O.OOE-01 ZR 97 5.57E-11 1.43E-05 6.53E-10 9.44E-11 1.36E-10 O.OOE-01 O.OOE-01 O.OOE-01 NB 95 1.22E+OO 3.14E+03 4.37E+OO 1.70E+OO 1.60E+OO O.OOE-01 O.OOE-01 O.OOE-01 M099 1.72E-01 5.77E-01 O.OOE-01 6.97E-01 1.49E+OO O.OOE-01 O.OOE-01 O.OOE-01 TC 99M 1.06E-23 3.65E-22 3.27E-25 6.42E-25 9.32E-24 O.OOE-01 3.26E-25 O.OOE-01 TC101 2.73E-27 6.85E-28 2.06E-28 2.15E-28 3.67E-27 O.OOE-01 1.14E-28 O.OOE-01 DAEC ODAM Page 245 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =CHILD PATHWAY= ANIMAL DRINKING WATER--MEAT TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN (mrem gaQ/(Ci min) RU103 8.12E+01 5.46E+03 2.11 E+02 O.OOE-01 5.32E+02 O.OOE-01 O.OOE-01 O.OOE-01 RU105 7.21 E-26 1.30E-22 1.99E-25 O.OOE-01 1.75E-24 O.OOE-01 O.OOE-01 O.OOE-01 RU106 5.78E+02 7.21E+04 4.64E+03 O.OOE-01 6.26E+03 O.OOE-01 O.OOE-01 O.OOE-01 AG110M 4.82E+OO 7.16E+02 8.92E+OO 6.02E+OO 1.12E+01 O.OOE-01 O.OOE-01 O.OOE-01 TE125M 9.48E+01 6.86E+02 7.11 E+02 1.93E+02 O.OOE-01 2.00E+02 O.OOE-01 O.OOE-01 TE127M 2.39E+02 1.63E+03 2.01 E+03 5.42E+02 5.75E+03 4.82E+02 O.OOE-01 O.OOE-01 TE127 2.58E-15 4.70E-13 1.20E-14 3.24E-15 3.42E-14 8.32E-15 O.OOE-01 O.OOE-01 TE129M 3.96E+02 3.11 E+03 2.55E+03 7.12E+02 7.49E+03 8.22E+02 O.OOE-01 O.OOE-01 TE129 1.21 E-26 3.18E-24 5.11 E-26 1.43E-26 1.50E-25 3.65E-26 O.OOE-01 O.OOE-01 TE131M 3.12E-03 1.19E-01 8.47E-03 2.93E-03 2.84E-02 6.03E-03 O.OOE-01 O.OOE-01 TE131 3.26E-27 5.75E-26 1.10E-26 3.34E-27 3.31E-26 8.38E-27 O.OOE-01 O.OOE-01 TE132 6.04E+OO 5.03E+01 1.13E+01 5.00E+OO 4.64E+01 7.28E+OO O.OOE-01 O.OOE-01 I 130 1.68E-11 1.53E-11 1.62E-11 3.27E-11 4.88E-11 3.60E-09 O.OOE-01 O.OOE-01 I 131 5.21 E+OO 8.16E-01 9.11E+OO 9.17E+OO 1.51 E+01 3.03E+03 O.OOE-01 O.OOE-01 1132 1.31E-26 3.34E-26 1.55E-26 2.84E-26 4.35E-26 1.32E-24 O.OOE-01 O.OOE-01 1133 9.14E-07 9.73E-07 1.95E-06 2.41E-06 4.03E-06 4.49E-04 O.OOE-01 O.OOE-01 1134 4.24E-27 6.10E-27 4.96E-27 9.20E-27 1.41E-26 2.12E-25 O.OOE-01 O.OOE-01 1135 4.88E-22 7.87E-22 5.74E-22 1.03E-21 1.58E-21 9.14E-20 O.OOE-01 O.OOE-01 CS134 3.27E+02 8.36E+OO 9.45E+02 1.55E+03 4.81 E+02 O.OOE-01 1.72E+02 O.OOE-01 CS136 5.96E+01 3.24E+OO 3.35E+01 9.21E+01 4.90E+01 O.OOE-01 7.32E+OO O.OOE-01 CS137 1.90E+02 8.06E+OO 1.34E+03 1.29E+03 4.19E+02 O.OOE-01 1.51E+02 O.OOE-01 CS138 2.00E-27 1.45E-27 2.26E-27 3.15E-27 2.21E-27 O.OOE-01 2.38E-28 O.OOE-01 BA139 2.09E-28 4.16E-25 7.21 E-27 3.85E-30 3.36E-30 O.OOE-01 2.26E-30 O.OOE-01 BA140 5.39E+OO 4.68E+01 9.24E+01 8.09E-02 2.63E-02 O.OOE-01 4.82E-02 O.OOE-01 BA141 1.93E-29 3.38E-28 5.93E-28 3.32E-31 2.87E-31 O.OOE-01 1.95E-30 O.OOE-01 BA142 2.88E-30 6.73E-31 5.16E-29 3.71E-32 3.01E-32 O.OOE-01 2.18E-32 O.OOE-01 LA140 6.23E-08 5.15E-03 5.28E-07 1.85E-07 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 LA142 6.01E-32 3.80E-26 6.02E-31 1.92E-31 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CE141 2.37E-03 1.99E+01 3.20E-02 1.59E-02 6.99E-03 O.OOE-01 O.OOE-01 O.OOE-01 CE143 2.90E-08 2.93E-03 3.69E-07 2.00E-04 8.39E-08 O.OOE-01 O.OOE-01 O.OOE-01 CE144 1.31 E-01 2.00E+02 2.44E+OO 7.66E-01 4.24E-01 O.OOE-01 O.OOE-01 O.OOE-01 PR143 3.39E-03 7.38E+01 6.84E-02 2.05E-02 1.11 E-02 O.OOE-01 O.OOE-01 O.OOE-01 PR144 2.47E-32 3.27E-28 4.91 E-31 1.52E-31 8.04E-32 O.OOE-01 O.OOE-01 O.OOE-01 ND147 1.70E-03 3.47E+01 2.71 E-02 2.19E-02 1.20E-02 O.OOE-01 O.OOE-01 O.OOE-01 w 187 1.35E-07 4.22E-05 5.07E-07 3.00E-07 O.OOE-01 0.00E-01 0.00E-01 0.00E-01 NP239 1.51 E-07 1.59E-02 3.00E-06 2.15E-07 6.22E-07 O.OOE-01 O.OOE-01 O.OOE-01 DAEC ODAM Page 246 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =CHILD PATHWAY= RIVER SHORELINE DEPOSITS TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN (mrem gal}/(Ci min) H 3 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 c 14 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 NA24 2.19E+OO 2.19E+OO 2.19E+OO 2.19E+OO 2.19E+OO 2.19E+OO 2.19E+OO 2.54E+OO p 32 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CR 51 8.55E-01 8.55E-01 8.55E-01 8.55E-01 8.55E-01 8.55E-01 8.55E-01 1.01E+OO MN 54 2.54E+02 2.54E+02 2.54E+02 2.54E+02 2.54E+02 2.54E+02 2.54E+02 2.98E+02 MN 56 1.61 E-01 1.61 E-01 1.61E-01 1.61 E-01 1.61 E-01 1.61 E-01 1.61 E-01 1.90E-01 FE 55 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 FE 59 5.01E+01 5.01E+01 5.01 E+01 5.01E+01 5.01E+01 5.01E+01 5.01E+01 5.88E+01 C058 6.98E+01 6.98E+01 6.98E+01 6.98E+01 6.98E+01 6.98E+01 6.98E+01 8.18E+01 C060 3.95E+03 3.95E+03 3.95E+03 3.95E+03 3.95E+03 3.95E+03 3.95E+03 4.65E+03 Nl63 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl65 5.31E-02 5.31E-02 5.31 E-02 5.31E-02 5.31E-02 5.31E-02 5.31E-02 6.17E-02 cu 64 1.11E-01 1.11E-01 1.11 E-01 1.11 E-01 1.11E-01 1.11E-01 1.11 E-01 1.25E-01 ZN 65 1.37E+02 1.37E+02 1.37E+02 1.37E+02 1.37E+02 1.37E+02 1.37E+02 1.58E+02 ZN 69 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 83 8.70E-04 8.70E-04 8.70E-04 8.70E-04 8.70E-04 8.70E-04 8.70E-04 1.26E-03 BR 84 3.27E-02 3.27E-02 3.27E-02 3.27E-02 3.27E-02 3.27E-02 3.27E-02 3.81 E-02 BR 85 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 86 1.65E+OO 1.65E+OO 1.65E+OO 1.65E+OO 1.65E+OO 1.65E+OO 1.65E+OO 1.89E+OO RB 88 4.83E-03 4.83E-03 4.83E-03 4.83E-03 4.83E-03 4.83E-03 4.83E-03 5.52E-03 RB 89 1.70E-02 1.70E-02 1.70E-02 1.70E-02 1.70E-02 1.70E-02 1.70E-02 2.04E-02 SR 89 3.97E-03 3.97E-03 3.97E-03 3.97E-03 3.97E-03 3.97E-03 3.97E-03 4.61 E-03 SR 90 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 91 3.91 E-01 3.91 E-01 3.91 E-01 3.91 E-01 3.91 E-01 3.91 E-01 3.91 E-01 4.57E-01 SR 92 1.39E-01 1.39E-01 1.39E-01 1.39E-01 1.39E-01 1.39E-01 1.39E-01 1.55E-01 y 90 8.25E-04 8.25E-04 8.25E-04 8.25E-04 8.25E-04 8.25E-04 8.25E-04 9.76E-04 Y 91M 1.69E-02 1.69E-02 1.69E-02 1.69E-02 1.69E-02 1.69E-02 1.69E-02 1.96E-02 y 91 1.97E-01 1.97E-01 1.97E-01 1.97E-01 1.97E-01 1.97E-01 1.97E-01 2.22E-01 y 92 3.26E-02 3.26E-02 3.26E-02 3.26E-02 3.26E-02 3.26E-02 3.26E-02 3.87E-02 y 93 3.34E-02 3.34E-02 3.34E-02 3.34E-02 3.34E-02 3.34E-02 3.34E-02 4.57E-02 ZR 95 4.51E+01 4.51E+01 4.51 E+01 4.51E+01 4.51E+01 4.51E+01 4.51E+01 5.23E+01 ZR 97 5.41 E-01 5.41 E-01 5.41 E-01 5.41 E-01 5.41 E-01 5.41 E-01 5.41 E-01 6.30E-01 NB 95 2.52E+01 2.52E+01 2.52E+01 2.52E+01 2.52E+01 2.52E+01 2.52E+01 2.96E+01 MO 99 7.33E-01 7.33E-01 7.33E-01 7.33E-01 7.33E-01 7.33E-01 7.33E-01 8.48E-01 TC 99M 3.34E-02 3.34E-02 3.34E-02 3.34E-02 3.34E-02 3.34E-02 3.34E-02 3.83E-02 TC101 2.79E-03 2.79E-03 2.79E-03 2.79E-03 2.79E-03 2.79E-03 2.79E-03 3.10E-03 DAEC ODAM Page 247 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =CHILD PATHWAY= RIVER SHORELINE DEPOSITS TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN mrem al I Ci min RU103 1.99E+01 1.99E+01 1.99E+01 1.99E+01 1.99E+01 1.99E+01 1.99E+01 2.32E+01 RU105 1.15E-01 1.15E-01 1.15E-01 1.15E-01 1.15E-01 1.15E-01 1.15E-01 1.30E-01 RU106 7.75E+01 7.75E+01 7.75E+01 7.75E+01 7.75E+01 7.75E+01 7.75E+01 9.31 E+01 AG110M 6.34E+02 6.34E+02 6.34E+02 6.34E+02 6.34E+02 6.34E+02 6.34E+02 7.39E+02 TE125M 2.86E-01 2.86E-01 2.86E-01 2.86E-01 2.86E-01 2.86E-01 2.86E-01 3.92E-01 TE127M 1.68E-02 1.68E-02 1.68E-02 1.68E-02 1.68E-02 1.68E-02 1.68E-02 1.99E-02 TE127 5.43E-04 5.43E-04 5.43E-04 5.43E-04 5.43E-04 5.43E-04 5.43E-04 5.97E-04 TE129M 3.63E+OO 3.63E+OO 3.63E+OO 3.63E+OO 3.63E+OO 3.63E+OO 3.63E+OO 4.24E+OO TE129 4.54E-03 4.54E-03 4.54E-03 4.54E-03 4.54E-03 4.54E-03 4.54E-03 5.37E-03 TE131M 1.47E+OO 1.47E+OO 1.47E+OO 1.47E+OO 1.47E+OO 1.47E+OO 1.47E+OO 1.73E+OO TE131 4.56E-03 4.56E-03 4.56E-03 4.56E-03 4.56E-03 4.56E-03 4.56E-03 5.38E+OO TE132 7.78E-01 7.78E-01 7.78E-01 7.78E-01 7.78E-01 7.78E-01 7.78E-01 9.15E-01 1130 1.01E+OO 1.01E+OO 1.01E+OO 1.01E+OO 1.01E+OO 1.01E+OO 1.01E+OO 1.22E+OO I 131 3.16E+OO 3.16E+OO 3.16E+OO 3.16E+OO 3.16E+OO 3.16E+OO 3.16E+OO 3.84E+OO 1132 2.22E-01 2.22E-01 2.22E-01 2.22E-01 2.22E-01 2.22E-01 2.22E-01 2.61 E-01 1133 4.49E-01 4.49E-01 4.49E-01 4.49E-01 4.49E-01 4.49E-01 4.49E-01 5.46E-01 1134 7.57E-02 7.57E-02 7.57E-02 7.57E-02 7.57E-02 7.57E-02 7.57E-02 8.99E-02 I 135 4.58E-01 4.58E-01 4.58E-01 4.58E-01 4.58E-01 4.58E-01 4.58E-01 5.35E-01 CS134 1.26E+03 1.26E+03 1.26E+03 1.26E+03 1.26E+03 1.26E+03 1.26E+03 1.46E+03 CS136 2.76E+01 2.76E+01 2.76E+01 2.76E+01 2.76E+01 2.76E+01 2.76E+01 3.13E+01 CS137 1.89E+03 1.89E+03 1.89E+03 1.89E+03 1.89E+03 1.89E+03 1.89E+03 2.21 E+03 CS138 5.81 E-02 5.81 E-02 5.81 E-02 5.81E-02 5.81E-02 5.81E-02 5.81E-02 6.64E-02 BA139 1.84E-02 1.84E-02 1.84E-02 1.84E-02 1.84E-02 1.84E-02 1.84E-02 2.07E-02 BA140 3.77E+OO 3.77E+OO 3.77E+OO 3.77E+OO 3.77E+OO 3.77E+OO 3.77E+OO 4.31 E+OO BA141 6.11E-03 6.11 E-03 6.11 E-03 6.11 E-03 6.11 E-03 6.11E-03 6.11 E-03 6.96E-03 BA142 5.59E-03 5.59E-03 5.59E-03 5.59E-03 5.59E-03 5.59E-03 5.59E-03 6.37E-03 LA140 3.53E+OO 3.53E+OO 3.53E+OO 3.53E+OO 3.53E+OO 3.53E+OO 3.53E+OO 4.00E+OO LA142 1.29E-01 1.29E-01 1.29E-01 1.29E-01 1.29E-01 1.29E-01 1.29E-01 1.55E-01 CE141 2.51 E+OO 2.51 E+OO 2.51 E+OO 2.51 E+OO 2.51 E+OO 2.51 E+OO 2.51 E+OO 2.83E+OO CE143 4.26E-01 4.26E-01 4.26E-01 4.26E-01 4.26E-01 4.26E-01 4.26E-01 4.84E-01 CE144 1.28E+01 1.28E+01 1.28E+01 1.28E+01 1.28E+01 1.28E+01 1.28E+01 1.48E+01 PR143 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 PR144 2.65E-04 2.65E-04 2.65E-04 2.65E-04 2.65E-04 2.65E-04 2.65E-04 3.04E-04 ND147 1.56E+OO 1.56E+OO 1.56E+OO 1.56E+OO 1.56E+OO 1.56E+OO 1.56E+OO 1.87E+OO W187 4.33E-01 4.33E-01 4.33E-01 4.33E-01 4.33E-01 4.33E-01 4.33E-01 5.02E-01 NP239 3.15E-01 3.15E-01 3.15E-01 3.15E-01 3.15E-01 3.15E-01 3.15E-01 3.64E-01 DAEC ODAM Page 248 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =CHILD PATHWAY= SWIMMING TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN {mrem gaQ/{Ci min} H 3 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 c 14 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 NA24 1.09E+02 1.09E+02 1.09E+02 1.09E+02 1.09E+02 1.09E+02 1.09E+02 O.OOE-01 p 32 8.99E-02 8.99E-02 8.99E-02 8.99E-02 8.99E-02 8.99E-02 8.99E-02 O.OOE-01 CR 51 7.30E-01 7.30E-01 7.30E-01 7.30E-01 7.30E-01 7.30E-01 7.30E-01 O.OOE-01 MN 54 2.11E+01 2.11 E+01 2.11 E+01 2.11 E+01 2.11E+01 2.11E+01 2.11 E+01 O.OOE-01 MN 56 4.38E+01 4.38E+01 4.38E+01 4.38E+01 4.38E+01 4.38E+01 4.38E+01 O.OOE-01 FE 55 8.99E-04 8.99E-04 8.99E-04 8.99E-04 8.99E-04 8.99E-04 8.99E-04 O.OOE-01 FE 59 3.09E+01 3.09E+01 3.09E+01 3.09E+01 3.09E+01 3.09E+01 3.09E+01 O.OOE-01 co 58 2.53E+01 2.53E+01 2.53E+01 2.53E+01 2.53E+01 2.53E+01 2.53E+01 O.OOE-01 C060 6.46E+01 6.46E+01 6.46E+01 6.46E+01 6.46E+01 6.46E+01 6.46E+01 O.OOE-01 Nl63 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl65 1.37E+01 1.37E+01 1.37E+01 1.37E+01 1.37E+01 1.37E+01 1.37E+01 O.OOE-01 cu 64 5.17E+OO 5.17E+OO 5.17E+OO 5.17E+OO 5.17E+OO 5.17E+OO 5.17E+OO O.OOE-01 ZN 65 1.55E+01 1.55E+01 1.55E+01 1.55E+01 1.55E+01 1.55E+01 1.55E+01 O.OOE-01 ZN 69 2.09E-02 2.09E-02 2.09E-02 2.09E-02 2.09E-02 2.09E-02 2.09E-02 O.OOE-01 BR 83 2.32E-01 2.32E-01 2.32E-01 2.32E-01 2.32E-01 2.32E-01 2.32E-01 O.OOE-01 BR 84 4.32E+01 4.32E+01 4.32E+01 4.32E+01 4.32E+01 4.32E+01 4.32E+01 O.OOE-01 BR 85 4.61E-02 4.61 E-02 4.61 E-02 4.61E-02 4.61E-02 4.61 E-02 4.61E-02 O.OOE-01 RB 86 2.39E+OO 2.39E+OO 2.39E+OO 2.39E+OO 2.39E+OO 2.39E+OO 2.39E+OO O.OOE-01 RB 88 1.34E+01 1.34E+01 1.34E+01 1.34E+01 1.34E+01 1.34E+01 1.34E+01 O.OOE-01 RB 89 4.81E+01 4.81E+01 4.81 E+01 4.81E+01 4.81E+01 4.81E+01 4.81E+01 O.OOE-01 SR 89 6.46E-02 6.46E-02 6.46E-02 6.46E-02 6.46E-02 6.46E-02 6.46E-02 O.OOE-01 SR 90 7.59E-03 7.59E-03 7.59E-03 7.59E-03 7.59E-03 7.59E-03 7.59E-03 O.OOE-01 SR 91 2.65E+01 2.65E+01 2.65E+01 2.65E+01 2.65E+01 2.65E+01 2.65E+01 O.OOE-01 SR 92 3.56E+01 3.56E+01 3.56E+01 3.56E+01 3.56E+01 3.56E+01 3.56E+01 O.OOE-01 y 90 1.83E-01 1.83E-01 1.83E-01 1.83E-01 1.83E-01 1.83E-01 1.83E-01 0.00E-01 Y 91M 1.29E+01 1.29E+01 1.29E+01 1.29E+01 1.29E+01 1.29E+01 1.29E+01 O.OOE-01 y 91 9.41E-02 9.41 E-02 9.41 E-02 9.41 E-02 9.41 E-02 9.41 E-02 9.41E-02 O.OOE-01 y 92 6.34E+OO 6.34E+OO 6.34E+OO 6.34E+OO 6.34E+OO 6.34E+OO 6.34E+OO O.OOE-01 y 93 2.65E+OO 2.65E+OO 2.65E+OO 2.65E+OO 2.65E+OO 2.65E+OO 2.65E+OO O.OOE-01 ZR 95 2.11E+01 2.11 E+01 2.11 E+01 2.11 E+01 2.11E+01 2.11E+01 2.11 E+01 O.OOE-01 ZR 97 2.10E+01 2.10E+01 2.10E+01 2.10E+01 2.10E+01 2.10E+01 2.10E+01 O.OOE-01 NB 95 1.97E+01 1.97E+01 1.97E+01 1.97E+01 1.97E+01 1.97E+01 1.97E+01 O.OOE-01 MO 99 6.60E+OO 6.60E+OO 6.60E+OO 6.60E+OO 6.60E+OO 6.60E+OO 6.60E+OO O.OOE-01 TC 99M 3.33E+OO 3.33E+OO 3.33E+OO 3.33E+OO 3.33E+OO 3.33E+OO 3.33E+OO O.OOE-01 TC101 7.13E+OO 7.13E+OO 7.13E+OO 7.13E+OO 7.13E+OO 7.13E+OO 7.13E+OO O.OOE-01 DAEC ODAM Page 249 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =CHILD PATHWAY= SWIMMING TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN (mrem gaQ/(Ci min} RU103 1.25E+01 1.25E+01 1.25E+01 1.25E+01 1.25E+01 1.25E+01 1.25E+01 O.OOE-01 RU105 1.66E+01 1.66E+01 1.66E+01 1.66E+01 1.66E+01 1.66E+01 1.66E+01 O.OOE-01 RU106 5.34E+OO 5.34E+OO 5.34E+OO 5.34E+OO 5.34E+OO 5.34E+OO 5.34E+OO O.OOE-01 AG110M 6.88E+01 6.88E+01 6.88E+01 6.88E+01 6.88E+01 6.88E+01 6.88E+01 O.OOE-01 TE125M 5.18E-02 5.18E-02 5.18E-02 5.18E-02 5.18E-02 5.18E-02 5.18E-02 O.OOE-01 TE127M 3.65E-03 3.65E-03 3.65E-03 3.65E-03 3.65E-03 3.65E-03 3.65E-03 O.OOE-01 TE127 3.91 E-02 3.91 E-02 3.91 E-02 3.91E-02 3.91 E-02 3.91E-02 3.91E-02 O.OOE-01 TE129M 2.95E+OO 2.95E+OO 2.95E+OO 2.95E+OO 2.95E+OO 2.95E+OO 2.95E+OO O.OOE-01 TE129 2.52E+OO 2.52E+OO 2.52E+OO 2.52E+OO 2.52E+OO 2.52E+OO 2.52E+OO O.OOE-01 TE131M 3.08E+01 3.08E+01 3.08E+01 3.08E+01 3.08E+01 3.08E+01 3.08E+01 O.OOE-01 TE131 8.81 E+OO 8.81 E+OO 8.81 E+OO 8.81 E+OO 8.81E+OO 8.81 E+OO 8.81 E+OO O.OOE-01 TE132 5.61 E+OO 5.61 E+OO 5.61 E+OO 5.61 E+OO 5.61 E+OO 5.61 E+OO 5.61E+OO O.OOE-01 1130 5.45E+01 5.45E+01 5.45E+01 5.45E+01 5.45E+01 5.45E+01 5.45E+01 O.OOE-01 I 131 1.10E+01 1.10E+01 1.10E+01 1.1 OE+01 1.10E+01 1.10E+01 1.10E+01 O.OOE-01 1132 6.00E+01 6.00E+01 6.00E+01 6.00E+01 6.00E+01 6.00E+01 6.00E+01 O.OOE-01 I 133 1.34E+01 1.34E+01 1.34E+01 1.34E+01 1.34E+01 1.34E+01 1.34E+01 O.OOE-01 I 134 5.45E+01 5.45E+01 5.45E+01 5.45E+01 5.45E+01 5.45E+01 5.45E+01 O.OOE-01 1135 4.59E+01 4.59E+01 4.59E+01 4.59E+01 4.59E+01 4.59E+01 4.59E+01 O.OOE-01 CS134 4.07E+01 4.07E+01 4.07E+01 4.07E+01 4.07E+01 4.07E+01 4.07E+01 O.OOE-01 CS136 5.76E+01 5.76E+01 5.16E+01 5.76E+01 5.76E+01 5.76E+01 5.76E+01 O.OOE-01 CS137 1.41E+01 1.41E+01 1.41E+01 1.41E+01 1.41E+01 1.41E+01 1.41E+01 O.OOE-01 CS138 4.94E+01 4.94E+01 4.94E+01 4.94E+01 4.94E+01 4.94E+01 4.94E+01 0.00E-01 BA139 1.03E+OO 1.03E+OO 1.03E+OO 1.03E+OO 1.03E+OO 1.03E+OO 1.03E+OO O.OOE-01 BA140 6.88E+OO 6.88E+OO 6.88E+OO 6.88E+OO 6.88E+OO 6.88E+OO 6.88E+OO O.OOE-01 BA141 1.23E+01 1.23E+01 1.23E+01 1.23E+01 1.23E+01 1.23E+01 1.23E+01 O.OOE-01 BA142 2.10E+01 2.10E+01 2.10E+01 2.10E+01 2.10E+01 2.10E+01 2.10E+01 O.OOE-01 LA140 5.75E+01 5.75E+01 5.75E+01 5.75E+01 5.75E+01 5.75E+01 5.75E+01 O.OOE-01 LA142 6.04E+01 6.04E+01 6.04E+01 6.04E+01 6.04E+01 6.04E+01 6.04E+01 O.OOE-01 CE141 1.83E+OO 1.83E+OO 1.83E+OO 1.83E+OO 1.83E+OO 1.83E+OO 1.83E+OO O.OOE-01 CE143 7.99E+OO 7.99E+OO 7.99E+OO 7.99E+OO 7.99E+OO 7.99E+OO 7.99E+OO O.OOE-01 CE144 1.21E+OO 1.21E+OO 1.21E+OO 1.21E+OO 1.21E+OO 1.21E+OO 1.21E+OO O.OOE-01 PR143 2.25E-02 2.25E-02 2.25E-02 2.25E-02 2.25E-02 2.25E-02 2.25E-02 O.OOE-01 PR144 6.18E-01 6.18E-01 6.18E-01 6.18E-01 6.18E-01 6.18E-01 6.18E-01 O.OOE-01 ND147 3.93E+OO 3.93E+OO 3.93E+OO 3.93E+OO 3.93E+OO 3.93E+OO 3.93E+OO O.OOE-01 w 187 1.16E+01 1.16E+01 1.16E+01 1.16E+01 1.16E+01 1.16E+01 1.16E+01 O.OOE-01 NP239 3.37E+OO 3.37E+OO 3.37E+OO 3.37E+OO 3.37E+OO 3.37E+OO 3.37E+OO O.OOE-01 DAEC ODAM Page 250 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =CHILD PATHWAY= BOATING TOTAL BODY GI-LU BONE LIVER KIDNEY THYROID LUNG SKIN (mrem gaQ!(Ci min} H 3 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 c 14 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 NA24 1.01E+02 1.01E+02 1.01 E+02 1.01 E+02 1.01E+02 1.01E+02 1.01E+02 O.OOE-01 p 32 8.35E-02 8.35E-02 8.35E-02 8.35E-02 8.35E-02 8.35E-02 8.35E-02 O.OOE-01 CR 51 6.78E-01 6.78E-01 6.78E-01 6.78E-01 6.78E-01 6.78E-01 6.78E-01 O.OOE-01 MN 54 1.96E+01 1.96E+01 1.96E+01 1.96E+01 1.96E+01 1.96E+01 1.96E+01 O.OOE-01 MN 56 4.06E+01 4.06E+01 4.06E+01 4.06E+01 4.06E+01 4.06E+01 4.06E+01 O.OOE-01 FE 55 8.35E-04 8.35E-04 8.35E-04 8.35E-04 8.35E-04 8.35E-04 8.35E-04 O.OOE-01 FE 59 2.87E+01 2.87E+01 2.87E+01 2.87E+01 2.87E+01 2.87E+01 2.87E+01 O.OOE-01 co 58 2.35E+01 2.35E+01 2.35E+01 2.35E+01 2.35E+01 2.35E+01 2.35E+01 O.OOE-01 C060 6.00E+01 6.00E+01 6.00E+01 6.00E+01 6.00E+01 6.00E+01 6.00E+01 O.OOE-01 Nl63 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl65 1.27E+01 1.27E+01 1.27E+01 1.27E+01 1.27E+01 1.27E+01 1.27E+01 O.OOE-01 cu 64 4.80E+OO 4.80E+OO 4.80E+OO 4.80E+OO 4.80E+OO 4.80E+OO 4.80E+OO O.OOE-01 ZN 65 1.44E+01 1.44E+01 1.44E+01 1.44E+01 1.44E+01 1.44E+01 1.44E+01 O.OOE-01 ZN 69 1.94E-02 1.94E-02 1.94E-02 1.94E-02 1.94E-02 1.94E-02 1.94E-02 O.OOE-01 BR 83 2.15E-01 2.15E-01 2.15E-01 2.15E-01 2.15E-01 2.15E-01 2.15E-01 O.OOE-01 BR 84 4.01E+01 4.01E+01 4.01E+01 4.01E+01 4.01E+01 4.01E+01 4.01E+01 O.OOE-01 BR 85 4.28E-02 4.28E-02 4.28E-02 4.28E-02 4.28E-02 4.28E-02 4.28E-02 O.OOE-01 RB 86 2.22E+OO 2.22E+OO 2.22E+OO 2.22E+OO 2.22E+OO 2.22E+OO 2.22E+OO O.OOE-01 RB 88 1.24E+01 1.24E+01 1.24E+01 1.24E+01 1.24E+01 1.24E+01 1.24E+01 O.OOE-01 RB 89 4.47E+01 4.47E+01 4.47E+01 4.47E+01 4.47E+01 4.47E+01 4.47E+01 O.OOE-01 SR 89 6.00E-02 6.00E-02 6.00E-02 6.00E-02 6.00E-02 6.00E-02 6.00E-02 O.OOE-01 SR 90 7.04E-03 7.04E-03 7.04E-03 7.04E-03 7.04E-03 7.04E-03 7.04E-03 O.OOE-01 SR 91 2.46E+01 2.46E+01 2.46E+01 2.46E+01 2.46E+01 2.46E+01 2.46E+01 O.OOE-01 SR 92 3.31E+01 3.31E+01 3.31 E+01 3.31E+01 3.31E+01 3.31E+01 3.31E+01 O.OOE-01 y 90 1.69E-01 1.69E-01 1.69E-01 1.69E-01 1.69E-01 1.69E-01 1.69E-01 O.OOE-01 Y 91M 1.20E+01 1.20E+01 1.20E+01 1.20E+01 1.20E+01 1.20E+01 1.20E+01 O.OOE-01 y 91 8.74E-02 8.74E-02 8.74E-02 8.74E-02 8.74E-02 8.74E-02 8.74E-02 O.OOE-01 y 92 5.89E+OO 5.89E+OO 5.89E+OO 5.89E+OO 5.89E+OO 5.89E+OO 5.89E+OO O.OOE-01 y 93 2.46E+OO 2.46E+OO 2.46E+OO 2.46E+OO 2.46E+OO 2.46E+OO 2.46E+OO O.OOE-01 ZR 95 1.96E+01 1.96E+01 1.96E+01 1.96E+01 1.96E+01 1.96E+01 1.96E+01 O.OOE-01 ZR 97 1.95E+01 1.95E+01 1.95E+01 1.95E+01 1.95E+01 1.95E+01 1.95E+01 O.OOE-01 NB 95 1.83E+01 1.83E+01 1.83E+01 1.83E+01 1.83E+01 1.83E+01 1.83E+01 O.OOE-01 MO 99 6.12E+OO 6.12E+OO 6.12E+OO 6.12E+OO 6.12E+OO 6.12E+OO 6.12E+OO O.OOE-01 TC 99M 3.10E+OO 3.10E+OO 3.10E+OO 3.10E+OO 3.10E+OO 3.10E+OO 3.10E+OO O.OOE-01 TC101 6.62E+OO 6.62E+OO 6.62E+OO 6.62E+OO 6.62E+OO 6.62E+OO 6.62E+OO O.OOE-01 DAEC ODAM Page 251 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =CHILD PATHWAY= BOATING TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN (mrem gaQ!(Ci min} RU103 1.16E+01 1.16E+01 1.16E+01 1.16E+01 1.16E+01 1.16E+01 1.16E+01 O.OOE-01 RU105 1.54E+01 1.54E+01 1.54E+01 1.54E+01 1.54E+01 1.54E+01 1.54E+01 O.OOE-01 RU106 4.96E+OO 4.96E+OO 4.96E+OO 4.96E+OO 4.96E+OO 4.96E+OO 4.96E+OO O.OOE-01 AG110M 6.39E+01 6.39E+01 6.39E+01 6.39E+01 6.39E+01 6.39E+01 6.39E+01 O.OOE-01 TE125M 4.81E-02 4.81 E-02 4.81E-02 4.81E-02 4.81E-02 4.81E-02 4.81E-02 O.OOE-01 TE127M 3.39E-03 3.39E-03 3.39E-03 3.39E-03 3.39E-03 3.39E-03 3.39E-03 O.OOE-01 TE127 3.63E-02 3.63E-02 3.63E-02 3.63E-02 3.63E-02 3.63E-02 3.63E-02 O.OOE-01 TE129M 2.74E+OO 2.74E+OO 2.74E+OO 2.74E+OO 2.74E+OO 2.74E+OO 2.74E+OO 0.00E-01 TE129 2.34E+OO 2.34E+OO 2.34E+OO 2.34E+OO 2.34E+OO 2.34E+OO 2.34E+OO O.OOE-01 TE131M 2.86E+01 2.86E+01 2.86E+01 2.86E+01 2.86E+01 2.86E+01 2.86E+01 O.OOE-01 TE131 8.18E+OO 8.18E+OO 8.18E+OO 8.18E+OO 8.18E+OO 8.18E+OO 8.18E+OO O.OOE-01 TE132 5.21 E+OO 5.21E+OO 5.21 E+OO 5.21E+OO 5.21 E+OO 5.21 E+OO 5.21 E+OO O.OOE-01 1130 5.06E+01 5.06E+01 5.06E+01 5.06E+01 5.06E+01 5.06E+01 5.06E+01 O.OOE-01 I 131 1.02E+01 1.02E+01 1.02E+01 1.02E+01 1.02E+01 1.02E+01 1.02E+01 O.OOE-01 1132 5.57E+01 5.57E+01 5.57E+01 5.57E+01 5.57E+01 5.57E+01 5.57E+01 O.OOE-01 1133 1.25E+01 1.25E+01 1.25E+01 1.25E+01 1.25E+01 1.25E+01 1.25E+01 O.OOE-01 I 134 5.06E+01 5.06E+01 5.06E+01 5.06E+01 5.06E+01 5.06E+01 5.06E+01 O.OOE-01 I 135 4.26E+01 4.26E+01 4.26E+01 4.26E+01 4.26E+01 4.26E+01 4.26E+01 O.OOE-01 CS134 3.78E+01 3.78E+01 3.78E+01 3.78E+01 3.78E+01 3.78E+01 3.78E+01 O.OOE-01 CS136 5.35E+01 5.35E+01 5.35E+01 5.35E+01 5.35E+01 5.35E+01 5.35E+01 O.OOE-01 CS137 1.31 E+01 1.31 E+01 1.31E+01 1.31E+01 1.31E+01 1.31 E+01 1.31 E+01 O.OOE-01 CS138 4.59E+01 4.59E+01 4.59E+01 4.59E+01 4.59E+01 4.59E+01 4.59E+01 O.OOE-01 BA139 9.55E-01 9.55E-01 9.55E-01 9.55E-01 9.55E-01 9.55E-01 9.55E-01 O.OOE-01 BA140 6.39E+OO 6.39E+OO 6.39E+OO 6.39E+OO 6.39E+OO 6.39E+OO 6.39E+OO O.OOE-01 BA141 1.14E+01 1.14E+01 1.14E+01 1.14E+01 1.14E+01 1.14E+01 1.14E+01 O.OOE-01 BA142 1.95E+01 1.95E+01 1.95E+01 1.95E+01 1.95E+01 1.95E+01 1.95E+01 O.OOE-01 LA140 5.34E+01 5.34E+01 5.34E+01 5.34E+01 5.34E+01 5.34E+01 5.34E+01 O.OOE-01 LA142 5.61E+01 5.61 E+01 5.61 E+01 5.61E+01 5.61E+01 5.61E+01 5.61E+01 O.OOE-01 CE141 1.?0E+OO 1.70E+OO 1.?0E+OO 1.70E+OO 1.70E+OO 1.?0E+OO 1.70E+OO O.OOE-01 CE143 7.42E+OO 7.42E+OO 7.42E+OO 7.42E+OO 7.42E+OO 7.42E+OO 7.42E+OO O.OOE-01 CE144 1.12E+OO 1.12E+OO 1.12E+OO 1.12E+OO 1.12E+OO 1.12E+OO 1.12E+OO O.OOE-01 PR143 2.09E-02 2.09E-02 2.09E-02 2.09E-02 2.09E-02 2.09E-02 2.09E-02 O.OOE-01 PR144 5.74E-01 5.74E-01 5.74E-01 5.74E-01 5.74E-01 5.74E-01 5.74E-01 O.OOE-01 ND147 3.65E+OO 3.65E+OO 3.65E+OO 3.65E+OO 3.65E+OO 3.65E+OO 3.65E+OO O.OOE-01 W187 1.08E+01 1.08E+01 1.08E+01 1.08E+01 1.08E+01 1.08E+01 1.08E+01 O.OOE-01 NP239 3.13E+OO 3.13E+OO 3.13E+OO 3.13E+OO 3.13E+OO 3.13E+OO 3.13E+OO O.OOE-01 DAEC ODAM Page 252 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =INFANT PATHWAY= POTABLE WATER TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN {mrem gaQ/{Ci min) H 3 2.91E+01 2.91 E+01 O.OOE-01 2.91E+01 2.91E+01 2.91E+01 2.91E+01 O.OOE-01 c 14 8.38E+02 8.38E+02 3.92E+03 8.38E+02 8.38E+02 8.38E+02 8.38E+02 O.OOE-01 NA24 5.53E+02 5.53E+02 5.53E+02 5.53E+02 5.53E+02 5.53E+02 5.53E+02 O.OOE-01 p 32 1.04E+04 3.63E+03 2.68E+05 1.58E+04 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CR 51 2.28E+OO 6.64E+01 O.OOE-01 0.00E-01 3.25E-01 1.49E+OO 2.89E+OO O.OOE-01 MN 54 7.45E+02 1.21E+03 O.OOE-01 3.29E+03 7.29E+02 O.OOE-01 O.OOE-01 O.OOE-01 MN 56 3.58E-02 1.89E+01 O.OOE-01 2.08E-01 1.79E-01 O.OOE-01 O.OOE-01 O.OOE-01 FE 55 3.97E+02 1.89E+02 2.30E+03 1.49E+03 O.OOE-01 O.OOE-01 7.26E+02 O.OOE-01 FE 59 3.46E+03 4.19E+03 5.02E+03 8.77E+03 O.OOE-01 O.OOE-01 2.59E+03 O.OOE-01 C058 1.47E+03 1.47E+03 O.OOE-01 5.90E+02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 co 60 4.22E+03 4.25E+03 O.OOE-01 1.79E+03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl63 3.64E+03 3.23E+02 1.05E+05 6.49E+03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl65 5.45E-02 9.11E+OO 1.06E+OO 1.20E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 cu 64 1.26E+01 5.57E+02 O.OOE-01 2.71E+01 4.59E+01 O.OOE-01 O.OOE-01 O.OOE-01 ZN 65 4.80E+03 8.80E+03 3.04E+03 1.04E+04 5.05E+03 O.OOE-01 O.OOE-01 O.OOE-01 ZN 69 5.00E-08 5.48E-05 3.73E-07 6.72E-07 2.79E-07 O.OOE-01 O.OOE-01 O.OOE-01 BR 83 5.73E-02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 84 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 85 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 86 1.34E+04 6.94E+02 O.OOE-01 2.71 E+04 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 88 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 89 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 89 1.18E+04 8.43E+03 4.10E+05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 90 9.50E+04 3.82E+04 4.69E+06 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 91 5.19E+01 1.70E+03 1.43E+03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 92 2.56E-01 7.43E+01 6.89E+OO O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 90 2.98E-01 1.53E+04 1.11E+01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Y 91M O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 91 4.93E+OO 1.33E+04 1.85E+02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 92 3.29E-04 2.24E+02 1.17E-02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 93 2.11E-02 6.10E+03 7.73E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 95 5.83E+OO 4.09E+03 3.37E+01 8.22E+OO 8.86E+OO O.OOE-01 O.OOE-01 O.OOE-01 ZR 97 7.17E-02 1.00E+04 9.15E-01 1.57E-01 1.58E-01 O.OOE-01 O.OOE-01 O.OOE-01 NB 95 1.62E+OO 2.37E+03 6.82E+OO 2.81E+OO 2.01E+OO O.OOE-01 O.OOE-01 O.OOE-01 MO 99 8.53E+02 1.44E+03 O.OOE-01 4.37E+03 6.54E+03 O.OOE-01 O.OOE-01 O.OOE-01 TC 99M 5.32E-01 1.20E+01 2.00E-02 4.13E-02 4.44E-01 O.OOE-01 2.16E-02 O.OOE-01 TC101 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 DAEC ODAM Page 253 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =INFANT PATHWAY= POTABLE WATER TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN (mrem gaQ/(Ci min} RU103 8.05E+01 2.93E+03 2.41 E+02 O.OOE-01 5.01E+02 O.OOE-01 O.OOE-01 O.OOE-01 RU105 1.78E-01 2.11E+02 5.30E-01 O.OOE-01 3.89E+OO O.OOE-01 O.OOE-01 O.OOE-01 RU106 4.97E+02 3.02E+04 3.98E+03 O.OOE-01 4.71 E+03 O.OOE-01 O.OOE-01 O.OOE-01 AG110M 7.94E+01 6.23E+03 1.64E+02 1.20E+02 1.72E+02 O.OOE-01 O.OOE-01 O.OOE-01 TE125M 5.15E+02 1.82E+03 3.81 E+03 1.27E+03 O.OOE-01 1.28E+03 O.OOE-01 O.OOE-01 TE127M 1.16E+03 3.88E+03 9.63E+03 3.19E+03 2.37E+04 2.78E+03 O.OOE-01 O.OOE-01 TE127 6.01 E+OO 5.86E+02 2.79E+01 9.36E+OO 6.82E+01 2.27E+01 O.OOE-01 O.OOE-01 TE129M 2.50E+03 9.68E+03 1.62E+04 5.56E+03 4.05E+04 6.23E+03 O.OOE-01 O.OOE-01 TE129 6.48E-06 2.22E-03 2.78E-05 9.57E-06 6.91E-05 2.33E-05 O.OOE-01 O.OOE-01 TE131M 4.80E+02 9.79E+03 1.44E+03 5.82E+02 4.00E+03 1.18E+03 O.OOE-01 O.OOE-01 TE131 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE132 1.29E+03 5.10E+03 2.78E+03 1.38E+03 8.62E+03 2.03E+03 O.OOE-01 O.OOE-01 1130 2.28E+02 1.22E+02 2.58E+02 5.68E+02 6.24E+02 6.37E+04 O.OOE-01 O.OOE-01 I 131 2.83E+03 2.29E+02 5.45E+03 6.43E+03 7.50E+03 2.11E+06 O.OOE-01 O.OOE-01 1132 1.44E-01 3.27E-01 1.99E-01 4.04E-01 4.50E-01 1.89E+01 O.OOE-01 O.OOE-01 1133 3.97E+02 2.29E+02 9.31 E+02 1.35E+03 1.59E+03 2.46E+05 O.OOE-01 O.OOE-01 1134 5.83E-07 1.69E-06 8.00E-07 1.64E-06 1.83E-06 3.82E-05 O.OOE-01 O.OOE-01 1135 3.51E+01 3.48E+01 4.84E+01 9.62E+01 1.07E+02 8.62E+03 O.OOE-01 O.OOE-01 CS134 1.17E+04 3.16E+02 6.24E+04 1.16E+05 2.99E+04 O.OOE-01 1.23E+04 O.OOE-01 CS136 7.92E+03 3.22E+02 7.21E+03 2.12E+04 8.45E+03 O.OOE-01 1.73E+03 O.OOE-01 CS137 7.17E+03 3.16E+02 8.64E+04 1.01E+05 2.72E+04 O.OOE-01 1.10E+04 O.OOE-01 CS138 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BA139 2.36E-05 5.16E-02 8.14E-04 5.40E-07 3.24E-07 O.OOE-01 3.27E-07 O.OOE-01 BA140 1.38E+03 6.59E+03 2.68E+04 2.68E+01 6.37E+OO O.OOE-01 1.65E+01 O.OOE-01 BA141 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BA142 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 LA140 2.35E-01 1.07E+04 2.31 E+OO 9.12E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 LA142 3.27E-07 2.32E-01 3.72E-06 1.37E-06 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CE141 9.16E-01 4.02E+03 1.28E+01 7.78E+OO 2.40E+OO O.OOE-01 O.OOE-01 O.OOE-01 CE143 1.12E-01 5.74E+03 1.48E+OO 9.84E+02 2.87E-01 O.OOE-01 O.OOE-01 O.OOE-01 CE144 2.76E+01 2.82E+04 4.92E+02 2.01 E+02 8.14E+01 O.OOE-01 O.OOE-01 O.OOE-01 PR143 6.34E-01 6.75E+03 1.28E+01 4.78E+OO 1.78E+OO O.OOE-01 O.OOE-01 O.OOE-01 PR144 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ND147 5.41 E-01 5.60E+03 8.60E+OO 8.84E+OO 3.41E+OO O.OOE-01 O.OOE-01 O.OOE-01 W187 1.79E+01 3.05E+03 7.46E+01 5.19E+01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 NP239 6.93E-02 3.54E+03 1.37E+OO 1.23E-01 2.44E-01 O.OOE-01 O.OOE-01 O.OOE-01 DAEC ODAM Page 254 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =INFANT PATHWAY= FRESH WATER FISH TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN (mrem gaQ/(Ci min} H 3 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 c 14 O.OOE-01 O.OOE-01 O.O.OE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 NA24 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 p 32 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CR 51 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 MN 54 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 MN 56 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 FE 55 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 FE 59 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 C058 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 C060 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl63 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl65 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 cu 64 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZN 65 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZN 69 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 BR 83 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 84 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 85 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 86 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 88 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 89 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 89 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 90 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 91 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 92 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 90 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Y 91M O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 91 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 92 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 93 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 95 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 97 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 NB 95 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 MO 99 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TC 99M O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TC101 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 DAEC ODAM Page 255 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =INFANT PATHWAY= FRESH WATER FISH TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN mrem al I Ci min RU103 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RU105 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RU106 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 AG110M O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE125M O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE127M O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE127 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE129M O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE129 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE131M O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE131 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE132 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 1130 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 I 131 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 1132 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 1133 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 1134 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 1135 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CS134 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CS136 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CS137 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CS138 0.00E-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BA139 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BA140 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BA141 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BA142 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 LA140 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 LA142 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CE141 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 CE143 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CE144 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 PR143 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 PR144 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ND147 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 W187 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 NP239 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 DAEC ODAM Page 256 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =INFANT PATHWAY= FRESH WATER INVERTEBRATES TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN (mrem gaQ!(Ci min} H 3 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 c 14 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 NA24 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 p 32 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CR 51 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 MN 54 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 MN 56 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 FE 55 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 FE 59 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 co 58 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 C060 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl63 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 N165 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 cu 64 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZN 65 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZN 69 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 83 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 84 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 85 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 86 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 88 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 89 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 89 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 90 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 91 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 92 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 90 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Y 91M O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 91 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 92 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 93 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 95 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 97 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 NB 95 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 M099 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TC 99M O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TC101 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 DAEC ODAM Page 257 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =INFANT PATHWAY= FRESH WATER INVERTEBRATES TOTAL BODY GI-LU BONE LIVER KIDNEY THYROID LUNG SKIN {mrem gal}/{Ci min} RU103 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RU105 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RU106 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 AG110M O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE125M O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE127M O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE127 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE129M O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE129 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE131M O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE131 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE132 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 1130 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 I 131 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 1132 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 1133 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 1134 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 1135 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CS134 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CS136 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CS137 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CS138 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BA139 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BA140 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BA141 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BA142 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 LA140 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 LA142 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CE141 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CE143 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CE144 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 PR143 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 PR144 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ND147 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 W187 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 NP239 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 DAEC ODAM Page 258 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =INFANT PATHWAY= IRRIGATED FRESH LEAFY VEGETABLES TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN (mrem gaQ/(Ci min} H 3 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 c 14 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 NA24 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 p 32 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CR 51 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 MN 54 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 MN 56 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 FE 55 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 FE 59 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 co 58 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 C060 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl63 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl65 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 cu 64 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZN 65 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZN 69 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 83 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 84 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 85 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 86 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 88 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 89 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 89 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 90 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 91 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 92 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 90 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Y 91M O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 91 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 92 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 93 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 95 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 97 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 NB 95 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 MO 99 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TC 99M O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TC101 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 DAEC ODAM Page 259 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =INFANT PATHWAY= IRRIGATED FRESH LEAFY VEGETABLES TOTAL BODY GI-LU BONE LIVER KIDNEY THYROID LUNG SKIN (mrem gal)/(Ci min) RU103 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RU105 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RU106 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 AG110M O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE125M O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE127M 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 0.00E-01 O.OOE-01 TE127 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE129M O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE129 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE131M O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE131 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE132 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 1130 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 I 131 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 1132 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 1133 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 1134 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 1135 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CS134 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 CS136 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CS137 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CS138 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BA139 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BA140 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BA141 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BA142 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 LA140 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 LA142 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CE141 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CE143 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CE144 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 PR143 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 PR144 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ND147 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 W187 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 NP239 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 DAEC ODAM Page 260 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =INFANT PATHWAY= IRRIGATED STORED FRUIT, VEGETABLES, GRAIN TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN (mrem gaQ/(Ci min} H 3 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 c 14 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 NA24 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 p 32 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CR 51 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 MN 54 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 MN 56 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 FE 55 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 FE 59 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 co 58 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 C060 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl63 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl65 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 cu 64 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZN 65 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZN 69 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 83 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 84 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 85 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 86 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 88 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 89 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 89 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 90 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 91 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 92 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 90 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Y 91M O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 91 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 92 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 93 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 95 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 97 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 NB 95 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 MO 99 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TC 99M O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TC101 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 DAEC ODAM Page 261 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =INFANT PATHWAY= IRRIGATED STORED FRUIT, VEGETABLES, GRAIN TOTAL BODY GI-LU BONE LIVER KIDNEY THYROID LUNG SKIN (mrem gaQ/(Ci min) RU103 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RU105 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RU106 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 AG110M O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE125M O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE127M O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE127 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE129M O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE129 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE131M O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE131 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE132 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 1130 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 I 131 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 1132 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 1133 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 1134 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 1135 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CS134 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CS136 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CS137 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CS138 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 BA139 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BA140 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BA141 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 BA142 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 LA140 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 LA142 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 CE141 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CE143 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CE144 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 PR143 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 PR144 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ND147 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 w 187 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 NP239 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 DAEC ODAM Page 262 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =INFANT PATHWAY= IRRIGATED FRESH FORAGE--MILK TOTAL BODY GI-LU BONE LIVER KIDNEY THYROID LUNG SKIN {mrem gaQ/{Ci min} H 3 1.32E+01 1.32E+01 O.OOE-01 1.32E+01 1.32E+01 1.32E+01 1.32E+01 O.OOE-01 c 14 6.12E+04 6.12E+04 2.87E+05 6.12E+04 6.12E+04 6.12E+04 6.12E+04 O.OOE-01 NA24 3.60E+02 3.60E+02 3.60E+02 3.60E+02 3.60E+02 3.60E+02 3.60E+02 O.OOE-01 p 32 1.43E+05 5.00E+04 3.69E+06 2.17E+05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CR 51 3.48E+OO 1.01E+02 O.OOE-01 O.OOE-01 4.96E-01 2.27E+OO 4.42E+OO O.OOE-01 MN 54 1.69E+02 2.74E+02 O.OOE-01 7.46E+02 1.65E+02 O.OOE-01 O.OOE-01 O.OOE-01 MN 56 9.56E-08 5.04E-05 O.OOE-01 5.54E-07 4.76E-07 O.OOE-01 O.OOE-01 O.OOE-01 FE 55 4.39E+02 2.09E+02 2.54E+03 1.64E+03 O.OOE-01 O.OOE-01 8.04E+02 O.OOE-01 FE 59 3.20E+03 3.88E+03 4.65E+03 8.13E+03 O.OOE-01 O.OOE-01 2.40E+03 O.OOE-01 co 58 1.22E+03 1.22E+03 O.OOE-01 4.88E+02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 C060 3.92E+03 3.96E+03 O.OOE-01 1.66E+03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl63 2.31 E+04 2.05E+03 6.66E+05 4.12E+04 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl65 3.37E-06 5.64E-04 6.55E-05 7.41E-06 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 cu 64 1.96E+OO 8.67E+01 O.OOE-01 4.22E+OO 7.14E+OO O.OOE-01 O.OOE-01 O.OOE-01 ZN 65 1.73E+05 3.16E+05 1.09E+05 3.75E+05 1.82E+05 O.OOE-01 O.OOE-01 O.OOE-01 ZN 69 7.68E-17 8.41E-14 5.73E-16 1.03E-15 4.29E-16 O.OOE-01 O.OOE-01 O.OOE-01 BR 83 1.74E-05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 84 1.42E-26 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 85 1.20E-34 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 86 2.46E+05 1.28E+04 O.OOE-01 4.99E+05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 88 1.23E-27 2.19E-27 O.OOE-01 2.24E-27 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 89 5.11 E-28 2.53E-28 O.OOE-01 7.42E-28 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 89 7.54E+03 5.40E+03 2.63E+05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 90 1.30E+05 5.25E+04 6.43E+06 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 91 2.21 E-01 7.23E+OO 6.11E+OO O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 92 3.32E-06 9.63E-04 8.93E-05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 90 4.38E-04 2.26E+01 1.63E-02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Y 91M 1.90E-25 1.86E-20 5.59E-24 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 91 3.97E-02 1.07E+02 1.49E+OO O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 92 3.15E-10 2.14E-04 1.12E-08 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 93 1.32E-06 3.83E-01 4.85E-05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 95 2.38E-02 1.67E+01 1.38E-01 3.36E-02 3.62E-02 O.OOE-01 O.OOE-01 O.OOE-01 ZR 97 7.40E-06 1.03E+OO 9.44E-05 1.62E-05 1.63E-05 O.OOE-01 O.OOE-01 O.OOE-01 NB 95 2.99E+OO 4.37E+03 1.26E+01 5.18E+OO 3.71E+OO O.OOE-01 O.OOE-01 O.OOE-01 M099 9.71E+02 1.64E+03 O.OOE-01 4.98E+03 7.44E+03 O.OOE-01 O.OOE-01 O.OOE-01 TC 99M 1.58E-02 3.56E-01 5.95E-04 1.23E-03 1.32E-02 O.OOE-01 6.41E-04 O.OOE-01 TC101 4.63E-29 7.96E-28 3.72E-30 4.68E-30 5.57E-29 O.OOE-01 2.55E-30 O.OOE-01 DAEC ODAM Page 263 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =INFANT PATHWAY= IRRIGATED FRESH FORAGE--MILK TOTAL BODY GI-LU BONE LIVER KIDNEY THYROID LUNG SKIN (mrem gal)/(Ci min) RU103 6.08E-02 2.21 E+OO 1.82E-01 O.OOE-01 3.78E-01 O.OOE-01 O.OOE-01 O.OOE-01 RU105 5.62E-08 6.64E-05 1.67E-07 O.OOE-01 1.23E-06 O.OOE-01 O.OOE-01 O.OOE-01 RU106 4.54E-01 2.76E+01 3.64E+OO O.OOE-01 4.30E+OO O.OOE-01 O.OOE-01 O.OOE-01 AG110M 3.61 E+03 2.83E+05 7.47E+03 5.45E+03 7.80E+03 O.OOE-01 O.OOE-01 O.OOE-01 TE125M 4.25E+02 1.50E+03 3.14E+03 1.05E+03 O.OOE-01 1.06E+03 O.OOE-01 O.OOE-01 TE127M 1.04E+03 3.48E+03 8.62E+03 2.86E+03 2.12E+04 2.49E+03 O.OOE-01 O.OOE-01 TE127 3.07E-02 3.00E+OO 1.43E-01 4.79E-02 3.49E-01 1.16E-01 O.OOE-01 O.OOE-01 TE129M 1.85E+03 7.16E+03 1.20E+04 4.12E+03 3.00E+04 4.61 E+03 O.OOE-01 O.OOE-01 TE129 8.74E-15 2.99E-12 3.74E-14 1.29E-14 9.32E-14 3.14E-14 O.OOE-01 O.OOE-01 TE131M 2.67E+01 5.44E+02 8.02E+01 3.23E+01 2.22E+02 6.54E+01 O.OOE-01 O.OOE-01 TE131 2.04E-29 2.94E-27 7.27E-29 2.69E-29 1.86E-28 6.49E-29 O.OOE-01 O.OOE-01 TE132 2.35E+02 9.32E+02 5.09E+02 2.52E+02 1.58E+03 3.72E+02 O.OOE-01 O.OOE-01 1130 1.43E+01 7.64E+OO 1.62E+01 3.57E+01 3.92E+01 4.00E+03 O.OOE-01 O.OOE-01 I 131 6.68E+03 5.42E+02 1.29E+04 1.52E+04 1.77E+04 4.99E+06 O.OOE-01 O.OOE-01 1132 3.77E-06 8.58E-06 5.22E-06 1.06E-05 1.18E-05 4.97E-04 O.OOE-01 O.OOE-01 1133 7.27E+01 4.20E+01 1.70E+02 2.48E+02 2.92E+02 4.51E+04 O.OOE-01 O.OOE-01 1134 2.75E-17 7.99E-17 3.77E-17 7.73E-17 8.64E-17 1.80E-15 O.OOE-01 O.OOE-01 1135 3.52E-01 3.49E-01 4.85E-01 9.65E-01 1.08E+OO 8.65E+01 O.OOE-01 O.OOE-01 CS134 1.30E+05 3.49E+03 6.90E+05 1.29E+06 3.31E+05 O.OOE-01 1.36E+05 O.OOE-01 CS136 4.98E+04 2.03E+03 4.54E+04 1.33E+05 5.32E+04 O.OOE-01 1.09E+04 O.OOE-01 CS137 8.06E+04 3.56E+03 9.72E+05 1.14E+06 3.05E+05 O.OOE-01 1.24E+05 O.OOE-01 CS138 3.49E-27 1.15E-26 4.43E-27 7.21 E-27 3.59E-27 O.OOE-01 5.61E-28 O.OOE-01 BA139 1.56E-13 3.41 E-10 5.38E-12 3.57E-15 2.14E-15 O.OOE-01 2.16E-15 O.OOE-01 BA140 2.87E+02 1.37E+03 5.56E+03 5.56E+OO 1.32E+OO O.OOE-01 3.42E+OO O.OOE-01 BA141 8.70E-31 3.37E-28 2.76E-29 1.89E-32 1.14E-32 O.OOE-01 1.15E-32 O.OOE-01 BA142 6.86E-32 5.75E-30 1.39E-30 1.16E-33 6.67E-34 O.OOE-01 7.01E-34 O.OOE-01 LA140 9.81E-05 4.48E+OO 9.68E-04 3.81E-04 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 LA142 1.17E-16 8.27E-11 1.33E-15 4.87E-16 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CE141 6.63E-02 2.91E+02 9.23E-01 5.63E-01 1.74E-01 O.OOE-01 O.OOE-01 O.OOE-01 CE143 7.18E-04 3.67E+01 9.49E-03 6.30E+OO 1.83E-03 O.OOE-01 0.00E-01 O.OOE-01 CE144 2.49E+OO 2.55E+03 4.44E+01 1.82E+01 7.35E+OO O.OOE-01 O.OOE-01 O.OOE-01 PR143 1.69E-03 1.80E+01 3.42E-02 1.28E-02 4.75E-03 O.OOE-01 O.OOE-01 O.OOE-01 PR144 9.26E-36 3.31E-30 1.84E-34 7.11 E-35 2.58E-35 O.OOE-01 O.OOE-01 O.OOE-01 ND147 1.30E-03 1.35E+01 2.07E-02 2.12E-02 8.19E-03 O.OOE-01 O.OOE-01 O.OOE-01 w 187 3.47E-01 5.90E+01 1.44E+OO 1.00E+OO O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 NP239 4.42E-05 2.26E+OO 8.75E-04 7.83E-05 1.56E-04 O.OOE-01 O.OOE-01 O.OOE-01 DAEC ODAM Page 264 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =INFANT PATHWAY= IRRIGATED FRESH FORAGE--MEAT TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN (mrem gal)/(Ci min) H 3 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 c 14 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 NA24 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 p 32 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CR 51 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 MN 54 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 MN 56 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 FE 55 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 FE 59 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 co 58 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 C060 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl63 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl65 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 cu 64 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZN 65 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZN 69 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 83 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 84 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 85 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 86 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 88 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 89 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 89 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 90 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 91 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 92 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 90 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Y 91M O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 91 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 92 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 93 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 95 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 97 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 NB 95 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 M099 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TC 99M O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TC101 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 DAEC ODAM Page 265 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =INFANT PATHWAY= IRRIGATED FRESH FORAGE--MEAT TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN (mrem gal)/(Ci min} RU103 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RU105 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RU106 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 AG110M O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE125M O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE127M O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE127 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE129M O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE129 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE131M O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE131 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE132 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 I 130 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 I 131 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 1132 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 1133 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 I 134 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 1135 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CS134 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CS136 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CS137 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CS138 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 BA139 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BA140 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BA141 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 BA142 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 LA140 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 LA142 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CE141 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CE143 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CE144 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 PR143 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 PR144 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ND147 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 w 187 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 NP239 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 DAEC ODAM Page 266 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =INFANT PATHWAY= IRRIGATED STORED FEED--MILK TOTAL BODY GI-LU BONE LIVER KIDNEY THYROID LUNG SKIN {mrem gaQ/{Ci min) H 3 1.32E+01 1.32E+01 O.OOE-01 1.32E+01 1.32E+01 1.32E+01 1.32E+01 O.OOE-01 c 14 6.33E+04 6.33E+04 2.96E+05 6.33E+04 6.33E+04 6.33E+04 6.33E+04 O.OOE-01 NA24 3.60E+02 3.60E+02 3.60E+02 3.60E+02 3.60E+02 3.60E+02 3.60E+02 O.OOE-01 p 32 1.51E+05 5.26E+04 3.89E+06 2.29E+05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CR 51 3.85E+OO 1.12E+02 O.OOE-01 O.OOE-01 5.49E-01 2.51 E+OO 4.89E+OO O.OOE-01 MN 54 2.05E+02 3.32E+02 O.OOE-01 9.03E+02 2.00E+02 O.OOE-01 O.OOE-01 O.OOE-01 MN 56 9.56E-08 5.04E-05 O.OOE-01 5.54E-07 4.76E-07 O.OOE-01 O.OOE-01 O.OOE-01 FE 55 5.37E+02 2.55E+02 3.11E+03 2.01 E+03 O.OOE-01 O.OOE-01 9.82E+02 O.OOE-01 FE 59 3.66E+03 4.44E+03 5.32E+03 9.28E+03 O.OOE-01 O.OOE-01 2.74E+03 O.OOE-01 co 58 1.42E+03 1.42E+03 O.OOE-01 5.70E+02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 C060 4.80E+03 4.84E+03 O.OOE-01 2.03E+03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl63 2.82E+04 2.50E+03 8.14E+05 5.03E+04 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl65 3.37E-06 5.64E-04 6.55E-05 7.41E-06 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 cu 64 1.96E+OO 8.67E+01 O.OOE-01 4.22E+OO 7.14E+OO O.OOE-01 O.OOE-01 O.OOE-01 ZN 65 2.08E+05 3.81E+05 1.31E+05 4.51 E+05 2.18E+05 O.OOE-01 O.OOE-01 O.OOE-01 ZN 69 7.68E-17 8.41E-14 5.73E-16 1.03E-15 4.29E-16 O.OOE-01 O.OOE-01 O.OOE-01 BR 83 1.74E-05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 84 1.42E-26 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 85 1.20E-34 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 86 2.65E+05 1.37E+04 O.OOE-01 5.36E+05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 88 1.23E-27 2.19E-27 O.OOE-01 2.24E-27 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 89 5.11 E-28 2.53E-28 O.OOE-01 7.42E-28 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 89 8.65E+03 6.20E+03 3.01 E+05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 90 1.46E+05 5.89E+04 7.22E+06 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 91 2.21E-01 7.23E+OO 6.11E+OO O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 92 3.32E-06 9.63E-04 8.93E-05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 90 4.38E-04 2.26E+01 1.63E-02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Y 91M 1.90E-25 1.86E-20 5.59E-24 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 91 4.60E-02 1.24E+02 1.73E+OO O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 92 3.15E-10 2.14E-04 1.12E-08 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 93 1.32E-06 3.83E-01 4.85E-05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 95 2.77E-02 1.95E+01 1.60E-01 3.91E-02 4.21E-02 O.OOE-01 O.OOE-01 O.OOE-01 ZR 97 7.40E-06 1.03E+OO 9.44E-05 1.62E-05 1.63E-05 O.OOE-01 O.OOE-01 O.OOE-01 NB 95 3.37E+OO 4.92E+03 1.41E+01 5.82E+OO 4.18E+OO O.OOE-01 O.OOE-01 O.OOE-01 M099 9.71E+02 1.64E+03 O.OOE-01 4.98E+03 7.44E+03 O.OOE-01 O.OOE-01 O.OOE-01 TC 99M 1.58E-02 3.56E-01 5.95E-04 1.23E-03 1.32E-02 O.OOE-01 6.41E-04 O.OOE-01 TC101 4.63E-29 7.96E-28 3.72E-30 4.68E-30 5.57E-29 O.OOE-01 2.55E-30 O.OOE-01 DAEC ODAM Page 267 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =INFANT PATHWAY= IRRIGATED STORED FEED--MILK TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN (mrem gaQ/(Ci min} RU103 6.89E-02 2.51 E+OO 2.06E-01 O.OOE-01 4.29E-01 O.OOE-01 O.OOE-01 O.OOE-01 RU105 5.62E-08 6.64E-05 1.67E-07 O.OOE-01 1.23E-06 O.OOE-01 O.OOE-01 O.OOE-01 RU106 5.51 E-01 3.35E+01 4.41E+OO O.OOE-01 5.22E+OO O.OOE-01 O.OOE-01 O.OOE-01 AG110M 4.35E+03 3.41E+05 9.01 E+03 6.58E+03 9.41E+03 O.OOE-01 O.OOE-01 O.OOE-01 TE125M 4.90E+02 1.73E+03 3.63E+03 1.21E+03 O.OOE-01 1.22E+03 O.OOE-01 O.OOE-01 TE127M 1.23E+03 4.10E+03 1.02E+04 3.37E+03 2.50E+04 2.94E+03 O.OOE-01 O.OOE-01 TE127 3.07E-02 3.00E+OO 1.43E-01 4.79E-02 3.49E-01 1.16E-01 O.OOE-01 O.OOE-01 TE129M 2.07E+03 8.02E+03 1.34E+04 4.61 E+03 3.36E+04 5.16E+03 O.OOE-01 O.OOE-01 TE129 8.74E-15 2.99E-12 3.74E-14 1.29E-14 9.32E-14 3.14E-14 O.OOE-01 O.OOE-01 TE131 M 2.67E+01 5.44E+02 8.02E+01 3.23E+01 2.22E+02 6.54E+01 O.OOE-01 O.OOE-01 TE131 2.04E-29 2.94E-27 7.27E-29 2.69E-29 1.86E-28 6.49E-29 O.OOE-01 O.OOE-01 TE132 2.35E+02 9.33E+02 5.09E+02 2.52E+02 1.58E+03 3.72E+02 O.OOE-01 O.OOE-01 1130 1.43E+01 7.64E+OO 1.62E+01 3.57E+01 3.92E+01 4.00E+03 O.OOE-01 O.OOE-01 I 131 6.79E+03 5.52E+02 1.31 E+04 1.54E+04 1.80E+04 5.08E+06 O.OOE-01 O.OOE-01 I 132 3.77E-06 8.58E-06 5.22E-06 1.06E-05 1.18E-05 4.97E-04 O.OOE-01 O.OOE-01 I 133 7.27E+01 4.20E+01 1.70E+02 2.48E+02 2.92E+02 4.51E+04 O.OOE-01 O.OOE-01 1134 2.75E-17 7.99E-17 3.77E-17 7.73E-17 8.64E-17 1.80E-15 0.00E-01 O.OOE-01 1135 3.52E-01 3.49E-01 4.85E-01 9.65E-01 1.08E+OO 8.65E+01 O.OOE-01 O.OOE-01 CS134 1.58E+05 4.26E+03 8.41E+05 1.57E+06 4.04E+05 O.OOE-01 1.66E+05 O.OOE-01 CS136 5.22E+04 2.12E+03 4.75E+04 1.40E+05 5.57E+04 O.OOE-01 1.14E+04 O.OOE-01 CS137 9.87E+04 4.35E+03 1.19E+06 1.39E+06 3.74E+05 O.OOE-01 1.51E+05 O.OOE-01 CS138 3.49E-27 1.15E-26 4.43E-27 7.21 E-27 3.59E-27 O.OOE-01 5.61E-28 O.OOE-01 BA139 1.56E-13 3.41E-10 5.38E-12 3.57E-15 2.14E-15 O.OOE-01 2.16E..:15 O.OOE-01 BA140 2.99E+02 1.43E+03 5.81 E+03 5.81E+OO 1.38E+OO O.OOE-01 3.57E+OO O.OOE-01 BA141 8.70E-31 3.37E-28 2.76E-29 1.89E-32 1.14E-32 O.OOE-01 1.15E-32 O.OOE-01 BA142 6.86E-32 5.75E-30 1.39E-30 1.16E-33 6.67E-34 O.OOE-01 7.01E-34 O.OOE-01 LA140 9.81E-05 4.48E+OO 9.68E-04 3.81E-04 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 LA142 1.17E-16 8.27E-11 1.33E-15 4.87E-16 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CE141 7.42E-02 3.26E+02 1.03E+OO 6.30E-01 1.94E-01 O.OOE-01 O.OOE-01 O.OOE-01 CE143 7.18E-04 3.67E+01 9.49E-03 6.30E+OO 1.83E-03 O.OOE-01 O.OOE-01 O.OOE-01 CE144 3.01E+OO 3.09E+03 5.38E+01 2.20E+01 8.90E+OO O.OOE-01 O.OOE-01 O.OOE-01 PR143 1.78E-03 1.89E+01 3.58E-02 1.34E-02 4.98E-03 O.OOE-01 O.OOE-01 O.OOE-01 PR144 9.26E-36 3.31E-30 1.84E-34 7.11 E-35 2.58E-35 O.OOE-01 O.OOE-01 O.OOE-01 ND147 1.35E-03 1.39E+01 2.14E-02 2.20E-02 8.48E-03 O.OOE-01 O.OOE-01 O.OOE-01 W187 3.47E-01 5.90E+01 1.44E+OO 1.00E+OO O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 NP239 4.42E-05 2.26E+OO 8.75E-04 7.83E-05 1.56E-04 O.OOE-01 O.OOE-01 O.OOE-01 DAEC ODAM Page 268 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =INFANT PATHWAY= IRRIGATED STORED FEED--MEAT TOTAL BODY GI-LU BONE LIVER KIDNEY THYROID LUNG SKIN (mrem gaQ/(Ci min} H 3 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 c 14 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 NA24 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 p 32 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CR 51 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 MN 54 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 MN 56 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 FE 55 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 FE 59 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 co 58 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 C060 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl63 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl65 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 cu 64 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZN 65 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZN 69 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 83 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 84 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 85 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 86 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 88 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 89 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 89 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 90 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 91 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 92 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 90 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Y 91M O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 91 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 92 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 93 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 95 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 97 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 NB 95 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 MO 99 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TC 99M O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TC101 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 DAEC ODAM Page 269 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =INFANT PATHWAY= IRRIGATED STORED FEED--MEAT TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN (mrem gal)/(Ci min) RU103 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RU105 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RU106 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 AG110M O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE125M O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE127M O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE127 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE129M O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE129 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE131M O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE131 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE132 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 1130 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 I 131 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 1132 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 1133 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 1134 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 1135 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CS134 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CS136 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CS137 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CS138 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BA139 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BA140 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BA141 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BA142 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 LA140 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 LA142 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CE141 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CE143 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CE144 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 PR143 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 PR144 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ND147 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 W187 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 NP239 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 DAEC ODAM Page 270 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =INFANT PATHWAY= ANIMAL DRINKING WATER--MILK TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN (mrem gaQ!(Ci min} H 3 1.59E+01 1.59E+01 O.OOE-01 1.59E+01 1.59E+01 1.59E+01 1.59E+01 O.OOE-01 c 14 6.03E+02 6.03E+02 2.83E+03 6.03E+02 6.03E+02 6.03E+02 6.03E+02 O.OOE-01 NA24 4.20E+02 4.20E+02 4.20E+02 4.20E+02 4.20E+02 4.20E+02 4.20E+02 O.OOE-01 p 32 1.48E+04 5.17E+03 3.82E+05 2.25E+04 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CR 51 2.93E-01 8.54E+OO O.OOE-01 O.OOE-01 4.17E-02 1.91 E-01 3.72E-01 O.OOE-01 MN 54 1.11E+01 1.81E+01 O.OOE-01 4.92E+01 1.09E+01 O.OOE-01 O.OOE-01 O.OOE-01 MN 56 6.29E-07 3.31E-04 O.OOE-01 3.65E-06 3.14E-06 O.OOE-01 O.OOE-01 O.OOE-01 FE 55 2.86E+01 1.36E+01 1.65E+02 1.07E+02 O.OOE-01 O.OOE-01 5.23E+01 O.OOE-01 FE 59 2.45E+02 2.97E+02 3.56E+02 6.21E+02 O.OOE-01 O.OOE-01 1.84E+02 O.OOE-01 co 58 8.75E+01 8.74E+01 O.OOE-01 3.51E+01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 C060 2.53E+02 2.55E+02 O.OOE-01 1.07E+02 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl63 1.46E+03 1.30E+02 4.22E+04 2.61 E+03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl65 2.26E-05 3.78E-03 4.39E-04 4.97E-05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 cu 64 2.69E+OO 1.19E+02 O.OOE-01 5.80E+OO 9.81 E+OO O.OOE-01 O.OOE-01 O.OOE-01 ZN 65 1.12E+04 2.05E+04 7.09E+03 2.43E+04 1.18E+04 O.OOE-01 O.OOE-01 O.OOE-01 ZN 69 1.36E-15 1.49E-12 1.02E-14 1.83E-14 7.59E-15 O.OOE-01 O.OOE-01 O.OOE-01 BR 83 1.23E-04 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 84 4.50E-25 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 85 4.22E-32 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 86 2.32E+04 1.20E+03 O.OOE-01 4.70E+04 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 88 6.94E-26 1.23E-25 O.OOE-01 1.27E-25 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 89 3.37E-26 1.67E-26 O.OOE-01 4.89E-26 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 89 5.56E+02 3.99E+02 1.94E+04 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 90 4.56E+03 1.84E+03 2.25E+05 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 91 4.01 E-01 1.31E+01 1.11E+01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 SR 92 2.06E-05 5.98E-03 5.55E-04 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 90 1.36E-04 7.02E+OO 5.09E-03 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Y 91M 3.87E-24 3.79E-19 1.14E-22 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 91 2.92E-03 7.86E+OO 1.1 OE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 92 1.50E-09 1.02E-03 5.35E-08 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 93 2.26E-06 6.56E-01 8.31E-05 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 95 1.73E-03 1.22E+OO 1.00E-02 2.44E-03 2.63E-03 O.OOE-01 O.OOE-01 O.OOE-01 ZR 97 7.71 E-06 1.08E+OO 9.84E-05 1.69E-05 1.70E-05 O.OOE-01 O.OOE-01 O.OOE-01 NB 95 2.39E-01 3.48E+02 1.00E+OO 4.13E-01 2.96E-01 O.OOE-01 O.OOE-01 O.OOE-01 MO 99 2.95E+02 4.99E+02 0.00E-01 1.51E+03 2.26E+03 O.OOE-01 O.OOE-01 O.OOE-01 TC 99M 4.48E-02 1.01E+OO 1.69E-03 3.48E-03 3.74E-02 O.OOE-01 1.82E-03 O.OOE-01 TC101 3.29E-27 5.64E-26 2.64E-28 3.32E-28 3.95E-27 O.OOE-01 1.81 E-28 O.OOE-01 DAEC ODAM Page 271 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =INFANT PATHWAY= ANIMAL DRINKING WATER--MILK TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN (mrem gal)/(Ci min) RU103 4.74E-03 1.72E-01 1.42E-02 O.OOE-01 2.95E-02 O.OOE-01 0.00E-01 O.OOE-01 RU105 2.15E-07 2.54E-04 6.40E-07 O.OOE-01 4.70E-06 O.OOE-01 O.OOE-01 O.OOE-01 RU106 2.98E-02 1.81E+OO 2.38E-01 O.OOE-01 2.82E-01 O.OOE-01 O.OOE-01 O.OOE-01 AG110M 2.38E+02 1.86E+04 4.92E+02 3.59E+02 5.14E+02 O.OOE-01 O.OOE-01 O.OOE-01 TE125M 3.05E+01 1.08E+02 2.26E+02 7.55E+01 O.OOE-01 7.60E+01 0.00E-01 O.OOE-01 TE127M 6.94E+01 2.31 E+02 5.74E+02 1.90E+02 1.41E+03 1.66E+02 0.00E-01 O.OOE-01 TE127 5.64E-02 5.51 E+OO 2.62E-01 8.79E-02 6.40E-01 2.14E-01 O.OOE-01 O.OOE-01 TE129M 1.47E+02 5.69E+02 9.52E+02 3.27E+02 2.38E+03 3.66E+02 O.OOE-01 O.OOE-01 TE129 1.26E-13 4.33E-11 5.41 E-13 1.86E-13 1.35E-12 4.54E-13 O.OOE-01 O.OOE-01 TE131M 1.62E+01 3.30E+02 4.87E+01 1.96E+01 1.35E+02 3.97E+01 O.OOE-01 O.OOE-01 TE131 8.17E-28 1.18E-25 2.91E-27 1.0BE-27 7.45E-27 2.60E-27 O.OOE-01 O.OOE-01 TE132 6.19E+01 2.45E+02 1.34E+02 6.63E+01 4.15E+02 9.78E+01 O.OOE-01 O.OOE-01 1130 2.02E+01 1.08E+01 2.28E+01 5.02E+01 5.52E+01 5.63E+03 O.OOE-01 O.OOE-01 1131 9.30E+02 7.55E+01 1.79E+03 2.11E+03 2.47E+03 6.95E+05 O.OOE-01 O.OOE-01 1132 2.77E-05 6.30E-05 3.83E-05 7.78E-05 8.68E-05 3.65E-03 O.OOE-01 O.OOE-01 1133 6.22E+01 3.59E+01 1.46E+02 2.12E+02 2.49E+02 3.86E+04 O.OOE-01 O.OOE-01 I 134 5.28E-16 1.53E-15 7.25E-16 1.48E-15 1.66E-15 3.46E-14 O.OOE-01 O.OOE-01 I 135 9.12E-01 9.05E-01 1.26E+OO 2.50E+OO 2.79E+OO 2.24E+02 O.OOE-01 O.OOE-01 CS134 8.45E+03 2.27E+02 4.49E+04 8.37E+04 2.15E+04 O.OOE-01 8.83E+03 O.OOE-01 CS136 5.39E+03 2.19E+02 4.91 E+03 1.44E+04 5.76E+03 O.OOE-01 1.18E+03 O.OOE-01 CS137 5.16E+03 2.28E+02 6.22E+04 7.28E+04 1.95E+04 O.OOE-01 7.92E+03 O.OOE-01 CS138 1.09E-25 3.60E-25 1.38E-25 2.25E-25 1.12E-25 O.OOE-01 1.75E-26 O.OOE-01 BA139 1.91 E-12 4.17E-09 6.59E-11 4.37E-14 2.63E-14 O.OOE-01 2.65E-14 O.OOE-01 BA140 3.14E+01 1.49E+02 6.08E+02 6.0SE-01 1.45E-01 O.OOE-01 3.74E-01 O.OOE-01 BA141 4.79E-29 1.86E-26 1.52E-27 1.04E-30 6.26E-31 O.OOE-01 6.33E-31 O.OOE-01 BA142 6.46E-30 5.41E-28 1.31 E-28 1.09E-31 6.28E-32 O.OOE-01 6.60E-32 O.OOE-01 LA140 4.57E-05 2.09E+OO 4.51 E-04 1.78E-04 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 LA142 1.28E-15 9.04E-10 1.45E-14 5.33E-15 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CE141 5.37E-03 2.36E+01 7.49E-02 4.57E-02 1.41E-02 O.OOE-01 O.OOE-01 O.OOE-01 CE143 3.99E-04 2.04E+01 5.28E-03 3.50E+OO 1.02E-03 O.OOE-01 O.OOE-01 O.OOE-01 CE144 1.65E-01 1.69E+02 2.95E+OO 1.21 E+OO 4.87E-01 O.OOE-01 O.OOE-01 O.OOE-01 PR143 1.SOE-04 1.92E+OO 3.64E-03 1.36E-03 5.06E-04 O.OOE-01 O.OOE-01 O.OOE-01 PR144 5.40E-34 1.93E-28 1.07E-32 4.15E-33 1.50E-33 O.OOE-01 O.OOE-01 O.OOE-01 ND147 1.52E-04 1.57E+OO 2.42E-03 2.48E-03 9.58E-04 O.OOE-01 O.OOE-01 O.OOE-01 W187 2.61 E-01 4.43E+01 1.08E+OO 7.54E-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 NP239 1.53E-05 7.83E-01 3.03E-04 2.71E-05 5.40E-05 O.OOE-01 O.OOE-01 O.OOE-01 DAEC ODAM Page 272 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =INFANT PATHWAY= ANIMAL DRINKING WATER--MEAT TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN (mrem gal)/(Ci min) H 3 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 c 14 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 NA24 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 p 32 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CR 51 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 MN 54 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 MN 56 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 FE 55 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 FE 59 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 C058 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 C060 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl63 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 N165 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 cu 64 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZN 65 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZN 69 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 83 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 84 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 85 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 86 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 88 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 89 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 89 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 90 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 91 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 92 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 90 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Y 91M O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 91 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 92 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 93 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 95 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 97 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 NB 95 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 MO 99 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TC 99M O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TC101 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 DAEC ODAM Page 273 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =INFANT PATHWAY= ANIMAL DRINKING WATER--MEAT TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN (mrem gaQ/(Ci min} RU103 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RU105 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RU106 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 AG110M O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE125M O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE127M O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE127 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE129M O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE129 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE131M O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE131 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE132 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 I 130 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 I 131 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 1132 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 1133 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 1134 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 1135 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CS134 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CS136 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CS137 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CS138 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BA139 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BA140 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BA141 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BA142 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 LA140 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 LA142 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CE141 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CE143 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CE144 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 PR143 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 PR144 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ND147 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 w 187 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 NP239 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 DAEC ODAM Page 27 4 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =INFANT PATHWAY= RIVER SHORELINE DEPOSITS TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN {mrem gaQ/{Ci min} H 3 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 c 14 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 NA24 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 p 32 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CR 51 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE"01 O.OOE-01 O.OOE-01 MN 54 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 MN 56 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 FE 55 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 FE 59 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 co 58 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 C060 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 Nl63 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl65 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 cu 64 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZN 65 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZN 69 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 83 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 84 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 85 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 86 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 88 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 89 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 89 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 90 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 91 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 92 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 90 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Y 91M O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 91 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 92 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 93 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 95 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 97 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 NB 95 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 M099 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TC 99M O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TC101 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 DAEC ODAM Page 275 of 280 Rev.37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =INFANT PATHWAY= RIVER SHORELINE DEPOSITS TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN (mrem gal)/(Ci min) RU103 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RU105 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RU106 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 AG110M O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE125M O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE127M O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE127 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE129M O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE129 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE131M O.OOE-01 0.00E-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE131 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 TE132 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 1130 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 I 131 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 I 132 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 1133 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 1134 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 1135 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CS134 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CS136 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CS137 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CS138 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 BA139 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BA140 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BA141 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BA142 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 LA140 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 LA142 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CE141 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CE143 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CE144 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 PR143 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 PR144 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ND147 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 W187 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 NP239 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 DAEC ODAM Page 276 of 280 Rev.37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =INFANT PATHWAY= SWIMMING TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN (mrem gaQ/(Ci min} H 3 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 c 14 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 NA24 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 p 32 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CR 51 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 MN 54 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 MN 56 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 FE 55 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 FE 59 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 co 58 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 co 60 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl63 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl65 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 cu 64 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZN 65 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZN 69 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 83 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 84 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 85 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 RB 86 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 88 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 89 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 89 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 90 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 91 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 92 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 90 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Y 91M O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 91 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 92 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 93 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 95 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 97 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 NB 95 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 MO 99 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TC 99M O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TC101 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 DAEC ODAM Page 277 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =INFANT PATHWAY= SWIMMING TOTAL BODY GI-LU BONE LIVER KIDNEY THYROID LUNG SKIN {mrem gaQ/{Ci min} RU103 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RU105 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RU106 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 AG110M O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE125M O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE127M O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE127 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE129M O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE129 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE131M O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE131 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE132 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 1130 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 I 131 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 I 132 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 I 133 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 I 134 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 I 135 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CS134 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CS136 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 CS137 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CS138 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BA139 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BA140 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 BA141 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BA142 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 LA140 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 LA142 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CE141 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CE143 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CE144 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 PR143 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 PR144 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ND147 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 W187 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 NP239 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 DAEC ODAM Page 278 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =INFANT PATHWAY= BOATING TOTAL BODY GI-LU BONE LIVER KIDNEY THYROID LUNG SKIN (mrem gal)/(Ci min) H 3 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 c 14 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 NA24 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 p 32 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CR 51 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 MN 54 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 MN 56 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 FE 55 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 FE 59 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 co 58 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 C060 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl63 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Nl65 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 cu 64 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZN 65 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZN 69 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 83 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 84 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BR 85 O.OOE-01 0.00E-01 O.OOE-01 0.00E-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 86 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 88 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RB 89 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 89 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 90 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 91 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR 92 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 90 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 Y 91M O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 91 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 92 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 y 93 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ZR 95 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 ZR 97 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 NB 95 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 M099 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TC 99M O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TC101 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 DAEC ODAM Page 279 of 280 Rev. 37 Appendix C DOSE TRANSFER FACTORS FOR RADIONUCLIDES IN EFFLUENT WATER AGE =INFANT PATHWAY= BOATING TOTAL BODY Gl-LLI BONE LIVER KIDNEY THYROID LUNG SKIN (mrem gal)/(Ci min) RU103 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RU105 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 RU106 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 AG110M O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE125M O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE127M O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE127 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE129M O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE129 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE131M O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE131 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE132 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 1130 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 I 131 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 1132 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 1133 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 1134 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 1135 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CS134 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CS136 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CS137 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CS138 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BA139 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BA140 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BA141 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 BA142 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 LA140 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 LA142 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CE141 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CE143 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 CE144 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 PR143 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 O.OOE-01 O.OOE-01 O.OOE-01 0.00E-01 PR144 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 ND147 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 w 187 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 NP239 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 DAEC ODAM Page 280 of 280 Rev. 37

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