ML20063N339
| ML20063N339 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 09/16/1982 |
| From: | VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | |
| Shared Package | |
| ML20063N333 | List: |
| References | |
| PROC-820916, NUDOCS 8209200221 | |
| Download: ML20063N339 (162) | |
Text
__
ATTACHMENT 2 NORTH ANNA UNITS 1 AND 2 0FFSITE DOSE CALCULATION MANUAL a
8209200221 820916 PDR ADOCK 05000338 P
HP-0DCM Page 1 of 3 VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION OFFSITE DOSE CALCULATION MANUAL UNITS 1 AND 2 b
Recommend Approval:
Approved By:
Date:
... _..__- w
HP-0DCM Paga 2 of 3 NORTH ANNA POWER STATION OFFSITE DOSE CALCULATION MANUAL
REFERENCES:
1.
North Anna Power Station Technical Specifications.
2.
Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I,"
Rev. 1 U.S.
Nuclear Regulatory Commission, October 1977.
3.
Regulatory Guide 1.111. " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light - Water -
Cooled Reactors," Rev. 1. U.S. Nuclear Regulatory Commission, July 1977.
4.
U.S. Nuclear Regulatory Commission, " Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," NUREG-0133, October 1978.
5.
U.S. Nuclear Regulatory Commission, "X0QD0Q, Program for the Meteorologi-cal Evaluation of Routine Effluent Releases at Nuclear Power Stations,"
NUREG-0324, September 1977.
6.
U.S.
Nuclear Regulatory Commission, " User's Guide to GASPAR Code,"
NUREG-0597, June 1980.
7.
North Anna Power Station Radioactive Release Reports for 1979, 1980, and 1981.
8.
Virginia Electric and Power Company, North Anna Power Station, Units 1 and 2 Final Safety Analysis Report.
9.
Virginia Electric and Power Company, Applicant's Environmental Report Supplement, North Anna Power Station, Units 1 and 2. March 15, 1972.
b l
IMPLEMENTATION:
The provisions in the North Anna Offsite Dose Calculttion Manual will be implemented upon approval of the North Anna Power Station Radiological Effluent Technical Specifications by the NRC.
(
HP-0DCM Page 3 of 3 NORTH ANNA POWER STATION OFFSITE DOSE CALCULATION MANUAL INDEX Section No.
Date 1.
Introduction 2.
Liquid Effluent Radiation Monitor Setpoints 3.
Liquid Effluent Concentration Limit 4.
Liquid Effluent Dose Limits 5.
Liquid Effluent Dose Projection 6.
Gaseous Effluent Radiation Monitor Setpoints 7.
Gaseous Effluent Release Rates 8.
Noble Gas Effluent Air Dose Limits i
9.
Iodine - 131. Tritium, and Radionuclides in Particulate Form Gascous Effluent Dose Limits 10.
Gaseous Effluent Dose Projection 11.
Total Dose 12.
Semiannual Radioactive Effluent Release Report 13.
Radiological Environmental Monitoring Locations Appendix A Appendix B I
~. _ _
HP-0DCM-1 Prga 1 of 2 NORTH ANNA POWER STATION OFFSITE DOSE CALCULATION MANUAL SECTION 1 Introduction Part Subject Page 1
Purpose 2
2 Scope 2
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HP-0DCM-1 Page 2 of 3 1.
PURPOSE The Offsite Dose Calculation Manual (ODCM) provides the methodology and parameters to be used in the calculation of offsite doses due to radioactive liquid and gaseous effluents to assure compliance with the dose limitations of the Radiological Effluent Technical Specifications.
These dose limitations assure that:
1) the concentration of radioactive liquid effluents to the UNRESTRICTED AREA will be limited to the concentration levels of
(
10CFR20, Apper. dix B. Table II; l
l 2) the exposure to the maximum exposed MEMBER OF THE PUBLIC in the UNRESTRICTED AREA from radioactive liquid effluents will not result in doses greater than the liquid dose limits of 10CFR50, Appendix I; 3) the dose rate at and beyond the SITE BOUNDARY from radioactive gaseous effluents will be limited to the annual dose limits of 10CFR20; 4) the exposure to the maximum exposed MEMBER OF THE PUBLIC in the UNRESTRICTED AREA from radioactive gaseous effluents will not result in doses greater than the gaseous dose limits of 10CFR50, Appendix I; and 5) the exposure to the maximum exposed MEMBER OF THE PUBLIC will not exceed 40CFR190 dose limits.
The Manual provides the methodology and parameters to be used in the assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the station.
Examples are provided to demonstrate methodology, and do not necessarily reflect procedure calculations.
l The Manual provides the methodology and parameters to be used in the calculation of radioactive liquid and gaseous effluent monitoring instrumentation alarm / trip setpoints to ensure compliance with the concentration and dose rate limitations of the Radiological Effluent Technical Specifications. The Manual provides simplified drawings of the radioactive liquid and gaseous effluent waste streams.
3 The Manual gives the specific locations for collecting radiological environmental monitoring samples.
2.
SCOPE The methodology used to assure compliance with the dose, dose rate, and
' concentration limitations described above shall be used to prepare the radioactive liquid and gaseous effluent procedures and reports required by the Technical Specifications.
This manual does not include the procedures and forms required to document compliance with the surveillance requirements in the Technical Specifications.
HP-ODCM-1 Pags 3 of 3 Changes to this manual shall be reviewed and approved by the Station Nuclear Safety and Operating Committee prior to implementation.
Changes to this manual shall be submitted to the Nuclear Regulatory Commission by inclusion in the Semi-Annual Radioactive Release Report for the period during which the change was made effective.
HP-0DCM-2 Pcgn 1 of 4 NORTH ANNA POWER STATION OFFSITE DOSE CALCULATION MANUAL SECTION 2 Liquid Effluent Radiation Monitor Setpoints Part Subject 1]a ge j
1 Technical Specification Requirement 2
2 Applicable Monitors 2
3 Setpoint Calculation 2
4 Example 3
b e
HP-0DCM-2 Page 2 of 4 1.
TECHNICAL SPECIFICATION REQUIREMENT Technical Specification 3.3.3.9 requires that: "The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3-12 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 3.11.1.1 are not exceeded.
The alarm / trip setpoints of these channels shall be determined and adjusted in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM)".
2.
APPLICABLE MONITORS l
Radioactive liquid effluent monitors for which alarm / trip setpoints are determined in accordance with this Manual are:
Radiation Monitor Plant Release Point Instrument Number Liquid Radwaste Effluent Line LW-111 Service Water System Effluent Line SW-108 Condenser Circulating Water SW-130, SW-230 Monitor locations on the liquid effluent waste stream are shown in Figure 2.0.
3.
SETPOINT CALCULATION 3.1 Radioactive liquid effluent monitor alarm / trip setpoints shall be determined such, for simultaneous releases from different release points, the limits of Specification 3.11.1.1 are not exceeded.
3.2 Maximum setpoint values shall be calculated as follows:
c = S-f-l where:
3 c=
the setpoint, in uCi/ml, of the radioactivity monitor measuring the radioactivity concentration in the effluent line prior to dilution; C=
the effluent concentration limit for this monitor used in implementing 10CFR20 for the site, in uCi/ml; f=
the flow setpoint as measured at the radiation monitor location, 300 gallons per minute; F=
the dilution water flow calculated as:
F = f + (238,000 GPM x No. of Cire. Pumps in Service).
HP-0DCM-2 Page 3 of 4 4.
EXAMPLE 4.1 Liquid effluent line monitor setpoints can be determined by comparing the response of the detector to known concentrations of radionuclides in the liquid effluent which are typical of the actual waste being discharged.
4.2 The following information is obtained from an isotopic analysis of liquid effluent sample:
Radionuclide Average Undiluted Concentration Released Released (uCi/ml)
Co-60 3.09E-06 Cs-137 4.08E-06 Cs-134 2.65E-06 Co-58 3.19E-06 Fe-59 1.78E-06 4.3 The net count rate of monitor LW-111 is 1000 CPM at the time the sample was obtained.
4.4 Calculate the fraction of maximum allowable concentration (FMAC) using the following equation:
FMAC = 1 x
" i' F
i MPCf l
4.5 UNRESTRICTED AREA MPC's are obtained from 10CFR20. Appendix B. Table II, Column 2 for the radionuclides released in 4.2.
The sum of the ratios of the average undiluted concentration released (uci/ml) for each radionuclide to its respective MPC is calculated:
l Radionuclide uCi/mi g Released MPC MPC Co-60 3E-05 1.03E-01 Cs-137 2E-05 2.04E-01 l
Cs-134 9E-06 2.94E-01 l
Co-58 9E-05 3.54E-02
(
Fe-59 SE-05 3.56E-02 l
l I uCi/mli = 6.72E-01 i MPCf 4.6 The flow, f,
at the radiation monitor location is 300 gpm, and 3 circulating water pumps are available.
F = f + (238,000 x f of Cire. Pumps)
I i
f
' P-0DCM-2 J
Page 4 of 4 F = 300 + (238,000 x 3)
F = 7.143E+05 GPM FMAC = 7.1 E+05 x 6.72 E-01 FMAC = 2.82E-04 4.8 The maximum allowable count rate for this mixture would be:
Max. CPM =
2.82E-04 Max. CPM = 2.8 E 04 Max. CPM = 3.55E+06 4.9 The setpoint, in uCi/ml, is:
C = Max. CPM x 2.00E-07 (uci/ml)
CPM where, 2.00E-07 (uCi/ml) is the LW-111 monitor conversion factor CPM for Cs-137.
C = 3.55E+06 (CPM) x 2.00E-07 (uCi/ml)
CPM l
C = 7.09E-01 uCi/ml.
l I
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FICURE 2.0 Pcge 1 cf 2 Chemical & Volume Control System V:nt & Drain System Sumps High Level Clarifier Waste Evaporators r
Spent Resa,n Flush Water Drain Tanks Tanks JL Equipment
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Hot Laboratory Drains (Details-Next Page) rf Ion Exchange (Administrative Filtration Control) 8 System
{
l V:nt & Drain Sumps U
Low Level Boron Recovery Test Tanks r
Waste Drain Tanks Fluid Water Treating Tanks Boron Recovery System Evaporator Boron Recovery Boron Test Tanks
^
Condensate System Stsan Generator Blowdown S/G Blowdown f
7 r
i O
Tank j
SS-122 thru 124 SS-222 thru 224 Service Water Resevoir Blowdown r-Cold Laboratory Drains
.I PCA Drains
' Contaminated Drain Tanks Laboratory Drains A Radiation Monitor
---Automatic Actuation NORTH ANNA LIQUID EFFLUENT SYSTEM
FIGURE 2.0 (cont.)
Peg 2 2'of 2 r-------
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l Clarifier Accelerator Clarifier Mixed Bed Demineraliser Hold-Up Tanks Surge-Tank Filter "*
Demineralizer Filter J
Tank g
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S LW-111 1
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Discharge Tunnel S
Flat Bed
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Filter g
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Clarifier Equipment
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Solid Waste 0
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Service Water Tunnel i
SW-108 Condenser Circulating Water Discharge
- Tunnel a
SW-130 SW-230 Station Stors i
Turbine B1da, (Floor Drain) Sumps Drain System
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NORTH ANNA LIQUID EFFLUENT SYSTEM
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Page 1 of 3
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Part Subject !
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Technical Specification Requirement 2
1 2
Calculation 2
3 Example 2
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1.':lTECHNICAL SPFCIFICATION REQUIREMENT
- (
/
Technical Specification 3.11.1.1 requires that: "The concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS (See Figure 5.1-3) shall be limited to the concentrations specified in 7-~
Table II, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolygd or entrained noble gases, the concentration shall be limited to 2 x 10 microcuries/ml".
- J 2.
CALCULATION 2.1 The daily concentrations of radioactive materials in liquid waste to unrestricted areas must meet the following:
Volume of Waste Diacharged + Volume of Dilution Water, y Volume of Waste Discharged x I uCi/mi v
g 1 MPCg
/
where:
the concentration of nuclide i in the liquid ef fluent uCi/mi
=
g discharge; the maximum permissible concentration in unrestricted a
=
g areas of nuclide, i, expressed as uCi/ml from 10CFR Part 20 Appendix B. Table II, for radionuclides other than noble gases and 2E-04 uCi/ml for dissolved or entrained noble gases.
I i
3.
EXAMPLE 3.1, Compilation of data from liquid effluent release records for a day
'ihdicated the following radionuclides and concentrations were l
released from the liquid radwaste effluent line.
l l
l Concentration (uCi/ml)
MPC uCi/ml/MPC l
Radionuclide l
Co-60 4.00E-06 3E-05 1.33E-01 l
Cs-137 3.00E-06 2E-05 1.50E-01 l
Cs-134 1.00E-06 9E-06 1.11E-01 Co-58 4.50E-06 9E-05 5.00E-02 i
I-131 5.00E-08 3E-07 1.67E-01 f
I uCi/mi 6.11E-01
=
g l
1 MPCf i
l Volume of Dilution Water for day = 1.71E+07 gal.
Volume of Waste Discharged for day = 2.88E+05 gal.
HP-ODCM-3 Pcga 3 of 3 3.2 The daily concentration must meet the following:
Volume of Waste Discharged + Volume of Dilution Water, y Volume of Waste Discharged x E uC1/mi g
i MPCg 2.88E+05 + 1.71E+07 2.88E+05 x 6.llE-01 1 98.8 > 1
+
HP-ODCM-4 Pega 1 of 5 NORTH ANNA POWER STATION OFFSITE DOSE CALCULATION MANUAL SECTION 4 Liquid Effluent Dose Limit Part Subject Pajgt 1
Technical Specification Requirement 2
2 Calculation 2
3 Example 3
4 Quarterly Composite Ar.alysee 4
b 9
HP-0DCM-4 Peg 2 2 of 5 1.
TECHNICAL SPECIFICATION REQUIREMENT Technical Specification 3.11.1.2 requires that: "The dose or dose commitment to the maximum exposed MEMBER OF THE PUBLIC 'from radioactive materials in liquid effluents released from each reactor unit, to UNRESTRICTED AREAS (see Figure 5.1-3) shall be limited:
a.
During any calendar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 arem to the critical organ, and b.
During any calendar year to less than or equal to 3 mrem to the l
total body and to less than or equal to 10 mrem to the critical organ".
I 2.
CALCULATIONS 2.1 Dose contribution shall be calculated for all radionuclides identified in liquid effluents released to UNRESTRICTED AREAS based on the following expressions:
D=tFEC A g g i
where:
D=
the cumulative dose commitment to the total body or critical organ, from the liquid effluents for the time period t,
in mrem; t=
the length of the time period over which C and F are averaged g
for all liquid releases; F=
the near field average dilution factor for C during any liquid g
effluent release. Defined as the ratio of the average undiluted liquid waste flow during release to the average flow from the site discharge structure to UNRESTRICTED AREAS; C = the average concentration of radionuclide, i, in undiluted f
liquid effluent during time period, t,
from any liquid releases, in uCi/ml; b
A, = the site related ingestion dose commitment factor to the total body or critical organ of an adult fn each identified principal gamma and beta emmitter listed in Table 4.0, in arem-al per hr-uCi; A = 1.14E+05 (730/D, + 21BF ) DFg g
f where:
1.14E+05 = IE+06 pCi/uCi x IE+03 ml/kg + 8760 hr/yr, units con-version factor;
HP-0DCM-4 Pega 3 of 5 730 = adult water consumption, kg/yr from NUREG-0133; D = dilution factor from the near field area within one-quarter mile of the release point to the potable water intake for the adult water consumption.
The dilution factor, D was calculated as the ratio of the average flow ra t e", a t the U.S.G.S.
gauging station at Doswell (302 cfs) to the average release rate at the No3th Anna dam (220 cfs), 1.37; BF = The bioaccumulation factor for nuclide, i, in fish, g
pCi/kg per pCi/1, from Table A-1 of Regulatory Guide 1.109.
DF = the critical organ dose conversion factor for nuclide, i, g
for adults, in mrem /pC1, from Table E-11 of Regulatory Guide 1.109. Rev. 1.
3.
EXAMPLE 3.1 Compilation of data from release records for a 31 day period provides the following information:
Total Volume of Undiluted Liquid Effluent Released - 2.00E+10 ml Total Volume of Dilution Water Used During Period
= 1.59E+14 ml Average Concentration of Radionuclides in Undiluted Liquid Effluent 6.23E-08 uCi/ml Cs-134 2.13E-07 uCi/ml Cs-137 5.17E-07 uCi/ml 1-131 Co-58 1.53E-07 uCi/ml 7.27E-07 uCi/ml Co-60 4.62E-03 uCi/ml H-3 3.2 31 Day Total Body Calculation:
D=tFIC A g g i
Obtain total body A values from Table 4.0 g
t = 744 hours0.00861 days <br />0.207 hours <br />0.00123 weeks <br />2.83092e-4 months <br />.
arem-al mrem A
Nuclide 1 (uCi/ml) x i uCi-hr hr
=
Cs-134 6.23E-08 x
5.87E+05 3.66E-02 Cs-137 2.13E-07 x
3.46E+05 7.37E-02 I-131 5.17E-07 x
3.29E+02 1.70E-04
=
Co-58 1.53E-07 x
3.01E+02 4.61E-05
=
Co-60 7.27E-07 x
8.51E+02 6.19E-04
=
H-3 4.62E-03 x
6.59E+00 3.04E-02
=
IC Ag = 1.42E-01 1
i
HP-0DCM-4 Page 4 of 5
- p., 2.00E+10 (ml) 1.59E+14 (ml)
Therefore' D = 744(hr) x 2.00E+10 (ml) x 1.42E-01 1.59E+14 (ml) hr D = 1.33E-02 mrem to Total Body.
3.3 31 Day Critical Organ Calculation:
D=tFIC A f g i
Obtain Critical Organ A values from Table 4.0.
1 t = 744 hours0.00861 days <br />0.207 hours <br />0.00123 weeks <br />2.83092e-4 months <br />.
arem-ml mrem A
Nuclide 1 (uCi/ml) x i uCi-hr hr
=
Cs-134 6.23E-08 x
7.18E+05 4.47E-02
=
Cs-137 2.13E-07 x
5.29E+05 1.13E-01 1-131 5.17E-07 x
5.74E+02 2.97E-04
=
Co-58 1.53E-07 x
1.34E+02 2.05E-05 Co-60 7.27E-07 x
3.86E+02 2.81E-04
=
H-3 4.62E-03 x
6.59E+00 3.04E-02
=
IC A = 1.89E-01 f f i
7, 2.00E+10 (ml) 1.59E+14 (ml)
Therefore,
(*
D = 744(hr) x 1.59E+14 (ml) x 1.89E-01 hr D = 1.77E-02 mrem to critical organ.
4.
QUARTERLY COMPOSITE ANALYSES For radionuclides not determined in each batch or weekly composite, the dose contribution to the current monthly or calendar quarter cumulative summation may be approximated by assuming an average monthly concentra-tion based on the previous monthly or quarterly composite analyses.
However, for reporting purposes, the calculated dose contribution shall be based on the actual composite analyses.
HP-ODCM-4 Pest 5 of 5 TABLE 4.0 j
LIQUID INGESTION PATHWAY DOSE FACTOR FOR NORTH ANNA POWER STATION l
I l
UNIT NOS. 1 AND 2 Total Body A Critical Organ A g
g l
Radionucl!.Je arem/hr arem/hr I
uCi/ml uCi/ml H-3 6.59E+00 6.59E+00 i
Na-24 5.10E+02 5.10E+02 i
Cr-51 1.43E+00 I
Mn-54 8.88E+02 4.65E+03 Fe-55 1.33E+02 5.70E+02 Fe-59 1.17E+03 3.06E+03 Co-58 3.01E+02 3.86E+02 Co-60 8.51E+02 1.34E+02 Zn-65 3.37E+04 7.47E+04
[
Rb-86 4.77E+04 1.02E+05 Sr-87 1.17E+03 Sr-90 2.46E+05 Y-91 4.54E-01 Zr-95 4.52E-01 6.68E-01 Zr-97 1.06E-02 2.32E-01 Nb-95 1.34E+02 2.49E+02 Mo-99 6.93E+01 3.64E+02 Ru-103 6.74E+01 s
Ru-106 2.94E+01 i
Ag-110m 5.82E+00 9.79E+00 Sb-124 7.00E+01 3.33E+00 Sb-125 2.68E+01 1.26E+00
+
Te-125m 3.66E+02 9.89E+02 Te-127m 8.40E+02 2.46E+03 Te-129m 1.85E+03 4.37E+03 Te-131m 7.18E+02 8.61E+02 Te-132 1.56E+03 1.66E+03 l
I-131 3.29E+02 5.74E+02 l
I-132 1.83E+01 5.24E+01
'I-133 7.27E+01 2.38E+02 I-134 9.94E+00 2.78E+01 1-135 4.13E+01 1.12E+02 Cs-134 5.87E+05 7.18E+05 Cs-136 8.97E+04 1.2SE+05 Cs-137 3.46E+05 5.29E+05 i
Cs-138 2.62E+02 5.29E+02 Ba-140 9.34E-01 1.79E+00 i
La-140 4.01E-02 1.52E-01 Ce-141 4.52E-02 3.99E-01
[
i Ce-143 8.51E-03 7.69E+01 l
Ce-144 1.65E+00 1.29E+01 l
Np-239 5.45E-03 9.89E-03
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HP-ODCM-5 Pagt 1 of 3 NORTH ANNA POWER STATION OFFSITE DOSE CALCULATION MANUAL SECTION 5 Liquid Effluent Dose Projections Part Subject Paggt 1
Technical Specification Requirement 2
2 Projected Total Body Dose 2
3 Projected Critical Organ Dose 2
4 Example 2
b
HP-0DCM-5 Pcgs 2 of 3 l
1.
TECHNICAL SPECIFICATION REQUIREMENT Technical Specification 3.11.1.3 requires that:
"The liquid radwaste treatment system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the projected doses due to the liquid effluent, from each reactor unit to UNRESTRICTED AREAS (see Figure 5.1-3) would exceed 0.06 arem to the total body or 0.2 arem to the critical organ in a 31 day period".
2.
PROJECTED TOTAL BODY DOSE
=
a y
se from liquid effluents in the 2.1 Determine D previous 31kBay period, calculated according to H.P.-0DCM-4.
2.2 Estimate R = ratio of the estimated volume of liquid effluent g
releases in the present 31 day period to the volume released in the previous 31 day period.
2.3 Estimate F = ratio of the estimated liquid effluent radioactivity inthepredent31dayperiodtotheliquideffluentactivityinthe previous 31 day period.
2.4 Determine PDTB " projected total body dose in a 31 day period.
PROJECTED CRITICAL ORGAN DOSE 3.1 Determine D = critical organ dose from liquid effluents in the previous 31 day period, calculated according to H.P.-0DCM-4.
3.2 Estimate R as in Step 2.2.
3 3.3 Estimate F as in Step 2.3.
3 3.4 Determine PD = projected critical organ dose in a 31 day period.
9 PD, = D, (R F )
gy b
Historical data pertaining to the volumes and radioactivity of liquid effluents released in connection to specific station functions, as maintenance or refueling outages, shall be used in the above projections as appropriate.
4.
' EXAMPLE 4.1 A total body dose in a 31 day period due to liquid effluent releases was calculated in H.P.-0DCM-4.3.2 using the data in H.P.-0DCM-4.3.1.
Therefore, D
~
~
l HP-0DCM-5 Paga 3 of 3 i
4.2 According to H.P.-0DCM-4.3.1, the total volume of undiluted liquid effluent released was 2.00E+10 ml.
It is estimated that the liquid effluent release may double to 4.00E+10 mi in the present 31 day period. Therefore, R = 4.00E+10 = 2.0.
g 2.00E+10 4.3 According to H.P.-0DCM-4.3.1, the total concentration of radio-nuclides in undiluted liquid effluents is 4.62E-03 uCi/ml.
The total concentration of radionuclides in undiluted liquid effluents in the present 31 day period is estimated to be 5.00E-03 uCi/ml.
Therefore, F = 5.00E-03 = 1.08.
3 4.62E-03 4.4 The projected total body dose in a 31 day period is:
~
(* **}
- PDTB "
~
~
~
TB 4.5 The projected critical organ dose, PD, in a 31 day period would be similarly obtained.
e-e e
HP-0DCM-6 Pago 1 of 3 NORTH ANNA POWER STATION OFFSITE DOSE CALCULATION MANUAL SECTION 6 Gaseous Effluent Radiation Monitor Setpoints Part Subject Page 1
Technical Specification Requirement 2
2 Applicable Monitors 2
3 Setpoint Calculation 2
4 Example 3
_m._.
HP-0DCM-6 Prgs 2 of 3 1.
TECHNICAL SPECIFICATION REQUIREMENT Technical Specification 3.3.3.10 requires that: "The radioactive gaseous-effluent monitoring instrumentation channels shown in Table 3.3-13 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 3.10.2.1 are not exceeded.
The alarm / trip setpoints of these channels shall be determined and adjusted in accordance with the ODCM".
l 2.
APPLICABLE MONITORS Radioactive gaseous effluent monitors for which alarm / trip setpoints are determined in accordance with this Manual are:
Radiation Monitor Plant Release Point Instrument Number Process Vent GW-102 Condenser Air Ejector SV-121, 221 Ventilation Vent A VG-104 Ventilation Vent B VG-113 Monitor locations on the gaseous effluent waste streams are shown in Figure 6.0.
l 3.
SETPOINT CALCULATIONS l
3.1 Radioactive gaseous effluent monitor alarm / trip setpoints shall be determined such, for simultaneous releases from different release points, the limits of Specification 3.11.2.1 are not exceeded.
3.2 Calculate, according to H.P.-0DCM-7 a limiting release rate, R,
y using Xe-133 as the nuclide to be released.
3.3 Calculate a maximum setpoint value for the monitor as follows:
(R ) 2.12E-03 3
C-l max a
where:
C=
the effluent concentration limit implementing 10CFR20 for the
(
site, uCi/ml; l
R = the release rate limit, uCi/sec; g
r l
2.12E-03 = CFM per al/sec; and r
F,,
= the maximum flow rate for the system, CFM.
HP-0DCM-6 Page 3 of 3 4.
EXAMPLE 4.1 From the example presented in H.P.-ODCM-7, obtain the release rate limit, R, calculated in Section 7.3.7.
g R
=Q x
+06 uci g
Xe-133 Ci R = 8.06E-01 Ci x IE+06 uCi g
see C1 R = 8.06E+05 uCi g
sec 4.2 F
= 330 CFM max 4.3 Calculate the process vent monitor setpoint:
C = (R ) 2.12E-03 g
F,,x C = (8.06E+05) x 2.12E-03 330 C = 5.18E+00 uCi/ml 4.4 To determine what the setpoint should be in CPM, the setpoint, C, should be multiplied by the process vent, GW-102, monitor Xe-133 conversion factor 8.57E-07 CPM uC1/ml n
I I
f l
l I
i
FIGURE 6.0 Pcge 1 cf 2
- e______,
Prsessa Effluent Surge Decay 8
Compressor Tank FCVh-101
?
Rscombiner Tank i
Process 8
Vent
___q d
Containment Vacuum System j
I I. _ _ _ _ _ _ _ _ _ _ __--D Gw-102 Liquid Waste Tank Vent r
a Equipnent Vent Charcoal Process (Particulate)
Vent
~
~
Pressurizer Relief Tank Puree r
7;g p_
Boron Recovery Tanks y
Nitrogen Supply Bleed Line y
Containment Vacuum Ptmo Discharea
-~~~.
Condenser Air Eiector g
{
- Vent Stack A
{
SV-121,221 To Containment A Radiation Monitor S/G Blowdown Tank Condenser Vent
> Atmosphere
--- Automatic Actuation NORTH ANNA GASEOUS. WASTE DISPOSAL SYSTEM
P:ge 2 cf 2 FIGURE 6.0 (cont.)
l r
Decontamination Area L
Fuel Building l
i Vent-Vent B l
Unit 1 Safeguards System Radiciodine HEPA 3
VG-104 r
Unit 2 Safeguards System Containment Purge r
P l
t, l
O Auxiliary Bldg. General O
Auxiliary Bldg. Central VG-113 -
i e
i NORTH ANNA GASEOUS. WASTE DISPOSAL SYSTEM t
HP-0DCM-7 P g2 1 of 9 NORTH ANNA POWER STATION OFFSITE DOSE CALCULATION MANUAL SECTION 7 Gaseous Effluent Release Rate Part Subject Page 1
Technical Specification Requirement 2
2 Calculations 2
3 Example 3
i l
l l
HP-0DCM-7 Pcg2 2 of 9 1.
TECHNICAL SPECIFICATION REQUIREMENT Technical Specification 3.11.2.1 requires that: "The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY (see Figure 5.1-3) shall be limited to the following:
a.
For noble gases: Less than or equal to 500 mrem /yr to the total body and less than or equal to 3000 mrem /yr to the skin, and b.
for iodine - 131, for tritium, and for all radionuclides in particulate form with half-live greater than 8 days: Less than or equal to 1500 mrem /yr to the critical organ".
2.
CALCULATION 1.
The dose rate limit for noble gases shall be determined to be within the Technical Specification limit by limiting the release rate to the lessor of:
h
] 1 500 mrem /yr to total body, I [K Qg+K g
gy gy p
p or g y) h
] $ 3000 mrem /yr gyy)h I [(L
+ 1.1M
+Ggy+ 1.1M gyy gyy gy p
p p
to the skin where:
Subscripts =
vv, refers to vent releases from the building ventilation vent; pv, refers to the vent releases from the process vent.;
i, refers to individual radionuclide; Kg,K The total body dose factor for ventilation vent
=
y or process vent release due to gamma emissions for each identified noble gas radionuclide, i, in arem/yr per Curie /sec. Factors are listed in Table 7.0 and Table 7.1; The skin dose factor for ventilation vent or Lg,L
=
gy p
process vent release due to beta emissions for each identified noble gas radionuclide i, in mrem /yr per Curie /sec.
Factors are listed in Table 7.0 and Table 7.1;
HP-0DCM-7 Page 3 of 9 ne ah dose factor for ventilation vent or M
M
=
- gyy, gy p
process vent release due to gamma emissions for each identified noble gas radionuclide, i, in arad/yr per Curie /sec.
Factors are listed in Table 7.0 and Table 7.1; The release rate for ventilation vent or process Qivv, Q
=
iV P
vent of noble gas radionuclide, i, in gaseous effluents in Curie /sec (per site);
1.1 The unit conversion factor that converts air
=
dose to skin dose, in mrem / mrad.
2.
The dose rate limit for iodine - 131, for tritium, and for all radionuclides in particulate form with half-live greater than 8 days shall be determined to be within the Technical Specification limit by limiting the release rate to:
E [P h
h
] < 1500 mrem /yr to critical organ gyy gyy + Pgy gy p
p where:
The critical organ dose factor for ventilation Pivv, P
=
iv P
vent or process vent for I-131 H-3, and all radionuclides in particulate form with half-lives greater than 8
days for the inhalation pathway, in mrem /yr per Curie /sec.
Factors are listed in Table 7.2; The release rate for ventilation vent or process Qivv, Q
=
Iv P
vent of I-131. H-3, and all radionuclides, i, in particulate form with half-lives greater than 8 days in gaseous effluents in Curie /sec (per site).
3.
All gaseous releases, not through the process vent, are considered ground level and shall be included in the determination of Qg.
A 3.
EXAMPLE 3.1 Technical Specification 3.3.3.11 requires that tha setpoints for radioactive gaseous effluent monitors be calculated to ensure that the limits of Specification 3.11.2.1 are not exceeded.
The methodology, used to determine that the limits of Specification 3.11.2.1 are not exceeded, is presented in H.P.-ODCM-6.
3.2 According to NUREG-0133, the radioactive gaseous effluent radiation monitor alarm / trip setpoints should be based on the radioactive noble gases.
It is not considered to be practicable to anO v instantaneous alarm / trip setpoints to integrating radistion monf. tors sensitive to radioiodines, radioactive materials in particulate form and radionuclides other than noble gases.
HP-0DCM-7 P:gs 4 of 9 3.3 To calculate the limiting release rate for the process vent, the following information is determined from process vent gaseous effluent release records:
Radionuclide Release Rate (Curies /sec)
Xe-133 4.43E-06 Xe-135 3.04E-07 Kr-88 2.84E-10 Xe-133m 1.38E-07 Normalizing the above radionuclide mixture to 1 Curie /sec of activity released:
Radionuclide Release Rate (Curies /sec)
Xe-133 9.09E-01 Xe-135 6.24E-02 Kr-88 5.83E-05 Xe-133m 2.83E-02 3.4 Obtain from Table 7.1 the appropriate K total body dose factors, I
and calculate the process vent Xe-133 Equivalent total body dose factor corrected for the normalized radionuclide mixture:
Normalized Radionuclide ipv x
Release Rate Q
=
3.21E+02 Xe-133 3.53E+02 x
9.09E-01
=
1.35E+02 Xe-135 2.17E+03 x
6.24E-02
=
1.03E+00 Kr-88 1.76E+04 x
5.83E-05
=
8.52E+00 Xe-133m 3.01E+02 x
2.83E-02 4.66E+02 IK x Normalized Q
=
y g
Xe-133 equivalent total body = I K x Normalized Q gpy f
dosefactor,be-133 Normalized QXe.133 Total Body K,_g33 = 4.66E+02 g
9.09E-01 Total Body be-133 = 5.13E+02
\\
HP-ODCM-7 Pegs 5 of 9 3.5 Obtain from Table 7.1 the appropriate L and M skin dose I
I factors, and calculate the process vent E-133 eq8fvalent dose factor for the normalized radionuclide mixture:
Radio-Normalized (L
y,g x gipv)
Q, x
nuclide ipv Xe-133 (3.67E+02 +
1.1 x 4.24E+02) x 9.09E-01 7.57E+02
=
Xc-135 (2.23E+03 +
1.1 x 2.30E+03) x 6.24E-02 2.97E+02
=
Kr-88 (2.84E+03 + 1.1 x 1.82E+04) x 5.83E-05 1.33E+00
=
Xe-133m (1.19E+03 +
1.1 x 3.92E+02) x 2.83E-02 4.59E+01
=
gy)xh]=
I [(L
+ 1.1 M 1.10E+03 gy p
g p
Xe-133 equivalent = {[(Lgpy + 1.1 Mgpy) x Normalized Q )
skin, beta and gamma dose factor Normalized QXe-133 (L + 1.1 M)
(L + 1.1 M) = 1.10E+03 9.09E-01 (L + 1.1 M) = 1.21E+03 3.6 As ventilation vent releases are not considered in this example, the dose rate limit for noble gases shall be limited to the lessor of:
E [K h
) 1500 mrem /yr total body, or gy gy p
p g y) h
] 13000 mrem /yr to sMn I [(L
+ 1.1 M gy yy p
p p
3.7 Calculate the process vent Xe-133 equivalent total body release rate, in Curies per sec, using the Xe-133 equivalent total body dose factor:
9Xe-133 1 500 be-133 Xe-133 I 5.
E+02 Q
1 9.75E-01 Curies /sec Xe-133
HP-0DCM-7 Pcg2 6 cf 9 3.8 Calculate the process vent Xe-133 equivalent skin release rate, in Curie /sec, using the Xe-133 equivalent beta and gamma skin dose factor Xe-133 " I'Xe-133
- I*
Xe-133) 000
=
Xe-133 1.21E+03
.48 +00 Curies /sec Q
=
Xe-133 3.9 The calculations indicate that the process vent Xe-133 equivalent total body release rate is limiting.
An appropriately conservative factor should be applied to the process vent release rate to ensure that the total noble gas releases from the site do not exceed the limits of T.S. 3.11.2.1.a.
uCi/s!E-I$$valuecalculatedinH.P.-0DCM-7.3.7canbeconvertedto 3.10 The Q a
used in the process vent monitor setpoint calculation presented in H.P.-0DCM-6.
The k -133 va ue is equivalent t R.
Xe g
HP-0DCM-7 Pcg2 7 cf 9 TABLE 7.0 CAMMA AND BETA DOSE FACTORS FOR NORTH ANNA POWER STATION UNIT NOS. 1 AND 2 X/Q = 9.3E-06 sec/m at 1416 meters SE Direction Dose Factors for Ventilation Vent K
L M
N Noble Gas TotakVIody SAYn Gamma Air Beta"Xir v
Radionuclide arem/yr urem/yr mrad /yr mrad /yr Curie /Sec Curie /See Curie /sec Curie /sec Kr-83m 7.03E-01 1.79E+02 2.68E+03 Kr-85m 1.09E+04 1.36E+04 1.14E+04 1.83E+04 Kr-85 1.50E+02 1.25E+04 1.60E+02 1.81E+04 Kr-87 5.51E+04 9.05E+04 5.74E+04 9.58E+04 Kr-88 1.37E+05 2.20E+04 1.41E+05 2.72E+04 Kr-89 1.54E+05 9.39E+04 1.61E+05 9.86E+04 Kr-90 1.45E+05 6.78E+04 1.52E+05 7.28E+04 Xe-131m 8.51E+02 4.43E+03 1.45E+03 1.03E+04 Xe-133m 2.33E+03 9.24E+03 3.04E+03 1.38E+04 Xe-133 2.73E+03 2.85E+03 3.28E+03 9.77E+03 Xe-135m 2.90E+04 6.61E+03 3.12E+04 6.87E+03 Xe-135 1.68E+04 1.73E+04 1.79E+04 2.29E+04 Xe-137 1.32E+04 1.13E+05 1.40E+04 1.18E+05 Xe-138 8.21E+04 3.84E+04 8.57E+04 4.42E+04
,Ar-41 8.22E+04 2.50E+04 8.65E+04 3.05E+04
HP-0DCM-7 Pcga 8 of 9 TABLE 7.1 CAMMA AND BETA DOSE FACTORS FOR NORTH ANNA POWER STATION UNIT NOS. 1 AND 2 X/Q = 1.2E-06 sec/m at 1513 meters S Direction Dose Factors for Process Vent K
L M
N Noble Gas Tota {PEody SkSn GammE* Air Beta Xir P
Radionuclide mrem /yr mrem /yr mrad /yr mrad /yr Curie /Sec Curie /Sec Curie /sec Curie /sec Kr-83m 9.07E-02 2.32E+01 3.46E+02 Kr-85m 1.40E+03 1.75E+03 1.48E+03 2.36E+03 Kr-85 1.93E+01 1.61E+03 2.06E+01 2.34E+03 Kr-87 7.10E+03 1.17E+04 7.40E+03 1.24E+04 Kr-88 1.76E+04 2.84E+03 1.82E+04 3.52E+03 Kr-89 1.99E+04 1.21E+04 2.08E+04 1.27E+04 Kr-90 1.87E+04 8.75E+03 1.96E+04 9.40E+03 Xe-131m 1.10E+02 5.71E+02 1.87E+02 1.33E+03 Xe-133m 3.01E+02 1.19E+03 3.92E+02 1.78E+03 Xe-133 3.53E+02 3.67E+02 4.24E+02 1.26E+03 Xe-135m 3.74E+03 8.53E+02 4.03E+03 8.87E+02 Xe-135 2.17E+03 2.23E+03 2.30E+03 2.95E+03 Xe-137 1.70E+03 1.46E+04 1.81E+03 1.52E+04 Xe-138 1.06E+04 4.96E+03 1.11E+04 5.70E+03
,Ar-41 1.06E+04 3.23E+03 1.12E+04 3.94E+03
HP-0DCM-7 Pega 9 of 9 TABLE 7.2 INHALATION PATHWAY DOSE FACTORS FOR NORTH ANNA POWER STATION UNIT NOS. 1 AND 2 3
Ventilation Vent X/Q = 9.3E-06 sec/m at 1416 Meters SE Direction Process Vent X/Q = 1.2E-06 sec/m at 1513 Meters S Direction P
P Radionuclide areUyr areUyr Curie /sec Curie /sec H-3 1.05E+04 1.35E+03 Cr-51 7.95E+02 1.02E+02 Mn-54 ND ND Fe-59 ND ND Co-58 ND ND Co-60 ND ND Zn-65 ND ND Rb-86 ND ND l
Sr-89 ND ND Sr-90 ND ND Y-91 ND ND Zr-95 ND ND Nb-95 ND ND Ru-103 ND ND Ru-106 ND ND Ag-110m ND ND Te-127m 5.64E+04 7.28E+03
- Te-129m 5.88E+04 7.59E+03 Cs-134 ND ND Cs-136 ND ND l
Cs-137 ND ND Ba-140 ND ND Ce-141 ND ND Ce-144 ND ND I-131 1.51E+08 1.95E+07 ND - No data for dose factor according to R.G. 1.109, Rev. 1.
HP-0DCM-8 Pcg2 1 of 4 NORTH ANNA POWER STATION OFFSITE DOSE CALCULATION MANUAL i
SECTION 8 Noble Gas Effluent Air Dose Limits Part Subject g
1 Technical Specification Requirement 2
r 2
Calculation 2
3 Example 3
i h
l 1
L l
1 6
l I
l
/
HP-0DCM-8 Peg 2 2 of 4 1.
TECHNICAL SPECIFICATION REQUIREMENT Technical Specification 3.11.2.2 requires that: "The air dose due to noble gases released in gaseous effluents, from each reactor unit, from the site to areas at or beyond SITE BOUNDARY (see Figure 5.1-3) shall be limited to the following:
a.
During any calendar quarter: Less than or equal to 5 mrada for gamma radiation and less than or equal to 10 mrads for beta radiation and, b.
During any calendar year: Less than or equal to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation.
2.
CALCULATIONS 2.1 The air dose to areas at or beyond the SITE BOUNDARY due to noble gases shall be determined by the following:
For gamma radiation:
igpy]
Dg = 3.17E-08 I [M Qgyy + Mgpy gy For beta radiation:
Db = 3.17E-08 I [N Q
+N Q y]
g hv y
where:
Subscripts =
vv, refers to vent releases from the building ventilation vent; pv, refers to the vent reldaset from the process vent; i, refers to individual radionuclide; the air dose for gamma radiation, in mrad; Dg
=
the air dose for beta radiation, in mrad; Db
=
the air dose factors for ventilation vent or Mivv, M
=
iV P
process vent release due to gamma emissions for each identified noble gas radionuclide, i, in arad/yr per Curie /sec.
Factors are listed in Tables 7.0 and 7.1; the air dose factor for ventilation vent or Nivv, Nipv
=
process vent release due.to bata emissions for each identified noble gas radionuclide, i, in mrad /yr per Curie /sec.
Factors are listed in Tab 1cc 7.0 and 7.1;
HP-0DCM-8 Page 3 of 4 the release for ventilation vent or process vent Qivv, QiPv
=
of noble gas radionuclide, i, in gaseous efflu-ents for 31 days, quarter, or year as appropri-ste in Curies (per site);
1 3.17E-08 the inverse of the number of seconds in a year.
=
2.2 All gaseous releases, not through the process vent, are considered ground level and shall be included in the determination of Q gyy.
3.
EXAMPLE 3.1 Compilation of data from release records for the process vent for a quarter provides the following information:
Noble Gas Radionuclide Activity Released (Curies) 1 Xe-133 6.25E+01 l
Xe-135 2.24E-01 Xe-131m 6.71E-02 4
Xe-133m 3.81E-02 3.2 Compilation of data from release records for the ventilation vents for a quarter provides the following information:
Noble Gas Radionuclide Activity Released (Curies) l 4
Xe-133' 5.62E+02 Xe-135 2.02E+00 Xe-131m 6.04E-01 Xe-133m 3.43E-01 3.3 The air dose for gamma radiation is calculated from:
Qg y]
Dg = 3.17E-08 E [M Qgy,+ Mgy fyy p
p b
The appropriate values of M and M shall be obtained from iv IVv P
Tables 7.0 and 7.1.
Noble Gas M
Q (mrad-sec)
(Cb"Ye)
Radionuclide (arad/yrpkEVCurie/sec) x yr
=
1.84E+06 Ae-133 3.28E+03 x 5.62E+02
=
3.62E+04 Xe-135 1.79E+04 x 2.02E+00
=
Xe-131m 1.45E+03 x 6.04E-01 8.76E+02
=
1.04E+03 Xe-133m 3.04E+03 x 3.43E-01
=
IM 5
1.88E+06
=
gyV fvv i
HP-0DCM-8 % -
Page 4 of 4
~7
,s 3
3-
~
}
Noble Gas M
Q
-(mrad Ae'c)/
i inv.
Radionuclide (mrad /yr pefvcurie/sec) x (cutte)-
=,
-yr.'.s.
-~-
7 -- g 6.25E+di =
.2.65E+04'#
Xe-133 4.24E+02 x
Xe-135 2.30E+03 x 2.24E-01 =
J.15E+02.
Xe-131m 1.87E+02 x 6.71E-02 N el.25E+01'
'~
~'
Xe-133m 3.92E+02 x 3.81E-02 1.49E+01
=
IM x.
2.70E+04 Q
=
iV iV P
e P
i
\\
l Dg = 3.17E-08 yr mrad'-sec mrad-sec
[1.88E+06
-+ 2.70E+04
]
see yu yr s
.w
~
j j'
(*c w
Dg = 6.05E-02 mrad
./
4-
~
j
.e, t
j 4 o ',
w Jc
^
/,_,
p'j?
e --
_e 3
3.4 A similar approach could be 'taken zo,calcuh..te. f)h_.,
m
.i
^%
_N l
~~
e
( _
p, u.) '
t s
/
,G*,
- [}
,f r. l,
fh
~ ~. -
. r;_
- J l7 '
- >J L'*
t' ~ ',
~,
j, I
i J
T
[
~
,e
(,
4 f
- f
~
' j'
~
~
y e
,i f
)
' I
/
.r i e
's
- 'f 1
J r
/
/
v, a
h
. e,'
n*
r f
q w
,o 1,
/
-?
/)
7
.e o w
/
I r
I i '
e I
f L ',
HP-0DCM-9
', ', ', 24,
4 *:
Pzga 1 of S
- m,,-
p 1-
,g gh
~
NORTH ANNA POWER STATION g
- ~,
')
OFFSITE DOSE CALCULATION MANUAL
~
e s
i s
SECTION 9 Iodine - 131. Tritium, and Radionuclides in Particulate Form Gaseous Effluent Dose Limits Part Subject Pm
,1 Technical Specification Requirement 2
2 Calculation 2
3 Example 3
i
). V
'+
i l
l 6
I I
l l
HP-0DCM-9 Pcgs 2 of 5 1.
TECHNICAL SPECIFICATION REQUIREMENT Technical Specification 3.11.2.3 requires that: "The dose to the maximum exposed MEMBER OF THE PUBLIC from iodine-131, from tritium, and from all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released, from each reactor unit, from the site to UNRESTRICTED AREAS (see Figure 5.1-3) shall be limited to the following:
a.
During any calendar quarter: Less than or equal to 7.5 mrems to the critical organ, and i
b.
During any calendar year: Less than or equal to 15 mrems to the critical organ".
2.
CALCULATION 2.1 The dose to the maximum exposed MEMBER OF THE PUBLIC from iodine-131, from tritium, and from all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents from the site to areas at and beyond the SITE B0UNDARY shall be determined as follows:
Dr = 3.17E-08 I [R k
+R ki V]
IVV IVV PV P
i where:
Subscripts =
vv, refers to vent releases from the building ventilation vent; pv, refers to the vent releases from the process vent; the dose to the critical organ of the maximum Dr
=
exposed MEMBER OF THE PUBLIC in mrem; I
R R
the dose factor for ventilation vent or process
=
- IVV, iV P
vent release due to iodine-131, tritium, and from all radionuclides in particulate form with half-lives greater than 8 days, in mrem /yr per l
3 Curie /sec. Factors are listed in Table 9.0; k
D the release for ventilation vent or process vent
=
- IVV, iPV of iodine-131, tritium, and from all radionu-clides in particulate form with half-lives
~
greater than 8 days in Curies (per site);
3.17E-08 the inverse of the number of seconds in a year.
=
2.2 All gaseous releases, not through process vent, are c nsidered ground level and shall be included in the determination of fyy.
HP-0DCM-9 Page 3 of 5 3.
EXAMPLE o
3.1 Compilation of data from release records for the process vent for a quarter provides the following information:
Radionuclide Activity Released (Curies) 1-131 7.20E-04 H-3 2.45E-01 Co-58 1.10E-06 3.2 Compilation of data from release records for the ventilation vent for a quarter provides the following information:
Radionuclide Activity Released (Curies)
I-131 6.48E-03 H-3 2.21E+00 Co-58 9.90E-05 3.3 The dose to the critical organ of the maximum exposed MEMBER OF THE PUBLIC is calculated from:
Dr = 3.17E-08 I (R h
+R hg y]
fy gy The appropriate values of R and R shall be obtained from Table gyy gy p
9.0.
R h
(mrem-sec)
Radionuclide (mrem /yrphE# Curie /sec) x (Cubles) yr
=
I-131 1.45E+09 x 6.48E-03 9.40E+06
=
3.82E+03 H-3 1.73E+03 x 2.21E+00
=
x 9.90E-05 Co-58
=
IR Qgyy 9.40E+06
=
gyy Due so Jack of information, according to Regulatory Guide 1.109, Rev. 1 Co-58 is not included in these calculations.
R h
(mrem-sec)
(CubSes)
Radionuclide (arem/yrpeE# Curie /sec) x yr
=
4.77E+05 I-131 6.63E+08 x 7.20E-04
=
H-3 9.36E+02 x 2.45E-01 2.29E+02
=
Co-58 x 1.10E-06 gyhyy 4.77E+05 IR
=
p p
HP-0DCM-9 Page 4 of 5 Dr = 3.17E-08
[9.40E+06 mrem-sec + 4.77E+05 y
Y#
mrem-sec see yr yr Dr = 3.13E-01 (mrem)
[
l l
l
\\
i l
l l
i 1
I
HP-0DCM-9 Page 5 of 5 TABLE 9.0 CRITICAL PATHWAY DOSE FACTORS FOR NORTH ANNA POWER STATION l
UNIT NOS. 1 AND 2
-2 Ventilation Vent D/Q = 2.4E-09 m at 3250 Meters N Direction
-2 Process Vent D/Q = 1.lE-09 m at 3250 Meters N Direction R
R Radionuclide arkEn7yr erE7yr Curie /sec Curie /sec H-3 1.73E+03 9.36E+02 Mn-54 ND ND Fe-59 ND ND Co-58 ND ND Co-60 ND ND Zn-65 ND ND Rb-86 ND ND Sr-89 ND ND Sr-90 ND ND Y-91 ND ND Zr-95 ND ND Nb-95 ND ND Ru-103 ND ND Ru-1C6 ND ND Ag-110m ND ND Te-127m 1.97E+05 9.04E+04 Te-129m 2.95E+05 1.35E+05 I-131 1.45E+09 6.63E+08 e
Cs-134 ND ND Cs-136 ND ND Cs-137 ND ND Ba-140 ND ND Ce-141 ND ND Ce-144 ND ND h3 - No data for dose factor according to R.G. 1.109, Rev. 1.
.. = _.
HP-0DCM-10 Pags 1 of 5 NORTH ANNA POWER STATION i
0FFSITE DOSE CALCULATION MANUAL SECTION 10 Gaseous Effluent Dose Projections Part Subject Pg 1
Technical Specification Requirement 2
2 Projected Gamma Dose 2
3 Projected Beta Dose 2
4 Projected Maximum Exposed MEMBER OF THE PUBLIC Dose 2
f Example 3
i
HP-0DCM-10 Page 2 of 5 1.
TECHNICAL SPECIFICATION REQUIREMENT Technical Specification 3.11.2.4 requires that: "The CASE 0US RADWASTE TREATMENT SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected gaseous effluent air doses due to gaseous effluent releases, from each reactor unit, from the site to areas at or beyond the SITE BOUNDARY (see Figure 5.1-3) would exceed 0.2 mrad for gamma radiation and 0.4 mrad for beta radiation over 31 days.
The VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses due to gaseous effluent releases, from each reactor unit, from the site to areas at and beyond the SITE BOUNDARY (see Figure 5.1-3) would exceed 0.3 mrem to the critical organ over 31 days".
2.
PROJECTED CAMMA DOSE 2.1 Determine Dg = the 31 day gamma air dose in the previous 31 day period calculated according to H.P.-0DCM-8.
2.2 Estimate Rg = ratio of the volume of gaseous effluent in the present 31 day period to the volume released during the previous 31 day period.
2.3 Estimate Fg = ratio of the estimated noble gas effluent activity in the present 31 day period to the noble gas effluent activity during the previous 31 day period.
I 2.4 Determine PD = projected 31 day gamma air dose 8
g (R F)
=D g
g g i
3.
PROJECTED BETA DOSE 3.1 Determine D = the 31 day beta air dose in the previous 31 day h
period, calculated according to H.P.-0DCM-8.
3.2 Estimate R and F as in Steps 2.2 and 2.3 above.
g g
3.3 Determine PDb " Projected 31 day period beta air dose l
j PD =Db (R F) b 4.
PROJECTED MAXIMUM EXPOSED MEMBER OF THE PUBLIC DOSE 4.1 Determine D
= the 31 day maximum exposed MEMBER OF THE PUBLIC dose in t$e** previous 31 day period, calculated according to l
H.P.-0DCM-9.
4.2 Estimate F = ratio of the estimated activity from
.-131, radio-active materials in particulate form with half-lives greater than 8 days, and tritium in the present 31 day period to che activity of I-131, radioactive materials in particulate fore with half-lives greater than 8 days, and tritium in the previous 31 day period.
HP-0DCM-10 Page 3 of 5 4.3 Determine PD
= projected 31 day maximum exposed MEMBER OF THE PUBLIC dose. "**
D (R F)
=
g Historical data pertaining to the volumes and radioactive concentrations of gaseous effluents released in connection to specific station functions, such as containment purges, shall be used in the above estimates as appropriate.
5.
EXAMPLE 5.1 Compilation of data from release records for the process vent in a 31 day period provides the following information:
Noble Gas Radionuclide Activity Released (Curie)
I Xe-133 2.08E+01 Xe-135 7.47E-02 Xe-131m 2.24E-02 Xe-133m 1.27E-02 5.2 Compilation of data from release records for the ventilation vents in a 31 day period provides the following information:
Noble Gas Radionuclide Activity Released (Curie)
Xe-133 1.87E+02 Xe-135 6.73E-01 Xe-131m 2.01E-01 Xe-133m 1.14E-01 5.3 The air dose for gamma radiation is calculated according to H.P.-0DCM-8 from:
D = 3.17E-08 I [M Q
+M Qg y]
gy p
g gyy gyy p
The appropriate values of M and M are obtained from Tables 7.0 gy gyy p
and 7.1.
Noble Gas M
Q (mrad-sec)
(CbEle)
Radionuclide (mrad /yrphE# Curie /sec) x yr
=
6.13E+05 Xe-133 3.28E+03 x 1.87E+02
=
1.20E+04 Xe-135 1.79E+04 x 6.73E-01
=
2.91E+02 Xe-131m 1.45E+03 x 2.01E-01
=
3.47E+02 Xe-133m 3.04E+03 x 1.14E-01
=
IM igyy 6.26E+05
=
gyy i
HP-0DCM-10 Page 4 of 5 Noble Gas M
Q (mrad-sec)
(CbEle)
Radionuclide (mrad /yr pee # Curie /sec) x
=
yr Xe-133 4.24E+02 x 2.08E+01 8.82E+03
=
Xe-135 2.30E+03 x 7.47E-02 1.72E+02
=
Xe-131m 1.87E+02 x 2.24E-02 4.19E+00
=
Xe-133m 3.92E+02 x 1.27E-02 4.98E+00
=
9.00E+03 IM Q
=
fpy 1py I
Y#
mrad-see mrad-sec Dg = 3.17E-08
[6.26E+05
+ 9.00E+03
)
see yr yr Dg = 2.01E-02 mrad 5.4 Total volume of gaseous effluent released in 31 day period is:
31 day average flow 31 day average flow rate "I"
4.46E+04 rate (CFM) for
+
(CFM) for ventilation x
31 day process vent vents A and B Total Volume (ft ) = (295 CFM + 120,000 CFM) x 4.46E+04 Total Volume (ft ) = 5.37E+09 i
3 l
Estimated total volume in 31 day period = 4.46E+09 (ft )
1 Therefore, Rg = 4.46E+09 - 0.83 5.37E+09 l
5.5 The total activity released in 31 day period is:
1 31 day process vent
+
31 day ventilation vent A + B total activity (Curies) total activity (Curies) b Total activity released = (2.09E+01 Curies + 1.88E+02 Curies)
Total activity released = 2.09E+02 Curies Estimated total activity released = 2.50E+02 Curies Therefore Fg = 2.50E+02 = 1.20 2.09E+02 g
HP-0DCM-10 Pegs 5 of 5 5.6 The projected 31 day gamma air dose is:
8 (Rg Fg)
=D 8
PD = 2.01E-02 mrad x 0.83 x i,20 g
PD = 2.00E-02 mrad 8
l l
l n
HP-0DCM-11 Page 1 of 2 NORTH ANNA POWER STATION OFFSITE DOSE CALCULATION MANUAL SECTION 11 Total Dose Part Subject
_Page 1
Technical Specification Requirement 2
2 Calculation 2
HP-0DCM-11 P ge 2 of 2 1.
TECHNICAL SPECIFICATION REQUIREMENT Technical Specification 3.11.4 requires that: "The annual (calendar year) dose or dose commitment to the maximum exposed MEMBER OF THE PUBLIC, due to releases of radioactivity and radiation, from uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the total body or any organ (except the thyroid, which shall be limited to less than or equal to 75 mrems)".
2.
CALCULATION Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with the methodology presented in H.P.-0DCM Sections 4, 8, 9, or Regulatory Guide 1.109, Rev. 1 (see Appendix B).
b
<---n-
H?-0DCM-12 Page 1 of 2 NORTH ANNA POWER STATION OFFSITE DOSE CALCULATION MANUAL SECTION 12 Semiannual Radioactive Effluent Release Report Dose Assessment Part Subject g
1 Technical Specification Requirement 2
2 Dose Assessment 2
i
)
l
HP-0DCM-12 Page 2 of 2 1.
TECHNICAL SPECIFICATION REQUIREMENT Technical Specification 6.9.1.12 requires that the Semiannual Radioactive Release Report submitted within 60 days af ter January 1 of each year include, in part, an assessment of the radiation doses to individuals due to the radioactive liquid and gaseous effluents from the station during the previous calendar year, and an assessment of the radiation doses to the maximum exposed MEMBER OF THE PUBLIC from reactor releases and radiation.
2.
DOSE ASSESSMENT 1.
The radiation doses to individuals due to the radioactive liquid and gaseous effluents from the station during the previous calendar year shall be calculated using the methodology presented in this Manual or in Regulatory Guide 1.109 (Revision 1), October 1977, "Calcula-tion of Annual Doses to Man from Routine Releases of Reactor Efflu-ents for the Purpose of Evaluating Compliance with 10CFR Part 50, Appendix I"
(see Appendix B).
Population doses are not to be included in the dose assessment.
2.
The dose to the maximum exposed MEMBER OF THE PUBLIC due to the radioactive liquid and gaseous effluents from the station shall be incorporated with the dose assessment performed above.
If the dose to the maximum exposed MEMBER OF THE PUBLIC exceeds twice the limits of Specification 3.11.1.2.a.
3.11.1.2.b, 3.11.2.2.a.
3.11.2.2.b, 3.11.2.3.a. or 3.11.2.3.b, the dose assessment shall include the contribution from direct radiation.
U.S.
Nuclear Regulatory Commission NUREG-0543, February 1980, " Methods for Demonstrating LWR Compliance With. the EPA Uranium Fuel Cycle Standard (40CFR Part 190)", states "There is reasonable assurance that sites with up to four operating reactors that have releases within Appendix I design objective values are also in conformance with the EPA Uranium Fuel Cycle Standard, 40CFR Part 190".
3.
The meteorological conditions during the previous calendar year or historical annual average atmospheric dispersion conditions shall be used for determining the gaseous pathway doses.
l 6
l l
l l
HP-ODCM-13 PIga 1 of 8 NORTH ANNA POWER STATION OFFSITE DOSE CALCULATION MANUAL SECTION 13 Radiological Environmental Monitoring Locations Part Subject Pm 1
Radiological Environmental Sampling Stations 2
2 Figures 9
e
HP-0DCM-13 Pegn 2 of 8 1.0 RADIOLOGICAL ENVIRONMENTAL SAMPLING STATIONS Exposure Pathway Sample and/or Sample (Station) Number Location Airborne:
Particulate &
Radioiodine 1
air sampler is mounted on the weather tower's first landing across from the main Security Building, behind "B"
parking lot on site 2
air sampler is mounted on the power pole approximately 200 yards East from the fork of Rt. 618 & 614 on Rt. 618 on the North side approx.
100 feet from the road 3
air sampler is mounted on the power pole in Mineral approx.
200 feet off Rt.
618 on Albermarle Street behind the house on the corner 4
air sampler is mounted on power pole approx. 100 feet behind store at Rt. 522 & 613 5
air sampler is mounted on the power pole approx. 150 feet East of B. Brook's home on Rt.
752 off of Rt.
208 on the North side of the road 5A air sampler is mounted on the power pole off Rt. 208 approx.
200 feet from the entrance of Sturgeon's Creek Marina on f
right 6
air sampler is mounted on the power pole off Rt. 601 on Rt.
622 across road from R. L.
Carlic's home, approx. 25 feet from the road 7
air sampler is mounted on the power pole approx. 175 feet behind the Bumpass Post Office at the fork of Rt. 601 8 618
HP-0DCM-13 Page 3 of 8 l
Exposure Pathway Sample and/or Sample (Station) Number Location Airborne (cont'd):
Particulate &
Radioiodine (cont'd) 21 air sampler is mounted on the power pole at the end of Rt.
685 at the barricade, approx.
1.5 miles from the junction of Rt. 652 & 685 22 air sampler is mounted on the power pole approx. 0.8 miles from North Anna's Visitor's Center, West on Rt.
700, at the exclusion area boundary on the West side of Rt. 700 23 air sampler is mounted on the power pole approx.
25 feet from the shoreline, inside the exclusion area
- boundary, located on lot #34 on Carr Circle in the Aspen Hill subdivision 24 (control) air sampler is mounted on top of the Orange Va Regional Vepco Office Building approx.
1 mile South of the junction of Rt. 20 & 15 on the right Soil 1,3,4,5,6,7, Previously Identified 21,22,23,24 Direct:
TLDs 1
is located at Bearing Cooling Tower on stairwell structure approximately 150 feet from Vepco security building on Vepco North Anna Power Station site 2
is located on power pole approximately 200 feet from entrance of Sturgeon's Creek Marina off Rt. 208 3
is located on Vepco North Anna Power Station site at rain gauge in construction parking lot "C" near weather tower
HP-0DCM-13 Page 4 of 8 Exposure Pathway Sample and/or Sample (Station) Number Location Direct (cont'd):
TLDs (cont'd) 4 is located on a power pole at Good Hope Church at the intersection of Rt.
208 and Rt. 601 5
is located on weather tower across from security building and behind Vepco's parking lot "B"
l 6
is located off Rt. 601 on Rt.
713 at Lake Anna Marina entrance on power pole 7
is located on island across from training facility on weather tower fence 8
is located on power pole at entrance of Rt. 689 off Rt.
601 on left 9
is located on island across from training facility on back of Vepco's Security obstacle course ladder 10 is located on 500 Kv Vepco power line off Rt.
601 at
" Morning Glory Hill":
near home of J. R. Humphries 11 is located on island after crossing dike from Vepco "A"
parking lot on first power pole approximately 0.1 mile from island entrance i
12 is located on a power pole on Rt. 622 off Rt. 601 across the road from R. L. Garlic's home, l
approximately 25 feet from the j
road i
13 is located on island across from Vepco training facility at Vepco Biology Lab entrance gate 14 is located at entrance to Dam off Rt.
601 at intersection with Rt. 701
=
r HP-0DCM-13 Pegn 5 of 8 Exposure Pathway Sample and/or Sample (Station) Number Location Direct (cont'd):
TLDs (cont'd) 15 is located on power pole approximately 25 feet from the shoreline on Lot #34 on Car Circle in the Aspen Hill subdivision 16 is located on power pole at intersection of Rt.
614 and Rt. 652 at Elk Creek l
17 is located on entrance to warehouse compound on gate 0.35 miles from Vepco main security building 18 is located on power pole at Rt. 614 intersection with Rt.
652 approximately 1/2 mile from Elk Creek Church 19 is located on light pole along Vepco site access road approximately 0.7 mile from Vepco main security building l
i 20 is located on a power pole approximately 200 yards from the fork of Rt. 618 and Rt.
614 on Rt.
618 North side approximately 100 feet from the road 21 is located on light pole on Vepco North Anna Power Station site access road approximately 0.85 miles from Vepco main Security Building g
22 is located on power pole approximately 2.5 miles from intersection of Rt.
652 and Rt.
700 exiting North Anna Power Station at abandoned house and dumpster site 23 is located on first power line (500 kv) upon entering Vepco North Anna Power Station site to right off Rt. 700
HP-0DCM-13 Pags 6 of 8 Exposure Pathway Sample and/or Sample
_(Station) Number Location Direct (cont'd):
TLDs (cont'd) 24 is located on a power pole approximately 0.8 miles from North Anna Power Station Visitor's Center, West on Rt.
700 25 is located at North Anna Power Station radio tower approximately 0.15 East on Rt.
700 from Visitor's Center entrance 26 is located on power pole on Rt.
685 off Rt.
652 approximately 1.0 miles from intersection at abandoned trailer 27 is located at power pole at the end of Rt.
685 at-barricade, approximately 1.5 miles from the junction of Rt.
652 and Rt. 685 28 is located on a power pole at the end of H. Purcells' private road off Rt. 685 29 is located past Unit I and 2 intake at end of road on transformer fence on North Anna Power Station site 30 is located on a power pole at Lake Anna Campground on Rt.
208 1
31 is located on fence near Unit 1 and 2 intake structure on North Anna Power Station site 32 is located approximately 3.3 i
miles from intersection of Rt.
l 652 and 208 going East on light point at Sam Hairfield i
and Bro. Store on Rt. 208 C-1/2 are located on a power pole approximately 175 feet behind the Bumpass Post Office at the fork of Rt. 601 and 618
HP-0DCM-13 Page 7 of 8 Exposure Pathway Sample and/or Sample (Station) Number Location Direct (cont'd):
TLDs (cont'd)
C-3/4 are located on the top of the Orange Va Regional Vepco Office Building approximately 1 mile South of the junction of Rt. 20 and Rt. 15 on the right C-5/6 are located in Mineral on a power pole approximately 200 feet off Rt. 618 on Albemarle Street behind the house on the corner C-7/8 are located on power pole at Glen Marye Shopping Center in Louisa Water Borne:
a.
Surface 8
sampled from 2nd lagoon on discharge 9
sampled from lake near Rt. 208 bridge 11 sampled from river just below dam b.
Ground 1A sampled from well at North Anna Power Station's Biology Lab on island across from discharge canal Aquatic:
Sediment 8,9,11 Previously Identified fngestion:
a.
Milk 12 milk sample from the farm of Mr. R. C. Goodwin, approx. 0.5 miles East on Rt. 612 off Rt.
522 13 milk sample from the farm of Mr. Verling, approx. 0.5 miles West on Rt.
618 past Fredericks
- Hall, on gravel road across railroad tracks
HP-0DCM-13 Page 8 of 8 Exposure Pathway Sample and/or Sample (Station) Number Location Ingestion (cont'd):
14 milk sample from the farm of Mr. R. L. Trice, approx. 1.75 miles South of Rt. 652 on Rt.
614. West side b.
Fish 8,9 Previously Identified c.
Food Products 21,23 Previously Identified 3
FIGURE 13.0
[
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/D ENVIRONMENTAL
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EP-0DCM-A Pagt 1 of 1 NORTH ANNA POWER STATION OFFSITE DOSE CALCULATION MANUAL I
Appendix A Section Date A1.
Meteorological Analysis A2.
Liquid Pathway Analysis A3.
Gaseous Pathway Analysis
)
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1
' EP-ODCM-Al'
(.
Page 3 of 3 i
V s
t NORTH ANNA POWER STATION
{
OFFSITE DOSE CALCULATION MANUA_L_
\\
d s \\[
s
(
ts t
3 Sectica Al Meteorological Analysis 1
Part Subject
. P.a ge.
1 Purpose 2>
i 2
Meteorological Cata, Parameters, and s
Methodology
(
2 3
Results 3
(
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HP-0DCM-Al Pegt 2 of 3 1.
PURPOSE The purpose of the meteorological analysis was to determine the annual average X/Q and D/Q values at critical locations around the station for yentilation vent (ground level) and process vent (mixed mode) releases.
The annual, average X/Q and D/Q values were used in performing a dose pathway analysis - to determine the maximum exposed individual at SITE BOULDARY and MDGER OF THE PUBLIC.
The X/Q and D/Q values resulting in the maxivm exposures were incorporated into the dose factors in Tables 7.0, 7.1, 7.2, and 9.0.
s 2.
METEOROLOGICAL DATA, PARAMETERS, AND METHODOLOGY Onsite meteorological data for the period January 1, 1981 through s,
December 31, 1981 was used in-calculations.
This data included windspeed, wind direction, and differential temperature for the purpose of determining joint frequency distributions for those releases characterized as. ground level (e.g.
ventilation vent),
and those characterized as mixed mode (i.e. process vent). The portions of release characterized as ground level were based f on AT158.9ft-28.2ft and 28.2 foot wind data, an( the portions characterized as mixed mode were based on AT158.9ft-28.2ft and 158.dft wind data.
X/Q's and D/Q's were calculated using the NRC computer code "XOQD0Q -
Program for the Meteorological Evaltation of Rc'utine Effluent Releases at Nuclear Power Stations", Sep' 1977.
The code is based upon a straight line airflow model
.senting the ' assumptions outlined in Section-C (excluding Cla and Clbf of Regulatory Guide 1.111. " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Feleases from Light - Water - Cooled Reactors".
The opNn terrain adjustment factors were applied to the X/Q values as I
recommended in Regulatory sGuide 1.111.
The sitairegion is characterized by gently rolling terrainisuch that~ opea terrain correction factors are considered appropriate.
The ground 1.pel ventilation vent releasg i -
calculations included a building wake ' correction based on a 1516m containment minimum cross-stictional area.( The ef fective release height used in mixed mode release calculations War based on a process vent release hiight of 157.5 ft,' and plume rise due to momentum for a vent diameter of 3 in, with plume exit velocity of 100 f t/sec.
Ventilation
(
vent, and vent releases other than from the process vent, are considered ground level as specified in Regulatory Guide 1.111 for release points less than the height., of adjacent solid structures. ' Terrain elevations s'
were obtained from ' North Anna Power Station Unitt I and 2 Virginia Electric and Power Company Final Safety Analysis Report Table 11C.2-8.
.X/Q and D/Q values were calculated for the nearest site boundary, x
resident, milk cow, and vegetable garden by sector for process vent and ventilation vent releases at distances specified from North Anna Power Station Annual Environmental Survey Data for 1981. ;X/Q values were also calculaced for the nearest lake shoreline by sector for the process vent
~
and ventilation vent releases.
j s
(
~
+
f,
/
J HP-0DCM-Al 7
Page 3 of 3 According to tha definition for short term in NUREG-0133 " Preparation of Radiological Effluent l'e chnical Specifications for Nuclear Power Stations", October, 197E, some gaseous releases may fit this category, primarily waste gas decay tank releases and containment purges. However, these releases are considered long term for dose calculations as past releases were both random in time of day and duration as evidenced by reviewing past release reports. 'Therefore, the use of annual average concentrations is appropriate according to NUREG-0133.
,e The X/Q and D/Q values calculated frem 1981 meteorologi5al d'ata are comparable to the values presented in the North Anna Power Station UFSAR.
3.
RESULTS The X/Q value that resulted in the maximum total body, skin and 3
inhalation exposure for ventilation vent releases was 9.3E-06 sec/m at a site boundary location 1416 meters SE sector. 3 For process vent releases, the site boundary X/Q value was 1.2E-06 sec/m at a location 1513 meters S sector.
The shoreline X/Q value that resulted in the mgximum inhalation exposure for ventilation vent releases was 1.0E-04 sec/m at a location 241 mete 3s NNE sector. The shoreline X/Q value for process vent was 2.7E-06 sec/m at a location 241 meters NNE secto".
Pathway analysis indicated that the maximam exposure from iodine-131, and from all radionuclides in particulate form.with half-lives greater than 8 days was through the grass-cow-milk pathway.
The D/Q value from ventil tion vent releases resulting in the maximun exposure was 2.4E-09 f
a location 3250 metefs N sector.
For process vent releases, per m at the D/Q value was 1.1E-09 per m at a location 3250 meters N sector.
For tritium, the X/Q value from ventilation vent releases regulting in the maximgm exposure Ior the milk pathway was 7.2E-07 sec/m, and 3.9E-07 sec/m for process vent releases at a location 3250 meters N sector.
e
s HP-0DCM-A2 Paga 1 of 2 NORTH ANNA POWER STATION
'/
OFFSITE DOSE CALCULATION MANUAL SECTION A2 Liquid Pathway Analysis
/
Part Subject Ppge i
1 Purpose 2
2 Data Parameters, and Methodology 2
3 Results 2
1
'T k
t I
b
HP-0DCM-A2 Pcgt 2 of 2 1.
PURPOSE The purpose of the liquid pathway analysis was to determine the maximum exposed MEMBER OF THE PUBLIC in UNRESTRICTED AREAS as a result of radioactive liquid effluent releases.
The analysis includes a
determination of the most restrictive liquid pathway, most restrictive age group, and the critical organ.
This analysis is required for Technical Specification 3.11.1.2.
2.
DATA, PARAMETERS, AND METHODOLOGY Radioactive liquid effluent release data for the years 1979, 1980, and 1981 was compiled from the North Anna Power Station semi-annual effluent release reports.
The data for each year, along with appropriate site specific parameters and default selected parameters, was entered into the NRC computer code LADTAP as described in NUREG-0133, " Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants",
October 1978.
Reconcentration of effluents using the small lake connected to larger water body model was selected with the appropriate parameters determined from Table 3.5.3.5, Design Data for Reservoir and Waste Heat Treatment Facility from Virginia Electric and Power
- Company, Applicant's Environmental Report Supplement, North anna Power Station, Units 1 and 2, March 15, 1972.
Dilution factors for aquatic foods, shoreline, and drinking water were set to one.
Transit time calculations were based on average flow rates.
All other parameters were default selected by the LADTAP computer code.
3.
RESULTS For each year, the fish pathway resulted in the largest dose.
The critical organ each year was the liver, and the adult and teenage age groups received the same organ dose. However, since the adult total body dose was greater than the teen total body dose for each year, the adult was selected as the most restrictive age group. The dose factors in ODCM Table 4.0 are for the maximum exposed MEMBER OF THE PUBLIC, an adult, with the critical organ being the liver.
HP-ODCM-A3 Pcgs 1 of 5 NORTH ANNA POWER STATION OFFSITE DOSE CALCULATION MANUAL Section A3 Gaseous Pathway Analysis Part Subject P_ age 1
Purpose 2
2 Data, Parameters, and Methodology 2
b i
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-2..__---____-._._.._._--__.____----____1.2-_'_
HP-0DCM-A3 Page 2 of 5 1.
PURPOSE A gaseous effluent pathway analysis was performed to determine the location that would result in the maximum doses due to noble gases for use in demonstrating compliance with Technical Specifications 3.11.2.1.a and 3.11.2.2.
The analysis also included a determination of the critical pathway, location, of maximum exposed MEMBER OF THE PUBLIC, and the critical organ for the maximum dose due to iodine-131, tritium, and for all radionuclides in particulate form with half-lives greater than 8 days for use in demonstrating compliance with Technical Specifications 3.11.2.1.b and 3.11.2.3.
2.
DATA, PARAMETERS. AND METHODOLOGY Annual average X/Q values were calculated, as described in ODCM-A1, for the nearest SITE BOUNDARY in each directional sector and at other critical locations beyond SITE BOUNDARY.
The largest X/Q value was 3
determined to be 9.3E-06 sec/m at SITE BOUNDARY for ventilation yent releases at a location 1416 meters SE direction, and 1.2E-06 sec/m at SITE BOUNDARY for process vent releases at a location 1513 meters S direction.
The maximum doses to total body and skin, and air doses for gamma and beta radiation due to noble gases would be at these SITE BOUNDARY locations.
The doses from both release points are summed in ODCM calculations to calculate total maximum dose.
Technical Specification 3.11.2.1.b dose limits apply specifically to the j
inhalation pathway.
Therefore, the locations and X/Q values determined for maximum noble gas doses can be used to determine the maximum dose from iodine-131, tritium, and for all radionuclides in particulate form with half-lives greater than 8 days for the inhalation pathway.
The NRC computer code CASPAR, " Evaluation of Atmospheric Releases",
l Revised 8/19/77, was run using 1979, 1980, and 1981 North Anna Power l
Station gaseous effluent release report data.
Doses from iodine-131, l
tritium, and particulatfs for the inhalation pathway were calculated using the 9.3E-06 sec/m SITE BOUNDARY X/Q.
Except for the source term data and the X/Q value, computer code default parameters were used.
The i
results for each year indicated that the critical age group was the child and the critical organ was the thyroid for the inhalation pathway.
The gamma and beta dose factors Kivv. Livy, Mivy, and Nivv in 3
HP-0DCM-Table 7.0 were obtained by performing a units conversion of the appropriatedosefactgrsfromTableB-1,Regu}atoryGuide1.109,Rev. 1, to mrem /yr per Ci/m or mrad /yr per Ci/m, and multiplying by the ventilation vent SITE BOUNDARY X/Q value of 9.3E-06 sec/m.
The same l
approach was used in calculating the gamma and beta dose factors Kipy, l
Lipv, Mipv, and Nipv in HP-0DCM-Tgble 7.1 using the process vent SITE BOUNDARY X/Q value of 1.2E-06 sec/m.
The inhalation pathway dose factors P and P in HP-0DCM-Table 7.2 i
iV were calculated using the following equaYion:
P P = K' (BR) DFAg (X/Q) (arem/yr per Curie /sec) g
HP-0DCM-A3 Pegs 3 of 5 where.
K' =
a constant of unit conversion, IE+12 pCi/Ci; 3
BR =
the breathing rate of the child age group, 3700 m /yr, from Table E-5, Regulatory Guide 1.109 Rev. 1; the thyroid organ inhalation dose factor for child age group DFA
=
g for the ith radionuclide, in arem/pCi, from Table E-9 Regulatory Guide 1.109 Rev. 1; 3
X/Q =
the ventilation vent SITE BOUNDARY X/Q, 9.3E 06 sec/m, or the 3
process vent SITE BOUNDARY X/Q, 1.2E-06 sec/m as appropriate.
Technical Specification 3.11.2.3 requires that the dose to the maximum exposed MEMBER OF THE PUBLIC from iodine-131, tritium, and from all radionuclides in particulate form with half-lives greater 8 days be less than or equal to the specified limits.
Dose calculations were performed for an exposed MEMBER OF THE PUBLIC within SITE BOUNDARY UNRESTRICTED AREAS, and to an exposed MEMBER OF THE PUBLIC beyond SITE BOUNDARY at locations identified in the North Anna Power Station Annual Environmental Survey Data for 1981.
It was determined that the MEMBER OF THE PUBLIC within SITE BOUNDARY would be using Lake Anna for recreational purposes a maximum of 2232 hours0.0258 days <br />0.62 hours <br />0.00369 weeks <br />8.49276e-4 months <br /> per year.
It is assumed that this MEMBER OF THE PUBLIC would be located the entire 2232 hours0.0258 days <br />0.62 hours <br />0.00369 weeks <br />8.49276e-4 months <br /> at the lake shoreline with the largest annual X/Q of 1.0E-04 at a location 241 meters NNE sector.
The NRC computer code GASPAR was run to calculate the inhalation dose to this individual.
The CASPAR results were corrected for the fractional year the MEMBER OF THE PUBLIC would be using the lake.
Using the NRC computer code GASPAR and annual average X/Q and D/Q values obtained as described in HP-0DCM-A1, the MEMBER OF THE PUBLIC receiving the largest dose beyond SITE BOUNDARY was determined to be located 3250 meters N sector.
The critical pathway was the grass-cow-milk, the maximum age group was the infant, and the critical organ the thyroid.
For each year 1979, 1980, and 1981 the dose to the infant from the grass-cow-milk pathway was greater than the dose to the MEMBER OF THE PUBLIC within SITE BOUNDARY.
Therefore, the maximum exposed MEMBER OF THE PUBLIC was determined to be the infant, exposed through the
(
grass-cow-milk pathway, critical organ thyroid, at a location 3250 meters i
N sector.
l The R and R dose factors, except for tritium, in HP-ODCM-Table 9.0 were'c"alculatN"by multiplying the appropriate D/Q value with the following equation:
~A *h if l
R = K' QF (Uap)
F, (r) (DFL ) [fpfs + (1-fpfs)e le i
f g
Y Y,
L Ag + A, p
- where, K' ='
a constant of unit conversion, 1E+12 pCi/Ci; the cow's consumption rate, 50, in Kg/ day (wet weight);
Q
=
p
HP-0DCM-A3 Page 4 of 5 the infant milk consumption rate, 330, liters /yr; U
=
ap the agriculturag productivity by unit area of pasture feed Y
=
P grass, 0.7, Kg/m ;
theagrjeulturalproductivitybyunitareaofstoredfeed,2.0, Y
=
a in Kg/m ;
the stable element transfer coefficients, from Table E-1, F
=
Regulatory Guide 1.109, Rev. 1; r-fraction of deposited activity retained on cow's feed grass, 1.0 for radioiodine, and 0.2 for particulates; the thyroid ingestion dose factor for the ith radionuclide for DFL
=
g the infant, in mrem /pCi, from Table E-14, Regulatory Guide 1.109, Rev. 1; the decay constant for the ith radionuclide, in sec-A
=
g A
the decay constant for removal of agivity on leaf and plant
=
surfaces by weathering, 5.73E-07 sec (corresponding to a 14 day half-life);
the transport time from pasture to cow, to milk, to receptor, t
=
g 1.73E+05, in sec; the transport time from pasture, to harvest, to cow, to milk, t
=
h to receptor, 7.78E+06, in sec; f
fraction of the year that the cow is on pasture. 0.58
=
P (dimensionless), 7 months per year from NUREG-0597; f
fraction of the cow feed that is pasture grass while the cow is
=
s on pasture, 1.0 (dimensionless).
Parameters used in the above equation were obtained from NUREG-0133 and Regulatory Guide 1.109 Rev. 1.
Since the concentration of tritium in milk is based on the airborne concentration rather than the deposition, the following equation is used:
H-3 "
0 ap ( b -3) [0.75(0.5/H)] x X/Q m F
- where, R
=
a constant of unit conversion, IE+03 gm/kg; 3
H=
absolute humidity of the atmosphere, 8.0, gm/m ;
0.75 =
the fraction of total feed that is water; 0.5 =
the ratio of the specific activity of the feed grass to the atmospheric water;
=-
HP-ODCM-A3 Page 5 of 5 X/Q =
the annual average congentration at a location 3250 meters N sector, 7.2E 07 sec/m for ventilation vent releases, and 3
3.9E-07 sec/m for the process vent releases.
other parameters have been previously defined.
i i
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1 1
HP-0DCM-B NORTH ANNA POWER STATION OFFSITE DOSE CALCULATION MANUAL I
APPENDIX B h
)
1 e
'O D
1 0
Revision 1 Ih)g i
[
U.S. NUCLEAR RESULATORY COMMBSS60N October 1977 REGULATORYGUIDE
(
OFFSCE OF STANDAR02 DEVELOPMENT REGULATORY GUIDE 1.109 CALCULATION OF ANNUAL DOSES TO MAN FROM ROUTINE RELEASES OF REACTOR EFFLUENTS FOR THE PURPOSE OF EVALUATING COMPLIANCE WITH 10 CFR PART 50, APPENDIX I 3
(.'
b usmmc asoutarony oucas p g g p g. c, g y ;.;.
.L' '."1"."..*c'O '.* ".".*O".,"Z7"lll.","" *c*.'" "'"
- ,0 :'J.~:::" '"'Z"::"," ~ "" ~ *:::::.:l"0"?lll::
.~-.'-
it"O- -.
T.,:.~,.r :::::
I h.f.:--
ll:.~ 0:::':'.'.".".*'..t.
!.; ~.,::f ;.:-
- - - - - = ~ -
Z ".* T..'"
T.
" *lll" *'_*' " """"*" "4
_.'". :lr ll" " "" "
'**O '::"l "!" *"*
- "* **1l'c" E *.~:.T* is:si. ".*"". *:Mll".:.*.*T."-l*.?
l'l..'".'.~ *'"." *".".'" ~". ',:ll *. * "" ::':" ".J ":".".
4
(,
The substantial number of changes, in this revision has made it impractical to indicate the changes with lines in the margin.
~___________.____._______._______________________A____m._____
__m_
I
(
TABLE OF CONTENTS f.eg A.
I NTRODUCT I ON..................................................................... 1.109 1 S.
D I SCU5 510N....................................................................... 1.109 - 1 C.
REGULATORY P051 TION.................................
4............................ 1.109-2 1.
Dose s from Li qu i d E f fl uent Pe thunys......................................... 1.109-2 l
I a.
Pota bl e un ter.............................. ;........................... 1.109 - 2 I
b.
Aqua t i c Foods.......................................................... 1 :109 - 2 l
c.
Shoreline Deposits.....................................................
1.109-2 d.
I rr f ga ted Foods........................................................ 1.109 3 2.
Game and Beta Doses from Roble Esses Discharged to the Atmosphere..........
1.109-4 t
p..
Annual Gama Air Dose from Roble Gas Releases from Free-5tanding Stacks i
Mo re The n 80 Me ters High............................................... 1.109 4 l
b.
Annual Gasma Air Dose from All Other Gas Releases; Annual Seta Air Dose from All Noble Gas Releases............................................
1.109-5 c.
Annual Total Body Dose from Noble Gas Releases from Free-Standing Stacks More Than 80 Me te rs Hi gh............................................... 1.109-5 l
d.
Annual Skin Dose from Noble Gas Releases from Free-Standing Stacks More The n 80 Me t er s M 19h................................................... 1.109 -6 e.
Annual Total Body Dose from All Other noble Gas Releases...............
1.109-6 f.
Annual Skin Oose from All Other noble Gas Releases.....................
1.109-6
(
3.
Doses from Radfotodines and Other Redtonuclides Released to the Atmosphere.. 1.109-6 Annual Organ Dose from E ento the Ground 5erface.gternal Irredtation from Radionuclides Depostted a.
................................................ 1.109-7 b.
Annual Organ Dose from Inhalation of Radionuclides in Air..............
1.109-7 c.
Annual Organ Dose from Ingestion of Atmospherically Released Radionucitdes in Food..................................................
1.109-7 4.
In tegra ted Doses to the Popul a t ion.......................................... 1.109-8 5.
Summa ry of Sta f f Pos i tion................................................... 1.109 S 0.
199L DE NT AT I ON................................................................... 1.109 -8 APPEND!r A. IETH005 FOR CALCULATING 00$E5 TO MAN FROM LIQUID EFFLUENT PATlRIAY5........
1.109-11 1.
Genere11:ed Equatten for Calculating mediatten asse via Liquid Pathueys...... 1.109-11 Radionuclide Concentratten in Emironmental Media (C 1.109-11 Usa ge ( U,,)..........................................y !).........
a.
b.
................ 1.109-11 c.
SoseFacter(0g ).................................................... 1.109-11 2.
Eque t t ens for L f guid Pe t1 mays................................................ ' 1.109-12 a.
Potable unter........................................................... 1.109 12 b.
Aquet1c Foods...........................................................
1.109-12 c.
Dese from Shoreline Deposits............................................ 1.109-12
, d.
Sose from Foods Groun en Land with Centaminated Meter................... 1.109-15 E FERENCES FOR APPENDIX A.............................................................. 1.109-18 111 e
4w
_ -,. - =_ _
\\
l l
TABLE OF CONTENTS (Continued) hae APPEN0!I S. M LS FOR CALCULATING 00SES FRON NOBLE GASES DISCMARGED TO THE
. ATM 5 PHE R E........................................................................... 1.109 - 19 1.
Annual Gassna Air Dose from Noble Gas Releases from Free-Standing Stacks More Tha n 80 Meters Ni gh.................................................... 1.109 1 g 2.
Annual Gaasna Air Dose from All Other Noble Gas Releases and Annual Seta Ai r Dose f rom Al l Nobl e Ga s Releases......................................... 1.109-20 3.
Annual Total Body and Skin Doses from Noble Gas Effluents.................... 1.109-20 a.
Releases from Free-Standing Stacks More Than 80 Meters High............. 1.109-20 b.
A l l Ot her Re l ea se s...................................................... 1.109 22 REFERENCES FOR APPEND!I $............................................................. 1.109-23 APPENDit C. MLS FOR CALCULATING DOSES VIA AD0!TIONAL PATMdAYS FROM RAD 10100!NES-AND UTHER RADIDNU CL IDE 5 D] 5 CHARGE D TD THE ATN 5PHE RE.................................. 1.109-24 1.
Annual External Dose from Direct Exposure to Activity Deposited on the Ground P 1 a ne................................................................ 1.109 - 2 4 2.
Annual Dose free Inhalation of Radionuclides in Air.......................... 1.109-25 3.
Concentra tions of Ai rborne Rad i onoc11 des in Foods............................ 1.109-25 a.
Parameters for Calculating Nuclide Concentrations in Forage Produce, a nd L ea fy Vege ta bl es.................................................... 1.109-25 b.
Parameters for Calculating Nuclide Concentrations in M11k..............
1.109-27 c.
Parameters for Calculating Nuclide Concentration in Meat................ 1.109-28 4.
Annual Dose from Atmospherically Released Radionuclides in Foods.............
1.109-28 REFERENCES FOR APPENDIX C..........
.................................................. 1.109-29 APPENDTI D. DODELS FOR CALCULATING PO P,ATION DOSES FROM' NUCLEAR POWER PLANT EFFLUENT..............................................................................
1.109-30 1.
General Expressions for Population Dose...................................... 1.109-30 2.
Use of the Models............................................................ 1.109-33 a.
Population-Integrated Doses from Liquid Effluents....................... 1.109-33 l
b.
Populattan-Integrated Doses from Airtorne Effluents.....................
1.109-34 RE FE RE NCE FOR APPEW i X D............................................................... 1.109-35 APPEND!I E. NUMERICAL DATA FOR THE CALCULATION OF Af88UAL DOSES TO MAN FROM NOUTINE RE L EA5E5 0F RE ACTDR EFFL UL wa........................................................
- 1. 109-M i
1.
Environmental Data..........................................................
1.109-M iE*
2.
Numa n Da ta................................................................. 1.109-M L.
l!
3.
Dese Factors................................................................. 1.109-36 4.
Other Parameters............................................................. 1.109-43 g
REFERENCES FOR APPENDIX E.............................................................. 1.109-70 i
1 l
iv I
l
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l
TEE OF CarTDIT3 (Continued) f1E MMOII F. IETH005 POR EVALUAfinE TE I FWICTION...................................... 1.109-72 1.
Seri vat t en of the I Function................................................. 1.109-72 2.
Evaluetten of the I Functfen.................................................. 1.109-75 N FE ttuCE S FOR APPDID i I F...............................................................
i 9
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b e-V l
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I LIST OF TABLES Table h
1 senary of Staff Position - Nothods of Evaluating Compliance with Appendix I..................................................................
1.109-9 A-1 Bioaccoulation Factors To Se used in the Absence of 5tte-5pecific Data.......
1.109-13 A-2 Shore. Width Factors for Use in Equations (A-5). (A-6), and (A-7)..............
1.109-15 B-1 Dose Factors for Exposure to a Semi-Infinite Cloud of Noble Gases.............
1.109-21 0-1 Recommended Values for the Transport Times in the Food Distribution System....
1.109-32 E-1 Sta bl e El ement Tra n s fer Da ta.................................................. 1.109-37 E-2 Nucl ide Trans fer Parameters for Gr,at's M11 k................................... 1.109'-38 E-3 Animal Cons eption Rates......................................................
1.109-38 Site-5pecific Data......U.To Be Used for the Average Individual in lieu of E-4 Reconnended Values for U 1.109-39 E-5 Reconnended Values for Usp To Be Used for the Maximum Exposed Individual in l i eu o f S i te-S pec i f f r. Da ta.................................................... 1.109-40 E-6 External Dose Factars for Standing on Contaminated Ground................'.....
1.109-41 E-7 Inha l a t i on Do se Fa c tors for Adu1 t s............................................ 1.109-44 E-8 Inhalation Dose Factors for Teenagers.....................................'....
1.109-47 E-9 Inhalation Dose Factors for Ch11dren..........................................
1.109-50 E-10 Inhalation Dose Factors for Infants...........................................
1.109-53 E-11 Ingestion Dose Factors for Adu1ts.............................................
1.109-56 E-12 I nge st i on Do se Fa ctor s for Teenagers.......................................... 1.109-59 E-13 Ingestion Dose Factors for Ch11dren...........................................
1.109-62 E-14 Ingestion Dose Factors for Infants............................................
1.109-65 E-15 Recommended Val ues for.0t her Pa rame ters....................................... 1.109-68 LIST OF FIGURES Fleure f.12L t>
Sta f f-Wri tten Computer L1 sting............................................. 1.109-76 f
Namavi-Wri tten Computer L1 s ting............................................ 1.109-78
\\.
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l A.
INTR 15UCTI1BI Appendix !. "Ihmerical Guides for Design Objectives and Lietting Conditions for*0peration tieter-Cooled aluclear power Reactor Effluents,g Achievable' for Radioactive letterial in Light-to 10 CFR part 50 provide to itset the Criterion 'As Low As Is Reasonabl radioactive effluent design eWectives and technical specification requirements for limiting conditions of operetten for light-meter-cooled nuclear power plants.
To tuplement Appendix !. the 1stC staff bas developed a series of guides that provide methods
. acceptable to the staff for the calculation of preoperational estimates of effluent releases, dispersion of the effluent in the atmosphere and different unter bodies, and estimation of the associated radiation doses
- te man. This guide describes basic features of these calculational models and suggests parameters for the estiaation of radiation doses to man from effluent releases.
W methods used herein are general approaches that the istC staff has developed for application in lieu of specific parameters for individual sites. The use of site-specific values by the applicant is encouraged. tiewever, the asseptions and methods used to obtain these parameters should be fully described and docuented.
portions of this (utde supersede Regulatory Guide 1.42. Revision 1. "Interia Licensing policy on as Low as practicable for Gaseous Radiolodine Releases free Light-Water-Cocied fluclear Power Reactors." which has been withdrawn.
B.
DISCU551001 Appendix ! to 10 CfR part 50 provides guidance en the doses to anseers of the general pubite resulting from effluent releases that may be considered to be as low as is reasonably achievable. This guide describes basic features of the calculations 1 models and assaptions in use by the IntC staff for the estination of doses.
Appendix A of this guide describes suggested models and assmetions for calculating the
(
estimated doses to een from discharges to the ltydrosphere. Appendix B of this guide describes suggested models and assumptions for calculating doses from noble gases discharged to the atmos-phere, and Appendix C gives models and ass eptions for estimating doses from radiciodines and other radionuclides released to the atmosphere. Appendix D describes the models and assumptions for calculating population doses (aan-ree and man-thyroid-rea) from radionuclide releases to the atmosphere and hydrosphere. Appendix E presents tabular data pertaining to two or more e' the other appendices. Appendix F provides a discussion of, and derivation for, the I function used in computing gamma doses from elevated noble pas releases.
In providing guidance for taplementing Section II of Appendix I the IstC staff has ande use of the mentaum exposed individual approach. In this approach the neerical design objectives of section II are compared to the calculated radiation exposures to maniam individuals in each of four age groups, h population is considered to be ande up of infants (0 to 1 year), children (1 to 11 years).
teenagers (11 to 17 years). and adults (17 years and older). For the purpose of evaluating dose cosaiternt, the maximum infant is assumed to be newborn, the manies child is taken to be 4 years old. the maximum teenager is taken to be 14 years old, and the annimum adult is taken to be 17 years old.
Ilantes individuals are character 1:ed as 'inanimum" with regard to food conseption, occupancy, and other usage of the region in the vicinity of the plant site and as such represent individuals with habits representing reasonable deviations from the average for the population in general.
In all physiological and metabolic respects the maxim o exposed individuals are ass med to have those characteristics that represent the averages for their corresponding age group in the general "In this guide. the term " dose." when applied to individuals is used instead of ths more precise terut " dose equivalent." as defined by the International Cennission on Radiological Units and IIsasureaants (ICRU). When applied to the evaluation of internal deposition of radioactivity.
the term " dose." as used here. Includes the prospective dose component arising free retention coenitment is evaluated over a period of 50 years.
~
The dose in the body beyond the period of enviromental exposure. i.e. the dose commitment.
(.
1.109-1
population. Although specific individuals will almost certafr.ly display dietary, recreational, and other Itving habits considerably different from those suggested here. and actual physfological and metabolic parameters may very considerably, the imC staff considers the mantes exposed individual to be a well-defined reference for tuplementation of Section !! ef Appendia I.
The characterf astion of mantas esposed individuals is subject to continuing review ty the IstC staff.
I and the app 1(cant is encouraged to use inforestion and data applicable to a specific region or site when possible. leiere site-spectffc information and data is used. Its justification should be documented for the IRC staff's review.
$1nce the radiation dose commitment per unit intake of a given radionucifde vsually varies as a function of age, four sets of internal dose conversten factors have been calculated. These dose factors are appropriate for the four different age groups deffned above.
Specifically these dose factors are based on continuout intake over a one-year anytrennental exposure per,iod and an associated dose con =*Nt estanding over a 50-year period fras initiation of fntake.
The models and assuptions descrfbed in Appendices A. S. C. and D of this guide are accept-able to the IRC staff for calculating doses to individuals and populations. If other andels are selected, they should include the same exposure pathwhys considered in the models described in this guide. The assumptions and methods used should be fully described and doceented.
As discussed in section !!!.A.2 of Appendix ! to 10 CFR part 50, the applicant may take into account any real phenomena or actual esposure conditions. Such conditions could include actual values for agricultural productivity, dietary habits, residence times, dose attenuation by structures, measured environmental transport factors (such as bloaccoulation factors). or similar values actually deterefned for a specific site. The applicant should provide enough information on the seasurements or other methods used to derive these substitute values to enable the NRC staff to evaluate their validity.,
M
. di. MrM
// M (yq)dy(hg' M E' M""8 y..
Equet1ons are provided below by whtch 'the letC staff will estfaste redfatfon exposure for anziam individuals and the population within 50 alles. These equations are appropriate for the exposure pathways that the staff routinely considers in its evaluations. In addition, other exposure pathways that may arise due to unique conditions at a specific site should be considered if they are Itkely to provide a significant contribution to the total dose. A pathway is con-sidered significant if a conservative evalustfon yields an additional dose increment equal to or more than 10 percent of the total from all pathways considered in this pufde.
1.
Doses from Lieutd Effluent pathways The Inc staff will calculate radiation doses from potable water, aquatic food, shoreline deposits, and irrigated food pathways by using the following equations which are described in detail in Appendix A of this guide.
a.
potable Water R,) = 1100
{ Og,9,yexp(-A t,)
(1)
D g
6.
Aquatic Foods I
O 8,0,,,jemp(- A t,)
(2) apj =
gg g
l c.
Shoreline Deposits 1
R,) = 110.000 0,T0,9,3[ esp (-at,)][1-empf-1tI3 I3I g
9b
.-.h 1.10g-2
{
\\
t d.
Irrigated Foods
(.-
For all radionuclides escept tritle:
f g,0 - esp (-A t Il FD - emp(-Agg,D t
gg gb
, 8 exp(4 t IO h1 Espj
- Uap gh stpj Yg Fy
~
- 0 - emp(-1Et,)]
t r
gen){F D
d esp (-1 t I gg,g,j pg 9h Y,1gg p
f g,D - esp (-a t I3' gg gb
- E 0
III pa h Aw g
For tritle:
apj =
C,0,,) + (, %,,j g(C,0 + C,,0,)
6)
F I
7 3
where O
is the equilibri e bioacc o ulation factor for nuclide 1 in pathway p. empressed gp as the ratio of the concentration in biota (in pC1/kg) to the radionuclide concentration in unter (in pC1/ liter) in liters /kg; I
g' is the concentration factor for uptake of radionuclide i from soil by edible I
parts of crops. In pC1/kg (met weight) per pC1/kg dry soil; 1
C is the concentration of radionuclide 1 in unter consumed by anteels. in g
pCf/ liter; C,
is the concentration of radionuclide 1 in vegetation in pC1/kg; g
l 0,9Pd is the dose factor, specific to a given age group a. radionuclide 1. pathuey p.
and organ J. which cen be used to calculatt the radiation dose from an
(
intake of a radionuclide. in aren/pC1. or from exposure to a given concentra-tion of a radionuclige in sediment, empressed as a retto of the dose rate.
2 (in aren/hr) and the areal radionuclide concentration (in PC1/m );
2 d
is the deposition rate of nuclide 1. in pC1/m per hr; g
3 F
is the flow rete of the liipid effluent. in ft /sec; f
is the fraction of the year crops are irrigated, dimensionless; g
F is the stable element transfer coefficient that relates the daily intake rete gg by an anteel to the concentration in an edible portion of animal product. In PC1/ liter (stik) per pC1/ day or pC1/kg (anteel product) per pC1/ day; M,
is the sizing retto (reciprocal of the dilution factor) at the point of esposure (or the point of withdrauel of drinking enter er point of harvest l
ef aquatic food), dimensionless; t
p is the effective " surface density" for soil. in kg(dry soil)/s ;
l On, is the censumption rete of contaminated unter by an anime) in liters / day; Gy is the conseption rete of contaminated feed or forage by an anteel. In kg/ day (met usight);
i 0,
is the release rete of aue11de 1. in C1/yr; r
is the fraction of deposited activity retained on crops dimenstenless; R,)
is the total annual dose te organ J of individuals of age group a from all l
of t:w muclides 1 in pathuey p. in arom/yr; l
1.10D 3 l
.h is the period of time for editch sediment er soll is exposed to the centaminated unter, in hours; t,
is the time period that crops are exposed to contamination during the growing season, in hours; t
is a holdup time that represents the time interval between harvest and h
conseption of the food. In hours; T
is the radioactive half Iffe of nuclide 1. in days; g
t, is the average transit time required for nuclides to reach the point of For internal do'se, t, is the total time elapsed between release exposure.
of the nuclides and ingestion of food or water, in hours; U,P is a usage factor that specifies the exposure time or intake rete for an individual of age group a associated with pathway p. In hr/yr. s/yr. or ig/yr; W
ts the shoreline width factor, dimensionless; 2
Y, is the agricultural productivity (yfeld). In kg(wat weight)/m ;
A is the effective renoval rate constant forMidi11de i from crops in hr g
uhere 1g=19 + 1,.1, is the radioactive decay constant, and 1, is the fm... y;:s p....,...remoVA] rate constant for physical loss by weathering (see Appendix E.
Table I-15);
is.the radioactive decay constant of nuclide 1. In hr*I; A g 3
1100 is the factor to convert from (C1/yr)/(ft /sec) to pCf/ liter; and 3
110.000 is the factor to convert from (C1/yr)/(ft /sec) to PC1/ liter and to account I
for the proportionality constant used in the sediment radioactivity model.
These equations yield the dose rates to various organs of individuals from the exposure pathw2ys mentioned above. Appendix ! of 10 CFR part 50 requires that the annual doses or dose comitments to the total body or any organ of any individual from the sum of the exposure path-ways from liquid effluents associated with each reactor should not exceed 3 mram and 10 arem.
respectively.
2.
Ganan and Beta Doses from Noble Geses Discharged to the Atmosohere The NRC staff will calculate radiation doses from noble gases using the following equations from Appendix B of this guide. Atmospheric dispersion models are found fn Regulatory Guide 1.111
" Methods for Estimating Atmospheric Transport and Dispersion for Saseous Effluents on Routine Releases from Lfght-Water-Cooled Reactors."
s.
Annual Gamma Air Dose from noble Gas Releases from Free-5tandian Stacks More Then 30 Meters Minh D'Cr.e) M j j f,, j m,(E ) E !(H.u.s.e,.E ) (A (6) g g g
gg uhere A
is the photon yield for gemaa-rey photons in energy group k from the decay gg of radionuclide 1. in photans/ disintegration; TD(r.0) is the annual game air dose at a distance r (meters) in the sector at angle e.
in nyad/yr; E
is the energy of the kth photen energy group in MeV/ photon;
)
g 1
t 1.109-4 l
f"8 is the joint freg'vency of occurrence of stability class s and wind speed class a for esctor e, dimenstenless; I(N v.s.e,E )
is the dimenstenless americal 1stegretten constant accounting for the ag distributten of radioactivity according to meteorological conditions of wind speed (v) and atmospheric stability (s) dich in part determine the effective s
stack height (N) and the eertical ples standard deviation (o ).
In addition.
g I is a function of the photen energy E and is T = T + kT, as formulated in g
i Slade(AppendiaB. Reference 1);
(g is the release rate of redlonuclide 1. corrected for decay during transit to the distance r under wind speed u, ta C1/yr; e,
is the mean wind speed W Mnd speed class n in Weect 40 is the sector width over dich atmospheric conditions are averaged in radians; w,(E )
is the air energy absorption coefficient for the kth photon energy group, in g
m ; and T
is the conversion factor to obtain D (r.0). in erad/yr. and has the units 260 of ored-radians-a -disintegration /sec-Mey-C1.
b.
Annual Gansna Air Dese from All Other Noble Gas Releases; Annual Beta Air Dose from All hoble Gas Releases D (r.o) or 0 (r.e) = 3.17 z'10"} O [x/Q)D(r.e)(DFj er DF )
T 8
8 (7) g wheru DF}.DFf are the gesuna and beta air dose factors for a uniform samt-infinite cloud of 3
rodfonucifde 1. in ered-a /ptt-yr; D (r.e) o.r i
T 80 (r.9) are the annual game and beta air doses at the distance r in the sector at angle e from the discharge point in arad/yr; Og is the release rate of the radionuclide 1. in C1/yr;
[x/Q)D(r.e) is the annual average gaseous dispersion factor (corrected for radioactive decay) at the distance r in sector e in arc /m3(seeRegulatoryGuide1.111
" Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors." for methods to estimate x/Q); and 8
3.17 x 10 is the neber of pC1 por Ct divided by the ne6er of seconds per year, c.
Annual Total tody Dose from Noble Gas Releases from Free-Standing Stacks More Then 80 Noters Minh T'
D(r.e)=1.11s['I('dl'"'I-"T(EI'd 1
(s) r k
where TD(r.0) is the annual total body dose at the distance r in sector o. in aren/yr;-
Dj(r.9) is the annual game str dose associated wtth the kth pheten energy group at the distance r in sector 9 in ered/yr; 1.109-5
8, is the attenuation facter that accounts for the dose reduction ese to shfelding provided by residential structures, dimensionless; a
t is the produc of tissue density and depth used to determine a total body g
dese in g/m t T
I y (E )
is the tissue energy absorption coefficient. in am /g; and g
1.11 is the average ratio of tissue to air energy absorption coefficients.
d.
Annual Skin Dose from hoble Gas Releases from Free-Standine stacks More Then 80 noters High 8{o[x/0]'(r.e) ors, 8
3 (r.e) = 1.115,0v(r.e) + 3.17 x 10 g
(s) where DFS is the beta skin dose factor for a s mi-infinite cloud of redfonuclide 1 I
whfen includes the attenuation by the outer " dead" layer of the skin. in 3
arem-e /pCf yr; and D'(r.e) is the annu'al skin dose at the distance r in sector e. in ersm/yr.
All other parameters are as defined in preceding paragraphs.
e.
Annual Total Body Dose from All Other Noble Gas Releases D[(r.e)=57{xg(r.0)DFe g
(10) where
- DFs, is the total body dose factor for a semi-infinite cloud of the radionucifde 1 2
3 which includes the attenuation of 5 g/cm of tissue in eres-a /pCl-yr; D[(r.0) is the annual total body dose due to tenersion in a semi-infinite cloud at the distance r in sector s. in eres/yr; and Ig(r.e) is the annual average ground-level concentration of radionuclide 1 at the 3
distance r in sector 9. in pC1/m.
All other parameters are as defined above.
f.
Annual Skin Dose from All Other noble Gas Releases l
l D'(r.0)=1.1157{xg(r.e)DFj+{ag(r.e)DFS g (11) where D,s(r.0) is the annual skin dose due to tenersion in a semi..#ir.f te cloud at the distance r in sector e. In arem/yr.
All other parameters are as defined above.
3.
Doses from Redfotodines and Other Radionuclides
- Released to the Atmosohere The NRC staff will calculate radiation doses from radiofodines and other radionuclides released to the atmosphere using the following equations from Appendia C of this guide.
- Not including noble gases.
~
I,.
o 1.100-4 e
e e. e. e s e.
,n_,,..-~
a.
Annual Orman Dose from Esternal treadiation from Radienuclides Desosited onto the Ground Surface
(
sj(r.e)=s760s,"Cg,,,3gpg,,
gig) a edere f(r.e) is the ground plane concentretten of redienucitem 1 at distance r in secter e, in pct /st's DFG is the open field ground plane dose conversion factor for organ j from radio-gj r
nacitee 1. in eres e j,cg.,,,
(r.e) is the annual dose to the organ j at location (r.e) in eres/yr; is a shielding factor that accounts for the dose reduction due to shielding e
7 provided by residential structures during occupancy. dimensionless; and 8760 is the n a ber of hours in a year.
b.
Annual Ornan Oose from Inhalation of Radionuclides in Air
(,(r.e)=R,{xg(r.e)DFA),
(13) g where 8(r.e) is the annual dose to organ j of an individual in the age group a at location (r.0) due to inhalation in area /yr; DFA is the inhalation dose facter for radionuclide 1. organ j. and age group a.
gy, in aren/ pct; 3
R, is the annual air intake for individuals in the age group a. in m /yr; and xg(r.9) is the annual average concentration of redienuclide 1 in air at location 3
(r.e),inpC1/m.
Annual urean Oose from incestion of Atmospherically Released Radionuclides in Food c.
D$,(r.e)={DFIgy, U{f,C{(r.e) + Q(r.e) + U C((r.0) + U,f C\\(r.e)
F L
(14) g wh"e C{(r.e). C"(r.e),
h(r.e).C((r.e) are the concentrations of radionuclide 1 in produce (non-leafy-vegetables, fruits, and grains), stik lasfy vegetables, and meat, respectively, at
- Iocation (r. e) in pC1/kg er pC1/s; h(r.e) n j of an individual in age roup a from esfyvegetables,andseatat$ocation(r.e)in is the annual dose to the ingestion of produce, silk area /yra 9FI *,
is the ingestion dose factor for radionuclidn't. organ J. and age group a.
g in aren* pct; f.f are the respective fractions of the ingestion rates of produce and leafy g g estetables that are produced in the garden of faterest; and u;.g.U'.v',
respectively, for indiviseals in the age group a. in kg/yr er s/yr (equivalent
.re the.nnuai int.ke (es.ge) of,coduce..iin.. eat..nd i.afy e.getabi...
to U,,).
1
(
1.109-7
._-w____-__-____--___.._
_ f__
4.
Inteersted Doses to the Population The NRC staff will calculate integrated doses to the local population from all pathways discussed in Sections C.I. 2. and 3.
secause of the various conditions under uhtch the equa-tions in Appendia 0 are used, they are not presented in this section. It is recommended that Appendia O be read for a detailed discussion of the staff's models.
5.
Sessnary of Staff Position A brief suusesry of the staff position on methods of evaluating compliance with the numerical I
guides for design objectives of Appendix ! is presented in Table 1. Methods of evaluating i
compliance with the cost-benefit provisions of Appendix ! are addressed in Regulatory Guide 1.110.
' Cost-Genefit Analysis for Radneste Systems for Light-Water-Cooled Nuclear power Reactors."
9.
DFLBIENTATION The purpose of this section is to provide information to applicants and licensees regarding the NRC staff's plans for utilizing this regulatory guide.
This guide reflects current Nuclear Regulatory Commission practice. Therefore. except in those cases in which the license applicant or licensee proposes an acceptable alternative method, the method described herein for complying with specified portions of the Commission's regulations is being and will continue to be used in the evaluation of submittals for operating ifcense or construction permit applications untti the guide is revised as a result of suggestions from the public or additional staff review.
i l
l' G
N l.
4 W*
1.10g-8
,.S
,^
.^.
TAOLE 1
$1pWOLRT OF STAFF P051T10ll -
NETIWUS OF EVALUATING COMPLIAlICE WITH App 01 DIX 1 AppDDII 1*
151-5 0 - 2 pelltf 0F DOSE WTIONS TTyt OF 90$E DESIGil OBJECTivt5 DESIGII OBJECTIVE 5*
EVALUATION _
- TO DE USED j
Lf eld Effluents i'
gese to tetel body 3 aren/yr per unit 5 erse/yr per site Locatten of the 1.2.3.4.85 I
from all pathmeys highest dose offstte.**
1 j
gone to any orgen 10 erse/yr per unit 5 mege/yr per site Same as above.
1.2.3.4.85
- frem all pattussys j
IIsn.tritten releases 5 Cf/yr per unit f
Oeseous Efflugats***
Gamme dose in air 10 ared/yr per unit 10 ared/yr per site Location of the 4 er 7. as highest dose offsite.' appropriate Deta dose fa air 20 ared/yr per unit 20 mrad /yr per site same as ateve.
7 j
Sese to totat body 5 aren/yr per unit 5 mesm/yr per site Locatten of the 8 er 10. es ef an Iadtvideel h1ghest dose appropeIate i
offsfte.**
Dese to skin of an 15 arem/yr per unit 15 mran/yr per site Some es above.'
9 er II. as 7
tid 1v1 duel appropr1ete 1
5ee feetnotes at end of table. on follearfng page.
j I
l
\\
i TABLE 1(Continued)
Stf95RT OF STAFy POSITI0II -
ILf1EOS OF EVALUATING COMPLIANCE WITH APPENDIX 1 I'
APPDBiX !*
156-50 2 P0iltf W 90$E EWIWS TTpt OF SOSE_
DESIGN OOJECTITES_
OESIGN OBJECTIVE 5*
EVALUATION TO BE USE9 Redteiediows and Particulates" Released to the Atmosphere Does to any orgen 15 ersmVyr per unit 15 aren/yr per site Location of the
- 12. 13. 8 14 from all pettneys highest dose effsite.***
1 Cf/yr per unit 1 131 releases
.Evolunted for a sentame indtvfdeel, as described in Section 3 of this guide.
pg "Evolunted at a locatfon that is entfcfpeted to be occupied during plant lifetime or evolunted with respect to such potential land and unter usage and food pathueys as could actually entst during the term of plant oferation.
- " Calculated only for noble gases.
'Evolunted at a location that could be occupied duiring the term of plant operation.
"geses due to carton-14 and tritten fatake from terrestrial food chains are included in this category.
- "Evolueted at a location utere an exposure pathuey and dose receptor actually entst at the time of licensing, lieuever. if the app 1fcant determines design objectives with respect to rodfonctive fodine on the bests ~ ~'**ing conditions and if potential changes in land and unter usage and feed pathueys could result in exposures in encess n.
,. 4 eline values given shove. the appiscent should provide reasonable assurance that a monitoring and surve111ance progra> w
- e. perfonned to determine:
(1) the guentities of redfoective fodine actually released to the atmosphere and deposit a 6,.tive to those estimated in the detenminetton of design objectives; (2) whether changes in land and water ugge and food pathueys uhtch would result in individual espesures greater then orfgtnelly estimated have occurred; and (3) the content of radioective lodine in feeds involved fn the changes, f f and when they occur.
O
- 3
- i. y
l l
(
AppDWII A IE11805 FM CALCEATIE 80$E3 TO MN FRm LIQUID EFFLUDIT PATied4Y5 The equations for estimett radiation esposure to man from four principal esposure path-ways in the aquatic enviroment potable unter, aquatic foods, shoreline deposits, and irrigated foods) are 1;:ted in Section C. Regulatory positten." of this guide.
1.
Seneralfred tauation for Calculatine Radiation Dose via Lieutd pathmeys l
Equation (A-1) is the generalised equation for calculating the radiation dose to men via Ifquid effluent pathueys.
at,j " C,U,,0,g3 (Aa)
R where C
is the co centration of nuclide 1 in the media of pathuny p. in pCf/s.
pC1/kg. er pC1M; D,9El 1s the dose factor, specific to age group a. radionuclide 1. pathway p.
and orgen J.
It represents the dose due to the intake of a radionuclide.
in erse/pC1. or from exposure to a given concentration of a radionuclide in t
sediment, in aram per br/pCf per a ;
R,gpj is the annual dose to organ j of an individual of age group a from nuclide i via pathuey p. in arem/yr; and U,,
is the er.posure time or intake rate (usage) associated with pathuey p for age group a. in br/yr.1/yr er kg/yr (as appropriate).
('
The three factors making op Equation (A-1) are discussed in the following sections. most of which were taken directly fran the WASH-1258 report (Ref.1). (An updated version of the portion of the WASH-1258 report describing models and coguter programs is contained in the gNWL-1754 report (Ref. 2).)
Radionuclide Concentration in Enviremental Media (C,)
a.
g The concentrations in environmental media of fatarest can be estimated from the mining ratio M. the discharge flow F. the radionuclide release rate Og. and other terms presented in the patby equations that appear later in this discussion.
- b. M (U,,)
The second ters of Equation (A-1) is the usage tore U,,.
Usage is empressed as a consumption rate in kg/yr or If ters/yr or as an esposure time in br/yr, as appropriate for the pathway and age group under consideration.
Thelutt staff encourages the use of site-speciffc data, edienever possible. Such data should be documented. In the absence of site-specific dets, however, the usage values (consumption rates and exposure tlass) presented in Appendia E. Table E-5. are recommended, DoseFactor(0,g,3) c.
Bose factors for internal exposure via incestion are provided in Appendia E. Tables E-11 12,13. and 14. Appendia I also provides farther discussion of the data, models, and assuetions used.
Itatorial ited from sedimentatten in an aquatic syste represents a fairly large.
searly uniform thin s t of contandmation. The factors for eenverting surface sentamination 2
given in pC1/m to the dose rete at one meter aheve a uniformly sentaminated plane have been describedbysoldetandothers(Refs.3and4). Sese facters for esposure to soil sediment have
{*
enits of aren/hr per gCfM and are presented in Appendia E. Table E-4.
1.19941 l
l
.L r :
2.
Eeustions for Lieufd Pethuays This section develops the equations required for the Itguld patfamy models. The principal difference between pathuays is the manner in editch the radionuclide concentrations are calculated.
The doses from the four pattesys should be added to determine the total dose.
a.
Petable lister.
Theannualdose'fremingestionofasteriscalculatedfromEquation(A-2)below:
D (A-2)
{Og,g,)exp(-at,)
R,,) = 1100 g
Systols for this equation were deffned earlier, in Section C.1 of this guide.
The swumation process adds the dose contrktion from each nuclide to yield the total The expression (1100 O M,/F)emp(-1 t,) yields dose for the pathway. organ combination selected.
g 9
the concentration of nuclide i et the time the seter is consmed in pC1/s. This concentration is the tere C, in Equation (A-1). As a minies, the transit time t, may be set equal to 12 g
hours to allow for radionuclid2 transport through the unter purification plant and the water distr N tion system (Ref. 5). The transit time should be increased as appropriate to allow for travel free the point of effluent release to the unter purification plant intake. Credit may be taken for redtonuclide removal by ester portfication processes using techniques such as those outlined in Reference 3.
It should be noted that, depending en the hydrological dispersion model employed, the sizing retto. M,. or dilution factor may not be empitettly deffned. In those instances (e.g.,
buildup of activity in a cooling pond). the relative concentration in the mixed stream (compared to the effluent concentration) may be supplied as a function of the redfological decay constant, with any potential effluent recycling taken into account. Suggested hydrological disperston models are presented in Regulatory Guide 1.113. *Estiesting Aquatic Dispersion of Effluents from
. I Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I."
b.
Aeustic Foods The concentrations of redfonuclfdes in aquatic foods are assmed to be directly related to the concentrations of the nuclides in unter. Equilibri m rettos between the two concentrations, called bioaccumulation factors in this guide, can be found in the literature (Ref. 6). The inclusion of the bioaccumulation factor B, in Equation (A-2) yields Equation (A-3). which is g
suitable for calculating the internal dose from consumption of aquatic foods.
g (A-3)
R,g = 1100
{Ogy,0,g,)exp(-1t,)
9 Values of O, are given in Table A-1; the other prometers have been previously defined.
The g
methodology presented in Reference 7 for the develegment of site-specific fresfasster bioaccoula-tion factors is considered to be acceptable by the NRC staff.
The transit time t, may be set equal to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />
- to allow for radionuclide decay during transit through the feed chain, as well as during food preparation.
c.
Dose from Shoreline Desosits The calculation of individual dose from shoreline deposits is complex since it involves estimation of sedloont lead, teenaport, and concentrations of redienuclides associated with "Nero, and in a am6er of other instances, the MC staff has found it necessary to set forth guidance as to a parameter value in the absence of empirical data. In such instances judgments have been made after considering values assmed by others and model sensitivity to the perseeter
'value in question. In this particular instance, th* tota l bedy dose from fish ingestion, for a typical situation, was found to very by less than a factor of two for a range of environmental g
transit times of from one to seven days.
1.109-12
____._J
TAALE A-1 l
810ACCLMILAT!0N FACTOR $ TO K USED IN THE ABSENCE OF SITE-SPECIFIC OATA (pCf/kg per pct / liter)*
FRE54edATER SA' TiflTER
{1Rgg,
{J21 IWWERTEORATE
{J2i INVERTEttATE N
9.0E-01 9.0E-01 9.0E-01
- 9. X-01 C
4.E 03 9.1E 03 1.E 03 1.4E 03 NA 1.E 02 2.0E 02 6.7E-C2 1.9E-01 P
1.E 05 2.E M 2.9E 04 3.E N CR 2.E 02 2.0E 03 4.E 02 2.0E 03 let 4.E 02 9.E 04 5.K 02 4.0E 02 FE 1.0E 02 3.K 03 3.0E 03 2.0E 04 C0 5.0f 01 2.0E 02 1.E 02 1.0E 03 NI 1.E 02 1.0E 02 1.0E 02 2.5E 02 CU 5.0E 01 4.E 02 6.7E 02 1.7E 03 IN 2.E 03 1.E 04 2.0E 03 5.0E 04 3R 4 2E 02 3.X O2 1.5E-02 3.1E 00 RS 2.0E 03 1.0E 03 8.X 00 1.7E 01
$R 3.0E 01 1.0E 02 2.0E 00 2.0E 01 Y
2.M 01 1.0E 03 2.5E 01 1.0E 03
(
ZR 3.X 00
'E.7E 00 2.0E 02 8.0E 01 NB 3.0E 04 1.0E 02 3.0C 04 1.0E 02 MO 1.0E 01 1.0E 01 1.0E 01 1.0E 01 TC 1.K 01 5.0E 00 1.0E 01 5.0E 01 RU 1.0E 01 3.0E 02 3.0E 00 1.0E 03 RH 1.0E 01 3.0E 02 1.0E 01 2.0E 03 TE**
4.0E 02 5.1E 03 1.0E 01 1.0E 02 l
I 1.E 01 5.E 00 1.0E 01 5.0E 01 C5 2.0E 03 1.E 03**
4.0E 01
- 2. K 01 BA 4.0E 00 2.0E 02 1.0E 01 1.0E 02 LA 2.K 01 1.0E 03 2.K 01 1.0E 03 CE 1.E 00 1.E 03 1.0E 01 6.0E 02 l
PP.
2.K 01 1.E 03 2.M 01 1.0E 03 NO 2.K 01 1.E 03 2.5E 01 1.E 03 W
1.2E 03 1.E 01 3.0E 01 3.0E 01 NP 1.E 01 4.E 02 1.0E 01 1.0E 01 t
Values in Table A-1 are taken from Reference 6 unless otherwise indicated.
" Data takan from Reference S.
j.
Onta taken from Reference 7.
'1.109-13 l
l
1 4
suspended enf deposited materials.' One method af approaching this problem mes presented in the s
(
Veer 2000 Study (Ref. 3). Based on this model, en estimets of the radionuclide concentration in sterellne sediments can be obtained from the faHeafteg d#ression:
C,[1 - esp ( A t II g
gh C,=E (A-4) g g
3t where
. )
l C,
is the concentration of nuclide 1 in sadiment. in pC1/kg; g
C, is the concentration of nucitee 1 fa teter adjacent to the sediment. In g
PC1/14 tar;
-K is ar. assmed transfer constant fmm estar th sediment. in liters /kg per hr; g
t is the seeth of time the sediment is esposed to the contaminated unter, b
nominally 15 years (apprestante nicpoint of facility operating If fe). in hours; and is it.4 decay constant
- ef nuclide 1.1a hours *I.
In the original evaluation A g of the equation. A was chosen to be the radiological decay constant. The g
true value skvid include an as yet unknown " environmental" removal constant.
The value of 2, jet derived for several radionuclides by using data from unter and l
se.itsent samples collected,over a perioc of several years in the Columbia River between Richland.
l Washington, and the river mouth aril in Tillamook Bay Oregon. 75 km south of the river mouth l-(Refs. g and 10). Since the pris. sty use of the equation is to facilitate estimates of the exposure rate from gamma emitters one noter above the sediment. an effective surface contamina-l tion was* estimated-This surface contamination was assumed to be contained within the top 2.5 cm (1 in.) of sediment (with a asss of 40 kg/m ofsurface). The dose contribution from the 2
radionuclides at depths below 2.5 cm uns (gnored. The resulting agostion is s
100T C,,v[1 - emp(-a t,1)
(A-5) g g
g where 2
$g is the " effective" surface contaminetten in pC1/m. that is used in subsequent calculations; T
is the radiological half-1tfe of nuclide 1. in days; y
W is a shore-width factor that describes the geometry of the exposure; and 2
2 100 is equal so (K (t/kg-hr)*40(kg/m )* 24(hr/ day)/0.693) in s/m,4,y, g
Shore-width factors were derived from emperimental data (Ref.11) and are sunnerized in Table A-2.
They represent the fraction of the dose from an infinite plane source that is estimated for these shoreline situations.
The condiination of Equations (A-4) and (A-5) into the general Equation (A-1) leads to Equation (A-6) below for calculation of radiation dose from esposure to shoreline sediments.
apfI0,9,)=WU,,W{C,T0,g,)D-emphatH (A-6)
Iapj
- U t
g g gb j.
As in the development of Equation (A-2), the espression (1100 O y F)emp(-1 t,) may be substituted g
g for C,. This results in the following relattenship:
l g
R,) = 110.000 Og g.g,3(est(-A t,)][1 - emp(-a t )]
(A-7)
TD g
gg
- If the presence of a radionuclide in unter and sediment is contro11ed primarily by radioactive equilibris with its parent nuclide, the unter concentration and decay constant of the parent should be used in Equations (A-4) and (A-5).
1.109-14 9
TABLE A-2
(
SHORE-WIDTH FACTORS FOR USE IN EQUATIONS (A-5). (A-6). AND (A-7)
EXPOSURE SITUATION -
SNORE-WIOTH FACTOR. W Discharge canal bank 0.1 River shoreline 0.2 Lake shore 0.3 Nominal ocean sita 0.5 Tidal basin 1.0 d.
Dose from Foods Grown on Land with Cortaminated Water The equations in the following paragraphs can be used to calculate doses from radio-auclider released in liquid effluents but appearing in crops or antesi products. Separate exeressions are presented for tritte because of its unique environmental behavior.
(1) Vegetation The concentration of radioactive material in vegetation results from deposition onto the plant foliage and from uptake from the soil of activity deposited on the ground. The model used fcr estimating the transfer of radionuclides from irrigation water to crops through water deposited on leaves and uptake from soil was derived for a study of the pctential doses to people from a nuclear power complex in the year 2000 (Ref. 3).
The equation for the model (for radionuclides except tritium) is presented below in slightly modified forw.. The first term in brackets relates to the concentration derived from direct foltar deposition during the growing season. The second term relates to uptake from soil f
and reflects the long-term deposition during operation of the nuclear factitty. Thus, for a
(
uniform release rate the concentration C, of radionuclide i in the edible portion of crop g
species v. in units of pC1/kg. is given by:
'r[? - exp(-1Et,)) + f 8,[1 - exp(-A t I t
g4 gb exp(-A t )
(A-8)
C,=dy gh g
I *Et PA v
g where the terms are defined in Section C. " Regulatory position." Appendix E. Table E-15, presents Values for B, are in Table E-1.
suggested values for the parameters r. Y,. t,. p. and t.
g h
The deposition rate, d. from irrigated water is defined by the relation g
d, = C,1 (water deposition)
(A-g) g mher's.
C,"
is the concentration of radionuclide 1 in water used for irrigation. in pC1/ liter,and t
I is the average irrigation rate. in liters /s /hr. during the growing season.
For a cow grazing on fresh forage. t,in Equation (A-8) is set equal to 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> (30 days), the typical time for a cow to retum to a particular portion of the grazing site (Refs. 3 and 12).
For tritte, the equation for estimating C, is (see Ref.13):
g C, = C, (A-10)
(
1.109-15
(2) himal Products l
l The radionuclide concentration in an animal product such as seat or sllk is
~
dependent on the amount of contaminated feed or foragt eaten by the animal and its intake of contaminated water. The radionuclide concentration in animal products C in terms of PCi/ liter yg er pC1/kg is proportional to the animal's intake of the radionuclide in feed or forage (sub-scriptF)andinwater(subscriptw):
C,g = F,atCypQp + C,g,0,]
(A-H) 3 The second set of terms in the brackets in Equation (A-11) can be omitted if the animal does not drink contaminated water. Values for O and Q are presented in Appendia E.
p h
Table E-3.
Values for B, and Fgg are given in Ap W 1x E. Table E-1.*
g (3) Total Dose from Food Grown on Land The total dose R,p) from irrigated foods and animal products (excluding trittun) is given by:
{C,D,gp)+@,"
{C D
"apj = U gg alpj (A-12) g If values for C, from Equation (A-8) and CIA from Equation (A-11) are substituted g
inEquation(A-12):
r[1-exp(-1Ei,)] + f l,[1 - exp(-1 t Il t
gy 9b apj = U,,,p9{desp(-At)D,gp)
I g
gh y
~
~
r[1-exp(-1 t)]
+("i"*I{F Et D
Q d exp(-A t I p
gg,gp) pg gh V,1Et f t,[1 - emp(-A t Il IA*I3I gi gb
+Cyg,0,
PA 3
I where the terms are defined in Section C. " Regulatory position."
It should be noted that the two components of Equation (A-12) imply that contribu-tions from the individual vegetable and animal products have already been summed. In actual use, it will be necessary to compute separately the milk and meat portions of the dose due to animal products (also applicable to Equation (A-16)).
For tritium, the concentration in animal products (milk or meat) is given by the folicwing equation:
A = F,(C,0 + C,0,)
(AA4)
C p
g 3 where the terms are defined in Section C.
- Regulatory position."
$1nce by Equation (A-10) C, = C,. and since for all practical purposes C, = C,.
Equation (A-14)canberestatedasfollows:
g = F C),(Qp + Og,)
(A-W C
g gg appear as F, and Fg n Table E-1.
Values for F i
1.109-16 a
i
\\
general Egusti
$)ff' equettens for tritim concentration can be combtw en g v,,) + /,p"fMI D
g0 (A-16) apj
- U A apj a
I c
t i
l l
l
(
1.109-17
REFERENCE 5 FOR APFENDIX A
- 1. " Final Enviromental Statement Concerning Proposed Rule Making Action: Neerical Guides for Design Objectives and Limiting Conditions for Operation to Meet the Criterion 'As Low As Practicable' for Radioactive Material in Light-Water-Cooled Power Reactor Effluents."
USAEC Report WASH-1258. Washington, D.C., July 1973.
2.
J. K. Soldat et al.. "Models and Computer Codes for Evaluating Environmental Radiation Doses." USAEC Report BMWL-1754. Pacific Northwest Laboratories. February 1974 3.
J. F. Fletcher and W. L. Dotson (compilers). " HERPES - A Digital Computer Code fcr Estimating Regional Radiological Effects from the Nu6 lear Power Industry." USAEC Report HEDL-T O 71-168. Hanford Engineering Development Laboratory 1971.
2 4.
J. K. Soldat.
- Conversion of Survey Meter headings to Concentration (uC1/m ),. Item 04.3.4 in " Emergency Radiological Plans and Procedures." K. R. Held (ed.). USAEC Report HW-70935 Hanford Laboratories.1962.
5.
D. H. Denham and J. K. Soldat. "A Study of Selected Parameters Affecting the Radiation Dose from Radionuclides in Drinking Water Downstream of the Hanford Project." Health Physics.
Vol. 28, pp. 139-144 February 1975.
6.
- 5. E. Thompson et al.. " Concentration Factors of Chemical Elements in Edible Aquatic Organisms." USAEC Report UCRL-50564. Rev.1. Lawrence Radiation Laboratory. October 1972.
7.
H. A. Vanderploeg et al.. "Stoacc o ulation Factors for Radionuclides in Freshwater Biota."
ORNL-5002. Oak Ridge. Tenn.. November 1975.
8.
G. G. K11augh and L. R. McKay. "A Methodology for Calculating Radiation Doses from Radio-activity Released to the Environment." 0RNL-4992. Oak Ridge National Laboratory. Oak Ridge.
Tenn.. March 1976.
9.
J. L. Nelson. " Distribution of Sediments and Associated Radionuclides in the Colabia River below Hanford." p. 3.80 in *Hanford Radiological Sciences Research and Development Annual Report for 1964." D. W.*Pearce and J. K. Green (eds.). USAEC Report BMWL-36 Pacific Northwest Laboratories. 1965.
10.
G. L. Toombs and P. B. Cutler (compilers). " Comprehensive Final Report for the Lower Coimbia River Environmental Survey in Oregon June 5.1961 - July 31,1967." Oregon State Board of Health. Div of Sanitation and Engineering.1968,
- 11. " Handbook of Radiological Protection. Part 1: Data." prepared by a panel of the Radioactivity Advisory Committee (H. J. Dunster. Chaiman). Department of Employment. Department of Health and Social Security. Ministry of Health and Social Services. Northern Ireland. Naber
$NB 11-360079-8 Her Majesty's Stationery Office. London. England.1971.
12.* J. J. Koranda. " Agricultural Factors Affecting the Daily Intake of Fresh Fallout by Dairy Cows." USAEC Report UCRL-12479.1965.
13.
L. R. Anspaugh et al., "The Dose to Man via Food-Chain Transfer Resulting from Exposure to Trittated Water vapor." in Tritte (A. A. Moghisst and M. W. Carter, eds.).
CONF-710809, 1973.
~
l 1.109-18
AppDGIX B ICDELS FOR CALCULATING 00$ls FROM EBLE GASES DISCHAAGED TO TE AimSMERE The following analytical undels are used for calculating doses from exposurc to noble gases discharged to the atmosphere. Separate models are given for air and tissue doses due to gaarna and beta rays. Encert for the case of noble pas doses resulting from elevated releases, all models assee lasersion in a semi-infinita cloud.
1.
Annual Gasse Air Oose* from Noble Gas Releases from Free-Standino Stacks Here Then 80 Meters M
Slade (Ref.1) describes a derivation of equations for estienting annual air doses from photon enitters dispersed in the atmosg%re. The following expression can be used for calculating annual doses:
D (r.0) = f a)I IInsf'a(E)El(Mu.s.o,.E){(ggg T
g g g
(B-1)
A r
Symbols for this equation were defined earlier. in Regulatory Position C.2.a of this guide.
A discussion of. and derivation for, the I function are presented in Appendia F of this guide.
"~
T The photons are cos61ned into energy groups, and each photon intensity within a group is weighted by its energy and energy absorption coefficient. Thus, the effective fraction of disintegrations of the nuclide 1 yielding photons corresponding to the photon energy group k.
Agg is determined to be gj"a((AE"a%)MEu,$gU (B-2)
(
A mm g
where l
(
is the fraction of the disintegrations of nuclide 1 yielding photons of energy E,;
E, is the energy of the ath photon within the kth energy group. In NeV; and 9,(t,)
is the energy absorption coefficient in air associated with the photon dnergy I,. In m l
All other parameters are as previously defined. The summation is carried out over all photons within energy group k.
Osta for the photon energies and abundances for most of the noble gas nuclides were taken from Reference 2.
For radionuclides not contained in Reference 2.
data were obtained from Reference 3.
l Decay during travel from the point of release to the receptor is (g=Oexp(-Ar/u,)
(s-3) g g
1 The teru " gamma air dose" refers to the couronents of the air dose associated with photons emitted during nuclear and atomic transforestions. i.e.. gasma and a-rays. Annihilation and bremsstrahlung photon radiations are possible centributors to this camponent of the air dose.
I
(
u os-Ig
I I
edicm Og is the initial misese este of nuclide 1. in C1/yr; r
is the distance from the source to the receptor. in m; and A
is the decay constant of nuclide 1. In sec'I.
g All other parameters are as previously defined.
2.
Meus1 Geens Air Oose from All Other Noble Gas Releases and Annual Seta Air 00se* from All Roble Ess Releases plumes of gaseous effluents are considered semi-infinite in the case of ground-level noble
- p s releases. The annual average ground-level concentration of radionuclide 1 at location (r.e) 1s detem.. sed from 4
ug(r.e) = 3.17 x 10 Qg[x/Q]D{,,,)
gg,4) where g (r.0) is the annual average ground-level concentration of nuclide i at the g
3 distance r in the sector at angle e from the release point. In pC1/m. and
[x/Q]O(r.0) is the annual average gaseous dispersion factor (corrected for radioactive decay) in the sector at angle e at the distance r from the release point.
3
~
in sec/m. (See Regulatory Guide 1.111 for atmospheric dispersion models.)
l All other parameters are as previously defined.
The associated annual gamme or beta air dose is then D(r.e)or0(r.e)={xg(r.e)(DF}orDFl)
T 8
(B-5) where the tems are as defined in Regulatory pos'ition C.I.b.
Table B-1 presents a tabulation of the dose factors for the noble gases of interest.
3.
Annual Total Sody and Skin Ooses from Noble Gas Effluents It is also necessary to determine annual doses to real individuals in unrestricted areas.
The staff computes the total body dose from external radiation at a depth of 5 cm into the body I
and the skin dose at a depth of 7 ag/cm of tissue (Ref. 4)."
a.
Releases from Free-Standine Stacks More Then to Meters Hinh The annual total body dose is computed as follows:
i T
T T
l 7{D(r.e)exp[-u(E)t]
(g-6)
D (r.e) = 1.11 a $
g g g
- The term " beta air dose" refers to the component of the air dose associated with particle emissions during nuclear and atomic transformations.1.e.
3+. 3. and conversten electrons.
g
" See discussion in Appendix E. Section 3.
1.10D-20
TABLE S-1 DOSE FACTOR 5 F08 EXPOSURE TO A 5EMI-IsFIm!TE CLOU0 0F WOBLE SASES Wuclide s-str*(0 )
B-Skin **(DF5 )
v-Afr(DFj) v-Sody**(Of 8 )
g 9
Kr-83a 2.88E-04.
1.93E-05 7.56E-08 Kr,85s 1.97E-03 1.46E-03 1.23E-03 1.17E-03 Kr-85 1.95E-03 1.34E-03 1.72E-05 1.61E-05 Kr-87 1.03E-02 9.73E-03 6.17E-03 5.92E-03 Kr-88 2.93E-03 2.37E-03 1.52E-02 1.47E-02 Kr-89 1.06E-02,
1.01E-02 1.73E-02 1.66E-02 Kr-90 7.83E-03 7.29E-03 1.63E-02 1.56E-02 Ie-131m 1.11E-03 4.76E-04 1.56E-04 9.15E-05 l
Ie-133m 1.43E-03 9.94E-04 3.27E-04 2.51E-04 Ie-133 1.0$E-03 3.06E-04 3.53E-04 2.94E-04 Ie-135m 7.39E-04 7.11E-04 3.36E-03 3.12E-03 Ie-135 2.46E-03 1.86E-03 1.92E-03 1.81E-03
(
Ie-137 1.27E-02 1.22E-02 1.51E-03 1.42E-03 Ie-138 4.75E-03 4.13E-03 9.21E-03, 8.83E-03 Ar-41 3.28E-03 2.69E-03 9.30E-03 8.84E-03 l
l
,.e-.=
l pti-yr i
3 eree-m pC1-yr
- 2.80E-04 = 2.88 x 10~4
(
1.109-21
Symbols for this equation are defined in Regulatory Position C.2.c of this guide. The factor 5, accounts for the dose reduction provided by the shielding effect of typical residential structures (see Appendia E. Section 4 and Table E-15).
The skin dose has two components, the gamma and beta contributions. The skin dose rate is cougwted by n'(r.e) - 1.11 's 5,oT(r.e) + 3.17 x 104{0,[x/of(r.e)DFS, (s-7)
Symbols for this equation are defined in Regulatory Position C.2.d of this guide.
The skin beta dose factors DFS were determined using the decay scheme source documents cited above and the methods used in References 5. 6. and 7.
They are presented in Table B-1.
b.
All Other Releases The annual total body dose is computed as follows:
T (3-8)
D,(r.e)=5,{xg(r.e)DFB 4 Symbols for this equation are defined in Regulatory Position C.2.e of this guide.
The annual skin dose is computed as follows:
FfX(r.e)DF}+
zg(r.e)DFS, (8-9)
D',(r.e) = 1.11 x S i
Symbols for this equation are defined in Regulatory Position C.2.f of this guide.
i 1.109-22
RETERENCES FOR APPEm!I B 1.
" Meteorology and Atomic Energy 1964." D. N.' 51ade (ed.). USAEC Report TID-24190.1968.
2.
M. J. Martin, " Radioactive Atams. Egplement I." USAEC Report ORNL-4923. Nevesber 1973.
3.
M. E. Meek and R. 5. Gilbert. " Summary of Gamma and tota Energy and Intensity Data." NEDO-12037, 1970.
4.
J. E. Soldat et al., "The Dosimetry of the Radioactive noble Gases." The Noble Gases (A. A. Moghissi and R. E. Stanley, eds.). ERDA-CDNF 730 915 U.S. Energy Research and Development Administration.1975.
5.
R. Loevinger et al.. in Radiation Dosimetry (G. 5. Mine and G. L. Brownell. eds.). Academic Press. New York.1956.
6.
M. J. Berger. " Improved Point ternels for Electron and Beta-Ray Dostmetry." NBS Report NBSIR 73-107, 1973.
7.
M. J. Berger. " Beta-Ray Dose in Tissue - Equivalent Material Ismersed in a Radioactive Cloud." Health Physics. Vol. 26, pp.1-12. January 1974.
l l
(
).109-23
O APPDIDIR C IWOELS FOR CALCULATING DD5ES VIA AD0!TIONAL PATiedAYS FROM RADIO 100!NES AND OTHER RADIONUCLIDE5*
DISCHARGED TO THE ATICSPHERE 1.
Annual External Dose from Of rect Esposure to Activity Deposited on the Ground Plane The ground plane concentration of radionuclide 1 at the location (r.e) with respect to the release point may be determined by 12)
Cf(r.e) = [1.0 x 10
[s(r.e)Og][1.exp(-AtIl g
gb IE"II 3
i where Cf(r.9) is the ground plane concentration of the radionuclide 1 in the sector at angle e at the distance r from the release point, in PC1/m?;
Q is the annual release rate of nuclide i to the atmosphere, in Ct/yr; g
t is the time period over which the accoulation is evaluated, which is 15 b
years (mid-point of plant operating life). This is a simplified method of approximating the average deposition over the operating lifetime of the facility; o (r.9) is the annual average relative deposition of effluent species i at location g
(r.9) considering depletion of the plume during transport. in m"2; is the radiological decay constant for nuclide 1. in yr"I; and A g 12 1.0 a 10 is the number of PC1 per C1.
The annual dose resulting from direct exposure to the contaminated ground plane, from all radionuclides is then Dj(r.e)=876057{C(r.e)DFG)
(C-2)
E y
where the terms are defined in Regulatory position C.3.a of this guide.
Values for the open field ground plane dose conversion factors for the skin and total body
- are given in Appendix E. Table E-6.
The annual dose to all other organs is taken to be equivalent l
to the total body dose. The factor 5 is assumed to have a value of 0.7. dimensionless.
7 t
~
"Does not include noble gases.
1.109-24
2.
Annual Dose from Inhalation of Radionuclides in Air
(
The annual average airborne concentration of radionuclide i at the location (r.e) with res.
^
pect to the release point may be determined as Xg(r.e) = 3.17 a 10 0g(x/Q)D(r.e)
(C-3) 8 where Qg is the release rete of nuclide i to the atmosphere, in C1/yr; zg(r.e) is the annual average ground-level concentration of nuclide i in air in 3
sector e at distance r in pC1/m ;
[x/Q)D(r.e) is the annual average atmosphere dispersion factor. in sec/m3 (see Regulatory guide 1.111). This includes depletion (for radiofodines and part!culates) and radioactive decay of the pime; and 4
3.17 a 10 is the saber of PC1/Cf divided by the amber of sec/yr.
The annual dose asiociated with inhalation of all radionuclides, to organ j of an individual in age group a. is then D",(r.e)=R.{xg(r.e)DFA (C-4) j gj, Values for DFA ), are given in Appendix E. Tables E-7 through E-10; values for R, are given g
in Appendix E. Table E-5.
All other symbols are as defined earlier in Regulatory position C.3.b.
{
3.
Concentrations of Airborne Radionuclides in Foods The concentration of radioactive material in vegetation results from deposition onto the plant foliage and from uptake of activity initially deposited on the ground. The model used for estimating the transfer of radionuclides from the atmosphere to food products is similar to the model developed for estimating the transfer of radionuclides from irrigation water given in Appendix A of this guide.
a.
Parameters for Calculatine huclide Concentrations in Forace. Produce. and Leafy Vecetables For all radiotodines and particulate radionuclides, except tritta and carbon-14 the concentration of nuclide 1 in and on vegetation at the location (r.0) is estiasted using C{(r.e)=d(r.e)<
tie))+s,,[1-exp(-1,t,1) r[1-exp(-a t resp (-a t )
(C-5) gh g
w s
See Regulatory position C.1 of this guide for definitions of terms. Values for the are provided in Appendia E. Table E-15. For the parameters t,.
parameters r t,. Y,. p. and th Y,. and t. different values are given (in Appendix E) to allow the use of Equation (C-5) for h
different purposes: estiaating concentrations in produce consmed by man; in leafy vegetables consumed by man; in forage consumed directly as pasture grass by dairy cows, beef cattle, or goats; and tri forage consmed as stored feed by dairy cows. beef cattle, or goats.
1.100-25
.-r
The deposition rate fra the pl ee is defined by 0
d (r.e) = 1.1 a 10 d (r.e)Q, (C-6) g g
where d (r.s) is the deposition rate of redionuclide 1 onto ground at location (r.e). in g
2 pC1/m -hr; o (r.8) is the relative deposition of radionuclide 1. considering depletion and g
decay in transit to location (r.0). in e-2 (see Regulatory 81mide 1.111); and 8
1.1 a 10 is the neber of pC1 per C1 (1012) divided by the neber of hours per year (8760).
For radiofodines, the model considers only the elemental fraction of the effluent. The deposition should be computed only for that fraction ef the effisent that is estimated to be elemental iodine. Heasurements at operating facilities indicate that about half the radiotodine emissions may be considered nonelemental (Ref.1). tHth this consideration included.
Equation (C-6) for radiciodine becomes 7
o (r.e) 5.5 a 10 d (r.e)og (C-7) g g
where Q is the total (elamental and nonelemental) radiciodine mission rate. The retention g
factor r fo. elemental radiciodine on vegetation should be taken as unity, since the esperimental measurements (Refs.1. 2. and 3) used to evaluate this transfer mechanism consisted of direct comparison of the gross radiciodine concentration on vegetation and the concentration in air (Refs. 4 and 5).
For radiciodines, the deposition model is based only on the dry deposition process. Idet deposition. including " washout" of the organic and non-organic fodine fractions. should be con.
sidered at some sites depending on the meteorological conditions (see Regulatory Guide 1.111).
For particulates, the deposition model considers both wet and dry deposition. There is also a retention factor (r of Equation (C-5)) that accounts for the interception and capture of the deposited activity by the vegetative cover. A value of 0.2 is taken for this factor (Refs. 6 and 7). All nuclides except noble gases, tritte. carbon-14. and the iodines are treated as particulates.
Carbon-14 is assmed to be released in smide form (C0 or C0 ).
The concentration of carbon-14 2
in vegetation is calculated by assuming that its ratio to the natural carbon in vegetation is the same as the ratio of carbon-14 to natural carbon in the atmosphere surrounding the vegetation (see Refs. 8 and 9). Also. in the case of intermittent releaset, such as from gaseous weste decay tanks, the parameter p is employed to account for the fractional equilibrim retto achieved. The parameter p is defined as the ratio of the total annual release time (for C-14 atmospheric releases) to the total annual time during which photosynthesis occurs (talten to be 4400 hrs). under the condition that the value of p should never arceed unity. For continuous C-14 releases. 5 is taken to be unity. These considerations yleid the follewing relationship:
7 Ci4(r.e) = 3.17 a lo po [a/0)(r.e) 0.11/o.16 u
I
= 2.2 Io p0p[u/03(r.e)
(C-8) where C{4(r.e) is the concentration of carton-14 in eegetation grown at 1ecation (r.e). in pC1/ks; 0
is the annual release rate of carbon-14, in C1/yr; g
p is the fractional equilibrium ratio. dimensionless; I
0.11 is the fraction of total plant mass that is natural carbon, dimensionless; 1.10g-26
- - - - L -
3 0.16 is equal to the concentration of natural carbon in the atmosphere, in g/m ;
eM 7
12 3
I 3.17 x 10 is equal to (1.0 x 10 pC1/C1)(1.0 x 10 g/kg)/(3.15 x 10 sec/yr).
The concentration of tritt a in~ vegetation is calculated from its concentration in the air surrounding the vegetation. Using the method described in Reference 10. the NRC staff derived the following equation:
7 C{(r.e) = 3'.17 a 10 0 [x/0)(r.e)(0.75)(0.5/H)
T 7
= 1.2 x 10 0 (x/Q](r.e)/H (C-g) 7 where C{(r.0) is tha concentration of tritte in vegetation grown at location (r.e), in pC1/ kg..
3 H
is the absolute hmidity of the atmosphere at location (r.e), in g/m ;
h is the annual release rate of tritt a. in C1/yr; 0.5 is the ratio of triti m concentration in plant water to triti m concentration in atmospheric water, dimensionless; and 0.75 is the fraction of total plant mass that is water, dimensionless.
b.
parameters for Calculating Nuclide Concentrations in Milk The radionuclide concentration in allk is dependent on the amount and contamination level of the feed consumed by the animal. The radionuclide concentration in milk is estimated as
(
C"(r.e)=F,C{(r.0)Q,exp(-At)
(C-10) gg where
((r.e) is the concentration in milk of nuclide 1, in pC1/ liter; C{(r.e) is the concentration of radionuclide 1 in the animal's feed. in pC1/kg; F*
is the average fraction of the animal's daily intake of radionuclide 1 which appears in each liter of milk in days / liter (see Appendix E. Tables E-1 and E-2 for cow and goat data, respectively; for nuclides not listed in Table E-2. use the values in Table E-1);
Q is the amount of feed consumed by the animal per day, in kg/ day; F
t is the average transport time of the activity from the feed into the milk g
and to the receptor (a value of 2 days is assumed); and is the radiological decay constant of nuclide 1. in days-I.
a g b
The concentration of rodienucilde i in the antaal's feed is estimated as CI(r.e)=f,f,CI(r.e)+(1-f,1C'(r.e)+f,(1-f,1Cj(r.e)
(C-11) whm C((r.0) is the concentration of radionuclide i en pasture grass (calculated using Equation (C-5)witht=0).inpC1/kg; h
(
tj(r.e) is the concentration of radionuclide 1 in stored feeds (calculated using Equation (C-5) with t =90 days), in pC1/kg; h
1.100-27
f, is the fraction of the year that antasis graze en pasture; and f,
is the fraction of daily feed that is pasture grass when the antaal grazes en pasture.
The values of the parameters t. t,. Y,. and t, that will be employed in evaluating h
the milk pathuay, unless site-specific data is supplied, are provided in Appendix E. Table E-15.
c.
parameters for Calculatine huclide Concentration in Meat As in the allk pathway the radionuclide concentration in meat is dependent on the amount and contamination level of the feed cons m ed by the animal. The radionuclide concentra-
- t. ton in most is estimated as C((r.e)=FC((r.e)Qp exp(-At,)
(C-12) g g
where C((r.e) is the concentration of nuclide i in antaal flesh. in pC1/kg; each kilogram of flesh. in days /kg (y intake of nuclide 1 which appears insee App is the fraction of the animal's dail Fg t,
is the average time from slaughter to consunption (see Appendix E. Table E-15).
All the other symbols are as previously defined.
Beef cattle will be assmed to be on open pasture for the grazing periods outlined i
for milk cattle.
.I 4.
Annual Dose from Atmospherically Released Radionuclides in Foods The annual dose to organ j of an individual in age group a resulting from ingestion of all radionuclides in produce, milk esat, and leafy vegetables is given by 0l,(r.e)={DFlyg [U,f,C}(r.e) + @(r.e) + U[C((r.e) + U,f,Ck(r.e))
L (C-13) where h(r 9) is the annual dose to organ j 'of an isdividual in age group a from dietary intake of atmospherically released radionuclides. In aren/yr; DFi is the dose conversion factor for the ingestion of nuclide 1. organ J. and gj, age group a. in ers/pci (from Tables E-11 through E-14 of Appendix E of thisguide);and a
U{. (. (, h are the ingestion rates of produce (non-leafy vegetables. fruit, and grains).
milk. seat and leafy vegetables, respectively for individuals in age group a (from Table E-5 of Appendix E of this guide).
All the other syueols are as previously defined. Values of f, and f to be assumed in the absence a
of s.ite-specific inforestion are given in Table E-15 of Appendix E as 0.M and 1.0. respectively.
D I
1.100-2s
(
K Fraturrt FOR APPD S!I C l
1.
B. N. Meiss et al.. "Oetalled Measurement of I-131 in Air. Vegetation and Wilk Around Three Operating Reactor $ttes." RRES-75/021. U.S. Nuc1ser Regulatory Commission.
Washington. D.C.. March 1975.
2.
D. F. Bunch (ed.)'. " Controlled Enviromental Radiotosine Test. Progress Report Ne6er Two."
35AEC Report 100-12063. January 1968.
- 3. J. D. Ziebrick and P. S. Voillegue. " Centro 11ed Enviremental Radiotodine Tests at the National Reactor Testing Station. Progress Report Number Faur." USAEC Report ID0-12065 December 1968.
e I3I 4.
F. O. Hoffhan. " Environmental Variables Involved with the Estimation of the Amount of I
in N11k and the Subscquent Dose to the Tityroid." Institute fur Reaktorsicherheit. Cologne.
West Gerusy. IR5-W-6. June 1973, 5.
F. O. Hoffman. "A Reassessment of the Parameters Used To Predict the Environmental Transport I3I of I from Air to Milk." Institute fEr Reaktorsicherheit. IRS-W-13. April 1975.
I37 5.
C. A. Pe11etter and P. S. Vo111eque. *The Behavior of Cs and Other Fallout Radionuclides on a Michigan Dairy Faps." Nealth Phys.. Vol. 21, p. 777.1971.
7.
P. G. Vo111eque and C. A. Pe11etter. " Comparison of External Irradiation and Consumption
- e # r Released to the I37Cs. N and C
P of Cow's Milk as Critical Pathways for Atmosphere " Health Phys.. Vol. 27. p.109.1974.
8.
V. C. Ng et al.. " Prediction of the Maximun Dosa e to Man from the Fallout of Nuclear e
Devices. IV Handbook for Estimating the Maxim a nternal Dose from Radionuclides Released
(
to the Biosphere." USAEC Report UCRL-50163. Part IV.1968.
9.
R. C. Weast (ed.). " Handbook of Chemistry and Physics." CRC Press. Cleveland. Ohio.1970.
10.
L. R. Anspaugh et al.. "The Dose to Man via the Food-Chain Transfer Resulting from Exposure to Tritiated Water Vapor." USAEC Report UCRL-73195. Rev.1.1972.
b O
~
(
u -29 e
e
l AppElIDIK D ISOELS FOR CALCULATIIIG p0PULATICII 005ES FRipt IRlCLEAR POWER PLAlli EFFLUENTS Calculation of the annual population-integrated total body and thyroid doses
- should be performed for the three effluent types identified in this guide. These doses shoult' he evaluated for the population within a 50-mile radius of the site, as specified in paragraph D.Section II of Appendix I to 10 CFR part 50.
For the purpose of calculating the annual population-integrated dose, the 50-elle region should be divided into a number of subregions consistent with the nature of the region. These subregions any represent, for example, the reaches of a river or land areas over which the appro-priate dispersion factor is averaged. Dispersion factors, population dita, and other information describing existing or planned uses of the subregions should be developed.
1.
General Expressions for population Dose For pathways in which the perunnent and transient population of the subregion can be con-sidered to be exposed to the average radionuclide concentrations estimated for the subregion.
the annual population-integrated dose is calculated as follows:
f INI d{D D = 0.001 p
jda di.
where 4
D is the annual dose to organ j (total body or thyroid) of an average jda Individual of age group a in subregion d. In aren/yr; D
is the annual population-integrated dose to organ j (total body or thyroid).
In man.ress or tityroid man-rems; f,
is the fraction of the population in subregion d that is in age group a; g
p is the population associated with subregion d; and d
0.001 is the conversion factor from eram to rem.
l The annual dose to the total body or thyroid of an average individual should be evaluated with the usage factors of Table E-4 of Appendix E.
lIndels and equations for the detailed dose calculations are presented in Appendices A. B. and C of this guide. The annual population-integrated doses from ingestion of potable water. inhalation of airborne effluents, and external exposure to airborne or deposited radionuclides should be evaluated. In addition to the pathways for which equations are presented in Appendices A. B. and C. other exposure pathways should be evaluated if conditions at a specific site indicate that they might provide a significant contri-
- bution to the total population dose from all pathways. In this context. a significant contribu-tion is defined as 10 percent or more.
For pathways that involve food products produced in the subregion, thg food products may be distributed to other areas for consumption. For all the food that is produced within the 50-alle radius. the radioactivity concentrations are averaged over the entire area by weighting the concentrations in each subregion by the amount produced in each subregion. This average concentra-l**
tion is used in calculating the population doses. The 50-e11e average concentration of nuclide 1 in food p is camputed as Igp * (1/V,) emp(4 t,)
C N) g gg,v,
i g
- The population-integrated dose is the summation of the dose received by all individuals and has units of man-ren when applied to the total body dose and units of man-thyroid-ren when applied to the sesumation of t8urrold dese.
^ "
- 4
-~-
'O*
L
Where
(..
C,p is the average concentration over subregion d of the nuclide 1 in pathway p, g
gn pC1/kg or pct / liter (see Appendices A and C of this guide for models and equations for calculation of pathuey concentrations);
E is the 54W1e average concentration of nuclide i in patiassy p. in gP l
pC1/kg or pC1/11ter; t,
is the transport time of the food media p through the distribution system, l
in days (Table D-1 presents estimates of the transport times that may be used in lieu of site-specific data);
v, is the annual mass or volume of food medium p produced in subregion d. in kg g
or liters; V
is the mass or volume of the food media p produced annually with the 50-mile p
radius about the site, in tg or liters; and is the radiological decay constant for nuclide 1. in days-I A g i
The population served by all the food prodsced within 50 miles of the site is estimated as
(
P,=V,/jU,,f, (o-3) where f,
is the fraction of the population within the age group a;
(
P is the estimated population that can be served by the quantity of food p p
likely to be produced within 50 miles of the site; U,p is the use or conseption factor of food medium p for the average individual in age group a. in kg/yr or liters /yr (taken from Table E-4); and V
is the annual mass or volme of food medium p itkely to be produced within P
a 50-mile radius about the site, in kg or liters.
The annual population-integrated dose is then calculated as f,f,U,,0F,9 (D-4)
D = 0.001 P,
g where P*,< P P
if g
e W
II E 1 E I
50 p
M ond DF,9 is the ingestion dose factor for age group e and nuclide 1. in aren/pCi (taken from Appendia E. Tables E-11 to E-14);
e 1.10g-31
~
9 grfgg w.-
~
.ing,g g.1 RECONENDED VALUES FOR THE TRANSPORT T!fES IN THE F000 DISTRIBUTION SYST9s F000 MEDIUM DISTRIBUTION TitANSPORT TIME fin days) l Fruits. grai.u. and vegetables 14 Milk 4
l Meat and poultry 20 Sport fish 7
Connercial fish 10 Orinking water 1
.To be used in lieu of site-specific data on food distribution.
l l
s l
l l.
l l*
1.100-32
-.?
l
('
D is the annual population-integested dose to organ j (total body or thyroid).
in man-ren/yr er thyroid een-ren/yr;
~- w.
~
x P,
is the populatten consming feed media p; and P
is the total populatten within 30 miles.
90 All other factors are as defined above.
Note that the above foruulation Itaits the evaluation of the exposed population evaluation to the populetten residing within 50 miles as spectfled in paragraph D.Section II of Appendix 1 to 10 CFR part 50, In calculating the annual population-integrated total body and thyroid doses. the age distribution of the population within 50 miles any be assmed to be the same as the age distribution of the U.S. population (Ref.1). Reference 1 indicates the fractional bregkdown to be as follows: children. 0.18; teenagers. 0.11; and adults. 0.71. Infants (0-1 year in age) are not projected to exceed 21 of the population (Ref.1), and their population fraction has been included in that given above for cht1dren.
2.
Use of the Itedels a.
population-inteersted Doses from Lieutd Effluents The annual total body and thyroid population-integrated doses due to exposure to lig-vid effluents should be evaluated for the following principal pathways: potable water. aquatic food products. enternal irradiation from shoreline deposits, and terrestrial food products irri-gated with water that has received the liquid effluent.
(1) poses from Potable Water The annual population-integrated total body and thyroid doses from water consump-tion are evaluated for all subregions that have water intakes existing or designated at the time of the license application. The products of the individual doses and the population exposed in
(~
each such subregion within 50 miles from the site are summed to obtain the total dose. The formulation expressed in Equation (D-1) any be used.
The total body and thyroid dose of the individuals should be evaluated using Equation (A-2) in Appendix A of this guide, together with the age-dependent usage factors U,p obtained from Table D-1.
The dilution from the discharge point to the usage point should be evaluated using appropriate hydrological models for the various subregions.
If the population served by a particular unter supply system is not known it can be estimated by the following:
(D-5) p,= v/c edure c
is the average delly usage of individuals on the systan. in gal / day per person; p,
is the estimated population served by the unter system; and a
v is the average daily intake of the unter supply system. in gal / day.
If the industrial usage t' rom the unter supply system is known. it can be sub-tracted from the average daily intake of the system before this value is entered into Equation (D-5).
The population served by a teter supply system shose intake is within the 50-m11e rodius may include individuals who reside outside the circle. This population may be pro-rated to include only the population within the 50-e11e radius. Conversely a unter supply system with an intake beyond the 50-a11e radius any serve the population within the 50-e11e radius. whose espesure via drinking water should be included in the 50-elle population dose evaluation.
1.100-33
-____-___2_-.____-_.
s
(2) goses from Aeustic Food Products The annuel population-integrated total body and thyroid doses from cons eption of aquatic food products are evaluated using the production of sport and commercial harvests in the various sobregions. The mixing ratio (or dilution) should be evaluated for each subregion using an appropriate hydrological model. For sport harvests, the entire edible harvest is assmed to be ingested by the population within 50 miles. The formulation empressed by Equation (D-4) should be used with the pop;1stion P, given by the results of Equation (D-3). The age-specific ingestion rates of Table E-4 may be used in lieu of site-specific data.
For ces.arcial harvests, the production within 50 miles from the site is con-sidered as part of the total U.S. harvest. Equation (D-2) should be used to compute the average concentration. with V, as the total estimated U.S. commercial harvest of the aquatic food medfian p.
The annual population-integrated dose is then computed using Equation (D-4) with The age-specific factors of Table E-4 may be used in Iteu of site-specific data.
P, = P50 (3) Ooses from Shoreline Deposits I
The annual population-integrated total nody and thyroid doses from recreational activities on the shoreline of the receiving water body are evaluated by summing the product of the individual doses in each subregion and the population exposed therein. All subregions within the 50-mile radius should be considered where existing or designated recreational facili-ties exist. If available, actual recreational usage in the vicinity of each facility should be used. The fomulation of Equation (D-1) is appropriate.
(4) Doses from Consumption of Terrestrial Food Products Irriested by Wate s Receiving the Liquid Effluent l
The annual population-integrated total body and thyroid doses from consumption of food irrigated with water from the body receiving the liquid effluent are evaluated following the procedures outlined in the development of Equation (D-4). Note that the tern V, of Equations (D-2) and (D-3) denotes the total production of food medfian p within 50 miles, not just the total production of irrigated food medium p.
The consumption rate data of Table D-1 may be used in lieu of site-specific data in the evaluation of Equation (D-4).
b.
population-Inteersted Doses from Airborne Effluents The annual total body and thyroid population-integrated doses should be evaluated for the following principal exposure pathways: noble gas submersion, inhalation of airborne efflu-ents, ingestion of contaminated terrestrial foods (milk. meat, and produce). and enternal irradiation from activity deposited on the ground. Available state or county agricultural pro-duction data may be used for estimating the population-integrated doses from food consumption.
For the evaluation of exposures from atmospheric releases, the 50-m11e region should be divided into 160 subregions formed by sectors centered on the 16 compass points (N. NNE. NE.
etc.) and annuli at distances of 1. 2. 3. 4. 5.10, 20, 30, 40, and 50 miles from the center of the facility. The atmospheric dispersion factors (x/Q) or similar factors should be evaluated at the radial midpoint for each of the subregions using appropriate atmospheric dispersion.
models such as those described in Regulatory Guide 1.111.
(1) Ooses due to Exposure to Noble Geses The annual population-integrated total body dose due to noble gas effluents 3
should be evaluated by summing the products of the individual deses in each subregion and the population in each subregion. Equation (0-1) may be used. For external empo,ure, the model does not differentiate between age groups. A structural shielding factor of 0.5 should be applied in conjunction with the dose factor data of Table 8-1.
(2) poses due to inhalation of Radiciodines and Particulates The annual population-integrated total body and thyroid doses from inhalation of a{rborne effluents should be evaluated by saaming the products of the individual doses received in each sobregion and the population in each subregion. Equation (D-1) may be used. The age-specific inhalation retos of Table E-4 may be used with the data of Tables E-7 to E-10.
1.109-34 l
(3) Deses due to ineestion of Terrestrial Food Products
.v 'u p y.3 9 -T..c.v.. n w i
-- The aniusi population-integrated total body and thyroid doses from ingestion of terrestrial food products should be evaluated using the production data for each subregion. For I
milk. meat, and commercial vegetables, the ferimlation of Equation (D-2) should be used to t
calculate the average concentrations in the foods. These concentrations are then used in Equation (D-4), along with the data of Tables D-1. E-4, and E-11 to E-14 to calculate population doses.
(4) Doses due to Enternal Irradiation fror Activity Deposited on the Ground The annus1 population-integrated total body and thyroid doses from external esposure to surface deposition of the effluent should be evaluated using Equation (D-1). A household shielding and occupancy factor of 0.5 should be applied in conjunction with the dose factors of Table E-6.
K FERE E E FDR APPE2 1I D 1.
" Current Population Reports." Sureau of the Census. Series P-25. No. 541. U.S. Dept. of l
Commerce 1975.
~
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./ w s/w w..
(.
1.109-35
NpDWII E immERICAL DATA POR THE CALCULATION OF ANNUAL DOSES 70 NAN FRON ROUTINE RELEASES OF MACTOR EFFLUENTS This appendix contains data for use in the equations presented in the Regulatory position and in Appendices A. B. C. and D of this guide. The numerical values presented in this appendix are those routinely used by the NRC staff. In instances where more appropriate information of.a site-specific natur1 has been developed and doceented, that infomation should be used.
In a number of instances the staff has found it necessary to provide guidance as to the value of a particular parameter in the absence of sub;tantial empirical data. In such instances the staff has exercised judgment and has considered values used by others and the sensitivity of the results to the value assmed.
Infomation is provided below under four broad categories: enviromental data, human data.
dose factors. and other parameters.
1.
Environmental Data Table E-1 provides values for the following stable element transfer coefficients:
S, for the estimation of produce, leafy vegetable, or pasture grass radioactivity a.
g from that in soil (pC1/kg in vegetation per pC1/kg in soll);
F, for the estimation of cow milk activity from that in feed (pCi/s in allk per PC1/
b.
day ingested by the animal); and c.
F for the estimation of meat activity from that in feed (pCi/kg in meet per PC1/ day g
ingested by the animal).
The data are largely derived from Reference l'.
The value of the cow milk transfer coefficient for radiotodine is based on the staff's review of the literature (Refs. 2-g).
Values of transfer coefficients for goat allk are presented in Table E-2 for a limited number of nuclides. For nuclides not listed in Table E-2, the milk transfer coefficient from Table E-1 should be used.
Various animal parameter values are presented in Table E-3 for use in estimating animal product activity levels as functions of the corresponding levels in feed and seter supplies.
2.
Human Data Tables E-4 and E-5 present usage rates of various environmental media by everage individuals and maximum individuals, respectively, according to age group. *5eafood" ic used to indicate a
intake of aquatic invertebrates such as lobster crab, class, and oysters. Ingestion of aquatic plant material is not nomally assmed.
l 3.
Dose Factors Dose factors for external irradiation from a uniformly contaminated ground plane are 2
presented in Table E-6 (Refs.10 and 11), in units of eren/hr per pC1/m. These factors are applicable for surface contaminatfor. via deposition of liquid effluents on shoreline sediments er airborne effluents on ground surfaces. Dose factors are provided for the total body and skin
. only. Doses ta other organs are assumed ogsel to the total body dose.
Dose factors provided in Table E-6 are derived fr7omconsideration of the dose rate to air 1 meter above the ground plane and the penetration of the radiation into the body. The total body dose is computed at a penetration depth of 5 cm; the skin dose is computed at a depth of 7 ag/cmI. These tissue depths are indicated by Reference 12, where it is suggested that. for 1.10g-36
~
~
.. M 1
n
I 1n8LE E-1 STABLE ELD 4ENT TRANSFDt DATA
- 8,,
F,(Cow)
Ff Element Ven/Soll N11k (d/s)
Neat (d/ko)
M**
4.8E 00 1.0E-02 1.N-02 C**
5.5E 00 1.2E-02 3.1E-02 Na 5.2E-02 4.0E-02
- 3.0E-02 P
1.1E 00 2.K-02 4.6E-02 Cr 2.K-04 2.2E-03 2.4E-03 Mn 2.9E-02 2.K-04 8.0E-04 Fe 6.6E-04 1.2E-03 4.0E 02 Co 9.4E-03 1.0E-03 1.3E-02 l
N1 1.9E-02 5.7E-03 5.3E-02 i
Cu 1.2E-01 1.4E-02 8.0E-03 l
Zn 4.0E-01 3.9E-02 3.0E-02 i
Rb 1.3E-01 3.0E-02 3.1E-02 l
$r 1.7E-02 8.0E-04***
5.0E-04 Y
2.6E-03 1.0E-05 4.K-03 Zr 1.7E-04 5.0E-06 3.4E-02 Ne 9.4E-03 2.5E-03 2.8E-01 No 1.2E-01 7.K-03 8.0E-03 Tc 2.5E-01 2.K-02 4.0E-01 Ru 5.0E-02 1.0E 46 4.0E-01 Rh 1.3E 01 1.0E-02 1.5E-03
(
Ag
- 1. K-01 5.0E-02 1.7E-02 Te 1.3E 00 1.0E-03 7.7E-02 I
2.0E-02 6.0E-03t 2.K-03 Cs 1.0E-02 1.2E-02*"
4.0E-03 Sa 5.0E-03 4.0E-04***
3.2E-03 La 2.5E-03 5.0E 06 2.0E-04 Ce 2.5E-03 1.0E-04***
1.2E-03 Pr 2.5E-03 5.0E-06 4.7E-03 Nd 2.4E-03 5.0E-06 3.3E-03 W
1.8E-02 5.0E-04 1.3E-03 Np 2.K-03 5.0E-06 2.0E-04tt
- 0ata presented in this table is from Reference 1 unless otherwise indicated.
" Neat and milk coefficients are based on specific activity considerations.
"From Refe.ence 15.
'See test.
"From Reference 13.
b C.
i 1.10D-37
TABLE E-2 IRJCLIDE TRANSFER PAIUMETERS FOR G0AT'S MILK
- In(days /11ter)
Element H
0.17 C
0.10 P
0.25 Fe 1.X-04 Cu 0.013 Sr 0.014**
I 0.06**
Cs 0.30 "
" Values in this table are from References 1 and 14 unless otherwise indicated.
"From Reference 15.
TABLE E-3 ANIMAL CONSUMPTION RATES S
Ok l
Feed or Forage blater l
Animal (ka/ day [ wet weight])
(t/ day)
Nilk cow to (Ref.10) 40 (Ref. 16)
Seef cattle 50 (Ref.10) 50 (Ref.16)
Goats 6 (Aef.17) 8 (Ref.18)
~
1.109-38 l
(
TABLE E-4 REC 010EIGED VALUES FOR U,,10 SE USED FOR TIE AVDtAGE Ile!VIOUAL Ill LIEU OF SITE-SPECIFIC OATA Pathuey Child Tgn Adult Fruits. vegetables, &
grain (kg/yr)*
200 240 190 Milk (t/yr)*
170 200 110 fleet & poultry (kg/yr)*
37 -
Sg 95 Fish (kg/yr)*
2.2 5.2 6.9 Seafood (kg/yr)*
O'.33 0.75 1.0 Drinking water (t/yr)**
260 260 370 Shoreline recreation (hr/yr)**
9.5 47 3.3 3
Inhalation (m/yr) 3700**
8000***
8000'
" Consumption rate obtained from Reference 1g and age-prorated using
(.
" Data obtained directly from Reference 10.
techniques in Reference 10.
" I h l tion rate derived froy data provided in Reference 20.
naa
'Osta obtained directly from Reference 20.
b 9
1.109-39
TABLE E-5 REcoletENDED VALUES FOR U,, TO BE USED FOR THE NAXIttm EXPOSE 0 INDIVIDUAL IN LIEU OF SITE-SPECIFIC DATA pathway Infant Child
- Tggn, Adult Fruits, vegetables &
520 630 520 grain (kg/yr)*.**
Leafy vegetables 26.
42 64 (kg/yr)*
Milk (s/yr)*
330 330 400 310 Neat 8 poultry 41 65 110 (kg/yr)*
Fish (fresh or salt) 6.g 16 21 (kg/yr)***
1.7 3.8 5
Other seafood (kg/yr)*
Drinkingunter(s/yr)t 330 510 510 730 Shoreline recreation 14 67 12 (hr/yr)t 3
Inhalation (m/yr) 1400tt 3700ttt 8000tte 8000tt
- Consstion rate obtained from Reference lg for average individual and age-prorated and maximited using techniques contained in Reference 10.
" Consists of the following (on a mass basis): 221 fruit. 541 vegetables (including leafy vegetables) and 241 grain.
"*Conseption rate for adult t5tained tiy averaging data from References 10 and 21-24 and age-prorated using techniques contained in Refere9ee 10.
'Oata obtained directly from Reference 10.
" Data obtained directly from Reference 20.
'" Inhalation rate derived from data pr6vided in Reference 20.
9 1.105-40 1
(..
1A K E E-4 HTERNAL 00$E FACTORS FOR STAWIIS ON CONTAMINATED MOLNW I
(aren/hr per pC1/m )
h TotalSod[
Skin N-3 0.0 0.0 C-14 0.0 0.0 RA-24 2.90E-08 2.90E-08 lr-[l 3
0.0 0.0 a
2.20E-10 2.60E-10 m -54 5.00E 09 6.00E-09 Mn-56 1.10E-08 1.30E-08 Fe-55 0.0 0.0 Fe-59 8.00E-09 9.40E-09 Co-58 7.00E-09 8.20E-09 Co 60 1.70E-08 2.00E-08 N1-63 0.0 0.0 Nr-65 3.70E-09 4.30E-09 4
1.50E-09 1.70E-09 bui5 4.00E-09 4.60E-09 2n 69 0.E 0.0 i
Br-83 5.40E-11 9.30E-11 i
Br-84 1.20E-08 1.40E-08 Br-85 0.0 0.0 Rb-86 5.30E-10 7.20E-10
(.
Rb-88 3.50E-09 4.00E-09 Rb-89 1.50E-08 1.00E fl8
$r-89 5.60E-13 6.50E-13 Sr-91 7.10E-09 8.30E-09
$r-92 9.00E-09 1.00E-08 Y-90 2.20E-12 2.60E-12 Y-91M 3.80E-09 4.40E-09 Y-91 2.40E-11 2.70E-11 Y-92 1.60E-09 1.90E-09 Y-93 5.70E-10 7.00E-10 Ir-95 5.00E-09 5.80E-09 Zr-97 5.50E-09 6.40E-09 It-95 5.10E-09 6.00E-09
.No-99 1.90E-09 2.20E-09 Tc-99M 9.60E-10 1.10E-09 Tc-101 2.70E-09 3.00E-09 Bu-103 3.60E-09 4.20E-09 Bu-105 4.50E-09 5.10E-09 Ru-106 1.50E-09 1.00E-09 A -110N 1.00E-08 2.10E-08 S
Te-125M 3.90E-11 4.80E-11 Te-12M 1.10E-12 1.30E-12 Te 127 1.00E-11 1.10E 11 Te-129N 7.70E-10 9.00E-10 Te-129 7.10E-10 0.40E-10 Te-131M 8.40E-09 9.90E-09 Te-131 2.20E-09 2.40E-06 Te-132 1.70E-09 2.00E-09 I-130 1.40E-08
~
3.40E-09 1.70E-08 I-131 2.00E 09 I-132 1.70E-08 2.00E-08 I-133 3.70E 4.00E-09 I-134 1.00E-08 1.90E-08 i- =
i.20E-08 i.40E.08 c
i.itt-41
TA8 LEE-6(Continued)
Element Total Body Skin Cs-134 1.20E-08 1.40E-08 Cs-136 1.50E-08 1.70E-08 Cs-137 4.20E-09 4.90E-09 Cs-138 2.10E-08 2.40E-08 Sa-139 2.40E-09 2.70E-09 Sa-140 2.10E-09 2.40E-09 8a-141 4.30E-09 4.90E-09 8a-142 7.90E-09 9.00E-09 La-140 1.50E-08 1.70E-08 La-142 1.50E-08 1.80E-08 Ce-141 5.50E-10 6.20E-10 Ce-143 2.20E-09 2.50E-09 Ce-144 3.20E-10 3.70E-10 Pr-143 0.0 0.0 Pr-144 2.00E-10 2.30E-10 Nd-147 1.00E-09 1.20E-09 W-187 3.10E-09 3.60E-09 NP-239 9.50E-10 1.10E-09 b
I 1.100-42
~
i 1
i l
calculattenal purposes, the average depth of the blood-forming organs may be assumed to be 5 cm.
l
('
Reference 12 also identifies the cells of the basal layer of epidernis as the tissue of interest 2
in the computation of skin dose and states an average depth for these cells of 7 ag/cm. This evidence is reflected in the dose factors presented in Table E-6 and also in those presented in Appendix B. Table B-1. for use in calculating esternal doses from noble gases.
Dese factors for internal esposure am provided in Tables E-7 through E-14 in units of eram per pC1 intake (Ref. 25).
Tables E-7 through E-10 are for inhalation (one table for each of the four age groups). uhile Tables E-11 through E-14 are for ingestion. Sese. factors provided for the inhalation of N-3 include an increase of 50 percent to account for the additional amount of this isotope absorbed through the skin (Ref. 25).
As discussed in Section B. " Discussion." these dose factors are appropriate for continuous intake over a ene-year period and include the dose commitment over a 50-year period. The cal-culational scheme by whi:h these dose factors are derived includes elementary consideration of changing physical and metabolic characteristics during the period over which the dose commitment is evaluated. For example, environmental exposure of an infant over a one-year period is treated as fo11ous: dose during the first year is computed based on infant physiological and metabolic characteristics considering both the buildup and decay of the appropriate organ burden; dcse during years 1-10 is computed based on child physiological and metabolic data considering decay of the organ burden from its peak value at age 1; dose during years 11-16 is treated in a similar fashion usine teenager characteristics; and dose during adulthood is computed based on the physiological and metabolic characteristics of an adult. Age-dependent parameters are changed in steps at the breaks betmeen age groups.
4.
Other parameters Table E-15 has been provided as a central location for the recommended values of many of the miscellaneous parameters appearing in equations in this guide. In some instances, a parameter's value or units is a function of the equation it is used in. Additionally, for some parameters used in calculating activities in vegetation. the value is also a function of the exposure path-may. Table E-15 has been 6rganized to note these complications.
Values of the parameter S. a structural shielding and occupancy factor, are given in p
k Table E-15 as 0.7 (for maximum individuals) and 0.5 (for the general population). Using the general approach given in Reference 26. the staff estimates an average structural shielding factor of 0.5 for typical reactor effluents. Assisning the maximum individual spends about 50 percent of the time indoors, the overall shielding and occupancy factor is then approximately 0.7.
The factor of 0.5 is used directly for population dose calculations. These factors are applicable for external gamma exposure from noble gases and for external exposure from contaminated ground surfaces.
l l
l 1
(
1.10g-43 1
- - ~ * * ~ - - -
. w, u_ z _ -__: _L? :
TASLE E-F PAGE 1 DF 3 INMALAftDN DO5E FACTORS FOR ADULTS
(* REM PEA PCI INMALEDI NUCLICE SONE liver T. AODY THYROID RIDNEY LUNG L1-LLI H
NO DATA 1.58E-07
- 1. 58F-0 7 1.58E-07 1 58E-07 1.58E-07 1.58E-07 C 14 2.27E-06 4.26E-07 4.26E-0 7 4.26E-07 4.26E-07 4.26E-07 4.26E-07 NA 24 1.28E-06 1.28E-06 1.28E-04 1.20E-06 1.28E-06 1.24E-06 1.28E-06
.g....
P 32 1.65E-04 9.64E-06 6.26 E-06 40 DATA NO DATA en DATA 1.00E-05 CR 51 40 DATA NO DATA 1.2 5 E-0 8 7.445-09 2.85E-09 1.80E-06 4.15E-07 MN 54 NO DATA 4.95E-06 T.8 F E-0 7 NO DATA 1.23E-06 1.75E-04 9.67E-06 NN 56 NO DATA 1.55E-10 2.29E-11 NO DATA 1.63E-10 1.18E-04 2.53E-06 l
FE 55 3.0TE-06 2.12C-06 4.91E-07 40 DATA NO DATA 9.01E-06 7.54E-07 l
FE 59 1.47E-06 1.47E-06 1.32 E-0 6 40 DATA NO DATA 1.27E-04 2.35E-05 CD 58 40 DATA 1.98E-07
- 59E-0 7 NO CATA NC DATA 1.16E-04 1.33E-05 CO 60 NO DATA 1.44E-06
- 1. S S E-0 6 40 DATA NO DATA 7.46E-04 1.56E-05 NI 43 5.40E-05 3.93E-06 1 81 E-06 40 DATA NO DATA 2.23E-05 1.67E-06 i-11 65 1.92E-10 2.62C-11 1.14F-11 NO DATA NO DATA 7.00E-07 1.54E-06 CU 64 NO DATA 1.83E-10 7.89E-11 NO DATA S.78E-10 8.48E-07 6.12E-06 ZN 65 4.05E-06 3.29E-05 9, 4 *E-0 6 40 DATA 8.62E-06 1.08E-04 6.68E-06 t.
24 69 4.23E-12 0.14C-12 5 i' IE-13 NO DATA 5 27E-12 1.15E-07 2.04E-09 WR 83 NO DATA 40 DATA 3.01E-08 NO DATA NO DATA NO DATA 2.90E-08 SR 84 NO DATA NO DATA 3.91E-08 NO DATA NO DATA NO DATA 2.05E-13 l
SR 8b NO DATA NO DATA 1.60E-09 'NO DATA NO DATA NO DATA LT E-24 MB 86 NU DATA 1.69E-05 7.37E-06 NO DATA NO DATA NO DATA 2.08E-06 RS 88 NO DATA 4.84E-08 2.41E-08 NO DATA 40 DATA NO DATA 4.18E-19 l
R8 59 NO DATA 3.20E-08 2.12E-08 NO DATA NO DATA NO DATA 1.16E-21 SR 89 3.80E-05 NO DATA 1.09E-06 NO DATA NO DATA 1.75E-04 4.37E-05 SR 90 1.24E-02 NO DATA
- 7. 62 E-0 4 NO DATA NC DATA 1 20E-03 9.02E-05 SR 91 7.74E-09 NO DATA 3.13E-10 NO DATA NO DATA 4.56E-06 2.39E-05 SR 92 8.43E-10 NO DATA 3.64E-11 NO DATA NO DATA 2.06E-06 5.38E-06 Y 90 2.61E-07 NO DATA 7.01 E-0 9 NO DATA NO DATA 2.12E-05 6.32E-05 Y 91M 3.26E-11 NO DATA 1.27E-12 NO DATA NO DATA 2.40E-07 1.66E-10 Y 91 5.TSE-05 NO DATA 1 55 E-06 40 DATA NO DATA 2.13E-04 4.81E-05 Y 92 1.29E-09 NO DATA 3.77E-11 40 DATA NO DATA 1.96E-06 9.19E-06 1
1.100-44
7ASLE E-7 CONT'D P43E 2 DF 3 l
INM&LATION DD5E F6CTORS FDR 60 ULT 5 i
184EM PER PCI INNALEDI l
buCLI3E SONE LIVER 7.803v TMVADID RIDNEY LUNG GI-LLI y 93 1.18E-50 40 DATA 5.26E-10 40 DATA NO DATA 4.06E-04 5.27E-05 2R 95 1 34E-05 4.3CE-06 2.91E 06 NO DATA 6.77E-06 2.21E-04 1.88E-05 2R 97 1.21E-08 2.45C-09 1.13E-0 9 NO DATA 3.71E-09 9.84E-06 6.54E-05 NS 95 1.76E-06 9.77E-07. 5.26E-07 40 DATA 9.67E-07 6.31E-05 1.30Em 5 no 99 NO DATA 1.51E-08
- 2. 87E-09 NO DATA 3.64E-08 1.14E-05 1.10E-t5 g...__-...................'.__._...__.....____.....
TC 99m 1.29E-13 3.64E-13 4.63E-12 40 0ATA 5.52E-12 9.55E-08 5.20E-tF TC101 5.22E-15 7.52E-15 7.38E-14 40 DATA 1.35i-13
- 4. 99E-08 I.36E-21
.AU103 1.91E-07 NO DATA 8.23E -0 8 NO DATA 7.29E-07 6.31E-05 1.38E AU105 9.88E-11 NO DATA 3.89E-11 NO DATA 1.27E-10 1.97E-06 6.02E-06 RU106 8.64E-06 NO DATA
- 1. 0 3E-0 6 40 DATA 1.67E-05 1.17E-03 1.14E-04 AC110p 1.35E-06 1.25E-06 7.43C-07 NO DATA 2.46E-06 5.79E-04 3.78E-05 TE125M 4.27E-07 1.90E-07
- 5. 84 E-0 8 1.31E-07 1.55s-06 3.92E-05 8.83E-06 TE127P 1.58E-06 7.21E-07 1.96E-0 7 4.11E-07 5.72E-06 1.20E-04 1.87E-05 TE127 1.75E-10 8.035-11 B. 8 7E-11 1.32E-10 6.37E-10 8.14E-07 7.17E-06 TE129* 1.22E-06 5.64E-07
- 1. 98 E-0 7 4.30E-07 4.57E-06 1.45E-04 4.79E-05 e
TEl29 6.22E-12 2.19E-12 1.5DE-12 4.87E-12 2.34E-11 2.42E-07 1.96E-08
(*
TF131 1.39E-12 7.44E-13 4.49E-13 1.17E-12 9.46E-12 1.74E-07 2.30E-09 TE131M 8.74E-09 5.45E-09 3.6 3 F-0 9 6.88E-09 3.86E-08 1.82E-05 6.95E-05 TE132 3.25E-08 2.69E-08 2.02E-08 2.37E-08 1.82E-07 3.60E-05 6.37E-05 I 130 5.72E-07 1.68E-06 6.60E-07 1.42E-04 2.61E-06 NO DATA 9.61E-07 1 131 3.15E-06 4.47E-06
- 2. 54 C-0 6 1.49E-03 7.66E-06 NO DATA 7.85E-07 8 132 1.45E-07 4.07E-07
- 1. 4 bE -0 7 1.43E-05 6.48E-07 NO DATA 5.08F-08 8 133 1.08E-06 1.85E-06 5.65E-07 2.69E-04 3.23E-06 NO DATA 1.11E-06 I 134 8.CSE-00 2.16E-07 7.69E-08 3.73E-06 3.44E-07 40 OATA 1.26E-10
. I 135 3.35E-07 8.73E-07 3.21 E-07 5.60E-05 1.39E-06 NO DATA 6.56E-07 C5134 4.665-05 1.06E-04 9.10E-0 5 NO DATA 3.59E-05 1.22E-05 1.30E-06 C5136 4.88E-06 1.83E-05 1.38E-05 40 DATA 1.07E-05 1.50E-06 1.46E-06 C1137 5.98E-05 7.76E-05
- 5. 3 5 E =0 5 NO DATA 2.78E-05 9.40E-06 1.05E-06 C1138 4.14E-08 7.76E-08 4.0$ E-0 8 40 DATA 6.00E -08 6.07E-09 2.33E-13 BA139 1.17E-10 8.32E-14 3.42 E-12 NO DATA 7.78E-14 4.70E-07 1.12E-07
-.. - ~._..........-..
b l
1.100-45 z -.
=
~u
=
F TABLL E-7, CONT'O P AG E 3 0F 3 14HALA7 ION 005E FACTom$ FOR ADULT $~
(" REM PER PCI letHALEDI NUCLicE SONE LIVER T.000Y THYR 010 Et04EY LUNG CI-LLI MA140 4.88E-06 6.13F-09 9.21 E-0 7 40 DATA 2.09E-99 1.59E-n4 2.73F-05 mA141 1.25E-11 9.41E-15 4.20E-13 40 DATA 8.75E-15 2.42E-07 1.45E-17 RA142 3.29E-12 3.38E-15 2.07E-19 NO DATA 2.86E-15 1.49E-07 1.96E-26 LA140 4.90E-00 2.17E-08 5.73E-09 40 DATA 40 DATA 1.70E-05 5.73E-05 LA142 8.54E-!!
3.88E-11 9.64E-12 NO 0#TA 4C DATA 7.91E-07 2.64E-07 CE141 2.49E-06 1.692-06
- 1. 91 L-0 7 NO CATA 7.83E-07 4.52E-05 1.50E-05 CE143 2.33E-09 1.72E-08 1.91E-09 40 DATA 7.60E-09 9.97E-06 2.83E-05 CE144 4.29E-04 1.79E-04
- 2. 30E-0 5 NO DATA 1.06E-04 9.72E-04 1.02E-04 PR143 1.17E-06 4.69E-07 5.00E-08 Mn DATA 2.70E-07 3.5tE-05 2.50E-05 PR144 3.76E-12 1.b6E-12
- 1. 91 E-13 90 CATA 8.m1E-13 1.27E-07 2.69E-18 40147 6.59E-07 7.62E-07 4.56E-08 NO OATA 4.45E-n7 2.76E-05 2.16E-05 W 187 1.06E-09 8.85E-10 3.10E-10 NO DATA 40 DATA 3.63E-06 1.94E-05 NP239 2.17E-08 2.82E-09
- 1. 55 E -0 9 NO DATA 8.75E-09 4.70E-06 1.49E-05 D
1 1.109-46
~
l FASLE E-B PAGE 1 DF 3 INHAL ATION DOSE FACTOR 5 FOR TEENAGER (NREW PER PCI INHALEDI NUCLICE DONE Liv [R T.00CY THvROIC RIONEY LUNG GI-LLt N
3 40 DATA 1.59E-OF
- 1. 59E -0 7 1.59E-07 1.59f-07 1.59E-07 1.59E-07 C 14 3.25E-06 6.C9E-0? 6.09E-0 7 6.09E-07 6.09E.07 6.09E-07 6.09E-07 14 24 1 72E-06 3.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1 72E-06 P 12 2.36E-04 1.57C-03 8.95E-06 90 DATA NC OATA NO DATA 1.16F-05 CR b1 NO DATA NO DATA 1.69F-08 9.37E-09 3.84E-09 2.62E-06 3.75E-07 MN 54 NO DATA 6.39F-06
- 1. 03E-0 6 40 DATA 1.59E-06 2.48E-04 8.35E-06 PN 56 NO DATA 2.12i-10 3.15E-13 NU DATA 2 246-10 1.90E-C6 7.18E-06 FE 55 4.18E-06 2.98E-06 6.93E-0 7 NO DATA 40 DATA 1.55E-05 7.99E-07 FE 51 1.19E-06 4.62E-06
- 1. 79E-0 6 NO DATA 40 DATA 1.91E-04 2.23E-05 o
CO $5 NO DATA 2.S9E-07 3.47E-07 NO DATA NO DATA 1.68E-04 1.19F-05 CD 60 40 DATA 1.8?E-06 2 4BE-06 NO DATA WG DATA 1.09E-03 3.24E-05
~
NI 6A 7 25E,05 5.43E-06 2.4 7E -0 6 NO DATA NO DATA 3.84E-05 1.77E-06 NI 6b 2.73E-In 3.o6F-11 1 59E-11 NO DATA NO DATA 1.17E-06 4.59E-06 CU 64 NO DATA 2.54E-10 1.06E-10 40 DATA 8.01E-10 1.39E-06 7.68E-06 IN 65 4.82E-06 1.07E-05
- 7. 80 E-0 6 NO DATA 1.08E-Ob 1.55E-04 5.83E-06 N
IN 69 6.04E-12 1.15F-11 8.07E-13 NO DATA 7.53E-12 1.98E-07 1.56F-08 MR 83 NO DATA NO DATA 4.30E-08 NO DATA NO DATA Mn DATA LT E-24 BR 44 NO DATA NO DATA 5.41E-08 NO DATA 40 DA1A NO DATA LT E-24 BR 85 NO DATA NO DATA
- 2. 2 9E-0 9 NO DATA NO DATA NO DATA LT E-24 48 86 40 DATA 2.38E-05
- 1. 0 $ E-0 5 40 DATA NO DATA NO DATA 2.21E-06 RS 88 NO DATA 6.82E-08 3.40E-08 NO DATA NO DATA NO DATA 3.65E-15 48 89 NO DATA 4.402-05 2.91E-04 NO DATA 40 DATA NO DATA 4.22E-17 SR 49 5.43E-05 40 DATA
- 1. 56E-0 6 NO DATA NC DATA 3.02E-04 4.64E-05 54 93 1.35E-02 NO DATA
- 8. 35E -0 4 NO DATA NO DATA 2 06E-03 9.56E-05 SR 91 1.10E-08 NO DATA 4.39E-10 NO DATA NO DATA 7.59E-06 3.24E-05 SR 92 1 19E-C9 WO DATA 5.08E-11 NO DATA NO DATA 3.43E-06 1 49E-05 Y 90 3 73E-07 NO DATA 1 00E-08 NO DATA 40 DATA 3 66E-05 4.99E-05 Y 91W 4.63E-11 NO DATA 1.77E-12 40 DATA NO DATA 4.00E-07 3.77E-09 Y 91 8.2aE-05 NO DATA 2.21E-06 NO DATA NO DATA 3 67E-04 5.11E-05 Y 92 1.84E-09 WO DATA 5.36E-11 40 DATA NO DATA 3.35E-06 2.06E-05
................ _...... -.. -. ~.. _............
('.
1.100-47
i 7ASLE E-8, CONT'D P AGE 2 0F 3 INMAL ATION DOSE FACTORS FOR TEFNAGER l# rem PER PCI 19HALEDI NUCLIOE BONE L!vFR 7.000Y TNVROID R104EY LUNG CI-LLI I
Y 93 1 69E-08 NO DATA 4.65E-10 NO DATA NO DATA 1.04E-05 7.24E-05 ZR 95 1.82E-05 5.73E-06
- 3. 94 E-06 NO DATA 8 42E-06 3.36E-04 1.06E-05 la 97 1.72E-08 3.40E-09
- 1. 5 7E-09 NO DATA 5.15E-09 1.62E-05 7.88E-05 N8 95 2.32E-06 1.29E-06
- 7. 08E-0 7 NO DATA 1.25E-06 9.39E-05 1.21E-05
'm0 99 NO DATA 2.11E-08 4.03E-09 NO DATA 5.14E-08 1.92E-05 1.36E-05 TC 998 1 73E-13
- 4. 8 3C-I l 6.24E-12 No DATA 7.20E-12 1.44E-07 7.66E-07 TC101 7.40E-15 1.05E-14 1.03E-13 NO DATA 1.90E-11 8.34E-08 1.09E-16 RU103 2.63E-07 NO DATA 1.12 E-0 7 NO DATA 9.29E-07 9.79E-05 1.36E-05 RU105 1.40E-10 NO DATA 5.42E-11 h0 DATA 1.76E-10 2.27E-06 1.13E-05
(
RU106 1.23E-05 NO DATA
- 1. 55E-06 NO DATA 2.38E-05 2.01E-03 1.20E-04 AG110M 1.73E-06 1.64E-06
- 9. 99E-0 7 NO DATA 3.13E-06 8.44E-04 3.41E-05 TE12s> 6.10E-07 2.80E-07
- 8. 34 E-0 8 1.75E-07 NO DATA 6.70E-05 9.38E-06 TE127m 2.25E-06 1.02E-04 2.73E-07 5.48E-07 8.17E-06 2.07E-04 1.99E-05 TE127 2.51E-10 1 14F-10 5.52E-11 1.77E-10 9.10E-10 1.40E-06 1.01E-05 l
TE129m 1.74E-06 8.23E-07
- 2. 81 E-0 7 5.72E-07 6.49E-06 2.47E-04 5.06E-05 i
l TE129 8.87E-12 4.22E-12 2.20E-12 6.4AE-12 3.12E-11 4.12E-07 2.02E-07 TE131m 1.23E-08 7.51E-09 5.03E -0 9 9.06E-09 5.49E-08 2.97E-05 7.76E-05 TE131 1.97E-12 1.04E-12 6.30E-13 1.55E-12 7.72E-12 2.92E-07 1.89E-09 TE132 4.50E-08 1.e3E-00
- 2. 74 E-0 8 3.07E-00 2.44E-07 5.61E-05 5.79E-05 I 130 7.80E-07 2.24E-06 8.96 E-0 7 1.86E-04 3.44E-06 NO DATA 1.14E-06 1 131 4.43E-06 6.14E-06
- 3. 30E-06 1.83E-03 1.05E-05 NO DATA 8.11F-07 I 132 1.99E-07 5.47E-07 1.97E-0 7 1.89E-05 8.65E-07 NO DATA 1.59E-07 I 133 1 52E-06 2.36E-06
- 1. 05 E-0 7 4.94E-06 4.58E-07 ho DATA 2.55E-09 8 135 4.62E-07 1.18 E-06 4.36E-07 7.76E-05 1.86E-06 NO DATA 8.69E-07 C5134 6.28E-05 1.41E-04 6.86E-0 5 NO DA TA 4.69E-05 1.83E-05 1.22E-06 C5116 6.44E-06 2.42E-05 1.71E-05 NO DATA 1.38E-05 2.22E-Oe 1.36E-06 C5137 8.38E-05 1.06E-04
- 3. 89E-0 5 N0 DATA 3.80E-05 1.51E-05 1.06E-06 C5138 5.82E-08 1.07E-07 5.58E-08 NO DATA 8.28E-08 9 84E-09 3.38E-11 84139 1 67E-10 1.18E-13 4.87E-12 NO DATA 1.11E-13 8.00E-07 8.06E-07 t
6 4
e e
I 1.HD-48
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TasLE E-8, CONT'O PAGE3OF3 INHALATION DUM F ACTOR $ FOR TEENAGER (MAEM PER PCI INM ALED)
NUCL10E SONE LIVER T. BO DY THYROID RIDNEY LUNG CI-LLI SA140 6.04E-06 S.3eF-09 4.40E-0 7 NO DATA 2.SSE-09 2.54E-04 2.86E-05 SA141 1.78E-11 1.42E-14 S.93E-13 NO DATA 1.23E-14 4.11E-07 9.33E-14 b4142 4.62E-12 4.63E-15 2.84E-13 NO DATA 3.92E-15 2.39E-07 5.99,E-20 L&140 5.99E-08 2.95E-08
- 7. 82 C-09 NO CATA NO DATA 2.6tE-05 6.09E-05 LA142 1.20E-10 5.3tE-11 1.32E-11 ho DATA 40 DATA 1.27E-06 1.50E-06 CE141 3.55E-06 2.37E-06 2.71E NO DATA 1.11E-06 7.67E-05 1.58E-05
.........-......._...-._-07..........................
CE141 3.32E-00 2 42E-00 2.70E-0 9 NO DATA 1.00E-00 1.63E-05 3 19E-05 CE144 4 11E-04 2.53E-04
- 3. 2 e E-0 5 NO DATA 1.51E-04 1.67E-03 1.00E-04 P*143 1 67E-06 4.64E-07 S.2 0 E-0 8 NO DATA 3.86E-07 6 04E-05 2 67E-05 PR144 5.37E-12 2.20E-12 2.72E-13 NO DATA 1.26E-12 2.19E-07 2.94E-14 ND147 9.83E-07 1.07E-06 6.41E-Os NO DATA 6.26E-07 4.65E-05 2.28F-05 W 187 1 50E-09 1.22E-09
- 4. 2 9 E-10 NO DATA NO DATA 5.92E-04 2.21E-05 NP239 4.23E-08 3.99E-09 2.21 E-0 9 40 DA1A 1.2SE-06 A.11E-06 8.65E-05
~
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l$ 1.10649
TAGLE E-7 PAGE 1 0F 3 IMHAL ATION OCSE FACTOR $ FOR CHILD 1matM PER PCI 14MALEDI 4UCLIUE SONE LIVER fiAODY THYROID RIONEY LUNG GI-LLI
......-4..............
et 3
NO DATA 3.c4E-07 3.04E-0 7 1.046-07 1.04E-07 3.04E-07 5.04E-07 C 14 9.70E-06 1.82E-06
- 1. 92 E-0 6 1.E2E-06 1.82E-06 1.02E-06 1.82E-06 NA 24 4.35E-06 4.350-06
- 4. 35E -0 6 4.3%E-06 4.35E-ro 4.15E-06 4.35E-06 P 32 7.04E-04 1.r9E-05 2.67[-05 NO DATA NO DATA NO DATA 1.14E-05 CR 51 NO DATA NO DATA 4.17 E-0 4 2.31F-08 4.57E-99 4.59E-06 2.93E-07 NN 54 40 DATA 1.I6E-05
- 2. 57f -0 6 NU DATA 2.71E-06 4.26E-04 6.19F-06 NN 56 NU DATA 4.4eE-10 9,43E-11 NO DATA 4.52E-10 3.55C-06 3.33E-05 FE 55 1.28E-05 6.00E-06 2.10E-0 6 MO DATA 40 CATA 3.00E-05 7.75E-07 FE 59 5.59C-06 9.c4E-06 4.51[-06 40 DAT4 40 DATA 3.430 04 1.91E-05 C0 SS 40 DATA 4.T9E-07 8.55E-07 NO Daft NO DATA 2.99E-04 9.29E-06 CO 60 NO DATA 3.55E-06 6.12E-06 90 DATA 40 DATA 1.91E-03 2.60E-05 NI 63 2.22E-04 1.257-05 7.56E-06 40 DATA NO DATA 7.43E-05 1.71F-06 tal 65 4.CSE-10 7.99E-11 4.44E-11 to DATA NO DATA 2.21E-06 2.27E-05 CU 64 NO DATA 5.39E-10 2.90E-10 NO DATA 1.63E-09 2.59E-06 9.92E-06 2.% 6S 1.15E-05 3.06E-05 1.900-05 40 DATA 1.93E-05 2.69E-04 4.41E-06 2 N 61 1.81E-11 2.61E-11 2.41E-12 NO DATA 1.5tE-11 3.84E-07 2.75F-06 MA 01 NO DATA NO DATA 1.28E-07 40 DATA NO DATA k0 DATA LT E-24 GR R4 NO DATA NU OATA 1.4AE-07 NO DATA NO DATA NC DATA LT E-24 et SS NO DATA NO DATA
- 6. 84 E-0 9 NO DATA NO DATA NO DATA LT E-24 MD 46 NO DATA 5.36C-05 1.09E-05 NO CATA NO DATA NO DATA 2.16E-06 RP 08 NO DATA 1.52E-OF 9.90E-08 NO DATA NO DATA NO DATA 4.66E-09 RB 89 NO DATA 9.33t-08 7.OsE-Os 40 DATA NO DATA NO DATA 5 11E-10 14 39 1.62E-04 NO DATA 4.66E-06 NO DATA NO DATA 5.81C-04 4.52E-05 1R 90 2.73E-02 NO DATA
- 1. 74E-0 3 NO DATA NC DATA 3.99E-03 9.28E-05 SP 91 3.25E-04 NO CATA 1.247.-09 40 DATA NO DATA 1.44E-05 4.70E-05 SR 92 3.54E-09 NO DATA 1.42E-10 NO DATA NO DATA 6.49[-06 6.55E-05 Y 90 1.11E-C6 NO DATA
- 2. 9 4F-0 0 NO DATA NO DATA 7.07E-05 7.24E-05 Y 91P 1.37E-10 NO DATA 4.94E-12 40 DATA NO DATA 7.60F-07 4.64E-07 Y 91 2.47E-04 40 DATA 6.5 9 E -0 6 40 DATA NO DATA 7.10E-04 4.97E-05 l
Y 92 5.50E-09 NO DATA 1.57E-10 40 DATA NO DATA 6.46E-C6 6.46E-05 l
I t
t
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1.100-50
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y
(
7ABLL E-9, C09f'D PC E 2 DF 3 INHAL ATION DLSE F ACT045 FOR CHILO 1* REM PER PCI INHALE 03 guCLIDE SO9E LIVER
- 7. 60DY THvm010 RIDgEY LU9G GI-LLI Y 93 5.04E-08 NO DATA
- 1. 30 E-0 9 NO 047%
NO DATA 2.01E-05 1.05E-04 2R 95 S.1AE-05 1.13E-05 1.00E-05 NO DATA 1.616-05 6.03F-04 1.65E-05 ER 97 5.07E-08 7.A4E-09 4.32E-09 NO DATA 1.05E.08 3.06E-05 9.49E-05 NB 95 6.35E-06 2.48E-06
- 1. 77E -0 6 NO DATA 2.33E-06 1.66E-04 1.00F-Ot MO 99 NO DATA 4.66E-06 1.15E-08 NO DATA l.06E-07 3.66E-05 1.42E-05 TC 99P 4.81E-13 9.41C-13 1.56E-11 NO DATA 1.37E-11 2.57E-07 1.30E-06 1
7C101 2.19C-14 2.30E-14 2.91E-13 No DATA 3.92E-13 1.SAE-07 4.41F-09 RU103 7.55E-07 NO DATA.
- 2. 90F-0 7 No DATA 1.40E-06 1.79E-04 1.21E-C5 RU105 4.13E-10 NU DATA 1.SCE-10 NO DATA 3.63E-10 4.30E-06 2.6)E-05 RU106 3.68E-05 NO DATA 4.5 7E-0 6 NO DATA 4.97F-05 3.87E-03 1 16E-04 AG110* 4.56E-06 3 00E-06 2.47E-06 ko DATA 5.74L-06 1.40F-03 2.71E-05 7E125m 1.02E-06 6.29E-07 2.47E-07 5.20!-07 NC OATA 1.29E-04 9.13E-06 TE127M 6.72E-06 2.31E-Oe 8.luf-07 1.64E-06 1.72E-05 4.00E-04 1.93F-05 TE127 7.49E-10 2.57[-10
- 1. 65 E-10 5.30E-10 1.911-09 2.71F-06 1.52E-05 TEl217 5.19E-C6 1.8bE-06 8.22E-07 1.71E-06 1.36E-05 4.76E-04 4.91E-05 1
TE129 2.64E-11 9.45E-12 6.44C-12 1.93E-11 6.94L-11 7.91E-07 6.89E-06 TE1317 3.63E-C8 1.60E-08 1.37E-00 2.64E-00.1.00E-07 5.56E-05 0.32E-05 Th131 S.87[-12 2.28E-12 1.78C-12 4.59L-12 1.59C-11 5.55E-07 3.60E-07 TF132 1.30E-07 7.36C-08 7.12 E-0 8 8.b8E-08 4.79L-07 1.02E-04 3.72E-05 1 130 2.21E-06 4.43!-06 2.2RE-06 4.99E-04 6.61L-06 NO DATA 1.30E-06 I 131 1 30E-05 1.30F-05
- 7. 37 E-0 6 4.39E-03 2.136-05 N9 OATA 7.60F-07 I 132 5.72E-07 1.10E-06 5.0FF-07 5.23F-05 1.69E-C6 NO DATA 8.65E-07 1 133 4.40C-06 5.49 -06 2 00E-06 1.04C-03 9.13E-06 NO DATA 1.48E-06 I 134 3.17E.07 5.845-07 2.6 9E -0 7 1.37E-05 8.92E-07 NO DATA 2.58E-07 I 135 1.13E-06
- 2. lee-06 1.12 E -0 6 2.14:-04 3.62E-06 NO DATA 1.20E-06 C5134 1.76E-04
- 2. 74 C-04
- 6. 0 7 E-0 5 90 DATA 8.13E-05 3.27E-05 1.04E-06 C5116 1.76E-05 4.62E-Ob 3.14E-05 b.? DATA 2.58E-05 3.93E-06 1.13t-06 C5137 2.45E-04 2.232-04 3.47F-05 NO DATA 7.63E-05 2.81E-05 9.7AE-07 C5138 1 71E-07 2.27E-07 1.50E-07 NO DATA 1.68E-07 1.04E-08 7.29F-08 A4139 4.98E-10 2.66F-13 1.4SE-11 NO DATA 2.33E-13 1.b6E-06 1.56E-05 s
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1.100-51 l'
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i 7 ABLE E-te CONT'D i
PAGE30F3 INHALATION DOSE FACTO 45 FOR CHILO INAtm PER PCI 89HALEDI NUCL1UE SONE LIVER 7.800Y THYRDID RIONEY LUNG GI-LLI 44140 2.00E-05 1.75E-OS 1.17E-0 6 NO DATA 5.71E-09 4.71E-04 2.75E-05 84141 5.2*E-11 2.95E-14 1.72F-12 NO DATA 2.56E-14 7.89E-07 7.44E-08 34142 1.e5E-11 9.73E-15 7.b4E-13 NO CATA 7.87E-15 4.44E-07 7.41F-10 f.4140 1.74E-07 6.08E-04
- 2. 04 E-0 8 NO DATA 40 DATA 4.94E-05 6.10E-05 LA142 S.50E-10 1.11E-10 3.49E-11 NO DATA NO DATA 2.35E-06 2.05E-05 i
CE141 1.06E-CS 5.20E-06
- 7. 83E-O F 40 DATA 2.31E-06 1.47E-04 1.53E-05 CE143 9.89E-08 5.37E-08 7.77E-09 NO DATA 2.26E-08 3.12E-05 3.44E-05 CE144 1 83E-03 5.72E-04 9.7 7 E-0 5 NO DATA 3.17E-04 3.23E-03 1.05f-04 PR143 4.99E-06 1 50E-06 2.47 E-0 7 40 DATA 0.11t-07 1.17E-04 2.63E-05 i
PRl44 1.61E-11 4.996-12 0.10E-13 No DATA 2.64E-12 4.23E-07 5.32E-08 N0147 2.92E-06 2.36E-06
- 1. 04 E-0 7 NO DATA 1.50E-06 S.87E-05 2.22F-05 I
W 107' 4.41E-09 2.61E-09 1 17F-09 NO DATA NC DATA 1.11E-05 2.46E-05 NP239 1.76E-07 9.04?-09 6.35E-09 NO DATA 2.43E-08
- 1. ?,7 E-05 1.73E-05 4
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TABLE E-10 PAGE 1 DF 3 INMALAY108e DOEE FACTDR5 FOR INFAlef (MREM PGA PCI la:NALE03
~.
m 7 uCL W.q.A._p-g;L4WER
-88.800E TMYR0lO RIONEY Lusec st-LLI
.~
3 -...
i De 3
NO DATA 4.62E-07 4.62E-07 4.62F-07 4.62E-07 4.62E-07 4.62E-07 i
C 14 1.89E-05 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 j
ee4 24 7.S4E-06 7.54E-06 7.54E-06 7.54si-06 7.54E-06 7.54E-06 7.54E-06 P 32 1 45E-03 8 03E-05 5.53E-Ob 900 DATA B00 DATA 000 DATA 1.15E-05 CR 51 es0 DATA J00 D AT A 6.39E-08 4.1~1E-08 9.45E-09 9 17E-06 2 55E-07 som 54 NO DATA 1.81E-05 3.56E-06 seo DATA 5.56E-06 7.14E-04 5.04E-06 NN 56 seO DATA 1.10E-09 1.58E-10 NO DATA 7.86E-10 8.95E-06 5.12E-05 I
FE 55 1.41E-05 8.59E-06 2.18E-06 800 DATA 800 D A T A 6.21E-05 7.82E-07 l
FE 59 9.69E-06 1.68E-05 6.7 FE- 06 etO DATA se0 DATA 7.25E-04 1.77E-05
[
CD 50 eeu DATA S.71E-07 1.30E-O& 800 DAT A 800 DATA 5.55E-04 7.95E-06 CO 60 800 DATA 5.73E-06 8.41 E-06 8eo DATA 800 DATA 3.22E-03 2.28E-05 fel 63 2.42E-04 1.46E-05 8.29C-0 6 800 DATA
- Sec DATA 1.49E-04 1.73E-06 set 65 1.71E-09 2.03C-10 9.79E-1g a00 DATA 800 DAT A 5.00E-06 3.58E-05 CU 64 000 DATA 1 44E-09 5.53E-10 800 DATA 2.04E-09 6.64E-06 1.07E-05 l
28e 65 1 38E-05 4.47E-05 2.22E-0 5 se0 DATA 2.32E-05 4.62E-04 3.67E-05
(
2N 69 3.85E-11 6.91E-11 5.13E-12 NO DATA 2.87E-11 1.05E-06 9.44E-06 SR 83 000 DATA 800 DATA
- 2. 72E-0 7 800 DATA sto DATA NO DATA LT E-24 SR 44 se0 DATA 800 DATA
- 2. 86E-0 7 toO DATA 000 DATA esO DATA LT E-24 OR 83 800 DATA 800 DATA 1.46E-08 te0 DATA 90 DATA 000 DATA LT E-24 28 86 te0 DATA 1.36E-04
- 6. 30E-0 5 000 DATA Is0 DATA DeO DATA 2.14E-06 28 88 800 D A T A 3.98E-07 2.0sE-07 suo DATA 800 DATA eso D AT A 2.42E-07 Rg og ee0 DATA 2.29E-07 1.47 E-0 7 peo DATA seo DATA 800 DATA 4.87E-08 SR 89 2.84E-04 se0 DATA S.15C-06 seO DATA 800 DATA t.45E-03 4.57E-05 SR 90 2.925-02 seu DATA 1.85E-03 see DATA 900 DATA S.03E-03 9.36E-05 SR 91 6.83E-08 alO DATA 2 47E-09 000 DATA 000 DATA 3.76E-05 5.24E-05 SR 92 7.50E-09 NO DATA 2 79E-10 800 DATA 800 DATA 1.70E-05 1.00E-04 Y 90 2,35E-06 000 DAT A 6 30E-08 esO DATA 800 DATA 1.92E-04 7.43E-05
. -. ~......-
Y 91P 2.91E-10 000 DATA 9.90E-12 NO DATA 90 DATA 1.99E-06 1.68E-06 Y 91 4.20E-O' 800 DATA 1.12E-05 880 DATA 800 DATA t.75E-03 5.02E-05 Y 92 1 17E-08 100 DATA 3.29E-10 ese DATA 900 DATA 1 75E*05 9.04E-05 O
1 I
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TABLE E-10 CONT'O PA3E 2 0F 3 Isew&LATION DCSE FACTORS FOR INFANT l# REM PCR PCI INH ALEDI NUCLICE SONE LIVER T.BOpf THYA0!D RIONEY LUNG GI LLI Y 93 1.07E-07 NO DATA 2.91E-09 40 DATA
'ND DATA S.46E-05
- 1. gut-04 2R 95 S.24E-03 1.99E-05 1.45E-0 5 NO DATA 2.22t-n5 1.2SE-03
- 4. 59E-06
- 2. 70E-06 NO DATA 3.57E-06 3.42E-04 9.05E-06 MO 19 NO DATA 1.18t-07
- 2. 31 E-0 8 NO DATA 1.99E-07 9.63E-05 3.48E-05 TC 99p 9.98E-13 2.0&E-12 2.66E-11 40 OATA 2.22E-11 5.79E-07 1.45E-06 TC101 4.65E-14 5.90E-14 S.00E-13 40 OATA 6.99E-13 4.17E-07 4.03E-07 RU103 1.44E-06 NO DATA
- 4. 85 E-0 7 NO DATA 3.03E-06 3.94E-04 1.15E-05 2U105 S.74E-10 40 DATA 2 93E-10 NO DATA 6.42E-10 1.12E-05 3.46E-05 RU106 4.20E-05 NO DATA
- 3. 5 7 E-06 40 DATA 7.00E-06 2.62E-03 2.36E-05 TE125M 3.40E-06 1.42C-06
- 4. 70 E-0 7 1.16E-06 NO DATA 3.19E-04 9.22E-06 TE127p 1.19E-05 4.9 3E-06 ' t.4 ti-0 6 3.40E-06 2.68E-05 9.37E-04 1.95E-05 TE127 1.59E-09 6.81E-10 3.49E-10 1 32E-09 3.47E-09 7.39E-06 1.74F-05 7E129*
- 1. elf-05
- 4. 3 5 E-06 1.59E-0 6 1.91E-04 2.27E-05 1 20E-05 4.93E-05 TE129 S.63E-11 2.4eE-11 1.34E-18 4.02E-11 1.2bE-10 2.14E-06 1.90E-05 TEt31M 7.62E-08 3.93E-08 2.59E-08 6.30E-00 1.89E-07 1 42E-04 S.51E-C5 TE131 1 24E-11 S.87E-12 3.57E-12 1.13E-11 2.85E-11 1.47E-06 5.87E-06 s...--
TE132 2.66E-07 1.69E-07 1.26E-07 1.99E-07 7.39E-07 2.43E-04 3.15E-05 1 130 4.54E-06 9.91E-06 3.90E-06 1.14E-03 1.99E-05 NO DATA t.42E-06 8 131 2.71E-05 3.17E-05 1.40E-0 5 1.06E-02 3.70E-05' NO DATA 7.56E-07 I 132 1.21E-06 2.53E-06 S.99E-07 1.21E-04 2.42E-06 40 DATA 1.36E-06 I 133 9.46E-06
- 1. 3 7E-05 4.00E-06 2.54E-03 1.60E-05 NO DATA 1.54E-06 8 134 6.60E-07 t.34E-06 4.75E-07 9.10E-05 1.49E-06 NO DATA 9.21E-07 8 135 2.76E-06 S.43E-06 1.99E-06
- 4. 97E- 04 4.05E-o6 NO DATA 1.31E-06 CS134
- 2. 8 3E-04 S.02E-04 S.32E-05 NO DATA t.36E-04 S.69E-05 9.53E-07 CS136 3.4SE-05 9.61E-05 3.78E-05 NO DATA 4.03E-05 S.40E n6 1.02E-06 CS137 3.92E-04 4.37F=04
- 3. 2SE-05 NO DATA t.23E-04 S.09E-05 9.53E-07 C$138 3.61E-07 S.SOE-07 2 84E-07 NO DATA 2.9 3E-07 4.47E-08 6.26F-07 54139 1 06E-09 7.03E-13 3.07E-11 NO DATA 4.73E-13 4.25E-06 3.64F-05 b
e 1.15-54
1 I.
TASLE E-19 CONT'D PAGE5DF 5 IantALATION DOSE FACIORS FOR INFANT (WREM PER PCI IMMALEOS NGCL l0E
, SONE LIVER E.50DY THYa010 RIDNEY LUNG GI-LLI j
e4140 4.00E-05 4.00E-04 2.07E-06 NU OATA 9.59E-09 1.14E-03 2.74E-05 FA141 1.92E-10 7.70f-14 3.55E-12 NO DATA 4.64L-14 2.12E-06 5 39F-06 MA142 2.84E-11 2.36!-14 1.40E-12 NO DATA 1.16E-14 1.15E-04 4.95E-07 LA140 3.61E-07 1.43t-07 3.60E-03 NO DATA NO DATA 1.20E-04 4.06E-05 LA142 7.36E-10 2.69E-10 6.4*E-11 No DATA NO DATA 5.07E-06 4.2SE-05 CE141 1.98E-05 1.19E-05 1.42E-0 6 NO OATA 3.75t-06 3 69E-04 1.54E-05 CE143 2.09E-07 1.90E-07 3.59E-OS NO DATA 4.03E-08 8.50E-n5 3.55E-05 CE!*4 2.2SE-03 S.eSt-04
- 1. 26E -04 NO DATA 3.84E-04 7.03E-03 1.06E-04 PA143 1.00E-05 9.74E-06 4.99E-0 7 NO DATA 1.41E-06 3.09E-04 2.66E-05 PR144 3.42t-11 1.32E-11 1.72E-12 NO DATA 4.40E-12 1.15F-06 3.06E-06 4014 F 5.67E-06 5.01F-06
- 3. 57 E-0 7 NO DATA 2.2SE-06 2.30E-04 2.23E-05 W 187
' 26E-09 6.44E-09 2.2 SE-0 9 NO DATA NO DATA 2.83E-05 2.54E-05 NP239 2.65E-07 2.37E-OS 1.34E-08 N0 DATA 4.73L-08 4.25E-05 1.78E-05 1
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TABLE E-11 PAGE l' 0F 3 BNGESTION 00$E FACTORS FOR ADULTS
(* REM PER PCI INGESTEDI NUCLII;E SONE LIVER T.ROGY TNYRDIO RIONEY LUNG GI-LLI H
3 NO DATA 1.05E-07 1.0S E-0 7 1.05E-07 1.05E-07 1.05E-07 1.05E-07 C 14 2.04E-06 5.68E-07 5.6 SE-0 7 5.68E-07 5.68E-07 5.6fE-07 5.68E-07 NA 24 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-96 1 70E-06 1.70E-06 P S2 1.93E-04 1.20E-05 7.46E-06 NO QATA NO DATA NO DATA 2.17k-05 CR 51 NO DATA 800 CATA 2.6*E-09 1.59E-09 5.86E-10 3.53E-09 6.69E-07 NN 54 eso DATA 4.57E-06
NN 56 NO DATA 1.15E-07 2.04E-08 NO DATA 1.46E-07 NO DATA 3.67E-06 FE 55 2.75E-06 f.90F-06 4.4 3 E-0 7 NO DATA NO DATA 1.06E-06 1.09E-06 FE 59 4.34E.06 1.02E-05 3.91E-06 NO DATA NO DATA 2.SSE-06 3.40E-05 CO 58 NO DATA 7.456-07 1.67E-06 N0 DATA NO DATA NO DATA 1.51E-05 CD 60 NO DATA 2.14E-06 4.72E-06 NO DATA NO DATA NO DATA 4.02E-05 NI 63 - 1 30E-04 9.01E-06 4.36E-06 NO DATA 40 DATA NO DATA 1.84E-06 N1 ob 5.20E-07 6.86E-08 3.13E-00 NO DATA NO D&TA NO DATA 1.74E-06 CU 64 NO DATA S.33E-08 3.91E-08 NO DATA 2.10E-07 NO DATA 7.10E-06 2N 65 4.84E-06 1.54E-05
- 1. 3 7 E-0 9 40 DATA 1.28E-Os NO DATA 2.96E-09 SR 83 40 DATA NO DATA 4.02E-08 NO DATA NO DATA NO DATA 5.79E-08 SR 84 NO DATA MO DATA 5.21E-08 NO DATA NO DATA NO DATA 4.09E-13 SR 85 NO DATA NO DATA 2.14 E-0 9 NO DATA NO DATA NO DATA LT E-24 RB 86 NO DATA 2.11E-05
- 9. 0 3 E-0 6 NO DATA NO DATA NO DATA 4.16E-06 Re se NO DATA 6.05E-00 1.21E-00 NO DATA 40 DATA NO DATA S.36E-19 R8 09 NO DATA 4.01E-08 2.82E-08 40 DATA NO DATA NO DATA 2.33E-21 SR 89 3.00E-04 40 DATA
- 8. 84 E-04 40 DATA NO DATA NO DATA 4.94E-05 SR 90 7.58E-03 NO DATA 1.86E-03 40 DATA NO DATA NO DATA 2.19E-04 SR 91 5.47E-06 NO DATA 2.29E-gy a00 DATA NO DATA 40 DATA 2.70E-05 SR 92 2.15E-06 40 DATA
- 9. 30E -0 8 MO DATA NO DATA NO DATA 4.26E-05 i
V 90 9 62E-09 40 DATA 2.58E-10 NO DATA 40 DATA NO DATA 1.02E-04 V 91M 9.09E-11 NO DATA 3.52E.12 NO DATA NO DATA NO DATA 2.67E-10 Y 91 1.41E-0.7 NO DATA 3.77E-09 NO DATA NO DATA NO 04TA 7.76E-05 Y 92 S.45E-10 NO DATA 2.47E-11 NO DATA NO DATA NO DATA 1.40E-05
. -........ _....-....~..... -.
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4 1.100-56 n--,---..,,n,-r-.-,--w,_n---,n,n,,n.,,,..,___,,n,,..,_,,,_,_,,,,,_-,---,n-___,-,-,-n,,,,_. -, - -,, -,, _,,,. _ _ _,, _ _ _ _ _ _ _ - - - - - -_-_ _,
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TABLE E-11, CONT'O I
PAGE 2 OF 3 INGESTIDN DOSE F6CTD95 FOR ADULIS (PREM PER PCI INGESTEDI NUCLICE BONE LIVER 7.8007 TNYROIC EIDNEY LUNG SI-LLI Y 93 2.60E-09 NO DATA 7.40E-11 NO DATA NO DATA NO DATA S.50E-05 2R 95 3.04E-On 9.75E-09 6.60E-0 9 NO DATA 1.53E-08 NO DATA 3.09E-05 2R 97 8.68E-09 3.39E-10 1 55E-10 NO DATA 5.12E-10 NO DATA 1.05E-04
..... -........ -.. ~.....
........_.... ~......
48 95 6.22E-09 3.46E-09
- 1. 86E-0 9 NO DATA 3.42E-09 NO DATA 2.IbE-05 i
NO 99 NO DATA 4.31E-06 S.20E-07 MO DATA 9.76E-04 NO DATA 9.99E-06 i
TC 99M 2.47E-10 6.90E-10 S.99E-09 NO DATA 3 061' ^1 3.42E-10 4.15E-07 TC101 2.b4E-10 3.6&E-10
- 3. 59E-0 9 NO DATA 4.59E-09 2.87E-10 1.10E-21 j
RU103 1.tSE-07 NO DATA 7.97E-03 NO DATA 7.06E-07 NO DATA 2.16E-05 i
RU105 1.54E-Os Nu OATA 6.08E-09 NO DATA 1 99E-07 NO DATA 9.42E-06 l
RU106 2 75E-06 40 DATA 3.48 E-0 7 NO DATA 5.31E-06 NO DATA 1.78E-04 AG110M 1.60E-07 1.48E-07 S.79E-08 NO DATA 2.91E-07 NO DATA 6.04E-05 TE125M 2.68E-06 9.71E-07 3.59E-0 7 8.06E-07 1.09E-05 NO DATA 1.07E-05 t
TE127M 6.77E-06 2.42[-06 8.25 E-0 7 1.73E-06 2.75E-05 NO DATA 2.27E-05 l
TE127 1.10E-07 3.95E-08
- 2. 38 E-0 8 S.15E-00 4.4BE-07 NO DATA S.6BE-06
(
TE129M 1.15E-05 4.29E-06
- 1. n2 E-0 6 3.95E-06 4.80E-05 NO DATA 5.79E-05
(
TE129 3.14E-08 1.18E-08
- 7. 63 E-0 9 2.41E-00 1.32E-07 NO DATA 2.37E-08 TE131M 1.73E-06 S.46C-07 7.05E -0 7 1.34E-06 0.57E-04 NO DATA 0.40E-05 TE131 1.97E-Os 5.23E-09 6.22 E-0 9 1.62E-08 8.63E-08 NO DATA 2.79E-09 TE132 2.52E-06 1.63E-06
- 1. 53 E-0 6 1.00E-06 1.57E-05 NO DATA 7.71E-05 1 130 7.56E-07 2.23E-06
- 0. 00E-0 7 1.99E-04 3.48E-06 NO DATA 1.92E-06 I 131 4.16E-06 5.95E-06
- 3. 41E-0 6 1.95E-03 1.02E-05 NO DATA 1.57E-06 8 132 2.031-07 5.43E-07 1.90E-0T 1.90E-05 0 65E-07 NO DATA 1.02E-07 3 133 1.42E-04 2.47E-06 7.53E-07 3.63E-04 4.31E-06 NO DATA 2.22E-06 I 134 1.06E-07 2.00E-07 1.03E-07 4.99E-04 4.58E-07 NO DATA 2.51E-10 1 135 4.43E-07 1.16E-04 4.2 BE-0 7 7.65E-05 1.06E-06 NO DATA 1.31E-06 C5134 6.22E'05 1.40E-04 1.21 E -0 4 NO DATA 4.79E-05 1.59E-05 2.59E-06 C5134 6.51E-06 2.57E-05
- 1. 05E-0 5 40 DATA 1 43E-05 8.96E-06 2.92E-06 C5137 7.97E-05 1.09E-04 7.14E-0 5 40 DATA 3.70E-05 1.23E-05 2.11E-06 C5138 5.52E-00 1.09E-07 5.40E-08 NO DATA 0.01E-08 7.91E-09 4.65E-13 84139 9.70E-00 6.91E-11
1.15-67
l I
f TABL8 E-11. CONT'O PA3 E 30F 3 INGESTION DOSE FACTOR $ FOR 40 ULT 5 184 TEM PER PCI INCESTEO S guCL it:E DONE LIWER T.000Y THVADID E104EY LUNC GI-LLI SA140 2.03C-05 2.55E-08
- 1. 33E-0 6 40 DATA S.67t-09 1.46E-08 4.18E-05 RA141 4.FIE-08 1.56C-11 1 59E-09 40 DATA 3.31E-11 2.02E-11 2.22E-17 44142 2.13E-08 2.19E-11 1.34k-09 800 DATA 1.85E-11 1.24E-11 3.COE-26 LA140 2.bOE-09 1.262-09 A.33C-10 40 DATA NO DATA NO DATA 9.25E-05 LA142 1.28E-10 5.82E-11 1.45E-11 NO DATA NC OATA a00 DATA 4.25E-07 CE141 9.36E-09 6.35E-09 F.18E-10 NO DATA 2.94E-09 NO DATA 2.42E-05 CE143 1.65E-09 1.22F-06 1.35E-10 NO DATA 5.37E-10 NO DATA 4.56E-05 CE144 4.ASE-07 2.04E-07
- 2. 62E-0 8 NO DATA 1.21E-07 NO DATA 1.65E-04 PR143 9.20E-09 3.692-09 4.56E-10 NO DATA 2.15E-09 N0 DATA 4.03E-05 PRt44 3.01E-11 1.2SE-11 1.5SE-12 40 DATA 7.05E-12 ND DATA 4.33E-18 N0147 6.29E-09 7.27E-09 4.15E-10 NO DATA 4 25E-09 40 DATA 3.49E-05 h 197-1.03E-07 8.61E-04 3.01E-Oh NO DATA NO DATA Nn DATA 2.82E-05 NP239 1.19E-09 1.17C-10 6.45E-11 seo DATA 3.65E-10 NO DATA 2.40E-05 e
5 e
1.109 58
l TABLE E-12 P AGE 1 OF 3 INGESTION DD5E F ACTORS FDa TEENAGEa (MAEM PER PCI 14CESTEDI NUCLICE L IVE 4 T.80cY THYROID KIDhEY LUNG GI-LLI
._....... 00NE H
3 ho DATA 1.06E-07 1.0eE-0 7 1.06E-07 1.06E-07 1.06E-07 1.06E-07 C to 4.06E-06 8.12F-07 8 12 E-0 7 8.12F-07 8.12E-07 S.12E-07 0.12F-07 94 24 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30k-06 2.30E-06 2.30E-06 P 32 2.76E-04 1.71E-05 1.07E-0 5 40 DATA NO DATA NO DATA 2.32E-05 CR 51 40 DATA 40 DATA 3.60E-09 2.00E-09 7.89E-10 5.14E-09 6.05E-07 PN S4 NO DATA 5.90E-Os 1.17E-0 6 NO DATA 1.76E-06 NO DATA 1.21E-05 NN 56 NO DATA 1.58[-07
- 2. 6 8 F'-06
- 6. 2 5E-0 7 N0 DATA 40 DATA 1.70E-06 1.16E-06 FE 59 5.87E-06 1.stE-05 5.29E-06 NO DATA NO DATA 4.32E-06 3.24E-05 CD 58 NO DATA 9.72E-07 2.24 E-0 6 NU DATA 40 UATA NO DATA 1.34E-05 CU 60 NO DATA 2.61E-06 6.33E-06 NO DATA
-12 DATA NO DATA 3.66E-05 MI es 1 77E-04 1.25[-05 e.00E-06 h0 DATA NO DATA NO DATA 1.99E-06 o.
41 65 7.49E-07 9.57E-08 4.36E-08 40 DATA NO DATA MO DATA 5.19E-06 CU 64 NO DATA 1.15E-07 5.41E-08 NO DATA 2.91E-07 NO DATA S.92E-06 FN eb 5.76E-06 2.COE-E5
- 9. 3 3E-0 6 MO 04T4 1.28E-05 NO DATA 8.47E-06 f
\\
IN 69 1 47E-08 2.60E-08 1.96E-0 9 NO DATA 1.83E-08 NO DATA 5.16E-08 Rt 8 5 40 DATA NO D4TA 5.74E-08 NO DATA h0 DATA NO DATA LT E-24 BR 84 20 DATA NO CATA
- 7. 22 E-0 8 NO DATA NO DATA WO DATA LT E-24 mA 8%
NO DATA NO DATA 3.0 $ E -0 9 NO DATA NO CA14 NO DATA LT E-24 a8 86 NO DATA.
2.98E-05 1.40E-05 NO DATA NO DATA NO CATA 4.41E-06 48 88 40 DATA 8.52E-08 4.54E-08 h0 DATA h0 DATA NO DATA 7.30E-15 MS 09 NO DATA 5.50E-08
- 3. 89 E-0 8 NO DATA NO DATA NO DATA 8.43F-17 ER 89 4.40E-04 NO DATA 1.26 E-0 5 NO DATA NO DATA ha DATA 5.24E-05 54 90 9 30E-03 NO D&TA
- 2. 0$ E-0 3 NO DATA NO DATA NO DATA 2 35E-04 SR 91 8.07E-06 NO DATA 3.21 E-0 7 40 DATA NO DATA NO DATA 3.66E-05 SR 92 3.05E-06 NO DATA
- 1. 30E-0 7 NO DATA NO DATA NO DATA 7.77E-05 Y 90 1.37E-08 NO DATA 3.61E-10 NO DATA NO DATA NO DATA 1.13E-04 Y 91p 1 29E-10 NO DATA
- 5. 39E -0 9 WO DATA NO DATA MO DATA 8.24E-05 Y 92 1.21E-09 NO DATA
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thele E-12 CONT'O PAGE 2 0F 3 INGESTION 005E FACTOR 5 FOR TEENAGER tesAEse PFR PCI INGE%TEDI NUCLIDE SONE LIVER T.800Y TNYROIO RIDeeEY LUNG GI-LLI Y 93 3.83E-09 800 DAT A 1.05E-10 NO DATA 800 DA T A NO DATA 1.17E-04 24 95 4.12E-08 1.30C-08 S. 9*E-0 9 NO DATA 1.91E-08 NO DATA 3.00E-05 ta 97 2.37E-09 4.69E-10 2.16E-10 NO DATA 7.18E-10 NO DATA 1.27E-04
.......... _. _.... ~... _........ _... _..
Ne 95 0.22E-09 4.5t!-09 2.51E-09 NO DATA 4.42E-09 8e0 DATA 1.95E-05 080 19 000 DATA 6.03E-06 1.15E-06 000 DATA 1.38E-05 800 DAT A 1.08E-05 j
TC 99M 3.32E-10 9.26E-10 1.20E-00 000 OATA 1.38E-08 S.14E-10 6.08E-07 TC101 3.60E-10 5.12E-10 5.03E-09 esO DATA 9.26E-09 3.12E-10 e.75E-17 RU103 2.55E-07 eso DATA
- 1. 09E-0 7 seo 04TA S.99E-07 NO DATA 2.13E-05 AU105 2.18E-08 NO DATA S.46E-09 800 OATA 2.75E-07 000 DATA 1.765-05 RU106 3.92E-06 800 O AT A 4.94E-07 000 DATA 7.56E-06 NO DATA 1.88E-04 AG110*e 2.05E-07 1.94E-07 1.18E-07 NO DATA 3.70E-07 900 DATA 5.45E-05 TE1254 3.83E-06 1.386-06 5.12E-07 1.07E-06 NO DATA NO DATA 1.13E-05 7E127eq 9.67E-06 3.4AE-06 1.15 E-06 2.30E-06 3.92k-05 800 DATA 2.41E-05 TE127 1 58E-07 5.60E-08 3.40E-0 8 1.09E-07 6.40E-07 NO DATA 1.22E-05 TE129M 1.63E-05 6.05E-06
- 2. 5 tE-06 S.26E-06 6.R2E-05 NO DATA 6.12E-05 TE129 4.45E-05 1.67E-00
- 1. 0?E-0 8 3.20E-08 1.SSE-07 NO OATA 2.45F-07 TE131m 2.44E-06 1.17E-06 9.76E-07 1.76E-06 1.22E-05 NO DATA 9.39E-05 TE131 2.79E-Os 1.15E-r' S.72 E-0 9 2.15E-08 1.22E-07 NO DATA 2.29E-09 TE132 3.49E-06 2.21E-06 2.04E-06 2.33E-06 2.12E-05 NO DATA 7.00E-05 1 130 1.03E-06 2.90E-06 1.19E-06 2.4 3E-04 4.59E-06 NO DATA 2.29E-06 I 131 5.85E-06 8.11C-06 4.40E-06 2.39E-03 1.41E-05 000 DAT A 1.62E-06 I 132 2.79E-07 7.30E-07 2.62 E-0 7 2.46E-05 1.15E-06 900 OATA 3.18E-07 1 133 2.01E-06 3.41k-06 1.04 E-0 6 4.76E-04 5.98E-06 000 DATA 2.50E-06 1 134 1.46E-07 1.07E-07 1.39E-0 7 6.45E-04 6.10E-07 800 DATA 5.10E-09 1 135 6.10E-07 1.57E-04 5.82E-07 1.01E-04 2.40E-06 NO DATA 1.74E-06 C5134 S.37E-05 1 97E-04 9.14 E-0 5 000 DATA 6.26E-05 2.39E-05 2.45E-06 C5136 S.59E-06 3.38E-06 2.27E-05 NO DATA 1.04E-05 2.90E-06 2.72E-06 C5137 1.12E-04 1 49E-04 5.19E-05 000 DATA 5.07E-05 1 97E-05 2.12E-06 C513e 7.76E-08 1.49E-07 7.45E-08 000 DATA 1.10E-07 1 2SE-08 6.76E-11 84139
~1.39E-07 9.78E-11 4.0$k-0 9 100 DATA 9.22E-11 6.74E-11 1.24E-06 3
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TA8LE E-12 CONT 8D PAGE 3 0F 3 INCEST 10N DOSE FACTORS F0a 7EFNAGER 1mREN PER PCI INGESTEDI 40CL1L'E DONE LIVER 7.00DY THYROID KID 4tY LUNC GI-LLI i
84140 2.84E-05 3.4RE-08 I. 83E-0 6 40 DATA 1.186-08 2.14E-08 4.38E-05 54141 6.71E-08 5.01E-11 2.2 4 E-0 9 40 DATA 4.65E-11 3.43E-11 1.43E-13 84142 2.99E-08 2.99E-11
- 40. DATA NO DATA NO DATA 9.82E'-65 LA142 1.79E-10 7.95E-11 1.98E -11 NO DATA NO DATA NO DATA 2.42E-fS CE141 1.33E-08 8.OSE-09 1.02 E-0 9 NO DATA 4.18E-09 NO DATA 2.54E-C.i CE143 2.35E-09 1.71E-06 1.91 E-10 NO DATA 7.67E-10 NO DATA 5.14E-05 CE144 6.96E-07 2.88E-07 3.74E-08 NO DATA 1.72E-07 40 DATA 1.75F-06 PR143 L.31E-04 5.23C-09
- 6. 52 E-10 40 DATA 3.n4E-09 N3 CATA 4.31E-0.
PR144 4.30E-11 1.76E-11 2.18E-12 NO DATA 1.01E-11 NO DATA 4.T4E-14 ND14T 9.18E-09 1.02E-08 6.11E-10 NO DATA 5.99E-09 NO DATA 3.68E-05
- - - + ~ - -
h 187 1.46E-07 1.19E-07 4.1FE-08 NO DATA 40 DATA naj...r,u p ----........,.,............. ~
NO DATA 3.22E-05 eoe r-NP239 1.76E-09 1.64E-10
- 9. 22 E-11 NO DATA 5.21E-10 NO DATA 2.67E-05
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PAGE 1 OF 3 INGESTION DOSE FACTORS FDR CHILD LNREM PER *CI INGESTEDI NuCL1DE DONE
,L 1 WE R T.nouV TMVROID RIDNEY LUNG GI-LLI H
3 40 DATA 2.03E-07
- 2. 01E-0 7 2.03E-07 2.03E-07 2.03E-07 2.03E-07 C 14 1.21E-05 2.*2E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 NA 24 b.00E-06 5.00E-06 5.00E-06 5.00E-06 5.90E-06 5.00E-06 5.80E-06 P 32 8.25E-04 3.86E-05 3.18E-Ob 40. DATA NO DATA NO DATA 2.2SE-05 CR 51 NO D A T A NO CATA S. 90E -0 9 4.94E-09 1.35E-09 9.02E-09 4.72E-07 MN 54 NO DATA 1.07k-05
- 2. 85E-0 6 NO DATA 3.00E-06 NO DATA 8.98E-06 NN 56 NO DATA 3.34E-0T 7.540-08 NO DATA 4.C4E-07 NO DATA 4.84E-05 FE Sb 1.15E-05 6.10E-06 1.89E-06 NO DATA NO DATA 3.45E-06 1.13E-06 FE 59 1.6SE-05 2.67E-05 1.3 AE-0 5 NO DATA NO DATA 7.74E-06 2.78E-05 CD Se NO DATA 1.80E-06
- 5. 51 E-0 6 NO DATA NC DATA NO DATA 1.05E-OS CO 60 NO DATA 5.29F-06 1.56 E-0 5 NO DATA NO DATA NO DATA 2.93E-05 41 63 5.30E-C4 2.88F-05
- 1. 8 3E-0 5 NO DATA NO DATA NO DATA 1.94E-06 NI 65 2.22E-06 2.09F-07 1.22E-07 NO DATA NO DATA NO DATA 2.56E-05 CU 64 NO DATA 2.45E-07 1.4tE-0T NO DATA 5.92E-07 NO DATA 1.15E-05 2N 65 1.37E-05 3.e5E-05 2.270-05 NO DATA 2.30E-05 NO DATA 6.41E-06 2N 69 4.38E-OS 6.s3E-08 5.tSE-09 NO DATA 3.94E-08 NO DATA 3.99E-06 et G A NO DATA NO DATA 1.71E-07 NO DATA NO DATA NO DATA LT E-24 BR 84 NO DATA NO DATA 1.986-07 NO DATA NO DATA NO DATA LT E-24 RR 85 NO DATA NO DATA 9.12E-09 NO DATA MO DATA NO DATA LT E-24 Mb 06 NO DATA 6.70E-05 4.12E-05 NO DATA NO DATA NO DATA 4.31F-06 Rt St NO DATA 1.90E-07 1.12 E-0 7 NO DATA NO DATA NO DATA 9.32C-09 RB 09 NO DATA 1.17E-07
- 1. D4 E-0 7 NO DATA NO DATA NO DATA 1.02E-09 SR 89 1.32E-03 NU CATA 3.7 7 E-0 5 NO DATA NO DATA NO DATA 5.11E-05 SR 90 1.70E-02 ND UATA 4.31 E-0 3 NO DATA NO DATA NO DATA 2.29E-04 SR 91 2.40E-05 NO DATA
- 9. 06E-0 7 NO DATA NO DATA NO DATA 5.30E-05 SR 92 9.03E-06 NO DATA 3.62E-07 40 DATA NO DATA NO DATA 1.71E-04 Y 90 4 11E-08 40 DATA 1.10E-0 9 NO DATA NO DATA NO DATA 1.17E-04 Y 91M 3.82E-10 40 DATA 1.31E-11 NO DATA NO DATA NO DATA 7.48E-07 Y 91 6.02E-07 NO DATA 1 61F-08 NO DATA NO DATA 40 DATA 9.02E-05 Y 92 3.60E-09 NO DATA 1.0AE-10 NO DATA NO DATA NO DATA 1.04E-04 J.109-42
i 4(
s 7ABLE E-13, CONT'D PAGE 2 OF 3 INCESTION DOSE FACTORS FOR CHILO IMREM PER PCI INCESTEO)
NUCLIOE
- SONE, LIVER 7.80pf TMVROIO RIOhEV LUNG GI-LLI V 93 1.14E-05 40 OATA 3.13E-10 NO DATA NO DATA NO DATA 1.70E-04 2R 95 1.16E-07 2.95E-OS 2.27E-04 NO DATA 3.65E-08 NO DATA 2.66E-05 2R 97 6.99E-09 1.01E-09 5.96E-10 NO DATA 1.45E-09 NO DATA 1.53E-04 48 95 2.2SE-08 8.76E-09 4.26E-0 9 40 DATA 8.23E-09 NO DATA 1 62E-05 MO 99 NO DATA 3.33E-05 3.29E-06 NO DATA 2.84E-05 NO DATA 1.10E-05 TC 99u 9.23E-10 1.81E-09 3.00E-06 NO DATA 2.63E-04 9.19E-10 1.03E-06 FC101 1.07E-09 1.12E-09 1.42E-08 NO DATA 1.91E-00 5.92E-10 3.56E-09 RU103 7.31E-07 NO DATA
- 2. 81 E-0 7 NO DATA t.04E-06 NO DATA 1.09E-05 RU105 6.45E-00 NO DATA 2.34E-08 40 DATA 5.67E-07 NO DATA 6.21E-05 20106 1.17E-05 NO DATA 1.46 E-0 6 NO DATA 8.5SE-05 NO DATA 1.52E-04 AC110M 5.39E-07 3.64E-07 2.91 E-0 7 NO DATA 6.78E-07 NO DATA 4.33E-05 TE125M 1.14E-05 3.09E-06
- 1. 52 E-0 6 1.20E-06 NO DATA NO DATA 3.10E-05 TE12TM 2.89E-05 7.78E-06 3.4 A E-06 6.91E-06 f.24E-05 NO CATA 2.34E-05 l
TE127 4.71E-07 1.27F-07 1.01 E-0 7 3.26E-07 1.34E-06 40 DATA 1.84E-05 I
TE129" 4.87E-05 1.36E-05
- 7. So E-06 1.57E-05 1.43E-04 NO DATA 5.94E-05
\\
TE129 1.34E-07 3.74E-08 3.18E-OS 9.56E-38 3.92E-07 NO DATA 8.34E-06 TE131M 7.20E-06 2.49E-06 2.65E-06 5.12E-04 2.41E-05 NO DATA 1.01E-04 TE131 0.30E-08 2.53E-00 2.47E-08 6.35E-00 2.51E-07 NO DATA 4.36E-07 TE132 1.01E-05 4.47E-06 5.40E-06 6.51E-04 4.15E-05 NO DATA 4.50E-05 I 130 2.92E-06 5.90E-06
- 3. 04 E-0 6 6.50E-04 8.02i-06 40 OATA 2.76E-06 I 131 1.72E-05 1 73E-05
- 9. 8 AE-0 6 5.72E-03 2.84E-05 40 DATA 1.54E-06 1 132 8.00E-07 1.47E-06 6.76E-07 6.82E-05 2.25E-06 NO DATA 1.73E-06 I 133 5.92E-06 7.32E-06 2.77E-06 1.36E-03 1.22E-05 NO DATA 2.95E-06 I 134 4.19E-07 7.70E-07 3.S S E-0 7 1.79E-05 1.19E-06 NO DATA 5.16E-07 I 135 1.75E-06 3.15E-06 1.49E-06 2 79E-04 4.83E-06 NO DATA 2.40E-06 C1134 2.34E-04
- 3. 84 E- 04 8.10E-0 5 NO DATA 1.19E-04 4.27E-05 2.07E-06 C1136 2.35E-05 4.46E-05 4.14E-0 5 NO DATA 3.44E-05 5.13E-06 2.27E-06 CS137 3.27E-04 3.13E-04
- 4. 62 E-0 5 NO DATA 1.02E-04 3.67E-05 1.96E-06 C5138 2.28E-07 3.17E-07 2.01E-07 NO DATA 2.23E-07 2.40E-05 1.46E-07 BA139 4.14E-07 2.21E-10 1.2 0E-0 8 40 DATA 1.93E-10 1.30E-10 2.39E-05
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i TAdLE E-13. CogT'D P AGE 3 OF 3 INGTSTION 005E FACTORS FOR CHILD (WAEP PER PCI INGESTEDI NUCLlut SONE LIVER
..T. 4 0 0T.......
.. LUNG GI-LLI TMYADID RIDNEY RA140 8.J1E-05 7.24E-08 4.85E-06 NO DATA
- 6. S I E-0 9 NO DATA 9.69E-11 6.58E-10 1.14E-07 54142 0.74E-08 6 29E-1 4.48 E-0 9 NO DATA 5.09E-
........... _1.....
...11 3.70E-11 1.14E-09 LA140 1.0!E-08 3.53E-09 1.19E-09 40 DATA NC DATA NO DATA 9.84E-05 Lal42 5.24E-10 1.67E-10 S.23E-11 NO DATA NO DATA NO DATA 3.31E-05 CE141 3.97E-08 1.98E-08 NO DATA 8.68E-D9 N
........................ 2. 9 4 E -0 9.........................O DATA 2.47E-05 l
CE14J 6 99E-09 3.79E-06 5.49E-10 NO DATA 1.59E-09 NO DATA S.55E-05 C E 144 2.08E-06 6.52E-07 1.11E-07 NO DATA 3.61t-07 NO DATA 1.70E-04 PR143 3 93E-08 1.18E-08 NO DATA 6 19E-09 NO
..........................1. 9 5 E -0 9............................. DATA 4.24E-05 PR144 1.29E-10 1.91E-11 6.49E-12 NO DATA 2.11E-11 NO DATA 8.59E-08 N0147 2.79E-0A 2.26E-08 1.75E-09 No DATA 1.24E-rL NO DATA 3.58E-05 W 187 4.29E-07 2.54T-07
......................._.1.14 E -0 7....
.O DATA 3.57E-05 Nu DATA NO DATA N
NP239 5.2SE-09
- 3. 7 7 E-10 2.6bE-10 NO DATA 1.09E-09 NO DATA 2.79E-05 l
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i TABLE E-14 P AG E 1 OF 3 INGESTION DO5E FNCTO45 FOR INFANT (MREM PEA PCI 84&ESTEDI NUCLICE SONE LIVER T.Sout THYtotD aIONEY LUNG
- I-LLI H
3 NO D A T A 3.00E-07 3.08E-0 7 3.08E-07 3.00E-07 3 00E-07 3.08E-07 0 14 2.37E-05 5.06E-06 5 06E-06 5.06E-06 5.06E-06 5.06F-06 5.06E-06 NA 24 1.01E-05 1.01E-05 1 01E-05 1.01E-05 1.01E-05 1 01E-Ob 1.,01E-05 P 32 1.70E-03 1 00E-04
- 6. 59E-0 5 NO DATA NO DATA NO DATA 2.10E-05 CR 51 NO DATA NO DATA 1.41E-08 9.20E-09 2.01E-09 1.79E-08 4.IIE-07 MN 54 NO DATA 1.99E-0$
- 4. 51 E-0 6 NO DATA 4.41E-06 MO DATA 7.31E-06 MN 56 NO DATA S.18E-07 1.41E-0 7 Nu DATA 7.03E-07 NO DATA 7.43E-05 FE 55 1.39E-05 8.90E-06 2.40E-06. 40 DAT A NO DATA 4.19E-06 1.14E-06 FE 59 - 3.08E-05 5.30E-05 2.12E-Ob NO CATA NO DATA 1.59E-05 2.57E-05 CD 58 NO DATA 3.60E-06 8.98E-06 NO DATA 40 DATA NO DATA S.97E-06 CD 60 NO DATA 1.08E-05
- 2. 55 E-0 5 40 DATA NO DATA No DATA 2.57E-05 41 63 6.34E-04 3.92E-05 2.20E-0 5 NO DATA 40 DATA NO DATA 1.95E-06 NI 65 4.70E-06 5 32E-07 2.42E-07 40 DATA NO DATA NO DATA 4.05E-05 CU 64 40 DATA 6.09E-07
- 2. 82 E-0 7 NO DATA 1.03E-06 NO DATA 1.25E-05 2N 65 1.54E-05 6.31E-05 2 91E-Ob NO DATA 3.06E-05 NO DATA 5.33E-05 C.
IN 69 9.33E-OS 1.68E-07 1.2 S E-0 8 40 DATA 6.90E-ce NO DATA 1.37F-05 MR 83 NO DATA NO DATA 3.63 E-0 7 NO DATA NO DATA NO DATA LT E-24 84 04 40 DATA NO DATA J. 82 E-0 7 NO DATA NO DATA NO DATA LT E-74 WR As NO DATA NO DATA 1.94E-Os NU DATA NO DATA NO DATA LT E-24 AR 86 NO DATA 1.70E-04 S.4 0E-0 5 NO DATA NO DATA NO DATA 4.35E-06 M8 88 NO DATA 4.98E-07
- 2. 73 E-0 7 No DATA NO DATA NO DATA 4.SSF-07 40 89 MO DATA 2.56E-07 1.97E-07 NO DATA NO DATA NO DATA 9.74E-08 l
1R 89 2.51E-03 40 DATA 7.20E-0 5 40 DATA NO DATA NO DATA 5.16E-05 SR 90 1.8SE-02 NO DATA 4.71E-0 3 40 DATA NO DATA NO DATA 2.3tE-04 1R 91 b.00E-05 NO DATA
- 1. 81 E-0 6 NO DATA NO DATA NO DATA 5.92E-05 SR 92 1.92E-05 40 DATA 7.13E-07 NO DATA NO DATA NO DATA 2.07E-04 Y 90 8.69E-08 40 DATA
- 2. 3 sE-09 40 DATA NO DATA NO DATA 1.20E-04 V 91p 8.10E-10 NO DATA 2.76E-11 NO DATA NO DATA NO DATA 2.70E-06 Y 91 1.13E-06 40 DATA 3.01E-08 NO DATA NO DATA NO DATA S.10E-05 Y 92 7.65E-09 NO DATA 2.15E-10 NO DATA NO DATA NO DATA 1.44E-04 h
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TABLE E-14. CONT'D P E E 2 0F 3 INGESTION UO5E F ACTORS FOR INSAhT INREM PER PCI INGESTE01 NUCL1CE BO9E liver 7.00DY TNYm0lO K10NEY LUNG GI-LLI Y 93 2.43E-03 NO DATA 6.62E-10 NO DATA NO DATA NO DAT A 1.92F-04 2R 95 2.06E-07 5.02E-08 3.56E-05 40 DATA 5.41E-os NO DATA 2.50F-05 2R 97 1.40E-08 2.54E-09 1 16E-09 40 DATA 2.56E-09 NO DATA 1.62E-04 95 95 4.20E-08 1.73E-08 1.03E-08 40 DATA 1.74k-OS NO DATA 1.46E-05 m0 91 NO DATA 3.4CE-05 6.63E-0 6 NO DATA 5.OBE-05 NO DATA 1 12E-05 TC 99P 1.92E-09 3.96E-09 5.10E-08 NO DATA
~4.26L-08 2.07E-09 1 15E-06 TC101 2.27E-09 2.06E-09' 2.8 3E-08 N0 DATA 3.40E-On 1 56E-09 4.06E-07 RU103 1.40E-06 NO DATA 4.95E-07 N0 DATA 3.08E-06 NO DATA 1.80E-05 RU105 1.36E-07 NO DATA 4.50E-08 800 DAT A 1.00E-06 NO DATA 5.41E-05 RU106 2.41E-05 NO DATA 3 015-06 40 DATA 2.05E-05 NO DATA 1.83F-04 4G110M 9*96E-07 7.27E-07 4 81E-07 NO DATA 1 04E-06 NO DATA 3.77E-05 TE12SM 2.35E-05 7.79E-06 3 15E-06 7.84E-06 NO DATA NO DATA 1.11E-05 TE127M 5.tSE-05 1.94E-05 7.00E-06 1.69E-05 1.44E-04 NO DATA 2.36E-05 TE127 1.00E-06 3.35E-07 2.15E-07 0.14E-07 2.446-06 NO DATA 2 10E-05 TE129M 1.00E-04 3.43E-05 1 54E-05 3.84E-05 2.50E-04 NO DATA 5 97E-05 TE129 2.84E-07 9.79E-08 6.63E-08 2.3BE-07 7.07E-07 NO DATA 2 27E-C5 TE131P 1.b2E-05 6.12E-06 5.05E-06 1.24E-05 4.21E-05 40 DATA 1.03E-04 TE131 1.76E-07 6.5CC-08 4.94E-08 1.57E-07 4 50E-07 NO DATA 7.11E-06 TE132 2.0SE-05 1.03E-Oh 9.61E-06 1.52E-05 6.44E-05 NO DATA 3.81E-05 1 130 6.00E-06
- 1. 32 E-15
- 1. 46E-0 5 1.39E-02 4.94E-05 40 DATA 1.51E-06 I 132 1 66E-06 3.37E-06 1.2 0E-0 6 1.SSE-04 3.76E-06 NO DATA 2.73E-06 I 133 1.2bE-05 1.02E-05 5.33E-06 3.31E-03 2.14E-35 NO DATA 3.08E-06 I 134 0.69E-07 1.78E-06
- 6. 3 3 E-0 7 4.15E-05 1.99E-06 NO DATA 1.04E-06 1 135 3.64E-06 7.24E-06 2.64E-06 6.49E-04 4.07E-06 NO DATA 2.62E-06 C5134 3 77E-04 7.03E-04 7.10E-0 5 NO DATA 1.01E-04 T.42E-05 1.91E-06 C5136 6.59E-05 1.35E-04 5.04 E-0 5 40 UATA 5.3BE-05 1 10E-05 2.05E-06 C5137 5.22E-04 6.11E-04
- 4. 33E-0 5 NO DATA 1.64E-04 6 64E-05 1.91E-06 C5138 4.81E-07 7.82E-07 3.79E-0 7 NO DATA 3.90E-07 6 09E-08 1.25E-06 84139 0.81E-07 5.e4E-10 2.55E-00 40 DATA 3.51E-10 3.54E-10 5.50E-05 I
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fasLE E-tee CDNT'D P43E 3 DF 3 INGEST 109 DOSE FACTORS FOR INFANT 1* REP PER PCI INCESTEDI NUCL IDE DONE LIVER T.40DY THYROID RIONEY LUNC Cl
................-LLI 84140 1.71E-04 1.71E-07 8.81E-06 NO DATA 4.06E-08 1.05E-07 4 20E-05 SA141 4.25E-07 2.91c-10
- 9. 06E-0 9 NO DATA S.01E-11 9.26E-11 7.59E-07 LA440 2.11E-08 8.32E-09 2.14E-09 MQ DATA NO DATA NO DATA 9.77E-*5 LA142 1.10E-09 4.04E-10 9.6 FF-11 NO DATA NO DATA NO DATA 4.06F-'5 CE141 7.87E-08 4.00E-08 5.65E -0 9 NO DATA 1.4SE-06 NO DATA 2.48E-*5 CE143 1.40E-08 9.52E-06 1.17E-0 9 NO DATA 2.96E-09 NO DATA 5.73E-05 CE144 2.90E-06 1.22E-06' 1.67E-07 N0 DATA 4.93E-07 NO DATA
- 1. 71 E-O S PR143 S.13E-08 3.04E-08
- 4. 03 E-0 9 NO DATA 1.13E-08 NO DATA 4.29E
',5 PR144 2.74C-10 1.06E-10 1.30E-11 NO DATA 3.44L-11 NO DATA 4.93E-06 N0147 5.53E-08 5.68E-04 S. 4 0 E-0 9 NO DATA 2.19E-OR NO DAfa 3.60E-05 N 107 9.03C-07 6.28t-07 2.17E-0 7 NO DATA NO DATA NO DATA 3.69E-05 NP231 1.11E-00 9.93E-10 5.61E-10 40 DATA 1.98E-09 NO DATA 2.87E-05 1
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,._,,y-_.,.____-m,,,--,..-.___,y
y I
I i
TABLE E-15 ret 01stnDED VAltES FOR OTHER PARAfETER$
2 parameter Equation (s) l Syuhol Definition Where Used_
Values Reference (s)*
f, Frection of produce ingested grown in garden of interest 14 & C-13 0.76 f
Frection of leefy vegetables grown in garden of interest 14 & C-13 1.0 g
2 i
p Effective surface density of soil (assumes a 15 cm plow
- 4. A-8. A-13. & C-5 240 kg/m 10 layer, empressed in dry weight)
~
r Frect4en of doyesited activity retained on crops leafy
- 4. A-8. & A-13 0.25 27
'. vegetables, or posture grass C-5 1.0(forto4tnes)
- 2. 4. 13 O.2 (for other 28-31 i
particulates)
S Atteneetten factor accounting for shielding provided by
- 8. 5. 10. 11. 12 0.7(formeatsum 26 p
residential structures 5-6. B-7. B-8. 8-g.
Individual)
"I
& C-2 0.5 (for general 26 k
population) 5 t
period of long-tern butidup for activity in sediment or
- 3. 4. A-4. A-5. A-6, 1.31 x 10 hr j
b I.
soil (nominally 15 yr)
A-7. A-8. A-13. & C-5
't t,
period of crop. leefy vegetable, or posture grass
- 4. A-8. A-13. & C-5 720 hrs (30ders.
10 & 32 exposure during growing season for grass-cow-eilk-men pathuey) 1440 hrs (60 days.
~
for crop /vegetatten.
men pathuey) l t
Trensport time from animal feed-milk-een C-10 2 days (formentouse g
individual) 4 days (for general j
population)
I parameter values given without references are based on staff judgments.
i
I i
\\
i y
a r>
j i
TA8 TEE-15(Continued) j Peremeter Symbol Equation (s)
Definttfon s
4 Where Used galses Reference (s)*
.l t
Tfee delay between hervest of vegetation or crops and h
ingest 1on 1
-3
- 1) For ingeatfon of forege by enfeels 1
- 4. A-8. A-13. & C-5 Zero(flerposture j
gross)
.i T160 hr (90 days for
'j
- 11) For ingestien of crops by men stored feed)
- 4. A-8. A-13. 8 C-5 24 he (1 day, for i
q A
leefy vegetables a maniumnindividual) d
/
1440 he (60 days, for I
produce a mentmum fndividual) d 335 hr (14 days, for generalpopulation) t, Envfrunnental transit time. release to receptor
's 1
(add time from release to exposure point to 1 S A-2 12hr(ftementmem s
minimens shown for distribution) indivfdual)
S 24 hr (for general i
populatten)
'g t
2 4 A-3 24 hr (for ematsum 3
indivfdwel)
{
1 108 hr (7 days fler h
i.
fishdoses) populatten spurt l
240 hr (10 days fler
- ieti-com-
- .)
mercial fish doses 3 & A-7 Fere I
-)
t, Average tier frec slaughtee of meet enteel to g
r.onseptfon C-12 20 days f,,'
Agriculturalproductivitybyunitares(meesured Inmetweight)
- 4. A-8. A-13. 8 C-5 0.7 kg/m2(9,,
{
2 cow-n11k-men,athemy) 33 p
( '4-2 r
+3 2.0 kg/m g,,,,,,g,,,
3g j
or leafy vegetables ingested by men) t
(
Rate constant for renoval of activity on plant or leaf surfaces by teethering (corresponds to a 14-day half-Ilfe) 0.0021 hr*I Parameter values given without references are based on staff judgments.
r
E.....o...-...,.-.-
.m y
1 4
J l
K FERENCES FOR APPENDIX E I
l 1.
Y. C. Ng et al.. " Prediction of the Mantana Dosa9e to Man from the Fallout of Ruclear Devices. Mandbook for Estimating the Maxians Internal Dese from Radionuclides Released to the Blosphere." USAEC Report UCAL-50163. Part IV.1968.
2.
B. H. Weiss et al.. " Detailed Measurement of I-131 in Afr. Vegetation and Milk around Three Operating Reactor Sites." Envirormental Surveillance Around Nuclear Installations. Inter-national Atomic Energy Agency. IAEA/5M-180/44. Vienna, Austria. Vol. I: pp. 169-190. 1974.
3.
F. O. Hoffman. " Environmental Variables Involved with the Estimation of the Jhnount of I-131 in Milk and the Subsequent Dose to the Thyrold." Institute fGr Reaktorsicherheit. Cologne.
West Germany. IR$-W-6. June 1973.
4.
F. O. Hoffman. " Parameters To Be Considered When Calculating the Age-Dependent I-131 Dose to the Thyroid." Institute fGr Reaktorsicherheit. Cologne. West Germany. IRS-W-5. April 1973.
5.
F. O. Hoffman. "A Reassessment of the Parameters Used To Predict the Environmental Transport of I-131 from Air to Milk." Institute fur Reaktorsicherheit. Cologne. West Germany. IRS-W-13 April 1975.
6.
F. W. Lengamann. "Radiofodine in the Milk of Cows and Goats After Oral Administration of Radfotodate and Radiotodide." Health Phys.. Vol.17. pp. 565-9,1969.
7.
R. J. Garner and R. 5. Russel Radioactivity and Human Diet. R. Scott Russel (ed.). Pergamon Press. Oxford. England.1966.
8.
P. M. Bryant. " Data for Assessments Concerning 'ontrolled and Accidental Releases of I-131 C
and Cs-137 to the Stratosphere.' Health Phys. Vol.17. p. 51.1969.
9.
J. D. Zimbrick and P. G. Vol11eque (eds.) "1967 CERT Progress Report." USAEC Report 100-12067, p. 36.1968.
i l
10.
J. F. Fletcher and W. L. Dotson (compilers). "HERES - A Digital Computer Code for Estimating l
Regional Radiological Effects from the Nuclear Power Industry." USAEC Report HEDL-TM-71-168 Hanford Engineering Development Laboratory.1971, l
11.
J. K. Soldat. " Conversion of Survey Meter Readings to Concentration (uC1/m ),. Item 04.3.4 2
in "Essergency Radiological Plans and Procedures." K. R. Heid (ed.). USAEC Report lei-70935 Hanford Laboratories.1962.
. 12.
" Permissible Dose from External Sources of Iontaing Radiation." Handbook 59. U.S. Dept. of Commerce. 1954.
13.
R. 5. Booth et al.. "A Systems Analysts Methodology for Predicting Dose to Man from a Radioactivity Centaminated Terrestrial Envirorment." Proceedings of the Third National Symposium on Radioecology, USAEC Report CONF-710501 Oak Ridge. Tenn.. pp. 877-893,1971.
14.
D. 5. Altman and P. L. Altman (eds.), " Metabolism." Federation of American Societies for i
Experimental Biology. Bethesda. Md.,1968,
- 15.
- R. J. Garner. " Transfer of Radioactive Materials from the Terrestrial Environment to Animals and Man " CRC Press. Cleveland. Ohio,1972.
16.
J. K. Soldat et al.. "Models and Computer Codes for Evaluating Radiation Doses." USAEC Report BMWL-1754. Pacific Northwest Laboratories. February 1974.
17.
A. L. Rogers. " Goat Keeping in the thited States." International Dairy Goat Conference.
London. July 1964.
18.
R. G. Sond and C. P. Straub (eds.). Handbook of Envirormental Control. Vol.111. " Water
~,
Supply ard Treatment." CRC Press. Cleveland. Ohio.1975.
1.10D-70 9
e!
y.
s
- 19. ' Food Consumption. Prices, and Empenditures." AER-138. U.S. Department cf Agriculture.
Washington. D.C.. Oncomber 1974.
- 20. *aeport of the Task Group en Reference Man." ICRP Publication 23. Pergamon Press Oxford.
England.1975.
l 21.
L. K. Busted and J. L. Terry. "Sasic Anatamical, Dietary and Pitysiological Data for j
Radiological Calculations." le64163C. General Electric Co.. Richland, Nash., February 1956.
22.
M. M. Miller and D. A. Nash. " Regional and Other Related Aspects of Shellfish Consumption -
Sose Preliminary Findings of the 1969 Consumer Panel Survey," IDEr5 Circular 361. USDC/NOAA.
Seattle, Wash.. June 1971.
- 23. "The Potential Radiological lapitcations of Nuclear Facilities in the Upper Mississippi River Basin in the Year 2000." USAEC Report WASH-1209, Washington. D.C.. January 1973.
24
- 0raf t Environmental Statement - Maste Management Operations. Manford Reservation. Richland.
Washington." USAEC Report NASH-1528. Washington, D.C.. September 1974.
25.
G. R. Noenes and J. K. Soldat. " Age-5pecific Radiation Dose Cammitment Factors for a One Year Chronic Intake." USNRC Report IRlREG-0172, to be issued in 1977. A draft is available in the Public Document Room.
26.
Z. G. Burson and A. E. Proflo. " Structural Shielding from Cloud and Fallout Genna Ray Sources for Assessing the Consequences of Reactor Accidents." EG4G-1183-1670 Las Vegas, Nev., 1975.
27.
D. A. Saker et al. "F000 - An Interactive Code to Calculate Internal Radiation Doses from Contaminated Food Products," SledL-5A.5523. February 1976.
28.
D. F. Bunch (ed.), " Controlled Environmental Radiolodine Test. Progress Report thmber Two."
USAEC Report 100-12063. January 1968.
29.
J. D. Zimbrick and P. G. Vo111eque. " Controlled Environmental Radioiodine Tests at the National Reactor Testing Station Progress Report Number Four," USAEC Report IDO-12065 December 1968.
30.
C. A. Pelletier and P. G. Vo111eque. "The Behavior of Cs-137 and Other Fallout Radionuclides on a Michigan Dairy Fam." Mealth Phys.. Vol. 21, p. 777.1971.
31.
P. G. Voilleque and C. A. Pe11etter. "Camparison of External Irradiation and Conseption of Cow's Milk as Critical Pathways for Cs-137, h-54 and Pr-144 Released to the Atmosphere."
Health Phys.. Vol. 27, p.189.1974.
32.
J. J. Koranda " Agricultural Factors Affecting the Daily Intake of Fresh Fallout by Dairy Cows." USAEC Report UCRL-12479.1965.
33.
M. E. Heath et al.. Fggg.s the Iowa State University Press. Ames. Iowa,1973.
34 " Statistical Abstract of the United States." U.S. Sureau of the Census, 93rd Edition,1972.
b 1.109-71 i'
t t
APPD e!I F
.i IETM005 FOR EVALUATING THE I FUNCTION r
I l
The NRC staff calculates ground-level gaans radiation doses from elevated noble gas releases wsf Equation (6) in Regulato Position C.2.a of this guide. Equation (6) is based on the mode presented in Slade (Ref.
). which can be characterfaed as a vertically finite sector-
~I averaged Gaussian plume model. Use of the model involves volume integration over a distributed source, resulting in certain integrals that define the I function, denoted by I I" "'I'""C' I*
T 1.
Derivation of the I Function The derivation of the I function presented below is taken directly from Reference 1, which should be consulted for further details.
The sector-average airborne radionuclide concentration resulting from a coettnuous release is given by the Gaussian plume model as (see Equation 1.60 of Ref.1):
l a
<> - h >2 -
<>. h>2
~
D 1(R.).
. e.,
Z
(,.i) 6 o uRe 2c,2 t
2og where h
is the effective release height, in meters;
[
is the effective release rate, considering decay in transit. in Ci/sec; R
is the downwind distance. In meters; is the average wind speed. in m/sec; u
I(R.2) is the sector-average concentration at location (R.z). in C1/m ;
3 is the vertical distance above the ground plane, in meters; a
a is the sector width, in radians; and is the vertical plume spread in meters.
og Equation (F-1) may be restated, for simplicity, as:
t I(R.r)
OII
=
1 6 o u.Re (F-2) g I
where 1
(r - h>2 I3
- hI G(z)=
esp
+ esp g
(F-3)
Io to*
z where the terms are as defined above.
1.109-72 l
...,m, 1
The gamme dose rate to air at a distance of r meters from a point source of q curies is expressed by (see Equation 7.33 of Ref.1):
p,q(3.7x1010)E(1.6x10-6)B(u.9,.r)exp(-pr)
D'
=
Asr (1293)(100)
II-4) 2 where B(u.9,.r) is the buildup factor, dimensionless; D'
is the dose rate to air. in rad /sec; E
is the gasuna rey energy per disintegration. in MeV; q
is the point source strength, in curies; r
is the distance, in meters; is the attenuation coefficient for air. in m'1; 9
u, is the energy absorption coefficient for air in m'I; 100 is the nunber of ergs per gram-rad; 1293 is the density of air at standard temperature and pressure. In g/m i 1.6 x 10-6 is the nwnber of ergs per MeV; and 10 3.7 x 10 is the number of disintegrations, per Ci-sec.
Equation (F-4) may be simplified as follows:
Ku,qEB(9.9,.r)exp(-pr)
O'
=
2 (F-5) der l
where l
(3.7 x 1010)(1.6 x 10-6) g 0.46 t
(1293)(100)
(F-6) l The next step is to incorporate Equation (F-2) into Equation (F-5) to arrive at an expression for the differential dose rate dD' from the differential volume dV containing the radionuclideconcentrationi(R.r). Consider a volume element of the plume located z seters above the ground and at a horizontal distance L meters from receptor location (R. 0) (see Figure 7.20 of Ref.1).
All such volume elements located at the horizontal distance L are included in the ring-shaped dif ferential volume 2,LdLdr. If R is sufficiently large that the concentration averaged over all such volume elements can be approximated by i(R.2). the contribution of the ring-shaped differential volume dV to the air dose rate at location (R.0) is given as Ku,EB(u.9,.r)exp(-pr)
- IR'*)##
(p,y) dO'
=
2 3
4sr l
8 l
l l'
t l
1.109-73 1
w~,..--....-~~-
' ' ' * * ~ ~
}
^ ^ ^ ^ ^ ^ ~ ^ - ^^
" ~ " " " " ~ " ~ ~
---~-~~-*--;-~==-*-'--
~
Substituting (LI + z )1/2 for r and teldLdz for dV in I
where q has been replaced by x(R.z)dV.
Equation (F-7). and integrating, the following empression is obtained:
Eng [
'v.u,. (L2,,2)1/2' g(,),,,
LdLdz
,,(g2,,2)
E t
D' Lh+23
=
2 /li Glo,e l
(F-8)
IE The I function, denoted by T in Reference 1. is defined as T
2,,2 1/2'
~
' 5.v.y.(L,,2)1/2' g(,),,, ",,(t 2
3 L
(
'}
a j
I=
(Z + z3 z
1,1, which, when substituted into Equation (F-8) yields (F-10)
I D'
=
rs Gle The constant K equal to 0.46, when divided by C yields the factor 0.260, which is the same as the factor of 260 la Equation (6) of Regulatory Position C.2.a. after multiplying by the nund>er of cred per rad.
The butidup factor given in Reference 1 is of the form (F-11)
B(u.u,r)=1+kur where (F-12)
W~Wa-
- a substituting the above expression for the buildup factor into Equati,on (F-9), the I function is then given as (F-13)
I=Iy + k!2 integrals can be written for this fom of the buildup factor as where the I; and 12
=>,
I (F-14)
II*
G(z)E(wz)dz g
- 1, (F-15)
G(z)exp(-wz)dz 4
and 12" j
z y where E (vz) is the exponential integral defined by F
y
'"8 *'"I (F-16)
E (vz) =
d(pr)
~;
j
,z 1.109-74
__^n n-- d
.....A 2.
Evaluation of the ! Function In Reference 1 the Ig and 12 integrals have been evaluated and the results presented graphically. Extraction of the data from these sf a-cycle leg-log multicurve plots is a formidable task. A more satisfactory approach is to prepare a tabulation of the integrals as evaluated using numerical methods. These data can snan he interpolated in implementing Equation (6) of Regulatory position C.2.a.
The NRC staff has developed a computer routine that evaluates the I function as formulated inEquation(F-9). The I function as expressed in Equation (F-9) is independent of the buildup factor form. A listing of this routine is provided in Figure F-1.
Communication with the routine is through the COPMON statement, which also communicates with the function subprogram BULDUP, which defines the dose buildup facter S(p,u er) desired by the user.
g 1
l Also. Yankee Atomic Electric Campany has supplied a routine written by Dr. John N. Hamawi ef that company (Ref. 2). This routine evaluates the Ij and 12 integrals as formulated in Equations (F-14)and(F-15),respectively. A listing of the routine is provided in Figure F-2 (reproduced with the permission of Yankee Atomic Electric Company). With the exceptions of changes in the title, the addition of the COMON statement, the computing of I from Ij and 1 '
2 and connent cards as to its authorship, the routine is reproduced as written by Dr. Hamswi. The
(
staff has compared the two routines and found their results to be in excellent agreement. The routine supplied by the Yankee Atomic Electric Company was found to be considerably faster than the staff's routine.
I b
~
1.109-75 1
r --.-
m v-- r - r - e = - ww --- - - -
y...............-
1 SUSROUT!tt O! 7 CDN#0N/D A TA I T/S %U, 2Ke NS,8282, t B A R,0 !,0 Coe
'WDBE INTESRAL SUSROUTINE =M.F.ECKERMAN 1t=24=T4
~
'C C
SUSRDUTINE EVALUATES TME DOSE INTESR AL '!T' 48 DEFINED SY ESN 7.61 P
C IN MET 4 Ar=1968 TME TWO O!NENSIONAL INTEGRATION 28 EVALUATED C
USINS SAUSSIAN=LESENORE SUADRATURE OF 0#0ER 48 4
C C
CDnNON ENFO 8
C SMuamA88 ATTENUAT!DN C0tFFIC! TNT (1/ptTERS) 8 C
ZK=SUILOUP PACTOR (NU=MUA)/MUA IF USEO C
M8= RELEASE PUINT MEITH C
RELEASE POINT Nt!SMT (METERS)
C SIGNZ 8TANDARD DEVIATIDN OF PLUME (NETERS)
C ESAR=8AMMA RAY ENERGY (NEV)
C O!=008t INTEGRAL C
N= ENERGY SROUP !Notx IF NEEDEO C
h0TE=2R,ESAR,8 N ARE Ust0 SY SULDUP Coe DIMENSION X(24)eMC24)
OATA NN/48/,A/2.828427125/
DATA N/
10.0323801709, 0.0970046992, 0.1612223560, 0.2247637903, 20.2873624873 0.3437558462, 0.4086464819, 0.4669029047, 30.5231609747, 0.5772247260, 0.6288673467, 0.6774723796, 40.7240341309, 0.7671590325, 0.8070662040, 0.8435082616, 50.8765720202, 8.9058791367, 0.9313866907, 0.9529877031, 60.9705915925c 0.9841245837, 0.9935301722, 0.9987710072/
OATA N/
10.0647376968, 0.0644661644, 0.0639242345, 0.0631141922, 20.0620394231, 0.0607044391, 0.0591348394, 4.0572772921,
^~
30.0551995036, 0.0528901894, 0.0503590355, 0.0476166584,
- w-s 7y _sq.04 4766f 84: 0.1M5450829,
' b.'
0.0382413510, 0.0347772225, M.0% 1672274,' O.0274265097, 0.023570760s, 0.0196161604, 60.0155793157, 0.0114772345, 0.0073275539, 0.0031533460/
SUMS 0.
Os0.5/C8!GMZe81GMZ)
ZLusM8=4.*SIGMZ ZU8sMS*4.e8IGMZ IF(ZL8.LT.O.)ZL8s0 YU8s15./GMU Cs0.5e(ZUd=2L8)
Geo.5e(ZUS*2LS)
Es0.5eVU8 00 70 !!st,NN
!s!!=11/2 Fa1 Eas0 IF(M00(!!,2).EG.9)Pa=1.
IZsFeX(IleC+G ARGUS 8e(ZZ=HS)e(ZZ-MS)
IF(ARGU.GT.20.)GO 70 55 i
ExetxP(=ARGU) 55 argus 8e(ZZ*M8le(ZZ+HS)
L IF(ARGU.GT.20.)GO TD 58 gastx*gxP(=ARGU) 58 IF(Ex.E0.0.)GO TO 70 00 60 KKa!,NN KsRK=KK/2 Fs1 IF(N00(KKe2).10.9)Pa=1.
[
Pfgure F-1. Stlff-Wrftten Computer Ltstfng 1.109-76 L
I
?
I I
... ~.
~
Aa%.
YYeFeI(KleE+E DieYYeVY+IIeII ARSUeBNueSGRT(D1)
IF(ARGU.sf.tp.)SO 70 60 1
tutagzegxPt.AmsulesULouP(ARGU)eYY/01 l
Sumssum+W(IleN(KleExt l
40 CONTINUE l
79 CONTINUE Dre8UmeceE/(AaBISMZ)
RETURN END f
Figure F-1 (continued) 1.109-77
- .w==,----.,
y, s
m....._
. w e.
.- u w..am - -
=-'
^- "'"*
-2
~
SUSROUTINE DINT REAL MU COMMON / DATA!T/ft.E,N,SISZ,0!el Ces C
DOSE INTEGRAL ROUTINE JRITTEN SY C
DR. J0MN N. MANAWI C
YANKEE 87Cw!C ELECTRIC COMPANY C
NUrttao.ERWICES DIVISION l
C 2D TbRNP!KE ROAD C
NESTROROUGN, NASSACMUSETTS 81581 C
YAEC REPORT No. 1105 C
C COMMON INFO C
NU-MASS ATTENUATION C0 EFFICIENT (1/ METERS)
C IK-SUILDUP FACTOR (MU.MUA)/MUA C
SIGZ 8TANDARD DEY!ATION OF PLUME (METERS)
C DI= DOSE INTEGRAL =! TOTAL C
L= DETERMINES NUMBER OF INTERVALB USED IN INTESRAT!DN Cee DIMENSION CDATA(5),E(49),8(49),P(49)
DATA N/9/(CDATA/5.0D*3el.0D*a,2.0D*a,5.00*a,1.8D*5/
DATA A0,A1,A2,A3eAseA5/ =0.57721566, 0.99999193, = 8.2a991055, C
0.05319968,=0.00976004, 0.00107457/
DATA 50,81,82,83/ 0.26777373a3e C 4.5733287a01/
4.63a7608925, 18.g590169730, DATA CO.CleC2,C3/ 3.9584969228e C 9.5733223a5a/
21.0994530827, 25.6329561486, DATA D,01,D2,03,Da,05,D6,07,04,D9/
C 35a 3.7 5,9st.,58 8 8..-928.,10 a 96.,-4 5a 0.,10 s96.,-92 8.,5 8 8 8.,9 8 9. /
Casse COMPUTE LIMITS OF INTEGRATION ZMIN AND ZMAX, AND INTERVAL N!DTM IF(L.LT.2.0R.L.GT.6) L e 4 C e CDATA(L-1)
N e tegn.1) +1 O!GZ2 e SIGZe8IGZ ALFA e N = Mue8!GZ2 SETA e SIGZe SQRT(2.0eALOGtc))
IFCALFA.GT.O.03 GO TO 150 ZMIN e 0.0 ZMAX e ALFA + SORT (ALFAeALFA + BETA
- BETA)
GO TO 200 150 ZMIN e ALFA = SETA IFCIMIN.LT.O.0) ZMIN s 0.0 l
ZMAX e ALFA + BETA 200 DZ s (ZMAX.ZMIN)/(Net)
Coene COMPUTE EXPONENTIAL INTEGRAL TERMS E(!) (SPECIAL PRDCED. FOR E(13)
EC1) e 2.18907-ALOG(MueDZ)
D0 250 I e 1, N I e ZMIN + (!*1)eDZ X e NUeZ IF(X.LE.0.9) 80 TO 250 X2 s XeX X3 s MeX2 Xs a XeX3 X5 e X.Xs IF(X.GT.1.0)) E(!)
IF(X.LE.1.0 E(I) e =ALOG(X) + A0*AleX*A2*X2*A3eX3*AseXa*AleX5 e (80*BleX*steX2*83*X3+Xa)/
. C 250 CONTINUE (Co*CleX+C2eX2*C3*X3*I43/(Xe EXP(X))
C**** COMPUTE INTEGRAND TERMS S(!) AND Pf!)
00 380 I e le N I e IMIN + (!=1}eDZ Figure F-Z. Masswi-Witten Computer Listing 1.109-78
1 tKP (.(2.Mle(2*M)/(3.ge81622))
Se EKPt.(I+M)e(I+M)/tt.Ge81sta)) e 5(1) e set (I)
Cemen Ptarona NUMERICAL INTEGRATION USINS 9*PDINT wtuf0N*C 300 P(!) a se tKP(.Mue!)
SUNS e 3.9 8
SUMP e 3.9 i
umon.t unaN.m+1 sunt a sunt + Diet (K)* Diet (K+1)+03eB(K+3 + Deet (K+3) 90 350 K e 1,Km,MM SUMP e sump + DieP(K)*02eP(K+1)*D3eP(K+2 *DaeP(K+3)+D5eP(K+s)
C
+04eP(K+5)+D7eP(K+o)* Deep (K+7)*D9eP(K*B)
C 350 CONT!wut
'D1sDZe(3UMt+10mpeZK)/(Det.Ste427es!S2)
RETUaN END I
i Figure F-2 (continued) 1.10s-79 l
l
^
~~ -
)
EOD M NIX F 1.
"Hoteorelegy and Atomic Emergy 1984.* 9. N. Slade (ed.). USAEC Aaport TID-241090.1968.
2.
J. N. Menewf. "A leathed for Campetty the Genue-Cose tatsgrals T and TI
- U"U'~
y 2
Cloud sector Average Model." Yankee Atomic Electric Caspey Report TAEC-1105.1976.
l
?
I
- e 9
a.
a 0
1.100-40 F._._
m,
,-,e
-