ML20138H465
| ML20138H465 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 08/31/1985 |
| From: | Bailey J GEORGIA POWER CO. |
| To: | Youngblood B Office of Nuclear Reactor Regulation |
| References | |
| GN-757, PROC-850831, NUDOCS 8512170203 | |
| Download: ML20138H465 (172) | |
Text
OFFSITE DOSE CALCULATION MANUAL FOR GEORGIA POWER COMPANY VOGTLE ELECTRIC GENERATING PLANT AUGUST 1985 d[cf/k'D-3.knjthfrcd}
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Ts ,j TABLE OF CONTENTS PAGE List of Tables v
. List'of Figures vil References ix Introduction xi
- 1. Liquid Effluents l-1 1.1 Liquid Effluent Monitor Setpoints 1-2 1.1.1 Liquid Waste Processing System Effluent Radioactivity Monitor 1-3 1.1.1.1 Monitor Setpoint Calculation Methodology-When_One Waste Monitor Tank per Unit Is to Be Released at a Time 1-5 1.1.1.2 Monitor Setpoint Calculation Methodology When Two Waste Monitor Tanks Per Unit Are to Be Released at a Time 1-14 1.1.2 . Steam
- Generator Blowdown Effluent Radioactivity Monitor; Turbine Building Drain Effluent Radioactivity Monitor; and Control Building Sump Effluent Radioactivity Monitor 1-17 O
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I TABLE OF CONTENTS (Cont.)
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PAGE 1.1.3 Nuclear Service Cooling Water System Effluent Radioactivity Monitor 1-18
, 1.2 Dose Calculation for Liquid Effluents 1-18 1.3 Dose Projections for Liquid Effluents 1-29 1.3.1 Thirty-One Day Dose Projections 1-29 1.3.2 Dose Projections for Specific Releases 1-30
- - 1.4 Definitions of Liquid Effluent Terms 1-31 1.5 Liquid Waste Processing System and Liquid Discharge Pathways 1-36
- 2. Gaseous Effluents 2-1 H2.1 Gaseous Effluent Monitor Setpoints 2-2 2.1.1 Unit 1 Turbine Building Vent; Unit 2 Turbine Building Vent; Radwaste Solidification Building vent 2-3 2.1.2 Unit 1 Plant Vent and Unit 2 Plant Vent 2-6 2.1.3 Gaseous Waste Processing System Discharge and Reactor Containment Purge 2-7 2.1.3.3 Gaseous Waste Processing System 2-7 2.1.3.2 Reactor Containment Purge 2-9 t
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TABLE OF CONTENTS (Cont.)
m 2.1.4 Consideration of Background and Monitor Response Adjustments in Establishing Gaseous Effluent Monitor Setpoints 2-11 2.1.5 Determination of Allocation Factor, AG 2-12 2.2 Gaseous Effluent Dose Rate and Dose Calculations 2-17 2.2.1 Dose Rates at or beyond the Site Boundary 2-17 2.2.1.1 Dose Rates Due to Noble Gases 2-17 2.2.1.2 Dose Rates Due to Radiciodines, Tritium, and Particulates 2-17 2.2.2 Air Doses and Dose to a Member of the Public at or beyond the Site Boundary 2-19 2.2.2.1 Air Doses at or beyond the Site Boundary 2-19 2.2.2.2 Dose to a Member of the Public at or beyond the Site ,
Boundary 2-21 2.2.2.3 Dose Calcuations to Support Other Technical Specifications 2-34 2.2.3 Dose Projections for Gaseous Effluents 2-72 2.2.3.1 Thirty-One Day Dose Projections 2-72
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TABLE OF CONTENTS (Cont.)
2.2.3.2 Dose Projections for Specific Releases 2-74 2.3 Meteorological Model 2-75 2.3.1 Atmospheric Dispersion 2-75 2.3.1.1 Ground-Level Releases 2-75 2.3.1.2 Mixed Mode Releases 2-77 2.3.2 Relative Deposition 2-80 2.3.2.1 Ground-Level Releases 2-80 2.3.2.2- Mixed Mode Releases 2-81 2.4 Definitions of Gaseous Effluent Terms 2-93 2.5 Gaseous Radwaste Treatment Systems 2-104
- 3. Radiological Environmental Monitoring Program 3-1
- 4. Total Dose Determinations 4-1
- 5. Potential Doses to Members of the Public Due to Their Activities Inside the Site Boundary 5-1
- 6. Interlaboratory Comparison Program 6-1 i
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) LIST OF TABLES TABLE TITLE PAGE 1.2 Bioaccumulation Factors 1-22 1.2-2 Adult Ingestion Dose Factors 1-24 1.2-3 Site Related Ingestion Dose Factors for Freshwater Fish and Drinking Water Consumption 1-27 ,
2.1-1 . Dose Factors for Exposure to a Semi-Infinite Cloud of Noble Gases 2-15 2.1-2 Gaseous Release Points Flow Rates - 2-16 2.2-1 Inhalation Dose Factors for Infant 2-35 2.2-2 Inhalation Dose Factors for Child 2-38 2.2-3 Inhalation Dose Factors for Teenager 2-41 2.2-4 Inhalation Dose Factors for Adult 2-44 2.2-5 Ingostion Doso Pactors for Infant 2-47 2.2-6 Ingestion Dono Factors for Child 2-50 2.2-7 Ingestion Doso Factors for Toonager 2-53 2.2-8 Ingostion Doso Pactors for Adult 2-56 2.2-9 External Doso Pactors for Standing on contaminated Ground 2-59 (D
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l LIST OF TABLES >
7-TABLE TITLE PAGE r
2.2-10 Individual Usage Factors 2-62 2.2-11 Stable Element Transfer Data 2-63 2.2-12 Controlling Receptor 2-64 2.2-13 Site-Specific (or Default) Values to Be Used l in Pathway Factor Calculations 2-65 2.2-14 Potential Receptor Locations and Pathways 2-70 2.2-15 Dispersion and Deposition Parameters 2-71 2.3-1 Terrain Elevation above Plant Grade 2-82 3.0-1 Radiological Environmental Sampling Locations 3-2 l
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(_) LIST OF FIGURES FIGURE TITLE PAGE 1.5-1 Liquid Waste Processing System (Unit 1) 1-37 1.5-2 Liquid Waste Processing System (Unit 2) 1-30 1.5-3 Liquid Discharge Pathways 1-39 2.3-1 Vertical Standard Deviation of Material in a Plume 2-84 2.3-2 Plume Depletion Effect for Ground-Lovel Roloason 2-85 2.3-3 Plume Depletion Effect for 30-Meter Releanoo 2-86 2.3-4 Plume Depletion Effect for 60-Motor Releanos 2-87 2.3-5 Plume Depletion Uffect for 100-Meter Releanos 2-88 2.3-6 Relativo Deposition for Ground-Loyal Roloanos 2-09 2.3-7 Relativo Deposition for 30-Motor Rolonnon 2-90 1.3-0 Relativo Deposition for 60-Motor Rolossen 2-91 2.3-9 Rolative Deposition for 100-Motor Rolonnea 2-92 2.5-1 Cancoun Wanto Proconsing System 2-105 2.$-2 Ventilation Exhaunt Trontment System 2-106 (Plant Vont)
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( LIST OF FIGURES FIGURE TITLE PAGE 2.5-3 Ventilation Exhaust Treatment System 2-107 (Turbine Building) 2.5-4 Ventilation Exhaust Treatment System 2-108 (Radwaste Solidification Building) 3.0-1 Terrestrial Stations Near Site Boundary 3-5 l
3.0-2 Terrestrial Stations beyond Site Boundary out l to Approximately Five Miles and Aquatic l Stations 3-6 l
l 3.0-3 Terrestrial Stationn beyond Five Milen 3-7 i 3.0-4 Drinking Water Stationo 3-0 l
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() REFERENCES
- 1. J. S. Boogli, R. R. Bellamy, W. L. Britz, and R. L.
Waterfield, " Preparation of Radiological Ef fluent Technical Specifications for Nuclear Power Plants", NUREG-0133 (October 1978).
- 2. Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR 50, Appendix I, U. S. NRC Regulatory Guide 1.109 (March 1976).
- 3. Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR 50, Appendix I, U. S. NRC Regulatory Guide 1.109 Rev. 1 (October 1977).
- 4. Vogtle Electric Generating Plant, Unit 1 and Unit 2, .
Environmental Report - Operating License Stage, Georgia Power Company.
- 5. Vogtle Electric Generating Plant, Unit 1 and Unit 2, " Final Safety Analysin Report", Georgia Power Company.
- 6. Mothods for Estimating Atmosphoric Transport and Dispersion of Gaceous Effluents in Routino Roloanos from Light-Wator-Cooled Roactors, U.S. NRC Regulatory Guide 1.111 (March 1976).
- 7. Methods for Entimating Atmosphoric Transport and Disporainn of Gancoun Ef fluento in Routino Rolonnon f rom Light-Wator -
Cooled Reactorn, U.S. NRC Regulatory Guido 1.111, Rev. 1 (July 1977) .
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5,, ,/ 8. Estimating Acquatic Dispersion.of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I, U. S. NRC Regulatory Guide 1.113, Rev. 1 (April 1977).
- 9. Vogtle Nuclear Plant, Units 1 and 2, Waste Water Effluent Discharge Structure Plume Analysis; Georgia Power Company; April 1981.
- 10. Direct communications with Water Resources Division; U.S.
Geological Survey; U. S. Department of Interior; February 1985.
- 11. Water Resources Data, Georgia, Water Year 1983; U. S.
Geological Survey, Water - Data Report GA-83-1; W. R.
Stokes, III, T. W. Hale, J. L. Pearman, and G. R. Buell; June 1984.
- 12. Vogtle Electric Generating Plant Land Use Survey - 1985; Georgia Power Company; May 1985.
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( j INTRODUCTION The OFFSITE DOSE CALCULATION manual is a supporting document of the RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS. As such the ODCM describes the methodology and parameters to be used in the calculation of offsite doses due to radioactive liquid and gaseous effluents and in the calculation of liquid and gaseous effluent monitoring instrumentation alarm / trip setpoints. The ODCM contains schematics of liquid and gaseous radwaste effluent treatment systems, which include release points to unrestricted ar'eas. Also included in the ODCM are a list and maps indicating specific sample locations for the radiological environmental monitoring program.
The ODCM will be maintained at'the plant for use as a reference guide-and training document of accepted methodologies and ,
calculations. Changes in the balculational methods or parameters
- will be incorporated into theI ODCM in order to assure that the ,,
ODCM represents current methodology in all applicable areas.
Computer software to perform the described calculations will be maintained current with the ODCM. ,
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F xj SECTION 1 LIOUID EFFLUENTS The Vogtle Electric Generating Plant is located on the west bank of the Savannah River approximately 151 river miles' from the Atlantic Ocean. There are two pressurized water reactors on the site. Each unit is served by a separate liquid waste processing system; however, certain components are shared between the two systems. All liquid radwastes treated by the liquid waste processing system are collected in waste monitor tanks for sampling and analysis prior to release. Releases from the waste monitor tanks are to the discharge line from the blowdown sump to the Savannah River. The blowdown sump receives input from the waste water retention basins, turbine plant a
cooling tower blowdown, and nuclear service cooling tower blowdown. Additional. dilution water is available from the cooling tower make-up water bypass line.
Although no significant quantities of radioactivity are expected in the nuclear service cooling water, the steam generator blowdown processing system, the turbine building drain system, or the control building sump, these effluent pathways are monitored as a precautionary measure. The monitors serving the latter three effluent pathways provide for automatic termination of release from these systems in the event radioactivity is detected above predetermined levels. These three systems discharge to the waste water retention basin.
h;( The Liquid Effluent Section of the ODCM describes the methodology for calculating monitor setpoints and for calculating
- individual doses due to liquid effluents released from Plant Vogtle to the Savannah River. Schematics of the liquid waste
, processing systems are presented in Figures 1.5-1 and 1.5-2.
b Liquid discharge pathways are shown in Figure 1.5-3.
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. 1-1
f) 1.1. LIQUID EFFLUENT MONITOR SETPOINTS Liquid monitor setpoint values calculated in accordance with the methodology presented in this Subsection will be regarded as upper bounds'for the actual monitor setpoints for high alarms. However, a lower setpoint may be established on the monitor if desired. Intermediate level setpoints should be established at an appropriate level to give sufficient warning prior to reaching the high alarm setpoint. The basic calculated monitor setpoint value is in terms of concentration, uCi/ml. The actual monitor setpoint established on the monitor is the calculated monitor setpoint value adjusted by appropriate calibration data, and monitor background. Monitor calibration data may include. operational data obtained from monitor response to concentrations determined by liquid sample analyses. In addition, monitor background must be controlled so that the monitor is capable of responding to concentrations in the range of the setpoint value.
For planned releases from the liquid waste processing systems' monitor tanks, monitor setpoints are determined t'o assure that the-limits of 10 CFR 20 are not exceeded. For the steam generator processing system effluent line, the turbine building drain effluent line and'the control building sump effluent line, the purpose of the monitor setpoints is to minimize releases of radioactivity from these systems by terminating releases upon detection of low levels of radioactivity. Therefore, setpoints for thase monitors should be established as close to background as practical to prevent spurious alarms and yet alarm should an inadvertent release
. occur. This approach should also be used for establishing monitor setpoints when no release is planned for a particular pathway, or if-there is no detectablo activity in the planned release, p
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,m k,) 1.1.1. . Liquid Waste Processing System Effluent Monitor (RE0018) (One monitor per unit)
The liquid waste processing system effluent line radioactivity monitors provide alarm and automatic termination of release prior to exceeding the concentration lirnits cpecified in 10 CFR 20, Appendix B, Table II, Column 2 at the release point to the unrestricted area. Concentration limits are specified in Technical Specification 3/4.11.1.1; setpoint requirements are specified in Technical Specification 3.3.3.10. To meet these specifications, the alarm / trip setpoint for this liquid effluent monitor is set to assure that the following equation is satisfied:
F+f I MPC III where:
CMPC = the effluent concentration limit cc responding to the specific mix of radionuclides in the waste monitor tank being considered for discharge, in uCi/ml.
c =
the setpoint, in uCi/ml, of the radioactivity monitor measuring the concentration of radioactivity in'the effluent line prior to dilution and subsequent release. (Note that tne monitor setpoint is directly proportional to the effluent flow rate, f, and inversely propertional to the dilution stream flow r a to , F + f . ) The setpoint represents a concentration value which, if exceeded, could result in concentrations exceeding the limits of 10 CFR 20 in the unrestricted area.
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3 ,) f =
the effluent flow rate at the location of the radioactivity monitor, in volume per unit time, and in the same units as F, below.
F =
the dilution stream flow rate as determined prior to the release point to the river, in volume.per unit time.
At Plant Vogtle, the liquid waste processing system collects liquid wastes in monitor tanks prior to release. There are two waste monitor tanks for each unit. The discharge lines from the two tanks join to form a common line, on which the radioactivity monitor is installed. The lines from each unit then join to form a common line which releases to the blowdown sump discharge line to the Savannah. River. (See Figure 1.5-3)
Dilution flow comes from the blowdown sump which receives water from nuclear service cooling tower blowdown, turbine plant cooling tower blowdown, waste water retention basin discharge, and the cooling tower make-up line. The two major sources for dilution are the turbine plant cooling tower blowdown and the cooling tower make-up line. A predetermined dilution flow rate must be assured for use in the ' calculation of the radioactivity monitor setpoint.
While equation (1) shows the relationships between the limiting concentration, CMPC, the effluent flow rate, f, the dilution flow rate, F, and the radioactivity monitor setpoint, it cannot practically b~e applied to a mixture of radionuclides with different limiting concentrations, i.e. different MPC values.
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For a mixture of radionuclides, equation (1) is satisfied in a practicable manner, based on measured radionuclide concentrations and a dilution stream flow rate which can be assured for the duration of the release, designated as Fd, by calculating the MPC fraction for the radionuclide mixture, the maximum permissible effluent flow rate, f m, and the . radioactivity monitor setpoint, c.
In order to facilitate effluent release control and accountability, liquid releases normally should be controlled.
administatively such that only one waste monitor tank per unit is released at a time. Subsection 1.1.1.1 presents the methodology for calculating the monitor setpoint for this situation. In the event'it becomes necessary to release both waste monitor tanks, of the same unit, at the same time, the methodology for calculating the monitor setpoint is more complex. This. increased complexity is due to the fact that the two waste monitor tanks discharge through a common line served by a single monitor.
Therefore, the radioactivity concentration at the. monitor is a function of the concentrations measured in each tank and the flow rates at which the tanks are released. The setpoint methodology for this situation is presented in Subsection 1.1.1.2.
1.1.1.1. Monitor Setpoint Calculation Methodology When One Waste Monitor Tank per Unit Is to Be Released at a Time Step 1) The radionuclide concentrations for the waste monitor tank planned for release are determined in accordance with Technical Specification Table-4.11-1. The relationship of the various required sample analyses is shown as follows: .,
' E T + (C a +C 1
C i=g C g s +Cg+C)t (2) 1-5 4
e ~ - - a ~< -v -, ,- s - - , - , -
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e f4-( ,) where Cg = the concentration of-each measured gamma emitter observed by gamma-ray spectroscopy of the particular waste sample.-
C, = the concentration of alpha emitters.in liquid
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waste as measured in the MONTHLY composite-sample. (NOTE: Sample is analyzed for, gross alpha.)
C s. = the measured concentrations of Sr-89 and 'Sr-
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90 in liquid waste as observed in the QUARTERLY' composite sample.
Cf =-
The measured concentrations of Fe-55 in liquid waste as observed in the QUARTERLY composite sample.-
J C'- Ce = the measured concentration of H-3 in liquid waste as determined from analysis of the
, MONTHLY composite sample.
1 The C g term will includeLthe analysis of each batch;
. terms for alpha, strontiums, iron', and tritium will be included in accordance with Tech'"Jal Specification Table 4.ll-1 as_
appropriate.
In order to' assure-that-sample analyses are based on.
samples which are' representative of the volume from which the samples are take'n,' liquid volumes must be- .
, t Mixing may be.
thoroughly mixed prior.to sampling.
5' accomplished by recirculating tank contents'fo'r a
. length of time' sufficient to result in a two-volume turnover of tank contents, or.by another method of mixing which has been demonstrated to achieve-mixing sufficient to allow repr'sentative e sampling.
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%f Step 2) Measured radionuclide concentrations are used to calculate MPC fractions. The MPC fractions'are used along with a safety factor to calculate a required dilution factor, which is the ratio of total dilution flow rate to monitor tank discharge flow rate which would be required to assure that the limiting concentrations of 10 CFR 20, Appendix B, Table II, Column 2 are not exceeded at the point of release to the river. The required dilution factor, RDF, is calculated as follows:
C.
RDF = Y MPC g
, (3)
C, C, 'C g Cy
[C9 q
MPC f MC where g a s t Ci = measured concentrations of Cg , C a ,'C s , Cf and Ct as defined in Step 1. Terms C,C,Cg, a s and C t will be included in the calculation as appropriate.
MPCi= .MPCg ,'MPC a rMPC s' MPCf , and MPCt are limiting concentrations of.the appropriate radionuclide from 10 CFR 20, Appendix B, Table-II,-Column.2. For dissolved or entrained noble gases, the concentration shall be limited to 2 x 10-4 uCi/ml. total activity. For gross alpha the maximum permissible concentration shall be 3x10-8 uCi/ml.
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q_,) SF = the safety factor, which is a conservative factor selected to compensate for statistical fluctuations and errors of measurements.
(For example, SF = 0.5 corresponds to a 100 percent variation.)
Step 3) . Determine the dilution stream flow rate which will be assured during the period of the release, which is designated as F d. For Plant Vogtle the flow rate which can be assured is the value selected as the setpoint for the dilution stream flow rate measurement device. Since the value selected as the setpoint for the dilution stream flow rate measurement device is.the dilution stream flow rate which can be assured during the release, this value must be used.as the basis for calculating the maximum permissible effluent release rate, f m, and-the radioactivity monitor setpoint, c.-
If simultaneous releases are planned from the.
liquid waste processing systems of Unit 1 and Unit 2, the dilution stream must be allocated between the two units. This is accomplished I
by multiplying the dilution stream flow rate, Fd , by an allocation factor, AF, to obtain a unit-specific dilution stream flow rate, F du Fdu = Fd (AF) (4)
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A._/ where AF = An allocation factor selected to apportion
' the diluting capacity of the dilution stream between the two units when simultaneous releases from the liquid waste processing systems.are planned. AF may be assigned any value between 0 and 1 for each unit under the condition that the sum.of the allocation factors does not exceed 1. For convenience AF may be assigned the value of 0.5 for each unit. Also, if it is desired to make liquid waste processing system releases from each unit without regard to releases from the other unit, AF should be assigned the value of 0.5 for each unit.
If more precise allocation values are desired, they may be determined-based on the relative radiological impact of each unit's-liquid waste processing system effluent stream on the dilution stream, whichimay be approximated by multiplying the MPC fraction of each effluent stream by its associated planned release flow rate and comparing these values for the two units.
If no simultaneous liquid waste processing f
- system. releases are being made, AF may be f assigned the value of 1 and then Fdu is equal to F d*
For the case RDF S 1, the waste monitor tank meets the limits of 10 CFR 20 without dilution and could be released at any desired
.[~'y flow rate. However, in order to maintain ~
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_ individual-doses due to radioactivity in liquids released to unrestricted areas ALARA, no releases from the liquid waste-processing system should be made if dilution stream flow rate, Fd, is less than 5000 gpm.
Step 4) For the case RDF>l, calculate the maximum permissible waste monitor tank discharge flow rate,fm, as follows:
F du f
m" RDF-1 I I-For the case RDFS 1, equation (5) is not valid. However, as discussed above, for the case RDF 1 the release may be made at full pump discharge capacity and the monitor setpoint calculated in accordance with Step 5.
NOTE 1: Waste monitor tank discharge flow rate is actually limited by pump design discharge capacity which is 100 gpm (maximum) . When calculated maximum permissible release flow rates are2 100 gpm, the release may be made at full pump capacity.
Release rates < 100 gpm may be achieved by throttling.
Note 2: If radioactivity due to plant operations is detected in any of the effluent streams discharging to the blowdown sump (waste water retention basin, nuclear service water cooling tower blowdown, or turbine plant
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cooling tower blowdown) , the 1-10 t-
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V diluting capacity of the dilution stream would be diminished. Under these conditions, equation (5) must be modified to include a term to account.for radioactivity present in the dilution stream prior to the introduction of the liquid waste processing system ef fluent:-
F
- du 1- i r m RDF-1
"(MPCilr i r, where (C1 /MPCg )r is the MPC fraction of the effluent stream (s) containing the detectable radioactivity.
f r is the flow rate of the effluent- stream (s) containing the radioactivity.
'If RDFS 1, NOTE 2 does not apply.
Step 5) Based on the values determined in the previous steps, a liquid. waste processing system effluent radioactivity monitor setpoint is calculated to provide assurance that the limits of 10 CFR 20, Appendix B,-
Table II, Column 2 will not be exceeded. The radioactivity monitor response is to gamma radiation primarily; therefore, the monitor setpoint calculation is based on C, g in units of uCi/ml, as follows:
c=A C (7) g m
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(s / where A = Adjustment factor which- will allow the setpoint to be established in a practical manner to prevent spurious alarms and to allow for the margin between measured concentrations and concentrations which would approach 10 CFR 20 limits:
A = ADF RDF (g)
NOTE: ADF is the actual dilution factor:
ADF = Fdu + f a f (8a) a and f a is the anticipated release flow rate from
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the waste monitor tank to be discharged.
If A2 1, calculate the monitor setpoint, c. However, if the calculated setpoint value is near the actual concentration planned for release, it may be impractical to set the monitor setpoint based on this value. If this situation should arise, it. indicates that measured concentrations are approaching values which could cause 10 CFR 20 limits to be exceeded. Therefor ~e, steps should be taken to reduce potential release concentrations. These steps may include decreasing the planned waste monitor tank release rate, increasing the dilution stream flow rate, postponing simultaneous releases, and/or by decreasing concentrations by further processing of the liquid waste planned for release. Following these 1-12
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(_/ actions, repeat the previous steps and calculate a new monitor setpoint.
I f A < 1, no release may be made under planned conditions. Consider the alternatives discussed above to reduce potential release concentrations, and calculate a new monitor setpoint based on the results of the alternatives selected.
The calculated setpoint establishes the base value for the radioacitvity monitor setpoint. However,~1n establishing the actual setpoint for a particular monitor, adjustments must be taken into account for background radiation levels and monitor calibration information. Background radiation levels must be controlled such that radioactivity levels in the effluent stream being monitored can accurately be assessed at levels below the setpoint value.
Calibration data may be supplied by the monitor-manufacturer; obtained by plant calibration utilizing calibration sources; or it may be developed, once plant operation is underway, by comparison of monitor response to results of sample analyses, if sufficient radioactivity is present in the stream served by the monitor.
The monitor setpoints determined in accordance with the methodology described above establishes the upper bound for a particular. monitor setpoint. Monitor setpoints may be established at lower values if desired.
If no release is planned for the discharge line served by a particular monitor or if the planned release contains no measurable radioactivity, the monitor setpoint should be established as close to background
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1.1.1.2 Monitor Setpoint Calculation Methodology When Two Waste Monitor Tanks per Unit Are to Be Released at a Time
-Step 1) Determine radionuclide concentrations for each waste monitor tank as described in Step
- 1 of Subsection 1.l'.l .1.
From the C g terms determin d for each tank, determine an effective ( Cg ), for the two tanks considered together as follows:
Y li q)1 + Y2 ( Cy )2 (9)
( Cg )e = V1+Y2 where Vi = Volume of liquid in tank containing greater quantity-(referred to throughout this Subsection as first tank.)
V = V lume of liquid in tank containing lesser 2
quantity (referred to throughout this Subsection as second tank).-
( Cg )y =
measured concentrations of gamma emitting radionuclides in first tank
( Cg )2 = measured concentration'of gamma emitting radionuclides in second tank Step 2) Octormine a required dilution factor, RDF,
-for each tank in accordance with Step 2 of Subsection 1.1.1.1. Using these values O calculate an effective required dilution b
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j-s s_ factor, (RDF)e, for the two tanks considered together as follows:
V 1 (RDF)i.+ V2 (RDF)2 (RDF)e * {l0)
V7 + .V2 where
= ' volume of first tank v1 V = volume of second tank 2
= required dilution' factor for first tank (RDF)1 (RDF)2
= required dilution factor for second tank Step 3) Determine the dilution stream flow'ra'te in accordance with step 3 of Subsection 1.1.1.1.
Step 4) To facilitate calculation of the monitor setpoint, determine release flow rates for each tank so that the durations of the releases from the two tanks are equal. First select a release flow rate'for the first .
tank, f.i Then determine the release flow rate for the second rank, f 2 , as follows:
V
- 1 2 f IIII 2 V 1
Next, determine a combined flow rate, fe , for releases.from both tanks, as follows:
f c" 1+E2 (12) n U
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'A ,/ Next, calculate a maximum permissible flow rate, f, m for the combined release in accordance with Step 4 of Subsection 1.1.1.1 using the effective.(RDF)e determined in Step 2 above.
Then compare the combined release flow ra'ce, f e, with the maximum permissible combined release flow rate, f' If fm>f, m c the release may be made under the assumed conditions. If fm ' fe , the-two release flow
-rates may be throttled, maintaining the same ratio of f 2 to ft , as determined earlier. .If it is impractical to throttle the release flow rates to the necessary degree to achieve fc 4f m, steps must be taken to reduce potential release concentrations prior to making the release, and a new f determined c
following the necessary actions. (Steps
.which may be undertaken to reduce potential release concentrations were discussed in Step 5 of Subsection 1.1.1.1.)
Step 5) Calculate the monitor setpoint in accordance with Step 5 of Subsection 1.1.1.1 with the following substitutions:
.Let C =
( Cg ) ,,
g RDF =
(RDF),,
and fa"f c observe the same limiting conditions discussed in Step 5 of Subsection 1.1.1.1.
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1.1.2.
) Steam Generator Blowdown Effluent Radioactivit Monitor (RE-0021);' Turbine' Building Drain Effluent Radio-activity Monitor (RE-0848); and Control Building Sump
~
Effluent Radioactivity Monitor-(RE-17646). (One of each monitor per unit)
Accceding tx) Plant Vogtle design and operating philosophy, the purpose of these radioactivity monitors is to-minimize release of radioactivity via these. effluent streams by automatically isolating or diverting effluent flow upon radioactivity ~in either of the effluent streams reaching certain low levels. In order to achieve the desired objective, setpoints for these monitors should be established as close to background radiation levels as practical to prevent spurious alarms and yet alarm should an inadvertent release occur. The actual setpoint for each monitor should be established under operating conditions and within the stated objective of preventing releases of radioactivity via these pathways. to the extent practicable (See NOTE at the end of Subsection 1.1.3). All three of these effluent ~ streams discharge to the waste water retention basin, '
which in turn releases to the. blowdown sump; the blowdown sump discharges to the Savannah River.
Should it become necessary to make releases from any of these three sources containing levels of radioactivity above that which would normally be isolated or diverted, radioactivity monitor setpoints should'be determined in the same manner as described in Subsection 1.1.1. However, special consideration
'must be given to Step 3. An allocation factor must be assigned to the release pathway under consideration here and allocation factors for other pathways, which may be releasing simultan-eously, adjusted if necessary so that for simultaneous liquid releases from the site the sum of the allocation factors does not exceed 1.
a 1-17
m
, 1.1. 3 . . Nuclear Service Cooling Water System Effluent Radioactivity Monitor (RE-0020 A and B) (Two monitors per unit) ~
Radioactivity in these effluent streams normally is expected to be below detectable levels. Therefore, the radioactivity monitor setpoints should be established as close to background as practical to prevent spurious alarms and yet alarm should an inad,vertent release occur. If any one (See NOTE below) of these effluent streams should become contaminated with radioactivity, radionuclide concentrations must be determined and a radioactivity monitor setpoint determined in the same manner as described in Subsection 1.1.1. However, special consideration must be given to Step 3. An allocation factor must be assigned to the release pathway under consideration here and allocation factors for other pathways, which may be releasing simultaneously, adjusted if necessary so that for simultaneous liquid releases from the site the sum of the allocation factors does not exceed 1.
NOTE: The initial monitor setpoint will not exceed 8.0E-07 uCi/ml relative to Co-60. This value is twice the minimum sensitivity of the detector (s). This value will be used until the radionuclide composition of the effluent stream can be determined in accordance with the sampling program.
1.2. DOSE CALCULATION FOR LIQUID EFFLUENTS For liquid releases from Plant Vogtle to the Savannah River, two human exposure pathways exist: consumption of drinking water and. fish taken from the river. Fish are considered to be taken from the vicinity of the plant discharge; drinking water is taken from the river for potable use at Beaufort, South Carolina, which is approximately 112 river miles downstream from the plant site. The methodology for calculating doses to an individual due to exposure to these two pathways is
('")
V presented in this Subsection.
l-18
. - - ~. - . _ - . - . - . . - . . - - - - - . - . - -.
(
x ,/ ._ The dose limits specified in Technical Specification 3.11.1.2 are on a per reactor basis. Therefore the doses calculated in accordance with this Subsection must be determined and recorded on a per reactor basis.
The dose to the maximum exposed individual due to radionuclides identified in liquid effluents released from each unit to unrestricted areas will be calculated for the purpose of i implementation of Technical Specification 3.11.1.2, as follows:
D g=E A g7g gty C gy F y (13) 1 where Dg = The cumulative dose commitment to the total body or any organ,T, due to radioactivity in liquid effluents for the total time period m
At y in mrem (Reference 1) .
i At1 = The length of the lth time period over which Cgi and F1 are averaged for any liquid release, in hours.
= The average concentration of radionuclide 1, '
C11 in undiluted liquid effluent during time period Ati from any liquid release, in uCi/ml. !
= The near field average dilution factor in the F1 Savannah River during any liquid effluent release, defined as the ratio of the undiluted liquid waste flow during release to the product of the average dilution stream flow rate into the river times Z.
i 1-19 I
e
, - - . - . - - - -. ~ _ . ... . - . . . = . . = .
f i-
. ["N NOTE: If simultaneous releases from both units l occur, the dilution stream flow rate must be apportioned between the two units as discussed in Subsection 1.1.1, Step 3. In such cases, F1 is unit-specific).
- - _(average undiluted liquid waste flow) (14)
F1 =
(average dilution stream flow during the period of release of radioactivity) xZ NOTE: The denominator of equation (14) is limited to 1000 cfs. (448,800 gpm) or less.
(Reference 1, Section 4.3).
Z = Applicable dilution factor for the Savannah River. For the months May through December, 1
Z=10; for the months January through April, '
Z=20. (Reference 5, Section 11.2.3.4; '
Reference 11)
Aig =
The site-related adult ingestion dose commitment factor to the total body or any organt for each identified radionuclide.
Site-related Atg values for Plant Vogtle are listed in Table 1.2-3 in mrem-ml per hr-uci.
A gg =Kg((U,/D,) e ~Atlw+U pDFge i tf) DFtz(15)
(_/ -
1-20
T K
o
= Units conversion factor 1.14 x 105, determined by:
6 3
, 10 pCi x 10 ml 8760 M uCi- 1 yr
- U, = Adult drinking water consumption (730 liters /yr; Reference 3, Table E-5)
D, = Dilution factor from the vicinity of the liquid release point for the plant site to the potable water intake location (8; j Reference 11) i = The decay constant for radionuclide i. (hr-1) t y. = Transit time from release to receptor for o
water consumption (48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />; Reference 3, Section A.2; Reference 10) l l Up = Adult fish consumption (21 kg/yr; Reference 3, Table E-5)
Bioaccumulation factor for radionuclide i, in BFi fresh water fish, in pCi/kg por pCi/l (See Table 1.2-1; Reference 3, Table A-1; Reference 2 for Ag) l tg
Transit time from release to receptor for
- fish consumption (24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />; Reference 3, I
Section A.2) l DFig = Dose conversion factor for.radionuclide i, for adults in organ,7, in mrem /pci, from
- Table 1.2-2 (Reference 3, Table E-11).
lO l-21.
i.
\._s TABLE 1.2-1 BIOACCUMULATION FACTORS (pCi/kg per pCi/ liter)*
Freshwater Element Fish H 9.0E-01 C 4.6E 03 Na 1.0E 02 P 1.0E 05 Cr 2.0E 02 Mn 4.0E 02 Fe 1.0E 02 Co 5.0E 01 Ni 1.0E 02 Cu 5.0E 01 Zn 2.0E 03 Br 4.2E 02 Rb 2.0E 03 Sr 3.0E 01 Y 2.5E 01 Zr 3.3E 00 Nb 3.0E 04 Mo 1.0E 01 Tc 1.5E 01 Ru 1.0E 01 Rh 1.0E 01 Ag 2.3E 00 ,
Te 4.0E 02 I 1.5E 01 Cs 2.0E 03 Da 4.0E 00 La 2.5E 01
['O ')
- Reference 3, Table A-1; Referenco 2 for Ag l-22
TABLE 1.2-1 (Continued)
BIOACCUMULATION FACTORS (pCi/kg per pCi/ liter)*
Freshwater Element Pish Ce 1.0E 00 Pr 2.5E 01 Nd 2.5E 01 W l.2E 03 Np 1.0E 01 f
1-23
Table 1.2-2 g3 Page 1 of 3 L )
Adult Ingestion Dose Factors *
(mrem per pCi ingested)
Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI H-3 No Data 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 C-14 2.84E-06 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 Na-24 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 P-32 1.93E-04 1.20E-05 7.46E-06 No Data No Data No Data 2.17E-05 Cr-51 No Data No Data 2.66E-09 1.59E-09 5.86E-10 3.53E-09 6.69C-07 Mn-54 No Data 4.57E-06 8.72E-07 No Data 1.36E-06 No Data 1.40E-05 Mn-56 No Data 1.15E-07 2.04E-08 No Data 1.46E-07 No Data 3.67E-06 Fe-55 2.75E-06 1.90E-06 4.43E-07 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 2.85E-06 3.40E-05 Co-58 No Data 7.45E-07 1.67E-06 No Data No Data No Data 1.51E-05 Co-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 No Data No Data 1.88E-06 Ni-65 5.28E-07 6.86E-08 3.13E-08 No Data No Data No Data 1.74E-06 Cu-64 No Data 8.33E-08 3.91E-08 No Data 2.10E-07 No Data 7.10E-06
- n-65 4.84E-06 1.54E-05 6.96E-06 No Data 1.03E-05 No Data 9.70E-06 Zn-69 1.03E-08 1.97E-08 1.37E-09 No Data 1.28E-08 No Data 2.96E-09 Br-83 No Data No Data 4.02E-08 No Data Na Data No Data 5.79E-08 Br-84 No Data No Data 5.21E-08 No Data No Data No Data 4.09E-13 Br-85 No Data No Data 2.14E-09 No Data No Data No Data LT E-24 Rb-86 No Data 2.llE-05 9.83E-06 No Data No Data No Data 4.16E-06 Rb-88 No Data 6.05E-08 3.21E-08 No Data No Data No Data 8.36E-19 Rb-89 No Data 4.01E-08 2.82E-08 No Data No Data No Data 2.33E-21 Sr-89 3.08E-04 No Data 8.84E-06 No Data No Data No Data 4.94E-05 Sr-90 7.58E-03 No Data 1.86E-03 No Data No Data No Data 2.19E-04 St-91 5.67E-06 No Data 2.29E-07 No Data No Data No Data 2.70E-05 Sr-92 2.15E-06 No Data 9.30E-08 No Data No Data No Data 4.26E-05 Y-90 9.62E-09 No Data 2.58E-10 No Data No Data No Data 1.02E-04 Y-91m 9.09C-ll No Data 3.52E-12 No Data No Data No Data 2.67E-10 Y-91 1.41C-07 No Data 3.77E-09 No Data No Data No Data 7.76E-05 Y-92 8.45E-10 No Data 2.47E-ll No Data No Data No Data 1.48E-05 f-
- Reference 3, Table E-11 U 1-24 J
Table 1.2-2 (Continued)
Page 2 of 3 Adult Ingestion Dose Factors *
(mrem per pCi ingested)
Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI Y-93 2.68E-09 No Data 7.40E-ll No Data No Data No Data 8.50E-05 Zr-95 3.04E-08 9.75E-09 6.60E-09 No Data 1.53E-08 No Data 3.09E-05 Zr-97 1.68E-09 3.39E-10 1.55E-10 No Data 5.12E-10 No Data 1.05E-04 Nb-95' 6.22E-09 3.46E-09 1.86E-09 No Data 3.42E-09 No Data 2.10E-05 Mo-99 No Data 4.31E-06 8.20E-07 No Data 9.76E-06 No Data 9.99E-06 Tc-99m 2.47E-10 G.98E-10 8.89E-09 No Data 1.06E-08 3.42E-10 '4.13E-07 Tc-101 2.54E-10 3.66E-10 3.59E-09 No Data 6.59E-09 1.87E-10 1.10E-21 Ru-103 1.85E-07 No Data 7.97E-08 No Data 7.06E-07 No Data 2.16E-05 Ru-105 1.54E-08 No Data 6.08E-09 No Data 1.99E-07 No Data 9.42E-06 Ru-106 2.75E-06 No Data 3.48E-07 No Data 5.31E-06 No Data 1.78E-04 Ag-110m 1.60E-07 1.48E-07 8.79E-08 No Data 2.91E-07 No Data 6.04E-05 Te-125m 2.68E-06 9.71E-07 3.59E-07 8.06E-07 1.09E-05 No Data 1.07E-05 Te-127m 6.77E-06 2.42C-06 8.25E-07 1.73E-06 2.75E-05 No Data 2.27E-05 Te-127 1.10E-07 3.95E-08 2.38E-08 8.15E-08 4.48E-07 No Data 8.68E-06 Te-129m 1.15E-05 4.29E-06 1.82E-06 3.95E-06 4.80E-05 No Data 5.79E-05 Te-129 3.14E-08 1.18E-08 7.65E-09 2.41E-08 1.32E-07 No Data 2.37E-08 Te-131m 1.73E-06 8.46E-07 7.05E-07 1.34E-06 8.57E-06 No Data 8.40E-05 Te-131 1.97E-08 8.23E-09 6.22E-09 1.62E-08 8.63E-08 No Data 2.79E-09 Te-132 2.52E-06 1.63C-06 1.53E-06 1.80E-06 1.57E-05 No Data 7.71E-05 I-130 7.56E-07 2.23E-06 8.80E-07 1.89E-04 3.48E-06 No Data 1.92E-06 I-131 4.16E-06 5.95E-06 3.41E-06 1.95E-03 1.02E-05 No Data 1.57E-06 I-132 2.03E-07 5.43E-07 1.90E-07 1.90E-05 8.65E-07 No Data 1.02E-07 I-133 1.42E-06 2.47E-06 7.53E-07 3.63E-04 4.31E-06 No Data 2.22E-06 I-134 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 No Data 2.51E-10 I-135 4.43E-07 1.16E-06 4.28E-07 7.65E-05 1.86E-06 No Data 1.31E-06 Cs-134 6.22E-05 1.48E-04 1.21E-04 No Data 4.79E-05 1.59E-05 2.59E-06 Cs-136 6.51E-06 2.57E-05 1.85E-05 No Data 1.43E-05 1.96E-06 2.92E-06 Cs-137 7.97E-05 1.09E-04 7.14E-05 No Data 3.70E-05 1.23E-05 2.11E-06 Cs-138 5.52E-08 1.09E-07 5.40E-08 No Data 8.01E-08 7.91E-09 4.65E-13 Ba-139 9.70E-08 6.91E-11 2.84E-09 No Data 6.46E-ll 3.92E-11 1.72E-07 Ba-140 2.03E-05 2.55E-08 1.33E-06 No Data 8.67E-09 1.46E-08 4.18E-05 Ba-141 4.71E-08 3.56E-11 1.59E-09 No Data 3.31E-ll 2.02E-ll 2.22E-17 Ba-142 2.13E-08 2.19E-11 1.34E-09 No Data 1.85E-ll 1.24E-11 3.00E-26
()
- Reference 3, Table E-11 1-25
Table 1.2-2 (Continued)
O Page 3 of 3 U Adult Ingestion Dose Factors
- l (mrem per pCi ingested)
Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI La-140 2.50E-09 1.26E-09 3.33E-10 No Data No Data No Data 9.25E-05 La-142 1.28E-10 l 5.82E-11 1.45E-ll No Data No Data No Data 4.25E-07 i Ce-141 9.36E-09 6.33E-09 7.18E-10 No Data 2.94E-09 No Data 2.42E-05 !
Ce-143 1.65E-09 1.22E-06 1.35E-10 No. Data 5.37E-10 No Data 4.56E-05 Ce-144 4.88E-07 2.04E-07 2.62E-08 No Data 1.21E-07 No Data 1.65E-04 Pr-143 9.20E-09 3.69E-09 4.56E-10 No Data 2.13E-09 No Data 4.03E-05 '
Pr-144 3.01E-11 1.25E-11 1.53E-12 No Data 7.05E-12 No Data 4.33E-18 Nd-147 6.29E-09 7.27E-09 4.35E-10 No Data 4.25E-09 No Data 3.49E-05 i
W-187 1.03E-07 8.61E-08 3.01E-08 No Data No Data No Data 2.82E-05 1
i Np-239 1.19E-09 1.17E-10 6.45E-11 No Data 3.65E-10 No Data 2.40E-05 i i
l
. t
~
I ,
l' s
.~ . l
~ . .
~
, -1 O
- Reference 3, Table E-ll ,
. ~
. % i
"[,b .
1-26' !
,p '
. p_ ,7-.- . , , - - ,
- Table 1.2-3 Page 1 of 2 -
to Related Ingestion Dose Factors, Aq , For Freshwater Fish and Drinking Water sumption*
(mrs/hr per uCi/ml)
NUCLIDE BONE LIVEP T. BODY THYROID KIDNEY LUNG GI-LLI H-3 0.00E+00 1.32E+00 1.32E+00 1.32E+00 1.32E+00 1.32E+00 1.32E+00 C-14 3.13E+04 6.26E+03 6.26E+03 6.26E+03 6.26E+03 6.26E+03 6.26E+03 NA-24 1.36E+02 1.36E+02 1.36E+02 'l.36E+02 1.36E+02 1.36E+02 1.36E+02 P-32 4.40E+07 2.74E+06' l.70E+06 0.00E+00 0.00E+00 0.00E+00 4.95E+06 CR-51 0.00E+00 0.00E+00 1.27E+00 7.58E-01 2.79E-01 1.68E+00 3.19E+02 MN-54 0.00E+00 4.41E+0'3 8.42E+02 0.00E+00 1. 31 E+ 0 3 0.00E+00 1.35E+04 MN-56 0.00E+00 1.73E-01 3.07E-02 0.00E+00 2.20E-01 0.00E+00 5.52E+00 PE-55 6.86E+02 4.74E+02 1.llE+02 0.00E+00 0.00E+00 2.65E+02 2.72E+02 FE-59 1.07E+03 2.51E+03 9.61E+02 0.00E+00 0.00E+00 7.01E+02 8.36E+03 CO-58 0.00E+00 9.59E+01 2.15E+02 0.00E+00 0.00E+00 0.00E+00 1.94E+03 CO-60 0.00E+00 2.78E+02 6.14E+02 0.00E+00 0.00E+00 0.00E+00 5.23E+03 NI-63 3'. 2 5 E+0 4 2.25E+03 1.09E+03 0.00E+00 0.00E+00 0.00E+00 4.70E+02 NI-65 1.94E-01 2.52E-02 1.15E-02 0.00E+00 0.00E+00 0.00E+00 6.39E-01 CU-64 0.00E+00 2.79E+00 1.31E+00 0.00E+00 7.02E+00 0.00E+00 2.37E+02 ZN-65 2.32E+04 7.37E+04 3.33E+04 0.00E+00 4.93E+04 0.00E+00 4.64E+04 ZN-69 1.24E-06 2.38E-06 1.65E-07 0.00E+00 1.55E-06 0.00E+00 3.57E-07 BR-83 0.00E+00 0. 0.0 E+0 0 4.02E-02 0.00E+00 0. 0 0'J+0 0 0.00E+00 5.80E-02 BR-84 0.00E+00 0.00E+00 1.16E-12 0.00E+00 0.00E+00 0.00E+00 9.12E-18 BR-85 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 RB-86 0.00E+00 9.75E+04 4.54E+04 0.00E+00 0.00E+00 0.00E+00 1.92E+04 RB-88 0.00E+00 1.18E-22 6.26E-23 0.00E+00 0.00E+00 0.00E+00 1.63E-33 RB-89 0.00E+00 1.38E-26 9.73E-27. 0.00E+00 0.00E+00 0.00E+00 0.00E+00 SR-89 2.50E+04 0.00E+00 7.16E+02 0.00E+00 0.00E+00 0.00E+00 4.00E+03 SR-90 6.23E+05 0.00E+00 1.53E+05 0.00E+00 0.00E+00- 0.00E+00 1.80E+04 SR-91 7.47E+01 0.00E+00 3.02E+00 0.00E+00 0.00E+00 0.00E+00 3.56E+02 SR-92 3.32E-01 0.00E+00 1.43E-02 0.00E+00 0.00E+00 0.00E+00 6.57E+00 Y-90 5.04E-01 0.00E+00 1.35E-02 0.00E+00 0.00E+00 0.00E+00 5.34E+03 Y-91M 1.31E-ll 0.00E+00 5.06E-13 0.00E+00 0.00E+00 0.00E+00 3.83E-ll Y-91 9.77E+00 0.00E+00 2.61E-01 0.00E+00 0.00E+00 0.00E+00 5.38E+03 Y-92 4.59E-04 0.00E+00 1.34E-05 0.00E+00 0.00E+00 0.00E+00 8.04E+00 Y-93 3.30E-02 0.00E+00 9.llE-04 0.00E+00 0.00E+00 0.00E+00 1.05E+03 ZR-95 5.47E-01 1.76E-01 1.19E-01 0.00E+00 2.75E-01 0.00E+00- 5.56E+02 ZR-97 7.45E-03 1.50E-03 6.87E-04 0.00E+00 2.27E-03 0.00E+00 4.66E+02 NB-95 4.38E+02 2.44E+02 1.31E+02 0.00E+00 2.41E+02 0.00E+00 1.48E+06 MO-99 0.00E+00 1.08E+02 2.05E+01 0.00E+00 2.44E+02 0.00E+00 2.50E+02 TC-99M 5.72E-04 1.62E-03 2.06E-02 0.00E+00 2.45E-02 7.92E-04 9.56E-01 TC-101 1.01E-33 1.45E-33 1.42E-32 0.00E+00 2.62E-32 7.42E-34 0.00E+00
- Calculated using Equation (15) 1-27
s Table 1.2-3 (Continud) '
Page 2 of 2 ;
,,.s Site Related Ingestion Dose Factors, Aq , For Freshwater Fish and
(%,/ ) Drinking Water Ccmsumption*
/
(mreWhr per uci/ml)
NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI
-RU-103 6.21E+00 0.00E+00 2.68E+00 '0.00E+00 2.37E+01 0.00E+00 7.25E+02 RU-105 8.81E-03 0.00E+00 3.48E-03 0.00E+00 1.14E-01 0.00E+00 5.39E+00 RU-106 9.42E+01 0.00E+00 1.19E+01 0.00E+00 1.82E+02 0.00E+00 6410E+03 AG-110M 2.53E+00- 2.34E+00 1.39E+00 0.00E+00 4.61E+00 0.00E+00 9.57E+02 TE-125M 2.56E+03 9.29E+02 3.43E+02 7.71E+02 1.04E+04 0.00E+00 1.02E+04 TE-127M 6.51E+03 2.33E+0.3 7.93E+02 1.66E+03 2.64E+04 0.00E+00 2.18E+04 TE-127 1.80E+01 6.46E+00 3.89E+00 1.33E+01 \7.33E+01 0.09E+00. 1.42E+03 TE-129M 1.09E+04 4.07E+03 1.73E+03 3.75E+03 4.55E+04 0.00E+00 3.49E+04i, TE-129 1.49E-05 5.59E-06 3.62E-06 1.14E-05 6.25E-05 0.00E+00 1.12E-05 TE-131M 9.58E+02 4.68E+02 3.90E+02 7.42E+02 4.74E+03 0.00E+00 4.65E+04 TE-131 5.82E-17 2.43E-17 1.84E-17 4.79E-17 2.55E-16 0.00E+00 8.24 E-18 TE-132 1.97E+03 1.27E+03 1.19E+03 1.40E+03 1.22E+04 0. 00E400 6.01E+04 I-130 7.56E+00 2.23E+01 8.80E+00 1.89E+03 3.48E+01 0.00E+00 1.92E+01 I-131 1.73E+02 2.48E+02 1. 42 E+ 02 8.13E+04 4.25E+02 0.00E+00 6.55E+01 I-132 4.60E-03 1.23E-02 4.31E-03 4 . 31E-01: 1.~96E-01 0.00E+00 2.31E-03 I-133 2.54E+01 4.41E+013 1. 35 E+ 01 6.49E+03' 7.70E+01 0.00E+00 3.97E+01 I-134 1.75E-08 4.74E-084 1.70E-08 8.22E-07 7.540-08 0.00E400 4.13E-ll
'I-135 1.34E+00 3.51E+00 1.30E+00 2.32E+02 5.64C+00 0.00E+00 3.97E+00 CS-134 .2.98E+05 7.10E+06 5.80E+05 0.00E+00 2.30r+05 7.62E+04 1.24E+04 CS-136 2.97E+04 1.17E+05 8.44E+04 ,0.00E+00 6.52Ef 04 8.94E+03 1.33E+04 CS-137 3.82E+05 5.23E+05 3.43E+05 'O.00E+00 1.78E+05 5.90E+04 1.01E+04 CS-138 9.47E-12 1. 87 E-ll 9.26E-12 0.00E+00 1.37E-11> 1.36E-12 7.98E-17 BA-139 5.44E-06 3.88E-09 1.595v07 0.00E+00 3.62E-09 2.20E-09 9.65E-06 BA-140 3.74E+02 4.69E-01 2.45E+01 0300E+00 1.60E-01 2.69E-01 7.69E+02 6 BA-141 3.78E-25 2.85E-28 1. 27 E-26 6 0. 0 0 E+ 00 2.65E-28 1.62E-28 1.78E-34 BA-142 0.00E+00 0.00E+00 0.00E+00 0.0GE+00 0.00E+00 0.00E+00 0.00E+00 LA-140 1.10E-01 5. 5 6 E-G2 1.47E-02 0 .'0 0 F+ 0 0 0.00E+00 0.00E+00 4.09E+03 LA-142 1.56E-07 7.llE-08 1. 7 7 E-0 8 0.00E+00 0.00E+00 0.00E+00 5.19E-04 CE-141 1.15E-01 7.79E'02 8 .' 8 4 E-0 3 0.00E+00 3.62E-02 0.00E+00 2.98E+02 CE-143 '8.65E-03 6.40E+00* 7.08E-04 0.00E+00 2.82E-03 0.00E+00 2.39E+02 CE-144 6.22E+00 2.60E+00 3.34E-01 0.00E+00 1.54E+00 0.00E+00 2.10E+03
.PR-143 6.10E 2.45E-01 3.02E-02 0.00E+00 1.41E-01 0.00E+00 ~2.67E+03 PR-144 1.37E-28 5.68E-29 6.95E-30 0.00E+00 3.20E-29 0.00E+00 1.97E-35 ND-147 4.llE-01 4.75E-01 2.84E-02 0.00E+00 2.78E-01 0. 00 E+0 0 2.28E+03 ,
-W-187 1.48E+02 1.24E+02 4.32E+01 0.00E+00 0.00E+00 t0.0CE+00 4.05E+04 ,
NP-239 2.81E-02 2.76E-03 1.52E-03 0.00E+00 8.61E-03 0.C O E+00 5.66E+02 e
t
- Calculated Using Equation (15)
' s s
[
, 1-28
1
)
,~
I ,) 1.3. DOSE PROJECTIONS FOR LIQUID EFFLUENTS l.3.1. Thirty-One Day Dose Projections In ~ order to meet the requirements of Technical Specification 3.11.1.3, which pertains to operation cf the liquid radwaste treatment systems, dose projections must be made at least once per thirty-one days, during perioda in which discharge of liquid effluents containing radioactive materials to unrestricted areas occurs or is expected.
Projected quarterly doses to individuals due to liquid effluents q may be determined as follows:
D tb(prj) = tb (c) x 91
, (16)
D D o(c) o(prj) = t
- 91 (17) j where D
tb(c)
=
the cumulative total body dose for the elapsed portion of the current quarter plus the release
-j i , under consideration.
V s t =
the number of days into the current quarter.
4 D =
the cumulative organ doses for specific o(c) organs, for the elapsed portion of the current quarter plus the release under consideration.
/
'yj 1-29
_\
.l 4 l l
I i.
a
() ~
If operational activities planned during the remainder of the quarter are expected to result in liquid' releases which will contribute a doseoin addition to the doce due to routine liquid effluents, this additional dose contribution should be included in the equations as follows:
D = tb(c) tb (prj) x 91 + D PA (18)
D o(prj) = (c) x 91 +D pg (yg) where.Dpg is the expected dose due to the particular. planned activity.
, 1.3.2. Dose Projections for Specific' Release Dose projections may be performed for a particular release by performing a pre-release dose calculation assuming that the planned release will proceed as anticipated. For' individual dose projections due to-liquid releases, follow the methodology presented in Subsection 1.2 using sample analyses values for the source.to be released and parametric values expected to exist for e
the release. period.
i i
e t
- V 1-30
I ~
c's 1.4 DEFINITIONS OF LIQUID EFFLUENT TERMS N,,Y Section Of Term Definition Initial Use A = adjustment factor applied to facilitate setting actual monitor setpoints 1.1.1 A ig = the site related ingestion dose commitment factor for the total body or any organt for each identified principal radionuclide listed in Table 1.2-3 in mrem-ml per br-uCi. 1.2 ADF =- the actual dilution factor, which is the ratio of unit-specific total dilution flow rate to actual (anticipated) effluent release rate. 1.1.1.1 BF i = Bioaccumulation Factor for nuclide i, in fresh water fish, pCi/kg per pCi/1, from table 1.2-1. 1.2 c =
the setpoint of the radioactivity monitor which measures the radioactivity concentration in the effluent line prior to dilution and subsequent release. 1.1.1 Ca = the effluent concentration of alpha emitting nuclides observed by gross alpha analysis of the MONTHLY composite samp'le. 1.1.1 Cg =
the concentration of Fe-55 in liquid wastes as observed in the QUARTERLY composite sample. 1.1.1
( ) 1-31 x_-
.a i
af Section Of
'D-Term Definition Initial Use
}
.C g = the' effluent concentration of a gamma emitting nuclide, g, observed by gamma-ray spectroscopy of the waste' sample. 1.1.1 L
~
C i. =
the concentration of nuclide i as determined by the analysis of the waste
-sample. 1.1.1 C i1 =
the average concentration of radionuclide .
1, in undiluted liquid effluent during
- time period Ait , for a release in uCi/ml. 1.2 CMPC " 'the' effluent concentration limit (Technical Specification 3.11.1.1) im menting 10 CFR 20 for.the site, in
[ Cs =
the concentration of Sr-89 'or Sr-90 in l
i liquid wastes as determined by analysis j of the QUARTERLY composite sample. 1.1.1 h- Ct =
the measured concentration'of H-3 in liquid waste as determined by analysis of the MONTHLY compc3ite sample. 1.1.1 I Dg =
the cumulative dose commitment to the L-total body or any-organ,T , from the liquid effluents for the total time period. 1.2 i.
D, =
Additional dilution factor between
( vicinity of release point and drinking L water location. 1.2 l-O l-32 I
Section Of v' N Term Definition' Initial Use h -
DFig = a dose conversion-factor for nuclide, i, for adults in organ,r , in mrem /pci.found
.in Table 1.2-2. 1.2 f =
the' flow as determined for the radiation monitor location. (General expression for equation ~1).. 1.1.1 F- =
the dilution' water flow rate as determined prior to the release point, in volume per unit time. (General expression for equation 1). 1.1.1 Fd =
the flow rate of the dilution stream which can be assured during the time of release. This is also the setpoint for the dilution stream flow rate measurement device. 1.1.1 P = the unit-specific minimum' flow rate of du the dilution stream used as the basis for setpoint calculations. 1.1.1 F1 = the near field average dilution factor for Ctt during any liquid effluent release. 1.2 f
a
=
ef fluent flow rate (actual value) . 1.1.1 f
m
= maximum permissible effluent flow rate. 1.1.1 K
o = 1.14 x 10 5 , units conversion factor. 1.2 n - .
1-33
Section Of
^'T Term Definition Initial Use l
m = number of liquid releases. 1.2 MPCi= MPC g, MPC a, MPCs , MPCg , and MPCt which are the limiting concentrations of the appropriate gamma emmitting radionuclides, alpha emitting radionuclides, strontium, iron and tritium, respectively, from'10 CFR, Part 20, Appendix B, Table II, Column 2. 1.1.1 RDF = The required dilution factor, which is the ratio of the total dilution flow rate to the effluent stream flow rate (s) required to assure that the limiting concentration of 10 CFR, Part 20, Appendix B, Table II, Column 2 are met at the point of discharge to the Unrestricted Area. 1.1.1 SF = the safety factor, which is a conservative f actor used to compensate for statistical fluctuations and errors of measurement. 1.1.1 tg = the transit time from release to receptor (fish consumption) . 1.2 tw = the transit time from release to receptor (drinking water consumption) . 1.2 Att = duration of release under consideration. 1.2 Up = 21 kg/yr, fish consumption '(adult) . 1.2 O
V l-34
_m .- .. ..- . . ~ _ _ _ ...._ _ _ .. _ _ _ _ . _ _ _.__ _ .___ .. .- . __ _ _..__.._ -. _ _ __.. _ ._ . ,__ _
i i
i Section Of !
Term Definition Initial Use l i
U, = 730 liters /yr, water consumption (adult) 1.2 ,
i I
Z = Applicable factor when additional -
receiving water body dilution is [
considered. 1.2 Al =. The decay constant for radionuclide 1.
- (sec-1)' l.2 !
i r
i I
a k
I i
(
i s
i 1-35 t i
'l 1
l
,m
! )
( ,/ 1.5 LIQUID WASTE PROCESSING SYSTEM AND LIQUID DISCHARGE PATHWAYS Figures 1.5-1 and 1.5-2 are schematics of the Liquid Waste Processing Systems for Unit 1 and Unit 2 respectively. The dotted lines indicate alternate pathways through which liquid wastes may be routed as appropriate. These alternate routes increase the operational flexibility of the liquid waste processing systems.
FIGURE 1.5-3 is a schematic of plant discharge pathways for liquids.
O v
1-36
gz ry v Figure 1.5-1 LIQUID WASTE PROCESSING SYSTEM (Unit 1)
Laundry and Hot Shower py,,,
Tank Dra M
($ hared) Tank Strainer
, l 5 trainer r-------4 Filter ! ! IIII !
I e .. .. i -- - O X w. t, . ! ---*O
-____ . Monitor Tank
..q_--_____ct..-.g
, Domin '
i 8 i
Waste I Monitor I Tank I Filter l i
,__,g i
_ _ _ _ _ _ _ s_ _ __ q_ _ _ _ _ _ _ . ,
I Waste i Weste I
Monitor Montter Tank .i fant i
I
& ~ '
g A Radfoactivity Monitor O RE 0018 1 From Unit 2 Waste o . Monitor Tank (s)
To Discharge
' Dotted and/or lines indicate additional alternate routes for increased operational flesibility processing.
To Unit 2 From/To Unit 2 To Drain Channel A From Drain Channel A k
1 .
(O.
'N) rigure 1.'5-2 LIQUID WASTE PROCESSING SYSTEM (Unit 2) !
J. ,
Q Floor
'I Dratn
, fank l
I
. Strainer r - - - - -- - - "
3
( Filter l l
i .__. o R we,,, G eenitor Tank .-d,---_--__e. . . .. g
.. Domin s I I
I Weste -
Monitor 3 Tank I IIII
g .. g
. _ _ _ _ _ _ L _ _ q_ _ _ _ _ _ _ . ,
Waste i Weste Monttor i Montter Tank i Tank i
I
& m 8 m &
9 Radioactivity Monitor g RC.C0!S To Otscharge ($ee figure 1,$.1)
- Dotted lines indicate alternate routet for increated operettonal flestbility nd/or additional processing, From Un1t i From/fo Unit I to Drain Channel A From Orain Channel A
. \_
l-38'
1 l
,m
(
)
v Figure 1.5-3 LIQUID DISCHARGE PATHWAYS l
(Typical of Both Units)
Steam Turbine Nuclear Genera tor Building Service Blowdown Drafn Cooling Water From Other Sumps C and Drains O
m Control Turbine O Building Plant Sump Cooling Tower From Other Sumps from Unit 2 Nuclear Service Cooling Water Sepa rator From Unit 2 Turbine Plant Cooling Tower I l
Waste Water Liquid Retention Waste Basin Processing System a from Unit 2 Waste i " 6 Water Retention Basin from Unf t 2 6 81owdown 'Coolfng Tower rakegg Ltouid Weste - I"*8 ### " "'
Processing System A
Radfo8Clivity Monitors!
Rt0020 RE0021 R(W48 R(17646 Rt0018
[ \ '
(
s s) 1-39
( ) SECTION 2 GASEOUS EFFLUENTS At Plant Vogtle there are five potential points where radioactivity is released to the atmosphere in gaseous discharges. These five potential release points are Unit 1 plant vent; Unit 2 plant vent; Unit 1 and Unit 2 turbine building vents, which are not normal release pathways until a confirmed primary to secondary leak exists; and the radwaste solidification building vent.
The turbine building vent serves as the discharge point for the condenser air ejector and steam packing exhauster system. The fuel handling building is common to both units; however ventilation from this area is through the Unit 1 plant vent. Certain components of the Gaseous Waste Processing System are shared between the two units and releases from this system are through the Unit 1 plant vent. Containment building releases are through the respective plant vents.
Gaseous releases from the turbine building vents and the radwaste solidification building vent are considered to be ground-level releases. Gaseous releases from the plant vents are considered to be mixed-mode releases as determined by the wake-split model. All five release points are considered to be continuous releases. In the absence of confirmed primary to secondary leak (s), the turbine building vents are not release points.
Gaseous offluent monitor setpoints are required only for noble gas' monitors serving the five release points.
Methodology for calculating noble gas monitor setpoints in presented in Subsection 2.1. Although setpoint calculations are not required for radioiodine and particulate monitors, the methodology for assuring the potential organ done rates due to
[) radiolodines, tritium, and particulates in gaseous releases from ,
\' the site do not exceed the limits of Technical Specification 3 .11. 2.1 ( b) is presented in the NOTE in Subsection 2.2.1.2.
2-1
r
/ 2.1 GASEOUS EFFLUENT MONITOR SETPOINTS V
Gaseous monitor setpoints are determined by calculating a basic setpoint value, es , f r a particular monitor, adjusting l this value by appropriate calibration and/or monitor response factors, and finally adding this adjusted setpoint value to monitor background to obtain the actual setpoint for the monitor.
Subsections 2.1.1, 2.1.2 and 2.1.3 present the methodology for calculating the basic setpoint value, e *s l Subsection 2.1.4 addresses monitor response adjustments and
! background considerations.
Monitor setpoints determined in accordance with this Subsection will be regarded as upper bounds for the high alarm setpoint. However, a lower setpoint may be established on the l monitor if desired. Also, intermediate alarm setpoints should be established at a level below the high alarm setpoint to give appropriate warning prior to reaching the high alarm setpoint.
If no release is planned for a particular pathway, or if there is no detectable activity in the planned release, the i monitor setpoint should be established an close to background as l practical to prevent spurious alarma and yet alarm should an inadvertent release occur. The monitor setpoint determined in l this manner must be less than the setpoint value calculated in accordance with Subsection 2.1.1 or 2.1.2 assuming Kr-88 as the radionuclide being released.
If a calculated setpoint is less than the monitor reading acoociated with the particular release pathway, no release may be made under current conditions. Steps must be taken to reduce contributing source terms and/or reassign allocation factors (discuaned in Subsection 2.1.5) and the notpoint recalculated, if releason via the pathway under
, consideration are to continue.
t O
2-2 L
Throughout this Subsection the term Cm is used to designate monitor response which corresponds to a concentration. The response for a particular monitor may be developed based on monitor calibration data or determined by observing monitor response to a measured concentration.
2.1.1 Unit 1 Turbine Building vent, Unit 2 Turbine Building Vent and Radwaste Solidification Building Vent Monitors: RE-12839C (Unit 1), RE-12839C (Unit 2) and ARE-0026C NOTE: Turbine Building Vent serves as the release point for the Condenser Air Ejector and the Steam Packing Exhauster.
For the purpose of implementation of Technical Specification 3.3.3.11, the notpoint for these noble gas monitors will be calculated as follows:
eg = calculated setpoint concontration value r
(AG) (SF) (Rt) (DTB) (1) c, =
the lessor of4 or (AG) (SF) (Rg) (Dgg) (2) 5 SF = safety factor, which is a conservative factor applied to each noble gas monitor to compensate for statistical fluctuations and errors of measurement. (For example, SF =
0.5 corresponds to a 100 percent variation.)
l l AG = an administrativo allocation factor applied
! to apportion the roloano setpoints among all gaseous release dischargo pathways (normally five) to assure that release limits will not be exceeded by. simultaneous releason. The 2-3 l
r.
l l
p V allocation factor for a particular discharge i
pathway may be assigned any desired value between 0 and 1 under the condition that the
- sum of the allocation factors for all i simultaneous release pathways does not exceed
- 1. For ease of implementation, AG may be set l equal to 1/n, where n is the number of simultaneous final gaseous release points.
For.a more exact determination of allocation-factors, see Subsection 2.1.5.
D TB = Dose rate limit to the total body of an individual which is 500 mrem / year.
l Rt = monitor reading per mrem /yr to the total body for vent releases.
Rt = C, + ((X/Q)g Kg Qgg ) (3)
'fhere C, = monitor response of a noble gas monitor corresponding to the grab sample radionuclide concentrations taken in accordance with Technical Specification Table 4.11-2.
(X/0)g = the highest annual average relative concentration at the site boundary. (If desired, the annual average relative concentration at the site boundary for the particular release point may be used.) The release points addressed in this Subsection are ground-level tuf.wases.
(X/Q)g =
2.2 x 10-6 sec/m 3 in the NE sector.
2-4
( ,) Ki = total body dose factor due to gamma emissions from radionuclide 1 (mrem /yr per uCi/m3 ) from Table 2.1-1.
= rate of release of noble gas radionuclide i Qig
,., . (uci/sec) from the vent release pathway under consideration (ground-level) , which is the product of Xiy and Py , where Xiy is the concentration of radionuclide i for the particular release and Fy is the maximum expected release flow rate for this release point. (Xiy in uCi/ml and F y in ml/sec.)
D as = Dose rate limit to the skin of the body of an individual in an uncestricted area which is 3000 mrem / year.
Rs = monitor reading per mrem /yr to the skin.
R, = Cm ((X/0)g (Lg + 1.1 Mg ) Ogg) (4) where Lg = skin done factor due to beta emissions from radionuclide 1 (mrem /yr per uC1/m3 ) from Table 2.1-1.
1.1 = mrom skin dose por mrad air done.
Mg = air dose factor due to gamma emissions from radionuclide 1 (mrad /yr per uci/m3 ) from Table 2.1-1.
iA) x ./
2-5 .
l l \
2.1.2 Unit 1 Plant Vent and Unit 2 Plant Vent
( Monitors: RE12442C (Unit 1) and RE12442C (Unit 2) l Gaseous releases from the plant vent (s) are regarded as mixed-mode. releases in that under certain conditions of vent exit. l velocity and meteorological conditions, the plume will behave as I' an elevated release. Under other conditions of vent exit velocity and meteorological conditions, the plume will behave as ;
a ground-level release. Using the wake-split model, dispersion l
l values have been calculated utilizing expected annual average l conditions. !
i The setpoint calculation methodology presented in !
Subsection 2.1.1 applies to these monitors with the following two !
l exceptions: [
l i
Exception 1: !
i l l
! In equation (3) and equation (4) replace r l (X/0)g with (X/Q)g where (X/Q)g is the mixed j mode dispersion parameter detetermined by the ;
l wake-split model.
= the highest annual average relative (X/0)M concentration at the site boundary for mixed t
l mode releases.
i l
(X/Q)M
= 2.0 x 10~7 sec/m3 in the NE sector. '
l Exception 2: [
and replace Qig with Q im whero Qi m in defined ao f follows: !
l !
l I Q,i = rate of release of nobio gan radionuclide i '
tan onn a n xe d c O the product of X{y and Py , where X ty in the concontration of radionuclido i for the
[
i 2-6
(,
t j particular release and F y is the maximum expected release flow rate for this release l point. (Xiy in uCi/ml and F y in ml/sec.) '
2.1.3 Gaseous Waste Processing System Discharge and Reactor Containment Purge Monitors: ARE0014, RE-2565C (Unit 1) and RE-2565C (Unit 2)
The Gaseous Waste Processing System discharges to the Unit 1 plant vent, Unit 1 containment purge dischargos to the Unit 1 plant vent, and Unit 2 containment purge dischargen to the Unit 2 plant vent. The plant vents are equipped with continuous final effluent monitors as discussed in Subsection 2.1.2.
!!owever, due to the potential significance of releases from those cources, the notpoint methodology in presented for the system effluent monitors also.
1 Sampling and analyson are completed and monitor setpointa determined prior to release. Those notpoints must take into account nimultaneous release pathways; the combined allocation factorn for contributing pathway monitors must not exceed the allocation factor for the final releano pathway monitor to which they contribute.
Downstream monitors must also take into consideration the combinations of source terms for the particular reloano pathway.
2.1.3.1 Gannoun Wanto Proconning system Monitor: ARE-0014 The Ganooun Wan'to Prococaing System dischargos through j the Unit 1 plant vents therefore, the Ganeous Wanto Proconning Syntom offluent monitor is not the finsi monitor for relonnes
(~N from thin system. Ilowever, because of the significance of this V
2-7 e
, release pathway and because the Unit 1 plant vont monitor setpoint has to accommodate releases from the Gaseous Waste Processing System, the setpoint methodology for this monitor is presented.
%, The methodology presented in subsection 2.1.2 applies to this monitor with the following five exceptions:
Exception 1:
Rt" Et" m & ((X/0)M K i 9) 1 (5)
Exception 2:
Cm = monitor responne of the Gaseous Waste Processing System monitor for radionuclide concentrations to be discharged (sample taken and analyzed prior to discharge).
Exception 3:
= rate of release of noble gas radionuclide 1 qi (uCi/nec) from the Ganeous Waste Procencing System, determined by multiplying the expected release rate by the concentration of radionuclide 1.
Exception 4:
R n
- E n = C, + ( ( X/Q) M Ibi + 1.1Mg) g) g (6)
Exception 5:
AG = A nelected allocation factor value which munt be lean than the allocation factor for the monitor nerving the final relenae point, Unit 1 plant vent.
2-0
t l
l l When releases are to be made from the Gaseous Waste l Processing System, it will be necessary to redetermine the setpoint for the Unit 1 plant vent monitor (RE-12442C) which is downstream from the Gaseous Waste Processing System effluent monitor (ARE-0014).
Redetermination of this setpoint is accomplished by applying the methodology of Subsection 2.1.2 with the following two exceptions:
Exception la A now sourco term, (Q imI GP, is determined which l includes the routino Unit 1 plant vont source term Oim (based on l sample results from Technical Specification Table 4.11-2) l combined with the Gaseous Waste Processing System source term for the tank planned for release, qt, as follows:
(O imI GP
- Oim + 91 (7) l l Exception 2:
l C, a monitor responno corresponding to tho l
concentration resulting from the combined l release, which is obtained by dividing (Qim Gp by the flow rate (ml/sec) through the plant vent.
2.1.3.2 Ronctor containment Puroa Monitors: RE-2565C (One for each unit) [
Unit 1 containment purgo dischargos through the Unit 1 j plant vont; Unit 2 containment purgo dischargon through the Unit 2 plant vent. Thoroforo, the containment purgo monitor is not I
l the final monitor for containment purge releanos. !!owever , l' 1
l 2-9 I
O because of the significance of these releases and because the respective plant vent monitor setpoint has to accommodate containment purge releases, the setpoint methodology for these monitors is presented.
l The methodology presented in Subsection 2.1.2 applies to this monitor with the following five exceptions:
l l Exception la l Rt"#t" m + ( M/0)g hK g q) g (8) l Exception 2 l
l l
Cm = monitor response of the containment purge l monitor for radionuclide concentrations to be j discharged (sample taken and analyzed prior to discharge) .
l l Excpetion 3:
l l
gg a rate of release of noble gas radionuclide 1 (uci/sec) from containment purge, determined l by multiplying the expected release rate by the concentration of radionuclide 1.
Exception 4:
l b
R, = r, = C, + ( p/Q) M i Ibi + 1.lM g) q) g (9) j Exception 5:
l l
AG = a selected allocation factor value which must l
be less than the allocation factor for the l monitor serving the final release point, the l (7 respective plant vent.
I V 2-10 l
I L
i When containment purge releason are to be mado, it will '
( be necessary to redetermine the notpoint for the respective plant f vent monitor (RE-12442C) which in downstream from the containment l purge monitor (RE-2565C).
l .
' :3,.
Redotormination of this setpoint in accomplished by applying the methodology of Subsection 2.1.2 with the following two exceptions:
Exception la l
l A new source term, (Ql mI CP, in dotormined which j includon the routine respective plant vont cource term Qim (banod j on sample results from Technical Specification Table 4.11-2) l combined with the containment purgo cource term for the unit containment planned for reloano, qg, as follows:
(Qgm)CP " Olm
- 91 (10) ,
Exception 2.
C, = monitor responne corresponding to the concentration resulting from the combined releano, which in obtained by dividing (Qi 'n I CP by the flow rato (ml/nec) through the plant vent.
, 2.1.4 _Connidoration of nackground and Monitor nonnonno Adiuntmentn in Entablishinq cannoun Effluent Monitor Satpointn The calculated notpoint concentration, e n, ontablinhon the bano value for the monitor notpoint. Ilowever, in ontablishing the actual monitor notpoint for a particular I monitor, background radiation lovola and monitor ronponno adjustmenta munt be considorod.
2-11..
O Contributions to background radiation levels may include ambient background, plant environmental background at monitor locations when plant is in shutdown status, plant environmental background at monitor location when plant is at power, and internal background of monitor due to contamination of sample chamber. Normally, the actual monitor setpoint includes the calculated setpoint value plus background. Background levels must be controlled such that radioactivity levels in the effluent stream being monitor 2d can be accurately assessed at or below the
. calculated notpoint value.
1 Monitor responno adjustments may be necessary to assure that monitor readout accurately reflects radioactivity levels in the monitored offluent stream. Monitor adjustments (monitor setting) may be based on monitor calibrations, monitor calibration data supplied by the monitor vendor, or by operational data which correlaten monitor ronponse to samplo analynes associated with actual gaseoun offluent releases.
2 1.5 Dotormination of Allocation Factor, AG I When simultaneous ganeous releanos are made to the environment, an (administrative) allocation factor must be applied to each discharge pathway. This la to ensure that I
simultaneous gaseous releanes from the site to unrestricted arcan will not exceed the dose rate limits specified in Technical Specification 3.11.2.1. For Plant Vogtle, final discharge pathways which may be released simultaneously are the Unit 1 plant vent, Unit 2 plant vent, Unit 1 turbine building vent, Unit l 2 turbine building vent, and the radwaste nolidification building vent. The allocation factor for each ganeous dischargo pathway munt be betwoon 0 and 1 ar.d the sum of the allocation factors for the simultaneoun reloanon must not exceed 1.
I l
-s G
2-12 L.
O Q There are three methods by which allocation factors may be determined:
- 1. The allocation factor for a particular release pathway may be administratively selected based on an estimate of the fraction of the total dose rate (from all simultaneous releases) which is contributed by the particular release pathway.
- 2. The allocation factor may be calculated using the expression AG = 1/n (11) where n = the number of release pathways to be released simultaneously.
- 3. The allocation factor may be determined for a particular '
dischargo pathway by calculating the ratio of the total body dono rato due to noblo gasen released from the particular dischargo pathway under consideration to the total body dose rate due to noble gases in all simultaneous releases, as follows:
For Unit 1 turbine building vent, Unit 2 turbine building vent, and radwasto colidification building vont (ground-level reloacco):
AG = IX/0)G [E i l 0 1o(r)
(12) k(M)g kK g O gg + [3g (X/0)g hK g O lm For Unit 1 plant vent and Unit 2 plant vont (mixed-modo roloanos):
(X/ol g hK g Og ,g,3 AG =
e]
/
g(xeo)G yxio,i + Dxeo), i. x1 oim (13) 2-13
i
}
, Where ng is the number of simultaneous vent releases (ground l level) ; nm in the number of simultaneous vent releases (mixed-mode) ; and (r) is the particular discharge pathway for which an l allocation factor is being determined.
l i
i L
~
. ~ rC .< , ,
~
.- l' .
8 l
Q
- TABLE 2.1-1 i e% 'l I
- w. 2' , . -
U w
- s l DOSE FACTORS FOR EXPOSURE TO'A SEMI-INFIH TE CLOUD OF NOBLS GAdES*
a -
l Gamma Beta , Gamma Beta L M
Nuclide -Body * * * ( X) -S k i n * * * ( T.) j,j r* * (M) -Air ** (N) '
Kr-83m 7.56E-02 1.9 3E+01 - 2.88EF02 % i Kr-85m ,
- 1.17Efd3 1.46E+03 1.23E+03 1.97E+03 i
l Kr-85 1.61E+01 1.34E+03 1.72E+01 1.95E+03 Kr-87 5.925+03 9.73E+03 6.17E+03 1.03c+04 '
,- , ff l ; ' a
! Kr-88 1.472+04 2.37E+03 1.52S+04 2.93E+03 Kr-89 '
1.66E+04 1.01E+04 1.'73E+%4 , 1.06E+0,4,
, Kr-90 1.56E+04 f. w ?.29E+03 1.63E+04 7 41E+03 ,[/
[ . - .
Xe-131m 9.15E+01 4.76E+02 1.56E+02 1.11E+03 -
- Xe-133m -
2.51E+02 9.94E+02 3.27E+02 1. 48):+0k l Xe-133 2.94E+02 3.06E+02 3.53E+02 1.05E+03' ,.
t l ,w ,
Xe-135m 3.12E+03 7. i1F.+ 02 3.36E+03 7.39E+b2 Xe-135 r 1.8lE+03 .,,
1.86E+03 1.92E+03 2.46E+03 Xe-137 -
1.42E+03
- 1.22E+04 1.51E+03 1.27E+04 Xe-138 8.83E+03 ,
4 .13 E,+ 9 3 9.21E+0$ '4.75E+03 ;
Ar-41 8.84E+03 .-
- 2. 69E* 01.* .
9.30E+03 ~L , 3.28E+03 L
[
\ [ .
v
- Values taken froel Refer,.ence 3,' Table B-1 ,
, /
/
- . i. . . . ,
- mrad-m 3 - c .;
. , ~
uCi-yr ,,
7 '
/
- mrem-m3, s uCi-yr . ., , ,
,**~.
e ', % I
% . o e g
, .t
- 2-15 ~
l ,
, a ., , , ,,
~
% *y
- i. _ _ _ _ _ _ _ _ _ . - ._- _ .-_-_-_-
_.--- id 2
i; I
i /' -
( TABLE 2.1-2 p
[ GASEOUS RELEASE POINTS FLOW RATES Release Point Flow Rates ft /3 min ml/see Plant. Vent (Unit 1) 1.5E05 7.08E07 Plant Vent (Unit 2) 9.0E04. 4.25E07
.Radwaste Solidification 3.4E04 1.60E07 Building Vent Turbine Building Vent 9.0E02 4.25EOS (Unit 1; Condenser Air Ejector and Steam Packing Exhaust)
Turbine Building Vent 9.0E02 4.25E05 (Unit 2; Condenser Air Ejector and Steam Packing Exhaust)
Reference 5,. Tables 11.5.2-1 and 11.5.5-1 0
2-16 1
l
V' t t
\.
.'/\ ,). '2.2 , GASEOUS EFFLUENT-DOSE RATE AND DOSE CALCULATIONS
~ ,s I I j 2 . 2. l~
Dose Rates at or beyond' Site Boundary -
~
'2.2.1.1 Dose Rates 'Due to Noble Gases s ,
For the purpose of implementing Technical Specification ,
3'.ll.2.1(a) , the dose rate in areas at or. beyond the site ;[l
' boundary due to noble gases shall be calculated as follows: ?,
ii 7
Dt = tot'al body dose rate at time of release >
- (mrem /yr)
Kg qg g +
\
- ng _ (X/Q) g , (X/Q)M b Oim I14) l .
Ds = skin, dose rate at time of release (mrem /yr), .
+
r
= 7 -(X/Q)g gg i JLi + 1. lM )g Qig +
nm (X/Q)M i l'i r + 1.1Mg) Qg, (15)\
Terms were defined previously in Subsection'2:.l.
~
The dose rate limits are site liyits at any point in time; therefore,) dose rates are summed over all gaseous releases occurring simultaneously.. For' Plant;Vogtle, Unit 1 turbine
- building vent,- Unit 2 turbine building vent, and radwaste solidification building vent are ground-level releases. Unit 1 plant vent and-Unit 2 plant vent are mixed-mode releases. o v,
H2.2.1.2 Dose Rates Due to I-131, I-133, Tritium, and Particulates ~p For the purpose of implementing Technical Specification 3.11.2.l(b), organ dose rates due to I-131, I-133, tritium and
-all radioactive materials-in particulate form with half lives
. greater . than eight . days, are required to be calculated for the
- /)
inhalation pathwa,y for.the child age group.
The child age group
% ,/ ' <
'l 2-17 *
., 4
'\ > '
'). 'j
,t
'a 5 ?
K, n
,o 9
/
-(j would experience the highest potential dose rate via the inhalation pathway. These dose rates are calculated as follows:
l Dg = organ dose rate at time of release (mrem /yr)
=
- ng (X/Q) G P gg O gg +
nm I !OI M P gg Q, g (16) where
= defined previously in subsection 2.1.1 (X/Q)G
= defined previously in subsection 2.1.2 (X/Q) M
=' . release rate (uCi/sec) of I-131, I-133, tritium Q{g and particulates from Unit 1 turbine building vent; Unit 2 turbine building vent; and radwaste solidification-building vent, which are ground-
' level releases.
01m
= release rate (uci/sec) of-I-131, I-133, tritium and particulates from Unit 1 plant vent and Unit-2 plant vent, which are mixed-mode releases.
P ig = organ dose parameter for organ o and radionuclide i, (mrem /yr per~uCi/m3 ) for inhalation determined
/y as follows:
- r ,,
P ig = K' (BR) DF ig (17)
- b. and where K' = constant of unit. conversion, 106 pCi/uCi SR = breathing' rate for child age group; 3700 m 3 /yr from Table 2.2-10
- v!
c> - 2-18 I
(,/ DFio = inhalation pathway dose factor for child age group for organ o and radionuclide i, from Table 2.2-2)
NOTE: In order to assure that potential dose rates (pre-release) to an organ due to I-131, I-133, tritium, and particulates in simultaneous gaseous releases from the' site do not exceed 1500 mrem /yr as specified in Technical Specification 3.ll.2.l(b) ,
the potential organ dose rate D g must be limited as'follows:
Dg $ (AG) (SF) 1500 mrem /yr (18) where AG *nd'SF are assigned the same values as were used in Subsection 2.1 for the gaseous discharge pathway under consideration. To further ensure that dose rate limits were not exceeded (post-release) , dose rates from simultaneous releases should be summed, as shown in equation (16) above.
2.2.2 Air Doses and Doses to a Member of the Public at or beyond the Site Boundary G
2.2.2.1 Air Doses at or beyond' the Site' Boundary For the purpose of implementing Technical Specification 3.11.2.2, air doses in areas.at.or beyond'the site boundary shall be determined as follows:
D gamma =- air dose due to gamma emissions from noble gas radionuclides (mrad)
~ P
= 3.17 x 10
-8 [ ~
+1, (X/0)M $I Mi Qi , (19) g(X/Q)G i i Q ig h.
g,/ -
2-19
40
- u where 3.17 x 10-8 = the fraction of one year per one second Q ig = cumulative release of noble gas radionuclide i over the period-of interest (uCi) from the vent release (ground-level) under consideration.
= cumulative release of noble gas.radionuclide Og, i over the period of in'terest (uCi) from the vent release (mixed-mode) - under consideration.
Mi =~ defined previously in Subsection 2.1.1 (X/0)g = defined previously in Subsection 2.1.1
= defined previously in Subsection 2.1.2 (X/Q) M -
~
D beta~
= air dose due to beta emissions-from noble gas radionuclides (mrad). ,
-8
= 3.17-x 10 Ixj0I G N h gg i
+
(X/Q)M' i- im (20)
.where.
N.
i
= air dose' factor due to beta emissions from noble gas ~radionuclide 1.(mrad /yr per
. uCi/m3 ) , from Table 2.1-1.
O 2-20
i ss ,)_ 2.2.2.2 Dose to a Member of the Public at or beyond the Site Boundary Doses to a member of the public due to I-131, I-133, tritium, and radioactive materials in particulate form, in gaseous releases, will be calculated for the purpose of implementing Technical Specification 3.11.2.3 as follows:
(NOTE: The member of the public expected to receive the highest dose'in the plant vicinity.is referred to as the controlling (or critical) . receptor. The dose received depends on the location, age-group, and exposure pathways present. For Plant Vogtle, the controlling receptor (s) for which doses must be calculated, and the-applicable exposure pathway =, are prcsonted in Table 2.2-12.)
= ' dose to an organ j of an individual in age-Dj i group a from radiciodines, tritium, and
-radionuclides in particulate-form'with half-lives greater than eight days (mrem).
= 3.17 X 10
-8 [ ~
+ Wgp
~
Qg ,) (21) pg R,g 3 (Wfp Q{
where 3.17 x 10-8 = fraction of one year per one second.
W6p = pathway-dependent' relative dispersion or deposition at.the location of the controlling receptor, associated with ground-level plant releases as-follows:
(X/Q')GP
= annual average relative dispersion parameter for location of controlling (critical) r.eceptor for ground-level plant releases.
(X/Q ' ) gp . applies only to inhalation and all-
%)
2-21
T ,/ the Q{ source term is limited to tritium.)
See Table 2.2-12 for value.
(D/Q')gp = annual average deposition parameter for the
~
location of controlling (critical) receptor for ground-level vent releases.
(D/Q')GP applies to all other pathways. See Table
~2.2-12 for value.
WAp = pathway-dependent relative dispersion or deposition at the location of the controlling receptor, associated with plant vent releases, which are mixed-mode as follows:
= annual average relative. dispersion parameter (X/Q')MP for location of controlling (critical) receptor for mixed mode releases. (X/Q')gp applies only to inhalation and all tritium pathways. (For all tritium pathways, the 01 source term is limited to tritium.) See Table 2.2-12 for values.
= . annual average deposition parameter for the
' (D/Q ' ) MP location of controlling (critical) receptor for mixed mode releases. (D/Q' ) MP -applies to all other pathways. .See Table 2.2-12 for values.
The selection of the dispersion or deposition parameter, X/O or D/Q, is dependent upon the pathway being considered. The dispersion parameter, X/0, is required for the inhalation pathway and the tritium contribution to ingestion pathways since tritium is taken up by vegetation directly from the surrounding air. The deposition parameter, D/Q, is required for the ground-plane pathway and I-131, I-133 and particulate
/~'\- contributions to ingestion pathways.
2-22
1 j'"'s
- i I '
\~s' - I
=
Olg cumulative release (uCi) , from ground-level plant releases, of radionuclide i as required by Technical Specification 3.11~.~2.3 over the period of' interest. Dose determinations required by Technical Specification 3.11.2.3 are on a per reactor basis; therefore, cumulative release quantities must also be unit-specific. Since the radwaste solidification building serves both' units, release quantities must be apportioned between the two units. In absence of evidence that one unit contributes a greater quantity of radioactivity than the other over
-the' period of interest release quantities may be apportioned equally between the two units. (For dose contributions due to tritium from the ingestion pathways, the Olg term is limited to tritium.)
= cumulative release (uCi), from the mixed-mode Olm plant vent releases, of radionuclide i as required by Technical Specification 3.11.2.3 over the period of interest. Dose determinations required by Technical Specification 3.11.2.3 are on a per reactor basis;'therefore, cumulative release quantities must also be unit-specific. (For dose' contributions due to tritium from the
-ingestion pathways, the term Olm is limited to tritium.)
'R aipj = pathway-specific, individual age-specific, organ. dose' factor for radionuclide i, pathway p, organ j, and individual age group, a.
[}
%../ .
Routine individual dose calculations address 2-23
' fD k,) the inhalation, ground-plane, grass-cow-milk, grass-goat-milk, grass-cow-meat, and garden vegetation pathways. However, the dose pathways actually present at the controlling location, as well as the controlling individual age group, are determined through the Land Use Census for the site vicinity-and are presented in Table 2.2-12. Pathway factors Ralpj are determined as shown in the following Subsections.
Plant Vogtle site-specific values, or appropriate default values, required in the pathway factor determinations are presented in Table 2.2-13.
Inhalation Pathway Factor R alpj = 3 K' (BR) a (DFA i j) a mrem /yr per uCi/m (22) where K' = constant of unit conversion 106 pCi/uCi
= the breathing rate for a particular age group (BR) a in m3 / year from Table 2.2-10.
= the inhalation dose factor for receptor age DFAi ja group a, organ j, and for radionuclide i, in mrem /pCi from Tables 2.2-1 through 2.2-4.
Ground-Plane Pathway Factor R alpj = K'K" t (SF' ) (DFGi3) ((1-e i )77 i)
(m2 mrem / year per uCi/sec) (23)
K' = constant of unit conversion, 10 6 pCi/uCi.
2-24
3 r
[
\J' K" =
constant of unit conversion, 8760 hr/yr.
SF' = shielding f actor, 0.7 (dimensionless)
= ground-plane dose conversion factor for DFGi j radionuclide 1 (same for all age groups and specific organs are assumed to receive the same dose as the total body) (mrem /hr per pCi/m 2 ) Table 2.2-9.
Ai = decay constant for radionuclide i, in see -1 t = exposure time, 4.73 x 10 8 sec (15 years) . -
Vegetation Pathway Factor R
aipj " Y y( I ij } a I al 1* + f e i hv) (24)
Ai +Ag) as. g (m2 mrem / year per uCi/m3) where
'K' = a constant'of unit conversion, 106 pCi/uci.
~
r = fraction of deposited activity retained on vegetation. (1.0 for radiciodines; 0.2 for particulates.)
U al =
the consumption rate of fresh leafy vegetation by the receptor in age group a, in kg/ year. (See Table 2.2-10)
U as = the consumption rate of stored vegetation by the receptor in age group a, in kg/ year.
.O (See Table 2.2-10)
N 2-25
\
b(%.
f i
=
the fraction of the annual intake of fresh leafy vegetation grown locally.
f g
=
the fraction of the annual intake of stored vegetation grown locally.
t1 =
the average time between harvest of leafy vegetation and its consumption in seconds. '(8.6 x 104) t hy = the average time between harvest of stored vegetation and its consumption in seconds.
(5.18 x 106)
Yy =
the vegetation areal density, in kg/m 2,
= the organ ingestion dose factor for the ith (DFLij) a _
radionuclide for the receptor in age group a, in mrem /pCi from Tables 2.2-5'through 2.2-8.
Ai = the decay constant for the ith radionuclide,
~
in sec -1 A, = the decay constant for removal of activity on
' leaf and plant surfaces by weathering, 5.73 x 10-7 sec -l'(corresponding to a 14 day half-life).
For tritium in vegetation, the vegetation pathway
' factor _is a special case due to the fact that the concentration of. tritium in vegetation is based on airborne concentration rather than deposition:
R aipj =
K'K"{(U al fl + Uasg)f (DFL j)i a (0. 75 (0. 5/H) )
(mrem /yr per uCi/m ) (25) v 2-26
' \~ -: ,
where '
K'"- = a constant of unit ccaversion, 103 gm/kg. ,
, H- =
absolute humidity of the atmosphere, in gm/m3 , ,
.0.75 = the fraction of total vegetation that is water.
0.5 =
the ratio of the specific activity of the
, vegetation water to the atmospheric water.
and other paramete'rs and values are given above.
Grass-Cow-Milk Pathway Factor p 'f p f (1-fp f )e -A ti hm"
.R,gp 3 = K'3O,7 (U,p) F,(r) (DFL gg),. y +
Y e if (26)
- p. s .
i (m2 mrem /yr per uCi/sec)- !
~
where K' =- a constant of unit conversion, 106 pCi/uci.
. Qp =
.the cow's consumption rate, in kg/ day (wet weight) .
U,p =
the receptor's milk consumption rate-for age group a, in liters /yr from Table 2.2-10.
t Yp =
the agricultural. productivity by unit area of pasture feed grass, in kg/m 2, ;
2-27
s G. Ys = the agricultural productivity by unit area of stored feed, in kg/m 2, F, = the stable element transfer coefficients, in days / liter. (See Table 2.2-11.)
r = fraction of deposited activity retained on feed grass. (1.0 for radiciodines; 0.2 for particulates)
=
(DFLi j) a the organ ingestion dose factor for the ith radionuclide for the receptor in age group a, in mrem /pci from Tables 2.2-5 through 2.2-8.
'A i = the decay constant for the ith radionuclide,
-in sec-1
=
Sw the decay constant for removal of activity on leaf and plant surfaces by weathering, 5.73 x 10-7 sec -1 (corresponding to a 14 day half-life).
tg = the transport time from pasture to cow, to milk,-to receptor, in sec. (1.73 x 10 5),
= the. transport time from pasture, to harvest, thm to cow, to milk, to receptor, in sec. (7.78 x 10 6),
f =- fraction of the year that the cow is on p
pasture (dimensionless) .
f s
= fraction of the cow feed tliat is pasture grass while the cow is on pasture (dimensionless). l
.!q 2-28 1
i
' f3 For tritium in milk, the grass-cow-milk pathway factor is a special case due to the fact that the concentration of tritium in milk is based on airborne concentration rather than deposition:
R aipj = U ,p (DFLi j ) a (0.75 (0.5/H) )
K ' K ' "F,Op (mrem /yr per uCi/m 3) (27) where-K'" = a constant of unit conversion, 10 3 gm/kg.
H = . absolute humidity of the atmosphere, in gm/m3 ,
0.75 = -the fraction of total feed that is water.
0.5 = the ratio of the specific activity of the feed grass water to the atmosoheric water.
and other parameters and values as previously defined.
Grass-Goat-Milk Pathway Factor
~
p R,gp 3 = K'7O([U
)
F w ,(r) (DFUg3),
~ff*+
y (1-f(f,)e k hm"e ik.(28) i p g (m2 mrem /yr per uCi/sec) where K' = a constant of unit conversion, 10 6 pCi/uci.
.Op -= the goat's consumption rate, in kg/ day (wet weight) .
O 2-29
p.
.( U ap = the receptor's milk consumption rate for age group a, in liters /yr from Table 2.2-10.
Y = the agricultural' productivity by unit area of p
pasture feed grass, in kg/m 2, Ys = the agricultural productivity by unit area of stored feed, in kg/m 2, F, = tht stable element transfer coefficients, in days / liter. (See Table 2.2-11.)
r = fraction of deposited activity retained on feed grass. (1.0 for radiciodines; 0.2 for particulates)
= the organ ingestion dose factor for the ith (DFLi j) a radionuclide for the receptor in age group a, in mrem /pCi from Tables 2.2-5 through 2.2-8.
Ei = the decay constant for the ith radionuclide, in sec-1
'A , = .the decay constant for removal of activity on leaf and plant surfaces by weathering, 5.73'x 10-7 sec -1 (corresponding to a 14 day half-life).
tg = the transport time from pasture to goat, to milk, to receptor, in sec. (1.73 x 10 5) t hm = the transport time from pasture, to harvest, to goat, to milk, to receptor, in sec. (7.78 x 106) l 2-30
i I
-em g l f p
= fraction of the year that the goat is on pasture (dimensionless) .
f = fraction of the goat feed that is pasture s
~
grass while the goat is on pasture (dimensionless).
For tritium in milk,'the grass-goat-milk pathway factor is a special case-due to the fact that the concentration of tritium in milk is based on airborne concentration rather than desposition:
R aipj =
K'K' "F,Qp Uap (DFLij ) a (0.75 (0.5/H) )
(mrem /yr per uCi/m3) (29) where:
a constant of unit conversion, 10 3 gm/kg.
~
K'" =
H = absolute humidity of the atmosphere, in gm/m3 .
0.75 = the fraction of total feed that is water.
0.5 = the ratio of the specific activity of the feed grass water to the.. atmospheric water.
and other parameters and values are given above.
Grass-Cow-Meat-Pathway-Factor -
~ff 8 -A i D hm" p (1-f f s )e R,gp 3 = K'7O+ (0,{)Ff (r) (DFLg3), y + y ,- A tff (30)
(m2 mrem /yr per uCi/sec)
O v
31
--.- where
( ')
\d K' = a constant of unit conversion, 106 pCi/uC1.
Op =
the cow's consumption rate, in kg/ day (wet weight) .
U ap =
the receptor's meat consumption rate for age group a, in kg/yr from Table 2.2-10.
y =
the agricultural productivity by unit area of p
pasture feed grass, in kg/m 2, Ys =
the agricultural productivity by unit area of stored feed, in kg/m 2,
=
Fg The stable element transfer coefficients, in days /kg. (see Table 2.2-11.)
l r = fraction of deposited activity retained on feed grass. (1.0 for radiciodines; 0.2 for particulates)
(DFLi j) a = the organ ingestion dose factor for the ith radionuclide for the receptor in. age group a, in mrem /pci from Tables 2.2-5 through 2.2-8.
=
7(i the decay constant for the ith radionuclide, in sea-l.
Ay = the decay constant for removal of activity on leaf and plant surfaces by weathering, 5.73 x 10-7 sec -1 (corresponding to a 14 day half-life).
tg = the transport time from pasture to cow, to
(~'y- meat, to receptor, in sec. (1.73 x 10 6)
LJ l
2-32
-- (
t = the transport time from pasture, to harvest, hm to cow, to meat, to receptor, in rec. (7.78 x 106 )
f = fraction of the year that the cow'is on p
pasture (dimensionless) .
f = fraction of the cow feed that is pasture s
grass while the cow is on pasture (dimensionless).
For tritium in meat, the grass-cow-meat pathway factor is a special case due to the fact that the concentration of tritium in meat is based on airborne concentration rather than deposition:
R alpj =
K' K'"FgQpUap (DFLi j) a (0.75 (0.5/H) )
(mrem /yr per uCi/m 3) (31) where
~
K'." = a constant of unit conversion, 10 3 gm/kg.
H = absolute humidity of the atmosphere, in gm/m3 ,
0.75 = the fraction of total feed that is water.
0.5 = the ratio of the specific activity of the feed grass water to the atmospheric water.
and other parameters and values are given above.
O 2-33
( ) 2.2.2.3 Dose Calculations to Support Other Technical' Specifications In the event radiological impact assessment becomes necessary to support Technical Specification 6.6.1, which pertains to reportable events, dose calculations may be performed using the equations in Subsection 2.2.2.2 with the substitution of average meteorological (dispersion and deposition) parameters for the period covered by the report, and the appropriate pathway dose factors (Raipj) for the receptor of interest.
For the purpose of supporting Technical Specification 3.12.2, which pertains to the Annual Land Use Survey, it may become necessary to perform dose calculations in addition to those required by Technical Specifications 3.11.2.3. In the event that the Land use Survey reveals that exposure pathways have changed at previously identified locations, or if new locations are identified, it may become necessary to perform dose calculations at two or more locations to either confirm the previously identified controlling receptor or identify the new receptor which should be designated as the controlling receptor. The necessary dose calculations may be performed using the equations presented in Subsection 2.2.2.2 substituting the appropriate pathway dose factors (Ralpj) and the appropriate meteorological (dispersion and deposition) parameters for the receptor (s) and location (s) of interest. Annual average meteorological paramaters may be used for these calculations.
Potential receptors are presented in Table 2.2-14; the associated dispersion and deposition parameters are shown in Table 2.2-15. Information contained in these two tables may be useful in performing dose calculations to support. Technical Specifications 6.6.1 or 3.12.2.
O 2-34 L
TABLE 2.2-1
<^x INHALATION DOSE FACTORS FOR INFANT *
(MREM PER PCI INHALED)
Page 1 of 3 Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI H-3 No Data 4.62E-07 4.62E-07 4.62F:-07 4.62E-07 4.62E-07 4.62E-07 C-14 1.89E-05 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 Na-24 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 P-32 1.45E-03 '8.03E-05 5.53E-05 No Data No Data No Data 1.15E-05 Cr-51 No Data No Data 6.39E-08 4.llE-08 9.45E-09 9.17E-06 2.55E-07 Mn-54 No Data 1.81E-05 3.56E-06 No Data 3.56E-06 7.14E-04 5.04E-06 Mn-56 No Data 1.10E-09 1.58E-10 No Data 7.86E-10 8.95E-06 5.12E-05 Fe-55 1.41E-05 8.39E-06 2.38E-06 No Data No Data 6.21E-05 7.82E-07 Fe-59 9.69E-06 1.68E-05 6.77E-06 No Data No Data 7.25E-04 1.77E-05 Co-58 No Data 8.71E-07 1.30E-06 No Data No Data 5.55E-04 7.95E-06 Co-60 No Data 5.73E-06 8.41E-06 No Data No Data 3.22E-03 2.28E-05 Ni-63 2.42E-04 1.46E-05 8.29E-06 No Data No Data 1.49E-04 1.73E-06 Ni-65 1.71E-09 2.03E-10 8.79E-ll No Data No Data 5.80E-06 3.58E-05 Cu-64 No Data 1.34E-09 5.53E-10 No Data 2.84E-09 6.64E-06 1.07E-05 Zn-65 1.38E-05 4.47E-05 2.22E-05 No Data 2.32E-05 4.62E-04 3.67E-05 Zn-69 3.85E-ll 6.91E-11 5.13E-12 No Data 2.87E-11 1.05E-06 9.44E-06 Br-83 No Data No Data 2.72E-07 No Data No Data No Data LT E-24 Br-94 No Data No Data 2.86E-07 No Data No Data No Data LT E-24 Br-85 No Data No Data 1.46E-08 No Data No Data No Data LT E-2.4 Rb-86 No Data 1.36E-04 6.30E-05 No Data No Data No Data 2.17E-06 Rb-88 No Data '3.98E-07 2.05E-07 No Data No Data No Data 2.42E-07 Rb-89 No Data 2.29E-07 1.47E-07 No Data No Data No Data 4.87E-08 Sr-89 2.84E-04 No Data 8.15E-06 No Data No Data 1.45E-03 4.57E-05 Sr-90 2.92E-02 No Data 1.85E-03 No Data No Data 8.03E-03 9.36E-05 Sr-91 6.83E-08 No Data 2.47E-09 No Data No Data 3.76E-05 5.24E-05 Sr-92 7.50E-09 No Data 2.79E-10 No Data No Data 1.70E-05 1.00E-04 Y-90 2.35E-06 No Data 6.30E-08 No Data No Data 1.923-04 7.43E-05 Y-91M 2.91E-10 No Data 9.90E-12 No Data No Data 1.99E-06 1.68E-06 Y-91 4.20E-04 No Data 1.12E-05 No Data No Data 1.75E-03 5.02E-05 Y-92 1.17E-08 No Data 3.29E-10 No Data No Data 1.75E-05 9.04E-05 g^ Reference 3, Table E-10.
2-35
l TABLE 2.2-1 CONT'D I -'
- INHALATION DOSE FACTORS FOR INFANT
- N-e
(.MREM PER PCI INHALED)
PAGE 2 of 3 Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI Y-93 1.07E-07 No Data 2.91E-09 No Data No Data 5.46E-05 1.19E-04 Zr-95 8.24E-05 1.99E-05 1.45E-05 No Data 2.22E-05 1.25E-03 1.55E-05 Zr-97 1.07E-07 1.83E-08 8.36E-09 No Data 1.85E-08 7.88E-05 1.00E-04 Nb-95. 1.12E-05 4.59E-06 2.70E-06 No Data 3.37E-06 3.42E-04 9.05E-06 Mo-99 No Data 1.18E-07 2.31E-08 No Data 1.89E-07 9.63E-05 3.48E-05 Tc-99M 9.98E-13 2.06E-12 2.66E-ll No Data 2.22E-ll 5.79E-07 1.45E-06 Tc-101 4.65E-14 5.88E-14 5.80E-13 No Data 6.99E-13 4.17E-07 6.03E-07 Ru-103 1.44E-06 No Data 4.85E-07 No Data 3.03E-06 3.94E-04 1.15E-05 Ru-105 8.74E-10 No Data 2.93E-10 No Data 6.42E-10 1.12E-05 3.46E-05 Ru-106 6.20E-05 No Data- 7.77E-06 No Data 7.61E-05 8.26E-03 1.17E-04 Ag-110M 7.13E-06 5.16E-06 3.57E-06 No Data 7.80E-06 2.62E-03 2.36E-05 Te-125M 3.40E-06 1.42E-06 4.70E-07 1.16E-06 No Data 3.19E-04 9.22E-06 Te-127M 1.19E-05 4.93E-06 1.48E-06 3.48E-06 2.68E-05 9.37E-04 1.95E-05 Te-127 1.59E-09 6.81E-10 3.49E-10 1.32E-09 3.47E-09 7.39E-06 1.74E-05 Te-129M 1.01E-05 4.35E-06 1.59E-06 3.91E-06 2.27E-05 1.20E-03 4.93E-05 Te-129 5.63E-ll 2.48E-11 1.'34E-11 4.82E-ll 1.25E-10 2.14E-06 1.88E-05 Te-131M 7.62E-08 3.93E-08 2.59E-08 6.38E-08 1.89E-07 1.42E-04 8.51E-05 Te-131 1.24E-11 5.87E-12' 3.57E-12 1.13E-ll 2.85E-ll 1.47E-06 5.87E-06 Te-132 2.66E-07 1.69E-07 1.26E-07 1.99E-07 7.39E-07 2.43E-04 3.15E-05 I-130 4.54E-06 9.91E-06 3.98E-06 1.14E-03 1.09E-05 No Data 1.42E-06 I-131 2.71E-05 3.17E-05 1.40E-05 1.06E-02 3.70E-05 No Data 7.56E-07 I-132 1.21E-06 2.53E-06 8.99E-07 1.21E-04 2.82E-06 No Data 1.36E-06 I-133 9.46E-06 l.'37E-05 4.00E-06 2.54E-03 1.60E-05 No Data 1.54E-06 I-134 6.58E-07 1.34E-06 4.75E-07 3.18E-05 1.49E-06 No Data 9.21E-07 I-135 2.76E-06 5.43E-06 1.98E-06 4.97E-04 6.05E-06 No Data 1.31E-06 CC-134 2.83E-04 5.02E-04 5.32E-05 No Data 1.36E-04 5.69E-05 9.53E-07 Cs-136 3.45E-05 9.61E-05 3.78E-05 No Data 4.03E-05 8.40E-06 1.02E-06
~
Cc-137 3.92E-04 4.37E-04 3.25E-05 No Data 1.23E-04 5.09E-05 9.53E-07 Cc-138 3.61E-07 5.58E-07 2.84E-07 No Data 2.93E-07 4.67E-08 6.26E-07 BC-139 1.06E-09 7.03E-13 3.07E-ll No Data 4.23E-13 4.25E-06 3.64E-05 Bc-140 4.00E-05 4.00E-08 2.07E-06 No Data 9.59E-09 1.14E-03 2.74E-05 BC-141 1.12E-10 7.70E-14 3.55E-12 No Data 4.64E-14 2.12E-06 3.39E-06 BO-142 2.84E-11 2.36E-14 1.40E-12 No Data 1.36E-14 1.llE-06 4.95E-07 7 Jo-140 g 3.61E-07 1.43E-07 3.68E-08 No Data No Data 1.20E-04 6.06E-05 2-36
TABLE 2.2-1 CONT'D
,N INHALATION DOSE FACTORS FOR INFANT *
(MREM PER PCI INHALED)
Page 3 of 3 Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI La-142 7.36E-10 2.69E-10 6.46E-ll No Data No Data 5.87E-06 4.25E-05 Ce-141 1.98E-05 1.19E-05 1.42E-06 No Data 3.75E-06 3.69E-04 1.54E-05 ce-143 2.09.E-07 1.38E-07 1.58E-08 No Data 4.03E-08 8.30E-05 3.55E-05 Ce-144 2.28E-03 8.65E-04 1.26E-04 No Data 3.84E-04 7.03E-03 1.06E-04 Pr-143 1.00E-05 3.74E-06 4.99E-07 No Data 1.41E-06 3.09E-04 2.66E-05 Pr-144~ 3.42E-11 1.32E-11 1.72E-12 No Data 4.80E-12 1.15E-06 3.06E-06 Nd-147 5.67E-06 5.81E-06 3.57E-07 No Data 2.25E-06 2.30E-04 2.23E-05 W-187 9.26E-09 6.44E-09 2.23E-09 No Data No Data 2.83E-05 2.54E-05 Np-239 2.65E-07 2.37E-08 1.34E-08 No Data 4.73E-08 4.25E-05 1.78E-05 G'
2-37
r-I TABLE 2.2-2
/~' INHALATION DOSE FACTORS FOR CHILD *
-t (MREM PER PCI INHALED)
I Page 1 of 3 Nuclide' Bone Liver T Body Thyroid Kidnev Lung ~GI-LLI
'H-3 No Data 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 C-14 9.70E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 Na-24 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 P-32 7.04E-04 3.09E-05 2.67E-05 No Data No Data No Data 1.14E-05 Cr-51 No Data No. Data 4.17E-08 2.31E-08 6.57E-09 4.59E-06 2.93E-07.
Mn-54 No Data 1.16E-05 2.57E-06 No Data 2.71E-06 4.26E-04 6.19E-06 Mn-56 No Data 4.48E-10 8.43E-ll No Data 4.52E-10 3.55E-06 3.33E-05 Fe-55 1.28E-05 6.80E-06 2.10E-06 No Data No Data 3.00E-05 7.75E-07 Fe-59 5.59E-06 9.04E-06' 4.51E-06 No Data No Data 3.43E-04 1.91E-05 Co-58 No Data 4.79E-07 8.55E-07 No Data No Data 2.99E-04 9.29E-06 Co-60 No Data 3.55E-06 6.12E-06 No Data No Data 1.91E-03 2.60E-05 Ni-63 2.22E-04 1.25E-05 7.56E-06 No Data No Data 7.43E-05 1.71E-06 Ni-65 8.08E-10 7.99E-11 4.44E-ll' No 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 Zn-65 1.15E-05 3.06E-05 1.90E-05 No Data 1.93E-05 2.69E-04 4.41E-06 Zn-69 1.81E-ll 2.61E-ll 2.41E-12 No Data 1.58E-ll 3.84E-07 2.75E-06 Br-83 No Data No Data 1.28E-07 No Data No Data No Data LT E-24 Br-84 No Data No Data 1.48E-07 No Data No Data' No Data LT E-24 Br-85 No Data No Data 6.84E-09 No Data No Data No Data LT E-24 Rb-86 No Data 5.36E-05 3.09E-05 No Data No Data No Data 2.16E-06 Rb-88 No Data 1.52E-07. 9.90E-08 No Data No Data No Data 4.66E-09 Rb-89 No Data 9.33E-08 7.83E-08 No Data No Data No Data 5.llE-10 Sr-89 1.62E-04 No Data 4.66E-06 No Data No Data 5.83E-04 4.52E-05 Sr-90 2.73E-02 No Data 1.74E-03 No Data No Data 3.99E-03 9.28E-05 Sr-91 3.28E-08 No Data 1.24E-09 No Data No Data 1.44E-05 4.70E-05 Sr-92 3.54E-09 No Data 1.42E-10 No Data No Data 6 '. 4 9E-06 6.55E-05 Y-90 1.llE-06 No Data 2.99E-08 No Data No Data 7.07E-05 7.24E-05 Y-91M 1.37E-10 No Data 4.98E-12 No Data- No Data 7.60E-07 4.64E-07 Y-91 2.47E-04' No Data- 6.59E-06 No Data No Data 7.10E-04 4.97E-05 Y-92 5.50E-09 No Data 1.57E-10 No Data No Data 6.46E-06 6.46E-05 7-~* Reference 3, Table'E-9.
2-38
~
TABLE 2.2-2 CONT'D 7 ') INHALATION DOSE FACTORS FOR CHILD *
'~
(MREM PER PCI INHALED)
Page 2 of 3 Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI Y-93 5.04E-08 No Data 1.38E-09 No Data No Data 2.01E-05 1.05E-04 Zr-95 5.13E-05 1.13E-05 1.00E-05 No Data 1.61E-05 6.03E-04 1.65E-05 Zr-97 5.07E-08 7.34E-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-06 No Data 2.33E-06 1.66E-04 1.00E-05 Mo-99 No Data 4.66E-08 1.15E-08 No Data 1.06E-07 3.66E-05 3.42E-05 Tc-99M 4.81E-13 9.41E-13 1.56E-ll No Data 1.37E-11 2.57E-07 1.30E-06 Tc-101 2.19E-14 2.30E-14 2.91E-13 No Data 3.92E-13 1.58E-07 4.41E-09 Ru-103 7.55E-07 No Data 2.90E-07 No Data 1.90E-06 1.79E-04 1.21E-05 Ru-105 4.13E-10 No Data 1.50E-10 No Data 3.63E-10 4.30E-06 2.69E-05 Ru-106. 3.68E-05 No Data 4.57E-06 No Data 4.97E-05 3.87E-03 1.16E-04 Ag-110M 4.56E-06 3.08E-06 2.47E-06 No Data 5.74E-06 1.48E-03 2.71E-05 Te-125M 1.82E-06 6.29E-07 '2.47E-07 5.20E-07 No Data 1.29E-04 9.13E-06 Te-127M 6.72E-06 2.31E-06 8.16E-07 1.64E-06 1.72E-05 4.00E-04 1.93E-05 Te-127. .7.49E-10 2.57E-10 1.65E-10 5.30E-10 1.91E-09 2.71E-06 1.52E-05 Te-129M 5.19E-06 1.85E-06 8.22E-07 1.71E-06 1.36E-05 4.76E-04 4.91E-05 Te-129 2.64E-ll 9.45E-12 6.44E-12 1.93E-ll 6.94E-ll 7.93E-07 6.89E-06 Te-131M 3.63E-08 1.60E-08 1.37E-08 2.64E-08 1.08E-07 5.56E-05 8.32E-05 Te-131 5.87E-12 2.28E-12 1.78E-12 4.59E-12 1.59E-ll 5.55E-07 3.60E-07 Te-132 1.30E-07 7.36E-08 7.12E-08 8.58E-08 4.79E-07 1.02E-04 3.72E-05 I-130 2.21E-06 4.43E-06 2.28E-06 4.99E-04 6.61E-06 No Data 1.38E-06 I-131 1.30E-05 1.30E-05 7.37E-06 4.39E-03 2.13E-05 No Data 7.68E-07 I-132 5.72E-07 'l.10E-06 5.07E-07 5.23E-05 1.69E-06 No Data 8.65E-07 I-133 4.48E-06 5.49E-06 2.08E-06 1.04E-03 9.13E-06 No Data 1.48E-06 I-134 3.17E-07 5.84E-07 2.69E-07 1.37E-05 8.92E-07 No Data 2.58E-07 I-135 1.33E-06 2.36E-06 1.12E-06 2.14E-04 3.62E-06 No Data 1.20E-06 Cs-134 1.76E-04 2.748-04 6.07E-05 No Data 8.93E-05 3.27E-05 1.04E-06 Cs-136 1.76E-05 4.62E-05 3.14E-05 No Data 2.58E-05 3.93E-06 1.13E-06 Cs-137 2.45E-04 2.23E-04 3.47E-05 No Data 7.63E-05 2.81E-05 9.78E-07 Cs-138 1.71E-07 2.27E-07 1.50E-07 No Data 1.68E-07 1.84E-08 7.29E-08 Ba-139 4.98E-10 2.66E-13 1.45E-ll No Data 2.33E-13 1.56E-06 1.56E-05 Ba-140 2.00E-05 1.75E-08 1.17E-06 No Data 5.71E-09 4.71E-04 2.75E-05 Ba-141 5.29E-ll 2.95E-14 'l.72E-12 No Data 2.56E-14 7.89E-07 7.44E-08 Ba-142 1.35E-ll 9.73E-15 7.54E-13 No Data 7.87E-15 4.44E-07 7.41E-10 a-140 1.74E-07 6.08E-08 2.04E-08 No Data No Data 4.94E-05 6.10E-05 2-39 u
TABLE 2.2-2 CONT'D 4 x INHALATION DOSE FACTORS FOR CHILD *
(MREM PER PCI INHALED)
Page 3 of 3 Nuclide Bone- Liver T Body Thyroid Kidney Lung GI-LLI La-142 3.50E-10 1.llE-10 3.49E-ll No Data No Data 2.35E-06 2.05E-05 Ce-141 1.06E-05 5.28E-06 7.83E-07 No Data 2.31E-06 1.47E-04 1.53E-05 Ce-143 9.89E-08 5.37E-08 7.77E-09 No Data 2.26E-08 3.12E-05 3.44E-05 Ce-144 1.83E-03 5.72E-04 9.77E-05 No Data 3.17E-04 3.23E-03 1.05E-04 Pr-143 4.99E-06 1.50E-06 2.47E-07 No Data 8.llE-07 1.17E-04 2.63E-05 Pr-144 1.61E-ll 4.99E-12 8.10E-13 No Data 2.64E-12 4.23E-07 5.32E-08 Nd-147 2.92E-06 2.36E-06 1.84E-07 No Data 1.30E-06 8.87E-05 2.22E-05 W-187 4.41E-09 2.61E-09 1.17E-09 No Data No Data 1.llE-05 2.46E-05 Np-239 1.26E-07 9.04E-09 6.35E-09 No Data 2.63E-08 1.57E-05 1.73E-05 s
e h
d i
P 2-40
I TABLE ~2.2-3 e INHALATION DOSE FACTORS FOR TEENAGER *
\
(MREM PER PCI INHALED)
Page l_of 3 Nuclid i Bone Liver T Body Thyroid Kidney Lung GI-LLI H-3 No Data 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 C-14 3.25E-06 6.09E-06 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 Na-24 1.72E-]6 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 P-32 2.36E-04 1.37E-05 8.95E-06 No Data No Data No Data 1.16E-05 Cr-51 No Data No Data 1.69E-08 9.37E-09 3.84E-09 2.62E-06 3.75E-07 Mn-54 No Data 6.39E-06 1.05E-06 No Data 1.59E-06 2.48E-04 8.35E-06 Mn-56 No Data 2.12E-10 3.15E-ll No Data 2.24E-10 1.90E-06 7.18E-06 Fe-55 4.18E-06 2.98E-06 6.93E-07 No Data No Data 1.55E-05 7.99E-07 Fe-59 1.99E-06 4.62E-06 1.79E-06 No Data No Data 1.91E-04 2.23E-05 Co-58 No Data 2.59E-07 3.478-07 No Data No Data 1.68E-04 1.19E-05 Co-60 No Data 1.89E-06 2.48E-06 No Data No Data 1.09E-03 3.24E-05 Ni-63 7.25E-05 5.43E-06 2.47E-06 No Data No Data 3.84E-05 1.77E-06 Ni-65 2.73E-10 3.66E-11 1.59E-ll No Data No Data 1.17E-06 4.59E-06 Cu-64 No Dars 2.54E-10 1.06E-10 No Data 8.01E-10 1.39E-06 7.68E-06 Zn-65 4.82E-06 1.67E-05 7.80E-06 No Data 1.08E-05 1.55E-04 5.83E-06 Zn-69 6.04E-12 1.lbE-ll 8.07E-13 No Data 7.53E-12 1.98E-07 3.56E-08 Br-83 No Data No Data 4.30E-08 No Data No Data No Data LT E-24 Br-84 No Data No Data 5.41E-08 !!o Data No Data No Data LT E-24 Br-85 No Data No Data 2.29E-09 No Data No Data No Data LT E-24 Rb-86 No Data 2.38E-05 1.05E-05 No Data No Data No Data 2.21E-06 Rb-88 No Data 6.82E-08 3.40E-08 No Data No Data No Data 3.65E-15 Rb-89 No Data 4.40E-08 2.91E-09 No Data No Data No Data 4.22E-17 Sr-89 5.43E-05 No Data 1.56E-06 No Data No Data 3.02E-04 4.64E-05 Sr-90 1.35E-02 No Data 8.35E-04 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-09 No Data 5.08E-ll No Data No Data 3.43E-06 1.49E-05 Y-90 3.73E-07 No Data 1.00E-08 No Data No Data 3.66E-05 6.99E-05
-Y-91M 4.63E-ll No Data 1.77E-12 No Data No Data 4.00E-07 3.77E-09 Y-91 8.26E-05 N'o Data 2.21E-06 No Data No Data 3.67E-04 5.llE-05 Y-92 1.84E-09 No Date 5.36E-11 No Data No Data 3.35E-06 2.06E-05
.} Reference 3, Table E-8 t
l Nd 2-41 L_
TABLE 2.2-3 CONT'D f^) INHALATION DOSE FACTORS FOR TEENAGER *
\"
(MREM PER PCI-INHALED)
Page 2 of 3 Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI 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 3.94E-06 No Data 8.42E-06 3.36E-04 1.86E-05 Zr-97 1.72E-08 3.40E-09 1.57E-09 No Data 5.15E-09 1.62E-05 7.88E-05
-Nb-95 2.32E-06 1.29E-06 7.08E-07 No Data 1.25E-06 9.39E-05 1.21E-05 Mo-99 No Data 2.llE-08 4.03E-09 No Data 5.14E-08 1.92E-05 3.36E-05 Tc-99M 1.73E-13 4.83E-13 6.24E-12 No Data 7.20E-12 1.44E-07 7.66E-07 Tc-101 7.40E-15 1.05E-14 1.03E-13 No Data 1.90E-13 8.34E-08 1.09E-16 Ru-103 2.63E-07 No Data 1.12E-07 No Data 9.29E-07 9.79E-05 1.36E-05 Ru-105 1.40E-10 No Data 5.42E-ll No Data 1.76E-10 2.27E-06 1.13E-05 Ru-106 1.23E-05 No Data 1.558-06 No Data 2.38E-05 2.01E-03 1.20E-04 Ag-110M 1.73E-06 1.64E-06 9.99E-07 No Data 3.13E-06 8.44E-04 3.41E-05 Te-125M 6.10E-07 2.80E-07 8.34E-08 1.75E-07 No Data 6.70E-05 9.38E-06 Te-127M 2.25E-06 1.02E-06 2.73E-07 5.48E-07 8.17E-06 2.07E-04 1.99E-05 Te-127 2.51E-10 1.14E-10 5.52E-ll 1.77E-10 9.10E-10 1.40E-06 1.01E-05 Te-129M 1.74E-06 8.23E-07 2.81E-07 5.72E-07 6.49E-06 2.47E-04 5.06E-05 Te-129 18.87E-12 4.22E-12 .2.20E-12 6.48E-12 3.32E-ll 4.12E-07 2.02E-07 Te-131M .l.23E-08 7.51E-09 5.03E-09 9.06E-09 5.49E-08 2.97E-05 7.76E-05 Te-131 1.97E-12 1.04E-12 6.30E-13' l.55E-12 7.72E-12 2.92E-07 1.89E-09 Te-132 4.50E-08 3.63E-08 2.74E-08 3.07E-08 2.44E-07 5.61E-05 5.79E-05 I-130 7.80E-07 2.24E-06 8.96E-07 1.86E-04. 3.44E-06 No Data 1.14E-06 I-131 4.43E-06 6.14E-06 3.30E-06 1.83E-03 1.05E-05 No Data 8 llE-07 I-132 1.99E-07 5.47E-07 1.97E-07 1.89E-05 8.65E-07 No Data 1.59E-07 I-133 1.52E-06 2.56E-06 7.78E-07 3.65E-04 4.49E-06 No Data 1.29E-06 I-134 1.llE-07 2.90E-07 1.05E-07 4.94E-06 4.58E-07 No Data 2.55E-09 I-135 4.62E-07 1.18E-06 4.36E-07 7.76E-05 1.86E-06 No Data 8.69E-07 Cs-134 6.28E-05 1.41E-04 6.86E-05 No Data 4.69E-05 1.83E-05 1.22E-06 Cs-136 6.44E-06 2.42E-05 1.71E-05 No Data 1.38E-05 2.22E-06 1.36E-06 Cs-137 8.38E-05 1.06E-04 3.89E-05 No Data ~ 3.80E-05 1.51E-05 1.06E-06 Cs-138 5.82E-08 1.07E-07 5.58E-08 No Data 8.28E-08 9.84E-09 3.38E-ll Ba-139 1.67E-10 1.18E-13 4.87E-12 No Data 1.llE-13 8.08E-07 8.06E-07 Ba-140 6.84E-06' 8.38E-09 4.40E-07 No Data 2.85E-09 2.54E-04 2.86E-05 Ba-141 1.78E-ll 1.32E-14 5.93E-13 No Data 1.23E-14 4.llE-07 9.33E-14 Ba-142 4.62E-12 4.63E-15 2.84E-13 No Data 3.92E-15 2.39E-07 5.99E-20 a-140 5.99E-08 2.95E-08 7.82E-09 No Data No Data 2.68E-05 6.09E-05 2-42
,t
'9'4 A '
f.
' m_ -
S
.c TABLE-2.2-3 CONT'D-- N'
~.. ,
'IAHALATION DOS'E FACTORS FOR TEENAGER
- N pd *
~. ~ . -
,.. - (MREM PER PCI.IN, HALED) f' y .x '-
Page 3 of 3 .
. .. ?. ~ r ,
Nuclide Bone Liver T Bo'dv 'Thyrhid ' / Kidney ._Lu'nq GI-LLI
'a-142 L 1.20E-10 5.31E-11 1.32E-ll - N$t Da't.t No Data 1.27E-06 1.50E-06 Ce-141- -3.55E-06 2.37E-06 2.71E-07 No' Data 1.llE-06 7.67E-05 1.58E-05 e .>
Ce-143- 3.32E-08 2.42E-08f,2.70E No;bata 1.08E-08 1.63E-05 3.19E-05 Ce-144- 6.llE-04 2.53E-04L.3.lBE-05 No, Data 1.51E-04 1.67E-03 1.08E-04 Pr-143 1.67E-06 6.64E f07 8.28E-08, No Data 3.86E-07 6.04E-05 -2.67E-05 Pr-144 5.37E-12 2 . 2 0E'-12 ' 2.725-13 No Data 1.26E-12 2.19E-07 -2.94E-14 Nd-147 9.83E-07 1.07E 6.41E-08 No Data 6.28E-07 4.65E-05 2.28E-05
- W-187 1.50E-09 1.'22E-09 4.29E-10 No Data No Data 5.92E-06 2.21E-05 Np-239 4.23E-08 3.99E-09 2.21E-09 No, Data 1.25E-08 8.llE-06 1.65E-05 t:m
?
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TABLE 2.2-4 INHALATION DOSE FACTORS FOR ADULTS *
\#
(MREM PER PCI INHALED)
Page 1 of 3 Nuylide Bone Liver T Body Thyroid Kidney Lung GI-LLI H-3 No Data 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 C-14 2.27E-06 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 Na-24 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 P-32 1.65E-04 9.64E-06 6.26E-06 No Data No Data No Data 1.08E-05 Cr-51 No Data No Data 1.25E-08 -7.44E-09 2.85E-09 1,80E-06 4.15E-07 Mn-54 No Data 4.95E-06 7.87E-07 No Data 1.23E-06 1.75E-04 9.67E-06 Mn-56 No Data 1.55E-10 2.29E-ll No Data 1.63E-10 1.18E-06 2.53E-06 Fe-55 3.07E-06 2.12E-06 4.93E-07 No Data No Data 9.01E-06 7.54E-07 Fe-59 1.47E-06 3.47E-06 1.32E-06 No Data No Data 1.27E-04 2.35E-05 Co-50 No Data 1.98E-07 2.59E-07 No Data No Data 1.16E-04 1.33E-05 Co-60 No Data 1.44E-06 1.85E-06 No Data No Data 7.46E-04 3.56E-05 Ni-63 5.40E-05 3.93E-06 1.81E-06 No-Data No Data 2.23E-05 1.67E-06 Ni-65 1.92E-10 2.62E-ll 1.14E-11 No Data No Data 7.00E-07 1.54E-06 Cu-64 No Data 1.83E-10 7.69E-ll No Data 5.78E-10 8.48E-07 6.12E-06 Zn-65 4.05E-06 1.29E-05 5.82E-06 No Data 8.62E-06 1.08E-04 6.68E-06 Zn-69 4.23E-12 8.14E-12 5.65E-13 No Data 5.27E-12 1.15E-07 2.04E-09 Br-83 No Data No Data 3.01E-08 No Data No Data No Data 2.90E-08 Br-84 No Data No Data 3.91E-08 No Data No Data No Data 2.05E-13 Br-85 No Data No Data 1.60E-09 No Data No Data No Data LT E-24 Rb-86 No Data 1.69E-05 7.37E-06 No Data No Data No Data 2.08E-06 Rb-88 No Data 4.84E-08 2.41E-08 No Data No Data No Data 4.18E-19 Rb-89 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 7.62E-04 No Data No 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-ll No Data No Data 2.06E-06 5.38E-06 Y-90 2.61E-07 No Data 7.01E-09 No Data No Data 2.12E-05 6.32E-05 Y-91M 3.26E-ll No Data 1.27E-12 No Data No Data 2.40E-07 1.66E-10 Y-91 5.78E-05 No Data 1.55E-06 No Data No Data 2.13E-04 4.81E-05 Y-92 1.29E-09 No Data 3.77E-ll No Data No Data 1.96E-06 9.19E-06
,- f Reference 3, Table E-7.
]
2-44
~
' j TABLE 2.2-4 CONT'D
.fw. INHALATION DOSE FACTORS FOR ADULTS
- l
>' (MREM PER PCI INHALED)
Page 2 of 3 7 Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI Y-93 1.18E-08 No Data 3.26E-10 No Data No Data 6.06E-06 5.27E-05
~Zr-95 1.34E-05 4.30E-06 2.91E-06 No Data 6.77E-06 2.21E-04 1.88E-05 Zr-97 1.21E-08 2.45E-09 1.13E-09 No Data 'J.71E-09 9.84E-06 6.54E-05 t,
Nb-95 1.76E-06 9.77E-07 ,5.26E-07 No Data Nk67E-07 6'. 31E-0 5 1.3DE-05 Mo-99 No Data 1.51E-08 2.87E-09 No Data 3.64E-08 1.14E-05 3.10E-05 3 Tc-99M 1.29E-13 3.64E-13 4.63E-12 No Data 5.52E-12 9.55E-08 5.20E-07 Tc-101 5.22E-15 7.52E-15 7.38E-14 No Data 1.35E-13 4.99E-08 1.36E-21 Ru-103 1.91E-07 No Data 8.23E-08 No Data 7.29E-07 6.31E-05 1.38E-05 Ru-105 9.88E-ll No Data 3.89E-ll No Data 1.27E-10 1.37E-06 6.02E-06 Ru-106 8.64E-06 No Data 1.09E-06 No Data 1.67E-05 1.17E-03 1.ldE-04 Ag-110M. -1.35E-06 1.25E-06 7.43E-07 No Data 2.46E-06 5.79E-04 3.78E-05 Te-125M 4.27E-07 1.98E-07 5.84E-08 1.31E-07 1.55E-06 3.92E-05 8.83E-06 Te-127M 1.58E-06 7.21E-07 1.96E-07 4.llE-07 5.72E-06 1.20E-04 1.87E-05 Te-127 1.75E-10 8.03E-11 3.87E-ll 1.32E-10 6.37E-10 8.14E-07 7.17E-06 Te-129M 'l.22E-06 5.84E-07 1.98E-07 4.30E-07 4.57E-06 1.45E-04 4.79E-05
.Te-129 6.22E 2.99E-12 1.55E-12 4.87E-12 2.34E-ll- 2.42E-07 1.96E-08 Te-131M 8.74E-09 5.45E-09 3.63E-09' 6.8SE-09 3.86E-08 1.82E-05 6.95E-05 Te-131 1.39E-12 7.44E-13 4.49E-13 1.l?E-12 5.46E-12 1.74E-07 2.30E-09 Te-132 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'. 6 0 E-0 7 1.42E-04 2.61E-06 No Data 9.61E-07~
I-131 3.15E-06 4.47E-06 2.56E-06 1.49E-03 7.66E-06 No Data 7.85E-07' I-132 1.45E-07 4.07E-07 1.45E-07 1.43E-05 6.48E-07 No Data 5.08E-08 I-133 1.08E-06 1.85E-06 5.65E-07 2.69E-04 3.23E-06 No Data 1.llE-06 I-134 8.05E-08 2.16E-07 7.69E-08 3.73E-06 3.44E-07' No Data 1.26E-10.
-I-135 3.35E-07 8.73E-07 3.21E-07 5.60E-05 1.39E-06 No Data 6.56E-07
'Cs-134 4.66E-05 1.06E-04 9.10E-05 No Data 3.59E-05 1.22E-05 1.30E-06 Cs-136 4.88E-06 1.83E-05 1.38E-05 No Data 1.07E-05 1.50E-06 1.46E-06 Cs-137 5.98E-05 7.76E-05 5.35E-05 No Data 2.78E-05 9.40E-06 1.05E-06 Cs-138 4.14E-08 7.76E-08 4.05E-06 No Data' 6.00E-08 6.07E-09 '2.33E-13 Ba-139 1.17E-10 8.32E-14 3.42E-12 No Data 7.78E-14 4.70E-07 1.12E-07 Ba-140- 4.88E-06 6.13E-09 3.21E No Data 2.09E-09 1.59E-04 2.73E-05 Ba-141 1.25E-ll 9.41E-15 4.20E-13 No Data 8.75E-15 2.42E-07 1.45E-17 Ba-142 3.29E-12 3.38E-15 2.07E-13 No Data 2.86E-15 1.49E-07 1.96E-26 i
i l - a-140 4.30E-08 2.17E-08 5.73E-09 No Data No Data 1.70E-05 5.73E-05 v s l 2-45
~
)
TABLE-2.2-4 CONT'D e- s -INHALATION DdSE FACTORS FOR ADULTS * '
! IN1.
(MREM PER PCI INHALED)
.}1 Page 3 of 3 1
j Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI La-142 8.54E-ll 3.88E-11 9.65E-12. No Data No Data 7.91E-07_ 2.64E-07 Ce-141-s- 2.49E-06 1.69E-06 1.91E-07 No Data 7.83E-07 4.52E-05 1.50E-05 Ce-143 2.33E-08 1.72E-08 1.91E-09 No Data- 7.60E-09 9.97E-06 2.83E-05 Ce-144 4.29E-04 1.79E-04 2.30E-05 No Data 1.06E-04 9.72E-04 1.02E-04 Pr-143 1.17E-06 4.69E-07 5.80E-08 No Data 2.70E-07 3.51E-05 2.50E-05
_P r-14 4 - 3.76E-12 1.56E-12 1.91E-13 No Data 8.81E-13 1.27E-07 2.69E-18
, M*Nd-147 6.59E-07 7.62E-07 4.56E No Data 4.45E-07 2.76E-05 2.16E-05
=W-187 1.06E-09' 8.85E-10 3.10E-10 No Data No Data 3.63E-06 1.94E-05 Np-239 2.87E-08 2.82E-09 1.55E-09 No Data 8.75E-09 4.70E-06 1.49E-05 iY ,
b v
f:
b r t
2-46
4 TABLE 2.2-5 INGESTION' DOSE FACTORS FOR INFANT *
- \'
(MREM PER PCI INGESTED)
Page'l of 3 p . Nuclide- ' Bone : L'ive r T Body Thyroid Kidney Lung GI-LLI-H-3 . No Data 3.08E-07' 3.08E-07 3.08E-07 3.08E-07 ~3.08E-07 3.08E-07 C ' 2.37E-05 5.06E-06 5.06E-06 ~5.06E-06 5.06E-06 5.06E 5.06E-06 Na-24 1.01E-05 'l . 01E-0 5 - 1.01E-05 1.01E-05 1.018-05 1.01E-05 1.01E-05 P-32 . 1.70E-03 1.00E-04' 6.59E No Data No' Data No Data 2.30E-05 lCr-51 No Data No Data 1.41E-08 9.20E-09 2.01E-09 1.79E-08 .4.llE-07
, . Mn-54 - No Data 1.99E-05 4.51E-06 No Data 4 . 41E No Data 7.31E-06 Mn-56 No Data 8.18E-07 1.41E-07 No Data 7.03E-07 No Data 7.43E-05 Fe-55 : l'39E-05
. 8 98E-06 2.40E-06 No Data No Data 4.39E-06 1.14E-06 Fe-59 3.08E-05 5.38E-05 2.12E-05 No Data No Data- 1.59E-05 2.57E-05 o
Co-58 No Data- 3.60E-06! 8.98E-06 No Data No Data No Data 8.97E-06
'Co-60 No Data 1.08E-05 2.55E-05 No Data No Data No Data 2.57E-05
!- 'Ni-63 6.34E-04 3.92E-05 2.20E-05' No Data No Data No Data 1.95E-06
.Ni-65 ~ 4.70E-06 5.32E-07 2.42E-07 No Data No Data- No Data 4.05E-05 Cu-64 No Data -6.09E-07 2.82E-07. No Data 1.03E-06 No Data 1.25E-05
, Zn-65' l.84E-05 6.31E-05 2.91E-05 No Data 3.06E-05 No Data 5.33E-05 Zn-69 ~9.33E-08 1.68E-07 1.25E-08 No Data 6.982-08 No Data 1.37E-05 Br-83 No Data No Data 3.63E-07 No Dat'a No Data No Data LT E-24 Br-84 No Data No Data 3.82E-07 No Data No Data No Data LT E-24 Br-85 No Data- No Data 1.94E-08 No Data No Data No Data- LT E-24 Rb-86' No Data 1.70E-04 8.40E-05 No Data. No Data No Data 4.35E-06
. Rb-88 No Data 4.98E-07 2.73E-07 No Data No Data No Data 4.85E-07
.Rb-89 No Data 2.86E-07 1.97E-07 No-Data No Data No Data 9.74E-08 i ' Sr-89 2.51E-03 No Data 7.20E-05 No Data No Data No Data 5.16E-05 cSr-90 1.85E-02 No Data 4.71E-03 No Data No Data No Data 2.31E-04:
5.00E-05
~
Sr-91 No Data 1.81E-06' 'No Data No Data No Data 5.92E-05
! Sr-92 1.92E-05 No Data' 7.13E-07 No Data No Data No Data 2.07E-04 .
b .Y .8.69E-08 No Data 2.33E-09 No Data No Data No Data 1.20E-04 L' . .
Y-91M- 8.10E-10 No Data 2.76E-11 No Data No Data No Data 2.70E-06 Y-91' l.13E-06 No Data 3.01E-08~ No Data No Data No Data- 8.10E-05 Y-92. 7.65E-09 No Data. 2.15E-10 No Data No Data No Data 1.46E-04 is
- Reference 3, Table E-14.
h 2-47 r y y-e m -m-- , ,,.,,v.-y.+---m-,,,e,,. - , , , - - - --
F TABLE 2.2-5 CONT'D f-s _ INGESTION DOSE FACTORS FOR INFANT
- YI
. (MREM PER PCI INGESTED)
Page 2 of 3 Nuclide Bone Liver T Body Thyroid Kidney Luno GI-LLI Y-93 2.43E-08 No Data 6.62E-10 No Data No Data No Data 1.92E-04
'Zr-95 2.06E-07 5.02E-08 3.56E-08 No Data 5.41E-08 No Data 2.50E-05 Zr-97 1.48E-08 2.54E-09 1.16E-09 No Data 2.56E-09 No Data 1.62E-04 Nb-95 4.20E-08 1.73E-08 1.00E-08 No Data 1.24E-08 No Data 1.46E-05 Mo-99 No Data 3.40E-05 6.63E-06 No Data 5.08E-05 No Data 1.12E-05 Tc-99M -1.92E-09 3.96E-09 5.10E-08 No Data 4.26E-08 2.07E-09 1.15E-06 Tc-101 2.27E-09 2.86E-09 2.83E-08 No Data 3.40E-08 1.56E-09 4.86E-07
-Ru-103- 1.48E-06 No Data 4.95E-07 No Data 3.08E-06 No Data 1.80E-05 Ru-105 1.36E-07 No Data 4.58E-08 No Data 1.00E-06 No Data 5.41E-05 Ru-106 2.41E-05 No Data 3.01E-06 No Data 2.85E-05 No Data 1.83E Ag-110M 9.96E-07 7.27E-07 4.81E-07 No Data 1.04E-06 No Data 3.77E-05 Te-125M 2.33E-05 7.79E-06 3.15E-06 7.84E-06 No Data No Data 1.llE-05 Te-127M 5.85E-05 1.94E-05 7.08E-06 1.69E-05 1.44E-04 Bk) Data 2.36E-05 Te-127 1.00E-06 3.35E-07 2.15E-07 8.14E-07 2.44E-06 No Data 2.10E Te-129M 1.00E-04 3.43E-05 1.54E-05 3.84E-05 2.50E-04 No Data 5.97E-05
.Te-129 2.84E-07 9.79E-08_ 6.63E-08 2.38E-07 7.07E-07 No Data 2.27E-05 Te-131M 1.52E-05 6.12E-06 5.05E-06 1.24E-05 4.21E-05 No Data 1.03E-04 Te-131 1.76E-07 6.50E-08 4.94E-08 1.57E-07 4.50E-07 No Data 7.llE-06 Te-132 2.08E-05 1.03E-05 9.61E-06 1.52E-05 6.44E-05 No Data 3.81E-05 I-130 6.00E-06 1.32E-05 5 ~. 3 0E-0 6 1.48E-03 1.45E-05 No Data 2.83E-06 I-131 3.59E-05 -4.23E-05 1.86E-05 1.39E-02 4.94E-05 No Data 1.51E-06 I-132 1.66E-06 3.37E-06 1.20E-06 1.58E-04 3.76E-06 No Data 2.73E-06 I-133 1.25E-05 1.82E-05 5.33E-06 3.31E-03 2.14E-05 No Data 3.08E-06 I-134 8.69E-07. 1.78E-06 .6.33E-07 4.15E-05 1.99E-06 No Data 1.8 4E -0 6 I-135 3.64E-06 7.24E-06 2.64E-06 6.49E-04 8.07E-06 No Data 2.62E-06 Cs-134 3.77E-04 7.03E-04. 7.10E-05 No Data. 1.81E-04 7.42E-05 1.91E-06 Cs-136 4.59E-05 1.35E-04 5.04E-05 No Data 5.38E-05 1.10E-05 2.05E-06 Cs-137 5.22E-04 6 llE-04 4.33E-05 No Data 1.64E-04 6.64E-05 1.91E-06 Cs-138 4.81E-07 7.82E-07 3.79E-07 !!o Data 3.90E-07 6.09E-08 1.25E-06
~Ba-139 8.81E-07 5.84E-10 2.55E-08 No Data 3.51E-10 -3.54E-10 5.58E-05 2--48
1 TABLE'2.2-5 CONT'D n INGESTION DOSE. FACTORS FOR INFANT *
\-<] (MREM PER.PCI INGESTED)
Page 3 of 3
~Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI Ba-140 1.71E-04 1.71E-07 8.81E-06 No Data 4.06E-08 1.05E-07 4.20E-05 Ba-141 4.25E-07 2.91E-10 1.34E-08 No Data 1.75E-10 1.77E-10 5.19E-06 Ba-142 1.84E-07 1.53E-10 9.06E-09 No Data 8.81E-ll 9.26E-11 7.59E-07 La-140 2.llE-08 8.32E-09 2.14E-09 No Data No Data No Data 9.77E-05 La-142 1.10E-09 4.04E-10 9.67E-ll No Data No Data No Data 6.86E-05 Ce-141 7.87E-08 4.80E-08 5.65E-09 No Data 1.48E-08 No Data 2.48E-05 Ce-143 -1.48E-08 9.82E-06 1.12E-09 No Data 2.86E-09 No Data 5.73E-05 Ce-144 2.98E-06 1.22E-06 1.67E-07 No Data 4.93E-07 No Data 1.71E-04 Pr-143 8.13E-08 3.04E-08 4.03E-09 No Data 1.13E-08 No Data 4.29E-05 Pr-144 2.74E-10' 1.06E-10 1.38E-ll No Data 3.84E-ll No Data 4.93E-06 Nd-147 5.53E-08 5.68E-08 3~.48E-09 No Data 2.19E-08 No Data 3.60E-05 W-187 9.03E-07 6.28E-07 2.17E-07 No Data No Data No Data 3.69E-05 Np-239 1.11E-08 9.93E-10 5.61E-10 No Data 1.98E-09 No Data 2.87E-05 e
. \, )
2-49
TABLE 2.2-6 7s INGESTION DOSE FACTORS FOR CHILD
- s -
(MREM PER PCI INGESTED)
Page 1 of 3 Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI H-3 No Data 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 C-14 1.21E-05 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 Na-24 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 P-32 8.25E-04 .-3.86E-05 3.18E-05 No Data No Data No Data 2.28E-05 Cr-51 No Data No Data 8.90E-09 4.94E-09 1.35E-09 9.02E-09 4.72E-07 Mn-54 No Data 1.07E-05 2.8hE-06 No Data 3.00E-06 No Data 8.98E-06 Mn-56 No Data 3.34E-07 7.54E-08 No Data 4.04E-07 No Data- 4.84E-05 LFe-55 1.15E-05 6.10E-06 1.89E-06 No Data No Data 3.45E-06 1.13E-06 Fe-59 1.65E-05 2.67E-05 1.33E-05 No Data No Data 7.74E-06 2.78E-05 Co-58 No Data 1.80E-06 5.51E-06 No Data ~ No Data No Data 1.05E-05 Co-60 No Data 5.29E-06 1.56E-05 No' Data No Data No Data 2.93E-05 Ni-63 5.38E-0.4 2.88E-05 1.83E-05 No Data No Data No Data 1.94E-06 Ni-65 2.22E-06 2.09E-07 1.22E-07 No Data No Data No Data 2.56E-05 Cu-64 No. Data 2.45E-07 1.48E-07 No Data 5.92E-07 No Data 1.15E-05 Zn-65 1.37E-05 3.65E-05 2.27E-05 No Data 2.30E-05 No Data 6.41E-06 Zn-69 4.38E-08 6.33E-08 5.85E No Data 3.84E-08 No Data 3.99E-06 Br-83 No Data No Data 1.71E-07 No Data No Data No Data LT E-24 Br-84 No Data No Data 1.98E-07 No Data No Data No Data LT E-24 Br-85 No Data No Data 9.12E-09 No Data No Data No Data LT E-24 Rb-86 No Data 6.70E-05 4.12E-05 No Data No Data No Data 4.31E-06 Rb-88 No Data 1.90E-07 1.32E-07 No Data No Data No Data 9.32E-09 Rb'-89 No Data 1.17E-07 1.04E-07 No Data No Data No Data 1.02E-09 Sr-89 1.32E-03 No Data 3.77E-05 No Data No Data No Data 5.llE-05 Sr-90 1.70E-02 No Data 4.31E-03 No Data No Data No Data 2.29E-04 Sr-91 2.40E-05 No Data 9.06E-07 No Data No Data No Data 5.30E-05 Sr-92 9.03E-06 No Data 3.62E-07 No Data No Data No Data 1.71E-04 Y-90 -4.llE-08 No Data 1.10E-09 No Data No Data No Data 1.17E-04 Y-91M 3.82E-10 No Data 1.39E-ll No Data No Data No Data 7.48E-07 Y-91 6.02E-07 No Data. 1.61E-08 No Data No Data No Data 8.02E-05 Y-92 3.60E-09 No Data 1.03E-10 No Data No Data No Data 1.04E-04
- Reference 3, Table E-13.
b V
2-50
~ .m ,
l TABLE 2.2-6 CONT'D INGESTION DOSE FACTORS-FOR CHILD *
(MREM PER PCI-IFGESTED)
, Page 2 of 3 Nuclide- Bone Liver T Body _ Thyroid Kidney Lung GI-LLI
-Y-93 1.14E-08 .No Data . 3.13E-10 No Data No Data :No Data .l.70E Zr-95: -1.16E-07 2.55E-08 2.27E-08 No Data 3.65E-08 No Data 2.66E-05 Zr-97 6.99E-09 1.01E-09 5.96E-10 No Data. 1.45E-09 No Data 1.53E-04
'Nb-95 2.25E-08 8.76E-09 6.26E-09 No Data 8.23E-09 No Data 1.62E-05
,Mo 'No Data -1.33E-05 3.29E-06 No Data- 2.84E-05 No Data 1.10E-05.
Tc-99M: 9.23E-10 1.81E-09 3.00E-08 No Data 2.63E-08 9.19E-10 1.03E-06 ;
.Tc-101: 1.07E-09 1.12E-09 1.42E-08 No Data 1.91E-08 5.92E-10' 3.56E-09' JRu-103' 7.31E-07 No Data 2.81E-07' No Data 1.84E-06 No Data 1.89E-05
'Ru-105 6.45E-08 bk) Data 2.34E-08 .No Data 5.67E-07 No Data 4 . 21E-0 5 -
Ru-106. 1.17E-05 No Data .1.46E-06 No Data 1.58E-05 No Data 1 'l.82E-04
~Ag-110M- 5 .~ 3 9 E-0 7 . 3.64E-07 2.91E-07 bk) Data . 6.78E-07 No_ Data 4.33E-05'.
LTe-125M 1.14E-05 '3.09E-06 1.52E-06 3.20E-06 No Data No Data 1.10E-05 L
Te-127M 2.89E-05 7.78E-06~ -3.43E-06 6.91E-06 8.24E No Data 2.34E-05 JTe-127 _4.71E-07 1.27E-07 1.01E-07 3.26E 1.34E-06 No Data ,1.84E-05 :
~Te-129M ~ .4.87E-05 1.36E-05 7.56E-06 1.57E-05 1.43E-04 No Data 5.94E-05.
Te-129 1.34E-07 3.74E-08 3.18E-08 9.56E-08 3.92E-07 No Data 8.34E-06 Te-131M . 7.20E-06 '2.49E-06 2.65E-06 5.12E-06 3.41E-05 No Data 1.01E-04 Te-131' 8.30E-08 2.53E-08 2.47E-08 6.35E-08 2.51E-07 No Data 4.36E-07
.Te-132 1.01E-05 4.47E-06 5.40E 6.51E-06 4.15E-05 No Data 4.50E-05 I-130 2.92E 5.90E-06 -3.04E-06 6'50E-04 . 8.82E-06 No Data- 2.76E-06 I-131- .l.72E-05 -1.73E-05. 9.83E-06 5.72E-03' 2.84E No Data _1.54E-06~
LI-132' 8.00E-07 1.47E-06 6.76E-07 6.82E-05 2.'25E-06 No Data' 1.73E-06 lI-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 7.78E-07 3.58E-07 1.'79E-05 1.19E-06 No Data 5.16E-07 I-135L 21.75E-06 3.15E-06 1.49E-06 2.79E-04 4.83E-06 No Data 2.40E-06' Cs-134 . 2 .'3 4 E'-0 4 3.84E-04 8.10E-05 No Data 1.19E-04 -4.27E-05 2.07E-06 (Cs-136 L2.35E-05 6.'46E-05 4.18E-05 No Data 3.44E-05 5.'13E-06 2.27E-06
~
Cs-137 3.27E-04 3 . '13E-0 4 4.62E-05 No Data .1.02E-04 3.67E-05 1.96E-06 Cs-138 2.28E-07 3.17E-07 2.01E-07 No Data 2.23E-07 2.40E-08 1.46E-07 .
-Ba-139 4.14E-07 2.21E-10 1.20E-08 No Data 1.93E-10 1.30E-10 2.39E-05
- B a'-14 0 ' 8.31E-05' 7.28E-08 4.85E-06 No Data. 2.37E-08 4.34E-08 4.21E-05 Ba-141' 2.00E 1.12E-10 6.51E-09 No Data 9.69E-ll '6.58E-10 1.14E-07 Ba-142 - 8.74E-08 6.29E-ll. 4.88E-09 No Data 5.09E-ll 3.70E-ll 1.14E-09 2-51 s
TABLE 2.2-6 CONT'D x INGESTION DOSE FACTORS FOR CHILD *
- -]s t
? (MREM PER PCI INGESTED)
Page 3 of 3 Nuclide Bone Liver T Body Thyroid ~ Kidney Lung GI-LLI La-140 1.01E-08. 3.53E-09 1.19E-09 No Data No Data No Data 9.84E-05 La-142 5.24E-10 1.67E-10 5.23E-ll No Data No Data No Data- 3.31E-05 Ce-141 3.97E-08 1.98E-08 2.94E-09 No Data 8.68E-09 No Data 2.47E-05 Ce-143 6.99E-09 3.79E-06 5.49E-10 No Data 1.59E-09 No Data 5.55E-05 Ce-144 2.08E-06 6.52E-07 1.11E-07 No Data 3.61E No Data 1.70E-04
-Pr-143 3.93E-08 1.18E-08 1.95E-09 No Data 6.39E-09 No Data- 4.24E Pr-144 1.29E-10 3.99E-ll 6.49E-12 No Data 2.llE-ll No Data 8.59E-08 Nd-147 2.79E-08 2.26E-08 1.75E-09 No Data 1.24E-08 No Data 3.58E-05 W-187 -4.29E-07 2.54E-07 1.14E-07 No Data No' Data No Data 3.57E-05 Np-239 5.25E-09 3.77E-10 _2.65E-10 No Data 1.09E-09 No Data 2.79E-05 l
() 2-52 l
l l
TABLE 2.2-7
., INGESTION DOSE FACTORS FOR TEENAGER *
/ s)
V (MREM PER PCI INGESTED)
Page 1 of 3 Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI H-3 No Data -1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 C-14 4.06E-06 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 Na-24 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 P-32 2.76E-04 1.71E-05 1.07E-05 No Data No Data No Data 2.32E-05 i' Cr-51 No Data No Data 3.60E-09 2.00E-09 7.89E-10 5.14E-09 6.05E-07 Mn-54 No Data 5.90E-06 1.17E-06 No Data 1.76E-06 No Data 1.21E-05 Mn-56 No Data. 1.58E-07 2.81E-08 No Data 2.00E-07 No Data 1.04E-05 Fe-55 3.78E-06 2.68E-06 6.25E-07 No Data No Data 1.70E-06 1.16E-06 Fe-59 5.87E-06 1.37E-05 5.29E-06 No Data No Data 4.32E-06 3.24E-05 Co-58 No Data 9.72E-07 2.24E-06 No Data No Data No Data 1.34E-05 Co-60 No Data 2.81E-06 6.-33E-06 No Data No Data No Data 3.66E-05 1.25E-05 6.00E-06 Ni-63 1.77E-04 No Data No Data No Data 1.99E-06 Ni-65 7.49E-07 9.57E-08 4.36E-08 No Data No Data No Data 5.19E-06 Cu-64 No Data 1.15E-07 5.41E-08 No Data 2.91E-07 No Data 8.92E-06 Zn-65 5.76E-06 2.00E-05 9.33E-06 No Data 1.28E-05 No Data 8.47E-06 Zn-69 1.47E-08 2.80E-08 1.96E-09 No Data 1.83E-08 No Data 5.16E-08 Br-83 No Data No Data ~ 5.74E-08 No Data No Data No Data- LT E-24 Br-84 No Data No Data 7.22E-08 No Data No Data No Data LT E-24 Br-85 No Data No Data 3.05E-09 No Data No Data No Data LT E-24 Rb-86 No Data 2.98E-05 1.40E-05 No Data No Data No Data 4.41E-06 Rb-88 No Data 8.52E-08 4.54E-08 No Data No Data No Data 7.30E-15 .
Rb-89 No. Data 5.50E-08 3.89E-08 No Data No Data- No Data 8.43E-17 Sr-89 4.40E-04 No Data 1.26E-05 No Data No Data No Data 5.24E-05 Sr-90 8.30E-03 No Data 2.05E-03 No Data No Data No Data 2.33E-04 Sr-91 8.07E-06 No Data 3.21E-07 No Data No Data No Data 3.66E-05 Sr-92 3.05E-06 No Data -1.30E-07 No Data No Data No Data 7.77E-05 Y-90 1.37E-08 No Data 3.69E-10 No Data No Data No Data 1.13E-04 Y-91M 1.29E-10 No Data 4.93E-12 No Data No Data No Data 6.09E-09
-Y-91 -2.01E-07 No Data 5.39E-09 No Data No Data No Data 8.24E-05 Y 1.21E-09 No Data 3.50E-ll No Data No Data No Data 3.32E-05
- Reference 3, Table E-12.
2-53
~r ,m., r r- , - . - - - -
, TABLE 2.2-7 CONT'D '
INGESTION DOSE- FACTORS FOR TEENAGER
- O (MREM PER PCI INGESTED)_
i Page 2 of 3 ,
Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI
.Y-93: 3.83E-09 No Data 1.05E-10 No Data- No Data No Data 1.17E-04 Zr-95 '4.12E-08 1.30E-08 8.94E No Data 1.91E-08 No Data 3.00E-05 Zr-971 _2.37E-09 4.69E-10 .2.16E-10 No Data- 7.11E-10 No Data 1.27E-04 Nb 8.22E-09 4.56E-09 2.51E-09 No Data 4.42E-09 No Data 1.95E-05 Mo-99 .No Data 6.03E-06 1.15E-06 No Data 1.38E-05 No Data 1.08E-05 Tc-99M 3.32E-10 9.26E-10 1.20E-08 No Data 1.38E-08 '5.14E-10 6.08E-07
- Tc-101 -3.60E-10 5.12E-10 5.03E-09 No Data 9.26E-09 3.12E-10 8.75E-17 Ru-103 2.55E-07 No Data 1.09E-07 No Data. 8.99E-07 No Data 2.13E-05 Ru-105 2.18E-08 No Data 8.46E-09 No Data 2.75E-07 No Data 1.76E-05 Ru-106 3.92E-06~ No Data 4.94E-07 No Data' 7.56E No Data 1.88E-04 Ag-110M. 2.05E-07 11.94E-07 1.18E-07 No Data 3.70E-07 No Data. 5.45E-05 Te-125M 3'.83E-06 -1.38E-06 5.12E-07 1.07E-06 No Data- No Data 1.13E-05 J
Te-127M 9.67E-06 3.43E-06 1.15E-06 2.30E-06 3.92E-05 No Data 2.41E-05 Te-127' -1.58E-07 5 ~. 60E-08 3.40E-08 1.09E-07 6.40E-07 No Data 1.22E-05 Te-129M 1.63E-05 .6.05E-06 -2.58E-06 5.26E-06 6.82E-05 -No Data 6.12E-05 Te-129- 4.48E 1.67E-08 1.09E-08 3.20E 1.88E-07 No Data 2.45E-07 Te-131M' .2.44E-06 ^1.17E-06 9.76E-07 1.76E-06 1.22E-05 No Data 9.39E-05 Te-131. 2.79E-08 1.15E-08 8.72E 2.15E-08 1.22E-07 No Data 2.29E-09 Te-132 3.49E-06 2.21E-06 2.08E-06 2.33E-06 2.12E-05 No Data 7.00E I-130 1.03E-06 2.98E-06 1.19E-06 -2.43E-04 4.59E-06 No Data 2.29E-06
- I-131; '5.85E-06 8.19E 4.40E-06 2.39E-03 1.41E-05 .No Data 1.62E-06 ,
I-132 2.79E-07 7.30E-07 2.62E-07 2.46E-05 1.15E-06 No Data 3.18E-07 I-133i 2.01E-06 3.41E-06 1.04E-06 4.76E-04 5.98E-06 No Data- 2.58E-06 .
I-134 1.46E-07 3.87E-07 1.39E-07 6.45E-06 6.10E-07 No Data 5.10E-09 I-135 6.~10E-07 1.57E-06 5.82E-07 1.01E-04 2.48E-06 No Data 1.74E-06 Cs-134' 8.37E-05 1.97E 9.14E No' Data' 6.26E-05J 2.39E-05 2.45E-06 '
Cs-136 8.59E-06 3.38E 2.27E-05 No Data 1.84E-05 2.90E-06 2.72E-06
-Cs-137 1.12E-04 1.49E-04 5.19E-05 No' Data 5.07E-05' l.97E-05 2 .'12E-0 6 Cs-138 7.76E-08 1.49E-07 7.45E-08 No Data 1.10E-07 1.28E-08 6.76E-ll
- Ba-139 1.39E-07 9.78E-11 4.05E-09. No Data 9.22E-ll 6.74E-ll 1.24E-06 L
O 2-54
h i
i TABLE 2.2-7 CONT'D g INGESTION DOSE FACTORS FOR TEENAGER *
~'
(MREM PER PCI INGESTED)
Page 3 of 3 Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI Ba-140 .2.84E-05 3.48E-08 1.83E-06 No Data 1.18E-08 2.34E-08 4.38E-05 Ba-141 6.71E-08 5.01E-ll 2.24E-09 No Data 4.65E-ll 3.43E-ll 1.43E-13 Ba-142 2.99E-08 2.99E-ll 1.84E-09 No. Data 2.53E-ll 1.99E-11 9.18E-20 La-140 3.48E-09 1.71E-09 4.55E-10 No Data No Data No Data 9.82E-05 La-142 'l.79E-10 7.95E-ll 1.98E-ll No Data No Data No Data 2.42E-06 Ce-141 1.33E-08 8.88E-09 1.02E-09 No Data 4 .18E-0 9 - No Data 2.54E-05 Ce-143 2.35E-09 1.71E-06 1.91E-10 No Data 7.67E-10 No Data 5.14E-05 Ce-144 6.96E-07 2.88E-07 3.74E-08 No Data 1.72E-07 No Data 1.75E-04 Pr-143 1.31E-08 5.23E-09 6.52E-10 No Data 3.04E-09 No Data 4.31E-05 Pr-144 4.30E-ll 1.76E-ll 2.18E-12 No Data 1.01E-ll No Data 4.74E-14 Nd-147 9.38E-09 1.02E-08 6.llE-10 No Data 5.99E-09 No Data 3.68E-05 W-187 1.46E-07 1.19E-07 4.17E-08 No Data No Data No Data 3.22E-05 Np-239 1.76E-09 1.66E-10 9.22E-ll No Data 5.21E-10 No Data 2.67E-05
/ \
k 2-55
TABLE 2.2-8 g, INGESTION DOSE FACTORS FOR ADULTS
- s-(MREM PER PCI INGESTED)
Page 1 of 3 Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI H-3 No Data 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07
'C-14 2.84E-06 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E Na-24 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 P-32 1.93E-04 1.20E-05 7.46E-06 No Data No Data No Data 2.17E-05 Cr-51 No Data No Data 2.66E-09 1.59E-09 5.86E-10 3.53E-09 6.69E-07 Mn-54 No Data- 4.57E-06 8.72E-07 No Data 1.36E-06 No Data 1.40E-05
.Mn-56 No Data 1.15E-07 2.04E-08 No Data 1.46E-07 No Data 3.67E-06 Fe-55 2.75E-06 1.90E-06 4.43E-07 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 2.85E-06 3.40E-05 Co-58 No Data 7.45E-07 1.67E-06 No Data No Data No Data 1.51E-05 Co-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 No Data No Data 1.88E-06 Ni-65 5.28E-07 6.86E-08 3.13E-08 No Data No Data No Data 1.74E-06 Cu-64 .No Data 8.33E-08 3.91E-08 No Data 2.10E-07 No Data 7.10E-06 Zn-65 4.84E-06 1.54E-05 6.96E-06 No Data 1.03E-05 No Data 9.70E-06 Zn-69 1.03E-08 1.97E-08 1.37E-09 No Data 1.28E-08 No Data 2.96E-09 Br-83 No Data No Data 4.02E-08 No Data No Data No Data 5.79E-08 Br-84 No Data No Data 5.21E-03 No Data No Data No Data 4.09E-13 Br-85 No Data No Data 2.14E-09 No Data No Data No Data LT E-24 Rb-86 No Data 2.llE-05 9.83E-06 No Data No Data No Data 4.16E-06 Rb-88 No Data 6.05E-08 3.21E-08 No Data No Data No Data 8.36E-19 Rb-89 No Data 4.01E-08 2.82E-08 No Data No Data No Data 2.33E-21 Sr-89 3.08E-04 No Data 8.84E-06 No Data No Data No Data 4.94E-05 Sr-90 7.58E-03 No Data 1.86E-03 No Data No Data No Data 2.19E-04 Sr-91 5.67E-06 No Data 2.29E-07 No Data No Data No Data 2.70E-05 Sr-92' 2.15E-06 No-Data 9.30E-08 No Data No Data No Data 4.26E-05 Y-90 9.62E-09 No Data 2.58E-10 No Data No Data No Data 1.02E-04 Y-91M 9.09E-ll. No Data 3.52E-12 No Data No Data No Data 2.67E-10 Y-91 1.41E-07 No Data 3.77E-09 No Data No Data No Data 7.76E-05
'Y-92 8.45E-10 No Data 2.47E-ll No Data No Data No Data 1.48E-05
- Reference 3,-Table E-ll.
O) t'"
2-56
~
TABLE 2.2-8 CONT'D
,-~ INGESTION DOSE FACTORS FOR ADULTS
- I N2 (MREM PER.PCI INGESTED)
Page 2 of 3 Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI Y-93 2.68E-09 No Data 7.40E-ll No Data No Data No Data 8.50E-05 Zr-95 3.04E-08 9.75E-09 6.60E-09 No Data 1.53E-08 No Data 3.09E-05 Zr-97 1.68E-09 3.39E-10 1.55E-10 No Data 5.12E-10 No Data 1.05E-04 Nb-95 6.22E-09 .3.46E-09 1.86E-09 No Data 3.42E-09 No Data 2.10E-05 Mo-99 No Data 4.31E-06 8.20E-07 No Data 9.76E-06 No Data 9.99E-06 Tc-99M 2.47E-10 6.98E-10 8.89E-09 No Data 1.06E-08 3.42E-10 4.13E-07 Tc-101 2.54E-10 3.66E-10 3.59E-09 No Data 6.59E-09 1.87E-10 1.10E-21 Ru-103 1.85E-07 No Data 7.97E-08 No Data 7.06E-07 No Data 2.16E-05 Ru-105 1.54E-08 No Data 6.08E-09 No Data 1.99E-07 No Data 9.42E-06 Ru-106 2.75E-06 No Data 3.48E-07 No Data 5.31E-06 No Data 1.78E-04 Ag-110M 1.60E-07 1.48E-07 8.79E-08 No Data 2.91E-07 No Data 6.04E-05 Te-125M 2.68E-06 9.71E-07 3.59E-07 8.06E-07 1.09E-05 No Data 1.07E-05 Te-127M 6.77E-06 2.42E-06 8.25E-07 1.73E-06 2.75E-05 No Data 2.27E-05 Te-127 1.10E-07 3.95E-08 2.38E-08 8.15E-08 4.48E-07 No Data 8.68E-06 Te-129M 1.15E-05 4.29E-06 1.82E-06 3.95E-06 4.80E-05 No Data 5579E-05 Te-129 3.14E-08 1.18E-08 7.65E-09 2.41E-08 1.32E-07 No Data 2.37E-08 Te-131M 1.73E-06 8.46E-07 7.05E-07 1.34E-06 8.57E-06 No Data 8.40E-05 Te-131 1.97E-08 8.23E-09 6.22E-09 1.62E-08 8.63E-08 No Data 2.79E-09 Te-132 2.52E-06 1.63E-06 1.53E-06 1.80E-06 1.57E-05 No Data 7.71E-05 I-130 7.56E-07 2.23E-06 8.80E-07 1.89E-04 3.48E-06 No Data 1.92E-06 I-131 4.16E-06 5.95E-06 3.41E-06 1.95E-03 1.02E-05. No Data 1.57E-06 I-132 2.03E-07 5.43E-07 1.90E-07 1.90E-05 8.65E-07 No Data 1.02E-07 I-133 1.42E-06 2.47E-06 7.53E-07 3.63E-04 4.31E-06 No Data 2.22E-06 I-134 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 No Data 2.51E-10 l I-135 4.43E-07 1.16E-06 4.28E-07 7.65E-05 1.86E-06 No Data 1.31E-06 Cs-134 6.22E-05 1.48E-04 1.21E-04 No Data 4.79E-05 1.59E-05 2.59E-06 Cs-136 6.51E-06 2.57E-05 1.85E-05 No Data 1.43E-05 1.96E-06 2.92E-06 Cs-137 7.97E-05 1.09E-04 7.14E-05 No Data 3.70E-05 1.23E-05 2.llE-06 Cs-138 5.52E-08 1.09E-07 5.40E-08 No Data 8.01E-08 -7.91E-09 4.65E-13 Ba-139 9.70E-08 6.91E-ll 2.84E-09 No Data 6.46E-11 3.92E-ll 1.72E-07 Ba-140 2.03E-05 2.55E-08 1.33E-06 No Data 8.67E-09 1.46E-08 4.18E-05 Ba-141 .4.71E-08 3.56E-ll 1.59E-09 No Data 3.31E-11 2.02E-11 2.22E-17 Ba-142 2.13E-08 2.19E-ll 1.34E-09 No Data 1.85E-ll 1.24E-ll 3.00E-26 i
(x_-)
2-57
TABLE 2.2-8 CONT'D INGESTION DOSE FACTORS FOR ADULTS *
~O-- (MREM PER PCI INGESTED)
Page 3 of 3 Nuclide Bone Liver T Body Thyroid Kidney Luno GI-LLI La-140 2.50E-09 1.26E-09 3.33E-10 No' Data No Data No Data 9.25E-05 La-142 1.28E-10 5.82E-11 1.45E-ll No Data No Data No Data 4.25E-07 Ce-141 9.36E-09 6.33E-09 7.18E-10 No Data 2.94E-09 No Data 2.42E-05 Ce-143 1.65E-09 1.22E-06 1.35E-10 No Data 5.37E-10 No Data 4.56E-05 Ce-144 4.88E-07 2.04E-07 2.62E-08 No Data 1.21E-07 No Data 1.65E-04 Pr-143 9.20E-09 3.69E-09 4.56E-10 No Data 2.13E-09 No Data 4.03E-05 Pr-144 3.01E-11 1.25E-11 1.53E-12 'No Data 7.05E-12 No Data 4.33E-18 Nd-147 6.29E-09 7.27E-09 4.35E-10 No Data 4.25E-09 No Data 3.49E-05 W-187 1.03E-07 8.61E-08 3.01E-08 No Data No Data No Data 2.82E-05 Np-239 1.19E-09 1.17E-10 6.45E-ll No Data 3.65E-10 No Data 2.40E-05 j 4
4 O 2-58 4
I
/i TABLE 2.2-9 Q
EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND *
(mrem /hr per pCi/m2)
RADIONUCLIDE TOTAL BODY SKIN
, H-3 0.0 0.0 C-14 0.0 0.0 Na-24 2.50E-08 2.90E-08
.P-32 0.0 0.0 Cr-51 2.20E-10 2.60E-10 Mn-54 5.80E-09 6.80E-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 Ni-63 0.0 0.0 Ni-65 3.70E-09 4.30E-09
-Cu-64 1.50E-09 1.70E-09 Zn-65 4.00E-09 4.60E-09 Zn-69 0.0 0.0 Br-83 6.40E-ll 9.30E-ll Br-84 1.20E-08 1.40E-08 ,.
Br-85 0.0 0.0 Rb-86 6.30E-10 7.20E-10 Rb-88 3.50E-09 4.00E-09 Rb-89 1.50E-08 1.80E-08
- Sr-89 5.60E-13 6.50E-13 Sr-91 7.10E-09 8.30E-09 Sr-92 9.00E-09 1.00E-08 Y-90 2.20E-12 2.60E-12
- Reference 3, Table E-6
[
2-59
-e - . , , ,.-r,-- . . , - , , - . . - , ~ , - , - . - , . - , . ~ , ~ . - - , , - ---,.,-..-,---n- ..-,----. , ,,, , ,, , , , , .
TABLE 2.2-9 (Continued)
EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND
- RADIONUCLIDE TOTAL BODY SKIN Y-91M- 3.80E-09 4.40E-09 Y 2.40E-11 2.70E-11 Y-92 1.60E-09 1.90E-09 Y-93 5.70E-10 7.80E-10 Zr-95 5.00E-09 5.80E-09 Zr-97~ '5.50E-09 6.40E-09 Nb-95 5.10E-09 6.00E-09
-Mo-99 1.90E-09 2.20E-09
'Tc-99M 9.60E-10 1.10E-09 Tc-101 2.70E-09 3.00E-09 Ru-103 3.60E-09 4.20E-09 Ru-105 4.50E-09 5.10E-09 Ru-106 1.50E-09 1.80E-09 Ag-110M 1.80E-08 2.10E-08 Te-125M 3.50E-11 4.80E-11 Te-127M 1.10E-12 1.30E-12 Te-127 1.00E-ll '1.10E-ll Te-129M 7.70E-10 9.00E-10 Te-129 7.10E-10 8.40E-10 Te-131M 8.40E-09 9.90E-09 Te-131 2.20E-09 2.60E-06 Te-132 1.70E 2.00E-09 I-130. 1.40E-08 1.70E-08 I-131 2.80E-09 3.40E-09 I-132 1.70E-08 2.00E-08 I-133 3.70E-09 4.50E-09
..,. I-134 1.60E-08 1.90E-08 I-135 1.20E-08 1.40E-08 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 Ba-139 2.40E-09 (f 2.70E-09 2-60
i l
l TABLE 2.2-9 (Continued)
,ew (s_- ) EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND
- RADIONUCLIDE TOTAL BODY SKIN Ba-140 2.10E-09 2.40E-09 Ba-141 4.30E-09 4.90E-09 F# Ba-142 7.90-09 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 O
V 2-61
TABLE 2.2-10 INDIVIDUAL USAGE FACTORS
- 4 INFANT' CHILD TEENAGER ADULT Milk Consumption Rate, U,p (liters / year) 330 330 400 310 Meat Consumption Rate,-
U,p (kg/ year) 0 41 65 110 Fresh Leafy Vegetation Consumption Rate, Uni (kg/ year) 0 26 42 64 Stored Vegetation Consumption Rate, U,, (kg/ year) 0 520 630 520 Breathing Rate (m3 / year) 1400 3700' 8000 8000 l
()
- Reference 3, Table E-5.
2-62
TABLE 2.2-11 STABLE ELEMENT TRANSFER DATA *
(Milk - days / liter; Meat-days /kg)
- D
-- ELEMENT F,- MILK F,- MILK Fg-MEAT (COW) (GOAT)
H 1.0E-02 1.7E 1.2E-02 C 1.2E-02 1.0E-01 3.lE-02 Na 4.0E-02 4.0E-02 3.0E-02 P 2.5E-02 2.5E-01 4.6E-02 Cr 2.2E-03 2.2E-03 2.4E-03 Mn 2.5E-04 2.5E-04 8.0E-04 Fe -1.2E-03 1.3E-04 4.0E-02 Co 1.0E-03 1.0E-03 1.3E-02 Ni 6.7E-03 6.7E-03 5.3E-02 Cu 1.4E-02 1.3E-02 8.0E-03 Zn 3.9E-02 3.9E-02 3.0E-02 Rb 3.0E-02 3.0E-02 3.lE-02 Sr 8.0E-04 1.4E-02 6.0E-04 Y 1.0E-05 1.0E-05 4.6E-03 Zr 5.0E-06 5.0E-06 3.4E-02 Nb 2.5E-03 2.5E-03 2.8E-01 Mo '7.5E-03 7.5E-03 8.0E-03 Tc 2.5E-02 2.5E-02 4.0E-01 Ru 1.0E-06 1.0E-06 4.0E-01 Rh 1.0E-02 1.0E-02 1.5E-03 Ag 5.0E-02 5.0E-02 1.7E-02 Te 1.0E-03 1.0E-03 7.7E-02 I 6.0E-03 6.0E-02 2.9E-03 Cs 1.2E-02 3.0E-01 4.0E-03 Ba 4.0E-04 4.0E-04 3.2E-03 La 5.0E-06 5.0E-06 2.0E-04 Ce 1. 0E-04 1.0E-04 1.2E-03 Pr 5.0E-06 5.0E-06 4.7E-03 Nd 5.0E-06 5.0E-06 3.3E-03 W 5.09-04 5.0E-04 1.3E-03 Np 5.0s-it 5.0E-06 2.0E-04
- References 3, Table E-1.
'( )
2-63 l
}
TABLE 2.2-12
( ) ' CONTROLLING RECEPTOR (To Support Subsection 2.2.2.2)
Sector: WSW- Distance: 1.3_ miles Age Group: Child Dispersion:
(X/Q')GP
=
.0E-7 sec/m (X/Q' ) MP = 9.8E-8 sec/m
~
Depositions -2 (D/Q')GP= 2.5E-9 m (D/Q ' ) MP = 9.6E-10 m Exposure pathways: Inhalation, ground plane, and vegetation NOTE: A milk cow was observed during the 1985 Land Use Survey. The owner indicated that the cow was on an irregular milking cycle, and is dry for long periods of time. 'However, because of the potentially significant dose associated with this pathway, dose calculations must be performed during periods in which the cow is being milked for human consumption. A garden is also present at this location. Under certain conditions, the individual exposed to these pathways could become the controlling receptor. The determining factor is likely to be the number of months the cow is milked in a year. Calculated dose results should be compared to the receptor presented above to determine which is the controlling receptor.
Sector: WNW Distance: 2.9 miles Age group: Child Dispersion b (X/Q')gy = 1.8E-7 sec/m (X/Q')pp = 4.0E-8 sec/m Deposition: -2 -2 (D/Q ' ) gp = 5.5E-10 m (D/Q')gp = 2.2E-10 m Exposure pathways: Inhalation, ground plane, vegetation, and milk cow
. ,m
- Reference 12 i \
L.. / l 2-64 l
TABLE 2.2-13 SITE-SPECIFIC (OR DEFAULT)' VALUES.TO
) -
BE-USED IN PATHWAY FACTOR CALCULATIONS (Supports Subsections 2.2.2.2 and 2.2.2.3)
Parameter Description Value Inhalation (BR), Breathing rate for Table'2.2-10 age group (DFA)t$, Inhalation dose factor- Tables 2.2-1 for age group 2.2-4 Ground plane-SF' Shielding factor-due to 0.7 structure (DFG)ij Ground plane dose factor Table 2.2-9 (Same for- all age groups)
\
l
- j. Garden Vegetation
!=
l-Y, Garden vegetation areal 2.0 kg/m 2 l density
( U,1 Leafy vegetation consump- Table 2.2-10 tion rate for age group
- U as Stored vegetation consump- Table 2.2-10 l
tion rate for age group l'
I O
2-65 L
1 1
TABLE 2.2-13 (Continund)
SITE-SPECIFIC (OR DEFAULT) VALUES _TO
)
BE USED IN PATHWAY FACTOR CALCULATIONS Parameter -Description Value fy Fraction of annual intake 1.0 of leafy vegetation grown locally
.f g Fraction of annual intake of 0.76 stored vegetation grown locally H Absolute humidity of the 8.0 gm/m 3 atmosphere O
2-66
l
. TABLE 2.2-13 (Continued)
SITE-SPECIFIC (OR DEFAULT) VALUES TO BE USED IN PATHWAY FACTOR CALCULATIONS Parameter Description Value Grass-Cow-Meat
.p Q Feed consumption rate for 50 kg/ day cow U,p Meat consumption rate for Table 2.2-10 age group (DFL)ij, Ingestion dose factor for Tables 2.2 age group 2.2-8 Y
p Pasture grass areal density 0.7 kg/m 2 Y s. Stored feed areal density 2.0 kg/m 2 f
p Fraction of year that cow 1.0 graxes on pasture f
s Fraction of total feed that 1.0 is pasture grass while cow is on pasture H Absolute humidity of the 8.0 gm/m 3 atmosphere Grass-Cow-Milk Op Feed consumption rate for 50'kg/ day cow V
2-67
i
)
TABLE 2.2-13 (Continued)
SITE-SPECIFIC (OR DEFAULT) VALUES TO
'M BE USED IN PATHWAY FACTOR CALCULATIONS Parameter Description Value U,p Milk consumption rate for Table 2.2-10 age group
- (DFL)ija Ingestion dose factor for Tables 2.2 age group 2.2-8 Y
p Pasture grass areal density 0.7 kg/m 2 Ys Stored feed areal density 2.0 kg/m 2 f
p Fraction of year that cow 1.0 grazes on-pasture f
s Fraction of total feed that 1.0 is pasture grass while cow is on pasture H Absolute humidity of the 8.0 gm/m 3 atmosphere Grass-Goat-Milk 07 Feed consumption rete for 6.0 kg/ day goat U ap Milk consumption rats for Table 2.2-10 age group (DFL)ija Ingestion dose factor for Tables 2.2 age group 2.2-8 O
2-68 l
TABLE 2.2-13 (Continued)
SITE-SPECIFIC (OR DEFAULT) VALUES TO BE USED IN PATHWAY FACTOR CALCULATIONS Parameter Descriotion Value Y
p Pasture grass areal density 'O.7 kg/m2 Yg Stored' feed areal density 2.0 kg/m 2 f
p Fraction of year that goat 1.0 grazes on pasture f . Fraction of total feed that 1.0 s
is' pasture grass while goat l's on pasture H- Absolute humidity of 8.0 gm/m 3 the atmosphere 4
2-69
TABLE 2.2-14
-POTENTIAL RECEPTOR LOCATIONS AND PATHWAYS (To Support Subsection 2.2.2.3) t
\- Distance Sector (Miles) Pathway *** Age Group N
- NNE
- NE
- ENE
- E
- ESE
- SE 4.3 Meat Animal Child SSE 4.7 Inhalation / Ground Plane Child S 4.5 Inhalation / Ground Plane Child SSW 4.7 Meat Animal Child SW 3.2 Meat Animal- Child WSW l.3 Vegetation Child W l.4 Vegetation Child WNW 2.4 Vegetation Child 2.9**** Vegetation / Milk Cow Child NW 4.4 Vegetation / Meat Animal Child NNW **
Savannah River Plant Property (closed to public)
- No receptor identified within five miles
- Inhalation and ground plane pathways are assumed at all locations where ingestion pathways exist.
A milk cow has been observed at this location. However she
! is on an irregular milking cycle. The pathway will exist
( during periods when the cow is being milked.
() Reference 12 l 2-70 r
-M- n w
v.
- s. : '
.: TABLE 2.2-15 DISPERSION AND DEPOSITON PARAMETERS (To Support Subsection 2.2.2.3) '
Distance Ground-Level Release '
Mix d-Mode Release Sector (Miles) 'X/O sec/m3 - D/O m-2 ._X70sec[al D/O m-2 7
- r. .
N *' ~-
NNE *
. , ,/ e ;
NE * - I' 7
' ~
- ENE-E
- ESE * ' -
SE 4.3 9.6E-8 3.0E-10 2.2E-8. 1.4E-10 SSE 4.7 6.6E-8 ," 1.5E-10 1.3E-8 6.9E-ll -
S 4.5 , ' ;1.0E-7 2.1E-10 1.7E-8 9.4E-ll SSW 4.7 9.4E-8 2.lE 1.7E-8 1.0E-10 ,
SW 3.2 1.9E-7 #
6.2E-10 . 5.2E-8 2.9E-10 '
WSW 1.3 6.0E-7 2.5E-9 9.8E-8 9.6E-10 W 1.4 6.4E 2.3E-9 7.4E-8 8.0E-10 WNW 2.4 2.3E-7 7.5E-10 4.6E-8 2.9E-10 2.9 1 8E-7 5.5E-10 ' 4.0'E-8 2.2E-10 NW .4.4 1.0E-7 2.6E-10 ~
3.0E-8 9.6E-11
. NNW **
s, F
b A
~~ \ >
, s Savannah River Plant- property (closed to public) 's No receptor identified within five miles Reference 5, Tables 2.3.5-8 and 2.3.5-9; Reference 12.
/
2-71 -
Y h
2.2.3 Dose Projections for Gaseous Effluents O)
'rj 2.2.3.1 Thirty-One Day Dose Proiections
.In order to meet the requirements of Technical Specification 3.11.2.4, which pertains to operation of the Ventilation Exhaust Treatment System and the Gaseous Waste Processing System, dose projections must be made'at least once per 31 days, during periods in which discharge of gaseous effluents containing radioactive materials to unrestricted areas occurs or is expected.
Projected 31-day air doses and doses to individudls due to gaseous effluents may be-determined as follows:
Air Doses:
D D " beta (c) beta (prj) t x 31 (32)
D gamma (c)
D " x 31 (33) gamma (prj) t Individual:
D D " o(c) o(prj) t x 31 (34) where D = the cumulative air dose, due to beta emissions beta (c) from noble gases, for the elapsed portion of the current quarter plus the release under consideration.
O 2-72
D gamma (c) = tha cumulativo air dono, due to gem'n'cmiesions a from, noble gases, for the elapsed portion of the l
current quarter plus the release under LJ ) consideration.
t D oge) = the cumulative organ dose, to an individual due to ,
I-131, I-133, tritium and particulates, for the elapsed portion of the current quarter plus the release under consideration.
t =
the number of days into the current quarter.
If operational activities, planned during the ensuing 31 day period are expected to result in gaseou's releases which will '
contribute a dose'in addition to the dose due to routide: gaseous effluents, this additional dose contribution should be included in the projected dose as follows:
Air Doses:
D D
- beta (c) x 31 + D beta (prj) t pg (35)
D gamma (c)
D gamma (prj) t x 31 + D pg (36i, 3
, 1
, 3
/ -
D o(c)
D o(prj)'
t
- 1+ PA.
(379' ,
Where D pg is the expected dose due to the particular planned U activity.
k e *4 /
f
.h v
2-73 ,
\
s
.n L_.
2.2.3.2 Done Projections for Specific Releases
(- Dose projections may be performed for a particular release by performing a pre-release dose calculation assuming that the planned a
release will proceed as anticipated. For air dose projections due to
.% noble gases, follow the methodology presented in Subsection 2.2.2.1 using sample analyses results for the particular release point and parametric values expected to exist for the release period. For individual organ dose projections, due to I-131, I-133, tritium and particulates, follow the methodology presented in Subsection 2.2.2.2 using sample analyses results for the particular release point and parametric values expected to exist for the release period.
I
,'}
4 o.
. 't h
2-74
2.3 METEOROLOGICAL MODEL O
() (Reference 7 and Section 2.3.5 of Reference 5) 2.3.1 Atmospheric Dispersion Atmospheric dispersion (long-term) may be calculated using the appropriate form of the sector-averaged straight line-flow Gaussian model. Gaseous releases are considered to be either ground-level or mixed-mode. Considered as ground-level are releases from the turbine building (s) vents and the radwaste solidification building vent. Releases from reactor building (s)
(plant) vent (s) are considered to be mixed-mode.
2.3.1.1 Ground-Level Releases (X/Q)g =
the ground-level sector-averaged relative concentration for a given wind direction (sector) and distance. (sec/m3)
= [
2.032 d p jk "ik ( }
Nu jk x2 zk where 2.032 = (2/n)bb divided by' the number of radians in a 22.5 sector (0.3927 radians) .
dp = plume depletion factor for all radionuclides other than noble gases at.a distance x shown in Figure 2.3-2 for ground-level releases; for noble gases the depletion factor is unity. If an undepleted relative concentration is desired, the depletion factor is unity. Only depletion by deposition is considered since depletion by decay would be of little significance at the
( } distances considered.
2-75 l
l o
=
.o njk number of hours meteorological conditions are
/ I observed to be in a given wind direction, V
windspeed class j, and stability class k.
NOTE: If periodic data (hourly) are used instead of the joint frequency data, the summation over j and k is deleted and the summation is accomplished for all hours at all distances for each direction.
N = total hours of valid meteorological data throughout the period of interest.
ujk = wind speed (mid-point of windspeed class j) at ground level (m/sec), during stability class k.
x = distance from release point'to location of interest (meters).
[zk= the vertical standard deviation of the plume concentration distribution considering the initial dispersion within the building wake.
(r 2 + (b2 /2w))l/2
= the lesser of or d(tr z)
U'zk = the vertical standard deviation of the plume concentration distribution (meters) for a given distance and stability category k as shown in Figure 2.3-1. The stability category is determined by the vertical temperature
~
gradient AT/ A Z (OC/100m).
v 2-76
. _ _ _ . . _ _. _ _ . _ _ - _ _ . _ . _. _~
l Tf = 3.1416
() b = maximum height of adjacent plant structure
-(55 meters) .
2.3.1.2 Mixed-Mode Releases (X/Q)M
= the mixed-mode sector-averaged relative concentration for a given wind direction l 3
(sector) and distance (sec/m )
E
= 2.032 d p
{ Sih 3k
."jk Izk
+ l-E g exp(-h /2rzk) (39)
.where dp = plume depletio. factor for all. radionuclides other than noble gases at a distance x shown i in Figures 2.3-3 through 2.3-5 for elevated releases; for noble gases the depletion factor is unity. If an undepleted relative concentration-is desired, the depletion factor is unity. Only depletion by.
deposition is considered since depletion by decay would be of little significance at the distances considered.
Y
= wind speed extrapolated to the effective
~
Ujk release height; extrapolation is accomplished by raising the ratio of th<s two heights to the n power. where n = 0.25, 0.33, and 0.5 for unstable, neutral, and stable conditions,~respectively. (Reference 5, Section 2.3.5).
2-77
5 E = fraction considered as ground level releases 1.0 for $ 1.0 2.58 - 1.58 ( ) for 1.0 < s l'. 5 W W 0.3 - 0.06 ( ) for 1.5 < $ 5.0
, O for > 5.0 i
j Wo = vent exit velocity.(m/sec) h = effective release height (m)
= hy + h pr
-h t
-c y (40) hy = height of release point (m) ht = maximum terrain height between the release point and the point of interest (m) (See Table 2.3-1) h pr = additional height due to plume rise (m)
=
1.44d (Wo /u)2/3 (x/d)1/3 g41)
I limited by the lesser of the following two equations:
h pr(max) =
3 (W o /u)d or h pr(max) =1.5((/u) S d = inside diameter of vent O
2-78 1
. . = _ . . . . - - . . - - . . . - - . _ - = _ . . . . .
t cy 'a correction for low vent exit-velocity (m) 3 (1. 5 - ) d for 5 1.5 W
0 for > 1.5 u
= momentum flux parameter (m4 /sec )2
=
(Wo )2 (d/2)2 S = stability parameter
! 8.75 x 10-4 .sec -2 for -0.5 4 aT 1 1.5 4 = 1.75 x 10-3 sec -2 for 1.5 < a T 5 4.0 2.45 x 10-3 sec -2 for 1
A T > 4.0 All other terms were defined in Subsection 2.3.1.1.
t t
O 2-79
2.3.2 Relative D* position
'm) 2.3.2.1 Ground-Level Releases (D/Q)g =
the ground-level sector-averaged relative deposition at a given distance and for a given sector (1/m 2),
= { 2.55 D, nk k N .x (42) ,
where 2.55 = the inverse of the number of radians in a 22.5 sector (2 ff /16)-1 Dg = deposition rate at a given distance, taken from Figure 2.3-6 for ground-level releases.
nk
=
the number of hours the wind is directed into the sector of interest, during which time 4
stability category k exists.
N = the total number of hours of valid meteorological data.
((()
2-80 1
-2.3.2.2- Mixed-Mode Releases
() - (D/Q) M
=
.the mixed-mode sector-averaged relative deposition at a given distance and for a given sector (1/m 2),
l
=
((E) (D ) + (1 - E) D) e (43) where
- r Dg =
relative deposition rate for the ground-level portion of mixe'd-mode releases from Figure 2.3-6.
D, = relative depoc! tion rate for the elevated
- portion of mixed-mode releases from Figures.
2.3-7 through 2.3-9.
E =
fraction of releases considered as~ ground-level.
Other terms were defined in previous
, subsections.
V 2-81
._,,.n-, - - -- -
m
' TABLE 2.3-1
) Terrain Elevat' ion Above Plant Grade (Page 1 of j!)
Wind Direction from Plant to Receptor Distance (m) N- NNE NE ENE E ESE SE SSE' 500 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 1000 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 1500- .0.0 0.0 0.0 0.0 0.0 0.0 Ol . 0 0.0 2000 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 2500- 0.0 0.0 0.0 0.0 .0 0.0 0.0- 0.0
'3000 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 3500 10 . 0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 4000- 0.0 0.0 0.0 0.0 0.0 0.0 4.5 0.0 5000 0.0 0.0 0.0 0.0 0.0. 0.0 11.1 0.0 6000. 0.0 0.0~ 0.0 0.0 0.0 0.0 11.1 0.0 7000- 0.0 0.0 0.0 7.8 0.0 0.0 11.1 0.0 8000 0.0 0.0 21.1 13.9 0.0 0.0- 11.8 0.0 9000 0.0 0.0 .24.4 14.6 0.0 0.0 12.7 7.1 10,000 .0.0 10.2 24.4 20.2 0.0 0.0 17.1 17.0 12,000 0.0 15.9 26 .8 20.2 0.0 0.0 17.1 19.5.
14,000 0.0 15.9 26.8 20.2 0.0 0.0 17.1 19.5 16,000 0.0 15.9 26.8 21.7 13.2 0.0 17.1 19.5- '
Reference 5 2-82
TABLE 2.3-1
) Terrain Elevation Above Plant Grade (Page 2 of 2)
Wind Direction from Plant to Receptor Distance (m) S SSW SW WSW W WNW NW NNW 500 0.0 4.7 8.7 5.7 1.4 5.8 5.7 3.5 1000 0.0 4.7 16.7 13.4 3.3 10.4 11.8 6.8 1500 0.0 4.7 21.7 18.6 7.3 12.2 14.3 7.3 4
2000 0.0 4.7 21.7 18.6 7.3 12.2 14.3 7.3 2500 0.0 4.7 21.7 18.6 .7 . 3 12.2 14.3 7.3 3000 0.0 4.7 23.7 18.6 7.3 12.2 14.3 7.3 3500 0.0 4.7 24.4 18.6 7.3 12.2 16.9 7.3 4000 0.0 4.7 24.4 18.6 7.3 12.2 16.9 7 .' 3 5000 0 '. 0 4.7 24.7 18.6 7.3 12.2 16.9 7.3 6000 0.0 4.7 26.8 18.6 7.3 12.2 16.9 7.3 7000 3.6 4.7 2
'.6.8 18.6 7.3 12.2- 16.9 7.3 8000 14.6 4.7 26.8 18.6 7.3 12.2 16.9 7 . 3..
9000 14.6 5.1 26.8 18.6 7.3 12.2 16.9. 7.3 10,000 14.6 6.8 26.8 18.6 7.3 12.2 16.9 7.3 12,000 14.6 6.8 34.1 28.9 13.4 12.2 16.9 7.3 14,000 14.6 6.8 34.1 28.9 .13.4 16.5 19.7 7.3
_16,000 14.6 6.8 34.1 28.9 13.4 16.5 25.7 7.3 I
4 i'
i 2-83 l
FIGURE 2.3-1
' Vertical Standard Deviation of Material in a Plume (O'g)
(Letters Denote Pasquill Stability Class) sees
. f . :-
l l . 1 /
- i . / '
l l /~ s
/:
/ / / 'll
,0,
/ / - -
/ :
/y
~~~
's _-
1 i / -- 7 s
. <.; -, - -i . .. - ,. .
t A yt 6xm /6 / . 66y 6 s ,w E- V VI A i W / I M lit i 7 ? s it
! /
/l/M lj#iV / IM llill
/ / /
/
/ i
/
/
l
,,u
^
-//-
/ c/
- : '~
I
,s'~ ,1 j,/ , ,
/ . / . v, i. ,ii . , ,iiii., , , . . . . .
,/t fi I ii til I I i i lilil I i i i t I ti
// Il 'l l l 'll l l l lllll
/
0.1 1.0 10 100
' PLune: TMAVEL DISTANCE (KILOMETER $1 Range of Vertical Range of Vertical Catecory Temperature Gradient (*C/100m) Temperature Gradient ( F/100ft)
A AT/aZ <--1.9 AT < -1.0 B
-1.9 5 t T/az < -1.7 -1.0 $ AT < -0.9 C
-1.7 5 AT/aZ < -1.5 -0.9 < AT < -0.8 0
-1.5 5 AT/a2 < -0.5 -0.8 5 AT < -0.3 E
-0.5 5 AT/aZ < 1.5 -0.3 $ AT < 0.8
.F 1.5 5 AT/aZ:< 4.0 0.8 5 AT < 2.2 G.
4.0 $ AT/aZ 2.2 5 AT s
Reference 7 2-84
FIGURE 2.3-2
'(, j - Plume ~ Depletion Effect for Ground-Level Releases (All Atmospheric Stability Classes) l 1.0 0.9 ' A O.8 N
b"'
e
\'N s 2 0.7 N A-0 2
E ' O.6 \
h \
5 0.5 50.4 \
V e
0.3 0.2 0.1 i
0.1 1.0 10.0 100.0 200.0 PLUME TRAVEL DISTANCE (KILOMETERS)
( ,) Reference 7
. 2-85
g.
. FIGURE 2.3-3
( ) Plume Depletion Effect'for 30-Meter Releases (Letters Denote P1 squill Stability Class) 1.o o.9 % NEUT AL( E, G) m 0.8 IA o.7 5
E 30.6 UNSTA34 % N BLE (A.B.C) -
,\ '(
- s o.s \
9 y\ s
- o.4 s' i 0.3
\\
0.2 0.1 4
I o.1 1.o 10.0 1oo.o' 200.o; PLUME TRAVEL DISTANCE (KILOMETERS)
[\,
(._,) Reference 7 i
2-86 a
y FIGURE 2.3-4 l \
\_ ,/ Plume Depletion Effect for 60-Meter Releases (Letters Denote Pasquill Stability Class) 1.0
. STABLE Q
- '% s (E.F,G) j 0.9 A NEUTRAL 3 h 2
~
0.7 UNSTABLE
\ %
o (A,B,C) >g h 0.6 L \
a ^
E \
p 0.5 \
z ;
o 5 50.4 4
\
5 0.3 0.2 0.1 0.1 1.0 10.0 100.0 200.0 PLUME TRAVEL DISTANCE (KtLOMETERS) p_. .
's. Reference 7 2-87
FIGURE 2.3-5
? 4
\s/ Plume Depletion Effect for 100-Meter Releases (Letters Denote Pasquill S.tability Class) 1 1.0 0.9 '
% m NEUTR AL (D)
~
= 0.s E
~- ,
\x\\
UNSTABLE
$ 0.7 A,B,C)
- q. % g, G STABLE (E.F G) Ns h 0.6 'N \ \
h
. E 0.5 (FRACTION REMAINING = 1.0) \
k \
5 \
h 0.4 \
.s 0.3 0.2 0.1 0.1 1.0 10.0 100.0 200.0 PLUME TRAVEL DISTANCE (KILOMETERS)
['N _
x___. Reference 7 2-88
FIGURE 2.3-6 s
7.
(,) Relative Deposition for Ground-Level Releases (All Atmospheric Stability Classes) 10-3 ,
10-4 N
k mg
=
A
' N m %t r
- wA W N
< N m
$ 10-5 N
p \ '
5 \; . .
O N !
$ X! l C
w XI
> wt i N
P T
\
m %
10-6 x
l l
10-7 0.1 1.0 10.0 100.0 200.0
- r'x PLUME TRAVEL DISTANCE (KILOMETERS) ks Reference 7 2-89
FIGURE 2.3-7
) Relative Deposition for 30-Meter Releases (Letters Denote Pasquill Stability Class)
~
104 i;.
UNSTABLE (A,B.C) 10-4 ^l iI!ll h,_ f f l i
!ll yi
- . i W i i '
N h I f! h y [ \\ NEUTRAL
< /
/ NN
\ \
c w w 2
i NEUTRAL (D) g5 gN 10-5 ,
l I I
_Q STABLE.
8
- c. /
i ,
1 w
i 6/ Y xA .
i
$ 1 1 i/! h I\
w /l i I fli N W X' .
5 /t ri x! A a / / NJ h i l l \d \
10-6 ,ST, iA, BL, E (E,F,G)
, l l
I ~'
N I 6 *
- l e 1 l I 6 I
I !I6 1 I I 1 Ill
/ ! l
/ l 20-7 0.1 1.0
[
10.0 100.0 200.0
,, ~-3 PLUME TRAVEL DISTANCE (KILOMETERS)
(,) Reference 7 2-90
FIGURE 2.3-8 (d) x Relative Deposition for 60-Meter Releases l
(Letters Denote Pa' squill Stability Class) 10-4 I
e : w UNSTABLE (A,B,C) l
[ \ '
)
/ N %
[
/ L 10-5 / NEUTRAL (D) Q'%g
/ i /
t 2y /
/
/
/
1
,T .;
i A- ii H / / NN ll
$ / \ N A UNSTABLE 5 / \l MI
! NEUTRA \
s / N N
$ 10-6 m
i:
I i i i
i a ~
o I i i i 6
6
! rf t/ t b i ,
t e a I (
s / /
E d
J /
I 10-7 STABLE (E,F,G)
- r I
1 l
f.
I I
I '
I f Il l l
f 10-8 i 0.1 1.0 10.0 100.0 200.0 PLUME TRAVEL DISTANCE (KILOMETERS) f~\
ss
/ Reference 7 2-91 m
FIGURE 2.3-9 7~
! \
(_,) Relative Deposition for 100-Meter Releases (Letters Denote Pasquill Stability Class) 104 l i i , l .
I e
.- 4 I l
UNSTABLE (A B.C) l l
x
\ N 10-5 ; As j ,' '% h ,
E / /I '
i 6
/ '
NN y f I
f NEUTRAL (D) y,y ,
i y /
= / /
/
\%.'
N t s
2
/ / R x Ns g
10-6 )
/ / e g ; :
o I I iit g I f i!i a / / Ii s / / i
/
y STABLE (E,F,G)
NO DEPLETION 10-7 ; I I !
,!,; : . ,;L
/ I I
'l II
/
[l 10-8 1 0.1 1.0 10.0 100.0 200.0 r~s PLUME TRAVEL DISTANCE (KILOMETERS)
/ i
'y/ Reference 7 2-92
t 2.4' DEFINITIONS OF GASEOUS EFFLUENT TERMS j m) Subsection of Term Definition Initial Use
, AG =
administrative allocation factor for 2.1.1 gaseous effluent pathways.
BR. = -breathing rate for individual from Table 2.2-10. 2 . 2 .-l . 2 b' = maximum height of the adjacent 2.3.1.1 building.
C m_ = m nitor response of a noble gas monitor 2.1.1 corresponding to associated grab sample radionuclide' concentrations. '
c s- = m nitor reading of the noble gas 2.1.1 monitor at the alarm setpoint concentration.
cy =
correction to effective release height due to low vent exit velocity. 2.3.1.2 DTB = limiting dose rate to the total body 2.1.1 of an individual in an unrestricted area which is 500 mrem / year.
Dt = total body dose rate at time of 2.2.1.1 release (mrem /yr) . '
D ss = : limiting dose rate to the skin of 2.1.1 an individual in an unrestricted area which is 3000 mrem / year.
Ds =
skin dose rate at time of release 2.2.1.1 (mrem /yr).
(
2-93
2.4 DEFINITIONS OF GASEOUS EFFLUENT TERMS (Continund)
.s Subsection of
) Term Definition Initial Use (G
.D o = organ dose rate at time of release 2.2.1.2 (mrem /yr).
DF io = inhalation pathway dose factor for 2.2.1.2 child age group for organ o and
-radionuclide i (mrem /pCi inhaled) from Table 2.2-2.
D beta =
air dose due to beta emissions from 2.2.2.1 noble gases (mrad).
D gamma = air dose due to gamma emissions from 2.2.2.1 noble gases (mrad).
D = dose to an organ of individual from 2.2.2.2 radioiodines, tritium, and radionuclides in particulate form with half-lives greater than eight days (mrem).
(DFAi j)a =
the inhalation dose factor for the ith 2.2.2.2 radionuclide for the receptor in age group a (mrem /pci) from Tables 2.2-1
, through 2.2-4.
= ground plane dose conversion factor DFGi j 2.2.2.2 for radionuclide 1 (same for all age groups) (mrem /hr per pCi/m2 ) from Table. 2.2-9.
(DFLi j)a = the organ ingestion dose factor for 2.2.2.2 the ith radionuclide for the receptor in' age group a (mrem /pCi) from Tables
[d \ 2.2-5 through 2.2-8..
2-94
2.4 DEFINITIONS OF GASEOUS EFFLUENT TERMS (Continued) g 3' Subsection of
$ l Term Definition
\_/ Initial Use dp = plume depletion factor for all 2.3.1.1 radionuclides other than noble gases at distance x.
d = inside diameter of plant vent 2.3.1.2 Dg = deposition rate for ground-level 2.3.2.1 releases D, = ' deposition rate for elevated releases 2.3.2.1 E =
fractionaof release considered to be 2.3.2.1 ground-level f
t
=
fraction of the annual intake of fresh 2.2.2.2 leafy vegetation grown locally (dimensionless).
f g
=
fraction of annual intake of-stored 2.2.2.2 vegetation grown locally (dimensionless).
f = fraction of the. year that the cow p 2.2.2.3 (or goat) is on pasture (dimensionless).
f = fraction of the cow (or goat) feed s 2.2.2.3 that is pasture grass while the cow or goat is on pasture (dimensionless) .
Ff' =
the stable element transfer 2.2.2.3 coefficient for meat (days /kg) from
- Table 2.2-11.
(__J '
2-95
i 2.4 DEFINITIONS OF GASEOUS EFFLUENT TERMS (Continued)
Subsection of
':/ ~.\ ~ Term Definition Initial Use V-F, = the stable element transfer. 2.2.2.3 coefficient for milk (days / liter) from Table 2.2-11.
Fy = momentum flux parameter 2.3.1.2 Fy = maximum expected release flow rate 2.1.1 through a particular release point (ml/sec) from Table 2.1-2 H = absolute humidity of the atmosphere 2.2.2.2 (gm/m 3 ),
h = effective release height (m) 2.3.1.2 h y_ = height of release point (m) 2.3.1.2 ht = maximum terrain height between the 2.3.1.2 release point and the point of interest (m) h pr = additional height _due to plume rise 2.3.1.2 (m)
Ki = total body dose factor ~due to gamma 2.1.1 emissions from radionuclide -i (mrem / year per uCi/m3 ) from Table 2.1-1.
K' = constant of unit con' version, 2.2.1.2 106 pCi/uCi.
K" = constant of unit conversion, 8760 2.2.2.2 hr/ year.
T
- (J 2-96
i
=2.4 DEFINITIONS ~OF GASEOUS-EFFLUENT TERMS (Continued) i j
Subsection of
[~'Y Term' Definition Initial Use
. \ ,)
K'" '= constant of unit conversion, 103 gm/kg 2.2.2.2
- - Lg; =
skin dose factor due to beta emissions 2.1.1 from radionuclide i (mrem / year per ,
f uCi/m3 ) from Table 2.1-1.
Mi =
air dose factor due to gamma emissions' 2.1.1 from radionuclide 1 (mrad / year per uCi/m3 ) from Table 2.1-1.
Ni =
' air dose factor due to beta emissions 2.2.2.1
} from noble gas radionuclide 1 (mrad / year pe'r uCi/m 3 ) from Table 2.1-1.
n =. the number ~of simultaneous gaseous 2.1.5 release pathways.
njk =
number of hours meteorological 2.3.1.1 conditions are observed to be in a given wind direction, wind-speed
~ class j, and atmospheric stability-
- . class k.
N =
total hoursaof valid meteorological 2.3.1.1
! data.
Pio ' =
dose parameter for radionuclide i, 2.2.1.2 (mrem /yr~per uC1/m 3 ) for the inhalation pathway.
=
Qig Source term for ground-level release 2.1.1 noble gas radionuclide 1 (uCi/sec)
( Qim '=
Source term for mixed-mode. release 2.1.1 2-97
-e
2.4 DEFINITIONS OF GASEOUS EFFLUENT TERMS (Continund)
Subsection of
.[3}
. u'-
Term Definition Initial Use noble gas radionuclide 1 (uCi/sec)
= source term for ground-level release Qi 'g (r) 2.1.5 noble gas radionuclide i~from a specific release point (uci/sec)
Qim(r)
=
source term for mixed-mode release 2.1.5 noble gas radionuclide i from a specific release point (uci/sec)
= source term for ground-level release Q{g 2.2.1.2 radiciodine, tritium and particulate radionuclide i (uci/sec)
O'{m =
source term for mixed-mode' release 2.2.1.2 radiciodine, tritium and particulate radionuclide i (uCi/sec)
Q ig- = cumulative ground-level. release of 2.2.2.1 noble gas radionuclide i (uCi)
Qim =
cumulative mixed-mode release of noble 2.2.2.1 gas radionuclide'i (uCi) 6{g = cumulative ground-level release of 2.2.2.2 radioiodines, . tritium and particulate radionuclide 1 (uCi)
Im i
=
cumulative' mixed-mode release of 2.2.2.2 radiciodines, tritium and particulate radionuclide i (uCi)
Op =
Feed consumption rate for cow or goat 2.2.2.3 (kg/ day)
. ,O v
2-98
3 2.4 DEFINITIONS OF GAGCOUS EFFLUENT TERMS (Continued) r s Subsection of.
-[~') Term Definition Initial Use
\_ / =
qi noble gas source term for the Gaseous 2,1.3.1
- Waste Processing System-or Containment and 2.113.2 s purge (uCi/sec) '
Rt = monitor reading per mrem /yr to'the 2. l'.1
' total body for vent releases.
R3 = monitor reading per mrem /yr to the 2.1.1 skin'for vent releases.
s rt.
= monitor' reading per mrem /yr to the 2 .1. 3 ', 1
' total body for Gaseous Waste Processing System or Containment purge releases. -
r s
=
m nitor reading per mrem /yr to the 2.1.3.1
~ skin for Gaseous Waste Processing System or CBnta'inment purge releases.
.a .
R alpj = pathcay-specific, individual 2.2.2.2 age-specific, organ dose" factor for radionuclide i, pathway p,.. organ j, and age group a, (mrem /yr'per uCi/m3) or (m 2-mrem /yr per uCi/sec).
r = fraction of deposited radionuclide 2.2.2.2 retained on vegetatlon. ;s _.
y -. ~ -
SF = . safety factor used to introduce a 2.1.1 <
margin of conservatism into se(point '
calculations. -
/
SF' = shielding factor afforded by structure 2.2.2.2
(~') S = stability parameter "2.3.1.2.
\_/ -
2-99 s
1 a A
/ - _ _., - - - - .
2.4 DEFINITIONS OF GASEOUS EFFLUENT TERMS (Continued)
,_s .
Subsection of 1
'i Term Definition Initial Use U
t = exposure time for radioactivity 2.2.2.2 deposited on ground t1 = time between harvest of leafy 2.2.2.2 vegetation and consumption
.t hy =
time between harvest of stored 2.2.2.2 vegetation and consumption t = transport time from feed to receptor hm 2.2.2.3 for stored feed tg =
transport time from feed to receptor 2.2.2.3 for pasture grass U ap = receptor's milk (liters / year) or meat 2.2.2.3 (kg/ year) consumption rate for age group a f rom Table 2.2-10.
r U as = consumption rate of stored vegetation 2.2.2.2 by the receptor in age group a (kg/ year) from Table 2.2-10.
U al = consumption rate of fresh leafy 2.2.2 2 vegetation by the receptor in age group a (kg/ year) from Table 2.2-10.
ujk = .wind speed (midpoint of windspeed 2.3.1.1 class j) at ground level (m/sec) during atmospheric stability class k.
- u r
i%
2-100 i
s s .I 12.4 DEFINITIONS OF GASROUS EFFLUENT TERMS (Continued) ;
\'
/
Subsection of h
G Term Definition Initial Use Ujk = wind speed (midpoint of wind speed 2.3.1.2 class j) at the height of release, h, of an elevated release during atmospheric stability class k.
W/;p = pathway-dependent relative dispersion 2.2.2.2 or deposition for ground-level releases
-at the location of the critical receptor.
=
Wb pathway-dependent relative dispersion 2.2.2.2 or deposition for mixed-mode releases at the location of the critical receptor.
x = distancefromreleasepointtopoibt 2.3.1.1 of interest.
i-Yy = vegetation areal density (kg/m )2 . 2.2.2.2 Yp = agricultural productivihr by unit area 2.2.2.3 of pasture feed grass % 112) , p 1
Ys = agricultural' productivity by unit area 2.f.2.3 of stored feed (kg/m 2).
(X/Q)g
=
W mdmg 2M concentration for a ground-level release type (sec/m 3 ),_
/
= highest annual average relative 2 .1. 2, gjg) concentration for a mixed-mode '
release type (sec/m 3),
D U
' l 2-101 / I
2.4 DEFINITIONS OF GASEOUS EFFLUENT TERMS (Continued) i Subsection of i Term Definition Initial Use LI
= annual average relative concentration 2.2.2.2
. X/Q')O for location of controlling (critical) receptor for inhalation and all tritium pathways for a ground-level release type (sec/m 3),
(X/Q')M for location of controlling (critical) receptor for. inhalation and all tritium pathways for a. mixed-mode release type (sec/m 3),
A- i
= decay constant for the ith 2.2.2.2 radionuclide (sec-1).
'Ag =
decay constant for removal of activity 2.2.2.2
^
on leaf and plant surfaces by weathering zk =
the vertical standard deviation of the 2.3.1.1 plume concentration distribution
, considering the initial-dispersion
,, within the building wake.
O~zk
=
vertical standard deviation of the 2.3.1.1 plume (in meters), for a given distance-under the stability category k i indicated by A T/ A Z from Figure 2.3-1.
4 T/ A z = vertical temperature gradient used to 2.3.1.1 determine the atmospheric stability N,
category ( C/100m or F/100 f t. )
O 2-102
, g <I '
- )$
ta
f 2.4 DEFINITIONS OF GASEOUS EFFLUENT TERMS (Continued) l Subsection of T e rm, . Definition Initial Use l
' X iy =
concentration-of radionuclide i for 2.1.1 l
I the particular. vent release ~ pathway.
under consideration (uci/ml) .
i t
4 i
F A
i e
i
,t-2-103 i
t
..:-+ = , , - . . . - , . . .,.-. - - . - - - . _a__., ,, . . , , - . - - . . . . . - _ . , , --
.. . . . _ . . . _ _ __ _ _.._ _ _ _ _. . . - _ . . . _ _ _ . - _ - _ . _ . . _ . ~ . _ _ _ . . . _ . _ . _ . _ _ . _ _ . . _ . _ . ._.__-- --_ _ . . _
l 2.5 GASEOUS RADWASTE TREATMENT SYSTEMS l
Figures 2.5-l', 2.5-2, 2.5-3, and 2.5-4 present
. schematics of the Gaseous Waste Processing System and 1
Ventilation Exhaust Treatment Systems. (Reference 5) i a
i a
4-p-
4 t e t
f i
2-104 i
?
s i
Lm , - . ,,, -n- , ,o m _ , . . , , - --.,,---------n..m,. +n-.,, - , . . -,~- g.,,. - , , , , , - - ,- - - , , p-w p----p-- , .- - , , - . ~ ~ . - - -. - .. .
FIGURE 2.5-1 I
.( Gaseous Waste Processing System (Typical of both ' units.. However, Unit 2 GWPS releases via Unit 1 plant vent.)
addtoactivity ARE-0014 Monitor % To Unit 1 Plant Vent via Ausillary Butiding gentilation Systase lI Catalytte 4, 4 - haste Gas Reco*D to Chemical volume a
Compre s s,, and Gas'ner .
% . Control Tant .
g Analyter
, Package 8
3 e
l l l* + fo haste Gas Decay pl,
, I ,
, Tant needer L.________h ,__,pg, , j 4 !o haste Gas : '" '
haste Gas Decay Iant May Iant (Shutdown)
(Seven per Unit)
(Te sured) i a
/ volume Control / Fra unit 2 Waste N Tank Purge ~ N Gas Decay fonts
/ necycle tvasorator N vent Consenser
/ waste tvaoorator N . vent Consenser
' / secycle nolduo N fant Eductor
/ neactor Coolant N Dratn fant
- Dotted line operational between 20 and 100 psig b
2-105
FIGURE 2.5-2
/m
( i
' %./ Ventilation Exhaust Treatment System (Plant Vent) '
L (Typical of both units. However, all Gaseous Waste
- Processing System and Fuel Handling Building releases are via Unit 1 plant vent.)
Plant Vent
.[
O Radioactivity Monitor RE12442A.B.C HEPA HEPA HEPA l l
. HEPA l HEPA l HEPA l l HC Radioactivity HC Auxiliary- O Monitor l-Building RE0039A i
_ l ME Radioactivity Mon'itor RE2565A.B.C From Waste Gas Processing Fuel Handling
- Area and System Building (Shared)*
Reactor Containment Building HEPA -High Efficiency Particulate Air Filter CF -Activated Charcoal Filter HC -Heating Coil .
ME -Holsture Eliminator
- Prior to treatment by the Fuel Handling Building Ventilation Exhaust Treatment ARE25338; exhaust from Unit 2 Spent Fuel Pool Area is monitor and ARE2533A.
O 2-106
FIGURE 2.5-3 f$ .
1 Ventilation Exhaust Treatment System (Turbine Building) '
(Typical of both units)
Turbine Building Vent Radioactivity Monitor RE12839A,B.C
- t 4
HEPA HEPA l
- CF CF l
l HEPA HEPA l
l HC HC I
DE DE
- 7. NO - NC
~[NO NC
-Steam Jet Air Ejector Steam Packing Exhauster l-HEPA -High Efficiency Particulate Air Filter CF
-Activated Charcoal Filter HC -Heating Coil DE -Demister NO --Normally Open NC -Normally Closed -
1 i
O l 2-107
~ FIGURE 2.5-4 l
n
' Ventilation Exhaust Treatment System (Radwaste Solidification Building) '
(Common to both units)
- ' - Redwaste Solidification Building Vent 7
i f
!- C Radioactivity Monitor ARE0026A,B.C i '
- - HEPA- HEPA I
PF HC l
pp- Low Contamination Areas Volume Reduction Process Off-gas Process Area 4
HEPA -High Efficiency Particulate Air Filter CF -Activated Charcoal Filter PF -Prefilter HC - -Heating Coil t
4
(
4 1
2-108 l
r v-. w , - - , , , ,, . . . - . , - , , . , , , , , , , , - , , , , , , ~ . - , - - - , - - . , . , , ,. .- , . ~ ,. - - . . , . . , , - . ~ . - - , , - - . - -
I SECTION 3.0 RADIOLOGICAL ENVIRONMENTAL' MONITORING PROGRAM Rad,iological-environmental sampling and' monitoring
~
locations are described in Table'3.0-1 and shown on maps in Figures 3.0-1, 3.0-2, 3.0-3, and 3.0-4 as required by Technical Specifications 3.12.1 and 4.12.1.
4.
1 1
1 4
4 k
4 5
1 1
1 2
I 3-1
TABLE 3.0-1 RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS
(
LOCATION DESCRIPTIVE DIRECTION DISTANCE SAMPLE NUMBER LOCATION (MILES) TYPE 1 Hancock Landing Road il 1.1 D
'2- River Bank NNE' O.8 D 3 River Bank NE 0.7 D 4 River Bank ENE 0.8 D 5 River Bank E 1.2 D 6~ Plant Wilson ESE 1.1 D 7 Simulator Building SE 1.5 D,V,A 8 River Road SSE 1.1 D-9 River Road S 1.1 D 10 Met Tower SSW 0.75 A River Road 1.1 D 11 River Road SW l.2 D 12 River Road WSW 1.1- D 13 River Road W 1.3 D 14 River Road WNW l.8 D 15 ~Hancock Landing Road NW l.5 D,V 16 Hancock Landing Road NNW l.4 D,A 17 Savannah River Plant 9- River Road N 5.4 D 18 Savannah River Plant D Area NNE 5.0 D
'19 Savannah River Plant Road A.13 NE- 4.6 D 20 Savannah River Plant
- . Road A.13.1 ENE 4.8 D H21 Savannah River Plant 4
Road A.17 E 5.3 D 22 River Bank Downstream of Buxton Landing ESE 5.2 D
(~') 25 Chance Road and Highway 23 S 5.2 D V
3-2
c_ TABLE 3.0-1 (Continued)
RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS LOCATION . DESCRIPTIVE DIRECTION DISTANCE- SAMPLE
-NUMBER' LOCATION (MILES) TYPE s
26 Highway 23', mile 15.5 SSW .4.6 D 27 Highway 23, mile 17 SW 4.8 D u 28 Claybon Road WSW 5.0 D L29 ; Claxton-Lively Road W 5.0 D
.30 Ben Hatcher Road WNW 4.7 D 31 1 River Road at Allen's
, a Church Fork NW 5.0 D 32 River Bank NNW 4.8 D 133 Nearby Residence SE- 3.3 D 34- - Girard Elementary School SSE 6.3 D H35 Girard SSE 6.6 D,A 36 Waynesboro WSW 15.0 D,A 37 Substation (Waynesboro) WSW 17.5 D,V (North Side of Road) 38 l Substation.(Waynesboro) WSW 17.5 D.
1 (South Side.of Road) 43 Employees Recreation Area SW 2.2 D 80 North Augusta Wa'ter Treatment Plant Upstream 51 W 81 Savannah River (mile.153.1) Upstream 2.2 R,S,F(2) 82 Savannah River-(mile 151.2) Upstream 0.2 R,S (3) 83 Savannah River (mile 150.4) ' Downstream 0.6 R 84 Savannah River (ml]e.149.5) Downstream 1.5 L R,S (3)
- 85. Savannah River - (mile 146.7) Downstream 4.3 R,F(2) 87 Beaufort-Jasper Wtter Treat-ment Plant; Beaufort, S.C. Downstream 112 ,'W 88 Cherokee Hill Water Treatment Plant;. Port Wentworth, Ga. Downstream 122 W 98 W. C. Dixon Dairy SE 9.8 M O
3-3
4
. TABLE 3.0-1 (Continued)
- -RADIOLOGICAL. ENVIRONMENTAL SAMPLING LOCATIONS TABLE NOTATION:
(1) -Sample Types A.- Airborne Radioactivity D - Direct Radiation M - Milk R - River Water S - River Shoreline Sediment W - Drinking Water.(at water
' treatment plant)
V - Vegetation
. (2)' These arefapproximate locations'for. fish sampling. It is generally necessary to-cover a' stretch of river up to five miles to obtain an adequate fish sample.
m
- (3) These are approximate locations for sediment sampling. High.
~
water may sometimes cause an otherwise suitable location for sediment sampling 1to be unavailable.
0 0
3-4
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FIGURE 3.0-3
,3
'-! Terrestrial Stations beyond Five Miles
( -
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woooi..a s,,,,,
,/ Graniteville Aiken i2 5+aar -
218 North 's '
ugusta 25 MILE RADIUS
Langley 3, 78 s.,.., n..
COLUMBIA CO. ,/ .
AIKEN I
'AU A """* ! ' no
. 78 y 278 New w e ., .
. : ,(* Ellentonn
/ 278 3 o e..c. i. 278 illist 83 .
c, .< .. a to j/' 278 , 4 3 l.
/
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o.8,w<.
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is . ,5 , uoor ,, i
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t r "ae*
, 25 i ,'-
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'U' t u,a,,,
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SCREVEN CO.
s.a. nn.n \, ' 'a**'
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3-7 1
I
- -._ ~_ -
FIGURE 3.0-4 Drinking Water' Stations NORTH AUGUSTA 180) WATER TREATMENT PLANT SAVANNAH RIVER PLANT .
VEGP (
N-
. )
Canal to Supply River Water to Beaufort hj \
Beaufort-Jasper County i Water Treatment Plant R .-
g8 EAU GEORGIA g p
.c .
5 in
,,4 s
c 0 10~ 20 30 CHE ROKEE HILL E p $
' WATER TREATMENT 96 PLANT 4 4 (PO'RT WENTWORTHI D SAVANNAH O O
3-8
l I
fh
'~
SECTION 4.0 TOTAL DOSE DETERMINATIONS Technical Specification 3.11.4 addresses the requirements of 40 CFR 190 and 10 CFR 20.105 (c) , which pertain to limitation of' annual doses to a member of the public from nuclear fuel cycle facilities. No other nuclear fuel cycle facility is located within five miles of' Plant Vogtle. Therefore, it is only necessary to include doses from the two Plant Vogtle units in the
' total dose determinations.
For the purpose of implementing Technical Specification 3.11.4, total dose determinations will be made by calculating doses due to liquid effluents in accordance with Technical Specification 3.11.1.2; by calculating doses due to gaseous effluents in accordance with 3.11.2.3; and by combining direct radiation doses based on direct radiation measurements with these effluent doses to determine total dose to a real individual.
Methodology for calculating individual doses due to liquid effluents was presented in Subsection 1.2. Methodology-for calculating individual doses due to. gaseous effluents was presented in Subsection 2.2.2.2.
O 4-1
,x k ~
]
SECTION 5.0 POTENTIAL DOSES TO MEMBERS OF ' THE PUBLIC
.DUE TO THEIR ACTIVITIES INSIDE THE SITE BOUNDARY For.the purpose of implementing Technical Specification 6.9.1.9, an assessment of potential doses to MEMBERS OF THE PUBLIC due to their activities within the SITE BOUNDARY will be performed if circumstances have changed such that any of the
. limits of Technical Specifications 3.11.2.2 or 3.11.2.3 are exceeded. The locations of interest within th5 SITE BOUNDARY at
-Plant Vogtle are the Visitors Center and Plant Wilson. (Plant Wilson is owned and operated by Georgia Power Company, but individuals working at Plant Wilson are not directly associated
.with Plant'Vogtle. Therefore, those individuals are considered in this dose determination as a precautionary measure.)
The. annual average atmospheric dispersion and deposition' values for these two locations and the expected occupancy factors, by an individual during the year, are as follows:
Location X/0(sec/m3) D/0(m-2) Estimated Occupancy Factor (by an individual during a year)
Visitors Center 6.98E-6 3.64E-8 0.00046 (4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />)
Plant Wilson 9.64E-6 3.56E-8 0.228 (2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br />)
In the event that any' limit of Technical Specification 3.11.2.2 is exceeded, an assessment will be performed considering direct radiation dose to an individual resulting from submersion in the plume. This assessment will take into consideration the annual average dispersion parameters and the estimated occupancy factor stated above, or a more precise value.if available, for the locations of interest.
In the event that any limit of Technical Specification 3.11.2.3 is. exceeded, an assessment will be performed considering
['\- )' ' the dose to an individual due to inhalation of airborne radioactive materials suspended in the plume and due to direct 5-1
^
'gN !
L .)
radiation from radioactive materials deposited on the ground.
This assessment will take into consideration the annual average dispersion and deposition parameters and the estimated occupancy factors stated above, or a more precise value if available for the location of interest.
If none of the limits discussed above is exceeded, potential annual doses to an individual at the Visitors Center are not expected to exceed 0.023 mrem to an organ due to inhalation and ground-plane or 0.009 mrem to the total body due to direct radiation from the plume. Likewise, potential doses to an individual at Plant Wilson are not expected to exceed 11.6 mrem to an organ due to inhalation and ground-plane or 6.3 mrem to the total body due to direct radiation from the plume.
These values are based on annual average dispersion and deposition parameters and the estimated occupancy factors stated above. The occupancy factor for the visitors Center is based en anticipated usage; the occupancy factor for Plant Wilson is based on a standard forty hour work week, assu:oing that an individual is assigned to the facility for the entire year.
l n
V 5-2 j
l i
I i
f b'N : SECTION 6'.0-U INTERLABORATORY COMPARISON PROGRAM
~
For the purpose of implementing Technical Specification - 3.12'3, Plant Vogtle will participate'in the Environmental
- Protection Agency's Environmental Radioactivity Laboratory Intercomparison Studies (Crosscheck) Program conducted by the
~
Environmental Monitoring and Support _ Laboratory in~Las Vegas, Nevada or in an equivalent program'which has been approved by the
'NuclearLRegulatory Commission.
Those sample media and analyses'specified in Technical Specification Table 3.12-1 and available in the EPA
~
Intercomparison. Studies Program will be included in'the
, crosscheck program for Plant Vogtle. For analyses performed by a contract vendor, the crosscheck analyses will be performed by
- that vendor. Participation-in the crosscheck program is as follows:
Sample Medium Analyses Performed Air filters Gross beta; gamma isotopics Water H-3; gross beta; gamma isotopics Milk I-131; gamma isotopics A summary showing the results obtained from Plant Vogtle's participation in.the crosscheck program will be included in the Annual Radiological Environmental Surveillance Report as
. required by Technical: Specification 4.12.3.
w 6-1
( - - - . - - - .
f' Georgis Power Com'pany
- D. Rout) ?. Box 299A - '~ * .
- Wrynesboro. Georgia 30830 -
, Telephone 404 554 9961 -
~4 04 724-8114 s
- Southern Company Services, Inc.-
' u Post Office Box 2625
, Birmingham, Alabama 35202 Telephone 205 870-6011 Vogtle Project w
k
-December 9,-1985-
. ' Director of-Nuclear Reactor Regulat' ion File: X7BC35
- Attention: -Mr. B. J. Youngblood . Log: GN-757 PWR-Project Directorate #4 1 Division ofLPWR Licensing A' U.:S. Nuclear. Regulatory Commission Washington, D.C. 20555
~
NRC: DOCKET NUMBERS 50-424 AND 50-425 CONSTRUCTION PERMIT NUMBERS CPPR-108 AND CPPR-109
'V0GTIE ELECTRIC GENERATING PIANT - UNITS 1 AND 2 0FFSITE DOSE CALCULATION MANUAL (ODCM)
Dear Mr. Denton:
Dtiring the September 11, 1984 Technical Specification meeting a reques't was made by your staff to provide the subject document. As agreed to in the
- meeting-the ODCM is herein provided for your staff's review one year prior to fuel load.
If you' staff requires any additional information,' please do not hesitate to contact me.
' Sincerely, J.'A.! Bailey Project. Licensing Manager ,
~ JAB /sm-
~
-Enclosure L' 'xc: R.' E. Conway- G. Bockhold, Jr.
R. A. Thomas- T. Johnson (w/o enclosure)
J. E. Joiner, Esquire . D. C. Teper (w/o enclosure)
B. _W. Churchill, Esquire L. Fowler M., A. Miller, (2) W. C. Ramsey B. Jones (w/o enclosure) Vogtle Project File L.'T. Gucwa (w/o enclosure) f
~
0263V
' 6$
AD i J, Knight (Itr '"III -
ES (BALLARD) h
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L~ EIC58 (ROSAI rsa (GA*81LLI ass tegnLIMcE8) 70s (BEMAROTAI a- :. -