ML20210A829
| ML20210A829 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 03/31/1987 |
| From: | Gucwa L GEORGIA POWER CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| PROC-870331, SL-2423, NUDOCS 8705050171 | |
| Download: ML20210A829 (176) | |
Text
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1 3
OFFSITE DOSE CALCULATION MANUAL i
FOR i
GEORGIA POWER COMPANY VOGTLE ELECTRIC GENERATING PLANT REVISION 3 L
MARCH 1987 4
4 a
4 8705050171 870331 PR ADOCK 05000424 P
PDR U
ii
TABLE OF CONTENTS PAGE
' List of Tables v
List of Figures vil i
References ix Introduc tion xi 1.
Liquid Effluents 1-1 1.1 Liqui,d 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
1.1.1.2 Monitor Setpoint Calculation Methodology When Two Waste Monitor Tanks Per Unit Are to i
Be Released at a Time 1-14 1
1.1.2 Steam Generator Blowdown Ef fluent Radioactivity Monitor; Turbine Building Drain Effluent Radioactivity Monitor; and Control Building Sump Effluent Radioactivity Monitor 1-18 i
o
TABLE OF CONTENTS (Cont-)
PAGE 1.1.3 Nuclear Service Cooling Water System Ef fluent Radioactivity Monitor 1-20 1.2 Dose Calculation for Liquid Effluents 1-20 1.3 Dose Projections for Liquid Effluents 1-31 1.3.1 Thirty-One Day Dose Projections 1-31 1.3.2 Dose Projections for Specific Releases 1-32 1.4 Definitions of Liquid Effluent Terms 1-33 1.5 Liquid Waste Processing System and Liquid Discharge Pathways 1-38 2.
Gaseous Effluents 2-1 2.1 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 2.1.3.1 Gaseous Waste Processing System 2-8 2.1.3.2 Reactor Containment Purge 2-10 ii
=as TABLE OF CONTENTS (Con t. )
PAGE 2.1.4 Consideration of Background and Monitor Response Adjustments in Establishing Gaseous Effluent Monitor Setpoints 2-12 2.1.5 Determination of Allocation Factor, AG 2-13 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 Radioiodines, Tritium, and Particulates 2-18 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 2-20 2.2.2.2 Dose to a Member of the Public at or beyond the Site Boundary 2-21 2.2.2.3 DoseCalcuktionstoSupportOther 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 iii
TABLE OF CONTENTS (Con t -)
PAGE 2.2.3.2 Dose Projections for Specific Relehses 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
iv
e LIST OF TABLES TABLE TITLE PAGE 1.2-1 Bioaccumulation Factors 1-24 1.2-2 Adult Ingestion Dose Factors 1-26
)
1.2-3 Site Related Ingestion Dose Factors for i
Freshwater Fish and Drinking Water Consumption 1-29 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 Ingestion Dose Factors for Infant 2-47 l
2.2-6 Ingestion Dose Factors for Child 2-50 l
2.2-7 Ingestion Dose Factors for Teenager 2-53 2.2-8 Ingestion Dose Factors for Adult 2-56 2.2-9 External Dose Factors for Standing on Contaminated Ground 2-59 V
LIST OF TABLES TABLE TITLE PAGE 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 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 I
I l
w l
vi y
+
d LIST OF FIGURES FIGURE TITLE PAGE 1.5-1 Liquid Waste Processing System (Unit 1) 1-39 J
1.5-2 Liquid Waste Processing System (Unit 2) 1-40 1.5-3 Liquid Discharge Pathways 1-41 2.3-1 Vertical Standard Deviation of Material in a Plume 2-84 2.3-2 Plume Depletion Effect for Ground-Level Releases 2-85 2.3-3 Plume Depletion Effect for 30-Meter Releases 2-86 2.3-4 Plume Depletion Effect for 60-Meter Releases 2-87 2.3-5 Plume Depletion Effect for 100-Meter Releases 2-88 l
2.3-6 Relative Deposition for Ground-Level Releases 2-89 2.3-7 Relative Deposition for 30-Meter Releases 2-90 2.3-8 Relative Deposition for 60-Meter Releases 2-91 2.3-9 Relative Deposition for 100-Meter Releases 2-92 2.5-1 Gaseous Waste Processing System 2-105 2.5-2 Ventilation Exhaust Treatment System 2-106 l
(Plant Vent) l vii
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 3.0-2 Terrestrial Stations beyond Site Boundary out to Approximately Five Miles and Aquatic Stations 3-6 3.0-3 Terrestrial Stations beyond Five Miles 3-7 3.0-4 Drinking Water Stations 3-8 i
t i
i viii
REFERENCES 1.
J. S. Boegli, R. R. Bellamy, W. L. Britz, and R. L.
Waterfield, " Preparation of Radiological Effluent 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.
S.
Vogtle Electric Generating Plant, Unit 1 and Unit 2, " Final Safety Analysis Report", Georgia Power Company.
6.
Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases f rom Light-Water-Cooled Reactors, U.S. NRC Regulatory Guide 1.111 (March 1976).
7.
Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors, U.S. NRC Regulatory Guide 1.111, Rev. 1 (July 1977).
ix
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 Efiluent Discharge Structure Plume Analysis; Georgia Power Company; 7pril 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 - 1986; 2
Georgia Power Company; April 1986.
13.
Letter to Georgia Power Company from Pickard Lowe, and 2,3 Garrick, Inc.; Washington, D.C.; December 16, 1986.
14.
Kahn, Bernd, et. al; " Bioaccumulation of P-32 in Bluegill 2
and Catfish"; NUREG/CR-3981 (February 1985).
15.
Sagendorf, et.al; "XOQD0Q: Computer Program for the 3
Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations"; NUREG/CR-2919 (September 1982).
x i
4
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 areas.
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 calculational methods or parameters will be incorporated into the ODCM in order to assure that the ODCM represents current methodology in all applicable areas.
Computer sof tware to perform the described calculations will be maintained current with the ODCM.
I i
l xi i
SECTION 1 LIQUID 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 cooling tower blowdown, and nuclear service cooling tower blowdown.
Additional dilution water is available f rom 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 blewdown 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.
Sampling and analysis of reieases via these effluent pathways must be 2
sufficient to assure that the dose limits specified in Technical Specification 3.11.1.2 are not exceeded.
The Liquid Effluent Section of the ODCM describes the i
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.
Liquid discharge pathways are shown in Figure 1.5-3.
1-1
N 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 concentratio,ns 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 to 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 these 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 detectable activity in the planned release.
1 1-2
M 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 limits specified 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:
iC p+g MPC III where:
CMPC =
the effluent concentration limit corresponding to the specific mix of radionuclides in the waste monitor tank being considered for discharge, in uCi/ml.
the setpoint, in uCi/ml, of the radioactivity c
=
monitor measuring the concentration of radioactivity in the effluent line prior to dilution and subsequent release.
(Note that the monitor setpoint is inversely propor-tional to the effluent flow rate, f, and t
directly proportional to the dilution stream flow rate, 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.
1-3
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.
l the dilution stream flow rate which can be F
=
assured prior to the release point to the 1
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 4
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 bypass line.
A predetermined i
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 be applied to a mixture of radionuclides with different limiting concentrations, i.e. different MPC values.
l 1-4
For a mixture of radionuclides, equation (1) is satisfied in a
'f 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 F, by calculating the MPC d
fraction for the radionuclide mixture, the maximum permissible effluent flow rate, f, and the radioactivity monitor setpoint, c.
m 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 l
Specification Table 4.11-1.
The relationship of the various required sample analyses is i
shown as follows:
I Cg=
C
+ (C,+ C, + Cg+C) (2) g 1-5
.. -. - -.. _ _,. -.. _ - _ =. _.. _ _ _ _ _. _,, _ _ _ - -,. _. -.,
where-C the concentration of each measured gamma
=
g emitter observed by gamma-ray spectroscopy of the particular waste sample.
C, the concentration of alpha emitters in liquid
=
waste as measured in the MONTHLY composite sample.
(' OTE:
Sample is analyzed for gross N
alpha.)
C the measured concentrations of Sr-89 and Sr-
=
s 90 in liquid waste as observed in the 4
QUARTERLY composite sample.
Cg
.=
The measured concentrations of Fe-55 in liquid waste as observed in the QUARTERLY i
composite sample.
t the measured concentration of H-3 in liquid C
=
waste as determined from analysis of the MORTELY composite sample.
The C term will include the analysis of each batch; g
terms for alpha, strontiums, iron, and tritium will be included in accordance with Technical Specification Table 4.11-1 as appropriate.
In order to assure that sample analyses are based on samples which are representative of the volume from l
which the samples are taken, liquid volumes must be thoroughly mixed prior to sampling.
Mixing may be 1
accomplished by any method of mixing which has been l
demonstrated to achieve mixing sufficient to allow representative sampling.
1-6 4
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 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:
MP C
C C
C C
yC RDF =
+
+ MP
+ MPC
+
+
MPC where g
a s
f-t Cg measured concentrations of Cg, C,, Cs, Cg and
=
Ct as defined in Step 1.
Terms C, C,C, a
s g
and C will be included in the calculation as t
appropriate.
g a
s g
t are limiting MPCi=
MPC, MPC, MPC, MPC, and MPC 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.
If specific alpha-emitting radionuclides are measured, the MPC for the specific radionuclide(s) shall be used.
1-7
.r, - - - -
.,,,,---,.,-.-..~--,,.-r
,--e
r M
SF
=
the safety factor, which is a conservative factor selected to compensate for statistical fluctuations and errors of measurements.
The value for the safety factor must be between 0 and 1; a value of 0.5 is a reasonable value i
for liquid releases.
A more precise value may be developed if desired.
l Step 3)
Determine the dilution stream flow rate which will be assured during the period of the release, which is designated as Fd.
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, and the m
radioactivity monitor setpoint, c.
i 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 by multiplying the assured dilution stream flow rate, Fd, by an allocation factor, AF, to obtain a unit-specific assured dilution stream flow rate, Fdu i
Fdu = Fd (AF)
(4) 1-8
where An allocation factor selected to apportion AF
=
the diluting capacity of the dilution stream between the two units when simultaneous releases from the liquid waste processing I
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 f actors does not exceed 1. ' For convenience j
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, which may 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 system releases are being made, AF may be assigned the value of 1 and then Fdu is equal to F
- d For the case RDF< 1, the waste monitor tank meets the limits of 10 CFR 20 without dilution and could be released at any desired flow rate.
However, in order to maintain 1-9
=-. _-
individual doses due to radioactivity in liquids released to unrestricted areas ALARA, no releases from the liquid waste processing system should be made if assured dilution 1
stream flow rate, Fd, is less than 5000 gpm.
Step 4)
For the case RDF>1, calculate the maximum permissible waste monitor tank discharge flow rate,f, as follows:
m
- u d
fm"
'RDF-1 (5)
For the case RDF5 1, equation (5) is not valid.
However, as discussed above, for the case RDF5 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 gpa (maximum).
When calculated maximum permissible release flow rates are 2100 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 j
tower blowdown, or turbine plant l
cooling tower blowdown), the 1-10 i
diluting capacity of the dilution stream would be diminished.
(Further, sampling and analysis of these effluent streams must be sufficient to assure that the dose limits specified in Technical Specification 3.11.1.2 are not exceeded.)
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 effluent:
F C
f 2
du 1-g r
fm " RDF-1 N@C
( }
il r where E (C /MPC ) r is the MPC fraction of the effluent stream (s) 1 g
g containing the detectable radioactivity.
f is the flow rate of the effluent stream (s) r containing the radioactivity.
If RDF1 1, NOTE 2 does not apply.
1-11
-.-,..--,.--.~ -.-.
_...,_-__._,,..,,_.--..-.-.,,,..,_..--n
Step 5)
Based on the values determined in the previous steps, a liquid waste processing system effluent radioactivity monitor base
- i 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, t e monitor setpoint calculation is based on C,
in g
units of uCi/ml, as follows:
c=AbC (7) 9 g
where Adjustment factor which will allow the A
=
setpoint to be established in a practical manner to prevent spurious alarms and to j
allow for the margin between measured j
concentrations and concentrations which would I
approach 10 CFR 20 limits:
ADF A=g (8) i r
NOTE:
ADF is the assured dilution factor:
l1 Fdu + fa ADF =
(8a) g a and f is the anticipated release flow rate from a
the waste manitor tank to be discharged.
h a
t I
1-12 t
_. - _ _.,..,.. ~,.. _,
12i l
If A ? 1, calculate the monitor setpoint, c.
- However, if the calculated setpoint value is within 10 percent of 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.
Therefore, 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 actions, repeat the previous steps and calculate a new monitor setpoint.
If A < l, no release may be made under planned conditions.
Consider the alternatives discussed above to reduce potential release concentrations, and calculate a new monitor l
setpoint based on the results of the I
alternatives selected.
l The calculated setpoint establishes the base value for the radioacitvity monitor setpoint.
However, in j
establishing the actual setpoint for a particular l
monitor, adjustments must be taken into account for background radiation levels and monitor calibration i
i information.
Background radiation levels must be controlled such that radioactivity levels in the effluent stream being monitored can accurately be i
assessed at levels below the setpoint value.
l l
1-13
3EJ Calibration of the monitors by the manufacturer utilized NBS traceable liquid solutions in the exact geometry of the production monitors over a gamma-ray emergy range of 0.08 to 1.33 MeV.
The calibration factor is a function of the radionuclide mix in the 2
liquid to be released and will be calculated for the monitor based on the results of the pre discharge sample results from the laboratory gamma-ray spectrometer system.
The actual monitor setpoint is determined as follows:
C,,
=
A Cg(CF)g + BG (8b)
Where
.CF = the calibration factor for the particular radionuclide g for the monitor.
BG = background level for the particular 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 as practical to prevent spurious alarms and yet alarm should an inadvertent release occur.
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 1.1.1.1.
1-14
g l
j From the C
terms determined for each g
tank, determine an effective (
C ), for the g
two tanks considered together as follows:
Y i q)1 + Y2(
C )2 (9)
( b c )e =
l q
g g
Vy+V2 where V1 Volume of liquid in tank containing greater
=
quantity (referred to throughout this Subsection as first tank.)
V2 Volume of liquid in tank containing lesser
=
quantity (referred to throughout this Subsection as second tank).
(
C )1 measured concentrations of gamma emitting
=
g radionuclides in first tank
(
C )2 measured concentration of gamma emitting
=
g radionuclides in second tank Step 2)
Determine a required dilution factor, RDF, for each tank in accordance with Step 2 of Subsection 1.1.1.1.
Using these values calculate an effective required dilution factor, (RDF),, for the two tanks considered together as follows:
V (RDF)y + V2 (RDF)2 1
(RDF),=
y
, y (10) where Vi volume of first tank
=
1-15
,,_m.v.a e----,----nw~-,----
,en-- - - -, -
, - - =
t r
l V2
,. volume of second tagk
=
r -
I J
t 4
(RDF)1
=#
required dilition factor for first tank 5
j (RDF)2 required dilution factor for second tank
=
St p 3)
Determine the dilut' ion stream flow rate in accordance with step 3 of Subsection 1.1.1.1.
7e
-t 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
,I select a release flow rate for the first tank,_f.
Then determine the release flow t
rate for the second rank, f, as follows:
2
[
1 2
1 f
2 V
Ill) 1
' J' l'
Next, determine a combined flow rate, f, for e
releases from both tanks, as follows:
f *fl + ',f2 (12) c 1
Next, calculate a maximum permissible flow
[
, rate, f, for the combined release in m
[}
- accordance with Step 4 of Subsection 1.1.1.1 using the effective (RDF), determined in Step 2 above.
s l-Then compare the combined release flow rate, f
f, with the maximum permissible combined e
release flow rate, f '
If fm> f, the m
c release may be made under the assumed
{
u i s
1-16 1
l~
.k'
'*c
v e
conditions.
If fm < f, the two release flow e
rates may be throttled, maintaining the same ratio of f to f, as determined earlier.
If 2
l it is impractical to throttle the release flow rates to the necessary degree to achieve f 4 f, steps must be taken to reduce c
m potential release concentrations prior to making the release, and a new f determined e
following the necessary actions.
(S teps 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 b
C )e;
(
=
g g
g g
RDF (RDF),,
=
and f,=
fc Observe the same limiting conditions discussed in Step 5 of Subsection 1.1.1.1.
e 1-17 l
~.
1.1.2.
Steam Generator Blowdown Effluent Radioactivity 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)
According to Plant Vogtle design and operating philosophy, the purpose of these radioactivity monitors is to minimize release of radioactivity via these effluent streams by i
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 r,adioactivity via these pathways to the extent practicable.
All I
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.
I 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.
1-18
As stated earlier, all three of these effluent streams discharge to the waste water retention basin.
Composite samples are collected from the discharge line from the waste water 2
retention basin to the blowdown sump.
Sample collection and analysis must be sufficient to assure that the dose limits specified in Technical Specification 3.11.1.2 are not exceeded.
e 1-19
1.1.3.
Nuclear Service Coolina 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 inadvertent release occur.
If any one 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 f actor 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.
Determination of concentrations of radioactivity in these streams must be adequate to assure that 2
the dose limits specified in Technical Specification 3.11.1.2 are not exceeded.
1 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 presented in this Subsection.
l l-20
,, ~,
.....,mm.._,n.r.
uu 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 implementation of Technical Specification 3.11.1.2, as follows:
7=E D
A g
gg at C
F (13) y gy 1
11 where D
.=
7 The cumulative dose commitment to the total body or any organ,r, due to radioactivity in liquid effluents for the total time period m
at in mrem (Reference 1).
l Att The length of the lth time period over which
=
Cil and F1 are averaged for any liquid release, in hours.
C i1 The average concentration of radionuclide i,
=
in undiluted liquid effluent during time period oti from any liquid release, in uCi/ml.
F 1 The near field average dilution factor in the
=
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.
1-21
NOTE:
If simultaneous releases from both units 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, Z=10; for the months January through April, Z=20.
(Reference 5, Section 11.2.3.4; Reference 11)
Ag i
The site-related adult ingestion dose
=
commitment factor to the total body or any organ for each identified radionuclide.
Site-related A ir values for Plant Vogtle are listed in Table 1.2-3 in mrem-m1 per br-uCi.
D e~*i w + U BF
~
A
=K
((U,/D,)
g7 p
ge i f) DFi7(15) e 1-22
Units conversion factor 1.14 x 105, K
=
o determined by:
6 3
10 pCi x 10 ml 8760 hr uCi 1
yr Adult' drinking water consumption (730 U,
=
liters /yr; Reference 3, Table E-5)
Dilution factor from the vicinity of the D,
=
liquid release point for the plant site to the potable water intake location (8; Reference 11)
Ei The decay constant for radionuclide i. (hr-1)
=
Transit time from release to receptor for t,
=
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) p Adult fish consumption (21 kg/yr; Reference U
=
3, Table E-5) i Bioaccumulation factor for radionuclide i, in BF
=
fresh water fish, in pCi/kg per pCi/l (See Table 1.2-1; Reference 3, Table A-1; Reference 2 for Ag)
Transit time from release to receptor for tg
=
i fish consumption (24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />; Reference 3, Section A.2)
I DFi7 =
Dose conversion factor for radionuclide i, for adults in organ,7, in mrem /pci, from Table 1.2-2 (Reference 3, Table E-ll).
1-23
n 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
3.0E 03 I2 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 j
Ag 2.3E 00 1
Te 4.0E 02 I
1.5E 01 Cs 2.0E 03 i
Ba 4.0E 00 La 2.5E 01 l
j
- Reference 3, Table A-1; Reference 2 for Ag; Reference 14 for P 2
l 1-24
r
~
2D$
TABLE 1.2-1 (Continued)
BIOACCUMULATION FACTORS (pCi/kg per pCi/ liter)*
Freshwater Element Fish Ce 1.0E 00 Pr 2.5E 01 Nd 2.5E 01 W
l.2E 03 Np 1.0E 01 J
i
- Reference 3, Table A-1; Reference 2 for Ag; Reference 14 for P l2 1-25
Table 1.2-2 Page 1 of 3 Adult Ingestion Dose Factors *
(ares per pCi ingested) l Nuclide Bone Liver T Body Thyroid Kidney Luno 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 5.685-07 5.685-07 5.68E-07 5.685-07 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 3
P-32 1.93E-04 1.20E-05 7.46E-06 No Data No Data No Data 2.17E !
'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 1.905-06 4.43E-07 No Data No Data 1.065-06
1.0 9E-06
Fe-59 4.34E-06 1.02E-05 3.91E-06 No Data No Data 2.855-06 3.40E-05 Co-58 No Data, 7.455-07 1.67E-06 No Data No Data No Data 1.51E Co-60 No Data 2.14E-06 4.72E-06 No Data No Data No Data 4.02E-05 Ni-63 1.30E-04 9.018-06 4.36E-06 No Data No Data No Data 1.888-06 1
i Ni-65 5.28E-07 6.86E-08 3.135-08 No Data No Data No Data 1.748-06 l
Cu-64 No Data 8.33E-08 3.915-08 No Data 2.10E-07 No Data 7.10E-06 l
Zn-65 4.84E-06 1.54E-05 6.968-06 No Data 1.035-05 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-08 No Data No Data No Data 4.09E-13i 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 9.838-06 No Data No Data No Data 4.16E-06 Rb-88 No Data 6.05E-08 3.215-08 No Data No Data No Data 8.36E-19 4
i Rb-89 No Data 4.013-08 2.82E-08 No Data No Data No Data 2.33E-21 Sr-89 3.08E-04 No Data 8.843-06 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 l
l Sr-91 5.67E-06 No Data 2.295-07 No Data No Data No Data
.2.70E-05 St-92 2.15E-06 Mo Data 9.30E-08 No Data No Data No Data 4.26E-05 Y-90 9.625-09 No Data 2.58E-10 No Data No Data No Data 1.02E-04 Y-91m 9.095-11 No Data 3.52E-12 No Data No Data No Data 2.67E-10 Y-91 1.415-07 No Data 3.77E-09 No Data No Data No Data 7.76E-05 Y-92 8.45E-10 No Data 2.47E-11 No Data No Data No Data 1.48E-05 i
- Reference 3, Table E-ll I
1-26
Table 1.2-2 (Continusd)
~
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 i
Nb-95 6.22E-09 3.46E-09 1.86E-09 No Data 3.42E-09 No Data 2.10E-05 l
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 To-125m 2.68E-06 9.71E-07 3.59E-07 8.06E-07 1.09E-05 No Data 1.07E-05 To-127m 6.77E-06 2.42E-06 8.25E-07 1.73E-06 2.75E-05 No Data 2.27E-05 Tc-127 1.10E-07 3.95E-08 2.38E-08 8.15E-08 4.48E-07 No Data 8.68E-06 To-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
-131m 1.73E-06 8.46E-07 7.05E-07 1.34E-06 8.57E-06 No Data 8.40E-05
.e-131 1.97E-08 8.23E-09 6.22E-09 1.62E-08 8.63E-08 No Data 2.79E-09 l
Te-132 2.52E-06 1.63E-06 1.53E-06 1.80E-06 1.57E-05 No Data 7.71E-05 i
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.llE-06 Co-138 5.52E-08 1.09E-07 5.40E-08 No Data 8.01E-08 7.91E-09 4.65E-13 Bo-139 9.70E-08 6.91E-11 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-ll 2.02E-ll 2.22E-17 Bc-142 2.13E-08 2.19E-ll 1.34E-09 No Data 1.85E-ll 1.24E-ll 3.00E-26
- Reference 3, Table E-ll 1-27
Table 1.2-2 (Con tinusd)
Page 3 of 3 Adult Ingestion Dose Factors *
(mrem per pCi ingested)
Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI Ls-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-ll 1.45E-ll No Data No Data No Data 4.25E-07 Ca-141 9.36E-09 6.33E-09 7.18E-10 No Data 2.94E-09 No Data 2.42E-05 Co-143 1.65E-09 1.22E-06 1.35E-10 No Data 5.37E-10 No Data 4.56E-05 Co-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-ll 1.25E-ll 1.53E-12 No Data 7.05E-12 No Data 4.33E-18 Nd-147 6.2sE-09 7.27E-09 4.35E-10 No Data 4.2SE-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
.l.19E-09 1.17E-10 6.45E-ll No Data 3.65E-10 No Data 2.40E-05 l
l l
- Reference 3, Table E-ll 1-28
Table 1.2-3 Page 1 of 2
.te Related Ingestion Dose Factors, Att, For Freshwater Fish and Drinking Water Consumption *
(mrem /hr per uCi/ml)
Nuclide Bone Liver T Body Thyroid
_ Kidney Luno 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 Nc-24 1.36E+02 1.36E+02 1.36E+02 1.36E+02 1.36E+02 1.36E+02 1.36E+02 P-32 4.40E+07 2.74E+06 1.70E+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+03 8.42E+02 0.00E+00 1.31E+03 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 Fo-55 6.86E+02 4.74E+02 1.llE+02 0.00E+00 0.00E+00 2.65E+02 2.72E+02 FG-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 3.25E+04 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 0.00E+00 4.02E-02 0.00E+00 0.00E+00 0.00E+00 5.80E-02 i
Br-84 0.00E+00 0.00E+00 1.16E-12 0.00E+00 0.00E+a0 0.00E+00 9.12E-18
~ -85 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
.-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 L
Sr-90 6.23E+05 0.00E+00 1.53E+05 0.00E+00 0.00E+00 0.00E+00 1.80E+04 l
Sr-91 7.47E+01 0.00E+00 3.02E+00 0.00E+00 0.00E+00 0.00E+00 3.56E+02 1
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 i
Y-92 4.59E-04 0.00E+00 1.34E-05 0.00E+00 0.00E+00 0.00E+00 8.04E+00 l
Y-93 3.30E-02 0.00E+00 9.11E-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).
Site related dose factors are presented as zero in this table when "not data" is reported for
,e dose f actors for specific radionuclide-organ combinations in Reference 3.
l-29
j Table 1.2-3 (Continued)
Page 2 of 2 Site Related Ingestion Dose Factors, A tz, For Freshwater Fish and Drinking Water Consumption *
(mrem /hr per uCi/ml)
?
Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI I
Ru-103 6.21E+00 0.00E+00 2.68E+00 0.00E+00 2,37E+01 0.00E+00 7.25E+02 i
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 6.10E+03 Ag-110M 2.53E+00 2.34E+00 1.39E+00 0.00E+00 4.61E+00 0.00E+00 9.57E+02 i
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+03 7.93E+02 1.66E+03 2.64E+04 0.00E+00 2.18E+04 I
Te-127 1.80E+01 6.46E+00 3.89E+00 1.33E+01 7.33E+01 0.00E+00 1.42E+03 Ta-129M 1.09E+04 4.07E+03 1.73E+03 3.75E+03 4.55E+04 0.00E+00 5.49E+04 Te-129 1.49E-05 5.59E-06 3.62E-06 1.14E-05 6.2SE-05 0.00E+00 1.12E-05 Ts-131M 9.58E+02 4.68E+02 3.90E+02 7.42E+02 4.74E+03 0.00E+00 4.65E+04 i
Te-131 5.82E-17 2.43E-17 1.84E-17 4.79E-17 2.55E-16 0.00E+00 8.24E-18 i
Te-132 1.97E+03 1.27E+03 1.19E+03 1.40E+03 1.22E+04 0.00E+00 6.01E+04 I-130 7.56E+00 2.23E+0?
8.80E+00 1.89E+03 3.48E+01 0.00E+00 1.92E+01 I-131 1.73E+02 2.48E+01 1.42E+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-02 0.00E+00 2.31E-03 I-133 2.54E+01 4.41E+01 1.35E+01 6.49E+03 7.70E+01 0.00E+00 3.97E+01 I-134 1.75E-08 4.74E-08 l'.70E-08 8.22E-07 7.54E-08 0.00E+00 4.13E-ll 1-135 1.34E+00 3.51E+00 1.30E+00 2.32E+02 5.64E+00 0.00E+00 3.97E+00
-134 2.98E+05 7.10E+05 5.80E+05 0.00E+00 2.30E+05 7.62E+04 1.24E+04 3
,-136 2.97E+04 1.17E+05 8.44E+04 0.00E+00 6.52E+04 8.94E+03 1.33E+04 Cs-137 3.82E+05 5.23E+05 3.43E+05 0.00E+00 1.78E+05 5.90E+04 1.01E+04 Cs-138 9.47E-12 1.87E-11 9.26E-12 0.00E+00 1.37E-11 1.36E-12 7.98E-17 Ba-139 5.44E-06 3.88E-09 1.59E-07 0.00E+00 3.62E-09 2.20E-09 9.65E-06 Ba-140 3.74E+02 4.69E-01 2.45E+01 0.00E+00 1.60E-01 2.69E-01 7.69E+02 Ba-141 3.78E-25 2.85E-28 1.27E-26 0.00E+00 2.65E-28 1.62E-28 1.78E-34 Ba-142 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 La-140 1.10E-01 5.56E-02 1.47E-02 0.00E+00 0.00E+00 0.00E+00 4.09E+03 La-142 1.56E-07 7.llE-08 1.77E-08 0.00E+00 0.00E+00 0.00E+00 5.19E-04 Co-141 1.15E-01 7.79E-02 8.84E-03 0.00E+00 3.62E-02 0.00E+00 2.98E+02 Ca-143 8.650-03 6.40E+00 7.08E-04 0.00E+00 2.82E-03 0.00E+00 2.39E+02 Co-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-01 2.45E-01 3.02E-02 0.00E+00 1.41E-01 0.00E+00 2.67E+03 i
Pr-144 1.37E-28 5.68E-29 6.95E-30 0.00E+00 3.20E-29 0.00E+00 1.97E-35 j.
Nd-147 4.llE-01 4.75E-01 2.84E-02 0.00E+00 2.78E-01 0.00E+00 2.28E+03 W-187 1.48E+02 1.24E+02 4.32E+01 0.00E+00 0.00E+00 0.00E+00 4.05E+04
]
Np-239 2.81E-02 2.76E-03 1.52E-03 0.00E+00 8.61E-03 0.00E+00 5.66E+02 i
l
- Calculated Using Equation (15).
Site related dose factorc are presented as zero in this table when "no data" is reported for 2
i dose factors for specific radionuclide-organ combinations in Reference 3.
i 1-30
--wn
- m --,~
,-,,m n w,,,..,w.n w w w..
.~~.-w,.
-~,-w.-
-,e.,__.
4 1.3.
DO3E PROJECTIONS FOR LIQUID EFFLUENTS 1.3.1.
Thirty-One Day Dose Projections In order to meet the requirements of Technical Specification 3.11.1.3, which pertains to operation of the liquid radwaste treatment systems, dose projections must be made at least once per thirty-one days, during periods in which discharge of liquid effluents containing radioactive materials to unrestricted areas occurs or is expected.
Projected 31-day doses to individuals due to liquid effluents may be determined as follows:
U b( I tb(prj) x 31
=
t (16) 1 Do(c)
D x 31 (17)
I o prj) is t
where Dtb(c) the cumulative total body dose for the elapsed
=
portion of the current quarter plus the release under consideration.
the number of days into the current quarter, t
=
including the period of the release under 1
consideration.
Do(c) the cumulative organ doses for specific
=
org ans, for the elapsed portion of the current quarter plus the release under consideration.
1-31
If operational activities planned during the ensuing 31-day period are expected to result in liquid releases which will contribute a dose in addition to the dose due to routine liquid effluents, this additional dose contribution should be included in the equations as follows:
D f
tb(prj) x 31
+
D
=
pA (18) 1 D
II o(prj) x 31
+D
=
PA (19)
I where Dpg is the expected dose due to the particular planned activity.
1.3.2. Dose Projections for Specific Releases 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 the release period.
f l
B l-32
r S
1.4 DEFINITICNS*OF LIQUID EFFLUENT TERMS Section Of Term Definition Initial Use adjustment factor used in calculating A
=
monitor setpoints, which is the ratio of the assured dilution factor to the required dilution fcetor (unitiess).
1.1.1 ig the site related ingestion doce A
=
commitment factor for the total body or any organ for each identified principal radionuclide listed in Table 1.2-3 in mrem-al per br-uci.
1.2 the assured dilution f actor, which is the ADF
=
ratio of unit-specific assured dilution flow rate to anticipated effluent release rate (unitiess).
1.1.1.1 1
BFi Bioaccumulation Factor for nuclide i, in
=
fresh water fish, pCi/kg per pCi/1, from table 1.2-1.
1.2 BG the background level for the
=
radioactivity monitor of interest.
1.1.1 l
the base setpoint of the radioactivity c
=
i monitor which measures the radioactivity concentration in the effluent line prior i
to dilution and subsequent release.
1.1.1 c
the actual setpoint for a radioactivity l
ms
=
monitor, including adjustments for j
calibration factor and background.
1.1.1 l
l-33 4
Ssction Of Term Definition Initial Use C,
the effluent concentration of alpha
=
emitting nuclides observed by gross alpha analysis of the MONTHLY composite sample, in uCi/ml.
1.1.1 Cg the concentration of Fe-55 in liquid
=
wastes as observed in the QUARTERLY composite sample, in uCi/ml 1.1.1 l
C the effluent concentration of a gamma
=
g emitting nuclide, g, observed by gamma-ray spectroscopy of the waste sample, in uCi/ml.
1.1.1 i
the concentration of nuclide i as C
=
determined by the analysis of the waste sample, in uCi/ml.
1.1.1 1
C it the average concentration of radionuclide
=
i, in undiluted liquid effluent during time period at, for a release in uCi/ml.
1.2 t
CMPC =
the effluent concentration limit (Technical Specification 3.11.1.1) implementing 10 CFR 20 for the site, in uCi/ml.
1.1.1 C
=
the concentration of Sr-89 and Sr-90 in s
liquid wastes as determined by analysis of the QUARTERLY composite sample, in uCi/ml.
1.1.1 the measured concentration of H-3 in C
=
t liquid waste as determined by analysis of the MONTHLY composite sample, in uCi/ml.
1.1.1 l'
l-34 i
-%,--.,_-~c.,,
...3-.
.-,,n_..-
-.y.
- - ~ _ _. - - - _,. - -
y SGction Of Term Definition Initial Use the calibration factor for a particular CF
=
radioactivity monitor.
1.1.1 the cumulative dose commitment to the D
=
7 total body or any organ, I, from the liquid effluents for the total time 4
period, in mrem.
1.2 Additional dilution factor between D,
=
vicinity of release point and drinking water location (unitiess).
1.2 DF ig a dose conversion factor for nuclide, i,
=
1 for adults in organ, T, in mrem /pci found in Table 1.2-2.
1.2 4
f the flow as determined for the radiation
=
monitor location in gym.
(General expression for equation 1).
1.1.1 4
i 4
the dilution water flow rate as F
=
1 determined prior to the point at which j
the dilution. stream discharges to the l
river, in gpm.
(General expression for equation 1).
1.1.1 l
l F
=
d the flow rate of the dilution stream l
which can be assured during the time of release in gym.
This is also the f
setpoint for the dilution stream flow rate measurement device.
1.1.1 l
Fdu the unit-specific assured flow rate of l
=
the dilution stream used as the basis for setpoint calculations, in gpm.
1.1.1 1-35 1
a SGction Of
~
Term Definition Initial Use F1 the near field average dilution factor f
=
for C11 during any liquid effluent release (unitiess).
1.2 f,
anticipated effluent flow rate in gpm.
1.1.1
=
maximum permissible effluent flow rate in f
=
m gpm.
1.1.1 1.14 x 105, units conversion factor, K
=
o which converts uCi to pCi, liters to m1, and hours to year.
l.2 number of liquid releases.
1.2 m
=
MPCi=
MPC, MPC, MPC, MPC, and MPC which g
a s
g t
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 f actor, which is the ratio of the dilution flow rate to the effluent stream flow rate (s) which I
would be 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 (unitiess).
1.1.1 l-36
W Scction Of Term Definition Initial Use
~
the safety factor, which is a SF
=
conservative f actor used to compensate for statistical fluctuations and errors of measurement.
The value for the safety factor must be between 0 and 1.
1.1.1 tg the transit time from release to receptor
=
(fish consumption), in hours.
1.2 t,
the transit time from release to receptor
=
(drinking water consumption), in hours.
1.2 duration of release under consideration, 1
aty
=
in hours.
1.2 p
21 kg/yr, fish consumption (adult).
1.2 U
=
730 liters /yr, water consumpt~1on (adult) 1.2 U,
=
Applicable factor when additional j
Z
=
receiving water body dilution is considered (unitiess).
1.2 Ai The decay constant for radionuclide 1.
=
(hr-1) 1.2 i
1-37
it5 1.5 LIQUID WASTE PROCESSING SYSTEM AND LIQUID DISCRARGE 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.
1-38
s:
H Figure 1.5-1 LIQUID WASTE PROCESSING SYSTEM (Unit 1)
F Q
5 Laundry and Hot 3 ""'"
py,,p Tank orain (Shared)
Tant l
l Strainer Strainer i
r-------H Filter l
[
Uter l
l c....!
i
--- - 0 I
l
---*C waste
..q---______ct.. g
. Monitor Tank Domin 8
I l
\\
Waste I
Monitor Tank I'
Filter
,,,, g
_ _ _ _ _ _ _ L _ _ q_ _ _ _ _ _ _ _,
ggggg I
Waste Monitor
"'IOP Tank i
Tank -
I m
A Radfoactivity Monitor RE-0018 1
From Unit 2 Waste Monitor Tant (s) y To Otscharge
- 00tted lines indicate alternate routes for increased operational flexibility and/or adatttonal processing.
To Unit 2 From/To Unit 2 To Orain Channel A From Orain Channel A 1-39
?
~
.A Figure 1.5-2 LIQUID WASTE PROCESSING SYSTEM (Unit 2)
?~
r g
Floor g
Crain Tant l
l I
S trs1ner p-
_a l
[
Filter l
l
.__. o I
---G
.-d,--------c we,,,
Monitor t.... g Tank Domin
(
l i
Este I
Monitor I
Tank I
Filter l
y I
t
t_
I Weste I
Weste Mon t tor' I
knt tar Tank l
Tank l
i s
b
( > Radioactivity Monitor 3 RE.0018 e
To Olsenerge (See Figure 1.5 1)
- Cotted lines indicate alternate routes for increased operational flexibility and/or additional processing.
From Unit 1 From/To Unit 1 To Orain Channel A From Orain Channel A 1-40
y m
Figure 1.5-3 LIQUID DISCHARGE PATHWAYS a
1 e
.a Steam Turbine Nuclear Genera tor Building Service 810woown Crain Cooling Water C
From Other Sumps and Orains O
(D Turbine Plant Id g Cooling Sump Tower
-From Other Sumos From Unf t 2 Nuclear Service Cooling Water Offy Waste Separa tor From Unf t 2 Turbine Plant Cooling Tower g
Weste Lfaufd Water Waste Retention Basin Sy,0"1 From Unft 2 unste Water Retention Basin 6
I"*
(,, nht 2 8"
t Processing System
- From Flushing Ponds (Curing Construction of Unit 2) g i
River N
Radfoactivity itnitors:
~
^
RE0020 REC 021 RE0848 RE11646 RE0018
- The 81cwdown Sump is cocymn to botn units.
1 I
I 1-41 i
- _, _.. - _ _. _ _ _ _. _ _.. _.... _.. _ ~. _. _. _ _ _ _ _ _ _ _ _.. _ _
~
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 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-modo releases as determined by the wake-split model.
(See NOTE in Subsection 2.1.1). All five release 3
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 effluent monitor setpoints are required only for noble gas monitors serving the five release points.
I:ethodology for calculating noble gas monitor setpoints is presented in Subsection 2.1.
Although setpoint calculations are not required for radiolodine and particulate monitors, the l
methodology for assuring the potential organ dose rates due to radiolodines, tritium, and particulates in gaseous releases from the site do not exceed the limits of Technical Specification 3.ll.2.l(b) is presented in the NOTE in Subsection 2.2.1.2.
2-1
2.1 GASEOUS EFFLUENT MONITOR SETPOINTS
' Gaseous monitor setpoints are determined by calculating a basic setpoint value, c,,
for a particular monitor, and then
-adding this basic 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, c, and the s
actual monitor setpoint, c Throughout these subsections the sp.
5 term C, is used to designate monitor response to a measured concentration.
Monitor response and background considerations are discussed further in Subsection 2.1.4.
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 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.
4 i
If no release is planned for a particular pathway, or if there is no detectable activity in the planned release, the monitor setpoint should be established as close to background as practical to prevent spurious alarms and yet alarm.should an inadvertent release occur.
The monitor setpoint determined in j
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.
< s If a calculated setpoint is less than the monitor reading associated 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 (discussed in Subsection 2.1.5) and the 2-2 E
l setpoint recalculated, if releases via the pathway under consideration are to continue.
t 2.1.1 Unit 1 Turbine Building Vent, Unit 2 Turbine Buildinq Vent and Radwaste Solidification Building Vent Monitors:
RE-12839C (Unit 1),2 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 setpoint for these noble gas monitors will be calculated as follows:
)
c, calculated basic setpoint value
=
r (AG) (SF) (R ) (DTB)
(1) t s
the lesser off or 1
c
=
(AG) (SF) (R ) (Dss)
(la) s t
c
=
cs + BG (2) sp SF
=
safety factor, which is a conservative factor applied to each noble gas monitor to compensate for statistical fluctuations and errors of measurement.
The value of the i
safety factor must be between 0 and 1; a value of 0.4 to 0.6 is a reasonable range of 1
values for gaseous releases.
A more precise value may be developed if desired.
BG background level for the particular monitor 1
=
2-3
v Las an administrative allocation factor applied AG
=
to apportion the release setpoints among all gaseous release discharge pathways to assure that release limits will not be exceeded by simultaneous releases.
The allocation factor for a particular discharge pathway may be assigned any desired value between 0 and 1 under the condition that the sum of the allocation factors for all simultaneous release pathways does not exceed 1.
For ease of implementation, AG may be set 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.
dose rate limit to the total body of an DTB
=
individual which is 500 mrem / year.
R t relationship between monitor response and the
=
dose rate to the total body for the 1
conditions of the release under consideration.
R
=
t C,
((X/Q)G Kg Qg )
(3) g where 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.
(See Subsection 2.1.4 for further discussion of I
monitor response).
2-4
\\
^
a-(x/Q)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 releases.
6.83 x 10-5 sec/m in the ENE sector.
2,3 3
(x/Q)g
=
g total body dose factor due to gamma emissions K
=
3 from radionuclide 1 (mrem /yr per uC1/m ) from Table 2.1-1.
Qig rate of release of noble gas radionuclide 1
=
(uC1/sec) from the vent release pathway under consideration (ground-level), which is the product of Xiy and F, where Xiy is the y
concentration of radionuclide i
for the particular release and F is the maximum y
expected release flow rate for this release point.
(Xiy in uCi/ml and F in ml/sec.)
y ss dose rate limit to the skin of the body of an D
=
individual in an unrestricted area which is 3000 mrem / year.
relationship between monitor response and the R
=
s dose rate to the skin for the conditions of 1
the release under consideration.
Cm i- ( (X/Q) G i[Ib*1*1M)
R i
1 019 )
(4)
=
s 2-5
l where L
skin dose factor due to beta emisg) ions from
=
i radionuclide i (mrem /yr per uCi/m from Table 2.1-1.
1.1 mrem skin dose per mrad air dose.
=
Mi air dose factor due to gamma emigsions from
=
radionuclide 1 (mrad /yr per uCi/m ) from Table 2.1-1.
2.1.2 Unit 1 Plant Vent and Unit 2 Plant Vent Monitors:
RE12442C (Unit 1) and 2RE1244 2C (Unit 2) 1 Gaseous releases from the plant vent (s) are regarded as mixed-mode releases in that under certain conditions of vent exit velocity and meteorological conditions, the plume will behave as 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 values have been calculated utilizing expected annual average conditions. (See NOTE below).
However, since setpoints for plant vent monitors must l 3 be ectablished to ensure that the limits of Technical Specification 3.11.2.1.a will not be exceeded at any point in time, the ground level dispersion value used in Subsection 2.1.1 is also used in the calculation of setpoints for plant vent monitors.
NOTE:
Default recirculation values are utilized for 3
determination of dispersion and deposition factors for calculation of the offsite effect of gaseous effluents.
Ground-level release parameters are used for plant vent releases in the east and east-northeast sectors (sectors in which the cooling towers are located) to account for any potential cooling tower wake effects.
2-6
L 2mL The setpoint calculation methodology presented in Subsection 2.1.1 applies to these monitors with the exception 2
that Qig must be replaced with Q m where Qim is defined as i
follows:
Q, i
rate of release of noble gas radionuclide 1
=
(uci/sec) from the plant vent release pathway under consideration (mixed-mode), which is l
the product of Xiy and F, where X is the y
iy concentration of radionuclide i for the particular release and F is the maximum l
y expected rclease flow rate for this release point.
(Xiy in uC1/ml and F in ml/sec.)
y 2.1.3 Gaseo'us Waste Processing System Discharge and Reactor Containment Purge Monitors:
ARE0014, RE-2565C (Unit 1) and 2RE-2565C (Unit 2)
The Gaseous Waste Processing System discharges to the Unit 1 plant vent, Unit 1 containment purge discharges to the Unit 1 plant vent, and Unit 2 containment purge discharges to the Unit 2 plant vent.
The plant vents are equipped with continuous l
final effluent monitors as discussed in Subsection 2.1.2.
However, due to the potential significance of releases from these sources, the setpoint methodology is presented for the system effluent monitors also.
The system monitors have the control i
3 logic to terminate the release at alarm trip point.
The final monitors have no trip logic.
Sampling and analyses are completed.and monitor setpoints determined prior to release.
These setpoints must take into account simultaneous release pathways; the combined allocation factors for contributing pathway monitors must not exceed the allocation factor for the final release pathway monitor to which they contribute.
2-7
WI 2'
Downstream monitors must also take into consideration the combinations of source terms for the particular release pathway.
2.1.3.1 Gaseous Waste Processing System Monitor:
ARE-0014 The Gaseous Waste Processing System discharges through the Unit 1 plant vent; therefore, the Gaseous Waste Processing System effluent monitor is not the final monitor for releases from this system.
However, because of the significance of this release pathway and because the Unit 1 plant vent monitor setpoint has to accommodate releases from the Gaseous Waste Processing System, and the trip logic is associated with this 3
monitor,the set' point 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:
b Rt**t=Cmi I( /C}M i
i 1)
(5) 9 Exception 2:
monitor response of the Gaseous Waste C
=
m Processing System monitor for radionuclide concentrations to be discharged (sample taken and analyzed prior to discharge).
(See Subsection 2.1.4 for further discussion of monitor response).
1 Exception 3:
gi rate of release of noble gas radionuclide i
=
(uCi/sec) from the Gaseous Waste Processing 2-8
__Q
~ System, determined by multiplying the expected release rate by the concentration of radionuclide 1.
Exception 4:
T Rs " #s = C, i'r ( (X/Q) M 5Ibi + 1.lM ) q)
(6) g g
Exception 5:
A selected allocation factor value which must AG
=
be less than.the allocation factor for the monitor serving the final release point, Unit 1 plant vent.
When releases are to be made from the Gaseous Waste 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 1:
(Q m)GP, is determined which A new source term, i
includes the routine Unit 1 plant vent source term C m (based on i
sample results from Technical Specification Table 4.11-2) combined with the Gaseous Waste Processing System source term for the tank planned for release, qt, as follows:
(Q I
(
im GP
- Oim + 91 2-9
. -y Exception 2:
monitor response corresponding to the C,
=
concentration resulting from the combined release; this concentration value is obtained by dividing b(Qm)GP by the combined flow i
1 rate (ml/sec) through the plant vent.
(See Subsection 2.1.4 for further discussion of monitor response.)
2.1.3.2 Reactor Containment Purge Monitors:
RE-2565C (One for each unit)
Unit 1 containment purge discharges through the Unit 1 plant vent; Unit 2 containment purge discharges through the Unit 2 plant vent.
Therefore, the containment purge monitor is not the final monitor for containment purge releases.
- However, 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.
The methodology presented in Subsection 2.1.2 applies to this monitor with the following five exceptions:
Exception 1:
[K t"#t = C,f- ( (X/Q) g i
g qt)
(8)
R Exception 2:
C, mcnitor response of the containment purge
=
monitor for radionuclide concentrations to be discharged (sample taken and analyzed prior to discharge).
(See Subsection 2.1.4 for further discussion of monitor response.)
2-10
Exception 3:
qt rate of release of noble gas radionuclide 1
=
(uci/sec) from containment purge, determined by multiplying the expected release rate by the concentration of radionuclide i.
Exception 4:
E R, = r
= C,
((X/Q)M i Ibi + 1.1M ) qt)
(9) s g
Exception 5:
AG
,=
a selected allocation factor value which must be less than the allocation factor for the monitor serving the final release point, the respective plant vent.
When containment purge releases are to be made, it will be necessary to redetermine the setpoint for the respective plant vent monitor (RE-12442C) which is downstream from the containment purge monitor (RE-2565C).
Redetermination of this setpoint is accomplished by applying the methodology of Subsection 2.1.2 with the following two exceptions:
f Exception 1:
A new source term, (Qim)CP, is determined which includes the routine respective plant vent source term Qim (based on sample results from Technical Specification Table 4.11-2) combined with the containment purge source term for the unit containment planned for release, qi, as follows:
(Qim)CP " Oim + 91
( 0) 2-11
t Exception 2:
C, monitor response corresponding to the
=
concentration resulting from the combined release; this concentration value is obtained by dividing (Qig)CP by the combined flow rate (ml/sec) through the plant vent.
(See I
Subsection 2.1.4 for further discussion of 1
l monitor response.)
2.1.4 Consideration of Monitor Response and Background in Establishing Gaseous Effluent Monitor Setpoints The calculated monitor setpoint, c, establishes the s
base value for the monitor setpoint.
The monitor setpoint calculation includes the monitor response term, C.
The monitor m
response is the net monitor reading corresponding to the measured concentration of the particular noble gas sample.
The monitor response may be obtained by observing the net monitor reading at the time the noble gas sample is taken.
The monitor response may I
also be determined by multiplying the measured noble gas concentration by the calibration factor for the particular 1
monitor.
It is important to note that the monitor response corresponds to the release rate and/or dose rate only for the specific conditions of release flow rate and radionuclide-specific concentrations determined for the release under consideration.
i If any monitor adjustments are to be made which affect
(
monitor response to radionuclide concentrations, such as gain factor adjustments, these adjustments must be made prior to determining the monitor response, C, which is to be used in the i
m setpoint calculation for a particular monitor.
2-12
The actual monitor setpoint, csp, must include the calculated basic setpoint, c, plus monitor background, BG.
s Contributions to background radiation levels may include ambient background, plant environmental background at monitor locations when plant is in shutdown status, plant environmental background 1
at monitor location when plant is at power, and internal background of monitor due to contamination of sample chamber.
Background levels must be controlled such that radioactivity levels in the effluent stream being monitored can be accurately assessed at or below the calculated setpoint value.
i 2.1.5 Determination of Allocation Factor, AG When simultaneous gaseous releases are made to the environment, an (administrative) allocation factor must be applied to each discharge pathway.
This is to ensure that simultaneous gaseous releases from the site to unrestricted areas 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 2 turbine building vent, and the radwaste salidification building vent.
The allocation factor for each gaseous discharge pathway must be between 0 and 1 and the sum of the allocation factors for the simultaneous releases must not exceed 1.
There are three methods by which allocation factors may be determined:
i I
l 1.
The allocation factor for a particular release pathway may be l
administrative 1y 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.
l l
l 2-13 l
- u -
t
'~~~v
^-
~3 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 discharge pathway by calculating the ratio of the total body dose rate due to noble gases released from the particular discharge 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 radwaste solidification building vent (ground-level releases) :
IX/OI
[K AG =
G i
gQiq(r)
(12) 2 (X/Q) G i
IO I
lg ng +
II/OI IO I
M i
im nm For Unit 1 plant vent and Unit 2 plant vent (mixed-mode releases) :
i II/OI KgQim(r)
AG =
M (13) 2 (X/Q) G Kg (Qg )ng +
g M
i im nm Where ng is the number of simultaneous vent releases (ground level); nm is the number of simultaneous vent releases (mixed-mode); and (r) is the particular discharge pathway for which an allocation f actor is being determined.
2-14
_ = x t.
- L
_.. :.._. 2 -.-- - -
L-2" TABLE 2.1-1 DOSE FACTORS FOR EXPOSURE TO A SEMI-INFINITE CLOUD OF NOBLE GASES
- Gamma Beta Gamma Beta Nuclidh
-B od y* * * ( K )
-S k in * * * (L)
-A i r* * (M)
-A i r * * (N )
Kr-83m 7.56E-02 1.93E+01 2.88E+02 Kr-85m 1.17E+03 1.46E+03 1.23E+03 1.97E+03 Kr-85
.l.61E+01 1.34E+03 1.72E+01 1.95E+03 Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03 Kr-89 1.66E+04 1.01E+04 1.73E+04 1.06E+04 Kr-90 1.56E+04 7.29E+03 1.63E+04 7.83E+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 1.48E+03 Xe-133 2.94E+02 3.06E+02 3.53E+02 1.05E+03 Xe-135m 3.12E+03 7.11E+02 3.36E+03 7.39E+02 Xe-135 1.81E+03' l.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 4.13E+03 9.21E+03 4.75E+03 l
Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03
- Values taken from Reference 3, Table B-1 3
- mead-m uCi-yr 3
- mrem-m uCi-yr 2-15
i'
. * - ~ _ _.
~ L_.. _ z. 2 - ^
..L.-- L TABLE 2.1-2 GASEOUS RELEASE POINTS FLOW RATES Release Point Flow Rates 3
f t / min ml/sec 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 6
2-16
2.2 GASEOUS EFFLUENT DOSE RATE AND DOSE CALCULATIONS 2.2.1 Dose Rates-at or beyond Site Boundary 2.2.1.1 Dose Rates Due to Noble Gases For the purpose of implementing Technical Specification 3.ll.2.l(a), the dose rate in areas at or beyond the site boundary due to noble gases shall be calculated as follows:
D
=
t total body dose rate at time of release (mrem /yr)
EE
^
M nm {i g E
(X/Q)G ng (01g)ng
+
IX/CI
=
K (Qgg)nm I14) i i
2 D
= skin doso rate at time of release (mrem /yr) 3
[ [ IL bb I
2 ig ng + IR70)M nm i Ibi + 1
- 1M ) (Qim}nm (15)
(X/C)G ng i i + 1* 1M ) IO
=
1 i
Where ng is the number of simultaneous ground-level vent releases and nm is the number of simultaneous 2
mixed-mode vent releases.
Other terms were defined previously in Subsection 2.1.
The dose rate limits are site limits 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.
However, since the limits of Technical Specification 3.11.2.1 2
apply at any point in time, ground-level dispersion values are used in lieu of mixed-mode values as discussed in Subsection 2.1.2.
(See NOTE in Subsection 2.1.2).
3 2-17
.n~.-
l3 4
2.2.1.2 Dose Rates Due to I-131, I-13 3, Tritium, and Particulates For the purpose of implementing Technical Specification 3.ll.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 pathway for the child age group.
The child age group would experience the highest potential dose rate via the inhalation pathway.
These dose rates are calculated as follows:
D
=
o organ dose rate at time of release (mrem /yr)
(X/Q)G ng io ig ng
=
P IO I
+
I I
P M
gg (Q{,)nm
(
}
2 where nm and ng
,=
defined previously in subsection 2.2.1.1 2
(X/Q) G defined previously in subsection 2.1.1
=
(X/Q)M defined previously in subsection 2.1.2
=
Q{g release rate (uci/sec) of I-131, I-133, tritium
=
and particulates from Unit 1 turbine building vent; Unit 2 turbine building vent'; and radwaste solidification building vent, which are ground-level releases.
Q{,
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.
i P go organ dose parameter for organ o and radionuclide
=
3 i, (arem/yr per uCi/m ) for inhalation determined as follows:
2-18
P
= K ' (BR) DF (17) gg ig and where 6
I: '
constant of unit conversion, 10 pci/uci
=
breathing rate for child age group; 3700 BR
=
3 m /yr from Table 2.2-10 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 3.11.2.l(b),
the potential organ dose rate D must be limited o
as follows:
g f{ (AG) (GF) 1500 mrem /yr (18)
D where AG and 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 (See NOTE in Subsection 2.1.2).
3 2-19
w p x -..
u..-
---w-
~~
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:
air dose due to gamma emissions from noble gas D
=
gamma radionuclides (mrad)
-8 g$gg+(X/Q)g M E, 3.17 x 10 (X/Q)g M
=
(19) 2 y
g g where 3.17 x 10-8 the fraction of one year per one second
=
Q tg cumulative release of noble gas radionuclide
=
i over the period of interest (uci) from the vent release (ground-level) under consideration.
Qg, cumulative release of noble gas radionuclide
=
i over the period of interest (uCi) from the vent release (mixed-mode) under consideration.
M g defined previously in Subsection 2.1.1
=
(X/Q)g defined previously in Subsection 2.1.1
=
6.83 x 10-5,,ef,3 in the ENE sector (X/Q)g 2[
=
beta air dose due to beta emissions from noble gas D
=
radionuclides (mrad).
E (X/Q)g[g
-8
~ '
~
3.17 x-10 (X/Q)g yNg gg
=
Q
+
N Q,
(20) 2 g
g 2-20 f
I where air dose factor due to beta emissions from Ng
=
noble gas radionuclide 1 (mrad /yr per 3
uCi/m ),
from Table 2.1-1.
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 pathways, are presented in Table 2.2-12.)
Dj dose to an organ j of an individual in age-
=
group a from radiolodines, tritium, and radionuclides in particulate form with half-lives greater than eight days (mrem).
-0 3.17 X 10 j
R p
alpj (wbP OEg
- NbP 0{m)
(21)
=
where I
l 3.17 x 10-8 fraction of one year per one second.
=
l lG l
pi for all pathways and all isotopes
=
l l
Wfp pathway-dependent relative dispersion or
=
i deposition at the location of the controlling 1
2-21 l
4 receptor, associated with ground-level plant a
releases as follows:
(X/Q')gp
. annual average relative dispersion parameter
=
for location of controlling (critical) receptor for ground-level plant releases.
(X/Q')gp applies only to inhalation and all tritium pathways.
(For all tritium pathways 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.
Wj'gp pathway-dependent relative dispersion or
=
deposition at the location of the controlling receptor, associated with plant vent releases, which are mixed-mode as follows:
(X/Q')gp annual average relative dispersion parameter
=
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 Q{
l source term is limited to tritium.)
See l
Table 2.2-12 for values.
l l
(D/Q ' ) MP annual average deposition parameter for the l
=
location of controlling (critical) receptor j
for mixed mode releases.
(lE77') MP applies to all other pathways.
See Table 2.2-12 for values.
l 2-22 l
_,,_._._m_
- -. - - + - - - - - - - -. - -
_,2 The selection of the dispersion or deposition parameter, X/Q or D/Q, is dependent upon the pathway being considered.
The dispersion parameter, X/Q, 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[{g 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 Q'ig term is limited to tritium.)
lla cumulative release (uCi), from the mixed-mode
=
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 2-23
m.
dose contributions due to tritium from the ingestionpathways,thetermQ}m is limited to tritium.)
alpj pathway-specific, individual age-specific, R
=
organ dose factor for radionuclide, i, pathway p, organ j, and individual age group, a.
Routine individual dose calculations address
'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 2
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 3
Raipj K ' (BR) a (DFA j)a mrem /yr per uCi/m (22)
=
i where constant of unit conversion 106 K'
pCi/uCi
=
(BR) a the breathing rate for a particular age group
=
3 in m / year from Table 2.2-10.
DFA ja the inhalation dose factor for receptor age l
=
group a, organ j, and for radionuclide i, in mrem /pci from Tables 2.2-1 through 2.2-4.
2-24 wr--
y v.
,y er-.-.r.
s,-.
,-,m rw-,,,.
---,---n,-r--y--r----,.,w--,,,-n,-,-c
,-p
-y-,
w--
, ~, -
tdr Ground-Plane Pathway Factor
=
t R,ipj K'K" (SHF) (DFG j) ((1-e i )fx )
i 2
(m mrem / year per uCi/sec)
(23) i constant of unit conversion, 106 K'
=
pCi/uCi.
K" constant of unit conversion, 8760 hr/yr.
=
SHF shielding factor, 0.7 (dimensionless) 1
=
DFG j ground plane dose conversion factor for
=
i radionuclide i (same for all age groups and specific organs are assumed to receive the same dose as the total body) (mrem /hr per 2
pCi/m ) Table 2.2-9.
A t decay constant for radionuclide i, in see -1
=
exposure time, 4.73 x 108 t
=
sec (15 years).
Vegetation Pathway Factor t
R,ip$ = K'y {7,3 )
(DFL gg)a I al 1,
il+U f
e i hv)
(24) as g
2 (m mrem / year per uCi/sec) where a constant of unit conversion, 106 K'
=
pCi/uci.
fraction of deposited activity retained on r
=
vegetation. (1.0 for radioiodines; 0.2 for particulates.)
2-25
__T U,1 the consumption rate of fresh leafy
=
vegetation by the receptor in age group a, in kg/ year.
(See Table 2.2-10) the consumption rate of stored vegetation by U
=
as the receptor in age group a, in kg/ year.
(See Table 2.2-10) f t the fraction of the annual intake of fresh
=
leafy vegetation grown locally.
f the fraction of the annual intake of stored
=
g vegetation grown locally.
1
,=
the average time between harvest of leafy t
vegetation and its consumption in 4
seconds. (8.6 x 10 )
thy the average time between harvest of stored
=
vegetation and its consumption in seconds.
6 (5.18 x 10 )
2 the vegetation areal density, in kg/m,
Y
=
y (DFL j),
the organ ingestion dose f actor for the ith
=
i radionuclide for the receptor in age group a, in mrem /pCi from Tables 2.2-5 through 2.2-8.
i A i the decay constant for the ith radionuclide,
=
in sec -1 Aw the decay constant for removal of activity on
=
leaf and plant surf aces by weathering, 5.73 x 10-7 sec -1 (corresponding to a 14 day half-life).
2-26
For tritium in vegetation, the vegetation pathway factor is a =pecial case due to the fact that the concentration of tritium in vegetation is based on airborne concentration rather than deposition:
aipj K'K' "(U R
f f
al l + Uasg) (DFL j), (0.75 (0.5/H) )
=
i (mrem /yr per uCi/m )
(25) where 3
K'"
a constant of unit conversion, 10 gm/kg.
=
H absolute humidity of the atmosphere, in
=
3 gm/m,
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 parameters and values are given aoove.
Grass-Cow-Milk Pathway Factor
-1 t
~
f f
R,g 3 = K'yO (U,p) F,(r) (DFLig)a s + Il-f f)e A. t i hm p
p ps e
1
( 6) p
,7 Y
Y p
3 2
(m mrem /yr per uCi/sec) where 0
K' a constant of unit conversion, 10 pCi/uCi.
=
Qp the cow's consumption rate, in kg/ day (wet
=
weight).
2-27
$ggp I
U,p the receptor's milk consumption rate for age
=
i group a, in liters /yr from Table 2.2-10.
the agricultural productivity by unit area of Y
=
p 2
pasture feed grass, in kg/m,
the agricultural productivity by unit area of Y
=
3 2
stored feed, in kg/m,
F, the stable element transfer coefficients, in
=
days / liter.
(See Table 2.2-11.)
fraction of deposited activity retained on r
=
feed grass. (1.0 for radioiodines; 0.2 for particulates) 1 (DFL j ) a the organ ingestion dose factor for the ith
=
i radionuclide for the receptor in age group a, in mrem /pci from Tables 2.2-5 through 2.2-8.
A the decay constant for the ith radionuclide,
=
i in sec-1 py, the decay constant for removal of activity on
=
leaf and plant surfaces by weathering, 5.73 x 10-7
-1 sec (corresponding to a-14 day half-life).
the transport time from pasture to cow, to tg
=
5 milk, to receptor, in sec. (1.73 x 10
),
thm the transport time from pasture, to harvest,
=
to cow, to milk, to receptor, in sec. (7.78 x 6
10 ),
2-28
M fraction of the year that the cow is on f
=
p pasture (dimensionless).
fraction of the cow feed that is pasture f
=
s grass while the cow is on pasture j.
(dimensionless).
For tritium in milk, the grass-cow-milk pathway factor is a special case due to the fact that the concentration of tritium in milk is based on airborne concentration rather than deposition:
alpj K'K'"F,Qp ap(DFLi$ ), (0. 75 (0. 5/H) )
R
=
U 3
(mrem /yr per uCi/m )
(27) where a constant of unit conversion, 103 K'"
gm/kg.
=
H absolute humidity of the atmosphere, in
=
3 gm/m,
s,
0.75 =
the fraction of total feed that is water.
4 i
0.5 the ratio of the specific activity of the
=
feed grass water to the atmospheric water.
and other parameters and values as previously defined.
Grass-Goat-Milk Pathway Factor Il~f f ), y ti hm R,g 3 = K'7Op (U,p) F,( r) (DFL g$),
ffps+
p s
-A t
(
}
p
,7 y
y p
s 2
(m mrem /yr per uCi/sec) 2-29
$4:
t where 6
K' a constant of unit conversion, 10 pCi/uci.
=
the goat's consumption rate, in kg/ day (wet Qy
=
weight).
s.
5 U,p the receptor's milk consumpt on rate for age
=
j group a, in liters /yr from Table 2.2-10.
s R
the'agricult' ural; productivity by unit area'of Y
=
p pasture feed grIss, in kg/m,
2 g,
Y the agricultural productivity.by unit area of
=
s I
stored feed, in kg/m,
2
.r m
the stable element transfer coefficients, in F
=
days / liter.
(See Table 2.2-11.)
d
/
r
=
fraction of deposited activity retained. on i
feed grass.
(1.0 for radioiodines; 0.2 for r
/
('
particulates) s; (DFL j),
the organ ingestion dose factor for the ith
=
i radionuclide for the receptor in ' age group a, in mrem /pci from Tables 2.2-5 through 2.2-8.
4 v
Ai the decay constant for the ith radionuclide,
=
in sec~1 i
A, the decay constant for removal of activity on
=
leaf and plant surf aces by weathering, 5.73 x
,V 10-7 sec (corresponding to a 14 day half-
-1 g,
!P, life).
V, 2-30
+,, - -,.,, - - _., -, _ _..
_,...... - _ _,. _ ~,. _ _..
,,.,,c
_m..., _.
tg the transport time from pasture to goat, to
=
5 milk, to receptor, in sec. (1.73 x 10 )
thm the transport time from pasture, to harvest,
=
to goat, to milk, to receptor, in sec. (7.78 6
x 10 )
fp fraction of the year that the goat is on
=
pasture (dimensionless),
f fraction of the goat feed that is pasture l
=
s grass while the goat is on pasture l
(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 K' K ' "F,Qp ap (DFL j ) a (0.75 (0.5/H) )
U
=
alpj i
3 (mrem /yr per uCi/m )
(29) l where:
3 K'"
a constant of unit conversion, 10 gm/kg.
=
l l
H absolute humidity of the atmosphere, in
=
i-gm/m.
3 l
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.
2-31
3 Grass-Cow-Meat-Pathway-Factor
~
t O (U
)
ffp s, (1-f f )e
-At i hm p
s R,g 3 = K'y Fg (r) (Eg3 ),
g f f (30) p y
Y w
p 2
(m mrem /yr per uCi/sec) where 6
K' a constant of unit conversion, 10 pCi/uCi.
=
Op the cow's consumption rate, in kg/ day (wet
=
weight).
U,p the receptor's meat consumption rate for age
=
group a, in kg/yr from Table 2.2-10.
p the agricultural productivity by unit area of Y
=
2 pasture feed grass, in kg/m,
the agricultural productivity by unit area of Y
=
s 2
stored feed, in kg/m,
Fg The stable element transfer coefficients, in
=
days /kg. (see Table 2.2-11.)
fraction of deposited activity. retained on r
=
feed grass.
(1.0 for radiolodines; 0.2 for I
particulates) 2-32
,n,-,,
w
=.9 (DFL j),
the organ ingestion dose factor for the ith
=
i 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
-1 sec (corresponding to a 14 day half-life).
tg the transport time from pasture to cow, to
=
6 meat, to receptor, in sec. (1.73 x 10 )
hm the transport time from pasture, to harvest, t
=
to cow, to meat, to receptor, in s ec. (7.78 x 6
10 )
fraction of the year that the cow is on f
=
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 f act that the concentration of tritium -in meat is based on airborne concentration rather than deposition:
R K'K'"F Qp ap (DFL j) a (0.75 (0.5/H) )
U
=
alpj f
i 3
(mrem /yr per uCi/m )
(31) 2-33
m where:
K'"
a constant of unit conversion, 103
=
gm/kg.
H absolute humidity of the atmosphere, in
=
l gm/m,
3 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.
2.2.2.3 Dose. Calculations to Support Other Technical Specifications 1
In the event radiological impact assessment becomes t
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 (Ralpj) for the receptor of interest.
l 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 recep tor.
The necessary dose calculations may be performed using 2-34
-9n
-___,_..m..
,-m
..u-,_y
,c-
.~%,
r,,_.
,,,,,.,,,,_.,.,,m..
,,%,,ey..~m,.,
g,.,
,w,,
..g.-.
-__.w
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 recep tor (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.
2-34a
L TABLE 2.2-1
.INEALATION 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 4.62E-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 Fa-55 1.41E-05 8.39E-06 2.38E-06 No Data No Data 6.21E-05 7.82E-07 4
FO-59 9.69E-06 1.68E-05 6.77E-06 No Data No Data 7.25E-04 1.77E-05 4
^
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
-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-ll 5.13E-12 No Data 2.87E-ll 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-84 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-24 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 i
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 j
Sr-92 7.50E-09 No Data 2.79E-10 No Data No Data 1.70E-05 1.00E-04 1
Y-90 2.35E-06 No Data 6.30E-08 No Data No Data 1.92E-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
' l.17E-08 No Data 3.29E-10 No Data No Data 1.75E-05 9.04E-05 Reference 3, Table E-10.
2-35 n
,-m,,~--.a
,-,----m,,,
-,,--.m-r
.,,m, n.w-,v,,-
.v,e
-e,
--w,
,-r--
n,--ees--,--m--me, w-e-
,r-
L TABLE 2.2-1 CONT'D j
INH"ALATION DOSE FACTORS FOR INFANT *
(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-11 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 3.74E-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 S.16E-06 3.57E-06 No Data 7.80E-06 2.62E-03 2.36E-05 1
Ta-125M 3.40E-06 1.42E-06 4.70E-07 1.16E-06 No Data 3.19E-04 9.22E-06 Ts-127M 1.19E-05 4.93E-06 1.48E-06 3.48E-06 2.68E-05 9.37E-04 1.95E-05 Ta-127 1.59E-09 6.81E-10 3.49E-10 1.32E-09 3.47E-09 7.39E-06 1.74E-05 Ta-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-ll 1.34E-ll 4.82E-ll 1.25E-10 2.14E-06 1.88E-05 Ta-131M 7.62E-08 3.93E-08 2.59E-08 6.38E-08 1.89E-07 1.42E-04 8.51E-05 To-131 1.24E-ll 5.87E-12 3.57E-12 1.13E-11 2.85E-ll 1.47E-06 5.87E-06 To-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 1.37E-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 Cs-134 2.83E-04 5.02E-04 5.32E-05 No Data 1.36E-04 5.69E-05 9.53E-07 Cc-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 Ba-139 1.06E-09 7.03E-13 3.07E-11 No Data 4.23E-13 4.25E-06 3.64E-05 f
B0-140 4.00E-05 4.00E-08 2.07E-06 No Data 9.59E-09 1.14E-03 2.74E-05 B C-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-ll 2.36E-14 1.40E-12 No Data 1.36E-14 1.11E-06 4.95E-07 140 3.61E-07 1.43E-07 3.68E-08 No Data No Data 1.20E-04 6.06E-05 2-36 c
t TABLE 2.2-1 CONT'D INHhLATION DOSE FACTORS FOR INFANT *
(MREM PE: PCI INHALE 0)
Page 3 of 3 Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI Lc-142 7.36E-10 2.69E-10 6.46E-ll No Data No Data 5.87E-06 4.25E-05 Ca-141 1.98E-05 1.19E-05 1.42E-06 No Data 3.75E-06 3.69E-04 -1.54E-05 Ca-143 2.09E-07 1.38E-07 1.58E-08 No Data 4.03E-08 8.30E-05 3.55E-05 Co-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-ll 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 I
i i
I 2-37
TABLE 2.2-2 INHALATION DOSE FACTORS FOR CHILD *
(MREM PER PCI INHALED)
Page 1 of 3 Nuclide Bone Liver T Body Thyroid _
Kidney 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 Nn-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 Fa-55 1.28E-05 6.80E-06 2.10E-06 No Data No Data 3.00E-05 7.75E-07 Fa-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 Z"-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-11 2.61E-11 2.41E-12 No Data 1.58E-11 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 l
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 6.49E-06 6.55E-05 Y-90 1.llE-06 No Data 2.99E-08 No Data No Data 7.07E-05 7.24E-05 l
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. 4 6E -05 R3ference 3, Table E-9.
2-38
TABLE 2.2-2 CONT'D IN8ALATION DOSE FACTORS FOR CHILD *
(MREM PER PCI INHALED)
{
Page 2 of 3 Nuclide Bone Liver T Body-Thyroid Kidney Lung GI-LLI l
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 Ta-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 Ta-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 iw-129 2.64E-ll 9.45E-12 6.44E-12 1.93E-ll 6.94E-ll 7.93E-07 6.89E-06 Ta-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-11 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 1.10E-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 Co-134 1.76E-04 2.74E-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 Co-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-11 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 1.72E-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 -10 140 1.74E-07 6.08E-08 2.04E-08 No Data No Data 4.94E-05 6.10E-05 2-39
TABLE 2.2-2 CONT'D INIALATION 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-11 No Data No Data 2.35E-06 2.05E-05 Co-141 1.06E-05 5.28E-06 7.83E-07 No Data 2.31E-06 1.47E-04 1.53E-05 l
Co-143 9.89E-08 5.37E-08 7.77E-09 No Data 2.26E-08 3.12E-05 3.44E-05
~
Co-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-11 4.99E-12 8.10E-13 No Data 2.64E-12 4.23E-07 5.32E-08 Nd-147 2.9 2E-0 6 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 j
9 2-40
TABLE 2.2-3 INHALATION DCSE FACTORS FOR TEENAGER *
(MREM PER PCI INHALED)
Page 1 of 3 Nuclide 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 Nn-24 1.72E-06 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-11 No Data 2.24E-10 1.90E-06 7.18E-06 FG-55 4.18E-06 2.98E-06 6.93E-07 No Data No Data 1.55E-05 7.99E-07 Fa-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 3.47E-07 No Data No Data 1.68E-04 1.19E-05 Co-60 No Data f.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-ll 1.59E-11 No Data No Data 1.17E-06 4.59E-06 Cu-64 No Data 2.54E-10 1.06E-10 No Data 8.01E-10 1.39E-06 7.68E-06 1 -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 1.15E-11 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 No 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. 8 2E-08 3.40E-08 No Data No Data No Data 3.65E-15 Rb-89 No Data 4.40E-08 2.91E-08 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 j
i 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-11 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 No Data 2.21E-06 No Data No Data 3.67E-04 5.11E-05 Y-92 1.84E-09 No Data 5.36E-ll No Data No Data 3.35E-06 2.06E-05 Reference 3, Table E-8 l
2-41 j
1 TABLE 2.2-3 CONT'D 3
INHALATION DOSE FACTORS FOR TEENAGER *
(MREM PER PCI INHALED)
P. age 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 1.55E-06 No Data 2.38E-05 2.01E-03 1.20E-04 Ag-110 M 1.73E-06 1.64E-06 9.99E-07 No Data 3.13E-06 8.44E-04 3.41E-05 To-125M 6.10E-07 2.80E-07 8.34E-08 1.75E-07 No Data 6.70E-05 9.38E-06 Ta-127M 2.25E-06 1.02E-06 2.73E-07 5.48E-07 8.17E-06 2.07E-04 1.99E-05 To-127 2.51E-10 1.14E-10 5.52E-ll 1.77E-10 9.10E-10 1.40E-06 1.01E-05 T -129M 1.74E-06 8.23E-07 2.81E-07 5.72E-07 6.49E-06 2.47E-04 5.06E-05 To-129 8.87E-12 4.22E-12 2.20E-12 6.48E-12 3.32E-ll 4.12E-07 2.02E-07 Ta-131M 1.23E-08 7.51E-09 5.03E-09 9.06E-09 5.49E-08 2.97E-05 7.76E-05 To-131 1.97E-12 1.04E-12 6.30E-13 1.55E-12 7.72E-12 2.92E-07 1.89E-09 To-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 8.11E-07 i
I-132 1.99E-07 5.47E-07 1.97E-07 1.89E-05 8.65E-07 No Data 1.59E-07 i
I-133 1.52E-06 2.56E-06 7.78E-07 3.65E-04 4.49E-06 No Data 1.29E-06 j
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 C2-134 6.28E-05 1.41E-04 6.86E-05 No Data 4.69E-05 1.83E-05 1.22E-06 l
Co-136 6.44E-06 2.42E-05 1.71E-05 No Data 1.38E-05 2.22E-06 1.36E-06 I
C3-137 8.38E-05 1.06E-04 3.89E-05 No Data 3.80E-05 1.51E-05 1.06E-06 Cc-138 5.82E-08 1.07E-07 5.58E-08 No Data 8.28E-08 9.84E-09 3.38E-11 Bo-139 1.67E-10 1.18E-13 4.87E-12 No Data 1.11E-13 8.08E-07 8.06E-07 i
B0-140 6.84E-06 8.38E-09 4.40E-07 No Data 2.85E-09 2.54E-04 2 86E-05 Be-141 1.78E-ll 1.32E-14 5.93E-13 No Data 1.23E-14 4.11E-07 9.33E-14 l
BB-142 4.62E-12 4.63E-15 2.84E-13 No Data 3.92E-15 2.39E-07 5.99E-20 140 5.99E-08 2.95E-08 7.82E-09 No Data No Data 2.68E-05 6.09E-05 2-42
^7 TABLE 2.2-3 CONT'D INHA'LATION DOSE FACTORS FOR TEENAGER *
(MREM PER PCI INHALED)
Page 3 of 3 i
Nuclide Bone Liver T Bcdy Thyroid Kidney Lung GI-LLI Ln-142 1.20E-10 5.31E-11 1.32E-ll No Data No Data 1.27E-06 1.50E-06
.CO-141 3.55E-06 2.37E-06 2.71E-07 No Data 1.llE-06 7.67E-05 1.58E-05 Ca-143 3.32E-08 2.42E-08 2.70E-09 No Data 1.08E-08 1.63E-05 3.19E-05 CO-144 6.llE-04 2.53E-04 3.28E-05 No Data 1.51E-04 1.67E-03 1.08E-04 Pr-143 1.67E-06 6.64E-07 8.28E-08 No Data 3.86E-07 6.04E-05 2.67E-05 Pr-144 5.37E-12 2.20E-12 2.72E-13 No Data 1.26E-12 2.19E-07 2.94E-14 Nd-147 9.83E-07 1.07E-06 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 8.11E-06 1.65E-05 I
1 a
2-43
]
TABLE 2.2-4 4-INHALATION DOSE FACTORS FOR ADULTS *
(MREM PER PCI INHALED)
Page 1 of 3 Nuclide 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 NC-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-11 No Data 1.63E-10 1.18E-06 2.53E-06 Fo-55' 3.07E-06 2.12E-06 4.93E-07 No Data No Data
- 9. ole-06 7.54E-07 Fo-59 1.47E-06 3.47E-06 1.32E-06 No Data No Data 1.27E-04 2.35E-05 Co-58 No Data 1.98E-07 2.59E-07 No Data No Data 1.16E-04 1.33E-05 Co-60 No Data 1*. 4 4E-0 6 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 4
Ni-65 1.92E-10 2.62E-11 1.14E-11 No Data No Data 7.00E-07 1.54E-06 i
Cu-64 No Data 1.83E-10 7.69E-ll No Data 5.78E-10 8.48E-07 6.12E-06
?n-65 4.05E-06 1.29E-05 5.82E-06 No Data 8.62E-06 1.08E-04 6.68E-06 I
tu-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 I
Rb-88 No Data 4.84E-08 2.41E-08 No Data No Data No Data 4.18E-19 i
Rb-89 No Data 3.20E-08 2.12E-08 No Data No Data No Data 1.16E-21 l
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 l
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 l
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-11 No Data No Data 1.96E-06 9.19E-06 i
i 6
Reference 3, Table E-7.
i 2-44 i
TABLE 2.2-4 CONT'D INHIALATION DOSE FACTORS FOR ADULTS *
(MREM PER PCI INHALED)
Page 2 of 3 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 3.71E-09 9.84E-06 6.54E-05 Nb-95 1.76E-06 9.77E-07 5.26E-07 No Data 9.67E-07 6.31E-05 1.30E-05 Mo-99 No Data 1.51E-08 2.87E-09 No Data 3.64E-08 1.14E-05 3.10E-05 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-11 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 1.14E-04 Ag-110M 1.35E-06 I.25E-06 7.43E-07 No Data 2.46E-06 5.79E-04 3.78E-05 To-125M 4.27E-07 1.98E-07 5.84E-08 1.31E-07 1.55E-06 3.92E-05 8.83E-06 To-127M 1.58E-06 7.21E-07 1.96E-07 4.11E-07 5.72E-06 1.20E-04 1.87E-05 To-127 1.75E-10 8.03E-ll 3.87E-11 1.32E-10 6.37E-10 8 14E-07 7.17E-06 Ta-129M 1.22E-06 5.84E-07 1.98E-07 4.30E-07 4.57E-06 1.45E-04 4.79E-05 te-129 6.22E-12 2.99E-12 1.55E-12 4.87E-12 2.34E-11 2.42E-07 1.96E-08 To-131M 8.74E-09 5.45E-09 3.63E-09 6.88E-09 3.86E-08 1.82E-05 6.95E-05 t
l To-131 1.39E-12 7.44E-13 4.49E-13 1.17E-12 5.46E-12 1.74E-07 2.30E-09 To-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 6.60E-07 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 f.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 Cc-134 4.66E-05 1.06E-04 9.10E-05 No Data 3.59E-05 1.22E-05 1.30E-06 Cc-136 4.88E-06 1.83E-05 1.38E-05 No Data 1.07E-05 1.50E-06 1.46E-06 Cc-137 5.98E-05 7.76E-05 5.35E-05 No Data 2.78E-05 9.40E-06 1.05E-06 Cc-138 4.14E-08 7.76E-08 4.05E-08 No Data 6.00E-08 6.07E-09 2.33E-13 Bc-139 1.17E-10 8.32E-14 3.42E-12 No Data 7.78E-14 4.70E-07 1.12E-07 Bc-140 4.88E-06 6.13E-09 3.21E-07 No Data 2.09E-09 1.59E-04 2.73E-05 Be-141 1.25E-ll 9.41E-15 4.20E-13 No Data 8.75E-15 2.42E-07 1.45E-17 Bo-142 3.29E-12 3.38E-15 2.07E-13 No Data 2.86E-15 1.49E-07 1.96E-26 14'O 4.30E-08 2.17E-08 5.73E-09 No Data No Data 1.70E-05 5.73E-05 2-45
.4.-_-+u._
s TABLE 2.2-4 CONT'D INH' LATION DOSE FACTORS FOR ADULTS
- A (MREM PER PCI INHALED)
Page 3 of 3 Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI LO-142 8.54E-11 3.88E-11 9.65E-12 No Data No Data 7.91E-07 2.64E-07 Co-141 2.49E-06 1.69E-06 1.91E-07 No Data 7.83E-07 4.52E-05 1.50E-05 Co-143 2.33E-08 1.72E-08 1.91E-09 No Data 7.60E-09 9.97E-06 2.83E-05 C2-144 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 Pr-144 3.76E-12 1.56E-12 1.91E-13 No Data 8.81E-13 1.27E-07 2.69E-18 Nd-147 6.59E-07 7.62E-07 4.56E-08 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 I
I J
k l
1 2-46
--c.-
r-r_,
.,-.._...m,
--y-...,-,,-,----,
TABLE 2 2-5 INdESTION DOSE FACTORS FOR INFANT *
(MREM PER PCI INGESTED)
Page 1 of 3
,Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI 1
3-H-3 No Data 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07
.C-14 2.37E-05 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 No-24 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 c
P-32 1.70E-03 1.00E-04 6.59E-05 No Data No Data No Data 2.30E-05 Cr-51 No Data No Data 1.41E-08 9.20E-09 2.01E-09 1.79E-08 4.11E-07 Mn-54 No Data 1.99E-05 4.51E-06 No Data 4.41E-06 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 FG-55 1.39E-05 8.98E-06 2.40E-06 No Data No Data 4.39E-06 1.14E-06 Fo-59 3.08E-05 5.38E-05 2.12E-05 No Data No Data 1.59E-05 2.57E-05 Cc-58 No Data 3.60E-06 8.98E-06 No Data No Data No Data 8.97E-06 i
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 i
Cu-64 No Data 6.09E-07 2.82E-07 No Data 1.03E-06 No Data 1.25E-05 2n-65 1.84E-05 6.31E-05 2.91E-05 No Data 3.06E-05 No Data 5.33E-05 L.-69 9.33E-08 1.68E-07 1.25E-08 No Data 6.98E-08 No Data 1.37E-05 Br-83 No Data No Data 3.63E-07 No Data 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 1
Br-85 No Data No Data 1.94E-08 No Data No Data No Data LT E-24 i
Rb-86 No Data 1.70E-04 8.40E-05 No Data No Data No Data 4.35E-06 I
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 Sr-89 2.51E-03 No Data 7.20E-05 No Data No Data No Data 5.16E-05 Sr-90 1.85E-02 No Data 4.71E-03 No Data No Data No Data 2.31E-04 Sr-91 5.00E-05 No Data 1.81E-06 No Data No Data No Data 5.92E-05 4
Sr-92 1.92E-05 No Data 7.13E -07 No Data No Data No Data 2.07E-04 Y-90 8.69E-08 No Data 2.33E-09 No Data No Data No Data 1.20E-04 4
Y-91M 8.10E-10 No Data 2.76E-ll No Data No Data No Data 2.70E-06 j
Y-91 1.13E-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 I
Reference 3, Table E-14.
2-47 l
- =
1 TABLE 2.2-5 CONT'D INdESTION DOSE FACTORS FOR INFANT *
(MREM PER PCI INGESTED)
Page 2 of 3
.Nuclide Bone Liver T Body Thyroid Kidney Lung 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 i
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 i
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 i
Ru-103 1.48E-06 No Data 4.95E-07 No Data 3.08E-06 No Data 1.803-05 i
Ru-10 5 1.36E-07 No Data 4.58E-08 No Data 1.00E-06 No Data 5.41E-05 1
Ru-106 2.41E-05 No Data 3.01E-06 No Data 2.85E-05 No Data 1.83E-04 Ag-110M 9.96E-07 7.27E-07 4.81E-07 No Data 1.04E-06 No Data 3.77E-05 To-125M 2.33E-05 7.79E-06 3.15E-06 7.84E-06 No Data No Data 1.llE-05 To-127M
.5.85E-05 1.94E-05 7.08E-06 1.69E-05 1.44E-04 No Data 2.36E-05 To-127 1.00E-06 3.35E-07 2.15E-07 8.14E-07 2.44E-06 No Data 2.10E-05 To-129M 1.00E-04 3.43E-05 1.54E-05 3.84E-05 2.50E-04 No Data 5.97E-05
'.-129 2.84E-07 9.79E-08 6.63E-08 2.38E-07 7.07E-07 No Data 2.27E-05 To-131M 1.52E-05 6.12E-06 5.05E-06 1.24E-05 4.21E-05 No Data 1.03E-04 To-131 1.76E-07 6.50E-08 4.94E-08 1.57E-07 4.50E-07 No Data 7.11E-06 i
Te-132 2.08E-05 1.03E-05 9.61E-06 1.52E-05 6.44E No Data 3.81E-05 i
I-130 6.00E-06 1.32E-05 5.30E-06 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 1.84E-06 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 i
Co-136 4.59E-05 1.35E-04 5.04E-05 No Data 5.38E-05 1.10E-05 2.05E-06 Co-137 5.22E-04 6.llE-04 4.33E-05 No Data 1.64E-04 6.64E-05 1.91E-06 CO-138 4.81E-07 7.82E-07 3.79E-07 No 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
?
4 j
2-48
D TABLE 2.2-5 CONT'D INCESTION DOSE FACTORS FOR INFANT *
(MREM PER PCI INGESTED)
Pag,e 3 of 3 Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI Bo-140 1.71E-04
- 1. 71E-07 8.81E-06 No Data 4.06E-08 1.05E-07 4.20E-05 Bc-141 4.25E-07 2.91E-10 1.34E-08 No Data 1.75E-10 1.77E-10 5.19E-06 Bc-142 1.84E-07 1.53E-10 9.06E-09 No Data
- 8. 81E-11 9.26E-ll 7.59E-07 LO-140 2.llE-08 8.32E-09 2.14E-09 No Data No Data No Data 9.77E-05 Lc-142 1.10E-09 4.04E-10 9.67E-11 No Data No Data No Data 6.86E-05 CO-141 7.87E-08 4.80E-08 5.65E-09 No Data 1.48E-08 No Data 2.48E-05 Co-143 1.48E-08 9.82E-06 1.12E-09 No Data 2.86E-09 No Data 5.73E-05 Co-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 3.4SE-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 2-49
TABLE 2 2-6 INGESTION DOSE FACTORS FOR CHILD *
(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 No-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 2.85E-06 No Data 3.00E-06 No Data 8.98E-06 j
Mn-56 No Data 3.34E-07 7.54E-08 No Data 4.04E-07 No Data 4.84E-05 l
Fo-55 1.15E-05 6.10E-06 1.89E-06 No Data No Data 3.45E-06 1.13E-06 FG-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 Cc-60 No Data 5.29E-06 1.56E-05 No Data No Data No Data 2.93E-05 Ni-63 5.38E-04 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 i
Cu-64 No Data 2.45E-07 1.48E-07 No Data 5.92E-07 No Data 1.15E-05 7"-65 1.37E-05 3.65E-05 2.27E-05 No Data 2.30E-05 No Data 6.41E-06 i
Zn-69 4.38E-08 6.33E-08 5.85E-09 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-?.4 1
l 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-L/
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 St-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 i
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 1
i l
Reference 3, Table E-13.
2-50 j
l
TAILE 2.2-6 CONT'D INGESTION DOSE FACTORS FOR CHILD *
(MREM PER PCI INGESTED)
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 1.70E-04 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-99 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 Ru-103 7.31E-07 No Data 2.81E-07 No Data 1.84E-06 No Data 1.89E-05 Ru-105 6.45E-08 No Data 2.34E-08 No Data 5.67E-07 No Data 4.21E-05 Ru-106 1 17E-05 No Data 1.46E-06 No Data 1.58E-05 No Data 1.82E-04 Ag-110M 5.39E-07 3'.64E-07 2 91E-07 No Data 6.78E-07 No Data 4.33E-05 To-125M 1.14E-05 3.09E-06 1.52E-06 3.20E-06 No Data No Data 1.10E-05 To-127M 2.89E-05 7.78E-06 3.43E-06 6.91E-06 8.24E-05 No Data 2.34E-05 To-127 4.71E-07 1.27E-07 1.01E-07 3.26E-07 1.34E-06 No Data 1.84E-05
- -129M 4.87E-05 1.36E-05 7.56E-06 1.57E-05 1.43E-04 No Data 5.94E-05 To-129 1.34E-07 3.74E-08 3.18E-08 9.56E-08 3.92E-07 No Data 8.34E-06 Ta-131M 7.20E-06 2.49E-06 2.65E-06 5.12E-06 2.41E-05 No Data 1.01E-04 To-131 8.30E-08 2.53E-08 2.47E-08 6.35E-08 2.51E-07 No Data 4.36E-07 To-132 1.01E-05 4.47E-06 5.40E-06 6.51E-06 4.15E-05 No Data 4.50E-05 I-130 2.92E-06 5.90E-06 3.04E-06 6.50E-04 8.82E-06 No Data 2.76E-06 I-131 1.72E-05 1.73E-05 9.83E-06 5.72E-03 2.84E-05 No Data 1.54E-06 l
I-132 8.00E-07 1.47E-06 6.76E-07 6.82E-05 2.25E-06 No Data 1.73E-06 I-133 5.92E-06 7.32E-06 2.77E-06 1.36E-03 1.22E-05 No Data 2.95E-06 I-134 4.19E-07 7.78E-07 3.58E-07 1.79E-05 1.19E-06 No Data 3 16E-07 i
I-135 1.75E-06 3.15E-06 1.49E-06 2.79E-04 4.83E-06 No Data 2.40E-06 Co-134 2.34E-04 3.84E-04 8.10E-05 No Data 1.19E-04 4.27E-05 2.07E-06 Co-136 2.35E-05 6.46E-05 4.18E-05 No Data 3.44E-05 5.13E-06 2.27E-06 Cc-137
.3.27E-04 3.13E-04 4.62E-05 No Data 1.02E-04 3.67E-05 1.96E-06 Cc-138 2.28E-07 3.17E-07 2.01E-07 No Dath 2.23E-07 2.40E-08 1.46E-07 Bo-139 4.14E-07 2.21E-10 1.20E-08 No Data 1.93E-10 1.30E-10 2.39E-05 Ba-140 8.31E-05 7.28E-08 4.85E-06 No Data 2.37E-08 4.34E-08 4.21E-05 Ba-141 2.00E-07 1.12E-10 6.51E-09 No Data 9.69E-ll 6.585-10 1.14E-07 Be-142 8.74E-08 6.29E-ll 4.88E-09 No Data 5.09E-ll 3.70E-11 1.14E-09 2-51
TABLE 2.2-6 COpr'D IN'GESTION DOSE FACTORS FOR CHILD *
(MREM PER PCI INGESTED)
Page 3 of 3 i
Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI Ln-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 Co-141 3.97E-08 1.98E-08 2.94E-09 No Data 8.68E-09 No Data 2.47E-05 Co-143 6.99E-09 3.79E-06 5.49E-10 No Data 1.59E-09 No Data 5.55E-05 Co-144 2.08E-06 6.52E-07 1.11E-07 No Data 3.61E-07 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-05 Pr-144 1.29E-10 3 99E-ll 6.49E-12 No Data 2.llE-11 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 i
Np-239 5.25E-09 3.77E-10 2.65E-10 No Data 1.09E-09 No Data 2.79E-05 i
2-52
-p TABLE 2.2-7 INGESTION DOSE FACTORS FOR TEENAGER *
(MREM PER PCI INGESTED)
Page 1 of 3 Nuclide Bone Liver T Body Thyroid K idrity, 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 No-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 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 FO-55 3.78E-06 2.68E-06 6.25E-07 No Data No Data 1.70E-06 1.16E-06 Fo-59 5.87E-06 1.37E-05 5.29E-06 No Data No Data 4.32E-06 3.24E-05 C2-58 No Data 9.72E-07 2.24E-06 No Data No Data No Data 1.34E-05 Co-60 No Data 2'. 81E-0 6 6.33E-06 No Data No Data No Data 3.66E-05 Ni-63 1.77E-04 1.25E-05 6.00E-06 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 5.413-08 No Data 2.91E-07 No Data 8.92E-06 Z"-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 Dsta 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 l
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 i
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 l
Y-92 1.21E-09 No Data 3.50E-ll No Data No Data No Data 3.32E-05 i
3 I
Reference 3, Table E-12.
i j
2-53 l
,y-----w,-,..-~-n---
.v,,-,,,%
~m,,w,ww-wmsm y---em_---.-.-
,,.-,-,w y.,-,
TABLE 2.2-7 CONT'D INGtSTION DOSE FACTORS FOR TEENAGER *
(MREM PER PCI INGESTED)
Page 2 of 3 Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI i
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-09 No Data 1.91E-08 No Data 3.00E-05 Zr-97 2.37E-09 4.69E-10 2.16E-10 No Data 7.llE No Data 1.27E-04 Nb-95 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-06 No Data 1.88E-04 Ag-110M 2.05E-07 1.94E-07 1.18E-07 No Data 3.70E-07 No Data 5.45E-05 To-125M 3.83E-06 1.38E-06 5.12E-07 1.07E-06 No Data No Data 1.13E-05 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 Ta-129M 1.63E-05 6.05E-06 2.58E-06 5.26E-06 6.82E-05 No Data 6.12E-05
'A=-129 4.48E-08 1.67E-08 1.09E-08 3.20E-08 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-09 2.15E-08 1.22E-07 No Data 2.29E-09 Ta-132 3.49E-06 2.21E-06 2.08E-06 2.33E-06 2.12E-05 No Data 7.00E-05 4
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-06 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-133 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 5.8 2E-07 1.01E-04 2.48E-06 No Data 1.74E-06 Cs-134 8.37E-05 1.97E-04 9.14E-05 No Data 6.26E-05 2.39E-05 2.45E-06 Cs-136 8.59E-06 3.38E-05 2.27E-05 No Data 1.84E-05 2.90E-06 2.72E-06 Co-137 1.12E-04 1.49E-04 5.19E-05 No Data 5.07E-05 1.97E-05 2.12E-06 Ca-138 7.76E-08 1.49E-07 7.45E-08 No Data 1.10E-07 1.28E-08 6.76E Ba-139 1.39E-07 9.78E-ll 4.05E-09 No Data 9.22E-11 6.74E-ll 1.24E-06
{
i L
l 3
2-54
1 TABLE 2.2-7 CONT'D ING5STION DOSE FACTORS FOR TEENAGER *
(MREM PER PCI INGESTED)
Page 3 of 3 Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI De-140 2.84E-05 3.48E-08 1.83E-06 No Data 1.18E-08 2.34E-08 4.38E-05 B E-141 6.71E-08 5.01E-ll 2.24E-09 No Data 4.65E-11 3.43E-ll 1.43E-13 Bs-142 2.99E-08 2.99E-11 1.84E-09 No Data 2.53E-ll 1.99E-ll 9.18E-20 Ln-140 3.48E-09
- 1. 71E-09 4.55E-10 No Data No Data No Data 9.82E-05 Ln-142 1.79E-10 7.95E-11 1.98E-ll No Data No Data No Data 2.42E-06 Cs-141 1.33E-08 8.88E-09 1.02E-09 No Data 4.18E-09 No Data 2.54E-05 Ca-143 2.35E-09 1.71E-06 1.91E-10 No Data 7.67E-10 No Data 5.14E-05 Ca-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 l
l 2-55
Y TA!LE 2.2-8 IN5ESTION DOSE FACTORS FOR ADULTS *
(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-07 Nc-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 FG-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 cc-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 7"-65 4.84E-06 1.54E-05 6.96E-06 No Data 1.03E-05 No Data 9.70E-06 an-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-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 9.63E-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'. 9 4E-0 5 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.
2-56
TABLE 2.2-8 CONT'D INGESTION DOSE FACTORS FOR ADULTS
- l (MREM PER PCI INGESTED)
't Page 2 of 3 i
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-110 M 1.60E-07 1.48E-07 8.79E-08 No Data 2.91E-07 No Data 6.04E-05 To-125M 2.68E-06 9.71E-07 3.59E-07 8.06E-07 1.09E-05 No Data 1.07E-05 To-127M 6.77E-06 2.42E-06 8.25E-07 1.73E-06 2.75E-05 No Data 2.27E-05 To-127 1.10E-07 3.95E-08 2.38E-08 8.15E-08 4.48E-07 No Data 8.68E-06 To-129M 1.15E-05 4.29E-06 1.82E-06 3.95E-06 4.80E-05 No Data 5.79E-05
'A
-129 3.14E-08 1.18E-08 7.65E-09 2.41E-08 1.32E-07 No Data 2.37E-08 i
Te-131M 1.73E-06 8.46E-07 7.05E-07 1.34E-06 8.57E-06 No Data 8.40E-05 To-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-0 5 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 1.0 2E-0 5 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 j
I-134 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 No Data 2.51E-10 i
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 i
Co-138 5.52E-08 1.09E-07 5.40E-08 No Data 8.01E-08 7.91E-09 4.65E-13 Bo-139 9.70E-08 6.91E-11 2.84E-09 No Data 6.46E-11 3.92E-11 1.72E-07
!l Be-140 2.03E-05 2.55E-08 1.33E-06 No Data 8.67E-09 1.46E-08 4.18E-05 Bo-141 4.71E-08 3.56E-11 1 59E-09 No Data 3.31E-11 2.02E-ll 2.22E-17 Be-142 2.13E-08 2.19E-11 1 34E-09 No Data 1.85E-ll 1.24E-ll 3.00E-26 i
4 2-57
,y.,_.__
__,.__._.--.___._y
_,_,.,,,e
_ = _. -
1 TABLE 2 2-8 CONT'D INdESTION DOSE FACTORS FOR ADULTS *
(MREM PER PCI INGESTED)
Page 3 of 3 Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI LO-140 2.50E-09 1.26E-09 3.33E-10 No Data No Data No Data 9.25E-05 Ln-14 2 1.28E-10 5.82E-ll 1.45E-ll No Data No Data No Data 4.2SE-07 Co-141 9.36E-09 6.33E-09 7.18E-10 No Data 2.94E-09 No Data 2.42E-05 Co-143 1.65E-09 1.22E-06 1.35E-10 No Data 5. 3 7E-10. No Data 4.56E-05 Co-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-14 7 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-11 No Data 3.65E-10 No Data 2.40E-05 2-58
+
TABLE 2.2-9 EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND
- 2 (mrem /hr per pCi/m )
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 i
Ni-65 3.70E-09 4.30E-09 Cu-64 1.50E-09 1.70E-09 4
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 l
Rb-88 3.50E-09 4.00E-09 Rb-89 1.50E-08 1.80E-08 i
St-89 5.60E-13 6.50E-13 St-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 1
i 2-59
TABLE 2.2-9 (C:ntinu;d)
EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND
- RADIONUCLIDE TOTAL BODY SKIN Y-91M 3.80E-09 4.40E-09 Y-91 2.40E-11 2.70E-ll 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-ll 4.80E-ll Te-127M 1.10E-12 1.30E-12 Te-127 1.00E-ll 1.10E-11 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-09 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 2.70E-09 2-60
TABLE 2.2-9 (C:ntinued)
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 l
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 l
Ce-144 3.20E-10 3.70E-10 i
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
~
N -239 9.50E-10 1.10E-09 P
2-61
. TABLE 2.2-10 INDIVIDUAL USAGE FACTORS
- 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, 0,1 (kg/ year) 0 26 42 64 Stored Vegetation Consumption Rate, U,, (kg/ year) 0 520 630 520 Breathing Rate 3
(m / year) 1400 3700 8000 8000 Reference 3, Table E-5.
2-62
TABLE 2.2-11 W
STABLE ELEMENP TRANSFER DATA *
(Milk - dayo/litor; M0ct-dnyc/kg)
ELEMENT F,- MILK F,- MILK F -MEAT g
(COW)
(GOAT)
H 1.0E-02 1.7E-01.
1.2E-02 C
1.2E-02 1.0E-01 3.1E-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
5.0E-04 5.0E-04 1.3E-03 Np 5.0E-06 5.0E-06 2.0E-04
- References 3, Table E-1; Reference 3, Table E-2 for H, C, P, Fe, Cu, Sr, I and Cs in goat's milk; the remainder of elements in goat's milk are taken from Table E-1 as presented for cow's milk.
2 2-63
7 TABLE 2.2-12 CONTROLLING RECEPTOR (To Support Subsection 2.2.2.2)
The location and exposure pathways associated with the controlling receptors are determined during the annual land use census.
Dispersion and deposition values were calculated based
. ib VEGP site meteorological data collected for the period February 1, 1984 through January 31, 1986.
2 Sector:
WSW Distance:
1.3 miles Age Group:
Child 3
Dispersion (X/Q')g, = 9.490-6 sec/m gy7g.)MP *
~
~
Deposition:
(D/Q ') gp= 6. 73E-9 m (57D ') MP *
~I "
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:
WNd Distance:
2.8 miles Age group Child Dispersion:
(X/Q ')g, = 1. 36C-6 sec/m3 (Y76') g, = 1. 55E-7 sec/m 3
Depositions (D/Q')gp = 8. 400-10 m"2 (D/Q')gp = 2.64c-10 m-2 Exposure pathways:
Inhalation, ground plane, vegetation, and milk cow
- Reference 12; Reference 13 2-64
._ q 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)t3, Inhalation dose factor Tables 2.2-1 for age group 2.2-4 Ground plane SKF Shielding factor due to 0.7 structu re (Reference 3, Table E-lS).
(DFG)tj Ground plane dose factor Table 2.2-9 (Same for all age groups)
Garden Vegetation Y
Garden vegetation areal 2.0 kg/m2 y
density (Reference 3, Table E-15);;
Ual Leafy vegetation consump-Table 2.2-10 tion rate for age group U,,
Stored vegetation consump-Table 2.2-10 tion rate for age group 2-65
TABLE 2.2-13 (Con tinued)
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 (Reference 1, page 36)l2 locally f
Fraction of annual intake of 0.76 g
stored vegetation grown (Reference 1, page 36)! 2 i locally 3
H Absolute humidity of the 8.0 gm/m a tmosphere (Reference 1, page 34)! 3 I
l 2-66
TABLE 2.2-13 (C:ntinutd)
SITE, SPECIFIC (OR DEFAULT) VALUES TO i
BE USED IN PATHWAY FACTOR CALCULATIONS Parameter Description Value Grass-Cow-Meat Qy Feed consumption rate for 50 kg/ day (Reference 3, Table E-3) g; cow U,p Meat consumption rate for Table 2.2-10 age group (DFL)tj, Ingestion dose factor for Tables 2.2 f l
age group 2.2-8 2
Y Pasture grass areal density 0.7 kg/m p
(Reference 3,TableE-15)l 1
2 Y,
Stored feed areal density 2.0 kg/m (Reference 3, Table E-15),;f f
Fraction of year that cow 1.0 3
p grazes on pasture (Reference 1, page 33).2 i
i f,
Fraction of total feed that 1.0 j
is pasture grasa while cow (Reference 1, page 33)l 2 j
is on pasture t
l i
H Absolute humidity of the 8.0 gm/m3 l
a tmosphe re (Reference 1, page 34)j 2 i
k j
Grass-Cow-Milk t
Oy Feed consumption rate for 50 kg/ day cow (Reference 3, Table E-3)'2 2-67 i
_----,m
..--,-_-.-_.-_r_.-----,-,---,--.-__--.
TABLE 2.2-13 (Continued)
SITE-SPECIFIC (OR DEFAULT) VALUES TO BE USED IN PATHWAY FACTOR CALCULATIONS Parameter Description Value U,p Milk consumption rate for Table 2.2-10 age group (DFL)13 Ingestion dose factor for Tables 2.2 age group 2.2-8 2
Y Pasture grass areal density 0.7 kg/m p
(Reference 3, Table E-15)'
2 Y,
Stored feed areal density 2.0 kg/m (Reference 3,TableE-15j,'
f Fraction of year that cow 1.0 p
grazes on pasture (Reference 1, page 33),2 f
Fraction of total feed that 1.0 s
is pasture grass while cow (Reference 1, page 33) 2 is on pasture 3
H Absolute humidity of the 8.0 gm/m a tmosphere (Reference 1,page34){?
G ra s s-Goa t-Milk Or Feed consumption rate for 6.0 kg/ day goat (References 3,'TableE-3)jl U,p Milk consumption rate for Table 2.2-10 age group 2-68
1 TABLE 2.2-13 (C:ntinued)
SITE-SPECIFIC (OR DEFAULT) VALUES TO BE USED IN PATHWAY FACTOR CALCULATIONS Parameter Description Value (DFL)ija Ingestion dose factor for Tables 2.2 age group 2.2-8 2
Y Pasture grass areal density 0.7 kg/m p
(Reference 3, Table E-lS) 2 Y
S tored feed, areal density 2.0 kg/m s
(Reference 3, Table E-15) l f
Fraction of year that goat 1.0 p
grazes on pasture (Reference 1, page 33)l, 2 f,
Fraction of total feed that 1.0 is pasture grass while goat (Reference 1, page 33)l 2 is on pasture 3
H Absolute humidity of 8.0 gm/m the atmosphere (Reference 1, page 34) 2 l
2-69
~
i TABLE 2 2-14 i
POTENTI AL RECEPTOR LOCATIONS AND PATTIIAYS (To Support Subsection 2 2 2 3) l D istance S ec to r (Mile s)
KJ1 P a th way* *
- Age Group 3
N NNE NE ENE I
3 ESE SE 33 53 Vege ta tion Child SSE 46' 74 Vege tation Child S
45 72 Vegetation / Heat Animal Child SSW 47 76 Heat Animal Child 2,3 SW 31 50 Meat Animal Child i
W5W 13 21 Vegetation Child W
42 68 Veg e ta tion Child WNW 23 37 Vege tat ion Child 2 8****
45 Vegetation / Milk Cow Child NW 39 63-Vege tat ion Child NtM7 l
l Savannah River Plant Property (closed to public)
No receptor identified wl' thin five miles Inhalation and ground plane pathways are assumed at all locations where inge ntlen pa thways exist.
A milk cow has been observed at this location.
H owe v er, 2
discussions whth the owner revealed that she is on an irregular milking cycle.
The pathway will exist during periods when the cow is being milked.
Ref e re nce 12 l
2-70 i
TABLE 2.2-15 DISPERSION AND DEPOSITON PARAMETERS (To Support Subsection 2.2.2.3)
Distance Ground-Level Release Mixed-Mode Release Sector (Miles)
Jgn X/O sec/m3 D/0 m-2 X/O sec/m3 D/0 m-2 3.
N NNE NE ENE E
ESE SE 3.3 5.3 6.80E-7 6.15E-9 7. 0 5 E-8 1.58E-10 SSE 4.6 7.4
- 4. 37 E-7 2.15E-10 4.49E-8 8.26E-ll S
4.5 7.2 4.48E-7 2.88E-10 5.35E-8 1.12E-10 SSW 4.7 7.6 3. 7 0 E-7 2.32E-10 5.30E-8 1.56E-10 SW 3.1 50 1.53E-6 1.02E-9 2.19 E-7 4.53E-10 2,
WSW l.3 2.1 9.49E-6 6.73E-9 1.07E-6 2.53E-9 S
W 4.2 6.8 6.20E-7 3.36E-10 7.41E-8 1.38E-10 WNW 2.3 3.7 2.03E-6 1.27E-9 2.16E-7 3.80E-10 2.8 4.5 1.36E-6 8.40E-10 1.55E-7 2.64E-10 NW 3.9 63 7. 25E-7 3.72E-10 7.99E-8 1.25E-10 NNW Savannah River Plant property (closed to public)
No receptor identified within five miles Reference 12; Reference 13.
2-71
2.2.3 Dose Projections for Ga^erun Ef fluents 2.2 3 1 Thirty-one Day Dose Projections In order to mest 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 individuals due to gaseous effluents may be determined as follows:
Air Doses:
Dbeta (c)
D x 31 (32) beta (prj) t D,,,,gc) g D,,,,(pg))
x 31 (33)
=
g g
1 Individual:
Do g,)
D
=
x 31 (34) agpg))
g where Dbeta (c) the cumulative air dose, due to beta emissions
=
from noble gases, for the elapsed portion of the current quarter plus the release under consideration.
2-72
D,,,,ge) the cuculctivo air doco, duo to gamma cmissienc o
g
- f rom n:blo gccoa, fer tho olcysed portion of the current quarter plus the release under consideration.
o g g) the cumulative org'an dose, to an individual due to D
=
I-131, I-133, tritium and particula tes, for the elapsed portion of the current quarter plus the release under consideration.
the number of days into the current quarter, t
=
including the period of the release under 1
consideration.
If operational activities planned during the ensuing 31 day period are expected to result in gaseous releases which will contribute a dose in addition to the dose due to routine gaseous effluents, this additional dose contribution should be included in the projected dose as follows:
l Air Doses:
i
~
D f
D x 31 +D (35) be ta (pej) t pg I
Dg amma (pr D =
x 31 +Dpg (36) 1 1
~
n ICI D
=
x 31 +D (37) a g p,3) g pg J
Where Dpg is the expected dose due to the particular planned activity.
2-73
2.2 3.2 D^se Prniectien1 for Specific R71nenns 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 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.
8 v.
2-74
~
2.3 METEOROLOGICAL MODEL (Reference 7, 13,15 and Section 2.3.5 of Reference 5) 3 2.3.1 Atmospheric Dispersion Atmocpheric dispersion (long-term) may be calculated using the appropriate form of the sector-averaged straight line flow Gaussian model.
Gaceous 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 f rom reactor building (s)
(plant) vent (s) are considered to be mixed-mode.
(See NOTE in 3
Subsection 2.1. 2).
2.3.1.1 Ground-Level neleases (X/C)g the ground-level sector-averaged relative
=
concentration for a given wind direction 3
(coctor) and distance. (sec/m )
[
=(ncr)2.032d njk (38) 3 p jk uu x
jk zk whore (2/7T)hh divided by the number of radians in a 2.032
=
0 22.5 coctor (0.3927 radians).
d plume depiction factor for all radionuclideo
=
p other than noble gacos at a distanco x chown in Figuro 2.3-2 for ground-levol rolescos; for noble ganon the deplotion factor in unity.
If an undoploted relativo concentration la donired, the depletion factor in unity.
Only deplotion by deposition in concidorod sinco doplation by decay would be of little significanco at the diatancon concidorod.
2-75
open terrain recirculation factor.
Values for RCP
=
specific distances are obtained from Figure 3
3.2 of Reference 15.
njk number of hours meteorological conditions are
=
observed to be in a given wind direction, 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.
l t
total hours of valid meteorological data N
=
throughout the period of interest.
l ujk wind speed (mid-point of windspeed class j) at
=
ground level (m/sec), during stability class k.
distance from release point to location of x
=
interest (meters).
[ezk=
the vertical standard deviation of the plume concentration distribution considering the initial dispersion within the building wake.
(d$+(bf3g)1/2 2
the lesser of or
=
@(q)
Cfak =
the vertical standard deviation of the l
plume concentration distribution (meters) for a given distance and stability category k as shown in Figure 2.3-1.
The stability category tu datormined by the vertical l
i i
2-76
temp 3roturogrcdiontdT/83 (OC/100m).
Tf =
3.1416 maximum height of adjacent plant structure (55 b
=
meters).
l 2.3.1.2 Mixed-Mode Releases (X/C)M the mixed-mode sector-averaged relative
=
concentration for a given wind direction 3
(sector) and distance (sec/m )
[
"jk E
3
- 2. 032 (RCF) d Nx u
=
p jk jk sk 1
1 2
+
exp(-h /
k)
(39) i where plume depletion factor for all radionuclides I
d
=
p other than noble gases at a distance x shown in Figures 2.3-3 through 2.3-5 for elevated I
releasesi for noble gases the depletion factor is unity.
If an undepleted relative l
concentrat. ion 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.
Ujk wind speed extrapolated to the effective
[
=
release height; extrapolation is accomplished by raising the ratio of the 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 t
1 E
.o frcctiCn c nsidorCd c3 gecund lOval rolocsoc W
l.0 for
$ 1.0 W
W 2.58 - 1.58 (
) for 1.0 <
5 1.5 u
0.3 - 0.06 (
) for 1.5 <
15.0 0
for
> 5.0 W
=
vent exit v,elocity (m/sec) o h
effective release height (m)
=
=
hy+h
-h
-C (40) pr t
v h
height of release point (m)
=
y h t maximum terrain height between the release
=
point and the point of interest (m) (See Table 2.3-1) hpr additional height due to plume rise (m)
=
1.44d (W,/u) 2/3 (x/d)l/3 i
=
g41) limited by the lesser of the following two equations
.j pr(max) 3(W /u)d or h
= 1.5 (F,/u)1/3 -1/6 h
S o
pr(max) l d
inside diameter of vent
=
i 2-78
careccticn for icw vcnt cxit volccity (m) c o
y W
W o
3 (1.5 -
) d for 5 1.5 u
W 0
for
> 1.5 4
2 Fj momentum flux parameter (m /sec )
=
(W )2 (d/2) 2
=
o S
stability parameter
=
8.75 x 10-4
-2 sec for -0.5 4 AT 1 1.5 1.75 x 10-3
,,e -2 for 1.5 < 4 T 1 4.0
=
2.45 x 10-3 sec for A T > 4.0
-2 All other terms were defined in Subsection 2.3.1.1.
h 2-79
2.3.2 R21Etiva Dnposition (See NOTE in Subsection 2.1.2).
3 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 2
sector (1/m ),
(RCF) [2.55D,n k 3
k Nx (42) where 2.55 =
the inverse of the number of radians in a sector (277/16) ~1 22.50 deposition rate at a given distance, taken D
=
g 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 stability category k exists.
the total number of hours of valid N
=
meteorological data.
open terrain recirculation factor.
Value#s for 3
=
specific distances are obtained from Figure 3.2 of Reference 15.
2-80
r-t 2.3.2.2 Mixtd-Moda RDISanas 1
(D/Q)M' the mixed-mode-sector-averaged relative
=
~
deposition'at'a given distance and for a given 2
sector (1/m ),
2.55 (RCF) ((E) (D ) + - (1 - E) D,)
(43) 3
=
g where l
relative deposition rate for the ground-level D
=
g portion of mixed-mode releases from Figure 2.3-6.
relative deposition rate for the elevated D,
=
portion of mixed-mode releases from Figures 2.3-7 through 2.3-9.
fraction of releases considered as ground-E
=
level.
Other terms were defined in previous Subsections.
1 2-81
TABLE 2.3-1 Terrain Elevation Above Plant Grade (Page 1 of 2)
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 0.0 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 0.0 3000 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 3500 0.0 -
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)
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 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 26.8 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 l
2-83 l
- w4 FIGURE 2.3-1 Vertical Standard Deviation of Material in a Plume (O~2 )
(Letters Denote Pasquill Stability Class) ime l
' jl
/'
!'! ;/
i v
.]
- s. /
L
\\
V
,V s
j' jl
/
/i I /'l
/
llli
,/
,/
p 4
/. <../.
./
s.
/
s A vi axoi t //i6av i
s.=-
5
/ /lfilW / l 3 f'Tlill # 1iili
/// l}'TeV /I l ) tTTI l
l l lll'
///1
/
/
/
,,/// ;/ / /
,c/
/
/
/
a s'/f s' l
/,/ i v;,..,
,, iiii.,
,,,,,,ii
/) ft l i l lli i
l i l i llli i
i i i t ill
/ /
lllllll I
lI 'lll I l l lllll
/
i.
Ps.Utst TRAVEL OtETMsCE (EILoneETER$1 Range of Vertical Range of Vertical Category Temoerature Gradient ('C/100m)
Temperature Gradient (*F/100f t)
A AT/aZ < -1.9 AT < -1.0 B
-1.9 < AT/AZ < -1.7
-1.0 5 AT < -0.9 C
-1.7 < AT/aZ < -1.5
-0.9 < AT < -0.8 D
-1.5 5 AT/aZ < -0.5
-0.8 5 AT < -0. 3 E
-0.5 $ AT/aZ < 1.5
-0.3 5 aT < 0.8 F
1.5 < AT/aZ < 4.0 0.8 5 aT < 2.2 G
4.0 < AT/aZ 2.2 < AT Reference 7 2-84
,--..-.----n.-m
a..
FIGURE 2.3-2 Plume Depletion Effect for Ground-Level Releases (All Atmospheric Stability Classes) e 1.0 0.9
'A N
O.8
\\
d s
z 0.7
\\
A E
0.8
\\ \\
E 0.5 8
A N
E 0.4 s '
N m
0.3 0.2 0.1 0.1 1.0 10.0 100.0 200.0 PLUME TRAVEL DISTANCE (KILOMETERS)
Reference 7 2-85
FIGURE 2.3-3 Plume Depletion Effect for 30-Meter Releases (Letters Denote Pasquill Stability Class) s 1.0 UABLE' O.9 NEUTR AL (D)
( E.F.'G )
w 0.8 A
0.7 I
hhQ E
g 0.6 UNSTABLE q (A.B.C)
O.5
,\\
s
- 0
.4
'\\N 0.3 0.2 0.1 0.1 1.0 10.0 100.0*
.200.0 PLUME TRAVEL DISTANCE (KILOMETERS) l l
l i
Reference 7 2-86 i
FIGURE 2.3-4 Plume Depletion Effect for 60-Meter Releases (Letters Denote Pasquill Stability Class) 1.0
- N'
'N-. STABLE (E F,G) 0.9 EUTRAL 3
h
%\\\\
07 z
UNSTABLE N
}
(A.S.C)
\\ g 3
0.6 0.5 x
60.4
\\
s 0.3
\\
0.2 0.1 0.1 1.0 10.0 100.0 200.0 PLUME TRAVEL DISTANCE (KILOMETERS)
Reference 7 2-87
- t. g FIGURE 2.3-5 Plume Depletion Effect for 100-Meter Releases (Letters Denote Pasquill Stability Class)
~
1.0 N
03 NEUTR AL (D)
\\ N w 0.8 m
w 0.7 ABC
\\
z q
STABL E (E.F.Gl 3
g NO DEPLETION g
\\
z (FRACTION RE AINING = 1.0)
\\
\\
E 0.5 N
z
\\
N U 0.4
\\
1 0.3
\\
0.2 0.1 0.1 1.0 10.0 100.0 200.0 PLUME TRAVEL DISTANCE (KILOMETERS)
Reference 7 2-88
FIGURE 2.3-6 Relative Deposition for Ground-Level Releases (All Atmospheric Stability Classes)
)
10-3 l
i i
1 i
I t
' i 4
l I
i i i
j t
i i
t lli i
II II l
i 10-4
\\ A m
gi, f a
C l
' i 5
6 fil I
N i
4
- i8 !'
y
' (
.i i
i 6 i!I W
\\
.I Illll
\\
lI il l
l E
N ll
.Y<
\\
1 x
$ 10-5 A
N i
e m
X i
I k
x
,,, i.,
i i
6\\ 6 1
( l l I It 1
g l
\\l I llil I
w 2
hi l i Ill E
ee 10-6 N
, i i
,,i i.'
i
).
lj 1
iit iP 1 i
t l
l l l lll l
l l Ill!
l ll 10-7 0.1 1.0 10.0 100.0 200.0 l
PLUME TRAVEL DISTANCE (KILOMETERS)
Reference 7 2-89
FIGURE 2.3-7 Relative Deposition for 30-Meter Releases (Letters Denote Pasquill Stability Class) 10-3
'i.,..
.l l l' l
e#1 6
i i
1 ll l
l l
\\
j ll 11 UNSTABLE (A,G,C) 10-4 Al I f Iil 2
X, m
e s.
i=
/
i i
\\'4 ii 6
6 ii e
i e i,ii i
I k'l il l
lll g
M'h I
i l
E
/
\\\\
NEUTRAL l
l E
/
NN m
g 2
NEUTRAL (D)
N y 10-s
! IIIll' g%
STABLE 8
i,/
! 'if T.
a.
,,,i
,,f x s,
I i
l I
i/t
\\\\
l \\
l w
/i I
l 1
It
/
N 'iWi l i
l!
l I
i
/!
I th
/l 1, X l.I M I 2
/
/
hs AN STbhE (E,FG) iO-e i,.
c i
4
[
O I
If Il l
l l
1 l }l I
l I
If
$1 i
i j il l i i i
f l
l l l llllI l
/
l l
I lll i
/
10-7 0.1 1.0 10.0 100.0 200.0 PLUME TRAVEL DISTANCE (KILOMETERS)
Reference 7 2-90
FIGURE 2.3-8 Relative Deposition for 60-Meter Releases (Letters Denote Pasquill Stability Class) 10-4
- 4 4
i
,,i I
i 6
'I jiei I
i l s i
i l
I 1
( l i 11 I
4 UNSTABLE (A,B,C) l l ll ti f
[
\\
l 1
l lll ll s
f l
10-5
/
NEUTR AL (D) g
/
,,/,
"m g
e
,i i
.,..s i
y
/
8 9
. ifi i i
t.
e
' s Ye 6ei.
H
/
I / i i
t i
\\Al l l I/
l1(l l
l' I
\\ NlUNSTABLE 5
/
l t
lill Al I NI
\\
NEUTRA g
y x
x Zo 10-6 lny 8
1 g"
6 f e t
e i
f e
e Q
t 1 i 9
8 i
/
I e
i *
(
6 e l efe '
h I[ t i
i l
I l 6
/III o
il l
I l
t i i/l I l i s
il l I/Illi l
a r
I
,e i
.J
(
l W
llr 10-7 STABLE (E,F,G) l.
lil
',l l l lll,'
4
,i, J
i lii ii is t
i le i t
t I
i 1
\\
li 1 \\\\
\\
I
/
I t
/
I i
10-8 1
0.1 1.0 10.0-100.0 500.0 PLUME TRAVEL DISTANCE (KILOMETERS)
Reference 7 2-91
l m
FIGURE 2.3-9 Relative Deposition for 100-Meter Releases (Letters Denote Pasquill Stability Class) 10-4 i
ii
...i
. iii i.
i iI,
i i i e
ei i
I i
li 1 -
UNSTABLE (A.B.C)I lll
/
\\
l l
l N N N 10-5 As
/,
/
1 1
.ii f,
iw i
i h
i l/
/ NEUTRAL (D)
'l x(
l l l l '. l y
V l/
'I N W1
/
I/
N I T%
=
/
/
R N
2 s
s
{
e
$ 10-6
)
5
/
- 4 l,..;
l...
a i
i t
i a.
I l
6
(
i i
i e
i
! i e iij o
/
l
/
l ii11 g
,/
/
lili r
j 4ay STABLE (E,F,G) l l
NO DEPLETION 10-7 2
if 9 f)
)
e i
6 4 6 i a l [i i
i(
4 i
j. s l l s l f
l 6
I I
I I iii
/
I l
lilli f
l lllIl
/
10-8 0.1 1.0 10.0 100.0 200.0 PLUME TRAVEL DISTANCE (KILOMETERS)
Reference 7 2-92
2.4 DEFINITIONS OF GASEOUS EFFLUENT TERMS 1
Subsection of Term Definition Initial Use administrative allocation factor for 2.1.1 AG
=
gaseous ef fluent pathways (unitiess).
1 BR breathing rate for individual from 1
=
3 Table 2.2-10 (m / year).
2.2.1.2 maximum height of the adjacent 2.3.1.1 b
=
i building (meters).
4 C,
monitor response of a noble gas monitor 2.1.1
=
corresponding to associated grab sample radionuclide concentrations.
s calculated basic monitor setpoint 2.1.1 c
=
value actual monitor setpoint which 2.1.1 e
=
sp includes the calculated basic monitor 1
setpoint value plus background.
correction to effective release c
=
y i
height due to low vent exit velocity 2.3.1.2 (me te r s),
i TB limiting dose rate to the total body 2.1.1 D
=
of an individual in an unrestricted area which is 500 mrem / year.
I D
=
t total body dose rate at time of 2.2.1.1
~
release (mrem /yr).
j D,,
limiting dose rate to the skin of 2.1.1
=
an individual in an unrestricted area which is 3000 mrem / year.
2-93 4
-,.---,,,c.,_
.__.-r--.-.,-.,-,-
- - - ~ - - - --
~ ~ ' n.
2.4 DEFINITIONS OF GASEOUS EFFLUElff TERMS (Centinutd)
Subsection of Term Definition Initial Use skin dose rate at time of release 2.2.1.1 D
=
s
- .l' (mrem /yr).
D
=
organ dose rate at time of release 2.2.1.2 o
(mrem /yr).
j DFio inhalation pathway dose factor for 2.2.1.2
=
i child age group for organ o and 4
radionuclide 1 (mrem /pci inhaled) from Table 2.2-2.
1
)
beta air dose due to beta emissions from 2.2.2.1 D
=
noble gases (mrad).
l i
air dose due to gamma emissions from 2.2.2.1 D
=
gamma noble gases (mrad).
Dj dose to an organ of individual from 2.2.2.2
=
radioiodines, tritium, and g
radionuclides in particulate form with half-lives greater than eight days 1
(mrem).
(DFA j) a the inhalation dose factor for the ith 2.2.2.2
=
i radionuclide for the receptor in age group a (mrem /pci) from Tables 2.2-1 through 2.2-4.
DFG j ground plane dose conversion factor 2.2.2.2
=
i i
for radionuclide 1 (same for all age 2
groups) (mrem /hr per pCi/m ) from l
Table. 2.2-9.
2-94 i
2.4 DEFINITIONS OF GASEOUS EFFLUENT TERMS (Continund)
Subsection of Tje,Em Definition Initial Use (DFL j)a the organ ingestion dose factor for 2.2.2.2
=
i the ith radionuclide for the receptor i
in age group a (mrem /pCi) f rom Tables 2.2-5 through 2.2-8.
d plume depletion factor for all 2.3.1.1
=
p radionuclides other than noble gases at distance x (unitless).
i inside diameter of plant vent 2.3.1.2 d
=
(meters).
I i
D
,=
deposition rate for ground-level 2.3.2.1 9
releases (m-1).
deposition rate for elevated releases 2.3.2.1 D.
=
(m-1).
fraction of release considered to be 2.3.2.1 E
=
ground-level (unitiess).
I f t fraction of the annual intake of fresh 2.2.2.2
=
1eafy vegetation grown locally (dimensionless).
(
f fraction of annual intake of stored 2.2.2.2
=
g vegetation grown locally (dimensionless).
f fraction of the year that the cow 2.2.2.3
=
p (or goat) is on pasture l
(dimensionless).
i 2-95
2.4 DEFINITIONS OF GASEOUS EFFLUElfr TERMS (Continuid)
~
Subsection of Term Definition Initial Use fraction of the cow (or goat) feed 2.2.2.3 f,
=
that is pasture grass while the cow or goat is on pasture (dimensionless).
g the stable element transfer 2.2.2.3 F
=
coefficient for meat (days /kg) from Table 2.2-11.
F, the stable element transfer 2.2.2.3
=
coefficient for milk (days / liter) from Table 2.2-11.
4 2
Fg momentum flux parameter (m /sec )
2.3.1.2
=
1 maximum expected release flow rate 2.1.1 F
=
y through a particular release point (ml/sec) f rom Table 2.1-2 H
=
absolute humidity of the atmosphere 2.2.2.2 3
(gm/m ),
h effective release height (meters).
2.3.1.2
=
hy height of release point (meters).
2.3.1.2
=
h t maximum terrain height between the 2.3.1.2
=
release point and the point of interest (meters).
hpr additional height due to plume rise 2.3.1.2
=
(meters).
2-96
_q 2,4 DEFINITIONS OF GASEOUS EFFLUENP TERMS (Continutd)
~
Subsection of Term Definition Initial Use Kg total body dose factor due to gamma 2.1.1
=
emissions from radionuclide 1 3
(mrem / year per uCi/m ) f rom Table
. 2.1-1.
constant of unit conversion 2.2.1.2 K'
=
6 (10 pci/uci).
K" constant of unit conversion (8760 2.2.2.2
=
hr/ year).
K'"
constant of unit conversion 2.2.2.2
=
3 (10 gm/kg).
t skin dose factor due to beta emissions 2.1.1 L
=
from radionuclide 1 (mrem / year per 3
uCi/m ) f rom Table 2.1-1.
Mi air dose factor due to gamma emissions 2.1.1
=
from radionuclide 1 (mrad / year per 3
uCi/m ) f rom Table 2.1-1.
i air dose factor due to beta emissions 2.2.2.1 N
=
from noble gas radionuclide i 3
(mrad / year per uCi/m ) f rom Table l
2.1-1.
i the number of simultaneous gaseous 2.1.5 n
=
release pathways.
i njk number of hours meteorological 2.3.1.1
=
conditions are observed to be in a given wind direct' ion, wind-speed class j, and atmospheric stability class k.
2-97
2.4 DEFINITIONS OF GASEOUS EFFLUElfI' TERMS (Continu7d)
Subsection of Term Definition Initial Use total hours of valid meteorological 2.3.1.1 N
=
data.
Pgg dose parameter for radionuclide i, 2.2.1.2
=
3 (mrem /yr per uC1/m ) for the inhalation pathway.
Q ig Source term for ground-level release 2.1.1
=
noble gas radionuclide i (uCi/sec) i Source term for mixed-mode release 2.1.1 Q,
=
noble gas radionuclide 1 (uci/sec)
Qig (r) source term for ground-level release 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)
Q{g source term for ground-level release 2.2.1.2
=
radioiodine, tritium and particulate radionuclide 1 (uci/sec)
Olm source term for mixed-mode release 2.2.1.2
=
l radioiodine, tritium and particulate radionuclide i (uCi/sec)
Qig cumulative ground-level release of 2.2.2.1
=
noble gas radionuclide 1 (uCi)
Qim cumulative mixed-mode release of noble 2.2.2.1
=
l gas radionuclide i (uCi) 2-98
91 2.4-DEFINITIONS OF GASEOUS EFFLUENT TERMS (Centinu':d)
Subsection of Term Definition Initial Use Q{g cumulative ground-level release of 2.2.'.2
=
2 radioiodines, tritium and particulate radionuclide 1 (uci)
Olm cumulative mixed-mode release of 2.2.2.2
=
radioiodines, tritium and particulate radionuclide 1 (uCi)
Op Feed consumption rate for cow or goat 2.2.2.3
=
(kg/ day) qt noble gas source term for the Gaseous 2.1.3.1
=
Waste Processing System or Containment ar.d 2.1.3.2 purge (uCi/sec) t relationship between monitor 2.1.1 R
=
response and the dose rate to the total body for the conditions of the l'
release under consideration.
I Rs relationship between monitor j
=
response and the dose rate to the 2.1.1 1
skin for the conditions of the release under consideration.
i t
relationship between monitor response 2.1.3.1 rt
=
and the dose rate to the total body for Gaseous Waste Processing System j
or Containment purge release for the conditions of the release under consideration.
2-99
,,n a
n ---
e
2.4 IEFINITIONS OF GASEOUS EFFLUEMP TERMS (Centinued)
Subsection of Term Definition Initial Use relationship between monitor response 2.1.3.1 r
=
s and the dose rate to the skin for Gaseous Waste Processing System or Containment purge release for the I
conditions of the release under consideration.
R,ipj pathway-specific, individual 2.2.2.2
=
age-specific, organ dose factor for radionuclide i, pathway p, organ j, 3
and age group a, (mrem /yr per uC1/m )
2 or (m -mrem /yr per uCi/sec).
fraction of deposited radionuclide 2.2.2.2 r
=
retained on vegetation (unitiess).
SF safety factor used to introduce a 2.1.1
=
margin of conservatism into setpoint calculations.
S HF shielding factor afforded by structure 2.2.2.2
=
(unitiess).
stability parameter (sec-2) 2.3.1.2 S
=
l t
=
exposure time for radioactivity 2.2.2.2 1
deposited on ground (seconds)
I t1 time between harvest of leafy 2.2.2.2
=
vegetation and consumption (seconds) f thy time between harvest of stored 2.2.2.2
=
vegetation and consumption (seconds) 2-100
- Lg 2.4 DEFINITIONS OF GASEOUS EFFLUENT TERMS (Continued) l Subsection of Term Definition Initial'Use hm transport time from feed to receptor 2.2.2.3 t
=
for stored feed (seconds) transport time from feed to receptor 2.2.2.3 tg
=
for pasture grass (seconds)
U,p receptor's milk (lite r s/ yea.-) or meat 2.2.2.3
=
(kg/ year) consumption rate for age group a from Table -2.2-10.
U,3 consumption rate of stored vegetation 2.2.2.2
=
by the receptor in age group a (kg/ year) f rom Table 2.2-10.
U,1 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 during atmospheric stability class k (m/sec).
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 (m/sec).
i Nfp pathway-dependent relative dispersion 2.2.2.2
=
or deposition for ground-level releases at the location of the critical receptor.
2 i
i 2-10 1
2.4 DEFINITIONS OF GASEOUS EFFLUElff TERMS (Crntinued)
Subsection of Term Definition Initial Use Wg pathway-dependent relative dispersion 2.2.2.2
=
or deposition for mixed-mode releases at the location of the critical receptor.
distance from release point to point 2.3.1.1 x
=
of interest (meters).
1 vegetation areal density (kg/m )-
2.2.2.2 Y
=
y Yp agricultural productivity by unit area 2.2.2.3
=
2 of pasture feed grass (kg/m ),
Y agricultural productivity by unit area 2.2.2.3
=
s 2
of stored feed (kg/m ),
highest annual average relative 2.1.1
=
(X/Q)g concentration for a ground-level 3
release type (sec/m ),
highest annual average relative 2.1.2
=
(X/Q)g concentration for a mixed-mode 3
release type (sec/m ),
annual average relative concentration 2.2.2.2
=
(X/Q'y for location of controlling (critical) receptor for inhalation and all tritium pathways for a ground-level release type 3
(sec/m ).
annual average relative concentration 2.2.2.2
=
X/Q')g for location of controlling (critical) receptor for inhalation and all tritium pathways for a mixed-mode release 3
type (sec/m ).
2-102
2.' 4 DEFINITIONS OF GLSEOUS EFFLUENP TERMi (Continued)
Subsection of Term Definition Initial Use At decay constant for the ith 2.2.2.2
=
radionuclide (sec-1).
),
decay constant for. removal of activity 2.2.2.2
=
on leaf and plant surfaces by weathering (sec-1).
l'
][zk the vertical standard deviation of the 2.3.1.1
=
plume concentration distribution considering the initial dispersion within the building wake (meters).
1 dFak vertical standard deviation of the 2.3.1.1
=
plume (in meters), for a given distance under the stability category k indicated by AT/ A Z from Figure 2.3-1.
A T/ A Z vertical temperature gradient used to 2.3.1.1
=
determine the atmospheric stability category (OC/100m or F/100 f t. )
O Xiy concentration of radionuclide i for 2.1.1
=
the particular vent release pathway under consideration (uci/ml).
)
2-103 i
' 1; 2.5 GASEOUS RADNhSTE TREATMElff SYSTEMS Figures 2.5-1, 2.5-2, 2.5-3, and 2.5-4 present schematics of the Gaseous Waste Processing System and Ventilation Exhaust Treatment Systems.
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O 3-8 i
.m 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 1 11.1.2; by calculating doses due to gaseous I
effluents in accordance with 3.11.2.3; and by combining direct
(
radiation doses based on direct radiation measurements, or calculations, 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.
4-1
1 n:.
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 6.8.1.4, an assessment of potential doses to MEMBERS OF THE 2
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 the 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 dispersien and deposition values for these two locations and the expected occupancy factors, by an individual during the, year, are as follows:
3 Location X/Ofsec/m 3 gjog,-2)
Estimated Occupancy Factor (by an individual during a year)
Visitors Center 2.53E-5 1.76E-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 5.37E-6 3.90E-9 0.228 (2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br />) 2 In the event that any limit of Technical. Specification 3.11.2.2 is exceeded, an assessment will be performed c'onsidering direct radiation dose to an individual resulting from su'bmersion in the plume.
This assessment will take into consideration the i
annual average dispersion parameters and the estimated occupancy factor stated above, or a more precise value if available, for the locations of interest.
l In the event that any limit of Technical Specification l
3.11.2.3 is exceeded, an assessment will be performed considering
{
the dose to an individual due to inhalation of airborne i
radioactive materials suspendea in the plume and due to direct i
5-1 y
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?j 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 0.05 mrem to an organ due to 2
inhalation and ground-plane or 0.004 mrem to th9 total body due to direct radiation from the plume.
Likewise, potential doses to an individual at Plant Wilson are not expect ed to exceed 5.20 2
mrem to an organ due to inhalation and ground plane or 0.42 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 on anticipated usage; the occupancy factor for Plant Wilson is based on a standard forty hour work week, assuming that an individual is assigned to the facility for the entire year.
5-2
SECTION 6.0 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 Nuclear Regulatory 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 folloWst 7
Sample Medium Analyses Performed Air filters Gross betas gamma isotopics Water B-3; gross betar gamma isotopics Milk I-131; gamma isotopics M
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
Georgis Fow:t Company 333 Piedmont Avenue Atlanta, Georgia 30308 telephone 404 526-6526 Mai!#ng Address Aost Office Box 4545 Atlanta, Georgia 30302 Georgia Power L T. Gucwe ite watten tutre system Manager Nuclear Safety und idCenSing SL-2423 0259m April 28,1987 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C.
20555 NRC 00CKETS 50-424, 50-425 OPERATING LICENSE NPF-68, CONSTRUCTION PERMIT CPPR-109 V0GTLE ELECTRIC GENERATING PLANT UNITS 1 AND 2 OFF-SITE DOSE CALCULATION MANUAL Gentlemen:
Enclosed for your information and use is Revision 3 of the Yogtle Off-Site Dose Calculation Manual (ODCM).
This revision incorporates the changes submitted by letters dated December 16, 1986, January 5,1987, and January 8,1987, thus satisfying the conditions of the NRC staff's approval of the ODCH.
Please contact this office if you have any questions.
Sincerely, L. T. Gucwa Jil/Im Enclosure f 1\\
l Georgialbwer A U. S. Nuclear Regulatory Commission April 28,1987 Page Two c: Georgia Power Company Mr. R. E. Conway (w/o)
Mr. J. P. O'Reilly (w/o)
Mr. G. Bockhold, Jr. (w/o)
Mr. J. F. D' Amico (w/o)
Mr. C. W. Hayes (w/o) l GO-NORMS (w/o) l Southern Company Services Mr. R. A. Thomas (w/o) l Mr. J. A. Bailey (w/o) l Shaw, Pittman, Potts & Trowbridge i
Mr. B. W. Churchill, Attorney-at-Law (w/o)
Troutman, Sanders, Lockerman & Ashmore l
l Mr. A. H. Domby, Attorney-at-Law (w/o) l U. S. Nuclear Regulatory Commission Dr. J. N. Grace, Regional Administrator (w) l Ms. M. A. Miller, Licensing Project Manager, NRR (2 copies, w) i Mr. J. F. Rogge, Senior Resident Inspector-0perations, Vogtle (w)
Georgians Against Nuclear Energy l
Mr. D. Feig (w/o)
Ms. C. Stangler (w/o) i l
l l
l l
0259m
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