ML20237H499
| ML20237H499 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 07/31/1987 |
| From: | GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20237H502 | List: |
| References | |
| PROC-870731, NUDOCS 8708250044 | |
| Download: ML20237H499 (160) | |
Text
{{#Wiki_filter:. _ , _ . _ _ _ _ _ _ . _ _ _ _ _ , - - - - - O Y OFFSITE DOSE CALCULATION MANUAL FOR GEORGIA POWER COMPANY l V0GTLE ELECTRIC GENERATING PLANT i JULY 1987 [k0 khof $ 0 4
INTRODUCTION The Offsite Dose Calculation manual is a supporting document of the Radiological Effluent Technical Specifications (RETS). As such, the ODCM describes the methodology and parameters to be used in the calculation of l 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 l 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 software to perform the described calculations will be maintained current with the ODCM. l C
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. DISTRIBUTION LIST RECIPIENT TITLE / LOCATION NO. OF COPIES Brent Quick Supervisor, Document Control 1-6 Plant Vogtle D. M. Hopper Manager, Radiological Safety 7 - 10 (acting). Georgia Power Company 333 Piedmont,14th floor Atlanta, Georgia L. T.'Gucwa Manager, Nuclear Engineering - 11 and Chief Nuclear Engineer Georgia Power Company 333 Piedmont, 14th floor Atlanta, Georgia l B. L. Maulsby Supervisor, Environmental Center 12 Georgia Power Company Decatur, Georgia R. L. George Manager, Nuclear Plant Support, Vogtle 13 Southern Company Services, Inc.
Inverness Center (' Building 40 Birmingham, Alabama i R. T. Oedamer Supervisor, Technical Writing 14 Southern Company Services, Inc. Inverness Center Building 42, Room 210 Birmingham, Alabana , 1
~1 L._ _ _ - - - - - - - _ - - - - - - - _ - - - - -
L l TABLE OF CONTENTS ; PAGE 1.0 LIOUID EFFLUENTS 1.0-1 1.1 LIQUID EFFLUENT MONITOR SETPOINTS 1.1 -1 1.1.1 Liquid Waste Processing System Effluent Radioactivity Monitor 1.1 -1 1 Monitor Setpoint Calculation Methodology 1.1.1.1 When One Waste Monitor Tank Per Unit Is to Be Released at a Time 1.1-4 1.1.1.2 Monitor Setpoint Calculation Methodology When Two Waste Monitor Tanks Per Unit Are to Be Released at a Time 1.1-11 1.1.2 Steam Generator Blowdown Effluent Radioactivity Monitor; Turbine Building Drain Effluent Radioactivity Monitor; and Control Building Sump Effluent Radioactivity Monitor 1.1-13 1 1.1.3 Nuclear Service Cooling Water System Effluent Radioactivity Monitor 1.1-14 ' 1.2 DOSE CALCULATION FOR LIQUID EFFLUENTS 1. 2-1 1.3 DOSE PROJECTIONS FOR LIQUID EFFLUENTS 1. 3-1 1.3.1 Thirty-One Day Dose Projections 1. 3-1 1.3.2 Dose Projections for Specific Releases 1.3-2 1.4 DEFINITIONS OF LIQUID EFFLUENT TERMS 1.4-1 1.5 LIQUID WASTE PROCESSING SYSTEM AND LIQUID DISCHARGE PATHWAYS 1. 5 -1 2.0 GASE0US EFFLUENTS 2. 0-1 2.1 GASEOUS EFFLUENT MONITOR SETPOINTS 2 .1 -1 2.1.1 Unit 1 Turbine Building Vent; Unit 2 Turbine Building Vent; Radwaste Solidification Building Vent 2.1 -2 2.1. 2 Unit 1 Plant Vent and Unit 2 Plant Vent 2.1-4 2.1. 3 Gaseous Waste Processing System Discharge and Reactor Containment Purge 2.1-5 2.1.3.1 Gaseous Waste Processing System 2.1-6 2.1.3.2 Reactor Containment Purge 2.1-8 2.1.4 Consideration of Monitor Response and Background in Establishing Gaseous Effluent Monitor Setpoints 2.1-10 VEGP ODCM, REV 4 7/30/87 i
TABLE OF CONTENTS (Cont.) PAGE 2.1.5 Determination of Allocation Factor, AG 2.1-11 2.2 GASEOUS EFFLUENT DOSE RATE AND DOSE CALCULATIONS 2.2-1 2.2.1 Dose Rates at or Beyond the Site Boundary 2.2-1 f 2.2.1.1 Dose Rates Due to Noble Gases 2.2-1 2.2.1.2 Dose Rates Due to I-131, _I-133, Tritium, and Particulate 2.2-2 2.2.2 Air Doses and Dose to a Member of the Public at or Beyond the Site Boundary 2.2-3 2.2.2 1 Air Doses at or_ Beyond the Site Boundary 2.2-3 2.2.2.2 Dose to a Member of the Public at or Beyond the Site Boundary 2.2-5 2.2.2.3 Dose Calculations-to Support Other Technical Specifications 2.2-16 2.2.3 Dose Projections for Gaseous Effluents 2.2-53 2.2.3.1 Thirty-One Day Dose Projections 2.2-53 2.2.3.2 Dose Projections for Specific Releases 2.2-54 2.3 METEOROLOGICAL MODEL 2. 3-1 2.3.1 Atmospheric Dispersion 2.3-1 l 2.3.1.1 Ground-Level Releases 2 . 3-1 2.3.1.2 Mixed-Mode Releases 2.3-3 2.3.2 Relative Deposition 2.3-5 2.3.2.1 Ground-Level Releases 2.3-5 2.3.2.2 Mixe'd-Mode Releases 2.3-5 2.4 DEFINITIONS OF GASEOUS EFFLUENT TERMS 2.4-1 2.5 GASEOUS RADWASTE TREATMENT SYSTEMS 2.5-1 3.0 RADIOLOGICAL ENVIRONMENTAL MONI.TO, RING FROGRAM 3.0-1 4.0 TOTAL DOSE DETERMINATIONS
' 4.0-1 5.0 POTENTIAL DOSES TO MEMBERS OF THE PUBLIC DUE iO ~~~
THEIR ACTIVITIES INSIDE THE SITE BOUNDARY 5.0-1 6.0 INTERLABORATORY COMPARISON PROGRAM 6.0-1
.VEGP ODCM, REV'4 7/30/87 11
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1 LIST OF TABLES 1 TABLE TITLE PAGE 1.2-1 Bioaccumulation Factors 1.2-4 1 1.2-2 Adult Ingestion Dose Factors 1.2-5 - 1.2-3 Site-Related Ingestion Dose Factors for Freshwater Fish and Drinking Water Consumption 1.2-8 { ' 2.1 -1 Dose Factors for Exposure to a Semi-Infinite Cloud ! of Noble Gases 2.1-13 ) 2.1 -2 Gaseous Release Points Flow Rates 2.1-14 l 2.2-1 Inhala'. Ion Dose Factors for Infant 2.2-18 i 2.2-2 Inhalation Dose Factors for Child 2.2-21 2.2-3 Inhalation Dose Factors for Teenager 2.2-24 I 2.2-4 Inhalation Dose Factors for Adult 2.2-27 2.2-5 Ingestion Dose Factors for Infant l 2.2-30 l 2.2-6 Ingestion Dose Factors for Child 2.2-33
- 2.2-7 Ingestion Dose Factors for Teenager 2.2-36 l 2.2-8 Ingestion Dose Factors for Adult 2.2-39 2.2 9 External Dcse Factors for Standing on Contaminated Ground 2.2-42 2.2-10 Individual Usage Factors 2.2-44 i 2.2-11 Stable Element Transfer Data 2.2-45 2.2-12 Controlling Receptor 2.2-46 ]-
2 2-13 Site-Specific (or Default) Values to Be Used in l l Pathway Factor Calculations 2.2-47 ! I '* 2. 2-14 Potential Receptor Locations and Pathways 2.2-51 2.2-15 Dispersion and Deposition Parameters 2.2-52 s 2.34 Terrain Elevation above Plant Grade 2.3-7
\ l 3,0-1 Radiological Environmental Sampling Locations 3.0-2 U
+
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I VEGP OD;M, REV 4 7/30/87 iii m a t r _ n
LIST OF FIGURES FIGURE TITLE PAGE 1.5-1 Liquid Waste Processing System (Unit.1) 1.5-2 1.5-2 Liquid Waste Processing System (Unit 2) 1.5-3 1.5-3 Liquid Discharge Pathways 1.5-4
- 2. 3-1 Vertical Standard Deviation of Material in a Plume 2.3-2 2.3-9 Plume Depletion Effect for Ground-Level Releases 2.3-10 2.3-3 Plume Depletion Effect for 30-Meter Releases 2.3-11 2.3-4 Plume Depletion Effect for 60-Meter Releases 2.3-12 2.3-5 Plume Depletion Effect for 100-Meter Releases 2.3-13 2.3-6 Relative Deposition for Ground-Level Releases 2.3-14 2.3-7 Relative Deposition for 30-Meter Releases 2.3-8 2.3-15 Relative Deposition for 60-Meter Releases 2.3-16 2.3-9 Relative Deposition for 100-Meter Releases 2.3-17 2.5-1 Gaseous Waste Processing System 2.5-2 2.5-2 Ventilation Exhaust Treatment System (Plant Vent) 2.5-3 2.5-3 Ventilation Exhaust Treatment System (Turbine Building) 2.5-4 2.5-4 Ventilation Exhaust Treatment System (Radwaste Solidification Building) 2.5-5
- 3. 0-1 Terrestrial Stations Near Site Boundary 3.0-2 3.0-4 Terrestrial Stations Beyond Site Boundary out to Approximately Five Miles and Aquatic Stations 3.0-5 3.0-3 Terrestrial Stations Beyond Five Miles l 3.0-4 - Drinking Water Stations 3.0-6 3.0-7 i
1 VEGP ODCM, REV 4 7/30/87 iv
V0GTLE ELECTRIC GENERATING PLANT OFFSITE DOSE CALCULATION MANUAL Revision No. Date 1 0 August 1985 l 1 August 1986 2 November.1986 ' 3 March 1987 4 July 1987 l I i l l I l l l l
l.0 LIOUID EFFLUENTS The Vogtle Electric Generating Plant is located on the west bank of the Savannah River approximately 151 river miles from the Atlantic Ocean. Tnere are two pressurized water reactors on the site. Each unit is served by a separate liquid waste prc:essing 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 f rom the bicwdown 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 from the cooling tower makeup water ; bypass line. . Although no significant quantities of radioactivity are expected in the nuclear service cooling water, the steam generator blowdown processing system, the turbine building drain system, or the control building sump, these effluent pathways are monitored as a precautionary measure. The monitors serving the latter three ef fluent 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 releases via tnese effluent pathways must be 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 methodology for calculating monitor setpoints and for calculating individual doses due to liquid effluents released from Plant Vogtle to the Savannah River. I 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. l VEGP 00CM, REV 4 7/30/87 1.0-1 l, I k _ _ _________ _ _ _ _ _
I 1.1 LIQUID EFFLUENT MONITOR SETPOINTS Liquid monitor setpoint values caiculated in accordance with the methodology presented in this subsection will be regarded as upper bounds for the actual l monitor setpoints for high alarms. However, a lower setpoint may be established on the monitor 1f desired. Intermediate level setpoints should 1 be established. at an appropriate level to give sufficient warning prior to f reaching t'he high alarm setpoint. The basic calculated monitor setpoint i value is in terms of concentration, pCi/ml. The actual monitor setpoint established on the monitor is the calculated monitor setpoint value adjusted by appropriate calibration data and monitor background. Monitor calibration data may include operational data obtained from monitor response to concentrations determined by liquid sample analyses. In addition, monitor l background must be controlled so that the monitor is capable of responding to l concentrations in the range of the setpoint value. For planned releases from the liquid waste processing system's monitor tanks, monitor setpoints are determined to assure that the limits of 10 CFR 20 are 1 l not exceeded. For the steam generator processing system ef fluent 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 j radioactivity from these systems by terminating releases upon detection of f low levels of radioactivity. Therefore, setpoints for these monitors should l 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. l 1.1.1 Liouid Waste Processino System Effluent Monitor (RE0018) (One monitor Der 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, VEGP ODCM, REV 4 7/30/87 1.1 -1
i i at the release point to the unrestricted area. Concentration lim'its are , specified in Technical Specification 3/4.11.?.1; setpoint requirements are ! specified in Technical Specification 3.3.3.9. To meet these specifications, l the alarm / trip setpoint for this liquid efflJent monitor is set to assure I that the following equation is satisfied: 1 ef <C (1) MPC t F+f j where: l l s C MPC
= the effluent concentration limit corresponding to the specific mix of radionuclides in the waste monitor tank being considered for discharge, in pCi/ml. )
c = the setpoint, in pC1/ml, of the radioactivity monitor measuring the concentration of radioactivity in the effluent line prior to dilution and subsequent release. (Note that the monitor setpoint.is inversely proportional to the effluent ) flowrate, f, and directly proportional to the dilution stream flowrate, F + f.) The setpoint represents a concentration i l value which, if exceeded, could result in concentrations { exceeding the limits of 10 CFR 20 in the unrestricted area. f
= the effluent flowrate at the location of the radioactivity monitor, in volume per unit time, and in the same units as F, below.
l l F = the dilution stream flowrate which can be assured prior to the ! release point to the river, in volume per unit time, i At Plant Vogtle, the liquid waste processing system collects liquid wastes in J monitor tanks prior to release. There are two waste monitor tanks for each s unit. The discharge lines from the two tanks join to form a common line, on which the radioactivity monitor is installed. The lines from each unit then join to form a common line which releases to the blowdown sump discharge line to the Savannah River. (See figure 1.5-3.) ! i VEGP 00CM, REV 4 7/30/87 1.1-2
~
1 Dilution flow comes from the blowdown sump which receives water from nuclear service cooling tower blowdown, turbine plant cooling tower blowdown, waste I water retention basin discharge, and the cooling tower makeup line. The two major sources for dilution are the turbine plant cooling tower blowdown and the cooling tower makeup bypass line. A predetermined dilution flowrate 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 flowrate, f, the dilution flowrate, F, and the radioactivity monitor setpoint, it cannot practically be applied to a u.1xture of radionuclides with dif ferent limiting concentrations, i.e., different MPC values. l l For a mixture of radionuclides, equation (1) is satisfied in a practicable manner, based on measured radionuclides concentrations and a dilution stream l flowrate which can be assured for the duration of the release, designated as Fd , by calculating the MPC fraction for the radionuclides mixture, the maximum permissible effluent flowrate, f,, and the radioactivity monitor setpoint, c. In order to facilitate effluent release control and accountability, liquid releases normally should be controlled administratively such that only one wastc 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 conynon 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 flowrates at which the tanks are released. The setpoint methodology for this situation is presented in subsection 1.1.1.2. VEGP ODCH, REV 4 7/30/87 1.1-3
1.1.1.1 Monitor Setpoint CalculaM on Methodology When One Waste Monitor Tank per b. lit Is to Be iteleased at a Time Step 1 The radionuclides' concentrations for the waste monitor tank planned for release are determined in accordance with Technical Specification table 4.11-1. The relationship of the various required sample analyses is shown as follows:
= C + + C + C g (C, 3 f + Ct) (2) j where:
1 C = the concentration of each measured ganrna 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. (NOTE: Sample is analyzed for gross alpha.) C, = the measured concentrations of Sr-89 and Sr-90 in liquid waste as observed in the QUARTERLY composite sample. C f
= the measured concentrations of Fe-55 in liquid waste as observed in the QUARTERLY composite sample.
C = the measured concentration of H-3 in liquid waste as determined l from analysis of the MONTHLY composite sample. The C 9 term will include the analysis of each batch; terms for alpha, strontiums, iron, and tritium will be included in accordance with Technical Specification table 4.11-1 as appropriate. VEGP ODCM, REV 4 7/30/87 1.1-4
In order to assure' that' sample ' analyses are based on samples which are representative of the volume from which the samples are taken, liquid volumes I must be thoroughly mixed prior to sampling. Mixing may be accomplished by any method of mixing which has been demonstrated to achieve mixing sufficient to allow representative sampling. I Step 2 Measured radionuclides concentrations are used to calculate'HPC fractions. The MPC fractions are used along with a safety factor to calculate a required dilution factor, which is the ratio of dilution flowrate to monitor tank discharge flowrate 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 j calculated as follows: I RDF = g + SF r i i i 1
~ -
C C C C C () a RDF = gp + * + * + gPC, MPC MPC MPC f t, where: 1 C
= the measured concentrations of C , C,, C,, C and C f
as defined in step 1. Terms C , C,, C , and C will f be included in the calculation as appropriate. MPC = MPC , MPC , MPC,, MPC l f , and MPC are limiting concentrations of l the appropriate radionuclides from 10 CFR 20, Appendix B, Table II, Column 2. For dissolved or ; i entrained noble gases, the concentration shall be limited to 2 x 10~ pCi/mi total activity. For gross alpha the maximum j permissible concentration shall be 3x10~ pCi/ml. If specific alpha- emitting radionuclides are measured, the MPC 1 for the specific radionuclides (s) shall be used. VEGP ODCM, REV 4 7/30/87 1.1-5 l
1 1 l SF .= the safety factor, which is a conservative factor selected to l. 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 for liquid releases. A more precise value may be developed if desired. Step 3 Determine the dilution stream flowrate which will be assured during the period of the release, which is designated as F . For Plant Vogtle the d flowrate which can be assured is the value selected as the setpoint for the
]
dilution stream flowrate measurement device. Since the value selected as the f setpoint for the dilution stream flowrate measurement device is the dilutio'n i stream flowrate 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 radioactivity monitor setpoint, c. If simultaneous releases are planned from the liquid waste processing systems of Unit 1 and Unit 2, the dilution stream must be allocated between the two , units. This is accomplished by multiplying the assured dilution stream flowrate, Fd , by an allocation factor, AF, to obtain a unit-specific i assured dilution stream flowrate, F du' i Fdu = Fd (AF) (4) ' where: 4 AF = an allocation factor selected to apportion the diluting capacity of the dilution stream between the two units when simultaneous releases from the liquid waste processing systems l l are planned. AF may be assigned any value between 0 and 1 for each unit under the condition that the sum of the allocation { factors does not exceed 1. For convenience AF may be assigned the value of 0.5 for each unit. Also, if it is desired to j make liquid waste processing system releases from each unit withcut regard to releases from the other unit, AF should be , assigned the value of 0.5 for each unit. VEGP ODCM, REV 4 7/30/87 1.1-6
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 flowrate 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 Fg 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 flowrate. However, in
)
order to maintain individual doses due to radioactivity in liquids released to unrestricted areas as low as reasonably achievable (ALARA), no releases i l from the liquid waste processing system should be made if assured dilution j stream flowrate, F , is less than 5000 gpm. i Step 4 For the case RDF > 1, calculate the maximum permissible waste monitor tank discharge flowrate, f,, as follows: F l f, , du (5) 1 RDF-1 l For the case RDF < 1, equation (5) is not valid'. However, as discussed l above, for the case RDF < 1, the release may be made at full pump discharge capacity and the monitor setpoint calculated in accordance with Step 5. 4 NOTE 1: Waste monitor tank discharge flowrate is actually limited by pump design discharge capacity which is 100 gpm (maximum). When calculated maximum permissible release flowrates are
> 100 gpm, the release may be made at full pump capacity.
Release rates < 100 gpm may be achieved by throttling. VEGP ODCM, REV 4 7/30/87 1.1-7 i
NOTE 2: If radioactivity due to plant operations is detected in any of the effluent streams discharging to the blowdown sump (waste water retention basin, nuclear service water cooling tower blowdown, or turbine plant cooling tower blowdown), the 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
*" du ~II i r RDF-1 ri MPC Ib) where:
i/ r ,
, j I(C1/MPC 1 )r the
= MPC fraction of the effluent stream (s).containing the detectable radioactivity.
f = the flowrate of the effluent stream (s) containing the radioactivity. If RDF < 1, NOTE 2 does not apply. Steo 5 Based on the values determined in the previous steps, a liquid waste-j processing system effluent radioactivity monitor base setpoint is calculated to provide assurance that the limits of 10 CFR 20, Appendix B Table II, Column 2, will not be exceeded. .The radioactivity monitor response is to gamma radiation primarily; therefore, the monitor setpoint calculation is based on C , in units of pCi/ml, t l as follows: 9 9 c= A g I Cg (7) VEGP ODCM, REV 4 7/30/87 1.1-8
where: A = the adjustment factor which will allow the setpoint to be established in a practical manner to prevent spurious alarms and to allow for the margin between measured concentrations and concentrations which would approach 10 CFR 20 limits: A= p (8) NOTE: ADF is the assured dilution factor: du a ADF = (8a) f a and f is the anticipated release flowrate from the waste monitor tank to be discharged. i ( 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 flowrate, postponing simultaneous releases, and/or by decreasing concentrations by i further processing of the liquid waste planned for release. Following these actions, repeat the previous steps and calculate a new monitor setpoint. l If A < 1, no release may be made under planned conditions. Consider the-alternatives discussed above to reduce potential release concentrations, and calculate a new monitor,setpoint based on the results of the alternatives selected. VEGP ODCM, REV 4 7/30/87 1.1-9 l
i l l l The calculated setpoint establishes the base value for the radioacitvity l monitor setpoint. However, in establishing the actual setpoint for a i particular monitor, adjustments must be taken into account for background -
)
radiation levels and monitor calibration-information. Background radiation '1 levels must be controlled such that radioactivity levels in the effluent j stream being monitored can accurately be assessed at levels below the setpoint value. l I Calibration of the monitors by the manufacturer utilized NBS traceable liquid solutions in the exact geometry of the production monitors over a gamma ray
- energy range of 0.08 to 1.33 MeV. The calibration factor is a function of I
the radionuclides mix in the liquid to be released and will be calculated for the monitor based on the results of the predischarge sample results from the j laboratory gamma-ray spectrometer system. The actual monitor setpoint is I l determined as follows:
=
C ms A g C g (CF)g i BG (8b) where: CF = the calibration factor for the particular radionuclides g for the monitor. i BG = the 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 l 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 ccntains no measurable radioactivity, the monitor setpcint should be established as close to background as practical to prevent spurious alarms and yet alarm should an inadvertent release occur. VEGP ODCM, REV 4 7/30/87 1.1-10
1.1.1.2 Monitor Setpoint Calculation Methodology When Two Waste Monitor Tanks per Unit'Are to Be Released at a Time Steo 1 Determine radionuclides concentrations for each waste monitor tank as described in step 1 of subsection 1.1.1.1. From the Cg terms determined for each tank, determine an effective I (g Cg ), for the two tanks considered together as followsi I E YI 1 a C,)) + Vg ( ,I Cg)2 I gC (9) g ), = y] ,y p where: V)
=
the volume of liquid in tank containing greater quantity (referred to throughout this subsection as first tank.) t V 2
=
the volume of liquid in tank containing lesser quantity-(referred to throughout this subsection as second tank). T
=
(g' Cg )) the measured concentrations of gamma-emitting radionuclides in first tank. ( Cg)2
=
the measured concentration of gamma-emitting 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: V3 (RDF)) +V2 (RDF)2 (10) (RDF),= y1,y2 VEGP ODCM, REV 4 7/30/87 1.1-11
1 where: I V)
=
the volume of first tank. I V 2
= the volume o'f second tank. .
1
= the required dilution factor for first . tank.
(RDF))
= the required dilution factor for second tank.
(RDF)2 I Steo 3 l Determine the dilution stream flowrate in accordance with step 3 of subsection 1.1.1.1. Steo 4 . To facilitate calculation of the monitor setpoint, determine release I flowrates for each tank so that the durations of the releases from the two tanks are equal. l First, select a release flowrate for the first tank, f). . Then, determine the release flowrate for the second rank, f ' #s f 11 Ws l 2
)
1 2 (11) f 2 V) Next, determine a combined flowrate, f , for releases from both tanks, as l follows:
=
f c f1+f2 (12) Next, calculate a maximum permissible flowrate, f , for the combined release in accordance with step 4 of subsection 1.1.1.1 using the ef fective (RDF) determined in step 2 above. Then, compare the combined release flowrate, f , with the maximum permissible combined release flowrate, f . If f > f , the release may VEGP ODCM, REV 4 7/30/87 1.1-12
- 1 e
_r f 4 i be made under the assumed conditions. If f < f , the two release flowrates may be throttled, maintaining the same ratio of2 f to f), as j determined earlier. If it is impractical to throttle the release flowrates. to the necessary degree to achieve f < f , steps must be taken to reduce c m l potential release concentrations prior to making the release, and a new f determined following the necessary actions. (Steps which may be undertaken l l, to reduce potential release concentrations were discussed in step 5 of { l subsection 1.1.1.1.) t l Steo 5 l , t Calculate the monitor setpoint in accordance with step 5 of subsection 1.1.1.1 with the following substitutions: f Let I I g cg - (g c g)e; ! l l RDF = (RDF),; and fa"fc Observe the same limiting conditions discussed in step 5 of subsection l 1.1.1.1. l i l 1.1.2, Steam Generator Blowdown Effluent Radioactivity Monitor (RE-0021): Turbine Building Drain Cf fluent Radioactivity Monitor (RE-0848): and , Control Buildino Sumo Effluent Radioactivity Monitor (RE-17646). (One of each monitor per unit) i 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 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 VEGP 00CM, REV 4 7/30/87 1.1-13
1 l i j under operating conditions and within the stated objective of ' preventing j releases of radioactivity via these pathways to the' extent practicable. All three of these effluent streams discharge to the waste water retention basin,. j which in turn releases to the blowdown sump; the blowdown sump discharges to the Savannah River. Should it-become necessary to make releases from any of these three sources { containing levels of radioactivity above that which would normally be isolated or diverted, radioactivity monitor setpoints should be determined in
~
the same manner as described in subsection 1.1.1. However, special i consideration must be given to step 3. An allocation factor must be assigned to the release pathway under consideration here and allocation factors for other pathways, which may be releasing simultaneously, adjusted if necessary. so that for simultaneous liquid releases from the site, the sum of the I allocation factors does not exceed 1. As stated earlier, all three of these effluent streams discharge to the waste water retention basin. Composite samples are collected'from the discharge j line from the waste water retention basin to the blowdown sump. Sample collection and analysis must be sufficient to assure that the dose limits l specified in Technical Specification 3.11.1.2 are not exceeded. l 1.1.3 Nuclear Service Cooling Water System Effluent Radioactivity Monitor (RE-0020 A and B) (Two monitors Der unit) l Radioactivity in these effluent streams normally is expected to be below l 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 ef fluent streams should become contaminated with radioactivity, radionuclides concentrations must be determined and a radioactivity monitor setpoint
, determined in the same manner as described in subsection 1.1.1. However, special consideration must be given to step 3. An allocation' factor must be l- assigned to the. release pathway under consideration'here and allocation factors for other pathways, which may be releasing simultaneously, adjusted l
VEGP ODCM, REV 4 7/30/87 1.1-14 l l
l if necessary so that for simultaneous liquid releases from the site the sum I of the allocation factors does not exceed 1. Determination of concentrations of radioactivity in these streams must be adequate to assure that the dose limits specified in Technical Specification 3.11.1.2 are not exceeded. l
. 1 l
l l l i l VEGP ODCM, REV 4 7/30/87 1.1-15
1.2 COSE 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. 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: m D, = fA,t=1 j I atg C$g 1F (13) where: i 0 = the cumulative dose commitment to the total body or any organ, t, due to radioactivity in liquid effluents for the total time period i m I at in g mrem (Reference 1). t=1 at = the length of the Eth time period over which C and F are g averaged for any liquid release, in hours. C h
=
the average concentration of radionuclides i, in undiluted liquid effluent during time period at from any liquid release, in pCi/ml. VEGP ODCM, REV 4 7/30/87 1,2-1 L . L .
- - - - - a
F = 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 flowrate into the river times Z. NOTE: If simultaneous releases from both units occur, the dilution stream flowrate must be apportioned between the two units as discussed in subsection 1.1.1, step 3. In such cases, F is unit-specific. F = (average undiluted liquid waste flow) + ((average dilution stream flow during the period of release of radioactivity) , l x Z) (14) l NOTE: The denominator of equation (14) is limited to 1000 cfs (448,800 gpm) or less. (Reference 1, section 4.3.) l Z = the applicable dilution factor for the Savannah River. For the l months May through December, Z-10; for the months January l through April, Z-20. (Reference 5, section 11.2.3.4; reference 11.) A h
=
the site-related adult ingestion dose commitment factor to the total body or any organ for each identified radionuclides. Site-related A values for Plant Vogtle are listed in h table 1.2-3 in mrem-m1 per h pC1. A, $
=
Kg ((U /Dg ) e +U p BF4e I) DF $ (15) K = g the units conversion factor 1.14 x 10 , determined by: 10 0C1 x 10 ml + 8760 h pCi 1 year U = the adult drinking water consumption (730 liters / year; reference 3, table E-5). VEGP ODCM, REV 4 7/30/87 1.2-2 l
D = the dilution factor from the vicinity of the liquid release point for the plant site to the potable water intake location (8; reference 11)- . {' A
= the decay constant for radionuclides 1 (h- ).
t = the transit' time from release to receptor for water consumption (48 h; reference 3, section A.2;' reference.10). U F
= the adult fish consumption (21 kg/ year; reference 3, table E-5).
BF,
= the bioaccumulation f actor for radionuclides 1, in f resh wate'r fish, in pCi/kg per pC1/1. (See table 1.2-1; reference 3, table A-1; reference 2. for Ag; reference 14 for P.)
t g
= the transit time from release to receptor for fish consumption (24 h; reference 3, section A.2).
DF
=
the dose conversion factor for radionuclides i, for adults in organ, r, in mrem /pci, from table 1.2-2 (reference 3, table E-11). l VEGP ODCM, REV 4 7/30/87 1.2-3
I TABLE 1.2-1 BI0 ACCUMULATION FACTORS ' (pC1/kg per pCi/ liter)* Freshwater - ! Element Fish 1 H 9.0E-01 l C 4.6E 03 Na 1.0E 02. J j P 3.0E 03 R Cr 2.0E 02 Mn 4.0E 02 Fe 1.0E 02 Co 5.0E 01 Ni 1.0E 02 Cu Zn 5.0E 01 2.0E 03 - jj Br 4.2E 02 Rb 2.0E 03 Sr 3.0E 01 Y 2.5E 01 Zr 3.3E 00 l Nb 3.0E 04 t l
~ Mo 1.0E 01 j Tc 1.5E 01 Ru 1.0E 01 Rh 1.0E 01 I
Ag 2.3E 00 Te 4.0E 02 I 1.5E 01 Cs 2.0E 03 i Ba 4.0E 00 La 2.5E 01 4 Ce - 1.0E 00 l Pr 2.5E 01 ' Nd 2.5E 01 W 1.2E 03 Np 1.0E 01
. i i
- Reference 3 Table A-1; Reference 2 for Ag; Reference 14 for P.
l (~ VEGP ODCM, REV 4 7/30/87 1.2-4 ' L_____________________.____._________.._ . _ . _
l l Table 1.2-2 (SHEET 1 0F 3) ADULT INGESTION DOSE FACTORS
- 1 (mrem 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 i C-14 2.84E-06 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 I Na-24 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 '
1 P-32 1.93E-04 1.20E-05 7.46E-06 No Data No Data No Data 2.17E-05 Cr-51 No Data No Data 2.66E-09 1.59E-09 5.86E-10 3.53E-09 6.69E-07 Mn-54 No Data 4.57E-06 8.72E-07 No Data 1.36E-06 No Data 1.40E-05 Mn-56 No Data 1.15E-07 2.04E-08 No Data 1.46E-07 No Data 3.67E-06 Fe-55 2.75E-06 1.90E-06 4.43E-07 No Data No Data 1.06E-06 1.09E-06 Fe-59 4.34E-06 1.02E-05 3.91E-06 No Data No-Data 2.85E-06 3.40E-05 Co-58 No Data 7.45E-07 1.67E-06 No Data No Data No Data 1.51E-05 1 Co-60 No Data 2.14E-06 4.72E-06 No Data No Data No Data 4.02E-05 ) Ni-63 1.30E-04 9.01E-06 4.36E-06 No Data No Data No Data 1.G8E-06 Ni-65 5.28E-07 6.86E-08 3.13 E-08 No Data No Data No Data 1.74E-06 Cu-64 No Data 8.33E-08 3.91E-08 No Data 2.10E-07 No Data 7.10E-06 Zn-65 4.84E-06 1.54E-05 6.96E-06 No Data 1.03E-05 No Data 9.70E-06 Zn-69 1.03E-08 1.97E-08 1.37E-09 No Data 1.28E-08 No Data 2.96E-09 8r-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 2.11E-05 9.83E-06 No Data No Data No Data 4.16E-06 Rb-88 No Data 6.05E-08 3. 21 E-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 i Sr-89 3.08E-04 No Data 8.84E-06 No Data No Data No Data 4.94E-05 { k Sr-90 7.58E-03 No Data 1.86E-03 No Data No Data No Data 2.19E-04 l 1 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 l Y-91m 9.09E-11 No Data 3. 52 E-12 No Data No Data No Data 2.67E-10 l Y-91 1.41E-07 No Data 3.77E-09 No Data No Data No Data 7.76E-05 j Y-92 8. 45 E-10 No Data 2.47E-11 No Data No Data No Data 1.48E-05 i l L i l l
- Reference 3, Table E-11.
VEGP ODCM, REV 4 7/30/87 I 1.2-5 j'l 1
)
Table 1.2-2 (SHEET 2 0F 3) ADULT INGESTION DOSE FACTORS * (mrem per pCi ingested) Nuclide Bone Liver T Body Thyroid Kidney Luno GI-LLI Y-93 2.68E-09 No Data 7.40E-11 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. 39 E-10 1. 55 E-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 I Tc-101 2.54E-10 3. 66E-10 3.59E-09 No Data 6.59E-09 1.87E-10 1.10E-21 l Ru-103 1.85E-07 No Data 7.97E-08 No Data 7.06E-07 No Data 2.16E-05 i Ru-105 1.54E-08 No Data 6.08E-09 No Data 1.99E-07 No Data 9.42E-06 Ru-106 2.75E-06 No Data 3.48E-07 No Data 5.31E-06 No Data 1.78E-04 Ag-110m 1.60E-07 1.48E-07 8.79E-08 No Data 2.91E-07 No Data 6.04E-05 Te-125m 2.68E-06 9.71E-07 3.59E-07 8.06E-07 1.09E-05 No Data 1.07E-05 Te-127m 6.77E-06 2.42E-06 8.25E-07 1.73E-06 2.75E-05 No Data 2.27E-05 Te-127 1.10E-07 3.95E-08 2.38E-08 8.15E-08 4.48E-07 No Data 8.68E-06 Te-129m 1.15E-05 4.29E-06 1.82E-06 3.95E-06 4.80E-05 No Data 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 l Te-131 m 1.73E-06 8.46E-07 7.05E-07 1.34E-06 8.57E-06 No Data 8.40E-05 Te-131 1.97E-08 8.23E-09 6.22E-09 1.62E-08 8.63E-08 No Data 2.79E-09 { Te-132 2.52E-06 1.63E-06 1.53E-06 1.80E-06 1.57E-05 No Data I-130 7.71E-05 ; 7.56E-07 2.23E-06 8.80E-07 1.89E-04 3.48E-06 No Data 1.92E-06 i 1-131 4.16E-06 5.95E-06 3.41E-06 1.95E-03 1.02E-05 No Data 1.57E-06 l l 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. 51 E-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 Cs-138 3.70E-05 1.23E-05 2.11E-06 5.52E-08 1.09E-07 5.40E-08 No Data 8.01E-08 7.91E-09 4.65E-13 8a-139 9.70E-08 6.91 E-11 2.84E-09 No Data 6.46E-11 3.92E-11 1.72E-07 Ba-140 2.03E-05 2.55E-08 1.33E-06 No Data Ba-141 8.67E-09 1.46E-08 4.18E-05 4.71E-08 3.56E-11 1.59E-09 No Data 3. 31 E-11 2.02E-11 2.22E-17 8a-142 2.13E-08 2.19E-11 1.34E-09 No Data 1.85E-11 1.24E-11 3.00E-26
*Ref erence 3, Table E-11.
VEGP ODCM, REV 4 7/30/87 1.2-6 L-___________ . _ _ _ _ _ _ .
i
.i Table,,1.2-2 (SHEET 3 0F 3)
ADULT INGESTION DOSE FACTORS
- I (mrem per pCi ingested) -
l Nuclide Bone Liver T Body Thyroid Kidney Luno GI-LLI i La-140 2.50E-09 1.26E-09 3. 33E-10 No Data No Data No Data 9.25E-05 ! La-142 1. 28 E-10 5.82E-11 1.45E-11 No Data No Data. No Data 4.25E-07 1 Ce-141 9.36E-09 6.33E-09 7.18E-10 No Data 2.94E-09 No Data 2.42E-05 i Ce-143 1.65E-09 1.22E-06 1.35E-10~ No Data 5.37 E-10 No Data 4.56E-05
'Ce-144 4.88E-07 2.04E-07 2.62E-08 No Data 1.21E-07 No Data 1.65E-04 Pr-143 9.20E-09 3.69E-09 4. 56 E-10 No Data 2.13E-09 No Data 4.03E-05 l Pr-144 3.01E-11 1.25E-11 ~ 1.53E-12 No Data 7.05E-12 No Data 4.33E-18 l Nd-147 6.29E-09 7.27E-09 4.35E-10 No Data 4.25E-09 No Data 3.49E-05 W-187 1.03E-07 8.61E-08 3.01E-08 No Data No Data No Data 2.82E-05 Np-239 1.19E-09 1.17 E-10 6.45E-11 No Data 3.65E-10 No Data- 2.40E-05 !
i 1 1 1 1 I l 1 I 4
- Reference 3, Table E-11.
VEGP ODCM, REV 4 7/30/87 1.2-7 ! 1
I l l l Table 1.2-3 (SHEET 1 0F 2) l SITE-RELATED INGESTION DOSE FACTORS, Aj, i (FOR FRESHWATER FISH AND DRINKING WATER CONSUMPTION)* (mrem /h per uC1/ml)
- Nuclide Bone Liver T Body Thyroid Kidney Luno GI-L L I 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 3.13 E +04 6.26E+03 6.26E+03 6.26E+03 6.26E+03 6.26E+03 6.26E+03 Na-24 1.36E+02 1.36E+02 1.36E+02 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 i l Mn-56 0.00E+00 1.73E-01 3.07E-02 0.00E400 2.20E-01 0.00E+00 5.52E+00 Fe-55 6.86E+02 4.74E+02 1.11E+02 0.00E+00 0.00E+00 2.65E+02 2.72E+02 l Fe-59 1.07E+03 2.51E+03 9.61E+02 0.00E+00 0.00E+00 7.01E+02 8.36E+03 l Co-58 0.00E+00 9.59E+01 2.15 E+02 0.00E+00 0.00E+00 0.00E+00 1.94E+03 l . Co-60 0.00E+00 2.78E+02 6.14E+02 0.00E+00 0.00E+00 0.00E+00 5.23E+03 ! l 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 i Cu-64 0.00E+00 2.79E+00 1. 31 E+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 i Zn-69 1.24E-06 2.38E-06 1.65E-07 0.00E+00 1.55E-06 0.00E+00 3.57E-07 i Br-83 0.00E+00 0.00E+00 4.02E-02 0.00E+00 0.00E+00 0.00E+00 5.80E-02 Br-84 0.00E+00 0.00E+00 1.16E-12 0.00E+00 0.00E+00 0.00E+00 9.12E-18 Br-85 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 9.75E+04 4.54E+04 0.00E+00 0.00E+00 0.00E+00 1.92E+04 l Rb-88 0.00E+00 1.18E-22 6.26E-23 0.00E+00 0.00E+00 0.00E+00 1.63E-33 ' Rb-89 0.00E+00 1.38E-26 9.73E-27 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sr-89 2.50E+04 0.00E+00 7.16E+02 0.00E+00 0.00E+00 0.00E+00 4.00E+03 Sr-90 6.23E+05 0.00E+00 1.53E+05 0.00E+00 0.00E&00 0.00E+00 1.80E+04 j l Sr-91 7.47E+01 0.00E+00 3.02E+00 0.00E+00 0.00E+00 0.00E+00 3.56E+02 ' Sr-92 3.32E-01 0.00E+00 1.43E-02 0.00E+00 0.00E+00 0.00E+00 6.57E+00 Y-90 5.04E-01 0.00E+00 1.35E-02 0.00E+00 0.00E+00 0.00E+00 5.34E+03 Y-91M 1. 31 E-11 0.00E+00 5.06E-13 0.00E+00 0.00E+00 0.00E+00 3.83E-11 Y-91 9.77E+00 0.00E+00 2.61E-01 0.00E+00 0.00E+00 0.00E+00 5.38E+03 Y-92 4.59E-04 0.00E+00 1.34E-05 0.00E+00 0.00E+00 0.00E+00 8.04E+00 Y-93 3.30E-02 0.00E+00 9.11E-04 0.00E+00 0.00E+00 0.00E+00 1. 05 E +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. 31 E +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 l
- Calculated using Equation (15). Site-related dose factors are presented as zero in this table when "no data" is reported for dose factors for specific
- radionuclides-organ combinations in Reference 3.
VEGP 00CM, REV 4 7/30/87 1.2-8 a_-_-_--____--________ _ - _ _ _ _ - _ _ _ - - _ - - - _ _ - - _ _ - - - - -
Table 1.2-3 (SHEET 2 0F 2) SITE-RELATE 0 INGESTION DOSE FACTnRS, Ai , (FOR FRESHWATER FISH AND DRINKING WATER CONSUMPTION)* (mrem /h per pCi/ml) Nuclide' Bone Liver T Body Thyroid Kidney Luno GI-LLI ! Ru-103 6.21E+00 'Ox00E+00 2.68E+00 0.00E+00 2.37E+01 0.00E+00 7.2SE+02 Ru-105 8. 81 E -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 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 Te-127 1.80E+01 6.46E+00 3.89E+00 1.33E+01 7.33E+01 0.00E+00 1.42E+03 Te-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 Te-131 M 9.58E+02 4.68E+02 3.90E+02 7.42E+02 4.74E+03 0.00E+00 4.65E+04 1 Te-131 5.82E-17 2.43E-17 1.84 E-17 4.79E-17 2.55E-16 0.00E+00 8. 24 E-18
- l 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+01 8.80E+00 1.89E+03 3.48E+01 0.00E+00 1.92E+01 I-131 l 1.73E+02 2.48E+02 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 1.70E-08 8.22E-07 7.54E-08 0.00E+00 4.13E-11 : 1-135 1.34E+00 3.51E+00 1.30E+00 ' 2.32E+02 5.64E+00 0.00E+00 3.97E+00 l Cs-134 2.98E+05 7.10E+05 5.80E+05 0.00E+00 2.30E+05 7.62E+04 1.24E+04 i Cs-136 2.97E+04 1.17E+05 8.44E+04 0.00E+00 6.52E+04 8.94E+03 1.33E+04 i 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. 87 E-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 l Ba-140 3.74E+02 4.69E-01 2.45E+01 0.00E+00 1.60E-01 2.69E-01 7.69E+02 8a-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 l l 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 { l 1.56E-07 7.11 E-08 1.77E-08 0.00E+00 0.00E+00 0.00E+00 5.19E-04 i Ce-141 1.15E-01 7.79E-02 8.84E-03 0.00E+00 3.62E-02 0.00E+00 2.98E+02 I Ce-143 8.65E-03 6.40E+00 7.08E-04 0.00E+00 2.82E-03 0.00E+00 2.39E+02 l Ce-144 6.22E+00' 2.60E+00 3.34E-01 0.00E+00 1.54E+00 0.00E+00 2.10E+03 I Pr-143 6.10E-01 2.45E-01 3.02E-02 0.00E+00 1.41E-01 0.00E+00 2.67E+03 Pr-144 1.37E-28 5.68E-29 6.95E-30 0.00E+00 3.20E-29 0.00E+00 1.97E-35 I Nd-147 4.11E-01 4.75E-01 2.84E-02 0.00E+00 2.78E-01 0.00E+00 2.28E+03 l W-187 1.4BE+02 1.24E+02 4.32E+01 0.00E+00 0.00E+00 0.00E+00 4.05E+04 Np-239 i 2.81E-02 2.76E-03 1.52E-03 0.00E+00 8.61E-03 0.00E+00 5.66E+02 l l l l l '
- Calculated Using Equation (15). Site-related dose factors are presented as zero in this table when "no data" is reported for dose factors for specific radionuclides-organ combinations in Reference 3.
l VEGP 00CM, REV 4 7/30/87 1.2-9 l l
~
3 y)- 1 7 .
.s 1.3 0094 1 P90]ECTIONS FOR LIQUID EFFLUENTS
'j s\ ,
, 3 p, *
,,1.3.19, Thir1.fone ppjt Dos,e Projections i
5, ,
,[ ,?
,\
]
I ? n In order to meet the requirements of Technical Specification [3.ll.l.3,+whicri { pertains to ' operation of the liquid radwaste treatment systems, dose j { j projectiotts muit be made at least once per 31. days, during perids,in which - t dischadje;of iTquid ef fluents containing radioactive ~ materials to- I unrestricted areas occurs or is expected. l [ .,, - l ,. \ l
~
l Pr6
,]jected31/4aydosestoindividuaisduetoliquidefffuentsmaybe etermined as follows: s ,[-
si g
<1 .
, i r L *
- F t; - !
4 - D [0 t h ? .I ! [3 tb(prj) =l Y CI ' (16)
\s ) x 3 ?). , ., k t t 7y s i
o(c) , lt Oo (prj) = t x 31 .?; (17) where: ,
' ']
i,, , 9 't s, s ,.4 s 2 N i) D = ine Culnult.tive total tddy cada for the elapsed portion 6fi sh tb(c) 5 . t the current quarter plus the releade under considitation. < S y i /
]
, / 'N '.
'h g t
,' ;' t
=
the number of days into the rur' 7 rent quarter, including the period oC the release under consideration. g , T , , 3
=
q\
"D (c) o thecumulativeorgandosesforspecificorgans,to-{the s i 1 elapsed portion._of the current quarter plus the r~ifease*under consideration. \- '
t 4[ ( ,g 5 s
'N l g If operations 1 activities pl b,Nd 5 x during the enruing 31-dly peribd are-x expected to result in lie,did r31 eases which will; contribute a do;(e in
,$ addition to"the dose due to rodtine liquid eft?uents, this additional s
1 - dose contribution should be included ( in the ecuations as follows: tg s y e n VEGP ODCM, REJ'4v 7/30/87 1. 3-1 -
"\ , ,
fy '] k / A x, b V>> JA%
& w 3 .
. t ,
V
- M
.l w -_- - - - - - - - - - - - - - . -- --
1 D tb(prj ) = tb(c) x 31 + D PA
~
(18)
'O (c) l Do (prj) = x 31 +D PA l (19) l where D is the (
p .xpected dose due to the particular planned activity. j r l l 1.3.2 Dose Projections for Specific Releases j Dose projections may be performed for a particular release by performing a l 1 pre-release dose calculation assuming that the planned release will proceed I as anticipated. For individual dose projections due to liquid releases, I 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. O m VEGP ODCM, REV 4 7/30/87 1.3-2
l 1.4 DEFINITIONS OF LIQUID EFFLUENT TERMS l l Section Of I Term Definition Initial Use l A = the adjustment factor used in calculating monitor setpoints, which is the ratio of the assured uilution factor to the required dilution factor ! (unitiess). 1.1.1
~
A = the site-related ingestion dose commitment l factor for the total body or any organ for each ider.tified principal radionuclides listed in table l'.2-3 in mrem-m1 per h uci. 1.2 ADF = the assured dilution factor, which is the ratio of unit-specific assured dilution flowrate to anticipated effluent release rate (unitiess). 1.1.1.1 BF = the bioaccumulation factor for nuclide i, in fresh water fish, pCi/kg per pCi/1, from table 1.2-1. 1.2 BG = the background 1evel for the radioactivity monitor of interest. 1.1.1 > c = the base setpoint of the radioactivity monitor which measures the radioactivity concentration l in the effluent line prior to dilution end subsequent release. 1.1.1 C l ms = the actual setpoint for a radioactivity monitor, including adjustments for calibration factor I and background. 1.1.1 C = the ef fluent concentration of alpha-emitting 1 nuclides observed by gross alpha analysis of 1 the MONTHLY composite sample, in pCi/ml. 1.1.1 VEGP ObCM, REV 4 7/30/87 1. 4 -1 l h
l-Section Of Te rm Definition Initial Use C f
= the concentration of Fe-55 in liquid wastes as observed in the QUARTERLY composite sample, in pCi/ml. 1.1.1 l
C g
=
the effluent concentration of a gamma ' emitting nuclide, g, ob' served by gamma -ray. spectroscopy-of the waste sample, in pCi/ml. 1.1.1 C 4
=
the concentration of nuclide i as determined by the analysis of the waste sample, in pC1/ml. 1.1.1-C g = the average concentration of radionuclides 1, in undiluted liquid effluent during time period I at g for a release in pCi/ml. 1.2 C = gp the effluent concentration limit (Technical Specification 3.11.1.1) implementing 10 CFR 20 for the site, in pC1/ml. 1.1.1 l C,
=
the concentration of Sr-89 and Sr-90 in. liquid wastes ~as determined by analysis of the QUARTERLY composite sample, in pCi/ml. 1.1.1 l C = the measured concentration of H-3 in liquid I waste as determined by analysis of the MONTHLY composite sample, in pCi/ml. 1.1.1 CF = the calibration factor for a particular radioactivity monitor. 1.1.1 0 = T the cumulative dose commitment to the total body or any organ, t, from the liquid i effluents for the totd1 time period, in mrem. 1.2 VEGP 00CM, REV 4 7/30/87 1.4-2
i i I Section Of i Term Definition Initial-Use D = the additional dilution factor between vicinity ; of release point and drinking water location l (unitiess). 1.2 0F = a dose conversion factor for nuclide, i, for adults in organ, r, in mrem /pci found in table 1.2-2. 1.2 , f, = the flow as determined for the radiation monitor location in gpm. (General expression for equation 1.) 1.1.1 ! F = the dilution water flowrate as determined prior to the point at which the dilution stream discharges to the river, in gpm. ' (General expression for equation 1.) 1.1.1 1 l F = the flowrate of the dilution stream which can be assured during the time of release in gpm. This is also the setpoint for the dilution stream flevrate measurement device. 1.1.1 F g
= the unit-specific assured flowrate of the dilution stream used as the basis for setpoint I calculations, in gpm. 1.1.1 '
1
- l F = the near-field average dilution factor for C during any liquid effluent release h
(unitiess). 1.2 I i f = the anticipated effluent flowrate in gpm. 1.1.1 l
)
VEGP 00CM, REV 4 7/30/87 1.4-3 I i
i Section Of Term Definition Initial Use f = the maximum permissible effluent flowrate in 1.1.1 ! gpm. I 1 K = 1.14 x 10 , units conversion factor, which converts pCi to pC1, liters to m1, and hours 1 to year'. 1.2 l m = the number of liquid releases. 1.2
=
MPC) MPC g , MPC,, MPC , MPC f
, and MPC t which are 1
the limiting concentrations of the appropriate gamma-emmitting radionuclides, alpha-emitting radionuclides, strontium, iron and tritium, j respectively, from l 10 CFR, Part 20, Appendix B, Table II, Column 2. 1.1.1 RDF = the required dilution factor, which is the ratio of the dilution flowrate to the effluent stream flowrate(s) which would be required to assure that the limiting concentration of 10 CFR, Part 20, Appendix B, Table II, Column 2, i are met at the point of discharge to the unrestricted area (unitiess). 1.1.1 SF = the safety factor, which is a conservative factor 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 - I t f
= the transit time from release to receptor j (fish consumption), in hours. 1.2 l VEGP ODCM, REV 4 7/30/87 1.4-4 l i
l i \ l L --_-____.J
- .j 1
Section Of Te rm Definition' Initial Use-t = .the transit time from release to receptor f{ (drinking water consumption), in hours. 1.2 at = the duration of release under consideration,
- 1 in hours. 1.2 U
p
= 21 kg/ year, fish consumption (adult). 1.2 U = 730 liters / year, water consumption (adult). 1.2 i
Z = the applicable factor when additional. receiving - , water body dilution is considered (unitiess). 1.2 l A g
= the decay constant for radionuclides 1 (h-I). 1.2 l
l I i i 1 VEGP ODCM, REV 4 7/30/87 1.4-5
r-j 1.5 LIQUID WASTE PROCESSING SYSTEM AND LIQUID DISCHARGE PATHWAYS Figures 1.5-1 and 1.5-2 are schematics of the Liquid Waste Processing Systems for Unit 1 and Unit 2, respectively. The dotted lines indicate alternate pathways through which liquid wastes may be routed as appropriate. These alternate routes increase the operational flexibility of the liquid waste processing systems. 1 Figure 1.5-3 is a schematic of plant discharge pathways for liquids. I l 1 i i 0945n VEGP ODCM, REV 4 7/30/87 1.5-1
Laundry and Hot Floor - Shower Drain Tank Tank
~ (Shared)
Strainer , Strainer r-------H Filter l I g _. .. l --- + @
)[ Waste
~~~
____ .. Monitor e -( - - - -- - _ - C1. . .. g Tank Demin l
. I l
I Waste Monitor I I Tank Filter ,__,g I _ _ _ _._ _t_ _ _ ____ _, i 1 j i Waste Waste i
.j Monitor Monitor i i Tank Tank i
I
& m I m A Radioactivity Monitor O RE-0018 j[
_ From Unit 2 Waste ' f MonitorTank(s) l To Discharge
- Dotted lines indicate alternate routes for increased operational flexibility and/or additional processing.
To Unit 2 From/To Unit 2 To Orain Channel A From Drain Channel A vooTLa LIQUID WASTE PROCESSING SYSTEM Georg'a Power d 5'Jr**f,25"JM""ur (Unit 1) FIGURE 1.5-1
**** VEGP 00CM REV 4 7/30/87 1.5-2
l 1 I
\
l Q Floor i Drain
, Tank l
I I i
. Strainer r-------H I
l Filter I I i .--,@ X Waite
~~~*
-----+ Monitor Tank e -h - - - -- _ -- C1. . _. g Demin i
i I I Waste Monitor *I I Tank l Filter ' 1 ' i
~---@ 4
.---_-__t___. _ -._ _ __ _ _ _ g I
Waste I Waste Monitor 1 Monitor Tank i Tank 1 1 4 mm m 4 Radioactivity Monitor I RE-0018 o To Discharge (See Figure 1.5-1)
- Dotted lines indicate alternate routes for increased operational flexibility and/or additional processing.
From Unit 1 From/To Unit 1 To Drain Channel A From Drain Channel A voGrtE LIQUID WASTE PROCESSING SYSTEM GeorgiaPowerkh ELECTRIC GENEMArtNG PLANT unir i ano unir 2 (Unit 2) FIGURE 1.5-2 VEGP ODCM REV 4 7/30/87 1.5-3
1 l l ' Steam Turbine Nuclear Generator Building Service Blowdown Drain Cooling Water From Other Sumps
@ and Drains Control !
t Turbine
^
$ Building l Sump Plant Cooling From Other Sumps From Unit 2 Nuclear Oily Service Cooling Water Waste l Separator From Unit 2 Turbine i
Plant Cooling Tower I l Waste Water Liquid Retention Waste Basin Processing l System . From Unit 2 Waste l Water. Retention Basin From Unit 2 Blowdown : Cooling Tower Makeup Liquid Waste - Sump ban Une Processing From Flushing Ponds (During System Construction of Unit 2) , Ww I River
% l 1
Radioactivity Monitors: i RE0020 I RE0021 !
- RE0848 l l RE17646 l
l RE0018
*The Blowdown Sump is common to both units.
1 l l VOGTLE ' ELECTRIC GENERATING PLANT LIQUID DISCHARGE PATHWAYS Georgia Power Jt unit uNo unit 2 i FIGURE 1.5-3
**** VEGP ODCM REV 4 7/30/87 1.5-4 i
l 2.0 GASEOUS EFFLUENTS 1 l At Plant Vogtle there are five potential points where radioactivity is released to the atm'osphere in gaseous discharges. These five potential I l 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 i to secondary leak exists;'and the radwaste solidification building vent. l 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 l 1 plant vent. Certain components of the Gaseous Waste Processing System are l shared between the two units and releases from this system are through the j ) Unit 1 plant vent. Containment building releases are through the respective plant vents. j l l Gaseous releases from the turbine building vents and the radwaste solidification building vent are considered to be ground-;evel releases. Gaseous releases from the plant vents are considered to be mixed-mode releases as determined by the wake-split model. (Sea NOTE in subsection 2.1. 2. ) All five release points are considered to be continuous releases. In the absence of confirmed primary to secondary leak (s), the turbine building vents are not release points. Gaseous effluent monitor setpoints are required only for noble gas monitors j serving the five release points. Methodology for calculating noble gas monitor setpoir.ts is presented in subsection 2.1. Although setpoint calculations are not required for radioiodine and particulate monitors, the methodology for assuring the potential organ dose rates due to radioiodines, tritium, and particulate in gaseous releases from the site do not exceed the limits of Technical Specification 3.11.2.l(b) is presented in the NOTE in subsection 2.2.1.2. VEGP 00CM, REV 4 7/30/87 2.0-1
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 thebasic'setpointvalue,c,,andtheactualmonitorsetpoint,cjp. Throughout.these subsections the 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 I alarm setpoints should be established at a level below the high alarm setpoint to give appropriate warning prior to reaching the high alarm setpoint. l If no release is planned for a particular pathway, or if there is' no I detectable activity in the planned release, the monitor setpoint should be l established as close to background as practical to prevent spurious alarms ! and yet alarm should an inadvertent release occur. The monitor setpoint determined in this maiiner must be less than the setpoint value calculated in accordance with subsection 2.1.1 or 2.1.2, assuming Kr-88 as the radionuclides l being released. 1 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 setpoint recalculated, if releases via the pathway under consideration are to continue. VEGP ODCM, REV 4 7/30/87 2.1 -1
where n.is the number of simultaneous final' gaseous release points. - For a more exact. determination of allocation factors, see subsection 2.1.5.
.t I
D = the dose rate limit.to the total body of an individual which TB is 500 mrem / year. ; l R = the relationship between monitor.. response and the dose rate to-the total body for the conditions of the release under consideration. l R t = C,+ ((X/Q)G i Oig} (} where: C = the monitor response of a noble gas monitor corresponding to the grab sample radionuclides concentrations taken in accordance with Technical Specification table 4.11-2. (See subsection 2.1.4 for further discussion of monitor response.) (X/Q)g = the highest annual average relative concentration at the site boundary. (If desired, the annual average relative I concentration at the site boundary for the particular release point may be used.) The release points addressed in this subsection are ground-level releases. i (X/Q)G = 6.83-x 10-5 s/m in the ENE sector. K = the total body dose factor due to gamma emissions from 3 radionuclides i (mrem / year per pC1/m ) f rom table 2.1-1. i l l Q ig
= the rate of release of noble gas radionuclides 1 (pCi/s) .from the vent release pathway under consideration (ground level)' ,
I VEGP ODCM, REV 4 7/30/87 2.1-3 __ ____ - _ -. _ _ ___ _ _ - . D
i i which is.the product of X g and F , where X is the concentration of radionuclides i for the particular release: and F is the maximum expected release flowrate for this release point. (X in pCi/ml and F in ml/s.) 4 D ss
= the dose rate limit to the skin of the body of an individual in an unrestricted-area which is 3000 mrem / year.
R = the relationship between monitor ' response and the dose rate to the skin for the conditions of the release under consideration. I
=
R 3 C , + ((X/Q)G Il + I*I H i) Oig) I4) where: ! L g
=
the skin dose factor due to beta emissions from radionuclides i 3 (mrem / year per pCi/m ) f rom table 2.1-1. l l 1.1 = the mrem skin dose per mrad air dose. I M g
= the air dose factor due to gamma emissions from radionuclides 3
i (mrad / year per pCi/m ) from table 2.1-1. I 4 2.1.2 Unit 1 Plant Vent and Unit 2 plant Vent Monitors: RE12442C (Unit 1) and RE12442C (Unit 2) u Gaseous releases from the plant vent (s) are regarded as mixed-mode releases t 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 ineteorological 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.) l VEGP 00CM, REV 4 7/30/87 2.1-4
However, since setpoints for plant vent monitors must be established 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. 1 NOTE: Default recirculation values are utilized for determination of dispersion and deposition factors for calculation of the offsite , effect of gaseous effluents. 1 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 i tower wake effects. 1 The setpoint calculation methodology presented in subsection 2.1.1 applies to these monitors with the. exception that O gg must be replaced with Q$ , where 0 5 is defined as follows: Qg = the rate of release of noble gas radionuclides 1 (pCi/s) from ) the plant vent release pathway under consideration (mixed mode), which is the product of X h and F , where X g is the concentration of radionuclides i for the particular release and F is the maximum expected release flowrate for this release point. (X in pCi/ml and F in ml/s.) l h 2.1.3 Gaseous Waste Processing System Discharge and Reactor Containment Purge l Monitors: ARE0014, RE-2565C (Unit 1) and RE-2565C (Unit 2) The Gaseous Waste Processing System discharges to the Unit 1 plant vent, Unit 1 containment purge 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 final effluent monitors as discussed in subsection I VEGP 00CM, REV 4 7/30/87 2.1 -5 d
2.1. 2 . However, due to the poten~tial significance of releases from these sources, the setpoint methodology is presented for the system effluent monitors also. The system monitors have the control logic to terminate the release at alarm trip point. The final monitors have no trip logic. : 1 Sampling and analyses are completed and monitor setpoints determined prior to release. These setpoints must take into account simultaneous release l 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. Downstream monitors must also take into consideration the combinations of source terms for the particular release pathway. 2.1. 3.1 Gaseous Waste Processina System Monitor: ARE-0014 i The Gaseous Waste Processing System discharges through the Unit 1 plant vent; therefore, the Gaseous Waste Processing System effluent monitor is not the j 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 Warte l Processing System, and the trip logic is associated with this manitor, the ) setpoint methodology for this monitor is presented. i The methodology presented in subsection 2.1.2 applies-to this monitor with the following five exceptions: Exception 1: 1 R t= r t = C, t W /Q)g fK$q) g (5) VEGP ODCM, REV 4 7/30/87 2.1 -6
l l j j Exception 2: ) C,
'= the. monitor response of the Gaseous Waste Processing System monitor for radionuclides concentrations to be discharged (sample taken and analyzed prior to discharge). (See subsection 2.1.4 for.further discussion of monitor response.) l Exception 3.
-l q$
= the rate of release of noble gas radionuclides 1 (pCi/s) from the Gaseous Waste Processing System, determined by multiplying j i
the expected release rate by the concentration of radionuclides ~
]
i. Exception 4: I R= r = C , + ( p/Q)g fR$ + 1.1M j)q$) (6) 3 s ] l Exception 5: AG = a selected allocation factor value which must be less than the allocation factor for the monitor serving the final release-point, Unit 1 plant vent. 4 I When releases are to be made from the Gaseous Waste Processing System, it will be necessary to redetermine the setpoint for the Unit 1 plant vent monitor (RE-12442C), which is downstream from the Gaseous Waste Processing System effluent monitor (ARE-0014). 4 i Redetermination of this setpoint is accomplished by applying the methodology of subsection 2.1.2 with the.following two exceptions: f Exception 1: i 4 A new source term, (Qg)GP, is determined which includes the routine Unit 1 plant vent source term Q$ ,(based on sample results from Technical VEGP 00CM, REV 4 7/30/87 2.1-7
] !
I l l Specification table 4.11-2) combined with the Gaseous Waste Processing System source term for the tank planned for release, q$, as follows: (0 im GP
- im + Ni (7)
Exception 2: 1
.y C, = ' the monitor. response corresponding to the concentration resulting from the combined release; this concentration value is obtainedbydividingf(Q,)gp $
by the combined flowrate. (ml/s) through the plant vent. (See subsection 2.1.4 for further discussion of monitor response.) 2.1. 3. 2 Reactor Containment Purge I 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: ' Rt=rt = C, + ((X/Q)g fK$ q$) (8) Exception 2: C, = the monitor response of the containment purge monitor for radionuclides concentrations to be discharged (sample taken and ! VEGP ODCM, REV 4 7/30/87 2.1 -8 l
l I i analyzed prior to discharge). (See subsection 2.1.4 for further discussion of monitor response.) Exception 3: I I q q
= the rate of release of noble gas radionuclides i' (pCi/s) from containment purge, determined by multiplying the expected l release rate by the concentration of radionuclides i.
Exception 4: R 3
=r s = C, + (( U Q)g f (L$ + 1.lM$ ) qq) -
(9)
. 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-124420) which is downstream f rom the containment purge monitor (RE-2565C). Redetermination of t'his setpoint is accomplished by applying the methodology . l of subsection 2.l.2 with the following two exceptions: Exception 1: A new source term, (Qg)CP, is determined which includes the routine respective plant vent source term Qg (based on sample results from ! Technical Specification table 4.11- 2) combined with the containment purge i source term for the unit containment planned for release, q , as follows: (0im)CP " 0im + Ni (10) VEGP ODCM, REV 4 7/30/87, 2.1 -9 l
Exception 2: 4 C = the monitor response corresponding to the concentration resulting from the combined release; this concentration value isobtainedbydividingf(Og)CP by the combined flowrate (ml/s) through the plant vent. (See subsection 2.1.4 for further discussion of monitor response.) I 2.1.4 Consideration of Monitor Response and Background in Establishing Gaseous Effluent Monitor Setooints I The calculated monitor setpoint, c,, establishes the base value for the monitor setpoint. The monitor setpoint calculation includes the monitor response term, C,. The monitor response is the net monitor reading 1 corresponding to the measured concentration of the particular noble gas I l 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 also be determined by multiplying the measured noble gas concentration by the { calibration factor for the particular 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 flowrate and radionuclides-specific concentrations determined for the release under consideration. If any monitor adjustments are to be made which affect monitor response to radionuclides 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 setpoint calculation for a particular monitor. The actual monitor setpoint, csp, must include the calculated basic setpoint, c,, plus monitor background, BG. Contributions to background radiation levels may include ambient background, plant environmental background at monitor locations when plant is in shutdown status, plant environmental background at monitor location when plant is at power, and internal background of monitor due to contamination of sample chamber. t Background levels must be controlled such that radioactivity levels in the VEGP ODCM, REV 4 7/30/87 2.1-10
f effluent stream being monitored can be accurately assessed at or below the calculated setpoint value. l l l 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 solidification 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. l There are three methods by which allocation factors may be determined:
- 1. The allocation factor for a particular release pathway may be l
l administrative 1y selected based on an estimate of the fraction of j l the total dose rate (from all simultaneous releases) which is { contributed by the particular release pathway. l
- 2. The allocation factor may be calculated using the expression l
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:
l VEGP ODCM, REV 4 7/30/87 2.1-11
l l For Unit 1 turbine building vent, Unit 2 turbine building vent, and radwaste solidification building vent (ground-level releases): 1 G r (12) AG = (X/0)G n Ki (Oig}ng + (X'0)M n Ki (Oim)nm l For Unit 1 plant vent and Unit 2 plant vent (mixed mode releases): ' M m (13) AG = (X/Q)G n i (O ig Ing + (X/Q)M n K i (0 $,)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 l 1 particular discharge pathway for which an allocation factor is being determined. l l I VEGP 00CM, REV 4 7/30/87 2.1-12
i I TABLE 2.1-1 DOSE FACTORS FOR EXPOSURE TO A SEMI-INFINITE CLOUD OF NOBLE. GASES
- l Gamma Beta- Gamma Beta Nuclide -Bodv***(K) -Skin ***(L) -Air **(M) -Air **(N) I
-Kr-83m 7.56E-02 1.93E+01 2.88E+02 I Kr-85m 1.17E+03- 1.46E+03 1.23E+03 1.97E+03' -
Kr-85 1.61E+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 1.86E+03 1.92E+03 2.46E+03
, i Xe-137 1.42E+03 1.22E+04 1. 51 E+03 1.27E+04 Xe-138 8.83E+03 4.13E+03 9. 21 E+03 4.75E+03 l l
Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03 l t i
- Values taken from Reference 3, Table B-1.
'i
** mrad-m pC1-year
*** mrem-m 3 j pCi-year i VEGP ODCM, REV 4 7/30/87 2.1-13 I
i
a TABLE 2.1-2 GASEOUS RELEASE POINTS FLOW RATES Release Point Flow Rates ft / min ml/s Plant Vent (Unit 1). 1.5E05 7.08E07' Plant. Vent (Unit 2) 9.0E04' 4.25E07-Radwaste Solidification Building Vent 3.4E04' 1.60E07 Turbine Building Vent (Unit 2; Condenser 9.0E02 4.25E05 Air. Ejector and Steam Packing Exhaust) Turbine Building Vent (Unit 2; Condenser 9.0E02 4.25E05 Air Ejector and Steam Packing Exhaust) Ref erence 5, Tables 11.5.2-1 and 11.5.5-1. i / VEGP 00CM, REV 4 7/30/87 2.1-14 a ____---_______:_______________-__. _ _ - . - _
1 j 2.2 GASE0US EFFLUENT DOSE RATE AND DOSE CALCULATIONS 1 2.2.1 Dose Rates at or beyond Site Boundary 1 1 2.2.1.1 Dose Rates Due to Noble Gases 4 For the purpose of implementing Technical Specification 3.ll.2.1(a), the dose rate in areas at or beyond the site boundary due to noble gases shall be calculated as follows: D = the total body dose rate at time of release (mrem / year). k
=
(X/0)G n Ki IOig)ng * ( #0)M n Ki IOim)nm II4) D5 = the skin dose rate at time of release (mrem / year). l
+
(X/0)G n (li + l'IM )(0$g)ng i X/0)M n (l i + l'IM i)(0 ,)nm (15) Where ng is the number of simultaneous ground-level vent releases and nm is the number of simultaneous mixed-mode vent releases. Other terms were I defined previously in subsection 2.1. . l 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 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.) VEGP ODCM, REV 4 7/30/87 2.2-1
I o j
- 2. 2.1. 2 Dose Rates Due to I-131, I-133, Tritium, and Particulate f For the purpose of implementing Technical Specification 3.11.2.1(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:
l 0 O
= the organ dose rate at time of release (mrem / year). .
I
= +
l . (X/0)G ng' P
$g (Qjg)ng (X/Q)H n P,(Qj,)nm 4
(16) i i where: - - - - l nm and ng = defined previously in subsection 2.2.1.1. (X/Q)G
= defined previously in subsection 2.1.1.
(X/Q)g = defined previously in subsection 2.1.2. l Qjg - the release rate (uci/s) of I-131, I-133, tritium, and particulate from Unit 1 turbine building vent; Unit 2 turbine building vent; and radwaste solidification building vent, which are ground-level releases. i Qim - the release rate (uti/s) of I-131, I-133, tritium, and particulate from Unit 1 plant vent and Unit 2 plant vent, which are mixed-mode releases. P g = the organ dose parameter for organ o and radionuclides i, 3 (mrem / year per uCi/m ) for inhalation determined as , follows:
=
P g K'(BR) DF g VEGP ODCM, REV 4 7/30/87 2.2-2
1 wherg- , 6 X'? = the constant of unit conversion, 10 Ci/pci. BR = the breathing rate for child age group; 3700 m /3 year from table 2.2-10. OF g = thz inhalation pathway dose factor for child age group for
. orgen o and radionuclides 1, f rom table 2.2-2.
NOTE: In order to ensure that potential dose rates (pre-release) to an organ due to I-131 I-133, tritium, and. particulate in-simultaneous gaseous releases from the site do not exceed 1500 ' mrem / year as specified in Technical Specification 3.11.2.1(b), the potential organ dose rate 0 must be limited as follows: 0 + ( AG)(SF) 51500 mrem / year ()g) 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.
\'
l 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.) l l
. 2.2.2.1 Air Ooses at or Beyond the Site Boundary l
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: 0 = the air dose due to gamma emissions from noble gas l radionuclides (mrad) VEGP ODCM, REV 4 7/30/87 2.2 j
,. y
- 6. p. ,
' 3 ..
- m 7 ma--- ,
,. r s - a
" , *( _
V t
+
w l , [,, k ', L R. v
, ; -) *
.; s. -
3.17 x 10 .a
~ -
s = (X/Q)g*g. $ Mg U $g + (X/Q)g g$ HQ, 44 (19) - T. where: ,<
=g. g s ..
+
- o. , 3 y
-8 V
- 3.17 x 10 3 thhiraction of one year per one becond.
v 't '. \( , b Q ig v = the cumulative release of noble gas radionuclides i over 1 the Seriod of interest (uC1).from the vent release (grodd level)'uNder consideration.
? , ,
~
O Q im u ci.nulative release-of noble gas radionuclides liover the a ,
% period >cf Tinterest (yci) from the vent releast (mixed
~
( \ as %, [~ \'?' " mods) under! consideration. N g <
,, s. b,. -
.t i,
\$f I'( = '
'inedpreviously,insubsection2.1.1.
L. , .t ,s
'()
) / ,
'Q '
f T' t? , f, (X/Q)g = der' red previously in subsection 2.1.1. I t (X/Q)g = 6.83 x 10-5 s/m in the ENE sector. s
=
D beta the air dose due to beta emissions from noble gat- ! radionuclides (;nrad)'
,e N l
it l < !
~0
}h .
- 3.17 x 10 (X/Q)g fNg5$g + 6 '
(20) (X/Qh f > l _ E r where: ti ,
=
the air dose factor due to beta enisdions from noble gas j [ j I, radionuclides 'i (mrad / year per pCi/m 3
), f rom table
/ ,, 2 .1 -1. 3
., l
,' i
{ VEGP'ODCM, REV 4 7/30/87 2.2-4
1 J 2.2.2.2 Dose to a Member of the Public at or Beyond the Site Boundary I Doses to a member of the public due to I-131, I-133, tritium, and radioactive j materials in particulate form, in gaseous releases, will be calculated for j the purpose of implementing Technical Specification 3.11.2.3 as follows: 1 (NOTE: The member of the public expected to receive the highest dose in the plant vicinity is referred to as the controlling (or critical) receptor. The ! dose received depen's d on the location, age group, and exposure pathways present. For Plant Vogtle, the controlling receptor (s) for which doses must be calculated, and the applicable exposure pathways, are presented in table ]
- 2. 2-12. )
= the dose to an organ j of an individual in age group a from D) radioiodines, tritium, and radionuclides in particulate form with half-lives greater than eight days (mrem).
i
= 3.17 X 10 -8 p R,$p)-(Wgp Djg +Wyp Qj,) 21) where:
~
3.17 x 10 = the fraction of one year per one second. l I pi = for all pathways and all isotopes. ! Wdp = the pathway-dependent relative dispersion or deposition at the location of the controlling receptor, associated with ground-level plant releases as follows: : (X/Q )gp = the annual average relative dispersion parameter for location of controlling (critical) receptor for ground-level plant releases. (X/Q')sp applies only to inhalation and all tritium pathways. (For all tritium pathways the Qj source term is limited to tritium.) See table 2.2-12 f or value. VEGP 0DCM, REV 4 .7/30/87 2.2-5 L _ _ - - - - - - ---- -
I (D/Q')gp = ne annual amage depos%n parae & W bcaWn M controlling (critical) receptor for ground-level vent 4 i releases. (D/Q')gp applies to all other pathways. See table 2.2-12 for value. Whp = the pathway-dependent relative dispersion or deposition at the location of the controlling receptor, associated with l plant vent releases, which are mixed mode as follows: ! (X/Q,g = the annual average relative dispersion parameter for location of controlling (critical) receptor for mixed-mode ' releases. (X/Q')gg applies only to inhalation and all l tritium pathways. (Foralltritiumpathways,theQi source term is limited to tritium.) See table 2.2-12 for ! values. (D/Q')gp = the annual average deposition parameter for the location of l controlling (critical) receptor for mixed-mode releases. l (D/Q')MP applies to all other pathways. See table 2.2-12 for values. l 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 1 plane, pathway and I-131, I-133, and particulate contributions to ingestion pathways. i 1 g
=
the cumulative release (vCi), from ground-level plant releases, of radionuclides i as required by Technical l Specification 3.11.2.3 over the period of interest. Dose determinations required by Technical Specification 3.11.2.3 l VEGP ODCM, REV 4 7/30/87 2.2-6 l b____1_ _ _
\
l i ! 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 I j absence of evidence that one unit contributes a greater j quantity of radioactivity than the other over the period of interest, release quantities say be apportioned equally between the two units. (For cose contributions due to ; I tritium f rom the ingestion patiwiays, the Qj term is j limited to tritium.) l 1 l Qlm = the cumulative release (pC1), from the mixed-mode plant ; vent releases, of radionuclides i as required by Technical Specification 3.11.2.3 over the period of interest. Dose I determinations required by Technical Specification 3.11.2.3 are on a per reactor basis; therefore, cumulative release quantities must also be unit-specific. (For dose i contributions due to tritium from the ingestion pathways, j thetermQjm is limited to tritium.) l R = the pathway-specific, individual age-specific, organ dose factor for radionuclides 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 i vegetation pathways. However, the dose pathways actually present at the controlling location, as well as the controlling individual age group, are determined through the l Land Use Census for the site vicinity and are presented in I
table 2.2-12. Pathway factors R are determined as aipj l 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. s VEGP 00CM, REV 4 7/30/87 2.2-7
1 Inhalation Pathway Factor i
=
R,$p) K'(BR),(DFA$3), mrem / year per pCi/m (22) where: K' = the constant of unit conversion 10 pCi/uci. (BR), = the breathing rate for a particular age group in m / year f rom table 2.2-10. DFA = the inhalation dose factor foi receptor age group a, organ j, and for radionuclides i, in mrem /pCi f rom tables 2.2-1 through 2.2-4. Ground-Plane Pathway Factor i
~
=
R,$p) K'K" (SHF)(DFG$3) ((1-e i )/X4) (23) 1 (m mrem / year per pCi/s). j where: K' = the constant of unit conversion, 10 pCi/pCi. K" = the constant of unit conversion, 8760 h/ year. ; J SHF = the shielding factor, 0.7 (dimensionless), i DFG = the ground plane dose conversion factor for radionuclides i q ) (same for all age groups and specific organs are assumed to receive the same dose as the total body) (mrem /h per pCi/m ) table 2.2-9.
~
l 1 4
= the decay constant for radionuclides i, in s .
t = the exposure time, 4.73 x 108 s (15 years). VEGP ODCM, REV 4 7/30/87 2.2-8 {
' Vegetation Pathway Factor R,9 ) = Cy {h + 1 )(DR$3), hat t* + * ( }
as g
~(m mrem / year per pCi/s) where:
K' = a constant of. unit conversion, 10 pCi/pci. . r = the fraction of deposited activity retained on vegetation (1.0 for radioiodines; 0.2 for particulate). I U = the consumption rate of. fresh leafy vegetation by the receptor in age group a, in kg/ year. (See table 2.2-10.) U = the consumption rate of stored vegetation by the receptor in age group a, in kg/ year. (See table 2.2-10.) f g
=
the fraction of the annual intake of fresh leafy vegetation grown locally. f g
=
the fraction of the annual intake of stored vegetation grown locally.. t = the average time between harvest of leafy vegetation and its consumption in s, (8.6 x 104 ). l t g = the average time between harvest of stored vegetation and its consumption in s, (5.18 x 106 ), Y y
=
the vegetation areal density, in kg/m . (DFL ) = the organ ingestion dose factor for the ith
, radionuclides for the receptor in age group a, in mrem /pCi-from tables 2.2-5 through 2.2-8.
l VEGP 00CM, REV 4 7/30/87 2.2-9 I i l
i
~
1 4
= the decay constant for the ith radionuclides, in s .
A = the decay constant for remova af activity on leaf and W 4 j plant surfaces by weathering, 5.73 x 10~7 s
-I (corresponding to a 14-day half-life).
For tritium in vegetation, the vegetation pathway factor is a special ! case due to the fact that the concentration of tritium in vegetation is l i based on airborne concentration rather than deposition: i R aipj
=
K'K'"(U at f t +U asf g) (DFLij)a (0.75(0.5/H)) (25) (mrem / year per pCi/m ) l l where: i l K'" = a constant of unit conversion,10 gm/kg. l H = the absolute humidity of the atmosphere, in gm/m3 . 0.75 = the fraction of total vegetation that is water. 0.5 = the ratio of the specific activity of the vegetation water to the atmospheric water. Other parameters and values are given above. Grass-Cow-Milk Pathway Factor Op (U "f D f R aipj = K,K4+A aD)F m (r)(DFL ij)a Y 5 + (1-f D5 f )e- i hm" Y e~ if t (26) _p 3 (m mrem / year per pCi/s) VEGP ODCM, REV 4 7/30/87 2.2-10
where: K' = a constant of unit conversion,10 pCi/uci. ! l 4 Q F
= the cow's consumption rate, in kg/ day (wet weight),
i U ap
= the receptor's milk consumption rate for age group a, in l
liters / year f rom table 2.2-10. 1 1 1 Y p
= the agricultural productivity by unit area of pasture feed i 2 I grass, in kg/m . '
l Y s
= the agricultural productivity by unit area of stored feed, l in kg/m2, j F = the stable element transfer coefficients, in days / liter.
(See table 2.2-11.) r = the fraction of deposited activity retained on feed grass (1.0 for radioiodines; 0.2 for particulate). (DFLg)
= the organ ingestion' dose factor for tne ith radionuclides for the receptor in age group a, in mrem /pCi from tables 2.2-5 through 2.2-8. l
}
i A q
= the decay constant for the ith radionuclides, in s' .
X = the decay constant for removal of activity on leof and j plant surfaces by weathering, 5.73 x 10 -7 s -I (corresponding to a 14-day half-life). 1 t f
=
the transport time from pasture to cow, to milk, to receptor, in s (1.73 x 10 5), i t g = the transport time from pasture, to harvest, to cow, to milk, to receptor, in s (7.78 x 10 6), ; 1 i
)
VEGP ODCM, REV 4 7/30/87 2.2-11
l i f = the fraction of the year that the cow is on pasture (dimensionless). f = the fraction of the cow feed that is pasture grass while the cow is on pasture (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:
=
R,$p) K'K'"F,Qpu,p(DFL$3),(0.75(0.5/H)) (27) (mrem / year per pCi/m ) K'" = a constant of unit conversion,10 gm/kg. H = the absolute humidity of the atmosphere, in gm/m . 0.75 .= the f raction of total feed that is water. 0.5 = the ratio of the specific activity of the feed grass water-to the atmospheric water. Other parameters and values as previously defined. Grass-Goat-Milk Pathway Factor
~
QF (U ff D5 (1-fD5f )e i hm Raipj = K, A$+1 ao)F m (r)(DFL ij)a Y.
+
Y e-Aif t (28) p 3 (m mrem / year per pCi/s) where: l K' = a constant of unit conversion, 10 pCi/pci. VEGP ODCM, REV 4 7/30/87 2.2-12
Qp = the goat's consumption rate, in kg/ day (wet weight). U ap
= the receptor's milk' consumption rate for age group a, in.
liters / year from table 2.2-10. l Y = the agricultural productivity by unit area of pasture feed P grass, in kg/m 2. i Y s
= the agricultural productivity' by unit area of stored feed, in kg/m2, i
l F, = the stable element transfer coefficients, in days / liter. (See table 2.2-11.) l r = the fraction of. deposited ~ activity retained _on feed grass (1.0 for radiciodines: 0.2 for particulate). (DFL ) = the organ ingestion dose factor for the ith radionuclides for the receptor in age group a, in mrem /pCi from tables 2.2-5 through 2.2-8. K 4
= the decay constant for the ith radionuclides, in s~ .
1 = the decay constant for remova1 of activity on leaf and plant surfaces by weathering, 5.73 x 10 ~I s -I (corresponding to a 14-day half-life), t g
=
the transport time f rom pasture to goat, to milk, to receptor, in s (1.73 x 10 ),5 t g
=
the transport time from pasture, to. harvest, to goat, to milk, to receptor, in s (7.78 x 106 ), f- = the fraction of the year'that the goat is on pasture p (dimensionless). VEGP ODCM, REV 4 7/30/87 2.2-13 ____._______m.___ _ - _ - - -_
f, = the fraction of the goat feed that is pastu.re grass while the goat is'on pasture (dimensionless). I 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 j on a.irborne concentration rather than. disposition: R = K'K'"F,0pu,p(DFL$ )),(0.75(0.5/H)) (29) (mrem / year per pC1/m ) l where: ) 1 I K'" =~ a constant of unit conversion,10 gm/kg. I H = the absolute humidity of the atmosphere, in gm/m . i 0.75 = the f raction of total feed that is water. 0.5 = the ratio of the specific activity of the feed grass water ! to the atmospheric water. l Other parameters and values are given above. Gra s s-Cow-Meat-Pathwa y-Fa ctor _ i QF (U ff D s ,(1-f Ds f )e" i hm - Raipj = K, K j +aD)1 fF (r)(DFL ij)a Y Y e-Aiyt (30) l p 3 (m mrem / year per pCi/s) where: K' = a constant of unit conversion, 10 pCi/uCi. l Qp = the. cow's consumption rate, in kg/ day (wet weight). VEGP ODCM, REV 4 7/30/87 2.2-14 i
-i
U p
= the receptor's mest consumption rate for age group a, .in kg/ year f rom table 2.2-10.
Y = the agricultural productivity by unit area of or.sture feed P grass, in kg/m2. Y s
= the agricultural productivity by unit area of stored feed, in kg/m2, F
f
= the stable element transfer coefficients, in days /kg.
(See table 2.2-11.) r = the fraction of deposited activity retained on feed grass (1.0 for radiciodines; 0.2 for particulate). (DFLg ),
= the organ ingestion dose factor for the-ith radionuclides for the receptor in age group a, in mrem /pCi from tables 2.2-5 through 2.2-8.
~
A g
= the decay constant for.the ith radionuclides, in s .
A = the decay constant for removal of activity on leaf and plant surfaces by weathering, 5.73 x 10-7 s -I (corresponding to a 14-day half-life), i t f
=
the transport time from pasture to cow, to meat, to receptor, in s (1.73 x 106), t g = the transport time from pasture, to harvest, to cow, to i meat, to receptor, in s (7.78 x 106 ), f p
=
the f raction of the year that the cow is on pasture (dimensionless). f 3
=
the fraction,of the cow feed that'is pasture grass while the cow is on pasture (dimensionless). VEGP ODCM, REV 4 7/30/87 2.2-15 L_______- _ ______ ___________________-___ _ - _ _ _ _ . ._ . - - - _
For tritium in meat. the grass-cow-meat pathway _ factor is a special case due to the fact that'the concentration of tritium in meat is based on airborne concentration rather than deposition: '
=
R K'K'"Ffp Q U (DFLg),(0.75(0.5/H)) (31) (mrem / year per pCi/m ) l where: K'" = a constant of unit conversion,10 gm/kg. l H = the absolute humidity of the atmosphere, in gm/m . 1 0.75 = the f raction of total feed that is water. l 0.5 = the ratio of the specific activity of the feed grass water to the atmospheric water. (, l Other parameters and values'are given above, i 1 2.2.2.3 Dose Calculations to Support Other Technical Specifications ~j In the event radiological impact assessment becomes necessary to support I 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 (R ) for the receptor of interest. For the purpose of supporting Technical Specification 3.12.2, which pertains to the Annual Land Use Survey, it may become necessary to perform dose calculations in addition to those required by Technical Specifications 3.11.2.3. In the event that the Lard Use Survey reveals that exposure ( pathways have changed at previously identified locations, or if new locations l VEGP ODCM, REV 4 7/30/87 2.2-16
l are identified, it may become necessary to perform dose calculations at two or more locations to either confirm the previously identified controlling receptor or identify the new receptor which should be designated as the controlling receptor. The necessary dose calculations may be performed using the equations presented in subsection 2.2.2.2 substituting the appropriate pathway dose factors (R ) and the appropriate meteorological (dispersion and deposition) parameters for the receptor (s) and location (s) of interest. I Annual average meteorological paramaters may be used for these calculations. . I 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. I I I Nb"00CM,REV4 7/10/87 2.2-17
TABLE 2.2-1 (SHEET.1 0F 3) INHALATION DOSE FACTORS FOR INFANT * (mrem per pci inhaled) 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 l P-32 1.45E-03 8.03E-05 5.53E-05 No Data No Data No Data 1.15E-05 C r-51 No Data No Data 6.39E-08 4.11E-08 9.45E-09 9.17E-06 2.55E-07 ) 3 Mn-54 No Data 1.81E-05 3.56E-06 No Data 3.56E-06 7.14E-04 5.04E-06 l Mn-56 No Data 1.10E-09 1. 58 E-10 No Data 7.86E-10 8.95E-06 5.12E-05 l Fe-55 1.41E-05 8.39E-06 2.38E-06 No Data No Data 6.21E-05 7.82E-07 , Fe-59 9.69E-06 1.68E-05 6.77E-06 No Data No Data 7.25E-04 1.77E-05 l Co-58 No Data 0.71E-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 l Ni-65 1.71E-09 2.03E-10 8.79E-11 No Data No Data 5.80E-06 3.58E-05 Cu-64 No Data 1.34E-09 5. 53 E-10 No Data 2.84E-09 6.64E-06 1.07E-05 Zn-65 1.38E-05 4.47E-05 2.22E-05 No Data 2.32E-05 4.62E-04 3.67E-05 In-69 3.85E-11 6.91 E-11 5.13E-12 No Data 2.87E-11 1.05E-06 9.44E-06 Br-83 No Data No Data 2.72E-07 No Data No Data No Data LT E-24 l 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 i Rb-86 No Data 1.36E-04 6.30E-05 No Data No Data No Data 2.17E-06 Rb-88 No Data 3.98E-07 2.05E-07 No Data No Data No Data 2.42E-07 Rb-89 No Data 2.29E-07 1.47E-07 No Data No Data No Data 4.87E-08
. Sr-89 2.84E-04 No Data 8.15E-06 No Data No Data 1.45E-03 4.57E-05 i 4
Sr-90 2.92E-02 No Data 1.85E-03 No Data No Data 8.03E-03 9.36E-05 f
\
Sr-91 6.83E-08 No Data 2.47E-09 No Data No Data 3.76E-05 5.24E-05 ! Sr-92 7.50E-09 No Data 2.79E-10 No Data No Data 1.70E-05 1.00E-04 j Y-90 2.35E-06 No Data 6.30E-08 No Data No Data 1.92E-04 7.43E-05 j Y-91M 2. 91 E-10 No Data 9.90E-12 No Data No Data 1.99E-06 1.68E-06 Y-91 4.20E-04 No Data 1.12E-05 No Data No Data 1.75E-03 5.02E-05 Y-92 1.17E-08 No Data 3. 29 E-10 No Data No Data 1.75E-05 9.04E-05 l l
- Ref erence 3, Table E-10.
VEGP ODCM, REV 4 7/30/87 2.2-18
TABLE 2.2-1 (SHEET 2 0F 3) INHALATION DOSE FACTORS FOR INFANT * (mrem per pci inhaled) Nuclide Bone Liver T Body Thyroid Kidney Luno GI-LLI Y-93 '1.07E-07 No Data 2.91E-09 No Data No Data 5.46E-05 1.19E-04 l Zr-95 8.24E-05 1.99E-05 1.45E-05 No Data 2.22E-05 1.25E-03 1.55E-05 l Zr-97 1.07E-07 1.83E-08 8.36E-09 No Data 1.85E-08 7.88E-05 1.00E-04 l Nb-95 1.12E-05 4.59E-06 2.70E-06 No Data 3.37E-06 3.42E-04 9.05E-06 i Mo-99 No Data 1.18E-07 2.31E-08 No Data 1.89E-07 9.63E-05 3.48E-05 i Tc-99M 9.98E-13 2.06E-12 2.66E-11 No Data 2.22E-11 5.79E-07 1.45E-06 1 l Tc-101 4. 65 E-14 5.88E-14 5.80E-13 No Data 6.99E-13 4.17E-07 6.03E-07 Ru-103 1.44E-06 No Data 4.85E-07 No Data 3.03E-06 3.94E-04 1.15E-05 Ru-105 8.74E-10 No Data 2. 93 E-10 No Data 6.42E-10 1.12E-05 3.46E-05
- Ru-106 6.20E-05 No Data 7.77E-06 No Data 7.61E-05 8.26E-03 1.17E-04 Ag-110M 7.13E-06 5.16E-06 3.57E-06 No Data 7.80E-06 2.62C-03 2.36E-05 Te-125M 3.40E-06 1.42E-06 4,70E-07 1.16E-06 No Data 3.19E-04 9.22E-06 Te-127M 1.19E-05 4.93E-06 1.48E-06 3.48E-06 2.68E-05 9.37E-04 1.95E-05 i Te-127 1.59E-09 6. 81 E-10 3.49E-10 1.32E-09 3.47E-09 7.39E-06 1.74E-05 l r- Te-129M 1.01E-05 4.35E-06 1.59E-06 3.91E-06 2.27E-05 1.20E-03 4.93E-05 Te-129 5.63E-11 2.48E-11 1.34E-11 4.82E-11 1. 25 E-10 2.14E-06 1.88E-05 Te-131M 7.62E-08 3.93E-08 2.59E-08 6.38E-08 1.89E-07 1.42E-04 8.51E-05 Te-131 1. 24 E-11 5.87E-12 3. 57 E-12 1.13E-11 2.85E-11 1.47E-06 5.87E-06 )
Te-132 2.66E-07 1.69E-07 1.26E-07 1.99E-07 7.39E-07 2.43E-04 3.15E-05 I-130 4.54E-06 9.91E-06 3.98E-06 1.14E-03 1.09E-05 No Data 1.42E-06 I-1 31 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. 21 E-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 C s-136 3.45E-05 9. 61 E-05 3.78E-05 No Data 4.03E-05 8.40E-06 1.02E-06 Cs-137 3.92E-04 4.37E-04 3.25E-05 No Data 1.23E-04 5.09E-05 9.53E-07 Cs-138 3.61E-07 5.58E-07 2.84E-07 No Data 2.93E-07 4.67E-08 6.26E-07 8a-139 1.06E-09 7. 03 E-13 3.07E-11 No Data 4.23E-13 4.25E-06 3.64E-05 Ba-140 4.00E-05 4.00E-08 2.07E-06 No Data 9.59E-09 1.14E-03 2.74E-05 Ba-141 1.12E-10 7. 70 E-14 3.55E-12 No Data 4. 64 E-14 2.12E-06 3.39E-06 8a-142 2.84E-11 2. 36 E-14 1.40E-12 No Data 1.36E-14 1.11E-06 4.95E-07
- Ref erence 3, Table E-10.
VEGP ODCM, REV 4 7/30/87 2.2-19
d lI
. l TABLE 2.2-1 (SHEET 3 0F 3) ]
1 INHALATION DOSE FACTORS FOR INFANT
- I (mrem per pci inhaled)
Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI i La-140 3. 61 E-07 1.43E-07 3.68E-08 No Data No Data 1.20E-04 6.06E-05 La-142 7. 36 E-10 2.69E-10 6.46E-11 No Data No Data 5.87E-06 4.25E-05 Ce-141 1.98E-05 1.19E-05 1.42E-06 No Data 3.75E-06 3.69E-04 1.54E-05 Ce-143 2.09E-07 1.38E-07 1.58E-08 No Data 4.03E-08 8.30E-05 3.55E-05 l Ce-144 2.28E-03 8.65E-04 1.26E-04 No Data 3.84E-04 7.03E-03 1.06E-04 Pr-143 1.00E-05 3.74E-06 4.99E-07 No Data 1.41E-06 3.09E-04 2.66E-05 Pr-144 3.42E-11 1. 32 E-11 1. 72 E-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 i W-187 9.26E-09 6.44E-09 2.23E-09 No Data No Data 2.83E-05 2.54E-05 l Np-239 2.65E-07 2.37E-08 1.34E-08 No Data 4.73E-08 4.25E-05 1.70E-05 l l l i l b l I l
- Reference 3, Table E-10.
( VEGP ODCM, REV 4 7/30/87 2.2-20
~
TABLE 2.2-2 (SHEET 1 0F 3) INHALATION DOSE FACTORS FOR CHILD * (mrem per pci inhaled) l Nuclide Bone Liver T Body Thyroid Kidney Luna GI-LLI H-3 No Data 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 4 C-14 9.70E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 Na-24 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 P-32 7.04E-04 3.09E-05 2.67E-05 No Data No Data No Data 1.14E-05 Cr-51 No Data No Data 4.17E-08 2.31E-08 6.57E-09 4.59E-06 2.93E-07 Mn-54 No Data 1.16E-05 2.57E-06 No Data 2.71E-06 4.26E-04 6.19E-06 Mn-56 No Data 4.48E-10 8.43E-11 No Data 4.52E-10 3.55E-06 3.33E-05 Fe-55 1.28E-05 6.80E-06 2.10E-06 No Data No Data 3.00E-05 7.75E-07 Fe-59 5.59E-06 9.04E-06 4.51E-06 No Data No Data 3.43E-04 1.91E-05 l 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 l Ni-65 8.08E-10 7.99E-11 4.44E-11 No Data No Data 2.21E-06 2.27E-05 Cu-64 No Data 5. 39 E-10 2.90E-10 No Data 1.63E-09 2.59E-06 9.92E-06 l Zn-65 1.15E-05 3.06E-05 1.90E-05 No Data 1.93E-05 2.69E-04 4.41E-06 1 Zn-69 1. 81 E-11 2. 61 E-11 2.41 E-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 j Rb-86 No Data .5.36E-05 3.09E-05 No Data No Data No Data 2.16E-06 i Rb-88 No Data 1.52E-07 9.90E-08 No Data No Data No Data 4.66E-09 l Rb-89 No Data 9.33E-08 7.83E-08 No Data No Data No Data 5.11 E-10 l Sr-89 1.62E-04 No Data 4.66E-06 No Data No Data 5.83E-04 4.52E-05 Sr-90 2.73E-02 No Data 1.74E-03 No Data No Data 3.99E-03 9.28E-05 Sr-91 3.28E-08 No Data 1.24E-09 No Data No Data 1.44E-05 4.70E-05 Sr-92 3.54E-09 No Data 1.42E-10 No Data No Data 6.49E-06 6.55E-05 Y-90 1.11E-06 No Data 2.99E-08 No Data No Data 7.07E-05 7.24E-05 Y-91M 1.37E-10 No Data 4.98E-12 No Data No Data 7.60E-07 4.64E-07 Y-91 2.47E-04 No Data 6.59E-06 No Data No Data 7.10E-04 4.97E-05 Y-92 5.50E-09 No Data 1. 57 E-10 No Data No Data 6.46E-06 6.46E-05
- Reference 3, Table E-9.
VEGP ODCM, REV 4 7/30/87 2.2-21
i l 1 1 TABLE 2.2-2 (SHEET 2 0F 3) l INHALATION DOSE FACTORS FOR CHILD * . (mrem per pci inhaled) I i l Nuclide Bone liver T Body Thyroid Kidney Luno GI-LLI I Y-93 5.04E-08 No Data 1.38E-09 No Data No Data 2.01E-05 1.05E-04 l Zr-95 5.13E-05 1.13E-05 1.00E-05 No Data 1.61E-05 6.03E-04 1.65E-05 l Zr-97 5.07E-08 7.34E-09 4.32E-09 No Data 1.05E-08 3.06E-05 9.49E-05 l Nb-95 6.35E-06 2.48E-06 1.77E-06 No Data 2.33E-06 1.66E-04 1.00E-05 i Mo-99 . No Data 4.66E-08 1.15E-08 No Data 1.06E-07 3.66E-05 3.42E-05 i Tc-99M 4. 81 E-13 9.41E-13 1. 56 E-11 No Data 1. 37 E-11 2.57E-07 1.30E-06 l l Tc-101 2.19E-14 2.30E-14 2. 91 E-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 i Ru-105 4.13E-10 No Data 1. 50 E-10 No Data 3. 63 E-10 4.30E-06 2.69E-05 i Ru-106 3.68E-05 No Data 4.57E-06 No Data 4.97E-05 3.87E-03 1.1.6 E-04 t Ag-110M 4.56E-06 3.08E-06 2.47E-06 No Data 5.74E-06 1.48E-03 2.71E-05 1 Te-125M 1.82E-06 6.29E-07 2.47E-07 5.20E-07 No Data 1.29E-04 9.13E-06 ) Te-127M 6.72E-06 2.31E-06 8.16E-07 1.64E-06 1.72E-05 4.00E-04 1.93E-05 Te-127 7.49E-10 2.57E-10 1.65E-10 5.30E-10 1.91E-09 2.71E-06 1.52E-05 l 7.- Te-129M 5.19E-06 1.85E-06 8.22E-07 1.71E-06 1.36E-05 4.76E-04 4.91E-05 Te-129 2. 64 E-11 9.45 E-12 6.44E-12 1.93E-11 6.94E-11 7.93E-07 6.89E-06 Te-131M 3.63E-08 1.60E-08 1.37E-08 2.64E-08 1.08E-07 5.56E-05 8.32E-05 Te-131 5. 87 E-12 2.28E-12 1. 78 E-12 4. 59 E-12 1. 59 E-11 5.55E-07 3.60E-07 i 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 Cs-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 Cs-138 1.71E-07 2.27E-07 1.50E-07 No Data 1.68E-07 1.84E-08 7.29E-08 Ba-139 4.98E-10 2. 66 E-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-11 2.95E-14 1.72E-12 No Data 2.56E-14 7.89E-07 7.44E-08 Ba-142 1. 35 E-11 9. 73 E-15 7.54E-13 No Data 7.87E-15 4.44E-07 7.41E-10
- Reference 3, Table E-9.
VEGP ODCM, REV 4 7/30/87 2.2-22 l
l i i TABLE 2.2-2 (SHEET 3 0F 3) l INHALATION DOSE FACTORS FOR CHILD * : (mrem per pci inhaled) l l Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI j La-140 1.74E-07 6.08E-08 2.04E-08 No Data No Data 4.94E-05 6.10E-05 l La-142 3.50E-10 1.11 E-10 3.49E-11 No Data No Data 2.35E-06 2.05E-05 l Ce-141 1.06E-05 5.28E-06 7.83E-07 No Data 2.31E-06 1.47E-04 1.53E-05 ] I Ce-143 9.89E-08 5.37E-08 7.77E-09 No Data 2.26E-08 3.12E-05 3.44E-05 Ce-144 1.83E-03 5.72E-04 9.77E-05 No Data 3.17 E-04 3.23E-03 1.05E-04 Pr-143 4.99E-06 1.50E-06 2.47E-07 No Data 8.11 E-07 1.17E-04 2.63E 05 I l Pr-144 1. 61 E-11 4.99E-12 8.10E-13 No Data 2.64E-12 4.23E-07 5.32E-08 ) Nd-147 2.92E-06 2.36E-06 1.84E-07 No Data 1.30E-06 8.87E-05 2.22E-05 W-187 4.41E-09 2.61E-09 1.17E-09 No Data No Data 1.11E-05 2.46E-05 l Np-239 1.26E-07 9.04E-09 6.35E-09 No Data 2.63E-08 1.57E-05 1.73E-05 l l 7 1 i
.ll l
l l
- Reference 3, Table E-9.
VEGP ODCM, REV 4 7/30/87 2.2-23 i
~ TABLE 2.2-3 (SHEET 1 0F 3) j 1
INHALATION DOSE FACTORS FOR TEEidGER* ! (mrce.' per pci inhaled) ; Nuclide 8one Liver T Body Thyroid Kidney Lung GI-LLI H-3 No Data 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 C-14 3.25E-06 6.09E-06 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 Na-24 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1. 72 E-0.6 1.72E-06 1.72E-06 ; 1 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 l 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 3.15 E-11 No Data 2. 24E-10 1.90E-06 7.18E-06 Fe-55 4.18E-06 2,98E-06 6.93E-07 No Data No Data 1.55E-05 7.99E-07 Fe-59 1.99E-06 4.62E-06 1.79E-06 No Data No Data 1.91E-04 2.23E Co-58 No Data 2.59E-07 3.47E-07 No Data No Data 1.68E-04 1.19E-05 , Co-60 No Data 1.89E-06 2.48E-06 No Data No Data 1.09E-03 3.24E-05 i Ni-63 '.25E-05 5.43E-06 2.47E-06 No Data No Data 3.84E-05 1.77E-06 ! Ni-65 2.73E-10 3.66E-11 1. 59 E-11 No Data No Data 1.17E-06 4.59E-06 i Cu-64 No Data 2. 54 E-10 1.06E-10 No Data 8.01 E-10 1.39E-06 7.68E-06 ; Zn-65 4.82E-06 1.67E-05 7.80E-06 No Data 1.08E-05 1.55E-04 5.83E-06 Zn-69 6.04E-12 1.15E-11 8.07 E-13 No Data 7. 53 E-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 6.82E-08 3.40E-08 No Data No Data No Data 3. 65 E-15 Rb-89 No Data 4.40E-08 2.91E-08 No Data No Data No Data 4. 22 E-17 Sr-89 5.43E-05 No Data 1.56E-06 No Data No Data 3.02E-04 4.64E-05 Sr-90 1.35E-02 No Data 8.35E-04 No Data No Data 2.06E-03 9.56E-05 Sr-91 1.10E-08 No Data 4. 39 E-10 No Data No Data 7.59E-06 3.24E-05 l 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 6.99E-05 Y-91M 4.63E-11 No Data 1.77E-12 No Data No Data 4.00E-07 3.77E-09 Y-91 8.26E-05 No Data 2. 21 E-06 No Data No Data 3.67E-04 5.11 E-05 Y-92 1.84E-09 No Data 5.36E-11 No Data No Data '3.35E-06 2.06E-05
- Reference 3. Table E-8.
VEGP ODCM, REV 4 7/30/87 2.2-24
TABLE 2.2-3 (SHEET 2 0F 3) INHALATION DOSE FACTORS FOR TEENAGER * (mrem per pci inhaled) Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLi ; Y-93 1.69E-08 No Data 4. 65 E-10 No lY.a No Data 1.04E-05 7,2dE-05 Zr-95 1.82E-05 5.73E-06 3.94E-06 No Data 8.42E-06 3.36E-04 1.06E-05 Zr-97 1.72E-08 3.40E-09 1.57E-09 to Data ".1'r-00 1.62E-O' ' 88E-05 l 1 Nb-95 2.32E-06 1.29E-06 7.08E-C No Data 1.25E-06 9.39E-05 1.21E-05 i Mo-99 No Data 2.11 E-08 4.03E-09 No Data 5.14E-08 1.92E-05 3.36E-05 1 Tc-99M 1. 73 E-13 4.83E-13 6.24E-12 No Data 7.20E-12 1.44E-07 7.66E-07 i Tc-101 7.40E-15 1.05 E-14 1. 03 E-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-11 No Data 1. 76 E-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-110M 1.73E-06 1.64E-06 9.99E-07 No Data 3.13E-06 8.44E-04 3.41E-05 Te-125M 6.10E-07 2.80E-07 8.34E-08 1.75E-07 No Data 6.70E-05 9.38E-06 Te-127M 2.25E-06 1.02E-06 2.73E-07 5.48E-07 8.17E-06 2.07E-04 1.99E-05 ! Te-127 2.51E-10 1.14E-10 5.52E-11 1.77E-10 9.10E-10 1.40E-06 1.01E-05 Te-129M l ( 1.74E-06 8.23E-07 2.81E-07 5.72E-07 6.49E-06 2.47E-04 5.06E-05 j Te-129 8. 87 E-12 4. 22 E-12 2. 20E-12 6.48E-12 3.32E-11 4.12E-07 2.02E-07 1.23E-08 Te-131 M 7. 51 E-09 5.03E-09 9.06E-09 5.49E-08 2.97E-05 7.76E-05 s Te-131 1.97E-12 1. 04 E-12 6.30E-13 1. 55 E-12 7.72E-12 2.92E-07 1.89E-09 l Te-132 4.50E-08 3.63E-08 2.74E-08 3.07E-08 2.44E-07 5.61E-05 5.79E-05 I-130 7.80E-07 2.24E-06 8.96E-07 1.86E-04 3.44E-06 No Data 1.14E-06 I I-131 4.43E-06 6.14E-06 3.30E-06 1.83E-03 1.05E-05 No Data 8.11E-07 l l I-132 1.99E-07 5.47E-07 1.97E-07 1. 8'9 E-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 ! I-134 1.11E-07 2.90E-07 1.05E-07 4.94E-06 4.58E-07 No Data 2.55E-09 I-135 4.62E-07 1.18E-06 4.36E-07 7.76E-05 1.86E-06 No Data 8.69E-07 ! Cs-134 6.28E-05 1.41E-04 6.86E-05 No Data 4.69E-05 1.83E-05 1.22E-06 i Cs-136 6.44E-06 2.42E-05 1.71E-05 No Data 1.38E-05 2.22E-06 1.36E-06 i 1 Cs-137 8.38E-05 1.06E-04 3.89E-05 No Data 3.80E-05 1.51E-05 1.06E-06 l Cs-138 5.82E-08 1.07E-07 5.58E-08 No Data 8.28E-08 9.84E-09 3.38E-11 l Ba-139 1.67E-10 1.18E-13 4. 87 E-12 No Data 1.11 E-13 8.08E-07 8.06E-07 J Ba-140 6.84E-06 8.38E-09 4.40E-07 No Data 2.85E-09 2.54E-04 2.86E-05 l Ba-141 1.78E-11 1.32E-14 5.93E-13 No Data 1. 23 E-14 4.11E-07 9. 33 E-14 Ba-142 4. 62 E-12 4.63E-15 2. 84 E-13 No Data 3.92E-15 2.39E-07 5.99E-20
- Reference 3, Table E-8.
VEGP ODCM, REV 4 7/30/87 2.2-25 3 I
TABLE 2.2-3 (SHEET 3 0F 3) INHALATION DOSE FACTORS'FOR TEENAGER * (mrem per pci inhaled) ' j Nuclide Bone Liver T Body Thyroid Kidney Luna GI-LLI La-140 5.99E-08 2.95E-08' 7.82E-09 No Data No Data 2.68E-05 6.09E-05 I La-142 1.20E-10 5.31E-11 1.32E-11 No Data No Data 1.27E-06 1.50E-06 Ce-141 3.55E-06 2.37E-06 2.71E No Data 1.11E-06 7.67E-05 1.58E-05 q Ce-143 3.32E-08 2.42E-08 2.70E-09 No Data 1.08E-08 1.63E-05 3.19E-05 Ce-144 6.11E-04 2.53E-04 3.28E-05 No Data 1. 51 E-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,. 22 E-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 (~~ l 1 1
- Reference 3, Table E-8.
I VEGP ODCM, REV 4 7/30/87 2.2-26 i
} TA8LE 2.2-4 (SHEET 1 0F 3) INHALATION DOSE FACTORS FOR ADULTS * , (mrem per pci inhaled) i i Nuclide Bone Liver T Body Thyroid Kidney Luno GI-LLI < l H-3 No Data 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 I C-14 2.27E-06 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 Na-24 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 P-32 1.65E-04 9.64E-06 6.26E-06 No Data No Data No Data 1.08E-05 Cr-51 No Data No Data 1.25E-08 7.44E-09 2.85E-09 1.80E-06 4.15E-07 ) Mn-54 No Data 4.95E-06 7.87E-07 No Data 1.23E-06 1.75E-04 9.67E-06 l Mn-56 No Data 1. 55E-10 2.29E-11 No Data 1.63E-10 1.18E-06 2.53E-06 i Fe-55 3.07E-06 2.12E-06 4.93E-07 'No Data No Data 9.01 E -06 7.54E-07 Fe-59 1.47E-06 3.47E-06 1.32E-06 No Data No Data 1.27E-04 2.35E-05 * { 1 i Co-58 No Data 1.98E-07 2.59E-07 No Data No Data 1.16E-04 1.33E-05 ! Co-60 No Data 1.44E-06 1.85E-06 No Data No Data 7.46E-04 3.56E-05 l Ni-63 5.40E-05 3.93E-06 1.81E-06 No Data No Data 2.23E-05 1.67E-06 l Ni-65 1.92 E-10 2.62E-11 1.14E-11 No Data No Data 7.00E-07 1.54E-06 Cu-64 No Data 1. 83 E-10 7.69E-11 No Data 5.78E-10 8.48E-07 t.12E-06
,. In-65 4.05E-06 1.29E-05 5.82E-06 No Data 8.62E-06 1.08E-04 6.68E-06 i
Zn-69 4.23E-12 8.14E-12 5.65E-13 No Data 5.27E-12 1.15E-07 2.04E-09 Br-83 No Data No Data 3.01E-08 No Data No Data No Data 2.90E-08 Br-84 No Data No Data 3.91E-08 No Data No Data No Data 2.05E-13 Br-85 No Data No Data 1.60E-09 No Data No Data No Data LT E-24 , Rb-86 No Data 1.69E-05 7.37E-06 No Data No Data No Data 2.08E-06 ' Rb-88 No Data 4.84E-08 2.41E-08 No Data No Data No Data 4.18E-19 Rb-89 No Data 3.20E-08 2.12E-08 No Data No Data No Data 1.16E-21 Sr-89 3.80E-05 No Data 1.09E-06 No Data No Data 1.75E-04 4.37E-05 Sr-90 1.24E-02 No Data 7.62E-04 No Data No Data 1.20E-03 9.02E-05 Sr-91 7.74E-09 No Data 3.13E-10 No Data No Data 4.56E-06 2.39E-05 Sr-92 8.43E-10 No Data 3.64E-11 No Data No Data 2.06E-06 5.38E-06 Y-90 2.61E-07 No Data 7.01E-09 No Data No Data 2.12E-05 6.32E-05 Y-91M 3.26E-11 No Data 1.27E-12 No Data No Data 2.40E-07 1.66E-10 Y-91 5.78E-05 No Data 1.55E-06 No Data No Data 2.13E-04 4.81E-05 Y-92 1.29E-09 No Data 3.77E-11 No Data No Data 1.96E-06 9.19E-0E
- Reference 3, Table E-7.
VEGP UDCM, REV 4 7/30/87 2.2-27
TABLE 2.2-4 (SHEET 2 0F 3) INHALATION DOSE FACTORS FOR ADULTS * (mrem per sci inhaled) - Nuclide Bone Liver T Body Thyroid Kidney Luno GI-LLI Y-93 1.18E-08 No Data 3. 26 E-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 . I 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. 51 E-08 2.87E-09 No Data 3.64E-08 1.14E-05 3.10E-05 ; Tc-99M 1.29E-13 3. 64 E-13 4. 63 E-12 No Data 5.52E-12 9.55E-08 5.20E-07 i Tc-101 5. 22 E-15 7.52E-15 7.38E-14 No Data 1. 35 E-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-11 No Data 3.89E-11 No Data 1. 27 E-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 i Ag-110M 1.35E-06 1.25E-06 7.43E-07 No Data 2.46E-06 5.79E-04 3.78E-05 I Te-125M 4.27E-07 1.98E-07 5.84E-08 1.31E-07 1.55E-06 3.92E-05 8.83E-06 Te-127M 1.58E-06 7.21E-07 1.96E-07 4.11E-07 5.72E-06 1.20E-04 1.87E-05 Te-127 1. 75 E-10 8.03E-11 3.87E-11 1. 32 E-10 6.37E-10 8.14E-07 7.17E-06 Te-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 Te-131M 8.74E-09 5.45E-09 3.63E-09 6.88E-09 3.86E-08 1.82E-05 6.95E-05 Te-131 1. 39 E-12 7.44E-13 4.49E-13 1.17E-12 5. 46 E-12 1.74E-07 2.30E-09 Te-132 3.25E-08 2.69E-08 2.02E-08 2.37E-08 1.82E-07 3.60E-05 6.37E-05 I-130 5.72E-07 1.68E-06 6.60E-07 1.42E-04 2.61E-06 No Data 9.61E-07 i 1-131 3.15E-06 4.47E-06 2.56E-06 1.49E-03 7.66E-06 No Data 7.85E-07 l 1-132 1.45E-07 4.07E-07 1.45E-07 1.43E-05 6.48E-07 No Data 5.08E-08 I-133 1.08E-06 1.85E-06 5.65E-07 2.69E-04 3.23E-06 No Data 1.11E-06 I-134 8.05E-08 2.16E-07 7.69E-08 3.73E-06 3.44E-07 No Data 1. 26 E-10 l I-135 3.35E-07 8.73E-07 3.21E-07 5.60E-05 1.39E-06 No Data 6.56E-07 l Cs-134 4.66E-05 1.06E-04 9.10E-05 No Data 3.59E-05 1.22E-05 1.30E-06 l C s-136 4.88E-06 1.83E-05 1.38E-05 No Data 1.07E-05 1.50E-06 1.46E-06 t Cs-137 5.98E-05 7.76E-05 5.35E-05 No Data 2.78E-05 9.40E-06 1.05E-06 Cs-138 4.14E-08 7.76E-08 4.05E-08 No Data 6.00E-08 6.07E-09 2.33E-13 - l Ba-139 1.17 E-10 8.32E-14 3.42E-12 No Data 7.78E-14 4.70E-07 1.12E-07 I Ba-140 4.88E-06 6.13E-09 3.21E-07 No Data 2.09E-09 1.59E-04 2.73E-05 Ba-141 1. 25 E-11 9.41 E-15 4.20E-13 No Data 8.75E-15 2.42E-07 1. 45 E-17 Ba-142 3.29 E-12 3.38E-15 2. 07 E-13 No Data 2.86E-15 1.49E-07 1.96E-26
- Reference 3, Table E-7. i VEGP ODCM, REV 4 7/30/87 2.2-28
l TABLE 2.2-4 (SHEET 3 0F 3) q INHALATION DOSE FACTORS FOR ADULTS
- l (mrem per pci inhaled) j Nuclide Bone Liver T Body Thyroid Kidney .Luno GI-LLI La-140 4.30E-08 2.17E-08 5.73E-09 No Data No Data 1.70E-05 5.73E-05 La-142 8.54E-11 3.88E-11 9. 65 E-12 No Data- No Data . 7.91E-07 2.64E-07 1 Ce-141 2.49E-06 1.69E-06 1.91E-07 No Data 7.83E-07 4.52E-05 .1.50E-05 l l
Ce-143 2.33E-08 1.72E-08 1.91E-09 No Data 7.60E-09 9.97E-06' 2.83E-05 l Ce-144 4.29E-04' 1.79E-04 2.30E-05 No Data 1.06E-04 9.72E-04 1.02E-04 u Pr-143 1.17E-06 4.69E-07 5.80E-08 No Data 2.70E-07 3.51E-05 2.50E-05 i Pr-144 3. 76 E-12 1. 56 E-12 1.91E-13 No Data 8. 81 E-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 l Np-239 2.87E-08 2.82E-09 1.55E-09 No Data 8.75E-09 4.70E-06 1.49E-05
)
I
- Reference 3. Table E-7.
VEGP ODCM, REV 4 7/30/87 2.2-29 _ _ _ _ . _ _ _ . . _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . ._ _ _ . _ _ _ . _ . . _ _ _ _ _ _ ._.____.___m._____________m._________ w
TA8LE 2.2-5 (SHEET 1 0F 3) INGESTION DOSE FACTORS FOR INFANT * (mrem per pci ingested) Nuclide Bone Liver T Body Thyroid Kidney Luna GI-LLI ) H-3 No Data 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 C-14 2.37E-05 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 Na-24 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 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. 51 E-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 Fe-55 1.39E-05 8.98E-06 2.40E-06 No Data No Data 4.39E-06 1.14E-06 Fe-59 3.08E-05 5.38E-05 2.12E-05 No Data No Data 1.59E-05 2.57E-05 I Co-58 No Data 3.60E-06 8.98E-06 No Data No Data No Data 8.97E-06 l Co-60 No Data 1.08E-05 2.55E-05 No Data No Data No Data 2.57E-05 i Ni-63 6.34E-0; 3.92E-05 2.20E-05 No Data No Data No Data 1.95E-06 Ni-65 4.70E-06 5.32E-07 2.42E-07 No Data No Data No Data 4.05E-05 Cu-64 No Data 6.09E-07 2.82E-07 No Data 1.03E-06 No Data 1.2SE-05 g
.- Zn-65 1.84E-05 6.31E-05 2.91E-05 No Data 3.06E-05 ~No Data 5.33E-05 Zn-69 9.33E-08 1.68E-07 1.25E-08 No Data 6.98E-08 No Data 1.37E-05 Br-83 No Data No Data 3.63E-07 No Data No Data No Data LT E-24 8r-84 No Data No Data 3.82E-07 No Data No Data No Data LT E-24 i
Br-85 No Data No Data 1.94E-08 No Data No Data No Data LT E-24 Rb-86 No Data 1.70E-04 8.40E-05 No Data No Data No Data 4.35E-06 l 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 1.01E-06 No Data No Data No Data 5.92E-05 i 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 Y-91M 8.10E-10 No Data 2.76E-11 No Data No Data No Data 2.70E-06 l 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 l l
- Ref erence 3 Table E-14.
VEGP ODCM, REV 4 7/30/87 2.2-30
\
J TABLE 2.2-5 (SHEET 2 0F 3) INGESTION DOSE FACTORS FOR INFANT * (mrem per pci ingested) Nuclide Bone Liver T Body Thyroid Kidnev ' Luno GI-LLI Y-93 2.43E-08 No Data 6. 62E-10 No Data No Data No Data 1.92E-04 Zr-95 2.06E-07 5.02E-08 3.56E-08 No Data 5.41E-08 No Data 2.50E-05 Zr-97 1.48E-08 2.54E-09 1.16E-09 No Data 2.56E-09 No Data 1.62E-04 Nb-95 4.20E-08 1.73E-08 1.00E-08 No Data 1.24E-08 No Data 1.46E-05 Mo-99 No Data 3.40E-05 6.63E-06 No Data 5.08E-05 No Data 1.12E-05 Tc-99M 1.92E-09 3.96E-09 5.10E-08 No Data 4.26E-08 2.07E-09 1.15E-06 Tc-101 2.27E-09 2.86E-09 2.83E-08 No Data 3.40E-08 1.56E-09 4.86E-07 Ru-103 1.48E-06 No Data 4.95E-07 No Data 3.08E-06 No Data 1.80E-05 l Ru-105 1.36E-07 No Data 4.58E-08 No Data 1.00E-06 No Data 5.41E-05
. Ru-106 2.41E-05 No Data 3.01E-06 No Data 2.85E-05 No Data. 1.83E-04 Ag-110M 9.96E-07 7.27E-07 4. 81 E-07 No Data 1.04E-06 No Data 3.77E-05 -
Te-125M 2.33E-05 7.79E-06 3.15E-06 7.84E-06 No Data No Data 1.11E-05 -) 1 Te-127M 5.85E-05 1.94E-05 7.08E-06 1.69E-05 1.44F-04 No Data- 2.36E-05 Te-127 1.00E-06 3.35E-07 2.15E-07 8.14E-07 2.44E-06 No Data 2.10E-05 g- Te-129M 1.00E-04 3.43E-05 1.54E-05 3.84E-05 2.50E-04 No Data 5.97E-05 Te-129 2.84E-07 9.79E-08 6.63E-08 2.38E-07 7.07E-07 No Data 2.27E-05 Te-131 M 1.52E-05 6.12E-06 5.05E-06 1.24E-05 4.21E-05 No Data 1.03E-04 Te-131 1.76E-07 6.50E-08 4.94E-08 1.57E-07 4.50E-07 No Data 7.11E-06 Te-132 2.08E-05 1.03E-05 9.61E-06 1.52E-05 6.44E-05 No Data 3.81E-05 I-130 6.00E-06 1.32E-05 5.30E-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 3.31 E-03 2.14E-05 No Data 3.08E-06 l 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 , C s-134 3.77E-04 7.03E-04 7.10E-05 No Data 1.81E-04 7.42E-05 1.91E-06 ' Cs-136 4.59E-05 1.35E-04 5.04E-05 No Data 5.38E-05 1.10E-05 2.05E-06 C s-137 5.22E-04 6.11E-04 4.33E-05 No Data 1.64E-04 6.64E-05 1.91E-06 : Cs-138 4.81E-07 7.82E-07 3.79E-07 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. 51 E-10 3.54E-10 5.58E-05 !
-i
- Reference 3, Table E-14.
VEGP ODCM, REV 4 7/30/87 2.2-31 i
\
i I TABLE 2.2-5 (SHEET 3 0F 3) l INGESTION DOSE FACTORS FOR INFANT * (mrem per pci ingested) Nuclide Bone Liver T Body Thyroid Kidney Luno GI-LLI 1 Ba-140 1.71E-04 1.71E-07 8.81E-06 No Data 4.06E-08 1.05E-07 4.20E-05 l Ba-141 4.25E-07 2. 91 E-10 1.34E-08 No Data 1. 75 E-10 1.77E-10 5.19E-06 ! 8a-142 1.64E-07 1.53E-10 9.06E-09 No Data 8.81E-11 9.26E-11 7.59E-07 j l l La-140 2.1 ] E-08 8.32E-09 2.14E-09 No Data No Data No Data ~ 9.77E-05 i La-142 1.10E-09 4.04E-10 9.67E-11 No Data No Data No Data 6.86E-05 Ce-141 7.87E-08 4.80E-08 5.65E-09 No Data 1.48E-08 No Data 2.48E-05 Ce-143 1.48E 08 9.82E-06 1.12E-09 No Data 2.86E-09 No Data 5.73E-05 Ce-144 2.98E-06 1.22E-06 1.67E-07 No Data 4.93E-07 No Data 1.71E-04 ] Pr-143 8.13E-08 3.04E-08 4.03E-09 No Data 1.13E-08 No Data 4.29E-05 ! Pr-144 2.74E-10 1.06E-10 1.38E-11 No Data 3.84E-11 No Data 4.93E-06 Nd-147 5.53E-08 5.68E-08 3.48E-09 No Data 2.19E-08 No Data 3.60E-05 W-187 9.03E-07 6.28E-07 2.17E-07 No Data No Data NT Data 3.69E-05 ) Np-239 1.11E-08 9.93E-10 5. 61 E-10 No Data 1.98E-09 No Data 2.87E-05 l ( l 1 4
)
- Reference 3, Table E-14.
VEGP ODCM, REV 4 7/30/87 2.2-32
i TABLE 2.2-6 (SHEET 1 0F 3) INGESTION DOSE FACTORS FOR CHILD * (mrem per pci ingested) Nuclide Bone Liver T Body Thyroid Kidney Luna _GI-LLI H-3 No Data 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 C-14 1.21E-05 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 Na-24 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 P-32 8.25E-04 3.86E-05 3.18E-05 No Data No Data No Data 2.28E-05 Cr-51 No Data No Data '8.90E-09 4.94E-09 1.35E-09 9.02E-09 4.72E-07 Mn-54 No Data 1.07E-05 2.85E-06 No Data 3.00E-06 No Data 8.98E-06 Mn-56 No Data 3.34E-07 7.54E-08 No Data 4.04E-07 No Data 4.84E-05 Fe-55 1.15E-05 6.10E-06 1.89E-06 No Data No Data 3.45E-06 1.13E-06 Fe-59 1.65E-05 2.67E-05 1.33E-05 No Data No Data 7.74E-06 2.78E-05 I Co-58 No Data 1.80E-06 5.51E-06 No Data No Data No Data 1.05E-05 Co-60 No Data 5.29E-06 1.56E-05 No Data No Data No Data 2.93E-05 Ni-63 5.38E-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 Cu-64 No Data 2.45E-07 1.48E-07 No Data 5.92E-07 No Data 1.15E-05 Zn-65 1.37E-05 3.65E-05 2.27E-05 No Data 2.30E-05 No Data 6.41E-06 Zn-69 4.38E-08 6.33E-08 5.85E-09 No Data 3.84E-08 No Data 3.99E-06 B r-83 No Data No Data 1.71E-07 No Data No Data No Data LT E-24 Br-84 No Data No Data 1.98E-07 No Data No Data No Data LT E-24 Br-85 No Data No Data 9.12E-09 No Data No Data No Data LT E-24 Rb-86 No Data 6.70E-05 4.12E-05 No Data No Data No Data 4.31E-06 Rb-88 No Data 1.90E-07 1.32E-07 No Data No Data No Data 9.32E-09 Rb-89 No Data 1.17E-07 1.04E-07 No Data No Data No Data 1.02E-09 Sr-89 1.32E-03 No Data 3.77E-05 No Data No Data No Data 5.11 E-05 l Sr-90 1.70E-02 No Data 4.31E-03 No Data No Data No Data 2.29E-04 Sr-91 2.40E-05 No Data 9.06E-07 No Data No Data No Data 5.30E-05 Sr-92 9.03E-06 No Data 3.62E-07 No Data No Data No Data 1.71E-04 l Y-90 4.11E-08 No Data 1.10E-09 No Data No Data No Data 1.17E-04 Y-91M 3.82E-10 No Data 1. 39 E-11 No Data No Data No Data 7.48E-07
- Y-91 6.02E-07 No Data 1.61E-08 No Data No Data No Data 8.02E-05 I Y-92 3.60E-09 No Data 1.03E-10 No Data No Data No Data 1.04E-04 i
l I i 1
- Reference 3, Table E-13. i VEGP ODCM, REV 4 7/30/87 2.2-33 '
l
)
TABLE 2.2-6 (SHEET 2 0F 3) INGESTION DOSE FACTORS FOR CHILD * (mrem per pci ingested) 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. 23 E-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. 67 E- 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 ( Te-125M 1.14E-05 3.09E-06 1.52E-06 3.20E-06 No Data No Data 1.10E-05 Te-127M 2.89E-05 7.78E-06 3.43E-06 6.91E-06 8.24E-05 No Data 2.34E-05 Te-127 4.71E-07 1.27E-07 1.01E-07 3.26E-07 1.34E-06 No Data 1.84E-05 Te-129M 4.87E-05 1.36E-05 7.56E-06 1.57E-05 1.a3E-04 No Data 5.9dE-05 i Te-129 1.34E-07 3.74E-08 3.18E-08 9.56E-08 3.92E-07 No Data 8.34E-06 Te-131M 7.20E-06 2.49E-06 2.65E-06 5.12E-06 2.41E-05 No Data 1.01E-04 Te-131 8.30E-08 2.53E-08 2.47E-08 6.35E-08 2.51E-07 No Data 4.36E-07 , Te-132 1. 01 E -05 4.47E-06 5.40E-06 6. 51 E-06 4.15E-05 No Data 4.50E-06 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 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 5.16E-07 I-135 1.75E-06 3.15 E-06 1.49E-06 2.79E-04 4.83E-06 No Data 2.40E-06 Cs -134 2.34E-04 3.84E-04 8.10E-05 No Data 1.19E-04 4.27E-05 2.07E-06 Cs-136 2.35E-05 6.46E-05 4.18E-05 No Data 3.44E-05 5.13E-06 2.27E-06 Cs-137 3.27E-04 3.13E-04 4.62E-05 No Data 1.02E-04 3.67E-05 1.96E-06 Cs-138 2.28E-07 3.17E-07 2.01E-07 No Data 2.23E-07 2.40E-08 1.46E-07 Ba-139 4.14E-07 2. 21 E-10 1.20E-08 No Data 1.93E-10 1.30E-10 2.39E-05 Ba-140 8. 31 E-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-11 6.58E-10 1.14E-07 Ba-142 8.,74E-08 6.29E-11 4.88E-09 No Data 5.09E-11 3.70E-11 1.14E-09
- Ref erence 3, Table E-13.
VEGP ODCM, REV 4 7/30/87 2.2-34
.J TABLE 2.2-6 (SHEET 3 0F 3) ')
1 INGESTION DOSE FACTORS FOR CHILD * (mrem per pci ingested) ; Nuclide 8one Liver T Body Thyroid Kidney Luna' GI-LLI La-140 1.01E-08 3.53E-09 1.19E-09 No Data- No. Data No Data '9.84E-05 < La-142 5. 24 E-10 1.67E-10 .5.23E-11 No Data No Data No Data 3.31E-05 Ce-141 3.97E-08 1.98E-08 2.94E-09 No Data 8.68E-09 No Data 2.47E-05 Ce-143 6.99E-09 3.79E-06 5.49E-10 No Data 1.59E-09 No Data 5.55E-05 Ce-144 2.08E-06 6.52E-07 1.11E-07 No Data 3.61E-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. 29 E-10 3.99E-11 6.49!-12 No Data 2.11 E-11 No Data 8.59E-08 i Nd-147 2.79E-08 2.26E-08 1.75E-09 No Data 1.24E-08 No Data 3.58E-05 l W-187 4.29E-07 2.54E-07 1.14E-07 No Data No Data No Data 3.57E-05 , Np-239 5.2SE-09 3.77E-10 2.65E-10 No Data 1.09E-09 No Data 2.79E-05 I i ! I i 4
- Reference 3, Table E-13.
VEGP ODCM, REV 4 7/30/87 2.2-35 e _._____._.______._____d
l l TABLE 2.2-7 (SHEET 1 0F 3) l INGESTION DOSE FACTORS FOR TEENAGER * ! (mrem per pci ingested) i Nuclide 8one Liver T Body Thyroid Kidnev _Ljtng_, .GI-LLI i H-3 No Data 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 C-14 4.06E-06 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 Na-24 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 P-32 2.76E-04 1.71E-05 1.07E-05 No Data No Data No Data 2.32E-05 Cr-51 No Data No Data 3.60E-09 2.00E-09 7.89E-10 5.14E-09 6.05E-07 Mh-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. 81 E-08 No Data 2.00E-07 No Data 1.04E-05 l Fe-55 3.78E-06 2.68E-06 6.25E-07 No Data No Data 1.70E-06 1.16E-06 l Fe-59 5.87E-06 1.37E-05 5.29E-06 No Data No Data 4.32E-06 3.24E-05 Co-58 No Data 9.72E-07 2.24E-06 No Data No Data No Data 1.34E-05 , Co-60 No Data 2.81E-06 6.33E-06 No Data No Data No Data 3.66E-05 I 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 5.41E-08 No Data 2.91E-07 No Data 8.92E-06 5.76E-06 2.00E-05 9.33E-06 No Data
, 2n-65 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 l
l Br-85 No Data No Data 3.05E-09 No Data No Data No Data LT E-24 Rb-86 No Data 2.98E-05 1.40E-05 No Data No Data No Data 4.41E-06 Rb-88 No Data 8.52E-08 4.54E-08 No Data No Data No Data 7.30E-15 Rb-89 No Data 5.50E-08 3.89E-08 No Data No Data No Data 8.43E-17 Sr-89 4.40E-04 No Data 1.26E-05 No Data No Data No Data 5.24E-05 Sr-90 8.30E-03 No Data 2.05E-03 No Data No Data No Data 2.33E-04 Sr-91 8.07E-06 No Data 3.21E-07 No Data No Data No Data 3.66E-05 Sr-92 3.05E-06 No Data 1.30E-07 No Data No Data No Data 7.77E-05 Y-90 1.37E-08 No Data 3. 69 E-10 No Data No Data No Data 1.13E-04 1 Y-91M 1.29E-10 No Data 4.93E-12 No Data No Data No Data 6.09E-09 l Y-91 2.01E-07 No Data 5.39E-09 No Data No Data No Data 8.24E-05 i Y-92 1.21E-09 No Data 3.50E-11 No Data No Data No Data 3.32E-05
- Ref erence 3, Table E-12.
l VEGP ODCM, REV 4 7/30/87 2.2-36 i
l TA8LE 2.2-7 (SHEET 2 0F 3) INGESTION DOSE FACTORS FOR TEENAGER * (mrem per pci ingested) 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. 69 E-10 2.16E-10 No Data 7.11 E-10 No Data 1.27E-04 i
Nb-95. 8.22E-09 4.56E-09 2. 51 E-09 No Data 4.42E-09 No Data 1.95E-05 ! l Mo-99 No Data 6.03E-06 1.15E-06 No Data 1.38E-05 No Data 1.08E-05 l Tc-99M 3. 32E-10 9. 26 E-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. 7 5 E-17 Ru-103 2.55E-07 No Data 1.09E-07 No Data 8.99E-07 No Cata 2.13E-05 1 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 N,o 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 Te-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 Te-129M 1.63E-05 6.05E-06 2.58E-06 5.26E-06 6.82E-05 No Data 6.12E-05 Te-129 4.48E-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 j Te-131 2.79E-08 1.15E-08 8.72E-09 2.15 E'-08 1.22E-07 No Data 2.29E-09 l Te-132 3.49E-06 2.21E-06 2.08E-06 2.33E-06 2.12E-05 No Data 7.00E-05 I-130 1.03E-06 2.98E-06 1.19E-06 2.43E-04 4.59E-06 No Data 2.29E-06 l I-1 31 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 j I-133 2.01E-06 3.41E-06 1.04E-06 4.76E-04 5.98E-06 No Data 2.58E-06 ; l I-134 1.46E-07 3.87E-07 1.39E-07 6.45E-06 6.10E-07 No Data 5.10E-09 I-135 6.10E-07 1.57E-06 5.82E-07 1.01E-04 2.48E-06 No Data 1.74E-06 - ! Cs-134 8.37E-05 1.97E-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 ! C s-137 1.12E-04 1.49E-04 5.19E-05 No Data 5.07E-05 1.97E-05 2.12E-06 l Cs-138 7.76E-08 1.49E-07 7.45E-08 No Data 1.10E-07 1.28E-08 6.76E-11 ! l Ba-139 1.39E-07 9.78E-11 4.05E-09 No Data 9.22E-11 6. 74 E-11 1.24E-06 ! i
- Reference 3, Table E-12. i I
VEGP ODCM, REV 4 7/30/87 2.2-37 l l l I __ E
t TABLE 2.2-7 (SHEET 3 0F 3) INGESTION DOSE FACTORS FOR TEENAGER * . (mrem per pci ingested) I Nuclide Bone Liver T Body Thyroid Kidney Luno GI-LLI Ba-140 2.84E-05 3.48E-08 1.83E-06 No Data 1.18E-08 2.34E-08 4.38E-05 Ba-141 6.71E-08 5.01E-11 2.24E-09 No Data 4. 65 E-11 3.43E-11 1.43E-13 l Ba-142 2.99E-08 2.99E-11 1.84E-09 No Data 2.53E-11 1. 99 E-11 9.18E-20 l La-140 3.48E-09 1.71E-09 4. 55 E-10 No Data No Data No Data 9.82E-05 ! La-142 1. 79 E-10 7.95E-11 1.98E-11 No Data No Data No Data 2.42E-06 , l Ce-141 1.33E-08 8.88E-09 1.02E-09 No Data 4.18E-09 No Data 2.54E-05 i ! Ce-143 2.35E-09 1.71E-06 1. 91 E-10 No Data 7. 67 E-10 No Data 5.14E-05 Ce-144 6.96E-07 2.88E-07 3.74E-08 No Data 1.72E-07 No Data 1.75E-04 i Pr-143 1.31E-08 5.23E-09 6.52E-10 No Data 3.04E-09 No Data 4.31E-05 I Pr-144 4.30E-11 1. 76 E-11 2.18E-12 No Data 1.01 E-11 No Data 4. 74 E-14 Nd-147 9.38E-09 1.02E-08 6.11E-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. 66 E-10 9. 22 E-11 No Data 5. 21 E-10 No Data 2.'67E-05 l l l l
- Ref erence 3', Table E-12.
VEGP ODCM, REV 4 7/30/87 2.2-38 l
.___--_______O
r_ TABLE 2.2-8 (SHEET 1 0F 3) INGESTION DOSE FACTORS FOR ADULTS * (mrem per pci ingested) l i l Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI l H-3 No Data 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 C-14 2.84E-06 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 Na-24 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 l 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 j Mn-54 No Data 4.57E-06 8.72E-07 No Data 1 36E-06 No Data 1.40E-05 l Mn-56 No Dat'a 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 l Fe-59 4.34E-06 1.02E-05 3.91E-06 No Data No Data 2.85E-06 3.40E-05 1 Co-58 No Data 7.45E-07 1.67E-06 No Data No Data No Data 1. 51 E-05 Co-60 No Data 2.14E-06 4.72E-06 No Data No Data No Data 4.02E-05 Ni-63 1.30E-04 9.01E-06 4.36E-06 No Data No Data No Data 1.88E-06 Ni-65 5.28E-07 6.86E-08 3.13E-08 No Data No Data No Data 1.74E-06 Cu-64 No Data 8.33E-08 3.91E-08 No Data 2.10E-07 No Data 7.10E-06 2n-65 4.84E-06 1.54E-05 6.96E-06 No Data 1.03E-05 No Data 9.70E-06 Zn-69 1.03E-08 1.97E-08 1.37E-09 No Data 1.28E-08 No Data 2.96E-09 Br-83 No Data No Data 4.02E-08 No Data No Data No Data 5.79E-08 Br-84 No Data No Data 5.21E-08 No Data No Data No Data 4.09E-13 1 j Br-85 No Data No Data 2.14E-09 No Data No Data No Data LT E-24 Rb-86 No Data 2.11E-05 9.83E-06 No Data No Data No Data 4.16E-06 Rb-88 No Data 6.05E-08 3.21E-08 No Data No Data No Data 8.36E-19 Rb-89 No Data 4.01E-08 2.82E-08 No Data No Data No Data 2.33E-21 ! Sr-89 3.08E-04 No Data 8.84E-06 No Data No Data No Data 4. 94 E- 05 I Sr-90 7.58E-03 No Data 1.86E-03 No Data No Data No Data 2.19E-04 j Sr-91 5.67E-06 No Data 2.29E-07 No Data No Data No Data 2.70E-05 ! S r-92 2.15E-06 No Data 9.30E-08 No Data No Data No Data 4.26E-05 i Y-90 9.62E-09 No Data 2.58E-10 No Data No Data No Data 1.02E-04 i Y-91M 9.09E-11 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 i Y-92 8.45E-10 No Data 2.47E-11 No Data No Data No Data 1.48E-05 l
- Reference 3, Table E-11.
VEGP ODCM, REV 4 7/30/87 2.2-39
TABLE 2.2-8 (SHEET 2 0F 3) INGESTION DOSE FACTORS FOR ADULTS * (mrem per pci ingested) Nuclide Bone Liver T Body Thyroid Kidney Luno GI-LLI Y-93 2.68E-09 No Data 7.40E-11 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. 55 E-10 No Data 5.12E-10 No Data 1.05E-04 Nb-95 6.22E-09 3.46E-09 1.86E-09 No Datz 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 l 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. 54 E-10 3.66E-10 3.59E-09 No Data 6.59E-09 1. 87 E-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 l Ru-106 2.75E-06 No Data 3.48E-07 No Data 5.31E-06 No Data 1.78E-04' l Ag-110M 1.60E-07 1.48E-07 8.79E-08 No Data. 2.91E-07 No Data 6.04E-05' l Te-125M 2.68E-06 9.71E-07 3.59E-07 8.06E-07 1.09E-05 No Data '1.07E-05 Te-127M 6.77E-06 2.42E-06 8.25E-07 1.73E-06 2.75E-05 No Data 2.27E-05 I Te-127 1.10E-07 3.95E-08 2.38E-08 8.15E-08 4.48E-07 No Data 8.68E-06 Te-129M 1.15E-05 4.29E-06 1.82E-06 3.95E-06 4.80E-05 No Data 5.79E-05 Te-129 3.14E-08 1.18E-08 7.65E-09 2.41E-08 1.32E-07 No Data 2.37E-08 Te-131M 1.73E-06 8.46E-07 7.05E-07 1.34E-06 8.57E-06 No Data 8.40E-05 Te-131 1.97E-08 8.23E-09 6.22E-09 1.62E-08 8.63E-08 No Data 2.79E-09 Te-132 2.52E-06 1.63E-06 1.53E-06 1.80E-06 1.57E-05 No Data 7.71E-05 I-130 7.56E-07 2.23E-06 8.80E-07 1.89E-04 3.48E-06 No Data 1.92E-06 I-131 4.16E-06 5.95E-06 3.41E-06 1.95E-03 1.02E-05 No Data 1.57E-06 I-132 2.03E-07 5.43E-07 1.90E-07 1.90E-05 8.65E-07 No Data i.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. 51 E-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 C s-136 6. 51 E-06 2.57E-05 1.85E-05 No Data 1.43E-05 1.96E-06 2.92E-06 Cs-137 7.97E-05 1.09E-04 7.14E-05 No Data 3.70E-05 1.23E-05 2.11E-06 Cs-138 5.52E-08 ' 09E-07 5.40E-08 No Data 8.01E-08 7.91E-09 4.65E-13 Ba-139 9.70E-08 6. 91 E-11 2.84E-09 No Data 6.46E-11 3.92E-11 1.72E-07 Ba-140 2.03E-05 2.55E-08 1.33E-06 No Data 8.67E-09 1.46E-08 4.18E-05 Ba-141 4.71E-08 3.56E-11 1.59E-09 No Data 3.31E-11 2.02E-11 2.22E-17 Ba-142 2.13E-08 2.19E-11 1.34E-09 No Data 1. 85 E-11 1. 24 E-11 3.00E-26
- Ref erence 3, Table E-11.
VEGP ODCM, REV 4 7/30/87 2.2-40
TA8LE 2.2-8 (SHEET 3 0F 3) INGESTION DOSE FACTORS.FOR ADULTS * (mrem per pei ingested) Nuclide' Bone Liver T Body Thyroid Kidney Luna GI-LLI' La-140 2.50E-09 1.26E-09 3.33E-10 No Data No Data No Data 9.25E-05 La-142 1. 28 E-10 5.82E-11 1.45E No Data No Data No Data 4.25E-07 Ce-141 9.36E-09 6.33E-09 7.18E-10 No Data 2.94E-09 No Data ,2.42E-05 Ce-143 1.65E-09 1.22E-06 1. 35 E-10 No Data 5.37E-10 No Data 4.56E-05 Ce-144 4.88E-07 2.04E-07 2.62E-08 No Data 1.21E-07 No Data 1.65E-04 i 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 7.05 E-12 No Data 4. 33 E-18 Nd-147 6.29E-09 7.27E-09 4. 35 E-10 No Data 4.25E-09 No Data' 3.49E-05 W-187 1.03E-07 8. 61 E-08 3.01E-08 No Data No Data No Data 2.82E-05 Np-239 1.15E-09 1.17E-10 6.45E-11 No Data 3.65E-10 No Data 2.40E-05 l
- Reference 3, Table E-11.
VEGP ODCM, REV 4 7/30/87 2.2-41
TA8LE 2.2 (SHEET 1 0F 2) EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND * (mrem /h per pCi/m2) { RADIONUCLIOE TOTAL BODY SKIN l 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. 60 E-10 Mn-54 5.80E-09 6.80E-09 Mn-56 1.10E-08 1.30E-08 Fe-55 0.0 0.0 Fe-59 8.00E-09 9.40E-09 Co-58 7.00E-09 8.20E-09 Co-60 1~.70E-08 2.00E-08 Ni-63 0.0 0.0 Ni-65 3.70E-09 4.30E-09 Cu-64 1.50E-09 1.70E-09 Zn-65 4.00E-09 4.60E-09 Zn-69 0.0 0.0 Br-83 6.40E-11 9.30E-11 Br-84 1.20E-08 1.40E-08
- Br-85 0.0 0.0 Rb-86 6. 30E-10 7.20E-10 Rb-88 3.50E-09 4.00E-09 Rb-89 1.50E-08 1.80E-08 Sr-89 5.60E-13 6. 50E-13 l Sr-91 7.10E-09' 8.30E-09 Sr-92 9.00E-09 1.00E-08 Y-90 2.20E-12 2.60E-12 l Y-91M 3.80E-09 4.40E-09 Y-91 2.40E-11 2.70E-11 Y-92 1.60E-09 1.90E-09 Y-93 5.70E-10 7.80E-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 Ag-110M 1.80E-08 2.10E-08 Te-125M 3.50E-11 4.80E-11
- Reference 3, Table E-6.
VEGP ODCM, REV 4 7/30/87 2.2-42 i'______--_--____----- u
TABLE 2.2-9 (SHEET 2 0F 2) EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND * (mrem /h per pCi/m2) RADIONUCLIDES TOTAL BODY SKIN Te-127M 1.10E-12 1. 30 E-12 Te-127 1.00E-11 1.10E-11 I , Te-129M 7.70E-10 9.00E-10 l Te-129 7.10E-10 8.40E-10 Te-131 M 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 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 C s-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 { Ba-140 2.10E-09 2.40E-09 )
/ 8a-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. 20 E-10 Ce-143 2.20E-09 2.50E-09 Ce-144 3. 20E-10 3.70E-10 Pr-143 0.0 0.0 Pr-144 2.00E-10 2. 30E-10 Nd-147 1.00E-09 1.20E-09 W-187 3.10E-09 3.60E-09 Np-239 9.50E-10 1.10E-09
- Reference 3, Table E-6.
VEGP ODCM, REV 4 7/30/87 2.2-43 L_____-__-. - _ - - _ _ _ _ _ _ _ _ - _ _ - _ _ - - - _ .
l TABLE 2.2-10 INDIVinUAL USAGE FACTORS
- l INFAP T CHILD TEENAGER ADULT Milk Consumption Rate, 0 330 330 400 310 ap (liters / year)
Heat Consumption Rate, U (kg/ year) 0 41 65 110 Fresh Leafy Vegetation l Consumption Rate, I
' U, (kg/ year) 0 26 42 64 l Stored Vegetation Consumption Rate, U , (kg/ year) 0 520 630 520 Breathing Rate 3
(m / year) 1400 3700 8000 8000 l l k
- Reference 3, Table E-5.
VEGP ODCM, REV 4 7/30/87 2.2-44
I - l TABLE 2.2-11 STABLE ELEMENT TRANSFER DATA * ! (Milk-days / liter; Meat-days /kg) F - MILK F - MILK F - MEAT f ELEMENT (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 l 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 3.1E-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 l Tc 2.5E-02 2.5E-02 4.0E-01 l / Ru 1.0E-06 1.0E-06 4.0E-01 Rh 1.0E-02 1.0E-02 1.5E-03 ' l Ag 5.0E-02 5.0E-02 1.7E-02 ' l Te 1.0E-03 1.0E-03 7.7E-02 l 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 i
- References 3, Table E-1; Reference 3, Table E-2 for H, C, P, Fe, Cu, Sr, I, I
and Cs in goat's milk; the remainder of elements in goat's milk are taken i from Table E-1 as presented for cow's milk. 1 VEGP ODCM, REV 4 7/30/87 2.2-45 __m - -
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 on VEGP site meteorological data collected for the period February 1,1984 through January 31, 1986. Sector: WSW Distance: 1.3 miles Age Group: Child Dispersion: (X/0')gp = 9.49E-6 s/m3 (X/Q')gp = 1.07E-6 s/m Deposition: -2 (D/Q')GP = 6.73E-9 m-2 (D/0')gp = 2.53E-9 m t 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 i 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 l conditions, the individual exposed to these pathways could become the ) controlling receptor. The determining factor is likely to be the number of months the cow is milked in a year. Calculated dose results should be compared to the receptor presented above to determine which is the controlling receptor. Sector: WNW Distance: 2.8' miles Age group: Child l Dispersion: 3 (X/Q')GP = 1.36E-6 s/m3 (X/0')gp = 1.55E-7 s/m Deposition: (D/Q')gp = 8.40E-10 m-2 (D/0')gp = 2.64E-10 m-Exposure pathways: Inhalation, ground plane, vegetation, and milk cow
- Reference 12; Reference 13.
VEGP ODCM, REV 4 7/30/87 2.2-46 4 _._m__.__ ____
i TABLE 2.2-13 (SHEET 1 0F 4) l SITE-SPECIFIC (OR DEFAULT) VALUES TO j BE USED IN PATHWAY FACTOR CALCULATIONS I (Supports subsections 2.2.2.2 and 2.2.2.3) { i l l l Pa rameter Description Value ! 1 j In;1alation I (BR)a Breathing rate for age group table 2.2-10 ) 1 l (DFA)ija Inhalation dose factor for tables 2.2-1, age group 2.2-4 i l Ground plane SHF Shielding factor due to 0.7 structure (Reference 3, ! table E-15) I (DFG)1j Ground plane dose factor table 2.2-9 j (Same for all j age groups) l l { ( Garden Vegetation l Yv Garden vegetation a real 2.0 kg/m2 density (Reference 3, table E-15) ) Dat Leafy vegetation consumption table 2.2-10 rate for age group Uas Stored vegetation consumption table 2.2-10 rate for age group fg Fraction of annual intake 1.0 of leafy vegetation grown (Reference 1, locally page 36) fg Fraction of annual intake of 0.76 stored vegetation grown locally (Reference 1, page 36) H Absolute humidity of the 8.0 gm/m3 atmosphere (Reference 1, page 34) VEGP ODCM, REV 4 7/30/87 2.2-47
I I i l TABLE 2.2-13 (SHEET 2 0F 4) l SITE-SPECIFIC (OR DEFAULT) VALUES TO j l BE USED IN PATHWAY FACTOR CALCULATIONS i I i l Parameter Description Value Grass-Cow-Meat 1 k Qp Feed consumption rate for cow 50 kg/ day ; (Reference 3, i table E-3) Vap Meat consumption rate for table 2.2-10 ' age group l (DFL)ija Ingestion dose factor for tables 2.2 l age g-oup 2.2-8 ! Yp Pasture grass areal density 0.7 kg/m2 f (Reference 3, l i table E-15) Y3 Stored feet. areal density 2.0 kg/m22 l (Reference 3, { table E-15) q fp Fraction of year that cow 1.0 grazes on pasture (Reference 1, page 33) I l f5 Fraction of total feed that 1.0 is pasture grass while cow is (Reference 1, on pasture page 33) H Absolute humidity of the 8.0 gm/m3 atmosphere (Reference 1, page 34) i Grass-Cow-Milk Qp Feed consumption rate for 50 kg/ day cow (Reference 3, l i table E-3) j i V ap Milk consumption rate for table 2.2-10 age group l
]
(DFL)ija Ingestion dose factor for tables 2.2 age group 2.2-8 l VEGP 00CM, REV 4 7/30/87 2.2-48 l l l l
.. j
I I l TABLE 2.2-13 (SHEET 3 0F 4) SITE-SPECIFIC (OR DEFAULT) VALUES TO BE USED IN PATHWAY FACTOR CALCULATIONS 1 Parameter Description Value f : I Yp Pasture grass areal density 0.7 kg/m2 j (Reference 3, ' table E-15) Ys Stored feed areal density 2.0 kg/m2 (Reference 3, table E-15) j fp Fraction of year that cow 1.0 grazes (Reference 1, page 33) f s Fraction of total feed that is 1.0 pasture grass while cow is on (Reference 1, pasture page 33) H Absolute humidity of the 8.0 gm/m3 atmosphere (Reference 1, page 34) - Grass-Goat-Milk 0F Feed consumption rate for 6.0 kg/ day goat (Reference 3, i table E-3) -l i V ap Milk consumption rate for table 2.2-10 age group q l (DFL)ija Ingestion dose factor for tables 2.2 age group 2.2-8 Yp Pasture grass areal density 0.7 kg/m2 (Reference 3, table E-15) Y3 Stored feed areal density 2.0 kg/m2 (Referencu 3, table E-15) fp Fraction of year that goat 1.0 [ is on pasture (Reference 1, l page 33) ? - VEGP ODCM, REV 4 7/30/87 2.2-49 L _
i l i TABLE 2.2-13 (SHEET 4 0F 4) SITE-SPECIFIC (OR DEFAULT) VALUES TO BE USED IN PATHWAY FACTOR CALCULATIONS Parameter Description Value l
)
fs Fraction of total-feed that is 1.0 l pasture gri. s while goat is on (Reference 1, I pasture page 33) H Absolute ramidity of the 8.0 gm/m3 atmosphere (Reference 1, l page 34) l i I J l l. VEGP ODCM, REV 4 7/30/87 2.2-50 i
TABLE 2.2-14 POTENTIAL RECEPTOR LOCATIONS AND PATHWAYS (To support subsection 2.2.2.3) i Distance Sector (Miles) Km Pathwav*** Age Group N
- NNE
- NE
- ENE * !
E ESE
- SE 3.3 5.3 Vegetation Child i SSE 4.6 7.4 Vegetation Child S 4.5 7.2 Vegetation / Meat Animal Child SSW 4.7 7.6 Meat Animal Child SW 3.1 5.0 Meat Animal Child WSW 1.3 2.1 Vegetation Child
/' W 4.2 6.8 Vegetation Child WNW 2.5 3.7 Vegetation Child 2.8**** 4.5 Vegetation / Milk Cow Child NW 3.9 6.3 Vegetation Child NNW **
- Savannah River Plant Property (closed to public).
** No receptor identified within five miles.
*** Inhalation and ground plane pathways are assumed at all locations where ingestion pathways exist.
**** A milk cow has been observed at this location. However, discussions f
with the owner revealed that she is on an irregular milking cycle. The pathway will exist during periods when the cow is being milked.
~
Reference 12. VEGP ODCM, REV 4 7/30/87 2.2-51 2 L - __-_ _-_-_-_____-_:- . _ - _
~
l. TABLE 2.2-15 DISPERSION AND DEPOSIT 0N PARAMETERS l (To Support Subsection 2.2.2.3) i Ground-Level Release Mixed-Mode Release Distance 3 -2 3 -2 Sector (kiles) Km X/0 s/m D/0 m X/0 s/m D/0 m N
- NNE
- NE
- l ENE
- E ESE
- SE 3.3 5.3 6.80E-7 6.15E-9 7.05E-8 1. 58 E-10 SSE 4.6 7.4 4.37E-7 2.15E-10 4.49E-8 8.26E-11 S 4.5 7.2 4.48E-7 2.88E-10 5.35E-8 1.12E-10 SSW 4.7 7.6 3.70E-7 2.32E-10 5.30E-8 1. 56 E-10 SW 3.1 5.0 1.53E-6 1.02E-9 2.19E-7 4. 53 E-10
/ WSW 1.3 2.1 9.49E-6 6.73E-9 1.07E-6 2.53E-9 W 4.2 6.8 6.20E-7 3.36E-10 7.41E-8 1. 38 E-10 l WNW 2.3 3.7 2.03E-6 1.27E-9 2.16E-7 3.80E-10 l 2.8 4.5 1.36E-6 8.40E-10 1.55E-7 2.64E-10 NW 3.9 6.3 7.25E-7 3.72 E-10 7.99E-8 1. 25 E-10 l NNW **
I
- Savannah River Flant property (closed to public).
** No receptor identified within five miles.
Reference 12; Reference 13. VEGP ODCM, REV 4 7/30/87 2.2-52 __________:__o
2.2.3 Dose Projections for Gaseous Effluents 2.2.3.1 Th'irty-One Day Dose Projections In order to maet 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 ef fluents may be determined as follows: Air Doses: beta (prj) = beta (c) x 31 (32) t D (33) gamma (prj) = ama(c) x 31 Individual: Do (c) x 31 Do (prj) t (34) Where: I D = the cumulative air dose, due to beta emissions from et@ noble gases, for the elapsed portion of the current quarter plus the release under consideration. D = the cumulative air dose, due to gamma emissions f rom noble gases, for the elapsed portion of the current quarter plus the release under consideration. l l VEGP ODCM, REV 4 7/30/87 2.2-53 l
i 0 = the cumulative organ dose to an individual due to 1-131, I-133, tritium and particulate, for the elapsed portion of the current quarter plus the release under consideration. 1
\
t = the number of. days into the current quarter, including the { period of the release under 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 l contribution should be included in the projected dose as follows: Air Doses:
~
"D D
beta (prj) " x 31 +D (35) PA D camma(c) (36) D gamma (prj) " t x 31 &D
- 7. _ _ PA D
c) D g p pg = x 31 &D (37) _ PA Where D is the expected dose due to the particular planned activity. PA 2.2.3.2 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 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 particulate, follow the methodology presented in subsection 2.2.2.2 using sample analyses results for the particular release point and I parametric values expected to exist for the release period. VEGP ODCM, REV 4 7/30/87 2.2-54
l 2.3 METEOROLOGICAL MODEL , (Reference 7, 13, 15, and section 2.3.5 of reference 5) 2.3.1 Atmospheric Dispersion Atmospheric dispersion (long-term) may be calculated using the appropriate , form of the sector-averaged straight line flow Gaussian model. Gaseous releases are considered to be either ground level or mixed mode. Considered as ground level are releases from the turbine building (s) vents and the ; radwaste solidification building vent. Releases from reactor building (s) .
'(plant) vent (s) are considered to be mixed mode. (See NOTE in subsection )
2.1.2). . l 2.3.1.1 Ground-Level Releases i I (X/Q)g
= the ground-level sector-averaged relative concentration for a given wind direction (sector) and distance (s/m3 ),
= (RCF) 2.032 d p "ik (38)
Nujk
- Izk j i
where: 2.032 = (2/w) divided by the number of. radians in a 22.5* sector (0.3927 radians), d = the plume depletion f actor for all radionuclides other than' p l noble gases at a distance x shown in figure 2.3-2 for
)
ground-level releases; for noble gases the depletion factor is unity. If an undepleted relative concentration is desired, the depletion factor is unity. Only depletion by deposition is considered since depletion by decay would be { of little significance at the distances considered. VEGP 00CM, REV 4 7/30/87 2.3-1
)
RCF = the open terrain recirculation factor. Values for specific distances are obtained from figure 3.2 of reference 15. n = the 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 f requency data, the summation , over j and k is deleted and the summation is accomplished for all hours at 'all distances for each direction. N = the total hours of valid meteorological data throughout the period of interest. u = the wind speed (mid-point. of windspeed class j) at ground level (m/s), during stability class k. x = the distance from release point to location of interest (meters). I = the vertical standard deviation of the plume concentration distribution considering the initici dispersion within the building wake. (og + (b /2*))
= the lesser of or i f(o )
o = the vertical' standard deviation of the plume concentration distribution (meters) for a given distance and stability category k as shown in figure 2.3-1. The stability category is determined by the vertical temperature gradient aT/a2 ('C/100m).
* = 3.1416 b = the maximum height of adjacent plant structure (55 meters).
VEGP ODCM, REV 4 7/30/87 2.3-2
.._._.__.____..m___m. .m-__.
2.3.1.2 Mixed-Mode Releases (X/Q)g = the mixed-mode sector-averaged relative concentration for a . given' wind direction (sector) and distance (s/m3 ), n
=
2.032(RCF)d p jf N u jk zk
~
_- '(39)
+U jk #zk exp(-h /2a*)
( where: d p
= the plume depletion factor for all radionuclides other than noble gases at a distance x shown in figures-2.3-3 through 2.3-5 for elevated releases; for noble gases the depletion factor is unity. If an undepleted relative concentration l 1s desired, the depletion factor is unity. Only depletion f
r f
,.. by deposition is considered since depletion by decay would-be of little significance at the distances considered.
U = the 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 condicions, respectively. (Reference 5, section 2.3.5.) 3 E = the f raction considered as ground-level releases. W 1.0 for 51.0 W W 2.58 - 1.58 ( ) for 1.0 < $ 1.5 W W 0.3 - 0.06 ( " ) for 1.5 < $ 5.0 l W 0 for > 5.0 1 VEGP ODCM, REV 4 7/30/87 2.3-3 ; i
-_-________a__-____________-__-____-___________. __ _ . _ - - _ _ . - _ .- . _ _ . _ _ _ _ _ _ - . _ - .
r i W = the vent exit velocity (m/s). I h = the effective release height (m).
= h +h -h -c (40) v pr t v l
l h = the height of release point (m). y f h = the maximum terrain height between the release point and j the point of interest (m). (See table 2.3-1.) h the additional height due to plume rise (m). i 9' ,
=
1.44d (Wg /u) (x/d) (41) l
= limited by the lesser of the following two equations: l l-
' l l hpr(max) = 3(Wo /u)d or h pr(max) = 1.5(F /u)1/3S -1/6 f i i d = the inside diameter of vent. ' c = the correction for low vent exit velocity (m). I W W 3(1.5 - )d for <l.5
=
for --- > 1. 5 FE = the momentum flux parameter (m4 /s2),
=
(Wg ) (d/2) S = the stability parameter.
~ ~
8.75 x 10 s for -0.5 < AT < 1.5
= 1.75 x 10~
~
s ~ for 1.5 < AT < 4.0
~
2.45 x 10 s for AT > 4.0 l 1 Other terms were defined in subsection 2.3.1.1. VEGP ODCM, REV 4 7/30/87 2.3-4 [
2.3.2 Relative Deposition ' (See NOTE in subsection 2.1.2.) 2.3.2.1 Ground-Level Releases
.( D/0)'g = the ground-level sector-averaged relative deposition _at a 2
'given distance and for a given sector (1/m ),
=
(RCF) I a "k (42) k Nx where: - 2.55 = the inverse of the number of radians in a 22.5' sector
~
(2 1r/16) .
'D = the deposition rate at a given distance, taken from figure r 2.3-6 for ground-level releases.
n = the number of hours the wind is directed into the sector of interest, during which time stability category k exists. l N = the total number of hours of valid meteorological data. RCF = the open terrain recirculation factor. Values for specific distances are obtained from figure 3.2 of reference 15, 2.3.2.2 Mixed-Mode Releases (D/0)g = the mixed-mode sector-averaged relative deposition at a given distance and for a given sector (1/m2 ). (RCF) ((E)(D g ) + (1 - E) D,)- (43) VEGP ODCM, REV 4" 7/30/87' ,2.3-5
~
f
/
w'h e re :' i l 0( 3 f
=' the relative deposition rate for the ground-level portion 9
! ' / of mixed-mode releases from figurt 2.3-6.
=, ,.. , ,
e i
,i j
'D = the relative deposition rate, for the e?evated portion of ^
e , t' ,
' r, mixed-mode releases from fig' ires 2.3-7 through ? 3-9.
. e 3
?
E = the fraction of releases considered as ground ievel.
! Other terme yere defined in previous subsections. ,
l J 1 i , 9 1 q
, .i t
- l 1
j 1 .
,e I
l L 1
, l l
l 1 x l 1 I f L Y ! 9 )) c
\
~ .
t
?
A *
- j
; I t'
?
VEGP ODCM,.REV 4 7/30/87 2.3-6
- l 1
L_-_______________________. _. _ - - .
k TABLE 2.3-1 (SHEET 1 0F 2) Terrain Elevation Above Plant Grade 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 1,000 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 1,500 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 2,000 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 2,500 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 3,000 0.0 0.0 ' O.0 0.0 0.0 0.0 0.0 0.0 3,500 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 4,000 0.0 0.0 0.0 0.0 0.0 0.0 4.5 0.0 5,000 0.0 0.0 0.0 0.0 0.0 0.0 11.1 0.0 6,000 0.0 0.0 0.0 0.0 0.0 0.0 11.1 0.0 7,000 0.0 0.0 0.0 7.8 0.0 0.0 11.1 0.0 8,000 0.0 0.0 21.1 13.9 0.0 0.0 11.8 0.0 9,000 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 1 14,000 0.0 15.9 26.8- 20.2 0.0 0.0 17.1 19.5 l l 16,000 0.0 15.9 26.8 21.7 13.2 0.0 17.1 19.5 l i l l 1 i l i i Reference 5. I VEGP ODCM, REV 4 7/30/87 2.3-7 l l l
l l TABLE 2.3-1 '(SHEET 2 0F 2) , I Terrain Elevation Above Plant Grade I l Wind Direction from Plant to Receptor l I Distance 1 (m) S SSW SW WSW W WNW NW NNW ) 500 0.0 4.7 8.7 5.7 1.4 5.8 5.7 3.5 1,000 0.0 4.7 16.7 13.4 3.3 10.4 11,8 6.8 1,500 0.0 4.7 21.7 18.6 7.3 12.2 14.3 7.3 2,000 0.0 4.7 21.7 18.6 7.3 12.2 14.3 7.3 2,500 0.0 4.7 21.7 18.6 7.3 12.2 14.3 7.3 3,000 0.0 4.7 23.7 18.6 7.3 12.2 14.3 7.3
- 3,500 0.0 4.7 24.4 18.6 7.3 12.2 16.9 7.3 i 4,000 0.0 4.7 24.4 18.6 7.3 12.2 16.9 7.3 l 5,000 0.0 4.7 24.7 18.6 7.3 12.2 16.9 7.3 6,000 0.0 4.7 26.8 18.6 7.3 12.2 16.9 7.3 7,000 3.6 4.7 26.8 18.6 7.3 12.2 16.9 7.3 l 8,000 14.6 4.7 26.8 18.6 7.3 12.2 16.9 7.3 9,000 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
l l i l I - l i ! l l 1 1 l l .
)
i I
- VEGP 00CM, REV 4 7/30/87 2.3-8
1 j i t.se j ,- [ t : / i
. . .f . . . . - , .t 6 46/ s/ 4 6 / e i U.
I/) / i / M I' ,
/ l / ;
/ f ill!
l// - ,,
/.- , -
=1 l s- s s ' y. Ie ,
y a ?; ,<( r s s .., g 6 A y e (7 } i t f) fe 6: L# 4 4 w f, / / fi i V / IJi' 'll # IIiil 5 ///lMV /'l ) 1'l llll
,, V///[/
, , , / ,l - ;
/ if i V e t is t e e e # 6 4 se t i , . . ii
[6 /t i I I ill l I i i I I ll l 1 I 8 8 iiil l l l l llll l ll i l lllll
/
'. . i. i.
PLusst TRAvfL DtETAMCE (KIL0w.ET1481 f. b
's Range of Verti' cal Range of Vertical Catecery Temperature Gradient ('C/100m) Temperature Gradient (*F/100f t)
A AT/a2 < -1.9 AT < -1.0 B
-1.9 5 AT/AZ < -1.7 -1.0 $ AT < -0.9 C -1.7 5 AT/AZ < -1.5 -0.9 5 AT < -0.8 D -1.5 5 aT/AZ < -0.5 -0. 8 5 AT < -0. 3 l l E
-0.5 5 AT/AZ < 1.5 -0.3 $ AT < 0.8 ;
F 1.5 5 AT/a2 < 4.0 0.8 5 AT < 2.2 ! G 4.0 .<. AT/a2 2.2 .<. AT
- Reference 7.
(. VERTICAL STANDARD DEVIATION OF-V MATERIAL IN A PLUME (0,)* GeorgiaPower A "OGrLE'""f,o"'u"='r"*""'^"' 1 (Letters Denote Pasauill Stability Class) FIGURE 2.3-1 VEGP ODCM REV 4 7/30/87 2.3-9 i e
I l t l 1h , I % i W 0.9 N-N % N 1 0.8
? -h s s 1 a
$ 0.7 s l h \ \
I E 0.s l l ! 'N
\
1 l E 0.5 8 ss i y 0.4 \ , 5 4 l 0.2 ) 0.1 1 0.1 1.0 10.0 100.0 200.0 PLUME TRAVEL DISTANCE (KILOMETERS) { l i
- Reference 7 PLUME UEPLETION EFFECT FOR GROUND-VOGTLE LEVEL RELEASES l
GeorgiaPower n ',"$ r o'u"u'r"^ " "*"' ( All Atmospheric Stability Classes) FIGURE 2.3-2
*
- VEGP ODCM REV 4 7/30/87 2.3-10 a-_____-___-______
1.0 l l STABLE; 0.9 NEUTRALID) lE.EG) w 0.8 . O.7 -- E E UNSTABLE k g 0.6 (A,8,C) . N 1 0.5 m l 9 %' g 0.4 5 w 0.3 . . . 0.2 0.1 0.1 1.0 10.0 100.0' .100.0; l PLUME TRAVEL DISTANCE (KlLOMETERS)
- i I
1 l Reference 7. l ( vocTLs PLUME DEPLETION EFFECT FOR 30-METER RELEASES
- Georgia Power d ELECTRIC GENERATING PLANT (letters Denote Pasquill Stability Class) unit 1 ANouNiT2 FIGURE 2.3-3
'"' VEGP ODCM REV 4 7/30/87 2.3-11 u------------------_-..-------- ---
( M*H I If 1.0 ' . j,STA8LE N4 % % E.F,G) { N g % g 0.9 % W i 7%Q%
- l NEUTRAL I w 0.8 l - '
3 T T(p) U \ 2 0.7 UNSTABLE ., j l.A,8,C) N 30.s ' E 2 y 0.5 \ 5 \ 50.4 \ 5 0.3 (' O.2 4 0.1 l 01 1.0 10.0 l00.0 200.0 I PLUME TRAVEL DISTANCE (KILOMETERS) i l 1 l 1 l '
- Reference 7, 1
VOGTLE PLUME DEPLETION EFFECT FOR 60-METER RELEASES
- Georgia PowerkL (Letters Def10te Pasquill Stability Class)
ELECTRIC GENERATING PLANT UNIT 1 AND UNIT 2 FIGURE 2.3-4 l VEGP ODCM REV 4 7/30/87 2.3-12
1.0
, % % NEUTR AL (D) w 0.a N,N 3 l UNSTABLE %
g z CJ (A 8.C) ( 3
\ '
~ s%
h. STABLE (E.F.Gl NO DEPLETION,
%( \
(FRACTION REMAINING = 1.01 \ E 0.5 g 5 N E c.4 \ W r-f O.3 0.2
\
0.1 I I 0.1 1.0 10.0 100.0 200.0 PLUME TRAVEL DISTANCE (KILCMETERS) I
- Reference 7.
vooTLs PLUME DEPLETION EFFECT FOR 100-METER RELEASES
- Georgia Power mI. dr*',"$o*'u"ET aAna etAaT (Letters en te pasquiti Stability class)
FIGURE 2.3-5
*** VEGP 0DCM REV 4 7/30/87-. 2.3-13
10-3 l 10-4 \ <
\
\ , 4-I. m ' H %w l $ \ l e 'N I $ % w \ E % c \ 5(
$ 10-5
;;: A N E A O
b \ Q A
\
l 5 % l 5 \ E \ j 10-6
\
l l 10-7 0.1 1.0 10.0 100.0 200.0 PLUME TRAVEL DISTANCE (KILOMET ERS) i RELATIVE DEPOSITION FOR GROUND-LEVEL VOGTLE RELEASES a Georgia Power n [,'u7,"$o**u"uir ;"""' (Ali Atmospheric stability classes) FIGURE 2.3-6
*
- VEGP ODCM REV 4 7/30/87 2.3-14
l j 10-3 !
, ,, , . , , . . . . , ', l
. , , , , , i , ,.. . , i eiii j i e i si ti i 6 ! l l l 6 ii Ii i !
ll l l 1 UNSTABLE (A,B,C) 10-4 Al !'I!l ' g ,' ,%, s . ,, 1 m ,
- f , i i i x,,,, . .
1
= , i i i mi eh w
! i
/ \\ NEUTRAL w
/ NN ss i I
Ill w w a: z I , NEUTRAL (D) i gs N I i 8 10-5 I I IIll \i N STABLE h I 3 9 % I X Q ,/ s 4 i 1 . 6 Y XI 6 i . i Q. il 8 ,e ' ' if Y A! i i y / i i /> NY' iX i i w /t i I
/ N'.N \ l I
$ /I
/ X i 17N11 2
=
/ / hs h STABL II .
N N 10-6 t i i t , E (E,F,G) , dl l
-l 6 ' . ,
/ , .
Al I i i / i f s t . . I i ! i 6 / i i i ! i f i / , ii I I I I ' l lill I / , IF l . / l l l 10-7 J 0.1 1.0 10.0 100.0 200.0 j l i l PLUME TRAVEL DISTANCE (KILOMETERS) J l
- Reference 7.
1 l voGTLE RELATIVE DEPOSITION FOR 30-METER REl. EASES
- Georgia Powerkh (Letters Denote Pasquil1 Stability C1 ass)
ELECTRIC GENERATING PLANT ' unit uno unit 2 FIGURE 2.3-7 VEGP ODCM REV 4 7/30/87 2.3-15 1
i j i 104
, , i .
e i i . .I , i i i e 4 e , i l l } 0 I l 1 ( I I i if i i i i j i i iI i i i j ii I jm UNSTABLE ( A,B,C) l ' l1I [ ' k l ll
/ N A I
i f f 10-5 / NEUTR AL (D) %
/ , / ,, % i -
g / f , , ef j , i i, 4i i i
.i,,..x i e ii %#
6 i e i! i, e y i i
> / i i/ NNI 6 i iii
$ I/ \ IM UNSTABLE 5 / \l NI ,
! NEUTRA \
s / N N i l@ , w ,a
+ , , / .
g . , , , , , , , , . . f ; o Q-
' f '
i i
' '! ' ' '/ ' I i/ i i i I i f i j
; l/ l l I I i ./ !
. il I/ 1 E
a / / )
\
LL8 l C , l l 10-7 STABLE (E,F,G) i 1 l
,i ,
. ,! ,,,,l .
f f l 8 I l [ l a l 6 i i i le i il Ii i
/ l
.I l
/
I 10-8 i 0.1 1.0 10.0- 100.0 200.0 PLUME TRAVEL DISTANCE (KILOMETER $)
- Reference 7 VOCTLE RELATIVE DEPOSITION FOR 60-METER RELEASES *
- aam naut (tetters en te Pasqu111 stability class)
Georgia Power 1 'h'1I"' J'u"'r FIGURE 2.3-8 o2
- VEGP ODCM REV 4 7/30/87 E.3-16
l l l I l 104 1 i i i i e e i, . i i a 6 ii e , e i,, ( i i i i , eiis i i
, i ..
i e i ii:: iiii l l l ll l l l l ll}ll l l 1 UNSTABLE (A,B.C)l . ' l l lll A __ N I
\ N !
l 10-5 3 pQs l "w l
/. e' .
i i
,f , , ! .,i f ,
! iiw , i ..i y
l[ ' l ll [ NEUTRAL (D') $;( 'l' I i/ I I/ NPN I I c: / I/ \ l % s E
/ I
)
V N N Nh I c: (
$ 10-6 , / ,
i:: ! . . . l
- g. i !
r . , ,
, , +' ! ., e: t s i i
o I i e i i II - 6 ' g / 4 f iili! c / / li I g / 1
/ '
ll l 1 P
<: )I I i
I' y STABLE (E,F,G) ; l NO DEPLETION 10-7 l I l
.i 9i o . , , i i
fi 8 3 I i i ie l I4 i i I i .iiei i I t !
/ I I I I il ,
l I l 10-8 0.1 1.0 10.0 100.0 200.0 PLUME TRAVEL DISTANCE (KILOMETERS) !
- Reference 7, i l
1 i VOGTLE RELATIVE DEPOSITION FOR 100-METER RELEASES
- GeorgiaPower A ELECTRIC GENERATING PLANT (letters Denote Pasquill Stability Class) 1 uniTunouniT2 FIGURE 2.3-9
- VEGP ODCM REV 4 7/30/87 2.3-17 3
'2.4 DEFINITIONS OF GASEOUS EFFLUENT TERMS Subsection of Term Definition Initial Use AG = the administrative allocation factor for - 2.1.1 gaseous effluent pathways (unitiess).
BR' = the breathing rate'for individual from l table 2.2-10 (m 3/ year). 2.2.1.2 i b
= the maximum height of the adjadent 2.3.1.1
~
.]
building (m). C, = the monitor response of a noble gas monitor 2.1.1 corresponding to associated grab ) sample radionuclides concentrations. s ' c, = the calculated basic monitor setpoint value. 2.1.1 l (~ c sp
= the actual monitor setpoint which includes 2.1.1 i.
the. calculated basic monitor setpoint ' value plus background. I l c v
= the correction to effective release height' l
l due to low vent exit velocity'(m). 2.3.1.2 i D TB
= the limiting dose rate to the total body of 2.1.1 an individual in an unrestricted area i which is 500 mrem / year.
D = the total body dose rate'at time of release '2.2.1.1 l (mrem / yea r) . l l
=
D s the limiting. dose rate to the skin of an 2.1.1 individual'in an unrestricted area - which is 3000 mrem / year. VEGP ODCM, REV 4 7/30/87 2.4-1 L ____ - -
- - -- 1
Subsection of t Term Definition InitialiUjLe, l_ D s
.= the skin dose rate at time of release 2.2.1.1 (mrem / yea r) .
D = the organ dose rate at time of release 2.2.1.2 (mrem / year). I i DF g = the inhalation pathway dose factor for child 2.2.1.2 age g'roup for organ o and radionuclides 1 (mrem /pCi inhaled) from table 2.2-2.- , D beta
= the air dose due to beta emissions from 2.2.2.1 !
nobie gases (mrad). l D = the air dose due to gamma emissions from 2.2.2.1 noble gases (mrad).
- D = the dose to an organ of individual from 2.2.2.2 l radioiodines, tritium, and radionuclides in particulate form with half-lives greater than eight days (mrem).
l . (DFA ij)a
=
the inhalation dose factor for the ith 2.2.2.2 - i radionuclides for the receptor in age j
- group a (mrem /pC1) f rom tables 2.2-1 l l
l through 2.2-4.
)
l DFG q = the ground plane dose conversion factor for 2.2.2.2
)
radionuclides i (same for all age groups) 1 (mrem /h per pCi/m ) from table 2.2-9.
=
(DFL the organ ingestion dose factor for the 2.2.2.2 ith radionuclides for the receptor in i age group a (mrem /pci) from tables 2.2-5 through 2.2-8. i l VEGP ODCM, REV 4 7/30/87 <.4-2 I
Subsection of Term Definition Initial Use d = the plume depletion factor for all p 2.3.1.1 radionuclides other than noble gases at distance x (unitless). d = the inside diameter of plant vent (m). 2.3.1.2 D = the deposition rate for ground-level 2.3.2.1 9 releases (m_1). l
=
D e the deposition rate for elevated releases 2.3.2.1 (m-I). E = the fraction of release considered to be 2.3.2.1 ground level (unitiess). f = the f raction of the annual intake of fresh 2.2.2.2 leafy vegetation grown locally (dimensionless). l ! = the fraction of annual intake of stored f 9 2.2.2.2 vegetation grown locally (dimensionless). f a the fraction of the year that the cow 2.2.2.3 (or goat) is on pasture (dimensionless). f, = the fraction of the cow (or goat) feed 2.2.2.3 that is pasture grass while the cow or goat is on pasture (dimensionless). F f
=
the stable element transfer coefficient for 2.2.2.3 meat (days /kg) from table 2.2-11. F = the stable element transfer coefficient for 2.2.2.3
, milk (days / liter) f rom table 2.2-11.
VEGP ODCM, REV 4 7/30/87 2.4-3
I I Subsection of Term Definition Initial Use F$ = the momentum flux parameter (m 4 /s 2 ). 2.3.1.2 F = the maximum expected release flowrate 2.1.1 j through a particular release point (ml/s) from table 2.1'-2. I H = the absolute humidity of the atmosphere 2.2.2.2 (gm/m ). h = the effective release height (m). 2. 3.1. 2 1
'h = the height of release point (m). 2. 3.1. 2 l
h = the maximum terrain height between the 2. 3.1. 2 release point and the point of interest (m).
, - . h pr
=
the additional height due to plume rise (m). 2.3.1.2 l I K
=
the total body dose' factor due to gamma 2.1.1 1 emissions from radionuclides 1 (mrem / year per pCi/m ) f rom table 2.1-1. K' = the constant of unit conversion (10 pCi/pci). 2.2.1.2 K" = the constant of unit conversion (8760 h/ year) 2.2.2.2 K'" = the constant of unit conversion (10 gm/kg). 2.2.2.2 L = the skin dose factor due to beta emissions 2.1.1 I from radionuclides 1 (mrem / year per pCi/m3 ) f rom table 2.1-1. M = the air dose factor due to gamma emissions 2.1.1 3 f rom radionuclides 1 (mrad / year per pCi/m ) f rom table 2.1-1. VEGP ODCM, REV 4 7/30/87 2.4-4 _ _ _ _ _ _ _ _ . '_____.____.______m__.___._____ _ _ _ _ _ _ _ _ . _ . _ _ . _ _ ._ _ _ _ _ __. ______.m____ ______
Subsection of Te rm Definition Initial Use
~
N
= the air dose factor due to beta emissions 2.2.2.1 from noble gas radionuclides i (mrad / year per pCi/m ) f rom table 2.1-1.
n = the number of simultaneous gaseous '2.1.5 release pathways. n p = the number of hours meteorological 2.3.1.1 conditions are observed to be in a given wind direction, windspeed class j, and atmospheric stability class' k. N = the total hours of valid meteorological 2.3.1.1 data. P g = the dose parameter for radionuclides i, 2. 2.1. 2 I (mrem / year per pCi/m 3
) for the inhalation pathway.
Q, = the source term for ground-level release 2.1.1
$~
noble gas radionuclides 1 (pCi/s). l Qg = the source term for mixed-mode release - 2.1.1 1 noble gas radionuclides i (pCi/s). 0 = the source term for ground-level release 2.1. 5 noble gas radionuclides i from a specific release point (pC1/s). 0
)
=
the source term for mixed-mode release 2.1. 5 noble gas radionuclides i from a specific release point (pci/s). VEGP ODCM, REV 4 7/30/87 2.4-5
Subsection of Term Definition Initial Use Qj g = the source term for ground-level release 2.2.1.2 radiciodine, tritium, and particulate radionuclides i (uci/s). Qjm = the' source term for mixed-mode release 2. 2.. l . 2 radiciodine, tritium, and particulate radionuclides 1 (uci/s). Qig the cumulative ground-level release of 2.2.2.1 noble gas radionuclides 1 (uCi). Qim = the cumulative mixed-mode release of noble 2.2.2.1 gas radionuclides 1 (uC1). l ~ Ojg = the cumulative ground-level release of 2.2.2.2 l ( radioiodines, tritium, and particulate radionuclides 1 (uC1). him = the cumulative mixed-mode release of 2.2.2.2 radioiodines, tritium, and particulate radionuclides 1 (vC1). Op = the feed consumption rate for cow or goat 2.2.2.3 (kg/ day). q$
= the noble gas source term for the Gaseous 2.1.3.1 Waste Processing System or Containment and 2.1.3.2 purge (uCi/s).
R = the relationship betwee'n monitor response 2.1.1 and the dose rate to the total body for the conditions of the release under consideration. VEGP 00CM, REV 4 7/30/87 2.4-6
)
j
)
l 1 Subsection of Term Definition Initial Use fq R,
= the relationship between monitor response 2.1.1 and the dose rate to the skin for the j conditions of the release under consideration. )
L r = the relationship between monitor response 2.1 3.1 and the dose rate to the total body for Gaseous Waste. Processing System or j containment purge release for the conditions
.]
l of the release under consideration. 1 j l r, = the relationship between monitor response 2.1.3.1 and the dose rate to the skin for ' Gaseous ) Waste Processing System or containment purge release for the conditions of the release under consideration.
/" R = the pathway-specific, individual age- 2.2.2.2 specific, organ dose factor for radionuclides 1, pathway p, organ j, and age group a, (mrem / year per pC1/m ) or (m -mrem / year per uCi/s).
r = the fraction of deposited radionuclides 2.2.2.2 1 retained on vegetation (unitiess). l SF = the safety factor used to introduce a margin 2.1.1 l of conservatism into setpoint' calculations. ] SHF = the shielding factor af forded by structure 2.2.2.2 (unitiess). S = the stability parameter (s~ ). 2 . 3.1. 2 t = the exposure time.for radioactivity 2.2.2.2 deposited on ground (seconds). ; VEGP ODCM, REV 4 7/30/87 2.4-7 ,
Subsection of i Term Definition
- Initial Use i t
g
= the time between harvest of leafy- 2.2.2.2 -
vegetation and consumption (seconds). t = the time between harvest of stored 2.2.'2.2 vegetation and consumption (seconds). ' t g = the transport time from feed to receptor 2.2.2.3 for stored feed (seconds). t f
= the transport time from feed to receptor 2.2.2.3 for pasture grass (seconds). ']
l U ap
= the receptor's milk (liters / year) or meat 2.2.2.3 l (kg/ year) consumption rate for age group I a f rom table 2.2-10. i /~ U =- the consumption rate of stored vegetation 2.2.2.2 as ,
by the receptor in age grdup a (kg/ year) i l f rom table 2.2-10. l l J ! U = the consumption rate of fresh leafy 2.2.2.2 vegetation by the receptor in age group a
]
(kg/ year) f rom table 2.2-10. u p = the wind speed (midpoint of wind speed 2.3.1.1 class j) at ground level during atmospheric j stability class k (m/s). I U = the 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/s). l l VEGP 00CM, REV 4 7/30/87 2.4-8 i j
Subsection of
- Term Definition Initial Use Wdp = the pathway-dependent relative dispersion 2.2.2.2 or deposition for ground-level releases at the lo':ation 'of the critical receptor.
~
,. Whp = the pathway-dependent relative dispersion 2.2.2.2 or deposition for mixed-mode releases at the location of the critical receptor. x = the distance from release point-to-point 2.3.1.1 of interest (meters). l Y y
= the vegetation areal density (kg/m ). 2.2.2.2 Y
p
= the agricultural productivity by unit area 2.2.2.3 of pasture feed grass (kg/m2 ).
! Y = the agricultural productivity by unit area 2.2.2.3 l l. ' 5 of stored feed (kg/m2 ). l l l (x/Q)G
= the highest annual average relative 2.1.1 t
concentration for a ground-level release ' 3 type (s/m ). j (x/0)g = the highest annual average relative 2.1.2 l concentration for a mixed-mode release type (s/m ). (X/Q') = the annual average relative concentration for 2.2.2.2 location of c ntrolling (critical) receptor for inhalation and all tritium pathways for a ground-level release type (s/m ). VEGP ODCM, REV 4 7/30/87 2.4-9 t_ _ - - -_ _ _ _ _ _ _ _ - - _ _ _ _ - _ _ _ _ _ _ _ _ _
Subsection of Term Definition Initial Use-f- (X/Q')g = the annual average relative concentration 2.2.2.2 for location of controlling (critical) receptor for inhalation and all tritium pathways for a mixed-mode release type (s/m ). A = the decay constant for the ith 2.2.2.2 radionuclides (s-l). A = the decay constant for removal of activity 2.2.2.2 on leaf and plant surfaces by
~
weathering (s ). Eg = the vertical standard deviation of the 2.3.1.1 plume concentration distribution considering the initial dispersion within the building wake (meters). 1. og = the vertical standard deviation of the 2.3.1.1 i plume (in meters), for a given-i distance under the stability category k indicated by AT/a2 from figure 2.3-1. , aT/a2 = the vertical temperature gradient used to 2.3.1.1 determine the atmospheric stability category (*C/100m or "F/100 f t) . - I i X 3y
= the concentration of radionuclides'i for 2.1.1 the particular vent release pathway l under consideration (vCi/ml).
)
0949n VEGP 00CM, REV 4 7/30/87 2.4-10 L _ 1
2.5 GASEOUS RADWASTE TREATMENT SYSTEMS I l i-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
]
(Reference 5).
.i l
l l
- l i
l ( i j i I l 1 i j I1 i Nh"00CM,REV4 7/30/87 2.5-1
Radioact nitor p y M via Auxiliary Building ventilation System E j Catalytic ' W Aecombiner To Chemical Volume
' n Control Tank .
f -- C e r jn,dj s I Package I- 3 I i . . 1' I I I I
- To Waste Gas Decay ig Tank Header L _ _ _ _ _ _. _ _ /yL _ _ _ _ /r s_ _ _l
, I v vo Waste Gas : M ste h s
.sy Tank d
(Seven per Unit) (Te Shared) i 46
/ volume Control /sv Unit 2 Wasta
( N Tank Purge N Gas Decay Tanks
/ Recycle Evaporator N vent Cr..idenser
/ Waste Evaporator {
N vent Condenser i
/ Recycle Holdup l N Tank Eductor
/ Reactor Coolant N Drain Tank
- Dotted line operational between 20 and 100 psig l
i NOTE: This is typical of both units. However, Unit 2 GWPS releases via Unit 1 plant vent. i t I voGTts ELECTRIC GENERATING PLANT GASEOUS WAFE PROCESSING SYSTEM GeorgiaPower uu,T , ,uo ou,T , FIGURE 2.5-1 033 9 VEGP ODCM REV 4 7/30/87 2.5-2
Plant Vent Radioactivity Monitor RE12442A,8,C
= 1 3
HEPA HEPA HEPA CF c7 CF . . I HEPA HEPA HEPA HC HC Radioactivity Auxiliary O Monitor Building RE0039A ME Radioactivity Monitor RE2565A,B.C l , From Waste Gas Processing Fuel Handling ! Building (Shared)* l Area and System l l Reactor Containment i Building l . I i HEPA -High Effici e ncy Particulate Air Filter CF -Activated Charcoal Filter HC -Heating Coil ME -Moisture Eliminator
- Prior to treatment by the Fuel Handling Building Ventilation Exhaust Treatment System, exhaust from Unit 1 Spent Fuel Pool Area is monitored by ARE25328 and ARE25338; exhaust from Unit 2 Spent Fuel Pool Area is monitored by ARE2532A l and ARE2533A.
NOTE: This is typical of both units. However, all Gaseous Waste Processing System and Fuel Handling Building releases are via Unit 1 plant vent. vooTLs VENTILATION EXHAUST TREATMENT SYSTEM Georgia Powerkh (PlantVent) ELECTRIC GENERATING PLANT unit uno unit 2 FIGURE 2.5-2 VEGP ODCM REV 4 7/30/87 2.5-3 l
Turbine Building Vent Radioactivity Monitor RE12839A,B.C
= =
o
-HEPA HEPA l
l l CF CF' l I HEPA HEPA l HC HC l DE DE [ NO NC [NO NC l Steam Jet Steam Packing Air Ejector Exhauster HEPA -High Efficiency Particulate Air Filter CF -Activated Charcoal Filter HC -Heating Coil DE -Demister NO -Normally Open NC -Normally Closed NOTE: This is typical of both units. l voGTLE VENTILATION EXHAUST TREATMENT SYSTEM Georgia Power Em k ELECTRIC GENERATING PLANT UNIT 1 AND UNIT 2
'(Turbine Building)
FIGURE 2.5-3
' " VEGP ODCM REV 4 7/30/87 2.5-4
i l 4 i Radwaste Solidification Building Vent Radioactivity Monitor ARE0026A,B.C ' HEPA HEPA l l CF' CF HEPA, , I I HEPA HEPA , l l n PF HC o g Low Contamination-
/.. PF Areas Volume Reduction )'
Process Off-gas Process Area HEPA -High Efficiency Particulate Air Filter CF -Activated Charcoal Filter PF -Prefilter HC -Heating Coil NOTE: This is comon to both units. i
~
voorts
'I VENTILATION EXHAUST TREATMENT SYSTEM ELECTRIC GENERATING PILANT (Radwaste Solidification Building)
Georgia Power UNIT 1 AND U911T 2 ' FIGURE 2.5-4
** VEGP ODCM REV 4 7/30/87 2.5-5
3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Radiological environmental sampling and monitoring locations are described in ll table 3.0-1 and shown on maps in figures 3.0-1, 3.0-2, 3.0-3, and - 3.0-4 as i i
, required by Technical Specifications 3.12.1 and 4.12.1. i
{; l i i l Y l t VEGP CDCM, REV 4 7/30/87 3. 0-1 i
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- D / .,
p> . p <*3 c TABLE 3.0-1 (SHEET 1 0F 2) t n RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS I i l, LOCATJGi8 DESCRIPTIVE DIRECTION DISTANCE SAMPLE f MUNCER > LOCATION (MILES) TYPF_ l i i i 'i Hancock Landing Road N 1.1 D
- I l 2' River Bank NNE 0.8 0 j Discharge Area 0.6 l R NE A l 3 River Bank NE 0.7 0 I f 4 River Bank ENE 0.8 D l l 5 River Bank E 1.0 0 ;
6 Plant Wilson ESE 1.1 D 1 7 Simulctor Building SE 1.5 D,V,A . 8 River Road SSE 1.1 0 9 River Road S 1.1 D 10 Met Tower SSW 0.8 A
'10 River Road SSW 1.1 D 11 River Road SW 1.2 0 f 12 River Road WSW 1.1 0,A i 13 River Road W 1.3 0 14 River Road WNW 1.8 0 15 Hancock Landing Road NW 1.5 D,V 16 Hancock Landing Road NNW 1.4 D,A {
17 Savannah River Plant l r River Road N 5.4 0
- 18 Savannah River Plant l l 0 Area NNE 5.0 0 19 Savannah River Plant Road A.13 NE 4.6 0 20 Savannah River Plant Road A.13.1 ENE 4.8 'D 21 Savannah River Plant Road A.17 E 5.3 0 22 River Bank Downstream of Buxton Landing ESE 5.2 0 23 River Road SE 4.7 0 24 Chance Road SSE 4.9 0 25 Chance Road and Highway 23 S 5.2 0 26 Highway 23, mile 15.5 SSW 4.6 0 27 Highway 23, mile 17 SW 4.8 0 28 Claybon Road WSW 5.0 0 29 Claxton-Lively Road W 5.0 D 30 Ben Hatcher Road WNW 4.7 0 31 River Road at Allen's Church Fork NW 5.0 0 32 River Bank NNW 4.8 D 33 Nearby Residence SE 3.3 0 34 Girard Elementary School SSE 6.3 0 35 Girard SSE 6.6 0,A 36 Waynesboro WSW 15.0 0,A 37 Substation (Waynesboro) WSW 17.5 D.V (North Side of Road)
VEGP ODCM, REV 4 7/30/87 3.0-2
1 i TABLE 3.0-1 (SHEET 2 OF 2) RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS LOCATION DESCRIPTIVE DIRECTION DISTANCE SAMPLE NUMBER LOCATION (MILES) TYPE l 38 Substation (Waynesboro) WSW 17.5 D (South Side of Road) 43 Employees Recreation Area SW 2.2 0 North Augusta Water 80 Treatmer,t Plant NNW 23.6 W 81 Savannah River (mile 153.1) N 2.2 R,S,F(2,3) 82 Savannah River (mile 151.2) NNE 0.8 R,S(3) 83 Savannah River (mile 150.4) ENE 0.8 R 84 Savannah River (mile 149.5) ESE 1.6 R S(3) 85 Savannah River (mile 146.7) ESE 5.0 R,F(2) 87 Beaufort-Jasper Water Treat-ment Plant; Beauf' ort, S.C. SE 84 W 88 Cherokee Hill Water Treatment Plant; Port Wentworth, Ga. SSE 82 W 91 Colemans WNW 2.8 M 98 W. C. Dixon Dairy SE 9.8 M 99 Boyceland Dairy W 24.5 M TABLE NOTATION: (1) Sample Types A - Airborne Radioactivity D - Direct Radiation ; F - Fish M - Milk R - River Water S - River Shoreline Sediment W - Drinking Water (at water treatment plant) V - Vegetation (2) These are approximate locations for fish sampling. It is generally necessary to cover a stretch of river up to five miles to obtain an adequate fish sample. I (3) These are approximate locations for sediment sampling. High water may I sometimes cause an otherwise suitable location for sediment sampling to j be unavailable. . VEGP ODCM, REV 4 7/30/87 3.0-3
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I E NORTH AUGUSTA WATER TREATMENT PLANT SOUTH CAROLINA SAVANNAH RIVER PLANT VEGP 5
> l Canal to Supply River Water to Beaufort Beaufort 4esper County Water Treatment Plant GEORGlA 1SEAU ,
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km W 0 10 20 30 4)b CHEROKEE HILL 4 p $ WATER TREATMENT b PLANT 4 (PORT WENTWORTH) b SAVANNA T O vocTLE DRINKING WATER STATIONS ELECTRIC GENERATING PLANT Georgia Power h UNIT 1 AND UNIT 2 FIGURE 3.0-4
**
- VEGP ODCM REV 4 7/ 30/87 3.0-7
l 4.0 TOTAL DOSE DETERMINATIONS l l l Technical Specification 3.11.4 addresses the requirements of 40 LTR 190 and 10 CFR 20.105(c), which pertain to limitation of annual doses to a member of the public f rom 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 l l determinations. ] l l l For the purpose of implementing Technical Specification 3.11.4, total dose
]
determinations will be made by calculating doses due to liquid effluents in I accordance with Technical Specification 3.11.1.2; by calculating doses due to ) gasecus ef fluents in accordance with 3.11.2.3; and by combining direct radiation doses based on direct radiation measurements, or calculations, with i these effluent doses to determine total dose to a real individual. Methodology for calculating individual doses due to liquid ef fluents was presented in subsection 1.2. Methodology for calculating individual doses due to gaseous effluents was presented in subsection 2.2.2.2. l l l I VEGP 00CM, REV 4 7/30/87 4. 0-1 l
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 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 Ccmpany, but individuals working at Plant Wilson are not directly associated with Plant Vogtle. Therefore, those-individuals are considered in this dose determination as a precautionary measure.) The annual average atmospheric dispersion and deposition values for these two locations and the expected occupancy factors, by an individual during the year, are as follows: Estimated Occupancy Factor (by Location X/0(s/m3 ) 0/0(m-2) an individual durina a year) Visitors Center 2.53E-5 1.76E-8 0.00046 (4 hours) Plant Wilson 5.37E-u 3.g0E-9 0.228 (E000 hours) In the event that any limit of Technical Specification 3.11.2.2 is exceeded, an assessment will be performed considering direct radiation dose to an individual resulting from submersion in the plume. This assessment will take into consideration the annual average dispersion parameters and.the estimated occupancy factor stated above, or a more precise value if available, for the locations of interest. In the ' event that any limit of Technical Specification 3.11.2.3 is exceeded, an assessment will be performed considering the dose to an individual due to inhalation of airborne radioactive materials suspended in the plume and due to direct radiation from radioactive materials deposited on the ground. This assessment will take into consideration the annual average dispersion and VEGP 00CM, REV 4 7/30/87 5.0-1
i 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 inhalation and ground plane or 0.004 mrem to the total body due to direct radiation from the plume. Likewise, potential doses to an individual at Plant Wilson are not expected to exceed 5.20 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
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Plant Wilson is based on a standard 40-h work week, assuming that an individual is assigned to the facility for the entire year.
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l I l l l l l I VEGP ODCM, REV 4 7/30/87 5.0-2 L___----___ J
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 equivalen.t 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 follows: Sample Medium Analyses Performed Air filters Gross beta; gamma isotopics Water H-3; gross beta; gamma isotopics [ l Milk I-131; gamma isotopics A summary showing the results obtained from Plant Vogtle's participation in the Crosscheck Program will be included in the Annual Radiological Environmental Surveillance Report as required by Technical Specification 4.12.3. 0948n VEGP 00CM, REV 4 7/30/87 6. 0-1
1 l REFERENCES r l
- 1. J. S. Boegli, R. R. Bellamy, W. L. Britz, and R. L. Waterfield,
" Preparation of Radiological Ef fluent Technical Specifications for j Nuclear Power Plants," NUREG- 0133, October 1978.
I
- 2. " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose nf Evaluating Compliance with 10 CFR 50, l Appendix I," U. S. NRC -Regulatory Guide 1.109, March 1976.
1
- 3. " Calculation of Annual Doses to Man from Routine Releases of Reactor l Effluents for the Purpose of Evaluating Compliance with 10 CFR 50, I Appendix I," U. S. NRC Regulatory Guide 1.109. Rev.1, Oc tober 1977.
- 4. Vogtle Electric Generating Plant Units 1 and 2 Environmental Report - l Operatina License Stage, Georgia Power Company.
- 5. Vogtle Electric Generating Plant Units 1 and 2 Final Safety Analysis j Report. Georgia Power Company. l l
- 6. " 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, March 1976.
- 7. "Methuds for Estimating Atmospheric Transport and Dispersion of Gaseous {
Effluents in Routine Releases from Light-Water-Cooled Reactors," l (_ U.S. NRC Regulatory Guide 1.111, Rev.1, July 1977. t
- 8. " Estimating Acquatic Dispersion of Effluents from' Accidental and Routine l Reactor Releases for the Purpose of Implementing Appendix I," U. S-. NRC Regulatory Guide 1.113, Rev.1, April 1977.
- 9. Vogtle Nuclear Plant Units 1 and 2 Waste Water Effluent Discharge j Structure Plume Analysis, Georgia Power Company, April 1981. i l
- 10. " Direct Communications with Water Resources Division," U. S. Geological {
Survey, U. S. Department of Interior, February 1985. '
- 11. W. R. Stokes, III, T. W. Hale, J. L. Pearman, and G. R. Buell, Water Resources Data. Georgia. Water Year 1983, U. S. Geological Survey, Water !
- Data Report GA-83-1, June 1984. .
- 12. Vogtle Electric Generating Plant Land Use Survey - 1986, Georgia Power Company, April 1986, i
- 13. Letter to Georgia Power Company f rom Pickard Lowe and Garrick. Inc. ,
Washington, D.C., December 16, 1986.
- 14. Kahn, Bernd, et. al, "Bioaccumula; ion of P-32 in Bluegill and Catfish,"
NUREG/CR-3981, February 1985.
- 15. Sagendorf, et.al, "X0QD00: Computer Program for the Meteorological Evaluation of Routine Ef fluent Relecses at Nuclear Power Stations,"
NUREG/CR-2919, September 1982. VEGP 00CM, REV 4 7/30/87 0948n , ( _ _ _ _ _ _ _}}