ML20094K172
| ML20094K172 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 12/31/1991 |
| From: | GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20094K166 | List: |
| References | |
| PROC-911231, NUDOCS 9203190222 | |
| Download: ML20094K172 (220) | |
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-ENCLOSURE 4 i a'
' 'V0GTLE ELECTRIC-GENERATING PLANT REQUEST.FOR TES:NICAL SPECIFICATION CHANGES
. RESPONSE'TO GENERIC LETTER 89-01 >
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. RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATION CHANGES
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L l 9 i t l (. \ 0FFSITE DOSE CALCULA(10N MANUAL
- l. FOR i-GEORGIA POWER COMPANY V0GTLE ELECTRIC GENERATING PLANT DRAFT 1991 ,
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i l l INTRODUCTION l The Offsite Dose Calculation Manual is a supporting oocument of the Technical Specifications. As such,-the ODCM describes the methodology and parameters to be _used in _the calculation of offsite doses due to radioactive liquid and gaseous effluents and in the calculation of liquid and gaseous )ffluent monitoring instrumentation alarm / trip setpoints. The ODCM contains schematics of liquid and gaseous radwaste effluent treatment systems, which include release points to. unrestricted areas. It includes a list and maps indicating l specific sample locations for the radiological environmental monitoring program. It also includes the radioactive effluent controls and radiological environmental monitoring programs required by section 6.7.4 of the Technical , Specifications and descriptions of the information that should be included in the' Annual Radiological Environmental Surveillance and Semiannual Radioactive Effluent Release Reports required by specifications 6.8.1.3 and 6.8.1.4. 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 ODCH. O i d i l l l^ . O V -- l VEGp ODCM, REV 8_ Draft
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DISTRIBUTION LIST O RECIPIENT- TITLE /l0 CATION. COPY NO. Shan Sundaram Chemistry Department 1 Plant Vogtle A. S. Parton Chemistry Department 2
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Plant Vogtle , J. B. Sills Chemistry Department 3 Plant Vogtle R.-C,. Hand Nuclear Operations - Administration _ 5 Bin 502, ISEG Plant Vogtle i Brent Quick Supervisor, Document Control 6 Plant Vogtle , W. C. Carr Manager, Environmental Services 7 - 10 Bin 8064, Building 40 i Southern Nuclear Operating Co.,B' ham,AL. A. G. Rickman Nuclear Safety and Compliance 11-
-Administration Building Plant Vogtle B. L. Maulsby Supervisor, Environmental Center 12 Georgia. Power Company, Decatur, GA J. S. Hempstead Supervisor, Technical Writing 14 Bin B847, 800 Building Southern Company Services, B' ham, AL
.J. A. Bailey . Manager, Licensing, Vogtle 1:
Bin- 8042, Building 40 Southern Nuclear Operating Co.,B' ham,AL. J. L. Wilcox Plant Vogtle W. C. Ramsey Manager, Nuclear P1 ant Support, Vogtle 18 Bin B232, Building 42 Southern Company Services, r' ham, AL-R. T.~' Wood Plant Farley. 19
-A. E. Cardona Vogtle Nuclear Administrative 20 Bin B042, Building 40 Southern Nuclear Operating Co.,B' ham,AL.
O l VEGP ODCM, REV 8 Draft acm L
OFFSITE DOSE CALCULATION MANUAL REVISION LOG Revision No. Q31g i '!f*?
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i 19' 8 raft O 4 O
TABLE OF CONTENTS (3 X,./ gg 1.0 L10VID EFFLUENTS 1.0 1.1 LIQUID EFFLUENT MONITOR SETPOINTS 1.1-1 1.1.1 Liquid Waste Processing System Effluent Monitor 1.1-1 1.1.1.1 Monitor Setpoint Calculation Methodology 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 'u? Are To Be Released at a Time 1.1-10 l.1.2 Steam Generator Blowdown Effluent Radioactivity Monitor; Turbine Building Drain Effluent Radioactivity Monitor 1.1-13 1.1.3 Nuclear Service Cooling Water System Effluent Radioactivity Monitor 1.1-14 1.2 DOSE CALCULATION F0P LIQUID EFFLUENTS 1.2-1 i 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 LIMITS OF OPERATION 1.5-1 1.5.1 Concentration in Liquid Effluents 1.5-1 1.5.1.1 Exceeding the Limits 1.5-1 1.5.1.2 Sampling and Analysis 1.5-1 1.5.2 Dose Due to Liquid Effluents 1.5-3 1.5.2.1 Calculated Dose That Exceeds Limits 1.5-4 1.5.2.' Requirements for Calculations 1.5-4 1.5.2.3 Bases for the Limits 1.5-4 l O l I -VEGP ODCM, REV 8 Draft i
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1.5.3 Liquid Radwaste Treatment System 1.5-5 1.5.3.1 Dose Limits for Operation of the Liquid Radwaste Treatment System 1.5-5 1.5.3.2 Prcjected Doses That Exceed Limits 1.5-6 1.5.3.3 Bases for Projecting Doses 1.5-6 1.5.4 Liquid Effluent Monitoring Instrumentation 1.5-7 1.5.4.1 Nonconservative Liquid Monitor Setpoint and ACTIONS 1.5-7 1.5.4.2 Liquid Monitor Operability 1.5-7 ' 1.6 LIQUID WASTE PROCESSING SYSTEM AND LIQUID DISCHARGE PATHWAYS 1.6-1 2.0 GASE0US EFFLUENTS 2.0-1 2.1 GASE0US EFrLUENT MONITOR SETPOINTS 2.1-1 2.1.1 !! nit 1 Turbine Building Vent, Unit 2 Turbine 0 Building Vent, and 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 " 2.1.5 Determination of Allocation factor, AG 2.1-10 2.1.6 Particulate Effluent Monitor Setpoints 2.1 2.2 GASE0US EFFLUENT DOSE RATE AND DOSE CALCULATIONS 2.2-1 2.2.1 Dose Rates at or Beyond Site Boundary 2.2-1 2.2.1.1 Dose Rates Due to Noble Gases 2.2-1 2.2.1.2 Dose Rates Due to I-131, 1-133, 4 Tritium, and Particulates 2.2-2 . VEGP ODCM, REV 8 Draft ii
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l TABLE OF CONTENTS (Continued) O ped 1 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.Z' 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 HETEOR0 LOGICAL MODEL 2.3-1 2.3.l~ Atmospheric Dispersion 2.3-1 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 2.3-5 r 4 2.3.2.1 Ground-Level Releases 2.3-5 2.3.2.2 Mixed-Mode-Releases- 2.3-5 2.4 DEFINITIONS OF GASEOUS EFFLUENT TERMS 2.4-1 2.5 LIMITS OF OPERATION 2.5-1 2.5.1 - Gaseous Effluents. Dose Rate 2.5-1 2.5.1.1 Exceeding Gaseous Effluent Dose Rate Limits ' 2.5-1 2.5.1.2 Sampling and Analysis of Gaseous Effluents 2.E 1 2.5.2 Noble Gas Air Dose 2.5-5 2.5.2.1 Exceeding the Noble Gas Air Doses 2.5-6 2.5.2.2 Cumulative Dose Calculation Requirements 2.5-6 2.5.2.3 Basis for Noble Gas Air Doses 2.5-6 O VEGP ODCM, REY 8 Draft lii 1
, . - . . - n - a .=-t m - J V TABLE OF_. CONTENTS (Continued)
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2.5.3 Dose to a Member of the Public from Tritium, Radiciodines, and Particulates 2.5-7 2.5.3.1 Exceeding the Dose Limits 2.5-7 2.5.3.2 Cumulative' Dose Calculation Requirements 2.5-8 2.5.3.3 Basis for Tritium, Radioiodine, and Particulate Dose Limits 2.5-8 2.5.4 Gaseous Radwaste Treatment System Operation 2.5-9 2.5.4.1 Exceeding the. Dose Limits for Operation
.. of the Gaseo!.s Waste Processing System 2.5-9 2.5.4.2 Requirement for Projecting Doses Due to Gaseous Releases 2.5-10 2.5.4.3 Basis for the Operability of the Gaseous 2.5-10 Waste Processing System 2.5.5 Dose to the Public from the Uranium Fuel Cycle 2.5-10 ,
2.5.5.1 Cumulative Dose Calculation Requirements 2.5-11 2.5.5,2 Conditions Required for Cumulative Dose Calculations 2.5-11
- 2.5.5.3 Exceediq the Dose Limitations 2.5-12 %.)
2.5.6 Gaseous Effluent Monitoring Instrumentation 2.5-12 2.5.5.1 Nonconservative Gaseous Effluent tionitor Setpoint and ACTIONS 2.5-13 2.5.6.2 Gaseous Effluent Monitor Operability 2.5-13
- 2.6 GASEOUS RADWASTE TREATMENT SYSTEMS 2.6-1 1
3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 3.0-1 3.1 Limits of Operation 3.1-1 3.1.1 Conduct of the Radiological Environmental
' Monitoring Program - 3.1-1 3.1.1.1 Reporting of Abnormal Conditions 3.1-1 3.1.1.2 - Collection and Analysis of Samples - 3.1-2 3.1.1.3 Basis for the Radiological Environmental
' . Monitoring Program _ 3.1-3 3.1.2 Land Use Census 3.1 3.1.2.1 Identification of. New Critical Locations 3.1-4 3.1.2.2 Conduct of Census 3.1-5
- l. 3.1.2.3 Identification of Changes 3.1-5 VEGP ODCM, REV 8 Draft iv a
JABLE OF CONTENTS (Continued)
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g 3.2 Interlaboratory Comparison Program 3.2-1 3.2.1 Requirements 3.2-1 3.2.2 Deviations 3.2-1 3.2.3 Summary of Results 3.2-1 3.2.4 Basis 3.2-1 i 4.0 TOTAL DOSE DETEj@LNATIONS 4.0-1 5.0 POTENTIAL DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE SITE BOUNDARY 5.0 { 6.0 REPORTS 6.1-1 6.1 Annual Radiological Environmental Surveillance Report 6.1-1 6.1.1 Due Date 6.1-1 6.1.2 Evaluation Content Requirement 6.1-1 ' 6.1.3 Data Content Requirement 6.1-1 6.1.4 -Program Content Requirement 6.1-2 6.2 Semiannual Radioactive Effluent Release Report 6.2-1 6.2.1 Gaseous and Liquid Effluent Summaries 6.2-1
=6.2.2 Meterological Data Summary. 6.2-1 6.2.3 - Radiation Doses .to the Public 6.2-2 6.2.4 Unplanned Releases 6.2-3 16.2.5 Changes to the PCP and the ODCM 6.2-3 ,
6.2.6 Inoperable Liquid or Gaseous Effluent Monitoring Instrumentation 6.2-3 6.2.7 Major Changes to Liquid, Gaseous, and Solid Radwaste Treatment Systems 6.2-4 s t U VEGP ODCM, REY _8_ Draft v
l LIST OF TABLES O TABLE TITLE - PAGI 1,2-1 Bioaccumulation factors 1,2-4 1.2-2 Adult Ingestion Dose Factors 1.2-5 1.2-3 Site-Related Ingertion Dose Factors (for Freshwater Fish and Drinking Water Consumption) 1,2-8 1.5-1 Liquid Effluent Monitoring Instrumentation 1.5-8 2.1-1 Dose Factors for Exposure to a Semi-Infinite Cloud
. of Noble Gases 2.1-13 2.1-2 Gaseous Release Points Flowrates 2.1-14 2.2-1 Inhalation Dose Factors for Infant 2.2-18 2.2-2 Inhalation Dose Factors for Child 2.2-21 2.2-3 Inhalation Dose Factors for Teunger 2.2-24 2.2-4 Inhalation Dose Factori. for Adults 2.2-27 2.2 Ingestion Dose Factors for Infant 2.2-30 2.2-6 Ingestion Dose Factors for Child 2.2-33 2.2-7 Ingestion Dose Factors for Teenager 2.2-36 2.2-8 Ingestion Dose Factors for Adults 2.2-39 2.2-9 External Dose Factors for Standing on Contaminated Ground 2.2-42 2.2-10 Individual Usage Factors 2.2-44 2,2-11 Stable Element Transfer Data 2.2-45 A)'2.2-12
%" Controlling Receptor 2.2-46 2.2-13 Site-Specific (or Default) Va?=s to Be Used in Pathway Factor Calculations 2.2-47 2.2-14 Potential Receptor Locations and Pathways 2.2-51 2.2-15 DHpersion and Deposition Parameters 2.2-52' 2.3-1 Terrain Elevation above Plant Grade Wind Direction 2.3-7 from Plant to Receptor 2.5-1 Gaseous Effluent Monitoring Instrumentation 2.5-14 3.0-1 Radiological Environmental Sampling Locatiens 3.0 3.1-1 Radiological Environmental Roni.oring Porgram _ 3.1-6 3.1-2 Reporting Levels for Radioactivity Concentrations in 3.1-12 Environmental Samples 3.1-3 Detectior. Capabilities for Environmental Sample Analysis 3.1-13 5.0-1 Location-Specific Parameters for Locations inside the Site Boundary 5.0-3 O VEGP ODCM, REV 8 Draft vi
LIST OF FIGURLE FIGURE TIT ([ P691 1.6-1 Liquid Waste Processing System (Unit 1) 1.6-2 1.6-2 Liquid Waste Processing System (Unit 2) 1.6-3 1.6-3 t.iquid Discharge Pathways 1.6-4 2.3-1 Vertical Standard Deviation of Material in a Plume 2.3-9 2.3-2 Plume Depletion Effect for Ground-Level Releases 2.3-10 k' 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 l 2.3-5 Plume Depletion Effect for 100-meter Releases 2.3-13 L 2.3-6 Relative Deposition for Ground-Level Releases 2.3-14 2.3-7 Relative Deposition for 30-meter Releases 2.3-15 2.3-3 Relative Deposition for 60-meter Releases 2.3-16 2.3-9 Relative Deposition for 100-meter Releases 2.3-17 2.6-1 Gaseous Waste Processing System 2.6-2 2.6-2 Ventilation Exhaust Treatment System Unit 1 (Plant Vent) 2.6-3 { 2.6-3 Ventilation Exhaust Treatment System Unit 2 (Plant Vent) 2.6-4 2.6-4 Ventilation Exhaust Treatment System (Turbine Building) 2.6-5 2.6-5 Ventilation Exhaust Treatment System (DAW Process Building) 2.6-6 l 3.0-1 Terrestiial Stations Hear Site Boundary 3.0-5 3.0-2 Terrestrial Stations Beyond Site Boundary out to Approximately 5 Miles and Aquatic Stations 3.0-6 3.0-3 Terrestrial Stations Beyond 5 Miles 3.0-7 3.0-4 Drinking-Water Stations 3.0-8 O VEGP ODCM, REV 8 Draft vii
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A 1.0 L10VID EFFLUENTS The Vogtle Electric Generating Plant is located on the west bank of the Savannah River approximately 151 river miles from the Atlantic Ocean. _There are two pressurized water reactors on the site. Each unit is served by a separate liquid waste processing system; however, certain components are shared between the two systems. All liquid radwastes treated by the liquid waste processing system are collected in waste monitor tanks for sampling and analysis prior to release. The 5000-gallon waste monitor tanks are recirculated for a minimum of 30 minutes, and the 20,000-gallon waste monitor tanks are recirculated for a minimum of 45 minutes. This mixing method assures that a representative sample can be taken from the tank. Releases from the waste monitor tanks are to the discharge line from the blowdown sump to the Savannah River. The blowdown sump receives input from the waste water retention basins, turbine plant cooling tower blowdown, and nuclear service cooling tower blowdown. Additional dilution water is available from the cooling tower makeup water bypass line. Although no significant quantities of radioactivity are expected in the L nuclear service cooling water, the steam generator blowdown processing system r or the turbine building drain system, these effluent pathways are monitored as a precautionary measure. The monitors serving the latter two effluent . pathways provide for_ automatic termination of release from these systems in th9 event radioactivity is detected above predetermined levels. These two systems discharge to the waste water-retention basin. Sampling and analysis-of releases via these effluent pathways must be sufficient to assure the dose limits specified in subsection 1.5.2 are not exceeded. Section 1.0 of the ODCM describes the methodology for calculating monitor L setpints and individual doses due to liquid effluents released from Plant li -Vogtle to the Savannah River.- - Schematics of the liquid waste processir.g systems are- presented in figures 1.6-1 and 1.6-2. Liquid discharge pathways are shown in figure 1.6-3. O VEGP ODCM, REV 8 Draft 1.0-1
1.1 LIQUID EFFLUENT MONITOR SETPOINTS G U Liquid monitor setpoint values calculated in accordance with the methodology presented in this section will be regarded as upper bounds for the actual monitor setpoints for high alarms. However, a lower setpoint may be established on the monitor if desired. Intermediate level-setpoints should be established at an appropriate level to give su/ficient warning prior to reaching the high -larm setpoint. The basic calculated monitor setpoint value is in-terms of concentration, Ci/ml. Monitor calibration data may include operational data obtained from monitor response to concentrations determined by liquid sample analyses. In addition, monitor background must be controlled so that the monitor is capable of responding to concentrations in the range of the setpoint value. For- planned releases from the liquid waste processing system's monitor tanks, monitor setpoints are determined to assure that the limits of 10 CFR 20 are not exceeded. For the steam generator processing system effluent line, and
.the turbine building drain effluent line, the purpose of the monitor setpoints is to minimize releases of radioactivity from these systems by terminating releases upon detection of low levels of radioactivity.
1.1.1 Liouid Waste Processina System Effluent Monitor (1(2)RE001Bl_[qnt monitor oer 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, l l VEGP ODCM, REV 6 9/30/88 1.1-1
at=the release point to the unrestricted area. Concentration limits are specified in subsection 1.5.1; setpoint requirements are specified in R subsection 1.5.4. To meet these specifications, the alarm / trip setpoint for this liquid effluent monitor is set to assure that the following equation is satisfied: _cf__ $ C MPC II) F+f 1 where: C,,,e = the effluent concentration limit corresponding to the specific mix of radionuclides in the waste monitor tank being considered : for discharge, in Ci/ml. c - the setpoint, in pCi/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 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.
lF - the dilution stream flowrate whirh-can be assured prior to the
'nlease point to-the river, in volume per unit time, ,
L At Plant Vogtle, the liquid waste _ processing _ system collects liquid wastes in
' monitor -tanks pr(ar:'o release. There are two waste monitor tanks for each L
- unit._ The discharge. lines from the two tanks join to form a common line, on L which the_ radioactivity monitor is installed. The lines from each unit then join to form a common line which releases to the blowdown sump dischargo line to the Savannah River. -(See figure 1.6-3.)
VEGP ODCH, REV_8 Draft 1.1-2 ,
Dilution flow comes from the blowdown sump which receives water from nuclear service cooling tower blowdown, turbine plant cooling tower blowdown, waste
!O.waterretentionbasindischarge,andthecoolingtowermakeupline. The two
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major sourc'es for di1ution 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, C , the effluent flowrate, f, the dilution flowrate, F, and the radioactivity monitor setpoint, it cannot practically be applied to a mixture of radionuclides with-different limiting concentrations, i.e., different MPC values. For a mixture of radionuclides, equation (1) is satisfied in a practicable manner, based on measured radionuclide concentrations and a dilution stream flowrate which can be assured for the duration of the release, designated as F., by calculating the MPC fraction for the radionuclide 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 waste monitor tank per unit is released at a time. Paragraph 1.1.1.1 presents the methodology for calculating the monitor setpoint for this situation. In the event it becomes necessary to release both waste monitor tanks, of the same unit, at the same time, the methodology for calculating the monitor setpoint is more complex. This increased complexity is due to the fact that-the two waste monitor tanks discharge through a common line served by a single-monitor.- Therefore, the radioactivity concentration at the monitor is a i function of the cuncentrations measured in each tank and the flowrates at which the tanks are released. The setpoint methodology for this situation is presented in paragraph 1.1.1.2. 1 VEGP ODCH, REV 4 7/30/87 1.1 -3 l _
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1.1.1.1 Monitor Setpoint Calculation Methodology When One L'aste Monitor Tank per Unit is To Be Released at a Time Sten 1 l l The radionuclide concentrations for the waste monitor tank planned for release are determined in accordance with subsection 1.5.1. The relationship of the various required sample analyses is shown as follows: I ff g C g + (C 3 + C 3 + C f + Ct) (2) j where: C, - the concentration of each measured gamma emitter observed by gamma ray spectroscopy of the particular waste sL ule. C. .the concentration of alpha emitters in liquid waste as measured in the MONTHLY composite sample. (N01E: Sample is analyzed for gross alpha.) C, - the measured concentrations of Sr 09 and Sr-90 in liquid waste as observed in the QUARTERLY composite sample. C, = 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 from analysis of the MONTHLY composite sample, p The C, term will include the analysis of each batch; terms for alpha, strontiums, iron, and tritium will be included in accordance with subsectio-l.5.1 as appropriate. Lo I VEGP ODCM, REV 8 Draft 1.1-4 l t - .-
To assure sample analyses are based on samples that are representative of the volume from which the samples are taken, liquid volumes must be thoroughly mixed prior to sampling. Mixing may oe accomplished by any method of mixing which has been demonstrated to achieve mixing sufficient to allow representative sampling. Sten 2 Measured radionuclide concentrations are used to calculate maximum permissible concentration (MPC) fractions. The MPC fractions are used along with a safety I factor to calculate a required dilution factor, which is the ratio of dilution flowrate to monitor tank discharge flowrate which are required to assure the limiting concentrations given in 10 CFR 20, Appendix B, Table 11, t >lumn 2 are not exceeded at the point of release to the river. The required dilution factor, RDF, is calculated as follows:
.)
C RDF = fgpf+SF a i C C I " C RDF - a s C C (3) g MPC
--+
MPC f
,_ t_ 3p g a MPC s MPC MPC 7 t<
where: _ C, = the measured concentrations of C,, C., C,, C, and C, as defined in step 1. Terms C., C., C,, and C, will be included in the calculation as appropriate. MPC, - MPC,, MPC,, MPC,, MPC,, and MPC, are limiting concentrations of the appropriate radionuclide from 10 CFR 20, Appendix B, Table II, Column 2. For dissolved or entrained noble gases, the a concentration snall be limited to 2 x 10" Ci/ml total activity. For gross alpha the maximum periaissible concentration shall be 3x10'* pCi/ml. If specific alpha-emitting radionuclides are measured, the MPC for the specific radionuclide(s) shall be used. VEGP ODCM, REV 6 9/30/88 1.1-5
i SF - the safety factor, which is a conservative factor selected to l O compensate for statistical fluctuations and errors of measurements. The value for the safety factor must be between 0 and I; 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 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 setpoint for the dilution stream flowrate measurement device is the dilution 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 radioaciisity monitor setpoint, c. If simultaneous-releases are planned from the liquid waste processing systems of Unit I and Unit 2, the dilution stream must be allocated between the two
's units. This is accomplished by multiplying the assured dilution stream finwrate, F., by an allocation factor, AF, to obtain a unf t-specific assured dilution stream flowrate, F,,:
F., - F, (AF) (4) where: I AF = an allocation factor selected to apportion the diluting capacity of the dilution stream between the two units when simu'1taneous releases from the liquid waste processing systems are planned. AF may be assigned any value between 0 and 1 for l each unit under the condition that the sum of the allocation factort does not exceed 1. For convenience AF may be assigned
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the value of 0.5 for each unit. Also, if it is desired to make l liquid waste processing system releases from each unit without regard t6 releases from the other unit, AF should be assigned O5 the wlue of 0.5 for each unit. VEGP. ODCli, REV 4 7/30/87 1.1-6 c-- , m e
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. -If more precise allocation values are desired, they may be determined based on I the relative radiological impact of each unit's liquid waste processing system l
effluent stream on the dilution stream. which may be approximated by multiplying the HPC 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 I and then F., is equal to F,. 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 from the liquid waste processing system should be made if assured dilution stream
- flowrate, F., is less than 5000 gpm.
Steo 4 p for the case RDF > 1, calculate the maximum permissible waste monitor tank ' i - discharge flowrate, f., as follows: F t m- du (5) RDF-1 ForthecaseRDFi1. equation (5)isnotvalid. However, as discussed above, for the case RDF s 1, the release may ba made at full pump discharge capacity .
-and the monitor setooin+ c&lculated in accordance with Step 5.
NOTE.1: Waste mot.itor tank discharge flowrate is actually limited by pump design discharge capacity which is 100 gpm (maximum). When calculated: maximum permissible release flowrates are 2100 gpm, the release may be made at full pump capacity. Release rates < 100 gpm may be achieved by throttling, i vO c l VEGP ODCM, REV 4 7/30/87 1.1-7
NOTE 2: If radioactivity due to plant operations is detected in any of q the effluent streams discharging to the blowdown sump (waste water retention basin, nuclear service w..er cooling tower blowdown, or turbine plant cooling tower blowdown), the diluting ; capacity of the dilution stream would be diminished. (Further, l sampling and analysis of these effluent streams must be sufficient to assure that the dose limits specified in , subsection 1.5.2 are not exceeded.) Under these conoitions, 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 F du II C f
" ~ t RDF-1 ri .
MPC ji r I d (6) where: f(C/MPC)p-g g the MPC fraction of the effluent stream (s) containing the detectable radioactivity. O h f, - the flowrate of the effluent stream (s) containing the radioactivity. If RDF 5_l, NOTE 2 does_not apply. Steo 5 Based on the values determined in the previous steps, a liquid waste-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 Ci/ml, as follows: g c= Af C g (7) O VEGP ODCM, REV 8 Draft 1.1-8
where: O 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 raargin between measured concentra! ions and concentrations which would approach 10 CFR 20 limits: A- E (8) RDF NOTE: ADF is the assured dilution factor: ADF - Fde + f a Sa) a and f, is the anticipated release flowrate from the waste monitor tank to , be discharged. I f A 2 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 further processing of the liquid waste planned for release. Following these actions, repeat-the previous steps and calculate a , new monitor setpoint. I f A < 1, no release may be made under planned conditions. Consider the alternatives discussed above to reduce potential release-concentrations, and calculate a new monitor setpoint based on the results of the alternatives selected. VEGP ODCM, REV 4 7/30/87 1.1-9
1 e e
-The setpoint thus calculated is in the units Ci/ml. The monitor actually i measures counts per minute -subtracts a predetermined background count rate,
-and then multipl_ies by a calibration factor to convert the counts per minute l to Ci/ml.
I l . Calibration of the monitors by the manufacturer and Georgia Power Company utilized NBS_ traceable liquid solutions in the exact geometry of each
- production monitor over a gamma-ray energy range of 0.08 to 1.33 MeV. The calibration factor is a function of the radionuclide mix in the liquid to be released and will be calculated for the monitor based on the results of the i
predischarge sample results from the laboratory gamma-ray spectrometer system. l The mix-dependent calibration factor will be used as the gain factor in the f PERMS monitor or used to modify the calculated base monitor setpoint so that the default calibration factor can be left in the PERMS monitor, ' The monitor setpointa determined in accordance with the methodology described above establish the upper bound for a particular monitor setpoint. Monitor
-setpoints may be established at lower values, if desired.
1.1.1. Monitor Setpoint Calculation Methodology When Two Waste Monitor Tanks per Unit Are To Be Released at a Time Steo_1 F Determine radienuclide concentrations for each waste monitor tank as described g in step l'of paragraph l.l.l.l. I FromthefCg terms determined for each tank, determine an effective g (g C )e L for the two tanks considered together as follows: I I I a1 2 5 a 92 (9) g Cg )e - V 3v V2 iO L I VEGP ODCH, REV 8 Draft 1.1-10 l
where: } V, - the volume of liquid in tank containing greater quantity (referred to throughout this subsection as first tank.) V, - the volume of liquid in tank containing lesser quantity - (referred to throughout this subsection as second tank). ( C )) g - the measured concentrations of gamma-emitting radionuclides in first tank. (g Cg )2 - the measured concentration of gamma-emitting radionuclides in second tank. Sten 2 Determine a required dilution factor, RDF, for each tank in accordance with step 2 of paragraph 1.1.1.1. Using these values calculate an effective required dilution factor, (RDF)e, for the two tanks considered together as follows: V) (RDF); + V2 (RDF)2 (10) (RDF)e " V1+V2 " where: Vi - the volume of first tank. V, - the volume of second tank.
= the required dilution factor for first tank.
(RDF)2 (RDF),- the required dilution factor for second tank. O VEGP ODCM, REV 8 Draft 1.1-11
m , q l 1 l MkP ) i j3 D -Determine the dilution stream flowrate in accordance with step 3 of paragraph 1.1.1.1.
-Heo 4 To facilitate calculation of the monitor setpoint, determine release flowrates for each tank so that the durations of the releases from the two tanks are equal. First, select a release flowrate for the first tank, fi . Then, determine th_e release flowrate for the second rank, f,, as follows:
I Y 7 ,, l 2 (11) 2 V 3 Ncxt, determine a combined flowrate, f,, for releases from both tanks, as follows: I c" fl+I2 (12) g Next, calculate a maximum permissible flowrate, fa, for the combined release in accordance with step 4 of paragraph L1.1.1 using the effective (RDF), determined in step 2 above. l Then, compare the combined release flowrate, f , with the maximun permissible L combined release flowrate, f.. If f > f,, the release may be made under the assumed conditions. -If f,, < f,, the two release flowrates may be throttled, j' maintaining the same ratio of f, to f , as determined earlier. If it is 3 impractical to throttle the release flowrates to the necessary degree to achieve f, < f., steps must be taken to reduce potential release concentrations prior to making the release, and a new -f, determined following j the necessary actions. (Steps which may be undertaken to reduce potential
.releate-concentrations were discussed in step 5 of paragraph 1.1.1.1.).
O VEGP 0DCM, REV 8 Draft 1.1-12
1 1 31e9_5 Calculate the monitor setpoint in accordance with step 5 of paragraph 1.1.1.1 with the following substitutions: Let I Cg - (Ig C o,l e; g RDF - (RDF),; and f, = f, Observe the same limiting conditions discussed in step 5 of paragraph 1.1.1.1. 1.1.2 Steam (tenerator Blowdqwn Effluent Radioactivity Monitor fl(2)RE-00tlh liliine Buildina Drain Effluent Radioac1]vity Monitor (l(2)RE-0848): (one of each monitor oer unit) According to Plant Vogtle design and operating philosophy, the purpose of these radioactivity monitors is to minimize release of radioactivity via O these effluent streams by automatically isolating or diverting effluent flow upon radioactivity in either of the effluent streams reaching certain low levels. To achieve the desired objective, setpoints for these monitors should be established as close to background radiation levels as practical to prevent spurious alarms and yet alarm should an inadvertent release occur. The actual setpoint for each monitor should be established under operating conditions and within the stated objective of preventing releases of radioactivity via these pathwa,vs to the extent practicable. All three of these effluent streams discharge to the waste water retention basin, which in turn releases to the blowdown sump; the blowdown sump discharges to the Savannah River. O VEGP ODCM, REV 8 Draft 1.1-13
I I Should it_become necessary to make releases from any of these two sources p containing levels of radioactivity above that whitn would normally be isolated O or diverted, radioactivity monitor setpoints should be determined in the same manner as described in subsection 1.1.1. However, special consideration must be given_to step 3. An allocation factor must be assigned to the release pathway under consideration here and allocation factors for other pathways, which may be releasing simultaneously, adjusted if necessary so that for simultaneous liquid releases from the site, the sum of the allocation factors does not exceed.l. As stated earlier, both of these effluent streams discharge to the waste water retention basin. Composite samples are collected from the discharge line from the waste water retention Dasin to the blowdown sump. Sample collection and analusis must be sufficient to assure that the dose limits specified in subsection 1.5.2 are not exceeded. 1.1.3 Nuclear Service Coolino Water System Effluent Radioactivity Monitor -(N (l(2)RE-0020 A and B) (Two monitors ner unit) O Racioactivity in these effluent streams normally is expected to be below detectable levels. Therefore, the radioactivity monitor setpoints should be established as close to background as practical to prevent spurious alarms and yet alarm should an inadvertent release occur. If any one of these effluent streams should become contaminated with radioactivity, radionuclide concentrations must be determined and a radioactivity monitor setpoint determined in the same-manner as described in subsection 1.1.1. However, special consideration must be given to step 3. An allocation-factor must be assigned to the release pathway under consideration here and allocation factors for other pathways, which mav ne releasing simultaneously, adjusted if necessary so that for simultaneous 4 mM releases from the site the sum of the allocation factors does not excf.; 21. Determination of concentrations of radioactivity in these streams must be adequate to assure that the dose limits specified in subsection 1.5.2 are not excevied. O VEGP ODCH, REV 8 Draft 1.1-14
1.2 DOSE r".CUL ATION FOR LIQUID EfflVENTS i
\
for liquia releases from Plant Vogtle to the Savannah River, two human expoiure pathways 6xist: consumption of drinking water and fish taken from tu 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 met!.odology for calculating doses to an individual due to I exposure to these two pathways is presented in thi$ :.ubsection. l The dose limits specified in subsection 1.5.2 are or, a per reactor basis. ! Therefore, the doses calculated in accordance with this subsection must be determined and recorded on a per reactor basis. i The dose ta the maximum exposed individual du radionuclides identified in liquid effluents released from each unit to unrestricted areas will be , calculated for the purpose of implementation of subsection 1.5.2 as follows: ! 1 f A, D, a Atf C jf ff 4 (33) , where: 0, - the cumulative dose commitment to '.Le total body or any organ, t, due to radioactivity in liquid effluents for the total time period: m I At f in mrem (Reftrance 1). 1-1 l At t = t} 1 length of the fth tin.c period over which C ie tnd fg are ; 2eraged for any liquid release, in hours. C ,, - the average concentrat', .m et radionuclide i, in undiluted - liquid effluent during i .... period' At, from any liquid release, in Ci/ml.
- VEGP ODCM, REV 8 Draft 1.2-1
, 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, = (acerage undiluted liquid waste flow) + ((average dilution stream flow during the period of release of radioactivity) x Z) (14) NOTE: The denominator of equation (14) is limited to 1000 cfs (448,800 gpm) or less. (Reference 1, sectica 4.3.) Z - the applicable dilution factor for the Savannah River. For the months May through December, Z 10; for the months January O- through April. Z=20. (Reference 5, paragraph 11.2.3.4; Reference 11.)
- A,, - the site-related adult ingestion dose commitment factor to ;
the total body or any organ for each identified radionuclide. Site-related A., values for Plant Vogtle are listed in table 1.2-3, in mrem-ml/h- Ci. . A,- I) DFj , g Kn (((/() e "+ Up BF9e (15) K, = the units conversion factor 1.14 x 10', determined by: 6 3 10 p_C.i x 10 El + 8?60 h
. Ci 1 year U,, - the adult drinking-water consumption (730 liters / year; Reference 3. - table E-5).
. (A)
.VEGP ODCM, REV 8 Draft 1.2-2
-- - . . _ _ . , _, . - _ . _ . - . - ~ , _ _ _ _ _ _ . _ _ . _ - . _ _-_.
D, = the tillution factor from the vicinity of the liquid release I J' point for the plant site to the potable water intake location O (8; Reference 11). A, = the decay constant for radionuclide 1 (h '). t, a the transit time from re19ase to receptor for water consumption (48 h; Reference 3, section A.2; RJference 10). U, - the adult fish consumption (21 kg/ year; Reference 3, table E-5). BF, - the bioaccumulation factor for radionuclide i, in fresh water . fish, in pCi/kg/pC1/l. (See table 1.2-1; Reference 3, , table A-1; Reference 2 for Ag; Reference 14 for P.) t, - the transit time from release to receptor for fish consumption (24 h; Reference 3, section A.2). DF ,, a the dose conversion factor for radionuclide i, for adults in organ, t in mrem /pC1, from table 1.2-2 (Reference 3, table E-ll).
?
O VEGP ODCM, REV 6 .9/30/88 1.2-3
--3. .- + 4 w ar.=:-- eyg- -,--m-ym_
TABLE 1.2-1 O B10ACCUMULA110N TAC 10RS (pCi/kg per pC1/ liter)* Freshwater l Element fish ! H 9.0E-01 C 4.6E 03 , Na 1.0E 02 > P 3.0E 03 Cr 2.0E 02 Mn 4.0E 02 fe 1.0E 02 Co 5.0E 01 N1 1.0E 02 Cu 5.0E 01 i Zn - 2.0E 03 - Br 4.2E 02 Rh 2.0E 03 Sr 3.0E 01 Y 2.5E 01 Zr 3.3E 00 Nb 5.5E 02 Mo 1.0E 01 Tc 1.5E 01 5O Ru 1.0E 01 Rh 1.0E 01 t Ag 2.3E 00 Sb 2.0E 02 Te 4.0E 02 ' 1 1.5E 01 . Cs 2.0E 03 Ba 4.0E 00 La 2.5E 01 Ce 1.0E 00 Pr 2.5E 01-Nd 2.5E 01 W l.2E 03 Np 1.0E 01 s
- Reference 3, Table A-1; Reference 2 for Ag; Reference 14 for P; and Reference 17 for Nb and Sb.
L VEGP ODCM, REV 6 9/30/88 1.2-4
Table 1.2-2 (SHEET 1 Of 3) ADULT INGESTION DOSE FACTORS * (mrem 9er pCi ingested) Nuclide Bone Liver T Body _ Thyroid Kidnev_ Luno GI-LLI H-3 No Data ~1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 C-14 2.84E-06 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 Na-24 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 P-32 1.93E-04 1.20E-05 7.46E-06 No Data No Data No Data 2.17E-05 i Cr-51 No Data No Data 2.66E-09 1.59E-09 5.86E-10 3.53E-09 6.69E-07 1 Mn-54 No Data 4.57E-06 8.72E-07 No Data 1.36E-06 No Data 1.40E-05 l 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 00-58 No Data 7.45E-07 1.67E-06 No Data No Data No Data 1.51E-05 Co-60 No Data 2.14E-06 4.72E-06 No Data No Data No Data 4.02E-05 Ni-63 1.30E-04 9.01E-06 4.36E-06 No D6ta No Data No Data 1.88E-06 Ni-65 5.28E-07 6.86E-08 3.13E-08 No Data No Data No Data 1.74E-06 Cu-64 No Data 8.33E-08 3.91E-08 No Data 2.10E-07 No Data 7.10E-06 Zn-65 4.84E-06 1.54E-05 6.96E-06 No Data 1.03E-05 No Data 9.70E-06 l 2n-69 1.03E-08 1.97E-08 1.37E-09 No Data 1.28E-05 No Data 2.96E-09 Br-83 No Data No Data 4.02E-08 No Data No Data No Data 5.79E-08 i Br No Data No Data 5.2]E-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 2.110-05 9.83E-06 No Data No Data No Data 4.16E-06 i Rb-88 No Data 6.05E-08 3.21E-08 No Data No Data No Data. 8.36E-19 Rb No Data 4.01E-08 2.82f-08 No Data No Data No Data 2.33E-21 Sr-89 3.08E-04 No Data 8.84E-06 No Data No Data No Data 4.94E-05 Sr-90 7.58E-03 No Data 1.86E-03 No Data No Data No Data 2.19E-04 Sr-9) 5.67E-06 No Data 2.29E-07 No Data No Data No Data 2.70E-05 Sr-92 2.15E-06 No Data 9.30E-08 No Data No Data No Data 4.26E-05 Y-90 9.62E.09 No Data 2.58E-10 No Data No Data No Data- 1.02E-04 Y-91m 9.09E-Il No Data 3.52E-12 No Data No Data. No Dat- 2.67E-10 . Y-91 1.41E-07 No Data 3.77E-00 No Data No Data No Data 7.76E-05 Y-92 8.45E-10 No Data 2.47E-Il No Data No Data No Data 1.48E-05 O ""- > . ~~ VEGP ODCM, REV 4 7/30/87- 1.2-5
vwm' , Table 1,2-2 (SHEE1 2 Of 3) l ADULT INGES110N DOSE FACTORS
- 4 '
(mrem per pCi ingested) ((gli@ _ Ape liver T Body lhyroid Kidnel _hn9_. El-l.l l Y-93 2.68E-09 No Data 7.40E-Il No Data No Data No Data 8.50E-05 Zr-95 3.04E-08 9.75E-09 6.60E-09 No Data 1.53E-08 No Data 3.09E-05 Zr-97 1.68E-09 3.39E-10 1.55E-10 No Data 5.12E-10 No Data 1.05E-04 Nb-95 6.22E-09 3.46E-09 1.86E-09 No Data 3.42E-09 No Data 2.10E-05 Mo-99 No Data 4.31E-06 8.20E-07 No Data 9.76E-06 No Data 9.99E-06 Tc-99m 2.47E-10 6.98E-10 8.89E-09 No Data 1.06E-08 3.42E-10 4.13E-07 Tc-101 2.54E-10 3.66E-10 3.59E-09 No Data 6.59E-09 1.87E-10 1.10E-21 Ru-103 1.85E-07 No Data 7.97E-08 No Data 7.06E-07 No Data 2.16E-05 Ru-105 1.54E-08 No Data 6.08E-09 No Data 1.99E-07 No Data 9.42E-06 Ru-106 2.75E-06 No Data 3.48E-07 No Data 5.31E-06 No Data 1.78E-04 Ag-110m 1.60E-07 1.48E-07 8.79E-08 No Data 2.91E-07 No Data 6.04E-05 Sb-124 2.81E-06 5.3E-08 1.llE-06 6.79E-09 No Data 2.180-06 7.95E-05** Sb-125 2.23E-06 2.4E-08 4.4BE-07 1.98E-09 No Data 2.33E-04 1.97E-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 1.10E-07 3.95E-08 2.38E-08 8.15E-08 4.48E-07 No Data 8.68E-06 (Vl Te-12'l 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 6.2iE-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 1-130 7.56E-07 2.23E-06 8.80E-07 1.89E-04 3.48E-06 No Data 1.92E-06 1-131 4.16E- L 5.95E-06 3.41E-06 1.95E-03 1.02E-05 No Data 1.57E-06 1-132 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 1-134 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 No Data 2.51E-10 1-135 4.43E-07 1.16E-06 4.28E-07 7.65E-05 1.86E-06 No Data 1.31E-06 Cs-134 6.22E-05 1.48E-04 1.21E-04 No Data 4.79E-05 1.59E-05 2.59E-06 Cs-136 6.51E-06 2.57E-05 1.85E-05 No Data 1.43E-05 1.96E-06 2.92E-06 Cs-137 7.97E-05 1.09E-04 7.14E-05 No Data 3.70E-05 1.23E-05 2.llE-06 Cs-138 5.52E-08 1.09E-07 5.40E-08 No Data 8.01E-08 7.91E-09 4.65E-13 Ba-139 3.70E-08 6.91E-ll 2.84E-09 No Data 6.46E-11 3.92E-ll 1.72E-07 Ba-140 2.03E-05 2.55E-08 1.33E-06 0.00E+00 8.67E-09 1.46E-08 4.18E-05 Ba-141 4.71E-08 3.56E-Il 1.59E-09 0.00E400 3.31E-ll 2.02E-Il 2.22E-17 Ba-142 2.13E-08 2.19E-Il 1.34E-09 0.00E+00 1.85E-Il 1.24E-11 3.00E-26 x
- Reference 3. Table E-ll.
** Reference 17.
VEGP 00CM, REV 7 3/01/91 1,2-6 m .o
Table 1.2-2 (SHEET 3 0F 3) f1
'> ADULT INGESTION DOSE FACTORS *
(mrem per pCi ingested) Nuclide Bgne liver .l_ Body Thyroid - Kidne_y Luna GL-ill_ 8a-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-Il 1.59E-09 No Data 3.31E-Il 2.02E-Il 2.22E-17 B:-142 2.13E-08 2.19E-ll 1.34E-09 No Data 1.85E-ll 1.24E-11 3.00E-26 La-140 2.50E-09 1.20E-09 3.33E-10 No Data No Data No Data 9.25E-05 La-142 1.28E-10 5.82E-Il 1.45E-11 No Data No Data No Data 4.25E-07 Ce-141 9.36E-09 6.33E-09 7.18E-10 No Data 2.94E-09 No Data 2.42E-05 Ce-143 1.65E-09 1.22E-06 1.35E-10 No Data 5.37E-10 No Data 4.56E-05 Ce-144 4.88E-07 2.04E-07 2.62E-08 No Data 1.21E-07 No Data 1.65E-04 Pr-143 9.20E-09 3 69E-09 4.56E-10 No Data 2.13E-09 No Data 4.03E-05 Pr-144 3.01E-Il 1.25E-Il 1.53E-12 No Data 7.05E-12 No Data 4.33E-18 Nd-147 6.29E-09 7.27E-09 4.35E-10 No Data 4.25E-09 No Data 3.49E-05 W-187 1.03E-07 8.61E-08 3.01E-08 No Data No Data No Data 2.82E-05 Np-239 1.19E-09 1.17E-10 6.45E-Il No Data 3.65E-10 No Data 2.40E-05 G l 4-l
- Reference 3, Table E-II.
(v) VEGP ODCM, REV 4 7/30/87 1.2-7
i Table 1.2-3 (SHEET 1 0F 2) O SITE.RELATED INCEST 10N DOSE FACTORS. A (FORFRESHWATEREISHANDDRINKINGWA1ERCONSUNPTION)* (mrem /h per Ci/ml) i Liver .l_Egdy_ Thyroid Nuclide Bone ._udnev __Luno 01-Ltl H-3 0.00E400 1.32E+00 1.32E400 1.32E400 1.3 E400 1.320400 1.32E400 C-14 3.13E+04 6.26E403 6.26E+03 6.26E403 6.26E403 6.26E403 6.26E403 ' Na-24 1.36E+02 1.36E+02 1.36E+02 1.36E402 1.36E402 1.36E402 1.36E402 P-32 1.32E+06 8.22E404 5.llE404 0.00E+00 0.00E400 0.00E400 1.49E405 t Cr-51 0.00E400 0.00E400 1.27E400 7.58E-01 2.79E-01 1.68E400 3.19E402 Mn-54 0.00E400 4.41E+03 8.42E402 0.00E400 1.31E403 0.00E+00 1.35E404 Mn-56 0.00E400 1.74E-01 3.09E-02 0.00E400 2.21E-01 0.00E400 5.55E400 Fe-55 6.86E402 4.74E+02 1.llE402 0.00E400 0.00E400 2.65E402 2.72E402 Fe-59 1.07E403 2.51E+03 9.61E402 0.00E+00 0.00E+00 7.01E402 8.36E403 Co-58 0.00E+00 9.59E+01 2.15E402 0.00E400 0.00E+00 0.00E400 1.94E403 Co-60 0.00E400 2.78E402 6.14E402 0.00E400 0.00E400 0.00E400 5.23E403 NI-63 3.25E+04 2.25E403 1.09E+03 0.00E400 0.00E400 0.00E+v0 4.70E+02
. Ni-65 1.72E-Ol 2.23E-02 1.02E-02 0.00E400 0.00E+00 0.00E400 5.67E-01 Cu-64 0.00E400 2.76E400 1.29E400 0.00E+00 6.95E400 0.00E400 2.35E402 Zn-65 2.32E+04 7.37E404 3.33E+04 0.00E+00 4.93E404 0.00E400 4.64E404 Zn 7.91E-07 1.51E-06 1.05E-07 0.000400 9.83E-07 0.00E400 2.27E-07 Br-83 0.00E400 0.00E400 3.84E-02 0.00E+00 0.00E+00 0.00E+00 5.53E-02
- Br-84 0.00E400 0.00E+00 1.23E-12 0.00E400 0.00E+00 0.00E400 9.67E-18
. Br-85 0.00E400 0.00E400 0.00E+00 0.00E+00 0.00E400 0.00E400 0.00E400 Rb-86 0.00E+00 9.75E+04 4.54E+04 0.00E+00 0.00E+00 0.00E400 1.92E404 0 Rb-88 Rb-89 0.00E400 1.30E-22 6.90E-23 0.00E400 0.00E400 0.00E400 1.80E-33 0.00E400 1.64E-26 1.38E-26 0.00E400 0.00E+00 0.00E400 0.00E400 Sr-89 2.49E+04 0.00E400 7.16E402 0.00E400 0.00E+00 0.00E400 4.00E403
' Sr-90 6.23E+05 0.00E400 1.53E+05 0.00E400 0.00E400 0.00E400 1.80E404 Sr-91 7.25E401 0.00E+00 2.93E+00 0.00E400. 0.00E+00 0.00E400 3.45E402 Sr-92 3.34E-01 0.00E+00 1.44E-02 0.00E+00 0.00E+00 0.00E400 6.61E400 Y-90 5.04E-01 0.00E+00 1.35E-02 0.00E400 0.00E+00 0.00E400 5.34E403 Y-91M 1.04E-Il 0.00E+00 ~4.03E-13 0.00E400 0.00E+00 0.00E+00 3.06E-Il Y-91 9.77E400 0.00E+00 2.61E-01 0.00E400 0.00E400 0.00E400 5.38E403 Y-92' 4.61E-04 0.00E+00 1.35E-05 0.00E+00 0.00E+00 0.00E+00 8.08E+00 Y-93 3.19E-02 0.00E+00 8.82E-04 0.00E400- 0.00E400 0.00E400 1.01E403 Zr-95 5.47E-01 1.75E-01 1.19E-01 0.00E400 2.75E-01 0.00E400 5.56E402 Zr-97 7.40E-03 1.49E-03 6.83E-04 0.00E+00 2.26E-03 0.00E400 4.63E+02 Nb-95 8.16E400 4.54E+00 2.44E400 0.00E+00 4.48E+00 0.00E400 2.76E+04 Sb-124 1.36E+03 2.56E+01 5.43E+02 3.28E+00 0.00E+00 1.05E+03 3.88E+04 Sb-125 1.09E+03 1.16E+01 2.19E402 9.57E-01 0.00E+00 1.13E405 9.63E+03 Mo-99 0.00E400 1.07E402 2.04E401 0.00E400 2.43E+02. 0.00E+00 2.49E402 l Tc-99M 5.70E-04 1.61E-03 2.05E-02 0.00E400 2.45E-02 7.89E-04 9.53E-01 l
Tc-101 2.75E-33 3.96E-33 3.89E-32 0.00E+00 7.14E-32 2.03E-33 0.00E+00
- Calculated-using Equation (15). When "no data" is reported for dose factors for specific radionuclide-organ combinations in Reference 3, site-related dose-()'factorsarepresentedaszerointhistable.
VEGP ODCfi, REV 8 Draft 1.2-8 oxm a .-.,_m..v.,_,,w.n . _,s,,,_w. ,,,+n,_ng.m., , . _ , , . .e.., ,_ge.n, ne,.,,,., -. -a,,- w - . , , ,, , , ,. ,,,
Table 1.2-? (SHEET 2 Of 2) SITE-RELATED IkSE5110N DOSE FAC10RS, A
\
(FOR FRESHWATER FISH ANi> DRINKING WATER CONSUNPTION)* i (mrem /h per C1/ml) Nuclide Bone Liver i Body Thyroid Kidney Lung Gl-LLl Ru-103 6.21E+00 0.00E400 2.68E400 0.00E+00 2.37E+01 0.00E+00 7.25E402 Ru-105 8.79E-03 0.00E400 3.47E-03 0.00E400 l'.14 E-01 0.00E400 5.38E400 Ru-106 9.42E+01 0.00E400 1.19401 0.00E400 1.82E402 0.00E400 6.10E403 Ag-110M 2.53E400 2.34E400 1.39E400 0.00E+00 4.61E+00 0.00E400 9.56E402 Te-125M 2.56E+03 9.29E+02 3.43E402 7.71E+02 1.04E+04 0.00E400 1.02E404 le-127M 6.51E403 2.33E403 7.93E402 1.66E+03 2.64E404 0.00E400 2.18E404 Te-127 1.78E+01 6.40E400 3.85E+00 1.32E401 7.26E+01 0.00E400 1.41E403 Te-129H 1.09E+04 4.07E403 1.73E403 3.75E403 4.55E404 0.00E400 5.49E+04 Te-129 1.78E-05 6.70E-05 4.34E-06 1.37E-05 7.50E-05 0.00E+00 1.35E-05 Te-131H 9.58E+02 4.68E+02 3.90E+02 7.42E402 4.74E403 0.00E400 4.65E+04 Te-131 8.71E-17 3.64E-17 2.75E-17 7.16E-17 3.82E-16 0.00E+00 1.23E-17 Te-132 'l.97E+03 1.27E+03 1.19E403 1.41E+03 1.23E404 0.00E+00 6.02E404 1-130 7.60E400 2.24E401 8.35E+00 1.90E403 3.50E401 0.00E+00 1.93E401 1-131 1.73E+02 2.48E+02 1.42E+02 8.13E404 4.25E402 0.00E400 6.55E401 1-132 5.28E-03 1.41E-02 4.94E-03 4.94E-01 2.25E-02 0.00E400 2.65E-03 1-133 2.59E+01 4.51E+01 1.37E401 6.62E+03 7.86E401 0.00E+00 4.05E401 1-134 2.19E-08 5.96E-08 2.13E-08 1.03E-06 9.48E-08 0.00E+00 5.19E-Il 1-135 1.31E400 3.44E+00 1.27E+00 2.27E402 5.52E400 0.00E+00 3.89E400 Cs-134 2.98E+05 7.10E405 5.80E+05 0.00E400 2.30E+05 7.62E+04 1.24E+04 Cs-136 2.96E+04 1.17E405 8.42E404 0.00E+00 6.51E404 8.92E403 1.33E+04
.O Cs-137 Cs-138 3.82E+0:, 5.23E405 3.43E+05 0.00E+00 1.78E+05 5.90E404 1.01E404 9.18E-11 1.81E-11 8.98E O.00E+00 1.33E-Il 1.32E-12 7.73E-17 Ba-139 5.66E-06 4.03E-09 1.66E- 0.00E400 3.77E-09 2.29E-09 1.00E-05 Ba-140 3.74E+02 4.69E-01 2.45E401 0.00E400 1.60E-01 2.69E-01 7.69E402 Ba-141 8.57E-25 6.47E-28 2.89E-26 0.00E+00 6.02E-28 3.67E-28 4.04E-34 Ba-142 0.00E400 0.00E+00 0.00E+00 0.00E400 0.00E400 0.00E400 0.00E+00 Ea-140 1.10E-01 5.56E-02 1.47E-02 0.00E+00 0.00E+00 0.00E+00 4.08E+03 La-142 2.19E-07 9.98E-08 2.49E-08 0.00E+00 0.00E400 0.00E+00 7.29E-04 Ce-141 1.15E-01 7.79E-02 8.84E-03 0.00E400 3.62E-02 0.00E+00 2.9BE+02 Ce-143 8.65E-03 6.40E+00 7.08E-04 0.00E+00 2.82E-03 0.00E+00 2.39E402 Ce-144 6.22E+00 2.60E400 3.34E-01 0.00E400 1.54E+00 0.00E400 2.10E+03 Pr-143 6.10E-01 2.45E-01 3.02E-02 0.00E400 1.41E-01 0.00E400 2.67E403 Pr-144 1.50E-28 6.22E-29 7.61E-30 0.00E400 3.51E-29 0.00E+00 2.15E-35 Nd-147 4.llE-01 4.75E-01 2.84E-02 0.00E400 2.78E-01 0.00E400 2.28E403 W-187 1.48E402 1.23E+02 4.31E+01 0.00E+00 0.00E400 0.00E400 4.04E+04 Np-239 2.81E-02 2.76E-03 1.52E-03 0.00E+00 8.61E-03 0.00E+00 5.67E+02
- Calculated Using Equacion (15). When "no data" is reported for dose factors for specific radionuclide-organ combinations'in Reference 3, site-related dose factors are presented as zero in this table, VEGP 00CM, REV 6 9/30/88 1,2-9 l
l L_ - - _ - - --
1.3 DOSE PROJECTIONS FOR LIQUID EFFLUENTS A U l.3.1 Thirtv-One-Day Qose Pro.igtijianji n in order to meet the requirements of subsection 1.5.3, which pertains to operation of the liquid radwaste treatment systems, dose projections must be made at least once per 31 days, during pericds in which discharge of liquid effluents containing radioactive materials to unrestricted areas occurs or is expected. Projected 31-day doses to individuals due to liquid effluents may be determined as follows:
'D U
tb(pej) = E x 31 (16) A t t
'D D M x 31 (17) q o(prj) -i t t b where:
r D,g,3 - the cumulative total body dose for the elapsed portion of the current quarter plus the release under consideration.
- t - the number of days into the current quarter, including the period of the release under consideration, 0,, , , 3 = the cumulative organ doses for specifir organs, for the 9 lapsed partien of the current quarter plus the release under consideration.
If operational activities planned during the ensuing 31-day period are expected to result in liquid releases which will contribute a dose in addition to the dose due to routine liquid effluents, this additional dose contribution should be included in the equations as follows: VEGP ODCH, REV 8 Draft 1.3-1 J
P U __tb(c) tb(prj) - x 31 + D t PA (18) D(prj) o = M x 31 +0 t . PA (19) where 0,4 i s the expected dose due to the particular planned activity. i 1.3.2 ~ Dose Projections for Specific Releases i Dose projections may be performed for a particular release by performing a pre-release dose calculation assuming that the planned release will proceed as anticipated, for individual dose projections due to liquid releases, follow the methodology presented in section 1.2 using sample analyses values for the source to be released and parametric values expected to exist for the release I period. O i e O VEGP ODCH, REV 8 Draft 1.3-2 w,n,4 mar, o ++-v ~+ - , --r . ,- r v- wnr-n-+g-r--s~ ,wrw -- ---wem-n----r- wa t
1 1.4 DEf!NITIONS Of LIQUID EFFLUENT TERMS l Section of O lem Dgfinition Initial U1g A - the adjustment factor used in calculating monitor setroints, which is the ratio of the assured dilution factor to the required dilution 4ctor (unitiess). 1.1.1 l A,i - the site-related ingestion dose commitment l factor for the total body or any organ for , each identified principal radionuclide listed l' in table 1.2-3, in mrem-m1 per h-pci. 1.2 I ANALOG CHANNEL OPERATIONAL TESTfACOT) An Analog Channel Operational Test shall be the injection of a simulated signal into the channel as close to the sensor as practicable to verify operability of alarm, interlock, and/or trip O V functions. The Analog Channel Operational Test , shall include adjustments, as necessary, of the ' alarm, interlock, and/or trip setpoints, such thatthesethointsarewithintherequired range and accuracy. 1.5 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 freshwater fish, pCi/kg per pCi/1, 1.2 from table 1.2-1. O VEGP ODCM,-REV 8 Draft 1.4-1
Section of Tern Definition Initial tise O BATCH RELEASE A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for analyses, each batch shall be isolated and then thoroughly mixed by a method described in the ODCH to as:;ure representative sampling. 1.5 c = the base setpoint of the radioactivity monitor which measures the radioactivity concentration in the effluent line prior to dilution and subsequent release. 1.1.1 t, = the effluent concentration of alpha-emitting nuclides observed by gross alpha analysis of the monthly composita sample, in vCi/ml. 1.1.1 C, = the concentration of fe-55 in liquid wastes as observed in the quarterly composite sample, in Ci/ml. 1.1.1 C, = the effluent concentration of a gamma-emitting nuclide, g, observed by gamma ray spectroscopy of the waste sample, in Ci/ml. 1.1.1 C, = the concentration of nuclide i as determined by the analysis of the waste sample, in Ci/ml. 1.1.1 Cu = the average concentration of radionuclide i, in undiluted liquid effluent during time period At,, for a release, in Ci/ml. 1.2 C. - the effluent concentration limit (Technical Specification 3.11.1.1) implementing 10 CFR 20 for the site, in Ci/ml. 1.1.1 VEGP ODCH, REV 8 Draft 1.4-2
, Section of i leng Definition Initial Use O C, - the concentration of Sr-89 and Sr-90 in liquid l wastes as determined by analysis of the
' QUARTERLY composite sample, in Ci/ml. 1.1.1 C, = the measured concentration of H-3 in liquid waste as determined by analysis of the MONTHLY composite sample, in Ci/ml. 1.1.1 ,
CHANNEL CALIBRATION A channel calibration shall be the adjustment, as necessary, of the channel, such that it responds within'the required range and accuracy to known values of input. The channel calibration shall encompass the entire channel including the sensors . and alarm, interlock, and/or trip functions and may be'perfe<med by any series of sequential, overlapping, or total channel steps, such that the entire channel is calibrated. 1.5 QLftNNEL CHECK A channel check shall be the qualitative assessment of channel behavior during operation by observation. This determination shall include, where possible, comparison of the channel indicattun and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter. 1.5 COMPOSITE SAMPlf A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and ir which the method of sampling employed results in a specimen that is representative of the liquids released. 1.5 VEGP ODCM, REV 8 Draft ~ 1,4-3
i Section of ltts Definition Initial Use O LQ!illWOUS RELEASE A continuous release is the discharge of liquid ' wastes of a nondiscrete volume, e.g., from a volume of a system that has an input flow during , the continuous release. 1.5 i D, = the cumulative dose commitment to the total body or any organ, t, from the liquid effluents for the total time period, in mrem. 1.2 . D,, * = the additional dilution factor between vicinity of release point and drinking water location (unitiess). 1.2 Dr u - a dose conversion factor for nuclide, i, for adults in organ, t, ir mrom/pCi found in i table 1.2-2. 1.2 , L
.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 whict, the dilution stream i discharges to the river, in gpm. (General ' expression for equation 1.) 1.1.1 l l 1; LO VEGP ODCM, REV 8- Draft 1.4-4 l
I Section of Jing Definition Initial Use i t FRE0VENCY NOTATION The f quency notation specified for the performance of surveillanco requirements shall correspond to the ! intervals defined below. 1.5 , NOTATION FRE0VENCY S At least once per 12 hours. , D At least once per 24 hours. ' W At least once per 7 days. M At least once per 31 days. : Q At least once per 92 days. SA At least once per 184 days. ' R At least once per 18 months. S/U Prior to each reactor startup. N.A. Not applicable. P Completed prior to each release. Fo = 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 flowrate measurement device. 1.1.1 . Fg -. the unit-spectfic-assured flowrate of the dilution stream used as the basis for setpoint calculations, in gpm. 1.5.1 Fe - the near-field average dilution factor for Ci , during any liquid effluent release (unitiess). 1.2 f,
-- the anticipated effluent flowrate in gpm. 1.1.1 lO F
VEGP ODCH, REV 8 Draft 1,4-5
l Section Of ; RCID Definition Initial list O f, - the maximum permissible effluent flowrate in 1.1 1 i gpm. K, 1.11 x 10', units conversion factor, which converts Ci to pCi, liters to m1, and hours to year. 1.2 , LOWER LIMIT OF DETECTION i The principal gamma emitters for which the lower limit of detection (LLD) specification applies include the following radionuclides: Mn-54, Fe-59, C0-58, Co-60, 2n-65, Ho-99, Cs-134, Cs-137, and Ce-141. Ce-144 shall i also be measured, but with an LLO of 5 x 10'6 This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also , be analyzed and reported in the semiannual , Radioactive Effluent Release Report pursuant to Technical Specification 6.8.1.4.
-i The-LLD-is defined, for purposes of these specifications, as the smallest concentration t.f radioactive material in a sample that will yield a net count above system background and that will be detected with 95-percent probability, with only 5-percent probability of falsely concluding that a blank observation
. represents a "real" signal. 4 VEGP ODCM, REV 8 Draft 1.4-6
7 1 Section Of IRIm Definition Initial Use
\
for a particular measurement system, which may include radiochemical separation: LLD - 4.66 s, E
- V
- 2.22 x 10'
- Y
- exp (-Aat) where:
LLD - the a priorf lower limit of detection (microcurie per unit mass or volume). s, - the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute). E = the counting efficiency (counts per disintegration). V - the sample size (alts of mass or volume). 2.22 x 10' - the number of disintegrations per minute per microcurie. Y - the fractional radiochmical yield, when applicable. A - the radioactive decay constant for the p;rticular
- i. d radionuclide (see ).
At - the elapsed time between the midpoint of sample collection and the timu of counting (:;ec). Typical values of E V, Y, and at should be used in the calculation. It should be recognized that the LLD is defined as an a priorf (h' fore the fact)_ limit _ representing the capability of a measurement system and not as an a posterforf (after the fact) limit for a particular measurement. m - the number of liquid releases. 1.2 i MPC, = hic,, MPC , _ MPC , HPC,, and MPC,, which are the limiting concentrations of the approp"t&te gamma-emitting radionuclides, alpha-emitting radionuclides, strontium, iron, and tritium, m respectively, from 10 CFR 20, Appendix B, l table 11, column 2. 1.1.1 VEGP ODCH, REV 8 Draft 1.4-7 ,
)
i Section Of le.tm Definition initiaLUse 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 20, Appendix B, table 11, column 2 are met at the point of discharge to the unrestricted area (unitiess). 1.1.1 REPRESENTATIVE SAMPLE FOR CON 11NVOUS RELEASES To be representative of the quantities and concentrations of radioactive matcrials in liquid effluents, samples shall be collected continuously in proportion to the rate of flow of the effluent stream. Prior to t' analyses, all sampics taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the , effluent release. 1.5 O , SF = the sefety factor, which is a comervative 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 50VHCE CllLQ; A source check shall be the qualitative assessment of channel response when the , channel sensor is exposed to a source of increased radioactivity. 1.5 t, - the-transit time from release to receptor (fish consumption), in hours. 1.2 ( VEGP ODCM, REV 8 Draft 1.4-0 t i p - - - __
, , , - y , .., .. _--_ , - _ . , , . 9-~- - . -, . , - . ,w ..%, ,,,y. , ,,m,, .-f ----,-,_.- -- -%
. -~ _ .- __ _.._...._._ -. .._...____ __ ___ .__. _.____.____.m____ _ . - _ .
Section Of
- Istm Definiting Initial Usg O- t, = the transit time from release to receptor I (drin'ttng-water consumption), in hours. 1.2 At, a the duration of release under consideration, '
in hours. 1.2 V, = 21 kg/ year, fish consumption (adult). 1.2 V, = 730 liters / year, water consumption (adult). 1.2 Z . the appitcable factor when additional receiving water body dilution is considered (unitiess). 1.2
^
A, - the decay constant for radionuclide 1 (h'8). 1.2 O h i I O VEGP ODCH, REV 8 Draft 1,4-9
l.5 LIM 115 Of OP[Rti10N O 1.5.1 Contstnuon in LioujiE11henh 1he concentration of radioactive material released in liquid effluents to unrestricted areas (see figures 3.0-1 and 7.0-2) shall be limited to the concentrations specified in 10 CFR 20, Appendix 0, table 11, column 2, for radionuclides other than dissolved or entraine(t noble gases, for dissolved or entrainec noble gases, the concentration shall be limited to 2.000-4 microCur'.eg, total activity. This limit applies at all times for all modes of operation. 1.5.1.1 Exceeding the Limits if the concentration of radioactive material released in liquid effluents to unrestricted areas exceeds the above limits, immediately restore the concentration to within the above limits. These litits do not affect mode changes. 1.5.1.2 Sampling and Analysis To assure these limits are not exceeded, the following sampling and analysis program must be implemented: 1.5.1.2.1 lbild! Releasn . For batch waste releases from any of the six waste monitor tanks or from the drainage of a system, each batch must be sampled prior to its release and analyzed for (1) principal gamma emitters to an LLD of 5.00E-7 microcurie /mi and (2) 1-131 to an LLO of 1.00E-6 microcurie /ml. These results shall be used to calculate setpoints and flowrates, per section 1.1, to assure that the concentrations at the point of release are maintained within the limits specified above. In addition, this same sample taken prior to release, shall be used to measure for dissolved and entrained gases (gamma l VEGP ODCM, REV 8 Draft 1.5-1 !
emitters) at least monthly. This analysis must meet an LLD of 1.000-5 micreturie/ml. Normally, this can be combined into the sa'ne analysis for O- principal gamma emitters. Also included in this samp11 taken prior to release, enough of the composite sample shall be set aside to prepare a monthly composite for monthly tritium analysis to an LLD of 1.00E-5 Ci/mi and monthly gross alpha analysis to an LLD of 1.00E-7 microcurie /ml. Finally, a quarterly composite shall be , analyzed quarterly for Sr-89 and Sr-90 to in LLD of 5.00E-8 microcurie /ml and for Fe-55 to an LLD of 1.00E-6 microcurie /ml. These composites are prepared for each unit. 4 1.5.1.2.2 Continuous Releases. All liquid effluents that do not normally contain contamination but could become contaminated in the event of steam generator tube leak are discharged from the site through the waste water retention basins (WWRB). Because of the potential for contamination, a representative sample of each WWRB is collected continuously with th3 composite sample container bbing changed weekly. The WWRB will not be considerad to be a release point until there is a confirmed primary to secondary release. Once a primary to secondary leak has been confirmed to occur, this composite shall be analyzed weakly for (1) principal gamma emitters to an LLD of 5.00E-7 C1/ml and (2) 1-131 to an LLD of 1.00E-6 . pCi/ml. These results can be used to calculate setpoints and flowrates, per section 1.1, to assure that the concentrations at'the point of release are maintained within the limits specified above. In addition, a monthly grab sample shall be taken and analyzed monthly for dissolved and entrained gases (gamma emitters) to an LLD of 1.00E-5 pC1/ml. Normally, this can be combined into the same analysis for principal gamma emitters. Also included in this sample teken continuously, a monthly composite shall be analyzed monthly for tritium to an LLD of 1.00E-5 pCi/ml and for gross al'pha to an LLD of 1.00E-7 C1/_ml . Finally, a quarterly composite shall be analyzed _ O VEGP ODCH, REV 8 Draft 1.5-2
- . , . ~ _ _ _ _ . _ . _ _ _ _ . _ _ , , . _ . _ . . _ _ _ . _ >
quarterly for Sr-89 and Sr-90 to an LLD of 5.00E-8 vCi/ml and for Fe-55 to an f LLO of 1.00E-6 pCi/ml. These composites are prepared for each unit. Once O i these composites begin, they shall continue until three consecutive weekly composite samples show no activity above LLD. 1 1 1.5.1.2.3 The low levels specified in 10 CFR 20 provide additional assurance that the levels of radioactive materials in bodies of water in unrestricted I areas will result in exposures within (1) the section 11.A, design objectives, . Appendix I,10 CFR 50, to a member of the public and (2) the limits of 10 CFR i 20.106(e) to the population. The concentration limit for dissolved or entrained noble gases is based upon the assumption that Xe-135 is the controlling radioisotope, and its HPC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2. The specification applies to the release of radioactive materials in liquid ! effluents from all units at the site. The required detection capabilities for radioactive materials in liquid waste l O samples are tabulated in terms of the LLD's. Detailed discussion of the LLD and other detection limits can be found in HASL Procedures Manual, RASL-300 (revised annually), L.. A. Currie, " Limits for -Qualitative Detection and , Quantitative. Determination - Application to Radiochemistry," Anal. Chem 40, 586-93, 1968, and J. K. Hartwell, " Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215, June 1975. Composite samples are sent to off-site labs at the plant's discretion; in this case, the-d' ate the sample is mailed via the warehouse is the date used to sign off the surveillance. t 1.5.2 Dose Due to Liouid Effluents The dose or dose commitment to a member of the public from radioactive materials in liquid effluents released from each unit to unrestricted areas (see figure 3.0-1 and.3.0-2) shall be limited (1) during any calendar quarter i VEGP ODCH, REV 8 Draft 1.5-3
. . _ . _ __ - _ _ __ _. _ _ _ . - - _ .. _ _ _ _ ._m._. _ .._.. _ . _ . to less than or equal to 1.5 mrems to the whole body and to less than or equal to 5 mrems to any organ and (2) during any calendar year to less than or equal O to 3 mrems to the whole body and to less than or equal to 10 mremt. to any organ. This limit applies at all tit.es for all modes of operatlon. 4 1.5.2.1 Calculated Dose That Exceeds Limits If the calculated dose from the relerie of radioactive materials in liquid effluents exceeds any of the above limits, prepare and submit to the NRC within 30 days, pursuant to Technical Specification 6.8.2, a special report that (1) identifies the cause(s) for exceeding the limit (s) and (2) defines the corrective action (s) that have been taken to reduce the releases and the proposed corrective actiors to be taken to assure that subsequent releases will be in compliance with the above limits. These limits do not affect mode changes. 1.5.2.2 Requirements for Calculations-To assure that these limits are not exceeded, the cumulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year shall be determined in accordance with subsection 1.3.1 at least once per 31 days. , 1.5.2.3 Bases for The Limits These limits are provided to implement the requirements of sections ll.A, Ill.A, and IV.A, Appendix I, 10 LFR 50. Also for fresh water sites with :' drinking water supplies that can be potentially affected by plant operations,
-these is reasonable assurance that the operation of the facility will not result in radionuclide concentrctions that are in excess of the requirements of 40 CFR 141, in the finished drinking water. The dose calcelation methodology and parameters in this ODCH implement the Appendix 1, section
!!I.A requirementt that conformance with the Appendix 1 guides be shown by VEGP ODCM, REV 8 Draft 1.5-4
calculational procedures based on models and data, such that the actual exposure to a member of the public through appropriate pathways ir, unlikely to be substantially underestimated. The equations specified in this ODCH for calculating the doses that are due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109 and 1.113. This specification applies to the release of radioactive materials in liquid effluents from each unit at the site. When shared radwaste treatment systems are used by more than one unit at the site, the wastes from all units are mixed for shared treatment. By such mixing, the effluent releases cannot accurately be ascribed to a specific unit, An estimate should be made of the contributions from each unit band on input conditions, e.g., flowrates and radioactivity concentrations, or, if not practicable, the treated effluent releases may be allocated equally to each of the radioactive waste-producing units sharing the radwaste treatment system. The laundry and hot shower tank liquids are common to both units. The recycle holdup tanks receive liquids from both the units. During normal operations the volume is proportioned equally between each processing unit. Whenever these is an outage, consideration is given to allocating more of the waste to the unit that is in the outage. The chemical drain tank liquid is charged to Unit 1 only. 1.5.3 Liquid Radwaste Treatment System 1.5.3.1 Dose i.imits for Operation of the Liquid Radwaste Treatment System The liquid radwatte treatment system shall be operable, and appropriate portions of the system shall be used to reduce radioactivity releases when the projected doses that are due to the liquid effluent, from each unit to unrestricted areas (see figure 3.0-1 and 3.0-2), would exceed 0.06 mrem to the whole body or 0.2 mrem to any organ in a 31-day period. This limit applies at all times for all modes of operation. l VEG.P 00CM. REV 8 Draft 1.5-5 p.m. . ..o.,-.
- ~..em - + .-i.,_,,y.-.y..,.. _ ,, .- , ,.,.,,,,,,,,.-,-._.,_._,..,,,%w ...y.,__ ,,_ . . _ - , . ,,---m. ,_e.m3_
1.5.3.2 Projected Doses That Exceed Limits O. If radic-ctive liquid waste is being discharged in excess of the above limits without treatment and if ar.y portion of the liquid radwaste treatment system is not in operation, prepare and submit to the NRC within 30 days, pursuant to Technical Specificar o 6.8.2, a special report that includes the following information:
- 1) An explanation of why liquid radwaste was being discharged without i treatment. Identification of any inoperable equipment or subsystems and the reason for inoperability.
- 2) What actions will be taken to restore the inoperable equipment to operable status.
- 3) A summary description of action (s) that will be taken to prevent a recurrence.
These limits do rot affect mode changes. 1.5.3.3 Bases for Projecting Doses lo assure these limits are not exceeded,-doses that are due to liquid releases, from each unit to unrestricted areas, shall be projected at least once per 31 days, in accordance with the methodology and parameters in this ODCM, when liquid radwaste treatment systems are not being fully utilized. The operability of the liquid radwaste treatment Ustem ensures that this ' syst;m will be available for use whenewr liquid effluents require treatment
- prior to release to the environment, lhe requirement that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liqu'd effluents will be kept "as low as -
is reasonably achievable." This specification. implements the requirements of 10 CFR 50.36a, General Design Criterion 60, Appendix A,10 CFR 50 and the design objective given in section II.D, Appendix 1,10 CFR 50. The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified as a suitable fraction of the dose design C,~objectivesthataresetforthinsectionII.A, Appendix 1,10CFR50,for liquid effluents.
.VEGP ODCM, REV 8 Draft 1.5-6 i
1 i 1,5.4 Liquid Effluent Henitoring Instrumentation O The radioactive liquid effluent monitoring instrumentation channels specified below shall be operable with their alarm / trip setpoints set to ensure that the
. limits in subsection 1.5.1 of this ODCM are not excet ed. T*.is limit applies at all times for all modes of operation.
i 1.5.4.1 Nonconservative Liquid Monitor Setpoint and ACTIONS If a radioactive liquid effluent monitoring instrumentation channel alarm / trip setpoint is less conservative than required, immediately suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel inoperable. If less than the minimum number of radioactive liquid effluent monitoring instrumentation channels are operable, take the ACTION shown in table 1.5-1. Restore the inoperable instrumentation to operable status within 30 days or, if unsuccessful, explain in the ne"t Semlannual Radioactive Effluent Release O Report, per Technical Specification 6.8.1.4, why this inoperability was not
-corrected in a timely manner. These limits do not affect modes changes. -
1.5.4.2 Liquid Monitor Operability Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated operable by performance of the channel check, source check, channel calibration, and analog channel operational test at the frequencies shown in table 1.5-1. Specific instrument numbers are provided in parentheses for information only. The numbers apply to each unit. These numbers will help to identify associated channels or loops ano are not intended to limit the' requirements to the specific instruments associated with the number. l lO i VEGP ODCM, REV 8 Draft 1.5-7 L - . - , ... ._ . _
1ABLE 1.5-1 (SHEE1 1 Of 4) LIQUID EffL0EN1 MON 110 RING INSTRUMENTATION , L Analog Hinimum Channel Channels Channel Source Channel Operational DEtal!12 Md103 lhtd_ l htth Calibration Test
- 1. Radwaste monitors providing alarm and auto termina-tion of release a) Liquid radwaste effluent (RE-0018) 1 37 D P R(3) Q(1) b) SG blowdown effluent (RE-0021) 1 38 D H R ' * ', Q(1) c) Turbine building ef fluent (RE-0848) 1 38 D H R(3) Q(1)
- 2. Radwaste snitors providine alarm but p not providing auto
( terminatloa of release a) NSCW effluent line (RE-0020 A&B) 1 39 0 N R(3) Q(2)
- 3. Flowrate measure-ment devices a) Liquid radwaste effluent line (fi-0018) or (FT-1035) or (fT-1036) 1 40 D(4) NA R NA b) Steam generator blowdown effluent (FT-0021) 1 40 0(4) NA R NA c) flow to blowdown sump (AfQl-7620, _
FR7620 pen 1) 1_ 40 D(4) NA _ _R Q O VEGP ODCH, REV 8 Draft 1.5-8 l l l- -- ,. ,._ __ - , - . . -- - , - - - - , - - , -- . . - - - - - - - - - . - - , - - -
TABLE 1.5-1 (SliEET 2 0F 4) O TABLE NOTATIONS (1) The analog channel operational test shall also demonstrate that automatic isolation of this pathway (for item a. below only) and control room alarm annunciation occur if any of the followUa conditions exists:
- a. 7.nstrument indicates measured levels above the alarm / trip setpoint.
- b. Circuit failure,
- c. Instrument indicates a downscale failure,
- d. Instrument controls not set in operate mode. (Annunciation via computer printout.)
(2) The analog channel operational test shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists: m a. Instrument indicates measured hvels, abovn the alarm setpoint. O, b. Circuit failure.
- c. Instrument indicates a downscale failure.
- d. Instrument controls not set in operate mode. (Annunciation via computer printout),
(3) The initial channel calibration shall be performed using one or more of the reference standards certified by the Natior;al Bureau of Standards (NBS) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS. These standards shall permit calibrating the system over its intended range of energy and measurement range. for subsequent channel calibration, sources that have been related to the initial calibration shall be used. (4) Channel check shall consist of verifying indication of flow during periods of release. Channel check shall be made at least once per 24 hours on days during which continuous, periodic, or batch releases are made.
~
VEGP ODCM, REV 8 Draft 1.5-9
__ . .. _. . _ .. _ . _ _ _ __. _-._m _. _ _ _ _ _ ._. ._ . _ _ _ _ _ TABLE 1.5-1 (SHEET 3_0F 4) ACTION STATEMENTS ACTION _37_- With the number of channels operable less than required by the minimum channels operable requirement, effluent releases _via this pathway may continue provided that prior to initiating a release:
- a. at least two independent samples are analyzed in accordance with subtection 1.5.1 of this ODCM
.b. at least two technically qualified members of the facility staff independently verify the release-rate calculations and discharge line valving.
Otherwise, suspend release of radioactive effluents via this pathway. ACTION 38 - With the number of channels cperr. ole less than required by the Ox minimum channels operable requirement, effluent releases via thie pathway may continue provided grab samples are analyzed for radioactivity at a lower limit of detection no more than 1 x 10'# Ci/ml:
-a. at least once per 12 tours when the specific activity of the_ secondary coclant is greater than 0,01 Ci/ gram i: 'ose equivalent I-131 d
- b. at least once per 24 hours when the specific activity of the secondary coolant is less than or equal to 0.01 pCi/gra$ dose equivalent I-ISI.
ACTION 39 - Withi the number of channels ~ operable less than required by the minimum channels operable requirement, effluent releases via
.this pathway may continue provided that, d least once-per 12 hours,- grab samples are collected and analyzed for radioactivity at a lower level of detection no more than 1 x 10" pC1/ml.
VEGF ODCM, REV 8 Draft - 1.5-10 J
TABLE 1.5-1 (SHEET 4 0F 4) ACTION STAT.WENTS ACTION 40 - With the number of channels operable less than required by the minimum channels operable requirement, effluent releases via thi3 pathway may continue provided the flewrate is estimated at least once per 4 hours during actual releases. Pump performance curves generated in place may be used to estimate flow. O O VEGP ODCM, REV 8 Draft 1.5-11
4 ( t 1.6 LLIQUID WASTE PROCESSING SYSTEM AND LIQUID DISCHARGE PATHWAYS
-E Figures.l.6-1 and 1.6-2 are schematics of the liquid waste processing systems i for Unit 1 and Unit 2, respectively. The dotted lines indicate alternate pathways through which liquid wastes may be routed as appropriate. These 1 alternate routes increase the operational flexibility of the liquid waste j processing systems.
l l Figure 1.6-3 is a schematic of plant discharge pathways for liquids. 4 1 i 1 5 t 1 e
. V i
?
.3
- A 4
VEGP ODCM, REV 8 Draft 1.6-1 axm t. m
-.$ w -,
e Leandry and Hot Slower Tank Floor Orain T ank (Shared) l l Strainer Stromer 7 _ _ __ _ _ _ F etter F ilter G-- - I
- -{D v I n@
Waste k ***** j Hondup - +- *-@ -_-_/b Tank Domin I I y Waste i F Momtor l k Filter l g 7___L__q_____ , Waste Weste Monitor Monitor Tank l Tain
+ w2 l +
r, w r 2, Radioactivity Monitor 1 RE@18 h I From Unit 2 Waste Monitor Tank (s) y To Distnarge
' Dotted lines indicate attemate routes for increased operational flexibility and/or add #tional processing.
@ To Unit 2 l From/To Unit 2.
To Drain Channel A
) From Drain Channel A ~
VOGTLE LIQUID WASTE PROCESSING SYSTEM ELECTRIC QENERATING PLANT (Unit i) GeorgiaPower h UNIT 1 AND UNIT 2 FIGURE 1.6-1 033-9 VEGP ODCM, REV 8-Draft 1.6-2 s
O i-I loor 0,s.n C1 T T s'* l l 5t... Holdup Tans a m., A
=4
; ...t.
i
-4
=-. ._ -_-- y D min Wesw uen.., I ..
~
l _ T a'* 20.000 set f g Mon.cor t .<*
,,, s n 20.000 p.
Monitoe g T ar* r .n.,
~
l 7-- t-- J ----- Wo.w w at. Momtur l Monttor T a'* Tasa 5.000 eel l 5.000 est I _ks L2 4 rm rm h Rufinnenvety Momtor 2RE 0018 II A e To Dscharge (See Figure 1.M.)
' Dotted liries indicate alternate routes for increased operational flexibility and/or prlchtional processing.
CD Frorn tinit 1 (7 Frorn/To Unit 1 (3) To Droin Channel A
@ Frorn Druin Channel A vozvLe LIQUID WASTE PROCESSING SYSTEM Georgia Power ELECTillC GENERATING PLANT (Urlit 2) u in uno umT 2 FIGURE 1.6-2
**" VEGP ODCM, REV 8 Draft 1.6-3
O Unit 2 Umt 1 Unit 1 Steam Steam Turtune Generator Generator Buildsig Blowdown Blowdown Drain Unit 1
~ Nuclear Servre l From Other Sumps Coobng Waier "
arut Drams Basm -:--- (2) (3) Uniti L Coatrof 6 Buikimg Sump k ("," I p F rom Other Sumps
" "9 *"
Unet 2 Turbme Dueldmq Drams 1P
*- Other Unit 2 bumps U*'I and Drams From Umt 2 Nucleas Servate Coohng O ae Water Basin Unit 2 Conte 01 fluildmq Sump
, 3 From Urut 2 Turbme Plant Coolmg Tower Unit 1 W*"*"'"' Umt 2 Ody Waste Retention $, ,,,
Daun Umt 1 h Lutud Waste + F rom Umt 2 Waste Processirq - System Water Retention Basm
, u <ro o Coohng Tower Makeup Bypau Line '
4 E"*d**" From Unit 2 E"'"P _ From Flushmg Poruts 'Durmg Liqud Waste ' Process.ap Constructeon of Umt 2) System
=
1t
,~
River
~-:
Radioactivity Monitors:
) 1(2) R E0020 1(2) RE0021 1(2) RE0848 1(a RE0018
*The blowdown sump n common to both units.
VOGTLE ELECTFIC GENERATING PLANT LIQUID DISCHARGE PATliWAYS Georgia POWC" JLS UNIT 1 s.ND UNIT 2 FIGURE 1,6 033 9 VEGP 00CM, REV 8 Oraft 1.6-4
2.0 DJUED,VS EFFLVENTS
-O l
At' Plant Vogtle, there are five potential points where radioactivity is l released to the atmosphere in gaseous discharges. These- five potential l 1 release points are: Unit 1 plant vent; Unit 2 plant vent; Unit 1 and Unit 2 turbine building vents, which are not normal release pathways until a primary to secondary leak ~ exists; and the dry active waste processing 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 plant vent, Certain components of the Gaseous Waste Processing System-are shared between the two; units and releases from this system are through the Unit'1 plant vent, Containment building releases are through the respective plant vents. Gaseous releases from the turbine building vents, the radwaste solidification O- building vent, and the-dry _ active _ waste processing building vent are
~
considered to be ground-level releases. Gaseous releases from the plant vents are considered to be mixed-mode releases, as' determined by the wake-split model. (See NOTE in subsection 2.1.2.) All six release points are considered to'be-continuous releases, in the absence of primary to secondary leak (s), the turbine building vents are not release points. Gaseous effluent monitor setpoints are required only for noble gas monitors - serving the five release points excluding the dry active waste processing building, Methodology for calculating noble gas monitor setpoints is presented in-section-2.1. Although setpoint ca':ulations are not required for radiciodine and particulate monitors, the cdhodology for assuring the potential organ-dose rates due to radiciodines, tritium, and particulates in gaseous releases from the site do not exceed the limits of subsection 2.5.1 is l presented in the NOTE in paragraph 2.2.1.2. O l VEGP ODCM, REV 8 Draft 2.0-1 l-
2 .1 GASEOUS EFFLUENT MONITOR SETPOINTS O The setpoint for a particular noble gas monitor is determined by calculating a basic setpoint value, c., which will assure the limits of subsection 2.5.1 are
.not exceeded.
Subsections 2.1.1, 2.1.2, and 2.1.3 present the methodology for calculating the basic setpoint value, c., for the respective noble gas monitors. Monitor response and background considerations are discussed in subsection 2.1.4. Monitor setpoints detennined in accordance with this subsection will be regarded as upper bounds for the high alarm setroint. However, a lower setpoint may be established on the monitor, if desired. Also, intermediate alarm setpoints should be established at a level below the high alarm setpoint to give appropriate-warning prior to reaching the high alarm setpoint. If no release is planned for a particular pathway or if there is no detectable a eO w.ctivity in the planned release, the setpoint must be calculated in accordance ith subsection 2.1.1 or 2.1.2, assuming Kr-88 as the radionuclide being i released. If a calculated setpoint is less than the current 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. (-,. 's .): VEG' ODCM, REV 8 Draft 2.1-1
-.. - . . - - . . - . . . - . _ -. .. - - - .~ . . - _ - - - ~ - - -
4 2.1.1 Unit 1 Turbine mBuildino Vent ind Unit 2 Turbine Buildina Vent l
.O
' Monitors: 1RE-12839C (Unit 1) and 2RE-12839C (Unit 2) l NOTE: Turbine. building vent serves as the release point for the condenser air ejector and the steam packing exhauster.
For the purpose of implementation of subsection 2.5.4, the setpoint for these l , noble gas monitors will be calculated as follows: s j- c, - the calculated basic setpoint value, i . (AG) (SF) (R,) (Dn ) (1) c, - the lesser of or ] (AG) (SF) (R,) (D,,) (2) i-the safety factor, which is a conservative factor applied to ! SF
- i. each noble gas monitor to compensate for statistical fluctuations and-errors of measurement. The value of the l safety factor must be between 0 and 1; a value of 0.4 to 0.6 l is a reasonable range of values for gaseous releases. A more f- precise value may be developed, if desired.
i [ AG - an administrative allocation factor applied to apportion the release setpoints among all gaseous release _ discharge-pathways j to assure that release limits will not be exceeded by [ simultaneous releases. The allocation factor for a particular-j- discharge pathway may be assigned any desired value I between 0 and I under the condition that the sum of the 4 allocation factors for all simultaneous release pathways does ! not exceed 1. For ease of implementation, AG may be set- equal 1 ~to 1/n, i 4 lO VEGP ODCM,_REV-8 Draft 2.1-2 i m'-'-'- Y ?-d- P- a te-
where n is the number of simultaneous final gascous release
. points. For a more exact determination of allocation factors, see subsection 2,1.5.
-Dn = the dose rate limit to the total body of an individual which is 500 mrom/ year.
R, - the relaticnship between the noble gas concentration and the dose rate to the total body for the conditions of the release under consideration. R t C,+((X/Q)gfK 4 Qjg) (3) where: C. - the noble gas grab sample radionuclide concentration taken in r accordance with subsection 2.5.2, the release point under _( consideration. (5[Q')G- the highest annual average relative concentration at the site boundary. The release points addressed in this subsection are ground-level releases. (X/Q)g = 2.55 x 10-6 s/m' in the NE sector. K, - the total-body dose factor due to gamma emissions from radionuclide 1 (mrem / year / Ci/m') from table 2.1-1. Q ,, - the rate of release of noble gas radionuclide 1 (pci/s) from the vent release pathway under consideration (ground level), O VEGP ODCM, REV 8 Draft 2.1-3
which is the product of X,, and F,, where X,, is the O- concentration of radionuclide i for the particular release and F, is the maximum expected release flowrate for this release point' (X,,in Ci/ml and F, in ml/s). 0,, - 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 the noble gas concentration and the dose rate to the skin for the conditions of the release under consideration. R 3 C, -e-((X/Q)g f(L + 1.1 Mj ) Qgg) (4) where: L, - the skin dose factor due to beta emissions from radionuclide i (mrem / year / Ci/m') from table 2.1-1. A V 1.1 - the mrem skin dose per mrad air dose. M, - the air dose factor due to gamma emissions from radionuclide 1 (mrad / year / Ci/m') from table 2.1-1. - 2.1.2 Unit 1 Plant Vent and Unit 2 Plant Vent Monitors: 1RE-12442C (Unit 1), 2RE-12442C (Unit 2) 1RE-12444C (Unit 1), 2RE-12444C'(Unit i) Gaseous releases from the plant. vent (s) are regarded as mixed-mode releases in that under certain-conditions of vent exit velocity and meteorological conditions, the plume will behave as an elevated release. Under other conditions of vent exit velocity and meteorological conditions, the plume will behave as a ground-level release. 'Using the wake-split model, dispersion h values have been calculated utilizing expected annual average conditions. VEGP ODCM, REV 6 9/30/88 2.1-4
;rg The setpoint calculation methodology presented in subsection 2.1.1 applies to U these monitors with the exception that Q,, must be replaced with Q,. and (X/Q). must be replaced with (X/Q),,, where Q,, and (X70), are defined as follows:
Q ,, = the rate of release of noble gas radionuclide 1 ( Ci/s) from the plant vent release pathway undor consideration (mixed mode), which is the product of X,, and F,, where X,, is the concentration of radionuclide i for the particular release and F, is the maximum expected release flowrate for this release point (X,,in i/ml and F in ml/s.). (X/Q),,- the highest annual average relative concentration for a mixed-mode release release type (s/m'). Currently 4.62 x 10" s/m' in the NE sector. r ( 2.1.3 Gaseout Waste Processino System Discharae and Reactor Containment Purae Mcnitors: ARE0014, IRE-2565C (Unit 1) and 2RE-2565C (Unit 2) The Gaseous Waste Processing System discharges to the Unit 1 plant vent, Unit 1 containment purge discharges to the Unit 1 plant vent, and Unit 2 containment purge discharges to the Unit 2 plant vent. The plant vents are equipped with continuous final effluent monitors as discussed in subsection 2.1.2. However, due to the potential significance of releases from these sources, the setpoint methodology is also presented for the system ef fluent monitors. The :;ystem monitors have the control logic to terminate the release at alarm trip point. The final monitors have no trip logic. Sampling and analyses are completed, end monitor setpoints determined prior to ! release. These setpoints must take into account sinultaneous release pathways; the combined allocation factors for contributing pathway monitors A must not exceed the allocation factor for the final release pathway monitor to which they contribute. VEGP ODCM, REV 6 9/30/88 2.1-5 i
1 1
- Downstream monitors must also take into consideration the combinations of V source terms for the particular release pathway.
2.1.3.1 Gaseous Waste Processing System Honitor: ARE-0014 The Gaseous Waste Processing System discharges through the Unit 1 plant vent; therefore, the Gaseous Waste Processing System effluent monitor is not the final monitor for releases from this system. However, because of the significance of this release pathway and because the Unit 1 plant vent monitor setpoint has to accommodate releases from the Gaseous Waste Processing System, and the trip logic is associated with this monitor, the setpoint methodology for this monitor is presented. The methodology presented in subsection 2.1.2 applies to this monitor with the
,3 following five exceptions:
- ( _) Exception 1:- R t- r t - C , + ((X/Q)g fK g)j g (5) Exception 2: C., - the Gaseous-Waste Processing System noble gas concentration to be discharged (sample taken and analyzed prior to discharge). Exception 3: q, m the rate of release of noble gas radionuclide i ( Ci/s) from the Gaseous Waste Processing System, determined by multiplying the expected release rate by the concentration of radionuclide i. VEGP ODCM, REV 6 9/30/88 2.1-6
+
- 'Excention.4:
.d R,- r s
- C, + ((@)g fR+1.lM)q) 3 g q (6)
Exception 5: AG = a selected allocation factor value which mus'; be less than the allocation factor for the monitor serving the final release point, Unit 1 plant vent. When releases are to be made from the Gaseous Waste Processing System, it will be necessary to redetermine the setpoint for the Unit 1 plant vent monitor (IRE-12442C or 1RE-12444C), which is downstream from the Gaseous Waste Processing System effluent monitor (ARE-0014). Redetermination of this setpoint is accomplished by applying the methodology of subsectien 2.1.2 with the following two exceptions: Exception 1: l A new source term, (Q,,),, which includes the routine Unit 1 plant vent source term Q, (based on sample results from subsection 2.5.2) combinad with the Gaseous Waste Processing System source term for the tank planned for release, q,, as follows: (Oim)GP
- Oim + 91 (7) l Exception 2:
- C, =. -the noble gas concentration determined for the combined release; this concentration value is obtained by dividing f (Qi ), by the l combined flowrate (ml/s) through the plant vent.
i 7-(- < VEGP ODCM, REV 8 Draft 2.1-7
2.1.3.2. Reactor Containment Purge g) . Monitors: 1(2)RE-2565C (one for each unit) Unit I 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: 4 4
._.g R t-rt"C + m((X/Q)g fK$ q4)
(8)
.\._)3 hception 2:
. C, = the containment purge noble gas concentration to be discharged (sample taken and analyzed prior to discharge),
Exception 3: q, = the rate of release of noble gas radionuclide 1 (vCi/s) from containment purge, determined by multiplying the expected release rate by the concentration of radionuclide i. Exception 4:
'R 3
=r s - C,+ ((X/Q)g fg+1.1M)q3) j 4 (g)
.nkj-L VEGP ODCM, REV 6 9/30/88 2.1-8
Exception 5: AG - a selected allocation factor value which must be less thar 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 (l(2)RE-12442C) which is downstream from the containment purge monitor (l(2)RE-2565C). Redettemination of this setpoint is accomplished by applying the methodology of subsection 2.1.2 with the following two exceptions: Exception 1: A new source term, (Q,,)<,, is determined which includes the routine respective plant vent source term Q,, (based on sample results from subsection 2.5.2) 4 combined with the contaiament purge source term for the unit containment O planned for release, q,, as follows: 4 I0 imI CP
- Oim + 41 (10)
Exception 2: C. - the noble gas concentration determined for the cenbined release; this concentration value is obtained by dividing I (Qi-)c, by the i flowrate (ml/s) through the plant vent. 2.1.4 Consideration of Monitor Resoonse and Backaround in Establisbjng Gaseous Efflueat Monitor Setroints The calculated monitor setpoint, c,, establishes the base value for the monitor setpoint. The monitor setpoint thus calculated is in the units O VEGP OOCM, REV 8 Draft i.1-9
4
._ m pCi/ml. The monitor actually measures counts per minute, subtracts a d predete. mined background count rate, and then multiplies by a calibration factor to convert the counts per minute to pCi/ml.
Calibration of the gas monitors by the manufacture and Georgia Power Company utilized at least one NBS traceable gaseous radionuclide source, except for the main steam lines in the exact geometry of each production monitor and point-sources covering the Beta end point energy range for 0.293 to at least 1.488 MeV. The calibration factor is a function of tne radionuclide mix in the gas to be released and will be calculated for the monitor based on the results of the predischarge sample results from the laboratory gamma-ray , spectrometer system, t The mix-dependent calibration factor will be used as the gain factor in the PERMS monitor or used to modify the calculated base monitor setpoint so the default calibration factor can be left in the PERMS monitor. l Contributions to background radiation levels may include ambient background, , V 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. Background levels must be controlled such that radioactivity levels , 1 in the effluent stream being monitored can be accurately assessed at or below the calculated setpoint value. s i 2.1.5 Determination of Allocation Factor. AG When simultaneous gaseous releases are made to the environment, an (administrative) allocation factor must be applied to each discharge pathway. This is to ensure that simultaneous gaseous releases from the site to unrestricted areas will-not' exceed the dose rate limits specified in Technical Specification 3.11.2.1. For Plant Vogtle, final discharge pathways which may 1 be released simultaneously are the Unit 1 plant vent, Unit 2 plant v L VEGP ODCM, REV 6 9/30/88 2.1-10 l
p vent, Unit 1 turbine building vent, Unit 2 turbine building vent, and the DAW l ( processing building vent, The allocation factor for each gaseous discharge i Lpathway must be between 0 and I and the sum of the allocation factors for the 1
- simultaneous releases must not exceed 1.
There are three methods by which allocation factors may be determined:
- 1. The allocation factor for a particular release pathway may be administratively selected based on an estimate of the fraction of the total dose rate (from all s.imultaneous releases) which is contributed
, by the particular release pathway. If the building is not in service for its intended function an allocation factor of zero can be used for that building.
- 2. The allocation factor may be calculated using the expression AG = 1/n (11) where: n = the number of. release pathways to be released simultaneously.
- 3. The allocation -factor may be determined for a particular discharge
. pathway by_- calculating the ratio of the total _-body dose rate due to noble gases released from the particular discharge pathway under consideration to the total-body dose rate due to noble _ gases in all simultaneous releases, as follows:
-For Unit I turbine building vent and Unit 2 turbine-building vent
! (ground-level releases): I gg , (X/0)G .i Ki Q idH (12) (X/Q)GnffN(Q i ig Ing + -(X/0)M nm fKi- (Qim)nm lQ 'VEGP.ODCM, REV 8 Draft 2.1-11 L
A i
,for Unit 1 plant vent and Unit 2 plant vent (mixed mode releases), )
L/ (X/Q)g I, K3 Qimlr) Ag , _ . _ _ (13) I I - I I ! (X/Q)G ng. i Ki (O ig Ing + (X/Q)H nm i Ei (O im Inm where ng .is the number of simultaneous vent releases (ground level); nm is the number of simultaneous vent releases (mixed mode); and (r) is the particular discharge pathway.for which an allocation factor is being determined. Wheri using equations 12 and 13, be sure to include the DAW pr(cessing building vent for.the particulate re_ leases. 2.1.6 Particulate Effluent Jonitor Setooints Particulate effluent monitor setpoints for nE-12442A, RE-2565A, and ARE-13256 are' determined using- the method outlined for gaseous effluent monitor setpoints. Co-60 and. lung organ were used as the main isotope and organ, Os . Reference 18 details the way the initial setpoint-calculations were made for certain monitors. f t O VEGP ODCM, REV 8 Draft .Z.1-12
TABLE 2.1-1 O DOSE FACTORS FOR EXPOSURE TO A SEMI-INFINITE CLOUD OF NOBLE GASES
- Gamma Beta Gamma Beta
!!qqlidg -Bodv***(K) -Skin ***(t) - Ai r** (til - -Air **(N)
Kr-83m 7.56E-02 1.93E+01 2.88E+02 Kr-85m 1.17E+03 1.46E+03 1.23E403 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 1.66Ev04 1.01E404 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.llE+03 O 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.llE+02 3.36E+03 7.39E+02 Xe-135 1.81E+03 1 86E+03 1.92E+03 2.46E+03 Xe-137 1.42E+03 1.22E+04 1.51E+03 1.27Etet Xe-138 8.33E+03 4.13E+03 9.21E+03 4.75E+03-Ar-il 8.84E+03 2.69E+03 9.30E+03 3.28E+03
- Values taken from Reference 3, Table B-1.
** _prad-m' pCi-year
*** mrem-m' pC1-year O
VEGP 00CM, REV 4 7/30/87 2.1-13 4
. . , - - - _ = . .- .- .. . -. . .- . -. - . ,
, t.
e s TABLE 2.1-2 - -(J GASE0US RELEASE PolNTS FLOWRATES Release Point Flowrates i ft /3 min mlja ,- Plant Vent (Unit 1) 1.5E05 7.08E07
- Plant Vent (Unit 2) 9.0E04 4.25E07 I .
Turbine Building Vent (Unit 1; Condenser 9.0E02 4.25E05 Air Ejector and Steam Packing Exhaust)
-Turbine Building Vent (Unit 2; Condenser 9.0E02 4.25E05 kir Ejector and. Steam PacU ng Exhaust)
Dry Active Waste Processing Building Vent 2.20E3 1.04E6
.n y
IIeference 5, Tables-11.5.2-1 and 11.5.5-1. 1 { VEGP ODCM, REV 8 Draft 2.1-14
~
l I l i ( qf-2.2 -GASECUS EFFLUENT DOSE RATE AWD DOSE CALCULATIONS i 2 2.2.1 ?Qase Rates at or Beyond Site Boundary . i e .
- 2.2.1.1' Dose Rates Due to Noble Gases For the purpose of implementing subsection 2.5.1, the dose rate in areas at or-l beyond_ the site boundary due to noble gases shall be calculated as fellows:
D, = the total-body: dose rate at time of release (nr em/ year),
= +
(X/Q)G n Ki (Nig)ng (X/Q)M nm Ki (O im Inm (14) D, - the- skin dose rate at time of release (mrem / year).
+
(l ia 1.lM )j Wg g)ng (X/Q)M'nm (l -.+ i 1.lM 3)(Q 4,)nm 1
'(X/Q)G n (15) _
Where: ng -- the number of simultaneous- ground-level vent releases, and nm =
= the number of simultaneous mixed-mode vent releases, Other terms were defined previously in subsection 2.1.
The-dose rate limits are site limits at any point in time; therefore, dose-i rates- are s'ummed over all-gaseous releases' occurring simultaneously. _ For Plant Vogtle, Unit-1 turbine building vent and Unit 2 turbine building vent -l are-ground-level. rcleases. _ Unit 1 plant vent and Unit 2 plant vent are mixed-mode-releases. l - 7 ' O(/ - VEGP ODCM, REV 8 Draft 2.2-1
_ . _..= _..- _ _. ~ 2.2.1.2 Dose Rates Due to 1-131, 1-133, Tritium, and Particulates L
-For the purpose of. implementing subsection 2.5.1, organ dose rates due to l 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 aga group. The child age group would experience the highest potential dose rate via the inhalation pathway. These dose rates are calculated as follows:
D, = the organ dose rate at time of release (mrem / year). (X/Q)G n P jg (Qj'g)ng + (X/Q)H nm P jg (Q3',)nm b6) where: nm and ng = defined previously in paragraph 2.2.1.1. ('X3)g defined previously in subsection 2.1.1. (X/Q)k
= defined previously in subsection 2.1.2.
Q[, = the release rate ( Ci/s)'of I-131,1-133, tritium, and particulates from Unit I turbine building vent; Unit 2 turbine building vent; and dry active waste processing - l' < building vent which are ground-level releases. NOTE: DAW is particulates only. F
^
. Q[, = the release rate-( Ci/s) of I-131,1-133, tritium, and particulates 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 radionuclide i, 3 (mrem / year per pCi/m ) for inhalation determined as
-follows:
'Pg =
K'(BR) DF jg
]37)
-VEGP ODCM, REV 8 Draft 2.2-2
- where:
G K' = the constant of unit conversion,10'pci/ Ci. BR = -the breathing rate for child age group; 3700 m'/ year from table 2.2-10. DF,, - the inhalation pathway dose factor for child age group for organ o and radionuclide i, from tablt 2.2-2. NOTE: To ensure that potential dose rates (pre-release) to an organ due to I-131, I-133, tritium, and particulates in simultaneous gaseous relenses from the site do not exceed 1500 mrem / year as specified , in subsection 2,5.1, the potential organ dose rate D, must be l limited as follows: Do + (AG)(SF) $ 1500 mrem / year (18) h V where AG and SF-are assigned the same values as were used in subsection 2.1 for the gaseous discharge pathway under consideration. To further ensure that dose rate limits were not exceeded (post-release), dose rates from simultaneous releases should be summed, as shown in equation (16) above. 2.2.2 Air Doiqs and Dose _to a Member of the Public at or Beyond the Site Boundary g 2,2.2.1 Air Doses at or Beyond the Site Boundary For the purpose of implementing subsection-2.5.2, air doses in areas at or-beyond the site boundary shall be determined as follows: O VEGP ODCM, REV 8 Draft 2.2-3
p D ,, _ = the air dose due to gamma emissions from noble gas A - radionuclides (mrad)
- 3.17 x 10'8 (X/Q)gfM $ ljg + (X/Q)g{Mg4, 4 (19) where:
3.17 x 10 - the fraction of one year /one second. Q,, - the cumulative release of noble gas radionuclide i over the period of interest ( Ci) from the vent release (ground level) under consideration. Q,, - cumulative release of noble gas radionuclide i over the period of interest (yci) from the' vent release (mixed-mode) under consideration. yN : $1, - defined previously in subsection 2.1.1. l . L) . (X/Q)g- - 2.55 x 10 s/m' in the NE sector. (X/Q)g = 4.62 x 10 s/m' in the NE sector. D,,,, - the air dose due to beta emist 'ons from noble gas c radionuclides (mrad).
- 3.17 x 10 -8 (X/Q)g fNg Ugg+(X/Q)gfNgH, j (20) where:
H, - the air dose factor due to beta emissions from noble gas radionuclide 1 (mrad / year /pCi/m'), from table 2.1-1.
. f-)
.u ,
VEGP ODCM, REV 8 Draft 2.2-4
p 2.2.2.2 Dose to a Member of the Public at or Beyond the Site Boundary
-U
. Doses to a member of the public due to 1-131, 1-133, tritium, and radioactive materials in particulate form, in gaseous releases, will be calculated for the purpose of implementing subsection 2.5.3 as fellows: l (NOTE: The member of the public expected to receive the highest dose in the plant vicinity is referred to as the controlling (or critical) receptor. The dose received depends on the location, age group, and exposure pathways present. For Flant Vogtle, the controlling receptor (s) for which doses must be calculated, and the applicable exposure pathways, are presented in table 2.2-12.)
0, - the dose to an organ j of an individt.al in age group a from radiciodines, tritium, and radionuclides in particulate form with half-lives greater than 8 aays (mrem).
~0
- 3.17 X 10 pfRaipj(UdP ig +NSP-iu) (21)
I where: 3.17 x 10 - the fraction of one year /one second. pi - for all pathways and all isotopes. Wfp
- the pathway-dependent relative dispersion or deposition at the location of the controlling receptor, associated with ground-level plant releases. as follows:
(X3')cp - the annual average relative dispersion parameter for location of controlling (critical) receptor for ground-level plant releases. (X/Q')gp applies only to inhalation and all tritium pathways. (For all tritium pathways the Q' p source term is limited to tritium.) See table 2.2-12 for l d value. i VEGP ODCM, REV 8 Draft 2.2-5
1 i ()__ (D/Q')gp = the annual average deoes" ion parameter for the location of ! controlling (critical) receptor for ground-level vent j releases. (D/Q')gp applies to all other pathways. See table 2.2-12 for value. . 1 Wfp
- the pathway-dependent relative dispersion or deposition at 3 the location of the controlling receptor, associated with ;
plant vent releases, which are mixed mode as follows: 1 (X/Q')dP = the annual average relative dispersion paramete. for location of controlling (critical) receptor for mixed-mode releases. (X/Q')gp applies only to inhalation and all tritium pathways. (for all tritium pathways, the Q'i 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 controlling (critical) receptor for mixed-; node releases. (D/Q')MP applies to all other pathways. 'See table 2.2-12 for values. The selection of the dispersion or deposition parameter, X/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, 13 required for the ground plane pathway and I-131,1-133, and particulate contributions- to ingestion. pathways; ( = the cumulative release ( Ci), from ground-level plant releases, of radionuclide i, as required by subsection 2.5.3 over the period of interest.. Dose determinations required by A V. VEGP ODCM, REV 8 Draft 2.2-6 L
d a I subsection 2.5.3 are on a per reactor basis; therefore, l cumulative release quantities must also be unit specific. Since the dry acthe waste processing butiding serves both l ; o units, release quantities must be Ppportioned between the two units. In absence of evidence that one unit contributes a _ greater quantity of radioactivity than the other over the l period of interest, release quantities may be apportioned l equally between the two units. (For dose contributions due to ! tritium from the ingestion pathways, the D 9 term is limited l to tritium.) i p
- 06 - the cumulative release (vCi), from the mixed-mode plant l vent releases, of radionuclide i as required by subsection l 2.5.3 over the period of interest. Dose determinations required by subsection 2.5.3 are on a-per reactor basis; '
l therefore, cuniulative release quantities must also be ;
~
unit-specific. (For dose contributtons due to tritium from the ingestion pathways, the term ha is limited to tritium.) R ug
- the pathway-specific,-individual age-speciftc. organ dose ,
factor for radionuclide 1,. pathway p, organ j, - - 3 individual . age group, a. Routine individual dose K'icu1Giors address ' the inhalation, ground plane, grass-cow-mik,
- . grass-goat-milk, grass-cow-meat, and garder /cgetation pathways. However, the dose pathways actually present at the ,
controlling. location, as well as the controlling individual age group, are determined through the Land Use Census for the site vicinity and are presented in table 2.2-12. Pathway ~ factors Rgg are determined as shown in the following subsections. g Plant Vogtle site-specific values, or appropriate default values,- required a L the pathway factor determinations are presented in table-2.2-13, ; y lL lO l VEGP.0DCM, REV 8 Draft 2.2-7 l
*m-e vr-+---We--,,_ ..,.%.,,.,--. ,... .-.....,ei.-m- .
--,.-eme%.,--
. 3 ._ :.-,s ..a-,---- e-~ww.---y.,..-,-.ew-,,,,,,,,-y,,ww-wwe,-ry Nw-
- InhalatioJL Pathway Facto.t ;
O R,gpj
=
X'(BR),(DFAgj),mram/ year /#Cl/m3 (22) 1 where: , i K' - the constant of unit conversion 10' pCi/vCl. I (BR), - the breathing rate for a particular ago group in m'/ year from table 2.2-10. i DfAy , - the inhalation dose factor for receptor age group a, organ j, i' and for radionuclide i, in mrem /pCi from tables 2.2-1 through 2.2-4. Ground-P1ane Pathway.J K 1.g.t
=
ic R,jpj K'K" (SHF)(OfG,3) ((1-e'Al l)/Ag) (23) (m' mrem / year / Ci/s). where: , K' = the constant of unit conversion,10' pCi/mC1. , 4 K" = the constant of unit conversion, 8760 h/ year, , SHF- = .the shieloing factor. 0,7 (dimensionless). DFG y - the ground-plane dose conversion factor for radionuclide 1
- (same for all age groups and specific organs are assumed to receive the same dose as the total body) (mrem /h/ pCi/m') table 2.2-9. ,
- A.,( a. the decay constant for radionuclide i, in s.
t a the exposure time, 4.73 x 10' s (15 years). r VEGP ODCM, REV 6 9/30/88 2.?-8 H /-gr-+-we+p-Tmi--yig-wyidag rgy v mwr'Tr-FM-PP'_ '
l l l l Veaetation Pathway Factor R,jp) = K'y gj j (OfLjj),(U,g ff e~Ait4 t U n yf e -Ai thv) (24) (m' mrem / year per Ci/s) where: K' = a constant of unit conversion,10' pC1/ Ci. r - the fraction of deposited activity retained on vegetation (1.0 for radiciodines; 0.2 for particulates). 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 n in age group a, in kg/ year. (See table 2.2-10.) U f, - the fraction of the annual intake of fresh leafy vegetation growa locally, f, = the fraction of the annual intake of stored vegetation grown locally. t, = the average time betweer harvest of leafy vegetation and its consumption in s, (8.6 x 10').
' t ,, - the average time between harvest of stored vegetation and its consumption in s, (5.18 x 10').
Y, - the vegetation areal density, in kg/m*, l (DFLy ), - t.he organ ingestion dose factor for the ith '_ radionuclide for the receptor in age group a, in mrem /pci from tables 2.2-5 throtgh 2.2-8. VEGPODCM,, KEV 4 7/30/87 2.2-9
.-. .-- ..--.- = _
):
A, - the decay constant for the ith radionuclide, in s. A, - the decay constant for removal of activity on leaf and plant surfaces by weathering, 5.73 x 10" s (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 bn en .'n airborne concentration rather than deposition: R. , ,, = K 'K'"(U., f, + U.,f,) (DFL,,), (0.75(0.5/H)) (25) (mrem / year / Ci/m') where: K'" - - a constant of unit conversion,10' gm/kg. H - the absolute humidity of the atmosphere, in gm/m'. 0.75 - the fraction of total vegetation that is water, 0.5 - the ratio of the specific activity of the vegetation water to the atmospheric water. Other parameters and values are given above. Erns-Cow-Hilk Pathway Factor l-os
~
R 8"gFm (r)(DFLij)a *+ ,-A tgf (26) aipj = K 'Aj+A Y p Y s
. (m' mrem / year /pCi/s)
O i VEGP ODCH, REV 6 9/30/88 2.2-10 l l
s where: K' - a constant of unit conversion,10' pCi/ Ct. O, - the cow's consumption rate, in kg/ day (wet weight). V., - the receptor's milk consumption rate for age group a, in liters / year from table 2.2-10. 1 Y, - the agricultural productivity by unit area of pasture feed grass, in kg/m'. Y, - the agricultural productivity by unit area of stored feed, in kg/m'. , 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 particulates). (OfL ), 3
- the organ ingestion dose factor for the ith radionuclide for the receptor in age group a, in mrem /pti from tables 2.2-5 through 2.2-8.
A, - the decay constant for the Ith radionuclide, in s". A,, - the decay constant for removal of activity on leaf and ! plant surfaces by weathering, 5.73 x 10" s" (corresponding i to a 14-day half-life), t, = the transport time from pasture to cow, to milk, to receptor, in s (1.73 x 10').
- the transport time from pasture, to harvest, to cow, to O t,.
milk, to_ receptor, in s (7.78 x 10'). VEGP ODCM, REV 4 7/30/87 2.2-11
- .*w--y -g-w wr,---wr..m-r-r-,-rs, wn.--,------erowse -- , ,, wy - .s,-~,.w. ---a. , - - , - - , , - - c -+ gr w w w r w - i., - r ipp ,ri--+
t i
'2.3 METEOROLOGICAL MODEL (References 7 tad 13. and subsection P.3.5 of Reference 5) 2.3.1 Atmospherie Dispersion >
Atmospharic 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 pround level are releases from the turbine building (s) vents and the dry l l active waste processing building vent. Releases from reactor building (s) (plant) vent (s) are considered to be mixed mode. (See NOTE in subsection 2.1.2). 2.3.1.1 Ground-level Releases (X/Q), - the ground-level sector-averaged relative concentration for a given wind direction (sector) and distance (s/m3 ). U
- (RCF) 2.032 d p jf .i k (38)-
NHjk
- I d '
wiare: 2.032- - (2/tr)uz divided by the number of radians in a 22.5r sector. (0.3927 radians). ' d, - the plume depletion factor for all radionuclides other than noble gases 'at a distance x shown in figure-2.3-2 for ground-level releases; for noble gases the depletion factor is unity. 'If an undepleted relative concentration is desired, the depletion .fa'ctor is unity. - Only depletion by deposition is considered.since. depletion by decay would be O-of-little significance; at the distances considered. VEGP ODCM, REV 8 DRAFT 2.3-1 e .
-~<vn.a,,,-, , , - - , .-.n., ....--..n . . , , , ...,,---,,,w--,,-,,,,, _,,wav_,
I I RCF = the open terrain recirculation factor. Values for specific distances are obtained from Appendix A of Reference 13. ny - 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 frequency data, the summation over j and k is deleted and the summation is accomplished for all hours at all distances for each direction. N = the total hours of valid meteorological data throughout the period of interest. up = the wind speed (mid-point of windspeed class j) at ground levol (m/s), during stability class k. x = the distance from release point to location of interest (m). I,, = the vertical standard deviation of the plume concentration distributaon considering the initial dispersion within the building wake, (o', + (b'/2n))"'
= the lesser of or
\ O(U.)
o,
- the vertical standard deviation of the plume concentration distribution (m) for a given distance and stability category k as shown in figure 2.3 1. The stability categnry is determined by the '.ertical temperature gradient AT/aZ (oC/100 rn),
n = 3.1416 b = the maximum height of adjacent plant structure (55 m). O VEGP ODCH, REV 6 9/30/88 2.3-2
1 2,3.1.2 Mixed-Hode Releases ( X/Q)., = the mixed-mode sectnr-averaged relative concentration for a given wind direction (sector) and distance (s/m').
= 2,032(RCF)d p % "ik E (39) jk Nx ug lik 2
+
exp(-h/20h) jk zk where: d, - the plume depletion factor for all radionuclides other than noble gases at a distance x shown in figures 2.3-3 inrough 2.3~5 for elevated releases; for noble gases the depletion factor is unity. If an undepleted relative concentration is desired, the depletion factor is unity. Only depletion by deposition is considered since depiction by decay would be of little significance at the distances considered. U3 = the wind speed extrapolated to the effective release height. Extrapolation is accomplished by rais1ng the ratio of the two heights to the n power where n = 0.25, 0.33, and 0.5 for unstable, neutral, and stable conditions, respectively. (Reference 5, subsection 2.3.5.) E = the fraction considered as ground-level releases. W U l.0 for. $ 1.0 W W 2.58 - 1,58 (-u ) for 1.0 < s 1.5 , W W 0 0.3 - 0.06 (-" ) for 1.5 < 5 5.0 W 0 for > 5.0 I VEGP ODCH, REV 8 Draft 2.3-3 7
---e -- m ,e y -----ee,e, a,=- ,-
---ee-rv--- ,,,..-y.- , - - ,wv ,--s e em n a. , c--rm u m e-<e.-n e-m,*
l W, - the vent exit velocity (m/s). h - the effective release height (m).
= h , + h ,, - h, - c , (40) h, a the height of release point (m).
- h. - the nximum terrain height between the release point and the point of interact (m). (Seetable2.3-1.)
h,, - the additional height due to plume rise (m).
=
1.44d (W g /u)2/3(x/d)I/3 (41)
- limited by the lessor of the follnwing two equations:
h ,, ,,,, , , - 3(Wg /u)d or hpr(max)=1.5((/u) S M d - the inside diameter of vent, c, . the correction for low vent exit velocity (m). W W 0 3(1.5 - )d for - s 1.5 W 0 for u
> 1.5 F ,' - the momentum flux parameter (m*/s').
(W.)' (d/2)' S- - the stability parameter. 8.75 x 10** s* for -0.5 < AT s 1.5 1.75 x 10** s for 1.5 < AT $ 4.0 2.45 x 10 s for AT > 4.0 r ( Other terms were defined in subsection 2.3.1.1. VEGP ODCM, REV 4 7/30/87 2.3-4 e- J. -v--' ..,.,w.. ., , ..,e - ,e - -,,.~,.,,,,,y ,.
l 2 .3.2 Ech.t.ive Dep2sition O 2.3.2.1 Ground Level Releeses (D/Q), - the ground-level sector-averaged relative deposition at a given distance and for a given sector (1/m'). n (RCF)f2.55Dq k (42) Nx where: 2.55 - the inverse of the number of radians in a 22.5c sector ( 2 17/16 ) . D, - the deposition rate at a given distance, taken from figure 2.3-6 for ground-level releases, n, a the number of hours the wind is directed into the sector of interest, during which time stability category k exists. N - the total cumber of hours of valid metect. logical data. RCF - the open terrain recirculation factoi'. Values for specific distances are obtained from Appendix A of Reference 13. 2.3.2.2 Miaed-Mode Releases (D/Q),, - the mixed-mode se. tor-averaged relative deposition at a given distance and for a given sector (1/m').
-2' (RCF) ((E)(D g ) + (1 - E) De )
(43) O , VEGP ODCM, REV 8 Draft 2.3-5
where: 3O ! D, = the relative deposition rate for the ground-level portion of i mixed-made releases from figure 2.3-6. i D, - the relative deposition rate for the elevated portion of l mixed-modo releases from figures 2.3-7 through 2.3-9. E = the fraction of releases considered as ground level. Other terms were defined in previous subsections. i . l l l-lO l 4 l i l l s i O VEGP ODCH, REV 4 7/30/87 2.3-6
r TABLE 2.3-1 (SHEET 1 0F 2) TERRAIN ELEVATION AB0VE PL ANT GRADE WIND DIRECTIC.4 FROM PLANT 10 RECEPT 0R 01 stance M. N NNE JL. [E _L [5.1 ,,SL 151 : 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 0.0 0.0 0.0 0.0 0.0 0.0 3,500 0.0 u.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 10,000 0.0 15,9 26.8 20.2 0.0 0.0 17.1 19.5 14,000 0.0 15.9 26.8 20.2 0.0 0.0 17.1 19.5 16,000 0.0 15.9 26.8 21.7 13.2 0.0 17.1 19.5 O
1 l p O Reference 5. VEGP ODCH, REV 4 7/30/87 2.3-7
TABLE 2.3-1 (SHEET 2 Of 2) O TERRAIN ELEVATION AB0VE PLANT GRADE WIND DIRECTION FROM FLANT TO RECEPT 0R Distance (mi_ _L ssw sw gs w gyg Jw_ gy 500 0.0 4.7 8.7 S.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 1.3 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 1 ". 6 7.3 12.2 16.9 7.3 1 4,000 0.0 4.7 24.4 d.6 1.3 12.2 16.9 7.3 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 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 7.2 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 O l l l l l O VEGP ODCM, REV 4 7/30/87 2.3-8
** . 1" ++ ,
,A jj',f* ;
3 i i / ! > 4 _[ > / M11
/ / / / \ !
q l
/
f - l/yf ,n
' ~'
<;/ .- - 'io1 - 1 11
- 1 A y'i W !i! /6 / e i i 1#' ! I 's l V / ! / i t,/ / lA i*ff ff ll 5
e"
, [,V,/l
/ /
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. r 7 1-Y;ff / . ... l , , . I t ii , i , ....i i i i i t e li- i i . l iii 7(([f i i gll i ali l l: l l lI , I I ll ll
/ l,
'ei u is im Ptutet TRAvf L CHETMcCt 7EttoastillL81 Range of Vertical Range of Vertical Catecory Temperature Gradient ('C/100m)
Tenperature Gradient (*F/100f t) A oT/AZ < -1.9 AT < -1.0 B -1.9 < 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 < AT/al < -0.5 -0. 8 < AT < -0. 3 E -0.5 5 ST/o1 < 1.5 -0.3 $ of < 0.8 F 1.5 5 4T/aZ < 4.0 0.8 5 AT < 2.2 G 4.0 $ AT/AZ 2.2 5 ST
- Ref erence 7.
O(j VOOTLE VERllCAL $1ANDARD DEylA110N Of MATERIAL IN A FLUME (0,)*
"*"""'**' (tetters De e te Pasqu111 st ai11ty class)
Georgia Power E.E',"$7u"u'ir FIGURE 2.3-1
" V GP ODCM REV 4 7/30/87 2.3-9
l l (m) v I 1 is _ N e.s __
%g~ ~-
w o I N % 5 N e r o.7 N ' b 5 E os \ \ 3 N a o.s \q 5 ss G e4 A os o.2 o.1 %J o.s 1.o so.o 100.0 200.0 PLUME TRAVEL DIST ANCE (KILOMETERS)
- Reference 7 h
L/ "OG T " PLOML DLPLEllON EfFLLI FOR GROUNU-LEVEL RELEASES Georgia Power Ml,l'/ j o"u l"* " " ^"' _( All Atmospheric Stability Classes) FIGURE 2.3-2
"" VEGP ODCM RLV 4 7/33/87 2,3-10 j
]
(') N.) 1.0 03 Nttsf AL (l) E r, I w 0.8 . M 0.7 _ . . . _ s E 3 UNST ABL E q\ g 0.6 --- ( A,0,Cl- , Q,
=05
- 9 y w
~
5 j 02 -- 0.1 -_. . . . 0.1 0.1 1,o 10.0 100.0' .200.0, PLUME TR AVEL DIST ANCE (KILOMETER $) 9 Reference 7. I VOGTLE PLUME DEPLETION EFFECT FOR 30-METER RELEASE 5* ELECTRIC GENERATINO PLANT (letters Denote Pasquill $tability Class) Georgialbwer univ i ANo unir a flGURE 2.3-3
'"' VEGP ODCM REV 4 7/30/87 2,3-11
l O V 1,0 _,. 57ABLE
^% % M ' '* % (f.F,0) i 09 -
)N,,,r--x-s -
- NEll1RAL x
0.8 - -~ op t -pygyg\agg '%. r 0.7 - 3 y IA.B.cl y 0s s. t r N e 0.6 - \ 8 N 604 \ I
" 0.3 -
b.
'y 0.2 0.1 0.1 1.0 10.0 100 0 200 0 PLUME TR AVEL DISTANCE (KILOMEf t P.Sl
- Reference 7.
C% .. 5 V voGTLE PLUME DEPLE110H EFFECT FOR 60-METER RELEASC$* LLECTRIC GE NE R ATING PL AN T (letter $ Denote P45 Quill St4bility Cl8$$) Georgia Power A unit i AununiT r FIGURE 2.3-4
"'" VEGP ODCM REV 4 7/30/87 2.3-12
O 1.0 _. i' ~
~m o.9 N w * % m NEUTRALID) ,
N , , K w o.s N \ f 0.7 UNSTABLE IA.s ci \ s\ N
~
ST ABLE (E,F,0) h 0.0 NO DEPLET10N
\
l (FRACTION REMAINING = 1.0) \
\
-\
E o.5 6 \
\
g o.4 J 0.3 o.2
' O.)
o.1 1.0 . 10.0 i 100.0 200.0 PLOME TRAVEL DISTANCE (KILOMETERS)
- Ref erence 7.
V vooTLs. PLUME DEPLETION EFFECT FOR 100-METER RELEASES
- Georgia Power A 'Z",'f.o*'"O^""'^"' (Letters Denote Pasquill $tability Class)
FIGURE 2.3-5
**" VEGP ODCM REV 4 7/30/87- 2.3-13
,i
~
[ 10A v ___ i--
^
I _ . _ .___ .._.., I 104 \ hat- . 2 ^% b W y
\..
y N. ---. Nt e . _. ..
; \ _
tiE %
.s NN
$ 10-5 L w m ,
x g -- m (o' s O \ C/ y
\ N P
5 W a
\ s 10-6 h
10-7 0.1 1.0 10.0 100.0 200.0 PLUME TR AVEL DISTANCE (KILOMETERS) n k-"j vooTLE RELATIVE DEPOSITION FOR GROUND-LEVEL RELEASES Georgia Power m_. L'5',",lol"Jir"$"""*' (All Atmospheric Stability Classes) FIGURE 2.3-6
"" VEGP ODCA REV 4 7/30/87 2.3-14
. .. - _-_ =- . - - . _ _ _ - _ . - _ . - - - - __ _ - . . .- ._- .-_
l h 10-3 i i 7
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y,y -
! f f Ii. .
i
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i i !it ! I i iili l UNSTABLE ( A,B,C) ill n 10 4 ^! It!!! y y / K_ i X .. i !_ i_ i p /
) i Q *i! i 1 3 i1 . > II W _f 1 i !N+ 1 !
$ i i fi h : l i g l [ l \\ NEUTRAL
- 1 I
Wss 2 ll llll \hg\ 9 10-5 l NEUTRAL l lllll (D) Q STABLE o _, if i ! !
' ", .! y f*t v i 3 1
4 4 4 1 e i i I ! If Y hi I'
$ I ii i i/! AN iXi O w
/i
/!
i I I ll /
/li li
'CW X XI W 2 / / l bJ lh
=
, nl STABLE (E,F G) xq N 10 6 . i ! !!! ! .
I l [ . ! I + i ' i l3 I I ! I i i
!t f i I i
_./ 1 i i ii
/ t I i l
/ I l /
10-7 0.1 1.0 10.0 100.0 200.0 PLUME TRAVEL DISTANCE (KILOMETERS) l
- Reference 7.
1 - VOOTLE RELATIVE DEF'SITION FOR 30-METER RELEASES
- Georgia Pon,er k EltcTnic otNERATING PL ANT (Letters Denote Pasquill 5tability Class)
- z. UNIT I AND UNIT 2 FIGURE 2.3-7
*'" VEGP ODCM REV 4 7/30/87 2.3-15
l C ~"
; i i i4 ,
iI ; ;
~
! i i
' I i jii UNST ABLE (A.D CilM _ .
VI N i li ! ! I !11
/l ,,N3 I l 10-5 NEUTRAL (D)l g 1
;, y
-j_ - xkg _
i[.!i!I
/
. 1
_ hkN \A
* / 3 !Ii i ! i i i ! l! 1i,
$ I/l I l l !!! ilI \ 'N UNST ABL E 5 / I i Ill i N 31 '
NEUTRAL i / NJ N
=
$ 10-6 I l ! },
- 1 h [~ 4 .i' .
i i '_f g I ! J! - . i ! i i i/1 C: ;;. t/i I
? f 5 i _
E f I l ' i STABLE (E,F.G) 10-7 7. 3 ' 4 _ i f l I f l ; Tj ,.____
! ii l li il i I 1 ji I
/
I 10-8 ). .. - 0.1 1.0 10.0 100.0 200.0 PLUME TRAVEL DISTANCE (KILOMCTERS)
- Re f e r ence 7, vooit E RflATIVE DEPOSITION FOR 60-METLR RELEASES *
(.JCorgia l,OWCf Ka*
- k LL EC1 HIC OE NE RATING PLANT UNIT 1 AND UNIT 2 (letters L)enote Pasquill Stability Class)
FIGURE 2.3-8
~ "" VEGP OLCM REV 4 7/30/87 2.3-16
f C . i . iiii ii: 1 1 i,1 i i i ii l i jli i ! i l i L_ UNSTABLE ( A,B,C)' i l l [ \ s NN 10-5 ; -4
- : li ii . ei i 4 m
.iw . 1 ii
~
h
/ , / NEUTRAL (D)
%k y / I/ NPN cc / I/ N '
't
! / / _
N N Nh E 10-6 . I ' p l , ,- G
-[ j ; ;
2
~
r , i i l I i a / y STABLE (E,F,G) , l NO DEPLETION 10-7 ; I I I
, ii .
,1 !li
/ I f i I j l
- s. l 0.1- 1.0 10.0 100.0 200.0 PLUME TRAVEL DISTANCE (KILOMETERS)
' Reference 7, O . . . a._ .
voorLE a RELATIVE DEPOSITION FOR 100-METER RELEASES * (teuns en te Pasquiii stability ciass) GeorgiaPower A Ed?',"L'u"dr;mmur , FIGURE 2.3-9
'" VEGP _0DCM REV 4 7/30/87 2.3-17
2.4 DEFINITIONS OF GASEOUS EFFLUENT TERMS Igr.a dan nition Initial Use AG = the administrativa allocation factor for t.l.1 l gaseous effluent pathways (unitiess). l l BR = the breathing rate for individual from table 2.2-10 (m'/ year). 2.2.1.2 b = the maximum height of the adjacent 2.3.1.1 building (m). C, = Noble gas grab sample concentrations, taken 2.1.1 in accordance with subsection 2.5.2, for
;he release under consideration, c, - the calculated basic monitor setpoint value. 2.1.1 i (vCi/cc) ,
c, - the correctica to effective release height due to low vent exit velocity (m). 2.3.1.2 i D,, - the limiting dose rate to the total body of 2.1.1 an individual in an unrestricted area which is 500 mrem / year. ! D, - the total body dose rate at time of release 2.2.1.1 (mrem / year). I D., = the limiting dose rate to the skir of an 2.1.1 individual in an unrestricted area which is 3000 mrem / year. ' O VEGP.0DCM, REV 8 Draft 2,4-1
l Subsection of Igng D.gfinition Initial Use D, - the skin dose rate at time of release 2-2.1.1 (mrem / year). D, - the organ dose rate at time of release 2.2.1.2 ; (mrem / year). DF , - the inhalation pathway dose factor for child 2.2.1.2 age group for organ o and radionuclide i (mrem /pti inhaled) from table 2.2-2. D,,, , - the air dose due to beta emissions from 2.2.2.1 noble gases (mrad). 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 radiciodines, tritium, and radionuclides in' particulate form with half-lives greater-than eight days (mrem). , I (DFA,n, - the inhalation dose f actor-for the ith 2.2.2.2 radionuclide for the receptor in age group a (mrem /pci) from tables 2.2 through 2.2-4. DFG,, - the ground plane dose conversion factor for 2.2.2.2 radionuclide i (saue for all age groups) (mrem /h per pCi/m') from table 2.2-9. 7
-(DFL,n,_ - the organ ingestion dose factor for the 2.2.2.2 ith radionuclide for the receptor in age group a (mrem /pC1) from. tables 2.2-5 l through 2.2-8.
p l VEGP ODCM, REY 4 7/30/07- 2.4-2
Subscetion of O Isra hfinition InitiaLuis d, - the plume depletion factor for all 2.3.1.1 radionuclides other than noble gases at distance x (unitiess). d - the inside diameter of plant vent (m). 2.3.1.2 l D, - the deposition rate for ground-level 2.3.2.1 releases (m *). D, = the deposition rate for elevated releases 2.3.2.1 (m) . E - the fraction of release considered to be 2.3.2.1 ground level (unitiess). the fraction of the annual intake of fresh 2.2.2.2 Oe f a leafy vegetation grown locally (dimer.sionless). f, - the fraction of annual intake of stored 2.2.2.2 vegetation grown locally (dimensionless), f, = 'he fraction of the year that the cow 2.2.2.2 wr goat) is on pasture (dimensionless), f, - the traction of the cow (or goat) feed 2.2.2.2 that is pasture grass while the cow or goat is on pasture (dimensionless). F, = the stable element transfer coefficient for 2.2.2.2 meat (days /kg) from table 2.2-11. F. - the stable element transfer coefficient for 2.2.2.2 milk (days / liter) from table 2.2-11. VEGP ODCM, REV 0 Draft 2.4-3
i Subsection of Igre D#f_laithD Initial Use F ,' - the momentum flux parameter (m'/5'). 2.3.1.2 F, - the maximum expected release flowrate 2.1.1 through a particular release point (ml/s) from table 2.1-2. H = the absolute humidity of the atmosphere 2.2.2.2 (gm/m') . h - the effective release height (m), 2.3.1.2 h,- = the height of release point (m). 2.3.1.2 ,
- h. - the maximum terrain height between the 2.3.1.2 release point and the point of interest (m).
h,, = the additional height due to plume rise (m). 2.3.1.2 K. = the total body dose factor due to gamma 2.1.1 emissions from radionuclide 1 (mrem / year - per vCi/m') from table 2.1-1. K' - the constant of unit convtrsion (10'pCi/ mci). 2.2.1.2 K" = the constant of unit cor. version (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 from radionuclide 1 (mrem / year per Ci/m') i- from table 2.1-1. M, - the air dose factor due to gamma emissions 2.1.1 t from radionuclide i (mrad / year per pCi/m') j from table 2.1-1. l VEGP ODCM, REV 4 7/30/87 2.4-4 ,
. - - . _ . . . . - - _ ~ . , . . . -
, , - - . , . . . - . _ . , ..__,1_.- . - - . - . _ - -
Subsection of Ifra Definition Initial Use N, - the air dose factor due to beta emissions 2.2.2.1 from noble gas radionuclide i (mrad / year pe pCi/m') from table 2.1-1. n . the number of simultaneous gaseous 2.1.5 release pathways, ng = the number of hour. .ateorological 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,, - the dose parameter for radionuclide i, 2 2.1.2 O. (mrem / year per Ci/m') for the inhalation pathway. Q,, . - the source term for ground-level release 2 1.1 1 noble gas radioauclide i (uti/s). Q ,. - the source term fur mixeo mode release .2.1.1 noble gas radionuclide 1 ( Ci/s). I: _ Q,,i,n - ti.e source. term for ground-level release 2.1.5 L noble gas radionuclide i from a specific L release point ( Ci/s). L Q,,c,.7 - .the source-term for-mixed-mode reler.se 2.1.5-L noble gas radionuclide i.- from a specific release point ( C1/s). i O VEGP 0D011, REV 4 7/30/87- 2.4-5
Subsection of J.qrJD r Definition initial Use Q/, = the source term for ground-level release 2.2.1.2 radiciodine, tritium, and particulate radionuclide 1 ( ci/s). Q/, = the source term for mixed mode release 2.2.1.2 radiciodine, tritium, and particulate radionuclide 1 ( Ci/s). Q,, - the cumulative ground-level release of 2.2.2.1 coble gas radionuclide 1 ( C1). Q,, - the cumulative mixed-mode release of noble 2.2.2.1 gas radionuclide 1 ( Ci). Q i, = the cumulative grour.d-level release of 2.2.2.2 radiolodines, tritium, and particulate radionuclide i.( Ci). Q t, = the cumulative mixed-mode release of 2.2.2.2 radiciodines, tritium, and particulate radionuclide 1 (pC1). Q, - 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 ( Ci/s). R. = the relatioriship between noble gas 2.1.1 concentration and the dose rate to the total body for the conditions of the release under consideration (mren/ year /pci/cc). VEGP ODCM, REV 6 3/30/88 2.4-6
Subsection of Term D1finition Initial Use R, - the relationship between noble gas 2.1.1 concentration and the dose rate to the skin for the conditions of the release under consideration (mrem / year /pCi/cc). r, - the relationship between noble gas 2.1.3.1 concentration and the dose rate to the total body for Gaseous Waste Processing System or containment nurge relcase for the conditions of the release under consideration (mrem / year / Ci/cc). r, = the relationship between noble gas 2.1.3.1 concentration and the dose rate to the , skin for Gaseous Waste Processing System i or containment purge reiease for the p conditions of the release under
\> -consideration.
R.,,3 = the pathway-specific, individual age- 2.2.2.2 specific, organ dose factor for radionuclide 1, y thway p, organ j, and age group a, (mrem / year par C1/m') or (m'-mrem / year / C1/s). r = the fraction of deposited radionuclide 2.2.2.2 retained on vegetation (unitiess). SF - the safety factor used to introduce a margin 2.1.1 of conservatism into setroint calculations. S;if - the shielding factor afforded by structure 2.2.2.2 (unitiess). f~N S- - the stability parameter (s). 2.3.1.2 VEGP ODCM, REV 6- 9/30/88 2.4-7
. . . . . _ _ _ _ _ . . _ . _ . _ _ _ . _ ~ _ _ _ _ _ _ ._ _ .. _ _ -
, e Subsection of 1py3 . Definition Iniljal Use O t .
the exp6sure time for radioactivity 2.2.2.2 deposited on ground (s), te - the time between ha vest of leafy 2.2.2.2 vegetation and consumption (s). , t ,,, - the time between harvest of stored 2.2.2.2 vegetation and consumption (s). to - the transport time from feed to receptor 2.2.2.3 for stored feed (s), t, - the transport time from feed to receptor 2.2.2.3 for pasture grass (s). U,, - the receptor's milk (liters / year) or meat 2.2.2.3. , (kg/ yea.-) consumption rate for age group
^
a from tablo 2.2-10. U ,- - the consumption rate of stored vegetation 2.2.2.2 by the-receptor in age group a (kg/ year) 4 from table 2.2-10. 0,, = the consumption rate of. fresh leafy 2.2.2.2 vegetation by the receptor in age group a (kg/ year) from table 2.2-10. up - the wind speed (ridpoint of wind speed 2.3.1.1 class j) at ground level during atmospheric stability class k.(m/s). U,. . - the wind speed-(midpoint of wind speed 2.3.1.2-class j) at the height of release, h, of an
]
v elevated release during atmospheric stability class k (m/s). VEGP ODCM, REV 6 9/30/88 2.4-8
l 1 Subsection of I
. O' Term. Q!!{1altion 10itial Vsf W;, - the pathway-dependent relative dispersion 2.2.2.2 or deposition for ground-level releases at the location of the critical receptor.
W' - the pathway-dependent relative disperd on 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). Y, = the vegetation areal density (kg/m'). 2.2.2 2 Y, - the agricultural productivity by unit area 2.2.2.3 of pasture feed grass (kg/m'). Y, - the agricultural productivity by unit area 2.2.2.3 of stored feed (kg/m'). (X/Q). - - - the highest annual average relative 2.1.1
- concentration for a ground-level release type- (s/m') .
(X/Q), - the-highest annual average relative 2.1.2
- concantration for a mixed-mode release
- type (s/m').
(X/Q ')n, - the annual average relative corcentration for 2 2.2.2 location of controlling (critical) receptor for inhalation and all tritium pathways for a ground-level release type (s/m'). AO VEGP ODCM, REV 6 9/30/88 2.4-9
.y,..,-..,_._,.y., .-
-l l
Subsection of
; IfrG Definition Initial Use
- (X/6'), - 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 radionuclide (s"). A,, - the decay constant for removal of activity 2.P.2.2 on leaf and plant surfaces by weathering -(s) . 1,, - the vertical standard d wiation of the 2.3.1.1
-plume cor. centration distribution
-considering the initial dispersion within the building wake (m).
o,, - the vertical-standard deviation of the 2.3.1.1 plume (m), for a given distance under-the stability category k., indicated by
-AT/AZ from figure-2.3-1.
AT/AZ - the vertical temperature gradient used to 2.3.1.1 determine the atmospheric stability category (oC/100 m or oF/100 ft). P X,, - the concentration of-radionuclide i for 2.1.1 the particular vent release pathway under consideration ( Ci/ml t VEGP ODCM, REV 6 9/30/88 2.4-10
.- .= .-- - . - _.-.. . -.. - - -. . . ..~ . . . . _ . _ . ~. .. . -_. - . ?
- 2.5 LIMITS OF OPERATION' 2.5.1 Gaseous Effluents Dose Rate The dose rate due to radioactive materials released in gaseous effluents, from the site to areas at and beyond the site boundary (see figures 3.0-1 and 3.0-
- 2) shall be limited to less than or equal to 500 mrems/yr to~ the whole body for noble gases and less than or equal to 3000 mrems/yr to the skin for noble gases. The dose rate shall also'be limited to 1500 mrems/yr to any organ for lodine-131, for Iodine-133, for tritium, and for all radionuclides in particulate form with half-lives greater than 8 days. This limit applies at all times for all modes of operation.
2.5.1.1 Exceeding Gaseous Effluent Dose Rate Limits if the dose rates exceed the above limits, immediately restore the release rate to within_the above' limits. These' limits do not affect mode changes. 2.5.1.2 Sampling and Analysis of Gaseous Effluents
.The dose rate due to Iodine-131, Iodine-133, tritium, noble gases, and ali radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents shall be determined to be within the above limits by
' obtaining representative samples and performing analyses in accordance with the following sampling and analysi program.
2.5.1.2.1 Waste Gas Decay Tank Releases For waste gas decay tanks,-each tank must be sampled prior to its release and-analyzed for noble gas principal gamma emitters to a LLD of 1.00E-4 Ci/ml. ms { (U l VEGP ODCM, REV 8 Graft 2.5-1
1. i 4 2 .5.1.2.2 Containment Purge (Venting)
- O 4
For containment; purges (14 in. mini or .74 in, maxi) the containment atmosphere
- must be sampled prior to each purge and analyzed for noble gas principal gacma i
emitters to a LLD of 1.00E-4 uti/ml. In addition, a monthly tritium from a containment purge must be sampled and analyzed to an LLD of 1.00E-G Ci/ml. i , If a purge is in progress and a shutdown, startup, or a thermal power change j exceeding 15 percent of rated thermal power within a one-hour period occurs, ! then a grab sample of the containment atmosphere must be taken and analyzed f for noble gas principal gamma emitters to an LLD of 1.00E-4 pCi/ml. However, this requirement does not apply if (1) analysis shows that the dose equivalent { I-131 cor. centration in tne primary coolant has not increased more than a d factor of 3 and (2) the noble gas monitor shows that effluent activity has not [ increased more than a factor of 3. i i 4 2.5.1.2.3 Plant Vent Continuous Release LO. [ for the plant vent a grab sample must be taken monthly and analyzed monthly i for (1) noble gas principal gamma emitters to an LLD of 1.00E-4 C1/ml and (2) l tritium to an LLD of 1.00E-6 Ci/ml. Tritium samples are also required at l least once per 24 hours-for the Unit 1 plant vent, when the refueling canal is j flooded. This does not apply to the Unit 2 plant vent, because the-refueling a floor ventilation exits the Unit-1 plant vent only. Also for Unit 1 plant vent only, tritium samples are required at least once per 7 days whenever L spent fuel is in the spent fuel pool. s l Tf a shutdown, startup, or a thermal power change exceeding 15 percent of rated thermal power within a 1-hour period occurs, then a grab sample of the plant vent for the affected unit must be taken and analyzed for noble gas principal-gamma emitters to an LLD of 1.00E-4-pCi/ml and for tritium to an LLD of 1.00E-6 pCi/ml. However,-this requirement does not apply if (1)' analysis shows that the dose equivalent I-131 concentration in the primary coolant has
- not increased more than a factor of 3 and (2) the plant vent noble gas monitor shows that effluent activity has not increased more than a factor of 3.
VEGP ODCM, REV-8 Draft 2.5-2
p in addition to the monthly sampling, a continuous composite charcoal sample V must be taken and analyzed weekly for 1-131 to an LLD of 1.00E-12 Ci/ml. A continuous composite particulate sample must be taken and analyzed (1) weekly for principal gamma emitters to an LLD of 1,00E-Il vCi/ml, (2) monthly for gross alpha contamination to an LLD of 1,00E-ll pCi/ml, and (3) quarterly for Sr-89 and 5R-90 to an LLD of 1.00E-Il pCi/ml. For both the charcoal and the particulate composite, the ratio of the sample flowrate to the sampled stream flowrate shall be known for the time period covered by each dose or dose rate calculation made in accordance with subsections 2.5.1, 2.5.2, and 2.5.3 of this 00CM. In addition, the charcoal and particulate samples shall be changed at least once per 7 days, and analysei shall be completed within 48 hours after removal from sampler. Sampling shall also be performed at least once per 24 hours for at least 7 days following each shutdown, startup, or thermal power change exceeding 15 percent of rated thermal power within a 1-hour period, and analyses shall be completed within 48 hours of changing. When samples collected for 24 hours are analyzed, the corresponding LLDs may be increased by a factor of 10. The O requirement cloes not apply if (1) analysis shows that the dose equivalent I-131 concentration in the reactor coolant has not increased more than a factor i of 3' and (2) the plant vent noble gas monitor shows that effluent activity has not increaved more than a factor of 3. 2.5.1.2.4 Turbine Building Vent Exhaust The turbine building vent is the release point for the condenser air ejector and steam packing exhaust. All sampling and analyses may be omitted for this
- vent, provided the absence of a primary to secondary leak has been demonstrated, that is, the gamma activity in the secondary water does not
, exceed background by more than 20 percent. l L If required, a grab sample must be taken monthly and analyzed monthly for (1) i noble gas principal gamma emitters to an LLD of 1.00E-4 Ci/ml and (2) tritium to an LLD of 1.00E-6 pCi/ml . VEGP ODCM, REV 8 Draft 2.5-3
In addition to the monthly sampling, a continuous composite charcoal sample ". must be taken and analyzed weekly for 1-131 to an LLD of 1.00E-12 pCi/ml. A
-continuous composite particulate sample must be taken and analyzed (1) weekly for principal gamma emitters to an LLD of 1.00E-Il vCi/ml, (2) monthly for gross alpha contamination to an LLO of 1.00E-ll Ci/mi, and (3) quarterly for j Sr-89 and Sr-90 to an LLD of 1.00E-Il vCi/ml. l For both the charcoal and the particulate composite, the ratio of the sample flowrate to the sampled stream flowrate shall t e known for the time period covered by each dose or dose rate calculation made in accordance with i subsections 2.5.1, 2.5.2, and 2.5.3 of this ODCM. In addition, the charcoal and particulate samples shall be changed at least once per 7 days, and analyses shall be completed within 48 hours after changing. Sampling shall also be performed at least once per /4 hours for at least 7 days following each shutdown, startup, or thermal power change exceeding 15 percent of rated l
thermal power within a 1-hour period and analyses shall be completed within 48 hours of changing. When samples collected for 24 hours are analyzed, the corresponding LLD's may be increased by a factor of 10. This requirement does not apply if (1) analysis shows that the dose equivalent I-131 concentration in the reactor coolant has not increased more than a factor of 3 and (2) the -
- turbine building vent noble gas monitor shows that effluent activity has not increased more than a factor of 3. ,
2.5.1.2.5 Basis for the Gaseous Effluent Dose Rate This specification is provided to ensure that the dose at any time at and beyond the site boundary from gaseous effluents from all units on the site will- be within the annual dose limits of 10 CFR 20 to unrestricted areas. The annual dose limits are the doses associated with the concentrations of 10 CFR 20, Appendix B, table II, column I. These limits provide reasonable assurance
.that radioactive material discharged in gaseous effluents will not result in the exposure of a member of the public in an unrestricted area, either within or outside the site boundary, to annual average concentrations exceeding the limits specified in Appendix B, table I.1, of 10 CFR 20 (10 CFR 20.106(b)).
O For members of the public who may at times De within the site boundary, the VEGP 00CM, REV 8 Draft 2.5-4
- occupancy of that member of the public will usually be sufficiently low to
( compensate for any increase in the atmospheric diffusion factor above that for
.the site boundary. Examples of calculations for such members of the public, with the appropriate occupancy factors, shall be given in the ODCM, The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to a member of the public at or beyond the site boundary to less than or equal to 500 mrem /yr to the whole body or to less than or equal to 3000 mrem /yr to the skin. These release-rate limits also restrict, at all times, the corresponding thyroid dose rate above background to a child, via the inhalation pathway, to less than or equal to 1500 mrem /yr.
This specification applies to the release of radioactive materials in gaseous effluents from all units at the site. The required detection capabilities for radioactive materials in gaseous waste samples are tabulated in terms of the LL0s. Detailed discussion of the LLO and other detection limits can be found in HASL Procedures Manual, HASL-300 (revised annually), L. A., Currie, " Limits for Qualitative Detection and Quantitative Determination - Application to Radio-chemistry," Anal. Chem. 40, 586-93, 1968, and J. K. Hartwell," Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215, June 1975. 2.5.2 Noble Gas- Air Dose The air dose due to noble gases released in gaseous effluents, from each unit [ :to areas at end beyond the site boundary (figures 3.0-1 and 3.0-2), shall be limited, during-any calendar quarter, to less than or equal to 5 mrad for gamma radiation and to less than or equal to 10 mrad far beta radiation. in L a'ddition, during any calendar year, it shall he limited to less than or equal l to 10 rtrad for gamma radiation and to less than or equal to 20 mrad for beta radiation. This limit applies at all times for all modes of operation, i O() -- VEGP 00CM, REV 8 Draft 2.5-5
l 2.5.2.1 Exceeding the Noble Gas Air Doses If the calculated air dose from radioactive noble gases in gaseous effluents exceeds any of the above limits, prepare and submit to the NRC within 30 days, pursuant to Technical Specification 6.8.2, a special report that identifies the cause(s) for exceeding the limit (s) and defines the corrective action (s) that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in crv'iance with the above limits. These limits do not affect mode changes. 2.5.2.2 Cumulative Dose Calculation Pequirements To assure these limits are not exceeded, the cumulative dose contributions for the current calendar quarter and current calendar year for noble gases shall be determined in accordance with the methodology and parameters of subsection 2.2.2 at least once per 31 days. O 2.5.2.3 Basis for Noble Gas Air Doses This specificatior, is provided to implement the requirements of sections ll.B. Ill. A, and IV. A of Appendt:: 1. 10 CFR 50. The limiting condition for e operation implements the guides set forth in section I.B of Appendix 1. The action statements provide the required operating flexibility and at the same time implement the guides set forth in section IV.A of Appendix 1 to assure that the releases of radioactive material in gaseous effluents to unrestricted areas will be kept "as low as is reasonably achievable " The surveillanct. requirements implement the requirements in section Ill.A of Appendix I that conformance with the guides of Appendix 1 be shown by calculational procedures based on models and data such that the actual exposure of a member of the public through appropriate pathways is unlikely to be substantially underestimated. The dose calculatiot, methodology and parameters established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guidt 1.109, " Calculation of Annual Doses VEGp ODCM, REV 8 Draft 2.5-6
to Man from Routine Releases of Reactor Effluents of for the Purpose ! Evaluating Compliance with 10 CFR 50, Appendix 1," Revision 1 and Regulatory Guide 1.111. " Methods for ' , October 1977 Dispersion of Gaseous Effluents in Routine Releases Reactors," Revision 1. July 1977. er Cooled from Light W the air doses at and beyond the site boundary average atmospheric conditions. e historical are based upon 2.5.3 Dose to A Member of the p gh]Li Particulates l from Tritium 3 dioipdines. anj The dose to a member of the public frcm I-131
, 1-133, tritium, and all radionuclides in particulate form with half-lives greater ys in than 8 da gaseous effluents released, from each unit to areas eatsite and beyond th boundary (figures 3.0-1 and 3.0-2), shall be limited y calendarduring an quarter to less than or equal to 7.5 mrem to any organ and durin g any calendar year to less than or equal to 15 mrem to any organ.
times for all modes of operation. This limit applies at all 2.5.3.1 Exceeding the Dose Limits If the calculated dose from the release of I-131,1-133 , tritium, and radionuclides in particulate form with half-lives greater ays, in than 8 d gaseous effluents exceeding any of the above limits, m prepare and sub it to the NRC within 30 days, pursuant to Technical .Specification . , a special 682 report that identifies the cause(s) for exceeding the limit (s) and d fi e nes the corrective action (s) that have to be takenreleases will be in compliance with the above limits. to assure that subs changes. These limits do not affect modes I VEGP ODCM, REV 8 Draft 2.5-7
- ~ - " ~
2.5.3.2 Cumulative Dose Calculation Requirements V To assure these limits are not exceeded, the cumulative dose contributions for the current calendar quarter and current calendar year for 1-131, 1-133, tritium, and radionuclides in particulate form witn half-lives greater than 8 days shall be determined in accordance with the methodology and parameters in subsection 2.2.2 at least once per 31 days. 2.5.3.3 Basis for Tritium, Radiciodine, and Particulate Organ Dose Limits lhis specification is provided to implement the requirements of sections 11.C, III.A, and IV.A of Aptendix 1, 10 CFR 50. The limiting conditions for operation are the guidts set forth in section II.C of Appendix 1. The action statements provide the required operating flexibility and at the same time implement the guides set forth in section IV.A of Appendix 1 to assure that the releases of radioactive materials in gaseous effluents to unrestricted areas will be- kept "as low as is reasonably achievable." The ODCM
\ calculational methods specified in the surveillance requirements irplement the ,
requirements in section-!!!.A of Appendix 1 that conformance with the guides of Appendix I be shown by calcu'ational procedures based on models and data, such that the actual exposure of a member of the public through appropriate pathways is unlikely to be substantially underestimated. The ODCM calculational methodology and parameters for calculating the doses due to the actual release rates of the subject materials are , consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR 50, Appendix I," Revieton 1, October 1977 and Regulato'ry Guide-1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled P.eactors," Revision 1, July 1977. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate specifications for Iodine-131 Iodine-133, truium, and radionuclides in particulate form with half-lives greater than 8 days are dependent upon the existing radionuclide pathways to man in the areas VEGP ODCM, REV 8 Draft 2.5-8
n at and beyond the site boundary. The pathways that were examined in the V development of the calculations were (1) individual inhalation of airborne radionuclides, (2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, (3) deposition onto grassy areas where milk animals and meat-producing animals graze, with consumption of the milk and meat by man, and (4) deposition on the ground with subsequent exposure of man. 2.5.4 Gaseous Radwaste Treatment System Operation . The ventilation exhaust treatment system and the gaseous waste processing system s' hall be operable, and appropriate portions of these systems shall oc used to reduce releases of radioactivity when the projected doses in 31 days due to gaseous effluent releases, from each unit to areas at and beyond the site boundary (figures 3.0-1 and 3.0-2), would exceed 2.00E-1 mrad to air from gamma radiation, 4.00E-1 mrad to air from beta radiation, or 3.00E-1 mrem to any organ of a member of the public. This limit applies at all tims for all V modes of operatpn. 2.5.4.1 Exceeding the Dose Limits for Operation of the Gaseous Waste Processing System If radioactive gaseous waste is being discharged without treatment and is in - excess of the above limits, prepare and submit to the NRC within 30 days, pursuant to Technical Specificatlon 6.8.2, a special report that includes the following information (1) identification of any inoperable equipment or subsystems and-the reason for the inoperability, (2) action (s) taken to restore the inoperable equipment to operable status, and (3) summary description of action (s)'taken to prevent a recurrence. These limits do not affect mode changes. i O l VEGP ODCH, REV 8 Draft 2.5-9
-2.5,4.2 Requirement for Projecting Doses Due to Gaseous Releases To assure these limits are not exceeded, doses due to gaseous releases, from each unit to areas at.and beyond the site boundary, shall be projected at
} least once per 31 days in accordance with the methodology and parameters in subsection 2.2.2, when gaseous radwaste treatment systems are not t.eing fully i utilized. 1
- 2.5.4.3 Basis for the Operability of the Gaseous Wastc Processing System
! The operability of the gaseous waste processing system and the ventilation exhaust treatment system ensures that the sy!,tems will be availablo for use f -whenever gaseous effluents req. ke treatment prior to re' lease to the j environment. The requirement that the appropriate portions of these systems be used, when specified, provides reasonable assuranc': that the releases of radioactive materials in gasecus effluents will be kept "as low as is 4,; = reasonably achievable " This specification implements the requirements of 10 CFR $0.36a, General Design Criterion 60, Appendix A,10 CFR 50, and the design objectives:piven in section II.D, Appendix I, 10 CFR 50. The specified limits .. governing the use of appropriate portions of the systems were specified.as a j suitable fraction of the. dose design objectives set forth in sections 11.8 and , II.C . Appendix I, ~10 CFR 50, for gaseous effluents, t 2.5.5 .~ Dose to lhe Public from the Urgniym fuel Cyclg i The annual- (calendar year) dose or dose commitment to any member of the public i-due to relcases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrem to the whole body or , any organ, except the thyroid, which shall be limited to less than or equal to 75 mrem. This-limit applies at all times for all modes of operation. O VEGP ODCM, REV 8 Draft 2.5-10
l 2.5.5.1 Cumulative Dose Calculation Requirements
-To assure these limits are not exceeded, cumulative dose contributions from direct radiation from each unit (including outside storage tanks, etc.) shall
- be determined in accordance with the methodology and parameters.in section 4.0. This requirement is applicable only if the conditions in paragraph 2.5.5.2 are met.
2.5.5.2 Conditions Required for Cumulative Dose Calculations
- If the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeds twice the limits of subsections 1.5.2, 2.5.2, or 2.5.3, calculations shall be made including direct radiation contributions i from the unit (including outside storage tanks etc.) to determine whether the
-above limits have been exceeded. If such is the case, prepare and submit to 1 the NRC within 30 days, pursuant to Technical Specification 6.8.2, a special report that (1)-defines the corrective action (s) to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and (2) includes the schedule for achieving conformance with the above. limits.
.This special report, as defined in 10 CFR 20.405(c), shall include an analysis that estimates the radiation exposure (dose) to a member of the public f.om uranium fuel-cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes-the release (s) covered by this report. it shall also describe. levels of radiation and concentrations of radioactive' material involveo, and the cause of the exposure levels or concentrations.- If the estimated dose (s) exceeds the above limits and if the-
. release condition resulting' in violation of 40 CFR 190 has not already been-corrected, the special report shall include a request for a variance in accordance with the provisions of 40 CFR 190. Submittal of the report is
-considered a timely request, and a variance.is granted until staff action on the request is complete. These limits do not affect mode changes, l
O VEGP ODCM, REV 8 Draft 2.5-11
g 2.5.5.3 Exceeding the Dose Limitations <d i This specification is provided to meet the dose limitations of 40 CFR 190 that have been incorporated into 10 CFR 20 by 46 FR 18525. The specification requires the preparation and submittal of a special report whenever the calculated doses due to releases of radioactivity and to radiation from uranium fuel cycle sources that directly support the production of electrical power for public use exceed 25 mrem to the whole body or any organ, except the
. thyroid, which shall be limited to less than or equal to 75 mrem. For sites containing up to four reactors, it is highly unlikely that the resultant dose to a member of the public will exceed the dose limits of 40 CFR 190 if the individual ructors remain within twice the dose design objectives of Appendix I and if direct radiation doses from the units including outside storage tanks, etc. are kept small. The special reoort will describe a course of action that should result in the limitation of the annual dose to a member of the public to within the 40 CFR 190 limits. For-the purposes of the special report, it may be assumed that the dose commitment to the member of the public . from other uranium fuel cycle sources is negiigible, with the exception that dose contributions from other- nuclear fuel cycle facilities at the same site or within a radius of 8 km must be considered. If the dose to any member of the public is estimated to exceed the requirements of 40 CFR 190, the special report with a request for a variance (provided the release conditions resulting in violation of 40 CFR 190 have not already been corrected),- in accordance with the provisions of 40 CFR 190.11 and 10 CFR 20.405c, is considered to be a timely request and fulfills the requirements of 40 CFR 190 until NRC staff action is _ completed. The variance only relates to the limits of 40 CFR 190 and does not apply in any way to the other requirements of dose limitation of 10 CFR 20, as addressed in subsections 1.5.1 and 2.5.1. An individual is not considered a member of the public during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.
O VEGP 00CM, REV 8 Draft 2.5-12
2.5.6 Caseous Effluent Monitorino Instrumentation O The radioactive caseous effluent monitoring instrumentation channels spuified below shall be operable with their alarm / trip setpoints set to ensure that the
- limits of subsection 2.5.1 of this 00CM are not exceeded. This limit applies at-all times for all modes of operation.
2.5.6.1 Nonconservative Gaseous Effluent Monitor Setpoint and ACTIONS If a radioactive gaseous tffluen+. monitoring instrumentation channel alarm / trip setpoint is less conservative than required by the above specification, immediately suspend the release of radioactive gaseous
; effluents monitored by the affected channel, or declare the channel inoperable ,
e If less than the minimum number of radioactive gaseous effluent monitoring p instrumentation channels are operable, take the ACTION shown in table 2.5-1. _ V Restore the ir. operable instrumentation to operable status within 30 days, or, if unsuccessful, explain in the next Semiannual Radioactive Effluent Release Report, pursuant to Technical Specification 6.8.1.4, why this inoperability was not corrected in a timely manner. These limits do not affect mode changes. 2.5.6.2 Gaseous Effluent-Monitor Operability Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated operable by performance of the channel check, source check, channel calibration, and analog channel operational test at the frequencies shown in table 2.5-1. Specific instrument numbers are provided in parentheses
'for information only. The numbers apply to each unit. These numbers will help to' identify associated channels or loops and are not intended to limit -
the' requirements to the specific instruments associated with the number.
- O
..VEGP 00CM, REV 8 Draft 2.5-13
( .
. TABLE 2'5-l'(SHEET I 0F 4)
GASEOUS EFFLUENT M0h!TORING INSTR'JMENTATION 8 o
- Minimum Channels- Channel Source Channel Analog Channel Modes Doerable ACTION Check Check Calibration Operational Test Peauired to 1. Gas waste processing system-o '
d a) Noble gas activity 1 45 P P R(3) Q(1)
- r monitor - providing alann and automatic termination of release ^
(ARE-0014) (common) b) Effluent system flowrate l' 45 P NA R NA
- measuring Device (AFT-0014) (common) y 2. Turbine building vent-u, i a) Noble gas activity 1 47 D H *
- R(3) Q(2) monitor (RE-12839C) b) Iodine and particulate 1 51 W(6) NA NA NA
- l samplers (RE-12839A&B) c) Flowrate monitor 1 46 D NA R NA *
(FT-12839 or.FIS-12862)** d) Sampler flowrate monitor ! 1 46 D NA R Q
- l l (FI-13211)
- 3. Plant vent l a) Noble gas activity monitor 1 47,48 D M R(3) Q(2) at all times (RE-12442C or RE-12444C)
! b) lodine sampler / monitor 1- 51 W(6) NA HA/R NA ai all times (RE-124428 or RE-124448) c) Particulate sampler / monitor 1 51 D NA NA/R Q at all times (RE-12442A or RE-12444A) d) Flowrate monitor (FT-12442 1 46 D NA R NA at all times or 12835) e) Sampler flowrate monitor 46 1 D NA R Q at all times (FI-17442 or FI-12444) _ _ = _ _ _ _ - _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ _
TABLE 2.5-1 (SHEET 2 0F 4) -l l TABLE NOTATIONS
- 1) The analog channel operational test shall also demonstrate that automatic isolation of this pathway (for item a, below only) and control room alarm annunciation occurs if any of the following conditions exists:
- a. Instrument indicates measured levels above the alarm / trip setpoint.
- b. Circuit failure.
- c. Instrument indicates a downscale failure.
- d. Instrument controls not set in operate mode. (Annunciation via
, computer printout.)
(2) The analog channel operational test shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:
- a. Instrumer.t indicates measured levels above the alarm setpoint.
- b. Circuit failure.
O c. Instrument indicates a downscale failure.
- d. Instrument controls not set in operate mode. (Annunciation via computer printout.)
(3) The initial channel calibration shall be pe; .ormed using one or more of the reference standards certified by the National Bureau of Standards (NBS) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS. These standards ri.all permit calibrating the system over its intended range of energy and measurement range. For subsequent channel calibration, sources that have been related to the initial calibration shall be used. (4) Not used. (5) Not used. (6) The channel check shall consist of visually verifying that the collection device (i.e., particulate filter or charcoal cartridge, etc.) is in place O for sampling. VEGP ODCM REV 8 Draft 2.5-15
TABLE 2.5-1 (SHEET 3 Of 4) h ACTION STATEMENTS ACTION 41-44 (Not Used) ACTION 45 - With the number of channels operable less than required by the minimum channels operable requirement, the contents of the tank (s) may be released to the environment provided that prior to initiating the release
- a. at least two indepentant samples of the tank's contents are analyzed
- b. at least two technically qualified members of the facility staff independently verify the release rate calculations and discharge valve lineup, p Otherwise, suspend release of radioactive effluents via this k/ pathway.
ACTION 46 - With the number of channels operable less than required by the minimum channels operable requirement, effluent releases via - this pathway may continue provided the flowrate is estimated at least once per.4 hours. ACTION 47 - With the number of channels operable less than required by the minimum channels operable requirement, effluent releases via j this pathway may continue provided grab samples are taken at least once per 12 hours and these samples are analyzed for i radioactivity within 24 hours. ACTION'48 - With the number of. channels operable less than required by the minimum channels operable requirement, immediately suspend containment purging of radioactive effluents via this pathway, f3 i k J . ACTION 49 - Not Used. VEGP ODCM REV 8 Draft 2.5-16
TABLE 2.5-1 ISHEET 4 0F 4)
'* ACTION 50,- Not Used.
ACTION 51 - With the number of channels operuble less than required by the minimum channels operable requirement, effluent releases via the affected pathway may continue provided samples are continuously collected with auxiliary sampling equipment.
*During radioactive releases via this pathway.
**During emergency filtration.
l O O VEGP ODC4 REV 8 Draft 2.5-17 l
g] f, - the fraction of the year that the cow is on pasture V (dimensionless). f, - the fraction of the cow feed that is pasture grass while the cow is on pasture (dimensionless). For tritium in milt., 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 titan deposition: R,3p) K'KF,Q Up 3p(DFL$3)a(0.75(0.5/H)) (27) (mrem / year / Ci/m') K'" - a constant of unit conversion,10' gn/kg, H - the absolute humidity of the atmosphere, in gm/m'. 1 r , I,'-), 0.75 - the fraction of total feed that is water. l l 0.5 - the ratio of the specific activity of the feed grass water to the atmospheric water. Other parameters ar.d values as previously defined. Grass-Goat-Milk Pathway Factor 0p(V Ib II-I os I )e ^i hm Raipj - K,j ,j an)F,(r)(DFL43)a y+ y *AtiI (28) (m' mrem / year / Ci/s) where: K' - a constant of unit conversion,10' pCi/ Ci. VEGP ODCM, REV 8 Draft 2.2-12
p Q, -- the goat's consumption rate, in kg/ day (wet weight), b U,, - the receptor's. milk consumption rate for age group a, in liters / year from table 2.2-10. Y, - the agricultural productivity by unit area of pasture feed grass, in kg/m'. Y, - the agricultural productivity by unit area of stored feed, in kg/m'. F. - the stable element transfer coefficients, in days / liter. (See table 2.2-11.) r - the fretion of deposited activity retained on feed grass (1.0 for radiciodines; 0.2 for particulates). (DFly ), - the organ ingestion dose factor for the ith
- radionuclide for. the receptor in age group a, in mrem /pCi from tables 2.2-5 through 2.2-8.
A, - the decay constant for the ith' radionuclide, in s". A., - the decay constant for removal of activity on leaf and plant surfaces by weathering, 5.73 x 10" s" (corresponding to a 14-day half-life). t,_ = the transport time from pasture to goat, to milk, to receptor, in s (1.73 x 10'). L l- t, - the transport time from pasture, to harvest, to goat, to milk, to receptor, in s (7.78 x 10'). f, - the fraction of the year that the goat is on pasture (dimensionless). O-VEGP 00CM, REV 4 7/30/87 2.2-13
f, - the fraction of the goat feed that is pasture grass while the goat is on pasture (dimensionless). For tritium in milk, the grass-goat-milk pathway factor is a special case due to the fact that the concentration of tritium in milk is based on l airborne concentration rather than desposition: R - aipj K'K'"F,Q U7 ap(UIlij)a(0.75(0.5/H)) (29) (mrem / year / Ci/m') where K'" - a constant of unit conversion,10' gm/kg. H - the absolute hur:,idity of the atmosphere, in gm/m'. .- 0.75 - the fraction of total feed that is water. L 3- 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. - L Grass-Cow-Meat-Pathway-Factor At g hm R aipj"Eg(Uan) I (r)(DFL ))a S + (I-I Ins)g *AtII (30) A+A i w f g Y p Y s (m' mrem / year / Ci/s) I where: j- K' - a constant of unit conversion,10' pCi/pci. i Q, = the cow's consumption rate, in kg/ day (wet weight). VEGP ODCM, REV 8 Draft 2.2-14
4 1 c U,, _ - the receptor's meat consumption rate for age _ group a, in kg/ year from table 2.2-10. Y, - the agricultural productivity by unit area of pasture feed grass, in kg/m'. Y, - the agricultural productivity by unit area of stored feed, in kg/m'. 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 particulates). (DFly ), - the organ ingestion dose factor for the ith radionuclide for the receptor in age group a, in mrem /pCi , q from tables 2.2-5 through 2.2-8. l .V A, - the decay constant for the ith radionuclide, in s. A. - the decay constant for removal of activity on leaf and plant surfaces by weathering, 5.73 x 10" s (corresponding to- a 14-day half-life), t, - the transport time from pasture to cow, to meat, to receptor, in s (1.73 x 10'). th - the transport time from pasture, to harvest, to cow, to meat, to receptor, in s (7.78 x 10'). 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 O, the cow-is on pasture (dimensionless). VEGP ODCM, REV 4 7/30/87 2.2-15
I For tritium in meat, the grass-cow-meat pathway factor is a_special case iO due to the fact that the concentration of tritium in meat is based on airborne concentration rather than deposition: R. , ,, = K ' K " F,Q,0,,( D F L ,,),( 0. 7 5 ( 0, 5 / H ) ) (31) (mrem / year / Ci/m') where: K" = a constant of unit conversion,10' gm/kg. H -- the absolute humidity of the atmosphere, in 9m/m'. 0.75 - the fraction of total feed that is- water. 0.5 = the ratio of the specific activity of the feed grass water p to the atmospheric water.
'd Other parameters and values are given above.
2.2.2.3 Dose Calculations to Support Other Technical Specifications
~In the event-radiological impact assessment becomes necessary to support Technical Specification 6.6.1, which pertains to reportable events, dose calculations may be performed using the equations in subsection 2.2.2.2 with the substitution of average meteorological (dispersion and deposition) parameters for the period covered by the report, and the appropriate y'hway de w- factors (R ,,,) for the receptor of interest.
For' the purpose of supporting subsection 3.1.2, which pertains to the Annual Land Use Survey, it may become necessary co perform dose calculations in addition to those required by subsection 2.5.3. In the event that the Land l Use Survey reveals that exposure pathways have changed at previously ' identified locations, or if new locaticn: are identified, it may become VEGP ODCM, REV 8 Draft- 2.2-16
i
,r - necessary to per form dose calculations-at two or more locations to either C)/ 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 paragraph 2.2.2.2, substituting the appropriate pathway dose factors (R,,,3) and the appropriate meteorological (dispersion and deposition) parameters for the receptor (s) and location (s) of interest. Annual average meteorological paramaters may be used for these calculations, rh V
~ VEGP.0DCM, REV.8 Draft 2.2-17 rn-,w..o.sw o.u
i n - O TABLE 2.2-1 (SHEET 1 0F 3)
- INHALATION DOSE FACTORS FOR INFANT *
(mrem per pci inhaled) i Nuclide Bone Liver T Body._ lhymid Kidney ._Luos_ -.GL-LU.-
- N-3 No Data 4.62E-07 4.52E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 C-14 1.89E-05 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06
{. Na-24 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7 54E-06 7.54E-06 < P-32 1.45E-03 8.03E-Ob 5.53E-05 No Data No Data No Data 1.15E-05 Cr-51 No Data No Data 6.39E-08 4.llE-08 9.45E-09 9.17E-06 2.55E-07 Mn-54 No Data 1.81E-05 3.56E-06 No Data 3.56E-06 7.14E 5.04E-06 i Mn-56 No Data 1.10E-09 1.58E-10 No Data 7.86E-10 8.95E-06 5.12E-05
- Fe-55 1.41E-05 8.39E-06 2.38E-06 No Data No Data 6.21E-05 7.82E-07 Fe-59 9.69E-06 1.68E-05 6.77E-06 No Data No Data 7.25E-04 1.77E-05 l Co-58 No Data 8.71E-07 1.30E-06 No Data No Data 5.55E-04 7.95E-06 Co-60 No Data 5.73E-06 8.41E-06 No Data No Data 3.22E-03 2.28E-05
{L N1-63 2.42E-04 1.46E-05 8.29E-06 No Data No Data 1.49E-04 1.73E-06 ! (3 Ni-65 1.71E-09 2.03E-10 8.79E-11 No Data ~ No Data 5.80E-06 3.58E-05 { V Cu-64 No Data 1.34E-09 5.53E-10 No Data 2.84E-09 6.64E-06 1.07E-05
- Zn-65 1.38E-05 4.47E-05 2.22E-05 No Data 2.32E-05 4.62E-04 3.67E-05 Zn-69 3.85E-ll 6.91E-11 5.13E-12 No Data 2.87E-Il 1.05E-06 9.44E-06 Br-83 No Data No Data 2.72E-07 No Data No Data No Data LT E-24
; Br-84 No Data No Data 2.86E-07 No Data No Data No Data LT E-24
?- Br-85 No Data No Data 1.46E-08 No Data No Data No Data LT E-24 Rb-86 No Data 1.36E-04 6.30E-05 No Data No Data No Data 2.17E-06 Rb-88 No Data 3.98E-07 2.05E-07 No Data ,No Data No Data 2.42E-07 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.iSE-06 No Data No Data 1.45E-03 4.57E-05 Sr-90 2.92E-02 No Data 1,85E-03 No Data No Data 8.03E-L" 9.36E-05 Sr-91 6.83E-08 No Data 2.47t-09 No Data No Data 3.76E-05 5.24E-05 Sr 7.50E-09 No Data 2.79E-10 No Data No Data 1.70E-05 1.00E-04 Y-90 2.35E-06 No Data 6.30E-08 No Data No Data 1.92E-04 7.43E-05 Y-91M 2.91E-10 No Data 9.90E-12 No Data No Data 1.99E-06 1.68E-06 Y-91 4.20E-04 No Data 1.12E-05 No Data No Data 1.75E-03 5.02E-05 Y 1.17E-08 No Data 3.29E-10 No Data No Data 1.75E-05 9.04E-05 O
- Reference 3, Table E-10.
i
;YEGP ODCM, REV 4 7/30/87 2.2-18 i
M l* TABLE 2.2-1 (SHEET 2 Of 3) INHAEAT11 DOSE FAC10R5 FOR INFANT * (mrem per pci inhaled) ((Ufl.idg Done _Llygr_. .J_fady _ Thyroid ridagy _Lunn_ ._g l _ L L I v-93 1.07E-07 No Data 2.91E-09 No Data No Data 5.46E-05 1.19E-04 2r-95 8.24E-05 1.99E-05 1.45E-05 No Data 2.22E-05 1.25E-03 1.55E-05 Zr-97 1.0?E-07 1.83E-08 8.36E-09 No Data 1.85E-08 7.88E-05 1.00E-04 Nb-95 1.12E-05 4.59E-06 2.70E-06 No Data 3.37E-06 3.42E-04 9.05E-06 Mo-99 No Data 1.18E-07 2.31E-08 No Data 1.89E-07 9.63E-05 3.48E-05 Tc-99M 9.98E-13 2.06E-12 2.66E-Il No Data 2.22E-Il 5.79E-07 1.45E-06 Tc-101 4.65E-14 b.BbE-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 Nr tta 2.93E-10 No Data 6.42E-10 1.12E-05 3.46E-05 Ru-106
/,g-110M 6.20E-05 No Data 7.77E-06 No Data 7.13E-06 5.16E-06 3.57E-06 No Data 7.80E-06 2.62E-03 2.3EE-05 7,61E-05 8.26E 03 1.17E-04 Y 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 1.4BE-06 3.4BE-06 2.68E-05 9.37E-04 1.95E-05 Te-127 1.59E-09 6.81E-10 3.49E-10 1.32E-09 3.47E-09 7.39E-06 1.74E-05 Te-129M 1.01E-05 4.35E-06 1.59E-Q6 3.91E-06 2.27E-05 1.20E-03 4.93E-05 Te-129 5.63E-Il 2.48E 'l 1.34E-Il 4.82E-ll 1.25E-10 2.14E-06 1.88E-05 Te-131M 7.62E-08 3.93E-08 2.59E-08 6.38E-08 1.89E-07 1.42E-04 8.51E-05 Te-131 1.24E-Il 5.87E-12 3.57E-12 1.13E-ll 2.85E-Il 1.47E-06 5.87E-06 he-132 2.66E-07 1.69E-07 1.26E-07 1.99E-07 7.39E-07 2.43E-04 3.15E-05 1-130 4.54E-06 9.91E-06 3.98E-06 1.14E-03 1.09E-05 No Data 1. 4 2 E--06 1-131 2.71E-05 3.17E-05 1.40E-05 1.06E-02 3.70E-05 No Datt 7.56E-07 l-132 1.21E-06 2.53E-06 8.99E-07 1.21E-04 2.82E-06 No Data 1.36E-06 1-133 9.46E-06 1.37E-05 4.00E-06 2.54E-03 1.60E-05 No Data 1.34E-06 1-134 6.58E-07 1.34E-06 4.75E-07 3.18E-05 1.49E-06 No Data 9.21E-07 1-135 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 Cs-136 3.45E-05 9.61E-05 3.78E-05 No Data 4.03E-05 8.40E-06 1.0/E-06 Cs-137 3.92E-04 4.37E-04 3.25E-05 No Data 1.23E-04 5.09E-05 9.53E-07 l Cs-138 3.61E-07 5.58E-07 2.84E-07 No Data 2.93E-07 4.67E-08 6.26E-07 Ba-139 1.06E-09 7.03E-13 3.07E-Il No Data 4.23E-13 4.25E-06 3.64E-05 J
Da-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 7.70E-14 3.55E-12 No Data 4.64E-14 2.12E-06 3.39E-06 Ba-142 2.84E-Il 2.36E-14 1.40E-12 No Data 1.36E-14 1 llE-06 4.95E-07 I~' Reference 3, Table E-10. VEGP ODCM, REV 4 7/30/87 2.2-19
I
)
1ABLE 2 2-1 (SHEET 3 Of 3) O- INHALA110N DOSE FAC10RS FOR INFANT * (nireni per pci inhaled) fluclide __ Bong _. liver .1 Body _ DatgM Kidney lyfL GI-LLL La-140 3.61E-07 1.43E-07 3.68E 08 No Data No Data 1.20E-04 6.06E-05 La 142 7.36E-10 2.69E-10 6.46E-11 No Data No Data 5.87E-06 4.25E-05 C0 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-00 8.300-05 3.550-05 Ce 144 2.38E-03 8.65E-04 1.26E-04 No Data 3.84E-04 7.03E-03 1.00E-04 Pr-143 1.00E-05 3.74F ^6 4.99E-07 No Data 1.41E-06 3.09E-Oi 2.66E-05 Pr-144 3.42E-Il 1.32E-Il 1.72E-12 No Data 4.80E-12 1.15E-06 3.06E-06 Nd-147 -5.67E-06 5.81E-06 3.57E-07 No Data 2.23E-06 2.30E-04 2.23E-05 W-187 9.26E-09 6.44E-09 2.23C-09 No Data No Data 2.83E-05 2.54E-05 ib-239 2. N -07 2.37E-08 1.34E-08 No Data 4.73E-08 4.25E-05 1.78E 05 O ' I i i k O a - - 3. m i u -10. L l VEGP ODCH, REV 4' 7/30/87 2.2-20 i l ' ' -, . . , _ - _
1ABLE 2.2-2 (SHEET 1 Of 3) INHALATION DOSE FACTORS FOR child * (mrem per pci inhaled) th&lidt .__DfnL. ._ Liver T Opiy_ lhynid Kidney luaq_ _G1-LLL H-3 No Data 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 C-14 9.70E-05 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 l P-32 7.04E-04 3.09E-05 2.67E-05 No Data No Data No Data 1.14E-05 tr-51 4.17E-00 2.31E-08 6.57E-09 4.59E-06 2.93E-07 No Data No Data 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-Il No Data 4.52E-10 3.55E-06 3.33E-05 Fe-55 1.28E 65 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 Date 3.43E-04 1.91E-05 ! C0-58 No Data 4.79E-07 8.55E-07 No Data No Data ?.99[-04 9.29E-06 00-60 No Data 3.55E-06 6.12E-06 No Data No Data 1.91E-03 2.60E-05 Ni-63 2.22E-04 1.25L 5 7.56E 06 No Data No Data 7.43E-05 1.71E-Ou Ni-65 8.08E-10 7.99E-11 4.44E-Il No Data No ' sata 2.21E-06 2.27E-05 Cu-64 No Data 5.39E-10 2.90E-10 N0 Data 1.63E-09 2.59E-06 9.920-06 Zn-65 1.15E-05 3.06E-05 1.90E-05 No Data 1.93E-05 2.69f-04 4.41E-06 Zn-69 1.81E-Il 2.61E-11 2.41E-12 No Data 1.5BE-Il 3.84E-07 2.75E-06 Br 83 No Data No Data 1.2BE-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 L1 E-24 Rb-86 No Data 5.36E-05 3.09E-05 No Dsta No Data No Data 2.16E-06 Rb-88 No Data 1.52E-07 9.90E-08 No Data No Data No Data 4.66E-09 Rb-89 No Data 9.33E-08 7.83E-08 No Data No Data No Data 5.llE-10 Sr-89 1.62E-04 No Data 4.66E-06 No Data No Data 5.83E-04 4.52E-05 Sr-90 2.73E-02 No Data 1.74E-03 No Data No Data 3.99E-03 9.28E-05 Sr-91 3.28E-08 No Data 1.24E-09 No Data No Data 1.44E-05 4.70E-05 Sr-92 3.54E-09 No Data 1.42E-10 No Data No Data 6.49E-06 6.55E-05 Y-90 1.llE-06 No Data 2.99E-08 No Data No Data 7.07E-05 7.24E-05 Y-91M 1.37E-10 No Data 4.98E-12 No Dat; 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 4.97f-05 Y-92 5.50E-09 No Data 1.57E-10 No Data No Data 6.46E-06 6.46E-05
- Reference 3, lable E-9.
VEGP ODCM, REV 4 ./20/87 2.2 .i
TABLE 2.2-2 (SHEET 2 Of 3) INHALATION DOSF FACTORS FOR CHILD * , (mrem per pei inhaled) lM lide Bpng___ __ L i ye r T Bply._ lhyroid Kidnev Lun.q_ _G1-LL1 Y-93 ~5.04E-08. No Data 1.38E-09 No Data No Data 2.01E-05 1.05E-04 ! Zr-95 5.13E-05 1.13E-05 1.00E-05 No Data 1.61E-05 6.03E-04 1.65E-05 1 Zr-97 5.07E-08 7.34E-09 4.32E-09 No Data 1.05E-08 3.06E-05 9.49E-05 Hb-95 6.35E 2.48E-06 1.77E-06 No Data 2.33E-06 1.66E-04 1.00E-05 Mo-99 No Data 4.66E-08 1.15E-08 No Data 1.06E-07 '. 66E-05 3.42E-05 Tc-99M 4.81E-13 9.41E-13 1.b6E-Il No Data 1.37E-Il 2.57E-07 1.30E-06 l Tc-101 2.19E-14 2.30E-14 2.91E-13 No Data 3.92E-13 1.58E-07 4.41E-09 Ru-103 7.55E-07 No Data 2.90E-07 No Data 1.90E-06 1.79E-04 1.21E-05 Ru-105 4.13E-10 No Dat -1.50E-10 No Data 3.63E-10 4.30E-06 2.69E-05 Ru-106 3.68E-05 No Data 4.57E-06 No Data 4.9/E-05 3.87E-03 1.16E-04 Ag-110M 4.56E-06 3.08C-06 2.47E-06 No Data 5.74E-06 1.48E-03 2.71E-05 Te-125H 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 2.3]E-06 8.16E-07 1.64E-06 1.72E-05 4.00E-04 1.93E-05 Te-127 7.49E-10 2 A'E-10 1.65E-10 5.30E-10 1.91E-09 2.71E-06 1.52E-05 Te-129M 5.19E-06 1.85 -06 8,22E-07 1.71E-06 1.36E-05 4.76E-04 4.91E-05 Te-129 2.64E-Il 9.45E-12 6.44E-12 1.93E-Il 6.34E-Il 7.93E-07 6.89fs06 Te-131H 3.63E-08 1.60E-08 1.37E-08 2.64E-08 1,08E-07 5.56E-05 8.32E-05 Te-131 5.87E-12 2.28E-12 1.78E-12 4.59E-12 1.59E-Il 5.55E-07 3.60E-07 Te-132 1.30E-07 7.36E-08 7.12E-08 8.58E-08 4.79E-07 1.02E-04 3.72E-05 1-130 2.21E-06 4.43E-06 2.28E-06 4.99E-04 6.61E-05 No Data i .3BE-06 I-131 1.30E-05 1.30E-05 7.37E-06 4.39E-03 2.13E-05 No Data ,.68E-07 1-132 5.72E-07 1.10E-06 5.07E-07 5.23E-05 1.69E-06 No Data 8.65E-07 . 1-133 4.48E-06 5.49E-06 2.0AE-06 1.04E-03 9.13E-06 No Data 1.48E-06 l-134 3.17E-07 5.84E-07 2.69E-07 1.37E-05 8.92E-07 No Data 2,58E-07 l-135 1.33E-06 2.36E-06 1.12E-66 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 2.5BE-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 Ba-139 4.98E-10 2.66E-13 1.45E-Il 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-Il 2.95E-14 1.72E-12 No Data 2.56E-14 7.89E-07 7.44E-08 Ba-142 1.35E-ll 9.73E-15 7.54E-13 No Data 7.87E-15 4.44E-07 7.41E-10 L O
- Reference 3 Table E-9.
VEGP ODCH, REV 4 7/30/87 2.2-22
l
'^"" ~' ""' ' '
(D INHALAil0N DOSE FACTORS FOR CHILD * (mrem per pci inhaled) lin~i.ide _ _Bonc _ Liver T Dody lhyroid Kidney Luno _11-LLI . La-140 1.74E-07 6.08E-08 2.04E-08 No Data No Data 4.94E-05 6.10E-05 La-142 3.50E-10 1.llE-10 3.49E Il No Data No Data 2.35E-06 2.05E-05 Ce-141 1.06E-05 5.28E-06 7.83E-07 No Data 2.31E-06 1.47E-04 1.53E-05 Co-143 9.89E-08 5.37E-08 7.7'F-09 Nn Data 2.26E-08 3.12E-05 3.44E-05 Co-144 1.83E-03 5.72E-04 9.7/i.-05 No Data 3.17E-04 3.23E-03 1.05E-04 Pr-143 4.99E-06 1.50E-06 2.47E-07 No Data 8.11E-07 1.17L-04 2.63E-05 Pr-144 1.61E-ll 4.99E-12 8.10E-13 No Data 2.64E 12 4.23E-07 5.32E-08 Nd-147 2.92E-06 2.36E-06 1.84E-07 No Data 1.30E v6 8.87E-05 2.22E-05 W-187 4.41E-09 2.61E-09 1.17E-09 No Data No Data 1.llE-05 2.46E-05 Np-239 1.26E-07 9.04E-09 6.35E-09 No Data 2.63E-08 1.57E-05 1.73E-05 0
- Reference 3. Table E-9.
VEGP ODCH, REV 4 7/30/87' 2.2-23
TABLE 2.2-3 ($HEET 1 0F 3) O INHALATION DOSE FACTORS FOR TEENAGER * , (mrem per pci inhaled) ' Nuclide Bone liver T Body Thyroid Kidney ._Lun.q _ GI-Lll 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 1.72E-06 1.71E-06 1.72E-06 P-32 2.36E-04 1.37E-05 8.95E-06 No Data No Data No Data 1.16E-05 Cr-51 No Data No Data 1.69E-08 9.37E-09 3.84E-09 2.62E-06 3.75E-07 ! Hn-54 No Data 6.39E-06 1.05E-06 No Data 1.59E-06 2.48E-04 8.35E-06 Mn-56 No Data 2.12E-10 3.15E-1: Nc . > 2.'aE-10 1.90E-06 7.18E-06 fe-55 4.18E-06 2.98E-06 6.93E-C h fat; h 'a 1.55E-05 7.99E-07 fe-59 1.99E-06 4.62E-06 1.79E-06 AL V ; Ro un a 1.91E-04 ?.23E-05 Co-58 No Data 2.59E-07 3.47E-07 No Dam 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 , hi-63 7.25E-05 5.43E-06 2.47E-06 No Dati No Data 3.84E-05 1.77E-06 Ni-65 2.73E-10 3.66E-11 1.59E-Il No Data No Data 1.17E-06 4.59E-06 Cu-64 No Data 2.54E-10 1.06E-10 Hu Data 8.01E-10 1.39E-06 7.68E-06 Zn-65 4.82E-06 1.67E-05 7.80E-06 No Dats 1.08E-05 1.55E-04 5.83E-06
- Zn-69 6.04E-12 1.15E-11 8.07E-13 No Data 7.53E-12 1.98E-07 3.56E-08 Br-83 No Data No Data 4.30E-08 No Data No Data No Data LT E-24 Dr-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 No Data 2.38E-05 1.05E-05 No Data No Data No Data 2.21E-06 Rb-88 'No Data 6.82E 3.40E-08 No Data No Data No Data 3.05E-15 Rb No Data '4.40E-02 }.91E-08 No Data No Data No Data 4.22E-17 Sr-89 5.43E-05 No Data 1.56E-06 No Data 'No Data 3.02E-04 4.64E-05 Sr-90 1.35E-02 No Data 8.35E-04 No Dats No Data 2.06E+03 9.56E-05 Sr-91 1.10E-08 No Data 4.39E-10 No Data No Data 7.53E-06 3.24E-05 -
Sr-92 1.19E-09 No Data .5.08E-11 No Data No Data 3.43E-06 -1.49E-05 Y-90 3.73E-07 No Data 1.00E No Data No Data 3.66E-05 6.99E-05
- Y-91M 4.63E-Il No Data 1.77E-12 No Data No Data 4.00E-07 3.77E-09 Y-91 8.26E-05 No Data 2.21E-06 No Data -No Data 3.67E-04 5.llE-05 Y-92 1.84E-09 No Data 5.36E-Il No Data No Data- 3.35E-06 2.06E-05' ,
- Reference 3, Table E-8.
VEGP ODCH, REV 4 7/30/87 2.2-24
1 TABLE 2.2-3 (SHEET 2 Of 3) INHALATION DOSE FACTORS FOR TEENAGER * (mrem per pci inhaled) BtgJide J,gne___ liver .T Body Thyroid Kidney Luna. ,_01 - L L I Y-93 1.69E-08 No Data 4.65E-10 No Data No Data 1.04E-05 7.24E-05 Zr-95 1.82E-05 5.73E-06 3.94E-06 No Data 8.42E-06 3.36E-04 1.86E-05 Zr-97 1.72E-08 3.40E-09 1.57E-09 No Data 5.15E-09 1.62E-05 7.88E-05 Nb-95 2.32E-06 1.29E-06 7.08E-07 No Data 1.25E-06 9.39E-05 1.21E-05 Mo-99 No Data 2.llE-08 4.03E-09 No Data 5.14E-08 1.92E-05 3.36E-05 Tc-99M 1.73E-13 4.83E-13 6.24E-12 No Data 7.20E-12 1.44E-07 7.66E-07 Tc-101 7.40E-15 1.05E-14 1.03E-13 No Data 1.90E-13 8.34E-08 1.09E-16 Ru-103 2.63E-07 No Data- 1.12E-07 No Data 9.29E-07 9.79E-05 1.36E Ru-105 1.40E-10 No Data 5.42E-Il No Data 1.76E-10 2.27E-06 1.13E-05 Ru-106 1,23E-05 No Data 1.55E-06 No Data 2.38E-05 2.01E-03 1.20E-04 Ag-110M -l.73E-06 1.64E-06 9.99E-07 No' Data 3.13E-06 8.44E-04 3.410-05 . 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-Il 1.77E-10 9.10E-10 1.40E-06 1.01E-05 Te-129M 1.74E-06 8.23E-07 2.81E-07 5.72E-07 6.49E-06 2.47E-04 5.06E-05 Te-129 8.37E-12 4.22E-12 2.20E-12 6.48E-12 3.32E-ll 4.12E-07 2.02E-07 ,
le-131M 1.23E-08 7.51E-09 5.03E-09 9.06E-09 5.49E-08 2.97E-05 7.76E-05 Te-131 1.97E-12 1.04E-12 6.30E-13 1.55E-12 7.72E-12 2.92E-07 1.89E-09 Te-132 4.50E-08 3.63E-08 2.74E-08 3.07E-08 2.44E-07 5.61E-05 5.79E-05 1-130 7.80E-07 2.24E-06 8.96E-07 1,86E-04 3.44E-06 No Data 1.14E-06 1-131 4.43E-06 6.14E-06 3.30E-06 1.83E-03 1.05E-05 No Data 8.llE-07 I-132- 1.99E 07 5.47E-07 1.97E-07 1.89E-05 8.65E No Data 1.59E-07 1-133 1.52E-06 2.560-06 7.78E-07 3.65E-04 4.49E-06 No Data 1.29E-06 1-134 1.llE-07 2.90E-07 1.05E-07 4.94E-06 4.58E-07 No Data 2.55E-09 l-135 4.62E 1.18E-06 4.36E-07 7.76E-05 1.86E-06 No Data 8.69E-07 Cs-134 6.28E-05 1.41E-04 6.86E-05 No Data 4.69E-05 1.83E-05 1.22E-06 Cs-136 6.44E-06 2.42E-05 1.71E No Data 1.38E-05 2.22E-06 1.36E-06 l- Cs-137 8.38E-05 1.06E-04 3.89E-05 No Data 3.80E-05 1.51E-05 1.06E-06 Cs-138 5.82E 1.07E-07 5.58E-08 No Data '8.28E-08 9.84E-09 3.38E-Il 4 ,0a-139 1.67E-10 1.18E-13 4.87E-12 No Data 1.llE-13 8.08E-07 8.06E-07 l' }' Ba-140' 6.84E-06 8.38E-09 4.40E-07. No Data 2.85E-09 2.54E-04 2.86E-05 Ba-141 1.78E-Il -l.32E-14 5.93E-13 No Data 1.23E-14 4.llE-07 l9.33E-14 4 Ba-142 4.62E-12 4.63E-15 2.84E-13 No Data 3.92E-15 2.39E-07 5.99E-20 l O
- ReferencelabIe 3', E-8.
-VEGP ODCM, REV 4 7/30/87 2.2-25
TABLE 2.2-3 (SHECT 3 Of 3) INHALATION DOSE FACTORS FOR TEENAGER * (mrem per pei inhaled) Nuclide Bone Liver __T Body _. Thyroid Kidney Luna _.p l- L L I . La-140 5.99E-08 2.95E-08 7.82E-09 No Data No Data 2.68E-05 6.09E-05 La-142 1.20E-10 5.31E-ll 1.32E-Il No Data No Data 1.27E-06 1.50E-06
';e-141 3.55E-06 2.37E-06 2.71E-07 No Data 1.11E-06 7.67E-05 1.58E-05 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.llE-04 2.53E-04 3.28E-05 No Data 1.51E-04 1.67E-03 1.08E-04 Pr-143 1.67E-05 6.64E-07 8.28E-08 No Data 3.86E-07 6.04E-05 2.67E-05 Pr-144 5.37E-12 2.70E-12 2.72E-13 No Data 1.26E-12 2.19E-07 2.94E-14 Nd-147 9.83E-07 1.6/E-06 6.41E-08 No Data 6.28E-07 4.65E-05 2.28E-05 W-187 1.50E-09 1.22E-09 4.29E-10 No Data No Data 5.92E-06 2.21E-05 Np-239 4.23E-08 3.99E-09 2.21E-09 No Data 1.25E 08 8.llE-06 1.65E-05 O
l l
- Reference 3,-Table E-8.
L VEGP ODCH, REV 4 7/30/87 2.2-26
I' 1ABLE 2.2-4 (SilEET 1 Of 3) INHAtATION DOSE FACTORS FOR ADVllS* (mrem per pci inhaled) Nuclide Bone liver 1 Bgdy_ 1hyroid Kidnc.y Lunt _01-LLI H-3 No Data 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 C-14 2.27E-06 4.20E-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 7.440-09 2.85E-09 1.80E-06 4.15L-07 Mn-54 No Data 4.95E-06 7.87E-07 No Data 1.23E-06 1.75E-04 9.6/E-06 Mn-56 No Data 1.55E-10 2.29E-ll No Data 1.63E-10 1.18E-06 7.53E-06 fe-55 3.07E-06 2.12E-06 4.93E-07 No Data No Data 9.01E-06 7.54E-07 fe-59 1.47E-06 3.47E-06 1.32E-06 No Data No Data 1.27E-04 2.35E-05 Co-58 No Data 1.98E-07 2.59E-07 No Data No Data 1.16E-04 1.33E-05 C0-60 No Data 1.44E-06 1.85E-06 No Data No Data 7.46E-04 3.56E-05 Ni-63 5.40E-05 3.93E-06 1.81E-06 No Data No Data 2.23E-05 1.67E-06 Ni-65 1.92E-10 2.62E-Il 1.14E-ll No Data No Data 7.00E-07 1.54E-06 Cu-64 No Data 1.83E-10 7.69E-Il No Data 5.78E-10 8.48E-07 6.12E-06 Zn-65 4.05E-06 1.29E-05 5.82E-06 No Data 8.62E-06 1.08E-04 6.68E-06 Zn-69 4.23E-12 8.14E-12 5.65E-13 No Data 5.27E-12 1.15E-07 2.04E-09 Br-83 No Data No Data 3.010-08 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 C-24 Rb-86 No Data 1.69E-05 7.37E-06 No Data No Data No Data 2.08i-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-2) Sr-89 3.80E-05 No Data 1.09E-06 No Data No Data 1.75[-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-Il 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-Il 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-Il No Data No Data 1.96E-06 9.19E-06
- Reference 3 Table E-7.
VEGP ODCM, REV 4 7/30/87 2.2-27 i
TABLE 2.2-4 (SHEET 2 0F 3) INHALATION DOSE FACTOR 5 FOR ADULTS * (mremperpciinhaled) Nuclide Bone _J.iver T Body Thyroid Kidney Luna. .GI-LLI f , Y-93 1.18E-08 No Date 3.26E-10 No Data No Data 6.06E-06 5.27E-05 . Zr-95 1.34E-05 4.30E-06 2.91E-06 No Data 6.77E-06 2.21E-04 1.8BE-05
- Zr-97 1.21E-08 2.45E-09 1.13E-09 No Data 3.71E-09 9.84E-06 6.54E-05 <
1 Nb-95 1.76E-06 9.77E-07 5.26E-07 No Data 9.67E-07 6.31E-05 1.30E-05 Mo-99 No Data 1.51E-08 2.87E-09 No Data 3.64E-08 1.14E-05 3.10E-05 Tc-99H 1.29E-13 3.64E-13 4.63E-12 No Data 5.52E-12 9.55E-08 5.20E-07 Tc-101 5.22E-15 7.52E-15 7.38E-14 No Data 1.35E-13 4.99E-08 1.36E-21 Ru-103 1.91E-07 No Data 8.23E-08 No Dat: 7.29E-07 6.31E-05 1.38E-05 Ru-105 9.88E-Il No Data 3.89E-Il No Data 1.27E-10 1.37E-06 6.02E-06 Ru-106 8.64E-06 No Data 1.09E-06 No Data 1.67E-05 1.17E-03 1.14E-04 Ag-110M 1.35E-06 1.25E-06 7.43E-07 No Data 2.46E-06 5.79E-04 3.78E-05 Te-125M 4.27E-07 1.98E-07 5.84E-08 1.31E-07 1.55E-06 3.92E-05 8.83E-06 Te-127M 1.58E-06 7.21E-07 1.96E-07 4.llE-07 5.72E-06 1.20E-04 1.87E-05 Te-127 1.75E-10 8.03E-Il 3.87E-ll 1.32E-10 6.37E-10 8.14E-07 7.17E-06 Te-129M J.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 1.56E-12 4.87E-12 2.34E-ll 2.42E-07 1.96E-08 Te-131H a.74E-09 5.45E-09 3.63E-09 6.88E-09 3.86E-08 1.82T 05 6.95E-05 i Te-131 1.39E-12 7.44E-13 4.49E-13 1;17E-12 5.46E-12 1.74E-07 2.30E 09 Te-132 3.25E-08 2.69E-08 2.02E-08 2.37E-08 1.82E-07 3.60E-05 6.37E-05 I-130 5.72E-07 1.68E-06 6.60E-07 1.42E-04 2.61E-06 No Data 9.61E-07 I-131 3.15E-06 4.47E-06 -2.56E-06 1.49E-03 7.66E-06 No Data 7.85E-07 I-132 1.45E-07 4.07E-07 1.45E-07 1.43E-05 6.48E-07 No Data 5.08E-08 I-133 - 1.08E-06 1.85E-06 5.65E-07 2.69E-04 3.23E-06 No Data 1.llE-06 1-134 8.05E-08 2.16E-07 7.69E-08 3.73E-06 3.44E-07 No Data 1.26E-10 1-135 3.35E-07 8.73E-07 3.21E-07 5.60E-05 1.39E-06 No Data 6.56E-07 Cs-134 4.66E-05 1.06E-04 9.10E-05 No Data 3.59E-05 1.22E-05 1.30E-06 Cs-136 4.88E-06 1,83E-05 1.38E-05 No Data 1.07E-05 1.50E-06 1.46E-06 Cs-137 5.98E-05 7.76E-05 5.35E-05 No Data 2.78E-05 9.40E-06 1.05E-06 Cs-138 4.14E-08 7.76E-08 4.05E-08 No Data 6.00E-08 6.07E-09 2.33E-13 Ba-139 1.17E-10 8.32E-14 3.42E-12 No Data 7.78E-14 4.70E-07 1.12E-07 Ba-140 4.88E-06 6.13E-09 3.21E-07 No Data 2.09E-09 1.59E-04 2.73E-05 Ba-141 1.25E-ll 9.41E-15 4.20E-13 No Data 8.75E-15 2.42E-07 1.45E-17 Ba-142 3.29E-12 3.38E-15 2.07E-13 No Data 2.86E-15 1.49E-07 1.96E-26
- Reference 3 Table E-7.
VEGP ODCM, REV 4 7/30/87 2.2-28
,--- .-...m ,_y,, -,
...~v _ _ . , , , ,-.c, _ . . ,-,~e ..w .. , _ , _ . . , , , . , . , - . . - . - , . - - . _ . , , , . , - . ,
l TABLE 2.2-4 (SHEET 3 0F 3) O INHALAT10f4 DOSE FACTORS FOR ADULTS * (mrem per pci inhaled) tiuclide Bone 1iver i E!pjf., lhyroid Kidney L una. ._(il-1L1_ 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-Il 3.88E-11 9.65E-12 No Date No Data 7.91E-07 2.64E-07 Ce-141 2.49E-06 1.69E-00 1.91E-07 No Data 7.83E-07 4.52E-05 1.50E-05 Ce-143 2.33E-08 1.72E-08 1.91E-09 No Data 7.60E-09 9.97f.-06 2.83E-05 Ce-144 4.29E-04 1.79E-04 2.30E-05 No Data 1.06E-04 9.72E-04 1.02E-04 Pr-143 1.17E-06 4.69E-07 5.80E-08 No Data 2.70E-07 3.51E-05 2.50E-05 Pr-144 3.76E-12 1.56E-12 1.91E-13 No Data 8.81E-13 1.27E-07 2.69E-18 Nd-147 6.59E-07 7.62E-07 4.56E-08 No Data 4.45E-07 2.76E-05 2.16E-05 W-187 1.06E-09 8.85E-10 3.10E-10 No Data No Data 3.63E-06 1.94E-05 Np-239 2.87E-08 2.82E-09 1.55E-09 No Data 3.75E-09 4.70E-06 1.49E-05 O O a-- 3.1am-7. VEGP ODCM, REV 4 7/30/87 2.2-29
l l TADLE 2.2-5 (SHEET 1 Of 3) O INGESTION DOSE FACTORS FOR INFANT
- l (mrem per pci ingested) i i
tkclitig Bone Liver i Body. Thyroid Kidney Lung- _GI-LLI l 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 l Cr-51 No Data No Data 1.41E-08 9.20E-09 2.01E-09 1.79E-08 4.llE-07 Mn-54 No Data 1.99E-05 4.51E-06 No Data 4.41E-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 8.9BE-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 Co-58 No Data 3.60E-06 8.98E-06 No Data No Data No Data 8.97E-06 Co-60 No Data 1.08E-05 2.55E-05 No Data No Data No Data 2.57E-05 Ni-63 6.34E-04 3.92E-05 2.20E-05 No Data No Data No Data 1.95E-06 Ni-65 4.70E 5.32E-07 2.42E-07 No Data No Data No Data 4.05E-05 Cu-64 No Data 6.09E-07 2.82E-07 No Data 1.03E-06 No Data -1.25E-05 Zn-65 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 Br-84 No Data No Data 3.82E-07 No Data No Data No Data LT E-24 Br-85 No Data No Data 1.94E-08 No Data No Data No Data LT E-24 Rb-86 No Data 1.70E-04 8.40E-05 No Data No Data No Data 4.35E-06 Rb-88 No Data 4.98E-07 2.73E-07 No Data No Data No Data 4.85E-07 - Rb-89 No Data 2.86E-07 1.97E-0' No Data No Data No Data 9.74E-08 Sr-89 2.51E-03 No Data 7.20E-05 No Data No Data No Data 5.16E-05 Sr-90 1.85E-02 No Data 4.71E-03 No Data No Data No Data 2.31E-04
'Sr-91 5.00E-05 No Data 1.81E-06 No Data No Data No Data 5.92E-05 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 ..ta No Data 1.20E-04 Y-91M 8.10E No Data 2.76E-Il No Data No Data No Data 2.70E-06 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
- Reference 3, Table E-14.
VEGP ODCM, REV 4 7/30/87 2.2-30
I TABLE 2.2-5 (SHEET 2 Of 3) O
\' / INGESTION DOSE FACTORS FOR INFANT *
(mrem per pei ingested) Nuclide Bone liver T Body Thyroid Kidnt,y ._ Lyn _g., _ji-LLL 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 1.560-09 4.86E-07 Ru-103 1.48E-06 No Data 4.95E-07 No Data 3.08E-06 No Data 1.00E-05 Ru-105 1.36E-07 No Data 4.58E-08 No Data 1.00E-06 No Data 5.41E-05 Ru-106 2.41E-05 No Data 3.01E-06 No Data 2.85E-05 No Data 1.83E-04 Ag-110M 9.96E-07 7.27E-07 4.81E-07 No Data 1.04E-06 No Data 3.77E-05 Te-125M 2.33E-05 7.79E-06 3.15E-06 7.84E-06 No Data No Data 1.llE-05 To-127M 5.85E-05 1.94E-05 7.08E-06 1.69E-05 1.44E-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
T Te-129M 1.00E-04 3.43E-05 1.54E-05 3.84E-05 2.50E-04 No Data 5.97E-05 (G Te-129 2.84E-07 9.79E-08 6.63E-08 2.3BE-07 7.07E-07 No Data 2.27E-05 Te-131M 1.52E-05 6.12E-06 5.05E-06 1.24E-05 4.21E-05 No Data 1.03E-04 Te-131 1.76E-07 6.50E-08 4.94E-08 1.57E-07 4.50E-07 No Data 7.llE-06 Te-132 2.08E-05 1.03E-05 9.61E-06 1.52E-05 6.44E-05 No Data 3.81E 1-130 6.00E-06 1.32E-05 5.30E-06 1.48E-03 1.45E-05 No Data 2.83E-06 1-131 3.590-05 4.23E-05 1.86E-05 1.39E-02 4.94E-05 No Data 1.51E-06 1-132 1.66E-06 3.37E-06 1.20E-06 1.58E-04 3:76E-06 No Data 2.73E-06 1-133 1.25E-0E 1.82E-05 5.33E-06 3.31E-03 2.14E-05 No Data 3.08E-06 1-134 8.69E-07 1.78E-06 6.33E-07 4.15E-05 1.99E-06 No Data 1.84E-06 1-135 3.64E-06 7.24E-06 2.64E-06 6.49E-04 8.07E-06 No Data 2.62E-06 Cs-134 3.77E-04 7.03E-04 7.10E-05 No Data 1.81E-04 7.42E-05 1.91E-06 Cs-136 4.59E-05 1.35E-04 5.04E-05 No Data 5.38E-05 1.10E-05 2.05E-06 Cs-137 5.22E-04 6.llE-04 4.33E-05 No Data 1.64E-04 6.64E-05 1.91E-06 Cs-138 4.81E-07 7.82E-07 3.79E-07 No Data 3.90E-07 6.09E-08 1.25E-06 Ba-139 8.81E-07 5.84E-10 2.55E-08 No Data 3.51E-10 3.54E-10 5.58E-05 tN.
( ,)
- Reference 3, Table E-14.
VECP ODCM, REV 4 7/30/87 2.2-31
__.._______y_ _ ___._ __.._______ _ _ ___. I TABLE 2.2-5 (SHEET 3 Of 3) O INCEST 10N DOSE FACTORS FOR INFAN1* (mrom per 9ci ingested) thtq11@ _f,,g n e __ Liver T Body Thyroid fddntY _Lun2_ -.01-LLI Ba-140 1.71E-04 1.71E-07 8.81E-06 No Data 4.06E-08 1.05E-07 4.20E-05 Ba-141 4.25E-07 2.91E-10 1.34E-08 No Data 1.75E-10 1.77E-10 5.19E-06 Ba-142 1,84E-07 1.53E-10 9.06E-09 No Data 8.81E-Il 9.26E-11 7.59E-07 La-140 2.llE-08 8.32E-09 2.14E-09 No Data No Data No Data 9.77E-05 La-142 1.10E-09 4.04E-10 9.67E-Il 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 Co-144 2.98E-06 1,22E 06 1.67E-07 No Data 4.93E-07 No Data 1.71E-04 Pr+143 8.13E-08 3.04E-08 4.03E-09 No Data 1.13E-08 No Data 4.29E-05 t Pr-144 2.74E-10 1.06E-10 1.3BE-Il No Data 3.84E-Il No Data 4.93E Nd-147 5.53E-08 5.68E-08 3.48E-09 No Data 2.19E-08 No Data 3.60E-05 W-187 -9.03E-07 6.28E-07 2.17E-07 No Data No Data No Data 3.69E-05 Np-239 1.llE-08 9.93E-10 5.61E-10 No Data 1.98E-09 No Data 2.87E-05 0 . t i l ()
- Reference 3, Table E-14.
VEGP ODCM, REV 4 7/30/87 2.2-32
f r TABLE 2.2-6 (SNEET 1 Of 3) INGESTION DOSE FACTORS FOR CHILD * (mrem per pci ingested) Nuclide Bone Liver T Body Thyroid Kidney -- L una - _Gl-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.SOE-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 C0-58 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 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 Br-83 No Data No Data 1.71E-07 No Data -No Data No Data LT E-24 Br-84 No Data No Data 1.98E-07 No Data No Data No Data LT E-24 Dr-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 No Data No Data -No Data 9.32E-09 Rb-89 No Data 1.17E-07 1.04E-07 No Data No Data No Data 1.02E-09 Sr-89 1.32E-03 No Data 3.77E-05 No Data No Data No Data 5.llE-05 Sr-90 1.70E-02 No Data 4.31E-03 No Data No Data No Data 2.29E-04 Sr-91 2.40E-05 No Data 9.06E-07 No Data No Data No Data 5.30E-05 Sr-92 9.03E-06 No Data 3.62E-07 No Data No Data No Data 1.71E-04 - Y-90 4.llE-08 No Data 1.10E-09 No Data No Data No Data 1.17E-04 Y-91M 3.82E-10 No Data 1.39E-11 No Data No Data No-Data 7.48E-07 Y-91 6.02E-07 No Data 1.61E-08 No Data Nc Data No Data 8.02E-05 Y-92 .3.60E-09 No Data 1.03E-10 No Data No Data No Data 1.04E-04 ()* Reference 3,TableE-13.
- VEGP ODCM, REV 4 7/30/87 2.2-33
TABLE 2.2-6 (SHEET 2 Of 3) O INGESTION DOSE FACTORS FOR CHILD * (mrem per pci ingested) Nuclide Bone .Livtr .T Body Thyroid Kidan Luna lil-t L__I _ 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 3.55E-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 Ho-99 No Data 1.33E-05 3.29E-06 No Data 2.84E-05 No Data 1.10E-05 Tc-99M 9.23E-10 1.81E-09 3.00E-08 No Data 2.63E-08 9.19E-10 1.03E-06 Tc-101 1.07E-09 1.12E 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-03 No Data 2.34E-08 No Data 5.67E-07 No Data 4.21E-05 Ru-106 1.17E-05 No Data 1.46E-06 No Data 1.58E-05 No Data 1.82E-04 Ag-110H 5.39E-07 3.64E-07 2.91E 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-127H 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-37 1.01E-07 3.26E-07 1.34E-06 No Data 1.84E-05 Te-129H 4.87E-05 1.36E-05 7.56E-06 1.57E-05 1.43E-04 No Data 5.94E-05 Te-129- 1.34E-07 3.74E-08 3.18E-08 9.56E-08 3.92E-07 No Data 8.34E-06 Te-131M 7.20E-06 2.49E-06 2.65E-06 5.12E-06 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 1.01E-05 4.47E-06 5.40E-06 6.51E-06 4.15E-05 No Data 4.50E-05 1-130 2.92E-06 5.90E-06 3.04E-06 6.50E-04 8.82E-06 No Data 2.76E-06 l-131 1.72[-05 1.73E-05 9.83E-06 5.72E-03 2.84E-05 No Data 1.54E-06 1-132 8.00E-07 1.47E-06 6.76E-07 6.82E-05 2.25E-06 No Data 1.73E-06 I-133 5.92E-06 7.32E-06 2.77E-06 1.36E-03 1.22E-05 No Data 2.95E-06 1-134 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 3.15E-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 2.3SE-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 2.21E-10 1.20E-08 No Data 1.93E-10 1.30E-10 2.39E-05 Ba-140 0.31E-05 7.28E-08 4.85E-06 No Data 2.37E-08 4.34E-08 4.21E-05 i Bri-141 2.00E-07 1.12E-10 6.51E-09 No Data 9.69E-Il 6.58E-10 1.14E-07 Ba-142 8.74E-08 6.29E-Il 4.88E-09 No Data 5.09E-Il 3.70E-Il 1.14E-09 l O
- Reference 3, Table E-13.
VEGP ODCH, REV 4 7/30/87 2.2-34 _ . - , , , ,.,._.,w -.wy
TABLE 2.2-6 (SHEE1 3 Of 3) INGESTION DOSE FACTORS FOR CHILD * (mrom per pei ingested) l ((gc].id.g Bone .11yer T Body _ *hyroid KLdHEY _Lun9- 01-lli- l l La-140 1.01E-08 3.53E-09 1.19E-09 No Data No Data No Data 9.84E-05 ) La-142 5.24E-10 1.67E-10 5.23E-11 No Data No Data No Data 3.31E-05 Ce-14] 3.97E-08 1.98E-08 2.94E-09 No Data 8.68E-09 No Data 2.47E-05 Cc-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 1.29E-10 3.99E-Il 6.49E-12 No Data 2.llE-Il No Data 8.59E-08 Nd-147 2,79E-08 2.26E-08 1.75E-09 No Data 1.24E-08 No Data 3.58E-05 W-187 4.29E-07 2.54E-07 1.14E-07 No Data No Data No Data 3.57E-05 Np-239 5.25E-09 3.77E-10 2.65E-10 No Data 1.09E-09 No Data 2.79E-05 1 O
- Reference 3. Table E-13.
VEGP ODCH, REV 4 7/30/87 2.2-35 _.-,- - ..- -_ . - . - - . - . . - ___--.= . - - - - .
I TABLE 2.2-7 (SHEET 1 0F 3) O INGESTION DOSE FACTORS FOR TEENAGER * (mrem per pci ingested) I 1 Lluclide Bqne __ Liver T Body Thyroid Kidney Luna _GI-Lll 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-01 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 ; Mn-54 No Data 5.90E-06 1.17E-06 No Data 1.76E-06 No Data 1.21E-05 Mn-56 No Data 1.58E-07 2.81E-08 No Data 2.00E-07 No Data 1.04E-05 Fe-55 ' 3.78E-06 2.68E-06 6.25E-07 No Data No Data 1.70E-06 1.16E-06 Fe-59 5.87E-06 1.37E-05 5.29E-06 No Data No Data 4.32E-06 3.24E-05 00-58 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 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 Zn-65 5.76E-06 2.00E-05 9.33E-06 No Data 1.28E-05 No Data 8.47E-06 2n-69 1.47E-08 2.80E-08 1.96E-09 No Data 1.83E-08 No Data 5.16E-08 Br 83 No Data No Data 5.74E-08 No Data No Data No Data LT E-24 Br-84 No Data No Data 7.22E-08 No Data No Data No Data LT E-24 Br-85 No Data No Data 3.05E-09 No Data No Data No Data LT E-24 Rb-86 No Data 2.98E-05 1.40E-05 No Data No Data No Data 4.41E-06 Rb-88 No Data 8.52E-08 4.54E-08 No Data No Data No Data 7.30E-15 Rb-89 No Data 5.50E-08 3.8;E-08 No Data No Data No Data 8.43E-17 Sr-89 4.40E-04 No Data 1.26E-05 No Data No Data No Data 5.24E-05 Sr-90 8.30E-03 No Data 2.05E-03 No Data No Data No Data 2.33E-04 Sr-91 8.07E-06 No Data 3.21E-07 No Data No Data No Data 3.66E-05 Sr-92 3.05E-06 No Data 1.30E-07 No Data No Data No Data 7.77E-05 Y-90 1.37E-08 No Data 3.69E-10. No Data No Data No Data 1.13E-04 Y-91H 1.29E-10 No Data 4.93E-12 No Data No Deta No Data 6.09E-09 Y-91 2.01E-07 No Data 5.39E-09 No Data No Data No Data 8.24E-05 Y-92 1.21E-09 No Data 3.50E-ll No Data No Data No Data 3.32E-05
- Reference 3,TaUeE-12.
VEGP ODCM, REV 4- 7/30/87 2.2-36
TABLE 2.2-7 (SHEET 2 Of 3)
' INGESTION DOSE FACTORS FOR lEENAGER*
(mrem per pci ingesteo) Nuclide Bone ,_. Liar __ _1_BMt Jhyroid tLtdan __Litn9_ ._RI-1LL Y-93 3.83E-09 No Data 1.05E-10 No Data No Data No Data 1.17E-04 Zr-95 4.12E-08 1.30E-08 8.94E-09 No Data 1.91E-08 No Data 3.00E-05 Zr-97 2.37E-09 4.69E-10 2.16E-10 No Data 7.11E-10 No Data 1.27E-04 Nb-95 8.22E-09 4.56E-09 7.51E-09 No Data 4.42E-09 No Data 1.95E-05 Mo-99 No Data 6.03E-06 1.15E-06 No Data 1.38E-05 No Data 1.08E-05 Tc-99M 3.32E-10 9.26E-10 1.20E-08 No Data 1.38E-08 5.14E-10 6.08E-07 1c-101 3.60E-10 5.12E-10 5.03E-09 No Data 9.26E-09 3.12E-10 8.75E-17 Ru-103 2.55E-07 No Dita 1.09E-07 No Data 8.99E-07 No Data 2.13E-05 Ru-105 2.18E-08 No Data 8.46E-09 No Data 2.75E-07 No Data 1.76E-05 Ru-106 3.92E-06 No Data 4.94E-07 No Data 7.56E-06 No Data 1.88E-04 Ag-110M 2.05E-07 1.94E-07 1.18E-07 No Dath 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 () V Te-129M 1.63E-05 6.05E-06 2.58E-06 5.26E-06 6.82E-05 No Data 6.120-05 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 1.76E-06 1.22E-05 No Data 9.39E-05 Te-131 2.79E-03 1.15E-08 8.72E-09 2.15E-08 1.22E-07 No Data 2.29E-09 Te-132 3.49E-06 2.21E-06 2.08E-06 2.33E-06 2.12E-05 No Data 7.00E 1-130 1.03E-06 2.98E-06 1.19E-06 2.43E-04 4.59E-06 No Data 2.29E-06 1-131 5.85E-06 8.19E-06 4.40E-06 2.39E-03 1.41E-05 No Data 1.62E-06 1-132 2.79E-07 7.30E-07 2.62E-07 2.46E-05 1.15E-06 No Data 3.18E-07 1-133 2.01E-06 3.41E-06 1.04E-06 4.76E-04 5.98E-06 No Data 2.58E-06 1-134 1.46E-07 3.87E-07 1.39E 07 6.45E-06 6.10E-07 No Data 5.10E-09 l-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 Cs-137 1.12E-04 1.49E-04 5.19E-05 No Data 5.07E-05 1.97E-05 2.12E-06 Cs-138 7.76E-08 1.49E-07 7.45E-08 No Data 1.10E-07 1.28E-08 6.76E-ll Ba-139 1.39E-07 9.78E-Il 4.05E-09 No Data 9.22E-Il 6.74E-Il 1.24E-06 ()
- Reference 3, Table E-12.
VEGP ODCM, REV 4 7/30/87 2.2-37
_ -_ _ _ _ _ . _ . _ = _ _ . _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ . _ _ _ _ TABLE 2.2-7 (SHEL1 3 0F 3) INGESTION DOSE FACTORS FOR 1EENAGER* (mrem per pei ingested) , Nuclide __1gng___ liver T Body 1hyroid Kidacy _ 1gng_ GI-LLI l Ba-140 2.84E-05 3.48E-08 1.83E-06 No Data 1.18E-08 2.34E-08 4.38E-05 Da-141 6.71E-08 5.01E-Il 2.24E-09 No Data 4.65E-Il 3.43E-Il 1.43E-13 Ba-142 2.99E-08 2.99E-Il 1.84E-09 No Data 2.53E-Il 1.99E-ll 9.18E-20 t La 140 3.48E-09 1.71E-09 4.55E-10 No Data No Data No Data 9.82E La-142 1.79E-10 7.95E-Il 1.98E-Il No Data No Data No Data 2.42E-06 Ce-141 1.33E-08 8.88E-09 1.02E-09 No Data 4.18E-99 No Data 2.54E-05 0e-143 2.35E-09 1.71E-06 1.91E-10 No Data 7.67E-10 No Data 5.14E-05
- Ce-144 6.96E-07 2.88E-07 3.74E-08 No Data 1.72E-07 iP 'ata 1.75E-04 Pr-143 1.31E-08 5.23E-09 6.52E-10 No Data 3.04E-09 No Data 4.31E-05
- Pr-144 4.30E-Il 1.76E-ll 2.18E-12 No Data 1.01E-Il No Data 4.74E-14 ,
Nd-147 9.38E-09 1.02E-08 6.1]E-10 No Data 5.99: No Data 3.68E-05 W-187 1.46E-07 1.19E-07 4.17E-08 No Data No Data No Data 3.220-05 Np-239 1.76E-09 1.66E-10 9.22E-11 No Data 5.21E-10 No Data 2.67E-05 : O
- Reference 3, Table E-12.
VEGP ODCH,-REV 4 7/30/87 2.2-38 rI e, . .- - , , . , , . , - - . , . _ , _-
, . , - - - - - m , y m_my,------,..m.,.,--m---,--m--w#,-,.m.,. , - , ,, .-mm >
TABLE 2.2-8 (SNEE1 1 Of 3) O INGES11(T 90SE fAC7 ORS FOR ADVT 1S* (nr per pci ingested) [httlMt _.J M t _. ..L11cL_ _T Body _ Jhyroid tMqty _LunL _ G1-LL L_ H3 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 r. 68E-07 5.68E-07 5.68E-07 5.68E-07 Na-24 1.70E-06 1.70E-06 1.700-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 P-32 1.93E-04 1.20E-05 7.46E-06 No Data No Data No Data 2.17E-05 Cr-51 No Data No Data 2.6bE-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 1.40E-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. E -06 Fe-59 4.34E-06 1.02E-05 3.91E-06 No Data No Data 2.85E-06 3.40E-05 00-58 No Data 7.45E-07 1.67E-06 No Data No Data No Data 1.51E-05 Co-60 No Data 2.14E-06 4.72E-06 No Data No Data No Data 4.02E-05 Ni-63 1.30E-04 9.01E-06 4.36E-06 No Data No Data No Data 1.88[-06 Ni-65 5.2BE-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 2n-69 1.03E-08 1.97E-08 1.37E-09 No Data 1.28E-08 No Data 2 96E-09 Br-83 No Data No Data 4.02E-08 No Data No Data No Data 5.79E-08 Br-84 No Data No Data 5.21E-08 No Data No Data No Data 4.09E-13 Br-85 No Data No Data 2.14E-09 No Data No Data No Data LT E-24 Rb-86 No Data 2.llE-05 9.83E-06 No Data No Data No Data 4.16E-06 Rb-88 No Data 6.05E-08 3.21E-08 No Data No Data No Data 8.36E-19 Rb-89 No Data 4.01E-08 2.82E-08 No Data No Data No Data 2.33E-21 Sr-89 3.08E-04 No Data 8.84E-06 No Data No Data No Data 4.94E-05 Sr-90 7.58E-03 No Data 1.86E-03 No Data No Data No Data 2.19E-04 Sr-91 5.67E-06 No Data 2.29E-07 No Data No Data No Data 2.70E-05 Sr-92 2.15E-06 No Data 9.30E-08 No Data No Data No Data 4.26E-05 Y-90 9.62E-09 No Data 2.38E-10 No Data No Data No Data 1.02E-04 Y-91M 9.09E-Il No Data 3.52C-12 No Data No Data No Data 2.67E-10 Y-91 1.41E-07 No Data 3.77E-09 No Data No Data No Data 7.76E-05 Y-92 8.45E-10 No Data 2.47E-Il No Data No Data No Data 1.48E-05
- Reference 3, Table E-ll.
VEGP ODCM, REV 4 7/30/87 2.2-39
-~ TABLE 2.2-8 (SHEET 2 Of 3)
INGESTION DOSE FACTORS FOR ADUL15* (mrem per pcl ingested) Nuclids Bone Liver T Body Ih.Yr0id KidDM .1UnU GI-lll 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-06 No Data 3.09E-05 Zr-97 1.68E-09 3.39E-10 1.65E-10 No Data 5.12E-10 No Data 1.05E-04 Nb-95 6.22E-09 3.40E-09 1.86E-09 No Data 3.42E-09 No Data 2.10E-05 Mc-99 No Data 4.31E-06 8.20E-07 No Data 9.76E-05 No Data 9.99E-06 Tc-99h 2.47E-10 6.98E-10 8.89E-09 No Data 1.06E-08 3.42E-10 4.13E-07 Tc-101 2.54E-10 3 66E 'O 3.59E-09 No Data 6.59E-09 1.87E-10 1.10E-21 Ru-103 1.85E-07 No Data 7.97E-08 No Data 7.06E-07 No Data 2.16E-05 Ru-105 1.54E-08 No Data 6.08E-09 No Data 1.99E-07 No Data 9.42E-06 Ru-106 2.75E-06 No Data 3.48E-01 No Data 5.3'E-06 No Data
. 1.78E-04 Ag-110M 1.60E-07 1.48E-07 8.)9E-08 No Data 2.91E-07 No Data 6.04E-05 Sb-124 2.81E-06 5.3E-08 1.llE-06 6.79E-09 No Data 2.18E-06 7.95E-05 Sb-125 2.23E-06 2.4E-08 4.48E-07 1.98E-09 No Data 2.33E-04 1.97E-05 Te-125M 2.68E-06 9.71E-07 3.59E-07 8.06E-07 1.09E-05 No Data 1.07E-05
() (m / Te-127M Te-127 6.77E-06 2.42E-06 8.25E-07 1.73E-06 2.75E-05 No Data 1.10E-07 3.95E-08 2.38E-08 8.15E-08 4.48E-07 No Data 2.27E-05 8.68E-06 le-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-J9 Te-132 2.52E-06 1.63E-06 1.53E-06 1.80E-06 1.57E-05 No Data 1.71E-05 1-130 7.56E-07 2.23E-06 8.80E-07 1.89E-04 3.48E-06 No Data 1.92E-06 1-131 4.16E-06 5.95E-06 3.41E-06 1.95E-03 1.02E-05 No Data 1.57E-06 1-132 2.03E-07 5.43E-07 1. 90 E- 07 1.90E-05 8.65E-07 No Data 1.02E-07 1-133 1.42E-06 2.47E-06 7.53E-07 3.63E-04 4.31E-06 No Data 2.22E-06 1-134 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 No Data 2.51E-10 1-135 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-126 6.51E-06 2.57E-05 1.85E-05 No Data 1.43E-05 1.96E-06 2.92E-Of Cs-137 7.97E-05 1.09E-04 7.14E-05 No Data 3.70E-05 1.23E-05 2.llE-06 Cs-138 5.52E-08 1.09E-07 5.40E-08 No Data 8.01E-08 7.91E-09 4.65E-13 Ba-139 9.70E-08 6.91E-ll 2.84E-09 No Data 6.46E-Il 3.92E-Il 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 f-'N Ba-141 4.71E-08 3.56E 'l 1.59E-09 No Data 3.31E-ll 2.02E-ll 2.22E-17 is
, ) Ba-142 2.13E-08 2.19E-Il 1.34E-09 No Data 1.85E-Il 1.24E-ll 3.00E-26
- Reference 3, Table E-ll.
VEGP ODCM, REV 7 3/01/91 2.2-40 new.
l l I TABLE 2.2-8 (SHEE! 3 Of 3) INGESTION DOSE FAC10RS FOR ADULTS * (mrem per pci ingested) Nuclide Bone liver T Body- Thyroid Kidney Jun0 GI-Lll La-140 2.50E-09 1.26E-09 3.33E-10 No Data No Data No Data 9.25E-05 La-142 1.28E-10 5.82E-11 1.45E-Il No Data No Data No Data 4.25E-07 Ce-141 9.36E-09 6.33E-09 7.18E-10 No Data 2.94E-09 No Data 2.42E-05 Ce-143 1.65E-09 1.22E-06 1.35E-10 No Data 5.37E-10 No Data 4.56E-05 Ce-144 4.88E-07 2.04E-07 2.62E-08 No Data 1.21E-07 No Data 1.65E-04 Pr-143 9.20E-09 3.69E-09 4.56E-10 No Data 2.13E-09 No Data 4.03E-05 Pr-144 3.01E-Il 1.25E-Il 1.53E-12 No Data 7.05E-12 No Data 4.33E-18 Nd-147 6.29E-09 7.27E-09 4.35E-10 No Data 4.25E-09 No Data 3.49E-05 W-187 1.03E-07 3.61E-08 3.01E-08 No Data No Data No Data 2.82E-05 Np-239 1.19E-09 1.17E-10 6.45E-Il No Data 3.65E-:, No Data 2.40E-05 0 O 8 r <e c 3. ' 81e <->>. VEGP ODCH, REV 4 7/30/87 2.2-41
+
TABLE 2.2-9 (SHEET 1 0F 2) f)s EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATEC GROUND *
\
l (mrem /h per pCi/m') ! RAD 10NUCllDE TOTAL BODY SK18 H-3 0.0 0.0 C-14 0.0 0.0 Na-24 2.50E-08 2.90E-08 P-32 0.0 0.0 Cr-51 2.20E-10 2.60E-10 Hn-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 2n-65 4.00E-09 4.60E-09 2n-69 0.0 0.0 Br-83 6.40E-Il 9.30E-Il Br-84 1.20E-08 1.40E-08 Br-85 0.0 0.0 Os Rb-86 Rb-88 6.30E-10 7.20E-10 3.50E-09 4.00E-09 Rb-89 1.50E-08 1.80E-08 Sr-89 5.60E 6.50E-13 Sr-91 7.10E-09 8.30E-09 Sr-92 9.00E-09 1.00E-08 Y 2.20E-12 2.60E-12 Y-91M 3.80E-09 4.40E-09 Y-91 2.40E-Il 2.70E-11 Y-92 1.60E-09 1.90E-09 Y-93 5.70E-10 7.80E-10 7 -45 5.00E-09 5.80E-09 i < 17 5.50E-09 6.40E-09 ND-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 l Ru-106 1.50E-09 1.80E-09 1 Ag-110M 1.80E-08 2.10E-08 Te-125M 3.50E-Il 4.80E-Il ()
- Reference 3, Table E-6, VEGP ODCM, REV 4 7/30/87 2.2-42 1- .
.. . __ _ - _ _ .. _ _ _ _ _ _..~._ . . .____ _ _
TABLE 2.2-9 (SHEET 2 Or 2) EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND * (mrem /h per pCi/m') i RAD 10NUCL10E TOTAL Bppl $Klfj Te-127M 1.10E-12 1.30E-12 Te-127 1.00E-Il 1.10E-Il Te-129M 7.70E-10 9.00E-10 . Te-129 7.10E-10 8.40E-10 ' Te-131M 8.40E-09 9.90E-09 le-131 2.20E-09 2.60E-06 Te-132 1.70E-09 2.00E-09 l-130 1.40E-08 1.70E-08 1-131 2.80E-09 3.40E-09 1-132 1.70E-08 2.00E-08 1-133 3.70E-09 4.50E-09 l-134 1.60E-08 1.90E-08 I-135 1.20E-08 1.40E-08 Cs-134 1.20E-08 1.40E-08 Cs-136 1.50E-08 1.70E-08 Cs-137 4.20E-09 4.90E-09 Cs-138 2.10E-08 2.40E-08 Ea-139 2.40E-09 2.70E-09 Ba-140 2.10E-09 2.40E-09 i Ba-141' 4.30E-09 4.90E-09 Ba-142 7.90-09 9.00E-09 La-140 1.50E-08 1.70E -La-142 1.50E-08 1.80E-08 Ce-141 5.50E-10 6.20E-10 Ce-143 2.20E-09 2.50E-09 - Ce-144 3.20E-10 3.70E-10 Pr-143 0.0 0.0 Pr-144 2.00E-10 2.30E-10 Nd-147 1.00E-09 1.20E-09
- W-187 3.10E-09 3.60E-09 Np-239 9.50E-10 1.10E-09 ,
u
- Reference 3, tan e E-6.
I VEGP ODCM, REV 4 7/30/87 2.2-43 1; .
- . , . . . - _ , . . _ - _ . ~ . , . . _ . . , ._, . _.
. - - - - . _ . . _ - . - - _ . .. - =_ - - - -. ._- . - . . - - ~ . . _ _ - - . . - i TABLE 2.2-10 INDIVIDUAL USAGE FACIOR$*
.11G!ll f.W10 lLULMLB ADML1 Milk Conshmptien Rate, U.,(liters / year) 330 330 400 310 Heat Consumption Rate, U,(kg'* tar) 0 41 65 110 Fresh Leafy Vegetation Consumption Rate, U,e(kg/ year) 0 26 47 64 Stored Vegetation Consumption Rate, 0,,(kg/ year) 0 520 630 520 Breathing Rate (m'/ year) 1400 3700 8000 0000 F
t' O"
- Reference 3, Table E-5.
-VEGP ODCM,.REV 4 7/30/87 2.2-44
TABLE 2.2-11
\- -
$1ABLE ELEMENT 1RANSEER DATA *
(Hilk-days / liter; Heat-days /kg) E,- HILK E,- HILK ff - HEAT ELEMEN1 _.LL010__ . (c0AT) H 1.0E-02 1.7E-01 1.2E-02 C 1.2E-02 1.0E-01 3.lE-02 - Na 4.0E-02 4.0E-02 3.0E-02 P 2.SE-02. 2.5E-01 4.6E-02 - Cr 2.20-03 2.2E-03 2.4E-03 Hn 2.5E-04 2.5E-04 8.0E-04 Ee 1.2E 03 1.3E-04 4.0E-02 Co 1.CE-03 1.0E-03 1.3E-02 Ni 6.7E-03 6.7E-03 5.3E-02 Cu 1.4E-OL 1.3E-02 8.0E-03 i 2n 3.9E 3.9E 02 3.0E-02 Rb 3.0E-02 3.0E-02 3 lE-02 Sr B.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.SE-01 Ho 7.5E-03 7.5E 03 8.0E-03 . Tc 2.5E-02 2.5E-02 4.0E-01
- Ru 1.0E-06 1.0E-06 4.0E-01 '
Rh 1.0E-02 1.0E-02 1.5E-03 Ag 5.0E-02 5.0E 02 1.7E-02 . 1,0E-03 To 1.0E-03 7.7E-02 1 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. 3 E-03 W 5.0E-04 5.0E-04 1.3E-03 Np 5.0E-06 5.0E-06 2.0E-04
- References 3, Table E-1; Reference 3, Table E-2 for H C, P, Fe, Cu, Sr, I, and Cs in goat's milk; the remainder of elements in goat's milk are taken from Tab're E-1 as presented for cow's milk.
O, . VEGP ODCH, REV 4 7/30/87 2.2-45
-. . _ - - _ _ . . . _-.- - . - - _ . . . . - . . - . - . . . _ - - . - . . -. - -. . - . - ~
I i TABLE 2.2-12 CONTROLLING RECEP10R (To support subrection 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 January 1, 1985, through December 31, 1987 (Reference 13). t Sector: WSW Distance: 1.2 miles Age Group: Ehild 3 Dispersion: (X/Q')gp 6.2E-7 s/m3 (IT6') gp 1.270-7 s/m Deposition (D/Q')gp = 2.8E-9 m-2 (D/Q') gp - 9.0E-10 m-2 Exposure pathways: Inhalation and ground plane.
/7 V
9 t
- References 12 13, 15'and 16.
_VEGP ODCH, REV 6 9/30/88 2.2-46
. . , , , , , ..,,--,,+-ra, r1--- ~-& 'e- -v== v~ *ve- a ~ "v' v~'" 4 " * ' ' ' ' ' ' ' ' ' ' ' " " ' ' ' "
- _ _ . . _ . . . . ._ __ - .._ _ -.___ - - ~ _ _ _. _
TABLE 2.2-13 (SHEET 1 0F 4) SITE-SPECIFIC (OR DLFAULT) VALUES TO BE USED IN PATHWAY FACTOR CA'.CULATIONS (Supports subsections 2.2.2.2 ard 2.2.2.3)
- farameter Description ,_ Value i Inhalation (BR), Breathing rate for age group table 2.2-10 (DFA)y, Inhalation dose factor for tables 2.2-1, age group 2.2-4 Ground plane SHF Shielding factor due to 0.7 structure (Reference 3, table E-15)
(DFG)y Ground plane dose factor table ?_?-9
.(Same for all age groups)
- Garden Vegetation V, Garden vegetation areal 2.0 kg/m' density (Reference 3, table E-lf)
U,e Leafy vegetation consumption table ?.2-10 rate for age group U., Stored vegetation consumption table 2.2-10 rate for age-group fe Fraction' of annual intake 1.0 of leafy vegetation grown (Reference 1, locally page 36) f, Fraction of annual intake of 0.76 stored vegetation grown locally (Reference 1, page 36) H Abso' lute humidity of the 8.0 gm/m' atmosphere (Reference 1, page 34) O v
- VEGP 00CM, REV 8 Draft 2.2-47 e e e ac_- -
TABLE 2.2-13 (SHEET 2 0F 4) ft i SITE-SPECIFIC (Ok DEFAULT) VALUES TO BE USED IN PATHWAY FACTOR CALCULATIONS Parameter Descrintion , Value Grass-Cow-Meat l: Q, - Feed consumption rate for cow 50 kg/ day (Reference 3, table L-3)
- ' U,, - Heat consumption rate for table 2.2-10 age group (DFL)y,, Ingestion dose factor for tables 2.2 ,
- age group 2.2-8 '
Y, Pasture grass areal density 0.7 kg/m' (Reference 3, table E-15) Y, Stored feed areal density 2.0 kg/m'2 , (Reference 3, l ,p
, ,V table E-15) i f, Fraction of year that cow 1.0 grazes are pasture (Reference 1,
- page 33) i f, 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/m' atmosphere (Reference 1, page 34) e I
Geass-Cow-Hilk Q, Feed consumption rate for 50 kg/ day cow (Reference 3, table E-3) U,, Milk consumption rate for table 2.2-10 age group
-(DFL)y, Ingestion dose factor for tables 2.2 age group 2.2-8 d
VEGP ODCM, REV 4 7 /30/87 2.2-48
l TABLE 2.2-13 (SHEET 3 0F 4) O SITE-SPECIFIC (OR DEFAULT) VALUES TO BE USED IN PATHWAY FACTOR CALCULATIONS Parameter Dn qription Valup_ Y, Pasture grass areal density 0.7 kg/m' (Reference 3, table E-15) Y. Stored fes' 3.'eal density 2.0 kg/m' (Reference 3, table E-15) - f, Fraction of year that cew 1.0 grazes (Reference 1, page 33) f, Fraction of total feed that is 1.0 pasture grass while cow is on (Reference 1, pasture page 33) H Absalute hutnidity of the 8.0 gm/m' ctmosphere (Reference 1, page 34) Grass-Goat-Milk Q, feed consumption rate for 6.0 kg/ day goat (Reference 3, table E-3) - U., Mi k consumption rate for tatle 2.2-10 ar group (DFL)y, Ingestion dose factor for tables 2.2 age group 2.2-8 Y, Pasture grass areal density 0.7 kg/m' (Reference 3, table E-15) Y. Stored feed ateal density 2.0 kg/m' (Reference 3, table E-15) f, Fraction of year that goat 1.0 is on pasture (Reference 1, page 33) O VEGP ODCM, REV 4 7/30/87 2.2-49
. ~ . _- - _. .
TABLE 2.2-13 (SHEET 4 0F 4) SITE-SPECIFIC (OR DEFAULT)-VALUES 10
- BE USED IN PATHWAY FACTOR CALCULAT10f1S Parameter Description Value f, Fraction of total feed that is 1,0 pasture _ grass while goat is on (Reference 1, pasture page 33)
H Absolute huraidity of the 8.0 gm/m' atmosphere (Reference 1, page 34) O is
.VEGP ODCM, REV 4 7/30/87 2.2-50
~
.q .1 j TABLE 2.2-14 POTENTIAL RECEPTOR LOCATIONS AND PATilWAYS (To support subsection 2.2.2.3)-
a F (This table has bes 'eleted.) LO \ j,. l i O VEGP ODCM,.REV 8 Draft 2.2-51
. . - . . - ~ .- - .-- . .. - - -.. ... ...- . . - ..-.. ..- -....
TABLE 2,2-15 DISPERSION AND DEPOSITION PARAMETERS (To Support Subsection 2.2.2.3) i i i-i 4 4
.(This table has been deleted.)
G . O i I i
. \
l i 1 l
-l l
i L l' y l' LO
- VECP?0DCM, REV 8 Draft 2.2-52 r e***"p-<v~1--'nv+r y w,- ,-
-wm
2.2.3 Dose Prgiections for Gaseous Effluents 2.2.3.1 Thirty-One-Day Dose Projections In order to meet the requirements of Technical Specification 3.11.2.4, which pertains to operation uf the Ventilation Exhaust Treatment System and the Gaseous Waste Processing System, dose projections must be made at least once per 31 days, during periods in which discharge of gaseous effluents containing radioactive materials to unrestricted areas occurs or is expected, Projected 31-day air doses and doses to individuals due to gaseous effluents may be determined as follows: Air Doses: U U beta (prj) = beta (c) x 31 (32) t (O D V O gamma (prj) - camma(c) x 31 (33) Individual:
- Do (cl x 31 Do (prj) t (34) where: ,
D,.. 9 3 - the cumulative air dose, due to beta-emissions from noble gases, for the elapsed portion of the current quarter plus the release under consideration. 0,. 93
= the cumulative air dose, due to-gamma emissions from noble gases, for the elapsed portion of the current quarter plus the release under consideration.
VEGP ODCM, REV 4 7/30/87 2.2-53 e
q D c,: - the- cumulative organ dose to an individual due to 1-131, b/ I-133, tritium and particulates, for the elapsed portion of the current quarter plus the release under consideration. t - the number of days into the current quarter, 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 contribution should be included in the projected dose as follows: Air' Doses: D,,,,,,,,3 = " ' x 31 + D,, D 0 ,, ,,,,3 = "" x 31 + D,, ,
- ~
D, , ,,, 3 = D x 31 + 0,,
.t .
Where D,, is the expected dose due to the particular planned activity. 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-_ paragraph 2.2.2.1 using sample analyses results for the particular release; point and parametric values exp ced to exist for the release period.- For individual organ dose projections, due to I-131, I-133, tritium, and particulates, follow the methodology presented in -paragraph 2.2.2.2 using sample analyses results for the particular release point and
= parametric values expected to-exist for the release period. VEGP ODCM, REV 8 Draft 2.2-54
2.6 GASEOUS RADWASTE TREATMENT SYSTEMS figures 2.6-1, 2.6-2, 2.6-3, and 2.6-4 present schematics of the Gaseous Waste Processing System and Ventilation Exhaust Treatment Systems (Reference 5). 1 O O VEGP ODCM, REV 8 Drafi 2.6-1 . n .s,.,o.,.c.
/x Ra dioac t t mttor .
/ 4 " via Austliary Bo.lding venttistion bystra I
Catalytic
~
d' O ^d be con o ank i C n re r Analyzer i Package 1 1 I 6 . I 1 l% l* 4, 10 Watte Gas Decay Tank Header I I e . L.--- -- Q -- i
.fu - .:
i e ! o
*--74 Weste WS Wa s te Ga s Decay fant pecay rang (Shutdown)
(Seven per Unit) (y , 53 red) o
/ volume Contml ,/ From Unit 2 Weste /~'N _
N Tank Purge N G s Decay Tanks ( ,
%J
/ Recycle Evaporator N vent Concenser
/ waste EvaMrator N vent Condenser
/ Recycle Holdup g lank Eductor
__,/ Reactor Coolant N Drain Tant
*00tted line operational between 20 and 100 psf g l
i NOTE: This is typical of both units. However, Unit 2 GWPS releases via Unit 1 plant vent. f~n
% .)
Georga Pon,erkn EL CTHIC Of NERATING PLANT uu,1, Auo ou,1, FIGURE 2.6-1 433-9
'VEGP'00CM, REV 8 Draft 2.6-2
O Plant Vent Radioactivity Monitor 1nE12442A.B.C . i$ l l HEPA HEPA HEPA I I I CF CF CF 1 I I ] HEPA RWidty HEPA HEPA I Monitor
._ RE0039A l l HC HC Auxiliary l Building ME ME 9 O Radeoectivity Monitor Radioactivity 1R E2545A,B,C Fuel Handling E 14 Building (Shared)'
Froen Waste Gas Processing Reactor Containnwnt Area and SystsHn- Buildmg HEPA - High Efficiency Particulate Air Fitter CF - Activated Charcoal Fitter HC - Heating Coil ME - Moisture Eliminator
' Prior to treatment by the Fuel Handimg Building Ventilation Exhaust Treatment System, Exhaust f rom Unit 1 Spent Fuel Pool Area is monitored by ARE25328 and ARE25338 : exhaust from Unit 2 Spent Fuel Pool Area is monitored by ARE2532A and ARE2533A, v VENTILATION EXHAUST TREATMENT SYSTEtt aAT8N PLANT GeorgiaPower A [,'oans' ',"L"'u*u'r UNIT 1 (PLANT VENT)
FIGURE 2.6-2
~ VEGP ODEll, REV '8 Drcft' 2.6-3
I I q) Plant Vent Radioactivity Monitor 2HE12442A.D.C ' l l HEPA HEPA , CF CF I 1 t . I ~l HEPA HEPA I HC Auxiliary
,q Duildmg l
l V ~ ME l l l Radeosctivity Monitor 2RE2566A,8,C Reactor Containment Buildmg l HEPA - High-Efficiency Particulate Air Filter CF - Activated Charcoal Filter HC - Heatmg Coil ME - Moisture Eliminator (dD voortE VENTILATION EXHAUST TREATMENT SYSTEM
'COrgia POWCTkh Unit 2 (Plant Vent)
ELECTRIC GENERATING PLANT UNIT 1 AND UNIT 2 FIGURE 2.6-3 l C334 t VEGP ODCM, REV 8 D aft 2.6-4
Turbine Building Vent Radioactivity Monitor 1(2)RE 12839A, B, C I : HEPA HEPA l ,.- ! CF CF HEPA HEPA I I HC HC l i DE DE u u NO NC NO NC l S;aam Jet Steam Packing Air Elector E xhauster HEPA - High Efficiency Particulate Air Filter CF - Activated Charcoal Filter HC - Heating Coil DE - Demis'er NO - Normally Open NC - Normally Closed NOTE: This is typical of both units. VOGTLE VENTILATION EXHAUST TREATMENT SYSTtM (IUrbine Building) GeorgiaPowerkL ELECTRIC GENERATING PLANT unit uur unit 2 FIGURE 2.6-4 VEGP ODCM, REV 8 Draft
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Dry Active Waste Processing Duilding Vent a () Radioactivity Monitor ARE 13256 HEPA HEPA
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l 'v/ voortE VENTILATI0f EXilAUST TREATMENT SYSTEM Georgia Ibwer d ELECTHic GENERAllNG PLANT (DAW Process Building) UNU 1 AND UNIM FIGURE 2.6-5 C33 9 VEGP ODCM, REV 8 Draft 2.6 6
~3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM y
e -Radiological environmental sampling and monitoring locations are described in table 3.0-1 and shown on maps in figures 3.0-1, 3.0-2, 3.0-3, and 3.0-4 as required by subsections 3.1.1 and 3.1.2. J VEGP 00CH, HEV 8 Draft 3.0-1
i ..q . TABLE 3.0-1-(SHEET 1 Of 3) RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS LOCATION DESCRIPTIVE DIRECTION DISTANCE SAMPLE _ NUMBER LOCATION Imiles) TYPE (" 1 Hancock Landing Road N 1.1 D 2 River Bank NNE 0.8 0 3 Discharge Area NE 0.6 A 3 River Bank NE 0.7 0 4 River Bank ENE 0.8 0 5 River Bank E 1.0 D 6 Plant Wilson ESE 1.1 0 7 Simulator Building SE _ l.7 0,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 l.1 D 11 River Road SW l.2 D 12 River Road. WSW l.1 D,A 13 River Road W l.3 D,V 14 River Road WNW l.8 D 15 Hancock Landing Road NW 1.5 D,V
.16 -Hancock. Landing Road NNW l.4 D,A 17 Savannah River Plant /7 River Road N 5.4 D V -18 Savannah River Plant D Area NNE 5.0 D 19 Savannah River Plant Road A.13 NE 4.6 D 20 Savannah River Plant Road A.13.1 ENE 4.8 D 21- -Savannah River Plant Road A.17 E 5.3 D 22 River Bank Downstream of Buxton Landing' ESE 5.2 0 23 River Road SE 4.7 D 24 Chance Road SSE 4.9 D 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 D 29 Claxton-lively Road W 5.0 0 30 Nathaniel Howard Road. WNW 5.0 D 31- River Road at Allen's Church Fork NW 5.0 D 32 River Bank NNW 4.8 D 33 Nearby Residence SE- 3.3 D 34 Girard Elementary School SSE 6.3 0 35 Girard SSE 6.6 D,A p 36 Waynesboro WSW 14.9 D,A
() 37 Substation (Waynesboro) WSW 17.5 0,V VEGP ODCM, REV 8 Draft 3.0-2 e -
J , l fm TABLE 3.0-1 (SHEET 2 0F 3) N-] RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS LOCATION DESCRIPTIVE DIRECTION DISTANCE SAMPLL _t[VMBEfL LOCATION (miles) TYPE"' 43 Employees Recreation Area SW 2.2 D 80 Augusta Water Treatment Plant NNW 24.5 W(" 81 Savannah River (RM 153.1) N 2.2 F'" 82 Savannah River (RM 151.2) NNE 0.8 R 83 Savannah River (RM 150.4) ENE 0.8 R 84 Savannah River (RM 149.5) ESE 1.6 R S"' 85 Savannah River (RM 146.7) ESE 5.0 f"l 87 Beaufort-Jasper Water Treat-ment Plant; Beaufort, S.C. SE 76 W'" 88 Cherokee Hill Water Treatment Plant; Port Wentworth, Ga. SSE 72 W'" 98 W. C. Dixon Dairy SE 9.8 M 99 Boyceland Dairy W 24.5 M TABLE NOTATIONS: (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) The intake for the Augusta Wier Treatment Plant is located on the Augusta Canal. The entrece to this canal is at river mile (RM) 207 on the Savannah River. The canal e ffectively parallels the river. The pumping station is 3.5 miles down the canal and only a few tenths of a mile from the river (across lar.d). (3) About a 5-mile stretch of the ~iver is generally needed to obtain adequate fish samples. Samples are normally gathered between RM 153 and L 158 for upriver collections and between RMs i44 and 149.4 for downriver collections. O O VEGP ODCM, REV 8 Draft 3.0-3
TABLE 3.0-1 (SHEET 3 0F 3) O RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS Table Notations (Continued) (4) Sediment is collected at locations with existing or potential recreational value. Because high water shifting of the river bottom or other reasons could cause a suitable location for sediment collection to beceme unavailable or unsuitable, a stretch of the river between RM 148.5 and 150.5 which is downriver of the discharge is assigned for sediment collections. In practice, collections are normally made at RM 150.2. (5) The intake for the Beaufort-Jasper Water Treatment Plant is located at the end of-a canal which begins at RM 59.3 on the Savannah River. This intake is about 16 miles by line of sight down the canal from its beginning on the Savannah River. (6) The intake for the Cherokee Hill Water Treatment Plant is located on Abercorn Creek which is about one and a quarter creek miles from its mouth on the Savannah River at RM 29.
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'IGURE 3.0-3 43.5-9 VEGP ODCM, REV 8 Draft 3.0-7 ^ - --_--_-_-_ __
i I I J v 5 AucusT A WATER TREAtufNT PtANT
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l l J l Canal to Supply River Water to Desafort Beauf ort 4esper County Water Treettrwnt Plant N**y GEORGIA seEAu b g _ 5'
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W r 0 10 20 30 g4 CHEROKEE HILL p $ WATER TRE ATMENT b PLANT 4 4 (PORT WENTWORTH) D SAVANNA T O O ELE RIC GENERATING PLANT Georgia Power m unit $ 4No unit 2 FIGURE 3.0-4 433-9 VEGP ODCM, REV 8 Draft 3.0-8
~
3.1 L'imits of Operation ( D %) 3.1.1 Conduct of the Radiological Environmental Monitoring Program The Radiological Environmencal Monitoring Drogram shall be conducted as specified in table 3.1-1. This limit applies at all times for all modes of operation. 3.1.1.1 Reporting of Abnormal Conditions If the Radiological Environmental Monitoring Prngram is not being conducted as specified in table 3.1-1, prepare and submit to the NRC, in the Annual Radiological Environmental Surveillance Report required by Technical Specification 6.8.1.3, a description of the reasons for not conducting the ptogram as required and the plans for preventing a recurrence. O V If the confirmed
- level of radioactivity as the result of plant effluents in an environmental sampling medium at a specified location exceeds the reporting levels of table 3.1-2 when averaged over any calendar quarter, prepare and submit to the NRC within 30 Dys, pursuant to Technical Specification 6.8.2, a special report that ider tifies the cause(s) for exceeding the limit (s) and defines the corrective action (s) to be taken to reduce radioactive effluents so that the potential annual dose ** to a member of the public is less than the calendar year limits of subsections 1.5.2 , 2.5.2, or 2.5.3. When more than one of the rcdionuclides in table 3.1-2 are detected in the sampling medium, this report shall be submitted if:
*A confirmatory reanalysis of the original, a duplicate, or a new sample may be desirable or appropriate. The result of the confirmatory analysis shall be completed at the earliest time consistent with the analysis but in any case within 30 days.
O V
**The methodology- and parameters used to estimate the potential annual dose to a member of the public shall be indicated in this report.
VEGP ODCM, REV 8 Draft 3.1-1 { l
concentration (1) + _ concentration (2L + . . 2: 1.0 O reporting level (1) reporting level (2) When radionuclides other than those in table 3.1-2 are detected and are the result of plant effluents, this report shall be submitted if the potential , annual dose
- to a member of the public from all radionuclides is equal to or greater than the calendar-year limits of subsections 1.5.2, 2.5.2, or 2.5.3.
This report is not required if the measured level of radioactivity was not the result of plant effluents. However, in such an event, the condition shall be reported and described in the Annual Radiol ;ical Environmental Surveillance Reort required by lechnical Lpecification 6.8.1.3. If milk or vegetation samples are unavailable from one or more of the sample locations required by table 3,1-1, identify specific locations for obtaining replacement samples, and add them within 30 days to the Radiological Environmental Monitoring Program given in section 3.0. The specific locations from which samples were unavailable may then be deleted from the monitoring program. Pursuant to Technical Specification 6.13, submit in the next O V Semiannual Radioactive Effluent Release Report documentation for a change in the ODCM including a revised figure (s) and table for this ODCH reflecting the new location (s), with supporting information identifying the cause of the unavailability of samples and justifying the selection of the new location (s) for obtaining samples. These limits do not affect mode changes. 3.1.1.2 Collection and Analysis of Samples To assure that these limits are not exceeded, the radiological environmental monitoring samples shall be collected pursuant to table 3.1-1 from the - l specific locations given _in the table and figure (s) in section 3.0 and shall
-be analyzed pursuant to the requirements of table 3.1-1 and the detection capabilities required by table 3.1-3.
l l l
*The methodology and parameters used to estimate the potential annual dose to
- - a member of the public shall be indicated in this report.
VEGP ODCM, REV 8 Draft 3.1-2
4 3.1.1.0 Basis for the Radiological Environmental Monitoring Program
-The Radictogical Environment Monitoring Program required by this specification provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposure of members of the public resulting from the plant operation. This monitoring program implements section IV.B.2, Appendix I,10 CFR 50, and thereby supplemes _ ine Radiological Effluent Monitoring Program by measuring concentrations of radioactive materials and levels of radiation that may be compared with those expected on the basis of the' effluent measurements and the modeling of the environmental exposure pathways. Guidance for this monitoring program is provided by the
" Radiological. Assessment Branch Technical Position on Environmental Monitoring," Revision 1, November 1979. The initially specified monitoring program will be effective for at least the first 3 years of commercial operation. Following this period, program changes may be initiated based on operational experience, j The required detection capabilities for environmental sample analyses are tabulated in terms of the LLDs. The LLDs required by table 3.1-3 are considered optimum for routine environmental measurements in industrial laboratories, it should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular
-measurement. ,
Detailed-discussion of the LLD, and other detection limits, can be found in [ L. A. Currie, " Limits 'for Qualitative Detection and Quantitative Determination - Application to Radiochemistry," Anal. Chem. 40, 586-93, 1968, and J. K. Hartwell, " Detection Limits for Radionnalytical Counting
- Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215, June 1975.
- -VEGP ODCM, REV C ' Draft 3.1-3
n , - ) i I 3.1.2 Land use Census i i A land use census shall be conducted and shall identify within a distance of 5 miles the location in each of the 16 meteorological sectors of the nearest milk animal, the nearest residence, and the nearest garden of greater than 500 ft' producing broad leaf vegetation. Land within the Savannah River plant may be excluded fram this survey. This limit applies at all times for all modes of operation. 3.1.2.1 Identification of New Critical Locations If a land use census identifies a location (s) that yields a calculated dose or dose commitment greater than the values currently being calculated in subsection 2.5.3 pursuar.t to Technical Specification 6.8.1.4, identify the new location (s) in the next Semiannual Radioactive Ef fluent Release Report. If a land use census identifies a location (s) that yields a calculated dose or O dose commitment (via the same exposure pathway) 20 percent greater than at a location from which samples are currently being obtained in accordance with subsection 3.1.1, add the new location (s) within 30 days to the Radiological Environmental Monitr, ring Program given in s'ection 3.0, if samples are available. The sampling lucation(s) (orcluding the control-station location) having the lowest calculated dose or dose commitment (s), via the same exposure pathway, may then be deleted from this monitoring program. Pursuant to Technical Specification 6.13, submit in the next Semiannual Radioactive Effluent Release Report documentation for a change in this ODCM including a revised figure (s) and table (s) reflecting the new location (s) with information supporting the change in sampling locations. These limits do not affect modes changes. O VEGP ODCM, REV 8 Draft 3.1-4
. .. . .. ~ _. = - -. - - . ..-.. .
/q 3.1.2.2 Conduct of Census Qf To assure that these limits are't t exceeded, the land use census shall be conducted during the growi.99 season at least cnce per 12 months using that information that will provide good results, such as by a door-to-door survoy, by visua; survey from automobile or aircraft, by consulting local agriculture
-authorities, or by some combination of these methods as feasible. The results of the land use census shall be included in the Annual Radiological Envleonmental Surveillance Report pursuant to Technical Specification 6.8.1.3.
~
..l.2.3 Identification of Changes This specification is provided to ensure that changes in the ase of areas at and beyond the site boundary are identified and that modifications to the Radiological Environmental Monitoring Program are made if required by the results of this census. The best information from the door-to-door survey, fm- from aerial survey, or from consulting with local agricultural authorities k_ - shail be used. - This census satisfies the requirements of section IV.B.3, Appendix I, 10 CFR 50. Restricting the census to gardens of greater than 500 ft' provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this sim is the minimum .
required to produce the quantity (26 kg/yr) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were made: (1) 20 percent of the garden was used for growing broad leaf vegetation (i.e.,:simila? to lettuce and cabbage) and (2) a vegetation yield of 2 kg/m' was obtained. (O 1 VEGP ODCM, RE',' 8 Draft 3.1-5 l t
(3)
.: TABLE 3.1-1 (S'iEET 10F 6) 8*
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGPAM 8 9 EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLING AND TYPE AND FREQUENCY AND/OR SAMPLE SAMPLES AND SAMPLE LOCATIONS",' COLLECTION FREQUENCI 0F ANALYSIS A*
-1. Direct Radiation"' Thir~y-six routine men. 3 -Quarterly. Gamma dose qu rterly.
stations, either with two or j Ef- more dosimeters or with one T, instrument for measuring and recording dose rate continuously, 4 placed as follows: An inner ring of stations, one in each meteorological sector in the general area of the site boundary. An ou".er ring of stations, one in o, each meteorological sector in i
, the 6-mile range from the site. ! '
. E.
The balancr of the stations to be placed in special interest areas such as population centers, nearby residences, schools, and 1 ' in one or two areas to serve as control stations. 1 i
O O O TABLE 3.1-1 (SHEET 2 0F 6) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM E3 EXPOSURE PATHWAY NUMBER OF-REPRESENTATIVE SAMPLING AND TYPE AND FREQUtdCY Q AND/0R SAMPLE . SAMPLES AND SAMPLE LOCATIONS") COLLECTION FREQUENCY OF ANALYSIS E? 2. Airborne Radiciodine and Samples from five locations. Continuous sampler Radioiodine Cannister: Particulates' 5? operation with sample I-131 analysis weekly. i' Three samples from close to collection weekly, or the three site boundary more frequently if locations, in different required by dust Particulate Sampler: sectors. loading. Gross beta radioactivity analysis following One sample from the vicinity filter change,'" and of a comunity having the ga::r.a isetopic highest calculated annual analysis"' of composite o, average ground-level D/Q. (by location) quarterly. L. 1, One sample from a cnatrol location, as, for ex.mple, a population center 10 to 20 miles distant and in the least prevalent wind direction.
- 3. Waterborne
- a. Surface"' One sample upstream. Composite sample over Gamma isotopic analysis"'
l-conth period."' monthly; composite for One sample downstream. tritium analysis quarterly.
O O O TABLE 3.1-1 (SHEET 3 0F 6) f a
$ RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 2-EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLING AND TYPE AND FREQUENCY
- AND/OR SAMPLE SAMPLES AND SAMPLE LOCATIONS"' - COLLECTION FREQUENCY OF ANALYSIS xr 2 3. Waterborne (Continued) i' co o b. Drinking Two samples at each of one to Composite sample of I-131 analysis on each J three of the nearest water river water near sa=ple when the dose 2 -treatment plants that could be intake at each water calculated for the con-affected by its discharge. treatment plant over sumption of the water 2-week period"' when is greater than I crem Two samoles at a control I-131 analysis is per- per year W Composite
, locatio... -formed, monthly com- for gross beta and gar a posite otherwise; and isotopic analyses") grab sample of monthly. Composite for finished water at each tritium analysis w water treatrent plant cuarterly. L every 2 ween or 4, monthly, as appropriate. ! c. Sediment One sample from downstream area Semiannual!y. Gama isote;:ic from with existing or potential analysis"' semiannually. Shoreline recreational value. . 4. Ingestion ' a. Milk Samples from milking animals Semimonthly. Ganna isotopic in three locations within 3 analysis"'"' semiconthly. miles distance having the
- highest dose potential; if
- there are none, then one sample from milking animals
- in each of three areas betwee.-
' 3 and 5 miles distance where doses are calculated to be j greater than I mrem per yr.* i z l
, ,-~.
p TABLE 3.1-1 (SHEET 4 0F 6) c> RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM g EXPOSURE PATHWAY 2 NUMBER OF REPRESENTATIVE SAMPLING AND AND/OR SAMPLC._ TYPE AND FREQUENCY SAMPLES AND SAMPLE LOCATIONS"' COLLECTION FREQUENCY
- n OF ANALYSIS Q 4. Ingestica (Continued) co e, a. Milk One samp"le from milking
- animals
? at a control loca-tion about 10 miles distant or beyond and preferably in a wind direction of lower ~ prevalence. _
- b. Fish At 1 cast one sample of any Semiannually. Gar.a isotopic comercially and recreationally analysis'"
important species in vicinity on edible portions. y of plant discharge area. 5 At least one sample of any species in areas not influenced by plant d.ischarge. At least one sample of any During spring spawning Ga=:a isotopic anadromous species in season. analyses'" vicinity of plant discharge. on edible portion.
- c. Grass or One sample from two onsite Leafy Monthly during Gama isotopic."""
locations near the site growing season. Vegetation boundary in different sectors. One sample from a control Monthly during Gama isotopic.""" location about 15 miles growiag season. distant.
h
, O O O TABLE 3.1-1 (SHEET 5 0F 6) ho TABLE NOTATIONS .
8
- g (I) Specific parameters of distance and direction sector from a point midway between the center of the two reactors, and additirnal description where pertinent, shall be provided for each and g every sample location in table 3.1-1 in a table and figure (s) in this ODCM. Each sample c'
location will be designated by a number, name, or some other labd. ;bfer to NUREG-0133,
" Preparation of Radiologhal Effluent Technical Specification for Nucleas %wer Plants,"
j W October 1978 and to "Radiclogical Assessment Branch TechnMal Position," Revision I, November
%,+ 1979.
I Deviations are permitted from the required sampling schedule if specimens are unobtainable due to circumstances, such as hazardous conditions, seasonal unavailability, and malfunction of sampling equipment. If specimens are unobtainable due to sampling equipment calfunction, effort shall be made to complete corrective action prior to the end of the next sampling 4 period. All deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Surveillance Report pursuant to Technical Specification 6.8.1.3. w L It is recognized that, at times, it may not be possible or practicable to continue to obtain
.L samples of the media of choice at the most desired location or time. In these instances, suitable alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions, if available, will be made within 30 days n the Radiological j Environmental Monitori~g Prograr' given in-this 00CM. Pursuant to Technical Specification 6.13,
- submit in the next Semiannt.al Rauscactive Effluent Release Report documentation for a change in this ODCM, including a revised figure (s) and table reflecting the new location (s), if any, with i
supporting information identifying the cause of the unavailability of samples for the pathway i and justifying the selection of the new location (s) for obtaining samples or the unavailability of suitable new locations. l (2) One or more instruments, such as a pressurized ion chamber, for mcasuring and recording dose rate continuously, may be used in place of or in addition to integrating dosimeters. For the f purpose of this table, a thermoluminescent dosimeter (TLD) is considered to be one phosphor; two or more phosphors in a p'.cket are considered as two or more dosimeters. Film badges shall . not be used as dosimeters for measuring direct radiation. (3) Airborne particulate sample filters shall be analyzed for gross beta radioactivity 2.4 hours or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in air particulate samples is greater than 10 times the yearly mean of control samples, gamma '( isotopic analysis shall be performed on the individual samples.
O O O rm - TABLE 3.1-1 (SNEET 6 0F 6) E- TASLE NOTATIONS 8 9 (4) Gama isotopic analysis means the identification and quantification of gama-emitting radionuclides that may be attributable to the effluents from the facility. m (5) The upstream sample shall be taken at a distance beyond significant influence of the discharge. {- The downst-eam sample shall be taken in an area beyond but near the mixing zone.
? (6) Composite sample aliquots shall be collected at time intervals that are very short (e.g.,
. hourly) relative to the compositing period (e.g., monthly) in order to assure obtaining a representative sample.
(7) The dose shall be calculated for the maximum organ and age group, using the methodology and parameters in the ODCM. (8) A milking animal is a cow or goat prodiang milk for human consumption. w (9) If gama isotopic analysis is not sensitive enough to meet the lower limit of detection for I-
$. 131, a separate analysis for I-131 will be performed.
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O O O TABLE 3.1-3 (SHEET 10F 3) y k DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS""*# k LOWER LIMIT OF DETECTION (LLD)"' h GRASS OR LEAFY a, WATER AIRBORNE PARTICULATE FISH MILK VEGETATION SEDIMENT o ANALYSIS -(pCi/1) OR GASES (pC1/m') (pCi/kg, wet) (ptt/1) (pct /kg, wet) -(pCi/kg, dry) 2
?
Gross Beta 4 0.01 I H-3 2000"' Mn-54 15 130 Fe-59 30 260
. Co-58 15 130 0 Co-60 15 130 I
Zn-65 30 260 Zr-95 30 Nb-95 15 I-131 1 "' 0.07 1 60
. Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-140 60 60 La-140 15 15
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O O O TABLE 3.1-3 (SHEET 2 0F 3) g TABLE NOTATIONS e
^
(1) This list does not mean that only these nuclides are to be considered. Other peaks that are g identifiable as plant effluents, together with those of the above nuclides, shall also be
< analyzed and reported in the Annual Radiological Environmental Surveillance Report pursuant to m Technical Specification 6.8.1.3.
?
~ ,
? (2) Required detection capabilities for thermoluminescent dosimeters used for environmental measurements shall be in accordance with the recommendations of Regulatory Guice 4.13.
(3) The LLD is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95-percent probability, with ,nly 5-percent probability of falsely
- concluding that a blank observation represents a "real" signal. '
y For a particular measurement system, which may include radiochemical separation: T LLD = ** E
- V = 2.22 *Y
- exp( ,Bt) where: .
LLD = the a priori lower limit of detection (picoCuries per unit mass or volume) s, - the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute) ' E - the counting efficiency (counts per disintegration) , V - the sample size (units of mass or voluce) [ t i l
O O O o TABLE 3.1-3 (SHEET 3 0F 3) i - 72 c) TABLE NOTATIDNS (Continued) 8 at
- o
! [2 2.2E = the number of disintegrations per minute per picocurie ). os ! c3 ;Y - the fractional radiochemical yield, when applicable 2
;2 A -
the radioactive decay constant for the practicular radionuclide (sec-*) i At - the' elapsed time between sample collection, or end of the sample collection period, and time of counting (sec) ~
- Typical values of E, V, Y, and AT should be used in the calculation.
l It :should be recognized that the LLD is defincd as an a priori (before the fact) limit j' representing the capability of a measurement system and not as an a posteriori (after the i un
' fact) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background i, 2- fluctuations, unavoidable small sa=ple sizes, the presence of interfering nuclides, or other ur. controllable circumstances may render these LLDs unachievable.
i In such cases, the [ contributing factors shall be identified and described in the Annual Radiological { Environmental Surveillance Report pursuant to Technical Specification 6.8.1.3. 1 (4). If no drinking water pathway exists, a value of 3000 pCi/l may be used. l 4. 1 1 (5) If no drinking water pathway ex'sts, a value of 15 pCi/l may be used. i s i n. 1 3 l-
l l 3.2 INTERLABORATORY COMPARISON PROGRAM 3.2.1 Requirements Analysis shall be performed on all radioactive materials, supplied as part of an interlaboratory comparison program that has been approved by the NRC, that correspond to samples and analysis required by table 3.1-1. This limit applies at all times for all modes of operation. 3.2.2 Deviations if analysas are not being performed as required above, report the corrective actions taken to prevent a recurrence to the NRC in the Annual Radiological Environmental Surveillance Report pursuant to Technical Specification 6.8.1.3. O 3.2.3 Summary of Results To assure that these limits are not exceeded, a summary of the results obtained as part of the above required interlaboratory comparison program shall be included in the Annual Radiological Environmental Surveillance Report pursuant to Technical Specification 6.8.1.3. 3.2.4 Basis The requirement for participation in an approved interlaboratory comparison , program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioact.tve materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are valid for the purposes of section IV.B.2, Appendix 1, 10 CFR 50. VEGP ODCM, REV 8 Draft 3.2-1 ,
4.0 10TAL DOSE DETERMINATIONS O Subsection 2.5.5 addresses the requirements of 40 CFR 190 and 10 CFR 20.105(c), which pertain to limitation of annual doses to . member of the public from nuclear fuel cycle facilities. No other nuclear fuel cycle facility is located within five miles of Plant Vogtle. Therefore, it is only ; necessary to include doses from the two Plant Vogtle units in the total dose ' determinations. For the purpose of implementing subsection 2.5.5, total dose determinations will be made by calculating doses due to liquid effluents in accordance with subsection 1.5.2 by calculating doses due to gaseous effluents in accordance-with subsection 2.5.3 and by combining direct radiation doses based on direct radiation measurements, or calculations, with these effluent doses to determine total dose to a real- individual. Methodology for calculating individual doses due to liquid effluents was presented in section 1.2. , Methodology for calculating individual doses due to gaseous effluents was presented in paragraph 2.2.2.2. ; i O l .VEGP ODCM, REV 8 Draft 4.0-1 1
5.0 POTENTIAL DOSES 10 MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE Slif 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 by calculating 1 total-body doses due to noble gas releases and organ doses due to raololodine, tritium, and particulates in gaseous releases. The locations of inttrest within the site boundary at Plant Vogtle are the Visitors Center and Plant Wilson. (Plant Wilson is cwned and operated by Georgia Power Company, but individuals working at Plant Wilson are not directly associated with Plant Vogtle. Therefore, those individuals are considered in this dose i determination as a precautionary measure.) ' Annual average atmospheric dispersion and deposition values for these two locations, expected occupancy factors. (for an individual during the year), and applicable age groups are presented in table 5.0-1. Total-body doses due to noble gases are determined using the following equation: D., - 3.17E-8 (X/Q). I K,Q,, + (X/Q),E K,0,. (OF) i i where-(X/Q). and -(X/Q),, are ground-level and mixed-mode dispersion terms for the location of interest; K, is the total-body dose factor from table , 2.1-1; and 0F is the occupancy factor. Other terms are described in subsection
- 2,2. 2. - '
Organ doses due to radioiodine, tritium, and particulates in gaseous releases are determined in accordance with the methodology presented in paragraph 2.2.2.2 (equatica (11)). Only the inhalation pathway (equation (22)) and the ground-plane pathway (equation (23)) are applicable for locations ,. Inside the site' boundary. After doses are calculated for the locations of interest inside the site boundary, using parameters from VEGP'0DCM, REV 8 Draft 5.0-1 L
l l l table 5;0-1, the results are multiplied by the appropriate occupancy factors to O' determine doses to individuals at the locations'of interest inside the site bundary. l 4 k VEGP ODCM, REV 6 9/30/88 5.0-2 r e e *vr- w y., gms +:. sw* p p - s ~-*--- -me- g y --- w,-T-.Tv- -- gw=y
TABLE 5.0-1 (SHEET 1 0F 2) LOCATION-SPECIFIC PARAMETERS FOR LOCATIONS INSIDE THE SITE BOUNDARY location: Visitors Center; SE at 447 meters Age group: Child Estimated occupancy factor: 4.6E-4 (4 hours) Ground-level dispersion and deposition parameters: (X/Q) = 5.93E-6 s/m' > Depleted: (X/Q) = 5.58E-6 s/m' (D/Q) - 2.28E-81/m' Mixed-mode dispersion and deposition parameters: ('X/Q) = 7.12E-7 s/m' Depleted: (X/Q) - 6.74E-7 s/m' (D/Q) = 5.77E-9 1/m' Location: Plant Wilson; ESE at 1420 meters Age group: Adult Estimated occapancy factor: 2,28E-1 (2000 hours)* Ground-level' dispersion and deposition parameters: ; L (X/Q) a 9.45E-7 s/m' Depleted: (X/Q) - 8.34E-7 s/m' (D/Q) - 4.20E-9 1/m' LO 1 VEGP 0DCM, REV 6 9/30/88 5.0-3 j 1 _ . . . ._...a_._.. - - . . - . . _ ,...__:...-.,
l TABLE 5.0-1 (SHEET 2 Of 2) O l Mixed-mode dispersion and deposition parameters: (5/6) = 1.76E-7 s/m' Depleted: (ITd) = 1.59E-7 s/m' (0/Q) = 2.07E-9 1/m' t
*This value is based on a 40-hour _ work week, assuming an individual is assigned to the facility for the entire year. '
L
.VEGP ODCH, REY 8 . Draft
. 5.0-4
_. ___ ._ ._ _____ _._._1 . . _ - _ _ _ . . _ . - . . _ . . .~
6.0 REPORTS 6.1 ANNVAL PAD 10 LOGICAL [NVIRONMENTAL SURVEILLANCE REPORT *** 6.1.1 Due Date Routine Annual Radiological Environnental Surveillance Reports covering activities of the radiological environmental monitoring program during the previous calendar year shall be submitted prior to May 1 of each year. The initial report shall be submitted prior to May 1 of the year following initial
~
criticality and shall include copies of reports of the preoperational radiological environmental monitoring program of the plant for at least two years prior to it'.tlal criticality. 6.1.2 Evaluation Content Requirement The Annual Radiological Environmental Surveillance Report shall include summaries, interpratations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including, as appropriate, a comparison with preoperational studies, with operational controls, and with previous environmental surveillance reports, and an assessment of any observed impacts of plant operations on the environment. The report shall also includ9 the results of the land use census required by section 3.1.2. l 6.1.3 Data Content Requirement The Annual Radiological Environmental Surveillance Report shall include the results of analysis of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the O U ***A single submittal may be made for Units 1 and 2. VEGP ODCM, REV 8 Draft 6.1-1
i locations specified in the table and figures in section 3.r. as well as - summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1 November 1979. The radiological level of radionuclides, which are . naturally occurring, not included in the plant effluents, need not be reported, in the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as practicable in a supplementary report. 6.1.4 Program Content Requirement The report shall also include the following: a summary description of the radiological environmental monitoring program, at least two legible maos covering all sampling locations keyed to a table giving distances and directions from a point midway between the two reactors, the results of licensee participation in the interlaboratory comparisen program and the corrective action taken if the specified program is not being performed, reasons for not conducting the ra.iiological environmental monitoring program and discussion of all deviations from the sampling schedule, discussion of environmental sample measurements that exceed the reporting levels but are not . the result of plant effluents, and dircussion of all analyses in which the LLO required was not achieved. O VEGP 0DCM, REV 8 Draft- 6.1-2 m _ - _ _
6.2 SEM1 ANNLAL RAD 10ACTlyE EFFLUENT RELEASE ELPORT* Routine Semiannual Radioactive Effluent Release Reports covering the operation of the unit during the previous 6 months of operation shall be submitted within 60 days after January 1 and July 1 of each year. 6.2.1 Gaseous and liquid Effluent Summaries The Semiannual Radioactive Effluent Release Reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from both units as outlined in Regulatory Guide 1.21, " Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power plants," Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix P thereof, for solid wastes, the format for table 3 in Appendix B shall be supplemented with three additional categories: class of solid wastes (as defined by 10 CFR 61), type O of container (e.g., LSA, type A, type B, large quantity), and solidification agent or absorbent (e.g., cement, urea formaldehyde). 6.2.2 Meterological Data Summary - The Semiannual Radioactive Effluent Release Report to be submitted within 60 days after January 1 of each year shall include an annual summary of hc trly metcorological data collected ovar the previous year. This annual summary may be either in the form of an hour-by-hour listing on magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured), or in the form of joint frequency distributi(ns of windspeed, wind direction,
*A single submittal may be made for Units 1 and 2. The submittal should combine those sections that are common to both units at the plant; however, O material from each unit.the submittal shall specify the releases of gaseous and liquid radioactive VEGP ODCM, REV 8 Draft 6.2-1
I and atmospheric stability.* This same report shall include an assessment of released from each unit during the previous calendar year. This same report the radiation doses due to the radioactive liquid and gaseous effluents shall also include an assessment of the radiation doses from radioactive liquid and gaseous efflu2nts to members of the public due to their activities inside the site boundary during the report period. All assumptions used in making these assessments (i.e., specific activity, exposure time, and location) shall be included in these reports. Historical annual average meteorological conditions or the metearological conditions concurrent with the time of release of radioactive materials in gaseous ef fluents, as determined by _ sampling frequency and measurement, shall be used for determining the gaseous pathway doses. The assessment of radiation deses sc all be performed in accordance with the methodology and parameters in this manual. 6.2.3 Radiation Doses to the Public The Semiannual Radioactive Effluent Release Report to be submitted within 60 O days after January 1 of each year shall also include an assessment of radiation doses to the likely most exposed member of the public from reactor releases and other uranium fuel cycle sources within 8 km, including doses from )rimary effluent pathways and direct radiation, f or the previous calendar year to show conformance with 40 CFR 190, " Environmental Radiation Protection " Standards for Nuclear Power Operation." Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Revision 1, October 1977.
*In lieu of submission with the Semiannual Radioactive Effluent Release Report, the licensee has the option of retaining this summary of required meteorological data on site in a file that shall be provided to the NRC upon O request.
VEGP CDCM, REV 8 Draft 6.2-2
6 .2.4 Unplanned Releases O . The Semiannual Radioactive Effluent Release Reports shall include a list and , description of unplanned releases from the site to unrestricted areas of ; radioactive materials in gaseous and liquid effluents mado during thc ' reporting period. . l 1 6.2.5 ' Changes to the ODCM 4 The Semiannual Radioactive Effluent Release Reports shall include any changes made during the reporting period to the Offsite Dose Calculation Manual (ODCM), pursuant to Technical Specification 6.13, as well as any major change to liquid, gaseous, or solid radwaste treatment systems pursuant _to subsection 6.2.7. It shall also include a listing of new locations for dose calculations ! and/or environmental monitoring identified by the land use census pursuant to I subsection 3.1.2. O 6.2.6 Inoperable t.iquid or Gaseous Effluent Monitoring Instrumentation i The-Semiannual Radioactive Effluent Release Reports shall also include the
- _ following: an _ explanation _ as to why the inoperability of liquid or gaseous I effluent monitoring instrumentation was not corrected within the time specified in subsection 1.5.4 or 2.5.6, respectively, and description of the ,
events leading to liquid heldup tanks or gas storage tanks exceeding the limits of-Technical Specification 3 -11.1.4 or 3.11.2.6, respectively. l l' O VEGP ODCM, REV.8 Oraft 6.2-3 L
6.2.7 Maior Chaoses to Liouid. Gastann_tqd Solid Radwaste Treatment Systems
- Licensee-initiated major changes to the radwaste treatment systems (liquid, gaseous, and solid)
- a. Shall be reported to the NRC in the Semiannual Radioactive Effluent Release Report for the period in which the evaluation was reviewed by the PRB, The discussion of each change shall contain the following:
- 1) A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR 50.59.
- 2) Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information.
- 3) A detailed description of the equipment, components, and processes involved and the interfaces with other plant systems.
- 4) An evaluation of the change, which shows the predicted releases of radioactive materials in liquid and gaseous effluents and/or quantity of solid waste that differ from those previously predicted in the license application and amendments thereto.
- 5) An evaluation of the change, which shows the expected maximum exposures to a member of the public in the unrestricted area and to the general population that differ from those previously estimated in the license application and amendments thereto.
1' L
- Licensees may choose to submit the information called for in
.this specification as part of the annual FSAR update.
VEGP ODCM, REV 8 Draft 6.2-4
- 6) A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents and in solid waste, to the actual releases for the period prier to when the change is to be made.
- 7) An estimate of the exposure to plant operating personnel as a result of the change.
- 8) Documentation of the fact that the change was reviewed and found acceptable by the PRB.
- b. Shall become effective upon approval by the General Manager - Nuclear Plant.
O l O VEGP ODCM, REV 8 Draft 6.2-5 n s .s, ,o.stum
r^ fif1EfE15 V)
- 1. J. S. Boegli, R. R. Bellamy, W. L. Britz, and R. L. Waterfield, "Preperation of Radiological Effluent Technical Specifications for Nuclear Power P! ants." NUREG- Ci u , October 1978.
- 2. " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR 50, Appendix 1," U. S. NRC Reaulatory Guide 1.102, March 1976.
- 3. " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Pur;,ose of Evaluating Compliance with 10 CFR 50, Appendix 1," U. S. NRC Reaulatory_Qttide 1.109. Revision 1, October 1977.
- 4. Voatie Electric Generatina Plant Units 1 and 2 Environ,mgntal Report -
Operatina license St,3ag, Georgia Power Company.
- 5. Voatle Electric Generatina Plant Units 1 and 2 Final Safety Analysi_s Report, Georgia Power Company.
- 6. " Methods for Estimating Atmospheric Transport and Dispersion of Geseous Effluents in Routine Releases from Light-Water-cooled Reactors," LL._flRC Reaulatory Guide 1.111, March 1976.
- 7. " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," U.S. NRC (V) fleaulatory Guide 1.111 Revision 1, July 1977.
- 8. " Estimating Acquatic Disperrion of Ef fluents from Accidental and Routine Reactor Reicases for the Purpose of Implementing Appendix 1," U. S. NRC Reaulatory Guide 1.113, Revision 1, April 1977.
- 9. Voatle Nuclear Plant Units 1 and 2 Wute Water Effluent Discharoe Structure Plume Analysis, Georgia Power Company, April 1981,
- 10. " Direct Comunications with Water Resources Division," U. S. Geolooical Survey, U. S. Department of Interior, Februarj 1985,
- 11. W. R. Stokes, Ill, T. W. Hale, J. L. Pearman, a~d G. R. Buell, " Water Resources Data, Georgia, Water Year 1983," U. S. Geoloaical Survey, Water - Data Report GA-83-1, June 1984.
- 12. Vogtle Electric Generatina Plant land Use Survey - 1988, Georgia Power Company, April 1988.
- 13. Letter to Southern Comnany Services from Pkkard lowe. and Garrick. Inc.,
Washington, D.C., April 27, 1988.
- 14. Kahn, Bernd, et. al, Bioaccumulation of P-32 in Bluegill and h !'; th,"
ti!! REG /CR-3981, February 1985. V VEGP ODCM, REV 8 Draft R-1
- 15. Letter to Bill 0111nger, Georgia Power Company, from T. L. Broadwell, Georgia Pover Company, Atlanta, Georgia, June 22, 1988.
- 16. Letter to Bill 0111nger, Georgia Power Company, from R. J. Just, Georgia Power Company, Atlanta, Georgia, July 8, 1988.
- 17. Memo from S. E. Ewald, Georgia Power Company, to C. C. Eckert, Georgia Power Company, May 9,198'3.
- 18. Memo from A. C. Stalker, Georgia Power Ccmpany, to D. F. Hallman, Georgia Power Company, February 5, 1987.
O O VEGP ODCM, REV 8 Draft R-2 x , s.,s...o.s cm
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