ML17346A670

Offsite Dose Calculation Manual for Gaseous & Liquid Effluents.

ML17346A670
Person / Time
Site:	Turkey Point
Issue date:	12/31/1984
From:	FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML17346A669	List: ML17346A668 ML17346A670
References
PROC-841231, NUDOCS 8412260242
Download: ML17346A670 (200)

Text

OFFSITE DOSE CALCULATIONMANUAL FOR GASEOUS AND LIQUID EFFLUENTS FROM THE TURKEY POINT PLANT UNITS 3 AND 0 Florida Power and Light Company December 1930 84i220 84i2260242 05000250 PDR ADOCK PDR P

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OFFSITE DOSE CALCULATIONMANUAL FOR GASEOUS AND LIQUID EFFLUENT 1.0 Introduction 2.0 Liquid Effluent '2 2.1 Radioactivity Concentration In Liquid Waste 2 2.2 Radioactivity Concentration in Water at the Restricted 2 Area Boundary 2.2.1 Aqueous Concentration 2 2.2.2 Batch Release 3 2.2.3 Continuous Release 2.3 Cumulative Dose 5 2.0 Method of Establishing Alarm and Trip Setpoints 6 2.0.1 Setpoint for a Batch Release 7 2.0.2 Setpoint for a Continuous Release 7 2.5 Projected Dose 8 Figure 2.1 Liquid Effluent Systems 9 3.0 Gaseous Effluent 10 3.1 Introduction 10 3.2 Radioactivity in Gaseous Effluent 10 3.3 Dose Rate Due to Gaseous Effluent 11 3.3.1 Total Body Dose Rate 12 3.3.2 Skin Dose Rate 12 3.3.3 H-3, I-131, I-133, and Particulate Dose Rate 13 3.0 Dose - Noble Gases 10 3.0.1 Noble Gas Gamma Radiation Dose 15 3.0.2 Noble Gas Beta Radiation Dose 16 3.5 Dose Due to Iodine, Tritium, and Particulates in Gaseous Effluents 17 3.5.1 Determining the Quantity of Iodine, Tritium, and Particulates 17 3.5.2 Calculating the Dose Due to Iodine, Tritium and Particulates 18 3.6 Effluent Noble Gas Monitor Alarm Setpoint 21 3.6.1 Setpoint Based on Dose Rate 22 3.6.2 Setpoint Based on Concentration 23 3.7 Projected Dose for Gaseous Effluents 20 Figure 3.1 Gaseous Effluent Systems 25 Figure 3.2 Locations at Which Doses Due to Airborne Effluents from the 26 Turkey Point Plant are Calculated REV.1: 12/19/84 C6:1

OFFSITE DOSE CALCULATIONMANUAL t

FOR GASEOUS AND LIQUID EFFLUENT 0.0 Dose Commitment from Releases over Extended Time 27 0.1 Releases during 12 Months 27 0.2 Environmental Measurements 28 0.3 Dose to a Person from Noble Gases 28 0.3.1 Gamma Dose to Total Body 28 0.3.2 Dose to Skin 29 Appendix A Pathway-Dose Transfer Factors A-1 B Deleted C Deleted D Technical Bases for Aeff D-l E Radiological Environmental Surveillances E-1 Turkey Point Plant Key to Sample Locations Table 3-1 Atmospheric Gaseous Release Points at the Turkey Point Units 3 and 0 3-2 Distribution of Radioactive Noble Gases in Gaseous Effluent from Turkey Point Units 3 and 0 3-3 Transfer Factors for Maximum Offsite Air Dose Transfer Factors for Maximum Dose to a Person Offsite Due to Radioactive Noble Gases 3-5 . Dose Conversion Factors for Deriving Radioactive Noble Gas Effluent Monitor S et points 4 Reference Meteorology: Annual Average Atmospheric Dispersion Factors 3-7 Reference Meteorology: Deposition Depleted Annual Average Atmospheric Dispersion Factors Reference Meteorology: Annual Averaged Relative Deposition Rate REV.1: 12/19/84 C6:I

OFFSITE DOSE CALCULATIONMANUAL FOR GASEOUS AND LIQUID EFFLUENT 1.0

~ Introduction

~

This Manual describes acceptable methods of calculating radioactivity concentrations in the environment and the potential resultant doses+ offsite~+ that are associated with liquid and gaseous ef fluents from the Turkey Point Nuclear Plant. The radioactivity concentrations and dose estimates are used to demonstrate compliance with Technical Specifications required by 10 CFR 50.36. The methodology stated in this Manual is acceptable for use in demonstrating operational compliance with 10 CFR 20.106, 10 CFR 50 Appendix I, and 00 CFR 190. Only the dose attributable to the Turkey Point Units 3 and 0 is considered in demonstrating compliance with 00 CFR 190 since no other nuclear facility exists within 50 miles of the Plant.

Monthly calculations are made to guide the management of station effluents and to verify that potential radioactivity concentrations and doses offsite satisfy the Technical Specifications. The receptor is described such that the exposure of any resident near the plant is unlikely to be underestimated. Even more conservative conditions (e.g. location and/or exposure pathways expected to yield higher computed doses) than appropriate for the maximally exposed person may be assumed when calculating the concentration or dose.

Monthly calculations made to assure that air dose and dose commitment specifications are not exceeded are based on atmospheric dispersion and deposition of gaseous effluents derived from reference meteorological conditions.+++ Calculations made to assess the radioactive noble gas dose to air are based on the location offsite that could be occupied by a person where the maximum air dose is expected.

Calculations of dose committed from radioactive releases over extended time (3 and 12 months) are also made for the purpose of verifying compliance with regulatory limits on offsite dose. For these calculations the receptor is selected on the basis of the combination of applicable exposure pathways identified in the land use census and the maximum ground level X/Q at a residence, or on the basis of more conservative conditions such that the dose to any resident near the Plant is unlikely to be underestimated.

+ Dose is commonly used to mean personal dose equivalent commitment.

~+ Offsite means outside the exclusion area.

++~ Reference meteorological conditions are annual averaged conditions during years 1976 and 1977.

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OFFSITE DOSE CALCULATIONMANUAL FOR, GASEOUS AND LIQUID EFFLUENT 2.1 Radioactivi Concentration In Li id Waste The concentration of radionuclides in liquid waste is determined by sampling and analysis in accordance with Table 3.9-1 of the Technical Specifications. EVhen a radionuclide concentration is below the lower limit of detection (LLD) for the analysis, it is not reported as being present in the sample.

2.2 Radioactivi Concentration in Water at the Restricted Area Bounda Technical Specification 3.9.1.a requires that the concentration of radioactive material, other than noble gases, in liquid effluent released into an unrestricted area not exceed the concentration specified in 10CFR Part 20, Appendix 8, Table 2, Column 2. A maximum concentration,.2 x 10<pCi/ml, of noble gas in aqueous releases into an unrestricted area applies separately since the potential exposure route, immersion in water, differs from that upon which Part 20, Appendix 8 is based.

Radioactive material in liquid effluent is diluted by condenser cooling water from fossil units 1 and 2 and from nuclear units 3 and 0 in the condenser cooling water mixing basin. Water in the basin flows into a closed cooling canal system onsite. Liquid effluent does not actually leave the site in a surface discharge.

For the purpose of compliance with Technical Specification 3.9.1.a, the total condenser cooling water flow from operating condenser cooling water pumps at the four units is assumed for dilution and the restricted area boundary is assumed to be at the end of the condenser cooling water mixing ba'sin where water enters the cooling canal system.

Some liquid effluents from both Units 3 and 0, discharge through a common liquid radwaste release point. To assure that the effluents are within allowable limits per reactor, the measured releases from the common release point are apportioned to each unit on a ratio equal to the ratio of specific isotopic concentrations in the primary coolant in the two reactors.

Sections 2.2.2 and 2.2.3 describe methods used to assess compliance with Technical Specification 3.9.1.a. Effluent monitor alarm/trip setpoints are computed on the same basis, as is described in section 2.0. As long as an alarm/trip setpoint is not exceeded, aqueous effluents are deemed to comply with Technical Specification 3.9.1.a.

2.2.1 ~

A ueous Concentration The diluted concentration of radionuclide i in the condenser cooling water mixing basin outflow is estimated with the equation C6:1

0 OFFSITE DOSE CALCULATIONMANUAL FOR GASEOUS AND LIQUID EFFLUENT where:

Czi = concentration of radionuclide i in the water in the condenser cooling water mixing basin, outflow (pCi/ml)

C; = concentration of radionuclide i in liquid radwaste released (pCi/ml)

Fl/F2 = dilution Fl = flow in radioactive liquid discharge line (gal/min)>>

F2 = total condenser cooling water flow (gal/min).+ Value not greater than the rated total condenser cooling water flow from operating condenser cooling water pumps at the four units.

2.2.2 Batch Release A sample of each batch of liquid radwaste is analyzed before release for I-131 and other principal gamma emitters, or for total gross 9-y activity concentration. iVith the activity concentration in a batch sample b based on the total isotopic activity or gross B-y activity, the fraction of the unrestricted area MPC due to a batch release is estimated by (2)

FMPCb =

3x108 where:

FMPCb = fraction of the unrestricted area MPC present in the condenser cooling water mixing basin outflow due to a batch release Cb = Czi (pCi/mi) 3 x 10+ = unrestricted area MPC for unidentified radionuclides in water (pCi/ml)

Alternately, the fraction of the unrestricted area MPC can be derived using the ratio of the individual isotopic concentrations and their related MPCs. FMPCb is estimated with the equation

<zx Eb (3)

NF0x l.

+ Fl and F2 may have any suitable but identical units of flow (volume/time).

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OFFSITE DOSE CALCULATIONMANUAL FOR GASEOUS AND LIQUID EFFLUENT where:

MPCI = activity concentration limit in water of radionuclide i according to 10 CFR 20, Appendix 8, Table 2, Column 2 (pCi/mo Quarterly average of the fraction of MPC in the batch tank due to I-131 and rinci al amma emitters Quarterly average of the fraction of MPC in the batch tank due to all radionuclides measured Eb is an adjustment to account for radionuclides not measured prior to release but measured in the monthly and quarterly sample per Technical Specification Table 3.9-1. The value of Eb has been determined based on past operating data and is 0.8 2.2.3 Continuous Release Continuous aqueous discharges are sampled and analyzed according to the schedule in Technical Specifications Table 3.9-1. The fraction of the unrestricted area VIPC present in a continuously discharged radioactive stream, FMPCc, is derived either from isotopic analyses or from gross B-y analysis. 'Vith the activity concentration in a continuous radioactive release stream based on the total isotopic or gross B-y activity alone, the fraction of the unrestricted area MPC due to a continuous release is estimated with Cc FMPCc =

3 x ]0 where:

FMPCc = fraction of the unrestricted area MPC present in the condenser cooling water mixing basin outflow due to a continuous release Cc = Czi (pCi/mo Alternately, the fraction of the unrestricted area MPC can be derived using the ratio of the individual isotopic concentrations and their related MPCs. FMPCc is estimated with the equation

<zx. (5)

FMPCc =  :

Ec MPCi I.

OFFSITE DOSE CALCULATIONMANUAL FOR GASEOUS AND LIQUID EFFLUENT where:

Quarterly average fraction of MPC due to I-131 and principal gamma emitters measured in weekly sam les of continuous releases durin the uarter Quarterly average f raction of MPC due to all radionuclides measured in samples of continuous releases Ec is an adjustment to account for radionuclides not measured in weekly samples of continuous releases but measured in the monthly and quarterly composite samples per Technical Specifications Table 3.9-1.

The value of Ec has been determined based on past operating data and is Ec = 0.9 2.3 Cumulative Dose Technical Specification 3.9.1.b requires that the dose or dose commitment per reactor to a member of the public due to radioactive material released in liquid effluent to an unrestricted area shall be limited, during any calendar quarter, to

<1.5 mrem to the total body and to <5 mrem to any organ, and, during any calendar year, to <3 mrem to the total body and <10 mrem to any organ.

Technical Specification 3.9.l.b.l requires the dose or dose commitment to a member of the public due to radioactive material released in liquid effluent to be calculated on a cumulative basis at least once per month. The condenser cooling water basin and closed canal system which receives aqueous effluent is entirely on FP and L property, without surface discharge offsite, and FP and L does not permit members of the public to use the water. As a result, potential exposure of a member of the public to radioactive material originating in aqueous effluent is limited to irradiation of campers by canal shoreline deposits.

Technical Specification 3.9.l.b.l is satisfied by calculating the cumulative total body dose to a person who may be irradiated by radionuclides deposited on the cooling canal shoreline from radioactive liquid effluent. Compliance with the organ dose limit is assured as long as the total body dose is below its limit.

The model that is used to evaluate doses due to radioactivity in liquid effluents is 0 P3 Q ++shore 1 inc Cik ' 1k (6) l.

v I,'-

~

where:

D = total body dose due to irradiation by radionuclides on the shoreline which originated in a liquid effluent release (mrem) 0.23 = units conversion constant =

1 Ci x 60 minx 3785 ml 106 pCi hr gal C6:1

1 OFFSITE DOSE CALCULATIONMANUAL FOR GASEOUS AND LIQUID EFFLUENT AI = transfer factor relating a unit aqueous concentration of radionuclide i (liCi) to dose commitment rate to the total body of an exposed person tabulated in Appendix A (m rem/Ci min/gal)

~

I Cik = the concentration of radionuclide i in the undiluted liquid waste to be discharged that is represented by sample k (iiCi/ml)

Flk = liquid waste discharge flow during release represented by sample k (gal/min)

V = cooling canal effective volume, approximately 3.75 x 109 gallons p= effective decay constant (minute 1) for nuclide i = (Q + F3/V) where: g = the radioactive decay constant F3 = canal-ground water interchange flow, approximately 2.25 x 105 gal/min

= period of time (hours) during which liquid waste represented by sample k is discharged Radionuclide concentrations (Cik) in effluent are measured by the sampling and analysis program specified in Technical Specification Table 3.9-1. Typically, more than 90 percent of the potential irradiation from radionuclides deposited along the shoreline is due to Mn-50, Co-58, Co-60, Cs-130, and Cs-137. Of these radionuclides, Co-60 has the maximum dose transfer factor, Ai. Thus, for the purpose of assessing compliance with Technical Specification 3.9.1.b.l, the radioactive effluent source term may be either:

a) principal gamma emitters measured by the effluent sampling and analysis program, or I b) Mn-50, Co-58, Co-60, Cs-130, and Cs-137 measured by the effluent sampling and analysis program and other identified gamma emitters assumed to be Co-60, or c) all gamma emitters measured by the effluent sampling and analysis program assumed to be Co-60.

2.0 Method of Establishin Alarm and Tri Set pints Technical Specification 3.9.1.c requires the radioactive liquid effluent monitoring instrumentation channel to be operable with its alarm/trip setpoints

'set to ensure the limit of Specification 3.9.1.a is not exceeded.

The alarm/trip setpoint for each liquid effluent radiation monitor is derived from the concentration limit provided in 10 CFR Part 20, Appendix B, Table 2, Column 2 applied in the condenser cooling water mixing basin outflow.

Radiation monitoring and isolation points are located in the steam generator blowdown lines, R-3-19, R-0-19, and the liquid waste disposal system line, R-18, through which radioactive waste effluent is eventually discharged into the canal basin. See Figure 2-1.

OFFSITE DOSE CALCULATIONMANUAL FOR GASEOUS AND LIQUID EFFLUENT The alarm setpoint for each liquid effluent monitor is based upon the measurements of radioactivity in a batch of liquid to be released or in the.

continuous aqueous discharge. Sample measurements are performed according to

~

Technical Specification Table 3.9-1.

2.0.1 Set int for a Batch Release The liquid radwaste effluent line radiation monitor alarm setpoint for a batch release is determined with the equation below or a method which gives a lower setpoint value.

(7)

Sb FMPCb Sb + BkS where:

Sb = radiation monitor alarm setpoint (cpm) for a batch release Ab = laboratory counting rate (cpm/ml) or activity concentration (pCi/ml) of sample from batch tank FMPCb = fraction of unrestricted area MPC present in the condenser cooling water mixing basin outflow due to a batch release; determined in section 2.2.2.

gb = ratio of effluent radiation monitor counting rate to laboratory counting rate or activity concentration in a given batch sample (cpm per cpm/ml or cpm per pCi/ml)

Bkg = background (cpm) 2.0.2 Set int for a'Continuous Release The liquid ef fluent line radiation monitor alarm setpoint, for a continuous release, is determined with the equation below or by a where:

method which gives a lower setpoint value.

gc =

FMPCc g c + Bkg Sc = radiation monitor alarm setpoint (cpm) for a continuous release P

laboratory counting rate (cpm/ml) or activity concen-tration (pCi/ml) of sample from continuous release FMPCc = fraction of unrestricted area MPC present in the condenser cooling water mixing basin outflow due to a continuous release; determined in section 2.2.3.

ratio of effluent radiation monitor counting rate to laboratory counting rate or activity concentration in a given continuous release sample (cpm per cpm/ml or cpm per pCi/ml)

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0 I

OFFSITE DOSE CALCULATIONMANUAL FOR GASEOUS AND LIQUID EFFLUENT Technical Specification 3.9.1.d requires that appropriate subsystems of the liquid radwaste treatment system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the projected doses to unrestricted areas due to liquid effluents, when averaged monthly, would exceed 0.06 mrem to the total body or 0.2 mrem to any organ.

Technical Specification 3.9.1.d.l requires the doses, to unrestricted areas, due to radioactive material released in liquid effluent to be projected at least once per month unless the liquid radwaste treatment system is being used.

This requirement is satisfied by extrapolating the dose to date during the current month to'include the entire month. The dose to date is calculated as described in section 2.3.

The dose is projected with the relation:

p 31'D (9)

X where:

P = the projected total body dose during the month (mrem) 31 = number of days in a calendar month (days)

X = number of days in current month to date represented by available radioactive effluent sample (days)

D = dose to date during current month calculated according to section 2.3 (mrem)

Alternatively, the monthly dose may be projected by computing the doses to the total body and most exposed organ accumulated during the most recent month and assuming the result represents the projected doses for the current month.

The dose during the preceeding month will be computed as described in section 2.3.

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4 Primary Primary Turbines Turbines oop Unit 3 Unit 4 Oop on ensers Steam Reactor .Reactor Steam Generato Condensers Generator Blowdown CVCS 3 CVCS 4 B LOWDOWN 0

EO C

lD

\ Blowdown Makeup water Blowdown flash and chemicals flash Vent to Vent to Atmosphere tank tank Atmosphere I

Reactor Reactor Xl Coolant Coolant R-4-19 C Drain Tank Drain Tank CL Pl I R-3-19 C

Chemical Laboratory Pt Containment Sumps Spe"nt Fuel Holdup Boric Acid Waste Pits Tanks Holdup Floor Drains Tanks Laundry S Showers Laundry Boric Acid Evaporator Water Concentrates Demineralizer Recovery Holding Tank System System Bottoms Intake Intake Canal Canal Monitor Solid Waste Tanks Drumming Facility Shipment Off-site R-18 Waste Monitor Discharge Canal Tanks Discharge Canal

OFFSITE DOSE CALCULATIONMANUAL FOR GASEOUS AND LIQUID EFFLUENT 3.1 Introduction Units 3 and 0 discharge gaseous effluent through the plant vent, Unit 3 Spent Fuel Pit vent and air ejector vents. These gaseous ef fluent streams, radioactivity monitoring points, and effluent discharge points are illustrated schematically in Figure 3-1. When calculating atmospheric dispersion of gaseous effluent, gaseous discharges from Units 3 and 0 are treated as a mixed mode ground-level release from a sin'gle composite vent.

3.2 Radioactivi in Gaseous Effluent For the purpose of estimating offsite radionuclide concentrations and radiation doses, measured radionuclide concentrations in gaseous effluents from the Plant are relied upon. Table 3.9-3 in'the Technical Specifications identifies specific radionuclides in gaseous discharges for which sampling and analysis is done.

In addition, the quantity of radioactive noble gas discharged during an interval of time and not accounted for by the above samples may be determined by integrating the release rate measurement of each effluent noble gas monitor identified in Figure 3-1. The total measured radioactivity discharged via a stack or vent during a counting interval is determined by the relation N ' (10)

Q 3.53 x 10 5 ~

h where:

Qj = total measured gaseous radioactivity release via a stack or vent during counting interval j (pCi)

I, Nj = counts accumulated during counting interval j (counts)

F = discharge rate of gaseous effluent stream (ft3/min) 3.53 x 10-5 = conversion constant (ft3/cm3) h = effluent noble gas monitor calibration or counting rate response for noble gas gamma radiation,

~cm pCi/cm3 The distribution of radioactive noble gases in a gaseous effluent stream is determined by gamma spectrum analysis of gas samples from that stream. ~

Results of previous analyses may be averaged to obtain a representative distribution.

In the event the radioactive noble gas distribution is not obtainable from sample(s) taken during the current period the distribution will be obtained from recently available data or from Table 3-2.

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OFFSITE DOSE CALCULATIONMANUAL FOR GASEOUS AND LIQUID EFFLUENT If fl represents the fraction of radionuclide i in a given effluent stream, based on the isotopic distribution of that stream, then the quantity of radionuclide i.

released in a given gaseous effluent stream during counting interval j is estimated by the relation where:

Qij = quantity of radionuclide i released in a given gaseous effluent stream during counting interval j (pCi) fi = the fraction of radionuclide i released in a given effluent stream Some gaseous effluents from both Units 3 and 0, whose sources are identified in Table 3-2, discharge in common through the Plant Vent. To assure that the effluents are within allowable limits per reactor, the measured release from the Plant Vent is apportioned to each unit on a ratio equal to the ratio of specific isotopic concentrations in the primary coolant in the two reactors. Iodine and particulate release contributions will also be adjusted to account for specific containment purge'releases.

3.3 Dose Rate Due to Gaseous Effluent Technical Specification 3.9.2.a provides that the dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the site boundary shall be limited to the following: <500 mrem/year to the total body and <3000 mrem/year to the skin due to noble gases and <1500 mrem/year to any organ due to I-131, I-133, tritium and for all radioactive materials in particulate form with half-lives greater than 8 days.

Compliance with the limits on dose rate from noble gases is demonstrated by establishing gaseous effluent monitor alarm setpoints such that an alarm will occur at or before a<<dose rate limit for noble gases is reached. If an alarm occurs when the monitor setpoint is at or below its limit, compliance may be assessed by comparing the monitor record with the setpoint (limit) calculated in accordance with section 3.6 or a more conservative method. In the event an alarm occurs and the monitored release exceeds the setpoint limit, then compliance may be evaluated by calculating dose rates in accordance with Sections 3.3.1 and 3.3.2.

Since Xe-133 has comprised most of the ef fluent noble gas radioactivity historically, alarm setpoints may be derived on the basis of Xe-133, an historical spectrum dominated by Xe-133, or on a measured spectrum. As long as Xe-133 is the dominant radioactive gas in airborne effluent, the gamma dose rate to a person's body is expected to be a larger fraction of the limit, 500 mrem/year, than is the beta plus gamma dose rate to skin, 3000 mrem/yr. In that case, a gaseous effluent monitor setpoint may be derived on the basis of gamma dose rate to a person's body alone; such that an alarm occurs at or before the total body dose rate off-site exceeds 500 mrem/year as given in Specification 3.9.2.a.

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4 OFFSITE DOSE CALCULATIONMANUAL FOR GASEOUS AND LIQUID EFFLUENT 3.3.1 Total Bod Dose Rate The total body dose rate from radioactive noble gases may be calculated at any location off-site by assuming a person is immersed in and irradiated by a semi-infinite cloud of the noble gases. The dose rate may be calculated with the equation Q = X,.1'

~

Q

~ ~

P where:

D = Dose rate to total body from noble gases (mrem/year)

X/Q = atmospheric dispersion factor at the off-site location of interest (sec/m~)

t = Averaging time of release, i.e., increment of time during which Qi was released (year)

Qi = quantity of noble gas radionuclide i released during the averaging time (pCi)

Pyi = factor converting time integrated concentration of noble gas radionuclide i at ground-level, to total body dosep mrem; See Reference Table 3-4 pCi sec/m3

~

Since dose rate limits for airborne ef fluents apply everywhere of f-site, compliance is assessed and alarm setpoints determined at the site boundary where the minimum atmospheric dispersion from the plant (maximum X/Q) occurs. Ordinarily, that location is selected on the basis of reference meteorology data in Appendix A. According to those data, the minimum dispersion off-site occurs at the site boundary 1950 meters SSE of the plant where X/Q = 5.8 x 10-" sec/m3. Alternatively, averaged meteorology data coincident with the period of release being evaluated may be used.

3.3.2 Skin Dose Rate The dose rate to skin from radioactive noble gases may be calculated at any location off-site by assuming a person is immersed in and irradiated by a semi-infinite cloud of the noble gases. The dose rate to skin may be calculated with the equation X 1 Q m ~ q- ~

Sg; + 1.11 9- ~

AY Q C REV.1: 12/19/84 C6:I

OFFSITE DOSE CALCULATIONMANUAL FOR GASEOUS AND LIQUID EFFLUENT where:

D = dose rate to skin from radioactive noble gases (m rem/year)

S 81 = factor converting time integrated concentration of noble gas radionuclide i at ground-level, to skin dose from beta radiation, mrem; Reference Table 3-0 pCi sec/m3

~

1.11 = ratio of tissue dose equivalent to air dose in a radiation field (mrem/mrad)

Apl = factor for converting time integrated concentration of noble gas radionuclide I in a semi-infinite cloud, to air dose from its gamma radiation, mrad 'isted in Table 3-3 pCi sec/m3 Since dose rate limits for airborne effluents apply everywhere off-site, compliance is assessed and alarm setpoints determined at the site boundary where the minimum atmospheric dispersion from the plant (maximum X/Q) occurs. Ordinarily, that location is selected on the basis of reference meteorology data in Table 3-6. According to those data, the minimum dispersion off-site occurs at the site boundary 1950 meters SSE of the plant where X/Q = 5.8 x 10" sec/m3. Alternatively, averaged meteorology data coincident with the period of release being evaluated may be used.

3.3.3 H-3 I-131 I-133 and Particulate Dose Rate The dose rate due to H-3, I-131, I-133, and radioactive material in particulate form with a half-life of more than 8 days is calculated with the equation anp = ggpp

' Xg~~ 'nip (14)

< Qk Q~ik i

where:

Danp dose equivalent rate to body organ n (most exposed organ) of a person in age group a (adult) exposed via pathway p (inhalation) to radionuclide i identified in analysis k of effluent air (mrem/year)

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OFFSITE DOSE CALCULATIONMANUAL FOR GASEOUS AND LIQUID EFFLUENT 3600 = conversion constant (sec/hr) t = period of time over which the effluent releases are averaged (hr)

Xd/Q = atmospheric dispersion factor, adjusted for depletion by deposition (sec/m3). (Alternatively X/Q, unadjusted, may be used.)

Qik = quantity of radionuclide i released during time increment t based on analysis k (pCi).

TAanip = a factor relating the airborne concentration time integral of radionuclide i to the dose equivalent to organ n of a person in age group a (adult) exposed via pathway p (inhalation),

~mrem/ r; See Appendix A pCi/m3 V/hen the dose rate due to H-3, I-131, I-133, and radionuclides in particulate form is calculated for the purpose of assessing compliance with Specification 3.9.2.a, a hypothetical adult located at the site boundary where the minimum atmospheric dispersion from the plant occurs is assumed as the receptor.

Ordinarily, the dose rate calculation will be based on the maximum Xd/Q (minimum dispersion) according to reference meteorology data in Table 3.7. The maximum Xd/Q at or beyond the site boundary which will be used to calculate the dose rate is Xd/Q = 5.0 x 10 sec/m3. According to those data, the minimum dispersion off-site occurs at the Site Boundary 1950 meters SSE of'the plant. That location is identified in Figure 3-2. Alternatively, averaged meteorological dispersion data coincident with the period of release may be used to evaluate the dose rate.

Assuming exposure of an adult by inhalation is appropriate, because it is also the basis of maximum permissible concentration (limits) for airborne radionuclides in unrestricted areas as given in 10 CFR Part 20, Appendix B. These radionuclides in airborne effluents are measured according to the sample and analysis schedule in Technical Specification Table 3.9-3.

The averaging time of the measured releases used to evaluate compliance will not exceed 98 days for Sr-89 and Sr-90 and will not exceed 9 days for the other radionuclides.

- 3.0 Dose - Noble Gases Technical Specification 3.9.2.b requires that the air dose per reactor at and beyond the site boundary due to noble gases released in gaseous effluents shall be limited, during any calendar quarter, to <5 mrad for gamma radiation and <10 rnrad for beta radiation and, during any calendar year, to <10 mrad for gamma radiation and <20 mrad for beta radiation.

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OFFSITE DOSE CALCULATIONMANUAL FOR GASEOUS AND LIQUID EFFLUENT 3.0.1 Noble Gas Gamma Radiation Dose Specification 3.9.2.b.l requires an evaluation be performed monthly to verify that the accumulated air dose due to gamma radiation does not exceed the limits as given in 3.0 above.

The gamma radiation dose to air offsite as a consequence of noble gas discharged from each unit can be calculated with the equation 1 X A Yeff (15) 0.8 Q where: 3 DY = noble gas gamma dose to air due to a mixed-mode release (mrad) 0.8 = a conservatism factor which, in effect, increases the estimated dose to compensate for variability in radionuclide distribution X/Q = atmospheric dispersion factor for a mixed-mode discharge (sec/m>)

Yeff effective gamma air dose factor converting time-integrated, ground-level, total activity concentration of radioactive noble gas, to air dose due to gamma radiation. This factor has been derived from noble gas radionuclide distributions in routine operational releases. Refer to Appendix D for a detailed explanation. The effective gamma air dose factor derived is:

A = 1.4 x 10 >

Qj = the measured gaseous radioactivity released via a stack or vent during a single counting interval j (@CO Specification 3.9.2.b.l is satisfied by calculating the noble gas gamma radiation dose to air at the location identified in Figure 3-2. At that location, 1950 meters SSE of the Plant, the reference atmospheric dispersion factor to be used is X/Q = 5.8 x 10 " sec/m3.

Alternately, Specification 3.9.2.b.l may be satisfied by calculating the gamma dose to air with the equation where:

f; = the fraction of radionuclide i released in a given effluent stream REV. 1: 12/19/84 C6:1

OFFSITE DOSE CALCULATIONMANUAL FOR GASEOUS AND LIQUID EFFLUENT factor converting time integrated, ground-level A>

concentration of noble gas radionuclide i to air dose from gamma radiation, listed in Table 3-3; mrad pCi sec/m3

~

3.0.2 Noble Gas Beta Radiation Dose Technical Specification 3.9.2.b.l requires an evaluation be performed monthly to verify that the accumulated air dose due to beta radiation does not exceed the limits as given in 3.0 above.

The beta radiation dose to air offsite as a consequence of noble gas discharged from each unit can be calculated with the equation X . A Beff (17) 0.8 Q Z Qi 3

where:

Dg = noble gas beta dose to air due to a mixed-mode release (mrad) 0.8 = a conservatism factor which, in effect, increases the estimated dose to compensate for variability in radionuclide distribution

'i Ag ff= effective beta air dose factor converting time-integrated, ground-level, total activity concentration of radioactive noble gas to air dose due to 'beta radiation. This factor has been derived from noble gas radionuclide distributions in routine operational releases. Refer to Appendix D for a detailed explanation. The effective beta air dose factor derived is:

Aa~e ff = 34x 10 5

~

sec/m3 Specification 3.9.2.b.l is satisfied by calculating the noble gas beta radiation dose to air at the location identified in Figure 3-2. At that location, 1950 meters SSE of the Plant, the reference atmospheric dispersion factor to be used is X/Q = 5.8 x 10 sec/m3.

Alternately, Specification-3.9.2.b.l may be satisfied by calculating the Dg =

Q Qg 'i beta radiation dose to air with the equation Aai

OFFSITE DOSE CALCULATIONMANUAL FOR GASEOUS AND LIQUID EFFLUENT where:

Ag1 factor converting time-integrated, ground-level concentration of noble gas radionuclide i to air dose from beta radiation, listed in Table 3-3; mrad pCi ~ sec/m3 3.5 Dose Due to Iodine Tritium and Particulates in Gaseous Effluents Technical Specification 3.9.2.c requires that the dose per reactor to a member of the public due to I-131, I-133, tritium, and particulates with half-lives greater than 8 days in airborne effluents released to areas at or beyond the site boundary shall not exceed 7.5 mrem to any organ during any calendar quarter and shall not exceed 15 mrem to any organ during any calendar year.

3.5.1 Determinin the anti of Iodine Tritium and Particulates Radionuclides other than noble gases in gaseous effluents that are measured by the radioactive gaseous waste sampling and analysis program described in Technical Specification Table 3.9-3 are used as the release term in dose calculations. Airborne releases are discharged

, either via a stack above the top of the containment building or via other vents and are treated as a mixed mode release from a single location.

Releases of steam from the blowdown flash tank concurrent with primary to secondary leakage will also result in the release of activity to the atmosphere. Using a blowdown sample analysis, it is assumed that 5% of the I-131 and I-133 and 33% of the tritium in the blowdown stream become airborne with the remainder staying in the liquid phase.

For each of these release combinations, samples are analyzed weekly, monthly, quarterly, or for each batch release according to Table 3.9-3.

Each sample provides a measure of the concentration of specific radionuclides, Ci, in gaseous effluent discharged at flow, F, during a time increment ht. Thus, each release is quantified according to the relation (19) where:

the quantity of radionuclide i released in a given effluent stream based, on analysis k (pCi)

Cik concentration of radionuclide i in gaseous effluent identified by analysis k (pCi/cc)

Fl effluent stream discharge rate during time increment At)(cc/sec) time increment j during which radionuclide i at concentration C;k is being discharged (sec)

C6:I

OFFSITE DOSE CALCULATIONMA'NUAL FOR GASEOUS AND LIQUID EFFLUENT 3.5.2 Calculatin the Dose Due to Iodine Tritium and Particulates A person may be exposed directly to an airborne concentration of r adioactive material discharged in an effluent gaseous stream and indirectly via pathways involving deposition of radioactive material onto the ground. Dose estimates should account for the exposure via the following pathways:

1) direct radiation from airborne radionuclides except noble gases

2) inhalation

3) direct radiation from ground plane deposition

0) fruits and vegetables

5) air-grass-cow-meat-

6) air-grass-cow-milk Of all these pathways, the air-grass-cow-milk pathway is by far the controlling dose contributor. The radioiodines contribute essentially all of the dose, by this pathway, with I-131 typically contributing greater than 9596. The dose transfer factors for the radioiodines are much greater than for any of the other radionuclides. The critical organ is the infant's thyroid. For this reason, the potential critical organ dose via airborne effluents can be estimated by determining an effective dose transfer factor for the radioiodines based on the typical radioactive effluent distribution, the air-grass-cow-milk pathway, and the infant thyroid as the receptor. Then for conservatism the total cumulative release of all radioiodines and particulates can be used along with the effective dose transfer factor to determine a conservative estimate of the'infant thyroid dose.

Technical Specification 3.9.2.c.l, requires an evaluation be performed monthly to verify that the accumulated total body or organ dose commitment does not exceed the limit. Dose commitment due to iodines and particulates may be calculated by, using the following equation 3.17 x 0.8 10, D TG131 Q k (Zo)

Q where:

DMk = the dose commitment to an infant's thyroid received from exposure via the air-grass-cow-milk pathway and attributable to iodines identified in analysis k of effluent air, (mrem) 3.17 x 10+ = conversion constant (yr/sec) 0.8 = a conservatism factor which, in effect, increases the estimated dose to compensate for variability in the radionuclide distribution C6:1

4 OFFSITE DOSE CALCULATIONMANUAL FOR GASEOUS AND LIQUID EFFLUENT D/Q = relative deposition rate onto ground from a mixed mode atmospheric release (m-2)

TG131 = factor converting ground deposition of radioiodines to the dose commitment to an infant's thyroid exposed

~

'@i/(m2 ~

sec)

Qik = The quantity of radionuclide i (I-131 and I-133) released in a given effluent stream based on a single analysis k (pCi)

Specification 3.9.2.c.l is satisfied by calculating the dose to a person from iodine and particulates discharged as airborne effluents via the air-grass-cow-milk pathway and is evaluated by assuming a cow on pasture 0.5 miles west of the plant. (There are no milch or meat animals within 5 miles.) At that location the reference atmospheric deposition factor is D/Q = 5 x 10-10 m-2 When equation 20 is used to estimate the critical organ dose commitment, the effective dose transfer factor is:

TG 6 5 1011 Qi/(m~ ~

sec)

The reference data from which TG131 was derived are summarized in Table D-2 of Appendix D.

Alternately, the requirement of Specification 3.9.2.c.l, to perform monthly determinations of dose commitments due to radioiodine, tritium and radioactive particulates in ef fluent air may be made by using equations (21), (22), (23), and (20).

The dose commitment from exposure to airborne concentrations of radioactive material other than noble gas from a release, Q;k, via the inhalation and irradiation pathways is calculated with the equation D~k = 3.17 x 10 ~

Xg '

Qik ~

TAanip (~1)

7. p where:

D~ = the dose commitment to organ n of a person in age group a due to radionuclides identified in analysis k of an air effluent, (mrem) 3.17 x 10< = conversion constant (yr/sec)

Xd/Q = atmospheric dispersion factor for a mixed mode release, adjusted for depletion by deposition (sec/m3)

The quantity of radionuclide i released in a given Qik effluent stream based on analysis k (pCi)

REV.1: 12/19/84 C6:1

OFFSITE DOSE CALCULATIONMANUAL FOR GASEOUS AND LIQUID EFFLUENT TAanip = a factor converting airborne concentration of radionuclide i to dose commitment to organ n of a person in age group a where exposure is directly to airborne material via pathway p 'inhalation, or external exposure to the plume),

See Appendix A pCi/m3 The dose to a person from iodine and particulates discharged as airborne effluents via the inhalation and irradiation pathways is evaluated at the nearest garden (with residence assumed) 3'.6 miles west northwest of the plant. At that location, the reference atmospheric dispersion factor adjusted for depletion by deposition is Xd/Q = 1 x 10-7 sec/m3.

The dose commitment via exposure pathways involving radionuclide deposition from the atmosphere onto vegetation, or the ground is calculated with the equation D

D~~ 3.17 x 10 Qzk TG<<zp (22)

1. P where:

D/Q = relative deposition rate onto ground from a mixed mode atmospheric release (m 2)

TGan>> = factor converting ground deposition of radionuclide i to dose commitment to organ n of a person in age group a where exposure is due to radioactive material

~i via pathway p (direct radiation from ground plane deposition, fruits and vegetables, air-grass-cow-meat, or air-grass-cow-milk),

pCi/(m2 sec)

~

'he dose to a person from iodine and particulates discharged as airborne effluents via the air-grass-cow-milk pathway is evaluated by assuming a cow on pasture 0.5 miles west of the plant. (There are no milch or meat animals within 5 miles). At this location, the reference atmospheric deposition factor is D/Q = 5 x 10-10 m-2.

The concentration of tritium in vegetation is a function of the airborne concentration rather than the deposition. Thus the dose commitment from airborne tritium via vegetation (fruit and vegetables), air-grass-cow:milk, or air-"rass-cow-meat pathways is calculated with the equation D~~ ~ 3.17 x 10 ~

X

'~k ~

TAa~~p (23)

C6:1

OFFSITE DOSE CALCULATIONMANUAL FOR GASEOUS AND LIQUID EFFLUENT where:

X/Q = atmospheric dispersion factor for a mixed mode release (sec/m3)

The dose to a person from tritium via the vegetation (fruit and vegetables), air-grass-cow-milk, or air-grass-cow-meat pathways is evaluated at the nearest garden (with residence assumed) 3.6 miles west northwest of the plant. At that location, the reference atmospheric dispersion factor is X/Q = 1 x 10-7 sec/m3.

The dose commitment via a given: pathway as a result of measured discharges from a release point is accumulated with

>an ~ >mac ( 24) where:

Dan = the dose commitment to organ n of a person in age group a k = the counting index; it may represent either p, analysis of a grab sample w, a weekly sample analysis m, a monthly composite analysis, or q, a quarterly composite analysis 3.6 Effluent Noble Gas Monitor Alarm Set oint I

Technical Specification 3.9.2.d requires the radioactive gaseous effluent monitoring instrumentation channels to be operable with their alarm setpoints set to ensure the limits of Specification 3.9.2.a are not exceeded.

Each radioactive noble gas effluent monitor setpoint is derived either on the basis of total body dose equivalent rate or noble gas concentration, in the unrestricted area beyond the exclusion area boundary. The setpoint derivations assume that noble gas releases occur at ground-level.

For the purpose of deriving a setpoint, the distribution of radioactive noble gases in an effluent stream may be determined in one of the following ways:

Preferably, the radionuclide distribution is obtained by gamma spectrum analysis of identifiable noble gases in effluent gas samples.

Results of analyses of one or more samples may be averaged to obtain a representative spectrum.

2. In the event a representative -'istribution is unobtainable from measurements by the radioactive gaseous waste sampling and analysis program, it may be based upon a historical spectrum appearing in Table 3-2.

3. Alternatively, the total activity concentration of radioactive noble gases may be assumed to be Xe-133.

REV.1: 12/19/84 C6:1

OFFSITE DOSE CALCULATIONMANUAL FOR GASEOUS AND LIQUID EFFLUENT 3.6.1 Set int Based on Dose Rate A noble gas effluent monitor setpoint, based on dose rate, is calculated with the equation below or a method which gives a lower setpoint value.

gc; (25)

= 1.06 h + Bkg i 'Fi S

where:

S = The alarm setooint (cpm) 1.06 = 500 mrem/yr.60 sec/min 35.37 ft3/m3 1 m3/106cm3 h = monitor response to activity concentration of effluent,

~Clll pCi/cm3 Ci = relative concentration of noble gas radionuclide i in effluent at the point of monitoring (pCi/cm3) f = flow of gaseous effluent stream, i.e., flow past the monitor (ft3/min)

X/Q = atmospheric dispersion from point of ground-level or split-wake release to the location of potential exposure (sec/m3)

DFI = factor converting ground-level or split-wake release of radionuclide 1 to the total body dose equivalent rate at the location of potential exposure, mrem yr pCi/m3

~

Bkg = monitoring instrument background(cpm)

Each monitoring channel has a unique response, h, which is determined by the instrument calibration.

Atmospheric dispersion depends upon the local atmospheric conditions.

For the purpose of calculating a radioactive noble gas effluent monitor setpoint, the atmospheric dispersion factor, X/Q, will be based on prevailing meteorological conditions or on reference meteorological conditions. The minimum atmospheric dispersion off-site derived from reference meteorological conditions at the site boundary is 5.8x 10-7 sec/m3 at a location 1950 meters south southeast of the Plant.

The applicable dose conversion factors, DF;, for deriving setpoints are in Table 3-5.

C6:1

OFFSITE'DOSE CALCULATIONMANUAL FOR GASEOUS AND LIQUID EFFLUENT 3.6.2 Set int Based on Concentration I

A noble gas ef fluent monitor setpoint, based on concentration, is calculated with the equation below or a method which gives a lower setpoint value.

MPC'h (26) 4 7 ~

10 f X/Q where:

S = alarm setpoint (cpm)

MPC = unrestricted area maximum permissible concentration for the effluent noble gas mixture. The MPC for noble gas is calculated from the distribution of noble gases in the release with the equation NPC = Ci i

where:

Ci = relative concentration of noble gas radionuclide i in a gaseous release (pCi/cm3)

MPCI = 10 CFR Part 20, Appendix B, Table 2, Column 1 value h = effluent noble gas monitor counting rate response or calibration for noble gas,

~cm pCi/cm3 0.7 x 10< = conversion constant 1 m3 x 1 min 35.37 ft3 60 sec f = discharge rate of gaseous ef fluent (ft3/min)

X/Q = atmospheric dispersion from release point to unrestricted area (sec/m3)

Bkg = monitoring instrument background (cpm)

The value of atmospheric dispersion used to derive a setpoint based on concentration is the reference atmospheric dispersion value from the discharge point to the location of maximum potential exposure off-site.

The applicable value is 5.8 x 10 7 sec/m3 at a location 1950 meters south southeast of the Plant.

In the event the distribution of radioactive noble gases is based on a historically measured'distribution appearing in Table 3-2 or on Xe-133 alone, the MPC for the noble gas is 3 x 10-7 pCi/cm3.

REV.1: 12/19/84 C6:1

OFFSITE DOSE CALCULATIONMANUAL FOR GASEOUS AND LIQUID EFFLUENT 3.7 Pro ected Dose for Gaseous Effluents Technical Specification 3.9.2.e requires that the gas decay tank system shall be used to reduce radioactive materials in gaseous waste prior to their discharge if the projected gaseous effluent dose per reactor due to gaseous effluent releases .

to areas at and beyond the site boundary when averaged over a month exceeds 0.2 mrad for gamma radiation and 0.0 mrad for beta radiation, and the ventilation exhaust treatment 'ystem shall be used to reduce radioactive materials in gaseous waste prior to their discharge if the projected gaseous effluent dose per reactor due to gaseous effluent releases to areas at and beyond the site boundary when averaged over a month exceeds 0.3 mrem to any organ.

Technical Specification 3.9.2.e.l requires the doses, to areas at and beyond the site boundary, due to radioactive material released in gaseous effluent to be projected at least once per month.

This requirement is satisfied by extrapolating the dose to date during the current month to include the entire month. The dose to date is calculated as described in sections 3.0.1, 3.0.2, and 3.5.2.

The dose is projected with the relation:

p 31 D (27)

X where:

P = the projected dose during the month (mrem) 31 = number. of days in a calendar month (days)

X = number of days in current month to date represented by available radioactive effluent sample (days)

D = dose to date during current month calculated according to sections 3.0.1, 3.0.2, and 3.5.2 (mrem)

Alternatively, the monthly dose may be projected by computing the dose accumulated during the most recent month and assuming the result represents the projected dose for the current month. The dose during the preceeding month will be computed as described in sections 3.0.1, 3.0.2, and 3.5.2.

Unit 3 Unit 4 Vent Turbines Turbines ,

Condenser Pr imary Primar Condenser Coo lant Coolan Exhaust Exhaust Exhaust Exhaust Slowdown S.J.A.E.:~*. Slowdown S.J.A.E. **

Flash and Gland Flash and Gland Tank Seal Exhaust Tank Seal Exhaus 35,000 cfm 35,000 cfm 35 000 Roughing cfm filter Unit 3 Unit 4 ontainment Containment rq~~hing 35,000 cfm Roughing To CVCS f i I ter I > 200 Holdup Tanks cfrh t

for reuse cu t Laundry Area Gas Decay Tank (6) 11,200 CVCS* Waste gas nl eakage cfm Holdup compressors I

HEPA Filter Tanks 40,000 cfm 13,500 cfm Auxiliary Sldg.

Outside Air Ventilation System Prefilter 13,500 cfm 40,000 cfm Roughing HEPA Filter Exhaust Filters HEPA HEPA 1000 Filter 1000 cfm filter 20,000 cfm

.cfm Unit 3 Unit 4 Fuel Pit 0,000 Fuel Pit Area cfm Area Prefilter Pref ii ter 2000 200 fm cfm 7500 cfm I nl eakage New Rad Waste In 1 eakage Building 7500 cfm CVCS - Chemical and Volume Control System SJAE - Steam Jet Air Ejector

' - Effluent Honitoring Instrumentation Figure 3-1 Gaseous Effluent Systems S4 44

)DELL

f

~

It it SQ.

O~

f jf I

f 14 2y i llNctl01t l ~

1

/

34 n'4 T RKEY:. PQjNT PLANT 2.60

<(gj)* =

I

( Laa ~

J ALNOWl tti oX 14 IS slit~

Sc5 "5 Z2 Cw Cess. g 41

~

1 21 22 Pl 24 24 JS S4 Figure 3-2 Locations At Which Doses Due to Airborne Effluents From the Turkey Point Plant are Calculated

l. Beta and Gamma Doses to Air1 1950 m SSE

2. Maximally Exposed Person1 5800 m/HKW

3. Assumed Beef and Milch Cow> 7250 m W

OFFSITE DOSE CALCULATIONMANUAL t

FOR GASEOUS AND LIQUID EFFLUENT 0.0 Dose Commitment from Releases over Extended Time 0.1 Releases durin 12 Months Technical Specification 3.9.2.h implements 00 CFR Part 190.102. It requires the annual (calendar year) dose or dose commitment to any member of the public from all uranium fuel cycle to be limited to less than or equal to 75 mrem to the thyroid and 25 mrem to the total body or any other organ.

Fuel cycle sources or nuclear power reactors other than the Turkey Point Plant itself do not measurably or significantly increase the radioactivity concentration in the vicinity of the Plant; therefore, only radiation and radioactivity in the environment attributable to the Plant itself are considered in the assessment of compliance with 00 CFR Part 190.102.

In the event a dose calculated for the purpose of assessing compliance with Specification 3.9.1.b, 3.9.2.b, or 3.9.2.c, exceeds 2 times the limit stated therein, then a calculation should be made to determine whether any limit in Specification 3.9.2.h has been exceeded. The calculation should be made on the basis of radioactive ef fluents during the year to date and reference meteorological data or averaged meteorological data during completed quarters of the year to date.

Separately, an evaluation of doses due to effluents during the year is performed annually and reported in the Semiannual Radioactive Effluent Release Report submitted within 60 days after the end of the year. This evaluation uses annual averaged meteorological data concurrent with the annual gaseous releases to evaluate atmospheric dispersion, deposition,and plume gamma exposure.

To assess compliance with Technical Specification 3.9.2.h, evaluations of dose due to liquid and gaseous effluent are calculated as described by the equations for:

1. total body dose due to liquid effluent via irradiation by radionuclides deposited on cooling canal shoreline as in section 2.3

, 2. total body dose due to noble gas y as in section 3.0.1

3. skin dose due to noble gas 9 as in section 3.0.2 total body and maximally exposed organ doses due to gaseous effluents other than noble gases+ as in section 3.5.2.

The doses are calculated on the basis of liquid and gaseous effluents from the Plant, sampled and analyzed in accord with Technical Specification Tables 3.9-1 and 3.9-3.

+ Radioactive I-131, I-133, tritium, and radioactive material in particulate form having a half-life greater than 8.0 days.

C6:1

OFFSITE DOSE CALCULATIONMANUAL FOR GASEOUS AND LIQUID EFFLUENT The receptor of the dose is described such that the dose to any resident near the Plant is not likely to be underestimated. The receptor is selected on the basis of.

the combination of applicable pathways of exposure to gaseous effluent identified in the annual land use census and maximum ground level X/Q at the residence. Conditions more conservative than appropriate for the maximally exposed person may be assumed in the dose assessment.

Environmental pathway-to-dose transfer factors used in the dose calculations appear in Appendix A.

0.2 Environmental Measurements When assessing compliance with 00 CFR 190 or 10 CFR Part 50 Appendix I dose limits, Radiological Environmental Monitoring Program results may be used to indicate actual radioactivity levels in the environment attributable to the Turkey Point Plant as an alternate to calculating the concentrations from radioactive effluent measurements. The measured environmental activity levels may thus be used to supplement the evaluation of doses to real persons for assessing compliance with 00 CFR Part 190 or 10 CFR Part 50 Appendix I.

0.3 Dose to a Person from Noble Gases Technical Specification 3.9.2.h requires the calculation of the annual (calendar year) dose or dose commitment to a person off-site exposed to radioactive liquid and gaseous effluents from the plant. One component of personal dose is total body irradiation by gamma rays from noble gases. Another is irradiation of skin by beta and gamma radiation from noble gases. The methods for calculating doses are presented in sections 0.3.1 and 0.3.2. 'hese The amount of radioactive noble gas discharges is determined in the manner described in section 3.2.

0.3.1 Gamma Dose to Total Bod The gamma radiation dose to the whole body of a member of the public as a consequence of noble gas released from the Plant is calculated with the equation:

(zs) where:

D> = noble gas gamma dose to total body (mrem)

Qi = quantity of radioactive noble gas i discharged in gaseous effluent (lrCi) !I X/Q = meteorological dispersion factor (sec/m3)

OFFSITE DOSE CALCULATIONMANUAL FOR GASEOUS AND LIQUID EFFLUENT P> - factor converting time integrated, ground level concentration of noble gas nuclide i to total body dose from gamma radiation listed in Table 3A, mrem pCi sec/m3

~

When the total body dose due to gamma radiation from noble gas required by Technical Specification 3.9.2.h is calculated, the most exposed receptor is located 3.6 miles west northwest of the plant where the reference meteorological dispersion factor, X/Q, is 1 x 10 7 sec/m3.

0.3.2 Dose to Skin The radiation dose to the skin of a member of the public due to noble gas released from the Plant may be calculated with the equation:

D x W QQi 'ki+0 ~ 56 Qi A (29) where:

D = dose to skin due to noble gases (mrem)

S gl = factor converting time integrated ground-level concentration of noble gas to skin dose from beta radiation listed in Table 3-0, mrem pCi sec/m3

~

0.56 = 1.11 0.5 (mrem/mrad) where 1.11 = ratio of tissue dose equivalent to air dose in a radiation field (mrem/mrad) 0.5 = factor for shielding by a building A> = factor for converting time integrated, ground-level concentration of noble gas radionuclide i to air dose from its gamma radiation listed in Table 3-3, mrad pCi ~ sec/m3 When the skin beta dose due to noble gas required by Specification 3.9.2.h is calculated, the most exposed receptor is located 3.6 miles west northwest of the Plant where the reference meteorological dispersion factor, X/Q, is 1 x 10 sec/m3.

The total dose to the skin from noble gases is approximately equal to the beta radiation dose to the skin plus the gamma radiation dose to the total body.

C6:1

APPENDIX h PATHWAY-DOSE TRANSFER FACTORS Environmental pathway transfer factors> usage factoxs, and dpse commitment factors appropriate for each exposure pathway> age> and organ are combined into integrated environmenCal concentx'aCion-to-dose factors for each radionuclide. This appendix includes Cables of values of the transfer factors calculated in accord with equations and values 1

xecommended in NUREG-0133 for individual environmental. pathways. In the event a single, composite transfer factor is desired for a given organ and age group> it can be obtained by summing the factors for appx'opriate pathways. Appropriate transfer- factors from Appendix A are

'used in performing dose assessment calculations prescribed in the ODCH.

lJ. Gaeoii, ae nE ,eds.., i978, ~Pre aiba'e fan of Radiomen ical FE81uene Technical~Siccif ication.'or Nuclear Power Plants, NUREG-0133; VSNRC, Of f icn Nuclear Reactor Regulation.

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4 I/25/19 FHVI ROtltIEHIAL PAIHIIAY COSc CONVERSIOtt FACIORS FOR GASEOUS OISCHAPGES PATH<<A V - HEAT ICOHIAtlIHATEQ FORAGE I AGE GROUP - ADULT HUCL 10c 0 R G A H 0 0 5 f F A C I 0 R S ISO ~ HcIER HFEH/Ya PEF UCI/SfCI DO<<f LIVER THYROIO . KIOHEY LUNG Gl-LLI SKIN 101AL 800Y tl 0~ 4 ~ 13E<< 02 4 ~ 13f <<OZ 4 ~ 13E t02 4>>13E<<02 4 ~ 13f <<4Z 4 ~ 4>> 13Etot r.--- 14 3~ .33E<<45 6>>llft44 6 ~ 61E <<04 6>>61f t04 6>>61E<<44 6 ~ 61 f << 44 ~ o 6.61f t 04 F --32 4 ~ 61E<<49 2.93E<<04 ~o 0~ 4~ 5 ~ ZSE ~ 44 0~ l>>41E<< ~ 4 Ctt 51 4~ 0~ 4 ~ 2IE <<03 1 ~ 56E <<43 9 '4Et43 1>> llE <<06 lo 1 llE<< 43 tIH--54 4~ '9 ~ 1 4 Et 46 0~ 2>>13E t46 0 ~ 2>>01E<<41 0~ 1>>15f <<06 Fc -59 2.61'h 6 ~ 33Eto ~ 4~ ~o 1>>16E<<0 ~ t>>09E'<<09 ~o 2>>4lf <<44 ro--51 0~ 5 ~ 64E t 46 ~o 0~ 4 ~ 1 43ftll ~ o- 9 ~ 34E << 06 CO--ch 4~ t ~ 43E <<Ol 4~ 0~ 4~ 3.10E ~ 44 0~ 4 ~ 09E t 41 CD--6) 0~ lo 55E<< 41 0~ 0~ 0~ 1 ~ 4tE ~ 09 Oo 1.66E<<44 lit -63 1 ~ h9E <<49 1 ~ 31E <<04 0 ~ l1,51ct04 ~ 4~ t >>13f <<41 ~o 6,335<<01 I<<--e5 ~8--he 3 '6'Etol 1 ~ 13ct49 0~ ~o 1 ~ 13E<<04 lo 5 ltf 04 ~ I ~ Ie ~ 49Eto4 0 ~ 4~ 0~ 9 ~ 64E ~ Ol 0~ 2>>20E<<0 ~ SR--49 3 '3c<<.04 0~ 0~ 0~ 0~ 4 ~ 44E << ~ 1 ~~ 4>>61E<<46 cI --94 Z5f<<14 l>>45E<<09 3 '5E<<09 Y --93 ZS--95 1 ~ 14f <<46 I~ llf <<46 0~ 0~ 1 ~ El f t06 ~o 4~ 4~ 4~ 0~ 2 ~ Olf <<46 ~o ~o 0~ 6 '6'4 l>>30E<<09 0~ 0~ ~o 3>>45Et44 4 Z6E<<05 t<<8--'IS 2 TIES 06 1 24-t46 4~ 1 ~ 21F. <<46 0~ l>>15E<< 09 ~~ 5>>42c ~ 05 )U IDS 1 06E <<Qtt 0~ 0~ 4 '6Et44 ~o 1~ 24E ~ 10 ~o 4 '9E<<01 FU-toe Z~ 30E<<09 0~ 0 ~ 5 ~ 41E <<49 4~ t>>4tt<<tt lo 3 '4E ~ 44 AG I I DH 6~1 lf<<06 6 '1E<<06 0 ~ 1~ ZZE <<ll 0~ t>>53E<<09 0~ 3 '9Et06 00115<< 0~ 1 ~ 46E<<46 0 ~ 1 ~ 166 <<06 4~ 6>> 15E ~ 01 4 ~ 4 ~ 61E t04 I AS <<9 Cg I IICl/5 C 0-LcA"E RA . CF EACH I CIOFE IH AHO 4 VALUE OF 1~ <OR X/0 OEPLEICO X/0 AHO RELAIIVE QEPOSI TIOI'IOI E - Tlot lt<<ITS FOC 0---14 A'IO H --3 AAE (IIREH/YR PER UCI/CU IIETERI 4 Ot/25/7< =NVTRO>>MENTAL FATMIIlY OOSE COHVO'.Sio>> FlGTORS FOR CASfoUS olSCMARCES PAT>>HAY - HEAT ICOHTAMlHATto FORIGEI Acf croup - Tft>>arfp IIUCLIOE 0 R G A H 0 0 S E F A G T 0 R S ISo ~ METER NREM/YR PER uct/SECI 'IOI0E LivER THYAoio Klo>>EY LUHG Cl LLT SKTN 'TOTAL GOOY N aiie 1 ~ 93Et02 93Et02 2 '<<Et02 1.93f ~ 02 93E t02 4~ 93f t02 Ceeet<< r---32 1 0 5~ 'el6E ~ 2IEt04 5.23ft04 1 ~ 5 '3E ~ 04 3 '<<Et44 5 '3f.t44 5 '3f 1 ~ A D<< 0~ 1~ 5 ~ 23= ~ 04 ~ 49 1 ~ 7'lf t 04 0~ 0 ~ 4~ 3~ 1~ Etb ~ 0 ~ t Olft44 liR -51 0~ 0~ 2 ~ 54E ~ 03 9.zzEtoz 5 '5Et03 l. ~ 5Et06 ~ ~ 4 ~ 14Et03 Mi4 e 54 0~ 5 ~ 42E ~ 06 4 ~ t ~ 61Et46 0 ~ 1 ~ 66Et47 4. le0<<f ~ 46 Ff- 59 1 '42 F 04 3e l4E t 44 0 ~ 0~ 1 ~ 0<<Et' 1~ 24ft09 4 ~ le<<2Et4 ~ CJ--57 ile 33f t46 4 ~ 4~ ~ 4.45f t47 0 ~ 5. 5<<f ~ 06 CQ--54 0. t-<<<<f t07 0 ~ 0~ 0~ 1 ~ 94E t44 ~e 3. zlf Ol ~ Co--64 0~ 5 73Et0l 0 ~ 4e 4~ 6 ~ blEt04 0~ 1~ 3tf t 44 >>t--et 1.12Et09 le l4f t 4l 0 ~ 0~ 0~ 1 ~ 61t ~ 07 0 ~ 3~ l<<f Ol ~ 7H--65 z.ttft04 6 ~ 69Et04 0 ~ 4.<<l f. t04 4~ 4 ~ 21E ~ 0 ~ ~ ~ 3e03tt04 I'0 b6 J~ 2 49Et04 0~ 0~ 0~ 5 ~ 69E t47 ~ e 1. 35ft04 CO 2 '6E>bb 0~ 0 ~ ~e 0~ 2 ~ 49E t Ol 0 ~ le64ft06 SR--40 0 ift 10 0- 0~ 4~ 2e l9E t04 1 ~ ~ 2Et09 Oe '9E ~ 09 Y---91 li--95 9 1 ~ T<<ft05 2 ~ 676 t06 4 ~ 2<<f t oe 4 0 ~ ~ ~e

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~e 3 '9ft44 4 ~ 20f t09 0 0~ ~ 2 2 '9t le61E ~ ~ 0<< 45 Iib--95 le 5bf, ~ 46 9 "5tf ~ 05 0 ~ le<<4t t05 ~e 3 '4Et09 0. 5~ 37Et05 PU-103 0 ~ 05ft07 0~ 0 ~ 2 '0ft4 ~ 0~ 6 '4E ~ 09 4~ 3~ 60f ~ Ol tU-106 2.<<dft09 4~ 4 ~ 3 '0E t09 ~~ 1~ 09f t 11 4~ 3.02ft04 A G I l ON le97E t06 3 '7Et06 0~ l.zlft46 4~ 1 ~ 50E ~ 49 0~ 2 'bEt46 C011 54 ~ ~ 4.6<<Et45 0 ~ 6.45ft05 0~ 3 '3f ~ 47 0 ~ 2~ l6E ~ 44

A':) o4 I url/Sfc Oftfasf Palf uF EACH ifoloPE lH AHn a vaLuE OF 1 ~ FoR X/0. 0EPLETEo x/0 A>>II RELallvf oEPDST'Tloi,

>>ot: - TM: u>>lTS sob r.---t<< l>>o M----3 Aff tNIEN/Yk PER ucl/GU.NETERI e It/25/79 EHV1%0HiIEHTAL PATHIIAV"OOSE COHVEHSlOH FACTORS FOR GASfOUS 01SCHA .GES IiATHllAY HEAT ICOHTAHTHATEO FCRAGEl AGE GROUP TEEHAGEP HUCL lci 0 R C A H 0 0 S E F A C T 0 R S ISO ~ Hc TER-iIREH/YR PcR UCl/SECl AOHE 'lVER THTROTO KTOHET LUHG Gl LLl SKTH TOTAL 800V SH 125 0~ 4~ 0 ~ 0~ 4~ I ~ ~~ 4 ~ cN 126 1 10ci14 2olbf>QI 6 ~ 3bf ~ar 0 ' 3obZE+46 3 '6E>09 0~ 3o 14E>04 S8-124 le lrf Cr ~ RoZtfiCS 2 ~ 44E ~ 04 0~ 9ottf~06 3 '2E>44 4~ 4o64E>06 f9-125 5 ~ 0 if~ 01 1 ~ 31f ~ 01 t oOZE401 to03E>04 1.4rf>09 2 ~ ZSE444 ~o 1 60fi46 TE 125H 5~ 93E ~ 00 teDOE ADO 4 ~ 55f tbr ~ o63ft00 I ~ I ~ 41E~O ~ 0~ 4~ 42ctlr Tf 121H 6 ~ 64E iO ~ Zo 34E>44 t.rrfo00 2 '9E ~ 49 I ~ 3 '5fi09 ~ o I ~ ZIEi01 1 i 129H 9. rbf i04 3 ~ 63E 4 00 3 ~ 13E 00 ~ 2 ~ 03E ~09 I ~ 3e4tf+49 ~o to53fto ~ 1--134 1~ 41E-46 4 '6E-O6 5 '0E-04 6 ~ 41f -06 0~ 3 '1E-06 I ~ 1~ 64E 46 1 131 I ~ 54E ~ 46 t.Ztfior 3 'IE~49 1 ~ 56E <41 ~o 2 ~ ZOE ~ 06 I ~ r. 19E F06 152 0~ I 4 0~ 0~ ~ ~~ 0~ l--i 53 1 3~ 69E-11 ~ 6 ~ 26E 01 ~ t.t4E~DZ 1 ~ 44E-Ot 4~ ~ Ii ~ 55E Ol 4 ~, 1~ 93E Ol l--l 14 0~ 4 ~ Do D~ ~e ~ o 03' ~o 0 1 -115 5~ OIE-02 4.69E-OR 0 ~ torbfo02 5 ~ 34E ~ 3 1~ tOE 4~ Zo44E OZ I~ CS CS cs 114 156 151 5~ 6 05E<44 6 '9E<C6 '2E F 44 2 9 '6'r toZtf<09 ttf>0 ~ 0 0 0 ~ ~ ~ 3 40E i00 1 ~ 54E 441 2 '0E<0 ~ 1 1~ ~ 41f F00 Zottf i06 24f< ~ I 1~ 40f ~Dr 3ot4E>06 24f F01 0~ ~o 5o66E >40 1 ~ 99E> ~ 1 3 Zrf~bo IIA-t<<0 2 ~ 31E <41 2 '3i>04 0 ~ 1 ~ 2 ~ E< ~ 3 1~ 95E~44 9 ~ t9f F06 ~o t ~ 53E i 06 Cf -t<<t 1 ~ lREi44 1 Stf+03 0 ~ 2 'tf403 lo 2 ~ 03f F41 4~ be6tft42 Ci-144 Fh-l<<5 teRhf ~ 06 262 '4 5-23f F05 5~ Olfi03 0 4 ~ ~ 2 '4E~OS 2 ~ 92f 403 lo ~o 3 ~ 40f ~ Ol 5 ~ 52f ~or I ~~ ~ 6 6 16'4 '6fi02 l>0 1 '-1 1 ~ 0 if 04 i i 5 ~ 49f 03 4 ~ 3 ~ 'lZE <03 ~~ Zo44E >Ir ~e tbfibZ 4a .:iI U I I Ucl /ScC RELEA"1 RATf CF EACH 1SCTOPE lH AHO I VALUE OF 1 ~ <OR X/0 ~ OEPLETEO X/0 AHI'ELATlVE OEPOSTTJON 'IOIc - TM-. UHI TS FOc C---14 AkO H- -3 AXE IHOEII/VW PER UC1/CUe'IETERI 01/25/7 9 ENV lRONMENlAL PAIHHA7-DOSE CONVEPS10N FAClORS FOR GAScOUS OlSCHARGES PAlNHAy COus MlLK 1CoHZAMlNAIEO F0RAGEI AGE GP.OUP 'lEEIIAGEP. PQCL lO" 0 R G A N 9 0 S E F A C l 0 R S lSO ~ MElfR NREM/YR PfR UCI/SECI OONE LlVE0 lHVROlO KlONEV LUNG Gl LLl SKlN lolAL BOOED M 4~ 9 '3ftOZ 'io93E F 42 1.26fi03 9.93fiot 9~ 9lf tot 0~ 9 ~ 93E ~ 42 C---tv tet5E ~ 05 lo25fio5 1 ~ 2SE ~ 45 9 ~ 39f <DC ta25fi05 1.25f i as 0 ~ lo Zsf +05 -- It 2~ Ztf~to 1 3 '>49 ~o ~e ~o ZaCaft09 ~o bosCE iob Gk--it 4~ 0~ 2~ Ztf 40C ~ otSE>43 C~ 90E <OC 9o29E ~ 46 0~ 3.69E ioc wV--Sc 0~ to09E i07 0~ 3ot3fi06 Oi 3 ~ 33E 407 0 ~ Zoblf >06 Ff --59 3.4CE ibr 'I ~ ttf >al 0~ ~o 2.53fior 3iatf t ~ 4 4~ 3~ elf ~ Ol C3 "57 0 ~ 1 'Sf<46 4 ~ 0~ 4~ c o 19E >al 0~ Ze l5E ~06 CO--54 Oo ~ .tofi06 0~ 0~ 4~ 1~ taf>44 0 ~ 1 ~ 45f ~ 47 GO -60 4~ te73E ~ al 0 ~ ~o 4~ 3 ~ Zrf ~ 04 6 '3E407 N't --63 ho6bc449 6 ~ Otftaa 0~ 0~ 0~ 1~ 26Etab ~o Zo9tf ~ 04 7H--65 t.rlfio9 5.63fi09 0~ 3~ rrf >09 ae 3 '5E ~ D9 ~o 2 ~ SSE <09 PS 46 0~ 3.35fi09 ~o 0 ~ 0~ 6 ~ 61f ~0 ~ oo 1~ 56E~49 Cg e 2 ~ OOE409 0~ ~e 0 ~ Oo 3.03fiab ~ o b. 43f tal SQ--30 3 '9fttb 4 ~~ 0~ 3o34E<06 ter6fi09 ~ ~ 2 ~ 05E ~ 1~ 3e t.scfooc ~ Oo 0~ 0~ 0~ S.93f F06 ~~ Co ttftot rk 95 C. rbf ~OC 2 '4E404 0~ Z.tsfiec 4~ 1~ lsf <4 ~ 0~ 1.60fiac Mfl hi 1~ Zcf los lo46E 4 OC 0~ So ~ rftoc ~o 3 ~ osf~o ~ 0~ C.ttfiac fU IO'I I ~ 69f ~ 03 0~ 0~ VOCE>03 4~ te32E ~ 45 ~o 7.56%~02 IO6 I hlfioa 0~ 0 ~ 5.09fiac 4~ 1 ellE e46 ~o C.btfi03 AG I IO.S 7.53fior 6 ~ 97E tbr 0~ 1 ~ 3rc ~C ~ 4~ 2 ~ 4CE i to ~o c.tcfiar Co I I sn 0~ 1~ 6tf ~06 0~ 1~ Zaft46 ~o 6irrfi47 0~ 5.1CE i Oc 'I S=.G RELEASc RA16 CF EACH lSOlOPE lH AHO 4 VAlUf, OF 1 ~ FOR g/0 OEPLflfO X/0 ANO RELAllVE OEPOS Ht rf -- IME UHllS Pof C---IV ANO H- 3 ARL IHRcH/VR PER UGl/CU HflERI i<<ylnc<<<<f N5AL Fal<<MAT-OJlf COHVii SlOH FAC1ORS FOR GASEOUS OLSCHAI'GcS Par<<<<AY - CO<<f NlLK lCCHta<<lHalco FORAGit ACiE G5CUP YcENACifR <<<<GL iOE OSGANOOScFAC1OWS 5SRNE'liRNHEH/Yit Pf R Ucl/Sf G 1 & oo& iohc L lyc ~ THY 4010 r lOHE 1 L UllG Ci1-LL 1 Srlo 1O (iL QOOY

<<-l?1 G~ 0~ 0 ~ a. 0 ~ I5=~ 4 ~ 0 ~

'N 12o 2 12c ~ 09 Co 2ti 407 1 ~ 2>>f >or 3~ 6 ~ OScid6 Ctii09 S ~ 6~ Sritor Sh-t2>> 3. 311 ~ 07 6 ~ 29E o 05 4.05f.o>> 4~ 2~ 59iior I ~ Clf<0 ~ 4 ~ to 32fior c io-1 ~5 3>>52 ~ itr 9,caic05 5.05E ~ 05 C ~ Oai 100 3 'SE409 2 '5Etoa 0 ~ 6 '2ft06 125<< Ooi) 47 5-oaiiar I ~ Crc ~ 06 0,55ctar .39'7 3 90E t46 1 l c 1? 7H lf l2'00 oo 02f ~ 47 1.1SE ~ 40 2o 1 lii C ~ tlftor 07 t.59Eior So6titor RoCSCOOI 3 Rrf+44 0~ 0~ ~o ~ 3 ~ ORE<0 ~ 3 ~ 93E>04 ~ 0 0 ~ ~ ~ 7.+5fio6 l.razor 1--1 50 5.5tf i05 63E106 2 ~ orf boa 2 53f ~ 06 a. 1 oC ~ f ~ 46 0 6. C lf~ 05 1--t 51 1- 152

5. t Rcio ~

2~ 16E-41 5 1 ro Rci>44 76c-01 2.49E 7 '9Eiot ~ ll 9o Slf >04 9 ~ 19c Ol 4~ 0~ 1.37fiaa 1 ~~ If ~ I 0~ 0~ ~ CD 35E F 00 2, ~ 5c 41 1 l 13 7 35fo06 toRCE ~ 07 2.26io09 5.56E iar 0~ 9 ~ IRE ~ l6 4 ~ 3 ~ ~ Sc ~ 06 1--l 5>> Oi 0~ 1 ~ 29E-49 0~ ~o I ~ 4 ~ 4~ 1 135 1 ~ 4li ~ QQ li ~ rrcioC 6.2qfi06 7~ 5lf ~ OC 9 ~ 79E 02 5~ 3iif 44C 0 ~ 1~ 75f ~ OC CS -1 tw 9-CCS ~ 49 2.2 ~ cita 5.63E ~ u9 2 '6if+09 R ~ 63fcaa 06E Fit-tent CS-5 CS -1%7 Sb s ~ 57E ~ 04 1 ~ Roil 14 5.%3fi09 1.72io la 0~ ~o ~o robtcta ~ c.~SE i09 1 ~ ORE 14 ~ 2 Rafi09 1~ 5lf '9fia ~ 4 ' ~ 0 ~ 0 ~ ~ ~ 1 ~ 9.5aE ~ oa 6.ICED 09 ~ 14 La l>>o Iuc ~ 0 5-95fioc 4~ 5o44i ~ 4C 3~ 94ftac 9.16E ~ 06 ~ o 3 ~ 1tf ~ 06 Cc 1st 5o05ciGC 3 ~ 39itQC I 1 ~ 1 ~ E ~ OC 4~ 9~ 1~E ~ lr I ~ 3 '9ft03 Ci-t>>C C~ 5 oct 06 1 ~ 64 it 06 ~o ~ 6 ~ arct05 ~o 9 '5E boa 0 ~ R.trfo05 2 45ii42 4.25caot lo ~.75iiat ~~ 4.94fc05 I ~ 1 IRE>at <<O-1 to+9E402 t.ccfioR I 4.7CE ~ 41 0~ 6 ~ IREc05 I ~ 9 CIEtoa -"A. iO ON 5 UCl/SEC ecLEASE Ralf Of EACH lSOIOPE lH aNO A VALUE OF l. FOR X/R. OEPLElfo X/R ANO RELallVE OEPOSlllOW <<Cl: - 1<<= <<nil'5 FOli C---tc ANO N----3 af f {NGiN/Yk PER UCl/QU ~ HElfR) 01/ts/rq EHVlROIIKEHTAL PATNMAY OOSE COHVERS10h FACTORS FOR GASEOUS OlSGHIRGE S PATNHAY FRE N IHO STOREO FRUlTS IHO VEGETISLES IGE GROUP TEENAGER IIUCLTOE 0 R G IH 0 0 S E F I C T 0 R S 150 HETER NREN/'YR PER Ucl/SEGI nnHE LTVER TNYRCTO KlOHEY LUNG Gl LLl SKTH TOTAL OOOY H toSlf 103 2 Slf F03 3 '4ft03 2.5l f F03 2~ Slf F 03 2~ srf~43 0~ t.rif ltf>05 t. lifebs ~o ~ C---14 2~ rtf ~ 05 t.rtf F05 ebs to ~ 3E ~ 05 t 4~ tel tf obs o---32 le 13f <Oq le06ftbr 4~ 0~ ~o 6.0bf ~04 1~ tlf<04 totsfibr ~o 4. 36Ei br C9 -51 0 ~ 0~ tor4E>04 1 Otf F04 ~e 4.50E F04 Nlt o So 0~ 3~ stf ebb I ~ 1~ Osf F00 bo 1~~ bf ~ 09 I 6~ rtf ibl tlf ~ Fc 59 1 ~ 3ii E ~ 40 3o tbf ebb ~~ bo Iobbf ebl io05EI09 ~ o to OOO CO Sl 0~ 1'o3tf >Or 4~ Io ~o 3 '4ft44 0 ~ to tqf t 4l CO -5% 4~ 4 '5ftbl ~~ ~o ~o 6obtEI ~ I I~ toOtftbb ro-64 Oo 2 '4ftbb ~o 0~ ~o 2 '3E>09 I ~ S.srfibb II 1 63 t ~ tbf>tb botbftbb torif404 I~ 3~ 96f ~40 rII--65 c~--be 3.5rf ~ F 0 ' t 14E<09 ~ 942 '4 ~o I I ~ ~ ~o loslf ebb ~o ~o ~o ~o ro}3ftb~ 3 '3E<bl ~e ~o

5. 1 tf F00 9 ~ Def ibl 6< 49 1.SOEi10 1

Oo I ~ 4~ Io t.rtf F09 9lf i lb ~~ 4e Ssf ~ 04 Sc --90 )o40ftlt Oo 0 ~ Oo 3o36f >49 2~ I ~ 2 ~ 33E > it qt r.eq'bc 4~ 4 ~ 0~ I ~ 2 '5fi09 bo 2 ~ 06E ~ 0$ 7%--95 t oblci06 l ~ 03ft 05 42 f ~ 0 ~ l0 9DE t45 ~o 1 ~ 06E i 09 0~ 4 ~ 66Et 05 IIO --95 t ~ 69E ~ 05 1 ~ DS 0~ ~ DOE> ~ 4 I ~ 4otSE ~ I~ ~o 5 l3E o04 IU 103 46fobe 93E ~ Ol 5 '4E>04 Io T.U-l ue AG110H 6~ to 154 ~ 04 1 19= ~ Dl D~ 0 1 ~ tbfibr 4 0~ 0 ~ ~ 1 4 2~ ~ '4'4 llE tbr ~o ~o ~o 4 1 o43E 4 1 ~ 'bft49 ~ ~ 4 ~ 2 ~ 49E 106 3 ~ qef>br 6.56E F06 COt 1 SN 0 ~ 5~ 4tf +Dl 0 ~ 4 '9E<br ~o totbf409 ~ ~ 1 o l3E ~ 06 ib 3, Oll 1 UCl/S G ~ "LEASE I'.ATE CF EACH 1SUTOPE lN INO I VALUE OF 1 FOR X/0 OEPLETEO X/0 ANO RELATlVE OEPOSlllOH

Ni 1- " 1 Ni UHl 15 Fnq C---t 4 AKO N- - 3 AFE t NWE I/YR PER UCl/Cu.<f TE%1

01/25/19 ctlVlNOllHENTAL PATHNAV "BOSE GONVEFSTOH FACTORS FOR GAScOUS 01SCHARGES PAYHllAY ~ FRESH AHO STOREO FRUl TS AHO VEGETABLES AGE GPOUP TffHAGER I:UGL10. OPGAH OOSE FACTO R S ISO ~ HETER NREH/VR PER UCl/SECI OCIIE L1VER TIIVR010 KlONE V LUHG G1 LLI SKlH TOTAL 800T Sll-123 9 ~ 25c 06 l>>53E Or 1 ~ ZZE 01 0~ Oe 1~ 33E 05 0 ~ 2 ~ 206 07 eM-126 7 '9E ~ 49 1.54fio ~ 4e53f ibr 4~ 6 ~ btf+or 1~ 02E < lb ~e 2>>54E ~ 04 cb 12>> l>>12fibb R>> 1 if 06 l>>66EI07 ~ R.rtf ~ 05 0~ 15fibb ~ ~ 69E+01 tfit 3.trfi09 I09 ~o 4 ~ CRE<07 '0E~07 58-125 2 '3E~OO 1 ~ t6E 107 1 R. ~ ~ t>>ORE 4>> 4 TE125H 1 ~ 44E~O ~ Se TOEID7 4 ~ 1 ~ f>07 4 ~ RREI ~ 4 4~ 4>>lvf I ~ 0 l>> 1~ 97'E ~ 47 Tc 127K bbf ~ 44 t ~ 56E>04 t ~ 03E iO ~ 56E>09 le 1 ~ 95E 409 4e blf ilr Tf 129'I l 134 3~ 3>>14EIOA 2~ SOEI05 t>>39ftbb 7>>64EF05 t>>20fib ~ 9 ~ 12E ~ 07 1~ te ~ OEI09 1>>19E i06 0~ 0~ 1 ~ 31E ~ 09 6>>55f F05 ~e 0~ ~ e 5 '0fi F1 3 ~ 0 ~ E>05 1--131 re 33E ~ 47 43ft ~ 4 2e99E ~ 10 34E IO ~ t>>96ftbr 0~ 6>>trf> 1--132 1- 133 3>>GSE ~ 1 ~ 9bf~b6 41 1~ 9 ~ 71 f ibt 3>> 36EI06 1 ~ 29f ~ 04 6>>tbfib ~ 1~ 1.56E iOR 4 '3E I06 ~e ~e ~~ 1~ 2 44E ~ ~ 1 '4ft06 0~ 0~ 3 1~ 'rfibt 04f f46 ~7 l--1 lv 6>>15c-05 1~ 43E 04 2~ 3lf 02 2 'RE-44 ~e 1~ 6lf 01 ~e 6 ~ 56E 45 1--135 2 ~ ASE ~ lv 1>>OOfi 04 9>>tSE>06 1~1 if 05 ~ relRE-OR r,ll foib I, ~ ~e 2-Srf F04 CS- I 14 6 ~ bvf ~09 t>>65E>tb 0~ 4 ~ 44E ~ l9 2>>40f ~ 09 t ~ 9bf ~ ~e 1 ~ 69f F09 3 ~ 25E ~br 04 13'1 9 ~ rbf ~ l6 l4l 9>>23fi01 CS 136 1 ROD Oe 1 ~ 1 ~ 46E ~ 01 ~ GS-137 9>>6bf~09 1>>31E>10 3 ~ 35E iC9 t>>73E>09 t.rCE ~ 0 ~ 4 ~ Srf 109 RA 1>>O C=-l>>1 1 '$ 2>>60'5 !~02 1 rbft05 t>>19E>05 ~e 0 ~e ~ 4 '2ft04 6>>25E >04 t.t3f I05 0~ 4 ~ 94E lb ~ 4>>brf >0 ~ Oe ~ ~ ~ >> 46E 06 2>>orf +44 i C= 144 S.vrfibr 2-25ftbr 4~ 9~ tr E I06 0~ 1 ~ 29E ~ tl 4~ 2~ 91f >06 FR-143 5>>20fibv 2>>02E F 04 0~ 1>>16E ~ 04 0~ 2 '9EIOO ~e 2>> 49E +43 HO-Ivr 9>>lb'4 3 ~ SSE 444 4 ~ 2.91fi04 ~e t>>45ftbb 0 ~ SDE >03 ~:Al: I 0:I I UGl/S.C 4ELEAi! KAI OF EACH 1 aITOPE lH AND A VALUE OF 1 ~ FOR X/4 ~ OEPLETEO X/0 ANO'EI.AT IVE OEPOSl rlON HCI= - Inf Unllb COR C---IV AHO H---3 AFE IHFEN/Vk PER UGl/GU NETCRI 01/2S/l9 EHVTRGNHEHTAL PATHNAT DOSE COHVERSlOH FACTORS FOR GASEOUS OTSCHAI?GES PATHIIA'V G tOUNO PLAHE OEPOSlT TON AGE GROUP CHTLO NUCL IDE 0 R G A H 0 0 S E F A C T 0 R S ISO.HETER NREH/TP. PER UCT/SECI PCNE LTVER . THTROTO XlONEV LUNG Gl LLl SKlH . TOTAL nOOT H---" I ' I I I ~ 0~ 4 ~ 0 ~ ~ ~ 4e 0~ C- 14 0~ 0~ 4 ~ ~ ~o ~o 4~ 0 ~ P>>>>32 Oe ~o lo 0 ~ lo ~o ~o 4~ CR--st 4 ~ 6df>06 4 'bfi06 4 ~ 6IEI06 4 ~ 64E I06 4 '4E~06 4 ~ 64E I 06 So53E >06 4 '4E+06 O'I>>>>54 1 ~ 31E 109 t ~ 3 ~ EI49 1 ~ 3%f ~ 09 1~ 34E I ~ 9 1 ~ 34f ~ 09 1 ~ 3IE ~ 49 1 6tf o09 1~ 34f ~ 09 Fc 59 -sl

t. l5E ~ 04 2~ l50 < 04 t lsf i0 ~ tol5E 40 ~

I tolsf >0 ~ t 49E> ~ I to lSE 000 1 09f > ~ I 3>>23E ebb Ilft~III tolsf >I ~ 49E 444 1 ~ $ 9E ibd 49E ~ 40 to I40 1 ~ 49E ~ ~ 2 ~ 1 e 49E ~ ~ ~ CO 1 >> CD- 54 3ehbf ~ 04 3>>IOE>0 ~ 3 ~ IIE~O ~ 3 ~ IOE 44 ~ 3 ~ ~ OE ~ 4~ 3ollf< ~ I 4 ~ 45E 3.40EIOI CO -60 2 ts=>10 2.15' ~ 2 ~ 15E ~ 1 ~ 2~ tsf Ill totsf~t ~ 2~ tsf 4 t4 toStf ~ 1 ~ 2~ tsf t 10 Nl --63 lo 4~ 0~ I ~ lo lN 65 Oe le 432 ~ Ob 0~ l>>43E >04 l ~ 43E Iob lo43E>O ~ 0~ le43E ~ 04 l>>43EII ~ ~ >>54EIOI l 43E>04 FO h6 9 ~ 01E ~ 06 9 ~ 01E ~ 06 9 ~ Otf ~ 06 9~ Itf>06 9 ' tft06 9 ~ OlE106 llf to03f~bl 9o ~ lE ~ ~ 6 tlfi04 54--49 2>> t lf i04 2ot lfi04 2 ~ tlE I 44 2otlf ~ 04 totlfF04 t ~ ~04 5 ~ 35E 406 2 ~ 5lf il4 '3E <46 2 I 46 cg>>>>40 5 ~ 35E i06 5 ~ TSE~06 5 ~ 35f ~ 06 5 ~ 35E <06 5>>35E <06 6 5 ~ 3SE >>>>41 lebhf 06 ~ tebbf<06 1 ~ 0%E ~ 06 t. ~ IE F06 goobf~06 1~ IIE ~06 1 et 2E II6 t. 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Gl LLl SKlN TOTAL BOOT SN 123 0~ 0~ 0 ~ I ~ 0 ~ I ~ 1 ~ 37E>46 4~ I'i-t?6 5.tdfitO I t6fito ~ 5 ~ 16E >10 5o16E F1 0 So)6filo 5 '6E ~ 1 ~ 5 ~ lef itO 5 '6f~t0 50-324 5 'df~04 5.40fto ~ 5 ~ 9OE iOI 5 ~ 90f F00 5 ~ 90E >OI 5 ~ 9OE ~ 0 ~ 6~ 901 0 ~ ~ ST 94fo0 ~ Sa-125 2 '05~09 to30E F 09 f 2 ~ 3 ~ 409 2 'OEA09 2 ~ 34f I09 2 ~ 3IEi09 2 ~ 59E tl9 to 30f t l9 ff 3255 to 55E ~ 06 toSSfi06 toSSE406 ).SSE i06 t oSSE >06 ).SSE i06 2~ l)f 46 ~ 1 o55f ~ 46 3 = 127N 4.79E i45 4 '92<05 I ~ 79E 405 I.l9E F05 I ~ 79f F05 ~ o l9E ~ 05 9ol4f 105 do79f <05 ff-1!3 129H ).OSE~O7 3 ~ OSE<07 3 '5E~07 3olSE t07 ~ 3ol5E <07 3 ~ ISf F07 4 52E ~ 07 3 ~ 05fo47 5~ 5)2 <06 5 5)fi06 5 ~ 53f f46 5.5)E i06 5 ~ 53c <06 5~ 5)f ~06 6olif 106 5o 53f ~ 46 ltE ~ Il ~ 1 1- 1 31 -132 1 ~ l tf ~ 1 ~ 25c>06 07 to72f ~ 47 1 ~ 25f F 06 1 oltE ~ 47 1 ~ 25f 46~ 1~ ltfF07 totSE<06 1 totSE<06 toltf407 t ~ 2SL F06 . t. ~ 9fi07 to47f F 06 t.ltf 1~ ~07 25E i 06 1 1--1 1) 2 ~ 4df >06 to44ft06 to44fi06 2 ~ Clf 406 to4lf ~ ~ 6 2 ~ 4IE 406 3'f<06 k'.40Ei06 1-1 --1 35 4 '4'5 2 ~ 56clo6 4 ~ 50fto5 2.56foo6 4 ~ 5 ~ E <05 to56E<06 I 50fi05 2 '6E>06 4 ~ 50E F 2 ~ 56E<IC 05 4 ~ SIE> ~ 5 2 '6EA06 S~ )SE ~ 45 to99E~I6 4 ~ SOE tlS 2o56f >06 CS 13~ 6 '9E~O9 6 ~ 9'9E 4 49 6o99E ~ 49 6 ~ 99E f09 6 '9fi09 6 ~ 99f 009 ~ ~ 15E ~ 09 6o 99E >l9 CS -136 l 1 ~ 49E ADO 1~ 49fi04 t ~ 49E F00 to49E40 ~ 1 ~ 49E ~ II 1 ~ 4'1E tOI 1 o69E 100 tlf 1~ 49E440 CS 1$ 03foto O)f>t ~ t ~ 0)E ~ 1 ~ lan )fwt0 toO)f~t ~ 4)EAll < 14 0)fit~ PA 140 3~ flf ~ Od 1~ 1 ~ EOE<04 1.6SE ~ OS to64E40 ~ t ~ 60f i ~ I 1~ to6IEII~ 1~ t o9IE i ~ I 1~ 60f <00 1 ~ 3lE ll 1 1 ~ Cf 1 1 37f Ol 37EI07 )lE~Ol to37E> ~ 7 54f <07 t 3lf ~ 07 tot)f ill 1 ~ ~ 1~ 1 ~ 37E ~ 47 1 ~ ~ 1 ~ ~ Cf 144 1 13E ~0 ~ t,t)ftoO 1 ~ 13E40 ~ tot)f i44 1 ~ 13E 4 I ~ 1~ 31E ~ 4l tot)E ~ 00 PR-143 Oo 0~ ~o lo ~o ~o ~ ~ 0~ fO 1>>7 S~ 4OE oo6 4 '4E>06 4 ~ 4OE ~ 06 Io40E >06 ~ o44E >06 ~ o4lf ~ 06 1~ Otf ~ Ol 4 ~ 44E106 >ASc0 0'f 1 UGl/SFG RELEA)f f RAfE fE CF EACHACH 11SOfOPE 1H AHD I VALUE OF 1 ~ FOR X/Oo OEPLETEO X/0 ANO RELAflvf Qf POSll)ON Dt/25/S9 EHVSRCNNEHtAL FA3NHAY DOSE GONVERS1OH FACTORS FOR GASEOUS 01SCHARGES PASNHAV - 1NMALA310H AGE GRON'fEHAGER NuCL lOc ORGAN DOSE F I G 1 os% 0 R S tMREM/VR PEF. UC1/CUeMflERl BONE L1VER 1Hf R010 . KlOHEV LUNG FACIE>06 ~ G1 LL1 SKlH 101IL 800M EH-125 Zel9E F 04 6.1CE~OZ C~ 92E402 4~ Se9tf>06 3~ 13f >05 ~ 0 ~ 9oZDE 142 SH-126 1.26Et46 SeSCEiDC 9 'CE I' Oe 9 '6E ~ 06 totlf405 I ~ 4 '4E ~ DC SO-1ZC 3.ttfiDC 5 '9E>02 lo55E F 01 Oo 2 Co06f <45 Oo 1 ~ 2CE ~ IC SU 125 6e6lf F04 lo 1 Sf~OR 5e4lf ~ 41 I ~ 2 ~ ROE~I& t ~ Itfi05 4~ 1~ SSE ~DC 3E 3250 Olf >02 le46f<DR t.tZE.DR le2Cf.104 5oSSE>05 7 ~ IIE ~IC I ~ 5o53EOIt 1= ltlM t. ZSE ~ 44 So&REaDS So29ft43 Co5IEIDC 9 '4E ~ 05 1 ~ 54'E ~ 45 Oo 1. 5ZE e 43 lc 12'9M 19c ~ 03 5e&CitOZ 94fi02 3 '6E<OC Ro03f.i06 S.ICE i45 Io le9tE F 02 1 134 CD 54f ~ 13 1.3CE> OC t.ZCE ~ 46 2 ~ 09ftDC Oo le &9E F03 4 ~ 5,29E <43 1--131 f 3 ~ 3 1 < 04 Ce 1tf ~ OC 1 ~ 39 44f &.tCE iOC Io 5 ~ 96E >IS Io ' 2oIZEIIC 1--1$ 2 te 16c ~ 01 3~ 2&fi43 C~ SIF oI5 5 '9E>03 Io C~ 0&E>02 I ~ ~ t&E~OS 1--133 le23fiOC te0&fi4C ISE446 60ftOC . 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DEPLflEO X/0 AHD ttfLAllvf OEPOSlllOtl Wulf - lui uttlls FGF C"--}I AtIO H----3 ARE lNREH/TR PER UCl/CU.NclERI ot/25/r9 FI<V lRONHEHTAL PATHIIAT OOSE CONVERS10h FAG'10RS FOR GASEOUS OTSGHARGES PATHWAY - HEA> ICONTAHTNATEO FORAGEI AGE GROUP - GH1LO NUGI. 10E 0 R G A N 0 0 S E F A C 1 0 R S lSR ~ Hc TER-HllfH/TR PcR UC1/SEGI 80NC L 1 Vfit TNT R010 KTOHET LUNG G 1-LL1 SK1H TO'TAL SOOT SN-123 4~ 0~ 4~ 0~ 4~ 0 ~ 0 ~ 0~ S4-126 6o 9ZEt 49 1 ~ 3rfi04 4 ~ OtE ~ 01 4~ 2 ~ 4tf >06 2 ~ 31E ~49 4 ~ 1 ~ '9 8E ~ 04 Sn-t24 le<<oi 46 te40E il5 1 el9E <44 0~ Sol4E ioe 2 ~ tof to ~ 0 ~ 2 '3E ~ 06 Sn-125 r.f ef ~ ~ 5 '9E ~ 44 ol leb4f 1.54fiO ill ~ t ~ 90E ior tofoc>04 6o41 f ~ 5 ~ 44f 104 Ol 9 ~ t6E ~ 00 ~o 1 ~ 44E ~ 0 ~ 5 '9f>44 0 4 ~ ~ 1 ~ oofior ro59E>or TE 125H Te ttlil 4.40ftoo 1~ stf>0 ~ lo24E<04 ol f 04 1~ llf c09 0 2 '4fc49 0 ~ 5 ~ 61E ~ 01 tehwc<49 5 ~ ttf<04 5 ~ llE>49 ~e R~ 21f ~09 4 ~ 2 ~ ~ 4Et4 ~ Tc 129H l--t 34 1--13l ae orf o 01 2 ~ 63E 46 3 '4f ~ 5 Rsf i49 44 1~ 4 '4E 9.46ft06 06 ~o 2 ~ ZSE-46 to34fc46 l ~ lo 43E 06 ll 1.5bi F 01 1~ 62E ~ 41 ~~ 4~ 1 ~ ZZE ~ 1- 13Z 0~ 0~ ~~ 0~ 4~ . 0~ 0~ le 1-- l II 6 ~ lef-41 4 4lc 01 to04E ~ OR 4 ~ 91E ol 0~ 3 ~ 43E ~ 1 ~o 3o33E-41 l--l t--t>5 14 4 ~ 4~ 'ef 0~ 0~ ltf lo Tl E-43 0 ~ 921'4 lo ~o )ZE-02 3 Zlc 42 '2 02 0 ~ 1~ OR 3~ 6~ 0~ 1~ Cs -I 14 4~ 43f~oo t ~ 49E<09 0 ~ to49e ~ ~ 4 1~ 65E F 0 ~ o04E ~ 46 ~ e 3 ~ 16E >44 CS 136 4 'tf>46 ter4f ~or 0~ 9e69fcoe 'e33ft06 1 ~ 9lE ~ 06 0 ~ 1~ Z5Eiol CS.131 21E149 t ~ 23et09 1 ~ 51E to ~ '4fi04 1 54E 006 ~ t 44f F44 ~ na-144 Gi 141 2~ ~ llf i a1 lof eo4 3 1 '4fi04 Ose>44 0 0 0~ ~ ~ 4 '9ft03 teesft03 1 Ro29E ~ 04 4 ~ 6 ~ 03E4 46 1 ~ 32E ~ 41 0 0 ~ ~ ~ 2~ sl f t 06 teSrfi43 rf -l<<4 2 ~ 3%E ~ 46 r. 4e f ~ os 3.tofi03 0~ 1 ~ 351 >05 4~ te94ftO ~ ll ~e 1 zrf>os 3"15't P%-I 1 96E i43 0~ I e44E F03 0~ 3 44E ~ 0~ I9 -I <<1 e.44E ~ o3 I 4lt~03 0~ 2 44E ~03 0~ t o53E Col ~e 3 'rf~ot co kn ON I url/SEG rELFall FATE CF EACH 1SOTOPE 1H AND A VALUE OF t~ FOR X/0 ~ OEPLETEO X/0 AWO RELAT1VE OEPOSlllON IHITI. - TH. Ul.lTS FO( C 14 AIIO H 3 Age tHREH/YR FER UGT/CUoHETERI II at/ts/r9 cNVIRGNHENTAL FAtHMAV-OOSE CUMVEhSIUN FACTORS FOR GASEOUS OISCHAGGES PATHMAY CONS MILK 1CONTAPINAlco FORAGEI AGE GROUP - CHILO IIVCL 10f 0 R G A H oJ 0 S f F A C t 0 R S ISO ~ HETER HPEIi/TR PER UCT/SECI 8CME L IVER THVRGIO KIOHEV LUNG Glriced LLI SKIH e0tAL 800V H 0~ 1~ 57E t 13 le575 t43 1~ aiof tl3 to57E F 03 lo57ct43 0~ 1-57ft03 C---I'o 3~ DbftDS 3 ~ ab Et OS 3 'SEt05 7 ~ 75ftah 3e44E ~ I5 3'Etas 4 ~ 3.14Et05 P---xt teb2E ~ 14 t. ttift09 0 ~ 0~ I ~ 2 '5Et49 0 ~ re 05Et 44 CR- Sl .1 ~ 4~ 1 ~ 42f. tate 6.72f ~ 03 4 ~ Oaf ~ Ot re66Ct46 0 ~ 3 '5E ~ ai HN--SS 0~ ~ o96f.t 46 I ~ to67ft06 Io 4 0 ~ to 71E' 06 FE--c9 4~ 17E ~ 17 7 52ftar ~o ~o to09Et47 2 ~ WIE ~ ~I ~ ~ te46ftar CO 1~ 1 ~ 36Et06 0~ 0~ ~o 3eL6ftar 0 ~ totrEt06 C3--54 ao 1 ~ 25ftar ~o 4~ ~o r.t tf tar I~ 3 ~ 76E t 07 Co-~0 I'I ~ 0~ 4~ ttftar 0~ I ~ ~o to33E ~ Il 4 ~ to 27Etll 63 7 160 t09 ~o97Etal 4~ 4 ~ ~e 1~ abfta ~ Oo 2 'D Et04 7 1--65 06 1 ~ %6cta9 4 '5ft49 77f ~ a9 0~ 3 11E t09 4~ t 93fta9 sita ~ 0~ to llf 09 ~ FB De 2~ 0 4~ ~o 5~I 29E l9 S9 -09 6 ~ 92f o19 0~ 0 ~ ~ ~o I ~ 2 '0f ~ ~ I ~~ lo 1 o ~ lo90Eta ~ SR--91 t. t3E ~ 1 t 1 ~ 4 ~ ~o I ~ 1~ 52Et49 ~~ 2 brf tl ~ v---91 3e baft a% 0~ 0 ~ ~e 0 ~ 5el5Et06 ~o 1~ Dlf 1 03 -95 16E ~ 15 Aebrfta4 le tob6fta4 0~ ro6IE t47 I~ 3.29E ~ ai Mo -95 FU 113 1~ 2 75c ~ 15 3 ~ 99E t13 1~ 14Etas 4 ~ to ~ Iteft44 t43 ~o 2 '3ftl le ~ 5ft05 ~ I ~ 0 ~ 63Et4ly 1~ 4 ~ 0 ~ 16E ~~ ~ ~ lo61E ~ 03 FU 1 ilo 9 39fta% 0~ 0~ 4 ~ 20E tatt ~o I e%6E t06 ~o 17E tai AG 111'I 6 ~ 215 ta7 ST 7Sftar 4 ~ 1~ 13c tl~ 0~ 2 ~ 35E ~ 1~ ~ ~ 1 ~ 3~I tf ~ 47 CO11SH 4~ 1~ 33E ~ 16 0 ~ 1~ 05ft06 ~o 5.cIEtlr ~ ~ i ~ tbctai "4'..=9 GN 1 UCl/5:C RELcASE RA>f OF EACN ISOtoFE IH ANO 4 VALUE OF 1 ~ FOR X/O. OEPLEtf0 X/0 AMO RELATIVE OEPOSI't toll Not=. THE UNITS FOR C . -14 AHO H 3 AIE IiifcN/Y I PER UCl/CU 'IE TER I 0 41/ZS/79 cttolHOHNE HlaL FalNIIAV-DOSE COHVERSlOtt FaC10 ~ 7 8-125 3e 1 3E <47 1 ~ 41E ~ 46 1~ tbf i06 3 ~ 96E 146 2 '3f<09 2 ~ 43E I 00 I ~ 5 '9E>06 1E }75tt 7~ 3bf <07 R. ~ ~ Ei07 2 '7E>07 7 ~ 05fto7 ~e 7 ~ tzf >07 0~ 9ebhf F46 3E}27N 5 ~ tbf ~47 le7bf F47 t ~ 46EI07 2 ~ QIE<0 ~ 4~ 2 ~ 99E col ~e 6 60E o46 lf l--l}29'I Ze 77E ibl 7 ~ 73E 4 07 lebSEi07 Re70fiob ~~ 3 ~ 33E c ~ I 4~ '4 ~ Rbfo07 $4 4 ~ Sef F05 1 ~ 35E ~ 46 1 ~ 7tf<0 ~ ze09fi46 I~ le l5f 106 le Se 29E > IS 1- }31 } ~ Zvf>49 }.27ft49 4 ~ tzf bt 7e5IE-01 I ~ ~ e 93E ~2 I ~ 1~ 69E 01 l--133 }.7tf i 47 2~ ZQE407 5 ~ 3QE <49 1~ 29E<07 ~e I ~ 90ft06 ~e I ~ 63E~ ~ 6 l--}34 te46E-49 I l--t 35 CS -134 4~ 1 2 '9'4 '7E>to 0~ 3 ~ 94 E404 1 ~ 65E F 14 5 0 ~ ~ 15E ~46 ~e 6.26E i44 4 ~ 65E i49 4~ 4 ~ 47f-02 4 '6E>09 1 ~ 4 ~ 41E ~04 ~ 97ftob ~e I~ 4~ 0~ 7 1 44E~44 76EI09 CS } I6 2~ 7bf~ob I e I IEI09 I ~ 6ettEI04 be37EI ~ 7 ARSE>0 ~ I ~ 90f ~0 ~ CS }.%7 3 ~ Obf~}0 2.94E ~ tO ~e 3 ~ 6ljf <49 3 ~ 49f >09 t ~ Itfiol le . 4.44f ~ 49 BA-}~4 } }7E~OI ~ teozf>05 I ~ }.zzf F04 6 ~ l9E 104 7 'SEc46 4 ~ 6. 44f i46 C }41 }.Zhfto5 6 'zftoh 4~ 9 ~ 72E F43 0~ 7 ~ bof F47 4 ~ 9e 26E< ~ 3 C" }44 te'Qof + 07 3.14EI46 4e 5 ~ 676' 45 I ~ ~ e}Sf~I ~ 0 ~ 5 ~ 34E F45 FR-}ot 0~ 3 ~ 92E cot I ~ 7 41f F45 I ~ be 44E440 HO 147 1 ~ 2}f~42' } A t9E>42 4 ~ 7 ~ 21E 401 ~e 5 '3ft05 4 ~ 7~ btf ~40 'ASc') CN I UCt/SEC 4ELcA 1 RAIE OF EACH tSOIOFE lH AHD A VALUc OF 1 FOR X/O OEPLE1fO X/O AHO RELA1IVE OEPOSl11ON tlot= 1N= UllllS F04 C --}4 AHO N-- 3 AFE }NIIEN/VR PER UCl/CU HE1ERI 01/25/r 9 6 HVlROHHEHEAL PA1HMA V-OOSE COHVEPS10H FAGlORS FOR GASEOUS 01SCHARGES PATHIIAY FRESH AHO S10REO FRUllS AHO VEGEEAOLES AGE GkGUP - CHlLO >>UGL lDE ORGAHOOS E F A C 1 0 R S ee ace %e e %e%e\ lSO.HflfR-HREH/VR PER UGL/SEC) 90HF LlvfI lHVR010 K10HEY LUHG Gl LL1 SK1H lorAL 40OV H- 0~ 3 ~ 94E 4 03 3 '4c F 03 2 ~ &ZE ~03 3.94fi03 3 '0E~43 0 ~ 3e 94f ~ 03 met4 6 'ec~05 6 54cIOS 6 ~ 54E IOS 65E I 45 6.54ft45 6 ~ 54f <05 54f ~ OS CR 32 51 re.II9E F 4 ~ ' 4 ~ 94E ~ 4~ lr 0 ~ to 14E ~ 04 1~ 4 ~ rorbfi03 lo 4~ 6rf i04 ~ o4rE ~ Or ~ e 44E ~ 46 4 ~ ~~ ~ ~ 6 3.45filr 3o 51E ~ 44 HII 54 0~ te04E t04 lo 4 ~ 45f ~0r le 0orlfi00 ~o 5.42E~01 FE -59 1.05E~04 2~ Slf 444 0~ ~o 6 ~ 95f tlr ~ o26f 000 0~ 9 ~ 52f ~0r co-Sr C~ t. l6EA4r 0~ 0~ 0~ 2 '9E< F 4 '4f< F 4 ~~ t.rrfilr CI3 54 4 ~ 6 ~ &2EI lr ~o ~o ~e 3 ~e te 0E~00 ~ CO- bl 4o 3o&9E ~ 0 ~ ~o ~o ~o tolSEA09 ~~ t-1 ifi09 >>l--bl 9 ~ 54f I 09 6 ~ btf >4 ~ ~o lo ~o io3lEA04 ~~ 3. ZOE F40 rH>>-65 2 ~ 4$ c ~ 40 9e 1 tf iC0 ~o 6~ tlf>0 ~ 4~ 5 ~ rSEAll 0~ 4o 13E ~ 04 gII we Ib 0~ te43EI ~ 4 ~o ~o l 2 'tEAlr ~o 6o 66E ilr SQ--$ 9 Sc ee90 3o 1~ r6Eo 26Eo ll 1 Z 0~ 4~ ~o 0~ ~o ~o lo ~e ~ io44EA09 2 '4EA10 0~ ~e 1 3 '4E>09 '9f~tl V---9i 1~ 42E ~ Or 0~ 0~ ~o lo 2 '2E~09 0~ 4~ 0lf <lS rq--95 4el5E ~ 46 1.09fi46 ~o 6.33fiOS 4~ 1~ 32E>09 ~~ 9e43E>05 HQ -95 3 ')5~0 te5tf>05 4~ 6 ~ 24f 444 ~o 2 ~ &ZE>00 ~~ 1~ ttf~45 PU 143 45f ~4r 0~ 0~ to 51E>Or ~e 3 Otf<44 4~ 5o 46E ~ Ob FU 146 AG114H 1 ~ r.Srfo44 9 ~ & let 46 4~ ~ o49f ~ 06 0~ le 3 ~ 34E All t.rSE>or ~o to 10E < 3 ~ 63E ~ ll l9 ~~ 9 '2E>0r 5 '9E>06 ~e ~e CD l I fn 4~ 4.2&fior 0 ~ 3ollEAlr 0~ tor9f >09 l ~ 1~ 36E<06 4'.-.0 OH 1 UGt/5 EC IIE Lf ASE RA. f OF EACH 15010PE 1H AHD A VALUE 'OF 1~ FOR X/4. OEPLflf0 X/0 AHO Rf LArlvf OEPOSlllOH

>>Il. - 1II: >>>>llS FGQ C --14 AHO H-- -3 AFE IIIlifII/VRPER UCl/CUo'IElERl

11/z5/r 9 ENV tRCtlHE N1AL FAT HttAV-OOSE GOtlVERS10N FAGlORS FOlt GASEOUS 01SCNARGES PAtllttAV FRESH AHO SlOREO FAUltS AHO VEGE3ADLES AGE GROUP GHlLO tiuCL10" 0 R G A H 0 0 S E F I lG 0 R 5 lSO Hclftt-HREH/VR Pf R UCl/SfC1 w 'pw&oo o &%oooo \%\Do& e% o+%%%%%o'%oooo BONE L1VER lttf RO10 KlOHEY LUHG Gl LLl SXlH 301AL 8001 SN-1?5 SN-126 le llf 6 '95~09 15 Ze 14E" Gl te?Sf<00 2 ~ ?6E Ol 3 ~ 66E tol 0 4 ~ ~ ~o 4~ 9tf tol 4 ~ 5IE D6 4 ~ 33E t09 ~e ~e 4 ~ 21E Zo06E tbi Il 50-1 2<< 4.905 t Dl 1 ~ 60Et06 2 ~ tSE>45 ~ ~ 6e90ftOr 2 ~ 5?ft09 I ~ 51f ~ ot 59-1?5 2 '4E ~ 04 2.46E ~ Dr  ?.Ioftir 9.4lc tor to 6?E tt ~ 1~ 46ft09 I ~ 4.44foor lc 1?5tt 3 ~ SOE ~ 40 '1 ~ 5 0 Et or 9.44Etil 3 '5Et04 ~o 3 ~ 3bf tb ~ ~~ 4 ~ 6r E ~ Il lc 1? ltt lf. t?QH 3 'SECTOR 4 '9fto ~ 2 lent?E ~ 04 '?Et ' 9 15E 2~ tir rrft~ 4 to?6E t09 I ~ 43ftob ~o 0. le 4l f ~ 09 to 45E <09 ~o ~o 4.14E 1~ ~ Il 34E t ob 1 -130 le6DfiD5 4 13ft05 6 ~ 0?E >Il l ~ 35ft05 0~ ISE tiS tIl ~o 1 ~ 46E405 1--131 36ftob t ~ 39f <00 4 ~ 5?E t 10 ~ .4bator I 19E 4 ~ 05ftbb t--t 32 1- 133 2 ~ 26E ~ Ol 3 'tft06 6e45ftOt 4 ~ 46E t06 l 9lobft09 ~ 1 ~ f >03 9o65ftot 2.6? f F06 4~ 0~ ~ 1~ 1~ 1 14f tit eitf ~ 46 ~~ 4 ~ 1 2.15ftbt terSEt06 l--t3<< 4othf-GS 1~ 14E" 14 1 ~ 4lf 02 to ~ lf 14 I ~ 9 '9E 0~ 0 ~ 4 '6E-DS 1--135 e64Ee14 4.33f t04 5 6l f ~ 46 6 ~ 49E 114 5 ~ l5E-DZ 4.05ft04 ~o 1 ~ 59E ~ 44 CS CS-136 134 1 1 54ftt4 2 ~ 23c ~ Ol 2.59f~to bobof tor 0-4~ ~ 3 29f t09 4 ~ 90 E t or 2 ~ 44E t 09 6ol?E t06 1 ~ 44E toi 40f >Ol ~o ~o 5 '1f tol09 6 ~ 34E F 1 ~ CS 13l 201 F 11 2~ 2lftlo 0~ 2 ~ l?E t09 2 ~ 59ft09 ~ 1.34t ~ Oo ~o 3 ~ 29E F09 RA-140 ?e l65 tbb 2 ~ 54Et 15 ~~ 2 ~ 09f t04 t.44f ~ 05 3 ~ 60E t ~ I I ~ te 6?f ior CE-141 6 ~ 21E >0'5 3etbf>05 0~ 4 '5E F 04 ~~ 3 '9fto ~ 0~ 4e6?ft04 Cc-144 1 ~ 3tf <Do 4~ tOE<or ~o ro39ft06 I ~ 1 ~ 46Et ti ~~ 6o 9l f >06 PR-t<<3 3.4bftb4 t.40ftc4 1~ 4.03ft03 I ~ to5?E>0 ~ . ~~ 1~ l?E ~ 43 tiO-14 l lebtit04 Ze46ft14 0~ Ze 1 lf ~ 04 ~o 9~ oiftir 3.40E F43 AttO A VALUE OF t FOR tt/Ot OcPLElf tlOlr - Tttc UtlllS FOP C---14 AtlO H - 3 ARE tNGE't/Ytt PER UCl/GUoHElfRl ot/z5/rs EHVlROHHENTAL PATH@AY-DOSE COHVERS10N FACTORS FOR GASEOUS OTSCNARGES PATH>>>>AY - GROUND PLANE OEPOSCTlOH AGE GROUP - >> LHFAHT t>>UCL LOE 0 R G A H 0 0 S E F A C T 0 R S LSO>>HETER HREH/YH PER UCl/SfCl ROHE LTVES TNYROTO KTOHE Y L.UHG GI-LLl SKTH TOTAL 800Y I>>-- 1~ D~ Oe 1~ 0 ~ 1~ 0 ~ 1~ C-- L4 0~ 0~ D~ 0 ~ 0~ ~e 0 ~ 4~ r---3Z 0~ 0~ 4 ~ 4~ ~e ~~ ~ e ~~ CReect 4>>ebf<<16 4 'DE<<06 4 '0E<<16 4>>ebf<<06 4 ~ ebf<<46 4 '4E<<06 5>>53E ~ 06 4 '4c<<16 I".L -e 54 1 ~ 01K <<09 t>>3 '<<09 1 ~ 34E <<09 1.34E <<09 1 ~ 34E<<09 1 ~ 34E t 09 1 .etf<<09 te3DE<<09 Fc--59 t e rSE<<04 ter5E<<0 ~ t ~ 75E<<0 ~ terSE<<0 ~ t ~ r5f<<04 ter5f <<04 3>>tlE<<4 ~ te r5E<<04 L'0 5r Fh 1~ 09c<<14 l>>89L F 04 1 ~ 49E<<0 ~ 1>>49E <<Dl 1 l9E<<ll i>>09f <<ll t Obf ~ I ~ << to 49E <<04 Ca IDE<<14 3>>44F<<44 3 '0f<<44 3 'IE<<4 ~ 3 ~ l4E ~ ~I 3 ~ DOE <<44 4 ~ 45E <<ll 3>>44E ~ 4 ~ CO-eo Hl 63 tet5t<LO 0~ te 15E ~ 1 ~ 0~ t Io ~ 15E<<tl t 0~ ~ 1SE <<1 ~ totSE<<t ~ ~e

t. 15E itD

~e t 5tf<<t4 0<< te 15E ~ 4~ ll zH--e5 r.43E ~ Db r.43f <<01 7 ~ 43E ~ Dd 7.43E <<0 ~ r>>43E F 0 r>>43E <<~ I 4 ~ 54E<<bl r.43f <<01 >>'8- h6 9~ 1lf <<16 9 ~ 0 1c<<16 9 ~ Otf <<06 9 'tf>46 ~ 1E<<06 telrf <<04 9~ Ilf ~ 16 t>>03E<<Dr 9>> Dtf <<06 SR--d9 t. t rE<<04 tetrf<<14 t.trE <<14 t trf<<04 tollE<<04 2 '1E ~ 44 to 1rf ~ 04 R- 5 ~ 35E<<16 5 '5E<< 16 5 ~ 35E ~ 16 5 '5E <<06 5 ~ 35E <<06 5 '5f ~ l6 6 ~ 33E <<46 5>> 35f ~ 06 Y---9L tebdf<<16 t ~ 1 ~ E<<06 1 ~ 14E<<06 l>>OIE<<06 1~ Olf <<06 1~ DDE<<46 1 ettf <<06 1>>0bf<<06 1% -95 US--95 5 ~ Dlf <<Ob 5~0 1f <<bb 5 ~ 41E <<04 5.41E>0 ~ 5. ~ lf<<04 5~ Itfcl~ 5.46E <<44 6tf<<0 ~ 5>>ltE<<04 t ~ 36f<<14 1~ 36E<<04 1 ~ 36E ~ 04 1~ 36E<<0 ~ 1 36E<<4 ~ 1 36E<<44 1 ~ 36f <<04 RU LU Lbe LOt 1 ~ LDE<<14 4 ~ 19E<<14 1~ 4~ 10E<<OD 19E<<4d 1 ~ 11E <<04 4 '9E<<04 1 ~ tlf<<lb 4>>19' ~ 1~ ~ 14E ~ 4>>19E ~ 40 44 1 ~ 4~ llf<<I 19E<<ll ~ t ~ tbf<<44 5 '3f<<44 1~ 1~ 1 lf<<04 4 ~ t9E<<04 AG 111H T~ 54E<<09 3>>54E<<19 3 'bf<<09 3 ~ Sbf <09 3 ~ 5 ~ E<<09 3 ~ SIE<<09 4>>trf<<49 3 '4E<<49 C9115'L 1~ 0 ~ 0 ~ 4~ 4~ ~e 0 ~ 0~ 'Ac c>>>> 0>>l 1 UCl/ScC>>LELcASE L>>ATE OF EACH lSOTOPE 1H AHO A VALUE OF 1 ~ FOR X/0 ~ OEPLETFO X/0 AHO RfLATlVc OEPOSTTlOH OL/25/79 ES VLRQHHEHtAL FAtnHAT-OOSE COHVE KS10H FaCtOrS FOR GASEOUS 01SCHAIKGES PATNHI l - GROUHO PLANE OEPOS11'loH AGE GRr UP - tSFAHT s uCL toe 0 R G A IS 0 0 3 E F 4 C 1 0 R S LSOoNE TER-HLEH/'fl PCR UCt/SECI OOHE L1VEr tssYR010 KTOHEY LUNG G1 LL1 SK1H TOTAL OOOV Sn-125 4~ 0~ 4 ~ 4 ~ 0~ 4 ~ 1 .3rfto& 4~ SH-5 ts S.L6c ~ LO 5.1& Et 10 5 ~ 1&i t14 5 '6Etto 5.1&Etio 5~ l&ctll 5 ~ Tf f tt ~ 5ol6ctti Ltw 5 ~ 946 ~ Ob 5 ~ 94Et44 5o9bf t44 So94Eta ~ 5o9bctO ~ 5 ~ 9IE t Ol 6 '4Eta ~ 5.9ectl ~ SB-Lti 2~ 50i ~ 09 te34ft09 2.3tft09 2 34ft09 t 30E to9 te30ftD9 2 59f tD9 2o 34f t09 tf 1250 1 ~ 55i ~ 46 1.55E ~ 06 1.55E ~ 46 1.55ft06 t.55E ~ 06 1 ~ 55E ~ 46 2 13E ~ 46 1~ 55Et06 t= LtrH ber9cta5 ie79ct45 I 79f t05 ~ .79ct45 lor9E tD5 79ftD5 9 '4it05 bo79Et05 3.05ftor 3. ~ Sc ~ 07 3. 05E ~ 07 ' SEtir '5Etlr 4.52E 3.45'7 1= 529is 1--1 33 1--1 lt 3 ~ 45E 5 lortct47 ~ 53ft06 07 5o53ftD& 1.72E ~ 47 5 53E ~ D6 1 ortctor 5 ~ 53f ta& 1.72EtaT 3 'ST 53Etl6 1~7 tf tlr 5 3 LEt46 1 ~ TtEt AT 6 2 '1'6 '9ctor ~ OT 5 ~ 53E 1~ tl6 Ttf~ 07 1--132 1.25fta& 1~ 25EtD& 1 ~ 25'6 le25f, ~ ~ 6 lot5Et06 1 ~ 25E ~ I& 1 oCTEtl6 t ~ 25ft06 1--133 2 '4Eta6 2.CIA 06 toC ~ Eto6 2.40ft06 to4 ~ Et06 2 ~ CIE t46 3.01E t06 2.4 ~ E ~ 46 1 -53w 4 'oft45 4 'ilft05 4.50E ~ 05 4 'OEt45 4 'aft45 4 54E ~ 45 5.35Et05 4 'aft45 1 -135 2.5&f ta6 2.56Et06 2 '&E ~ 06 2.56E ~ 06 2.56ft46 2 '6E ~ 46 2 ~ 99E tl6 2o5&ft46 CS.13h 6 99E ~ 49 '9Eta9 '9ita9 t09 6 ~ 99f t09 6 '9Et09 ~ e15E tl9 6 ~ 99it09 CS-1 36 c -137 1 ~ 49i ~ Ob lf

1. 4 ~ Lo 6

1 e49f t Ob 1.43Etto 6 1 1~ '9'4 43c ~ Lil 6 ~ 99E 1 ~ 03E tll LE 49E F 04 1~ 1 ~ 49f 03E tll ~ LO 1 49E ~ 44 1 ~ 03E ~ ll 1 ~ 69Eto ~ 1~ 2IEt tl 1 ~ 49Et44

1. 43Et la AA-LCO 1 64c ~ 44 1,64Et ab le&iftal 1 60ctai 1.6if tlb 1 ~ 64E tel 1 90ftii 1~ 6lf tel Ci-Lht 37i F 07 37c ~ 47 t.37Etor 37ft47 t.3rEt ~ 7 37Etlr 1.5CE F 07 37f t47 Ci~thh PR" 545 1 ~

1.13ftOI 1~ t.t3EtOI 4 1.13E ~ 04 0 1 ~ 1.13E toi lel3Etil 1~ 1 13E tol 1.31E tll 1 ~ le 13Et44 0 ~ ~ ~ 0 ~ ~e ~o ~~ 4~ HO-Lir I.hbf tb& 4.44fto6 4.44ft46 I Cef to& ~ .4 ~ Etl& 0.40'6 1 oitEtlr lohifte& ~ laSio OH 5 UC1/S:C RiLEASE RATE OF EACH 1SOTOPE 1H AHO A VALUE OF 1 ~ fOR X/4 ~ OEPLEYEO X/0 AHO RELATlVE OEPOS1110H 41/25/79 EHVtgOHsIEHlaL PAJHNaf OOSE COHVERSloH FACTORS FOR Fsasfous 01SCHAPGE S Isa lHIIAV 1HsIAL Al 1 OH Arsf CROUP 1HFAH7 HUG LEOS OHrsaHOOSE FACTO R S EHREH/YR PER Ucl/CueHElf01 eeee&Q\eeooeae\oeeeeeeeeae\eeee aaA IICHE L1VER THOR Clo K10HEV LUHrs rs1 LL1 SK1H 107AL QOOV 4~ '46143 4 '0E<02. 4otIlt 03 4e30E F42 4etIfi ~ 3 t ~ IIE tOR ~ 4t 4 '0ft ~2 4 '01 ~F2 I~ 4 305 iOZ C 14 5 Se90E 4.ROE' 3 4 ~ ZIE403 ~ ~ 4e ROE 103 P - lt Ze 3tfi05 te 15EWI+ ~e ~e ~e te5lft04 ~~ ~ e70E~ ~ 3 re-St Oe ~e 1.04E~It 3 ~ 99E F 00 Ro52E>03 5.0tf ~ 02 ~e 1~ 75EOIt IsH e5ss 6 '3E403 t ~ 72E 403 te45f ~ ~ 5 1 3$ fi04 10f ~ ~ 3 F-CQ- 57 59 ~e te46fi43 I ~ 4'EII6 1~ 2 tf402 ~e ~e ~e ~e ~e te70fi05 6e47E ~ 04 3 '9'4 5.5if F03 ~~ I~ ~e 1~ to 05E+03 tetOE<02 CO 50 ~e telIE>IR ~e ~e ~ e79E<IS 1~ ttf404 ~~ te60fiIZ CO 6I 0~ I ~ 4IE<02 I ~ I ~ 5 ~ 57E ~ 06 3.20fo04 I~ 1 ~ t7E ~03 Hl --43 7 56E<44 t.IIEET 5.49f t ~ 3 ~ ~ I ~ 3 ~ 1RE F04 t.34E ~ ~ 3 I ~ 2.53E F 03 7H-45 5 '7E~03 t ~ I tf404 I ~ t.2 ifi04 le53E iIS 9 '5E> ~ 3 ~~ I ~ 15E ~ 03 r t--s6 I ~ t.37E 104 ~~ I ~ ~e 2 '1E4 ~ 3 ~e te ~ 3E<04 Se--09 4 ~ l1f ~ 44 I ~ ~o ~e to31E >06 6 00f <04 I ~ te24E~03 Estee)4 1 ~ 3tfo97 0~ ~ ~ I~ te53E407 1 ~ 39E ~ IS I ~ 4 ' 6'E~05 gee<<91 5. IOEi44 Oe ~e ~e 2 63E ~06 7 'lfi04 ~~ 1~ 64E ~ 03 7W--95 44 2.73fo43 I ~ 9 '0E~03 1 ~ ~ 1E ~ 06 1.4tf ~ 04 Ie 1 ~ 95E~ ~ 3 H9--95 au 143 1 20! 69E F 02 5e75ft02 I I ~ 1 ~ 3SE F03 Rft03 4.77E Se66E ~~ 5 1 ~ ttf404

i. SIE i 04

' I ~ 3o 37f i '5E It 1 0~ ~ 1~~ ~ ~5 ~ 5 ~ 41 fU-106 9e 31E o43 4~ 0~ Re34f ~ 04 1~ SIE < ~ 7 t.76f F05 ~ e le 14E043 AGttOH 09fi43 1 756>43 I ~ 3e44E003 ~ ettf >05 5.29fi ~ 4 ~~ t ~ 04E ~ ~ 3 CD 115H 0 ~ 3 '4E ~ 44 I ~ Re77E~04 2 '6E>05 6 ~ 72E 104 ~e 1~ 1 if103 ,S-.q CH 1 uCl/SEC HELENA".E ISarE OF EaCH tSOlOPE lH AHD A VaLuE Of t. FOR X/4o OEPLflfo X/O AIIO RELA71VE OEPOSlilOH ~ lluCL lul: . 0-l?3 50-3 26 <<0-1?C cist o5 1 c 125H )c ttlH l c 129H ) 130 ) --151. ) e~t 32 ) oat 33 1--13~ ) -t>$ CS-13C CS-1)c CS AA -13l th0 CE-1st Cc -tCC Fc-tC5 Pi 3HNA'T 5~ 50HE ttcoCC ?o?tf ~ 05 5oCEct03 t.16ct?C C.5CE AD? 2 ?tEt03 t.3?c 4 '?ftit 3o63fo4C ~ 2 ~ Qlct4?

1. )Cc ~ QC S

1~ ~ 03 13c ~ 0? 14it42 C.eai F 05 6.05? ~ 43 6.eei 2 52 o03 ~ 0$ 5 ~ 14E t 03 C ~ 64c ~ 05 6Cit03 )HHALA1 100 6,C5i 5 1 5~ 3 2 ~ 0<GAH L )VER '5ft03 ~

t. ~ 3Etit 1,25ft42 95Etit 9o43ft42 5oiif 42 2 35ct43

~ C ?lt tie F littit 02 9)f t4C 02ct 1.??ft43 0.25ft05 '6Et0C 02 ls.?13tcEt 6504 ~ 1.55c ~ 03 1 42it il5 6o5lit02 le EHV)RGHHE HfAL PAf HHAT Aa)SE COHVEHS)OH FACfORS l 5)f $.~ 4 4 4 4 4 1 ~ l.6lf OOSE )HTRO)0 6.CSct0? l.l2E 03 S.l5E ~ .C.66ft06 C.Q?EtQC 2~ ~ ~ ~ ~ ~ ~ .1 ~ 3?Etil )Evil ~ ~ 1.6si ~ 45 4 ~ Qt it QEtit 3 ~ 4%ct4$ etc'l~C 0~ 4~ 0~ 0~ to ~ FACl 0 K)AHET llf t43 oilft ~ 3 6olif ~ 43 3 '$ Et43 t.irftia 9o49ftit C.%SEE 43 Ioi? f ~ ilt 1~ 1 ~ 95Et43 5 ~ QCE ~ QC SiftQC 3 '9<<tQC to93Etii 1 ~ lie t03 1 Cif t4% 3. ~ lif 42 ~ R S ~o 4~ 4~ Il ~ 4~ '0 LUHG 5 ~ 61E 1.6CE t46 Co 3.i%Ed 45 Wo96ft4% 1.6 ~ 4$ lo ~ 4~ loilf 05 tolift03 9.CSE 1 5.?CEt45 lotlE til t46 34i t ~ 5 '.3ct46 ~ ~ QV 6I E ~ 46 9tftQW FOR GASEOUS 01SCHARGES IHMiH/TR Pca UC)lCUo HE1cRI \ o o&o o% 9 3 % 'o'o%% '%'o o% G1 LL1 5 ~ '39f t4l 2 ~ 2)f t44 l.ttEtiC lo16ftQC 1.36f tQC ?.ftftQC 1.3?ftQC lo3$ E F 43 1 ~ Qlf t43 l.ttEtil ?.tif ti3 toNE 1~ lictit l ~ 3?f ti3 3,44Eti3 toi6c ~ QC 1 6)ft0% '4ftQC il 3lf t ~ 3 2.4<ft43 AGE GROUP o %% &\wo oo o o A 4~ ~~ 4~ 4 ~ 4~ ~o 4~ ~o 4~ ~o ~o ~o 4~ ~o ~o ~o 4 4~ 4~ ~ ~ o SK)ii )hFAHf \\ 01I?5/l9 )01AL 800Y 1.0?ft03 ~ oC4ft43 2 'lEt03 2 ~ 3?E ~ 43

6. 16f

?. lCE ~ 9o?5E it to%)f t 2oi)c it 5~ 1~ C,Stftit l.3?Etio C~ 2 til to06f tit ~ ~ ilct03 viftit 1,95i ~ QC C1Et46 95Etit lo ~ lEt42 2 C')ED 4C io 11Et41 it QC 6 '3ftit 1 ~ CD 00-1 9 ~ 2 3c ~ 0? 1 ilft03 ~o 3.4eitia 3.4?EtiC 4 ~ 6 ~ 34<<til nl 1 u )TS 4 "':LEA'C Riff CF EACH )SOfDPf )H AHG 4 VALUC Of 1 ~ FOli X/4 OEPLEffO XIO illA RELA1)VE OEPOS)110ll 4 l/25 ct..V TRCOIHEHTAL FATtWAT-DOSE GOHVERS10H FaCTORS FOR GASEOUS PTSCHAFsGES PATHIIAT COstS tslLst tCOHTAHlttalc9 FORAGE) AGE GROUP - TNFAHT HUGL lOF ORGAH DOSE F ACT 0 R S lSQ DIETER NREN/TR PE R UG1/SE G1 tsCtif L lvER THTROTD KTOHET l. UHG Gl LL1 St(TH TOTAL OOOT H -lo D~ 6>>55co45

t. 31Eo43 6>>55EOOS 315 6 SSEo45 Ill l 44f

~ 1 ~ 156 ~ 03 o04 2.31E ool 6.55colS 2 ~ 31E o03 6 ~ 55colS 4 ~ ~ ~ te 31EO43 6 ~ 55f o05 P l. Stf o 10 l ~ 14E ~ 09 4~ 0~ ~e tol5f ol9 4 ~ 1 '5fo ~ 4 Cgrrft 0 ~ ~o t.ltfoos 6 ~ ltco03 4 ~ 04E ~ 04 66fol6 oil l ~ 3. DSEol4 HH r>> 54 0~ ~ e96E ol6 ~o 2 ~ btfo06 ~e te14E ~o le 1lEo 06 FE --59 De l1=oD1 1 '2E ~ 07 lo ~o 2e ~ 9E ~ 01 to40foll 0 ~ te 06E o 01 CO 51 4~ le 36fo46 ~o ~o ~o 3.46fo F 1 0 ~ 2 21fo46 C)>> c) Qe 2 ~ 55Eo 01 0~ 0~ ~o 6 '0Eol1 ~ ~ 6>>24fo01 CO->>60 4~ ~ 13fo01 ~o ~e ~o tol6f oil lo 2.09fo ~ 0 ttl --43 1.16E. S9 f 4 ~ 91 ~ Oi 4~ ~o 0~ le04E Oli 0~ 2 Islfo04 1tt 65 1.46fo09 4 ~ 65Eo49 ~o Tottfo09 ~ 2e93Eo09 ~o l ~ Eo09 '5E ~ 0 ~ o'o R9 rh6 te11f oi9 0~ 5 0~ lot9 o09 S""49 Oo l.416 o l 4 ~o l 0~ ~o 2 ~ 1$ E oil ~~ 4.22E ~ 00 cR--90 r>> >>91 le 65Eoll 0-ltEIOI 0 0. ~ 0~ ~ lo l ~ l o6tf o09' '1Eoll 0~ 4e tlf ll ~ 0 ~ ~o lo ~o 0 ~ 2~ 16f ~ 03 th -95 2 ltd 05 9.I. lfo04 ~~ 1~ Dbto44 ~o 1 ~ 41E oil ~~ 5. 56Eo04 tsS--95 5 '9E F 05 2.41foOS l ~ 4 '4to04 le l.o94E oil ~o le 45fo05 t U-l>>3 4~ TilfI C3 0~ 0 ~ 4 ~ 16E>>03 ~e lol4fo0$ ~e 2.46fo03 ~U-tDb 2.41 f I 05 0~ ~e 4 ~ 2 ~ E ~ 04 ~o l 56f ol6 ~ 2.I6E ~ 04 AG l 1 ilH 6 ~ Elf ~ 41 5.15E o 01 0~ tol3E OD ~ ~e 2 ~ '5E 'lfo01 ~ ll lo ~ 3.42E 4.24'4 ~ F1 CD l l Stt 3~ 1.131 o06 0~ t.05fo06 0~ 5 0~ cQ 0.'I l ttCl/SEG tiELEASE RATE OF EACH TSOTOPE TH AttO A VALUE OF l ~ FOR X/0 ~ DEPLETED tt/0 AHD RELA11VE OEPOSTTTOti IIOT-: - Ttsf Utsll FOR G- -14 AHD H- -3 ARE lHA N/T4 P R UCl/CU stfTERI 41/25/ ,t<VgnOHttf tilAL PAlnttAX-CNcf CONVE~S34n-FAC1ORS FOR CiAStOUS 41SCMAI:C<ES Pt<lnNA't CONf tt1LK ICOM1AnlHAlcl FOhAGE 1 AGE GkOUP 1MF ANY t<llCL 10c O R G A tt 3 C 5 E F A C 1 4 S IS4 nclftt-tU<fn/'fil PER UC1/SfCl e\Q&\ %%%>>o>>%>>%>>\%>>%\oo>>>>%>>oo>>ooo>>0\woo ooo>>\>>\%%%%%%% OOt<f L1VEC tnt RClO FEONE w LUNG G1 LL1 SK1M 101At BOOL LN-123 0~ 4~ 0 0 ~ 4~ ~ o I ~ I ~ 6:i-1 za 1.75ioo9 3.44ctor Oti tol 4>>9lieo6 tothic49 I>> ol Eit- I <.'4 St)-125 Z. l5f ~ Ol 3 '9cghr 5 '9ci05 3.2rfeoh 1 ~ 6.C>>i ~ 04 2 '3c a,6 ~ 0~ 0 ~ 3 ~ 96i ~ 06

2. 13E 2.43ft09 ill r.rlfio~

2 ~ 43f toO ~~ ~ 5 ~ 256 1~ 6>>62Etih ~ 09t ~or li l '4fcOO ~ lc 1 lGH 1. 5 ~ 4~ 5. 30itor . 5 toe Ol ~ r.oSctor I Srf>lr I>> 2>> 1 of ~ 4l li 129tt 1c tzln 5 f5+cool S.itritott t>>936 t 4l 2.02feol ~ t oliftor zozli Ol~ 2 ~ 44t 2 to ~ rlfio~ 0~ lo ~ 3 3.5>>ceo ~ I>> I ~ lo 30ic46 ~ .95fclr 1- 50 4.54c PCS to 35cc Cih l.rlc 00~ 2>>09E 406 ~o tSE noh ~ 5 ~ 29f t05 1-- 1- -1 lz 1 1 ll 2.59ft09

l. 1 lf-0 1

3. ~ 9Eel9

>>o lhE ~ 1 9.94c ~ 6.26fe ~ 1 ll lo ltsf 4 ~ I l>>5lf ol ~~ I ~ 1 o l.thfc44 4>>93t 02 I ~o ~ ~ 1~ 1~ 41Et l9 69c ~ 1 1--l 13 3. rSc ~ Ol 5.40teol 1.3IE ~ 1 ~ 1~ 29fclr 0~ 9.r4fc46 lo' 1.66E ior 4 ~ ~o 1 ~ 46c Oi 4~ ~o lo ~ 0~ '4c 1--134'- 13S l. 496 ~ 04 3 ~ 04 5-1SE ~ 06 6.Zhfc04 o.ort-oz ti ~ t<tf ~ ~ 4 lo 1~ 44E t04 CS l 1>> 4 ~ 43c ~ l4 9rcc 14 I ~ 4.65E ~ 09 9>>tZEt09 1 ~ 94E < 40 4~ 6 rSft09 C -1 la Cc-1 ll 2~ llc ~ 04 l.lotto<9 ~o 6.ttfco ~ ~ 3ricor 1 ~ 25f cO ~ 0~ l o 'lOE ~ 00 >>Qf ~ l 4 l 2tf ~ 14 3.66c ~ 09 0.69E ~ 49 t >>46EC04 4.tcft09 PA-t-4 Ci 141 D~ 2 2 '5'0 '5ct05 2 ~ 4rieOS t.hzce05 ~>> ~>> 4~ t.zzfc04

9. l2E ~ 43 1.5tf ~ 05 4~

i>>lit 06 l Irf<ll ~ ~ ~ ~ ~o ~~ 1~ 1~ 2lE ~ 4l 90fcoti 2~ ~ Etor ~ .29'6 ~>> 5 ~ hrit05 I l>>66EFIO lo t3ie06 Pi OO ter 1 1 ~ 1 >>69i ~ 02 23ieoz 6.loctot l>>19'2 I ~o ~ 3 '2ftlt r.ztfclt lo ~~ ~ r.4tf>05 5.63fo0$ ~o ~~ 1~ 0>>t<ofeoo lo ~ tf ~ 40 'ts 'Ott UC1/SLC "ct 1 A i HArE Of ESCn t 1 1SOtOPE 1H ANO I VALUE Of 1 ~ FOR X/4 OEPLElEO X/4 A!IO RELA11VE OEPOS31141< 1 t - lw= untl'Oi C---14 Ati0 n----3 ARE tnfiil/TR PcR UC1/CU nffcRl PAIHAAV - ULbCHAK4i ~ANAL SHUKLLH= ukPu~fI~ Auc GKOul' ) kcNAQCg NQ~Lluf Ok Ci N Il U S c Kk N l oONk LiVER fHfk010 KlONc'0 I.Uhti Gl-a.L i SCLN lu)AL Q4>Y gamma 3 4~ il ~ 0 ~ U~ U~ u ~ U ~ 0 ~ Pmm m 32 Uo 4~ Il ~ ue 0 ~ U~ 0 ~ U~ 5L 2 ~ u6ctuo 2 '6ktDU 2 ~ Gbk+QQ 2 ~ ubc tuu 4 ~ uoftuu 2 ~ Dbctuu 2 '3ctu4 4 ~ Uoc. tuU GR IlN--50 6 'Qct62 b e U gk t Il 2 6.49E tu4 bo ugi:tu4 ao4 Jktu4 beugctu2 l ~ Lokt48 6 U9ctIlg fk--bb 0~ 0 ~ Il ~ 0~ u~ 4~ 0~ 0~ Fi--59 lo21Etu4 le 41E t42 L~ 2lf tU2 leClctu2 lo 4lctu4 1 ~ 2lr.tu2 1 e44E til2 lo 2lc t02 oil '-Sd L.blft02 1 blE+02 1 6lft04 1.6lf t42 1 oblf tu2 S ~ DlCtII2 1 ~ 9bf tU2 1~ 6lc t U2 l'0--bIl gov5ftu3 g.w5c.tQS go~Sf t03 go 05E tIli vi Et03 9 ~ Qbitu3. lollbtUQ 9.w~ft03 7N--o5 3.4lc,tu2 3 ~ 2lc,t42 3 ~ 2l c t02 3e 4lr.tU4 3.2lf t02 >.4IEtOc 4 olbf tu4 Oe 2lE tIl4 Kli- do Slf+u4 3 ~ Qlh.tu0 3~ 9lf toil 3 ~ 9l t4ui S ~ ll ctu0 3 ~ glf tuu 0 ~ b4C ~ UU l.llf-u2 3 ~ 9lc. tgu 9.5sf-u4 SR--Sg 9.~It f-u3 .9. oaE.-03 9o5%k-03 9o 54c. U3 gobhf-U3 9o JOE U4 iit9U 2 ~ Sbftuu 2e36Etilil 2.86f tUU 2 36E+uu 4 ~ Jbct40 4ek6ftQu 2 o l9r. tuil c ~ 3oftUQ 'f mmw9 j w.llc-DL w ~ llh.-QL llE-01 2 21kt02 4 llf-01 ~ 0o llf 4 'lctU4 -01 0 ~ )lf-01 2 ~ 21i tu2 So3oc, OL 4 ebSctu2 lt ~ llC, 2.2LEtQR 04 LR--9i 4 ~ 41E t02 2 Z>ft02 2o 4lc. tUC N--91 victUQ .2 ~ Slf tUQ 2 'LftGQ 2 ~ QlctuU 2 ~ Wiktuu 4 'lktUu 2 ~ S2E too c, ~ Wikt00 Ni-- 95 2 bo uiftii 1 bouif till 6 ~ ULEtDL 6 uli t01 bo 0LE t4l o~ Illf t'ai l4'Qctuu o Ql c t.u 1 boulftUL 4 ~ 6uc t00 NQ--99 2.bactOO 2.DDEtGQ 2 bQEt00 2 ~ 6Ilc tilU 4 ~ 6UC+UU 2 ~ 60r. ~ u 4 fcU- 104 Sed5itUL y ~ SSEt01 0 ~ dSEtoi 4 ~ Si= t01 0 ~ 55c.t01 'a ~ S5E tIll SebDCtQL 4 ~ doc tQL 1 ~ d5<<.t SSk tu2 L od5E+02 1 ~ dik tsl2 lod5ft42 lod5E t42 2 ~ 21E t u2 1 ~ S&c ll2t RU-Lub AI lluN 1 ~ 5dkt03 42 1.58itW 1 ~ SSktud 1 SSE Il3 t L.oSft04 1 eSdktU3 1 ~ Sect& 'lvftu2 j 1 ~ Slct43 4 '0ft04 2 ~ DIek tu 2 2 6vft42 2~ bitt U2 2 ~ chct04 2eovf tU2 3 2 ~ bItc t42 Sd-12'G-145 Loulftu3 i. SSE-DL Ulk t03 L.OLEtu3 ioDLct04 l. ULEt03

o. Sw E.-OL leulk t03 boSWk-UL 1 e LwctuS s 3SE,>>Ga le uic tu4

6. SSE-0l=-

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b. 5lc t01 0 ~ Jvi til3 CS-L37 s.54ctu3 s.ovf tu3 v 50c!43 we vebvh,+il3 o ~ 2gc dA-lou 3dc.t ul l.adktul l Sdktol l ~ dditda I 3dr.t Ill 1 ~ 3df tel 6 ~ Woc t00 de4octuL 5)ttuu le 3oc, tUL LA-LQU d ~ QoctuD d ~ Wbh tIlu d e4ok tIJU Se 4sf tUQ 4 ~ voftuD 9~ d ~ QbctUU o 04itUU UZE tDU be tuU be 02k thou 0 ~ U4h t'u U o olgf tuu. 6 ~ u2E tuu I'c-Lv 1 PE U4ctuu b ~ aJZC 1 loktuU I.'i-1 v ~ 1~ U2ctuu 7-ukhtuLI l.ucw tdu 1 ~ UCc. 4 4u leu4ctuu loUCEtUO 1 ~ 02ctu4 I'i-LQS 4 'gctUL 9+tDL 99k. td' Qadi t Ul v sdc t41 y~bgc tu 1 5 ~ Zoktul v ~ 'J4c t41 NP-43.l I ~4c-u l

~ o l.b4E-U1 e52r.-41 e' >CL.-UL / ~ 52c-ul I ~ JZc. 41 d ~ )Lc uL I ~ >4c Ul UUzi I AU1 kalb t assa I. 1 IJISI U Ul ouIIAIIGCU usahLU Uu 1 ULC IH KCCLASC ISF Casiili lu41ISI'i. IH Ulbi IIAKGL FI.UU QF 1 Iai'II 4 jill IIU aIUJS ILUIIAL IsLCUI lUH I'AIIIUIIU bALl KAI CII F cCN A4C 4HUUI'CC IsaaukH ssuik LUC UK4 HOOUC liiut ill ~ IUKC c.LVC0 1HI'ltUlU <<luui I 6L-ca.'1 UClH luluc Uncut sl o U~ I eoIC-VL I . b IL.-U l j~ lilt. Ol I. olc-ul IeaIC-UL 4~ I col c-4L I'-t - Jc V ~ I'.9C ~ 41 C ~ out ~ 4o 4~ 0~ 4 ~ IS ~ aCF.tub ~ e l ~ Isoc t44 I II--SL U~ Ue v ~ 99C tu4 1~ 4t=t 44 L. Llctul C. luE tu J 4~ 0~ Jtt t4U llH--4 Is 4~ Ce IS CC. t 4 V U~ aeuUctOJ ue I .LUtto<< 4~ ge 45CtuJ 1k--54 1 ~ a>uk t u5 b 13ktua 4~ 0~ I ~ IUC 'sua CeolEt JS IS ~ le IIC ~ 43 ik--t9 LE 43ctub C~ Vail.t45 0~ 4~ O~ Idk I ulS 0 ~ 00ct45 4 ~ 9 ~ Jlc. tu ~ I.as- -b 4 u~ 1 90E ~ UC 4~ 4~ U~ 1 eOIctuv ls ~ c ~ Uuc tut uu -uu ue C ~ 2CC t43 U~ 0~ 4~ cebaE ~ ub U~ 0 ~ Sac ~ J3 Cai ua I I uc.t isis ~ c e Isll. ~ US 0 ~ = 1 ~ bSctuS 4~ 1 ~ >bctUS 4 ~ l tot ~ LCc KO ub 4~ L.Jak ~ 03 4 ~ U~ 4~ CeahCt4C 4 ~ a. JJC t JC 44 I ~ 34ct4J 4~ 0~ 0~ 4~ I 9CE ~ VC 4 ~ C~ 4)= t UC oC--94 1 41EtuS 0~ 4~ 4~ 1~ ICc. ~ u J uebvctU3 4 ~ 4 ~ LJC t Vis I---QL 3 ~ 09ct41 li ~ 4~ 0~ 4~ 1 e hilk tub 4~ 1 ~ 4vs. ~ 44 cl--Ot 9eClct41 3 ~ 9uc. t41 ~e b~ Vlct UL 4 ~ LeCSktuS 4 ~ 2 ~ Sec tui CC--91 a.L3ttu ~ 1 ~ 54c. ~ 00 0~ 1~ Alct04 IS ~ o.u3ttuv U~ 5 ~ atk UL ilU--43 1 ~ Ils.tu 3 L.uJc.tOJ ouija U~ ~e llct02 4~ v ~ RLEtuo U~ be0a.E t JC slil- L.VLE.-42 2 ~ IUC ~ 02 4~ be Littu2 1~ 9tk-VC a.SLEtu2 0 ~ at s9c tQL KU-LVS aea2c ~ 40 4~ ~e le 60E,t01 4~ Is ~ J9ctuC 4 ~ c ~ 5lc.t 40 ~ .il-lua )eb3CtoL 4~ 4~ le CStt02 4~ Is ~ 36E ~ 4J 4 ~ l ~ clc. t Ui ss 1 lail v Clsitu3 3 9CEtuJ ~e I ~ 10ct4J 0~ Leauctua 0 ~ C~ Jtct4$ oal- L2II 4 'istt42 l.a9E t01 C~ LIIE tu4 0~ 6.9Jktuu 2eSJt t0i Il ~ 3 ~ SJC ~ u2 Jp LC7 I ~ lAEt02 4 ~ uui ~ 40 Oebssk-QL ~ C. luctuu Cev4ktOII ae JJEtuJ 4 ~ leISVC tuC 1 t. 1 CSii Jeuvctu2 1.09k ~ UC 0,54EtOL ~ eb6ct42 4~ 4.>UEt02 ~ ~ v ~ Uvs. Ult It.121H 5 '2ctuC JJC ~ UC 1 bSE ~ 42 C ~ CSE ~ 03 Ue 2.alE ~ U J ~ I~ ae ulC ~ uo Ic.li9ll 1 JLE ~ JJ U2 'ute '9ituJ 4.5IE tu3 4 612 t42 ICL JLII IE-l Jc C 1 ~ 41E t 42 v5c. ~ OC I leOUC Ilk'l ~ OC 0 1 15kt4v 4.93Et03 02 3 sse39t,t02 le UUit4 3 V~ 4~ 4~ JeUUEtOJ SeCLCtoJ IS 4 ~ ~ ~ C~ aebtCtbL 1 ~ Is'Sa. t u2 -13l l lc. ~ uC ae uLEtuC l.o4k ~ 4> I.S3c tUC Ue 1 LOE ~ 4C 0 J ~ Isa t uc l--lJ3 Is ~ I 39ktul 1 ~ C>t. t4 2 2 '0ttUis 1~ 50k ~ 4C 4~ ~ 9.14ttul 0 ~ ~ 3 ~ Uac. t4i aao 1 JII 2 ~ >9c tubs aeCvt tuv 0~ 1~ Sbk t04 y>itUJ lec0c,t JC 4 ~ L ~ 9LC tuo 46-Lou le 99EtaJ I.ossktu 3 4~ ts ~ JhctUJ 4 ~ 94ctOC . ~ eULE ~ 42 Is ~ >eoisc to 3 I'3 1 JC JevVctuls v ~ a3c ~ Ut 4~ le Lect UU oe LvctU3 a<<LUC tuC U~ leaa.s. tuV u4-Lvu C~ Loc ~ u3 C~ Iac.t44 4~ oeoLEouL leIUCtJV oeb0Ct43 IS ~ 1 ~ J tc ~ 42 a.i-lvls veoJC-OL r ~ C tk-uL 4~ U~ U~ LE Cbctuls as ~ a ~ uSt Jc vc.- 1 VL 9 ~ ucc Isl aeuuc IIL 4 ~ Ce JLc ul IS ~ 1 ~ 44Et43 is ~ Ie bee 4c UL lvJ LeaCC 41 5 VJLtuc 4~ 4 ~ CIC UC 4~ C.>>JCtOJ 4~ leulc-UC us. lua-C Ju 1 'I ~ 5 ~ I 'Sc' I J Ic ~ as uc L CD Joc.til Iec4L 4J 0 4 ~ ~ 9~ ll CeCOc-02 c tu4 4~ 4~ c ~ JVEtJII l ~ VvE tU J IS ~ al ~ oe ulk taJ J ~ 9cc-41 Table 3-8 REPZREam XETZOROuKY g~ggg R~~~ DEPOSITION ~TE 9 e g/q are annie mode afgbornk gabe on a square aeter're)L o land averag ed re lease, ease, from f f 2 ctors representing the fraction of a )))ized rom the Turkey Point RIant vhich is deposited an at a given distance and direction. from the Plant, Period of Record: Ol/OL/76 to 12/31/77 BASK DISTANCE IN NIL.ES / KII.OYSTERS AFTO OES I%I SECT DIST oZS ~ 75 I 50 ZoSO 3>>SO 4>>SO 5>>SO 7e00 HI ~ 40 ) oZI Z>>41 4>>02 So&3 Te24 . 8e85 II>>26 NNK HK 0~ 0~ 6>>4K-09 loSK 09 4o7E 10 Z ~ OK-10 9o IK>>) ) S>>SE LI 3>>SE 09 8>>7K 10 2>>8E 10 2E 10 6>>4K ll 4>>3K li 2 5E ll 1.7K-II II 2>>7K-gl KHK 0~. 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Ilf<<05 H Creel>> 4o 05 3 3ollE<<05 ~ 3olIE ~ 45 2 ~ TSE<<0to 3 ~ 4E<< ~ 5 3~ llf <<45 0~ I 3~ I P %2 2-19E<<l ~ 1 ~ Ttf<<09 I ~ 0~ f ~o 2 ~ LCE<<09 ~ ~ 46E<<4 ~ Ck cl Oo lo 2 ~ 19E <<01 I ~ 41 ~ 02 ls ~ ~ 5E<<03 9ol9E<<IS ~~ 3 ~ 66f << ~ 3 tltt" 54 ~o lo ~ ~ E ~ 46 ~o 3otlE<<05 ~o 3 '9E<<06 ~~ 2 ~ 5E<<IS 4 ~ 12E<<45 9ot ~ E<<45 ~o toltf<<05 3 '3E<<06 I~ Ttf<<05 FE CO 59 57 Oo 1 F6%EGOS ~~ I~ ~o ~o Co 15E<<06 ~ ~ 2~ ltf 05 ~ 4o5lf ~ 06 C0--53 0~ loSIE<<$ 6 ~o lo ~o ~ o9IE<<IC ~o CO -60 I 5o ~ 6E<<IC lo ~o ZollE<<02 ~~ lo 52E <<IT H1 61 ~ lo60E ~ 44 5 '6E<<07 ~o ~o ~~ ~o 1 o ZCE ~ 02 <<ll ~~ 2~ Ilf<<IF <<ll Ztt--65 1ol6E<<4 ~ f I 5 ~ Sl << ~ I ~ 3.23f << ~ I ~o 3.511 ~ ~ 2 Stf lt 8 AC lo T~ Ttf<<00 I ~ ~o ~o 6 'CE<< ~ F ~~ 1o 55f <<00 c(aa)9 45E ~ 14 lo ~o 5 '3E I ~~ lo 4 ~ 16f <<00 SR 90 Z.SFE<<lt 4~ I ~ ~~ 4~ ~o ~o 3 16f <<l9 ~o 6o ~ ZE << ll T---91 4.56E<<43 4 ~ 0~ lo ~o 6 'CE ~ IS ~~ 1~ 22E<<lt FR 95 lotlf<<44 5 'TE<<43 ~~ 2 '3L<<03 ~o 9 ~ ZZE ~ IC ~o 3 '6E<< ~ 3 ttn--a5 lo3OE<<44 1 ~ 41E<<44 ~~ Sollf<<43 lo Zo%4E<<02 I ~ 1~ 04f ~ ~ ls Fu-103 4o 296 ~ 42 ~o 4~ It ~ 99E<<lt ~o lotCE<<04 ~~ 1~ 94E <<02 r U-146 I ~ 13E<<44 5 '%E<<03 I tolSE<<05 ~~ 4lf<< ~ 3 AG114H lo>>5E ~ 06 0~ 6 '0E<<06 4~ ~o 1 ~ 36E ~ Il ~o ~ Zollf<<09 Collf<<06 ~~ 1~ 4~ llf 06 5 '9E<<03 ~ COllltl 4~ 1.59E<<05 lo loZCE<<05 ~o ~o a1510 CH 1 UC1/SEC RELEASE FATE OF EACH 1 OTOPE ltl AIID I VALUE OF 1 FOR X/0<<QEPLETEP X/0 AttO RELATTV OEPOSTTTOH IIOT Till UIITTS FOR C 1>> AIID H 3 AFE 1tIC tt/YR PER UC1/CUo'IE TERT 0 1/25/ l9 cHVIHOHUEHYAL PAYHNAV-DOSE GOHvff S10H FAGIORS FOI GeASEOUS 01SCHA>GES PAYHMAY - GOAYS HlLK ICOH1AHlHAIEO FOFAGEI AG f GROUP Cli1 LO HUGL IOE 0 R G A H 0 0 S E F A C 1 0 R S ISO ~ HEIER HREH/YFL PfR UC1/SEGI OGHE L1VER THVR010 KlOHEY LUHG Gl-LL1 SKIH IOYAL Oooo SH-1Z-I 0~ 4~ 0 ~ 0 ~ 4 ~ 0~ 0 ~ 0~ SH-I?6 2.1OE ~ 00 4ellE F 06 22E<<06 4~ 5 ~ 9lE ~ ~ 5 t.40E F 00 4 ~ 6 ~ YOE <<46 S~ 124 5. 30E ~ 06 6 ~ ZZE<<04 l ~ 9lc <<03 4 2 '6E<<06 9 ~ 33E ~ 4l lo le 30E<<06 ES l?5 I ~ lSE<<46 t I lit<<05 1 o43E <<OS ~

4. l6E <<05 3 ~ 4IE << ~ 4 t ~ 92E ~ Il ~ e l 19E <<45 o

1 c IZS'l Ieb5E F 06 40E<<06 2.49c ~ 06 ~ o46E<<06 I ~ ~ o54f F 06 I ~ le IIE<<06 I I 121M 6. Ztf F 06 2.14E ~ 06 1. lSE ~ 06 to4IE <<Ol ~o 3 ~ 50 E~ Il ~ o l. 92f 45~ lf I29H 3 ~ 3ZE ~ Ol 9 ~ 2lE <<46 I6E <<Ol le Z3E <<Ol lo 4.04f <<Il ~o 5 ~ 15E <<06 130 5 '5E<<05 1.61E ~ 06 2 ~ ~ Sf ~ ~ I Z.SIE<<06 ~e lollf<<06 ~o 6. 35E ~ 05 1--I 31 I ~ 40E ~ 09 1.52E<<09 4.94E ~ 11 9etic<<II 4~ lollf I~~ I~ I ~ 15f <<09 1--132 1 133 Zot)E 2.146 01 all Se l IE-Ot 64f <<Ol l 6 '6f ~ 51E <<01 ~ 09 9etlf Ot leSSE <<ll ~o 4 ' 1~ llf ~ lellf<<ll 1 ~ I~ o 2o03E 41 I ~ 04E<<ll 1--134 I ~ Zl= 49 I I 1--135 4~ t ~ 790<<04 4 4 ~ ~ l 2E<<04 6.1 ~ E ~ 06 ~ l 51E <<04 ~ to39j<<t ~ 4~ 2 ~ 426 t ~ ZZE<<l ~ 01 ~e 5 '9'4 0 ~ ~ ~o le llf<<04 2.33f <<1 ~ CS CS CS 114 -156 -tll 6 ~ 54E<<14 Oe 34E<<40 9 ~ 21c<<10 to 14E<<11 3 ~ 29E ie9lf<<le ~ 09 ~~ 4~ ~~ t,l3E ~ 09 }.10E ~ 14 2 'if tl~ ~ I'el5f ST 92E<<00 lo l4E <<I ~ S.44E<<00 ~e ~ lo ~ 2e 1~ 3lf <<49 33E<<ll QAet 40 I ~ 40E<<0l 1 23f<<44 I ~ 1 ~ 4lf <<43 le 31E ~ 43 9 clif<<05 I~ 4 ~ ZIE<<05 Cf 141 I. 49E <<04 l.46E<<03 I 1 llE ~ 3 ~ << ~e 9.l6f <<06 ~ ~ io 1lE<< ~ 3 CE -144 I ~ 20E<<06 3~ leE<<05 I ~ 6eiif <<04 ~o 9.llE Il~ I ~ 6. 41E ~ 04 PR-tv 3 2 F 03'1 0.16f <<00 4ollf <<00 .~o ~ ol9f ~ 04 ~ o 1~ IIE ~ ~ 4 HO 14l 5.41E ~C I le42f<<OI ~o  %.66E<<ED ~o lelSE <<04 ~o 9. 50E-Ot ~AScO OH I UCI/ScC MELcASE KAIE OF EACH lSOIOPE 1H AHO A VALUE OF t. FOR X/0<<OEPLflfo X/0 AHO RELAllVE OEPOS1110u 005 - 1HI UH11S FOR G-- 14 AHO H-- -3 AI'f IHI EA/VR PER UC1/CUeHE1CRI =IIV190!INEIITAL FATHltAY OOSE COttVEI(S10tt FACTORS FOR GASfOUS OlSCHASGES PATHNAY GOATS tllLK ICOHTAN1HATED FOf AGEI AGE CROUP 1NFAH1 NUGL 10i ORGAH OOSE FACTOIIS elf 0-NPEN/YR PER UG1/SECI ISO ~ Nf OOZE LlVf.R THV9ola @LONE Y LUHG Gl LL1 SKlN TOTAL OOOV H----3 4>>hbfi43 i.osft43 2 ~ 11E ~43 S.oif i43 Lo&f~ 43 Ibf~ 43 F --32 6 0>> '5'5 2 ~ 19E ~ 14 6>>55fc05 1>>3rf ~ 49 . 6 ~ SSE ~e t05 r>>TSE ~e ioe 6>>SSEi05 ~o & ~ 55E R.LCE ~ ~5 ~ 49 0~ ~e I ~ o>> ~ b>>SSE445 4 '&E~I~ CR--51 Oe 0. t.19'3 4 ITE>02 h ~ ISE4 ~ 3 9 ~ 19E~IS ~o 3 66ft43 I 04Eio6. 3>>tot f05 3>>29fiDC I to OSE F45 NN Fc -59 CO 5% -57 I ~ ~. IZE ~ oS ~ 1~ 9 74E ~ 45 1>>etof ~ 45 ~ ~o I ~ ~ 4~ 4~ ~e RE TREt4S I ~ 3 e~ '3'6 15f ~06 ~o ~~ ~ 3.TRELLIS 2~ Ttf il5 CO -54 0~ 3 ~ 4&E>46 ~e 0~ ~o 7 ~ 9tf toe ~o 7 ~ t>>9f >46 CO--aO 4~ l>>ISE i or ~o 0~ lo 2 >> 59E ~ 01 I ~ R ~ Slf oor t<1--t 3 4 ~ &OE ~ 04 5 ~ 96E ~ 07 ~o 0~ 4~ l>>RSECIT I ~ 2>>IIE+IT rv>>-eS 1.76EI ~ I 5>>STEt40 ~~ 3~ 73E400 0~ 3 ~ Slf ~ ~I I~ 2 ~ SRE~ ~ I Ge 'I ~ Tt f ~ ~ I ~~ ~e ~~ 6 ~ Stof c lr ~e 1~ SSE>4 ~ SR 49 3~ 09ftlo 4~ 4~ ~o ~o S.Trails ~ o 4>> ~ Tfill St 90 }e~&L~11 0~ ~e I ~ I~ 3 ~ 3%E a 09 ~o 4 ~ 43f ~ 1 ~ v 9.7ifi03 0~ I ~ I ~ ~o 6 ~ t>>SE >05 ~~ t>>EIE~ ~ 2 14 95 2 ~ 54f 404 .1>>13f o Oa 4~ t>>23E F03 I ~ I ~ 9SE F06 4~ 6>>67fi03 H9--95 6.59f ~ oh R.srfioi 4~ 5~~ lf 443 ~ ~ t>>37E >lr ~e 1.7SEioa i'U -143 9.9&foot 4~ 0. to>>99E ~ ~ R I ~ 1-taf boa ~~ 3 ~ t 3E~IR RU 1)e R.~lfiOS 4 ~o 5 ~ ~ tof 103 I 1~ lrfF05 I ~ 2 ~ 96E > 43 AGI SIN 7 ~ 45itoe ~ 6>>94fiO& ~o 1.36'ar ~o ~ 2 ~ Ilf>46 il9 I ~ e>>1OE446 CQ 11 Stl 0 ~ 1 '9E>45 ~ o let6f F05 ~o 6 ~ Tlf I~ 5 '9E ~ ~ 3 <AScO Qtt I UGI/ScG Rf LE ASE ttATE OF fAGH 15 OTOFE 1H AHO I VALUf, OF 1 ~ FOR X/Oo PEPLETEO X/O AHO Rf LA11VE Of POSl 11ON tOTE - lHE UtilTS FOR C - Ia AttO H- 3 AFE INFE'I/'fit PER UGl/CU>>NETERI 0 0)/25/79

t.V 1>>rcrttr Err 1AL PA 3 trtrAV-riOSE a;OHVc hst Ort FAC10RS FOR rASEOUS ntSCHAAGES PA 1HllAV GOA)S rlLK Icor)TA')1 trA tiO FOR AGc ) AGE GROUP 1trF AN7 trUCL )0 OPGAt)00scFAC70 k S )SO.HE1ER-t)RcH/VR PER ucl/SEC) ee e ee ee e ee e Stcam rlulrc L1Vf.R THVROli) K10HEV LUtle GleLL1 SK1H 101AL OOOV

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GlSCtiA(.GiS "A tliiar F'";ti FRUllS AHC viGcfaaiiS AGE Gs'CUP llcUAGER t'UCLsui 0 F G A tl 0 O S = F A C l 0 R S, ISO ~ Nilfrs HFEH/rk Pft'cl/SECl 90!if L 1VEt'HTRClD KlDHE V LUHG Gl-LL1 SKlh lOlAL SOOT 'si- t? 5 s. 1.5 5E-V7 22i 47 33E-45 '4E SH-l est so 2%c-OS be25c ~ 44 le 65f ~ s57 1~ 24it47 3 ~ 52ct05 1 ~ 3oe4E 3 '9E F 06 ~ 44 4 0~ 0~ ~ 4 2 ~ '3c loaf>07 F 06 1 ~ 5 '5E '7ft0 F 0 ' ~ 4 0 0 ~ ~ ~ 2 1~ 94it07 6o53f tOS 17 =n-5 5 l. 7 5E ~ 07 5.97ct35 5.44i ~ 45 3 '4c t06 1 ~ 60ft09 1 ~ 45E<04 Oo 3.44ft06 1 1 5 25't 2 '3E ~ 07 7e99E ~ 06 os 30c ~ 46 6 '6E <07 Oo 6 '4E ~ 07 0 ~ 2 '6ft06 lc 527it e.isct47 1~ 55ct07 1 ~ 10c t47 5 ~ OOE<04 Oe 2 '3ftfi4 0 ~ 5 '5E<06 lc 12 in 4 ~ 46'7 3.14E F 07 2 'lce47 2 '5c ~ 00 ~o 2 '5it40 ~o 1~ 33f t47 J--1 lu 2 '4ct05 7 '4Et05 9 '2ct ~ 7 le 19i t 06 Oo 6 '5Et45 Oo le ~ Of 4 05 5--l 55 6~ 44itu7 9 '6c ~ 47 2 '9E ~ 10 5~ 25ft00 Oo le ~ 3E ~ 07 Il ~ 5.76E t,07 l -532 5~ c5E ~ 41 9 '7ft01 1~ 29i>44 5 ~ 56ft02 ~o le ~ 4ft ~ 1 ~o 3 ~ 47f >41 I--155 1~ 94it06 3~ 36E F 46 6 ~ 10c ~ 4 ~ 4 '3ft46 0~ 2.ls4ft06 0~ 1~ 44ft06 1--) 54 o.75i-05 1 ~ blc 04 2 '4c-42 2o92fe44 Oo 1 ~ EOE 07 0~ 6o56f-05 1--155 ).E5fo04 7 ~ 44E llft05 '7E 03 '4Et44 2. 57ft44 C 5 .154 CS-l 5S 5 '9E 2o54i ~ 47 ~ 40 1.441 ~ ~ 60it47 44 ~ 49 9 ~ 15E ~ Oo 4 4o ~ 5 ~ 3 '5itO ~ 4 '0ct07 5 1 ~ 69E<4 ~ 6e56E ~ 06 7 1 ~ 9 61f t07 77f t06 ~o Il ~ Oo 6o52E ~ ~ 4 59f 407 CS-l lr 7 ~ ii3it04 1 ~ 45E t 49 4 ~ 2 '2ft0 ~ 1~ 40ftO ~ 1 ~ 45E>07 ~~ 3o70f t ~ 0 I A-1 ail 9e 5stf ~ 07 5 ~ 25it45 0 ~ 2 '4ft04 7 '3it04 3e 19E ~ 04 ~~ 6o04fi06 C 6 ~ 52i ~ 04 4~ 24it Ols 0 ~ 5 ~ 47ft04 Oo 5 ~ 55ft0 ~ ~o 4 ~ 06ft43 Ci -1 i4 5~ Olf t46 2 ~ 06E ~ 46 0~ 4 43E ~ 45 Ilo 1~ 59ft09 ~~ 2o 67f ~ 05 fa-ts5 5 17i ~ 4is 1.24E ~ 44 4~ 7 '4Et ~ 3 0. 5 ~ 39ft ~ 4 0~ 1~ 54Et03 t'O-147 2e24E ~ 44 2o26ct04 4 ~ 1~ 36E t44 ~e 5~ 06ft00 4 ~ 5~ 47E ~03 ~ a=; s Ok 1 ui'l/SEC RALEASE sialf OF EACtl 1SDIOPE lN AND A VALUi OF 1 FOR X/Oo DiPLiliD N/O Attrs RELAllVE DEPOSlllON APPEHDTX D Technical Bases for A ff eff Overview The evaluation of doses due to releases of radioactive material to the atmosphere can be simplified by the use of'ffective dose transfer factors instead of using dose factors which are radionuclide specific These effective factors~ which are based on the typical radionuclide distribution in the releases> can be applied to the total radioactivity released to approximate the dose in the environment> ie> instead of having to sum the isotopic distribution multiplied by the isotope specific dose factor only a single multiplication (A times the total quantity of radioactive material released) would be needed. This approach provides a reasonable estimate of the actual dose while. eliminating the need for a detailed calculational technique Determination of A ff The effective dose transfer factor is based on past operating data. The radioactive effluent distribution for the past years can be used'o derive a single effective factor by the following equation. Aff Ai'i i where Aeff ~ the f< effective dose transfer factor A ~ the dose transfer factor for radionuclide i . f ~ the fractional abundance of radionuclide i in the radioactive effluents This equation yields a single dose factor> weighted by the typical radionuclide distribution. 0 To determine the appropriate effective factox to be used and to evaluate the degree of variability~ the atmospheric radioactive effluents for the past- 3 years have been evaluated. An effective dose transfer factor has been detexmined for the gaseous effluents for all pathways of interest. Tables D-1 and D-2 present the results of this evaluation. For the radioiodines and particulates with half-lives greater than 8 days, the effective dose transfer factor is based solely on the radioiodines (I-131> 133> and 13S). This approach was selected because the radioiodines contribute essentially all of the dose to the infant's thyroid via the cow-milk pathway. The infant's thyroid and the cow-milk pathway are the critical organ and controlling pathway> respectively, for the releases of radioiodine and particulates. All othex'articuLates contribute less than LX of the dose. The effective dose txansfer factox is determined by applying equation D-1 to the radioiodines. However, indetermining the dose> this effective dose transfer factor should be applied to the total release of all radioiodines and to particulates with half Lives greater than 8 days. .This uniform application is conservative in pxoviding reasonable assuxance that the actual dose will not be underestimated by the use of this simpLified method. The determination of Aeff was limited to the past three years ( 1978> 1979> and 1980) because of the changes that have occurx'ed in the waste processing system. A demineralizer system replaced the previously used evaporator in the Liquid waste processing system. As can be seen from Tables D-1 and D-2> the effective dose transfer factor varies little from yeax to year. The maximum observed variability from the avexage value is 13K for the noble gases and 25K for the radioiodines This variability is minor considering other areas. of uncertainty and conservatism inherent in the environmentaL dose calculational models. To provide an additional degree of conservatism> a factor of 0 8 is ~ introduced into the dose calculational process vhen the effective dose. transfer fa'ctor is used. This added conservatism provides additional assurance that the evaluation of doses by the use of a single ef fective factor vi11 not significantly underestimate any actual doses in the "environment. Table D-l Effective Dose Transfer Factors Noble Gases Air Dose A8 eff eff mrad mrad

i. sec/m 3 i. sec/m 3 1978 1.3 x 10 34x10 1.979 1.3 x 1.0 3.4 x 10 1980 16x10 3.4'x 1.0 Average 1.4 x 10 34x10

4, Table D-2 Effective Dose Transfer Factor for Air-Grass-CowWilk-Infant-Th roid Pathwa Radionuclide Annual Fraction Dose Weighted Airborne Factor a Dose Release mrem/ Factor (Ci) ~i/(m 2 . sec) mrem/ i/(m2 . sec) Year 1978-I-131 0. 381 0.688 9.9E11 I-133 I-135 0 129

0. 044 0 233 0 079 1

S. 2E6'.9E11 3E10 Year 1979 I-131 0.0188 0 520 9.9E11 I-133 0 0156 0 432 1.3E10 5 2Ell I-13S 0 0018 0.048 5.2E6 Year 1980 I-131 I-133

0. 0518 0 756 9 'Ell

0. 0124 0. 181 1. 3E10 7. SE11 I-135 0 0043 0. 063 S~ 2E6 b

avg 6. SEll a air-grass-cow-milk-infant-thyroid dose transfer factor b Effective dose commitment transfer factor is the average of weighted dose transfer factor over three years. APPBNOIX E RhDIOLOGIChL ENVlRONMEÃfhLSURVHlUANCE TURKEY POINT PLhNT Key to Sample Loc'runs It is the policy of Florida Power and Light Company (FPL) that the Turkey Point 3 and 0 and St. Lucie l and 2 Radiological Environmental Monitoring R'ograms are conducted by the State of Florida Department of Health and Rehabilitative Services (OHRS), pursuant to an Agreement between FPL and OHRS and; that coordination of the Radiological Environmental Monitoring Programs with DHRS and compliance with the Radiological Environmental Monitoring Program Technical Specifications are the responsibility of the Enenp'ervices Department 'uclear 0 RAOIOLOG IC AL ENVIRONHENTAL SURVEILLAN'E TURKEY POINT PLANT Key to Sample Locations amp e Col lection Ap proximate . Direction Pathway Location Description Samples Col lected Frequency Oi stance (miles) Sector N-1 Convoy Point TLO quarterly 'N DIRECT RADIATION 0 IRECT RAD IATION N-5 North of Hoody Dr. TLO quarterly DIRECT RAD IATION N-10 Old Cutler Rd. at TLD quarterly 12 S.Q. 87th Ave. DIRECT RAD IATION NNW-1 Turkey Point TLD quarterly NNW Entrance Road 0 IRECT RAD IATION NNW-10 Burr Rd. at Hainlin TLD quarterly NNQ Kingl Or. Hil 0 IRECT RAD IATION NW/WNW-I Turkey Point TLD quarterly Entrance Road DIRECT RADIATION NW-5 Dolan's Fana on TLD ~ quarterly 's Highway D IRECT RAO IATION NW-10 Intersection of Fans TLO quarterly Life Rd. and Coconut Palm Dr. OXM RADIOLOGICAL ENVIRONMENTAL SURVEILLAN:E TURKEY POINT PLANT Key to Sample Locations Sample Col lection Approximate Direction Path~ay Location Description Samples Collected Frequency Distance (miles) Sector DIRECT RADIATION M/MNM-5 Palm Drive at TLO quarterly Tallahassee Rd. D IRECT RAD IATION MNW-10 Homestead near vehicle TLD quarterly MNW inspection station DIRECT RAD IATION On site near cooling TLD quarterly tower D IRECT RAD IATION M-10 Florida City near quarterly lu fire tower D IRECT RAD IATION MSM-10 Old Hawk missile site TLD quarterly MSM south of Florida City DIRECT RADIATION SW/SSM-1 On site near land TLO quarterly util izai ton of fices D IRECT RAD IATION SM-10 U.S. 1 south of TLO quarter ly Fl orida C i ty DIRECT BAD IAT ION SSM/SM-5 On site, southeast TLO quarterly SSM corner of cooling canals ~ RAO IOL'OG ICAL ENVIRONHENTAL SURVE ILLAtCE TURKEY POINT PLANT Key to Sample Locations amp e Col lection Approximate 'irection Pathway Location Description Samples Collected Frequency Distance (miles) Sector D IRECT RAO IATION SSM-10 At Card Sound Bridge TLO quarterly 10 SSM DIRECT RAD IATION S-5 On site, south end of TLO quarterly cooling canals D IRECT RAD IATION S-10 Card Sound Rd. at TLO I)uarterly 10 Steamboat Creek D I RECT RAO I ATION SSE/S-I .Turtle Point TLO Quarter ly SSE DIRECT RADIATION SSE-10 Ocean Reef TLD quarterly SSE AIRBORNE T51 Homestead Bayfront Radioiodine Meekly Park and particulates AIRBORNE T57 Tree Nursery Radi oiodi ne Meekly 316th Street and particulates AIRBORNE T58 Turkey Point Radi oi odi ne Meekly Entrance Rd. and particulates ~ ox~ RAD IOLOG ICAL ENVIRONHENT'AL TURKEY POINT PLANT SURVEILLACE Key to Sample Locations amp e Col lection Approximate Direction Pathway Location Description Sampl es Col l ected Frequency Di stance (mi1 es) Sector AIRBORNE T64* Natoma Substation Radioiodine Weekly 22 NNE and particulates AIRBORNE T72 Turkey Point Boy Radioiodine Weekly WSM Scout Camp and particulates WATERBORNE T42 Biscayne,Bay, at Surface water Honthly ONE Turkey Point Sediment fraa Semi-shore line annually WATERBORNE T67* Bi scayne Bay, Sur face water Honthly 13-18 Ns NNE vicinity of Cutler Plant, north Sediment frau Saai-to Hatheson Haauaock shoreline annually Park WATERBORNE T81 Card Sound, near Surface water Honthly mouth of old di scharge canal Sediment frau Semi-shoreline annually ~ Denotes control sample. 4 XN SURVEILLANCE RADIOLOGICAL ENVIRONHENTAL TuRKEY POINT PLANT Key to Sample Locations Samp e Collection Approximate Direction Pathway Location Description Samples Collected Frequency Distance (miles) Sector FOOD PRODXTS T67* Biscayne Bay, vicini ty Crustacea Semi- 13-18 N, NNE of Cutler Plant north annually to Hatheson Hammock Park Fish Semi-annually FOOD PRODXTS TBI Card Sound, vicinity Crustacea Seni-of Turkey Point annually Facility Fish Sani-annually FOOD PRODlKTS T40 South of Palm Or. Broad leaf Honthly on SM 117th St. vegetation extension FOOD PRODXTS T41 Palm Or. Nest of old Broad leaf Monthly l4NM missile site near vegetation the site boundary FOOD PRODlKTS T67 Near Biscayne Bay, Broad leaf monthly 13-18 N, NNE vicinity of Cutler vegetation Plant north to Natheson Hammock Park

• Denotes Control Sample.

REV.1: 12/19/84 4 ~ If ~ ~ O P 1 ~ C O ef P t ~ ~ I pp '~ af ~ pat I D hh7.", T ll- V/ ~: '+++ T I ~ +w 1,' ' V a ~,, P O A.. I ~ P I ~ lapp P i1 ~ hP I pP P ~ ~ ~ I I ~ l>>pa ~ ~P lt e ~ I~ ~ ~ vaar ~ I av ~~ I ~ II ~ trl I I-,+.+-.~-.+ f.+ p ~ D ~ ~ ~ ~ >>hla e p+ ~i +I Alla~ I ~ ~ ~ g(cI ='( +.'+ I I ~ a "P, r~~ ~'+ Y ~ ~ I ~ O I.-'=+ ~" -,', ++-+ I ~~~~ ~~ ~ g ~ ' ~ A' I P > ~ Pa+ ~ ( 11 ~ f' 5ga ~ I ~ (:,l (p mT- I ~ II ~ a pap pllp ~ I I ~ CI " . AP.PI' ,vagV pa P Pt I A II g; ~W .I+() 'p(efp aa,; ~ Ia III + ~ a a~lb ~ V aftI ~ ~ T-64 * ~ Sa ~~ ~~ CI N"- J ~ L' ~ pall a '/ Pl OCIICAJL LtOtttO Lt i P ~P ~ I ( ~ I ~a ~ P>>>> (7 A ~ PW /P a I N-10 I ~ {e NNM-10

l h '

O,~p 4 ~ I p pppl ap I ~ I NW-10 r P ~ ~I P P ~I a N-5 I ~ I t,a P P lait ~ % ~ I ~ - ~ ve I'a I l ~ = WNW-10 PV Qga / ~ ~P a I

f. ~

t- v pap p 'P ~ P ~ ~ I Zl I S r(e af A~ ~ at rr ~ PL ~ Th ~ lr P I ~ I ~ i I {a I ~ ~ ~ I IAI v ap a e ~ (A (PA I \ AC I . I . ~ ~ ~ I WSH-10 'l. '1 I ~ I ~ '1 >>I '1 r~i ~ ~ aa ~ I. ~h GENERAL HIGHWAY ~IA. I" DADE COUNTY I' lap SW-10 Sl g ~0 CO SSE-10 ~ lett paapa at ~ FLOR1DA p aa ev(clap>> Alta(c thv>>>> aaa j: ~ '-l', CTAIC Of fIOPeOA OtrAATIICPT Of TPAPSPCPITATICAI 1 12/19/84 IIX OCPAATHCIIT Of TAAPSPOATATIOP ~ DIAIIp>>pal a>>>>e a a I >> S i-:: XI

5 Ql

/ Ml I I r r / r ~ F 0 Table 3-1 Atmospheric Gaseous Release Points at the Turks Point Units 3 and 4 Effluent Release Source Point Gas decay 'tanks Plant vent Radwaste Building Plant vent Auxiliary Building Plant vent Containment Purge Pl'ant vent No. 4 spent fuel pit Plant vent No. 3 spent fuel pit Spent fuel pit vent Air ejectors Turbine deck Steam generator Blowdown vent blowdown Table 3-2 Distribution of Radioactive Noble Cases in Csseous Effluent fram Turke Point Units 3 Ea 4 Nuclide Release fraction ayb Ar-41 9 ~ 2E 3 Kr-83m Kr-85m 2 5E 4 Kr 8S 2.5E-4 Kr-87 1 ~ 6E-4 Kt-88 2 IE-4 Xe-131m 4,4E-4 Xe 133m 1 ~ 2E-3 Xe-133 Oi99 Xe-135m 8 OEM

3. 4E-3 Xe-13'e-137 Xe-138 3. 7E-4 Based on measured discharge from Turkey Point Units 3 6 4 during 1978 thru 1980.

b To estimate radionuclide concentrations in a sample in which only the total activity concentration has been measured> multiply the total activity concentration by the fraction of respective radionuclides listed here. Table 3-3 Transfer paceors for Maximum Offsite hfr Dose Radionuclide Air Dose Transfer Factors 'Yi'onad I i sec/m 3 Ci seel'm 3 Kr-83'Cr-85m

6. IZ-7 9 IE-6 3.9E<<5 6.2E;5

. Kz-85 5.4E-7 6.2E-5 . ~ Kr-87 2.0E-4 3.3E-4 Kr-88 4.8E-4 9 3E-5 Kr-89 5.5E-4 3.4E-C Kr-90 5; ZE-.4. 2.5E-4 Xe-13 ha 4 9E-.6 3 5E-5 .Xe-'133ra 1 OE-5 4.7E-5 Xe-133 1 IE-.5 3E 5 Xe>>135m 1 IE-4 2 3E-5 6.ZE-5 ' Xe-135 7 SE-5 Xe-137 4.8E-5 OE-4 Xe-138 2 BE-4 1.5E-4 Ar-41 2-9E-4 IOE4 Ref: Reyxlaeory Guide 1.109~ Revision 1> Table B'-I 4 Table 3W Transfer Factors for Maximum Dose to a Person Offsite due to Radioactive Noble Gases Radionuclide Dose Transfer Factors Yi UKL em Ci seclm 3 i sec/m 3 Kr-83m 2.4E-9 Kr-85m 3.7E-5 4.6E-5 Kr-85 5 1E-7 4 2E-5 Kr-87 1 9E>>4 3 1E-4 Kr-88 4.7E-4 '7., 5E<<$ Kr-89 53E4 3 2E-4 Kr-90 4.9E-4 ~ 2 3E-4 Xe-131m 2 9E 6 1+5K-5 Xe-133m 8 OE-6 3 1E-5 Xe-133 9 3E-6 9.7E-6 Xe-135m 9.9E-5 23E5 Xe-135 5 7E-5 5 98-5 Xe>>137 4 5E-5 3.9E-4 Xe-138 2. SE-4 1 3E-4 Ar-41 2 GEM 8 5E-5 Ref: Regulatory Guide 1 109> Revision 1> Table B-l. Table 3-5 Dose Conversion Factors for Der ivinf Radioactive Hoble Gas Effluent Monitor Setroints Factor DF. for Radi onucl i de Ground-level or Svlit-Qake Release area a3 Kr83a 7+56 E-2 I Kr85a 1o17 K3 Kr85 le61 El Kr87 5 '0 K3 Kr88 loh7 Kh KF89 le66 Kh Kr90 1 ~ 56 Eh Xei31a 9o15 El , Xei33a 2e51 E2 Xei33 2o9h K2 Xei35a 3+12 E3 Xa135 lo81 K3 Xei37 loh2 K3 Xai38 So83 K3 Xei39 5e02 E3 4rhl SoSh K3 Table 3-6 RE&MBtCE METEOROLOGY ANNIIAr, AlIERAGE ~osPHERIC DISPERSION FACT0RS X/Q are annual averased factors of atmospheric dispersion of a mixed made gaseous release from the Turkey Point Plane. Period of record: 01./01/76 to 12/31/77 SASK 0!STA>>CE rN Hrl KS f KIL.OHETERS AFTO r DESIGNS sEcT orsT ~ 7.5 o?S l <<SO 2 ~ 50 3 50 4<<50 S<<50 7 00 HZ ~ 4Q 1 Zl 2 41 ' 02 So&3 7<<Z4 8<<85 11.26 NNE Oe e.9K-o? 1 ~ 98 07 8 ~ 3K-08 S<<OK 08 3<< OEM8 Z.ZE-ca 1 9KMS l<<4E g5 NE 0~ 6<<9K 07 l<<5K-07 6<<3K-08 3<< 8K~00 Ze SE-08 2<<1E 08 1.3K-O8 1<<QK 08 ENE 0. Or 8<<4K 07 i<<4K 07 ?<<SE 08 3 8<<&K-07 1 ~ 9K-07 9<<lK-08 S<<1K 08 'K 06 Z.GE-08 2<<3E 08 3.&E-08 2.?E-os loSE-08 le3E-08 Z<<ZE 08 1 ~ 7K-08 E KSE'e 6<<6E-07 1 SK 07 7 'K 08 4<<SK-08 7<<9E-08 2<<3E-"'08 l<<5E-08 1 Z~-'Ge SE Qe 1 &K 06 7 'K"07 1 ~ lK 0? 6<<1K 08 4 2E 08 3<< OE>>08 2 5E-08 2 ~ 1E 08 SSE Oo 4.9K-ob 9<<2K OT 3<<&K 07 l<<8E-07 lolK-07 '9 ~ OE 08 7<<1E-08 4 9E-08 S Oe 2-9E-06 4<<&E-0? l<<BE-07 OE-07 QE pg S 4E-08 FAZE-0? 4<<6K~08 3 'E-.OS SSM SW WSW 0 0 6<<SK-O? I ~ &K 07 6<<5K<8 4<<&E 08 '1 ~ SK 06 3.2K-O? 1.4K-O? 7 2 'K 06 6 3K-07 2 3K 07 1 ~K>>OY 'c 08 2<< 4K~OS Zo &K-08 4 'K-08 l<<8E 08 lo4E~OS 3<<ZE-OS 2<<YK-08 1 ~ 9K 08 7<<&K-08 5e 5"-O8 4 ZE-08 3 1E W WNM 0~ oe 6 ~ 3K 06' 'tE 06 SIZE-07 2 ~ &K 07 'K 1 06 8 'K 07 3 4K 07 1 ~ YK-07 1.?K-O7 4 <<2K~0? 9 1 'E SelE Q8 6.3E-ps 4ocE p8 6 OS NW Or Z ~ TK-06 5<<OK-07 2<<4&07 1 ~ 2E 07 7 &E-08 5.1E-os 4 'E 08 3 ZE-Or. NNM Ge l<<4K-06 2.9K-OY 1.ZE-O7 5 ~ eE 08 4<<SK-08 3 qK-08 Zeir -08 1<<SE PO N Oe 9<<SE-07 2 'E-07 8<<SK 08 ASK-08 3<<ZE 08 2 ZE-08 le?E 08 1 <<3K~0,~ I eAsE orsTANcE r>> k{rLKs r ~ILok{KTKas AFTO DESIGN SECT OLST 9<<OO 11.00 ~ ?9 5<<00 1 ~ 00 2<<00 2 ~ ?5 4<<30 ~I 14;48 17<<70 l<<27 e.o4 1061 3<<22 4<<42 92 NNK 0. 9<<SK 09 6<<6K'9 1 ~ 8E 07 Zo OK-08 1.4K-O7 &-ZE-08 4 4E-08 2 'K-Oe NF. KNK K Oe 0~ 0 7 <<3K 09 5<<4K~09 1 '1 lEO87 4K09 ~ 3E-08 9 'K-09 1 SK 07 I <<&K-OS 1 ~ lE-07 4<<uK-p& 3 ~ SE-08 2 ~ i<<4K OY Z.OK-oe l<<OK-07 5 ZE-08 3.&K-pa 2 le7E 07 2<<4K'8 1.3f-o? 6.3K-O8 4 &K-08 7 'E-08 '4'-08GQ SE 0 0~ lo)K-08 9<<5K 09 ASK-08 l<<3E-08 1.4K-07 2 ~ OK~08 1. 2"=-0? 5<<?E-03 4 ~ OK'-0 s 2 2<<7E-.07 Z<<7K-08 1 ~ 9K-07 Y.GE-OA 5<<SE 09 3 ~ 1K 08 'E OG SSE C~ 3<<SE-08 2 'E-08 8-YK-07 7<<5F 08 6 3K-0? 7 ~ SK'? 1.&E-o7 9 4r ming S 0~ 2<<3K-08'.SE-OS 4.2E-07 S.OK-G8 3<<IK-07 1 3K-07 9 SK 08 5.eK-O8 SS'A G. 9<<4K-O9 7 'E 09 1.5E-07 2 'r-GS 1 'K"OY 5<<4E-08 3.8E-c8 2<<S; -08 SW n<< 1.4K-OO 1.OE-O& 2<<ZE-OS USE"08 3<<OE OY 7 'K 06 2 3<i~07 3C-07 6.9K-08 S<<9K OY 4<<GK-GR 4 ~ 3K' 1<<?K-07 lo<<OE-07 5.&E-OS Ge @Std 0<< " lg 0~ 4<<SK-OS ASK-08 ) ~ ZK-06 1.0K-o7 9 'K-07 2 3E07 1 3K<<0? Okapi 0~ 2 'K-OG 2 ~ K-OS Y ~ IK-OG 5 9K-07 2.3E-o7 1.GE-OY NM 0<< 2.OE-O8 1.5E-O8 S<<&K~0? Yr 08 4<<JK 07 1 ~ 6K-07 Or-0 7 N>AI 0<< 1.OK-O8 8.3r-o9 2 'K OY 2<<&K 08 2 ~ OK 0? 9.1K-QS boLE-08 N a. 1 Oc 08 pc 09 1 'K-OY 2 'E 08 1 SE-07 5 9K-08 4 ~ OE 08 Z 3" -08 NOH'+ OF V LID OSSERVATIONS 16538 >>Uk{&Co Or I'<V<LiO CG~KRVAT IOUS 1006 Nvk.AK> GF CAL {S LC.ocP LcVKL 155 NL.P R OF C-'LHS VeoKA Lr')KL ~ 383 Table 3-7 REMtENCE HETEOROGKY DEPOSITION DEPLETED ANNUAI AVERhGE AMOSPHERIC DISPERSXOM FACTORS X sec 3 J g /g are annuaL averaged factors of atmospheric dispersion of & m~ mode release fro)m the Turkey Point Plant which have been corrected fox depletion from the plume by fallout and deposition. Period of Record: QL/01/76 to 12/3L/77 BASK OISTANCK IN i4lILES / Kll.OHETERS kFTO OK SIGN SKiT 0 I ST e25 ~ 75 lo50 2oSO . 3o50 4oSO SeSO 'Te OO Ht ~ 40 lozl Zo4'l '4' 02 5o63 To24 So85 LL oZ6 NNK Oo ~ So7K 07 1 ~ 7K 07 7o3K 08 4o4K 08 2oVK 08 1e9K 08 1 oCK-08 I.ZE-QO t4K 0~ 6e9E 07 1 4K>>07 SoSE .08 3o3K 08 ZoZK-08 1 ~ 7K OS le?c 08 8 Gc C9 ENE 0~ 8eOK-07 loZK 07 6eSK 08 3o4E 08 2 o4K-OS ZeOE>>08 le6E 08 1 ZE-CS E Oe &oGK-07 1 ?K-07 7o6K 08 4e4K-08 ~ 3 1K-08 Ze4&08 1 o9K>>08 I SE"QQ 6 '1K 07 1 ~ ~~-'07 6o9~-08 3o Fi-08 l 2 'SK-08 2 OK OS o6E-Oe lolK-08 ESK sK ssK Oe Oo Qo leSE-06 2 'K 07 ASK Oh 5 ZK 08 4o?E-06 8 'E-07 3 IE-07 1 ~ SE 07 3o4K 08 24K08 2 lKOS 1 9 ZE"08 ?o4K>>08 5 RK-OS 3oSE 38 'K 08 0 ~. 2 BE 06 4 ZK 07 loSK 07 BISE-08 5 4F 08 4.4E-OB 3e?K 08 2o6h-Ce S SSM 0~ 6~ '5elE-07 1 (oE-Or So5E 08 3 ~ lo3E 66 Ze&K"07 1.3E-o? 6 'c,>>08 'E 08 2 OE-08 2.2E-O8 1 Sc 08 1 'K>>08 4o?E 08 2.7E-08 zo3K-OB SH ASM 0~ Zo?E-66 So6E-Or 2o1K-0? 1 'K-07 6e4E 0& 4o 6E-06 3eSE-08 Zo(tK 08 Oe ,'5o9K 05 1 2E 46 4e4K 07 2 ~ ZK-07 1 4E-07 9 9E-08 7o6K-08 5.4K-QS QNQ 0~ Oo 3 BE-66 ? ~ ?K-07 2 'E-07 1 SE-07 2oS"-06 5 4E-07 2olc 07 1 ~ 1K 07 9 'K ~ 08 ?oOE 08 BK-OB 4:SK-Oe So4E 08 3 6K 68 3o&K-08 Z.&E-oa NM ~ NN'e! 0~ 1 o4c. 06 7. ~ AE-4? lo1C-07 6oQE>>08 4 ~ OE-08 Zo 6E-0$ ZoOK G8 1 o~E-) 0 0~ Ge BK-07 1 ~ 9E 07 ?oRE 08 3o9E-08 Z.BE'>>a8 le 9E-08 loSE-08 le LE OO BASK OISTANCE IN HILKS J l(lIL.OHETERS AfTO OESIGN SECT GIST MI 9 ~ 00 14 48 11 ~ OO 1?o70 ~ le27 79 5 ~ Oo Be04 1 ~ OO 1o6j 2oOO 3o22 4o@'o30 2o75 6o92 'NNE 0~ B.SE-o9 6.OK-O9 1.6E-O7 BE 68 1.2E-.O7 SoSK>>08 3e SK-OG 2 o 1E-CD NK 0~ 6o3E 49 4oSE 09 1 ~ 3E 07 le4E-08 9o4E-08 4 ZE 08 30KOS ENE K 4~ 0 9.OK-O9 6 'K 09 1 ZE 07 lE-CB 7 9K-09 .,1oSK 07 loSE-08 9olE-68 4o5c 08 2 'E-08 ).ZK-O? SoSE-08 3r 1K 08 3 9KQB ZO-68 Z ~ 4K-68 ESK Ce 8 ~ BK-09 Se3K 09.1e3K 07 >.a -OS ).QE>>07 SAUCE-08 3 ~ 4c, 08 ZeCC-0& SK 0~ le3K-08 l~OK 08 2 4E 07 Zo3K-QB 1 ~ 7E-07 4 e7E-QB SSK 0~ Zo7E-08 2 ~ lK-OB 7'o7K-07 6o4K 08 Se6K-07 ~ 2K 07 L ~ 3c'>>07 7o(K-03 S Oo 1 'E-08 lo3c. 08 3oQK 07 4 'E-06 'E-0?2 1~ 1K-07 7 CE Ou 4oSC"OB SS'M Oo 7 9K 09 A ?~-09 lo4E 07 1 ~ GE 08 9o6C OB 4o7C 08 3 ~ ZE-OR 2.? c S'8 0~ l,lK-QS 8 ~ 6E-O9 2 ~ ?E. 07 2 4K-o& 2 OK-O7 LE>>OB 5 9E>>oo 2 'c-OB WSM Oe lo&K 08 )o4E>>08 5 ZE-07 4oOK OS 3 SE-07 lo4K>>07 8.7E-.O& 4 ~ OE-(;0 Oo 'E-03 USE-OO lolE 66 8 6+ 08 7 o9K-07 3 lK-O 2 ~ OE 07 NV 6 3 USE>>OG 2 'E BE-08 1 'K-OB 09 7 'K 07 5 ~ ] E-0? 2 ~ O~-07 1 o4K 07 SilK-07 lK>>08 3 ~ 6E>>O? lo4K>>O? 7+4f

5. QC-r,2 0~

NNH N Oe 0~ 1 9 ~ 1E 69 6 ~ 9K Q9 Be7E-09 6-3E-09 2 'E 07 7 'K 08 1.RK-O? 7 7K-08 5 4E GS 1.&K-O? 1 ~ 7C-08 1 o3K>>07 3oSK>>OG 2 ~ GE>>08 2 ~ QE QS NU(ABER Of VALI 0 CBSE.".Vk TI Ot4S 1G538 NVNeE~ Of INVA( IO CHSERvAYIC'-'S 1006 NlJYQ 2 Cf Ck) ',15 l.C J 9 l.EVEL 195 NUBBER CF Ckt.HS V&PER t.F.'lEl 383 I 0