Text

Offsite Dose Calculation Manual
	ML20024F553
Person / Time
Site:	Wolf Creek
Issue date:	08/31/1983
From:	; KANSAS GAS & ELECTRIC CO.
To:	;
Shared Package
ML20024F547	List: ML20024F546; ML20024F553;
References
	PROC-830831, NUDOCS 8309090470
	Download: ML20024F553 (65)
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OFFSITE DOSE CALCULATION MANUAL for i

Kansas Gas and Electric Wolf Creek Generating Station i

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P309090470 830831 PDR ADOCK 05000482 -

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TABLE OF CONTENTS Page 1.0 Introduction 1 2.0 Liquid Ef fluents 1 2.1 Liquid Ef fluent Monitor Setpoints 1 2.2 Liquid Effluent Concentration - Compliance with 10 CPR 20 4 2.3 Liquid Effluent Doses - Compliance with 10 CFR 50, Appendix I 5 3.0 Gaseous Ef fluents 7 3.1 Gaseous Ef fluent Monitor Setpoints 7 3.2 Gaseous Effluent Concentration / Dose Rate - Compliance with 10 CFR 20 9 3.3 Gaseous Effluent Doses - Compliance with 10 CPR 50, Appendix I 14 4.0 Radiological Environmental Monitoring Program 22 Appendix A: Dose Conversion Factor Tables A-1 Appendix B: Accident Doses B-1

m LIST OF TABLES Table Page 4-1 Radiological Environmental Monitoring Program 23 4-2 Sampling Location Numbers, Distance (miles) and Directions 26 A.1-1 Bioaccumulation Factors to be Used in the Absence A-2 of Site Specific Data A.1-2 Dose Factors for Noble Gases A-3 A.2-1 Inhalation Dose Factors for Adults A-4 A.2-2 Inhalation Dose Factors for Teenagers A-7 A.2-3 Inhalation Dose Factors for Child A-10 A.2-4 Inhalation Dose Factors for Infant A-13 A.2-5. External Dose Factor for Standing on A-16 Contaminated Ground A.3-1 Ingestion Dose Factor for Adults A-18 A.3-2 Ingestion Dose Factor for Teenagers A-21 A.3-3 Ingestion Dose Factor for Child A-24 A.3-4 Ingestion Dose Factor for Infant A-27 A.3-5 Stable Element Transfer Data A-30 A.4-1 Total Dose Factors for Radionuclides A-31

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1.0 INTRODUCTION

The Offsite Desa Calculation Manual (ODCM) describes the methodology and parameters to be used in the calculation of of fsite doses due to radioactive liquid and gaseous ef fluents.

These dose estimates are used to demonstrate compliance with the Radiological Ef fluent Technical Specifications as requir-ed by 10 CFR 50.36,10 CPR 20.106,10 CFR 50 Appendix I, and 40 CFR 190. The ODCM contents are based on " Preparation of Radiological Ef fluent Technical Specifications for Nuclear Power Plants (NUREG-0133) ," and Regulatory Guide 1.109, Revision 1.

The ODCM provides the methodology to be used in the calcula-tion of liquid and gaseous effluent monitor alarm / trip setpoints to assure compliance with the concentration and dose limitations of the Radiological Ef fluent Technical Specifications.

The ODCM provides the Radiological Environmental Monitoring Prog ram . The program consists of monitoring stations and sampling programs designed to confirm the dose estimates made under normal or accident conditions, and conform to NRC requiremnts in 20 CFR Part 50.

The ODCM also provides a description of the methods used to calculate offsite doses in the event of an emergency.

2.0 LIQUID EFFLUENTS 2.1 LIQUID EFFLUENT MONITOR SETPOINTS The alarm / trip setpoints for the liquid effluent radiation monitors are based on the instantaneous concentration limits of 10 CFR 20, Appendix B, Table II, Column 2 applied at the boundary of the restricted area. Specifically, the High Alarm setpoint will correspond to the 10 CFR Part 20 limits a*. the boundary of the restricted area; the alert alarm setpoint is set one order of magnitude below the High Alarm / Trip setpoint. Since the High Alarm / Trip initiates isolation of the particular system and termination of the release, this setpoint represents assurance that the instan-taneous liquid release limit of 10 CFR Part 20 is not exceeded. Auditable records shall be maintained indicating the actual setpoints used at all times.

ODCM 1 08-29-83

O s 2.1.1 CONTINUOUS LIOUID EFFLUENT MONITORS The two monitors associated with continuous liquid releases are listed below:

Monitor ID Description 0-BM-RE-52 Steam Generator Blowdown Discharge Monitor 0-LE-RE-59 Turbine Building Drain Monitor The steam generator blowdown discharge effluent monitor continuously monitors the blowdown discharge pump outlet to detect excess radioactivity due to system domineralizer breakthrough or abnormal primary to secondary leakage. The blowdown discharge monitor's high alarm setpoint initiates closure of the blowdown isolation valves and the blowdown discharge valve. Similarly, the high radiation alarm on the turbine building drain monitor initiates closure of the drain line isolation valve to prevent the release of radio-active effluents.

Monitor setpoints will be conservatively based on I-131, the most restrictive isotope expected to be present. This is particularly appropriate for the turbine building drain line monitor since the most probable source is the secondary steam system which is expected to have negligible activity unless there is a significant primary to secondary leak.

Due to changing activities, it will not be possible to select a radionuclide distribution on which to base the monitor setpoint. Additionally, maximum ef fluent flows and minimum dilution flows will normally be assumed.

The High Alarm / Trip Setpoint will be set to correspond to the I-131 MPC limit at the boundary of the restricted area from 10 CFR Part 20, Appendix B, Table II, Column 2. The alert alarm is set one order of magnitude below the high alarm / trip setpoint. This high alarm / trip setpoint assures the limits of Specification 3.11.1.1 are not exceeded at the boundary of the restricted area.

. In the event that an alarm is tripped, an evaluation of the

, system will be made by taking an actual isotopic and flow analysis of the discharge.

The above continuous liquid effluents are not radioactive effluents until activity has been detected by the liquid effluent monitor, a tritium analysis of the secondary system, or a gross beta analysis of the secondary system.

At that time an analysis of the effluent will be made to' i

verify activity in the system effluent.

ODCM 2 08-29-83

1 i

2.1.1.1. STEAM GENERATOR BLOWDOWN DISCHARGE MONITOR Fm+ Fg SETPOINT ( ACi/ml) = MPCI -131 X FB where, MPC I -131 = Maximum Permissible Concentration of I-131, 3.0 E-7 juCi/ml.

Fm = Dilution flow rate.

FB = Blowdown flow rate.

The setpoint calculation is based on the minimum dilution flow rate, the maximum possible blowdown flow rate, and, due to changing conditions, I-131 which is the most restrictive isotope expected to be present.

On the event that an alarm is reached, the setpoint will be re-evaluated using the actual dilution flow rate, the actual blowdown flow rate, and the actual isotopic analysis. This evaluation will be used to ensure the limit of Specification 3.11.1.1 was not exceeded. The setpoint will still be based on the MPC of I-131 due to the changing conditions of activity and I-131 being the most restrictive isotope.

2.1.1.2 TURBINE BUILDING DRAIN MONITOR Fm+ FT Setpoint pgCi/ml) = MPCI-131 X FT where, MPC I -131 = 3.0 E-7j uCi/ml.

Fm = Dilution flow rate.

FT = Turbine Building drain flow rate.

l The setpoint is based on the minimum dilution flow rate, the maximum possible Turbine Building drain flow rate, and the most restrictive isotope expected to be present, I-131.

On the event that an alarm is reached, the release will be evalu-ated to see if the limit of Specification 3.11.1.1 was exceeded by using the actual dilution flow rate, the actual Turbine Building drain flow rate, and the actual isotopic analysis. The setpoint will still be based on the MPC of I-131 due to the changing conditions of activity and I-131 being the most restrictive isotope.

ODCM 3 08-29-83

l 2.1.2 BATCH RADIOACTIVE LIQUID EFFLUENT MONITOR The two monitors associated with liquid batch releases are listed below:

Monitor ID Description 0-HF-RE-45 Secondary Liquid Waste System Monitor 0-HB-RE-18 Liquid Radwaste Discharge Monitor The setpoint is a function of dilution flow rate, tank flow rate, and isotopic composition. A laboratory isotopic analysis is made of each batch prior to discharge. Based on the isotopic analysis and existing flow condition, the setpoint will be calculated and set on the appropriate monitor to ensure the concentration limits of 10 CPR 20, Appendix B, Table II, Column 2 are not exceeded. The setpoints are determined using the following methodology:

1. A sample will be taken from the tank to be discharged and an isotopic analysis performed.

2. A monthly sample will be taken from the lake at the discharge area and an isotopic analysis performed.

SetpointjgCi/ml) (f (P ) (MPCi - LC )) (F + Frh

=

i i p j where, Pi = C i/CT where, Pi = Fraction of the total activity which is the ith isotope.

Ci = Concentration of the ith isotope,jaci/ml.

CT

Ci = Total concentration of sample.

LCi = Concentration of the ith isotope,fCi/ml already contained in the receiving water at the boundary of the unrestricted area.

MPCi = Maximum Permissible Concentration of the ith isotope.

Fw = Dilution flow rate.

F = Waste tank discharge rate.

ODCM 4 08-29-83 r -

r- *, - - - - . - -

- ~ ~ - - .

2.2 LIQUID EFFLUENT CONCENTRATION - COMPLIANCE WITH 10 CFR 20 Specification 3.11.1.1 requires that the radioactive material released in liquid effluents to unrestricted areas shall be limited to:

a. The concentrations specified in 10 CFR Part 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases.

b. For dissolved or entrained noble gases, the concen-tration shall be limited to 2 x 10-4 su.Ci/ml total activity.

To show compliance with this specification, concentrations of actual liquid ef fluents will be determined by performing an isotopic analysis. The liquid effluent monitors will provide assurance that the liquid concentration limits are not exceeded.

2.3 RADIOACTIVE LIQUID EFFLUENT DOSES - COMPLIANCE WITH 10 CFR 50, Appendix I Specification 3.11.1.2 requires that the dose to an individual from radioactive materials in liquid ef fluents released to unrestricted areas shall be limited to:

a. During any calendar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 mrem to any organ, and

b. During any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ.

To show compliance with this specification, cumulative dose

contributions from actual liquid ef fluents will be determined using the following methodology

m D

T=i (AiT 13L=1 6 t L Cin FL) where, l DT = the cumulative dose commitment to the total body or

any organ, T, from the liquid effluent for the total l m timeperiod{l Att, in mrem.

l otL = the length of the Lth time period over which C i n j and FL are averaged for all liquid releases, in hours.

l ODCM S 08-29-83 i

C i n = the average concentration of radionuclide, 'i', in undiluted liquid ef fluent flow during time period at g, in jtCi/ml FL = the near field average dilution f actor for Cin during any liquid ef fluent release where:

f FL= (F) K where:

f = Liquid Radioactive Waste Flow F = Discharge Structure Exit Flow, the sum of the release and dilution flow.

K = Applicable factor; the site dependent value for the mixing ef fect of the discharge structure.

This value is conservatively assumed to be 1 (one) for this section.

AiT = the site related ingestion dose commitment factor to the total body or any organ, 'T', for each identified principal gamma and beta emitter, mrem /hr per uCi/ml:

j AiT = 1.14E5 (Uw/pg + Up. BFi) DFi where, DW = Dilution factor from the near field area to the potable water intake for water consumption, for Wolf Creek Generating Station this factor is 1 (one).

BFi = Bioaccumulation f actor for radionuclide, 'i', in fish, pCi/Kg per pCi/1, from Table A.1-1 from Regulatory Guide 1.109 (Rev. 1)

DPi = Dose Conversion factor for radionuclide, 'i',

in mrem /pci, from Table A.3-1 thru A.3-4 from Regulatory Guide 1.109 (Rev. 1) .

Uw = Water consumption, in kg/yr.

Up = Fish consumption, in kg/yr.

1.14E5 = units conversion factor = 10 6 pCi/xCi X 10 3 ml/Kg 87 6'O hr/yr ODCM 6 08-29-83

The dose calculations are based on the actual isotopic analysis of the radioactive liquid ef fluents, the radioactive liquid effluent flow, and the dilution flow.

3.0 GASEOUS EFFLUENTS 3.1 GASEOUS EFFLUENT MONITOR SETPOINTS The alarm / trip setpoints for the gaseous ef fluent radiation monitors are based on the instantaneous concentration limits of 10 CFR Part 20, Appendix B, Table II, Column 1 applied at the boundary of the restricted area. Specifically, the setpoints will be based on maintaining the concentrations of the most significant isotope, expected to be present and detectable, below the maximum-permissible concentrations for an unrestricted area. Although the gaseous effluent monitors are also sensitive to radioiodine and particulates accumulated on filters, these channels are not suitable for instantaneous release limits; therefore, the alarm / trip setpoints will be based on Xe-133, which during changing conditions would be the most significant isotope.

3.1.1 CONTINUOUS, GASEOUS EFFLUENT MONITORS The plant has ' tato gaseous ef fluent release points. The associated monitors are' listed below.

Monitor ID Release Point Description O-GT-RE-21 A and B Unit Vent (fuel / auxiliary building, access control area, o containment purge, condenser air discharge)

O-GH-RE-10 A and B Radwaste Building Vent (Radwaste building, waste

, gas decay tank discharge) l The unit vent monitor has only an alarm function and is used to monitor the normally low activity associated with continuous releases.The radwaste building vent serves as both a continuous and batch monitor; this monitor has an alarm function and also functions to isolate the waste gas decay tank discharge.

ODCM 7 '08-29-83

Since there are two gaseous ef fluent release points, a fraction of the total MPC will be allocated to each release point. The fraction can be assigned based on the results of the PWR-GALE results (FSAR Table 11.1-2) . Neglecting the batch releases, the plant unit vent monitor will be originally allocated 0.7 MPC and the radwaste building exhaust will be allocated 0.3 MPC and will be changed or set as required but limited to 1.0 MPC of Xe-133.

Therefore, a particular monitor reaching the fractional MPC setpoint would not necessarily mean the MPC limit at the site boundary is being exceeded; the alarm only indicates that the specific release point is contributing a greater fraction of the MPC limit than was allocated to the associated monitor and will constitute an evaluation of both systems.

The gaseous ef fluent monitor setpoints will be determined by using the most significant isotope (Xe-133) .

Setpoint ( Ci/cc) = (3 E-7)AF F *

(X/Q) where, 3 E-7 = MPC for Xe-133. (most significant isotope)

F = Vent flow, M 3/sec.

X/O = Atmospheric dispersion factor, 1.5 E-4 sec/m3, or current X/Q.

AF = Allocation Factor which takes into account the fraction of the MPC allotted to each individual moni to r.

The value of the X/O adopted in the setpoint calculation is based on the worst 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months value at the restricted area boundary in a 3 year measurement period.

l I

3.1.2 BATCH GASEOUS EFFLUENT MONITORS The monitors associated with the batch releases are listed below:

Monitor Release Point Description 0-GT-RE-22&33 Containment Purge System Monitor (acts to isolate the purge; is not an ef fluent monitor) 0-GH-RE-10 A and B Radwaste Building Vent (acts to isolate waste Gas Decay Tank Discharge Line)

ODCM 8 08-29-83

i Prior to each batch release an isotopic analysis is made of the

!~

contained activity to determine the identity and quantity of the principle radionuclides. If necessary, the existing setpoint will be decreased or increased.to ensure the concentration limits of 10

CFR Part 20 are not exceeded. Actually, since the primary purpose of the containment purge system monitor is to isolate the purge in

, the event of-accidental release, the setpoints will be maintained l at a level which is much more restrictive than is required by 10 CFR 20.

Setpoint ( Ci/ml)

= f - ((P4 F *

) (MPC1))

(X/Q))

where, Pi = C i /CT = Fraction of the total activity which is the ith isotope.

Ci = Concentration of the ith isotope,juCi/ml.

= Ci = Total concentration of sample.

CT 4

' MPCi = Maximum Permissible Concentration of the ith isotope.

F = Vent flow rate, in m3/sec.

X/Q = Atmospheric dispersion factor, 1.5 E-4 sec/m3,

, or current X/Q.

3.2 GASEOUS EFFLUENT CONCENTRATION / DOSE RATE

! - Compliance with 10 CFR 20 The Standard Technical Specification 3.11.2.1 requires that the instantaneous 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 values:

a. The dose rate limit for noble gases shall be <500 mrem /yr to the total body and <3000 mrem /yr to the skin, and i

i b. The dose rate limit for all radioiodines and for all radioactive materials in particulate form and radio-nuclides other than noble gases with half lives greater than 8 days shall be <l500 mrem /yr to any organ. .

L ODCM 9 08-29-83

- , , , . ~ , -n,., , , , , - - , , .~.-.,-,-v-.,- .--,-n- - v--, r---,--m.--n-..-,,,n,,n,~,, -,v-+,,,-,,, y

Based on the methodology of NUREG-0133;

a. Release rate limit for noble gases:

f*K i (X/Q) Qi <500 mrem /yr for the total body, and f(Li + 1.1 M ) i(X/Q) Qi <3000 mrem /yr for the skin.

where:

Ki = Total body dose factor due to gamma emissions for each identified noble gas radionuclide, in mrem /yr per juCi/m3 , from Table A.1-2.

(X/Q) = 1.5 E-4 sec/m 3 , the most restrictive X/0, during a 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months period, at the restricted area boundary, (Based upon historical data contained in the FSAR.) or current X/Q.

Qi = Release rate of radionuclide i from vent, in

,gCi/sec.

Li = Skin dose factor due to beta emissions for each identified noble gas radionuclide, in mrem /yr perj uci/m3 , from Table A.1-2.

Mi = Air dose factor due to gamma emissions for each identified noble gas radionuclide, in mrad /yr perj aci/m3 from Table A.1-2.

1.1 = Conversion constant of air dose to skin dose.

b. Release rate limit for all radionuclides and radio-active materials in particulate form and radionuclides other than noble gases:

f(Pox (i) Qi) <l500 mrem /yr to any organ, where:

Qi = The release rate of radionuclides, i, in gaseous effluent from all vent releases, in j aci/sec.

Pox (i) = P(i)IN * (X/Q) + P(i)GR - (D/Q) + P(i}p * (D/Q)

See Table A.4-1.

ODCM 10 08-29-83

where:

P(i)IN = The dose parameter for radionuclides other than noble gases for the inhalation pathway, in mrem /yr perjaci/m3 See Table A.4-1.

P(i)GR = The dose parameter for radionuclides other than noble gases for the ground plane pathways in (m2. mrem /yr per juCi/sec). See Table A 4-1.

P(i) p = The dose parameter for radionuclides other than noble gases for food pathways, in (m2. mrem /yr perj aci/sec) . See Table A.4-1.

X/O = 1.5 E-4 sec/m3 (most restrictive value for 0-2 hr. release and is used in FSAR) .

The highest calculated dispersion parameter for estimating the dose to an individual at the unrestricted area boundry in the NNW sector, or current X/Q.

D/0 = The highest calculated annual average relative deposition parameter for estima-ting the dose to an individual at the restricted area boundary in the N sector,

. 1.8 E-8 m-2 based on the FSAR.

NOTE: When calculating the dose due to tritium, use the X/O relative concentration (sec/m3) factor in place of the D/Q average dispersion (m-2) parameter.

All radionuclides are assumed to be released in elemental form.

The specification is applicable to the location (unrestricted area boundary or beyond) , characterized by the value of X/O which results in the maximum total body or skin dose commitment.

The factors Ki, Li, and Mi relate the radionuclide airborne concentrations to various dose rates assuming a semi-infinite cloud. These factors are taken from Table B-1 of the Regulatory Guide 1.109 and multiplied by 106 to convert pCi-1 to jnCi-1 and listed in Table A.1-2.

The following equations for Pi were taken from NUREG 0133:

P(i)IN (Inhalation) ;

P(i)IN = K' (BR) DFAi (mrem /yr perjaCi/m3)

ODCM 11 08-29-83

, - - - . . , , , , .- --- -. ,--,n.------v - - - -

o .

where:

K' = a constant of unit conversion, 106 pCi/jaci BR = the breathing rate of the inf ant age group in m3/yr DFA1 = the maximum organ inhalation dose factor for the infant age group for the ith radionuclide, in mrem /pCi. The total body is considered as an organ in the selection of DFA1 The age group considered is the inf ant group.

The infant's breathing rate is taken as 1400 m3/yr from Table E-5 of Regulatory Guide 1.109. The inhalation dose f actors for the inf ant, DFAi are presented in Table E-10 of Regulatory Guide 1.109, in units of mrem /pci.

. Resolution of the units yields:

Pi (Inhalation) = 1.4 X 109 DFAi See Table A.4-1 P (i) GR (Ground) ;

P(i) GR = K'K" (DFGi) (1-e- it) Ai (m2. mrem /yr perjuCi/sec) where:

K' = a constant of unit conversion, 106 pCi/aci K" = a constant of unit conversion, 8760 hr/yr Ai = the decay constant for the ith radionuclide, sec-1 t = the exposure period, 3.15 x 107 sec (1 year)

DFGi = the ground plane dose conversion factor for the ith radionuclide (mrem /hr per pCi/m2)

The deposition rate onto the ground plane results in a ground plane concentration that is assumed to persist over a year with radiological decay being the only operating removal mechanism for each radionuclide. The ground plane dose conversion factors for the ith radionuclide, DFGi, are presented in Table E-6 of Regulatory Guide 1.109, in units of mrem /hr per pCi/m2, ODCM 12 08-29-83 4

O s

, Resolution of units yields:

Pi (Ground) = 8.76 X 109 DFGi (1-e iA t}/A i See Table A.4-1.

P(i}p (Food) ;

P(1} p = K'r Op (Uap)A FmDFLi (e- itfj Yp(li+ w)

(m2. mrem /yr per j uCi/sec) where:

K' = a constant of unit conversion, 106 pCi/aci Op = the cow's consumption rate, in kg/ day (wet weight)

= the infant's milk consumption rate, in Uap liters / year Yp = the agricultural productivity by unit area, in kg/m2

= the stable element transfer coefficients, Fm in days / liter r = fraction of deposited activity retained on cow's feed grass DFLi = the maximum organ ingestion dose factor for the ith radionuclide, in sec-1 Ai = the decay constant for the ith radionu-l clide, in sec-1.

l Aw = the decay constant for removal of l

activity on leaf and plant surfaces by weathering, 5.73 x 10-7 sec-1 (corresponding to a 14 day half-time) .

l tg = the transport time from pasture to cow, to milk, to infant, in sec.

A fraction of the airborne deposition is captured by the ground plane vegetation cover. The captured i material is removed from the vegetation (grass) by

both radiological decay and weathering processes.

l l

l ODCM 13 08-29-83 l

-- - =, -. _- _ _ _ - _ . -.

and Yp are provided The values of QF, in Regulatory Uap,109, Guide 1. Tables E-3, E-5, and E-15, as 50 kg/ day , 330 liters / day , and 0.7 kg/m2, respectively. The value tp is provided in Regula-i tory Guide 1.109, Table E-15, as 2 days (1.73 X 105 sec). The fraction, R, has a value of 1.0 for radioiodines and 0.2 for particulates, as presented in Regulatory Guide 1.109, Table E-15.

Table E-1 of Regulatory Guide 1.109 provides the stable element transfer coefficients, Fm, and Table C-14 provides the ingestion dose factors, DFLi, for the inf ant's organs. The organ with the maximum value of DFLi is to be used.

Resolution of the units yields:

rm Pi (Food) = 2.4 x 1010 ( ) DFLi (e-Ei tg)

(: m2 . mrem /yr per pCi/sec)

See Table A.4-1.

The Pi values for tritium are:

Pi (Inhalation) = 1.4 x 109 DFAj Pi (Ground) = 0, due to being a weak beta emitter Pi (Food) = 2.4 x 103 mrem /yr perjaci/m3 1

3.3 GASEOUS EFFLUENT DOSES

- Compliance with 10 CFR 50 Appendix I 3.3.1 NO,BLE GASES Specification 3.11.2.2 requires that the air dose due to noble gases released in gaseous effluents to areas at and beyond the site boundary shall be limited to the following :

{ a. During any calendar quarter, to < 5 mrad for gamma radiation and j[ 10 mrad for beta' radiation;

b. During any calendar year, to < 10 mrad for gamma

! radiation and j( 20 mrad for beta radiation.

l l To show compliance with this specification, the dose calculations for the actual releases of radioactive noble gases in gaseous l effluent will be consistent with the methodology provided in Reg. Guide 1.109, Rev. 1. The following dose calculations will be performed:

i l

ODCM 14 08-29-83 l

a. During any calendar quarter; For gamma radiation; D= 3.17 E-8 d

,y Mi [(X/Q)

Qi] 1 5 mrad.

For beta radiation; D=3.17E-8fy Ni [(X/Q) -

Qi] 1 10 mrad.

b. During any calendar year:

For gamma radiation:

D = 3.17 E-8 ,y Mi [(X/Q)

Qi] 1 10 mrad.

For beta radiation:

D=3.17E-8fy Ni [(X/Q)

Qi] 1 20 mrad where:

3.17 E-8 = The inverse of the number of seconds in a year.

Mi = The air dose factor due to gamma emissions for each identified noble gas radionuclide, in mrad /yr persuCi/m3 from Table A.1-2 (Reg. Guide 1.109, Table B-1, Col. 4)

Ni = The air dose factor due to beta emissions for each identified noble gas radionuclide, in mrad / year perj uCi/m3 from Table A.1-2 (Reg.

Guide 1.109, Table B-1, Column 2). ,

X/Q = 1.5 E-4 sec/m3 The highest calculated relative concentration for any area at or beyond the unre-stricted area boundary for a two hour period, or current X/Q.

Qi = The average release of noble gas radionuclides,

'i', in gaseous effluents, in juCi.

An average monthly air dose schedule should be setup to ensure section 3.11.2.2 of Wolf Creek Technical Specifications are not exceeded. The average monthly air dose should be as follows:

a. For gamma radiation f 1.6 mrad /mo.

For beta radiation 13.3 mrad /mo.

b. For gamma radiation < 0.8 mrad /mo.

For beta radiation <~1.6 mrad /mo.

ODCM 15 08-29-83

If the monthly average air dose for: (a) is exceeded, it should be noted that if the release is continued at the same (or higher) frequencies or activities, Section 3.11.2.2 A of Wolf Creek Technical Specifications will be exceeded.

If the monthly average air dose for: (b) is exceeded, it should be noted that if the release is continued at the same (or higher) frequencies or activities, Section 3.11.2.2 B of Wolf Creek

. Technical Specifications will be exceeded.

If any of the above monthly average air doses are exceeded, evaluation of the causes of the high air dose should be performed and steps should be taken to reduce the activity or frequency of the release.

3.3.2 RADIOIODINES, PARTICULATES, AND OTHER RADIONUCLIDES Specification 3.11.2.3 requires that the dose to an individual from iodine-131 and 133, tritium, and all radioactive materials in particulate form with half-lives greater than 8 days in gaseous effluents released to areas at and beyond the site boundary shall be limited to the following:

a. During any calendar quarter to f 7.5 mrem; and

b. During any calendar year to f 15 mrem.

To show compliance with this specification, the dose calculations for the actual releases of the subject materials are consistent with the methodology provided in Regulation Guide 1.109, Revision

1. The following dose calculation will be performed:

a. 8 D (mrem) =

3.17E-8 i R1 (WQi) 1 7.5 mrem E

b. D (mrem) =

3.17E-8 i Ri (WQi) i 15 mrem where:

3.17E-8 = The inverse of the number of seconds in a year.

t Qi = The release of radioiodines, radioactive materials in particulate form and radionuclides other than noble gases in gaseous effluents, 'i',

in suci. Releases shall be cumulative over the calendar quarter or year as appropriate.

ODCM 16 08-29-83

. o W = The annual average dispersion parameter for estimating the dose to an individual at the controlling location.

W= (X/0) , 1.5 x 10-4 sec/m3, or current X/O for the inhalation pathway.

W= (D/Q), 1.8 E-8 m-2, for the food and ground plane pathways.

Ri = The dose factor for each identified radionuclide,

'i', in mrem /yr per ,jtci/m3 Ri=Rf[X/Q] +R[(D/Q] +R((D/g,x/g)

+R{[D/g,x/Q] + RV [D/g, x/g]

where:

Inhalation Pathway Factor, R [X/Q]

RI[X/Q] = K'(BR) a(DFAg ) a (mrem /Yr perjuCi/m3) where:

K' = a constant of unit conversion, 10 pCigaCi.6 (BR)a = The breathing rate of the receptor of age group (a) , in m3/yr.

The breathing rates (BR)a for the various age groups are tabulated below, as given in Regulatory Guide 1.109, Table E-5.

AGE GROUP (a) BREATHING RATE (* /yr)

Infant 1400 Child 3700 Teen 8000 Adult 8000 (DFA1)a = The maximum organ inhalation dose f actor for the receptor of age group (a) for the i th radionuclide, in mrem /pCi.

The total body is considered as an organ in the selection of (DPA1)a. See Tables A.2-1, A.2-2, A.2-3, & A.2-4. From Regula-tory Guide 1.109, Tables E-7, E-8, E-9, and E-10.

OCDM 17 08-29-83

Ground Plane Pathway Factor, RO[D/Q]

i RO[D/Q] = K'K" (SF) DFG i [(1-e- it} / A )1 (m2 . mrem /yr per,jtCi/sec) where:

K' = A constant of unit conversion, 106 pCi/aci.

K" = A constant of unit conversion, 8760 hr/ year.

t

= The decay constant for the i th radionuclide, sec-1 t = The exposure time, 4.73 E8 sec (15 years).

DFGi = The ground plane dose conversion factor for the ith radionuclide (mrem /yr per pCi/m2), see Table A.2-5. (Regulatory Guide 1.109, Table E-6) .

SF = The shielding factor (dimensionless), 0.7 (Reg.

Guide 1.109)

Grass-Cow-Milk Pathway Factor, R [D/Q]

1 R [D/Q] =K' (kF( ap)) Fm(r) (DFLi) a ( /Yp) (e - itf (m2. mrem /yr per j aci/sec)

K' = A constant of unit conversion, 106 pCi/uCi.

Op = The cow's consumption rate, in Kg/ day (wet we igh t) , 50 kg / day . (Reg. Guide 1.109, Table E-3).

U ap = The receptor's milk consumption rate for age (a), in liters /yr. (Reg. Guide 1.109, Table E- 5)

Infant = 330 1/yr Child = 330 1/yr Teen = 400 1/yr Adult = 310 1/yr Yp = The agricultural productivity by unit area of

.l pasture feed grass, in kg/m2, 0.7 kg/m2 (Reg.

Guide 1.109, Table E-15)

Pm = The stable element transfer coefficients, in days / liter, See Table A.3-5. (Reg. Guide 1.109, Table E-1)

OCDM 18 08-29-83

r =

Fraction of deposited activity retained on cow's feed grass, r=1 for radiciodine and r= 0.2 for particulates. (Reg . Guide 1.109, Table E-15) .

(DFLi)a = The maximum organ ingestion dose factor for the i th radionuclide for the receptor in age group 'a ', in mrem /pCi. See Tables A.3-1, A.3-2, A.3-3, and A.3-4. (Reg. Guide 1.109, Table E-ll, E-12, E-13, and E-14) di = The decay constant for the ith radionuclide, in see -1 Aw = The decay constant for removal of activity on leaf and plant surf aces by weathering , 5.73 E-7 sec-1 (corresponding to a 14 day half-life) .

tg = The transport time from pasture to cow, to milk, to receptor, in sec, 1.73 E5 secs (2 days). (Reg. Guide 1.109, Table E-15) .

NOTE: The fraction of the year that the cow is on pasture

.and the fraction of the cow feed that is pasture grass is assumed to be 1.0, which is the most '

restrictive case.

The concentration of tritium in milk is based on the airborne concentration rather than the deposition. Therefore, the RC is based on (X/Q), 1 R [X/Q] = K ' K" ' FmOPUap (DFLi)a [0.75 ( 0. 5/H) ]

(mrem /yr perjuCi/m3) where:

K"' = a constant of unit conversion, 103 gm/Kg. .

H = Absolute humidity of the atmosphere, 8 gm/m3 (Reg. Guide 1.109) .

0.75 = The fraction of total feed that is water. (NUREG 0133) 0.5 = The ratio of the specific activity of the feed grass water to the atmospheric water. (NUREG 0133)

Grass-Cow-Meat Pathway Factor, R ID/Q]

1 R"[D/Q] =K' (SPdEapl)Pg (r) (DFLi) a (1/Yp) e ~if i

Ag+A, (m2 mrem /yr per ,pCi/sec) l OCDM 19 08-29-83

- - - , , - . . -, -- - - - < - - e ---4 ---, - - - , - , - , -,,

_ _ . _ _ . . . - _ _ . _ ._. _ ._. _m_ _ _ _ - _ _ _

where:

Ff = The stable element transfer coefficients, in days /kg, Table A.3-5. (Reg. Guide 1.109, Table E-1).

Uap = The receptor's meat consumption rate for age (a), in kg/yr. (Reg . Guide 1.109, Table E-5)

Infant = 0 Child = 41 i Teen = 65 4

Adult = 110 i

tg = The transport time from pasture to receptor, in sec., 1.73 E6 (20 days) (Reg Guide 1.109, Table E-15) .

s The concentration of tritium in meat is based on its airbornc concentration rather than the deposition. Therefore, the RM is based on (x/g) : i R [X/Q] = K'K"' Pg Qg Uap (DFLi)a [0. 75 (0. 5/H) ]

(mrem /yr perj aci/m3) i where:

All terms defined above.

Vegetation Pathway Factor, R [D/Q]

Man is considered to consume two types of vegetation (fresh and stored) that differs only in the time period between harvest and consumption, therefore:

R [D/Q] =K' -[y gg #A )] (DFLi) a [ (Uh) (fL) (e it L)+(U$) (f g ) (eith))

(m2 . mrem /yr perpCi/sec) j where:

l K' = A constant of unit conversion, 106 pCi/uCi.

f l

OCDM 20 08-29-83 I

t

~

Ua = The consumption rate of fresh leafy vegetation .by the receptor in age group (a) ,

in kg/yr. (Reg Guide 1.109, Table E-5) .

Infant = 0 kg/yr ,

Child = 26 kg/yr Teen n 42 kg/yr Adult = 64 kg/yr 8

U a

= The consumption rate of stored vegetation ~ by the receptor in age group (a) ,

Kg/yr. .(Reg Guide 1.109, Table E-5) .

Infant = 0 kg/yr Child = 520 kg/yr Teen = 630 kg/yr Adult = 520 kg/yr.

fL =

The fraction of the an.nual intake of fresh leafy vegetation grown, locally. (def ault = 1. 0)

(Reg. Guide 1.109) .

fg = The fraction of the annual intake of stored ,

vegetation grown locally. (def ault = 0.76) ,

(Reg . Guide 1.109) .

tL = The average time between harvest of loafy vegetation and its consumption,-in seconds, 8.6 E4 secs (1 day). Reg. Guide 1 109) . -

th = The average time between harv~est of stored vegetation and its consumption, in seconds, 5.18 E6 secs (60 days) (Reg. Guide 1.109, Table E-15) .

~

Yv = The vegetation area density, 2.0 kg/m 2, (Reg. Guide 1.109, Table E-15) . ,

All other factors previously defined r The concentration of tritium in vegetation is based on the alr-borne concentration rather than the deposition. Therefore, the RV is based on (X/Q):

R [X/Q] = K' K"' [UhfL + U! f ]g (DFLi)a [0.75 (0. 5/H) ]

(mrem /yr perjnCi/m3) where:

All terms defined previously. All values indicated are default values from Reg. Guide 1.109, Rev. 1.

t OCDM 21 08-29-83

~ \

l

~

An average monthlyf air dose cchedule should be setup to ensure Section 3.11.2.3 of Holf Creek Technical Specifications are not exceeded. The average, monthly air dose due to radiciodines, particulates, and other radionuclides which are included in this

section should be as follows

a. < 2.5 mrem /mo.

,' b. < 1.25 mrem /mc.

'I #

If _'the monthly average air dose for (a) is exceeded, it should be

- 'ndted that if .the release is continued at the same (or higher)

' ' . 'O ' ~

~ frequencies or activities the quarterly limit of Specification

- 7,3.11.2.3 A will be exceeded.

i i t. \ '

' 'If the monthly average air dose for (b) is exceeded, it should be

._ noted that if ~ the release is continued at the same (or higher)

,. frequencies or activities the yearly limit of Specification l / 3.11. 2. 3 B will ' be . exceeded .

If any of the above, monthly air doses are exceeded, evaluation of the causes should to performed and steps taken to reduce the activity or f requency of ' the release. ,

4.0 RADIOLOGICAL ENVINONMENTAL' MONITORING PROGRAM Table 4.1 gives'.. specific Radiological Environmental sampling pathways,

, locations and frequencies corresponding to Table 3.12-1 of Wolf

" Creek Technical; Specifications. Maps showing these locations in relation to the Wolf Creek site are shown in Figures 4.1, 4.2 and 4.3; Table 4.2;11s~ts distances and directions from the site to the sampling locations.

w /

f g

~

- p 4

ODCM 22 08-29-83 t

, - , , s - . . . , - - - - - . , - . - - - - - --- , , , . - . , - _ _ , , , . . , , , _ . , , , , - . . . _ , , , - - - - - _ _ , . . , . . _ . _ _ . , , _

s.

o O

' TABLE.4.1 Sheet 1,0f 3' n

3 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM' _

Number of Samples Exposure Pathway and . Sampling and . Type and Prequency and/or Sample Sample Locations Collection Frequency of Analysis

1. AIRBORNE RadioiOd'ine and Five locations, ' Continuous operation Radiciodine canister.

Particulates station numbers 2, of sampler with sample Analyze weekly for 3, 31, 37 and 40 collection as required for I-131.

(control) Figure 4.1. by dust loading but at least weekly. Analyze for gross beta

. radioactivity not less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following w filter change. Perform

~

gamma isotopic analysis l 3 on cach sample whensgross-

' beta activity is greater than 10 times the yearly mean of control samples.

Perform ~ gamma isotopic analysis on composite (by location) once per -

quarter.

, 2. DIRECT RADIATION 38 TLD_ locations within Quarterly at each _ Gamma dose quarterly.

, 5-mile radius of site location. '

(station numbers 1-38 '

on Figure 4.1) and

two offsite locations

'o , (stations 39 and 40);

i y 7- two TLD dosimeters at N each location.

-1 m

i W

l

a TABLE 4.1 Sheet 2 of 3 O

8 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 2

Number of Samples Exposure Pathway and Sampling and Type and Frequency and/or Sample Sample Locations Collection Frequency of Analysis

3. WATERBORNE

a. Surface One upstream location Monthly grab sample ~ Monthly gamma isotopic near the John Redmond analysis. Ouarterly Reservoir spillway, one tritium analysis of sample _from Wolf Creek composite sample.

Cooling Lake.

b. Ground Three locations at Quarterly Quarterly gamma iso-C-10, C-49, D-65, topic and tritium N

one control location analysis.

at B-12 (see Figure 4.2).

c. Drinking Municipal water Monthly composite Monthly gross beta and supplies at Burlington gamma isotopic analysis.

(upstream) and Le Roy Quarterly tritium analysis (downstream). of composite sample,

d. Sediment from One sample from Semiannually Semiannual gamma iso-Shoreline discharge cove area topic analysis.

of the Wolf Creek Cooling Lake.

o 3 *

.i composite sampling shall be performed by collecting an aliquot at intervals not exceeding 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

W

i i

~

TABLE 4.1 Sheet 3 of 3 o

S RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM x

Number of Samples Exposure Pathway and Sampling and Type and Frequency and/or Sample Sample Locations Collection Frequency of Analysis

! 4. INGESTION l

l a. Milk Samples from B-8, F-1, Semimonthly when Gamma isotopic and

! Q-5, and a control animals are on pasture; I-131 analysis of each l sample from S-3 monthly at other times. sample.

(Hartford); alternate locations are P-2, l and C-11 (see l

Figure 4.3).

i lN b. Fish One sample from Wolf Semiannually _ Gamma isotopic analysis l Creek Cooling Reser- on edible portions.

! voir, similar sample l from John Redmond l Reservoir spillway I as control.

l c. Food Products Broad leaf vegetation Monthly during harvest. Gamma isotopic analysis l samples at site bound- on edible portions.

l ary in sector with highest D/O (location A-1 on Figure 4.3);

control at S-4 (Hartford); alternate samples from locations l Q-1, R-1, and 0-2 as l m o available.

i 8

' N W

w

8 a -

3 TABLE 4.2 SAMPLING LOCATION NUMBERS, DISTANCES (miles) AND DIRECTIONS TLD and Air Particulate Location Distance / Location Distance / Loca tion Distance / Location Distance Number Direction Number Direction Number Direction Number Direction 1 1.4/N 11 1.6/E 21 3.8/S 31 3.0/WNW 2 2.7/N 12 1.8/ESE 22 4.1/SSW 32 2.8/WNW 3 3.0/NNE 13 1.5/SE 23 4.5/SW 33 4.1/WNW 4 3.7/NNE 14 2.6/SE 24 4.1/WSW 34 4.0/NW 5 4.0/NE 15 4.5/ESE 25 3.6/W 35 4.6/NNW 6 4.4/ENE 16 4.2/E 26 2.6/WSW 36 4.2/N 7 1.9/NE 17 3.6/SE 27 2.1/SW 37 2.1/NNW 8 1.6/NNE 18 2.8/SSE 28 2.8/SW 38 1.2/NW

$ 9 2.0/ENE 19 4.0/SSE 29 2.6/SSW 39 13.0/N 10 2.4/ENE 20 3.3/S 30 2.2/W 40 15.0/WNW Groundwater B-12 2.2/NE C-10 2.8/W C-49 2.9/SW D-65 3.9/S Milk and Food Products A-1 1.4/N F-1 1.6/ESE Q-1 1.3/NW R-1 2.2/NNW B-8 4.9/NNE G-1 1.4/SE Q-2 1.4/NW S-3 15.0/WNW o C-ll 5.2/NE P-2 2.9/WNW Q-5 3.6/NW S-4 15.0/WNW 7

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9 TLD $ Proadlear 'iegetation REV. 8/83 A Air Particulate A y ,suringing .. a3 ter E Milk

APPENDIX A Dose Conversion Factor Tables l

OCDM A-1 08-29-83

TABLE A.1-l*

BIOACCUMULATION FACTORS TO BE USED IN THE ABSENCE OF SITE-SPECIFIC DATA (pCi/kg per pCi/ liter)

FRESHWATER ELEMENT FISH INVERTEBRATE H 9.0E-01 9.0E-01 C 4.6E 03 9.lE 03 Na 1.0E 02 2.0E 02 P 1.0E G5 2.0E 04 Cr 2.0E 02 2.0E 03 Mn 4.0E 02 9.0E 04 Fe 1.0E 02 3.2E 03 Co 5.0E 01 2.0E 02 Ni 1.0E 02 1.0E 02 Cu 5.0E 01 4.0E 02 Zn 2.0E 03 1.0E 04 Br 4.2E 02 3.3E 02 Rb 2.0E 03 1.0E 03 Sr 3.0E 01 1.0E 02 Y 2.5E 01 1.0E 03 Zr 3.3E 00 6.7E 00 Nb 3.0E 04 1.0E 02 Mo 1.0E 01 1.0E 01 Tc 1.5E 01 5.0E 00 Ru 1.0E 01 3.0E 02 Rh 1.0E 01 3.0E 02 Te 4.0E 02 6.lE 03 I 1.5E 01 5.0E 00 Cs 2.0E 03 1.0E 03 Ba 4.0E 00 2.0E 02 La 2.5E 01 1.0E 03 Ce 1.0E 00 1.0E 03

Pr 2.5E 01 1.0E 03 Nd 2.5E 01 1.08 03 i

, W l.2E 03 1.0E 01 Np 1.0E 01 4.0E 02 I

l l

I

'Taken from Regulatory Guide 1.109 (Rev. 1) .

l l

l OCDM A-2

TABLE A.1-2 ~

DOSE FACIORS FOR NOBLE GASES AND DAUGIfrERS*

Total Body Gamma Air Beta Air Dose Factor Skin Dose Factor Dose Factor Dose Factor Ki Li Mi Ni Radionuclide (mreny'yr per A.Ci/m3 1 (mrem /yr per p Ci/m3 1 (mrad /yr per u Ci/m3) (mrad /yr per/<.Ci/m 3)

Kr-83m 7.56E-02** 1.93E+01 2.88E+02 Kr-85m 1.17E+03 1.46E+03 1.23E+03 1.97E+03 Kr-85 1.61E+01 1.34E+03 1.72E+01 1.95E+03 Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03

> Kr-89 1.66E+04 1.01E+04 1.73E+04 1.06E+04 Kr-90 1.56E+04 7.29E+03 1.63E+04 7.83E+03 Xe-131m 9.15E+01 4.76E+02 1.56E+02 1.llE+03 i

! Xe-133m 2.51E+02 9.94E+02 3.27E+02 1.48E+03 Xe-133 2.94E+02 3.06E+02 3.53E+02 1.05E+03 Xe-135m 3.12E+03 7.11E+02 3.36E+03 7.39E+02 ,

Xe-135 1.81E+03 1.86E+03 1.92E+03 2.46E+03 Xe- 137 1.42E+03 1.22E+04 1.51E+03 1.27E+04 Xe-138 8.83E+03 4.13E+03 9.21E+03 4.75E+03 Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03 Based on Regulatory Guide 1.109 (Rev. 1).

- 7.56E-02 = 7.56 x 10 -2

l TABLE A.2-l*

INHALATION DOSE FACIORS EDR ADULTS (MREM PER PCI INHALED)

C NUCLIDE BONE LIVER T BODY 'IHYROID KIDNEY LUNG GI-LLI H 3 NO DATA 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 C 14 2.27E-06 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 NA 24 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 P 32 1.65E-04 9.64E-06 6.26E-06 10 DATA NO DATA NO DATA 1.08E-05 CR 51 NO DATA 10 DATA 1.25E-08 7.44E-09 2.85E-09 1.80E-06 4.15E-07 MN 54 BO DATA 4.95E-06 7.87E-07 NO DATA 1.23E-06 1.75E-04 9.67E-06 MN 56 to DATA 1.55E-10 2.29E-ll NO DATA 1.63E-10 1.18E-06 2.53E-06 FE 55 3.07E-06 2.12E-06 4.93E-07 NO DATA NO DATA 9.01E-06 7.54E-07 FE 59 1.47E-06 3.47E-06 1.32E-06 NO DATA NO DATA 1.27E-04 2.35E-05 CD 58 NO DATA 1.98E-07 2.59E-07 NO DATA NO DATA 1.16E-04 1.33E-05 CD 60 10 DATA 1.44E-06 1.85E-06 ?O DATA 10 DATA 7.46E-04 3.56E-05 NI 63 5.40E-05 3.93E-06 1.81E-06 NO DATA IO DATA 2.23E-05 1.67E-06 NI 65 1.92E-10 2.62E-ll 1.14E-ll NO DATA NO DATA 7.00E-07

( CU 64

.ZN 65 BO DATA 1.83E-10 4.05E-06 1.29E-05 7.69E-ll 5.82E-06 NO DATA

?O DATA 5.78E-10 8.62E-06 8.48E-07 1.08E-04 1.54E-06 6.12E-06 6.68E-06 ZN 69 4.23E-12 8.14E-12 5.65E-13 10 DATA 5.27E-12 1.15E-07 2.04E-09 BR 83 NO DATA NO DATA 3.01E-08 NO DATA NO DATA NO MTA 2.90E-08 BR 84 NO DATA FO DATA 3.91E-08 NO DATA NO DATA NO DATA 2.05E-13 BR 85

NO DATA NO DATA 1.60E-09 10 DATA to DATA PO DATA LT E-24 RB 86 NO DATA 1.69E-05 7.37E-06 10 DATA to DATA tO DATA 2.08E-06 RB 88 10 DATA 4.84E-08 2.41E-08 10 DATA NO DATA NO DATA 4.18E-19 PB 89 10 DATA 3.20E-08 2.12E-08 NO DATA ?O DATA PO DATA 1.16E-21 SR 89 3.80E-05 NO DATA 1.09E-06 NO DATA NO DATA 1.75E-04 4.37E-05 SR 90 1.24E-02 to DATA 7.62E-04 NO DATA to DATA 1.20E-03 9.02E-05 SR 91 7.74E-09 to DATA 3.13E-10 to DATA to DATA 4.56E-06 2.39E-05 SR 92 8.43E-10 to DATA 3.64E-ll NO DATA to DATA 2.06E-06 5.38E-06 Y 90 2.61E-07 NO DATA 7.01E NO DATA NO DATA 2.12E-05 6.32E-05 Y 91M 3.26E-ll NO DATA 1.27E-12 NO DATA NO DATA 2.40E-07 1.66E-10 Y 91 5.78E-05 PO DATA 1.55E-06 NO DATA NO DATA 2.13E-04 4.81E-05 Y 92 1.29E-09 to DATA 3.77E-ll ?O DATA to DATA 1.96E-06 9.19E-06

Taken from Regulatory Guide 1.109 (Rev.1)

A-4

TABLE A.2-1 (cont'd)

INHALATION DOSE FACIORS FOR ADULTS (MREM PER PCI INHALED)

NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI Y 93 1.18E-08 to DATA 3.26E-10 NO DATA NO DATA 6.06E-06 5.27E-05 ZR 95 1.34E-05 4.30E-06 2.91E-06 ZR 97 NO DATA 6.77E-06 2.21E-04 1.88E-05 1.21E-08 2.45E-09 1.13E-09 NO DATA 3.71E-09 9.84E-06 6.54E-05 NB 95 1.76E-06 9.77E-07 5.26E-07 BO 99 NO DATA 9.67E-07 6.31E-05 1.30E-05 NO DATA 1.51E-08 2.87E-09

'IC 99M NO DATA 3.64E-08 1.14E-05 3.10E-05 1.29E-13 3.64E-13 4.63E-12 NO DATA 5.52E-12 9.55E-08 5.20E-07 TC 101 5.22E-15 7.52E-15 7.38E-14 NO DATA RU 103 1.35E-13 4.99E-08 1.36E-21 1.91E-07 NO DATA 8.23E-08 to DATA 7.29E-07 RU 105 9.88E-ll NO DATA 6.31E 1.38E-05 3.89E-ll NO DATA 1.27E-10 1.37E-06 6.02E-06 RU 106 8.64E-06 NO DATA 1.09E-06 AG 110M NO DATA 1.67E-05 1.17E-03 1.14E-04 1.35E-06 1.25E-06 7.43E-07 NO DATA 2.46E-06 5.79E-04 TE 125M 4.27E-07 1.98E-07 3.78E-05 5.84E-08 1.31E-07 1.55E-06 3.92E-05 8.83E-06 TE 127M 1.58E-06 7.21E-07 1.96E-07 4.llE-07 TE 127 5.72E-06 1.20E-04 1.87E-05 1.75E-10 8.03E-11 3.87E-ll C TE 129M 1.22E-06 5.84E-07 1.98E-07 1.32E-10 4.30E-07 6.37E-10 4.57E-06 8.14E-07 1.45E-04 7.17E-06 4.79E-05 TE 129 6.22E-12 2.99E-12 1.55E-12 TE 131M 4.87E-12 2.34E-ll 2.42E-07 1.96E-08 8.74E-09 5.45E-09 3.63E-09 6.88E-09 3.86E-08 1.82E-05 TE 131 1.39E-12 7.44E-13 6.95E-05 4.49E-13 1.17E-12 5.46E-12 1.74E-07 2.30E-09 TE 132 3.25E-08 2.69E-08 2.02E-08 2.37E-08 I 130 1.82E-07 3.60E-05 6.37E-05 5.72E-07 1.68E-06 6.60E-07 1.42E-04 2.61E-06 NO DATA I 131 3.15E-06 4.47E-06 9.61E-05 2.56E-06 1.49E-03 7.66E-06 NO DATA 7.85E-07 I 132 1.45E-07 4.07E-07 1.45E-07 1.43E-05 6.48E-07 NO DATA 5.08E-08 I 133 1.08E-06 1.85E-06 5.65E-07 2.69E-04 3.23E-06 I 134 8.05E-08 2.16E-07 7.69E-08 3.73E-06 NO DATA 1.llE-06 3.44E-07 NO DATA 1.26E-10 I 135 3.35E-07 8.73E-07 3.21E-07 5.60E-05 1.39E-06 BD DATA 6.56E-07 CS 134 4.66E-05 1.06E-04 9.10E-05 NO DATA 3.59E-05 CS 136 1.22E-05 1.30E-06 4.88E-06 1.83E-05 1.38E-05 NO DATA 1.07E-05 1.50E-06 1.46E-06 CS 137 5.98E-05 7.76E-05 5.35E-05 to DATA 2.788-05 9.40E-06 1.05E-06

( CS 138 BA 139 4.14E-08 7.76E-08 1.17E-10 8.32E-14 4.05E-08 3.42E-12 NO DATA NO DATA 6.00E-08 7.78E-14 6.07E-09 4.70E-07 2.33E-13 1.12E-07 A-5

TABLE A.2-1 (cont'd)

IN!!ALATION DOSE FACIORS FOR ADULTS (MREM PER PCI INHALED)

NUCLIDE BONE LIVER T BODY 'IHYROID KIDNEY LUNr. GI-LLI BA 140 4.88E-06 6.13E-09 3.21E-07 NO DATA 2.09E-09 1.59E-04 2.73E-05 BA 141 'l.25E-11 9.41E-15 4.20E-13 NO DATA 8.75E-15 2.42E-07 1.45E-17 BA 142 3.29E-12 3.38E-15 2.07E-13 NO DATA 2.86E-15 1.49E-07 1.96E-26 LA 140 4.30E-08 2.17E-08 5.73E-09 NO DATA NO DATA 1.70E-05 5.73E-05 T.A 142 8.54E-ll 3.88E-ll 9.65E-12 NO DATA NO DATA 7.91E-07 2.64E-07 CE 141 2.49E-06 1.69E-06 1.91E-07 NO DATA 7.83E-07 4.52E-05 1.50E-05 1

CE 143 2.33E-08 1.72E-08 1.91E-09 NO DATA 7.60E-09 9.97E-06 2.83E-05 CE 144 4.29E-04 1.79E-04 2.30E-05 -NO DATA 1.06E-04 9.72E 1.02E-04 PR 143 1.17E-06 4.69E-07 5.80E-08 NO DATA 2.70E-07 3.51E-05 2.50E-05 PR 144 3.76E-12 1.56E-12 1.91E-13 NO DATA 8.81E-13 1.27E-07 2.69E-18 ND 147 6.59E-07 7.62E-07 4.56E-08 NO DATA 4.45E-07 2.76E-05 2.16E-05 W 187 1.06E-09 8.85E-10 3.10E-10 NO DATA' NO DATA 3.63E-06 1.94E-05 NP 239 2.87E-08 2.82E-09 1.55E-09 NO DATA 8.75E-09 4.70E-06 1.49E-05 9 g A-6

TABLE A.2-2*

INHALATION DOSE FAC'IORS EUR TEENAGER (MREM PER PCI INHALED)

NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI H 3 NO DATA 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 C 14 3.25E-06 6.09E-07 6.09E-07 6.09E-07 6.09E-07 NA 24 6.09E-07 6.09E-07 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 P 32 2.36E-04 1.37E-05 8.95E-06 NO DATA 10 DATA to DATA 1.16E-05 CR 51 to DATA NO DATA 1.69E-08 9.37E-09 3.84E-09 2.62E-06 3.75E-07 MN 54 to DATA 6.39E-06 1.05E-06 No DATA 1.59E-06 2.48E-04 8.35E-06 MN 56 PO DATA 2.12E-10 3.15E-ll NO DATA 2.24E-10 1.90E-06 7.18E-06 FE 55 4.18E-06 2.98E-06 6.93E-07 NO DATA NO DATA 1.55E-05 7.99E-07 FE 59 1.99E-06 4.62E-06 1.79E-06 NO DATA PO DATA 1.91E-04 2.23E-05 CO 58 to DATA 2.59E-07 3.47E-07 NO DATA ?O DATA 1.68E-04 1.19E-05 CO 60 ?O DATA 1.89E-06 2.48E-06 10 DATA NO DATA 1.09E-03 3.24E-05 NI 63 7.25E-05 5.43E-06 2.47E-06 10 DATA NO DATA 3.84E-05 1.77E-06

( NI 65 CU 64

.ZN 65 2.73E-10 3.66E-11 to DATA 2.54E-10 4.82E-06 1.67E-05 1.59E-ll 1.06E-10 7.80E-06 NO DATA 10 DATA IO DATA NO DATA 8.01E-10 1.08E-05 1.17E-06 1.39E-06 1.55E-04 4.59E-06 7.68E-06 5.83E-06 ZN 69 6.04E-12 1.15E-11 8.07E-13 NO DATA 7.53E-12 1.98E-07 3.56E-08 BR 83 NO DATA NO DATA 4.30E-08 NO DATA to DATA NO DATA BR 84 LT E-24 NO DATA NO DATA 5.41E-08 NO DATA NO DATA NO DATA LT E-24 BR 85 No DATA 10 DATA 2.29E-09 NO DATA 10 DATA to DATA RB 86 LT E-24 to DATA 2.38E-05 1.05E-05 No DATA NO DATA NO DATA RB 88 2.21E-06 to DATA 6.82E-08 3.40E-08 NO DATA NO DATA NO DATA 3.65E-15 RB 89 10 DATA 4.40E-08 2.91E-08 No DATA NO DATA to DATA SR 89 4.22E-17 5.43E-05 NO DATA 1.56E-06 to DATA No DATA 3.02E-04 4.64E-05 SR 90 1.35E-02 NO DATA 8.35E-04 NO DATA NO DATA 2.06E-03 9.56E-05 SR 91 1.10E-08 NO DATA 4.39E-10 PO DATA NO DATA 7.59E-06 SR 92 3.24E-05 1.19E-09 to DATA 5.08E-ll NO DATA to DATA 3.43E-06 1.49E-05 Y 90 3.73E-07 NO DATA 1.00E-08 to DATA NO DATA 3.66E-05 6.99E-05 Y 91M 4.63E-ll NO DATA 1.77E-12 to DATA to DATA 4.00E-07 3.77E-09 Y 91 8.26E-05 NO DATA 2.21E-06 to DATA 3.67E-04 Y 92 NO DATA 5.llE-05 1.84E-09 NO DATA 5.36E-ll NO DATA to DATA 3.35E-06 2.06E-05 I

Taken trcm Regulatory Guide 1.109 (Rev.1)

A-7

TABLE A.2-2 (cont'd)

INHALATION DOSE FACTORS FOR TEENAGERS (MREM PER PCI INHALED)

NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI Y 93 1.69E-08 NO DATA 4.65E-10 10 DATA NO DATA 1.04E-05 7.24E-05 ZR 95 1.82E-05 5.73E-06 3.94E-06 10 DATA 8.42E-06 3.36E-04 1.86E-05 ZR 97 1.72E-08 3.40E-09 1.57E-09 to DATA 5.15E-09 1.62E-05 7.88E-05 NB 95 2.32E-06 1.29E-06 7.08E-07 NO DATA 1.25E-06 9.39E-05 1.21E-05 MO 99 to DATA 2.11E-08 4.03E-09 10 DATA 5.14E-08 1.92E-05 3.36E-05 7C 99M 1.~/.st:-13 4.83E-13 6.24E-12 to DATA 7.20E-12 1.44E-07 7.66E-07 TC 101 7.40E-15 1.05E-14 1.03E-13 NO DATA 1.90E-13 8.34E-08 1.09E-16 RU 103 2.63E-07 NO DATA 1.12E-07 NO DATA 9.29E-07 9.79E-05 ~1.36E-05 RU 105 1.40E-10 NO DATA 5.42E-ll NO DATA 1.76E-10 2.27E-06 1.13E-05 RU 106 1.23E-05 to DATA 1.55E-06 to DATA 2.38E-05 2.01E-03 1.20E-04 AG 110M 1.73E-06 1.64E-06 9.99E-07 NO DATA 3.13E-06 8.44E-04 3.41E-05 TE 125M 6.10E-07 2.80E-07 8.34E-08 1.75E-07 to DATA 6.70E-05 9.38E-06 2.25E-06 1.02E-06

( TE 127M TE 127 TE 129M 2.51E-10 1.14E-10 1.74E-06 8.23E-07 2.73E-07 5.52E-ll 2.81E-07 5.48E-07 1.77E-10 5.72E-07 8.17E-06 9.10E-10 6.49E-06 2.07E-04 1.40E-06 2.47E-04 1.992-05 1.01E-05 5.06E-05 TE 129 8.87E-12 4.22E-12 2.20E-12 6.48E-12 3.32E-11 4.12E-07 2.02E-07 TE 131M 1.23E-08 7.51E-09 5.03E-09 9.06E-09 5.49E-08 2.97E-05 7.76E-05 TE 131 1.97E-12 1.04E-12 6.30E-13 1.55E-12 7.72E-12 2.92E-07 1.89E-09 TE 132 4.50E-08 3.63E-08 2.74E-08 3.07E-08 2.44E-07 5.61E-05 5.79E-05 I 130 7.80E-07 2.24E-06 8.96E-07 1.86E-04 3.44E-06 10 DATA 1.14E-06 I 131 4.43E-06 6.14E-06 3.30E-06 1.83E-03 1.05E-05 70 DATA 8.llE-07 I 132 1.99E-07 5.47E-07 1.97E-07 1.89E-05 8.65E-07 NO DATA 1.59E-07 I 133 1.52E-06 2.56E-06 7.78E-07 3.65E-04 4.49E-06 to DATA 1.29E-06 I 134 1.llE-07 2.9 0E-07 1.05E-07 4.94E-06 4.58E-07 NO DATA 2.55E-09 I 135 4.62E-07 1.18E-06 4.36E-07 7.76E-05 1.86E-06 to DATA 8.69E-07 CS 134 6.28E-05 1.41E-04 6.86E-05 NO DATA 4.69E-05 1.83E-05 1.22E-06 CS 136 6.44E-06 2.42E-05 1.71E-05 NO DATA 1.38E-05 2.22E-06 1.36E-06 CS 137 8.38E-05 1.06E-04 3.89E-05 NO DATA 3.80E-05 1.51E-05 1.06E-06

(~ CS 138 5.82E-08 1.07E-07 5.58E-08 BD DATA 8.28E-08 9.84E-09 3.38E-ll L BA 139 1.67E-10 1.18E-13 4.87E-12 to DATA 1.11E-13 8.08E-07 8.06E-07 A-8

TABLE A.2-2 (cont'd)

' INHALATION DOSE FAC'IORS FOR TEENAGERS (MREM PER PCI INHALED)

NUCLIDE BONE LIVER T. BODY 'IHYROID KIDNEY LUNG GI-LLI

, BA 140 ,6.84E-06 .8.38E-09 4.40E-07 NO DATA 2.85E-09 2.54E-04 2.86E-05 BA 141 1.78E-ll 1.32E 5.93E 10 DATA 1.23E-14 4.llE-07 9.33E-14 BA 142 4.62E-12 4.63E-15 2.84E-13 NO DATA ~3.92E-15 2.39E-07 5.99E-20 LA 140 5.99E-08 2.95E-08 ' 7.82E-09 NO DATA NO DATA 2.68E-05 6.09E-05 LA 142 1.20E-10 5.31E-ll 1.32E-ll NO DATA NO DATA 1.27E-06 1.50E-06 4

CE 141 3.55E-06 2.37E-06 2.71E-07 NO DATA 1.llE-06 7.67E-05 1.58E-05 1

CE 143 3.32E-08 2.42E-08 2.70E-09 NO DATA 1.08E-08 1.63E-05 3.19E-05 CE 144 '6.llE-04 2.53E-04 3.28E-05 NO DATA 1.51E-04 1.67E 1.08E-04 PR 143 1.67E-06 6.64E-07 8.28E-08 NO DATA 3.86E-07 6.04E-05 2.67E-05 PR 144 5.37E-12 2.20E-12 2.72E-13 10 DATA 1.26E-12 2.19E-07 2.94E-14

.ND 147 9.83E-07 1.07E-06 .6.41E-08 NO DATA 6.28E-07 4.65E-05 2.28E-05 W - 187 ' 1.50E-09 1.22E-09 4.29E-10 NO DATA NO DATA 5.92E-06 2.21E-05 NP 239 4.23E-08 3.99E-09 2.21E-09 NO DATA 1.25E-08 8.11E-06 1.65E-05 i .

l l

k I,

A-9

TABLE A.2-3*

(

INHAEATION DOSE FAC'IORS NR CHILD (MREM PER PCI INHALED)

NUCLIDE BONE LIVER T BODY 'IHYROID KIDNEY LUNG GI-LLI H 3 to DATA 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 C 14 9.70E-06 3.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 NA 24 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 P 32 7.04E-04 3.09E-05 2.67E-05 PO DATA NO DATA NO DATA 1.14E-05 CR 51 NO DATA 10 DATA 4.17E-08 2.31E-08 6.57E-09 4.59E-06 2.93E-07

MN 54 PO DATA 1.16E-05 2.57E-06 NO DATA 2.71E-06 4.26E-04 6.19E-06 MN 56 NO DATA 4.48E-3 0 8.43E-ll PO DATA 4.52E-10 3.55E-06 3.33E-05 FE 55 1.28E-05 6.80E-06 2.10E-06 to DATA NO DATA 3.00E-05 '7.75E-07 FE 59 5.59E-06 9.04E-06 4.51E-06 NO DATA NO DATA 3.43E-04 1.91E-05 CO 58 to DATA 4.79E-07 8.55E-07 NO DATA 10 DATA 2.99E-04 9.29E-06 CO 60 NO DATA 3.55E-06 6.12E-06 ?O DATA 10 DATA 1.91E-03 2.60E-05 NI 63 2.22E-04 1.25E-05 7.56E-06 NO DATA NO DATA 7.43E-05 1.71E-06

( NI 65 CU 64 ZN 65 8.08E-10 7.99E-ll 10 DATA 1.15E-05 3.06E-05 5.39E-10 4.44E-ll 2.90E-10 1.90E-05 NO DATA to DATA 10 DATA NO DATA kg3E-09 r.93E-05 2.21E-06 2.59E-06 2.69E-04 2.27E-05 9.92E-06 4.41E-06 ZN 69 1.81E-ll 2.61E-11 2.41E-12 NO DATA 1.58E-ll 3.84E-07 2.75E-06 BR 83 NO DATA NO DATA 1.28E-07 NO DATA NO DATA NO DATA LT E-24 BR 84 NO DATA NO DATA 1.48E-07 to DATA NO DATA NO DATA LT E-24 BR 85 NO DATA NO DATA 6.84E-09 NO DATA NO DATA NO DATA LT E-24 RB 86 to DATA 5.36E-05 3.09E-05 NO DATA NO DATA 10 DATA 2.16E-06 RB 88 10 DATA 1.52E-07 9.90E-08 NO DATA NO DATA NO DATA 4.66E-09 RB 89 to DATA 9.33E-08 7.83E-08 NO DATA NO DATA 10 DATA 5.llE-10 SR 89 1.62E-04 NO DATA 4.66E-06 NO DATA 10 DATA 5.83E-04 4.52E-05 SR 90 2.73E-02 NO DATA 1.74E-03 to DATA tO DATA 3.99E-03 9.28E-05 SR 91 3.28E-08 NO DATA 1.24E-09 to DATA NO DATA 1.44E-05 4.70E-05 SR 92 3.54E-09 to DATA 1.42E-10 tO DATA 10 DATA 6.49E-06 6.55E-05 Y 90 1.11E-06 to DATA 2.99E-08 NO DATA 10 DATA 7.07E-05 7.24E-05 Y 91M 1.37E-10 PO DATA 4.98E-12 NO DATA tO DATA 7.60E-07 4.64E-07 Y 91 2.47E-04 NO DATA 6.59E-06 NO DATA NO DATA 7.10E-04 4.97E-05 Y 92 5.50E-09 10 DATA 1.57E-10 to DATA tO DATA 6.46E-06 6.46E-05

Taken trom Regulatory Guide 1.109 (Rev.1)

A-10 1

TABLE A.2-3 (cont'd)

INHALATION DOSE FICTORS EOR CHILD (MREM PER PCI INHALED)

LIVER T BODY THYROID KIDNEY LUNG GI-LLI NUCLIDE BONE 5.04E-08 NO DATA 1.38E-09 10 DATA 10 DATA 2.01E-05 1.05E-04 Y 93 5.13E-05 1.13E-05 1.00E-05 10 DATA 1.61E-05 6.03E-04 1.65E-05 ZR 95 5.07E-08 7.34E-09 4.32E-09 FO DATA 1.05E-08 3.06E-05 9.49E-05 ZR 97 6.35E-06 2.48E-06 1.77E-06 10 DATA 2.33E-06 1.66E-04 1.00E-05 NB 95 to 99 10 DATA 4.66E-08 1.15E-03 10 DATA 1.06E-07 3.66E-05 3.42E-05 TC 99M 4.81E-13 9.41E-13 1.56E-ll NO DATA 1.37E-ll 2.572-07 1.30E-06 7C 101 2.19E-14 2.30E-14 2.91E-13 10 DATA 3.92E-13 1.58E-07 4.41E-09 RU 103 7.55E-07 NO DATA 2.90E-07 NO DATA 1.90E-06 1.79E-04 ~1.21E-05 RU 105 4.13E-10 to DATA 1.50E-10 NO DATA 3.63E-10 4.30E-06 2.69E-05 RU 106 3.68E-05 NO DATA 4.57E-06 NO DATA 4.97E-05 3.87E-03 1.16E-04 AG 110M 4.56E-06 3.08E-06 2.47E-06 10 DATA 5.74E-06 1.48E-03 2.71E-05 TE 125M 1.82E-06 6.29E-07 2.47E-07 5.20E-07 10 DATA 1.29E-04 9.13E-06 6.72E-06 2.31E-06 8.16E-07 1.64E-06 1.72E-05 4.00E-04 1.93E-05

( TE 127M TE 127 TE 129M 7.49E-10 2.57E-10 5.19E-06 1.85E-06 1.65E-10 8.22E-07 5.30E-10 1.71E-06 1.91E-09 1.36E-05 2.71E-06 4.76E-04 1.52E-05 4.91E-05 TE 129 2.64E-ll 9.45E-12 6.44E-12 1.93E-ll 6.94E-ll 7.93E-07 6.89E-06 3.63E-08 1.60E-08 1.37E-08 2.64E-08 1.08E-07 5.56E-05 8.32E-05 TE 131M TE 131 5.87E-12 2.28E-12 1.78E-12 4.59E-12 1.59E-ll 5.55E-07 3.60E-07 TE 132 1.30E-07 7.36E-08 7.12E-08 8.58E-08 4.79E-07 1.02E-04 3.72E-05 I 130 2.21E-06 4.43E-06 2.28E-06 4.99E-04 6.61E-06 10 DATA 1.38E-06 I 131 1.30E-05 1.-30E-05 7.37E-06 4.39E-03 2.13E-05 10 DATA 7.68E-07 I 132 5.72E-07 1.10E-06 5.07E-07 5.23E-05 1.69E-06 10 DATA 8.65E-07 I 133 4.48E-06 5.49E-06 2.08E-06 1.04E-03 9.13E-06 10 DATA 1.48E-06 I 134 3.17E-07 5.84E-07 2.69E-07 1.37E-05 8.92E-07 NO DATA 2.58E-07 I 135 1.33E-06 2.36E-06 1.12E-06 2.14E-04 3.62E-06 10 DATA 1.20E-06 CS 134 1.76E-04 2.74E-04 6.07E-05 NO DATA 8.93E-05 3.27E-05 1.04E-06 CS 136 1.76E-05 4.62E-05 3.14E-05 NO DATA 2.58E-05 3.93E-06 1.13E-06 CS 137 2.45E-04 2.23E-04 3.47E-05 10 DATA 7.63E-05 2.81E-05 9.78E-07 CS 138 1.71E-07 2.27E-07 1.50E-07 NO DATA 1.68E-07 1.84E-08 7.29E-08 k BA 139 4.98E-10 2.66E-13 1.45E-ll 10 DATA 2.33E-13 1.56E-06 1.56E-05 i

A-ll

TABLE A.2-3 (cont'd)

INIIALATION DOSE FACIORS EOR CIIILD

( (MREM PER PCI ' INHALED)

NUCLIDE BONE LIVER T BODY 'IHYROID KIDNEY IUNG GI-LLI BA 140 2.00E-05 1.75E-08 1.17E-06 NO DATA 5.71E-09 4.71E-04 2.75E-05 BA 141 5.29E-ll 2.95E-14 1.72E-12 NO DATA 2.56E-14 7.89E-07 7.44E-08 BA 142 1.35E-11 9.73E-15 7.54E-13 NO DATA 7.87E-15 4.44E-07 7.41E-10 LA 140 1.74E-07 6.08E-08 2.04E-08 NO DATA NO DATA 4.94E-05 6.10E-05 IA 142 3.50E-10 1.llE-10 3.49E-ll NO DATA NO DATA 2.35E-06 2.05E-05 CE 141 1.06E-05 5.28E-06 7.83E-07 NO DATA 2.31E-06 1.47E-04 1.53E-05 CE 143 9.89E-08 5.37E-08 7.77E-09 NO DATA 2.26E-08 3.12E-05 3.44E-05 CE 144 1.83E-03 5.72E-04 9.77E-05 NO DATA 3.17E-04 3.23E 1.05E-04 PR 143 - 4.99E-06 1.50E-06 2.47E-07 NO DATA 8.llE-07 1.17E-04 2.63E-05 PR 144 1.61E-11 4.99E-12 8.10E-13 10 DATA 2.64E-12 4.23E-07 5.32E-08 ND 147 2.92E-06 2.36E-06 1.84E-07 NO DATA 1.30E-06 8.87E-05 2.22E-05 W 187 4.41E-09 2.61E-09 1.17E-09 NO DATA NO DATA 1.llE-05 2.46E-05 NP 239 1.26E-07 9.04E-09 6.35E-09 NO DATA 2.63E-08 1.57E-05 1.73E-05

(.

L A-12

TABLE A.2-4*

INHALATION DOSE FACIORS FOR INFANT (MREM PER PCI INHALED)

NUCLIDE BONE LIVER T BODY 'IHYROID KIDNEY LUNG GI-LLI H 3 to DATA 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 C 14 1.89E-05 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 NA 24 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 P 32 1.45E-03 8.03E-05 5.53E-05 to DATA NO DATA 10 DATA 1.15E-05 CR 51 10 DATA NO DATA 6.39E-08 4.llE-08 9.45E-09 9.17E-06 2.55E-07 MN 54 10 DATA 1.81E-05 3.56E-06 PO DATA 3.56E-06 7.14E-04 5.04E-06 MN 56 10 DATA 1.10E-09 1.58E-10 to DATA 7.86E-10 8.95E-06 5.12E-05 FE 55 1.41E-05 8.39E-06 2.38E-06 NO DATA NO DATA 6.21E 7.82E-07 FE 59 9.69E-06 1.68E-05 6.77E-06 10 DATA NO DATA 7.25E-04 1.77E-05 CO 58 NO DATA 8.71E-07 1.30E-06 NO DATA NO DATA 5.55E-04 7.95E-06 CD 60 10 DATA 5.73E-06 8.41E-06 NO DATA NO DATA 3.22E-03 2.28E-05 NI 63 2.42E-04 1.46E-05 8.29E-06 NO DATA NO DATA 1.49E-04 1.73E-06 NI 65 1.71E-09 2.03E-10

( CU 64 ZN 65 10 DATA 1.34E-09 1.38E-05 4.47E-05 8.79E-ll 5.53E-10 2.22E-05 NO DATA 10 DATA to DATA NO DATA 2.84E-09 2.32E-05 5.80E-06 6.64E-06 4.62E-04 3.58E-05 1.07E-05 3.67E-05 ZN 69 3.85E-ll 6.91E-11 5.13E-12 NO DATA 2.87E-ll 1.05E-06 9.44E-06 BR 83 10 DATA PO DATA 2.72E-07 NO DATA NO DATA 10 DATA LT E-24 BR 84 to DATA to DATA 2.86E-07 NO DATA DO DATA PO DATA LT E-24 BR 85 10 DATA tO DATA 1.46E-08 NO DATA NO DATA tO DATA LT E-24 RB 86 10 DATA 1.36E-04 6.30E-05 PO DATA 10 DATA NO DATA 2.17E-06 RB 88 10 DATA 3.98E-07 2.05E-07 NO DATA NO DATA NO DATA 2.42E-07 RB 89 10 DATA 2.29E-07 1.47E-07 NO DATA 10 DATA NO DATA 4.87E-08 SR 89 2.84E-04 NO DATA 8.15E-06 20 DATA NO DATA 1.45E-03 4.57E-05 SR 90 2.92E-02 NO DATA 1.85E-03 to DATA tO DATA 8.03E-03 9.36E-05 SR 91 6.83M-08 NO DATA 2.47E-09 tO DATA NO DATA 3.76E-05 5.24E-05 SR 92 7.50E-09 to DATA 2.79E-10 to DATA to DATA 1.70E-05 1.00E-04 Y 90 2.35E-06 to DATA 6.30E-08 NO DATA NO DATA 1.92E-04 7.43E-05 Y 91M 2.91E-10 10 DATA 9.90E-12 to DATA NO DATA 1.99E-06 1.68E-06

( Y 91 4.20E-04 ?O DATA 1.12E-05 10 DATA NO DATA 1.75E-03 5.02E-05

( Y 92 1.17E-08 to DATA 3.29E-10 to DATA to DATA 1.75E-05 9.04E-05

Taken tron Regulatory Guide 1.109 (Rev.1)

A-13

TABLE A.2-1 (cont'd)

IN!!ALATION DOSE FACTORS FOR INFANT (MREM PER PCI INHALED)

NUCLIDE PONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI Y 93 1.07E-07 NO DATA 2.91E-09 NO DATA NO DATA 5.46E-05 1.19E-04 ZR 95 8.24E-05 1.99E-05 1.45E-05 NO DATA 2.22E-05 1.25E-03 1.55E-05 ZR 97 1.07E-07 1.83E-08 8.36E-09 NO DATA 1.85E-08 7.88E-05 1.00E-04 NB 95 1.12E-05 4.59E-06 2.70E-06 NO DATA 3.37E-06 3.42E-04 9.05E-06 MO 99 NO DNEA 1.18E-07 2.31E-08 NO DATA 1.89E-07 9.63E-05 3.48E-05 TC 99M 9.98E-13 2.06E-12 2.66E-ll NO DNIA 2.22E-ll 5.79E-07 1.45E-06 TC 101 4.65E-14 5.88E-14 5.80E-13 NO DATA 6.99E-13 4.17E-07 6.03E-07 RU 103 1.44E-06 NO DATA 4.85E-07 NO DATA 3.03E-06 3.94E-04 ~1.15E-05 RU 105 8.74E-10 NO DNIA 2.93E-10 NO DNEA 6.42E-10 1.12E-05 3.46E-05 RU 106 6.20E-05 NO DATA 7.77E-06 NO DATA 7.61E-05 8.26E-03 1.17E-04 AG 110M 7.13E-06 5.16E-06 3.57E-06 NO DNEA 7.80E-06 2.62E-03 2.36E-05 TE 125M 3.40E-06 1.42E-06 4.70E-07 1.16E-06 NO DNIA 3.19E-04 9.22E-06 3

TE 127M 1.19E-05 4.93E-06 1.48E-06 3.48E-06 2.68E-05 9.37E-04 1.95E-05

( TE 127 1.59E-09 6.81E-10 3.49E-10 1.32E-09 3.47E-09 7.39E-06 1.74E-05 TE 129M 1.01E-05 4.35E-06 1.59E-06 3.91E-06 2.27E-05 1.20E-03 4.93E-05 TE 129 5.63E-11 2.48E-ll 1.34E-ll 4.82E-11 1.25E-10 2.14E-06 1.88E-05 TE 131M 7.62E-08 3.93E-08 2.59E-08 6.38E-08 1.89E-07 1.42E-04 8.51E-05 TE 131 1.24E-11 5.87E-12 3.57E-12 1.13E-ll 2.85E-ll 1.47E-06 5.87E-06 TE 132 2.66E-07 1.69E-07 1.26E-07 1.99E-07 7.39E-07 2.43E-04 3.15E-05 I 130 4.54E-06 9.91E-06 3.98E-06 1.14E-03 1.09E-05 NO DATA 1.42E-06 I 131 2.71E-05 3.17E-05 1.40E-05 1.06E-02 3.70E-05 NO DATA 7.56E-07 I 132 1.21E-06 2.53E-06 8.99E-07 1.21E-04 2.82E-06 NO DATA 1.36E-06 I 133 9.46E-06 1.37E-05 4.00E-06 2.54E-03 1.60E-05 NO DNEA 1.54E-06 I 134 6.58E-07 1.34E-06 4.75E-07 3.18 E-05 1.49E-06 No DNIA 9.21E-07 I 135 2.76E-06 5.43E-06 1.98E-06 4.97E-04 6.05E-06 No DATA 1.31E-06 CS 134 2.83E-04 5.02E-04 5.32E-05 NO DATA 1.36E-04 5.69E-05 9.53E-07 CS 136 3.45E-05 9.61E-05 3.78E-05 NO DATA 4.03E-05 8.40E-06 1.02E-06 CS 137 3.92E-04 4.37E-04 3.25E-05 NO DNTA 1.23E-04 5.09E-05 9.53E-07

(' CS 138 3.61E-07 5.58E-07 2.84E-07 NO DNTA 2.93E-07 4.67E-08 6.26E-07

( BA 139 1.06E-09 7.03E-13 3.07E-ll NO DATA 4.23E-13 4.25E-06 3.64E-05 A-14

TABLE A.2-4 (cont'd)

INHALATION DOSE FAC10RS FOR INFANT (MREM PER PCI INHALED)

NUCLIDE BONE LIVER T BODY 'IHYROID KIDNEY LUNG GI-LLI

.BA 140 4.00E-05 4.00E-08 2.07E-06 NO DATA 9.59E-09 1.14E-03 2.74E-05 BA 141 1.12E-10 7.70E-14 3.55E-12 NO DATA 4.64E-14 2.12E-06 3.39E-06 BA 142- 2.84E-ll 2.36E-14 1.40E-12 NO DATA 1.36E-14 1.llE-06 4.95E-07 LA 140 3.61E-07 1. 43E-O'7 3.68E-08 NO DATA NO DATA 1.20E-04 6.06E-05 LA 142 7.36E-10 2.69E-10 6.46E-11 NO DATA NO DATA 5.87E- 6 4.25E-05 CE 141 1.98E-05 1.19E-05 1.42E-06 NO DATA 3.75E-06 3.69E-04 1.54E-05 CE 143 2.09E-07 1.38E-07 1.58E-08 NO DATA 4.03E-08 8.30E-05 3.55E-05 CE 144 2.28E-03 8.65E-04 1.26E-04 NO DATA 3.84E-04 7.03E 1.06E-04 PR 143 1.00E-05 3.74E-06 4.99E-07 NO DATA 1.41E-06 3.09E-04 . 2.66E-05

-PR 144 3.42E-ll 1.32E-ll 1.72E-12 NO DATA 4.80E-12 1.15E-06 3.06E-06 ND 147 5.67E-06 5.81E-06 3.57E-07 10 DATA 2.25E-06 2.30E-04 2.23E-05 W 187 9.26E-09 6.44E-09 2.23E-09 NO DATA NO DATA 2.83E-05 2.54E-05 NP 239 2.65E-07 2.37E-08 1.34E-08 NO DATA 4.73E-08 4.25E-05 1.78E-05

+

e A-15 4 4 + -

c 4 F m y4r---+y y er'y'wM+--+.W--*-==y-+t--- * , + - ---et -Pw p

TABLE A.2-5*

EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND

( (mrem /hr per pCi/m2}

Elemerit Total Body Skin H-3 0.0 0.0 C-14 0.0 0.0 NA-24 2.50E-08 P-32 2.90E-08 0.0 0.0 Cr-51 2.20E-10 Mn-54 2.60E-10 5.80E-09 6.80E-09 Mn-56 1.10E-08 1.30E-08 s Fe-55 0.0 0.0 Fe-59 8.00E-09 9.40E-09 Co-58 7.00E-09 8.20E-09 Co-60 1.70E-08 2.00E-08 l'i-63 0.0 0.0 Nr-65 3.70E-09 4.30E-09 Cu-64 1.50E-09 1.70E-09 Zn-65 4.00E-09 4.60E-09 Zn-69 0.0 0.0 Br-83 6.40E-11 9.30E-ll Br-84 1.20E-08 Br-85 1.40E-08 0.0 0.0 Rb-86 6.30E-10

(

7.20E-10 Rb-88 3.50E-09 4.00E-09 Rb-89 1.50E-08 1.80E-08 Sr-89 5.60E-13 6.50E-13 Sr-91 7.10E-09 8.30E-09 Sr-92 9.00E-09 1.00E-08 Y-90 2.20E-12 2.60E-12 Y-91M. 3.80E-09 4.40E-09 Y-91 2.40E-ll 2.70E-ll Y-92 1.60E-09 1.90E-09 Y-93 5.70E-10' 7.80E-10 Zr-95 5.00E-09 Zr-97 5.80E-09 5.50E-09 6.40E-09 Nb-95

5.10E-09 6.00E-09 Mo-99 1.90E-09 2.20E-09 Tc-99M 9.60E-10 1.10E-09 Tc-101 2.'70E-09 3.00E-09 Ru-103 3.60E-09 4.20E-09 Ru-105 4.50E-09 5.10E-09 Ru-106 1.50E-09 1.80E-09 Ag-110M 1.80E-08 2.10E-08 Te-125M 3.50E-ll 4.80E-ll Te-127M 1.10E-12 1.30E-12 Te-127 1.00E-11 1.10E-11 Te-129M 7.70E-10 9.C0E-10 Te-129 7.10E-10 8.401-10

( *Taken from Regulatory Guide 1.109 (Rev. 1)

A-16

TABLE A.2-5 (cont'd)

EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND

{ (mrem /hr per PCi/m2)

Element Total Body Skin Te-131M 8.40E-09 9.90E-09 Te-131 '

2.20E-09 2.60E-06 Te-132 1.70E-09 2.00E-09 I-130 1.40E-08 1.70E-08 I-131 2.80E-09 3.40E-09 I-132 1.70E-08 2.00E-08 I-133 3.70E-09 4.50E-09 I-134 1.60E-08 1.90E-08 I-135 1.20E-08 1.40E-08 Cs-134 1.20E-08 1.40E-08 Cs-136 1.50E-08 1.70E-08 Cs-137 4.20E-09 '4.90E-09 Cs-138 2.10E-08 2.40E-08 Ba-139 2.40E-09 2.70E-09 Ba-140 2.10E-09 2.40E-09 Ba-141 4.30E-09 4.90E-09 Ba-142 7.90E-09 9.00E-09 La-140 1.50E-08 1.70E-08 La-142 1.50E-08 1.80E-08 Ce-141 5.50E-10 6.20E-10

_f Ce-143 2.20E-09 2.50E-09

( Ce-144 3.20E-10 3.70E-10 Pr-143 0.0 0.0 Pr-144 2.00E-10 2.30E-10 Nd-147 1.00E-09 1.20E-09 W-187 3.10E-09 3.60E-09 Np-239 9.50E-10 1.10E-09 A-17

TABLE A.3-lo INGESTION DOSE FACIORS FOR ADULTS (MREM PER PCI INGESTED)

NUCLIDE BONE LIVER T Bony 'IIIYROID KIDNEY LUNG GI-LLI H 3 t0 DATA 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 C 14 2.84E-06 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 NA 24 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 P 32 1.93E-04 1.20E-05 7.46E-06 to DATA NO DATA to DATA 2.17E-05 CR 51 PO DATA NO DATA 2.66E-09 1.59E-09 5.86E-10 3.53E-09 6.69E-07 MN 54 NO DATA 4.57E-06 8.72E-07 NO DATA 1.36E-06 PO DATA 1.40E-05 MN 56 NO DATA 1.15E-07 2.04E-08 NO DATA 1.46E-07 NO DATA 3.67E-06 FE 55 2.75E-06 1.90E-06 4.43E-07 NO DATA 10 DATA 1.06E-06 ~ 1.09E-06 FE 59 4.34E-06 1.02E-05 3.91E-06 to DATA NO DATA 2.85E 3.40E-05 00 58 10 DATA 7.45E-07 1.67E-06 PO DATA NO DATA to DATA 1.51E-05 00 60 to DATA 2.14E-06 4.72E-06 to DATA NO DATA NO DATA 4.02E-05 NI 63 1.30E-04 9.01E-06 4.36E-06 NO DATA ?O DATA NO DATA 1.88E-06

( NI 65 CU 64 ZN 65 5.28E-07 6.86E-08 NO DATA 8.33E-08 4.84E-06 1.54E-05 3.13E-08 3.91E-08 6.96E-06 to DATA NO DATA NO DATA 10 DATA 2.10E-07 1.03E-05 NO DATA

?O DATA 10 DATA 1.74E-06 7.10E-06 9.70E-06 ZN 69 1.03E-08 1.97E-08 1.37E-09 NO DATA 1.28E-08 to DATA 2.96E-09 BR 83 to DATA 10 DATA 4.02E-08 NO DATA NO DATA NO DATA 5.79E-08 BR 84 10 DATA NO DATA 5.21E-08 NO DATA NO DATA NO DATA 4.09E-13 BR 85 NO DATA to DATA 2.14E-09 10 DATA NO DATA 10 DATA LT E-24 RB 86 NO DATA 2.llE-05 9.83E-06 to DATA 10 DATA PO DATA 4.16E-06 RB 88 to DATA 6.05E-08 3.21E-08 10 DATA to DATA NO DATA 8.36E-19 i

l RB 89 10 DATA 4.01E-08 2.82E-08 NO DATA NO DATA NO DATA 2.33E-21 SR 89 3.08E-04 NO DATA 8.84E-06 NO DATA NO DATA NO DATA 4.94E-05 SR 90 7.58E-03 to DATA 1.86E-03 NO DATA NO DATA NO DATA 2.19E-04 t

SR 91 5.67E-06 tD DATA 2.29E-07 NO DATA NO DATA NO DATA 2.70E-05 SR 92 2.15E-06 NO DATA 9.30E-08 NO DATA t0 DATA NO DATA 4.26E-05 Y 90 9.62E-09 to DATA 2.58E-10 NO DATA NO DATA NO DATA 1.02E-04 Y 91M 9.09E-ll NO DATA 3.52E-12 FD DATA to DATA to DATA 2.67E-10

/ Y 91 1.41E-07 ?O DATA 3.77E-09 to DATA NO DATA NO DATA 7.76E-05 L Y 92 8.45E-10 to DATA 2.47E-ll NO DATA NO DATA NO DATA 1.48E-05

Taken tran Regulatory Guide 1.109 (Rev.1)

A-18

TABLE A.3-1 (cont'd)

( INGESTION DOSE FACIORS FOR ADULTS (MRE4 PER PCI INGESTED)

NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI Y 93 2.68E-09 NO DATA 7.40E-ll NO DATA 10 DATA 10 DATA 8.50E-05 ZR 95 3.04E-08 9.75E-09 6.60E-09 NO DATA 1.53E NO DATA 3.09E-05 ZR 97 1.68E-09 3.39E-10 1.55E-10 to DATA 5.12E-10 10 DATA 1.05E-04 NB 95 6.22E-09 3.46E-09 1.86E-09 to DATA 3.42E-09 tD DATA 2.10E-05 l

MO 99 NO DATA 4.31E-06 8.20E-07 NO DATA 9.76E-06 tD DATA .9.99E-06 K 99M 2.47E-10 6.98E-10 8.89E-09 10 DATA -1.06E-08 3.42E-10 4.13E-07 K 101 2.54E-10 3.66E-10 3.59E-09, NO DATA 6.59E-09 1.87E-10 1.10E-21 RU 103 1.85E-07 NO DATA 7.97E-08 .NO DATA 7.06E-07, 10 DATA ' 2.16E-05 EU 105 1.54E-08 NO DATA- 6.08E-09 NO DATA 1.99E-07 to DATA 9.42E-06 RU 106 2.75E-06 NO DATA 3.48E-07 NO DATA 5.31E-06 ID DATA 1.78E-04 AG 110M 1.60E-07 1.48E-07 8.79E-08 NO DATA 2.91E-07 to DATA 6.04E-05 TE 125M 2.68E-06 9.71E-07 3.59E-07 8.06E-07 1.09E-05 NO DATA 1.07E-05 r

( TE 127M TE 127 TE 129M 6.77E-06 2.4 2E-06 1.10E-07 3.95E-08 l.15E-05 4.29E-06 8.25E-07 2.38E-08 1.82E-06 1.73E-06 8.15E-08 3.95E-06 2.75E-05 4.48E-07 4.80E-05 IO DATA 10 DATA to DATA 2.27E-05 8.68E-06 5.79E-05 TE 129 3.14E-08 1.18E-08 7.65E-09 2.41E 1.32E-07 to DATA 2.37E-08 TE 131M 1.73E-06 8.46E-07 7.05E-07 ^ 1.34E-06 'O.57E-06 NO DATA 8.40E-05 TE 131 1.97E-08 8.23E-09 6.22E-09 1.62E-08 8.63E-08 10 DATA 2. 79E-09..

TE 132 2.52E-06 1.63E-06 1.53E-06 1.80E-06 1.57E-05' 10 DATA i 7.71E iO5 I 130 7.56E-07 2.23E-06 8.80E-07 1,89E-04. 3.48E-06 10 DATA 'l.92C-06 I 131 4.16E-06' 5.95E'06 -

3.41E-06 1.95E-03' l.02E-05 BO DATA 1.57E-06 I 132 2.03E-07 5.43E-07 1.90E-07 1.90E-05 .65E-07 NO DATA 1.02E-07 I 133 1.42E-06 2.47E-06 7.53E-07 3.63E-04 4.31E-06 to DATA 2.22E-06 I 134 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 PO DATA 2.51E-10

I 135 4.43E-07 1.16E-06 4.28E-07 7.65E-05 1.86E-06 to DATA 1.31E-06 CS 134 6.22E-05 1.48E-04 1.21E-04 NO DATA 4.79E-05 1.59E-05 2.59E-06 CS 136 6.51E-06 2.57E-05 1.85E-05 NO DATA 1.43E 1.96E-06 2.92E-06 ,

CS 137 7.97E-05 1.09 E-04 _ 7.14E-d5 NO DATA 3.70E-05 1.23E-05 2.llE-06 h CS 138 BA 139 5.52E-08 1.09E-07 5'40E-08 9.70E-08 6.91E-ll. 2.84E-09

. NO DATA 1D DATA 8.012-08 6.46E-ll 7.91E-09 3.92E-11 4.65E-13 1.72E-07 A-19

? . .

~

1 TABLE A.3-1 (cont'd)

(

INGESTION DOSE FAC'IORS EUR ADULTS (MREM PER PCI INGESTED)

NUCLIDE BONE LIVER T BODY 'IHYROID KIDNEY LUNG GI-LLI BA 140 2.d3E-05 2.55E-08 1.33E-06 10 DATA 8.67E-09 1.46E-08 4.18E-05 BA 141 4.71E-08 3.56E-ll 1.59E-09 NO DATA 3.31E-11 2.02E-11 2.22E-17 BA 142 2.13E-08 2.19E 1.34E-09 NO DATA 1.85E-ll 1.24E-11 3.00E-26 LT 140 . 2.50E-09 1.26E-09 3.33E-10 10 DATA NO DATA 10 DATA 9.2SE-05 LA 142 1.28E-10 5.82E-11 1.45E-ll NO DATA NO DATA NO DATA 4.25E-07 CE 141 9.36E-09 6.33E-09 7.18E-10 NO DATA 2.94E-09 NO DATA 2.42E-05 CE 143 1.65E-09 1.22E-06 1.35E-10 10 DATA 5.37E-10 NO DATA 4.56E-05 CE 144 4.88E-07 2.04E-07 2.62E-08 10 DATA 1.21E-07 10 DATA 'l.65E-04 PR 143 9.20E-09 3.69E-09] 4.56E-10 NO DATA 2.13E-09 NO DATA 4.03E-05 PR 144 3.01E-ll 1.2SE-ll 1.53E-12 NO DATA 7.05E-12 10 DATA 4.33E-18 ND 147 6.29E-09 7.27E-09 4.35E-10 to DATA 4.25E-09 NO DATA 3.49E-05

. W 187 1.03E-07 8.61E-08 3.01E-08 NO DATA NO DATA 10 DATA 2.82E-05 NP 239 1.19E-09 1.17E-10 6.45E-ll to DATA 3.65E-10 NO DATA 2.40E-05

' . T -

n

(

/

q *d a

a 4

1

= A

}

f s .

i A-20

?

S.

%l ,

TABLE A'.3-2*

INGESTION DOSE FACIORS EOR TEENAGERS (MREM PER PCI INGESTED) e NUCLIDE BONE LIVER T BODY 'HiYFOID KIDNEY LUhG GI-LLI H 3 to DATA 1.06E-07 1.06E-07 1.06E-07' 1.06E-07 1.06E-07 1.06E-07

.C 14 4.06E-06 8.12E-07 S.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 NA 24 2.30E,-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 P 32 2.76E-04 1.71E-05 1.07E-05 NO DATA NO DATA 10 DATA 2.32E-05

, , CR 51 NO DATA to DATA 3.60E-09 2.00E 7.89E-10 5.14E-09 6.05E-07

,c MN 54 10 DATA 5.90E-06 1.17E-06 10 DATA 1.76E-06 1

NO DATA -1.21E-05

.(

f. s v IN 56 tD DATA 1.58E-07 2.81E-08 NO DATA 2.00E-07 NO DATA 1.04E-05

- ' tTjiS' -

3.78E-06 2.68E-06 6.25E-07 to DATA to DATA 1.70E-06 1.16E-06

/ < [U 39 a ~ ?5.87E-06 1.37E-05 5.29E-06 10 DATA NO DATA 4,32E-06 3.24E-05

(//<

.( y -

9

/ 00j 58 ' NO DATA J9.72E-07 2.24E-06 .NO DATA NO DATA to DATA 1.34E-05 i, CO 60 10 DATA ' ' 2.81E-06 6.33E-06' 10 DATA NO DATA t0 DATA 3.66E-05

' '/ NI 63 1.77E-04 1.25E-05 6.00E-06 IO DATA NO DATA IO DATA 1.99E-06

'((,4 , ; '

!O c 1.

/ L NI 65 7.49E-07. 9.57F[0S J 4.36E-08I NO DATA to DATA . ID CATA 5.19E-06 CU 64 to DATA 1.152--07' 5.41E-08s IP DATA 2.91E-07 PO DATA 8.92E-06

.ZN 65 5.76E-06 2.00It-05 9.33E-06 NO DATA 1.28E-05 20 DATA 8.47E-06

[ ( '

e

~

I, ,-_ --

(

, if4, i ZN 69 1.47E-08 2.60E-08 " 1.96E-09 10 DATA 1.83E-08 10 DATA

,. 2 5.16E-08

' 'BR 83

. ?O DATA NO rhTA 5.74E-08 to DATA 10 DATA to DATA LT E-24

[/k.[ 'Yi , ,

BR 84 NO DATA 1

NO DATA 7.22E-08 to DATA to DATAs FO DATA Lt E-24 1l. 4,/

1 p BR 85 10' MTA :

10 DATA 3.05E-09 10 DATA 10 DATA 10 DATA LT E-24 RB 86 10 DATA / 2.98E-05 1.40E-05 10 DATA to DATA ' to DATA 4.41E-06 Y RB 88. NO DATA ~ 8.52E-08 .4.54E-08 !O DATA 10 DATA PC DATA 7.30E-15

.; T' b .

,7 ( ,

d V Sh89; NO DATA 5.50E-08 3.89E-08 10 DATA NO DATA NO DATA 8.43E-17

.j SPl89' T 4.40E-04 N3 DATA 1.26E-05 NO DATA ?O DATA NO DATA 5.24E-05

{ ,, y T SR 90 8.30E-03 NO DATA ! 2.05E-03 NO DATA NO DATA NO DATA 2.33E-04 f 3 t

-i ! s( ,1

, g SR 91 E 07E-06 NO DATA '

'3.21E-07 NO DATA NO DATA NO DATA 3.66E-05

, SR 92 3.05E-06' NO DATA , 1.30E-07 NO DATA 10 DATA to DATA 7.77E-05 Y 90 , ^1.378-08 NODATA; '3.69E-10 ?O DATA NO DATA NO DATA 1.13E-04 i

Y '91M 1.29E-10 NO DATAT 4.952-12 10 DATA to DATA to DATA ~6.09E-09 Y 9L '

2.01E-07 ,NO DATA 5.39E-09 10 DATA !O DATA- to DATA 8.24E-05

./,

.k Y 92' l.21E-09 tO DATA l 3.50E-ll BO DATA NO DATA to DATA 3.32E-05

/~ *Takem r: rom Regulatory Gpice 1.1091(Rev.1).

6 >

l ' ll \ a . .

,. 9

y. ,j .A-21 N jdf s _. . _ .

TABLE A.3-2 (cont *d)

INGESPION DOSE FAC'IORS EUR TEENN3ERS

{ (MREM PER PCI INGESTED)

NUCLIDE DONE LIVER T BODY 'IHYROID KIDNEY LUNG GI-LLI Y 93 3.83E-09 to DATA 1.05E-10 10 DATA ?O DATA 10 DATA 1.17E-04 2R 95 4.12E-08 1.30E-08 8.94E-09 to DATA 1.91E-08 10 DATA 3.00E-05 ZR 97 2.37E-09 4.69E-10 2.16E-10 to DATA 7.llE-10 to DATA 1.27E-04 NB 95 8.22E-09 4.56E-09 2.51E-09 NO DATA 4.42E-09 to DATA 1.95E-05 MO 99 10 DATA 6.03E-06 1.15E-06 !O DATA 1.38E-05 to DATA 1.08E-05

'IC 99M 3.32E-10 9.26E-10 1.20E-08 NO DATA 1.38E-08 5.14E-10 6.08E-07

'IC 101 3.60E-10 5.12E-10 5.03E-09 10 DATA 9.26E-09 3.12E-10 8.75E-17 RU 103 2.55E-07 to DATA 1.09E-07 NO DATA 8.99E-07 to DATA ~ 2.13E-05 RU 105 2.18E-08 NO DATA 8.46E-09 10 DATA 2.75E-07 NO DATA 1.76E-05 RU 106 3.92E-06 10 DATA 4.94E-07 NO DATA 7.56E-06 PO DATA 1.88E-04 AG 110M 2.05E-07 1.94E-07 1.18E-07 to DATA 3.70E-07 NO DATA 5.45E-05 TE 125M 3.83E-06 1.38E-06 5.12E-07 1.07E-06 to DATA to DATA 1.13E-05 TE 127M 9.67E-06 3.43E-06 1.15E-06 2.30E-06 3.92E-05 NO DATA 2.41E-05 C. TE 127 1.5RR-07 5.60E-08 3.40E-08 1.09E-07 6.40E-07 10 DATA 1.22E-05 TE 129M 1.63E-05 6.05E-06 2.58E-06 5.26E-06 6.82E-05 to DATA 6.12E-05 TE 129 4.48E-08 1.67E-08 1.09E-08 3.20E-08 1.88E-07 NO DATA 2.45E-07 TE 131M 2.44E-06 1.17E-06 9.76E-07 1.76E-06 1.22E-05 10 DATA 9.39E-05 TE 131 2.79E-08 1.15E-08 8.72E-09 2.15E-08 1.22E-07 10 DATA 2.29E-09 TE 132 3.49E-06 2.21E-06 2.08E-06 2.33E-06 2.12E-05 10 DATA 7.00E-05 I 130 1.03E-06 2.98E-06 1.19E-06 2.43E-04 4.59E-06 PO DATA 2.29E-06 I 131 5.85E-06 8.19E-06 '4.40E-06 2.39E-03 1.41E-05 to DATA 1.62E-06 I 132 2.79E-07 7.30E-07 2.62E-07 2.4 6E-Oc '5E-06 to DATA 3.18E-07 I 133 2.01E-06 3.41E-06 1.04E-06 4.76E-04 a.98E-06 NO DATA 2.58E-05 I 134 1.46E-07 3.87E-07 1.39E-07 6.45E-06 6.10E-07 10 DATA 5.10E-09 I 135 6.10E-07 1.57E-06 5.82E-07 1.01E-04 2.48E-06 NO DATA 1.74E-06 CS 134 8.37E-05 1.97E-04 9.14E-05 to DATA 6.26E-05 2.39E-05 2.45E-06 CS 136 8.59E-06 3.38E-05 2.27E-05 NO DATA 1.84E-05 2.90E-06 2.72E-06 CS 137 1.12E-04 1.49E-04 5.19E-05 NO DATA 5.07E-05 1.97E-05 2.12E-06 CS 138 7.76E-08 1.49E-07 7.45E-08 NO DATA 1.10E-07 1.28E-08 6.76E-ll BA 139 -1.39E-07 9.78E-11 4.05E-09 NO DATA 9.22C-ll 6.74E-ll 1.24E-06 A-22

TABLE A.3-2 (cont'd)

INGESTION DOSE FACTORS EOR TEENAGERS C (MREN PER PCI INGESTED)

NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI EA 140 2.84 E-05 3.48E-08 1.83E-06 NO DATA 1.18E-08 2.34E-08 4.38E-05 !

BA 141 6.71E-08 5. ole-ll 2.24E-09 NO DATA 4.65E-ll 3.43E-ll 1.43E-13 BA 142 2.99E-08 2.99E-ll 1.84E-09 NO DATA 2.53E-11 1.99E-11 9.18E-20 LA 140 3.48E-09 1.71E-09 4.55E-10 NO DATA 10 DATA tO DATA 9.82E-05 LA 142 1.79E-10 7.95E-ll 1.98E-ll NO DATA 10 DATA 10 DATA 2.42E-06 -

CE 141 1.33E-08 8.88E-09 1.02E-09 NO DATA 4.18E-09 NO DATA 2.546-05 CE 143 2.35E-09 1.71E-06 1.91E-10 NO DATA 7.67E-10 to DATA 5.14E-05 CE 144 6.96E-07 2.88E-07 3.74E-08 NO DATA 1.72E-07 to DATA

1.75E-04

, PR 143 1.31E-08 5.23E-09 6.52E-10 fO DATA 3.04E-09 to DATA 4.31E-05 PR 144 4.30E-ll 1.76E-ll 2.18E-12 NO DATA 1.01E-ll to DATA 4.74E-14 ND 147 9.38E-09 1.02E-08 6.11E-10 NO DATA 5.99E-09 to DATA 3.68E-05 W 187 1.46E-07 1.19E-07 4.17E-08 NO DATA NO DATA 10 DATA 3.22E-05

( NP 239 1.76E-09 1.66E-10 9.22E-11 NO DATA 5.21E-10 to DATA 2.67E-05 A-23

'IABLE A.3-3*

( INGESTION DOSE FACTORS EOR OIILD (MREM PER PCI INGESTED)

NUCLIDE BONE LIVER T BODY 'nWROID KIDNEY LUNG GI-LLI H 3 NO DATA 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 C 14 1.21E-05 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 NA 24 2.42E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 P 32 8.25E-04 3.86E-05 3.18E-05 ?O DATA to DATA to DATA CR 51 NO DATA 2.28E-05 NO DATA 8.90E-09 4.94E-09 1.35E-09 9.02E-09 4.72E-07 MN 54 to DATA 1.07E-05 2.85E-06 to DATA 3.00E-06 NO DATA 8.98E-06 MN 56 NO DATA 3.34E-07 7.54E-08 NO DATA 4.04E-07 FE 55 NO DATA .4.84E-05 1.15E-05 6.10E-06 1.89E-06 NO DATA to DATA 3.45E-06 1.13E-06 FE 59 1.65E-05 2.67E-05 1.33E-05 to DATA PO DATA 7.74E-06 2.78E-05 CO 58 to DATA 1.80E-06 5.51E-06 10 DATA PO DATA to DATA 1.05E-05 CD 60 to DATA 5.29E-06 1.56E-05 NO DATA to DATA 10 DATA 2.93E-05 NI 63 5.38E-04 2.88E-05 1.83E-05 ?O DATA NO DATA PO DATA 1.94E-06

( NI 65 CU 64

~ZN 65 2.22E-06 2.09E-07 to DATA 2.45E-07 1.37E-05 3.65E-05 1.22E-07 1.48E-07 2.27E-05 NO DATA NO DATA tO DATA 5.92E-07 to DATA NO uhTA 2.56E-05 1.15E-05

?O DATA 2.30E-05 to DATA 6.41E-06 ZN 69 4.38E-08 6.33E-08 5.85E-09 NO DATA 3.84E-08 NO DATA 3.99E-06 BR 83 10 DATA NO DATA 1.71E-07 10 DATA 10 DATA PO DATA LT E-24 BR 84 NO DATA NO DATA 1.98E-07 NO DATA NO DATA to DATA LT E-24 BR 85 10 DATA NO DATA 9.12E-09 10 DATA NO DATA FO DATA LT E-24 RB 86 NO DATA 6.70E-05 4.12E-05 NO DATA to DATA ?O DATA 4.3]E-06 RB 88 NO DATA 1.190E-07 1.32E-07 NO DATA NO DATA to DATA 9.32E-09 RB 89 10 DATA 1.17E-07~ 1.04E-07 NO DATA FO DATA 10 DATA 1.02E-09 SR 89 1.32E-03 NO DATA 3.77E-05 NO DATA NO DATA NO DATA 5.11E-05 SR 90 1.70E-02 to DATA 4.31E-03 NO DATA NO DATA NO DATA 2.29E-04 SR 91 2.40E-05 to DATA 9.06E-07 NO DATA NO DATA 10 DATA 5.30E-05 SR 92 9.03E-06 ?O DATA 3.62E-07 NO DATA NO DATA to DATA 1.71E-04 Y 90 4.llE-08 to DATA 1.10E-09 NO DATA PO IMTA PO DATA 1.17E-04 Y 91M

( Y 91 Y 92 3.82E-10 to DATA 6.02E-07 NO DATA 3.60E-09 NO DATA 1.39E-ll 1.61E-08 J.03E-10 NO DATA 10 DATA to DATA NO DATA NO DATA NO DATA to DATA NO DATA to DATA 7.48E-07 8.02E-05 1.04E-04 "Taken fran Regulatory Gulce 1.109 (Rev.1)

A-24

TABLE A.3-3 (cont'd)

( INGESTION DOSE FACTORS EOR CHILD (MREM PER PCI INGESTED)

NUCLIDE BONE LIVER T BODY 'IHYROID KIDNEY LUNG GI-LLI Y 93 1.14E-08 FO DATA 3.13E-10 PO DATA 10 DATA 10 DATA 1.70E-04 ZR 95 1.16E-07 2.55E-08 2.27E-08 10 DATA 3.65E-08 NO DATA 2.66E-05 2R 97 6.99E-09 1.01E-09 5.96E-10 10 DATA 1.45E-09 to DATA 1.53E-04 NB 95 2.25E-08 8.76E-09 6.26E-09 to DATA 8.23E-09 10 DATA 1.62E-05 BD 99 to DATA 1.33E-05 3.29E-06 to DATA 2.84E-05 10 DATA 1.10E-05 TC 99M 9.23E-10 1.81E-09 3.00E-08 to DATA 2.63E-08 9.19E-10 1.03E-06 TC 101 1.07E-09 1.12E-09 1.42E-08 NO DATA 1.91E-08 5.92E-10 3.56E-09 BU 103 7.31E-07 to DATA 2.81E-07 NO DATA 1.84E-06 to DATA ~1.89E-05 RU 105 6.45E-08 10 DATA 2.34E-08 NO DATA 5.67E-07 to DATA 4.21E-05 RU 106 1.17E-05 10 DATA 1.46E-06 PO DATA 1.58E-05 t0 DATA 1.82E-04 AG 110M 5.39E-07 3.64E-07 2.91E-07 NO DATA 6.78E-07 to DATA 4.33E-05 TE 125M 1.14E-05 3.09E-06 1.52E-06 3.20E-06 PO DATA 10 DATA 1.10E-05

( TE 127M TE 127

'rE 129M 2.89E-05 7.78E-06 4.71E-07 1.27E-07 4.87E-05 1.36E-05 3.43E-06 1.01E-07 7.56E-06 6.91E-06 3.26E-07 1.57E-05 8.24E-05 1.34E-06 1.43E-04 BO DATA 10 DATA PO DATA 2.34E-05 1.84E-05 5.94E-05 TE 129 1.34E-07 3.74E-08 3.18E-08 9.56E-08 3.92E-07 IO DATA 8.34E-06 TE 131M 7.20E-06 2.49E-06 2.65E-06 5.12E-06 2.41E-05 to DATA 1.01E-04 TE 131 8.3GE-08 2.53E-08 2.47E-08 6.35E-08 2.51E-07 to DATA 4.36E-07 TE 132 1.01E-05 4.47E-06 5.40E-06 6.51E-06 4.15E-05 to DATA 4.50E-05 I 130 2.92E-06 5.90E-06 3.04E-06 6.50E-04 8.82E-06 10 DATA 2.76E-06 I 131 1.72E-05 1.73E-05 9.83E-06 5.72E-03 2.84E-05 to DATA 1.54E-06 I 132 8.00E-07 3.47E-06 6.76E-07 6.82E-05 2.25E-06 to DATA 1.73E-06 I 133 5.92E-06 7.32E-06 2.77E-06 1.36C-03 1.22E-05 10 DATA 2.95E-06 I- 134 4.19E-07 7.78E-07 3.58E-07 1.79E-05 1.19E-06 lO DATA 5.16E-07 I 135 1.75E-06 3.15E-06 1.49E-06 2.79E-04 4.83E-06 ?O DATA 2.40E-06 CS 134 2.34E-04 3.84E-04 8.10E-05 to DATA 1.19E-04 4.27E-05 2.07E-06 CS 136 2.35E-05 6.46E-05 4.18E-05 PO DATA 3.44E-05 5.13E-06 2.27E-06 I

CS 137 3.27E-04 3.13E-04 4.62E-05 to DATA 1.02E-04 3.67E-05 1.96E-06 CS 138 2.28E-07 3.17E-07 2.01E-07 NO DATA 2.23E-07 2.40E-08 1.46E-07

{ BA 139 4.14E-07 2.21E-10 1.20E-08 NO DATA 1.93E-10 1.30E-10 2.39E-05 A-25 l

L

o .

l TABLE A.3-3 (cont'd)

( INGESTION DOSE FACIORS FOR CHILD (MREM PER PCI IfGESTED)

NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI BA 140 8.31E-05 7.28E-08 4.85E-06 NO DATA 2.37E-08 4.34E-08 4.21E-05 BA 141 2.00E-07 1.12E-10 6.51E-09 NO DATA 9.69E-ll 6.58E-10 1.14E-07 BA 142 8.74E-08 6.29E-ll 4.88E-09 NO DATA 5.09E-ll 3.70E-11 1.14E-09 l

LA 140 1.01E-08 3.53E-09 1.19E-09 NO DATA NO DATA 10 DATA 9.84E-05 l IA 142 5.24E-10 1.67E-10 5.23E-ll NO DATA to DATA NO DATA 3.31E-05 CE 141 3.97E-08 1.98E-08 2.94E-09 NO DATA 8.68E-09 NO DATA 2.47E-05 CE 143 6.99E-09 3.79E-06 5.49E-10 NO DATA 1.59E-09 NO DATA 5.55E-05 CE 144 2.08E-06 6.52E-07 1.llE-07 NO DATA 3.61E-07 NO DATA

1.70E-04 f

PR 143 3.93E-08 1.18E-08 1.95E-09 NO DATA 6.39E-09 ?O DATA 4.24E-05 PR 144 1.29E-10 3.99E-ll 6.49E-12 NO DATA 2.llE-ll ?O DATA 8.59E-08 ND 147 2.79E-08 2.26E-08 1.75E-09 NO DATA 1.24E-08 NO DATA 3.58E-05 W 187 4.29E-07 2.54E-07 1.14E-07 NO DATA NO DATA NO DATA 3.57E-05 NP 239 5.25E-09 3.77E-10 2.65E-10 NO DATA 1.09E-09 NO DATA 2.79E-05

d A-26

TABLE A.3-4*

INGESTION DOSE FACIORS FOR INFAtir (MREM PER PCI ItDESTED)

NUCLIDE BONE LIVER T BODY 'IHYROID KIDNEY UJNG GI-LLI H 3 NO DATA 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 C 14 2.37E-05 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 NA 24 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 P 32 1.70E-03 1.00E-04 6.59E-05 ?O DATA FO DATA to DATA 2.30E-05 CR 51 NO DATA to DATA 1.41E-08 9.20E-09 2.01E-09 1.79E-08 4.11E-07 MN 54 to DATA 1.99E-05 4.51E-06 NO DATA 4.41E-06 ?O DATA 7.31E-06 MN 56 to DATA 8.1E E-07 1.41E-07 NO DATA 7.03E-07 BD DATA 7.43E-05 FE 55 1.39E-05 8.9uE-06 2.40E-06 NO DATA NO DATA 4.39E-06 'l.14E-06 FE 59 3.08E-05 5.36E-05 2.12E-05 IO DATA to DATA 1.59E-05 2.57E-05 CO 58 to DATA 3.60E-06 8.98E-06 NO DATA to DATA NO DATA 8.97E-06 CD 60 to DATA 1.08E-05 2.55E-05 PO DATA !O DATA NO MTA 2.57E-05 NI 63 6.34E-04 3.92E-05 2.20E-05 ?O DATA NO DATA 10 DATA 1.95E-06 NI 65 4.70E-06 5.32E-07 2.42E-07 to DATA NO DATA to DATA 4.05E-05

( CU 64

.ZN 65 to DATA 6.09E-07 1.84E-05 6.31E-05 2.82E-07 2.91E-05 NO DATA to DATA 1.03E-06 3.06E-05 ID DATA ID DATA 1.25E-05 5.33E-05 ZN 69 9.33E-08 1.68E-07 1.25E-08 to DATA 6.98E-08 10 DJ.TA 1.37E-05 BR 83 to DATA 10 DATA 3.63E-07 NO DATA NO DATA tO DATA LT E-24 BR 84 NO DATA NO DATA 3.82E-07 NO DATA to DATA NO DATA LT E-24 BR 85 10 DATA NO DATA 1.94E-08 NO DATA 10 DATA to DATA LT E-24 RB 86 ?O DATA 1.70E-04 8.40E-05 NO DATA NO DATA 10 DATA 4.35E-06 RB 88 NO DATA 4.98E-07 2.73E-07 NO DATA to DATA IO DATA 4.85E-07 RB 89 to DATA 2.86E-07 1.97E-07 10 DATA to DATA NO DATA 9.74E-08 SR 89 2.51E-03 NO DATA 7.20E-05 10 DATA to DATA PO MTA 5.16E-05 SR 90 1.85E-02 NO DATA 4.71E-03 to DATA NO DATA FD DATA 2.31E-04 SR 91 5.00E-05 ?O DATA 1.81E-06 to DATA NO DATA NO DATA 5.92E-05 SR 92 1.92E-05 to DATA 7.13E-07 IO DATA 10 DATA 10 DATA 2.07E-04 Y 90 8.69E-08 NO DATA 2.33E-09 NO DATA to DATA 10 DATA 1.20E-04 Y 91M 8.10E-10 PO DATA 2.76E-ll ?O DATA to DATA to MTA 2.70E-06 Y 91 1.13E-06 to DATA 3.01E-08 NO DATA to DATA to DATA 8.10E-05 Y 92 7.65E-09 ?O DATA 2.15E-10 10 DATA NO DATA to DATA 1.46E-04

Taken fran Regulatory Guide 1.109 (Rev.1)

A-27

TABLE A.3-4 (cont'd)

I

( INGESTICN DOSE FACIORS FOR INFANT (MREM PER PCI INGESTED)

NUCLIDE BONE LIVER T BODY TilYROID KIDNEY IENG GI-LLI Y 93 2.43E-08 10 DAR 6.62E-10 NO DAM to DAM NO DAB 1.92E-04 ZR 95 2.06E-07 5.02E-08 3.56E-08 NO DAM 5.41E-08 NO DAM 2.50E-05 ZR 97 1.48E-08 2.54E-09 1.16E-09 to dam 2.56E-09 NO dam 1.62E-04 NB 95 4.20E-08 1.73E-08 1.00E-08 to dam 1.54E-08 to dam 1.46E-05 I MO 99 to DATA 3.40E-05 6.63E-06 NO dam 5.08E-05 NOmm 1.12E-05 TC 99M 1.92E-09 3.96E-09 5.10E-08 NO DAM 4.26E-08 2.07E-09 1.15E-06 i TC 101 2.27E-09 2.86E-09 2.83E-08 NO dam 3.40E-08 1.56E-09 . 4.86E-07 RU 103 1.48E-06 NO dam 4.95E-07 to dam 3.08E-06 NOmm 1.80E-05 RU 105 1.36E-07 10 DAM 4.58E-08 NO dam 1.00E-06 NO mm 5.41E-05 RU 106 2.41E-05 to DAM 3.01E-06 NO dam 2.85E-05 NO DAR 1.83E-04 AG 110M 9.96E-07 7.27E-07 4.81E-07 NO dam 1.04E-06 NO dam 3.77E-05 TE 125M 2.33E-05 7.79E-06 3.15E-06 7.84E-06 NO DAR 10 mm 1.11E-05 TE 127M 5.85E-05 1.94E-05 7.08E-06 1.69E-05 1.44E-04 NOmm C TE 127 1.00E-06 3.35E-07 2.15E-07 8.14E-07 2.44E-06 NO dam 2.36E-05 2.10E-05

TE 129M 1.00E-04 3.43E-05 1.54E-05 3.84E-05 2.50E-04 NO mm 5.97E-05 TE 129 2.84E-07 9.79E-08 6.63E-08 2.38E-07 7.07E-07 NO DAR 2.27E-05 TE 131M 1.52E-05 6.12E-06 5.05E-06 1.24E-05 4.21E-05 NO DAM 1.03E-04 TE 131 1.76E-07 6.50E-08 4.94E-08 1.57E-07 4.50E-07 NO DAM 7.11E-06 TE 132 2.08E-05 1.03E-05 9.61E-06 1.52E-05 6.44E-05 NO DAM 3.81E-05 I 130 6.00E-06 ~1.32E-05 5.30E-06 1.48E-03 1.45E-05 NO DAM 2.83E-06 I 131 3.59E-05 4.'23E-05 1.86E-05 1.39E-02 4.94E-05 NO mm 1.51E-06 I 132 1.66E-06 3.37E-06 1.20E-06 1.58E-04 3.76E-06 NOmm 2.73E-06 I 133 1.25E-05 1.82E-05 5.33E-06 3.31E-03 2.14E-05 NO mm 3.08E-06 I 134 8.69E-07 1.78E-06 6.33E-07 4.15E-05 1.99E-06 NO mm 1.84E-06 I 135 3.64E-06 7.24E-06 2.64E-06 6.49E-04 8.07E-06 NO m m 2.62E-06 CS 134 3.77E-04 7.03E-04 7.10E-05 NO DATA 1.81E-04 7.42E-05 1.91E-06 CS 136 4.59E-05 1.35E-04 5.04E-05 NO DATA 5.38E-05 1.10E-05 2.05E-06

( CS 137 CS 138 BA 139 5.22E-04 6.llE-04 4.81E-07 7.82E-07 8.81E-07 5.84E-10 4.33E-05 3.79E-07 2.55E-08 NO DATA NO DATA NO dam 1.64E-04 3.90E-07 3.51E-10 6.64E-05 6.09E-08 3.54E-10 1.91E-06 1.25E-06 5.58E-05 A-28

TABLE A.3-4 (cont'd)

INGESTICN DOSE FACIORS EOR INFANT (MREM PER PCI INGESTED)

NUCLIDE BONE LIVER T BODY THYPOID KIDNEY LUNG GI-LLI BA 140 1.71E-04 1.71E-07 8.81E-06 NO DATA 4.06E-08 1.05E-07 4.20E-05 BA 141 4.25E-07 2.91E-10 1.34E-08 NOmm 1.75E-10 1.77E-10 5.19E-06 BA 142 1.84E-07 1.53E-10 9.06E-09 NO DAM 8.81E-11 9.26E-ll 7.59E-07 LA 140 2.11E-08 8.32E-09 2.14E-09 NO DATA NO DATA LA 142 NO DATA 9.77E-05 1.10E-09 4.04E-10 9.67E-ll NO DATA NO DATA NO DATA 6.86E-05 CE 141 7.87E-08 4.80E-08 5.65E-09 NO DATA 1.48E-08 NO DATA 2.48E-05 CE 143 1.48E-08 9.82E-06 1.12E-09 NO DATA 2.86E-09 NO DAM 5.73E-05 CE 144 2.98E-06 1.22E-06 1.67E-07 NO DAM 4.93E-07 NO DAM 'l 71E-04 PR 143 8.13E-08 3.04E-08 4.03E-09 NO DAS 1.13E-08 NO DATA 4.29F-05 PR 144 2.74E-10 1.06E-10 1.38E-11 NO DATA 3.84E-ll NO DA m 4.93E-06 ND 147 5.53E-08 5.68E-08 3.48E-09 NO DAS 2.19E-08 NO DATA 3.60E-05 W 187 9.03E-07 6.28E-07 2.17E-07 NO DATA NO mm NOmm 3.69E-05 NP 239 1.llE-08 9.93E-10 5.61E-10 NO DATA 1.98E-09 NO DAR 2.87E-05 o

L A-29

TABLE A.3-5*

STABLE ELEMENT TRANSFER DATA B Fg y Fm (Cow)

Element Veg/ Soil Milk (d /.t) Meat (d/kg)

H 4.8E 00 1.0E-02 1.2E-02 C 5.5E 00 1.2E-02 3.lE-02 Na 5.2E-02 4.0E-02 3.0E-02 P. 1.1E 00 2.5E-02 4.6E-02 Cr 2.5E-04 2.2E-03 2.4E-03 Mn 2.9E-02 2.5E-04 8.0E-04 Fe 6.6E-04 1.2E-03 4.0E-02 Co 9.4E-03 1.0E-03 1.3E-02 Ni 1.9E-02 6.7E-03 5.3E-02 Cu 1.2E-01 1.4E-02 8.0E-03 Zn 4.0E-01 3.9E-02 3.0E'02 Rb 1.3E-01 3.0E-02 3.lE-02 Sr 1.7E-02 8.0E-04 6.0E-04 Y 2.6E-03 1.0E-05 4.6E-03 Zr 1.7E-04 5.0E-06 3.4E-02 Nb 9.4E-03 2.5E-03 2.8E-01 Mo 1.2E-01 7.5E-03 8.0E-03 Tc 2.5E-01 2.5E-02 4.0E-01 Ru 5.0E-02 1.0E-06 4.0E-01 Rh 1.3E 01 1.0E-02 1.5E-03

( Ag 1.5E-01 5.0E-02 1.7E-02 Te 1.3E 00 1.0E-03 7.7E-02 I 2.0E-02 6.0E-03+ 2.9E-03 Cs 1.0E-02 1.2E-02 4.0E-03 Ba 5.0E-03 4.0E-04 3.2E-03 La 2.5E-03 5.0E-06 2.0E-04 Ce 2.5E-03 1.0E-04 1.2E-03 Pr 2.5E-03 5.0E-06 4.7E-03 Nd 2.4E-03 5.0E-06 3.3E-03 W l.8E-02 5.0E-04 1.3E-03 Np 2.5E-03 5.0E-06 2.0E-04

Taken from Regulatory Guide 1.109 (Rev. 1)

+Fm for goat is 6.0E-2.

L A-30

TABLE A.4-1 Total Dose Factors for Radionuclides ELEMENT PiI pig piF po x ( t)

H 3 646.8 2.4E3 4.57E-1 C 14 2.65E4 2.4E9 4.72E1 Na 24 1.06E4 1.98E7 1.58E7 2.23 P 32 2.03E6 1.63 Ell 3.24E3 Cr 51 1.28E4 7.88E6 5.44E5 2.07 Mn 54 1.0E6 1.27E9 1.46E15 2.63E7 Mn 56 7.17E4 1.52E7 3.04E5 1.10El Fe 55 8.69E4 1.37E8 1.55El Fe 59 1.02E6 4.61E8 4.00E8 1.68El Co 58 7.77ES 6.23E8 6.16E7 1.29E2 Co 60 4.51E6 5.17E9 2.14E8 7.73E2 Ni 63 3.39E5 3.56E10 6.92E2 Ni 65 5.01E4 5.0155 3.85El 7.52 Cu 64 1.50E4 9.93E5 4.03E6 2.34 Zn 65 6.47ES 7.92E8 1.94E10 4.61E2 Zn 69 1.32E4 7.05E-9 1.98 Br 83 3.81E2 1.02E4 ---

5.74E-2 Br 84 4.00E2 3.38E5 ---

6.61E-2 Br 85 2.04El ---

3.'06E-3 Rb 86 1.90E5 1.47E7 6.04E8 3.96El

( Rb 88 5.57E2 5.40E4 1.91E-44 8.45E-2 Rb 89 3.21E2 2.10E5 2.45E-52 5.19E-2 Sr 89 2.03E6 3.71E4 1.29E10 5.37E2 Sr 90 4.09E7 1.24 Ell 2.27E4 Sr 91 7.34E4 3.65E6 3.55ES 1.llEl Sr 92 1.4E5 1.23E6 4.86El 2.10E1 Y 90 2.69E5 7.59E3 9.59ES 4.04El Y 91m 2.79E3 1.68E5 2.95E-15 4.22E-1 Y 91 2.45E6 1.72E6 5.36E6 3.68E2 Y 92 1.27ES 3.03E5 9.30E0 1.91El Y 93 1.67ES 3.65ES 1.88E4 2.51El Zr 95 .l.75E6 4.08E8 8.45E5 2.70E2 Zr 97 1.40E5 4.96E6 4.64E4 2.llEl Nb 95 4.79E5 2.29E8 2.10E8 7.98El Mo 99 1.35E5 6.71E6 3.23E8 2.62E8 Tc 99m 2.03E3 3.01E5 1.67E4 3.10E-1 Tc 101 8.44E2 3.19E4 7.32E-58 1.27E-1 Ru 103 5.52E5 1.81E8 1.07E5 8.61El Ru 105 4.84E4 1.0336 3.24E0 7.28 Ru 106 1.16E7 3.59ES 1.47E6 1.75E3 Ag 110m 3.67E6 3.6789 1.49E10 8.85E2 Te 125m 4.47E5 3.01E6 L.54E8 6.99El Te 127m 1.31E6 1.3985 l.06E9 2.16C2 Te 127 2.44E4 4.59E3 1.24E5 3.66 Te 129m 1.68E6 3.35E7 1.43E9 2.78E2

[ Te 129 2.63E4 4.38E4 1.54E-7 3.95

( Te 131m 1.99ES 1.36E7 2.34E7 3.05El Te 131 3.22E3 4.89E7 7.23E-31 2.11 ODCM A-31

a .

TABLE A.4-1 (Cont.)

ELEMENT Pil pig 'PiF pox (i)

Te 132 3.40E5 7.06E6 6.59E7 5.23El I 130 1.60E6 9.61E6 1.82E8 , 2.43E2 I 131 1.48E7 2.99E7 2.15 Ell 6.09E3 I 132 1.69ES 2.06E6 2.llEl 2.54El I 133 3.56E6 4.16E6 1.84E9 5.67E2 I 134 4.45E4 7.50E5 1.12E-10 6.69 I 135 6.96ES 4.26E6 4.36E6 1.05E2 Cs 134 7.03E5 3.28E9 6.92E10 1.41E3 Cs 136 1.35ES 2.55E8 6.07E9 1.34E2 Cs 137 6.12E5 1.34E9 6.13E10 1.22E3 Cs 138 8.76E2 5.86E5 2.13E-22 1.42E-1 Ba 139 S.10E4 1.70E5 2.76E-5 7.65 Ba 140 1.60E6 3.35E7 2.45E8 2.45E2 '-

Ba 141 4.75E3 6.69E4 9.02E-45 7.14E-1 Ba 142 1.55E3 7.17E4 2.99E-80 2.34E-1 La 140 1.68E5 3.llE7 1.91E5 2.58El La 142 5.95E4 1.26E6 5.32E-6 8.95 Ce 141 5.17ES 2.26E7 1.40E7 7.82El Ce 143 1.16ES 3.78E6 1.58E6 1.75El Ce 144 9.84E6 6.77E7 1.36E8 1.48E3 Pr 143 4.33E5 7.99ES 6.50El Pr 144 4.28E3 3.02E3 1.15E-48 6.42E-1

( Nd 147 3.22E5 1.45E7 5.87ES 4.86El W 187 3.96E4 3.92E6 2.55E6 4.84El Np 239 5.95E4 2.82E6 9.55E4 8.98

- a-ODCM A-32 L

ML20024F553

Text

1.0 INTRODUCTION

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