ML20112F980
| ML20112F980 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 01/09/1985 |
| From: | KANSAS GAS & ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20112F975 | List: |
| References | |
| PROC-850109, NUDOCS 8501160128 | |
| Download: ML20112F980 (106) | |
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OFFSITE DOSE' CALCULATION MANUAL i
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/N TABLE OF CONTENTS
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Page 1.0 Introduction 1
2.0 Liquid Effluents 1
2.1 Liquid Ef fluent Monitor Setpoints 1
2.2 Liquid Ef fluent Concentration - Compliance with 10 CFR 20 9
- 2. 3 ' Liquid Effluent Doses - Compliance with 10 CFR 50, Appendix I 10 2.4 Calibration Of Liquid Effluent Monitors 12 3.0 Gaseous Effluents 12 3.1 Gaseous Effluent Monitor Setpoints 12 3.2 Gaseous Effluent Concentration / Dose Rate - Compliance with 10 CFR 20 19 3.3-Gaseous Effluent Doses - Compliance with 10-CFR 50, Appendix I 22 3.4 Calibration Of Gaseous Ef fluent Monitors 30 4.0 Radiological Environmental Monitoring Progran 33 5.0 40 CFR.190 Dose Evaluation 38 Appendix,As Dose Conversion Factor Tables A-1 l
Appendix B:
Meteorological Model B-1 I
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LIST OF TABLES
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Table Page is_s/
.4-1 Radiological Environmental Monitoring Program 34 4-2 Sampling Location Numbers, Distance (miles) and Directions 37 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 and Daughters 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
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A.3-2~
Ingestion Dose Factor for Teenagers A-21 A.3-3 Ingestion Dose Factor for Child A-24 A.3 Ingestion Dose Factor for Infant A-27 A.3-5 Stable Element Transfer Data A A.4-1 Site Related Ingestion Dose Commitment. for Adult A-31 A.4-2 ' Site -Related Ingestion Dose Commitment Factor for A-34 Teenager A.4-3 Site Related Ingestion Dose Commitment Factor for '
A-37 Child A.4-4 Site Related Ingestion Dose Commitment Factor for A-40 Infant A.5-1 Inhalation Dose Parameter for the Child A-43 A.5-2 R ' Pathway Dose Factors for Adult A-44 I
A.5-3 RI Pathway Dose Factors for Teenager A-47 i
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'A.5-4 RI Pathway Dose Factors for Child A-50
'A.5-5 RI Pathway Dose Factors for Infant A-53 - -
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LIST OF FIGURES 4.1 Atmospheric Sampling 4.2
~ Water Sampling Locations r
4.3 Milk and Vegetation Sampling Locations 4.4 Distant Sampling Location B-1 Vertical Standard Deviation of Material in a Plume i
i B-2 Plume' Travel Distance Versus Fraction Remaining in Plume B-3 Plume Travel Distance Versus Relative Deposition Rate f
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l.0 INTRODUCTION The Offsite Dose Calculation Manual (ODCM) describes the methodology %nd parameters to be used in the calculation of offsite doses due to radioactive liquid and gaseous effluents.
.These dose estimates are used to demonstrate compliance with the Radiological Effluent Technical Specifications as requir-ed by 10CFR50.36,10 CFR 20.106,10 CFR 50 Appendix I, and 40CFR190.
The ODCM contents are based on " Preparation of Radiological Effluent 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.
~
~" provides the Radioicgical :.v '.r nmental Monitoring Prog raa.
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 requirements in 10 CFR Part 50.
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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 ef fluent radiation monitors are based on the instantaneous concentration limits of 10CFR20, 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 at 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 exceed ed.
Auditable records shall be maintained indicating, the actual setpoints used at all times.
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ODCM 1
12-20-84
i The' calculated alarm and trip action setpoints for the liquid effluent line monitors must satisfy the following equation:
cf
< C W~
Where:
C = The liquid effluent concentration limit (MPC) implementing Radiological Ef fluent Technical Specification 3.11.1.1 in uCi/ml.
c = The setpoint, in uC1/ml, of the radioactivity monitor measuring the radioactivity concentration in the effluent line prior to dilution and subsequent release; the setpoint,
)
which is inversely proportional to the volumetric flow of the effluent line and directly proportional to the volumetric flow of the dilution stream plus the effluent stream, represents a value, which, if exceeded, would result in
. concentrations exceeding the limits of 10CFR20 in the unrestricted area.
/ h f = The pump flow rate as measured at the radiation Is_,)
monitor location, in volume per unit time, but in the same units as F, below F = The dilution water flow rate as measured prior to the release point, in volume per unit time.
Thus, the expression for determining the setpoint on the liquid radwaste effluent line monitor becomes:
c < C( F+f)
(uCi/ml) f f"'s
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t%J occa 2
12-20-a4
2.1.1 CONTINUOUS LIQUID 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 demineralizer 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 conser. :.e4.y cased on I-131, tne most restrictive isotope expected to be present.
This is 7-s particularly appropriate for the turbine building drain line
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monitor since the most probable source is the secondary
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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
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select a radionuclide distribution on which to base the monitor setpoint.
Additionally, maximum effluent 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 tne 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 tne secondary system.
At that time an analysis of the effluent will be made to
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verify activity in the system ef fluent.
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12-20-84
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f x, 2.1.1.1 STEAM GENERATOR BLOWDOWN DISCHARGE MONITOR
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b SETPOINT (.Ci/ml) = MPC.131 X
- +
8 I
- where, MPCy_131 = Maximum Permissible Concentration of I-131, 3.0 E-7jACi/ml.
Fm
= Dilution flow rate.
= 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 31u7 ?d usi.
- he actual dilution "Isw ra o, the actual clowdown flow race, and the actual isotopic analysis as outlined in Section 2.1.2.
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
(.rs)isotope.
v 2.1.1.2 TURBINE BUILDING DRAIN MONITOR Fm+ FT Setpoint (Sci /ml) = MPCg 131 X FT
- where, MPC _131 = 3.0 E-7,nci/ml.
I Fm
= Dilution flow rate.
FT
= Turbine Building drain flow rate.
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 as outlined in Section 2.1.2.
Tne setpoint will still be based on the MPC of
()
I-131 due to the changing conditions of activity and I-131 being t
j the most. restrictive isotope.
v ODCM 4
12-20-84
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v 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 i
Monitor The setpoint is a function of dilution flow rate, tank flow rate, and isotopic composition.
A laboratory isotopic analysis is made of eacn oaten 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 CFR 20, Appendix B, Table II, Column 2 are not exceeded.
The setpoints are determined using the following methodology:
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1)
Determine concentrations of radioactivity of the batch being
(,j considered for release.
The isotopic concentration of the batch is the sum of the concentrations for the isotopes present as determined from the analysis required in Table 4.11-1 of the Radiological Effluent Technical Specifications.
I Ci=
- f. Cg + Ca + Cs + Ct + Cg i
9 Where:
Ci The concentration of nuclide i as determined by the analysis
=
of the waste sample.
The sum of the concentrations Cg of each measured C
=
g gamma emitting nuclide observed by gamma-ray spectros-copy of the waste sample.
The measured concentration Ca of alpha emitting
- Ca
=
nuclides observed by gross alpha analysis of.the monenly composite samplo.
The measured concentrations of Sr-89 and Sr-90 in
- Cs a
liquid waste as determined by analysis of the quarterly
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composite sample.
ODCM 5
12-20-84 j
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- Ct The measured concentration of H-3 in liquid waste as
=
determined by analysis of the monthly composite.
- Cg The measured concentration,of Fe-55 in liquid waste as
=
determined by analysis of'the quarterly composite.
- Values for these concentrations will be based on previous composite sample analysis as required by Table 4.11-1 of the Radiological Ef fluent Technical Specifi-cations.
2)
The measured radionuclide concentrations are used to calculate a dilution factor, P, which is the ratio of total dilution flow d
rate to tank flow rate required to assure that the limiting concentrations of Tecnnical Specification 3.11.1.1 are met at the point of discharge.
This is referred to as the required dilution factor and is datormined according to:
Fd=
(:E Ct
) x Fs (i RFc_t
)
Whores Ci Measured concentrations of Ca, Ca, Co, Ce and
=
Cg, as defined in Stop 1.
T6rms Ca, Cs, Ct and Cg, will be included in the calculation as appropriate.
MPCi MPC, MPCa, MPCs, MPCt and MPCg, are limiting a
g concentrations of the appropriate radionuclide from 10CFR20, Appendix B, Tablo II, Column 2.
For dissolved or entrained noble gason, the concentration shall ce limited to 2.0E-04, uCi/ml total activity.
the safety factor; a conservative factor used to Fa
=
compensate for statistical fluctuations and errors of measuromont default value is 1.0 3)
For the caso Fd < 1, the waste tanx offluent concentration moots the limits of 10CFR20 without dilution and the offluent may be released at any desired flow rato.
For the caso Pd > 1, a modified dilution factor, P n, must bo dotormined so that d
availablo dilution flow may be apportioned among simultaneous dischargo pathways.
ODCM 6
12-20-94
- d
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I' Fdn = Fd + Fa
. Where Fa is the allocation factor which will modify the required dilution factor so that simultaneous liquid releases may be made without exceeding 10CFR20 limits.
The most straight-forward determination of allocation f actor is Fa " 1/A where:
The number of liquid discharge pathways for which Fd>1
.n
=
and which are planned for simultaneous release.
However, this value for Fa may be unnecessarily restrictive in that all release pathways are apportioned the same fraction of the available dilution stream, regardless of the relative concentrations of each of the sources.
Since the radionuclide concentration of the two continuous sources is expected to be less than that of the batch release
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source, it is acceptable to allocate smaller portions of the
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dilution stream to the continuous releases and a larger
,j portion to the batch releases.
Therefore, Fa is defined as.a flexible quantity with a default value of 1/n.
Prior to initiating simultanecus
-release, a check will oe made to assure that the sum of the allocation f actors assigned to pathways for the simultaneous rt'.ss31 is 4 1.
4)
The calculated maximum permissible waste tank effluent flow rate, Fmax, is based on'the modified dilution factor, F n, and tne effective dilution flow rate, Pegg.
d The cooling lake into which the effluent is discharged is also the source of the dilution stream.
It is therefore necessary to take'into account the recirculation of previously emitted radionuclides should they be detected by sample analysis of the cooling' lake water.' This is accomplished by defining an effective dilution flow rate as Feff a Fm 1-I
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,J ODCM
.7 12-20-84 j
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Where:
The expected minimum dilution water flow rate.
Fm.
=
LCt Measured concentration of<nuclide i in the cooling
=
lake water-sample.
-MPCi Limiting concentration of radionuclide i from 10CFR20
=
Appendix B, Taole II, Column 2.
.For the purpose of setpoint calculations the expected minimum
. dilution flow rate is assigned a value based upon the type and number of pumps running into the circulating water piping.
Having established the values of F n and F rg, the d
3 calculated maximum permissiole waste tank flow race is
- /en by f ax i Far f
for fp << F gg m
p e
Where f is the expected effluent flow rater normally the p
fQ rated capacity of tne effluent pump.
Thus the pump flow rate (U) is set at or below fmax.
Even though the value of fmax may be larger than the actual effluent pump capacity, f,p it does represent the upper limit to the effluent flow rate, wnereby the requirement of 10CFR20 may still be met.
If Fd
<.1, the effluent pump flow rate may be assigned any value-t since the waste tank effluent concentration meets the limits of 10CFR20 without dilution and the release may be made without' regard to the-setpoints for other release pathways.
For those discharge pathways selected to be secured during the release under consideration, the pump flow rate should be set at as low a value as practicable to detect any inadvertent release.
A setpoint'for the dilution stream flow rate is not applicable since the minimum flow rate is administrative 1y set.
5)
The liquid radiation monitor setpoint may now be determined based.on the values of ' C, and fmax.
The monitor i
response is primarily tb gamma radiation, therefore, the actual setpoint is based on t.C The calculated monitor setpoint g.
concentration is dete? mined as follows:
c=A y
(uci/ml) l j
- k, ODCM 8
12-20-84 i
,m
.J Where:
A
=
Adjustment factor which will allow the setpoint to be establisned in a practical mhnner for convenience and to prevent spurious alarms.
f P
If A > 1, Calculate e and determine the maximum value for the actual monitor setpoint (uci/ml).
If A < 1, No release may be made.
If Fd < 1, no further dilution is required and the release may be made without regard to available dilution or to other releases made simultaneously.
However, it is necessary to establish a monitor setpoint which will provide alarm should
~~'S the release concentration inadvertently exceed 10CFR20
)
limits.
This can be accomplished by establishing the adjust-ment factor as follows:
A = 1/Fd 2.2 LIQUID EFFLUSNT CONCENTRATION - CCdPLIANCE WITH 10 CFA ;J Specification 3.11.1.1 requires that the radioactive material released in liquid effluents to unrestricted areas shall be li.nited :::
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 Aci/ml total activity.
To show compliance with this specification, concentrations of actual liquid effluents will be determined by performing an isotopic analysis. The liquid effluent monitors will provide sj assurance that the liquid concentration limits are not exceeded.
ODCM 9
12-20-84
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 f rom 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 oody 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 effluents will be determined using tne following methodology:
m d
A tL DT" (AiT CnF) i L
L=1
- where,
,-s k
,)
DT
= the cumulative dose commitment to the total body or any organ, T, from the liquid effluent for the total m
time period E A tc, in mrem.
L=1 tL
= -the length of the Lth time period over which Cin and FL are averaged for all liquid releases, in hours.
C n = the average concentration of radionuclide,
'i',-in i
undiluted liquid effluent flow during time period in scCi/ml tg, FL
= the near field average dilution factor for C n i
during any liquid effluent release where:
f FL=
(py g
.Wneres f = Liquid Radioactive Waste Flow
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ODCM 10 12-20-o4
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F = Discharge Structure Exit Flow, the sum of the release and dilution flow.
K = Applicable factor; the site dependent value for the mixing effect 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/ACi/ml.
See Tables A.4-1 through A.4-4.
AiT = 1.14E5 (Uw/pg + Up.BF ) DFi i
- where, DW
= Dilution factor from the near field area to the ja:aale water intaxe :or water conau.mption, for Wolf Creek Generating Station this factor is 1 (one).
BFi
= Bioaccumulation factor for radionuclide, 'i', in
(s fish, pCi/Kg per pCi/1, from Table A.1-1 from
)
Regulatory Guide 1.109 (Rev. 1)
(.v DFi
= Dose. Conversion f actor for radionuclide, 'i',
in mrem /pCi, from Tatte A.3-1 through A.3-4 from Regulatory Guide 1.109 (Rev. 1).
Uw
= Water consumption, in kg/yr.
Up.
= Fish consumption, in kg/yr.
l'.14E5 = units conversion factor = 10 pci/ACi X-10 ml/Kg 6
3 8760 nr/yr.
Tne dose calculations are based on the actual isotopic analysis
'of the radioactive liquid effluents, the radioactive _ liquid effluent. flow, and the dilution flow.
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'ODCM-
-11 20-84 j
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2.4 CALIBRATION OF LIQUID EFFLUENT MONITORS The four monitors associated with liquid releases are listed
'below
,e Monitor ID Description O-BM-RE-52 Steam Generator Blowdown Discharge Monitor O-LE-RE-59 Turbine Building Drain Monitor 0-HF-RE-45 Secondary Liquid Waste System Monitor 0-HB-RE-19 Liquid RLPeast? Oiset. r7e Monitor 2.4.1 Liquid effluent streams are monitored by an NaI(Tl) detector..The detector operates in a gross counting mode'and is gamma sensitive.
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N' 2.4.2
~ Calibration of the liquid monitors shall.be performed using three standard solutions of.Cs-137.
The solu-tions shall cover the appropriate range of the detector and have' concentrations of approximately 5 x 10-7 uCi/ce, 1 x.10-5.uCi/cc, and 1 x 10-3 uCi/cc.
The solutions shall be presented to the' detector and the meter reading in counts per minute shall be recorded.
A
-graph of counts-per minute versus concentration shall be produced from the data.
Immediately following monitor calibration the 9 uCi Cs-137 checksource shall be actuated.. The counts per minute produced by the check-source'snall be logged.
3.0 GASEOUS EFFLUENTS
- 3. l' GASEOUS EFFLUENT MONITOR SETPOINTS Technical Specification 3.3.3.11 requires-the gaseous effluent monitoring ' instrumentation channels shown in Table -3.3-13 to be operable with their, Alarm / Trip setpoints set to ensure that the limits of Specification 3.11.2.1 are not exceeded.
Specification
'3.ll.2.1-states that the dose rate due'to. radioactive materials
/~'T released in. gaseous effluents from the site _shall oe limited to less I
i than or equal to 500' mrem /yr.to the total body and less than or equal to.3000 mrem /yr to the. skin due to noble gases.
ODCM 12 12-20-84 j
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~ Gaseous effluent releases from the Unit Vent and Radwaste Building Vent are monitored continuously.
The Unit Vent is the release point for the fuel / auxiliary building, access control area, containment purge, and. condenser air discharge.
Th,e Radwaste Building Vent is the release point for Waste Gas Decay Tanks and the Radwaste Building Ventilation System.
Waste Gas Decay Tank releases and Containment Building releases are treated as batch releases.
Waste Gas Decay Tank releases are
- monitored by the Radwaste Building Exhaust Monitor.
Containment Building ' releases (purges) are monitored by the Containment Purge System monitors and the Plant Unit Vent Monitor.
Monitor identifications are as follows:
o
' Monitor ID Release Point Description 0-GT-RE-21 A and B Unit Vent (fuel / auxiliary building, access. control area, containment. purge, 7_s condenser air discharge)
\\s_jl 0-GH-RE-10 A and B Radwaste Building Vent (Radwaste building, waste gas decay tank discharge.
Acts to isolate Waste Gas-Decay Tank discharge)
-O-GT-RE-22&33 Containment Purge System Monitor-(acts tolisolape the purga;..
2.
effluent monitor) 0-GT-RE-31&32 Containment Atmosphere Monitor (acts to isolate purge; not an effluent monitor) w
. ~
The setpoint-for_ monitors may.1be determined either based on *otal body. dose.oriskin dose rate..The dose rate limits are for dose-
.ratesfat.the unrestricted area boundary.
The monitor setpoint is ithe' lesser of the total cody dose rate or skin dose rate. "
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ODCM' 13-12-20-84
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. TOTAL' BODY DOSE RATE SETPOINT CALCULATION 3.1.2
-The limit of the total body dose rate is 500 mrem /yr at the unrestric-ted area bouncary.
The monitor alarm / trip setpoint based on total body dose will be calculated as follows:
Stb i (SF x AF) xDtb x Rt (1) wnere:
l Stb The monitor alarm / trip setpoint based on the total
=
body dose rate.
Dtb Radiological Effluents Technical Specification
=
3.11.2.1 limit of 500 mrem /yr total body, conserva-tively interpreted as a continuous release over a one 7?ar peried.
Normally will be set to 0.85.
This number is chosen SF
=
since the gaseous monitors are set using Xe-133 energy level.
Xe-133 comprises 85% of total noble gaseous activity expected.
(See'FSAR Table 11.1-1).
./s If necessary the 0.85 can be further modified to 4
)
compensate for statistical fluctuations and errors of measurement.
Allocacion factor for each release so that simultaneous
'AF
=
releases can-be made without exceeding the Technical Specification Limit.
Normally AF is calculated as follows:
AF = RF TF Where:
RF = Release Flow rate of the release _ point under consideration TF = Total Flow rate of cll release points including release under consideration R't monitor response per' mrem /yr to the total cody,
=
_ determined according'to:
c f-K-Qi.)
' '\\-
(- (X/Q) i V
ODCM-14 12-20-84
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'Ib'
.wh'ere:
The monitor response to the gaseous effluent noble gas c
=
corresponding to grab sample radionuclide concentrations.
The highest calculated annuaT average atmospheric dispersion (x/Q)
=
(sec/mJ) at the restricted area boundary.
Ki The total body dose factor due to gamma emissions from
=
isotope 1 (mrem /yr per uCi/m3) from Table A.1-2.
Qi Rate of release of noble gas radionuclide 1 (uCi/sec)
=
(concentration of radionuclide i x release flow rate) 3.1.3 SKIN DOSE RATE CALCULATION Tne limit of'the skin dose rate is 3000 mrem /yr at the restricted area boundary.
The monitor alarm / trip setpoint is calculated as follows:
S 1
(SF x AF) xD xR (2) s s
s
/~~
where:
'S The monitor alarm / trip setpoint based on the skin dose
=.
s_
rate.
Radiological Effluents. Technical Specification 3.11.2.l' D
=
s; limit of 3000 mrem /yr to the skin of the body, conserva-tir Q in:2 rpre: d u
. : r- '. : m n '. a a. -
-.?
year period.
~
R Monitor response per mrem /yr to the skin of the body.
=
s C
. ( (X/Q)
'(Li + 1.1M ) Qi_ )
i where:
L" i
Skin dose factor due to beta emissions from isotope 1
=
3 (mrem /yr per uCi/m ) from Table A.1-2.
1.1 Conversion factor to mrem skin dose per mrad air' dose.
=
Mi Air dose factor due to gamma emissions from isotope 1
=
3
-(mrad /yr per uCi/m ) ~ f rom Table A.1 7,o f
N e _5vl-
'ODCM-15 12-20-84 Qu
7 i
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The factors SF, AF, c, (X/Q) and Qi are as defined in Section 3.1.2.
,e The _results of equations (1) and (2) are compared to determine the smaller setpoint.
The actual monitor setpoint is the lower of the two values.
A pre-release isotopic analysis is performed for batch releases from Waste. Gas Decay Tanks and Containment Building Purges to
' determine-the identity and quantity of the principal radionuclides.
The appropriate alarm / trip setpoint(s) are adjusted accordingly to ensure that the limits of Radiological Technical Specification 3.11.2.1 are not exceeded.
3.1.4 ALERT ALARM SETPOINT CALCULATIONS FSAR Table 11.5-4 states that the alert alarm for the Plant Unit Vent (0-GT-RE-21), Radwaste Building Exhaust Monitor (0-GT-RE-10 ),
Auxiliary Ventilation. Exhaust-Monitor (0-GL-RE-60) and Access
,s N_,-)
Control Area Ventilation Monitor (0-GK-RE-4) is set to alert
. operators to that average concentration.which if maintained for a
. full. year would result in the 10 CPR 50 Appendix I annual dose guidelines being reached.
Technical Specification 3.11.2.2 limits the annual dose due to noble gases to < 10 mrads for gamma radiation and < 20 mrads for beta radiation.
Technical Specification 3.1172.3 limits the annual dose.tx) a Member of the Public from Iodine-131,. Iodine-133, tritium and all radionuclides in particu-late form with _ half-lives greater than 8 days in gaseous.ef fluents to <-15 mrem to any organ.
These two Technical Specifications contain the annual dose limits due tx) gaseous releases found in 10 CFR 50 Appendix I.
3.1.4.1-
' NOBLE GAS ALERT ALARM SETPOINT CALCULATION Thealertsalarm setpoint is-the lesser-of Sr <
(SI: x _AF) x Dr x - R y.
(3)
Sp (SF x AF) xDgxRg (4)
Jx N
h J-
- ODCM 16
_12-20-84 j
__m
(D
.d j where:
Sy Monitor setpoint based on gamma radiation.
=
Dr=
TechnicalSpecification3.llI2.2limitof10 mrad /yr conservatively interpreted as a continuous release over a one year period.
y Monitor response per mrad /yr determined according to:
=
~
R c
R
=
y
( (X/Q) j Mi x Qi )
i where:
Gamma Air Dose Factor (mrad /yr per Mi
=
3 uCi/m ).
See Table A.1-2.
SA Monitor setpoint based on beta raaiation.
=
Dg Technical Specification 3.11.2.2 limit of
=
20 mrad /yr conservatively interpreted as a 7._.
./
\\
continuous release over a one year period.
U Rp Monitor response per mrad /yr determined
=
according to:
C l
(X/Q') $
(
Ni x Qi )
i where:
Ni Beta Air Dose Factor (mrad /yr per
=
uCi/m3).
See Table.A.1-2.
' Formulas 3 and 4 are used to calculate the alert alarm setpoints J
-for the gaseous monitors listed in Section 3.1.1 and for actual
-concentrations of radionuclides found-in the effluent-streams.
lA semi-fixed ^ alert alarm setpoint for the Plant Unit Vent monitor
( 0-GT-RC-21) and Radwaste Building Vent' monitor (0-GT-RE-10) is
- calculated using the.following:
(10 mrad /yr) (.85) (AF) jx Setpoint;(uci/cc) g
-(5)
=
l(
)?
( (X/Q)
Pi x Mi x Q) g v
ODCM 17 12-20-84 u
.. _ _,. ~ - _.. _ _
~
-r i
f
)
uJ where:
.Pi Fractional value of isotope expected, C /C e
=
i T
where:
Ci Concentration in uCi/cc of isotope.
=
CT Total Gaseous Activity from FSAR
=
Table 11.1-1.
AF Eitner Unit Vent Flow or Radwaste Building
=
-Vent Flow divided oy the comoined flow of the Unit Vent and Radwaste Building Vent.
.Q Vent flow rate in cc/sec.
=
Isotopes used and Pi values are as follows:
ISOTOPE Pi
'- [)s- ~
'Kr-87
.010 Kr-85M
.018
(
V Kr-88
.033 Xe-133m
.017 Xe-133
.851 Xe-135
.051 Should tnis semi-fixed alert alarm causeia continuous alarm condition, then actual setpoints will be calculated.
-3.1.4.2 PARTICULATE AND IODINE ALARM SETPOINTS 1
Setpoints for the gaseous effluent particulate and iodine channels are set'using Cs-137 MPC for~particulates and.I-131 MPC for iodines.-
TheJfollowing is the calculation used:-
L (MPCi) (AF) (SF)
Setpoint _(uCi/cc)
=
(Q)
.(X/Q) e l k.
i v
ODCM 18 12-20-84 1:
s
,e-4 e~w
-,,,--e.--,g4
--mm. -, -
,-.4s,w o.
ee---,vo-
---w---n...o-ee-
.,oe
~m,---e
,.w,
-m
-~~s
-se,-
w em.-e
~s
\\)
where:
MPC -=
5 x 10-10 uCi/cc for Cs-137 i
1 x 10-10 uCi/cc for I-131.'
=
'AF as defined previously
=
SF
=
.0625 for I-131 *
.9375 for Cs-137 *
=
- derived from ratio of isotope activity (either I-131 or Cs-137) to sum of activity of Cs-137 and I-131 found in FSAR Table 11.1-1 for reactor
~
Coolant.
3
' Vent flow in M /sec Q
=
This will provide the Hi alarm setpoint.
The alert alarm setpoint is 10% of the Hi alarm setpoint.
- r"N_
3.2 GASEOUS EFFLUENT CONCENTRATION / DOSE RATE
.t
)
'\\~ /
- 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 De 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 ti.
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.
LBased on the methodology of NUREG-0133; e
a.
Release rate limit for noble gases:
]fKi (X/Q) 01-<500 mrem /yr for the total body,'
and
/v'~'h f.(Li + 1.1 M ) (X/Q)- Qi <3000 mrem /yr for the skin.
i ODCM 19 12-20-84
1 OU where:
i Total body dose factor due to gamma emissions K-
=
for each identified nob,le gas radionuclide, in mrem /yr per jcci/m, from Table A.1-2.
3 (X/Q) 2.2 E-06 sec/m, The highest calculated annual
=
average relative concentration at the restricted area boundary in the North Sector.
Release rate of radionuclide i from vent, in Qi
=
suci/sec.
Li Skin dose factor due to beta emissions for
=
each identified noble gas radionuclide, in 3
mrem /yr per uCi/m, from Table A.1-2.
s Air dose factor due to gamma emissions for Mi
=
each identified noble gas radionuclide, in mrad /yr peracci/m3 from Table A.1-2.
II.1
= Conversion constant of air dose to skin dose.
f~'N k._,
b.
Release rate limit for all radionuclides and radio-active materials in particulate form and radionuclides other than noble gases:
T (P(i)'IN (X/Q) - Qi) <1500 mrem /yr to any organ.
i
~
where:
Qi The release rate'of radionuclides, i, in
=
gaseous effluent from all vent releases, in-jACi/sec.
l P(i)IN The dose parameter for radionuclides
=
other than noble gases for the inhalation L
. pathway, in mrem /yr perjACi/m3.- See Table A.5-1.
X/Q. =
2.2 E-06 sec/m3 _ (the highest annual' average).
The highest calculated relative concentration for estimating the dose to an individual at the unrestricted area boundary in the.
L N-sector.
/~N.
- :(
)
!w ODCM 20 12-20-84
/~N
~(N-)
All radionuclides are assumed to be released in elemental form.
The specification is applicaole to the location (unrestricted area boundary or beyond), characterized by the value of X/Q which results in the maximum total body or skin dose commitment.
The. factors Ki, L, and Mi relate the radionuclide airborne i
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 uCi-1 and listed in Table A.1-2.
The following equation for P(i)IN was taken from NUREG 0133:
P(i)IN (Inhalation) ;
P(i)IN = K' (BR) DFAi (mrem /yr persnCi/m3) where:
K'
= a constant of unit conversion, 106 pCi/ sac 4 BR
= the breathing rate of the child age group
...s 3
in m /yr DFAi= the maximum organ inhalation dose factor for the child age group for the ith radionuclide, in mrem /pCi.
The total body is considered as an organ in the selection of.DFA.
1 The age group considered is the. child group.
The child's breathing rate is taken as 3700,3 /yr from Table E-5 of Regulatory Guide 1.109.
The inhalation dose factors for the child, DFAi are presented in Table E-9 of Regulatory Guide 1.109, in units of mrem /pCi.
Resolution of the units yields:
Pi (Inhalation) = 3.7 X 109 DFAi js
(
)
, L/
ODCM 21 12-20-84
- y.
- - ~--
=. -..-
v d
7~'(
i (V
1 The Pi value for tritium is:
Pi (Inhalation) = 3.7 x 109 DFAi 3.3 GASEOUS EFFLUENT DOSES
- Cor.pliance with 10 CFR 50 Appendix I 3.3.1 NOBLE GASES
-Specification 3.11.2.2 requires that the air dose due to noble Jgases 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 i 10 mrad for beta radiation; p
b.
During any calendar year, to i 10 mrad for gamma radiation and i 20 mrad for beta radiation.
~
To show compliance with this specification, the dose calculations for the actual releases of radioactive noble gases in gaseous jr s)
'ef.tluent.will De consistent with the methodology provided in (s_ /
Rag.: Guide 1.109, Rev.
1.
The following dose calculations will be-performed:
a.
During any calendar quarter; For' gamma radiation; 2E g,y Mi [(X g)
D = 3.17 E-8
/
Qi] 1 5 mrad.
For' beta radiation; 3.17E-8fhy Ni [(X/Q)
D=
Qil -1 10 mrad..
b.:
During any calendar year:
For gammaLradiation:
E D = 3.17 E-8 Mi [(X/Q) g,y Qi] 1 10 mrad.
' For beta radiation:
2E D = 3.17 E-8 Ni [(X g) fQi][120 mrad
/
g,y
[
22 12-20-84 4
,i-+
w
.,y
-,-w-,
4-
-w,
,---3-,
,, emw--
--wy--
-n-,_,,-
,,,.,--w,,.+,,,-,-.w---
-,c,,
.,,,-,.,-w--,--,---.-,.w..,-
e W
.(
Y 1.)
where:
^
3.17 E-8 = The inverse of the number of seconds in a year.
Mi
= The air dose factor dd$ to gamma emissions for each identified noble gas radionuclide, in arad/yr per/cci/m3 from Table A.1-2 (Reg. Guide 1.109, Table B-1, Col. 4)
-N-
= The air dose factor due to beta emissions for i
each identified noble gas radionuclide, in mrad / year peracci/m3 from Table A.1-2 (Reg.
Guide 1.109, Table B-1, Column 2).
3 X/Q
= 2.2 E-6 sec/m.
The highest calculated annual average relative concentration for any area at the unrestricted area boundary.
Qi
= Tne. release of noble gas radionuclides,
'i', in gaseous effluents, inAcCi.
Releases shall be. cumulative over the calendar quarter or year as appropriate.
. /-m -
An average monthly air dose schedule should be setup to ensure section 3.~11.2.2 of.dolf Creek Technical Specifications are not exceeded.
The average monthly air dose should be as follows:
a.
For gamma radiation <.l.6 mrad /mo.
'Forbeta.radiationjf3.3 mrad /mo.
tIf t'ne monenly average: air dose for: (a) is exceeded, it should be. noted that if the release -is continued at the same - (ort higher)
. frequencies or activities, Section 3.11.2.2 A of Wolf Creek
- Technical Specifications will be exceeded.
b.
For gamma radiation < 0.8 mrad /mo.
For beta radiation 3 1.6 mrad /mo.
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 anonthly 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
'(e.g. - delay the release of: a Waste Gas Decay Tank) of the release.
rh I'\\
[
~
L l
ODCM-23 12-20-84
g(3 3.3.2 RADIOIODINES, PARTICULATES, AND OTHER RADIONUCLIDES l
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 17.5 mremto any organ; and b.
During any calendar year to f 15 mremto any organ.
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:
1 [i1 p
Ri (WQL)] 1 7.5 mrem a.
D (mrem) = 3.17E-8 4 [i p
i Ri (WQi)] 1 15 mrem b.
D (mrem) = 3.17E-8 where:
3.17E-8 = The inverse of the number of seconds in a year.
[~~st
(_,/
Qi. = The release of radioiodines, radioactive materials in particulate form and radionuclides other than noble gases in gaseous effluents, 'i',
in Ci.. Releases-shall be cumulative over the calendar quarter or year as appropriate.
The Qi value shall be determined as the product of the flow rate through the release point and grab samples of the effluent analyzed in accordance with Radiological. Effluent Technical Specifica-tion 3.11.2.1.
W
= The annual average dispersion parameter for estimating the dose to an individual at the controlling location.
(X/Qf), 2.2 x 10-6 sec/m3 for the inhalation, W =-
. 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 joCi/m3 See Table A.5-2 through Table A.5-5.
i'
-s g>
ODCM 24 12-20-84
u
}
l-
/O 4
\\'~') ~
where:
s Inhalation Pathway Factor, R [X/Q]
R [X/Ql = K' (BR) (DFA ),
(mrem /yr per,uci/m3) g where:
K'
= a constant of unit conversion,10 pCi/jcCi.
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
,\\
)
(DFA )a = The maximum organ inhalation dose
' (d 1
factor 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 (DFA1)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.
Ground Plane Pathway Factor, R [D/Q]
~
= R [D/Q] = K'K" (SP) DFG
[(1-e
)/)L i} (m
. mrem /yr pers(Ci/sec) 2 where:
K'
= A constant of unit conversion, 10 -pCi/saCi.
6 K"
= A constant of unit conversion, 8760 hr/ year.
1
= The decay constant for the i th radionuclide, sec t
= The exposure time', 4.73 E8 see (15 years).
r~'s:
Iv).'
- ODCM 25 12-20-84 Mw'--
e,-c,'
-+
,*r.e, w-er---
p-----vr,c,--..,yc-w.r--yw-.-s,--..r.
.-,y e-+e
,-twe,gn e'-Try*=y twy-esww'-t--c y-w r e w e -1 v e+ - tw s-w e -*
-s DFGi
= The ground plane dose conversion factor for the 2
ith radionuclide (mrem /hr per pCi/m ), 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]
A R [D/Q] = K' (SF( ap)) Fm(r) (DFL ) a (
/Yp) (e t
ig i
2 (m. mrem /yr perjuCi/sec)
K'
= A constant of unit conversion, 106 pCi/x,Ci.
Op
= The cow's consumption rate, in Kg/ day (wet weight), 50 kg/ day.
(Reg. Guide 1.109, Table E-3).
Uap
= The receptor's milk consumption rate for age
/
(a), in liters /yr.
(Reg. Guide 1.109, Table i
E-5)
Infant 330 1/yr
=
Child 330 1/yr
=
400 1/yr Teen
=
310 1/yr Adult
=
Y
= The agricultural productivity by unit area of p
2 2
pasture feed grass, in kg/m, 0.7 kg/m. (Reg.
Guide 1.109, Table E-15)
F
= The stable element transfer coefficients, in m
days / liter, see Table A.3-5.
(Reg. Guide 1.109, Table E-1) r r
= Fraction of deposited activity retained on cow's feed grass, r=1 for radioiodine and r= 0.2 for particulates.
(Reg. Guide 1.109, Table E-15).
(DFL ), = The maxinum organ. ingestion dose f actor I
i 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, l
Table E-11, E-12, E-13, and E-14)
/-~,
ODCM 26 12-20-84 l
f G
Ai
= The. deca constant for the ith radionuclide, in sec -
- tw
= The decay constant for removal of activity on leaf and plant surfaces 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-lS).
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/g),
i Rf[X/Q] = K'K"' FmOF ap (DFL )a (0.75 (0.5/H)]
U i
1 (mrem /yr per zCi/m3) s
- () -
where:
K"'
= a constant of unit conversion, 103 gm/Kg.
3 H
= Absolute humidity of the atmosphere,.8 gm/m,
0.75
= The fraction of total feed that is water.
- 0.5-
= The ratio of the specific activity of the feed grass water to the atmospheric water. (NUREG-
[
0133) t
' Grass-Cow-Meat F,thway Factor, Ri[D/Q]
(QFIU.ap) ) Pg ( r) (DFLi) a (l/Yp)
~
i[D/Q]
R
=
t.
e Ai+ ),
(m2. mrem /yr per uCi/sec) f~%
)
v(
ODCM.
27 12-20-84
/
a,
where:
Fg
= 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 Teen
= 65 Adult
= 110 tg
= The transport time from pasture to receptor, in sec., 1.73 E6 (20 days) (Reg Guide 1.109, Table E-15).
The concentration of tritium in meat is based on its airborne concentration rather than the deposition.
Therefore, the RM is based on (X/Q) :
i
[~~'s R"[X/Q] = K'K"' Fg Og Uap (DFL )a [0.75(0.5/H)]
i
\\--
3 (mrem /yr perjAC1/m )
where:
All terms defined above.
Veget'ation Pathway Factor, Ri[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 j,3 )] (DFLi) a [ (Uk) (f ) (e i L) +(U$) (f ) (e, ith))
~
L g
(m2. mrem /yr per/4Ci/sec) where:
A constant of unit' conversion, 106 pCi/suCi.
K'
=
. fN A
~0DCM 28 12-20-84
. - ~ ~..
/h Uk
=
The consumption rate of fresh leafy
(,,/
vegetation by the receptor in age group (a),
in kg/yr. (Reg Guide 1.109, Taole E-5).
Infant 0
kg/yr
=
Child 26 kg/yr
=
42 kg/yr Teen
=
Adult 64 kg/yr
=
6 U*
The consumption rate of stored
=
vegetation by the receptor in age group (a),
Kg/yr.
(Reg Guide 1.109, Table E-5).
Infant 0 kg/yr
=
Child 520 kg/yr
=
Teen 630 kg/yr
=
Adult 520 kg/yr.
=
ft The fraction of the annual intake of fresh
=
leafy vegetation grown locally.
(default = 1.0)
f The fraction of the annual intake of stored
=
g vegetation grown locally. (default = 0.76)
- p. -
Ll
)
tn
=
The average time between harvest of leafy
\\s_/
vegetation and its consumption, in seconds, 8.6
- E4 secs (1 day). Reg. Guide 1.109).
th Tne average time betWeen harvest of stored o
=
vegetation and its consumption, in seconds, 5.18 E6 secs (60 days)
(Reg. Guide 1.109, Table E-15).
The vegetation area density, 2.0 kg/m2, Yv
=
(Reg. Guide 1.109, Table E-15).
All other factors previously defined.
The concentration of tritium in vegetation is based on the air-borne concentration rather than the deposition.
Therefore, the R
is based on - (X/Q) :
R [X/Q] = K' K"'
[UhfL + U$ f ]
(DFL ) a [0.75 (0.5/H)]
i g
(mrem /yr per/tCi/m3) where:
All terms defined previously._LAll values indicated are 2-'s default values from Reg. Guide _1.109, Rev. 1.
t ODCM-29 12-20-84 u
~
/
\\
_I
)
hs /
An average monthly dose schedule should be setup to ensure Section 3.11.2.3 of Wolf Creek Technical Specifications are not exceeded.
The average monthly dose due to radiciodines, particu-lates, and other radionuclides which are included in this section should be as follows:
.a. < 2.5 mrem /mo.
If the ' monthly average dose for (a) is exceeded, it should be noted that if the release is continued at the same (or higher)
' frequencies or activities the quarterly limit of Specification 3.11.2.3 A will be exceeded.
- b. < l.25 mrem /mo.
If-the monthly average dose for (b) is exceeded, it soould be noted that if the release is continued at the same (or higher) frequencies or activities the yearly limit of Specification 3.11.2.3 8 will be exceeded.
If any of the above monthly doses are exceeded, evaluation of tne causes should be performed and steps taken to reduce the activity or frequency of the-Release.
,-_s 3.4 CALIBRATION OF GASEOUS EFFLUENT MONITORS The.following monitors are asociated with gaseous releases Monitor.ID Monitor. Description Monitor Type O-GT-RE-21A Plant-Unit Vent Particulate, Iodine O-GH-RE-10A Radwast'e Building Effluent Particulate, Iodine O-GT-RE-218 Plant Unit Vent Wide Range Gas y
iO-GH-RE-10B Radwaste Building Effluent Wide Range Gas
'O-GT-RE-22 & 33
-Containment. Purge Exhaust Particulate, Iodine, Gas-O-GT-RE-31 &L32 Containment Atmosphere Particulate, Iodine, Gas f
.Q
-ODCM 30 12-20-84 J1
.A I
S-3.4.1 PARTICULATE DETECTOR CALIBRATION V
3.4.1.1 l Beta particulate is monitored by a 50 mm diamter by 0.25 mm thick plastic scintillator optically coupled to a 50 mm diameter photomultiplier tube.
This detector shall be calibrated over its range of energy and rate capabilities.
13.4.1.2 For energy range calibration four sources shall be used.
Each source consists of a 35 mm diameter filter paper impregnated with a beta emitting radionuclide.
The radionuclides used should be Tc-99, Cs-137, Cl-36, and Rh-106.
Each source shall be positioned in the filter paper retaining ring and counted separately.
The count rates for each radionuclide source shall be recorded and_the data plotted on a graph of cpm /uCi versus average beta-energy.
This curve represents the detectors response characteristics over the range of beta energies observed.
The efficiency for setpoint calculations shall be based on the efficiency of the detector for Cs-137.
3.4.1.3' The detector shall be calibrated for its rate capabilities f/Nc using a filter paper impregnated with stand activities k"" )
of Cs-137.
Increasing amounts of a standard Cs-137 solution shall be impregnated on a filter paper.
The i
counts _ per minute for each Cs-137 standard shall be recorded and the data plotted on a graph of counts per minute versus activity.
At least three sources covering approximately 1/4,- 1/2, and 3/4 of full scale shall be
'enecked.
Immediately following monitor calibration the O.05 uCi Cl-36 checksource shall be actuated.
The counts per minute produced by the checksource shall be logged.
3.4.2 IODINE DETECTOR CALIBRATION 3.4.2.1 Iodine gas is monitored by absorbing the gas on a charcoal filter element.
The charcoal filter is viewed by'an NaI(TI): integral line gamma scintillator assembly.
t 3.4.2.2 Because of its short half life and.tne difficulty in handling gaseous iodine, barium sources shall be used for calibration.
The photo peaks of' interest are as follows:
+
.[ g);
A.
Ba-133: 356 kev gamma is.0.69 efficient / disintegration qj B.
I-131: 364 kev ' gamma is 0.82 ef ficient/ disintegration ODCM 31 12-20-84
m
=
l Y
O Therefore, each iodine disintegration will produce 0.82/0.69 x barium disintegrations.
Assuming that the
(
detector efficiency for 356 Kev is the same as for the 1364 kev, the sensitivity for I-131 equals 1.19 x Ba-133 l
.(counts / min)/uci.
The standa,rd sources shall be construc-l ted by impregnating a standard Ba-133 solution into the charcoal filter element.
The geometry shall simulate the iodine retention on the first surface of the charcoal.
Sources shall be prepared to cover approximately 1/4, 1/2, and 3/4 of full scale.
The barium counts per minute for each standard shall be adjusted to iodine counts per minute as described above.
The adjusted counts per minute shall be plotted on a graph of counts per minute versus activity.
Immediately following
~
calibration the checksource shall be actuated.
The e
counts per minute proudced by the Ba-133 checkscurce
(
shall De logged.
3.4~3 GAS DETECTOR CALI3 RATION I
l 3.413.1 The gas detectors associated with monitors 0-GT-RE-22&33, 0-GT-RE-31&32.and the low-range detectors of monitors O-GT-RE-21B and 0-GH-RE-10B are a plastic scintillator identical to the particulate detector.
The mid-range and high-range detectors of monitors O-GT-RE-21B and 0-GH-RE-10E are cadmium telluride, solid state sensors.
~
3.4.3.2-
.-Sources-for all gas detectors.shall be produced by evacuating the sample chamber with a vacuum pump..The sample chamberithen shall be' backfilled to the desired 1
pressure with a source of standard Xe-133.
The source
)
s is then counted and the counts per minute recorded.
A graph of counts per minute versus concentration _shall be j
~'
^J
. produced from the data.
Sources shall.be prepared to
_ cover approximately 1/4, 1/2, and 3/4 of full-scale for.
the detectorsLassociated with monitors 0-GT-RE-22&33, 0-GT-RE-31&32:and'tne low-range' detectors of monitors
.O-GT-RE-21B and 0-GH-RE-10B.
Sources!shall be prepared for the:mid/high range detector to. cover two. points on
' the mid-range' scale.
For ALARA purposes, -response 'for
_l the high-range scale.shall be extrapolated using the.
data _from the mid-range. calibration.
Immediately
^
following calibration of a gas detector, the checksource shall be actuated.
The counts per' minute produced by.
the checksource shall be logged.
c'y s_ -
ODCM 32-12-20,
~
,m
)
. 4/
4.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
. Table 4.1 gives specific Radiological Environmental sampling I
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 lists distances and directions from the site to the sampling locations.
4.1 INTERLABORATORY COMPARISON PROGRAM Analysis of KG&E Radiological Environmental samples is presently performed' by Teledyne Isotopes, which takes part in the EPA Labor,atory Intercomparison Program.
Results of intercomparisons are then provided to KG&E in revisions to Teledyne's Quality Control Manual (IWL-0032-361) which is maintained at KG&E corporate offices.
i u
. \\
n I
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l t
't 9
4
- [%
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ODCM 33 12-20-84
- - a
.=
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/
- t.
C o
N TABLE 4.1 Sheet 1 of 3 i.
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 1
l Number of. Samples.
Exposure Pathway and Sampling.and Type and Frequency.
l-
' and/or Sample
. Sample Locations Collection Frequency of Analysis t
L
- 1. AIRBORNE Continuous operation Radioiodine canister.
Radioiodine and Five locations,..
-of sampler with sample Analyze weekly for i-Particulates station numbers 2, 3, 31, 37 and 40.
collection as required I-131.
(control) Figure 4.1.
by dust loading but at i :.
least weekly.
Analyze for gross beta radioactivity not less 4
i:
than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following i-filter change.
Perform u,
gamma isotopic analysis i-l on each sample when gross i
beta activity is greater than 10'. times the yearly mean of control samples.
Perform gamma isotopic analysis on composite (by location) once per j.
quarter.
l-
- 2. DIRECT RADIATION 38 TLD' locations within Quarterly at each Gamma dose quarterly.
5-mile radius of site location j
(station numbers 1-38 on. Figure 4.1) and U
two offsite locations 4
(stations 39 and 40);
o two TLD dosimeters at i
each location.
s
~
g y yy-v-
-w--
+ y
,-y
,ww e
,.yw is w
t 5--'&
-9N mM9
wW
- S7-T w
T "m
~ - " - '
'- +
m p
Og TABLE 4.1 Sheet 2 of 3 2
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Number of Samples Exp.ure Pathway and Sampling and Type and Frequency a 1/or Sample Sample Locations Collection Frequency of Analysis i.
- 3. DATER 80RNE
.. Surface One upstream location Monthly grab sample Monthly gamma isotopic i
near the John Redmond analysis.
Quarterly i
Reservoir spillway, one trituim analysis of sample from Wolf Creek composite sample.
I Cooling Lake, i
- b. Ground Three locations at Quarterly Quarterly gamma iso-l l
C-10, C-49, D-65, topic and trituim w
one control location analysis.
at B-12 (see Figure 4.2).
s I
l
... 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.
l d.
Sediment from One sample from Neosho Semiannually Semiannual gamma iso-Shoreline River below Wolf topic analysis.
l Creek confluence.
I
\\
l i
I
. U 4
wo I
i l
- C6mposite sampling shall ne performed by collecting an aliquot at intervals not exceeoing l
2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
1 l
s
-'i
]
1 3
5
. TABLE 4.1 Sheet 3 of 3 I
x RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Number of Samples Exposure Pathway and Sampling and Type and Frequency andfar Sample Sample Locations Collection Frequency of Analysis 4.
ING8STION Samples from B-8, F-1, Semimonthly when Gamma isotopic and Q-5, and a control animals are on pasture; I-131 analyais of each
- a. Milk sample f rom S-3 monthly at other times. sample.
(Hartford); alternate locations are P-2, a
and C-ll (see i
Figure 4.3).
- b. Fish One sample from Wolf Semiannually Gamma isotopic analysis l
Creek Cooling Reser-on edible portions l
1 jp voir, similar sample 4
from John'Redmond Reservoir spillway
(
as control i
- c. Food Products Broad leaf vegetation Monthly during harvest. Gamma isotopic analysis samples locations Q-1 on edible portions.
[
and A-1 on Figure 4.3; control.at S-4 (Hartford); alternate 1
samples from locations 4
R-1 and Q-2 as available.
N
<l Iuo
rw 3
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/
'o.
."8 TABLE 4.2
^3
. SAMPLING LOCATIOlf NUMBERS,-DISTANCES (miles) AND DIRECTIONS
'TLD and Air Particulate Location Distance /
Location Distance /
Location Distance /
Location Distance Number Direction Number Direction Number Direction Number Direct ion a
1 1.4/N 11 1.6/E 21 3.8/S 31 3.0/WNW t
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 j
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/NU 9
2.0/ ENS 19 4.0/SSE 29 2.6/SSW 39 13.0/N
}.g 10 2.4/ENE 20 3.3/S
'.n l 2.2/W 40 15.0/Wtu sa Groundwater j
B-12
'2.2/NE C-10 2.8/W C-49 2.9/SW D-65 3.9/S
)
M_ ilk and Food Products j'
A-1 1.4/N F-1 1.6/ESE Q-1 1.3/NW R-1 2.2/NNW l
B-8 4.9/NNE G-1 1.4/SE Q-2 1.4/NW S-3 15.0/UNW j
C-11 5.2/NE P-2 2.9/WNW 0-5 3.6/NW S-4 15.0/WNW E.
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Th 5.0 40 CFR 190 DOSE EVALUATION
~!This section demonstrates compliance with Surveillance Requirements 4.11.4.1 and 4.11.4.2 of the Wolf Creek' Generating Station Technical Specifications.
Specifically, the annual (calendar year) dose or dose commitment to any Member of the Public due to release of radioactivity and to radiation from uranium fuel cycle sources shall be limited-to less than or equal to 25 mrems to the whole body or any organ, except the thyroid, which shall be limited to less..than or equal to 75 mrems.
Dose evaluations to demonstrate compliance with Technical Specifica-tion 3.11.4 only need to be performed if the release of radioactive materials in liquid or gaseous effluents exceed twice the limits of Technical Specification 3.ll.l.2a, 3.11.1.2b, 3.11.2.2a, 3.11.2.2b, 3.ll.2.3a, or 3.11.2.3b.
Otherwise, no further evalua-tion is required.-
For the evaluation of doses to an individual from liquid releases, the method described in Section 2.0 will be used.
For the evalua-tion of doses to an individual from gaseous releases, the methods
~ described in Section 3.0 will be used.
p-s k,
Cumulative dose. contributions from direct radiation from the reactor unit and - from radwaste storage tanks shall be determined
. utilizing the results of routine plant perimeter surveys, TLD data or a. combination. of.both, when necessary.
L 1 ~..,11
. ~
f
- ODCM 38 12-20-84
d i
I 4
+
APPENDIX A Dose Conversion Factor Tables l
l t-ODCM A-1 12-20-84
. =..
TABLE A.1-l*
b BIOACCUMULATION FACTORS TO BE USED IN
(
THE ABSENCS OF SITE-SPECIFIC DATA (pCi/kg per pCi/ liter)
FRESHWATER ELEMENT
.?
FISH H
9.0E-01 C
4.6E 03 Na 1.0E 02 P
1.0E 05 Cr 2.0E 02 Mn 4.0E 02 Fe 1.0E 02 Co 5.0E 01 Ni 1.0E 02 Cu 5.0E 01 2n 2.0E 03 Br 4.2E 02 Rb' 2.0E 03 Sr 3.0E 01 Y
2.5E 01
.Zr 3.3E 00 Nb 3.0E 04 Mo 1.0E 01 Tc 1.5E 01-s/
Ru 1.0E 01 Rh 1.0E 01 Te 4.0E 02 I-1.5E 01~
Cs 2.0E 03 Ba 4.0E 00 La 2.5E 01 Ce 1.0E 00
~
Pr.
2.5E 01 Nd=
2.5E 01
'W l.2E 03 Np 1.0E 01 L
- Taken from Regulatory Guide 1.109 (Rev. 1).
m)_
L ODCM A-2
___...___,2...
_........_..--._.-_._.___.-._._..,_,,._,._--..__......_._._.2
e
']:
JQ
- (
.j 4
TABLE A.1-2 DOSE FAClORS FOR NOBLE GASES AND DAUGrn?RS*
'Ibtal Body Gamma Air-Beta Air-Doce Factor Skin Dose Factor Dcrae Factor Dose Factor i:
Ki Li Mi Ni Radionuclide (mreWyr per Adi/m3)
~ (mreWyr per - Ci/m3)
(mrad /yr per >4C1/m3)
(mrad /yr per A.Ci/m )
3 Kr-83m 7.56E-02*
- 1.93E+01 2.88E+02 Kr-85m 1.17E+03 1.46Et03 1.23E+03 1.97E+03 i
Kr-85 1.61E+01 1.34Et03 1.72E+01 1.95E+03 1
l 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 1
i Kr-89 1.66E+04.
1.01E+04 1.73E+04 1.06E+04 j.
s Ii 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 1
l Xe-133m 2.51E+02 9.94E+02 3.27E+02 1.48E+03
{
Xe-133-2.94E+02 3.06Et02 3.53E+02 1.05E+03 4
j Xe-135m 3.12E+03 7.11E+02 3.36E+03 7.39E+02 3
3 Xe-135 1.81E+03 1.868+03 1.92E+03 2.46E+03 Xe-137 1.42E+03 1.22E+04 1.51E+03 1.27 E+04 i
l
{
Xe-138 8.83E+03 4.13E+03 11.lE+03 4.75E+03 Ar-41 8.84E+03 2.69E+03 9 10E+03 3.28E'03 g
i j
- Based on Regulatory Guide 1.109 (Rev.1).
- 7.56E-02 = 7.56 x 10 -2 l
L.
~
3 T.'21.E A.2-l*
N p INHALATION DOSE FACIORS EUR ADULTS (MREM PER PCI INHALED)
NUCLIDE' BONE LIVER T BODY
'IWYROID KIDNEY LUNG GI-LLI H
.'3 NO DATA 1.58E-07 1.58E-07 1.58E-Q7 1.58E-07 1.58E-07 1.58E-07
, C ' 14 -
2.27E-06 4.26E-07 4.26E-07 4.2f,E-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 h
P. ' 32 -
1.65E-04 9.64E-06 6.26E-06 NO DATA NO DATA NO DATA 1.08E-05 CR 51:
NO DATA-NO DATA 1.25E-08 7.44E-09 2.85E-09 1.80E-06 4.15E-07 m 54
'NO DATA 4.95E-06 7.87E-07 NO DATA 1.23E-06 1.75E-04 9.67E-06
- m 56 NO 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
'l.47E-06 3.47E-06 1.325-06 NO DATA NO DA".3 1.27E-01 2.35E-05 1
.00 58 NO DATA 1.98E-07 2.59E-07 NO DATA NO DATA 1.16E-04 1.33E 00 60 NO DATA 1.44E-06 1.85E-06 NO DATA NO DATA 7.46E-04 3.56E-05
.NI 63 15.40E-05 3.93E-06 1.81E-06 NO DATA NO DATA 2.23E-05 1.67E-06
.NI 65-1.92E-10 2.62E-ll-1.14E-ll NO DATA NO DATA 7.00E-07 1.54E-06
- CU 64 NO DATA 1.83E-10 7.69E-ll NO DATA 5.78E-10 8.48E-07 6.12E-06
' ~
- 2N 65-4.05E-06 1.29E-05 5.82E-06 NO DATA 8.62E-06' -1.08E-04 6.68E y 7
- ZN-69;
~4.23E-12 8.14E-12 5.65E-13 NO DATA 5.27E-12 1.15E 2.04E-09' 1
-BR 83 LNO DATAJ NO' DATA 3.01E-08 NO DATA NO DATA NO DATA 2.90E-08' BR 84
'NO DATA-NO DATA 3.91E-08 NO DATA NO DATA NO DATA'
'2.05E-13 BR 85
'NO DATA NO DATA- ~1.60E-09 NO DATA NO DATA NO DATA-LT E-24
-RB 86~
N0' DATA' l.69E-05' 7.37E-06 NO DATA.
NO DATA NO DATA
2.0 8E-06
2 RB' 88 -'
!NO DATA
^4.84E 2.41E-08 NO DATA NO DATA NO DATA-4.18E-19:
Re 89 NO DATA 3.20E-08 2.12E NO DATA ~
NO DATA NO DATA
'1.16E-21 J SR 89
.3.80E-05 NO DATA-1.09E-06 NO DATA
'NO DATA-
- 1.75 E-04 4.37E-05~
- SR 90 ;
1.24E NO DATA 7.62E-04 N3 DATA NO DATA 1.20E-03 9.02E-05'
[
~SR 914 7.74E-09 -NO DATA
-3.13E-10' NO DATA NO DATA
'4.56E-06 2.39E-05
'SR 92-8.43E-10 NO DATA
'3.64E-ll NO DATA NO DATA 2.06E-06 5.38E-06'
.Y;1907 s2.61E-07 'NO DATA, 7.01E-09 NO DATA' NO DATA-2.12E-05 6.32E n
.f Y -91M.
3.26E-11 NO DATA-1.27E-12.
NO DATA
-NO DATA 2.40E-07 1.66E-10,
!' k '
Y. 91' 5.79E D TATA 1.55E-06 NO DATA NO DATA 2.13E-04 4.d I-95
' L Y ~. 92 41~.29E-09 NO DATA:
3.77E-11 NO DATA NO DATA ~
^1.96E-06 9.19E-06
- Taken fran Regulatory Guide 1.109.(Rev.1)-
A '
0 "e
a.
_,., -. _.. _. _..... _,... -, _. _.....,. _.,.... ~. -.. -.
TABLE A.2-1 (cont'd)
INHALATIQ4 DOSE FACIORS EOR ADULTS (MREM PER PCI INHALED) 4 -
NUCLIDE BONE LIVER T BODY
'IEYROID KIDNEY UJNG GI-LLI Y 93 1.18E-08 NO DATA 3.26E-10 NO DATA NO DATA 6.06E-06 5.27E-05 ZR 95 1.34E-05 4.30E-06 2.91E-06 NO DATA
6.77E-06 2.21E-04 1.88E-05 ZR 97 1.21E-08 2.45E-09 1.13E-09 NO DATA 3.71E-09 9.84E-06 6.54E-05 i
.NB 95' 1.76E-06 9.77E-07 5.26E-07 NO DATA 9.67E-07 6.31E-05 1.30E-05 MD 99 NO DATA 1.51E-08 2.87E-09 NO DATA 3.64E-08 1.14E-05 3.10E-05 K 99M 1.29E-13 3.64E-13 4.63E-12 NO DATA 5.52E-12 9.55E-08 5.20E-07
'IC 101 -
5.22E-15 7.52E-15 7.38E-14 NO DATA 1.35E-13 4.99E-08 1.36E-21 BU 103 1.91E-07 NO DATA 8.23E-08 NO DATA 7.29E-07 6.31E-05 1.38E-05 BU 105 9.88E-ll NO DATA 3.89E-ll NO DATA 1.27E-10 1.37E-06 6.02E-06 BU 106 8.64E-06 NO DATA 1.09E-06 NO DATA 1.67E-05 1.17E-03 1.14E-04 AG 110M -1.35E-06 1.25E-06 7.43E-07 NO DATA 2.46E-06 5.79E-04 3.78E-05 TE 125M 4.272.: : _ -
. _4 2 l' ?
. 3*2-G7 1.55E-06 3.922-05 6.336 ud
[
TE 127M 1.58E-06 7.21E-07 1.96E-07 4.11E-07 5.72E-06 1.20E-04 1.87E-05 g
TE 127 1.75E-10 8.03E-11 3.87E-11 1.32E-10 6.37E-10 8.14E-07 7.17E-06 1
TE 129M 1.22E-06 5.84E-07 1.98E-07 4.30E-07 4.57E-06 1.45E-04 4.79E-05
.TE 129 6.22E-12 2.99E-12 1.55E-12 4.87E-12 2.34E-11 2.42E-07 1.96E-08 TE 131M - 8.74E-09 5.45E-09 3.63E-09 6.88E-09 3.86E-08 1.82E-05 6.95E-05 TE 131 1.39E-12 7.44E-13 4.498-13 1.17E-12 5.46E-12 1.74E-07 2.30E-09 TE 132 3.25E-08 '2.69E-08 2.02E-08 2.37E-08 1.82E-07 3.60E-05 6.37E-05 I 130 5.72E-07 l'.68E-06 6.60E-07
-1.42E-04 2.61E-06 NO DATA 9.61E-05'
~ I 131 3.15E-06 4.47E-06 2.56E-06 1.49E-03 7.66E-06 NO DATA 7.85E-07 I 132-1.45E-07 4.07E-07 1.45E-07 1.43E-05 6.48E-07 NO DATA 5.08E-08
)
I;'133-1.08E-06 1.85E-06 5.65E-07' 2.69E-04 3.23E-06
. NO DATA 1.llE-06 I.134
-8.05E-08 2.16E 7.69E-08 3.73E-06 3.44E-07 NO DATA 1.26E-10
-I L135 3.35E-07 8.73E-07 3.21E-07 5.60E-05 1.39E-06 NO DATA 6.56E-07 CS 134' 4.66E-05 1.06E-04 9.10E-05 NO DATA 3.59E-05 1.22E-05.
1.30E-06 CS 136-4.88E-06 1.83E-05 1.38E-05 NO. DATA _ - 1.07E-05 1.50E-06 1.46E-06 CS 137-
.5.98E-05 7.76E-05 5.35E-05 NO DATA 2.78E-05 9.40E-06 1.05E-06 CS 138 4.14E-08 '7.76E-08
.4.05E-08 NO DATA 6.00E-08 6.07E-09 2.33E-13
~_ (/
BA'139
.1.17E-10 8.32E-14, 3.42E-12 NO DATA 7.78E-14 4.70E-07
- 1.12E-07 A-5 y
.-<,,m--
,.-..p.~-
-.-,..,c,,
,......n-,e--e,,.,
,,,,r-,
v,
..-*se e
i-TABLE A.2-1 (cont'd)
-n INHALATION DOSE FACIORS FOR ADULTS i
f i
(MREM PER PCI INHALED)
NUCLIDE fGE LIVER T BODY
'IWYROID KIDNEY WNG 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 1.2SE-ll 9.41E-15 4.20E-13 NO DATA' 8.75E-15 2.42E-07 1.45E-17 BA 142 3.29E-12 3.38E-15 2.07E-13 NO DATA 2.86E-15 1.49E-07 1.96E-26 IA 140 4.30E-08 2.17E-08 5.73E-09 NO DATA NO DATA 1.70E-05, 5.73E-05
'IA 142 8.54E-11 3.88E-ll 9.65E-12 NO DATA NO DATA 7.91E-0/
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 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-04 1.02E-04
~
PR 143 1.17E-06 4.69E-07 5.80E-08 NO DATA 2.70E-07 3.51E-05 2.50E-05 PR 1 *J 2.75E-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 NC, DATA 4.45E-07 2.76E-05 2.16E v5 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
(
T e
4 u
A-6
TABLE A.2-2*
ImiALATICN DOSE FACIORS EOR TEENAGER (MREM PER PCI INHALED)
NUCLIDE BCNE LIVER T BODY THYPOID KIENEY LUNG GI-LLI B
-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 6.09E-07 6.09E-07 NA 24 -
1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 P 32
~2.36E-04 1.37E-05 8.95E-06 NO DATA NO DATA NO DATA 1.16E-05 CR 51 NO DATA NO DATA 1.69E-08 9.37E-09 3.84E-09 2.62E-06 3.75E-07 M 54; NO DATA 6.39E-06 1.05E-06 NO DATA 1.59E-06 2.48E-04 8.35E-06 m 56'
-NO 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 NO DATA 1.91E-04 2.23E-05 CO 58 NO DATA 2.59E-07 3.47E-07 NO DATA NO DATA 1.68E-04 1.19E-05 CO 60 10 DATA 1.89E-06 2.488-06 NO DATA NO DATA 1.09E-03 3.24E-05 NI 63 '
-7.25E-05 5.43E-06 2.47E-06 NO DATA NO DATA 3.84E-05 1.77E-06 i;
O)
NI 65 2.73E 3.66E-ll 1.59E-ll NO DATA NO DATA 1.17E-06 4.59E-06 Li CU 64 NO DATA 2.54E-10
~1.06E-10 NO DATA S.01E-10 1.39E-06 7.68E-06 D
ZN 65 4.82E-06 1.67E-05 7.80E-06 NO DATA 1.08E-05 1.55E-04 5.83E-06 ZN 69.
~6.04E-12 1.15E-ll 8.07E-13 NO DATA 7.53E-12 1.98E-07 3.56E-08 BR' 83
'NO DATA NO DATA 4.30E-08 NO DATA NO DATA NO DATA LT E-24
. BR 84 NO DATA NO DATA 5.41E-08 NO DATA NO DATA NO DATA-LT E,
- BR 85 NO DATA-NO DATA-2.29E-09 NO Dr.TA NO DATA NO DATA LT E-24
.RB 86-NO DATA 2.38E-05 1.05E-05 NO DATA NO DATA; NO DATA 2.21E-06 RB 88 NO DATA 6.82E-08 3.40E-08 NO DATA NO EATA NO DATA 3.65E-15 i
RB 89 NO DATA 4.40E-08~
2.91E-08 NO DATA NO DATA NO DATA 4.22E-17
- SR 89 5.43E-05 NO DATA
-1.56E-06 NO DATA NO DATA 3.02E-04 4.64E-05 SR 90 1.35E-02,NO DATA 8.35E-04 NO. DATA NO DATA 2.06E-03 9.56E-05 i
/SR 91, 1.10E-08 NO DATA 4.398-10 NO DATA NO DATA 7.59E-06 3.24E-05 SR 92 1.19E-09.NO DATA' 5.08E-ll NO DATA NO DATA 3.43E-06' l.49E-05 Y' 90 3.73E-07 NO DATA.
1.00E-08 NO DATA NO DATA 3.66E-05 6.99E-05
'Y-91M-4.63E-11
'NO~ DATA
'1.77E-12 NO DATA NO DATA 4.00E-07 3.77E-09 O
Y -91
'8.26E-05 NO DATA 2.21E-06 NO DATA NO DATA 3.67E-04 5.11E-05
)
' Y L 92,
1.84E-09 L NO DATA 5.36E-ll NO DATA NO DATA 3.35E-06 2.06E-05 "Taxen fran Regulatory Guioe 1.109. (Rev.1)
A-7
. = - _ - -. -,.
.-..--.. _ _ _ --_.=-- _.- - -,-
. - _ ~ _ - _ -
TABLE A.2-2 (cont'd)
, o INHAIATIQ4 DOSE FACIORS FOR TEENAGERS m
~[q) h<
(MIG PER PCI INHALED)
NUCLIDE DCNE LIVER T BODY THYBOID KIDNEY IUNG GI-LLI Y 93
.:1.69E-08 NO DATA 4.65E-10 NO DATA NO DATA 1.04E-05 7.24E-05 ZR 95 1.82E-05 5.73E-06 3.94E-06 NO DATA' 8.42E-06 3.36E-04 1.86E-05 ZR 97 1.72E-08 3.40E-09 1.57E-09 NO DATA 5.15E-09 1.62E-05 7.88E-05
~ NB 95 2.32E-06 1.29E-06 7.08E-07 NO DATA 1.25E-06 9.39E-05 1.21E-05
. MD 99 NO DATA 2.11E-08 4.03E-09 NO DATA 5.14E-08 1.92E-05 3.36E-05 K 99M 1.73E-13 4.83E-13 6.24E-12 NO DATA 7.20E-12 1.44E-07 7.66E-07 TC 101 7.40E-15 1.05E-14 1.03E-13 NO DATA 1.90E-13 8.34E-08 1.09E-16 RU 103.
2.63E-07 NO DATA 1.12E-07 NO DATA 9.29E-07 9.79E-05 1.36E-05 IU 105 1.40E-10 NO DATA 5.42E-ll NO DATA 1.76E-10 2.27E-06 1.13E-05
.EU 106 1.23E-05 NO DATA 1.55E-06 NO DATA 2.38E-05 2.01E-03 1.20E-04 AG 110M 1.73E-06 1.64E-06 9.99E-07 NO DATA 3.13E-06 8.44E-04 3.41E-05 TE 125M 6.10E-07 2.80E-07 8.34E-08 1.75E-07 NO DATA 6.70E-05 9.38E-06 q[
- TE 127 2.51E-10 1.14E-10 5.52E-ll 1.77E-10 9.10E-10 1.40E-06 1.01E-05 TE 127M 2.25E-06 1.02E-06 2.73E-07 5.48E-07 8.17E-06 2.07E-04 1.99E-05 TE 129M-1.74E-06 8.23E-07 2.81E-07 5.72E-07 6.49E-06 2.47E-04 5.06E-05 TC 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
. TB 132 4.50E-08 3.63E-08 2.74E-08 3.07E-08 2.44E-07 5.61E-05 5.79E-05
- I.
130
' 30E-07 2.24E-06 8.96E-07 1.86E-04 3.44E-06 NO DATA 1.12E M -
- I. 131 4.432-06 6.14E-06 3.30E-06 1.d3E-03 1.05E-05 NO DATA 8.llE-07 I 132
~1.99E-07 5.47E-07 1.97E-07 1.89E-05
'8.65E-07 NO DATA
'1.59E-07 I !133-1.52E-06 2.56E-06 7.78E-07 3.65E-04 4.49E-06 NO DATA 1.298-06
-- I -134 1.llE-07 2.90E-07 1.05E 4.94E-06 4.58E-07 NO DATA 2.55E-09 t
I 135 4.62E-07 1.18E-06 4.36E-07 7.76E-05 1.86E-06 NO DATA 8.69E-07 CS 134 6.28E-05 1.41E-04 6.86E-05
.NO DATA 4.69E-05 1.83E-05 1.22E-06
-CS 136 6.44E-06 2.42E-05 1.71E-05 NO DATA 1.38E-05 2.22E-06 1.36E-06 O
.CS 137 8.38E-05 1.06E-04 3.89E-05 NO DATA 3.80E-05 1.51E-05 1.06E-06
- k )
CS .33 5.82E-08 1.07E-07~ 5.58E-08 NO DATA 8.28E-08 9.84E-09 3.38E-ll BA 139 =
1.67E-10 1.18E-13 4.87E-12 NO DATA
.l.llE-13 8.08E 8.06E-07 t
A-8
~ _ _ _ _
TABLE A.2-2 (cont'd)
INHAIATION DOSE FAC'IORS EVR TEENAGERS j
(MREM PER PCI INHALED)
,-. g NUCLIDE BONE LIVER T BODY THYROID KIDNEY IDNG GI-LLI ilA 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-14 5.93E-13 NO DATd 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 IA 140
.5.99E-08 2.95E-08 7.82E-09 to DATA NO DATA 2.68E-05 6.09E-05 IA 142 1.20E-10 5.31E-ll 1.32E-ll NO C ATA NO DATA 1.27E-06 1.50E-06 CE 141 -
3.55E 2.37E-06 2.71E-07 NO CA"'A 1.11E-06 7.67E-05 1.58E-05 t
CE 143 3.32E-08 2.42E-08 2.70E-09 NO DATA 1.08E-08 1.63E-05 3.19E-05 CE 144 _
6.llE-04 2.53E-04 3.28E-05 NO DATA 1.51E-04 1.67E-03 1.08E-04 PR 143 1.67E-06 6.64E-07 8.28E-08 NO DATA 3.86E-07 6.04E-05 2.67E-05 4
PR 144 5.37E-12 2.20E-12 2.72E-13 NO DATA 1.26E-12 2.19E-07 2.94E-14
.No 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 2
NP 239"
~4.23E-08 3.99E-09 2.21E-09 NO DATA 1.25E-08 8.11E-06 1.65E-05 a
m A-9 L
TABLE A.2-3*
p INHALATION DOSE FACIORS EUR OlILD I
(J (MREM PER PCI INHALED)
NUCLIDE BCNE LIVER T BODY DIYROID KIDNEY LUtG GI-LLI II 3
'No DATA 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 C 14 9.708-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 NA 24 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 P 32 7.04E-04 3.09E-05 2.67E-05 NO DATA NO DATA NO DATA 1.14E-05 CR 51 NO DATA NO DATA 4.17E-08 2.31E-08 6.57E-09 4.59E-06 2.93E-07 m 54 NO DATA 1.16E-05 2.57E-06 NO DATA 2.71E-06 4.26E-04 6.19E-06 m 56 NO DATA 4.48E-10 8.43E-ll NO DATA 4.52E-10 3.55E-06 3.33E-05 PE 55 1.28E-05 6.80E-06 2.10E-06 NO DATA NO DATA 3.00E-05 7.75E-07 FE 59 5.59E-06 9.04E-06 4.51E-05 NO DATA NO DATA 3.43E-04 1.91E-05 CD 58 NO DATA 4.79E-07 8.55E-07 NO P TA NO DATA 2.99e-04 9.??? M CO 60 9 Clcis
- ..,32-C6 6.12E-06 N0 asA z.0 clJ.s 1.91E-03 2.00E-05
- NI 63 2.22E-04 1.25E 7.56E-06 NO DATA NO DATA 7.43E-05 1.71E-06
-[
NI 65 8.08E-10 7.99E-Il 4.44E-ll NO DATA NO DATA 2.21E-06 2.27E-05 T
/
CU 64 No DATA 5.39E-10 2.90E-10 NO DATA 1.63E-09 2.59E-06 9.92E-06 ZN 65 1.15E-05 3.06E-05 1.90E-05 NO DATA 1.93E-05 2.69E-04 4.41E-06 ZN 69 1.81E-ll 2.61E-11 2.41E-12 NO DATA 1.58E-11 3.84E-07 2.75E-06 BR 83 NO DATA NO DATA 1.28E-07 NO DATA NO DATA NO DATA LT E-24 DR 84 NO DATA NO DATA 1.43E-07
- D ?ATA NO DATA NO DATA LI i-! '
BR 85 NO DATA NO DATA 6.84E-07 7.*
WO DATA NO DATA LT E-24 R8 86 in DATA 3.36E-05 3.09E-05 NO DATA NO DATA NO DA!A RB 88 NO DATA 1.52E-07 9.90E-08 NO DATA NO DATA NO DATA 4.66E-09 R8 89 NO DATA 9.33E-08 7.83E-08 NO DATA NO DATA' NO DATA 5.11E-10 SR 89 1.62E-04 NO DATA 4.66E NO DATA NO DATA 5.83E-04 4.52E-05 SR 90 2.73E-02 NO DATA 1.74E-03 NO DATA NO DATA 3.99E-03 9.28E-05 SR 91 '
3.28E-08 NO DATA 1.24E-09 NO DATA NO DATA 1.44E-05 4.70E-05 SR 92 3.54E-09 NO DATA 1.42E-10 NO DATA No DATA 6.49E 6.55E-05 Y 90 1.llE-06 NO DATA 2.99E-08 NO DATA NO DATA 7.07E-05 7.24E-05
,o Y 91.i 4.M -10 to CATA 4.98E-12 MO DAfA MO DATA 7.60E-07 4. o 4.:, %,
fi
(
Y 91 2.47E-04 NO DATA 6.59E-06 NO DATA NO DATA 7.10E-04 4.97E-05
' m)
Y 92 5.50E-09 NO DATA 1.57E-10 NO DATA NO DATA 6.46E-06 6.46E-05
- Taxern fran Regulatory Guide 1.109 (Bev.1)
A-10
TABLE A.2-3 (cont'd)
INHAIATION DOSE FACIORS EOR CHILD (MREM PER PCI INHALED) 20CLIDE BONE LIVER T BODY THYROID KIDNEY IUNG GI-LLI
'Y 93 5.04E-08 NO DATA 1.38E-09 NO DATA NO DATA 2.01E-05 1.05E-04 3R 95' 5.13E-05 1.13E-05 1.00E-05 NO DATA' 1.612-05 6.03E-04 1.65E-05
.ZR 97.
5.07E-08 7.34E-09 4.32E-09 NO DATA 1.05E-08 3.06E-05 9.49E-05 IB 95 6.35E-06 2.48E-06 1.77E-06 NO DATA 2.33E-06 1.66E-04 1.00E-05
' m 99 NO DATA 4.66E-08 1.15E-08 NO DATA 1.06E-07 3.66E 3.42E-05 TC 99M 4.81E-13 9.41E-13 1.56E-ll NO DATA 1.37E-ll 2.57E-07 1.30E-06 1C 101 s2.19E-14 2.30E 2.91E-13 NO DATA 3.92E-13 1.58E-07 4.41E-09 RU 103 7.55E-07 NO DATA 2.90E-07 NO DATA 1.90E-06 1.79E-04 1.21E-C5 RJ 105 4.13E-10 'NO DATA
- 1.50E-10 NO DATA 3.63E-10 4.30E-06 2.69E-05 1RU 106 3.68E-05 NO DATA 4.57E-06 NO DATA 4.97E-05 3.87E-03 1.16E-04 AG'110M~ 4.56E-06 3.08E-06 2.47E-06 NO DATA 5.74E-06 1.48E-03 2.71E-05 TE 125M. 1.82E-06 6.29E-07 2.47E-07 5.20E-07 NO DATA 1.29E-04 9.13E-06 TE 1274 - 6.72E-06 2.31E-06 8.16E-07 1.64E-06 1.72E-05 4.00E 1.93E-05 g
TE 127 -
7.49E-10 2.57E-10 1.65E-10 5.30E-10 1.91E-09 2.71E-06 1.52E-05 TE 129M 5.19E-06 1.85E-06 8.22E-07 1.71E-06 1.36E-05 4.76E-04 4.91E-05 TE 129.
2.64E-11 9.45E-12 6.44E-12 1.93E-ll
'6.94E-11 7.93E-07 6.89E-06 TE 131M 3.63E-08 1.60E-08 1.37E-08 2.64E-08 1.08E-07 5.56E-05' 8.32E-05 TE 131 5.87E-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 8.58E-08 4.79E-97 1.02E-04 3.72E ~
-... R-3
..CZ. 2
.: OA*A 1.388-06 i~
- I 131
~ 1.30E-05 1.30E-05 7.37E-ud 4.3 M-03 2.!,3E-05 NO DATA.
7.68E-07 C
I 132
- 5.72E-07 -1.10E-06 5.07E-07 5.23E-05 1.69E-06 NO DATA 8.65E-07 I 133 4.48E-06 5.49E-06_
2.08E-06
-1.04E-03 9.13E-06 NO DATA 1.48E-06
.I.
134 3.17E-07 5.84E-07 2.69E-07 1.37E-05 8.92E-07 NO DATA-2.58E-07
'I -135
' 1.33E-06 2.36E-06 1.12E-06
'2.14E-04 3.62E-06 NO DATA 1.20E-06 CS 134 1.76E-04 '2.74E-04 6.07E-05 N0 0ATA 8.93E-05 3.27E-05 1.04E-06
'CS 136 1.76E-05 4.62E-05 i3.14E-05 NO DATA 2.58E-05 3.93E-06 1.13E-06 e
-CS 137:
2.45E-04 2.23E-04 3.47E-05 NO DATA.
-7.63E-05 2.81E-05 9.78E-07 i
CS 138.
. 4.98E-10 2.66E-13 1.45E-ll NO DATA 2.33E-13 1.56E-06 1.56E-05 n
1.71E-07 2.27E-07 1.50E NO DATA 1.68E-07 1.84E-08 7.29E-08
,' " Q
' BA 139.
A-11
,...~ae,--.,J,.---.
,e m w, -
Wg P-*-**'-^r~NwT*-"C=NF+e"'"e*rW"wve'*-*wt+""=TWPw'WW'*P-*Nwf'va' * ' rwe'e W'W
TABLE A.2-3 (cont'd) m IMIALATICN DOSE FACIORS EUR CHILD f
I (MREM PER PCI INHALED)
LJ NUCLIDE BONE LIVER T BODY THYIOID KIINEY LUNG GI-LLI
$A 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 IA 140 1.74E-07 6.08E-08 2.04E-08 NO DATA NO DATA 4.94E-05 6.10E-05 IA 142 3.50E 1.11E-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-03 1.05E-04 PR 143 4.99E-06 1.50E-06 2.47E-07 NO DATA 8.llE-07 1.17E-04 2.63E-05 PR 144 1.61E-ll 4.99E-12 8.10E-13 NO DATA 2.64E-12 4.23E-07 5.32E-08
-ND 147 2.92E-06 2.36E-06 1.84E-07 NO DATA 1.30E-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 O
NP 239 1.26E-07 9.04E-09 6.35E-09 NO DATA 2.63E-08 1.57E-05 1.73E-05 I
(v 4
O xj A-12
TABLE A.2-4*
INHAIATION DOSE FACIORS EUR INFANT (MREM PER PCI INHALED)
IWCLIDE BOiE LIVER T BODY
'IHYROID KIDNEY WNG GI-LLI H :3-NO DATA 4.62E 4.62E-07 4.62E-07, 4.62E-07 4.62E-07 4.62E-07 C l14 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 t1.45E-03' 8.03E-05 5.53E-05 NO DATA NO DATA NO DATA 1.15E-05 CR 51'
.NO DATA NO DATA 6.39E-08 4.11E-08 9.45E-09 9.17E-06 2.55E-07 m 54 NO DATA 1.81E-05 3.56E-06 NO DATA 3.56E-06 7.14E-04 5.04E-06
) M 56-NO DATA l.' 10E-09 1.58E-10 NO DATA 7.86E-10 8.95E-06 5.12" **
FE 55
-1.41E-05 8.39E-06 2.38E-G NO.'.C.;
NO DATA 5.21E-05 7.82E-07 FE 59i>
_9.69E-06 1.68E-05 6.77E-06 NO DATA NO DATA 7.25E-04 1.77E-05
'CO 58 NO DATA 8.71E 1.30E-06 NO DATA NO DATA 5.55E-04 7.95E-06 00 60 '
NO DATA - 5.73E-06 8.41E-06 NO DATA NO DATA 3.22E-03 2.28E-05 NI 63 2.428-04 1.46E-05
.8.29E-06 NO DATA NO DATA 1.49E-04 1.73E-06 L NI 65 1.71E-09 2.03E-10 8.79E-11 NO DATA NO DATA 5.80E-06 3.58E-05 i
QJ 64 '
NO DATA' 1.34E-09 5.53E-10 NO DATA 2.84E-09 6.64E-06 1.07E-05 b
ZN 65 1.38E-05 4.47E-05 2.22E-05 No DATA 2.32E-05 4.62E-04
.3.67E-05
^
ZN 69 3.858-11 6.J1E-11 5.13E-12 NO DATA-2.87E-11 1.05E-06 9.44E-06 2A E 2D OAra 30 CATA 2.72E-07
.NO CATA NO DATA NO DATA LT E-24 BR 84,
'ND DATA NO DATA 2.86E-07 NO DATA NO DATA NO DATA LT E-24 BR 85T INO DATA NO DATA 1.46E-08 NO DATA NO DATA NO DATA.
LT E-24 RB 86 NO DATA cl.36E-04 6.30E-05 NO DATA NO DATA NO DATA 2.17E-06 2 RB 88 NO DATA 3.98E-07 2.05E-07 NO DATA NO DATA NO DATA 2.42E-07 RB '89 NO DATA 2.29E-07 1.47E-07 NO DATA NO DATA NO DATA 4.87E-08 SR 89
~2.84E-04 NO DATA 8.15E-06 NO DATA NO DATA 1.45E-03 4.57E-05 SR 90
-2.92E-02 NO DATA 1.85E-03 NO DATA NO DATA 8.03E-03 9.36E-05 SR 91^ _ '6.83E-08 'NO DATA 2.47E-09 NO DATA NO DATA-3.76E-05 5.245-05
- SR 92 '
'7.50E-09 NO DATA 2.79E-10 NO DATA' NO DATA 1.70E-05 1.00E-04 Y' 90
-2.358-06. NO DATA-6.30E-08 NO DATA
.NO DATA 1.92E-04 7.43E-05 o
'Y.91M-2.91E-10 NO DATA 9.90E-12 NO DATA NO DATA 1.99E-06'- 1.68E-06
'Y 91.
4.20E-04 NO DATA 1.128 NO DATA NO DATA 1.75E-03 5.02E-05
\\
Y 92.
1.17E-08 NO DATA 3.29E-10 NO DATA NO DATA
~1.75E-05 9.04E-JS
=TE tran;.Hegulatory Guide 1.109 (aev.1)
'i H
A-13 4
f TABLE A.2-4 (cont'd)
INHALATION DOSE FAC'IORS EUR INFANT
,(J (MREM PER PCI INHALED)
NUCLIDE BCNE LIVER T BODY MfYROID KIDNEY IEG 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 2 95 1.12E-05 4.59E-06 2.70E-06 NO DATA 3.37E-06 3.42E-04 9.05E-06 MD 99 NO DATA 1.18E-07 2.31E-08 m DATA 1.89E "
9.63E-05
!M-M TC 99M 9.98E-13 2.06E-12 2.66E-11 NO DATA 2.22E-11 5.79E-07 1.45E-06 IC 101.
4.65E-14 5.88E-14 5.80E-13 NO DATA 6.99E-13 4.17E-07 6.03E-07 E 103 1.44E-06 NO DATA 4.85E-07 NO DATA 3.03E-06 3.94E-04 1.15E-05 E 105 8.74E-10 NO DATA 2.93E-10 NO DATA 6.42E-10 1.12E-05 3.46E-05 RU 106 6.20E-05 NO DATA 7.77E-06 NO DATA 7.61E-05 8.26E-03 1.17E-04 AG 110M 7.13E-06 5.16E-06 3.57E-06 NO DATA 7.80E-06 2.62E-03 2.36E-05 TE 125M 3.40E-06 1.42E-06 4.70E-07 1.16E-06 NO DATA 3.19E-04 9.22E-06
( T TE 127M 1.19E-05 4.93E-06 1.48E-06 3.48E-06 2.68E-05 9.37E-04 1.95E-05 TE 12'I 1.59E-09 6.81E-10 3.49E-10 1.32E-09 3.47E-09 7.39E-06 1.74E-05 gv)
.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 2.48 E-11 1.34E-11 4.82E-11 1.25E-10 2.14E-06 1.88E-05
. C 13',M
'.32E-03 3.932-08 2.59E-03 6.33E-08 1.39E-07 1.42E-04 8.512-05 TE 131 1.24E-11 5.87E-12 3.57E-12 1.13E-11 2.85E-11 1.47E-06 5.87E-06 TE 132 2.66E-07 1.69E-07 1.26E-07 1.998-07 7.39E-07 2.43E-04 3.15E-05 I 130 4.54E-06 9.91E-06 3.98E-06 1.14E-03 1.09E-05 NO DATA 1.42E-06 I 131 2.71E-05 3.17E-05 1.40E-05 1.06E-02 3.70E-05 NO DATA 7.56E-07 I 132 1.21E-06 2.53E-06 8.99E-07 1.21E-04 2.82E-06 NO DATA 1.36E-06 I 133 9.46E-06 1.37E-05 4.00E-06 2.54E-03 1.60E-05 NO DATA 1.54E-06 I 134 6.58E-07 1.34E-06 4.75E-07 3.18E-05 1.49E-06 NO DATA 9.21E-07 I 135 2.76E-06 5.43E-06 1.98E-06 4.97E-04 6.05E-06 NO DATA 1.31E-06 f 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 3.7bE-05 NO. DATA 4.03E-05 8.40E 1.02E-06 CS 137 3.92E-04 4.37E-04 3.25E-05 NO DATA 1.23E-04 5.09E-05 9.53E-07
(
i CS 138 3.61E-07 5.58E-07 2.84E-07 NO DATA 2.93E-07 4.67E-08 6.26E-07 (j '8A 139 1.06E-09 7.03E-13 3.07E-11 NO DATA 4.23E-13 4.25E-06 3.64E-05 A-14
TABLE A.2-4 (cont'd)
INHALATION DOSE FACIORS EUR INFAtfr (MREM PER PCI INHALED) i NUCLIDE BONE LIVER T BODY
'IHYROID KIDNEY Il)NG 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 IA 140 3.61E-07 1.43E-07 3.68E-08 NO DATA NO DATA 1.20E-04 6.06E-05 LA 142 7.36E-10 2.69E-10 6.46E-11 NO DATA NO DATA 5.87E-06 4.25E-05 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 1.48E-07 1.58E-08 NO DATA 4.032-08 8.30E-05 3.55E-05 CE 144 2.28E-03 8.65E-04 1.26E-04 NO DATA 3.84E-04 7.030-0?
1.06E-04 PR 143 1.00E-05 3.74E-06 4.99E-07 NO DATA 1.41E-06 3.09E-04 2.66E-05 PR 144 3.42E-11 1.32E-11 1.72E-12 NO DATA 4.80E-12 1.15E-06 3.06E-06 ND 147 5.67E-06 5.81E-06 3.57E-07 NO DATA 2.25E-06 2.30E-04 2.23E-05 W 187 9.26E-09 6.44E-09 2.23E-09 NO DATA NO DATA 2.83E-05 2.54E-05 NP 239 2.65E-07 2.37E-08 1.34E-08 NO DATA 4.73E-08 4.25E-05 1.78E-05
!(
hv A-15
TABLE A.2-5*
EXTElWAL DOSE FACIORS EUR STANDING ON COtfrAMINATED GROUND 2
(mratVhr per pCi/m )
v Elenent Total Body Skin H-3 0.0 0.0 0-14 0.0 0.0 NAr24 2.50E-08 2.90E-08 P-32 0.0 0.0 Cc-51 2.20E-10 2.60E-10 Mn-54 5.80E-09 6.80E+09 Mn -56 1.10E-08 1.30E-08 Fe-55 0.0 0.0 Fe-59 8.00E-09 9.405-09 Co-58 7.00E-09 8.20E-09 Co-60 1.70E-08 2.00E-08 Ni-63 0.0 0.0 No-65 3.70E-09 4.30E-09 Cu-64 1.50E-09 1.70E-09 2n-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 1.40E-08 Be-85 0.0 0.0 Rb-86 6.30E-10 7.20E-10 rs Rb-88 3.50E-09 4.00E-09
[
)
Rb-89 1.50E-08 1.80E-08
\\_/
St-89 5.60E-13 6.50E-13 s
Sr-91 7.10E-09 8.30E-09 St-92 9.00E-09 1.005-08 Y-90 2.20E-12 2.60E-12 Y-91M 3.80E-09 4.40E-09 Y-91 2.40E-11 2.70E-11 Y-92 1.60E-09 1.90E-09 Y-93 5.70E-10 7.80E-10 Zr-95 5.00E-09 5.80E-09 Zr-97 5.50E-09 6.40E-09 Nb-95 5.10E-09 6.00E-09 Mo-99 1.90E-09 2.20E-09 Tc-99M 9.60E-10 1.10E-09 Tc-101' 2.70E-09 3.00E-09 Ro-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 TW-125M 3.50E-11 4.80E-11 TW-127M 1.10E-12 1.30E-12 TW-127 1.00E-11 1.105-11 TW-129M 7.70E-10 9.00E-10 Te-129 7.10E-10 8.40E-10 f3
- Taken fran Regulatory Guide 1.109 (Rev.1)
A-16 u
TABLE A.2-5 (cont'd)
EXTEBNAL DOSE FACIORS EUR STANDIN3 ON CONTAMINATED GROUND 2
(mrenVhr per pCi/m )
Element Total Body Skin Te-131M 8.40E-09 9.90E-09 i
b l31 2.20E-09 2.605-06 h-132 1.70E-09 2.005-09 I-130 1.40E-08 1.708-08 I-131 2.80E-09 3.40E-09 I-132 1.705-08 2.005-08 I-133 3.70E-09 4.505-09 I-134 1.606-08 1.905-08 I-135 1.205-08 1.405-08 Co-134 1.20E-08 1.405-06 4
Cs-136 1.50E-08 1.708-08 Cs-137 4.205-09 4.90E-09 Cs-138 2.10E-08 2.408-06 Ba-139 2.40E-09 2.70E-09 Be-140 2.10E-09 2.40E-09 Be-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 1.80S-08 Ce-141 5.50E-10 6.20S-10 Ce-143 2.20E-09 2.50E-09 Ce-144 3.20E-10 3.706-10 g
Pr-143 0.0 0.0 Pr-144 2.00E-10 2.30E-10 Nd-147 1.00E-09 1.20E-09 W187 3.10E-09 3.60E-09 Np-239 9.50E-10 1.10E-09 4
l (J i
l l
A-17
TABLE A.3-l*
INGESTICN DOSE FACIORS EUR MXJLTS
/D (MREM PER PCI INGESTED)
NUCLIDE BCNE LIVER T BODY
'IWYBOID KIDNEY UJNG GI-LLI H
3 NO DATA 1.05E-07 1.05E-07 1.055-07 1.05E-07 1.05E-07 1.05E-07 C 14 2.84E-06 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 NA 24 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 P 32 1.93E-04 1.20E-05 7.46E-06 NO DATA NO DATA NO DATA 2.17E-05 CR 51 NO DATA NO DATA 2.66E-09 1.59E-09 5.86E-10 3.53E-09 6.69E-07 m 54 NO DATA 4.57E-06 8.72E-07 10 DATA 1.36E-06 NO DATA 1.40E-05 MN 56 NO DATA 1.15E-07 2.04E-08 NO DATA 1.46E-07 NO DATA 3.67E-06 FE 55 2.75E-06 1.90E-06 4.43E-07 NO DATA NO DATA 1.06E-06 1.09E-06 FE 59 4.34E-06 1.02E-05 3.91E-06 NO DATA NO DATA 2.85E-06 3.40E-05 00 58 NO DATA 7.45E-07 1.67E-06 NO DATA NO DATA NO DATA 1.51E-05 00 60 NO DATA 2.14E-06 4.72E-06 NO DATA NO DATA NO DATA 4.02E-05 NI 63 1.30E-04 9.01E-06 4.36E-06 NO DATA NO DATA NO DATA 1.88E-06 p
NI 65 5.28E-07 6.86E-08 3.13E-08 NO DATA NO DATA NO DATA 1.74E-06 e
i OJ 64 No DATA 8.33E-08 3.91E-08 NO DATA 2.10E-07 NO DATA 7.10E-06 V
ZN 65 4.84E-06 1.54E-05 6.96E-06 NO DATA 1.03E-05 NO DATA 9.70E-06 ZN 69 1.03E-08 1.97E-08 1.37E-09 NO DATA 1.28E-08 NO DATA 2.96E-09 BR 83 NO DATA NO DATA 4.02E-08 NO DATA NO DATA NO DATA 5.79E-08 BR 84 NO DATA NO DATA 5.21E-08 NO DATA NO DATA 20 DATA 4.09E-13 BR 85 NO DATA NO DATA 2.14E-09 NO DATA NO DATA NO DATA LT E-24 RB 86 NO DATA 2.llE-05 9.83E-06 NO DATA NO DATA NO DATA 4.16E-06 RB 88 NO DATA 6.05E-08 3.21E-08 NO DATA NO DATA NO DATA 8.36E-19 RB 89 NO DATA 4.01E-08 2.82E-08 NO DATA NO DATA NO DATA 2.33E-21 SR 89 3.08E-04 NO DATA 8.84E-06 NO DATA NO DATA NO DATA 4.94E-05 SR 90 7.58E-03 NO DATA 1.86E-03 NO DATA NO DATA NO DATA 2.19E-04 SR 91 5.67E-06 NO DATA 2.29E-07 to DATA NO DATA NO DATA 2.70E-05 SR 92 2.15E-06 NO DATA 9.30E-08 NO DATA NO DATA NO DATA 4.26E-05 Y 90 9.62E-09 NO DATA 2.58E-10 NO DATA NO DATA NO DATA 1.02E-04 Y 91M 9.09E-11 NO DATA 3.52E-12 NO DATA NO DATA NO DATA 2.67E-10 (7
/
Y 91 1.41E-07 NO DATA 3.77E-09 NO DATA NO DATA NO DATA 7.76E-05 Y 92 8.45E-10 NO DATA 2.47E-11 NO DATA NO DATA NO DATA 1.48E-05 "Taken frun Regulatory Guide 1.109 (Rev.1)
A-18
TABLE A.3-1 (cont 'd)
INGESTION DOSE FACIORS EUR hDULTS (MREM PER PCI INGESTED)
/
WCLIDE BCNE LIVER T BODY THYROID KIDNEY IENG GI-LLI Y 93 2.68E-09 NO DATA 7.40E-11 NO DATA NO DATA NO DATA 8.50E-05 ZR 95 3.04E-08 9.75E-09 6.60E-09 NO DATA 1.53E-08 NO DATA 3.09E-05 ZR 97 1.68E-09 3.39E-10 1.55E-10 NO DATA 5.12E-10 NO DATA 1.05E-04 NB 95 6.22E-09 3.46E-09 1.86E-09 NO DATA 3.42E-09 NO DATA 2.10E-05 MD 99 m DATA 4.31E-06 8.20E-07 NO DATA 9.76E-06 NO DATA 9.99E-06 E 99M 2.47E-10 6.98E-10 8.89E-09 NO 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 m 103 1.85E-07 NO DATA 7.97E-08 NO DATA 7.06E-07 NO DATA 2.16E-05 m 105 1.54E-08 NO DATA 6.08E-09 NO DATA 1.99E-07 NO DATA 9.42E-06 m 106 2.75E-06 NO DATA 3.48E-07 NO DATA 5.31E-06 NO DATA 1.78E-04 AG 110M 1.60E-07 1.48E-07 8.79E-08 NO DATA 2.91E-07 NO DATA 6.04E-05 TE 125M 2.68E-06 9.71E-07 3.59E-07 8.06E-07 1.09E-05 NO DATA 1.07E-05 TE 127M 6.77E-06 2.42E-06 8.25E-07 1.73E-06 2.75E-05 NO DATA 2.27E-05 C )N TE 127 1.10E-07 3.95E-08 2.38E-08 8.15E-08 4.48E-07 NO DATA 8.68E-06 Q
TE 129M 1.15E-05 4.29E-06 1.82E-06 3.95E-06 4.80E-05 No DATA 5.79E-05 TE 129 3.14E-08 1.18E-08 7.65E-09 2.41E-08 1.32E-07 NO DATA 2.37E-08 TE 131M 1.73E-06 8.46E-07 7.05E-07 1.34E-06 8.57E-06 NO DATA 8.40E-05 TE 131 1.97E-08 8.23E-09 6.22E-09 1.62E-08 8.63E-08 NO DATA 2.79E-09 E 132 2.52E-06 1.63E-06 1.53E-06 1.80E-06 1.57E-05 to DATA 7.71E-05 I 130 7.56E-07 2.23E-06 8.80E-07 1.89E-04 3.48E-06 NO DATA 1.92E-06 I 131 4.16E-06 5.95E-06 3.41E-06 1.95E-03 1.02E-05 NO DATA 1.57E-06 I 132 2.03E-07 5.43E-07 1.90E-07 1.90E-05 8.65E-07 NO DATA 1.02E-07 I 133 1.42E-06 2.47E-06 7.53E-07 3.63E-04 4.31E-06 NO DATA 2.22E-06 I 134 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 NO DATA 2.51E-10 I 135 4.43E-07 1.16E-06 4.28E-07 7.65E-05 1.86E-06 NO DATA 1.31E-06 CS 134 6.22E-05 1.48E-04 1.21E-04 NO DATA 4.79E-05 1.59E-05 2.59E-06 CS 136 6.51E-06 2.57E-05 1.85E-05 NO DATA 1.43E-05 1.96E-06 2.92E-06 CS 137 7.97E-05 1.09E-04 7.14E-05 NO DATA 3.70E-05 1.23E-05 2.11E-06 CS 138 5.52E-08 1.09E-07 5.40E-08 NO DATA 8.01E-08 7.91E-09 4.65E-13 p) i BA 139 9.70E-08 6.91E-11 2.84E-09 NO DATA 6.46E-11 3.92E-11 1.72E-07 v
A-19
1 TABLE A.3-1 (cont'd)
INGESTICN DOGE FACIORS EUR ADULTS (MREM PER PCI INGESTED) v NUCLILE BCNE LIVER T BODY THYROID KIONEY I11tG GI-LLI BA 140 2.03E-05 2.55E-08 1.33E-06 NO DATA 8.67E-09 1.46E-08 4.18E-05 BA 141 4.71E-08 3.56E-ll 1.59E-09 NO DATA 3.31E-11 2.02E-ll 2.22E-17 BA 142 2.13E-08 2.19E-11 1.34E-09 NO DATA 1.85E-ll 1.24E-11 3.00E-26 IA 140 2.50E-09 1.26E-09 3.33E-10 NO DATA NO DATA NO DATA 9.2SE-05 IA 142 1.285-10 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 NO DATA 5.37E-10 NO DATA 4.56E-05 CE 144 4.88E-07 2.04E-07 2.62E-08 NO DATA 1.21E-07 NO DATA 1.65E-04 PR 143 9.20E-09 3.69E-09 4.56E-10 NO DATA 2.13E-09 NO DATA 4.03E-05 PR 144 3.01E-ll 1.25E-11 1.53E-12 NO DATA 7.05E-12 NO DATA 4.33E-18 ND 147 6.29E-09 7.27E-09 4.35E-10 NO DATA 4.25E-09 NO DATA 3.49E-05 W 187 1.03E-07 8.61E-08 3.01E-08 NO DATA NO DATA NO DATA 2.82E-05 NP 239 1.19E-09 1.17E-10 6.45E-Il NO CATA 3.65E-10 NO DATA 2.40E-05 7
b A-20
TABLE A.3-2*
I INGESPION DOSE FACIORS EOR TEENAGERS (MREM PER PCI INGESTED)
NUCLIDE BCNE LIVER T BODY THYROID KIINEY WNG GI-LLI H
3 NO DATA 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 C 14 4.06E-06 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 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 2.768-04 1.71E-05 1.07E-05 NO DATA NO MTA NO DATA 2.32E-05 CR 51 NO DATA NO DATA 3.60E-09 2.00E-09 7.89E-10 5.14E-09 6.05E-07 m 54 10 DATA 5.90E-06 1.17E-06 NO DATA 1.76E-06 NO DAM 1.21E-05 W 56 NO DATA 1.59E-07 2.81E-08 NO DATA 2.00E-07 NO DATA 1.04E-05 FE 55 3.78E-06 2.68E-06 6.25E-07 NO DATA NO DATA 1.70E-06 1.16E-06 FE 59 5.87E-06 1.37E-05 5.29E-06 NO DATA NO DATA 4.32E-06 3.24E-05 CD 58 NO DATA 9.72E-07 2.24E-06 NO DATA NO DATA 10 DATA 1.34E-05 CO 60 NO DATA 2.81E-06 6.33E-06 NO DATA NO DATA NO DATA 3.66E-05 NI 63 1.77E-04 1.25E-05 6.00E-06 NO DATA NO DATA No DATA 1.99E-06 rh NI 65 7.49E-07 9.57E-08 4.36E-08 NO DATA NO DATA NO DATA 5.19E-06 (U 64 NO DATA 1.15E-07 5.41E-08 NO DATA 2.91E-07 20 DATA 8.92E-06 ZN 65 5.76E-06 2.00E-05 9.33E-06 NO DATA 1.28E-05 NO DATA 8.47E-06 ZN 69 1.47E-08 2.80E-08 1.96E-09 NO DATA 1.83E-08 to DATA 5.16E-08 BR 83 NO DATA NO DATA 5.74E-08 NO DATA NO DATA NO DATA LT E-24 BR 84 NO DATA NO DATA 7.22E-08 NO DATA NO DATA NO DATA Lt E-24 BR 85 NO DATA NO DATA 3.05E-09 NO DATA NO DATA NO DATA LT E-24 RB 86 NO DATA 2.98E-05 1.40E-05 NO DATA NO DATA NO DATA 4.41E-06 RB 88 -
NO DATA 8.52E-08 4.54E-08 NO DATA NO DATA NO DATA 7.30E-15 BB 89 NO DATA 5.50E-08 3.c9E-08 NO DATA NO EATA NO DATA 8.43E-17 SR 89 4.40E-04 NO DATA 1.26E-03 NO DATA NO DATA NO DATA 5.24E-05 SR 90 8.30E-03 NO DATA 2.05E-03 NO DATA NO DATA NO DATA 2.33E-04 SR 91 8.07E-06 NO DATA 3.21E '7 NO DATA NO DATA NO DATA 3.66E-05 SR 92 3.05E-06 NO DATA 1.30E-07 NO DATA NO DATA NO DATA 7.77E-05 Y 90 1.37E-08 NO DATA 3.69E-10 NG DATA NO DATA NO DATA 1.13E-04
/
Y 91M 1.29E-10 NO DATA 4.93E-11 NO DATA NO DATA NO DATA 6.09E-09
()
Y 91 2.015-07 NO DATA 5.39E-09 NO DATA NO DATA NO DATA 8.24E-05 j
Y 92 1.21E-09 NO DATA 3.50E-ll NO DATA NO DATA NO DATA 3.32E-05
- Taken fran Regulatory Guide 1.109 (Nev.1)
A-21
TABLE A.3-2 (cont'd)
INGESPICN DOSE FACIORS FOR TEENMERS 1O (MREM PER PCI INGESTED) i NUCLIDE BCsE LIVER T BODY
'IHYRDID KIDNEY IENG GI-LLI Y 93 3.83E-09 NO DATA 1.05E-10 NO DATA NO DATA NO DATA 1.17E-04 ZR 95 4.12E-08 1.30E-08 8.94E-09 NO DATA 1.91E-08 NO DATA 3.00E-05 ZR 97 2.37E-09 4.69E-10 2.16E-10 NO DATA 7.11E-10 Nu L\\TA 1.27E-04 NB 95 8.22E-09 4.56E-09 2.51E-09 NO DATA 4.42E-09 NO DATA 1.95E-05 m 99 NO DATA 6.03E-06 1.15E-06 NO DATA 1.38E-05 NO DATA 1.08E-05 TC 99M 3.32E-10 9.26E-10 1.20E-08 NO DATA 1.38E-08 5.14E-10 6.08E-07 TC 101 3.60E-10 5.12E-10 5.03E-09 NO DATA 9.26E-09 3.12E-10 8.75E-17 m 103 2.55E-07 NO DATA 1.09E-07 NO DATA 8.99E-07 NO DATA 2.13E-05 W 105 2.18E-08 NO DATA 8.46E-09 NO DATA 2.75E-07 NO DATA 1.76E-05 RU 106 3.92E-06 NO DATA 4.94E-07 NO DATA 7.56E-06 NO DATA 1.88E-04 M 110M 2.05E-07 1.94E-07 1.18E-07 NO DATA 3.70E-07 NO DATA 5.45E-05 TE 125M 3.83E-06 1.38E-06 5.12E-07 1.07E-06 NO DATA NO DATA 1.13E-05 TE 127M 9.67E-06 3.43E-06 1.15E-06 2.30E-06 3.92E-05 NO DATA 2.41E-05
(
TE 127 1.58E-07 5.60E-08 3.40E-08 1.09E-07 6.40E-07 NO DATA 1.22E-05 TE 129M 1.63E-05 6.05E-06 2.58E-06 5.26E-06 6.82E-05 NO DATA 6.12E-05
'IT 129 4.48E-08 1.67E-08 1.09E-08 3.20E-08 1.88E-07 NO DATA 2.45E-07 TE 131M 2.44E-06 1.17E-06 9.76E-07 1.76E-06 1.22E-05 NO DATA 9.39E-05 TE 131 2.79E-08 1.15E-08 8.72E-09 2.15E-08 1.22E-07 NO DATA 2.29E-09 TE 132 3.49E-06 2.21E-06 2.08E-06 2.33E-06 2.12E-05 NO DATA 7.00E-05 I 130 1.03E-06 2.98E-06 1.19E-06 2.43E-04 4.59E-06 NO DATA 2.29E-06 I 131 5.85E-06 8.19E-06 4.40E-06 2.39E-03 1.41E-05 NO DATA 1.62E-06 I 132 2.79E-07 7.30E-07 2.62E-07 2.46E-05 1.15E-06 NO DATA 3.18E-07 I 133 2.01E-06 3.41E-06 1.04E-06 4.76E-04 5.98E-06 NO DATA 2.58E-06 I 134 1.46E-07 3.87E-07 1.39E-07 6.45E-06 6.10E-07 NO DATA 5.100-09 I 135 6.10E-07 1.57E-06 5.82E-07 1.01E-04 2.48E-06 NO DATA 1.74E-06 CS 134 8.37E-05 1.97E-04 9.14E-05 NO DATA 6.26E-05 2.39E-05 2.45E-06 CS 136 8.59E-06 3.38E-05 2.27E-05 NO DATA 1.84E-05 2.00E-06 2.72E-06 CS 137 1.12E-01 1.495-04 5.19E-05 NO DATA 5.07E-05 1.97E-05 2.12E-06
[
G 138 7.76E-08 1.49E-07 7.45E-08 NO DATA 1.10E-07 1.28E-08 6.76E-11
(/
BA 139 1.39E-07 9.78E-11 4.05E-09 NO DATA 9.22E-11 6.74E-11 1.24E-06 A-22
TABLE A.3-2 (cont'd) g INGESTICN DOSE FACIOPS EUR TEENAGERS (MREM PER PCI INGESTEE)
NUCLIDE BCNE LIVER T BODY
'IHYIOID KIDNEY IljNG GI-LLI BA 140 2.84E-05 3.48E-08 1.83E-06 NO DATA 1.18E-08 2.34E-08 4.38E-05 BA 141 6.71E-08 5.01E-ll 2.24E-09 NO DATA 4.65E-11 3.43E-ll 1.43E-13 BA 142 2.99E-08 2.99E-ll 1.84E-09 NO DATA 2.53E-ll 1.99E-11 9.18E-20 IA 140 3.48E-09 1.71E-09 4.55E-10 NO DATA NO DATA NO DATA 9.82E-05 IA 142 1.79E-10 7.95E-ll 1.98E-ll NO DATA NO DATA NO DATA 2.42E-06 3 141 1.33E-08 8.88E-09 1.02E-09 NO DATA 4.18E-09 NO DATA 2.54E-05 CE 143 2.35E-09 1.71E-06 1.91E-10 NO DATA 7.67E-10 NO DATA 5.14E-05 CE 144 6.96E-07 2.88E-07 3.74E-08 10 DATA 1.72E-07 NO DATA 1.75E-04 PR 143 1.31E-08 5.23E-09 6.52E-10 NO DATA 3.04E-09 NO DATA 4.31E-05 PR 144 4.30E-ll 1.76E-11 2.18E-12 NO DATA 1.01E-ll NO DATA 4.74E-14 ND 147 9.38E-09 1.02E-08 6.llE-10 NO DATA 5.99E-09 NO DATA 3.68E-05 W 187 1.46E-07 1.19E-07 4.17E-08 NO DATA NO DATA NO DATA 3.22E-05
('~
NP 239 1.76E-09 1.66E-10 9.22&-11 NO DATA 5.21E-10 NO DATA 2.67E-05 t.U Il A-23
TABLE A.3-3*
INGESTION DOSE FACIORS EUR CHIID (MREM PER PCI INGESTED)
NUCLIDE BCNE LIVER T BODY
'INYEID 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 i
C 14 1.21E-05 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 NA 24 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 P 32 8.25E-04 3.86E-05 3.18E-05 NO DATA NO DATA NO DATA 2.28E-05 CR 51 NO DATA NO DATA 8.90E-09 4 94E-09 1.35E-09 9.02E-09 4.725-07 m 54 NO DATA 1.07E-05 2.85E-06 NO DATA 3.00E-06 NO DATA 8.98E-06 m 56 NO DATA 3.34E-07 7.54E-08 NO DATA 4.04E-07 NO DATA 4.84E-05 FE 55 1.15E-05 6.10E-06 1.89E-06 NO DATA NO DATA 3.45E-06 1.13E-06 FE 59 1.65E-05 2.67E-05 1.33E-05 to DATA NO DATA 7.74E-06 2.76E-05 00 58 NO DATA 1.80E-06 5.51E-06 NO DATA NO DATA NO DATA 1.05E-05 00 60 NO DATA 5.29E-06 1.56E-05 NO DATA NO DATA NO DATA 2.93E-05 NI 63 5.38E-04 2.88E-05 1.83E-05 NO DATA NO DATA NO DATA 1.94E-06 fG NI 65 2.22E-06 2.09E-07 1.22E-07 NO DATA NO DATA NO DATA 2.56E-05 (v)
CU 64 NO DATA 2.45E-07 1.48E-07 NO DATA 5.92E-07 NO DATA 1.15E-05 ZN 65 1.37E-05 3.65E-05 2.27E-05 NO DATA 2.30E-05 NO DATA 6.41E-06 ZN 69 4.38E-08 6.33E-08 5.85E-09 NO DATA 3.84E-08 NO DATA 3.99E-06 BR 83 NO DATA NO DATA 1.71E-07 HO DATA NO DATA 10 DATA LT E-24
. BR 84 NO DATA NO DATA 1.98E-07 NO DATA NO DATA NO DATA LT E-24 t
BR 85 NO DATA NO DATA 9.12E-09 NO D*JA NO CATA NO DATA LT E-24 RB 86 NO DATA 6.70E-05 4.12E-05 NO DATA NO DATA NO DATA 4.31E-06 R8 88 NO DATA 1.90E-07 1.32E-07 NO DATA NO DATA NO DATA 9.32E-09 RB 89 NO DATA 1.17E-07 1.04E-07 NO DATA NO DATA NO DATA 1.02E-09 SR 89 1.32E-03 NO DATA 3.77E-05 NO DATA NO DATA No DATA 5.llE-05 SR 90 1.70E-02 NO DATA 4.31E- 03 NO DATA NO DATA NO LATA 2.29E-04 SR 91 2.40E-05 NO DATA 9.06E-07 NO DATA NO DATA NO DATA 5.30E-05 SR 92 9.03E-06 NO DATA 3.62E-07 NO DATA NO DATA NO DATA 1.71E-04 Y 90 4.llE-08 NO DATA 1.10E-09 NO DATA NO DATA NO DATA 1.17E-04 Y 91M 3.82E-10 NO DATA 1.39E-11 NO DATA NO DATA NO DATA 7.48E-07
[)T Y 91 6.02E-07 NO DATA 1.616-08 NO DATA NO DATA NO DATA 8.02E-05
(
Y 92 3.60E-09 NO DATA 1.03C-10 NO DATA N3 DATA NO DATA 1.04E-04
- Taken fran Hegulatory Guide 1.109 (Bev.1)
A-24
TABLE A.3-3 (cont'd)
INGESTION DOSE FACIORS FOR CHIID (MREM PER PCI ItCESTED)
NUCLIDE BCNE LIVER T BODY THYRDID KIDNEY IDG GI-LLI i
Y 93 1.14E-08 NO MTA 3.13E-10 NO MTA NO MTA NO MTA 1.70E-04 2R 95 1.16E-07 2.55E-08 2.27E-08 NO DATA 3.658-08 NO MTA 2.66E-05 a
ER 97 6.99E-09 1.01E-09 5.968-10 NO DATA 1.45E-09 NO DATA 1.53E-04 NB 95 2.25E-08 8.768-09 6.265-09 NO DATA 8.23E-09 NO DATA 1.62E-05 MD 99 NO DATA 1.33E-05 3.295-06 NO DATA 2.84E-05 NO DATA 1.10E-05 TC 99M 9.238-10 1.818-09 3.00E-08 NO MTA 2.63E-08 9.19E-10 1.035-06 TC 101 1.07E-09 1.12E-09 1.42E-08 NO DATA 1.91E-08 5.92E-10 3.56E-09 E 103 7.315-07 NO DATA 2.81E-07 NO DATA 1.84E-06 NO DATA 1.89E-05 au 105 6.455-08 NO DATA 2.345-08 NO DATA 5.67E-07 NO DATA 4.21E-05 EU 106 1.17E-05 NODFA 1.46E-06 NO DATA 1.58E-05 NO DATA 1.82E-04 l
AG 110M 5.39E-07. 3.64E 07 2.91E-07 NO DATA 6.78E-07 NO DATA 4.33E-05 TE 125M 1.14E-05 3.09E-06 1.52E-06 3.20E-06 NO DATA NO DATA 1.10E-05 TE 127M 2.89E-05 7.78E-06 3.43E-06 6.91E-06 8.24E-05 NO DATA 2.34E-05 O
TE 129M TE 127 4.71E-07 1.27E-07 1.01E-07 3.26E-07 1.34E-06 NO DATA 1.84E-05 4.87E-05 1.36E-05 7.56E-06 1.57E-05 1.43E-04 NO DATA 5.94E-05 TE 129 1.34E-07 3.74E-08 3.18E 9.56E-08 3.92E-07 NO DATA 8.34E-06 TE 131M 7.20E-06 2.49E-06 2.65E-06 5.12E-06 2.41E-05 NO DATA 1.01E-04 i
TE 131 8.30E-08 2.53E-08 2.47E-08 6.35E-08 2.51E-07 NO DATA 4.36E-07 I
TE 132 1.01E-05 4.47E-06 5.40E-06 6.51E-06 4.15E-05 NO DATA 4.50E-05 I 130 2.92E-06 5.90E-06 3.04E-06 6.50E-04 8.62E-06 NO DATA 2.76E-06 I 131 1.72E-05 1.73E-05 9.83E-06 5.72E-03 2.84E-05 NO DATA 1.54E-06 I-132 8.005-O'i 1.47E-06 6.76E-07 6.82E-05 2.2SE-06 NO DATA 1.73E-06 I-133 5.928-06 7.32E-06 2.775-06 1.36E-03 1.22E-05 NO DATA 2.95E-06 I 134 4.19E-07 7.78E-07 3.58E-07 1.79E-05 1.19E-06 NO DATA 5.16E-07 l
'I -135-1.75E-06 3.15E-06 1.49F06 2.79E-04 4.83E-06 NO DATA 2.408-06 L
L CS 134
-2.34E-04 3.84E-04^ 8.10E-05 NO DATA 1.19E-04 4.27E-05 2.07E-06 CS 135' 2.355-05 6.465-05 4.18E-05' NO DATA 3.44E-05 5.13E-06
.2.27E-06 CS 137 3.275-04 3.13E-04 4.62&OS NO DATA 1.02E-04 3.67E-05 1.96E-06 L
/
- CS 138 2.28&O7 3.17E-07.
- 2. ole 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 I
. ~. - - - -. - -. - - - - -. - - - - -
TABLE A.3-3 (cont'd)
INGESTION DOSE FACIORS EOR CHILD f
(M PER PCI INGESTED)
V NUCLIDE fK:NE LIVER T BODY
'IHYICID KIINEY 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-11 3.70E-ll 1.14E-09 4
IA 140 1.01E-08 3.53E-09 1.19E-09 NO DATA NO DATA NO DATA 9.84E-05 IA 142 5.24E-10 1.67E-10 5.23E-11 10 DATA NO DATA NO DATA 3.31E-05 CE 141 3.97E-08 1.98E-08 2.94E-09 NO DATA 8.68E-09 NO DATA 2.47E-05 CE 143 6.99E-09 3.79E-06 5.49E-10 NO DATA 1.59E-09 NO DATA 5.55E-05 CE 144 2.08E-06 6.52E-07 1.11E-07 10 DATA 3.61E-07 NO DATA 1.70E-04 PR 143 3.93E-08 1.18E-08 1.95E-09 NO DATA 6.39E-09 NO DATA 4.24E-05 PR 144 1.29E-10 3.99E-ll 6.49E-12 NO DATA 2.llE-ll NO DATA 8.59E-08 ND 147 2.79E-08 2.26E-08 1.75E-09 NO DATA 1.24E-08 NO DATA 3.58E-05 W 187 4.29E-07 2.54E-07 1.14E-07 NO DATA NO DATA NO DATA 3.57E-05 NP 239 5.25E-09 3.77E-10 2.65E-10 NO DATA 1.09E-09 NO DATA 2.79E-05
~ (O
\\
i U
A-26
. _ -. ~ _. _ - _. _.,... _ _..
. = -
TABLE A.3-4*
IEESTION DOSE FACIORS EOR INFANP (MRD4 PER PCI IEESIED)
NUCLIDE BONE LIVER T BODY
'IHYROID KIDNEY IUNG GI-LLI H
3 NO DATA 3.08E-07 3.08E-07 3.0BE-07 3.08E-07 3.08E-07 3.08E-07 C 14 2.37E-05 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 NA 24 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 P 32 1.70E-03 1.00E-04 6.59E-05 NO DATA NO DATA NO DATA 2.30E-05 CR 51 NO DATA NO DATA 1.41E-08 9.20E-09 2.01E-09 1.79E-08 4.11E-07 M 54 NO DATA 1.99E-05 4.51E-06 NO DATA 4.41E-06 NO DATA 7.31E-06 M 56 10 DATA 8.18E-07 1.41E-07 NO DATA 7.03E-07 NO DATA 7.43E-05 FE 55 1.39E-05 8.98E-06 2.40E-06 NO DATA to DATA 4.39E-06 1.14E-06 FE 59 3.08E-05 5.38E-05 2.12E-05 NO DATA NO DATA 1.59E-05 2.57E-05 CO 58 NO DATA 3.60E-06 8.98E-06 NO DATA NO DATA NO DATA 8.97E-06 CO 60 NO DATA 1.08E-05 2.55E-05 NO DATA NO DATA NO DATA 2.57E-05 NI 63
'6.34E-04 3.92E-05 2.20E-05 NO DATA NO DATA NO DATA 1.95E-06
-(
NI 65 4.70E-06 5.32E-07 2.42E-07 NO DATA NO DATA NO DATA 4.05E-05 CU 64 NO DATA 6.09E-07 2.82E-07 NO DATA 1.03E-06 NO DATA 1.25E-05 ZN 65 1.84E-05 6.31E-05 2.91E-05 NO DATA 3.06E-05 NO DATA 5.33E-05 ZN 69 9.33E-08 1.68E-07 1.25E-08 NO DATA 6.98E-08 NO DATA 1.37E-05 BR 83 NO DATA NO DATA 3.63E-07 NO DATA NO DATA NO DATA LT E-24 BR 84 NO DATA NO DATA 3.82E-07 NO DATA NO DATA NO DATA LT E-24 BR 85 NO DATA NO DATA 1.94E-08 NO DATA NO DATA tiO DATA LT E-24 RB 86 NO DATA 1.70E-04 8.40E-05 NO DATA NO DATA NO DATA 4.35E-06
.RB 88 NO DATA 4.98E-07 2.73E-07 NO DATA NO DATA NO DATA 4.85E-07 RB 89
-NO DATA 2.86E-07 1.97E-07 NO DATA NO DATA NO DATA 9.74E-08 SR 89 2.51E-03 NO DATA 7.20E-05 NO DATA NO DATA NO DATA 5.16E-05 SR 90 1.85E-02 NO DATA 4.71E-03 NO DATA NO DATA NO DATA 2.31E-04 SR 91 5.00E-05 NO DATA 1.81E-06 NO DATA-NO DATA NO DATA 5.92E-05 SR 92
-1.92E-05 NO DATA 7.13E-07 NO DATA NO DATA NO DATA 2.07E-04 Y-90 8.69E-08 to DATA 2.33E-09 NO DATA NO DATA NO DATA 1.20E-04 q
Y 91M 8.10E-10 NO DATA 2.76E-ll NO DATA NO DATA NO DATA 2.70E-06 Y 91 1.13E-06 NO DATA 3.01E-08 NO DATA NO DATA NO DATA 8.10E-05 Y 92 7.65E-09 NO DATA 2.15E-10 NO DATA NO DATA NO DATA 1.46E-04
'*Taken fran Regulatory Guide 1.109 (Rev. 1)
A-27
l TABLE A.3-4 (cont'd)
INGESTION DOSE FACIORS EOR INFANT j
(MPIM PER PCI INGESTED)
~
t 4
i NUCLIDE BONE LIVER T BODY
'IHYRDID KIDNEY LUNG GI-LLI 4
Y 93 2.43E-08 NO DATA 6.62E-10 NO DATA NO DATA NO DATA 1.92E-04 ZR 95 2.06E-07 5.02E-08 3.56E-08 NO DATA 5.41E-08 NO DATA 2.50E-05 t
ZR 97 1.48E-08 2.54E-09 1.16S-09 NO DATA 2.56E-09 NO DATA 1.62E-04 le 95 4.20E-08 1.73E-08 1.00E-08 NO DATA 1.24E-08 NO DATA 1.46E-05 MD 99 NO DATA 3.40E-05 6.63E-06 NO DATA 5.08E-05 NO DATA 1.12E-05 E 99M 1.92E-09 3.96E-09 5.10E-08 NO DATA 4.26E-08 2.07E-09 1.15E-06 K 101 2.27E-09 2.86E-09 2.83E-08 NO DATA 3.40E-08 1.56E-09 4.86E-07 N 103_
1.48E-06 NO DATA 4.95E-07 NO DATA 3.08E-06 NO DATA 1.80E-05 au 105 1.36E-07 NO DATA 4.58E-08 NO DATA 1.00E-06 NO DATA 5.41E-05 1
W 106 2.41E-05 NO DATA 3.01E-06 NO DATA 2.85E-05 NO DATA 1.83E-04 AG'110M 9.96E-07 7.27E-07 4.81E-07 NO DATA 1.04E-06 NO DATA 3.77E-05
{
TE 125M 2.33E-05 7.79E-06 3.15E-06 7.84E-06 NO DATA NO DATA 1.11E-05 TE 127M 5.85E-05 1.94E-05 7.08E-06 1.69E-05 1.44E-04 NO DATA 2.36E-05 TE 127 1.00E-06 3.35E-07 2.15E-07 8.14E-07 2.44E-06 NO DATA 2.10E-05 TE 129M-1.00E-04 3.43E-05 1.54E-05 3.84E-05 2.50E-04 NO DATA 5.97E-05 TE 129 2.84E-07 9.79E-08 6.63E-08 2.38E-07 7.07E-07 NO DATA 2.27E-05 TE 131M 1.52E-05 6.12E-06 5.05E-06 1.24E-05 4.21E-05 NO DATA 1.03E-04 TE 131.
1.76E-07 6.50E-08 4.94E-08 1.57E 4.50E-07 NO DATA 7.llE-06 TE 132
-2.08E-05: 1.03E-05 9.61E-06 1.52E-05 6.44E-05 NO DATA 3.81E-05
.I 130-6.00E-06 1.32E-05 5.30E-06 1.48E-03 1.45E-05 NO DATA 2.83E-06 I ~131 3.59E-05 4.23E 1.86E-05 1.39E-02 4.94E-05 NO DATA 1.51E-06 I. 132 1.66E-06 3.37E-06 1.20E 1.58E-04 3.76E-06 NO DATA
-2.73E-06
'I ?133 1.25E-05 1.82E-05 5.33E-06 '3.31E-03 2.14E-05 NO DATA 3.08E-06 I '134 8.69E-07 1.78E-06 6.33E-07 4.15E-05 1.99E-06 NO DATA 1.84E-06
, r-I. 135 3.64E-06' 7.24E 2.64E-06 6.49E-04 8.07E-06 NO DATA 2.62E-06 CS 134-3.77E-04 7.03E-04 7.10E-05 NO. DATA 1.81E-04 7.42E-05 1.91E-06
-CS 135~
4.59E-05 1.35E-04 5.04E-05 NO DATA 5.38E-05 1.10E-05 2.05E-06' CS 137 5.22E-04; 6.11E-04 4.33E-05 NO DATA 1.64E-04 6.64E-05 1.91E ;CS 138 4.81E-07 7.82E-07 -3.79E-07 NO DATA:
3.90E-07 6.09E-08 1.25E '
(
. BA 139 :
8.81D-07 5.84E-10 2.55E-08 NO DATA 3.51E-10 3.54E-10 5.58E-05 t
A-28
.. -.-..... _._ _ _._,__ _._,. ~... - _.. _ _ _. _ _._. _. _. _._ _. _ _ _ _
TABLE A.3-4 (cont'd)
INGESTICN DOSE FACIORS FOR INFANT g
(MREM PER PCI INGESTED)
NUCLIDE BONE LIVER T BODY
'IHYROID KIDNEY IUNG 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 NO DATA 1.75E-10 1.77E-10 5.19E-06 BA 142 1.84E-07 1.53E-10 9.06E-09 NO DATA 8.81E-ll 9.26E-11 7.59E-07 IA 140 2.11E-08 8.32E-09 2.14E-09 NO DATA NO DATA NO DATA 9.77E-05 IA 142 1.10E-09 4.04E-10 9.67E-11 NO DATA NO DATA NO DATA 6.86E-05 CE 141 7.87E-08 4.80E-08 5.65E-09 NO DATA 1.48E-08 NO DATA 2.48E-05 CE 143 1.48E-08 9.82E-06 1.12E-09 NO DATA 2.86E-09 NO DATA 5.73E-05 CE 144 2.98E-06 1.22E-06 1.67E-07 NO DATA 4.93E-07 NO DATA 1.71E-04 PR 143 8.13E-08 3.04E-08 4.03E-09 NO DATA 1.13E-08 10 DATA 4.29E-05 PR 144 2.74E-10 1.06E-10 1.38E-ll NO DATA 3.84E-ll NO DATA 4.93E-06 ND 147 5.53E-08 5.68E-08 3.48E-09 NO DATA 2.19E-08 NO DATA 3.60E-05 W 187 9.03E-07 6.28E-07 2.17E-07 NO DATA NO DATA NO DATA 3.69E-05 p
NP 239 1.11E-08 9.93E-10 5.61E-10 NO DATA 1.98E-09 NO DATA 2.87E-05 O
l-(D L/
A-29 l
l i
TABLE A.3-5*
STABLE ELEMENT TRANSFER DATA V
B F,(Cow)
F gy g
Element Veg/ Soil Milk (d/ )
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 3.0s-02 P
1.lE 00 2.5E-02 4.6E-02 Cr 2.5E-04 2.2E-03 2.4E-03 Mn 2.9E-02 2.55-04 8.0S-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 It) 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
.g Rh 1.3E 01 1.0E-02 1.5E-03 5.0E-02 1.7E-02 Ag 1.5E-01 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.
U A-30
TABLE A.4-1 1-SITE REIATED DOSE COMMI'IMENT FACIOR AIT O
2' MREh/tiR PER UCI/ML ADULT NUCLIDE BCNE LIVER T BODY THYROID KIDNEY IUNG GI-LLI H-3 0.00E-01 8.96E 00 8.96E 00 8.96E 00 8.96E 00 8.96E 00 8.96E 00 C-14 3.15E 04 6.308 03 6.30E 03 6.30E 03 6.30E 03 6.30E 03 6.30E 03 NA-24 5.48E 02 5.48E 02 5.48E 02 5.48E 02 5.48E 02 5.48E 02 5.48E 02 4
P-32 4.62E 07 2.87E 06 1.798 06 0.00E-01 0.00E-01 0.00E-01 5.20E 06 CR-51 0.00E-01 0.00E-01 1.49E 00 8.945-01 3.29E-01 1.98E 00 3.76E 02 5 54 0.00E-01 4.76E 03 9.08E 02 0.00E-01 1.42E 03 0.005-01 1.46E 04 1
M4-56 0.00E-01 1.20E 02 2.12E 01 0.00E-01 1.52E 02 0.00E-01 3.82E 03 FE-55 8.87E 02 6.13E 02 1.43E 02 0.00E-01 0.00E-01 3.42E 02 3.52E 02 FS-59 1.40E 03 3.29E 03 1.26E 03 0.00E-01 0.00E-01 9.19E 02 1.10E 04 O}-58 0.00E-01 1.51E 02 3.39E 02 0.00E-01 0.00E-01 0.00E-01 3.C6E 03 CO -60 0.00E-01 4.34E 02 9.58E 02 0.00E-01 0.00E-01 0.00E-01 8.16E 03 NI-63 4.198 04 2.94E 03 1.41E 03 0.00E-01 0.00E-01 0.00E-01 6.07E 02 NI-65 1.70s 02 2.21E 01 1.01E 01 0.00E-01 0.00E-01 0.00E-01 5.61E 02 CU-64 0.00E-01 1.69E 01 7.93E 00 0.00E-01 4.26E-01 0.00E-01 1.44E 03 i.
ZN-65 2.368 04 7.50E 04 3.39E 04 0.00E-01 5.02E 04 0.00E-01 4.73E 04 ZN-69
-5.028 01 9.60E 01 6.67E 00 0.00E-01 6.24E-01 0.00E-01 1.44E 01 BR-83 0.00E-01 0.00E-01 4.38E 01 0.00E-01 0.00E-01 0.00E-01 6.30E 01 BR-84 0.00E-01 0.00E-01 5.67E 01 0.00E-01 0.00E-01 0.00E-01 4.45E-04 I
BR-85 0.00E-01 0.00E-Ol' 2.33E 00 0.00E-01 0.00E-01 0.00E-01 1.09E-19
_RB-86
'O.00E-01 1.03E 05 4.79E 04 0.00E-01 0.00E-01 0.00E-01 2.03E 04 l_
RB-88 0.00E-01 2.95E 02 1.56E 02 0.00E-01 0.00E-01 0.00E-01 4.07E-09 RB-89 0.00E-01 1.95E 02 1.37E 02 0.00E-01 0.00E-01 0.00E-01 1.13E-ll L
SR-89 4.78E 04 0.00E-01 1.37E 03 0.00E-01 0.00E-01 0.00E-01 '7.66E 03 SR-90 1.18E 06 - 0.00E-01 2.88E 05_
0.00E-01 0.00E-01 0.00E-01 3.40E 04 a
l SR-91 b.79E'02 0.00E-01 3.55E 01 0.00E-01 0.00E-01
-0.00E-01 4.19E 03:
L SR-92 3.33E 02 0.00E-01 1.44E 01 0.00E-01 0.00E-01 0.00E-01 6.60E 03 Y-90.
1.38E 00 0.00E-01 3.69E-02 0.00E-01 0.00E-01 0.00E-01 1.46E 04 Y-91M 1.30E-02 0.00E-01 5.04E-04 0.00E-01 0.00E-01 0.00E-01 3.82E-02 Y-91 2.02E 01. 0.00E-01 5.39E 0.00E-01 0.00E-01 0.00E-01 1.llE 04 Y-92 1.21E-01 0.00E-01 3.53E 0.00E-01 0.00E-01 0.00E-01 2.12E 03 A-31 l'
. = -
TABLE A.4-1 (cont'd) 4 SITS REIATED DOSE G)MMITMENT FACIOR AIT MREM /HR PER UCI/ML
)
ADULT NUCLIDE BCNE LIVER T BCIN THYROID KIDNEY IANG GI-LLI 1
Y-93 3.83E-01 0.00E-01 1.06E-02 0.00E-01 0.00E-01 0.00E-01 1.22E 04 ZR 2.77E 00 8.88E-01 6.01E-01 0.00E-01 1.39E 00 0.00E-01 2.82E 03 ZR-97 1.53E-01 3.09E-02 1.41E-02 0.00E-01 4.67E-02 0.00E-01 9.57E 03 t 95
'4.478 02 2.49E 02 1.34E 02 0.00E-01 2.46E 02 0.00E-01 1.51E 06 h 99 0.005-01 4.62E 02 8.79E 01 0.00E-01 1.05E 03 0.00E-01 1.07E 03 TC-99M-2.948-02 8.32& 02 1.06E 00 0.00E-Ol' l.26E 00 4.07E-02 4.92E 01 TC-101 3.03E-02 4.36E-02 4.28E-01 0.00E-01 7.85E-01 2.23E-02 1.31E-13 10-103 1.98E 01.0.00E-01 8.54E 00 0.00E-01 7.578 01 0.00E-01 2.31E 03 p 105 1.65E 00 0.00E-01 6.52E-01 0.00E-01 2.13E 01 0.00E-01 1.01E 03 a
' h 106 2.95E 02 0.006-01 3.73E 01 0.00E-01 5.69E 02 0.00E-01 1.91E 04 G il0M-1.33E 01 1.23E 01 7.32E 00 0.00E-01 2.42E 01 0.00E-01 5.03E 03 TE-125M 2.79E 03 1.01E 03 3.74E 02 8.39E 02 1.13E 04 0.00E-01 1.llE 04 I
TE-127M 7.05E 03 2.52E 03 8.59E 02 1.80E 03 2.86E 04 0.00E-01 2.36E 04 l
TS-127 1.14E 02 4.llE 01 2.48E 01 8.48E 01 4.66E 02 0.00E-01 9.03E 03
. TE-129M-1.20E 04 4.47E 03 1.89E 03 -4.llE 03 5.00E 04 0.00E-01 6.03E 04 r
TE-129 3.27E 01 1.23E 01 7.96E 00 2.51E 01-1.37E 02 0.00E-01 2.47E 01 TS-131M 1.80E _03 - 8.~81E 02 7.34E 02 1.39E 03-8.92E 03 0.00E-01 -8.74E 04 L
TE-131 2.05E 01 8.57E 00 6.47E 00 1.69E 01 8.98E 01 0.00E-01 2.90E 00 TE-132
'2.62E 03 1.70E'03 1.59E 03-1.87E 03 1.63E 04 0.00E-01 8.02E 04
- I-130 9.01E 01 2.66E 02.
1.05E 02.2.25E 04 4.15E 02 'O.00E-01 2.29E 02
- I-131
'4.96E 02 7.09E 02 4.06E 02 2.32E 05 1.22E 03 0.00E-01 1.87E 02 I
fy I-132 2.42E 01 6.47E 01 2.26E 01 2.26E 03 1.03E 02 0.00E-01 1.22E 01 I-133-1.69E 02 2.948 02 8.97E 01 4.32E 04 '5.13E 02 0.00E-01 2.64E 02 l -
'I-134 1.26E 01 3.438 01- 'l.23E 01 5.94E 02-5.46E 01 0.00E-01 2.99E-02 I--135
-5'.28E 01 1.38E 02 I5.10E 01
--9.llE 03 2.22E 02 0.00E-01 1.56E 02 CS-134
~3.03E 05 7.21E 05 5.898 05 0.00E-01 2.33E 05 7.75E 04 1.26E 04 CS-136 3.17E 04 1.25E 05 9.01E 04 0.00E-01 6.97E 04 9.55E 03 1.42E 04 l
?f. k j
~CS-138 CS-137 3.88E 05 5.31E 05 3.48E 05 0.00E-01 1.80E 05 5.99E 04 1.03E 04
-2.69E 02.5.31E 02 2.63E 02 -0.00E-01 3.90E 02 3.85E 01 2.27E -
BA-139 9.00E 00 6.415-03 2.648-01, 0.00E-01 5.99E-03 3.64E-03 1.60E Ol'
~
- Bioaccumulation factor asstaaed to be zero since no data.was available.
A-32
..._..,_._.m m.
TABLE A.4-1 (cont'd)
SITE RELATED DOSE (DMMI1 MENT FACIOR AIT
~
MRE24/HR PER UCI/ML ADULT 4
NUCLIDE BCNE LIVER T BODY THYBOID KIDNEY WNG GI-LLI BA-140 1.88E 03 2.37E 00' M.23E 02 0.00E-01 8.05E-01 1.35E 00 3.88E 03 BA-141 4.37E 00 3.30E-03 1.48E-01 0.00E-01 3.07E-03 1.87E-03 2.06E-09 BA-142 1.98E 00 2.03E-03 1.24E-01 0.00E-01 1.72E-03 1.15E-03 2.78E-18 IA-140 3.58E-01 1.80E-01 4.76E-02 0.00E-01 0.00E-01 0.00E-01 1.32E 04 IA-142 1.83E-02 8.33E-03 2.07E-03 0.00E-01 0.00E-01 0.00E-01 6.08E 01
+
CE-141-8.01E-01 5.42E-01 6.15E-02 0.00E-01 2.52E-01 0.00E-01 2.07E 03 CE-143 1.41E-01 1.04E 02 1.16E-02 0.00E-01 4.60E-02 0.00E-01 3.90E 03 CE-144 4.18E 01 1.75E 01 2.24E 00 0.00E-01 1.04E 01 0.00E-01 1.41E 04 PR-143 1.32E 00 5.28E-01 6.52E-02 0.00E-01 3.05E-01 0.00E-01 5.77E 03
'PR-144 4.31E-03 1.79E-03 2.19E-04 0.00E-01 1.01E-03 0.00E-01 6.19E-10 ND-147 9.00E-01 1.04E 00 6.22E-02 0.00E-01 6.08E-01 0.00E-01 4.99E 03
-W-187 3.04E 02 2.55E 02 8.90E 01 0.00E-01 0.00E-01 0.00E-01 8.34E 04 NP-239 1.28E-01 1.25E-02 6.91E 0.00E-01 3.91E-02 0.00E-01 2.57E 03 O
4 A-33
l i
TABLE A.4-2 i
' f SITC RELATED DOSE COMMI'IMENT FACIOR AIT
-t MREM /HR PER UCI/ML 3
TEEN NUCLIDE BONE-LIVER T BODY THYBOID KIDNEY Il3NG GI-LLI l
-0.00E-01 6.34E 00 6.34E 00 6.34E 00 6.34E 00 6.34E 00 6.34E 00
- C-14 3.43E 04 6.86E 03 6.86E 03 6.86E 03 6.86E 03 6.86E 03 6.86E 03 i
NA-24~
5.53E 02 5.53E 02 5.53E 02 5.53E 02 5.53E 02 5.53E 02 5.53E 02 P-32 5.04E 07 3.12E 06 1.95E 06 0.00E-01 0.00E-01 0.00E-01 4.23E 06 CR-51 0.00E-01 0.00S-01 1.52E 00 8.46E-01 3.34E-01 2.17E 00 2.56E 02 3
m-54 0.00E-01 4.65E 03 9.22E 02 0.00E-01 1.39E 03 0.00E-01 9.53E 03 m-56 0.00E-01 1.24E 02 2.21E 01 0.00E-01 1.58E 02 0.00E-01 8.19E 03
-FS-55 9.09E 02 6.45E 02 1.50E 02 0.00E-01 0.00E-01 4.09E 02 2.79E 02 FE-59 1.41E 03 3.30E 03 1.27E 03 0.00E-01 0.00E-01 1.04E 03 7.79E 03 CO-58 0.00E-01 1.45E 02 3.35E 02 0.00E-01 0.00E-01 0.00E-01 2.00E 03 CD-60 0.00E-01 4.20E 02 9.45E 02 0.00E-01 0.00E-01 0.00E-01 5.47E 03 NI-63 4.26E 04 3.01E 03 1.44E 03 0.00E-01 0.00E-01 0.00E-01 4.79E 02 NI-65 1.80E 02 2.30E 01 1.05E 01 0.00E-01 0.00E-01 0.00E-01 2.25E 03' CD-64 0.00E-01 1.72E 01 8.08E 00 0.00E-01 4.35E 01 0.00E-01 1.33E 03
'ZN-65 2.13E 04 7.41E 04 3.46E 04.
0.00E-01 4.74E 04 0.00E-01 3.14E 04 ZN-69 5.45E 01 1.04E 02 7.26E 00 0.00E-01 6.78E 01 0.00E-01 1.91E 02 BR 0.00E-01 0.00E-01 4.73E 01 0.00E-01 0.00E-01 0.00E-01 8.24E-16 BR-81 0.00E-01 0.00E 5.95E 01 0.00E-01 0.00E-01 0.00E-01 8.24E-16 BR-85 0.00E-01 0.00E 2.51E 00 0.00E 0.00E-01 0.00E-01~ 8.24E-16 RB 0.00E 1.10E 05 - 5.19E 04 0.00E-01 0.00E-01 0.00E-01 -1.63E 04 "RB-88 0.00E-01 3.16E 02 1.68E 02 0.00E-01 0.00E-01 0.00E-01 2.71E-05 l
L l
- 0.00E-01 2.04E 02 1.44E 02 0.00E-01 0.00E-01 0.00E-01 3.12E-07 l:
SR-89:
4.97E 04 0.00E-01 1.42E 03 0.00E-01 0.00E-01 0.00E-01 5.91E 03 -
- ~
SR-90 9.37E 05 0.00E-01 2.31E 05 0.00E-01 0.00E 0.00E-01 2.63E 04~
p-SR 9.llE 02.0.00Fe01 3.62E 01 0.00E-0.
-0.00E-01.
0.00E 4.13E 03 g
SR-92
' 3.44E 02 0.00E-01 1.47E 01 0.00E-01 0.00E-01 0.00E-01 8.77E 03-
- Y-90 1.42E 00 0.00E-01 3.83E-02 0.00E-0) 0.00E-01 0.00E-01 1.17E 04 z
l:
Y-91M'
-3.34E-02-~0.00E-01 5.llE-04 0.00E-01 0.00E 0.00E-01 '6.32E-01 f
Y-91;
- 2.09E 01 -0.00E-01 5.59E-01 -0.00E-01 0.00E-01 0.00E-01 8.55E 03
~
-Y-92 1.26E 0.00E-01 3.63E-03 0.00E-01 0.00E-01 0.00E-01 3.44E 03 A-34.
L
.l TABLE A.4-2 (cont'd)
O-SITS RELATED DOSE COMMI'INENT FACIOR AIT MREtVHR PER UCI/ML TEEN MJCLIDE BQ4E LIVER T BODY THYRDID KIDNEY IUNG GI-LLI
-Y-93 3.97E-01 0.00E-01 1.09E-02 0.00E-01 0.00E-01 0.00E-01 1.21E 04 3R-95 2.64E 00 8.34E-01 5.74E-01 0.00E-01 1.23E 00 0.00E-01 1.92E 03 3a-97
-1.52E-01 3.01E-02 1.39E-02 0.00E-01 4.56E-02 0.00E-01 8.15E 03 NS-95 4.50E 02 2.50E 02 1.37E 02 0.00E-01 2.42E 02 0.00E-01 1.07E 06 MC)-99 0.00E-01 4.61E 02 8.7CE 01 0.00E-01 1.05E 03 0.00E-01 8.25E 02 L
. E-99M 2.84E-02 7.92E-02 1.03E 00 0.00E-01 1.18E 00 4.39E-02 5.20E 01 i
K-101 3.08E-02 4.385-02 4.30E-01 0.00E-01 7.92E-01 2.67E-02 7.48E-09
.RD-103 1.95E 01 0.00E-01 8.33E 00 0.00E-01 6.87E 01 0.00E-01 1.63E 03 RD-105 1.67E 00 0.00E-01 6.46E-01 0.00E-01 2.10E 01 0.00E-01 1.34E 03 RU-106 2.99E 02 0.00E-01 3.77E 01 0.00E-01 5.77E 02 0.00E-01 1.44E 04 AG-110M-1.19E 01 1.13E 01 6.86E 00 0.00E-01 2.15E 01 0.00E-01 3.17E'03
.TS-125M 3.02E 03 1.09E 03 4.03E 02 8.43E 02 0.00E-01 0.00E-01 8.90E 03 TE-127M 7.62E 03 2.70E 03 9.06E 02 1.81E 03 3.09E 04 0.00E-01 1.90E 04 TS-127 1.24E 02 4.41E 01 2.68E 01 8.59E 01 5.04E 02 0.00E-01 9.61E 03 TE-129M 1.28E 04 4.77E 03 2.03E 03 4.14E 03 5.37E 04 0.00E-01 4.82E 04 r
TE-129 3.53E 01 1.32E 01
'8.59E 00 2.52E 01 1.48E 02 0.00E-01 1.93E 02 i
TE-131M 1.92E 03 9.22E 02 7.69E 02 1.39E 03 9.61E 03 0.00E 7.40E 04 TE-131l
'2.20E 01 9.06E 00 6.87E 00 1.69E 01 9.61E 01 0.00E- 01 1.80E 00 L
~
2.75E 03 1.74E 03' l.64E 03 1.84E 03 1.67E 04 0.00E-01 5.51E 04 L
TE-132 L
I-130 8.81E'01 2.55E 02 1.02E 02 2.08E 04 3.92E 02 0.00E 1.96E 02-I-131-5.00E 02 7.00E 02 3.76E 02 2.04E 05 1.21E 03. 0.00E-01 1.39E 02
~~
L
- I-132 2.39E 01 6.24E 01 2.24E 01
-2.10E 03 9.83E 01 0.00E 2.72E 01 I-133 1.72E 02 2.92E 02 8.89E 01 4.07E 04 5.llE 02 0.00E-01 2.21E 02 I-134 1.258 O L 3.31E 01 1.19E 01 5.51E 02 -5.22E 01 0.00E-01 4.36B h
'I-135
'5.22E 01 1.34E 02 4.98E 01 8.64E 03-2.12E 02 0.00E-01 1.49E 02 CS-134-3.10E 05 7.30E 05 3.39E 05 0.00E-01 2.32E 05 8.86E 04 9.08E 03-l l
CS-136.
3.18E 04. 1.25E 05 8.41E 04 0.00E-01 6.82E 04 1.07E 04' l.01E 04 f:
CS-137-4.15E 05 '5.52E 05 1.92E 05 0.00E-01 1.88E 05 7.30E 04 7.86E 03 CS-138 2.88E 02 5.52E 02 -2.76E 02 0.00E-01 4.08E 02 4.74E 01 2.51C L BA-139 9.10E 00 -6.40E-03 2.65E-01 0.00E-01 6.03E-03 4.41E-03 8.llE 01 I
.* 81oacetsnulation factor asstaned to be zero since no data was available.
l A-35 L
.______._-.__.,_.___,i,..,,.
TABLE A.4-2 (cont'd)
[
SITE RELATED DOSE OOWITMENT FACIOR AIT
(
MREt@lR PER UCI/ML TEM NUCLIDE BGiE LIVER T BODY THYROID KIDNEY IljNG GI-LLI BA-140 1.86E 03 2.28E 00 1.20E 02 0.00E-01 7.72E-01 1.53E 00 2.87E 03
+
.BA-141 4.39E 00 3.28E-03 1.47E-01 0.00E-01 3.04E-03 2.24E-03 9.36E-06 BA-142 1.96E 00 1.96E-03 1.20E-01 0.00E-01 1.66E-03 1.30E-03 6.0lE-12 IA-140 3.61E-01 1.77E-01 4.72E-02 0.00E-01 0.00E-01 0.00E-01 1.02E 04 IA-142 1.86E-02 8.25E-03 2.05Fe03 0.00E-01 0.00E-01 0.00E-01 2.51E 02 CE-141 7.98E-01 5.32E-01 6.12E-02 0.00E-01 2.51E-01 0.00E-01 1.52E 03 CE-143 1.41E-01 1.03E 02 1.15E-02 0.00E-01 4.60E-02 0.00E-01 3.08E 03 CE-144
- 4.17E 01-1.73E 01 2.24E 00 0.00E-01 1.03E 01 0.00E-01 1.05E 04 PR-143.
1.368 00 5.43Fe01 6.76E-02 0.00E-01 3.15E-01 0.00E-01 4.47E 03 PR-144 4.46E-03 1.83E-03 2.26E-04 0.00E-01 1.05E-03 0.00E-01 4.92E-06 ND-147 9.73E-01 1.06E 00 6.34E-02 0.00E-01 6.21E-01 0.00E-01 3.82E 03 W-187-3.28E 02 2.67E 02 9.37E 01 0.00E-01 0.00E-01 0.00E-01 7.24E 04 NP-239 1.34E-01 1.27E-02 7.04E-03 0.00E-01 3.98E-02 0.00E-01 2.04E 03 1
t A --
TABLE A.4-3 SITE RELATED DOSE COMMI'IMENT FACIOR AIT MREM /tiR PER UCI/ML CHILD NUCLIDE BCNE LIVER T BODY
'IEYROID KIDNEY IUNG GI-LLI b
H-3 0.00E-01. 1.198 01 1.19E 01 1.19E 01 1.19E 01 1.19E 01 1.19E 01 0-14 4.45E 04 8.90E 03 8.90E 03 8.90E 03 8.90E 03 8.90E 03 8.90E 03 NA-24 7.93E 02 7.93E 02 7.93E 02 7.93E 02 7.93E 02 7.93E 02 7.93E 02 l
P-32 6.49E 07 3.04E 06 2.50E 06 0.00E-01 0.00E-01 0.00E-01 1.79E 06 CR-51 0.00E-01 0.00E-01 1.92E 00 1.06E 00 2.91E-01 1.94E 00 1.02E 02 Mi-54 0.00E-01 3.998 03-1.06E 03 0.00E-01 1.12E 03 0.00E-01 3.35E 03 MN 0.00E-01 1.25E 02 2.81E 01 0.00E-01 1.51E 02 0.00E-01 1.80E 04 FE-55 1.57E 03 8.34E 02 2.59E 02 0.00E-01 0.00E-01 4.72E 02 1.55E 02 FE-59 2.26E 03 3.65E 03 1.82E 03 0.00E-01 0.00E-01 1.06E 03 3.80E 03 CCb 0.00E-01 1.75E 02 5.37E 02 0.00E-01 0.00E-01 0.00E-01 1.02E 03 C&60 0.00E-01 5.16E 02 1.52E 03 0.00E-01 0.00E-01 0.00E-01 2.86E 03 NI-63 7.36E 04 3.94E 03 2.50E 03 0.00E-01 0.00E-01 0.00E-01 2.65E 02 4
NI-65 3.04E 02 2.86E 01 1.67E 01 0.00E-01 0.00E-01 0.00E-01 3.50E 03 CU-64 0.00E-01 2.39E 01 1.44E 01 0.00E-01 5.77E 01 0.00E-01 1.12E 03 ZN-65
'2.23E 04 5.95E 04 3.70E 04 0.00E-01 3.75E 04 0.00E-01 1.05E 04 ZN-69 7.15E 01 l'.03E 02 9.54E 00 0.00E-01 6.26E 01 0.00E-01 6.51E 03 F
BR-83 0.00E-01 0.00E-01 6.64E.01 0.00E-01 0.00E-01 0.00E-01 3.89E-16 BR-84 0.00E-01 0.00E-01 7.69E 01 0.00E-01 0.00E-01 0.00E-01 3.89E-16 BR-85 0.00E-01. 0.00E-01.
3.54E 00 0.00E 0.00E-01 0.00E-01 3.89E-16
~ RIF 86
.0.00E-01 1.098 05 6.72E 04- 0.00E-01 0.00E-01 0.00E-01 7.03E 03 RB-88 0.00E-01' 3.10E 02 2.15E 02 0.00E-01 0.00E-01' O.00E-01 1.52E 01 REF-89 0.00E-01 1.91E 0'2 1.70E 02- 0.00E-01 0.00E-01 0.00E-01 1.66E 00 SR 1.08E'05.0.00E-01 3.08E 03 0.00E-01 0.00E-Ol' O.00E-01 4.18E 03 SR-90 1.398 06: 0.00E-01 3.52E 05 0.00E-01 0.00E-01 0.00E-01 1.87E 04
- SR-91 '
.1.96E 03 0.00E-01 7.41E 01 0.00E-01 0.00E-01 0.00E-01 4.33E 03-2:
-SR-92.
.7.388 02 0.00E-01.2.96E 01 0.006-01 0.00E 0.00E-01 1.40E 04 Y-90
- 3.20E 00 -0.00E-01 8.56E-02 'O.00E-01 0.00E-01 0.00E 9.10E 03 i;
Y-91M 2.97E-02 0.00E-01' l.08E-03 0.00E-01 0.00E-01
'O.00E-01 5.82E 01
.Y 4;68E 01 ~ 0.00E-01 "1.25E-02 0.00E-Ol' O.00E-01 0.00E-01 6.24E 03 Y-92 2.80E.01 0.00E-01
~ 8.01E-03 0.00E-01 0.00E-01 0.00E-01 8.09E 03 A-37
.u..
~
's 4
TABLE A.4-3 (cont'd)
~
SITE RELATED DOSE COMMI'IMENf FACIOR AIT MREWHR PER UCI/ML CHIID NUCLIDE BOiE LIVER T BODY
'IWYBOID KIMEY LUNG GI-LLI Y 8.87E-01 0.00E-01 2.44E-02 0.00E-01 0.00E-01 0.00E-01 1.32E 04 ZR-95' 7.05E 00 1.55E 00 1.38E 00 0.00E-01 2.22E 00 0.00E-01 1.62E 03 3R 4.25E-01 6.13E-02 3.62E-02 0.00E-01 8.81E-02 0.00E-01 9.29E 03 15-95 5.32E 02 2.07E 02 1.48E 02 0.00E-01 1.95E 02 0.00E-01 3.83E 05
.MD-99 0.00E-01 8.78E 02 2.17E 02 0.00E-01 1.87E 03 0.00E-01 7.26E 02 K-99M 6.46E-02 1.275-01 2.10E 00 0.00E-01 1.84E 00 6.43E-02 7.20E 01 L
i-K-101 7.48E-02 7.83E-02 9.93E-01 0.00E-01 1.34E 00 4.14E-02 2.49E-01 RU-103 4.83E 01 0.00E-01 1.85E 01 0.00E-01 1.21E 02 0.00E-01 1.25E 03 BU-105 4.26E 00 0.00E-01 1.54E 00 0.00E-01 3.74E 01 0.00E-01 2.78E 03 50-106 7.72E 02' O.00E-01 9.64E 01 0.00E-01 1.04E 03 0.00E-01 1.20E 04 JAG-110M 3.13E 01 2.12E 01 1.69E 01 0.00E-01 3.94E 01 0.00E-01 2.52E 03 TE-125M 4.25E 03 1.15E 03 5.67E 02 1.19E 03 0.00E-01 0.00E-01 4.10E 03
)
T&l27M 1.08E 04 2.90E 03 1.28E 03 2.58E 03 3.07E 04 0.00E-01 8.72E 03 TS-127 1.76E 02 4.73E 01 3.77E 01 1.22E 02 5.00E 02 0.00E 6.86E 03 TE-129M 1.82E 04 5.07E 03 1.70E 03 5.85E 03 5.33E 04 0.00E-01 2.21E 04 i-1.19E 01 3.56E 01 1.46E 02 0.00E-01 3.11E 03 TE-129 5.00E 01 1.39E 01 TS-131M 2.68E 03 9.28E 02 9.88E 02 1.91E 03 8.98E 03 0.00E-01 3.77E 04 TE-131 3.09E 01 9.43E 00 9.21E 00 2.37E 01 9.36E 01 0.00E-01 1.63E 02
' T&l32 3.77E 03 1.67E 03 2.01E 03 2.43E 03 1.55E 04
~.00E-01 1.68E 04 0
I-130 2.04E 02 4.13E 02 2.13E 02.'
4.55E 04 6.17E 02 0.00E-01 1.93E 02 I-131 1.20E 03 1.21E 03 6.88E 02 4.00E 05 1.99E 03. 0.00E-01 1.08E 02 I-132
.5.60E 01 1.03E 02 4.73E 01 4.77E 03 1.57E 02 0.00E-01 1.21E 02 I-133 4.14E 02 5.128-02 1.94E 02 9.51E 04 8.53E 02 0.00E-01 2.06E 02
- I-134
.2.938 01 5.44E 01 2.50E 01 1.25E 03 8.32E 01 0.00E-01 3.61E 01 F
LI-135 1.22E 02 2.20E 02 1.04E 02 1.95E 04 3.38E 02 0.00E-01 1.68E 02
'CS-134 3.82E 05: 6.26E 05 1.32E 05
'0.00E-01 1.94E 05 6.97E 04 3.38E 03 CS-136 3.83E 04. 1.05E 05 6.82E 04 0.00E-01 5.61E 04 8.37E 03 3.70E 03
[
CS-137 5.33E 05' 5.llE 05 7.54E 04 0.00E-01' l.66E 05 5.99E 04 3.20E 03 CS-138
- 3.72E 02 5.17E 02 3.28E 02 0.00E-01 3.64E 02 3.92E 01 2.38E 02 BA-139 2.54E 01.1.35E-02
-7.35E-01 0.00E-01 1.ISE-02 7.97E-03 1.47E 03
- Bioaccumulation factor assumed to be zero since no data was available.
TABLE A.4-3 (Accert"@
SITE RELATED DOSE CDWII2EENT TACrQR ATT b/
MREWHR PERICL/5L CHILD NUCLIDE B33E LIVER T BODY
'rsmrJTn rmmpy 2;DDE; Q-ILI W 140
'5.09E 03 4.46E 00 2.97E 02 0.0EE-el 1.4SE OB LEEE IDE 2.58E 03 W 141 1.23E 01 6.86E-03 3.99E-01 0.025-41 5.S&B-B 4 23EHB2 6.99E 00 BA-142-5.36E 00 3.85E-03 2.99E-01 0.0C5-41 3.12EHD3 2.22EHB 5.99E-02 IA-140
'7.86E-01 2.75E-01 9.26E-02 0.0tE-01 0.SOEFA1 2 arNE1 71.6EE 03 '
IA-142 4.08E-02 1.30E-02 4.07E-03 0.005-01 0.DOEFE1
<3 GDEHD1 2.5SE 03 CE-141 2.34E 00 1.17E 00 1.73E-01 0.015-41 5.11EHD1 S.SMEHD1 L46E 03 4
CE-143 4.12E-01 2.23E 02 3.24E-02 0.0M1 9.I E-D2 S 0DE-El 3.TE 03 CE-144 1.23E 02 3.84E 01 6.54E 00 0.00E-01 2.13E 01 0.DDEHB1 LODE 04 PR-143 3.06E 00 9.18E-01 1.52E-01 0.00EH01 4.97EHD1 S.DOEHal 3.3DE 03 PR-144 1.00E-02 3.10E-03 5.05E-04 0.00FA l 1.MEHII3 a.CDEHD1 6.6SE 00 ND-147 2.17E 00. 1.76E 00 1.36E-01 0.005-01 9.655-D1 S.SDEHal 2.79E 03 W-187 4.30E 02 2.55E 02 1.14E 02 0.00E-01 0.00EHD1
@.QDEHEl 3.SSE 04 NP-239 3.47E-01 2.49E-02 1.75E-02 0.00E-01 7.19EHD2
@.CDEHE1 1.34E: 43 a
l I'
(
l i
I' p-r LO A-39
_,. - _..., _ _.. _ _ _. _ _ -.. _ _.. _ _ -. - _ _ _. _. _. _ _ ~... _ _ _. _ _
1 TABLE A.4-4 3O SITE RELATED DOSE COPEEDENT FAC20R AIT MRDMIR PER II'I/E INFAART a.
IUCLIDE BCNE LIVER T BODY M
N IGDIG G-ILI
~
5-3 0.00E tl6E 01 1.16E-01 1.1E Li 1.is E Las LIE si C-14 __
8.92E 02 1.90E 02 1.90E 02 1.90E G2 L9et 92 TL*M E2 L90E 02 NA-24 3.80E 02 -3.80E 02 3.80E 02 3.BBE $2 3.aSE $2 3.3EE $2 3.30E 02 f
P-32 6.40E 04 3.76E 03 2.48E 03 0.005-01 S.SEE-M EUDDE-G 3.65E 02 CR-51 0.00E-01 0.00E-01 5.30E-01 3.465-01 7.5EEhD2 6 7Z55-G 1 54R 01 h 54 0.00E-01 7.49E 02 1.70E 02 0.005 41 L6EE 82 EUDDB-G 2.75E 02 h 56 0.00E-01 3.08E 01 5.30E 00 0.cDEHD1 2.64E @l
@.SDE-111 2.80E 03 N 55 5.23E 02 3.38E 02 9.03E 01 0.006-01 SJDDEHD1 M m' S2 4.29E 01 FE-59 1.16E 03 2.02E 03 7.98E 02 0.405-01 4.3DEHD1 iSSE 22 3.67E 02
- 00-58 0.00E-01 1.35E 02 3.38E 02 0.005-91
@.205-21 m mn4M 3.37E 02 CO-60 0.00E-01 4.06E 02 9.59E 02 0.QDEhD1 3.ODEhE
@JDDEhB1 9.67E 02 NI-63 2.39E 04 1.47E 03 8.28E 02 0.OGEHD1
@.DDEHm m.1nM-M 7.34E 01 O
NI 1.77E 02 2.00E 01 9.10E 00 0.DDEHB1 0.00EFM
@ BDEHM L52E 03 CU-64 0.00E-01 2.29E 01 1.06E 01 0.00EH01 3.87E @l
@.SDEhlli - 4.70E 02 ZN-65 6.92E 02 2.37E 03 1.09E 03 0.00EkD1 LISE (D3 S.2EEHM
- 2. DIE 03
>ZN-69 3.51E 00 6.32E 00 4.70E-01 0.006-G1 2.63E $8 EUDDE-M 5.15E 02 BR-83 0.00E-01 0.00E-01 1.37E 01 0.00EH01 0400EHD1
@.AGEHD1 3.765-17
~BR-84 0.00E-01 0.00E-01 1.44E 01 0 ODEHE 8.085-D1 a.3DEHD1 3.765-17 J
BR-85
-0.00E-01 0.00E-01 7.30E-01 0.0Ld,01 S.00EHE - S BDEHE 3.765-17
. h 86-0.00E-01 6.40E 03 3.16E 03 0.DGEHG1 4.00EHD1 SJDDEH E L64E 02 RS 0.00E-01 1.87E 01 1.03E 01 0.005-01 8.088-Q1 A.2DEHm La2E 01 1
RB-89 0.00E-01 1.08E 01 7.41E 00 0.005-01 0.30EHR SJESEHM 3.6EE 00 l
SR-89 9.44E 04 0.GOE-01 2.71E 03 0.OGEH01 0.98EHD1
@JDDEHD1 L94E 03 SR-90.
6.96E 05 0.003-01 1.77E 05 0.905-01 8.OSF-21 S.SSEHD1 S.69E 03
'SR-91 1.88E 03 0.00E-01 6.81E 00 0.095 41 0.aOIFEl
@JBDE-G ' 2 M 03 S&-92
-7.22E 02- 0.00E-01 2.68E 01 0.30EHD1 S.805-51 SJDGEH M 7.795 03 Y-90 3.27E 00 0.00E-01 8.77E-02 0.00EH81 8.BBEH E JJBDEHE 4.51E 03 t
Y-91M 3.05E-02 0.00E-01 1.04E-03 0.00EHD1
$JOSEHE
@JDDEHE L82E 02 j
Y.4.25E 01 0.00E-01 1.13E 00 0.OGEHS1 9.aSEHD1 9.2DEH R 3.95E 03 Y 2.88E-01 0.00E-Ol' 8.09E-03 0.80s-41 4.88EHD1 SJEEEHE 5.49E 03 u
l A-40
TABLE A.4-4 (cont'd) p.3 U
SITE REIATED DOSE COMMITMENT FACIOR AIT MREWHR PER UCI/ML INFANT NUCLIDE BCNE LIVER T BODY THYROID KIDNEY LUNG GI-LLI Y-93 9.14E-01 0.00E-01 2.49E-02 0.00E-01 0.00E-01 0.00E-01 7.22E 03 ZR-95 7.75E 00 1.89E 00 1.34E 00 0.00E-01 2.04E 00 0.00E-01 9.41E 02 ER-97 5.57E-01 9.56E-02 4.36E-02 0.00E-01 9.63E-02 0.005-01 6.09E 03 NS-95 1.58E 00 6.51E-01 3.76E-01 0.00E-01 4.66E-01 0.00E-01 5.49E 02 MD-99 0.00E-01 1.28E 03 2.49E 02 0.00E-01 1.01E 03 0.00E-01 4.21E 02 TC-99M 7.22E-02 1.49E-01 1.92E 00 0.00E-01 1.60E 00 7.795-02 4.33E 01 TC-101 8.54E-02 1.08E-01 1.06E 00 0.00E-01 1.28E 00 5.87E-02 1.83E 01 RD-103 5.57E 01 0.00E-01 1.86E 01 0.00E-01 1.16E 02 0.00E-01 6.77E 02 RD-105 5.12E 00 0.00E-01 1.72E 00 0.00E-01 3.76E 01 0.000-01 2.04E 03 BU-106 9.07E 02 0.00E-01 1.13E 02 0.00E-01 1.07E 03 0.00E-01 6.88E 03
.AG-110M 3.75E 01 2.73E 01 1.81E 01 0.00E-01 3.91E 01 0.00E-01 1.42E 03 TE-125M 8.77E 02 2.93E 02 1.19E 02 2.95E 02 0.00E-01 0.00E-01 4.18E 02 i
f-wg TE-127M 2.20E 03 7.30E 02 2.66E 02 6.36E 02 5.42E 03 0.00E-01 8.88E 02 TE-127 3.76E 01 1.26E 01 8.09E 00 3.06E 01 9.18E 01 0.00E-01 7.90E 02 TE-129M 3.76E 03 1.29E 03 5.79E 02 1.44E 03 9.41E 03 0.00E-01 2.25E 03 TE-129 1.07E 01 3.68E 00 2.49E 00 8.95E 00 2.66E 01 0.00E-01 8.54E 02 TE-131M 5.72E 02 2.30E 02 1.90E 02 4.66E 02 1.58E 03 0.00E-01 3.87E 03 TE-131 6.62E 00 2.45E 00 1.86E 00 5.91E 00 1.69E 01 0.00E-01 2.67E 02 TE-132 7.82E 02 3.87E 02 3.62E 02 5.72E 02 2.42E 03 0.0GE-01 1.43E 03 I-130 2.26E 02 4.97E 02 1.99E 02 5.57E 04 5.45E 02 0.00E-01 1.06E 02 I-131 1.35E 03 1.59E 03 7.00E 02 5.23E 05 1.86E 03 0.00E-01 5.68E 01 I-132 6.24E 01 1.27E 02 4.51E 01 5.94E 03 1.41E 02 0.00E-01 1.03E 02 I-133 4.70E 02 6.85E 02 2.01E 02 1.25E 05 8.05E 02 0.00E-01 1.16E 02 I-134 3.27E 01 6.70E 01 2.38E 01 1.56E"D3===7.49E 01 0.005-01 6.92E 01 I-135 1.37E 02 2.72E 02 9.93E 01 2.44E 04 3.04E 02 0.00E-01 9.86E 01 CS-134 1.42E 04 2.64E 04 2.678 03 0.00E-01 6.81E 03 2.42E 03 7.19E 01 CS-136 1.73E 03 5.08E 03 1.90E 03 0.00E-01 2.02E 03 4.14E 02 7.71E 01 CS-137 1.96E 04 2.30E 04 1.63E 03 0.00E-01 6.17E 03 2.50E 03 7.198 01 J
CS-138 1.81E 01 2.94E 01 1.43E 01 0.00E-01 1.47E 01 2.29E 00 4.70E 01 BA-139
- 3.31E 01 2.20E-02 9.59E-01 0.00E-01 1.32E-02 1.33E-02 2.10E 03
- Bioacctmulation factor asstrned to be zero since no data was available.
A-41
i TABLE A.4-4 (cont'd)
~
SITE REIATED DOSE COMMI'INENT FACIOR AIT MREW HR PER UCI/ML INFANT NUCLIDE no LIVER---
T BODY
'IHYlOID KIDNEY EOMG
'GI-LLI BA-140 6.43E 03 6.43E 00 3.31E 02 0.00E-01 1.53E 00 3.95E 40 LSBE 03 BAr-141 1.60E 01 1.09E-02 5.04E-01 0.00E-01 6.585-03 E.6EB B L95E 02 Bh-142 6.92E 00 5.76E-03 3.41E-01 0.00E-01 3.31E-03 3.aBIHEB 2.96E 01 i
IA-140 7.943-01 3.13E-01 8.058-02 0.00E-01 0.006-01 MM 3.SBE 03 IA-142 '
4.148-02 1.525-02 3'645-03 0.005-01 0.00E-01 EDDEHM 2.58E 03 CS-141 -
2.96E 00 1.81E 00 2.135-01 0.00E-01 5.57E-01 EADEHM
%33E 02 4
N' CE-143 5.57E-01 3.69E 02 4.21E-02 0.00E-01 1.08E-01 W EDEH M
'P 3 die 03 CE-144 1.12E 02 4.59E 01 6.28E 00 0.005-01 1.85E 01 1L1HNkH1 di 43E 03 PR-143 3.06E 00 1.14E 00 1.52E-01 0.00E-01 4.25E-01 EDDIHM 34d.E: 03 PR-144 1.03E-02 3.99E-03 5.19E-04 0.00E-01 1.44E-03
@.EIDEHH1 Tl_Mr D2 ND-147 2.08E 00 2.14E 00 1.31E-01 0.00E-01 8.24E-01 m mmHE1 11 M 03 W-187 3.40E 01 2.36E 01 8.16E 00 0.00E-01 0.00E-01
.n mmkgl naeR 03 i O NP-239 4.18E-01 3.74E-02 2.115-02 0.00E-01 7.45E-02
@JEEHIII LDRE 03 i
(
L-
[
l O
v l
^
t- --
w
TABLE A.5-1 INHALATION DOSE PARAMETER EVR THE CHIID, PI MREN/YR PER UCI/M3 H-3 1.12E 03 h 103 6.62E 05 C-14 3.59E 04 h 105 9.95E 04 NA-24 1.61E 04 RJ-106 1.43E 07 P-32 2.60E 06 AG-110M 5.48E 06 CR-51 1.70E 04 TS-125M 4.77E 05 4
1W-54 1.58E 06 TS-127M 1.48E 06 PN-56 1.23E 05 TE-127 5.62E 04 h 55 1.11E 05 TS-129M 1.76E 06 FE-59 1.27E 06 TS-129 2.55E 04 CD-58 1.llE 06 TFr-131M 3.08E 05 CD-60 7.07E 06 TS-131 2.05E 03 NI-63 8.21E 05 TE-132 3.77E 05 NI-65 8.40E 04 I-130 1.85E 06 G-64 3.67E 04 I-131 1.62E 07 2N-65 9.95E 05 I-132 1.94E 05 2N-69 1.02E 04 I-133 3.85E 06 BR-83 4.74E 02 I-134 5.07E 04 BR-84 5.48E 02 I-135 7.92E 05 BR-85 2.53E 01 CS-134
- 1. ole 06 W 86
.l.98E 05 G-136 1.71E 05 E 88 5.62E 02 G-137 9.07E 05 i
h 89 3.45E 02 CS-138 8.40E 02 SR-89 2.16E 06
& l39 5.77E 04
}
SR-90 1.01E 08 BA-140 1.74E 06 SR-91 1.74E 05 BA-141 2.92E 03 s
SR-92 2.42E 05
& l42 1.64E 03 Y-90 2.68E 05 IA-140 2.26E 05
'Y-91M 2.81E 03 IA-142 7.59E 04 i
Y-91 2.63E 06 CE-141 5.44E 05 Y-92 2.39E 05 CE-143 1.27E 05 Y-93 3.89E 05 CE-144-1.20E 07 ZR-95 2.23E 06 PR-143 4.33E 05 ZR-97 3.51E 05 PR-144 1.57E 03 NS-95 6.14E 05 ND-147 -
3.28E 05 M>-99 1.35E 05 W-187 9.10E 04
'IC-99M 4.81E 03 NP-239 6.40E 04 TC-101 5.85E 02 J
4 A-43
TABLE A.5-2 PAT;MAY DOSE, c'ACIORS RI NJCLIDE INHALATION GROUND GRASS GRASS VEGETATION PAT!MAY PLANE COW CXM PAIM1AY MILE MEAT B-3 1.26E 03 0.00E-01 7.63E 02 3.25E 02 2.26E 03 C-14 1.82E 04 0.00E-01 2.63E 08 2.41E 08 2.28E 08 NA-24 1.02E 04 1.19E 07 2.44E 06 1.36E-03 2.69E 05 P-32.
1.32E 06 0.00E-01 1.71E 10 4.65E 09 1.40E 09 CR-51 1.44E 04 4.66E 06 7.19E 06 1.77E 06 1.17E 07 MN-54 1.40E 06 1.39E 09 2.58E 07 2.81E 07 9.58E 08 i
MN-56 2.02E 04 9.03E 05 1.33E-01 0.00E-01 5.08E 02 FE-55 7.21E 04 0.00E-01 2.51E 07 2.93E 08 2.09E 08 FE-59 1.02E 06 2.73E 08 2.33E 08 2.08E 09 9.88E 08
- n v ;)
00-58 9.28E 05 3.79E 08 9.56E 07 3.70E 08 6.23E 08 CC 60 5.97E 06 2.15E 10 3.08E 08 1.41E 09 3.14E 09 NI-63 4.32E 05 0.00E-01 6.73E 09 1.89E 10 1.04E 10
^ONI 1.23E 04 3.02E 05 1.53E 00 0.00E-01 2.28E 02 CD-64 4.90E 04 6.07E 05 2.03E 06 2.33E-05 7.85E 05 EN-65 8.64E 05 7.46E 08 4.37E 09 1.13E 09 1.01E 09 ZN-69 9.20E 02 0.00E-01 9.99E-12 0.00E-01 1.68E-05 BR-83 2.41E 02 4.87E 03 0.00E-01 0.00E-01 4.48E 00 BR-84 3.13E 02 2.03E 05 0.00E-01 0.00E-01 2.49E-ll BR-85 1.28E 01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 RB 1.35E 05 8.99E 06 2.59E 09 4.87E 08 2.19E 08 RB '3.87E 02 3.31E 04 0.00E-01' O.00E-01 3.47E-22 RB-89 !
2.56E 02
-l.21E 05 0.00E-01 0.00E-01 1.41E-26 SR-89' l.40E 06 2.16E 04 1.45E 09 3.02E 08 9.97E 09 SR-90
' 9.92E 07 0.00E-01 4.68E 10 1.24E 10 6.05E 11 SR-91 1.91E 05 2.14E 06 1.37E 05 6.76E-10 1.44E 06
'SR-92 4.30E 04
-7.77E 05 9.70E 00 0.00E-01 8.46E 03 Y-90 5.06E 05
'4.49E 03 7.50E 05 1.13E 06 1.41E 08 Y-91M 1.92E 03 1.00E 05 1.77E-19 0.00E-01 3:
1.54E-08 p,)
(_,
Y-91~
1.70E 06 1.07E 06-4.73E 06 6.23E 08 2.81E 09 Y 7.35E 04 1.808 05 9.79E-01 0.00E-01 1.60E 04 A-44 z
TABLE A.5-2 (cont'd)
PATHWAY DOSE FACIORS RI ADULT NUCLIDE INHAIATION GROUND GRASS GRASS VEGETATION PA'ItMAY PLANE W
CCM PATIMAY MILK MEAT Y-93 4.22E 05 1.85E 05 7.398 03 2.09E-07 5.52E 06 ZR-95 1.77E 06 2.45E 08 9.59E 05 1.90E 09 1.20E 09 ZR-97 5.23E 05 2.96E 06 2.71E 04 1.30E 00 2.llE 07 NB-95 5.05E 05 1.37E 08 2.79E 08 7.76E 09 4.81E 08 MD-99 2.48E 05 3.99E 06 5.74E 07 2.32E 05 1.43E 07
~TC-99M-
~4.16E 03
~1.84E 05 5.56E 03 7.53E-18 5.19E 03 TC-101 3.99E 02 2.04E 04 0.00E-01 0.00E-01 2.16E-29 RD-103 5.05E 05 1.08E 08 1.19E 05 1.23E 10 5.56E 08 RD-105 4.82E 04 6.36E 05 5.25E-01 3.59E-25 3.30E 04
- RD-106-9.36E 06 4.21E 08 1.32E 06 1.81E 11 1.25E 10 AG-110M 4.63E 06 3.44E 09 2.20E 10 2.52E 09 3.98E 09 TS-125M 3.14E 05 1.55E 06 6.63E 07 1.46E 09 3.93E 08 O
TE-127M.
9.60E 05 9.17E 04 1.86E 08 4.53E 09 1.42E 09 i
TE-127
'5.74E 04 2.988 03 5.16E 04 1.69E-08 4.47E 05 TE-129M -
1.16E 06 1.98E 07 3.03E 08 5.71E 09 1.27E 09 TE-129
-1.94E 03 2.62E 04 1.19E-09 0.00E-01 3.22E-03 TE-13LM 5.56E 05 8.03E 06 1.75E 07 2.20E 04 4.43E 07 TE-131-1.39E 03 2.92E 04 1.61E-32 0.00E-01 6.63E-15 TE-132 5.10E 05 4.23E 06-7.35E 07 4.35E 07 1.32E 08 I-130 1.14E 06 5.51E 06 1.05E 08 5.30E-04 9.81E 07 I-131 1.19E 07 1.72E 07 1.39E 11 5.04E 09 3.79E 10 I
n;
-I-132 1.14E 05.
1.25E 06 1.54E 01 0.00E-01 5.40E 03 I-133 2.15E 06 2.45E 06 9.90E 08 9.37E 01 5.33E 08 I-134 2.98E 04_
4.47E 05 9.57E-Il 0.00E-01 4.56E-03 I-135' 4.48E 05 2.53E 06 2.22E 06 7.73E-15 6.74E 06 CS-134 8.48E 05 6.86E 09 1.35E 10 1.56E 09 1.11E 10
~CS-136 1.46E 05 1.49E 08 1.03E 09 4.66E 07 1.66E 08 i
{' / CS-138).CS-137 6.21E 05 1.03E 10 1.01E 10 1.19E 09 8.70E 09 s _,
6.21E 02 3.59E 05 1.81E-23 0.00E-01 7.78E-11
- BA-139 3.76E 03 1.06E 05 8.09E-08 0.00E-01 5.15E-02 Ar45 A
TABLE A.5-2 (cont'd) i PATHWAY DOSE FACIORS RI ADULT NUCLIDE INHALATION GROUND GRASS GRASS VEGETATION PATfMAY PLANE CDW COW PAIYMAY MIIJC MEAT BA-140 1.27E 06 2.05E 07 5.54E 07 5.92E 07 2.65E 08 BA-141 1.94E 03 4.18E 04 0.00E-01 0.00E-01 1.28E-21 BA-142 1.19E 03 4.49E 04 0.00E-01 0.00E-01 0.00E-01 IA-140 4.58E 05 1.92E 07 1.67E 05 1.39E 03 7.33E 07 IA-142 6.33E 03 7.378 05 3.12E-08 0.00S-01 4.70E-01 CE-141 3.62E 05 1.37E 07 1.2SE 07 3.63E 07 5.10E 08 CE-143 2.26E 05 2.31E 06 1.15E 06 5.56E 02 2.76E 07 CE-144 7.78E 06 6.96E 07 1.21E 08 4.93E 08 1.llE 10 PR-143 2.81E 05 0.00E-01 6.92E 05 9.19E 07 2.74E 08
-PR-144 1.02E 03 1.83E 03 0.00E-01 0.00E-01 3.13E-26 ND-147 2.21E 05 8.46E 06 5.25E 05 3.98E 07 1.87E 08 W-187 1.55E 05 2.36E 06 1.80E 06 5.93E 00 1.05E 07 4
NP-239 1.19E 05 1.71E 06 7.41E 04 5.22E 03 2.88E 07 4
)
V 4
A-46
1 TABLE A.5-3 i ~
PADMAY DOSE FN"mE 'HI s
TEEN NUCLIDE IttlALATICN GROUND GRASS GEGS T! IGE 3EI23g PADMAY PIANE CDW CDW EB2HMLY MIII MEAT
+
S 1.27E 03 0.005-01 9.9aE 22 L94E S2 T_ame m3 C 2.60E 04 0.00E-01 4.96E 08 2.94E G8 3LE9E QS Nh-24 1.38E 04 1.19E 07 4.2EE 06 2.895-A3 T ME RS i'
P-32 1.89E 06 0.005-01 3.15E 10
- 3. M 99 2.Ett 09 CR-51 2.10E 04 4.66E 06 8.39E 06 9.M OS 3.JDEE G7
' lei-54 1.98E 06 1.39E 09 2.57E 07 L44E 57 9.32E QB L
E 56 5.74E 04 9.03E 05 4.858-01 0.005,01 9.AtSE S2 FE-55 1.24E 05 0.00E-01 4.45E 07 2.30E OB
't 753E 08 FS-59 1.53E 06 2.738 08 2.86E 08 L172 49 9.3DE QS O>58 -
1.34E 06 3.79E 08 1.09E 08 L94E OB 6.21E @B CD-60 8.72E 06 2.15E 10 3.62E 00 7.60E 08 3.24E 09
-NI-63 5.80E 05 0.00E-01 1.18E 10 1.52E la L61E la i
NI-65 3.67E 04 3.02E 05 5.88E 00 0.005-01 4.47E 02 00-64 6.14E 04 6.07E 05 3.30E 06 L738-05 6.47E 05 E 65 1.248 06 7.46E 08
.7.31E 09 S.695 08 L47E 09 i -
5 69 1.588 03 0.00fb-01 3.385-11 0.005-01 2.SSEHD5 BR-83 3.44E 02 4.87E 02 0.00E-01 0.005-01 2.92E 00 1-BR-84 4.33E 02 2.03E 05 0.00E-01 0.0GC-41 2.275-21 a
BR-85 1.83E 01 0.00E-01 0.005-01 0.005-01 0.00EHD1 R
RS-86 1.90E 05 8.99E 06 4.73E 09 4.07E 08 2.74E 08
& 88 5.46E 02 3.31E 04 0.005-01 0.005-01 3.215-22 E 89 3.52E 02 1.21E 05-0.00iFC1 0.005-41 L2Eb-26 SR.-89 2.42E 06 2.16E 04 2.67E 09 2.55E 08-L51E 34 SR-90 1.08E 08 0.00E-01 6.61E 10 S.05E 09 7.51E 11 SR-91
'2.598 05 2.14E'06
'2.39E 05 5.418-18 L2BE 96 p
i SR-91' 1.19E 05 7.77E 05 2.23E el S.805-01 LalE se Y-90 5.59E 05 4.49E 03 1.97E 06 7 41E 25 LS2E SS
. n'
.{ /.
Y-91
)
Y-91M 3.20E 03 1.00E 05 5.22EHIS 4.0EIHE1 2 3DEHD7 2.94E 06 1.07E 06.
5.4ME e6 3.91E S8 3.21E 39
.Y-92 1.65E 05 1.80E 05 2.53E @s 3 20EHE1 T ME 54 A-47
. -a
=_
TABLE A.5-3 (cont'd)
PATHWAY DOSE FACIORS RI O-TEEN
-NUCLIDE INHAIATION GROUND GRASS GRASS VD3CFATICN PATHWAY PLANE COW COW PADMAY MILK MEAT Y-93 5.79E 05 1.85E 05 1.31E 04 1.70E-07 4.99E 06 ZR-95 2.69E 06 2.45E 08 1.20E 06 1.09E 09 1.25E 09 ZR-97 6.30E 05 2.96E 06 4.23E 04 9.27E-01 1.67E 07 NB-95 7.51E 05 1.37E 08 3.34E 08 4.26E 09 4.57E 08 MD-99 2.69E 05 3.99E 06 1.02E 08 1.89E 05 1.29E 07 TC-99M 6.13E 03 1.84E 05 1.06E 04 6.55E-18 5.02E 03 TG-101 6.67E 02 2.04E 04 0.00E-01 0.00E-01 2.00E-29 B0-103 7.83E 05 1.08E 08 1.51E 05 7.15E 09 5.69E 08 RD-105 9.04E 04 6.36E 05 1.27E 00 3.96E-25 4.04E 04 RD-106 1.61E 07 4.21E 08 1.80E 06 1.13E 11 1.48E 10 AG-110M 6.75E 06 3.44E 09 2.56E 10 1.35E 09 4.03E 09 TE-125M 5.36E 05 1.55E 06 8.86E 07 8.94E 08 4.38E 08
\\
/
TE-127M 1.66E 06 9.17E 04 3.42E 08 3.82E 09 2.24E 09 TE-127 8.08E 04 2.98E 03 9.35E 04 1.40E-08 4.12E 05 TE-129M 1.98E 06 1.98E 07 4.61E 08 3.97E 09 1.51E 09 TE-129 3.30E 03 2.62E 04 2.86E-09 0.00E-01 3.92E-03 TE-13LM 6.21E 05 8.03E 06 2.53E 07 1.45E 04 3.25E 07 TE-131 2.34E 03 2.92E 04 2.93E-32 0.00E-01 6.155-15 TE-132 4.63E 05 4.23E 06 8.61E 07 2.33E 07 7.84E 07 I-130 1.498 06 5.51E 06 1.74E 08 4.03E-04 8.28E 07 I-131 1.46E 07 1.72E 07 2.20E 11 3.65E 09 3.14E 10 I-132 1.51E 05 1.25E 06 2.58E 01-0.00E-01 4.59E 03 I-133 2.92E 06 2.45E 06 1.67E 09 7.26E 01 4.59E 08
'I-134 3.95E 04 4.47E 05 1.60E-10 0.00E-01 3.87E-03 I-135 6.21E 05 2.53E 06 3.78E 06 6.03E-15 5.84E 06 CS-134 1.13E 06 6.86E 09 2.31E 10 1.23E 09 1.67E 10 CS-136 1.94E 05 1.49E 08 1.75E 09 3.62E 07 1.68E 09
[
)
CS-137 8.48E 05 1.03E 10 1.78E 10 9.63E 08 1.35E 10 A _,/
CS-138 8.56E 02 3.59E 05 3.19E-23 0.00E-01 6.98E-11 s
BA-139 6.46E 03 1.06E 05 7.53E-07 0.00E-01 2.44E-01 Ar48
TABLE A.5-3 (cont'd) 4 PNIHWAY DOSE FACIORS RI TEEN NUCLIDE IttiAIATICN GROUND GRASS G %SS VEGETATICN PA29&Y PLANE CDR CDW PAINWAY MIIJC MFAT i
BA-140 2.03E 06 2.05E 07 7.48E 07 3.67E 07 2.13E 08 BA-141 3.298 03 4.18E 04 0.00S-01 0.00E-01 1.195-21 Bar-142 1.91E 03 4.49E 04 0.00E-01 0.00E-01 0.00E-01 IA-140 -
4.87E 05 1.92E 07 2.29E 05 8.72E 02 5.llE 07 IA-142 1.208 04 7.378 05 2.295-07 0.006-01 1.768 00
{
CPel41 6.148 05 1.37E 07 1.70E 07 2.25E 07 5.41E 08 i
CS-143 2.55E 05 2.31E 06 1.67E 06 3.70E 02 2.04E 07
'CS-144 1.34E 07 6.96E 07 1.66E 08 3.09E 08 1.33E 10 PR-143 4.83E 05 0.00E-01 9.55E 05 5.81E 07 2.31E 08 PR-144 1.75E 03 1.83E 03' O.00E-01 0.00E-01 2.93E-26 ND-147 3.72E 05 8.46E 06 7.15E 05 2.48E 07 1.44E 08 4
W-187-1.77E 05 2.36E 06 2.65E 06 4.00E 00 7.84E 06
' /
NP-239 1.32E 35 1.71E 06 1.06E 05 3.43E 03 2.10E 07 4
i
+
4 -
4 e
I f
O 4
A-49
d 9
TABLE A.5-4 PAniWAY DOSE FACIORS RI OIILD NUCLIDE INHAIATION GOUND GRASS GRASS VEGETATION PADMAY '
FLANE COW COW PATHWAY MIIJC MEAT H-3 1.12E 03 0.00E-01 1.57E 03 2.34E 02 4.01E 03 C-14 3.59E 04 0.00E-01 1.19E 09 3.83E 08 8.89E 08 NA-24 1.61E 04 1.19E 07 8.86E 06 1.73E-03 3.73E 05 P-32 2.60E 06 0.00E-01 7.77E 10 7.41E 09 3.37E 09
-CR-51 1.70E 04 4.66E 06 5.40E 06 4.66E 05 6.21E 06 E 54 1.58E 06 1.39E 09 2.10E 07 8.01E 06 6.65E 08 h 56' 3.23E 05 9.03E 05 1.86E 00 0.00E-01 2.72E 03 FS-55 1.llE 05 0.00E-01 1.12E 08 4.57E 08 8.00E 08 FE-59 1.27E 06 2.73E 08 2.02E 08 6.34E 08 6.69E 08 00-58 1.llE 06 3.79E 08 7.07E 07 9.58E 07 3.76E 08 CD-60 7.07E 06 2.15E 10 2.39E 08 3.84E 08 2.10E 09 NI-63 8.21E 05 0.00E-01 2.96E 10 2.91E 10 3.95E 10 NI-65 8.40E 04 3.02E 05 2.39E 01 0.00E-01 1.37E 03 CU-64 3.67E 04 6.07E 05 3.51E 06 1.41E-05 5.16E 05 ZN-65 9.95E 05 7.46E 08 1.10E 10 1.00E 09 2.16E 09 1
i ZN-69 1.02E 04 0.00E-01 2.15E-09 0.00E-01 1.38E-03 8R-83 4.74E 02 4.87E 03 0.00E-01 0.00E-01 5.38E 00 BR-84
.5.48E 02 2.03E 05 0.00E-01
.0.00E-01 3.85E-ll I
-BR-85 2.53E 01 0.00E-01 0.00E 0.00E-01 0.00E-01 6 86 1.98E 05 8.99E 06 8.77E 09 5.77E 08 4.52E 08 RS-88 5.62E 02 3.31E 04 0.00E-01 0.00E-01 4.43E-22 D 89 3.45E 02 1.21E 05 0.00E-01 0.00E-01 1.67E-26 SR-89 2.16E 06
'2.16E 04 6.62E 09 4.82E 08 3.60E 10 SR-90 1.01E 08 0.00E-01 1.12E 11 1.04E 10 1.24E 12 i
SR 1.74E 05 2.14E 06 2.85E 05 4.94E-10 1.15E 06 SR-92 2.42E 05 7.77E 05 4.15E 01 0.006-01 1.38E 04
.Y-90 2.68E 05 4.49E 03 9.15E 05 4.84E 05 6.56E 07 JO 1 Y-91M 2.81E 03 1.00E 05 5.29E-16 0.00E-01 1.75E-05
.Y-91 2.63E 06 1.07E 06 5.20E 06
'2.40E 08 2.48E 09
" Y-92 2.39E 05 1.80E 05 7.33E 00-0.00E-01 4.58E 04 L
A-50
TABLE A.5-4 (cont'd)
PATHWAY DOSE FACIORS RI O
CHIID MJCLIDE INHAIATICN GROUND GRASS GRASS VEGETATIOi PA'1900f-PIANE CXM 00W PATHWAY MIIK MEAT Y-93 3.89E 05 1.85E 05 1.57E 04 1.56E-07 4.48E 06 l
ZR-95 2.23E 06 2.45E 08 8.79E 05 6.llE 08 8.85E 08
~
ZR-97 3.51E 05 2.96E 06 4.20E 04 7.055-01 1.25E 07 NB-95 6.14E 05 1.37E 08 2.29E 08 2.23E 09 2.96E 08 5 99 1.35E 05 3.99E 06 1.74E 08 2.45E 05 1.65E 07 TC-99M 4.81E 03 1.84E 05 1.48E 04 7.00E-18 5.26E 03 i
TC-101 5.85E 02 2.04E 04 0.00E-01 0.00E-01 2.55E-29 D 103 6.62E 05 1.08E 08 1.llE 05 4.00E 09 3.96E 08 NJ-105 9.95E 04 6.36E 05 2.50E 00 5.98E-25 5.99E 04 l
5 106 1.43E 07 4.21E 08 1.44E 06 5.90E 10 1.16E 10 AG-110M 5.48E 06 3.44E 09 1.68E 10 6.74E 08 2.58E 09 TE-125M 4.77E 05 1.55E 06 7.38E 07 S.69E 08 3.51E 08 4
1 TE-127M 1.48E 06 9.17E 04 5.93E 08 5.06E 09 3.77E 09 TE-127
- 5.62E 04 2.988 03 1.16E 05 1.33E-08 3.85E 05 TE-129M 1.76E 06 1.98E 07 7.97E 08 5.26E 09 2.47E 09 TE-129 2.55E 04 2.62E 04 8.03E-08 0.00E-01 8.25E-02 TS-131M 3.088 05 8.03E 06 2.24E 07 9.84E 03 2.16E 07 TFel31 2.05E 03 2.92E 04 8.64E-32 0.00E-01 1.36E-14 TS-132 3.77E 05 4.23E 06 4.57E 07 9.46E 06 3.12E 07 I-130 1.85E 06 5.51E 06 3.85E 08 6.80Fe04 1.37E 08
-I-131 1.62E 07 1.72E 07 4.33E 11 5.51E 09 4.76E 10 I-132 1.94E 05 1.2SE 06 5.89E 01 0.005-01 7.87E 03 I-133 3.85E 06 2.45E 06 3.95E 09 1.31E 02 8.12E 08 I-134 5.07E 04 4.47E 05 3.65E-10 0.00E-01 6.65E-03 I-135 7.92E 05 2.53E 06 8.62E 06 1.058-14 9.98E 06'
- CS-134 1.01E 06 6.86E 09 3.72E 10.
1.51E 09 2.63E 10 CS-136 1.71E 05 1.49E 08 2.76E 09 4.36E 07 2.21E 08 CS-137 9.07E 05 1.03E 10 3.22E 10 1.33E 09 2.398 10 Cfr138-8.40E 02 3.59E 05 5.60E-23 0.00Fe01 9.20E-ll BA-139 5.77E 04 1.06E 05 1.20E-05 0.00E-01 2.91E 00 A-51
[
,w---.,p.4--
g-.g,r.=
, - -m-e,-_m.---
--n,,e.,mng,.,-wwe,-rwe,m,+a.~r-,w-,-wm
.w.,,w.+
e
-ow,,,e-,,
w' TABLE A.5-4 (cont'd)
PATHWAY DOSE FACIORS RI
, f CHILD MJCLIDE INHALATION GROUND GRASS GRASS VEXIETATION PA'IEWAY PLANE CKM
(%M PA'HMAY MIM MEAT W 140 1.74E 06 2.05E 07 1.17E 08 4.39E 07 2.77E 08 Bh-141 2.92E 03 4.18E 04 0.00E-01 0.00E-01 2.20E-21 h l42 1.64E 03 4.49E 04 0.00E-01 0.00E-01 0.00E-01 IA-140 2.26E 05 1.92E 07 1.898 05 5.51E 02 3.17E 07 IA-142 7.598 04 7.37E 05 2.58Fe06 0.006-01 1.49E 01 CE-lal-5.44E 05 1.37E 07 1.36E 07 1.38E 07 4.08E 08 CS-143 1.27E 05 2.31E 06 1.49E 06 2.52E 02 1.36E 07 CE-144 1.20E 07 6.96E 07 1.33E 08 1.89E 08 1.04E 10 PR-143 4.33E 05 0.00S-01 7.75E 05 3.60E 07 1.57E 08 PR-144 1.57E 03 1.83E 03 0.00E-01 0.00E-01 3.62E-23 ND-147 3.28E 05 8.46E 06 5.73E 05 1.52E 07 9.29E 07 i
E-187 9.10E 04 2.36E 06 2.42E 06 2.80E 00 5.38E G6 3
NP-239 6.40E 04 1.71E 06 9.16E 04 2.26E 03 1.36E 07 I
fH
.r i
J O
4 A,~
~
TABLE A.5-5 PATHWAY DOSE FACIORS RI INFANP A
NUCLIDE INHA[ATION GIOUND GRASS GRASS VEGEFATION PATIMAY PLANE CDW COW PADMAY MIM MEAT H-3 6.47E 02 0.00E-01 2.38E 03 0.00E-01 0.00E-01
[
- C-14 2.65E 04 0.00E-01 2.34E 09 0.00E-01 0.00E-01 Nh-24 1.06E 04 1.19E 07 1.54E 07 0.00E-01 0.00E-01
.P-32 2.03E 06 0.00E-01 1.60E 11 0.00E-01 0.COE-01 CR-51 1.28E 04 4.66E 06 4.70E 06 0.00E-01 0.00E-01 25-54 1.00E 06 1.39E 09 3.90E 07 0.00E-01 0.00E-01 MS-56 7.17E 04 9.03E 05 2.86E 00 0.00E-01 0.00E-01
-FE-55 8.69E 04 0.00E-01 1.35E 08 0.00E-01 0.00E-01
'FE-59 1.02E 06 2.73E 08 3.92E 08 0.00E-01 0.00E-01 00-58 7.77E 05~
3.79E 08 6.05E 07 0.00E-01 0.00E-01 00-60 4.51E 06 2.15E 10 2.10E 08 0.00E-01 0.00E-01 NI-63 3.39E 05 0.00E-01 3.49E 10 0.00E-01 0.00E-01 NI-65 5.01E 04 3.02E 05 3.78E 01 0.00E-01 0.00E-01
.CD-64 1.50E 04 f.07E 05 3.81E 06 0.00E-01 0.00E-01
~ZN-65
'6.47E 05 7.46E 08 1.90E 10 0.00E-01 0.00E-01 ZN-69 1.32E 04 0.00E 7.40E-09 0.00E-01 0.00E-01 BR-83 3.81E 02 4.87E 03 0.00E-01 0.00E-01 0.00E-01 SBR-84 4.00E 02-2.03E 05 0.00E-01 0.002-01 0.0CS-01
' BR-85 2.04E Ol' O.00E-01 0.00E-01 0.00E-01 0.00E-01 RB 1.90E 05 8.99E 06 2.23E 10 0.00E-01 0.00E-01 h 88 5.57E 02 3.31E 04 0.00E-01 0.00E-01 0.00E-01 R
6 89 3.21E 02 1.21E 05
'O.00E 0.00E-01!
0.00E-01 SR-89 2.03E 06 2.16E 04 1.26E 10 0.00E-01 0.00E-01 SR-90 4.09E 07 0.00E 1.22E 11 0.00E-01 0.00E-01
>SR-91 7.34E 04 2.14E 06 3.19E 05.
0.00E-01
~ 0.00E-01 SR-92 1.40E 05 7.77E 05 5.02E 01 0.00E-01 0.00E-01
.Y-90' 2.69E 05 4.49E 03 9.39E 05
.0.00E-01 0.00E-01 Y-91M-L2.79E 03-1.00E 05 1.91E-15
'O.00E-01
.0.00E-01.
j Y-91 2.45E 06 1.07E 06 5.25E 06 0.00E-01 0.00E-01~
b 7 "Y-92L 1.27E 05 1.80E 05 1.03E 01 0.00E-01 0.00E-01 A-53 ea
. - ~...
A TABLE A.5-5 (cont'd)
PATHWAY DOSE FACIORS RI INFANT NUCLIDE INHAEATICN GROUND GRASS GRASS VEGETATIW PADMAY PLANE COW OJW PAUMAY MIM MEAT Y-93 1.67E 05 1.85E 05 1.78E 04 0.00E-01 0.00E-01 1R-95' l.75E 06 2.45E 08 8.26E 05 0.00E-01 0.00E-01 ER-97 1.40E 05 2.96E 06 4.45E 04 0.00E-01 0.00E-01 h 95 4.79E 05 1.37E 08 2.06E 08 0.00E-01 0.00E-01 MD-99 1.35E 05 3.99E 06 3.11E 08 0.00E-01 0.00E-01 1C-99M 2.03E 03 1.84E 05 1.65E 04 0.00E-01 0.00Fe01 TC-101 8.44E 02 2.04E 04 0.00E-01 0.00E-01 0.00E-01 D 103 5.52E 05 1.08E 08 1.05E 05 0.00E-01 0.00E-01
- h l05 4.84E 04 6.36E 05 3.21E 00 0.00E-01 0.00E-01
~ h 106 1.16E 07 4.21E 08 1.44E 06 0.00E-01 0.00E-01
~AG-110M 3.67E 06 3.44E 09 1.46E 10 0.00E-01 0.00E-01
-TE-125M 4.47E 05 1.55E 06 1.51E 08 0.00E-01 0.00E-01 TE-127M 1.31E 06 9.17E 04 1.04E 09 0.00E-01 0.00E-01 TS-127 2.44E 04 2.98E 03 1.33E 05 0.00E-01 0.00E-01 TS-129M -
-1.68E 06 1.98E 07 1.39E 09 0.00E-01 0.00E-01
'TE-129 2.63E 04-2.62E 04
'2.19E-07 0.00E-01 0.00E-01 TE-131M
.1.99E 05 8.03E 06 2.29E 07 0.00E-01 0.00E-01
.TE-131, 8.22E 03 2.92E 04 1.41E-30 0.00E-01 0.00E-01 l
h TE-132
~3.40E 05 4.23E 06 6.53E 07 0.00E-01 0.00E-01 L
I-130 1.60E 06~
5.51E 06 8.76E 08 0.00E-01 0.00E-01 l
I-131 1.48E 07 1.72E 07 1.05E 12 0.00E-01 0.00E-01
.1
~I-132 ~
1.69E 05 1.25E 06 1.37E'02 0.00E-01 0.00E-01 I-133 3.56E 06 2.45E 06 9.61E 09 0.00E-01 0.00E-01' I-134 4.45E 04 4.47E 05' 8.47E-10 0.00E-01 0.00E-01 s
1
-I-135
~6.96E 05' 2.53E 06' 2.00E 07~
0.00E-01 0.00E-01
.CS-134
~7.03E 05
.6.86E 09 6.80E 10 0.00E-01 0.00E-01 CS-136 1.35E 05-1.49E 08 5.76E'09-
-0.00E-01 0.00E-01 b
l1
.. (5-17
,6.12E 05.
1.03E 10 6.02E 10 0.00E-01
'0.00E-01
\\
CS-138.
8.76E 02 3.59E 05 2.21E-22 0.00E-01' O.00E-01 N
.BA-139 5.10E 04.
1.06E 05 2.80E-05 0.00E-01 0.00E-01 l
[
- A-54_
TABLE A.5-5 (cont'd) i PATHWAY DOSE FACIORS RI INFANT MJCLIDE INHALATICN CIOUND GRASS GRASS VEGEPATICN PADMAY PLANE COW COW PATHWAY MIIJC MEAT BA-140-1.60E 06 2.05E 07 2.41E 08 0.00E-01 0.00E-01 BA-141' 4.75E 03 4.18E 04 0.005-01 0.00E-01 0.00E-01
' p l42 1.55E 03 4.49E 04 0.00E-01 0.00E-01 0.00E-01 s
IA-140 1.68E 05 1.92E 07 1.88E 05 0.00E-01 0.00E-01 IA-142 5.958 04 7.37E 05 5.36Fe06 0.00E-01 0.00Fe01
'CE-141 5.17E 05 1.37E 07 1.37E 07 0.00E-01 0.00E-01 CE-143 1.16E 05 2.31E 06 1.54E 06 0.00E-01 0.00E-01
.CE-144 9.84E 06 6.96E 07 1.33E 08 0.00S-01 0.00E-01 PR-143
.4.33E 05 0.00E-01 7.84S 05 0.00E-01 0.00E-01 PR-144 4.28E 03 1.83E 03 0.00E-01 0.00E-01 0.00E-01 i
ND-147 3.22E 05 8.46E 06 5.77E 05 0.00E-01 0.00E-01
.W-187 3.96E 04 2.36E 06 2.50E 06 0.00E-01 0.00E-01 I
NP-239 5.95E 04 1.71E 06 9.43E 04 0.00E-01 0.00E-01 i
F e
N.J.
d A-55
-. - - - - -. - - - - - - - - - - ~ ~ - - - - - - - - ~ ~ ~
Appendix B Meteorological Model i
l l
l l-I i
t
+
i l
ODCM B-1 12-20-84 l
' O APPENDIX B PROPRIETARY INFORMATION SUPPLIED BY SAI The X/Q's and D/Q's are calculated using the guidance of Reg. Guide 1.111 The constant mean wind direction model, as defined in equation 3 of Reg. Guide 1.111, is used to calculate X/Q values.
2.032fn)exp[-hj/2({j(x)]
g NxUi
)
(x) l Where:
he =
Ef fective release height (m).-
(All releases from Wolf Creek Generating Station are considered as ground releases therefore h,= 0.)
Hours of valid data for weather conditions in nij =
given direction, windspeed class i, and atmospheric stability class j.
N=
Total hours of valid data Ui=
Midpoint of windspeed class (m/s) 4x =
Distance downwind (m)
Vertical plume spread without volumetric correction (x)
=
z at distance x and stability class j.
See Figure C.1 L(x)
Vertical plume spread with volumetric correction
=
zj for release within buildings wake cavity,_at distance x and stability class j.
1 (x). is the lesser of For ground level releases zj 2
([,3(x) + 0.5D /
) 1/2 or N
zj I*I O
where Dz =
Maximum adjacent building height either up-or down-wind from the
)
release point ODCM' B2 12-20-84
2.032 = (2/r ) 1/2 divided by width, in radians, of a 22.5 sector (X/Q)D = Average effluent concentration, X, normalized to source strength, Q, at distance x in sector D.
For WCGS the above Meteorological Model will simplify to the following equation for X/Q:
(X/Q)o =
s (x)
NUi x ij The calculation of the relative deposition per unis area, D/Q, is performed using the deposition rate graphs found in Reg. Guide 1.111.
For a 22.5 sector, since the effluent concentration is assumed uniform across the sector, the relative deposition per unit area is assumed uniform across the sector.
The calculation of D/Q is determined from relative deposi-tion by the following relationship:
[
-\\
Dij(x)
DEPLij(x)
D/Q =
(2'V/16) x Where:
D j(x)
Relative deposition rate for windspeed class
=
i i and stability class j at downwind distance L
x (1/m).
(2 ' 16) x 7/
Length of arc across sector at downwind
=
distance x (m).
L D/Q Relative deposition per unit area (m).
=
DEPLij(x)
. Reduction factor due to plume depletion at
=
distance x for windspeed i and stability class l
j.
1 (m) i ODCM.
B-3 12-20-84
1000 i, -
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1 0.1 1.0 10 100 PLUME TRAVEL DISTANCE (KILOMETERS) r
- Figure 1. Vertical Standard Devi tion of Materialin a Plume (Letters denote Pasquill Stability Class)
NOTE: THESE ARE STANDARD RELATIONSHIPS AND MAY HAVE TO DE j-M001FIED FOR CERTAIN TYPES OF TERRAIN AND/OR CLIMATIC CONDITIONS (E.G., VALLEY, DESERT, OVER WATERI.
3 J (v l
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'ODCM B-4 12-20-84
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B-5 12-20-84 i.
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d (v'
10-3 i
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104 N-
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e s
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,m Ift,k
.ODCM B-6 12-20-84
. ~, -,
- -. -.