ML20080R054
| ML20080R054 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 01/31/1984 |
| From: | KANSAS GAS & ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20080R053 | List: |
| References | |
| PROC-840131, NUDOCS 8402280062 | |
| Download: ML20080R054 (105) | |
Text
,,
i^
- O e-t OFFSITE DOSE CALCULATION MANUAL for Kansas Gas and Electric Wolf Creek Generating Station 8402280062 840224 PDR ADOCK 05000482 A
?
o TABLE OF CONTENTS Page 1.0 Introduction 1
2.0
-Liquid Ef fluents 1
2.1 Liquid Effluent Monitor Setpoints 1
2.2 Liquid Effluent 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 Ef fluent Monitors 11 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 Effluent Monitors 30 4.0 Radiological Environmental Monitoring Program 33 5.0 40 CFR 190 Dose Evaluation 38 Appendix A:
Dose Conversion Factor Tables A-1 Appendix B:
Accident Doses B-1 Appendix C:
Meteorological Model C-1
?
LIST OF TABLES Table Pace 4-1 Radiological Environmental Monitoring Program 23 4-2 Sampling Location Numbers, Distance (miles) and Directions 26 A.1-1 Bioaccumulation Factors to be Used in the Absence A-2 of Site Specific Data A.1-2
- Dose Factors for Noble Gases A-3 A.2-1 Inhalation Dose Factors for Adults A-4 A.2-2 Inhalation Dose Factors for Teenagers A-7 A.2-3 Inhalation Dose Factors for Child A-10 A.2-4 Inhalation Dose Factors for Infant A-13 A.2-5 External Dose Factor for Standing on A-16 Contaminated Ground A.3-1 Ingestion Dose Factor for Adults A-18 A.3-2 Ingestion Dose Factor for Teenagers A-21 A.3-3 Ingestion Dose Factor for Child A-24 A.3-4 Ingestion Dose Factor for Infant A-27 A.3-5 Stable Element Transfer Data A-30 A.4-1 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 Ry Dose Factors for Adult A-44 A.5-3 RI Dose Factors for Teenager A-47 A.5-4 Ry Dose Factors for Child A-50 A.5-5 RI Dose Factors for Infant A-53
-ii-
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)
l'0 INTRODUCTION The Offsite Dose Calculation Manual (ODCM) describes the methodology and 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 Ef fluent 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 gaseoun effluent monitor alarm / trip setpoints to assure compliance with the concentration and dose limitations of the Radiological Effluent Technical Specifications.
The ODCM provides the Radiological Environmental Monitoring Program..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.
The ODCM also provides a description of the methods used to calculate of fsite doses in -the event of an emergency.
2.0
. LIQUID EFFLUENTS 2.1 LIQUID EFFLUENT MONITOR SETPOINTS The alarm / trip setpoints for the liquid effluent radiation monitors are based on the instantaneous concentration limits of 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 ex ceeded..Auditable records shall be maintained indicating the actual setpoints used at all times.
ODCM-1 01-31-84 1
J s-LThe calculated alarm and trip action setpoints for the liquid
.. effluent line monitors must satisfy the following equation:
cf F+f
~<C Where:
C = The liquid effluent concentration limit (MPC) implementing Radiological-Effluent Technical Specification 3.11.1.1 in uCi/ml.
c.= The setpoint, in pCi/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.
f = The pump flow rate as measured at the radiation imonitor-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)
(pCi/ml) f ODCM 2
01-31-84 he alia am neums ii im i mm i iiu-i i- -
9 a
2.1.1 CONTINUOUS LIQUID EFFLUENT MONITORS The two monitors associated with continuous liquid releases are listed below:
Monitor IL 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 conservatively based on I-131, the most restrictive isotope expected to be present.
This is particularly appropriate for the turbine building drain line monitor since the most probable source is the secondary steam system which is expected to have negligible activity unless there is a significant primary to secondary leak.
Due to changing activities, it will not be possible to select a radionuclide distribution on which to base the monitor setpoint.
Additionally, maximum ef fluent rlows and
~
minimum dilution flows will normally be assumed.
The High Alarm / Trip Setpoint will be set to correspond to the I-131 MPC limit at the boundary of the restricted area from 10 CFR Part 20, Appendix B, Table II, Column 2.
The alert alarm is set one order of magnitude below the high alarm / trip setpoint.
This high alarm / trip setpoint assures the limits of Specification 3.11.1.1 are not exceeded at the boundary of the restricted area.
In the event that an alarm is tripped, an evaluation of the system will be made by taking an actual isotopic and flow analysis of the discharge.
The above continuous liquid effluents are not radioactive effluents until activity has been detected by the liquid effluent monitor, a tritium analysis of the secondary system, or a gross beta analysis of the secondary system.
At that time an analysis of the effluent will be made to verify activity in the system effluent.
ODCM 3
01-31-84
t-e 2.1.1.1 STEAM GENERATOR BLOWDOWN DISCHARGE MONITOR Fm+ Pn SETPOINT (,Ci/ml) = MPC -131 X I
- where, MPC -131 = Maximum Permissible Concentration of I
I-131, 3.0 E-7 aci/ml.
j Fm-
= Dilution flow rate.
= Blowdown flow rate.
The setpoint calculation is baced on the minimum dilution flow rate, the maximum possible blowdown flow rate, and, due to changing conditions, I-131 which is the most restrictive isotope
~
expected-to be present.
On the event that an alarm is reached, the setpoint will be re-evaluated using the actual dilution flow rate, the actual blowdown flow rate, and the actual isotopic analysis as outl 9d 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 isotope.
2.1.1.2 TURBINE BUILDING DRAIM MONITOR Fm+ Fm Setpoint (gCi/ml) = MPC -131 X I
FT
- where, MPC -131 = 3.0 E-7 uCi/ml.
I j
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 t'ne actual dilution flow rate, the actual-Turbine Building drain flow rate, and the actual isotopic analysis as outlined in
- Section 2.1.2.
The setpoint will still be based on the MPC of I-131 due to the changing conditions of activity and I-131 being the most restrictive isotope.
ODCM 4
01-31-84
7 2.1.2 BATCH RADIOACTIVE LIQUID EFFLUENT MONITOR The two monitors associated with liquid batch releases are listed below:
Monitor ID Description O-HP-RE-45 Secondary Liquid Waste System Monitor O-HB-RE-18 Liquid Radwaste Discharge Monitor The setpoint is a function of dilution flow rate, tank flow rate, and isotopic composition.
A laboratory isotopic analysis is made of each batch prior to discharge.
Based on the isotopic analysis and existing flow condition, the setpoint will be calculated and set on the appropriate monitor to ensure the concentration limits of 10 CFR 20, Appendix B, Table II, Column 2 are not exceeded.
The setpoints are determined using the following methodology:
1)
Determine concentrations of radioactivity of the batch being 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 Ef fluent Technical Specifications.
ECi=
[C+Ca+Cs+Ct+Cg g
i g
Where:
Ci The concentration of nuclide i as determined by the analysis
=
of the waste sample.
The sum of the concentrations C of each measured C
=
g g
gamma emitting nuclide observed by gamma-ray spectros-copy of the waste sample.
The measured concentration Ca of alpha emitting
- C
=
a nuclides observed by gross alpha analysis of the monthly composite sample.
The measured concentrations of Sr-89 and Sr-90 in
- Cs
=
liquid waste as determined by analysis of the quarterly composite sample.
.ODCM' 5
01-31-84
1 4
2 The measured concentration of H-3 in liquid waste as
- Ct
=
determined by analysis of the monthly composite.
- Cf The measured concentration of Fe-55 in licuid waste as
=
determined by analysis of the quarterly composite.
- Values for these concentrations will be based on prev'ious composite sample analysis as required by Table 4.11-1 of the Radiological Ef fluent Technical Specifi-cations.
4 2)
The measured radionuclide concentrations are used to calculate a dilution factor, Fa, which is the ratio of total dilution flow rate to tank f1 0w rate required to assure that the limiting concentrations of Technical Specification 3.11.1.1 are met at the point of discharge.
This is referred to as the required dilution factor and is determined according to:
Fd" I _.C_i_
) xPs (i MPCi
)
Where:
and Measured concentrations of Cg,Ca, Cs, Ct Ci
=
Cf, as defined in Step 1.
Terms Ca, Cs, Ct and Cf, will be included in the calculation as appropriate.
MPCg, MPCa, MPCs, MPCt and MPCg, are limiting MPCi
=
concentrations of the appropriate radionuclide from 10CFR20, Appendix B, Table II, Column 2.
For dissolved or entrained noble gases, the concentration shall be limited ?.o 2.0E-04, pCi/ml total activity.
o the safety factor; a conservative factor used to F
=
s compensate for statistical fluctuations and errors of measurement default value is 1.0 3)
Fo': the case Fd f 1, the waste tank effluent concentration meets the limits of 10CFR20 without dilution and the effluent may be released at any desired flow rate.
For the case Pd> 1a a modified dilution factor, F n, must be determined so that d
available. dilution flow may be apportioned among simultaneous discharge pathways.
ODCM 6
01-31-84
--__----__________0
(
'f
,s i
Fdn = Fg Fa Where.F is the. allocation factor which will modify the a
required dilution factor so that simultaneous liquid releases may be made without exceeding 10CFR20 limits.
The most straight-forward. determination of allocation factor is Fa " 1/D 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 br*.ch release source, it.is acceptable to allocate smaller portions of the dilution stream to the continuous releases and a larger portion to.the batch releases.
Therefore, F is defined. as a flexible quantity with a a
default value of 1/n.
Prior to initiating simultaneous release, a check will;be made to assure that the sum of the allocation factors assigned to pathways for the simultaneous release is-< 1.
4)
The calculated maximum permissible: waste tank ef fluent flow rate, Fmax, is based on the modified dilution factor, Fdn, and the effective dilution flow rate, Feff.
The cooling lake into which the effluent is discharged is also the source of the dilution stream.
It is therefore necessary to take into accoant the recirculatien 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 = Fm [1 - [ LCi
]
[
i MPCi) oDCM 7
01-31-84 v-
?
o Where:
The expected minimum dilution water flow rate.
F
=
m LCi Measured concentration of nuclide i in the cooling
=
lake water sample.
MPCi Limiting concentration of radionuclide i from 10CFR20
=
Append ix B, Table II, Column 2.
For the purpose of setpoint calculations the expected minimum di1ution flow rate ia assigned a value based upon the type and number of pumps running into the circulating water piping.
Itaving established the values of Fdn and Fegg, the calculated maximum permissible waste tank flow rate is given by f ax < Forp +
fn Forf for fp << F gg e
m fn Fdn d
Where f is the expected effluent flow rate; normally the p
rated capacity of the effluent pump.
Thus the pump flow rate is set at or below f Even though the value of f max.
max may be larger than the actual effluent pump capacity, f,
p it does represent the upper limit to the effluent flow rate, whereby the requirement of 10CFR20 may still be met.
If Fd
< 1, the ef fluent pump flow rate may be assigned any value 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 min' ium flow rate is administratively set.
5)
The liquid radiation monitor setpoint may now be determined based on the values of 4 C i and f The monitor response is primarily td gam,ma radiation, therefore, the actual max.
setpoint is based on E C The calculated monitor setpoint g.
concentration is deteEmined as follows:
c=A C
(pCi/ml) g g
ODCM 8
01-31-84
r Wh ere :
Adjustment factor which will allow the setpoint to be A
=
established in a practical manner for convenience and to prevent spurious alarms.
Emnx fp If A > 1, Calculate c and determine the maximum value for the actual monitor setpoint (pci/ml).
If A < 1, No release may be made.
If Fd < 1, no further dilution is reauired 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 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 EFFLUENT CONCENTRATION - COMPLIANCE WITH 10 CFR 20 Specification 3.11.1.1 reauires that the radioactive material released in liauid effluents to unrestricted areas shall be limited to:
a.
The concentrations specified in 10 CPR 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 uCi/ml total j
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 assurance that the liquid concentration limits are not exceeded.
ODCM 9
01-31-84
)
9 2.3 RADIOACTIVE LIQUID EFFLUENT DOSES - COMPLIANCE WITH 10 CFR 50, Appendix I Specification 3.11.1.2 requires that the dose to an individual from radioactive materials in liquid effluents released to unrestricted areas shall be limited to:
a.
During any calendar quarter to less than or eaual to 1.5 mrem to the total body and to less than or eaual 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 ecual to 10 mrem to any organ.
To show compliance with this specification, cumulative dose contributions from actual liquid ef fluents will be determined using the following methodology:
m DT" i (AiT [3 at CnF) i L
t n=1
- where, DT
= the cumulative dose commitment to the total body or any organ, T, from the liquid offluent for the total m
time period {'
A t g
L, in mrem.
AtL
= the length of the Lth time pericd over which C n i
and FL are averaged for all liquid releases, in hours.
Cin = the average concentration of radionuclide, 'i', in undiluted liquid effluent flow during time period t
in jaCi/ml g,
FL
= the near field average dilution factor for Cin during any liquid effluent release where:
f FL=
(F) K Where:
f = Liquid Radioactive Waste Flow CDCM 10 01-31-84 1
__________________________________b
i h
F = Discharge Structure Exit Flow, the sum of the release and dilution flow.
K = Applicable f actor; 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 uci/ml.
j See Tables A.4-1 through A.4-4.
AiT = 1.14E5 (Uw/DW + Up.BF ) DFi i
- where, DW
= Dilution factor from the near field area to the potable water intake for water consumption, for Wolf Creek Generating Station this factor is 1 (one).
BFi
= Bioaccumulation factor for radionuclide, 'i', in fish, pCi/Kg per pCi/1, from Tcble A.1-1 from Regulatory Guide 1.109 (Rev. 1)
DFi
= Dose Conversion f actor for radionuclide, 'i',
in mrem /pci, from Table 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.
6 3
1.14E5 = units conversion factor = 10 pC!./p.Ci X 10 ml/Kg 8760 hr/yr The dose calculations are based on the actual isotopic analysis of the radioactive liquid effluents, the radioactive liquid effluent flow, and the dilution flow.
ODCM 11 01-31-84
r 2.4 CALIBRATION OF LIQUID EFFLUENT MONITORS
.The - four monitors associated with liquid releases are listed below
. Monitor ID Description O-BM-RE-52 Steam Generator Blowdown Discharge Monitor 0-LE-RE-59 Turbine Building Drain Monitor S
O-HF-RE-45 Secondary Liquid Waste System Monitor 0-HB-RE-18 Liquid Radwaste Discharge 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.
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/ce, 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 nCi Cs-137 checksource shall be actuated.
The counts por minute produced by the check-source shall be logged.
-3.0 GASEOUS EFFLUENTS 3.1 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 3.11.2.1-states that the dose rate due to radioactive materials released in gaseous effluents from the site shall be limited to less 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, aDDCM 12
.01-31-84
s m
s A
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.
The Radwaste Building Vent is the release point for Maste Gas Decay Tanks cnd the Radwaste Building Ventilation System.-
Waste Gas Decay Tank releases and Containment Buildine 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'n.onitors and the Plant Unit Vent Monitor.
N Monitor identifications are as follows:
Monitor ID
' Release Point Description 0-GT-RE 21 A and B Unit Vent (fuel / auxiliary building, access control area, containment purge, condenser air discharge) 0-GH-RE-10 A and 3 Radwaste Building Vent (Radwaste building, waste gas decay tank discharge.
Acts to isolate Waste Gas Decay Tank discharge) 0-GT-RE-22&33 Containment Purge System Monitor (acts to isolate the purge; is not an effluent monitor)
O-GT-RE-31&32 Containment Atmosphere Monitor (acts to isolate purge; not an effluent monitor)
The setpoint for monitors may be determined either based on total body dose or skin dose rate.
The dose rate limits are for dose rates at the unrestricted area boundary.
The monitor setpoint is the lesser of the total body dose rate or skin dose rate.
ODCM 13 01-31-84
I, 3.1.2 TOTAL BODY DOSE BATE SETPOINT CALCULATION The li. nit of the total body dose rate is 500 mrem /yr at the unrestric-ted area boundary.
The monitor alarm / trip setpoint based on total body dose will be calculated as follows:
Stb i
(SF x AF) xDtb x Rt (1) where:
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 year period.
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 PSAR Table 11.1-1).
If necessary the 0.85 can be further modified to compensate for statistical fluctuations and errors of measurement.
Allocation 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 all release points includ ing release under consideration Rt monitor response per mrem /yr to the total body,
=
determined according to:
C Rt" ( (X/Q) g Ki Qi )
1 ODCM 14 01-31-84 u-
where:
The monitor response to the gaseous effluent noble gas c
=
corresponding to grab sample radionuclide concentrations.
The highest calculated annual average atmospheric dispersion (X/Q)
=
(sec/m ) at or beyond the unrestricted area boundary.
(
The total body dose factor due to gamma emissions from Ki
=
isotope i (mrem /yr per DCi/m3) from Table A.1-2.
Rate of release of noble gas radionuclide 1 (pCi/sec)
Qi
=
Iconcentration of radionuclide i x release flow rate) 3.1.3 SKIN DOSE RATE CALCULATION The limit of the skin dose rate is 3000 mrem /yr at the restricted area boundary.
The monitor alarm / trip setpoint is calculated as follows:
Ss I
(SF x AF) x Ds x Rs (2) where:
The monitor alarm / trip setpoint based on the skin dose Ss
=
rate.
Radinic-cical Ef fluents Technical Specification 3.11.2.1 Da e
11relt on 3000 mrem /yr to the skin of the body, conserva-tively interpreted as a continuous release over a one year period.
Monitor response per mrem /yr to the skin of the body.
R
=
s c
Rs "
(X/0), 2 (Li + 1.lM ) Qi )
(
f i
where:
Li Skin dose factor due to beta emissions from isotope i
=
(mrem /yr per pC1/m3) from Table A.1-2.
Conversion factor to mrem skin dose per mred air dose 1.1
=
Mi Air dose factor due to gamma emissions from isotope i
=
(mrad /yr per pCi/m3) from Table A.1-2.
ODCM 15 01-31-84 j
s L
a
. The factors SF, AF,-c, (X/Q) and Qi are as defined in Section 3.1.2.
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 FShR-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 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 CFR 50 Appendix I' annual dose guidelines being reached.
Technical Specification 3.11.2.2 limits thez annual dose due to noble gases to < 10 mrads for gamma radiation and < 20 mrads for beta radiation.
Technical Specification 3.11.2.3 limits the annual dose to 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 effluents to j[ 15 mrem'to any organ.
These two Technical Specifications contain the annual dose limits due to gaseous releases found in 10 CFR~50 Appendix I.
~
3.1.4.1 NOBLE GAS ALERT ALARM SETPOINT CALCULATION The alert alarm setpoint is the lesser of S
f, (SF x AF) xD x Ry (3) r S
f, (SF x AF) xDj x R3 (4)
ODCM 16 01-31-84
where:
Monitor setpoint based on gamma radiation.
Sg
=
Technical Specification 3.11.2.2 limit of 10 mrad /yr D
=
r conservatively-interpreted as a continuous release over a one year period.
Monitor response per mrad /yr determined according to:
Rg
=
c R y*=
g
( (X/Q)
Mi x Qi )
g where:
Gamma Air Dose Factor (mrad /yr per Mi
-=
,pCi/m3).
See Table A.1-2.
Monitor setpoint based on beta radiation.
S
=
j Dg Technical Specification 3.11.2.2 limit of
=
20 mrad /yr conservatively interpreted as a continuous release over a one year period.
Rp-'=
Monitor response per mrad /yr determined according to:
c
/
E
( (X/Q)
Ni x Qi )
g where:
Beta Air Dose Factor (mrad /yr per Ni
=
pCi/m3).
See Table A.1-2.
Formulas 3 and 4 are used to calculate the alert alarm setpoints
- for the gaseous monitors listed in Section 3.1.1 and for actual
-concentrations of radionuclides found in the effluent streams.
A semi-fixed alert alarm satpoint for the Plant Unit Vent monitor (0-GT-RE-21) and Radwaste Building Vent monitor (0-GT-RE-10 ) is calculated using the following:
(10 mrad /yr) (.85) (AF)
(5)
Setpoint (pC1/cc) g Pi x Mi x Q)
=
( (X/Q) g ODCM 17 01-31-84
i I
where:
Fractional value of isotope expected, C /CTr i
Pi
=
where:
Ci Concentration in pCi/cc of isotope.
=
Total Gaseous Activity from FSAR CT
=
Table 11.1-1.
Either Unit Vent Flow or Radwaste Building AF
=
Vent Flow divided by the combined flow of the Unit Vent and Radwaste Building Vent.
Vent flow rate in cc/sec.
0
=
Isotopes used and Pi values are as follows:
ISOTOPE Pi Kr-85M
.018 Kr-87
.010 Kr-88
.033 Xe-133m
.017 Xe-133
.851 Xe-135
.051 Should this semi-fixed alert alarm cause a continuous alarm condition, then actual setpoints will be calculated.
3.1.4.2 PARTICULATE AND IODINE ALARM SETPOINTS Setpoints for the gaseous effluent particulate and iodine channels are set using Cs-137 MPC for particulates and I-131 MPC for iodines.
The following is the calculation used:
(MPCi ) (AP) (SF)
Setpoint (pCi/cc)
=
(Q)
(X/Q)
{
ODCM 18 01-31-84
where:
MPCi =
5 x 10-10 pCi/co for Cs-137 1 x 10-10 pCi/cc for I-131
=
as defined previously AF
=
.0625 for I-131
- SF
=
.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.
This will provide the Hi alarm setpoint.
The alert alarm setpoint is 10% of the Hi alarm setpoint.
3.2 GASEOUS EFFLUENT CONCENTRATION / DOSE RATE
- Compliance with 10 CFR 20 The Standard Technical Specification 3.11.2.1 requires that the instantaneous dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the site Loendary shall be limited to the following values:
a.
The dose rate limit for noble gases shall be <500 mrem /yr to the total body and <3000 mrem /yr to the skin, and b.
The dose rate limit for all radioiodines and for all E
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.
Based on the methodology of NUREG-0133;
.a.
Release rate limit for noble gases:
f Ki (X/Q) Qi <500 mrem /yr for the total body, and f(Li+1.1Mi) (X/Q) Qi <3000 mrem /yr for the skin.
ODCM 19 01-31-84
(.
where:
Ki
= Total body dose factor due to gamma emissions for each identified noble gas radionuclide, in 3
mrem /yr per /4 Ci/m, from Table A.1-2.
3
= 2.2 E-06 sec/m, The highest calculated annual (X/Q) average relative concentration at the restrictcd area boundary in tne North Sector or current X/Q.
-Qi
= Release rate of radionuclide i from vent, in suci/sec.
Li
= Skin dose factor due to beta emissions for each identified noble gas radionuclide, in 3
mrem /yr per aci/m, frcm Table A.1-2.
Mi
= Air dose f actor due to gamma emissions for each identified noble gas radionuclide, in mrad /yr per,4Ci/n3 from Table A.1-2.
1.1
= Conversion constant of air dose to skin dose.
b.
Release rate limit for all radionuclides and radio-active materials in particulate form and radionuclides other than noble gases:
E (P(i}IN *
(X/Q) - Qi) <l500 mrem /yr to any organ.
g where:
The release rate of radionuclides, i, in 01
=
gaseous effluent from all vent releases, in pCi/sec.
The dose parameter for radionuclides P(i)IN
=
other than noble gases for the inhalation pathway, in mrem /yr per,pci/m3, see Table A.5-1.
2.2 E-06 sec/m3 (the highest annual average).
X/O
=
The highest calculated relative concentration for estimating the dose to an individual at the unrestricted area boundary in the N sector, or current X/Q.
ODCM 20 01-31-84 1
I
All radionuclides are assumed to be released in elemental form.
The specification is appli, cable 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, Li, and Mi relate the radionuclide airborne concentrations to various dose rates assuming a set.i-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 pCi-1 and listed in Table A.1-2.
The following eauation for P(i)IN was taken from NUREG 0133:
P(i)IN," Inh al atio n) ;
3 P(i)IN = K' (BR) DFAi (mrem /yr per aCi/m )
j where:
K'
= a constant of unit conversion, 106 pCi/j4Ci BR
= the breathing rate of the child age group in m3/yr DFAi = the maximum organ inhalation dose factor for the child age group for the ith radionuclide, in mrem /pci.
The total bod 5 is considered as an organ in the selection of DFA1 The age group considered is the child group.
3 The child's breathing rate is taken as 3700 m /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 ODCM 21 01-31-84
{
J
The Pi value for tritium is:
Pi (Inhalation) = 3.7 x 109 DFAi 3.3 GASEOUS EFFLUENT DOSES
- Compliance with 10 CFR 50 Appendix I 3.3.1 NOBLE GASES Specification 3.11.2.2 requires that the air dose due to noble gases released in gaseous effluents to areas at and beyond the site boundary shall be limited to the following:
a.
During any calendar quarter, to < 5 mrad for gamma radiation and i 10 mrad for beta radiation; b.
During any calendar year, to < 10 mrad for gamma radiation and < 20 mrad for beta radiation.
To show compliance with this specification, the dose calculations for the actual releases of radioactive noble gases in gaseous ef fluent will be consistent with the methodology provided in Reg. Guide 1.109, Rev.
1.
The following dose calculations will be performed:
a.
During any calendar quarter; For gamma radiation; D=3.17E-8fy Mi [(X/0) 01] 1 5 mrad.
For beta radiation;
)gy Ni [ (X/Q)
- Qi] 1 10 mrad.
D= 3.17 E-8 b.
During any calendar year:
For gamma radiation:
ghy Mi [ (X g). Qi] 1 10 mrad.
/
D= 3.17 E-8 For beta r&diation:
ghkNi [ (X g) 01] 1 20 mrad f
D = 3.17 E-8 ODCM 22 01-31-84 I
where:
f 3.17 E-8 = The inverse of the number of seconds in a year.
Mi
= The air dose factor due to gamma emissions for each identified noble gas radionuclide, in mrad /yr per pCi/m3 from Table A.1-2 (Reg. Guide 1.109, Table B-1, Col. 4)
Ni
= The air dose factor due to beta emissions for each identified noble gas radionuclide, in mrad / year per ACi/m3 from Table A.1-2 (Reg.
Guide 1.109, Table B-1, Column 2).
X/O
= 2.2 E-6 sec/m3 The highest calculated annual average relative concentration for any area at the unrestricted area boundary or current X/Q.
Qi
= The release of noble gas radionuclides,
'i', in gaseous effluents, inj Ci.
Releases u
shall be cumulative over the calendar quarter or year as appropriate.
An average monthly air dose schedule should be setup to ensure section 3.11.2.2 of Wolf Creek Technical Specifications are not exceeded.
The average monthly air dose should be as follows:
a.
For gamma radiation i 1.6 mrad /mo.
For beta radiation 5 3.3 mrad /mo.
If the monthly average air dose for: (a) is exceeded, it should
-be noted that if the release is continued at the same (or higher) frequencies or activities, Section 3.11.2.2 A of Wolf Creek Technical Specifications will be exceeded.
b.
For gamma radiation f 0.8 mrad /mo.
For beta radiation f 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 monthly average air doses are exceeded, evaluation of the causes of the high air dose should be performed and steps should be taken to reduce the activity or frequency (e.g. delay the release of a Waste Gas Decay Tank) of the release.
ODCM 23 01-31-84
___L_______-_______
f 3.3.2 RADIOIODINES, PARTICULATES, AND OTHER RADIONUCLIDES Specification 3.11.2.3 requires that the dose to an individual from iodine-131 and 133, tritium, and all radioactive materials in particulate form with. half-lives greater than 8 days in gaseous effluents released to areas at and beyond the site boundary shall be -limited to the following:
a.
During any calendar quarter to f 7.5 mremto any organ; and b.
During any calendar year to f 15 mremt 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:
T [E p
i Ri (WQi)] 1 7.5 mrem a.
D (mrem) = 3.17E-8 E [I p
i Ri (WQi) ] 1 15 mrem b.
D (mrem) = 3.17E-8 wnere:
3.17E-8 = The inverse of the number of seconds in a year.
The release of radiciodines, radioactive Qi a
materials in particulate form and radionuclides other than noble gases in gaseous ef fluents, 'i',
in 4Ci. Releases shall be cumulative over the s
calendar guarter 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 wit' Radiological Effluent Technical Specifica-tion 3.11.2.1.
The annual average dispersion parameter for W
=
estimating the dose to an individual at the controlling' location.
W=
(X/0), 2.2 x 10-6 sec/m3, or current X/Q for the inhalation pathway.
W=
(D/Q), 1.8 E-8 m-2, for the food and ground plane pathways.
Ri The dose factor for each identified radionuclide,
=
'i', in mrem /yr per j4 Ci/m3 See Table A.5-2 through Table A.5-5.
ODCM 24 01-31-84 1
where:
Inhalation Pathway Factor, 3
R [X/Q] = K' (BR) a '
(mrem /yr per pri/m )
I where:
6 K'
= a constant of unit conversion, 10 pCifaci.
(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 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 [u/C]
i t
[D/Q) = K'K" (SP) DFG
[ (1-e i )/
2. n em/g pet g /s d g
where:
K'
= A constant of unit conversion, 106 pCifaci.
K"
= A constant of unit conversion, 8760 hr/ year.
A
= The decay constant for the i th radionuclide, g
sec~l.
t
= The exposure time, 4.73 E8 sec (15 years).
-ODCM 25 01-31-84
__u
L l:
DFGi
= The ground plane dose conversion factor for the ith radionuclide (mrem /hr per pCi/m2), see Table A.2-5.
(Regulatory Guide 1.109, Table E-6).
SF
= The shielding factor (dimensionless), 0.7 (Reg.
Guide 1.109)
. Grass-Cow-Milk Pathway Factor, R [D/Q]
1 R [D/Q] = K' (9F(Uap)) Fm(r) (DFLi) a (
/Yp) (8 f) i i
w 2
(m. mrem /yr per gCi/sec) j K'
= A constant of unit conversion, 106 pCi/juCi.
Op
= The cow's consumption rate, in Kg/ day (wet weight), 50 kg/ day.
(Reg. Guide l.109, Table E-3).
.Dap
= The receptor's milk consumption rate for age-(a), in liters /yr.
(Reg. Guide-l.109, Table E-5) 330 1/yr Infant
=
Child 330 1/yr
=
400 1/yr Teen
=
310 1/yr Adult
=
Y
= The agricultural productivity by unit area of p
in kg/m, 0.7 kg/m2 (Reg.
2 pasture feed grass, Guide 1.109, Table E-15).
Fm
= The stable element transfer coefficients, in days / liter, See Table A.3-5.
(Reg. Guide 1.109, Table E-1) 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).
(DFLi), = The maximum organ ingestion dose factor for the i th radionuclide for the receptor in age group
'a',
in mrem /pci.
See Tables A.3-1, A.3-2, A.3-3, and A.3-4.
(Reg. Guide 1.109, Table E-ll, E-12, E-13, and E-14)
ODCM 26 01-31-84
Ai
= The decay constant for the ith radionuclide, in sec -1 Aw
= 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-15).
NOTE:
The fraction of the year that the cow is on pasture and the fraction of the cow feed that is pasture grass is assumed to be 1.0, which i:s 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 R
[X/Q] = K'K"' F QpUap (DFL )a [0.75 (0. 5/H) ]
m i
(mrem /yr per, Ci/m3) where:
K"'
= a constant of unit conversion, 103 gm/Kg.
H
= Absolute humidity of the atmosphere, 8 gm/m3, (Reg. Guide 1.109).
0.75
= The fraction of total feed that is water.
(NUREG 0133) 0.5
= The ratio of the specific activity of the feed grass water to the atmospheric water. (NUREG 0133)
Grass-Cow-Meat Pathway Factor, R"[D/Q]
i R"[D/Q] =K' (SFEapl) Fg (r) (DFLi) a ( /Yp)
~
e i
A +A, i
(m2. mrem /yr per pCi/sec)
ODCM 27 01-31-84
where:
Ff
=.The stable element transfer coefficients, in days /kg, Table A.3-5.
(Reg. Guide 1.109, Table E-1).
Uap = The receptor's meat consumption rate for age (a), in kg/yr.
(Reg. Guide 1.109, Table E-5)
Infant = 0 Child
= 41 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 M is concentration rather than the deposition.
Therefore, the R based on (x/Q):
i R [X/Q) = K'K"' Ff Of Uap (DFLi)a [0.75(0.5/H)]
3 (mrem /yr per nC1/m )
j where:
All terms defined above.
Vegetation 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:
t R [D/Q] = K' [7 gy,3 ) ] (DFL1) a [ (Uk) (f ) (e-itL)+(U$) (f ) (e-i h))
L g
(m2. mrem /yr perjuci/sec) where:
A constant of unit conversion, 106 K'
pCi/juCi.
=
ODCM 28 01-31-84 l
u
Uk
=
The consumption rate of. fresh leafy vegetation by the receptor in age group (a),
in kg/yr. (Reg Guide 1.109, Table E-5).
0 kg/yr Infant
=
Child
=-26 kg/yr Teen
= 42 kg/yr Adult
= 64 kg/yr The consumption rate of stored U
=
a vegetation by the receptor in age group (a),
Kg/yr.
(Reg Guide 1.109, Table E-5).
0 kg/yr Infant
=
Child 520 kg/yr
=
630 kg/yr Teen
=
520 kg/yr.
Adult
=
The fraction of the annual intake of fresh fn
=
leafy vegetation grown locally.
(default = 1.0)
The fraction of.the annual intake of stored f
=
g
)
vegetation grown locally. (def ault = 0.76)
The average time between harvest of leafy tn
=
vegetation and its consumption, in seconds, 8.6 E4 secs (1 day). Reg. Guide 1.109).
th The average time between harvest of stored
=-
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 Y
=
y (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{isbasedon (X/0) :
L+U!f] (DFL1)a [0.75 (0. 5/H) ] -
K' K"'
[Ua f R [X/Q]
=
g (mrem /yr per p.Ci/m3) where:
All~ terms defined previously.
All valu ; indicated are default values from Reg. Guide 1.109, Rev. 1.
ODCM 29 01-31-84
.~
An average monthly' dose schedule should be setup to ensure Section 3.11.2.3 of Wolf Creek Yechnical Specifications are not exceeded.
The average monthly dose due to radioiodines, 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 should 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 B will be exceeded..
If any of the above monthly doses.are exceeded, evaluation of
~
the'causes should be performed and steps taken to reduce the activity or frequency of the. Release.
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 0-GH-RE-10A Radwaste Building Ef fluent Particulate, Iodine O~GT-RE-21B Plant Unit Vent Wide Range Gas O-G H-RE-10 B Radwaste Building Ef fluent Wide Range Gas
'O-GT-RE-22'& 33 Containment Purge Exhaust Particulate, Iodine, Gas O-GT-RE-31 & 32 Containment Atmosphere Particulate, Iodine, Gas
. ODCM -
30 01-31-84 I
E A
s 3.4.1 PARTICULATE DET3CTOR CALIBRATION 3.4.1.1 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.
3.4.1.2 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 /,pci 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 using a filter paper impregnated with stand activities of Cs-137.
Increasing amounts of a standard Cs-137 solution shall be impregnated on a filter paper.
The 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 checked.
Immediately following monitor calibration the 0.05 #Ci 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(Tl) integral line gamma scintillator assembly.
3.4.2.2 Because of its short half life and the difficulty in handling gaseous iodine, barium sources shall be used for calibration.
The photo peaks of interest are as follows:
A.
Ba-133: 356 kev gamma is 0.69 efficient / disintegration B.
I-131: 564 kev gamma is 0.82 efficient / disintegration ODCM 31 01-31-84
__-_______-______-__-_-____-_____-______-_____-_______A
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 364 kev, the sensitivity for I-131' equals 1.19 x Ba-133 (counts / min)/
The standard sources shall be construc-ted by impreg;pCi.
nating a standard Ba-133 solution into the l
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 t
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 counts per minute proudced by the Ba-133 checksource shall be logged.
3.4.3 GAS DETECTOR CALIBRATION 3.4.3.1
.The gas detectors associated with monitors O-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 plactic scintillator identical to the particulate detector.
The mid-range and high-range detectors of monitors 0-GT-RE-21B and 0-GH-RE-10B 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 chamber then shall tue backfilled to the desired pressure-with a source of standard Xe-133.
The source is then counted-and the counts per n.inute recorded.
A graph of counts per minute versus concentration shall lxe produced from the ' data.- Sources shall be prepared to scover approximately 1/4, 1/2, and 3/4 of full scale for the detectors' associated with monitors O-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.
Sources shall be prepared for the mid/high range detector to cover two points on the mid-range scale.
Por ALARA purposes, response for 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.
ODCM 32 01-31-84
4.0 RADIOLOGICAL ENVIRONMENTAL MONIT^'ING PROGRAM Table 4.1 gives specific Radiological Envitunmental sampling.
pathways, locations and frequencies corresponding to Table 3.12-1 of Wblf Creek Technical Specifications.
Maps showing these locations in relation to the Wblf 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 Laboratory 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.
ODCM 33 01-31-84
o 8
TABLE 4.l' Sheet 1 of 3 3
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Number of Samples Exposure Pathway and Sampling and
-Type and Frequency and/or Sample Sample Locations Collection Frequency of Analysis
- 1. AIRBORNE l
Radioiodine and Five locations, Continuous operation Radioiodine canister.
Particulates station numbers 2, of sampler with sample Analyze weekly for 3, 31, 37 and 40 collection as required I-131.
(control) Figure 4.1.
by dust loading but at least weekly.
Analyze for gross beta radioactivity not less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following filter change.
Perform g
gamma isotopic analysis on each sample when gross beta activity is greater than 10 times the yearly mean of control samples.
Perform gamma isotopic analysis on composite (by location) once per quarter.
- 2. DIRECT RADIATION 38 TLD locations within Quarterly at each Gamma dose quarterly.
5-mile radius of site location (station numbers 1-38 on Figure 4.1) and two offsite locations a
(stations 39 and 40);
H de two TLD dosimeters at 7
each location.
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SAMPLING LOCATION NUMBERS, DISTANCES (miles) AND DIRECTIONS 1
i TLD and Air Particulate Location Distance /
Location Distance /
Location Distance /
Location Distance Number Direction Number Direction Number Direction Number Direction 1
1.4/N 11 1.6/E 21 3.8/S 31 3.0/WNW 2
2.7/N 12 1.8/ESE 22 4.1/SSN 32 2.8/WNW 3
3.0/NNE 13 1.5/SE 23 4.5/SW 33 4.1/WNW 4
3.7/NNE 14 2.6/SE 24 4.1/WSW 34 4.0/NW 5
4.0/NE 15 4.5/ESE 25 3.6/W 35 4.6/NNW 6
4.4/ENE 16 4.2/E 26 2.6/WSW 36 4.2/N 7
1.9/NE 17 3.6/SE 27 2.1/SW 37 2.1/NNW 8
1.6/NNE 18 2.8/SSE 28 2.8/SW 38 1.2/NW 9
2.0/ENE 19 4.0/SSE 29 2.6/SSW 39 13.0/N 10 2.4/ENE 20 3.3/S 30 2.2/W 40 15.0/WNW Groundwater B-12
.2.2/NE C-10 2.8/W C-49 2.9/SW D-65 3.9/S Milk and Food Products A-1 1.4/N F-1 1.6/ESE Q-1 1.3/NW R-1 2.2/NNW B-8 4.9/NNE G-1 1.4/SE Q-2 1.4/NW S-3 15.0/WNW C-11 5.2/NE P-2 2.9/WNW 0-5 3.6/NW S-4 15.0/WNW O
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l 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 ef fluents exceed twice the limits o f Technical Specification 3.ll.l. 2a, 3.11.1.2b, 3.11.2.2a, 3.11.2.2b, 3.ll.2.3a, or 3.ll.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.
Cumulative dose contributions from direct radiation mi om the reactor utiit and from radwaste storage tanks shall u; determined utilizing the results of routine plant perimeter surveys, TLD data or a combination of both, when necessary.
ODCM 38 01-31-84 a
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APPENDIX A Dose Conversion Factor Tables i
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T'
'E A.1-1*
~ BIOACCUMULATION FACTORS TO BE USED IN THE ABSENCE 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 Zn 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 Ru 1.0E 01 Rh 1.0E 01 Te 4.0E 02 I
1.5E Ol' 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
' *Taken from Regulatory Guide 1.109 (Rev. 1).
ODCM-A-2 I-t
TABLE A.1-2 DOSE FACTORS FOR EBLE GASES AND IRUGiffERS*
Tbtal Body Gansna Air Beta Air Dose Factor Skin Dose Factor Dose Factor Dose Factor K-Li Mi Ni Radionuclide (mrern/yr kr p.Ci/m )
(mren/yr per ACi/m3)
(mrad /yr per u.Ci/m3)
(mrad /yr per 2(Ci/m )
3 3
Kr-83m 7.56E-02**
1.93E+01 2.88E+02 Kr-85m 1.17E+03 1.46E+03 1.23E+03 1.97E+03 Kr-85 1.61E+01 1.34E+03 1.72E+01 1.95E+03 Kr-87 5.92E+03 9.73E+03 f.17E+03 1.03E+04 Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03 Kr-89 1.66E+04 1.01E+04 1.73E+04 1.06E+04 b
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 Xe-133m 2.51E+02 9.94E+02 3.27E+02 1.48E+03 Xe-133 2.94E+02 3.06E+02 3.53E+02 1.05E+03 Xe-135m 3.12E+03 7.11E+02 3.36E+03 7.39E+02 Xe-135 1.81E+03 1.86E+03 1.92E+03 2.46E+03 Xe-137 1.42E+03 1.22E+04 1.51E+03 1.27E+04 Xe-138 8.83E+03 4.13E+03 9.21E+03 4.75E+03 Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03 Based on Regulatory Guide 1.109 (Rev.1).
- 7.56E-02 = 7.56 x 10 -2
- ~_. _
i TABLE A.2-l*
IMIAIATION DOSE FACIORS FOR ADULTS (MREM PER PCI INHALED)
NUCLIDE BOiE LIVER T BODY THYROID' KIDNEY IUNG GI-LLI H
3.
NO DATA 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 C 14 2.27E-06 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 NA 24 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 P 32 1.65E-04 9.64E-06 6.26E-06 NO DATA NO DATA NO DAM 1.08E-05 CR 51 NO DATA ' NO DAM 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 DAM 1.23E-06 1.75E-04 9.67E-06 l
M 56 NO DATA 1.55E-10 2.29E-11 NO DATA 1.63E-10 1.18E-06 2.53E-06 FE 55 3.07E-06 2.12E-06 4.93E-07 NO DATA NO DATA 9.01E-06 7.54E-07 FE 59 1.47E-06 3.47E-06 1.32E-06 NO DATA NO DATA 1.27E-04 2.35E-05 CO 58~
NO DATA-1.98E 2.59E-07:
NO DATA NO DATA 1.16E-04 1.33E-05 CO 60 N') DATA 1.44E-06 1.85E-06 NO DATA NO DATA 7.46E-04 3.56E-05 NI 63 5.40E-05 3.93E-06 1.81E-06 NO DATA NO DATA 2.23E-05 1.67E-06 NI 65 1.92E-10 2.62E-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 ZN 65 4.05E-06 1.29E-05 5.82E-06 NO DAM 8.62E-06 1.08E-04 6.68E-06 1
ZN 69' 4.23E-12 8.14E-12 5.65E-13 NO DATA 5.27E-12 1.15E-07 2.04E-09 BR 83 NO DATA NO DAM 3.01E-08 NO DP.m NO DATA NO DATA 2.90E-08 R 84 NO DATA 10 DAM 3.91E-08 NO DATA NO DATA NO DATA 2.05E-13 i
t e
BR 85 NO DATA NO DAM 1.60E-09 NO DATA NO DATA NO DATA LT E-24 PR 86 '
NO DATA 1.69E-05 7.37E-06 NO DATA NO DATA NO DAM 2.08E-06
~4.18E-19 RS 88 NO DATA 4.84E-08 2.41E-08 NO DATA NO DATA NO DAM A 89 NO DATA 3.20E-08 2.12E-08 NO DATA NODAT}
NO DATA 1.16E-21 L
SR 89 3.80E-05 NO DATA 1.09E NO DATA NO DATn 1.75E-04 4.37E-05 SR 9G 1.24E-02 NO DATA 7.62E-04 NO DATA NO DATA 1.20E-03 9.02E-05
' SR 91
-7.74E-09 NO DATA 3.13E-10 NO DATA NO DATA 4.56E-06 2.39E-05 E
SR 92 8.43E-10 NO DAM 3.64E-ll NO DATA NO DATA 2.06E-06 5.38E-06 Y 90:
2.61E-07 NO DATA 7.01E-09 NO DAM NO DATA 2.12E-05 6.32E-05
.Y 91M 3.26E-ll NO DAM 1.27E-12 NO DATA NO DATA 2.40E-07 1.66E-10 Y 91 ~
5.78E-05 NO DATA 1.55E-06 NO DATA NO DATA 2.13E-04 4.81E-05 Y 92 1.29E-09 NO DATA 3.77E-ll 10 DATA NO DATA 1.96E-06 9.19E-06 1
- Taken fran Regulatory Guide 1.109 (Rev.1)
A-4
~.. _, _ _.. _ _ _ _.. _. _.. _ _ _ _. _ _ _. _ _ _ _ _ _ _ _ _. _ _ _. _ _ _ _ -
TABLE A:.2-1 (cont'd)
INHALATION DOSE FACIORS Fm ADULTS (MREM PER PCI INHALED)
NUCLIDE BONE LIVER T BCDY
'IEYROID KIDNEY LUNG 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 NB 95 1.76E-06 9.77E-07 5.26E-07 NO DATA 9.67E-07 6.31E-05 1.30E-05 MO 99 NO DATA 1.51E-08 2.87E-09 NO DATA 3.64E-08 1.14E-05 3.10E-05 TC 99M 1.29E-13 3.64E-13 4.63E-12 NO DATA 5.52E-12 9.55E-08 5.20E-07 TC 101 5.22E-15 7.52E-15 7.38E-14 NO DATA 1.35E-13 4.99E-08 1.36E-21 RU 103 1.91E-07 NO DATA 8.23E-08 m DATA 7.29E-07 6.31E-05 1.38E-05 RU 105 9.88E-ll NO DATA 3.89E-ll NO DATA 1.27E-10 1.37E-06 6.02E-06 RU 106 8.64E-06 NO DATA 1.09E-06 NO DATA 1.67E-05 1.17E-03 1.14E-04 AG 110M 1.35E-06 1.25E-06 7.43E-07 NO DATA 2.46E-06 5.79E-04 3.78E-05 TE 125M 4.27E-07 1.98E-07 5.84E-08 1.31E-07 1.55E-06 3.92E-05 8.83E-06 l
TE 127M 1.58E-06 7.21E-07 1.96E-07 4.11E-07 5.72E-06 1.20E-04 1.87E-05 TE 127 1.75E-10 8.03E-ll 3.87E-ll 1.32E-10 6.37E-10 8.14E-07 7.17E-06 TE 129M 1.22E-06 5.84E-07 1.98E-07 4.30E-07 4.57E-06 1.45E-04 4.79E-05 TE 129 6.22E-12 2.99E-12 1.55E-12 4.87E-12 2.34E-11 2.42E-07 1.96E-08 TE 131M 8.74E-09 5.45E-09 3.63E-09 6.88E-09 3.86E-08 1.82E-05 6.95E-05 TE 131 1.39E-12 7.44E-13 4.49E-13 1.17E-12 5.46E-12 1.74E-07 2.30E-09 l
l TE 132 3.25E-08 2.69E-08 2.02E-08 2.37E-08 1.82E-07 3.60E-05 6.37E-05 l
I 130' 5.72E-07 1.68E-06 6.60E-07 1.42E-04 2.61E-06 NO DATA 9.61E-05 l
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-07 7.69E-08 3.73E-06 3.44E-07 NO DATA 1.26E-10 I 135 3.35E-07 8.73E-07 3.21E-07 5.60E-05 1.39E-06 NO DATA 6.56E-07 CS 134 4.66E-05 1.06E-04 9.10E-05 m 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 1.12F 07 l
A-5
TABLE A.2-1 (cont'd)
INHALATION DOSE FACIORS EER ADULTS (MRDI PER PCI INHALED)
NUCLIDE BONE LIVER T BODY
'IHYROID KIDNEY IUNG GI-LLI BA 140 4.88E-06 6.13E-09 3.21E-07 110 DATA 2.09E-09 1.59E-04 2.73E-05 BA 141 1.25E-ll 9.41E-15 4.20E-13 NO DATA 8.75E-15 2.42E-07 1.45E-17 BA 142 3.29E-12' 3.38E-15 2.07E-13 NO DATA 2.86E-15 1.49E-07 1.96E-26 LA 140 4.30E-08 2.17E-08 5.73E-09 NO DATA NO DATA 1.70E-05 5.73E-05 LA 142 8.54E-ll 3.88E-ll 9.65E-12 NO DATA NO DATA 7.91E-07 2.64E-07 CE 141 2.49E 1.69E-06 1.91E-07 NO DA'1A 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
'. 70E-07 3.51E-05 2.50E-05 PR 144 3.76E-12 1.56E-12 1.91E-13 10 DATA 8.81E-13 1.27E-07 2.69E-18 ND 147 6.59E-07 7.62E-07 4.56E-08 NO DATA 4.45E-07 2.76E-05 2.16E-05 W 187 1.06E-09 8.85E-10 3.10E-10 NO DATA NO DATA 3.63E-06 1.94E-05 NP 239 2.87E-08 2.82E-09 1.55E-09 NO DATA 8.75E-09 4.70E-06 1.49E-05 i
{
l l
l A-6 i
TABLE A,2-22 INHALATION DOSE FACIORS FOR TEENAGER (MREM PER PCI INHALED)
NUCLIDE BONE LIVER T BODY
'IHYROID KIDNEY LUNG GI-LLI H
3 to 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 MN 54 NO DATA 6.39E-06 1.05E-06 NO DATA 1.59E-06 2.48E-04 8.35E-06 tN 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 00 58 NO DATA 2.59E-07 3.47E-07 NO DATA NO DATA 1.68E-04 1.19E-05 CO 60 NO DATA 1.89E-06 2.48E-06 NO DATA NO DATA 1.09E-03 3.24E-05 NI 63 7.25E-05 5.43E-06 2.47E-06 NO DATA NO DATA 3.84E-05 1.77E-06 NI 65 2.73E-10 3.66E-ll 1.59E-ll NO DATA NO DATA 1.17E-06 4.59E-06 CU 64 NO DATA 2.54E-10 1.06E-10 NO DATA 8.0lE-10 1.39E-06 7.68E-06 ZN 65 4.82E-06 1.67E-05 7.80E-06 NO DATA 1.08E-05 1.55E-04 5.83E-06 ZN 69 6.04E-12 1.15E-ll 8.07E-13 NO DATA 7.53E-12 1.98E-07 3.56E-08 BR 83 NO DATA 10 DATA 4.30E-08 NO DATA NO DATA NO DATA LT E-24 BR 84 NO DATA NO DATA 5.41E-08 NO DATA 10 DATA NO DATA LT E-24 BR 85 NO DATA NO DATA 2.29E-09 NO DATA 10 DATA NO DATA LT E-24 l
RB 86 NO DATA 2.38E-05 1.05E-05 NO DATA NO DATA NO DATA 2.21E-06 l
RB 88 NO DATA 6.82E-08 3.40E-08 NO DATA NO DATA NO DATA 3.65E-15 RB 89 NO DATA 4.40E-08 2.91E-08 NO DATA NO DATA NO DATA 4.22E-17 l
SR 89 5.43E-05 NO DATA 1.56E-06 10 DATA NO DATA 3.02E-04 4.64E-05 i
SR 90 1.35E-02 NO DATA 8.35E-04 10 DATA NO DATA 2.06E-03 9.56E-05 SR 91 1.10E-08 NO DATA 4.39E-10 NO DATA NO DATA 7.59E-06 3.24E-05 SR 92 1.19E-09 NO DATA 5.08E-ll NO DATA to DATA 3.43E-06 1.49E-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-ll NO DATA 1.77E-12 NO DATA NO DATA 4.00E-07 3.77E-09 Y 91 8.26E-05 NO DATA 2.21E-06 NO DATA NO DATA 3.67E-04 5.11E-05 Y 92 1.84E-09 NO DATA 5.36E-Il NO DATA NO DATA 3.35E-06 2.06E-05
- Taken frcm Regulatory Guide 1.109 (Rev.1)
A-7
MBLE A.2-2 (cont'd)
INHAIATIOi DOSE FAC'IORS FOR TEENAGERS (MREM PER PCI INHALED)
NUCLIDE BONE LIVER T BODY
'IHYBOID KIDNEY IUNG GI-LLI
'Y 93
'l.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 m DATA 1.25E-06 9.39E-05 1.21E-05 MO 99
.NO DATA 2.llE-08 4.03E NO DATA 5.14E-08 1.92E-05 3.36E-05 TC 99M 1.73E-13 4.83E-13' 6.24E-12 NO DATA 7.20E-12 1.44E-07 7.66E-07 TC 101
-7.40E-15 1.05E-14 1.03E-13 NO DATA 1.90E-13 8.34E-08 1.09E-16 RU 103 2.63E-07 NO DATA 1.12E-07 NO DATA 9.29E-07 9.79E-05 1.36E-05 RU 105-1.40E-10 NO DAR 5.42E-ll NO DATA 1.76E-10 2.27E-06 1.13E-05 RU 106 1.73E-05 NO DATA 1.55E-06 m DATA 2.38E-05 2.01E-03 1.20E-04 i
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 m DATA 6.70E-05 9.38E-06 TE 127M 2.25E-06 1.02E-06 2.73E-07 5.48E-07 8.17E-06 2.07E-04 1.99E-05 TE 127 2.51E-10 1.14E-10 5.52E-ll 1.77E-10 9.10E-10 1.40E-06 1.01E-05 TE 129M 1.74E-06 8.23E-07 2.81E-07 5.72E-07 6.49E-06 2.47E-04 5.06E-05 TE 129 8.87E-12 4.22E-12 2.20E-12 6.48E-12 3.32E-ll 4.12E-07 2.02E TE 131M 1.23E-08 :7.51E-09 5.03E-09 9.06E-09 5.49E-08 2.97E-05 7.76E-05 TE 131 1.97E-12 1.04E-12 6.30E-13 1.55E-12 7.72E-12 '2.92E-07 1.89E-09 TE 132 4.50E-08 3.63E-08 2.74E-08 3.07E-08 2.44E-07 5.61E-05 5.79E-05 I -130 7.80E-07 2.24E-06 8.96E-07 1.86E-04 3.44E-06 NO DATA 1.14E-06 I 131 4.43E-06 6.14E-06 3.30E-06 1.83E-03 1.05E-05 NO DATA 8.llE-07 I 132' l.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 1.29E-06 I 134 1.llE-07 2.90E-07 1.05E-07 4.94E-06 4.58E-07 NO DATA 2.55E-09 I 135 4.62E-07 1.18E-06 4.36E-07
'7.76E-05 1.86E-06 NO DATA 8.69E-07 l
CS 134 6.28E-05 1.41E-04 6.86E-05 m DATA 4.69E-05 1.83E-05 1.22E-06 l
CS 136 6.44E-06 2.42E-05 1.71E-05 NO DATA 1.38E-05 2.22E-06 1.36E-06 CS 137 8.38E-05 1.06E-04 3.89E-05 NO DATA 3.80E-05 1.51E-05 1.06E-06 CS 138 5.82E-08 1.07E-07 5.58E-08 NO DATA 8.28E-08 9.84E-09 3.38E-ll BA 139 1.67E-10 1.18E-13 4.87E-12 NO DATA 1.llE-13 8.08E-07 8.06E-07 l
l A-8 i
TABLE A.2-2 (cont'd)
IMIAIATION DOSE FAC'IORS FOR 'IEENAGERS (MREM PER PCI INHALED)
NUCLIDE BONE LIVER T DODY THYROID KIDNEY IUNG GI-LLI BA 140 6.84E-06 8.38E-09 4.40E-07 NO DATA 2.85E-09 2.54E-04 2.86E-05 BA 141 1.78E-11 1.32E-14 5.93E-13 m DATA 1.23E-14 4.llE-07 9.33E-14 BA 142 4.62E-12 4.63E-15 2.84E-13 NO DATA 3.92E-15 2.39E-07 5.99E-20 IA 140 5.99E-08 2.95E-08 7.82E-09 NO DATA NO DATA 2.68E-05 6.09E-05 LA 142 1.20E-10 5.31E-Il 1.32E-ll NO DATA NO DATA 1.27E-06 1.50E-06 CE 141 3.55E-06 2.37E-06 2.71E-07 NO DATA 1.llE-06 7.67E-05 1.58E-05 CE 143 3.32E-08 2.42E-08 2.70E-09 NO DATA 1.08E-08 1.63E-05 3.19E-05 CE 144 6.llE-04 2.53E-04 3.28E-05 NO DATA 1.51E-04 1.67E-03 1.08E-04 j
PR 143 1.67E-06 6.64E-07 8.28E-08 NO DATA 3.86E-07 6.04E-05 2.67E-05 PR 144 5.37E-12 2.20E-12 2.72E-13 NO DATA 1.26E-12 2.19E-07 2.94E-14 ND 147 9.83E-07 1.07E-06 6.41E-08 NO DATA 6.28E-07 4.65E-05 2.28E-05 W 187 1.50E-09 1.22E-09 4.29E-10 NO DATA NO DATA 5.92E-06 2.21E-05 NP 239 4.23E-08 3.99E-09 2.21E-09 NO DATA 1.25E-08 8.llE-06 1.65E-05 4
I l
l l
l I
1 i
A-9 I
l
~
~.
TABLE A.2-3*
4 INHALMPION DOSE FACIORS FOR OIIID (MREM PER PCI INHALED) i NUCLIDE 3OIE LIVER T BODY
'IUYIOID KI N 1 IUNG GI-LLI H
'3-NO DATA.3.04E-07
-3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 I
~ 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 C 14 9.70E-06 1.82E-06
. NA 24 4.35E-06 4.35E-06 4.35E 4.35E-06 4.35E-06 4.35E-06 4.35E-06 P 32' 7.04E-04' 3.09E-05 2.67E-05 NO DATA NO DATA NO DATA 1.14E-05 CR 51 NO DATA NO DATA 4.17E-08 2.31E-08 6.57E-09 4.59E-06 2.93E-07
- MN 54 NO DATA 1.16E-05 2.57E NO DATA 2.71E-06 4.26E-04 6.19E-06 PN 56 NO DATA 4.48E-10 8.43E-ll 10 DATA 4.52E-10 3.55E-06 3.33E-05 FE 55 1.28E-05 6.80E-06 2.10E-06 NO DATA NO DATA 3.00E-05 7.75E-07 FE 59 5.59E-06 9.04E-06 4.51E NO DATA NO DATA 3.43E-04 1.91E-05 00 58 N0' DATA
-4.79E-07 8.55E-07 NO DATA NO DATA 2.99E-04 9.29E-06 CO 60 NO DATA
.3.55E-06 6.12E-06 NO DATA NO DATA 1.91E-03 2.60E-05 NI 63 2.22E 1.25E-05 7.56E-06 NO DATA NO DATA 7.43E-05 1.71E-06 NI 65 8.08E-10 7.99E-ll 4.44E-ll NO DATA NO DATA 2.21E-06 2.27E-05 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 3.0.6E-05 1.90E NO DATA 1.93E-05 2.69E-04 4.41E-06 i
ZN'69 1.81E-ll 2.61E-ll 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 BR 84 NO DATA NO DATA 1.48E NO DATA NO DATA NO DATA LT E-24 i
BR 85 NO DATA NO DATA 6.84E-09 10 DATA NO DATA NO DATA LT E-24 RB 86 20 DATA 5.36E-05 3.09E-05 NO DATA NO DATA NO DATA 2.16E-06 l
' RB 88 NO DATA 1.52E-07 9.90E-08 NO DATA NO DATA NO DATA 4.66E-09 P
RB 89 NO DATA 9.33E-08 7.83E-08 NO DATA NO DATA NO DATA 5.llE-10 SR 89 1.62E-04 NO DATA ~
4.66E-06 PO 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 h
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 to DATA NO DAM 6.49E-06 6.55E-05 Y 90 1.llE-06 NO DATA 2.99E-08 NO DATA NO DATA 7.07E-05 7.24E-05 i
i Y 91M 1.37E-10 NO DATA
.4.98E-12 NO DATA NO DATA 7.60E-07 4.64E-07 Y 91 2.47E-04 NO DATA 6.59E-06 NO DATA NO DATA 7.10E-04 4.97E-05 Y 92 5.50E-09 NO DATA 1.57E-10 NO DATA NO DATA 6.46E-06 6.46E-05 i
i
- Taken fran Regulatory Guide 1.109 (Rev.1)
A-10
. - - ~
TABLE A,2--3 (cont'd)
INHALATION L3E FAC'IORS FOR OIIID (MREM PER PCI INHALED)
NUCLIDE BONE LIVER T BCDY 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 ZR 95 5.13E-05 1.13E-05 1.00E-05 NO DATA 1.61E-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 NB 95 6.35E-06 2.48E-06 1.77E-06 NO DATA 2.33E-06 1.66E-04 1.00E-05 MO 99 NO DATA 4.66E-08 1.15E-08 NO DATA 1.06E-07 3.66E-05 3.42E-05
'IC 99M 4.81E-13 9.41E-13 1.56E-ll NO DATA 1.37E-ll 2.57E-07 1.30E-06 TC 101 2.19E-14 2.30E-14 2.91E-13 NO DATA 3.92E-13 1.58E-07 4.41E-09 RU 103 7.55E-07 NO DATA 2.90E-07 NO DATA 1.90E-06 1.79E-04 1.21E-05 RU 105 4.13E-10 NO DATA 1.50E-10 NO DATA 3.63E-10 4.30E-06 2.69E-05 RU 106 3.68E-05 NO DATA 4.57E-06 PO DATA 4.97E-05 3.87E-03 1.16E-04 AG 110M 4.56E-06 3.08E-06 2.47E-06 NO EATA 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 127M 6.72E-06 2.31E-06 8.16E-07 1.64E-06 1.72E-05 4.00E-04 1.93E-05 TE 127 7.49E-10 2.57E-10 1.65E-10 5.30E-10 1.91E-09 2.71E-06 1.52E-05 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-ll 9.45E-12 6.44E-12 1.93E-ll 6.94E-ll 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 l
TE 132 1.30E-07 7.36E-08 7.12E-08 8.58E-08 4.79E-07 1.02E-04 3.72E-05 I 130-2.21E-06 4.43E-06 2.28E-06 4.99E-04 6.61E-06 NO DATA 1.38E-06 I 131 1.30E-05 1.30E-05 7.37E-06 4.39E-03 2.13E-05 NO DATA 7.68E-07 I 132 5.72E-07 1.10E-06 5.07E-07 5.23E-05 1.69E-06 NO IRTA 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 10 DATA 8.93E-05 3.27E-05 1.04E-06 CS 136 1.76E-05 4.62E-05 3.14E-05 NO DATA 2.58E-05 3.93E-06 1.13E-06 CS 137 2.45E-04 2.23E-04 3.47E-05 NO DATA 7.63E-05 2.81E-05 9.78E-07 CS 138 1.71E-07 2.27E-07 1.50E-07 10 DATA 1.68E-07 1.84E-08 7.29E-08 BA 139 4.98E-10 2.66E-13 1.45E-ll NO DATA 2.33E-13 1.56E-06 1.56E-05 A-11
TABLE A.2-3 (cont'd)
INHAIATIN DOSE FACIORS FOR CHIID (MREM PER PCI INHALED)
NUCLIDE BONE LIVER T BODY THYBOID KIDNEY IUNG GI-LLI BA 140 2.00E-05 1.75E-08 1.17E-06 NO DATA 5.7]E-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 7.44f-08 BA 142 1.35E-ll 9.73E-15 7.54E-13 NO DATA 7.87E-15 4.44E-07 7.41E-10
.., ' 40 1.74E-07 '6.08E-08 2.04E-08 NO DATA NO DATA 4.94E-05 6.10E-05 LA 142 3.50E-10 1.llE-10 3.49E-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 to DATA 2.64E-12 4.23E-07 5.32E-08 ND 147 2.92E-06 2.36E-06 1.84E-07 NO DATA 1.30E-06 8.87E-05 2.22E-05 W 187 4.41E-09 2.61E-09 1.17E-09 NO DATA NO DATA 1.llE-05 2.46E-05 NP 239 1.26E-07 9.04E-09 6.35E-09 NO DATA 2.63E-08 1.57E-05 1.73E-05 l
A-12
TABLE A.2-4*
INHALATION DOSE FACIORS FOR INFANI' (MREM PER PCI INHALED) i NUCLIDE BONE LIVER T BODY THYROID KIDNEY WNG GI-LLI H
3 NO DATA 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 i
C 14 1.89E-05 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 NA 24 7.54E-06 '7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 P 32 1.45E-03 8.03E-05 5.53E-05 PO DATA NO DATA NO DATA 1.15E-05 CR 51 NO DATA NO DATA 6.39E-08 4.llE-08 9.45E-09 9.17E-06 2.55E-07 1
MN 54 NO DATA 1.81E-05 3.56E-06 NO DATA 3.56E-06 7.14E-04 5.04E-06 1
MN 56 NO DATA 1.10E-09 1.58E-10 NO DATA 7.86E-10 8.95E-06 5.12E-05 FE 55 1.41E-05 8.39E-06 2.38E-06 NO DATA NO DATA 6.21E-05 7.82E-07 FE 59 9.69E-06 1.68E-05 6.77E-06 10 DATA NO DATA 7.25E-04 1.77E-05 1
l i
i CO 58 10 DATA 8.71E-07 1.30E-06 10 DATA NO DATA 5.55E-04 7.95E-06 l
CO 60 NO DATA 5.73E 06 8.41E-06 10 DATA NO DATA 3.22E-03 2.28E-05 NI 63 2.42E-04 1.d6E-05 8.29E-06 NO DATA NO DATA 1.49E-04 1.73E-06 NI 65 1.71E-09 2.03E-10 8.79E-ll NO DATA NO DATA 5.80E-06 3.58E-05 CU 64 PO DATA 1.34E-09 5.53E-10 NO DATA 2.84E-09 6.64E-06 1.07E-05 ZN 65 1.38E-05 4.47E-05 2.22E-05 PO DATA 2.32E-05 4.62E-04 3.67E-05 ZN 69 3.85E-11 6.91E-11 5.13E-12 NO DATA 2.87E-ll 1.05E-06 9.44E-06 BR 83 NO DATA PO DATA 2.72E-07 NO DATA NO DATA NO DATA LT E-24 BR 84 NO DATA 10 DATA 2.86E-07 PO DATA NO DATA NO DATA LT E-24 BR 85 NO DATA NO DATA 1.46E-08 10 DATA NO DATA NO DATA LT E-24 RB 86 NO DATA 1.36E-04 6.30E-05 NO DATA NO DATA NO DATA 2.17E-06 RB 88 NO DATA 3.98E-07 2.05E-07 NO DATA NO DATA NO DATA 2.42E-07 RB 89 NO DATA 2.29E-07 1.47E-07
!O 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 PO DATA NO DATA 3.76E-05 5.24E-05 SR 92 7.50E-09 NO DATA 2.79E-10 NO DATA NO DATA 1.70E-05 1.00E-04 Y 90 2.35E-06 NO DATA 6.30E-08 10 DATA NO DATA 1.92E-04 7.43E-05 Y 91M 2.91E-10 PC DATA 9.90E-12 NO DATA NO DATA 1.99E-06 1.68E-06 Y 91 4.20E-04 to DATA 1.12E-05 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-05
- Taken frca Regulatory Guide 1.109 (Rev.1) l A-13 b
TABLE A,2-1 (cont'd)
IMIAIATION DOSE FAC'IORS ECR INFANP (MREM PER PCI I?: HALED)
NUCLIDE bCNE LIVER T BCri CNRCID KIDNEY LUNG GI-LLI Y 93 1.07E-07 NO DATA 2.91E-09 NO DATA NO DATA 5.46E-05 1.19E-04 ZR 95 8.24E-05 1.99E-05 1.45E-05 NO DATA 2.22E-05 1.25E-03 1.55E-05 ZR 97 1.07E-07 1.83E-08 8.36E-09 NO DETA 1.85E-08 7.88E-05 1.00E-04 NB 95 1.12E-05 4.59E-06 2.70E-06 NO DATA 3.37E-06 3.42E-04 9.05E-06 MO 99 to DATA 1.18E-07 2.31E-08 to DATA 1.89E-07 9.63E-05 3.48E-05
'IC 99M 9.98E-13 2.06E-12 2.66E-11 NO DATA 2.22E-ll 5.79E-07 1.45E-06 TC 101 4.65E-14 5.88E-14 5.80E-13 PO DATA 6.99E-13 4.17E-07 6.03E-07 RU 103 1.44E-06 NO DATA 4.85E-07 NO DATA 3.03E-06 3.94E-04 1.15E-05 RU 105 8.74E-10 10 DATA 2.93E-10 10 DATA 6.42E-10 1.12E-05 3.46E-05 RU 106 6.20E-05 NO DATA 7.77E-06 10 DATA 7.61E-05 8.26E-03 1.17E-04 AG 110M 7.13E-06 5.16E-06 3.57E-06 to 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 TE 127M 1.19E-05 4.93E-06 1.48E-06 3.48E-06 2.68E-05 9.37E-04 1.95E-05 TE 127 1.59E-09 6.81E-10 3.49E-10 1.32E-09 3.47E-09 7.39E-06 1.74E-05 TE 129M 1.01E-05 4.35E-06 1.59E-06 3.91E-06 2.27E-05 1.20E-03 4.93E-05 TE 129 5.63E-11 2.48E-ll 1.34E-ll 4.82E-11 1.25E-10 2.14E-06 1.88E-05 TE 131M 7.62E-08 3.93E-08 2.59E-08 6.38E-08 1.89E-07 1.42E-04 8.51E-05 TE 131 1.24E-ll 5.87E-12 3.57E-12 1.13E-11 2.85E-ll 1.47E-06 5.87E-06
[
TE 132 2.66E-07 1.69E-07 1.26E-07 1.99E-07 7.39E-07 2.43E-04 3.15E-05 I 130 4.54E-06 9.91E-06 3.98E-06 1.14E-03 1.09E-05 NO DATA 1.42E-06 I 131 2.71E-05 3.17E-05 1.40E-05 1.06E-02 3.70E-05 NO DATA 7.56E-07 l
l 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 l
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 CS 134 2.83E-04 5.02E-04 5.32E-05 10 DATA 1.36E-04 5.69E-05 9.53E-07 CS 136 3.45E-05 9.61E-05 3.78E-05 NO DATA 4.03E-05 8.40E-06 1.02E-06 CS 137 3.92E-04 4.37E-04 3.25E-05 PO DATA 1.23E-04 5.09E-05 9.53E-07 CS 138 3.61E-07 5.58E-07 2.84E-07 NO DATA 2.93E-07 4.67E-08 6.26E-07 BA 139 1.06E-09 7.03E-13 3.07E-ll NO DATA 4.23E-13 4.25E-06 3.64E-05 A-14
TABLE A.2-4 (cont'd)
INHAIATION DOSE FAC'IORS EDR INFANT (MRDi PER PCI INHALED)
NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI BA 140 4.00E-05 4.00E-08 2.07E-06 NO DATA 9.59E-09 1.14E-03 2.74E-05 BA 141 1.12E-10 7.70E-14 3.55E-12 NO DATA 4.64E-14 2.12E-06 3.39E-06 BA 142 2.84E-11 2.36E-14 1.40E-12 NO DATA 1.36E-14 1.llE-06 4.95E-07 LA 140 3.61E-07 1.43E-07 3.68E-08 NO DATA NO DATA 1.20E-04 6.06E-05 LA 142 7.36E-10 2.69E-10 6.46E-ll NO DATA NO DATA 5.87E-06 4.25E-05 CE 141 1.98E-05 1.19E-05 1.42E-06 m DATA 3.75E-06 3.69E-04 1.54E-05 CE 143 2.09E-07 1.38E-07 1.58E-08 NO DATA 4.03E-08 8.30E-05 3.55E-05 CE 144 2.28E-03 8.65E-04 1.26E-04 NO DATA 3.84E-04 7.03E-03 1.06E-04 PR 143 1.00E-05 3.74E-06 4.99E-07 10 DATA 1.41E-06 3.09E-04 2.66E-05 PR 144 3.42E-11 1.32E-ll 1.72E-12 NO DATA 4.80E-12 1.15E-06 3.06E-06 ND 147 5.67E-06 5.81E-06 3.57E-07 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 to DATA 4.73E-08 4.25E-05 1.78E-05 A-15
~
. TABLE A.2-5*
EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND 2
(mrem /hr per pCi/m )
e.
Element Total Body Skin H-3 0.0 0.0 C-14 0.0 0.0 NA-24' 2.50E-08 2.90E-08 P-32 0.0 0.0 Cr-51 2.20E-10 2.60E-10 i
Mn-54 5.80E-09 6.80E-09 Mn-56 1.10E-08 1.30E-08
.Fe-55 0.0 0.0 Fe 8.00E-09 9.40E-09 Co-58 7.00E-09 8.20E-09 Co-60 1.70E-08 2.00E-08 Ni-63 0.0 0.0 Nr-65 3.70E-09 4.30E-09 Cu-64 1.50E-09 1.70E-09 Zn-65 4.00E-09 4.600-09 Zn-69 0.0 0.0
-Br-83 6.40E-ll 9.30E-ll Br-84 1.20E-08 1.4 0E-08 Br-85 0.0 0.0 Rb-86 6.30E-10 7.20E-10 Rb-88 3.50E-09 4.00E-09 Rb-89 1.50E-08 1.80E-08 Sr 5.60E-13 6.50E-13 Sr-91 7.10E-09 8.30E-09 i
Sr-92 9.00E-09 1.00E-08 Y-90 2.20E-12 2.60E-32 Y-91M.
3.80E-09 4.40E-09 Y-91 2.40E-11 2.70E-ll
'Y-92 1.60E-09 1.90E-09 Y-93 5.70E-10 7.80E-10 l
Zr-95 5.00E-09 5.80E-09 l
'Zr-97 5.50E-09 6.40E-09 l
Nb-95 5.10E-09 6.00E-09 Mo-99 1.90E-09 2.20E-09 Tc-99M 9.60E-10 1.10E-09 Tc-101 2.70E-09 3.00E-09 Ru-103 3.60E-09 4.20E-09 Ru-105 4.50E-09 5.10E-09 Ru-106 1.50E-09 1.80E-09 Ag-110M 1.80E-08 2.10E-08 Te-125M 3.50E-11 4.80E-ll Te-127M-1.10E-12 1.30E-12 Te-127 1.00E-ll 1.10E-ll l-Te-129M 7.70E-10 9.00E-10 l
Te-129 7.10E-10 8.40E-10
- Taken from Regulatory Guide 1.109 (Rev. 1) i l
A-16
TABLE A.2-5 (cont'd)
~
EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND 2
(mrem /hr per pCi/m )
Element.
Total Body Skin
-Te-131M 8.40E-09 9.90E-09
.Te-131 2.20E-09 2.60E-06 Te-132 1.70E-09 2.00E-09 I-130 1.40E-08 1.70E-08 I-131 2.80E-09 3.40E-09
-I-132 1.70E-08 2.00E-08 I-133 3.70E-09 4.50E-09 I-134 1.60E-08 1.90E-08 I-135 1.20E-08 1.40E-08 Cs-134 1.20E-08 1.40E-08 Cs-136 1.50E-08 1.70E-08 Cs-137 4.20E-09 4.90E-09 Cs-138 2.10E-08 2.40E-08 Ba-139 2.40E-09 2.70E-09 Ba-140 2.10E-09 2.4 0E-09 Ba-141 4.30E-09 4.90E-09 Ba-142 7.90E-09 9.00E-09 La-140 1.50E-08 1.70E-08 La-142 1.50E-08 1.80E-08 Ce-141 5.50E-10 6.20E-10 Ce-143 2.20E-09 2.50E-09 Ce-144 3.20E-10 3.70E-10 Pr-143 0.0 0.0 Pr-144 2.00E-10 2.30E-10 Nd-147 1.00E-09 1.20E-09 W-187 3.10E-09 3.60E-09 Np-239 9.50E-10 1.10E-09 i
i r
l k'
I i
I A-17 l
TABLE A 3-l*
INGESPION DOSE FACIORS FOR ADULTS (MREM PER PCI INGESTED)
NUCLIDE BONE LIVER T BODY
'IEYROID KIDNEY WNG GI-LLI
~
H 3
NO DATA 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 C 14 2.84E-06 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 NA 24 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-05 P 32 1.93E-04 1.20E-05 7.46E-06 NO DATA NO DATA NO DATA 2.17E-05 CR 51 NO DATA NO DATA 2.66E-09 1.59E-09 5.86E-10 3.53E-09 6.69E-07 MN 54 NO DATA 4.57E-06 8.72S-07 to 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 10 DATA to DATA 1.06E-06 1.09E-06 FE 59 4.34E-06 1.02E-05 3.91E-06 NO DATA NO DATA 2.85E-06 3.40E-05 CO 58 NO DATA 7.45E-07 1.67E-06 PO DATA NO DATA NO DATA 1.51E-05 CO 60 to DATA 2.14E-06 4.72E-06 10 DATA NO DATA NO DATA 4.02E-05 NI 63 1.30E-04 9.01E-06 4.36E-06 NO DATA NO DATA NO DATA 1.88E-06 NI 65 5.28E-07 6.86E 3.13E-08 NO DATA NO DATA 10 DATA 1.74E-06 CU 64 NO DATA 8.33E-08 3.91E-08 10 DATA 2.10E-07 NO DATA 7.10E-06 ZN 65 4.84E-06 1.54E-05 6.96E-06 NO DATA 1.03E-05 NO DATA 9.70E-06 ZN 69 1.03E-08 1.97E-08 1.37E-09 to DATA 1.28E-08 NO DATA 2.96E-09 BR 83 NO DATA NO DATA 4.02E-08 NO DATA NO DATA 10 DATA 5.79E-08 BR 84 NO DATA 10 DATA 5.21E-08 10 DATA NO DATA NO DATA 4.09E-13 BR 85 NO DATA NO DATA 2.14E-09 NO DATA NO DATA NO DATA LT E-24 RB 86 NO DATA 2.llE-05 9.83E-06 NO DATA BO 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 l
SR 89 3.08E-04 NO DA'"A 8.84E-06 NO DATA 10 DATA NO DATA 4.94E-05 SR 90 7.58E-03 10 DATA 1.86E-03 NO DATA NO DATA NO DATA 2.19E-04 SR 91 5.67E-06 NO DATA 2.29E-07 NO DATA NO DATA NO DATA 2.70E-05 SR 92 2.15E-06 NO DATA 9.30E-08 10 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-ll 10 DATA 3.52E-12 NO DATA NO DATA NO DATA 2.67E-10 Y 91 1.41E-07 NO DATA 3.77E-09 to DATA NO DATA NO DATA 7.76E-05 Y 92 8.45E-10 NO DATA 2.47E-ll NO DATA NO DATA NO DATA 1.48E-05
- Taken from Regulatory Guide 1.109 (Rev.1)
A-18 t
TABLE A.3-1 (cont'd)
INGESTION DOSE F/CIORS FOR ADULTS (MREM PER PCI INGESTED)
NUCLIDE BONE LIVER T BODY
'IEYROID KIDNEY WNG GI-LLI Y 93 2.68E-09 NO DATA 7.40E-ll BO DATA NO DATA NO DATA 8.50E-05 ZR 95 3.04E-08 9.75E-09 6.60E-09 to 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 to DATA 3.42E-09 NO DATA 2.10E-05 MO 99 NO DATA 4.31E-06 8.20E-07 10 DATA 9.76E-06 NO DATA 9.99E-06 TC 99M 2.47E-10 6.98E-10 8.89E-09 NO DATA 1.06E-08 3.42E-10 4.13E-07 TC 101 2.54E-10 3.66E-10 3.59E-09 NO DATA 6.59E-09 1.87E-10 1.30E-21 RU 103 1.85E-07 NO DATA 7.97E-08 10 DATA 7.06E-07 NO DATA 2.16E-05 RU 105 1.54E-08 NO DATA 6.08E-09 10 DATA 1.99E-07 NO DATA 9.42E-06 RU 106 2.75E-06 NO DATA 3.48E-07 BO DATA 5.31E-06 10 DATA 1.78E-04 AG 110M 1.60E-07 1.48E-07 8.79E-08 NO DATA 2.91E-07 NO DATA 6.04E-05 TE 125M 2.68E-06 9.71E-07 3.59E-07 8.06E-07 1.09E-05 NO DATA 1.07E-05 TE 127M 6.77E-06 2.42E-06 8.25E-07 1.73E-06 2.75E-05 NO DATA 2.27E-05 TE 127 1.10E-07 3.95E-08 2.38E-08 8.15E-08 4.48E-07 10 DATA 8.68E-06 TE 129M 1.15E-05 4.29E-06 1.82E-06 3.95E-06 4.80E-05 NO DATA 5.79E-05 TE 129 3.14E-08 1.18E-08 7.65E-09 2.41E-08 1.32E-07 NO DATA 2.37E-08 TE 131M 1.73E-06 8.46E-07 7.05E-07 1.34E-06 8.57E-06 NO DATA 8.40E-05 TE 131 1.972-08 6.23E-09 6.22E-09 1.62E-08 8.63E-08 NO DATA 2.79E-09 TE 132 2.52E-06 1.63E-06 1.53E-06 1.80E-06 1.57E-05 NO DATA 7.71E-05 I 130 7.56E-07 2.23E-06 8.80E-07 1.89E-04 3.48E-06 NO DATA 1.92E-06 I 131 4.16E-06 5.95E-06 3.41E-06 1.95E-03 1.02E-05 NO DATA 1.57E-06 t
i 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 l
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 10 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 l
CS 137 7.97E-05 1.09E-04 7.14E-05 NO DATA 3.70E-05 1.23E-05 2.llE-06 CS 138 5.52E-08 1.09E-07 5.40E-08 NO DATA 8.01E-08 7.91E-09 4.65E-l.,
BA 139 9.70E-08 6.91E-ll 2.84E-09 NO DATA 6.46E-11 3.92E-ll 1.72E-07 A-19 t
TABLE A.3-1 (cont'd)
INGESTI(E DOSE FACTORS FOR ADULTS (MREM PER PCI INGESTED)
NUCLIDE BONE LIVER T BODY THYROID KIDNEY IUNG 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-11 1.59E-09 NO DATA 3.31E-11 2.02E-11 2.22E-17 BA 142 2.13E-08 2.19E-ll 1.34E-09 NO DATA 1.85E-ll 1.24E-11 3.00E-26 LA 140 2.50E-09 1.26E-09 3.33E-10 NO DATA NO DATA NO DATA 9.25E-05 IA 142 1.28E-10 5.82E-ll 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 DA'1A 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-ll 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-ll NO DATA 3.65E-10 NO DATA 2.40E-05 A-20
TABLE A.3-2*
INGESTION DOSS FACIORS EDR TEENEGERS (MREM PER PCI INGESTED)
NUCLIDE BONE LIVER T BODY
'IHYROID KIDNEY IUNG G 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 2.76E-04 1.71E-05 1.07E-05 NO DATA NO DATA NO DATA 2.32E-05 CR 51 NO DATA NO DATA 3.60E-09 2.00E-09 7.89E-10 5.14E-09 6.05E-07 MN 54 NO DATA 5.90E-06 1.17E-06 NO DATA 1.76E-06 NO DATA 1.21E-05 MN 56 NO DATA 1.58E-07 2.81E-08 NO DATA 2.00E-07 NO DATA 1.04E-05 FE 55 3.78E-06 2.68E-06 6.25E-07 NO DATA NO DATA 1.70E-06 1.16E-06 FE 59 5.87E-06 1.37E-05 5.29E-06 NO DATA NO DATA 4.32E-06 3.24E-05 00 58 NO DATA 9.72E-07 2.24E-06 NO DATA NO DATA NO DATA 1.34E-05 CO 60 10 DATA 2.81E-06 6.33E-06 NO DATA NO DATA NO DATA 3.66E-05 NI 63 1.77E-04 1.25E-05 6.00E-06 NO DATA NO DATA NO DATA 1.99E-06 NI 65 7.49E-07 9.57E-08 4.36E-08 NO DATA NO DATA NO DATA 5.19E-06 CU 64 NO DATA 1.15E-07 5.41E-08 NO DATA 2.91E-07 NO DATA 8.92E-06 ZN 65 5.76E-06 2.00E-05 9.33E-06 NO DATA 1.28E-05 NO DATA 8.47E-06 ZN 69 1.47E-08 2.80E-08 1.96E-09 NO DATA 1.83E-08 NO DATA 5.16E-08 BR 83 NO DATA NO DATA 5.74E-08 NO DATA NO DATA NO DATA LT E-24 BR 84 NO DATA NO DATA 7.22E-08 NO DATA NO DATA NO DATA Lt E-24 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 7 DATA 7.30E-15 RB 89 NO DATA 5.50E-08 3.89E-08 NO DATA NO DATA NO DATA 8.43E-17 SR 89 4.40E-04 NO DATA 1.26E-05 NO DATA NO DATA NO DATA 5.24E-05 SR 90 8.30E-03 NO DATA 2.05E-03 NO DATA NO DATA NO DATA 2.33E-04 SR 91 8.07E-06 PO DATA 3.21E-07 NO DATA NO DATA NO DATA 3.66E-05 SR 92 3.05E-06 NO DATA 1.30E-07 NO DATA NO DATA NO DATA 7.77E-05 Y 90 1.37E-08 NO DATA 3.69E-10 NO DATA NO DATA NO DATA 1.13E-04 Y 91M 1.29E-10 NO DATA 4.93E-12 NO DATA NO DATA NO DATA 6.09E-09 Y 91 2.01E-07 NO DATA 5.39E-09 NO DATA NO DATA NO DATA 8.24E-05 Y 92 1.21E-09 NO DATA 3.50E-ll NO DATA NO DATA NO DATA 3.32E-05
- Taken frcm Regulatory Guide 1.109 (Rev.1)
A-21
TABLE A.3-2 (cont'd)
INGESTICN DOSE FACIORS FOR TEENAGERS (MREM PER PCI INGESTED)
NUCLIDE BONE LIVER T BODY
'IHYROID KIDNEY IUNG 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.llE-10 NO DATA 1.27E-04 NB 95 8.22E-09 4.56E-09 2.51E-09 NO DATA 4.42E-09 NO DATA 1.95E-05 MO 99 NO DATA 6.03E-06 1.15E-06 NO DATA 1.38E-05 NO DATA 1.08E-05 l
'IC 99M 3.32E-10 9.26E-10 1.20E-08 NO DATA 1.38E-08 5.14E-10 6.08E-07
'IC 101 3.60E-10 5.12E-10 5.03E-09 NO DATA 9.26E-09 3.12E-10 8.75E-17 RU 103 2.55E-07 NO DATA 1.09E-07 NO DATA 8.99E-07 NO DATA 2.13E-05 RU 105 2.18E-08 NO DATA 8.46E-09 NO DATA 2.75E-07 NO DA%
1.76E-05 RU 106 3.92E-06 NO DATA 4.94E-07 NO DATA 7.56E-06 NO DATA 1.88E-04 AG 110M 2.05E-07 1.94E-07 1.18E -07 NO DATA 3.70E-07 NO DATA 5.45E-05 TE 125M 3.83E-06 1.38E-06 5.12E-07 1.07E-06 NO DATA NO DATA 1.13E-05 TE 127M 9.67E-06 3.43E-06 1.15E-06 2.30E-06 3.92E-05 NO DATA 2.41E-05 TE 127 1.58E-07 5.60E-08 3.40E-08 1.09E-07 6.40E-07 NO DATA 1.22E-05 TE 129M 1.63E-05 6.05E-06 2.58E-06 5.26E-06 6.82E-05 NO DATA 6.12E-05 TE 129 4.48E-08 1.67E-08 1.09E-08 3.20E-08 1.88E-07 NO DATA 2.45E-07 TE 131*.1 2.44E-06 1.17E-06 9.76E-07 1.76E-06 1.22E-05 m DATA 9.39E-05 TE 13i 2.79E-08 1.15E-08 8.72E-09 2.15E-08 1.22E-07 NO DATA 2.29E-09 i
i TE 111 3.49E-06 2.21E-06 2.08E-06 2.33E-06 2.12E-05 NO DATA 7.00E-05 I lh 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 5.10E-09 l
I 135 6.10E-07 1.57E-06 5.82E-07 1.01E-04 2.48E-06 NO DATA 1.74E-06 CS 134 8.37E-05 1.97E-04 9.14E-05 NO DATA 6.26E-05 2.39E-05 2.45E-06 CS 136 8.59E-06 3.38E-05 2.27E-05 NO DATA 1.84E-05 2.90E-06 2.72E-06 CS 137 1.12E-04 1.49E-04 5.19E-05 NO DATA 5.07E-05 1.97E-05 2.12E-06 CS 138 7.76E-08 1.49E-07 7.45E-08 m DATA 1.10E-07 1.28E-08 6.76E-ll BA 139 1.39E-07 9.78E-ll 4.05E-09 NO DATA 9.22E-ll 6.74E-ll 1.24E-06 A-22
TABLE A.3-2 (cont'd)
INGESPION DOSE FACIORS FOR TEDRGERS (MREM PER PCI IN3ESTED)
NUCLIDE BONE LIVER T BODY
'IEYROID KIINEY IUNG GI-LLI BA 140 2.84E-05 3.48E-08 1.83E-06 NO DATA 1.18E-08 2.34E-08 4.38E-05 BA 141 6.71E-08 5.01E-11 2.24E-09 NO DATA 4.65E-11 3.43E-11 1.43E-13 BA 142 2.99E-08 2.99E-11 1.84E-09 NO DATA 2.53E-ll 1.99E-ll 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 PATA NO DATA NO DATA 2.42E-06 CE 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 NO 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-ll 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 9.22E-ll NO DATA 5.21E-10 NO DATA 2.67E-05 l
l 1
\\
t A-23 l
w TABLE A.3-3*
INGESTION DOSE FACIORS EUR CHILD (MREM PER PCI INGESI'ED)
NUCLIDE BONE LIVER T BODY THYROID KIDNEY IUNG GI-LLI H
3 NO DATA 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 C 14 1.21E-05 2.42E-06
-2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 NA 24 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 P 32 8.25E-04 3.86E-05 3.18E-05 NO DATA NO DATA NO DATA 2.28E-05 CR 51 NO DATA NO DATA 8.90E-09 4.94E-09 1.35E-09 9.02E-09 4.72E-07 MN 54 NO DATA 1.07E-05 2.85E-06 NO DATA 3.00E-06 NO DATA 8.98E-06 MN 56 NO DATA 3.34E-07 7.54E-08 NO DATA 4.04E-07 NO DATA 4.84E-05 FE 55 1.15E-05 6.10E-06 1.89E-06 NO DATA NO DATA 3.45E-06 1.13E-06 FE 59 1.65E-05 2.67E-05 1.33E-05 NO DATA NO DATA 7.74E-06 2.78E-05 CO 58 NO DATA 1.80E-06 5.51E-06 NO DATA E DATA NO DATA 1.05E-05 CO 60 m DATA 5.29E-06 1.56E-05 NO DATA NO DATA NO DATA 2.93E-05 NI 63 5.38E-04 2.88E-05 1.83E-05 NO DATA NO DATA NO DATA 1.94E-06 NI 65 2.22E-06 2.09E-07 1.22E-07 NO DATA NO DATA NO DATA 2.56E-05 CU 64 NO DATA 2.45E-07 1.48E-07 NO DATA 5.92E-07 NO DATA 1.15E-05 ZN 65 1.37E-05 3.65E-05 2.27E-05 NO DATA 2.30E-05 NO DATA 6.41E-06 I
l ZN 69 4.38E-08 6.33E-08 5.85E-09 NO DATA 3.84E-08 NO DATA 3.99E-06 BR 83 NO DATA NO DATA 1.71E-07 NO DATA NO DATA NO DATA LT E-24 BR 84 NO DATA NO DATA 1.98E-07 NO DATA NO DATA NO DATA LT E-24 I
BR 85 NO DATA NO DATA 9.12E-09 NO DATA NO DATA NO DATA LT E-24 RB 86 NO DATA 6.70E-05 4.12E-05 NO DATA NO DATA NO DATA 4.31E-06 RB 88 NO DATA 1.90E-07 1.32E-07 NO DATA NO DATA NO DATA 9.32E-09 l
PB 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 DA"JA NO DATA NO DATA 2.29E-04 SR 91 2.40E-05 NO DATA 9.06E-07 NO DATA NO DATA NO DATA 5.30E-05 SR 92 9.03E-06 NO DATA 3.62E-07 NO DATA NO DATA NO DATA 1.71E-04 Y 90 4.llE-08 NO DATA 1.10E-09 NO DATA NO DATA NO DATA 1.17E-04 I
Y 91M 3.82E-10 NO DATA 1.39E-11 NO DATA NO DATA NO DATA 7.48E-07 Y 91 6.02E-07 NO DATA 1.61E-08 NO DATA NO DATA NO DATA 8.02E-05 Y 92 3.60E-09 NO DATA 1.03E-10 NO DATA NO DATA NO DATA 1.04E-04
- Taken frcm Regulatory Guide 1.109 (Rev.1)
A-24
TABLE A.3-3 (cont'd)
INGESTION DOSE FACIORS FOR CHILD (MREM PER PCI INGESTED)
NUCLIDE BCNE LIVER T BODY
'IEYROID KIDNEY UJNG GI-LLI Y 93 1.14E-08 NO DATA 3.13E-10 NO DATA NO DATA NO DATA 1.70E-04 ZR 95 1.16E-07 2.55E-08 2.27E-08 NO DATA 3.65E-08 NO DATA 2.66E-05 ZR 97 6.99E-09 1.01E-09 5.96E-10 NO DATA 1.45E-09 NO DATA 1.53E-04 NB 95 2.25E-08 8.75E-09 6.26E-09 NO DATA 8.23E-09 NO DATA 1.62E-05 MO 99 NO DATA 1.33E-05 3.29E-06 NO DATA 2.84E-05 BD DATA 1.10E-05 l~
'IC -99M 9.23E-10 1.81E-09 3.00E-08 NO DATA 2.63E-08 9.19E-10 1.03E-06 TC 101 1.07E-09 1.12E-09 1.42E-08 NO DATA 1.91E-08 5.92E-10 3.56E-09 RU 103 7.31E-07 NO DATA 2.81E-07 NO DATA 1.84E-06 NO DATA 1.89E-05 I
RU 105 6.45E-08 NO DATA 2.34E-08 NO DATA 5.67E-07 NO DATA 4.21E-05 RU 106 1.17E-05 NO DATA 1.46E-06 NO DATA 1.58E-05 NO DATA 1.82E-04 1G 110M 5.39E-07 3.64E-07 2.91E-07 NO DATA 6.78E-07 NO DATA 4.33E-05 TE 125M 1.14E-05 3.09E-06 1.52E-06 3.20E-06 NO DATA NO DATA 1.10E-05 TE 127M 2.89E-05 7.78E-06 3.43E-06 6.91E-06 8.24E-05 NO DATA 2.34E-05 TE 127 4.71E-07 1.27E-07 1.01E-07 3.26E-07 1.34E-06 NO DATA 1.84E-05 TE 129M 4.87E-05 1.36E-05 7.56E-06 1.57E-05 1.43E-04 NO DATA 5.94E-05 i
i TE 129 1.34E-07 3.74E-38 3.18E-08 9.56E-08 3.92E-07 NO DATA 8.34E-06 TE 131M 7.20E-06 2.49E-06 2.65E-06 5.12E-06 2.41E-05 NO DATA 1.01E-04 TE 131 8.30E-08 2.53E-08 2.47E-08 6.35E-08 2.51E-07 NO DATA 4.36E-07 TE 132 1.01E-05 4.47E-06 5.40E-06 6.51E-06 4.15E-05 NO DATA 4.50E-05 I 130 2.92E-06 5.90E-06 3.04E-06 6.50E-04 8.82E-06 NO DATA 2.76E-06 I 131 1.72E-05 1.73E-05 9.83E-06 5.72E-03 2.04E-05 NO DATA 1.54E-06 I 132 8.00E-07 1.47E-06 6.76E-07 6.82E-05 2.25E-06 BD DATA 1.73E-06 I 133 5.92E-06 7.32E-06 2.77E-06 1.36E-03 1.22E-05 NO DATA 2.95E-06 i
l I 134 4.19E-07 7.78E-07 3.58E-07 1.79E-05 1.19E-06 NO DATA 5.16E-07 I 135 1.75E-06 3.15E-06 1.49E-06 2.79E-04 4.83E-06 NO DATA 2.40E-06 CS 134 2.34E-04 3.84E-04 8.10E-05 NO DATA 1.19E-04 4.27E-05 2.07E-06 CS 136 2.35E-05 6.46E-05 4.18E-05 NO DATA 3.44E-05 5.13E-06 2.27E-06 CS 137 3.27E-04 3.13E-04 4.62E-05 NO DATA 3.02E-04 3.67E-05 1.96E-06 CS 138 2.28E-07 3.17E-07 2.01E-07 NO DATA 2.23E-07 2.40E-08 1.46E-07 BA 139 4.14E-07 2.21E-10 1.20E-08 NO DATA 1.93E-10 1.30E-10 2.39E-05 A-25
TABLE A.3-3 '(cont'd)
INGESTION DOSE FACIORS FOR CHILD (MREM PER PCI INGESTED)
NUCLIDE BONE LIVER T BODY THYROID KIENEY IUNG 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 LA 140 1.01E-08 3.53E-09 1.19E-09 PO DATA NO DATA NO DATA 9.84E-05 IA 142 5.24E-10 1.67E-10 5.23E-ll NO DATA NO DAB NO DATA 3.31E-05 CE 141 3.97E-08 1.98E-08 2.94E-09 NO DATA 8.68E-09 NO DATA 2.47E-05 CE 143 6.99E-09 3.79E-06 5.49E-10 NO DATA 1.59E-09 NO DATA 5.55E-05 CE 144 2.08E-06 6.52E-07 1.llE-07 NO DATA 3.61E-07 NO DATA 1.70 E-04 PP. 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 A-26
TABLE A.3-4*
INGESPION DOSE FACIORS FOR INFANT (MREM PER PCI IBGESTED)
NUCLIDE BONE LIVER T BCDY
'IHYROID KIDNEY LUNG GI-LLI H
3 NO DATA 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 C 14 2.37E-05 5.063-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 NA 24 1.0lE-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.0lE-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 2.0lE-09 1.79E-08 4.llE-07 MN 54 NO DATA 1.99E-05 4.51E-06 NO DATA 4.41E-06 NO DATA 7.31E-06 MN 56 NO DATA 8.18E-07 1.41E-07 NO DATA 7.03E-07 NO DATA 7.43E-05 FE 55 1.39E-05 8.98E-06 2.40E-06 NO DATA NO DATA 4.39E-06 1.14E-06
- FE 59 3.08E-05 5.38E-05 2.12E-05 NO DATA NO DATA 1.59E-05 2.57E-05 00 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 10 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 l
ZN 69 9.33E-08 1.68E-07
.1.25E-08 NO DATA 6.98E-08 NO DATA 1.37E-05 BR 83 10 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 l
BR 85 NO DATA NO DATA 1.94E-08 NO DATA NO DATA NO DATA LT E-24 l
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 PO IRTA NO DATA NO DATA 5.16E-05 SR 90 1.85E-02 NO DATA 4.71E-03 NO DATA NO DATA NO DATA 2.31E-04 SR 91 5.00E-05 NO DATA 1.81E-06 NO DATA NO DATA NO DATA 5.92E-05 SR 92 1.92E-05 NO DATA 7.13E-07 NO DATA NO DATA NO DATA 2.07E-04 Y 90 8.69E-08 NO DATA 2.33E-09 NO DATA NO DATA NO DATA 1.20E-04 Y 91M 8.10E-10 NO DATA 2.76E-ll NO DATA NO DATA NO DATA 2.70E-06 l
Y 91 1.13E-06 NO DATA 3.01E-08 NO DATA NO DATA NO DATA 8.10E-05 i
Y 92 7.65E-09 NO DATA 2.15E-10 NO DATA NO DATA NO DATA 1.46E-04 l
- Taken frm Regulatory Guide 1.109. (Rev.1)
A-27
TABLE A.3-4 (cont'd)
IN3ESTION DOSE FACIORS FOR INFANT (MREM PER PCI INGESTED)
NUCLIDE BONE LIVER T BODY
'IEYROID KIDNEY WNG GI-LLI Y 93 2.43E-08 NO DATA 6.62E-10 NO DATA NO DATA NO DATA 1.92E-04 ZR 95 2.06E-07 5.02E-08 3.56E-08 NO DATA 5.41E-08 NO DATA 2.50E-05 ZR 97 1.48E-08 2,54E-09 1.16E-09 10 DATA 2.56E-09 10 DATA 1.62E-04 NB 95 4.20E-08 1.73E-08 1.00E-08 NO DATA 1.24E-08 NO DATA 1.46E-05 MO 99 NO DATA 3.40E-05 6.63E-06 NO DATA 5.08E-05 NO DATA 1.12E-05
'IC 99M 1.92E-09 3.96E-09 5.10E-08 NO DATA 4.26E-08 2.07E-09 1.15E-06 TC 101 2.27E-09 2.86E-09 2.83E-08 NO DATA 3.40E-08 1.56E-09 4.86E-07 RU 103 1.48E-06 NO DATA 4.95E-07 NO DATP.
3.08E-06 NO DATA 1.80E-05 RU 105 1.36E-07 NO DATA 4.58E-08 NO DATA 1.00E-06 NO DATA 5.41E-05 RU 106 2.41E-05 NO DATA 3.01E-06 NO DATA 2.85E-05 NO DATA 1.83E-04 AG 110M 9.96E-07 7.27E-07 4.81E-07 NO DATA 1.04E-06 NO DATA 3.77E-05 TE 125M 2.33E-05 7.79E-06 3.15E-06 7.84E-06 NO DATA NO DATA 1.llE-05 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 10 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 2 31M 1.52E-05 6.12E-06 5.05E-06 1.24E-05 4.21E-05 NO DATA 1.03E-04
. TE 131 1.76E-07 6.50E-08 4.94E-08 1.57E-07 4.50E-07 NO DATA 7.llE-06 TE 132 2.08E-05 1.03E-05 9.61E-06 1.52E-05 6.44E-05 NO DATA 3.81E-05 I 130-6.00E-06 1.32E-05 5.30E-06 1.48E-03 1.45E-05 NO DATA 2.83E-06 I 131 3.59E-05 4.23E-05 1.86E-05 1.39E-02 4.94E-05 NO DATA 1.51E-06 I 132 1.66E-06 3.37E-06 1.20E-06 1.58E-04 3.76E-06 NO DATA 2.73E-06 I 133 1.25E-05 1.82E-05 5.33E-06 3.31E-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 I 135 3.64E-06 7.24E-06 2.64E-06 6.49E-04 8.07E-06 NO DAfA 2.62E-06 CS 134 3.77E-04 7.03E-04 7.10E-05 NO DATA 1.81E-04 7.42E-05 1.91E-06 CS 136 4.598-05 1.35E-04 5.04E-05 NO DATA 5.38E-05 1.10E-05 2.05E-06 CS 137 5.22E-04 6.llE-04 4.33E-05 NO DATA 1.64E-04 6.64E-05 1.91E-06 CS 138
-4.81E-07 7.82E-07 3.79E-07 NO DATA 3.90E-07 6.09E-08 1.25E-06 BA 339 8.81E-07 5.84E-10 2.55E-08 NO DATA 3.51E-10 3.54E-10 5.58E-05 A-28
GBLE A.3-4 (cont'd) i 1
l IEESTION DOSE FACIORS FOR INFANT (MREM PER PCI INGESTED) i NUCLIDE BONE LIVER T BODY
'IEYROID KIDNEY URE GI-LLI i
BA 140 1.71E-04 1.71E-07 8.81E-06 NO DATA 4.06E-08 1.05E-07 4.20E-05 l
BA 141 4.25E-07 2.91E-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 LA 140 2.11E-08 8.32E-09 2.14E-09 10 DATA NO DATA NO DATA 9.77E-05 IA 142 1.10E-09 4.04E-10 9.67E-ll NO DATA NO DATA NO DATA 6.86E-05 CE 141 7.87E-08 4.80E-08 5.65E-09 NO DATA 1.48E-08 NO DATA 2.48E-05 CE 143 1.48E-08 9.82E-06 1.12E-09 NO DATA 2.86E-09 NO DATA 5.73E-05 CE 144 2.98E-06 1.22E-06 1.67E-07 NO DATA 4.93E-07 NO DATA 1.71E-04 PR 143 8.13E-08 3.04E-08 4.03E-09 NO DATA 1.13E-08 NO DATA 4.29E-05 PR 144 2.74E-10 1.06E-10 1.38E-ll NO DATA 3.84E-ll NO DATA 4.S3E-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 NP 239 1.llE-08 9.93E-10 5.61E-10 NO DATA 1.98E-09 NO DATA 2.87E-05
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I TABLE A.3-5*
STABLE ELEMENT TRANSFER DATA B
F, (Cow)
F gy g
Element Veg/ Soil Milk (d/1)
Meat (d/kg)
H 4.8E 00 1.0E-02 1.2E-02 C.
5.5E 00 1.2E-02 3.lE-02 i
Na 5.2E-02 4.0E-02 3.0E-02
-P-1.lE.00 2.5E-02 4.6E-02
.Cr 2.5E-04 2.2E-03 2.4E-03 l
Mn.
2.9E-02 2.5E-04 8.0E-04 Fe 6.6E-04 1.2E-03 4.0E-02 Co 9.4E-03 1.0E-03 1.3E-02 Ni 1.9E-02 6.7E-03 5.3E-02 Cu 1.2E-01 1.4E-02 8.0E-03 i
Zn 4.0E-01 3.9E-02 3.0E-02 Rb 1.3E-01 3.0E-02 3.lE-02 Sr 1.7E-02 8.0E-04 6.0E-04 Y
2.6E-03 1.0E-05 4.6E-03 Zr.
1.7E-04 5.0E-06 3.4E-02 Nb 9.4E-03 2.5E-03 2.8E-01 Mo-1.2E-01 7.5E-03 8.0E-03 Tc 2.5E-01 2.5E-02 4.0E-01 i
Ru
.5.0E-02 1.0E-06 4.0E-01
.Rh 1.3E 01 1.0E-02 1.5E-03 Ag 1.5E-01 5.0E-02 1.7E-02
- Te -
1.3E 00 1.0E-03 7.7E-02 I..
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-02 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
.?4) 2.5E-03 5.0E-06.
2.0E-04
- Taken'from Regulatory Guide 1.109 (Rev. 1) l
+Fm'for goat'is 6.0E-2.
l A-30
TABLE A.4-1 SITE RELATED DOSE COMMITMENT FACIOR AIT MREM /HR PER UCI/ML ADULT NUCLIDE BONE LIVER T Il01 THYROID KIIEEY 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 6.30E 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 P-32 4.62E 07 2.87E 06 1.79E 06 0.00E-01 0.00E-01 0.00E-01 5.20E 06 CR-51 0.00E-01 0.00E-01 1.49E 00 B.94E-01 3.29E-01 1.98E 00 3.76E 02 MN-54 0.00E-01 4.76E 03 9.08E 02 0.00E-01 1.42E 03 0.00E-01 1.46E 04 MN-56 0.00E-01 1.20E 02 2.12E 01 0.00E-01 1.52E 02 0.00E-01 3.B'E 03 FE-55 8.87E 02 6.13E 02 1.43E 02 0.00E-01 0.00E-01 3.42E 02 3.52E 02 FE-59 1.40E 03 3.29E 03 1.26E 03 0.00E-01 0.00E-01 9.19E 02 1.10E 04 CO-58 0.00E-01 1.51E 02 3.39E 02 0.00E-01 0.00E-01 0.00E N.
3.06E 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 4.19E 04 2.94E 03 1.41E 03 0.00E-01 0.00E-01 0.00E-01 6.07E 02 NI-65 1.70E 02 2.21E 01
- 1. ole 01 0.00E-01 0.00E-01 0.00E-01 5.61E 02 CU-64 0.00 E-01 1.69E 01 7.93E 00 0.00E-01 4.26E-01 0.00E-01 1.44E 03 ZN-65 2.36E 04 7.50E 04 3.39E 04 0.00E-01 5.02E 04 0.00E-01 4.73E 04 ZN-69 5.02E 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 BR-85 0.00E-01 0.00E-01 2.33E 00 0.00E-01 0.00E-01 0.00E-01 1.09E-19 l
RB-86 0.00E-01 1.03E 05 4.79E 04 0.00E-01 0.00E-01 0.00E-01 2.03E 04 RB-88 0.00E-01 2.95E 02 1.56E 02 0.00E-01 0.00E-01 0.00E-01 4.07E-09 l
RB-89 0.00E-01 1.95E 02 1.37E 02 0.00E-01 0.00E-01 0.005-01 1.13E-ll 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 l
SR-91 8.79E 02 0.00E-01 3.55E 01 0.00E-01 0.00E-01 0.00E-01 4.19E 03 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-01 0.00E-01 0.00E-01 0.00E-01 1.llE 04
.Y-92 1.21E-01 0.00E-01 3.53E-03 0.00E-01 0.00E-01 0.00E-01 2.12E 03 l
A-31
TABLE A.4-1 (cont'd)
SITE REIATED DOSE COMMITMENT FACTOR AIT MREM /HR PER UCI/ML ADULT NUCLIDE BONE LIVER T BODY THYROID KIDNEY IDMs GI-LLI Y-93 3.83E-01 0.00E-01 1.06E-02 0.00E-01 0.00E-01 0.00E-01 1.22E 04 ZR-95 2.77E 00 8.88E-01 6.01E-01 0.00E-01 1.39E 00 0.00 E-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 NB-95 4.47E 02 2.49E 02 1.34E 02 0.00E-01 2.46E 02 0.00E-01 1.51E 06 2'-99 0.00E-01 4.62E 02 8.79E 01 0.00E-01 1.05E 03 0.00E-01 1.07E 03 P.99M 2.94E-02 8.32E-02 1.06E 00 0.00E-01 1.26E 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 RU-103 1.98E 01 0.00E-01 8.54E 00 0.00E-01 7.57E 01 0.00E-01 2.31E 03 RU-105 1.65E 00 0.00E-01 6.52E-01 0.00E-01 2.13E 01 0.00E-01 1.01E 03 RU-106 2.95E 02 0.00E-01 3.73E 01 0.00E-01 5.69E 02 0.00E-01 1.91E 04
$r AG-110M 1.33E 01 1.23E 01 7.32E 00 0.00 E-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 TE-127M 7.05E 03 2.52E 03 8.59E 02 1.80E 03 2.86E 04 0.00E-01 2.36E 04 TE-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 TE-129 3.27E 01 1.23E 01 7.96E 00 2.51E 01 1.37E 02 0.00E-01 2.47E 01 TE-131M 1.80E 03 8.81E 02 7.34E 02 1.39E 03 8.92E 03 0.00E-01 8.74E 04 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 l
I-130
- 9. ole 01 2.66E 02 1.05E 02 2.25E 04 4.15E 02 0.00E-01 2.29E 02 l
I-131 4.96E 02 7.09E 02 4.06E 02 2.32E 05 1.22E 03 0.00E-01 1.87E 02 l
l 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 2.94E 02 8.97E 01 4.32E 04 5.13E 02 0.00E-01 2.64E 02 I-134 1.26E 01 3.43E 01 1.23E 01 5.94E 02 5.46E 01 0.00E-01 2.99E-02 I-135 5.28E 01 1.38E 02 5.10E 01 9.11E 03 2.22E 02 0.00E-01 1.56E 02 CS-134 3.03E 05 7.21E 05 5.89E 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 CS-137 3.88E 05 5.31E 05 3.48E 05 0.00E-01 1.80E 05 5.99E 04 1.03E 04 CS-138 2.69E 02 5.31E 02 2.63E 02 0.00E-01 3.90E 02 3.85E 01 2.27E-03 BA-139 9.00E 00 6.41E-03 2.64E-01 0.00E-01 5.99E-03 3.64E-03 1.60E 01
- Bioaccmulation factor assmed to be zero since no data was available.
l A-32 I
TABLE A.4-1 (cont'd)
SITE RELATED DOSE CCMMI'INENT FAC'IOR AIT MREM /HR PER UCI/ML ADULT NUCLIDE BONE LIVER T BODY
'IWYROID KIDNEY WNG GI-LLI BA-140 1.88E 03 2.37E 00 1.23E 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 LA-140 3.58E-01 1.80E-01 4.76E-02 0.00E-01 0.00E-01 0.00E-01 1.32E 04 LA-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-233 1.28E-01 1.25E-02 6.91E-03 0.00E-01 3.91E-02 0.00E-01 2.57E 03 A-33
TABLE A.4-2 SITE RELATED DOSE COMMI'INENT FAC'IOR AIT MREM /HR PER UCI/ML TEEN NUCLIDE B(NE LIVER T BODY THYROID KIDNEY WNG GI-LLI H-3 0.00D-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 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 0.00E-01 1.52E 00 8.46E-01 3.34E-01 2.17E 00 2.56E 02 MN-54 0.00E-01 4.65E 03 9.22E 02 0.00E-01 1.39E 03 0.00E-01 9.53E 03 MN-56 0.00E-01 1.24E 02 2.21E 01 0.00E-01 1.58E 02 0.00E-01 8.19E 03 FE-55 9.09E 02 6.45E 02 1.50E 02 0.00E-01 0.00E-01 4.09E 02 2.79E 02 FJ-59 1.41E 03 3.30E 03 1.27E 03 0.00E-01 0.00E-01 1.04E 03 7.79E 03 00-58 0.00E-01 1.45E 02 3.35E 02 0.00E-01 0.00E-01 0.00E-01 2.00E 03 CO-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 1.25E 03 CU-64 0.00E-01 1.72E 01 8.08E 00 0.00E-01 4.35E 01 0.00E-01 1.33d 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-83 0.00E-01 0.00E-01 4.73E 01 0.00E-01 0.00E-01 0.00E-01 8.24E-16 BR-84 0.00E-01 0.00E-01 5.95E 01 0.00E-01 0.00E-01 0.00E-01 8.24E-16 BR-85 0.00E-01 0.00E-01 2.51E 00 0.00E-01 0.00E-01 0.00E-01 8.24E-16 l
RB 0.00E-01 1.10E 05 5.19E 04 0.00E-01 0.00E-01 0.00E-01 1.63E 04 l
RB-88 0.00E-01 3.16E 02 1.68E 02 0.00E-01 0.00E-01 0.00E-01 2.71E-05 RB-89 0.00E-01 2.04E 02 1.44E 02 0.00E-01 0.00E-01 0.00E-01 3.12E-07 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-01 0.00E-01 2.63E 04 SR-91 9.llE 02 0.00E-01 3.62E 01 0.00E-01 0.00E-01 0.00E-01 4.13E 03 SR-92 3.44E 02 0.00E-01 1.47E 01 0.00E-01 0.00E-01 0.00E-01 8.77E 01 Y-90 1.42E 00 0.00E-01 3.83E-02 0.00E-01 0.00E-01 0.00E-01 1.17E 04 Y-91M 1.34E-02 0.00E-01 5.llE-04 0.00E-01 0.30E-01 0.00E-01 6.32E-01 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-01 0.00E-01 3.63E-03 0.00E-01 0.00E-01 0.00E-01 3.44E 03 i
A-34 i
~
=
TABLE A.4-2 (cont'd)
SITE REIATED DOSE (DMMITMDTP FAC'IOR AIT MREM /HR PER UCI/ML i
MJCLIDE BONE LIVER T BODY
'IHYROID KIONEY 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 ZR-95 2.64E _00 8.34E-01 5.74E-01 0.00E-01 1.23E 00 0.00E-01 1.92E 03 ZR-97 1.52E-01 3.01E-02 1.39E-02 0.00E-01 4.56E-02 0.00E-01 8.15E 03
'~
NB-95 4.50E 02 2.50E 02 1.37E 02 0.00E-01 2.42E 02 0.00E-01 1.07E 06
.MO-99 0.00E-01 4.61E 02 8.78E 01 0.00E-01 1.05E 03 0.00E-01 8.25E 02 E-99M 2.84E-02 7.92E-02 1.03E 00 0.00E-01 1.18E 00 4.39E-02 5.20E 01 K-101 3.08E-02 4.38E-02 4.30E-01 0.00E-01 7.92E-01 2.67E-02 7.48E-09 RU-103 1.95E 01 0.00E-01 8.33E 00 0.00E-01 6.87E 01 0.00E-01 1.63E 03 RU-105 1.67E 00 0.00E-01 6.46E-01 0.00E-01 2.10E 01 0.00E-01 1.34E 03 J
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 TE-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 TE-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 TE-129 3.53E 01 1.32E 01 8.59E 00 2.52E 01 1.48E 02 0.00E-01 1.93E 02 TE-131M 1.92E 03 9.22E 02 7.69E 02 1.39E 03 9.61E 03 0.00E-01 7.40E 04 TE-131 2.20E 01 9.06E 00 6.87E 00 1.69E 01 9.61E 01 0.00E-01 1.80E 00 TE-132 2.75E 03 1.74E 03 1.64E 03 1.84E 03 1.67E 04 0.00E-01 5.51E 04 I-130 8.31E 01 2.55E 02 1.02E 02 2.08E 04 3.92E 02 0.00E-01 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 I-132 2.39E 01 6.24E 01 2.24E 01 2.10E 03 9.83E 01 0.00E-01 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 1.25E 01 3.31E 01 1.19E 01 5.51E 02 5.22E 01 0.00E-01 4.36E-01 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 CS-136 3.18E 04 1.25E 05 8.41E 04 0.00E-01 6.82E 04 1.07E 04 1.01E 04 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 2.51E-01
-BA-139 9.10E 00 6.40E-03 2.65E-01 0.00E-01 6.03E-03 4.41E-03 8.llE 01
'
- Bioaccunulation factor asstned to be zero since no data was available.
A-35 I
e
.l TABLE A.4-2 (cont'd)
SITE RELATED DOSE CDMMI'IMENT FACTOR AIT MREM /HR PER UCI/ML TEEN MJCLIDE BONE LIVER T BODY THYBOID KIDNEY UJNG '
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 6.01E-12 IA-140 3.61E-01 1.77E-01 4.72E-02
-0.00a-01 0.00E-01 0.00E-01 1.02E 04 LA-142 1.86E-02 8.25E-03 2.05E-03 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 1.36E 00 5.43E-01 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
'O.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 t
i l
A-36
.~
_ _ _ _ _ _.. ~. _. -.. _ _ _,. _ _. _.,. _. _
'mBLE A.4-3 SITE REIATED DOSE COMMITMENP FAC'KR AIT MREM /HR PER UCI/ML OIIID NUCLIDE BONE LIVER T BODY THYlOID KIENEY IUNG GI-LLI l
H-3 0.00E-01 1.19E 01 1.19E 01 1.19E 01 1.19E 01 1.19E 01 1.19E 01 C-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 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 21-54 0.00E-01 3.99E 03 1.06E 03- 0.00E-01 1.12E 03 0.00E-01 3.35E 03 Mi-56 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 0.0CE-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 i
CO-58 0.00E-01 1.75E 02 5.37E 02 0.00E-01 0.00E-01 0.00E-01 1.02E 03 CO -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 i
NI-65 3.04E 02 2.06E 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 l
l ZN-69 7.15E 01 1.03E 02 9.54E 00-0.00E-01 6.26E 01 0.00E-01 6.51E 03 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 7.69E 01 0.00E-01 0.00E-01 0.00E-01 3.89E-16 I
-BR-85 0.00E-01 0.00E-Ol' 3.54E 00 - 0.00E-01 0.00E-01 0.00E-01 3.89E-16 RB-86 0.00E-01 1.09E 05 6.72E 04 0.00E-01 0.00E-01 0.00E-01 7.03E 03
~ REF88 0.00E-01 3.10E 02 2.15E 02 0.00E-01 0.00E-01 0.00E-01 1.52E 01 l.
l RB 0.00E-01 1.91E 02 1.70E 02 0.00E-01 0.00E-01 0.00E-01 1.66E 00 SR-89
-1.08E 05 0.00E-01 3.08E 03 0.00E 0.00E-01 0.00E-01 4.18E 03 SR-90 1.39E 06 0.00E-01 3.52E 05 0.00E-01 0.00E-01 0.00E-01 1.87E 04
,~
t b
SR-91.
1.96E 03 0.00E-01 7.41E 01 0.00E-01 0.00E-01 0.00E-01 4.33E 03 SR 7.33E 02 0.00E-01 2.96E 01 0.00E-01 0.00E-01 0.00E-01 1.40E 04 Y-90 3.20E 00 0.00E-01 8.56E-02 0.00E-01 0.00E-01 0.00E-01 9.10E 03
-Y-91M 2.97E-02 0.00E-01 1.08E-03' O.00E-01 0.00E-01 0.00E-01 5.82E 01
,Y-91 4.68E 01 0.00E-01 1.25E-02 0.00E-01 0.00E-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 i
A-37 i-
TABLE A.4-3 (cont'd)
SITE RELATED DOSE COMMITMENT FAC10R AIT MREM /HR PER UCI/ML CHILD NUCLIDE BONE LIVER T BODY THYROID KIDNEY IUNG GI-LLI Y-93 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 ZR-97 4.25E-01 6.13E-02 3.62E-02 0.00E-01 8.81E-02 0.00E-01 9.29E 03 NB-95 5.32E 02 2.07E 02 1.48E 02 0.00E-01 1.95E 02 0.00E-01 3.83E 05 MO-99 0.00E-01 8.78E 02 2.17E 02 0.00E-01 1.87E 03 0.00E-01 7.26E 02 TC-99M 6.46E-02 1.27E-01 2.10E 00 0.00E-01 1.84E 00 6.43E-02 7.20E 01 TC-101 7.48E-02 7.83E-02 9.93E-01 0.00E-01 1.34E 00 4.14E-02 2.49 E-01 RU-103 4.83E 01 0.00E-01 1.85E 01 0.00E-01 1.21E 02 0.00E-01 1.25E 03 RU-105 4.26E 00 0.00E-01 1.54E 00 0.00E-01 3.74E 01 0.00E-01 2.78E 03 RU-106 7.72E 02 0.00E-01 9.64E 01 0.00E-01 1.04E 03 0.00E-01 1.20E 04
- AG-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 TE-127M 1.08E 04 2.90E 03 1.28E 03 2.58E 03 3.07E 04 0.00E-01 8.72E 03 TE-127 1.76E 02 4.73E 01 3.77E 01 1.22E 02 5.00E 02 0.00E-01 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 TE-129 5.00E 01 1.39E 01 1.19E 01 3.56E 01 1.46E 02 0.00E-01 3.llE 03 TE-131M 2.68E 03 9.28E 02 9.88E 02 1.91E 03 8.988 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 TE-132 3.77E 03 1.67E 03 2.01E 03 2.43E 03 1.55E 04 0.00E-01 1.6SE 04 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 5.12E 02 1.94E 02 9.51E 04 8.53E 02 0.00E-01 2.06E 02 I-134 2.93E 01 5.44E 01 2.50E 01 1.25E 03 8.32E 01 0.00E-01 3.61E 01 I-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 8.378 03 3.70E 03 CS-137 5.33E 05 5.llE 05 7.54E 04 0.00E-01 1.66E 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 1.18E-02 7.97E-03 1.47E 03
- Bioacctznulation factor assumed to be zero since no data was available.
A-38
TABLE A.4-3 (cont'd)
SITE PELATED DOSE COMMI'INENT FACIOR AIT MREN/HR PER UCI/ML OIIID NUCLIDE BONE LIVER T BODY
'HIYROID KIDNEY IUNG GI-LLI BA-140 5.09E 03 4.46E 00 2.97E 02 0.00E-01 1.45E 00
~2.66E 00 2.58E 03 BA-141 1.23E 01 6.86E-03 3.99E-01 0.00E-01 5.94E-03 4.03E-02 6.99E 00 BA-142 5.36E 00 3.85E-03 2.99E-01 0.00E-01 3.12E-03 2.27E-03 6.99E-02 LA-140 7.86E-01 2.75E-01 9.26E-02 0.00E-01 0.00E-01 0.00E-01 7.66E 03 LA-142 4.08E-02 1.30E-02 4.07E-03 0.00E-01 0.00E-01 0.00B-01 2.58E 03 CE-141 2.34E 00 1.17E 00 1.73E-01 0.00E-01 5.llE-01 0.00E-01 1.46E 03 CE-143 4.12E-01 2.23E 02 1.24E-02 0.00E-01 9.37E-02 0.00E-01 3.27E 03 CE-144 1.23E 02 3.84E 01 5.54E 00 0.00E-01 2.13E 01 0.00E-01 1.00E 04 PR-143 3.06E 00 9.18E-01 1.52E-01 0.00E-01 4.97E-01 0.00E-01 3.30E 03 PR-144 1.00E-02 3.10E-03 5.05E-04 0.00E-01 1.64E-03 0.00E-01 6.68E 00 ND-147 2.17E 00 1.76E 00 1.36E-01 0.00E-01 9.65E-01 0.00E-01 2.79E 03 W-187 4.30E 02 2.55E 02 1.14E 02 0.005-01 0.00E-01 0.00E-01 3.58E 04 NP-239 3.47E-01 2.49E-02 1.75E-02 0.00E-01 7.19E-02 0.00E-01 1.84E 03 l
l I
[
l l
l A-39
TABLE A.4-4 SITE RELATED DOSE COMMI'IMENT FACIOR AIT MREN/HR PER UCI/ML INFANT NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI H-3 0.00E-01 1.16E 01 1.16E 01 1.16E 01 1.16E 01 1.16E 01 1.16E 01 C-14 8.92E 02 1.90E 02 1.90E 02 1.90E 02 1.90E 02 1.90E 02 1.90E 02 NA-24 3.80E 02 3.80E 02 3.80E 02 3.80E 02 3.80E 02 3.80E 02 3.80E 02 P-32 6.40E 04 3.76E 03 2.48E 03 0.00E-01 0.00E-01 0.00E-01 8.65E 02 CR-51 0.00E-01 0.00E-01 5.30E-01 3.46E-01 7.56E-02 6.73E-01 1.55E 01 MN-54 0.00E-01 7.49E 02 1.70E 02 0.00E-01 1.66E 02 0.00E-01 2.75E 02 MN-56 0.00E-01 3.08E 01 5.30E 00 0.00E-01 2.64E 01 0.00E-01 2.80E 03 FE-55 5.23E 02 3.38E 02 9.03E 01 0.00E-01 0.00E-01 1.65E 02 4.29E 01 FE-59 1.16E 03 2.02E 03 7.98E 02 0.00E-01 0.00E-01 5.98E 02 9.67E 02 i
CO-58 0.00E-01 1.35E 02 3.38E 02 0.00E-01 0.00E-01 0.00E-01 3.37E 02 CO-60 0.00E-01 4.06E 02 9.59E 02 0.00E-01 0.00 E-01 0.00E-01 9.67E 02 NI-63 2.39E 04 1.47E 03 8.28E 02 0.00E-01 0.00E-01 0.00E-01 7.34E 01 NI-65 1.77E 02 2.00E 01 9.10E 00 0.00E-01 0.00E-01 0.00E-01 1.52E 03 CU-64 0.00E-01 2.29E 01 1.06E 01 0.00E-01 3.87E 01 0.00E-01 4.70E 02 ZN-65 6.92E 02 2.37E 03 1.09E 03 0.00E-01 1.15E 03 0.00E-01 2.01E 03 l
ZN-69 3.51E 00 6.32E 00 4.70E-01 0.00E-01 2.63E 00 0.00E-01 5.15E 02 l
BR-83 0.00E-01 0.00E-01 1.37E 01 0.00E-01 0.00E-01 0.00E-01 3.76E-17 BR-84 0.00E-01 0.00E-01 1.44E 01 0.00E-01 0.00E-01 0.00E-01 3.76E-3 7 BR-85 0.00E-01 0.00E-01 7.30E-01 0.00E-01 0.00E-01 0.00E-01 3.76E-17 RB-86 0.00E-01 6.40E 03 3.16E 03 0.00E-01 0.00E-01 0.00E-01 1.64E 02
~
RB-88 0.00E-01 1.87E 01 1.03E 01 0.00E-01 0.00E-01 0.00E-01 1.82E 01 RB-89 0.00E-01 1.08E 01 7.41E 00 0.00E-01 0.00E-01 0.00E-01 3.66E 00 SR-89 9.44E 04 0.00E-01 2.71E 03 0.00E-01 0.00E-01 0.00E-01 1.94E 03 SR-90 6.96E 05 0.00E-01 1.77E 05 0.00E-01 0.00E-01 0.00E-01 8.69E 03 SR-91 1.88E 03 0.00E-01 6.81E 00 0.00E-01 0.00E-01 0.00E-01 2.23E 03 SR-92 7.22E 02 0.00E-01 2.68E 01 0.00E-01 0.00E-01 0.00E-01 7.79E 03 Y-90 3.27E 00 0.00E-01 8.77E-02 0.00E-01 0.00E-01 0.00E-01 4.51E 03 Y-91M 3.05E-02 0.00E-01 1.04E-03 0.00E-01 0.00E-01 0.00E-01 1.02E 02 Y-91 4.25E 01 0.00E-01 1.13E 00 0.00E-01 0.00E-01 0.00E-01 3.05E 03 l
Y-92 2.88E-01 0.00E-01 8.09E-03 0.00E-01 0.00E-01 0.00E-01 5.49E 03 l
A-40 i
i
TABLE A.4-4 (cont'd)
SITE RELATED DOSE COMMITNENP FACTOR AIT MREM /HR PER UCI/ML INFANT NUCLIDE BONE LIVER T BODY TEYROID KIDNEY WNG GI-LLI Y-93 9.14E-01 0.00E-01 2.49E-02 0.00E-0]
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 ZR-97 5.57E-01 -9.56E-02 4.36E-02 0.00E-01 9.63E-02 0.00E-01 6.09E 03 NB-95 1.58E 00 6.51E-01 3.76E-01 0.00E-01 4.66E-01 0.00E-01 5.49E 02 MO-99 0.00E-01 1.28E 03 2.49E 02 0.00E-01 1.91E 03 0.00E-01 4.21E 02 TC-99M 7.22E-02 1.49E-01 1.92E 00 0.00E-01 1.60E 00 7.79E-02 4.33E 01 TC-101 6.54 E-02 1.08E-01 1.06E 00 0.00E-01 1.28E 00 5.87E-02 1.83E 01 RU-103 5.57E 01 0.00E-01 1.86E 01 0.00E-01 1.16E 02 0.00E-01 6.77E 02 RU-105 5.12E 00 0.00E-01 1.72E 00 0.00E-01 3.76E 01 0.00E-01 2.04E 03 RU-106 9.07E 02 0.00D-01 1.13E 02 0.00E-01 1.07E 03 0.00E-01 6.88E 03
- AG-110M 3.75E 01 2.72B 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 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 0.00E-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 l
I-134 3.27E 01 6.70E 01 2.38E 01 1.56E 03 7.49E 01 0.00E-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 2.67E 03 0.00E-01 6.81E 03 2.42E 03 7.19E 01 CS-136 1.73E 03 5.08E 03 1.90E 03 0.00 E-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 7.19E 01 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
- Bioaccmulation factor asstrned to be zero since no data was available.
A-41 l
i
'DSLE A.4-4 (cont'd) i SITE RELATED DOSE CmMI'IMINP FACTOR AIT MREM /HR PER UCI/ML INFANP PUCLICE BONE LIVER T BODY
'INYBOID KIONEY Il]NG GI-LLI BA-140 6.43E 03 6.43E 00 3.31E 02 0.00E-01 1.53E 00 3.95E 00 1.58E 03 BA-141' l.60E 01 1.09E-02 5.04E-01 0.00E-01 6.58E-03 6.66E-03 1.95E 02 BA-142 6.92E 00 5.76E-03 3.41E-01 0.00E-01 3.31E-03 3.48E-03 2.86E 01
.IA-140
.7.94E-01 3.13E-01 8.05E-02 0.00E-01 0.00E-01 0.00E-01 3.68E 03 LA-142 4.14E-02 1.52E-02 '3.64E-03 0.00E-01 0.00E-01 0.00E-01 2.58E 03 CE-141 2.96E 00 1.81E 00 2.13E 0.00E-01 5.57E-01 0.00E-01 9.33E 02
^
CE-143 5.57E-01 3.69E 02 4.21E-02 0.00E-01 1.08E-01 0.00E-01 2.16E 03
-CE-144 1.12E 02 4.59E 01 6.28E 00 0.00E-01 1.85E 01-0.00E-01 6.43E 03 i
PR-143
-3.06E 00 1.14E 00 1.52E-01 0.00E-01 4.25E-01 0.00E-01 1.61E 03 PR-144 1.03E-02 3.99E-03 5.19E '4 0.00E-01 1.44E-03 0.00E-01 1.85E 02-ND-147 2.08E 00 2.14E 00 1.31E 0.00E-01 8.24E-01 0.00E-01 1.35E 03 W-187 3.40E 01 2.36E 01 8.16E 00 0.00E-01 0.00E-01 0.00E-01 1.39E 03 NP-239
'4.18E-01 3.74E-02 2.llE-02 0.00E-01 7.45E-02 0.00E-01 1.08E 03 e
I l
j A-42 l
TABT.E A.5-1 INHALATION DOSE PARAMIH'ER FOR 'IYlE CHILD, PI MREN/YR PER UCI/M3 H-3 1.12E 03 RU-103 6.62E 05 C-14 3.59E 04 RU-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 TE-125M 4.77E 05 M-54 1.58E 06 TE-127M 1.48E 06 m-56 1.23E 05 TE-127 5.62E 04 FE-55 1.llE 05 TE-129M 1.76E 06 FE-59 1.27E 06 TE-129 2.55E 04 cow-58 1.11E 06 TE-131M 3.08E 05 CD-60 7.07E 06 TE-131 2.05E 03 NI-63 8.21E 05 TE-132 3.77E 05 NI-65 8.40E 04 I-130 1.852 06 CU-64 3.67E 04 I-131 1.62E 07 ZN-65 9.95E 05 I-132 1.94E 05 ZN-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 G-134 1.01E 06 RB-86 1.98E 05 CS-136 1.71E 05 RB-88 5.62E 02 CS-137 9.07E 05 RB-89 3.45E 02 CS-138 8.40E 02 SR-89 2.16E 06 BA-139 5.77E 04 SR-90 1.01E 08 BA-140 1.74E 06 SR-91 1.74E 05 BA-141 2.92E 03 SR-92 2.42E 05 BA-142 1.64E 03 Y-90 2.68E 05 LA-140 2.26E 05 Y-91M 2.81E 03 LA-142 7.59E 04 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 NB-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 6.408 04 TC-101 5.85E 02 l-l A-43 t
TABLE A.5-2 PATIMAY DOSE FACIORS RI ADULT NUCLIDE IM1ALATION GROU!O GRASS GRASS VEGETATION PA11MAY PIANE CON CXW PATEMAY MILK MEAT H-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 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 00-58 9.28E 05
?.79E 08 9.56E 07 3.70E 08 6.23E 08 C0+60 5.97E 06 3.15E 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 NI-65 1.23E 04 3.02E 05 1.53E 00 0.00E-01 2.28E 02 CU-64 4.90E 04 6.07E 05 2.03E 06 2.33E-05 7.85E 05 ZN-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-86 1.35E 05 8.99E 06 2.59E 09 4.87E 08 2.19E 08 RB-88 3.87E 02 3.31E 04 0.00E-01 0.00E-01 3.47E-22 RB-89 2.56E 02 1.21E 05 0.00E-01 0.00E-01 1.41E-26 l
SR-89 1.40E 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 1.54E-08 Y-91 1.70E 06 1.07E 06 4.73E 06 6.23E 08 2.81E 09 Y-92 7.35E 04 1.80E 05 9.79 E-01 0.00E-01 1.60E 04 A-44
TABLE A.5-2 (cont'd)
PA'IHWAY DOSE FACIORS RI ADULT NUCLIDE INHALATICN GROUND JASS GRASS VEGETATION PATHWAY PIANE CON CON PATHWAY MILK MEAT Y-93 4.22E 05 1.85E 05 7.39E 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 MO-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 RU-103 5.05E 05 1.08E 08 1.19E 05 1.23E 10 5.56E 08 RU-105 4.82E 04 6.36E 05 5.25E-01 3.59E-25 3.30E 04 RU-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 TE-125M 3.14E 05 1.55E 06 6.63E 07 1.46E 09 3.93E 08 TE-127M 9.60E 05 9.17E 04 1.86E 08 4.53E 09 1.42E 09 TE-127 5.74E 04 2.98E 03 5.16E 04 1.69E-08 4.47E 05 TE-129M 1.16E 06 1.98E 07 3.032 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-131M 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 l
I-131 1.19E 07 1.72E 07 1.39E 11 5.04E 09 3.79E 10 l
i l
I-132 1.14E 05 1.25E 06 1.54E 01 0.00E-01 5.40E 03 I
I-133 2.15E 06 2.45E 06 9.90E 08 9.37E 01 5.33E 08 l
I-134 2.98E 04 4.47E 05 9.57E-ll 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.llE 10 CS-136 1.46E 05 1.49E 08 1.03E 09 4.66E 07 1.66E 08 CS-137 6.21E 05 1.03E 10 1.01E 10 1.19E 09 8.70E 09 CS-138 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 A-45
TABLE A.5-2 (cont'd)
PATHWAY DOSE FACIORS RI ADULT NUCLIDE IM1AIATIN GROUND GRASS GRASS VEGE7fATION PA'IHWAY PIANE COW-CW PNm WAY MILK MEAT BA-140' l.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 LA-140 4.58E 05 1.92E 07 1.67E 05 1.39E 03 7.33E 07 LA-142 6.33E 03 7.37E 05 3.12E-08 0.00E-01 4.70E-01 CE-141 3.62E 05 1.37E 07 1.25E 07 3.63E 07 5.10E 08 e
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 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 NP-239 1.19E 05 1.71E 06 7.41E 04 5.22E 03 2.88E 07 1
r A-46
~..
TABLE A.5-3 PATIMAY DOSE FACIORS RI TEEN NUCLIDE IMIAIATION GROUND GRASS GRASS VEGETATION PA'I1MAY PLANE CON CON PATIMAY MILK MEAT H-3 1.27E 03 0.00E-01 9.94E 02 1.94E 02 2.59E 03 0-14 2.60E 04 0.00E-01 4.86E 08 2.04E 08 3.69E 08 NA-24 1.38E 04 1.19E 07 4.26E 06 1.09E-03 2.39E 05 P-32 1.89E 06 0.00E-01 3.15E 10 3.93E 09 1.dlE 09 CR-51 2.10E 04 4.66E 06 8.39E 06 9.47E 05 1.04E 07 MN-54 1.98E 06 1.39E 09 2.87E 07 1.44E 07 9.32E 08 MN-56 5.74E 04 9.03E 05 4.85E-01 0.00E-01 9.45E 02 FE-55 1.24E 05 0.00E-01 4.45E 07 2.38E 08 3.25E 08 FE-59 1.53E 06 2.73E 08 2.86E 08 1.17E 09 9.90E 08 00-58 1.34E 06 3.79E 08 1.09E 08 1.94E 08 6.01E 08 CO-60 8.72E 06 2.15E 10 3.62E 08 7.60E 08 3.24E 09 NI-63 5.80E 05 0.00E-01 1.18E 10 1.52E 10 1.61E 10 NI-65 3.67E 04 3.02E 05 5.88E 00 0.00E-01 4.47E 02 CD-64 6.14E 04 6.07E 05 3.30E 06 1.73E-05 6.47E 05 ZN-65 1.24E 06 7.46E 08 7.31E 09 8.69E 08 1.47E 09 l
ZN-69 1.58E 03 0.00E-01 3.38E-ll 0.00E-01 2.889-05 BR-83 3.44E 02 4.87E 02 0.00E-01 0.00E-01 2.92E 00 1
BR-84 4.33E 02 2.03E 05 0.00E-01 0.00E-01 2.27E-ll l
BR-85 1.83E 01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 RB-86 1.90E 05 8.99E 06 4.73E 09 4.07E 08 2.74E 08 l
R3-88 5.46E 02 3.31E 04 0.00E-01 0.00E-01 3.21E-22 I
/
RB-89 3.52E 02 1.21E 05 0.00E-01 0.00E-01 1.26E-26 SR-89 2.42E 06 2.16E 04 2.67E 09 2.55E 08 1.51E 10 SR-90 1.08E 08 0.00E-01 6.61E 10 8.05E 09 7.51E 11 SR-91 2.59E 05 2.14E 06 2.39E 05 5.41E-10 1.28E 06 SR-92 1.19E 05 7.77E 05 2.28E 01 0.00E-01 1.01E 04 Y-90 5.59E 05 4.49E 03 1.07E 06 7.41E 05 1.02E 08 Y-91M 3.20E 03 1.00E 05 5.22E-18 0.00E-01 2.30E-07 Y-91 2.94E 06 1.07E 06 6.48E 06 3.91E 08 3.21E 09 Y-92 1.65E 05 1.80E 05 2.83E 00 0.00E-01 2.36E 04 A-47 L
TABLE A.5-3 (cont 9d)
PNIfMAY DOSE FAC'IORS RI TEFN NUCLIDE IMIALATICN GROUND GRASS GPASS VEGETATION PATHWAY PIR,'E CON CON PATIMAY 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 6.00E 05 2.96E 06 4.23E 04 9.27E-01 1.67E 07 NB-95 7.5]E 05 1.37E 08 3.34E 08 4.26E 09 4.57E 08 MO-99 2.69E 05 3.998 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 TC-101 6.67E 02 2.04E 04 0.00E-01 0.00E-01 2.00E-29 RU-103 7.83E 05 1.08E 08 1.51E 05 7.15E 09 5.69E 08 RU-105 9.04E 04 6.36E 05 1.27E 00 3.96E-25 4.04E 04 RU-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 4.3BE 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-131M 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 6.15E-15 TE-132 4.638 05 4.23E 06 8.61E 07 2.33E 07 7.84E 07 I-130 1.49E 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 l
l 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 08 CS-137 8.48E 05 1.03E 10 1.78E 10 9.63E 08 1.35E 10 CS-138 8.56E 02 3.59E 05 3.19E-23 0.00E-01 6.98E-ll BA-139 6.46E 03 1.06E 05 7.53E-07 0.00E-01 2.44E-01 A-48
TABLE A.5-3 (cont'd)
PA'IffHAY DOSE FACIORS RI TEEN NUCLIDE IMIAIATICN GROUND GRASS GRASS VEGETATION PA'IffWAY PLANE CON CCM PATEMAY MILK MEAT BA-140 2.03E 06 2.05E 07 7.48E 07 3.67E 07 2.13E 08 BA-141 3.29E 03 4.18E 04 0.00E-01 0.00E-01 1.19E-21 BA-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 LA-142 1.20E 04 7.37E 05 2.29E-07 0.00E-01 1.76E 00 CE-141 6.14E 05 1.37E 07 1.70E 07 2.25E 07 5.41E 08 CE-143 2.55E 05 2.31E 06 1.67E 06 3.70E 02 2.04E 07 CE-144 1.34E 07 6.96E 07 1.66E 08 3.090 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 0.00E-01 0.00E-01 2.93E-26 ND-147 3.72E 05 8.46E 06 7.15E 05 2.48E 07 1.44E 08 W-187 1.77E 05 2.36E 06 2.65E 06 4.00E 00 7.84E 06 NP-239 1.32E 05 1.71E 06 1.06E 05 3.433 03 2.10E 07 A-49
TABLE A.5-4 PADMAY DOSE FACIORS RI CHILD NUCLIDE INHAIATICN GROUND GRASS GRASS VEGETATION PAUMAY PIANE CON CCW PATIMAY MILK 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 MN-54 1.58E 06 1.39E 09 2.10E 07 8.01E 06 6.65E 08 MN-56 1.23E 05 9.03E 05 1.06E 00 0.00E-01 2.72E 03 FE-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 1.11E 06 3.79E 08 7.07E 07 9.58E 07 3.76E 08 CO-60 7.07S 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 ZN-69 1.02E 04 0.00E-01 2.15E-09 0.00E-01 1.38E-03 BR-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
(
BR-85 2.53E 01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 RB-86 1.98E 05 8.99E 06 8.77E 09 5.77E 08 4.52E 08 RB-88 5.62E 02 3.31E 04 0.00E-01 0.00E-01 4.43E-22
[
RB-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 SBF90 1.01E 08 0.00E-01 1.12E 11 1.04E 10 1.24E 12 SR-91 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 0.00E-01 1.38E 04 Y-90 2.68E 05 4.49E 03 9.15E 05 4.84E 05 6.56E 07 Y-91M 2.81E 03 1.00E 05 5.29 E-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)
PAMAY DOSE FAC'IORS RI CHILD NUCLIDE INiAIATION GROUND GRASS GRASS VEGETATION PA N AY PIANE CON CXM PATHWAY MILK MEAT Y-93 3.89E 05 1.85E 05 1.57E 04 1.56E-07 4.48E 06 ZR-95 2.23E 06 2.45E 08 8.79E 05 6.llE 08 8.85E 08 ZR-97 3.51E 05 2.56E 06 4.20E 04 7.05E-01 1.25E 07 NB-95 6.14E 05 1.37" 08 2.29E 08 2.23E 09 2.96E 08 MO-99 1.35E 05 3.99E 06 1.74E 08 2.45E 05 1.65E 07 TC-99M 4.81E 03 1.84E 05 3.48E 04 7.00E-18 5.26E 03 TC-101 5.85E 02 2.04E 04 0.00E-01 0.00E-01 2.55E-29 RU-103 6.62E 05 1.08E 08 1.llE 05 4.00E 09 3.96E 08 RU-105 9.95E 04 6.36E 05 2.50E 00 5.98E-25 5.99E 04 B0-106 1.43E 07 4.21E 08 1.44E 06 6.90E 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 5.69E 08 3.51E 08 TE-127M 1.48E 06 9.17E 04 5.93E 08 5.06E 09 3.77E 09 TE-127 5.62E 04 2.98E 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 TE-131M 3.08E 05 8.03E 06 2.24E 07 9.84E 03 2.16E 07 TE-131 2.05E 03 2.92E 04 8.64E-32 0.00E-01 1.36E-14 TE-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 6.80E-04 1.37E 08 I-131 1.62E 07 1.72E 07 4.33B ll 5.51E 09 4.76E 10 I-132 1.94E 05 1.25E 06 5.89E 01 0.00E-01 7.87E 03 t
l I-133 3.85E 06 2.45E 06 3.95E 09 1.31E 02 8.12E 08 i
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 1.05E-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 2.39E 10 CS-138 8.40E 02 3.59E 05 5.60E-2' O.00E-01 9.20E-11 BA-139 5.77E 04 1.06E 05 1.20E-05 0.00E-01 2.91E 00 A-51
TABLE A.5-4 (cont'd)
PA'IEWAY DOSE FACIORS RI CHILD NUCLIDE IMIAIATION GROUND GRASS GRASS VEGETATION PA'IHWAY PIANE CON 00W PATHWAY MIIK MEAT BA-140 1.74E 06 2.05E 07 1.17E 08 4.39E 07 2.77E 08 BA-141 2.92E 03 4.18E 04 0.00E-01 0.00E-01 2.20E-21 BA-142 1.64E 03 4.49E 04 0.00E-01 0.00E-01 0.00E-01 LA-140 2.26E 05 1.92E 07 1.89E 05 5.51E 02 3.17E 07 IA-142 7.59E 04 7.37E 05 2.58E-06 0.00E-01 1.49E 01 CE-141 5.44E 05 1.37E 07 1.36E 07 1.38E 07 4.08E 08 CE-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 0.00E 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 W-187 9.10E 04 2.36E 06 2.42E 06 2.80E 00 5.38E 06 NF239 6.40E 04 1.71E 06 9.16E 04 2.26E 03 1.36E 07 i
l I
l l
A-52
TABLE A.5-5 PAnlWAY DOSE FACIORS RI INFANT NUCLIDE INHALATION GROUND GRASS GRASS VEGETATION PATHWAY PIANE 00R CCW PATHWAY MILK MEAT H-3 6.47E 02 0.00E-01 2.38E 03 0.00E-01 0.00E-01 0-14 2.65E 04 0.00E-01 2.34E 09 0.00E-01 0.00E-01 NA-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 0.00E-01 CR-51 1.28E 04 4.66E 06 4.70E 06 0.00E-01 0.00E-01 MN-54 1.00E 06 1.39E 09 3.90E 07 0.00E-01 0.00E-01 MN-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 Co-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 6.07E 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-01 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 BR-84 4.00E 02 2.03E 05 0.00E-01 0.00E-01 0.00E-01 f
BR-85 2.04E 01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 l
RB-86 1.90E 05 8.99E 06 2.23E 10 0.00E-01 0.00E-01 RB-88 5.57E 02 3.31E 04 0.00E-01 0.00E-01 0.00E-01 l
l RB-89 3.21E 02 1.21E 05 0.00E-01 0.00E-01 0.00E-01 1
SR-89 2.03E 06 2.16E 04 1.26E 10 0.00E-01 0.00E-01 SR-90 4.09E 07 0.00E-01 1.22E 11 0.00E-01 0.00 E-01 l
l SR-91 7.34E 04 2.14E 06 3.19E 05 0.00E-01 0.00E-01 i
SR-92 1.40E 05 7.77E 05 5.02E 01 0.00E-01 0.00E-01 l
Y-90 2.69E 05 4.49E 03 9.39E 05 0.00E-01 0.00E-01 i
Y-91M 2.79E 03 1.00E 05 1.91E-15 0.00E-01 0.00E-01 Y-91 2.45E 06 1.07E 06 5.25E 06 0.00E-01 0.00E-01 l
Y-92 1.27E 05 1.80E 05 1.03E 01 0.00E-01 0.00E-01 A-53 l-i,
' TABLE A.5-5 (cont'd)
PATfMAY DOSE FACTORS RI INFANT ECLIDE IE ALATIN GICUND GRASS GRASS VEGETATICN PATtMAY PIANE CN CN PATIMAY MIIK MERP Y-93 1.67E 05 1.85E 05 1.78E 04 0.00E-01 0.00E-01 ZR-95
.1.75E 06 2.45E 08 8.26E 05 0.00E-01 0.00E-01
~ZR-97 1.40E 05 2.96E 06 4.45E 04 0.00E 0.00E-01 3
'NB-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.llE 08 0.00E-01 0.00E-01 T-99M.
2.03E 03 1.84E 05 1.65E 04 0.00E-01 0.00E-01 K-101 8.44E 02 2.04E 04 0.00E-01 0.00E-01 0.00E-01 E-103 5.52E 05 1.08E 08 1.05E 05 0.00E-01 0.00E-01 E-105 4.84E 04 6.36E 05 3.21E 00 0.00E-01 0.00E-01 J
E-106 1.16E 07 4.21E 08 1.44E 06 0.00E-01 0.00E-01 M-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 i
TE-127M 1.31E 06 9.17E-04 1.04E 09 0.00E-01 0.00E-01 L
TE-127 2.44E 04 2.98E 03 1.33E 05 0.00E-01 0.00E-01
~ TE-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 TE-132 3.40E 05 4.23E 06-6.53E 07 0.00E-01 0.00E-01
'I-130
-1.60E 06 5.51E 06 8.76E 08 0.00E-01 0.00E-01 I-131 1.48E 07 1.72E 07-
' l.05E 12 0.00E-01 0.00E-01 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 l
I-134 4.45E 04-4.47E 05 8.47E-10 0.00E-01 0.00E-01
~
l I-135' 6.96E 05 2.53E 06
'2.00E 07 0.00E-01 0.00E-01 L
G-134 7.03E 05 6.86E 09 6.80E40 0.00E-01" 0.00E-01 1
CS-136
,1.35E 05 1.49E 08 5.76E' 09 0.00E-01 0.00E-01 CS-17 6.12E 05 1.03E 10 -
6.028 10 0.00E-01 0.00E-01 1
.e 0.00E-01 G-138 '
8.76E 02 3.59E 05 2.21E 22 0.00E-01 '
D.00E-01 BA-139.
5.10E 04
- 1.06E 05
- 2.80E-05 0.00E-01 l
A 4
A-54 c.
s.
e mee v.
TABLE A.5-5 (cont'd)
PNIIMAY DOSE FACIORS RI INFANT NUCLIDE INHALATION GROUND GRASS GRASS VEGETATICN PA'IHWAY PLANE (XM CCW PATIMAY MILK 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 0.00E-01 0.00E-01 0.00E-01 BA-142 1.55E 03 4.49E 04 0.00E-01 0.00E-01 0.00E-01 IA-140-1.68E 05 1.92E 07 1.88E 05 0.00E-01 0.00E-01 TA-142 5.95E 04 7.37E 05 5.36E-06 0.00E-01 0.00E-01 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 0.00E-01 0.00E-01 PR-143 4.33E 05 0.00E-01 7.84E 05 0.00E-01 0.00E-01 PR-144 4.28E 03 1.83E 03 0.00E-01 0.00E-01 0.00E-01 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 NP-239 5.95E 04 1.71E 06 9.43E 04 0.00E-01 0.00E-01 i
l A-55
Appendix B Accident Doses
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N #fAPPENDIX B t
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B. 4. ACCIDENTAL' RELEASES.
?
~
w m *< A u,Qthe eventsof an: accidental ^, release of radios.ctive
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s
- I
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Tiquids or gases from the plant,dhe nornfal effluent b-4 fristfictione set 4tm -in -10CFR P, arts 20 cand 50 may ;or
.R,
l9 mhy':not'be liol'ated." Proper emerge $dy response plan-9 j, ' '.lninb(as, described _in NOREG-0654), requires rapid; esti-
~
..a fmates'o euncontrolled releases.'1Radi.ological Emergency
-Z 7 Plan Imp 1hm'enting Proc _edureg(EPIP) ADM 12-11.0, " Dose 4
-i Projections,".will'bevthe-guiding'procedurb in the event
' of an-'accidentai'rolease.
x g
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+
3D.1 VACCIDEN? DOSES u LIQUID RET, EASES. -
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~;
y
..s'In'the e vent o'f'an acdidentarllicuid selease, the re-J l
-1.
', _y[# operationar recordsleased,ghaneity cf' activity Will'be estimated based upon i
. Jhe:prdjected accident dose will
-l s
'then be calculatsd'in;tlid;stme manner as normal effluent 3
,dosasf(Sectionjf.3). jM;
~ %,
i
, m.
1
+
y g
F If the calculated release-concentrations,at the'circulat-vy ing' water;dischargotare above Part 50 and Part 20_ limits, a cample will bF taken from the lake once every.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> i.
c
- \\.
^
and an ~isotop,ic analysis performed Lonce ;every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 3 "until lake concentrations are below Part'50 and Part 20
- \\'
l-imits.
~
T g,
'If activity measured in the lake is' above' Part 50 and Part 20 limits tl2e~n the Radiological Embrgency Plan 3
. Implementingo: Procedure TCPIP) AD:4 12-11.3 " Dose Projections"lwill~be used to control. emergency
^
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ACCIDENT' DOSES - MASEOUS' RELEASES---
a i-N l
- The4Rddioactive Releade Information Syste'm ' (RRIS) is specifichlly. designed to provide this information.
The
'mW system'makes use of on-line effluedt nonitors and meteor-y,,o16 'ical' do' nit; ors,,, as well as: s~amplingiand computer 9
-modelling? o estimate.and predict doses to the surround-t
,;ing 'popul'atlon It the RRIS is unavailable at the time of l
1 d..,,.,an,accidsnh,^ Emergency Plan Implementing Procedure ADM I:
A
'12r1172," Dose Pdojections" will be used to' control emergency L
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Appendix C Meteorological Model i
l 1
l i
1 i
l ODCM C-1 01-31-84
9 APPENDIX C PROPRIETARY INFORMNTION 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.
2.032fng. exp [-h3/2 r]j (x)]
(X/0)D hj(x)
NxUi Where:
he=
Effective release height (m).
(All releases from Wolf Creek Generating Station are considered as ground releases therefore h = 0.)
nij =
Hours of valid data for weather conditions in given direction, windspeed class i, and atmospheric stability class j.
N=
Total hours of valid data Ui=
Midpoint of windspeed class (m/s) x=
Distance downwind (m)
Czj (x)
Vertical plume spread without volumetric correction
=
at distance x and stability class j.
See Figure C.1 hz](x)
Vertical plume spread with volumetric correction
=
for release within buildings wake cavity, at l
distance x and stability class j.
l For ground level releases hj (x) is the lesser of 2
2 (e zj (x) + 0.5D /Tr ) 1/2 or
[3 C I*)
l zj l
where i
l Dz=
Maximum adjacent building height l
either up-or down-wind from the l
release point ODCM C-2 01-31-84 I
O b
2.032 = (2/n-) 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:
2.032f.nij 3
(X/Q) g =
N Ui x j (x)
The calculation of the relative deposition per unit 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/O is determined from relative deposi-tion by the following relationship:
Dij(x)
DEPLij(x)
(2e/16) x Where:
D j(x)
Relative deposition rate for windspeed class i
=
i and stability class j at downwind distance x (1/m).
Length of arc across sector at downwind (2w/16) x
=
distance x (:m).
Relative deposition per unit area (:m).
D/O
=
Reduction factor due to plume depletion at DEPL j(x) i~
distance x for windspeed i and stability class
=
j.
ODCM C-3.
01-31-84
l r,
1000 l
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0.1 1.0 10 100 PLUME TRAVEL DISTANCE (KILOMETERS)
Figure 1. Vertical Standard Deviation of Materialin a Plume (Letters denote Pasquill Stability Class)
NOTE: THESE ARE STANDARD RELATIONSHIPS AND MAY HAVE TO BE MODIFIED FOR CERTAIN TYPES OF TERRAIN AND/OR CLIMATIC CONDITIONS (E.G., VALLEY, DESERT, OVER WATER).
r ODCM C-4 01-31-84 a
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M C-6 01-31-84
.