ML20087N263
| ML20087N263 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 03/31/1984 |
| From: | TOLEDO EDISON CO. |
| To: | |
| Shared Package | |
| ML20087N246 | List: |
| References | |
| PROC-840331-03, NUDOCS 8404030277 | |
| Download: ML20087N263 (186) | |
Text
.
OFFSITE DOSE CALCULATION MANUAL FOR DAVIS-BESSE NUCLEAR POWER STATION Margh 1984
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OFFSITE DOSE CALCULATION MANUAL TABLE OF CONTENTS Page INTRODUCTION . . . . . . . . . . . . . . . . . . . . . . . . . . v 1.0 LIQUID EFFLUENTS 1.1 Liquid Effluent Monitor Setpoints . . . . . . . . . 1.0-1 1.1.1 Liquid Radwaste Effluent Line Monitors . . . 1.0-1 1.1.2 Turbine Building (Floor Drains) Sump Effluent Line (Applicable Upon Completion of Modification) . . . . . . . . . . . . . 1.0-6 1.2 Dose Calculation for Liquid Effluents . . . . . . . . 1.0-10 1.3 Projected Personal Maximum Dose . . . . . . . . . . 1.0-12 1.4 References to 1.0 Liquid Effluents . . . . . . . . . . 1.0-13
.2.0 GASEOUS EFFLUENTS 2.1 Gaseous Effluent Monitor Setpoints . . . . . . . . . . 2.0-1 2.1.1 Station Vent Monitor . . . . . . . . . . . 2.0-1 2.1.2 Waste Gas Decay System and Containment urge Monitors . . . . . . . . . . . . . . 2.0-3 2.2 Gaseous Effluent Dose Rate and Dose Calculations . . 2.0-5 2.2.1 Unrestricted Area Boundary Dose Rate . . . 2.0-5 2.2.2 Unrestricted Area Dose to Individual . . . 2.0-8 i
2.3 Meteorological Model . . . . . . . . . . . . . . . . 2.0-11 2.3.1- Long-Term Atmospheric Dispersion . . . . . . 2.0-11 2.3.2 Long-Term Deposition . ....... . . . . 2.0-14 2.4 Definitions of Gaseous Effluents Parameters . . . . . 2.0-15 2.5 References to 2.0 Gaseous Effluents . . . . . . . . . 2.0-20
, 3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING . . . . . . . . . . 3.0-1 l
l 3.1 Land Use Census . . . . . . . . . . . . . . . . . . 3.0-1 i
3.2 Sample Analyses ..... .......... . . . . 3.0-2 l
DAVIS BESSE, UNIT 1 i t
u _. ._ . _ _ _ .m -
OFFSITE DOSE CALCULATION MANUAL TABLE OF CONTENTS (Continued)
Page APPENDIX A Figures
- 1. Calibration curve for Liquid Effluent Monitors .'. . . A-1
- 2. Open terrain correction factor . . . . . . . . . . . . A-2
- 3. Plume depletion effect for ground-level releases . . . A-3
- 4. Plume depletion effect for 30-m releases . . . . . . . A-4
- 5. Plume depletion effect for 60-m releases . . . . . . . A-5
- 6. Plume depletion effect for 100-m releases . . . .. . A-6
. 7. Vertical standard deviation of material in a plume . . A-7
- 8. Relative deposition for ground-level releases . . . . A-8
- 9. Relative deposition for 30-m releases . .. . . . . . A-9
- 10. Relative deposition for 60-m releases . .. . . . . . A-10
- 11. Relative deposition for 100-m releases . . . . . . . . A-11
- 12. Map of sampling locations on the site periphery of the Davis-Besse Nuclear Power Station . . . . .. . A-12
- 13. Map of sampling locations greater than 1.5 miles from site . . . . . . . . . . . . . . . . . . . . . . A-13
- 14. Davis-Besse Gaseous Discharge . . . . . . . . . . . . A-14
- 15. Davis-Besse Liquid Discharge . . . . . . . . . . . . . A-15 16-50. Maps of individual sampling locations . .. . . . . . A-16 APPENDIX B Tables
- 1. Bioaccumulation factors . .. . . . .. . . . . .. . B-1
- 2. Ingestion dose factors for adults . . . . . . . . . . B-2
- 3. Site-related ingestion dose commitment factor . .. . B-5 4 Dose factors for exposure to semi-infinite cloud of noble Eases . . . . . . . . . . . . . . . . . . . . B-7 DAVIS BESSE, UNIT 1 ii
.~
OFFSITE DOSE CALCULATION MANUAL TABLE OF CONTENTS (Continued)
Page
- 5. Pathway dose parameter factors for implementing 10 CFR Part 20 . . . . . . . . . . . . . . . . . . . . B-8
- 6. Pathway dose parameter factors for implementing 10 CFR Part 50 . . ......... ... . ... . . B-20
- 7. Controlling receptors, locations, pathways and Atmospheric Dispersion Parameters . . ... ... . . B-59
- 8. Sampling locations . . . ...... ... ... . . . B-60
- 9. Type and Frequency of Sample Collection, Environmental Radiation Monitoring Program . .. . . . B-62
- 10. Sample Collection Codes .. . .... .. . .. .. . B-64 APPENDIX J Justifications Safety Evaluation . . . . . . . . . . . . . . . . . . . . . J-1 Service Water System-Radiological Effluent Monitoring Requirements . ... . ...... . . J-4 Radioactive Effluent Instrumentation -
- Automatic Isolation Feature ............ . . J-5 Technical Bases for Eliminating Curie Inventory Limit for Gaseous Waste Decay Tanks . . . . . . . . . . . . . . . . . . . . . J-6 Lower Limit of Detection-Decay Correction Factor . . . . . . . . . . . . . . . . . . . . . J-9 Technical Basis for Liquid Radwaste System Operations ....... ..... . . . . J-13 Waste Gas Decay System and Ventilation System-Operability Requirements . ... . . . . . . . . . . . . . . . . . . . J-16 Radiological Effluent Dose Analysis-Meteorology for Short Term Releases . . . . . . . . . . . . . . . . . . . J-18 Radiological Environmental Reporting Levels . . . . . . . . . . . . . . . . . . . . . J-19
, Technical Basis for Eliminating Curie Inventory' Limit of Outside Liquid Tanks ..... . . . . . . . . . . . . . . . . . . J-20 DAVIS BESSE, UNIT 1 iii
OFFSITE DOSE CALCULATION MANUAL TABLE OF CONTENTS (Continued)
Page Sampling Frequency for I-131:
Significance of Power Changes and "
Increases in Coolant Activity Levels . . ,. ... . . . . J-21 Condensate Demineralizer Backwash Receiving Tank - Radioactivity Control .... . . . . . . J-24 Lower Limit of Detection, Definition and Application tb Detection Capabilities for Ce-144. . . . . . J-26 I
m DAVIS BESSE, UNIT 1 iv
INTRODUCTION This OFFSITE DOSE CALCULATION MANUAL (CDCM) ce.ct Los the methodology and parameters to be used in the calculation of offsite doses due to radioactive
. liquid and gaseous effluents and in the calculatioa of liquid and gaseous effluent monitoring instrumentation alarm / trip setpoints. The ODCM also contains a list and graphic description of the specific sample locations for the radiological environmental monitoring program.
The ODCM will be maintained at the Station for use as a reference guide and training document of accepted methodologies and calculations. Changes in the calculational methods or parameters will be incorporated into the ODCM in order to assure that the ODCM represents the present methodology in all applicable areas.
The methodology stated in this manual is acceptable for use in demonstrat-ing compliance with 10 CFR Part 20.106, 10 CFR Part 50 Appendix I, and 40 CFR Part 190. 0nly the dose attributable to the Davis-Besse Nuclear Power Station is considered in demonstrating compliance with 40 CFR Part 190. .
More conservative calculation methods and/or conditions (e.g., location and/or exposure pathways expected to yield higher computed doses) than appropriate for the maximally exposed person may be assumed in the dose evaluations.
For the calculation of individual doses from gaseous effluents, the receptor is selected on the basis of applicable exposure pathways identi-fied in the land use census. Methodologies and pathways considered in NUREG-0133 are consistent with those in the ODCM.
For liquid releases, doses are evaluated for the drinking water and freshwater fish pathways. In the Great Lakes region, invertebrates do not constitute a direct ingestion pathway to man.
DAVIS-BESSE, UNIT 1 v
1.0 LIQUID EFFLUENTS 1.1 Liquid Effluent Monitor Setpoints 1.1.1 Liquid Radwaste Effluent Line Monitors Liquid Radwaste Effluent Line Monitors provide alarm and
. automatic termination of release prior to exceeding the concentration limits specified in 10 CFR Part 20, Appendix B, Table II, Column 2 at the release point to the unrestricted area. To meet this specification, the alarm / trip setpoints for liquid effluent monitors and flow measurement devices are set to assure that the following equation is satisfied:
cf <C, (1-1)
F+f where:
C = the effluent concentration limit (RETS, section 3.11:1) implementing 10 CFR Part 20.106 for the site, in pCi/ml .
. c = the setpoint, in pCi/ml, of the radioactivity monitor measuring the radioactivity concentration in the effluent line prior to dilution and sub-sequent release; the setpoint, which is propor-tional to the volumetric flow of the effluent line and inversely 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 10 CFR Part 20.106 in the unrestricted area f = the flow setpoint as measured at the radiation monitor location, in volume per unit time, but in l the same units as F, below DAVIS-BESSE, UNIT 1 1.0-1 L
F = the dilution water flow setpoint as measured prior to the release point in volume per unit ,
time.
At Davis-Besse Unit 1, the available dilution water flow , I (F) is constant for a given release, and the waste tank flow (f) and monitor setpoint (c) are set to meet the condition of Equation 1-1 for a given effluent concentra-tion, C. The method by which this is accomplished is as follows:
- 1) The isotopic concentration for a waste tank to be released is determined by the analyses required in RETS Table 4.11-1. The ratio of the concentration to the unrestricted area MPC (10 CFR Part 20, Appendix B, Table II, Column 2) is calculated with the equation:
C
- g. (1-2) h MPC.
1 1 where:
FMPC = fraction of the unrestricted area MPC ,.
C g = concentration of each radionuclide i measured !
in each tank prior to release (pCi/ml)
MPCg . = unrestricted area MPC for each radionuclide i from 10 CFR Part 20, Appendix B, Table II, Column 2. For dissolved and entrained noble gases a value of 2 x 10-4 pCi/ml shall be used.
~ DAVIS-BESSE, UNIT 1 1.0-2
The total or gross beta or gamma activity alone may be used to conservatively determine the NPC fraction by the equation:
C FMPC = t (1-3) 1x10 '
Where:
Cg = the total or gross beta or gamma activity 1 x 10-7 = MPC value for an unidentified mixture of radionuclides (from footnote 3.b to 10 CFR Part 20, Appendix B).
- 2) The MPC fraction (FMPC) as determined for each batch used to calculate a Dilution Factor, D.F., which is the ratio of total dilution flow rate to tank flow rate required to assure that the limiting concentra-tion of 10 CFR Part 20, Appendix B, Table II, Column 2 are met at the point of discharge.
D.F. = IMPC (1-4)
S.F.
where:
D.F. = dilution factor S~.F. = an administrative safety factor normally applied at Davis-Besse which causes the calculated Dilution Factor to be 3.33 times larger than the dilution factor required for compliance with 10 CFR Part 20 limits.
' DAVIS-BESSE, UNIT 1 1.0-3
- 3) The maximum permissible waste tank flow rate, f , is d
calculated based on a fixed dilution flow rate, F d fd= d+Id3 F
d for Fd >> Id (1-5)
D.F. D.F.
where:
E d
= 0.9 x (dilution flow rate), as readout in control room fd m Ximum Permissible waste tank flow rate D.F. = Dilution Factor from Step 2.
NOTE that the equation is valid only for D.F. >1; for D.F. <1, the waste tank concentration meets the limits of 10 CFR Part 20 without dilution, and f may d take on any desired value.
- 4) The minimum dilution flow (F), and waste tank maximum flow rate setpoint (f) are calculated as follows:
F=Fd = 0.9 x actual dilution flow rate as observed from the control room readout, f = 0.9 x fd = 0.9 calculated maximum waste tank flow rate for the stated release conditions.
A control room alarm occurs if the dilution flow rate falls below the preset flow rate, or if the tank flow rate exceeds 0.9 of the preset flow rate, and the release is terminated.
DAVIS-BESSE, UNIT 1 1.0-4
- 5) The monitor setpoint may now be specified based on the values of F, and f which were specified to assure that releases are maintained below the concentrations of 10 CFR Part 20, Appendix B, Table II, Column 2. The monitor setpoint in counts per minute (cpm) is taken from the monitor calibration graph (e.g. , Figure 1) to correspond to three times the concentration in the batch.
S.P. = 3 x A (pCi/ml) (1-6) where:
S.P. = the monitor setpoint obtained from the calibration curve for the monitor (cpm)
A = total radioactivity concentration in the batch A=IC i 8i or, if based on gross or total beta or gamma analysis, A=C g Normally, only one liquid release is conducted at a time. If more than one release of radioactive effluents is conducted simultaneously, the setpoints for the individual radiation monitors for the combined releas-es will be set to prevent exceeding the concentrations of 10 CFR Part 20, Appendix B, Table II, Column 2 in the environment.
1 NOTE that the setpoint contains a factor of conserva-tism, even if'the calculated setpoint tank flow rate DAVIS-BESSE, UNIT 1 1.0-5 t-
is attained, since the calculated rate contains the factors as shown:
0.3 x 0.9 x 3 = 0.81
_ fraction of limit for trip setpoint
_ multiplier for setpoint from equation (1-4)
_ waste tank rate margin
_ dilution factor margin In practice, the actual tank flow rate normally is many times less than the calculated tank flow rate, thus providing an additional safety factor during a release.
1.1.2 Turbine Building (Floor Drains) Sump Effluent Line (Applicable upon completion of modification)
The purpose of the monitor for the turbine building sump effluent line (or Unit Storm Sewer Outlet) is to detect abnormal radionuclide concentrations in the sump effluent system. Because the only sources to the sump effluent
. system are from the secondary steam system, activity is
-expected in the turbine building sump effluent system only if a significant primary-to-secondary leak is present. If a primary-to-secondary leak is present, the activity in the sump effluent system would be comprised of or.ly those radionuclides found in the secondary system, but with reduced activity from decay and dilution.
Until activity is measured in the secondary system, it will not be practical to select radionuclides on which to calculate the setpoint of the inline monitor. The monitor ,
is, therefore, operated normally as a gross gamma detector DAVIS-BESSE, UNIT I 1.0-6
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at the lowest practical activity level to prevent false ala rms . The lowest practical level has been determined to be three times the background count rate of the monitor when filled with clean water.
When activity above the level specified in RETS Table 4.11-1 is detected in the secondary system, the principal nuclide or nuclides comprising a major fraction of the activity in the secondary system condensate will be identified by gamma ray spectroscopy in the laboratory. The monitor setpoint will then be determined as follows:
- 1) The isotopic concentration for the turbine building sump effluent is determined by the sampling and analytical requirements per RETS Table 4.11-1 (only required when secondary system concentration exceeds 10-5 pCi/ml). The ratio of the concentration to the unrestricted area MPC is calculated with the equation:
C
- g. .
(1-7)
FMPC1= I d1 i :Where: ,
l FMPC = fraction of the unrestricted area MPC C
g = concentration of'each radionuclide i measured in each grab sample c
MPC . = unrestricted. area MPC for each radionuclide i f
from 10 CFR Part 20, Appendix B, Table II, Column 2. For dissolved and entrained gases, a value of 2x10-4 pCi/ml shall be used.
DAVIS-BESSE, UNIT 1 1.0-7
e If based on gross or total beta or gamma analysis, the unrestricted area MPC fraction is simply:
(1-8)
C' FMPC = 1x10 '
Cg = the total or gross beta or gamma activity 1x10-7 = MPC value for an unidentified mixture of radio-nuclides (from footnote 3.b to 10 CFR Part 20, Appendix B).
- 2) The actual dilution factor from fixed flow rates of the turbine building sump effluent flow rate and dilution flow rate is as follows:
actual dilution factor = f + F f
where:
f = turbine building sump effluent flow rate (8Pe)
F = dilution flow rate (gpm) - -
- 3) The concentration in the turbine building sump which corresponds to an unrestricted area MPC value after dilution is calculated from the previously defined quantities, and is:
A (1-9) c_pyg ,f+F f
~ DAVIS-BESSE, UNIT 1 1.0-8
where:
c = concentration corresponding to the unrestricted area MPC value after dilution A = total radioactivity concentration (pCi/ml)
A=IC i 8i or, if based on total or gross beta or gamma analysis, A=C g The calibration curve for the monitor (e.g., Figure 1) is then used to determine the count rate (cpm) corre-sponding to the radionuclide concentration (c). The monitor setpoint is the sum of the calculated count rate plus the observed background count rate of the monitor.
To simplify the determination of setpoint or in the event that the concentration of radioactive material in the sample from the turbine building sump is below measurable levels (i_.e., less than 5 x 10-7 pCi/ml for principal gamma emitters), the value of 1 x 10-7 pCi/ml may be substituted for the factor A (i.e., A = 1 x 10-7).
FMPC FMPC l
It may conservatively be assumed that the radionuclide concentrations in the secondary system are identical to those in the turbine building sump. Therefore, the results of the sampling and analysis of the secondary system may be used in conservatively determining the values of FMPC and c, above.
DAVIS-BESSE, UNIT 1 1.0-9
1.2 Dose Calculation for-Liquid Effluents Technical Specification 4.11.1.2.1 requires that an assessment be performed at least once every 31 days in any quarter in which radio-active effluent is' discharged to determine whether the dose or dose commitment to a person offsite due to radioactive material released in liquid effluent calculated on a cumulative basis exceeds Specifi-cation 3.11.1.2. The requirement is satisfied by computing the accumulated dose commitment to the most exposed organ and to the total body of a hypothetical person exposed by eating fish and drinking water taken from Lake Erie.
g .
The dose contribution from all radionuclides identified in liquid effluents released to unrestricted areas is calculated using the following expressions:
I atg Cig gF D7 ={A17 i f=1 _
where:
D 7
= dose or dose coannitment to organ I, including total body (mrem).
w+U pBF.1 DFg , the site-related ingestion does coramitment At =K-i o factor from radionuclide'i ("p#*C ) (f#
- Table 3 of Appendix B).
th atg= length of the f time period over which C gg and Fg are averaged for all_ liquid releases, in hours.
C it = average concentration of radionuclide i observed in undiluted liquid effluent during time period atg from any liquid release, in pCi/ml. Concentrations are determined DAVIS-BESSE, UNIT 1 1.0-10 L -_-_
primarily from a gamma isotopic analysis of a liquid effluent sample. For Fe-55, Sr-89, Sr-90, and H-3, the last measured value will be used in dose calculations.
=
Fg near-field average dilution factor for Cf during any liquid effluent release. Defined as the ratio of the average undiluted liquid waste flow during release to the product of the average flow from the site discharge structure to unrestricted receiving waters times the near-field dilution factor of 10 times the collection box factor of 1.0 (Ref. 2).
Fg = average undiluted liquid waste flow average flow from the site discharge x 10 x 1.0 K, = units conversion factor 1.14 x 103 (108 x 1031 " + 8,760 ) ,
U, = adult water consumption (730 liters /yr) (Ref. 3)
D, = dilution factor from the near-field area within one quarter mile of the release point to the potable water intake for adult water consumption. D, is (57/(10 x 1.0)) = 5.7, where 57 = lowest dilution factor corresponding to beach wells located approximately 966 m NW of the discharge point (Ref. 2). The near-field dilution factor of 10, represents the mixing effect of the discharge structure (Ref. 2).
U F
= adult fish consumption (21 kg/yr) (Ref. 3).
BF 1
= bioaccumulation factor for nuclide, i, in fish, in pCi/kg per pCi/ liter from Table 1 of Appendix B (taken from Reference 3, Table A-1).
DAVIS-BESSE, UNIT 1 1.0-11
DF = dose conversion factor for nuclide, i, for adults in t
preselected organ, T, in mrem /pci, from Table 2 of Appendix B (taken from Reference 3, Table E-11).
1.3 Projected Personal Maximum Dose The dose commitment to a person offsite due to radioactive
, material released in liquid effluent may be projected by calcu-f lating the extrapolated total body and most e:: posed organ dose commitments to a hypothetical person exposed by eating fish and drinking water. The potential dose commitments to organs and to the total body are computed separately.
The dose commitment to a maximally exposed hypothetical person will be projected by calculating the doses accumulated during the most recent three months according to the method described in Section 1.2 and by assuming that the result represents the projected doses during the current quarter.
Alternatively, the quarterly dose commitment may be projected by using the equation:
P7 = 91 D 7 (1-11)
X where:
P 7
= projected dose commitment (mrem) to organ I (including total body) for the current quarter 91 = number of days in a quarter X = number of. days to date in current quarter D = accumulated personal dose to data during the current 7
quarter via radioactive material in liquid effluent
-(mrem). .
DAVIS-BESSE, UNIT 1.0-12
1.4 REFERENCES
TO 1.0 LIQUID EFFLUENTS 1.4.1 J.S. Boegli, W.L. Britz, R.R. Bellamy, and R.L. Waterfield. ;
1978. " Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," NUREG-0133, Office of Nuclear Reactor Regulation, U.S. Nuclear Regula-tory Commission.
1.4.2 D.W. McDougall. 1980. " Aquatic Dilution Factors within 50 miles of the Davis-Besse Unit 1 Nuclear Power Plant."
Stone & Webster Engineering Corporation.
1.4.3 United States Nuclear Regulatory Commission. 1977.
" Calculation of Annual Dose to Man from Routine Releases of Reactor. Effluents for the Purpose of Evaluating Compliance with 10CFR50, Appendix I," Regulatory Guide 1.109, Revision 1.
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2.0 GASEOUS EFFLUENTS 2.1 Gaseous Effluent Monitor Setpoints
.1.1 Station Vent M.onitor The station vent is the only normal radioactive gaseous release point.
For the purpose of implementation of section 3.3.3.10 of the RETS, the alarm setpoint level for the station vent noble gas monitor will be calculated as follows:
0.5 (Rg) 500 S
y
= the lesser of or (2-1)
_0.5 (R,) 3000 Where:
S y
= count rate of station vent noble gas monitor at alarm setpoint level (cpm) 0.5 = safety factor allowing 100% margin for cumulative uncertainties of measurements (dimensionless)
Rg = count rate per mrem /yr to the total body R, = count rate per mrem /yr to the skin.
The values of Rg and R, are dependent on the radionuclide distribution and are derived by the equations:
Rg , C + [ X/QNG i
i ( i)] (2-2)
DAVIS-BESSE, UNIT 1 2.0-1
=
R, C + [( MNG ) Ii (bi
- I*A M ) i li (2'3) where:
C = count rate of the station vent monitor corresponding to grab sample radionuclide concentrations (cpm)
@= highest sector annual average atmospheric dis-NG persion at the unrestricted area boundary 1
3
= 1.83 x 10-6 sec/m in the north-northeast sector Kg = total body dose factor due to gamma emissions from isotope 1 (mrem /yr per pCi/m3 ) from Table 4 of Appendix B kg = rate of release of each noble gas radionuclide i identified by the sampling and analysis per RETS Table 4.11-2 (pCi/sec)
Lg = skin dose factor due to beta emissions from isotope i (arem/yr per pCi/m3 ) from Table 4 of Appendix B 1.1 = mrem skin dose per mrad air dose Mg = air dose factor due to gamma emissions from isotope 1 (mrad /yr per pCi/m3 ) from Table 4 of Appendix B.
DAVIS-BESSE, UNIT 1 2.0-2
A more conservative setpoint may be calculated to minimize requirements for adjustment of the monitor by using the equations:
R[ = C' + [(i7Q3g)K] (2-4)
R' = C' + [(i[QNG)(L + 1.1M)] (2-5) where:
R' = conservative count rate per mres/yr to the total body (Xe-133 detection, Kr-89 dose)'
R' = conservative count rate per mrem /yr to the skin (Xe-133 detection, Kr-89 dose)
C' = count rate of station vent monitor for an effluent concentration of Xe-133 corresponding to 1.0 pCi/sec release rate of Xe-133 (cpm)
K = total body dose factor for Kr-89, from Table 4 of
' Appendix B L =- skin dose -factor for Kr-89, from Table 4 of Appendix B
.M = ' air dose factor for Kr-89, from Table 4 of Appendix B t
~2.1.2 Waste Gas Decay System and Containment Purge Monitors The waste gas decay tank releases and containment purges, in addition to being monitored by the station vent monitor, are controlled individually to provide additional assurance that releases do not exceed the limits of Technical Speci-fications 3.11.2.1.
DAVIS-BESSE, UNIT 1 2.0-3
{
The setpoint level (S d) f r discharge through the waste gas decay system monitor will be calculated in a corresponding manner:
-0.5 (r g) 500 S
d
= the lesser of or (2-6)
_0.5 (r,) 3000
,w here:
S d
= count rate of waste gas decay system monitor at alarm setpoint level r
g
= count rate per mrem /yr to the total body r, = count rate per mrem /yr to the skin The values of rgand r, are dependent on the radionuclide distribution and are derived by the equations:
= c (
r g [(X/QNG)! 1 i i}
r s
- C I( ONG)h(i*I* i) i 1
(~}
where:
c '= count rate of the waste gas decay system monitor for radionuclide concentrations to be discharged (cpm) dg = rate of release of noble gas radionuclide i (pCi/sec)
V
~ DAVIS-BESSE, UNIT 1 2.0-4
For a more conservative, simpler setpoint for the waste gas system monitor, the equations are:
c' = c' + [(i7Q )K] (2-9)
NG c's = c' + [(i7Q )(L + 1.1M)] (2-10)
NG where:
c' = conservative count rate per mrem to the total body (Xe-133 detection, Kr-89 dose) r' = conservative count rate per mrem to the skin (Xe-133 detection, Kr-89 dose) c' = count rate of the waste gas decay system monitor for an effluent concentration corresponding to 1.0 pCi/sec release rate for Xe-133 The setpoint level for the containment purge noble gas monitor will be calculated using the same methodology as indicated for the waste gas decay system, utilizing the appropriate corresponding count and release rates.
The calculated setpoint values will be regarded as upper bounds for the actual setpoint adjustments (ie, setpoint adjustments are not required to be performed if the exist-ing setpoint level corresponds to a lower count rate than
'the calculated value).
2.2 Gaseous Effluent Dose Rate and Dose Calculations 2.2.1 Unrestricted Area Boundary Dose Rate
- a. Technical Specification 3.11.2.la limits the dose rate ,
in the unrestricted area due to noble gas releases DAVIS-BESSE, UNIT 1 2.0-5
from the station to 1500 mrem /yr, total body and 13000 mrem /yr, skin. Radiation monitor alarm setpoints are established to assure that these release limits are not exceeded. In the event any gaseous releases from the station results in the alarm setpoints being exceeded, an evaluation of the unrestricted area dose rate resulting from the release shall be performed using the following equations:
D tb
- (EkNG) I E i i (2-11) i D, =
(FQ3g) I (I,g + 1.1Mg ) 6 1 (2-12) i where:
D tb
= t tal body dose rate (mrem /yr)
D, = skin dose rate (mrem /yr)
FQ = highest sector annual average atmospheric NG dispersion at the unrestricted area boundary 3
= 1.83 x 10-6 sec/m in the north-northeast sector
- b. For I-131 and particulates with half-lives greater than 8 days, Technical Specification 3.11.2.1.b limits the dose rate to 11500 mrem /yr to any organ. To demonstrate compliance with this limit, an evaluation is performed at a frequency corresponding to the i
DAVIS-BESSE, UNIT 1 2.0-6 L ..
I sampling and analysis time period (e.g., normally once per 7 days for I-131). The following equation'may be used for evaluation:
=
D, (X/Q (2-13)
I )1 I (P Q't) g where:
= average organ dose rate over the sampling D,
time period (mrem / year)
((Q = controlling sector annual average atmos-I pheric dispersion at the site boundary for the inhalation pathway.
= 3 1.68 x 10-8 sec/m in the north-northeast sector.
'. g = dose parameter for radionuclide i, (mrem /yr per pCi/m3 ) for inhalation pathway from Table 5 of Appendix B. Values for Pg are derived in accordance with the methods described in NUREG-0133.
Q't
= average release rate over the appropriate sampling period and analysis frequency for isotope i, I-131 or other radionuclide in
- particulate form with half-life greater than eight days (pCi/sec).
I i
By substituting 1500 mrem /yr for D, (equation 2-13) and solvingforQ[,anallowablereleaserateforI-131can be determined. Based on the annual average meteorological dispersion (1.68 x 10-8 sec/m 3
) and the child inhalation 7 3 pathway (Pg = 1.62 x 10 mrem /yr per pCi/m ), the release rate for I-131 is 44.1 pCi/sec. An added conservatism i
l DAVIS-BESSE, UNIT 1 2.0-7 w.
factor of 0.8 has been included in this calculation to account for any potential dose contribution fron other radioactive particulate material. For a 7 day period which
'is the sampling and analysis frequency for I-131, the cumulative allowable release is 26.7 Ci. Therefore, as ,,
long as the I-131 releases in any 7 day period do not exceed 26.7 Ci, no additional analyses are needed to verify compliance with the Technical Specification 3.11.2.1.b limits on allowable release rate.
2.2.2 Unrestricted Area Dose to Individual
- a. Techracal specification 4.11.2.3 requires at least a monthly assessment of releases of noble gases te evaluate compliance with the quarterly dose limits of 15 mrad, gamma-air dose and 110 mrad, beta-air dose.
The following equations may be used to calculate the gamma-air and beta-air doses:
4 D = 3.17x10-8y3[(gNG)il (2-14) 1 D
g
=
3.17 x 10-8.I gN [( M NG ) i]
(2-15)
I where:
D = air dose due to gamma emissions for noble gas radionuclide i (mrad)
X/Q .= dispersion parameter for unrestricted areas NG
= 1.83 x 10-6 sec/m 3 Qi = cumulative release of noble gas radionuclide i over the period of interest (pCi)
DAVIS-BESSE, UNIT 1 2.0-8 L_ _
=
D g air dose due to beta emissions from noble gas radionuclide i (mead)
=
Ng air dose factor due to beta emissions from noble gas radionuclide i (mrad /yr per pCi/m3 ) from Table 4 of Appendix B.
3.17x10-8 = conversion factor (yr/sec)
- b. Technical Specification 4.11.2.3 requires an assess-ment at least once per 31 days to evaluate compliance with the quarterly dose limit of <7.5 mrem to any organ. The following equation may be used to evaluate the maximum organ dose due to releases of I-131 and particulates with half-lives greater than 8 days.
D p
= 3.17 x 10-8 I R g(W'Q'g) (2-16) 1 where:
D = dose or dose commitment to organ p, includ-P ing the total body, from I-131 and radio-nuclides in particulate form with half-life greater than eight days (mrem) l l
t r
I- DAVIS-BESSE, UNIT 1 2.0-9 L
W' = dispersion or deposition parameter for the controlling receptor location 3
57Q' = 1.19 x 10-s sec/m for inhalation pathway and H-3 dose contribution via other pathways (from Table 7 of Appendix B)
=
D7Q' = 1.39 x 10-8 m -2 vegetation path-way (from Table 7 of Appendix B)
Rg = dose factor for radionuclide i, (mrem /yr per pCi/m3 ) or (m2 - mrem /hr per pCi/sec) from Table 6 of Appendix B. Values for Rg were derived in accordance with the methods described in NUREG-0133.
4 Q'1
= cumulative release of radionuclide i of I-131 or material in particulate form in long-term releases over the period of interest (pCi).
i The location of exposure pathways and the maximum organ dose may be based on the available pathways in the surrounding environment of Davis-Besse as identified by the annual land-use census (Technical Specifica-tion 3.12'.2). Table 7 of Appendix B will be supple- ,
mented yearly by including in the Semi-Annual Radioactive Effluent Report the applicable exposure pathways as identified by the census.
5 DAVIS-BESSE, UNIT 1 2.0-10'
- c. For the purpose of implementing RETS Technical Speci-fication 3.11.3 on the EPA environmental radiation dose standard and 6.9.1.13 on reporting, dose calcula-tions will be performed using the above equations with the substitution of average or actual meteorological parameters for the period of interest and applicable pathways.
2.3 Meteorological Model 2.3.1 Long-Term Atmospheric Dispersion Atmospheric disper:: ion for long-term releases is calculated using a mixed-mode, wake-split form of the straight-line flow Gaussian dispersion model, referenced in Regulatory Guide 1.111, Revision 1.
X/Q = atmospheric dispersion (sec/m3) 2.03 k6 1-E h2- E (2-17) r
_z uo exP p
z- +ng_
.a .
s where:
k = open terrain recirculation factor at distance r from Figure 2 of Appendix A.
6 = plume depletion factor at distance r for appro-priate stability class and effective height from Figures 3-6 of Appendix A. (Note: This plume depletion factor applies only to releases of radioiodines. The depletion factor for noble gases is unity.)
-DAVIS-BESSE, UNIT 1 2.0-11
E = fraction considered as ground level 1.0 v 11.0 for 2.58-1.58 v for 1.0< v $1.5 u u 0.3-0.06 v for 1.5< v 15.0 u u 0 for
{>5.0 v = station vent exit velocity (13.4 m/sec) u = wind speed at vent height from the 75-m level of the main meteorological tower (m/sec)
J u = wind spaed at ground level from the 10-m level of 8
the satellite meteorological tower (m/sec) 0, = vertical standard deviation of the plume at distance r for effective height under stability category indicated by temperature lapse rate AT
. (*C/100m) from Figure 7 of Appendix A.
AT = temperature differential with vertical separation between the 10-m and 75-m levels of the main meteorological tower ( K/100m) h = effective height of release (m)
= h v
+h pr -h t hy = height of station vent
= 75.3m
' DAVIS-BESSE, UNIT 1 2.0-12
h pr
= additional height due to plume rise (m) for stability classes A, B, C, D 2/3 1/3 -
the lesser of 1,44 " j d
-c y or 3 vd-subject to, for stable conditions (AT > - 0.5 *K/100m):
_ 1/4
_F the lesser of 4 _-j_
or
_ 1/3
_F -1fs 1.5 -" S d = diameter of station vent
= 2.12 m
-c y = correction for low vent exit velocity (m) v v 3 d for - < 1.5
_1.5 - u_ u
=
0 for{>1.5 4
F, = momentum flux parame,ter (m /sec2 )
=
(If) 2.0-13
S = restoring acceleration per unit vertical dis-placement for adiabatic motion in the atmosphere 8.7 x 10-4 sec -2 for AT 1 1.5 (E)
.. 1.75 x 10-3 sec -2 for AT $ 4.0 (F) 2.45 x 10-3 sec -2 for AT > 4.0 (G) hg = height of terrain at distance r in sector of interest (m) r = downwind' distance (m)
I = vertical standard deviation of the plume with building wake correction (m)
= the lesser of 02 , (0.5)b 2 1/2
_z n_
or
/3oz b = height of reactor building
= 73.5m 2.3.2 Long-Term Deposition Relative deposition per unit area for long term releases is calculated for a mixed mode release.
D/Q = relative deposition per unit area (m-2) 2.0-14 f
= 2.55k r
(1-E) De + ED g (2-18) where:
D, = relative deposition rate for elevated releases from Figures 9 through 11 of Appendix A.
D = relative deposition rate for ground level releases g
'frem Figure 8 of Appendix A.
2.4 Definitions of Gaseous Effluents Parameters b = height of reactor building (m) (Section 2.3.1)
C = count rate of the station vent monitor corresponding to grab sample radionuclide concentrations (cpm)
(Section 2.1.1)
C' = count rate of station vent monitor corresponding to a 1.0 pCi/sec release rate of Xe-133 (cpm) (Section 2.1.1) c = count rate of the waste gas decay system monitor for radionuclide concentrations to be discharged (cpm)
(Section 2.1.2) c' = count rate'of the waste gas decay system monitor corre-sponding to a 1.0 pCi/sec- release rate of Xe-133 (cpm)
-(Section 2.1.2) cy = effective plume height correction for low vent exit velo-city (m) (Section 2.3.1) 2.0-15
-o ,e ,.
l l
D, = relative deposition rate for elevated releases from Figure 6.
of Appendix A (Section 2.3.2)
~
D 8
= relative deposition rate for ground level releases from Figure 7 of Appendix A (Section 2.3.2)
Dg = average organ dose rate (mrem / year) (Section 2.2.1.b)
D = dose ov dose commitment to organ p, including the total P
body, from I-131 and radionuclides in particulate form, with half-life greater than eight days (mrem)'
(Section 2.2.2.b)
D, = average skin dose rate (mrem / year) (Section 2.2.1.a)
.D tb
= average total body dose rate (mrem / year) (Section 2.2.1.a)
D p
= air dose due to beta emissions from noble gas radionuclide i (mrad) (Section 2.2.2.a)
D = sir dose due to gamma emissions from noble gas radionuclide i (mrad) (Section 2.2.2.a)
D/Q .= relative deposition per unit area (m-2) (Section 2.3.2) d = diameter of station vent (m) (Section 2.3.1) 6 == plume depletion factor at distance r for appropriate stability class and effective height from Figures 3 and 4 of Appendix A (dimensionless) (Section 2.3.1) ,
E = fraction of release-considered as ground level (dimension-less) (Section 2.3.1) 4 2 F, = momentum flux parameter (m /sec ) (Section 2.3.1) 2.0-16
4 h = effective height of release (m) (Section 2.3.1) hg = height of terrain at distance r in sector of interest (m)
(Section 2.3.1)
' hy = height of station vent (m) (Section 2.3.1) h,p
= additional plume height due to plume rise (m)
(Section 2.3.1)
K = total body dose factor for Kr-89, (mrem /yr per'pci/m3) from Table 4 of Appendix B (Section 2.1.1)
K-g
= total body dose factor due to gamma emissions from radio-nuclide (mrem /yr per pCi/m3 ) from Table 4 of Appendix B (Section 2.1.1) k = open terrain recirculation factor at distance r from Figure 2 of Appendix'A (dimensionless) (Section 2.3.1)
L = skin dose factor for Kr-89, the most restrictive radio-nuclide, from Table 4 of Appendix B (mrem /fr per pCi/m3 )
(Section 2.1.1)
L i
= skin dose factor due to beta emissions from radionuclide i (mres/yr per pCi/m3) from Table 4 of Appendix B (mrem /yr per pCi/m3 ) (Section 2.1.1)
M = air dose factor for Kr-89, the most restrictive radio-nuclide,'from_ Table 4 of Appendix B (mrad /yr per pCi/m3 )
(Section 2.~1.1)
Mg = air. dose factor due'to gamma emissions from radionuclide i (mrad /yr per pCi/m3 ) from Table 4 of Appendix B (Section 2.1.1) 2.0-17
Ng = air dose factor due to beta emissions from noble gas radionuclide i (mrad /yr per pCi/m3 ) from Table 4 of Appendix B (Section 2.2.2.a)
Pg = dose parameter for radionuclide i, (mrem /yr per pCi/a3 ) for inhalation from Table 5 of Appendix B (Section 2.2.1.b) 61 = rate of release of noble gas radionuclide i (pCi/sec)
(Section 2.1.1)
Q'1
= average release rate over appropriate sampling period of isotope i of I-131 or other radionuclide in particulate form, with half-life greater than eight (8) days (pCi/sec)
(Section 2.2.1.b) 41 = cumulative release of noble gas radionuclide i over the period of interest (pCi) (Section 2.2.2.a) 4'1
= cumulative release of radignuclide i of I-131 or material in particulate form over the period of interest (pCi)
(Section 2.2.2.b) ilf = rate of release of noble gas radionuclide i (pCi/sec)
(Section 2.1.2)
Rg = dose factor for radionuclide i, (mrem /yr per pCi/m3 ) or
-(m2 - mrem /yr per pCi/sec) from Table 6 of Appendix B (Section 2.2.2.b)
R, = count rate per mrem /yr to the skin based on current isotope distribution (Section 2.1.1)
R t
= count rate per mrem /yr to the total body based on current isotope distribution (Section 2.1.1)
R', = conservative count rate per mrem /yr to the skin (Xe-133 detection Kr-89 dose) (Section 2.1.1) 2.0-18
=
R'g conservative count rate per mrem /yr to the total body (Xe-133 detection, Kr-89 dose) (Section 2.1.1)
=
r downwind distance (m) r, =-
count rate per mrem /yr to the skin based on waste gas decay
-system isotope distribution (Section 2.1.2) %
r = count rate per mrem /yr to the total body based on current waste gas decay system isotope distribution (Section 2.1.2) r = conservative count rate per mrem to the skin for waste gas s
decay system only (Section 2.1.2) r' '= Conservative count rate per mrem to the total body for waste gas decay system only (Section 2.1.2)
S = restoring acceleration per unit vertical displacement for adiabatic motion in the atmosphere (sec-2) (Section 2.3.1)
S d
= count rate of waste gas decay system noble gas monitor at alarm setpoint level (Section 2.1.2) ,
S y
= count rate of station vent noble gas monitor at alarm setpoint level (Section 2.1.1)
I = vertical standard deviation of the plume with building wake correction (m) (Section 2.3.1)
I l- a z
= vertical standard deviation of the plume at distance r for effective height under stability category indicated by AT from Figure 5 of Appendix A (m) (Section 2.3.1)
AT = temperature differential with vertical separation (*K/100m)
(Section 2.3.1) 2.0-19 t.
u = wind speed at vent height from the 75-m level of the main meteorological tower (m/sec) (Section 2.3.1) u g
= wind speed at ground level from the 10-m level of the
. satellite meteorological tower (m/sec) (Section 2.3.1) v = plant vent exit velocity (m/sec) (Section 2.3.1)
- W' = dispersion and deposition parameter for the controlling receptor location (dispersion: sec/m3 , deposition: m -2)
(Section 2.2.2.b)
X/Q = atmospheric dispersion (sec/m 3 ) (Section 2.3.1)
X/Q = highest sector annual average atmospheric dispersion value at the unrestricted area boundary (sec/m3 ) (Section 2.1.1)
X/Q7= controlling sector annual average atmospheric dispersion at the site boundry for the inhalation pathway (Section 2.2.1.b)
X7iiNG= highest sector annual average atmospheric dispersion at the unrestricted area boundary (sec/m3 ) (Secton 2.2.2.a) 2.5 References to 2.0 Gaseous' Effluents 2.5.1 J. S. Boegli, W. L. Britz, R. R. Belamy, and R. L. Waterfield.
1978. " Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," NUREG-0133, Office of Nuclear Reactor Regulation, U.S. Nuclear Regula-tory Commission.
2.5.2 United States Nuclear Regulatory Commission. 1977.
" Methods for Estimating Atmospheric Transport and Disper-sion of Gaseous Effluents in Routine Releases from Light- j Water-Cooled Reactors," Regulatory Guide 1.111, Revision 1.
2.0-20 i
3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING Sampling locations as required in Section 3/4.12.1 of the Radiologi-cal Effluent Technical Specifications are described in Table 8 of Appendix B and shown on maps in Appendix A, pages A-12 and A-16 through A-50.
3.1 Land Use census A land use census shall be conducted annually for the purpose of identifying changes in the use of the offsite area surrounding Davis-Besse which may substantially affect the radiological dose assessment or which may indicate needed adjustments to the Program. This census satisfies the criteria of 10 CFR Part 50, Appendix I, Section IV.B.3.
The census will include land within 5 miles of Davis-Besse and will be conducted at least annually. It will be conducted by either a door-to-door survey, aerial survey, or by consulting local agricultural authorities or by a combination thereof.
The locations of: 1) the nearest milk animal, 2) the nearest vegetable garden greater than 500 square feet, and 3) the' nearest resident, within 5 miles of Davis-Besse in each of 16 sectors in cardinal compass point directions from the plant, are to be identified in the census. If a milk animal is not identi-fied in a sector within 5 miles, one may conservatively assume that one is located at the 5-mile distance for purposes of evaluating maximum potential organ dose and identifying the con-trolling pathway, except in those sectors over Lake Erie.
If the land use census identifies a location (s) at which the dose or dose commitment calculated at the time is greater than the maximum calculated dose associated with the like pathway (s) at a location where sampling is conducted as specified by the monitoring program, then the pathways having maximum exposure 3.0-1
- potential at the newly identified location will be added to the program, if samples are reasonably obtainable at the new loca-tion. Like pathways monitored (sampled) at a location, exclud-ing control station location (s), having a lower associated calculated personal dose may be deleted from the program at the
' time the new pathway (s) and location (s) are added. ,.
3.2 Sample Analyses Radioactivity in environmental samples described in Table 8 of Appendix B may be analyzed either at Davi,s-Besse or at an offsite laboratory. In order to provide a comparative check on the accuracy and precision of these analyses, the laboratory participates in the USEPA Interlaboratory Comparison Program by analyzing radioactive samples distributed for the purpose.
i Tables 9 and 10 of Appendix B identify the type and frequency of environmental sample collection.
e t
DBP 4306G 3.0-2'
h 4 < a s._.' a - -
- 1. + - -
I E.
t I APPENDIX A Figures l
I
- - - .- , , - ~_-. . , - -. ._,,_.--., , - -. , , _ , , . .. . - , _ , . ,, ,,...,, , , _ ...,.,_.., . , ..._ ,._. .._.. , . . , _ , , , . , . _ . , _ _ _ __._ _
I t
i i
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'i i Figure 1 ; i i ; ..- Calibration Curve -
2
. 18888 8
'8 for Liquid Effluent Monitors , ,' , ; ,' ;l,l i
, '....I !
iilil i ll (RE 1770 A & B RE 1878 A & B)
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! DAVIS-BESSE, UNIT 1 t
A-1
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it c
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(
o 0.4 (
4
, k l 0.3 __
i 0.2 l
0.1 0.1 1.0 104 100.0 200.0 PLUME TRAVEL DISTANCE (KILOMETERS)
Figure 3 Plume Depletion Effect for Ground Level Releases (All Atniospheric Stability Classes)
- - h 0.
0 3 0 2
0 _
N 0 _
0 y
,s 1 _
p,\ )
s
. s _
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z
- -UNSTABLE N
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h0.6 a
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! h0.4 4 k i
E j 0.3 0.2
- 0.1 i
0.1 1.0 10.0 100.0 2M.0 PLUME TRAVEL DISTANCE (KILOMETERS) l Figure 5 Plume Depletion Effect for 60m Releases (Letters denota Pasquill Stability Class)
, ^
$ E j @ 1.0 g ~ - -
~%
0.9 s A " #
e N s .
4 us 0.8 -
E ' T 3
N UNSTABLE
- 8 i
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z gg i
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1 E
0.3 I 0.2 0.1 0.1 1.0 10.0 100.0 200.0 PLUME TRAVEL DISTANCE (KILOMETERS)
Figure 6 Plume Depletion Eflect for 100m Releases (Letters denote Pasquill Stability Class)
1000 l /
s'
/ j s
/
,/
/ /
/ ,
f r l }
f . s 1 s '
/ / ' / l
/
l l
/ - / ' /
- - l too / s' , '- s 1
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' 100 ME TRAVEL. DISTANCE (KILOMETERS)
Fig. 7 tim of Material in a Plume (Letters denote Pasquill Stability Class DAVIS.BESSE, UNIT 1 g_7 e
- 'e' es ,
g y w ,-->v--- - - - ,-e- v-- p - , - --
.-r--,-----y.,-
10-3 1 104 \ ~
~
E W
w p A w
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w A I- NN g g
104 A i X E '
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s y \
E s 5 \
=
m Ns 104 i ....
x I
10-7 0.1 - 10.0 100.0 200.0 r
PLUME TRAVEL DISTANCE (KILOMETERS)
Figure 8 Refetive Deposition for Ground Level Releases (All Atmospheric Stability Classes)
~ DAVIS-BESSE, UNIT 1 A-8 t
, i 104 i
s.
.E F
l i :
- i ... UNSTABLE (h,B,C)
,t 10-4 '
s%
j ',' g ,s s
.- b '\
3
, f 'sN g ,[ \\ NEUTRAL e / NN m
2 f
NEUTRAL (D)
T Kg%
h 104 % STABLE
- a. i
/ '
v'
,r x N x E i f/ NN _2 m / / K7N\ '
$ / / \ %
2 / / N %
=
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- x 10-6 I I I I r i f
l
/
10-7
. 0.1 1.0 10.0 100.0 20C PLUME TRAVEL DISTANCE (KILOMETERS)
Figure 9 Relatiw Deposition for 30e Releases (Letters denote Pasquill Stability Class)
DAVIS-BESSE. UNIT 1 A-9
104 s- w UNSTABLE (A,B,C)
[ \
/
. [
\
1G4
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5 / / .! X c ! / xw 3 / \ N w UNSTABLE 6 [ \ %
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. n' f I
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T-28 Surface Water-Treated Statio'n is located on-site in the Water Treatment Building.
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The Water Treatment Building is located within the Protected Area of the Station.
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T-33 Fich s:=pico et T-33 is located in Lake Erie within an 8.0 km radius of the site.
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T-35 Fish Samples T-35 is located in Lake Erie at a distance greater than a 16 km radius from the site.
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TABLE 1 BI0 ACCUMULATION FACTORS (pCi/kg per pCi/ liter) g FRESHWATER FISH H 9.0E C 4.6E+03 NA 1.0E+02 P 3.0E+03 CR 2.0E+02 MN 4.0E+02 FE 1.0E+02 CO 5.0E+01 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' l.0E+01
'RH 1.0E+01 TE 4.0E+02 I 1.5E+01 CS 2.0E+03 BA 4.0E+00 LA 2. 5E+01 CE 1.0E+00 PR 2.5E+01 ND 2.5E+01 W 1.2E+03 NP 1.0E+01
' Values in this Table are taken from Regulatory Guide 1.109 except:for Phosphorus which~is'taken from NUREG/CR-1336.
DAVIS-BESSE, UNIT 1 B-1
Table 2 Page 1 of 3 INGES T ION OUSE F ACTORS FOR ADULTS
(" REM *ER 8CI INGESTE01 fiUCL I CE BCNE liver T.800Y THYR 0!O KIONEY LUNG GI-LLI H 3 NO DATA 1.05E-07 1. 0 S E -0 7 1.05d-07 1.05E-07 1 05E-07 1.05E-07 C 14 2.84E-06 -5.68E-07 5.685-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 NA 24 1.70E-06 1.70E-06 1. 70 E-0 6 1. TOE-06 1.70E-06 1.70E-06 1.70E-06 P 32 1.93E-04 1.20E-05 7. 40 E-0 6 NO DATA NC OATA NO DATA 2.17E-05 CR 51 NO DATA NO DATA 2.6o!-09 1 59E-09 5.86E-10 3.53E-09 6.69E-07 MN 54 NO DATA 4.575-06 S . 72 E-0 7 NO DATA 1.36E-06 NO DATA 1 40E-05 MN $6 .NO DATA 1.15E-07 2 045-08 NO DATA 1 46E-07 NO DATA 3 67E-06 FE 55 2.75E-06 1.90E-06 4. 4 3 E-0 7 NO DATA NO DATA 1.06E-06 1.09E-06 FE 59 4.34E-C6 1.02E-05 3.91E-06 NO DATA NO DATA 2 85E-06 3.40E-05 CO 58 NO DATA 7.456-07 1. 67 E-0 6 NO DATA NO DATA NO DATA 1 51E-05 CD 60 NO DATA 2.14F-06 4. 72 C-0 6 NO DATA NO DATA NO DATA 4.02E-05 NI 63 1.30E-04 9.01E-on 4.36E-06 NO DATA NO CATA NO DATA 1 88E-06 NI 65 5.23E-07 6.86E-08 3.13E-08 NO DATA NO DATA NO DATA 1.74E-06 CU 64 NO DATA 8.335-08 3. 91 E-0 8 NO DATA 2.10E-07 NO DATA 7.10E-06 ZN 65 4.84E-06 1.54E-05 c . 9e E-0 6 NO DATA 1.03E-05 NO DATA 9.70E-06 2.96E-09
~
ZN 69 1.03E-08 1.17E-08 1. 3 7 E-0 9 NO DATA 1.28E-0! NO DATA dR 83 NO DATA NO DATA 4.02E-08 NO DATA NO DATA NO DATA 5.79E-08 BR 84 NO DATA NO DATA 5. 21 E -0 8 NO DATA NO DATA NO DATA 4.09E-13
'BR 85 NO DATA NO DATA 2.14 E-0 9 NO DATA NO DATA NO DATA LT E-24 R8 86 NO DATA 2.115-05 9. 8 3 E-0 6 NO DATA NO DATA NO DATA 4.16E-06 28 88 NO DATA 6.055-08 3.21E-0E NO D A' . NO DATA NO DATA 8.36E-19 RB 89 NO DATA 4.01E-08 2. 82 E-0 8 NO DATA NO DATA NO DATA 2.33E-21 SR 89 3.08E-04 NO DATA 8. 84 E-0 6 NO DATA NO DATA NO DATA - 4.94E-05 SR 90 7.58E-03 NO DATA 1. 86 E-0 3 NO DATA NO DATA NO DATA 2.19E-04 SR 91 5.67E C6 NO DATA 2.29E-07 NO DATA NG DATA NO DATA 2 70E-05 SR 92 2.15E-06 NO DATA 9.30E-08 NO DATA NG DATA NO DATA 4.26E-05 Y 90 9.62E-09 NO DATA 2 58E-10 NO DATA NG DATA NO DATA 1 02E-04 Y 91M 9.09E-11 NO DATA 3.52E-12 NO DATA NO DATA NO DATA 2.67E-10 Y 91 1. 41 E-0.7 NO DATA 3.77E-09 NO DATA NO DATA NO DATA 7.76E-05 Y 92 8.45E-10 NO DATA 2.47E-11 NO CATA NO DATA NO DATA 1.48E
Reference:
Regulatory Guide. 1.109. Table E-ll DAVIS-BESSE, UNIT 1. B-2
TABLE 2, continued Page 2 of 3 INGESTION DOSE F ACT005 FCM AcutTS (MREM PE4 #CI INGESTEDI NUCL10E SONE LIVER T.500Y THYR 010 <!ONEY LUNG GI-LLI
- ==-
Y 93 2.68E-09 NO DATA 7.40E-11 NO DATA NO DATA NO DATA 8.50E-05 ZR 95 3.04E-08 9.75E-09 6.60E-09 NO DATA 1.53E-08 NO DATA 3.09E-05 ZR 97 1.68E-09 3.392-10 1 55E-10 NO DATA 5.12E-10 NO DATA 1.05E-04 NS 95 6.22E-09 3.64E-09 1. 86 E-0 9 NO DATA 3.42E-C9 NO DATA 2.10E-05 MO 99 NO DATA 4.31E-06 8. 20 E-0 7 40 DATA 9.76E-06 NO DATA 9.99E-06 TC 99M 2.47E-10 6.98E-10 8. 89 E-0 9 NO DATA 1.06E-08 3.42E-10 4.13E-07 TC101 2.54E-10 3.66E-10 3. 59 E-0 9 NO DATA 6.59E-09 1.87E-10 1.10E-21 RU103 1 8 5 E-07 NO DATA 7. 9 7E-0 8 NO DATA 7.06E-07 NO DATA 2.16E-05 RU105 1.54E-08 NU OATA 6. 0 S E-09 NO DATA 1 99E-07 NO DATA 9.42E-06 tul06 2.75E-06 NO DATA 3. 48 E-0 7 NO 04TA 5.31E-06 NO DATA 1.78E-06 AG110M 1.40E-07 1 68E-07 8. 79 E-0 8 NO DATA 2.91E-07 NO DATA 6.04E-05 TE125M 2.6SE-06 9.71E-07 3. 59 E-0 7 8.06E-07 1.09E-05 NO DATA 1.07E-05 TE127m 6.77E-06 2.42E-06 8. 25 E-0 7 1.73E-06 2.75E-05 NO DATA 2.27E-05 TE127 1.10E-07 3.95E-08 2. 38 E-0 8 8.15E-08 6.48E-07 NO DATA 8.68E-06 TE129" 1.15E-05 4.29E-0o 1. 82 E-0 6 3.95E-06 6.80E-05 NC CATA 5.79E-05 rE129 3.14E-08 1.18E-08 7. 6 s E-0 9 2.41E-08 1.32E-07 NO DATA 2.37E-08 TE131M 1.73E-06 8.46E-07 7. 0 5 E-0 7 1.34E-06 8.57E-06 NO DATA 8.40E-05 TE131 1.97E-08 8.23E-09 6.22 E-0 9 - 1.62E-08 3.63E-08 NO DATA 2.79E-09 TE132 2.52E-06 1 63E-06 1. 53 E-0 6 1.80E-06 1.57E-05 NO DATA 7.71E-05 1.130 7.56E-37 2.23E-06 8. 80 E-0 7 1 89E-04 3.482-06 NO DATA 1.92E-06 1 131 4 16E-06 5.95E-06 3. 41 E-0 6 1.15E-03 1.02E-05 NO DATA 1.57E-06
-! 132 2.03E-37 5.43E-07 1.90E-0 7 1.90E-05 8.65E-07. NO DATA 1.02E-07 1 133 1 42E-06 2.47E-06 7. 53 E-0 7 3 63E-04 4.31E-06 NO DATA 2.22E-06
!~134 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 NO DATA 2.51E-10 I 135 4.43E-07 1.16E-06 4. 2 S E-0 7 7.65E-05 1.86E-06 NO DATA 1.31E-06 C5134 6.22E-05 1.68E-04 1. 21 E -0 4 NO DATA 4.79E-05 1.59E-05 2.59E-06 C5136 6.51E-06 2.575-05 1. 85 E-0 5 NO DATA 1.43E-05 1.96E-06 2.925-06 CS137 7.97E-05 1.09E-04 7.14 E-0 5 NO DATA 3.70E-05 1.23E-05 2 11E-06 C5138 5.52E-08 1.09E-07 5. 60 E-0 8 NO DATA 8.01E-08 7.91E-09 4.65E-13 SA139 9.70E-08 6.91E-11 2. 84 E-0 9 NO DATA 6.46E-11 3.92E-11 1.72E-07 DAVIS-BESSE. UNIT 1 B-3
TABLE .2, Continued Page 3 of 3
' 1NOESTf0N 005E FACTORS FCR ADULTS tmREM PCR PCI INGESTEDI T.800Y THYRO 10 %IONEY LUNG G1-LL1 NUCLILE SONE LIVER 2.55E-08 1 3 3 E-0 6 -40 OATA 8.676-09 1.46E-08 4.18E-05 3A140 2.03E-05 3.312-11 2.02E-11 2.22E-17 04141 4. T I E-08 1.56E-11 1.545-09 NO CATA 1.00E-26 1.S5E-11 1.24E-11 8,A142 2.13E-08 2 195-11 1 34h-0 9 NO DATA NC CATA NO DATA 9.25E-05 LA160 2.300-09 1.262-09 3.33E-10 NO DATA NO DATA 4.255-07 5 82E-11 1 45E-11 NO DATA NC DATA LA142 1.28E-10 2 94E-09 NO DATA 2.42E-05 OE141 9.36E-09 6 33E-09 T.14E-10 NO DATA 1.35E-10 NO DATA 5.37E-10 NO DATA 4.56E-05 OE143 1.65E-09 1.225-06 1.65E-04 4.A8E-07 2.345-07 2 62E-0 8 NO DATA 1.21E-07 NO DATA CE144 2.13E-09 NO DATA 4.03E-05 DR143 9.20E-09 3.693-09 4 56E-10 NO DATA 7.05E-12 NO DATA 4.33E-18
-PR144 3.015-11 1.2SE-11 1.5sE-12 NO DATA 3.49E-05 6.29E-09 7.275-09 4. 3 5 E-10 90 DATA 4.25E-09 NO DATA N0147 3 01E-0 8 NO DATA NO DATA NO CATA 2.82E-05 w 197 1.032-07 8.61E-08 6.455-11 NO DATA 3.65E-10 NO DATA 2.40E-05 T4P239 1.19E-09 1.17C-10 t
1 DAVIS-BESSE, Unit 1 B-4 i
. . . - .. l
)
TABLE 3 SITE-RELATED INGESTION DOSE COMMITMENT FACTOR A
iT (mrem /hr per 11Ci/ml)
Page 1 of 2 HUCLIDE BONE LI'JER YPODY THYROID KIDHEY LUNG OT-LLI H-3 0.00E-01 1.76E+00 1.74E+00 1.76E+00 1.74E+00 1.74E+00 1.76E+00 C-14 3.13E+04 6.26E+03 4.26E+03 6 26E+03 4.26E+03 6.26E+03 4 26E+03 NA-24 4.32E+02 4.32E+02 4.32E+02 4.32E+02 4.32E+02 4.32E+02 4.32E+02 CR-51 0.00E-01 0.00E-01 1.*1E+00
. 7.85E-01 2.89E-01 1.7?E+00 3.30E+02 MN-54 0.00E-01 4.44E+03 8.48E+02 0.00E-01 1.32E+03 0.00E-01 1.36E+04 MN-56 0.00E-01 1.12E+02 1.98E+01 0.00E-01 1.42E+02 0.00E-01 3.57E+03 FE-55 6.98E+02 4.83E+02 1.13E+02 0.00E-01 0.00E-01 2.49E+02 2.7?E+02 FE-59 1.10E+03 2.59E+03 9 93E+02 0.00E-01 0.00E-01 7.24E+02 9.64E+03 CO-58 0.00E-01 1.00E+02 2 24E+02 0.00E-01 0.00E-01 0.00F-01 2.03E+03 CD-60 0.00E-01 2.87E+02 6 34E+02 0.00E-01 0.00E-01 0.00E-01 5.40E+03 NI-59 2.48E+03 9 51E+02 4.14E+02 0.00E-01 0.00E-01 0.00E-01 1.75E+02 NI-63 3.30E+04 2.29E+03 1.11E+03 0.00E-01 0.00E-01 0.00E-01 4.78E+02 NI-65 1.34E+02 1.74E+01 7.95E+00 0.00E-01 0.00E-01 0.00E-01 4.42E+02 CU-64 0.00E-01 1.12E+01 5.25E+00 0.00E-01 2.82E+01 0.00E-01 9.54E+02 ZN-65 2.32E+04 7.40E+04 3.34E+04 0.00E-01 4.95E+04 0.00E-01 4.66E+04 BR-84 0.00E-01 0.00E-01 5.31E+01 0.00E-01 0.00E-01 0.00E-01 4.17E-04 RB-88 0.00E-01 2.91E+02 1.54E+02 0.00E-01 0.00E-01 0.00E-01 4.01E-09 RB-89 0.00E-01 1.93E+02 1.35E+02 0.00E-01 0.00E-01 0.00E-01 1.12E-11 SR-89 2.66E+04 0.00E-01 7 44E+02 0.00E-01 0.00E-01 0.00E-01 4.27E+03 SR-90 6.55E+05 0.00E-01 1 61E+05 0.00E,-01 0.00E-01 0.00E-01 1.89E+04 SR-91 4.90E+02 0.00E-01 1.98E+01 0.00E-01 0.00E-01 0.00E-01 2.33E+03 SR-92 1.86E+02. 0.00E-01 8.04E+00 0.00E-01 0.00E-01 0.00E-01 3.68E+03 Y-90 7.16E-01 0.00E-01 1.92E-02 0.00E-01 0.00E-01 0.00E-01 7.59E+03 Y91M 6.77E-03 0.00E-01 2.62E-04 0.00E-01 0.00E-01 0.00E-01 1.99E-02 Y-91 1.05E+01 0.00E-01 2.81E-01 0.00E-01 0.00E-01 0.00E-01 5.78E+03 Y-92 6.29E-02 0.00E-01 1.84E-03 0.00E-01 0.00E-01 0.00E-01 1.10E+03 2R-95 6.84E-01 2.19E-01 1.49E-01 0.00E-01 3.44E-01 0.00E-01 6.95E+02 2R-97 3.78E-02 7.63E-03 3.49E-03 0.00E-01 1.15E-02 0.00E-01 2.36E+03 NB-95 4.47E+02 2.49E+02 1.34E+02 0.00E-01 2.46E+02 0 00E-01 1.51E+06 NB-97 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 2.87E+03 Calculations made according to the methods specified in Section 1.2 of the Offsite Dose Calculation Manual B-5
TABLE 3 (continued)
SITE-RELATED INGESTION DOSE COMMITMENT FACTOR A
it (mrem /hr per taci/ml)
Page 2 of 2 LIVER TBODY THYROID KIDHEY LUNG - GI-LLI tfUCLIDE BONE MO-99 0.00E-01 1.66E+02 3.16E+01 0.00E-01 3.77E+02 0.00E-01 3.85E+02 TC99M 1.25E-02 3 53E-02 4.49E-01 0.00E-01 5.35E-01 1.73E-02 2 09E+01 RU-103 7 13E+00 0.00E-01 3 07E+00 0.00E-01 2.72E+01 0.00E-01 8.32E+02 RU-106 1.06E+02 0.00E-01 1 34E+01 0.00E-01 2 05E+02 0.00E-01 6.86E+03 AG110M 3 22E+00 2 98E+00 1.77E+00 0.00E-01 5.85E+00 0.00E-01 1.21E+03 CD115H 0.00E-01 9.08E+02 2.47E+01 0.00E-01 7.20E+02 0.00E-01 3.82E+04 SB-124 4.78E+01 S.50E-01 1.89E+01 0.00E-01 0.00E-01 3.70E+01 1.35E+03 TE-132 2.45E+03. 1.5BE+03 1.49E+03 1.75E+03 1 53E+04 0.00E-01 7.50E+04 I-131 2.10E+02 3.01E+02 1.72E+02 9.85E+04 5.15E+02 0.00E-01 7.93E+01 1-132- 1.03E+01 2.74E+01 9.60E+00 9.60E+02 4.37E+01 0.00F-01 5.15E+00 I-133 7.17E+01 1.25E+02 3.80E+01 1.83E+04 2.18E+02 0.00E-01 1.12E+02 T-134 5.35E+00 1.45E+01 5.20E+00 2.52E+02 2.31E+01 0.00E-01 1.27E-02 I-135 2.24E+01 5.86E+01 2.16E+01 3.86E+03 9.39E+01 0.00E-01 6 62E+01 C5-134 2.99E+05 7.11E+05 5.81E+05 0.00E-01 2.30E+05 7.64E+04 1.24E+04 CS-136 3.13E+04 1 23E+05 8.88E+04 0.00E-01 6.87E+04 9.41E+03 1.40E+04 CS-137 -3.83E+05 5.23E+05 3.43E+05 0.00E-01 1.79E+05 5.91E+04 1.01E+04 CS-138 2.65E+02 5 23E+02 2.59E+02 0.00E-01 3.85E+02 3.80E+01 2.23E-03 CS-139 1.44E+02 2.40E+02 4.80E+01 0.00E-01 1.92E+02 0.00E-01 0.00E-01 BA-139- 2.35E+00 1.47E-03 6.87E-02 0 00E-01 1.56E-03 9.48E-04 4.16E+00 BA-140 4.91E+02 6.16E-01 3.22E+01 0.00E-01 2.10E-01 3 53E-01 1.01E+03 1.86E-01 9.38E-02 2 48E-02 0 00E-01 0.00E-01 0.00E-01 6.89E+03 LA-140 1.59E-01 1 22E-02 0.00,E-01 5.00E-02 0.00E-01 4.11E+02 CE-141- 1.08E-01_
CE-143 2.80E-02 2 07E+01 2.29E-03 0.00E-01 9 13E-03 0.00E-01 7.75E+02
-8.29E+00 3.47E+00 4.45E-01 0.00E-01 2 06E+00 0.00E-01 2.80E+03 CE-144 PR-144 2.24E-03 9.31E-04 1 14E-04 0.00E-01 5.25E-04 0.00E-01 3.22E-10 W-187 2.97E+02 2.49E+02 8.69E+01 0.00E-01 0.00E-01 0 00E-01 8.14E+04 1.55E+04 0.00E-01 9.42E+02 0 00E-01 3.63E+03 0.00E-01 1.51E+03 U-235 U-238 1.49E+04 0.00E-01 9.82E+02 0.00E-01 3.39E+03 0.00E-01 3.22E+03 4.59E-02 4.51E-03 2.49E-03 0.00E-01 1.41E-02 0.00E-01 9.25E+02 NP-239' P-32 1.39E+06 8.44E+04 5.37E+04 0.00E-01 0.00E-01 0 00E-01 1.56E+05 B-6
TABLE 4 DOSE FACTORS FOR EXPOSURE TO A SEMI-INFINITE CLOUD OF NOBLE GASES Nuclide y-Body **(K) 8-Skin **(L) y-Air *(M) 8-air *(N)
.Kr-85m. 1.17E+03*** 1.46E+03 1.23E+03 1.97E+03 Kr-85 1.61E+01 1.34E+03 1.72E+01 1.95E+03 Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03 Kr-89 1.66E+04 1.01E+04 1.73E+04 1.06E+04 Kr-90 1.56E+04 7.29E+03 1.63E+04 7.83E+03 Xe-131m 9.15E+01 4.76E+02 1.56E+02 1.11E+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 L-
Reference:
Regulatory Guide 1.109 Table B-1 and Section 2.1.1 of the Offsite Dose Calculation Manual
'~
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U: Page 2 of 12 a
~
PATHWAY DOSE PARANETER FACTORS lFDR IMPLEMENTING 10 CFR PART 20-
..M
=
. AGE 1-ADULT g PATHWAY 1 IHilALATION N Ho" ISOTOPE' W. DODY THYROID BONE LIVER. ' KIDNEY LUNG GI-LLI SKIN CRITICAL
, 36 ND-95 4.200Ef03 0.000E-01.1.408Et04 7.816Ef03 7.736Ef03 5.040Ef05 1.040Ef05 4.208Et03 LUNG 37 ND+97 2.040E-02 0.000E-01 2.224E-01'5.624E-02'6.544E-02 2.400Ef03 2.416Ef02 0.000E-01 LUNG'
- 38 HO-99 2.296EIO1 0.OOOE-01 0.000E-01 1.200E+02 2.912E102 V.120E104 2.480E105 0.000E-01 GI-LLI- t 39 TC-99H -3.704E-02 0.000E-01 1.032E-03 2.912E-03 4.416E-02 7.640Et02 4.160E603 0.000E-01 GI-LLI 40 TC-101 5.904E-04 0.000E-01 4.176E-05 6.016C-05 1.000E-03 3.992Et02 1.0SOE-11 0.000E LUNG 41-RU-103 -4.534El02 0.000E-01-1.528Et03.0.000E-01 5.032E603 5.040E105 1.104E605 0.000E-01 LUNG i.
i 42 RU-105 3.112C-01 0.0005-01 7.904E-01 0.000E-01 1.016Ef00 1.096Et04 4.816Et04 0.000E-01 GI-LLI 43 RU-106 U.720E103 0.000E-01 6.912Ef04 0.000E-01 1.336Ef05 9.360E106 9.120El05 0.000E-01 .Lut4G
. 44 AG-110H 5.944Et03 0.000E-01 1.080Et04 1.000Ef04'1.960EiO4 4.632Ef06 3.024E405 0.000E-01 LUNG t' 45 ED-115H 6.360EiO3 0.000E-01 0.000E-01 1.968EiO5 1.504EiOS 1.400CIO6 3.840E105 0.000E-01 LUNG g 46 SD-124 '1.240E104 7.552EiO1'3.120E104 5.038Elo2 0.000E-01 2.400Ct06 4.064Ef05 0.000E-01 LUNG
- e 47 TE-125H 4.672Et03 1.040Et03 3.416Et03 1.504Et03 1.240EiO4 3.136E105 7.044EIO4 0.OOOE-01 LutlG ~ 8' 43 4, 48 1L-127H 1.56GEt03 3.200E403 1.264C+04 5.76SEiO3 4.576Et04 9.600E105 1.496Et05 0.000E-01 LONG '
49 TE-127 '3.096E-01 1.056E100 1.400Ef00 6.424E-01 5.096EtOO 6.512EiO3 5.734Ef04 0.000E-01l GI-LLI 50 TE-129H -1.504E103 3.440E103 9.760Ef03 4.672El03 3.656El04 1.160EiO6 3.832EIO5 0.000E-01 LUNG' 8-51 TE-129 1.240E-02 3.096E-02 4.976E-02 2.392E-02 1.072E-01 1.936Ef03 1.560Ct02 0.000E-01 LUNG 52 TE-131H 2.904Ef01 5.504E401 6.992Et01 4.360E101 3.088Et02 1 456Et05 5.560E105 0.000E-01 GI-LLI 53 TE-131 3.592E-03 9.360E-03 1.112E-02 5.952E-03 4.368E-02 1.392EiO3 1.040Ef01 0.000E-01 . LUNG 8 i- 54 TE-132 1.416El02 1.096Ef02 2.600Ef02 2.152E102 1.456Et03 2.800EiO5 5.096El05 0.000E-01 GI-LLI 55.I-130 .5.200EiO3 1.136Et06 4.576Et03 1.344Ef04 2.0aSEiO4 0.000E-01 7.600E103 0.000E-01 TilYROID -9
! 56 I-131 2.040Et04 1.192E107 2.520EiO4 3.576El04 6.120EiO4 0.000E-01 6.200EiO3 0.000E-01 TliYRDID 6 57 I-132 1.160EIO3 1.144EIOS 1.160El-03 3.256E103 5.184EiO3 0.000E-01 4.064EiO2 0.000E-01 TilVROID 58.I-133 4.520E103 2.152Ef06 8.640Et03 1.400Et04 2.584EiO4 0.000E-01 8.800E103 0.000E-01 TilYRDID j 59 I-134 6.152Et02 2.984Et04 6.440Et02 1.720Et03 2.752El03 0.000E-01 1.000Et00'O.000E-01 1HYROID t i
60 I-135 2.56DE103 4.400Ef05 2.600Et03 6.904E103 1.112E404 0.000E-01 5.248EiO3 0.000E TilYROID I
61 CS-134 7.200El05 0.000E-01 3.720Ef05 0.400E105 2.872E105 9.760El04 1.040Ef04 0.000E-01 LIVER 62 CS-134 1.104E105 0.000E-01 3.904E104 1.464El05 0.560Et04 1.200E104 1.169El04. 0.000E-01 LIVER
- 1 63 CS-137 -4.200El05 0.000E-01 4.784EiO5 6 200Ef05 2.224El05 7.520Et04 8.400EIO3 0.000E-01 LIVER 64 CS-138 3.240E102 0.0'00E-01 3.312E102 6.200Et02 4.800El02 4.856E101 1.064E-03 0.000E-01 LIVER 65 CS-139 1.112E102 0.000E-01 2.040E102 2 904E602 2.440Et02 2.272El01 0.000E-01 0.000E-01 LIVER
, 66 BA-139 2.736E-02 0.000E-01 9.360E-01 6.656E-04 6.224E-04 3.760Et03 8.940Ef02 0.000E-01 LutlG i 67 BA-140 2.568E103 0.000E-01 3.904E404 4.904Et01 1.672Et01 1.272El06 2.104El05 0.000E-01 LONG 60 BA-141 3.360E-03 0.000E-01 1.000E-01 7.520E-05 7.000E-05'1.936Et03 1.160E-07 0.000E-01 LUNG t i 69.BA-142 1.656E-03 0.000E-01 2.432E-02 2.704E-05 2.288E-05 1.172El03.1.566E-16 0.000E-01 LUNG 70 LA-140 4.504Et01 0.000E-01 3.440Ef02 1.736Et02'O.000E-01 1.360EiO5 4.584Etob 0.000E-01 GI-LLI 1
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TABLE 5 (CONT)
' fi - Page 3 of 12 Y
~
$ PATHWAY DOSE PARANETER FACTORS FORMI'PLEMENTING 10 CFR PART 20 s
M AGE I ADULT
'PATilWAY 8 INHALATION
$ NO ISOTOPE W. BODY 'THYRDID BONE LIVER KIDNEY LUNG GI-LLI SKIN CRITICAL 71 LA-142 .7.720E-02 0.000E-01 6.832E-01 3.104E-01'O.000E-01 6.328Et03 2.112EiO3 7.720E-02 Lut.'G 72 CE-141 1.520E103 0.000E-01 1.992Ef04 1.352C+04 6.264E103 3.616Ef05 1.200E105 0.000E-01 LUNG 73 CE-143 1.52EEf01 0.000E-01 1.864E102 1.376EiO2 6.000E101 7.976E+04 2.264EtO5 0.000E-01 01-LLI 74 CE-144 1.040E605 0.000E-01 3.432Ef06 1.432E+06 0.480Ef05 7.776E+06 8.160Ef05 0.000E-01 LUNG 75 PR-143- 4.610Et02 0.000E-01 9.360E103 3.752F403 2.160Et03 2.008E105 2.000Et05 0.000E-01 LUMG 76 PR-144 1.520E-03 0.000E-01 3.000E-02 1.240E-02 7.040E-03 1.014E103 2.152E-00 0.000E-01 LullG 77 ND-147 3.640EiO2 0.000E-01 5 272Ef03 6.096Ef03 3.560Et03 2.200Et05 1.720E105 0.000E-01 LUNG 70 W-105 5. 410E 101 0.000E- 01 1.560EiO3 5.176Ef02 0.000E-01 4.456El05 8.560EiO4 0.000E-01 LUNG 79 W-107 2.400E100 0.000E-01 8.400E100 7.000Et00 0.000E-01 2.904Ef04 1.552E605 0.000E-01 GI-LLI 110 U-235 4.056E106 0.000E-01 0.000ElO7 0.000E-01 1.072E107 3.920El00 3.072Ef05 0.000E-01 LUNG f 01 U-238 4.S36Ef06 0.000E-01 7.664E107 0.000E-01 1.741Ei07 3.664Ef00 0.240Et05 0.000E-01 LUNG g 02 NP-239 1.240Et01 0.000E-01 2.296E102 2.25eEf01 7.000Et01 3.740EiO4 1.192E105 0.000E-01 GI-LLI 4
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~
3 TABLE 5 (CONT)
_$ Page 4 of 12 m
$ PATHWAY DOSE PARAMETER FACTORS FOR IMPLENENTING 10 CFR PART 20, m
M AGE i TEEN PATHWAY 1 INHALATION b-s NO ISOTOFE W. bouY THYROID BONE LIVER
- 1 KIDNEY LUNG OI-LLI SKIN CRITICAL H 1 11 - 3 2 C-14 1.272Ef03 1.272Ef03 0.000E-01 1.272Ef03 1.272Et03 1.272Ef03 1.272Et03 1.272Ef03 W. DODY 4.872Ef03 4.872Ef03 2.600Ef04 4.072Ef03 4.072Ef03 4.072Ef03 4.072Et03 4.072Ef03
^
3 NA-24 BONE 4 P-32 1.376Et04 1.376E+04 1.376Ef04 1.376E404 1.376Et04 1.376E604 1.376Ef04 0.000E-01 W. DODY 5 SC-46 7.160Et04 0.000E-01 1.880Ef06 1.096Ef05 0.000E-01 0.000E-01 9.200E404 0.000E-01 DOHC 6 CR-51 2.400E605 0.000E-01 4.400E105 0.540Ef05 8.000E105 0.000E-01 2.504Ef05 0.000E-01 LIVER 7 MN-54 1.352Ef02 7.496Et01 0.000E-01 0.000E-01 3.072E101 2.096Ef04 3.000EiO3 0.000E-01 LUNG H MN-56 8.400E403 0.000E-01 0.000E-01 5.112El04 1.272C104 1.904EiO4 6.600E104 0.000E-01 LUNG 9 FE-SS 2.520E-01 0.000E-01 0.000E-01 1.696E+00 1.792EiOO 1.520EiO4 5.7-14El04 0.000E-01 GI-LLI 10 FE-59 5.U14Et03 0.000E-01 3.344E+04 2.384Ef04 0.OOCE-01 1.240E105 6.392E103 0.000E-01 LOHG 11 CO-58 1.432E toi O.000E-01 1.592Et04 3.696Ef04 0.OOOE-01 1.520EiC6 1.701E105 0.000E-01 LUNG f 12 CO-60 2.776Et03 0.000E-01 0.000E-01 2.072Et03 0.000E-01 1.344E106 9.520Etoi 0.000E-01 LUNG H 13 HI-59 1.904Ef01 0.000E-01 0.000E-01 1.512EiO4 0.000E-01 0.720EiO6 2.592E105 0.000E-01 LUNG 14 NI-63 5.416Et03 0.000E-01 3.240E104 1.1400104 0.000E-01 6.560EiO4 4.00 LEIO 3 0.000E-01 LUNG 15 HI-65 1.976El04 0.000E-01 5.800Ef05 4.344Ef04 0.000E-01 3.072Ef05 1.4?6ElO4 0.000E-01 LONE 16 CU-64 1.272E-01 0.000E-01 2.104E100 2.920E-01 0.000E-01 9.360Ef03 3.672E404 0.000E-01 GI-LLI 17 Zil-65 0.400E-01 0.000E-01 0.000E-01 2.032Et00 6.400Ef00 1.112Ef04 6.141Et04 0.000E-01 GI-LLI 10 ZH-69 6.240Ef04 0.000E-01 3.056Et04 1.336Ef05 8.640E104 1.240Ef06 4.661Et04 0.000E-01 LUNG 19 LR-83 6.456E-03 0.000E-01 4.832E-02 9.200E-02 6.024E-02 1.504E+03 2.010Et02 0.000E-01 LUNG 20 BR-04 3.440Et02 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 W. DODY 21 BR-05 4.320Et02 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 W. D0DY 22 RD-06 1.032Et01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 W. D0DY 23 RD-00 0.400Et04 0.000E-01 0.000E-01 1.904Et05 0.000E-01 0.000E-01 1.760Et04 0.000E-01 LIVER 24 RB-09 2.720Et02 0.000E-01 0.000E-01 5.456C102 0.000E-01 0.OOOE-01 2.920E-05 0.000E-01 LIVER 25 SR-09 2.320E402 0.000E-01 0.000E-01 3.520Elo2 0.000E-01 0.000E-01 3.374E-07 0.000E-01 LIVER 26 SR-90 1.240Et04 0.000E-01 6.600E106 0.000E-01 4.344Et05 0.000E-01 0.000E-01 2.416Ef06 3.712Ef05 0.000E-01 LUNG 27 SR-91 1.000Ef00 0.000E-01 0.000E-01 1.640Ef07 7.640El05 0.000E-01 DONE 20 GR-92 3.512Et00 0.000E-01 8.000E101 0.000E-01 0.000E-01 6.072Ef04 2.592EiOS 0.000E-01 GI-LLI 29 Y-90 4.044E-01 0.000E-01 9.520Ef00 0.000E-01 0.000E-01 2.741E104 1.190Ef05 0.000E-01 0.000E101 GI-LLI 30 Y-91H 0.000E-01 2.904Et03 0.000E-01 0.000E-01 2.920EtOS 5.592E105 0.000E-01 GI-LLI 31 Y-91 1.416E-02 0.000E-01 3.704E-01 0.000E-01 0.000E-01 3.200Et03 3.016E101 0.000E-01 LUHG 32 Y-92 1.76 del 040.000E-01 4.200E-01 0.000E-01 4.603El05 0.000E-01 0.000E-01 2.936Et06 4.000E105 0.000E-01 LUNG 33 Y-93 1.472El01 0.000E-01 0.000E-01 2.600Et04 1.640E105 0.000E-01 GI-LLI 34 ZR-95 3.720Et00 0.000E-01 1.352El02 0.000E-01 0.000E-01 H.320Ef01 5.7Y2El05 0.000E-01 GI-LLI 35 ZR-97 3.152E604 0.000E-01 1.456E605 4.501Ef04 6.734EIO4 2.6DSEf06 1.400E105 0.000E-01 LUHG 1.256E101 0.000E-01 1.376Et02 2.720E101 4.120EiO1 1.296Ef05 6.304El05 0.000E-01 GI-LLI v
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) E E EEEEEEEEEEEEEEEEEECLE0EECEEEEEEEEEE T L N 04200204440060262622002402404000060 N P D 04162300000030959755029605012400430 O h I 051754195500521631 9747564710640201 0 C 2
( 1 I K .
16451711210067524412063313136202930 R
f O 42235111452331321324434336552241452 S o F 00000000000O00000000000000O00000000 t - t - - - - - 6 t ti 1 1 - t - t tt l l1 ttit 1l - t - - f 5 S R EEEEEEEEEEEEEEEEEEEEEEEECECEEEEEEEE R E 240400002000004400422600006001 0161 0 E e OT V 320600001604620702091 74242306040506 L g I 06604000390211530397930341945947073 B C L .
A a A 15138000115289636021442291100296132 T P F 41135304414340421223434235452204122 R 00000000O0O000000000000000000000000 E t - - - - l ftI - it tf t ftfl ltl 1t t 1t 6 1 - - f T EEEEEEEEEEEECEEEEEEEEEEEEEEEEEEEEEE E E 640404004 00000260600426064246062462 N N 52002024002000994704491092505437299 A O 02039110301000300562552060176034467 R D . .
A 12015219103412179136311035564215134 P
111111111 113303212267S64511 1111111 1 E D 00000000000000O000000O0000000000000 S I - - - - - - - - - - ft t fi - t - 6 1t t 11 t - - - - - - - - - -
O O EEEEEEEEEEEEEEEEEEEEEEECEEEEEEEEEEE D R 00000000002046640060420200000000000 Y 00000000005001784450412500000000000 Y t i 00000000005434512214459920000000000 A T .
W 00000000007141457121112340000000000 H
T 32124214334231321323433235552223331 A Y 00000O000000O0000000000000000000000 P N D 1 t - - i - 1t 6 6 1 i - t - l - t f1 l 1t 1 tt 1 1 l - t - - f O O EEEEEEEEEELLEEEEEEEECEEEEEEEEEEEEEE I D 4042006020024600i028064000024260426 T 44294634V6470144249617200061 6192175 A
L W 6 0 2 9 2 9 3 2. V. 3 2 6 1 42700116524443141 05722 A
l 52340041761424214527216035134133426 i
N I
N E HH HH H H E1 P H135605457799112 4670990120 E O 579900001 122222233301 23453333334444 TY T 999911111 111 111111133333311 111 11111 A O - - - - - - - - - - - - - - - - - - - 11 111 1 - - - - - - - - - -
IW S DDOCCUUU0DDEEEEEEEE- - - - - - SSSSSAAAAA l
i I NNNTTRRRACSTTTTITTTIIIII ICCCCCBBLDL ET GA O 670901 23456709012345670901234567090 AP N 33334444444444555555555566666646667 s
$ M v$ $ mM* h HH H ,:[
O TABLE 5 (CONT)
~
r Page 6 of 12 Y
'N PATHWAY DOSE PARAHETER FACTORS FOR INPLEMENTIllG 10 CFR PART 20 12 tg AGE ! TEEN
@ PATHWAY I INHALATION
!!0 ISOTOPE W. DODY Tif fROID DONE LIVER KIDNEY LUNG GI-LLI SKIN CRITICAL 71 1A-142 1.056E-01 0.000E-01 9.600E-01 4.240E-01 0.000E-01 1.016Ef04 1.200E104 1.056E-01 GI-LLI 72 CE-141 2.16CE103 0.000E-01 2.040Et04 1.096E+04 0.000Et03 6.136Et05 1.264ElO5 0.000E-01 LUNG t 73 CE-143 2.160Et01 0.000E-01 2.656Ef02 1.936E102 0.640Et01 1.304El05 2.552E105 0.000E-01 GI-LLI 74 CE-144 2.624El05 0.000E-01 4.000EiO6 2.024E106 1.200E106 1.336Ef07 0.640Ef05 0.000E-01 LUNG 75'PR-143 6.624E102 0.000E-01 1.336Et04 5.312E103 3.000EIO3 4.032Et05 2.136El05 0.000E-01 LUNG (
76 PR-144 2.176E-03 0.000E-01 4.296E-02 1.760E-02 1.000E'02 1.752E103 2.352E-04 0.000E-01 LUNG 77 HD-147 5.120Ef02 0.000E-01 7.064Et03 0.560E103 5.024Et03 3.720ElOS 1.024E105 0.000E-01 LUNG 70 W-105 5.440Et01 0.000E-01 1.560E603 5.174E402 0.000E-01 4.456Ef05 0.560Et04 0.000E-01 LUHG '
(
79 W-187 3.432EiOO 0.000E-01 1.200E101 9.740E100 0.000E-01 4.736Ef04 1.740Et05 0.000E-01 GI-LLI UO U-235 4.054E106 0.000E-01 0.000Et07 0.000E-01 1.072E107 3.920Ef00 3.072Et05 0.000E-01 LUNG Y 01 U-230 4.536Ef06 0.000E-01 7.664Et07 0.000E-01 1.744Ei07 3.664Ef00 0.210E105 0.000E-01 LUNG
[* 02 NP-239 1.76DEt01 0.000E-01 3.304Et02 3.192E101 1.000E602 6.408Ef04 1.320E405 0.000E-01 UI-LLI k
(
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t s
L Y Y YYY A D D I II IDDD III II I C O O R L LL ORNR LLL LL L I
T BEDEEGGLGGGGGELLGLDIL00.DEEEGELLLGG1LGL N NVNH- HHHHNH- - H- VVVHN- - - HH - - N-I .O .OIUUIUUUUUDIIUI . . . IIIUOIIIUUIIUI R WDWDLLLGLLLLLDGGLGWWWLLLLDGGGLLGGLG E
3311111111111 11111111111111 111 11111 00000000000000000000000000000000000 f1 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
EEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEE N 54000000000000000000000000000000000 I 23000000000000000000000000000000000 K 17000000000000000000000000000000000 S
16000000000000000000000000000000000 3344531534443344441113105S555355S45 0 O000000000OO000000000O000O000O00O00 2 I i61 1ft t 4 4 6 ll 9 11 t t1 - - - i44l I1 fti t fI l1 L EEEEEECE0ECE0EEEEEEEEEEEEEEEEEEEEEE T L 5108540207701 7902000021124949790551 R - 231190936632629731000929733271 39001 A I 17421022004623366000097064746703015 P G 1614112127392603110007111 31 22112363 R
F 334114645666453353111 11167445364465 C O0000000O000000O000000000000000000O ift - - l t 1i 1 f1 1 14i 6l - - - - - -
- 6 1l t t6 fl1 1 i 0 EEEEEEEEEEEEEEEECEEEEEEEEECEEEEEEEE 1 G 54000064096709733100000076016270712 N 231 009711604347052000000572011 29333 G U N
I L 1760065312100715.V.400000014346063421 1610011111 1732099100000021522222721 T
N 334151 401 i111110421111111 11 11111141 E 0O00O0000O000000000000000000000000O M Y 1If it l t - - - - - - - 1 f - - - - - - - - - - - - - - - - li
) E E EEEEEEEEEEEEEEEECEEEEEEEEEEEEEEEEEE T L N 540001 32000000011600000000000000075 N P D 231 00307o00000034400000000000000050 N
O 2 C 1 I I
K 17607406.O.00000001000000000000000090 16103211000000067500000000000000053
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f R o O 334551404434341052111 522111111 11141 F 0000O000O000O0000000000000000000000 5 t fft i - t1it 6 l I t - t 6 - - - 1ll - - - - - - - - - l f 7 S R EEEEEEEEEEEEEEEEEEEEECEEEEEEEEEEEEE R E 54039020652425612700034200000000016 E e O V 231 450951 47102593500082500000000001 L
g T I 17619026537346991600094400000000017 a C L B
A P FA 16113041231154211900015300000000042 T 14465111441145014211111150213151252 R 000000000O00O0000000000000000000000 E - ffff - - - ti - - il l - l - - - - - - - l 6 t l f - fft t l T EEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEE E E 090590006000240057000000401 07995506 N N 001 030003600017059000000911 10633697 A O 05660000700052902600000090231010000 R B A 03122000420010204600000051114592111 P
33411111111t111111111111111111111 11 E D 00000000000O00000000000000000000000 S I tft - l - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
O D EEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEE D R 54000700000000000O00000000000000000 Y 231 00400000000000O00000000000000000 Y H 1 7600500000000000.O.00000000000000000 A T W 1 6100000000000000000000000000000000 H
T 334452313434341 04322152246012241041 A Y 00000O00O00000000000000000000000000 P N D ftl ffI t - I 1 t t 4 l - l 1 - t l4 t ll l t1 - t - l - t t 4 O O EEEEEEEEEEE0EEEEEEEEFEEEEEEEEEEEEEE I B 540913990941573307661 3371 01 : ) 63dVL00 T 231 754017666094731373469230504 30009 A . 176015517612576009745160745210401 75 L W . . .
A 16191193713222117045213216451125531 H
N DI L E I1 P H O 4 61465930935459345409901 2 H 57 CY T 42245555556566666000088099901 12399 A O 31 - - - - - - - - - - - - - - - - - - - - - - - 99999 - -
1W S - - A CRHHEE0OI IIUNNRRRDDDRRRR- - - - - RR H I 1 CNPSCNNFFECHNHCZZDDDRRiSECEYYYYYZZ 1
s ET GA O 12345470901234567f 901 231 5670?012345 t AP N 1111111 1i 12222222222333333
{ys$mn gHH t*H fH"
. s e TABLE 5 (CONT)
$ Page 8 of 12 y -
y PATilWAY DOSE PARAMETER FACTORS FOR IMPLEMENTING 10 CFR PART 20 a
I" AGE : CilILD PATilWAY 1 IHilALATION f y NO ICOTOPE W. DODY TilVROID BONE LIVER KIDNEY LUNG GI-LLI SKIN CRITICAL
" t 34 HD-95 6.549Et03 0.000E-01 2.350E104 9.176Et03 0.621El03 6.142E105 3.700E404 6.549E103 LUNG 37 NB-97 9.472C-03 0.000E-01 1.029E-01'2.601E-02 3.02/E-02 1.110E103 1.117E102 0.000E-01 LUNG 30 HO-99 4.255E101 0.OOOE-01 0.000E-01 1.724E102 3.922El02 1.354E105 1.265E105 0.000E-01' LilHG t 39 TC-99H 5.772E-02 0.000E-01'1.700E-03 3.402E-03 5.069E-02 9.509Ef02 4.010EIO3 0.000E-01 GI-LLI 40 TC-101 1.077E-03 0.000E-01 0.103E-05 0.510E-05 1.450E-03 5.046E102 1.632E101 0.000E-01 LUNG 41 RU-103 1.073Z603 0.000E-01 2.060E103 0.000E-01 7.030E103 6.623El05 4.477E404 0.000E-01 LONG 6 42 RU-105 5.550E-01 0.000E-01 1.520El00 0.000E-01 1.343E100 1.591El04 9.953El01 0.000E-01 GI-LLI 43 RU--106 1.6Y1El04 0.000E-01 1.362El05 0.000E-01 1.039E105 1.432E107 4.292E105 0.000E-01 LUNG 44 AG-110H 9.13YEl03 0.000E-01 1.607E604 1.140Et04 2.124E104 5.476EIO6 1.003E105 0.000E-01 LullG &
45 CD-115H 2.942EIO3 0.000E-01 0.000E-01 9.102EiO4 7.326EIO4 6.512E105 1.776Lt05 0.000E-01 LUNG W 46 SD-124 5.735E103 3.493E101 1.443Et04 2.723E102 0.000E-01 1.147Et06 1.0000105 0.000E-01 LUNU h
Ln 47 TE-125H 9.137Et02 1.92iE103 6.734El03 2.32PEiO3 0.000E-01 4.773E105 3.370EiO4 0.000E-01 Ll1NG t 40 TE-127tl 3.027EiO3 6.060E103 2.436E104 0.54TE103 6.364E104 1.400E106 7.141EiO4 0.000E-01 LullG -
49 TE-127 6.105E-01 1.941Ef00 2.771EtOO 9.50YE-01 7.067EiOO 1.003El04 5.621E104 0.000E-01 GI-LLI 50 TE-129H 3.041E103 6.327Et03 1.920E-104 4.045E403 5.032E404 1.761E106 1.017E105 0.000E-01 LUNG .
51 TE-129 2.303E-02 7.141E-02 9.768E-02 3.497E-02 2.560E-01 2.934Et03 2.54YE404 0.000E-01 GI-LLI 52 TE-131H 5.069El01 9.740Et01 1.343EiO2 5.920El01 3.996Elo2 2.057E105 3.070El05 0.000E-01 GI-LLI 53 TE-131 6.506E-03 1.4?CE-02 2.172E-02 0.436E-03 5.003E-02 2.054E103 1.332E103 0.000E-01 Littl0 4 51 TE-132 2.631El02 3.1?5El02 4.010El02 2.723El02 1.772E103 3.771El05 1.376C105 0.000E-01 LtJtlG 55 I-130 0.4360103 1.016E106 0.177Et03 1.639EiO4 2.4460404 0.000E-01 5.10aEIO3 0.000E-01 THYRGID 56 I-131 2.727E104 1.621E107 4.010El04 4.010El04 7.001E104 0.000E-01 2.012E103 0.000E-01 TilVROID .
57 I-132 1.076EIO3 1.935El05 2.116E103 4.070Et03 6.253EiO3 0.000E-01 3.201El63 0.000E-01 TilYROID Su I-133 7.4V6El03 3.010E606 1.650E4 04 2.031E104 3.37CEl04 0.000E-01 5.474EiO3 0.000E-01 TilYROID 59 I-134 9.953El02 5.069E104 1.173El03 2.161E103 3.300Et03 0.000E-01 9.544EIO2 0.000E-01 TilYROID .
60 I-135 4.141E103 7.910E405 4.921EIO3 0.732E103 1.339Ef04 0.000E-01 4.410ElO3 0.000E-01 TilVROID 61 CS-134 2.246Et05 0.000E-01 6.512El05 1.0110106 3.301Et05 1.210EIOS 3.040C103 0.000E-01 LIVER 42 CS--136 1.162El05 0.000E-01 6.512El04 1.709C105 9.546EiO4 1.454El04 4.181E103 0.00CE-01 LIVER .
63 CS-137 1.204El05 0.000E-01 9.065El05 0.251El05 2 023EiO5 1.040E105 3.619E103 0.000E-01 DuttC 64 CS-130 5.550El02 0.000E-01 6.327E602 0.399El02 6.216EiO2 6.000Et01 2.697E102 0.000E-01 LIVER 45 CS-139 5.113El01 0.000E-01 9.472E101 1.343Et02 1.129E102 1.051E101 0.000E-01 0.000E-01 LIVER .
66 DA-139 5.365E-02 0.000E-01 1.043E100 9.012E-04 0.621E-04 5.772El03 5.772EIO4 0.000E-01 GI-LLI 67 DA-140 4.329L103 0.000E-01 7.400E104 6.475El01 2.113El01 1.743E106 1.010E105 0.000E-01 LUNG 60 DA-141 6.344E-03 0.000E-01 1.957E-01 1.092E-04 9.472C-05 2.919C103 2.753EiO2 0.000E-01 LUNG .
69 UA-142 2.790E-03 0.000E-01 4.995E-02 3.600E-05 2.912E-05 1.643EiO3 2.742Ef00 0.000E-01 LUNG 70 LA-140 7.540El01 0.000E-01 6.430E102 2.250El02 0.000E-01 1.020Ef05 2.257Et05 0.000E-01 GI-LLI i
i e TABLE 5 (CONT)
$ Page 9 of 12 Y
=
y PATilWAY DOSE PARAHETER FACTORS FOR IMPLEHENTING 10 CFR PART 20
?'
g AGE : CHILD g PATHWAY 3 INHALATION H
g NO ISOTOFE W. D0DY TilYROID BONE LIVER KIDNEY LUNG GI-LLI' SKIN CRITICAL
/1 LA-142 72 CE-141 1.291E-01 0.000E-01 1.295E100 4.107E-01 0.000E-01 0.695Et03 7.505EIO4 1.291E-01 GI-LLI 73 CE-143 2.097Cf03 0.000E-01 3.922Et04 1.954Ef04 8.547E+03 5.439EiO5 5.661EiO4 0.000E-01 LUNG 74 CE-144 2.075El01 0.000E-01 3.659E102 1.987E102 0.362E101 1.154E105 1.273Ef05 0.000E-01 GI-LLI 75 fR-143 3.61 set 05 0.000E-01 6.771E106 2.116EiO6 1.173E106 1.195Cl07 3.035E105 0.000E-01 LUNG 76 PR-144 9.139Et02 0.000E-01 1.046Ef04 5.550EIO3 3.001Ef03 4.32?C105 9.731E104 0.000E-01 LUNG 77 HD-147 2.997E-03 0.000E-01 5.957C-02 1.846E-02 9.760E-03 1.565EiO3 1.960Cf02 0.000E-01 LONG 70 W-105 6.000ElO2 0.000E-01 1.000E104 0.732Ef03 4.010E103 3.202EiO5 0.214Ef04 0.000E-01 LilHO 08 79 U-187 2.5 0E101 0.000E-01 7.215E102 2.494El02 0.000E-01 2.061EiO5 3.959E104 0.000E-01 LtittG M 00 U-235 4.329El00 0.000E-01 1.632Ef01 9.657EiOO 0.000E-01 4.107Ef04 9.102CIO4 0.000E-01 GI-LLI cs 81 U-230 2.216Et06 0.000E-01 3.700Et07 0.000E-01 0.650E406 1.013F400 1.771Et05 0.000E-01 LUNG U2 HP-230 2.0V0El06 0.000E-01 3.545Et07 0.000E-01 0.066Et06 1.695Cf00 3.011El05 0.000E-01 LUNG 2.350E101 0.000E-01 4.662El02 3.345E101 9.731E101 5.009Et04 6.401E104 0.000E-01 GI-LLI O
L Y Y fY(
A D D I II IhDD II II I E O O R L LL L0HORRR LL LL L I DEBEEGGLGGUGGELLGL0DDEEEGELLGGGLLGL T N NVNN NNHNHN- - H- VVVNH- - NHN- - N-I .O .OIUUIUUUUUOIIUI . . . III UDIIOUUIIUI R WDWDLLLGLLLLLDGGLGWWWLLLLIGGLLLGGLG :
C 23111111111111111111111111111111111 0O000000000000000000000000000000000 fi - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
EEEEEEEEEECEEEEEEEEEEEEECEEEEEEEEEC N H6000000000000000000000000000000000 I 60000000000000000000000000000000000 K 43000000000000000000000000000000000 S
65000000000000000000000000000000000 234442343414231444111321451 55345545 0 000000O0000000000000000000000000O00 2 I ft tt t1 i 11 l tl 1 l t f6 9 - - - 1 11 1 11 1 1 t t ftft L EEEEEEECEEEEEEEECEEEEEEEEEEECEEEEEE T L 06602060503242?002000000C0600206600 R - 605127569719521 932000301 91301526670 A I 430655010411 54041300003033340302614 P G .
65114377121302515100033661711271121 R
F 23411454465645335311111167445364465 C 0000000OO000O0000000000000O00000000 ft t - - 41 ii 111 i 1 4111 - - - - - - 1tl l l t tf1 1l 0 . EEEEECEEEEEEEEEEEECEEEEEEEEEEECECEE 1 G 86600463450096060000000004400600403 N 60500095917040296700000032600055450 G U 43000292407510124400000001234744671 N L .
I 65100191017412096100000021522222711 T
N 234151301111 111 042111 111111 111111 41 E 00000000000000000000000000000000000 -
M Y ftt 61 t t - - - - - - - t 4 - - - - - - - - - - - - - - - - l 1 E E EEEEEEEEEEEEECEEEEEEEECELEEEEEEEECE -
) L N B6400310000000060000000000000000000 .
T2 P D 60500200000000074100000000000000009 N1 M I 43004391000000092000000000000000015 O I K Cf 65101141000000033400000000000000032
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o O 2345514O443334104211152211111111141 F O00000OO00000O0000000O0000000000000 5 10 *S R ittl l - i t1 + t1 + i - tl - - - - t 41 - - - - - - - - - t t EEEEEEEEEEEEEECEEEEECEEEEEECECEEEEE R E 86640020529244260400042600000000062 .
E V 60S29051751244475700007000000000006 L ge TO I 4 3. ). 1406513200000260,0095200000000075 B a C L 65111011121822216900015300000000022 A
T P A F .
144641114411350142111111571131S1252 R. 000000000O000O0000000000000000O0000 E tf1 f - - - + I - - l i4 - - - - - - 1 f1 1f - l l t l t T EEEEEEEEEEEEEEEEEEEEEEEEEEELEEEECEE E E 0660400047004340200000006520040001 0 M N 04531000750008903900000070609703959 A O 06007000930063309300000090502006414 R B A 02127000110053201500000034913451111 P
234111111111111111111111111 11111111 E D 00000000000000000000000000000000000 S I ttt - l O O CEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEE D R 06600400000000000000000000000000000 Y 60500500000000000000000000000000000 Y i l 43000700000000000000000000000000000 A T W 65100500000000000000000000000000000 H
T. 23444131333424114322142244011241041 A Y 00O0000000000000O00000O0000000000O0 P N D 1fiftf1 - t ftf6 f - - I - t 1 l f i1 1 t1 t - t - 1 I l O 0 EEEEEEEEEEEEEECEEECECEECEEEEEEEEEEE I D 0662161223070112020140001 00606061 00 T 605454013727763400001275495o2060737 A .
4307399234014127118000001 5 4 v. 0 3 5 6 0 0 1 L W . . .
A' 6517404239119117373420221233011 4421 H
TN NI A E F8 P N O 4 61i659009354593456S9901 2 M 57 IY T 42245S555565666660080O0099901 12399 A O 31 - - - - - - - - - - - - - - - - - - - - - - 99999 - -
1W S - - A CRHHEE00IIIUNHRRRBBDRRRR- - - - - RR l
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ET' GA o 123456709012345670901 23154709012345 AP N 111 111 1111 2222222222333333 Edvs s
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. TABLE 5 '(CONY)' .J
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- y. ,Page.11 of 12 ,
~
PATHWAYkDOSEfPARAMETER FACTORS FOR IMPLEMENTING'10 CFR PART 20'
$ ~/ -
'f 'I* ' AGE'l INFANT'
. PATHWAYJ1 INHALATION -
.t b'
- U; NO ISOTOPE W. DODY THYROID' IBONE. " LIVER. . KIDNEY. LUNG' GI-LLI' . SKIN. ' CRITICAL G , ,.
II 36 NB-95' [3.780Et03 0.000E-01'1.568Ef04 6.426Et03 4.710Et03 4.780E405 1.267EiO4 3.780Et03 LUNG'
. ?- 'N i37 HD 3.504E-03 0.000E-01 3 392E-02 9.842E-03,1.145E-02 4.200E102 4.228EiO1 0.000E-01 . LUNG 38 HO-99 x3.234Et01 0.000E-01 0.000E-01'1.652EiO2 2.646El02 1.340E405 4.072El04 0.000E-01 LUNG 39 TC-99M 3.724E-02 0.000E-01 1.397E-03 2.884E-03 3.100E-02 8.106Et02 2.030El03 0.000E-01 GI-LLI
- t 40 1C-101' O.120E-04 0.000E-01 6.510E-05 8.232E-05 9.706E-04 5.838EiO2 8.442E102 0.000E-01 GI-LLI i 41 RU-103 -6.790Ef02 0.OOOE-01 2.016EiO3 0.000E-01 4.24REiO3 5.516EiOS 1.610EiO4 0.000E-01 LUNG.
42 RU-105 s4.102E-01 0.000E-01'1.224Ef00 0.000E-01 8.980E-01 1.560E404 4.811El04 0.000E-01. GI-LLI 43 RU-106- 1 000Et04 0.000E-01 8.600E404 0.000E-01 1.06SEiO5 1.154E607 1.630E105 0.000E-01 LUNG y 44 AG-110M 4.998E603 0.000E-01 9.902Ef03 7.224Et03 1.092Et04,3.660EiO4 3.304Et04 0.000E-01 LUNG 45 ED-115M. 1 113E103 0.000E-01 0.000E-01 3.444EiO4 2.772Et04 2.464El05 6.720E104 0.000E-01 LUHG
'/ us 46 SD-124 2.170E-103 1.322E101 5.460E103 1.030Et02 0.000E-01 4.340E105 7.112E104 0.000E-01 LONG
/ b 47 TE-125M 6.580Et02 1.624Et03 4.760EiO3 1.900E103 0.000E-01 4.464E105 1'.291E104 0.000E-01 LUNG OD 40 TE-127M '2.072E603 4.872EiO3 1.664EiO4 6.902El03 3.752EiO4 1.312Ct06 2.730EiOi 0.000E-01 LUNG-49 TE-127 '4.006C-01 1.040E400 2.226E100 9.534E-01 4.050E100 1.035El04 2.434E104 0.000E-01 GI-LLI 50 1E-129M. 2.226E103 5.474EiO3 1.414Et04 6.090E103 3.170El04.1.600E106 6.902EiO4 0.000E-01 LUNG 1.076E-02 6.740E-02 7.882C-02 3.472E-02 1.750E-01 2.996EiO3 2.632E101 0.000E-01 GI-LLI 51 TE-129 52 TE-131M 3.624C101 0.932EiO1.1.067Et02 5.502Et01 2.646Elo2 1.90BCt05 1.19tE105 0.000E-01 LUNG 53 TE-131 4.9?DE-03 1.502E-02 1.736E-02 8.210E-03 3.990E-02 2.05 bel 03 0.210E403 0.000E-01 GI-LLI-51 1E-132 1.764EiO2 2.786Et02 3.724EiO2 2.366Et02 1.035EiO3 3.402E105 4.410El04 0.000E-01 LUNG 55 I-130 5.572EiO3 1.596E106 6.356Et03 1.387E+04-1.526E104 0.000E-01 1.90 bet 03 0.000E-01 1HYRDID 56 I-131 1.960E104~1.404Et07 3.794El04 4.438Ef04 5.180EiO4 0.000E-01 1.05DE403 0.000E-01 TilYROID 57 I-132 1.259E103 1.694E105 1.694Et03 3.542Et03 3.940El03 0.000E-01 1.904E103 0.000E-01 TilYROID SS I-133 5.600Ef03 3.556El06 1.324EiO4 1.910E404 2.240Et04 0.000E-01 2.156EiO3 0.000E-01 TilYROIDTilYROID 59 I-134 6.650E102 4.452E404 9.212El02 1.876E103 2.004Et03 0.000E-01 1.209EiO3 0.000E-01 40.I-135 2.772E103 6.950EiO5 3.064El03 7.602Et03 0.470El03 0.000E-01 1.034EiO3 0.000E-01 TilYRUID 61 ES-134 7 440El04 0.000E-01 3.962E105 7.020E105 1.904E105 7.966Etot 1.334E103 0.000E-01' LIVLR 62 EU-134.. 5.292E604 0.000C-01 4.030E104 1.345E105 5.642E104 1.176El04 1.420El03 0 000E-01 LIVE R 43 ES-137 4.550E604 0.000E-01 5.400El05 6.110C105 1.722El05 7.126El04 1.334El03 0.000E-01 LIVER
- 64 CS-130 3.V76C602 0.000E-01 5.054El02 7.012Et02 4.102El02 6.530E101 8.761El02 0.000E-01 GI-LLI 45 EG-139 1.946El01 0.000E-01 3.584El01 5.002E101 4.270E101 3.974ElOO 0.000E-01 0.000E-01 LIVER 66 DA-139 4.290E-02 0.000E-01 1.404E100 9.042E-04 5.922E-04 5.950EiO3 5.096Et04 0.000E-01 GI-LLI 67 UA-140 '2.890E103 0.000E-01 5.600E104 5.600E101 1.343Ef01 1.596EiO6 3.036E104 0.000E-01 LUNG
- 60 DA-141 4.970E-03 0.000E-01 1.560E-01 1.070E-04 6.496E-05 2.960E103 4.746E103 0.000E-01 GI-LLI E 69 DA-142 1.960E-03 0.000E-01 3.974E-02 3.304E-05 1.904E-05 1.554E403 6.930C602 0.000E-01 LUNG 70'LA-140 s 5.152E101 0.000E-01 5.054EiO2,2.002E102 0'.000E-01 1.600E105 8.404EiO4 0.000E-01 LUNG 9 _ _
.< $ TABLE 5 -(CONT)
G Page-12 of 12 ds
- Ci PATilWAY DDSE PARAMETER FACTORS FOR IMPLEMENTING 10 CFR PART 20 E
H AGE 8 INFANT g-PATilWAY 3 INifALATION NO ISOTOPE W. DODY TilVROID BONE LIVER KIDNEY- LUNG GI-LLI SKIN CRITICAL 71 LA-142 72 CE-141 9.04 4E-02 0.000E-01 1.030Ef 00 3.766E-01 0.000E-01 8.21dEf 03~ 5.950EiO4 9.04 4E-02 GI-LLI 73 CE-143 1.900Et03 0.000E-01 2.772E104 1.666Ef04 5.250E603 5.166Ef05 2.156Et04 0.000E-01 LONG 74 CE-144 2.212Cf01 0.000E-01 2.926E402 1.932EiO2 5.642E101 1.162EiOS 4.970Ef04 0.000E-01 LUNG 75 PR-143 1.764EtOS 0.000E-01 3.192E106 1.211E406 5.376Ef05 9.042Ef06 1.401Et05 0.000E-01 LUtJG 76 PR-144 6.905Ef02 0.000E-01 1.400Et04 5.236E403 1.974Ef03 4.326Et05 3.724E104 0.000E-01 LUNG 77 HD-147 2.400E-03 0.000E-01 4.700E-02 1.840E-02 6.720E-03 1.610Et03 4.201E103 0.000E-01 GI-LLI
, 70 W-185 4.990Ef02 0.000E-01 7.939Et03 8.134E103 3.150Ef03 3.220E105 3.122E601 0.000E-01 LUr10 s 79 W-107 9.534E100 0.000E-01 2.730E102 9.05GEf01 0.000E-01 7.790Ef04 1.49uEf04 0.000E-01 LUNG
[j 80 U-235 3.122EiOO O.000E-01 1.296Ef01 9.016Et00 0.000E-01 3.942Ef04 3.556E104 0.000E-01 LUtlG 01 U-238 8.498Et05 0.000E-01 1.400Ef07 0.000E-01 3.276Ef06 6.060EtO7 6.776Ef04 0.000E-01. LONG U2 tiP-239 7.930EIOS 0.000E-01 1.341E107 0.000E-01 3.052Ef06 6.412El07 1.412EiO5 0.000E-01 LUNG 1.074Ef01 0.000E-01 3.710Ef02 3.310Ef01 4.422Ef01 5.950Ef04 2.492E104 0.000E-01 LUNG 9
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l L Y Y YY YY A D D IIII III II DD DD IIII C O 0 LLLL LLL LLRRl.I.O IIIII.LLLL
' El 0bDEDDEELLLLLLLLL ROO LLLLt I BEDCLLLLELLLCELLT f T N H- - - - N- - - HN- - '.V- V NH- - - - - - - - -
I .O .OIIIIOIIIOOIIIII . .I . .O0IIIIIII II R WBWDGGGGDGGGbDGGLLGWWLWWD0GGGGGCGGG C
241111 111111111111 111111111 1111 11 11 00000000000000000000000000000000000 ff - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
EEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEE
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L EEEEECEEEECEEEEECEEEELEEEEECEECEEEE L 9393737L1 65231023694090062024573992 R - 265299715:737321 4 v61000025602025430 A I 62496153935057207441010033355077367 P G 772117219293391221 11050021197149792 R
F 246114116711111111 1111111 11111 11111 C 00000000000000000000000000000000000 41t - - 4 6 0 EEEEEECEEEEECEEEEEEEEEEEEEEEEEEEEEE 1 G 93900500000000000000000000000000000 N 26500900050000000000000000000000000 G U 62400700690000000000000000000000000 N ) L I 77200300910000000000000000000000000 T b.
N 2 246123631111111492111 111111111 111 21 E 00O00000000000000100000000000000000 M 2 Y +4i 6t l - - - - - - - - tl - - - - - - - - - - - - - - - - t -
E E EEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEC 9 L 2 N 939060420 00000020900000000000000030 9 P D 26505004000000051700000000000000071 M I 3 I n K 6 2 4 0 2 3 5 2 0 0 0 0 0 0 0 5. V. 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 7 3 o 77203625000000052600000000000000041 6 f R i o O t 2469216377670024Y2111 91111111111122 E F c 00O00000000O00000100000000000000000 e
L B 1 . S s A e R E ftl f 1 tttI tt - - - t - - - - - - - - - - - t -
R EEEEEEEEECEEEEEEEEEEEEEEEEEEEEEEEEE 939370495041 5401 340001 000000000001 4 T g O rT V 265610123724361 66500090000000000042 a o I 42405041797676033300050000000000007 P C f L A ( 77213004164114424900020000000000030 F
156021 11771189119211111190411 035121 R 000100000O000O00o100000001O00200000 E - +4+4 - - - 1t - - 4i - - f - - - - - - - 6 tI 1 - - f -
T EEEEEEEEEEEEEEEEEEEEEEEEEEEEEELEEEE E E 02904000190099201200000000264098733 M N 035190001600520079000000507391 061 02 A O 06477000590007703000000046000455343 R B A 032110002200563014C0000014247605294 P -
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es TABLE 6 (CONT)
$ Page 2 of 39 us i
g PATifWAY DOSE PARAMETER FACTORS FOR IMPLEMENTING 10 CFR PART 50 I" AGE 1 ADULT l'ATifUAY 1 COW MILK y HD IS010PE W. DODY TitYROID DONE LIVER K1DNEY LUNG GI-LLI SKIN CRITICAL
" 36 NB-95 2.460E t 04 0.000E-01 0.253Et04 4.591Et04 4.530Et04 0.000E -01 2.706El00 0.000E-01 GI-LLI 37 ND-97 5.419E-13 0.000E-01 5.000E-12 1.401E-12 1.731E-12 0.000E-01 5.475E-09 0.000E-01 GI-LLI 33 NO-99 4.70 set 06 0.000E-01 0.000E-01 2.473Et07 5.600Ct07 0.000E-01 5.732E807 0.000E-01 GI-LLI 39 TC-99M 1.216E102 0.000E-01 3.370E100 9.545Ef00 1.450C402 4.677E100 5.640C603 0.000E-01 GI-LLI 40 TC-101 0.000C-01 0.000E-01 0.000E-01 0.00CC-01 0.000E-01 0.000E-01 0.000C-01 0.000E-01 W. D0DY 41 RU-103 4.390Ef02 0.000E-01 1.021E103 0.000E-01 3.096Et03 0.000E-01 1.192E 05 0.000C-O! GI-LLI 42 RU-105 3.425E-04 0.000E-01 8.476E-04 0.000E-01 1.121E-02 0.000E-01 5.307E-01 0.000E-01 GI-LLI 43 RO-106 2.582Et03 C.000E-01 2.040Et04 0.000E-01 3.939Et04 0.00CE-01 1.3210106 0.000E-01 GI-LLI 41 AG-110M 3.200Ef 07 0.000E-01 5.025E107 5.300Et07 1.05VE t 00 0.000E-01 2.1*/9Et 10 0.000E-01 GI-LLI 45 ED-115M 3.901LiO4 0.000E-01 0.000E-01 1.216E t 06 9.001El05 0.000E-01 5.210L107 0.000E-01 GI-LLI b3 16 SB-121 1.021Et07 6.243E104 2.501Et07 4.073Et05 0.000E-01 2.005E107 7.310Et00 0.000E-01 G1-LLI '
h 17 TE-125M 2.103CiO6 4.YO2El06 1.630El07 5.905C606 6.629Et07 0.000E-01 6.507EIO7 0.000E-01 KIIttiEY H 40 TE-127M 5.57?CIOS 1.170E607 4.5700107 1.636E107 1.040E400 0.0000-01 1.535L100 0.000E-01 NIDilEY 49 TE-127 1.142E 6 02 1.93/El02 6.663CiO2 2.393E t 02 2.714Et 03 0.000E-01 5.250L 6 04 0.000E-01 GI-LLI l 50 IE-129M 9.511E606 2.064Et07 6.009E107 2.242Et07 2.500Lt03 0.000E-01 3.026E100 0.000E-01 GI-LLI l St TC-129 8.203E-11 2.501E-10 3.3670-10 1.245E-10 1.415C-09 0.000E-01 2.5410-10 0.000E-01 KIbHEY I 52 10-131M 1.470E105 2.795E605 3.600Et05 1.761E105 1.707Et06 0.0000-01 1.752El07 0.000C-01 GI-tLI l 53 TE-131 0.000E-01 0.000E-01 0.000E-01 0.000E-01 1.913E-32 0.000E-01 0.000E-01 0.000E-01 hIbHEY l 54 IE-132 1.452Et06 1.70VE106 2.392E104 1.5t7E406 1.440E607 0.000E-01 7.31YEtO7 0.000E-01 GI-LLI l 55 I-l'0 4.900Et05 1.070Ef00 4.270Ct05 1.262Et06 1.969Et06 0.000E-01 1.006Et04 0.000C-01 1HYLUID I 56 I-131 2.42 set 00 1.309E111 2.9630600 4.237E400 7.244E600 0.000E-01 1.110E100 0.000E-01 4HfhulD l 57 I-132 1.405C-01 1.405Et01 1.501E-01 4.015E-01 6.397E-01 0.OOOE-01 7.543E-02 0.000E-01 THYROID l 50 1-133 2.056Et04 9.910El00 3.077El06 6.713E106 1.177Et07 0.000E-01 4.0610906 0.000E-01 TilYRUID l 59 I-134 1.031E-12 0.00SE-11 1.007E-12 5.120E-12 0.155E-12 0.000E-01 4.469E-15 0.G00E-01 TitYROID l 40 I-135 1.222E404 2.104El06 1.265Et04 3.312Ct01 5.311Et01 0.000E-01 3.7110101 0.000C-01 TilYROID 61 CS-131 1.100Et10 0.000E-01 5.652EIO9 1.315Et10 4.353Ct09 1.445Et09 2.351Et00 0.OOOE-01 LIVER 62 CS-134 7.425C600 0.000E-01 2.613C100 1.032Et0V 5.739Et00 7.067E107 1.172E100 0.000E-01 LIVE R I 63 CL-137 6.613El09 0.000E-01 7.301EtOV 1.00VEi!O 3.427E109 1.139Et09 1.951E100 0.000E-01 LIVLR l 64 EG-130 1.013E-23 0.000E-01 1.036E-23 2.015E-23 1.503E-23 1.404E-21 0.724E-29 0.000E-01 LIVER l 65 CC-137 0.000E-01 0.000E-01 0.000E-01 0.000C-01 0.000E-01 0.000C-Ol 0.000E-01 0.000E-01 W. BODY l 66 DA-139 1.290E-09 0.000E-01 4.434E-00 3.159E-11 2.953L-11 1.7V2E-11 7.063E-00 0.000E-01 G1-LLt 67 1:A-110 1.760E106 0.000E-01 2.606El07 3.374Et04 1.147Et01 1.932Et09 5.531EtO7 0.000E-01 GI- LLI 60 DA-1 -11 0.000C-01 0.000C-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 W. DODY 69 DA-112 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 W. BODY l 70 LA-140 6.025E-01 0.000E-01 4.523Et00 2.200E400 0.000E-01 0.OOOE-01 1.674Et05 0.000E-01 GI-LLI a
9
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! 3" AGE ! EllILD PATilWAY 1. COW MIIK
, $$ NO ISOTOPE W. BODY TitYROID BONE LIVER KIDNEY LONG GI-LLI SKIN CRITICAL H
36 ND-95 0.042E104 0.000E-01 3.170El05 1.237E105 1.162EtOS 0.000E-01 2.200E100 0.000E-01 GI-LLI 37 ttD-97 5.760E-13 0.000E-01 6.259E-12 1.500E-12 1.043E-12 0.000E-01 5.020E-09 0.000E-01 GI-LLI l.
30 HO-Y9 2.009El07 0.000E-01 0.000E-01 0.123E107 1.735Et00 0.000E-01 6.719Et07 0.000E-01 KIDNEY 39 TC-99M 4.367E102 0.000E-01 1.344E101 2.635E101 3.029Et02 1.330Ct01 1.499Et04 0.000E-01 GI-LLI 40 TC-101 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 W.. BODY 41 RU-103 1.651Et03 0.000E-01 4.294Et03 0.000E-01 1.001El04 0.000E-01 1.110El05 0.000E-01 GI-LLI 42 RU-105 1.403C-03 0.000E-01 3.060E-03 0.000E-01 3.400E-02 0.000E-01 2.525El00 0.000E-01 GI-LLI 43 RU-106 1.153E104 0.000E-01 9.240E104 0.000E-01 1.240E105 0.000E-01 1.437Ct06 0.000E-01 GI-LLI 44 AG-110H 1.120EIOD 0.000E-01 2.009Et00 1.411E100 2.627EIOS 0.000E-01 1.673Et10 0.000E-01 GI-LLI I 45 CD-115M 4.237E104 0.000E-01 0.000E-01 1.326E606 1.052Et06 0.000E-01 5.570Et07 0.000E-01 GI-LLI f 46 SD-121 1.086EIO7 6.646E104 2.751EtO7 5.100EiO5 0.000E-01 2.134Et07 7.702E100 0.000E-01 GI-LLIi N
47 1E-125M 9.041Et06 2.072Et07 7.300EtO7 2.000Et07 0.000E-01 0.000L-01 7.121E607 0.000E-01 DONE .
40 TE-127H 2.469Et07 4.974Et07 2.000E100 5.601Et07 5.932Et00 0.000E-01 1.601Et00 0.000E-01 KIDHLY 49 TE-127 6.513Et02 2.102Et03 3.037Et03 0.190Et02 0.641Et03 0.000E-01 1.107E105 0.000E-01 GI-LLI i 50 TE-129H 4.20%E107 0.734EIC7 2.709E100 7.565Et07 7.955E100 0.000E-01 3.304EIOD 0.000E-01 KIbHEY
( 51 TE-129 3.630E-10 1.091E-09 1.530E-09 4.269E-10 4.475E-09 0.000E-01 9.520E-00 0.000E-01 GI-LLI l
52 1E-131M 5.UU4Et03 1.137Et06 1.599E106 5.520Et05 5.351Et06 0.000E-01 2.212E107 0.000E-01 GI-LLI l 53 TE-131 0.000E-01 1.499E-32 1.?S9E-32 0.000E-01 5.923E-32 0.000E-01 1.02VE-31 0.000E-01 GI-LLI 51 TE-132 5.457E104 6.570Et06 1.021E107 4.517E106 4.194E107 0.000E-01 4.547Et07 0.000E-01 GI~LLI Sh I-130 1.031Et04 3.916E100 1.759El06 3.554Et06 5,313Ef06 0.000E-01 1.663El06 0.000E-01 TityROID 56 I-131 7.452E103 4.336Et11 1.304EtO9 1.312EtO9 2.153E109 0.000E-01 1.167Et00 0.000E-01 TilYROAD 57 I-132 5.321E-01 5.369Et01 6.290E-01 1.157Et00 1.771Et00 0.000E-01 1.362Et00 0.000E-01 11tVROID 50 I-133 0.050Ct06 3.952Et09 1.720Et07 2.127Et07 3.545E107 0.000E-01 H.573Et06 0.000E-01 ItlYROID 59 I-134 6.706C-12 3.3V3C-10 7.942E-12 1.475C-11 2.256E-11 0.000E-01 9.701E-12 0.000E-01 TilVROID 40 I-135 4.52?Et04 0.401Et06 5.319E104 9.575Et04 1.460Et05 0.000E-01 7.295EIO4 0.000E-01 TitiROID 61 CS-134 7.036Etov O.000E-01 2.264E110 3.715Et10 1.151Et10 4.1310409 2.002E600 0.000E-01 LIVER 62 LS-136 1.706Et09 0.000E-01 1.001EtO9 2.760EIC9 1.4700409 2.192E+00 9.499E107 0.000E-01 LIVER 63 CS-137 4.555C109 0.000E-01 3.224E110 3.006Et10 1.006Lt10 3.610Et09 1.9320100 0.000E-01 B0HE 64 CS-130 4.01-lE-23 0.000E-01 4.554E-23 6.331E-23 4.454E-23 4.793E-24 2.916E-23 0.000E-01 LIVER 65 CS-139 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 W. DODY 66 DA-139 5.039E-09 0.000E-01 2.015E-07 1.075E-10 9.392E-11 6.326E-11 1.143E-05 0.000E-01 GI-LLI 67 I:A-140 6.031E606 0.000E-01 1.170E100 1.025E105 3.338El04 6.113C104 5.930E107 0.000E-01 DONE 60 PA-141 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 W. DODY 69 DA-142 0.000E-01 0.000E-01 0.000C-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 W. BODY 70 LA-110 2.119Et00 0.000E-01 1.945Et01 6.79fEtOO 0.000E-01 0.000E-01 1.095E105 0.000E-01 GI-LLI v
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I
@ TABLE 6 (CONT)
$ Page 9 of.39 ds D
, PATHWAY DOSE PARAMETER FACTORS FOR IMPLEMENIANG 10 CFR PART 50 E
g AGE CHILD H PATHWAY I COW MILK
' F4 . -
NO ISOTOPE W. D0DY' THYROID BONE LIVER KIDNEY . LUNG GI-LLI SKIN CRITICAL 71 LA-142 3.904C-12 0.000E-01 3.992E-11 1.272E-11 0.000E-01 0.000E-01 2.522E-06 0.000E-01 GI-LLI 72 CE-141 1.420E403 0.000E-01 2.107E104 1.071Et04 4.701Et03 0.000E-01 1.361Et07 0.000E-01 GI-LLI 73 CE-143 1.474Et01-0.000E-01'1.877Ef02 1.010Et05 4.270E601 0.000E-01 1.490E606 0.000E-01 GI-LLI 74 CE-144 8.640Et04 0.000E-01 1.623Et06 5.087Et05 2.814EtOS 0.000E-01 1.326E100 0.000E-01 GI-LLI 75 PR-143 3.561Et01 0.000E-01.7.177E102 2.155E402 1.167E102 0.000E-01 7.744E105 0.000E-01 GI-LLI 74 PR-144 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 W. DODY 77 ND-147 2.700E401 0.000E-01 4.444E102 3.600Et02 1.975E-t02 0.000E-01 5.703EtOS 0.000E-01 GI-LLI 78 W-155 4.032E+04 0.000E-01 1.382E606 4.594Et05 0.000E-01 0.000E-01 5.300E607 0.000E-01 GI-LLI f 79 W-187 7.719Et03 0.000E-01 2.905EiO4 1.720Et04 0.000E-01 0.000E-01 2.417E106 0.000E-01 GI-LLI
- p 80 U-235 1.999E108 0.000E-01 3.299Et09 0.000E-01 7.693Et00 0.OOOE-01 3.213Et00 0.000E-01 BONE 00 01 U-230 1.072E t08 0.000E-01 3.155E t09 0.000E-01 7.199E t08 0.000E-01 6.82 vet 03 0.000E-01 B0HE 02 HP-239 '8.657E-01 0.000E-01 1.715E101 1.232Et00 3.561E600 0.000E-01 9.115Et04 0.000E-01 GI-LLI I
t 1
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M- . .. TABLE- 6 (CONT)
T. Page 10 of 39-as
@ PATHWAY DOSE PARAMETER-FACTORS FOR IMPLEMENTING 10 CFR PART 50 y.
--AGE 1 INFANT
!@L PATHWAY ! COW MILK
.y' NO ISOTOPE .W. BODY THYROID . BONE LIVER KIDNEY LUNG GI-LLI SKIN- CRITICAL e.
1 11- 3 2.302E103 2.382Et03 0.000E-01 2.302E403 2.382EiO3 2.382E103 2.382E103 2.382Ef03 W. BODY 2 C-14 . ~6.880E105 6.088E405 3.226Ef06 6.888Et05 6.880Ef05 6.888Et05 6.083Et05 6.088Et05 BONE
, 3 NA-24 1.555Ef07 1.555E107 1.555Et07 1.555E407 1.555E107 1.555Et07 1.555E107 0.000E-01 W. BODY 4 P-32 . 6.215Et09 0.000E-01 1.603Et11 9.432E109 0.000E-01 0.000E-01 2.169El09 0.000E-01 BONE 5 SC-46 1.078Et03 0.000E-01 1.910E102 3.744Ef02 3.466E102 0.000E-01 1.806E606 0.000E-01 GI-LLI 6 ER-51 1.614Et05 1.053Et05 0.000E-01 0.000E-01 2.300Et04 2.049ElG5 4.704Et06 0.000E-01 .GI-LLI 7 MN-54 8.839E106 0.000E-01 0.000E-01 3.900Et07 8.643E406 0.000E-01 1.433Et07 0.000E-01 LIVER 8 MN-56 5.389E-03 0.000E-01 0.000E-01 3.126E-02 2.687E-02 0.000E-01 2.840Et00 0.000E-01 GI-LLI 9 FE-55 2.333Ef07 0.000E-01 1.351Et08 8.729Et07 0.000E-01 4.267Et07 1.100Cl07 0.000E-01 BONE 10 FE-59 1.541Et08 0.000E-01 2.243E400 3.910Et08 0.000E-01 1.150E408 1.872Et03 0.000E-01 LIVER ao 11 CO-58 6.020Et07 0.000E-01 0.000E-01 2.430Et07 0.000E-01 0.000E-01 6.055E107 0.000E-01 GI-LLI I 12 CO-60 2.001Et08 0.000E-01 0.000E-01 0.015E107 0.000E-01 0.000E-01 2.0?OtiOO 0.000E-01 GI- LLI
$' 13 NI-59 8.985E107 0.000E-01 5.386Et08 1.847E100 0.000E-01 0.000E-01 3.003Et07 0.000E-01 BONE 14 NI-63 1.212E409 0.000E-01 3.493Et10 2.160Et09 0.000E-01 0.000E-01 1.074Et08 0.000E-01 DONE 15 NI-65 1.806E-01 0.000E-01 3.508Ef00 3.971E-01 0.000E-01 0.000E-01 3.023E801 0.000E-01 G I-1.LI 16 CU-64 8.509Et04 0.000E-01.0.000E-01 1.037Ef05 3.100Et05 0.000E-01 3.772Et06 0.000E-01 GI-LLI 17 ZN-65 8.777Et0? 0.000E-01 5.550E109 1.903Et10 9.229El09 0.000E-01 1.4000110 0.000E-01 LIVER 10 ZN-69 6.319E-12 0.000E-01 4.717E-11 8.493E-11 3.529E-11 0.000E-01 6.924E-09 0.0000-01 GI-LLI 19 PR-83 9.002E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 W. BODY 20 BR-04 1.107E-22 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000L-01 W. DODY 21 DR-05 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 W. 00DY 22 RD-06 1.090Et10 0.000E-01 0.000E-01 2.223Et10 0.000E-01 0.000E-01 5.607EiOO 0.000E-01 LIVER 23 RD-80 0.000E-01 0.000E-01 0.000E-01 1.311E-32 0.000E-01 0.000E-01 1.276E-32 0.000E-01 LIVER 24 RB-09 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000C-01 W. 00DY 2*5 SR-09 3.609Et00 0.000E-01 1.25BEf10 0.000E-01 0.000E-01 0.000E-01 2.506El08 0.000E-01 DONE 26 SR-90 3.096Ef10 0.000E-01 1.214Et11 0.000E-01 0.000E-01 0.000E-01 1.510E409 0.000E-01 DONC 27 SR-91 9.75VE103 0.000E-01 2.696E105 0.000E-01 0.000E-01 0.000E-01 3.192E105 0.000E-01 CI-LLI 20 SR-92 1.707E-01 0.000E-01 4.597E100 0.000E-01 0.000E-01 0.000E-01 4.956E101 0.000E-01 GI-LLI 29 Y-90 1.030Et01 0.000E-01 6.023Et02 0.000E-01 0.000E-01 0.000E-01 9.422E105 0.000E-01 GI-Lt!
30 Y-91M 2.075E-20 0.000E-01 6.088E-19 0.000E-01 0.000E-01 0.000E-01 2.02VE-15 0.000E-01 GI-LLI 31 Y-91 1.952E603 0.000E-01 7.327Cl04 0.000E-01 0.000E-01 0.000E-01 5.252E104 0.000E-01 GI-LLI 32 Y-92 1.500E-05 0.000E-01 5.367E-04 0.000E-01 0.000E-01 0.000E-01 1.024Et01 0.000E-01 GI-LLI 33 Y-93 6.093E-02 0.000E-01-2.237EiOO 0.000E-01 0.000E-01 0.000E-01 1.767Et04 0.000E-01 GI-LLI 31 ZR-95 1.102E103 0.000E-01 6.041E103 1.667E103 1.797Et03 0.000E-01 0.302Et05 0.000C-01 GI-LLI 35 ZR-97 .3.170E-01 0.000E-01 4.054E100 6.950E-01 7.013E-01 0.000E-01 4.430E104 0.000E-01 GI-LLI e
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O E E EEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEE C L N 44260246040066620060e44222040042000 (9 P D 3411 03136804/95706502tl 051 74J0427000 3 M I I K 7 5 9 4 0 8 0 3 9 5 0 2 5 0 4. u. 0 3 4 0115 710 . 5 2 0 4. 2 6 0 2 0 f 76241511110145313412652212024261720 o R O 32235111452331321324434335552241552 64 .F 0000000000000000C00C00000000000000O 1 f - f - - - - t 41l t l - l I1 t 1t t 41 1 ll - l - - i E S R EEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEE0EE L e R E 640260000004 042202246600404001 64046 B g O V 12011000060862796551750200400050203 T I 06290000090574433913521794422969577 Aa C L TP A . 75126000115156424521331160166264721 F
4113531441434032122343323545221 1 122 R 00000000000O0000000O000O00000000000 E 1 - - - - t f1 - tI tl l - t - 1itf1I l lt 1ll - l - - l T . EEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEE E E 040260420006400622060000004 42004020
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T 321242133342313213231 33235552223331 A Y 00000000O0O00000000000O000000000000 P l t D t 1 - t - fl 1 It f - l - l - f 1 1 t I6 1 1 l tl l - 1 - - 1 0 O EEE0EtEEEEEEEECEEEEEELE6 EEEEEE0CEEE I B 00644i20400206i0i2600002001 0026u064 T 0490001246176704091 04 625600041 36650 A . 202795179326505295620151521 22175365 .
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.PATilWAY DOSE PARAMETER FACTORS FOR IMPLEMENIING 10 CFR PART 50 0-us .
M- AGE ! ADULT PATHWAY.: INHALATION hs NO ISOTOPE. W. DODY - THYROID BONE- LIVER H KIDNEY LUNG GI-LLI SKIN' ' CRITICAL ~
F4 -71 LA-142 ,
72 CC-141 7.720E-02 0.000E-01'6.832E-01 3.104E-01 0.000E-01 6.320EiO3 2.112E103 7.720E-02 LUNG 73 CC-143 1.520El03 0.000E-01 1.992Et04 1.352EiO4.6.264E103 3.616E105'1.200EtOS 0.000E-01 LUNG 74 CE-144 1.52 bel 01 0.000E-01 1.864E102 1.376E402 6.080E101 7.976Et04 2.244EiOS 0.000E-01 GI-LLI (
75 PR-143 1.840E105.0.000E-01 3.432E106 1.432Ef06 8.400EiOS 7.774EiO6 8.160E105 0.OOOE-01 LUNG 76 PR-141 4.640E102 0.000E-01 9.360Ef03 3.752E103 2.160EIO3 2.800El05 2.000El05 0.000E-01 LUNG 77 HD-147 1.52CE-03 0.000E-01 3.00DE-02 1.248E-02 7.040E-03.1.016EiO3 2.152E-OG 0.000E-01 LUNG (
7U W-185 3.610CiO2 5.44 0.000E-01 5.272Et03 6.0V6E+03 3.560Ef03 2.200Et05 1.728Et05 0.000E-01 LUNG bel 01 0.000E-01 79 W-107 1.560E103 5.176E102 0.000E-01 4.456Et05 0.560Et01 0.000E-01 LUNG 00 U-235 2.400El00 0.000E-01 8.400EtOO 7.000Ef00 0.000E-01 2.904E104 1.552Ef05 0.000E-01 GI-LLI (
UI U-230 4.056EiO4 0.000E-01 0.000El07 0.000E-01 1.872C407 3.920Et08 3.072El05 0.000E-01 LUNG g 02 ffP-239 4.534E106 0.000E-01 7.664E107 0.000E-01 1.744El07 3.661E100 0.210E605 0.000E-01 LUNG 1.210Et01 0.000E-01 2.296Et02 2.256EiL1 7.000E101 3.740EIO4 1.192El05 0.000E-01 .GI-LLI L b.
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N EEEEEEEEEEEEEEEEEEEEEEEEEELLEEEEEEE 40000000000000000000000G00000000000 I
K 60000000000000300000000O00000000000 S 60000000000000000000000.O.00000000000 50000000000000000000000000000000000 0 42S375455554S45351533341331311 35405 O0O000000000OO0O0000O000O00O0000010 5 I i1 t f - 8 4 f t t 6 t t i : I 1 l t lI 1 tt I 1 1 I - t 1 - - 1 T L L EEEEELCEEEEEEELECEEEEEEEEEEEEEEEEEE 04C000000041 200su220322020u01000122 R -
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R 922601v923171011614Y6112691U2062744 F 53532547666561635351111115451136335 C 00000000000000000000000000O000O0000 0 1 t1 f1 t 8 11 t6 t 4 t1 11 t l - - - - - - 4 i 1t1 It44t 1 O ECEEEEEEEEEEEEECEEEEEEEEEEEEE0EEECE 20622260200060446c000000014G2242024 N 103573105006527?7300000006707743014 G U N
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A D 10 3 010 0 0 3 0 0 5 6 2 5 5 2. e. 6 017 6.0. 3. .4. 4. 6 7 P 12015219103412179136311035564215134 E 1111111111133O3212267S6451111111111 S D I 0000000000000O0000000O0000000000000
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$ e Page 19 of 39 u,
FATHWAY DOSE PARAMETER FACTORS FOR IMPLENENTING 10 CFR PART 50
- un M
AGE 1 CHILD g Pall!UAY 1 INilALATION H
H t!D ISOTOPE W. 00DY Tl!(ROID BONE LIVER KIDNEY LUNG GI-LLI SKIN CRITICAL e-a 1 H-3 1.125Et03 1.125Et03 0.000E-01 1.125E403 1.125Et03 1.125Ef03 1.125Et03 1.125Ef03 W. DODY 2 C-14 6.731E103 6.734Ef03 3.509Et04 6.731Et03 6.734E103 6.734Et03 6.734E603 6.73tEf03 DONE 3 NA-24 1.607Etoi 1.60 vet 04 1.609E 6 04 1.609E 6 04 1.60VE t 0 4 1.609E f 01 1.609E t 0 4 0.000E-01 W. BODY 4 P-32 9.079Et04 0.000E-01 2.605Et06 1.143EtOS 0.000E-01 0.000E-01 4.210Et04 0.000E-01 bOHE 5 SC-46 1.151E405 0.000E-01 2.039E105 3.959Et05 3.700Et05 0.000E-01 1.195Et05 0.000E-01 LIVER 6 ER-51 1.513Ct02 0.54/E601 0.000E-01 0.000E-01 2.431Et01 1.690Et04 1.001E103 0.000E-01 LurfG 7 MN -54 9.50 vet 03 0.000E-01 0.000E-01 4.292El01 1.003Et04 1.574Et06 2.290E104 0.000E-01 Lut!G D Hit- 56 3.119F- 01 0.000E-01 0.000E-01 1.6500600 1.672Et00 1.313Et04 1.232EIO5 0.000E-01 GI-LLI
? FE-55 7.770Et03 0.000E-01 4.7360+0i 2.516E604 0.000E-01 1.110EtOS 2.06/Et03 0.000E-01 LUHG 10 I E- 59 1.669Etoi 0.000E-01 2.068EiO4 3.315Ef04 0.000E-01 1.269Ct06 7.067L404 0.OOOE-01 LUHG 11 CO-50 3.163Et03 0.000E-01 0.000E-01 1.772Et03 0.000E-01 1.106Et06 3.437Lt01 0.000E-01 LONG Y 12 LO-60 2.264Et04 0.000E-01 0.000E-01 1.313Et04 0.000E-01 7.067E106 v.620Et04 0.000E-01 LUNG y 13 NI-59 2.505Et03 0.000E-01 1.502E104 5.102Et03 0.000E-01 3.030Etoi 2.261EIO3 0.000E-01 LUHC 11 HI-63 2./97Et01 0.000E-01 0.214El05 4.625Et04 0.000E-01 2.74?Et05 6.327Et03 0.000E-01 00HE 15 H1-45 1.443E-01 0.000E-01 2.990Et00 2.954E-01 0.000C-01 0.177Et03 0.3"VE104 0.000E-01 GI-LLI 16 EU-64 1.073C100 0.000E-01 0.000E-01 1.991Et00 6.031Et00 9.503Et03 3.670El01 0.000E-01 GI-LLI 17 Z1!-65 7.030E t04 0.000E- 01 4.255Et04 1.132E105 7.111Et04 9.953EtO5 1.632Lt04 0.000E-01 LUNG IC Zd- 69 U.Y17E-03 0.000C-01 6.697E-02 9.657E-02 5.046E-02 1.421Et03 1.017Et01 0.000E-01 GI-LLI 1Y lth-03 1.736Et02 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 u. DobY 20 Uh 01 5.176El02 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.00)E-01 W. PODY 21 1R-05 2.531Et01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.00CE-01 0.000E-01 W. BODY 22 RC-06 1.143E105 0.000E-01 0.000E-01 1.903CtO5 0.000E-01 0.000E-01 7.9V2E103 0.000E-01 LIVLR 23 KD-80 3.662E102 0.000E-01 0.OOOE-01 5.424Et02 0.000E-01 0.000E-01 1.72tE601 0.000E-01 LIVER 21 RS-99 2.097E602 0.000E-01 0.000E-01 3.452Et02 0.000E-01 0.000E-01 1.091Et00 0.000E-01 LIVER 23 UR-09 1.721L404 0.000E-01 5.991Et05 0.000E-01 0.000E-01 2.157Et06 1.612Et05 0.0COE-01 LtJt!G J6 CR-90 6.430El06 0.000E-01 1.010EIOD 0.000E-01 0.0000-01 1.476C107 3.131Et05 0.000E-01 00tlE 2/ LR-Y1 4.50DEt00 0.000E-01 1.211Et02 0.000E-01 0.000E-01 5.3200601 1.739Et05 0.000E-01 GI-LLI 2d LR-92 5.254E-01 0.000E-01 1.3100101 0.000E-01 0.000E-01 2.401E104 2.423Et05 0.000E-01 GI-LLI 2V Y-90 1.106E602 0.000E-01 4.107L403 0.000E-01 0.000E-01 2.616Ct05 2.67YE105 0.000E-01 GI-LLI 30 V-V1h 1.043C-02 0.000E-01 5.069E-01 0.000E-01 0.000E-01 2.812Et03 1.717Et03 0.000E-01 LUNG 31 Y-91 2.430Et01 0.000E-01 9.139Et05 0.000E-01 0.000E-01 2.627EIO6 1.839E105 0.000E-01 LONG 32 Y- 92 5.30"E-01 0.000E-01 2.035Et01 0.000E-01 0.000E-01 2.390Et04 2.390EtOS 0.000E-01 GI-LLI 33 Y-93 5.10 set 00 0.000E-01 1.065Et02 0.000E-01 0.000E-01 7.437Et04 3.885E105 0.000E-01 GI-LLI 31 24-95 3.700Et04 0.000E-01 1.0YUEt05 4.101Et04 5.Y57Ct04 2.231Et06 6.105El04 0.000E-01 LUNG 35 2R-Y7 1.5906601 0.000E-01 1.076E602 2.716Ef01 3.005E401 1.132Et05 3.511E605 0.000E-01 GI-LLI i
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} TABLE 6 (CONT)-
'N Page 20 of 39
$ F ATilWAY DOSE PARAMETER. FACTORS FDR IMPLEMENTING 10 CFR PART 50 '
s M
ACE 1 CllILD
!, g PATiiWAY I INitALATION
.H H NO ISOTOPE W. 00DY THYRDID BONE LIVER KIDNEY LUNG GI-LLI SNIN CRITICAL
, W
- 33 HD-95 6.549Et03 0.000E-01 2.349E104 9.174El03 0.421Et03 6.142Et05 3.700E104 6.549Ef03 LUNG t- 37 t!D-97 '9.472E-03 0.000E-01 1.029E-01 2.601E-02 3.027E-02 1.110ElO3 1.117E102 0.000E-01 LUNG 30 NO-99 1.255Et01 0.000E-01 0.000E-01 1.724Et02 3.V22Et02 1.354Ct05 1.265E105 0.000E-01 LUNG 39 TC-??M 5.772E-02 0.000E-01 1.700E-03 3.432E-03 5.049E-02 9.509Et02 4.010Ct03 0.000E-01 GI-LLI 40 IC-101 1.077E-03 0.000E-01 0.103E-05 0.510E-05 1.450E-03 5.046El02 1.632Et01 0.000E-01 LUNG
- 41 RU-103 1.073El03 0.OOOE-01 2.047EiO3 0.000E-01 7.030EiO3 6.623Et05 4.477Et04 0.000E-01 Lt!NG 4 2 RU-105 5.550E-01 0.000E-01 1.520Ef00 0.000E-01 1.343E400 1.591E104 9.953Et01 0.000E-01 GI-LLI j 43 fiu-106 1.6?! Clot 0.000E-01 1.362E405 0.000E-01 1.039E405 1.432E107 4.292E105 0.000E-01 LUNG 48 AG-110M 9.13YE603 0.000E-01 1.407Ef04 1.140E404 2.124Et04 5.476Et06 1.003Et05 0.000E-01 LONG 15 CD-115M 2.941Et03 0.000E-01 0.000E-01 9.102Et04 7.326Et04 6.512Et05 1.776Etob 0.000E-01 LUNG 4 46 SD-124 5.735Et03 3.493Et01 1.443E104 2.723EIO2 0.000E-01 1.147ElO4 1.0u0E805 0.000E-01 LUNG
! Y W
17 TE-125M 9.13?E102 1.92tEf03 6.734Ef03 2.327E103 0.000E-01 4.773EIOS 3.37eE101 0.000E-01 LUMG
- 43 TE-127M 3.027El03 6.06DEt03 2.406E104 0.517Ef 03 6.364Et04 1.400E106 7.131E to t 0.000E-01 LONG 49 TE-127' 6.105E-01 1.941EiOO 2.771E t 00 9.509E-01 7.067E 100 1.003E 4 01 5.62 tE t o t 0.000E-01 GI-LLI 50 1E-129M 3.011EIO3 6.327E103 1.920Et01 4.DiSEt03 5.032Ef04 1.741Et06 1.017Et05 0.000E-01 LONG Si TE-129 2.303E-02 7.141E-02 9.760E-02 3.496E-02 2.56UE-01 2.934Et03 2.549E401 0.000E-01 G1-LLI 52 lE-131H 5.04YEt01 9.74CE101 1.343Et02 5.920E101 3.V96Et02 2.057EIOS 3.070E405 0.000C-01 GI-L LI L3 1E-131 6.5060-03 1.690E-02 2.172E-02 8.436E-03 5.003E-02 2.053Et03 1.332El03'O.000E-01 LilNG Si TE-132 2.631E102 3.175E102 4.010Et02 2.723E102 1.772Ct03 3.771E105 1.374Et05 0.000E-01 LUNG 53 I-130 0.436Et03 1.016El06 0.177Et03 1.639Etoi 2.ii4E104 0.000E-01 5.106E103 0.000E-01 litVRulD
- J4 I-131 2.727EIO4 1 624Et07 4.010E104 4.010Et04 7.001E104 0.C00E-01 2.042Cl03 0.000E-01 TliYl:0ID 57 I-132 1.076E103 1.935E105 2.114E103 4.070Et03 6.253EIO3 0.000E-01 3.200L103 0.000E-01 Til)ROID 511 I-133 7.6V6Et03 3.010Et06 1.650CiO4 2.031Et04 3.378E t01 0.000E-01 5.476Et03 0.000E-01 it!YROID 59 I-131 9.953E402 5.069Eloi 1.173Et03 2.141E403 3.300Et03 0.000E-01 9.516Et02 0.000E-01 TIIYRUID 40 1-135 4.111E103 7.918E105 4.921E103 0.730E103 1.339Et04 0.000E-01 4.440E103 0.000E-01 TitVROID 61 ES-134 2.216f.105 0.000E-01 6.512Et05 1.014C106 3.304El05 1.210E105 3.040E103 0.000E-01 LIVER 62 CS-136 1.162E105 0.000E-01 6.512El01 1.709El05 v.546Et04 1.454Et01 4.1010103 0.000E-01 LIVER 63 CG-137 1.201E105 0.000E-01 9.065El05 0.251EIOS 2.023El05 1.0400605 3.61VE103 0.000E-01 DONE 61 CS-130 5.LSOC102 0.000E-01 6.327E102 0.39 vel 02 6.216E t02 4.000Et01 2.6V7Et02 0.000E-01 LIVER 65 CS-13Y 5.113Et01 0.000E-01.9.472Et01 1.313El02 1.120E102 1.051Et01 0.000E-01 0.000E-01 1.IVER 46 Da-139 5.365E-02 0.000E-01 1.043E100 9.042E-04 0.621E-04 5.772E103 5.772Cl04 0.000E-01 UI-LLI 67 BA-110 4.329E403 0.000E-01 7.400Etoi 6.475E101 2.113E101 1.743E106 1.017Et05 0.000E-01 LUNG 60 DA-141 6.364E-03 0.000E-01 1.957E-01 1.091E-04 9.472E-05 2.919El03 2.753E102 0.000E-01 LUHG 49 UA-142 2.790E-03 0.000E-01 4.995E-02 3.600E-05 2.912C-05 1.643Et03 2.742E600 0.000E-01 LUNG 70 LA-140 7.54CEf01 0.000E-01 6.430Et02 2.250E402 0.000E-01 1.020E105 2.257Et05 0.000E-01 GI-LLI O
9-
'E TABLE. 6 (CONT)
'5un 4 Page 21 of 39 5
~ $, PATilWAY DOSE PARAMETER FACTURS FOR IMPLEMENTING 10 CFR PART 50 AGE 1 Cil1LD
.. e4 - PhillUAY : INHALATt0N w
!!O ISOTOPE W. BODY TilYROID .DONE . LIVER KIDNEY LUNG G1-LLI SKIN CRITICAL 71 LA-142 1.291E-01 0.000E-01 1.295E100 4.107E-01 0.000E-01 0.695Et03 7.505Ef04 1.291E-01 GI-LLI 72 CE-141 2.097EiO3 0.000E-01 3.922E104 1.954E104 0.547E103 5.439Et05 5.661E101 0.000E-01 LUNG 73 CE-143 2.075EiO1 0.000E-01 3.659Ef02 1.907El02 8.362EiOI 1.154Et05 1.273E105 0.000E-01 GI-LLI 74 EE-144 3.615E105 0.000E-01 6.771EIO6 2.116Et06 1.173E106 1.195E107 3.005El05 0.000E-01 LUHG
?UIR-143 9.13?Et02 0.000E-01 1.046E104 5.5bOEt03 3.001EiO3 4.329E105 9.731Et04 0.000E-01 LUNG 76 PR-144 2.997E-03 0.OOOE-01 5.957E-02 1.84LE-02 9.76BE-03 1.565E103 1.96 eel 02 0.000E-01 LullG 77 110-147 6.0000102 0.000E-01 1.000E404 0.732EiO3 4.010E103 3.202Et05 0.21tElol 0.000E-01 Lut!G 70 W-185 2.520Et01 0.000E-01 7.215Et02.2.494El02 0.000E-01 2.061Et05 3.V5SEloi 0.000E-01 LONG 08 79 U-187' 4.32VEf00 0.000E-01 1.632E101 9.657Et00 0.000E-01 4.107Et04 9.102E104 0.000E-01 GI-LLI M 80 U-235 2.246Et06 0.000E-01 3.700Ef07 0.000E-01 0.65EE104 1.013E100 1.791EIOS 0.000E-01 LutlG O 81 U-230 2.0Y0Et06 0.000E-01 3.54SEl07 0.000E-01 0.066EiO6 1.695E10D 3.811El05 0.000E-01 LUHG 82 fif-239 2.349Et01 0.000E-01 4.642Ef02 3.345C101 9.731Et01 5.009Et04 6.1010104 0.000E-01 GI-LLI t
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o 6 TABLE (CONT)
U: Page 23 of 39 txs y
u, PATilWAY DOSE PARAMETER FACTORS FOR IMPLEMENTING 10 CFR PART 50 M
AGE I INFANT
@ PATitWAY 8 INltALATION H
NO ISOTOFE W. DODY THYROID BONE LIVER KIDNEY LUNG GI-LLI SKIN CRITICAL w
36 ND-95 3.700Et03 0.000E-01 1.560Et04 6.426Et03 4.710Et03 4.700EtO5 1.267Et04 3.700Et03 LUNG 37 ND-97 3.504E-03 0.000E-01 3.092E-02 9.842E-03 1.145E-02 4.200Et02 4.223EiO1 0.000E-01 LUNG 30 MD-99 3.234E101 0.000E-01 0.000E-01 1.652E402 2.646Et02 1.34CEt05 4.072Et04 0.000E-01 LUNG I
39-TC-??M 3.724E-02 0.000E-01 1.377E-03 2.804E-03 3.10HE-02 0.104E402 2.030Et03 0.000E-01 GI-LLI 10 TC-101 0.120E-04 0.000E-01 4.510E-05 0.232C-05 9.706E-04 5.830E402 0.442Ef02 0.000E-01 GI-LLI 41 RU-103 6.790Et02 0.000E-01 2.016E+03 0.000E-01 4.242Et03 5.516E+05 1.6100404 0.000E-01 LUNG 42 RU-105 4.102E-01 0.000E-01 1.224E100 0.000E-01 0.900E-01 1.56cEf04 4.011E101 0.000E-01 GI-LLI 43 RU-106 1.000Et04 0.000E-01 8.600Et04 0.000E-01 1.065Et05 1.156Et07 1.6300605 0.000E-01 LUNG 44 AG-110M 4.9900 6 03 0.000E-01 9.902E t 03 7.221E 6 03 1.092E t04 3.660E4 06 3.304E 604 0.000E-01 LUNG 45 CD-115M 1.113Et03 0.000E-01 0.000E-01 3.444Et04 2.772Et04 2.464Et05 6.720Et04 0.000E-01 LUNG D8 46 SD-121 2.170Et03 1.322Et01 5.460gf03 1.030E402 0.000E-01 4.340Ct05 7.112EtOt 0.000E-01 LUNG E 47 TE-125M 6.580Et02 1.624E103 4.760E103 1.900Et03 0.000E-01 4.466Et05 1.291E401 0.000E-01 LUNG N 40 TE-127M 2.072C403 4.072E103 1.666EIO4 6.902Et03 3.752E104 1.312E606 2.730Et04 0.000E-01 LUNG 19 TE-127 4.086E-01 1.040Et00 2.226EiOO 9.53tE-01 4.05DEt00 1.035E104 2.436Et04 0.000E-01 GI-LLI 50 1E-129M 2.226E4 03 5.474Et03 1.414E t04 6.090Et03 3.178Et04 1.600EioS 6.9020604 0.000E-01 LUNG 51 TE-129 1.076E-02 6.740E-02 7.082C-02 3.4720-02 1.750E-01 2.996E103 2.632E404 0.OO0E-01 GI-LLI 52 TE-131M 3.626E101 0.932Et01 1.067Et02 5.502Et01 2.646Et02 1.980E105 1.191E405 0.000E-01 LUNG 53 TE-131 4.990E-03 1.502E-02 1.736E-02 0.2100-03 3.990E-02 2.0500603 U.21110t03 0.000E-01 GI-LLI 51 TE-132 1.764Et02 2.706E402 3.724Lt02 2.366E602 1.035Et03 3.402E105 4.4100101 0.000E-01 Lut!G 55 1-130 5.572Et03 1.596E404 6.356E103 1.3370404 1.526Et04 0.000E-01 1.?c0Et03 0.000E-01 TitYROID 56 I-131 1.960Et01 1.484E407 3.794E104 4.430Et04 5.1000604 0.000E-01 1.05HEt03 0.000E-01 TilYROID 57 I-132 1.259Et03 1.694Et05 1.694Et03 3.512Et03 3.940E103 0.000E-01 1.901Et03 0.000E-01 TelYROID 50 I-133 5.600Et03 3.556Et06 1.32iEt04 1.910Et01 2.240E104 0.000E-01 2.154Et03 0.000E-01 TilfROID ,
59 I-131 6.650Et02 4.152Et01 9.212Et02 1.07aEt03 2.036Et03 0.000E-01 1.289L103 0.000E-01 TitT ROID I 60 1-135 2.772Et03 6.958C105 3.044Et03 7.602E103 0.4500403 0.000E-01 1.03tEt03 0.000E-01 THYROIb 61 E5-131 7.440E101 0.000E-01 3.962E605 7.023EtOS 1.901E105 7.966Et04 1.334E403 0.000E-01 LIVER 42 ES-136 5.292Etot 0.000E-01 4.030E104 1.315Et05 5.612Et04 1.176E104 1.4200603 0.000E-01 LIVER 43 ES-137 1.550E404 0.003E-01 5.100Et05 6.11CEt05 1.722Ct05 7.124Et04 1.334El03 0.000E-01 LIVER j at C5-130 3.974E302 0.000E-01 5.051Et02 7.012Et02 4.102E402 6.5300601 0.761Et02 0.000L-01 GI-LLI l 65 ES-139 1. 914E t 01 0.000E-01 3.Lc4Et01 5.002E101 4.270Et01 3.976E600 0.000E-01 0.OOCE-01 L1VCH 64 ItA-139 4.290E-02 0.000E-01 1. 4010100 9.812E-04 5.922E-0 4 5.950E t 03 5.094E 0 01 0.000E-01 GI-LLI 47 UA-140 2.U?OEt03 0.000E-01 5.6000404 5.600EiO1 1.313Et01 1.596Et06 3.036E604 0.000E-01 LUNG 60 PA-141 n.970E-03 0.000E-01 1.560E- 01 1.07CE-04 6.r.96E-05 2.940Et03 4.7460403 0.000E-01 GI-LLI 6Y DA-li2 1.Y40E-03 0.000E-01 3.976E-02 3.30lE-05 3.904E-05 1.551Et03 6.930Et02 0.OOCE-01 LUNG 70 LA-140 5.152Et01 0.000E-01 5.051Et02 2.002Et02 0.000E-01 1.600Et05 0.4040404 0.000E-01 LONG v
5.
M . TABLE 6 (CONT)
Es -
Cl Page 24 of 39 E
PATHWAY DOSE PARAMETER FACTORS FDR IMPLEMENTING 10 CFR PART 50 H
"I AGE 1 INFANT r PATHWAY 1 INHALATION NO ISOTOPE W. D0DY THYRDID BONE LIVER KIDNEY LUNG GI-LLI GKIN CRITICAL 71 LA-142 9.044E-02 0.000E-01 1.030E400 3.766E-01 0.000E-01 8.218E103 5.950E604 9.044E-02 GI-LLI !
72 EE-141 1.900Ef03 0.000E-01 2.772Et04 1.666E104 5.250E603 5.166E105 2.1S6E604 0.000E-01 LUNG 73 CE-143 2.212E601 0.000E-01 2.926Et02 1.932E102 5.642E101 1.162E105 4.970E601 0.000E-01 LUNG 74 EE-144 1.764Et05 0.000E-01 3.192Et06 1.211Et06 5.376E105 9.042E106 1.404E405 0.000E-01 LUNG 75 PR-143 .6.906E602 0.000E-01 1.400Ef04 5.234Et03 1.974Et03 4.326Et05 3.724E604 0.000E-01 LUNG 76 PR-144 2.400E-03 0.OOOE-01 4.700E-02 1.810E-02 6.720E-03 1.610E t03 4.2C IEt03 0.000E-01 GI-LLI 77 HD-147 4.9VDE102 0.000E-01 7.938E103 8.134E403 3.150Et03 3.220Et05 3.122E104 0.000E-01 LONG D8 78 W-185 9.534E400 0.000E-01 2.730Et02 9.050E101 0.000E-01 7.790Et04 1.498E104 0.000E-01 LUNG !
5 79 u-187 3.122Ef00 0.000E-01 1.296E401 9.016E100 0.000E-01 3.962E104 3.556Et04 0.000E-01 LUNG W 80 0-235 0.4VDEtOS 0.000E-01 1.400E107 0.000E-01 3.274Et06 6.860Et07 6.776E404 0.000E-01 LUNG Ut U-230 7.93GEt05 0.000E-01 1.341Ef07 0.000E-01 3.052E106 6.412Et07 1.442E105 0.000E-01 LUNG 02 NP-239 1.076Et01 0.000E-01 3.710E102 3.310E101 6.622Et01 5.950EIO4 2.492Et01 0.000E-01 LUNG i
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o g TABLE 6 ~(CONT)
U Page 26 of 39
-a y PATHWAY DOSE PARAMETER FACTORS FOR IMPLEMENTING 10 CFR PART 50-vs ;
tus ace : ALL
@ PATHW6Y ! GROUND PLANE H
d NO ISOTOPE W. BODY THYROID BONE LIVER KIDNEY LUNG OI-LLI SKIN CRITICAL w ,
36 NB-95 1.366E108 1.366EtOS 1.366Ef00 1.366Et08 1.366E108 1.366E408 1.366Et00 1.607Et08 SKIN 37 ND 1.797E+05 1.797Ef05 1.797Ef05 1.797E105 1.797Ef05 1.797Et05 1.797Et05 2.109Ef05 SKIN 30 h0-99 3.990Et06 3.990Ef06 3.990Ef06 3.990Et06 3.990Et06 3.990E106 3.990Et06 4.620EIO6 SNIN .
39 TC-99M 1.015Ef05 1.045E105 1.845E105 1.845Et05 1.045Ef05 1.045EtOS 1.045Et05 2.115Ef05 SKIN 40 TC-101 2.031E104 2.034Et04 2.034Et04 2.034E104 2.034Et04 2.034Et04 2.034Lt04 2.260Ef04 SKIN 41 RU-!O3 1.093E100 1.093Et03 1.093Et08 1.093Et00 1.093Et00 1.093C108 1.093Et00 1.27bEtO8 SKIN L 42 f<u-105 6.373E105 6.373Et05 6.373Ef05 6.373E105 4.373E105 6.373Et05 6.373Et05 7.223E905 SKIN 43 RU-106 4.239Et03 4.239Ef00 4.239Ct00 4.239E100 4.239E400 4.23?E100 4.239E100 5.006E108 SKIN 44 AG-110M 3.460C109 3.460E109 3.460Et09 3.460Eto? 3.460E+09 3.440L10? 3.460Et09 4.037El0? SKIN .
45 CD-115M 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01.0.000E-01 W. LUDY 46 SD-124 5.994Ef00 5.994Et00 5.994E100 5.994E100 5.994C100 5.994Ef00 5.99tEt00 6.914Ef00 SKIf t D8 47 TE-125M 1.5b5Et06 1.555El06 1.555Ef06 1.555Et06 1.555EIO6 1.555Ct06 1.555Et04 2.133E606 SKIH =
b LA 40 TE-127H 9.165E104 9.145Ct04 9.165Et04 9.165Ef04 9.165E604 9.165E604 9.165E104 1.003EtOS LKIN 40 TE-127 2.9VIEt03 2.991Et03 2.991E103 2.991E103 2.991Et03 2.991E103 2.991Et03 3.290Et03 SKIN 50 IE-129H 1.947Ef07 1.967Et07 1.967E107 1.967Ef07 1.967Et07 1.967Et07 1.967E107 2.300E107 SKIN 4 51 1E-129 2.639Et01 2.63?Ef04 2.639Et01 2.43 vet 04 2.639Eto1 2.639Et01 2.439Et01 3.122Et04 Skill 52 IE-131N Q.023Et06 0.023Et06 0.023Et04 0.023Et06 0.023Et06 0.023Et06 8.023Ct04 ?.456E106 SKIN 53 TE-131 2.926Et04 2.926Et04 2.926E604 2.926Et04 2.924Et04 2.?26Eloi 2.924E604 3.150EIO7 SKIN t 54 1E-132 4.220E106 4.220E106 4.220Ef06 4.220Et06 4.220Ef06 4.220Et04 4.2200606 4.945Et06 SKIN 55 I-130 5.539El06 5.539Et06 5.539E606 5.539E106 5.53YEt06 5.539E106 5.539Et04 6.724E106 SKIH Si I-131 1.722E107 1.722E607 1.722E107 1.722C607 1.722Et07 1.722Et07 1.722El07 2.091Et07 SKIN s; 57 I-132 1.23 set 06 1.230Et04 1.230Et06 1.230Et06 1.230Et06 1.230Et06 1.230E606 1.457El06 SKIN 50 I 133 2.153E606 2.153Et06 2.453E106 2.453Et06 2.453Et06 2.453El06 2.453E604 2.903Et06 SKIN 59 I-134 1.160E105 4.160Et05 4.460E105 4.440Ef05 4.460E105 4.460Ef05 4.460E605 5.294Et05 SKIN 4 60 I-135 2.520Et06 2.520E606 2.520Et06 2.520Ct06 2.520E606 2.520Et06 2.520Ef06 2.9400106 SKIH 61 CS-131 4.031E10V 6.034C109 6.031E109 6.031E109 6.034E 609 6.831E109 6.03 tEt09 7.972E t09 LKIH 42 CC-136 1.491E100 1.491E100 1.191Et00 1.4VIEt03 1.1910100 1.491E100 1.491E 00 1.690Et00 SKIN s 43 ES-13/ 1.030Ct10 1.030Et10 1.030Et10 1.030Et10 1.030E110 1.030Elio 1.030E110 1.202Et10 SKIN 61 CS-130 3.59.'E105 3.597C105 3.597Et05 3.597E105 3.L97Et05 3.597EIO5 3.597Et05 4.111E105 SKIN 65 CS-139 3.115E101 3.115El04 3.115E604 3.115Et04 3.115Et01 3.115EIO1 3.115E101 3.561Ef04 SKIN s 66 I:n-13V 1.05 vet 05 1.059Et05 1.059E105 1.05VC105 1.059E105 1.05?EtOS 1.059EIO5 1.191E105 SKIN 6/ DA-140 2.051E907 2.051Et07 2.051E107 2.051ClO7 2.051E907 2.051Ef07 2.051Et07 2.343EtO7 skill 40 1:A-141 4.17?Et01 4.179E 604 4.1790004 4.179C t04 4.179Et04 4.179Ef 04 4.179Eloi 4.742Ef 04 SKIH (
69 06-142 4.406Ct04 4.iS4Et04 4.404E904 4.406Et01 4.404E604 4.404Ef04 4.484Et04 5.110Et04 Shlli 70 LA-140 1.924Et07 1.921E107 1.92iEtO7 1.921E607 1.92iEt07 1.924E107 1.924E607 2.101Et07 SKIN s
s o *
'\ /
y" TABLE 6 .(CONT)
Page 27.of 39 he i
i
. g' PATHWAY DOSE PARAttETER FACTORS FOR. IMPLEMENTING 10 CFR PART 50
~
. ~AGC 1'ALL.
PATHWAY 1. GROUT!D PLANE
'l NO ISOTOPE W. BODY TitVROID BONE' LIVER KIONEY LUNG G1-LLI SKIN
- CRITICAL
" '7.35?Et05 7.359E105 7.359Ef05 7.359E405 7.359Et05 7.359E405 7.359Et05 8.830E405 SKIN 71 LA-142 72 CE-141 1.365Et07 1.365Et07 1.365Et07 1.365Ef07 1.365Et07 1.365Ef07 1.365E407 1.539EtC7 SKIN 73 CC-143 2.314Et06 2.314E+06 2.314Et06 2.314Et06 2.314E606 2.314E106 2.314EiO6'2.630Et06 CKIN 6.934E107 6.934El07 6.934E407 6.934E407 6.934Et07 6.934E107 6.931E407 0.017E107 GKIN .
I
'.74 CE-144. 0.000E-01 0.000E-01 0.000E-01 0.000E-01.0.000E-01 0.000E-01 0.000E-01 0.000E-01 W. BODY 75 PR-143 76 PR-144 1 033E103 1.033E+03 1.833Et03 1.033Et03 1.033Lt03 1.833El03 1.033El03 2.100EiO3 SKIN 77 ND-147 8.309E606 0.30 vet 06 8.389El06 8.389Et06 8.309E406 8.309Et06 0.309El06 1.007E107 SKIN 70 u-135' O.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 W. BODY 7V U-107 2.358E106 2.350Ef06 2.350E606 2.350E+06 2.350Et06 2.358E106 2.358Et06 2.739Et06 CKIN 00 U-235' O.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 W. BODY 01 t1-233 0.000E-01 0.000E-01 0.000E-01 0.000E-01,0.000E-01 C.000E-01 0.000E-01 0.000E-01 W. DODY 02 HP-239 1.703Et06 1.703Et06 1.703Et06 1.703Ef06 1.703Ff06 1.703E106 1.703E106 1.972Et06 ~ SKIN I \
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- p. Page 30.of.39-I
- g' PATHWAY DOSE PARAMETER FACTORS FOR IMPLEMENTING -10 CFR PART 50
~$ .
0" AGE I ADULT PATilWAY 8 VEGETATION 1
$ NO ISOTOPE. W. BODY THYROID . BONE LIVER , KIDNEY LUNG GI-LLI SKIN CRITICAL
" 71 LA-142 1.500E-05 0.000E-01 1.331E-04 6.051E-05 0.000E-01'O.000E-01 4.419E-01 0.000E-01 GI-LLI 72 CE-141 1.511Et04 0.000E-01 1.970Ef05 1.332EtOS 6.100Ef04 0.000E-01 5.094E408 0.000E-01 GI-LLI 73 CE-143 8.154Et01 0.000E-01.9.966Ef02 7.369Et05'3.244E102 0.000E-01 2.754Et07 0.000E-01 GI-LLI 74.EE-144 1./65E106 0.000E-01 3.208E107 1.375E407 8.153EiO6 0.000E-01 1.112Et10 0.000E-01 GI-LLI 75 PR-143 . 3.101Et03 0.000E-01 6.256Ef04 2.509E104 1.4100104 0.000E-01 2.710El00 0.000E-01 GI-LLI
- 74 PR-144 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E 01 0.000E-01 0.000E-01 0.000E-01 W. Il0DY 77 ND-147 2.303E103 0.000E-01 3.330Et04.3.849Et04 2.250Et04 0.000E-01 1.040E100 0.000E-01 GI-LLI 170 W-105 6.065Ef05 0.000E-01 1.734E107 5.766Ef06 0.000E-01 0.000E-01 6.663E100 0.000E-OS GI-LLI 79 W-107 1.112El04 0.000E-01'3.006E404 3.101E104 0.000E-01-0.000E-01 1.012EIO7 0.000E-01 GI-LLI 80 U-235' 3.095Et09 0.000E-01 6.427Cf10 0.000E-01 1.499El10 0.000E-01 6.2S9EiO9 0.000E-01 B0HE j
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01 U-230 2 3.646El09 0.000E-01 6.147Et10 0.000E-01 1.402E110 0.000E-01 1.33CEt10 0.000E-01 BONE j8 02 NP-239 7.693E101 0.000E-01 1.419Et03 1.396EiO2 4.351EiO2 0.000E-01 2.063E107 0.000E-01 GI-LLI 1
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- TABLE 6' -(CONT) s Page 32 of 39 m
'S PATl!WAY DDSE PARAMETER FACTORS FOR IMPLEMENTING 10 CFR PART 50 m
j4 AGE 1 TEEN PAlllWA f 1 VEGETATION' b
y NO ISOTOPE W. DODY T!!YROID DONE LIVER KIDHEY LUNG GI-LLI SKIN - ERITICAL H 34 HD-V5 5.065EtO9 0.000E-01 1.921E105 1.065E105 1.033EtOS 0.000E-01 4.551Et00 0.000E-01 GI-LLI 37 HD-V7 1.651E-07 0.000E-01 1.791E-06 4.521E-07 5.274E-07 0.000E-01 1.660E-03 0.000E-01 GI-LLI 30 h0-99 1.070Ef06 0.000E-01 0.000E-01 5.631Ef06 1.209Et07 0.000E-01 1.009Et07 0.000E-01 f(IDNEY 39 TC-99H 9.061E101 0.000E-01 2.720E100 7.610El00 1.134E102 4.224EtOO 4.996EiO3 0.000E-01 GI-LLI 40 TC-101 0.0002-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 W. BODY il RU-103 2.95LEf06 0.000E-01 6.091E106 0.000E-01'2.429EIO7 0.000E-01 5.75LEt00 0.000E-01' GI-LLI 42 RU-105 1.922El01 0.000E-01 4.952Et01 0.000E-01 6.217Et02 0.000E-01 3.990Et04 0.000E-01 GI-LLI 13 RU-106 3.903Et07 0.000E-01 3.097E100 0.000E-01 5.973Ef00 0.000E-01 1.405E110 0.000E-01 GI-LLI 44 AG-110M Q.735E106 0.000E-01 1.517EiO7 1.436Et07 2.739Et07 0.000E-01 4.03tCl09 0.000E-01 GI-LLI 45 CD-115N 1.726E606 0.000E-01 0.000E-01 5.401Ef07 4.205E407 0.000E-01 2.272E109 0.000E-01 GI-LLI 14 SD-121 4.433E107 2.712Ef05 1.122Et00 2.116El04 0.000E-01 0.706E107 3.175E109 0.000E-01 GI-LLI 47 10-125H 1.906Et07 4.150El07 1.406E100 5.352EiO7 0.000E-01 0.000E-01 4.303EIOS 0.000E-01 GI-LLI Y 40 1E-127M 6.559El07 1.312Et03 5.515Ef00 1.956Et00 2.236Efo9 0.000E-01 1.371EIO9 0.000E-01 KIDHEY
'n
" 49 TE-127 1.153Et03 3.696El03 5.350Et03 1.099E103 2.170Et04 0.000E-01 4.137E105 0.000E-01 GI-LLI
$0 TE-129M 5.609El07 1.160El00 3.594E100 1.331E100 1.501El09 0.000E-01 1.319El09 0.000E-01 KIDHEY 51 TE-129 1.700E-04 5.225E-04 7.315E-04 2.727E-Oi 3.070E-03 0.000E-01 4.001E-03 0.000E-01 GI-LLI 52 1E-131M 3.366Et05 6.070EIO5 0.416C105 4.035E105 4.200Et06 0.000E-01 3.239E107 0.000E-01 GI-LLI 53 TE-131- 3.9?1E-16 9.010E-16 1.270E-15 5.267E-16 5.500E-15 0.000E-01 1.019E-16 0.000E-01 KIDNEY St TE-132 2.319FiO4 2.590Ef06 3.091Ef06 2.444El06 2.36.4Et07 0.000E-01 7.005E107 0.000E-01 GI-LLI 55 1-130 4.074EtOS 0.320E107 3.527EiO5 1.020El06 1.572El06 0.000E-01 7.011El05 0.000E-01 THYROID 54 I-131 5.703Ei07 3.141Et10 7.609E107 1.076El00 1.053El00 0.000E-01 2.12VLtO7 0.000E-01 TitYR01D 57 I-132 4.496E101 4.221Et03 4.700El01 1.253EIO2 1.973El02 0.000E-01 5.457El01 0.000E-01 TilVROID 50 I-133 9.990E105 1.574E100 1.932El06 3.270EiO4 5.749E106 0.000E-01 2.400E404 0.000E-01 illYROID 59 I-131 7.354E-05 3.413E-03 7.726E-05 2.040E-04 3.220E-04 0.000E-01 2.699E-06 0.000E-01 TilYROID 60 I-135 3.2? jet 04 5.715Ef06 3.452El04 U.004E104 1.403C405 0.000E-01 9.016E101 0.000E-01 THYROID 61 CS-134 7.750EtO9 0.000E-01 7.097El09 1.6700110 5.300E109 2.027E109 2.077Ef00 0.000E-01 LIVER 62 CS-136 1.133L100 0.000E-01 4.209E107 1.680E100 9.107Eio7 1.410E107 1.350E107 0.000E-01 LIVER 43 EG -137 4.69bE60V 0.000E-01 1.013El10 1.310El10 4.506El0V 1.702C109 1.910El00 0.000E-01 LIVER 61 CS--13tl 3.210E-11 0.000E-01 3.352C-11 6.436E-11 4.751E-11 5.52?E-12 2.920E-14 0.000E-01 LIVER 65 EG-139 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 W. B0bY o6 UA-13V 7.117E-01 0.000E-01 2.545E-02 1.791E-05 1.600E-05 1.234E-05 2.271E-01 0.000E-01 GI-LLI 67 DA-110 0.De2Ei04 0.000E-Oi 1.370Ei00 1.409Ei05 5.727EiO4 1.136Ei05 2.126EiOO o.000E-01 GI-LLI 60 ba-141 3.131E-23 0.000E-01 9 307E-22 7.009E-25 6.505E-25 4.790E-25 0.000E-01 0.000E-01 DONE 49 DA -142 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000C-01 0.000E-01 0.000E-01 W. DODY 70 I A-140 2.362EiO2 0.000E-01 1.007El03 0.078E102 0.000E-01 0.OOOE-01 5.090E407 0.000E-01 GI-LLI M
es g TABLE 6 (CONT)
G- Page 33 of 39 i
.$. PATHWAY LOSE PARANETER FACTORS FOR IMPLEMENTIHO 10 CFR PART 50 12
.m AGE I TEEN
@ PATilWAY : VEGETATIDH H
H' HD ISOTuf E W. DODY- TilYROID BONE LIVER KIDHEY LUNG GI-LLI SKIN CRITICAL w
71 LA-112 1.351E-05 0.000E-01 1.221E-04 5.424E-05 0.000E-01 0.000E-01 1.651E-t00 0.000E-01 GI-LLI 72 EE-141 2.16 del 04 0.000E-01 2.027Ef05 1.088Ef05 8.006E104 0.000E-01 5.399EiOO 0.000E-01 GI-LLI 73 CE-143 -7.571Et01 0.000E-01 9.315Ef02 6.770EiO5 3.040Ef02 0.000E-01 2.037Et07 0.000E-01 CI-LLI 71 CE-144 2.833Ef06 0.000E-01'5.271Et07 2.101Ef07 1.303Ef07 0.000E-01 1.325Ei10 0.000E-01 GI-LLI 75 PR-143- 3.402Et03 0.000E-01 6.995Et04 2.793E404 1.623Et04 0.000E-01 2.301EIOO O.000E-01 GI-LLI .
7s PR-144 0.000E-01 0.000E-01 0.OO0E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 W. BODY 77 HD-147 2.354E103 0.000E-01 3.617Et04 3.933Et04 2.310ElO4 0.000E-01 1.419Et00 0.0002-01 GI-LLI 70 W-10S 6.613E105 0.000E-01 1.091Et07 6.207Ef06 0.000E-01 0.000E-01 7.265El08 0.000E-01 GI-LLI 4 ,
7V U-107 1.011Et04 0.000E-01 3.510Ef04 2.085E604 0.000E-01 0.000E-01 7.000El04 0.000E-01 GI-LLI 80 U-235 4.417Et09 0.000E-01 7.289Et10 0.000E-01.1.700Ef10 0.000E-01 7.099Et09 0.000E-01 BONE Ds 01 U-238 4.136E409 0.000E-01 6.971Et10 0.000E-01 1.591EIl0 0.000C-01 1.509Ll10 0.000E-01 LONE 8 dn N
02 HP-239 7.217Et01 0.000E-01 1.370Ef03 1.299Et02 4.070EiO2 0.000E-01 2.090Et07 0.000E-01 GI-LLI t
t 6-I i
) . . . . . _.. ....._.. . . . . . . . . . -_
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q A
~I TABLE 6 (CONT)
$ Page 34 of 39- -
y i E PATifWAY DOSE PARAMETER FACTORS FOR IMPLEHENTING 10 CFR PART 50 un t-un
eq AGE ! CtlILD g PATHWAY 1. VEGETATION f, M
H NO ISOTOPE W. BODY TitVROID BCNE LIVER KIDNEY LUNG GI-LLI SKIN CRITICAL H .
{;
1 11 - 3 4.000Et03 4.000E403 0.000E-01 4.008Et03 4.000Et03 4.008Ef03 4.000Et03 4.000Ef03 W. BODY 2 C-14 7.000Et05 7.000Et05 3.504El06 7.008Ef05 7.003E+05 7.000E105 7.OODE105 7.000Cf05 BONE 3 NA-24 3.732Et05 3.732El05 3.732Et05 3.732E+05 3.732Ct05 3.732Et05 3.732E105 0.000E-01 W. BODY (;
4 P-32 1.301E600 0.000E-01.3.375E109 1.579Ef00 0.000E-01 0.000E-01 9.326Et07 0.000E-01 DONE 5 SC-46 1.239EIO5 0.000E-01 2.195E105 4.302EtOS 3.903Et05 0.000E-01 2.075E109 0.000E-01 GI-LLI 6 CR-51 1.175E105 6.522El04 0.000E-01 0.000E-01 1.702Et04 1.191Ef05 6.232E106 0.000E-01 GI-LLI (d 7 MN-54 1.770E100 0.000E-01 0.000E-01 6.646Ef00 1.063E100 0.000E-01 5.570Ef00 0.000E-01 LIVER 0 MH-56 4.100Et00 0.000E-01 0.000E-01 1.016E101 2.197E101 0.000E-01 2.632E103 0.000E-01 GI-LLI 9 I'E-55 1.317Ef00 0.000E-01 0.012EtOB 4.250E108 0.000E-01 2.404El00 7.073E107 0.000E-01 BONE ()
10 FE-59 3.200Et00 0.000E-01 3.970Et00 6.423Et00 0.000E-01 1.062E100 6.60BE100 0.000E-01 GI-LLI g 11 CO-50 1.907Et03 0.000E-01 0.000E-01 6.490E107 0.000E-01 0.000E-01 3.706E400 0.000E-01 GI-LLI 1 12 CO-60 1.116ElO? 0.000E-01 0.000E-01 3.703Et00 0.000E-01 0.000E-01 2.095Et09 0.000E-01 GI-LLI LJ 13 HI-59 1.190Et00 0.000E-01 7.182E608 2.463Et00 0.000E-01'O.000E-01 5.072E107 0.000E-01 LONE
'14 HI-63 1.343El09 0.000E-01 3.94YE110 2.111E109 0.000E-01 0.000E-01 1.424El00 0.000E-01 DONE 15 HI-65 5.601Et00 0.000E-01 1.019EiO2 9.595E100 0.000E-01 0.000E-01 1.175E003 0.000E-01 GI-LLI C/
16 CU-64 6.561E103 0.000E-01 0.000E-01 1.006El04 2.624Ef04 0.000E-01 5.090El05 0.000E-01 GI-LLI-17 2H-65 1.344E109 0.000E-01 0.112EIOD 2.161Et09 1.352EiO9 0.000E-01 3.795Et00 0.000E-01 LIVER 10 ZN-69 1.004E-06 0.000E-01 1.351E-05 1.952E-05 1.104E-05 0.000E-01 1.230E-03 0.000E-01 GI-LLI L-19 DR-03 5.334Et00 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 W. HODY 20 DR-04 3.101E-11 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 W. D0DY 21 DR-05 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 W. BODY (>
22 RD-04 2.767Et00 0.000E-01 0.000E-01 4.500Ef00 0.000E-01 0.000E-01 2.095Et07 0.000E-01 LIVER 23 RD-OS 1.651E-22 0.000E-01 0.000E-01 2.376E-22 0.000E-01 0.000E-01 1.166E-23 0.000E-01 LIVER 24 RD+39 0.000E-01 0.000E-01 0.OOOE-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.OOOE-01 W. BODY -
25 CR-09 1.025Et09 0.000E-01 3.590Et10 0.000E-01 0.000E-O! 0.000E-01 1.390E109 0.000E-01 DONE 26 SR-YO 3.152Et11 0.000E-01 1.213Et12 0.000E-01 0.000E-01 0.000E-01 1.675El10 0.000E-01 DONE 27 hk-91 1.953E101 0.000E-01 5.175E105 0.000E-01 0.000E-01 0.000E-01 1.143El06 0.000E-01 GI-LLI As 20 ER-92 2.021Et01 0.000E-01 7.030Et02 0.000E-01 0.000E-01 0.000E-01 1.333E604 0.000E-01 GI-LLI 29 Y-VO 6.177Et02 0.000E-01 2.300Et04 0.000E-01 0.000E-01 0.000E-01 6.570EIO7 0.000E-01 GI-LLI 30 Y-91H 3.0630-10 0.000E-01 0.417E-09 0.000E-01 0.000E-01 0.000E-01 1.640E-05 0.000E-01 GI-LLI le 31 Y-91 4.990Et05 0.000E-01 1.066E107 0.000E-01 0.000E-01 0.000E-01 2.406E109 0.000E-01 GI-LLI 32 Y-92 4.430E 02 0.000E-01 1.548E100 0.000E-01 0.000E-01 0.000E-01 4.473EiO4 0.000E-01 GI-LLI 33 Y-93 0.164El00 0.000E-01 2.973El02 0.000E-01 0.000E-01 0.000E-01 4.434E106 0.000E-01 GI-LLI 's 34 ZR-95 7.702Et05 0.000E-01 3.936El06 0.652El05 1.23CEt06 0.000E-01 9.025E100 0.000E-01 GI-LLI 35 2R-97 4.033Et01 0.000E-01 5.669E102 0.191Et01 1.174EIO2 0.000E-01 1.241Et07 0.000E-01 GI-LLI V
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Ui Page;35 Of 39
% PATitWAY' DOSE PARAMETER FACTDRS FOR IMPLLMENTING 10 CFR PART 50 0 LAGE I CHILD PATiiWAY I VEGETATION
.y NO ISOTOPE ~ W. DODY TilVROID BONE LIVER KIDNEY LUNG GI-LLI SKIN CRITICAL' 36 ND-95 1.141Ef05 0.000E-01 4 101EiO5 1.597Et05 1.500Et05 0.000E-01 2.953Et00 0.000C-01 GI-LLI 37 dD-97 1.022E-07 0.000E-01 1.109E-06 2.799E-07 3.265E-07 0.000E-01 1.033E-03 0.000E-01 GI-LLI 30 NO-99 1.903Ct06 0.000E-01LO.000E-01 7.693Et06 1.643Et07 0.000E-01 6.3620t06 0.000E-01 KIDHEY 39 TC-99N 1.526Et02 0.000E-01 4.695EtOO 9.20CEf 00 1.330E t02 4.475EiOO 5.210EiO3 0.000E-01 GI-LLI 40 TC-101 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 W. DODY 41 RU-103 5.959Ef06 0.000E-01 1.550E107 0.000E-01 3.902E107 0.000E-01 4.000E108 0.000E-01 GI-LLI 42 RU-105- 3.290Ef01 0.000E-01 9.070El01 0.000E-01 7.973Et02 0.000E-01 5.V200101 0.000E-01 GI-LLI 43 RU-106 9.300Ef07 0.000E-01 7.459E100 0.000E-01 1.007Ct09 0.000E-01 1.160Et10 0.000E-01 GI-LLI 44 AG-110H 1.736Et07 0.000E-01 3.216E107 2.172E107 4.046Ef07 0.000E 01 2.501Et09 0.000E-01 GI-LLI 15 CD-115H 1.359E t06 0.000E-01 0.000E-01 4.251E tO7 -3.373Ef 07 0.000E-01' 1.7dOLIO9 0.000E-01 GI-LLI gz 14 SD-124 '3.524E107 2.154El05 0.921EtO7 1.603Et06 0.000E-01 6.921Ef07 2.521Et0V 0.000E-01 GI-LLI .
I 47 TE-125M 4.603E107 9.859E107 3.512Et00 9.520Ef07 0.000E-01 0.000E-01~3.309Et00 0.000E-01 B0HE j2 10 1E-127M 1.569Et03 3.161Et00 1.322EiO9 3.559Ct00 3.76 vel 09 0.000E-01 1.070Et09 0.000E-01 K1DHEY 49 TE-127 2.1200603 6.043EiO3 9.007Et03 2.466Et03 2.013Ef01 0.000E-01 3.u62Et05 0.000E-01 GI-LLI 50 TE-129M 1.297Et00 2.693E100 0.354E100 2.333Etod 2.453Et09 0.000E-01 1.019Et09 0.000E-01 KIDHEY 51'IE-129 3.215E-01 9.661E-04 1.355E-03 3.701E-04 3.963E-03 0.000E-01 0.131E-02 0.000E-01 GI-LLI 52 TE-131H 5.450E105 1.093Et06 1.537E106 5.316E105 5.146El04 0.000E-01 2.154Cio7 0.000E-01 GI-LLI 53 TE-131 7.003E-16 1.000E-15 2.353E-15 7.174E-16 7.117E-15 0.000E-01 1.236C-14 0.000E-01 GI-LLI 54 TE-132 3.727Et06 4.494E106 6.972E406 3.006Et06 2.'65Et07 0 0.000E-01 3.106Cl07 0.000E-01 GI-LLI 55 I-130 '!
6.413E105 1.370E100 6.109E105 1.251E106 1.069El06 0.000E-01 5.050E105 0.000E-01 TitYROID 56 I-131 0.175Et07 4.757Et10 1.430Et00 1.439E100 2.362E100 0.000E-01 1.201EiO7 0.000E-01 THYROID 57 I-132 7.101E101 7.245Et03 0.498Et01 1.562Et02 2.390Et02 0.000E-01 1.030C002 0.000E-01 THYROID 50 1-133 1.649El06 0.094E100 3.523Et06 4.356E406 7.261Et06 0.000E-01 1.756Et06 0.000E-01 TilYROID 59 I-134 1.173E-04 5.064E-03 1.373E-04 2.549E-04 3.090E-04 0.000E-01 1.690E-04 0.000E-01 THYROIb 60 I-135 5.220E104 9.774Et06 6.130Et04 1.103Ct05 1.692EiOS 0.000E-01 0.407Eioi 0.000E-01 THYROID 61 CS-134 5.549Et09 0.000E-01 1.603Ef10 2.631Et10 0.152Ef09 2.V25Et09 1.110Et00 0.000E-01 LIVER 62 CS-136 1.434Et00 0.000E-01 0.042E407 2.216Et03 1.100E400 1.740Et07 7.707E106 0.000E-01 LIVER 63 ES-137 3.300E109 0.000E-01 2.3V2Et10 2.290E410 7.462E109 2.605Et09 1.434EiOU 0.000E-01 BONE 64 CS-130 5.375E-11 0.000C-01 6.097E-11 0.476E-11 5.963E-11 6.417E-12 3.904E-11 0.000E-01 LIVER 65 CS-139 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 W. EDDY 66 DA-139 1.360E-03 0.000E-01 4.693E-02 2.505E-05 2.100E-05 1.474E-05 2.709E600 0.000E-01 GI-LLI 67 BA-140 1.611Et07 0.000E-01 2.761Et00 2.41 vet 05 7.075Et04 1.442Ef05 1.399E100 0.000E-01 BONE 60 DA-141 5.630E-23 0.000E-01 1.732E-21 9.699E-25 0.392E-25 5.690E-24 9.072E-22 0.000E-01 DOHC 69 LA-142 0.000E-01 0.000E-01 0.000E-01'O.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 W. LODY 70 LA-140 3.535C102 0.000E-01.3.246E103 1.134EiO3 0.000E-01 0.000E-01 3.162E407 0.000E-01 GI-LLI 2
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- DAVIS-BESSE, UNIT 1 B-58 E
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7.
TABLE 7
' CONTROLLING RECEPTORS, LOCATIONS, PATHWAYS, AND ATMOSPHERIC DISPERSION PARAMETERS Distance Sector (meters) Pathways Age Group X/QI D/Q N* 870 Inhalation Infant 8.76E-07 8.09E-09 NNE- 900 Vegetation Infant 1.19E-06 1.39E-08
-NE** 900 Inhalation Child 1.26E-06 1.58E-08 ENE** -- --- --
E** -- --- ---
ESE** -- ---
.SE*** 8000 Cow / Milk Infant 3.43E-08 1.45E-10 SSE_ 2680 Vegetation Child 7.38E-08 9.13E-10 S 1990 ' Vegetation Child 7.66E-08 1.29E-09 SSW 1000 Vegetation Child 1.92E-07 4.18E-09 SW -990 Vegetation Child 3.10E-07 5.64E-09 WSW 4250 Cow / Milk Infant 5.74E-08 5.36E-10 W 980 Vegetation Child 6.21E-07 9.58E-09 WNW 2500 Vegetation Child 8.58E-08 8.61E-10 NW 1160 Vegetation Child 2.29E-07 1.97E-09
.NNW 1250 Vegetation Child 2.51E-07 1.79E-09
- Default value, no vegetable gardens within five miles.
C*These sectors are located over Lake Erie, so no ingestion pathways are present.
00* Default value, no real receptors within five miles.
r-l I
i i
DAVIS-BESSE, UNIT I B-59
- * *
- yy7, L p.,
TABLE 8 Page 1 of 2 SAMPLING LOCATIONS, DAVIS-BESSE NUCLEAR POWER STATION Appendix A Type of Code' Page Reference Location
- Location T-1 A-16 I Site boundary, 0.96 km NE of station, near intake canal.
T-2 A-17 I Site boundary,- 1.44 km E of Station.
T-3 A-18 I Site boundary, 2.24 km ESE of station, near Toussaint River and storm drain.
T-4 A-19 I Site boundary,1.28 km S of station, near Locust Point and Toussaint River.
T-5 A-20 I Main entrance to site, 0.80 km W of station.
T-7 'A-21 1 Sand Beach,1,44 km NNW of site.
T-8 A-22 I Earl Moore Farm, 4.32 km WSW of site.
T-9 A-23 C Oak Harbor, 10.9 km SSW of site.
-T-11 A-24 C Port Clinton, 18.4'km SE of site.
T-12 1A-25 C Toledo, 37.6 km WNW of site (water samples are taken from an intake located 17.6 km NNW of site).
T-17 A-26 I Irv Fick's well on site, 1.12 km SW of station.
T-20 A-27 C Carl Gaeth, 12639 W. Toussaint E Road, 7.20 km WSW of site.
T-24 A-28, A-29 C Sandusky, 39.8 km SE of site.
T-25 A-30 I Miller Farm, 5.92 km S of site.
Magee Marsh, 8.48 km Lani of site.
~
T-27 A-31 C T-28 A-32. I Unit 1 - treated and untreated water supply, onsite.
T-33 A-33 I Lake Erie, within a 8.0 km radius of site.
l .
T-35 A-34 C Lake Erie, greater than 16.0 km radius of site.
.T-37 A-35 C Fruit stand,19.2 km SW of station (or the farm 16 to 30 km from the site in the least prevalent I wind direction).
T-38 A-36 I Site boundary 0.96 km ENE of station near lake.
T-40 A-37 I' Site boundary 1.12 km SE of station near ditch to Toussaint.
~ T-41 A-38 I Site boundary 0.96 km SSE of station near ditch to Ioussaint.
- I= Indicator locations; C= Control Locations -
. DAVIS-BESSE, UNIT I B-60
- y. -
l
~
TABLE 8 (continued)
Page 2 of 2 SAMPLING LOCATIONS. DAVIS-BESSE NUCLEAR POWER STATION Appendix A Type of Code Page Reference Location
T-43 A-40 I Site boundary 0.80 km SW of. station along Route 2 fence.
T-44 A-41 I Site boundary 0.80 km WSW of station by railroad tracks.
T-45 A-42 I Site boundary 0.80 km WNW of station on access road behind Cooling Tower.
T-46 A-43 I Site boundary 0.80 km NW of station along access road.
T-47 A-44 I Site boundary 0.80 km N of station along access road by gate.
.T-48 A-45 I Site boundary 0.80 km NNE of station along access road by lake.
T-50 A 46 -I Erie Industrial Park 7.20 km SE of station by Water Tower.
T-51 A-47 I Daup Farm, 600 Tettau Road, Port Clinton, Ohio 8.80 km SSE of the station.
T-52 A-48 I Miller Farm 5.92 km S of site on West Camp
. Perry Road W.'
T-54 A-49 I M. Beier Farm 7.68 km SW of site on Genzman Road.
T-55 A-50 I Lenke Farms 8.0 km W of site on Route 2.
- I= Indicator location; C= Control locations.
4 DAVIS-BESSE, UNIT 1 B-61
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U -Page 2 of 2 h Type and Frequency of Sample Collection y Environmental Radiation Monitoring Program (Continued) m E
4 Weekly Monthly g Location Type Quarterly Semi-annually Annually 42 I' TLD 43 I TLD 44 I TLD 45 I TLD 46 I TLD 47 I TLD to 48 I TLD 0 50 I TLD 51 1 TLD 52 I TLD 54- I TLD 55 I TLD
" Composite sample over 1-week period Semi-monthly when animals are on pasture (May-October), monthly at other times
" Summer months d
Monthly when available (July, August, September)
Table 10 Sample Collection Codes Code Description AP Airborne Particulates i
AI Airborne Iodine TLD Thermoluminescent Dosimeter M Milk WW Well Water (Ground Water)
GLV Green Leafy Vegetables SWT Surface Water - Treated 1
SWU Surface Water - Untreated F Fish
'BS- Bottom Sediments l
l=
I DAVIS-BESSE,' UNIT 1 B-64 l
b - - - -
r-0FFSITE DOSE CALCULATION MANUAL APPENDIX J JUSTIFICATIONS DAVIS-BESSE, UNIT 1
( -_
Safety Evaluation for the Davis-Besse Radiological Effluent Technical Specifications Amendment Overview
. Revisions to the Davis-Besse Appendix A and Appendix B Technical Specifi-cations are proposed which will implement the regulatory requirement of 10 CFR 50, Appendix I on ALARA for radioactive effluents and other NRC regulations and criteria on radioactive material monitoring instrumenta-tion, radioactive material. control, and radiological environmental moni-toring. In keeping with NRC guidelines,-all radiological requirements are being deleted from Appendix B and placed in Appendix A.
This proposed amendment is a revision to a previously submitted amendment to the NRC dated March 16, 1979 (Serial No. 483).
The major areas that are addressed in the revised submittal are as follows:
. Liquid and gaseous effluent monitoring instrumentation--operation and periodic operability checks; Liquid and gaseous radioactive material releases--maximum release rates, quarterly does limits and yearly dose limits; Sampling and analysis requirements on batch and continuous radioac-tive material releases; Operation requirements on the liquid radwaste treatment system; Curie inventory limit on outside temporary liquid storage tanks', ,
L
- Maximum allowable oxygen concentration in the waste gas systeia; DAVIS-BESSE, UNIT 1 J-1 n, .-r. n-np.-y.-y y , v n-- y,c ,, - -we , -- , - --,r-w, e-,
,,e *,r,n , e av~.w - , ~ - -- -- .,v. . -- -, ,
Requirements to assure all solid waste meets applicable burial site requirements;
- ~ Radiological environmental monitoring program--minor revisions to 4
reflect current program and current NRC guidelines.
Changes have also been made to Section 6 of Appendix A to reflect the
- applicable administrative controls needed for the Section 3/4 revisions.
' A notable addition to the amendment is the inclusion of a requirement for an Off-site Dose Calculation Manual (ODCM) and a Process Control Program (PCP). The ODCM and PCP are not licensed documents but are referenced in the Technical Specification as presenting acceptable methods for evaluat-ing compliance with applicable Technical Specification requirements. The ODCM provides calculational ~ methods for determining radioactive effluent instrumentation alarm setpoints, and for evaluating releases of radioac-tive effluents and corresponding doses. The ODCM also includes the sampling locations for.the environmental monitoring program. The PCP presents the methods used to verify that waste (dewatered resins) as processed for disposal meets appropriate shipping and burial ground regulations. Changes may be made to these documents without NRC approval; review by the SRB is required.
Safety Evaluation An evaluation of the revised amendment has been performed to assure that the revisions as proposed do not involve an unreviewed safety question as defined in 10 CFR 50.59. The three criteria of 10 CFR 50.59 for the unreviewed safety question determination are addressed below.
1 i) Probability _of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the safety analysis report.
DAVIS-BESSE, UNIT 1 J-2
m Except for the addition of the turbine building liquid effluent radiation monitor (for which an FCR has already been initiac;d), no plant equipment modifications are required by the proposed amendment. Certain procedural l requirements will need to be developed but these address routine radioac- f i
tive material effluents and controls; no accident procedures are involved.
ii) -Probability for accident or malfunction of a different type than any evaluated previously in the SAR may be created.
For reasons as stated in response to item (i) above, the proposed amend-ment does not directly or indirectly pose a probability for an accident or malfunction. The amendment will implement the NRC regulations for routine releases and controls of radioactive material. The amendment does not address any engineered safety features of the plant design.
iii)LMargin of safety as defined in the basis for any technical specifi-cation is reduced.
The proposed amendment does not reduce the margin of safety. The proposed amendment addresses routine releases and control of radioactive' material; except as noted in item (i), no plant modifications are involved. Several operating procedure changes may be needed, but these changes will be only for routine operations and will have no impact on accident probability or consequences.
For the reasons ' discussed above for each of the criteria of 10 CFR 50.59, it is concluded that the amendment as proposed does not involve an unre-viewed safety question.
o
--DAVIS-BESSE, UNIT 1- J-3
Service Water System--Radiological Effluent Monitoring Requirements The service water system is classified as a non-radioactive system, being removed from radioactive systems by two boundaries. Radioactive systems are serviced by the component cooling water system interface; and, the service. water system provides cooling to the component cooling water system through closed loop heat exchangers. Therefore, any leaks from radioactive systems into the plant water systems would first be identified by the monitoring of the component cooling water system prior to any additional unexpected leakage into the service water system. As a prudent measure, the service water system is monitored in accordance with the NRC guidance of Standard Review Plan, Section 11.5. However, because this system is a non-radioactive system and is separated from radioactive systems through two closed-loop boundaries, no Technical Specification requirements are needed for routine monitoring and analysis for radioac- i tive' effluents.
l DAVIS-BESSE, UNIT 1 J-4 l 1
Radioactive Effluent Instrumentation--Automatic Isolation Feature The radioactive effluent monitoring instrumentation at Davis-Besse does not include provisions as called for in the NRC Standard Radiological
~ Effluent Technical Specifications for automatic isolation should any of
'the following conditions exist: circuit failure, downscale failure, or instrument not set in operate mode. Even though the automatic isolation features do not exist, administrative controls have been established such that.should any of these conditions exist the control of radioactive effluents would not be significantly impacted. Essentially all releases of liquid radwaste are controlled as individual batch releases with predetermined allowable release conditions. Thereby the radiation monitor serves mainly as a back-up; primary control is established by the prerelease radiological analyses and evaluations. To assure the availability of the back-up monitoring, the status of the instruments is checked once per shift by the control room-operators. Indicator lights on the instrument panel are checked to verify operability. An indicator would illuminate
-should a failure occur such as the ones delineated above. Therefore, in addition to the administrative controls on allowable releases, the verifi-cation of instrument operability prior to releases of radioactive effluents and the "once per shift status check by the control room operators provides adequate assurance of the proper control of the radioactive effluents.
DAVIS-BESSE, UNIT 1 J-5
. - - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - - - _ )
Technical Bases for Eliminating Curie Inventory Limit for Gaseous Waste Decay Tanks The'NRC Standard' Technical Specifications include a limit for the amount
-of radioactivity that can be stored in a single waste gas decay tank.
This curie inventory limit is established to assure that in the event of a tank failure releasing the radioactive content to the environment the resulting total body dose at the site boundary would not exceed 0.5 rem.
For Davis-Besse the inventory limit in the waste gas storage tank has been determined-to be approximately 45,000 curies (Xe-133, equivalent).
'An allowable primary coolant radioactivity concestration is established by the Technical Specifications which limit the primary coolant radioactivity concentrations to-100/E with E being the average energy of the radioactiv-ity in Hev. This equation yields an upper primary coolant gross activity limit of about 200 pCi/ml. By applying this activity concentration limit to the total liquid volume of the primary system, a total activity limit can be determined. For Davis-Besse the primary system volume is about 56,000 gallons, .which yields a limiting total inventory of approximately 41,000 Ci.
~By assuming a typical radionuclide distribution an equivalent Xe-133 inventory can be determined. Table 1 provides the typical radionuclide
-(noble gases) distribution and the Xe-133 equivalent concentration. The equivalent concentration is determined by multiplying the radionuclide concentration by the ratio of the nuclide total body dose factor to the Xe-133 total body dose factor. Summing all the individual radionuclide equivalent concentrations provides the overall Xe-133 equivalent concen-tration. For' determining concentration in a waste gas decay tank, a conservative. assumption of 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> decay in degassing the primary system has been used to correct the primary coolant concentrations. The data show that the equivalent concentration (decay corrected) is less than the gross concentration (i.e., 16 pCi/gm total in primary coolant versus 12 pCi/gm equivalent). The resulting Xe-133 equivalent curie inventory for WGDT input is approximately 31,000 Ci. !
')
i
. DAVIS-BESSE, UNIT 1- J-6 L ;
Therefore, even if the total primary system at the maximum Tech Spec allowable concentration was degassed to a single waste gas decay tank, the
. tank curie inventory would be well below the 45,000 Ci limit. Based on this evaluation, the curie inventory limit on a single waste gas storage tank has not been included as a Technical Specification requirement.
DAVIS-BESSE, UNIT 1 J-7
Table 1 Xe-133 Effective Concentration Primary
- Half-life Concentration Reg Guide 1.109 Ratio Xe-133 Coolant @ 48 hr decay TB Dose Factor TB DF Effective Cone (pCi/GM) (pCi/ml) mrem /yr Xe-133 DF @ 48 hr decay pCi/m 3 (pCi/ml)
Kr-83M 2.0-02 1.9 hr --
7.6x10-8 __ __
Kr-85M 1.1-01 4.5 hr --
1.2x10-3 4.1 --
Kr-85 7.4 10.7 yr -7.4x10-2 1.6x10-s 0.06 4.4x10-3 Kr 5.8-02 76.3 min --
5.2x10-3 20. --
Kr 1.9-01 2.84 hr --
1.5x10-2 52. --
Kr-89 4.8-03 3.16 min- --
1.7x10-2 57. --
X -131M 8.4 12 days' 7.5x10-2 9.2x10-5 0.32 2.4x10-2 Xt-133M 2.0-01 2.2 days 1.1x10-1 2.5x10-4 0.86 9.5x10-2 X2-133 1.5+01 5.3 days 1.2x10+1 2.9x10-4 1.0 1.2x10+1
- Xn-135M 1.3-02 16 min --
3.1x10-3 11. --
, X2-135 3.3-01 9.1 hr 8.5x10-3 1.8x10-3 6.2 5.3x10-2 XI-137- 8.7-03 4 min --
1.4x10-3 4.8 --
Xe-138 4.3-02 17 min --
8.8x10-3 30 --
- Tctal 1.6x10+1 1.2x10+1 1.2x10+1
- Adapted from Davis-Besse Evaluation of Compliance with Appendix I to 10 CFR 50, June 4, 1976.
DAVIS-BESSE, UNIT 1 J-8
4 Lower Limit of Detection--Decay Correction Factor The equation and definition of the 1 wer limit of detection in the NRC Standard Radiological Effluent TechnicaLSpecification include the term NDwhich is used to decay correct the analysis. The LLD is further defined as an a priori (before the fact) limit representing the capabilities of a Jmeasurement system and not an a posteriori (after the fact) limit for a particular. measurement.
Providing a decay correction for an evaluation of the capabilities of a system does not appear appropriate < It may be appropriate to decay correct certain analyses of specific samples to determine radionuclide concentra-
~
tions at the time of release. Even in this case,'such a correction is not appropriate for batch releases. Analyses are performed prior to any re-lease; and, the sample will be decaying at the same rate as the batch from which the sample was taken. For continuous releases, decay correcting analyses of samples obtained over a specified sampling interval must take into account the accumulation of radioactivity in_the sampling medium, the decay during the sampling interval a'ad, especially for short lived radio-nuclides, equilibrium or quasi-equilibrium conditions that may'be achieved.
Short-lived radionuclides will tend to reach an equilibrium value in the sampling medium as a function-of source input and half-life. A single decay correction to adjust for sampling interval will provide an unacceptable overestimate.; Equilibrium concentrations must be considered if analyses are to be indicative of actual release quantities.
Employing exp(-Mt) to adjust for radioactive decay between the end of sampling and the time of analysis.is straightforward. However, to attempt to use the same term to adjustifor decay during the sampling period is not
. proper. As a practical matt;:r7 when the half-life,. of a radionuclide is long relative to the sampling time and the. time between sampling and analysis, i.e., minimal decay, the correc't ion' term will be near unity. In that event, the correction term is relatively unimportant.
DAhIS-BESSE,UEIT1 J-9
At. the other extreme, when the half-life of a radionuclide is much shorter than the sampling time or the time between the end of sampling and the analysis, the term exp(-Aat) could be used to adjust for decay between the sad of sampling and the analysis. However, it would not be appropriate in that case to use the same term to attempt to adjust for decay during sampling.
- The relationship between the radioactivity in a sample at the end of sam-pling and the activity concentration in the medium being sampled is somewhat more involved. To explain this in the simplest condition, assume the radionuclide concentration is constant in the medium being sampled and that the medium is sampled at a constant rate, g
, In the instance of water sampling, the relationship between the activity concentration in the water being sampled and the activity concentration in the water sample at the end of sampling is:
C1=C2 At (2) 3 , ,-At where Ci =_radionuclide concentration in the water being sampled C2 = radionuclide concentration in the water sample at the end of sampling t'-= duration of sampling A = radionuclide decay. constant
- when A t >> 1, C1 ~ C2 At In the separate case of sampling a radionuclide in air by filtering the air and analyzing radioactive material collected on the filter, the radionuclide of interest is concentrated. Absent diluent air in the sample'being analyzed, the relation between radioactivity on the sample media'and radionuclide concentration in the air being sampled is:
C1=C At (2) 4 F(1 - e'^U)
DAVIS-BESSE, UNIT 1 J-10
where Ct = radionuclide concentration in the air being sampled q = radioactivity on the sample media (assuming 100% collection efficiency)
F = sampler flow rate (volume / time)
A = radionuclide decay constant t= duration of sampling when A t n 1, C : q A/F.
t This merely recognizes that the rate of loss from the filter by radioac-tive decay equals the rate of collection onto the filter at equilibrium.
The NRC proposed equation appears to incorporate an adulterated way of encouraging analysis soon after the end of sampling and to encourage efficient sample concentration or radiochemical extraction. Although not rigorous, it combines both objectives in a simple and thus practical way, provided the decay correction is not extrapolated to a time earlier than the end of sampling.
A more nearly rigorous way of determining the activity concentration (or minimum detectable activity) in the medium being sampled is to assess the LLD in the sample at the time of analysis. Then the activity concentra-
-tion in the medium being sampled can be calculated with the product of exp(-AAt) for decay between the end of sampling and the analysis and one of the equations derived herein for the relation between the medium being sampled and the activity in-the sample at the end of sampling.
However, this method is not very practical or necessary considering the types-of. sampling and analysis at nuclear power plants, the significant radionuclides, and the offsite potential doses. The bulk of the radioac-tivity is released as batch releases with all sampling and analysis performed prior-to release. Therefore, no decay corrections are applica-ble. It is in'the sampling and analysis of continuous releases that the accumulation and' decay of the radioactive material' may need to be consid-
.ered. The use of NRC's guidance for. decay correction to the mid point of
.the sampling period can grossly overestimate actual release qualities of short-lived radionuclides, while providing little improvement for the DAVIS-BESSE, UNIT 1 J-11
=
l quantification of the longer half-life radionuclides that are the major dose contributors.
Overall, it may be appropriate to decay correct certain analysis to account for radionuclide decay during the sampling period. However, simple decay correction to the mid point of sampling will grossly overes-timate any short-lived radionuclides that may be detected. More consider-ation needs to be given by the NRC to address this problem. In any case, the use of a decay correction factor in defining a lower limit of detec-tion is inappropriate. The LLD is a measurement of the capability of the measurement system and should not be used to try to establish a regulatory position on sampling and decay correction for quantification of releases.
DAVIS-BESSE, UNIT'l J-12
f Technical Basis for Liquid Radwaste System Operations Technical Specification 3.11.1.3 requires that appropriate subsystems of the liquid radwaste treatment system be routinely used to reduce the radioactive material levels prior to discharge when cumulative doses averaged over 31 days would exceed 0.25 mrem to the total body or 0.833 mrem to any organ. This specification implements the requirements of 10 CFR 50.36a(a) (1). The liquid radwaste treatment system should be used to process liquid waste in order to maintain potential doses to members of the public to less than the Appendix I design objective values of 3 mrem /yr, total body and 10 mrem /yr, any organ. Also, additional processing should be conducted to further reduce releases of radioactive material if it is cost-beneficial. This cost-benefit evaluation of the radwaste equipment operation should be based on a cost value of $1,000 per man-rem.
For the Davis-Besse Appendix I evaluation,* the quantities of radioactive material in liquid effluents released annually have been calculated to be:
total iodines 0.104 Ci total others (excluding H-3) 0.123 Ci Total 0.227 Ci
- Davis-Besse Nuclear Power Station Unit No. 1, " Evaluation of Compliance with Appendix I to 10 CFR 50," June 4, 1976.
DAVIS-BESSE, UNIT 1 J-13
The population dose commitments resulting from these releases have been calculated to be:.
thyroid 0.41 man-rem total body 0.64 man-rem Therefore, population doses are about 4 man-res/Ci of iodines released and about 5 man-res/Ci of other radionuclides (excluding H-3).
At Davis-Besse, liquid radwaste is processed by demineralization. From Regulatory Guide 1.110, the operating cost of a demineralizer is $75/ft3
-for resins and $20/ft3 for disposal or $95, total per ft of 3 resins used.
Based on a 100 ft3 resin bed with'a service life of 200,000 gallons, the cost to process waste is about $0.05 per gallon. To proceso a 13,000 gallon batch of miscellaneous liquid radwaste would cost about $650. Thereby, the radioactivity concentration below which it is not cost-baneficial to process can be calculated as follows:
$650 , 1 Ci ,10 8 pCi ,1 man-rem C = 13,000 gal
- 3785 ml/ gal 5 man-rem Ci $1,000
= 2.6x10-3 pCi/ml Individual doses have been calculated to be:
thyroid 0.034 mrem /0.104 Ci (iodines) total body- 0.032 mrem /0.123 Ci (others, excluding H-3)
Conservatively assuming that 100% of the dirty radwaste (2875 gpd) and 20%
of the clean radwaste (890 gpd) is discharged to the environment contain-ing all of the radioactive. material released, the average gross radioac-tivity concentration corresponding to the Appendix I individual dose design objectives can be determined as follows:
i DAVIS-BESSE, UNIT 1 J-14
3 mrem, total body = 0.123 Ci
- 3 mrem , 1 ,10 8pci 0.032 mrem 1.4x108 gal
- 3785 m Ci
= 2.2 x 10-3 pCi/ml 10 mrea, thyroid = 0.104/Ci
- 10 mrem , 1 , 10 8pci 0.034 mrem 1.4x108 gal
- 3785 1 O
,1
= 5.8 x 10-8 pCi/ml The radioactivity concentrations below which it is not cost-beneficial to process (2.6 x 10-3 pCi/ml) are about the same as the limiting concentra-tion corresponding to the Appendix I design objective dose (2.2 x 10-3 pCi/ml). Therefore, it is reasonable to establish the liquid radwaste system operation requirement at a value corresponding to the Appendix I design objective class (i.e., 0.25 mrem /31 days, total body and 0.833 mrem /31 days, any organ).
DAVIS-BESSE, UNIT 1 J-15 L _ . - - _ _ .
-Waste Gas Decay System and Ventilation System--Operability Requirements At Davis-Besse, the operation of the waste gas decay system is essentially continuous, similar to the routine operation of such a system at other PWRs. The system consists of a surge tank which receives the waste gases from the primary system, dual compressors (one in-service and the other in reserve), and three waste gas hold-up tanks (one in-service, one isolated for gas decay, and the third in reserve). Once the system is on-line with a waste gas decay tank receiving primary system gases for the surge tank,
, operation is automatic; no operator actions are required.
f The operating philosophy at Davis-Besse is to essentially operate the waste gas system continuously. Not only is this philosophy prudent from an ALARA standpoint, but it is also conservative and protective from an operational standpoint. Having to periodically evaluate primary system off gas activity levels and anticipate unexpected increases in radioactiv-ity would be an unnecessary burden in determining needed waste gas system operation.
For the ventilation systems, the operating philosophy is similar to that for the waste gas system; operation is continuous. But for the ventila-tion systems, the reasons for continuous operation are even more straight-
! forward. _ Areas within the plant must be provided with outside air in order to provide an inside environment suitable for continued occupancy.
! Without continuous ventilation system operation, heat, humidity, and
- airborne radioactive material levels would increase and worker occupancy would be jeopardized.
% As described in the Davis-Besse Appendix I evaluation, the ventilation
- systems contain HEPA filters for removal of airborne radioactive particu-late material prior to release to'the outside environment. (As. evaluated for Appendix I compliance, only_the waste gas vent includes charcoal
' filters for removal of radioiodines) The operation of the systems can essentially be considered a passive operation. No active operational I
J-16
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procedures are required for normal system operation for removal of airborne radioactive material.
Davis-Besse's operating philosophy (and operating procedures) for the waste gas system and ventilation systems is a commitment in itself to the routine continuous operation of the systems. Having to commit to such a requirement (in lieu of a technical specification requirement on opera-tion) without appropriate consideration of system down-time and plant shut-down (where operation may not be needed or. feasible) is unacceptable and not in keeping with the principles of ALARA. Including special technical specifications that would impose additional procedures and periodic surveillance requirements in excess of those already established (which at present assure appropriate operation) is unnecessary and excessive.
DAVIS-BESSE, UNIT 1 J-17
. . . =-
Radiological Effluent Dose Analysis--
Meteorology for Short Term Releases l
Except for the waste gas decay tank (WGDT) releases and the containment purges releases, gaseous effluents from the Davis-Besse Station are from l ventilation systems and are considered continuous releases. Most of the radioactive material in gaseous effluents is released from the WGDT.
However, because of the essentially random nature of WGDT releases (i.e.,
no prescribed diurnal time, frequency or duration), the dose analysis of these releases is better modeled by the use of annual average meteorologi-cal conditions ra,ther than short term meteorology. Containment purges are so infrequent that special meteorological analyses are not warranted; reasonable evaluations of off-site doses can be provided by the use of annual average meteorological conditions.
DAVIS-BESSE, UNIT 1 J-18
l I
J Radiological Environmental Reportina Levels i
- Only the radionuclides listed in Table 3.12-2 of the proposed Radiological Effluent. Technical Specifications for Davis-Besse are considered in the reporting requirements for elevated levels of radioactive material in environmental sampling media. The radionuclides listed are those that are dominant in the plant effluents and contribute essentially all of the environmental dose. Other radionuclides will be present in plant effluents, but their contribution to the calculated total environmental dose will be
- minor compared to the contribution of the radionuclides listed in Table 3.12-2.
Even the contents of the NRC's Standard RETS reflect this position; not all. pathways include reporting levels for all the radionuclides listed (e.g., no reporting levels are presented for Co-58, Co-60, or Fe-59 for 4' the' milk, airborne particulate, or vegetable pathway). This very selec-tive identification of pathway and important radionuclides reflects the
~ very well defined concept of significant radionuclides for each particular pathway.
- Based on past experience in monitoring plant effluents and environmental sampling media, it can be stated with confidence that for the routine operation of Davis-Besse the radionuclides listed in Table 3.12-2 with i
applicable reporting levels by the identified pathways are the only
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- radionuclides that need be considered when evaluating potential doses in the offsite environment. Also, even if reporting levels were included for other radionuclides, the values would be higher than those for the signif-icant radionuclides and would have a very minor role in determining actual
. reporting requirements. 'The reporting levels for the significant radio-nuclides-would be reached well before any identified levels of other radionuclides would even be controlling.
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DAVIS-BESSE, UNIT 1 J-19 r
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Technical Basis for Eliminating Curie Inventory Limit of Outside Liquid Tanks a
At Davis-Besse, outside liquid tanks that potentially contain radioactive material are limited to the borated water storage tanks (2 tanks @ 550,000 gallons) and the primary water storage tank (1 tank, @ 140,000 gallons).
The borated water storage tanks are part of ECCS and are of seismic design. These tanks are designed to withstand extremely adverse environ-mental conditions and for purposes of this evaluation can be considered rupture proof. Also, overflow from the tanks is piped back to radwaste.
For these reasons, it is considered unnecessary to impose curie inventory limits on these tanks.
The primary water storage tank is used for normal make-up and letdown to the primary system. Water contained within the PW storage tank is typi-cally' processed primary coolant or clean (non-radioactive) water. Prior to adding primary system water to the PW storage tank, the water is processed by evaporation and demineralization. This processing limits the levels of radioactivity in the tank. Past sampling and analysis of the tank has indicated only detectable levels of tritium, no other radionu-clides have been identified. Also, the overflow on the PW storage tank is piped to radwaste. Therefore, due to the processing of any radioactive waste prior to addition to the PW storage tank and the piping of the overflow to radwaste, the probability of'any abnormal discharges to the environment that could exceed the concentrations of 10 CFR 20, Appendix B, Table II, Column 2 at the nearest drinking water supply is extremely remote.
Because of the design of the BWST and the design and operating conditions of the PW storage tank, it is considered unnecessary to impose curie inventory limits on these tanks. -Having to routinely sample and analyze for radioactivity concentration imposes an undue ~ burden on plant personnel without providing any additional assurance of the public health and safety.
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-DAVIS-BESSE, UNIT 1 J-20
d' 4
- Samplina Frequency for I-131: Significance of Power Changes and Increases in Coolant Activity Levels i-The NRC guidance on effluent monitoring for I-131 (RETS Table 4.11-2, footnote c) calls for increased sampling frequency for I-131 during increases (or decreases) in reactor power level and increases in prims.cy i coolant level or noble gas effluent activity level. By system design, ,
1
- releases of radioactive material from plant operation are minor. Trying to identify small increases in I-131 releases that may (or may not) be associated with power changes is unnecessary. To evaluate the potential significance of increases in I-131 releases associated with power changes and the effect that sampling time may have on actual quantification of releases, the following example situation is evaluated.
Consider a power increase (or decrease) on the first day of a seven
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(7) day sampling period that leads to an increase in I-131 release rate by a factor of 10 for one (1) day. After this one day increase, the release rate returns to the steady-state condition for the remaining 6 days of the sampling period. To evaluate the amount of
. I-131 on the sampling cartridge as a function of sampling time and
, concentration,-the following equation is used:
q =Cf F (g_,-Ag t)- ,
i mA g
- where:
Q. = quantity of activity on collection medium Ct = air concentration of radionuclide i A[=decayconscantforradionuclidei t = sample time m = correction factor for collection efficiency L. Assuming'100% collection efficiency, at the end of the one day
- increase the total amount of activity (I-131) on the collection cartridge is determined to be 9.54 C;F. (For this example, the steady-state 1-131 concentration is de'signated as C. and the one day increase is 10 C.. For the remainder of the sampling period with a '
concentration eqda) l to C , the I-131 activity on the collection cartridgeisequalto4.86CF. g By decaying the activity on the collection cartridge for the one day increase to the end of the sampling period and adding this quantity to'4.66 Cg F, the total I-131. activity is determined to be 10.3 C gF.
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If this value'is' decay corrected to the mid point of the sampling period in accordance with the guidance of Regulatory Guide 1.21, the I-131 activity which is used to determine the release quantity is equal to 14.0 Cg F.
If a similar analysis is performed for the case of analyzing the collection cartridge at the end of the one day increase and analyzing a new cartridge at the end of 6 days sampling (constituting a 7 day sampling period), the total activity (decay corrected to mid-point of sampling periods) is determined to be 16.0 C gF.
By not analyzing the collection cartridge at the end of the one day increase, th'e total quantity of I-131 is underestimated by 14%. This analysis represents a somewhat worse case situation. The later into the l sampling period that the. increase occurs, the less the error. If the increase in release rate occurs after the mid point of the 7 day sampling period,.the actual release will be overestimated.
Over a period of time involving numerous increases and decreases in effluent level, the rules of probability dictate that the overestimations and underestimations will tend to cancel out, providing an overall closer approximation to actual releases.
Both the~NRC in plant measurement program and a study by EPRI* have indicated that minor increases in I-131 releases may be associated with reactor power changes and the iodine spiking phenomenon. However, these
, studies also indicate.that overall such increases are minor, not being a significant centributor to the total releases of I-131. As was concluded
.by the EPRI study for other PWRs, the main source of I-131 releases at Davis-Besse is associated with containment purges.
Regardless of the source, the total I-131 releases are negligible. Since initial start-up of Davis-Besse', the annual releases of I-131 have been less than 0.06 C gand' calculated' maximum individual doses less than 0.01 area. Even considering a hypothetical 14% increase for sampling periods
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that may include iodine spiking in the-primary coolant, the effect on
- EPRI NP-939, " Sources of Radioiodine at Pressurized Water Reactors".
! Science Applications,:Inc., November 1978 DAVIS-BESSE, UNIT'1 J-22
i total releases and calculated doses is still negligible. The actual
-increase will be even more insignificant considering the fact that the
. major. source of I-131 at Davis-Besse is from containment purges.
Based on a review of plant operating data and the above analysis of the I-131 release quantification as a function of concentration and sampling time, it is concluded that for Davis-Besse, a sampling frequency based on power changes and increases in primary coolant I-131 concentrations is not justified. Determining the releases (and the insignificant environmental doses of these releases) on a weekly basis is sufficient verification of the negligible impact of plant operation. Trying to " fine tune" these releases is not justified considering the manpower and material costs associated with the additional sampling and analysis.
4 l
- DAVIS-BESSE, UNIT 1 J-23 a
Condensate Demineralizer Backwash Receiving Tank - Radioactivity Control f
The discharge from the condensate demineralizer backwash receiving tank is controlled on a batch-by-batch basis in lieu of continuous radioactive
-effluent monitoring. .This method of operation has been determined to provide better control over the discharge of the backwash receiving tank, preventing any unanticipated, unevaluated releases of radioactively contaminated secondary-side clean-up resins to the on-site settling basin.
Prior to discharge, the contents of the backwash receiving tank are sampled and analyzed for radioactivity. As required, radioactively contaminated resins are transferred to radwaste for processing and dispos-
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al as radioactive material.
The condensate demineralizer backwash receiving tank discharge line as '
originally designed included a radiation monitor. However, because of the -
nature of'the_ resin-slurry mixture and the accumulation of resin beads in the monitor line, the radiation monitor has failed to provide the reliable indication of radioactivity and control as originally intended. For this
-reason, it has'been determined that the sampling and analysis of each batch prior to discharge is nee'ded to' identify and evaluate radioactive contamination resulting from minor steam generator tube leaks (or residual radioactive material from previous leaks) that might otherwise go unde-tected and unevaluated by a gross _ radiation effluent monitor.
The condensate demineralizer backwash receiving tank discharges to an
'on-site settling basin. No resin discharges are made directly to the
'off-site environment. Therefore, even in the event of personnel error resulting in the inadvertent discharge of unacceptably radioactive, 3 contaminated: resins to the settling basin, no off-site releases would occur.- All resins and radioactive material would be retained on-site l within the settling basin. Appropriate follow-up measures could then be initiated to control the radioactive material and prevent any potential for releases-to.the off-site environment in excess of the regulatory limits.
DAVIS-BESSE, UNIT 1 J-24
Controlling the discharge of the condensate demineralizer backwash receiv-ing tank on a batch-by-batch basis provides adequate control over the releases of any radioactive material to the off-site environment from this pathway. Also, the discharge is to an on-site settling basin, represent-ing an additional passive barrier from release off-site. Even in the unlikely event of personnel error, by discharging to an on-site settling basin and its isolation from the off-site environment, the probability of unwanted, unevaluated releases of radioactive material to the off-site environment is exceedingly remote. Any additional protective measures provided by a continuous radiation monitor (for which operational perfor-mance and reliability are unlikely, based on past experience) are not considered needed. ,
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DAVIS-BESSE, UNIT 1 J-25 L
Lower Limit Of Detection
. Definition And Application To Detection Capabilities For Ce-144 The lower limit of detection (LLD), as defined in the Radiological Effluent Technical Specifications (RETS) is an "... a priori (before the fact) limit representing the capabilities of a measurement system and not as a posteriori (after the fact) limit for a particular measurement." As defined by this definition applicable to the detection capability for
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radioactive effluent analysis, the LLD is a statistical analysis of a background spectrum and represents the detection limits for a radionuclide if it is the only radionuclide present above background. LLDs should be determined based 9a an analysis of a blank (or background) sample.
However, even with this definition and application of LLD, it can be increasingly difficult to achieve a predesignated LLD value for particular radionuclides as the photon abundance (i.e., decay yield) decreases. To address this problem, specific radionuclides have been identified in the RETS as being the principal radionuclides for which the required LLD must be met. For the analysis of samples of liquid radioactive effluents, an LLD of 5 x 10-7 pCi/ml is required. For the principal gamma emitters listed, all have characteristic gammas with energy levels and abundances that provide for sufficient analytical sensitivity yielding LLDs within the required value of 5 x 10-7 pCi/mi - except Ce-144. With a 10.8%
abundance and an energy level of 133.5 kev, being able to meet the LLD of
- 5 x 10-7 pCi/ml requires optimum conditions--conditions which cannot be repeatedly achieved for an operational radiochemistry program at Davis-Besse.
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- The low gamma yield is a major factor; however, with an energy level which is located within the Compton continuum, the detection capability for Ce-144 even for a blank, ' background sample is significantly higher com-pared with other so-called principal gamma emitters.
The. equation for LLD in the Davis-Besse RETS is:
- 4.66 S
- EV 2.22 + Y DAVIS-BESSE,' UNIT 1 .J-26
where:
S b
= the standard deviation of the background counting rate
= VR/T R = background counting rate T = counting time E = counting efficiency V = sample size 2.22 = conversion factor (transformations per minute per picoeurie)
Y = fractional chemical yield (when applicable)
By substitution of typical values in this equation, the LLDs for different principal gamma emitters can be compared. For analysis of a typical background sample at Davis-Besse, the ratio of the LLDs for Ce-144 and Co-60 is about 5.35; for Ce-144 and Mn-54 the ratio is 8.34. These large ration are demonstrative of some of the relative difficulties in achieving an LLD of 5 x 10-7 pCi/ml for Ce-144 compared with other principal gamma emitters.
Examining the equation of LLD, two main factors can be altered in an attempt to improve the detection capability - counting time and detector efficiency. (Altering sample size is not considered realistic since larger samples would pose operational and standard calibration problems.
It can also be shown that increasing sample volume does not strongly influence efficiency for counting on contact with the detector face due in part to sample self-shielding and decreased relative efficiency for the increased volume).
DAVIS-BESSE, UNIT 1 J-27
LLD improves at best as the square root of the counting time. Therefore, increasing the counting time from 2000 seconds to 5000 seconds would only '
provide a 1.6 reduction in LLD. A 5000 second count is considered to be a reasonable maximum for radioactive effluent analysis. Having to extend to longer ccunting times would introduce a potential operational delay without commensurate improvement in detection capability.
An improvement in the efficiency can be accomplished by the use of a more efficient GeLi detector. However, this increased efficiency is negated in part by the corresponding increase in background count rate. A comparison of 5 GeLi detectors with relative efficiencies ranging from 7.2% to 22%
was performed at the University of Michigan *. For a 500 m1 sample on contact witi, the detectors, the 15% relative efficiency detector demon-strated the highest photopeak efficiency in the 80-200 kev range. Even the 10% relative efficiency detector had a higher photopeak efficiency in this energy range than did the 21% and 22% relative efficiency detectors.
Some unexplainable differences may be due to inherent manufacturer speci-fications; however, a valid conclusion is that increasing the detector efficiency provides little if any improvement in detection capa'bility, especially in the low energy range (<200 kev).
Therefore, the analysis of effluent samples at Davis-Besse with a 10%
relative efficiency GeLi and a 5000 second counting time provides a detection system that is not only practical for an operational radio-
' chemistry program but can also be considered as representative of state-of-the-art for routine, general purpose radionuclide detection.
Since the required LLD of 5 x 10-7 pCi/ml can not be met on a routine basis for Ce-144, therefore the LLD for Ce-114 will be 2.0 x 10-8 pCi/ml (Table 4.11-1, footnote b.).
~*D.-M. Minnema, C. G. Hudson and J. D. Jones. "A Comparison of Ge(Li)
Detectors with Different Efficiencies for Low-Level General Purpose Counting"; University of Michigan, 1978.
DBP 4306G DAVIS-BESSE, UNIT 1 J-28