ML20087G571

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Offsite Dose Calculation Manual for Davis-Besse Nuclear Power Station
ML20087G571
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 03/31/1984
From:
TOLEDO EDISON CO.
To:
Shared Package
ML20087G521 List:
References
PROC-840331-01, NUDOCS 8403200063
Download: ML20087G571 (186)


Text

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0FFSITE 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. I 1.1.2 Turbine Building (Floor Drains) Sump l 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 i

1.4 References to 1.0 Liquid Effluents . . . . . . . . . 1.0-13 2.0 GASE0US 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 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 Gasecus Effluents . . . . . . . . . 2.0-20 3.0 EADIOLOGICAL ENVIRONMENTAL MONITORING . . . . . . . . . . 3.0-1 3.1 Land Use Census . . . . . . . . . . . . . . . . . . .-3.0-1 l 3.2 Sample Analyses . . . . . . . . . . . . . . . . . . 3.0-2 l

l DAVIS BESSE, UNIT 1 i l

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, 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

.l 11. Relative deposition for 100-m releases . . . . . . . . A-11

, 12. Map of sampling locations on the site periphery 1

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 i APPENDIX B l Tables i

l 1. Bioaccumulation factors . . . . .-. . . . . . . . . . B-1 l

l 2. Ingestion dose factors for adults . . . . . . . . . .'B-2 l

! 3. Site-related ingestion dose commitment factor . . . . B-5 l

4. Dose factors for exposure to semi-infinite cloud of noble gases . . . . . . . . . . . . . . . . . . . . B-7 DAVIS BESSE, UNIT 1 ii-

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a 0FFSITE 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 . . . ...... .... ... . . . 3-20
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 Effle.ent 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 .. ....... .... . . . J413 Waste Gas Decay System and Ventilation System-Operability Requirements ... .. . ....... .. . .... . . . J-16 4

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

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0FFSITE DOSE CALCULATION MANUAL li TABLE OF CONTENTS (Continued) i Page  !

Sampling Frequency for I-131:

Significance of Power Changes and "

Increases in Coolant Activity Levels ...... . . . . . J-21 l

Condensate Demineralizer Backwash i Receiving Tank - Radioactivity Ccatrol . . . . . . . . . . J-24 Lower Limit of Detection, Definition and Application to Detection Capabilities for Cc-144. . . . . . J-26 i

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t A INTPODUCTION This 0FFSITE DOSE CALCULATION MANUAL (0DCM) describes the methodology and parameters to be used in the calculation of offsite doses due to radioactive liquid and gaseous effluents and.in the calculation 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 0DCM 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 5) 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 coaservative 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 KUREG-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 LIQtlID 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 dilutir.n str-am 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 radiatica

{

j 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 (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 (1-2) 81 FMPC = hI MPC.1 where:

FMPC = fraction of the unrestricted area MPC C

gi = concentration of each radionuclide i measured in each tank prior to release (pCi/ml)

MPC g = unrestricted area MPC for each radionuclide i 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.

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  • l The total or gross beta or gamma activity alone may be used to conservatively determine the MPC fraction by the equation:

FMPC = t (1-3) 1x10 '

Where:

Ct = 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) Ths '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. = FMPC (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,df , is calculated based on a fixed dilution flow rate, Fd fd= d+Id3 F

d for Fd >> Id (1-5)

D.F. D.F.

where:

F = 0.9 x (dilution flow rate), as readout in d

cont'rol room f

d maximum 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 dmay 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 cbserved 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 P --r

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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 'aelow the concentrations of 10 CFR Part 2", 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 btained from the calibration curve for the monitor (cpm) total radioactivity concentration in the A =

batch A: 2C 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.

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

1 is attained, since the calculated rate contains the I

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) 4

_ waste tank rate margin i

_ dilution factor margin i

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 cf 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 i

if a significant primary-to-secondary leak is present. If f a primary-to-secondary leak is present, the activity in the

sump effluent system would be comprised of-only those j radionuclides found in the secondary system, but with I

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 1 1.0-6 l

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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 systen, 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 labo atory. 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 8-(1-7)

FMPC={MPC.1 1 Where:

FMPC = fract. ion of the unrestricted area MPC

= concentration of each radionuclide i measured gg in each grab sample i

MPC g = unrestricted area MPC for each radionuclide i 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 l

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- a If based on gross or total beta or gamma analysis, the '

unrestricted area MPC fraction is simply:

(I~0)

C' FMPC = lx10 '

Ct = 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 o' 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 (gps) 1 F = dilution flow rate (gpm) -

i

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:

l

,A C _ FHPU , f +f F (1-9) l DAVIS-BESSE, UNIT 1 1.0-8

& m e e W r

-where:

c = concentration corresponding to the unrestricted i

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 aaalysis, A=C t The calibration curve for the monitor (e.g. , Figure 1) is.,then used to determine the count rate (cpa) corre- i i

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.

.I To simplify the deternination of setpoint or in the event that the concentration of radioactive material in the sample from the turbine building sump ir below measurable levels (i.e., less than 5 x 10-7 pCi/ml s

for principal gamma emitters), the value of 1 x 10-7 pCi/ml may be sub4 : tuted Ior the factor A' (i.e.', L = 7 -1 M >

, .FMPC ,

FMPC It ray conservatively b assumed that the radionuclide e- +

concentrations in the secondary system are identical l }.. tpthoseintheturbine:buT1dingsump. Therefore, the.

. .- p se results of the sampling and analysis of *.he secondary system may be used in conservatively, determining the 4

values of FMPC.and

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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 chich 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. .

The dose contribution from all radionuclides identified in liquid effluents releas.ed to unrestricted areas is calculated using the following expressions:

D7 ={Ag7 I atg Cgg Fg i f=1 _

where:

D 7

= dose or dose commitment to organ I, including total body (arem).

F , the site-related ingestion does commitment A"=K w+U FBF.* 1 factor from radionuclide i ("#*C ) (I# "

Table 3 of Appendix B).

th time period over which C and F are Atg= length of the f gg g avera ged for all liquid releases, in hours.

C if = average concentration of radionuclide i observed in undiluted liquid effluent during time period At gfrom any liquid release, in pCi/ml. Concentrations are determined DAVIS-BESSE, UNIT 1 -1.0-10

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.

Fp = near-field average dilution factor for Cg 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 j

K, = units conversion factor .14 x 103 8

(10 x 103 lher+8,760 ) ,

4 U, = adult water consumption (730 liters /yr) (Ref. 3)

D, = dilution factor from the near-field area within one-quarter' mi'e 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, 1, 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

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DF g = dose conversion factor for nuclide, i, for adults in 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-lating the extrapolated total body and most erposed 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= 9J1 D 7 (1-11)

X where:

P 7

= projected dose commitment (arem) 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

7

= accumulated personal dose to data during the current quarter via radioactive material in liquid effluent (mrem).

DAVIS-BESSE, UNIT 1 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 Fuclear 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 Annus1 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.

DAVIS-BESSE, UNIT *t 1.0-13

l 2.0 GASEOUS EFFLUENTS 2.1 Gaseous Effluent Monitar Setpoints

.1.1 Station Vent Monitor 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:

l 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)

R t

= count rate per mrem /yr to the total body R

s

= 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 ( -2)

[MNGfi(i)]

DAVIS-BESSE, UNIT 1 2.0-1.

=

R, C + [(i7Q NG ) I Ili+ I*I M ) 1]

i (2-3)

I where:

C = count rate of the station vent monitor corresponding to grab sample radionuclide concentrations (cpm) i7Q = highest sector annual average atmospheric dis-NG persion at the unrestricted area boundary 3

= 1.83 x 10-6 sec/m in tbe north-northeast sector Kg = total body dose factor due to gamma emissions from isotope i (mrem /yr per pCi/m3 ) from Table 4

, of Appendix B 61 = 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 (mrem /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 i (mrad /yr per pCi/m3 ) from Table 4 of Appendix B.

DAVIS-3 ESSE, UNIT _1 -2.0-2

, , e r

A more conservative setpoint may be calculated to minimize requirements for adjustment of the monitor by using the equations:

R' = C' + [(i7QNG)Kl (2-4)

R' = C' + [(i?QNG)(L + 1.1M)] (2-5) where:

R' = conservative count rate per mrem /yr to the total body (Xe-233 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 4

to 1.0 pCi/sec release rate of Xe-133 (cpm)

I j K = total body dose factor for Kr-89, from Table 4 of I

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 2.1.2 Waste Gas Decay System and Containment Purge Monitors t

The waste gas decay tank releases and containment purges, j 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.

l 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 y) 3000

.where:

S = c unt rate f waste gas decay system monitor-at d

alarm setpoint level r

g

= count rate per mrem /yr to the total body-r s

C unt rate Per mrem /yr to the skin The values of rt and r are s

dependent on the radionuclide distribution and are derived by the equations:

r g

=

c + [( M NG )h i i}

L

(~}

r s

  • C*

{(E NG)!(bi 1

  • I'1 i) i I (~)

where:

c = count rate of the waste gas decay system monitor for radionuclide concentrations to be discharged (cpm) di = rate of release of noble gas radicnuclide i (pci/sec).

DAVIS-BESSE, UNIT 1 2.0-4

I For a more conservative, simpler setpoint for the waste gas system monitor, the equations are:

i e' = c' + [(i7Q )K] (2-9)

NG r's = c' ((5[Q )(L + 1.1M)) (2-10)

NG where:

r' = 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 tne 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 Dese Rate

a. Tecanical 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

C

, 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 (EIIE NG ) h i i 1

(2-11)

= (2-12)

D, (i7Q NG ) I (bi + I Idi ) 9i i

where:

D tb

= t tal body dose rate (mrem /yr)

U s

= skin dose rate (mrem /yr)

X/Q = highest sector annual average atmospheric NG dispersion at the unrestricted area boundary

= 1.83 x 10-s 3,cj,3 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 3,1500 mrem /yr to any organ. _ To deraonstrate compliance with this limit, an evaluation is performed at a frequency corresponding to the l

l DAVIS-BESSE, UNIT 1 2.0-6

sampling and analysis time period (e.g., normally once per 7 days for I-131). The following equation'may be used for evaluation:

=

D, ( FQ ) I (PgQ'g) (2-13)

I i where:

D, = average organ dose rate over the sampling time period (mrem / year)

FQ = 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.

P g

= dose parameter for radionuclide i, (mrem /yr per pCi/m3 ) for inhalation pathway from Table 5 of Appendix B. Values for P are 1

derived in accordance with the methods described in NUREG-0133.

= average release rate over the appropriate Q1 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).

By substituting 1500 mrem /yr for D, (equation 2-13) and solving for Q{, an allowable release rate for I-131 can be determined. Based on the annual average meteorological dispersion (1.68 x 10-8 sec/m 3

) and the child inhalation pathway (Pg = 1.62 x 107 mrem /yr per pCi/m 3

), the release

! rate for I-131 is 44.1 pCi/sec. An added conservatism l

DAVIS-BESSE, UNIT 1 2.0-7 i

factor of 0.8 has been included in this calculation to account for any potential dose contribution from 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. Technical specification 4.11.2.2 requires at least a monthly assessmen* of releases of noble gases to evaluate compliance with the quarterly dose limits of 15 mrad, gamma-air dose and $10 mrad, beta-air dose.

The following equations may be used to calculate the i gamma-air and beta-air doses:

D = (2-14) 3.17 x 10-8 1{ Mi [(i7i}NG) i]

D = (2-15) g 3.17 x 10-81 { gN [(i7iiNG ) i]

where:

D = air dose due to gamma emissions for noble gas radionuclide i (mrad)

M= dispersion parameter for unrestricted areas NG

= 1.83 x 10-8 sec/m3 Q1 = cumulative release of noble gas radionuclide i over the period of interest (pCi)-

DAVIS-BESSE, UNIT 1 2.0-8 r

=

D g air dose due to beta emissions from noble gas radionuclide i (mrad)

I Ng = air dose factor due to beta emissions from noble gas radionuclide i (mrad /yr per l pCi/m3 ) from Table 4 of Appendix B. l 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 (W'Q'g) (2-16) t 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 (arem)

DAVIS-BESSE, UNIT 1 2.0-9

W' = dispersion or deposition parameter for the controlling receptor location M'= 1.19 x 10-8 sec/m 3 for inhalation pathway and H-3 dose contribution via other pathways (from Table 7 of Appendix B)

=

D7ii' = 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 Rgwere derived in accordance with the methods described in NUREG-0133.

Q'g = cumulative release of radionuclide i of I-131 or material in particulate form in long-term releases over the period of interest (pCi).

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.

l I

DAVIS-BESSE, UNIT 1 2.0-10 l

i

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 3eteorological Model 2.3.1 Long-Term Atmospheric Dispersion Atmospheric dispersion 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-r uo eXP z -

p z- +ng_

E (2-17) 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 v 11.0 1.0 for t

2.58-1.58 v for 1.0< v $1.5 u u 0.3-0.06 v for 1.5< v $5.0 u u l 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) u = wind speed at ground level from the 10-m level of i 8 the satellite meteorological tower (m/sec) a z

= 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.

4

, 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)

I

+h

  • pr -h t h

l v-t l

hy = height of station vent l

! = 75.3m l

DAVIS-BESSE, UNIT 1 2.0-12

I

. 1 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 y 5 d -

cy u d _

or 3 $u subject to, for stable conditions (AT > - 0.5 *K/100m):

_ 1/4

_F the lesser of 4

_i_

or

_ 1/3

_F -ifs 1.5 S

_ u_

d = diameter of station vent

= 2.12 m cy c correction for low vent exit velocity (m) 3 1.5 1 d for Ia< 1.5

_ u_

=

0 for{>1.5_

= momentum flux parame,ter (m 4 /sec2 )

F,

= ()

1 2.0-13 i

y e + .e 4 y -,

q- q - e

S = restoring acceleration per unit vertical dis-placement for adiabatic motion in the atmosphere 8.7 x 10-4 sec -2 for ST $ 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)

7. = vertical standard deviation of the plume with building wake correction (m)

= the lesser of a2 , (0.5)b 2_ 1/2

_z n_

or J3 az 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.

i D/Q = relative deposition per unit area (m-2).

I i

t 2.0-14 i

. .- ~-

i l

2.55k

=

r (1-E) De + EDg (2-18) l where: '

D, = relative deposition rate for elevated releases from Figuras 9 through 11 of Appendix A.

D = relative deposition rate for ground level releases 8

from Figure 8 of Appendix A.

2.4 Definitions of Gaseou; Effluents Parameters b = height of reactor buildinE (m) (Section 2.3.1) i C = count rate of the station veat 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) i i

cy = effective plume height correction for low vent exit velo-city (m) (Section 2.3.1)

I 2 0-15 l

D, = relative deposition rate for elevated releases from Figure 6.

of Appendix A (Section 2.3.2)

D g

= relative deposition rate for ground level releases from Figure 7 of At pendix 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 = air dose due to gamma emissions from noble gas radionuclide i (arad) (Section 2.2.2.a)

R= 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)

= momentum flux parameter (m 4 2 ) (Section 2.3.1)

/sec F,

2.0-16

h = effective height of release (m) (Section 2.3.1) h t

= 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 pr

= additional plume height due to plume rise (m)

(Section 2.3.1)

K = total body dose factor for Kr-89, (arem/yr per pCi/m3 ) from Table 4 of Appendix B (Section 2.1.1)

K = total body dose factor due to gamma emissions from radio-t nuclide (mreic/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 /yr per pCi/m3 )

(Section 2.1.1)

Lg =

skin dose factor due to beta emissions from radionuclide i (arem/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-(

l 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

(arad/yr per pCi/23) from Table 4 of Appendix B (Section 2.1.1) i 2.0-17 l

l

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)

P g

= dose parameter for radionuclide i, (mrem /yr per pCi/m 3 ) for inhalation from Table 5 of Appendix B (Section 2.2.1.b) di = rate of release of noble gas radionuclide i (pCi/sec)

(Section 2.1.1)

= average release rate over appropriate sampling period of Q't isotope i of I-131 or other radionuclide in particulate form, with half-life greater than eight (8) days (pCi/ sed (Section 2.2.1.b) 61 = cumulative release of noble gas radionuclide i over the period of interest (pCi) (Section 2.2.2.a)

= cumulative release of radionucliae i of I-131 or material Q't in particulate form over the period of interest (pCi)

(Section 2.2.2.b) lig = 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 i

distribution (Section 2.1.1)

R t

= C unt rate Per mrem /yr to the total body based on current isotope distribution (Section 2.1.1) i R'

s

= conservative count rate per mrem /yr to the skin (Xe-133 detection Kr-89 dose) (Section 2.1.1) a 2.0-18 W:

I I

= conservative count rate per mrem /yr to the total body R'g (Xe-133 detection, Kr-89 dose) (Section 2.1.1) r = downwind dis.tance (m) r, = count rate per mrem /yr to the skin based on waste gas decay system isotope distribution (Section 2.1.2) r t

= c unt rate per mrem /yr to the total body based on current waste gas decay system isotope distribution (Section 2.1.2) r' s = c nservative count rate per mrem to the skin for waste gas decay system only (Section 2.1.2) r'g = 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 = count rate oi waste gas decay system noble gas monitor at d

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) og = vertical standard deviation of the plume at distance r for effective height under stability category indicated by AT from Figure 5 of Appendix A (n.) (Section 2.3.1)

AT = temperature differential with. vertical separation (*K/100m)

(Section 2.3.1) 2.0-19

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)

XTQ = highest sector annual average atmospheric dispersion value at the unrestricted area boundary (sec/m3 ) (Section 2.1.1)

X/Qg= controlling sector annual average atmospheric dispersion at the site boundry for the inhalation pathway (Section 2.2.1.b)

X/QNG= 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-Water-Cooled Reactors," Regulatory Guide 1.111, Revision 1.

2.0-20

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 ccuducted as specified by the monitoring program, then the pathways having maximum exposure 3.0-1

potential at th'e newly identified location will be added to the program, if samples are reasonably obtainable at the net: Icca-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 camples 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.

l i

Tables 9 and 10 of Appendix B identify the type and frequency of environmental sample collection.

4 i

l l

'DBP 4306G b

3.0-2

' t%

4 a

APPENDIX A Figures

l

\ , . -

l

!I 10 ==. -

. i

. ~-

( .

'lig i ii..:. i -

.ints 1 .  :. i i i e n:I i i .ii.:

l ll l l 1 illli i l l ll1 I l l lilli l i I ll 1111 I I Itlist l i ;l '

. 4 11 l-l ,

8l Ili,. l 1 I i

~ =

l

, .. Figure 1. Calibration Curve -

. isi'-

i l"

8 for Liquid Effluent Monitors * * ' ' ' " ' '

(RE 1770 A & 8, RE 1878 A & 8) ' ' '"'

4 Illil l l1 From Victorcen Instruction Manual I I I I II"I I I I*III".

l for Model go-1 ' l [

l j ,!

3 i

\

i,i i i e , i o,e .i:.... i i i e i e i. i . . . . .e . i...."

ll i i ! I lill!  ! l 1 I ill!- l' l I I l111l l I I ll1131 /l 1 i '.13:

ga ill!V i l I i I!!Ili s

4

e. .

' . . . . . . . . .. . .. . f.. ... ..

esin i i itine i , i i i . i: i iiein- i /. s i n i .e . .. .ni lilli l I I f ilil i II Illi .I l 1 iilli 4 I i 111111 1 II ..!.

!i

.'V i!it l  ! 1 I li

10 3 - -

. ,e . . . . . . . . . . . . .

is ei e i . . . s i .e . ii...., . /A . . . . .# e i s i . . .. , . . .. ..

k 11 i l i Illl!l  ! ll Illi i /.tf ll ill
i l I ilil!Il i I l1811?  !

4 t5 o_4 I I 11 . I V i* li . i li !_!!!!

.g n i nil lilli

.: i.no . / r i it.ii

..iei.: a ii.....

.....a . .

..i l

l I i iIlli u / I l l!lil: 1 I i i litil i I I I111:1 1 I I I!!i!

10-5.

l

/ I l li- lil!!

. . ., .m. . , , .

s. i / iiii i , ,i.o., e s i , i .. , e.... . . ......
I l li / I I t illi i i lilitl i 1 l l lll11 1 I l illi! I I I I!!;il I!!  ! I' .I I  !!!!I io-s -

. h--t _ .

l , _,,

.si.2n. z. . . . . . . . . . . . . . . . . . . . . .........

e r:.o i  : . .ri i iei n- i_ s i . ii.e i . n .:

a l 111

" ~

l l ilill I l i llll -

l l l l lill' l I l 11111 i l l !!li:

g .7 up q -

. g.

.I I I l d.!I

  • 10-71 I c IO ~

1OE:

10 3 -

104 105 106 101

)? -

COUNT 3 PCR MIN'JTE ' ,

DM IS-BESSE. UNIT 1 g,,1 u-i e ,

3' *

-_. _ _ _ _ _ . . _ _ .- - . . _ _ 2. .$_ .

- . . ~ . . . ...-J.--_.--_. -.-. --- -. ., .4 L - . - .

l l l

[

l 1 -

t g -

4

10 m.

4 m

i m

m m

m i

E 4 M

- \ t h

3

u. b g i N N %

E 1.0 ' '

?

n

.O E

.l -

t E -

1 O ,

o i

l l i

I 4

4 0.1 '

0.1 1.0 10 100 DISTANCE (KILOMETERS)

Figure 2 Open Terrain Correction Factor 4

?

+ .

i 1

o

. 8 a

i O.

/ ' 8 e

' n

/ R

/ _ G

/ E k

/

a m

O

.2 a

.c i

M 'O m E I w -

I >- 4 l

w -

l O 5 e

aeb s l 5 S

/

I

\

- l $

2 E

f 4 1 i 8 S 3 Q 4c

/ -3 5 w -

> cm E .2 e-m 3 2 =

3 m o a' 8 '

1 i

1

" '.a 2 l l  % \

O '

I I i 2

E I n.

/

c .,

( 5 C

ci q mo o 9 h o 9 o 9 w M. N n

,. o a o o a 3Wald NI DNINIVW3W NO110VWd DAVIS-BESSE, UNIT 1 g_3

Y .

2 T

m 1.0 m

~

0.9 N NEUTRAL (D) E.F I e N%g a

H w 0.8 s

t:D s g

O.7 k, (

L 0 UNSTABLE N3 3

3 0.6 (A,B,C) \ % hT N

< N 0.5

\

T '

T 2  %

9 (

$ 0.4 4

k 0.3 0.2 0.1 0.1 1.0 10.0 100.0 l200.0 PLUME TRAVEL DISTANCE (KILOMETERS)

Floure 4 Plume Depletion Ef fect for 30-m Releases (Letters denote Pasquill Stabil:ty Class).

l l -

- , i l

s<

U

~'

E m

M 1.0 STABLE' O.9 h

,s:s s au 0.8 a w (o 2 07 \

-UNSTABLE N 5

\ \ %\

3 (A,B.C)

  • 2 -

g 0.6 L I

E E 0.5 2

'\

o h N

h 3.-4

< k*

E 0.3 0,2 0.1 -

~L l' O.1 1.0 10.0 100.0 200.0 PLUME TP.AVEL DISTANCE (KILOMETERS)

Figure 5 PRme Depletion Effect for 60m Releases (Letters denota Pasquill Stability Class)

?

E

^

i

= 1.0 m

'" 0.9 s '[ K i

N m

, . NEUTRAL (D)

E D N ,

g 0.8 \ ,

\ ,

w 3 UNSTABLE N

" 0.7 z

(A,B,C)  %

> c STABLE (E,F,G) N 1 0.6 O DEPL,ETION, j (FRACTION REMAINING = 1.0) h E 0.5  % ,

z 3

\

D 0.4

( (

E 0.3 0.2 4

0.1 0.1 1.0 10.0 100.0 200.0 ,

PLUME TRAVEL DISTANCE (KILOMETERS)

Figure 6 Plume Depletion Effect for 100m Releases (Letters denote Pasquill Stability Class) -

1000 l i

l l ,'

/ / ,

/ / /

l / ./ ,

f r  ; ,

r

) ) ,/ /

,r /

/ /

/

/

/

100 A

> / /

l /

7

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- -8 ,

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~,

s / 7 , , , /

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g l ! /c- / / , ,. f _

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g s , y E Y / ,

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1 s J

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/ / / /

/ / / / _

l / / ~

/ , / -

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T-33 Fish cr ples T-33 is located in Lake Erie within an 8.0 km radius of the site.

A-33

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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t APPENDIX B Tables i

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TABLE 1 BI0 ACCUMULATION FACTORS (pCi/kg per pCi/ liter)

FRESHWATER ,

ELEMENT FISH H 9.0E C 4.6E403 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 i

RB 2. 0E+03 SR 3. 0E+01 Y 2.5E+01 ZR' 3.3E400 NB 3.0E+04 4

MO 1.0E+01 1

TC 1.5E4Cl RU l.0E401 RH 1.0E+01 TE 4.0E+02 i I l'. 5E+01 CS 2.0E+03 BA 4.0E+00 l

LA .2.5E+01 l CE 1.0E+00 PR 2.5E+01 ND 2.5E+01 W l.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 INGEST!On DesE FACTORS FOR A0utrs (wREM *ER #CI INGESTE01 NUCLICE BONE liver T.80CY THYR 0!O KIDNEY LUNG GI-LLI H 3 NO DATA 1.05E-07 1. 0 $ E -0 7 1.05d-07 1.05E-07 1.0$E-07 1.05E-07 C 14 2.846-06 5.68E-07 5.68E-07 5.68E-07 5 2 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-35 7. 40 E -0 6 NO DATA NC CATA NO DATA 2.17E-05 CR 51 40 DATA NO CATA 2. 0o E -0 9 1 59E-09 4.86E-10 3.53E-09 6.69E-07 MN 54 NO DATA 4.575-06 8.72 E-0 7 NO DATA 1.36E-06 NO DATA 1 40E-05 MN 56 .NO DATA 1.150-07 2.04 E-0 8 NO CATA 1.46E-07 NO DATA 3.67E-06 FE $5 2.75E-06 1.90E-06 4. 4 s E -0 7 NO DATA NO OATA 1 06E-06 1.09E-06 FE 59 4.34E-06 1 025-05 3.91E-06 NO DATA NO DATA 2.85E-06 3.40E-05 CO $8 NO DATA 7.456-07 1. 6 7 E-0 6 NO DATA NO DATA NO DATA 1.51E-05 CO 60 NO DATA 2.14F-06 4. 72 C-0 6 NO DATA NO DATA NO DATA 4.02E*05 N1 63 1.30E-06 9.01E-0e 4.36E-06 N0 DATA NO DATA NO DATA 1 886-06 NI 65 5.28E-07 e.86E-08 3 13E-0 8 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 05 4.84E-06 1.54E-05 e . 9a E -0 6 NO DATA 1.03E-05 NO DATA 9.70E-06

- ZN 69 1.0 3E-03 1.97E-08 1. 3 7 E-0 9 NO DATA 1.28E-0! NO DATA 2.96E-09 d4 83 10 DATA NO DATA 4. 02 E -0 8 NO DATA NO DATA NO DATA 5.79E-08 SR 84 NO DATA NO DATA 5. 21E -0 8 NO DATA NO DATA NO DATA 4.09E-13 BR 95 NC CATA NO DATA 2.14 E-0 9 NO DATA NO DATA NO DATA LT E-24 RS 66 NO DATA 2.11E-05 9. 8 3 E-0 6 NO DATA NO DATA NO DATA 4.16E-06 48 88 NO DATA 6.055-08 3.21E-08 NO DATA NO DATA NO DATA 8.36E-19

._....3..................-.______.....___......_.-.

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-06 NO'OATA 2.29E-07 10 DATA NC OATA NO DATA 2.70E-OL SR 92 2.15E-06 NO DATA 9.30E-08 NO DATA NC CATA NO DATA 4.26E-05 Y 90 9.62E-09 NO DATA 2.58E-10 No DATA NO CATA 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 1.41E-07 NO DATA 3. 77 E-0 9 NO DATA NO DATA NO DATA 7.76E-05 y 92 8.45E-10 NO CATA 2. 4 7E-11 NO DATA NO DATA NO DATA 1.48E-05

Reference:

Regulatory Guide. 1.109. Table E-11 DAVIS-BESSE, UNIT 1 B-2

TABLE 2, continued Page 2 of 3 INCESTION 00$E FACTO'S PC2 AcutTS (M4EM PE4 #CI INGESTE39 NUCL10E SONE L!vE4 T.800v THY 901C (IONEY LUNG GI-(L!

Y 93 2.68E-C1 No DATA 7.40E-11 NO DATA NO DATA NO DATA 8.50E-05 LR 9S 3.04E-08 9.75E-C9 6.60E-09 NO DATA 1 53E-08 NO DATA 3.09E-05 IR 97 1.68E-09 3.39E-10 1.55E-10 NO DATA 5.12E-10 NO DATA 1.05E-04 N8 95 6.22E-09 3.64E-09 1. 86E-0 9 NO DATA 3.42E-09 NO OATA 2.10E-05 MO 99 NO DATA 4.31E-06 8.2 0E-0 7 NO DATA 9.76E-06 NO DATA 9.99E-06 TC 99M 2.47E-10 6.985-10 8.81E-09 NO DATA 1 06E-08 3.42E-10 4.13E-07 TC101 2.$4E-10 3.66E-10 3. 59 E -0 9 NO OATA 6.59E-09 1 87E-10 1.10E-21 4U103 1.85E-07 NO DATA 7. 9 7 E-0 8 NO CATA 7.06E-07 NO OATA 2.16E-05 2U10S 1.54E-08 Nu DATA 6. 08 E-09 No DATA 1.99E-07 NO CATA 9.42E-06 tutb6 2.7SE-06 NO DATA 3. 48 E-0 7 NO DATA 5.31E-06 NO DATA 1.78E-04 AG110M 1 60E-07 1.4aE-07 8. 79 E-0 8 NO DATA 2.91E-07 NO CATA 6.04E-05 TE125M 2.65E-06 9.71E-07 3. 59E-0 7 S.06E-37 1.09E-05 NO DATA 1.07E-05 TE127" 6.77E-06 2.42E-06 8. 2 5 E-0 7 1.73E-06 2.75E-05 NO DATA 2.27E-05 TE127 1.10E-07 3.95E-08 2. 3 8 E-0 8 8.15E-08 4.48E-07 NO DATA 8.68E-06 TE129" 1.15E-05 4.29E-Co 1. A 2 E-0 6 3.95E-06 6.80E-05 NC CATA 5.79E-05 TE129 3 14E-08 1.18E-08 7. 6 3 E -0 9 2 61E-08 1.32E-07 NO DATA 2.375-08 TE131M 1.73E-06 8.46E-07 7.0 5 E-0 7 1.34E-06 S.57E-06 NO DATA 8.40E-05 TE131 1 97E-08 9.23E-09 6. 22 E-0 9 1.62E-08 5.63E-08 NC CATA 2.79E-C9 TE132 2.525-06 1.63E-06 1. 53 E-0 6 1 80E-06 1.57E-05 NO DATA 7.71E-05 t 130 7.56E-07 2.23E-06 8. 40E-0 7 1 89E-C4 3 48E-06 NO DATA 1.92E-06 1 131 4.16E-C6 5.95E-06 3. 41 E-0 6 1.95E-C3 1.02E-05 NO DATA 1.57E-06 1 132 2.03E-07 5.43E-07 1. 90E-0 7 1.90E-05 8.65E-07. NO DATA 1.02E-07 1 133 1.425-06 2.47E-06 7.53E-07 3.63E-04 4.31E-06 NO DATA 2.22E-06 I 134 1.06E-07 2.88E-07 1.03 E-0 7 4.99E-06 4.58E-07 NO DATA 2.51E-10 1 135 4.43E-07 1.16E-06 4. 2 5E -0 7 7.65E-05 1.46E-C6- NO DATA 1.31E-06 C5134 6.22E-05 1.48E-04 1. 21E-0 4 NO DATA 4.79E-05 1.595-05 2.59E-06 C5136 6.51E-06 2.575-05 1. 85 E-0 5 NO DATA 1.43E-05 1.96E 2.92E-06 C5137 7.97E-05 1.09E-09 7.14 E-0 5 NO DATA 3.70E-05 1.23E-05 2.11E-06 C5138 5.52E-08 1.09E-07 5.40E-08 NO DATA 8.01E-08 7.91E-C9 4.65E-13 SA139 9.70E-08 6.91E-11 2. 84 E-0 9 40 DATA 6.46E-11 3.92E-11 1 72E-07 DAVIS-BESSE, UNIT 1 B-3

d TABLE .2, Continued Page 3 of 3 th0ESTTON 005Z FAC7045 FCA ADULT $

tuREM Ps4 BC1 INGESTEDI T.a00Y THYR 010 <10NEY LUNG GI-LLI vuCLICE SONE L!v54 3.67t-09 1 46E-08 4.1SE-05 3A140 2.03C-05 2 55E-08 1. 3 3 E-0 6 - NO DATA 2.02E-11 2 225-17 4.71E-08 1.56C-11' 1 515-09 NO DATA 3.31E-11 94141 1.SSE-11 1.24E-11 1.00E-26 94142 2.13!-08 2 195-11 1. 3 *k-0 9 40 DATA NC CATA NO DATA 9.25E-05 LA140 2.500-09 1 262-09 3 3 AC-10 90 DATA NC OATA NO DATA 4.25E-07 LA142 1.20E-10 5 825-11 1 45E-11 NO DATA 2.94E-09 NO DATA 2.42E-05 CE141 9.36E-09 6.33E-09 7.19E-10 No Caft 1.35E-10 NO DATA 5.37E-10 No DATA 4.56E-05 OE143 1.e5E-09 1.228-06 1 65E-04 4.48E-07 2.04E-07 2. 62 E-0 8 NO CATA 1.21E-07 No DATA CE144 NO DATA 2.13E-09 NO DATA 4.03E-05 84143 9.20E-09 3 69E *.5eE-10

1. 5 sE-12 NO DATA 7.05E-12 NO DATA 4.33E-18 92144 3.01E-11 1.255-11 3.49E-05 N0147 6.29E-09 7.275-09 4.15 E-10 NO DATA 4.25E-09 NO DATA 3.01E-08 NO CATA NO DATA NO CATA 2 825-05 w 197 1.0 3E-0 7 8.etE-08 1.17C-10 o.455-1,1 NO DATA 3.65E-10 NO DATA 2.40E-05 49239 1.19E-09 1

i

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DAVIS-B' ESSE, Unit 1 B-4

'~

l

~ 4,

TABLE 3 SITE-RELATED INGESTION DOSE COMMITMDT FACTOR A

iT (mrem /hr per pCi/ml)

Page 1 of 2 t'UCLI DE BONE LIVER 790DY THYROID KIDNFY LUNG GT-LLI H-3 0.00E-01 1.76E+00 1.76E+00 1.76E+00 1.76E+00 1.76E+00 1.76E+00 C-14 3.13E+04 6.26E+03 6.26E+03 6 26E+03 4 26E+03 6 26E+03 6.26E+03 MA-24 4.32E+02 4.32E+02 4.32E+02 4.32E+02 4 32E+02 4.32E+02 4.32E+02 CP-51 0.00E-01 0.00E-01 1.31E400 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-41 1.36E+04 MN-56 0.00E-01 1.12E+02 1.98E+01 0.00E-01 1.42E+02 0.00E-01 3.37E+03 FE-55 6.98E+02 4.83E+02 1.13E+02 0.00E-01 0.00E-01 2 69E+02 0 7?E+02 FE-59 1.10E+03 2.59E+03 9.93E+02 0.00E-01 0.00E-01 7.24E+02 9.44E+03 CG-58 0.00E-01 1.00E+02 2.24E+02 0.00E-01 0.00E-01 0.00F-01 2 03E+03 CO-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 8.51E+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 25(+00 0.00E-01 2.82E+01 0.00E-01 9.54E+02 IN-65 2.32E+04 7.40E+04 3.34E+04 0.00E-01 4.95E+04 0.00E 4.e6E+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 1R-89 2.66E+04 0.00E-01 7.64E+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 1.89E+04 0.00E,-01 0 00E-01 1R-91 4.90E+02 0.00E-01 1 98E+01 0.00E-01 0.00E-01 0.00E-01 2.33E+03 9R-92 1.86E+02 0.00E-01 8 04E+00 0.00k-01 0.00E-01 0.00E-01 3 68E+03 v-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 i

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 Ns-97 0.00E-01 0.00E-01 0.00E-01 0 00E-01 0.00E-01 0.00E-01 -2 87E+03 1

l Calcult.tions made according to the methods specified in Section 1.2 of the Offsite i Dose Calculation Manual l l

B-5 i

e - .

TABLE 3' (continued)

SITE-RELATED INGESTION DOSE COMMITNENT 4 ACTOR A

- iT (mrem /hr per pCi/al)

Page 2 of 2 TBOUY THYROID KIDHEY LUNG- GI-LLI t'UCLIDE 80HE LIVER 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.bE+01 0.00E-01 2 05E+02 0.00E-01 6 86E+03 A3110M 3.22E+00 2 98E+00 1.77E+00 0.00E-01 5 85E+00 0.00E-01 1 21E+03 CD115M 0.00E-01 9.08E+02 2.47C+01 0.00E-01 7.20E+02 0.00E-01 3.82E+04 SB-124 4.78E+01 8.50E-01 1.89E+01 0.00F-01 0.00C-01 3 70E+01 1 35E+03 TE-132 2.45E+03 1.58E+03 1. 49 L+0 3 1.75E+03 1.53F+04 0.00E-01 7.50E+04 1-131 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 9.63E+00 9.60E+02 4.37E+01 0.00F-01 5 15E+00 1-133 7.17E+01 1 25E+02 3.f0E+01 1 83E+04 2.18E+02 0.00E-01 1.12E+02 T-134 5.35E+00 1 45E+01 5 20EfC0 2.52E+02 2.31501 0.00E-01 1.27E-02 I-135 1.24E+01 5.d6E+01 ,2 16E+01 3.86E+03 9.39E+01 0.00E-01 6 62E+01 cS-134 U.99E+05 7.11E+05 5.f1E+05 0.00E-01 2.30E+05 7.64E+04 1.24E+04 CS-136 3 13E+04 " .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-159 1 '4E+02' 2.40L+02 4.80E+01 0.00E-01 1 92E'02 0 00F-01 0.00E-01 8 A-139 ' 2.35E+00 1 67E-03 6.87E-02 0.00E-01 1.56E-03 9.48E-04 4.16E+00 8A-140 4.91E+02 6.16E-01' 3.22E+01 0.00E-01 2 10F-01 3.53E-01 1.01E+03-LA-140 1.86E-01 9.38E-02 2.48E-02 0 00E-01 0.007.-01 0 00E-01 6 89E+03 CE-141 1.59F-01 1.08E-01 1 22E-02' O.00,E-01 5.00E-02 0 00E-01 4.11E+02 1

CE-143,. 2 80E-02 2.07E401- 2.29E-03 0.00E-01 9 13E-03 0 00E-01 7.75E+02 CE-144 8.29E+00 3 47 +00 4.45E-01 0.00E-01 2 06E+00 0.00E-01 2.80E+03 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 2.97t+02 2.49E402 8.69E+01 0.00E-01 0 00E-01 0.00E-01 8 14E+04

'J-235 1 55E+04 0 00E-01 9.42E+02 0.00E-01 3.63E+03 0.00E-01 1.51E+03 U-238 1.49E+Et 0.00E-01 9.82E+02 0.00E-01 3 39E+03 0.00E-01 3 22E+03 NP-239 4 59E-02 4.51E-03 2.4*E-03 0.00E-01 1.41E-02 0.00E-01 9.25E+02 P-32 1.39E+06 8.64E+04 5.37E+04 .0 00E-01 0.00E-01 0.00E-01 1.56E+05

/

B-6 N W

.g.

TABLE 4 DOSE FACTORS FOR EXPOSURE TO A SEMI-INFINITE CLOUD OF NOBLE GASES i

Nuclide y-Body **(K) s-Skin **(L) y-Air *(M) B-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+0.1 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 1.5EE+04 7.29E403 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

Reference:

Regulatory Guide 1.109 Table B-1 and Section 2.1.1 cf the Offeite Dcae Calculation Manual

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E TABLE 5 (CONT) 5 s Page 2 of 12 E PATHWAY DOSE PARAMETER FACTORS FOR IMPLEMENTING 10 CFR PART 20 a

tg AGE i ADULT g PATHWAY 8 INIIALATION N HO ISOTOPE W. DODY THYROID BONE LIVER KIDNEY LUNG GI-LLI SKIN CRITICAL 36 NB-95 4.200:103 0.000E-01 1.408Ef04 7.016E403 7.735Ef03 5.040Ef0S 1.040E405 4.209Et03 LUNG 37 ND-97 2.04CE-02 0.00!E-01 2.224E-01 5.624E-02 6.544E-02 2.400Ef03 2.416E402 0.000E-01 LUNG 30 MO-99 2.294EIO1 0.0600-01 0.000E-01 1.200Ef02 2.912E402 Y.120Et04 2.4800605 0.000E-01 OI-LLI e 39 TC-99N 3.704E-02 0.000E-01 1.U32E-03 2.912E-03 4.414E-02 7.640Et02 4.160E403 0.000E-01 GI-LLI 40 T2-101 5.901E-04 0.000E-01 4.174E-05 6.014C-05 1.000E-03 3.992El02 1.0 LOC-11 0.000E-01 LUNG 41 RU-103 6.504Ct02 0.000E-01 1.520Et03 0.000E-01 5.832Et03 5.040Et05 1.101EtC5 0.000E-01 LUNG '

42 RU-105 3.112E-01 0.000E-01 7.904E-01 0.000E-01 1.016Ef00 1.096Et04 4.014E604 0.000E-01 GI-LLI 43 RU-106 U.720Et03 0.000E-01 6.912Et04 0.000E-01 1.336Et05 9.340Et06 9.120Et05 0.000E-01 LUNG 44 AG-110M 5.944Et03 0.000E-01 1.000El04 1.000Et04 1.960E104 1.6320606 3.024E105 0.000E-01 LUNG t 45 ED-115M 4.360Et03 0.bO0E-01 0.000E-01 1.960E405 1.504E105 1.40SE406 3.DiOCt05 0.000E-01 LONG

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E TABLE 5 (Cott)

M en Page 3 of 12 I

$ PATHWA( DOSE PARAMETER FACTORS FOR IMPLEMENTING 10 CFR PART 20 N

M AGE I ADULT ,

PATHWAY I INH /.L ATION '

gg E NO ISOTOPE W. BODY THVROID BONE LIVER KIDNEY LUNG GI-LLI SKIN CRITICAL 71 LA-142 7.720E-02 0.000E-01 6.032E-01 3.104E-01 0.000E-01 6.320Ef03 2.112E103 7.720E-02 LUNG 72 CE-141 1.520Et03 0.000E-01 1.992E104 1.352Ef04 6.264Ef03 3.616E405 1.200Et05 0.000E-01 LUNG 73 CC-143 1.52EEt01 0.000E-01 1.864Ef02 1.376Ef02 6.000E101 7.976E104 2.264Et05 0.000E-01 GI-LLI 74 CE-144 1.040Et05 0.000E-01 3.432Ef06 1.432E106 0.480EiOS 7.776Et06 8.160E405 0.000E-01 LUNG 75 Pls-143 4.610Et02 0.000E-01 9.360E103 3.752Ff03 2.160Et03 2.000E105 2.000E105 0.000E-01 Lut!G 76 PR-144 1.520E-03 0.000E-01 3.000E-02 1.210E-02 7.048E-03 1.016Et03 2.152E-00 0.000E-01 LUHG

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9 E TABLE 5 (CONT)

M vs Page 5 of 12 E PATHWAY DOSE PARAMETER FACTORS fog IhPLEMENTING 10 CFR PART 20 un i P8

  • AGE 1 TEEN

, PATHWAY : INHALATION t Ei H NO ISOTOPE W. DODY THYROID DONE LIVER KIDNEY LUNG GI-LLI SKIN CRITICAL "3

1 ;

I - M '36 ND-95 5.664Et03 0.000E-01 1.856Ef04 1.032Ef04 1.000Et04 7.512Ef05 9.480Et04 5.664Ef03 LONG l 37 ND-97 2.040E-02 0.000E-01 2.224E-01 5.624E-02 6.544E-02 2.400Et03 2.416Ef02 0.000E-01 LONG 38 MD-99 3.224Et01 0.000E-01 0.000E-01 1.688E102 4.112E402 1.536EtOS 2.680E105 0.002E-01 GI-LLI i a 39 TC-99H 4.992E-02 0.000E-01.1.384E-03 3.844E-03 5.760E-02 1.152Ef03 6.12CE403 0.000E-01 GI-LLI 40 TC-101 U.240E-04 0.000E-01 5.920E-05 8.400E-05 1.520E-03 6.672Et02 8.720E-07 0.000E-01 LUNG 41 RU-103 8.960Ef02 0.000E-01 2.104Et03 0.000E-01 7.432Et03 7.832E105 1.0000605 0.000E-01 LONG 42 RU-105. 4.336E-01 0.000E-01 1.120E400 0.000E-01 1.400Ct00 1.816E404 9.040Et01 0.000E-01 GI-LLI

'43 RU-106 1.240Et04 0.000E-01 9.840Et04 0.000E-01 1.904Et05 1.60GEf07 9.600E105 0.000E-01 LilHG 44 AG-110M 7.992E103 0.000E-01 1.384Et04 1.312Et04 2.504E104 6.752EiO4 2.72cEt05 0.000E-01 Luild s

  • 45 CD-115M- 6.360Et03 0.000E-01 0.000E-01 1.960Et05 1.504EiO5 1.400E606 3.040Et05 0.000E-01 LUNG '

g 46 SD-124 1.240Ef04 7.552Ef01 3.120Et04 5.880E602 0.000E-01 2.400Et06 4.0610405 0.000E-01 LbHG I 47 TE-125M 6.672Ef 02 1.400Ef 03 4.800E+03 2.240Ef 03 0.000E-01 5.360EiO5 7.504C101 0.000E-01 LUNG t 7l 48 TE-127M 2.104EiO3 4.304E103 1.800Et04 8.160Et03 6.536E404 1.656Et06 1.592[105 0.000C-01 LUHG 49 TE-127 4.416E-01 1.416Ef00 2.008Ef00 9.120E-01 7.200Ef00 1.120E404 0.000Et04 0.000E-03 GI-LLI 50 TE-129M 2.248E403 4.574E103 1.392Et04 6.504E103 5.192Ef04 1.976E t06 4.0 98Et05 0.000E- 01 LUMG  %

1 51 TE-129 1.760E-02 5.184E-02 7.096E-02 3.376E-02 2.654E-01 3.296E403 1.416Et03 0.000E-01 LuftG 52 TE-131H 4.024Et01 7.248Et01'9.840Ef01 6.000Ct01 4.392Et02 2.376Ef05 6.20CEt05 0.000E-01 UI-LLI h '.53 TE-131 5.040E-03 1.240E-02 1.576E-02 8.320E-03 6.176E-02 2.336Ef03 1.512EiO1 0.000E-01 LUNG i:

54 TE-132 2.192Et02 2.iS6Ef02 3.600Ef02 2.904Ef02 1.V52E103 4.480ClO5 4.632E105 0.000E-01 GI-LLI '

55 I-130 7.160E103 1.408Ef06 6.240Ef03 1.792E104 2.752Ef04 0.00JE-01 9.120E403 0.000E-01 THYROID 54 I-131 2.640Et04 1.464Et07 3.544Ef04 4.912Et04 0.400Et04 0.000E-01 6.400Et03 0.000E-01 THYh01D L 57 I-132 1.576E103 1.512Et05 1.592E603 4.376E103 4.720Et03 0.000E-03 1.272Ef03 0.000E-01 1Hyh01D 58 I-133 6.224E103 2.920E106 1.216E604 2.04GEt04 3.592Et04 0.000E-01 1.032E104 0.000E-01 THYROID ,

59 I-134 8.400Et02 3.950Et04 8.880Et02 2.320Ef03 3.664E103 0.000E-01 2.040El01 0.000E-01 THYkOID s 60.I-135 3.408EiO3 6.200E105 3.696Et03 9.440CiO3 1.430E404 0.000E-01 6.952Ef03 0.000E-01 THYl401D s 41 CS-134 5.400Et05 0.000E-01 5.024Ef05 1.120E606 3.7h2El05 1.464Et05 9.760El03 0.000E-01 L1VER "

62 CS-136 1.360Et05 0.000E-01 5.152Et04 1.936Ef05 1.104El05 1.776E104 1.090E104 0.000E-01 LIVER .

63 CS-137 3.112Et05 0.000E-01 6.704E105 8.400Ef05 3.040E105 1.200Et05 3.400E103 0.000E-01 LIVER 64 CS-138 4.464Et02 0.000E-01 4.656Ef02 8.560E102 6.624E102 7.872El01 2.704E-01 0.0000-01 LIVER

65 CS-139 1.112Et02.0.000E-01 2.040E102 2.904Et02 2.440E102 2.272Et01 0.000E-01 0.000E-01 LIVER  %

66 BA-139 3.096E-02 0.000E-01:1.336E100 Y.440E-04 8.0SOE-04 6.161E103 6.440E103 0.000E-01 LUNG

-67 BA-140 -3.520Et03 0.000E-01 5.472EiO4 6.704Et01 2.200EiO1 2.032Et06 2.20CEt05 0.000E-01 LuffG 60 BA-141 4.714E-03 0.000E-01 1.424C-01 1.056E-04 9.840E-05 3.200E103 7.464E-04 0.000F-01 Lut:0 .

69 BA-142 2.272E-03 0.000E-01 3.696E-02 3.704E-05 3.136E-05 1.912EiO3 4.792E-10 0.000E-01 LUNG 70 LA-140' 6.256Et01 0.000E-01 4.792Ef02 2.360Ef02 0.000E-01 2.144E105 4.072Et05 0.000E-01 GI-LLI

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y. TABLE 5 (CDR)

'N Page 6 of 12 Y

is y PATHWAY LOSE PARAMETER FACTORS FOR IMPLEMENTIttG 10 CFR PART 20 si AGE 1 TEEN

.@ FATHWAY 1 INHALATION NO ICOIDPE W. BODY THfRDID BONE LIVER KIDNEY t.UNG GI-LLI SKIN CRITICAL 71 LA-142- 1.056E-01 0.000E-01 9.600E-01 4.248E-01 0.000E-01 1.016Ef04 1.200E104 1.056E-01 GI-LLI 72 CE-141 2.14CEiO3 0.000E-01 2.840Ef04 1.896Ef04 0.800E403 6.136Et05 1.264Ef05 0.000E-01 LUNG '

73 CE-143 2.160EiO1 0.000E-01 2.456Et02 1.936E102 0.640E601 1.304EiO5 2.552Et05 0.000E-01 GI-LLI 74 CE-144 2.624Ef05 0.000E-01 4.088Ef06 2.024E406 1.200E106 1.336Ef07 0.640Ef05 0.000E-01 LUNG

  • , 75 PR-143 6.624Et02 0.000E-01 1.336E104 5.312E103 3.008Et03 4.032Et05 2.134Et05 0.000E-01 Lut!G i 76 PR-144 2.176E-03 0.000E-01 4.296E-02 1.760E-02 1.000E-02 1.752EiO3 2.352E-04 0.000E-01 LuttG 77 HD 147 5.120Et02 0.000E-01 7.864Et03 0.560Ef03 5.024Et03 3.720E105 1.024E105 0.000E-01 Lut!G 78 W-105 5.44DEt01 0.000E-01 1.560Et03 5.174Ef02 0.000E-01 4.456Et05 8.560Et04 0.000E-01 LuttG *

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4 79 W-107 3.432E100 0.000E-01 1.200EiO1 9.740EiOO O.000E-01 4.734Et04 1.76U2905 0.000E-01 GI-LLI 00 U-235 4.056E106 0.000E-01 0.000Et07 0.000E-01 1.072E107 3.920EtOD 3.072E105 0.000E-01 LUNG

-Y 81 U-238 4.G34Ef06 0.000E-01 7.664Et07 0.000E-01 1.741Et07 3.644EtOD 0.210E105 0.000E-01 LUNG

[* 02 NP-239 1.76CEt01 0.000E-01 3.384Et02 3.192Et01 1.000E102 6.488Et04 1.320Et05 0.000E-01 GI-LLI k

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> TABLE 5 (CONT)

$ Page 8 of 12 y -

@ PATitWAY DOSE PARAMETER FACTOIS FOR IMPLEMENTING 10 CFR PART 20 m -

0 AGE 1 CHILD

. PATHWAY 1 INitALATION f N NO ICOTOPE W. D0DY THYROID DONE LIVER KIDNEY LUNG GI-LLI SKIN CRITICAL 36'ND-95 6.549E603 0.000E-01 2.350E104 9.176Et03 0.621E103 6.142Ef05 3.700E404 6.549E403 LONG 37 NB-97 9.472C-03 0.000E-01 1.029E-01 2.601E-02 3.027E-02 1.110Ef03 1.117Et02 0.000E-01 LUNG 30 MD-99 4.255Et01 0.000E-01 0.000E-01 1.724Ef02 3.922E+02 1.354Et05 1.265Et05 0.000E-01 LutIG t i 39 TC-99M 5.~72E-02 0.000E-01 1.780E-03 3.402E-03 5.069E-02 9.509Et02 4.810Et03 0.000E-01 GI-LLI 40 TC-101 1.077E-03 0.000E-01 8.103E-05 0.510E-05 1.450E-03 5.846Et02 1.632E601 0.000E-01 LUNG 41 RU-103 1.073Et03 0.000E-01 2.060E403 0.000E-03 7.030E 6 03 6.623E t 05 4.477Et04 0.000E -01 LUNG t 42 RU-105 5.550E-01 0.000E-01 1.520E100 0.000E-01 1.343EtOO 1.591EIC4 9.953Et04 0.000E-01 GI-LLI 43 RU-106 1.691Et04 0.000E-01 1.362Ef05 0.000E-01 1.039E605 1.432Ef07 4.290Et05 0.000E-01 LUNG 44 AG-110M 9.139Et03 0.000E-01 1.687Et04 1.140Ct04 2.124Ef 04 5.476E 606 1.003E 9 05 0.000E -01 LUHG i 45 CD-115M 2.942E603 0.000E-01 0,000E-01 9.102E104 7.326Et04 6.510Et05 1.776LtOS 0.000E-01 LUNG 08 46'SD-124 5.735Et03 3.493Ef01 1.443Et04 2.723Ef02 0.000E-01 1.147Et06 1.800Et05 0.000E-01 LUNG h

La 47 TE-125M 9.139E102 1.921Ef03 6.734E603 2.327Ef03 0.000E-01 4.773C105 3.370Etot 0.000E-01 LU IG t 40 TE-127tl 3.027Et03 6.068Et03 2.486Et04 8.547E403 6.364Et04 1.480E606 7.1410104 0.000E-01 LUHG 49 TE-127 6.105E-01 1.941Ef00 2.771Et00 9.509E-01 7.067Et00 1.003Et04 5.62tEt04 0.000E-01 GI-LLI 50 TE-129M 3.011Et03 6.327E103 1.920EiO4 6.045Ef03 5.032Et04 1.761Et06 1.817Ct05 0.000E-01 LUNG -

51 TE-129 2.303E 02 7.141E-02 9.768E-02 3.497E-02 2.568E-01 2.934Et03 2.54YEt04 0.000E-01 GI-LLI 52 TE-131M 5.069Et01 9.768E+01 1.343EiO2 5.920Et01 3.996Et02 2.057Ef05 3.078E605 0.000E-01 GI-LLI 53 TE-131 6.506E-03 1.6?DE-02 2.172E-02 0.436E-03 5.003E-02 2.054Et03 1.332Ct03 0.000E-01 LudG &

St TE-132 2.634E4 02 3.175El02 4.810Ct02 2.723Ct02 1.772Ef 03 3.771Ct05 1.374El05 0.000E-01 LudG 55 I-130 0.436Et03 1.81aE106 0.177E103 1.639E404 2.416E104 0.000E-01 5.106Et03 0.000E-01 IHYROID 56 I-131 2.727Ct04 1.62tEt07 4.810Et04 4.010Et04 7.001E104 0.000E-01 2.042E103 0.000E-01 TilVROID .

57 I-132 1.076Et03 1.935EIO5 2.116Et03 4.070Et03 6.253E403 0.000E-01 3.201Et03 0.000E-01 THYROID

. 50 I-133 7.694EIO3 3.0100406 1.650Et04 2.031Et04 3.370Et04 0.000E-01 5.476E403 0.000E-01 TilYRO1D 59 I-134 9.953El02 5.06?EiO4 1.173Et03 2.161E103 3.300Et03 0.000E-01 9.546Et02 G.OOOC-01 litYkOID i 60 I-135 .4.144Ct03 7.918Et05 4.921Et03 8.732Et03 1.339E104 0.000E-01 4.410Et03 0.000E-01 TitYROID 61 CS-134 2.246Ef05 0.000E-01 6.512Et05 1.014Et06 3.301Et05 1.210E105 3.840Et03 0.000E-01 LIVER 62 CS-136 1.160Et05 0.000E-01 6.512Et04 1.709E405 9.546Ef04 1.454Et04 4.181Et03 0.000E-01 LIVER .

63 CS-137 1.284Et05 0.000E-01 9.065E105 8.251El05 2.023Et05 1.040Et05 3.619E103 0.000E-01 DONE 64 CS-130 5.550E102 0.000E-01 6.327Et02 8.399Et02 6.216E102 4.000Et01 2.697Et02 0.000E-01 LIVER 65 CS-139 5.113EtC1 0.000E-01 9.472Et01 1.343Et02 1.129E402 1.051Et01 0.000E-01 0.000E-01 LIVER s 66 DA-137 5.365E-02 0.000E-01 1.843Et00 9.842E-04 8.621E-04 5.772Et03 5.772Et04 0.000E-01 GI-LLI 67 BA-140 4.329Ct03 0.000E-01 7.400E104 6.475Et01 2.113Et01 1.713Et06 1.018EiOS 0.0bOE-01 LONG 68 DA-141 6.364E-03 0.000E-01 1.957E-01 1.092E-04 9.472E-05 2.919E103 2.753Et02 0.000E-01 LUNG .

69 BA-142 2.790E-03 0.000E-01.4.995E-02 3.600E-05 2.912E-05 1.643E103 2.742Et00 0.000E-01 LUNG 70 LA-140- 7.540Et01 0.000E-01 6.438Ef02 2.250E402 0.000E-01 1.020E105 2.257Et05 0.000E-01 GI-LLI

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> TABLE 5 (CONT) g Page 11 of 12 g PATifWAY DOSE FARAMETER FACTORS FOR IMPLEMENTING 10 CFR PART 20 m

m .

I ACE 1 INFANT PATt!MAY 1 INilALnT ION b,

y NO ISOTOPE W. DODY THYROID BONE LIVER KIDNEY LUNG GI-LLI CNIH CRITICAL

" 3.700Et03 0.000E-01 1.560Et04 4.426Et03 4.710Et03 4.700Et05 1.267E104 3.700E103 LUNG 36 flD-95 37 NL-97 3.504C-03 0.000E-01 3.092E-02 9.042E-03 1.145E-02 4.2000402 4.220Et01 0.000E-01 LONG 30 MO-99 3.231Et01 0.000E-01 0.000E-01 1.6522102 2.646Et02 1.340EtOS 4.072EIO4 0.000E-01 LONG 39 TC-99M 3.72iE-02 0.000E-01 1.397E-03 2.804E-03 3.100E-02 0.106L602 2.030Et03 0.000E-01 Gi-LLI 10 TC-101. 8.120E-04 0.000E-01 6.510E-05 0.232E-05 9.7060-04 5.030Et02 0.442EiO2 0.000E-01 GI-LLI 41 RU-103 6.790Et02 0.000E-01 2.016Ef03 0.000E-01 4.242E103 5.516E105 1.610Et04 0.000E-01 LUtlG GI-LLI 42 RU-105 4.102E-01 0.000E-01 1.224Ef00 0.000E-01 0.900E-01 1.560Et04 4.011El01 0.000E-01 LUNG 43 RU-106 1.OuGEt04 0.000E-01 0.60uE104 0.0CGE-01 1.045Et05 1.156Et0/ 1.630EtOS 0.000E-01 44 AG-110M 4.990ElO3 0.000E-01 9.902Et03 7.224LiO3 1.092El04 3.660Et06 3.30tEt04 0.000L-01 LudG 45 ED-115M 1.113E103 0.000E-01 0.000E-01 3.444Ef04 2.772Et04 2.464E105 6.720Et04 0.000E-01 LUtiG 08 46 SB-124 2.170E103 1.322Et01 5.460Et03 1.030Et02 0.000E-01 4.34GCt05 7.112E404 0.000E-01 LUttG M 47 TE-125M 6.580E402 1.624Et03 4.760E403 1.900Et03 0.000E-01 4.466Et05 1.291E404 0.000E-01 LUHG 00 40 1E-127M 2 0/2El03 4.072Et03 1.666EiO4 6.902E103 3.752EiO4 1.312Et06 2.750Et01 0.000E-01 LUuG 4? 1E-127 4.006E-01 1.040El00 2.226E100 9.534E-01 4.050E400 1.035Et04 2.134E104 0.000E-01 GI-LLI 50 TE-129M 2.226Et03 5.474E103 1.414E101 6.090Et03 3.17 bet 04 1.600E106 6.902EiO4 0.000E-01 Lung

$1 1E-129 1.076E-02 6.740E-02 7.002E-02 3.472C-02 1.750E-01 2.9?dE t 03 2.632f l01 0.000E-01 GI-LLI 52 TE-131M 3.626E101 0.932Et01 1.067Et02 5.502Et01 2.646Et02 1.90UE605 1.1y1Et05 0.000E-01 LUNG 53 TE-131 4.990E-03 1.502E-02 1.736E-02 0.21UE-03 3.990L-02 2.05dE105 0.21bCt03 0.000E-01 GI-LLI 51 TE-132 1.764L102 2.70eEt02 3.724E102 2.364Et03 1.035Et03 3.402E105 4.410E404 0.000E-01 LudG 55 I-130 5.572E403 1.596Et06 6.356Et03 1.30/Et04 1.526Etog 0.000E-01 1.960Lt03 0.000E-01 1HYROID 56 I-131 1.960Et04 1.404Et07 3.794Et04 4.430Et04 5.100Et04 0.000E-01 1.050L403 0.000L-01 TilY ROID 57 I-132 1.259Et03 1.694Et05 1.694Et03 3.542Et03 3.940Et03 0.000E-01 1.904Et03 0.000E-01 TitYROID 53 I-133 TitTh01D 5.6000603 3.556Et06 1.324Et04 1.910ElO4 2.240Et04 0.000E-01 2.156Et03 0.000E-01 iltVROID 59 I-134 6.650Et02 4.452Ef04 9.212Et02 1.076E403 2.004EIO3 0.000C-01 1.20YEt03 0.000E-01 60 1-135 2.772Et03 6.950Et05 3.064E103 7.602Et03 0.470Et03 0.000E-01 1.03tE403 0.000E-01 TliYROID 61 CG-134 7.440E104 0.000E-01 3.962Et05 7.020EIO5 1.904EIOS 7.V64Et01 1.3340603 0.000E-01 LIVLR 62 ES-136 5.292E604 0.000E-01 4.030Et04 1.315Et05 5.610EIO4 1.174C604 1.4200103 0.000E-01 L IV1 R 63 CS-137 4.550Et04 0.000E-01 5.400Et05 6.11ect05 1.722Et05 7.126Et04 1.334E603 0.000E-01 LIVER 64 CS-130 3.V74Et02 0.000E-01 5.05tEt02 7.012Et02 4.102EIO2 6.5300101 0.761Et02 0.000E-01 G1-LLI 65 ES-139 1.946Ef01 0.000E~01 3.504Et01 5.002E101 4.270Et01 3.974Et00 0.000E-01 0.000E-01 LIVER 66 UA-139 4.290E-02 0.000E-01 1.404Et00 9.042E-04 5.92?L-04 5.950EiO3 5.096Et04 0.000E-01 GI-LLI 67 DA-140 2.090Et03 0.000E-01 5.600Et04 5.600Et01 1.343Ef01 1.596EiO6 3.036Et04 0.000E-01 LUNG 60 BA-141 4.970E-03 0.000E-01 1.560E-01 1.070E-04 6.496E-05 2.460Et03 4.746EiO3 0.000E-01 GI-LLI 69 DA-142 1 960L-03 0.000E-01 3.976E-02 3.30iE-05 1.904E-05 1.554Ef03 6.930E602 0.000E-01 LUNG 70 LA-140 5.152EiO1 0.000E-01 5.054Et02 2.002EiO2 0.000E-01 1.600E405 0.404E404 0.000E-01 LUNG s

j! - TABLE 5 (CONT)

-U Page 12 of 12

$s PATHWAY DOSE PARAMETER FACTORS FOR IMPLEMENTING 20 CFR PART 20 E

H AGE I INFANT d

PATHWAY 3 INHALATION w

t!O ISOTOPE W. 00DY THYROID BONE LIVER KIDNEY LUNG GI-LLI SKIN CRITICAL 71 LA-142 9.044E-02 0.000E-01 1.030Ef00 3.766E-01 0.000E-01 0.218Ef03 5.950Ef04 9.044E-02 GI-LLI 72 EE-141 1.900Ef03 0.000E-01 2.772E104 1.666Ef04 5.250El03 5.166Ef05 2.154E604 0.000E-01 LUNG

/3 EE-143 2.212Ef01 0.000E-01 2.926E402 1.932Ef02 5.642E101 1.162Ef05 4.970El04 0.000E-01 LUNG 74 CE-144 1.764Et05 0.000E-01 3.192EIO6 1.211E406 5.374Ef05 9.042E106 1.40tE105 0.000E-01 LUNG 75 PR-143 6.906Et02 0.000E-01 1.400Ef04 5.236E103 1.974Ef03 4.326Et05 3.724E101 0.000E-01 LONG 74-PR-144 2.400E-03 0.000E-01 4.700E-02 1.040E-02 6.720E-03 1.610Et03 4.20iEl03 0.000E-01 GI- LLI 77 ND-147 4.99dEf02 0.000E-01 7.930Ef03 8.134E103 3.150EiO3 3.220E605 3.122E101 0.000E-01 LudG

.70 W-105- 9.534Et00 0.000E-01 2.730E102 9.053El01 0.000E-01 7.790E404 1.490E104 0.000E+01 LUttG Y' 79 W-187- 3.122E100 0.000E-01 1.296E101 9.016Ef00 0.000E-01 3.962Ef04 3.S56El01 0.000E-01 Lut!G

,)) 00.U-235 U.4YDEt05 0.000E-01 1.400Ef07 0.000E-01 3.276E406 6.060Et07 6.776El04 0.000E-01 LUNG 01 U-230 02 tlP-23V 7.930E105 0.000E-01 1.341E107 0.000E-01-3.052Ef06 6.412E107 1.412Et05 0.000E-01 LUNG 1.076Ef01 0.000E-01 3.710Et02 3.310Ef01 6.622E101 5.950EiO4 2.492Et04 0.000E-01 LutlG W

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DAVIS-BESSE, UNIT 1 B-20

) P

c TABLE 6 (CO!TI)

$ Page 2 Of 39 Y

y PATHWAY DOSE PARAMETER FACTORS FOR INPLEMENTING 10 CFR PART 50 E AGE 1 ADULT PA!!!UAY 1 COW HILK y ffO ISOIOPE W. DODY THYROID DONE LIVER KIDNEY LUNG GI-LLI SKIN CRITICAL 36 NB-95 2.460C f 04 0.000E-01 0.253El04 4.591Ef 04 4.530E t04 0.000E -01 2.704Et 03 0.000E-01 GI-LLI 37 NB-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 38 NO-99 4.705Et06 0.000E-01 0.000E-01 2.473EtO7 5.600EtO7 0.000E-01 5.732E407 0.000C-01 GI-LLI 39 TC-99H 1.216Et02 0.000E-01 3.370Ef00 9.545Ef00 1.450EiO2 4.677Ef00 5.640C603 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. D0DY 41 RU-103 4.390Ef02 0.000E-01 1.021Et03 0.000E-01 3.096Et03 0.000E-01 1 192Et05 0.000C-01 GI-LLI 42 RU-105 3.42SE-04 0.000E-01 B.676E-04 0.000E-01 1.121E-02 0.000E-01 5.307E-01 0.00CC-01 GI-LLI 43 RU-106 2.582Et03 0.000E-01 2.040Ef04 0.000E-01 3.939Et04 0.000E-01 1.321E806 0.000E-01 GI-LLI

'44 AG-110H 3.200Ef07 0.000E-01 5.025E107 5.300E107 1.059E100 0.000E-01 2.199Et10 0.000E-01 GI-LLI 15 CD-115H 3.901LiO4 0.Oo0E-01 0.000E-01 1.246Et06 9.004El05 0.000E-01 5.210L607 0.000E-01 GI-LLI W' 46 SB-124 1.021E t07 6.243E f 04 2.50 4E 607 4.073E105 0.000E-01 2.005E t 07 7.310Et 00 0.000E-01 GI-LLI h 47 TE-125M 2.103Cf06 4.902Et06 1.630E107 5.905Et06 6.629Et07 0.000E-01 6.507EtO7 0.000E-01 KIDHEY Fd 40 TE-127H 5.579Ef06 1.170Et07 4.570E107 1.636Ef07 1.060El00 0.000E-01 1.535Et00 0.000E-01 NIbHEY 4? TE-127 1.142Ef02 1.93/Et02 6.463Ef02 2.393C402 2.714Et03 0.000E-01 5.250E404 0.000E-01 GI-LLI 50 IE-129M 9.511Et06 2.064Et07 6.OO9Et07 2.242Ef07 2.500Ef00 0.000E-01 3.024E100 0.000E-01 GI-LLI 51 TE-129 0.203E-11 2.504E-10 3.367E-10 1.2650-10 1.415E-09 0.000E-01 2.541E-10 0.000E-01 KIDNEY 52 1E-131H 1.4700405 2.795Et05 3.600El05 1.744Et05 1.707Ef06 0.000E-01 1.752E407 0.000E-01 GI-LLI 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 KIDNEY 51 TE-132 1.452E106 1.709Ct06 2.392Et06 1.547Et06 1.4f0Cl07 0.000E-01 7.31YEt07 0.000E-01 GI-LLI 55.I-130 4.900El65 1.070E100 4.270E405 1.262E106 1.969C106 0.000E-01 1.0060606 0.000E-01 IltYh01D

, 56 I-131 2.420Ef00 1.309Et11 2.963E100 4.237Ef00 7.244El00 0.000E-01 1.1100100 0.000E-01 linROID 57 I-132 1.405E-Of 1.405Et01 1.501E-01 4.015E-01 6.397E-01 0.000E-01 7.543C-02 0.000E-01 111YROID 50 I-133 2.056Et06 9.910Et00 3.077Et06 6.743Et06 1.177Et07 0.000E-01 6.061Et06 0.000E-01 TilYRUID

'59 I-134 1.034E-12 0.005E-11 1.007E-12 5.120E-12 0.155E-12 0.000E-01 4.449E-15 0.000E-01 TitVROID 60 I-135 1.222Et04 2.104Ef06 1.265E104 3.312Et04 5.311E104 0.000E-01 3.741E401 0.000E-01 TilYko t D 61 CS-134 1.100Et10 0.000E-01 5.652Et09 1.345Et10 4.353E109 1.445Et09 2.351E100 0.000E-01 LIVER 62 CS-136 7.425Et00 0.000E-01 2.613E400 1.032E109 5.739Ef00 7.067E107 1.172E400 0.000E-01 LIVER 63 CS-137 6.613E109 0.000E-01 7.301E109 1.00 vet 10 3.427E40V 1.139E109 1.954Et00 0.000E-01 LIVER 64 CS-130 1.013E-23 0.000E-01 1.036E-23 2.045E-23 1.503E-23 1.404E-21 0.724E-29 0.000E-01 LIVER 45.CS 439 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 66 DA-139 1.2?OE-09 0.000E-01 4.434E-00 3.159E-11 2.953E-11 1.792E-11 7.063E-00 0.000E-01 GI-LLI 67 UA-140 1.760Ef06 0.000E-01 2.606El07 3.374Et04 1.147E104 1.932Et04 5.531El07 0.000E-01 GI-LLI 60 LA-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 49 BA-142 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 70 LA-140 6.025C-01 0.000E-01 4.523Et00 2.200E400 0.000E-01 0.000E-01 1.674E105 0.000E-01 GI-LLI s ,

l 1 ;*

l I -E TABLE 6 (CONT)

Page 3 of 39 i

y On 50 g PAllfWAY DOSE PARAMETER FACTORS FOR IMPLEMENTING 10 CFR PART AGE 1 ADULI zg- PATitWAY 1 CDW MILK H

H No.ISOTOFE W. DODY IHYROID DONE LIVER t:IDNEY LUNG GI-LLI EKIN CRITICf.L e

71 LA-142 1.030E-12 0.000E-01 9.161E-12 4.165E-12'O.000E-01 0.000E-01 3.042E-00 0.000E-01 GI-LLI 72 EE-141 3.715Ef02 0.000E-01 4.044E103 3.276EiO3 1.521EiO3 0.000E-01 1.252E107 0.000E-01 GI-LLI 73 EE-143 3.406Et00 0.000E-01 4.162Et01 3.078Ef04.1.355E101 0.000E-01 1.150Et06 0.000E-01 GI-LLI 74 CE-144 1.920E104 0.000E-01 3.577E605 1.495Et05 0.860El04 0.00nE-01 1.209El00 0.000E-01 GI-LLI 75 PR-143 '7.023E100 0.000E-01 1.570C102 6.331E101 3.654E101 0.000E-01 6.914E105 0.0000-01 W. GI-LLI DODY 76 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 77 ND-147- 6.50?C100 0.000E-01 9.412E101.1.000Ef02 6.359Et01 0.000E-01 5.222E905 0.000E-01 GI-LLI

' 78 W-105 4.539Etoi 0.000E-01 1.298E406. 4.315E105 0.000E-01 0.000E- 01 4.9070407 0.000E-01 GI-LLI i l

- 79 W-187 1.915Ef03 0.000E-01 6.551E103 5.476E103 0.000L-01 0.000E-01 1.794E606 0.000E-01 GI-LLI 80 U-235 1.070Et08 0.000E-01 3.099Et09 0.000E-01 7.226Ef08 0.000E-01 3.010E608 0.000E-01 BONE I 08 ' 81 U-238 1.758Et00 0.000E-01 2.964E109 0.000E-01 6.743Et08 0.000E-01 6.415Et08 0.000E-01 B0ttE d2 82 tiP-239 1.979E-01 0.000E-01 3.652Ef00 3.591E-01 1.120E100 0.000E-01 7.365C404 0.000E-01 GI-LLI 64, -

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t TABLE 6 (CONT)

D-r4 Page 5 of 39 7

. os PATHWAY DOSE PARAMETER FACTORS FOR IMPLEMENTING 10 CFR PART 50

$ AGE 1 TEEN ~

. PATHWAY 1 COW MILK HQ ISOTOPE W. D0DY TilYROID BONE LIVER KIDNEY LUNG SKIN GI-LLI CRITICAL et 36 H8-95 4.297E404 0.000E-01 1.407E405 7.007E104 7.567Et04 0.000E-01 3.339E600 0.000E-01 GI-LLI 37 itD-97 6.992E-13 0.000E-01 7.587E-12 1.915E-12 2.234E-12 0.000E-01 7.061E-09 0.000E-01 GI-LLI 30 MD-99 0.514Ef06 0.000E-01 0.000E-01 4.464Et07 1.022Et00 0.000E-01 7.996El07 0.000E-01 KIDNEY 39 TC-99M .2.117Et02 0.000E-01 5.050Ef00 1.634L101 2.435E!O2 9.070EtOO 1.073E604 0.000E-01 GI-LLI 40 TC-101 0.000E-01 0.OOOE-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 W. LODY I 41 00-103 7.761Ef02 0.000E-01 1.016Ef03 0.000E-01 6.101Ef03 0.000E-01 1.517E105 0.000E-01 GI-LLI 42 RU-105< 6.150E-04 0.000E-01 1.505E-03 0.000E-01 1.999E-02 0.000E-01 1.279El00 0.000E-01 GI-LLI

[. 43 kil-106 4.729Ef03 0.000E-01 3.752Ef04 0.000E-01 7.237El04 0.000E-01 1.000E606 0.000E-01 GI-LLI

! 14 AG-liOM 5.593Ef07 0.000E-01 9.629Ef07 9.113EtC7 1.730E608 0.000E-01 2.560Et10 0.000E-01 GI-LLI i- 45 CD-115M 46 SG-124 5.136Et04 0.000E-01 0.000E-01 1.607Ef06 1.275Et06 0.000E-01 6.7610407 0.000E-01 GI-LLI Ds 47 TE-125M 1.317Et07 0.054Et04 3.334Ef 07 6.20SEf 05 0.000E-01 2.506Et 07 9.132E 600 0.000E-01 GI-LLI i b 4.010Ef04 8.397Et06 3.006Et07 1.CD3E407 0.000E-01 0.000E-01 8.067E407 0.000E-01 GI-LLI l 40 TE-127M 1.003E107 2.007Ef07 0.430Et07 2.9V3EIO7 3.4200f00 0.000E-01 2.100El90 0.000E-01 KIDffEY S' - 49 TE-127 50 TE-129M 2.45HEf02 0.520E402 1.235Et03 4.377El02 5.003Et03 0.000E-01 9.536Et04 0.000E-01 GI-LLI 51 TE-12V 1.740EiO7 3.547E907 1.099Et00 4.079Ll07 4.599El00 0.000E-01 4.127Et00 0.000E-01 KIDitEY 52 TE-131tl 1.500E-10 4.420E-10 6 199E-10 2.311E-10 2.601E-09 0.000E-01 3.390E-09 0.000E-01 GI-LLI b3 TE-131 2.627Et05 4.736Ef05 6.566Et05 3.149Et05 3.203Et06 0.000E-01 2.527E607 0.000E-01 GI-LLI 54 IE-132 0.000E- 01 0.000E-01 0.000E-01 0.000E-01 3. 490E-32 0.000E-01 0.000E-01 0.000E-01 KIDHEY 55 I-130 2.510C606 2.051E406 4.275E106 2.707Et06 2.597Et07 0.000E-01 0.574EtO7 0.000E-01 01-LLI 56 I-131 0.639EtO5 1.774Ef08 7.521Ef05 2.176E106 3.351E606 0.000E-01 1.672Et06 0.000E-01 TitYROID 57 1-132 4.043Et00 2.196Et11 5.376E100 7.526E100 1.296E109 0.000E-01 1 40VCt00 0.000E-01 TliYROID 50 I-133

2. BODE-01 2.347f101 2.662E-01 6.965E-Of 1.097E100 0.000E-01 3.034E-01 0.000E-01 IHYROID 59 1-134 1.663E606 1.677L109 7.000Et06 1.201Ef07 2.106Ef07 0.000E-01 9.003Et06 0.000E-01 TilYR0lb 60 I-13b 3.194L-12 1.482E-10 3.355E-12 0.092E-12 1.402E-11 0.000E-01 1 172E-13 0.000E-01 TilVRUID .

61 ES-134 2.144Ef01 3.721E106 2.240Et04 5.705Et04 9.137Et04 0.000E-01 6 411El04 0.000E-01 111YROID

'62 CS-136 1.072Ef10 0.000E-01 9.015E109 2.310Lt10 7.340Et09 2.002Et09 2.073El00 0.000E-01 LIVER 63 EG-137 1.176Et0? O.000E-01 4.419El00 1.750El09 9.529Et03 1.502Et00 1.409El00 0.000E-01 LIVER i 61 C5-130 6.202L109 0.000C-01 1.330Et10 1.7010110 6.05YEf09 2.3546609 2.533Et00 0.000E-01 LIVER 65 ES-139. 1.001E-23 0.000E-01 1 879E-23 3.607E-23 2.663E-23 3.099E-24 1.637E-26 0.000E-01 LIVER 66 DA-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. DubY s 67 0A-140 2.33?E-09 0.000E-01 0.19VL-00 5.769E-11 5.430E-11 3.Y76E-11 7.314E-07 0.000C-01 GI-LLI 43 UA-lil 3.124Et06 0.OOOE-01 4.049Et07 5.941Et01 2.015E104 3.Y95Et01 7.470E407 0.COOC-01 GI-LLI 69 DA-142 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 .

70 LA -140 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 1.062E100 0.000E-01 0.124El00 3.V92Et00 0.000E-01 0.000E-01 2 292E105 0.000E-01 GI-LLI s

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g TABLE 6 (CONT) l!

m Page 7 of 39 e

y PAlifWAY DOSE PARAMETER FACTORS FOR IMPLEMEt! TING 10 CFR PARI 50 m

m AGE ; CHILD PATilWAY 1 COW NILN H0 ISOTOPE W. 00DY Tl4YROID DONE LIVER KIDHEY LUNG GI-LLI SKIN CRITICAL N

1 ll-3 1.570E403 1.570E403 0.000E-01 1.570Ef03 1.570Et03 1.570Et03 1 570Et03 1.570Et03 W. BODY 2 C-14 3.294Et05 3.294Et05 1.647Et06 3.294Et05 3.294Et05 3.291Et05 3.294EtO5 3.294E+05 LONE 3 NA-24 0.932E606 0.932Et06 8.932Et06 0.932Et06 0.932Et06 0.932E406 0.932Et06 0.000E-01 W. D0DY 4 P-32 2.VY9E409 0.000E-01 7.701Et10 3.641E409 0.000E-01 0.000E-01 2 150E409 0.000E-01 DONE 5 SC-46 1.0700602 0.000E-01 1.910Et02 3.744Et02 3.466E402 0.000E-01 1.406Et06 0.000E-01 GI-LLI 6 CR-51 1.019E405 5.654Et04 0.000E-01 0.000E-01 1.545E404 1 032E405 5.402Et06 0.000E-01 GI-LLI 7 MM-54 5.505Et06 0.000E-01 0.000E-01 2.097Et07 5.079E406 0.000E-01 1.760E407 0.000E-01 LIVER 0 MH-56 2.002E-03 0.000E-01 0.000E-01 1.277E-02 1.544E-02 0.000E-01 1.050L100 0.000E-01 GI-LLI 9 FE-55 1.03/Et07 0.000E-01 1.110Et00 5.930Z607 0.000E-01 3.351E407 1.090E307 0.000E-01 bOHC 10 FE-59 9.606EtO7 0.000E-01 1.202E400 1.944E900 0.OOOE-01 5.637E407 2 0250100 0.000E-01 GI-LLI W 11 CO-50 3.719E407 0.000E-01 0.000E-01 1.215Et07 0.000E -01 0.000E-01 7.080E4 07 0.000E-01 GI-LLI b 12 CO-60 1.273Et00 0.000E-01 0.000E-01 4.310Et07 0.000E-01 0.000E-01 2.3V10100 0.000E-01 GI-LLI

  • 13 HI-59 0.985Et07 0.000E-01 5.306Ef08 1.047Ct00 0.000E-01 0.000E-01 3.003EtO7 0.000E-01 EONE 14 HI-63 1.00GE409 0.000E-01 2.964Et10 1.587EtO9 0.000E-01 0.000E-01 1.069E400 0.000E-01 BUNE 15 NI-65 9.107E-02 0.000E-01 1.657EiOO 1.560E-01 0.000E-01 0.000E-01 1.9110101 0.000E-01 GI-LLI 16 CU-64 4.465EF04 0.000E-01 0.000E-01 7.392E404 1.706Et05 0.000E-01 3.4700106 0.000E-01 GI-LLI 17 ZH-65 6.047Et09 0.000E-01 4.132E109 1.101Et10 6.937Et09 0.000E-01 1.933El09 0.000E-01 LIVER 18 ZH-69 2.950E-12 0.000E-01 2.214E-11 3.200E-11 1.9 41C-11 0.000E-01 2.017E-09 0.00')E-01 GI-LLI 19 DR-03 4.617E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000L-01 0.000E-01 0.000E-01 W. BODY 20 DR-04 5.739E-23 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 W. DODY 21 FR-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. DODY 22 RD-04 5.307Et09 0.000E-01 0.000E-01 0.760EtO9 0.000E-01 0.000E-01 5.635Et00 0.000C-01 LIVER 23 RB-d3 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 24 RC-09 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. DubY 25 CR-09 1.090Et03 0.000E-01 6.416Et09 0.000E-01 0.000E-01 0.000E-01 2.561Et00 0.000E-01 PONE 26 LR-90 2.833Et10 0.OOOE-01 1.117Et11 0.000E-01 0.000E-01 0.000E-01 1.505Et09 0.000E-01 DONE 27 SR-91 4.005E403 0.000E-01 1.294E105 0.000E-01 0.000E-01 0.000E-01 2.053Et05 0.000E-01 GI-LLI 2'3 CR-92 0.663E-02 0.000E-01 2.162Ef00 0.000E-01 0.000E-01 0.000E-01 4.094E101 0.000C-01 GI-LLI 29 Y-90 0.637E100 0.000E-01 3.227Et02 0.0000.-01 0.000E-01 0.000E-01 9.107E105 0.000E-01 GI-LLI 30 Y-9111 1.0150-20 0.000E-01 2.071E-19 0.000E-01 0.000E-01 0.000E-01 5.622C-16 0.00CE 01 GI-LLI 31 Y-91 1.044Ct03 0.000E-01 3.904Et04 0.000E-01 0.000E-01 0.000E-01 5.200E106 0.000E-01 GI-LLI 32 Y-92 /.226E-06 0.000E-01 2.525E-04 0.000E-01 0.000C-01 0.000E-01 7.296Et00 0.000E-01 GI-LLI

'33 Y-93 2.001E-02 0.000E-01 1.0i?E100 0.000E-01 D.000E-01 0.000E-01 1.565C604 0.000E-01 GI-LLI 34 ZR-95 7.530Et02 0.000E-01 3.052Et03 0.460E402 1.212Et03 0.000E-01 0.033Et05 0.000E-01 GI-LLI 35 ZR-97 1.633E-01 0.OOOE-01 1.915Et00 2.767E-01 3.972E-01 0.000E-01 4.191Et04 0.000E-01 GI-LLI O

L Y DDDDDD Y YY A LLEL0LLLLLL,YIYIIIIII IIYIDIIIIII I II I DI DDI C LLELLLLO0OUOORR ROL OOL I LLNL1LLLLLLENLMLLLLRI l

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1 1111111111111111111111111111111111 00000000000000000000000000000000000 EEEEEEE0ECEEEEEEEEEEEEEEEEEEEEEEEEE N 0000000000000000000000000000000^000 I 000000000000000000000000000O0000000 R

S 000000000000000000000000000.O.0000000 00000000000000000000000000000000000 09741506070705037176006240703157115 0 000000001000000003O000010000200O000 5 I t - f t - l t t t 6 t 1 1 t I lt t 6 - t ti l - - - I - - 4 L EEECEEEEL0EEEEEECEEEEEEEEEEEEEELEEE T L 309V00570021 1 7102V737231 5292603O005 _

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0 1 G EEEEEEEC"EEELEEEEEEEEEEEEEEEEEEEEEEE 000O0000004000000000000001203063000 M 000J0000003000000000000003919021000 G U 00030000001000000000000001167031000 N

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3 R 11130131210050745545213211114093000 _

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111111 11114773796260119041111111111 E D 000000000000000003001 0O100000000000 G I - - - - - - - - - - tt t 6l t1tti - t - - - - - - - - - -

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5 Page 9 of 39 li $s

{ $

PATiiWAY DOSE PARAMETER FACTORS FOR IMPLEMENIING 10 CFR PART 50 Si AGE 1 EllILD g

H F ATitWAY 1 COW MILK r .

CRITICAL NO ISOTOPE W. BODY TilYROID BONE LIVCR KIDNEY LUNG GI-LLI SNIN 71 LA-142 3.904E-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 1.620E403 0.000E-01 2.107Ef04 1.091Et04 4.701Et03 0.000E-01 1.341El07 0.000E-01 GI-LLI ,

73 CE-143 1.474E101 0.000E-Os 1.877Et02 1.010Ef05 4.270E401 0.000E-01 1.490Et06 0.000E-01 GI-LLI l

'74 CE-144 8.660Ef04 0.000E-01 1.623Et06 5.087Et05 2.816E105 0.000E-01 1.326Et00 0.000E-01 GI-LLI 75 PR-143 3.561Et01 0.000E-01 7.177E102 2.155E102 1.167E102 0.000E-01 7.744Et05 0.000E-01 GI-LLI 76 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 HD-147 2.700Et01 0.000E-01 4.444E402 3.600Et02 1.975E102 0.000E-01 5.703EtOS 0.000E-01 GI-LLI 78 W-155 4.032E104 0.000E-01 1.382E106 4.594Cf05 0.000E-01 0.000E-01 5.300Et07 0.000E-01 GI-LLI j8 79 W-187 7.719Et03 0.000E-01 2.90$Et04 1.720E104 0.000E-01 0.OOOE-01 2.417E406 0.000E-01 GI-LLI N DO U-235 1.999Et00 0.000E-01 3.299Et09 0.000E-01 7.693Et00 0.000E-01 3.213Et03 0.000E-01 bot!E 08 81 U-230 1.072El00 0.000E-01 3.155Et09 0.000E-01 7.199E408 0.000E-01 6.029Et03 0.000E-01 B0tlE

-82 ffP-239 0.657E-01 0.000E-01 1.715Et01 1.232Et00 3.561Et00 0.000E-01 v.115E604 0.000E-01 GI-LLI f

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S 3. U. 0 0 0 0. O. 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 26000000000000000000000000000000000 0

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R O 357921727877091 50111102111111111131 6 o F 0000000000000O0O11000130000000000O0 414ft - f - t t t4 ti - it - - - - t - - - - - - - - - - - i-0 S R EEEEEEEEEEEEEECEEEEEEE0EEEEEEEEEEEE 1 R E 205240069005701 73300031000000000070 E O V 00534002213146730900021000000000065 L e T I 38547091794001909400023000000000069 B g C L A a A 26193033032012311800021000000000016 T P F 1671211100110001911111110i502944030 R 0001000000000100010000001l000100000 E - tftt - - - +4 - - ttf -{ - - - - - - - tlt t l - t - 1 tt T EEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEE E E 06530O00130063000700000086673877714 M N 02501C00540089005100000051992026345 A O 02569000320034505700000022650033200 R B A 03111000120053305400000011246475264 P "

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TO NC A E F1 P N O 4 614659809354593456099012 M 57 IY T 4224555555656666600000089V901 12399 A O 31 - 3- - - - - - - - - - - - - - - - - - - - - - - - 99999 - -

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A 5602000130214653342321311 31 59042004 P

111 1111 11 1 4?0309627S22907111 1111111 E D 0000000000000000030O100100000000000 S I - - - - - - - - - - tt tl 6 - 4 - t tt1 t - 6 - - - - - - - - - -

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f 537213340477737062669171499131071 10 A Y 0100000000O0000103000001 00002000000 P D t 1 - t t f ttt t1 - t - ttt - 1

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G Page 14 of 39

"$(4 PAillWAY DOSE PARAMETER FACTORS FOR IMPLEMENTING 10 CFR PART 50 M '

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H PATitWAY I INilALATIDM ' l NO ISOTOPE W. BODY THYROID DONE LIVER KIDNEY LUNG GI-LLI SKIN CRITICAL

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36 ND-95 4.20 Lit 03 0.000E-01 1.408E604 7.014Et03 7.734Et03 5.040Et05 1.040Et05 4.208Et03 LUNG 37 HD-97 2.040E-02 0.000E-01 2.224E-01 5.624E-02 6.544E-02 2.400Et03 2.416E402 0.000E-01 LUNG 30 MD-99 2.296E101 0.000E-01 0.000E-01 1.200Et02 2.912E402 9.120E104 2.400E605 0.000E-01 GI-LLI e 39 TC-99M 3.7040-02 0.000E-01 1.032E-03 2.912E-03 4.414E-02 7.640E402 4.140El03 0.000E-01 GI-LLI 40 IC-101 5.904E-04 0.000E-01 4.176E-05 6.016E-05 1.000E-03 3.992E102 1.000E-11 0.000E-01 LUNG 41 3U-103 6.501E102 0.000E-01 1.520EiO3 0.000E-01 5.832E103 5.040Et05 1.1010105 O.000E-01 LONG (

42 RU-105 3.112E-01 0.000E-01 7.904E-01 0.000E-01 1.016E400 1.096Et04 4.016E604 0.000E-01 GI-LLI

'43 RU-106 8.720E103 0.000E-01 6.912Ef04 0.000E-01 1.336Et05 9.360E106 9.120Et05 0.000E-01 LUNG 44 AG-110M 5.944El03 0.OOCE-01 1.000Et04 1.0000104 1.968E104 4.632Et06 3.024Et05 0.000E-01 LUNG g 15 CD-115M 6.360Et03 0.000E-01 0.000E-01 1.560Et05 1.504Et05 1.400EiO4 3.040E605 0.000E-01 LUNG

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57 I-132 1.160E t 03 1.14 4E 605 1.160E l03 3.256E t 03 5.1814E t 03 0.000E-01 4.064Ct02 0.000E-01 lilYRUID 50 I-133 4.5?OEIO3 2.152E106 0.640Et03 1.400Et04 2.504LiO4 0.000E-01 8.0000103 0.000E-01 lil(ROID 59 I-134 6.1520t02 2.901E104 6.440E102 1.720EiO3 2.752Et03 0.000E-01 1.000Et00 0.000E-01 TiliNOID t 40 I-135 '2.568Ef03 4.400Ef05 2.600E603 6.904Et03 1.112El04 0.000E-01 5.248El03 0.000E-01 THYROID 61 CS-134 7;200Et05 0.000E-01 3.720Et05 0.400E105 2.072Et05 9.760E104 1.040Et04 0.000E-01 LIVER 62 ES-134 1.101E t OS 0.000E-01 3.904E t04 1 464E105 0.540EiO4 1.200Et04 1.160Et04 0.000E-01 LIVER s. i 43 CS-137 4.200Et05 0.000E-01 4.704E105 4.200EtOS 2.224El05 7.520Et01 8.400E103 0.000E-01 LIVER 44 CS-130 3.240E602 0.000E-01 3.312Et02 6.200E102 4.000Cl02 4.056Et01 1.064E-03 0.000E-01 LIVER, 65 CS-139 1.112Et02 0.000E-01 2.040E102 2.901EIO2 2.440E102 2.27?Ef01 0.000E-01 0.000E-01 LIVER L i 66 1:A-139 2.736E-02 0.000E-01 9.360E-01 6.456E-04 6.224E-04 3.740Ct 03 0.960E4 02 0.000E-01 1.UNG 67 DA-140 2.560Et03 0.000E-01 3.904El04 4.901El01 1.672Et01 1.272E104 2.104Et05 0.000E-01 LUNG 40 DA-141 3.340E-03 0.000E-01 1.000E-01 7.520E-05 7.000E-05 1.936Et03 1.160E-07 0.000E-01 LUNG L t 69 DA-142 1.656E-03 0.000E-01 2.632E-02 2.704E-05 2.200E-05 1.192Et03 1.560E-16 0.009E-01 LUHG l 70 LA-140 4.504E401 0.000E-01 3.440E602 1.736Et02 0.0006-01 1.340EiO5 4.584El05 0.000E-01 GI-LLI L

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g ,g N H NO ISOTOPE W. BODY THYROID BONE

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' 75 PR-113 - LUNG 76 PR-141 ' 4.640Et02 0.000E-01 9.360Ct03 3.752Et03 2 160E t03 2'.800C105 2.000Et05 0.000E-01 LUNG

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G Page 18 of 39 Os

'$ PATHWAY DOSE PARAMETER FACTORS FOR IMPLEMENTING 10 CFR PART 50 F

.N

~ ACE 1 TEEN (

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. e4 HD ISOTorE W. LODY THYROID BONE . LIVER KIDNEY LUNG GI-LLI SKIN CRITICAL .(.

'71 LA-142 1.056E-01 0.000E-01 9.600E-01 4.240E-01 0.000E-01 1.016Et04 1.200Ef04 1.056E-01 GI-LLI 72 CE-141 2.160Et03 0.000E-01 2.040Et04 1.896E104 8.030Et03 6.136Et05 1.264El05 0.000E-01 LUNG (-

73 CE-143 2.160E t 01 0.000E-01 2.656Ef 02 1.936Ef 02 8.610E 601 1.304Et05 2.552Ef05 0.000E-01 DI-LLI 74 CE .44 -2.624Et05 0.000E-01 4.080Et06 2.024E106 1.200Et06 1.336Ef07 8.640Et05 0.000E-01 LUNG 75 PR-143 6.624El02 0.000E-01 1.336Et04 5.312Et03 3.0SOEt03 4.032Et05 2.136Et05 0.000E-01 LUNG l.

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 5.120Et02 0.000E-01 7.064Ef03 0.560Et03 5.024EiO3 3.720E105 1.024El05 0.000E-01 LUNG 70 W-135 5.440Et01 0.000E-01 1.560Et03 5.176Et02 0.000E-01 4.456Et05 8.56CE104 0.000E-01 LUNG .

Ci 79 u-107' 3.432Et00 0.000E-01 1.200Et01 9.760Ef00 0.000E-01 4.736Et04 1.768Et05 0.000E-01 GI-LLI 80 U-235 .4.856Et06 0.000E-01 0.000E107 0.000E-01 1.072E107 3.920Et00 3.072Et05 0.000E-01 LUNG Y 81 U-230 4.536Et06 0.000E-01 7.664E107 0.000E-01 1.744Et07 3.664Et08 8.240L105 0.000E-01 LUNG l' tj 02 NP-239 1.768Et01 0.000E-01 3.394Ef02 3.192Ef01 1.000Et02 6.488E104 1.320E105 0.000E-01 GI-LLI

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16000000000000000000000000000000000 33445345341433i1411113105555535S545 0 00000000000000o00000000000O0000O000 - - - t lt 6 1 I f4t 4lt t 1 5 I ftt t t t4tt 1 4 4 tt l 14 1 L EEEEELEEELL0EEEEEEEEEEEEEEEEEEEEEEE 54V8L402/77017V02700C2i12193979O551 1 L R - 2301?893663262P7310009297332713?801 A I 17621022004423366000097064716783015 F G 161 41121273926U31100071113122112363 R

r 331114645666453353111 1116744536i465 C 0O000000000O0000000000000000000o000 fif - 1 t t t t ti tt 1t4 t - - - - - - f1 tf4f1l4 ff 0 EEEELEEEEEEECEEEEEEEEEEEEEEEEEEEEEE 1 G 54?00063096789733100000076016270712 N 23000971160634785200000057201129333 G U N

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I L 176190265373.i6991400096400000000017 161 13041231154211900015300000000042 1

E F 1446511114 1145O14211111150213151252 L e R 00000000000000O00000000000000000000 B g E - ff1t - - - f1 - - f1 it - - - - - - - 11l t 1 fttt f A a T EEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEE T P E N E

N 09959000A8002400570000001 01 079Y55a6 080030003600019059000000911106336Y7 A O 05660000700052902600000090231010800 R B A 03122O00420018204600000051114592111 P .

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N Page 20 of 39 m i FATIIWAY DOSE PARAMETER FACTORS FOR IMPLEMENTING 10 EFR PART 50 m

m M

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.1 EU-103 1.073Et03 0.000E-01 2.067Ef03 0.000E-01 7.030Et03 6.623Et05 4.477Et01 0.000C-01 LUNG l 42 RU-105 5.550E-01 0.000E-01 1.520E100 0.000E-01 1.343E100 1.591Et04 9.953Lf01 0.000E-01 GI-LLI

) 43 hu-106 1.69tEf01 0.000E-01 1.362Ef05 0.000E-01 1.039Et05 1.432Et0/ 4.2V2Et05 0.000E-01 LUNG

! 4i AG-110H 9.13YCt03 0.000E-01 1.607Et04 1.1400404 2.124Ef04 5.476Et06 1.0030f05 0.000E-01 LUNG 45 CD-115M 2.941Et03 0.000E 01 0.000E-01 9.102Et04 7.326Etot 6.512Et05 1.776Ef0b 0.000E-01 LU 4G l LudG

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311111111111111111111 11111111111111 00000000000000000000000000000000000 t - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

EEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEE N 000000000O0000000000000000000000000 I 000000000O0000000000000000000000000 K

S 700000000.O.0000000000000000000000000 30000000000000000000000000000000000 41432445444444445343333333332114324 0 00000000000000000000000000000000000 l t4 1 f 5 I 4+l tl 6 l t t l t l 1 t tt t t t tt l lt t + 6t 4 -

L EEEEEEEEEEEEEEEEEEEEEEEEECEEEEEEEEE T L 7S2020404 02I06221:1 00H4691 4044064604 R - 627341 13021V330391 10505033236093430 A I P G 2 2 8 0 4 6 0 6 3 71. J 7 4 9 612 4 9 0 912 0 3 4 3 7 0 0 0 7. V. 4 14428141367122621841112111110053468 R

F 52522547655564635351111114441036335 C 000O0000000000000OO00000000000O00O0 ftt i +++tt ttt 1 ff4 tii - - - - - - t t1 tt itt i t 0 EEEEEEEEECEEEEEEEEEEEEEEEEEEEEEEEEE 1 G 0006060604062506uC20000006660606340 N 004031 65664613098500000006723759658 G U 72318551643430699040000009115995956

) N L T I 44105511324411121230000007176351211 N T O N 32324315441140412231434335452141551 C E 00000000O000O00000000O0000000000000

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O 33235111342331321324434335552141452 3 F 00O00000000000000000O0000000000O000 2 t - i - - - - - l tttf - l - f - t 1i tftt ttttt - i - - t E S R EEEECEEEEEEEEEEEEEEEEEEEEEEEEEEEEEE L e R E 62242O00440021 0220470206205C2220C1 2 B g O V 24583O002430039701 60311702111040700 A a T P T

C A

I L 48682.J.00240995045233459060310086030 69128000731169635021431177167595132 F

4213530431331O422223434235452101122 R 0000000000000O00000000000O000000000 E f - - - - fttf - tft it - t - t t1 1t t t il 1t t 11 - t T EEEEEEEEEEgEEEEEEEEEEEEEEEEEEEEEEEE E E L207064020006642764644424200441 0044 M N 69091128006662186325992146305000675 A O 50035024904762400773763289040546590 R L A 13016218905412171136311933455315135 P

111111111113303212267564511 11111111 E D 00000000000000000000o00000000000000 S I - - - - - - - - - - f11t t - f - 11i t t1 f - - - - - - - - - -

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000000000011415601211134600'00000000 T 331242143332313213231 332241 42123331 A Y 000000000000000000O000000000000O000 P N D t - l - - t - tt +tt t - t ilt 1 t t t ft 1 11 - I - - t O O EEEEEECEEEEEEEEEEEEEEEEEEEEEEEEEEEE I D 0444002003002666604209002L206600002 T 003209009178702729676505749571 97765 A . 75271710911500204975926674259920991 L W A 33330641412624213415115627513142415 H

TN NI A E HM MM H H F! F M135605457799112 4673990120 N O 57990000112222223330123453333334414 IY T 999911111111111 111133333311111 11111 A O - - - - - - - - - - - - - - - - - - - 11 1111 - - - - - - - - - -

I W S DDOCCUUUGDDEEEEEEEE- - - - - - SSSSSAAAAA H I HNMTTRRRACSt TTTTTTTII IIIICEECEBDDDL ET GA O 67090123456789012315670V0l2345670Y0 AP N 3333444444444455555555556A6666466S7 h$EyN~@4w DbN 8

g .

g TABLE 6 (CONT) e

[ Page 24 of 39 PATilWAY DOEE PARANETER FACTORS FOR IMPLEMENTING 10 CFR PART 50 h

H "i

AGE : INFANT r PATHUAY I.INilALATION Ho ISOTOPE W. DODY TilYRDID DONE LIVER KIDNEY Ll!NG GI-LLI GKIN CRITICAL 71 LA-142 9.044E-02 0.000E-01 1.030EtOO 3.766E-01 0.000E-01 8.210Et03 5.950E604 9.044E-02 GI-LLI 72 CE-141 1.900E603 0.000E-01 2.772Et04 1.666Et04 5.250Et03 5.166EiO5 2.136C104 0.000E-01 LONG 73 CE-143 2.212E601 0.000E-01 2.926Et02 1.932C102 5.642E101 1.162E105 4.970E101 0.000E-01 LUNG 74 EC-144 1.764Et05 0.000E-01 3.19'5906 1.211Et06 5.376EiOS 9.042E106 1.404E105 0.000E-01 LUNG 75 PR-143 6.90iEt02 0.000E-01 1.400Et04 5.236Et03 1.974E103 4.326EtOS 3.724Et04 0.000E-01 LUNG 76 It-144 2.408E-03 0.000E-01 4.700i-02 1.010E-02 6.720E-03 1.610E t03 4.2C 4C t 03 0.000E-01 GI-LLI 77 ND-147 4.990E602 0.000E-01 7.930Et03 0.134Et03 3.150C603 3.220Et03 3.122E104 0.000E-01 LUNG 08 70 W-105 9.534E600 0.000E-01 2.730E102 9.050EiO1 0.000E-01 7.790EiO4 1.490Et04 0.000E-01 LUNG -

E 79 U-107 3.122Et00 0.000E-01 1.296Et01 9.016EtOO 0.000E-01 3.962E104 3.556Et04 0.000E-01 LUNG L2 00 U-235 0.4VUE105 0.000E-01 1.400E107 0.000E-01 3.276Et06 6.860ClO7 6.776E104 0.000E-01 LONG U1 U-238 7.930Et05 0.000E-01 1.341EtO7 0.000E-01 3.052EIO6 6.412E107 1.442Et05 0.000E-01 LUNG 02 NP 239 1.076Et01 0.000E-01 3.710Et02 3.310Et01 6.622C101 5.950EiO4 2.4?2Et01 0.000E-01 Lut!G t-O __ _ _ - _ _

7 O

r

'D

'D s TABLE 6 (CONT)-

y Page 25 of 39 to

.Q PAlliWAY DOSE PARAMETER FACTORS FOR IMPL EMENTIHO 10 CFR' PART 50 un AGE 1 ALL t

~@ PATitWAY 8 GROUND FLANE

.y No ISOTOPE W. BODY TilVRDID DONE LIVER KIDNEY LUNO DI-LLI SKIN CRITICAL s

4

.r 1 H-3 0.000E-01 0.000E-01'O.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 W. BODY 4

2 C-14 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 3 ilA-24 1.190Et07 1.190El07 1.198E+07 1.198E107 1.190Et07 1.190Ef07 1.190E107 1.3u9El07 SKIN (

4 P-32 0.000E-01 0.000E-01 0.000E-Ot 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 W. 00DY 5 SC-46 0.321EIOD 8.321Et08 8.321E108 0.321E100 0.321EiOO 0.321E100 0.321El08 9.601Et00 SKIN 6 ER-51 4.468EiO6 4.668E106 4.660Et06 4.658E406 4.660E106 4.668Et06 4.66 bet 06 5.517E106 SKIN t 7 hn-54 1.304Et09'1.304Et09 1.384E+09 1.301Efo9 1 30iEt09 1.304E109 1.301Efo9 1.622E109 SKIH 0 1111 - 5 6 9.030Et05 9.030EiO5 9.030E+05 9.030E+05 9 030Et05 9.030El05 9.030Et05 1.067EIO6 SKIN 9 l'E-55 0.000E-01 0.OOOE-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 W. 00DY C 10 t'E-59 ' 2.725Efou 2.725Ef03 2.725El08 2.725EiOO 2.725Etca 2.725EIOS 2.725Et03 3.202EiOD GNIH be 11 EU-58 3.lu3Et00 3.033E600 3.033EiOD 3.833EtOS 3.033EiOO 3.033E100 3.033E100 4.490EiOO SKIN L

$. 12 EO-60 2.152E110 2.152E110 2.152E110 2.152Ef10 2.152Et10 2.152Et10 2.152E110 2.532E110 SKIN '

  • 13 NI-59 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. D0DY 11 til-63 0.00CJ-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 15 111-45 2.970Et05 2.970Et05 2.970El05 2.970Et05 2.970Et05 2.Y70Ef05 2.970EiOS 3.451E405 SVIN 16 EU-64 6.051EIO5 4.051EiO5 6.051Et05 6.051Et05 6.051EtOS 6.051Et05 6.051Et05 6.050EiO5 SKIN 17 It?-65' 7.410Et00 7.410EfC0 7.410EiO8 7.410Et00 7.410Et00 7.410Et00 7.4100i00 0.522E100 SKIN '.

10 ZiF69 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.0ptE-01 0.000E-01 W. BODY 19 2R-03 4.007Et03 4.087E103 4.807Et03 4.007E103 4.80?E603 4.007El03 4.007Et03 7.102E603 SNIT!

  • 20 DR-04 0.022E105 2.022El05 2.022Et05 2.022El05 2.022E105 2.022Et05 2.022EIO5 2.356Et05 SKIN '

21 BR-85' O.000E-01 0.000E-01'O.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 W. 00DY '.

22 Rii-06 0.V43El06 0.943Et04 U.V43E106 0.963Et06 8.963Et06 8.943EiO4 5.963E606 1.02iE607 GKIst 23 lut-00 3.207El04 3.287Et04 3.207E104 3.207Etoi 3.207Et04 3.207Et04 3.~07Et01 3.756Et04 Sh1N 4 21 RD-09 1.20VE-l O5 1.209EiO5 1.209EtOS 1.209E105 1.209E t 05 1.20VE t 05 1.209El05 1. iG0E 105 SKIN 25 ER-09 2.160Et04 2.160Ef04 2.160Et04 2.160E104 2.160E404 2.160E+04 2.140Et04 2.507EIO4 SKIN 26 GR-90 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 k 27 Sle91 2.115El06 2.145El06 2.145El06 2.i IGE 106 2.145Et 06 3.145E104 2.145ElO6 2.507E106 SKIN 20 SR-92 7.762Et05 7.762El05 7 762El05 7.762Et05 7.762E105 7.762C105 7.742E105 0.625Et05 SKIN i 29 Y-90 4.49?E103-4.497EiO3 4.4Y7El03 4.497E603 4.497E103 4.497E103 4.497E103 5.311E103 SKIN 30 Y-91M- 1.00iEt05 1.004El05 1.004Et05 1.004Et05 1.004EiOS 1.004Et05 1.004EiO5 1.163EiO5 SNIN

  • 31 Y-91 1.071Et06 1.074E106 1.074Ef06 1.074Et06 1.071Et06 1.074El06 1.074E106 1.209E106 SKIN 32 Y-92 1.00:El05 1.004Et05 1.004Et05 1.001Et05 1.0040605 1.001EIOS 1.004E605 1.916El05 SKIN (

33 Y-93 .1.049Et05 1.049EiO5 1.049Et05 1 049Et05 1.049El05 1.049E105 1.049El05 2.531EiO5 SKIN 31 ZR-95 2.513Et00 2.513E100 2.513Et00 2.513Et00 2.513Et08 2.513E400 2.513E600 2.915E100 skill 6 35 ZR-97 2.950Et06 2.950EiO6 2.95GEiO6 2.950E106 2.950E106 2.950E106 2.950Et06 3.443E106 CKill L e

J

, - .g .  %

i 1

l es g TABLE 6 (CONT)

U Page 26 of 39 5

g2 PATitWAY DOSE PARANETER FACTORS FOR IMPLEMENTIttG 10 EFR PART 50 ,

m tus

'ACC : ALL

@ PATHWAY I GROUND PLANE

.HQ ISOTOPE W. BODY TilYROID DONE LIVER KIDNEY 1.UNG OI-LLI SKIN CRITICAL w .

36 ND-95 1.366Ef00 1.366Et00 1.366Ef00 1.366Ef00*1.366Et00 1.366E100 1.366Et00 1.607E108 SKIN 37 ND-97 1.797Ct05 1.797E405 1.797Ef05 1.797E105 1.797Ef05 1.797Ef05 1.797Ct05 2.109Ef05 SNIN 30 NO-99 3.990Et06 3.990Et06 3.990Ef06 3.990Et04 3.990Cf06 3.990Ef06 3.990Et06 4.620Ef06 SKIN .

3V TC-??N 1.045Et05 1.045EiO5 1.045E605 1.845Et05 1.045Ef05 1.045Et05 1.045EtO5 2.115E105 SKIN 40 TC-101 2.03)Ef04 2.034E604 2.034E604 2.034Et04 2.034Ef04 2.034E104 2.0340804 2.260EiO4 SKIN 41 RU-103 1.093E400 1.093Ef00 1.093Ct03 1.093E100 1.093 ETOH 1.093Ef00 1.093C100 1.275Et00 SKIN i 42 RU-105 6.373E105 6.373Ef05 6.373Et05 6.373El05 4.373Ct05 6.373Et05 6.373Et05 7.223E105 GKIN 43 RU-106 4.239E100 4.239Et00 4.239Et00 4.239EiGO 4.239El00 4.239E100 4.239El00 5.004Et00 SKIti 44 AG-110N 3.460Efo9 3.460EiO9 3.460E109 3.460Et0V 3.460Et09 3.440Eto? 3.4600609 4.037Ct0? SAItl 45 ED-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. DODY 46 SD-124 5.991E100 5.?V4El00 5.994El00 5.994Et08 5.994Et03 5.994E100 5.991Et00 6.V16Et08 SE186 08 47 TE-125N 1.555El06 1.555E106 1.555Ef06 1,555Et06 1.555El06 1.555Et06 1.555Et06 2.133Et06 SKIN 4 LA 43 TE-127N Y.165Ef04 9.165Ct04 9.165E104 9.165Et04 9.165EIO4 9.165E104 9.165El04 1.003Ef05 LKIN 44 TE-127 2.991E103 2.991Ef03 2.991Ef03 2.991Et03 2.991E103 2.991Ef03 2.991Et03 3.290El03 SKIN j 50'TE-129M 1.967Et07 1.967Eio7 1.967Et07 1.967EiO7 1.967E107 1.967Et07 1.96?E107 2.300E107 GKIN i<

51 1E-129 2.639Et0% 2.639EiO4 2.639 Clot 2.639EiO4 2.639El04 2.639Et01 2.63?E101 3.122Et04 Skill 52 10-131N 0.023E106 0.023E106 0.023Et04 0.02JE106 0.023Et04 0.023Ef06 0.023ClO6 9.456Ct04 SKIN 53 IE-131 -2.V26El04 2.926Et04 2.926Et04 2.926E104 2.926Et04 2.926Et04 2.924El04 3.150E107 SKIN 5!

l 51 TE-132 4.220E606 4.220Ef06 4.220E106 4.220Et04 4.220Ef06 4.220El06 4.220Et06 1.V65EIO6 SKIN f 55 I-130 5.539Et04 5.539Et06 5.539El06 5.539E106 5.53YEt06 5.539Et06 5.53VCt06 6.724E-106 SKIN 56 I-131 1.722Cl07 1.722E107 1.722Et07 1.722Ct07 1.722E107 1.722E107 1.722Et07 2.091E107 'EKIN s 57 I-132 1.23SE106 1.230El06.1.230Ef06 1.230Et06 1.230Et06 1.230E106 1.230El06 1.457El06 SKIN 50 I-133 2.153E t 06 2.-153Ef 06 2.453EiO4 2.453EiO6 2.453EIOS 2.453EIO4 2.453E406 2.903EiO6 SK16 59 I-134 1.160El05 4.160El05 4.460E105 4.460E405 4.460EIO5 4.460E105 4.460E105 5.296Et05 SKIN t 60 I-135 2.520El06 2.520El06 2.520Et06 2.520El06 2.520El06 2.520E106 2.520E106 2.940El06 SKIN 61 EU-134 4.031El09 6.034EIO9 6.031E109 6.03tE109 6.034EtO9 6.031E109 6.03tEl09 7.V72El0V SKIN-t 62 EC-136 '1.491E100 1.491ElG9 1.191Et00 1.4VIEiOO 1.1910i00 1.491Ef03 1.4?tEt00 1.690E100 SKIN s l 63 EG-137 1.030Et10 1.030Et10 1.030E-110 1.030Et10 1.030Et10 1.030E110 1.030Et10 1.202E110 SKIN 61 ES-130 3.59?E105 3.597C105 3.597E105 3.59/E105 3.597El05 3.597El05 3.597E105 4.111E105 SKIN SS C'3-139 3.115E104 3.115E104 3.115El04 3.115E104 3.115E101 3.115El04 3.115Ef04 3.561EIO4 SKIN s 66 JO-139 1.05 vel 05 1.059Ef05 1.059E605 1.05?Et05 1.059El05 1.059El05 1.059El05 1.191El05 SKIN 67 BA-110 2.051EtO7 2.051E107 2.051EIO7 2.051E107 2.051Et07 2.051E107 2.051E107 2.343E107 SKIN 60 1:A-141 4.17?Ef01 4.179E104 4.179Et04 4.179C104 4.179E104 4.179E404 1.179E104 4.762E104 SKIH (

69 1A-142 4.406Ef04 4.186Et04 4.406E104 4.406EiO4 4.406E804 4.406EiO4 4.406El04 5.110El04 SKIN 70 LA-140 1.V24E107 1.921E407 1.?21E107 1.924Et07 1.924Et07 1.924El07 1.924El07 2.101El07 SNIN g

o .

f f 3- (

g _ ._ _ __

-y TABLE 6 (CONT)

<a g Page 27 of 39 e

y PATilWAY DOSE PARAHETER FACTORS FOR IMPLEMENTING 10 CFR PART 50

=

0 AGE'1 ALL c: PATilWAY 1 GROUND PLANE 2.

N NO ISOTOPE 'W. DODY TilYROID DONE LIVER KIDNEY LUNG GI-LLI SKIN CRITICAL 71 LA-142 7.359E105 7.359Ef05 7.359EtOS 7.359Et05 7.359Et05 7.359EiO5 7.35SE105 0.030Ef05 SKIN 72 CE-141 1.365Et07 1.365Ef07 1.365E107 1.365E107 1.365Ef07 1.365Ef07 1.345Ef07 1.539Ef07 SKIN 73 CE-143 2.314E106 2.314Et04 2.314Et04 2.314E406 2.314Et06 2.314Et06 2.314EiO4 2.630Et04' SKIN 74 CE-144 4.934E107 6.934Et07 6.934E+07 6.934Ef07 6.934Ef07 6.934Et07 6.931E407 C.017Et07 LKIN 75 PR-143 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 74 PR-144 1.033E103 1.033Et03 1.033Et03 1.033f:f03 1.033Ef03 1.033Et03 1.033E103 2.100E103 CKIN

~77 ND-147 0.309E106 0.309Et04 0.309ElO6 0.30VEf06 0.30VEIO6 0.309Et04 U.309Ct04 1.007Et07 CKIN 70 u-185 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 79 W-107 2.358E104 2.350Et04 2.35DEt06 2.350Ef06 2.350Et06 2.350Et06 2.358E606 2.739Et06 SKIN 00 U-235 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.0000-01 0.000E-01 0.000E-01 0.000E-01 W. BODY 01 11-233 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 Y 02 MP-239 1.703Et06 1.703Et06 1.703Et06 1.703Et06 1.703Ff06 1.703Et04 1.703EiO4 1.Y72Et06 SNIN Os

L Y Y YY Y A D D IIII III II IDD D IIIIIIIII LLRRLODRRO C

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- - - N - - - NH- - VV- VV l H-i L.LLLLLLLL LLLLLLLL I .O .OIIII OIIIOOIIIII . .II 0OIIIIIIIII R WBWBGGGGDGGGDDCGLLGWWLLWDDGGGGGGGGG E

351111111111111111111 1111 1111111111 00000000000000000000000000000000000 t1 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

EEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEE N 030O0000000C00000000G00000000000000 I 690O0000000O00000000O00000000000000 K

S 270.O.0000000.O.00000000.O.00000000000000 21000000000000000000000000000000000 355097027009702506061 71190630094697 0 000000000000000000010000010000000O0 l - - t tl tl - t t 4 i t 5 I t ft 1t ft t t t t t t ft 6 1 - t - -

L EEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEE T L 02209t 32691?0t6:1 0?6/01 0067320867766 R - 6998670106733061 5t 1 7010094371414519 A I 27653159302155973245030057414105420 P G .

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T 21200600000000000000000000000000000 N 355154711111111406111 111111 11111152 E 00000000000000000000000000000000000

) M Y t tf t1 t t - - - - - - - l l - - - - - - - - - - - - - - - - 1 t T E E EEEEEEEEEEECEEEECEEEEEEEEEEEEEEEEEE L N 03207694000000022600000000000000092 N P D 69904205000000094100000000000000012 O M I 27605039000000027700000000000000000 C I K

( 21204191000000024900000000000000061 R

9 O 3557510100700003951110211111111 11S!

3 F 000000000000000000000020000000000O0 ttftt - tt t t1t 4 1t6t - - - - f - - - - - - - - - - - tl 6 f S R EEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEE R E 03200009016151200500073000000000057 o O V 69941023469701b90900006000000000034 T I 27679015490662700400010000000000007 8 C L 2 A 21284031123127791100021000000000036 E F L e 15595111001100110611111191524961262 B g R 00000000000001000000000001000000O00 A a E - fff1 - - - t t - - tt 4 - t - - - - - - - 1 tftt t - l t1 TP T EEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEEE E E 04265000600000700900000044950066164 M N 0690000096003460410000 A

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B 09645000020080901000000054023314295 0090013919713 A 08212000210071503700000096341450113 P

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T 35575470707000030601103101112052051 A Y 0000000000000000000'002001000100000 P N D fftflt t tt1t t1 6t t 1 - t - - t - - ll t t t - 1 - t tt O O EEEEEEEEEEEEE EEEEEEEEEEEEEEEELEELEE I D 03234690659669776070092071 b1 4905161 T 29931563733000365400010050106061599 A . 27644697319634525000000004275936750 T W E 21251452316313344132019021113112423 G

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g TABLE 6 (CONT) 50 Page 35 of 39

% PATitWAY DOSE PARAME1ER FACTORS FOR IMPLLMCNTING 10 CFR PART 50 a

- AGE 1 CHILD PATHWAY 1 VEGETATION N NO ISOTOFE W. D0DY THYROID BONE LIVER KIDHEY LUNG GI LLI SKIN CRITICAL

^

36 NB-95 1.141Et03 0.000E-01 4.101Ef05 1.597Et05 1.500E605 0.000E-01 2.953E600 0.000E-01 GI-LLI 37 ND-97 1.022C-07 0.000E-01 1.109E-06 2.79?E-07 3.265E-07 0.000E-01 1.033E-03 0.000E-01 .GI-LLI 30 MD-99 1.903E106 0.000E-01 0.000E-01 7.693Et06 1.643Et07 0.000E-01 6.342C106 0.000E-01 KIDf!EY 39 TC-9VM 1.526Et02 0.000E-01 4.495Et00 9.20CEt00 1.330E102 4.675Ef00 5.2iOEt03 0.000E-01 GI-LLI 40 TC-101 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E *1 0.000E-01 0.000E-01 0.000E-01 W. D0DY 11 RU-103 5.959Et06 0.000E-01 1.550Ef07 0.000E-01 3.902EtO7 0.000E-01 4.OOSE108 0.000E-01 GI-LLI 42 RU-105 3.290Et01 0.000E-01 9.070E401 0.000E-01 7.973Et02 0.000E-01 5.9200601 0.000E-01 GI-LLI 43 RU-106 9.300CtO7 0.000E-01 7.459Ef00 0.000E-01 1.0070609 0.000E-01 1.160Ef10 0.000E-01 GI-LLI 44 AG-110M 1.734Ef07 0.000E-01 3.216Ef07 2.172Et07 4.046Et07 0.000E-01 2.50tC409 0.000E-01 GI-LLI 15 CL-115M 1.359Et04 0.000E-01 0.000E-01 4.251Et07 3.373Eto/ 0.000E-01 1.7 del 40V O.000E-01 GI-LLI g 46 SI'124 3.524E107 2.154EiO5 0.921EIO7 1.603EiO4 0.000E-01 6.921Et07 2.521Et0V 0.000E-01 GI-LLI s 47 TE-125M 4.687E107 9.859E107 3.512E100 9.520E607 0.000E-01 0.000E-01 3.30?Ef00 0.000E-01 LOHE IQ 43 10-127M 1.569E100 3.161Et00 1.322E409 3.559El00 3.74 vet 09 0.000E-01 1.010E409 0.000E-01 KIDHEY 49 TE-127 2.120Et03 6.043Et03 9.007Et03 2.666Et03 2.013Etoi 0.000E-01 3.U62Et05 0.000E-01 GI-LLI 50 lE-12SH 1.297Et00 2.693Et00 0.354Et00 2.333Et00 2.453E409 0.000E-01 1.019EtO9 0.OOOE-01 KIDHEY 51 1E-129 3.215E-01 9.664E-04 1.355E-03 3.701E-01 3.963E-03 0.000E-01 0.131E-02 0.000E-01 GI-LLI 52 TE-131H 5.65CCt05 1.093E606 1.537Ef06 5.314EtOS 5.146Et06 0.000E-01 2.156Et07 0.000E-01 GI-LLI 53 TE-131 7.003C-16 1.000E-15 2.353E-15 7.174E-16 7.117E-15 0.000E-01 1.236E-14 0.000E-01 GI-LLI 54 1E-132' 3.727Et06 4.491Et06 6.972E406 3.006Et06 2.015Et07 0.000E-01 34104E107 0.000E-01 GI-LLI

'55 1-130 6.413El05 1.37CEt00 6.10?Et05 1.251E106 1.06?Et06 0.000E-01 5.e50EIO5 0.000E-01 THYROID 56 I-131 0.175EtO7 4.757Et10 1.430Et00 1.439EIOD 2.362Et00 0.000E-01 1.201E107 0.000E-01 THYROID 57 IJ132 7.101E101 7.245E103 0.498El01 1.562Ct02 2.390Et02 0.000E-01 1.03CC102 0.000E-01 TilVRO1D 50 I-133 1.449Et06 0.094EtOS 3.523Et06 4.356E406 7.241Et06 0.000E-01 1.756E106 0.000E-01 TilVROID 59 I-134 1.173E-04 5.064E-03 1.373E-04 2.549E-01 7.29CE-04 0.000E-01 1.690E-04 0.000E-01 iltYROID 60 I-135 5.220Ef04 9.774Et06 6.130Et04 1.103Et05 1.692Ef05 0.000E-01 0.407E101 0.000E-01 1HYROID 61'CG-134 5.549EiO9 0.000E-01 1.603Et10 2.631Et10 0.152Et09 2.925EtO9 1.110E100 0.000E-01 LIVER 62 CS-136 1.434Et00 0.000E-01 8.062E107 2.216Ef00 1.100E100 1.760Et07 7.707E106 0.000E-01 LIVER 63 CS-137 3.300Et09 0.000E-01 2.392Et10 2.290Efl0 7.462Cl09 2.605Et09 1.434EiOH 0.000E-01 BONE 64 CS-130 5.375E-11 0.000E-01 4.097E-11 0.474E-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. BODY 6 5 DA-139 1.360E-03 0.000E-01 4.693E-02 2.505E-05 2.100E-05 1.474E-05 2.709El00 0.000E-01 GI-LLI 67 BA-140 1.611Et07 0.000E-01 2.761El00 2.419Et05 7.875E604 1.442Ef05 1.399Ef00 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 UONE 49 DA-142 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 70 LA-140- 3.535Et02 0.000E-Ot 3.246Et03.1.134Ef03 0.000E-01 0.000E-01 3.162E407 0.000E-01 3I-LLI ss 1 f)

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000000000000 107033704907 0 O00102000010 5 I i1 6l 1 - 1 1 f t t1 L EELEEELE L0EE .

T L 0C2S921091 02 R - 976363605125 A I 303056103723 P G 141112955511 R

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N 152741111002

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o TABLE 6 (CONT)

$ Page 37 of 39 M

PATitWAY DOSE PARANETER FACTORS FOR IMPLEMENTING 10 CFR PART 50 M

i AGE : INFANT

  • l g PAIHUAY I VEGETATION H

'H NO 100 TOPE W. D0DY THYRDID BONE LIVER KIDNEY LUNG GI-LLI GKIN ERITICAL w 'l l 1 H-3 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 j 2 C-14 . 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. BOD (

3 NA-24 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. D0bY t 4 P-32 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

-5 SC-46 0.000E-01 0.000E-01 c.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 W. DODY 6 ER-51 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 t 7 Mif-54 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 8 MN-56 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000C-01 0.000E-01 W. DODY 9 FE-55 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.OOOE-01 0.000E-01 0.000E-01 W. DODY

  • 10 FE-59 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000L-01 0.000E-01 W. DODY 11 CO-50 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 f 12 CD-60 -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. D0DY 4 La 13 HI-59 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 14 NI-63 0.000E-01 0.000E-01 0.000E-01 0.OO0E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 W. D0DY 15 NI-65 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.OOOC-01 0.000E-01 W. D0bY 16 CU-64 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 17 ZN-65 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. Dub 1 10 ZN-69 0.000E-01 0.000E-01 0.000E-01 0.000Z-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 W. D0DY .

._19 DR-03 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

.20 DR-04 .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 21 DR-85 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 l 22 RD-06 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 23 RD-88 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. D0DY 24 RD-39 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 t 25 CR-09

  • 0.000E-01 0.000E-01 0.000E-01;O.000F-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 W. DODY 26 ER-90 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 H. DODY 27 SR-91 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 L 23 Sh-V2 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..D0DY 29 Y-90 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. D0DY 30 Y-91H 0.000E-01 0.000E-01 0.000E-01 0.OOOE-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 W. D0DY t 31 Y-91 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 32 Y-92 .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 33 Y 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. D0DY L 31 ZR-95 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E-01 0.000E--01 0.000E-C1 0.000E-01 W. DODY 35 2R-97 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. D0DY t

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i DAVIS-BESSE, UNIT 1 B-57

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Ca = snsssssssano DAVIS-BESSE, UNIT 1 B-58

)

) A

TABLE 7 CONTROLLING RECEPTORS, LOCATIONS, PATHWAYS, AND ATMOSPHERIC DISPERSICN 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.
    • These sectors are located over Lake Erie, so no ingestion pathways are present.
      • Default value, no real receptors _within five miles.

DAVIS-BESSE, UNIT I B-59

s i ~ 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 I 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 c,f site.

T-ll A-24 C Port Clinton, 18.4 km SE of site.

T-12 A-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 s Carl Caeth,12639 W. Toussaint E Road, 7.20 km WSW,cf site.

T-24 A-23, A-29 C Sandusky, 39.8 km SE of site.

- T-25 A-30 1 Miller Farm, 5.92 km S of site.

T-27 A-31 C Magee Marsh, 8.48 km WNW of site.

T-28 A-32 I Unit 1 treated and untreteed water supply, onsite.

T-33 A-33 I ' Lake Erie, within a 8.0 km radius of site.

2 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 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 Toussaint.

i l

  • I= Indicator locations; C= Control Locations DAVIS-DESSE, UNIT.I B-60 l

TABLE 8 (continued) '

Page 2 of 2

-SAMPLING LOCATIONS, DAVIS-BESSE NUCLEAR POWER STATION Appendix A Type of Code Page Reference Location

  • Location T-42 A-39 I Site boundary 1.28 km SSW of station by ECC.

T-43 A-40 I Site boundary 0.8 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 Farme 8.0 km W of site on Route 2.

  • I= Indicator location; C= Control locations.

DAVIS-BESSE, UNIT'1 B-61 l

l

,, - , + - - _

TABLE 9 Page 1 of 2 4

.h 5 Type and Frequency of Sample Collection Environmental Radiation Monitoring Program h

E T

g . . _ _

Semi-annually Annually q Location Type Weekly Monthly Quarterly r.

'1 I /J AI TLD 2 I aP AI TLD 3 I AP AI D m" US 4 I AP AI SWU" 5 I TLD 7 I TLD to 8 I M CLV

& AP A1 TLD N 9 C

-11 C TLD 12 C AP AI SWil" SWT" TLD 17 I W 20 I M 24 C M TLD 25' I CLV 27 C TLD BS 28- I SWI" 33 I F 35- C F" 37 C CLV 38 I TLD 40 I TLD 41 I TLD .

lContinued on next pagG. .

~ w ,

o g- Table 9, continued -

U e

Page 2 of 2 g Type and Frequency of Sample Collection g Environmental Radiation Monitoring Program (Continued)

E' E

n g Location Type Weekly Monthly Quarterly Semi-annually Annually 42 I TLD 43 I TLD 44 I TLD 45- I TLD 46 I TLD 47 I TLD y 48 I TLD O 50 I TLD

'51 1 TLD

'52 I TLD 54 1 TLD 55 I TLD a

composite sample over 1-week period b

Semi-monthly when animals are on pasture (May-October), monthly at other times

" Summer months d

Monthly when available (July, August, September) h

Table 10 Sample Collection Codes Code Description .

AP Airbc ne Particulates AI Airborne Iodine TLD Thernoluminescent bosimeter M Milk WW Well Water (Ground Water)

GLV Green Leafy Vegetables SWT Surface Water - Treated SWU Surface Water - Untreated F Fish BS . Bottom Sediments DAVIS-BESSE, UNIT 1 _B-64

OFFSITE DOSE CALCULATION MANUAL APPENDIX J JUSTIFICATIONS 1

l l

DAVIS-BESSE, UNIT 1

+

4 Safety Evaluation for the Davis-Besse ,

Radiological Effluent Technical Specifications Amendment i i

(

Ove rview i

Revisions to the Davis-Besse Appendix A and Appendix B Technical Specifi-cations are proposed which will implement the regulatory requirement of f 10 CFR 50, Appendix I on ALARA for radioactive effluents and other NRC 2 regulations and criteria on radioactive material monitoring instrumenta-i- tion, radioactive material control, and radiological environmental moni- ,

i toring. In keeping with NRC guidelines, all radiological requirements are being deleted from Appendix B and placed in Appendix A.

i This proposed amendment is a revision to a previously submitted amendment l to the NRC dated March 16, 1979 (Serial No. 488).

The major areas that are addressed in the revised submittal are as i follows:

1 P

Liquid and gaseous effluent monitoring instrumentation--operation and l periodic operability checks; Liquid.and gaseous radioactive material releases--maximum release
rates, quarterly does limits and yearly dose limits; f

Sampling and analysis requirements on batch and coctinuous'radioac-tive material releases; Operation requirements on the liquid radwaste treatment system';.

Curie inventory limit'on outside temporary liquid storage tanks;

~

Maximum sllowable oxygen concentration in the waste gas system; L

. DAVIS-BESSE, UNIT 1 J-1 i

i

'w e-- e a .~r 4 - .---.44- = , . .-M .-s.1- '.m-

Requirements to assure all solid waste meets applicable 'aurial site requirements; Radiological environmental monitoring program--minor revisions to 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 revisioas.

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 prevides 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 tLe 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.

i f

Safety Evaluation I.n evaluation of the revised amendment has been performed to assure that the revisions as proposed do not involve an unreviewed safety question as.

l defined in 10 CFR 50.59. The three criteria of 10 CFR 50.59 for the 1

i unreviewed safety question determination are addressed below.

1) Probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the safety analysis report.

l l

_ DAVIS-BESSE, UNIT 1 J-2

Except for the addition of the turbine building liquid effluent radiation monitor (for which an FCR has already been initiated), no plant equipment modifications are required by the proposed amendment. Certain procedural requirements will need to be developed but these address routine radioac-tive material effluents and controls; no accident procedures are involved,

11) 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) Margin 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 releascs 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.

DAVIS-BESSE, UNIT 1 J-3

__ _ . . _ ~ _ _ .

~___ _ _ _ _ _ _ _ _ _ _

Service Water System--Radiological Effluent Monitorina Requirements The service water system is classified as a non-radioactive system, being removed f rom 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-tive effluents.

DAVIS-BESSE, UNIT 1 J-4

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 controis 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

1 i .

Technical Bases for Eliminating Curie Inventory L_imit 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 I

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 concentration 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 Mev. 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 volmne 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 cor en-tration. For determining concentration in s waste gas decay tank, a conservative assump fon 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 i show that the equivalent concentration (decay corrected) is les'sithan the j gross concentration (i.e., 16 pCi/gm total in primary coolant versus q l

j 12 pCi/gm equivalent). The resulting Xe-133 equivalent curie'. inventory _ l l for WGDT input is approximately 31,000 Ci.

DAVIS-BESSE, UNIT;l- J-6 l

r l

l

. 1 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 l this evaluation, the curie inventory limit on a single waste gas storage tank has not been included as a Technical Specification requirement.

4 DAVIS-BESSE, UNIT-1 J-7

Table 1 Xe-133 Effective Concentration Prima ry* Half-life Concentration Reg Guide 1.109 Ratio Xe-133 Coolant @ 48 hr decay TB Dose Factor TB DF Effective Conc (pCi/GM) (pCi/ml) ares /yr Xe-133 DF @ 48 hr decay pCi/m 3 (pCi/ml) 1 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 7.4-02 10.7 yr 7.4x10-2 1.6x10-5 0.06 4.4x10-3 Kr-87 5.8-02 76.3 min --

5.2x10-3 20. --

Kr-88 1.9 2.84 hr --

1.5x10-2 52. --

Kr-89 4.8-03 3.16 min --

1.7x10-2 57. --

Xe-131M 8.4-02 12 days 7.5x10-2 9.2x10-5 0.32 2.4x10-2 Xe-133M 2.0-01 2.2 days 1.1x10-1 2.5x10-4 0.86 9.5x10-2 Xe-133 1.5+01 5.3 days 1.2x10+1 2.9x10-4 1.0 1.2x10+1 Xe-135M 1.3-02 16 min --

3.1x10-3 11. --

Xe-135 3.3-01 9.1 hr 8.5x10-3 1.8x10-3 6.2 5.3x10-2 Xe-137 8.7-03 4 min --

1.4x10-3 4.8 --

Xe-138 4.3-02 17 min --

8.8x10-3 30 --

4 Total 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' A e ~ -

- - r- w

I i

l Lower Limit of Detection--Decay Correction Factor The equation and definition of the lower limit of detection in the NRC Standard Radiological Effluent Technical Specification include the term I

e which 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 measurement 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 and, 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(-AAt) to adjust for radioactive decay between the era of-sampling and the time of analysis is straightforward. However, to attempt to use the same term to adjust for decay during the sampling period is not proper. As a practical matter, 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 correction term will be near unity. In that ev'ent, the correction term is relatively unimportant.

DAVIS-EESSE, UNIT 1 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(-Mt) could be used to adjust for decay between the end of sampling and the analysis. However, it would not be appropriate in that case to use the same term to : wept 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 'nvolved. 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.

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:

Ci=C2 At (2) 1-e^ ~

where i

Ci = radionuclide coicentration in the water being sampled C2= radionuclide concentration in the water sample at the end of sampling 4

t = duration of sampling A = radionuclide decay constant when A t >> 1, Ci ~ C2At 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:

C=C i At (2)

~

F(1 - e ^')

DAVIS-BESSE, UNIT 1 J-10

.)

i where l

l C = radionuclide concentration in the air being sampled q = radioactivity on the sample media (assuming 100% collection efficisney)

F = sampler flow rate (volume / time)

A = radionuclide decay constant t= duration of sampling when A t >> 1, Ct ~ q A/F.

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 correctioa to the' aid 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

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 1 J-12

Technical Basis for Liquid Radwaste System Operations Technical Specification 3.11.1.3 requires that appropriate subsystems of the liquid radwaste treatment system be rouCnely 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 C1

  • Davis-Besse Nuclear Power Station Unit No.1, " Evaluation of Compliance with Appendix I to 10 CFR 50," June 4, 1976.

DAVIS-BESSE, UNIT I J-13

r 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-rem /Ci of iodines released and about 5 man-rem /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 desineralizer is $75/ft3 for resins and $20/ft3 for disposal or $95, total per ft3 of 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 process a 13,000 gallon batch of miscellaneous liquid radwaste would cost about $650. Thereby, the radioactivity concentration be. low which it is not cost-beneficial to process can be calculated as follows:

$650 , 1 Ci ,10 6 pCi ,1 man-rem C = 13,000 gal

  • 3785 ml/ gal 5 man-rem Ci $1,000 4

= 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 m:Lerial released, the average gross radioac-tivity concentration corresponding to the Appendix I individual dose design objectives can be determined as follows:

DAVIS-BESSE, UNIT 1 J-14

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

3 arem, total body = 0.123 Ci

  • 3 mres , 1 ,10 8pci 0.032 arem Ci 1.4x10s gal *3785{ft

= 2.2 x 10-3 pCi/ml 10 mrem, thyroid = 0.104/L1

  • 10 arem , 1 , 10spCi Ci 0.034 mrem 1.4x108 gal *3785"fp t

= 5.8 x 10-3 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 j design objective class (i.e., 0.25 mrem /31 days, total body and 0.833 mrem /31 days, any organ). ,

d i-DAVIS-BESSE, UNIT 1 J-15

)

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 receiven 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.

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 systen , 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, huridity, 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 DAVIS-EESSE, UNIT 1 J-16

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 eFcess of those already established I (which at present assure appropriate operation) is unnecessary and excessive.

. l DAVIS-BESSE, UNIT 1 J-17

"1 Radiological Effluent Dose Analysis--

Meteorology for Short Term Releases Except for the waste gas decay tank (WGDT) releases and the containment purges releases, gaseous effluents from the Davis-Besse Station are from 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 rather 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

. e s

Radiological Environmental Reporting Levels 1

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 saeplfng media. The radionuclides listed are those that are dominant in tre plant effluents and contribute essentially all of the environmental c.se. 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 :t 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 ,

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 applicable reporting levels by the identified pathways are the only 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.

r DAVIS-BESSE, IDiIT 1 J-19

i Technical Basis for Eliminating Curie Inventory Limit of Outside Liquid Tanks 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 l 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 4

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 cculd 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.

DAVIS-BESSE, UNIT 1 J-20 ,

. . . ~ _ . . . _ - . _ _ - ~ _ - - --_- ._ - - _ - _ _ - . - - . ~-

t l

1 Sampling Frequency for I-131: Significance of Power Changes and Increases in Coolant Activity Levels 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 primary coolant level or noble gas effluent activity level. By system design, releases of radioactive material from plant operation are minor. Trying i

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 l l and the effect that sampling time may have on actual quantification of releases, the following example situation is evaluated.

f Consider a power increase (or decrease) on the first day of a seven (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 1

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 i concentration, the following equation is used:

} q =C1 F (1-e d it)

i mA g
where

Qg = quantity of activity on collection medium C air concentration of radionuclide i A!==decayconstantforradionuclidei j tl = sample time

= correction factor for collection efficiency m

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 I-131 concentration is 8esignated as C, and the one day increase is 10 C concentrationeqb.) l toFor C , the the remainder I-131 activity of the sampling on the collection period with a cartridgeisequalto'4.b6CF. 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.

. DAVIS-BESSE, UNIT 1 J-21

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 increase and analyzing collection cartridge at the end of the one a new cartridge at the end of 6 days sampling day (constituting a 7 day sampling period), the total activity (decay corrected to mid point of sampling periods) is determined to be 16.0 CgF.

By not analyzing the collection cartridge at the end of the one day increase, the total quantity of I-151 is underestimated by 14%. This analysis represents a somewhat worse case situation. The later into the 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 underestinations 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 contributor 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 C1and calculated maximum individual doses less than 0.01' aren. Even considering a hypothetical 14% increase for' sampling periods that may include iodine spiking in the primary coolant, the effect on

  • EPRI NP-939, " Sources of Radiciodine at Pressurized Water Reactors".

Science Applications, Inc., November 1978 DAVIS-BESSE, UNIT 1 J-22 l

t .

l l

i total releases and calculated doses is still negligible. The actual increase vill 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

i DAVIS-BESSE, UNIT 1 J-23 L s'

I Condensate Demineralizer Backwash Receiving Tank = Radioactivity Control 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-oide 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-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 needed 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 demineralizar 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, contaminated resins to the settling basin, no off-site releases would occur. All resins and radioactive material would be retained on-site 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 vf the regulatory limits.

DAVIS-BESSE, UNIT 1 J-24 l

Y .- - _ _ _ _ _ _ _ _ _ _ _ __ _

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 fror 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.

DAVIS-BESSE, U:11T 1 ~J-25 g 9- wsv,-\'

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 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 on 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/ml - 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.

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.

l The equation for LLD.in the Davis-Besse RETS is:

, 4.66 Sb E V 2.22 Y DAVIS-BESSE, UNIT 1 J-26

. - . . - __ ,- _m. A -- _ _ _ . ._

1 where:

)

S = the standard deviation of the background counting rate b

l

= JklT l

R = background counting rate T = counting time l

f E = counting efficiency V = sample size 2.22 = conversion factor (transformations per minute per picocurie)

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 tyiical 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 ratios are demonstrative of some of the relative difficulties in achieving in LLD of 5 x 10-7 uCi/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 sij o j 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 i

- ~

r 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 counting times would introduce a potential operational delay without commensurcte improvenent in detection capability. '

An improvement in the efficiency can be accomplished by the use of a more etficient GeLi detector. However, this increased efficiency is negated iu 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 with 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 capability, 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 10-6 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.

4 P

DBP 4306G DAVIS-BESSE, UNIT 1 J-28 i I

+_1. _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ __ _ _ _ _ _ _ _ _ _ _

_ _ _ _ _ _ _ a