Text

Offsite Dose Calculation Manual
	ML20098G340
Person / Time
Site:	Hatch
Issue date:	09/30/1984
From:	; GEORGIA POWER CO.
To:	;
Shared Package
ML20098G337	List: ML20098G336; ML20098G338; ML20098G340;
References
	PROC-840930-01, NUDOCS 8410040401
	Download: ML20098G340 (120)
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i TFSITE DOSE CALClLATION MANUAL e .

for GEORGIA POER COWANY E. I.-HATCH NUCLEAR PLANT ,

E SEPTEMBER 1984 h

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l i CFFSITE DOSE CALCULATION MANUAL for GEORGIA PO W.R COWANY i -

E. I. HATCH NUCLEAR PLANT a

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4 SEPTEMER 1984 1 -

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00CM, Hatch RE'V.1 2879W/0152W, 05/11/84 i-i r s.

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TAELE & CONTENTS SECTION TITLE PAGE LIST F T AELE S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11 L IST F F I GUE S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . iii EFE ENCE S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . iv INTRODUCTION .................................................. v

1. LIQUIO EFFLUENT S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1.0- 1 1.1 LIQUID EFFLUENT MONITOR SETPUINTS ....................... 1.0- 1 1.1.1 LIQUID RADWASTE EFFLUENT MONITORS . . . . . . . . . . . . . . 1.0- 2 1.1.2 PLANT SERVICE WATER MCNITORS . . . . . . . . . . . . . . . . . . . 1.0- 8 1.2 DOSE CALCULATION FOR LIQUID EFFLUENTS . . . . . . . . . . . . . . . . . . . 1.0-10 1.3 DOSE PROICTIONS FOR LIQUID EFFLUENTS . . . . . . . . . . . . . . . . . . . 1.0-18 1.3.1 MONTH.Y DOSE PROICTIONS . . . . . . . . . . . . . . . . . . . . . . . 1.0-18 1.3.2 DOSE PROICTIONS F OR SPECIFIC RELEASES . . . . . . . . . 1.0-19 1.4 DEFINITICNS & LIQUID EFFLUENT TERMS . . . . . . . . . . . . . . . . . . . . 1.0-20 1.5 LIQUID RADWASTE TEATENT SYSTEMS . . . . . . . . . . . . . . . . . . . . . . . 1.0-23 1.6 MIXING F LIQUID WASTE TANKS . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1.0-26

2. GASE QJS EFFLUENTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.0- 1 2.1 GATOUS EFFLUENT MONITOR SETPCINTS . . . . . . . . . . . . . . . . . . . . . . 2.0- 1 2.1.1 UNIT 1 REACTOR BUILDING VENT STACK , . . . . . . . . . . . . 2.0- 2 UNIT 2 EACTOR BUILDING VENT STACK, AND UNIT 1 RECOMIER BUILDING VENT 2.1.2 MAIN STA CK . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.0- 4 2.1.3 DETERMINATION & ALLOCATION FACTOR ............. 2.0- 5 2.2 GATOUS EFFLLENT DOSE RATE AND DOSE CALCLA.ATICNS ........ 2.0-10 2.2.1 UNESTRICTED AREA BOLNDARY DOSE RATE . . . . . . . . . . . 2.0-10 2.2.1.a Dose Rates Due To Noble Gases .................. 2.0-10 2.2.1.b Dose Rates Due to Radiciodines, Tritiun, ....... 2.0-10 and Particulates 2.2.2 UNRESTRICTED AKA AIR DOE AND DOSE TO INDIVIDUAL ..................................... 2.0-12 2.2.2.a Air Dose in Unrestricted Area .................. 2.0-12 2.2.2.b Dose To An Individual In Unrestricted Area ..... 2.0-13 2.2.2.c Dose Calculations To Stoport Other Specific .... 2.0-19 Technical Specifications 2.3 ETEORQ.0GICAL M00EL .................................... 2.0-57 2.3.1 ATMOS)HERIC DITERSION . . . . . . . . . . . . . . . . . . . . . . . . . 2.0-57 2.3.1.a Ground Level Releases . . . . . . . . . . . . . . . . . . . . . . . . . . 2.0-57 2.3.1.b Elevated Releases .............................. 2.0-58 2.3.2 RELATIVE DEPOSITION ............................ 2.0-61 2.4 DEFINITIONS CF GASEQJS EFFLUENT PARAETERS . . . . . . . . . . . . . . 2.0-69 2.5 GASEOUS RADWASTE EFFLUENT TREATENT SYSTEM . . . . . . . . . . . . . . 2.0-77

3. RADIQ_0GICAL ENVIRONENTAL HCNITORING PROGRAM . . . . . . . . . . . . . . . . . 3.0- 1 4 TOTAL DOSE DETERMINATIONS ..................................... 4.0- 1

5. POTENTIAL DOSES TO EMEERS T THE PUBLIC DUE TO TEIR '

ACTIVITIES INSIDE TE SITE BOUNDARY . . . . . . . . . . . . . . . . . . . . . . . . . . . 5.0- 1 00CM, Hatch REV.1 2879W/0152W, 05/11/84 i

LIST OF TABLES TABLE TITLE PAGE 1.2-1 Bioaccumulation Factors ........................................ 1.0-13 1.2-2 Adult Ingestion Dose Factors ................................... 1.0-14 1.2-3 Site Related Ingestion Dose Commitment Factors, ................ 1.0-16 Ah (Fisn Consumption) 2.1-1 Dose Factors for Exposure to a Semi-Infinite ................... 2.0- 8 Cloud of Noble Gases 2.1-2 Dose Factors for Exposure to Direct Radiation from ............ 2.0- 9 Noole Gases in the Elevated Finite Plume 2.2-1 Inhalation Dossi Factors For Infant ............................. 2.0-26 2.2-2 Inhalation Dose Factors for Child . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2.0-29 2.2-3 Inhalation Oose Factors For Teenager ........................... 2.0-32 2.2-4 Innalation Dose Factors For Adults ............................. 2.0-35 2.2-5 Ingestion Dose Factors for Infant .............................. 2.0-38 2.2-6 Ingestion Dose Factors for Child ............................... 2.0-41 2.2-7 Ingestion Oose Factors For Teenager ............................ 2.0-44 2.2-8 Ingestion Dose Factors For Adults .............................. 2.0-47 2.2-9 External Dose Factors for Standing on Contaminated Ground ...... 2.0-50 2.2-10 Individual Usage Factors ....................................... 2.0-52 2.2-11 Stable Element Transfer Data ................................... 2.0-53 2.2-12 Site-Specific (or Default ) values to be used in. . . . . . . . . . . . . . . . . 2.0-54 Pathway Factor Calculations 2.2-13 Site-Specific (or Default) Values to be used in Additional Pathway Factor Calculations .................................... 2.0-55 3.0-1 Radiological Environmental Sampling Locations .................. 3.0- 3 ODCM, Hatch REV.1 2879W/0152W, 05/11/84 11

LIST OF FIGURES FIGURE TITLE PAT 1.0-1 Example Calibration Curve for Liquid Effluent Monitor ......... 1.0-9 1.5-1 Liquid Radwaste Treatment System (Unit 1) ..................... -1.0-24 1.5-2 Liquid Radwaste Treatment System (Unit 2) . . . . . . . . . . . . . . . . . . . . . 1.0-25 2.3-1 Vertical Standard Deviation of Material in a PlumeZ (a ) * *'". 2.0-63 2.3-2 Open Terrain Recirculation Factor ............................. 2.0-64 2.3-3 Plume Depletion Effect for Ground-Level Releases .............. 2.0-65 2.3 4 Plume Depiction Effect for Greater Than 100-m Releases ....... 2.0-66 2.3-5 Relative Deposition for Ground-Level Releases ................. 2.0-67 2.3-6 Relative Deposition for Greater Than 100-m Releases .......... 2.0-68 2.5-1 Condenser Offgas Treatment System ............................. 2.0-78 3.0-1 Radiological Environmental Sampling Location Map (Site Periphery) .......................................... 3.0- 5 3.0-2 Radiological Environmental Sampling Location Map (Beyond the Site Vicinity) ................................

3.0- 6 ,

00CM, Hatch REV.1 2879W/0152W, 05/11/84 111

References

1. J. S. Beagli, R. R. Bellamy, W. L. Britz, and R. L. Waterfield,

" Preparation of Rxilological Effluent Technical Specifications for Nuclear Power Plants", NUREG-0133 (October 1978).

2. Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR 50, Appendix I, U.S. NRC Regulatory Guide 1.109 (March 1976).

3. Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Pug ose' of Evaluating Compliance with 10CFR 50, Appendix I, U.S. NRC Regulatory. Guide 1.109, Rev.1 (October 1977).

4 HNP-2 Environmental Report - Operating License Stage, Georgia Power Company, July 1975; (including Appendix A "Edwin I. Hatch P.lant Unit-1 Preoperational Environmental Surveillance Report Nunber 1; st.bnitted March 1, 1975.") -

5. " Final Safety Analysis Report", Georgia . Power Company, latch Nuclear Plant, Unit 1 ( M -1).

6. " Final Safety Analysis Report," Georgia Power Company, Hatch Nuclear Plant, Unit 2 (H W -2).

7 Methods for Estimating Atmospheric Transport and Distarsion of Gasecus Effluents in Routine Releases from Light-Water-Cooled Reactors, U.S. NRC Regulatory Guide 1.111 (March 1976). < ,

8. Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors, U.S. NRC ,

Regulatory Guide 1.111, Rev. 1 (July 1977).

9. Handbook of Mathematical Functions with Formulas, Graphs and Mathematical Tables; Edited by Abramowitz, M. and Stegun, I.A.; National Bureau cf Standards; U.S. Department of Commerce (1965).

10. Meteorology and Atomic Energy; Edited by' Slade, D.H.; U.S. Department of Commerce (July 1968).

11. 'EstimatinD Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Pugose of Implementing Appendix I, U.S. NRC Regulatory Guide 1.113, Rev. 1 (April 1977).

12. Plant Edwin I. Hatch Units 1 and 2 Thermal Plune Model Verification; M. C. Nichols and S. D. Holder; Georgia Power Comp'any Environmental Affairs Center; March 1981.

13 Effect of Eductors in Plant Hatch Liquid Waste Tanks; Georgia Power Company; October 1978.

4 00CM, Hatch REV.1 2879W/0152W, 05/11/84 iv

INTRODUCTION The TFSITE DOSE CALQJLATION manual is a stpporting docunent of the RADIO-LOGICAL EFFLUENT TECMICAL SPECIFICATIONS. As sLch the COCM describes the methodology and parameters to be used in the calculaticn of offsite doses due to radioactive liquid and gaseous effluents and in the calculaticn of liquid and gaseous effluent monitoring instrunentaticn alarm / trip setpoints. The

' 00CN contains a list and graphical descripticn of the specific sanple loca-tions for .the radiological environmental monitoring program. Schematic ccnfigurations cf liquid and gaseous radwaste effluent syster.s releases to (nrestricted areas are also included.

The 00CM will be maintained at the plant f ar use as a reference guide and

! ' training docunent of accepted methodologies and calculations. Changes in the calculational methods or parameters will be incorpcrated into the - 00CM in ceder to assure that the 00CM represents the present methodology in all applicable areas. Conouter scf tware to perf orm the described calculaticns will be maintained ctrrent with the ODCM.

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f 1

i G)CM, Hatch EV.1 V 2879W/0152W, 05/1.1/84

SECTION 1.

LIQUID EFFLUENTS Ine E. I. Hatch Nuclear Plant is located on the Altamaha River which supplies makeg water to the Circulating Water System and receives decant from the Cooling Tower. There are two Boiling Water Reactors'on the site; each unit is served by its own Liquid Radwaste System. The two units release liquid radwaste to separate discharge lines from the Circulating Water Systems.

Additional dilution flow is furnished by the Cooling Tower blowdown, Turbine Building service water, and the Plant Service Water System, ~ if. necessary.

Since each unit is served-by a separate dilution stream, liquid releases may be made independently from each of the two units. Releases from the Plant Service Water ' Systems are to the Main Condenser Circulating Flume or to the Cooling Tower Blowdown Discharge Line when needed for additional dilution.

Althougn no significant releases of radioactivity are expected from the Plant Service Water Systems, these effluent pathways are monitored as a precautionary measure.

1.1 LIQUID EFFLUENT MONITOR SETPOINTS Although each unit has unique liquid release sources, a separate radwaste system, independent liquid effluent radiation monitors and separate dilution streams, the radiation monitor setpoint methodology presented below is appropriate for both units.

The calculated liquid monitor setpoint values will be regarded as upper bounds for the actual setpoint adjustments. Setpoint adjustments are not required to be performed if the existing setpoint level corresponds to a lower count rate than the calcula,ted value. The actual monitor setpoint, which corresponds to the calculated concentration plus background for the specific monitor, is determined from calibration data or from operational data associated with liquid sample analysis data. (See Section 1.1.1). If no release is planned 00CM, Hatch REV.1 1.0-1 2879W/0152W, 05/11/84

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i; I for a particular pathway, or if there is no detectable activity in the planned releasea -the monitor setpoint should be established as close to background as practical ' to prevent spurious alarms and yet alarm should an inadvertent release occur.

1.1.1 LIQUID RADWASTE EFFLUENT RADIATION MONITORS The liquid radwaste effluent line monitors provide alarm and automatic termination of release functions prior to exceeding the concentration limits specified in 10CFR 20, Appendix B, Table II, Column 2 at the release point to Lthe unrestricted area. To meet this specification, the alarm / trip setpoints for the liquid effluent monitors and flow measurement devices are set to assure that the following equation is satisfied:

SCypg U g 7 (pg = the effluent concentration limit (RETS 3.15.1.1 for Unit 1; 3.11.1.1 for Unit 2) implementing 10CFR 20 for the site, corresponding to the specific mix of radionuclides in the waste tank being considered for discharge, in pCi/ml.

c = the 'setpoint, in pCi/ml, of the r&dioactivity monitor which measures the radioactivity concentration in the effluent line prior to dilution and subsequent release; the Setpoint, which is inversely proportional to the volumetric flow of the effluent line and proportional to the volumetric flow of the dilution stream plus

-the effluent stream, represents a value which, if exceeded, would result in concentrations exceeding the limits of 10CFR 20 in the unrestricted area. ,

f = the flow setpoint as determined at the radiation monitor location, in volume per unit time, but in the same units as F, below.

F = the dilution water flow setpoint as determined prior to the release point, in volume per unit time.

0004, Hatch REV.1 1.0-2 2879W/0152W, 05/11/84 u

i As stated earlier, at Plant Hatch, each of the two units is served by its own independent Liquid Radwaste System; the two Liquid Radwaste Systems discharge .

to separate dilution streams. If additional dilution flow is needed for either dilution stream,'it is available from the Plant Service Water System.

The two dilution streams release to the Altamaha River.

The sources of liquid radioactive effluents from Unit-1 are Waste Sample Tank A, Waste Sample Tank B, Chemical Waste Sample Tank A, Chemical Waste Sample

' Tank 8, Floor Drain Sample Tank, Laundry Drain Tank A, Laundry Drain Tank B, and Domineralizer Feed Tank. All of these sources discharge to a common line

[ which is served by Radiation Monitor 1011-N007. These Unit-1 sources release to a dilution stream . served by flow element FE N-501, which is capable of isolating liquid radwaste discharges from Unit-1 if pre-defined minimum dilution flow is not available in the dilution stream.

The sources of liquid radioactive effluents from Unit-2 are Waste Sample Tank A, Waste Sample Tank B, Chemical Waste Sanple Tank A, Chemical Waste Sample Tank B, and Floor Drain Sample Tank. All of these sources discharge to a '

common line which -is served by Radiation Monitor 2011-N007. These Unit-2 sources release to a dilution stream served by flow element FE N-502, which is capable of isolating liquid radwaste discharges from Unit-2 if pre-defined

, minimum dilution flow is not available in the dilution stream.

i !

Liquid radwaste releases from the two units may proceed independently and concurrently. Liquid radweste releases from each unit, however, will be administrative 1y controlled so that only one source of liquid radwaste will be released at a time from that unit.

The maximum liquid radwaste effluent flow from the source selected for release and the setpoint for the radiation monitor serving the discharge pathway are i .. ._ determined and set to meet the general conditions of equation (1) for a given eff. bent concentration. The method by which this is accomplished is as fallows:

ODCN, Hatch REV.1 1.0-3 j

2879W/0152W, 05/11/84 1:

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Step 1) The radionuclide concentration for a waste tank to be released is cotained from the sum of measured concentrations as determined by the analyses required in RETS Tables 4.15.1-1 (Unit-1) and 4.11.1-1 (Unit-2):

Ci= Cg + (Ca+Cs + Cr + Ct }

(2) where C

g

= the concentration of each measured gama emitter observed by gamma-ray spectroscopy of the particular waste sanole.

C, = the concentration of alpha emitters in liquid waste as measured in <

the MONTii.Y composite sample. (NOTE: Sagle is analyzed for gross a).

C, = the measured concentrations of Sr-89 and Sr-90 in liquid waste as observed in the QUARTERLY composite sample.

C = The measured concentrations of Fe-55 in liquid waste as observed in 7

the QUARTERLY composite sample.

C = the measured concentration of H-3 in liquid waste as determined t

from analysis of the MONTit.Y composite sagle.

The C g term will be included in the analysis of each batch; terms for alpha, strontiums, iron, and tritiun will be included in accordance with RETS Tables 4.15.1-1 and 4.11.1-1 as appropriate.

Step 2) The measured radionuclide concentrations are used to calculate a Dilution Factor, DF, which is the ratio of total dilution flow rate to tank flow rate required to assure that the limiting concentration of 10CFR 20, Appendix B, Table II, Column 2 are met at the point of discharge.

ODCM, Hatch REV.1 , 1.0-4 2879W/0152W, 05/11/84

DF = [ i t SF i MPCi C C C C a s + SF

= [ _.CJL. + , , f , t (3) g% % MPCs MPCr MPCt

~ ~

where Cg = measured concentrations of C, g C, , C,, C 7

and C t as defined in Step 1. Terms C, , C,, C, 7

and Cg

,will be included in the calculation as appropriate.

MPCg = MPC ,

g MPC,, MPC, , MPC ,

7 and MPC t

are limiting concentrations of the appropriate radionuclide from 10CFR 20, Appendix B, Tacle II, Column 2. For dissolved or entrained nocle gases, the concentration shall be limited to 2 x 10-' pCi/ml total activity.

SF = the safety factor; a conservative factor selected to compensate for statistical fluctuations and errors of measurements. (For example, SF = 0.5 corresponds to a 100 percent variation.) .

Step 3) The dilution flow monitor setpoint is determined for the minimum dilution flow rate, F; d for Plant Hatch, F d

is normally estaolished at 10,000 Epm.

Step 4) For the case DF '< ,1, the waste tank effluent concentration meets the limits of 10CFR 20 without dilution and effluent disenarge flow rate may be assigned any desired value. For OF > 1, the maximum permissible discharge flow rate, fg, must be calculated

~

f + p for F ## I b) t= W W d 9 wnere F

d

= Minimtm dilution flow rate to De used in effluent monitor setpoint calculations wnich is normally 10,000 gpm.

00CM, Hatch ~REV.1 1.0-5 2879W/0152W, 05/11/84 4

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I DF = Dilution Factor from step 2.

f p

= Flow rate of waste tank discharge. (This value will have an upper limit of the maximum discharge capacity of tne particular waste tank pisp.)

NOTE: If radioactivity from plant operations is detected in the dilution stream, the equation for calculation of f est is1We a term to t

account for radioactivity present in the dilution stream prior to the introduction of the waste tank effluents d

bI l d.

(5) 7 "

t of wnere, Cg is the MPC fraction of the dilution stream prior to g

i NK, d introduction of waste tank effluent.

Step 5) The liquid radwaste effluent radiation monitor setpoint may new be determined based on the values of I C1 , ft and Fo whien were i

specified to provide compliance with the limits of 10CFR 20, Appendix B, Taele II, Column 2. The monitor response is primarily to gamma radiation,therefore,theactualsetpointisbasedongC.g The mordtor setpoint which corresponds to the particular setpoint concentration, c, is determined based on monitor calibration data or on werational data whicn correlates monitor response to sample analyses associated with actual effluent releases. (Example of monitor calleration graph is shown in Figure 1.0-1.)

The setpoint concentration, c, is determined as follows:

c = A [ CgpCi- (6) g ml ODCM,Haten REv.1 1.0-6 i 2879W/0152W, 05/11/84 G

-.._..-------__-.h._____

e-whers -

A = Adjustment factor which will allow the setpoint to be established in a practical manner for convenience and to prevent spurious alarms.

t

= (See Note 2 below) (7) f(actual)

If A > 1, Calculate c and determine .the maximum value for the actual monitor setpoint (uC1/ml).

If A < 1, No release may be made. Re-evaluate Steps 2, 3, and 4.

NOTE 1: The calculated setpoint concentration, c, establishes the base value for the monitor setpoint. However, in establishing the actual monitor setpoint for a particular monitor, background radiation levels must be considered. Normally, the actual monitor setpoint includes the calculated' setpoint value plus

, background. Background levels must be controlled such that radioactivity levels in the effluent stream being monitored can be accurately assessed at or below the calculated setpoint value.

NOTE 2: If 0F < 1, A = (1/DF). As stated earlier, if DF=0 the .

radiation monitor setpoint should be establisned as close to background as practicable to prevent spurious alarms and yet alarm should an inadvertent radioactive release occur.

If calculated setpoint values are near actual concentrations planned for release, it may be impractical to set the monitor alarm based on tnis value.

In this case a new setpoint may be calculated by decreasing the effluent flow, increasing the dilution flow, or by decreasing Ci by further processing of the liquid radwaste planned for release, an{d by following the method presented in Steps 2, 3. and 4.

Within the limits of the conditions stated above, monitor setpoints for Liquid Radwaste Effluent Radiation Monitors may be determined as follows:

0004, Hatch REV.1 1.0-7 2879w/0152W, 05/11/84 i

i

Liquid Radweste Effluent Radiation Monitor 1011 - N007 (Unit 1) or 2011-N007 (Unit 2)

Perform Step 2), solving equation (3) for OF using the appropriate values in the concentration term from the sample analyses for the particular waste tank catch to be discharged. Then perform Steps 3), 4), and 5) to determine tne monitor setpoint.

If no disenarge is planned for tnis pathway, or if the planned release contains no measurable radioactivity, the monitor setpoint should be established as close to background as practical to prevent spurious alarms and yet alarm should an inadvertent radioactive release occur.

1.1.2 PLANT SERVICE WATER MONITORS

, Monitors: 1011-N008 (Unit 1) and 2011-N008 (Unit 2) ,

Concentration of radioactivity in these effluent lines normally is expected to be insignificant. Therefore, the monitor setpointt should be establisned as close to background as practical to prevent spurious alarms and yet alarm snould an inadvertent release occur.

If either of these effluent streams should become contaminated witn radioactivity, radionuclide cont entrations must be determined and a radiation monitor setpoint determined as follows:

c = ( I Cg) + OF (8) g where ICg and 0F are determined using the sample analysis results for this ef-g fluent stream ind applyin'g'the metnocology of Section 1.1.1 Step 1 and Step 2.

For these release patnways no additional dilution is taken into account.

Therefore, no releases are permissible if 0F > 1.

0004, Hatch REV.1 1.0-8 2879W/0152w, 05/11/84

FIGLRE 1.0-1 EXAMPLE CALIBRATION CURVE FOR LIQUID EFFLUENT MONITOR 18* *> ,

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af u kre p i 'l M f.d -1.c 4 u ~ -. , t4. l - '-l l M * : 2 H f a s s

40 9

....4 ..

1411 f44w c m y g. i. 1 i ; i.n i , i . . .v . . :.

i m, .r.. .n _ .,. , , . ,r 1 ?-

.' . ~)(i i a* b .-- t'- i ^ ?- :- A . : l ,.1' ';..>'

8

. ~.;

t t fs

l. ..a... . - J=._..__..

se es,

..l: .- - - - - - .---<--r . . 11. . -. -. -: -. -. . .-

_~i . . .. ! ... .I.gi l to' to' cm to* tos 0004, Heten REY.1 1.09 2879W/0152W, 05/11/84

1.2 DOSE CALCULATION FOR LIQUID EFFLUENTS For liquid releases from Plant Hatch to the Altamaha River, the only human l

exposure pathway is due to ' consumption of fish taken from tne river. No drinking water is taken from the Altamaha River downstream from Plant Hatch.

The methodology for calculating doses to an individual due to fish consumption is presented in tnis section.

The dose contribution to the maximum exposed individual by way of fisn consumption from radionuclides identified in liquid effluents released to unrestricted areas will be calculated for the purpose of iglementation of RETS 3.15.1.2 (Unit 1) and 3.11.1.2 (Unit 2). In accordance with Appendix A of Reference 3, noble gases are excluded from these dose calculations. Doses to an ir.dividual are calculated as follows:

m At ic y (9)

D, a {A, y . Atg C h, where 0 = The cumulative dose commitment to the total body or any organ, t ,

due to radioactivity in liquid effluents for the total time period ,

m I A tg , in mrem (Reference 1).

t =1 Atg = The length of the tth time period over which Cg and Fg are averaged for all liquid releases, in hours. ,

Cg = The average concentration of radionuclide 1, in undiluted liquid effluent during time period Atg from any liquid release, in p C1/ml.

A g

= The decay constant for radionuclide 1. (sec."1) t = The transit time from release to receptor. (24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ; Table C-D, c

Reference 3).

0004, Hetch REV.1 1.0-10 2879W/0152W, 05/11/84

l s Fg = The near field average dilution factor in the receiving water body during any liqu'i d effluent release. Defined as the ratio of the indiluted liquid waste flow during release to the product of the average flow from the discharge structure to unrestricted receiving water times Z.

Fg = (average undiluted liquid waste flow) (10)

(average flow from the discharge structure during periods of radioactive materials release) x (Z)

NOTE: The denominator of equation (10) is limited to 1000 cfs or less.

(Reference 1, Section 4.3).

where Z = Applicable dilution factor for the receiving water body.

Z = 10 (Reference 4, Section 5.1; Reference 11, Section B; Reference 12).

A 1

= The site related fish ingestion dose commitment factor to the total body or any organ i for each identified principal gamma and beta emitter listed in Table 1.2-3 in mrem-m1 per hr-pC1.

Ah=Kg (4 BF1) 0Fh (ll}

where K

g

= Units conversion factor 1.14 x 10' 106 pCi x 10 3ml + 8760 hr pCi 1 yr U

F

=. Adult fish consumption (21 kg/yr).

BF = Bioaccumulation factor for radionuclide 1, in fisn, in 1

pCi/kg per pC1/1 from Table 1.2-1 (ta<en from Table 2.3-1 of Appendix A of Reference 4).

ODCM, Hatch REY.1 1.0-11 2879W/0152W, 05/11/84

OF h

= Dose conversion factor 'for radionuclide 1, for adults in preselected organ, T, in mrem /pC1, from Taole 1.2-2 (taken from Reference 3, Table E-11). -

At Plant Match no measurable radioactivity is expected to be present in the dilution stream prior to the junction with the Liquid Radwaste Discharge Line. However, if radioactivity due to plant operations thould be detected in the dilution stream prior to the junction with the Liquid Radwaste Discharge Line, the concentrations of those radionuclides found to be present must be included in the dose determination. For this part of the dose calculation, equation (9) is .used with Fg = 1/Z and a t = the entire time period for whicn the dose is being calculated.

ODCM, Hatch REV.1 1.0-12 2879W/0152W, 05/11/84

. TABLE 1.2-1 BIDACCLMULATION FACTORS (pCi/kg per pCi/ liter)*

FRESHWATER ELDENT FISH H 9.0E-01 C 4.6E 03 NA 6.6E 01 P 2.5E 04 CR 1.5E O2 MN 8.9E 01 FE 6.0E 00 CO 1.7E 02 NI 1.0E 02 CU 4.4E 01 ZN 2.9E 02 BR 4.2E 02 RB 2.0E 03 SR 3.8E 00 Y 2.5E 01 ZR 1.9E 02 NB 4.lE 01 AU l.BE 02 TC 1.5E 01 RU 4.6E 00 RH 1.0E 01 AG 3.5E 02 TE 4.0E 02 I 4.3E 01 CS 5.8E 02 BA 5.0E 00 LA 2.5E Ol' CE 8.4E 01 PR 2.5E 01 ND 4.6E 01 W l.2E 03 NP 1.0E 01 e

i

' Values in Table 1.2-1 are taken from Table 2.3-1 of Appendix A of Reference 4.

0004, Hatch REV.1 1.0-13 2879W/0152W,'05/11/84 L

TABLE 1.2-2 Page 1 of 2 ADULT INGESTION DOSE FACTORS *

(mrem /pCi ingested) l NUCLICE DONE L I Ytt T.40CY TNYEDIO ElDNEY LUNG GI-LLI N 3 40 DATA 1.05E-07 1. 05E -0 7 1.C5E-07 1.05E-07 1.0$E-07 1.05E-07 C 14 2.84E-06 5.68E-07 5. 6 8E -0 7 5.68E-07 5.68E-07 5.68E-07 5.685-07 NA 24 1.70E-06 1.70E-06 1. 70E-06 1.F0E-06 1.70E-06 1.70E-06 I.70E-06 P 32 1.93E-04 1.20E-05 7. 46 E -0 6 40 DATA NC OATA NO DATA 2.17E-05 C4 51 No DATA 40 CATA 2. 66E -0 9 1.59E-09 5.86E-10 3.53E-09 6.69E-07 MN 54 40 OATA 4.57E-04 8. 72 E-0 7 NO DATA 1.36E-06 NO DATA 1.40E-05 mm 56 No DATA 1.15E-07 2.04E-08 NO DATA 1.46E-07 NO DATA 3.67E-06 FE 55 2.75E-06 1.90F-04 4.4 J E-0 7 NO DATA NO DATA 1.06E-06 1.09E-06 FE 59 4.34E-06 1.02E-05 3. 9 t E-0 6 NO DATA NO DATA 2.85E-06 3.40E-05 CD 58 NO DATA 7.456-07 1.67E-06 40 DATA No DATA NO DATA I.51E-05 CO 60 NO DATA 2.14F-04 4.72E-06 NO DATA N0 DATA NO DATA 4.02E-05 MI 63 1.30E-C4 9.01E-06 4. 3 6 E -0 6 No DATA No DATA NO DATA 1.44E-06 NI 45 5.28E-07 6.s6E-08 3.13 E -0 8 40 OATA NO DATA No DATA 1.74E-06 CU 64 NO DATA 8.33E-04 3. 91 E-0 8 NO DATA 2.10E-07 Nn DATA 7.80E-06 2N 65 4.84E-06 1.54E-05 6. 9e E -0 6 NO DATA 1.03E-05 NO DATA 9.70E-06 2N 69' t.03E-08 1.97E-08 3.37E-09 NO DATA 1.28E-08 No DATA 2.96E-09

, S4 83 NO DATA No DATA 4. 02 E-0 8 40 DATA NO DATA NO DATA 5.79E-08 SR 84 NO DATA NO DATA 5.2tE-08 NO DATA NO DATA NO DATA 4.09E-13 SR 85 NO DATA NO DATA 2.14 E-0 9 NO DATA NO DATA NU DATA LT E-24 48 86 NO DATA 2.t!E-05 9. 8 3 E-0 6 Nn DATA NO DATA 40 DATA 4.16E-06 28 88 NO DATA 6.0SE-08 3.21E-08 NO DATA No DATA NO DATA 8.36E-19 48 09 NO DATA 4.0tE-08 2 82E-58 NO DATA NO DATA NO DATA 2.33E-21 SR 89 3.08E-04 NO DATA 8. 84 E-0 6 No DATA No CATA NO DATA 4.94E-05 l SR 90 7.58E-03 NO DATA 1.86E-03 NO DATA NO DATA NO DATA 2.19E-04 l

SR 91 5.67E-06 No DATA 2. 29 E -0 7 NO CATA NC DATA NO DATA 2.70E-05 SR 92 2.15E-06 M0 DATA 9.30E-08 NO DATA NO DATA N0 DATA 4.26E-05 Y 90 9.62E-09 MO DATA 2.58E-10 40 DATA N0 DATA NO DATA 1 02E*04 Y 9tN 9.09E-11 NO DATA 3.52E-12 No DATA No DATA No DATA 2.67E-10 l Y 91 1.4tf-07 40 DATA 3.77E-09 NO DATA NO DATA NO DATA 7.76E-05

! Y 92 8.45E-10 NO CATA 2. 4 7 E-11 NO DATA NO DATA NO DATA 1.48E-05 l

V 93 2.68E-C1 No DATA 7.40E-11 NO DATA No DATA NO DATA 8.50E-05 23 95 3.04E-08 9.75E-09 6. 60 E-0 9 NO OATA 1.53E-08 NO DATA 3.09E-05 la 97 1.68E-09 3.39E-10 1.5 5 E-10 NO DATA 5 12E-10 NO DATA 1.0$E-04 M4 95 6.22E-09 3.46E-09 1. 86 E -0 9 NO DATA 3.42E-09 NO DATA 2.10E-05 Mn 99 NO DATA 4.31E-06 8.20E-07 NO DATA 9.76E-06 NO DATA 9.99E-06 TC 99a 2.67E-10 6.98E-10 0.89E-09 NO DATA 1 06E-08 3.42E-10 4.13E-07 TClot 2.54E-10 3.66E-10 3. 59 E -0 9 10 OATA 6.59E-09 1.87E-10 1.10E-21 aut03 1.85E-07 40 04th T.9fE-08 40 DATA T.06E-0T NO DATA 2.16E-05 mul0S 1.54E-08 NU DATA n.00E-01 NO DATA 1.99E-07 NO OATA 9.42E-06

Values in Table 1.2-2 are taken from Reference 3, Table E-11.

ODCN, Hatch REV.1 1.0-14 2879W/0152W, 05/11/84 i

I r,,-, .

_ . _ --__..--_._-----,---.r__. . . , . _ - . -w, ,_-_-

l TABLE 1.2-2 (Continued) i Page 2 of 2 ,

l l

seUCi10E 8088E L IVE S T.800f TNv8010 SiONEY LussG GI-LLI SU106 2 75E-06 No DATA 3. 48E -0 7 NO DATA 5.3tE-06 NO DATA 1. 7 8 E -04 ACllON 1 60E-07 1 48E-07 8.79E-05 40 DATA 2.9tE-07 NO DATA 6,04E-05 fE125N 2 68E-06 9.71E-07 3.59E-0 7 8.06E-07 1.09E-05 NO DATA 1.07E-05 TE127m 6.77E-06 2.42C-06 8.25 E -0 7 1.73E-06 2.75E-C5 NO DATA 2.27E-05 TE127 1 10E-07 3.95E-08 2. 38E -0 8 8.15E-08 4.48E-07 ND DATA 8.68E-06 '

TE129N 1.15E-05 4.29E-06 1.A2E-06 3.95E-06 4.80E-05 NO DATA 5 79E-05 TE129 3 14E-08 1.18E-04 7.63E-09 2.4tE-08 1.32E-07 NO DATA 2.37E-08 TEt3tN 1 73E-06 8.46E-07 7. 05 E-0 7 1.34E-06 8.57E-04 NO DATA 8.40E-05 TE131 .1 97E-08 8.23E-09 6. 22 E-0 9 1 62E-08 s.63E-08 No DATA 2.79E-09 TE132 2.52E-06 1. 6 3E- 06 1. 5 3E-0 6 1 80E-06 1 57E-05 NO DATA 7.71E-05 I 130 7.56E-07 2. 2 3E-06 8. 80E -0 7 1.89E-04 3.48E-06 NO DATA 1.92E-06 1 131 4.16E-06 5. 9 5 E-06 3. 4 t E-0 6 1 95E-03 1.02E-05 NO DATA 1.57E-06 I 132 2.03E-07 5.43E-07 1.90E-07 1.90E-05 8.65E-07 .NO DATA 1.02E-07 1 133 1.42E-06 2.4FE-06 7. 53 E-0 7 3.63E-04 4.31E-06 NO DATA 2.22E-06 I 134 1.06E-07 2.88E-07 1.03E-OF 4.99E-06 4.58E-07 NO DATA 2.5tf-10 1 135 4.43E-07 1.16E-04 '4.28E-07 7.65E-05 1.86E-06 NO DATA 1.3tE-06' C5134 6.22E-05 1.48E-04 1.2tE-04 No DATA 4.79E-05' l.59E-05 2.59E-06 C5136 6.51E-06 2.57E-05 1. 85E -0 5 NO DATA 1.43E-05 1.96E-06 2.92E-06 C5137 7.97E-05 1.09E-04 7.14 E -0 5 NO DATA 3.70E-05 1.23E-05 2.llE-06 C5138 5.52E-08 1.09E-07 5. 40E -0 8 No Data 8.01E-08 7.9tE-09 4.65E-13 SA139 9.70E-08 6.91E-11 2. 84 E -0 9 NO DATA- 6.46E-11 3 92E-11 1.72E-OF P

SAI40 2.uJE-05 2.55E-08 1. 3 )f-0 6 N0 DATA 8.67E-09 1.46E-08 4.18E-05 n4141 4.FIE-08 1.56E-11 1 59E-09 No DATA 3.31E-It 2.02E-11 2.22E-17 44142 2.13E-08 2.19E-11 1. 34 E-0 9 NO DATA 1.85E-11 1.24E-11 1.00E-26 Lal40 2.50E-09 1.26E-09 J.3JE-10 NO DafA NO DATA NO DATA 9.25E-05 L A142 1.28E-10 5.825-!! 1.45E-11 NO DATA NO DATA NO DATA 4.25E-07 CE141 9.36E-09 6.33E-09 7.18 E-10 NO DATA 2.94E-09 NO DATA 2.42E-05 CE143 1.65E-09 1.22E-06 1.35E-10 ~ NO DAT A 5.37E-10 NO DATA 4.56E-05 C E 144 4.ASE-07 2.04E-07 2.62E-08 NO DATA- 1.21E-07 NO DATA 1.65E-04 Pal 43 9.20E-09 3.69E-09 4.56E-10 No DATA 2.13E-09 NO DATA 4.03E-05 PRI44 3.0lE-!! 1.25E-11 1.5 sE-12 NO DATA 7.05E-12 NO DATA 4.33E-18

i. Not47 6.29E-09 7.27E-09 4.35E-10 NO DATA 4.25E-09 NO DATA 3.49E-05 3

= 197 1.01E-07 8.6tE-08 3.01 E-0 8 NO DATA NO DATA NO DATA 2.82E-05 NP239 1.19E-09 1.17E-10 6.4 5E-1 1 .NO DATA 3.65E-10 NO DATA 2.40E-05

Values in Taole 12 .- 2 are taken from Reference 3 Table E-ll. ,

ODCM, Hatch- REV.1 1.0-15 2879w/0152W, 05/11/84

, . . _, _ __ . - - . _ - . ~ - _ - - - - . , . _ - . _ . _ . ~ _ _ . _ _ , _ _ . . . . . _ _ . _

TABLE 1.2-3 Page 1 of 2 SITE RELATED INGESTION DOSE COMMITMENT FACTOR, A (FISH CONSLNPTION) l h

(mrem /hr per pCi/ml)

WUCL1DE SONE liver i T. BODY THYROID FIDHEY LUNG 31-LL1 H-3 0.00E+00 2.26E-01;2.26E-81 2.26E-01 2.26E-01 2.26E-81 2.26E-01 C-14 3.13E+04 6.26E+0316.26E+03

, 6.26E+03 6.26E+03 6.26E+03 6.26E+03 Ma-24 2.69E+02 2.69E+02 2.69E+02 2.69E+02 2.69E+02 2.69E+02 2.69E+02 P-32 1.16E+0? 7.18E+05 4.46E+05 0.00E+00 0.00E+00 0.00!+00 1.30E+06 Cr-51 0.00E+00 0.00E+08 9.55E-81 5.71E-01 2.10E-01 1.27E+00 2.40E+02-Mn-54 0.00E+00 9.74E+02 1.06E+02 0.00E+00 2.90E+02 0.00E+00 2.90E+03 Mn-56 0.00E+00 2.45E+01 4.35E+00 0.00E+00 3.11E+01 0.00E+00 7.82E+02 Fe-55 3.95E+01 2.73E+01 6.36E+00 0.00E+00 0.00E+00 1.52E+01 1.57E+01 Fe-59 6.23E*01 1.47E+02:5.62E+01 0.00E+00 0.00E+00 4.09E+01 4.88E+02 Co-53 0.00E+00 3.03E+02:6.80E+02 0.00E+00 0.00E+00 0.00E+00 6.15E+03 Co-iO 0.00E+00 8.71E+02 1.92E+03 0.00E+00 0.00E+00 0.00E+00 1.64E+04 Ni-63 3.11E+04 2.16E+03;1.04E+03 0.00E+00 0.00E+00 0.00E+00 4.50E+02 Ni-i! 1.26E+02 1.64E+01 7.49E+00 0.00E+00 0.00E+00 0.00E+00 4.17E+02 Cs-i4 0.00E+00 8.??E+00 4.12E*00 0.00E+00 2.21E+01 0.00E+00 7.48E+02 Zn-65 3.36E+03 1.07E+04 4.63E+03 0.00E+00 7.15E+03 0.00E+00 f.73E+03 Zn-69 7.15E+00 1.37E+01 9.51E-01 0.00E+00 6.89E+00 0.00E+00 2.06E+00 Be-83 0.00E+00 0.00E+00 4.04E+01 0.00E+00 0.00E+00 0.00E+00 5.22E-01 3r-84 0.00E+00 0.00E+00 5.24E+01 0.00E+00 0.00E+00 0.00E+00 4.11E-04 3r-85 0.00E+00 0.00E+00j2.15E+08 0.00E+00 0.00E+00 0.00E*00 1.01E-15 Rb-86 0.00E+00 1.01E+05 4.71E+04 0.00E+00 0.00E+00 0.00E+00 1.99E+04 Rb-88 0.00E+00 2.90E+02 1.54E+02 0.00E+00 0.00E+00 0.00E+00 4.00E-09 Re-39 0.00E+00 1.92E+02:1.35E+02 0.00E+00 0.00E+00 0.00E+00 1.12E-11 Sr-89 2.80E+03 0.00E+00j8.04E+01 0.00E+00 0.00E+0e 0.00E+00 4.49E+02

$r-90 6.90E*04 0.00E+00:1.69E+04 0.00E+00 0.00E+00:0.00E+00 1.99E+03 Sc-91 5.16E+01 0.00E+00!2.08E+00 0.00E+00 0.00E+00 0.00E+00 2.46E+02 Se-92 1.96E+01 0.00E+00lS.46E-01 0.00E+00 0.00E+00 0.00E+00 3.3SE*02 Y-?O 5.76E-01 0.00E+00,1.54E-02 0.00E+00 0.00E+00 0.00E+00 6.10E+03 Y-918 5.44E-03 0.00E+00'2.11E-04 0.00E+00 0.00E+00 0.00E+00 1.60E-02 Y-91 S.44E+00 0.00E+00 2.26E-01 0.00E+00 0.00E+00 0.00E+00 4.64E*03 i Y 42 5.06E-02 0.00E+00 1.46E-03 0.00E+00 0.00E+00 0.00E*00 8.?6E*02 Y-93 1.60E-01 0.00E+00[4.43E-03 0.00E+00 0.00E+00 0.00E+00 5.09E+03 Zr-95 1.3?E+01 4.43E+00*3.00E+00 0.00E+00 6.96E+00 0.00E+00 1.41E+04 2r-97 7.64E-01 1.54E-01 7.05E-02 0.00E+00 2.33E-01 0.00E+00 4.78E+04 Nb-95 6.11E-01 3.40E-01 1.83E-01 0.00E+00 3.36E-01 0.00E+00 2.06E+03 Mo-99 0.00E+00 1.06E+03 3.53E+02 0.00E+00 4.21E+03 0.00E+00 4.30E+03 Tc-99m 8.87E-03 2.51E-02.3.19E-81 0.00E+00 3.01E-01 1.23E-02 1.48E+02 '

~

Tc-101 9.12E-03 1.31E-02 1.29E-01 0.00E+00 2.37E-01 6.72E-03 3.95E-14 Ru-103 2.04E+00 0.00E+00 0.70E-01 0.00E+00 7.77E+00 0.00E+00 2.38E+02 Ru-105 1.~0E-01 3.00E+00.6.70E-02 0.00E+00 2.19E+00 0.00E+00 1.04E*02 Calculated using Equation (11)

ODO4, Hatch REV.1 1.0-16 2879W/0152W, 05/11/84 ew, --- -wwe,,--w--eww-e ,,---e--vm- e=-ww~- - - - , * = - w

TABLE 1.2-3 (Continued)

Page 2 Of 2 NuCL1DE BONE LIVEE i T.50DY THYROID AIDNEY LuHG *1-LLI l Ru-106 3.03E+01 0.00E+00'1.93E+00 0.00E+00 5.85E+01 0.00E+00 1.96E+03'!

Ag-110m 1.34E+02 1.24E+02'7.37E+01 0.00E+00 2.44E+02 0.60E+00 Te-125m 2.57E+03 9.30E+02 3.44E+02 7.72E+02 1.04E+04 0.00E+00 5.06E+04l 1.02E+04 Te-127m 6. die +03 2.32E+03.7.90E+02 1.66E+03 2.63E+04 0.00E+00 2.17E+04' Te-127 1.0!E+02 3.73E+01!2.28E+01 7.80E+01 4.29E+02 0.00E+00 5.31E+03' Te-129m 1.10E+04 4.11E+03;1.74E+03 3.78E+03 4.60E+04 0.00E+00 5.54E+04l Te-129 3.01E+01 1.13E+01,7.33E+00 2.31E+01 1.26E+02 0.00E+00 2.27E-01' Te - 131 r ,1. 66E+ 03 ?.10E+02;6.7?E*02 1.28E+03 S.21E+03 0.00E+00 6.04E*04' Te-121 1.??E+01 7.89E+00'5.9fE+00 1.55E+01 8.26E+01 0.00E+00 2.iTE-06 Te-132 2.41E+0? 1.56E+03 1.47E+03 1.72E+03 1.50E+04 0.00E+00 7.39E-04 I-130 7.78E-01 2.30E+02 1.95E+04 3.58E+02 0.00E+00 1.?8E+02-I-131 4.2?E+02 6.13E+02l9.06E+01 1 3.51E+02 2.01E+05 1.05E+03 0.00E+00 1.62E+02' I-132 2.09E+01 5.59E+01!1.96E+01 1.96E+03 9.90E+01 0.00E+00 1.05E+01 1-153 1.46E+02 2.54E+02'7.7!E+01 3.74E+04 4.44E+02 0.00E+00 2.29E+02' I-114 1.0?E+01 2.96E+01!1.06E+01 5.14E+02 4.71E+01 0.00E+00 2.53E-02' I-135 4.56E+01 1.19E+CT!4.41E+01 ?.8CE+03 1.91E+02 0.00E+00 1.35E+02 CJ-134- 8.64E+04 2.06E+05:1.6EE-05 0.00E+00 6.65E+04 2.21E+04 3.60E+03 C2-136 9.04E+03 3.57E+04 2.57E+04 0.00E+00 1.99E+04 2.72E+03 4.05E+03 C2-137 1.11E+05 1.51E+05;9.?tE+0* 0.00E+00 5.14E+04 1,71E+04 2.93E+03!

C2-138 7.66E+01 1.51E+02j7.50E+01 0.00E+00 1.11E+02 1.10E+01 6.46E-04!

3a-139 1.16E+00 8.27E-04'3.40E-02 0.00E+ve 7.73E-04 4.69E-04' 2.06E+00!

Es-140 2.43E+02 3.05E-01 1.59E+01 0.00E+00 1.04E-01 1.75E-01 5.00E+02:

Es-141 5.64E-01 4.26E-04,1.90E-02 0.00E+00 3.96E-04 2.42E-04 2.66E-19!

Ba-142 2.55E-01 2.62E-04 1.60E-02 0.00E+00 2.21E-04 1.48E-04 3.59E-19?

L a- 8 40 1.50E-01 7.54E-02l1.99E-02 0.00E+00 0.00E+00 0.00E+00 5.54E+03!

Lm-142 7.66E-03 3.49E-03*8.60E-04 0.00E+00 0.00E+00 0.00E+00 2.54E+01-Ce-141 1.88E+00 1.27E+00;1.44E-01 0.00E+00 5.91E-01 0.00E+00 4.87E+03

Ce-143 3.32E-01 2.45E+02:2.71E-02 0.00E+00 1.08E-01 0.00E+00 9.17E+03 C'e-144 9.81E+01 4.10E+01'5.27E+00 0.00E+00 2.43E+01 0.00E+00 3.32E+04 Pr-143 5.51E-01 2.21E-01 2.73E-02 0.00E+00 1.27E-01 0.00E+00 2.41E+03 Pr-144 1.80E-03 7.48E-04 9.16E-05 0.00E+00 4.22E-04 0.00E+00 2.59E-10 Nd-147 6.93E-01 8.01E-01 4.79E-02 0.00E+00 4.68E-01 0.00E+00 3.84E+03 W-187 2.96E+02 2.47E+02 8.65E+01 0.00E+00 0.00E+00 0.00E+00 8.10E+04 Np-239 2.85E-02 2.80E-03 1.54E-03 0.00E+00 8.74E-03 0.00E+00 5.75E+02 Calculated using Equation (11)

ODCN, Hatch REV.1 1.0-17 2879W/0152W, 05/11/84

.1 1.3 DOSE PROICTIONS FOR LIQUID EFFLUENTS 1.3.1 MONTH.Y DOSE PROICTIONS In order to meet the requirements of RETS 3.15.1.3 (Unit 1) and 3.11.1.3 (Unit 2), which pertain to operation of the liquid radwaste treatment systems, dose projections must be made at least monthly, during periods in which discharge of untreated liquid effluents containing radioactive materials to unrestricted areas occurs or is expected. .

Projected quarterly doses to individuals due to liquid effluents may be determined as follows:

D U "

tb(c) * 'I tb(prj) t

/

D = , 93 ogp,3y ofc) where D = the cumulative total body dose for the elapsed portion of tb(c) the current quarter plus the release under consideration, t = the number of days into the current quarter.

= the cumulative organ doses for the elapsed portion of the Do (c) current quarter plus the release under consideration.

If activities planned during the remainder of the quarter are expected to contribute a significant dose and the determination can be reasonably made, tnis contribution should be included in the equations:

tb(c) * #1 +

O tD(prj ) *[ t hA 70 \

9 +

hA Do (prj) where hA is the expected dose due to the particular planned activity.

0D04, Hatch REV.1 1.0-18 2879W/0152W, 05/11/84 A

. -I m

1.3.2. DOSE PROICTIONS FOR SPECIFIC RELEASES Dose projections may be performed for a particular release by performing a

. pre-release dose calculation assuming that the planned release will proceed as i anticipated. For individual dose projections due to liquid releases follow the methodology presented in Section 1.2 using sanple analysis values for the source to be released and parametric values expected to exist for the release period. ,

I I

ODO4, Hatch REV.1 1.0-19 2879W/0152W, 05/11/84

' 3 i

. ..:.N 1.4 DEFINITIONS OF LIQUID EFFLUENT TERMS Section of Term Definition Initial use A = adjustment factor applied to facilitate setting actual 1.1.1 monitor setpoints.

A h

= the site related ingestion dose commitment factor due 1.2 to fish consumption to the total body or any organ

.T for each identified principal gamma and beta emitter listed in Table 1.2-3 in mrem-ml per br-pC1.

BF = Bioaccumulation Factor for nuclide 1, in fish, pCi/Kg per 1 1.2.1 pCi/1, from Table 1.2-1.

c = tne setpoint of the radioactivity monitor which measures the 1.1.1 radioactivity concentration in the effluent line prior to dilution and subsequent release.

C,. = the effluent concentration of alpha emitting nuclides 1.1.1 observed by gross alpha analysis of the MONTit.Y composite sample.

C 7

= the concentration of Fe-55 in liquid wastes as 1.1.1 observed in the QUARTERLY composite sample.

C =

the effluent concentration of a gamma emitting nuclide, g, g 1.1.1 observed by gamma-ray spectroscopy of the waste sample.

Cy = the concentration of nuclide i as determined by the 1.1.1 analysis of the waste sample. - -^-

Cg = the average concentration of radionuclide i, in undiluted 1.2.1 liquid effluent during time period A(, in yCi/ml.

0004, Hatch REV.1 1.0-20 2879W/0152W, 05/11/84

, --e,,,s.,-m,-n,,,--w -,,--,,,,,,r. , - -----,w,-m-,--,-w- - - , , , - .

v, Y

i Section of i

Term Definition Initial Use !

I

= the effluent concentration limit (RETS 3.15.1.1 for Unit 1; 1.1.1

'hC 3.11.1.1 for Unit 2) implementing 10 CFR 20 for the site, in pCi/ml.

C = the concentration of Sr-89 or Sr-90 in liquid wastes 1.1.1 s

as determined by analysis of the QUARTERLY composite sample.

C = the measured concentration of H-3 in liquid waste 1.1.1 t

as determined by analysis of the MONTH.Y composite.

D = the cumulative dose commitment to the total body or an,' 1.2.1 organ , T , from the liquid effluents for the total time period.

DF = the dilution factor, which is the ratio of the total 1.1.1 dilution flow rate to the effluent stream flow rate (s) required to assure that the limiting concentration of 10CFR, Part 20, Appendix B, Table II, Column 2 are met at the point of discharge to the Unrestricted Area.

DF = a dose cc1 version factor. for nuclide, i, for adults in 1.2.1 f7 preselected organ, t, in mrem /pCi found in Table 1.2-2.

f = the flow setpoint as determined for the radiation monitor 1.1.1 lbcation. (General expression for equation 1.)

F = the dilution water flow monitor setpoint as determined 1.1.1 prior to the release point, in volume per unit time.

(General expression for equation 1.)

F = the minimum flow rate of the dilution stream used for 1.1.1 d

setpoint calculations during the time of release.

ODCM, Hatch REV.1 1.0-21 2879W/0152W, 05/11/84 -

y Section of Term Definition Initial Use Fg = the near field average dilution factor for C g during any 1.2.1 liquid effluent release.

f p

= effluent flow rate (actual pum value). 1.1.1 f

t

= maximun permissible effluent flow rate. 1.1.1 K

g = 1.14 x 105 , units conversion factor. 1.2.1 m = number of liquid releases. 1. 2.1 s , WC7 , and MPCt which are 1.1.1 MPC = MPC f g , MPC,, MPC the limiting concentrations of the appropriate gamma emitting radionuclides, alpha emitting radionuclides, strontium, iron and tritiun, respectively, from 10CFR, Part 20, Appendix B, Table II, Column 2.

SF = the safety factor; a conservative factor used to compen- 1.1.1 '

sate for statistical fluctuations and errors of measure--

ments.

] t c = The transit time from release to receptor. 1.2.1 At = duration of release under consideration. 1.2.1

% = 21 kg/yr, fish consunption (adult). 1.2.1 Z = Applicable factor when additional receiving water body 1.2.1 dilution is ' considered; Z = 10.

A y = The decay constant for radionuclide 1. (sec ) 1.2.1 ODO4, Hatch REV.1 1.0-22 2879W/0152W, 05/11/84 7 T- % ~ v-av-- -% --=ye-7--te*--e w-e- --e%-ce& s -

+-----**p"=**s-et -m-gey-gt c -+y-=f=ww'ri--e-e*-e W v* *r*' -=w- - - ' ?9*-TT9'*'*-3

W

. .A 1.5 LIEJID RADWASTE TREATMENT SYSTEMS FIGLRES 1.5-1 and 1.5-2 are schematics of the Liquid Radwaste Treatment Systems for Unit 1 and Lhit 2 respectively. The dotted lines indicate alternate pathways through which liquid radwaste mcy be routed. These alte::nate routes increase the operational flexibility of the Liquid Radwaste Trcatment Systems.

1 OD04, Hatch REV.1 1.0-23 l 2879W/0152W, 05/11/84 l

FIGURE 1.5-1 Liquid Radwaste Treatment System (Unit 1)

Waste Surge Off Standard Recycle Tank __.______I______,,i 1 I :

Off Standard Recycle : ,

,r- - - - -@- - - -- - - - - - - - - - - - P- - -. _ _ _ _ _ _ _ l 1

I I I Waste Waste '

Waste Collector 4 l l Waste 8

g

, To Collector Demin 8 i Sample Condensate Tank Filter +6; M Tank ~ ~1 " Storage I' I I I Tank Off Standard Recycle c---

I'i 8

,______.!__.A________,, ,l lI 1 I !

Floor Drain Floor Drain l1i Drain Floor i I

Floor Drain t

Radiation Collector - :r-* -hy "

Tank Filter Demin

[i Sample Tank I ' D

- E i *

i. _ J To Discharge Canal Chemical Chemical Waste Waste Tank -

Sample -

L Tank n

Demin

' Feed Tank Laundry Laundry Drain % Drain Tank Filter 1.0-24

~ . - -

- . . - - .- - - - - - .a. _ n... .-

- ._ 7 q

. .us FIGURE 1.5-2 Liquid Radwaste Treatment System (Unit 2)

Waste Surge Off Standard Recycle

,_______._______ c_______ y Tank j ,

I '

i '

e 1 l l 8 I '

,_ .4. .. Off Standard Recycle 4 I -_..m_---_--...3i I

I ' ;

Waste i Waste Waste 1

Waste i To i

Collector i Collector g Demin '

Sample ' :

Condensate Tank Filter la i f.i g

a Tank SE #88*

Tank il l 1 I I

l i

lu.__--> ,

i I I

Off Standard Recycle I i 1 -

I _ _ _ _ _ _ _. _ _ _ _ _ _I .th- - _ _ - _ _ I_ A. - -- - - I I

,I ,l ; Radiation Floor Floor i Floor Floor i Monitor Drain Collector '

Drain Filter

'g i

Drain Demin i

': Drain Sample a @

Tank I "

l Tank .

' ! To

~~~~~~~~'

Discharge Canal Chemical Chemical Waste Waste Tank - ;

Sample Tank n

1P Chemical Waste Neutralizer Tank j -

l -

l 1.0-25

__ . . ..)

1.6 MIXING CF LIQUID WASTE TANKS In order to assure that sanples taken from liquid waste tanks planned for release are representative, the contents of the tank to be sanpled will be recirculated for a minimun time period to allow adequate mixing of the tank contents. Recirculation times are as follows (Reference 13):

Tank (s) Recirculation Times Unit 1 Unit 2 Waste Sanple Tanks 40 minutes 40 minutes ,

Floor Drain Sample Tanks 70 minutes 105 minutes Chemical Waste Sanple Tanks 65 minutes 65 minutes Domin Feed Tank 115 minutes NA Laundry Drain Tanks 50 minutes NA i

s 00CM, Hatch FEV.1 1.0-26 2879W/0152W, 05/11/84

SECTION 2. -

GASEOUS EFFLLENTS At Pl~ ant Hatch there are four points where radioactivity is released to the atmosphere in gaseous discharges. These four release points are: (1) The main stack .which serves both units; (2) Unit 1 reactor building vent stack; (3)

Unit 2 reactor building vent stack; and (4) Unit I recantainer building vent.

The main stack serves as the discharge point for the following release sources from each tnit: . mechanical vacuta punps, off-gas system, gland seal exhaust, and staney gas treatment system, through which drywell purges are discharged. The waste gas treatment building ventilation also discharges

. through.the main stack.

Each reactor building vent stack serves as the discharge point for the reactor building, refueling floor' ventilation, turbine building, and radwaste building of each respective unit.

-The Unit 1 recont)iner building vent discharges directly to the atmosphere.

.a Gaseous effluent monitor setpoints are required only for noble gas monitors

, serving these four release points; methodology for calculating noble gas monitor setpoints is presented in Section 2.1. Although setpoint calculations are not required for radiciodine and particulate monitors, the methodology for

[ assuring the potential a gan dose rates due to radiolodines, tritium and particulates in gaseous releases from the site do not exceed the limits of RETS 3.15.2.1.(b) (Unit 1) and 3.11.2.1(b) (Unit 2) is presented in the Note following section 2.2.1.b.

j 2.1 GASEOUS EFFLUENT MONITOR SETPOINTS The gaseous monitor setpoint values determined in the following sections will ,

be regarded as tpper bounds for the actual. setpoint adjustments. That is, setpoint adjustments are not required to be performed if the existing setpoint 00CM, Hatch REV.1 2.0-1 l 2877W/0152W, 05/11/84 1

v -

in 'm-w-----s 4-y-.,g--w. g.g y .epwq-- p wp g - p .pgye,,v.,, 9. gw g.g , p-9,-.--y wp- y w.9 9,.7g-g-94. _9g-gwg,,7 .pgq-%.y.,--,n,gys-9,p.--.p ,,v,9-g..w,,yq

f'

}

l level corresponds to a lower couit rate than the calculated value. Setpoints l may be established at values lower than the calculated values if desired.

i l

If no release is plamed for e. particular pathway, or if there is no detectable activity in the plamed release, the monitor setpoint should be established as close to backgromd as practical to prevent spurious alarms and yet alarm should an inadvertent release occur.

1 If a calculated setpoint is less than the monitor reading associated with the particular release pathway, no release may be made under current conditions.

Under such circunstances, the nunt)er of simultaneous release pathways may be reduced or contributing source terms may be reduced and the setpoint recal-culated.-

, 2.1.1 LNIT 1 REACTOR BUILDING VENT STACK, UNIT 2 REACTOR BUILDING VENT STACK, AND UNIT 1 RECODGIER BUILDING VENT Monitors: D11-K619 A and B, 2D11-K636 A and B, Dll-P003 A and B For the purpose of inplementation of RETS 3.14.2 (Unit 1) and 3.3.6.10 (Unit 2), the alarm setpoint level for these noble gas monitors will be

. calculated as follows:

C = monitor reading cf the ncele gas monitor at the alarm setpoint 3

concentration.

f(AGxSF)xRv t xDTB (1)

Cs = the lesser of 5 or

((AGxSF)xR sv x Dss (2) 7 = safety factor; a conservative factor applied to each noble gas monitor to compensate for statistical fluctuations and errors of measurement. (For example, SF = 0.5 corresponds to a 100 percent variation.)

I AG = an administrative allocation factor applied to apportion the release setpoints ammg all gaseous release discharge pathways (normally four) to assure that release limits will not be exceeded by simultaneous releases. The allocation factor for a particular discharge pathway may be assigned any desired value between 0 and 1 00CM, Hatch REV.1 2.0-2 2877W/0152W, 05/11/84

^

under the condition that the sum of the allocation factors for all simultaneous release pathways does not - exceed 1. For ease of implementation, AG may be set equal to 1/n, where n is the number of simultaneous final gaseous release points. For a more exact determination of allocation factors, .see Section 2.1.3.

D = Dose rate limit to the total body of an individual which is 500 TB mrem / year.

R tv

= monitor reading per mrem /yr to the total body for vent releases Rtv- = C + ((XM) [Ki Qi v) (3)

Gi where 3

C = monitor reading of a noble gas moniter corresponding to the grab sample radionuclide concentrations taken in accordance with RETS Tables 4.15.2-1 (Unit 1) and 4.11-2 (Unit 2). The monitor response corresponding to the measured concentration is determined from the monitor calibration curve for the particular monitor.

(TM)g = the highest annual average relative concentration at the site boundary. (If desired, the annual average relative concentration at the site boundary for the particular release point may be used.) The release points addressed in this section are ground-level releases.

3 (XM)g = - 6.8 x 10-6 sec/m in the W sector.

. .Kg = total body dose factor due to gamma emissions from radionuclide 1 (mrem /yr per pCi/m3 ) from Table 2.1-1. ,

- .~ . --.

Q,1

= rate of release of noble gas radionuclide 1 (pCi/sec) from the vent release pathway under consideration, which is the product of Xyy and F, y. where Xfy is the concentration of radionuclide i for the particular release and Fy is the maximum expected . release flowrate for this release point. (Xyy in pCi/ml and Fy in ml/sec.)

ODCM, Hatch REY.1 2.0-3 2877W/0152W,-05/11/84 8 ,

f s

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

.---r. ,,w_,,,.,,,.,,,..--,,__n,.-,,..,,,v._+,n,.a.--, .,,w,--~

.b-Dss = Dose rate limit to the skin of the body of an individual in an unrestricted area which is 3000 mrem / year.

R,y = monitor reading per mrem /yr to the skin Rsv = C + ((X/Q)g I (Li + 1.1 M1) Qiv) (4) i dere Ly = skin dose factor due to beta emissions from radionuclide 1 (mrem /yr per pC1/m ) from Table 2.1-1.

1.1 = mrem skin dose per mrad tir dos 1*. ,

My = air dose factor due to gamma emissions from radionuclide 1 (mrad /yr per pCi/m3 ) from Table 2.1-1.

2.1.2 MAIN STACK Monitor: 011-K600 A and B ,

For the purpose of implementation of RETS 3.14.2 (Unit 1) and 3.3.6.10 (Unit 2), the alarm setpoint level for tne main stack noble gas monitor will be calculated as follows:

C 3 = monitor reading of the noble gas monitor at the alarm setpoint-concentration.

r

(

( AG x SF) x ks

kB

! C 3 = the lesser of 4 or

( AG x SF) x Rss xD ss (6) i R

ts = C + I VQ is (

i i R,3

= C+ I (Ly (X/Q)E + 1.1 Bg )Qh (0)

. 1 0004, Hatch REV.1 2.0-4 2877W/0152W, 05/11/84

g where Vy = constant, which includes the dose factor, for each identified noble gas radionuclide accounting for the gamma radiation from the elevated finite plume resulting from the main stack release in mrem / year per pCi/sec

'from Table 2.1-2.

By = constant, which includes the air dose factor, for each identified noble gas radionuclide accounting for the gamma radiation from the elevated finite' plume resulting from the mein stack release in mrad / year per pCi/sec from Table 2.1-2.

Q is = rate of release of noble gas radionuclide 1 (pCi/sec)

', from the main stack, which is equal to the product of X, and F, where X is the concentration of f s is radionuclide i fcr the main stack release and Fs is the maximum expected main stack release flowrate.

(Xf , in pC1/ml and F, in ml/sec.)

the highest annual average relative concentration in the

=

- CIM)E unrestricted area associated with releases from the main stack. The main stack is an elevated release.

'( N E = 1.0 x 10 4 sec/m3 in the W sector.

All other terms were identified previously in Section 2.1.1.

2 2.1.3 DETERMINATION OF ALLOCATION FACTOR, AG When simultaneous gaseous releases are made to the environment, an (adninistrative) allocation factor must be applied to each discharge pathway.

This is to ensure that simultaneous gaseous releases from the site to unrestricted areas will not exceed the dose rate limits specified in RETS 3.15.2.1 (Unit 1) or 3.11.2.1 (Unit 2). For Plant Hatch, final discharge pathways which may be released simultaneously are the main stack, Unit 1 00CM, Hatch REV.1 2.0-5 2877W/0152W, 05/11/84

., , , _ . - . _ . , _ , ..,_,..-,,,.,_,,_.,,,_.._,_,,,,_.,,,.__,-_,.y,,w_.,,,,,c,-m , , _ . - _ , , . _ - _ . , -.m

-- ^

g.f reactor building vent stack, Unit 2 reactor building vent stack, and Unit 1 recombiner bd1 ding vent. The allocation factor for each discharge pathway must be between 0 and 1 and the sum of the allocation factors for the simultaneous releases must not exceed 1.

There are three methods by which allocation factors may be deterir.ined:

1. The allocation factor for a particular release pathway may be adninistratively selected based on an estimate of the fraction of the total dose rate (from all simultaneous releases) which is contributed by the particular release pathway.

2. The allocation factor may be calculated using the expression AG = 1/n where n = the number of release pathways to be released simultaneously.

3. The allocation factor may be determined for a particular discharge pathway by calculating the ratio of the total body dose rate due to noble gases released ~ from the particular discharge pathway under consideration to the total body dose rate due to noble gases in all simultaneous releases.

For the Main Stack:

l t i ls 1

AG = ~

'I V iQ is

G IKQy 1y i n i where n is the number of simultaneous vent releases.

l.

0004, Hatch REY.1 2.0-6 2877W/0152W, 05/11/84 i . . . _ . _- . , _ _ _ . - _ _ _ _ . , _ _ _ __. _ _, _ _ , _ _ . _ _ _ _ _ _ _ . , _ __

.5

?

For Vent releases:

0 0 AG = , Gi 1 iv(r)

IVQ, fg + I (77Q)g IKQ, y1

..i n i Where n is the number of simultaneous vent releases and (r) is the particular discharge pathway number for which an allocation factor is being determined.

t 0004, Hatch REY.1 2.0-7 2877W/0152W, 05/11/84

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

.g N

TABLE 2.1-1 00SE FACTORS FOR EXPOSLRE TO A SEMI-IPFINITE CLOUO OF NOBLE GASES

Nuclide y 4ody*** (K) 8-Skin ***(L) y-Air **(M) 8-Air **(N)

Kr43m 7.56E-02 " * - 1.93E+01 2.88E+02 Kr-85m 1.17E+03 1.46E+03 1.23E+03 1.97E+03 Kr-85 1.61E+01 1.34E+03 1.72E+01 1.95E+03 Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03 Kr-89 1.66E+04 1.01E+04 1.73E+04 1.06E+04 Kr-90 1.56E+04 7.29E+03 1.63E+04 7.83E+03 Xe-131m 9.15E+01 4.76E+02 1.56E+02 1.11E+03 i Xe-133m 2.51E+02 9.94E+02 3.27E+02 ,

1.48E+03 Xe-133 2.94E+02 3.06E+02 3.53E+02 -1.05E+03 Xe-135m 3.12E+03 7.11E+02 3.36E+03 7.39E+02 Xe-135 1.S1E+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

! ' Values taken from Reference 3, Table B-1

,, -y_ . . . .

pG1-yr

- - mrem-m3 yCi-yr

- - - 7.56E-02 = 7.56 x 10-2 i

0004, Hatch REV.1 2.0-8 l

2877W/0152W, 05/11/84 i

l

_ _ . . _ _ , _ . _ _ _ _ _ _ . . _ . _ _ _ _ . . _ _ . _ . . _ _ . - _ . . . . , . _ _ _ . _ _ . _ . ,m _ . . ,_- , , . - _ _ _ _ _ _ _ _ . _ . .

~

s . . . . . . )

TABLE 2.1-2 00SE FACTORS FOR EXPOSURE TO DIRECT RADIATION FR(N NGILE GASES IN TE ELEVATED FINITE PLLBE' Location: Site Boundary in West Sector at 1501 meters Nuclide y - Body (V)** y - Air (B)***

Kr-85m 6.77E-05 7.1E-05 Kr-85 9.46E-07 1.01E-06 Kr-87 3.59E-04 3.75E-04 Kr-88 9.22E 9.58E-04 Kr-89 8.90E-04 9.31E-04 Kr-90 6.39E-04 6.74E-04 Xe-131m 1.41E-06 1.4E-06 Xe-133m 1.54E-05 1.79E-05 Xe-133 1.17E-05 1.21E-05 Xe-135m 1.y 7E-C 4 2.10E-04 Xe-135 1.10E-04 1.17E-04 Xe-137 9.11E-05 9.71E-05 Xe-138 5.14E-04 5.37E-04 Ar-41 5.94E-04 6.25E-04

' Values calculated in accordance with methodologies presented in Section 5.2.1 of Reference 1 and Appendix F of Reference 3, with meteorological joint frequency distributions presented in Table E.4-7 of Appendix E of Reference 5.

- mram-sec pCi-yr

- - mrad-sec pCi-yr 0004, Hatch REV.1 2.0-9 2877W/0152W, 05/11/84

2.2 GASEDUS EFFLLENT DOSE RATE AIO DOSE CALCULATIONS 2.2.1 UleESTRICTED AREA BOL20ARY DOSE RATES 2.2.1.a Dose Rates Due To Noble Gases For the purpose of implementation of RETS 3.15.2.1.a (Unit 1 ) and 3.11.2.1.a (Unit 2), the dose rate in the unrestricted area due to noble gases shall be calculated as follows:

D t

= total body dose rate at time of release (mrom/yr)

= I (T/4)g I Kg Q, 1

+ IVQ, fg W v i i D, = skin dose rate at time of release (mram/yr) 1

=

Iv (YM)G i- I I'i + 1*1 M 1) Oiv +

Ii I'iI N)E + 1.1 8 )1 Q is (10)

Terms were defined previously in Sections 2.1.1 and 2.1.2.

The oose rate limits are site limits at any point in time; therefore, dose rates are summed over all releases occurring simultaneously. For Plant Haten the three- vent releases are: Unit 1 reactor building vent stack, Unit 2 reactor building vent stack, and the Unit 1 recombiner h"41 ding vent. The only elevated release is the main stack which serves both units. Simultaneous releases may include any combination of these four release points.

2. 2.1. b Dose Rates Due to Radiciodines. Tritium, and Particulates For the purpose of implementing RETS 3.15.2.1.b (Unit 1) and 3.11.2.1.b (Unit i 2), organ dose rates due to radiciodines, tritium and all radioactive materials in particulate form with half lives greater than eight days, are i required to be calculated for the inhalation pathway for the child age group. ,

The child age group would experience the highest potential dose rate via the inhalation pathway. In accordance with Appendix C to Reference 3, noble gases are excluded from these calculations. These dose rates are calculated as follows:

0004, Hatch REV.1 2.0-10 ;

! 2877W/0152W, 05/11/84 !

l l

l

iq s . .

M:

D = organ dose rate at time of release (mrem /yr) o i

= (X/O g Pig Q{y + Pg Q{, (11) y (X/Q)E where (T/Og = defined in Section 2.1.1.

(X/Q)E

= f in ection 2.1.2.

Qfy = release rate (pCi/sec) of radiciodines, tritium and particulates (required by RETS 3.15.2.1 for Unit 1 and 3.11.2.1 for Unit 2) from the Unit 1 reactor building vent stack, the Unit 2 reactor building vent stack, and the Unit 1 recombiner building vent.

Qfs = release rate (pCi/sec) of radiciodines, tritium, and particulates (required by RETS 3.15.2.1 for Unit 1 and 3.11.2.1 for Unit 2) from the main stack.

P g = organ dose parameter for organ o and radionuclide 1, (mrem /yr per p C1/m' ) for inhalation determined as fallows:

Pg = K (BR) DFg (12) and where K = constant of unit conversion, 0

10 pCi/pCi BR = breathing rate for child age group; 3700 m3 / year (Table 2.2-10) (from Reference 3) 00CM, Hatch REV.1 2.0-11 2877W/0152W, 05/11/84

y DFgg = inhalation pathway dose factor for child age group for organ o and radionuclide i (Table 2.2-2) (from Reference 3) l NOTE: In order to assure that potential dose rates (pre-release) to an organ due to radiciodine, tritium and particulates in simultane-ous gaseous releases from the site do not exceed 1500 mrem / year as specified in RETS 3.15.2.1(b) and 3.11.2.1(b), the potential organ dose rate D, must be limited as follows:

(AG x SF) < 1500 mrem / year (13)

Do+

re AG and SF are assigned the same values as were used in Se ion 2.1 for the release source pathway under consideration.

To furttier ensure that dose rate limits were not exceeded, (post-release) dose rates from simultaneous releases shall be summed, as shown above.

4 2.2.2 UPRESTRICTED AREA AIR DOSE AND DOSE TO IPOIVIDUAL 2.2.2.a Air Dose in Unrestricted Area For the purpose of implementation of RETS 3.15.2.2 (Unit 1) and 3.11.2.2 (Unit 2) and 3.15.2.4 '(Unit 1) and 3.11.2.4 (Unit 2), the air dose in unrestricted areas shall be determined as follows:

D = air dose due to gama emissions from noble gas radionuclides (mrad)

Y

~ ~

= 3.17 x 10'8 [(X/Q)g y [Mg 1 gy +

[181 Q, 1 (14)

.= .

3.17 x 10-8 = the fraction of one year per one second ODCN, Hatch REV.1 2.0-12 2877W/0152W, 05/11/84

^ ._.

l 2;

llky = cumulative release of noble gas radionuclide i over the period of interest 4 C1) from the vent release under consideration.

ks . = cumulative release of noble gas radionuclide i over the period of interest 6 Ci) from the main stack.

.M = defined previously in Section 2.1.1.

1 By = defined previously in Section 2.1.2.

(X/Q)g = defined previously in Section 2.1.1.

Dg = air dose due to beta emissions from noble gas radionuclides (mrad).

~

= 3.17 x 10-8 (T/4)g N Q, +

(X/Q)E Ni ks (15) 1 1 4

N = air. dose factor due to beta emissions from noole gas 1 3 radionuclide 1 (mrad /yr per pCi/m from Table 2.1-1).

= defined previously in Section 2.1.2.

(X/Q)E 2.2.2.b Dose To An Individual In Unrestricted Area Dose to an individual from radiciodines, tritium, and radioactive materials in particulate form will De calculated for the purpose of implementation of RETS 3.15.2.3 and 3.15.2.4 (Unit 1) and 3.11.2.3 and 3.11.2.4 (Unit 2). In accordance with Appendix C of Reference 3, noble gases are excluded from these dose calculations. Doses to an individual are calculated as follows:

(Note: At Plant Hatch the ' controlling receptor is an individual in the infant age group, located in the NPE sector at a distance of 3.2 miles, exposed to

! inhalation, grourd-plane, and grass-cow-milk pathways.)

D j

= dose to an organ j of an individual in age-group a from radiciodines, tritium, and radionuclides in particulate form with

.1 half-lives greater tnan eight days (mrem).

OD04, Hatch REY.1 2.0-13 287M/01524, 05/11/84 l

9T 4

= 3.17 x 10'8 pg [ Rdpj (w ' '0vp 1v + w' ~0e 1s] (16) where-3.17 x 10-8 = fraction of one year per one second.

Wyp' = pathway-dependent relative dispersion or deposition in the unrestricted area at the location of the controlling receptor, associated with plant vent releases. ,

( (X/Q')yp

= annual average relative dispersion parameter for location of controlling (critical) receptor for plant vent releases.. (X/Q')yp applies only to inhalation

. and all tritium pathways. . (For all tritium pathways the k' source term is limited to tritiun.)

(T70')yp = 6.1 x 10' ? sec/d in the NNE sector for inhalation and all tritium pathways. .

wvp'*

(D/Q')yp = annual average deposition parameter for the location of controlling (critical) receptor for plant vent releases. (U7llP )yp applies to all other pathways.

(U7Q')yp = 1.9 x 10' ' m-2 in NtE sector for all other pathways.

4 CDCM, Hatch REV.1 2.0-14 2877W/0152W, 05/11/84

N W,p' = pathway-dependent relative dispersion or deposition in the unrestricted area at the location of the controlling receptor, associated with main stack 1

releases. i i

(T/Q'),p = annual average relative dispersion parameter for location of controlling (critical) receptor for main stack releases. (X77')sp applies only to inhalation

~

aad all tritium pathways. (For all tritium pathways, the Qi ' source term is limited to tritium.)

= 4.2 x 10'8 sec/m' in the NtE sector for

('X75')sp inhalation and all tritit.n pathways.

-W sp (D/Q')sp = annual average deposition parameter for the location of contre 111ng (critical) recept.or for main stack releases. (D77 )sp applies to all other pathways.

in NNE sector for all other (D/Q') = 6.9 x 10'" m-2 pathways.

The selection of the dispersion or deposition parameter, X/Q or D/Q, is ~

dependent upon the pathway being considered. The dispersion parameter, X/.Q, is required for the inhalation pathway. The deposition parameter, D/Q, is required for the ground-plane pathway and the grass-cow-eilk pathway.

However, since tritium is taken up by vegetation directly from surrounding air, X/Q is required for tritium contributions from the grass-cow-eilk pathway.

5 ODO4, Hatch REV.1 2.0-15 2877W/0152W, 05/11/84 .

- - - - , yi. , ,-,,,.w-,,..y,,. --

p ,,v --+y------.-r,r---,-u-- - -

,,,y -

a i

~

Qi y' = cumulative release (pCi), from plant vent releases, of radio-nuclide i as required by RETS 3.15.2.3 (Unit 1) and 3.11.2.3 (Unit 2) over the period of interest. Dose determinations required by RETS 3.15.2.3 and 3.11.2.3 are on a per reactor basis; therefore, cumulative release quantities must also

- be reactor-specific. (For dose contributions due to tritium from

- the grass-cowwnilk pathway, the Qi y term is limited to tritium.)

ks ' = cumulative release (pC1), from the main stack releases, of radio-nuclide i as required by RETS 3.15.2.3 (Unit 1) and 3.11.2.3 (Unit 2) over the period of interest. Dose determinations required by RETS 3.15.2.3 and 3.H.2.3 are on a per reactor basis; therefore, cumulative release quantities must also be reactor-specific. Since the main stack serves both reactors, release quantities must be apportioned between- the two units.

In absence of evidence that one reactor contributes a greater quantity of radioactivity than the other over the period of interest, release quantities may be apportioned equally between -

the two units.

R = pathway-specific, individual age-specific, organ dose factor for dpj radionuclide i, pathway p, organ j, and individual age group,

a. Routine individual dose calculations address the inhalation, f

ground-plane, grass-cow (or goat)wnilk, grass-cowwneat, and

- garden vegetation pathways. However, the dose pathways actually present at the controlling location, as wen as the controlling

~

individual age group, are determined through the Land Use Census for the site. Pathway factors Rdd are determined as shown in the following sub-sections.

! As stated earlier, the controlling receptor for Plant Hatch is an infant exposed to inhalation, grced-clane and grass-cowanilk pathways.

i l

l-l 0004,' Hatch REV.1 2.0-16 2877W/0152W, 05/11/84 l

l l.

s a, e,- - .p.- ,.,,e-,, - _ ,,, ,--a, ,-,,y y,p mww, p e m e-e- ,. p

- , , ,w, y., , , , , , g,,,-,,,,m..-o,-..me.m,,,,,,.,.,e-.,,g,.,,y,,e-.,mm,,v.,.

a l

Plant Hatch site-specific values, or appropriate default values, required in the pathway factor determinations for the critical I

receptor are presented in Table 2.2-12.

Inhalation Pathway Factor R,ipj = K'(BR), (DFAij), mrem /yr per pCi/m where -

K' = constant of unit conversion 10 pCi/pCi (BR), = the breathing rate for a particular age group in m / year from Table 2.2-10.

DFg, = the inhalation dose factor for receptor age group a, organ j, and for radionuclide i, in mres/pCi from Tables 2.2-1 through 2.2-4.

Ground-Plane Pathway Factor

'R aipj = K'K" (SF')(DFG i j) ((1-e

)/A i) (m2 mrem / year per pCi/sec) 6

.K' = constant of unit conversion, 10 Ci/pC1.

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

SF' = shielding factor, 0.7 (dimensionless)

DF = ground plane dose conversion factor for radionuclide 1 (same for all age groups and specific organs are assumed to receive the same 2

dose as the total body) (mrem /hr per pC1/m ) Table 2.2-9.

.A g = decay constant for radionuclide 1.

t = exposure time, 4.73 x 108 sec (15 years).

ODCM, Hatch REY.1 2.0-17

' 2877W/0152W, 05/11/84 i

Grass-Cow-Nilk Pathway Factor

~

ff

=

g( U,,) p s + II~IDsI )e ih ,Atg7 (17)

R,gp) K, y .A F,(r)(DFyj), y y (m mres/yr per yCi/sec) where 6

K' = a constant of unit conversion,10 pCi/pC1.

S = the cow's consumption rate, in kg/ day (wet weight).

U,p = the receptor's milk consumption rate for age group (a), in liters /yr from Table 2.2-10.

Y = the agricultural productivity by unit area of pasture feed grass, in P 2

. kg/m .

2 Y = the agricultural productivity by unit area of stored feed, in kg/m ,

s F, = The stable element transfer coefficients, in' days / liter.

(see Table 2.2-11.)

r = fraction of deposited activity retained on feed grass.

(1.0 for radiciodines; ',.2 for particulates)

(DF(j)a = the organ ingestion dose factor for the ith radionuclide for the receptor in age group (a), in mrem /pCi from Tables 2.2-5 through 2.2-8.

~1 A

i

= the decay constant for the ith radionuclide, in sec .

A, = the decay constant for removal of ' activity on leaf and plant sur-faces by weathering, 5.73 x 10~7 sec ~1 (corresponding to a 14 day half-life).

00CM, Hatch REY.1 2.0-18 2877W/0152W, 05/11/84

~ .- -

s t

f

= the transport time from pasture to cow, to milk, to receptor, in sec. (1.73 x 10 5),

t = the transport time from pasture, to harvest, to cow, to milk, to h

receptor, in sec. (7.78 x 10b.

f = fraction of the year that the cow is on pasture (dimensionless). >

p f = fraction of the cow feed that is pasture grass while the cow is on s

' pasture (dimensionless).

For tritium in milk, the grass-cowwnilk pathway factor is a special case due to the fact that the concentration of -tritium in milk is based on airborne concentration rather than deposition:

(18)

R,fp) = K'K'"F ,QpU,p(DFLyj), [0.75(0.5/H)] (mrem /yr per pC1/m )

where

' 3 K'" = a constant of unit conversion,10 gn/kg.

H = absolute humidity of the atmosphere, in gm/m .

0.75 = the fraction of total feed that is water.

0.5 = the ratio of the specific activity of the feed grass water to the atmospheric water.

and other parameters and values as previously defined.

2.2.2.c Dose Calculations To Sey m rt Other' Spec'ifi~c~ Technical Specifications In the event radiological impact assessment becomes necessary to implement RETS 6.9.1.12 or 6.9.1.13, dose calculations will be performed using the equations in Section 2.2.2.c with the substitution of average meteorological parameters for the period of the report, and the appropriate pathway receptor dose factors (Rgpy).

0D04, Hatch REV.1 2.0-19 2877W/0152W, 05/11/84

g

.a For the purpose of inplementing RETS 3.16.2, dose calculations may be per-formed using the equations in Section 2.2.2.c substituting the appropriate pathway receptor dose factors (R,gpj ) and the appropriate dispersion parameters for the location (s) of interest. Annual average dispersion parameters may be used for these calculations.

The receptor for which dose calculations may be required in order to implement RETS 6.9.1.12, 6.9.1.13 or 3.16.2 may not be the previously identified critical receptor. The receptor age group and exposure pathways present (and applicable) at the location of interest must be determined. In addition to the inhalation, ground-plane, and grass-cow-milk pathways presented in Section 2.2.2.b, it may be necessary to consider the grass-cow-meat and/or the garden vegetation pathways. The equations for calculating the pathway factors R, for these two additional pathways are presented below. Historically milk goats have not been present within five miles of Plant Hatch. However, in order to facilitate implementation of RETS 3.16.2 in the event milk goats are located within five miles of Plant Hatch, the equation for calculating the '

grass-goat-milk pathway factor is also presented. Plant Hatch site-specific values, or appropriate default values, required in the pathway factor determinations are presented in Table 2.2-13.

Grass-Cow-Meat Pathway Factor

~

, %(U,p) fpf, * (1-fpsf )' ID e~Ai7 t (19) alpj Af + A, [a _

Y p

Y s ,

(m mrem /yr per pCi/sec) where 6

K' = a constant of unit conversion, 10 Ci/pC1.

= the cow's consumption rate, in kg/ day (wet weight).

U,p

= the receptor's meat constrption rate for age group (a), in kg/yr from Table 2.2-10.

00CM, Hatch REV.1 2.0-20 287N/0152W, 05/11/84

i

~

Y p

= the agricultural productivity by unit area of pasture feed grass, in kg/m .

Y, = the agricultural productivity by unit area of stored feed, in

- kg/m .

F -= The stable element transfer coefficients, in days /kg.

7 (see Table 2.2-11.)

r = fraction of dept 'ited activity retained on feed grass.

(1.0 for radiciodines; 0.2 for particulates)

~

(D%), = the organ ingestion dose factor for the ith radionuclide for the receptor in age group (a), in mrem /pC1 from Tables 2.2-5 through 2.2-8.

~

A = the decay constant for the ith radionuclide, in sec .

1 A

= the decay constant for removal of activity on leaf and plant sur-faces by weathering, 5.73 x 10~7 sec ~1 (corresponding to a 14 day half-life).-

tg = the transport time from pasture to cow, to meat, to receptor, in 6

sec. (1.73 x 10 )

t = the transport time from pasture, to harvest, to cow, to meat, to h

receptor, in sec. (7.78 x 106) f = fraction of the year that the cow is on pasture (dimensionless).

p f = fraction of the cow feed that is pasture grass while the cow is on l ,

s pasture (dimensionless).

f For tritiun in meat, the grass-cow-meat pathway factor is a special case due f

to the fact that the concentration of tritium in meat is based on airborne concentration rather than deposition:

?

ODCM, Hatch REV.1 2.0-21 l 28774/0152W, 05/11/84 y--~-- , , -_ . , -, --_--.-y -~,-.,

-,---_.y7 ~ , - . . . . , , - . . _ _ , , . - _ . , , , , _ . , _ - . , ,.,_r.-,. 9,,_m., ,,,,,,,_m..f._ _ , , , _

, ,_y- _

, , _-,__,._...--,..c. . . -

1l R,gpj = K'K'"F fQpU ,p(DFLgj), [0.75(0.5/H)] (mrem /yr per pCi/m ) (20) l where:

3 K'" = a constant of unit conversion,10 gn/kg.

H = absolute huraidity of the atmosphere, in gm/m .

0.75 = the fraction of total feed that is water. '

O.5 = the ratio of the specific activity of the feed grass water to the atmospheric water.

and other parameters and values are given above.

Vegetation Pathway Factor 0 asIe (21)

= +

R,gpj Y0 y + A ,) ij a s. It " g where 6

K' = a constant of unit conversion,10 pCi/pC1.

U = the consumption rate of fresh leafy vegetation by the receptor in age group a, in kg/ year.

(See Table 2.2-10))

U,3 = the consumption rate of stored vegetation by the receptor in age group a, in kg/ year.

(See Table 2.2-10))

f = the fraction of the annual intake of fresh leafy vegetation grown locally.

f g

= the fraction of the annual intake of stored vegetation grown locally.

l i

. ODCM, Hatch REV.1 2.0-22

, 2877W/0152W, 05/11/84 I

i l

~ ~ ~

,_ Q t

g = the average time between harvest of leafy vegetation and its

.conse ption in seconds. (8.6 x 104) t h

= the average time between harvest of stored vegetation and its cons e ption in seconds. (5.18 x 106)

Y y

= the vegetation areal density, in kg/m .

(D ), = the organ ingestion dose factor for the ith radionuclide for the receptor in age group (a), in mrem /pCi from Tables 2.2-5 through 2.2-8.

Ag = the decay constant for the ith radionuclide, in sec-1 1, = the decay constant for removal of activity on leaf and plant sur-faces by weathering, 5.73 x 10-7 sec -1 (corresponding to a 14 day half-life).

For tritium in vegetation, the vegetation pathway factor is a specia1 case due ,

to the fact that the concentration of tritium in vegetation is based on air-borne concentration rather than deposition:

R,gp) = K'K"'(U gg+U f asI g) (DFL1 )), [0.75(0.5/H)] (mrem /yr per pCi/m ) (22) wheire 3

K'" = a constant of unit conversion,10 gm/kg.

H = absolute hmidity of' the atmosphere, in gm/m .

0.75 = the fraction of total vegetation that is water.

0.5 = the ratio of the specific activity of the vegetation water to the atmospheric water.

and other parameters and values are given above.

( 0D04, Hatch REV.1 2.0-23 l

2877d/0152W, 05/11/84 l

I

a

~ .~ ~ _ . . ..

Grass-Goat 4411k Pathway Factor

~

ffps II-IpsI )e ih ,Atff

= K,%(l,p)F,(r)(DFyj), + (23) alpj , y y (m mrem /yr per pCi/sec) where K' = a constant of unit conversion,10 6pCi/pC1.

g = the goat's consunption rate, in kg/ day (wet weight).

U,p . = the receptor's milk consumption rate for age group (a), in

-liters /yr from Table 2.2-10.

Y p = the agricultural productivity by unit area of pasture feed grass, in kg/m .

Y, = the agricultural productivity by unit area of stored feed, in kg/m . .

F, = the stable element transfer coefficients, in days / liter.

(see Table 2.2-11.)

r = fraction of deposited activity retained on feed grass.

(1.0 for radiciodines; 0.2 for particulates)

(DFq)), = the organ ingestion dose factor for the ith radionuclide for the receptor in age group (a), in mrem /pCi from Tacles 2.2-5 through 2.2-8. , , _ , ,

A g = the decay constant for the ith radionuclide, in sec-1 .

A, = the decay constant for removal of activity on leaf and plant sur-faces by weathering, 5.73 x 10-7 sec -1 (corresponding to a 14 day half-life).

COCM, Hatch REN.1 2.0-24

'2877W/0152W, 05/11/84

tg = the transport time from pasture to goat, to milk, to receptor, in 5

sec. (1.73 x 10 )

t h = the transport time from pasture, to harvest, to goat, to milk, to l receptor, in sec. (7.78 x 10')

f p

= fraction of the year that the goat is on pasture (dimensionless).

f = fraction of the goat feed that is pasture grass while the goat is s

on pasture (dimensionless).

For tritium in milk, the grass-goat-ellk pathway factor is a special case due to the fact that the concentration of tritium in milk is based on airborne concentration rather than deposition:

R,gp) = K'K'"F ,Q pU ,p(DFLgj), [0.75(0.5/H)] (mrem /yr per pCi/m ) (24) where:

! K'" = a constant of unit conversion,10 3gn/kg.

H = aDsolute humidity of the atmosphere, in gm/m .

0.75 = the fraction of total feed that is water.

0.5 = the ratio of the specific activity of the feed grass water to the atmospheric water. ,

and otherJparameters and values are given above.

l 4

0004, Hatch REV.1 2.0-25 2877W/0152W, 05/11/84

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

5 l

TABLE 2.2-1 IWALATION DOSE FACTORS FOR INFANT *

(MEM PER PCI IMALED) )

Page 1 of 3 muCt!DE se=E ElvEn f.eScv 7m9aoto anenEv Lums s!-tLa

~

e. 3 no Oafa 4.62E-07 4. 62E-0 7 4.62E-e7 4.62E-07 4.62E.e7 4.62E.07 C 34 t.895-OS 3. 79C-06 3.79E-06 3.79E-66 3.79E-M 3. 79E-M 3.79E-06 44 24 7.S4E-06 7.S4E-06 7. S S E-06 7.54E-06 7.94E-06 7.54E-M 7.94E-06 P 32 1.4SE-03 0 038-05 S.53E-OS se0 Data me Safa me Safa 1.1SE-05 Ce St =0 OATA 100 Data 6.39E-08 4 11E-08 9.4SE-09 9.17E-06 2.SSE-07 am 94 NO cafa 1 01E-05 3.54C-06 =0 Data 3.56t=06 7.14E-06 S.04E-66 ene 96 no 04f4 1.10E-09 1. Set-8 0 40 Data 7.86E-10 0.91E-04 S.12E-OS pt SS 1.4tE-OS 8. 39E-06 2.1 B E-0 6 40 DAfa 40 Defa 4.21E-05 7.02E-07 PE $9 9.69E-06 1 68E-05 6.7tE-06 90 Data 800 Data 7.2SE-04 1.77E-OS CO Se seu Defa 8.71E-07 1.30E-36 800 Def a 40 Data S.SSE 04 7.99F-06 CO to 40 Data S.73E- h S.41E-04 8e0 Data se0 Saf a 3 22E-03 2.2SE-OS sof 63 2.42E-04 1.46E-OS 8.29E-0 4 90 Defa ese Data 1.49E-04 1 73E-06 ,

_ .. - t se! el 1.71E-09 2.33C-10 8.79E-11 90 04f4 as0 cafa S. set-04 3.50E-OS CU 64 800 Caf a 1.34E-09 S.53E-10 soo Defa 2.e4E-09 6. 64E-M 1.07E-OS Ace 65 1 38E-05 4.=ff-05 2.22E-OS soo Safa 2.32E-OS 4.62E-04 3.47E-SS 2ee 69 3.8SE-11 6.91E-11 S.13E-t2 mo OaTA 2.07E-11 1.0SE-06 9.44E-06 84 83 Ise Safa 'as0 Safa 2. 72 E-0 7 800 Data es0 OATA se0 Dafa LT E-24 pa se se0 Cafa 180 Data 2. 86E-0 7 se0 Data 8ec Data se0 Defa L7 E-24 ga e6 ano 0474 age 04fa 1.464.ge sec 047a teC 04fa ese Deta LT E-24 se et ase DefA 1.36E-04 6. 30E-0 5 NO Cafe le0 O&fa suo Oafa 2.17E-06 ge se see Defa 3 98E-07 2.0sE-0 7 8ec Data se0 Data ese Data 2. 4 2 E-f) ?

et 89 90 0474 2.29E-07 1.47E-0 7 sec 0474 ase Data me Safa 4.87E-0e Sa 89 2.04t=04 see Cafa 8.1SC-06 8ec Data me Data 1.4SE-03 4.S7E.0S i la 90 2.92E-02 800 04f4 1. SSE-0 3 no Oafa see Da f a ' 8.03E-03 9.36E-OS l t

la 91 4.83E-00 40 Data 2 4 f t-09 Inc SafA 800 Data 3.76E-05 S.24t=0S

. 14 92 7.50E-09 800 Data 2.79E-10 =0 Data see Data 1.70E-05 1.00E-04

Y 9e 2.3SE-06 ase DATA 4 30E-te seo Safa see DATA 1.92E-04 7.43E-OS l T 91P 2.91E-10 Is0 Data 9.90E-12 see Safa See Def& 1.99E-06 1.6tE-M I 9 98 4.20E-04 ese Safa 1.12E-05 8ee Defa est Safa 3.?SE.93 S.82E-05 l

' y e2 a.37E.0e me safa 3.29E-te as mata me esta 3 7st.03 9.e4E-OS ;

I :

I L

i I

I

Reference 3, Tacle E-10. !

I t

l ODO4s Hatch EV.1 2.0-26 -

- 2877W/0152W, 05/11/84 t

)

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

n f

er

. . .__J TABLE 2.2-1 CONT'O IP44ALATION DOSE FACTORS FOR INFANT *

(MEM PER PCI I!+1ALED)

Page 2 of 3 auctlet a0=E Liven f.s00v Twen010 sto=Er tuas st-tti v 95 1 07E-07 =0 Dafa 2.9tE-09 =0 Data =0 Data S.46E-eS 1.19E-04 2a SS s.24E-03 a.19E-c5 1. 4SE-O S w Data 2.22E-a5 1.2SE-03 t.SSE-05 2e 97 1.07F-07 1.e3E-Os s. 36E-0 9 =0 cafa t.sSE-Os 7. set-OS 1.00E-04 et 95 1.12E-05 4. 59E-06 2.70E-06 NO Data 3 57E-06 3.42E-04 9.0SE-06 me 99 8s0 Data 1.tBi=07 2.31E-04 40 cafa 1.a 9E -07 9.63E-OS 3.44E-OS TC 99m 9.9et-13 2.06E-12 2. 66E-! ! 40 Data 2.22E-11 S.79E-07 1.4SE-06 TC101 4.6SE-14 S.9tE-14 S.80E-13 40 04f4 6.99E-13 4 87E-37 6.03E-07 89103 1.44E-06 NO Cafa 4. 4 S E-0 7 40 DafA 3.03E-04 3.94E-04 1.lSE-05 au1OS 8.74E-10 40 Data 2.93E-10 h0 Data 6.42E-10 1 12E-05 3.46E-05 eW106 4.20E-05 mu Data 7.77E-06 40 Data 7.41E-05 S.26E-C3 1.17E-04 astica 7,13E-06 S.16E-06 3. 5 7E-0 6 40 Data 7.80E-06 2.62E-03 2.36E-OS TE125* 3.40E-06 1.42E-06 4.70E-07 1.148-06 NO Cafa 3.19E-C4 9.22E-06 TE127P 1.19E-CS 4.93E-06 f.488-06 3.40E-06 2.646-05 9.37t=04 1.9%E-OS TE127 1.S9E-09 6. ale-10 3.49E-10 1 32E-09 3.4fE-09 7.39E-06 1 74E-01 TE129* 1.Ptf-05 4.3SE-06 1 59E-06 1.9tE-06 2.27E-OS 1.20E-03 4.93E-05 TE129 S.63E-Il 2.48E-It 1.34E-11 4.02E-!! 1.2SE-10 2.14E-06 1.80E-05 TE13tM 7.htt-08 1.93E-08 2. 5 9E-O s 6.30E-08 1.89E-07 1 42E-04 0.StE-CS TEl31 1.24E-Il S.47E-82 3.57E-12 1.13E-11 2.8SE-It 1.47E-06 S.47E-06 TE132 2.66E-07 1.69E-07 1.26E-07 1.99E-07 7.39E-07 2.43E-04 1.tSE-01 1 130 4.54E-06 9.9tt-16 3 96E-06 1.14E-03 1.09E-05 to Cafa 1 42E-06 8 131 2.7tE-05 3.17E-OS 1. 40E-0 5 1.06E-02 3.70E-05 40 Data 7.56E-07 t 132 1.2tE-06 2.S3E-06 8. 99E -0 7 8.2tt-04 2.42E-06 40 Data 1.36E-06 1 135 9.46(-06 1.37E-05 4.03E-06 2.54E-03 1.60E-05 20 Data 1.$4E-06 f 134 6.SOE-Of 1.34E-04 4. 7 S E-0 7 3 18E-05 1 49E-04 NO Data 9.2tE-Of I 13S 2.76E-06 S.*lf-06 1. 9 5 E-0 6 4.9fE-04 6.0SE-06 NO Dafa 1.3tt-06 C1134 2.83E-04 S.02E-04 S.32E-05 NO Data 1.36E-04 S.69E=0S 9.$3E-07 C1136 3 4SE-05 9.6tt-05 3.7st-05 20 Data 4.03E-05 0.40E-a6 1.02E-06 C1137 3.92E-04 4.37F-04 3.2SE-OS see Data 1.23E-04 S.09E-05 9.S3E-07 C1134 3.6tE-07 S.58E-07 2.84E-07 soo cafA 2.93E-07 4.67E-08 6 267-07 sal 39 1 06E-09 7.09E-t3 3.0ff-It me Data 4.23E-13 4.2SE-06 3 64E-03 ODCM, Hatch IEV.1 2.0-27 2877W/0152W, 05/11/84

q TABLE 2.2-1 CONT'D ItttALATION DOSE FAC' TORS FOR IWANT*

(MRE'4 PER PCI IPetALED)

Page 3 of 3 assCL ICE Dest L ivE2 F.5007 FMveOlO RieseE T LussG GI-LLt satte 4.00f=0S 4.00C-Os 2.07E-06 Is0 Data 9.S9E-09 1.14E-03 2.74E-OS potet 1.12E-10 7.70f=t* 3.SSE-12 40 Data 4.64k-14 2.12E-04 3 398-06 paint 2.44E-t! 2.36E-14 1.40E-12 40 Data 1.36E-14 1.tlt-06 4.99E-07 Lat40 3.61 E-0 7 1. 4 h-07 3.64E-04 soo Oafa No Defa 1.20E-04 6.56E-05 LS142 7.36E-10 2.69E-10 6.4et-11 40 Data NO DATA S . 0 7 E -04 4.2SE-OS CEl41 1.98f=0D 1.19E-OS 1. 42 E-0 6 40 Data 3.75t-06 3.69E-04 1.54E-05 CE143 2.39(-07 1.10E-97 1.54E-05 40 04T4 4.03E-08 8.3CE-05 3.SSE-0$

"E144 2.2SE-03 3.eSE-04 1.26E-04 40 Data 3.84E-04 7.03E-93 1 36E-04 ett43 1.00E-05 S.74E-04 4. 99E -0 7 'to O&fa 1 4tE-06 3 09E-04 2.66E-05 Pel44 3.42g 11 1.32E-11 1.72E-12 me cafa 4.40E-12 1.1SE-06 3.06E-06 aes t4 F S.67E-Oe S.8tF-06 3. 5 7 E-0 7 NO Cata 2.2SE-36 2.30E-04 2.23E-CS 6 ter 9.26E-09 6.44E-09 2.2 3 E-0 9 40 Data se0 Data 2.83E-OS 2.54E-0S me23, 2.6SE-of 2.37E-Os 1 34E-O s me 04:a 4.73L-Os 4.2SE-OS 117st-05 0004, Hatch REV.1 2.0-28 2877W/0152W, 05/11/84

41 .

1 1

TABLE 2.2-2 i

I WALATION DOSE FACTORS FOR CHILD *

( MEM PER PCI IWALED)

Page 1 of 3 l

l l

4 14CLIGE temE LivEt 7.800f 7478080 ElemEY LussG GI-LLt M 3 40 Data 3.04E-07 3.04E-O f 3.04d-07 3.04C-07 3.04E-r? 3.04E-Of C to 9.70E-06 1.82E-04 1 82E-06 8 22E-06 1.82E-06 I.82E-06 1 82E-06 44 24 4.35E-06 4.JS*-06 4 35E-04 4.3%E-ot 4.35E-e6 4.3SE-06 4.3SE-06 P 32 7.04E-04 1.09E=0S 2 670-05 40 Data 40 Data 40 Data 1.14E-03 CA Sl 40 Defa 40 O&fa 4. t f E -o g 2. 3 t r-ce 6.574-09 4.59E-04 2 93E-07 mm S4 mp OATA 1.86E-05 2 57f-06 20 Data 2.7tE-04 4.26E-04 6.19?-06 mm 56 40 Data 4.44E-10 0.43E-Ll mo Data 4.S2E-10 3.55E-06 3.33f=0S FE SS 1.20E-OS 6.80E-06 2. IGE-06 No Data 40 Data 3.00E-05 7.75E-07 PE 59 S.>9C-04 9.C*E-06 4. Sit-06 40 Data 40 Data 3.43C-04 1.91E-0$

, CO SS 40 Cafa 4.799-07 8.SSE-07 40 Daft WC 04f4 2.99E-04 9.2*E-06 5

CC to 40 Data 3.SSE-06 6.12 E -0 4 40 Data no DATA 1.91E-03 2.60E-05 l 41 63 2.22E-04 1.257-05 7. S 6E-0 6 40 Data no pafa 7.43E*05 I.71E-06 48 65 8.'C S E - 10 7.99E-It 4.44E-Lt mn Data NU Data 2.2tE-06 2.27E-05 CU 64 40 Data S.39E-10 2.90C-10 40 Data 1.63E-09 2.59E-06 9.92E-06 i

th 6S l.ISE-05 3.065-05 1.90E-05 40 Dafs 1.93E-OS 2.69E-04 4.4tE-06 im 69 1.8tE-11 2.6tC-11 2.4 t t-12 40 Data I.SOE-Il 3.84E-07_2$75E-04 at 8 3 40 Cafa NG Cafa 1.2 8E-0 7 40 Data 40 Data =0 Data LT E-24 88 #4 40 Data mu 0474 1. 4 a t -0 7 40 paTA N0 Data 40 Data LT E-24 29 05 40 Oafa 40 Data 6.84E-09 40 Cafa 40 Data 40 Defa Lt E-24 88 a6 NO Data S.36C-05 3.C9E-05 40 Cafa 40 Data 40 Data 2.16E-06 At 48 40 Data 1.52E-Of 9.90E-05 NO Data 40 Data 40 Data 4.665-09 ES 59 40 Date 9 3 3!-03 ' ,7. sat-0 4 40 Data 40 Data 40 Data 5.1tE-10 59 39 1.62E-04 40 Data 4.66E-06 no Data 40 Data S.81C-04 4.52E-05 58 90 2.73E-02 40 cafa 1.74 E-0 3 =0 Data Mc Data 3.99C-03 9.2BE-OS SR 91 3.28E-09 40 Data 1.248-09 40 Data 40 Data 1.44E-05 4.fCc-OS 58 92 3.54E-09 NO cara 1.42E-LO 40 Data 20 Defa 6.49C-06 6.53E-03 Y 90 1.1tE-C6 40 Dafa 2. 94f -0 8 =0 04T4 40 Data 7.07E-05 7.2*E-05 l V 9tP 1.37E-10 40 Data 4.98E-12 40 Data no nafa 7.60F-07 4.64E-07 Y 98 2.47E-04 40 Data 6.59E-04 40 DATA me Data 7.10E-04 4.97E-OS v 92 S.Sof-09 No Cafa 1.5 7E-10 mo Cafa 40 Defa 4.46e.C6 6.46E.05

.

Reference 3, Table E-9.

ODCM, Hatch REY.1 2.0-29 2877W/0152W, 05/11/84 1

1

, , - - - , - - - - , - . . , - , , _ , _ , , . , - , , , - , , _ , - - , _ _ , . , . _ . ..__,,--,-__,_n._,n,-n--~_--

- ,A TABLE 2.2-2 CONT'D IPHALATION DOSE FACTORS FOR CHILD *

(PREN PER PCI IPHALED)

Page 2 of 3 euCLICE 809E L t vet 7.400r TMvecto ElDeEY LUgG Cl-LLI v 91 .5.04E-08 NO Da7A 1. 3eE-09 40 0474 NO cafa 2. ate-05 1.0$E-04 2R 95 S.tJE-05 1.13E-05 1 00 E-0 5 he Data 1.616-0% 6.03E-04 1.65E-05 ER 97 5 07E-08 7.J4E-09 4.32E-09 NO Data 1.05E-08 3.06E-05 9.49E-05 40 95 6.35E-06 2.48E-06 1. 77 E -0 6 40 Defa 2 33E-06 1.66E-04 1.00E-05 MO 99 NO 047A 4.66E-04 1.13 E -0 8 k0 DAT1 1.06E-07 3.64E-05 9.42E-05 TC 99* 4.stE-13 9.41C-13 1.56E-11 40 Data 1.37E-11 2.57E-c7 1.30E-06 7Cl31 2.19E-14 2.30E-14 2.915-13 No cafA 3.9FE-13 t. Sat-of 4.418-09 RUIO3 7.55E-07 NO DATA 2. 90E-0 7 WO Data 1.90E-06 1.79E-04 1.2tE-C5 Aut05 4.13E-10 40 DafA 1.DCE-10 40 DATA 3.63E-10 4.3n[-06 2.69E-05 autot 3.6aE-OS NO Dafa 4.57E-06 90 DATA 4.9FE 3.87E-C3 1 1 E-04 AC110* 6.56E-06 3.08E-06 2.47E-06 ko DATA 5.74L-06 1.48E-03 2.71E-05 TE1254 1.82E-06 6.295-C7 2.47E-07 5.202-07 NG OATA 1.29E-04 9.13f-06 TE127* 6.72E-06 2.3tt-ce 8.loE-07 1.64E-06 1.72E-45 4.C0C-34 1.93E-05 TE127 7.49E-10 2.57E-10 1. 6 5 E-10 5.30E-10 1.9tE-09 2.71F-06 1.525-05 1E121* 5.19E-C6 .t.85E-06 8.22E-07 1.71E-06 1.166-05 4.76E-04 4.9tE-05 7E127 2.64E-11 9.45E-12 6.44[-12 1.93E-Il 6.94L-11 7.9tE-07 6.89E-06 TE13tr 3.63E-C8 1.60E-Os 1. 3 7E-0 8 2.64E-os I.DaE-07 5.56E-05 8.32E-05 TE131 5.87E-12 2.28E-12 1.7st-12 4.59t-12 1.59C-It 5.55E-07 3.60E-07 t TE132 1.30E-07 7.36E-08 7.12E-os 8.58E-Os 4.79t-37 1.02E-04 3.72E-05 l t 130 2 21E-06 4.435-06 2.2aE-36 4.99E-04 6.61k-06 40 DATA 1.385-Og t 131 .,s0E-C5 1.30E-05 7. 3 7 E -0 6 4.39E-03 2.13f-05 N3 0474 7.68E-07 l

t-132 5.72E-07 1.1C!-06 5.0 lE-0 7 5.23E-05 1.69E-C6 40' Data 8.65E-07 I 133 4.48C-06 5.49~-06 2. 00 E-0 6 1.04E-03 9 13E-06 40 DafA 1.48E-06 I 136 3.17E-07 5.84E-07 2.6 9E -0 7 1.37E-05 8.92E-07 40 Dafa 2.SSE-07 I 135 1.33E-06 2.56E-06 1.12 E-0 6 2.14C-c4 3.62E-06 40 DafA 1 20E-06 C1134 1.76E-04 2.74C-04 6. 0 T E -0 5 90 DafA 8.93E-05 3.27E-05 1.048-06 C5116 1.76E-C5 4.62E-05 3.14E-05j wo Da7a 2.58E-35 3 93E-06 1.13E-06 l C1137 2.45E-04 2.23E-04 1.47E-05 40 cafa 7.63E-05 2.stE-05 9.74E-07 l C1138 1.71E-07 2.27E-07 1.50E-07 WO DATA 1 60E-47 1 84E-08 7.29E-08 l

t sats* 4.9et-10 2.66a.13 1.ast-1: =0 DATA 2.33E-13 1.56E-06 1.56E-05 l

l l

i l

ODCM, Hhtch REV.1 2.0-30 2877W/0152W, 05/11/84

-if TABLE 2.2-2 CONT'D IfedLATION DOSE FACTORS FOR CHILD *

( MEM PER PCI IteMLED)

Page 3 of 3 kWCLIDE SONE LivEE 7.2007 TNTROIO RIDmET tuses GI-Itt 54t40 2.00E-OS 1.75E-08 1 17E-06 NO DATA S.7tE-09 4.71E-04 2.71E-84441 S.29E-11 2.9SE-L4 1.72F-12 40 047A 2.56E-14 7.89E-07 7.44E-04 Sat 42 1 3SE-11 9.73C-IS 7.MC-13 40 CATA 7.87E-15 4.44E-07 7.4tF=to Lat40 1.74E-07 6.04E-08 2.04E-08 40 DAT4 40 04fA 4.94E-05 6.10E-05 LAI42 3.50E-10 1.11E-10 3.49E-t1 90 0474 20 Data 2.35E-06 2.0$E-0%

CEt41 1.06E-OS 5 28E-04 7. 83E-0 7 NO cafa 2.3tE-06 1.47E-04 1.53E-05 CE143 9.89E-08 S . 3 7 E-Ot. 7.77E-09 90 DafA 2.26E-08 3.12E-0$ 1.44E-05 CEt44 1.83E-03 S . 72 E- 04 9.77E-05 90 DATA 3.17E-04 3.23C-03 1.0$E-94 Pet 43 4.99E-06 1.30E-06 2.47E-07 40 Data 4.116-07 1.17E-04 2.63E-05 Pat 44 1.6tt-11 4.996-12 4.10E-13 40 DATA 2.64E-12 4.23E-97 S.32E-04 90147 2.92E-06 2.36E-06 1 84F-0 7 40 0474 1.307-06 8.87E-05 2.227-01 w 187 4.4tE-09 2.61E-09 1 1 TF-0 9 90 CATA mC CATA 1.1tE-05 2.44E-01

=P239 1.764-07 9.04e-09 6.3SE-o9 =0 OafA 2 63E-oS 1.57E-05 1.73E-05 00CM, Hatch REV.1 2.0-31 '

2877W/0152W, 05/11/84

._-y-----,---.-,--.,-y- , - - . - - - , , - - . -,-n.~-,,

- - - --..-,-.ye---- ,.r. -

-3 y.,wy-r-, -,--w, %--- p.,-.-+,w,- - , - - . , - - ,

e._

Yj TABLE 2.2-3 IM4ALATION DOSE FACTORS FOR TEENAGER *

(MREM PER PCI Il@iALED)

Fage 1 of 3

[

muttlet sont Liven v.meer 7mve0 e stoute tums s -(t

a me Dafa 3.598-0r 1. S 98 -0 7 1.S98-07 1.59e.07 a .598-0 7 1.598-07 C 14 3.2SE-C6 6.C9E-07 4. 09t-0 7 6.098-07 6.r9E-07 6.09E-07 6.09E-07 4 me 24 1.72E-04 1 72E-06 1.72E-06 1.72E-04 1.72E-06 1.72E-06 1.72E-04 P 32 2.34E-04 1.57 -09 8.95C-04 me DafA #C OATA me DafA 1.167-05 CR 51 40 04f4 40 Data 1.69F-08 9 37E-09 3.84E-a9 2.62E-04 3.75t=0F pm $4 NO 04fA 6.318-06 1. 03E-04 20 OATA 1.19E-06 2.48E-04 8 3SE-06 mm S6 NO DATA 2.124-10 3.lSE-11 40 Data 2.24E-10 1.9CE-C6 7.1EE-06 FE $$ 4.18E-06 2.984=06 4. 9)E-S I NO DATA 40 Lafa 1.S$f-05 7.99E-07 FE 59 1.19L-06 4.42E-06 I . 79E-0 6 NO 04fa 40 DafA 1.9tf-04 2.23E-CS CO SE =0 DafA 2. 397-C 7 3.4 7E -0 7 40 DATA =0 O&fa 1.68E-04 8.19F-OS CU 40 40 Cara 1.81E-C6 2. 4 8f -0 6 NO 04f4 NC OATA 1.09E-03 3.24E-CS 48 63 7.2SE-CS 5.*3E-06 2. 4 7 E -0 6 40 Data mc Cara 3.84E-35 1.77E-06 at et 2.73E-in 3.64f-11 1.598-11 NO 04f4 me DATA 1.17E-46 4. S 9E-06 CU 66 40 Oafa 2. Set-13 1.04E-10 20 Data 8.clE-10 1.39E-te 7.48E-06 Am 65 4.E2E-06 1.e7E-OS 7.4CE-0 6 40 04fa 8.00E-OS 1.SSE-04 5.83E-06 Em 69 4.046-12 1.!SF-11 8.0ft-13 NO DATA 7.93E-12 1 90E-07 1.56F-00 na e3 me DafA NO Def4 4.30C-08 40 Defa NO 04f4 N0 DafA (T E-24 na 84 NO Data 20 Cafa S.4 t E-0 8 40 CATA WC Cafa NO Cata .LT E-24 AG ab 40 Data me CATA 2.2 9E-0 9 #4 Cafa 40 DATA me cafa (7 E-24 08 86 40 04fA 2.3eE-OS 1. C S E-0 5 40 Data 40 Data 40 Data 2.28t-06 89 09 NO 0414 6.82E-Og 3.*GE=ce 20 Data me DATA NO 04fA 3.6SE-!S as 39 40 Data 4..CT-os 2.9 t E -0 8 20 Data .mC CATA 40 Data 4.22E-17 SR 89 S.43E-CS NO Cata 1.56E-06 40 Data NC Data 3.C2E-04 4 64E-0S 1

Sa 93 1.3SE-02 no Defa 3. 3 S E -0 4 NO Defa NO Cata 2.04E-03 9-S6E-05 SR 91 1.10E-08 40 CafA 4.19E-10 NO DafA me Data 7.59E-06 3.24E-01 14 92 1.19E-C9 40 Cafa S.00E-11 40 Defa 40 04f4 3.41E-06 1.49f-05 v 90 3.F3E-07 NO 04f4 1 00E -0 8 40 Data 40 Data 3 66E-05 6.v9E-05 V 9t* 4.638-11 to Oafa 1.77E-t2 40 OATA me Data 4.0CE-C7 3.7tE-09 y el e.26E-OS me para 2.215-06 no Data 20 Defa 3.67E-04 S.18E-OS v 92 1.e4E=en 20 sata S.3*E. 1 ne safA me oata 3.355-06 2.e6E=0S r

I

Reference 3, Table E-8.

l i

r l ODCM, Hetch REY.1 2.0-32 287m/0152W, 05/11/84

_-. . wA l TABLE 2.2-3 CONT'D INHALATION DOSE FACTORS FOR TEENAGER *

(MREM PER PCI IM1ALED)

Page 2 of 3 gwCLICE 80mf LIW4 f.aOOT Twve010 Elemtv Lugs St-LLI V 93 1.69E-00 NO DATA 4.6SE-10 90 Dafa he DATA 1.04E-05 7.24E-OS 24 95 1.02E-05 S.73E-06 3.94E-06 40 Data 8 42E-06 3.36E-04 1.06E-0S 24 97 1.72E-08 3.40E-09 ! . S T E-0 9 40 DATA S.tSE-09 1.62E-OS 7.88E-05 to 9b 2.32C-06 1.29E-06 7. 08 E-0 7 20 DafA 1.2SE-06 9.39E-OS 1.21E-0S pc 99 20 Data 2.Itt-08 4.03E-09 40 CATA S.14E-08 1.92E-0S 3.36E-OS IC 998 1.73E-13 4.83(-15 6.24E-12 40 DafA F.20E-12 1.44E-07 7.66E-07 TCt0! 7.40E-IS 1.0SE-14 1.03E-13 40 04T4 1.90E-11 9.34E-08 1.09E-te aut03 2.63E-07 40 CATA 1.12 E-0 7 NO 04fA 9.29E-07 9.79E-OS 1.36E-OS SutOS 1.40E-10 40 04fA S.42E-11 20 CatA 1.76E-to 2.27E-06 1.13E-OS 89806 1 23E-0S 20 DATA 1. S SE-0 6 20 04f4 2.38E-OS 2.01E-03 1.20E-04 44410p 1.73E-04 8 64C-06 9. 99E -0 7 40 DATA 3.13E-06 0.4*E-04 3.41E-OS TE121= 6 10E-0F 2.80E-0F 8.34E-00 1. 75E-O F 90 DATA 6.70E-OS 9 38E-06 TEt27m 2.2SE-06 1.CFC-06 2.73E-07 S.4 EE-0 7 8.17E-06 2.0ff=04 1.99E-05 IE127 2.51E-10 3 14F-10 S.S2C-l! 1.77E-10 9.10E-10 1.40E-06 1.01E-05 TE129= 1.74E-06 0 23C-0F 2 8 t t-0 F S.72E-07 6.496-04 2.47E-04 S.06E-OS TE129 8.87E-12 4.22E-12 2.20E-12 6.4RE-12 3.32E-11 4.12E-07 2 02E-07 TE13tr 1.23E-08 7.S!C-09 S . 0 J E-0 9 9.06E-09 S.49E-00 2.9fE-05 7.74E-0$

TEtJI 1 9fE-12 1.042-I2 6.30E-13 1.SSE-12 7.72E-12 2.92E-G7 1.89E-09 TE132 4.50E-08 1.e3E-OS 2.74E-08 3.07E-08 2. 44 E-0 7 S.6tE-OS S.79E-OS I 130 7.80E-07 2.24E-06 0.96E-0 7 8.86E-04 3.4*E-06 k0 DATA 1.14E-06 8 131 4.43E-04 6.14E-04 3. 3 0 E-0 6 3.83E-03 1 0SE-05 NO DafA 8 11F-07 I 132 1.99E-07 S.4ff-07 8.97E-07 1.8 9E-05 0.65E-07 NO Cafa t.S9E-07 8 133 1.$2E-06 2.36E-06 7.70E*0F 3 4SE-04 4.49E-06 20 Cafa 1.2 9E-06 8 134 1.1tE-07 2.90E-07 1. 0 S E-0 7 4.94E-04 4.58E-07 40 Data 2.SSE-09 1 ISS 4.42E-07 1 10C-06 4. 36E -0 7 7.76E-OS 1.06E-06 40 Data e.69E-07 C$t34 6 28E-05 1 4tt-04 6. 86E-0 5 NO Data 4.49E-OS 1.81E-05 1.22E-06 l C$li6 6.4*E-06 2.42E-05 1.78t 40 Data 1.3sE=0S 2.22E=ce 1.36E-06 i

. .. . ~ ._-0__5 -

CS137 8.30E=0S 1.06E-04 3.89 E-O S 40 Data 3.80E-05 1.Stt-OS 1.06E-06 CS138 S.82E-08 1.07E-07 S . 5 0 E -0 8 40 Defa 8.20E-08 9.84E-09 3.38E-Il sat 9 1.67E-te 1.seE-13 4.87E- 2 no SATA 1.t E-t3 8.00E-07 8.06E-07 l

l 0004, Hatch REV.1 2.0-33 2877W/0152W, 05/11/84 i

.- _ _ . . _ ~ . . , _ . , _ _ _ _ . . . _ _ ____,_ _ ___ ___ _ _._ . _ - . _ _

m c

TABLE 2.2-3 CONT'D IltlALATION 00SE FACTORS FOR TEENAGER *

(WlEM PER PCI IttiALED)

Page 3 of 3 aansgL3 gg geest LIVE 8 7.500T 79eveOle RieseEY LussG GI-LLI sat 40 6.84E-06 8.38E-09 4.40E-07 800 Data 2.85E-69 2.54E-04 2.86E-05 Salot 1.78E-tt 1.s2E-14 5.9AE-L3' NO Data 1.23E-14 4.1tE-07 9.33E-14 64142 4.62E-12 4. 6 3E- 15 2.84E-13 20 Data 3.92E-15 2.39E-07 5.99E-20 Lal40 5.99E-08 2.95C-08 7. 82E-09 8eo Data se0 DATA 2.68E-05 6.09E-05 Lat42 1.20C-10 5.31E-11 1.32E-tI seo Data ato Data 1.27E-06 1 50C-06 CElet 3.55E-06 2.37C-06 2. 7 t t-0 7 aso Safa 1.1IE-06 7.67E-05 1.58E-05 CEt43 3.32E-08 2.42E-08 2. 70E-0 9 me cara 1.084-c8 1.63E-05 3.19E-05 CEt44 6.ItE-04 2.53E-04 3.28E-05 ese Cafa t.StE-04 1.67E-03 1.08E-04 P9143 1 67E-C6 6.64E-07 8.28E-08 No cafa 3.86E-07 6.04E-05 2.67E-05 Fel44 5.37E-12 2.20E-12 2.72E-13 40 Defa 1.26E-12 2.19E-07 2.94E-14

'e014 7 9.83E-C7 1.07E-04 4. 4 t E-0 8 aen Data 6.29E-C7 4.65E-05 2.28F-05 et 187 1 50E-09 1.228-09 4.29E-10 800 Data se0 Data 5.92E-06 2 21E-05

'vF239 4.23E-08 3.99E-09 2.2tE-0* ae0 O&fa 1.2SE-08 8 11E-06 -1.65E-05 l

i 0004, Hatch REV.1 2.0-34 2877W/0152W, 05/11/84

'l i

TABLE 2.2-4 INHALATION DOSE FACTORS FOR ADULTS

OREM PER PCI If+1ALED)

Page 1 of 3 seuCLICE sont LivEt 7.80c7 fava 080 aIONEY Lums st-LLI m 3 40 Def a

1.SM-07 1. 58F-4 7 1.58E-C7 1.58E-07 1.58E-07 1.58E-07 l- C 14 '2.27E-06 4.26E-07 4.26E-OF 4.26E-07 4.26E-07 4.26E-07 4.2 6E-0 7 MA 24 1.28E-06 1.28E-04 1.28E-06 1.28E-06 1.20E-06 -1.28E-06 .

1.28E-06 P S2 1 65E-04 9.64E-06 6.26E-06 NO 0474 seC DATA son Data 1.08E-OS CA 51 8e0 DATA 20 DafA 1.25 E-0 8 7.44E-09 2.85E-09 1.80E-04 4.tSE-07 mm 54 NO DATA 4.95E-06 7.8 TE-0 T 8eo DafA 1.23E-06 1.7SE-04 9.67E-06 mee S6 40 DATA 1.SSE-10 2.29E-11 40 DAfa 1 63E-10 1.18E-06 2.SSE-06 FE SS 3.0TE-06 2 12C-06 4. 91E-0 7 880 Da f A 40 Data 9.C1E-06 7.54E-07 PE $9 1 47E-06 1.*fE-Oo 1 32E-06 40 DATA me CATA 1.27E-04 2.35E-63 CD SS 40 OATA 1.98E-07 2.59E-0 7 40 CaTA esc CATA 1.16E-04 1.33E-05 CO 60 20 DATA 1 44E-06 1 8SE-0 6 40 DafA mc CAIA 7.46E-04 3.56E-05 sel 63 5.40E-05 3.9 3E-06 1 81 E-0 6 soO DATA NO DATA 2.23E-OS 1.67E-06 I 11 65 1.92E-10 2.e2E-11 1.14F-11 NO CATA secDATA 7.00E-07 1.54E-06 CU 64 NO DATA 1.8JE-10 F.69E-!! NO DATA S.78E-10 8.48E-07 6.12E-06, 24 65 4'.05E-06 1.29E-05 s.82E-06 40 DATA 8.62E-06 1 08E-04 6.68E-oe 24 69 4.23E-12 8 14C-12 S.6SE-13 NO Data 5 27E-12 1 15E-07 2.04E-09 68 83 NO DATA 880 Cafa 3.01E-Os 90 OATA wo Cafa no DATA 2.90E-08 l SR 84 40 04f4 NO DATA 3.9tE-08 '90 04f4 esc O&fA NO CATA 2.0SE-13 l

l sg SS ase Data NO Cafa 1.60E-09 seo CATA se0 Data sto DefA LT E-24 42 Se 40 esfA 1.69E-05 7.37E-Os se0 OATA sec 04T4 h0 Data 2 08E-06 48 88 20 DATA 4.84E-08 2 41E-38 8e0 Data P:0 CATA soo Data 4.18E-19 SS 89 NO DATA 3 2CE-08 2.12E-08 NC 3ATA NO Data 40 CATA 1.16E-21 SR 89 3.80E-05 40 Caf& t . 3?E-0 6 NO Cafa 20 DATA 1.75E-04 4.37E-05 i

% 90 1 24E-02 NO Cafa 7.62E-04 8ec Caf a NC OATA 1.20E-03 9.02E-OS EK 91 7.74E-09 No Caf4 3.13E-10 see DATA eso 0474 4.56E-06 2.39E-05 1A 92

8.43E-10 40 Cafa 3.44E-11 40 DATA NO O&fa 2.06E-06 5.38E-06 Y 90 2 6tE-07 40 CATA 7.01 E-0 9 No DATA soo DATA 2.12E-05 6.32E-OS Y 91st 3.26E-11 se0 DATA 1.27E-12 880 DATA NO O&fA 2.40E-07 t.66E-10 Y 98 S.78E-05 age 04Ta 4.51E-06 ese DATA no DATA 2.13E-04 4.8tE-01 V 92- 1 29E-09 me Defa 3 77E-11 to DATA Is0 Data 1 96E-06 9 19E-04 l

I .

l

Reference 3, Table E-7.

l EXN, Hatch IEY.1 2.0-35 2877W/0152W, 05/11/84 1

l I _ . . _ _ _ _

1.s .

TABLE 2.2-4 CONT'D IPHu.ATION DOSE FACTORS FOR ADULTS *

(MD4 PER PCI IPHALED)

Page 2 of 3 wCs,1::t 90mf tivfa 7.Soav Twen010 a10=Ev tuas s!-u!

y 93 1.18E-08 =0 OAfa 3.26E-10 no OATA =0 Data 6.06E-06 S.27E-OS In 95 1.34E-05 4.30E-06 2.91E-06 me oaf 4 6.77E-06 2.21E-04 1.88E-OS In 97 1.21E-08 2.4SE-09 1.13E-09 20 DATA 3.71E-09 9.84E-06 6.S4E-05 me 9% 1.76E-06 9. 77E-07 S.26E-0 7 me OaTA 9.67E-07 6 31E-05 1.30E-05 I

m0 99 40 CATA 1.51E-08 2. 8 7E-09 20 Data 3.64E-08 1.14E-05 1.10E-05 fc ,,* i.29E-il 3. 4E-i3 4. 6 n-i 2 me 0.fA 3.52E-12 9.SSE-00 S.20E-07 fC101 S.22E-15 7.S2E-15 7.3st-14 me DATA 1.354-13 4.99E-08 E.36E-21 AU103 1.91E-07 NO DATA 8.2J E-0 8 NO cara 7.29E-0 7 6 31E-05 1.38E-OS au1OS 9.88E-11 20 DATA 3.89E-11 m0 OATA 1.27E-10 1 17E-06 6.02E-06 eU196 8.64E-06 NO DATA 1.0 DE-06 no Defa 1.67E-05 1.17E-03 1.14E-04 AG110P 1.3SE-06 1.2SE-06 7.4 AC-0 7 me 0474 2.46E-06 S.79E-04 3.74E-05 TE1254 4.27E-07 1 98E-07 S . 84E-0 4 1.31E-07 1.SSE-04 3.92E-05, 0.83E-06 TE127p 1.SSE-06 7.21E-07 1. 96E -0 7 4.11E-07 S.72E-06 1.2cE-04 1.87E-OS l TE127 1.7SE-10 0.039-11 3.4FE-11 1.32E-10 6.37E-10 0.14E-07 7.17E-06 IE129* 1.22E-06 S.64E-07 1 90E-0 7 4 30E-07 4.57E-06 1 4SE-04 4.79E-05 TE129 6.22E-12 2.99E-12 1.SSE-12 4.87E-12 2.34E-11 2.42E-07 1.96E-08 ,

TE131m 8.74E-09 5.4SE-09 3 43F-09 6.88E-09 3 06E-08 1.82E-05 6.95E-OS

) TE131 1.39E-12 7.44E-13 4.49E-13 1.17E-12 S.46E-12 1.74E-07 2.30E-09 TE132 3 2SE-00 2.69E-08 2.02E*08 2.37E-08 1.82E-07 3.60E-05 4.37E-0S I 430 S. 72 E-0 7 1 68E-04 6. 60E-0 7 1.42E-04 2.61E-06 #0 Date 9.61E-07

, 1 131 3.15E-04 4.47E-Os 2.56E-06 1.49E-03 7.66E-06 20 Data 7.8 SE-0 7 l '

1 132 1.45E-07 4.07E-07 1. 4 bE-0 7 1.43E-05 6.48E-07 N0 Data S.00F-08 1 1 133 1.08E-06 1.8SE-06 S.6tE-07 2.69E-04 3.23E-06 NO Cata 1 11E-06 1 134 0.0SE-00 2.16E-07 7.69E-05 3.T3E-06 3.44E-07 me Gefa 1.26E-10

i. I 135 3.35E-C7 8.73E-07 3.21E-07 S.e0E-05 1.39E-06 N0 Data 6.56E-07 CS134 4.64E-05 1.06E-04 9.10E-05 MO cara 3.59E-OS 1.22E-0$ 1.30E-06 CS136 4.88E-06 1. 8 3E = 0 S 1. 3 8E-0 5 me Data 1.07E-05 1 50E-06 1.46E-06

!" CS137 S.98E-05 7.74E-OS 5.3 S E-O S NO ca74 2.78E-05 9.40E-06 1.0SE-04 CS138 4 14E-08 7.76E-08 4.85E-0 8 to DATA 6.00E-08 6.07E-09 2 33E-13 i 84139 1.17E-10 0.32E-14 3 42E-12 =0 Defa 7.78E-14 4.70E-07 1.125 07 1 -

I r

i l

0004, H8tch REY.1 2.0-36 2871W/0152W, 05/11/84 l

I

, _, - - - - - . . , , - . - - - - ~ , , - - - - - - - - , ,--~c~~~~~ "~'~*'~~"~~**A*~ " " ' " " ~ ' " ' ~ ~ ' '

(( ,

I i

TABLE 2.2-4 CONT'D INHALATION DOSE FACTORS FOR ADULTS *

(MEM PER PCI IPHALED)

Page 3 of 3 auCLIUE 00mE E IvEa 7. Ster TseveOf0 alOsety Lipet gg ggg uit. . . ut -. . . u 09 9.,i E-0 7 0 ura 2.On- 9 1.59E 4 2.7 r G malet 1.2SE-11 9.48E-IS 4 20E-13 NO DATA 0.75E-15 2.42E-07 1.4SE-t?

4842 2.29E-42 3.30E-15 2.07E-19 20 SATA 2.06E-tS 1.49E-07 1.96E-24 Lal40 4.10E-C8 2.17E-04 S.73E-0 9 fee OAfa 40 DATA 1.70E-OS S.73E-CS L4142 8.54E-II 3.88E-11 9.64E-12 NO 047a se0 DATA 7.9tt-07 2.64t=07 CE141 2.49E-06 1.69E-06 1. 9 t E-0 7 90 DaT4 7.834-07 4 52E-OS 1.SOE-05 Cit 43 2.33E-C4 1 72E-Os 1.9 t E-0 9 son Daft 7.60E-09 9 97E-04 2.43E-05 CEl44 4.21E-04 1.79E-C4 2.30E-OS NO 0474 1.04E-04 9 72E-04 1.02E-04 pe143 1.17E-04 4.69E-07 S. 80E-0 0 NO DAfA 2.70E-07 3. Sit-05 2.SOE-05 Pet 44 3.76E-12 1.S6E-12 1. 91 E-13 40 Cafa 40847 6.S9E-07 7.62E-07 4.56E-08. eso Data s.stE-13 1.277-07 2.69E-te w 187 4.4SE-07 2 76E-05 2.16C-OS 1.C6E-09 0.4SE-13 3 10E-10 WO DATA 40 DATA 3 6)E-04 1.94E-OS IsP239 2.37E*04 2.82E-09 1.SSE-09 ase SafA ,0.754-09 4.70E-06 1.49E-05 l

i 0D04, Hatch REV.1 2.0-37 287M/0152W, 05/11/84

TABLE 2.2-5 INGESTION DOSE FACTORS FOR IWANT*

(MEM PER PCI INGESTED)

Pege 1 Of 3 quCtIDE Sent Ltwie f.00w fuvecle stemtv Luns st-LLI M. 3 .he Safa 3 006-07 3.088-07 3.088-07. 1.006-07 3. 08E-0 7 3.00E-07 E I4 2.3FE-OS S.068-06 S . 06C-0 6 1.06t=e6 S.06t-04 S.06F-04 S.064-04 to 24 1.014-05 3.01C=0S 1 0t t-O S 1.018-05 1 03E-05 1 01E-Oh 1.0BE-OS P 32 1.70E-03 1 004-04 6.594-05 see cafa No DATA see Data 2.50E-09 Ca St me DATA 8ec Defa 1. 4 t E*0 s 9.208-09 2.01E-09 1.79E-os 4.ttt-07 see S4 90 Data 1.99f-05 4.588-06 40 04f4 4.4tt-04 NO DATA 7.3tE-06 see $6 NO Cata S.10E-07 1.4 t E =0 F *eu 04f4 7.014-07 90 Data 7.43f=0S FC SS 1.39t-0S 8.90E-06 2 40E-06 NO DefA 880 O&ta 4.19E-06 1.14E-06 FE $9 3.csE-05 S. set-Os. 2.12E-Oh 40 CATA NO DATA 1.S9t-OS 2.$7E-0S C0 SS 800 04 f 4 3.60t=06 8.938-06 MO DATA 40 DATA 40 DATA 8.97t=06 CO 60 8e0 OATA 1.484-05 2.SSt-OS 8e0 04f 4 NO DATA too 04f4 2.SFf=0S

%I 63 6. 3 4 E-G4. 3.928-OS 2.20E-0 5 seO DATA NO DATA se0 DafA 1 998-04 el 65 4.704-06 S.325-0V 2.42f-07 see UATA 40 CATA ho 04fA 4.0SE-05 CW 64 90 Data 4.096-OF 2 82E-07 10 04f4 1.03t-06 NC DATA 1.25t-CS Im 65 1.348-05 6.314 2.9tE-03 8e0 DATA 3 06t-05 sec OATA S.33E-05 2N 69 9.33f-08 1.ast=0F t.2SE-00 800 DafA 4.90E-OS son 04Ta 1.378-01

. se 03 10 04f4 800 04f A 3.63E-07 8so 04f4 =0 DATA NO Osta Lt E-24 to 84 8e4 DafA 800 OAT A J.82E-07 sec 04f A =0 OATA NO 04f4 LT t-24 et es too CATA NO O&fa 1 94 f-O g see CafA pec OATA NO Data LT E-24 as 36 NO Data 1.708-04 0.44f-0 5 40 04f4 peo OafA NO 04fA 4.3St-04 40 84 Is0 04f4 4.904-07 2.738-07 800 Da t a =0 O&TA 8e6 OATA 4 4Sf-07 et 89 suo DATA 2.86t=07 8.976-17 8e4 OAfa se0 04f4 NO 04fA 9.74E-08 la 09 2.51E-03 40 04fA 7.208-0S 90 Data 8ec 04f4 no cafa S.16E-05 SR 90 1.8SE-02 800 CATA 4. 7 8 t =0 3 880 D A T A NO DATA NO 04f4 2.318-04 SR 91 S.00E-OS NO 04f4 1. 0 t E-0 6 MO 04T4 NO Cafa 8ec 04fA S.92t=0S le 92 1 92t=0S 800 DAf a 7.338-07 8e0 Defa 800 De f a NO 04f4 2.07E*04 Y 90 S.698-08 aee DATA 2.346-09 se0 DafA 8e0 04 f 4 ase 04fa 1.20E-04 2 Y 9tm 8.108-10 800 04T A 2.76E-l1 peo 04f4 8ec Data see CafA 2.70E-06 Y 98 1.13E-06 se 04fA 3 048-08 Is0 DafA Ise SATA 8se Defa 0.10E-OS e 92 7.6Sf-09 se sera 2. t St-t e me Saf4 me Safa no 04fa 1.46e-04 i

Reference 3, Table E.14.

I i

0004, Hatch REV.1 2.0-38 2871W/0152W, 05/11/84

- . - _ . , _ . _ _ . _ - _ _ . . . ~ . - . _ , , . _ _ , _ . . , _ _ _ . . ,___.- _ .__. _ _ _ _,_- m.-. .

n 1

i 4

TABLE 2.2-5 CONT'O INGESTION DOSE FACTORS FOR INFANT *

(MEM PER PCI INGESTED)

Page 2 of 3 1

autt st sent Livf4 7.sost Tavecto alamtv tuas of-u !

~~

v 93 2.43e.00 se sava .6.42E=l e me Data me omfa me Data 1.928-0 2n 95 2.068-07 S.02t-ce 3. Set-Os =0 Data S.4tt-na me Safa 2.507-OS 28 97 1.44E-04 2. Set-09 1 46E-09 =0 DATA 2.S44-09 n0 Data 1.42E-04 90 95 4 208-08 1.71E-04 1. 038-0 e ase Oafa 1.24t-00 =0 Data 1.464-0S ne 99 no Oafa 3.444-05 4.638-06 sos Defa S.004-OS ese Safa 1.12E-OS TC 997 l.928-09 3.948-99 S.100-08 Is0 04f4 4.264-04 2.07t-09 1.158-04 FClet 2.27E-09 2.868-09 2.836-08 =0 Data 3.404-08 8. Set =09 4.860-07 89403 1.444-06 see 04f 4 4.998-07 90 Da74 3.006-04 =0 Defa 1.00E-01 eul0S 1.364-07 =0 enTA 4.588-04 800 Data 1 004-04 886 Data S.418-05 Rulee 2.411-01 20 Data 3.01t-36 esp O&fa 2.494-01 8eo Oafa 1.03F-04 '

44tten 9.964-47 7.27E-Of 4.818-37 40 Data 1 044-06 see O&fa 3.778-09 ft12Sp 2.338-05 7.79C-04 3.15E-06 7.84t-06 mc Data soo O&ta 1.11t-OS TEl27M S.8St=0S l.94t=0S 7.088-04 1.69f*05 1.440-04 see nata

~

2.368-11 TE427 1.00E-04 3.355-07 2. l S E-0 7 8.14E-47 2.444-04' en Oafa 2.10E-09 fil29# 1.004-04 3.4)E-09 1.548-05 3.84E-OS 2.508-04 8e6 Data S.9ff=0S 18129' 2.848-07 9.19t=0e 6.63t-04 2.308-07 7.c7t=47 20 O&fa 2.278-05 TEt3ir 1.h2E-OS 6.12t-06 S.058-06 1.248-0$ -4.218-0S 40 Data 4.03t=04 tilat 1.76E-07 6. Set =08 4.944-00 1.374-07 4.508-07 8on Oafa 7.ttt-04 FEt32 2.08E-05 1. 0 38-Ob 9.618-06 1.52F-GS 6.444-05 =0 Data 3.818-05 1 130 4.00E-06 1.321-15 S.304-06 1.48E-03 1.498-0S f.O Oafa 2.83E-04 I 131 3.198-05 4.235-05 1. 4et-O S 1.396-02 4.948-05 soo Cafa 1.11E-06 4 132 1.664-06 3.l?t=04 1.2 0f-0 6 1.984-04 3.76t-06 feo Oafa 2.73t-06 I 133 1 258-09 1.82T-0$ S. 3 5t-04 3.Jtt-01 2.148-35 me Cafa 3.00t-06 I L34 8.696-07 1.78t-06 6.338-07 4.!Stans t.998-04 see Oafa 1.e48-06 8 135 3.64t-06 7.24t=06 2. 64 t -04 4.49t-04 8.078-06 =0 Data 2.628-06 cst 34 3.778-04 7.038-04 7. t C E-0 5 see Caf a 1.stt-04 7.42E-05 1.918-04

C$lle 4.59t-OS 1.358-04 S.04 E-0 5 see Data S.388-OS l.10E-OS 2.0SE-06 C$t37 S.22E-04 6 11E-04 4. 3 3E-O S NO Cafa 1.648-04 6.64t=0S 1.918-06 C$lle . 4.4tt-07 7.428-of 3.79t-OF see Defa 3.908-07 6.098-00 1.2 SE-06 sat 19 a. elf-Gr S.eet-Le see esta 3. Sit-te 3.948-le S. Set-OS 2.SSt._-O s .

i .

i i ODCM, Hatch REV.1 2.0-39 2871W/0152W, 05/11/84 e

. ,-- - - , _m-, ,,-.% -,._--y,--.,-,w,,.,,gn,-_-,,.n,-,--. . . , - . .-..,.,.,,,,--,e. - - - . . - - ,we

TABLE 2.2-5 CONT'O INGESTION DOSE FACTORS FOR INFANT *

(> REM PER PCI INGESTED)

Page 3 of 3 guctioE come Lives r.aeor rhveole stoefv Lwas cr-tti 84443 8.7tE-04. 1.71E-07 8. 4 8 E-06 40 04T4 4.06E-OS 1.0SE-07 4.20E-OS 84441 4.2SE-07 2.912-10 1.34E-O s ' son D Af 4 3.TSE-10 1.77E-to S.19E-06 sat 42 8.84E-07 1.$3E-10 9.06E-09 880 Daf A 3 01E-18 9.26E-t! 7.59E-07 Lat40 2.IIE-00 0.32E-09 2 14E-09 aoO OaTA sec 0414 NO DATA 9 77E-OS Lat42 1 10E-09 4.04E-10 9.6ff-t1 pen 04Ta seC Def a leo Oara 4 46E-OS CE148 7.8 FE-08 4.80E-08 S. 6 > E-0 9 esO Data 1.4eE-04 NO DATA 2.48E-05 CEt43 1.40E-Ce 9.82E-06 1.17 E-0 9 40 Data 2.96E-09 NO cafa S.73E-05 CE144 2.9st-04 1.22E-06 8.67E-17 40 Data 4.93E*0F NO Oafa 1.FIE-04 pel43 e.83E-08 3.G4E-00 4. 0 3 E-0 9 NO Data 1.13E-ne NO DATA 4 29E-OS Pel44 2.74C-10 1.04E-10 1.30E-!! N0 Data 3.446-11 NO DATA 4.93E-06 18014 F S.53E-00 S.60E-08 3. 4 8E-0 9 40 OATA 2.19E-0A NO Defa 3.60E-OS w 107 9 03E-07 6.2se-OF 2 17E-0 F 40 04tA NO DefA NO C&Ta 3.69E-05 me239 8.!!E-os 0.9st.10 S.alf-t o w para 1.9st-09 no 04ra 2.8 7t-05 0004, Hatch REY.1 2.0-40 287he/0152W, 05/11/84

A TABLE 2.2-6 INGESTION DOSE FACTORS FOR CHILD *

( EEM PER PCI INGESTED)

Page 1 Of 3 mutt:aE ao=v L i vf = T. sour TNve0:0 RIONEv tu=c c:-(t N 3 1W3 O&ft 2.03E-07 2. 01E-0 7 2.03E-07 2.93E-07 2.03E-07 2.03E-07 C 14 1.21E-05 2.*2E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-66 2.42E-06 94 24 S.80E-06 S.80E-C6 5.8CE-06 S.80E-06 S.00E-06 S.80E-06 5.80E-04 P 32 8.2SE-04 3.86E-06 3.18E-OS 40 Data 40 cafA No cafa 2.28E-05 CR St NO DATA #0 &ATA 8. 9 0 E-0 9 4.94E-09 t.3SE-09 9.02E-C9 4.72E-07 mN S4 40 DATA 1.07E*CS 2. 8 SE-04 NO DafA 3.00E-06 NO 04TA 3.98E-06 NN S6 40 DATA 3.34E=0F 7. S = E -0 4 NO DATA 4.C4E-07 NO DafA FE SS 4.84E-05 1.1SE-05 6 10E-06 1.89?-06 No Cafa NO Data 3.4SE-06 1.13E-06 FE $9 1.63E-05 2.6FE-05 1.3st-05 90 DATA NO DAfa 7.74E-06 2.78E-OS CD SS NO DATA 1 80E-06 S .51 E-0 6 No cafA NC Cata CO to no Data No cafa 1.0SE-03 S.29F-06 1. 56 E -0 5 NO Data NO DafA NO CATA 2.93E-01 98 63 S.38E-C4 2.88F-OS 1. 8 s E-0 5 NO Cafa N0 Data No CATA 1.94E-06 4: 6S 2.22E-06 2.09F-07 1.22E-07 No DATA NO DATA NO DATA 2.56E-05 Cu 64 no DAfa 2.4SE-07 1. 4 8 E-0 7 NO 04f4 S.92E-07 NO cafA t.15E-05 2N 65 1.37E-05 3.=SE-03 2.27E-05 No Cafa 2.30E-05 Nn DATA 6.4tE-06 IN 69 4.38E-08 6.43E-08 S. 8 S E -0 9 NO Cafa 3.84E-08 NO CATA 3.99E-06 54 SJ NO Data NO cafA 1.7tE-07 NO DAfa 40 04fa NO CafA LT E-24 sa 84 NO DATA NO CATA 1.996-07 NO CATA NO DafA NO CATA LT E-24 RR 85 k0 DAfa No cafa 9.12E-09 NO Cata NC cafa No CAfa LT E-24 Rt 86 NO DATA 6.70E-05 4.12E-05 NO DATA NO DATA NO 0474 NO 0a74 4.31F-06 at 88 1.90E-07 1.32E-07 NO Data 40 Dafa No Data 9.32E-09 85 89 NO 04fa 1.17E-07 1.04E-07 NO Data NO Data NO Cafa 1.02E-09 SR 89 1.32E-03 MU cafa 3. 7 7E-0 5 40 cafa 40 DarA NO Data S.11E-CS SR 90 1.70E-02 No pafa 4.3 t f -0 3 f40 Data No 04eA No cafa 2 29E-G4 SA 91 2.40E-05 No Data 9. 06E-0 7 N0 Data NO caf& NO Data S.30E-05 SR 92 9.03E-C6 N0 cafa

3. 62 E-0 7 NO Data NO DATA No 04f4 1.71E-04 Y 90 4.11E*08 NO Data 1.10 E -0 9 NO DATA NO Data NO Data 1.17E-04 Y 9tM 3.82E-10 No tafa 1.31E-11 ho caTA wo DATA wn Cafa 7.48E-CT Y 91 6.02E-07 he D4fA 1.6 t F-0 8 me DafA 40 Data 40 caTA 8.02E-c5 Y 92 3.60E-09 wo r,ata 1.O sE-t o no oaTA wo DAra no Cara t.04E-04

Reference 3, Table E-13.

0D04, H8tch REV.1 2.0-41 2877W/0152w, 05/11/84 i

..m. . . . , . . .. - - - -

?l l l

TABLE 2.2-6 CONT'D INGESTION DOSE FACTORS FOR CHILD *

(MEM PER PCI INGESTED)

Page 2 of 3 seuCLIDE 00mE LI984 7.800t feeveal0 RIShE9 LussG GI-tLI 9 93 1.14E-08 fee DATA 3.13C-10 800 DATA age OAfa 800 DATA 1.70E-04 2R 95 1.16E-07 2.3SE-08 2.27E-08 NO DATA 3.6SE-08 8eo OATA AR 97 6.99E-09 1.01E-09 b.96E-10 8ee Data 2.64E-OS 1.4SE-09 h6 OATA t.53E-04 48 95 2 2SE-08 8.76E-09 6.26E-99 800 OATA 8.23E-09 8e6 OATA see 99 800 OAT A 1.33E-05 3.29E-06 peo 047A 1.62E-OS 2.84E-05 sec 04Ya 1.IOE-05

TC 998 9.23E-10 1.8tE-09 3.00E-08 anc DATA 2.63E-08 9.19E-10 1 03E-06 FC101 1.07E-09 1.12E-09 1.42E-08 peo DATA SWIO) 7.31E-07 40 DATA 1.91E-08 S.92E-10 3 56E-09

2. 81 E-0 7 800 Def A 1.84E-06 soo DATA 1.89E-05 autos 6.4SE-08 800 ca f 4 2.34E-08 8eo DATA S.67E-07 eso Data 4.21E-05 20106 1 17E-05 880 DAT A 1 46E-0 6 esc OATA 1.58E-95 800 Daf A 1.42E-04 AG110M S.39E-07 3.64C-07 2.91 E-0 7 8en DATA 6.78E-C7 NO DATA 4 33E-OS TE12SM 1.14E-05 3.09E-06 1. 52 E-06 3.20E-06 800 DATA NO DATA 1.108-0S TE127M 2.49E-05 7.78E-06 3.4AE-06 6.9tE-06 E.24E-05 ho CATA 2.34E-05 TE127 4.71E-07 1.27F=07 . l . 01 E-0 7 3.26E-07 1.344-06 sen DATA 1 84E-05 FE129" 4.87E-05 1.36E-05 7. Set-06

1.57E-45 1.43E-04 No cara S.94E-05 TE129 1.34E-07 3.74E-08 3.18E-08 9. 56E-3 8 3.92E-0.7 see DATA 8.34E-06 TE13tm 7.20E-06 2.49E-06 2.6SE-06 S.12E-06 2.41E-OS neo CafA 1.01E-04 TE131 8.30E-08 2.53E-08 2.47E-08 6.3SE-00 2.51E-07 800 DAT A 4.36E-07 TE132 1.01E-CS 4.47E-Oe S . 40E-0 6 6.Sif-06 4.tSE-05 seo DATA 4.50E-OS I 130 2.921-06 S.90E-06 3. 04 E-0 6 6.SOE-04 8.82i-06 880 D AT A -2.76E-06 1 1.31 1.72E-05 1.73C-05 9. 8 JE-0 6 S.72E-03 2.84E-el se0 DATA 1.S4E-06 I 132 8.00E-07 1.47E-06 e.76E-07 6.82E-05 2.2SE-66 mn CATA 1.73E-06 I 133 S.92E-06 7.32E-06 2.77E-06 1 36E-03 1.22E-05 NO DATA 2.95E-06 I 134 4.19E-07 7.78E-07 3.S S E-0 7 1.79E-05 1.19E-06 kn Dafn 5.16E-07 I 135 1.7SE-06 3.1SE-Oe 1.49E-06 2.79E-04 4.83E-06 40 DATA 2.40E-06 CS134 2.34E-04 3.84C-04 8.10E-05 se0 DATA 1.19E-04 4.27E-05 2.07E-06 CS136 2.3SE-05 6.46E-05 4.18E-0 5 N0 DATA 3.44E-os S.13E-06 2.27E-06 CSI17 3.27E-04 3.13E-04 4.62E-OS 800 DAT A 1.02E-C4 3.67E-05 1.96E-06 cst 3s 2.20E-07 3. 4 7E-07 2. 0 t t-0 7 8e0 DafA 2.23E-07 2.40E-et 1.46E-07 san 39 4.14E-07 2.21E-te 1.20E-Os ese DafA 1.93e-se 1.30E-10 2.39E-05 4

4 00CM, Hatch REY.1 2.0-42 2871W/0152W, 05/11/84

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

?

TABLE 2.2-6 CONT'D INGESTION DOSE FACTORS FDR CHILD *

( M EM PER PCI INGESTED)

Page 3 of 3 WWCLlut 809t LIVE t - f.e infacto stehEv Lipsc gg-(tg sA140 e.J1E-OS 7.2SE-08 4.45E-06 8ec Data 2.37t-ce 4.34E-08 4 21E-05 l Sat 41 2 00E-07 1 122-10 6.SI E-0 9 - 8e0 Data 9.e9E-11 4.50E-10 1.14E-07 !

Sat 42 8.F4E-00 6 29E-11 4.88E-09 90 OATA 5.09E-Il 3.70E-11 1 14E-09 Lat40 1 01E-08 3.S'3E-09 1.11E-0 9 .-40 D A T A NC DAf4 8e0 Daf A 9 84E-05 Lat42 S.74E-10 1.67f-10 S.235-11 NO Data ha Oaft 800 D At a 3.31E-05 CE141 3.97E-08 I.98C-05 2.94E-09 ho OATA 8.68E-09 20 O&fA 2.4TE-05 CE14J 6 99C-09 3.79E-04 5.49E-t o soo cafa 1.59E-09 NO D&fA S.55C-05 CE144 2 00E-C6 6 52E-07 1. I I E-0 7 ho Cafa 3.686-07 NO DATA t.70E-04 Petel 3 93E-08 1.tet-03 1. 95 E-0 9 90 04f4 6.196-09 ho DATA 4 24E-05 Pel44 1.29E-10 1.91E-11 4.49E-12 90 Data 2.itE-!! NO DATA 8.59E-Og se014 7 2.79E-0A 2.26E-08 1 75E-09 No Data 1 24E-08 90 DATA 3.58E-05 m ter 4 2 9E-0 7 2.ser-07 1.1.E O r No cara No esta ho cafa 3.57E-Os we239 s.2SE-09 3.77E-to 2.6>t-10 en oaTA 1 09E-09 =0 nafA 2.r9E-Os J

l 2

ODCM, Hatch REY.1 2.0-43 2877W/0152W, 05/11/84

E

-a L

E E

I E

, TABLE 2.2-7 INGESTION DOSE FACTORS FOR TEENAGER *

(MREM PER PCI INGESTED)

Page 1 Of 3 r

=

NuCLICE SONE LIVf4 f.enET TNYactO EtDNEY LUNG C1-LLI if 3 b0 DATA 1.06E-07 . 1.coE-0 7 1.06E-07 1.06E-07 1.06E-07 1.06E-07 k C 14 4.06E-06 8.12E-07 8 12 E-0 7 8 12F-07 0.12E-07 8.12E-07 8 12F-07 '

44 24 2.30E-06 2.30E-06 2.30E-0.- 6 2.30E-06 2.30t-06 2.10E-06 2.30E-06 P 32 2.76E-04 1.71E-05 1. 0 TE-0 5 NO DATA NO 04TA No DATA 2.32E-05

$s Ca $1 Nu DATA NO Data 3 60E-0 9 2.00E-09 7.89t-10 5 14E-09 6.05E-07 PN 54 NO DATA 5.10E-Ce 1.17E-06 NG Data 1.76E-06 No caTA 1.21E-05

"!E NN 56 NO DATA 1. TIE-07 2.Alf-08 NO DATA 2.00E-07 NO DAfa 1,04E-05

(( Ff 53 3.18E-06 2.68F-06 6 2SE-0 7 No DATA NC CATA 1.70E-06 1 16E-06 g- FE 19 5.87E-06 1.JFE-05 5.29E-06 No DATA NO 04TA 4.32E-06 3.24E-05

., CO 58 N0 DATA 9.72E-07 2.24 E-06 No DATA NO DATA No Data 1.34E-05 lL CD 60 NO DATA 2.CIE=06 6.13 E-0 6 NO DATA NO DATA NO DATA 3.66E-05 NI 4 A 1.77E-04 1.25E-05 e. 00E-0 6 90 CATA NO DATA NO DATA 1.99E-06 gt 65 7.49E-07 9.S7E-03 4.36E-Os NO DATA 40 DATA NO DATA 5.19E-06 I Cu 64 No Data 1.15E-07 5.41 E-O s No DATA 2.9tE-07 NO DATA 8.92E-06 2N 6S 5.76E-06 7.00E-C5 9. 3 3E-0 6 NO 04T4 1.2SE-05 No DATA 8.47E-06 (N 69 1.47E-08 2.60E-08 1.96E-0 9 NU OATA 1.81E=0B NO DATA 5.16E-08

-- 99 43 NO DATA NO 04TA S.74E-os No DATA NO DATA NO DATA LT E-24 P SR 84 NO DATA NO DATA 7.22E-Os 40 DAfa NC CATA NO Cata L7 E-74 e

64 8% NO DATA 40 DATA 3. 05 E-09 NO OATA NO DAfa NO DATA LT E-24 2

at 86 NO CATA 2.18E-05 1 40E-0 5 NO DATA NO DATA NO CATA 4.4tE-06 hb 48 88 NO CaTA S.52E-08 4.54E-03 NO DATA NO DATA NO Data 7.30E-15 H

~

48 89 No DATA 5.50E-08 J . 89 E-0 8 NO caTA No 04TA NO CAfa 8.43E-17 SR 87 4.40E-04 NO DATA 1. 26 E-0 5 NO DATA NO DATA NO DATA S.24E-05

$ *. 9 0 E.30E-03 NO 04TA 2 0$E-03 NO DATA No DATA No DATA 2.31E-04 SR il 0.076-06 NO DATA 3.21 E-0 7 90 DaT4 NO DATA No CATA 3.66E-05 NF Sa 92 3.0$E-06 NO C&T4 1. 30E-0 7 40 DATA NO DATA NO DATA 7.77E-05 Y 90 1.37E-08 N0 CATA 3. 61E-10 NO CaTA NO D&TA NO DATA 1.13E-04 p Y 91P t.29E-to NO CaTA 4.93E-12 NO DATA NO DATA NO DATA 6 09E-09 Y 91 2.01E-07 NO DATA 5. 39E-09 N0 DATA NO DATA mn DATA 8.24E-05 l T 92 1 21E-09 N0 04TA 3.50E-11 NO DATA N0 DATA NO DATA 3 32E-05

[ .

E_r

=

+

L r :

Reference 3, Table E-12.

=

ODCM, Hatch REV.1 2.0-44 2871W/0152W, 05/11/84 hb i

4 TABLE 2.2-7 CONT'D INGESTION DOSE FACTORS FOR TEENAGER *

(MEM PER PCI INGESTED)

Page 2 of 3 NUCL13E COME LifEa T.8007 TNya010 K10NEY LUNG C1-tLI T 93 3.83E-09 90 DATA 1.05E-10 NO DATA se0 CATA NG DATA 1 17E-04 24 95 4.12E-08 1.30C-08 8. 9* E-0 9 NO DATA 1.91E-08 NO CATA 3.00E-05 Em 97 2.37E-09 4.e9E-10 2.16E-10 40 DATA 7.11E=10 NO DATA 1.27E-04 NS 95 8.22E-09 4.56!-09 2.51E-09 880 D AT A 4.42E-09 N0 DATA 1.95E-05 se0 99 40 DATA 6.03C-06 1.15F-06 NO DATA 1.38E-05 NO DATA 1.08E-05 TC 99N 3.12E-10 9.26E-10 1.20E-08 NO 04fA 1.18E-08 5.14E-10 6.08E-07 TC101 3.60E-10 5.125-10 5. 01 E-0 9 sen Data 9 26E-09 3.12E-10 8.75E-17 Sut03 2.55E-07 NO DATA 1. 09E-0 7 NO 04iA 8.99E-07 mn 04fA 2.13E-05 aU105 2 18E-04 NO UATA 8.4 6 E-0 9 40 OATA 2.75E-07 NO DATA 1.76E-05 av106 3.12E-06 40 CATA 4. 94 E -0 7 40 DATA 7.56E-06 NO DATA 1.88E-04 AG110* 2.05E-07 1.94E-07 1.laE-07 90 DATA 3.70E-07 NO DATA 5.45E-05 TE125m 3.83E-06 1.384-06 5.12E-07 1.0fE-06 40 Data NO DATA 1.13E-05 TE127N 9.67E-06 3.4sE-06 1.15 E-0 6 2.30E-06 1.92k-05 NO DATA 2.41E-05 1E127 1.58E-07 5.6CE-08 3.40 E-0 8 1. 09E-0 7 6.40E-07 NO 047a 1.22E-05 TE129N 1.63E-05 6.C5F-06 2.58E-06 5.26E-06 6.42E-05 Nn DATA 6.12E-05 TE129 4.48E-08 1.67E-08 1.01E-08 3.20E-08 1.88E-07 NO DATA 2.45F-07 TE131m 2.44E-06 1.!TC-06 9. 76 E-0 7 1.76E-06 1 22E-05 NU OATA 9.39E-05 TE131 2.79E-08 1.15E-08 8.72E-08 2.15E-08 1.22E-07 NO DATA 2.29C-09 TE132 3.4 9 E-06 2.21E-06 2.0EE-06 2.33E-06 2.12E-05 NO DATA 7.00E-05 1 130 1.03E-06 2.984-06 1.19E-0 6 2.41E-04 4.59E-06 NO 047a 2 29E-06 1 131 5.85E-06 8.11C-06 4.40E-06 2.39E-03 1.41E-05 NO DAT4 1.62E-06 1 132 2.79E-07 7.30E-07 2. 62 E-0 7 2.4eE-05 1 15E-06 NO DATA 3.18E-07 1 133 2.01E-06 3.41E-06 1. 04 E-0 6 4.76E-04 5.98E-06 NO DATA 2.58E-06 1 134 1.46E-07 3.87E-07 1.39E-0 7 6.45E-06 6 10E-07 NO Cata 5. '. 0 E-0, 1 135 6.10E-07 1.57E-06 5. 82 E-0 7 1.01E-04 2.48E-06 NO DATA 1.74E-06 C5134 8.37E-05 1.97E-04 9.14 E-0 5 NO DATA 6 26E-05 2.39E-05 2.45E-06 C5136 8.59E-06 3.38E-OS 2.27E-05 NO DATA 1.84E-05 2.90E-06 2.72E-06 C5137 1.12E-04 1.49E-04 5.19E-0 5 NO DATA 5.07E-05 1.9fE-c5 2.12E-06 C5138 7.76E-08 1.49E-07 7.45E-08 NO 04fA 1.10E-07 1.28E-08 6.76E-11 84139 1.39E-07 9.78E-11 4 0bE-09 sto DATA 9.22E-11 6.74E-11 1.24E-06 ODCM, H8tch REV.1 2.0-45 287N/0152W, 05/11/84

y m

, TABLE 2.2-7 CONT'D INGESTION DOSE FACTORS FOR TEENAER*

(M PER PCI INGESTED)

Page 3 of 3 1

wCurt some uvEn f.e00f twee010 a10=Ev Lwas st-tt:

a4140 2.ser-03 3.4at-Os 1. a st-06 w OATA 1. lee-Os 2.34E-Os 4. set-05 0A141 6.71E-08 5.01E-11 2.24E-09 90 O&fa 4.65E-11 3.43E-11 1.43E-13 84142 2.99E-04 2.99E-11 1.44E-09 10 DATA 2.53t-11 1.99E-11 9.18E-20 LA140 3.48E-09 1.71C-09 4. 5 5E-10 880 OATA WC OATA h6 OATA 9.82E-05 LA142 1.79E-10 7.95E-11 1.98E-11 90 DATA NO DATA he OATA 2.42E-06 CE141 1.33E-00 0.88E-09 1. 02E-0 9 see OATA 4.10E-09 h0 CATA 2.54E-05 CE143 2.35E-09 1.71E-06 1.91E-10 40 CATA F.67E-10 as0 OATA 5 14E-05 !

CE144 6.96E-07 2. set-07 3 74E-08 =0 DATA 1.72F-07 aso 04f4 1.75F-04 l Petes 1.31E-08 5.23C-09 4.52E-10 40 Data 3.64E-09 esc OATA 4.31E-05 P9144 4.3CE-11 1.762-11 2.18 E-12 NO DATA 1.01E-11 aso DATA 4.74E-14 90147 9.18C-09 1.02F-04 6.11E-10 NO Data 5.99E-09 Nn 04fA 3.68E-05 h 187 1.46E-07 1.19E-07 4 1FE-Os eso DATA. 880 DATA aso DATA 3.22E-05 seP239 1 7M-09 1.6 M-10 9.22E-11 see DATA S.21C-10 8se OATA 2.47E-05 l

l

[

h.

l l.

l l

l l 0004, Hatch REV.1 2.0-46 287M/0152W, 05/11/84 t

' - -. . . - . - . . - - . . , - - . - - - - - . . . - - - - - - - - - ~ ~ - - . < - ~ ~ ~ ~ - , ~ . - - - - - - - ~ ~ - - ~ ~ ~ - - - - - ~ ~ ~ - ~ '

m __

13 6

5

=

TABLE 2.2-8 INGESTION DOSE FACTORS FOR ADULTS

DR2M PER PCI INGESTED)

{

Page 1 Of 3 s

b

[

, NUCLICE SONE tivER T.40CY THYROIO RIONEY LUNG GI-LLI H 3 NO DATA 1.35E-0? t . 05 E-0 7 1.05E-07 1.05E-07 1.05E-07 1.05E-07 C 14 2.84E-06 5.68E-07 5.6 8 E-0 7 5.68E-47 5.68E-07 5.68f-07 5.68E-07 k NA 24 1.70E-06 1.70E-06 1.70E-06 1.f0E-06 1.70E-04 1.70E-06 1.70E-04 k

P 32 1.9JE-04 1.20E-05 7. 46E-0 6 40 DATA kC CATA NO DATA 2.17E-05 CR 51 No DATA 40 DATA 2. 6*E-0 9 1.59E-49 5.86E-10 3.51E-09 6.69E-07 NN 54 40 DATA 6.575-C6 8.72 E-0 7 NO DATA 1.36E-C6 NO DATA 1.40E-05 1 - - - - --

[ NN 56 NO DATA 1.15E-07 2 04E-08 NO DATA 1 46E-07 NO DATA 3.67E-06 e ~

rt 55 2.75E-06 1.90F-06 4.4 AE-0 7 NO DATA No DATA 1.06E-06 1.09E-06 FE 59 4.34E-C6 1.02E-05 3. 9 t E-0 6 40 DATA No DATA 2.85E-06 3.40E-05 CO 58 NO DATA 7.456-07 1.67 E-0 6 40 DATA NO DATA NO DATA 1.51E-05 L CO 60 NO DATA 2.14F-06 4.72E-06 No DATA NO DATA NO DATA 4.02E-05 7 NI 63 1.30E-04 9.01E-On 4. 3 6 E-0 6 NO Cata 40 DATA NO DATA 1.88E-06 NI 45 5.28E 'T 6.86E-08 3 13E-08 40 DATA NO DATA NO DATA 1.74E-06 L CU 64 NO DATA 8.335-08 3.9tE-08 NO DATA 2.10E-07 NO DATA 7.10E-06 -

[ ZN 65 4.84E-06 1.545-05 e.9eE-06 No DATA 1.03E-05 NO DATA 9.70E-06 IN 69 '1.03E-08 1.97E-08 1. 37 E-0 9 No DATA 1.28E-08 No cafa 2.96E-09 84 83 NO DATA NO DATA 4. 0 2 E-0 8 40 DATA NO DATA No CATA 5.79E-08 .

SR 84 5.21E-08 NO DATA NO DATA NO DATA NU OATA NO DafA 4.09E-13

84 85 NO DATA NO DATA 2.14 E-0 9 NO DATA NO DATA NO DATA LT E-24

[ 45 86 No DATA 2.11E-05 9. 8 3 E-0 6 NO DATA NO DATA NO DATA 4 16E-06 NO DATA 48 SS 6.05E-08 1 21E-08 No DATA No CATA NO DATA 8.36E-19 0 48 89 NO DATA 6.01E-OS 2.82E-08 40 DATA NO CATA NO OdfA 2.33E-21 F SR 89 3.08E-04 NO DATA 8. 8 4 E-0 6 NO DATA NO DATA NO DATA 4.94E-05 '

, SR 90 7.58E-03 NO DATA 1. 8 6 E-0 3 NO CATA NO DATA NO DATA 2.19E-04 (E SR 91 5.67E-C6 NO DATA 2.29E-17 40 CATA NO DATA NO DATA 2.70E-05 SR 92 2.15E-06 NO. DATA 9.30E-08 NO DATA NO DATA NO DATA 4.26E-05 Y 90 9.62E-09 N0 DATA 2.58E-10 40 QATA 40 DATA NO DATA 1.02E-04

, Y 9tN 9.09E-11 No Cafa 3.52E-12 NO DATA NO DATA NO DATA 2.67E-10 Y 91 1.4tE-02 NO DATA 3. 77 E-09 NO DATA NO DATA No CATA 7.76E-05 v 92 2.47E-1 3 8.45E-to No CATA NO DATA NO DATA NO DATA 1.68E-05 w

5 c

Reference 3, Table E-Il.

i I 0D04,. Hatch REV.1 2.0-47 p 2877W/0152W, 05/11/84

=

b ..

___m_25 TABLE 2.2-8 CONT'D INGESTION DOSE FACTORS FOR ADULTS *

(MREM PER PCI INGESTED)

Page 2 of 3 NUCLICE DONE liver 7.800Y TNv90!C EIONEY LUNG GI-LLI Y 93 2.68E-C9 NO DATA 7.40E-11 NO DATA NO DATA NO DATA S.50E-05 ZR 95 3.04E-08 9.75E-C9 6.60E-0 9 No DATA 1.53E-05 No DATA 3.09E-05 ZA 97 1.44E-09 1.392-10 1 55E-10 NO DATA 5 12E-10 NO DATA 1.05E-04 NS 95 6.22E-09 3.46E-09 1. 86 E-0 9 NO DATA 3.42E-C9 No DATA 2.10E-05 NO 99 NO DATA 4 31E-06 8.20E -07 NO DATA 9.!&E-04 NO DATA 9.99E-06 7C 99M 2.47E-10 6.98E-10 8. 8 9 E-09 No DATA 1.06E-08 3.42E-10 4 13E-07 TC101 2.54E-10 3.66E-10 3. 59 E-0 9 40 CATA 6.59E-09 1.87E-10 1.10E-21 4U103 1.85E-07 NO DATA 7.9fE-08 No CATA 7.06E-C7 NO CATA 2.16E-05 2u105 1.54E-08 NU DATA 4. 08 E -09 MO DATA 1 99E-07 NO DATA 9.42E-06 20106 2.75E-04 40 DATA 3. 4 8 E-0 7 NO DATA 5.31E-06 No DATA. 1.78E-04 AG110m 1.60E-07 1.48E-07 8.79E-08 40 CATA 2.9tE-07 NO DATA 6.04E-05 TE125M 2.6SE-06 9.71E-07 3. 59 E-0 7 8.06E-07 1.09E-05 NO DATA 1.07E-05 TE127* 6.77E-06 2.42E-06 8.25 E-0 7 1.73E-06 2.75E-05 NO DATA 2.27E-C5 TE127 1.10E-OF 3.95E-08 2.38E-08 8.15E-08 4.48E-07 NO DATA 8.68E-06 TE129" 1.15E-05 4 298-06 1. 82 E-0 6 3.95E-06 4.80E-05 NO DATA 5.79E-05 TE129 3.34E-08 1.18E-08 7. 6SE-0 9 2.41E-08 1.32E-07 NO DATA 2.37E-08 7E131M 1.73E-06 8.465-07 7.05E-0 7 1.34E-06 8.57E-06 NO DATA 8.40E-05 TE131 1.97E-08 8.232-C9 6. 22 E-0 9 1.42E-08 8.63E-08 NO DATA 2.79E-C9 TE132 2.52E-06 1 63E-06 1. 5'J E-0 6 1.80E-06 1.57E-05 NO DATA 7.71E-05 1 130 7.56E-07 2.23E-06 8. 80E-0 7 1.89E-C4 3.40E-06 NO DATA 1.92E-06 I 131 4.16E-C6 5.95E-06 3. 41 E-0 6 1.95E-03 1.02E-OS NO DATA 1.57E-06 I 132 2.03E-07 5.43E-07 1. 90E-0 7 1.90E-05 8.65L-07 NO DATA 1.02E-07 8 133 1.42E-06 2.4TE-06 7.5 3 E-0 7 3.63E-04 4.31E-06 No DATA 2.22E-06

=

I 134 1 06E-07 2.88E-07 1 03E-0 7 4.99E-06 4.58E-07 NO CATA 2.51E-10 1 135 4.43E-07 1.16E-06 4. 2 8E-0 7 7.65E-05 1.86E-C6 NO CATA 1.31E-06 C5134 6.22E-05 1.48E-04 1. 21 E-0 4 No DATA 4.79E-05 1.59E-05 2.59E-06 C5136 6.51E-06 2.57E-05 1. 85 E-0 5 40 DATA 1.43E-05 1.96E-06 2.92E-06 C5137 7.97E-05 1.09E-04 7.14 E-0 5 40 DATA 3.70E-05 1.23E-05 2.11E-06 C5138 5 52E-08 1.C9E-07 5.40E-0 8 NO DATA 8.01E-08 7 11E-09 4.65E-13 sat 39 9.70E-08 6.91E-11 2. 84E-0 9 NO DATA 6.46E-11 3.42E-11 1.72E-07 ODm , Hatch REV.1 2.0-48 287M/0152W, 05/11/84

..A 9

TABLE 2.2-8 CONT'D INGESTION DOSE FACTORS FOR ADULTS *

(MtEM PER PCI INGESTED)

Page 3 of 3 8euCLICE SONE Livfa T.40er TNya080 AIO4EY LUNG CI-LLI sat 40 2.03E-05 2.55E-08 1.3AE-06 40 DATA 54141 4.71E-08 1.h6E-11 1 59E-0 9 40 DATA S.6ft-09 1.46E-08 4 18E-05 44142 2.13E-08 2.19E-11 1.34E-09 No DATA 3.3tE-It 1.8SE-11 2.02E-11 2 22E-17 1.24E-II -

1.00E-26 LAl40 2.SOE-09 1.263-09 J.3JE-10 40 DATA NO Data 40 DATA LA142 1.28E-10 5.82E-11 1.45E-11 NO DATA 9.25E-05 NC OATA as0 OATA 4.2SE-07 CE141 9.3tE-09 6.J3E-09 F.18E-10 40 OATA 2.94E-09 NO DATA 2.42E-05 CE143 1.4SE-09 1.22E-06 1.3SE-10 No DATA 5. 37E-10 NO DATA 4.56E-05 CE144 4.40E-07 2. 04E-0 T 2.62E-08 NO DATA 1.21E-07 NO DATA 1.65E-04 j

P4143 9.20E-09 3.69E-09 4.56E-10 40 DATA 2.13E-09 90 DATA 4.03E-05 Pt144 3.01E-!! 1.25E-11 1. S et-12 40 DATA 7.05E-12 NG DATA 40147 6.29E-09 7.27E-09 4.33E-ta

4. 35E-10 No DA TA 4.25E-0, n0 e DATA 3.49E-05 h 11F 1.03E-07 8.6tE-08 3.01E-08 90 DATA NO CATA NO DATA 2.82E-05 NF239 1.19E-09 1.1TC-10 4.45E-It see OATA 3.6SE-10 NO DATA 2.40E-05 I

l l

i j

l l

l 00CM, Hatch REY.1 2.0-49

[ 287M/0152W, 05/11/84 l

\

,, , _ _ . . . - . _ _ _ . . ..,- - - - - - - - - - - -------- - -- -~~~~~~~"~~'~~~ " ~ " ~ ~~~ ' ~ ~'~ ~ ~ ~ ~ ~

. - -. b TABLE 2.2-9 EXTERNAL DOSE FACTORS FOR STAPOING ON CONTAMINATED GROUND *

(mrem /hr per pci/m2 )

l ELEMENT TOTAL BODY SKIN 1

H-3 0.0 0.0 j 0.0 0.0 C-14 NA-24 2.5E-08 2.90E-08 P-32 0.0 0.0 Cr-51 2.2E-10 2.60E-10 Mn-54 5.8E-09 6.80E-09 Mn-56 1.1E-08 1.30E-08 Fe-55 0.0 0.0 Fe-59 8.0E-09 9.4E-09 Co-58 7.0E-09 8.20E-09 Co-60 1.7E-08 2.00E-08 Ni-63 0.0 0.0 Ni-65 3.7E-09 4.30E-09 Cu-64 1.5E-09 1.7E-09 Zn-65 4.00E-09 4.6E-09 Zn-69 0.0 0.0 Br-83 6.4E-11 9.30E-11 Br-84 1.2E-08 1.4E-08 Br-85 0.0 0.0 Rb-86 6.3E-10 7.2E-10 Rb-88 3.5E-09 4.0E-09 Rb-89 1.50E-08 1.80E-08 Sr-89. 5.6E-13 6.5E-13 Sr-91 7.1 E-09 8.3E-09 Sr-92 9.0E-09 , 1.00E-08 Y-90 2.20E-12 2.60E-12 Y-91M 3.8E-09 4.4E-09 Y-91 2.4E-11 2.70E-11 Y-92 1.6E-09 1.90E-09 Y-93 5.70E-10 7.80E-10 Zr-95 5.0T-09 5.80E-09 Zr-97 5.50E-09 6.4E-09 Nb-95 5.1E-09 6.00E-09 Mo-99 1.9T-09 2.20E-09 Tc-99M 9.6E-10 1.1 E-09 Tc-101 2.70E-09 3.00E-09 Ru-103 3.6T-09 4.20E-09 Ru-105 4.50E-09 5.1E-09 Ru-106 1.5E-09 1.80E-09 Ag-110M 1.80E-08 2.10E-08 Te-125M 3.5E-11 4.80E-11 Te-127M. 1.10E-12 1.30E-12 Te-127 1.00E-11 1.10E-11 Te-129M 7.70E-10 9.00E-10 Te-129 7.1T-10 8.40E-10

Reference 3, Table E-6 0004, Hatch REY.-1 2.0-50 2877W/0152W, 05/11/84

'. 3_

TABLE 2.2-9 (Continued)

ELEMENT TOTAL BODY SKIN Te-131M 8.4E-09 9.90E-09 Te-131 2.2E-09 2.60E-06 Te-132 1.70E-09 2.00E-09 I-130 1.4T-08 1.70E-03 I-131 2.8E-09 3.40E-09 I-132 1.7E-08 2.0E-08 I-133 3.7E-09 4.50E-09 I-134 1.6E-08 1.9E-08 I-135 1.20E-08 1.40E-08 Cs-134 1.2E-08 1.40E-08 Cs-136 1.50E-08 1.7E-08 Cs-137 4.2E-09 4.9E-09 Cs-138 2.1E-08 2.40E-08 Ba-139 2.4E-09 2.7E-09 Ba-140 2.1E-09 2.40E-09

-Ba-141 - 4.3E-09 4.90E-09 Ba-142 7.90E-09 9.00E-09 La-140 1.5E-08 1.7E-08 La-142 1.5E-08 1.80E-08 Ce-141 5.5E-10 6.20E-10 Ce-143 2.2E-09 2.5E-09 Ce-144 3.2E-10 . 3.7 E-10 Pr-143 0.0 0.0 Pr-144 2.00E-10 2.30E-10 Nd-147 1.00E-09 1.20E-09 W-187 3.1E-09 3.60E-09 Np-239 9.5E-10 1.10E-09 l

I t

0004, Hatch REV.1 2.0-51 2877W/0152W, 05/11/84

Ml l

TABLE 2.2-10 I!OIVIDUAL USAGE FACTORS

IWANT CHILD TEENAGER ADULT

, Milk Consumption Rate, Uap (liters / year)' 330 330 400 310 Meat Constaption Rate, U,p (kg/ year) 0 41 65 110 Fresh Leafy Vegetation Consumption Rate, ua g (kg/ year) 0 26 42 64 Stored Vegetation Constaption Rate, Uas (kg/ year) 0 520 630 520 Brqathing Rate (m'/ year) 1400 3700 8000 8000

Refe:ence 3, Table E-5.

l l

0004, Hatch REV.1 2.0-52 2877W/0152W, 05/11/84 I

Y TABLE 2.2-11 STABLE ELEENT TRANSFER OATA*

ELENENT F MILK F - MILK Fr - MEAT m (COW) m(GOAT) l H 1.E-02 1.7E-01 1.2E-02 C 1.2E-02 1.E-01 3.1E-02 Na 4.E-02 4. E-02 3.K-02 1 P 2.5E-02 2.5E-01 4.6E-02 Cr 2.2E-03 2.2E-03 2.4E-03 Mn 2.5E-04 2.5E-04 8. E-04 Fe 1.2E-03 1.3E-04 4.0E-02 Co 1. E-03 1.E-03 1.X-02 Ni 6.7E-03 6.7E-03 5. X-02 Cu 1.4E-02 1. X-02 8.0E-03 Zn 3.9E-02 3.9E-02 3. E-02 Rb 3.E-02 3.E-02 3.1E-02 Sr 8. E-04 1.4E-02 6.0E-04 Y. 1.E-05 1.T-05 4.6E-03 Zr 5.0E-06 5.0E-06 3.4E-02

Nb 2.5E-03 2.5E-03 2.8E-01 4 Mo 7.5E-03 7.5E-03 8. E-03 Tc 2.5E-02 2.5E-02 4.E-01 Ru 1.E-06 1.E-06 4.0E-01 Rh 1.E-02 1. E-02 1.5E-03 Ag 5. E-02 5.0E-02 1.7E-0z Te 1.T-03 1. E-03 7.7E-02 I 6.0E-03 6. E-02 2.9E-03 Cs 1.2E-02 3.T-01 4.0E-03 -

Ba 4.0E-04 4.0E-04 3.2E-03 La 5.E-06 5.T-06 2.E-04 Ce 1.0E-04 1.E 04 1.2E-03 Pr 5.E-06 5.E-06 4.7E-03 Nd 5. E-06 5.E-06 3. X-03 W 5.E-04 5.T-04 1.3E-03 Np 5. E-06 5.0E-06 2.0E-04

References 3, Table E-1.

0004, Hatch REV.1 2.0-53 2877W/0152W, 05/11/84

131 TABLE 2.2-12 SITE-SPECIFIC (OR DEFAULT) VALUES TO BE USED IN PATHWAY FACTOR CALCULATIONS (Supports Section 2.2.2.b)

The critical receptor is an infant exposed to the inhalation, ground-plane, and grass-cow-milk pathways. 1 Parameter Description Value l

Inhalation l

, (BR)a Breathing rate for infant 1400 d / year l (DFA)ija Inhalation dose factor for Table 2.2-1 infant Ground plane SF' Shielding factor due to structure 0.7 (DFG)ij Ground plane dose factor Table 2.2-9 (Same for all age groups)

Grass-Cow-Milk Q- Feed consunption rate for cow 50 kg/ day Uap Milk consumption rate for infant 3301/yr (DFL)ija Ingestion dose factor for infant i Table 2.2-5 Yp Pasture grass areal density 0.7 kg/d Ys Stored feed areal density 2.0 kg/d fp Fraction of year that cow grazes on pasture 1.0 fs Fraction of total feed that is I pasture grass while cow is on l pasture 1.0 H Absolute hunidity of the atmosphere 8.0 gm/d l

l l

l i 0004, Hatch REV.1 2.0-54 l 2877W/0152W, 05/11/84 l

,es-eg--en ew---t wwsw3,+-vw,-:-----*---re- g y7, , wa-mey- w-y ++-g - y-p-e- -

-ww----+-*-pe+e-,- *- -- y

a .1 A

TABLE 2.2-13 SITE-SPECIFIC (OR DEFAULT) VALUES TO BE USED IN ADDITIONAL PATHWAY FACTOR CALCULATIONS (Supports Section 2.2.2.c) l Parameter Description Value Inhalation (BR)a Breathing rate for age group Table 2.2-10 (DFA)ija Inhalation dose factor for age group Tables 2.2 2.2-4 (arass-Cow-Meat Gp Feed consunption rate for cow 50 kg/ day Sp Meat consunption rate for age group Table 2.2-10 (DFL)ija Ingestion dose factor for age group Tables 2.2 2.2-8 Yp Pasture grass areal density 0.7 kg/m2 Y

s Stored feed areal density 2.0 kg/d fp . Fraction of year that cow grazes on pasture 1.0 fs Fraction of total feed that is pasture grass while cow is on pasture 1.0 -

H Absolute humidity of the 8.0 gm/m 3 atmosphere Garden Vegetation Yy Garden vegetation areal density 2.0 kg/d Ug Leafy vegetation consumption rate for age group Table 2.2-10 Uas Stored vegetation consunption rate for age group Table 2.2-10 fg Fraction of annual intake of leafy vegetation grown locally 1.0 fg Fraction of annual intake of stored vegetation grown locally 0.76 H Absolute humidity of the 8.0 gm/m3 atmosphere ODCM, Hatch REV.1 2.0-55 287M/0152W, 05/11/84

jg-l TABLE 2.2-13 (Continued) l Parameter Description Value Grass-Goat-Milk

$ Feed consum tion rate for goat 6.0 kg/ day Uap Milk consunption rate for age group Table 2.2-10 (DFL)ija Ingestion dose factor for age group Tables 2.2 2.2-8 Yp Pasture grass areal density 0.7 kg/m2 Y

s Stored feed areal density 2.0 kghf

'fp Fraction of year'that goat grazes on pasture 1.0 fs Fraction of total feed that is pasture grass while goat is on

pasture 1.0 H Absolute humidity of 8.0 gm/m 3 ,

the atmosphere I

e . . - .--

l l 0004, Hatch REV.1 2.0-56

2877W/0152W, 05/11/84

... a2i 2.3. METEGt0 LOGICAL MG)EL 2.3.1 ATMOSPERIC DISPERSION Atmospheric dispersion may be calculated using the appropriate form of the sector averaged Gaussian model. Gaseous releases are considered to be either elevated or at ground-level. Included in the ground-level . category are releases from the Reactor Building Vent (Unit 1), the Reactor Building Vent (Unit 2) and the Recombiner Building Vent (Unit 1). Releases from the main stack are considered to be elevated.

2.3.1.a Ground Level Releases X/Q = The sector-averaged annual average relative concentration at any distance in the given sector.

njk (sec 6 8)

= 2.032 6 K g I Nu jk

Z zk jk

. . where 2.032' = (2Ar )l/2 divided by the number 'of radians in a 22.5' sector

! .(3r/16).

l r-6 = Plume depletion factor for all radionuclides other than noble gases at a distance r shown in Figure 2.3-3. For noble gases the depletion factor is unity. Only depletion by deposition is considered since depletion by decay would be of little significance at the distances considered.

K = Terrain recirculation factor corresponding to a distance r taken from Figure 2.3-2.

n jk

= Number of hours the wind of wind speed class j is directed into the given sector during the time atmospheric stability category k existed. These values may be obtained from Table E.4-8 of Reference 5.

N = Total hours of valid meteorological data recorded for all sectors, wind speed classes, and stability categories from Table E.4-8 of Reference 5.

0004, Hatch REV.1 2.0-57 2877W/0152W, 05/11/84 .

.y f r = Distance from the point of release to the receptor location (meters).

, u jk

= Wind speed (mid-point of wind speed class j) at ground level (m secf1) during atmospheric stability k.

= The vertical standard deviation of the plume concentration kk distribution considering the initial dispersion within the building wake.

(a z2 + b2 /2 x)l/2

= The lesser of< or

('z) ok z

= The vertical standard deviation of the plume concentration distribution (meters) for a given distance and stability category k as shown in Figure 2.3-1. The stability category is determined by the vertical temperature gradient a TA z (oC/100m).

n = 3.1416 b = Maximum height of adjacent plant structure (47 meters).

2.3.1.b Elevated Releases X/Q = The sector-averaged annual average relative concentration at any distance in the given sector for radionuclides other than noble gases,

= 2.032 K I 6 n yexp (-tf /2 g2 )

k jk NUj r az k 6

k = The_ plume depletion factor taken from Figure 2.3-4. For an elevated release this factor is stability dependent.

h = Height of main stack (120 meters).

0D04, Hatch REY.1 2.0-58 2877W/0152W, 05/11/84

_. .. .______-_.m_ _ m

t l n = Number of hours the wind of wind speed class j is directed into the giver: sector during the time atmospheric stability category k existed. These values may be obtained from Table E.4-7 of Reference 5.

U p - = Wind speed (mid-point of wind speed class j) at the height of release h (m sec 1) during atmospheric stability k.

N = Total hours of v.alid meteorological data recorded for all sectors, wind speed classes, and stability categories from Table E.4-7 of Reference 5.

The remaining symbols are the same as those previously defined.

When considering the direct gamma radiation from an elevated finite plume the constants ' B and V defined in Section 2.1.2 for each identified noble gas y f radionuclide are calculated using the following:

~ .

O K bbb "jk ^ti N a 1 (r)ld. mrad /yr i " r j k 1, N Uj "'

pU1/sec bb "jk ^11 N a 1 (r)ld, V

f= 1.1' Krjki N U **P I- N TTd) mrem /yr pC1/sec

- J .,

K =A nunerical constant- representing the aggregai.ed numerical constants and unit conversions.

= 2.1 x 1(?

= The number of photons of energy corresponding to the Eth energy

$1 group emitted per transformation of radionuclide 1 (number / transformation).

p, = The energy absorption coefficient in air for photon energy Eg (meters-1).

0004, Hatch REV.1 2.0-59 2877W/0152W, 05/11/84

~

' ~

._. q M

E g = The energy assigned to energy group A (MeV).

pT = The tissue energy absorbtion coefficient for photons of energy Eg (cnf gnr 1 ).

T d

= The tissue density thickness taken to represent the total body dose (5 gm car ),

1.1 = An average ratio of the tissue to air absorbtion coefficients over the energy range of interest. The ratio converts dose (rad) to dose equivalent (rem).

I(7)g = The results of nunerical integration over the plume spatial distribution of airborne activity; this value is dependent on atmospheric stability, downwind distance and gamma energy.- ,

The above mentioned integral is used in representing the sunmation of the dose rates from all the points (the concentration within a differential volume element) of a distributed source (plume). For the sector-averaged Gaussian model the integral is given by:

1 2 1 2 1 (, Oc b ' " a ' (' +* } 3 G(*} **P ['" (' **) 3 ' dL d*

28 8 a g J, L2 +z 8 where B = Build-up factor.

g

= 1 - 4 (La + z2 )1/2 y = Total absorbtion coefficient for air (meters-1).

k = (p -y ,) 42,.

L = Horizontal distance from the receptor to the differential volume element.

ODO4, Hatch REV.1 2.0-60 2877W/0152W, 05/11/84

ij -

, z- = The vertical distance from the receptor to the differential volume element.

G(z) = A function relating the variation of radionuclide concentration with height for a given differential volume element.

= exp [- (z-h)8/2a 2] + exp [-(z+hF /2 a 2]

2r L dL dz = The differential volume element of the integral (the 2r is subsequently factored out of the integral leaving L dL dz).

A derivation of the model describing the gamma dose rate from a finite elevated pitme is found in Chapter 7 of Reference 10. NLaerical methods for evaluating the dose intggral are found in Appendix F of Reference 3 in the form of two computer code listings. The first listing performs the integration using a Gauss-Legendre quadrature; the other utilizes a Newton-Cotes formulation. Details of these two methods may be found in Reference 9.

2.3.2 RELATIVE DEPOSITION Relative deposition per unit area is given by:

D/Q = The sector averaged annual average deposition at any distance for a given sector.

2.55 K Dgk n

, p (nr2) k r N 2.55 = The inverse of the number of radians in a 22.50 sector (2r/16)- 8 K = Terrain recirculation factor described in previous section.

00CM, Hatch REV.1 2.0-61

2877W/0152W, 05/11/84

+ ----,---w, oms ~+-,w,vw,--w---erw-~,,w-,em-- --w--c-- ,,-w-e - , - - ~~m r,--,w-- w n-me-- r w e-.e*w,e -- an g m e, w e w <- -- r~-v

' ~

, 1:$

O = Deposition rate at a given distance taken from Figure 2.3-5 for g

gromd-level releases and Figure 2.3-6 for elevated releases.

nk = The nunber of hours the wind is directed into the sector of interest for. a ground-level release or for an elevated release during which time stabilty category k exists. These values may be found in Tables E.4-7 and E.4-8 of Reference 5.

N = The total hours of valid meteorological data.

ti l

l l

l ODCN, Hatch REV.1 2.0.-62 2877W/0152W, 05/11/84

2 .r FIGLRE 2.3-1 Vertical Standard Deviation of Material in a Plume (oZ )*

(Letters denote Pasquill Stability Class) l

/

l

/

s' .*

l l / /

f f f f

/ /'y ~ ~

/ '//

su . . . .

,'r, ,

s:

l ,~ "

l n ,

l / 7 / / .. . -~ ,

I / / / r// .

,,- ~~ s r

~

/// fif f g . -

// / ,/ , /

,/ / / / af /

r 7 ,f, . 7,

// / v ,

/ / A

'/ /

/,f

. /

% i, ,.

nums mves.osumu nuumsma

{

, Range of Vertical Range of Vertical Category Temperature Gradient (*C/100m) Tenperature Gradient (*F/100f t)

A AT/AZ < -1.9 AT < -1.0 B

-1.9 i AT/AZ < -1.7 -1.0 1 AT < -0.9 C -1.7 < AT/AZ < -1.5 ' 0.9 5 AT < -0.8 l

0 -1.5 < AT/AZ < -0.5 -

-0. 8 < AT . < -0. 3 l E -0.5 5 AT/AZ < 1.5 -0.3 $ AT < 0.8 .

.F 1.5 5 AT/AZ < 4.0 0.8 5 AT < 2.2 G 4.0 < AT/AZ 2.2 1 AT t

Misference 8 l ODCN, Hatch REY.1 2.0-63 l; . 2877W/0152W, 05/11/84 i

O FIGURE 2.3-2 Open Terrain Recirculation Factor *

,e 4

\

8

- N ,

I

- \s I.

a i.

E 8

u a.i -

e.1 1.s se vos DISTANCE (MIL 0 METERS) l i

i l

l Meference 7 l

l l

00CM, Hatch REV.1 2. M 287M/0152W, 05/11/84 l

. _ . - - - . . . . . , . ,_ __.,_-_-....~_,-___,,,,__...;_...,__,,,..._.-_,,__. _ , _ . _ . . . . . . . , _ _ - _ , _ , - . , , - _ -

+

FIGURE 2.3-3 Plume Depletion Effect for Ground-Level Releases 1 (All Atmospheric Stability Classes) u

~* =

u N

I" 's N 2 '

.y a2 h

\ \

Ies

= as N

N, I 8.4 N\

u e.:

8.1 1A 18A 10BA 388 4 0.1 PLURSE TRAVEL DeBTANCE (KILonIETEngl

Reference 8 ODO4, Hatch REV.1 2.0-65 1

287M/0152W, 05/11/84 i

L

. . . :4 FIGLRE 2.3-4 Plume Depletion Effect for Greater Than 100-m Releases (Letters denote Pasquill Stability Class) th

--- ~

es - m = u nturnAa. ro

, N N N

-I u= ram.ig N l as

- 8^8 C3 ( \

K(

srasta ts.r.as N "8'"" \

'\

les l

es (FRACTIdelREA = 1 Al

\

h

.\

\

gu

\

K 0.i s.1 is ,, ,, ,,,,

PLUIRE TRAVEL D03rA80CE rKIL00sETth31 i

l Reference 8 0004, Hatch REV.1 2.0-66 287M/0152W, 05/11/84 i

, . . . _ - . . , . _ , , - - . - , . , ,. , . . . , . . - -_. -ye. .-,,,m. , , _ . - . . - , . , _ , ,

l 1

l FIGtRE 2.3-5 Relative Deposition for Ground-Level Releases (All Atmospheric Stability Classes) 104 N \

104 N

E Q '

L E

g X

g h w

& T C S

< sg a

E 1e6 (

g Tm

!~ w i E \ '

5 %

r. %,

w 9 3 .

! 104

! x 10-7 0.1 1A 18A 100.0 200.0 PLURSE TRAVEL DISTANCE (KILOMETERS) j Reference 8 00CM, Hatch REY.1 2.0 67 2877W/0152W, 05/11/84 l

i . , _ _ _ _ _ . . _ _ _ . . . _ _ _ _ _ . _ _ _ _ . _ . _ _ _ , _ . _ .

h FIGURE 2.3-6 Relative Deposition for Greater Than 100-m Releases (Letters denote Pasquill Stability Class) 104 UNSTABLE (A,B,C)

[ \ %

\s 104 ) ,' t_

- l s' i %

[ [ NEUTRAL (D) N s j ( / \ '

N

= ; / N N E

e

/ / N s Ns I

4 ! ,

l 10 .

l )

i I E

J F

E f / STABLE (E,F,G)

NO DEPLETION l

10-7 ;

f I

I f

Y 4

104 I 0.1 1A 10A 100.0 200.0 PLURSE TRAVEL DISTANCE (KILORAETERS)

Refemme 8 0004, Hetch REV.1 2.0-68 28TM/0152W, 05/11/84

- - - .--,<~,e- .,-,.,,_,,..._.,,,,---,,.,m-

, - - - , . - , , , - , . , -en,, . , , , _ , .m.,,,,_n,,w,,,.,.,v,m,gw..,,.-wn y.-_.,-em- . -

M

2. 4 DEFINITIONS OF GASEDUS EFFLUENTS PARAMETERS Section of Term Definition Initial Use A

gg

= Numer of photons of energy corresponding to the ith 2.3.1 energy group emitted per transformation of radionuclide 1 (nunber/ transformation).

AG = administrative allocation factor for gaseous 2.1.1 effluent pathways.

b = maximum height of the adjacent building. 2.3.1 By = constant wt.fch includes the air dose factor, for each identi- 2.1.2 fled noble gas radioruclide, accounting for the gamma radiation from an elevated finite plume (mrad /yr per pCi/sec).

B = Build up factor 2.3.1 g

C = ' monitor reading of a noble gas monitor corresponding to 2.1.1 associated grab sample radionuclide concentrations.

C = monitor reading of tne noble gas monitor at the alarm set- 2.1.1 s

point concentration.

D = deposition rate at a given distance taken from Figure 2.3-5 2.3.1 g

for ground-level releases and Figure 2.3-6 for elevated releases.

Dj = dose to an organ of indiv!#11 tom radiciodines, 2.2.2.b tritite, and radionucl,4t 4 r . ticulate form with half-lives greater than sight cays (mrem).

Og = organ dose rate at time of release (mrem /yr). 2. 2.1.b ODCM, Hatch REV.1 2.0-69 2877W/0152W, 05/11/84

^

4 9

<: Section of Term Definition Initial Use !

= skin dose rate at time of release (mrem /yr). 2.2.1.a

- D, D = limiting dose rate to the skin of the body of an 2.1.1 ss individual in an unrestricted area which is 3000 mrem / year.

2.2.1.a

~

D = total body dose rate at time of release (mrem /yr).

= limiting dose rate to the total body of an individual 2.1.1 kB which is 500 mrem / year.

Dg = air dose due to beta emissions from noble gases (mrad). 2.2.2.a D = air dose due to gama emissions from noble gases (mrad). 2.2.2.a Y

D/Q

= the sector averaged relative deposition for any 2.3.2 distance in a given sector.

=. annual average deposition parameter for the location 2.2.2.0 .

(D/Q')yp of controlling (critical) receptor for plant vent releases.

(E =

-2 1.9 x 10~9 m in the NNE sector. 2.2.2.b yp

= annual average deposition parameter for the location of 2.2.2.b (D/Q? )sp controlling (critical) receptor for main stack releases.

E = 6.9 x 10' H m- 2 in NNE sector. 2.2.2.b sp

= energy assigned to energy group f. (MeV). 2.3.1 E,

h- = elevated release height (m). 2.3.1 ODCM, Hatch REV.1 2.0-70 2877W/0152W, 05/11/84

2 l vv]

Section of Term Definition Initial Use

= the results of numerical integration over the spatial 2.2.1 I(r)kl.

' distribution of an elevated finite plune.

6 = plume depletion factor for all radionuclides other than noble gases at distance r.

6 = plume depletion factor for all radionuclides other 2.3.1 k

than noble gases at a distance r for the appropriate

. stability class k (radiciodines and particulates).

a constant associated with the gK and V 2.3.1 1 calcu-K =

lation representing a combination of constants and ,

unit conversions.

K = total body dose factor due to gamma emissions from 2.1.1-radionuclide 1 (mrem / year per pCi/m ) from Table 2.1-1.

K = terrain recirculation factor. 2.3.1 L = horizontal distance from ground-level receptor 2.1.1 to the volume element considered as a point source in the evaluation of I(g.

L = . skin dose factor due to beta emissions from rad'onuclide i 2.1.1 3

'i (mrem /yr per pC1/m ) from Table 2.1-1.

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

My = air dose factor due to gama emissions from radionuclide 2.1.1 i (mrad /yr per pC1/m ) from Table 2.1-1.

n = number of hodrs the wind of wind speed class j is 2.3.1 directed into the given sector during the existence of atmospheric stability class k.

ODCM, Hatch REV.1 2.0-71 2877W/0152W, 05/11/84

q Section of Term Definition Initial Use N = air dose factor due to beta emissions from noble gas 2.2.2.a radionuclide i (mrad /yr per pCi/m3) from Table 2.1-1.

'njk = number of hours meteorological conditions are 2.3.1 observed to be in a given wind direction, wind-speed class j, and atmospheric stability class R.

N = total hours of valid meteorological data. 2.3.1 Pyg = dose parameter for radionuclide i, (arem/yr per 2.2.1.b pCi Y ) for the inhalation pathway from Table 2.2-1.

rate of release of noble gas radionuclide i 2.1.1 gy =

(pCi/sec) from the vent release pathway under consideration.

Q = rate of release of noble gas radionuclide i 2.1.2 is (pC1/sec) from the main stack.

~

cumulative release of noble gas radionuclide i over 2.2.2.a gy =

the period of interest (pC1) from the vent release under consideration.

= cumulative release of noble gas radionuclide i over 2.2.2.a ks

,the period of interest (pC1) from the main stack.

= cumulative release of radiciodine, trititsn or 2.2.2.b

'C1y' material in particulate form from plant vent releases over the period of interest (pC1).

cumulative release of radiciodine, trititsn or 2.2.2.b ks' =

material in particulate form from the main stack over the period of interest (pC1).

0D04, Hatch REV.1 2.0-72 2877W/0152W, 05/11/84 I

. -LL Section of Term Definition _

Initial Use r = distance fron. t% point of release to the receptor 2.3.1 of interest for dispersion calculations (meters).

R = pathway-specific, individual age-specific, organ dose 2.2.2.b factor for radionuclide i, pathway p, organ j, and age 3 2 group a, (mrem /yr per pCi/m ) or (m -mrem /yr per yCi/sec).

R = monitor reading per mrem /yr to the skin for vent 2.1.1 sv releases.

= monitor reading per mrem /yr to the skin for stack 2.1.1 R,,

releases.

R = monitor reading per mrem /yr to the total body for vent 2.1.1 releases.

R

= monitor reading per mrem /yr to the total body for stack 2.1.1 ts releases.

Ij = vertical standard deviation of the plume with 2.3.1 building wake correction.

I = the vertical standard deviation of the plume concen- 2.3.1 zk tration distribution considering the initial dis-persion within the building wake.

= vertical standard deviation of the plune (in meters), 2.3.1 ok z for a given distance for ground level releases under the stability category k indicated by AT/Az, from Figure 2.3-1.

-CDCM, Hatch REV.1 2.0-73 2877W/0152W, 05/11/84'

.-...._A Section of Term Definition Initial Use AT/a z = vertical temperature gradient used to determine the 2.3.1 atmospheric stability category (*C/100n or 'F/100 ft.).

T = tissue density thickness taken to represent the total 2.1.1 d

body dose (5 gm cm-2 ),

p = total absorbtion coefficient for air (m-1). 2.3.1 p, = energy absorbtion coefficient for air (m-1). 2.3.1 pT = the tissue energy absorbtion coefficient for photons 2.3.1 of energy Q (cm'gni1).

^

= wind speed (midpoint of wir49;::1 class j) at the 2. 3'. 1 u) heiWit of release (h).

ujk = wind speed (midpoint of wird9;::1 class j) at ground 2.3.1 level (m/sec) during atmospheric stability class k.

U = wind speed (midpoint of wind speed class j) at the 2.3.1 jk height of release, h, of an elevated release during atmospheric stability class k.

V = constant, which includes the dose factor, for each 2.1.2 f

identified noble gas radionuclide accouting for the gamma radiation from the elevated finite plume resulting from the main stack release in mrem / year per pCi/sec from Table 2.1-2.

W'

. yp

= pathway-dependent relative dispersion or deposition 2.2.2.b in the unrestricted area at the location of the controlling receptor associated with plant vent releases.

0D04, Hatch REV.1 2.0-74 2877W/0152W, 05/11/84 l i

,,.,---.,-,,..,-.-.----.,,m... , , - - -

,.%, w w ,,v- -,_.n-.---,,-,.--w-,.7 ,r.y,m,.,.,,._-, . , , , _ _ _ - , , , ,

g

- b Section of Term Definition Initial Use Wsp

' = pathway-dependent relative dispersion or deposition 2.2.2.b in the unrestricted area at the location of the controlling receptor, associated with stack releases.

X/Q = the sector-averaged annual average relative concen- 2.3.1 tration at any distance in the given sector.

X/g = the highest annual average relative concentration 2.1.1 at the site boundary when considering ground-level releases. ,

Y7@g = 6.8 x 10 sec/d in the W sector.

X/Q E = the highest annual average relative concentration in 2.1.1 the unrestricted area associated with releases from the main stack.

Y77E = 1.0 x 10' 7 sec/d in the W sector.

(X/Q')yp = annual average relative dispersion parameter for the 2.2.2.b location of the controlling receptor for plant vent releases.

(77Q')yp = 6.1 x 10'7 sec/d in the NNE sector.

OD04, Hatch REV.1 2.0-75 2877W/0152W, 05/11/84

-$k

^

Section of Term Definition Initial Use (X/Q')sp = annual average relative dispersion parameter for 2.2.2.b location of controlling receptor for main stack releases.

OUT')sp = 4.2 x 10 s sec/d in the NE sector.

z = vertical distance from a ground-level receptor to 2.3.1 the volume element considered as a point source in the evaluation of I(r)M

0004, Hatch REV.1 2.0-76 2877W/0152W, 05/11/84 1

!~

_a 2.5 GASEOUS RADWASTE TREATMENT SYSTEM Figure 2.5-1 is a schematic of the Condenser Offgas Treatment System showing the release points to unrestricted areas. This schematic is representative of Unit 1 and Unit 2.

f ODCM, Hatch REV.1 2.0-77 287/W/0152W, 05/11/84

~

@}

- d i

FIGURE 2.5-1 hser Offgas Treatment System

~

raon Conocus a

\/'

[ ist stAcs zJacrot 1stsTActImCoucosa-b 2nd sTAcz uncTom 2 4 sTAct t m Como os u 6 3rd sTAcE EJECTot orr-cAs n - arra camer:c ascoustm II J orr-cAs conoas u mA:t4Tras MoNITot h1 15ATER strABATo1 8 '

M .

noto-ur r.zza .

V coor.xx . *

~

Cosousu . I >. .

I > '

H

. ~, - -

notsTvas ststr

- strAnATot n ATu I

f.'

Y CMARCoAL ru.Tras CRARCoAL trLTras (6 etACEs) (6 r: Acts) l .---d RADIAT!oN HoNITot

)

\/ .

.rRoM

. sTANo8Y RADIATIoM TREA ENT ArTER .

rILT 3 NoNITom g f

i STACK j

+

C o SEAL SYSTE:t i

l l

t l

l~ 00CM, Hatch REY.1 2.0-78 i 2877W/0152W, 05/11/84

SECTION 3.

RADIG.0GICAL ENVIROP# ENTAL MONITORING PROGRAM Saspling locations as required by RETS 4.16.1 are described in Table 3.0-1 and shown on maps in Figures 3.0-1 and 3.0-2.

There are no known drinking water users downstream of FfF. Therefore, the LLD for I-131 in water need not be as stringent as that for milk.

The survey of milk animals is based on the requirement in Appendix I to 10 CFR Part 50 that the licensee " Identify changes in the use of unrestricted areas (e.g., for agricultural purposes) to permit modifications in monitoring programs ~for evaluating doses to individuals from principal pathways of exposure." The constaption of~ milk from animals grazing on contaminated pasture and the constaption of vegetation contaminated by airborne radiciodine are major potential sources of exposure. Samples from milk animals are considered a better indicator of radiciodine in the environment than

- vegetation. Because sufficient milk samples frequently are not available within five miles, vegetation samples will be collected also.

t Grass is available almost year-romd, whereas leafy vegetation is available only for eight months of the year at best. The sanpling stations for grass are located near the site boundary in two sectors with high offsite 0/Q values where it might be practical to establish a vegetation plot. The highest offsite D/Q for each. individual sector occurs approximately at the site bomdary.

Although either fish or clam samples may be collected from the river, fish

! samples are preferred because the maximun dose consnitment to a member of the ptblic as a result of liquid effluents is through the fish consunption pathway.

F

00CH, Hatch REV.1 3.0-1 2878W/0152W, 05/11/84

+.;

,I Sediment will be collected annually because shoreline recreational areas are under water and, therefore not in use approximately half the year.

Allowing deviations from the sampling schedule is based on the recognition of unavoidable practical difficulties which, in the absence of the allowed deviations, would result in violation of the RETS.

1 00CM, Hatch REN.1 3.0-2 2878W/0152W, 05/11/84

.f;

,-D TABLE 3.0-1 RADIOLOGICAL ENVIROWENTAL SAMPLING LOCATIONS LOCATION DESM IPTIVE LOCATION DIRECTION DISTANCE SAMPLE NLAGER (MILES) TYPE (1) 064 Roadside Park WNW 0.8 D 101 Inner Ring N 1.9 D 102 Inner Ring WE 2.5 D 103 Inner Ring NE 1.8 AD 104 Inner Ring ENE 1.6 0 105 Inner Ring E 3.6 0 106 Inner Ring ESE 1.1 DV 107 Inner Ring SE 1.2 AD 108 Inner Ring SSE 1.6 0 109 Inner Ring S 0.9 0 110 Inner Ring SSW 1.1 D 111 Inner Ring SW 0.9 D 112 Inner Ring WSW 1.0 ADV 113 Inner Ring W 1.1 0 Inner Ring 114 WNW 1.2 D 115 Inner Ring NW 1.1 0 1_16 Inner Ring NNW 1.6 AD 152 Williamson's WE 3.2 M 170 Upriver ' WNM

R 172 Downriv'er E R 201 Outer Ring N. 5.0 0 202 Outer Ring

WE 4.9 0 203 Outer Ring NE 5.0 0 204 Outer Ring ENE 4.9 D

, '205 Outer Ring E 7.2 D

,~ 206 Outer Ring ESE 5.0 0 207 Outer Ring SE 4.3 0 208 Outer Ring SSE 4.7 D 209 Outer Ring S 4.4 D 210 Outer Ring SSW 4.3 0 211 Outer Ring SW 4.5 0 212 Outer Ring WSW 4.4 0 213 Outer Ring W 4.3 D 214 Outer Ring WNW 5.4 D 215 Outer Ring NW 4.5 0 216 Outer Ring WW 4.8 0 301 Toombs Central School N 8.2 0 - .~

304 State Prison ENE 11.3 AD 304 State Prison ENE 10.8 M 309 Baxley Substation S 10.0 ADV 311 m son Brothers SW 9.1 H ODO4, Hatch REY.1 3.0-3 2878W/0152W, 05/11/84

~; . _ .,

3

- . ... ed TABLE 3.0-1 (CONTINUED)

(i TABLE NOTATION:

1. Sample Types A - Airborne Radioactivity D - Direct Radiation M - Milk 3

R - River (fish or clams, shoreline sediment, and surface water)

V - Vegetation

Station 170 is located at approximately 0.8 miles for riverwater,1.1 miles for sediment and clams, and 0.9 miles for fish.

Station 172 is located at approximately 2.3 miles for riverwater, 0.5 miles for sediment and clams, and 1.7 miles for fish.

, The location from which riverwater, and sometimes clams and sediment may be taken can be rather precisely defined. Often, however, the sampling locations for clans have to be extended over a wide area to obtain a sufficient quantity; even then the quantity may not be sufficient. High water adds tn the difficulty in obtaining clam sangles; high water might also make an otherwise suitable location for sediment sampling unavailable. A stretch of the river on the order of a mile or so is generally needed. to obtain adequate fish samples. The mile locations given above represent approximations of the locations about which the catches are taken.

I j -e 4

0004, Hatch REV.1 3.0-4 2878W/0152W, 05/11/84

-f

as

('.i

M FIGURE 3.0-1 RADI0I4GICAL ENVIROM GITAL SAMPLING LOCATION MAP (SITE PERIPHERY) i.,

t

~ .

\" =\ g . .y9 . - -

yn.s i

' i.,...

\ '/

s

/ t' .'= % -

dd 12

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t,% *

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3 FIGURE 3.0-2 (PART I)

RADICLOGICAL ENVIROMIENTAI. SAMPLING I4 CATION MAP

~

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-- . ~h FIGURE 3.0-2 (PART 2)

, RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATION MAP (BEYOND THE SITE VICINITY)

. a, . .F / t . -r- T i -ls ;

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_22 FIGURE 3.0-2 (PART -)

RADIOLOGICAL ENVIRO M NTAL SAMPLING LOCATION MAP (BEYOND THE SITE VICINITY)

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"i SECTION 4.0

' TOTAL DOSE DETERMINATIONS For the purpose of inglementing RETS 3.15.2.5 (Unit 1) or 3.11.2.5 (Unit 2),

total dose determinations will be made by calculating doses due to liquid effluents in accordance with RETS 3.15.1.2 (Unit 1) and 3.11.1.2 (Unit 2); by calculating doses due to gaseous effluents in accordance with RETS 3.15.2.3 (Unit 1) and 3.11.2.3 (Unit 2); and by canbining direct radiation doses based on direct radiation measurements with these effluent doses to detemine total dose to a real individual. Methodology for calculating individual doses due to liquid effluents was presented in Section 1.2. Methodology for calculating ?

individual doses due to gaseous effluents was presented in Section 2.2.2.b.

1 0004, Hatch REV.1 4.0-1 2878W/0152W, 05/11/84 r ..

k SECTION 5.0

. POTENTIAL DOSES TO MDGERS OF THE PtBLIC DUE TO TEIR ACTIVITIES INSIDE TE SITE 80UPDARY.

For the purpose of implementing RETS 6.9.1.9, an assessment of potential doses to MOSERS OF TE PLSLIC due to their activities within the SITE BOUPOARY win be performed if circumstances have changed such that any of the limits of RETS 3.u.2.2 (Unit 2), 3.H.2.3 (thit 2), 3.15.2.2 (Unit 1) or 3.15.2.3 (thit 1) are exceeded. The locations of concern within the SITE BOLM)ARY are the Roadside Park, the Camping Area, Recreation Area and the Visitors Center. The relationships between annual average atmospheric dispersion of airborne radioactive materials at various locations are as foHows:

Estimated Occupancy Factor Location X/Q (Sec/d ) (by an individual during a year)

Site Boundary 3.26 x 10 1005 Critical Receptor 6.10 x 10~7 100%

Roadside Park 3.74 x 10"' < 0.1 % (2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months )

Camping Area ~ 3.36 x 10 < 0.6 % (48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months )

Visitors Center 1.00 x 10-5 < 0.1 % (4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months )

Recreation Area 6.71 x 10~7 2.4 % (208 hours0.00241 days 0.0578 hours 3.439153e-4 weeks 7.9144e-5 months )

In the event that any limit of RETS 3.11.2.2 or 3.15.2.2 is exceeded, an assessment will be performed considering direct radiation dose to an individual resulting in submersion in the ground level plume. This assessment win take into consideration the annual average dispersion parameters and the estimated occupancy factor stated above, or a more precise value if available, for the locations of interest.

ODO4, Hatch REV.1 5.0-1 2878W/0152W, 05/11/84

-_ _,__--__,------m.

li

_ . . i In the event that any limit of RETS 3.11.2.3 - or 3.15.2.3 is exceeded, an assessment will be performed considering the internal dose to an individual due to inhalation of airborne radioactive materials suspended in the ground level plune. This assessment will take into consideration the annual average dispersion parameters and the er,timated occupancy factor stated above, or a more precise value if available, far the locations of interest.

If none of the limits discussed above is exceeded, potential annual doses to an individual at the Visitors Center are not expected to exceed 0.001 mrem due to inhalation and 0.01 mrem due to direct radiation; potential doses to an individual at the Roadside Park are not expected to exceed 0.001 mrem due to inhalation and 0.01 mram due to direct radiation; potential doses to an individual at the Camping Area are not expected to exceed 0.003 mrem due to inhalation and 0.06 mrom due to direct ' radiation; potential doses to an individual at the Recreation Area are not expected to exceed 0.002 mrem due to inhalation and 0.05 mram due to direct radiation.

These values are based on annual average dispersion parameters and the estimated occupancy factors stated above. Occuhncy factors for the Visitors Center, the Roadside Park, and the Camping Area are based on activities observed at these locations over the last several years. The occupancy factor for the Recreation Area is based on anticipated use of this facility.

i t

0004, Hatch REV.1 5.0-2 2878W/0152W, 05/11/84 I

ML20098G340

Text

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