ML20155C896

Rev 1 to Offsite Dose Calculation Manual

ML20155C896
Person / Time
Site:	Hatch
Issue date:	09/30/1984
From:	GEORGIA POWER CO.
To:
Shared Package
ML20155C874	List: ML20155C870 ML20155C884 ML20155C896
References
PROC-840930-03, TAC-62143, TAC-62144, NUDOCS 8604170158
Download: ML20155C896 (134)

Text

Georgia Power Company 333 Piedmont Avenue Atlanta. Georgia 30308 Telephone 404 526-6526 Mailing Address:

Post Office Box 4545 Atlanta. Georgia 30302

? GeorgiaPower Nuclear operations Department IN 5 * '" *** C S M '"

November 8, 1985 10: DISTRIBLTTION RE: OFFSITE DOSE CALQJLATION MANUAL (ODOf)

Attached is your controlled copy of the Offsite Dose Calculation Manual (Revision 1) for Georgia Power Company Edwin I. Hatch Nuclear Plant. This copy supercedes all previous versions of the Plant Hatch ODOf.

Distribution of controlled copies of the Plant Hatch ODO! is being administered by Southern Company Services. In order to reproduce the document efficiently, it was necessary to alter slightly the format of the original version of the Plant Hatch ODOf. However, no changes were made to technical content nor methodology.

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Recipient Title / Location No. of Copies E. C. Sorrell Supervisor-Document Control 8 Plant Ibtch S. C. Ewald hbnager-Radiation Safety 4 Georgia Power Company 333 Piedmont,14th Floor Atlanta, Georgia -

L. T. Gucwa Manager-hbclear Engineering 1 and 011ef Nuclear Engineer Georgia Power Company 333 Piedmont,14th Floor Atlanta, Georgia B. L. Maulsby Supervisor-Environmental Center 2 Georgia Power Company Decatur, Georgia W. F. Garner Manager-Nuclear Plant Support-lbtch 1 Southern Company Services Inverness Center Building 10, Room 300 (o

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! Birmingham, Alabama J. N. McLeod Supervisor-Safety Analaysis 1 Southern Company Services Inverness Center Building 40, 6th Floor Birmingham, Alabama

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ii 0FFSITE. DOSE CALCULATION MANUAL  ;

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OISTRIBUTION LIST Recipient Title / Location No. of Copies E. C. Sorrell Supervisor-Document Control 8 Plant Hatch l S. C. Ewald Manager-Radiation Safety 4

) Georgia Power Company 333 Piedmont, 14th Floor Atlanta, Georgia

! L. T. Gucwa Manager-Nuclear Engineering 1 and Chief Nuclear Engineer l Georgia Power Company i

333 Piedmont, 14th Floor Atlanta, Georgia l

l I 8. L. Maulsby Supervisor-Environmental Center 2 Georgia Power Company Decatur, Georgia W. F. Garner Manager-Nuclear Plant Support-Hatch 1 l

Southern Company Services Inverness Center Building 10, Room 300 O Birmingham, Alabama i J. N. McLeod Supervisor-Safety Analysis 1 l Southern Company Services

! Inverness Center Building 40, 6th Floor Birmingham, Alabama f

i f i O 0689n HATCH ODCM, REV 1 5/11/84

r TA8LE OF CONTENTS

[7 N~-)

Eait 1.0 LIQUID EFFLUENTS 1.0-1 1.1 LIQUID EFFLUENT MONITOR SETPOINTS 1.1 -1 1.1.1 Liquid Radwaste Effluent Monitors 1.1 -1 l

1.1.2 Plant Service Water Monitors 1.1-9 1.2 00SE CALCULATION FOR LIQUID EFFLUENTS 1. 2 -1 l 1.3 DOSE PROJECTIONS FOR LIQUID EFFLUENTS 1.3-1 1.3.1 Monthly Dose Projections 1. 3-1 1.3.2 Dose Projections for Specific Releases 1.3-2 1.4 DEFINITIONS OF LIQUID EFFLUENT TERMS 1,4 -1 1.5 LIQUID RADWASTE TREATMENT SYSTEMS 1.5-1 1.6 MIXING OF LIQUID WASTE TANKS 1.6-1 2.0 GASEOUS EFFLUENTS 2.0-1 2.1 GASEOUS EFFLUENT MONITOR SETPOINTS 2.1 -1 2.1.1 Unit 1 Reactor Building Vent Stack, 2.1 -1 Unit 2 Reactor Building Vent Stack, and

(%)

(m.

Unit 1 Recombiner Building Vent 2.1.2 Main Stack 2.1 -4 2.1.3 Determination of Allocation Factor, AG 2.1-6 2.2 GASEOUS EFFLUENT DOSE RATE AND 00SE CALCULATIONS 2. 2 -1 2.2.1 Unrestricted Area Boundary Dose Rate 2. 2 -1 2.2.1.a Dose Rates Due to Noble Gases 2. 2 -1 2.2.1.b Dose Rates Due to Radiciodines, 2.2-2 Tritium, and Particulates 2.2.2 Unrestricted Area Air Oose and Dose 2.2-4 to Individual 2.2.2.a Air Dose in Unrestricted Area 2.2-4 2.2.2.b Dose to An Individual in 2.2-5 ,

Unrestricted Area 2.2.2.c Dose Calculations to Suppcet 2.2-12 Other Specific Technical Specifications i

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HATCH 00CN, REY 1 5/11/84 i .

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L f TABLE OF CONTENTS (CONTINUED) em 2.3 METEOROLOGICAL MODEL 2. 3-1 l 2.3.1 Atmospheric Dispersion 2. 3-1 2.3.1.a Ground-Level Releases 2. 3 -1 2.3.1.b Elevated Releases 2.3-3 l

, 2.3.2 Relative Deposition 2.3-6 2.4 DEFINITIONS OF GASEQUS EFFLUENT PARAMETERS 2.4-1 l

2.5 GASEOUS RA0 WASTE EFFLUENT TREATMENT SYSTEM 2.5-1 3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 3.0-1 4.0 TOTAL DOSE DETERMINATIONS 4.0-1 5.0 POTENTIAL DOSES TO MEMBERS OF THE PUBLIC DUE TO THEIR 5.0-1 ACTivlTIES INSIDE THE S :TE BOUNDARY O

O HATCH 00CM, REV 1 5/11/84 11

LIST OF TABLES LO!

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Table Title Pa28 l

1. 2-1 Bioaccumulation Factors 1.2-4 1.2-2 Adult Ingestion Oose Factors 1.2-5 l 1.2-3 Site-Related Ingestion Dose Commitment Factors, 1.2-7 Aj, (Fish Consumption) 2.1 -1 Dose Factors for Exposure to a Semi-Infinite 2.1-8 Cloud of Noble Gases 2.1 -2 Dose Factors for Exposure to Direct Radiation 2.1 -9 from Noble Gases in the Elevated Finite Plume

2. 2-1 Inhalation Dose Factors for Infant 2.2-19 2.2-2 Inhalation Oose Factors for Child 2.2-22 2.2-3 Inhalation Oose Factors for Teenager 2.2-25

2. 2-4 Inhalation Dose Factors for Adult 2.2-28 2.2-5 Ingestion Dose Factors for Infant 2.2-31 2.2-6 Ingestion Dose Factors for Child 2.2-34

2. 2 -7 Ingestion Oose Factors for Teenager 2.2-37 2.2-8 Ingestion Dose Factors for Adult 2.2-40 2 . 2 -9 F.xternal Dose Factors for Standing on 2.2-43 Contaminated Ground 2.2-10 Individual Usage Factors 2.2-45 2.2-11 Stable Element Transfer Data 2.2-46 2.2-12 Site-Specific (or Default) Values to be 2.2-47 i Os Used in Pathway Factor Calculations 2.2-13 Site-Specific (or Default) Values to be 2.2-48 Used in Additional Pathway Factor Calculations 3.0-1 Radiological Environmental Sampling Locations 3.0-3 HATCH 00CM, REV 1 5/11/84 111 ,

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-,,,-c , ., - , - . , - - - . - - - , - - - - - - - - - - - - - - +

LIST OF FIGURES Figure Title Page 1.1 -1 Example Calibration Curve for Liquid Effluent Monitor 1.1-10

1. 5-1 Liquid Radwaste Treatment System (Unit 1) 1.5-2 1.5-2 Liquid Radwaste Treatment System (Unit 2) 1.5-3

2. 3-1 Vertical Standard Deviation of Material in a Plume (oZ) 2.3-7 2.3-2 Open Terrain Recirculation Factor 2.3-8 2.3-3 Plume Depletion Ef fect for Ground-Level Releases 2.3-9 2.3-4 Plume Depletion Ef fect for Greater Than 100-m Releases 2.3-10 2.3-5 Relative Deposition for Ground-Level Releases 2.3-11 2.3-6 Relative Deposition for Greater Than 100-m Releases 2.3-12

2. 5 -1 Condenser Offgas Treatment System 2.5-2

3. 0-1 Radiological Environmental Sampling Location Map 3.0-5 (Site Periphery) 3.0-2 Radiological Environmental Sampling Location Map 3.0-6 (Beyond the Site Vicinity)

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HATCH ODCM, REV 1 5/11/84 iv l

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INTRODUCTION O The Offsite Dose Calculation Manual (00CM) is a supporting document of the Radiological Effluent Technical Specifications (RETS). As such, the 00CM describes the methodology and parameters to be used in the calculation of offsite doses due to radioactive liquid and gaseous effluents and in the calculation of liquid and gaseous effluent monitoring instrumentation alars/ trip setpoints. The 00CM contains a list and graphical description of the specific sample locations for the radiological environmental monitoring program. Schematic configurations of liquid and gaseous radwaste effluent systems releases to unrestricted areas are also included.

The ODCM will be maintained at the plant for use as a reference guide and training document of accepted methodologies and calculations. Changes in the calculational methods or parameters will be incorporated into the 00CM in order to assure that the 00CM represents the present methodology in all applicable areas. Computer sof tware to perform the described calculations will be maintained current with the 00CM.

O 0672n HATCH ODCM, REV 1 5/11/84

1.0 LIQUID EFFLUENTS O

V The Edwin I. Hatch Nuclear Plant is located on the Altamaha River which supplies make-up 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 fiume or to the cooling tower blowdown discharge line when needed for additional dilution. Although no significant releases of radioactivity are expected from the plant service water systems, these effluent pathways are monitored as a precautionary measure.

O D

O 0682n HATCH 00CM, REV 1 5/11/84 1.0-1

l.1 LIQUID EFFLUENT MONITOR SETPOINTS O Although each unit has unique liquid release sources, a separate radwaste system, independent liquid ef fluent 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 calculated value. The actual monitor setpoint, which corresponds to the calculated concantration 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 for a particular pathway, or if there is no detectable activity in the planned release, the monitor setpoint should be established as close to background as practical to prevent spurious alarms and yet alarm should an inadvertent release occur.

O 1.1.1 Liouid Radwaste Effluent Radiation Monitors The liquid radwaste effluent line monitors provide alarm and automatic termination of release functions prior to exceeding the concentration limits l specified in 10 CFR 20, Appendix B, Table II, Column 2 at the release point to the 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:

l Cf F+f $ CMPC (1) l l

O 1 HATCH 00CM, REV 1 5/11/84 1.1 -1

where:

(vD CMPC

=

the ef fluent concentration limit (RETS 3.15.1.1 (Unit 1) and 3.11.1.1 (Unit 2)) implementing 10 CFR 20 for the site, corresponding to the specific mix of radionuclides in the waste tank being considered for discharge, in uCi/ml.

c = the setpoint, in uCi/ml, of the radioactivity 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 ef fluent 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 10 CFR 20 in the unrestricted area.

f = the flow setpoint as determined at the radiation monitor i 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.

l f

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.

l l The sources of liquid radioactive effluents from Unit 1 are:

i

. Haste sample tank A.

. Waste sample tank B.

. Chemical waste sample tank A.

. Chemical waste sample tank B.

O HATCH ODCM, REV 1 5/11/84 1.1-2 I

i

. Floor drain sample tank.

tm) . Laundry drain tank A.

l

. Laundry drain tank B.

- Demineralizer feed tank.

All of these sources discharge to a comon line which is served by radiation monitor 1Dil-N007. These Unit i sources release to a dilution stream served by ficw element FE N-501, which is capable of isolating liquid radwaste discharges from Unit 1 if predefined 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 sample tank A.

{

. Chemical waste sample tank B.

. Floor drain sample tank.

All of these sources discharge to a common line which is served by radiation monitor 2Dil-N007. These Unit 2 sources release to a dilution stream served by flow element FE N-502, which is capable of isolating liquid radwaste O' discharges from Unit 2 if predefined minimum dilution flow is not available in the dilution stream.

Liquid radwaste releases from the two units may proceed independently and I concurrently. Liquid radwaste releases from each unit, however, till be l

administratively controlled so that only one source of liquid radwaste will be released at a time from that unit.

The maximum liquid radwaste ef fluent flow from the source selected for ,

release and the setpoint for the radiation monitor serving the discharge pathway are determined and set to meet the general conditions of Equation 1 for a given effluent concentration. The method by which this is accomplished is as follows:

v HATCH ODCM, REV 1 5/11/84 1.1-3

SteD 1 J The radionuclide concentration for a waste tank to be released is obtained 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):

I Cj =

ICg + (Ca+Cs+Cf+C) t (2) i g where:

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

t Ca

= the concentration of alpha emitters in liquid waste as measured in the MONTHLY composite sample. (NOTE: Sample is analyzed for gross a).

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

= the measured concentrations of Fe-b5 in liquid waste as Cf observed in the QUARTERLY composite sample.

Ct = the measured concentration of H-3 in liquid waste as determined from analysis of the MONTHLY composite sample.

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

SteD 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 O

HATCH ODCM, REV 1 5/11/84 1.1-4

required to assure that the limiting concentrations of 10 CFR 20, Appendix B, h Table II, Column 2 are met at the point of discharge.

OF =

I Ci , sp i MPCj

, y Ca + Ca + Cs , Cf , Ct + SF (3) g MPC g MPCa MPCs MPCf MPCt where:

Ci = the measured concentrations of C g , Ca. Cs, cf. and Ct as defined in Step 1. Terms aC , C s , C f . and Ct will be included in the calculation, as appropriate.

MPCj = MPCg , MPCa, MPCs, MPC f , and MPCt are limiting concentrations of the appropriate radionuclide from 10 CFR 20, Appendix B.

Table II, Column 2. For dissolved or entrained ' noble 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.)

SteD 3 The dilution flow monitor setpoint is determined for the minimum dilution flow rate, Fd; for Plant Hatch, Fd is normally established at 10,000 gpm.

O  ;

HATCH ODCM, REV 1 5/11/84 1.1-5

SteD 4 For the case DF < 1, the waste tank ef fluent concentration meets the limits of 10 CFR 20 without dilution, and the ef fluent discharge flow rate may be assigned any desired value. For DF > 1, the maximum permissible discharge flow rate. ft, must be calculated:

ft . Fd+fp -

Fd for Fd >> f p (4)

DF DF where:

Fd

= the minimum dilution flow rate to be used in effluent monitor setpoint calculations which is normally 10,000 gpm.

DF = the dilution factor from Step 2.

fp = the flow rate of waste tank discharge. (This value will have an upper limit of the maximum discharge capacity of the U particular waste tank pump.)

NOTE: If radioactivity from plant operations is detected in the dilution stream, the equation for calculation of ft must include a term to account for radioactivity present in the dilution stream prior to the introduction of the waste tank effluent:

C 1-I i\

ft =

Fq ,

j (MPCi > d_ (5)

DF where:

I

/Ci = the MPC fraction of the dilution stream prior to i \MPCij d introduction of the waste tank effluent.

O HATCH 00CM, REV 1 5/11/84 1.1 -6 i

Steo S O The liquid radwaste ef fluent radiation monitor setpoint may now be determined based on the values of I Cj, ft and Fd which were specified to provide i

compliance with the limits of 10 CFR 20, Appendix B, Table II, Column 2. The monitor response is primarily to gamma radiation; therefore, the actual setpoint is based on I Cg. The monitor setpoint which corresponds to the g

particular setpoint concentration, c, is determined based on monitor calibration data or on operational data which correlates monitor response to sample analyses associated with actual effluent releases. (Example of monitor calibration graph is shown in Figure 1.1-1.)

The setpoint concentration, c, is determined as follows:

c =

AIC g uCi (6) g al where:

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

ft

=

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

If A > 1, calculate c and determine the maximum value for the actual monitor setpoint (vC1/ml).

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

O HATCH 00CM, REY 1 5/11/84 1.1-7

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. Nomally, 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, i

NOTE 2: If DF < 1, A = (1/DF). As stated earlier, if DF = 0, the radiation monitor setpoint should be established as close to background as practicable to prevent spurious alarms and yet 4

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 this value.

In this case a new setpoint may be calculated by decreasing the effluent flow, increasing the dilution flow, or by decreasing { Cj by further processing of the liquid radwaste planned for release, and by following the 1

methodology presented in Steps 2, 3, and 4.

i Within the limits of,'the conditions stated above, monitor setpoints for liquid radwaste efflgent radiation monitors may be determined as follows:

Liouid Radwaste Effluent Radiation Monitor ID11-N007 (Unit 1) or 2Dil-N007 l

(Unit 2) 3 Perform Step 2, solving Equation 3 for DF using the appropriate values in the concentration term f rom the sample analyses for the particular waste tank batch to be discharged. Then perform Steps 3, 4, and 5 to determine the l- monitor setpoint.

4

<. g

, O I HATCH ODCM, REY l S/11/84 1.1-8 i

If no discharge is planned for this 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 setpoints should be established as close to background as practical to prevent spurious alarms and yet alarm should an inadvertent release occur.

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

c =

(I Cg ) + DF (8) 9 where:

{Cg and DF are determined using the sample analysis results for this effluent stream and applying the methodology of Section 1.1.1, Step 1 and Step 2.

For these release pathways no additional dilution is taken into account; therefore, no releases are permissible if DF > 1.

O 0674n HATCH ODCM, REV 1 5/11/84 1.1-9

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H ATCH OOCM. R EV 1 5/11/84 l l

/m s EXAMPLE CALIBRATION CURVE FOR ,

b- EMINI. HATCH LIQUID EFFLUENT MONITOR l Georgia Power [ noCuu uur FIGURE 1.1-1 3* 1.1-10

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=

,, 1.2 DOSE CALCULATION FOR LIQUID EFFLUENTS For liquid release from Plant Hatch to the Altamaha River, the only human exposure pathway is due to consumption of fish taken from the river. No drinking water is taken from the Altamaha River downstream f rom Plant Hatch.

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

The dose contribution to the maximum exposed individual by way of fish consumption from radionuclides identified in liquid effluents released to unrestricted areas will be calculated for the purpose of implementation 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 individual are calculated as follows:

m -Aite D, = I Aj, I att Cge i Ft (9) i t=1 O

v where:

D, = 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 at t, in mrem, (Reference 1).

t=1 atg = the length of the Lth time period over which C ig and Fg are averaged for all liquid releases, in hours.

Cg i = the average concentration of radionuclide i, in undiluted liquid effluent during time period att from any liquid release, in pCi/ml.

11

= the decay constant for radionuclide i (sec' ).

O HATCH ODCM, REV 1 5/11/84 1. 2-1

tc = the transit time from release to receptor (24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />; Reference 3, Table E-15) .

Fg = the near-field average dilution factor in the receiving water body during any liquid effluent release. Defined as the ratio of the undiluted liquid waste flow during release to the product of the average flow from the discharge structure to unrestricted receiving water times Z.

= (averaae undiluted liauid 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 ft*/sec or less (Reference 1, Section 4.3).

where:

Z = the applicable dilution factor for the receiving water body.

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

Aj, = the site-related fish ingestion dose commitment factor to the total body or any organ, t, for each identified principal gansna and beta emitter listed in Table 1.2-3 in mrem-m1 per hr uC1.

A,=Ko 1 (Up BFj) DFj, (11) where:

Ko = the units conversion factor 1.14 x 10'.

= 10' x 10' m + 8760 O '

HATCH ODCM, REV 1 5/11/84 1.2-2 j

Up = the adult fish consumption (21 kg/yr).

m BFj = the bioaccumulation factor for radionuclide 1, in fish, in pCi/kg per pCi/1, f rom Table 1.2-1 (taken from Reference 4, Appendix A Table 2.3-1).

OFj, = dose conversion factor for radionuclide i, for adults in preselected organ, t, in mrem /pC1, from Table 1.2-2 (taken from Reference 3, Table E-il) .

At Plant Hatch no measurable radioactivity is expected to be present in the dilution stream prior to the junction with- the liquid radwaste discharge line. However, if radioacilvity due to plant operations should 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 Ft = 1/Z and at = the entire time period for which the dose is being calculated.

HATCH 00CM, REV 1 5/11/84 1.2-3

TABLE 1.2-1

~

BI0 ACCUMULATION FACTORS (pCi/kg per pCi/1)*

Freshwater Element Fish H 9.0E-01 C 4.6E 03 NA 6.6E 01 P 2.5E 04 CR 1.5E 02 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 N8 4.lE.01 MO 1.8E 02 TC 1.5E 01 RU 4.6E 00 RH 1.0E 01 AG 3.50 02 TE 4.0E 02 I 4.3E 01 CS 5.8E 02 BA 5.0E 00 LA 2.5E 01 CE 8.4E 01 PR 2.5E 01 ND 4.6E 01 W 1.2E 03 NP 1.0E 01

• Values in Tables 1.2-1 are taken from Reference 4, Appendix A, Table 2.3-1.

O HATCH 00CM, REV 1 5/11/84 1.2-4

TABLE 1.2-2 (SHEET 1 0F 2)

/3 k/

m ADULT INGESTION DOSE FACTORS *

(mrem /pCi ingested)

Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI H 3 NO DATA 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 C 14 2.34E-06 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.6SE-07 NA 24 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 P 32 1.93E-04 1.20E-05 7.46E-06 NO DATA NO DATA NO DATA 2.17E-05 CR 51 N3 DATA NO DATA 2.66E-09 1.59E-09 5.86E-10 3.53E-09 6.69E-07 MN 54 NO DATA 4.57E-06 8.72E-07 NO DATA 1.36E-06 NO DATA 1.40E-05 MN 56 NO DATA 1.15E-07 2.04E-08 NO DATA 1.46E-07 NO DATA 3.67E-06 FE 55 2.75E-06 1.90F-06 4.43E-07 NO DATA NO DATA 1.06E-06 1.09E-06 FE 59 4.34E-06 1.02E-05 3.91E-06 NO DATA NO DATA 2.85E-06 3.40E-05 CO 58 NO DATA 7.45E-07 1.67E-06 NO DATA NO DATA NO DATA 1.51E-05 00 60 NO DATA 2.14F-06 4.72E-06 NO DATA NO DATA NO DATA 4.02E-05 NI 63 1.30E-04 9.01E-06 4.36E-06 NO DATA NO DATA NO DATA 1.88E-06 NI 65 5.28E-07 6.86E-08 3.13E-08 NO DATA NO DATA NO DATA 1.74E-06 CU 64 NO DATA 8.33E-08 3.91E-08 NO DATA 2.10E-07 NO DATA 7.10E-06 ZN 65 4.84E-05 1.54E-05 6.96E-06 NO DATA 1.03E-05 NO DATA 9.70E-06 ZN 69 1.03E-08 1.97 E-08 1.37E-09 NO DATA 1.28E-08 NO DATA 2.96E-09 BR 83 NO DATA NO DATA 4.02E-08 NO DATA NO DATA NO DATA 5.79E-08 BR 84 NO DATA NO DATA 5.21E-08 NO DATA NO DATA NO DATA 4.09E-13 BR 85 NO DATA NO DATA 2.14E-09 NO DATA NO DATA NO DATA LT E-24 RB 86 NO DATA 2.11E-05 9.83E-06 NO DATA NO DATA NO DATA 4.16E-06 RB 88 NO DATA 6.05E-08 3.21E-08 NO DATA NO DATA NO DATA 8.36E-19 RB 89 NO DATA 4.01E-08 2.82E-08 NO DATA NO DATA NO DATA 2.33E-21 SR 89 3.08E-04 NO DATA 8.84E-06 NO DATA NO DATA NO DATA 4.94E-05 SR 90 7.58E-03 NO DATA 1.86E-03 NO DATA NO DATA NO DATA 2.19E-04 SR 91 5.67E-06 NO DATA 2.29E-07 NO DATA NO DATA NO DATA 2.70E-05 SR 92 2.15E-06 NO DATA 9.30E-08 NO DATA NO DATA NO DATA 4.26E-05 Y 90 9.62E-09 NO DATA 2.58E-10 NO DATA NO DATA NO DATA 1.02E-04 Y 91M 9.09E-11 NO DATA 3.52E-12 NO DATA NO DATA NO DATA 2.67E-10 Y 91 1.41E-07 NO DATA 3.77E-09 NO DATA NO DATA NO DATA 7.76E-05 Y 92 8.45E-10 NO DATA 2.47E-11 NO DATA NO DATA NO DATA 1.48E-05 Y 93 2.68E-09 NO DATA 7.40E-11 NO DATA NO DATA NO DATA 8.50E-05 ZR 95 3.04E-08 9.75E-09 6.60E-09 NO DATA 1.53E-08 NO DATA 3.09E-05 ZR 97 1.68E-09 3.39E-10 1. 35E-10 NO DATA 5.12E-10 NO D3TA 1.05E-04 NB 95 6.22E-09 3.46E-09 1.86E-09 NO DATA 3.42E-09 NO DATA 2.10E-05 MO 99 NO DATA 4.31E-06 8.20E-07 NO DATA 9.76E-06 NO DATA 9.99E-06 TC 99M 2.47E-10 6.98E-10 8.89E-09 NO DATA 1.06E-08 3.42E-10 4.13E-07 TC101 2.54E-10 3.66E-10 3.59E-09 NO DATA 6.59E-09 1.87E-10 1.10E-21 RU103 1.85E-07 NO DATA 7.97E-08 NO DATA 7.06E-07 NO DATA 2.16E-05 RU105 1.54E-08 NO DATA 6.08E-09 NO DATA 1.99E-07 NO DATA 9.42E-06

(

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

HATCH ODCM, REV 1 5/11/84 1.2-5

,_s TA8LE 1.2-2 (SHEET 2 0F 2)

- ADULT INGESTION DOSE FACTORS *

(mrem /pci ingested)

Nuclide Bone Liver T. Body Thyroid Kidney Lung GI-LLI RU106 2.75E-06 NO DATA 3.48E-07 NO DATA 5.31E-06 NO DATA 1.78E-04 AG110M 1.60E-07 1.48E-07 8.79E-08 NO DATA 2.91E-07 NO DATA 6.04E-05 TE125M 2.68E-06 9.71E-07 3.59E-07 8.06E-07 1.09E-05 NO DATA 1.07E-05 TE127M 6.77E-06 2.42E-06 8.25E-07 1.73E-06 2.75E-05 NO DATA 2.27E-05 TE127 1.10E-07 3.95E-08 2.38E-08 8.15E-08 4.48E-07 NO DATA 8.68E-06 TE129M 1.15E-05 4.29E-06 1.82E-06 3.95E-06 4.80E-05 NO DATA 5.79E-05 TE129 3.14E-08 1.18E-08 7.65E-09 2.41E-08 1.32E-07 NO DATA 2.37E-08 TE131M 1.73E-06 8.46E-07 7.05E-07 1.34E-06 8.57E-06 NO DATA 8.40E-05 TE131 1.97E-08 8.23E-09 6.22E-09 1.62E-08 8.63E-08 NO DATA 2.79E-09 TE132 2.52E-06 1.63E-06 1.53E-06 1.80E-06 1.57E-05 NO DATA 7.71E-05 I 130 7.56E-07 2.23E-06 8.80E-07 1.89E-04 3.48E-06 NO DATA 1.92E-06 I 131 4.16E-06 5.95E-06 3.41E-06 1.95E-03 1.02E-05 NO DATA 1.57E-06 I 132 2.03E-07 5.43E-07 1.90E-07 1.90E-05 8.65E-07 NO DATA 1.02E-07 I 133 1.42E-06 2.47E-06 7.53E-07 3.63E-04 4.31E-06 NO DATA 2.22E-06 I 134 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 NO DATA 2. 51 E-10 I 135 4.43E-07 1.16E-06 4.28E-07 7.65E-05 1.86E-06 NO DATA 1.31E-06 CS134 6.22E-05 1.48E-04 1.21E-04 NO DATA 4.79E-05 1.59E-05 2.59E-06

,f 3 CS136 6. 51 E-06 2.57E-05 1.85E-05 NO DATA 1.43E-05 1.96E-06 2.92E-06

(~ l CS137 7.97E-05 1.09E-04 7.14E-05 NO DATA 3.70E-05 1.23E-05 2.11E-06 CS138 5.52E-08 1.09E-07 5.40E-08 NO DATA 8.01E-08 7.91E-09 4.65E-13 BA139 9.70E-08 6.91 E-11 2.84E-09 NO DATA 6.46E-11 3.92E-11 1.72E-07 BA140 2.03E-05 2.55E-08 1.33E-06 NO DATA 8.67E-09 1.46E-08 4.18E-05 BA141 4.71E-08 3.56E-11 1.59E-09 NO DATA 3.31E-11 2.02E-11 2.22E-17 8A142 2.13E-08 2.19E-11 1.34E-09 NO DATA 1.85E-11 1.24E-11 3.00E-26 LA140 2.50E-09 1.26E-09 3.33E-10 NO DATA NO DATA NO DATA 9.25E-05 LA142 1.28E-10 5.82E-11 1.45E-11 NO DATA NO DATA NO DATA 4.25E-07 CE141 9.36E-09 6.33E-09 7.18E-10 NO DATA 2.94E-09 NO DATA 2.42E-05 CE143 1.65E-09 1.22E-06 1.35E-10 NO DATA 5.37E-10 NO DATA 4.56E-05 CE144 4.88E-07 2.04E-07 2.62E-08 NO DATA 1.21E-07 NO DATA 1.65E-04 PR143 9.20E-09 3.69E-09 4. 56E-10 NO DATA 2.13E-09 NO DATA 4.03E-05 PR144 3.01 E-11 1.25E-11 1. 53E-12 NO DATA 7.05 E-12 NO DATA 4.33E-18 ND147 6.29E-09 7.27E-09 4. 35 E-10 NO DATA 4.25E-09 NO DATA 3.49E-05 W 137 1.03E-07 8.61E-08 3.01E-08 NO DATA NO DATA NO DATA 2.82E-05 NP239 1.19E-09 1.17E-10 6.45E-11 NO DATA 3.65E-10 NO DATA 2.40E-05

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

HATCH 00CM, REV 1 5/11/84 1.2-6

TABLE 1.2-3 (SHEET 1 0F 2)

~'

SITE-RELATED INGESTION DOSE COMMITMENT FACTOR, Aj, (FISH CONSUMPTION)*

(mrem /hr per pCi/ml)

Nuclide 80ne Liver T. Body Thyroid Kidney Lung GI-LLI H-3 0.00E+00 2.26E-01 2.26E-01 2.26E-01 2.26E-01 2.26E-01 2.26E-01 C-14 3.13E &O4 6.26E&O3 6.26E&O3 6.26E+03 6.26E&O3 6.26E+03 6.26E+03 Na-24 2.69E&O2 2.69E+02 2.69E+02 2.69E+02 2.69E+02 2.69E+02 2.69E&O2 P-32 1.16E&O7 7.18E&05 4.46E*05 0.00E+00 0.00E+00 0.00E+00 1.30E&O6 Cr-51 0.00E&00 0.00E+00 9.55E-01 5.71E-01 2.10E-01 1.27E+00 2.40E+02 Mn-54 0.00E&00 9.74E+02 1.86E+02 0.00E+00 2.90E&O2 0.00E+00 2.98E*03 Mn-56 0.00E&00 2.45E+01 4.35E&00 0.00E+00 3.11E*01 0.00E+00 7.82E&O2 Fe-55 3.95E+01 2.73E+01 6.36E+00 0.00E+00 0.00E+00 1. 52 E +01 1. 57 E +01 Fe-59 6.23E&01 1.47E+02 5.62E&01 0.00E+00 0.00E&00 4.09E+01 4. 88 E +02 Co-58 0.00E&00 3.03E+02 6.80E+02 0.00E+00 0.00E&00 0.00E*00 6.15E&O3 Co-60 0.00E&OO 8.71E+02 1.92E*03 0.00E+00 0.00E&00 0.00E+00 1.64E*04 Ni-63 3.11E&O4 2.16E+03 1.04E*03 0.00E+00 0.00E*00 0.00E+00 4.50E*02 Ni-65 1.26E&O2 1.64E+01 7.49E&00 0.00E+00 0.00E+00 0.00E&00 4.17E&O2 Cu-64 0.00E*00 8.77E&00 4.12E&00 0.00E+00 2.21E&01 0.00E +00 7.48E&O2 Zn-65 3.36E+03 1.07E+04 4.83E&O3 0.00E+00 7.15E+03 0.00E+00 6.73E+03 Zn-69 7.15E&OO 1.37E+01 9. 51 E-01 0.00E+00 8.89E+00 0.00E&00 2.06E&O0 8r-83 0.00E&00 0.00E+00 4.04E*01 0.00E+00 0.00E&00 0.00E +00 5.82E+01 0.00E +00 0.00E+00 5.24Ee01 0.00E+00 0.00E&00 0.00E&00 4.11E-04 i ) Br-84 Br-05 0.00E&00 0.00E +00 2.15E+00 0.00E+00 0.00E&00 0.00E+00 1.01 E-15 Rb-86 0.00E&OO 1.01E+05 4.71EF04 0.00E&00 0.00E&O0 0.00E+00 1.99E&04 Rb-88 0.00E&O0 2.90E+02 1.54E&O2 0.00E+00 0.00E&00 0.00E+00 4.00E-09 Rb-89 0.00E+00 1.92E+02 1.35E*02 0.00E&00 0.00E+00 0.00E+00 1.12E-11 Sr-89 2.80 E +03 0.00E +00 8.04E+01 0.00E+00 0.00E&00 0.00E+00 4.49E&O2 Sr-90 6.90E&04 0.00E +00 1.69E&O4 0.00E +00 0.00E&00 0.00E&00 1.99E+03 Sr-91 5.16E&01 0.00E+00 2.08E&00 0.00E+00 0.00E&00 0.00E+00 2.46E*02 Sr-92 1.96E&01 0.00E&00 8.46E-01 0.00E+00 0.00E*00 0.00E+00 3.88E*02 Y-90 5.76E-01 0.00E+00 1.54E-02 0.00E +00 0.00E*00 0.00E+00 6.10E+03 Y-91m 5.44E-03 0.00E&OO 2.11E-04 0.00E+00 0.00E&OO 0.00E&00 1.60E-02 Y-91 8.44E&00 0.00E+00 2.26E-01 0.00E+00 0.00E*00 0.00E +00 4.64E+03 Y-92 5.06E-02 0.00E&00 1.48E-03 0.00E&00 0.00EF00 0.00E&00 8.86E&O2 Y-93 1.60E-01 0.00E+00 4.43E-03 0.00E*00 0.00E&00 0.00E+00 5.09 E +03 Zr-95 1.38E&01 4.43E+00 3.00E&00 0.00 E +00 6.96EFOO 0.00E&00 1.41E&O4 Zr-97 7.64E-01 1.54E-01 7.05E-02 0.00E +00 2.33E-01 0.00E+00 4. 78 E +04 Nb-95 6.11 E -01 3.40E-01 1.83E-01 0. 00E +00 3.36E-01 0.00E+00 2. 06E +03 Mo-99 0.00E+00 1.86E+03 3.53E&O2 0.00E +00 4.21E+03 0.00E+00 4.30E+03 Tc -99m 8.87E-03 2. 51 E-02 3.19E-01 0.00E+00 3.81E-01 1.23E-02 1.48E&O1 Tc -101 9.12E-03 1.31E-02 1. 29 E -01 0.00E&00 2. 37 E -01 6.72E-03 3.95E-14 Ru-103 2.04EF00 0.00E+00 8.78E-01 0.00E+00 '7.77E *00 0.00E+00 2.38E+02 Ru -105 1.70E-01 0.00E*00 6.70E-02 0.00E*00 2.19E&OO 0.00E&OO 1.04E*02 i

r s

• Calculated usin9 Equation 11.

HATCH ODCM, REV 1 5/11/84 1.2-7

- ,s TABLE 1.2-3 (SHEET 2 0F 2)

. SITE-RELATED INGESTION DOSE COMMITMENT FACTOR, Aj, (FISH CONSUMPTION)*

(mrem /hr per pCi/ml)

Nuclide Bone Liver T. Body Thyroid Kidney Luno GI-LLI Ru-106 3.03E&01 0.00E+00 3.83E+00 0.00E+00 5.85E+01 0.00E+00 1.96E+03 Ag-110m 1.34E&O2 1.24E+02 7.37E+01 0.00E+00 2.44E+02 0.00E+00 5.06E&O4 Te-125m 2.57E&O3 9.30E+02 3.44E+02 7.72E+02 1.04E&O4 0.00E+00 1.02E+04 Te-127m 6.48E&O3 2.32E+03 7.90E+02 1.66E+03 2.63E*04 0.00E+00 2.17E&O4 Te-127 1.05E+02 3.78E+01 2.28E+01 7.80E+01 4.29E&O2 0.00E+00 8.31E&O3 Te-129m 1.10E+04 4.11 E+03 1.74E&O3 3.78E+03 4.60E+04 0.00E+00 5.54E+04 Te-129 3.01E*01 1.13E+01 7.33E&00 2.31 E+01 1.26E+02 0.00E+00 2.27E+01 Te-131m 1. 66 E +03 8.10E+02 6.75E&O2 1.28E+03 8.21E*03 0.00E+00 8.04E+04 Te-131 1.89E&01 7.88E+00 5.96E+00 1.55E+01 8.26E&O1 0.00E+00 2.67E+00 Te-132 2.41E&O3 1.56E+03 1.47E&O3 1.72E+03 1.50E*04 0.00E&00 7.38E&O4 I-130 7.78E+01 2.30E+02 9.06E&01 1. 95 E +04 3.58E+02 0.00E+00 1.98E+02 1-1 31 4.28E+02 6.13 E +02 3.51E&O2 2.01E+05 1.05E+03 0.00E+00 1.62E&O2 I-132 2.09E+01 5.59E+01 1.96E&01 1.96E+03 8.90E&01 0.00E+00 1.05E+01 I-133 1.46E&O2 2.54E+02 7.75E&01 3.74E+04 4.44E+02 0.00E+00 2.29E&O2 1-134 1.09E+01 2.96E+01 1.06E&01 5.14E+02 4.71E+01 0.00E+00 2.58E-02 I-135 4.56E+01 1.19 E +02 4.41E&01 7.88E+03 1.91E+02 0.00E+00 1.35 E +02 Cs-134 8. 64 E +04 2.06E+05 1.68E+05 0.00E+00 6.65E&04 2.21E+04 3.60E&O3

(') Cs-136 Cs-137 9.04EF03 3.57E+04 2.57E&04 0.00E+00 1.99E+04 2.72E+03 4.05E*03 1.11E&05 1. 51 E+05 9.91E+04 0.00E +00 5.14E&04 1.71E+04 2.93E+03 Cs-138 7.66E+01 1. 51 E+02 7.50E+01 0.00E +00 1.11E&O2 1.10E+01 6.46E-04 Ba-139 1.16E&00 8.27E-04 3.40E-02 0.00E+00 7. 73 E -04 4.69E-04 2.06E&00 Ba-140 2.43E+02 3.05E-01 1.59E+01 0.00E+00 1.04E-01 1. 75 E-01 5.00E+02 8a-141 5.64E-01 4.26E-04 1.90E-02 0.0CE&00 3.96E-04 2.42E-04 2.66E-10 Ba-142 2.55E-01 2.62E-04 1.60E-02 0.00E+00 2.21E-04 1.48E-04 3.59E-19 La-140 1.50E-01 7.54E-02 1.99E-02 0.00E&00 0.00E&OO 0.00E&00 5.54E&O3 La-142 7.66E-03 3.48E-03 ' 8.68E-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&O3 Ce-143 3.32E-01 2.45E&O2 2.71E-02 0.00E+00 1.08E-01 0.00E+00 9.17E&O3 Ce-144 9.81 E&01 4.10E+01 5.27E*00 0.00E+00 2.43E+01 0.00E&00 3.32E&O4 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 8.6lE-01 4.79E-02 0.00E+00 4.68E-01 0.00E+00 3.84E+03 W-187 2.96E&O2 2.47E+02 8.65E&01 0.00E+00 0.00E&00 0.00E+00 8.10E&O4 Np-239 2.85E-02 2.80E-03 1.54E-03 0.00E+00 8.74E-03 0.00E+00 5.75E+02 i

O

• Calculated using Equation 11.

0675n HATCH 00CM, REV 1 5/11/84 1.2-8

~

h,, 1.3 DOSE PROJECTIONS FOR LIQUID EFFLUENTS 1.3.1 Monthly Dose Projections 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:

Otb(prj) " tb(c)\x91

( t j Do(prj) = 00fCI x 91 where:

Dtb(c)

= the cumulative total-body dose for the elapsed portion of the current quarter plus the release under consideration, t = the number of days into the current quarter.

Do (c)

= the cumulative organ doses for the elapsed portion of the 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, this contribution should be included in the equations:

Otb(prj) . [0tb(c))x91 + DPA

( t /

Q U

HATCH ODCM, REV 1 5/11/84 1. 3-1 l

) Do(prj) . D (c) lx 91 + OpA

( t /

where:

OpA = the expected dose due to the particular planned activity.

1.3.2 Dose Projections for Specific Releases Dose projections may be performed for a particular release by performing a prerelease dose calculation, assuming that the planned release will proceed as anticipated. For individual dose projections due to liquid releases, follow the methodology presented in Section 1.2, using sample analysis values for the source to be released and parametric values expected to exist for the release period.

O 0676n O

HATCH 00CM, REV 1 5/11/84 1.3-2

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

Aj, = the site-related ingestion dose commitment factor 1.2 due 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-m1 per hr uC1.

BFj = the bioaccumulation factor for nuclide i, in 1. 2.1 fish, in pCi/kg per pCi/1, f rom Table 1.2-1.

c = the setpoint of the radioactivity monitor which 1.1.1 (3 measures the radioactivity concentration in the ef fluent line prior to dilution and subsequent release.

= the effluent concentration of alpha-emitting 1.1.1 Ca nuclides observed by gross alpha analysis of the MONTHLY composite sample.

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

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

, Cj = the concentration of nuclide i as determined by 1.1.1 the analysis of the waste sample.

HATCH 00CM, REV 1 S/11/84 1. 4 -1

/' Section of

(_)/

. Term Definition Initial Use Cg i = the average concentration of radionuclide i, in 1.2.1 undiluted liquid effluent during time period att, in pCi/ml.

CMPC

= the effluent concentration limit (RETS 3.15.1.1 1.1.1 for Unit 1 and 3.11.1.1 for Unit 2) implementing 10 CFR 20 for the site in pCi/ml.

Cs

= the concentration of Sr-89 or Sr-90 in liquid 1.1.1 wastes as determined by analysis of the QUARTERLY composite sample.

Ct = the measured concentration of H-3 in liquid waste 1.1.1 as determined by analysis of the MONTHLY composite.

D, = the cumulative dose commitment to the total body 1.2.1 O or any organ, v, from the liquid ef fluents for the total time period.

DF = the dilution factor, which is the ratio of the 1.1.1 total dilution flow rate to the effluent stream flow rate (s) required to assure that the limiting concentration of 10 CFR, Part 20, Appendix B.

Table II, Column 2 are met at the point of discharge to the unrestricted area.

DFi , = a dose conversion factor for nuclida 1, for adults 1.2.1 in preselected organ, t, in mrem /pci, from Table 1.2-2.

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

HATCH ODCM, REV 1 5/11/84 1.4-2 4

^

Section of (x Initial Use Term Definition F = the dilution water flow monitor setpoint as 1.1.1 determined prior to the release point, in volume per unit time. (General expression for Equation 1.)

Fd

= the minimum flow rate of the dilution stream used 1.1.1 for setpoint calculations during the time of release.

Fg = the near-field average dilution factor for C ig 1.2.1 during any liquid effluent release.

fp = the effluent flow rate (actual pump value). 1.1.1 ft = the maximum permissible effluent flow rate. 1.1.1 Ko = 1.14 x 105, units conversion factor. 1.2.1 m = the number of liquid releases. 1.2.1 MPCj = MPC g , MPCa , MPCs , MPC f , and MPCs which are 1.1.1 the limiting concentrations of the appropriate gamma-emitting radionuclides, alpha-emitting radionuclides, strratium, iron, and tritium, respectively, from 10 CFR, Part 20, Appendix B, Table II, Column 2.

SF = the safety factor; a conservative factor used to 1.1.1 compensate for statistical fluctuations and errors of measurec:ents.

tc = transit time from release to receptor. 1.2.1 at = the duration of release under consideration. 1.2.1 HATCH 00CM, REV 1 5/11/84 1.4-3

4 Section of

,i Term Definition Initial Use l- UF

= 21 kg/yr, fish consumption (adult). 1.2.1 l Z = the applicable factor when additional receiving 1. 2.1 water body dilution is considered; Z = 10.

8 1

I 1- = the decay constant for radionuclide 1 (sec-1). 1.2.1 3

4 f-i 1 i

J I

4 1

lo j

i l

i 4

1 l

! l l

i 0677n f

4 l HATCH ODCM, REV 1 5/11/84 1.4-4 4

i

l.5 LIQUID RADWASTE TREATMENT SYSTEMS w

Figures 1.5-1 and 1.5-2 are schematics of the liquid radwaste treatment systems for Unit 1 and Unit 2, respectively. The dotted lines indicate alternate pathways through which liquid radwaste may be routed. These alternate routes increase the operational flexibility of the liquid radwaste treatment systems.

O I

I l

i I

0678n HATCH ODCM, REV 1 5/11/84 1.5-1 i

_..-.--,,_-_____._,,_._,.__,_,__.___,_,___,_m..- -

O WASTE OFF STANDARD RECYCLE SURGE e---------7--.----

TANK y ,

I I I I

, OFF STANDARD RECYCLE r- - - - -?- - -- - - - - - - - - - - - - - r -T-. l t

- - - - - - - - II E l I ' '

I I WASTE I TO WASTE , WASTE WASTE  :

I e SAMPLE I CONDENSATE COLLECTOR COLLECTOR DEMIN STORAGE TANK FILTER 4 i; N' TANK a .

TANK g i l l 3 i  ! l 1 g

I I OFF STANDARD RECYCLE '----- dI I r------------i----- <u

'  ! I I

FLOOR FLOOR I FLOOR FLOOR I RADIATION DRAIN DRAIN I DRAIN I DRAIN I MONITOR

- - . FILTER DEMIN +  ; SAMPLE o f COLLECTOR ._

TANK g . TANK I '

l ,

1 I

' TO L- - .J DISCHARGE CANAL V

CHEMICAL CHEMICAL WASTE WASTE -

TANK -

SAMPLE TANK

<r DEMIN FEED TANK LAUNDRY LAUNDRY DRAtN DRAIN TANK FILTER HATCH ODCM, REV 1 5/11/94 LIQUID RADWASTE TREATMENT E DWIN I. HATCH SYSTEM (UNIT 1)

GeorgiaPower NuCtEAR PtANT FIGURE 1.5-1

• • " 1.5-2

]

l c

WASTE OFF STANDARO RECYCLE SURGE TANK 4--_ - . - - -

---g-----===q 8

r '

l '

l '

g e I

• g 1 4 OFF STANDARD RECYCLE I 8 r-+---------------------+--------1 4 I I I

I i

WASTE I WASTE WASTE WWE l C EpsSATE COLLECTOR 4 COLLECTOR d DEMies 4 'ai SAMPLE , STORAGE TANK FILTER ge g TANK

' I TMK 31 l- I e la l I g.

r u _ _ _ _ _ _ _ .4 i i ,

I I I

OFF STANDARO RECYCLE I I l

,. _ - - _. .th_ _ _ _ - _ _ _ _ Jh. -- - - - - '

s

• i I I I l I RAOIATION FLOOR FLOOR . l FLOOR FLOon MONITOR ORAIN DRAIN e. DRAIN * ' '

y , g ORAIN o COLLECTOM d

FILTER DEMIN O SAMPLE g

TANK 8 1 TANK 9 TO 3- - - - - - - d oisCHARGE l CANAL )

CHEMICAL CHEMICAL WASTE WASTE TANK _  ; SAMPLE TANK n

ir CHEMN:AL l WASTE NEUTRALIZER TANK HATCH OOCM, REV 1 5/11/04 l.IQUI0 RADWASTE TREATMENT EDWIN O. HATCH SYSTEM (UNIT 2)

GeorgiaPower NUCLEAR runt FIGURE 1.5-2 was-o 1.5-3

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

Recirculation Times Tank (s) (minutes)

Unit 1 Unit 2 Waste sample tanks 40 40 i Floor drain sample tanks 70 105 Chemical waste sample tanks 65 65 Demin feed tank ,

115 NA

- Laundry drain tanks 50 NA O ,

T 1

s, Os s 0679n HATCH 00CM, REV 1 5/11/84 g 1. 6-1 3

.J

l 2.0 GASEOUS EFFLUENTS O

At Plant Hatch there are four points where radioactivity is released to the atmosphere in gaseous discharges. These four release points are:

. The main stack which serves both units.

. Unit 1 reactor building vent stack.

. Unit 2 reactor building vent stack.

. Unit i recombiner building vent.

The main stack serves as the discharge point for the following release sources from each unit:

. Mechanical vacuum pumps.

. Off-gas system.

. Gland seal exhaust.

. Standby gas treatment system through which drywell purges are discha rged.

l The waste gas treatment building ventilation also discharges through the main stack.

1 Each reactor building vent stack serves as the discharge point for the following (of each respective unit):

. Reactor building.

- Refueling floor ventilation.

- Turbine building.

- Radwaste building.

The Unit I recombiner building vent discharges directly to the atmosphere.

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

HATCH 00CM, REV 1 5/11/84 2.0-1 l

l l

methodology for assuring that the potential organ dose rates due to radioiodines, tritium, and particulates in gaseous releases from the site do i

not exceed the limits of RETS 3.15.2.1(b) fc Unit 1 and 3.11.2.1(b) for J Unit 2 is presented in the note following Section 2.2.1.b.

i l l l

l l

l l

l lO l

l l

l O 0683n HATCH ODCM, REV 1 5/11/84 2.0-2

l l 2.1 GASEOUS EFFLUENT MONITOR SETPOINTS The gaseous monitor setpoint values determined in the following sections will be regarded as upper bounds for the actual setpoint adjustments. That is, setpoint adju3tments are not required to be performed if the existing setpoint level corresponds to a lower count rate than the calculated value.

Setpoints may be established at values lower than the calculated values, if desired.

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

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 circumstances, the number of simultaneous release pathways may be reduced or contributing source terms may be reduced and the setpoint O recalculated.

U 2.1.1 Unit 1 Reactor Building Vent Stack. Unit 2 Reactor Building Vent Stack, and Unit 1 Recombiner Building Vent Monitors: 011-K619 A and B, 2Dll-K636 A and 8, Dil-P003 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 these noble gas monitors will be calculated as follows:

CS

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

O HATCH ODCM, REV 1 5/11/84 2.1 -1

(AG x SF) x Rtv xDT8 (I)

Cs = the lesser of or (AG x SF) x Rsv x Dss (2)

SF = the 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.)

AG = an administrative allocation factor applied to apportion the release setpoints among 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 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 f.

( to 1/n, where: n = the number of simultaneous final gaseous release points. For a more exact determination of allocation factors, see Section 2.1.3.

1

= the dose rate limit to the total body of an individual which is DT8 500 mrem /yr. I 1

Rvt

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

= C + ((X/Q)G I K; QNi. (3) i '

O HATCH ODCM, REV 1 5/11/84 2.1 -2

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

where:

C = the monitor reading of a noble gas monitor corresponding to the grab sample radionuclide concentrations taken in accordance with RETS Tables 4.15.2-1 (Unit 1) and 4.11.2-1

.(Unit 2). The monitor response corresponding to the measured concentration is determined from the monitor calibration I curve for the particular monitor.

(XM)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.

i (X/Q)G

= 6.8 x 10-* sec/ms in the W sector.

l Ki = the total-body dose factor due to gamma emissions from radionuclide 1 (arem/yr per pCi/ms) from Table 2.1-1.

Qiy = the rate of release of noble gas radionuclide 1 (vC1/sec) i from the vent release pathway under consideration, which is

! the product of Xiv and Fv, where: Xiv = the concentration of radionuclide i for the particular release, 4

and Fy = the maximum expected release flow rate for this

release point (Xiy in pCi/ml and Fy in ml/sec).

Dss

= the dose rate limit to the skin of the body of an individual ,

4 in an unrestricted area which is 3000 mrem / year.

4 i Ry5

= the monitor reading per mrem /yr to the skin.

i a

O

HATCH 00CM, REV 1 5/11/84 2.1 -3 d

Ry =

C + ((X/Q)G I (li + l l M 1) Giv) (4) 4

(/i

-. x_ s i

where:

Lj = the skin dose factor due to beta emissions from radio-

. nuclide 1 (mrem /yr per vC1/ms) f rom Table 2.1-1.

1.1 = the mrem skin dose per mrad air dose.

Mj = the air dose factor due to gamma emissions from radio-nuclide 1 (mrad /yr per vC1/m*) f rom Table 2.1-1.

2.1.2 Main Stack Monitor: 011-K600 A and B ,

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

CS

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

(AG x SF) x Rt s xDTB (5)

= the lesser of or (AG x SF) x Rss x Oss (6)

Rs t

=

C+1Vi Qis (7) i O ,

HATCH ODCM, REV 1 5/11/84 2.1 -4

.----,-.,,..~r-..-,e ,,.e,---m-.,-, ,,,.,-..ne,._,n, ,_n-,., e.,,,,,.,. .,.mm.,,,w,,, e , -.nny_,,eg,n,,y-.,

R ss =

C+I (Lj (X/Q)E + 1.1 Bj) Qjs (8) where: ,

Vi = the constant, which includes the dose factor, for each identified noble gas radionuclide accounting for the gama radiation from the elevated finite plume resulting from the main stack release, in mrem /yr per pCi/sec, f rom Table 2.1-2.

Si = the 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 main stack release, in mrad /yr per vCi/sec, f rom Table 2.1-2.

Qis

= the rate of release of noble gas radionuclide i i

(vCi/sec) from the main stack, which is equal to the product of Xis and Fs, where: Xis = the concentration of radionuclide i for the main stack release, and Fs = the maximum expected main stack release flow rate (Xis in pCi/ml and Fs in m1/sec).

1 (X/Q)E = the highest annual average relative concentration in the unrestricted area associated with releases from

. the main stack. The main stack is an elevated release.

= the 1.0 x 10-7 sec/m* in the W sector.

All other terms were identified previously in Section 2.1.1.

O V

j HATCH ODCM, REV 1 S/11/84 2.1 -5

n 2.1.3 Determination of Allocation Factor. AG b

When simultaneous gaseous releases are made to the environment, an (administrative) 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 I reactor building vent stack.

. Unit 2 reactor building vent stack.

. Unit 1 recombiner building 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 determined:

hJ 1. The allocation factor for a particular release pathway may be administratively 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 f rom the particular discharge pathway under consideration to the total-body dose rate due to noble gases in all simultaneous releases.

O HATCH 00CM, REV 1 5/11/84 2.1-6

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

For the main stack:

I vi Qis i AG = 1

+ I (X/0)s I Ki Qiv I vi 013 i n i where: n = the number of simultaneous vent releases.

i For vent releases: '

(X/Q)g I Ki Qiv(r)

AG = 1 IVi i Qs + I (X/0)s I Ki Qv i

i i n where:

i J n = the number of simultaneous vent releases.

N- .

(r) = the particular discharge pathway number for which an allocation factor is being determined.

i 1

4 i

i a

1

O HATCH 00CM, REV 1 5/11/84 2.1 -7 6

TA8LE 2.1-1

() DOSE FACTORS FOR EXPOSURE TO A SEMI-INFINITE CLOUD OF NOBLE GASES

• Nuclide y-Body (K)*** S-Skin (L)*** y-Ai r (M)** 8-Air (N)**

4 Kr-83m 7.56E-02**** --

1.93E+01 2.88E+02 Kr-85m 1.17E+03 1.46E+03 1.23E&O3 1.97E+03 4

Kr-85 1. 61 E+01 1.34E+03 1.72E+01 1.95 E +03 Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 l Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03 Kr-89 1.66E+04 1.01E+04 1.73 E +04 1.06E+04 Kr-90 1.56E+04 7.29E+03 1.63E+04 7.83E+03 i

Xe-131m 9.15E+01 4.76E+02 1.56E+02 1.11 E+03 Xe-133m 2. 51 E+02 9.94 E +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 7.11 E +02 3.36E+03 7.39E+02 Xe-135 1.81E+03 1.86E+03 1.92E+03 2.46E+03 Xe-137 1.42E+03 1.22E+04 1.51E+03 1.27E+04

Xe-138 8.83E+03 4.13E+03 9.21E+03 4.75E+03 i

Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03 0

1 T

I i

• Values taken from Reference 3, Table B-1.

i

• • mrad-m8 pCi-yr i

• • • mrem-m8

pCi-yr

, **** 7.56E 7.56 x 10-2 O

HATCH 00CM, REV 1 5/11/84 2.1 -8

TABLE 2.1-2 DOSE FACTORS FOR EXPOSURE TO DIRECT RADIATION FROM NOBLE GASES IN THE ELEVATED FINITE PLUME *

(Location: Site Boundary in West Sector at 1501 m)

Nuclide Y-BodV (V)** Y-Ai r ( B)***

Kr-85m 6.77E-05 7.13E-05 Kr-85 9.46E-07 1.01E-06 Kr-87 3.59E-04 3.75E-04 Kr-88 9.22E-04 9.58E-04 Kr-89 8.90E-04 9.31E-04 Kr-90 6.39E-04 6.74E-04 Xe-131m 1.41E-06 1.48E-06 Xe-133m 1.54E-05 1.79E-05 Xe-133 1.17E-05 1.21E-05 Xe-135m 1.97E-04 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 O

• 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 Reference 5, Appendix E, Table E.4-7.

• • mrem-sec pCi-yr

• • • mrad-sec pCi-yr

'( ) 0684n HATCH ODCM, REV 1 5/11/84 2.1-9

2.2 GASEOUS EFFLUENT DOSE RATE AND DOSE CALCULATIONS 2.2.1 Unrestricted Area Boundary 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:

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

= I (X/Q)g I Kj Qjy + 1 Vj Q is (9) v i i Os

= the skin dose rate at time of release (arem/yr).

=

I (X/Q)G I (li + I I M 1) Oiv +

I (l i(N)E + llB)Os i i (10) l Terms were defined previously in Section 2.1.1 and 2.1.2.

i The dose rate limits are site limits at any point in time; therefore, dose rates are summed over all releases occurring simultaneously. For Plant Hatch I the three vent releases are:

. Unit 1 reactor building vent stack.

. Unit 2 reactor building vent stack.

• Unit I recombiner building vent.

The only elevated release is the main stack which serves both units.

Simultaneous releases may include any combination of these four release points.

O HATCH ODCM, REV 1 5/11/84 2.2-1

2. 2.1. b Dose Rates Due to Radioiodines, Tritium, and Particulates V

For the purpose of implementing RETS 3.15.2.1.b (Unit 1) and 3.11.2.1.b (Unit 2), organ dose rates due to radioiodines, tritium, and all radioactive materials in particulate form with half-lives greater than 8 d'ays are 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:

Do

= the organ dose rate at time of release (mrem /yr).

= I (X/Q)s I P oi Qiy + (X/Q)EIPjoQjs (11) v i i where:

(X/Q)s = defined in Section 2.1.1.

O (X/Q)E

= defined in Section 2.1.2.

Qiy = the release rate (pC1/sec) of radioiodines, tritium, and particulates (required by RETS 3.15.2.1 (Unit 1) and 3.11.2.1 (Unit 2) from the Unit i reactor building vent stack, the Unit 2 reactor building vent stack, and the Unit 1 recombiner building vent.

Qjs = the release rate (pC1/sec) of radioiodines, tritium, and particulates (required by RETS 3.15.2.1 (Unit 1) and 3.11.2.1 (Unit 2) from the main stack.

Pjo = the organ dose parameter for organ o and radionuclide 1 (mrem /yr per pCi/m') for inhalation determined as follows:

O HATCH 00CM, REV 1 5/11/84 2.2-2

Pjo = K (BR) DFjo (12)

( and where:

K = the constant of unit conversion, 10' pCi/pci.

BR = the breathing rate for child age group (3700 m*/ year) Table 2.2-10, f rom Reference 3.

DFjo = the inhalation pathway dose factor for child age group for organ o and radionuclide 1, Table 2.2-2, from Reference 3.

i.

NOTE: In order to assure that potential dose rates (prerelease) to an organ due to radioiodine, tritium, and particulates in simultaneous gaseous releases from the site do not exceed 1500 mres/yr as specified in RETS 3.15.2.1(b) (Unit 1) and 3.11.2.1(b)

(Unit 2), the potential organ dose rate Do must be limited as follows

Do + ( AG x SF) < 1500 mrem /yr (13) where: AG and SF are assigned the same values as were used in Section 2.1 for the release source pathway under consideration. ,

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

l i

O i

HATCH ODCM, REV 1 5/11/84 2.2-3

r-1~ 2.2.2 Unrestricted Area Air Oose and Dose to Individual sc

. 2.2.2.a Air Oose in Unrestricted Area

< t 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:

I  :

Dy = the air dose due to gamma emissions from noble gas l

l radionuclides (mrad).

', = 3.17 x 10 -* I (X/Q)G IMi Ov i + IBi Osi (14) t .

_V i . .i _

where:

3.17 x 10 8 = the fraction of 1 yr per 1 sec.

4 Qiy = the cumulative release of noble gas radionuclide i over the period of interest (wCi) f rom the vent release under consideration.

r

, Qis = the cumulative release of noble gas radionuclide l 1 over the period of interest (wC1) from the main stack.  !

Mj = defined previously in Section 2.1.1.  !

}

Bi = defined previously in Section 2.1.2.

l (X/Q)G

= defined previously in Section 2.1.1.

I LO l

! HATCH 00CM, REY 1 5/11/84 2.2-4

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

.~

= 3.17 x 10 ~' I (X/Q)g I NjQjy & (X/Q)E I NjQjs (15)

.V i

I .

I where:

Nj = the air dose factor due to beta emissions from noble gas radionuclide 1 (mrad /yr per vC1/m*) from Table 2.1-1.

(X/Q)E

= defined previously in Section 2.1.2.

2.2.2.b Dose to An Individual In Unrestricted Area Dose to an individual from radioiodines, tritium, and radioactive materials in particulate form will be 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 inf ant age group, located in the NNE sector at a distance of 3.2 miles, exposed to inhalation, ground-plane, and grass-cow-milk pathways.

Dj = do e to an organ j of an individual in age group a from radioiodines, tritium, and radionuclides in particulate f' with half-lives greater than 8 days (mrem).

e ~e e ~e

= 3.17 x 10-8 I Raipj [Wyp Qiv + Wsp Qis) (16) pi O

HATCH ODCM, REV 1 5/11/84 2.2-5

~'

where:

r\

V 3.17 x 10-8 = the fraction of l' yr per 1 sec.

Wyp' = the 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 = the annual average relative dispersion parameter for location of controlling (critical) receptor for plant vent releases.

(X7Q')yp applies only to inhalation and all tritium pathways. (For all tritium pathways, the Qj' source term is limited to tritium.)

= 6.1 x 10-7 sec/ma in the NNE sector for inhalation and all tritium pathways.

=

Wyp' (D/Q')yp = the annual average deposition parameter for the location of controlling (critical) recept'or for plant vent releases. (U7Q')yp applies to all other pathways.

= 1.9 x 10-' m-2 in NNE sector for all other pathways.

(

O HATCH 00CM, REV 1 5/11/84 2.2-6

Wsp' = the pathway-dependent relative dispersion

( or deposition in the unrestricted area at the location of the controlling receptor, associated with main stack releases.

(X/Q')sp = the anr.ual average relative dispersion parameter for location of controlling (critical) receptor for main stack releases. (X70')3p applies only to inhalation and all tritium, pathways. (For all tritium pathways, the Qj' source term is limited to tritium.)

= 4.2 x 10-8 sec/m8 in the NNE sector for inhalation and all tritium pathways.

Wsp' (0/Q')3p = the annual average deposition parameter for the location of controlling (critical) receptor for main stack releases. (D7G')sp applies to all other pathways.

- 6.9 x 10-20 m-* in NNE sector for all other pathways.

The selection of the dispersion or deposition parameter, X/0 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-milk pathway. However, since tritium is taken up by vegetation directly f rom surrounding air, X/Q is required for tritium contributions from the grass-cow-milk pathway.

O HATCH 00CM, REV 1 5/11/84 2.2-7

-(\ hjy' = the cumulative release (pCi), from plant vent releases, of radionuclide 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-cow-milk pathway, the Qj' term is limited to tritium.)

his' = the cumulative release (9C1), from the main stack releases, of radionuclide i as required by RETS 3.15.2.3 (Unit 1) and 3.11.2.3 (Unit 2) over the period of intarest. 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. 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.

Raipj = the pathway-specific, individual age-specific organ dose factor for radionuclide i, pathway p, organ j, and individual age group a. Routine individual dose calculations address the inhalation, ground-plane, grass-cow (or goat)-milk, grass-cow-meat, and garden vegetation pathways. However, the dose pathways actually present at the controlling location, as well as the controlling individual age group, are determined through the Land Use Census for the site. Pathway factors Raipj are determined as shown in the following subsections.

O HATCH 00CM, REV 1 5/11/84 2.2-8

As stated earlier, the controlling receptor for Plant Hatch is an infant exposed to inhalation, ground-plane, and grass-cow-milk pathways.

Plant Hatch site-specific values, or appropriate default values, required in the pathway factor determinations for the critical receptor are presented in Table 2.2-12.

Inhalation Pathway Factor Raipj = K'(BR)a (DFAjj)a (mrem /yr per vCi/m*)

where:

K' = the constant of unit conversion, 105 pCi/pci.

(BR)a = the breathing rate for a particular age group, in ms/yr, f rom Table 2.2-10.

O V = the inhalation dose factor for receptor age group a, 0FAi ja organ j, and for radionuclide 1, in mrem /pci, from Tables l 2.2-1 through 2.2-4.

~. -

Ground-Plane Pathway Factor t

Raipj = K'K" (SF')(DFGjj) ((1-e i )fki) g ,, mrem /yr per uCi/sec) where:

K' = the constant of unit conversion, 10* pCi/vC1.

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

l l

O HATCH 00CM, REY 1 5/11/84 2.2-9 l

SF' = the shielding factor. 0.7 (dimensionless).

O DFGjj = the ground-plane dose conversion factor for radionuclide 1 (same for all age groups and specific organs are assumed to receive the same dose as the total body), in mrem /hr per pCi/ma, from Table 2.2-9.

Aj = the decay constant for radionuclide 1.

t = the exposure time, 4.73 x 108 sec (15 yri.

Grass-Cow-Milk Pathway Factor Raipj . gi 0F(Uao) Fm(r)(DFLi j)a + ~ Df s)' g-kjtf (17}

Ai + Aw Yp Ys (m8 mrem /yr per vCi/sec) where:

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

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

Uap = the receptor's milk consumption rate for age group a, in liters /yr, f rom Table 2.2-10.

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

Ys = the agricultural productivity by unit area of stored feed, in kg/ma.

Fm

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

(See Table 2.2-11.)

O HATCH ODCM, REY 1 5/11/84 2.2-10

i r = fraction of deposited activity retained on feed grass

> ~f (1.0 for radioiodines; 0.2 for particulates).

i v (DFli 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.

11

= the decay constant for the ith radionuclide, in sec-5 N = the decay constant for removal of activity on leaf and plant surfaces 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 milk, to receptor, in sec, (1.73 x 105).

th = the transport time from pasture, to harvest, to cow, to milk, to receptor, in sec, (7.78 x 10*).

' O fp = fraction of the year that the cow is on pasture (dimensionless),

f5 = "r . tion of the cow feed that is pasture grass while the cow is on pasture (dimensionless).

For tritium in milk, the grass-cow-milk 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:

Raipj - K'K'"Fm0FU ap(0FLjj)a [0.75(0.5/H)] (mrem /yr per pC1/m8) (10)

where

K'" = a constant of unit conversion,108 gm/kg.

I O

HATCH ODCM, REV 1 5/11/84 2.2-11 l

4

!s  :

l

'N = the absolute humidity of the atmosphere, in ge/m*.

j. -

7 0.75 = .the fraction of total feed that is water. l O.5 ' = the ratio of the specific activity of the feed grass water i- to the atmospheric water.

Other parameters and values as previously defined.

2.2.2.c Dose Calculations To Support Other Specific Technical Specifications f

l In the event radiological impact assessment becomes necessary to implement i RETS 6.9.1.1% 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 f

parameters for the period of the report and the appropriate pathway receptor l dose factors (Raipj)- >

h For the purpose of implementing RETS 3.16.2, dose calculations may be j performed using the equations in Section 2.2.2.c substituting the  ;

i appropriate pathway receptor dose factor (Raipj) and the appropriate l dispersion parameters for the location (s) of interest. Anrual average dispersion parameters may be used for these calculations.

1 The receptor for which dose calculations may be required in order to l l implement RETS 6.9.1.12, 6.9.1.13, or 3.16.2 may not be the previously l 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-cowmilk pathways l 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 ,

j ,

calculating the pathway factors Raipj for these two additional pathways are i presented below. Historically, milk goats have not been present within 5 miles of Plant Hatch. However, in order to facilitate implementation of RETS '

l I 3.16.2 in the event milk goats are located within 5 miles of Plant Hatch, the

) equation for calculating the grass-goat-milk pathway factor is also I

iO  !

HATCH 00CM, REV 1 5/11/84 2.2-12 L  !

(' presented. Plant Hatch site-specific values, or appropriate default values, d required in the pathway factor determinations are presented in Table 2.2-13.

Grass-Cow-Meat Pathway Factor h

Raipj . gi QF(Vao) F f (r)(DFlij)a of s + W o fs)e- e-Ajtf (19)

Ai + Aw Yp Ys (n mrem /yr per pCi/sec) 3 where:

K' = a constant of unit conversion, 105 pCi/pci.

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

Uap = the receptor's meat consumption rate for age group a, in kg/yr, f rom Table 2.2-10.

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

Ys

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

Ff = the stable element transfer coefficients, in days /kg. (See Table 2.2-11.)

r = the fraction of deposited activity retained on feed grass (1.0 for radioiodines; 0.2 for particulates).

(DFLjj)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.

O HATCH 00CM, REV 1 5/11/84 2.2-13

t

, Aj = the decay constant for the ith radionuclide, in sec-1 V

Aw

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

tr = the transport time from pasture to cow, to meat, to receptor, in sec, (1.73 x 10*).

th = the transport time from pasture to harvest, to cow, to meat, to receptor, in sec, (7.78 x 10*).

t fp = fraction of the year that the cow is on pasture (dimensionless).

f5 = fraction of the cow feed that is pasture grass while the cow is on pasture (dimensionless).

For tritium in meat, the grass-cow-meat pathway factor is a special case

/']

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

Raipj =

K'K'"F f0pUap(DFLjj)a (0.75(0.5/H)] (mrem /yr per pCi/m8) (20) where:

K'" = a constant of unit conversion, 108 gm/kg.

l H = absolute humidity of the atmosphere, in gm/m8 l 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.

Other parameters and values are given above.

O b'

HATCH 00CM, REV 1 5/11/84 2.2-14

[

l Vegetation Pathway Factor l

l

-Ajth Raipj . gi r (DFLi j)a Uatf ie-Ajtg + Uas fe g (21)

Yv(Ai + Aw) .

where:

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

Uat

= the consumption rate of fresh leafy vegetation by the receptor in age group a, in kg/yr. (See Table 2.2-10.)

U 45 = the consumption rate of stored vegetation by the receptor in age group a, in kg/yr. (See Table 2.2-10.)

fg = the f raction of the annual intake of f resh leafy vegetation grown locally.

'O the fraction of the annual intake of stored vegetation fg =

grown locally.

tg = the average time between harvest of leafy vegetation and its consumption, in sec, (8.6 x 10*).

th = the average time between harvest of stored vegetation and its consumption, in sec, (5.18 x 105).

Yy = the vegetation areal density, in kg/m*.

(DFLjj)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.

Aj = the decay constant for the ith radionuclide, in sec-1 O

HATCH 00CM, REV 1 5/11/84 2.2-15

4 Kw = the decay constant for removal of activity on leaf and plant surfaces by weathering, 5.7J x 10-7, in sec-1 (corresponding to a 14-day half-life).

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

Raipj = K'K"'(Uat ft + Uasf g) (DFLjj)a [0.75(0.5/H)] (mrem /yr per pCi/m*) (22)

where

l l

K'" = a constant of unit conversion, 108 gs/kg.

I H = absolute humidity of the atmosphere, in gm/m8 l

0.75 = the fraction of total vegetation that is water. l l

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

I Other parameters and values are given above.

Grass-Goat-Milk Pathway Factor Raipj " gi QF(Uap) Fm(r)(DFLjj)a + (I~ID fs)' Ib e-Altf (19)

A1 + Aw Yp Ys (m8 mrem /yr per pC1/sec) where:

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

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

O HATCH ODCM, REV 1 5/11/84 2.2-16

s 3

Uap = the receptor's milk consumption rate for age group a, in liters /yr, f rom Table 2.2-10. '

Yp = the agricultural productivity by unit area of! pas'ture feed ,

4 grass, in kg/ma.

= the agricultural productivity by unit area of stored feed '

Ys in kg/ms. 7 Fm = the stable element transfer.coef ficients, in days / liter. ,

(See Table 2.2-11.) ,

s r - fraction of deposited activit) retained on feed grass (1.0 for radioiodines; 0.2 for particulates).

(

(DFLjj)a = the organ ingestion dose factor for the ith radionuclide for the receptor in age group a, in mrem /pci, f rom Tables '

2.2-5 through 2.2-8.

Aj the decay constant for the ith radionuclide, in sec-1 N = the decay constant for removab.'of activity on leaf and -

plant surfaces by weathering, 5.73 2 10-7, in sec-1 (corresponding to a 14-day half-life).

l l

l I

tr = the transport time from pasture to goat, to milk, to receptor, in sec (1.73 x 105).

th = the transport time from pasture, to harvest, to goat, to milk, to receptor, in sec (7.78 x 10*). i fp = the fraction of the year that the goat is on pasture (dimensionless).

f ,

O HATCH ODCM, REV 1 5/11/84 2.2-17 f

l l

1 f3 = the fraction of the goat feed that is pasture grass while the goat is on pasture (dimensionless).

For tritium in milk, the grass-goat-milk 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:

Raipj =

K'K'"Fm0F U ap(DFlij)a [0.75(0.5/H)] (mrem /yr per pCi/m8) (24) where:

K'" = a constant of unit conversion, 108 gm/kg.

H = absolute humidity of the atmosphere, in gm/m8 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.

O Other parameters and values are given above.

l l

0680n HATCH 00CM, REV 1 5/11/84 2.2-18

(

TABLE 2.2-1 (SHEET 1 0F 3)

O INHALATION DOSE FACTORS FOR INFANT *

(mrem per pCi inhaled)

Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI H-3 No Data 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 C-14 1.89E-05 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 Na-24 7. 54 E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 P-32 1.45E-03 8.03E-05 5.53E-05 No Data No Data No Data 1.15E-05 Cr-51 No Data No Data 6.39E-08 4.llE-08 9.45E-09 9.17E-06 2.55E-07 Mn-54 No Data 1.81E-05 3.56E-06 No Data 3.56E-06 7.14E-04 5.04E-06 Mn-56 No Data 1.10E-09 1.58E-10 No Data 7.86E-10 8.95E-06 5.12E-05 Fe-55 1.41E-05 8.39E-06 2.38E-06 No Data No Data 6.21E-05 7.82E-07 Fe-59 9.69E-06 1.68E-05 6.77E-06 No Data No Data 7.25E-04 1.77E-05 Co-58 No Data 8.71E-07 1.30E-06 No Data No Data 5.55E-04 7.95E-06 Co-60 No Data 5.73E-06 8.41E-06 No Data No Data 3.22E-03 2.28E-05 Ni-63 2.42E-04 1.46E-05 8.29E-06 No Data No Data 1.49E-04 1.73E-06 Ni-65 1.71E-09 2.03E-10 8.79E-ll No Data No Data 5.00E-06 3.58E-05 Cu-64 No Data 1.34E-09 5.53E-10 No Data 2.84E-09 6.64E-06 1. 0 7 E-0' Zn-65 1.382-05 4.47E-05 2.22E-05 No Data 2.32E-05 4.62E-04 3.67E-05 2n-69 3.85E-Il 6.91E-11 5.13E-12 No Data 2.87E-Il 1.05E-06 9.44E-0G Br-83 No Data No Data 2.72E-07 No Data No Data No Data LT E-24 Br-84 No Data No Data 2.86E-07 No Data No Data No Data LT E-24 Br-85 No Data No Data 1.46E-08 No Data No Data No Data LT E-24 Rb-86 No Data 1.36E-04 6.30E-05 No Data No Data No Data 2.17E-06 Rb-88 No Data 3.98E-07 2.05E-07 No Data No Data No Data 2.42E-07 Rb-89 No Data 2.292-07 1.47C-07 No Data No Data No Data 4.87E-08 Sr-89 2.84E-04 No Data 8.15E-06 No Data No Data 1.45E-03 4.57E-05 Sr-90 2.92E-02 No Data 1.85E-03 No Data No Data 8.03E-03 9.36E-05 St-91 6.83E-08 No Data 2.47E-09 No Data No Data 3.76E-05 5.24E-05 Sr-92 7.50E-09 No Data 2.79E-10 No Data No Data 1.70E-05 1.00E-04 Y-90 2.35E-06 No Data 6.30E-08 No Data No Data 1.92E-04 7.43E-05 Y-91M 2.91E-10 No Data 9.90E-12 No Data No Data 1.99E-06 1.68E-06 Y-91 4.20E-04 No Data 1.12E-05 No Data No Data 1.75E-03 5.02E-05 Y-92 1.17E-08 No Data 3.29E-10 No Data No Data 1.75E-05 9.04E-05

• Ref erence 3, Table E-10.

O 1

HATCH 00CM, REV 1 5/11/84 2.2-19 l l

l l

x TABLE 2.2-1 (SHEET 2 0F 3)

/ T

-' INHALATION DOSE FACTORS FOR INFANT *

(mrem per pCi inhaled)

Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI Y-93 1.07E-07 No Data 2.91E-09 No Data Nc Data 5.46E-05 1.19E-04 Zr-95 8.24E-05 1.99E-05 1.45E-05 No Data 2.22E-05 1.2SE-03 1.55E-05 Zr-97 1.07E-07 1.83E-08 8.36E-09 No Data 1.85E-08 7.88E-05 1.00E-04 1

Nb-95 1.12E-05 4.59E-06 2.70E-06 No Data 3.37E-06 3.42E-04 9.05E-06 )

Mo-99 No Data 1.18E-07 2.31E-08 No Data 1.89E-07 9.63E-05 3.48E-05 Tc-99M 9.98E-13 2.06E-12 2.66E-ll No Data 2.22E-Il 5.79E-07 1.45E-06 Tc-101 4.65E-14 5.88E-14 5.80E-13 No Data 6.99E-13 4.17E-07 6.03E-07 Ru-103 1.44E-06 No Data 4.85E-07 No Data 3.03E-06 3.94E-04 1.15E-05 Ru-105 8.74E-10 No Data 2.93E-10 No Data 6.42E-10 1.12E-05 3.46E-05 Ru-106 6.20E-05 No Data 7.77E-06 No Data 7.61E-05 8.26E-03 1.17E-04 Ag-110M 7.13E-06 5.16E-06 3.57E-06 No Data 7.80E-06 2.62E-03 2.36E-05 Te-125M 3.40E-06 1.42E-06 4.70E-07 1.16E-06 No Data 3.19E-04 9.22E-06 Te-127M 1.19E-05 4.93E-06 1.48E-06 3.48E-06 2.68E-05 9.37E-04 1.95E-05 Te-127 1.59E-09 6.81E-10 3.49E-10 1.32E-09 3.47E-09 7.39E-06 1.74E-05 Te-129M 1.01E-05 4.35E-06 1.59E-06 3.91E-06 2.27E-05 1.20E-03 4.93E-05 Te-129 5.63E-11 2.48E-ll 1.34E-ll 4.82E-11 1.25E-10 2.14E-06 1.88E-05 Te-131M 7.62E-08 $.93E-08 2.59E-08 6.38E-08 1.89E-07 1.42E-04 8.51E-05 cm Te-131 1.24E-11 $.87E-12 3.57E-12 1.13E-11 2.85E-ll 1.47E-06 5.87E-06 (s,/ Te-132 2.66E-07 1.69E-07 1.26E-07 1.99E-07 7.39E-07 2.43E-04 3.15E-05 I-130 4.54E-06 9.91E-06 3.7?E-06 1.14E-03 1.09E-05 No Data 1.42E-06 I-131 2.71E-05 3.17E-05 1.40E-05 1.06E-02 3.70E-05 No Data 7.56E-07 I-132 1.21E-06 2.53E-06 8.99E-07 1.21E-04 2.82E-06 No Data 1.36E-06 I-133 9.46E-06 1.37E-05 4.00E-06 2.54E-03 1.60E-05 No Data 1.54E-0C I-134 6.58E-07 1.34E-06 4.75E-07 3.18E-05 1.49E-06 No Data 9.21E-07 I-135 2.76E-06 5.43E-06 1.98E-06 4.97E-04 6.05E-06 No Data 1.31E-06 Cs-134 2.83E-04 5.02E-04 5.32E-05 No Data 1.36E-04 5.69E-05 9.53E-07 Cs-136 3.45E-05 9.61E-05 3.78E-05 No Data 4.03E-05 8.40E-06 1.02E-06 Cs-137 3.92E-04 4.37E-04 3.252-05 No Data 1.23E-04 5.09E-05 9.53E-07 Cs-138 3.61E-07 5.58E-07 2.84E-07 No Data 2.93E-07 4.67E-08 6.26E-07 Ba-139 1.06E-09 7.03E-13 3.07E-11 Nu Data 4.23E-13 4.25E-06 3.64E-05 l Ba-140 4.00E-05 4.00E-08 2.07E-06 No Data 9.59E-09 1.14E-03 2.74E-05 Ba-141 1.12E-10 7.70E-14 3.55E-12 No Data 4.64E-14 2.12E-06 3.39E-06 Ba-142 2.84E-ll 2.36E-14 1.40E-12 No Data 1.36E-14 1.llE-06 4.95E-07 La-140 3.61E-07 1.43E-07 3.68E-08 No Data No Data 1.20E-04 6.06E-05

• Reference 3, Table E-10.

HATCH ODCM, REV 1 5/11/84 2.2-20

TABLE 2.2-1 (SHEET 3 0F 3)

INHALATION DOSE FACTORS FOR INFANT *

(mrem per pCi inhaled) l I

Nuclide Bone Liver T Body Thyroid Kidney Luno CI-LLI La-142 7.36E-10 2.63E-10 6.46E-ll No Data No Data 5.87E-06 4.25E-05 Co-141 1.98E-05 1.19E-05 1.42E-06 No Data 3.75E-06 3.69E-04 1.54E-05 Ce-143 2.09E-07 1.38E-07 1.58E-08 No Data 4.03E-08 8.30E-05 3.55E-05 Ce-144 2.28E-03 3.65E-04 1.26E-04 No Data 3.84E-04 7.03E-03 1.06E-04 Pr-143 1.00E-05 3.74E-06 4.99E-07 No Data 1.41E-06 3.09E-04 2.66E-05 Pr-144 3.42E-ll 1.32E-ll 1.72E-12 No Data 4.80E-12 1.15E-06 3.06E-06 Nd-147 5.67E-06 5.81E-06 3.57E-07 No Data 2.25E-06 2.30E-04 2.23E-05 W-187 9 26E-09 6.44E-09 2.23E-09 No Data No Data 2.83E-05 2.54E-05 Np-239 2.65E-07 2.37E-08 1.34E-08 No Data 4.73E-08 4.25E-05 1.78E-05 O

• Reference 3, Table E-10.

O HATCH ODCM, REV 1 5/11/84 2.2-21

s TABLE 2.2-2 (SHEET 1 0F 3)

' ()

INHALATION DOSE FACTORS FOR CHILD *

(arem per pCi inhaled)

Nuclide Bone Liver T Body Thyroid Kidney Luno GI-LLI H-3 No Data 1 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 C-14 9.70E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 Na-24 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 P-32 7.04E-04 3.09E-05 2.67E-05 No Data No Data No Data 1.14E-05 Cr-51 No Data No Data 4.17E-08 2.31E-08 6.57E-09 4.59E-06 2.93E-07 Mn-54 No Data 1.16E-05 2.57E-06 No Data 2.71E-06 4.26E-04 6.19E-06 Mn-56 No Data 4.48E"10 8.43E-11 No Data 4.52E-10 3.55E-06 3.33E-05 Fe-55 1.28E-05 6.80E-06 2.10E-06 No Data No Data 3.00E-05 7.75E-07 Fe-59 5.59E-06 9.04E-06 4.51E-06 No Data No Data 3.43E-04 1.91E-05 Co-58 No Data 4.79E-07 8.55E-07 No Data No Data 2.99E-04 9.29E-06 Co-60 No Data 3.55E-06 6.12E-06 No Data No Data 1.91E-03 2.60E-05 Ni-63 2.22E-04 1.25E-05 7.56E-06 No Data No Data 7.43E-05 1.71E-06 Ni-65 8.08E-10 7.99E-11 4.44E-ll No Data No Data 2.21E-06 2.27E-05 Cu-64 No Data 5.39E-10 2.90E-10 No Data 1.63E-09 1.59E-06 9.92E-06 Zn-65 1.15E-05 3.06E-05 1.90E-05 No Data 1.93E-05 2.69E-04 4.41E-06 Zn-69 1.81E-ll 2.61E-ll 2.41E-12 No Data 1.58E-11 3.84E-07 2.75E Br-83 No Data No Data 1.28E-07 No Data No Data No Data LT E-24 Br-04 No Data No Data 1.48E-07 No Data No Data No Data LT E-24 Br-85 No Data No Data 6.84E-09 No Data No Data No Data LT E-24 Rb-86 No Data 5.36E-05 3.09E-05 No Data No Data No Data 2.16E-06 Rb-88 No Data 1.52E-07 9.90E-08 No Data No Data No Data 4.66E-09 Rb-89 No Data 9.33E-08 7.83E-08 No Data No Lata No Data 5.11E-10 Sr-89 1.62E-04 No Data 4.66E-06 No Data No Data 5.83E-04 4.52E-05 Sr-90 2.73E-02 No Data 1.74E-03 No Data No Data 3.99E-03 9.28E-05 Sr-91 3.28E-08 No Data 1.24E-09 No Data No Data 1.44E-05 4.70E-05 St-92 3.54E-09 No Data 1.42E-10 No Data No Data 6.49E-06 6.55E-05 Y-90 1.llE-06 No Data 2.99E-08 No Data No Data 7.07E-05 7.24E-05 Y-91M 1.37E-10 No Data 4.98E-12 No Data No Data 7.60E-07 4.64E-07 Y-91 2.47E-04 No Data 6.59E-06 No Data No Data 7.10E-04 4.97E-05 Y-92 5.50E-09 No Data 1.57E-10 No Data No Data 6.46E-06 6.46E-05

• Reference 3, Table E-9.

U(M HATCH ODCM, REV 1 5/11/84 2.2-22

es TABLE 2.2-2 (SHEET 2 0F 3)

U INHALATION DOSE FACTORS FOR CHILD *

(mrem per pCi inhaled)

Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI Y-93 5.04E-08 No Data 1.38E-09 No Data No Data 2.01E-05 1.05E-04 Zr-95 5.13E-05 1.13E-05 1.00E-05 No Data 1.61E-05 6.03E-04 1.65E-05 Zr-97 5.07E-08 7.34E-09 4.32E-09 No Data 1.05E-08 3.06E-05 9.49E-05 Nb-95 6.35E-06 2.48E-06 1.77E-06 No Data 2.33E-06 1.66E-04 1.00E-05 Mo-99 No Data 4.66E-08 1.15E-08 No Data 1.06E-07 3.66E-05 3.42E-05 Tc-99M 4.81E-13 9.41E-13 1.56E-ll No Data 1.37E-11 2.57E-07 1.30E-06 Tc-101 2.19E-14 2.30E-14 2.91E-13 No Data 3.92E-13 1.58E-07 4.41E-09 Ru-103 7.55E-07 No Data 2.90E-07 No Data 1.90E-06 1.79E-04 1.21E-05 Ru-109 4.13E-10 No Data 1.50E-10 No Data 3.63E-10 4.30E-06 2.69E-05 Ru-106 3.68E-05 No Data 4.57E-06 No Data 4.97E-05 3.87E-03 1.16E-04 Ag-110M 4.56E-06 3.08E-06 2.47E-06 No Data 5.74E-06 1.48E-03 2.71E-05 Te-125M 1.82E-06 6.29E-07 2.47E-07 5.20E-07 No Data 1.29E-04 9.13E-06 Te-127M 6.72E-06 2.31E-06 8.16E-07 1.64E-06 1.72E-05 4.00E-04 1.93E-05 Te-127 7.49E-10 2.57E-10 1.65E-10 5.30E-10 1.91E-09 2.71E-06 1.52E-05 Te-129M 5.19E-06 1.85E-06 8.22E-07 1.71E-06 1.36E-05 4.76E-04 4.91E-05 Te-129 2.64E-ll 9.45E-12 6.44E-12 1.93E-ll 6.94E-ll 7.93E-07 6.89E-06 Te-131M 3.63E-08 1.60E-08 1.37E-08 2.64E-08 1.08E-07 5.56E-05 8.32E-05

- Te-131 5.87E-12 2.28E-12 1.78E-12 4.59E-12 1.59E-11 5.55E-07 3.60E-07

- Te-132 1.30E-07 7.36E-08 7.12E-08 8.58E-08 4.79E-07 1.02E-04 3.72E-05 I-130 2.21E-06 4.43E-06 2.28E-06 '4.99E-04 6.61E-06 No Data 1.38E-06 I-131 1.30E-05 1.30E-05 7.37E-06 4.39E-03 2.13E-05 No Data 7.68E-07 I-132 5.72E-07 1.10E-06 5.07E-07 5.23E-05 1.69E-06 No Data 8.65E-07 I-133 4.48E-06 5.49E-06 2.08E-06 1.04E-03 9.13E-06 No Data 1.48E-06 I-134 3.17E-07 5.84E-07 2.69E-07 1.37E-05 8.52E-07 No Data 2.58E-07

~

I-l35 1.33E-06 2.36E-06 1.12E-06 2.14E-04 3.62E-Oo No Data 1.20E-06 Cs-134 1.76E-04 2.74E-04 6.07E-05 No Data 8.93E-05 3.27E-05 1.04E-06 Cs-136 1.76E-05 4.62E-05 3.14E-05 No Data 2.58E-05 3.93E-06 1.13E-06 Cs-137 2.45E-04 2.23E-04 3.47E-05 No Data 7.63E-05 2.81E-05 9.78E-07 Cs-138 1.71E-07 2.27E-07 1.50E-07 No Data 1.68E-07 1.84E-08 7.29E-08 Ba-139 4.98E-10 2.66E-13 1.45E-11 No Data 2.33E-13 1.56E-C6 1.56E-05 Ba-140 2.00E-05 1.75E-08 'l.17E-06 No Data 5.71E-09 4.71E-04 2.75E-05 Ba-141 5.29E-ll 2.95E-14 1.72E-12 No Data 2.56E-14 7.89E-07 7.44E-08 Ba-142 1.35E-ll 9.73E-15 7.54E-13 No Data 7.87E-15 4.44E-07 7.41E-10 La-140 1.74E-07 6.08E-08 2.04E-08 No Data No Data 4.94E-05 6.10E-05

• Reference 3, Table E-9.

HATCH ODCM, REV 1 5/11/84 2.2-23

TABLE 2.2-2 (SHEET 3 0F 3) 7-

\' INHALATION DOSE FACTORS FOR CHILD *

(mrem per pCi inhaled)

Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI La-142 3.50E-10 1.llE-10 3.49E-ll No Data No Data 2.35E-06 2.05E-05 Co-141 1.06E-05 5.28E-06 7.83E-07 NO Data 2.31E-06 1.47E-04 1.53E-05 Ce-143 9.89E-08 5.37E-08 7.77E-09 No Data 2.26E-08 3.12E-05 3.44E-05 Ce-144 1.83E-03 5.72E-04 9.77E-05 No Data 3.17E-04 3.23E-03 1.05E-04 Pr-143 4.99E-06 1.50E-06 2.47E-07 No Data 8.11E-07 1.17E-04 2.63E-05 Pr-144 1.61E-ll 4.99E-12 8.10E-13 No Data 2.64E-12 4.23E-07 5.32E-08 Nd-147 2.92E-06 2.36E-06 1.84E-07 No Data 1.30E-06 8.87E-05 2.22E-05 W-187 4.41E-09 2.61E-09 1.17E-09 No Data No Data 1.llE-05 2.46E-05 Np-239 1.26E-07 9.04E-09 6.35E-09 No Data 2.63E-08 1.57E-05 1.73E-05 O

• Reference 3, Table E-9.

O HATCH ODCM, REV 1 5/11/84 2.2-24

rs TABLE 2.2-3 (SHEET 1 0F 3)

A' ,)

INHALATION DOSE FACTORS FOR TEENAGER *

(mrem per pCi inhaled)

Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI H-3 No Data 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 C-14 3.'25E-06 6.09E-06 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 Na-24 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 P-32 2.36E-04 1.37E-05 8.95E-06 No Data No Data No Data 1.16E-05 Cr-51 No Data No Data 1.69E-08 9.37E-09 3.84E-09 2.62E-06 3.75E-07 Mn-54 No Data 6.39E-06 1.05E-06 No Data 1. 59E-0 6 2.48E-04 8.35E-06 Mn-56 No Data 2.12E-10 3.15E-11 No Data 2.24E-l'0 1 90E-06 7.18E-06 Fe-55 4.18E-06 2.98E-06 6.93E-07 No Data No Data 1.55E-05 7.99E-07 Fe-59 1.99E-06 4.62E-06 1.79E-06 No Data No Data 1.91E-04 2.23E-05 Co-58 No Data 2.59E-07 3.47E-07 No Data No Data 1.68E-04 1.19E-05 Co-60 No Data 1.89E-06 2.48E-06 No Data No Data 1.09E-03 3.24E-05 Ni-63 7.25E-05 5.43E-06 2.47E-06 No Data No Data 3.84E-05 1.77E-06 Ni-65 2.73E-10 3.66E-ll 1.59E-ll No Data No Data 1.17E-06 4.59E-06 Cu-64 No Data 2.54E-10 1.06E-10 No Data 8.01E-10 1.39E-06 7.68E-06 Zn-65 4.82E-06 1.67E-05 7.80E-06 No Data 1.08E-05 1.55E-04 5.83E-06 Zn-69 6.04E-12 1.15E-ll 8.07E-13 No Data 7.53E-12 1.98E-07 3.56E-08 Br-83 No Data No Data 4.30E-08 No Data No Data No Data LT E-24

's jg Br-84 No Data No Data 5.41E-08 No Data No Data No Data LT E-24 x- Br-85 No Data No Data 2.29E-09 No Data No Data No Data LT E-24 Rb-86 No Data 2.38E-05 1.05E-C5 No Data No Data No Data 2.21E-06 Rb-88 No Data 6.82E-08 3.40E-08 No Data No Data No Data 3.65E-15 Rb-89 No Data 4.40E-08 2.91E-08 No Data No Data No Data 4.22E-17 Sr-89 5.43E-05 No Data 1.56E-06 No Data No Data 3.02E-04 4.64E-05 Sr-90 1.353-02 No Data 8.35E-04 No Data No Data 2.06E-03 9.56E-05 Sr-91 .l.10E-08 No Data 4.39E-10 No Data No Data 7.59E-06 3.24E-05 Sr-92 1.19E-09 No Data 5.08E-ll No Data No Data 3.43E-06 1.49F-05 Y-90 3.73E-07 No Data 1.00E-08 No Data No Data 3.66E-05 6.99E-05 Y-91M 4.63E-ll No Data 1.77E-12 No Data No Data 4.00E-07 3.77E-09 Y-91 8.26E-05 No Data 2.21E-06 No Data No Data 3.67E-04 5.11E-0 5 Y-92 1.84E-09 No Data 5.36E-ll No Data No Data 3.35E-06 2.06E-05

• Reference 3, Table E-8.

0\

v HATCH 00CM, REV 1 5/11/84 2.2-25

fx TABLE 2.2-3 (SHEET 2 0F 3)

INHALATION DOSE FACTORS FOR TEENAGER *

(mrem per pCi inhaled)

Nuclide. Bone Liver T Body Thyroid Kidney Luno GI-LLI Y-93 1.69E-08 No Data 4.65E-10 No Data No Data 1.04E-05 7.24E-05 Zr-95 1.82E-05 5.73E-06 3.94E-06 No Data 8.42E-06 3.36E-04 1.86E-05 Zr-97 1.72E-08 3.40E-09 1.57E-09 No Data 5.15E-09 1.62E-05 7.88E-05 Nb-95 2.32E-06 1.29E-06 7.08E-07 No Data 1.25E-06 9.39E-05 1.21E-05 Mo-99 No Data 2.llE-08 4.03E-09 No Data 5.14E-08 1.92E-05 3.36E-05 Tc-99M 1.73E-13 4.83E-13 6.24E-12 No Data 7.20E-12 1.44E-07 7.66E-07 Tc-101 7.40E-15 1.05E-14 1.03E-13 No Data 1.90E-13 8.34E-08 1.09E-16 Ru-103 2.63E-07 No Data 1.12E-07 No Data 9 29E-07 9.79E-05 1.36E-05 Ru-105 1.40E-10 No Data 5.42E-ll No Data 1.76E-10 2.27E-06 1.13E-05 Ru-106 1.23E-05 No Data 1.55E-06 No Data 2.38E-05 2.01E-03 1.20E-04 Ag-110M 1.73E-06 1.64E-06 9.99E-07 No Data 3.13E-06 8.44E-04 3.41E-05 Te-125M 6.10E-07 2.80E-07 8.34E-08 1.75E-07 No Data 6.70E-05 9.3SE-06 Te-127M 2.25E-06 1.02E-06 2.73E-07 5.48E-07 8.17E-06 2.07E-04 1.99E-05 Te-127 2.51E-10 1.14E-10 5.52E-ll 1.77E-10 9.10E-10 1.40E-06 1.01E-05 Te-129M 1.74E-06 8.23E-07 2.81E-07 5.72E-07 6.49E-06 2.47E-04 5.06E-05 Te-129 8.87E-12 4.22E-12 2.20E-12 6.48E-12 3.32E-11 4.12E-07 2.02E-07 Te-131M 1.23E-00 7.51E-09 5.03E-09 9.06E-09 5.49E-08 2.97E-05 7.76E-05

- Te-131 1.97E-12 1.04E-12 6.30E-13 1.55E-12 7.72E-12 2.92E-07 1.89E-09 Te-132 4.50E-08 3.63E-08 2.74E-08 3.07E-08 2.44E-07 5.61E-05 5.79E-05 I-130 7.80E-07 2.24E-06 8.96E-07 1.86E-04 3.44E-06 No Data 1.14E-06 I-131 4.43E-06 6.14E-06 3.30E-06 1.83E-03 1.05E-05 No Data 8.llE-07 I-132 1.99E-07 5.47E-07 1.97E-07 1.89E-05 8.65E-07 No Data 1.59E-07 I-133 1.52E-06 2.56E-06 7.78E-07 3.65E-04 4.49E-06 No Data 1.29E-06 I-134 1.llE-07 2.90E-07 1.05E-07 4.94E-06 4.58E-07 No Data 2.55E-09 I-135 4.62E-07 1.18E-06 4.36E-07 7.76E-05 1.86E-06 No Data 8.69E-07 Cs-134 6.28E-05 1.41E-04 6.86E-05 No Data 4.69E-05 1.83E-05 1.22E-06 Cs-136 6.44E-06 2.42E-05 1.71E-05 No Data 1.38E-05 2.22E-06 1.36E-06 Cs-137 8.38E-05 1.06E-04 3.89E-05 No Data 3.80E-05 1.51E-05 1.06E-06 Cs-138 5.82E-08 1.07E-07 5.58E-08 No Data 8.28E-08 9.84E-09 3.38E-ll Ba-139 1.67E-10 1.18E-13 4.87E-12 No Data 1.llE-13 8.08E-07 8.06E-07 Ba-140 6.84E-06 8.38E-09 4.40E-07 No Data 2.85E-09 2.54E-04 2.86E-05 Ba-141 1.78E-ll 1.32E-14 5.93E-13 No Data 1.23E-14 4.11E-07 9.33E-14 Ba-142 4.62E-12 4.63E-15 2.84E-13 No Data 3.92E-15 2.39E-07 5.99E-20 La-140 5.99E-08 2.95E-08 7.82E-09 No Data No Data 2.68E-05 6.09E-05

• Reference 3, Table E-8.

(

v' HATCH 00CM, REV 1 5/11/84 2.2-26

~_ TABLE 2.2-3 (SHEET 3 0F 3)

\ INHALATION DOSE FACTORS FOR TEENAGER *

(mrem per pCi inhaled)

Nuclide Bone Liver T Body thyroid Kidney Lung GI-LLI La-142 1.20E-10 5.31E-11 1.32E-ll No Data No Data 1.27E-06 1.50E-06 Ce-141 3.55E-06 2.37E-06 2.71E-07 No Data 1.llE-06 7.67E-05 1.58E-05 Ce-143 3.32E-08 2.42E-08 2.70E-09 No Data 1.08E-08 1.63E-05 3.19E-05 Ce-144 6.llE-04 2.53E-04 3.28E-05 No Data 1.51E-04 1.67E-03 1.08E-04 Pr-143 1.67E-06 6.64E-07 8.20E-08 No Data 3.86E-07 6.04E-05 2.67E-05 Pr-144 5.37E-12 2.20E-12 2.72E-13 No Data 1.26E-12 2.19E-07 2.94E-14 Nd-147 9.83E-07 1.07E-06 6.41E-08 No Data 6.28E-07 4.65E-05 2.28E-05 W-187 1.50E-09 1.22E-09 4.29E-10 No Data No Data 5.92C-06 2.21E-05 Np-239 4.23E-08 3.99E-09 2.21E-09 No Data 1.25E-08 8.llE-06 1.65E-05 1

/"'T O

I I

l

• Reference 3, Table E-8.

O HATCH ODCM, REY 1 5/11/84 2.2-27

frs TABLE 2.2-4 (SHEET 1 0F 3)

(N I INHALATION DOSE FACTORS FOR ADULT *

(mrem per pCi inhaled)

Nuclide Bone Liver T Body Thyroid Kidney Lunq__ GI-LLI H-3 No Data 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 C-14 2.27E-06 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 Na-24 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 P-32 1.65E-04 9.64E-06 6.26E-06 No Data No Data No Data 1.08E-05 Cr-51 No Data No Data 1.25E-08 7.44E-09 2.85E-09 1.80E-06 4.15E-07 Mn-54 No Data 4.95E-06 7.87E-07 No Data 1.23E-06 1.75E-04 9.67E-06 Mn-56 No Data 1.55E-10 2.29E-ll No Data 1.63E-10 1.18E-06 2.53E-06 Fe-55 3.07E-06 2.12E-06 4.93E-07 No Data No Data 9.01E-06 7.54E-07 Fe-59 1.47E-06 3.47E-06 1.32E-06 No Data No Data 1.27E-04 2.35E-05 Co-58 No Data 1.98E-07 2.59E-07 No Data No Data 1.16E-04 1.33E-05 Co-60 No Data 1.44E-06 1.85E-06 No Data No Data 7.46E-04 3.56E-05 Ni-63 5.40E-05 3.93E-06 1.E1E-06 No Data No Data 2.23E-05 1.67E-06 Ni-65 1.9 2E-10 2.62E-ll 1.14E-ll No Data No Data 7.00E-07 1.54E-06 Cu-64 No Data 1.83E-10 7.69E-ll No Data 5.73E-10 8.48E-07 6.12E-06 Zn-65 4.05E-06 1.29E-05 5.82E-06 No Data 8.62E-06 1.08E-04 6.68E-06 Zn-69 4.23E-12 8.14E-12 5.65E-13 No Data 5.27E-12 1.15E-07 2.04E-09 Br-83 No Data No Data 3.01E-08 No Data No Data No Data 2.90E-08 Be-84 No Data No Data 3.91E-08 No Data No Data No Data 2.05E-13

. ,_s Br-85 No Data No Data 1.60E-09 No Data No Data No Data LT E-24 Rb-86 No Data 1.69E-05 7.37E-06 No Data No Data No Data 2.08E-06 Rb-88 No Data 4.84E-08 2.41E-08 No Data No Data No Data 4.18E-19 Rb-89 No Data 3.20E-08 2.12E-08 No Data No Data No Data 1.16E-21 Sr-89 3.80E-05 No Data 1.09E-06 No Data No Data 1.75E-04 4.37E-05 1

J St-90 1.24E-02 No Data 7.62E-04 No Data No Data 1.20E-03 9.02E-05 Sr-91 7.74E-09 No Data 3.13E-10 No Data No Data 4.56E-06 2.39E-05 Sr-92 8.43E-10 No Data 3.64E-11 No Data No Data 2.06E-06 5.38E-06 Y-90 2.61E-07 No Data 7.01E-09 No Data No Data 2.12E-05 6.32E-05 Y-91M 3.26E-ll No Data 1.27E-12 No Data No Data 2.40E-07 1.66E-10

Y-91 5.78E-05 No Data 1.55E-06 No Data No Data - 2.13E-04 4.81E-05 4

Y-92 1. 29E-0 9 No Data 3.77E-11 No Data No Data 1.96E-06 9.19E-06 l

l

l

• Reference 3, Table E-7.

O V

HATCH 00CM, REV 1 5/11/84 2.2-28 i

fw TABLE 2.2-4 (SHEET 2 0F 3)

( ') INHALATION DOSE FACTORS FOR ADULT *

(mrem per pCi inhaled)

Nuclide Bone ,

Liver T Body . Thyroid Kidney Lung CI-LLI Y-93 1.18E-08 No Data 3.26E-10 No Data No Data 6.06E-06 5.27E-05 Zr-95 1.34E-05 4.30E-06 2.91E-06 No Data 6.77E-06 2.21E-04 1.88E-05 Zr-97 1.21E-08 2.45E-09 1.13E-09 No Data 3.71E-09 9.84E-06 6.54E-05

- Nb-9 5 1.76E-06 9.77E-07 5.26E-07 No Data 9.67E-07 6.31E-05 1.30E-05 Mo-99 No Data 1.51E-08 2.87E-09 No Data 1.64E-OS 1.14E-05 3.10E-05 Tc-99M 1.29E-13 3.64E-13 4.63E-12 No Data 5.52E-12 9.55E-08 5.20E-07 Tc-101 5.22E-15 7.52E-15 7.38E-14 No Data 1.35E-13 4.99E-08 1.36E-21 Ru-103 1.91E-07 No Data 8.23E-08 No Data 7.29E-07 6.31E-05 1.38E-05 Ru-105 9.88E-ll No Data 3.89E-ll No Data 1.27E-10 1.37E-06 6.02E-06 Ru-106 8.64E-06 No Data 1.09E-06 No Data 1.67E-05 1.17E-03 1.14E-04 Ag-110M 1.35E-06 1.25E-06 7.43E-07 No Data 2.46E-06 5.79E-04 3.78E-05 Te-125M 4.27E-07 1.98E-07 5.84E-08 1.31E-07 1.55E-06 3.92E-05 8.83E-06 Te-127M 1.58E-06 7.21E-07 1.96E-07 4.llE-07 5.72E-06 1.20E-04 1.87E-05 Te-127 1.75E-10 8.03E-ll 3.87E-11 1.32E-10 6.37E-10 8.14E-07 7.17E-06 Te-129M 1.22E-06 5.84E-07 1.98E-07 4.30E-07 4.57E-06 1.45E-04 4.79E-05 Te-129 6.22E-12 2.99E-12 1.55E-12 4.87E-12 2.34E-11 2.42E-07 1.96E-08 Te-131M 8.74E-09 5.45E-09 3.63E-09 6.88E-09 3.86E-08 1.82E-05 6.95E-05

~~ Te-131 1.39E-12 7.44E-13 4.49E-13 1.17E-12 5.46E-12 1.74E-07 2.30E-09

(_ / Te-132 3.25E-08 2.69E-08 2.02E-08 2.37E-08 1.82E-07 3.60E-05 6.37E-05 I-130 5.72E-07 1.68E-06 6.60E-07 1.42E-04 2.61E-06 No Data 9.61E-07 I-131 3.15E-06 4.47E-06 2.56E-06 1.49E-03 7.66E-06 No Data 7.85E-07 I-132 1.45E-07 4.07E-07 1.45E-07 1.43E-05 6.48E-07 No Data 5.08E-08 I-133 1.08E-06 1.85E-06 5.65E-07 2.69E-04 3.23E-06 No Data 1.11E-06 I-134 8.05E-08 2.16E-07 7.69E-08 3.73E-06 3.44E-07 No Data 1.26E-10 I-135 3.35E-07 8.73E-07 3.21E-07 5.60E-05 1.39E-06 No Data 6.56E-07 Cs-134 4.66E-05 1.06E-04 9.10E-05 No Data 3.59E-05 1.22E-05 1.30E-06 Cs-136 4.88E-06 1.83E-05 1.38E-05 No Data 1.07E-05 1.50E-06 1.46E-06 Cs-137 5.98E-05 7.76E-05 5.35E-05 No Data 2.78E-05 9.40E-06 1.05E-06 Cs-138 4.14E-08 7.76E-08 4.05E-08 No Data 6.00E-08 6.07E-09 2.33E-13 Ba-139 1.17E-10 8.32E-14 3.42E-12 No Data 7.78E-14 4.70E-07 1.12E-07 Ba-140 4.88E-06 6.13E-09 3.21E-07 No Data 2.09E-09 1.59E-04 2.73E-05 Ba-141 1.25E-11 9.41E-15 4.20E-13 No Data 8.75E-15 2.42E-07 1.45E-17 Ba-142 3.29E-12 3.38E-15 2.07E-13 No Data 2.86E-15 1.49E-07 1.96E-26 La-140 4.30E-08 2.17E-08 5.73E-09 No Data No Data 1.70E-05 5.73E-05

• Reference 3, Table E-7.

v HATCH 00CM, REV 1 5/11/84 2.2-29

f- TABLE 2.2-4 (SHEET 3 0F 3)

('

INHALATION DOSE FACTORS FOR ADULT *

(mrem per pCi inhaled)

Nuclide Bone Liver T Body Thyroid Kidney Lung CI-LLI La-142 8.54E-ll 3.88E-ll 9.65E-12 No Data No Data 7.91E-07 2.64E-07 Ce-141 2.49E-06 1.69E-06 1.91E-07 No Data 7.83E-07 4.52E-05 1.50E-05 Ce-143 2.33E-08 1.72E-08 1.91E-09 No Data 7.60E-09 9.97E-06 2.83E-05 Ce-144 4.29E-04 1.79E-04 2.30E-05 No Data 1.06E-04 9.72E-04 1.02E-04 Pr-143 1.17E-06 4.69E-07 5.80E-08 No Data 2.70E-07 3.51E-05 2.50E-05 Pr-144 3.76E-12 1.56E-12 1.91E-13 No Data 8.81E-13 1.27E-07 2.69E-18 Nd-147 6.59E-07 7.62E-07 4.56E-08 No Data 4.45E-07 2.76E-05 2.16E-05 W-187 1.06E-09 8.85E-10 3.10E-10 No Data No Data 3.63E-06 1.94E-05 Np-239 2.87E-08 2.82E-09 1.55E-09 No Data 8.75E-09 4.70E-06 1.49E-05

• Reference 3, Table E-7.

HATCH 00CM, REV 1 5/11/84 2.2-30

4

- TABLE 2.2-5 (SHEET -1 0F 3)

INGESTION DOSE FACTORS FOR INFANT *

(mrem per pCi ingested)

Nuclide Bone Liver T Body Thyroid Fidney Lung CI-LLI

. H-3 No Data 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07

, C-14 2.37E-05 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 Na-24 1.01E-05 1. ole-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 P-32 1.70E-03 1.00E-04 6.59E-05 No Data No Data . No Data 2.30E-05 Cr-51 No Data No Data - 1.41E-08 9.20E-09 2.01E-09 1.79E-08 4.llE-07 Mn-54 No Data 1.99E-05 4.51E-06 No Data 4.41E-06 No Data 7.31E-06 Hn-56 No Data 8.18E-07 1.41E-07 No Data 7.03E-07 No Data 7.43E-05 Fe-55 1.39E-05 8.98E-06 2.40E-06 No Data No Data 4.39E-06 1.14E-06 Fe-59 3.08E-05 5.38E-05 2.12E-05 No Data No Data 1.59E-05 2.57E-05 i Co-58 No Data 3.60E-06 8.98E-06 No Data No Data No Data 8.97E-06 Co-60 No Data 1.08E-05 2.55E-05 No Data No Data No Data 2.57E-05 Ni-63 6.34E-04 3.92E-05 2.20E-05 No Data No Data No Data 1.95E-06 8

Ni-65 4.70E-06 5.32E-07 2.42E-07 No Data No Data No Data 4.05E-05 Cu-64 No Data 6.09E-07 2.82E-07 No Data 1.03E-06 No Data 1.25E-05 Zn-65 1.84E-05 6.31E-05 2.91E-05 No Data 3.06E-05 No Data 5.33E-05

• Zn-69 9.33E-08 1.68E-07 1.25E-08 No Data 6.98E-08 No Data 1.37E-05 Br-83 No Data No Data 3.63E-07 No Data No Data No Data LT E-24 4 Br-84 No Data No Data 3.82E-07 No Data No Data No Data LT E-24 i

Be-85 No Data No Data 1.94E-08 No Data No Data No Data LT E-24 Rb-86 No Data 1.70E-04 8.40E-05 No Data No Data No Data 4.35E-06 Rb-88 No Data 4.98E-07 2.73E-07 No Data No Data No Data 4.85E-07 Rb-89 No Data 2.86E-07 1.97E-07 No Data No Data No Data 9.74E-08 Sr-89 2.51E-03 No Data 7.20E-05 No Data No Data No Data 5.16E-05 Sr-90 1.85E-02 No Data 4.71E-03 No Data No Data No Data 2.31E-04 Sr-91 5.00E-05 No Data 1.81E-06 No Data No Data No Data 5.92E-05 Sr-92 1.92E-05 No Data 7.13E-07 No Data No Data No Data 2.07E-04 Y-90 8.69E-08 No Data 2.33E-09 No Data No Data No Data 1.20E-04 Y-91M 8.10E-10 No Data 2.76E-ll No Data No Data No Data 2.70E-06 Y-91 1.13E-06 No Data 3.01E-08 No Data No Data No Data 8.10E-05 Y-92 7.65E-09 No Data 2.15E-10 ao Data No Data No Data 1.46E-04 J

• Ref erence 3, Table E-14.

O HATCH ODCM, REV 1 5/11/84 2.2-31

,-s TABLE 2.2-5 (SHEET 2 0F 3)

\"') INGESTION DOSE FACTORS FOR INFANT *

(mrem per pCi inge5ted)

Nuclide Bone Liver T Body Thyroid Kidney Luno GI-LLI Y-93 2.43E-08 No Data 6.62E-10 No Data No Data No Data 1.92E-04 Zr-95 2.06E-07 5.02E-08 3.56E-08 No Data 5.41E-08 No Data 2.50E-05 Zr-97 1.48E-08 7.54E-09 1.16E-09 No Data 2.56E-09 No Data 1.62E-04 Nb-95 4.20E-08 1.73E-08 1.00E-08 No Data 1.24E-08 No Data 1.46E-05 Mo-99 No Data 3.40E-05 6.63E-06 No Data 5.08E-05 No Data 1.12E-05 Tc-99M 1.92E-09 3.96E-09 5.10E-08 No Data 4.26E-08 2.07E-09 1.15E-06 Tc-101 2.27E-09 2.86E-09 2.83E-08 No Data 3.40E-08 1.56E-09 4.86E-07 Ru-103 1.48E-06 No Data 4.95E-07 No Data 3.08E-06 No Data 1.80E-05 Ru-105 1.36E-07 No Data 4.58E-08' No Data 1.00E-06 No Data 5.41E-05 Ru-106 2.41E-05 No Data 3.01E-06 No Data 2.85E-05 No Data 1.83E-04 Ag-110M 9.96E-07 7.27E-07 4.81E-07 No Data 1.04E-06 No Data 3.77E-05 Te-125M 2.33E-05 7.79E-06 3.15E-06 7.84E-06 No Data No Data 1.llE-05 Te-127M 5.85E-05 1.94E-05 7.08E-06 1.69E-05 1.44E-04 No Data 2.36E-05 Te-127 1.00E-06 3.35E-07 2.15E-07 8.14E-07 2.44E-06 No Data 2.10E-05 Te-129M 1.00E-04 3.43E-05 1.54E-05 3.84E-05 2.50E-04 No Data 5.97E-05 Te-129 2.84E-07 9.79E-08 6.63E-08 2.38E-07 7.07E-07 No Data 2.27E-05 Te-131M 1.52E-05 6.12E-06 5.05E-06 1.24E-05 4.21E-05 No Data 1.03E-04 Te-131 1.76E-07 6.50E-08 4.94E-08 1.57E-07 4.50E-07 No Data 7.llE-06 7-s.

\-

~ Te-132 2.08E-05 1.03E-05 9.61E-06 1.52E-05 6.44E-05 No Data 3.81E-05 I-130 6.00E-06 1.32E-05 5.30E-06 1.48E-03 1.45E-05 No Data 2.83E-06 I-131 3.59E-05 4.23E-05 1.863-05 1.39E-02 4.94E-05 No Data 1.51E-06 I-132 1.66E-06 3.37E-06 1.20E-06 1.58E-04 3.76E-06 No Data 2.73E-06 I-133 1.25E-05 1.82E-05 5.33E-06 3.31E-03 2.14E-05 No Data 3.08E-06 I-134 8.69E-07 1.78E-06 6.33E-07 4.15E-05 1.99E-06 No Data 1.84E-06 I-135 3.64E-06 7.24E-06 2.642-06 6.49E-04 8.07E-06 No Data 2'.62E-06 Cs-134 3.77E-04 7.03E-04 7.10E-05 No Data 1.81E-04 7.42E-05 1.91E-06 Cs-136 4.59E-05 1.35E-04 5.04E-05 No Data 5.38E-05 1.10E-05 2.05E-06 Cs-137 5.22E-04 6.11E-04 4.33E-05 No Data 1.64E-04 6.64E-05 1.91E-06 Cs-138 4.81E-07 7.82E-07 3.79E-07 No Data 3.90E-07 6.09E-08 1.25E-06 Ba-139 8.81E-07 5.84E-10 2.55E-08 No Data 3.51E-10 3.54E-10 5.58E-05

• Reference 3, Table E-14.

HATCH ODCM, REV 1 5/11/84 2.2-32

/" s TABLE 2.2-5 (SHEET 3 0F 3)

U INGESTION DOSE FACTORS FOR INFANT *

(mrem per pC) ingested)

Nuclide Bone Liver ,,T Body Thyroid Kidney Lung GI-LLI Ba-140 'l.71E-04 1.71E-07 8.81E-06 No Data 4.06E-08 1.05E-07 4.20E-05 Ba-141 4.25E-07 2.91E-10 1.34E-08 No Data 1.75E-10 1.77E-10 5.19E-06 Ba-142 1.84E-07 1.53E-10 9.06E-09 No Data 8.81E-ll 9.26E-il 7.59E-07 La-140 2.11E-08 8.32E-09 2.14E+09 No Data No Data No Data 9.77E-05 La-142 1.10E-09 4.04E-10 9.67E-ll No Data No Data No Data 6.86E-05 Ce-141 7.87E-08 4.80E-08 5.65E-09 No~ Data 1.48E-08 No Data 2.48E-05 Ce-143 1.48E-08 9.82E-06 1.12E-09 No Data 2.86E-09 No Data 5.73E-05 Ce-144 2.98E-06 1.22E-06 1.67E-07 No Data 4.93E-07 No Data 1.71E-04 Pr-143 8.13E-08 3.04E-08 4.03E-09 No Data 1.13E-08 No Data 4.29E-05 Pr-144 2.74E-10 1.06E-10 1.38E-ll No Data 3.84E-ll No Data 4.93E-06 Nd-147 5.53E-08 5.68E-08 3.48E-09 No Data 2.19E-08 No Data 3.60E-05 W-187 9.03E-07 6.28E-07 2.17E-07 No Data No Data No Data 3.69E-05 Np-239 1.11E-08 9.93E-10 5.61E-10 No Data 1.98E-09 No Data 2.87E-05 O

1

• Reference 3, Table E-14. .

l l

HATCH ODCM, REV 1 5/11/84 2.2-33 j

\

l

. . . =-- _. . _

l

.> TABLE 2.2-6 (SHEET 1 0F 3)

INGESTION DOSE FACTORS FOR CHILD *

(mrem per pCi inge5ted)

Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI H-3 No Data 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 C-14 1.21E-05 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 Na-24 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 P-32 8.25E-04 3.86E-05 3.18E-05 No Data No Data No Data 2.28E-05 Cr-51 No Data No Data 8.90E-09 4.94E-09 1.35E-09 9.02E-09 4.72E-07 Mn-54 No Data 1.07E-05 2.85E-06 No Data 3.00E-06 No Data 8.98E-06 Mn-56 No Data 3.34E-07 7.54E-08 No Data' 4.04E-07 No Data 4.84E-05 t Fe-55 1.15E-05 6.10E-06 1.89E-06 No Data No Data 3.45E-06 1.13E-06 Fe-59 1.65E-05 2.67E-05 1.33E-05 No Data No Data 7.74E-06 2.78E-05 Co-58 No Data 1.80E-06 5.51E-06 No Data No Data No Data 1.05E-05 Co-60 No Data 5.29E-06 1.56E-05 No Data No Data No Data 2.93E-05 Ni-63 5.38E-04 2.88E-05 1.83E-05 No Data No Data No Data 1.94E-06

Ni-65 2.22E-06 2.09E-07 1.22E-07 No Data No Data No Data 2.56E-05 I

Cu-64 No Data 2.45E-07 1.48E-07 No Data 5.92E-07 No Data- 1.15E-05 Zn-65 1.37E-05 3.65E-05 2.27E-05 No Data 2.30E-05 No Data 6.41E-06 Zn-69 4.38E-08 6.33E-08 5.85E-09 No Data 3.84E-08 No Data 3.99E-06 Br-83. No Data No Data 1.71E-07 No Data No Data No Data LT E-24 Br-84 No Data No Data 1.98E-07 No Data No Data No Data LT E-24 Br-85 No Data No Data 9.12E-09 No Data No Data No Data LT E-24 Rb-86 No Data 6.70E-05 4.12E-05 No Data No Data No Data 4.31E-06 Rb-88 No Data 1.90E-07 1.32E-07 No Data No Data No Data 9.32E-09 I- Rb-89 No Data 1.17E-07 1.04E-07 No Data No Data No Data 1.02E-09

-Sr 1.32E-03 No Data 3.77E-05 No Data No Data No Data 5.llE-05 Sr-90 1.70E-02 No Data 4.31E-03 No Data No Data No Data 2.29E-04 Sr-91. 2.40E-05 No Data 9.06E-07 No Data No Data No Data 5.30E-05 Sr-92 9.03E-06 No Data 3.62E-07 No Data No Data No Data 1.71E-04 Y-90 4.11E-08 No Data 1.10E-09 No Data- No Data No Data 1.17E-04 Y-91M 3.82E-10 No Data 1.39E-11 No Data No Data No Data 7.48E-07 i

Y-91 6.02E-07 No Data 1.61E-08 No Data No Data No Data 8.02E-05 i Y-92 3.60E-09 No Data 1.03E-10 No Data No Data No Data 1.04E-04 l

l l

l

• Ref erence 3, Table E-13.

O HATCH ODCM, REV 1 5/11/84 2.2-34

TABLE 2.2-6 (SHEET 2 0F 3) 4 7.~) INGESTION DOSE FACTORS FOR CHILD *

(mrem per pCi ingested)

Bone Liver T Body Thyroid Kidney Lung GI-LLI Nuclide Y-93 1.14E-08 No Data 3.13E-10 No Data No Data No Data 1.70E-04 Zr-95 1.16E-07 2.55E-08 2.27E-08 No Data 3.65E-08 No Data 2.66E-05 Zr-97 6.99E-09 1.01E-09 5.96E-10 No Data 1.45E-09 No Data 1.53E-04 Nb-95 2.25E-08 8.76E-09 6.26E-09 No Data 8.23E-09 No Data 1.62E-05 Mo-99 No Data 1.33E-05 3.29E-06 No Data 2.84E-05 No Data 1.10E-05 Tc-99M 9.23E-10 1. 81E-09 3.00E-08 No Data 2.63E-08 9.19E-10 1.03E-06 Tc-101 1.07E-09 1.12E-09 1.42E-08 No Data 1.91E-08 5.92E-10 3.56E-09 Ru-103 7.31E-07 No Data 2.81E-07 No Data 1.84E-06 No Data 1.89E-05 Ru-105 6.45E-08 No Data 2.34E-08 No Data 5.67E-07 No Data 4.21E-05 Ru-106 1.17E-05 No Data 1.46E-06 No Data 1.58E-05 No Data 1.82E-04 Ag-110M 5.39E-07 3.64E-07 2.91E-07 No Data 6.78E-07 No Data 4.33E-05 Te-125M 1.14E-05 3.09E-06 1.52E-06 3.20E-06 No Data No Data 1.10E-05 Te-127M 2.89E-05 7.78E-06 3.43E-06 6.91E-06 8.24E-05 No Data 2.34E-05 Te-127 4.71E-07 1.27E-07 1.01E-07 3.26E-07 1.34E-06 No Data 1.84E-05 Te-129M 4.87E-05 1.36E-05 7.56E-06 1.57E-05 1.43E-04 No Data 5.94E-05 Te-129 1.34E-07 3.74E-08 3.18E-08 9.56E-08 3.92E-07 No Data 8.34E-06 Te-131M 7.20E-06 2.49E-06 2.65E-06 5.12E-06 2.41E-05 No Data 1.01E-04 Te-131 8.30E-08 2.53E-08 2.47E-08 6.35E-09 2.51E-07 No Data 4.36E-07 Te-132 1.01E-05 4.47E-06 5.40E-06 6.51E-06 4.15E-05 No Data 4.50E-05 I-130 2.92E-06 5.90E-06 3.04E-06 6.50E-04 8.82E-06 No Data 2. 76E -06 I-131 1.72E-05 1.73E-05 9.83E-06 5.72E-03 2.84E-05 No Data 1.54E-06 I-132 8.00E-07 1.47E-06 6.76E-07 6.82E-05 2.25E-06 No Data 1.73E-06 I-133 5.92E-06 7.32E-06 2.77E-06 1.36E-03 1.22E-05 No Data 2.95E-06 I-134 4.19E-07 7.78E-07 3.58E-07 1.79E-05 1.19E-06 No Data 5.16E-07 I-135 1.75E-06 3.15E-06 1.49E-06 2.79E-04 4.83E-06 No Data 2.40E-06 Cs-134 2.34E-04 3.84E-04 8.10E-05 No Data 1.19E-04 4.27E-05 2.07E-06 Cs-136 2.35E-05 6.46E-05 4.18E-05 No Data 3.44E-05 5.13E-06 2.27E-06 Cs-137 3.27E-04 3.13E-04 4.62E-05 No Data 1.02E-04 3.67E-05 1.96E-06 Cs-138 2.28E-07 3.17E-07 2.01E-07 No Data 2.23E-07 2.40E-08 1.46E-07 Ba-139 4.14E-07 2.21E-10 1.20E-08 No Data 1.93E-10 1.30E-10 2.39E-05 Ba-140 8.31E-05 7.28E-08 4.85E-06 No Data 2.37E-08 4.34E-08 4.21E-05 Ba-141 2.00E-07 1.12E-10 6.51E-09 No Data 9.69E-11 6.58E-10 1.14E-07 Ba-142 8.74E-08 6.29E-11 4.88E-09 No Data 5.09E-11 3.70E-ll 1.14U-09

• Ref erence 3, Table E-13.

O HATCH ODCM, REV 1 5/11/84 2.2-35

' TABLE 2.2-6 (SHEET 3 0F 3)

INGESTION DOSE FACTORS FOR CHILD *

(mrem per pCi ingested)

Nuclide Bone Liver T Body Thyroid Kidney Lung _ CI-LLI La-140 -1.01E-08 3.53E-09 1.19E-09 No Data No Data No Data 9.84E-05 La-142 5.24E-10 1.'67E-10 5.23E-ll No Data No Data No Data 3.31E-05 Ce-141 3.97E-08 1.98E-08 2.94E-09 No Data 8.68E-09 No Data 2.47E-05 Ce-143 6.99E-09 3.79E-06 5.49E-10 No Data 1.59E-39 No Data 5.55E-05 Ce-144 2.0BE-06 6.52E-07 1.llE-07 No Data 3.61E-07 No Data 1.70E-04 Pr-143 3.93E-08 1.18E-08 1.95E-03 No Data 6.39E-09 No Data 4.24E-05 Pr-144 1.29E-10 3.99E-ll 6.49E-12 No Data 2.11E-ll No Data 8.59E-08 Nd-147 2.79E-08 2.26E-08 1.75E-09 No Data 1.24E-08 No Data 3.58E-05 W-187 4.29E-07 2.54E-07 1.14E-07 No Data No Data No Data 3.57E-05 Np-239 5.2SE-09 3.77E-10 2.65E-10 No Data 1.09E-09 No Dats 2. 79E -0 5

• Reference 3, Table E-13.

O HATCH 00CM, REV 1 5/11/84 2.2-36 J

y3 TABLE 2.2-7 (SHEET 1 0F 3) s

' ^ '

/

INGESTION DOSE FACTORS FOR TEENAGER *

(mrem per pCi ingested)

Nuclide Bone Liver T Body Thyroid Kidney Lung CI-LLI H-3 No Data 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 C-14 4.06E-06 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 Na-24 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 P-32 2.76E-04 1.71E-05 1.07E-05 No Data No Data No Data 2.32E-05 Cr-51 No Data No Data 3.60E-09 2.00E-09 7.89E-10 5.14E-09 6.05E-07 Mn-54 No Data 5.90E-06 1.17E-06 No Data 1.76E-06 No Data 1.21E-05 Mn-56 No Da!.a 1.58E-01 2.81E-08 No Data 2.00E-07 No Data 1.04E-05 Fe-55 3.78E-06 2.683-06 6.25E-07 No Data No Data 1.70E-06 1.16E-06 Fe-59 5.87E-06 1.37E-05 5.29E-06 No Data No Data 4.32E-06 3.24E-05 Co-58 No ') ate 9.72E-07 2.24E-06 No Data No Data No Data 1.34E-05 Co-60 No Data 2.81E-06 6.33E-06 No Data No Data No Data 3.66E-05 Ni-63 1.77E-04 1.25E-05 6.00E-06 No Data No Data No Data 1.99E-06 Ni-65 7.49E-07 9.57E-08 4.36E-08 No Data No Data No Data 5.19E-06 Cu-64 No Data 1.15E-07 5.41E-08 No Data 2.91E-07 No Data 8.92E-06 Zn-65 5.76E-06 2.00E-05 9.33E-06 No Data 1.28E-05 No Data 8.47E-06 Zn-69 1.47E-08 2.80E-08 1.96E-09 No Data 1.83E-08 No Data 5.16E-08 No Data No Data 5.74E-08 No Data No Data No Data LT E-24 Br-83 Br-84 No Data No Data 7.22E-08 No Data No Data No Data LT E-24 Br-85 No Data No Data 3.05E-09 No Data No Data No Data LT E-24 Rb-86 No Data 2.98E-05 1.40E-05 No Data No Data No Data 4.41E-06 Rb-88 No Data 8.52E-08 4.54E-08 No Data No Data No Data 7.30E-15 Rb-89 No Data 5.50E-08 3.89E-08 No Data No Data No Data 8.43E-17 St-89 4.40E-04 No Data 1.26E-05 No Data No Data No Data 5.24E-05 Sr-90 8.30E-03 No Data 2.05E-03 No Data No Data No Data 2.33E-04 St-91 8.07E-06 No Data 3.21E-07 No Data No Data No Data 3.66E-05 Sr-92 3.05E-06 No Data 1.30E-07 No Data No Data No Data 7.77E-05 Y-90 1.37E-08 No Data 3.69E-10 No Data No Data No Data 1.13E-04 Y-91M 1.29E-10 No Data 4.93E-12 No Data No Data No Data 6.09E-09 Y-91 2.01E-07 No Data 5.39E-09 No Data No Data No Data 8.24E-05 Y-92 1.21E-09 No Data 3.50E-ll No Data No Data No Data 3.32E-05

• Reference 3, Table E-12.

. O HATCH 00CM, REV 1 5/11/84 2.2-37

TABLE 2.2-7 (SHEET 2 0F 3)

INGESTION DOSE FACTORS FOR TEENAGER *

(mrem per pCi ingested)

Bone Liver T Body Thyroid Kidney Lung GI-LLI Nuclide Y-93 3.83E-09 No Data 1.05E-10 No Data No Data No Data 1.17E-04 Er-95 4.12E-08 1.30E-08 8.94E-09 No Data 1.91E-06 No Data 3.00E-05 Zr-97 2.37E-09 4.69E-10 2.16E-10 No Data 7.llE-10 No Data 1.27E-04 Nb-95 8.22E-09 4.56E-09 2.51E-09 No Data 4.42E-09 No Data 1.95E-05 Mo-99 No Data 6.03E-06 1.15E-06 No Data 1.38E-05 No Data 1.08E-05 Tc-99M 3.32E-10 9.26E-10 1.20E-08 No Data 1.38E-08 5.14E-10 6.08E-07 Tc-101 3.60E-10 5.12E-10 5.03E-09 No Data 9.26E-09 3.12E-10 8.75E-17 Ru-103 2.55E-07 No Data 1.09E-07 No Data 8.99E-07 No Data 2.13E-05 Ru-105 2.18E-08 No Data 8.46E-09 No Data 2.75E-07 No Data 1.76E-05 Ru-106 3.92E-06 No Data 4.94E-07 No Data 7.56E-06 No Data 1.88E-04 Ag-110M 2.05E-07 1.94E-07 1.18E-07 No Data 3.70E-07 No Data 5.45E-05 Te-125M 3.83E-06 1.38E-06 5.12E-07 1.07E-06 No Data No Data 1.13E-05 Te-127M 9.67E-06 3.43E-06 1.15E-06 2.30E-06 3.92E-C5 No Data 2.41E-05 Te-127 1.58E-07 5.60E-08 3.40E-08 1.09E-07 6.40E-07 No Data 1.22E-05 Te-129M~ 1.63E-05 6.05E-06 2.58E-06 5.26E-06 6.82E-05 No Data 6.12E-05 Te-129 4.48E-08 1.67E-08 1.09E-08 3.20E-08 1.88E-07 No Data ~ 2.45E-07 Te-131M 2.44E-06 1.17E-06 9.76E-07 1.76E-06 1.22E-05 No Data 9.39E-05 Te-131 2.79E-08 1.15E-08 8.72E-09 2.15E-08 1.22E-07 No Data 2.29E-09 Te-132 3.49E-06 2.21E-06 2.08E-06 2.33E-06 2.12E-05 No Data- 7.00E-05 I-130 1.03E-06 2.98E-06 1.19E-06 2.43E-04 4.59E-06 No Data 2.29E-06 I-131 5.85E-06 8.19E-06 4.40E-06 2.39E-03 1.41E-05 No Data 1.62E-06 I-132 2.79E-07 7.30E-07 2.62E-07 2.46E-05 1.15E-06 No Data 3.18E-07 I-133 2.01E-06 3.41E-06 1.04E-06 4.76E-04 5.98E-06 No Data 2.58E-06 I-134 1.46E-07 3.87E-07 1.39E-07 6.45E-06 6.10E-07 No Data 5.10E-09 I-135 6.10E-07 1.57E-06 5.82E-07 1.01E-04 2.48E-06 No Data 1.74E-06 Cs-134 8.37E-05 1.97E-04 9.14E-05 No Data 6.26E-05 2.39E-05 2.45E-06 Cs-136 8.59E-06 3.38E-05 2.27E-05 No Data 1.84E-05 2.90E-06 2.72E-06 Cs-137 1.12E-04 1.49E-04 5.19E-05 No Data 5.07E-05 1.97E-05 2.12E-06 Cs-138 7.76E-08 1.49E-07 7.45E-08 No Data 1.10E-07 1.28E-08 6.76E-ll Ps-139 1.39E-07 9.78E-11 4.05E-09 No Data 9.22E-11 6.74E-11 1.24E-06

• Reference 3, Table E-12.

O-V HATCH 00CM, REV 1 5/11/84 2.2-38

( ' TABLE 2.2-7 (SHEET 3 0F 3)

INGESTION DOSE FACTORS FOR TEENAGER *

(mrem per pCi ingested)

Nuclide Bone Liver T Body Thyrold Kidney Lung GI-LLI Ba-140 2.84E-05 3.4SE-08 1.83E-06 No Data 1.18E-08 2.34E-08 4.38E-05 Ba-141 6.71E-08 5. ole-ll 2.24E-09 No Data 4.G5E-11 3.43E-11 1.43E-13 Ba-142 2.99E-08 2.99E-ll 1.84E-09 No Data 2.53E-ll 1.99E-11 9.18E-20 1

La-140 3.48E-09 1.71E-09 4.55E-10 No Data No Data No Data 9.82E-05 La-142 1.79E-10 7.95E-ll 1.98E-ll No Data No Data No Data 2.42E-06 Ce-141 1.33E-08 8.88E-09 1.02E-09 No Data 4.18E-09 No Data 2.54E-05 Ce-143 2.35E-09 1.71E-06 1.91E-10 No Data 7.67E-10 No Data 5.14E-05 Ce-144 6.96E-07 2.88E-07 3.74E-08 No Data 1.72E-07 No Data 1.75E-04 Pr-143 1.21E-08 5.23E-09 6.52E-10 No Data 3.04E-09 No Data 4.31E-05 Pr-144 4.30E-11 1.76E-ll 2.18E-12 No Data 1.01E-11 No Data 4.74E-14 Nd-147 9.38E-09 1.02E-08 6.11E-10 No Data 5.99E-09 No Dats 3.68E-05 W-187 1.46E-07 1.19E-07 4.17E-08 No Data No Data No Data 3.22E-05 Np-239 1.76E-09 1.66E-10 9.22E-11 No Data 5.21E-10 No Data 2.67E-05 1-

-s J

• Ref erence 3, Table E-12.

(::) l l

HATCH ODCM, REV 1 5/11/84 2.2-39 l

r~'s TABLE 2.2-8 (SHEET 1 0F 3) ,

'\s ,)

INGESTION DOSE FACTORS FOR ADULT *

(mrem per pCi ingested)

Nuclide Bone Liver T Body Thyroid Kidney Luno CI-LLI H-3 No Data 1.05E-07 1.05E-07 1.053-07 1.05E-07 1.05E-07 1.05E-07 C-14 2.84E-06 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-C7 Na-24 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 P-32 1.93E-04 1.20E-05 7.469-06 No Data No Data No Data 2.17E-05 Cr-51 No Data de Data 2.66E-09 1.59E-09 5.86E-10 3.53E-09 6.69E-07 Mn-54 No Data 4.57E-06 8.72E-07 No Data 1.36E-06 No Data 1.40E-05 Mn-56 No Data 1.15E-07 2.04E-08 No Data 1.46E-07 No Data 3.67E-06 Fe-55 2.75E-06 1.90E-06 4.43E-07 No Data No Dats 1.06E-06 1.09E-06 Fe-59 4.34E-06 1.02E-05 3.91E-06 No Data No Data 2.85E-06 3.40E-05 Co-58 No Data 7.45E-07 1.67E-06 No Data No Data No Data 1.51E-05 Co-60 No Data 2.14E-06 4.72E-06 No Data no Data No Data 4.02E-05 Ni-63 1.30E-04 9.01E-06 4.36E-06 No Data No Data No Data 1.88E-06 Ni-65 5.28E-07 6.86E-08 3.13E-08 No Data No Data No Data 1.74E-06 Cu-64 No Data 8.33E-08 3.91E-08 No Data 2.10E-07 No Data 7.10E-06 Zn-65 4.84E-06 1.54E-05 6.96E-06 No Data 1.03E-05 No Data 9.70E-06 2n-69 1.03E-08 1.97E-08 1.37E-09 No Data 1.28E-08 No Data 2.96E-09 Br-83 No Data No Data 4.02E-08 No Data No Data No Data 5.79E-08

s Br-84 No Data No Data 5.21E-08 No Data No Data No Data 4.09E-13 No Data No Data 2.14E-09 No Data No Data No Data LT E-24 Br-85 Rb-86 No Data 2.11E-05 9.83E-06 No Data No Data No Data 4.16E-06 Rb-88 No Data 6.05E-08 3. 21E-0 fl No Data No Data No Data 8.36E-19 Rb-89 No Data 4.01E-08 2.82E-08 No Data No Data No Data 2.33E-21 Sr-89 3.08E-04 No Data 8.84E-06 No Data No Data No Data 4.94E-05 Sr-90 7.58E-03 No Data 1.86E-C3 No Data No Data No Data 2.19E-04 Sr-91 5.67E-06 No Data 2.29E-07 No Data No Data No Data 2.70E-05 Sr-92 2.15E-06 No Data 9 30E-08 No Data No Data No Data 4.26E-05 Y-90 9.62E-09 No Data 2.58E-10 No Data No Data No Data 1.02E-04 Y-91M 9.092-11 No Data 3.52E-12 No Data No Data No Data 2.67E-10 Y-91 1.41E-07 No Data 3.77E-09 No Data No Data No Data 7.76E-05 Y-92 8.45E-10 No Data 2.47E-ll No Data No Data No Data 1.48E-05

• Ref erence 3, Table E-11.

f-~ i k -)s s

HATCH 00CM, REV 1 5/11/84 2.2-40 i

i l

1

TABLE 2.2-8 (SHEET 2 0F 3) l s (Q INGESTION DOSE FACTORS FOR ADULT *

(mrem per pCi ingested)

T Body Thyroid Ridney Luno GI-LLI Nuclide_ Bone Liver No Data 8.5CE-05 Y-93 2.68E-09 No Data 7.40E-11 No Data No Data 1.53E-08 No Data 3.09E-05 Zr-95 3.04E-08 9.75E-09 6.60E-09 No Data 5.12E-10 No Data 1.05E-04 Zr-97 1.68E-09 3.39E-10 1.55E-10 No Data 3.42E-09 No Data 2.10E-05 Nb-95 6.22E-09 3.46E-09 1.86E-09 No Data 9.76E-06 No Data 9.99E-06 Mo-99 No Data 4.31E-06 8.20E-07 No Data 4.13E-07 Tc-99M 2.47E-10 6.98E-10 8.89E-09 No Data 1.06E-08 3.42E-10 6.59E-09 1.87E-10 1.10E-21 Tc-101 2.54E-10 3.66E-10 3.59E-09 No Data .7,06E-07 No Data 2.16E-05 Ru-103 1.85E-07 No Data 7.97E-08 No Data 9.42E-06 Ru-105 1.54E-08 No Data 6.08E-09 No Data 1.99E-07 No Data 3.48E-07 No Data 5.31E-06 No Data 1.78E-04 Ru-106 2.75E-06 No Data 2.91E-07 No Data 6.04E-05 Ag-110M 1.60E-07 1.48E-07 8.79E-08 No Data 1.07E-05 Te-125M 2.68E-06 9.71E-07 3.59E-07 8.06E-07 1.09E-05 No Data 2.27E-05 Te-127M 6.77E-06 2.42E-06 8.25E-07 1.73E-06 2.75E-05 4.48E-07 No Data No Data 8.68E-06 Te-127 1.10E-07 3.95E-08 2.38E-08 8.15E-08 5.79E-05 Te-129M 1.15E-05 4.29E-06 1.82E-06 3.95E-06 4.80E-05 No Data 2.37E-08 Te-129 3.14E-08 1.18E-08 7.65E-09 2.41E-08 1.32E-07 No Data 8.40E-05 Te-131M 1.73E-06 8.46E-07 7.05E-07 1.34E-06 8.57E-06 8.63E-08 No Data No Data 2.79C-09

-~ Te-131 1.97E-08 8.23E-09 6.22E-09 1.62E-08 1.57E-05 No Data 7.71E-05 s- Te-132 2.52E-06 1.63E-06 1.53E-06 1.80E-06 3.48E-06 No Data 1.92E-06 I-130 7.56E-07 2.23E-06 8.80E-07 1.89E-04 1.02E-05 No Data 1.57E-06 I-131 4.16E-06 5.95E-06 3.41E-06 1.95E-03 8.65E-07 No Data 1.02E-07 I-132 2.03E-07 5.43E-07 1.90E-07 1.90E-05 4.31E-06 No Data 2.22E-06 I-133 1.42E-06 2.47E-06 7.53E-07 3.63E-04 4.58E-07 No Data 2.51E-10 I-134 1.06E-07 2.88E-07 1.03E-07 4.99E-06 1.86E-06 No Data 1.31E-06 I-135 4.43E-07 1.16E-06 4.28E-07 7.65E-05 4.79E-05 1.59E-05 2.59E-06 Cs-134 6.22E-05 1.48E-04 1.21E-04 No Data 1.43E-05 1.96E-06 2.92E-06 Cs-136 6.51E-06 2.57E-05 1.85E-05 No Data 3.70E-05 1.23E-05 2.llE-06 Cs-137 7.97E-05 1.09E-04 7.14E-05 No Data 8.01E-08 7.91E-09 4.65E-13 Cs-138 5.52E-08 1.09E-07 5.40E-08 No Data 6.46E-11 3.92E-11 1.72E-07 Ba-139 9.70E-08 6.91E-ll 2.84E-09 No Data 8.67E-09 1.46E-08 4.18E-05 Ba-140 2.03E-05 2.55E-08 1.33E-06 No Data 3.31E-ll 2.02E-11 2.22E-17 Ba-141 4.71E-08 3.56E-11 1.59E-09 No Data 1.85E-ll 1.24E-11 3.00E-26 Ba-142 2.13E-08 2.19E-11 1.34E-09 No Data

• Reference 3, Table E-11.

n.

HATCH 00CM, REV 1 5/11/84 2.2-41

. ~ . . . . _ .

8 i

TABLE 2.2-8 (SHEET 3.0F 3)

.O. INGESTION DOSE FACTORS FOR ADULT *

(arem per pCi ingested)

Bone Liver T Body Thyroid Eidney Lung GI-LLI Nuclide La-140 2.50E-09 1.26E-09 3.33E-10 No Data No Data No Data 9.25E-05 i 4.25E-07 La-142 1.28E-10 5.82E-11 l.45E-ll No Data No Data No Data Ce-141 9.36E-09 6.33E-09 7.18E-10 No Data 2.94E-09 No Data 2.42E-05 l 4

Co-143 1.65E-09 1.22E-06 1.35E-10 No Data 3.37E-10 No Data 4.56E-05 Co-144 4.88E-07 2.04E-07 2.62E-08 No Data 1.21E-07 No Data 1.65E-04 Pr-143 9. 20E-09 3.69E-09 4.56E-10 No Data 2.13E-09 No Data 4.03E-05 Pr-144 3.01E-11 1.25E-11 1.53E-12 No Data 7.05E-12 No Data 4.33E-18 Nd-147 6.29E-09 7. 27E-09 4.35E-10 No Data 4.25E-09 No Data 3.49E-05 N-187 1.03E-07 8.61E-08 3.01E-08 No Data No Data No Data 2.82E-05 Np-239 1 19E-09 1.17E-10 6.45E-ll No Data 3.65E-10 No Data 2.40E-05 i

l

. t O

1 4

i i

I I i i

i 1

J l

l l

t

• Ref erence 3, Table E-11.

!O HATCH 00CM, REV 1 5/11/84 2.2-42 1

TABLE 2.2-9 (SHEET 1 0F 2)

EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND *

(mrem /hr per pCi/m2)

Element Total Body Skin H-3 0.0 0.0 C-14 0.0 0.0 NA-24 2.50E-08 2.90E-08 P-32 0.0 0.0 Cr-51 2.20E-10 2.60E-10 Mn-54 5.80E-09 6.80E-09 Mn-56 1.10E-08 1.30E-08 Fe-55 0.0 0.0 Fe-59 8.00E-09 9.40E -09 Co-58 7.00E-09 8.20E-09 Co-60 1.70E-08 2.00E-08 Ni-63 0.0 0.0 Ni-65 3.70E-09 4.30E-09 Cu-64 1.50E-09 1.70E-09 )

Zn-65 4.00E-09 4.60E-09 Zn-69 0.0 0.0

Br-83 6.40E-11 9.30E-11 l ' Br-84 1.20E-08 1.40E-08 l /h Br-85 0.0 0.0 U Rb-86 6.30E-10 7.20E-10 Rb-88 3.50E-09 4.00E-09 Rb-89 1.50E-08 1.80E-08 Sr-89 5.60E-13 6.50E-13 Sr-91 7.10E-09 8.30E-09 Sr-92 9.00E-09 1.00E-08 Y-90 2.20E-12 2.60E-12 Y-91M 3.80E-09 4.40E-09 Y-91 2.40E-11 2.70E-11 Y-92 1.60E-09 1.90E-09 Y-93 5.70E-10 7.80E-10 Zr-95 5.00E-09 5.80E-09 Zr-97 5.50E-09 6.40E-09 Nb-95 5.10E-09 6.00E-09 Mo-99 1.90E-09 2.20E-09 Tc-99M 9.60E-10 1.10E-09 Tc-101 2.70E-09 3.00E-09 Ru-103 3.60E-09 4.20E-09 Ru-105 4.50E-09 5.10E-09

• Reference 3, Table E-6.

O HATCH 00CM, REV 1 5/11/84 2.2-43

I 1

l TA8LE 2.2-9 (SHEET 2 0F 2)

[}

EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND *

(mrem /hr per pCi/ma) l l

Element Total Body Skin Ru-106 1.50E-09 1.80E-09 Ag-110M 1.80E-08 2.10E-08 Te-125M 3. 50E-11 4.80E-11 Te-127M 1.10E-12 1.30E-12 l l

Te-127 1.00E-11 1.10E-11 l Te-129M 7.70E-10 9.00E-10 Te-129 7.10E-10 8.40E-10 Te-131M 8.40E-09 9.90E-09 l Te-131 2.20E-09 2.60E-06 Te-132 1.70E-09 2.00E-09 I-130 1.40E-08 1.70E-08 I-131 2.80E-09 3.40E-09 I-132 1.70E-08 2.00E-08 I-133 3.70E-09 4. 50E -09 I-134 1.60E-08 1.90E-08 I-135 1.20E-08 1.40E-08 Cs-134 1.20E -08 1.40E-08 Cs-136 1.50E-08 1.70E-08

' () Cs-137 Cs-138 4.20E-09 2.10E-06 4.90E-09 2.40E-08 Ba-139 2.40E-09 2.70E-09

Ba-140 2.10E-09 2.40E-09

Ba-141 4.30E-09 4.90E-09

! Ba-142 7.90E-09 9.00E-09 La-140 1.50E-08 1. 70E -08 La-142 1.50E-08 1.80E-08 Ce-141 5.50E-10 6.20E-10 Ce-143 2.20E-09 2.50E-09 Ce-144 3.20E-10 3.70E-10 Pr-143 0.0 0.0 Pr-144 2.00E-10 2.30E-10 Nd-147 1.00E-09 1.20E-09 W-187 3.10E-09 3.60E-09 Np-239 9.50E-10 1.10E-09

• Reference 3, Table E-6.

'O HATCH ODCM, REV 1 5/11/84 2.2-44

f S a

i s

~

TABLE 2.2-10 ss INDIVIOUAL USAGE FACTORS

• Ns Infant Child Teenager Adult p

Milk consumption rate Uap.(liters /yr) 330 330 400 310 Meat consumption rate, Vap (kg/yr) 0 41 65 110 Fresh leafy vegetation consumption rate, Uat (kg/yr) 0 26 42 64 Stored vegetation consumption rate, Uas (kq/yr) 0 ^ 520 > 630 520 Breathing rate 4 8000 (ms /yr) 1405 .'3 7 00 ., 8000

. i.

O l .

1

{

l

.* s

-f +

1 r' \

}

\

1

• Reference 3, Table E-5.

HATCH 00CM, REV 1 5/11/84 2.2-45..

5 6

y

.A,,

TABLE 2.2-11 STABLE ELEMENT TRANSFER DATA

• Fm - Milk Fm - Milk Element (Cow) (Goat) Fr - Meat H 1.0E-02 1.7E-01 1.2E-02 C 1.2E-02 1.0E-01 3.1E-02 Na 4.0E-02 4.0E-02 3.0E-02 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 8.0E-04 Fe 1.2E-03 1.3E-04 4.0E-02 Co 1.0E-03 1.0E-03 1.3E-02 Ni 6.7E-03 6.7E-03 5.3E-02 Cu 1.4E-02 1.3E-02 8.0E-03 Zn 3.9E-02 3.9E-02 3.0E-02 Rb 3.0E-02 3.0E-02 3.1E-02 Sr 8.0E-04 1.4E-02 6.0E-04 Y 1.0E-05 1.0E-05 4.6E-03 Zr 5.0E-06 5.0E-06 3.4E-02 Nb 2.5E-03 2.5E-03 2.8E-01 Mo 7.5E-03 7.5E-03 8.0E-03 Tc 2.5E-02 2.5E-02 4.0E-01 Ru 1.0E-06 1.0E-06 4.0E-01 Rh 1.0E-02 1.0E-02 1.5E-03 O' Ag Te 5.0E-02 1.0E-03 5.0E-02 1.0E-03 1.7E-02 7.7E-02 1 6.0E-03 6.0E-02 2.9E-03 Cs 1.2E-02 3.0E-01 4.0E-03 Ba 4.0E-04 4.0E-04 3.2E 03 La 5.0E-06 5.0E-06 2.0E-04 Ce 1.0E-04 1.0E-04 1.2E-03 Pr 5.0E-06 5.0E-06 4.7E-03 Nd 5.0E-06 5.0E-06 3.3E-03 W 5.0E-04 5.0E-04 1.3E-03 Np 5.0E-06 5.0E-06 2.0E-04

• Reference 3, Table E-1.

O HATCH ODCM, REV 1 5/11/84 2.2-46

TABLE 2.2-12 SITE-SPECIFIC (OR DEFAULT) VALUES TO BE USED IN PATHWAY FACTOR CALCULATIONS

• The critical receptor is an infant exposed to the inhalation, ground-plane, and grass-cow-milk pathways.

Parameter Description Value Inhalation (BR)a Breathing rate for infant 1400 m8/yr (DFA)ija Inhalation dose factor for infant Table 2.2-1 Ground plane SF' Shielding factor due to structure 0.7 (DFG)jj Ground-plane dose factor Table 2.2-9 (same for all age groups)

Grass-Cow-Milk

QF Feed consumption rate for cow 50 kg/ day U ap Milk consumption rate for infant 330 liters /yr (DFL)ija Ingestion dose factor for infant Table 2.2-5 l Yp Pasture grass areal density 0.7 kg/m2 l

Ys Stored feed areal density 2.0 kg/m2 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 atmosphere 8.0 gm/m s l

l l

• Supports Section 2.2.2b.

l O l HATCH ODCM, REV 1 5/11/64 2.2-47

TABLE 2.2-13 (SHEET 1 0F 2)

O(N SITE-SPECIFIC (OR DEFAULT) VALUES TO BE USED IN ADDITIONAL PATHWAY FACTOR CALCULATIONS

• Parameter Description Value Inhalation (BR)a Breathing rate for age group Table 2.2-10 (DFA)gj, Inhalation dose factor for age group Tables 2.2-1 thru 2.2-4 Grass-Cow-Meat QF Feed consumption rate for cow 50 kg/ day U ap Meat consumption rate for age group Table 2.2-10 (DFL)ija Ingestion dose factor for age group Tables 2.2-6 thru 2.2-8 Yp Pasture grass areal density 0.7 kg/m2 Ys Stored feed areal density 2.0 kg/m2 fp Fraction of year that cow grazes on pasture 1.0 l f3 Fraction of total feed that is t pasture grass while cow is on pasture 1.0 H Absolute humidity of the atmosphere 8.0 gm/m3 Garden Vegetation Yy Garden vegetation areal density 2.0 kg/m2 Uat Leafy vegetation consumption rate for age group Table 2.2-10 V as Stored vegetation consumption rate for age group Table 2.2-10

• Supports Section 2.2.2.c.

O HATCH ODCM, REV 1 5/11/84 2.2-48

TABLE 2.2-13 (SHEET 2 0F 2)

SITE-SPECIFIC (OR DEFAULT) VALUES TO BE USED IN ADDITIONAL PATHWAY FACTOR CALCULATIONS

• Parameter Description Value Garden Vegetation (continued) 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 atmosphere 8.0 gm/m*

Grass-Goat-Milk QF Feed consumption rate for goat 6.0 kg/ day Uap Milk consumption rate for age group Table 2.2-10 (DFL)ija Ingestion dose factor for age group Tables 2.2-5 thru 2.2-8 Yp Pasture grass areal density 0.7 kg/m2 Ys Stored feed areal density 2.0 kg/ma 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 the atmosphere 8.0 gm/ms

• Supports Section 2.2.2.c.

0680n HATCH 00CM, REV 1 5/11/84 2.2-49

.%) O 2.3 METEOROLOGICAL MODEL 2.3.1 Atmospheric 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:

. Reactor building vent (Unit 1).

. Reactor building vent (Unit 2).

. 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.

=

2.032 4 Kr I "jk (sec m-8) jk Nujk r Izk where:

2.032 = (2/v)1/2 divided by the number of radians in a 22.5* sector (2w/16).

& = the 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.

HATCH ODCM, REV 1 5/11/84 2.3-1

Kr = the terrain recirculation factor corresponding to a distance r

'L/ taken from Figure 2.3-2.

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

r = the distance from the point of release to the receptor location, in meters.

ujk = the wind speed (mid-point of wind speed class j) at ground level (m sec-1) during atmospheric stability k.

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

1 (o* & b'/2v)*'*

= the lesser of or F ( z) okz

= 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 AT/az

(*C/100 m).

< = 3.1416.

b = the maximum height of the adjacent plant structure (47 m).

C HATCH 00CM, REV 1 5/11/84 2.3-2 I

2.3.1.b Elevated Releases v(^')

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 r I 3 k

jk NUjr ozk where:

ak

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

h = the height of the main stack (120 m).

n = the 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.4-7 of Reference S.

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

N = the total hours of valid 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 Bi and Vi defined in Section 2.1.2 for each identified noble gas radionuclide are calculated using the following:

Bj = K. I I E nik Ati va Et I(rikt mrad /vr rjki N Uj pCi/sec HATCH ODCM, REV 1 5/11/84 2.3-3

Vj = 1.1 K "ik ti "a 1 (rikt exp ( u Td I#VP T ) p"C1/sec rjk1 N Uj where:

K = a numerical constant representing the aggregated numerical constants and unit conversions.

= 2.1 x 10*.

Agj = the number of photons of energy corresponding to the ith energy group emitted per transformation of radionuclide i (number / transformation).

Da

= the energy absorption coefficient in air for photon energy Et (m-1).

Et = the energy assigned to energy group 1 (MeV).

C UT

= the tissue energy absorbtion coefficient for photons of energy Eg (cmagm 1).

Td

= the tissue density thickness taken to represent the total-body dose (5 gm cm-2).

1.1 = an average ratio of the tissue-to-air absorbtion coef ficients over the energy range of interest. The ratio converts dose l

(rad) to dose equivalent (rem).

I(r)kt = the results of numerical integration over the plume spatial distribution of airborne activity; this value is dependent on atmospheric stability, downwind distance, and gamma energy.

O HATCH 00CM, REV 1 5/11/84 2.3-4 i

The aforementioned integral is used in representing the summation of the dose

)

rates from all the points (the concentration within a differential volume element) of a distributed sou ce (plume). For the sector-averaged Gaussian model, the integral is given by:

oo oo Balveva,(L8 + Z2 ) 1'2 ] G(z) exp [ y (L2 + z2)*/2] L dL dz 1

[ L2 + z2 22'2ez f, where:

Bg = the buildup factor.

= 1 - ky (L2 + z2)1'2 y = the total absorbtion coefficient for air (m-L).

k = (p ya)/Va-L = the horizontal distance from the receptor to the differential volume element.

T = the vertical distance from the receptor to-the differential volume element.

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

2

= exp [- (z-h)2/2oz2 ] + exp [-(z+h)2/2oz]

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

O l I

HATCH ODCM, REV 1 5/11/84 2.3-5 l

____---_--__-_____-__-_____-______-___-__-______--_______--_______-______-________-____________\

l A derivation of the model describing the gamma dose rate from a finite

} elevated plume is found in Chapter 7 of Reference 10. Numerical methods for '

evaluating the dose integral 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/0 = the sector-averaged annual average deposition at any distance for a given sector.

2.55 K rak Dn I (m-2) k r N where:

l 2.55 = the inverse of the number of radians in a 22.5* sector

( 2ir/16)-1 Kr = the terrain recirculation factor described in the previous section.

Og = the deposition rate at a given distance taken f rom Figure 2.3-5 for ground-level releases and Figure 2.3-6 for elevated releases.

l l

l nk = the number of hours the wind is directed into the sector of interest for a ground-level release or for an elevated release during which time stability 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.

O 0681n HATCH ODCM, REV 1 5/11/84 2.3-6 l

.s 'No ,

) , , , '

( ,

'~' i / i r

/ /

/ / -

! i ./ fi

/ / / / l

/ / / / , - -

^/l -

r

/ -

- ,/

i 8 1^ s' . ,' s-s' 4[

E . /.7 t/ / ii / i i 1 F !l 5 1 / P'ik#ili /i / 6 6 # 1 iiw 0 / Vif I DV / i V il M ii I E

o

//j/l I/fE[ [ l/ l ll il 7// / / / ,' y /

                                                                                        /

10 l/ - 4 ,' ^ s / /r s'

                                    / i/ i vi i i i l        i i         i e i

i l ,; , si e i i i iiiei

                                                                                                                                        ,l fi f i s t i l              l             i       i i      i      li       !     } i i il!
                                  'Il l l :ll                                              !         ,
                                                                                                                       !         I  lli
                                  /

1 0.1 1.0 to 100 PLUME DISTANCE (KILOMETERS) .O tv i Range of Vertical Range of Vertical Category Temperature Gradient (*C/100 m) Teinperature Gradient (*F/100 f t) A AT/a2 < -1.9 AT < -1.3 B -1.9 5 aT/a2 < -1.7 -1.0 5 ai < -0.9 C -1.7 1 AT/aZ < -1.5 -0.9 5 AT < -0.8 0 -1.5 5 aT/a2 < -0.5 -0.8 5 aT < -0.3 E -0.5 5 AT/aZ < 1.5 -0.3 5 AT < 0.8 F 1.5 5 AT/a2 < 4.0 0.8 5 aT < 2.2 G 4.0 5 AT/aZ 2.2 1 AT

• Reference 8.

HATCH ODCM, REV 1 5/11/84 A l VERTICALSTANQARDDEVIATIONOFMATERIAL IN A PLUME (ozi* (Letters Denote Pasquill

\s)                                        E DVvlN I. H ATCH                                                                g g jjjt gj $$)

Georgia Power NUCLEAR PLANT FIGURE 2.3-1 aos4 2.3-7

(~') V to

                                      .i.;,' , , ,
                           ,    , . .                          ,                   i, I    ! ! l       !!!h               l 4

i I I I itiit i l I I i  ! I i !IIII N l l ! I g ll ll h. c 5 N ss 5 1.o 5 ,  !,,,l,U  ; , (l (> 8 i ;i4 . . , , i i ii i , I  ! ! 6 ititt  !  ! I , t I I Ill  !!I I II i l ll l l l l o.1 o.1 1.0 to too OfSTANCE (KILOMETERS)

• Reference 7.

H ATCH ODCM, R EV 1 5/11/84 OPEN TERRAIN RECIRCULATION O' EDWIN l. HATCH FACTOR

• GeorgiaPower NUCLEAR PLANT FIGURE 2.3-2 aow 2.3-8

i L) 1.0 0.9 w  % 2 2 0.s 0.7 N'N \ 2 2 0.6 \ E N 0.5 \ \s 5 0.4

u. O.3 0.2 Le 0.1 0.1 1.0 10.0 100.0 200.0 PLUME TRAVEL DISTANCE (KILOMETERS)

• Reference 8.

HATCH ODCM, REV 1 5/11/84 p/C EDWIN I. HATCH PLUME DEPLETION EFFECT FOR GROUND-LEVEL RELEASES * (All Atmospheric Stability ClaS5eS) Georgia Power NUCLEAR PLANT FIGURE 2.3-3

   ** "                                        2.3-9

                                                                                                                     ,h-p, l    i

'\u./ 1.0

                                                                    %      NEUTRALtD) 0.9                                      N  m     %
                                                                      %  m\
                                                                         \ \

0.8

                .a                                                      UNsTA8LE      h g   q7 (A.B.C)          N h                           STABL E (E.F.G)                                   h fQ  0.6 NO DEPLETtON

( \

                                                                                                       \

(FRACTION REMAINING = 1.01 \ 3 0.5 \i E 0.4 , \ U I o $ o.2 0.1 0.1 1.0 10.0 100.0 200.0

      ,                                 PLUME TRAVEL DISTANCE (KILOMETERS)

• Reference 8.

H ATCH ODCM, REV 1 5/11/84 h v A Eomu r. HATcw PLUME DEPLETION EFFECT FOR GREATER THAN 100-m RELEASES * (Letters Denote Pasquill Stability Class) G,eorgia Power mA NUCLEAR PLANT FIGURE 2.3-4

        '""                                               2.3-10

                  /"%

w 10 4 k m A N Ng E E w

                                                                                                          %L A

O E ' NN 10 (s E N N 8

                                                                 $                                                                    \

(m )  % t./ 3 K E -5 d .: s a N

                                                                      '10 4                                                                                   ,

x 10'I 10.0 1MO 200.0 0.1 1.0 PLUME TRAVEL DISTANCE (KILOMETERS) l

• Reference 8. I H ATCH OOCM, REV 1 5/11/84

                   ,O                                                                                                  RELATIVE DEPOSITION FOR GROUND-LEVEL RELEASES * (All Atmospheric Stability O                                                                   EDWIN I. HATCH classes)

Georgia Power nuCtEARetAur FIGURE 2.3-5 nos* 2.3-11

,r S b 10 4 UNSTABLE (A,B,C) [ N

                                                                                                                        \ N 10                      ;                                      pQ       (

1 , m . i / I /l * \\ I

                                                                        /                    I              /                     1 \\

g f f NE'UTRAL (D) gg

                                                                      /                                 !/                                N N     %

i ) I/ N T s .

                                              !                  /                                    /                                         N Nb       %

10 4 e _1 r i 8 d I6 I i i

                                              $                1                                                6    4                                  !    6 0               /                              F                   '   i sy a              /     I                       J                         i lE            f       ,                 ,
                                                                                         /          1                I d
                                                                                        )f STABLE (E F,G)

NO DEPLETION 10'I  ; I I I I I f

                                                                          /

10 0.1 1.0 10.0 100.0 200.0 PLUME TRAVEL OtSTANCE (KILOMETERS)

• Reference 8.

HATCH ODCM, REV 1 5/11/84 RELATIVE DEPOSITION FOR GREATER V,O "" THAN 100-m RELEASES * (Letters Georgia Power d EtEIR rY2NT

                                                                                                         "                    oenote Pasquill Stability class)

FIGURE 2.3-6 2505o 2.3-12

2.4 DEFINITIONS OF GASE0US EFFLUENT PARAMETERS .fh a Section of Term Definition Initial Use Agj = the number of photons of energy corresponding to 2.3.1 the tth energy group emitted per transformation of radionuclide 1 (number / transformation). AG = the administrative allocation factor for gaseous 2.1.1 effluent pathways. b = the maximum height of the adjacent building. 2.3.1 Bj = the constant which includes the air dose factor, 2.1. 2 for each identified noble gas radionuclide, accounting for the gamma radiation from an elevated finite plume (mrad /yr per pCi/sec). , Bg = the buildup factor. 2.3.1 C = the monitor reading of a noble gas monitor 2.1.1 corresponding to associated grab sample i radionuclide concentrations. Cs

               = the monitor reading of the noble gas monitor at    2.1.1 the alarm setpoint concentration.

Og = the deposition rate at a given distance taken 2.3.1 f rom Figure 2.3-5 for ground-level releases and Figure 2.3-6 for elevated releases. l l l !O HATCH ODCM, REV 1 5/11/84 2. 4-1

Section of p Term Definition Initial Use 'Q Dj = the dose to an organ of individual from 2.2.2.b radioiodines, tritium, and radionuclides in particulate form with half-lives greater than 8 days (mrem). Do = the organ dose rate at time of release (mrem /yr). 2.2.1.b l Ds

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

Dss = the limiting dose rate to the skin of the body of 2.1.1 an individual in an unrestricted area which is 3000 mrem /yr. Dt = the total body dose rate at time of release 2.2.1.a (mrem /yr) . DTB

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

Og = the air dose due to beta emissions from noble 2.2.2.a i gases (mrad). 1 Dr = the air dose due to gama emissions from noble 2.2.2.a gases (mrad). D/0 = the sector-averaged relative deposition for any 2.3.2  : distance in a given sector. (D77)yp = the annual average deposition parameter for the 2.2.2.b location of controlling (critical) receptor for i I plant vent releases. O HATCH 00CM, REV 1 5/11/84 2.4-2

l Section of Term Definition Initial Use (D/Q')yp = 1.9 x 10

• m-2 in the NNE sector. 2.2.2.b (D/Q')sp = the annual average deposition parameter for the 2.2.2.b location of controlling (critical) receptor for main stack releases.

             =  6.9 x 10-10 m-2 in the NNE sector.                  2.2.2.b Et         =  the energy assigned to energy group 1 (MeV).        2.3.1 h          =  the elevated release height (meters).               2.3.1 I(r)kg   =   the results of numerical integration over the        2.2.1 spatial distribution of an elevated finite plume.

, 6 = the plume depletion factor for all radionuclides 2.3.1 ( other than noble gases at distance r. 4k

             =  the plume depletion factor for all radionuclides    2.3.1 other than noble gases at a distance r for the appropriate stability class k (radioiodines and particulates).

s K = a constant associated with the Kj and Vj calcu- 2.3.1 lation representing a combination of constants and unit conversions. Ki = the total body dose factor due to gamma emissions 2.1.1 from radionuclide 1 (mrem /yr per uCi/ms) f rom Table 2.1-1. O HATCH 00CM, REV 1 5/11/84 2.4-3

Section of .C v Ters' Definition Initial Use Kr = the terrain recirculation factor. 2.3.1 L = the horizontal distance from the ground-level 2.1.1 receptor to the volume element considered as a point source in the evaluation of I(r)kt-Lj = the skin dose factor due to beta emissions from 2.1.1 radionuclide 1 (mrem /yr per pCi/ms) from Table 2.1-1. Mi

           =   the air dose factor due to gamma emissions from       2.1.1 radionuclide 1 (mrad /yr per pCi/ms) from Table 2.1-1.

n = the number of hours the wind of wind speed class j 2.3.1 is directed into the given sector during the existence of atmospheric stability class k. Nj = the air dose factor due to beta emissions f rom 2.2.2.a noble gas radionuclide 1 (mrad /yr per uti/ms) f rom Table 2.1-1. njk = the number of hours meteorological conditions 2.3.1 are observed to be in a given wind direction, windspeed class j, and atmospheric stability class k. N = the total hours of valid meteorological data. 2.3.1 Pjo = the dose parameter for radionuclide i (mrem /yr per 2.2.1.b pCi/ms) for the inhalation pathway. O HATCH 00CM, REV 1 5/11/84 2.4-4

Section of [ Term Definition Initial Use Qiy = the rate of release of noble gas radionuclide i 2.1.1 (vCi/sec) from the vent release pathway under consideration. Qg3 = the rate of release of noble gas radionuclide i 2.1. 2 (vC1/sec) from the main stack. Qiv = the cumulative release of noble gas radionuclide i 2.2.2.a over the period of interest (pCi) f rom the vent release under consideration. 4 $ Qis = the cumulative release of noble gas radionuclide i 2.2.2.a i over the period of interest (vCi) from the main stack. ) Qiv' = the cumulative release of radioiodine, tritium, or 2.2.2.b material in particulate form f rom plant vent releases over the period of interest (uci). I I 61s' = the cumulative release of radioiodine, tritium, or 2.2.2.b material in particulate form from the main stack i over the period of interest (pC1). I r = the distance from the point of release to the 2.3.1 receptor of interest for dispersion calculations (meters). 4 Raipj = the pathway-specific, individual age-specific 2.2.2.b organ dose factor for radionuclide 1, pathway p, organ j, and age group a (mrem /yr per pCi/ms) or (ma-mrem /yr per pCi/sec). 1 4 O HATCH ODCM, REV 1 5/11/84 2.4-5 -i

Section of Tam Definition Initial Use Rsv

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

Rss

               =   the monitor reading per mrem /yr to the skin for    2.1.1 stack releases.

Rv t

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

Rst

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

Ej = the vertical standard deviation of the plume with 2.3.1 building wake correction. I zk = the vertical standard deviation of the plume 2.3.1

 \)                concentration distribution considering the initial dispersion within the building wake.

ckz

               =   the vertical standard deviation of the plume        2.3.1 (meters) for a given distance for ground-level releases under the stability category k indicated by AT/az, f rom Figure 2.3-1.

AT/az = the vertical temperature gradient used to 2.3.1 determine the atmospheric stability category ('C/100 m or 'F/100 ft). Td

               =   the tissue density thickness taken to represent     2.1.1 the total body dose (5 gm cm-2).

O HATCH ODCM, REV 1 5/11/84 2.4-6

Section of J Term Definition initial Use v = the total absorbtion coef ficient for air (m-1). 2.3.1 wa

            =   the energy absorbtion coef ficient for air (m-1). 2.3.1
            =   the tissue energy absorbtion coefficient for        2.3.1 "T

photons of energy Eg (cm8gm-1).

            =   the wind speed (midpoint of windspeed class j)      2.3.1 u) at the height of release, h.

ujk

            =   the wind speed (midpoint of windspeed class j)      2.3.1 at ground level (m/sec) during atmospheric stability class k.

U jk

            =   the wind speed (midpcint of windspeed class j)      2.3.1 at the height of release, h, of an elevated release during atmospheric stability class k.

Vi = a constant, which includes the dose factor, for 2.1.2 each identified noble gas radionuclide accounting for the gamma radiation from the elevated finite plume resulting from the main stack release (mrem /yr per pCi/sec) f rom Table 2.1-2. Wyp' = the pathway-dependent relative dispersion or 2.2.2.b deposition in the unrestricted area at the location of the controlling receptor associated with plant vent releases. l G O HATCH ODCM, REV 1 5/11/84 2.4-7

Section of n Initial Use g- Term Definition Ws p ' - = the pathway-dependent relative dispersion or 2.2.2.b deposition in the unrestricted area at the location of the controlling receptor associated with stack releases. X/Q = the sector-averaged annual average relative 2.3.1 concentration at any distance in the given sector.

               =  the highest annual average relative concentration          2.1.1 DQG at the site boundary when considering ground-level releases.
     'X3G      =   6.8 x 10-* sec/m8 in the W sector.
               =   the highest annual average relative concentration          2.1.1 X/QE in the unrestricted area associated with releases from the main stack.

X/QE

                =  1.0 x 10-7 sec/ms in the W sector.

(X74'),p = the annual average relative dispersion parameter 2.2.2.b l for the location of the controlling receptor for plant vent releases. (X/Q')yp

                =  6.1 x 10-7 sec/m* in the NNE sector.

(X/Q')3p = the annual average relative dispersion parameter 2.2.2.b for the location of the controlling receptor for main stack releases. (X/Q')3p = 4.2 x 10-8 sec/m* in the NNr sector. 2.2.2.b O HATCH 00CM, REV 1 5/11/84 2. 4 -8 i

4

 +

1 Section of Term Definition jnitial Use i a z = the vertical distance from a ground-level receptor 2.3.1 t-

- to the volume element considered as a point source- .

i 4 j in the evaluation of I(r)kt. 4 4' 4 1 i J 1 4 i ! ) !O i l s ! l 1 i I I }  ! t { i t 1 j i j i IO 0685n HATCH 00CM, REV 1 5/11/84 2.4-9 4 4

2.5 GASEOUS RA0 WASTE TREATMENT SYSTEM i Figure 2.5-1 is a schematic of the condenser offgas treat.i.ent system showing the release points to unrestricted areas. This schematic is representative of Unit 1 and Unit 2. i l O I l 0686n HATCH 00CH, etEV 1 5/11/84 2.5-1

[ v FROM CONDENSER f

                 ~

IST STAGE EJECTOR IST STAGE INTERCONDENSER 2NO ST AGE EJECTOR 2N0 STAGE INTERCONDENSER h P-d 3RO STAGE EJECTOR I u OFFGAS REME Alf R CATALYTIC RECOMetNE R Ii ) OFFGAS CONOENSE R RA06ATION MONITOR hI WATER SEPAR ATOR I

                         -dVWV HOLOUP LINE V

COOLER CONDENSE R I } O l s r

                                      -          )       '

H (,, MOISTURE STRIP SEPARATOR HEATER Y CHARCOAL CHARCOAL FILTE RS l FILTERS (GPLACES) (G PL ACESI .... RAOIATION y MONITOR Y FROM STANOSY GAS 1

                                                              /    AFTER        RADIATION                                 TREATMENT FILTER       MONITOR                            d      SYSTEM s                       STACK              p g, GLAND SEAL SYSTEM l

l HATCH OOCM, REV 6 :/t1/34 l CONDENSER OFFGAS TREATMENT EDWIN 1. HATCH SYSTEM Georgia Power NUCtEAR runt FIGURE 2.5-1 2.5-2

v 3.0 RADIOLOGICALE5VIRONMENTALMONITORINGP'ROGRAM m-- Sampling locations._as required by RETS 4.16.1 are discribed in Table 3.0-1 ' and shown on maps $1n Figures 3.0-1 and 3.0-2. There are no known drinking water users downstream of Plant Hatch. 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 s 10 CFR Part 50 that the licensee " Identify cnanges in the use of unrestricted areas (e.g., for agricultural purposes) to permit modifications in monitoring programs for evaluating doses to individuals f rom-principal pathways of exposure." The consumption of milk from animals grazing on contaminated pasture and the consumption of vegetation t.ontaminated_by airborne radiciodine are major potentiqrsources of exposure. Samples from milk animals are considered a bette'r -indicator of radiciodine in the environment than vegetation. Because sufficient milk samples frequently are not available within 5 miles, vegetation samples will be collect'ed also. , Grass is available almost year.-round,whereas leafy vegetaticn is available only for 8 months of the year at best. The sampling stations for grass are located near the site boundary in two sectors with high offsite D/Q values where it might be practical to establish a vegetation plot. The highest offsite 0/0 for each individual sector occurs approximately at the site boundary. Although either fish or clam samples may be colic'cted f rom the . river, fish samples are preferred, because the maximum dose commitment to a member of the public as a result of liquid effluents is through the fish consumption pathway. O l HATCH ODCM, REV 1 5/11/04 3.0-1 l b.

Sediment will be collected annually, because shoreline recreational areas are under water and, therefore, not in use approximately half of 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. I i O O HATCH ODCM, REV 1 5/11/84 3.0-2 {

TABLE 3.0-1 (SHEET 10F 2) RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS Location Distance Sample Number Descriptive Location Direction (miles) Type

• 064 Roadside park WNW 0.8 0 101 Inner ring N 1.9 0 102 Inner ring NNE 2.5 0 103 Inner ring NE I.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 0 111 Inner ring SW 0.9 0 112 Inner ring WSW 1.0 ADV 113 Inner ring W 1.1 D 114 Inner ring WNW 1.2 0 115 Inner ring NW 1.1 0 116 Inner ring NNW 1.6 AD 152 Williamson's NNE 3.2 M 170 Upriver WNW ** R 172 Downriver E

                                                                           **     R 201             Outer ring                   N                          5.0    0 202             Outer ring                   NNE                        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    0 209             Outer ring                   S                          4.4    0 210             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    0 214             Outer ring                   WNW                        5.4    0 215             Outer ring                   NW                         4.5    0 216             Outer ring                   NNW                        4.8    0
  *See Sheet 2 of 2 for footnote.
 **See Sheet 2 of 2 for footnote.

O HATCH ODCM, REV 1 5/11/84 3.0-3

TABLE 3.0-1 (SHEET 2 0F 2) 6 RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS Location Distance Sample Number DescriDtive Location Direction (miles) Tvoe

• 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 Johnson Brothers SW 9.1 M
• Sample Types:

A - Airborne radioactivity D - Direct radiation M - Milk O- 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. 4 The location from which riverwater and sometimes clams and sediment may be taken can be rather precisely defined. Of ten, however, the sampling locations for clams have to be extended over a wide area to obtain a sufficient quantity; even then the quantity may not be sufficient. High water adds to the difficulty in obtaining clam samples; high water might also make an otherwise suitable loca*. ion 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. O 0687n HATCH 00CM, REV 1 5/11/84 3.0-4

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s  % HATCH ODCM, REV 1 5/11/84 RADIOLOGICAL ENVIRONMENTAL SAMPLING p\d EDWIN 1. HATCH LOCATION MAP (BEYOND Georgia Power uuCuAn i uuT SITE VICINITY) FIGURE 3.0-2 (SHEET 3 0F 3) mos.o 3.0-8

4.0 TOTAL DOSE DETERMINATIONS For the purpose of implementing 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) .
                              - Calculating doses due to gaseous effluents in accordance with RETS 3.15.2.3 (Unit 1) and 3.11.2.3 (Unit 2).

• Combining direct radiation doses based on direct radiation measurements with these effluent doses to determine total dose to a real individual.

The methodology for calculating individual doses due to liquid effluents was presented in Section 1.2, and the methodology fbr calculating individual doses due to gaseous effluents was presented 1. .02 ction 2.2.2.b. f C\ V 0690n l HATCH ODCM, REV 1 5/11/84 4.0-1

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5.0 POTENTIAL DOSES TO MEMBERS OF THE PUBl.IC DUE [mT nl TO THEIR ACTIVITIES INSIDE THE SITE BOUNDARY For the purpose of implementing RETS 6.9.1.9, an assessment of potential doses to members of the public due to their activities within the site boundary will be performed if circumstances have changed such that any of the limits of RETS 3.11.2.2 (Unit 2), 3.11.2.3 (Unit 2), 3.15.2.2 (Unit 1) or 3.15.2.3 (Unit 1) are exceeded. The locations of concern within the site boundary are the roadside park, the camping area, the recreation area, and the Visitors Center. The relationships between annual average atmospheric dispersion of airborne radioactive materials at various locations are as follows: Estimated Occupancy Factor (by an individual Location X/0 (sec/m8) during a year) Site boundary 3.26 x 10-6 100%. Critical receptor 6.10 x 10-7 100% Roadside park 3.74 x 10-6 < 0.1% (2 hr) Camping area 3.36 x 10-6 < 0.6% (48 hr) Visitors Center 1.00 x 10-5 < 0.1% (4 hr) Recreation area 6.71 x 10-7 2.4% (208 hr) 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 will 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. 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 inhabition of airborne radioactive materials suspended in the ground-level plume. This assessment will take into consideration the annual nv HATCH ODCM, REV 1 5/11/84 5. 0-1

average dispersion parameters and the estimated occupancy factor stated f_ (s,)' above, or a more precise value if available, for the locations of interest. If none of the limits discussed above is exceeded, potential annual doses to a member of the public at a location of concern within the site boundary are as follows:

                                                         -         Potential 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.

l

                                                         -         Potential doses to an individual at the roadside park 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 camping area are not expected to exceed 0.003 mrem due to inhalation and 0.06 mren due to direct radiation.
  /~'                                                              Potential doses to an individual at the recreation area are not V) 3 t

expected to exceed 0.002 mrem due to inhalation and 0.05 mrem due to i direct radiation. These values are based on annual average dispersion parameters and the

estimated occupancy factors stated above. Occupancy 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.

J J O 0691n HATCH ODCM, REV 1 5/11/84 5.0-2 _ - . - - . _ . _ - _ . . . _ _ ~ ~ _ _ - _ _ _ _ _ _ _ _ , _ _ _ _ _ . - . . . . ~ . . _ . _

r q REFERENCES V

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

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

2. " Calculation of Annual Doses to Man from Routine Releases of Reactor Ef fluents for the Purpose of Evaluating Compliance with 10 CFR 50, Appendix I," U. S. NRC Reculatory Guide 1.109, March 1976.

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

4. HNP-2 Environmental Report - Operatina license Stage, Georgia Power Company, July 1975, (including Appendix A, "Edwin I. Hatch Plant-Unit 1 Preoperational Environmental Surveillance Report Number 1," submitted March 1, 1975). '

5. Edwin I. Hatch Nuclear Plant-Unit 1 Final Safety Analysis Report, Georgia Power Company.

6. Edwin I. Hatch Nuclear Plant-Unit 2 Final Safety Analysis Report, Georgia Power Company.

7. " Methods for Estimating Atmospheric Transpret and Dispersion of Gaseous Effluents in Routine Releases from Light-Vater-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. Graohs and Mathematical Tables, edited by Abramowitz, M. and Stegun, I. A.,

National Bureau of Standards, U. S. Department of Commerce,1965.

10. Meteoroloov and Atomic Eneray, edited by Slade, D. H., U. S. Department of Commerce, July 1968.

11. " Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I,"

U. S. NRC Regulatory Guide 1.113. Rev.1, April 1977.

12. Nichols, M. C. and Holder, S. D., Plant Edwin I. Hatch Units 1 and 2 Thermal Plume Model Verification, Georgia Power Company Environmental Af f airs Center, March 1981.

13. Effect of Eductors in Plart Hatch Liquid Waste Tanks, Georgia Power Company, October 1978.

O HATCH ODCM, REV 1 5/11/84}}