ML20108B459

.h TABLE OF CONTENTS

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1.0 INTRODUCTION

9 2.0 LIQUID BFFLUENTS 10 2.1 CONCENTRATION - COMPLIANCE WITH 10 CFR 20 10 2.2 DOSE - COMPLIANCE WITH 10 CFR 50 APPENDIX I 16 2.3 PROJECTED DOSE 18 2.4 INSTRUMENTATION 19 3.0 GASBOUS EFFLUENTS 37 3.1 DOSE RATE - COMPLIANCE WITH 10 CFR 20 37 t 3.2 DOSE - COMPLIANCE WITH 10 CFR.50 APPENDIX I 45 3.3 PROJECTED DOSE 55 3.4 INSTRUMENTATION 57 4.0 TOTAL DOSE 72 4.1 REMEDIAL ACTION 72 4.2 SURVEILLANCE REQUIREMENTS 73 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 73 5.1 MONITORING PROGRAM 73 5.2 LAND USE CENSUS 74 5.3 INTERLABORATORY COMPARISON PROGRAM 74 5.4 REPORTING REQUIREMENTS 75 6.0 BASES 92 7.0 REPORTS 101 7.1 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING 101 REPORT 7.2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 102 APPENDIX A DOSE CONVERSION FACTOR TABLES 106 APPENDIX B: METEOROLOGICAL MODEL 183

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\ OFFSITE DOSE CALCUIATION MANUAL LIST OF TABLES h Table PAgg l\ ,

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, g- 2-I RADIOACTIVE LIQUID NASTE SAMPLING AND ANALYSIS PROGRAM 2-2 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 21 2-3 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 24 l

SURVEILLANCE REQUIREMENT:s 3-1 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM 41 3-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 58 1 l

3-3 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 60 I SURVEILLANCE REQUIREMENTS 5-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 76 5-2 SAMPLING LOCATION NUMBERS, DISTANCES (MILES) AND 82 DIRECTIONS 5-3 DETECTION CAPABILITIES FOR ENVIROl#4 ENTAL SAMPLE 83 ANALYSIS 5-4 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN 86 ENVIRONMENTAL SAMPLES A.1-1 BIOACCUMULATION FACTORS TO BE USED IN THE ABSENCE OF 107 SITE SPECIFIC DATA A.1-2 DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS 108 A.2-1 INHALATION DOSE FACTORS FOR ADULTS 109 A.2-2 INHALATION DOSE FACTORS FOR TEENAGERS 111 A.2-3 INHALATION DOSE FACTORS FOR CHILD 113 A.2-4 INHALATION DOSE FACTORS FOR INFANT 115 l

A.2-5 EXTERNAL DOSE FACTOR FOR STANDING ON CONTAMINATED 117 GROUND A.3-1 INGESTION DOSE FACTOR FOR ADULTS 119

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\ OFFSITE DOSE CALCULATION MANUAL LIST OF TABLES h Table p g ,

.D g- A.3-2 INGESTION DOSE FACTOR FOR TEENAGERS 122 a

A.3-3 INGESTION DOSE FACTOR FOR CHILD 125 A.3-4 INGESTION DOSE FACTOR FOR INFANT 128 A.3-5 STABLE ELEMENT TRANSFER DATA 131 A.4-1 SITE RELATED INGESTION DOSE COMMITMENT FOR ADULT 132 A.4-2 SITE RELATED INGESTION DOSE COMMITMENT FACTOR FOR 135 TEENAGER A.4-3 BITE RELATED INGESTION DOSE COMMITMENT FACTOR FOR CHILD 138 A.4-4 SITE RELATED INGESTION DOSE COMMI'INENT FACTOR FOR 141 INFANT A.5-1 INHALATION DOSE PARAMETER FOR THE CHILD 144 A.5-2 INHALATION PATHWAY FACTOR FOR ADULT (RI FACTOR) 145 A.5-3 INHALATION PATHWAY FACTOR FOR TEENAGER (RI FACTOR) 147 A.5-4 INHALATION PATHWAY FACTOR FOR CHILD (RI FACTOR) 149 A.5-5 INHALATION PATHWAY FACTOR FOR INFANT (RI FACTOR) 151 A.5-6 GRASS-COW-MILK PATHWAY FACTOR ADULT (RI FACTOR) OF SITE 153 SPECIFIC DATA A.5-7 GRASS-COM-MILK PATHWAY FACTOR THEN (RI FACTOR) 155 A.5-8 GRASS-COW-MILK PATHWAY FACTOR CHILD (RI FACTOR) 157 I I

A.5-9 GRASS-COW-MILK PATHWAY FACTOR INFANT (RI FACTOR) 159 A.5-10 GRASS-COW-MEAT PATHWAY FACTOR ADULT (RI FACTOR) 161 A.5-11 GRASS-COW-MEAT PATHNAY FACTOR TEEN (RI FACTOR) 163 A.5-12 GRASS-COM-MEAT PATHWAY FACTOR INFANT (RI FACTOR) 165

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LIST OF TABLES g pagg Tabla ,

,D A.5-13 VEGETATION PATHWAY FACTOR ADULT (RI FACTOR) 167 0-A.5-14 VEGETATION PATHWAY FACTOR TEEN (RI FACTOR) 169 A.5-15 VEGETATION PATHWAY FACTOR CHILD (RI FACTOR) 171 A.5-16 GROUND PLAME PATHWAY FACTOR (RI FACTCR) 173 A.5-17 GRASS-GOAT-MILK PATHWAY FACTOR ADULT (RI FACTOR) 174 A.5-18 GRASS-GOAT-MILK PATHWAY FACTOR TEEN (RI FACTOR) 176 A.5-19 GRASS-GOAT-MILK PATHWAY FACTOR CHILD (RI FACTOR) 179 A.5-20 GRASS-GOAT-MILK PATHWAY FACTOR INFANT (RI FACTOR) 181 LIST OF FIGURES Figure Enga 2.1 BOUNDARY FOR LIQUID EFFLUENTS 36 3.1 BOUNDARY FOR GASEOUS EFFLUENTS 71 5.1 AIRBORNE PATHWAY SAMPLING LOCATIONS 87 5.2 DIRECT RADIATION PATHWAY SAMPLING LOCATIONS 88 5.3 WATERBORNE PATHWAY SAMPLING LOCATIONS 89 5.4 INGESTION PATHWAY SAMPLING LOCATIONS 90 5.5 DISTANT SAMPLING LOCATIONS 91 B-1 VERTICAL STANDARD DEVIATION OF MATERIAL IN A PLUME 186 B-2 PLUME TRAVEL DISTANCE VERSUS FRACTION REMAINING IN 187 PLUME l

B-3 PLUME TRAVEL DISTANCE VERSUS RELATIVE DEPOSITION RATE 188 j

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'\ OFFSITE DOSE CALCULATION MANUAL

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g 1.0 Introduction

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j The Offsite Dose Calculation Manual describes the Radioactive r Effluent Controls Program. The implementation of this program ensures compliance with the requirements of 10 CFR 50.36, 10 CFR 20.106, 10 CFR 50 Appendix I and 40 CFR 190.

On January 1, 1994, 10CFR20.1001-20.2402 shall be implemented.

Wolf Creek will continue to maintain the existing level of effluent control (10CFR20.106) to comply with the new requirements. This method of compliance has been determined by the NRC to be ALARA. 22/93 The ODCM describes the methodology and parameters used in the calculation of offsite doses due to radioactive liquid ana gaseous effluents. The ODCM contents for calculation of dose are based on " Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants (NUREG-0133)," and Regulatory Guide 1.109, Revision 1.

Dose calculations are performed for the limiting age group i.e.

Adult age group for the liquid pathway, and the Child age group for gaseous effluent organ doses. 22/95 The ODCM provides the limitations on the operability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination. Each Surveillance Requirement shall be performed within the specified surveillance interval with a maximum allowable extension not to exceed 25% of the specified interval.

The ODCM provides the Radiological Environmental Monitoring Program. The program consists of monitoring stations and sampling programs designed to confirm the dose estimates made under normal or accident conditions, and conform to NRC requirements in 10 CFR Part 50.

The ODCM provides descriptions of the information that should be included in the Annual Radiological Environmental Operating and Annual Radioactive Effluent Release Reports.

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,} 2.0 Liquid Effinants

\ concentration - ca-alt = nam with 10 cyn 20 j 2.1 r ,

The concentration of radioactive material released in liquid I effluents to UNRESTRICTED AREAS (see Figure 2.1) shall be limited to the concentration specified in 10 CFR Part 20, f Appendix B, Table II, Column 2, for radionuclides other than l dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2x 10" I microcurie /mL total activity.

2.1.1 n=--dial Action With the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS exceeding the above limits, immediately restore the concentration to within the above limits.

2.1.2 surveill=nea meanir - nts To show compliance with this requirement, concentrations of l actual liquid effluents will be determined by performing Isotopic Analyaes. Rad.aactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program of Table 2-1. 3/92 l

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TABLE 2-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM LOWER j

g. MINIMUM TYPE OF ACTIVITY LIMIT OF l LIQUID RELEASE SAMPLING ANALYSIS ANALYSIS DETECTION I TYPE FREQUENCY FREQUENCY (1) (LLD)

{ C1/mL)

Principal Gamma i 1. Batch Waste P P 5x10 '

Release (2) Each Batch Each Batch (3) Emitters Tanks ~

1x10' I-131 l a. Waste P M Dissolved and 1x10' Monitor Tank One Entrained Cases Batch /M (Gamma Emitters) ~

b. Secondary P M (4) H-3 1x10" Liquid Waste Each Batch Composite Monitor Tank 1x10 '

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l Gross Alpha f ~

P Q (4) 5x10' Each Batch Composite SR-89, Sr-90 1x10 "

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l Fe-55

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2. Continuous (6) W (4) 5x10 '

! (5) Releases Daily Grab Composite Principal Gamma Sample (3) Emitters -

1x10' I-131

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Steam Generator M M Dissolved and 1x10'

' Blowdown Grab Entrained Gases Sample (Gamma Emitters) -

(6) M (4) 1x10' Daily Grab Composite H-3 Sample 1x10 '

Gross Alpha (6) Q (4) 5x10*

Daily Grab Composite SR-89, Sr-90 Sample ~

1x10"

" Fe-55 3/93

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TABLE 2-1 (continued) l N TABLE NOTATIONS l

\ (1) The LLD is detined, as the smallest concentration of radioactive f material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5%

probability of falsely concluding that a blank observation represents a 'real" signal.

For a particular measurement system, which may include radiochemical separation:

LLD =

E x V x 2.22 x 10' x Y x Decay !

Where:

LLD = the "a priori" lower limit of detection j (microcuries per unit mass or volume), ;

sb = the standard deviation of the background counting rate or of the counting rate of a blank sample l as appropriate, (counts per minute), g - 5/ tr l Where: B = background sum (counts)

LT = live time (minutes) ,

E = the counting efficiency (counts per disintegration),

V = the sample size (units of mass or. volume),

2.22 x 106= the number of disintegrations per minute per microcurie, Y = the fractional radiochemical yield, when applicable, Decay = decay factor (s), There are three decay factors that may be appropriate for use depending on the nature of the sample and the half life of the nuclide. Any combination of the three may be used. The factors are as follows:

A) This decay factor corrects for decay from the time of sampling to the start of the analysis, e*ts, where:

Ats = decay time = acquisition start time - sample time 4/92

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\ OFFSITE DOSE CALCULATION MANUAL TABLE 2-1 (Continued) h TABLE NOTATIONS g

ID l(r A = In2/ half-life

,B) This decay factor corrects for decay during the analysis.

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l A x RT i

! A= In2/ half-life RT = real time of counting i C) This decay factor corrects for decay during sampling.

1-e" AAtd A = In2/ half-life td = deposition time = sample time - deposition start time

! l EZEI All times used in decay calculations should be in the same units. i l

Typical values of E, V, Y, ts, td should be used in the calculation.

i It should be recognized that the LLD is defined as an a priori (before ;

the fact) limit representing the capability of a measurement system and not as an a noateriori (after the fact) limit for a particular measurement.

(2) A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for analyses, each batch shall be isolated,

and then thoroughly mixed by a method described in plant procedures to assure representative sampling. 4/.92

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TABLE 2-1 (Continued)

N TABLE NOTATIONS

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a. (3) The principal gamma emitters for which the LLD specification applies include the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144. This list does not mean that only these nuclides are to be considered. Other gamma peaks l

that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the semiannual Radioactive Effluent Release Report in the format outlined in Regulatory Guide 1.21, Appendix B, Revision 1, June 1974. l (4) A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method or :tampling employed results in a specimen that is ,

representative of the liquids released. Prior to analysis, all l samples taken for the composite shall be thoroughly mixed in order for !

the composite samples to be representative of the effluent release.

l (5) A continuous release is the discharge of liquid wastes of a nondiscrete volume, e.g., from a volume of a system that has an input flow during the continuous release.

(6) Samples shall be taken at the initiation of effluent flow and at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter while the release is occurring. To be representative of the liquid effluent, the sample volume shall be proportioned to the effluent stream discharge volume. The ratio of sample volume to effluent discharge volume shall be maintained constant for all samples taken for the conposite sample.

FREQUENCY NOTATION NOTATION FREQUENCY S At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

D At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

W At least once per 7 days M At least once per 31 days.

Q At least once per 92 days.

SA At least once per 184 days.

R At least once per 18 months.

S/U Prior to each reactor startup.

N.A. Not applicable.

P Completed prior to each release.

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2.2 nom. - ca p11==-a with 10 cra so apr==div I

)y The dose or dose commitment to'a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each unit, to UNRESTRICTED AREAS (see Figure 2.1) shall be limited:

a. During any calendar quarter to less than or equal to 1.5 mrems to the whole body and to less than or equal to 5 mrems to any organ, and

b. During any calendar year to less than or equal to 3 mrems to the whole body and to less than or equal to 10 mrems to any organ.

2.2.1 Remedial Action With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to ;

Technical Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that I subsequent releases will be in compliance with the above limits. !

This Special Report shall also include the results of radiological analyses of the drinking water source, and the radiological impact on finished drinking water supplies with regard to the requirements of 40 CFR Part 141, Clean Drinking Water Act. This requirement of (1.) and (2. ) are applicable only if drinking water supply is taken from the receiving body I within 3 miles of the plant discharge. 3/92 2.2.2 Burveillance Reauirements Cumulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year shall be determined using the following methodology at least once per 31 days.

f a 3 D, = E, Ag}] A toCaFt A L-1 >

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ATTACHMENT A o (Page 13 of 184) g g OFFSITE DOSE CALCULATION MANUAL Where, g

DT= the cumulative dose commitment to the total body jg or any organ, T, from the liquid effluent for the total time period f A tn ,innuun L-1 At t = the length of the Lth timo period over which Cn i and Fu are averaged for all liquid releases, in hours.

l Cnt - the average concentration of radionuclide, 'i', in undiluted liquid effluent flow during time period Atn, in pCi/mL.

Fn = the near field average dilution factor for C in during any liquid effluent release where:

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f t

F = (F)K Where:

f= Liquid Radioactive Waste Flow F= Discharge Structure Exit Flow, the sum of the release and dilution flow.

K= Applicable factor; the site dependent value for the mixing effect of the discharge structure. This value is conservatively assumed to be 1 (one) for this section.

A,= The site related ingestion dose commitment factor 1

to the total body or any organ, 'T', for each l

identified principal gamma and beta emitter, mrem /hr

! per pCi/mL. See Tables A.4-1 through A.4-4.

! The limiting age group for liquid dose calculations is i the Adult age group. 12/95 Ar=i 1.14E5 (U, / D, + U, x BF)F,

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Where, DW = Dilution factor from t'he near field area to the 7 potable water intake for water consumption, for Wolf Creek Generating Station thio factor is 1 (one).

BFi= Bioaccumulation factor for radionuclide 'i', in fish, pCi/Kg per pCi/1, from Table A.1-1 from Regulatory Guide 1.109 (Rev. 1).

DFi- Adult dose Conversion factor for radionuclide,

'i', in mrem /pci, from Table A.3-1 through A.3-4, from Regulatory Guide 1.109 (Rev. 1).

Uw = Adult water consumption, (730 1/yr.from Reg. Guide 1.109)

Up = Adult fish consumption, (21 kg/yr.from Reg. Guide 1.109) 12/95 10'pCi/ Clx 10'ml/ Kg 1.14E5 - Unitsconversionfactor =

8760 hr/yr The dose calculations are based on the actual isotopic analysis of the radioactive liquid effluents, the radioactive liquid effluent flow, and the dilution flow.

2.3 Erg 8facted Dosa The Liquid Radwaste Treatment System shall be OPERABLE and appropriate portions of the system shall be used to reduce releases of radioactivity when the projected doses due the liquid effluent, from each unit, to UNRESTRICTED AREAS (see Figure 2.1) would exceed 0.06 mrem to the whole body or 0.2 mrem to any organ in a 31 day period.

2.3.1 Resandial Action With radioactive liquid waste being discharged without treatment and in excess of the above limits and any portion of the Liquid Radwaste Treatment System not in operation, prepare and submit to the Commission within 30 days pursuant to Technical Specification 6.9.2, a Special Report that includes the following information: J/D1

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! ATTACHMENT A (Page 15 of 184) jg OFFSITE DOSE CALCULATION MANUAL I~ a. Explanation of why liquid radwaste was being discharged

! . without treatment, identification of any inoperable .

l3 equipment or subsystems, and the reason for the g- inoperability,

b. Action (s) taken to restore the inoperable equipment to OPERABLE status, and

c. Summary description of action (s) taken to prevent a l recurrence. 3/91 2.3.2 surveillanca Requirements 2.3.2.1 Doses due to liquid releases from each unit to l UNRESTRICTED AREAS shall be projected at least once per

31 days in accordance with the following methodology j when Liquid Radwaste Treatment Systems are not being fully utilized.

Du = - x 31

_T.

Where, D31 = Projected 31 day dose A = Cumulative dose for previous three months i

T = Number of days that the cumulative dose occurred in A above 12/95 i 2.3.2.2 The installed Liquid Radwaste Treatment System shall be considered OPERABLE by meeting the requirements of Sections 2.1 and 2.2.

2.4 Instrumentation The radioactive liquid effluent monitoring instrumentation

! channels shown in Table 2-2 shall be OPERABLE with their i Alarm / Trip Sotpoints set to ensure that the limits of Section 2.1 are not exceeded. The Alarm / Trip Setpoints of these

( channels shall be determined and adjusted in accordance with the !

methodology and parameters described in Section 2.4.4. l 4

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ATTACHMENT A (Page 16 of 184) g OFFSITE DOSE CALCULATION MANUAL 2.4.1 Ramadini Acklan fd ,

2.4.1.1 With a radioactive liquid effluent monitoring

g. instrumentation channel Alarm / Trip Setpoint less conservative than required by the above, immediately suspend the release of radioactive liquid effluents monitored by the affected channel, or declare the channel inoperable.

2.4.1.2 With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 2-2. Restore the inoperable instrumentation to OPERABLE status within the time specified in the ACTION, or explain in the next Annual Radioactive Effluent Release Report, why

- this inoperability was not corrected within the time specified. s/s3 2.4.2 survaillanca Requ$yamanta Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and ANALOG CHANNEL OPERATIONAL TEST at the frequencies shown in Table 2-3.

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OFFSITE DOSE CALCULATION MANUAL TABLE 2-2 ,

h} RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION

\ insTauManT MINIMux ACTION 2 caaMMans I OPERABLE

1. Radioactivity Monitors Providing Alarm and Automatic Termination of Release

a. Liquid Radwaste Discharge Monitor (HB-RE-18) 1 31

b. Steam Generator Blowdown Discharge Monitor 1 32 (BM-RE-52)

c. Turbine Building Drain Monitor (LE-RE-59) 1 32

d. Secondary Liquid Waste System Monitor (HF-RE-45) 1 33

e. Wastewater Treatment System Influent Monitor 1 32 (HF-RE-95)

2. Flow Rate Measurement Devices

a. Liquid Radwaste Discharge Line

1) Waste Monitor Tank A Discharge Line 1 34

2) Waste Monitor Tank B Discharge Line 1 34

b. Steam Generator Blowdown Discharge Line 1 34

c. Secondary Liquid Waste System Discharge Line 1 34 3/92

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\ ACTION STATEMENTS

.D (r Action 31 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, offluent releases via this pathway may continue for up to 14 days provided that prior to initiating a release:

a. At least two independent samples cre analyzed in accordance with Section 2.1.2, and

b. At least two technically qualified members of the facility staff independently verify the release rate calculations and discharge line valving.

Otherwise, suspend release of radioactive effluents via this pathway.

Action 32 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided grab samples are

, analyzed for principle gamma emitters and I-131 at a lower limit of detection as specified in Table *2-1.

a. At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when the specific activity of the secondary coolant is greater than 0.01 microcurie / gram DOSE EQUIVALENT I-131, or

b. At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the specific activity of the secondary coolant is less than or equal to 0.01 microcurie / gram DOM EQUIVALENT I-131.

Action 33 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided that prior to initiating a release:

a. At least two independent samples are analyzed in accordance with Section 2.1.2, and

b. At least two technically qualified members of the facility staff independently verify the release rate calculations and discharge line valving.

Otherwise, suspend release of radioactive effluents via this pathway.

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TABLE 2-2 (Continued)

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ACTION STATEMElfrS

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f Action 34 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual releases. Pump performance curves generated in place may be used to estimate flow.

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TABLE 2-3

N RADIOACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION

\ SURVEILLANCE RROUIREMENTS J INSTRIE4ENT CHANNEL SOURCE CHANNEL ANALOG 6' CHECK CHECK CALIBEATION CHANNEL OPERATIONAL TEST

1. Radioactivity Monitors providing !

alarm and automatic termination l of release

a. Liquid Radwaste Discharge Monitor D P R(2) Q(1)

(HB-RE-18) l

b. Steam Generator Blowdown Dis- D M R(2) Q (1) charge Monitor (BM-RE-52)

c. Turbine Building Drain Monitor D M R(2) Q (1)

(LE-RE-59)

d. Secondary Liquid Waste System D F R(2) O(1)

Monitor (HF-RE-45)

e. Wastewater Treatment System D M R (2) Q (1)

Influent Monitor (HF-RE-95)

I 2. Flow Rate Measurement Devices

a. Liquid Radweste Discharge Line D(3) N.A. R N.A.

b. Steam Generator Blowdown Dis- D(3) N.A. R N.A.

charge Line l

c. Secondary Liquid Maste System D(3) N.A. R N.A.

Discharge Line 3/93 l

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TABLE 2-3 (Continued)

N TABLE NOTATIONS (1) The ANALOG CHANNEL OPERATIONAL TEST shall also demonstrate that f automatic isolation of this pathway and control room alarm annunciation occur as appropriate if any of the following conditions exists:

a. Instrument indicates measured levels above the Alarm / Trip setpoint (isolation and alarm), or

b. Circuit failure (alarm only), or

c. Instrument indicates a downscale failure (alam only), or

d. Instrument controls not set in operate mode (alarm only).

(2) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference (gas or liquid and solid) standards certified by the National Institute of Standards and Technology (NIST) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards shall permit calibrating the system over its intended range or energy, measurement range, and establish monitor response to a solid calibration source. For subsequent CHANNEL CALIBRATION, NIST traceable standard (gas, liquid, or solid) may be used; or a gas, liquid, or solid source that has been calibrated by relating it to equipment that was previously (within 30 days) calibrated by the same geometry and type of source standard traceable to NIST.

(3) CHANNEL CHECK shall consist of verifying indication of flow during periods of release. CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months on days on which continuous, periodic, or batch releases are made. 3/91

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ATTACHMENT A (Page 22 of 184) g OFFSITE DOSE CALCULATION MANUAL

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2.4.3 Lianid h4 tar calibration Ma&haAnloav M

)

g.

The five monitors associated with liquid releases are listed below:

Mnniter ID Description 0-BM-RE-52 Steam Generator Blowdown Discharge Monitor 0-LE-RE-59 Turbine Building Drain Monitor ,

0-HF-RE-45 Secondary Liquid Waste System Monitor l t 0-HB-RE-18 Liquid Radwaste Discharge Monitor l 0-HF-RE-95 Wastewater Treatment System Influent Monitor Liquid effluent streams are monitored by an NaI(Tl) Detector.

The detector operates in a gross counting mode and is gamma ,

I sensitive.

Calibration of the liquid monitors shall be performed using three standard solutions of Cs-137. The solutions shall cover the appropriate range of the detector and have concentrations of approximately 5 x 10-7 pCi/cc, 1 x 10-5 pCi/cc, and 1 x 10-3 pCi/cc. The solutions shall be presented to the detector and the meter reading in counts per minute shall be recorded. A determination of linearity shall be produced using the counts per minute vs. concentration data. 5/.95 1

2.4.4 Liatid Effluent Monitor Setpointa j The Alarm / Trip Setpoints for the Liquid Effluent Radiation 1 Monitors are based on instantaneous concentration limits of 10 l CFR 20, Appendix B, Table II, Column 2 applied at the boundary of the restricted area. Specifically, the High Alarm Setpoint j will correspond to the 10 CPR Part 20 limits at the Boundary of the restricted area; the Alert Alarm Setpoint is set one order of magnitude below the High Alarm / Trip Setpoint. Since the high alarm / trip initiates isolation of the particular system and I termination of the release, this setpoint represents assurance I that the instantaneous liquid release limit of 10 CFR Part 20 is not exceeded. Auditable records shall be maintained indicating the actual setpoints used at all times.

1

_ . ~. _

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ATTACHMENT A 0

g (Page 23 of 184) g OFFSITE DOSE CALCULATION MANUAL The calculated Alarm and Trip Action Setpoints for the Liquid

]

g Effluent.Line Monitors must satisfy the following equation:

.0 y cf gg F+f Where: ,

C = The liquid effluent concentration limit (MPC) implementing Section 2.1 in pCi/mL. !

J c = The Setpoint, in pCi/mL, of the Radioactivity Monitor measuring the radioactivity concentration in the effluent line prior to dilution and subsequent release; the Setpoint, which is inversely proportional to the Volumetric Flow of the effluent line and directly proportional to the Volumstric 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 restricted area.

f = The Pump Flow Rate as measured at the Radiation Monitor Location, in Volume per Unit Time, but in the same units as F, below.

F = The Dilution Water Flow Rate as measured prior to the release point, in Volume per Unit Time.

Thus, the expression for determining the setpoint on the Liquid Radwaste Effluent Line Monitor becomes:

es C(F+ f) (pCi/ ml) 2.4.4.1. Continunum Limild Ef finant Man 4 tors The three monitors associated with continuous liquid releases are listed below:

Mnnftor ID Description 0-BM-RE-52 Stm Generator Blowdown Discharge Monitor 0-LE-RE-59 Turbine Building Drain Monitor 0-HF-RE-95 Waste Water Treatment System Influent Monitor

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.g The Steam Generator Blowdown Discharge Effluent Monitor j\ continuously monitors the Blowdown Discharge Pump

,0 Outlet to detect excess radioactivity due to System F Demineralizer breakthrough or abnormal Primary to Secondary leakage. The Blowdown Discharge Monitor's L High Alarm Setpoint initiates CLOSURE of the Blowdown Isolation Valves and the Blowdown Discharge Valve.

Similarly, the High Radiation Alarm on the Turbine Building Drain Monitor and Waste Water Treatment l Monitor initiates CLOSURE of the Drain Line Isolation valves to prevent the release of radioactive effluents.

Monitor setpoints will be conservatively based on I-131, the most restrictive isotope expected to be l present. This is particularly appropriate for the i Turbine Building Drain Line Monitor since the most probable source is the Secondary Steam System which is expected to have negligible activity unless there is a significant Primary to Secondary leak. Due to changing i activities, it will not be possible to select a

! radionuclide distribution on which to base the monitor l setpoint. Additionally, maximum effluent flows and j minimum dilution flows will normally be assumed.

The High Alarm / Trip Setpoint will be set to correspond to the I-131 MPC limit at the boundary of the restricted area from 10 CFR Part 20, Appendix B, Table II, Column 2. The alert alarm is set one order of magnitude below the High Alarm / Trip Setpoint for release points that have dilution and to the High Alarm value for those without dilution. This High Alarm / Trip Setpoint assures the limits of Section 2.1 are not exceeded at the boundary of the restricted area. 22/S5 In the event that an alarm is TRIPPED, an evaluation of the system will be made by taking an actual isotopic and flow analysis of the discharge.

h

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i ATTACHMENT A o (Page 25 of 184)

OFFSITE DOSE CALCULATION MANUAL !

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g The above continuous liquid effluents are not g -

radioactive effluents until activity has been detected a by the Liquid Effluent Monitor, a Tritium analysis of r the Secondary system, or a gross Beta analysis of the Secondary system. At that time an analysis of the effluent will be made to verify activity in the system effluent. During periods of time when the above liquid effluents are not radioactive the High Alarm / Trip setpoint may be set to 1.5 times the background count rate.

2.4.4.1.1 Steam. Generator Blogs1 min Disch=rge Monitor 1

SETPOINT( Ci/ml) - MPC un x B

where, '

MPCI -in = Maximum Permissible Concentration of I-131, i 3.0 E-7 pCi/mL.

Fm = Dilution flow rate.

1 FB = Blowdown flow rate.

The setpoint calculation is based on the minimum dilution flow rate, the maximum possible blowdown flow rate, and, due to changing conditions, I-131 which is the most restrictive isotope expected to be present, j i

on the event that an alarm is reached, the cetpoint will be '

reevaluated using the actual dilution flow rate, the actual blowdown flow rate, and the actual isotopic analysis as outlined in Section 2.4.4.2. This evaluation will be used to ensure the !

limit of Section 2.1 was not exceeded. The setpoint will still be based on the MPC of I-131 due to the changing conditions of activity and I-131 being the most restrictive isotope.

3

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ATTACHMENT A (Page 26 of 184) g OFFSITE DOSE CALCULATION MANUAL h 2.4.4.1.2 Turbina Buildina Drain vanitor and wasta water g Trea&==at Bvatan Tnfluent Manitor -

D r F, + F7 SETPOINT( Ci/ml) = MPCi-ui x Fr MPC2 .1n = 3. 0 E-7 pCi/mL.

F = Dilution flow rate Fe = Effluent flow rate The setpoint is based on the minimum dilution flow rate, the maximum possible effluent flow rate, and the most restrictive isotope expected to be present, I-131.

On the event that an alarm is reached, the release will be evaluated to see if the limit of Section 2.1 was exceeded by using the actual Dilution Flow Rate, the actual Effluent Flow Rate, and the actual isotopic analysis as outlined in Section 2.4.4.2. The setpoint will still be based on the MPC of I-131 due to the changing conditions of activity and I-131 being the most restrictive isotope.

2.4.4.2 natch n=d4oactive Lianid Effluent Monitor The two monitors associated with liquid batch releases are listed below:

Monitor ID Description 0-HP-RE-45 Secondary Liquid Waste System Monitor 0-HB-RE-18 Liquid Radwaste Discharge Monitor The setpoint is a function of dilution flow rate, tank flow rate, and isotopic composition. A laboratory isotopic analysis is made of each batch prior to discharge. Based on the isotopic analysis and existing flow condition, the setpoint will be calculated and set on the appropriate monitor to ensure the concentration limits of 10 CFR 20, Appendix B, Table II, Column !

2 is not exceeded.

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ATTACHMENT A l0 (Page 27 of 184)

OFFSITE DOSE CALCULATION MANUAL l{ The setpoints are determined using the following methodology:

\

j 1) Determine concentrations of radioactivity of the batch r being considered for release.

t

The isotopic concentration of the batch is the sum of l the concentrations for the isotopes present as

! determined from the analysis required in-Table 2-1.

l l [Cg = [C, + C, + C, + C + Cr i s l

Where:

j Ci = The concentration of nuclide i as determined by ;

the analysis of the waste sample.

Cg = The sum of the concentrations Cg of each measured gamma emitting nuclide observed by gamma-ray spectroscopy of the waste sample.

i l *Ca = The measured concentration c a of alpha emitting nuclides observed by gross alpha analysis of the monthly composite sample.

l l *Cs = The measured concentrations of Sr-89 and Sr-90 l

in liquid waste as determined by analysis of the quarterly composite sample. ,

l

Ct= The measured concentration of H-3 in liquid

waste as determined by analysis of the monthly composite.

l *Cg - The measured concentration of Fe-55 in liquid l waste as determined by analysis of the quarterly l composite.

l

Values for these concentrations will be based on

! previous composite sample analysis as required by Table 2-1.

I 4

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ATTACHMENT A O (Page 28 of 184) g OFFSITE DOSE CALCULATION MANUAL

{g 2) The measured radionuclide concentrations are used to calculate a dilution factor, Fd , which is the ratio of a total dilution flow rate to tank flow rate required to r assure that the limiting concentrations of Section 2.1 are met at the point of discharge. This is referred to as the required dilution factor and is determined according to:

F, = C' ' x F'

( E, h0PCp Where:

Ci = Measured concentrations of C g, C, a Cs, Ct and C f, as defined in Step 1. Terms Ca, Cs, C t and C f , will be included in the calculation as appropriate.

MPCi = MPC g , MPCa, MPCs, MPCt and MPC f , 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 2.0E-04, pCi/mL total activity.

Fs - The safety factor; a conservative factor used to compensate for statistical fluctuations and errors of measurement default value is 0.5. 12/D5

3) For the case Fd < 1, the waste tank effluent concentration meets the limits of 10 CFR 20 without dilution and the effluent may be released at any desired flow rate. For the case Fd>1, a modified dilution factor, Fd n, must be determined so that available dilution flow may be apportioned among simultaneous discharge pathways.

FL = F, / F, Where Fa is the allocation factor which will modify the required dilution factor so that simultaneous liquid releases may be made without exceeding 10 CFR 20 limits.

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.O ATTACHMENT A o (Page 29 of 184) g l g OFFSITE DOSE CALCULATION MANUAL

~

g The most straight-forward determination of allocation g -

factor is:

D E F, = 1/ n Where n - The number of liquid discharge pathways for which Fd > 1 and which is planned for simultaneous release.

However, this value for Fa may be unnecessarily restrictive in that all release pathways are apportioned the same fraction of the available dilution stream, regardless of the relative concentrations of each of the sources.

Since the radionuclide concentration of the two continuous sources is expected to be less than that of the batch release source, it is acceptable to allocate smaller portions of the dilution stream to the continuous releases and a larger portion to the batch releases.

Therefore, Fa is defined as a flexible quantity with a default value of 1/n. Prior to initiating simultaneous release, a check will be made to assure that the sum of the allocation factors assigned to pathways for the simultaneous release is < 1.

4) The calculated maximum permissible waste tank effluent flow rate, Fmax, is based on the modified dilution factor, F dn, and the effective dilution flow rate, Feff.

The cooling lake into which the effluent is discharged is also the source of the dilution stream. It is therefore necessary to take into account the recirculation of previously emitted radionuclides should they be detected by sample analysis of the cooling lake water. This is accomplished by defining an effective dilution flow rate as:

F,g = F. 1

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ATTACHMENT A O

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] Where: '

\

j Fm = The expected minimum dilution water flow rate.

r LCi = Measured concentration of nuclide i in the ;

cooling lake water sample.

1 MPCi = Limiting concentration of radionuclide i from ;

10CFR20, Appendix B, Table II, Column 2. l I

For the purpose of setpoint calculations the expected minimum dilution flow rate is assigned a value based upon the type and number of pumps RUNNING into the circulating water piping.

Having established the values of Fdn and F egg, the calculated maximum permissible waste tank flow rate is given by f_ s En p+ f, E, for f,((Feff 6 fu Where f p if the expected effluent flow rate; normally the rated capacity of the effluent pump. Thus the pump flow rate is set-at or below fmax. Even though the value of fmax may be larger than the actual effluent pump capacity, fp , it does represent the upper limit to the effluent flow rate, whereby the requirement of 10CFR20 may still be met. If Fd s 1, the effluent pump i flow rate may be assigned any value since the waste tank effluent concentration meets the limits of 10CFR20 1

without dilution and the release may be made without regard to the setpoints for other release pathways.

For those discharge pathways selected to be secured during the release under consideration, the pump flow rate should be set at as low a value as practicable to detect any inadvertent release.

A setpoint for the dilution stream flow rate is not applicable since the minimum flow rate is administratively set.

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5) The liquid radiation monitor setpoint may now be g determined based on the values of E,C, i 1and f max-a The monitor response is primarily to gamma radiation, r therefore, the actual setpoint is based on-E g, C g. The calculated monitor setpoint concentration is determined as follows:

c - A [Cg h0/d) i Where:

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

A = f""

f, If A > 1, calculated c and determine the maximum value for the actual monitor setpoint (pCi/mL).

If A < 1, no release may be made.

If Fd < 1, no further dilution is required and the release may be made without regard to available dilution or to other I releases made simultaneously. However, it is necessary to l establish a monitor setpoint which will provide alarm should the release concentration inadvertently exceed 10CFR20 limits. This can be accomplished by establishing the adjustment factor as follows:

A = 1/ F,

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ATTACHMENT A O (Page 32 of 184)

OFFSITE DOSE CALCULATION MANUAL FIGURE 2.1 M BOUNDARY FOR LIQUID EFFLUENTS '

\

.D (T

1

/ ,

t !

k j ,

i :

m'\ (,f b =Nc\A. T i

s , m . __

l .--m .

3

- ~ ~ ' -

aN -

f: 51heV['g\T e

._. s. , .

m J- -'

m

. L Y 2 1

g %:

4 t 7 --

y -

-- wenuges,m um '

\\,N

,._ m

(\ > ' t \ .-= =

.= b.

=. '-

&E=' y h-

:=:

_J -- -

25 3/91

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ATTACHMENT A O (Page 33 of 184)

OFFSITE DOSE CALCULATION MANUAL 3.0 Gaseous Effluents h)

\ Gaseous effluent releases from the Unit Vent and Radwaste f Building Vent are monitored continuously. The Unit Verit is the release point for the Fuel / Auxiliary Building, access control area, containment purge, and condenser air discharge. The Radwaste Building Vent is the release point for Waste Gas Decay Tanks and the Radwaste Building Ventilation System.

Waste Gas Decay Tank releases and Containment Building releases are treated as batch releases. Maste Gas Decay Tank releases are monitored by the Radwaste Building Exhaust Monitor.

Containment Building releases (purges) are monitored by the Containment Purge System monitors and the Plant Unit Vent Monitor.

Monitor identifications are as follows:

Mnn{ tor ID Relaman Point Description 0-GT-RE-21 A and B Unit Vent (Fuel / Auxiliary Building, access control area, containment purge, condenser air discharge) 0-GH-RE-10 A and B Radwaste Building vent (Radwaste Building, waste gas decay tank discharge. Acts to isolate Waste Gas Decay Tank discharge) 0-GT-RE-22 & 23 Containment Purge System Monitor (acts to isolate the purge; is not an effluent monitor) 0-GT-RE-31 & 32 containment Atmosphoro Monitor (acts to isolate purge; not an effluent monitor)

The setpoint for monitors may be determined either based on total body dose or skin dose rate. The dose rate limits are for dose rates at the unrestricted area boundary. The monitor setpoint is the lesser of the total body dose rate or skin dose rate.

(

I l

H 2

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3.1 Dona nata h iinnan with 10 crn 20 l The dose rate due to radioactive materials released in gaseous <

g effluents from the site to areas at and beyond the SITE BOUNDARY (see Figure 3.1) shall be limited to the following:

a. For noble gases: Less than or equal to 500 mrems/yr to the whole body and less than or equal to 3000 mrems/yr i to the skin, and I l

b. For Iodine-131 and 133, for tritium, and for all l radionuclides in particulate form with half-lives l greater than 8 days: Less than or equal to 1500 mrems/yr to any organ. l 3.1.1 Restadial Action With the dose rate (s) exceeding the above limits, immediately restore the release to within the above limit (s). l 3.1.2 surveillance _Raquiramants j The dose rate to radionuclides in gaseous effluents shall be l I

determined to be within the above limits in accordance with the methodology described below by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 3-1. 3/.92 !

Based on the methodology of NUREG-0133;

a. Release rate limit for nobles gases:

[KdX / Qp, < 500 mrem / yr for the total body, and (L, + 1.1 M XX i / Q) Q, < 3000 mrem / yr for the skin Where:

Ki = Total body dose factor due to gamma emissions for each identified noble gas radionuclide, in mrem /yr l per Ci/m3, from Table A.1-2.

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ATTACHMENT A O (Page 35 of 184)

N OFFSITE DOSE CALCULATION MANUAL 1 (X/Q) = 2.2E-06 sec/m3, the highest calculated annual N average relative concentration at the restricted area

\ boundary in the north sector. 3/91

.9 F

Qi = Re.l. ease rate of radionuclide i from vent, in pCi/sec.

Li - Skin dose factor due to bota emissions for each identified noble gas radionuclide, in mrem /yr per pCi/m3, from Table A.1-2.

Mi - Air dose factor due to gamma emissions for each identified noble gas radionuclide, in mrad /yr per pCi/m3 from Table A.1-2.

1.1 = Conversion constant of air dose to skin dose.

b. Release rate limit for all radionuclides and radioactive materials in particulate form and radionuclides other than noble gases:

(P,)IN x (X / Q)x Q,)< 1500 mrem / yr to any organ.

Where:

Qi - The release rate of radionuclides, i, in gaseous effluent from all vent releases, in pCi/sec.

P(1}IN = The dose' parameter for radionuclides other than nobles gases for the inhalation pathway, in mrem /yr per pCi/m3 See Table A.5-1.

(r/Q) = 2.2E-06 sec/m3 (the highest annual average).

The highest calculated annual average relative concentration for estimating the dose to any individual at the unrestricted area boundary in the H sector.

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All radionuclides are assumed to be released in elemental form.

The limit is applicable to the location (unrestricted area boundary or beyond), characterized by the value of X/Q which -

j results in the maximum total body or skin dose commitment. The r factors Ki , Li , and Mi relate the radionuclide airborne concentrations to various dose rates assuming a semi-infinite cloud. These factors are taken from Table B-1 of the Regulatory Guide 1.109 and multiplied by 106 to convert pCi-1 to pCi-1 and s

listed in Table A.1-2.

The following equation for P(1}ry was taken from NUREG 0133:

P(i)IN (Inhalation);

Pmm = K' (BR) DFA (mrem / yr per Ci / m')

Where:

K' = a constant of unit conversion, 106 pCi/pci.

BR = the breathing rate of the child age group in 3

m /yr DFAi = the maximum organ inhalation dose factor for the child age group for the i th radionuclide, in mrem /pci. The total body is considered as an organ in the selection of DEA 1 The age group considered is the child group. The child's breathing rate is taken as 3700 m3/yr from Table E-5 of Regulatory Guide 1.109. The inhalation dose factors for the child, DFAi are presented in Table E-9 of Regulatory Guide 1.109, in units of mrem /pCi.

Resolutions of the units yield:

Pi (Inhalation) = 3 . 7 X 109 DFAi The Pi value for tritium is:

Pi (Inhalation) = 3 . 7 x 109 DFAi

-- -+ -

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ATTACHMENT A O

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OFFSITE DOSE CALCULATION MANUAL TABLE 3-1 j

! M RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM <

\ GASEOUS, SAMPLING MINIMUM TYPE OF ACTIVITY LOWER

RELEASE TYPE FREQUENCY ANALYSIS ANALYSIS LIMIT OF I FREQUENCY DETECTION I (LLD) (1) ]

(pCi/ML) j Principal Gam:na P P 1x10' l

1. Waste Gas Each Tank Each Tank Emitters (2) I Decay Tank Grab Sample '

Principal Gamma

~

P P 1x10'

2. Containment Each Purge Each Purge Emitters (2)

Purge or Vent (3) Grab (3)

Sample M 1x10' H-3 (oxide) ~

M(3), (4) M(3) Principal Gamma 1x10'

3. Unit Vent Grab Sample Emitters (2) ~

)

M(4) 1x10"

~

H-3 (oxide)

M I M Principal Gama 1x10 '

5. Radwaste Grab Sample Emitters (2)

Building Vent M 1x10' H-3 (oxide)

Continuous 1x10

6. Release (6) W(7) I-131 Types as listed in 3.

and 5. above

~

Charcoal 1x10'"

Sampic I-133 Principal Gamma continuous W(7) 1x10 "

(6) Particulate Emitters (2)

Sample Continuous M Particulate 1x10

(6) Sample Gross Alpha Composite Continuous Q Composite 1x10~"

(6) Particulate Sr-89, Sr-90 Sample 12/91

- -+ - _

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ATTACHMENT A O (Page 38 of 184)

M OFFSITE L003 CALCULATION MANUAL

\

~

N TABLE 3-1 (Continued)

TABLE NOTATIONS

\. (1) The LLD is defined, as the smallest concentration of radioactive f material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5%

probability of falsely concluding that a blank observation represents a 'real" signal.

For a particular measurement system, which may include radiochemical separation:

LLD = 4.66 s*

E x V x (2.22E +6)x Y x Decay Where:

LLD = the "a priori" lower limit of detection (microcurics per unit mass or volume),

sb = the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate, (counts per minute), sn - Va / LT Where: B = background sum (counts)

LT = live time (minutes),

E = the counting efficiency (counts per disintegration),

V = the sample size (units of mass or volume),

2.22E-6 = the number of disintegrations per minute per microcurie, Y = the fractional radiochemical yield, when applicable, Decay = decay factor (s), There are three decay factors that may be appropriate for use depending on the nature of the sample and the half life of the nuclide. Any combination of the three may be used. The factors are as follows:

A) This decay factor corrects for decay from the time of sampling to the start of the analysis, eMts, where:

Ats = decay time = acquisition start time - sample time 4/P2

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ATTACHMENT A O (Page 39 of 184)

\

TABLE 3-1 (Continued) h) .

TABLE NOTA"' IONS

\

(r A = In2/ half-life B) This decay factor corrects for decay during the analysis.

i 1-e" A x RT A = In2/ half-life RT - real time of counting C) This decay factor corrects for decay during sampling.

1-e*

Aatd A = In2/ half-life Atd = deposition time = sample time - deposition start time 4/92 MQ23 All times used in decay calculations should be in the same units.

Typical values of E, V, Y, t s, td should be used in the calculation.

It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as at a posteriori (after the fact) limit for a particular measurement.

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ATTACHMENT A o (Page 40 of 184)

N

~

N TABLE 3-1 (Continued)

TABLE NOTATIONS -

(2) The principal gamma emitters for which the LLD specification applies !

7 include the following radionuclides: Kr-87, Kr-88, Xe-133, 133, Xe-133m, Xe-135, and Xe-138 in noble gas releases and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, I-131, Cs-134, Cs-137, Ce-141 and Ce-144 in iodine and particulate releases. This list does not moan that only thoco nuclides are to be considered. ocher gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the semiannual Radioactive Effluent Release Report in the format outlined in Regulatory Guide 1.21, Appendix B, Revision 1, June 1974.

(3) Sampling and analysis shall also be performed following shutdown, startup, or a THERMAL POWER change exceeding 15% of RATED THERMAL POWER within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period.

(4) Tritium grab samples shall be taken and analyzed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the refueling canal is flooded.

(5) The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with Sections 3.1, 3.2 and 3.3.

(6) Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after changing, or after removal from sampler. For unit vent, sampling shall also be performed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for a least 7 days following each shutdown, startup or THERMAL POWER change exceeding 15% of RATED THERMAL POWER within a 1-hour period, and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of changing. When samples collected for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months are analyzed, the corresponding LLD's may be increased by a factor of 10. This requirement does not apply if: (1) analysis shows that the DOSE EQUIVALENT I-131 concentration in the reactor coolant has not increased more than a factor of 3, and (2) the noble gas monitor shows that effluent activity has_not increased more than a factor of 3.

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I\ OFFSITE DOSE CALCULATION MANUAL l

h 3.2 Dona - c - li=nem With 10 CFR 50 Anpand4w I

\ .

a 3.2.1 Noble Games T

The e3r dose due to noble gases released in gaseous effluents, fron e.ith unit, to areas at and beyond the SITE BOUNDARY (see Figure 4.1) shall be limited to the following:

a. During any calendar quarter: Less than or equal to 5 mrads for gamma radiation and less than or equal to 10 mrads for beta radiation, and

b. During any calendar year: Less than or equal to 10 ;

mrads for gamma radiation and less than or equal to 20 mrads for beta radiation.

3.2.1.1 Ramadial Action With the calculated air dose from radioactive noble gases ir gaseous ef fluents exceeding any of the above limits, prepar and I l

submit to the Commissica within 30 days, pursuant to Technical Specification 6.9.2, a ,1pecial report that identifies the cause(s) for exceeding the limit (s) and defines the corrective j actions that have been taken to reduce the releases and the '

proposed correccive actions to be taken to sasure that subsequent releases will be in compliance with the above limits.

3.2.1.2 Surveillanca Requiramanta Cumulative dose contributions for the current calendar quarter and calendar year for noble gases shall be determined in accordance with the following methodology at least once per 31 ;

l days. The doce calculations for the actual releases of l radioactive noble ganes in gaseous effluent will be consistent i

with the methodology provided in Reg. Guide 1.109, Rev. 1. The following dose calculations will be performed: 3/$2 i

a. During any calendar quarter; For gamma radiation; D = 3.17E-8 [M, (X/ Q)x Q[ s S mrad.

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Reference Use Page 46 of 188 ATTACHMENT A (Page 42 of 184) I l OFFSITE DOSE CALCULATION MANUAL For beta radiation: 1 i

D = 3.17E-8 Ni (X/Q)xQ,f10 mrad.

b. During any calendar years For gamma radiation; D = 3.17E-8 [Mi (X/Q)x Q,f10 nuad.

j i-l For beta radiation:

D=

l

.17E-8 [N i-i i

(X / Q)x Qh 20 mrad.

Where l 3.17 E-8 = The inverse of the number of seconds in a year.

Mi - The air dose factor due to gamma emissions for each identified noble gas radionuclide, in mrad /yr per pCi/m3 from Table A.1-2 (Reg. Guide 1.109, Table B-1, Col. 4).

Ni =

The air dose factor due to beta emissions for each identified noble gas radionuclide, in mrad / year per Ci/m3 from Table A.1-2 (Reg. Guide 1.109, Table B-1, Column 2).

(X/Q) = 2.2E-06 sec/m3, the highest calculated annual average relative concentration at the restricted area boundary in the north sector.

Qi - The release of noble gas radionuclides, 'i', in gaseous effluents, in Ci. Releases shall be cumulative over the calendar quarter or year as appropriate.

An average monthly air dose schedule should be setup to ensure {

section 3.2.1 is not exceeded. The average monthly air dose i should be as follows:

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'O ATTACHMENT A (Page 43 of 184) lg OFFSITE DOSE CALCULATION MANUAL 1y a. For gamma radiation s 1.6 mrad /mo.

l

\

j For beta radiation s 3.3 mrad /mo.

r If the monthly average air doses for: (a) is exceeded, it should be noted that if the release is continued at the same (or higher) frequencies or activities the quarterly limit of Section 3.2.1.A will be exceeded.

b. For gamma radiation s 0.0 mrad /mo.

For beta radiation s 1.6 mrad /mo.

If the monthly average air doses for: (b) is exceeded, it should l be noted that if the release is continued at the same (or higher) frequencies or activities the annual limit of Section l 3.2.1.B will be exceeded.

If any of the above monthly average air doses are exceeded,

! evaluation of the causes of the high air dose should be l performed and steps should be taken to reduce the activity or frequency (e.g. delay the release of a Waste Gas Decay Tank) of the release.

l 3.2.2 *=dioindin=m. Particulatam and O*har D=dinnnelid==

! The dose to a MEMBER OF THE PUBLIC from Iodine-131 and 133, I tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released, from

! each unit, to areas at and beyond the SITE BOUNDARY (see Figure 1.1) shall be limited to the following:

a. During any calendar quarter: Less than or equal to 7.5 mrems to any organ; and

b. During any calendar year: Less than or equa: to 15 mrems to any organ.

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3.2.2.1 namadini Action

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g-With' the calculated dose from the release of Iodine-131 ard 133, tritium, and radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a special report that identifies the cause(s) for exceeding the limits and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

3.2.2.2 surveillance naquirementa Cumulative dose contributions for the current calendar quarter and current calendar year for Iodine-131 and 133, tritium, and radionuclides in particulate form with half-lives greater than 8 days shall be determined in accordance with the following methodology at least once per 31 days. To show compliance, the dose calculations for the actual releases of.the subject materials are consistent with the methodology provided in Regulation Guide 1.109, Revision 1. The following dose calculations will be performed:

a. D (mrem) = 3.17E-8 R,[WQ,)]s 7.5 mrem

b. D (mrem) = 3.17E-8 R,[WQ,)]s 15 mrem 3/s2 Where4 3.17 E-8 = The inverse of the number of seconds in a year.

4

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ATTACIE4ENT A l 0

(Page 45 of 184) g OFFSITE DOSE CALCULATION MANT7AL

{g Qi - The release of radiciodines, radioactive materie.ls in particulate form and radionuclides other 1 A than noble gases in gaseous effluents, 'i', in pCi. j F Releases shall be cumulative over the calendar quarter l

or year as appropriate. The 01 value shall be determined as the product of the flow rate through the release point and grab samples of the effluent analyzed in accordance with Table 3-1.

W = The annual average dispersion parameter for estimating the dose to an individual at the controlling location.

W = (X/Q), 2.2 x 10-6 sec/m3 for the inhalation pathway.

W = (D/Q), 1.8 E-8 m-2, for the food and ground plane pathways.

Ri - The dose factor for each identified radionuclide, 'i', in-mrem /yr per pCi/m3 See Table A.5-2 through Table A.5-20.

Where:

Inhalation Path.vay Factor, RI l [X/Q)

R5 [X / Q] = K' (BRl(DFA,), (mrem / yr per pCi / m')

Where:

K' = a constant of unit conversion, 10 6 pCi/ C1. I (BR) a = The breathing rate of the receptor of age group (a), in m3/yr.

The breathing rates (BR)a for the various age groups are tabulated below, as given in Regulatory Guide 1.109, Table E-5.

Anu annUp fa) BREATMTNG RATE (d g Infant 1400 Child 3700 Teen 8000 Adult 8000

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( g -

(DFA1)a = The maximum organ inhalation dose factor for the receptor of age group (a) for the i th y

j.D radionuclide, in mrem /pCi. The body is considered as ,

tr an organ in the selection of (DFA )1a. See Tables l A.2-1, A.2-2, A.2-3, & A.2-4. From Regulatory Guide

, 1.109, Tables E-7,E-8, E-9 and E-10. 1 i

Ground Plane Pathway Factor, RG g[p/g) 8 R 6 (D/Q]= K'K" (SF)DF0f.c-','h, m' h miem/yr per pCi/ soc)

Where:

K' = A constant of unit conversion, 106 pCi/pC1.

l K" = A constant of unit conversion, 8760 hr/ year.

l A,1 = The decay constant for the i th radionuclide, sec-1 t = The exposure time, 4.73 E8 sec (15 years).

DFGi= The ground plane dose conversion factor for the l 1 th radionuclide (mrem /hr per pCi/m*) . See Table A.2-5. (Regulatory Guide 1.109, Table E-6).

l' l SF = The shielding factor (dimensionless), 0.7 (Reg.

l Guide 1.109) i Grass-Cow-Milk Pathway Factor, RC g[pfg]

RCi (D/Q] = K' F,(r)(DFLM/Y,[*i'fh' mrem / yr per pCi / sec) 1 Where:

K' = A constant of unit conversion, 106 pCi/pCi. ;

1 Qy = The cow's consumption rate, in Kg/ day (wet 4 weight), 50 kg/ day. (Reg. Guide 1.109, Table E-3).

The receptor's milk consumption rate for age Uap (a,, =in liters /yr. (Reg. Guide 1.109, Table E-5). I

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] Infant = 330 1/yr g Child = 330 1/yr -

l m' Teen = 400 1/yr l r Adult = 310 1/yr Yp = The agricultural productivity by unit area of pasture feed-grass, in kg/m2, 0.7 kg/m2 . (Reg. Guide 1.109, Table E-15)

Fm - The stable element transfer coefficients, in days / liter, see Table A.3-5. (Reg. Guide 1.109, Table E-1) r = Fraction of deposited activity retained on cow's feed grass, r=1 for radioiodine and r= 0.2 for particulates. (Reg. Guide 1.109, Table E-15)

(DFLi )a = The maximum organ ingestion dose factor for the i th radionuclide for the receptor in age group

'a', in mrem /pCi. See Tables A.3-1, A.3-2, A.3-3, and A.3-4. (Reg. Guide 1.109, Table E-11, E-12, E-13, and E-14)

Ai = The decay constant for the i th radionuclide, in sec-1 Aw - The decay constant for removal of activity on leaf and plant surfaces by weathering, 5.73 E-7'sec-1

' corresponding to a 14 day half-life).

MQ2R The fraction of the year that the cow is on pasture and the fraction of the cow feed that is pasture grass is assumed to be j 1.0, which is the most restrictive case. 1 tg - The transport time from pasture to cow, to' milk, to receptor, in sec, 1.73 E5 sec (2 days) . (Reg. Guide 4 1.109, Table E-15). ;

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}g .

Grass-Goat-Milk Pathway Factor, R$ [D/Q]

f C R a[D/Q) = K'

8 F,(r)(DFLi ),('/Y,[i'f{m mrem /yrperpCi/sec)

Where:

Op - The goat's consumption rate, in Kg/ day (wet weight), 6 Kg/ day. (Reg. Guide 1.109, Table E-3),

tg = The transport time from pasture to goat, to milk, to receptor, in sec, 1.73 E5 sec (2 days) . (Reg.

Guide 1.109, Table E-15).

all other terms are defined under the Grass-cow-Milk-Pathway Factor.

NOTE The fraction of the year that the goat is on pasture and the fraction of the goat feed that is pasture grass is assumed to be 1.0, which is the most restrictive case.

The concentration of tritium in milk is based on the airborne concentration rather than the deposition. Therefore, the RC f is based on (X/g),

C R a[X/Q) = K'K" ' F,Q,U,,(DFL,),[0.75 (0.5/ H)](mrem /yr per pCi/m')

Where:

K"' = a constant of unit conversion, 103 gm/Kg.

H = Absolute humidity of the atmosphere, 8 gm/m' (Reg. Guide 1.109).

0.75 = The. fraction of total feed that is water.

(NUREG 0133) 0.5 = The ratio of the specific activity of the feed grass water to the atmospheric water. (NUREG 0133)

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~

g Grass-Cow-Meat Pathway Factor, RM g[p/g)

\

[ R"'[D / Q] = K' F,(r)(DFiglh,f*i'ffm' mrem / yr per mci / sec)

Where:

1 Ff = The stable element transfer coefficients, in ;

days /kg, Table A.3-5. (Reg. Guide 1.109, Table E-1). I Uap = The receptor's meat consumption rate for age (a), in kg/yr. (Reg. Guide 1.109, Table E-5).

Infant n 0 Child = 41 i

Teen - 65 Adult = 110 tg = The transport time from pasture to receptor, in sec., 1.73 E6 (20 days) (Reg. Guide 1,109, Table B-15).

The concentration of tritium in meat is based on its airborne I concentration rather than the deposition. Therefore, the RM i is based on (x/Q):

1 8

R"a(X/Q) = K'K" ' F,Q,U,,(DFLa),h.75 (0.5/H)]h/yr per pCi/m )

Where:

All terms defined above.

Vegetation Pathway Factor, RVg [p/g) l l Man is considered to consume two types of vegetation (fresh and stored) that differs only in the time period between harvest and consumption, therefore:

V '

l R 4 [D / Q]= K' (DFLi '.ffsk*i'L)+hs, f g t i'hh* x mrem /yrperpCi/sec)

Where:

K' = A constant of unit conversion, 106 pCi/pC1.

l l

1

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ATTACHMENT A O (Page 50 of 184)

OFFSITE DOSE CALCULATION MANUAL L The consumption rate of fresh leafy vegetation

] Ua =

g 4

by the receptor in age group (a), in kg/yr. (Reg. Guide ;

j 1.109, Table E-5). t Q'. l

-Infant = 0 kg/yr Child = 26 kg/yr ;

Teen = 42 kg/yr )

Adult = 64 kg/yr l

US a =

The consumption rate of stored vegetation by the receptor in age group (a), Kg/yr. (Reg. Guide 1.109, Table E-5).

Infant = 0 kg/yr Child = 520 kg/yr '

Teen = 630 kg/yr Adult = 520 kg/yr fL - The fraction of the annual intake of fresh leafy vegetation grown locally. (default = 1.0) (Reg. Guide 1.109).

fg = The fraction of the annual intake of stored vegetation grown locally (default = 0.76) (Reg. Guide 1.109).

tL = The average time between harvest of leafy vegetation and its consumption, in seconds, 8.6 E4 sec (1 day). (Reg. Guide 1.109).

th - The average time between harvest of stored ,

vegetation and its consumption, in seconds, 5.18 E6 sec (60 days) (Reg. Guide 1.109, Table E-15).

Yy - The vegetation area density, 2.0 kg/m2 (Reg. l Guide 1.109, Table E-15).

All other factors previously defined.

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N OFFSITE DOSE CALCULATION MANUAL i

\

~

N The concentration of tritium in vegetation is. based on the airborne concentration rather than the deposition. Therefore, :

the RV i is based on (X/Q): i r

V R i(X/Q) = K'K"' h'.ft + Us*sf }DRyQ.75(0.5/H))h/yrperpCi/m8 )

Where:

All terms defined previously. All values indicated are default

]

values from Reg. Guide 1.109, Rev. 1.

An average monthly dose schedule should be setup to ensure Section 3.2.2 is not exceeded. The average monthly dose due to radioiodines, particulates, and other radionuclides which are included in this section should be as follows:

a. < 2.5 mrem /mo.

If the monthly average dose for (a) is exceeded, it should be noted that if the release is continued at the same (or higher) frequencies or activities the quarterly limit of Section 3.2.2.a will be exceeded.

b. < 1.25 mrem /mo.

If the monthly average dose for (b) is exceeded, it should be noted that if the release is continued at the same (or higher) frequencies or activities the yearly limit of Section 3.2.2.b ;

will be exceeded. '

If any of the above monthly doses are exceeded, evaluation of the causes should be performed and steps taken to reduce the activity or frequency of the release.

3.3 Proiactad Dasa The VENTILATION EXHAUST TREATMENT SYSTEM and the WASTE GAS HOLDUP SYSTEM shall be OPERABLE and appropriate portions of these systems shall be used to reduce releases of radioactivity when the projected doses in 31 days due to gaseous effluent releases, from each unit, to areas at and beyond the SITE BOUNDARY (see Figure 3-1) would exceed:

a. 0.2 mrad to air from gamma radiation, or 3/71

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b. 0.4 mrad to air from beta radiation, or M '

\

A

c. 0.3 mrem to any organ of a MEMBER OF THE PUBLIC.

I 3.3.1 Raanadial. Action With radioactive gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a special report that includes the following information:

a. Identification of any inoperable equipment or subsystems, and the reason for the inoperability,

b. Action (s) taken to restore the inoperable equipment to OPERABLE status, and

c. Summary description of action (s) taken to prevent a recurrence. 3/s2 3.3.2 surveil 1= nam namstr- to 3.3.2.1 Doses due to gaseous releases from each unit to areas at and beyond the SITE BOUNDARY shall be projected at least once per 31 days in accordance with the following methodology when Gaseous Radwaste Treatment Systems are not being fully utilized.

Dai = x 31 Where:

D31 = Projected 31 day dose A = Cumulative dose for previous three months T = Number of days that the cumulative dose occurred in A above 22/95 3.3.2.2 The installed VENTILATION EXHAUST TREATMENT SYSTEM and WASTE GAS HOLDUP SYSTEM shall be considered OPERABLE by meeting Section 3.1 and 3.2 limits.

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] 3.4 Instrumentation

\

j The radioactive gaseous effluent monitoring instrumentation r channels shown in Table 3-2 shall be OPERABLE with their Alarm / Trip Setpoints set to ensure that the limits of Section 3.1 are not exceeded. The Alarm / Trip Setpoints of these channels meeting Section 3.1 shall be determined and adjusted in accordance with the methodology and parameters of Section 3.4.4 below. ;

3.4.1 Ramadial Action

a. With a radioactive gaseous effluent monitoring instrumentation channel Alarm / Trip Setpoint less conservative than required by the above specification, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel, or declare the channel inoperable.

b. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE take the ACTION shown in Table 3-2. Restore the inoperable instrumentation to OPERABLE status within the time specified in the ACTION, or explain in the next Annual Radioactive Effluent Release Report, why this inoperability was not corrected within the time specified. 9/93 3.4.2 surveillance Reauir===nts Each radioactive gaseous effluent monitoring instrumentation ,

channel shall be demonstrated OPERABLE by performance of the l CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and ANALOG CHANNEL OPERATIONAL TEST at the frequencies shown in Table 3-3.

3/91

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OFFSITE DOSE CALCULATION MANUAL TABLE 3-2 M

RADIOACTIVE GASBOUS EFFLUENT MONITORING INSTRUMENTATION

\ INSTRIDENT MINIMt]M APPLIckBILITY ACTION

.A CHAMMELS I QEEE&BLE

1. Unit Vent System

a. Noble Cao Activity 1

40 Monitor - Providing Alarm (GT-RE-21B) '

b. Iodine Sampler (GT-RE-21A) 1

43 l

c. Particulate Sampler (GT-RE-21A) 1

43 l

d. Flow Rate N.A.

45

e. Sampler Flow Rate 1

39 Monitor

2. Containment Purge System

a. Noble Gas Activity Monitor - 41 Providing Alarm and Automatic 1

Termination of Release (GT-RE-22, GT-RE-33)

b. Flow Rate N.A.

45 l

3. Radweste Building Vent System

a. Noble Gas Activity Monitor - 38,40 Providing Alarm and Automatic 1

Termination of Release (GH-RE-10B)

b. Iodine Sartpler(GH-RE-10A) 1

43 l

c. Particulate Sampler (GH-RE-10A) 1

43 l

d. Flow Rate N.A.

45

e. Sampler Flow Rate Monitor 1

39 12/92

At all times.

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TABLE 3-2 (Continued) l M TABLE NOTATIONS '

\ ACTION STATEMENTS

.0

i ACTION 38 - With the number of channels OPERABLE less than required by.the ;

minimum channels OPERABLE requirement, the contents of the tank (s) may be released to the environment for up to 14 days provided that prior i to initiating the release: l i

a. At least two independent samples of the tank's contentu are analyzed, and l

b. At least two technically qualified members of the facility staff independently verify the release rate calculations and discharge valve lineup.

1 Otherwise, suspend release of radioactive effluents via this pathway. 1 ACTION 39 - With the number of channels OPERABLE less than required by the I minimum channels OPERABLE requirement, effluent releases via this l pathway may continue for up to 30 days provided the flow rate is- l estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

ACTION 40 - With.the number of channels OPERABLE less than required by the ,

minimum channels OPERABLE requirement, effluent releases via this J pathway may continue for up to 30 days provided grab samples are taken I at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and these samples are analyzed for radioactivity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 41 - With the number of channels OPERABLE less than required by the minimum channels OPERABLE requirement, immediately suspend PURGING of radioactive effluents via this pathway. l ACTION 43 -

With the number of channels OPERABLE less than required by the j minimum channels OPERABLE requirement, effluent releases via the l affected pathway may continue for up to 30 days provided samples are continuously collected with auxiliary sample equipment as required in Table 3-1.

ACTION 45 - Flow rate for this system shall be based on fan status and operating curves or actual measurements. 3/92 i

I l

-=

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NO (Page 56 of 184)

\\ OFFSITE DOSE CALCULATION MANUAL m ;

RADInnt*fIVE n1C!EOffa EFFTITENT MONITonfun Tum rui-s-rmTION BimVETT T ANCE REQUIR]DMNTS INSTRUMENT CHAMMEL M CHANNEL ANAIZXI S MODES FOR ,

CHECK CHECK CALIBRATION CHANNEL HEICH I

(I OPERATIONAL sta vatt.t.mwea 2ESI IS REOUIRED

1. Unit Vent System

a. Noble Gas Activity Monitor- D M R(3) Q(2)

Providing Alam (GT-RE-21)

b. Iodine Sampler N N.A. N.A. N.A. *

c. Particulate Sampler W N.A. N.A. N.A. *

d. Flow Rate N.A. N.A. R (4 ) N.A. *

e. Sampler Flow Rate Monitor D N.A. R Q *

2. Containment Purge System

a. Noble Gas Activity Monitor- D P R(3) Q(1)

Providing Alam and Auto- .

matic Termination of Re- l lease (GT-RE-22, GT-RE-33) I

b. Iodine Sampler W N.A. N.A. N.A. *

c. Particulate Sampler N N.A. N.A. N.A. *

d. Flow Rate N.A. N.A. R(4) N.A. *

e. Sampler Flow Rate Monitor D N.A. R N.A. *

3. Radwasta Building Vent Syatem

a. Noble Gas Activity Monitor- D,P M,P R(3) Q(1)

Providing Alarm and Auto-matic Temination of Release (GH-RB-10)

b. Iodine Sampler N N.A. N.A. N.A. *

c. Particulate Sampler W N.A. N.A. N.A. *

d. Flow Rate N.A. N.A. R (4) N.A. *

e. Sampler Flow Rate Monitor D N.A. R N.A.

3/R e *At all times.

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M

\\r OFFSITE DOSE CALCULATION MANUAL TABLE 3 (Continued)

$) TABLE NCYfATIONS gg . ' .

.# (1) f The ANALOG CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation as appropriate occur if any of the following conditions exists:

a. Instrument indicates measured levels above the Alarm / Trip Setpoint (isolation and alarm), or

b. Circuit failure (alam only), or c.

Instrument indicates a downscale failure (alarm only) or

d. Instrument controls not set in operate mode (alarm only) .

(2)

The ANAIOG CHANNEL OPERATIONAL TEST shall also demonstrate that control room alarm annunciation occuro if any one or combination of the following conditions exists:

a. Instrument indicates measured levels above the alarm setpoint

b. Circuit failure

c. Instrument indicates a downscale failure

d. Instrument controls not set in operate mode.

(3) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference (gas or liquid and solid) standards certified by the National Institute of Standards and Technology (NIST) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards shall pemit calibrating the syste.1 over its intended range of energy, measurement range, and establish monitor response to a solid calibration source. For subsequent CHANNEL CALIBRATIOh, !

NIST traceable standard (gas, liquid or solid) may be used; or a gas, liquit'.. j or solid source that has been calibrated by relating it to equipment that eras

{

previously (within 30 days) calibrated by the same geometry and type of source traceable to NIST.

(4) If flow rate is determined by exhaust fan status and fan performance curves, the following surveillance operations shall be performed at least once per 18 months:

a. The specific vent flows by direct measurement, or I

b. The differential pressure across the exhaust fan and vent flow established by the fan's " flow- P" curve, or

c. The fan motor horsepower measured and vent flow established by the fan's " flow-horsepower" curve. 3/DI

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\ OFFSITE DOSE CALCULATION MANUAL l 3.4.3 Airborna mmdiation maniter calibration um+hadoloav M

\ The following monitors are associated with gaseous releases

.0 I Mnn4 tor ID Mnniter Descrint4nn Mnniter Tvne i l

O-GT-RE-21A Plant Unit Vent Particulate, Iodine 0-GH-RE-10A Radwaste Building Effluent Particulate, Iodine o-GT-RE-21s Plant Unit Vent Wide Range Gas 0-GH-RE-10B Rar1 waste Building Effluent Wide Range cas o-GT-RE-22 t. 33 Containment Purge Exhaust Particulate, Iodine, Gas o-GT-RE-31 Ts 32 Containment Atmosphere Particulate, Iodine, Gas 3.4.3.1 Particulate Detector Beta particulate is monitored by a 50 mm diameter by 0.25 mm thick plastic scintillator optically coupled to a 50 mm diameter photomultiplier tube. This detector shall be calibrated over its range of energy and rate capabilities.

For energy range calibration four sources shall be used. Each source consists of a filter paper impregnated with a beta emitting radionuclide. The radionuclides used should be Tc-99, Cs-137, Cl-36, and Rh-106. Each source shall be positioned in the filter paper retaining ring and counted separately. The count rates for each radionuclide source shall be recorded and the data plotted on a graph of cpm /pci versus average beta energy. This curve represents the detectors response characteristics over the range of beta energies observed. The efficiency for setpoint calculations shall be based on the efficiency of the detector for Cs-137.

The detector shall be calibrated for its rate capabilities using a filter paper impregnated with standard activities of Cs-137.

Increasing amounts of a standard Cs-137 solution chall be impregnated on a filter paper. The counts per minute for each Cs-137 standard shall be recorded. A determination of linearity shall be produced using the counts per minute vs. concentration l data. At least three sources covering approximately M, M, and M of full scale shall be checked. 5/S5 3.4.3.2 rad 4== nate: g Iodine gas is monitored by absorbing the gas on a charcoal filter element. The charcoal filter is viewed by an NaI(Tl) integral line gamma scintillator assembly.

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\ OFFSITE DOSE CALCULATION MANUAL iN Because of its short half-life and the difficulty in handling gaseous iodine, barium sources shall be used for calibration.

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lD The photo peaks of interest are as follows:

a. Ba-133: 356 Ker gamma is 0.69 efficient / disintegration l

b. I-131: 364 kev gamma is 0.82 efficient / disintegration Therefore, each iodine disintegration will produce 0.82/0.69 x barium disintegrations. Assuming that the detector efficiency for 356 kev is the same as for the 364 kev, the sensitivity for I-131 equals 1.19 x Ba-133 (counts / min) pCi. The standard sources shall be constructed by impregnating a standard Ba-133 solution into the charcoal filter element. The geometry shall simulate the iodine retention on the first surface of the charcoal. Sources shall be prepared to cover approximately M, M and M of full scale. The barium counts per minute for each standard shall be adjusted to iodine counts per minute as l

described above. A determination of linearity shall be produced using the corrected counts per minute vs. concentration data.

5/95 3.4.3.3 Gas Detectgr The gas detectors associated with monitors O-GT-RE-22 & 33, 0-GT-RE-31 & 32 and the low-range detectors of monitors O-GT-RE-21B and O-GH-RE-10B are a plastic scintillator identical to the particulate detector. The mid-range and high-range detectors of monitors O-GT-RE-21B and O-GH-RE-10B are cadmium telluride, solid state sensors.

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\ OFFSITE DOSE CALCULATION MANUAL l~ Sources for all gas detectors shall be produced by evacuating

'g the sample chamber with a vacuum pump. The sample chamber then lf shall be backfilled to the desired pressure with a source of r standard Xe-133. The source is then counted and the counts per minute recorded. A determination of linearity shall be produced using the counts per minute vs. concentration data. Sources shall be prepared to cover approximately M, H and M of full scale for the detectors associated with monitors 0-GT-RE-22 and 33, 0-GT-RE-31 and 32 and the low-range detectors of monitors O-GT-RE-21B and 0-GH-RE-10B. Sources shall be prepared for the mid/high range detector to cover two points on the mid-range scale. For ALARA purposes, response fo:r the high-range scale shall be ext apolated using the data from the mid-range calibration. 5/95 3.4.4 Airborne unnitor setneinem ~

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3.4.4.1 Total Body Dona nata smennint calculatiana The limit of the total body dose rate is 500 mrem /yr at the l

unrestricted area boundary. The monitor alarm / trip setpoint based on total body dose will be calculated as follows

S. s (SF x AF)x D. x R, !

l j Where:

i Stb = The monitors alarm / trip setpoint based on the ;

total body dose rate. (pci/cc)

NOTE l If the monitor setpoint units needed are (pci/sec), multiply (pci/cc) calculated setpoint by the waste gas stream flow rate l (cc/sec).

12/95 Db=

t Limit of 500 mrem /yr total body, conservatively interpreted as a continuous release over a one year period.

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{g SF = Normally will be set to 0.85.

chosen since the gaseous monitors are set using Xe-133 This number is j energy level. Xe-133 comprises 85% of total noble r gaseous activity expected. (See USAR Table 11.1-1) .

If necessary the 0.85 can be further modified to compensate for statistical fluctuations and errors of measurement.

4 AF = Allocation factor for each release so that simultaneous releases can be made without exceeding the limit. Normally AF is calculated as follows:

AF = RF--

TF Where:

RF = Release flow rate of the release point under consideration.

TF = Total flow rate of all release points including release under consideration.

Rt= monitor response per mrem /yr to the total body, determined according to:

R=r 3 i

e((/Q)n[K > Qi Where:

c- The monitor response to the gaseous effluent noble gas (pC1/cc) corresponding to grab sample radionuclide concentrations.

(X/Q) = The highest calculated annual average atmospheric dispersion (sec/m3) at the restricted area boundary.

Ki= The total body dose factor due to gamma emissions from isotope i (arem/yr per pCi/m3) from Table A.1-2.

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Qi - Rate of release of noble gas radionuclide i g (pci/sec) (concentration of radionuclide i x release a_ flow rate) r 3.4.4.2 skin Dome Rata calculation The limit of the skin dose rate is 3000 mrem /yr at the restricted area boundary. The monitor alarm / trip setpoint is calculated as follows:

S, s (SF x AF)x D, x R, Where: I Sg = The monitors alarm / trip setpoint based on the skin dose rate. ( Ci/cc)

NOTE If the monitor setpoint units needed are (pci/seo), multiply the pCi/cc), calculated setpoint by the waste gas stream flow rate (cc/sec).

12/95 Ds = Limit of 3000 mrem /yr to the skin of the body, l conservatively interpreted as a continuous release over )

a one year period. j Rg = Monitor response per mrem /yr to the skin of the body.

R, = r 3 i

<(X/Q)[(L i + 1.lM )Qi Where:

Li - Skin dose factor due to beta emissions from isotope 1 (mrem /yr per pCi/m3) from Table A.1-2.

1.1 = Conversion factor to mrem skin dose per mrad air dose.

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Mi= Air dose factor due to gamma emissions from

g. isotope 1 (mrad /yr per ci/m3) from Table A.1-2.

D r The factors SF, AF, c, (E70)andQiareasdefinedinSection 3.4.4.1.

The results of equations from Sections 3.4.4.1 and 3.4.4.2 are compared to determine the smaller setpoint. The actual monitor setpoint is the lower of the two values.

A pre-release isotopic analysis is performed for batch releases from Waste Gas Decay Tanks and Containment Building purges to determine the identity and quantity of the principal radionuclides. The appropriate alarm / trip setpoint (s) are adjusted accordingly to ensure that the limits of 3.1 are not exceeded.

3.4.4.3 Alert 11=r= s.*aaint c=1en1=tia==

The Noble Gas Alert Alarm for the Plant Unit Vent (0-GT-RE-21) and Radwaste Building Exhaust Monitor (0-GH-RE-10) , is set to alert operators to that average concentration which if' maintained for a full year would result in the 10 CFR 50, Appendix I Annual Dose Guidelines being reached. Section 3.2.1 limits the annual dose due to noble gases to s 10 mrads for gamma radiation and s 20 mrada for beta radiation. Section 3.2.2 limits the annual dose to a MEMBER OF THE PUBLIC from Iodine-131, Iodine-133, tritium and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents to A 15 mrem to any organ. These two sections contain the annual dose limits due to gaseous releases found in 10 CFR 50, Appendix I.

3.4.4.3.1 nahl. m. 11.re Alar = satyaint emientation The alert alarm setpoint is the lesser of Sy1 (SF x AF) x Dy x Ry Sps (SF.x AF) x D$ x R Where:

Sy = Monitor setpoint based on gamma radiation.

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{g Dy= Limit of 10 mrad /yr conservatively interpreted as a continuous release over a one year period.

.D o- Ry = Monitor response per mrad /yr determined according to:

R, , , ,

<(X/Q)EM,n xQis Where Mi = Gamma air dose factor (mrad /yr per pCi/m3),

See Table A.1-2.

Sp = Monitor setpoint based on beta radiation.

D, = Limit of 20 mrad /yr conservatively interpreted as a continuous release over a one year period.

Rp = Monitor response per mrad /yr determined according to:

R, = y _

3

<(X/QKNs i xQ, Where:

Ni = Beta air dose factor (mrad /yr per pCi/m3).

See Table A.1-2.

A semi-fixed alert alarm setpoint for the Plant Unit Vent Monitor (0-GT-RE-21) and Radwaste Building Vent Monitor (0-GH-RE-10) is calculated using the following r 3 (10 mrad /yr)(.85XAF)

Setpom. t(pCi/cc) = r (X/Q)[P, x M, x Q o e >>

Where:

Pi = Fractional value of isotope expected, Ci/CT '

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,M Where:

,r

) Ci = Concentration in Ci/cc of isotope.

CT = Total Gaseous Activity from USAR Table 11.1-1 l AF = Either unit vent flow or Radwaste Building vont flow divided by the combined flow of the unit vent and l Radwaste Building vent.

Vent flow rate in cc/sec.

Q =

Isotopes used and Pi values are as follows:

ISOTOPE El Kr-85M .018 l

Kr-87 .010 i

Kr-88 .033 l Xe-133M .017 l Xe-133 .851 Xe-135 .051 Should this semi-fixed alert alarm cause a continuous alarm condition, then actual setpoints will be calculated.

3.4.4.4 Particulata and Iodine Alarm setc_ ointe setpoints for the gaseous effluent particulate and iodine channels are set using Cs-137 MPC for particulates and I-131 MPC for iodines. The following is the ca.lculation used:

Setpoint(pCi/cc) = (MPC,XAF)(SF)

, ( I Where:

MPCi = 5 x 10" Ci/cc for Cs-137 4

- 1 x 10 pCi/cc for I-131 i

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g AF = as defined previously SF = .0625 for I-131 *

!r i = .9375 for Cs-137

l

derived from ratio of isotope activity (either I-131 or Cs-137) to sum of activity of Cs-137 and I-131 found in USAR Table 11.1-1 for reactor coolant.

Q = Vent flow in M3/sec l

This will provide the hi alarm setpoint. The alert alarm setpoint is 10% of the hi alarm setpoint.

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FIGURE 3.1 M

' BOUNDARY FOR GASEOUS EFFLUENTS

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D T j i

4 1

I

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3 g

( ,

$[

i

- . - -- a=;

M i ; 'L .e4 a. T _

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f.h." t"- \

. a j

a \ .

c. -

- l wm W W W E550' gj gg gg $hMM W Sul 4NIIT MQ. 4 E

rim 3.1

% r., sm.a trnes eeJ emme N4es.

/\ ) % \ --

_..s y -

. L -...=.-

40 3/SI

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] 4.0 Total Dose The annual (Calendar year) dose or dose commitment to any MEMBER 7 OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.

4.1 Remindini Action With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Section 2.2a, 2.2b, 3.2.la, 3.2.lb, 3.2.2.a and 3.2.2b calculation should be made including direct radiation contributions from the units and from outside storage tanks to determine whether the above limits of Section 4.0 above has been exceeded. If such is the case, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a special report that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits. This special report, as defined in 10 CFR 20.405c, shall include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release (s) covered by this report. It shall also describe levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations. If the estimated dose (s) exceeds the above limits, and if the release condition resulting in violation of 40 CFR Part 190 has not already been corrected, the special report shall include a i request for a variance in accordance with the provisions of 40 l CFR Part 190. Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete. 3/92

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OFFSITE DOSE CALCULATION MANUAL 4.2 surveillanne Requir--- ts

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4.2.1 Cumulative dose contributions from liquid and gaseous effluents

~f shall be determined in accordance with the methodology of Sections 2.2 and 3.2 at least once per 31 days when the release of radioactive materials in liquid or gaseous effluents exceed twice the limits of Section 2.2a, 2.2b, 3.2.la, 3.2.lb, 3.2.2a and 3.2.2b. Otherwise, no further evaluation is required.3/91 4.2.2 Cumulative dose contribution from direct radiation from the reactor unit and from Radwaste storage tanks shall be determined utilizing the results of routine plane perimeter surveys, TLD l data or a combination of both, when necessary. This requirement i is applicable only under conditions set forth in the remedial action above.

5.0 Radiological Enviran==ntal unnitorina Program This section describes the Radiological Environmental Monitoring Program specified in Section 6.8.4 F of the Wolf Creek Technical Specifications.

5.1 Man 4torina Proaram

Table 5-1 provides a schedule which describes the pathways, specific locations, sample collection frequencies, and analyses 1 to be performed to implement the Radiological Environmental Monitoring Program. j Figures 5.1 through 5.5 contain maps depicting sampling locations in relation to the WCGS site. Table 5-2 lists distances and directions to these locations from the WCGS site. l Table 5-3 lists required detection capabilities for the analyses performed. 3/92

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5.2 Land Uma census M

) A Land Use Cc.nsus shall be conducted annually during the growing season to identify the nearest (1) milk animal, (2) residence, r l and (3) garden of greater than 500 squaro feet producing I broadleaf vegetation

in each of the 16 meteorological sections within five miles of the WCGS site. Methods shall be used in conducting the census that provides the best results, such as j door-to-door surveys, telephone surveys, consulting the U.S.D.A l office in Burlington, inspection of aerial photographs of the l

area, or reviewing leasing records for area farms and residences. 3/91 If a location (s) is identified which yields a calculated dose or dose commitment (via the same exposure pathway) 20% greater than at a location from which samples are currently being obtained, the new location (s) shall be added to the Radiological ;

Environmental Monitoring Progmc= sitbin 30 days as described in i Table 5-1, Note (1). The indicator sampling location (s) having l the lowest calculated dose or dose conmitment may then be deleted from the monitoring program. The revision to Table 5-1 and the corresponding Figure (s) as a result of such substitutions shall be documented in accordance with section 6.14 of the Wolf Creek Technical Specifications.

The results of the Land Use Census shall be included in the Annual Radiologirfal Environmental Operating Report described in Section 7.1.

5.3 Interl=ha-atorv ca===riman Prear==

The analysis laboratory contracted to analyze samples from the Radiological Environmental Monitoring Program participates in the EPA Laboratory Intercomparison Program or similar program.

12/95

Broad leaf vegetation sampling of available vegetution may be performed at the site boundary in each of two different direction sectors with the highest predicted D/Qs in lieu of the garden census. Specifications for broad leaf vegetation sampling in Table 5-1, Part 4.c. shall be followed, including analysis of control samples. 3/91 i

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A summary of intercomparison results shall be included in the M Annual Radiological Environmental Operating Report described in

\ Section 7.1.

D 5.4 Reporting Requiramanta 5.4.1 Annumi n=dioloaical Envirnn==ntal Ocarating Renort To meet the requirements of Wolf Creek Technical Specification l 6.9.1.6, the Annual Radiological Environmental Operating Report covering the previous year of operation shall be submitted to the NRC by May 1 of each year. The content of this report is described in Section 7.1. 22/94 5.4.2 special naparta A special report shall be prepared and submitted to the NRC within 30 days if levels of radioactivity as a result of plant effluents detected in an environmental medium at a specified location exceed the reporting levels of Table 5-4 when averaged over any calendar quarter. The special report shall identify the cause(s) for exceeding the limit (s) and define the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose

to a member of the public is less than the calendar year limits of Wolf Creek Technical Specification 6.8.4.e. When one or more of the radionuclides in Table 5-4 is detected in the sampling medium, this report shall be submitted if:

Concentration (1) + Concentration (2) +..>1.0 Reporting Level (1) Reporting Level (2)

When radionuclides other than those in Table 5-4 are detected and are the result of plant effluents, this report shall be l submitted if the potential annual dose

to a member of the public from all radionuclides is equal to or greater than the calendar year limits of Technical Specification 6.8.4.e.

1

The methodology and parameters used to estimate the potential annual dose to a member of the public shall be indicated in this report. 3/92 i

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TABLE 5-1 h) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM i 1

,0 evanmura pathwav/ Mn=har cf C=" lam anA Emmni e r'n11act i nn Tyne and Pracrumnev 0" s==m1= Tvna

7 a1 Teaatinna (1) Freouanev of inm1vm4m

1. AIRBORNE FIGURES 5.1 & 5.5 Radioiodine and Samples from five locations Continuous sampler Analyze radiciodine l Particulates operation with canister weekly for l F2mple collection I-111 j weekly, or more fre-quently if required by dust loading I Samples from locations near the site boundary in three sectors having the highest calculated annual average D/O (locations 2,3 & 37 on l Figure 5.1);

1 Sanple from the vicinity of Analyze particulate i a community having the filter weekly for !

highest calculated annual gross beta activity average D/Q(Location 32 on (2); perform quar-Figure 5.1, New Strawn); terly gamma isotopic analysis (3)compo-site (by location).

Sample from a control location 10-20 miles dis-tant in a low D/0 sector (Location 40 on Figure 5.5). (11)

2. DIRECT FIGURES 5.2 AND 5.5 RADIATION (4) 40 routine monitoring sta- Quarterly Gamma dose quarterly tions with two or more dosimeters measuring dose continuously, placed as follows:

An inner ring of stations, l one '.n each meteorological 6ector 0-3 mile range from the site (Locations 1,7-9,11-13, 18, 26, 27, 29-31, 12/S4 37, & 38 on Figure 5.2).

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TABLE 5-1 (Continued)

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J r w ance pathwav/ Ninehar of emelen and C ==1 m collectinn Tvna and Frm,visanc v g- s*7 e1 Tvne n==le fmcatinna (1) Precuency of Analvnin DIRECT RADIATION An outer ring of stations, (4) (CONTINUED) one in each meteorological sector in the 3 to 5 mile range from the site (Loca-tions 4-6, 15-17, 19-25 and 33-36 on Figure 5.2).

Five sectors (A,B,D,G & Ll contain an additional sta-tion (Locations 2,3,10, 14 and 28) II/M The balance of the stations to be placed in opecial interest areas such as population centers (Loca-tions 23 and 32), nearby residences (many locations are near a residence),

schools (Location 23), and j in one or two areas to serve as control stations 10-20 miles distant from the site (Locations 39 and 40 on Figure 5.5) (11) l

3. NATERBORNE FIGURE 5.3 Surface one sample upstream (5) Monthly grab sample Monthly gamma iso-(Location MUSH on Figure topic analysia (3) l S.3) and one sangle down- and composite for stream (Location DC on tritium analysis Figure 5.3) quarterly.

I Ground Samples from one or two Quarterly Quarterly gamma '

sources only if likely to isotopic analysis be affected (3) and tritium analysis.

Indicator samples at loca-tions hydrologically down-gradient of the site (Loca-tions C-10, C-49 and D-65 on Figure 5.3); control sample at a location hydro-logically upgradient of the site (Location B-12 on Figure 5.3) (6)

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TABLE 5-1 (Continued) h) RADIOLOGICAL ENVIROIDEIFfAL MONITORING PROGRAM

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,j) m y mura Dae h v/ Mumbar of Bamplaa and a - la en11act 4 an ivna and Irra- ==>v g- Sample Type "7m 1 f"

Plana fi) Frecuency of Analyain

3. NATERBORNE Sample of municipal water Monthly composite Monthly gamma iso-(CONT.) supply at an indicator (7) topic analysis (3)

Drinking location downstream of the and gross beta site (Location LN-40 on analysis of compo-Figure 5.5): control sample site sample.

from location upstream of Quarterly tritium the site (Location BW-15 on analysis of Figure 5.3) composites (B) .

Shoreline Sediment One sample from the vic- Semiannually semiannual gamma inity of Wolf Creek Cooling isotopic analysis Lake discharge cove (Loca- (3) tion DC on Figure 5.3)s contrei aample from John Redmc rA temervoir. 22/J4

4. INGESTION FIGURES 5.4 AND 5.5 Milk Samples from milking Semimonthly while Gamma isotopic animals at three indicator animals are on analysis (3) and I-locations within 5 miles of pasture (April to 131 analysis of each the site having the highest November) : monthly sample . .

dose potential (currently at other times there are no locations pro- (December-March) (9) ducing slik for human con-sumption within 5 miles of the site);one sample from a cont al location greater than 10 miles from the site (Location S-3 on Figure 5.5). (11)

Fish Indicator samples of 1 to 3 Semiannually Camma isotopic recreationally important analysis (3) on species from Wolf Creek edible portions cooling Lake (several samp-ling areas indicated in Figure 5.4): control sam-ples of similar species from John Redmond Reservoir Spillway (indicated on Figure 5.4).

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M RADIOLOGICAL ENVIRoteMNTAL MONITORING PROGRAM

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.D w.mm.u ,. p.ew v/ un.w., nee--1. g a. la en11.re 4 nn tun. nA prainimar v O' n=-ai. Tvne a*--1. r ~ .etan. m Frequancy of an.1ymin

4. INGESTION Samples of availa.ble Nonthly when Gamaa isotopic (CONT.) broadleaf vegetation from available (9) analysis (3) on Food Products two indicator loca.tions edible portions.

with highest calcalated annual average D/O (Loca- ,

tions R-1 and G-1 and l alternate Location C-1 on >

Figure 5.4); sample of similar broadleaf vegeta-tion from a control loca- ;

tion greater than 10 miles from the site in a low D/0 section (Location S 4 on 22/75 1 Figure 5.5) . (11)

Food Products Sample of crgs irrigated At time of harvest Gamma isotopic )

with water from the Neosho (10) analysis (3) on River down-stream of the edible portions ;

Neosho River-Wolf Creek j confluence (locations will ;

vary from year to year, !

e.g., Location NR-D1 fi NR-D2 on Figure 5.5).

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TABLE 5-1 (continued)

N- ' TABLE NOTATIONS . i

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~F (1) Deviations are permitted from the required sampling schedule if

, specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment, and other legitimate reasons. If specimens are unobtainable due to sampling equipment malfunction, every effort shall be made to complete corrective action prior to the end of the next sampling period. All deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report described in Section 7.1.

It is recognized that, at times, it may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time. In these instances, suitable specific alternative media and locations may be chosen for-the particular pathway in question and appropriate substitutions made within 30 days.

Revisions to this Table and to the corresponding Figure (s) as a result of such substitutions shall be documented in accordance with Section 6.14 of Wolf Creek Technical specifications. This documentation shall provide information identifying the cause of the unavailability of samples for that pathway and justifying the selection of the new location (s) for obtaining samples.

(2) Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or more after sampling to allow for RN-220 and Rn-222 daughter decay. If gross beta activity in air particulate samples are greater than 10 times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples.

(3) Gamma isotopic analysis means the identification and quantification of ,

gamma-emitting radionuclides that may be attributable to the effluents !

from the facility.

(4) One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters. For the purposes of this table, a thermoluminescent dosimeter (TLD) is considered to be one phosphor; two or more phosphors in a packet are considered as two i or more dosimeters. Film badges shall not be used as dosimeters for measuring direct radiation. The 40 stations are not an absolute number. The number of direct radiation monitoring stations may be reduced according to geographical limitations, e.g., some sectors are over water so that the number of dosimeters may be reduced accordingly. The frequency or analysis or readout for the TLD system

-depends upon the characteristics of the specific system used and is selected to obtain optimum dose information with minimal fading. 3/.92

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TABLE 5-1 (continued) l M TABLE NOTATIONS

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8 ' (5) The " upstream" sample is taken at a distance beyond significant !

F influence of the discharge. '

(G) Ground water samples shall be taken when this source is tapped for l drinking or irrigation purposes in areas where the hydraulic gradient i or recharge properties.are suitable for contamination.

(7) A composite sample is one in which the quantity (aliquot) of liquid sampled is consistent over the sampling period and in which the method ;

of sampling employed results in a specimen that is representative of j the liquid concentrate. In this program, composite sample aliquots ;

shall be collected at time intervals that are very short (e.g., every ;

to assure obtaining a representative sample. I 1

(8) If the dose calculated for consumption of water (using ODCM methodology and parameters) exceeds one millirem per year, composite sampling at the indicator location shall be performed every two weeks and I-131 analysis shall be performed on the composite samples.

(9) Milk ead broadleaf vegetation samples are often temporarily, but not perusuantly, unavailable at the scheduled sample collection times.

Alternate sampling locations may therefore be listed in the Table and used at these times to provide continued monitoring of these pathways.

If samples are considered permanently unavailable at a location, another location will be selected (if available) as described in Note (1).

(10) If harvest occurs more than once a year, sampling shall be performed during each discrete harvest. If harvest occurs continuously, sampling shall be monthly. Attention shall be paid to including samples of tuberous and root food products.

(11) The purpose of this sample is to obtain background information. If it is not practical to establish control locations in accordance with the distance and wind direction criteria, other sites that provide valid background data may be substituted. 3/$1 i l

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TABLE 5-2 M SAMPLING LOCATION NUMBERS, DISTANCES (miles) AND DIRECTIONS

\ ' Air Particulate S Location Distanea/

F Number Direction 2 2.7/N 3 3.0/NNE 32 3.2/WNW 37 2.1/NNW 40 >15.0/WNW

.TLR Location Diseance/ Location Diseance/ Location Dime nnea / Location Diaranem/

Number Direction Number Direction Number Direction Number Direction 1 1.4/N 11 1.6/E 21 3.8/S 31 3.0/WhW 2 2.7/N 12 1.8/ESE 22 4.1/SSW 32 3.2/WNW 3 3.0/NNE 13 1.5/SE 23 4.5/SW 33 3.7/WNW 4 4.0/NNE 14 2.6/SE 24 4.1/WSW 34 4.0/NW 5 4.0/NE 15 4.5/ESE 25 3.6/W 35 4.6/NNW 6 4.4/ENE 16 4.2/E 26 2.6/WSW 36 4.2/N 7 1.9/NE 17 3.6/SE 27 2.1/SW 37 2.1/NNW 8 1.6/NNE 18 3.0/BSE 20 2.8/SW 38 1.2/NW l 9 2.0/ENE 19 4.0/SSE 29 2.6/SSW 39 13.0/N 10 2.4/ENE 20 3.3/S 30 2.2/W 40 >15.0/WNW Groundwater Drinkina water Surface Water B-12 2.2/NNE BW-15 3.9/SW MUSH 3.6/W C-10 2.8/W LW-40 >10/SSE DC 0.6/WNW C-49 2.9/SW D-65 3.9/S Milk & FQQd Products C-1 2.6/NE R-1 2.1/NNW G-1 1.6/SE S-3 >15.0/WNW l S-4 >15.0/WNW M Shorelina gart4mmnta Irriaated Crone WCCL DC 0.6/WNW NR-D1 9.2/S l Jan 4/W Jan 4/W NR-D2 >10/S l 12/95

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TABLE 5-3

h): DETECTION CAPABILITIES FOR ENVIRO 3 MENTAL SAMPLE ANALYSIS *

(a,33 l\ Lower Limit of Detection.(LLD) lA lr AIRBORNE SEDIMENT PARTICULATE FOOD (pCi/kg, WATER OR GAS FISH MILK PRODUCTS dry)

ANALYSIS (pCi/1) (pCi/m') (pC1/kg, wet) (pC1/1) (pCi/kg, wct) _

Gross Beta 4 0.01 H-3 2000(4)

Mn-54 15 130 Fe-59 30 260 Co-58,60 15 130 En-65 30 260 Zr-Nb-95 15 I-131 1(5) 0.07 1 60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-La-140 15 15 3/.9.1 i

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j- TABLE 5-3 (continued)

!M TABLE NOTATIONS I\ .

>D.

(1) This list does not mean that only these nuclides are to be considered.

other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report described in Section 7.1.

(2) Required detection capabilities for thermoluminescent dosimeters used for environmental measurements shall be in accordance with the recommendations of Regulatory Guide 4.13, Revision 1, 1977.

i (3) The LLD is defined, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only'5%

probability of falsely concluding that a blank observation represents i a "real" signal.

For a particular measurement system, which may include radiochemical separation:

LLD = **

E V 2.22 Y exp(-A At)

Where:

LLD = the "a priori" lower limit of detection (picocuries per unit mass or volume),

Sb = the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute),

E =

the counting efficiency (counts per disintegration),

V = the sample size (units of mass or volume),

2.22 = the number of disintegrations per minute per picocurie, l

Y = the fractional radiochemical yield, when applicable, A = the radioactive decay constant for the particular radionuclide (s-1), and i 3/93 l

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TABLE 5-3 (continued) 1 N TABLE NOTATIONS

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.D

'7 At = the elapsed time between sample collection, or end I of the sample collection period, and time of counting (s) .

Typical values of E, V, Y, and At should be used in the calculation.

It should be recognized that the LLD is defined as an a priori (before j i

the fact) limit representing the capability of a measurement system '

l and not as an a posteriori (after the fact) limit for a particular measurement. Analyses shall be performed in such a manner that the j stated LLDs will be achieved under routine conditions. Occasionally l l

background fluctuations, unavoidable small sample sizes, the presence i of interfering nuclides, or other uncontrollable circumstances may l render these LLDs unachievable. In such cases, th:a contributing i factors shall be identified and described in the Annual Radiological Environmental Operating Report described in Section 7.1.

! (4) LLD for drinking water samples. If no drinking water pathway exists, a value of.3000 pCi/ liter may be used.

l (5) LLD for drinking water samples. If no drinking water pathway exists, the LLD of gamma isotopic analysis may be used. 3/92 I i

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TABI2 5-4 M REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES

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.D

AIRBORNE FOOD WATER PARTICUIKIE OR FISH MILK PRODUCTS ANALYSIS (pCi/1) GAS (pC1/m') (pCi/kg, wet) (pCi/1) (pCi/kg, wet)

H-3 20,000*

Mn-54 1,000 30,000 Fe-59 400 10,000 Co-58 1,000 30,000 Co-60 300 10,000 Zn-65 300 20,000 Zr-Nb-95 400 I-131 2 0.9 3 100 Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 Ba-La-140 200 300

For drinking water samples. This is 40 CFR Part 141 value. If no drinking water pathway exists, a value of 30,000 pCi/l may be used. 3/D1 l

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FIGURE 5.5 h)

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= AIR 80RNE PARTICULATE & RADIOlOONE 12/.92

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l ATTACHMENT A

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M OFFSITE DOSE CALCULATION MANUAL +

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6.0 Banas N :

\ The bases contained on the succeeding pages summarizes the lU general requirements of Section 2.0, 3.0, 4.0 and 5.0 of the !

ODCM. -

Section 2.0 Liquid. Effluents section 2.1 cananntration This'section is provided to ensure that the concentration of l radioactive materials released in liquid waste effluents to UNRESTRICTED AREAS will be less than the concentration levels

specified in 10 CFR Part 20, Appendix B, Table II, Column 2.

l This limitation provides additional assurance that the levels of radioactive materials in bodies of water in UNRESTRICTED AREAS will result in exposures within: (1) the section II. A design objective of Appandiv I, 10 CPR Part 50, to a MEMBER'OF THE PUBLIC, and (2) the limits of 10 CFR Part 20.106 (e) to the l

population. The concentration limit for dissolved or entrained i' L noble gases are based upon the assumption that Xe-135 is the controlling radioisotope and its MPC in air .(submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2.

The required detection capabilities for radioactive materials in liquid waste samples are tabulated in terms of the lower limits of detection (LLDs) . Detailed discussion of the LLD, and other detection limits can be found in HASL Procedures Manual, H&SL:

Inn (revised annually), Currie, L.A., " Limits for Qualitative Detection and Quantitative Determination - Application to l Radiochemistry," Anal. Cham. 40, 586-93 (1968), and Hartwell, L

J.K., " Detection Limits for Radioanalytical Counting Techniques,

" Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975). 3/$1 i l l !

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Section 2.2 Dona J

M ' i

\ This section is provided to implement the requirements of I E

Section II.A, III.A and IV.A of Appendix I, 10 CFR Part 50. The remedial action implements the guides set forth in Section II.A ,

of Appendix I and provides the required operating flexibility I and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." Also, for fresh water sites with drinking water supplies that can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in-the finished drinking water that are in excess of the requirements of 40 CFR Part 141. The dose calculation methodology and parameters in the ODCM implement the requirements in Section III.A of Appendix I which specify that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are-consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I, " Revision 1, October 1977 and Regulatory Guide 1.113, " Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April 1977. 3/91

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g Baction 2.3 Linuid Radwasta Trea&mant Sv_atam

\

The OPERABILITY of the Liquid Radwaste Treatment Systems ensures

[

1 that this system will be available for use whenever liquid l effluents require treatment prior to release to the environment. '

The requirement that the appropriate portions of this system be used when specified provides assurance that the releases of ,

radioactive materials in liquid effluents will be kept *as low as is reasonably achieveable." This section implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CPR Part 50 and design objective given in 4 Section II.D of Appendix I to 10 CFR Part 50. The specified l limits governing the use of appropriate portions of the Liquid Radwaste Treatment System were specified as a suitable fraction )

of the dose design objective set forth in Section II.A of l Appendix I, 10 CFR Part 50, for liquid effluents.

i Section 2.4 Madiometive Lianid Effinant Manitoring l Instrumentation '

The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents. The Alarm / Trip Setpoints for these instruments shall be calculated and adjusted in accordance tiith the methodology and parameters in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50. 3/9I

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Section 3.0 ammeour Effluents M

Beation 3.1 Dome Rate r

This section is provided to ensure that the dose at any time at and beyond the SITE BOUNDARY from gaseous effluents from all units on the site will be within the annual dose limits of 10 CFR Part 20 to UNRESTRICTED AREAS. The annual dose limits are the doses associated with the concentrations of 10 CPR Part 20, Appendix B, Table II, Column 1. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC in an UNRESTRICTED AREA, either within or outside the SITE BOUNDARY, to annual average concentrations exceeding the limits specified in Appendix B, Table II of 10 CFR Part 20 (10 CFR 20.106 (b) ) . For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy of that MEMBER OF THE PUBLIC will usually be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to a MEMBER OF THE PUBLIC at or beyond the SITE BOUNDARY to less than or equal to 500 mrems/ year to the whole body or to less than or equal to 3000 mrems/ year to the skin.

These release rate limits also restrict, at all times the corresponding thyroid dose rate above background to a child via the inhalation pathway to less than or equal to 1500 mrems/ year.

The required detection capabilities for radioactive materials in gaseous waste samples are tabulated in terms of the lower limits of detection (LLDs). Detailed discussion of the LLD, and other detection limits can be found in HASL Procedures Manual, HASL-300 (revised annually), Currie, L.A., " Limits for Qualitative Detection and Quantitative Determination -

Application to Radiochemistry," Anal. Chem 40, 586-93 (1968),

and Hartwell, J.K., " Detection Limits for Radioanalytical j Counting Techniques," Atlantic Richfield Hanford Company Report '

ARM-9A-215 (June 1975). 3/91 l

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H 2

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(Page 92 of 184)

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Baction 3.2.1 Dama - Noble Gamma This section is provided to implement the requirements of y Section II.B, III.A and IV.A of Appendix I, 10 CFR Part 50. The remedial action implements the guides set forth in Section II.B of Appendix I and provides the required operating flexibility and at the same time implement the guides set forth in Section l IV.A of Appendix I to assure that the releases of radioactive l material in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." The surveillance requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through l appropriate pathways is unlikely to be substantially underestimated. The dose calculation methodology and parameters established in the ODCM for calculating the doses due to the actual release rates of radioactive materials in gaseous effluento are consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CPR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors,"

Revision 1, July 1977. The ODCM equations provided for determining the air doses at and beyond the SITE BOUNDARY are based upon either the historical average or real time atmospheric conditions. 3/$2 i

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N.

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Smetien 3.2.2 Dama - TaA4mm.131 ==A 133. Tritium ==d Bad 4nmative M Material in Darkieulata Fae= .

\

J

This section is provided to implement the requirements of l Sections II.C, III.A and IV.A of Appendix I, 10 CFR Part 50.

The remedial actions are the guides set forth in Section II.C of l Appendix I, and provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." The ODCM calculational methods specified in the surveillance requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The ODCM calculational methodology and parameters for calculating i the doses due to the actual release rates of the subject '

materials are consistent with the methodology provided in Regulatory Guide 1.109, " Calculational of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CPR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-cooled Reactors,"

Revision 1, July 1977. These equations also provide for determining the actual doses based upon either the historical average or real time conditions. The release rate limits for Iodine-131 and 133, tritium, and radionuclides in particulate form with half lives greater that 8 days are dependent upon the l existing radionuclide pathways to man, in the areas at and I beyond the SITE BOUNDARY. The pathways that were examined in the development of these calculations were: (1) individual inhalation of airborne radionuclides, (2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, (3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, (4) deposition on the ground with subsequent exposure of man. 3/DI

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Section 3.3 Gameous Radwasta..Treatalent Systema M

The OPERABILITY of the WACTE GAS HOLDUP SYSTEM and the y VENTILATION EXHAUST TREATMENT SYSTEM ensures that the systems will be available for use whenever gaseous effluents require treatment prior to release to the environment. The requirement l that the appropriate portions of this system be used when !

specified provides reasonable assurance that the releases of radioactive materiala in gaseous effluents will be kept "as low as is reasonably achievable." This section implements the requirements of 10 CFR 50.36a, General, Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objectives given in Section II.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in Section II.B and II.C of Appendix I, 10 !

CFR Part 50, for gaseous effluents.

Section 3.4 D=dioactive cameous Effluent Manitorinn _

Instrumentation The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive i materials in gaseous effluents during actual or potential {

releases of gaseous effluents. The Alarm / Trip Setpoints for l these instruments shall be adjusted to values calculated in accordance with the methodology and parameters in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50.

The sensitivity of any noble gas activity monitor used to show compliance with the gaseous effluent release requirements of Section 3.2 shall be such that concentrations as low as 1 x 10-6 Ci/cc are measurable. 3/92 l

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Baetion 4.0 Total nama

.M ,

i This section is provided to meet the dose limitations of 40 CFR I

((\ Part 190 that have been incorporated into 10 CFR Part 20 by 46 FR 18525. The section requires the preparation and submittal of a special report whenever the calculated doses due to releases of radioactivity and the radiation from uranium fuel cycle sources exceed 25 mrems to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 l

l mrems. For sites containing up to four reactors, it is highly l unlikely that the resultant dose to a MEMBER OF THE PUBLIC will i exceed the dose limits of 40 CFR Part 190 if the individual reacters remain within twice the dose design objectives of l Appendix I, and if direct radiation doses from the reactor Units and from outside storage tanks are kept small. The Special Report will describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits.

For the purposes of the I

! Special Report, it may be assumed that the dose commitment to l l the MEMBER OF THE PUBLIC from other uranium fuel cycle sources )

is negligible, with the exception that dose contributions from

! other nuclear fuel cycle facilities at the same site or within a radius of 8 km must be considered. If the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFR

Part 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 ;

CFR Part 190 have not already been corrected), in accordance with the provisions of 40 CFR 190.11 and 10 CFR'20.405c, is considered to be a timely request and fulfills the requirements l of 40 CFR Part 190 until NRC staff action is complcted. The l variance only relates to the limits of 40 CFR Part 190, and does not apply in any way to the other requirements for dose limitation of 10 CFR Part 20. An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle. 3/91 i

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4 an s . o ==di oinnin=1 =nvirn ,e . i = = = 4 e n ,4 prac==

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\ amaann 5.1 vanthaef==_ proa_ r===

The Radiological Environmental Monitoring Program provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposures of MEMBERS OF THE PUBLIC resulting from the station operation.

This monitoring program implementsSection IV.B.2 of Appendix I to 10 CFR Part 50 and thereby supplements the Radiological Effluent Monitoring Program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent maacurements and the modeling of the environmental exposure pathways. Guidance for this monitoring program is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring, Revision 1, November 1979.

The required detection capabilities for environmental sample analyses are tabulated in terms of the lower limits of detection (LLDs). The LLDs are considered optimum for routine environmental measurements in industrial laboratories. It should be recognized that the LLD is defined as an a prinri (before the fact) limit representing the capability of a measurement system and not as an a pontarlori (after the fact) limit for a particular measurement.

Detailed discussion of the LLD, and other detection limits, can be found in HASL Procedures Manual, MARL-300 (revised annually),

Currie, L.A., " Limits for Qualitative Detection and Quantitative Determination-Application to Radiochemistry," Anal- cham. 40, 586-93 (1968), and Hartwell, J.K., " Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARM-SA-215 (June 1975). 3/92

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Baction 5.2 T=ad Uma Canmus N '

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This section is provided to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the Radiological Environmental Monitoring l

Program given in the ODCM are made if required by the results of i this census. Information that will provide the best results,

)

such as door-to-door survey, aerial survey, or consulting with local agricultural authorities, ahall be used. This censua l satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50. Restricting the census to gardens of greater than )

50 m2 provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/ year) of leafy vegetables assume in Regulatory Guide 1.109 for consumption by a child.

l To determine this minimum garden size, the following assumptions were made: (1) 20% of the garden was used for growing broad l leaf vegetation (i.e., similar to lettuce and cabbage), and (2) l a vegetation yield of 2 kg/m2, Santion 5.3 Interinharatory camnarison Proaram l

The requirement for participation in an approved Interlaboratory Comparison Program is provided to ensure that independent checks ;

on the precision and accuracy of the measurements of radioactive i material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are valid for the purposes of Section IV.B.2 of Appendix I to 10 CFR Part 50. 3/92 I

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7.0 Reports 7.1 1 ann.1 n Ainimaiemi unvi emi onaratian_ n==_crt 3 -

l The Annual Radiological Environmental Operating Report shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studics, with operational controls and with previous environmental surveillance reports, and an assessment of the observed impacts of the plant operation on the environment. The reports shall also include the results of the Land Use Census described in Section 5.2.

The Annual Radiological Environmental Operating Report shall include the results of analysis of all radiological l environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in Table 5-1 as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiologica') Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report, the !

report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.

The reports shall also include the following: a summary description of the Radiological Environmental Monitoring Program; legible maps covering all sampling locations keyed to a table giving distances and directions from the centerline of the I reactor; the results of licensee participation in the Interlaboratory Comparison Program and the corrective actions being taken if the specified program is not being performed as I required by Section 5.3; reasons for not conducting the Radiological Environmental Program as required by Section 5.1

, with plans for preventing a recurrence and discussion of all deviations from the sampling schedule of Table 5-1; discussion .

of environmental sample measurements that exceed the reporting levels of Table 5-4 but are not the result of plant effluents, and discussions of all analyses in which the LLD required by l Table 5-3 was not achievable.

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7.2 1==um1 nadioactive Effluent Releana Report M

) The Annual Radioactive Effluent Release Report shall include a y summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the Unit as outlined in Regulatory Guide 1.21, " Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof. For solid wastes, the format for Table 3 in Appendix B shall be supplemented with three additional categories: class of solid waste (as defined by 10 CFR Part 60), type of container (e.g., LSA, Type A, Type B, Large Quantity), and SOLIDIFICATION agent or absorbent (e.g., cement, urea formaldehyde). 9/$3 The Annual Radioactive Effluent Release Report to be submitted before May 1 of each year shall also include an annual summary of hourly meteorological data collected over the previous year.

This annual summary may be either in the form of an hour-by-hour listing on magnetic tape of wind speed, wind direction, and atmospheric stability, and precipitation (if measured) , or in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability.* This same report shall include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the Unit or Station during the previous calendar year. This same report shall also include an assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY during the report period. All assumptions used in making these assessments, i.e., specific activity, exposure time and location, shall be included in these reports. Historical average meteorological conditions or the meteorological conditions concurrent with the time of release of radioacti're materials in gaseous effluents, as determined by sampling frequency and measurement, shall be used for determining the gaseous pathway doses. The assessment of radiation doses shall be performed in accordance with the methodology and parameters in the ODCM. 12/95

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The Annual Radioactive Effluent Release Report to be submittod before May 1 of each year shall also include an assessment of j radiation doses to the likely most exposed MEMBER OF THE PUBLIC y from reactor releases and other nearby uranium fuel cycle sources, including doses from primary effluent pathways and direct radiation, for the previous calendar year to show conformance with 40 CFR Part 190 5 " Environmental Radiation Protection Standards for Nuclear Power Operation." Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev. 1, October 1977.

The Annual Radioactive Effluent Release Report shall include:

9/93

a. A list and description of unplanned releases from the site to UNRESTRICTED AREAS of radioactive materials in gaseous and . liquid effluents made during the reporting period.

In lieu of submission with the Annual Radioactive Effluent Release Report, the licensee has the option of retaining this summary of required meteorological data on site in a file that shall be provided to the NRC upon request. #/93

b. Any changes made during the reporting period to the ODCM, pursuant to Technical Specification 6.14.

c. Major changes to the Radwaste Treatment Systems for the period in which the evaluation was reviewed and accepted by the PSRC. The discussion of each change shall contain:

1) A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR 50.59;

2) Sufficient detailed information to totally support the reason for the change without benefit of additional and supplemental information;

3) A detailed description of the equipment, components, and processes involved and the interfaces with other plant systems.

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4) An evaluation of the change which shows the predicted releases of radioactive materials in

)y liquid and gaseous affluents and/or quantity of solid waste that differ from those previously predicted in the license application and amendments thereto;

5) An evaluation of the change, which shows the expected maximum exposures to a MFh1BER OF THE PUBLIC in the UNRESTRICTED AREA and to the general population that differ from those previously estimated in the license application and amendments thereto;

6) A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents and in solid waste, to the actual releases for the period prior to when the changes are to be made;

7) An estimate of the exposure to plant operating personnel as a result of the change; and

8) Documentation of the fact that the change was reviewed and found acceptable by the PSRC.

d. A listing of new locations for dose calculations identified by the Land Use Census,

e. A description of the events leading to liquid holdup tanks or gas storage tanks exceeding the limits of Technical Specification 3.11.1.4 or 3.11.2.6 respectively.

f. An explanation as to why the inoperability of a liquid or gaseous effluent monitoring instrumentation was not corrected within the time specified.

g. A description of the events leading to a missed sample required by Table 2-1 or 3-1.

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APPEEDIX A Dose Conversion Factor Tables 1

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BIGACCUMULATION FACTQRS TO BE USED IN .

E THE ABSENCE OF SITE-SPECIFIED DATA ar- (pci/kg per pCi/ liter)

ELEMENT FRESHWATER FISH H 9.0E-01 C 4.6E 03 Na 1.0E 02 P 1.0E 05 Cr 2.0E 02 Mn 4.0E 02 Fe 1.0E 02 Co 5.0E 01 Ni 1.0E 02 Cu 5.0E 01 Zn 2.0E 03 Br 4.2E 02 Rb 2.0E 03 j Sr 3.0E 01 !

Y 2.5E 01 Zr 3.3E 00 Nb 3.0E 04 Mo 1.0E 01 Tc 1.5E 01 Ru 1.0E 01 Rh 1.0E 01 Te 4.0E 02 I 1.5E 01 Cs 2.0E 03 Ba 4.0E 00 La 2.5E 01 Ce 1.0E 00 Pr 2.5E 01 Nd 2.5E 01 ;

. W 1.2E 03 Np 1.OE 01

- Ag 2.3E 00

- Sb 1.0E 00

Taken from Regulatory Guide 1.109 (Rev.1)

- Taken from Regulatory Guide 1.109 (Rev.0)

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\ DOSE FACTORS FOR NOBLE. GASES AND DAUGHTERS

3 Radionuclida Total undv BHn Dona Factor Gamma Air Bata Air y Dome Factor Lg Dose Factor Dona Factor 1 Eg (mram/vr nar Mg 31 (mram/vr ner pci/m a l (mrad /vr ner (mrad /vr car pei/m*1 pCiAna l pCi/m*1 )

l Kr-83M 7.56E-02** --- 1.93E+01 2.88E+02 l Kr-85M 1.17E+03 1.46E+03 1.23E+03 1.97E+03 Kr-05 1.61E+01 1.34E+03 1.72E+01 1.95E+03 Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03 Kr-89 1.66E+04 1.01E+04 1.73E+04 1.06E+04 Kr-90 1.56E+04 7.29E+03 1.63E+04 7.83E+03 Ke-131M 9.15E+01 4.76E+02 1.56E+02 1.11E+03 Xe-133 2.94E+02 3.06E+02 3.53E+02 1.05E+03 j Xe-133M 2.51E+02 9.94E+02' 3.27E+02 1.48E+03 Xe-135M 3.12E+03 7.11E+02 3.36E+03 7.39E+02 Xe-135 1.81E+03 1.86E+03 1.92E+03 2.46E+03 l

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 l l

Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03 j l

Based on Regulatory Guide 1.109 (Rev.1)

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- 7.56E-02 = 7.56 x 10

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TABLE A.2-1*

N INHALATION DOSE FACTORS FOR ADULTS

\ (MREM PER PCI INHALED)

JD s' NUCLIDE BCNE LIVER T BODY THYROID KIDNEY LUNG GI-LL1 l

H 3 NO DATA 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.5BE-07 1.585-07 C 14 2.27E-06 4.26E-07 4.263-07 4.26H-07 4.26E-07 4.26E-07 4.26E-07 j NA 24 1.28E-06 1.28E-06 1.28E-06 1.28E-06 ,.28E-06 1 1.28E-06 1.28E-06 j I

P 32 1.65E-04 9.645-06 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 1.808-06 4.15E-07 i MN 54 NO DATA 4.95E-06 7.87E-07 NO DATA 1.23E-06 1.75E-04 9.67E-06 l

MN 56 NO DATA 1.55E-10 2.293-11 NO DATA 1.63E-10 1.18E-06 2.53E-06 FE 55 3.07E-06 2.12E-06 4.93E-07 NO DATA NO DATA 9.01E-06 7.54E-07 l FE 59 1.47E-06 3.47E-06 1.32E-06 NO DATA NO DATA 1.27E-04 2.35E-05 CO 5d NO DATA 1.98E-07 2.59E-07 NO DATA NO DATA 1.1GE-04 1.33E-05 00 60 NO DATA 1.44B-06 1.85E-06 NO DATA NO DATA 7.465-04 3.56E-05 NI 63 5.40E-05 3.93E-06 1.81E-06 NO DATA NO DATA 2.23E-05 1.67E-06 i

NI 65 1.92E-10 2.62E-11 1.14E-11 NO DATA NO DATA 7.00D-07 1.54E-06 l CU 64 NO DATA 1.83E-10 7.69E-11 NO DATA 5.78E-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 2.902-08 BR 84 NO DATA NO DATA 3.91E-08 NO DATA NO DATA NO DATA 2.05E-13 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 j 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-06 2.12E-08 NO DATA NO DATA NO DATA 1.16E-21 l SR 89 3.80E-05 NO DATA 1.09E-06 NO DATA NO DATA 1.75E-04 4.37E-05 !

SR 90 1.24E-02 NO DATA 7.625-04 NO DATA NO DATA 1.20E-03 9.02E-05 SR 91 7.74E-09 NO DATA 3.135-10 NO DATA UO 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 91N 3.26E-11 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 Y 92 1.29E-09 NO DATA 3.77E-11 NO DATA NO DATA 1.96E-06 9.19E-06 Y 93 1.18E-08 NO DATA 3.?6E-10 NO DATA NO DATA 6.06E-06 5.27E-05 ZR 95 1.34E-05 4.30E-06 2.91E-06 NO DATA 6.77E-06 2.21E-04 1.88E-05 ZR 97 1.21E-08 2.45E-09 1.13E-09 NO DATA 3.71E-09 9.84E-06 6.54E-05 NB 95 1.76E-06 9.77E-07 5.26E-07 NO DATA 9.67E-07 6.31E-05 1.30E-05 NO 99 MO DATA 1.51E-08 2.87E-09 NO DATA 3.64E-08 1.14E-05 3.10E-05 TC 99M 1.29E-13 3.64E-13 4.63E-12 NO DATA 5.52E-12 9.55E-08 5.20E-07

Taken from Regulator Guide 1.109 (Rev. 1)

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TABLE A.2-1*(cont'd)

INHALATION DOSE FACTORS FOR ADULTS

\ (MREM PER PCI INHAI.ED)

.D U" NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI )

i 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 6.313-05 1.38E-05 1 RU 105 9.88E 11 NO DATA 3.89E-11 NO DATA 1.27E-10 1.37E-06 6.02E-06 j RU 106 8.64E-06 NO DATP, 1.09E-06 NO DATA 1.67E-05 3.17E-03 1.14E-04 AO 110M 1.355-06 1.2 G-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 4.11E-07 5.72E-06 1.20E-04 1.87E-05 TE 127 1.75E-10 8.03E-11 3.87E-11 1.32E-10 6.37E-10 B.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 6.228-12 2.99E-12 1.55E-12 4.878-12 2.34E-11 2.42E 07 1.962-09 TE 131M 8.74E-09 5.45E-09 3.63E-09 6.88E-09 3.06E-08 1.82E-05 6.95E-05 TE 131 1.398-12 7.44E-13 4.49E-13 1.17E-12 5.46E-12 1.748-07 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 1 132 1.45E-07 4.07E-07 1.45E-07 1.43E-05 6.48E-07 NO DATA 5.08E-08 I 133 1.088-06 1.85E-06 5.65E-07 2.69E-04 3.23E-06 NO DATA 1.11E-06 I 134 8.055-08 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 1.3BE-05 NO DATA 1.07E-05 1.50E-06 1.46E-06 l CS 137 5.98E-05 7.76E-05 5.358-05 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 2.428-07 1.45E-17 BA 142 3.29E-12 3.38E-15 2.073-13 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 IA 142 8.54E-11 3.88E-11 9.65E-12 NO DATA NO DATA 7.91E-07 2.64E-07 CE 141 2.495-06 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 3.765-12 1.56E-12 1.91E-13 NO DATA 8.815-13 1.27E-07 2.69E-18 ND 147 6.59E-07 7.62E-C7 4.56E-08 NO DATA 4.45B-07 2.76E-05 2.16E-05 N 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

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TABLR A.2-2*

N INNALATION DOSI FACTORS FOR TEENAGER Y '

(98 TEN PER PCI INHALED)

.0 (T NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNO OI-LLI H 3 NO DATA 1.59E-07 1.59E-07 1.59E-07 1.598-07 1.59E-07 1.59E-07 C 14 3.25E-06 6.09E-07 6.09E-07 6.095-07 6.095-07 6.09E-07 6.095-07 NA 24 1.723 06 1.72E-06 1.72E-06 1.725-06 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 1.698-08 9.37E-09 3.84E-09 2.62E-06 3.758-07 NN 54 NO DATA 6.39E 06 1.05E-06 NO DATA 1.59E-06 2.48E-04 _ 8.35E-06 NN 56 NO DATA 2.12E-10 3.15E-11 NO DATA 2.24E-10 1.90E-06 7.18E-C6 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 WO 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 2.478-06 NO DATA NO DATA 3.84E-05 1.77E-06 NI 65 2.73E-10 3.66E-11 1.59E-11 NO DATA NO DATA 1.17E-06 4.595-06 CU 64 NO DATA 2.545-10 1.06E-10 NO DATA 8.01E-10 1.39E-06 7.6BE-06 EN 65 4.82E-06 1.67E-05 7.80E-06 NO DATA 1.085-05 1.55E-04 5.835-06 ZN 69 6.04E-12 1.15E-11 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 BR 84 NO DATA NO DATA 5.415-08 NO DATA NO DATA NO DATA LT E-24 BR 85 NO DATA NO DATA 2.295-09 NO DATA NO DATA NO DATA LT E-24 RB 86 NO DATA 2.38E-05 1.05E-05 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 5.435-05 NO DATA 1.56E-06 NO DATA NO DATA 3.02E-04 4.64E-05 SR 90 1.35E-02 NO DATA 8.35E-04 NO DATA NO DATA 2.06E-03 9.563-05 SR 91 1.10E-08 NO DATA 4.39E-10 NO DATA NO DATA 7.598-06 3.24E-05 SR 92 1.19E-09 NO DATA 5.088-11 NO DATA NO DATA 3.4*JE-06 1.495-05 Y 90 3.73E-07 NO DATA 1.00E-05 NO DATA NO DATA 3.66E-05 6.99E-05 Y 91N 4.63E-11 NO DATA 1.77E-12 NO DATA NO DATA 4.00E-07 3.775 09 Y 91 8.26E-05 NO DATA 2.21E-06 NO DATA NO DATA 3.67E-04 5.11E-05 Y 92 1.84E-09 NO DATA 5.36E-11 NO DATA NO DATA 3.35E-06 2.063-05 Y 93 1.69E-08 NO DATA 4.65E-10 NO DATA NO DATA 1.04E-05 7.248-05 3R 95 1.82E-05 5.73E-06 3.94E-06 NO DATA 8.42E-06 3.36E-04 1.86E-05 ER 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 1.255-06 9.39E-05 1.21E-05 l MO 99 NO DATA 2.11E-08 4.03E-09 NO DATA 5.14E-08 1.92E-05 3.36E-05 TC 99N 1.73E-13 4.83E-13 6.24E-12 NO DATA 7.20E-12 1.44E-07 7.665-07 ]

Tr*s.m from Regulator Guide 1.109 (Ber.1)

'I 3 Rsvision: 0 0FFSITE DOSE CALCULATION MANUAL AP 07B-003 F) m Reference Use Page 112 of 188 O

ATTACHMENT A O

g (Page 108 of 184) g OFFSITE DOSE CALCULATION MANUAL TABLE A.2-2* (most*d)

INHALATION DOSE FAcrORS FOR TRENAGER

\ (MEEN PER PCI IENALED)

.0 F NUCLIDE BONE LIVER T BODY THYROID EIDNEY LUNG CI-LLI 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 9.795-05 1.36E-05 RU 105 1.40E-10 NO DATA 5.42E-11 NO DATA 1.76E-10 2.27E-06 1.135-05 RU 106 1.23E-05 NO DATA 1.553-06 NO DATA 2.3BE-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 9.38E-06 TE 127M 2.25E-06 1.02E-06 2.73E-07 5.40E-07 0.175-06 2.07E-04 1.995-05 TI 127 2.51E-10 1.14E-10 5.52E-11 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 5.063 TE 129 6.87E-12 4.22E-12 2.203-12 G.48E-12 3.32E-11 4.12E 07 2.02E-07 TE 131M 1.23E-08 7.51E-09 5.03E-09 9.06E-09 5.49E-08 2.975-05 7.76E-05 TE 131 1.97E-12 1.04E-12 6.30E-13 1.55E-12 7.72E-12 2.925-07 1.89E-09 TR 132 4.50E-00 3.633-08 2.74E-OS 3.07E-00 2.44E-07 5.61E-05 5.79E-05.

I 130 7.00E-07 2.24E-06 8.96E-07 1.865-04 3.44E 06 NO DATA 1.14E-06 I 131 4.43E-06 6.14E-06 3.30E-06 1.03E-03 1.05E-05 NO DATA 5.11E-07 I 132 1.99E-07 5.47E-07 1.97E-07 1.89E-05 8.65E-07 NO DATA 1.595-07 I 133 1.525-06 2.56E-06 7,78E-07 3.65E-04 4.495-06 NO DATA 1.293-06 !

I 134 1.11E-07 2.905-07 1.05E-07 4.94E-06 4.58E-07 NO DATA 2.555-09 l l

I 135 4.625-07 1.185-06 4.36E-07 7.76E-05 1.06E-06 NO DhTA 8.69E-07 j C8 134 6.285-05 1.415-04 6.065-05 NO DATA 4.69E-05 1.03E-05 1.22E-06 !

CS 136 6.44E-06 2.425-05 1.71E-05 NO DATA 1.38E-05 2.22E-06 1.365-06 1 CS 137 8.30E-05 1.06E-04 3.893-05 NO DATA 3. DOE-05 1.51E-05 1.063-06 CS 138 5.82E-08 1.07E-07 5.58E-08 NO DATA 8.2OE-08 9.84E-09 3.38E-11 EA 139 1.67E-10 1.185-13 4.873-12 NO DATA 1.11E-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 l

BA 141 1.78E-11 1.32E-14 5.93E-13 NO DATA 1.23E-14 4.11E-07 9.333-14 EA 142 4.62E-12 4.63E-15 2.84E-13 NO DATA 3.92E-15 2.39E-07 5.99E-20 IA 140 5.995-00 2.95E-08 7.825-09 NO DATA NO DATA 2.68E-05 6.095-05 LA 142 1.20E-10 5.31E-11 1.328-11 NO DATA NO DATA 1.27E-06 1.50E-06 CE 141 3.55E-06 2.37E-06 2.71E-07 NO DATA 1.11E-06 7.67E-05 1.58E-05 CE 143 3.325-00 2.42E-08 2.70E-09 NO DATA 1.00E-08 1.63E-05 3.19E-05 CE 144 6.11E-04 2.53E-04 3.28E-05 NO DATA 1.51E-04 1.67E-03 1.08E-04 PR 143 1.675-06 6.64E-07 8.20E-08 NO DATA 3.06E-07 6.04E-05 2.67E-05 PR 144 5.37E-12 2.205-12 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 2.2BE-05 W 187 1.50E-09 1.22E-09 4.29E-10 NO DATA NO DATA 5.92E-06 2.213-05 1

NP 239 4.23E-08 3.99E-09 2.21E-09 NO DATA 1.252-04 8.11E-06 1.65E-05

2 p Rsvision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 '

G1 m Reference Use Page 113 of 188 O

ATTACHMENT A O

g (Page 109 of 184) g OFFSITE DOSE CALCULATION MANUAL

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TABLE A.2-3*

N' '

INHALATION DOSE FACTORS FOR CHILD

\ (MREM PER PCI INHALED)

.D (T NUCLIDE BONE LIVER T BODY THYROID KIDNEY 1A250 GI-LLI H 3 NO DATA 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 C 14 9.70E-OK 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 4.35u-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 I 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 j FE 59 5.598-06 9.04E-06 4.51E-06 NO DATA NO DATA 3.43E-04 1.91E-05 !

CO $8 NO DATA 4.79E-07 8.55E-07 NO DATA NO DATA 2.9DE-04 9.2DE-C6 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-11 NO DATA NO DATA 2.21E-06 2.27E-05

.CU 64 NO DATA 5.39E-10 2.90E-10 NO DATA 1.63E-09 2.59E-06 9.92E-06 ZN 65 1.15E-05 3.06E-05 1.90E-05 NO DATA 1.93E-05 2.69E-04 4.41E-06 ZN 69 1.81E-11 2.613-11 2.41E-12 NO DATA 1.585-11 3.84E-07 2.75E-06 BR 83 NO DATA NO DATA 1.28E-07 NO DATA NO DATA NO DATA LT E-24 BR 84 NO DATA NO DATA 1.40E-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 DATA NO DATA 5.11B-10 SR 89 1.62E-04 NO DATA 4.66E-06 NO DATA NO DATA 5.83E-04 4.528-05 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 SR 92 3.548-09 NO DATA 1.42E-10 NO DATA NO DATA 6.49E.36 6.55E-05 l Y 90 1.11E-06 NO DATA 2.995-08 NO DATA NO DATA 7.07E-05 7.24E-05 i Y 91M 1.37E-10 NO DATA 4.98E-12 NO DATA NO DATA 7.60E-07 4.64E-07 Y 91 2.47E-04 NO DATA 6.59E-06 NO DATA NO DATA 7.10E-04 4.97E-05 Y 92 5.50E-09 NO DATA 1.57E-10 NO DATA NO DATA 6.46E-06 6.46E-05 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 5.075-08 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 NO 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-11 NO DATA 1.37E-11 2.57E-07 1.30E-06

Taken from Reguintor emide 1.109 (Rev 1)

~

'H 3

9 Rsvisions 0 OFFSITE DOSE CALCUIATION MANUAL AP 07B-003 R Reference Use Page 114 of 188 h

ATTACHMENT A y@ (Page 110 of 184) l\ OFFSITE DOSE CALCULATION MANUAL

?

y TABLE 1.2-3* (coatPd)

INHALATION DOSE FACTORS FOR CHILD '

\ (MREM PER PCI INHALED)-

A.

l0' NUCLIDE BCNE LIVER T BODY THYROID EIDNEY LUNG GI-LLI TC 101 2.19E-14 2.30E-14 2.91E-13 NO DATA 3.92E-13 1.58E-07 4.41E-09 RU 103 7.55E 07 NO DATA 2.90E-07 NO DATA 1.90E-06 1.79E-04 1.21E-05 RU 105 4.138-10 NO DATA 1.50E-10 NO DATA 3.63E-10 4.30E-06 2.69E-05 l

l RU 106 3.68E-05 NO DATA 4.57E-06 NO DATA 4.975-05 3,87E-03 1.16E-04 l AG 110M 4.56E-06 3.085-06 2.47E-06 NO DATA 5. 74E- Oti 1.485-03 2.71E-05 TB 125M 1.82E-06 6.29E-07 2.47E-07 5.20E-07 NO DATA 1.29E-04 9.13E-06 l

TE 127M 6.72E-06 2.31E-06 8.16E-07 1.645 06 1.72E-05 4.00E-04 1.935-05 TE 127 7.495-10 2.57E-10 1.65E-10 5.30E-10 1.91E-09 2.715-06 1.52E-05 TE 129M 5.193-06 1.853-06 8.223-07 1.71E-06 1.36E-05 4.76E-04 '4.915-05 TE 129 2.648-11 9.45E-12 6.44E-12 1.93E-11 6.49E-11 7.93E-07 G.09E-06 TE 131M 3.63E-08 1.60E-08 1.37E-08 2.645-08 1.08E-07 5.56E-05 8.32E-05 TE 131 5.87E-12 2.285-12 1.78E-12 4.59E-12 1.59E-11 5.55E-07 3.60E-07 TE 132 1.30E-07 7.36E-08 7.12R-08 8.583-08 4.79E-07 1.02E-04 3.72B-05 I 130 2.21E-06 4.43E-06 2.28E-06 4.99E-04 6.61E-06 NO DATA 1.38E-06 l I 131 1.30E-05 1.30E-05 7.375-06 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 7 133 4.485-06 5.493-06 2.085-06 1.04E-03 9.135-06 NO DATA 1.48E-06 l 1 134 3.17E-07 5.84E-07 2.69E-07 1.37E-05 8.92E-07 NO DATA 2.58E-07 l

I 135 1.33E-06 2.36E-06 1.125-06 2.14E-04 3.625-06 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 1 CS 136 1.76E-05 4.62E-05 3.14E-05 NO DATA 2.588-05 3.93E-06 1.13E-06 l

l_ C8 137 2.45E-04 2.23E-04 3.47E-05 NO DATA 7.633-05 2.81E-05 9.788-07

! CS 138 1.71E-07 2.278-07 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-06 1.56E-05 l

BA 140 2.00E-05 1.75E-08 1.17E-06 NO DATA 5.71E-09 4.71E-04 2.75E-05

,- BA 141 5.29E-11 2.95E-14 1.72E-12 NO DATA 2.56E-14 7.89E-07 7.44E-08 l BA 142 1.35E-11 9.735-15 7.545-13 NO DATA 7.87E-15 4.44E-07 7.41E-10 l

LA 140 1.74E-07 6.08E-08 2.04E-08 NO DATA NO DATA 4.94E-05 6.10E-05 LA 142 3.50E-10 1.11E-10 3.495-11 NO DATA NO DATA 2.353-06 2.05E-05 CE 141 1.06E-05 5.28E-06 7.83E-07 NO DATA 2.313-06 1.475-04 1.53E-05 CE 143 9.895-08 5.37E-08 7.77E-09 NO DATA 2.265-08 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 i PR 143 4.99E-06 1.50E-06 2.47E-07 NO DATA 8.11E-07 1.17E-04 2.63E-05 l-PR 144 1.61E-11 4.99E-12 8.10E-13 NO DATA 2.64E-12 4.23E-07 5.32E-08 i ND 147 2.92E-06 2.36E-06 1.84E-07 NO DATA 1.30E-06 8.87E-05 2.22E-05 N 187 4.41E-09 2.61E-09 1.17E-09 NO DATA NO DATA 1.11E-05 2.46E-05 MP 239 1.26E-07 9.04E-09 6.35E-09 NO DATA 2.63E-08 1.57E-05 1.73E-05

T D Revision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 0

m Reference Use Page 115 of 188 O

ATTACHMENT A O

y (Page 111 of 184)

\

~

TABLE A.2-4*

N IISIALATION DOSE FACTORS FOR INFANT

\ (MREM PER PCI INHALED)

.o F NUCLIDE BO8tB LIVER T BODY TEYROID EIDNEY LUNG GI-LLI H 3 NO DATA 4.62E-07 4.625-07 4.625-07 4.62E-07 4.62E-07 4.62E-07 C 14 1.898-05 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 f NA 24 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 P 32 1.45E-03 8.03E-05 5.53E-05 No DATA NO DATA NO DATA 1.15E-05 CR 51 NO DATA NO DATA 6.39E-08 4.11E-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 NN 56 NO DATA 1.10E-09 1.58E-10 NO DATA 7.86E-10 8.95E-06 5.125-05 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 DhTA NO DATA 7.25E-04 1.77E-05 CO 58 NO DATA 0.71E-07 1.30E-06 NO DATA No DATA 5.55E-04 7.955-06 CO 60 NO DATA 5.73E-06 8.41E-06 NO DATA NO DATA 3.22E-03 2.285-05 NI G3 2.42E-04 1.46E-05 8.29E-06 NO DATA NO DATA 1.49E-04 1.73E-0G NI 65 1.71E-09 2.035-10 0.79E-11 NO DATA NO DATA 5.80E-06 3.58E-05 CU 64 NO DATA 1.34E-09 5.53E-10 WO DATA 2.84E-09 6.64E-06 1.07E-05 EN 65 1.383-05 4.47E-05 2.22E-05 110 DATA 2.325-05 4.62E-04 3.67E-05 ZN 69 3.85E-11 6.91E-11 5.13E-12 NO DATA 2.875-11 1.055-06 9.44E-06 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 1.365-04 6.30E-05 NO DATA NO DATA No DATA 2.17E-06 RB 88 HO DATA 3.98E-07 2.05E-07 NO DATA NO DATA NO DATA 2.42E-07 RB 89 NO DATA 2.29E-07 1.472-07 NO DATA NO DATA NO DATA 4.875-08 SR 89 2.845-04 NO DATA 8.15E-06 NO DATA NO DATA' 1.45E-03 4.575-05 BR 90 2.92E-02 NO DATA 1.85E-03 NO DATA NO DATA 8.033-03 9.36E-05 SR 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 9.045-05 Y 4 1.07E-07 NO DATA 2.91E-09 NO DATA NO DATA 5.46E-05 1.19E-04 ER 95 8.24E-05 1.99E-05 1.45E-05 NO DATA 2.22E-05 1.25E-03 1.55E-05 ER 97 1.07E-07 1.83E-08 8.36E-09 NO DATA 1.85E-08 7.88E-05 1.00E-04 MB 95 1.12E-05 4.595-06 2.70E-06 NO DATA 3.37E-06 3.42E-04 9.05E-06 MO 99 NO DATA 1.18E-07 2.315 08 NO DATA 1.89E-07 9.63E-05 3.485-05 TC 99M 9.983-13 2.06E-12 2.66E-11 NO DATA 2.22E-11 5.79E-07 1.45E-06

Taken from Regulator Guide 1.109 (Rev. 1)

3 p Rovision: 0 OFFSITE DOSE CALCUIATION MANUAL AP 07B-003 G)

M Reference Use Page 116 of 188 0

ATTACHMENT A U

g (Page 112 of 184) g OFFSITE DOSE CALCUIATION MANUAL

~

TABLE A.2-4* (oost'd)

INHAIATION DOSE FACTORS FOR INFANT

\ (MREN PER PCI INHALED)

.0 5' NUCLIDE SONE LIVER T BODY '11fYROID EIDNEY 1ABIG GI-LLI TC 101 4.65E-14 5.88E-14 5.80E-13 NO DATA 6.995-13 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 6.428 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 5.165 06 3.57E-06 NO DATA 7.80E-06 2.62E-03 2.365-05 TE 125M 3.40E-06 1.42E-06 4.70E-07 1.16E-06 NO DATA 3.19E-04 9.225-06 TE 127M 1.19E-05 4.93E-06 1.488-06 3.48E-06 2.68E-05 9.37E-04 1.95E-05 TE 127 1.595-09 6.815-10 3.49E-10 1.325-09 3.475-09 7.393-06 1.74E-OS TB 129M 1.01E-05 4.35E-06 1.59E-06 3.915-06 2.27E-05 1.20E-03 4.93E-05 TE 129 5.63E-11 2.48E-11 1.34E-11 4.82E-11 1.2"E 10 4.1*R-06 1.88R-05 TE 131M 7.625-08 3.93E-08 2.59E-08 6.38E-08 1.89E-07 1.425-6s 8.51E-05 TE 131 1.24E-11 5.87E-12 3.57E-12 1.135-11 2.85E-11 1.47E-06 b.f."'U O6_

e l TE 132 2.66E-07 1.69E-07 1.26E-07 1.99E-07 7.39E-07 2.43E-04 3.15E-05 '

l I 130 4.54E-06 9.91E-06 3.98E-06 1.14E-03 1.093-05 NO DATA 1.42E-06 I 131 2.71E-05 3.175-05 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-06 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 1.985-06 4.975-04 6.055-06 NO DATA 1.31E-06 CS 134 2.83E-04 5.025-04 5.325-05 NO DATA 1.365-04 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 3.253-05 NO DATA 1.233-04 5.09E-05 9.53E 07 CS 138 3.61E-07 5.58E-07 2.84E-07 NO DATA 2.93E-07 4.675-08 6.26E-07 BA 139 1.06E-09 7.03E-13 3.075-11 NO DATA 4.23E-13 4.25E-06 3.64E-05 BA 140 4.005-05 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 2.125-06 J.39E-06 BA 142 2.84E-11 2.36E-14 1.40E-12 NO DATA 1.36E-14 1.11E-06 4.95E-07 IA 140 3.61E-07 1.43E-07 3.68E-08 NO DATA NO DATA 1.20E-04 6.06E-05 IA 142 7.36E-10 2.69E-10 6.46E-11 NO DATA NO DATA 5.87E-06 4.25E-05 CE 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 2.283-03 8.65E-04 1.26E-04 NO DATA 3.84E-04 7.03E-03 1.06E-04 PR 143 1.00E-05 3.74E-06 4.99E-07 NO DATA 1.41E-06 3.09E-04 2.56E-05 PR 144 3.425-11 1.32E-11 1.72E-12 NO DATA 4.80E-12 1.153-06 3.06E-06 ND 147 5.67E-06 5.81E-06 3.57E-07 NO DATA 2.2SE-06 2.305-04 2.23E-05 N 187 9.26E-09 6.445-09 2.23E-09 NO DATA NO DATA 2.83E-05 2.54E-05 NP 239 2.655-07 2.375-08 1.34E-08 NO DATA 4.73E-04 4.25E-05 1.78E-05

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!O-

!g (Page 113 of 184) lg OFFSITE DOSE CALCULATION MANUAL g TABLE A.2-5*

. EETERMAL DOSE FACTORS FOR STANDING ON CONTANINATED GROUND

\ (mrom/hr per pCi/m')

, .D G* utznamarr TOTAL BODY REIM 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 2.205-10 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 Hi-GS 3.703-09 4.30E-09 Cu-64 1.50E-09 1.70E-09 En-65 4.00E-09 4.60E-09 En-69 0.0 0.0 Br-83 6.40E-11 9.30E-11 Br-84 1.20E-08 1.40E-08 Br-85 0.0 0.0 Rb-86 6.30E-10 7.20E-10 Rb-88 3.50E-09 4.00E-09 Rb-89 1.505-08 1.80E-08 Sr-89 5.60E-13 6.50E-13 Sr-91 7.10E-09 8.30E-09 Br-92 9.00E-09 1.00E-08 Y-90 2 . 20 E-17. 2.60E-12 Y-91M 3.80E-09 4.40E-09 i Y-91 2.40E-11 2.705-11 Y-92 1.60E-09 1.90E-09 Y-93 5.70E-10 7.80E-10 Er-95 5.00E-09 5.80E-09 Er-97 5.50E-09 6.40E-09 i Nb-95 5.10E-09 6.00E-09 l 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 l Ru-105 4.50E-09 5.10E-09 Ru-106 1.50E-09 1.80E-09 Ag-110M 1.80E-08 2.10E-08 Te-125M 3.50E-11 4.805-11 Te-127M 1.10E-12 1.30E-12 Te-127 1.00E-11 1.10E-11 i Te-129M 7.70E-10 9.00E-10 l

Te-129 7.10E-10 8.40E-10 l

Taken from Regulatory Guide 1.109 (Rev. 1) i 1

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ATTACHMENT A 0

g (Page 114 of 184)

\ OFFSITE DOSE CALCULATION MANUAL g TABLE A.2-5* (cont' d)

EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND (mrom/hr per pCi/m')

T ELEMENT 'r0TAL BODY SEIN Te-131M 8.40E-09 9.90E-09 Te-131 2.20E-09 2.60E-06 Te-132 1.70E-09 2.00E-09 I-130 1.40E-08 1.70E-08 I-131 2.80E-09 3.40E-09 I-132 1.70E-08 2.00E-08 I-133 3.70E-09 4.50E-09 I-134 1.60E-08 1.90E-08 I-135 1.20E-08 1.40E-08 Cs-134 1.20E-08 1.40E-08 Cs-136 1.50E-08 1.70E-08 Cs-137 4.20E-09 4.903-09 Cs-138 2.10E-08 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 6.205-10 Ce-143 2.20E-09 2.50E-09 Ce-144 3.20E-10 3.70E-10 Pr-143 0.0 0.0 Pr-144 2.00E-10 2.30E-10 Nd-147 1.00E-09 1.20E-09 W-187 3.10E-09 3.60E-09 Np 239 9.50E-10 1.10E-09 I

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. ATTACIOtENT A (Page 115 of 184) l g OFFSITE DOSE CALCULATION MANUAL

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TABLE A.3-1*

N INGESTION DOSE FACTORS FOR ADULTS

\ (NREN PER PCI INGESTED)

.D g' NUCLIDE BONE LIVER T BODY THY 2OID KIDNEY LUNO GI-LLI ;

H 3 NO DATA 1.053-07 1.05E-07 1.05E-07 1.05E-07 1.055-07 1.05E-07 C 14 2.84E-06 5.685-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 NA 24 1.70E-06 1.70R-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 l P 32 1.93E-04 1.20E-05 7.465-06 NO DATA NO DATA NO DATA 2.17E-05 I CR 51 NO DATA NO DATA 2.66E-09 1.595-09 5.865-10 3.53E-09 6.69E-07 MN 54 NO DATA 4.57E-06 8.72E-07 NO DATA 1.365-06 NO DATA 1.40E-05 NN 56 NO DhTA 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 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 50 NO DATA 7.452-07 1.675-06 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 MI 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-04 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 EN 65 4.84E-06 1.54E-05 6.965-06 NO DATA 1.03E-05 NO DATA 9.70E-06 ZN 69 1.03E-08 1.97E-08 1.37E-09 NO DATA' 1.20E-08 NO DATA 2.96E-09 I

BR 83 NO DATA NO DATA 4.025-08 NO DhTA NO DATA NO DATA 5.795-08 BR 84 NO DATA NO DATA 5.21E-08 NO DATA NO DATA NO DATA 4.095-13 BR 85 NO DATA NO DATA 2.14E-09 NO DATA NO DATA NO DATA LT E-24 RE 86 NO DATA 2.11E-05 9.83E-06 NO DATA NO DATA NO DATA 4.162-06 RB 8B NO DATA 6.05E-08 3.21E-08 NO DATA NO DATA NO DATA 8.36E-19 RB 89 NO DATA 4.01E-08 2.823-08 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 7.585-03 NO DATA 1.863-03 NO DATA NO DATA NO DATA 2.19E 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 i

Y 91N 9.09E-11 NO DATA 3.53r-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 WO DATA 7.40E-11 NO DATA NO DA'TA NO DATA 8.50E-05 ER 95 3.04E-08 9.75E-09 6.60E-09 NO DATA 1.53E-08 NO DATA 3.09E-05 j 1.55E-10 ER 97 1.68E-09 3.39E-10 NO DATA 5.12E-10 NO DATA 1.05E-04 NB 95 6.22E-09 3.465-09 1.86E-09 NO DATA 3.42E-09 NO DATA 2.10E-05 i NO 99 NO DATA 4.31E-06 8.20E-07 NO DATA 9.76E-06 NO DhTA 9.99E-06 l TC 99N 2.47E-10 6.98E-10 8.89E-09 NO DATA 1.06E-08 3.42E-10 4.13E-07

Taken from Regulator Gaide 1.185 (Rev. 1) i

3

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ATTACHMENT A (Page 116 of 184) lg OFFSITE DOSE CALCUIATION MANUAL

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TABLE A 3 1* (oost'd) lN INGESTION DOSE FACFORS FOR ADULTS '

\ (NREM PER PCI INGESTED)

.D (f NUCLIDE DONE LIVER T BODY THYROID KIDDIEY LUNG GI-LLI TC 101 2.54E-10 3.665-10 3.59E-09 NO DATA 6.595-09 1.87E-10 1.10E-21 RU 103 1.85E-07 NO DATA 7.97E-08 NO DATA 7.06E-07 NO DATA 2.163-05 RU _

105 1.54E-08 NO DATA 6.08E-09 NO DATA 1.99E-07 NO DATA 9.42E-06 i RU 106 2.75E-06 NO DATA 3.485-07 NO DATA 5.31E-06 NO DATA 1.78E-04 AG 110M 1.60E-07 1.49E-07 8.79E-08 NO DATA 2.91E-07 NO DATA 6.04E-05 TE 125M 2.68E-06 9.71E-07 3.59E-07 8.06E-07 1.09E-05 NO DATA 1.07E-05 TR 127M 6.77E-06 2.425-06 8.25E-07 1.73E-06 2.75E-05 NO DATA 2.27E-05 TR 127 1.10E-07 3.95E-08 2.385-08 8.15E-08 4.48E-07 NO DATA 8.68E-06 TE 129M 1.15E-05 4.29E-06 1.82E-06 3.95E-06 4.80E-05 NO DATA 5.79E-05 ,

TC 129 3.14E.00 1.18E-0D 7.C0E-09 2.41E-08 1.32E-07 NO DATA 2.37E-08 TE 131M 1.73E-06 8.46E-07 7.05E-07 1.34E-06 8.575-06 NO DATA 8.40E-05 l I

TE 131 1.97E-08 8.23E-09 6.22E-09 1.62E-08 8.63E-08 NO DATA 2.79E-09 TE 132 2.525-06 1.63E-06 1.53E-06 1.80E-06 1.575-05 NO DATA 7.71E-05 I 130 7.56E-07 2.23E-06 8.80E-07 1.895-04 3.48E-06 NO DATA 1.925-06 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 1.025-07 I 133 1.42E-06 2.475-06 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 4.995-06 4.58E-07 NO DATA 2.51E-10 l

I 135 4.433 07 1.16E-06 4.28E-07 7.655-05 1.865-06 NO DATA 1.31E-06 CS 134 6.22E-05 1. 4 8 E- 04 1.215-04 NO DATA 4.793-05 1.59E-05 2.598-06 CS 136 6.51E-06 2.57E-05 1.85E-05 NO DATA 1.43E-05 1.96E-06 2.92E-06 CS 137 7.975-05 1.09E-04 7.14E-05 NO DATA 3.70E-05 1.23E-05 2.11E-06 ]

CS 138 5.525-08 1.09E-07 5.40E-08 NO DATA 8.013-08 7.91E-09 4.65E-13 BA 139 9.70E-08 6.91E-11 2.84E-09 NO DATA 6.46E-11 3.92E-11 1.72E-07 I

BA 140 2.038-05 2.55E-08 1.33E-06 NO DATA 8.67E-09 1.46E-08 4.18E-05 j BA 141 4.71E-08 3.56E-11 1.59E-09 NO DATA 3.31E-11 2.02E-11 2.22E-17 )

l BA 142 2.13E-08 2.19E-11 1.34E-09 NO DATA 1.85E-11 1.24E-11 3.00E-26 ;

LA 140 2.50E-09 1.26E-09 3.33E-10 NO DATA NO DATA NO DATA 9.25E-05 1 IA 142 1.285-10 5.82E-11 1.45E-11 NO DATA NO DATA NO DATA 4.25E-07 CE 141 9.36E-09 6.335-09 7.18E-10 NO DATA 2.94E-09 NO DATA 2.42E-05 7

CE 143 1.655-09 1.22E-06 1.35E-10 NO DATA 5.37E-10 NO DATA 4.56E-05 j CE 144 4.883-07 2.045-07 2.62E-08 NO DATA 1.21E-07 NO DATA 1.65E-04 l PR 143 9.20E-09 3.69E-09 4.56E-10 NO DATA 2.135-09 NO DATA 4.03E-05 i

l. PR 144 3.01E-11 1.253-11 1.53E-12 NO DATA 7.05E-12 NO DATA 4.333-18 ND 147 6.295-09 7.27E-09 4.35E-10 NO DATA 4.2SE-09 NO DATA 3.49E-05 W 187 1.03E-07 8.61E-08 3.01E-08 NO DATA NO DATA NO DATA 2.82E-05

~H 1 ~~

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ATTACHMENT A O (Page 117 of 184) g OFFSITE DOSE CALCULATION MANUAL

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TABLE A.3-1* (coat'd)

N '

INGESTION DOSE FACTORS FOR ADULTS

\ (MREM PER PCI INGESTED)

.D

[r NUCLIDE BONE LIVER T BODY THYROID KIDMEY LUNG GI-LLI l I

i NP 239 1.19E-09 1.17E-10 6.45E-11 NO DATA 3.65E-10 NODATA 2.40E-05 Sb 124** 2.80E-06 5.29E-08 1.11E-06 6.79E-09 NO DATA 2.105-06 7.95E-05 Sb 125** 1.*198-06 2.00E-08 4.26E-07 1.82E-09 NO DATA 1.38E-06 1.97E-05 Sb 126** 1.15E-06 2.34E-08 4.15E-07 7.04E-09 NO DATA 7.055-07 9.40E-05 Co 57** NO DATA 1.75E-07 2.91E-07 NO DATA NO DATA NO DATA 4.44E-06

- Taken from Regulator Guide 1.109 (Rev. 0)

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ATTACHMENT A O (Page 118 of 184)

\

TABLE A-3.2 i M INOESTION DOSE FACTORS FOR TEENAGERS l

\ (MREM PER PCI INGESTED)

.D g- NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNO OI-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 NO DATA NO DATA 2.32E-05 l P 32 2.76E-04 1.71E-05 1.07E-05 NO DATA CR 51 NO DATA NO DATA 3.60E-09 2.00E-09 7.898-10 5.14E-09 6.05E-07 MN 54 NO DATA 5.90E-06 1.17E-06 NO DATA 1.76E-06 NO DATA 1.21E-05 MN 56 NO DATA 1.58E-07 2.81E-08 NO DATA 2.00E-07 NC DATA 1.04E-05 PE 55 3.78E-06 2.68E-06 6.25E-07 NO DATA NO DATA 1.7W 06 1.16E-06 i FE 59 5.87E-06 1.37E-05 5.29E-06 NO DATA NO DATA 4.32E-06 3.24E-05 j i

CO 50 NO DATA 9.72E 07 2.24E-06 NO DATA NO DATA NO DATA 1.3dR-05 CO 60 NO DATA 2.81E-06 6.338-06 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 i

NI 65 7.49E-07 9.57E-08 4.36E-08 NO DATA NO DATA NO DATA 5.19E-06 l 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 8.475-06 EN 69 1.478-08 2.80E-08 1.96E-09 NO DATA 1.83E-08 NO DATA 5.16E-00 BR 83 NO DATA NO DATA 5.74E-08 NO DATA NO DATA NO DhTA LT E-24 )

BR 84 NO DATA NO DATA 7.22E-08 NO DATA NO DATA NO DATA LT E-24 BR 85 NO DATA NO DATA 3.05E-09 NO DATA NO DATA NO DATA LT E-24 RB 86 NO DATA 2.98E-05 1.40E-05 NO DATA NO DATA NO DATA 4.41E-06 i RB 88 NO DATA 8.52E-08 4.54E-08 NO DATA NO DATA NO DATA 7.30E-15 I I

RB 89 NO DATA 5.50E-06 3.89E-08 NO DATA NO DATA NO DATA 8.43E-17 SR 89 4.40E-04 NO DATA 1.26E-05 NO DATA NO DATA NO DATA 5.24E-05 SR 90 8.30E-03 NO DATA 2.05E-03 NO DATA NO DATA NO DATA 2.33E-04 SR 91 8.07E-06 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 6.098-09 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-11 NO DATA NO DATA NO DATA 3.32E-05 I

Y 93 3.83E-09 NO DATA 1.05E-10 NO DATA NO DATA NO DATA 1.178-04 ZR 95 4.12E-06 1.30E-08 8.94E-09 NO DATA 1.91E-08 NO DATA 3.00E-05 ZR 97 2.37E-09 4.69E-10 2.16E-10 NO DATA 7.11E-10 NO DATA 1.27E-04 NB 95 8.22E-09 4.56E-09 2.51E-09 NO DATA 4.42'n-09 NO DATA 1.95E-05 NO 99 NO DATA 6.03E-06 1.15E-06 NO DATA 1.385-05 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

Taken from Regulator Guide 1.109 (Rev. 1) i

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ATTACHMENT A O (Page 119 of 184)

\

TABLE A-3.2 (coat'd)

E- INGESTION DOSE FACTORS FOR TEENAGERS

\ '(DEtEM PER PCI INGESTED)

.D g* NUCLIDE BOBEE LIVER T BODY THYROID KIDNEY LUNG OI-LLI TC 101 3.60E 10 5.12E-10 5.03E-09 NO DATA 9.26E-09 3.12E-10 8.755-17 RU 103 2.55E-07 NO DATA 1.09E-07 NO DATA 8.99E-07 NO DATA 2.13Ee05 RU 105 2.18E-08 NO DATA 8.46E-09 WO 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 TR 125M 3.83E-06 1.30E-06 5.12E-07 1.07E-06 NO DATA NO DATA 1.13E-05 TE 127M 9.67E-06 3.43E-06 1.15E-06 2.30E-06 3.92E-05 NO DATA 2.41E-05 TE 127 1.58E-07 5.60E-08 3.405-08 1.09E-07 6.40E-07 NO DATA 1.22E-05 TE 129M 1.63E-05 6.05E-06 2.585-06 5.2EE-06 6.82E-05 NO DATA 6.12E-05 TE 129 4.48E-08 1.67E-08 1.092-08 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 2.005-06 2.33E-06 2.12E-05 NO DATA 7.00E-05 I 130 1.03E-06 2.98E-06 1.193-06 2.43E-04 4.59E-06 NO DATA 2.29E-06 I 131 5.855-06 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 1.045-06 4.76E-04 5.98E-06 NO DATA 2.58E-06 I 134 1.465-07 3.87E-07 1.393-07 6.45E-06 6.10E-07 NO DATA 5.10E-09 I 135 6.10E-07 1.57r-06 5.82E-07 1.01E-04 2.48E-06 NO DATA 1.74E-06 C8 134 8.37E-05 ~.97E-04 4 9.145-05 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 C8 137 1.12E-04 1.49E-04 5.19E-05 NO DATA 5.07E-05 1.97E-05 2.12E-06 C8 138 7.76E-08 1.49E-07 7.45E-08 NO DATA 1.10E-07 1.28E-08 6.765-11 BA *19 1.39E-07 9.78E-11 4.05E-09 NO DATA 9.223-11 6.74E-11 1.24E-06 BA 140 2.84E-05 3.48E-08 1.835-06 NO DATA 1.18E-08 2.34E-08 4.38E-05 BA 141 6.71E-08 5.01E-11 2.24E-09 NO DATA 4.65E-11 3 43E-11 1.43E-13 BA 142 2.99E-08 2.99E-11 1.84E-09 NO DATA 2.53E-11 1.99E-11 9.18E-20 1A 140 3.48E-09 1.71E-09 4.55E-10 NO DATA NO DATA NO DATA 9.82E 05 1A 142 1.79E-10 7.95E-11 1.98E-11 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 2.355-09 1.71E-06 1.91E-10 NO DATA 7.67E-10 NO DATA 5.14E-05 CE 144 6.96E-07 2.88E-07 3.745-08 NO DATA 1.72E-07 NO DATA 1.75E-04 PR 143 1.31E-08 5.23E-09 6.525-10 NO DATA 3.04E-09 NO DATA 4.31E-05 PR 144 4.30E-11 1.76E-11 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 DATA 3.68E-05 W 187 1.46E-07 1.19E-07 4.17E-08 NO DATA NO DATA NO DATA 3.22E-05

3 '

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py Reference Use Page 124 of 188 O

ATTACHMENT A o (Page 120 of 184) g g OFFSITE DOSE CALCULATION MANUAL l

~

TABLE A-3.2 (oost*d) >

INGESTIOtt DOSI FACTORS FOR TEINAGERS '

\ (MtEM PER PCI INGESTED) '

.D F

NUCLIDE BOBIE LIVER T BODY TKiROID KIDNEY LUNG GI-LLI ND 239 1.76E-09 1.66E-10 9.22E-11 NO DATA 5.21E-10 NO DATA 2.67E-05 Rb 124** 3.87E-06 7.33E-08 1.51E-06 8.78E-09 NO DATA 3.38E-06 7.00E-0S Sb 123** 2.40E-06 2.71E-08 S.80E-07 2.37E-09 NO DATA 2.18E-06 1.93E-05 i Sb 126** 1.59E-06 3.25E-08 5.71E-07 8.99E-09 NO DATA 1.14E-06 9.41E-05 ;

Co 57** NO DATA 2.38E-07 3.99E-07 MO D7.TA No DF,TA NO DATA 4.44E-06

- Taken from Regulator Guide 1.109 (Rev. 0) l l

l 1

3 3 Revision: 0 OFFBITE DOSE CALCULATION MANUAL AP 07B-003 C) m Reference Use Page 125 of 188 O

ATTACHMENT A O (Page 121 of 184)

N OFFSITE DOSE CALCUIATION MANUAL

\ l

~~

TABLE A.3-3 1 N INGESTION DOSE FACTORS FOR CHILD

\ (NREM PER PCI INGESTED) ,

.D '

y 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 I C 14 1.21E-05 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.425-06 NA 24 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 i 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 ;

l MN 56 NO DATA 3.34E-07 7.54E-08 NO DATA 4.04E-07 NO DATA 4.84E-05 l FE 55 1.15E-05 6.50E-06 1.898-06 NO DATA NO DATA 3.45E-06 1.13E-06 l 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-03 l CO 60 NO DATA 5.29E-06 1.56E-05 NO DATA NO DATA NO DATA 2.93E-05 l 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 1.225-07 NO DATA NO DATA NO DATA 2.563-05 CU 64 NO DATA 2.45E-07 1.485-07 NO DATA 5.92E-07 NO DATA 1.15E-05 I ZN 65 1.37E-05 3.65E-05 2.27E-05 NO DATA 2.30E-05 NO DATA 6.41E-06 EN 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 l BR 84 NO DATA NO DATA 1.98E-07 NO DATA NO DATA NO DATA LT E-24 BR 85 NO DATA NO DATA 9.125 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 4.315-06 RB 88 NO DATA 1.90E-07 1.325-07 NO DATA NO DATA NO DATA 9.32E-09 1 l

RB 89 NO DATA 1.17E-07 1.045-07 NO DATA NO DATA NO DATA 1.02E-09 SR 89 1.32E-03 NO DATA 3.773-05 NO DATA NO DATA NO DATA 5.11E-05 l 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 3.625-07 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 1.395-11 NO DATA NO DATA NO DATA 7.48E-07 l Y 91 6.02E-07 NO DATA 1.61E-05 NO DATA NO DATA NO DATA 8.02E-05 l Y 92 3.60E-09 NO DATA 1.03E-10 NO DATA NO DATA NO DATA 1.04E-04 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 ER 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 3.293-06 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

Taken from ReBulator Guide 1.109 (Rev.1)

2 3 Ravision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 ,

C1 i g Reference Use Page 126 of 188 i O

ATTACHMENT A U (Page 122 of 184)

M-g OFFSITE DOSE CALCULATION MANUAL TABLE A 3-3 (oost'd)

N INOESTION DOSE FACTORS FOR GILD '

\ (MREM PER PCI INGESTED)

.O (y- NUCLIDE BONE LIVER T BODY 'DIYROID EIDNEY LUNG GI-LLI TC 101 1.07E-09 1.12E-09 1.42E-06 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 1.895-05 RU 105 6.45E-06 NO DATA 2.34E-08 NO DATA 5.67E-07 NO DATA 4.215-05 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 3.645 07 2.91E-07 NO DATA 6.78E-07 NO DATA 4.33E-05

_TE 125M 1.145-05 3.09E-06 1.52E-06 3.20E-06 NO DATA NO DATA 1.10E-05 1 TE 127M 2.89E-05 7.78E-06 3.43E-06 6.918-06 8.24E-05 NO DATA 2.345-05 i TE 127 4.71E-07 1.275-07 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-00 3.10E 00 9.5CE-08 3.922-07 1:0 DATA 8.3 4E -06 !

I TE 131M 7.20E-06 2.498-06 2.65E-06 5.125-06 2.41E-05 NO DATA 1.01E-04 TE 131 8.30E-00 2.538-08 2.47E-08 6.35E-08 2.51E-07 NO DATA 4.36E-07 TE 132 1.015-05 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 2.768-06 I 131 1.72E-05 1.73E-05 9.83E-06 5.725-03 2.84E-05 NO DATA 1.54E-06 I 132 8.00E-07 1.475-06 6.76E-07 6.82E-35 2.2SE-06 NO DATA 1.73E-06 I 133 5.92E-06 7.32E-06 2.773-06 1.36E-03 1.22I-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 C8 137 3.27E-04 3.13E-04 4.62E-05 NO DATA 1.02E-04 3.67E-05 1.96E-06 C8 138 2.28E-07 3.17E-07 2.015-07 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 2.375-08 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 i BA 142 0.74E-08 6.29E-11 4.88E-09 NO DATA 5.09E-11 3.70E-11 1.14E-09 LA 140 1.015-08 3.53E-09 1.195-09 NO DATA NO DATA NO DATA 9.84E-05 LA 142 5.24E-10 1.67E-10 5.23E-11 NO DATA NO DATA NO DATA 3.31E-05 3 141 3.975-08 1.98E-08 2.94E-09 NO DATA 8.68E-09 NO DATA 2.478-05 3 143 6.99E-09 3.79E-06 5.49E-10 NO DATA 1.59E-09 NO DATA 5.555-05 3 144 2.00E-06 6.52E-07 1.11E-07 NO DATA 3.61E-07 NO DATA 1.70E-04 PR 143 3.93E-08 1.18E-08 1.95E-09 NO DATA 6.39E-09 NO DATA 4.245-05 PR 144 1.29E-10 3.99E-11 6.495-12 NO DATA 2.11E-11 NO DATA 8.59E-08 ND 147 2.79E-08 2.27A-08 1.75E-09 NO DATA 1.24E-08 NO DATA 3.58E-05 N 187 4.29E-07 2.54E-07 1.14E-07 NO DATA NO DATA NO DATA 3.575-05

r

$ Rovicion: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 0

m Reference Use Page 127 of 188 O

ATTACHMENT A O (Page 123 of 184)

\

~

TABLE A.3-3 (coat'd)

N '

INGESTION DOSE FACTORS FOR CHILD

\ (MREM PER PCI INGESTED)

.0 (f NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG OI-LLI NP 239 5.25C-09 3.77E-10 2.65E-10 NO DATA 1.09E-09 NO DATA 2.79E-05 Sb 124** 1.11E-05 1.44E-07 3.89E-06 2.45E-08 NO DATA 6.16E-06 6.94E-05 Bb 125** 7.16E-06 5.52E-08 1.50E-06 6.63E-09 NO DATA 3.99E-06 1.71E-05 Sb 124** 4.40E-06 6.73E-08 1.59R-06 2.58E-06 NO DATA 2.10E-06 8.87F-05 Co 57** NO DATA 4.93E-07 9.98E-07 NO DATA NO DATA NO DATA 4.04E-06

- Taken from Regulator Guide 1.109 (Rev. 0) i I

l I

1 3 Rsvision: 0 OFFSITE DOSE CALCUIATION MANUAL AP'07B-003

.. O m Reference Use Page 128 of 188 0

ATTACHMENT A D (Page 124 of 184)

\

TABLE A.3-4*

M- INGESTION DO6I FACTORS 111 INFANT ,

\ (NREN PER PCI INGESTED)

.D g- NUCLIDE BONE LIVER T BODY THYROID KIDNEY LIBIG GI-LLI H 3 NO DATA 3.083-07 3.08E-07 3.085-07 3.00E-07 3.00E-07 3.08E-07 C 14 2.37E-05 5.06E-06 5.06E-06 5.065-06 5.06E-06 5.06k-06 5.06E-06 NA 24 1.01E-05 1.013-05 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 1.415-08 9.20E 09 2.01E-09 1.79E-08 4.11E-07 1 MN 54 NO DATA 1.99E-05 4.51E-06 NO DATA 4.41E-06 NO DATA 7.31E-06 i NN 56 NO DATA 8.18E-07 1.41E-07 NO DATA 7.03E-07 NO DATA 7.43E-05 FE 55 1.393-05 8.98E-06 2.405-06 NO DATA NO DATA 4.39E-06 1.14E-06 FE 59 3.085-05 5.38E-05 2.12E-05 NO DATA NO DATA 1.59E-05 2.57E-05 CO 50 NO DATA 3.60E-06 0.903-06 NO DATA !!O DATA NO DATA 8.97E 06 CO 60 NO DATA 1.00E-05 2.55E-05 NO DATA NO DATA NO DATA 2.57E-05 NI 63 6.34E-04 3.928-05 2.20E-05 NO DATA NO DATA- NO DATA 1.95E-06 NI 65 4.70E-06 5.32E-07 2.42E-07 NO DATA NO DATA NO DATA 4.05E-05 CU 64 NO DATA 6.09E-07 2.82E-07 NO DATA 1.03E-06 NO DATA 1.25E-05 EN 65 1.84E-05 6.313-05 2.91E-05 No DATA 3.06E-05 NO DATA 5.33E-05 EN 69 9.33E-08 1. 6 8 B'-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 BR 84 NO DATA NO DATA 3.82E-07 NO DATA NO DATA NO DATA LT E-24 j BR 85 NO DATA NO DATA 1.94E-08 NO DATA NO DATA NO DATA LT E-24 l RB 86 NO DATA 1.70E-04 8.40E-05 NO DATA NO DATA NO DATA 4.35E-06 RB 88 NO DATA 4.98E-07 2.73E-07 NO DATA NO DATA NO DATA 4.85E-07 ;

i 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 l SR 91 5.00E-05 MO 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-11 NO DATA NO DATA NO DATA 2.70E-06 Y 91 1.13E-06 NO DATA 3.01E-08 NO DTJA NO DATA NO DATA 8.10E-05 Y 92 7.65E-09 NO DATA 2.15E-10 No DATA NO DATA NO DATA 1.46E-04 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 ER 97 1.48E-08 2.54E-09 1.16E-09 NO DATA 2.56E-09 NO DATA 1.62E-04 NE 95 4.20E-08 1.73E-08 1.00E-08 NO DATA 1.24E-08 NO DATA 1.465-05 NO 99 NO DATA 3.405-05 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

Taken from Regulator Ouide 1.109 (Rev. 1)

H 3

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ATTACHMENT A o (Page 125 of 184)

N OFFSITE DOSE CALCUIATION MANUAL

\

~

TABLE A.3 4* (oost'd) lN l

INGESTION DO8E FACTORS FOR INFANT

\ (MREM PER PCI INGESTED)

.0 g- NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI g TC 101 2.27E-09 2.86E-09 2.83E-08 NO DATA 3.40E-08 1.56E-09 4.86E-07 !

2U 103 1.48E-06 NO DATA 4.95E-07 NO DATA 3.083-06 NO DATA 1.80E-05 l RU 105 1.36E-07 NO DATA 4.58E-08 NO DATA 1.00E-06 NO DATA 5.41E-05 RU 106 2.41E-085 NO DATA 3.01R-06 NO DATA 2.85E-05 NO DATA 1.63E-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 1.11E-05 l l

TE 127M 5.85E 1.94E-05 7.08E-06 1.69E-05 1.44E-04 NO DATA 2.36E-05 I 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 .50 DATA 5.975-05 i TE . 129 2.84E-07 9.79E-03 6.63E-08 2.38E-07 7.07E-07 UO DATA 2.273-05 l TE 131M 1.525-05 6 . '.".E- 0 6 5.05E-06 1.24E-05 4.21E-05 NO DATA 1.035-04 TE 131 1.76E-07, 4.ME-22 4.94E-08 A.57E-07 4.50E-07 NO DATA 7.11E-06 TE 132 2.08E-05 1.03E-05 9.61E-06 1.52E-05 6.44E-05 NO DATA 3.81E-05 I 130 6.005-06 1.325-05 5.30E-06 1.485-03 1.45E-05 NO DATA 2.83E-06 I 131 3.59E-05 4.23E-05 1.86E-05 1.393-02 4.94E-05 NO DATA 1.515-06 I 132 1.66E-06 3.37E-06 1.20E-06 1.58E-04 3.76E-06 NO DATA 2.73M-06 I 133 1.25E-05 1.825-05 5.33E-06 3.31E-03 2.14E-05 NO DATA 3.08E-06 I 134 8.695-07 1.78E-06 6.33E-07 4.15E-05 1.99E-06 NO DATA 1.84E-06 I 135 3.64E-06 7.24E-06 2.64E-06 6.495-04 8.07E 06 NO DATA 2.62E-06 l CS 134 3.77E-04 7.03E-04 7.10E-05 NO DATA 1.81E-04 7.42E-05 1.91E-06 l CS 136 4.595-05 1.35E-04 5.04E-05 NO DATA 5.385-05 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 i 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

!. BA 140 1.71E-04 1.71E-07 8.81E-06 NO DATA 4.06E-08 1.05E-07 4.20E-05 j BA 141 4.25B-07 2.91E-10 1.34E-08 NO DATA 1.75E-10 1.77E-10 5.19E-06 BA 142 1.845-07 1.533-10 9.06E-09 NO DATA 8.81E-11 9.26E-11 7.59E-07 j 1A 140 2.11E-08 8.32E-09 2.145-09 NO DATA NO DATA NO DATA 9.77E-05 LA 142 1.10H-09 4.04E-10 9.67E-11 NO DATA NO DATA NO DATA 6.86E-05 CE 161 7.87E-08 4.80E-08 5.653-09 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 j PR 143 8.13E-08 3.04E-08 4.03E-09 NO DATA 1.135-08 NO DATA 4.29E-05

{ PR 144 2.743 1.06E-10 1.38E-11 NO DATA 3.84E-11 NO DATA 4.93E-06

. ND 147 5.535-08 5.68E-08 3.483-09 NO DATA 2.19E-08 NO DATA 3.60E-05 N 187 9.035-07 6.28E-07 2.17E-07 NO DATA NO DATA NO DATA 3.69E-05

f Rsvision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B 003 Reference Use Page 130 of 188 0

ATTACHMENT A O (Page 126 of 184) '

N

\ OFFSITE DOSE CALCULATION MANUAL <

~~ I TABLE A.3-4* (coat'd)

N INGESTION DOSE FACTORS FOR INFANT '

'\ (MREM PER PCI INGESTED)

.D g- NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI ,

NP 239 1.11E-08 9.93E-10 5.61E-10 NO DATA 1.98E-09 NO DATA 2.87E-05 Sb 124** 2.14E-05 3.15E-07 6.63E-06 5.68E-08 NO DATA 1.34E-05 6.60E-05 Sb 125** 1.23E-05 1.19E-07 2.53E-06 1.54E-08 NO DATA 7.72E-06 1.64E-05 '

l Sb 126** 8.06E-06 1.58E-07 2.91E-06 6.19E-08 NO DATA 5.07E-06 8.35E-06 l Co 57+* NO DATA 1.15E-06 1.87E-06 NO DATA NO DATA NO DATA 3.92E-06

- Taken from Regulator Guide 1.109 (Rev. 0) l l

i

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m Reference Use Page 131 of 188 O

ATTACHMENT A O (Page 127 of 184)

N

\

OFFSITE DOSE CALCULATION MANUAL TABLE A.3-5*

N STABLE ELEMENT TRANSFER DATA k Element Rh #; # #" II

.0 Vaa /ani l Milk (d/11 Meat (d/ka)

U" H 4.BE 00 1.0E-02 + 1.20E-02 C 5.5E 00 1.2E-02 + 3.1E-02 Na 5.2E-02 4.0E-02 3.0E-02 P 1.1E 00 2.5E-02 4.6E-02 Cr 2.5E-04 2.2E-03 2.4E-03 Mn 2.9E-02 2.5E-04 8.0E-04 Fe 6.6E-04 1.25-03 + 4.0E-02 Co 9.4E-03 1.0E-03 1.3E-02 Ni 1.9E-02 6.7E-03 5.3E-02 Cu 1.2E-01 1.4E-02 + 8.0E-03 Zn 4.0E-01 3.9E-02 3.0E-02 Rb 1.3E-01 3.0E-02 3.1E-02 Sr 1.78-02 8.0E-04 + 6.0E-04 Y 2.EE-03 1.0E-05 4.6E-03 Zr 1.75-04 5.0E-06 3.4E-02 Nb 9.4E-03 2.5E-03 2.8E-01 Mo 1.2E-01 7.5E-03 8.0E-03 Tc 2.5E-01 2.5E-02 4.0E-01 Ru 5.0E-02 1.0E-06 4.0E-01 Rh 1.3E 01 1.0E-02 1.5E-03 Ag 1.5E-01 5.0E-02 1.7E-02 Te 1.3E 00 1.0E-03 7.7E-02 I 2.0E-02 6.0E-03 + 2.9E-03 Cs 1.0E-02 1.2E-02 + 4.0E-03 Ba 5.0E 03 4.0E-04 3.2E-03 La 2.5E-03 5.0E-06 2.0E-04 Ce 2.5E-03 1.0E-04 1.2E-03 Pr 2.5E-03 5.0E-06 4.7E-03 Nd 2.4E-03 5.0E-06 3.3E-03 W 1.8E-02 5.0E-04 1.3E-03 Np 2.5E-03 5.0E-06 2.0E-04

+ F. (Goat) values for milk (d/l)

Elamant Milk (d/11 H 1.78-01 C 1.0E-01 P 2.5E-01 !

Fe 1.3E.04 Cu 1.3E-02 Sr 1.4E-02 l I 6.0E-02 Cs 3.0E-01

Taken from Regulatory Guide 1.109 (Rev. 1)

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TABLE A.4-1 M '

SITE RELATED DOSE COMMITMENT FACTOR AIT

\ #GtEM/HR PER pCI/ML 3 ADULT O'

NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI H 3 0.00E-01 8.96E 00 8.96E 00 8.f6E 00 8.96E 00 8.96E 00 8.96E 00 C 14 3.15E 04 6.30E 03 6.30E 03 6.30E 03 6.30E 03 6.30E 03 6.30R 03 NA 24 5.48B 02 5.48E 02 5.48E 02 5.48E 02 5.48E 02 5.48E 02 5.48E 02 P 32 4.62E 07 2.87B 06 1.79E 06 0.00E-01 0.00E-01 0.003-01 5.20E 06 CR 51 0.00E-01 0.00E-01 1.49E 00 8.94E-01 3.29E-01 1.9BE 00 3.76E 02 MN 54 0.00E-01 4.76E 03 9.08E 02 0.00E-01 1.42E 03 0.00E-01 1.46E 04 MN 56 0.00E-01 1.20E 02 2.12E 01 0.00E-01 1.52E 02 0.00E-01 3.82E 03 FE 55 8.87E 02 6.13E 02 1.43E 02 0.00E-01 0.00E-01 3.42E 02 3.52E 02 FE 59 1.40E 03 3.29E 03 1.26E 03 0.00E-01 0.00E-01 9.19E 02 1.10E 04 CO 58 0.00E-01 1.51E 02 3.39E 02 0.00E-01 0.00E-01 0.00E-01 3.06E 03 CO 60 0.00E-01 4.34E 02 9.5BE 02 0.00E-01 0.00E-01 0.00E-01 8.16E 03 NI 63 4.19E 04 2.94E 03 1.41B 03 0.00E-01 0.00E-01 0.00E-01 6.07E 02 NI 65 1.70E 02 2.21E 01 1.01E 01 0.00E-03. 0.00E-01 0.00E-01 5.61E O2 CU 64 0.00E-01 1.69E 01 7.93E 00 0.00E-01 4.26E-01 0.00E-01 1.44E 03 KN 65 2.36E 04 7.50E 04 3.39E 04 0.00E-01 5.02E 04 0.00E-01 4.73E 04 ZN 69 5.02E 01 9.60E 01 6.67E 00 0.00E-01 6.24E-01 0.00E-01 1.44E 01 BR 83 0.00E-01 0.00E-01 4.38E 01 0.00E-01 0.00E-01 0.00E-01 6.30E 01 BR 84 0.00E-01 0.00E-01 5.67E 01 0.00E-01 0.00E-01 0.00E-01 4.45E-04 BR 85 0.00E-01 0.00E-01 2.33E 00 0.00E-01 0.00E-01 0.00E-01 86 1.09E-15l RB 0.00E-01 1.03E 05 4.79E 04 0.00E-01 0.00E 01 0.00E-01 2.03E 04 RB 88 0.005-01 2.95E 02 1.56E 02 0.00E-01 0.00E-01 0.00E-01 4.07E-09 RB 89 0.005-01 1.95E 02 1.37E 02 0.00E-01 0.00E-01 0.00E-01 1.13E-11 SR 89 4.78B 04 0.00E-01 1.37E 03 0.00E-01 0.00E-01 0.00E-01 7.66E 03 SR 90 1.18E 06 0.00E-01 2.88E 05 0.00E-01 0.00E-01 0.00E-01 3.40E 04 SR 91 8.79E 02 0.00E-01 3.55E 01 0.00E-01 0.00E-01 0.00E-01 4.19E 03 BR 92 3.33E 02 0.00E-01 1.44E 01 0.00E-01 0.00E-01 0.00E-01 6.60E 03 Y 90 1.38E 00 0.00E-01 3.69E-02 0.00E-01 0.00E-01 0.00E-01 1.46E 04 Y 91M 1.30E-02 0.00E-01 5.04E-04 0.00E-01 0.00E-01 0.00E-01 3.82E-02 Y. 91 2.02E 01 0.00E-01 5.39E-01 0.00E-01 0.00E-01 0.00E-01 1.11E 04 Y 92 1.21E-01 0.00E-01 3.538-03 0.00E-01 0.00E-01 0.00E-01 2.12E 03 Y 93 3.83E-01 0.00E-01 1.065-02 0.00E-01 0.00E-01 0.00E-01 1.22E 04 ER 95 2.77E 00 8.88E-01 6.01E-01 0.00E-01 1.39B 00 0.00E-01 2.82E 03 ZR 97 1.53E-01 3.09E-02 1.41E-02 0.LJE-03m 4.67E-02 0.00E-01 9.57E 03 NB 95 4.47E 02 2.49E 02 1.34E 02 0.00E-01 2.46E 02 0.00E-01 1.51E 06 MO 99 0.00E-01 4.62E 02 8.79E 01 0.00E-01 1.05E 03 0.00E-01 1.07E 03 TC 99M 2.94E-02 8.32E-02 1.06E 00 0.00E-01 1.26E 00 4.07E-02 4.92E 01 L

9 / 92

3 . _ - .

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TABLE A.4-1 (coat'd)

N SITE RELATED DOSE COpetITMENT FACTOR AIT

\ MtEM/HR PER'pCI/ML

.S ADULT tT NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI TC 101 3.03E-02 4.36E-02 4.28E-01 0.00E-01 7.85E-01 2.23E-02 1.31E-13 RU 103 1.98E 01 0.00E-01 8.548 00 0.00E-01 7.57E 01 0.00E-01 2.31E 03 RU 105 1.65E 00 0.00E-01 6.522-01 0.00E-01 2.13E 01 0.00E-01 l'.01E 03 RU 106 2.95E 02 0.00E-01 3.73E 01 0.00E-01 5.69E 02 0.00E-01 1.91E 04 AG 110M 1.42E 01 1.31E 01 7.80E 00 0.00E-01 2.56E 01 0.00E-01 5.36E 03 TE 125M 2.79E 03 1.01E 03 3.74E 02 8.39E 02 1.13E 04 0.00E-01 1.11E 04 TE 127M 7.05E 03 2.52E 03 8.59E 02 1.80E 03 2.86E 04 0.00E-01 2.36E 04 TE 127 1.14E 02 4.11E 01 2.48E 01 8.48E 01 4.66E 02 0.00E-01 9.03E 03 TE 129M 1.20E 04 4.47E 03 1.89E 03 4.11E 03 5.00E 04 0.005-01 6.03E 04 TE 129 3.27E 01 1.23E 01 7.96E 00 2.51E 01 1.37E 02 0.00E-01 2.47E 01 TE 132M 1.80E 03 8.81E 02 7.34E 02 1.39E 03 8.92E 03 0.00E-01 8.74E 04 TE 131 2.05E 01 8.57E 00 6.47E 00 1.69E 01 8.98E 01 'O.00E-01 2.90E 00 TE 132 2.62E 03 1.70E 03 1.59E 03 1.87E 03 1.63E 04 0.00E-01 8.02E 04 I 130 9.01E 01 2.66E 02 1.055 02 2.25E 04 4.15E 02 0.005-01 2.29E 02 I 131 4.96E 02 7.09E 02 4.06E 02 2.328 05 1.22E 03 0.00E-01 1.87E 02 I 132 2.42E 01 6.47E 01 2.263 01 2.26E 03 1.03E 02 0.00E-01 1.22E 01 I 133 1.69E 02 2.94E 02 8.973 01 4.32E 04 5.13E 02 0.00E-01 2.64E 02 I 134 1.26E 01 3.43E 01 1.23E 01 5.94E 02 5.46E 01 0.00E-01 2.99E-02 I 135 5.28E 01 s.38E O2 5.10E 01 9.11E 03 2.22E 02 0.00E-01 1.56E 02 CS 134 3.03E 05 7.11E 05 5.89E 05 0.00E-01 2.33E 05 7.75E 04 1.26E 04 CS 136 3.17E 04 1.20E 05 9.01E 04 0.00E-01 6.97E 04 9.55E 03 1.42E 04 CS 137 3.44E 05 5.31F 05 3.48E 05 0.00E-01 1.80E 05 5.99E 04 1.03E 04 CS 138 2.69E 02 5.311' 02 2.63E 02 0.00E-01 3.90E 02 3.85E 01 2.27E-03 BA 139 9.00E 00 6.415-03 2.64E-01 0.00E-01 5.99E-03 3.64E-03 1.60E 01 BA 140 1.88E 03 2.37E 00 1.23E 02 0.00E-01 8.05E-01 1.35E 00 3.88E 03 BA 141 4.37E 00 3.30E-03 1.48E-01 0.00E-01 3.07E-03 1.873-03 2.06E-09 RA 142 1.98E 00 2. 0 3 E,- 03 1.24E-01 0.00E-01 1.72E-03 1.15E-03 2.78E-18 LA 140 3.585-01 1.80E-01 4.76E-02 0.005-01 0.00E-01 0.00E-01 1.32E 04 LA 142 1.83E-02 8.33E-03 2.07E-03 0.00E-01 0.00E-01 0.00E-01 6.00E 01 CE 141 0.01E-01 5.42E-01 6.15E-02 0.00E-01 2.52E-01 0.00E-01 2.07E 03 CE 143 1.41E-01 1.04E 02 1.16E-02 0.00E-01 4.60E 02 0.00E-01 3.905 03 CE 144 4.18E 01 1.75E 01 2.24E 00 0.00E-01 1.04E 01 0.00E-01 1.41E 04 PR 143 1.32E 00 5.28E-01 6.52E-02 0.00E-01 3.05E-01 0.00E-01 5.77E 03 PR 144 4.31E-03 1.79E-03 2.19E-04 0.00E-01 1.015-03 0.00E-01 6.19E-10 ND 147 9.00E-01 1.04E 00 6.22E-02 0.00E-01 6.08E-01 0.00E-01 4.99E 03 W 187 3.04E 02 2.55E 02 8.9CE 01 0.00E-01 0.00E-01 0.00E-01 8.34E 04

H 7

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TABLE A.4-1 (coat'd)

M. SITE RELATED DOSE COPEITMNT FACTOR AIT

\ MREM /HR PER pCI/ML y ADULT NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI NP 239 1.20E-01 1.25E-02 6.91E-03 0.00E-01 3.91E-02 0.00E-01 2.57B 03 Sb 124 2.40E 02 4.53E 00 9.50E 01 5.81E-01 0.00E-01 1.87E 02 6.81E 03 Sb 125 1.53E 02 1.71E 00 3.65E 01 1.56E-01 0.00E-01 1.18E 02 1.69E 03 Sb 126 9.85E 01 2.00E 00 3.55E 01 6.03E-01 0.00E-01 6.04E 01 8.05E 03 Co 57 0.00E-01 3.55E 01 5.90E 01 0.00E-01 0.005-01 0.00E-01 S.01'3 02

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ATTACHMENT A O (Page 131 of 184)

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TABI.E 4. 4 2 M SITE RELATED DOSE ColetI3NENT FACTOR AIT

\ MREN/HR PER pCI/ML

.D TREN U*

NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI H 3 0.00E-01 6.34E 00 6.34E 00 6.34E 00 6.34E 00 6.34E 00 6.34E 00 C 14 3.43E 04 6.86E 03 6.86E 03 6.86E 03 6.86E 03 6.86E 03 6.06E 03 NA 24 5.53E 02 5.53E 02 5.53E 02 5.53I 02 5.53E 02 5.53I 02 5.53E 02 P' 32 5.04E 07 3.12E 06 1.95E 06 0.00E-01 0.00E-01 0.00E-01 4.23E 06 CR 51 0.00E-01 0.00E-01 1.52E 00 8.46E-00 3.34E-00 2.17E 00 2.56E 02 MN 54 0.00E-01 4.65E 03 9.22E 02 0.00E-01 1.39E 03 0.00E-01 9.53E 03 MN 56 0.00E-01 1.24E 02 2.21E 01 0.00E-01 1.58E 02 0.00E-01 8.19E 03 FE 55 9.093 02 6.45E 02 1.50E 02 0.00E-01 0.00E-01 4.09E 02 2.79E 02 FE 59 1.41E 03 3.30E 03 1.27E 03 0.00E-01 0.00E-01 1.04E 03 7.79E 03 CO 58 0.00E-01 1.45E 02 3.35E 02 0.005-01 0.00E-01 0.00E-01 2.00E 03 CO 60 0.00E-01 4.20E 02 9.45E 02 0.00E-01 0.00E-01 0.00E-01 5.47E 03 NI 63 4.26E 04 3.01E 03 1.44E 03 0.00E-01 0.00E-01 0.00E-01 4.79E 02 NI 65 1.80E 02 2.30E 01 1.05E 01 0.00E-01 0.00E-01 0.00E-01 1.25E 03 CU 64 0.00E-01 1.72E 01 8.08E 00 0.00E-01 4.35E 01 0.00E-01 1.33E 03 EN 65 2.13E 04 7.41E 04 3.46E 04 0.005-01 4.74E 04 0.00E-01 3.14E 04 EN 69 5.45E 01 1.04E 02 7.26E 00 0.00E-01 6.78I 01 0.00E-01 1.91E 02 BR 83 0.00E-01 0.00E-01 4.73E 01 0.00E-01 0.00E-01 0.00E-01 8.24E-16 BR 84 0.00E-01 0.00E-01 5.95E 01 0.00E-01 0.00E-0.1 0.00E-01 8.24E-16 BR 85 0.00E-01 0.00E-01 2.51E 00 0.00E-01 0.005-01 0.00E-01 8.24E-16 RB 86 0.00E-01 1.10E 05 5.193 04 0.00E-01 0.00E-01 0.005-01 1.63E 04 RB 88 0.00E-01 3.16E 02 1.68E 02 0.00E-01 0.00E-01 0.00E-01 2.71E-05 RB 89 0.00E-01 2.04E 02 1.44E 02 0.00E-01 0.00E-01 0.00E-01 3.12E-07 SR 89 4.973 04 0.00E-01 1.42E 03 0.005-01 0.00E-01 0.00E-01 5.91E 03 SR 90 9.37,E 05 0.00E-01 2.31E 05 0.00E-01 0.00E-01 0.00E-01 2.63B 04 SR 91 9.11E 02 0.00E-01 3.62E 01 0.00E-01 0.00E-01 0.00E-01 4.13E 03 SR 92 3.44E 02 0.00E-01 1.47E 01 0.00E-01 0.00E-01 0.005-01 8.77E 03 Y 90 1.42E 00 0.005-01 3.83E-01 0.00E-01 0.00E-01 0.00E-01 1.17E 04 Y 91M 1.345-01 0.00E-01 5.11E-03 0.00E-01 0.00E-01 0.00E-01 6.325-01 Y 91 2.095 01 0.00E-01 5.59E-00 0.00E-01 0.005-01. 0.00E-01 8.55E 03 Y 92 1.26E-00 0.00E-01 3.63E-02 0.00E-01 0.00E-01 0.00E-01 3.44E 03 Y 93 3.97E-00 0.00E-01 1.09E-01 0.00E 01 0.00E-01 0.00E-01 1.21E 04 ER 95 2.64E 00 8.34E-01 5.74E-00 0.00E-01 1.23E 00 0.00E-01 1.92E 03 ER 97 1.52E-00 3.01E-02 1.39E-01 0.00E-01 4.565-01 0.00E-01 8.15E 03 NB 95 4.50E 02 2.50E 02 1.37E 02 0.005-01 2.42E 02 0.00E-01 1.07E 06 MO 99 0.00E-01 4.61E 02 8.78E 01 0.00E-01 1.05E 03 0.00E-01 8.25E 02 TC 99M 2.84E-01 7.92E-02 1.03I 00 0.00E-01 1.18E 00 4.39E-01 5.20E 01

-__ _ = - ,

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a ATTACHMENT A O (Page 132 of 184) '

N OFFSITE DOSE CALCULATION MANUAL i

\ '

l TABLE A.4-2 (coat'd)

M ' SITE RELATED DOSI ColetITMENT FACTOR AIT .

\ MREN/HR PER pCI/ML 3 TREN ,

G* l NUCLIDE B00lE L%VER T BODY THYROID KIDNEY IABIG GI-LLI ;

TC 101 3.085-01 4.38E-02 4.30E-00 0.00E-01 7.92E-00 2.67E-01 7.48E-09 L RU 103 1.95E 01 0.00E-01 8.33E 00 0.00E-01 6.87E 01 0.005-01 1.63E 03 RU 105 1.67E 00 0.00E-01 6.462-00 0.00E-01 2.10E 01 0.00E-01 1'.'34E 03 RU 106 2.99E 02 0.00E-01 3.77E 01 0.00E-01 5.77E 02 0.00E-01 1.44E 04 AG 110M 1.28E 01 1.21E 01 7.36E 00 0.00E-01 2.31E 01 0.00E-01 3.40E 03 TE 125M 3.02E 03 1.095 03 4.03E 02 8.43E 02 0.00E-01 0.00E-01 8.90E 03 l

TE 127M 7.62E 03 2.70E 03 9.06E 02 1.01E 03 3.095 04 0.00E-01 1.905 04 l TE 127 1.24E 02 4.41E 01 2.68E 01 8.59E 01 5.04E 02 0.005-01 9.61E 03 I TE 129M 1.28E 04 4.775 03 2.03E 03 4.14E 03 5.37E 04 0.00E-01 4.42E 04 l TE 129 3.53E 01 1.32E 01 8.59E C0 2.52E 01 1.48E 02 0.00E-01 1.93E 02 TE 131M 1.92E 03 9.22E 02 7.69E 02 1.39E 03 9.61E 03 0.00E-01 7.40E 04 TE 131 2.20E 01 9.06E 00 6.87E 00 1.69E 01 9.61E 01 0.00E-01 1.80E 00 TE 132 2.75E 03 1.74E 03 1.64E 03 1.84E 03 1.675 04 0.005-01 5.51E 04 I 130 8.81E 01 2.55E 02 1.023 02 2.085 04 3.925 02 0.00E-01 1.96E 02 I 131 5.00E 02 7.00E 02 3.76E 02 2.045 05 1.21E 03 0.00E-01 1.39E 02 I 132 2.39E 01 6.24E 01 2.24E 01 2.10E 03 9.83E 01 0.00E-01 2.72E 01 I 133 1.725 02 2.92E 02 8.89E 01 4.07E 04 5.11E 02 0.005-01 2.215 02 I 134 1.25E 01 3.31E 01 1.19E 01 5.51E O2 5.22E 01 0.005-01 4.36E-01 I 135 5.22E 01 1.34E 02 4.90E 01 8.64E 03 2.12E 02 0.005-01 1.495 02 CS 134 3.105 05 7.30E 05 3.395 05 0.00E-01 2.32E 05 0.86E 04 9.08E 03 CS 136 3.18E 04 1.25E 05 8.41E 04 0.00E-01 6.82E 04 1.07E 04 1.01E 04 CS 137 4.15E 05 5.52E 05 1.925 05 0.00E-01 1.88E 05 7.30E 04 7.86E 03 Cs 138 2.88E 02 5.52E 02 2.76E 02 0.00E-01 4.08E 02 4.74E 01 2.515-01 BA 139 9.10E 00 f.40E-03 2.655-00 0.00E-01 6.03E-02 4.415-02 8.11E 01 BA 140 1.86E 03 2.28E 00 1.20E 02 0.00E-01 -7.72E-00 1.53E 00 2.87E 03 BA 141 4.39E 00 3.28E-03 1.475-00 0.00E-01 3.04E-02 2.24E-02 9.36E-06 BA 142 1.96E 00 1.96E-03 1.20E-00 0.00E-01 1.66E-02 1.305-02 6.01E-12 LA 140 3.61E-00 1.77E-01 4.72E-01 0.00E-01 0.00E-01 0.00E-01 1.025 04 i LA 142 1.86E-01 8.25E-03 2.05E-02 0.00E-01 0.00E-01 0.00E-01 2.51E 02 ,

CE 141 7.98E-00 5.32E-01 6.12E-01 0.005-01 2.51E-00 0.00E-01 1.52E 03 '

CE 143 1.415-00 1.03E 02 1.158-01 0.00E-01 4.60E-01 0.00E-01 3.00E 03 CE 144 4.175 01 1.73E 01 2.24E 00 0.005-01 1.03E 01 0.00E-01 1.05E 04 PR 143 1.36E 00 5.43E-01 6.76E-01 0.00E-01 3.15E-00 0.00E-01 4.47E 03 PR 144 4.46E-02 1.83E-03 2.265-03 0.00E-01 1.05E-02 0.00E-01 4.92E-06 ND 147 9.73E-00 1.06E 00 6.34E-01 0.00E-01 6.21E-00 0.00E-01 3.42E 03 M 187 3.28E 02 2.67E 02 9.37E C1 0.00E-01 0.00E-01 0.00E-01 7.24E 04

i 3 Revision: 0' 3 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 m

g Reference Use Page 137 of 188 O

ATTACHMENT A O (Page 133 of 184)

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TABLE A.4 2 (coat'd)

M SITE REIATED DOSE COISEITMENT FACTOR AIT

\ MREM /HR PER pCI'ML

/

J TREN W

NUCLIDE B0ltE LIVER T BODY THYROID KIDNEY LUBIG GI-LLI NP 239 1.34E-00 1.27E-02 7.04E-02 0.00E 01 3.98E-01 0.00E-01 2.04E 03 Sb 124 2.32E 02 4.28E 00 9.05E 01 5.26E-00 0.005-01 2.03E 02 4.68E 03 l- Sb 125 1.49E 02 1.63E 00 ~3.49E 01 1.42E-00 0.00E-01 1.31E 02 1.16E 03 Sb 126 9.53E 01 1.95E 00 3.42E 01 5.39E-00 0.00E-01 6.848 01 5.64E 03 i

Co 57 0.00E-01 3.55E 01 5.96E 01 0.00E-01 0.00E-01 0.00E-01 6.63E 02 l

l l

i l

I

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g Reference Use Page 138 of 188 O i ATTACHMENT A

'O .(Page 134 of 184)

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TABLE A.4-3 M '

SITE REIATED DOSE C00MITNENT FACTOR AIT l

\ MREN/HR.PER pCi/ML y CHILD 0~

NUCLIDs BONE LIVER T BODY 'lWYROID KIDNEY LUNG GI-LLI H 3 0.00E-01 1.19E 01 1.19E 01 1.19E 01 1.19E 01 1.19E 01 1.19E 01 C 14 4.45E 04 8.905 03 8.905 03 8.90E 03 8.90E 03 8.90E 03 8.90E 03 NA 24 7.93E 02 7.93E 02 7.93E 02 7.93E 02- 7.93E 02 7.93E 02 7.93E 02'~

P 32 6.495 07 3.04E 06 2.50E 06 0.005-01 0.00E-01 0.00E-01 1.79E 06 CR 51 0.00E-01 0.00E-01 1.92E 00 1.06E 00 2.91E-00 1.94E 00 1.02E 02 MN 54 0.00E-01 3.99E 03 1.06E 03 0.00E-01 1.12E 03 0.00E-01 3.35E 03 MN 56 0.00E-01 1.25E 02 2.81E 01 0.00E-01 1.51E 02 0.00E-01 1.80E 04 FE 55 1.57E 03 8.34E 02 2.59E 02 0.00E-01 0.00E-01 4.72E 02 1.55E 02 FE 59 2.26E 03 3.65E 03 1.82E 03 0.00E-01 0.00E-01 1.06E 03 3.80E 03- 1 CO 58 0.00E-01 1.75E 02 5.37E 02 0.00E-01 0.00E-01 0.00E-01 1.02E 03 00 60 0.00E-01 5.16E 02 1.525 03 0.00E-01 0.00E-01 0.00E-01 2.86E 03 NI 63 7.36E 04 3.94E 03 2.50E 03 0.005-01 0.00E-01 0.00E-01 2.65E 02 NI 65 3.04E 02 2.86E 01 1.67E 01 0.00E-01 0.00E-01 0.00E-01 3.50E 03 CU 64 0.005-01 2.39E 01 1.44E 01 0.00E-01 5.77E 01 0.00E-01 1.12E 03 ;

EN 65 2.23E 04 5.95E 04 3.70E 04 0.00E-01 3.75E 04 0.005-01 1.055 04 EN 69 7.15E 01 1.03E 02 9.54E 00 0.00E-01 6.26E 01 0.00E-01 6.51E 03 BR 83 0.00E-01 0.00E-01 6.64E 01 0.00E-01 0.00E-01 0.00E-01 3.89E-16 BR 84 0.00E-01 0.00E-01 7.695 01 0.00E-01 0.00E-01 0.00E-01 3.89E-16 BR 85 0.00E-01 0.00E-01 3.54E 00 0.00E-01 0.00E-01 0.00E-01 3.895-16 RB 86 0.00E-01 1.09E 05 6.72E 04 0.00E-01 0.00E-01 0.00E-01 7.03E 03 RB 88 0.00E-01 3.10E 02 2.15E 02 0.00E-01 0.00E-01 ~0.00E-01 1.52E 01 RB 09 0.00E-01 1.91E 02 1.70E 02 0.00E-01 0.00E-01 0.00E-01 1.665 00 SR 89 1.08E 05 0.00E-01 3.08E 03 0.00E-01 0.005-01 0.00E-01 4.183 03 SR 90 1.395 06 0.00E-01 3.525 05 0.00E-01 0.00E-01 0.00E-01 1.87E 04 SR 91 1.96E 03 0.00E-01 7.41E 01 0.00E-01 0.00E-01 0.00E-01 4.33E 03 SR 92 7.38E 02 0.00E-01 2.96E 01 0.00E-01 0.00E-01 0.00E-01 1.40E 04 Y 90 3.20E 00 0.00E-01 8.563-01 0.00E-01 0.00E-01 0.00E-01 9.10E 03 Y 91M 2.975-01 0.00E-01 1.085-02 0.005-01 0.00E-01 0.00E-01 5.82E 01 Y 91 4.68E 01 0.00E-01 1.25E-01 0.00E-01 0.00E-01 0.00E-01 6.24E 03 Y 92 2.80E-00 0.00E-01 8.01E-02 0.00E-01 0.005-01 0.00E-01 8.09E 03 Y 93 8.87E-00 0.005-01 2.445-01 0.00E-01 0.005-01 0.00E-01 1.32E 04 ER 95 7.05E 00 1.55E 00 1.385 00 0.00E-01 2.22E 00 0.00E-01 1.62R 03 ER 97 4.25E-00 6.13E-02 3.62E-01 0.00E-01 8.81E-01 0.005-01 9.295 03 NB 95 5.32E 02 2.07E 02 1.48E 02 0.00E-01 1.95E 02 0.005-01 3.83E 05 MO 99 0.00E-01 8.78E 02 2.17E 02 0.005-01 1.87E 03' O.00E-01 7.26E 02 TC 99M 6.46E-01 1.27E-01 2.10E 00 0.00E-01 1.84E 00 6.43E-01 7.20E 01

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\ OFFSITE DOSE CALCULATION MANUAL TABLE A.4-3 (coat'd)

M SITE RBIATED DOSE COBetITMENT FACTOR,AIT

\ MREN/HR PER pC1/ML

,g CHILD 0* -

NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI TC 101 7.48E-01 7.83E-02 9.93E-00 0.00E-01 1.34h 00 4.145-01 2.49E-01 RU 103 4.83E 01 0.00E-01 1.85E 01 0.00E-01 1.21B 02- 0.005-01 1.25E 03

_RU 105 4.26E 00 0.00E-01 1.54E 00 0.00E-01 3.74E *)1 0.00E-01 2.78E 03 RU 106 7.72E 07 0.00E-01 9.64E 01 0.00E-01 1.04E 03 0.00E-01 1.20E 04 AG 110M 3.23E 01 2.18E 01 1.74E 01 0.00E-01 4.06E 01 0.00E-01 2.60E 03 TE 125M 4.25E 03 1.15E 03 5.67E 02 1.19E 03 0.00E-01 0.00E-01 4.10E 03 TE 127M 1.08E 04 2.90E 03 1.28E 03 2.58E 03 3.07E 04 0.00E-01 8.725 03 TE 127 1.76E 02 4.73E 01 3.77E 01 1.22E 02 5.00E 02 0.00E-01 6.86E 03 TE 129M 1.82E 04 5.07E 03 1.70E 03 5.85E 03 5.33E 04 0.00E-01 2.21E 04 TE 129 5.00E 01 1.39E 01 1.19E 01 3.56E 01 1.46E 02 0.00E-01 3.11E 03 TE 131M 2.68E 03 9.28E 02 9.88E 02 1.91E 03 8.98E 03 0.00E-01 3.77E 04 TE 131 3.09E 01 9.43B 00 9.21E 00 2.37E 01 9.36E 01 0.00E-01 1.63E 02 TE 132 3.77E 03 1.67E 03 2.01E 03 2.43E 03 1.55E 04 0.00E-01 1.68E 04 I 130 2.04E 02 4.13E 02 2.135 02 4.55E 04 6.17E 02 0.00E-01 1.93E 02 I 131 1.20E 03 1.21E 03 6.88E 02 4.00E 05 1.99E 03 0.00E-01 1.08E 02 I 332 5.60E 01 1.03E 02 4.73E 01 4.775 03 1.57E 02 0.00E-01 1.21E 02 I 133 4 1/E 02 5.12E 02 1.94E 02 9.51E 04 8.53E 02 0.00E-01 2.06E 02 I 134 2.'shE 01 5.44E 01 2.50E 01 1.25E 03 8.32E 01 0.00E-01 3.61E 01 I 135 1.22E 02 2.205 02 1.04E 02 1.95E 04 3.385 02 0.005-01 1.68E 02 l CO 314 3.82E 05 6.26B 05 1.32E 05 0.00E-01 1.94E 05 6.973 04 3.38E 03 CS 136 3.83E 04 1.05E 05 6.82E 04 0.00E-01 5.61E 04 8.37E 03 3.70E 03 1 CS 137 5.33E 05 5.11E 05 7.54E 04 0.00E-01 1.66E 05 5.99E 04 3.20E 03 C8 138 3.72E 02 5.17E 02 3.28E 02 0.00E-01 3.64E 02 3.92E 01 2.38E 02 RA 139 2.54E 01 1.35E-02 7.35E-00 0.005-01 1.18E-01 7.97E-02 1.47E 03 RA 140 5.09E 03 4.46E 00 '2.97E 02 0.00E-01 1.45E 00 2.66E 00 2.58E 03 BA 141 1.23E 01 6.86E-03 3.99E-00 0.00E-01 5.94E-02 4.035-01 6.99E 00 RA 142 5.36E 00 3.85E-03 2.99E-00 0.00E-01 3.12E-02 2.27E-02 6.99E-02 LA 140 7.86E-00 2.75E-01 p.26E-01 0.00E-01 0.00E-01 0.00E-01 7.66E 03 LA 142 4.08E-01 1.30E-02 4.0!M-02 0.005-01 0.00E-01 0.00E-01 2.58E 03 CE 141 2.34E 00 1.17E 00 - 1.733-00 0.005-01 5.11E-00 0.00E-01 1.46E 03 CE 143 4.12E-00 2.23E 02 3.245-01 0.00E-01 9.37E-01 0.00E-01 3.27E 03 CE 144 1.23E 02 3.84E 01 6.54E 00 0.00E-01 2.13E 01 0.00E-01 1.005 04 PR 143 3.06E 00 9.18E-01 1.52E-00 0.00E-01 4.97E-00 0.00E-01 3.30E 03 PR 144 1.00E-01 3.10E-03 5.05E-03 0.00E-01 1.64E-02 0.00E-01 6.68E 00 ND 147 2.17E 00 1.76E 00 1.36E-00 0.00E-01 9.65E-00 0.00E-01 2.79E 03 W 187 4.30E 02 2.55E 02 1.14E 02 0.00E-01 0.00E-01 0.CSE-01 3.58E 04 m ,

---.-t * - ~ + ' - ----------'--&

-H f Revision: 0 OFFSITE DOSE CALCULATION MANUAL AP 078-003 l q Reference Use Page 140 of 188 1O ATTACHMENT A C3 (Page 136 of 184)

OFFSITE DOSE CALCULATION MANUAL ,

\

~~

TABLE A.4-3 (cont'd) !

h) '

SITE REIATED DOSE C089tITMENT FACTOR AIT '

\ MREN/HR PER pC1/ML J CHILD U-NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI NP 239 3.47E-00 2.495-02 1.75E-01 0.00E-01 7.19E-01 0.00E-01 1.84E 03 Sb 124 6.54E 02 8.49E 00 2.298 02 1.44E 00 0.00E-01 3.63E 02 4.09E 03 Sb 125 4.22E 02 3.25E 00 8.84E 01 3.91E-On 0.00E-01 2.35E 02 1.01E 03 Sb 126 2.598 02 3.97E 00 9.31E 01 1.52E 00 0.005-01 1.24E 02 5.23E 03 Co 57 0.00E-01 4.81E 01 9.73E 01 0.00E-01 0.00E-01 0.00E-01 3.94E 02 I l

i l

l l

I l

i

(.

f l

l i

l__________ _ _ _ _ _ _ _ _ ---

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Reference Use Page 141 of 188 m

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ATTACHMENT A ,

O (Page 137 of 184)

M [

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TABLE A.4-4 M SITE RE1ATED DOSE ColetI'INENT FACTOR AIT

\ MREM /HR PER pCI/ML

,g INFANT t

NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI H 3 0.005-01 1.16E 01 1.16E 01 1.16E 01 1.16E 01 1.16E 01 1.16E 01 C 14 8.92E 02 1.90E 02 1.90E 02 1.90E 02 1.90E 02 1.90E 02 1.90E 02 NA 24 3.80E 02 3.80E 02 - 3.80E 02 3.80E 02 3.80E 02 3.80E 02 3.80E 02 P 32 6.40E 04 3.76E 03 2.4BE 03 0.00E-01 0.00E-01 0.00E 8.65E 02 CR 51 0.00E-01 0.00E-01 5.30E-01 3.46E-01 7.56E-02 6.73E-01 1.55E 01 MN 54 0.00E-01 7.49E 02 1.70E 02 0.00E-01 1.66E 02 0.00E-01 2.75E 02 '

MN 56 0.00E-01 3.08E 01 5.30E 00 0.00E-01 2.645 01 0. 0 W- 01 2.00E 03 FE 55 5.235 02 3.38E 02 9.03E 01 0.005-01 0.003-01 1.65h 02 4.29E 01 FE 59 1.16E 03 2.02E 03- 7.98E 02 0.00E-01 0.00E-01 5.98E 02 9.67E 02 l j

CO 58 0.00E-01 1.35E 02 3.38E 02 0.00E-01 0.00E-01 0.00E-01 3.37E 02 ;

CO 60 0.00E-01 4.06E 02 9.59E 02 0.00E-01 0.00E-01 0.00E-01 9.G7E 02 NI 63 2.39E 04 1.47E 03 8.28E 02 0.00E-01 0.00E-01 0.00E-01 7.34E 01 NI 65 1.77E 02 2.00E 01 9.10E 00 0.00E-01 0.00E-01 0.00E-01 1.52E 03 CU 64 0.00E-01 2.29E 01 1.06E 01 0.00E-01 3.87E 01 0.00E-01 4.70E 02 ZN 65 6.925 02 2.37E 03 1.09E 03 0.00E-01 1.15E 03 0.005-01 2.01E 03 EN 69 3.51E 00 6.32E 00 4.70E-01 0.00E-01 2.63E 00 0.00E-01 5.15E 02 BR 83 0.00E-01 0.00E-01 1.37E 01 0.00E-01 0.00E-01 0.00E-01 3.76E-17 3R 84 0.00E-01 0.00E-01 1.44E 01 0.00E-01 0.00E-01 0.00E-01 3.76E-17 BR 85 0.00E-01 0.00E-01 7.30E-01 0.00E-01 0.00E-01 0.005-01 3.76E-17 RE 86 0.00E-01 6.40E 03 3.16E 03 0.00E-01 0.00E-01 0.00E-01 1.64E 02 RB 88 0.00E-01 1.87E 01 1.03E 01 0.00E-01 0.00E-01 0.00E-01 1.82E 01 RB 09 0.00E-01 1.00E 01 7.415 00 0.00E-01 0.00E-01 0.00E-01 3.66E 00 SR 89 9.44E 04 0.00E-01 2.71E 03 0.00E-01 0.00E-01 0.00E-01 1.94E 03 SR 90 6.96E 05 0.00E-01 1.77E 05 0.00E-01 0.00E-01 0.00E-01 8.695 03 SR 91 1.88E 03 0.00E-01 6.81E 00 0.00E-01 0.00E-01 0.00E-01 2.23E 03 SR 92 7.22E 02 0.00E-01 2.68E 01 0.00E-01 0.00E-01 0.00E-01 7.79E 03 Y 90 3.27E 00 0.00E-01 8.775-02 0.005-01 0.00E-01 0.003-01 4.51E 03 i 1

Y 91M 3.053-02 0.00E-01 1.04E-03 0.005-01 0.005-01 0.00E-01 1.02E 02 Y 91 4.255 01 0.00E-01 1.135 00 0.00E-01 0.005-01 0.00E-01 3.05E 03 Y 92 2.88E-01 0.005-01 8.09E 03 0.00E-01 0.00E-01 0.00E-01 5.49E 03 Y 93 9.145-01 0.005-01 2.495-02 0.00E-01 0.00E-01 0.00E-01 7.22E 03 ER 95 7.75E 00 1.89E 00 1.34E 00 0.00E-01 2.04E 00 0.00E-01 9.41E 02 ZR 97 5.57E-;1 9.565-02 4.36E-02 0.00E-01 9.63E-02 0.00E-01 6.095 03 NB 95 1.58E 00 6.51E-01 3.76E-01 0.00E-01 4.66E-01 0.00E-01 5.49E 02 NO 99 0.005-01 1.28E 03 2.49E 02 0.00E-01 1.91E 03 0.00E-01 4.21E 02 TC 99M 7.225-02 1.49E-01 1.92E 00 0.00E-01 1.60E 00 7.79E-02 4.33E 01

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Rafarcnce Usa Page 142 of 188 m

O ATTACHMENT A O (Page 138 of 184)

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TABLE A.4-4 (oont'd)

A)

SITE RELATED DOSE COPG(ITMENT FACTOR AIT g MREN/HR PER pCI/ML j INFANT NUCLIDE BONE LIVER T BODY THYROID KID 8tEY LUNG GI-LLI TC 101 8.54E-02 1.08E-01 1.06E 00 0.008-01 1.28E 00 5.87E-02 1.83E 01 RU 103 5.57E 01 0.00E-01 1.86E 01 0.00E-01 1.16R 02 0.00E-01 6.77E 02 RU 105 5.12E 00- 0.00E-01 1.72E 00 0.00E-01 3.76E 01 '0.00E-01 2.04E 03 RU 106 9.07E 02 0.00E-01 1.13E 02 0.00E-01 1.075 03 0.00E-01 6.88E 03 AG 110M 3.75E 01 2.73E 01 1.81E 01 0.00E-01 3.91E 01 0.00E-01 1.425 03 TB 125M 8.77E 02 2.93E 02 1.198 02 2.95E 02 0.00E-01 0.00E-01 4.18E 02 TE 127M 2.20E 03 7.30E 02 2.66E 02 6.36E 02 5.42E 03 0.00E-01 8.08E 02 TE 127 3.76E 01 1.26E 01 8.09E 00 3.06E 01 9.18E 01 0.005-01 7.90E 02 TE 129M 3.765 03 1.295 03 5.79E 02 1.44E 03 9.41E 03 0.00E-01 2.2SE 03 TI 129 1.07E 01 3.68E 00 2.49E 00 8.95E 00 2.66E 01 0.00E-01 8.54E 02 TB 131M 5.72E 02 2.30E 02 1.90E 02 4.66E 02 1.58E 03 0.00E-01 3.87E 03 TE 131 6.62E 00 2.45E 00 1.86E 00 5.91E 00 1.69E 01 0.00E-01 2.67E 02 TE 132 7.825 02 3.87E 02 3.62E 02 5.72E 02 2.42E 03 0.00E-01 1.435 03 I 130 2.26E 02 4.97E 02 1.998 02 5.57E 04 5.45E 02 0.00E-01' 1.06E 02 I 131 1.35E 03 1.59E 03 7.005 02 5.23E 05 1.86E 03 0.00E-01 5.68E 01 I 132 6.24E 01 1.27E 02 4.51E 01 5.94E 03 1.41E 02 0.005-01 1.03E 02 I 133 4.70E 02 6.85E 02 2.01E 02 1.25E 05 8.05E 02 0.005-01 1.16E 02 1 134 3.27E 01 6.70E 01 2.38E 01 1.56E 03 7.49E 01 0.00E-01 6.92E 01 I 135 1.37E 02 2.728 02 9.93E 01 2.44E 04 3.04E 02 0.00E-01 9.86E 01 CS 134 1.42E 04 2.64E 04 2.67E 03 0.00E-01 6.81E 03 2.42E 03 7.195 01 C8 136 1.73E 03 5.08E 03 1.90E 03 0.00E-01 2.02E 03 4.14E 02 7.71E 01 CS 137. 1.96E 04 2.30E 04 1.63E 03 0.005-01 6.175 03 2.505 03 7.19E 01 CS 138 1.81E 01 2.948 01 1.43E 01 0.00E-01 1.47E 01 2.29E 00 4.70E 01 BA 139 3.31E 01 2.20E-02 9.59E-01 0.00E-01 1.325-02 1.33E-02 2.10E 03 BA 140 6.43E 03 6.43E 00 3.31E 02 0.00E-01 1.53E 00 3.95E 00 1.58E 03 RA 141 1.60E 01 1.09E-02 5.04E-01 0.00E-01 6.58E-03 6.66E-03 1.95E 02 EA 142 6.92E 00 5.76E-03 3.41E-01 0.00E-01 3.31E-03 3.40E-03 2.06E 01 LA 140 7.94E-01 3.13E-01 8.05E-02 0.00E-01 0.00E-01 0.00E-01 3.68E 03 LA 142 4.14E-02 1.52E-02 3.64E-03 0.00E-01 0.00E-01 0.00E-01 2.58E 03 CE 141 2.96E 00 1.81E 00 2.135-01 0.00E-01 5.57E-01 0.00E-01 9.33E 02 CE 143 5.575-01 3.69E 02 4.21E-02 0.00E-01 1.08E-01 0.00E-01 2.16E 03 CE 144 1.12E 02 4.595 01 6.28E 00 0.005-01 1.85E 01 0.00E-01 6.43E 03 PR 143 3.06E 00 1.14E 00 1.52E-01 0.003-01 4.25E-01 0.005-01 1.61E 03 PR 144 1.03E-02 3.99E-03 5.193-04 0.00E-01 1.44E-03 0.00E-01 1.85E 02 ND 147 2.08E 00 2.14E 00 1.31E-01 0.00E-01 8.245-01 0.00E-01 1.35E 03 W -187 3.40E 01 2.365 01 8.16E 00 0.00E-01 0.005-01 0.00E-01 1.39E 03

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

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m Reference Use Page 143 of 188 Cf ATTACHMENT A O

(Page 139 of 184)

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!N OFFSITE DOSE CALCULATION MANUAL

~~

TABLE A.4-4 (coat'd)

N SITE RELATED DOSE C000lITMENT FACTOR AIT

\ ' MREN/HR PER pCI/ML A INFANT tJ' NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUt0G GI-LLI NP 239 4.188-01 3.74E-02 2.118-02 0.00E-01 7.45E-02 0.00E-01 1.08E 03 Sb 124 8.05E 02 1.19E 01 2.49E 02 2.14E 00 0.00E-01 5.04E 02 2.48E 03 Bb 125 4.63E 02 4.48E 00 9.525 01 5.798-00 0 . 0 0E 2.90E 02 6.17E 02 Sb 126 3.03E P2 5.94E 00 1.09E 02 2.33E 00 0.00E-01 1.91E 02 3.14E 03 Co 57 0.00E-01 4.33E 01 7.03E 01 0.00E-01 0.00E-01 0.00E-01 1.475 02

f Revision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 Reference Use Page 144 of 188 iU ATTACHMENT A O (Page 140 of 184)

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TABLE A.5-1 N.

\

INHALATION DOSE PARAMETER FOR THE CHILD, PI -

.D MREM /YR per pCi/MS r

H-3 1.12E 03 RU-103 6.62E 05 C-14 3.59E 04 RU-105 9.95E 04 NA-24 1.61E 04 RU-106 1.43E 07 j P-32 2.60E 06 AG-110M 5.48E 06 l CR-51 1.70E 04 TE-125M 4.77E 05

^

l' MN-54 1.58E 06 TE-127M 1.48E 06 l MN-56 1.23B 05 TE-127 5.62E 04 FE-55 1.11E 05 TE-129M 1.76E 06 FE-59 1.27E 06 TB-129 2.55E 04 CO-58 1.11E 06 TE-131M 3.08E 05 l CO-60 7.07E 06 TE-131 2.05E 03 NI-63 l 8.21E 05 TE-132 3.77E 05 !

NI-65 8.40E 04 I-130 1.85E 06 )

l CU-64 3.67E 04 I-131 1.62B 07 ZN-65 9.95E 05 I-132 1.94E 05 ZN-69 1.02E 04 I-133 3.85E 06 l BR-83 4.74E 02 I-134 5.07E 04 BR-84 5.48E 02 I-135 7.92E 05 BR-85, 2.53E 01 CS-134 1.01E 06 RB-86 1.98E 05 CS-136 1.71E 05 RB 88 5.62E 02 CS-137 9.07E 05 RB-89 3.45E 02 CS-138 8.40E 02 SR-89 2.16E 06 BA-139 5.77E 04 SR-90 1.01E 08 BA-140 1.74E 06 SR-91 1.74E 05 BA-141 2.92E 03 SR-92 2.42E 05 BA-142 1.64E 03 l Y-90 2.68E 05 LA-140 2.26E 05 l Y-91M 2.81E 03 LA-142 7.59E 04 I Y-92 2.39E 05 CE-141 5.44E 05 Y-93 3.89E 05 CE-143 1.27E 05 ZR-95 2.23E 06 .PR-143 4.33E 05 ZR-97 3.51E 05 PR-144 1.57E 03 NB-95 6.14E 05 ND-147 3.28E 05 MO-99 1.35E 05 W-187 9.10E 04 TC-99M 4.81E 03 NP-239 6.40E 04 TC-101 5.85E 02 i

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ATTACHMENT A O (Page 141 of 184)

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TABLE A.5 2 M INNA1ATION PATHNAY FACTOR

\ NREM/YR PER pCI/M' J ADULT (RI FACTORS)

(T' NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI H 3 0.005 01 1.26E 03 1.265 03 1.26E 03 1.26E 03 1.26E 03 1.26E 03 C 14 1.82E 04 3.41E 03 3.41E 03 3.41E 03 3.41E 03 3.41E 03 3.41E 03 NA 24 1.02E 04 1.02E 04 1.02E 04 1.02E 04 1.025 04 1.02E 04 1.02E 04 P 32 1.32E 06 7.71E 04 5.01E 04 0.00E-01 0.00E-01 0.005-01 8.64E 04 CR 51 0.00E 01 0.00E 01 1.00E 02 5.95E 01 2.28E 01 1.44E 04 3.32E 03 MN 54 0.00E 01 3.96E 04 6.30E 03 0.00E-01 9.84E 03 1.40E 06 7.74E 04 MN 56 0.005 01 1.24E 00' 1.83E-00 0.005-01 1.30E 00 9.44E 03 2.02E 04 FE 55 2.46E 04 1.70E 04 3.94E 03 0.00E-01 0.00E-01 7.21E 04 6.03E 03 FI 59 1.18E 04 2.78E 04 1.06E 04 0.00E-01 0.00E-01 1.02E 06- 1.88E 05 e CO 58 0.00E 01 1.58E 03 2.07E 03 0.00E-01 0.005-01 9.28E 05 1.06E 05 00 60 0.00E 01 1.15E 04 1.48E 04 0.00E-01 0.00E-01 5.97E 06 2.85E 05 NI 63 4.32E 05 3.14E 04 1.45E 04 0.00E-01 0.00E-01 1.78E 05 1.34E 04 NI 65 1.54E 00 2.10E-01 9.12E-02 0.00E-01 0.00E-01 5.60E 03 1.23E 04 CU 64 0.005 01 1.46E 00 6.15E-01 0.00E-01 4.62E 00 6.785 03 4.90E 04 KN 65 3.24E 04 1.03E 05 4.66E 04 0.00E-01 6.90E 04 8.64E 05 5.34E 04 EN 69 3.38E-02 6.513-02 4.52E-03 0.00E-01 4.22E-02 9.20E 02- 1.63E 01 BR 83 0.00E-01 0.00E-01 2.41E 02 0.00E-01 0.00E-01 0.00E-01 2.32E 02 BR 84 0.00E-01 0.00E-01 3.13E 02 0.00E-01 0.00E-01 0.00E-01 1.64E-03 BR 85 0.00E-01 0.00E-01 1.285 01 0.002-01 0.005-01 0.00E-01 8.005-15 RB 86 0.00E-01 1.35E 05 5.90E 04 0.005-01 0.00E-01 0.00E-01 1.66E 04 RB 88 0.00E-01 3.87E 02 1.93E 02 0.00E-01 0.00E-01 0.00E-01 3.34E-09 RB 89 0.005-01 2.56E 02 1.705 02 0.00E-01 0.00E-01 0.005-01 9.285-12 SR 89 3.04E 05 0.00E-01 8.72E 03 0.00E-01 0.00E-01 1.40E 06 3.50E 05 SR 90 9.92E 07 0.00E-01 6.10E 06 0.00E-01 0.00E-01 9.60E 06 7.22E 05 SR 91 6.19E 01 0.00E-01 2.50E 00 0.00E-01 0.00E-01 3.65E 04 1.91E 05 SR 92 6.74E 00 0.00E-01 2.91E-01 0.005-01 0.00E-01 1.65E 04 4.30E 04 Y 90 2.09E 03 0.005-01 5.61E 01 0.00E-01 0.005-01 1.70E 05 5.065 05 Y SIN 2.613-01 0.00E-01 1.02E-02 0.00E-01 0.00E-01 1.92E 03 1.33E 00 Y 91 4.625 05 0.00E-01 1.24E 04 0.00E-01 0.00E-01 1.70E 06 3.85E 05 Y 92 1.03E 01 0.00E-01 3.02E-01 0.00E-01 0.005-01 1.57E 04 7.35E 04 Y 93 9.44E 01 0.00E-01 2.613 00 0.00E-01 0.00E-01 4.85E 04 4.22E 05 ZR 95- 1.07E 05 3.44E 04 2.33E 04 0.00E-01 5.42E 04 1.77E 06 1.50E 05 ER 97 9.68E 01 1.96E 01 9.04E 00 0.00E-01 2.97E 01 7.87E 04 5.235 05 NB 95 1.41E 04 7.82E 03 4.21E 03 0.00E-01 7.74E 03 5.05E 05 1.04E 05 MO 99 0.00E-01 1.21E 02 2.30E 01 0.005-01 2.91E 02 9.12E 04 2.48E 05 TC 99M 1.03E-03 2.91E-03 3.70E-02 0.00E-01 4.42E-02 7.64E 02 4.16E 03 l

F4 3 Revision: 0 D 0FFSITE DOSE CALCULATION MANUAL AP 07B-003 U

til Reference Use Page 146 of 188 O

ATTACHMENT A O (Page 142 of 184)

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l TABLE A.5-2 (c oat'd) {

h) INHALATION PATHNAY FACTOR .

\ MREM /YR PER pCI/M'

,g- ADULT (RI FACTORS) 0*

NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI j TC 101 4.18E-05 6.02E-05 5.90E-04 0.00E-01 1.08E-03 3.99E 02 1.09E-11 RU 103 1.53E 03 0.00E-01 6.58E 02 0.00E-01 5.83E 03 5.05E 05 1.10E 05 RU 105 7.90E-01 0.00E-01 -3.11E-01 0.00E-01 1.02E 00 1.10E 04 '4.82E 04 RU 106 6.91E 04 0.00E-01 8.72E 03 0.00E-01 1.34E 05 9.36E 06 9.12E 05 AG 110M 1.04E 04 1.00E 04 5.94E 03 0.00E-01 1.97E 04 4.63E 06 3.02E 05 TE 125M 3.42E 03 1.58E 03 4.67E 02 1.05E 03 1.24E 04 3.14E 05 7.06E 04 TE 127M 1.26E 04 5.77E 03 1.573 03 3.29E 03 4.58E 04 9.60E 05 1.50E 05 TE 127 1.40E 00 6.425-01 3.10E-01 1.06E 00 5.10E 00 6.51E 03 5.74E 04 TR 129M 9.76E 03 4.67E 03 1.58E 03 3.44E 03 3.66E 04 1.165 06 3.83E 05 TE 129 4.98E-02 2.39E-02 1.24E-02 3.90E-02 1.87E-01 1.94E 03 1.57E 02 TB 131M 6.99E 01 4.36E 01 2.90E 01 5.50E 01 3.09E 02 1.46E 05 S.56E 05 TE 131 1.11E-02 5.95E-03 3.59E-03 9.365-02 4.375-02 1.39E-03 1.845 01 TE 132 2.60E 02 2.15E 02 1.62E 02 1.90E 02 1.46E 03 2.88E 05 5.10E 05 I 130 4.585 03 1.34E 04 5.28E 03 1.14E 06 2.09E 04 0.00E-01 7.69E 05 I 131 2.52E 04 3.58E 04 2.05E 04 1.19E 07 6.13E 04 0.00E-01 6.28E 03

)

I 132 1.16E 03 3.26E 03 1.165 03 1.14E 05 5.18E 03 0.00E-01 4.06E 02 I 133 8.64E 03 1.48E 04 4.52E 03 2.15E 06 2.58E 04

)

0.005-01 8.88E 03 !

I 134 6.44E 02 1.73E 03 6.15E 02 2.98E 04 2.75E 03 0.00E-01 1.01E 00 I 135 2.68E 03 6.98E 03 2.57E 03 4.48E 05 1.11E 04 0.00E-01 5.25E 03 I CS 134 3.73E 05 8.488 05 7.28E 05 0.00E-01 2.878 05 9.76E 04 1.04E 04 i CS 136. 3.905 04 1.46E 05 1.10E 05 0.00E-01 8.56E 04 1.20E 04 1.17E 04 !

C8 137 4.78E 05 6.21E 05 4.205 05 0.00E-01 2.22E 05 7.52E 04 8.40E 03 C8 138 3.31E 02 6.21E 02 3.24E 02 0.00E-01 4.805 02 4.86E 01 1.86E-03 RA 139 9.36E-01 6.66E-04 2.74E-02 0.00E-01 6.22E-04 3.76E 03 8.96E 02 BA 140 3.90E 04 4.90E 01 2.57B 03 0.00E-01 1.67E 01 1.27E 06 2.18E 05 BA 141 1.00E-01 7.53E-05 3.368-03 0.00E-01 7.00E-05 1.945 03 1.165-07 BA 142 2.63E-02 2.70E-05 1.66E-03 0.00E-01 2.29E-05 1.19E 03 1.57E-16 LA 140 3.44E 02 1.74E 02 4.585 01 0.00E-01 0.00E-01 1.36E 05 4.58E 05 LA 142 6.83E-01 3.10E-01 7.72E-02 0.00E-01 0.00E-01 6.33E 03 2.11E 03 CE 141 1.99E 04 1.35E 04 1.53E 03 0.00E-01 6.26E 03 3.625 05 1.20E 05 CE 143 1.06E 02 1.385 02 1.53E 01 0.00E-01 6.00E 01 7.98E 04 2.26E 05 CE 144 3.43E 06 1.43E 06 1.84E 05 0.00E-01 8.48E 05 7.78E 06 8.16E 05 PR 143 9.36E 03 3.75E 03 4.64E 02 0.00E-01 2.16E 03 2.81E 05 2.005 05 PR 144 3.10E-02 1.25E-02 1.53E-03 0.00E-01 7.05E-03 1.02E 03 2.15E-08 ND 147 5.273 03 6.10E 03 3.65E 02 0.00E-01 3.56E 03 2.21E 05 1.735 05 W 107 8.485 00 7.08E 00 2.48E 00 0.00E-01 0.00E-01 2.90E 04 1.55E 05 NP 239 2.30E 02 2.26E 01 1.24E 01 0.90E-01 7.00E 01 3.76E 04 1.19E 05

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'O (Page 143 of 184)

\

T& ELE A.5-3 M INHALATION PATHWAY FAC'IM

\ MREM /YR PER pCI/M' ,

D TEEN (RI FACTORS)

D' l NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI H 3 0.005-01 1.27E 03 ~ 1.27E 03 1.27E 03 1.27E 03 1.27E 03 1.27E 03 l C 14 2.60E 04 4.87B 03 4.87E 03 4.87E 03 4.87E 03 4.87E 03 4.87E 03 I NA 24 1.38E 04 1.38E 04 -1.38E 04 1.38E 04 1.38E 04 1.38E 04 1.38E 04 P 32 1.895 06 1.10E 05 7.165 04 0.00E-01 0.00E-01 0.00E-01 9.283 04 CR 51 0.00E-01 0.00E-01 1.35E 02 7.50E 01 3.07E 01 2.10E 04 3.00E 03 MN 54 0.005-01 5.11E 04 8.40E 03 0.00E-01 1.27E 04 1.98E 06 6.68E 04 Def 56 0.00E-01 1.70E 00 2.52E-01 0.00E-01 .1.795 00 1.53E 04 5.74E 04 FE 55 3.34E 04 2.38E 04 5.54E 03 0.00E-01 0.00E-01 1.24E 05 6.39E 03 FE 59 1.59E 04 3.70E 04 1.43E 04 0.00E-01 0.00E-01 1.53E 06 1.78E 05 00 58 0.00E-01 2.07E 03 2.78E 03 0.00E-01 0.00E-01 1.348 06 9.52E 04 CO 60 0.005-01 1.51E 04 1.90E 04 0.00E-01 0.00E-01 8.725 06 2.59E 05 NI 63 5.80E 05 4.34E 04 1.90E 04 0.00E-01 0.00E-01 3.075 05 1.42E 04 NI 65 2.185 00 2.93E-01 1.27E-01 0.00E-01 0.003-01 9.36E 03 3.67E 04 CU 64 0.00E-01 2.03E 00 8.48E-01 0.005-01 6.41E 00 1.11E 04 6.14E 04 IN 65 3.86E 04 1.34E 05 6.245 04 0.00E-01 8.64E 04 1.24E 06 4.66E 04 EN 69 4.83E-02 9.20E-02 6.465-03 0.00E-01 6.025-02 1.58E 03 2.855 02 BR 83 0.00E-01 0.00E-01 3.44E 02 0.00E-01 0.00E-01 0.005-01 0.005-15 BR 84 0.00E-01 0.00E-01 4.33E 02 0.00E-01 0.00E-01 0.00E-01 8.00E-15 BR 85 0.00E-01 0.00E-01 1.83E 01 0.00E-01' O.00E-01 0.00E-01 8.00E-15 RB 86 0.00E-01 1.90E 05 8.40E 04 0.00E-01 0.00E-01 0.005-01 1.77E 04 RB 88 0.00E-01 5.46E 02 2.72E 02 0.00E-01 0.00E-01 0.00E-01 2.923-05 RB 89 0.00E-01 3.52E 02 2.33E 02 0.00E-01 0.005-01 0.00E-01 3.38E-07 I SR 89 4.34E 05 0.00E-01 1.25E 04 0.00E-01 0.00E-01 3.42E 06 3.71E 05 i SR 90 1.08E 08 0.00E-01 6.68E 06 0.00E-01 0.005-01 1.65E 07 7.65E 05 SR 91 8.808 01 0.005-01 3.51E 00 0.00E-01 0.00E-01 6.078 04 2.59E 05 SR 92 9.52E 00 0.00E-01 4.06E-01 0.00E-01 0.00E-01 2.74E 04 1.195 05 Y 90 2.983 03 0.005-01 8.005 01 0.005-01 0.005-01 2.93E 05 5.59E 05 I Y 91M 3.70E-01 0.00E-01 1.425-02 0.005-01 0.00E-01 3.20E 03 3.02E 01 Y 91 6.61E 05 0.00E-01 1.77E 04 0.005-01 0.00E-01 2.94E 06 4.09E 05 Y 92 1.475 01 0.00E-01 4.295-01 0.00E-01 0.00E-01 2.68E 04 1.655 05 Y 93 1.35E 02 0.00E-01 3.72E 00 0.00E-01 0.00E-01 8.32E 04 5.795 05 ER 95 1.46E 05 4.58E 04 3.15E 04 0.00E-01 6.74E 04 2.69E 06 1.495 05 ER 97 1.38E 02 2.72E 01 1.265 01 0.00E-01 4.12E 01 1.30E 05 6.30E 05 NE 95 1.86E 04 1.03E 04 5.665 03 0.00E-01 1.00E 04 7.51E 05 9.68E 04 MO 99 0.00E-01 1.69E 02 3.22E 01 0.00E-01 4.11E 02 1.54E 05 2.69I 05 TC 99M 1.38E-03 3.86E-03 4.99E-02 0.00E-01 5.765-02 1.15E 03 6.13E 03

H 2 Revision: 0 3 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 01 g Reference Use Page 148 of 188 0

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~~

TABLE A.5-3 (oont'd)

M '

INHALATION PATHWAY FACFOR 8

\ MREN/YR PER HCI/M

,f) TEEN (RI FACTORS)

D' NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI TC 101 5.92E-05 8.40E-05 6.24E-04 0.00E-01 1.52E-03 6.67E 02 8.72E-07 !

RU 103 2.10E 03 0.00E-01 8.96E 02 0.00E-01 7.43E 03 7.83E 05 1.09E 05 RU 105 1.12E 00 0.00E-01 4.34E-01 0.00E-01 1.41E 00 1.82E 04 9.04E 04 1 RU 106 9.84E 04 0.00E-01 1.24E 04 0.00E-01 1.90E 05 1.61E 07 9.60M 05 AG 110M 1.38E 04 1.31E 04 7.99E 03 0.00E-01 2.50E 04 6.75E 06 2.73E 05 !

TE 125M 4.88E 03 2.24E 03 6.74E 02 1.40E 03 0.00E-01 5.36E 05 7.50E 04 I TE 127M 1.805 04 8.16E 03 2.18E 03 4.38E 03 6.54E 04 1.66E 06 1.59E 05 TE 127 2.01E 00 9.12E-01 4.42E-01 1.42E 00 7.28E 00 1.12E 04 8.08E 01 TE 129M 1.39E 04 6.58E 03 2.25E 03 4.58E 03 5.19E 04 1.90E 06 4.05E 05 TE 129 7.10E-02 3.38E-02 1.76E-02 5.18E-02 2.66E-01 3.30E 03 1.62E 03 TE 131M 9.84E 01 6.01E 01 4.20E 01 7.25E 01 4.39E 02 2.38E 05 6.21E 05 !

TR 131 1.58E-02 8.32E-03 5.04E-03 1.24E-02 6.18E-02 2.34E 03 1.51E 01 TE 132 3.60E 02 2.90E 02 2.19E 02 2.465 02 1.95E 03 4.49E 05 4.635 05 I 130 6.24E 03 1.79E 04 7.17E 03 1.49E 06 2.75E 04 0.00E-01 9.125 03 I 131 3.54E 04 4.91E 04 2.64E 04 1.46E 07 8.40E 04 0.005-01 6.49E 03 I 132 1.59E 03 4.38E 03 1.58E 03 1.51E 05 6.92E 03 0.00E-01 1.27E 03 I 133 1.22E 04 2.05E 04 6.22E 03 2.92E 06 3.59E 04 0.00E-01 1.03E 04 I 134 8.88E 02 2.32E 03 8.40E 02 3.95E 04 3.66E 03 0.00E-01 2.04E 01 I 135 3.70E 03 9.44E 03 3.49E 03 6.21E 05 1.49E 04 0.00E-01 6.95E 03 CS 134 5.02E 05 1.13E 06 5.49E 05 0.00E-01 3.75E 05 1.46E 05 9.76E 03 CS 136 5.15E 04 1.94E 05 1.37E 05 0.00E-01 1.10E 05 1.78E 04 1.09E 04 CS 137 6.70E 05 8.48E 05 3.11E 05 0.00E-01 3.04E 05 1.21E 05 8.48E 03 CS 138 4.665 02 8.56E 02 4.465 02 0.00E-01 6.62E 02 7.87E 01 2.70E-01 RA 139 1.34E 00 9.44E-04 3.90E-02 0.00E-01 8.88E-04 6.46E 03 6.45E 03 BA 140 5.47E 04 6.70E 01 3.52E 03 0.00E-01 2.28E 01 2.03E 06 2.29E 05 BA 141 1.42E-01 1.06E-04 4.74E-03 0.00E-01 9.04E-05 3.29B 03 7.46E-04 RA 142 3.70E-02 3.70E-05 2.27E-03 0.00E-01 3.14E-05 1.915 03 4.79E-10 LA 140 4.79E 02 2.36E 02 6.26E 01 0.00E-01 0.00E-01 2.14E 05 4.87E 05 LA 142 9.60E-01 4.25E-01 1.06E-01 0.005-01 0.00E-01 1.02E 04 1.20E 04 CE 141 2.843 04 1.90E 04 2.17E 03 0.00E-01 8.88E 03 6.14E 05 1.26E 05 CE 143 2.66E 02 1.94E 02 2.165 01 0.00E-01 8.64E 01 1.30E 05 2.55E 05 CE 144 4.89E 06 2.02E 06 2.62E 05 0.00E-01 1.21E 06 1.34E 07 8.64E 05 PR 143 1.34E 04 5.31E 03 6.625 02 0.00E-01 3.09E 03 4.835 05 2.14E 05 PR 144 4.30E-02 1.76E-02 2.18E-03 0.00E-01 1.01E-02 1.75E 03 2.35E-04 ND 147 7.86E 03 8.56E 03 5.13E 02 0.005-01 5.02E 03 3.725 05 1.82E 05 W 147 1.20E 01 9.* IGE 00 3.43E 00 0.00E-01 0.00E-01 4.74E 04 1.77E 05 NP 239 3.38E 02 3.19E 01 1.77E 01 0.00E-01 1.00E 02 6.49E 04 1.32E 05

H l 3s Revision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 O i m Reference Use Page 149 of 188 O

ATTACHMENT A !

0 (Page 145 of 184)

N !

\

TABLE A.5-4 ;

h) INHALATION PATHNAY FACTOR .

( MtEN/YR PER pCI/M 3 3 CHILD (RI FACTORS) r NUCLIDE BONE LIVER T BODY THYROID KIDNEY- LUNG GI-LLI H 3 0.00E-01 1.12E 03 1.12E 03 1.12E 03 1.12E 03 1.12E 03 1.12E 03 C 14 3.59E 04 6.73E 03 6.73E 03 6.73E 03 6.73E 03 6.73E 01 6.73E 03 t!A 24 1.61E 04 1.61E 04 1.61E 04 1.61E 04 1.61B 04 1.61E 04 1.615 04 P 32 2.60E 06 1.145 05 0.00E-01 9.88E 04 0.00E-01 0.005-01 4.22E 04 CR 51 0.00E-01 0.00E-01 1.54E 02 8.55E 01 2.43E 01 1.70E 04 1.08E 03 MN 54 0.00E-01 4.29E 04 9.51E 03 0.00E-01 1.00E 04 1.58E 06 2.29E 04 MN 56 0.00E-01 1.66E 00 3.125-01 0.005-01 1.67E 00 1.31E 04 1.23E 05 FE 55 4.745 04 2.52E 04 7.77E 03 0.005-01 0.00E-01 1.11E 05 2.87E 03 FE 59 2.07E 04 3.34E 04 1.67E 04 0.00E-01 0.00E-01 1.27E 06 7.07E 04 CO 58 0.00E-01 1.77E 03 3.16E 03 0.00E-01 0.00E-01 1.11E 06 3.44E 04 CO 60 0.00E-01 1.31E 04 2.26E 04 0.00E-01 0.00E-01 7.07E 06 9.62E 04 NI 63 8.21E 05 4.63E 04 2.80E 04 0.00E-01 0.00E-01 2.75E 05 6.33E 03 NI 65 2.99E 00 2.96E-01 1.64E-01 0.00E-01 0.005-01 8.18E 03 8.405 04 CU 64 0.00E-01 1.99E 00 1.07E 00 0.00E-01 6.03E 00 9.58E 03 3.67E 04 EN 65 4.26E 04 1.135 05 7.038 04 0.00E-01 7.14E 04 9.95E 05 1.63E 04 EN 69 6.70E-02 9.66E-02 8.92E-03 0.00E-01 5.85E-02 1.423 03 1.023 04 BR 83 0.00E-01 0.00E-01 4.74E 02 0.001-01 0.00E-01 0.00E-01 3.70E-15 BR 84 0.00E-01 0.00E-01 5.48E 02 0.00E-01 0.00E-01 0.00E-01 3.70E-15 BR 85 0.00E-01 0.00E-01 2.53E 01 0.00E-01 0.005-01 0.00E-01 3.70E-15 RB 86 0.00E-01 1.98E 05 1.14E 05 0.00E-01 0.00E-01 0.00E-01 7.99E 03 RB 88 0.005-01 5.62E 02 3.66E 02 0.00E-01 0.00E-01 0.00E-01 1.72E 01 RB 09 0.00E-01 3.458 02 2.90E 02 0.00E-01 0.00E-01 0.00E-01 1.89E 00 SR 89 5.99E 05 0.005-01 1.725 04 0.00E-01 0.00E-01 2.16E 06 1.67E 05 SR 90 1.01E 08 0.00E-01 6.44E 06 0.00E-01 0.005-01 1.48E 07 3.43E 05 SR 91 1.21E 02 0.00E-01 4.59B 00 0.00E-01 0.00E-01 5.33E 04 1.74E05l SR 92 1.31E 01 0.00E-01 5.255-01 0.00E-01 0.00E-01 2.40E 04 2.42E 05 '

Y 90 4.11E 03 0.00E-01 1.11E 02 0.00E-01 0.00E-01 2.62E 05 2.68E 05 Y 91M 5.07E-01 0.00E-01 1.84E-02 0.00E-01 0.00E-01 2.81E 03 1.72E 03 Y 91 9.145 05 0.00E-01 2.44E 04 0.00E-01 0.00E-01 2.63E 06 1.84E 05 Y 92 2.04E 01 0.00E-01 5.81E-01 0.00E-01 0.00E-01 2.39E 04 2.395 65 Y 93 1.86E 02 0.00E-01 5.11E 00 0.00E-01 0.00E-01 7.44E 04 3.895 05 ER 95 1.90E 05 4.18E 04 3.70E 04 0.00E-01 5.96E 04 2.23E 06 6.11E 04

_ER 97 1.88E 02 2.72E 01 1.60E 01 0.00E-01 3.88E 01 1.13E 05 3.51E 05 NB 95 2.35E 04 9.18E 03 6.55E 03 0.00E-01 8.62E 03 6.14E 05 3.70E 04 MO 99 0.00E-01 1.723 02 4.25E 01 0.00E-01 3.92E 02 1.35E 05 1.27E 05 TC 99M 1.785-03 3.48E-03 5.77E-02 0.00E-01 5.07E-02 9.515 02 4.81E 03 9/93

3 3 Revision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 (T)

M Rnferenca Use Page 150 of 188 i O

ATTACHMENT A !

0 (Page 146 of 184)

' N

\ OFFSITE DOSE CALCULATION MANUAL TABLE A.5-4 (coat'd)

M INNA1ATION PATHWAY FACTOR

\ MREN/YR PER SCI /M s

t

,f) CHILD (RI FACTORS) 0' NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI TC 101 8.10E-05 8.51E-05 1.08E-03 0.00E-01 1.45E-03 5.85E 02 1.63E 01 RU 103 2.79E 03 0.00E-01 1.07E 03 0.00E-01 7.03E 03 6.62E 05 4.48E 04

_RU 105 1.53E 00 0.00E-01 5.55E-01 0.00E-01 1.34E 00 1.59E 04 9.95E 04 RU 106 1.36E 05 0.00E-01 1.69E 04 0.005-01 1.84E 05 1.43E 07 4.29E 05 AG 110M 1.69E 04 1.14E 04 9.14E 03 0.00E-01 2.12E 04 5.48E 06 1.00E 05 TE 125M 6.73E 03 2.33E 03 9.14E 02 1.92E 03 0.00E-01 4.77E 05 3.38E 04 TB 127M 2.49E 04 8.55E 03 3.02E 03 6.07E 03 6.36E 04 1.40E 06 7.14E 04 TE 127 2.77E 00 9.515-01 6.10E-01 1.96E 00 7.07E 00 1.00E 04 TE 129M 1.92E 04 6.85E 03 3.04E 03 6.33E 03 5.62E04l 5.03E 04 1.76E 06 1.82E 05 TE 129 9.77E-02 3.50E-02 2.38E-02 7.14E-02 2.57E-01 2.93E 03 2.55E 04 TE 131M 1.34E 02 5.92E 01 5.07E 01 9.775 01 4.00E 02 2.06E 05 3.08E 05 TE 131 2.17E-02 B.44E-03 6.59E-03 1.70E-02 5.88E-02 2.05E 03 1.33E 03 TE 132 4.81E 02 2.725 02 2.635 02 3.17E 02 1.775 03 3.77E 05 1.38E 05 I 130 8.18E 03 1.64E 04 8.44E 03 1.85E 06 2.45E 04 0.00E-01 5.11E 03 I 131 4.81E 04 4.81E 04 2.73E 04 1'.62B 07 7.88E 04 0.00E-01 2.84E 03 I 132 2.12E 03 4.07E 03 1.885 03 1.94E 05 6.25E 03 0.00E-01 3.20E 03 I 133 1.66E 04 2.03E 04 7.70E 03 3.85E 06 3.38E 04 0.00E-01 5.48E 03 I 134 1.17E 03 2.16E 03 9.95E 02 5.07E 04 3.30E 03 0.00E-01 9.55E 02 I 135 4.32E 03 8.73E 03 4.14E 03 7.928 05 1.34E 04 0.00E-01 4.44E 03 CS 134 6.51E 05 1.01E 06 2.25E 05 0.00E-01 3.30E 05 1.21E 05 3.85E 03 CS 136 6.51E 04 1.71R 05 1.165 05 0.00E-01 9.55E 04 1.45E 04 4.18E 03 CS 137 9.07E 05 8.25E 05 1.28E 05 0.00E-01 2.82E 05 1.04E 05 3.62E 03 CS 138 6.33E 02 8.40E 02 5.55E 02 0.00E-01 6.22E 02 6.81E 01 2.70E D2 RA 139 1.84E 00 9.84E-04 5.36E-02 0.00E-01 8.625 04 5.77E 03 5.77E 04 BA 140 7.40E 04 6.48E 01 4.33E 03 0.00E-01 2.11E 01 1.74E 06 1.02E 05 BA 141 1.96E-01 1.09E-04 6.36E-03 0.00E-01 9.47E-05 2.92E 03 2.75E 02 RA 142 4.99E-02 3.60E-05 2.79E-03 0.00E-01 2.91E-05 1.64E 03 2.74E 00 LA 140 6.44E 02 2.25E 02 7.55E 01 0.00E-01 0.00E-01 1.83E 05

' 2.26E 05 LA 142 1.29E 00 4.11E-01 1.29E-01 0.00E-01 0.00E-01 8.70E 03 7.59E 04 CE 141 3.92E 04 1.95E 04 2.908 03 8.55E 03 0.00E-01 5.44E 05 5.66E 04 CE 143 3.66E 02 1.99E 02 2.47E 01 0.00E-01 8.36E 01 1.155 05 1.27E 05 CE 144 6.77E 06 2.12E 06 3.61E 05 0.00E-01 1.17E 06 1.20E 07 3.89E 05 PR 143 1.85E 04 5.55E 03 9.14E 02 0.00E-01 3.00E 03 4.33E 05 9.73E 04 PR 144 5.96E-02 1.85E-02 3.005-03 0.00E-01 9.77E-03 1.57E 03 1.97E 02 ND 147 1.08E 04 8.73E 03 6.81E 02 0.00E-01 4.81E 03 3.28E 05 8.21E 04 W 187 1.63R 01 9.E6E 00 4.33E 00 0.005-01 0.00E-01 4.11E 04 9.10E 04 NP 239 4.665 02 3.34E 01 2.35E 01 0.00E-01 9.73E 01 5.81E 04 6.40E 04 s/93

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\ OFFSITE DOSE CALCULATION MANUAL RanLE A.5-5 M INHAIATION PATHWAY FAC'IOR ,

\ MREN/YR PER pCI/M'

.0 INFANT (RI FACTORS)

O' NUCLIDE BONE LIVER T BODY THYROID KIDNEY IAEGG GI-LLI H 3 0.00E-01 6.47E 02 6.47E 02 6.47E 02 6.47E 02 6.47E 02 6.47E 02 C 14 2.65E 04 5.31E 03 5.315 03 5.31E 03 5.31E 03 5.31E 03 5.31E 03

_NA 24 1.06E 04 1.06E 04 1.06E 04 1.06E 04 1.06E 04 1.06E 04 1.06E 04 P 32 2.03E 06 1.123 05 7.745 04 0.00E-01 0.00E-01 0.00E-01 1.61E 04 CR 51 0.00E-01 0.00E-01 8.95E 01 5.75E 01 1.325 01 1.28E 04 3.575 02 MN 54 0.00E-01 2.53E 04 4.98E 03 0.00E-01 4.98E 03 1.00E 06 7.06E 03 MN 56 0.00E-01 1.54E 00 2.21E-01 0.00E-01 1.10E 00 1.25E 04 7.175 04 FE 55 1.87E 04 1.175 04 3.33E 03 0.00E-01 0.00E-01 8.69E 04 1.09E 03 FE 59 1.36E 04 2.35E 04 9.48E 03 0.00E-01 0.00E-01 1.02E 06 2.48E 04 CO 58 0.00E-01 1.22E 03 1.82* 1 0.00E-01 0.00E-01 7.77E 05 1.11E 04 CO 60 0.005-01 8.025 03 1.lt. 14 0.00E-01 0.00E-01 4.51E 06 3.19E 04 NI 63 3.39E 05 2.04E 04 1.16E 04 0.00E-01 0.00E-01 2.09E 05 2.42E 03 NI 65 2.395 00 2.84E-01 1.235-01 0.00E-01 0.00E-01 8.12E 03 5.01E 04 CU 64 0.00E-01 1.88E 00 7.74E-01 0.005-01 3.98E 00 9.30E 03 1.50E 04 EN 65 1.93E 04 6.26E 04 3.115 04 0.00E-01 3.25E 04 6.47E 05 5.14E 04 EN 69 5.39E-02 9.675-02 7.18E-03 0.00E-01 4.02E-02 1.47E 03 1.32E 04 BR 83 0.00E-01 0.00E-01 3.81E 02 0.00E-01 0.00E-01 0.005-01 1.40E-15 BR 84 0.00E-01 0.00E-01 4.005 02 0.00E-01 0.00E-01 0.00E-01 1.40E-15 BR 85 0.00E-01 0.00E-01 2.04E 01 0.00E-01 0.00E-01 0.00E-01 1.40E-15 RB 06 0.00E-01 1.90E 05 8.82E 04 0.00E-01 0.00E-01 0.005-01 3.04E 03 RB 88 0.00E-01 5.57E 02 2.87E 02 0.00E-01 0.00E-01 0.00E-01 3.39E 02 RB 89 0.001-01 3.21E 02 2.06E 02 0.005-01 0.00E-01 0.00E-01 6.82E 01 SR 89 3.98E 05 0.00E-01 1.14E 04 0.00E-01 0.00E-01 2.03E 06 6.405 04 SR 90 4.095 07 0.00E-01 2.59E 06 0.005-01 0.00E-01 1.12E 07 1.31E 05 SR 91 9.56E 01 0.00E-01 3.46E 00 0.00E-01 0.00E-01 5.26E 04 7.34E 04 SR 92 1.05E 01 0.00E-01 3.91E-01 0.00E-01 0.00E-01 2.38E 04 1.40E 05 Y 90 3.293 03 0.00E-01 8.82E 01 0.00E-01 0.00E-01 2.69F 05 1.04E 05 Y 91M 4.07E-01 0.00E-01 1.39E-02 0.00E-01 0.00E-01 2.79E 03 2.35E 03 Y 91 5.30E 05 0.00E-01 1.57E 04 0.00E-01 0.00E-01 2.45E 06 7.03E 04 Y 92 1.64B 01 0.00E-01 4.61E-01 0.00E-01 0.00E-01 2.45E 04 1.27E-05 Y 93 1.50E 02 0.00E-01 4.07E 00 0.00E-01 0.00E-01 7.64E 04 1.67E 05 ER 95 1.15E 05 2.79E 04 2.03E 04 0.00E-01 3.11E 04 1.75E 06 2.175 04 ER 97 1.50E 02 2.56E 01 1.175 01 0.00E-01 2.59E 01 1.10E 05 1.40E 05 NB 95 1.57E 04 6.43E 03 3.78E 03 0.00E-01 4.72E 03 4.79E 05 1.27E 04 MO 99 0.00E-01 1.65E 02 3.23E 01 0.00E-01 2.65E 02 1.35E 05 4.87F 04 TC 99M 1.40E-04 2.88E-03 3.72E-02 0.00E-01 3.11E-02 8.11E 02 2.03E 03

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TABLE A.5-5 (cont'd)

M ' INHAIATION PATHWAY FACTOR

\ MREN/YR PER pCI/M' J INFANT (RI FACTORS) 0" i NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI TC 101 6.51E-05 8.23E-05 8.12E-04 0,00E-01 9.79E-04 5.84E 02 8.44E 02 RU 103 2.02E 03 0.00E-01 6.79E 02 0.002-01 4.24E 03 5.528 05 1.61E 04 l RU 105 1.22E 00 0.00E-01 4.10E-01 0.00E-01 8.99E-01 1.57E 04 4.84E 04 RU 106 8.68E 04 0.00E-01 1.09E 04 0.00E-01 1.07E 05 1.16E 07 1.64B 05 AG 110M 9.98E 03 7.22E 03 5.005 03 0.00E-01 3.67W 06 1.09E 04 3.30E 04 TE 125M 4.76E 03 1.998 03 6.58E 02 1.G2B 03 0.00E-01 4.47E 05 1.29E 04 TE 127M 1.67E 04 6.90E 03 2.07E 03 3.75E 04 4.87E 03 1.31E 06 2.73E 04 TE 127 2.23E 00 9.53E-01 4.89E-01 1.85E 00 4.86E 00 1.03E 04 2.44E 04 I TE 129M 1.41E 04 6.09E 03 2.23E 03 5.47E 03 3.18E 04 1.68E 06 6.90E 04 l TE 129 7.88E-02 3.47E-02 1.88E-02 6.75E-02 1.75E-01 3.00E 03 2.63E 04 TE 131M 1.07E 02 5.50E 01 3.63E 01 8.93E 01 2.65E 02 1.99E 05 1.19E 05 TE 131 1.74E-02 8.22E-03 5.00E-03 1.58E-02 3.99E-02 2.06E 03 8.22E 03 TE 132 3.725 02 2.37E 02 1.76E 02 2.79E 02 1.03E 03 3.40E 05 4.41E 04 I 130 6.36E 03 1.39E 04 5.57E 03 1.60E 06 1.53E 04 0.00E-01 1.99E 03 I 131 3.79E 04 4.44E 04 1.96E 04 1.48E 07 5.18E 04 0.00E-01 1.06E 03 I 132 1.69E 03 3.54E 03 1.26E 03 1.69E 05 3.95E 03 0.00E-01 1.90E 03 I 133 1.32E 04 1.92E 04 5.60E 03 3.56E 06 2.24E 04 0.00E-01 2.16E 03 I 134 9.21E 02 1.98E 03 6.65E 02 4.45E 04 2.09E 03 0.00E-01 1.29E 03 I 135 3.86E 03 7.60E 03 2.77E 03 6.96E 05 8.47E 03 0.00E-01 1.83E 03 CS 134 3.96E 05 7.03E 05 7.45E 04 0.00E-01 1.90E 05 7.97E 04 1.33E 03 i

j CS 136 4.83E 04 1.35E 05 5.29E 04 0.00E-01 5.64E 04 1.18E 04 1.43E 03 l CS 137 5.49E 05 6.12E 05 4.55E 04 0.00E-01 1.72E 05 7.13E 04 1.33E 03 CS 138 5.05E 02 7.81E 02 3.98E 02 0.00E-01 4.10E 02 6.54E 01 8.76E 02 BA 139 1.48E 00 9.84E-04 4.30E-02 0.00E-01 5.92E-04 5.95E 03 5.10E 04 BA 140 5.60E 04 5.60E 01 2.90E 03 0.00E-01 1.34E 01 1.60E 06 3.84E 04 BA 141 1.57E-01 1.00E-04 4.97E-03 0.00E-01 6.50E-05 2.97E 03 4.75E 03 BA 142 3.98E-02 3.30E-05 1.96E-03 0.00E-01 1.90E-05 1.55E 03 6.93E 02 l

LA 140 5.05E 02 2.00E 02 5.15E 01 0.00E-01 0.00E-01 1.685 05 8.48E 04 LA 142 1.03E 00 3.77E-01 9.04E-02 0.00E-01 0.00E-01 8.22E 03 5.95E 04 CE 141 2.77E 04 1.67E 04 1.99E 03 0.00E-01 5.25E 03 5.17E 05 2.16E 04 CE 143 2.93E 02 1.93E 02 2.21E 01 0.00E-01 5.64E 01 1.16E 05 4.97E 04 CE 144 3.19E 06 1.21E 06 1.76E 05 0.00E-01 5.3BE 05 9.84E 06 1.48E 05 PR 143 1.40E 04 5.24E 03 6.99E 02 0.00E-01 1.97E 03 4.33E 05 3.72E 04 PR 144 4.79E-02 1.85E-02 2.41E-03 0.00E-01 6.72E-03 1.61E 03 4.28E 03 ND 147 7.94E 03 8.13E 03 5.00E 02 0.00E-01 3.15E 03 3.22E 05 3.12E 04 W 187 1.30E 01 9.02E 00 3.12E 00 0.00E-01 0.00E-01 3.96E 05 3.56E 04 NP 239 3.71E 02 3.32E 01 1.88E 01 0.00E-01 6.62E 01 5.95E 04 2.49E 04

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TAELE A.5-6 M GRASS-CON-MILK PATHNAY FACTOR

\ 8 M MREM /YR PER pCI/SEC

.D ADULT (RI FACTORS) r i NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI l

H 3 0.00E-01 7.63E 02 7.63E 02 7.63E 02 7.63E 02 7.63E 02 7.63E 02 C 14 2.63E 08 5.27E 07 5.27E 07 5.27E 07 5.27E 07 5 27E 07 5.27E 07 NA 24 2.44E 06 2.44E 06 2.44E 06 2.44E 06 2.44E 06 2.44E 06 2.44E 06 P 32 1.71E 10 1.06E 09 6.60E 08 0.005-01 0.00E-01 0.00E-01 1.92E 09 CR 51 0.00E-01 0.00E-01 2.86E 04 0.00E-01 6.30E 03 3.79E 04 7.19E 06 MN 54 0.00E-01 8.415 06 1.61E 06 0.00E-01 0.00E-01 0.005-01 2.58E 07 MN 56 0.00E-01 4.16E-03 7.30E-04 0.00E-01 5.20E-03 0.00E-01 1.33E-01 FE 55 2.51E 07 1.73E 07 4.04E 06 0.00E-01 0.00E-01 9.67E 06 9.95E 06 FE 59 2.97E 07 6.90E 07 2.68E 07 0.00E-01 0.00E-01 1.95E 07 2.33E 08 CO 58 0.00E-01 4.71E 06 1.06E 07 0.00E-01 0.00E 01 0.00E-01 9.56E 07 CO 60 0.00E-01 1.64E 07 3.62E 07 0.00E-01 0.00E-01 0.00E-01 3.08E 08 NI 63 6.73E 09 4.71E 08 2.26% 38 0.00E-01 0.00E-01 0.00E-01 9.73E 07 NI 65 4.63E-01 6.02E-02 2.75E-02 0.00E-01 0.00E-01 0.00E-01 1.53E 00 CU 64 0.00E-01 2.39E 04 1.12E 04 0.00E-01 6.02E 04 0.00E-01 2.03E 06 ZN 65 1.37E 09 '4.37E 09 1.97E 09 0.00E-01 2.92E 09 0.00E-01 2.75E 09 CN 69 5.22E-12 9.99E-12 6.95E-13 0.00E-01 6.495-12 0.00E-01 1.50E-12 BR 83 0.005-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 BR 84 0.005-01 0.00E-01 0.002-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 BR 85 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 RB 86 0.00E-01 2.59E 09 1.21E 09 0.00E-01 0.00E-01 0.00E-01 5.123 08 RB 88 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 1

RB 89 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.005-01 0.00E-01 ;

SR 89 1.45E 09 0.005-01 4.16E 07 0.00E-01 0.00E-01 0.00E-01 2.33E 08 l SR 90 4.68E 10 0.00E-01 1.15E 10 0.00E-01 0.00E-01 0.005-01 1.35E 09 I SR 91 2.87B 04 0.00E-01 1.16E 03 0.005-01 0.00E-01 0.00E-01 1.37E 05 SR 92 4.90E-01 0.00E-01 2.12E-02 0.003-01 0.00E-01 0.00E-01 9.70E 00 Y 90 7.07E 01 0.00E-01 1.903 00 0.00E-01 0.00E-01 0.00E-01 7.50E 05 Y 91M 6.03E-20 0.005-01 2.345-21 0.00E-01 0.00E-01 0.00E-01 1.77E-19 Y 91 8.59E 03 0.005-01 2.305 02 0.00E-01 0.00E-01 0.00E-01 4.735 06 1 Y 92 5.595-05 0.00E-01 1.635-06 0.00E-01 0.00E-01 0.00E-01 9.795-01 Y 93 2.33E-01 0.00E-01 6.44E 03 0.00E-01 0.00E-01 0.00E-01 7.39E 03 ER 95 9.448 02 3.03E 02 2.05E 02 0.00E-01 4.75E 02 0.00E-01 9.59E 05 ZR 97 4.33E-01 8.75E-05 4.00E-02 0.00E-01 1.32E-00 0.00E-01 2.71E 04 NB 95 8.26E 04 4.59E 04 2.47E 04 0.00E-01 4.54E 04 0.00E-01 2.79E 08 MO 99 0.00E-01 2.48E 07 4.71E 06 0.003-01 5.61E 07 0.00E-01 5.74E 07 TC 99N 3.335 00 9.40E 00 1.20E 02 0.00E-01 1.43E 02 4.60E 00 5.56E 03

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!N

\

TABLE A.5-6 (oostt'd) )

N GRASS-COW-MILK PATHWAY FACTOR I

\ M* MREM /YR PER pCI/SEC j ' .D ADULT (RI FACTORS)

T NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI f TC 101 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01

] RU 103 1.02E 03 0.00E-01 4.38E 02 0.00E-01 3.88E 03 0.00E-01 1.19E 05 RU 105 8.58E-04 0.00E-01 3.39E-04 0.00E-01 1.11E-02 0.00E-01 5.25E-01 RU 106 2.04E 04 0.00E-01 2.58E 03 0.00E-01 3.94E 04 0.00E-01 1.32E 06 I

AG 110M 5.82E 07 . 5.39E 07 3.20E 07 0.00E-01 1.06E 08 0.00E-01 2.205 10 TE 125M 1.63E 07 5.90E 06 2.18E 06 4.90E 06 6.63E 07 0.00E-01 6.50E 07 1

TE 127M 4.58E 07 1.64E 07 5.58E 06 1.17E 07 1.86E 08 0.00E-01 1.54E 08 TE 127 6.54E 02 2.35E 02 1.41E 02 4.84E 02 2.66E 03 0.00E-01 5.16E 04 TE 129M 6.02E 07 2.2SE 07 9.53E 06 2.07E 07 2.51E 08 0.00E-01 3.03E 08 TE 129 2.84E-10 1.07E-10 6.29E-11 2.18E-10 1.19E-09 0.00E-01 2.14E-10 j TE 131M 3.61E 05 1.77E 05 1.47E 05 2.80E 05 1.79E 06 0.00E-01 1.73E 07 TE 131 3.67E-33 1.53E-33 1.16E-33 3.01E-33 1.61E-32 0.00E-01 0.00E-01 1

?

TE 132 2.40E 06 1.55E 06 1.46E 06 1.72E 06 1.50E 07 0.00E-01 7.35E 07 I 130 4.20E 05 1.24E 06 4.89E 05 1.05E 08 1.94E 06 0.00E-01 1.07E 06 I 131 2.96E 08 4.24E 08 2.43E 08 1.39E 11 7.26E 08 0.00E-01 1.12E 08 I 132 1.65E-01 4.41E-01 1.54E-01 1.54E 01 7.02E-01 0.00E-01 8.20E-02 I 133 3.87E 06 6.73E 06 2.05E 06 9.90E 08 1.18E 07 0.00E-01 6.05E 06 I 134 2.03E-12 5.52E-12 1.98E-12 9.57E-11 8.78E 12 0.00E-01 4.81E-15 I 135 1.29E 04 3.37E 04 1.24E 04 2.228 06 5.40E 04 0.00E-01 3.80E 04 CB 134 5.65E 09 1.35E 10 1.10E 10 0.00E-01 4.35E 09 1.455 09 2.35E 08 CS 136 2.61E 08 1.03E 09 7.42E 08 0.00E-01 5.73E 08 7.86E 07 1.17E 08 J

CS 137 7.38E 09 1.01E 10 6.61E 09 0.00E-01 3.43E 09 1.14E 09 1.95E 08 CS 138 9.16E-24 1.81E-23 8.97E-24 0.00E-01 1.33E-23 1.31E-24 7.72E-29 BA 139 4.56E-08 3.25E-11 1.34E-09 0.00E-01 3.045-11 1.84E-11 8.09E-08 BA 140 2.69E 07 3.38E 04 1.76E 06 0.00E-01 1.15R 04 1.93E 04 5.54E 07 BA 141 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E 01 0.00E-01 BA 142 0.005-01 0.00E-01 0.00E-01 0.005-01 0.00E-01 0.00E-01 0.00E-01 LA 140 4.525 00 2.28E 00 6.025-01 0.00E-01 0.00E-01 0.00E-01 1.67E 05 LA 142 9.39E-12 4.27E-12 1.06E-12 0.00E-01 0.00E 0.00E-01 3.12E-08 CE 141 4.84E 03 3.28E 03 3.72E 02 0.002-01 1.52E 03 0.00E-01 1.25E 07

, CE 143 4.165 01 3.07E 04 3.40E 00 0.00E-01 1.35E 01 0.00E-01 1.15E 06 CE 144 3.58E 05 1.50E 05 1.92E 04 0.00E-01 0.87E 04 0.00E-01 1.21E 08 i

PR 143 1.58E 02 6.33E 01 7.83E 00 0.00E-01 3.66E 01 0.00E-01 6.92E 05 PR 144 0.00E-01 0.005-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 ND 147 9.46E 01 1.095 02 6.55E 00 0.00R-01 6.40E 01 0.00E-01 5.25E 05 W 187 6.56E 03 5.49E 03 1.92E 03 0.005-01 0.00E-01 0.00E-01 1.005 06 NP 239 3.67E 00 3.61E-01 1.995-01 0.00E-01 1.13E 00 0.00E-01 7.41E 04

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TABLE A.5-7 M GRASS-COW-MILK PATHNAY FACIOR ,

\ M* MREM /YR PER pCI/SEC 3 TEEN (RI FACTORS) 0' WUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI II 3 0.00E-01 9.94E 02 9.94E 02 9.94E 02 9.94E 02 9.94E 02 9.94E 02 .

C 14 4.86E 08 9.72E 07 9.72E 07 9.72E 07 9.72E 07 9.72E 07 9.72E 07 MA 24 4.26E 06 4.26E 06 4.26E 06 4.26E 06 4.263 06- 4.26E 06 4.26E 06 P 32 3.15E 10 1.95E 09 1.22E 09 0.00E-01 0.00E-01 0.00E-01 2.65E 09 CR 51 0.00E-01 0.00E-01 4.99E 04 2.77E 04 1.09E 04 7.13E 04 U.39E D6 MN 54 0.00E-01 1.40E 07 2.78E 06 0.00E-01 4.18E 06 0.00E-01 2.87E 07 MN 56 0.00E-01 7.37E-03 1.31E-03 0.00E-01 9.33E-03 0.00E-01 4.85E-01 FE 55 4.45E 07 3.16E 07 7.36E 06 0.00E-01 0.00E-01 2.00E 07 1.37E 07 FE 59 5.18E 07 1.21E 08 4.67E 07 0.00E-01 0.00E-01 3.81E 07 2.86E 08 CO 58 0.00E-01 7.94E 06 1.83E 07 0.00E-01 0.00E-01 0.00E-01 1.09E 08 CO 60 0.00E-01 2.78E 07 6.26E 07 0.00E-01 0.005-01 0.00E-01 3.62E 08 NI 63 1.18E 10 8.35E 08 4.01E 08 0.00E-01 0.00E-01 0.00E-01 1.33E 08 NI 65 8.485-01 1.08E-01 4.94E-02 0.005-01 0.00E-01 0.00E-01 5.88E 00 CU. 64 0.00E-01 4.25E 04 2.00E 04 0.00E-01 1.005 05 0.00E-01 3.30E 06 ZN 65 2.11E 09 7.31E 09 3.41E 09 0.00E-01 4.685 09 0.00E-01 3.10E 09 l

ZN 69 9.62E-12 1.83E-11 1.28E-12 0.00E-01 1.20E-11 0.00E-01 3.38E-11 BR 83 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 BR 84 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 BR 85 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 RB 86 0.005-01 4.73E 09 2.22E 09 0.00E-01 0.00E-01 0.00E-01 7.00E 08 RB 88 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 RB 89 0.00E-01 0 00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 SR 89 2.67E 09 0.005-01 7.66E 07 0.00E-01 0.00E-01 0.00E-01 3.198 08 l SR 90 6.61E 10 0.00E-01 1.63E 10 0.00E-01 0.00E-01 0.00E-01 1.865 09 '

SR 91 5.27E 04 0.00E-01 2.10E 03 0.00E-01 0.00E-01 0.00E-01 2.398 05 l SR 92 8.96E-01 0.005-01 3.82E-02 0.00E-01 0.00E-01 0.00E-01 2.28E 01 ;

Y 90 1.30E 02 0.005-01 3.50E 00 0.00E-01 0.00E-01 0.00E-01 1.07E 06 Y 91M 1.11E-19 0.005-01 4.22E-21 0.00E-01 0.00E-01 0.00E-01 5.22E-18 Y 91 1.58E 04 0.00E-01 4.24E 02 0.00E-01 0.00E-01 0.00E-01 6.48E 06 Y 92 1.03E-04 0.00E-01 2.99E-06 0.00E-01 0.005-01 0.00E-01 2.83E 00 Y 93 4.303 01 0.00E-01 1.1tE-02 0.00E-01 0.00E-01 0.00E-01 1.31E 04 I 2R 95 1.65E 03 5.21E 02 3.58E 02 0.00E-01 7.65E 02 0.00E-01 1.20E 06 ZR 97 7.89E-01 1.56E-01 7.19E-02 0.00E-01 2.37E-01 0.00E-01 4.23E 04 NB 95 1.41E 05 7.81E 04 4.30E 04 0.00E-01 7.57E 04 0.00E-01 3.34E 08 NO 99 0.005-01 4.47E 07 8.535 06 0.00E-01 1.02E 08 0.00E-01 8.01B 07 TC 99M 5.775 00 1.61E 01 2.08E 02 0.00E-01 2.40E 02 8.93E 00 1.06E 04 N =-r-

H

- - - - - , - - v-- - ~ - - - - - - - - - - - - - -

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\ OFFSITE DOSE CALCULATION MANUAL TABLE A.5-7 (coat'd)

M GRASS-CON-MILK PATHNAY FACTOR

\ M* MREM /YR PER SCI /SEC j TEEN (RI FAC1VRS) 0' NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI TC 101 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 RU.

0.00E-01 0.00E-01 103 1.81E 03 0.00E-01 7.74E 02 0.00E-01 6.38E 03 0.00E-01 1.51E 05 RU 105 1.575-03 0.00E-01 6.00E-04 0.00E-01 1.98E-02 0.00E-01 1.27E 00 RU 106 3.75E 04 0.00E-01 4.73E 03 0.00E-01 7.23E 04 0.00E-01 1.80E 06 AG 110M 9.63E 07 9.11E 07 5.54E 07 0.00E-01 1.74E 08 0.00E-01 2.56E 10 TE 125M 3.00E 07 1.08E 07 4.02E 06 8.39E 06 0.00E-01 0.00E-01 8.86E 07 TE 127M 8.44E 07 2.99E 07 1.00E 07 2.01E 07 3.42B 08 0.00E-01 2.10E 08 TE 127 1.21E 03 4.29E 02 2.61E 02 8.36E 02 4.91E 03 0.00E-01 9.35E 04 TE 129M 1.10E 08 4.09E 07 1.74E 07 3.55E 07 4.61E 08 0.00E-01 4.13E 08 TE 129 5.23E-10 1.95E-10 1.27E-10 3.74E-10 2.20E-09 0.00E-01 2.86E-09 TE 131M 6.57E 05 3.15E 05 2.63E 05 4.74E 05 3.29E 06 0.00E-01 2.53E 07 TE 131 6.70E-33 2.76E-33 2.09E-33 5.16E-33 2.93E-32 0.00E-01 5.50E-34 TR 132' 4.29E 06 2.72E 06 2.56E 06 2.87E 06 2.61E 07 0.00E-01 8.61E 07 I 130 7.39E 05 2.14E 06 8.54E 05 1.745 08 3.26E 06 0.005-01 1.64E 06 I 131 5.375 08 7.52E 08 4.04E 08 2.20E 11 1.30E 09 0.00E-01 1.49E 08 I 132 2.92E-01 7.65E-01 2.74E-01 2.58E 01 1.20E 00 0.00E-01 3.33E-01 I 133 7.07E 06 1.20E 07 3.66E 06 1.67E 09 2.10E 07 0.00E-01 9.08E 06 I 134 3.61E-12 9.5BE-12 3.44E-12 1.60E-10 1.51E-11 0.00E-01 1.26E-13 I 135 2.28E 04 5.88E 04 2.18E 04 3.78E 06 9.288 04 0.00E-01 6.51E 04 CS 134 9.82E 09 2.31E 10 1.07E 10 0.00E-01 7.34E 09 2.805 09 2.87E 08 CS 136 4.44E 08 1.753 09 1.17E 09 0.00E-01 9.52E 08 1.50E 08 1.41E 08 CS 137' 1.34E 10 1.76E 10 6.20E 09 0.00E-01 6.06E 09 2.35E 09 2.53E 08 CS 138 1.66E-23 3.19E-23 1.60E-23 0.00E-01 2.36E-23 2.74E-24 1.45E-26 BA 139 8.44E-08 5.94E-11 2.465-09 0.00E-01 5.60E-11 4.09E-11 7.53E-07 BA 140 4.85E 07 5.95E 04 3.13E 06 0.00E-01 2.02B 04 4.005 04 7.48E 07 BA 141 0.00E-01 0.002-01 0.00E-01 0.00E-01 0.00E-01 0.005-01 0.00E-01 BA 142 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 LA 140 8.123 00 3.99E 00 1.06E 00 0.00E-01 0.00E-01 0.00E-01 2.29E 05 LA 142 1.695-11 7.52E-12 1.87E-12 0.005-01 0.00E-01 0.00E-01 2.29E-07 CE 141 8.88E 03 5.93E 03 6.81E 02 0.00E-01 2.79E 03 0.00E-01 1.70E 07 CE 143 7.64E 01 5.56E 04 6.21E 00 0.00E-01 2.49E 01 0.00E-01 1.67E 06 CE 144 6.58E 05 2.72E 05 3.54B 04 0.00E-01 1.63E 05 0.00E-01 1.66E 08 PR 143 2.90E 02 1.16E 02 1.44E 01 0.00E-01 6.73E 01 0.005-01 9.55E 05 PR 144 0.005-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 ND 147 1.82E 02 1.98E 02 1.192 01 0.005-01 1.165 02 0.00E-01 7.15E 05 W 187 1.20E 04 9.78E 03 3.43E 03 0.005-01 0.00E-01 0.00E-01 2.65E 06 NP 239 7.01E 00 6.61E-01 3.675-01 0.00E-01 2.07E 00 0.00E-01 1.06E 05

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\ OFFSITE DOSE CALCULATION MANUAL i 1

TABLE a.s-8 M GRASS-00W-MILK PATMNAY FAC10R

\ x* MREN/YR PER HCI/SEC l

,f) CHILD (RI FACTORS)

(T NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI l '

H 3 0.00E-01 1.57E 03 1.57E 03 1.57E 03 1.57E 03 1.57E 03 1.57E 03 !

C 14 1.19E 09 2.39E 08 2.39E 08 2.39E 08 2.39E 08 2.39E 08 2.39E 08 NA 24 8.96E 06 - 8.86E 06 8.86E 06 8.86E 06 8.86E 06 8.86E 06 8.85E 06 P 32 7.77E 10 3.64E 09 3.00E 09 0.00E-01 0.00E-01 0.00E-01 2.15E 09 CR 51 0.00E-01 0.00E-01 1.02E 05 5.65E 04 1.54E 04 1.03E 05 5.40E 06

( MN 54 0.00E-01 2.10E 07 5.59E 06 0.00E-01 5.88E 06 0.00E-01 1.76E 07 MN 56 0.00E-01 1.29E-02 2,90E-03 0.00E-01 1.56E-02 0.00E-01 1.86E 00 FE 55 1.12E 08 5.93E 07 1.84E 07 0.00E-01 0.00E-01 3.35E 07 1.10E 07

! FE 59 1.20E 08 1.94E 08 9.69E 07 0.00E-01 5.64E 07 2.02E 08

0. 00.E. - 01 CO 58 0.00E-01 1.21E 07 3.71E 07 0.00E-01 0.00E-01 0.00E-01 7.07E 07 CO 60 0.00E-01 4.32E 07 1.27E 08 0.00E-31 0.00E-01 0.00E-01 2.39E 08 NI 63 2.96E 10 1.59E 09 1.01E 09 0.00E-01 0.00E-01 0.00E-01 1.07E 08 NI 65 2.07E 00 1.95E-01 1.14E-01 0.00E-01 0.005-01 0.00E-01 2.39E 01 CU 64 0.00E-01 7.475 04 4.51E 04 0.00E-01 1.81E 05 0.00E-01 3.51E 06 EN SS 4.13E 09 1.10E 10 6.85E 09 0.00E-01 6.94E 09 0.00E-01 1.93E 09 EN 69 2.36E-11 3.42E-11 3.163-12 0.005-01 2.075-10 0.005-01 2.15E-09 BR 83 0.00E-01 0.003-01 0.005-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 BR 84 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E 01 BR 85 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 RB 86 0.00E-01 8.77E 09 5.39E 09 0.00E-01 0.00E-01 0.00E-01 5.64E 08 RB 88 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 RB 89 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 SR 89 6.62E 09 0.00E-01 1.89E 08 0.00E-01 0.00E-01 0.00E-01 2.56E 08 SR 90 1.12E 11 0.00E-01 2.83E 10 0.00E-01 0.00E-01 0.00E-01 1.50E 09 SR 91 1.29E 05 0.00E-01 4.88E 03 0.00E-01 0.00E-01 0.00E-01 2.85E 05 SR 92 2.19E 00 0.00E-01 8.78E-02 0.00E-01 0.00E-01 0.00E-01 4.15E 01 l Y 90 3.22E 02 0.00E-01 8.61E 00 0.00E-01 0.00E-01 0.00E-01 9.15E 05 l

Y 91M 2.70E-19 0.00E-01 9.82E-21 0.00E-01 0.00E-01 0.00E-01 5.29E-16 Y 91 3.90E 04 0.00E-01 1.04E 03 0.00E-01 0.005-01 0.00E-01 Y 92 2.54E-04 0.00E-01 7.26E-06 0.00E-01 5.20E06l 0.00E-01 0.00E-01 7.33E 00 Y 93 1.06E 00 0.00E-01 2.90E-02 0.00E-01 0.00E-01 0.00E-01 1.57E 04 ER 95 3.83E 03 8.43E 02 7.50E 02 0.00E-01 1.21E 03 0.00E-01 8.79E 05 ER 97 1.92E 00 2.77E-01 1.64E-01 0.00E-01 3.98E-01 0.00E-01 4.20E 04

! NB 95 3.18E 05 1.24E 05 8.85E 04 0.00E-01 1.16E 05 0.00E-01 2.29E 08 MO 99 0.00E-01 8.14E 07 2.01E 07 0.00E-01 1.74E 08 0.00E-01 6.73E 07

. TC 99M 1.32E 01 2.59E 01 4.30E 02 0.01E-01 3.77E 02 1.32E 01 1.48E 04 9/M

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TABLE A.5-4 (oost'd)

M GEA88-CON-MILK PATHNAY FACTOR

\ M8 MREN/IR PER pCI/SEC

,p CHILD (RI FACTORS)

- G*

NUCLIDE SONE LIVER T BODY THYE0ZD EIDNEY LUNG GI-I.LI I

TC 101 0.00E-01 0.00E=01 0.00E-01 0.005-01 0.00E-01 0.005-01 0.00E-01 RU 103 4.285 03 0.00E-01 1.65E 03 0.00E-01 1.08E 04 0.00E-01 1.11E 05 )

RU 105 3.835-03 0.00E-01 1.39E-03 0.00E-01 3.36E-02 0.00E 2.50E 00 l l

RU 106 9.24E 04 0.00E-01 1.15E 04 0.00E-01 1.25E 05 0.005-01 1.44E 06 AG 110M 2.09E 08 1.41E 08 1.13E 08 0.00E-01 2.63E 08 0.00E-01 1.68E 10 TE 125M 7.38E 07 2.00E 07 9.84E 06 2.07E 07 0.00E-01 0.00E-01 7.12E 07 )

TB 127M 2.08E 08 5.60E 07 2.47E 07 4.97E 07 5.93E 08 0.00E-01 1.68E 08 -

TE 127 2.90E 03 8.03E 02 6.39E 02 2.06E 03 8.47E 03 0.00E-01 1.165 05 ;

TE '129M 2.715 08 7.58E 07 4.21E 07 8.75E 07 7.973 08 0.00E-01 3.31E 08 l TE 129 1.295-09 3.60E-10 3.06E-10 9.213-10 3.78E-09 0.00E-01 8.03E-08 TE 131M 1.60E 06 5.53E 05 5.898 05 1.14E 06 5.36E 06 0.00E-01 2.24E 07 i TE 131 1.645-32 5.01E-33 4.89E-33 1.26E-32 4.97E-32 0.00E-01 8.64E-32 I 1

TE 132 1.02E 07 4.54E 06 5.485 06 6.61E 06 4.21E 07 0.005-01 4.57E 07 !

I 130 1.73E 06 3.49E 06 1.80E 06 3.05E 08 5.22E 06 0.00E-01 1.63E 06 I 131 1.30E 09 1.31E 09 7.45E 00 4.33E 11 2.15E 09 0.00E-01 1.17E 08 I 132 6.91E-01 1.275 00 5.645-01 5.89E 01 1.94E 00 0.00E-01 1.49E 00 L I 133 1.72E 07 2.12E 07 8.04E 06 3.955 09 3.54E 07 0.00E-01 8.56E 06 .

I 134 8.55E-12 1.595-11 7.31E-12 3.65E-10 2.43E-11 0.00E-01 1.05E-11 j i

I 135 5.41E 04 9.73E 04 4.60E 04 8.628 06 1.49E 05 0.00E-01 7.41E 04 [

CS 134 2.27E 10 3.72E 10 7.84E 09 0.00E-01 1.15E 10 4.13E 09 2.00E 08 CS 136 1.00E 09 2.76E 09 1.785 09 0.005-01 1.47E 09 2.19E 08 9.693 07 CS 137 3.22E 10 3.09E 10 4.55E 09 0.00E-01 1.01E 10 3.62E 09 1.93E 08 CS 138 4.03E-23 5.60E-23 3.55E-23 0.00E-01 3.94E-23 4.24E-24 2.58E-23 i RA 139 2.07E-07 1.11E-10 6.01E-09 0.00E-01 9.67E-11 6.51E-11 1.20E-05 -

RA 140 1.17E 05 1.03E 05 6.84E 06 0.00E-01 3.34E 04 6.125 04 5.94E 07 BA - 141 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.005-01 0.00E-01 ;

RA 142 0.005-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0 00E-01 LA 6.80E 00 140 1.94E 01 2.29E 00 0.00E-01 0.00E-01 0.00E-01 1.89E 05 LA 142 4.09E-11 1.30E-11 4.00E-12 0.00E-01 0.00E-01 0.00E-01 2.585-06 CE 141 2.19E 04 1.09E 04 1.62E 03 0.00E-01 4.78E 03 0.00E-01 1.36E 07 j i

CE 143 1.88E 02 1.02E 05 1.47E 01 0.00E-01 4.27E 01 0. 00m;- 01 1.493 06 CE 144 1.62E 06 5.09E 05 8.66E 04 0.00E-01 2.82E 05 0.00E-01 1.33E 08 PE 143 7.18E 02- 2.16E 02 3.56E 01 0.00E-01 1.175 02 0.00E-01 7.75E 05 f PR 144 0.00E-01. 0.005-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 MD 147 4.47E 02 3.62E 02 2.80E 01 0.00E-01 1.99E 02 0.00E-01 5.73E 05 !

W 187 2.91E 04 1.72E 04 7.73E 03 0.00E-01 0.00E-01 0.00E-01 2.42E 06 i 3

NP 239 1.72E 01 1.24E 00 8.70E-01 0.00E-01 3.58E 00 0.00E-01 9.165 04 j 9/93 i i

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~

TABLE A.5-9 M GRASS-COW-MILE PATHNAY FAC'!OR

\ M* MREN/YR PER pCI/SEC

.D INFANT (RI FACTORS)

I D' j NUCLIDE BONE LIVER T BODY THYROID EIDNEY LUNG GI-LLI h 3 0.00E-01 2.38E 03 2.38E 03 2.38E 03 2.38E 03 2.38E 03 2.38E 03 C 14 2.34E 09 5.00E 08 5.00E 08 5.00E 08 5.00E 08 5.00E 08 5.00E 08 NA 24 1.548 07 1.54E 07 1.54E 07 1.54E 07 1.54E 07 1.54E 07 1.54E 07 l P 32 1.605 11 9.42E 09 6.21E 09 0.00E-01 0.00E-01 0.00E-01 2.17E 09 l CR 51 0.00E-01 0.00E-01 1.61E 05 1.05E 05 2.30E 04 2.05E 05 4.70E 06 {

MN 54 0.00E-01 3.90E 07 8.84E 06 0.00E-01 8.64E 06 0.00E-01 1.43E 07 I MN 56 0.00E-01 3.15E-02 5.43E-03 0.00E-01 + 2.71E-02 0.00E-01 2.86E 00 FE 55 1.35E 08 8.72E 07 2.33E 07 0.00E-01 0.00E-01 4.26E 07 1.11E 07 FE 59 2.24E 08 3.92E 08 1.54E 08 0.00E-01 0.00E-01 1.16E 08 1.87E 08 CO 58 0.00E-01 2.43E 07 6.05E 07 0.00E-01 0.00E-01 0.00E-01 6.04E 07 CO 60 0.00E-01 8.82E 07 2.08E 08 0.00E-01 0.00E-01 0.00E-01 2.10E 08 NI 63 3.49E 10 2.16E 09 1.21E 09 0.00E-01 0.00E-01 0.00E-01 1.07E 08 NI 65 4.39E 00 4.97E-01 2.26E-01 0.00E-01 0.00E-01 0.00E-01 3.78E 01 CU 64 0.00E-01 1.86E 05 8.60E 04 0.00E-01 3.14E 05 0.00E-01 3.81E 06 EN 65 5.55E 09 '1.90E 10 8.78E 09 0.00E-01 9.23E 09 0.00E-01 1.61E 10 EN 69 5.04E-11 9.07E-11 6.75E-12 0.00E-01 3.77E-11 0.00E-01 7.40E-09 BR 83 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 BP 84 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 BR A5 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 RB 86 0.00E-01 2.23E 10 1.10E 10 0.00E-01 0.00E-01 0.00E-01 5.70E 08

_RB 28 0.00E-05 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 RB 89 0.00E-01 0.00E 01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 SR 89 1.26E 10 0.00E-01 3.61E 08 0.00E-01 0. or,E-01 0.00E-01 2.59E 08 SR 90 1.22E 11 0.00E-01 3.10E 10 0.00E-01 0.00E-01 0.00E-01 1.52E 09 SR 91 2.69E 05 0.00E-01 9.75E 02 0.00E-01 0.00E-01 0.00E-01 3.19E 05 SR 92 4.66E 00 0.00E-01 1.73E-01 0.00E-01 0.00E-01 0.00E-01 5.02E 01 Y 90 6.80E 02 0.00E-01 1.82E 01 0.00E-01 0.00E-01 0.005-01 9.39E 05 Y 91M 5.72E-19 0.00E-01 1.95E-20 0.00E-01 0.00E-01 0.00E-01 1.91E-15 Y 91 7.33E 04 0.00E-01 1.95E 03 0.00E-01 0.00E-01 0.00E-01 5.25E 06 Y 92 5.39E-04 0.00E-01 1.51E-05 0.00E-01 0.00E-01 0.00E-01 1.03E 01 Y 93 2.25E 00 0.00E-01 6.13E-02 0.00E-01 0.00E-01 0.00E-01 1.78E 04 ER 95 6.81E 03 1.66E 03 1.18E 03 0.00E-01 1.79E 03 0.00E-01 8.26E 05 ER 97 4.06E 00 6.98E-01 3.195-01 0.00E-01 7.03E-01 0.00E-01 4.45E 04 NB 95 5.94E 05 2.45E 05 1.41E 05 0.00E-01 1.75E 05 0.00E-01 2.06E 08 MO 99 0.00E-01 2.08E 08 4.06E 07 0.00E-01 3.11E 08 0.00E-01 6.85E 07 TC 99M 2.75E 01 5.68E 01 7.315 02 0.00E-01 6.11E 02 2.97E 01 1.65E 04 1

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\

TABLE A.5-9 (cont'd)

M GRASS-CON-MILK PATHNAY FI N R

\ M' MREN/YR PER p'CI/SEC

,3 INFANT (EI FACTORE)

D' NUCLIDE BC8IE LIVER T BODY THYROID EIDNEY LIE 0G GI-LLI TC 101 0.005-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 .J0E-01 0.00E-01 kU 103 3.67E 03 0.00E-01 2.90E 03 0.00E-01 1.80E 04 0.00E-01 1.05E 05 RU 105 8.07E-03 0.00E 2. 72E-02 0.00E-01 5.93E-01 0.00E-01 3.21E 00 RU 106 1.90E 05 0.00E-01 2.38E 04 0.005-01 2.25E 05 0.00E-01 1.44E 06 AG 110M 3.86E 08 2.82E 08 1.86E 08 0.00E-01 4.03E 08 0.00E-01 1.46E 10 TE 125M 1.51E 08 5.04E 07 2.04E 07 5.07E 07 0.09E-01 0.00E-01 7.18E 07 TE 127M 4.21E 08 1.405 08 5.10E 07 1.22E 08 1.04E 09 0.00E-01 1.70E 08 TE 127 6.32E 03 2.12E 03 1.36E 03 5.15E 03 1.54E 04 0.00E-01 1.33E 05 TE 129M 5.57E 08 1.915 08 8.58E 07 2.14E 08 1.39E 09 0.005-01 3.33E 08 TE 129 2.745-09 9.43E-10 6.393-09 2.29E-08 6.81E-08 0.00E-01 2.19E-07 TE 131M 3.38E 06 1.365 06 1.12E 00 2.76E 06 9.36E 06 0.00E-01 2.29E 07 TE 131 3.49E-32 1.295-32 9.78E-32 3.11E-31 .31E 31 0.00E-01 1.41E-30 TE 132 2.115 07 1.05E 07 9.75E 06 1.54E 07 6.545 07 0.00E-01 3.87E 07 I 130 3.55E 06 7.81E 06 3.14E 06 8.76E 08 8.58E 06 0.00E-01 1.68E 06 I 131 2.72E 09 3.21E 09 1.41E 09 1.05E 12 3.74E 09 0.00E-01 1.14E 08 I 132 1.435 00 2.91E 00 1.04E 00 1.37E 02 3.25E 00 0.00E-01 2.36E 00 I 133 3.63E 07 5.28E 07 1.55E 07 9.61E 09 6.21E 07 0.00E-01 8.94E 06 I 134 1.77E-11 3.63E-11 1.29E-10 8.47E-09 4.06E-10 0.00E-01 3.76E-11 I 135 1.12E 05 2.24E 05 8.15E 04 2.002 07 2.49E 05 0.00E-01 8.098 04 CS 134 3.65E 10 6.00E 10 6.87E 09 0.005-01 1.75E 10 6.21E 09 1.85E 08 CS 136 1.96E 09 5.76E 09 2.15E 09 0.00E-01 2.30E 09 4.70E 08 8.75E 07 CS 137 5.15E 10 6.02E 10 4.27E 09 0.00E-r* 1.62E 10 6.55E 09 1.88E 08 CS 138 8.50E-23 1.38E-22 6.70E-22 0.00's 08 6.89E-22 1.00E-23 2.21E-22 BA 139 4.415-07 2.93E-10 1.28E-07 0.00E-01 1.765-09 1.775-10 2.00E-05 ,

RA 140 2.41E 08 2.41E 08 1.24E 07 0.00E-01 5.72E 04 1.48E 05 5.92E 07 l BA 141 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 BA 142 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.005-01 0.005-01 0.00E-01 LA 140 4.06E 01 1.60E 01 4.12E 00 0.00E-01 0.00E-01 0.00E-01 1.88E 05 LA 142 8.595-11 3.15E-11 7.55E-11 0.00E-01 0.00E-01 0.005-01 5.36E-06 CE 141 4.34E 04 2.64E 04 3.115 03 0.00E-01 8.16E 03 0.00E-01 1.375 07 CE 143 3.973 02 2.63E 05 3.005 01 0.00E-01 7.67E 01 0.00E-01 1.54E 06 CE 144 2.33E 06 9.52E 05 1.30E 05 0.00E-01 3.85E 05 0.00E-01 1.33E 08 PR 143 1.49E 03 5.56E 02 7.36E 01 0.00E-01 2.07E 02 0.00E-01 7.84E 05 l

PR 144 0.005-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 ND 147 8.86E 02 9.10E 02 5.57E 01 0.00E-01 3.51E 02 0.00E-01 5.77E 05 W 187 6.12E 04 4.26E 04 1.47E 04 0.00E-01 0.00E-01 0.00E-01 2.50E 06 NP 239 3.65E 01 3.26E 00 1.84E 00 0.00E-01 1.50E 00 0.00E-01 9.43E 04

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D0 l 8 R2 visions 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 N Reference Use 60 Page 161 of 188 l@

ATTACHMENT A ,

!@ (Page 157 of 184)

@ OFFSITE DOSE CALCULATION MANUAL i\

P TABLE A.5-10

@ GRASS-CON-MEAT PATHNAY FACTOR

!\

M* MEEM/YR PER pCI/SEC LD ADULT (RI FAC'! ORS) p ,

NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI i

H 3 0.00E-01 3.25E 02 3.25E 02 3.25E 02 3.25E 02 3.25E 02 3.25E 02 l C 14 2.41E 08 4.83E 07 4.83E07 4.83E 07 4.83E 07 4.83E 07 4.83E 07 1.36E-03 r

NA 24 1.36E-03 1.36E-03 3.36E-03 1.36E-03 1.36E-03 1.36E-03 l

P 32 4.65E 09 2.89E 08 1.80E 08 0.00E-01 0.00E-01 0.00E-01 0.00E-01 CR 51 0.00E-01 0.00E-01 7.05E 03 4.21E 03 1.55E 03 9.35E 03 1.77E 06 MN 54 0.00E-01 9.18E 06 1.75E 06 0.00E-01 2.73E 06 0.005-01 2.81E 07 i

MN 56 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 FE 55 2.93E 08 2.20E 08 4.72E 07 0.00E-01 0.00E-01 1.13E 08 1.16E 08 FE 59 2.65E 08 6.24E 08 2.39E 08 0.00E-01 0.00E-01 1.74E 08 2.08E 09 CO 58 0.00E-01 1.82E 07 4.095 07 0.00E-01 0.00E-01 0.00E-01 3.70E 08 7.52E 07 i

CO 60 0.00E-01 1.66E 08 0.00E-01 0.00E-01 0.00E-01 1.41E 09 NI 63 1.89E 10 1.32E 09 6.33E 08 0.00E-01 0.00E-01 0.00E-01 2.73E 08 ;

l NI 65 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.005-01 0.00E-01 CU 64 0.00e-01 2.73E-07 1.28E-07 0.00E-01 6.89E-07 0.00E-01 2.33E-05 EN 65 3.56E 08 1.13E 09 5.12E 08 0.00E-01 7.575 08 0.00E-01 7.13E 08 EN 69 0.005-01 0.00E-01 0.00E-01 0.003-01 0.00E-01 0.00E-01 0.00E-01 BR 83 0.00E-01 0.005-01 0.00E-01 0.00E-01 0.005-01 0.00E-01 0.00E-01 BR 84 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 l

l BR 85 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.005-01 0.00E-01 0.00E-01 RB 86 0.005-01 4.875 08 2.27E 09 0.00E-01 0.00E-01 0.00E-01 9.61I 07 RB 88 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 RB 89 0.00E 01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 i SR 89 3.02E 08 0.00E-01 8.66E 06 0.00E-01 0.005-01 0.00E-01 4.84E 07 SR 90 1.24E 10 0.00E-01 3.05E 09 0.00E-01 0.00E-01 0.00E-01 3.5PE 08 i

SR 91 1.43E-10 0.00E-01 5.73E-12 0.00E-01 0.00E-01 0.00E-01 6.76E-10 SR 92 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Y 90 1.07E 02 0.00E-01 2.86E 00 0.005-01 0.00E-01 0.00E-01 1.13E 06 Y 91M 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Y 91 1.13E 06 0.00E-01 3.03E 04 0.00E-01 0.00E-01 0.00E-01 6.23E 08 Y 92 0. DOE-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 !

Y 93 6.59E-12 0.00E-01 1.82E-13 0.00E-01 0.00E-01 0.00E-01 2.0PE-07 l ER 95 1.87E 06 6.01E 05 4.07E 05 0.00E-01 9.43E 05 0.00E-01 1.90E 09 l ZR 97 2.088-05 4.19E-06 1.92E-06 0.00E-01 6.33E-06 0.00E-01 1.30E 00 NB 95 2.30E 06 1.28E 06 6.88E 05 0.00E-01 1.26E 06 0.00E-01 7.76E 09 MO 99 0.00E-01 9.99E 04 1.90E 04 '0.00E-01 2.26E 05 0.00E-01 2.32E 05 i TC 99M 4.50E-21 1.27E-20 1.62E-10 0.005-01 1.93E-19 6.23E-21 7.53E-18 l

l TC 101 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 l

l

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ATTACHMENT A D (Page 158 of 184)

N

\ OFFSITE DOSE CALCUIATION MANUAL

[~ TABLE 1.5-10 (coat'd)

M GRASS-CON-MEAT PATHWAY FACIOR

\ 8 M NREM/YR PER PCI/SEC '

.D ADULT (RI FACTORS) ;

0' NUCLIDE BONE LIVER T BODY THYROID EIDNEY LUNG GI-LLI RU 103 1.05E 08 0.00E-01 4.53E 07 0.00E-01 4.01E 08 0.00E-01 1.23E 10 RU 105 5.87E-28 0.00E-01 2.32E-28 0.00E-01 7.58E-27 0.00E-01 3.595-25 RU 105 2.90E 03 0.00E-01 3.545 03 0,003-01 5.40E 03 0.00E-01 1. Sir 11 AG 110M 6.685 06 6.18E 06 3.67E 06 0.00E-01 1.22E 07 0.00E-01 2.52E 09 TE 125M 3.59E 08 1.30E 08 4.81E 07 1.083 08 1.46E 09 0.00E-01 1.43E 09 j TE 127M 1.125 09 3.99E 08 1.36E 08 2.85E 08 4.53E 09 0.00E-01 3.74E 09 TE 127 2.14E-10 7.68E-11 4.63E-11 1.58E-10 8.71E-10 0.00E-01 1.69E-08 TE 129M 1.13E 09 4.23E 08 1.80E 08 3.90E 08 4.73E 09 0.005-01 5.71E 09 TR 129 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 TE 131M 4.52E 02 2.21E 02 1.84E 02 3.50E 02 2.24E 03 0.00E-01 2.20E 04 TE 131 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.005-01 TE 132 1.42E 06 9.19E 05 8.63E 05 1.01E 06 8.85E 06 0.005-01 4.35E 07 I 130 2.12E-06 6.26E-06 2.47E-06 5.30E-04 9.76E-06 0.00E-01 5.39E-06 I 131 1.07E 07 1.54E 07 8.81E 06 5.04E 09 2.64E 07 0.00E-01 4.06E 06 l

I 132 0.00E-01 0.00E-01 0.005-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 l 1 133 3.67E-01 6.38E-01 1.94E-01 9.37E 01 1.11E 00 0.00E-01 5.73E-01 I 134 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 I 135 4.47E-17 1.17E-16 4.32E-17 7.735-15 1.88E-16 0.00E-01 1.32E-16 CS 134 6.58E 08 1.56E 09 1.28E 09 0.00E-01 5.06E 08 1.68E 08 2.74E 07 l

CS 136 1.18E 07 4.66E 07 3.35E 07 0.00E-01 2.59E 07 3.55E 06 5.24E 06 l CS 137 8.72E 08 1.195 09 7.81E 08 0.00E-01 4.05E 08 1.35E 08 2.315 07 ,

CS 138 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.005-01 BA 139 0.005-01 0.00E-01 0.00E-01 0.00E-01 0.005-01 0.00E-01 0.00E-01 i RA 140 2.87E 07 3.61E 04 1.88E 06 0.00E-01 1.23E 04 2.07E 04 5.92E 07 BA 141 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.005-01 0.00E-01 0.00E-01 I BA 142 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 LA 140 3.76E-02 1.89E-02 5.00E-03 0.00E-01 0.00E-01 0.00E-01 1.39E 03 LA 142 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 CE 141 1.40E 04 9.50E 03 1.08E 03 0.00E-01 4.41E 03 0.00E-01 3.63E 07 1

l CE 143 2.01E-02 1.49E 01 1.65E-03 0.00E-01 6.55E-03 0.00E-01 5.56E 02

- CE 144 1.46E 06 6.09E 05 9.83E 04 0.00E-01 3.61E 05 0.00E-01 4.93E 08

{ PR 143 2.10E 04 8.41R 03 1.04E 03 0.00E-01 4.86E 03 0.00E-01 9.19E 07 l PR 144 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 l ND 147 7.17E 03 8.29E 03 4.96E 02 0.00E-01 4.84E 03 0.00E-01 3.98E 07

{ W 187 2.17E-02 1.81E-02 6.33E-03 0.005-01 0.00E-01 0.00E-01 5.93E 00 NP 239 2.593-01 2.55E-02 1.40E-02 0.00E-01 7.94E-02 0.00E-01 5.22E 03 l- ._

'I

p. Revision: 0 OFFSITE DOSE CALCUIATION MANUAL AP 07B-003 D

g Reference Use Page 163 of 188 C I ATTACHMENT A O (Page 159 of 184)

\

TABLE A.5-11 M '

GRASS-COW-MEAT PATHNAY FACTOR

\ M* MREN/YR PER pCI/SEC A TEEN (RI FAC70RS)

U*

MUCLlDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI N 3 0.00E-01 1.94E 02 1.94E 02 1.94E 02 1.94E 02 1.94E 02 1.94E 02 C 14 2.04E 08 4.085 07 4.00E 07 4.08E 07 4.08E 07 4.08E 07 4.00E 07 NA 24 1.095-03 1.095-03 1.09E-03 1.09E.03 1.09E-03 1.09E-03 1.09E-03 P 32 3.93E 09 2.44E 08 1.52E 08 0.005-01 0.00E-01 0.00E-01 3.30E 08 CR 51 0.00E-01 0.00E-01 5.64E 03 3.13E 03 1.24E 03 8.05E 03 9.47E 05 MN 54 0.00E-01 7.00E 06 1.395 06 0.00E-01 2.09E 06 0.00E-01 1.44E 07 MN 56 0.00E-01 0.00E-01 0.005-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 YE 55 2.38E 08 1.69E 08 3.935 07 0.00E-01 0.00E-01 1.07E 08 7.30E 07 FE 59 2.12E 08 4.95E 08 1.01E 08 0.00E-01 0.00E-01 1.56E 08 1.17E 09 CO 58 0.00E-01 1.41E 07 3.24E 07 0.00E-01 0.00E-01 0.00E-01 1.94E 08 CO 60 0.00E-01 5.83E 07 1.31E 08 0.00E-01 0.00E-01 0.00E-01 7.60E 08 NI 63 1.52E 10 1.07E 09 5.15E 08 0.00E-01 0.00E-01 0.00E-01 1.71E 08 NI 65 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.005-01 0.00E-01 0.00E-01 CU 64 0.00E-01 2.23E-07 1.055-07 0.00E-01 5.64E-07 0.00E 1.73E-05 EN 65 2.50E 08 8.69E 08 4.05E 08 0.00E-01 5.56E 08 0.00E-01 3.68E 08 EN 69 0.00E-01 0.00E-01 0.005-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 BR 83 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 BR 84 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.005-01 BR 85 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.005-01 0.00E-01 RB 86 0.00E-01 4.07E 08 1.91E 08 0.00E-01 0.00E-01 0.00E-01 G.02E 07 RB 88 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.005-01 0.00E-01 0.00E-01 RB 89 0.00E-01 0.005-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 SR 89 2.55E 08 0.00E-01 7.295 06 0.00E-01 0.00E-01 0.00E-01 3.03E 07 SR ## 8.05E 09 0.00E-01 0.00E-01 1.99E 09 0.00E-01 0.00E-01 2.26E 08 SR 91 1.19E-10 0.00E-01 4.75E-12 0.00E-01 0.00E-01 0.00E-01 5.41E-10 SR 92 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Y 90 8.98E 01 0.00E-01 2.42E 00 0.00E-01 0.00E-01 0.00E-01 7.41E 05 Y 91M 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.005-01 Y 91 9.54E 05 0.00E-01 2.56E 04 0.00E-01 0.00E-01 0.005-01 3.91E 08 Y 92 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.005-01 0.00E-01 Y 93 5.56E-12 0.00E-01 1.53E-13 0.00E-01 0.00E-01 0.00E-01 1.70E-07 ER 95 1.50E 06 4.73E 05 3.26E 05 0.005-01 6.96E 05 0.00E-01 1.09E 09 ZR 97 1.73E-05 3.42E-06 1.58E-06 0.00E-01 5.19E-06 0.00E-01 9.27E-04 NB 95 1.80E 06 9.96E 05 5.48E 05 0.00E-01 9.66E 05 0.00E-01 4.26E 09 MO 99 0.00E-01 8.26E 04 1.54E 04 0.00E-01 1.89E 05 0.00E-01 1.48E 05 TC 99M 3.58E-21 9.97E-21 1.29E-19 0.00E-01 1.49E-19 5.54E-21 6.55E-18

.~ _ _ ,

H M

@ Revision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 m Reference Use Page 164 of 188 O

l ATTACHMENT A

'O l (Page 160 of 184)

M ,

\ l l- TABLE A.5-11 (coat'd) lM GRASS-COM-MEAT PATHNAY FACTOR '

\^ M* MREM /YR PER pCI/SEC

, ,g; TEEN (RI FACTORS) l I G' \

l NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI l TC 101 0.00E-01 0.00E-01 0.00E-01 0.005-01 0.00E-01 0.00E-01 0.00E-01 RU 103 8.56E 07 0.00E-01 3.66E 07 0.00E-01 3.02E 08 0.00E-01 7.15E 09 l RU 1u5 4.91E-28 0.00E-01 1.91E-28 0.00E-01 6.91E-27 0.00E-01 3.96E-25 l l l RU 106 2.36E 09 0.00E-01 2.97E 0.9 0.00E-01 4.55E 09 0.005-01 1.13E 11 !

AG 110M 5.06E 06 4.79E 06 2.915 06 0.00E-01 9.135 06 0.00E-01 1.35E 09 l

TE 125s4 3.03E 08 1.09E 08 4.05E 07 8.475 07 0.00E-01 0.00E-01 8.94E 08 l

t TE 127M 9.42E 08 3.34E 08 1.12E 08 2.24E 08 3.82B 09 0.00E-01 2.35E 09 TE 127 1.81E-10 6.43E-11 3.91E-11 1.25E-09 7.35E-10 0.00E-01 1.40E-08 TB 129M 9.50E 08 3.53E 08 1.50E 08 3.07E 08 3.97E 09 0.00E-01 3.575 09 l l

TE 129 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 !

TE 131M 3.77E 02 1.81E 02 1.51E 02 2.72E 02 1.88E 03 0.00E-01 1.45E 04 TE 131 0.00E-01 0.00E-01 0.005-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 l

' TE 132 1.16E 06 7.36E 05 6.93E 05 '7.76E 05 7.065 06 0.005-01 2.33E 07 I 130 1.71E-06 4.943-06 1.975-06 4.03E-04 7.61E-06 0.005-01 3.80E-06 ,

I 131 8.93E 06 1.255 07 6.72E 06 3.65E 09 2.15E 07 0.00E-01 I 2.47E.06 l I 132 0.00E-01 0.005-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 l I 133 3.07E-01 5.20E-01 1.59E-01 7.26E 01 9.125-01 0.00E-01 3.933-01

! I 134 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E 0.00E-01 I 135 3.64E-17 9.37E-17 3.475-17 6.03E-15 1.48E-16 0.00E-01 1.04E-16 CS 134 5.23E 08 1.23E 09 5.715 08 0.00E-01 3.91E 08 1.49E 08 1.53E 07 CS 136 9.20E 06 3.625 07 2.43E 07 0.00E-01 1.97E 07 3.115 06 2.91E 06 l CS 137 7.24E 08 9.63E 08 3.36E 08 0.00E-01 3.20E 08 1.27E 08 1.37E 07 C8 138 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01

! BA 139 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 BA 140 2.38E 07 2.91E 04 1.53E 06 0.00E-01 9.88E 03 1.96E 04 3.67E 07 BA 141 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 BA 142 0.00E-01 0.00E-01 0.00E-01 0.003-01' O.00E-01 0.00E-01 0.00E-01 LA 140 3.09E-02 1.52E-02 4.04E-03 0.00E-01 0.00E-01 0.00E-01 8.72E 02 LA 142 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 CE 141 1.18E 04 7.88E 03 9.055 02 0.00E-01 3.71E 03 0.00E-01 2.255 07 CE 143 1.69E-02 1.23E 01 1.38E-03 0.00E-01 5.53E-03 0.00E-01 3.70E 02 CE 144 1.23E 06 5.08E 05 6.60E 04 0.00E-01 3.04E 05 0.00E-01 3.09E 08 PR 143 1.77E 04 7.05E 03 8.78E 02 0.00E-01 4.10E 03 0.00E-01 5.81E 07 4

PR 144 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.003-01 0.00E-01 0.00E-01 I

! ND 147 6.32E 03 6.87E 03 4.11E 02 0.00E-01 4.03E 03 0.00E-01 2.485 07 N 187 1.815-02 1.483-02 5.18E-03 0.00E-01 0.00E-01 0.00E-01 4.00E 00 l

- NP 239 2.26E-01 2.'.3E-02 1.19E-02 0.00E-01 6.70E-07 0.00E-01 3.43E 03 l

1

1 Revision: 0 OFFSITE DOSE CALCULATION MANUAL

.D AP 07B-003 U

FI Reference Use Page 165 of 188 O

ATTACHMENT A D (Page 161 of 184)

N OFF'JITE DOSE CALCULATION MANUAL

\ ,

TABLE A.5-12 M. '

GRASS-CON-MEAT PATHNAY FAC10R 8

\ M MREM /YR PER pCI/SEC l

,g CHILD (RI FACIORS)

W NUCLIDE LIVER T BODY THYROID KIDNEY L1JNG GI-LLI

_ BONE 1 H 3 0.005-01 2.34E 02 2.34E 02 2.34E 02 2.34E 02 2.34E 02 2.34E 02 C 14 3.83E 08 7.67E 07 7.67E 07 7.67E 07 7.67E 07 7.67E 07 7.675 07 NA 24 1.73E-03 1.73E-03 1.73E-03 1.73E-03 1.735-03 1.73E-03 1.73E-03 P 32 7.41E 09 3.47E 08 2.86E 08 0.00E-01 0.00E-01 0.00E-01 2.05E 08 t CR 51 0.00E-01 0.00E-01 8.79E 03 4.88E 03 1.33E 03 8.915 03 4.66E 05 ,

MN 54 0.00E-01 8.01E 06 2.13E 06 0.00E-01 2.25E 06 0.00E-01 6.72E 06 !

Mt. 56 0.00E-01 1.63E-53 3.67E-54 0.00E-01 1.97E-53 0.00E-01 55 0.00E-01 2.36E-51l l FE 4.57E 08 2.42E 08 7.50E 07 0.00E-01 1.37E 08 4.49E 07 FE 59 3.76E 08 6.09E 08 3.03E 08 0.00E-01 0.00E-01 1.76E 00 6.34E 08 l

CO 58 0.00E-01 1.64B 07 5.03E 07 0.00E-01 0.00E-01 0.00a-01 9.58E 07 l CO 60 0.00E-01 6.93E 07 2.04E 08 0.00E-01 0.00E-01 0.00E-01 ?.44E 08 'j NI 63 2.91E 10 1.56E 09 9.91E 08 0.00E-01 0.00E-01 0.00E-01 1.05h 08-NI 65 0.00E-01 0.00E-01 0.005-01 0.00E-01 0.005-01 '0.005-01 0.00E-01 CU 64 0.005-01 3.00E-07 1.815-07 0.00E-01 7.24E-07 0.00E-01 1.41E-05 EN 65 3.75E 08 1.00E 09 6.22E 08 0.005-01 6.30E 08 0.005-01 1.76E 08 EN 69 0.00E-01 0.005-01 0.00E-01 0.00E-01 0.00E-01 0.005-01 0.00E-01 BR 83 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.005-01 0.005-01 BR 84 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.005-01 0.00E-01 l BR 85 0.00E-01 0.006-01 0.00E-01 0.00E-01 0.00E-01 0.005-01 0.00E-01 RB 86 0.00E-01 5.77E 08- 3.55E 08 0.00E-01 0.00E-01 0.00E-01 3.71E 07 RB BB 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 RB 89 0.005-01 0.00E-01 0.005-01 0.00E-01 0.00E-01 0.005-01 0.00E-01 SR 89 4.82E 08 0.00E-01 1.388 07 0.00E-01 0.00E-01 0.00E-01 1.87E 07 SR 90 1.04E 10 0.00E-01 2.64E 09 0.00E-01 0.00E-01 0.005-01 1.40E 08 SR 91 2.24E-10 0.00E-01 8.45E-12 0.00E-01 0.00E-01 0.00E-01 4.94E-10 SR 92 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Y 90 1.70E 02 0.00E-01 4.555 00 0.00E-01 0.00E-01 0.00E-01 4.84E 05 Y 91M 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Y 91- 1.80E 06 0.00E-01 4.82E 04 0.00E-01 0.00E-01 0.005-01 2.40E08l Y 92 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 )

! Y 93 1.04E-11 0.00E-01 2.87E-13 0.00E-01 0.00E-01 0.00E-01 1.56E-07 SR 95 2.66E 06 5.86E 05 5.21E 05 0.005-01 8.38E 05 0.00E-01 6.11E 08 ,

l ER 97 3.225-05 4.65E-06 2.74E-06 0.00E-01 6.68E-06 0.00E-01 7.05E-01 i )

i NB 95 3.10E 06 1.21E 06 8.63E 05 0.00E-01 1.13E 06 0.00E-01 2.23E 09 !

NO 99 0.005-01 1.15E 05 2.84E 04 0.00E-01 2.45E 05 0.00E-01 9.51E 04 TC 99M 6.27E-21 1.23E-20 2.04E-19 0.003-01 1.79E-19 6.245-21 7.00E-18 9/93 i

3 3 Rsvision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 Reference Use Page 166 of 188 y U

ATTACHMENT A O (Page 162 of 184)

M t OFFSITE DOSE CALCULATION MANUAL

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~

TABLE A.5-12 (oost'd)

M GRASS-CON-MEAT PATHNAY FACTOR ,

8

\ M MREN/YR PER pCI/SEC !

.J CHILD (RI FACTORS)

W NUCLIDE BONE LIVER T BODY THYROID EIDNEY LUNG -GI-LLI TC 101 0.00E-01 0.005-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.003-01 RU 103 1.55E 08 0.00E-01 5.95E 07 0.00E-01 3.90E 08 0.00E-01 4.00E 09 '

RU 105 9.16E-28 0.00E-01 3.32E-28 0.00E 01 8'.05E-27 0.00E-01 5.98E-25 RU 106 4.44E 09 0.005-01 5.54B 08 0.005-01 5.99E 09 0.00E-01 6.905 10 AG 110M 8.34E 06 5.67E 06 4.53E 06 0.00E-01 1.06E 07 0.00E-01 6.74E 08 TE 125M 5.698 08 1.54E 08 7.59E 07 1.60E 08 0.00E-01 0.00E-01 5.49E 08 i TE 127M 1.77E 09 4.74E 08 2.11E 08 4.24E 08 5.06E 09 0.00E-01 1.44E 09 l TE 127 3.41E-10 9.20E-11 7.325-11 2.36E-10 9.71E-10 0.00E-01 1.33E-08 ,

TR 129M 1.79E 09 5.00E 08 2.785 08 5.772 08 5.26E 09 0.00E-01 2.18E 09 l TE 129 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 TE 131M 7.01E 02 2.43E 02 2.58E 02 4.995 02 2.35E 03 0.00E-01 9.84E 03 TE 131 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.005-01 0.00E-01 0.00E-01

'TE 132 2.12E 06 9.39E 05 1.13E 06 1.37E 06 8.72E 06 0.00E-01 9.46E 06 I 130 3.05E-06 6.175-06 3.185-06 6.80E-04 9.225-06 0.00E-01 2.89E-06 I 131 1.66E 07 1.67E 07 9.47E 06 5.51E 09 2.74E 07 0.00E-01 1.485 06 I 132 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 I 133 ~5 .700-01 7.04E-01 2.66E-01 1.31E 02 1.175 00 0.005-01 2.84E-01 I 134 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 I 135 6.59E-17 1.19E-16 5.61E-17 1.05E-14 1.825-16 0.00E-01 9.04E-17 CS 134 9.22E 08 1.51E 09 3.19E 08 0.00E-01 4.69E 08 1.68E 08 8.16E 06 CS 136 1.59E 07 4.36E 07 2.82E 07 0.00E-01 2.325 07 3.46E 06 1.53E 06 i

I

-CS 137 1.33E 09 1.28E 09 1.88E 08 0.00E-01 4.16E 08 1.50E 08 7.993 06 1 CE 138 0.00E-01 0.00E-01 0.00E-01 0.005-01 0.00E-01 0.00E-01 0.005-01 )

BA 139 0.00E-01 0.00E-01 0.005-01 0.005-01 0.00E-01 0.00E-01 0.00E-01 BA 140 4.39E 07 3.84E 04 2.56E 06 0.00E-01 1.25E 04 2.29E 04 2.22E 07 ;

BA 141 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 BA 142 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 LA 140 5.665-02 1.98E-02 6.66E-03 0.00E-01 0.00E-01 0.00E-01 Lk 142 0.005-01 0.005-01 5.51E02l 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 CE 141 2.22E 04 1.11E 04 1.64E 03 0.00E-01 4.86E 03 0.005-01 1.38E 07 CE 143 3.18E-02 1.72E 01 2.50E-03 0.00E-01 7.23E-03 0.003-01 2.52E 02 CE 144 2.32E 06 7.2EE 05 1.24E 05 0.005-01 4.02E 05 0.00E-01 1.895 08 PR 143 3.34E 04 1.003 04 1.66E 03 0.005-01 5.43I 03 0.00E-01 3.60E 07 PR 144 0.005-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 ND 147 1.19E 04 9.60E 03 7.43E 02 0.00E-01 5.27E 03 0.005-01 1.52E 07 N 187 3.36E-02 1.99E-02 8.94E-03 0.00E-01 0.00E-01 0.005-01 2.80E 00 NP 239 4.26E-01 3.06E-02 2.15E-02 0.00E-01 8.84E-02 0.00E-01 2.26E 03 ]

s/s)

,H-.- .

3 Revision: 0 D OFFSITE DOSE CALCULATION MANUAL AP 07B-003

' O m Reference Use Page 167 of 188 U l ATTACHMENT A

, 0 (Page 163 of 184)

)N

4. \

i TABLE A.5-13 lM '

VEGETATION PATHWAY FACTOR

]\

M* MREN/YR PER pCI/SEC J ADULT (RI FACTORS) 0" !

NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI l H 3 0.00E-01 2.26E 03 2.26E 03 2.26E 03 2.26E 03 2.26E 03 2.26B 03 C 14 2.3BE 08 4.55E 07 4.55E 07 4.55E 07 4.55E 07 4.55E 07 4.55E 07 f NA 24 - 2.69E 05 2.69E 05 2.69E 05 2.69E 05 2.69E 05 2.69E 05 2.698 05 P 32 1.40E 09 8.735 07 5.42E 07 0.00E-01 0.00E-01 0.00E-01 1.58E 08 I l CR 51 0.00E-01 0.00E 01 4.64E 04 2.78E 04 1.02E 04 6.16E 04 1.17E 07

{ MN 54 0.00E-01 3.13E 08 5.97E 07 0.005-01 9.31E 07 0.00E-01 9.58E 08 l

j MN 56 0.00E-01 1.59E 01 2.82E 00 0.00E-01 2.02E 01 0.00E-01 5.08E 02 l

' FE 55 2.09E 08 1.45E 08 3.37E 07 0.00E-01 0.00E-01 8.06E 07 8.29E 07 i FE 59 1.26E 08 2.96E 08 1.14E 08 0.00E-01 0.00E-01 8.2BE 07 9.83E 08 CO 58 0.00E-01 3.07E 07 6.89E 07 0.00E-01 0.00E-01 0.00E-01 6.23E 08 CO 60 0.00E-01 1.67E 08 3.69E 08 0.00E-01 0.00E-01 0.00E-01 3.14E 09 NI- 63 1.04E 10 7.28E 08 3.495 08 0.00E-01 0.00E-01 0.00E-01 1.50E 08 NI 65 6.93E 01 9.01E 00 4.11E 00 0.00E-01 0.00E-01 0.00E-01 2.28E 02 a

CU 64 0.00E-01 9.21E 03 4.32E 03 0.00E-01 2.32E 04 0.005-01 7.85E 05 ZN 65 3.17E 08 1.01E 09 4.568 08 0.00E-01 6.75E 08 0.00E-01 6.36E 08 1

j EN 69 8.77E-06 1.68E-05 1.17E-06 0.00E-01 1.09E-05 0.005-01 2.523-06 i BR 83 0.00E-01 0.00E-01 3.11B 00 0.00E-01 0.00E-01 0.00E-01 4.48E 00 BR 84 0.00E-01 0.00E-01 2.49E-11 0.00E-01 0.00E-01 0.00E-01 1.96E-16 BR 85 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 RB 86 0.00E-01 2.19E 08 1.02E 08 0.00E-01 0.00E-01 0.00E-01 4.33E 07 RB 88 0.00E-01 3.47E-22 1.843-22 0.00E-01 0.00E-01 0.005-01 0.00E-01 a

RB 89 0.00E-01 1.41E-26 9.88E-27 0.00E-01 0.00E-01 0.00E-01 0.00E-01 SR 89 9.97E 09 0.00E-01 2.86E 08 0.00E-01 0.00E-01 0.00E-01 1.60E 09 ;

y SR 90 6.05E 11 0.00E-01 1.48E 11 0.00E-01 0.00E-01 0.00E-01 1.75E 10 SR 91 3.03E 05 0.00E-01 1.22E 04 0.00E-01 0.00E-01 0.00E-01 1.44E 06 SR 92 4.27E 02 0.00E-01 1.85E 01 0.00E-01 0.00E-01 0.00E-01 0.46E 03 Y 90 1.33E 04 0.00E-01 3.56E 02 0.005-01 0.0 01 0.00E-01 1.41E 08 i' Y 91M 5.24E-09 0.00E-01 2.03E-10 0.00E-01 0.00E-01 0.00E-01 1.545-08 Y 91 5.11E 06 0.00E-01 1.37E 05 0.00E-01 0.00E-01 0.00E-01 2.81E 09 Y 92 9.16E-01 0.00E-01 2.68E-02 0.005-01 0.00E-01 0.00E-01 1.60E 04 Y 93 1.74E 02 0.00E-01 4.81E 00 0.00E-01 0.00E-01 0.00E-01 5.52E 06 ZR 95 1.18E 06 3.77E 05 2.55E 05 0.00E-01 5.92E 05 0.00E-01 1.20E 09 ER 97 3.37E 02 6.81E 01 3.11E 01 0.00E-01 1.03E 02 0.00E-01 2.11E 07 NB 95 1.43E 05 7.93E 04 4.26E 04 0.00E-01 7.84E 04 0.00E-01 4.815 08 MO 99 0.00E-01 6.15E 06 1.175 06 0.00E-01 1.39E 07 0.00E-01 1.43E 07 TC 99M 3.10E 00 8.77E 00 1.12E 02 0.00E-01 1.33E 02 4.30E 00 5.19E 03

D Revision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 U~

m Reference Use Page 168 of 188

! CI l_ ATTACHMENT A lO (Page 164 of 184) lM OFFSITE DOSE CALCULATION MANUAL

\

TABLE A.5-13 (oost'd)

M VEGETATION PATHMhY FACTOR

\ M* MEEM/YR PER pCI/SEC A. ADULT (RI FACTORS)

.T NUCLIDE B00lE LIVER T BODY THYROID KIDNEY 1ARIG GI-LLI TC 101 8.34E-31 1.20E-30 1.185-29 0.00E-01 2.165-29 6.14E-31 0.00E-01 RU 103 4.76E 06 0.00E-01 2.05E 06 0.00E-01 1.82E 07 0.00E-01 5.56E 08-RU 105 5.39E 01 0.00E-01 2.135 01 0.00E-01 6.97E 02- 0.00E-01 3.30E 04 I

f i RU 106 1.93E 08 0.00E-01 2.44E 07 0.00E-01 3.725 08 0.00E-01 1.25E 10 f

AG 110M. 1.05E 07 9.75E 06 5.79E 06 0.00E-01 1.92E 07 0.00E-01 3.98E 09 TE 125M 9.66E 07 3.50E 07 1.29E 07 2.90E 07 3.93E 08 0.005-01 3.86E 08 l TE 127M 3.49E 08 1.25E 08 4.26E 07 8.935 07 1.42E 09 0.00E-01 1.17E 09 l

TE' 127 5.66E 03 2.03E 03 1.23E 03 4.20E 03 2.31E 04 0.00E-01 4.47E 05 TE . 129M 2.51E 08 9.38E 07 3.90E 07 8.63E 07 1.05E 09 0.00E-01 1.273 09 l TE 129 7.65E-04 2.87E-04 1.86E-04 5.87E-04 3.22E-03 0.00E-01 5.77E-04 I TE 131M 9.12E 05 4.46E 05 3.72E 05 7.07E 05 4.52E 06 0.00E-01 4.43E 07 TE 131 1.51E 15 6.32E-16 4.78E-16 1.24E-15 6.63E-15 0.00E-01 2.14E-16 TE 132 4.30E 06 2.785 06 2.61E 06 3.07E 06 2.68E 07 0.00E-01 1.325 08 I 130 3.95E 05 1.165 06 4.57E 05 9.81 07 1.81E 06 0.00E-01. 9.97E 05 I 131 8.085 07 1.16E 08 6.62E 07 3.79E 10 1.985 08 0.005-01 3.05E 07 I 132 5.775 01 1.54E 02 5.40E 01 5.40E 03. 2.465 02 0.00E-01 -2.90E 01 1 133 2.09E 06 3.63E 06 1.11E 06 5.33E 08 6.33E 06 0.00E-01 3.26E 06 I 134 9.69E-05 2.63E-04 9.42E-05 4.56E-03 4.195-04 0.00E=01 2.30E-07 l I 135 3.90E 04 1.02E 05 3.77E 04 6.74E 06 1.64E 05 0.00E-01 1.15E 05 l CS 134 4.67E 09 1.11E 10 9.08E 09 0.00E-01 3.59C 09 1.19E 09 1.94E 08 l

CS 136 4.205 07 1.66E 08 1.19E 08 0.00E-01 9.22E 07 1.26E 07 1.88E 07 i

( CS 137 6.36E 09 8.70E 09 5.703 09 0.00E-01 2.95E 09 9.81E 08 1.68E 08 CS 130 3.94E-11 7.78E-11 3.86E-11 0.00E-01 5.72E-11 5.655-12 3.32E-16 EA 139 2.90E-02 2.07E-05 8.50E-04 0.005-01 1.93E-05 1.17E-05 5.15E-02 EA 140 1.29E 08 1.61E 05 8.42E 06 0.00E-01 5.49E 04 9.25E 04 2.65E 08 BA 141 1.28E-21 9.64E-25 4.31E-23 0.00E-01 8.96E-25 5.472-25 6.01E-31 BA 142 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.005-01 0.00E-01 0.00E-01 LA 140 1.985 03 9.995 02 2.64E 02 0.00E-01 0.00E-01 0.00E-01 7.33E 07

. LA 142 1.42E-04 6.443-05 1.61E-05 0.00E-01 0.00E-01 0.00E-01 4.703-01 CE 141 1.975 05 1.33E 05 1.515 04 0.00E-01 6.195~04 0.00E-01 5.10E 08

. CE 143 9.98E 02 7.38E 05 8.17E 01 0.00E-01 3.25E 02 0.00E-01 2.76E 07

l. CE 144 3.29E 07 1.38E 07 1.77E 06 0.00E-01 8.16E 06 0.00E-01 1.11E 10

[ PR 143 6.26E 04 2.51E 04 3.11E 03 0.00E-01 1.45E 04 0.00E-01 2.74E 08 PR 144 3.13E-26 1.30E-26 1.59E-27 0.005-01 7.325-27 0.00E-01 0.00E-01 ND 147 3.36E 04 3.89E 04 2.32E 03 0.005-01 2.27E 04 0.00E-01 1.87E 08

,N 187 3.82E 04 3.20E 04 1.12E 04 0.00E-01 0.00E-01 0.00E-01 1.05E 07 i

NP 239 1.43E 03 1.40E 02 7.745 01 0.00E-01 4.30E 02 0.00E-01 2.88E 07 l l

(H

!3 3 Rsvision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 C1 y Reference Use Page 169 of 188 lc ATTACHMENT A

D' (Page 165 of 184)

\

l ~~ TABLE A.5-14 .

lM VEGETATION PATHNAY FACTOR l\ MI MtEM/YR PER pCI/SEC lJ TREN (RI FAC'IORS) '

'O' NUCLIDE BONE LIVER T BODY THYROID KIDNEY LIBIG GI-LLI i

H 3 0.00E-01 2.59E 03 2.59E 03 2.59E 03 2.59E 03 2.59E 03 2.59E 03 l C 14 3.69E 08 7.38E 07 7.38E 07 7.38E 07 7.38E 07 7.38E 07 7.38E 07 i L

NA 24 2.39E 05 2.39E 05 2.39E 05 2.39E 05 2.39E 05 2.39R 05 2.395 05 I

l P 32 1.61E 09 9.96E 07 6.23E 07 0.00E-01 0.00E-01 0.003-01 1.35E 08 )

CR 51 0.00E-01 0.005-01 6.17E 04 3.43E 04 1.35E 04 8.815 04 1.04E 07 j MN 54 0.00E-01 4.54E 08 9.01E 07 0.00E-01 1.36E 08 0.00E-01 9.32E 08 I

MN 56 0.00E-01 1.44E 01. 2.55E 00 0.00E-01 1.825 01 0.00E-01 9.45E 02

! FE 55 3.25E 08 2.31E 08 5.38E 07 0.00E-01 0.00E-01 1.46E 08 9.98E 07 FE 59 1.79E 08 4.18E 08 1.625 08 0.00K-01 0.00E-01 1.32E 08 9.90E 08 CO 58 0.00E-01 4.362 07 1.01E 08 0.00E-01 0.00E-01 0.00E-01 6.01E 08 CO 60 0.00E-01 2.49E 08 5.60E 08 0.00E-01 0.00?-01 0.00E-01 3.24E 09 NI 63 1.61E 10 1.13E 09 5.44E 08 0.00E-01 0.00E-01 0.00E-01 1.81E 08 NI 65 6.455 01 8.245 00 3.76E 00 0.005-01 0.00E-01 0.00E-01 4.47E 02 CU 64 0.00E-01 8.34E 03 3.92E 03 0.005-01 2.11E 04 0.00E-01 6.47E 05 EN 65 4.24E 08 1.47E 09 6.86E 08 0.00E-01 9.42E 08 0.00E-01 6.23E 08 EN 69 8.21E-06 1.56E 05 1.108-06 0.00E-01 1.02E-05 0.00E-01 2.88E-05 BR 83 0.00E-01 0.00E-01 2.92E 00 0.00E-01 0.00E-01 0.00E-01 5.08E-16 BR 84 0.00E-01 0.00E-01 2.37E-11 0.00E-01 0.00E-01 0.00E-01 3.14E-28 BR 85 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.005-01 0.00E-01 RB 86 0.00E-01 2.74E 08 1.29E 08 0.00E-01 0.00E-01 0.00E-01 4.05E 07 j RB 88 0.00E-01 3.21E-22 1.71E-22 0.00E-01 0.00E-01 0.00E-01 2.75E-29 l

l RB 89 0.00E-01 1.26E-26 8.94E-27 0.005-01 0.00E-01 0.00E-01 1.94E-35 SR 89 1.51E 10 0.00E-01 4.34E 08 0.00E-01 0.00E-01 0.00E-01 1.80E 09 SR 90 7.51E 11 0.00E-01 1.85E 11 0.00E-01 0.005-01 0.00E-01 2.11E 10 SR 91 2.8*E J 05 0.00E-01 1.13E 04 0.00E-01 0.00E-01 0.00E-01 1.28E 06 l SR 92 3.98E 02 0.00E-01 1.70E 01 0.00E-01 0.00E-01 0.00E-01 1.01E 04 Y 90 1.24E 04 0.00E-01 3.34E 02 0.00E-01 0.00k-01 0.00E-01 1.02E 08 Y 91M 4.88E-09 0.00E-01 1.87E-10 0.00E-01 0.00E-01 0.00E-01 2.30E-07 Y 91 7.84E 06 0.00E-01 2.10E 05 0.00E-01 0.003-01 0.00E-01 3.21E 09 Y 92 8.61E-01 0.00E-01 2.49E-02 0.00E-01 0.005-01 0.00E-01 2.36E 04 i

Y 93 1.63E 02 0.00E-01 4.47E 00 0.005-01 0.00E-01 0.00E-01 4.99E 06 l ER 95 1.72E 06 5.44E 05 3.74E 05 0.00E-01 7.99E 05 0.00E-01 1.25E 09

' ER 97 3.12E 02 6.18E 01 2.85E 01 0.005-01 9.375 01 0.00E-01 1.67E 07 1

j NB 95 1.93E 05 1.07E 05 5.88E 04 0.00E-01 1.04E 05 0.00E-01 4.57E 08

MJ 99 0.00E-01 5.655 06 1.08E 06 0.00E-01 1.29E 07 0.00E-01 1.01E 07 TC 99M 2.74E 00 7.64E 00 9.90E 01 0.005-01 1.14E 02 4.24E 00 5.02E 03

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I ATTACHMENT A i i

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g OFFSITE DOSE CALCULATION MANUAL I 1

- l TABLE 1.5-14 (oost'd)

M

VEGETATION PATHNAY FACTOR

! 8 '

\ M MREN/YR PER kCI/SEC '

j ,g TEEN (RI FAC'!VRS)

G" NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI l TC 301 7.76E-31 1.10E-30 1.08E-29 0.00E-01 2.00E-29 6.72E-31 0.00E-01 l RU 103 6.81E 06 0.00E-01 2.91E 06 0.00E "1 2.40E 07 0.00E-01 5.69E 08 RU 105 S.01E 01 0.00E-01 1.94E 01 0.003-01 6.32E 02 0.00E-01 4.04E 04 l RU 106 3.09E 08 0.00E-01 3.90E 07 0.00E-(1 5.97E 08 0.00E-01 1.48E 10 AG 110M 1.52E 07 1.43E 07 8.72E 06 0.00E-01 2.74E 07 0.00E-01 4.03E 09 l TE 125M 1.48E 08 5.34E 07 1.98E 07 4.14E 07 0.00E-01 0.00E-01 4.393 08 TE 127M 5.52E 08 1.96E 08 6.56E 07 1.32E 03 2.24E 09 0.00E-01 1.37E 09 TB 127 5.34E 03 1.895 03 1.15E 03 3.68E 03 2.16E 04 0.00E-01 4.12E 05 '

TE 129M 3.62E 08 1.34E 08 5.73E 07 1.17E 08 1.51E 09 0.00E-01 1.36E 09 TE 129 7.16E-04 2.67E-04 1.74E-04 5.12E-04 3.01E-03 0.00E-01 3.92E-03 TE 131M 8.44E 05 4.05E 05 3.38E 05 6.09E 05 4.228 06 0.00E-01 3.25E 07 TE 131 1.41E-14 5.80E-16 4.40E-16' 1.08E-15 6.15E-15 0.00E-01 '1.15E-16 TE 132 3.91E 06 2.48E 06 2.33E 06 2.61E 06 2.37E 07 0.C0E-01 7.84E 07 I 130 3.51E 05 1.02E 06 4.05E 05 8.285 07 1.56E 06 0.00E-01 7.80E 05 I 131 7.69E 07 1.08E 08 5.78E 07 3.14E 10 1.85E 08 0.005-01 2.13E 07 l

l I 132 5.20E 01 1.36E 02 4.89E 01 4.59E 03 '2.14E 02 0.00E-01 5.93E 01 l

I 133 1.94E 06 3.29E 06 1.005 06 4.59E 08 5.77E 06 0.00E-01 2.49E 06 I 134 8.76E-05 2.325-04 8.34E-05 3.87E-0* 3.66E-04 0.00E-01 3.065-06 I 135 3.52E 04 9.07E 04 3.36E 04 5.84E 06 1.43E 05 0.00E-01 1.01E 05 CS 134 7.10E 09 1.67E 10 7.75E 09 0.00E-01 5.31E 09 2.03E 09 2.08E 08 I CS 136 4.28E 07 1.68E 08 1.13E 08 0.00E-01 9.16E 07 1.44E 07 1.35E 07 CS 137 1.01E 10 1.35E 10 4.69E 09 0.00E-01 4.59E 09 1.78E 09 1.92E 08 i CS 138 3.64E-11 6.98E-11 3.495-11 0.00E-01 5.15E-11 6.00E-12 3.17E-14 BA 139 2.73E-02 1.92E-05 7.96E-04 0.00E-01 1.81E-05 1.32E-05 2.44E-01

. BA 140 1.38E 08 1.69E 05 8.91E 06 0.00E-01 5.74E 04 1.14E 05 2.13E 08 I

BA 141 1.19E-21 8.90E-25 3.98E-23 0.00E-01 8.27E-25 6.10E-25 2.54E-27 BA 142 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.005-01 0.00E-01 l

LA 140 1.81E 03 8.89E 02 2.37E 02 0.00E-01 0.00E-01 0.00E-01 5.11E 07 LA 142 1.30E-04 5.78E-05 1.44E-05 0.00E-01 0.00E-01 0.00E-01 1.76E 00 l CE 141 2.83E 05 1.89E 05 2.175 04 0.00E-01 8.90E 04 0.00E-01 5.41E 08 CE 143 9.33E 02 6.79E 05' 7.58E 01 0.00E-01 3.04E 02 0.00E-01 2.04E 07 CE 144 5.27E 07 2.18E 07 2.83E 06 0.00E-01 1.30E 07 0.005-01 1.33E 10 PR 143 7.01E 04 2.80E 04 3.49E 03 0.00E-01 1.63E 04 0.00E-01 2.31E 08 I PR 144 2.93E-26 1.20E-26 1.49E-27 0.00E-01 6.88E-27 0.00E-01 3.23E-29 i ND 147 3.66E 04 3.98E 04 2.38E 03 0.00E-01 2.34E 04 0.00E-01 1.44E 08 N 187 3.56E 04 2.90E 04 1.02E 04 0.00E-01 0.005-01 0.00E-01 7.84E 06 NP 239 1.39E 02 1.31E 02 7.26E 01 0.00E-01 4.10E 02 0.00E-01 2.10E 07 l

l

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ATTACHMENT A

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l-- TABLE A.5-15 M- VEGETATION PATIDIAY FACTOR

!\ N' MREM /YR 'PER SCI /SEC g CHILD (RI FACTORS)

NUCLIDE B00fE LIVER T BODY THYROID KIDNEY LUNG GI-LLI

. II 3 0.00E-01 4.01E 03 4.01E 03 4.01B 03 4.01E 03 4.01E 03 4.01E 03 C 14 8.89E 08 1.78E 08 1.78E 08 1.78E 08 1.78E 08 1.78E 08 1.78E 08 NA 24 3.73E 05 3.73E 05 3.73E 05 3.73E 05 3.73E 05 3.73E 05 3.73E 05 P 32 3.37E 09 1.58E 08 1.30E 08 0.00E-01 0.00E-01 0.00E-01 CR 51 0.00E-01 0.00E-01 6.50E 04 9.30E07l

[ 1.17E 05 1.78E 04 1.19E 05 6.21E 06 l MN 54 0.00E-01 6.65E 08 1.77E 08 0.00E-01 1.86E 08 0.00E-01 S.58E 08 l

MN 56 0.00E-01 1.88E 01 4.24E 00 0.00E-01 2.:s sE 01 0.00E-01 2.725 03 FE 55 0.003 00 4.24E 08 1.31E 08 0.00E-01 0.00E-01 2.40E 00 7.865 07 l FE 59 3.975 08 6.43E 08 3.20E 08 0.00E-01 0.00E-01 1.868 08 6.69E 08 l l

CO 58 0.00E-01 6.44E 07 1.97E 08 0.00E-01 0.00E-01 0.00E-01 3.765 08 CO 60 0.00E-01 3.785 08 1.12E 09 0.00E-01 0.00E-01 0.00E-01 2.10E 09 NI 63 3.95E 10 2.11E 09 1.34E 09 0.00E-01 0.00E-01 0.00E-01 1.42E 08 NI 65 1.18E 02 1.11E 01 6.51E 00 0.00E-01 0.00E-01 0.00E-01 1.37E 03 t CU 64 0.00E-01 1.10E 04 6.65E 03 0.00E-01 2.66E 04 0.005-01 5.16E 05 EN 65 8.12E 08 2.16E 09 1.35E 09 0.00E-01 1.36E 09 0.00E-01 3.80E 08 l

l EN 69 1.51E-05 2.19E-05 2.02E-06 0.00E-01 1.33E-05 0.00E-01 1.38E-03 BR 83 0.00E-01 0.00E-01 5.30E 00 0.00E-01 0.00E-01 0.00E-01 3.145-17

( BR 84 0.00E-01 0.00E-01 3.85E-11 0.00E-01 0.00E-01 0.00E-01 1.94E-28 l

BR 85 0.005-01 0.00E-01 0.00E-01 0.00E-01 0.005-01 0.00E-01 0.00E-01 l RB 86 0.00E-01 4.52E 08 2.78E 08 0.00E-01 0.00E-01 0.00E-01 2.91E 07 l

RB 88 0.00E-01 4.43E-22 3.08E-22 0.00E-01 0.00E-01 0.00E-01 2.17E-23 I

l RB 89 0.00E-01 1.67E-26 1.48E-26 0.00E-01 0.005-01 0.005-01 1.45E-28 SR 89 3.60E 10 0.00E-01 1.03E 09 0.00E-01 0.00E-01 0.00E-01 1.39E 09 SR 90 1.24E 12 0.00E-01 3.15E 11 0.00E-01 0.00E-01 0.00E-01 1.67E 10 l SR 91 5.21E 05 0.00E-01 1.978 04 0.00E-01 0.00E-01 0.00E-01 1.15E 06 I SR 92 7.29E 02 0.00E-01 2.92E 01 0.00E-01 0.00E-01 0.00E-01 1.38E 04 Y 90 2.30E 04 0.00E-01 6.17E 02 0.00E-01 0.00E-01 0.00E-01 6.56B 07 l Y 91M 8.95E-09 0.00E-01 3.26E-10 0.00E-01 0.00E-01 0.00E-01 1.75E-05 Y 91 1.865 07 0.00E-01 4.99E 03 0.00E-01 0.00E-01 0.00E-01 2.48E 09 Y 92 1.59E 00 0.00E-01 4.54E-02 0.00E-01 0.00E-01 0.00E-01 4.58E 04 i

I Y 93 3.01E 02 0.00E-01 8.26E 00 0.00E-01 0.00E-01 0.00E-01 4.48E 06 2R 95 3.865 06 8.49E 05 7.56E 05 0.00E-01 1.22E 06 0.005-01 8.85E 08 1 ER 97 5.70E 02 8.24E 01 4.86E 01 0.00E-01 1.18E 02 0.00E-01 1.25E 07 i

NB 95 4.11E 05 1.60E 05 1.14E 05 0.00E-01 1.50E 05 0.00E-01 2.96E 08 MO 99 0.00E-01 7.71E 06 1.91E 06 0.005-01 1.65E 07 0.00E-01 6.38E 06 TC 99M 4.71E 01 9.24E 00 1.51E 02 0.00E-01 1.34E 02 4.69E 00 5.26E 03 l s/s.1 m

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

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i ATTACHMENT A

)0

' M (Page 168 of 184) i OFFSITE DOSE CALCULATION MANUAL i i \

l TABLE A.5-15 (oost'd)

M ' VEGETATION PATHWAY FACTOR .

\ M' MREM /YR PER pC1/8EC f) CHILD (RI FACTORS) l O* s NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI ,

l TC 101 1.43E-30 1.495-30 1.895-29 0.00E-01 2.55E-29 7.90E-31 4.75E-30 RU 103 1.53E 07 0.00E-01 5.88E 06 0.00E-01 3.85E 07 0.00E-01 3.96E 0A RU 105 9.17E 01 0.00E-01 3.33E 01 0.00E-01 8.06E 02 0.00E-01 5.99E 04 !

l RU 106 7.45E 08 0.00E-01 9.30E 07 0.00E-01 1.01E 09 0.00E-01 1.16E 10 AG 110M 3.21E 07 2.17E 07 1.73E 07 0.00E-01 4.04E 07 0.00E-01 2.58B 09 '

TE 125M 3.51E 08 9.50E 07 4.67E 07 9.84E 07 0.00E 01 0.00E-01 3.38E 08 l

TE 127M 1.32E 09 3.56E 08 1.57E 08 3.16E 08 3.77E 09 0.00E-01 1.07E 09 TE 127 9.85E 03 2.66E 03 2.11E 03 6.82E 03 2.80E 04 0.00E-01 3.85E 05 TE 129M 8.41E 08 2.35E 08 1.30E 08 2.71E 08 2.47E 09 0.00E-01 1.03E 09 l l TE 129 1.33E-03 3.70E-04 3.15E-04 9.46E-04 3.88E-03 0.00E-01 8.25E-02

) TE 131M 1.54E 06 5.33E 05 5.68E 05 1.10E 06 5.16E 06 0.00E-01 2.16E 07 TE 131 2.59E-15 7.90E-16 7.71E-16 1.98E-15 7.84E-15 0.00E-01 1.36E-14 TE 132 7.00E 06 3.10E 06 -3.74E 06 4.51E 06 2.883 07 0.005-01 3.12E 07 I 130 6.16E 05 1.24E 06 6.41E 05 1.37E 08 1.86E 06 0.00E-01 5.82E 05 I 131 1.43E 08 1.445 08 8.17E 07 4.76E 10 2.36E 08 0.00E-01 1.28E 07 l

I 132 9.235 01 1.70E 02 7.80E 01 7.87E 03 2.60E 02 0.003-01 2.00E 02 I 133 3.53E 06 4.37E 06 1.65E 06 8.123 08 7.28E 06 0.003-01 1.76E 06 I 134 1.56E-04 2.89E-04 1.33E-04 6.65E-04 4.42E-04 0.00E-01 1.92E-04 i

l I 135 6.26E 04 1.13E 05 5.33E 04 9.98E 06 1.73E 05 0.005-01 8.59E 04 l CS 134 1.60E 10 2.63E 10 5.55E 09 0.00E-01 8.15E 09 2.93E 09 1.42E 08 CS 136 8.04E 07 2.21E 08 1.43E 08 0.005-01 1.18E 08 1.76E 07 7.773 06 CS 137 2.39E 10 2.295 10 3.38E 09 0.00E-01 7.46E 09 2.68E 09 1.43E 08 C8 138 6.61E-11 9.20E-11 5.83E-11 0.00E-01 6.47E.11 6.96E-12 4.24E-11 RA 139 5.04E-02 2.69E-05 1.465-03 0.00E-01 2.355 05 1.58E-05 2.91E 00 BA 140 2.77E 08 2.43E 05 1.62E 07 0.00E-01 7.90E 04 1.45E 05 1.40E 08 BA 141 2.20E-21 1.23E-24 7.16E-23 0.00E-01 1.07E-24 7.24E 24 1.2SE-21 RA 142 0.005-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 LA 140 3.25E 03 1.14E 03 3.83E 02 0.00E-01 0.00E-01 0.00E-01 3.17E 07 LA 142 2.36E-04 7.51E-05 2.35E-05 0.00E-01 0.00E-01 0.00E-01 1.49E 01 CE 141 6.56E 05 3.27E 05 4.86E 04 0.00E-01 1.43E 05 0.00E-01 4.08E 08 l CE 143 1.72E 03 9.31E 05 1.35E 02 0.00E-01 3.913 02 0.005-01 1.36E 07 CE 144 1.27E 08 3.98E 07 6.78E 06 0.00E-01 2.21E 07 0.00E-01 1.045 10 PR 143 1.46E 05 4.38E 04 7.23E 03 0.00E-01 2.37E 04 0.00E-01 1.57E 08 PR 144 5.44E-26 1.68E-26 2.74E-27 0.00E-01 8.90E-27 0.00E-01 3.62E-23 i ND 147 7.24E 04 5.86E 04 4.54E 03 0.00E-01 3.225 04 0.00E-01 9.29E 07 W 187 6.47E 04 3.83E 04 1.72E 04 0.00E-01 0.00E-01 0.00E-01 5.38E 07 NP 239 2.56E 03 1.84E 02 1.29E 02 0.00E-01 5.31E 02 0.00E-01 1.36E 07 9/93

H }

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ATTACHMENT A O (Page 169 of 184)

M OFFSITE DOSE CALCULATION MANUAL I

\

TABLE A.5-16 l M GROUND PLANE PATHWAY FACTOR

\ M' MREM /YR PER pCI/SEC !

.D (RI FACTOR)

I j H-3 0.00E 00 Y-91M 1.00E 05 CS-134 6.86E 09 l C-14 0.00E 00 Y-91 1.07E 06 CS-136 1.49E 08 NA-24 1.19E 07 Y-92 1.80E 05 CS-137 1.03E 10 l P-32 0.002 00 Y-93 1.85E 05 CS-138 3.59E 05 l CR-51 4.66E 06 ZR-95 2.45E 08 BA-139 1.06E 05 l MN-54 1.398 09 ZR-97 2.96E 06 BA-140 2.05E 07 !

MN-56 9.03E 05 NB-95 1.37E 08 BA-141 4.18E 04 l FE-55 0.00E 00 MO-99 3.99E 06 BA-142 4.49E 04 l FE-59 2.73E 08 TC-99M 1.84E 05 LA-140 1.9 E 07 l TC-101 2.04E 04 {

CO-58 3.79E 08 RU-103 1.0BE 08 IA-142 7.37E 05 i CO-60 2.15E 10 RU-105 6.36E 05 CE-141 1.37E 07 NI-63 0.00E 00 RU-106 4.21E 08 CE-143 2.31E 06 )

NI-65 3.02E 05 AG-110M 3.44E 09 CE-144 6.96E 07 I CU-64 6.07E 05 TE-125M 1.55E 06 PR-143 0.00E 00 ZN-65 7.46E 08 TE-127M 9.17E 04 PR-144 1.83E 03 ZN-69 0.00E 00 TE-127 2.98E 03 ND-147 8.46E 06 BR-83 4.87E 03 TE-129M 1.98E 07 W-187 2.36E 06 BR-84 2.03E 05 TE-129 2.62E 04 NP-239 1.71E 06 BR-85 0.00E 00 TE-131M 8.03E 06 RB-86 8.99E 06 TE-131 2.92E 04 l RB-88 3.31E 04 TE-132 4.23E 06 l RB-89 1.21E 05 I-130 5.51E 06 SR-89 2.16E 04 I-131 1.72E 07 SR-90 0.00E 00 I-132 1.25E 06 SR-91 2.14E 06 I-133 2.45E 06 SR-92 7.77E 05 I-134 4.47E 05 l Y-90 4.49E 03 I-135 2.53E 06 l S/9J

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fil Reference Use Page 174 of 188 O

ATTACHMENT A O (Page 170 of 184)

'M OFFSITE DOSE CALCULATION MANUAL

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.ABLE A.5-17 M '

GRASS-00AT-MILK PATHNAY FACTOR 8

\ M MREM /YR PER pCI/SEC j ADULT NUCLIDE BONE LIVER T BODY THYROID KIDNEY IAJNG GI-LLI H 3 0.00E-01 1.56E 03 1.56E 03 1.56E 03 1.56E 03 1.56E 03 1.56E 03 C 14 2.63E 08 5.27E 07 5.27E 07 5.27E 07 5.27E 07 5.27E 07 5.27E 07 NA 24 2.93E 05 2.93E 05 2.93E 05 2.93E 05 2.93E 05 2.93E 05 2.93E 05 P 32 2.05E 10 1.27E 09 7.93E 08 0.00E-01 0.005-01 0.00E-01 2.31E 09 CR 51 0.00E-01 0.00E-01 3.43E 03 2.0$E 03 7.55E 02 4.55E 03 8.62E 05 MN 54 0.00E-01 1.01E 06 1.93E 05 0.00E-01 3.00E 05 0.00E-01 3.09E 06 MN 56 0.00E-01 4.99E-03 8.85E-04 0.00E-01 6.34E-03 0.00E-01 1.59E-01 FE 55 3.26E 05 2.25E 05 5.26E 04 0.00E-01 0.00E-01 1.26E 05 1.29E 05 FE 59 3.86E 05 9.07E 05 3.48E 05 0.00E-01 0.00E-01 2.54E 05 3.02E 06 CO 58 0.00E-01 5.66E 05 1.27E 06 0.00E-01 0.00E-01 0.00E-01 1.15E 07 00 60 0.00E-01 1.97E 06 4.34E 06 0.00E-01 0.00E-01 0.00E-01 3.70E 07 NI- 63 8.07E 08 5.65E 07 2.71E 07 0.00E-01 0.00E-01 0.00E-01 1.175 07 NI 65 5.56E-02 7.22E-03 3.30E-03 0.00E-01 0.00E-01 0.00E-01 1.83E-01 CU 64 0.00E-01 2.665 03 1.25E 03 0.005-01 6.70E 03 0.00E-01 2.27E 05 ZN 65 1.65E 08 5.24E 08 2.375 08 0.00E-01 3.50E 08 0.00E-01 3.30E 08 EN 69 6.27E-13 1.20E-12 8.34E-14 0.00E-01 7.79E-13 0.00E-01 1.80E-13 BR 83 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 BR 84 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 BR 85 0.00E-01 0.005-01 0.00E-01 0.00E-01 0.005-01 0.00E-01 0.00E-01 RB 86 0.00E-01 3.11E 08 1.45E 08 0.00E-01 0.00E-01 0.00E-01 6.14E 07 RB 88 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 RB 89 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 SR 89 3.05E 09 0.00E-01 8.75E 07 0.00E-01 0.005-01 0.00E-01 4.89E 08 SR 90 9.83E 10 0.00E-01 2.41E 10 0.00E-01 0.00E-01 0.00E-01 2.84E 09 SR 91 6.02E 04 0.00E-01 2.43E 03 0.00E-01 0.00E-01 0.00E-01 2.87E 05 SR 92 1.03E 00 0.00E-01 4.45E-01 0.00E-01 0.00E-01 0.00E-01 2.04E 01 Y 90 8.49E 00 0.00E-01 2.28E-00 0.005-01 0.00E-01 0.00E-01 9.00E 04 Y 91M 7.24E-21 0.00E-01 2.80E-22 0.00E-01 0.00E-01 0.00E-01 2.13E-20 Y 91 1.03E 03 0.00E-01 2.76E 01 0.00E-01 0.00E-01 0.00E-01 5.67E 05 Y 92 6.71E-06 0.00E-01 1.96E-07 0.00E-01 0.00E-01 0.00E-01 1.18E-01 Y 93 2.80E-02 0.00E-01 7.73E-04 0.00E-01 0.00E-01 0.00E-01 8.87E 02 ZR 95 1.13E 02 3.63E 01 2.46E 01 0.00E-01 5.70E 01 0.00E-01 1.15E 05 ZR 97 5.20E-02 1.05E-01 4.80E-03 0.00E-01 1.58E-01 0.00E-01 3.25E 03 NB 95 9.91E 03 5.51E 03 2.96E 03 0.00E-01 5.45E 03 0.00E-01 3.35E 07 MO 99 0.00E-01 2.97E 06 5.65E 05 0.00E-01 6.73E 06 0.00E-01 6.89E 06 TC 99M 3.99E-01 1.13E 00 1.44E 01 0.00E-01 1.71E 01 5.53E-01 6.67E 02

2 Revision: 0 3 . OFFSITE DOSE CALCUI.ATION MANUAL AP 07B-003 Raference Use Page 175 of 188 l ATTACHMENT A o- (Page 171 of 184) i lN OFFSITE DOSE CALCULATION MANUAL l

\-

So TABLE A.5-17 (coat'd)

M GRASS-OOAT-MILK PATHNAY FACTOR,

!\ . 8 M MREN/YR PER pCI/SEC J ADULT tr NUCLIDE BONE LIVER T BODY THYROID EIDNEY LUNG GI-LLI l TC 101 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.005-01 0.00E-01 0.00E-01

'RU 103 1.225 02 0.00E-01 5.26E 01 0.00E-01 4.66E 02 0.00E-01 1.43E 04 RJ 105 1.03E-04 0.00E-01 4.07E-05 0.00E-01 1.33E-03 0.00E-01 6.30E-02 RU 106 2.45E 03 0.00E-01 3.10E 02 0.00E-01 4.73E 03 0.00E-01 1.58E 05 f AG 110M 6.99E 06 6.46E 06 3.84E 06 0.00E-01 1.27E 07 0.005-01 2.64E 09 TE 125M 1.95E 06 7.08E 05 2.62E 05 5.8BE 05 7.95E 06 0.00E-01 7.81E 06 TE 127M 5.49E 06 1.96E 06 6.70E 05 1.40E 06 2.233 07 0.00E-01 1.84I 07 TE 127 7.84E 01 2.82E 01 1.70E 01 5.81E 01 3.19E 02 0.00E-01 6.19E 03 {

TE 129M 7.22E 06 2.693 06 1.14E 06 2.48E 06 3.02E 07 0.00E-01 3.64E 07 j 1

l TE 129 3.41E-11 1.28E-11 8.315-12 2.62E-11 1.43E-10 0.00E-01 2.57E-11 l TE 131M 4.33E 04 2.12E 04 1.77E 04 3.36E 04 2.15E 05 0.00E-01 2.10E 06

! TE 131 4.40E-34 1.84E-34 1.39E-34 3.62E-34 1.93E-33 0.00E-01 6.23E-35 i

TE 132 2.88E 05 1.86E 05 1.75E 05 2.06E 05 1.80E 06 0.00E-01 8.82E 06 I 130 5.04E 05 1.495'06 5.87E 05 1.26E 08 2.32E 06 0.00E-01 1.28E 06-I 131 3.55E 08 5.00E 08 2.915 08 1.67E 11 0.71E 08 0.00E-01 1.345 08 I 132' 1.985-00 5.29E-00 1.85E-00 1.85E 01 8.43E-00 0.00E-01 9.94E-01 I 133 4.65E 06 8.085 06 2.465 06 1.19E 09 1.41E 07 0.005-01 7.26E 06 I 134 2.44E-12 6.63E-12 2.37E-12 1.153-10 1.05E 0.00E-01 5.78E-15 I 135 1.54E 04 4.04E 04 1.49E 04 2.665 06 6.48E 04 0.00E-01 4.56E 04 CS 134 1.70E 10 4.04E 10 3.30E 10 0.00E-01 1.31E 10 4.34E 09 7.06E 08 CS 136 7.83E 08 3.095 09 2.23E 09 0.00E-01 1.72E 09 2.36E 08 3.51E 08 CS 137 2.21E 10 3.03E 10 1.98E 10 0.00E-01 1.03E 10 3.42E 09 5.86E 08

j. C8 138 2.755-23 5.43E-23 3.99E-23 3.94E-24 2.69E-23 0.00E-01 2.32E-28 ;

) BA 139 5.40E-09 3.90E-12 1.60E-10 0.00E-01 3.65E-12 2.21E-12 9.71E-09 i

l BA 140 3.23E 06 4.05E 03 2.11E 05 0.005-01 1.388 03 2.32E 03 6.64E 06 i RA 141 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 BA 142 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 LA 140 5.43E-01 2.73E-01 7.23E-02 0.005-01 0.005-01 0.005-01 2.01E 04 LA 142 1.13E-12 5.12E-13 1.28E-13 0.00E-01 0.00E-01 0.00E-01 3.745-09 CE 141 5.81I 02 3.93I 02 4.46E 01 0.00E-01 1.83E 02 0.00E-01 1.50E 06 i

CE 143 4.99E 00 3.69E 03 4.08E-00 0.00E-01 1.62E 00 0.00E-01 1.38E 05

) CE 144 4.29E 04 1.79E 04 2.30E 03 0.00E-01 1.06E 04 0.00E-01 1.45E 07 PR 143 1.90E 01 7.60E 00 9.395-00 0.00E-01 4.395 00 0.00E-01 8.30E 04

{

i

\ PR 144 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 ND 147 1.14E 01 1.31E 01 7.85E-01 0.00E-01 7.67E 00 0.00E-01 6.30E 04

$ W 187 7.875 02 6.58E 02 2.30E 02 0.00E-01 0.00E-01 0.00E-01 2.16E 05 NP 239 4.415-01 4.33E-02 2.39E-02 0.00E-01 1.35E-01 0.00E-01 8.89E 03

@ Revision: 0 g

l OFFSITE DOSE CALCULATION MANUAL AP 07B-003 g Reference Use Page 176 of 188 ATTACHME.NT A

@ (Page 172 of 184)

N OFFSITE DOSE CALCULATION MANUAL A i i

A TABLE A.5-18 Q

GRASS-CCAT-MILK PATHWAY FACTOR 8

A M MREM /YR PER pCI/SEC j TEEN NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI 1

H 3 0.00E-01 2.03E 03 2.03E 03 2.03E 03 2.03E 03 2.038 03 2.03H 03 C 14 4.86E 08 9.72E 07 9.72E 07 9.72E 07 9.72E 07 9.72E 07 9.72E 07 luk 24 5.11E 05 5.11E 05 5.11E 05 S.11E OS b.11E 05 5.11E 05 5.11E 05 P 32 3.78E 10 2.34E 09 1.47E 09 0.00E-01 0.00E-01 0.00E-01 3.18E 09 CR 51 0.00E-01 0.00E-01 5.99E 03 3.33E 03 1.31E 03 8.55E 03 1.01E 06 MN 54 0.005-01 1.68E 06 3.34E 05 0.00E-01 5.02E 05 0.00E-01 3.45E 06 MN 56 0.00E-01 8.858-04 1.57E-04 0.00E-01 1.12E-03 0.00E-01 5.82E-02 FE 55 5.79E 05 4.10E 05 9.57E 04 0.00E-01 0.00E-01 2.60E 05 1.78E 05 PE 59 6.74E 05 1.57E 06 6.07E 05 0.00E-01 0.00E-01 4.96E 05 3.72E 06 CO 58 0.00E-01 9.52E 05 2.19E 06 0.00E-01 0.00E-01 0.00E-01 1.31E 07 CO 60 0.00E-01 3.34E 06 7.52E 06 0.00E-01 0.00E-01 0.00E-01 4.35E 07 NI 63 1.42H 09 1.008 08 4.81E 07 0.00E-01 0.00E-01 0.00E-01 1.59E 07 NI 65 1.02E-01 1.30E-02 5.92E-03 0.00E-01 0.00E-01 0.00E-01 7.0$E-01 l CU 64 0.00E-01 4.74E 03 2.23E 03 0.00E-01 1.20E 04 0.00E-01 3.67E 05 ZN 65 2.53E 08 8.78E 08 4.093 08 0.00E-01 5.62E 08 0.00E-01 3.723 08 n

l ZN 69 1.15E-12 2.20E-12 1.54E-13 0.00E-01 1.44E-12 0.00E-01 4.05E-12 i BR 83 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 l BR 84 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 BR 85 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 l

RB 86 0.00E-01 5.67E 08 2.67E 08 0.00E-01 0.00E-01 0.00E-01 8.40E 07 '

RB 88 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 RB 89 0.00E-01 0.00E-01 0.00E-01 0.00F-01 0.00E-01 0.00E-01 0.00E-01 SR 89 5.62E 09 0.00E-01 1.61E 08 0.003-01 0.00E-01 0.00E-01 6.69E 08 SR 90 1.39E 11 0.00E-01 3.43E 10 0.002-01 0.00E-01 0.00E-01 3.90E 09 SR 91 1.11E 05 0.00E-01 4.40E 03 0.00E-01 0.00E-01 0.00E-01 5.02E 05 SR 92 1.88E 00 0.00E-01 8.02E-02 0.00E-01 0.00E-01 0.00E-01 4.80E 01 Y 90 1.56E 01 0.00E-01 4.20E-00 0.00E-01 0.00E-01 0.00E-01 1.29E 05 Y 91M 1.33E-20 0.00E-01 5.07E 22 0.00E-01 0.00E-01 0.00E-01 6.26E-19 Y 91 1.90E 03 0.00E-01 5.088 01 0.00E-01 0.00E-01 0.00E-01 7.77E 05 Y 92 1.24E-05 0.00E-01 3.59E-07 0.0CE-01 0.00E-01 0.00E-01 3.40E-01 l Y 93 5.16E-02 0.00E-01 1.41E-03 0.00E-01 0.00E-01 0.00E-01 1.58E 03 ZR 95 1.98E 02 6.25E 01 4.30E 01 0.00E-01 9.18E 01 0.00E-01 1.44E 05 ZR 97 9.47E-02 1.87E-02 8.63E-03 0.00E-01 2.84E-02 0.00E-01 5.07E 03 NB 95 1.69E 04 9.37E 03 5.16E 03 0.00E-01 9.09E 03 0.00E-01 4.01E 07 i

MO 99 0.00E-01 5.37E 06 1.02E 06 0.00E-01 1.23E 07 0.00E-01 9.61E 06 TC 99M 6.92E-00 1.93E 00 2.50E 01 0.00E-01 2.88E 01 1.07E 00 1.27E 03 TC 101 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01

[

D Revision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 8

9 Reference Use -

Page 177 of 188 l C)

ATTACHMENT A lO (Page 173 of 184)

\

l-- TABLE A.5-18 (coat'd) tM GRASS-00AT-MILK PATHNAY FACTOR

\ M' MREN/YR PER pCI/SEC

,o TEES

. G~

NUCLIDI BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI l RU 103 2.17E 02 0.00E-01 9.28E 01 0.00E-01 7.66E 02 0.00E-01 1.81E 04 i EU 105 1.88E-04 0.00E-01 7.30E-05 0.00E-01 2.37E-03 0.00E-01 1.52E-01

=

V I

j RU 106 4.50E 03 0.00E-01 5.678 02 0.003-01 8.68E 03 0.00E-01 2.16E GE j AG 110M 1.16E 07 1.095 07 6.65E 06 0.00E-01 2.085 07 0.00E-01 3.07E 09 t ;

TE 125M 3.60E 06 1.30E 06 4.82E 05 1.01E 06 0.00E-01 0.005-01 1.06E 07 l J

TE 127M 1.01E 07 3.59E 06 1.20E 06 2.41E 06 4.10E 07 0.00E-01 2.52E 07 l l

TE 127 1.45E 02 5.15E 01 3.135 01 1.00E 02 5.895 02 0.00E-01 1.12E 04 l

, TE 129M 1.32E 07 4.90E 06 2.09E 06 4.26E 06 5.53E 07 0.00E-01 4.96E 07 I I

l TE 129 6.28E-11 2.345-11 1.53E-11 4.48E-11 2.63E-10 0.00E-01 3.43E-10 l TE 131M 7.89E 04 3.78E 04 3.16E 04 5.69B 04 3.94E 05 0.00E-01 3.04E 06 TE 131 8.04E-34 3.31E-34 2.51E-34 6.19E-34 3.513-33 0.00E-01 6.60E-35 TE 132 5.15E 05 3.26E 05 3.07E 05 3.44E 05 3.13E 06 0.00E-01 1.03E 07 I 130 8.87E 05 2.57E 06 1.02E 06 2.09E 08 3.95E 06 0.005-01 1.97E 06 l

I 131 6.45E 08 9.03E 08 4.85E 08 2.63E 11 1.55E 09 0.00E-01 1.79E 08 l

) I 132 3.51E-01 9.18E-01 3.29E-01 3.09E 01 1.45E 00 0.00E-01 4.00E-01 1 l 2 133 8.493 06 1.44E 07 4.39E 06 2.01E 09 2.52E 07 0.00E-01 1.09E 07 I 134 4.34E-12 1.15E-11 4.13E-12 1.92E-10 1.81E-11 0.00E-01 1.51E-13 I 135 2.74E 04 7.05E 04 2.61E 04 4.54E 06 1.11E 05 0.00E-01 7.82E 04 j CS 134 2.94E 10 6.93E 10 3.22E 10 0.005-01 2.20E 10 8.41E 09 8.62E 08 l CS 136 1.33E 09 5.25E 09 3.52E 09 0.00E-01 2.86E 09 4.50E 08 4.22E 08 i

(

CS 137 4.02E 10 5.34E 10 1.86E 10 0.00E-01 1.82E 10 7.06E 09 7.60E 08 CS 138 4.99E-23 9.58E-23 4.79E-23 0.00E-01 7.07E-23 8.235-24 4.34E-26 l

BA 139 1.01E-08 7.13E-12 2.95E-10 0.00E-01 6.72E-12 4.91E-12 9.045-08 l

l BA 140 5.82E 06 7.14E 03 3.75E 05 0.00E-01 2.42E 03 4.08E 03 8.90E 06 t BA 141 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01

!' BA 142 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 LA 140 9.75E-01 4.79E-01 1.27E-01 0.00E-01 0.00E-01 0.00E-01 2.75E 04 LA 142 2.03E-12 9.03E 13 2.255-13 0.00E-01 0.00E-01 0.00E-01 2.75E-08 CE 141 1.07E 03 7.12E 02 8.18E 01 0.00E-01 3.35E 02 0.00E-01 2.04E 06

' CE 143 9.17E 00 6.67E 03 7.45E-00 0.00E-01 2.99E 00 0.00E-01 2.01E 05 CE 144 7.90E 04 3.27E 04 4.24E 03 0.00E-01 1.95E 04 0.00E-01 1.99E 07 PR 143 3.48E 01 1.39E 00 1.73E 00 0.00E-01 8.08E 03 0.00E-01 1.15E 05 l"

PR 144 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 ND 147 2.193 01 2.38E 01 1.42E 00 0.00E-01 1.40E 01 0.00E-01 8.57E 04 I N 187 1.44E 03 1.17E 03 4.11E 02 0.00E-01 0.00E-01 0.00E-01 3.18E 05 MP 239 8.41E-01 7.93E-02 4.41E-02 0.00E-01 2.49E-01 0.00E-01 1.29E 04

H 3 Revision: 0 D OFFSITE DOSE CALCULATION MANUAL AP 07B-003 O

m Reference Use Page 178 of 188 O

ATTACHMENT A O (Page 174 of 184)

'OFFSITE DOSE CALCULATION MANUAL N

\

TABLE A.5-19 M '

GRASS-GOAT-MILK PATHWAY FACTOR

\ M* MREM /YR PER pCI/SEC

.D CHILD T

NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI H 3 0.00E-01 3.20E 03 3.20E 03 3.20E 03 3.20E 03 3.20E 03 3.20E 03 C 14 1.19E 09 2.39E 08 2.39E 08 2.39E 08 2.39E 08 2.39E 08 2.39B 08 NA -24 1.0GE 06 1.06E 06 1.06E 06 1.06E 06 1.06E 06 1.06E 06 1.06E 06 P 32 9.33E 10 4.375 09 3.60E 09 0.00E-01 0.00E-01 0.00E-01 2.58E 09 CR 51 0.00E-01 0.00E-01 1.22E 04 6.78E 03 1.858 03 1.24E 04 6.48E 05 MN 54 0.00E-01 2.52E 06 6.70E 05 0.00E-01 7.06E 05 0.00E-01 2.11E 06 MN 56 0.00E-01 1.54E-03 3.48E-04 0.00E-01 1.87E-03 0.00E-01 2.24E-01 FE 55 1.45E 06 7.70E 05 2.39E 05 0.00E-01 0.00E-01 4.36E 05 1.43E 05 FE 59 1.56E 06 2.53E 06 1.26E 06 0.00E-01 0.00E-01 7.33E 05 2.63E 06 CO 58 0.00E-01 1.46E 06 4.45E 06 0.00E-01 0.00E-01 0.00E-01 8.49E 06 CO 60 0.00E-01 5.18E 06 1.53E 07 0.00E-01 0.005-01 0.00E-01 2.87E 07 I NI 63 3.56E 09 1.90E 08 1.21E 08 0.00E-01 0.00E-01 0.00E-01 1.28E 07 NI 65 2.49E-01 2.34E-02 1.37E-02 0.00E-01 0.00E-01 0.00E-01 2.875 00 CU 64 0.00E-01 8.23E 03 5.03E 03 0.00E-01 2.01E 04 0.00E-01 3.91E 05 ZN 65 4.96E 08 1.32E 09 8.22E 08 0.00E-01 8.33E 08 0.005-01 2.328 08 ZN 69 2.84E-12 4.10E-12 3.79E-13 0.00E-01 2.49E-12 0.00E-01 2.58E-10 BR 83 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 BR 84 0.00E-01 0.00E-01 0.00E-01 0.005-01 0.00E-01 0.00E-01 0.00E-01 BR 85 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 RB 86 0.005-01 1.05E 09 6.47E 08 0.00E-01 0.00E-01 0.00E-01 6.77E 07 RB 88 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 j RB 89 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 l SR 89 1.398 10 0.00E-01 3.97E 08 0.00E-01 0.00E-01 0.00E-01 5.38E 08 I SR 90 2.35E 11 0.00E-01 5.95E 10 0.00E-01 0.00E-01 0.00E-01 3.16E 09 SR 91 2.71E 05 0.00E-01 1.02H 04 0.00E-01 0.00E-01 0.00E-01 5.99E 05 SR 92 4.60E 00 0.00E-01 1.84E-01 0.00E-01 0.00E-01 0.00E-01 8.71E 01 Y 90 3.86E 01 0.00E-01 1.03E-00 0.00E-01 0.00E-01 0.00E-01 1.10E 05 Y 91M 3.24E-20 0.00E-01 1.18E-21 0.00E-01 0.00E-01 0.00E-01 6.34E-17 Y 91 4.68E 03 0.00E-01 1.25E 00 0.00E-01 0.00E-01 0.00E-01 6.24E 05 Y 92 3.04E-05 0.00E-01 8.71E-07 0.00E-01 0.00E-01 0.00E-01 8.793-01 Y 93 1.27E-01 0.00E-01 3.48E-03 0.00E-01 0.00E-01 0.00E-01 1.89E 03 2R 95 4.60E 02 1.01E 02 9.00E 01 0.00E-01 1.45E 02 0.00E-01 1.05E 05 ZR 97 2.30E-01 3.33E-02 1.96E-02 0.00E-01 4.78E-02 0.00E-01 5.04E 03 NB 95 3.82E 04 1.49E 04 1.06E 04 0.00E-01 1.40E 04 0.00E-01 2.75E 07 MO 99 0.00E-01 9.76E 06 2.42E 06 0.00E-01 2.08E 07 0.00E-01 8.07E 06 TC 99M 1.59E 00 3.11E 00 S.16E 01 0.00E-01 4.52E 01 1.58E 00 1.77E 03 TC 101 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01

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D (Page 175 of 184)

'M

tamLa A.s-19 (ooaE*d) lM GRASS-OQhT-MILK PATHNAY FACTOR ,

\ M' MREN/YR PER pCI/SEC i j CHILD NUCLIDE BCNE LIVER T BODY THYROID EIDNEY LUNG GI-LLI i RU 103 5.14E 02 0.00E-01 1.97E 02 0.00E-01 1.29E 03 0.00E-01 1.33E 04 RU 105 4.59E-04 0.0CE-01 1.67E-04 0.00E-01 4.04E-03 0.00E-01 3.00E-01 I RU 106 1.11E 04 0.00E-01 1.38E 03 0.00M-01 1.50E 04 0.00E-01 1.72E 05 i

i AG 110M 2.51E 07 1.69F 17 1.35E 07 0.00E-01 3.15E 07 0.00E-01 2.015 09 j TE 125M 8.85E 06 2.40E 06 1.18E 06 2.48E C5 0.00E-01 0.00E-01 8.542 06 TE 127M 2.50E 07 6.72E 06 2.96E 06 5.97E 06 7.12E 07 0.00E-ul 2.02E 07 TE 127 3.57E 02 9.645 01 7.67E 01 2.47E 02 1.02E 03 0.00E-01 1.40E 04

- TE 129M 3.26E 07 9.09E 06 5.05E 06 1.05E 07 9.565 07 0.00E-01 3.97E 07 l ,

l TE 129 1.55E-10 4.32E-11 3.68E-11 1.11E-10 4.53E-10 0.00E-01 9.64E-09 '

TN 131M 1.92E 05 6.64E 04 7.07E 04 1.37E 05 6.43E 05 0.00E-01 2.69E 06 ,

i TE 131 1.97E-33 6.01E-34 5.87E-34 1.51E-33 5.97E-33 0.00E-01 1.04E-32 l I TE 132 1.23E 06 5.44E 05 6.585 05 7.93E 05 5.05E 06 0.003-01 5.48E 06 1 I 130 2.07E 06 4.19E 06 2.16E 06 4.62E 08 6.27E 06 0.005-01 1.96E 06 I 131 1.56E 09 1.57E 09 8.94E 08 5.20E 11 2.58E 09- 0.00E-01 1.40E 08 I 132 8.30E-01 1.52E 00 7.013-01 7.07E 01 2.33E 00 0.005-01 1.79E 00 I 133 2.06E 07 2.55E 07 9.65E 06 4.745 09 4.25E 07 0.00E-01 1.03E 07 I 134 1.03E-11 1.91E-11 8.77E-12 4.395-10 2.925-11 0.00E-01 1.263-11 1 135 6.49E 04 1.17E 05 5.52E 04 1.03E 07 1.79E 05- 0.00E-01 8.90E 04 CS 134 6.79E 10 1.11E 11 2.35E 10 0.00E-01 3.45E 10 1.24E 10 6.01E 08 CS '136 3.01E 09 8.27E 09 5.35E 09 0.00E-01 4.40E 09 6.57E 08 2.91E 08

l. CS 137 9.67E 10 9.26E 10 1.37E 10 0.00E-01 3.02E 10 1.09E 10 5.80E 08 l CS 138 1.21E-22 1.68E-22 1.07E-22 0.00E-01 1.18E-22 1.275-23 7.74E-23 i INL 139 2.49E-08 1.33E-11 7.21E-10 0.00E-01 1.16E-11 7.823-12 1.44E-06 BA 140 1.41E 07 1.23E 04 8.21E 05 0.00E-01 4.01E 03 7.34E 03 7.12E 06 I BA 141 0.00E-01 0.00E 01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 BA 142 0.00E-01 0.005-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 LA 140 2.33E 00 8.16E-00 2.75E-01 0.00E-01 0.00E-01 0.00E-01 2.27E 04 LA 142 4.91E-12 1.56E-12 4.90E-13 0.00E-01 0.00E-01 0.00E-01 3.10E-07 CE 141 2.63E 03 1.31E 03 1.94E 02 0.00E-01 5.74E 02 0.00E-01 1.63E 06 4

CE 143 2.25E 01 1.22E 04 1.77E 00 0.00E-01 5.12E 00 0.00E-01 1.79E 05 l CE 144 1.95E 05 6.11E 04 1.04E 04 0.00E-01 3.38E 04 0.00E-01 1.59E 07 f PR 143 8.62E 01 2.59E 01 4.28E 00 0.00E-01 1.40E 01 0.00E-01 9.30E 04

] PR 144 0.00E-01 0.005-01 0.00E-01 0.00E 01 0.005-01 0.00E-01 0.00E-01 ND 147 5.36E 01 4.34E 01 3.36E 00 0.00E-01 2.38E 01 0.00E-01 6.88E 04 W 187 3.493 03 2.07E 03 9.28E 02 0.00E-01 0.005-01 0.00E-01 2.90E 05 l NP 239 2.07E 00 1.49E-01 1.04E 01 0.00E-01 4.30E-01 0.00E-01 1.10E 04 9/93 I

-= --

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M OFFSITE DOSE CALCULATION MANUAL l

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TABLE A.5-20 M GEA88-GOAT-MILK PATHNAY FACTOR !

\ 'M 8 MREM /YR PER SCI /SEC l A INFANT (r r NUCLIDE BONE LIVER T BODY THYROID EIDNEY LINE3 GI-LLI t

H 3 0.00E-01 4.86E 03 4.86E 03 4.86E 03 4.86E 03 4.86E 03 4.86E 03 C 14 2.34E 09 5.00E 08 5.00E 08 5.00E 08 5.00E 08 5.00E OB 5.00E 08 NA 24 1.85E 06 1.85E 06 1.85E 06 1.85E 06 1.85E 06 '1.85E 06 -1.85E 06 ,

P 32 1.92E 11 1.135 10 7.45E 09 0.003-01 0.00E-01 0.00E-01 2.60E 09 CR 51 0.005-01 0.00E-01 1.94E 04 1.265 04 2.76E 03 2.46E 04 5.64E 05 MN 54 0.00E-01 4.68E 06 1.06E 06 0.00E-01 1.04E 06 0.00E-01 1.72E 06 MN 56 0.00E-01 3.78E-03 6.51E-04 0.00E-01 3.25E-03 0.00E-01 3.43E-01 l FE 55 1.76E 06 1.13E 06 3.035 06 0.005-01 0.00E-01 5.54E 05 1.445 05 FE 59 2.92E 06 5.09E 06 2.01E 06 0.00E-01 0.00E-01 1.51E 06 2.43E 06 l

CO 58 0.00E-01 2.91E 06 7.26E 06 0.00E-01 0.00E-01 0.00E-01 7.25E 06 J CO 60 0.00E-01 1.06E 07 2.50E 07 0.00E-01 0.00E-01 0.00E-01 2.52E 07 j NI 63 4.19E 09 2.59E 08 1.45E 08 0.00E-01 0.005-01 0.00E-01 1.29E 07 NI 65 5.27E-01 5.96E-02 2.715-02 0.00E-01 0.00E-01 0.00E-01 4.54E 00 CU 64 0.00E-01 2.07E 04 9.58E 03 0.00E-01 3.50E 04 0.00E-01 4.25E 05-IN 65 6.66E 08 2.28E 09 1.05E 09 0.00E-01 1.11E 09 0.00E-01 1.93E 09 EN 69 6.04E-12 1.09E-11 8.10E-13 0.005-01 4.52E-12 0.00E-01 8.87E-10 BR 83 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 BR 84 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 BR 85 0.00E-01 0.00E-01 0,00E-01 0.005-01 0.00E-01 0.00E-01 0.005-01 RB 86 0.00E-01 2.67E 09 1.32E 09 0.00E-01 0.00E-01 0.00E-01 6.83E 07 RB 88 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 )

RB 89 0.00E-01 0.005-01 0.00E-01 0.003-01 0.00E-01 0.005-01 0.00E-01 l SR 89 2.64E 10 0.00E-01 7.58E 08 0.00E-01 0.00E-01 0.00E-01 5.43E 08 '

SR- 90 2.55E 11 0.00E-01 6.50E 10 0.00E-01 0.00E-01 0.00E-01 3.19E 09 i

SR 91 5.65E 05 0.00E-01 2.05E 03 0.00E-01 0.00E-01 0.00E-01 6.69E 05 '

SR 92 9.78E 00 0.00E-01 3.63E-01 0.00E-01 0.00E-01 0.00E-01 1.05E 02 Y 90 8.16E 01 0.00E-01 2.195 00 0.00E-01 0.00E-01 0.00E-01 1.13E 05 Y 91M 6.875-20 0.00E-01 2.34E-21 0.005-01 0.00E-01 0.00E-01 2.29E-16 Y 91 8.79E 03 0.00E-01 2.345 02 0.005-01 0.00E-01 0.00E-01 6.30E 05 Y 92 6.473-05 0.00E-01 1.823-06 0.000-01 0.00E-01 0.00E-01 1.23E 00 Y 93 2.70E-01 0.00E-01 7.36E-03 0.0'E-01 0.00E-01 0.00E-01 2.13E 03 ;

ER 95 8.17E 02 1.99E 02 1.41E 02 0.00E-01 2.14E 02 0.00E-01 9.91E 04 ER 97 4.88E-01 8.37E-02 3.82E-02 0.005-01 8.44E-02 0.00E-01 5.345 03 NB 95 7.12E 04 2.93E 04 1.70E 04 0.00E-01 2.10E 04 0.00E-01 2.48E 07 MO 99 0.00E-01 2.50E 07 4.87E 06 0.00E-01 3.73E 07 0.00E-01 8.22E 06 TC 99M 3.30E 00 6.81E 00 8.77E 01 0.005-01 7.33E 01 3.56E 00 1.98E 03

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ATTACHMENT A O (Page 177 of 184)

.\ .

~

TABLE A.5-20 (cont'd)

M GRASS-GOAT-MILK PATHNAY FACTOR '

\ M* MREM /YR PER pCI/SEC

.D INFANT D'

NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI TC 101 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 RU 103 1.04E 03 0.00E-01 3.48E 02 0.00E-01 2.16E 03 0.00E-01 1.26E 04 3

RU 105 9.68E-04 0.00E-01

)

3.26E-04 0.00E-01 7.12E-03 0.00E-01 3.85E-01 RU 106 2.285 04 0.00E-01 2.85E 03 0.00E-01 2.70E 04 0.00E-01 1.73E 05 AG 110M 4.63E 07 3.38E 07 2.24E 07 0.00E-01 4.83I 07 0.00E-01 1.75E 09 TB 125M 1.818 07 6.05E 06 2.45E 06 6.09E 06 0.00E-01 0.00E-01 8.62E 06 TE 127M 5.05E 07 1.68E 07 6.125 06 1.46E 07 1.24E 08 0.005-01 2.04E 07 TE 127 7.59E 02 2.54E 02 1.635 02 6.18E 02 1.85E 03 0.00E-01 1.59E 04 TE 129M 6.695 07 2.29E 07 1.03E 07 2.57E 07 1.67E 08 0.00E-01 3.99E 07 TE 129 3.28E-10 1.13E-10 7.66E-11 2.75E-10 8.17E-10 0.005-01 2.62E-08 TB 131M 4.05E 05 1.63E 05 1.35E 05 3.31E 05 1.12E 06 0.00E-01 2.75E 06 TE 131 4.18E-33 1.54E-33 1.17E-33 3.73E-33 1.07E-32 0.00E-01 1.695-31 TE 132 2.53E 06 1.25E 06 1.175 06 1.85E 06 7.84E 06 0.00E-01 4.64E 06 I 130 4.26E 06 9.38E 06 3.76E 06 1.05E 09 1.03E 07 0.005-01 2.01E 06 I 131 3.26E 09 3.85E 09 1.69E 09 1.26E 12 4.49E 09 0.005-01 1.37E 08 I 132 1.72E 00 3.49E 00 1.24E 00 1.64E 02 3.90E 00 0.00E-01 2.83E 00 I 133 4.35E 07 '6.34E 07 1.86E 07 1.15E 10 7.45E 07 0.00E-01 1.07E 07 I 134 2.13E-11 4.36E-11 1.55E-11 1.02E-09 4.88E-11 0.00E-01 4.51E 11 i I 135 1.35E 05 2.68E 05 9.79E 04 2.41E 07 2.99E 05 0.00E-01 9.715 04 CS 134 1.09E 11 2.04E 11 2.06E 10 0.00E-01 5.25E 10 1.86E 10 5.54E 08 CS 136 5.88E 09 1.733 10 6.45E 09 0.00E-01 6.89E 09 1.41E 09 2.63E 08 CS 137 1.54E 11 1.81E 11 1.20E 10 0.00E-01 4.85E 10 1.96E 10 5 3 65E 08 CS 138 2.55E-22 4.15E-22 2.01E-22 0.00E-01 2.07E-22 3.235-23 6.63E-22 RA 139 5.30E-08 3.51E-11 1.53E-09 0.00E-01 2.11E-11 2.13E-11 3.35E-06 BA 140 2.89E 07 2.89E 04 1.498 06 0.00E-01 6.87E 03 1.78B 04 7.11E 06 EA 141 0.00E-01 0,00E-01 0.00E-01 0.00E-01 0.00E-01 0.003-01 0.00E-01 BA 142 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 LA 140 4.88E 00 1.92E 00 4.94E-00 0.00E-01 0.00E-01 0.00E-01 2.26E 04 LA 142 1.03E-11 3.78E-12 9.063-13 0.00E-01 0.00E-01 0.00E-01 6.433-07 I CE 141 5.20E 03 3.175 03 3.74E 02 0.00E-01 9.79E 02 0.00E-01 1.64E 06 1

CE 143 4.76E 01 3.16E 04 3.61E 00 0.00E-01 9.21E 00 0.00E-01 1.84E 05 CE 144 2.79E 05 1.14E 05 1.56E 04 0.00E-01 4.62E 04 0.00E-01 1.60E 07 PR 143 1.78E 02 6.67E 01 8.84E 00 0.00E-01 2.48E 01 0.00E-01 9.41E 04 l PR 144 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 ND 147 1.06E 02 1.09E 02 6.69E 00 0.005-01 4.21E 01 0.00E-01 6.92E 04 W 187 7.35E 03 5.11E 03 1.77E 03 0.00E-01 0.00E-01 0.00E-01 3.00E 05 NP 239 4.38E 00 3.913-01 2.21E-01 0.00E-01 7.80E-01 0.00E-01 1.13E 04

,,-m ,- . , , ,

H

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\ OFFSITE DOSE CALCULATION MANUAL M '

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lA

'r l

APPENDIX B Meteorological Model l

i i

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a 1 I

APPEMDIX B '

\

PROPRTETARY TNPORMATION SUPPLIED BY SAI_

The X/Q's and D/Q's are calculated using the guidance of Reg. 1 Guide 1.111.

l The constant mean wind direction model, as defined in equation 3 of Reg. Guide 1.111, is used to calculated X/Q valuce.

't 2.032[ny exp -h

~

, /2 oz ij (x)'

~

= 8 (X/Q)D __

Nx Ui 1(x) 4 Where:

l h, = effective release height (m). (All releases from Wolf Creek Generating Station are considered as ground releases therefore he = 0.)

n13 = hours of valid data for weather conditions in l given direction, windepeed class I, and atmospheric stability class j.

N =

total house of valid data

Di - midpoint of windepeed class (m/s) x = distance downwind (m) l l o,3(x) = vertical plume spread without volumetric l correction at distance x and stability class j. See Figure B.1.

E,3(x) = vertical plume spread with columetric correction for release within buildings wake cavity, at distance x and stability class j.

For ground level releases E,3 (x) is the lesser of 2

h2 (x) + 0.5 D2 ,f, or]3 og (x)

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APPENDIX B (CONT'D}

Where:

f D, - maximum adjacent building height either up- or down-wind from the release point 2.032 = (2/n)

divided by width, in radians, of a 22.5 sector (X/Q)o = Average effluent concentration, X, normalized to source strength, Q, at distance x in sector D.

For WCGS the above Meteorological Model will simplify to the following equation for X/Q:

2.032 E ny U

(X / Q)g = _

N Un x X(x)

U The calculation of the relative disposition per unit area, D/Q, is performed using the deposition rate graphs found in Reg.

Guide 1.111. For a 22.5 sector, since the effluent concentration is assumed uniform across the sector, the relative deposition per unit area is assumed uniform across the sector.

The calculation of D/Q is determined from relative deposition by the following relationship:

Do (x) e DEPL,(x)

DlQ =

(2 x /16)x where:

Dy(x) = Relative deposition rate for windspeed class i and stability class j at downwind distance x (1/m). See Figure B.3.

(2n/16)x = length of arc across sector at downwind distance x (m).

D/Q = relative deposition per unit area (m) l l

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\

! fd APPENDIX B (CONT'D)'

\

, DEPLy(x) = Reduction factor due to plume depletion at dis'. tnce x

l. for windspeed i and stability class j.

l 1

l 1 l

i l

l l

f O

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M OFFSITE DOSE CALCUIATION MANUAL

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~

Figure 3.1 ;

N '

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g. ,

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l 1 1

O.1 1.0 10 100 PLUME TRAVEL DISTANCE (KILOMETERS)

Vwtical Stant'.atd Deviation of Materialin a Plunw (Letters denote Pasquilt Statnlity Class)

NOTE: THESE ARE STANOARO RELATSONSHIPS AND MAY H AVE TO OE MOOlFIED FOR CEATAIN TYPE $ OF TERRAIN AN0 TOR CLtMATIC CONORTION1tE.G. VALLEY DESERY OVER WATERI.

~

B-4

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M OFFSITE DOSE CALCUIATION MANUAL

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~

Figure B.2 M

\

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8

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