ML20206D967

..D TABLE OF CONTENTS

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\ Page 0

1.0 INTRODUCTION

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\ 2.0 LIQUID EFFLUMNTS 11 ,

O 2.1 CONCENTRATION - COMPLIANCE WITH 10 CFR 20 11 l QJ 2.2 DOSE - COMPLIANCE WITH 10 CFR 50 APPENDIX I 17 i 2.3 PROJECTED DOSE 19 l 2.4 INSTRUMENTATION 20 3.0 GASEOUS EFFLUENTS 38 3.1 DOSE RATE - COMPLIANCE WITH 10 CFR 20 39 3.2 DOSE - COMPLIANCE WITH 10 CFR 50 APPENDIX I 46 3.3 PROJECTED DOSE 56 3.4 INSTRUMENTATION 58 4.0 TOTAL DOSE 73 4.1 REMEDIAL ACTION 73 4.2 SURVEILLANCE REQUIREMENTS 74 S.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (Contained in AP 07B-004) 6.0 BASES 75 7.0 REPORTS 7.1 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT (contained in AP 07B-004) 7.2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 83 APPENDIX A: DOSE CONVERSION FACTOR TABLES 86 APPENDIX B: METEOROLOGICAL MODEL 162

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OFFSITE DOSE CALCULATION MANUAL I

..D 4 LIST OF TABLES J Table Page

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O 2-1 RADIOACTIVE LIQUID WASTE SAMPL7NG AND ANALYSIS PROGRAM 13 i W

\ 2-2 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 22 l O

u 2-3 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 25 SURVEILLANCE REQUIREMENTS 3-1 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM 42 3-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 59 3-3 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 61 SURVEILLANCE REQUIREMENTS A.1-1 BIOACCUMULATION FACTORS TO BE USED IN THE ABSENCE OF 87 SITE SPECIFIC DATA A.1-2 DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS 88 A.2-1 INHALATION DOSE PA4CTORS FOR ADULTS 89 l

i A.2-2 INHALATION DOSE FACTORS FOR TEENAGERS 91 5 A.2-3 INHALATION DOSE FACTORS FOR CHILD 93 A.2-4 INHALATION DOSE FACTORS FOR INFANT 95 A.2-5 EXTERNAL DOSE FACTOR FOR STANDING ON CONTAMINATED 97 GROUND A.3-1 INGESTION DOSE FACTOR FOR ADULTS 99 l l

A.3-2 INGESTION DOSE FACTOR FOR TEENAGERS 102 i

A.3-3 INGESTION DOSE FACTOR FOR CHILD 105 l l

A.3-4 INGESTION DOSE FACTOR FOR INFANT 108 l A.3-5 STABLE ELEMENT TRANSFER DATA 111 j A 4-1 SITE RELATED INGESTION DOSE COMMITMENT FOR ADULT 112 !

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A.4-2 SITE RELATED INGESTION DOSE COMMITMENT FACTOR FOR 115 i TEENAGER A.4-3 SITE RELATED INGESTION DOSE COMMITMENT FACTOR FOR CHILD 118 I

A.4-4 SITE RELATED INGESTION DOSE COMMITMENT FACTOR FOR 121 INFANT

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\ l 0 A.5-1 INHALATION DOSE PARAMETER FOR THE CHILD 124 l W = '

N A.5-2 INHALATION PATHWAY FACTOR FOR ADULT (RI FACTOR) 125 I O l 83 A.5-3 INHALATION PATHWAY FACTOR FOR TEENAGER (RI FACTOR) 127 A.5-4 INHALATION PATHWAY FACTOR FOR CHILD (RI FACTOR) 129 A.5-5 INHALATION PATHWAY FACTOR FOR INFANT (RI FACTOR) 131 A.5-6 GRASS-COW-MILK PATHWAY FACTOR ADULT (RI FACTOR) OF SITE 133 l SPECIFIC DATA A.5-7 GRASS-COW-MILK PATHWAY FACTOR TEEN (RI FACTOR) 135 A.5-8 GRASS-COW-MILK PATHWAY FACTOR CHILD (RI FACTOR) 137 A.5-9 GRASS-COW-MILK PATHWAY FACTOR INFANT (RI FACTOR) 139 A.5-10 GRASS-COW-MEAT PATHWAY FACTOR ADULT (RI FACTOR) 141 A.5-11 GRASS-COW-MEAT PATHWAY FACTOR TEEN (RI FACTOR) 143 A.5-12 GRASS-COW-MEAT PATHWAY FACTOR INFANT (RI FACTOR) 145 A.5-13 VEGETATION PATHWAY FACTOR ADULT (RI FACTOR) 147 A.5-14 VEGETATION PATHWAY FACTOR TEEN (RI FACTOR) 149 A.5-15 VEGETATION PATHWAY FACTOR CHILD (RI FACTOR) 151 A.5-16 GROUND PLANE PATHWAY FACTOR (RI FACTOR) 153 A.5-17 GRASS-GOAT-MILK PATHWAY FACTOR ADULT (RI FACTOR) ,

154 A.5-18 GRASS-GOAT-MILK PATHWAY FACTOR TEEN (RI FACTOR) 156 A.5-19 GRASS-GOAT-MILK PATHWAY FACTOR CHILD (RI FACTOR) 158 A.5-20 GRASS-GOAT-MILK PATHWAY FACTOR INFANT (RI FACTOR) 160 LIST OF FIGURES Fiqure Page 2.1 BOUNDARY FOR LIQUID EFFLUENTS 37 3.1 BOUNDARY FOR GASEOUS EFFLUENTS 72 B-1 VERTICAL STANDARD DEVIATION OF MATERIAL IN A PLUME 166

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OFFSITE DOSE CALCULATION MANUAL !

..o E LIST OF FIGURES

'S Figure Page

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O W B-2 PLUME TRAVEL DISTANCE VERSUS FRACTION REMAINING IN 167

\ PLUME

'(3 M B-3 PLUME TRAVEL DISTANCE VERSUS RELATIVE DEPOSITION RATE 168

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A

.0 1.0 Introduction a

\ The Offsite Dose Calculation Manual describes the Radioactive O Effluent Controls Program. The implementation of this program W ensures compliance with the requirements of 10 CFR 50.36, 10 CFR

\ 20.106, 10 CFR 50 Appendix I and 40 CFR 190.

O U 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.

The ODCM describes the methodology and parameters used in the calculation of offsite doses due to radioactive liquid and 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.

The ODCM provides the limitations on tha. operability of i 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. 1 The ODCM provides descriptions of the information that should be included in the Annual Radioactive Effluent Release Reports.9/98 2.0 Liquid Effluents l

2.1 Concentration - Complicnce With 10 CFR 20 l

The concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS Isee Figure 2.1)' shall be '

limited to the concentration specified in 10 CFR Part 20, Appendix B, Table II, Column 2, for radionuclides other than ,

dissolved or entrained noble gases. For dissolved or entrained )

noble gases, the concentration shall be limited to 2x 10-* !

microcurie /mL total activity.

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OFFSITE DOSE CALCULATION MANUAL J 2.1.1 Rassedial Action ,

J l 0 With the concentration of radioactive material released in l

\ liquid effluents to UNRESTRICTED AREAS exceeding the above O limits, immediately restore the concentration to within the above limits.

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U 2.1.2 surveillance Requirements 1

To show compliance with this requirement, concentrations of actual liquid effluents will be determined by performing Isotopic Analyses. Radioactive liquid wastes shall be sampled and anal 3 zed according to the sampling and analysis program of Table 2-1.

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.0 D TABLE 2-1

.0 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM

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O LIQUID RELEASI SAMPLE PRINCIPAL I-131 DISSQLVED/ GROSS ALPHA Sr-89, re-55 y TYPE FREQUENCY GAMMA ENTRAINED AND H-3 Sr-90 EMITTERS GASES

,\ lGAMMA) fj 1. Batch Tanks Q g (2) Composite (4)

a. THB07A&S P P(3)- P M M Q Composite (4) Composite (4)

LLD (1) 55-7 1E-6 1E-5 IE-7 for SE-8 1E-6 Alpha j 1E-5 for H-3 1

b. THFC4A&B P P(3) P M M Q Q l Composite (4) Composite (4) Composite (4)

LLD (1) SE-7 1E-6 1E-5 1E-7 for SE-8 IE-6 l Alpha IE-5 for H-3

2. Continuous Releases (5)

a. Steam Daily (6) W(3) W M M Q Q Generator Composite (4 ) Composite (4) Composite (4) Composite (4) Composite (4) ,

Blowdown q LLD(1) SE-7 IE-6 IE-5 1E-7 for SE-8 1E-6 3

Alpha 1E-5 for H-3

b. 7urbine Daily (6) N(3) W M H Q Q Building Surap Composite (4) Composite (4) Composite (4) Composite (4) Composite (4)

LLD(1) SE-7 1E-6 1E-5 1E-7 for SE-8 1E-6 Alpha it-$ for H-3

c. Waste Water Daily 16) W(3) W M M O Q Treatment Composite (4) Composite (4 ) Composite (4) Composite (4) Composite (4)

LLDil) 5E-7 IE-6 1E-5 1E-7 for SE-8 1E-6 Alpha 1E-5 for H-3

d. Lime Sludge Daily (6) N(J) W M M Q Q Pond Corcposite(4) Composite (4 ) Composite (4) Composite (4) Composite (4 )

LLD (1) SE-7 1E-6 IE-5 1E-7 for SE-8 1E-6 Alpha IE-5 for H-3 LLD = ( Ci/mL) 9/9C

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.0 TABLE 2-1 (Continued)

..D TABLE NOTATIONS

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

%, probability of falsely concluding that a blank observation represents O a "real" signal..

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

4.66 s*

LLD =

E x V x 2.22 x 10' x Y x Decay Where:

LLD = the "a priori" lower limit of detection (microcuries 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), g - Jii/ 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),

2.22 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 sangM and the half life of the nuclide. Any combination of the thite 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 AAts, where:

Ats = decay time = acquisition start time - sample time

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.0 TABLE 2-1 (Continued) i D TABLE NOTATIONS j

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O A = In2/ half-life .

W.

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

O IJ g,,m ,

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

1-e* I Ahtd A = In2/ half-life l

td = deposition time = sample time - deposition start time l NOTE All times used in decay calculations should be in the same units.

Typical values of E, V, Y, ts, 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 an a_ posteriori (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.

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OFFSITE DOSE CALCULATION MANUAL A

J TABLE 2-1 (Continued)

,0 TABLE NOTATIONS

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O (3) The principal gamma emitters for which the LLD specification applies N 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 Q mean-that only these nuclides are to be considered. Other gamma peaks M that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the annual Radioactive Effluent Release Report in the format outlined in Regulatory Guide 1.21, Appendix B, Revision 1, June 1974. 9/98 (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 of sampling employed results in a specimen that is representative of the liquids released. Prior to analysis, all samples taken for the composite shall be thoroughly mixed in order for the composite samples to be representative of the effluent release.

(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 composite 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.

O 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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.0 0 2.2 Dose - Courpliance With 10 CFR 50 Appendix I

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

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O a. During any calendar quarter to less than or equal to M 1.5 mrems to the whole body and to less than or equal <

to 5 mrems to any organ, and I

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 ]

I 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 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 within 3 miles of the plant discharge.

2.2.2 Surveillance Requirements 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.

/ m S Dr=E AdAt s t.r ComtF s

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.0 Where,

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\ DT= the cumulative dose commitment to the total body 0 or any organ, T, from the liquid efiluent for the total N

\

a time period f A tt ,in mrem u t.i Att= the length of the Lth time period over which Cn i and Fu are averaged for all liquid releases, in hours.

Cit =

the average concentration of radionuclide, 'i', in undiluted liquid effluent flow during time period At t, in pCi/mL.

Ft = the near field average dilution factor for Cit during any liquid effluent release where:

f 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,=

1 The site related ingestion dose commitment factor to the total body or any organ, 'T', for each 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 the Adult age group.

Ar= i 1.14E5 (U / D, + U, x BF,)DF,

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.o Where,

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\ DW = Dilution factor from the near field area to the o potable water intake for water consumption, for Wolf W Creek Generating Station this factor is 1 (one).

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O BFi= Bioaccumulation factor for radionuclide 'i', in M l fish, pCi/Kg per pCi/1, from Table A.1-1 from l 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) 10'pCi/ pCix 10'ml/ Kg 1.14E5 - Units conversion factor =

8760 k /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 Projected Dose 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 Remedial 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:

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.o a. Explanation of why liquid radwaste was being discharged J without treatment, identification of any inoperable

\ equipment or subsystems, and the reason for the o inoperability, N

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

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c. Summary description of action (s) taken to prevent a recurrence.

2.3.2 Surveillance Requirements 2.3.2.1 Doses due to liquid releases from each unit to UNRESTRICTED AREAS shall be projected at least once per 31 days in accordance with the following methodology when Liquid Radwaste Treatment Systems are not being fully utilizad.

Du = --

x 31

.T.

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 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 Alarm / Trip Setpoints 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.

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.0 2.4.1 Rennedial Action

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\ 2.4.1.1 With a radioactive liquid effluent monitoring O instrumentation channel Alarm / Trip setpoint less W conservative than required by the above, immediately

\ suspend the release of radioactive liquid effluents O monitored by the affected channel, or declare the M

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 Eftluent Release Report, why this inoperability was not corrected within the time specified.

2.4.2 surveillance Requirements 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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o TABLE 2-2

. Jj RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION

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\ INSTRUMENT MINIMUM ACTION O CHANNELS l y OPERABLE

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g 1. Radioactivity Monitors Providing Alarm and y Automatic Termination of Release

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

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

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

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

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OFFSITE DOSE CALCULATION HANUAL

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TABLE 2-2 (continued)

J ACTION STATEMENTS

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O Action 31 - With the number of channels OPERABLE less than required by the W Minimum Channels OPERABLE requirement, effluent releases via this

\ pathway may continue for up to 14 days provided that prior to 0 initiating a release:

U

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 lino 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 DOSE 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 14 days provided that prior to initiating a release: 9/98

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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.0 TABLE 2-2 (Continued) l J ACTION STATEMENTS

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O Action 34 - With the number of channels OPERABLE less than required by the W Minimum Channels OPERABLE requirement, effluent releases via this

\ pathway may continue for up to 30 days provided the flow rate is p 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 IJ performance curves generated in place may be used to estimate flow.

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0 TABLE 2-3

,.0 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION

\ SURVEILLANCE REQUIREMENTS O INSTRUMENT CHANNEL SOURCE CHANNEL ANALOG y CHECK CHECK CALIBRATION CHANNEL

.g OPERATIONAL TEST C 1. Radioactivity Monitors providing N alarm and automatic termination of release

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

(HB-RE-18)

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) O(1)

(LE-RE-59)

d. Secondary Liquid Waste System D P R(2) Q(1)

Monitor (HF-RE-45)

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

Influent Monitor (HF-RE-95)

2. Flow Rate Measurement Devices

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

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

charge Line

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

. Discharge Line

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.M U ATTACHMENT A

, (Page 21 of 163)

.D

'.D TABZ2 2-3 (Continued) 0 TABLE NOTATIONS

\. (1) The ANALOG CHANNEL OPERATIONAL TEST shall also demonstrate th'at

-Q automatic isolation of this pathway and control room alarm W annunciation occur as appropriate if any of the following conditions

\ exists:

o-JJ 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 (alarm 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 l 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.

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O ATTACHMENT A (Page 22 of 163) !

.0

.0 2.4.3 Liquid Monitor Calibration Methodology

.0

\ The five monitors associated with liquid releases are listed O below:

bl

\ Monitor ID Description O

M 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 0-HB-RE-18 Liquid Radwaste Discharge Monitor 0-HF-RE-95 Wastewater Treatment System Influent Monitor Liquid effluent streams are monitored by an NaI(Tl) Detector. l The detector operates in a gross counting modo and is gsmma l 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 Ci/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.

2.4.4 Liquid Effluent Monitor Setpoints The Alarm / Trip Setpoints for the Liquid Effluent Radiation Monitors are based on instantaneous concentration limits of 10 CFR 20, Appendix B, Table II, Column 2 applied at the boundary of the restricted area. Specifically, the High Alarm Setpoint will correspond to the 10 CFR Part 20 limits at the Boundary of the restricted area; the Alert Alarm Setpoint is set to 80% of the High Alarm / Trip Setpoint. Since the high alarm / trip initiates isolation of the particular system and termination of the release, this setpoint represents assurance 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. 9/98 I

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fo ATTACHMENT A (Page 23 of 163)

~

.0 .

o The calculated Alarm and Trip Action Setpoints for the Liquid j

,o Effluent Line Monitors must satisfy the following equation: =

\

O cf w I g F+f.SC j h Where:

C = The liquid effluent concentration limit (MPC) ;

inplementing Section 2.1 in pCi/mL. j l

c = The Setpoint, in pCi/mL, of the Radioactivity l 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 Volumetric Flow of the !

dilution stream plus the effluent stream, represents a Value, which if exceeded would result in concentrations exceeding the limits of 10 CFR 20 in the restricted 3 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:

cs C(F+f) (#:i/ ml)

If no gamma activity is detected calculate the monitor setpoint by assigning the available MPC fraction to I-131, 2.4.4.1 Continuous Liquid Effluent Monitors The three monitors associated with continuous liquid releases are listed below:

Monitor 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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O ATTACHMENT A (Page 24 of 163) .

-. OFFSITE DOSE CALCULATION MANUAL o l

~0 The Steam Generator Blowdown Discharge Effluent Monitor J continuously monitors the Blowdown Discharge Pump a

\

O Outlet to detect excess radioactivity due to System N

Demineralizer breakthrough or abnormal Primary to l Secondary leakage. The Blowdown Discharge Monitor's j

\ High Alarm Setpoint initiates CLOSURE of the Blowdown j Isolation Valves and the Blowdown Discharge Valve. {

Similarly, the High Radiation Alarm on the Turbine !

Building Drain Monitor and Waste Water Treatment !

Monitor initiates CLOSURE of Lae 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 present. This is particularly appropriate for the l 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 activities,'it will not be possible to select a l radionuclide distribution on which to base the monitor l setpoint. Additionally, maximum effluent flows and l minimum dilution flows will normally be assumed. !

The High Alarm / Trip Setpoint will be set to corre.spond 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 Setpcint assures the limits of Section 2.1 are not exceeded at the boundary of the restricted area.

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.

l

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.0 4

The above continuous liquid effluents are not

D radioactive effluents until activity has been detected U

s by the Liquid Effluent Monitor, a Tritium analysis of W 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 g 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.

g i

2.4.4.1.1 Steam Generator Blowdown Discharge Monitor

/

SETPOINT(pCi/ml) = MPCnu x "+ "

F, where, MPCs in = Maximum Permissible Concentration of I-131, 3.0 E-7 pCi/mL.

4 Fn = Dilution flow rate.

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.

On the event that an alarm is reached, the setpoint 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.

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.0

.0 2.4.4.1.2 Turbine Building Drain Monitor And Waste water

,0 Treatment System Influent Monitor SETPOINT(pCi/ ml) = MPCn3, x *+b

\ Fr 1 0

d MPC. tai = 3.0 E-7 pCi/mL.

2 l

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 Batch Radioactive Liquid Effluent Monitor The two monitors associated with liquid batch releases are i listed below: ,

Monitor ID Description !

l 0-HF-RE-45 Secondary Liquid Waste System Monitor !

0-HB-RE-18 Liquid Radwaste Discharge Monitor l The setpoint is a function of dilution flow rato, tank flow ,

rate, and isotopic composition. A laboratory isotopic analysis j 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.

i

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J A_

The setpoints are determined using the following methodology:

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

\ The isotopic concentration of the batch is the sum of the concentrations for the isotopes present as determined from-the analysis required in Table 2-1.

[C; = [C +s C. + C, + C, + Cr 6

Where:

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.

Ca = The measured concentration Ca of alpha emitting nuclides observed by gross alpha analysis of the monthly composite sample.

Cs = The measured concentrations of Sr-89 and Sr-90 in liquid waste as determined by analysis of the quarterly composite sample.

Ct= The measured concentration of H-3 in liquid waste. 9/98

Cf= The measured concentration of Fe-55 in liquid waste as determined by analysis of the quarterly composite.

Values for these concentrations will be based on previous composite sample analysis as required by Table 2-1.

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9 ATTACHMENT A (Page 28 of 163)

.0 J 2) The measured radionuclide concentrations are used to 4 calculate a dilution factor, F, d which is the ratio of

\ total dilution flow rate to tank flow rate required to O assure that the limiting concentrations of Section 2.1

'd are met at the point of discharge. This is referred to

\ as the required dilution factor and is determined according to:

C' 6= (

Ei MPCp x F*

Where:

Ci= Measured concentrations of Cg , Ca, C, 3 Ct and Cg, as defined in Step 1. Terms Ca, C 3 , Ct and C f , will be included in the calculation as appropriate.

i MPCi =

MPCg , MPCa, MPC 3 , MPCt and MPC f , are limiting j concentrations of the appropriate radionuclide from 10 i 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.

F3 = The safety factor; a conservative factor used to acmpensate for statistical fluctuations and errors of measurement default value is 0.5.

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, Fdn, must be determined so that 1 available dilution flow may be apportioned among simultaneous discharge pathways.

FL = 6 / 6 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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ATTACHMENT A (Page 29 of 163)

~

OFFSITE DOSE CALCULATION MANUAL 4 o i

~0 The most straight-forward determination of allocation i factor is:

(U h F, = 1/ n

\

a Where:

M n = The number of liquid discharge pathways for which Ed > 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 relativa 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, Edn, and the effective dilution flow rate, Pe gg.

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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, Reference Use Page 35 of 168 ilt!

'O ATTACHMENT A i (Page 30 of 163)

~ '

.0 J Where:

D

\ Em = The expected minimum dilution water flow rate.

O W

LCi = Measured concentration of nuclide i in the I cooling lake water sample.

N MPC1 = Limiting concentration of radionuclide i from 10CFR20, Appendix B, Table II, Column 2.

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 Feff, the calculated maximum permissible waste tank flow rate is given by En + f, F f., 5 d- for f,((Feff Em fu Where f p if the expected effluent flow rate; normally I the rated capacity of the effluent pump. Thus the pump i flow rate is set at or below fmax. Even though the l 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 < 1, the effluent pump flow rate may be assigned any value since the waste tank effluent concentration meets the limits of 10CFR20 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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-10 T3 ATTACHMENT A (Page 31 of 163) 0FFSITE DOSE CALCULATION MANUAL A

J 5) The liquid radiation monitor setpoint may now be (8 determined based on the values of Ei , C1, and fmax-g The monitor response is primarily to gamma radiation, y therefore, the actual setpoint is based on E g , C g. The g calculated monitor setpoint concentration is determined o as follows:

N c = A[C (ACUSI) s 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, 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 releases made simultaneously. However, it is necessary to 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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.,0

'O FIGURE 2.1

\ BOUNDARY FOR L10UID EFFLUENTS o

W O

\ N 2J S)( RPE l w- s ACCESS ROA !\

' * \ S i*s' mon'P NUCLEAR LEARNING CENTER

/

e vi .

D 1 i

)

i

\ u j 9

COFFEY COUNTY LAKE

_4 j ,A... -

(m g c '^-

L.U-EE,CENC, C

OPERATIONS CENTER I

r.

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.0 0 3.0 Gaseous Effluents

.,0

\ Gaseous effluent releases from the Unit Vent and Radwaste O Building Vent are monitored continuously. The Unit Vent is the W release point for the Fuel / Auxiliary Building, access control

\ area, containment purge, and condenser air discharge. The O Radwaste Bu'lding i Vent is the release point for Waste Gas Decay N Tanks and the Radwaste Building Ventilation System.

Waste Gas Decay Tank releases and Containment Building relcases are treated as batch releases. Waste 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. l I

Monitor identifications are as follows: l Monitor ID Release 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 i monitor) l O-GT-RE-31 & 32 Containment Atmosphere Monitor (acts to l 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 l dose rates at the unrestricted area boundary. The monitor setpoint is the lesser of the total body dose rate or skin dose rate.

CIrrent 01py Proc fure 99-0412 09 07101 H

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P1 U ATTACHMENT A (Page 34 of 163)

.0

3.1 Dose Rate - Compliance With 10 CFR 20

.,0

\ The dose rate due to radioactive materials released in gaseous O

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 to the skin, and

b. For Iodine-131 and 133, for tritium, and for all radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to 1500 mrems/yr to any organ.

3.1.1 Remedial Action With the dose rate (s) exceeding the above limits, immediately restore the release to within the above limit (s). j 3.1.2 surveillance Requirements The dose rate to radionuclides in gaseous effluents shall be 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.

Based on the methodology of NUREG-0133;

a. Release rate limit for nobles gases:

[KdX / Q)Q, < 500 mrem / yr for the total body, i

and

[(L, + 1.1 M,)(X / Q) Q, < 3000 mrem / yr for the skin i

Where: .

Ki = Total body dose factor due to gamma emissions for each identified noble gas radionuclide, in mrem /yr per C1/m3, from Table-A.1-2.

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~

.D D

g = 2.2E-06 sec/m3, the highest calculated annual

(.Y/Q)

O average relative concentration at the restricted area boundary in the north sector.

U Release rate of radionuclide i from vent, in Qi =

pCi/sec.

Li = Skin dose factor due to beta 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 pC1/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 matezials 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 Ci/sec.

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

(X/QJ = 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 N sector, s

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~

(Page 36 of 163)

..D

.0 D

All radionuclides are assumed to be released in elemental form. '

\ The limit is applicable to the location (unrestricted area U boundary or beyond), characterized by the value of X/Q which W resulta in the maximum total body or skin dose commitment. The

\

U factors K i, L,i and Mi relate the radionuclide airborne g 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 listed in Table A.1-2.

The following equation for P(i)IN was taken from NUREG 0133:

P (i) IN (Inhalation);

Pp ), = K' (BR) DFA,(mrem / yr per pCi / m')

Where:

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

BR = the breathing rate of the child age group in m3/yr i DFAi = the maximum organ inhalation dose factor for the child age group for the i th radionuclide, in mrem /pC1. The total body is considered as an organ in the selection of DFA 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 /pC1.

1 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 l

I

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U ATTACHMENT A (Page 37 of 163)

- D TABLE 3-1 0 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM

\ Gaseous Release Sample Principal H-3 I-131/ Gross Sr-89, p Type Frequency Gamma (Oxide) I-133 Alpha Sr-90 g Emitters O

1. Unit Vent-Gas M M(3) (2) M(4)

N LLD(1) 1E-4 1E-6 Particulate Continuous (6) N(7) M Q Composite LLD(1) 1E-11(2) 1E-11 1E-11 Charcoal Continuous (6) W(7)

LLD(1) 1E-12/

1E-10

2. Radwaste Building Vent Gas M M(2) M LLD(1) 1E-4 1E-6 Particulate Continuous (6) W(7) (2) M Q (Composite)

LLD(1)- 1E-11 1E-11 1E-11 Charcoal Continuous (6) W(7)

LLD(1) 1E-12/

1E-10

3. Containment M Purge or Vent I Gas P(3) P (3) (2) I LLD(1) 1E-4 1E-6

4. Waste Gas Decay Tanks Gas P P(2)

LLD(1) 1"-4 LID = (pC1/ml) 2/90 i

I i

r

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.0

,o TABLE 3-1 (Continued)

TABLE NOTATIONS

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

\

D probability of falsely concluding that a blank observation represents ;

a "real" signal.

L1 For a particular measurement system, which may include radiochemical l separation: ,

{

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

LLD = the "a priori" lower limit of detection (microCuries 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), s, - JB / 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, 2/98 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 -A6ts, where:

6ts = decay time = acquisition start time - sample time

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..o

)

.A TABLE 3-1 (continued)

J TABLE NOTATIONS

\

O A = In2/ half-life W

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

O h) 1 . e .ar 2 x RT 1 = In2/ half-life RT = real time of counting C) This decay factor corrects for decay during sampling.

1- e'""

Abtd A = In2/ half-life Atd = deposition time = sample time - deposition start time NOTE All times used in decay calculations should M in the same units.

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

It should be recognized that the LLO is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as ar

_a posteriori (after the fact) limit for a particular measurement.

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.0

~D 0

TABLE 3-1 (Continued)

TABLE NOTATIONS

\ (2) The principal gamma emitters for which the LLD specification applies O include the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, W 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 O and particulate releases. This list does not mean that only these IJ nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the annual Radioactive Effluent Release Report in the format outlined in Regulatory Guide 1.21, Appendix B, Revision 1, June 1974. 9/98 (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.

(6) 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. j i

(7) Samples shall be changed at least once per 7 days and analyses shall j 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 J 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 at 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 I corresponding LLDs may be increased.by a factor of 10. This l requirement to sample once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months does not apply if analysis shows that both the DOSE EQUIVALENT I-131 concentration in the reactor coolant and the unit vent noble gas monitor activity have not increased more than a factor of 3. 2/98 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.

9/98

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.0 3.2 Dose - Coseliance With 10 CFR 50 Appendix I 0

\ 3.2.1 Noblo Gases a

W The air dose due to noble gases released in gaseous effluents,

\ from each unit, to areas at and beyond the SITE BOUNDARY (see O Figure 3.1) shall be limited to the following:

tJ

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 Remedial Action With the calculated air dose from radioactive noble gases 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 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 subsequent releases will be in compliance with the above limits.

3.2.1.2 surveillance Requirements 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 days. The dose calculations for the actual releases of radioactive noble gases in gaseous effluent will be consistent with the methodology provided in Reg. Guide 1.109, Rev. 1. The following dose calculations will be performed:

a. During any calendar quarter; For gamma radiation; D = 3.17E- 8 [M, {X/Q) x Q, s 5 mrad.

i=1

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D For beta radiation:

0

\

o D = 3.17E-8 [N, (X/Q)x Q, s 10 mrad.

g 6-i -

h. b. During any calendar year:

M For gamma radiation; D = 3.17E - 8 [ M, ..(X/ Q) x Q,$ 10 mrad.

si For beta radiation:

D = 3.17E-8 [N, (X/ Q)x Q, s 20 mrad.

-i Where:

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 pC1/m3 from Table A.1-2 (Reg. Guide 1.109, Table B-1, Col. 4).

N1

=

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

01 = The release of noble gas radionuclides, 'i', in gaseous effluents, in pCi. 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 should be as follows:

I

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a. For gamma radiation 5 1.6 mrad /mo.

\ For beta radiation < 3.3 mrad /mo.

O W 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 5 0.8 mrad /mo.

For beta radiation f 1.6 mrad /mo.

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

3.2.2 Radioiodines, Particulates and Other Radionuclides The dose to a MEMBER OF THE PUBLIC from Iodine-131 and 133, 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 3.1) 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 equal to 15

. mrems to any organ.

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o 3.2.2.1 Remedial Action

..o O

\ With the calculated dose from the release of Iodine-131 and 133, tritium, and radionuclides in particulate form with half-lives W greater than 8 days, in gaseous effluents exceeding any of the

\

O above limits, prepare and submit to the Commission within 30 M 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 Requirements 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 i [(WQ,))s 7.5 mrem

b. D (mrem) = 3.17E-8 Ri [(WQ,))s 15 mrem Where:

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

l:

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..o -

,o =

Q4 The release of radiciodines, radioactive

'8 materials in particulate form and radionuclides other than noble gases in gaseous effluents, 'i', in C1.

g Releases shall be cumulative over the calendar quarter g or year as appropriate. The Qi value shall be a determined as the product of the flow rate through the DJ 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 inhal'ation pathway. l 1

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 Pathway Factor, RI i [X/Q) l i l R s (X / Q] = K' (BR),(DFA,), (mrem / yr per pCi / m')

Where:

K' =

a constant of unit conversion, 10 6pC1/pC1.

= The breathing rate of the receptor of age (BR)a group (a), in m3/yr.

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

AGE GROUP (a) BREATHING RATE (m3/yr)

Infant 1400 Child 3700 Teen 8000 Adult 8000 l

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$ Reference Use Page 51 of 168 Vr 9 ATTACHMENT A (Page 46 of 163)

.o J = The maximum organ inhalation dose factor (DFA1 )a f\ for the receptor of age group (a) for the i th radionuclide, in mrem /pCi. The body is considered as O ;

an organ in the selection of (DFA i)a. See Tables N A.2-1, A.2-2, A.2-3, & A.2-4.

i

From Regulatory Guide i

\

1.109, Tables E-7,E-8, E-9 and E-10. l o i N

Ground Plane Pathway Factor, RGi[D/Q]

I (l.ed,')/ 4 G 2 R i(D/Q)= K'K'(SF) DFG, (m x mrem /yrperpCi/sec)

Where:

K' = A constant of unit conversion, 106 pct /pci.

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

11 = The decay constant for the i th radionuclide. l sec-1 J

t = The exposure time, 4.73 E8 sec (15 years).

DFGi= The ground plane dose conversion factor for the ;

i th radionuclide (mrem /hr per pCi/m )2 . See Table i A.2-5. (Regulatory Guide 1.109, Table E-6). f SF = The shielding factor (dimensionless), 0.7 (Reg.

Guide 1.109)

Grass-Cow-Milk Pathway Factor, R Ci [D/Q]

d Rc i[D / Q) = K' F,(r) (DFLi ),('/Y,)(c i'f)(m' mrem / yr per pCi / sec)

Where:

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

Op =

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

Uap = The receptor's milk consumption rate for age

(a), in liters /yr. (Reg. Guide 1.109, Table E-5).

l

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J Infant - 330 1/yr J Child = 330 1/yr

\ Teen = 400 1/yr O

Adult = 310 1/yr W.

\

Yp pastureTheagriculturalproductivitybgunitareaof

=

feed grass, in kg/m2, 0.7 kg/m . (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)

(DFL1 )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 l A.3-4. (Reg. Guide 1.109, Table E-11, E-12, E-13, and l 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 l (corresponding to a 14 day half-life). l NOTE 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 1.0, which is the most restrictive case.

tg = The transport time from pasture to cow, to milk, to receptor, in sec, 1.73 E5 sec (2 days) . (Reg. Guide 1.109, Table E-15).

r

]

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.0 Grass-Goat-Milk Pathway Factor, R Ci[D/Q]

D

\

O C 'Q,(U j' 4 R i(D/Q) = K' F,(r)(DFl),('/Y,)(c i i'ffm' mrem /yrperpCi/sec) w s ,

\ j O Where: l U ;

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

I 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 l Factor.

1 NOTE i

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 l 1.0, which is the most restrictive case.

I

{

The concentration of tritium in milk is based on the airborne j concentration rather than the deposition. Therefore, the R Cg is ;

based on (X/g),

C R ,[X /Q) = K'K" ' F,Q,U,,(DFL,),(0.75 (0.5/ H))(mrem /yr per jfilm') l Where:

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

H =

Absolute humidity of the atmosphere, 8 gm/m 3 (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) 1 i

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.,D 4 Grass-Cow-Meat Pathway Factor, RM i(D/Q)

A 2

R"'[D/Q) = K' F,(r) (DF4),('/Y,{ei'f{m mrem / yr per mci / sec)

\

O IJ Where:

Ff =

The stable element transfer coefficients, in days /kg, Table A.3-5. (Reg. Guide 1.109, Table E-1).

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

Infant = 0 Child = 41 Teen = 65 Adult = 110 tf

=

The transport time from pasture to receptor, in sec., 1.73 E6 (20 days) (Reg. Guide 1,109, Table E-15).

The concentration of tritium in meat is based on its airborne concentration rather than the deposition. Therefore, the R Mg 13 based on (X/Q):

R"i[X/Q) = K'K' ' F,Q,U,(DFL,),(0.75 (0.5/ H)](mrem /yrperpCi/m')

Where:

All terms defined above.

Vegetation Pathway Factor, RV i[D/Q]

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 '

8 R ilD/Q)= K' (DFLi ), (U'.)(f ei'L) +(U .ff,{c"I'h)(m' x mrem /yrper pCi/ sec)

Where:

K' =

A constant of unit conversion, 106 pCi/pci.

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.0 ' '

'A UL a -

The consumption rate of fresh leafy vegetation J

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

\ 1.109, Table E-5).

O N'

Infant =-0 kg/yr

\'

O Child = 26 kg/yr Teen -= 42 kg/yr Adult = 64 kg/yr S

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

Infant = 0 kg/yr Child - 520 kg/yr Teen - 630 kg/yr Adult = 520 kg/yr f_L = 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. Guido 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/m 2. (Reg.

Guide 1.109, Table E-15).

All other factors previously defined.

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\

0 the RVi is based on (X/Q):

3 Rh(X/Q) = K'K"' (U'.fo + U'.fyDFL,),{0.75 (0.5/ H))(mrem /yrperpCi/m )

O q Where:

All terms defined previously. All values indicated are default values from Reg. Guide 1.109, Rev. 1.

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

a. < 2.5-mrem /mo. l 1

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

1

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 Projected Dose The VENTILATION EXHAUST TREATMENT SYSTEM and the WASTE GAS l HOLDUP SYSTEM shall be OPERABLE and appropriate portions of l 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

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OFFSITE DOSE CALCULATION MANUAL a

4 b. 0.4 mrad to air from beta radiation, or A

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

O W 3.3.1 Remedial 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.

3.3.2 surveillance Requirements l 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.

Du - x 31 Where:

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

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3.4 Instrumentation

.c

\

The radioactive gaseous effluent monitoring instrumentation

.U channels shown in Table 3-2 shall be OPERABLE with their f Alarm / Trip Setpoints set to ensure that the limits of Section y 3.1 are not exceeded. The Alarm / Trip Setpoints of these y 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 Remedial 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 4 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 i the next Annual Radioactive Effluent Release Report, why this inoperability was not corrected within the time specified.

3.4.2 Surveillance Requirements Each radioactive gaseous 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 3-3.

l l

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..D TABI2 3-2 D RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION t - INSTRUMENT MINIMUM APPLICABILITY ACTION

\

U CHANNELS OPERABLE W -

\ 1. Unit Vent System 9 .

y'

a. Noble Gas Activity 1

40 Monitor - Providing ,

Alarm (GT-RE-21B) l l

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

43

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

43 l

d. Flow Rate F.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

3. Radwaste Building Vent System

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

Termination of Release (GH-RE-108)

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

43

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

43

d. Flow Rate N.A.

45

e. Sampler Flow Rate Monitor 1

39 At all times.

1 J

]

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0 TABLE 3-2 (Continued) 0 TABLE NOTATIONS y ACTION STATEMENTS 0

y ACTION 38 - With the number of channels OPERABLE less than required by the g minimum channels OPERABLE requirement, the contents of the tank (s) may a be released to the environment for up to 14 days provided that prior DJ to initiating the release:

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

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.

ACTION 39 - With the number of channels OPERABLE less than required by the minimum channels OPERABLE requirement, effluent releases via this l pathway may continue for up to 30 days provided the flow rate is i 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 pathway may continue for up to 30 days provided grab samples are taken 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 . '

l 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. I i

ACTION 43 - With the number of channels OPERABLE less than required by the minimum channels OPERABLE requirement, effluent releases via the 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 ope, rating curves or actual measurements.

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.0

.,0 TABLE 3-3 J RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE

\ REQUIREMENTS D INSTRUMENT CHANNEL SOURCE CHANNEL ANALOG MODES FOR bl CHECK CHECK CALIBRATION CHANNEL WHICH I g.

OPERATIONAL SURVEILLANCE g TEST IS REQUIRED d 1. Unit vent System

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

Providing Alarm (GT-RE-21)

b. Iodine Sampler W 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.

I

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

l

2. 'l Containment Purge System

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

Providing Alarm and Auto-matic Termination of Re-lease (GT-RE-22, GT-RE-33)

b. Iodine Sampler W 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. Radwaste Building Vent System

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

Providing Alarm and Auto-matic Termination of Release (GH-RE-10)

b. Iodine Sampler W 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. *

*At all times.

l l

l 1

E ]

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$1 O ATTACHMENT A (Page 57 of 163)

~

.0 0 TABLE 3-3 (Continued) 0 TABLE NOTATIONS

\

O (1) The ANALOG CHANNEL OPERATIONAL TESO shall also demonstrate that automatic y isolation of this pathway and control room alarm annunciation as appropriate g occur if any of the following conditions exists:

l 0

L)

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 (alarm only) or

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

(2) The ANALOG CHANNEL OPERAT70NAL TEST shall also demonstrate that control room alarm annunciation occurs 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.

l (3) The initial CHANNEL CALIBRATION shall be performed using one or more of the i reference (gas or liquid and solid) standards certified by the National a Institute of Standards and Technology (NIST) or using standards that have f been obtained from suppliers that participate in measurement assurance {

activities with NIST. These standards shall permit calibrating the system j over its intended range of 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, I or solid source that has been calibrated by relating it to equipment that was i previously (within 30 days) calibrated by the same geometry and type of l 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:

l

a. The specific vent flows by direct measurement, or 4

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

{

c. The fan motor horsepower measured and vent ficw established by the l f an's " flow-horsepower" curve. '

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30 O ATTACHMENT A (Page 58 of 163)

~

..o

,,o 3.4.3 Airborne Radiation Monitor Calibration Methodology

.0 A The following monitors are associated with gaseous releases c

y Monitor ID Monitor Description

Monitor Type 0-GT-RE-21A Plant Unit Vent Particulate, Iodine O o-GH-RE-10A Radwaste Building Effluent Particulate, Iodine U o-GT-RE-21B Plant Unit Vent Wide Range Gas o-GH-RE-10B Radwaste Building Effluent Wide Range Gas 0-GT-RE-22 & 33 Containment Purge Exhaust Particulate, Iodine, Gas o-GT-RE-31 & 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 officiency 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 shall 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 data. At least three sources covering approximately k, b, and k of full scale shall be. checked.

3.4.3.2 Iodine Detector 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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o ATTACHMENT A (Page 59 of 163)

,,o Because of its short half-life and the difficulty in handling

.o gaseous iodine, barium sources shall be used for calibration.

\ The photo peaks of interest are as follows:

O W a. Ba-133: 356 kev gamma is 0.69 efficient / disintegration N

O b. I-131: 364 kev gamma is 0.82 efficient / disintegration h)

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 4, H and h of full scale. The barium counts per minute for each standard shall ce adjusted to iodine counts per minute as described above. A determination of linearity shall be produced using the corrected counts per minute vs. concentration data.

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

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0 0

Sources for all gas detectors shall be produced by evacuating the sample chamber with a vacuum pump. The sample chamber then

\

O shall be backfilled to the desired pressure with a source of standard Xe-133. The source is then counted and the counts per W minute recorded. A determination of linearity shall be produced

\ using the counts per minute vs. concentration data.

U Sources N shall be prepared to cover approximately 4, H and h 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 0-GT-RE-21B and O-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 for the high-range scale shall be extrapolated using the data from the mid-range calibration.

3.4.4 Airborne Monitor setpoints 3.4.4.1 Total Body Dose Rate Setpoint Calculations The limit of the total body dose rate is 500 mrem /yr at the unrestricted area boundary. The monitor alarm / trip setpoint !

based on total body dose will be calculated as follows:

I S. s (SF x AF) x D x R, Where:

Stb = The monitors alarm / trip setpoint based on the total body dose rate. ( Ci/cc)

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

l l

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

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U ATTACHMENT A (Page 61 of 163)

J SF = Normally will be set to 0.85. This number is chosen since the gaseous monitors are set using Xe-133

[\ energy level. Xe-133 comprises 85% of total noble D

gaseous activity expected. (See USAR Table 11.1-1) .

If necessary the 0.85 can be further modified to O

compensate for statistical fluctuations and errors of g measurement.

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:

8: " r , .

3 i

s(X/Q)EKQi i s Where:

c= The monitor response to the gaseous effluent noble gas ( Ci/cc) corresponding to grab sample radionuclide

, concentrations.

(X/d) = 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 1 (mrem /yr per pCi/m3) from Table A.1-2.

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.0 O

0 Qi = Rate of release of noble gas radionuclide i (pCi/sec) (concentration of radionuclide i x release flow rate) 3.4.4.2 Skin Dose Rate' Calculation O 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:

S3 = The monitors alarm / trip setpoint based on the skin dose rate. (pCi/cc)

NOTF.

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

D3 = Limit of 3000 mrem /yr to the skin of the body, conservatively interpreted as a continuous release over a one year period.

R3 = Monitor response per mrem /yr to the skin of the body.

R,=, 3

( (X/Q) E(L + 1.lMi )Qis i

i 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 nrem skin dose per mrad air dose.

1

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~

.,0 Mi= Air dose factor due to gamma emissions from

[\ isotope 1 (mrad /yr per pCi/m3) from Table A.1-2.

43 - .

w The factors SF, AF, c, (X/Q) and Qi are as defined in Section

\ 3.4.4.1.

o U The results of equations from Sections 3.4.4.1 and 3.4.4.2 are l I

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 Alarm setpoint Calculations The Noble Gas Alert Alarm for the Plant Unit Vent (0-GT-RE-21) and Radwaste Building Exhaust Moniter (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 5 10 mrads for gamma radiation and < 20 mrads 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 5 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 Nobla Gas Alert Alana Setpoint Calculation The alert alarm setpoint is the lesser of S, 5 (SF x AF) x Dy x Ry S, 5 (SF x AF) x D x Rp Where:

S, = Monitor setpoint based on gamma radiation.

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.,0 A D, = Limit of 10 mrad /yr conservatively interpreted as a continuous release over a one year period.

(0

[

g R, = Monitor response per mrad /yr determined according to:

O h) R7 =

r, ,

s (X/QJEMii x Qi, 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.

R, = Monitor response per mrad /yr determined according to:

Rp=g, 3

((X/Q)ZN i xQi i s Where:

Ni = Beta air dose factor (mrad /yr per C1/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:

e >

, (10 mrad /yr)(.85)(AF)

. Setpoint(pCi/cc) = ,

(X /Q)[P, x M, x Q a s >>

Where:

Pi = Fractional value of isotope expected, C 1/C T'

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9 ATTACHMENT A ;

(Page 65 of 163) !

"..D O i

.',0 Where: i

\ = Concentration in pCi/cc of isotope.

g Ci

(

0 CT

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

Q = Vent flow rate in cc/sec.

Isotopes used and Pi values are as follows:

ISOTOPE Pi

~

Kr-85M .018 j l

Kr-87 .010 I Kr-88 .033 Xe-133M .017 i

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 Particulate And Iodine Alarm Setpoints !

i 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 calculation used Setpo.

in t(/Ci/cc) = (MPC,)(AF)(SF)

(Q)(X/Q)

Where:

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

= 1 x 10-10 Ci/cc for I-131

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$3 ATTACHMENT A (Page 66 of 163)

} OFFSITE DOSE CALCULATION MANUAL j AF = as defined previously SF = .0625 for I-131'*

(O = .9375 for Cs-137

y

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 M 3/sec This will provide the hi alarm setpoint. The alert alarm setpoint is 10% of the hi alarm setpoint.

i

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r; D ATTACHMENT A (Page 67 of 163) l

~

,o -

0 FIGURE 3.1

.,0 BOUNDARY FOR GASEOUS EFFLUENTS

\

o w N

\

O u

SR RPS l W E ACCES8 ROA E0P/DWIQ HT 8 U LEAR LEARNING CENTER h

E USE LUENTB 9

01 D

q

\ u l

COFFEY COUNTY LAKE FAS 10 DURLINGTO AIN DAW FAS 10 E~= =

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OFFSITE DOSE CALCULATION MANUAL o

4.0 Total Dose

\

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

4.1 Remedial 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, 3.2.2a 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 request for a variance in accordance with the provisions of 40 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. 1/98

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'~

(Page 69 of 163)

j 4.2 surveillance Requirements

\

O 4.2.1 Cumulative dose contributions from liquid and gaseous effluents y shall be determined in accordance with the methodology of g Sections 2.2 and 3.2 at least once per 31 days when the release o of radioactive materials in liquid or gaseous effluents exceed U twice the limits of Section 2.2a, 2.2b, 3.2.la, 3.2.1b, 3.2.2a and 3.2.2b.- Otherwise, no further evaluation is required.

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 data or a combination of both, when necessary. This requirement is applicable only under conditions set forth in the remedial action above.

o l

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J 6.0 Bases A

\ The bases contained on the succeeding pages summarizes the O general requirements of Section 2.0, 3.0, 4.0 and 5.0 of the N ODCM,

\

Section 2.0 Liquid Effluents Section 2.1 Concentration This section is provided to ensure that the concentration of 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.

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 Appendix I, 10 CFR Part 50, to a MEMBER OF THE PUBLIC, and (2) the limits of 10 CFR Part 20.106(e) to the population. The concentration limit for dissolved or entrained 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 dettetion 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 Counting Techniques,

" Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).

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".D D Section 2.2 Dose

..a

\ This section is provided to implement the requirements of C Section II.A, III.A and IV.A of Appendix I, 10 CFR Part 50. The W remedial action implements the guides set forth in Section II.A

\ of Appendix I and provides 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 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.

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.0 0 Section 2.3 Liquid Radwaste Treatment System 0

\ The OPERABILITY of the Liquid Radwaste Treatment Systems ensures O that this system will be available for use whenever liquid effluents require treatment prior to release to the environment.

y, The requirement that the appropriate portions of this system be y used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low )

as is reasonably achievable." This section implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and design objective given in Section II.D of Appendix I to 10 CFR Part 50. The specified 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 Appendix I, 10 CFR Part 50, for liquid effluents.

Section 2.4 Radioactive Liquid Effluent Monitoring 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 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.

I

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] OFFSITE DOSE CALCULATION MANUAL Section 3.0 Gaseous Effluents

\

o Section 3.1 Dose Rate W

g This section is provided to ensure that the dose at any time at p and beyond the SITE BOUNDARY from gaseous effluents from all o 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 CFR 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 Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).

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!M U ATTACHMENT A (Page 74 of 163)

} .

fg Section 3.2.1 Dose - Noble Gases

\

p This section is provided to implement the requirements of

. Section II.B, III.A and IV.A of Appendix I, 10 CFR Part 50. The g-~ remedial action implements the guides set forth in Section II.B p of Appendix I and provides the required operating flexibility U 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 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 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 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 1.111, " Methods for Estimsting 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.

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~

(Page 75 of 163)

A section 3.2.2 Dose - Iodine-131 and 133, Tritium and Radioactive S Material in Particulate Form

\

O This section is provided to implement the requirements of (O 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 y 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 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 CFR 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 existing radionuclide pathways to man, in the areas at and 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.

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~0 Section 3.3 Gaseous Radwaste Treatment System 0

\ The OPERABILITY of the WASTE GAS HOLDUP SYSTEM and the U

VENTILATION EXHAUST TREATMENT SYSTEM ensures that the systems N

will be available for use whenever gaseous effluents require treatment prior to release to the environment. The requirement g that the appropriate portions of this system be used when specified provides reasonable apsurance that the releases of radioactive materials 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 Radioactive Gaseous Effluent Monitoring Instrumentation The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The Alarm / Trip Setpoints for 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 pCi/cc are measurable.

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".D

,0 Section 4.0 Total Dose D

\'

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

[g Part 190 that have been incorporated into 10 CFR Part 20 by 46 FR 18525. The section requires the preparation and submittal of g a.special report whenever the calculated doses due to releases j y 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 mrems. For sites containing up to four reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR Part 190 if the individual reactors remain within twice tne dose design objectives of

' Appendix I, and if direct radiation doses from the reactor Units and from outside storage tanks are kept small. The Special !

I 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 Special Report, it may be assumed that the dose commitment to 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 of 40 CFR Part 190 until NRC staff action is completed. The 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.

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.0 7.2 Annual Radioactive Effluent Release Report The Annual Radioactive Effluent Release Report shall include a 1 y summary of the quantities of radioactive liquid and gaseous i effluents and solid waste released from the Unit as outlined in d Regulatory Guide 1.21, " Measuring, Evaluating, and Reporting y 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 i 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). j 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 radioactive 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.

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.0

,0 The Annual Radioactive Effluent Release Report to be submitted before May 1 of each year shall also include an assessment of g radiation doses to the likely most exposed MEMBER OF THE PUBLIC g from reactor releases and other nearby uranium fuel cycle g sources, including doses from primary effluent pathways and a direct radiation, for the previous calendar year to show y conformance with 40 CFR Part 190, " 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:

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 me'teorological data on site in a file that shall be provided to the NRC upon request.

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 CPR 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.

i L

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4) An evaluation of the change which shows the l

( predicted releases of radioactive materials in liquid and gaseous effluents and/or quantity of l

l O

g solid waste that differ from those previously i predicted in the license application and amendments s

theret.o; a

W '

5) An evaluation of the change, which shows the expected maximum exposures to a MEMBER OF THE PUBLIC in the UNRESTRICTED AREA and to the general population that differ from those previously ,

estimated in the license application and amendments I 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 USAR 16.11.1.1 OR 16.11.3.1. 2/98 l

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

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

I

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I

,0 '

\

O W

\

o DJ APPENDIX A ,

Dose Conversion Factor Tables l l

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.0 TABLE A.1-1*

BIOACCUMULATION FACTORS TO BE USED IN

\ THE ABSENCE OF SITE-SPECIFIED DATA

O (pci/kg per pCi/ liter)

W

\ ELEMENT FRESHWATER FISH O

-M 11 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 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 Co 1.0E 00 Pr 2.5E 01 Nd 2.5E 01 W 1.2E 03 Np 1.0E 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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.0 TABI2 A.1-2 J DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS *

\ Radionuclide Total Body Skin Dose Factor Gamma Air Beta Air O Dose Factor Li Dose Factor Dose Factor N Kg (mrem Iyr per Mg Ng

\ (mremIyr per pCi/m 3) (mrad /yr per (mrad /yr D pCi/m 3) pCi/m') per pCi/m')

)J Kr-83M 7.56E-02** ---

1.93E+01 2.88E+02 Kr-85M 1.17E+03 1.46E+03 1.23E+03 1.97E+03 Kr-85 1.61E+01 1.34E+03 1.72E+01 1.95E+03 Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03 Kr-89 1.66E+04 1.01E+04 1.73E+04 1.06E+04 l Kr-90 1.56E+04 7.29E+03 1.63E+04 7.83E+03 Xe-131M 9.15E+01 4.76E+02 1.56E+02 1.11E+03 Xe-133 2.94E+02 3.06E+02 3.53E+02 1.05E+03 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 Xe-137 1.42E+03 1.22E+04 1.51E+03 1.27E+04 Xe-138 8.83E+03 4.13E+03 9.21E+03 4.75E+03 Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03

Based on Regulatory Guide 1.109 (Rev.1)

-2

- 7.56E-02 = 7.56 x 10

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.0 0 TABLE A.2-1*

.0 INHALATION DOSE FACTORS FOR ADULTS g (MREM PER PCI INHALED)

O NUCLIDE DONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI W

g H 3 NO DATA 1.58E-07 1.58r.-07 1.585-07 1.58E-07 1.58E-07 1.58E-07 O

C 14 2.27E-06 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 NA 24 1.20E-06 1. 2 8:':-0 6 1.28E'06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 h.)

P 32 1.65E-04 9.64E-06 6.26E-06 NO DATA NO DATA NO DATA 1.08E-05 CR 51 NO DATA NO DATA 1.25E-08 7.44E-09 2.85E-09 1.80E-06 4.15E-07 MN 54 NO DATA 4.95E-06 7.87E-07 NO DATA 1.23E-06 1.75E-04 9.67E-06 MN 56 NO DATA 1.55E-10 2.29E-11 NO DATA 1.63E-10 1.18E-06 2.53E-06 i

FE 55 3.07E-06 2.12E-06 4.93E-07 NO DATA NO DATA 9.01E-06 7.54E-07 FE $9 1.47E-06 3.47E-06 1.32E-06 NO DATA NO DATA 1.27E-04 2.35E-05 CO 58 NO DATA 1.98E-07 2.59E-07 NO DATA NO DATA 1.16E-04 1.33E-05 CO 60 NO DATA 1.44E-06 1.85E-06 NO DATA NO DATA 7.46E-04 3.56E-05 NI 63 5.40E-05 3.93E-06 1.81E-06 NO DATA NO DATA 2.23E-05 1.67E-06 NI 65 1.91E-10 2.62E-11 1.14E-11 NO DATA NO DATA 1.00E-07 1.54E-06 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 l ZN 69 4.23E-12 8.14E-12 5.65E-13 NO DATA 5.27E-12 1.15E-07 2.04E-09 BR 83 NO DATA NO DATA 3.01E-08 NO DATA NO DATA NO DATA 2.90E-08 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 RB 88 NO DATA 4.84E-08 2.41E-08 NO DATA NO DATA NO DATA 4.18E-19 RB 89 NO DATA 3.20E-08 2.12E-08 NO DATA NO DATA NO DATA 1.16E-21 SR 89 3.80E-05 NO DATA 1.09E-06 NO DATA NO DATA 1.75E-04 4.37E-05 SR 90 1.24E-02 NO DATA 7.62E-04 NO DATA NO DATA 1.20E-03 9.02E-05 SR 91 7.74E-09 NO DATA 3.13E-10 NO DATA NO DATA 4.56E-06 2.39E-05 SR 92 8.43E-10 NO DATA 3.34E-11 NO DATA NO DATA 2.06E-06 5.38E-06 Y 90 2.61E-07 NO DATA 7.01E-09 NO DATA NO DATA 2.12E-05 6.32E-05 Y 91M 3.26E-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 3.26E-10 NO DATA NO DATA 6.06E-C6 5.27E-05 ER 95 1.34E-05 4.30E-06 2.91E-06 NO DATA 6.77E-06 2.21E-04 1.08E-05 3R 97 1.21E-08 2.45E-09 1.13E-09 NO DATA 3.71E-09 9.84E-06 6.54E-05 NB 95 1.16E-06 9.77E-07 5.26E-07 NO DATA 9.67E-07 6.31E-05 1.30E-05 MO 99 NO DATA 1.51E-08 2.87E-09 NO DATA 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 Regulatory Ouide 1.109 (Retr. 1)

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(Page 85 of 163)

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OFFSITE DOSE CALCULATION' MANUAL 0

0 TAaLE A.2-1*(cont *d)

.0 INHALATION DOSE FACTORS TOR ADULTS

( (MREM PER PCI INHALED)

O NUCLIDE SONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI (4

\. TC 101 5.225-15 7.52F,-15 7.38E-14 NO DATA 1.35E-13 4.995-08 1.36E-21 iD AU 103 1.91E-01 NO DATA 8.23E-08 NO DATA 7.29E-07 6.31E-05 1.38E-05 g RU 105 9.88E-11 NO DATA 3.89E-11 NO DATA 1.27E-10 1.37E-06 6.02E-06 RU 106 8.64E-06 NO DATA 1.09E-06 NO DATA 1.67E-05 1.17E-03 1.14E-04 AG. 110M 1.35E-06 1.25E-06 7.43E-07 .NO DATA 2.46E-06 5.79E-04 3.78E-05 TE 125M 4.27E-07 1.98E-07 5.84E-08 1.31E-07 1.55E-06 3.92E-05 8.83E-06 TE .127M 1.58E-06 7.21E-07 1.96E-07 4.11E-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 8.14E-07 7.17E-06 TE 129M 1.22E-06 5.84E-07 1.98E-07 4.30E-07 4.57E-06 1.45E-04 4.79E-05 TE 129 6.22E-12 2. 99E-12 1.55E-12 4.87E-12 2.34E-11 2.42E-07 1.96E TE' 131M 8.74E-09 5.45E-09 3.63E-09 6.88E-09 3.86E-08 1.82E-05 6.95E-05 TE 131 1.39E-12 7.44E-13 4.49E-13 1.17E-12 5.46E-12 1.74E-07 2.30E-09 .

1 TE 132 3.25E-08 2.69E-00 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 2.56E-06 1.49E-03 7.66E-06 NO DATA 7.85E-07

]

I 132 1.45E-07 4.07E-07 1.45E-07 1.43E-05 6.48E-07 NO DATA 5.08E-08 I 133 1.08E-06 1.85E-06 5.65E-07 2.69E-04 3.23E-06 NO DATA 1.11E-06 I 134 0.0$E-08 2.16E-07 7.69E-08 3.13E-06 3.44E-07 NO DATA 1.26E-10

.I 135 3.35E-07 8.73E-07 3.21E-07 5.60E-05 1.39E-06 NO DATA 6.56E-07 CS 134 4.66E-05 1.06E-04 9.10E-05 NO DATA 3.59E-05 1.22E-05 1.30E-06 CS 136 4.88E-06 1.83E-05 1.38E-05 NO DATA 1.07E-05 1.50E-06 1.46E-06 CS 137 5.98E-05 7.76E-05 5.35E-05 NO DATA 2.70E-05 9.40E-06 1.05E-06 CS 138 4.14E-08 7.76E-08 4.05E-08 HO 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 1.21E-07 NO DATA 2.09E-09 1.59E-04 2.73E-05 BA 141 1.25E-11 9.41E-15 4.20E-13 NO DATA 8.75E-15 2.42E*01 1.45E-17 BA 142 3.29E-12 3.38E-15 2.07E-13 NO DATA 2.86E-15 1.49E-07 1.96E-26 LA 140 4.30E-08 2.17E-08 5.73E-09 NO DATA NO DATA 1.70E-05 5.73E-05 LA 142 0.54E-11 3.88E-11 9.65E-12 NO DATA NO DATA 7.91E-07 2.64E-07 CE 141 2.49E-06 1.69E-06 1.91E-07 NO DATA 7.83E-07 4.52E-05 1.50E-05 CE 143 2.33E-08 1.72E-08 1.91E-09 NO DATA 7.60E-09 9.97E-06 2.83E-05 CE 144 4.29E-04 1.79E-04 2.30E-05 NO DATA 1.06E-04 9.72E-04 1.02E-04 PR 143 1.17E-06 4.69E-07 5.80E-08 NO DATA 2.70E-07 3.51E-05 2.50E-05 PR 144 3.76E-12 1.56E-12 1.91E-13 NO DATA 8.81E-13 1.27E-07 2.69E-18 ND 147 6.59E-07 7.62E-07 4.56E-03 NO bATA 4.45E-07 2.76E-05 2.16E-05 W 187 1.06E-09 8.85E-10 3.10E-10 NO DATA NO DATA 3.63E-06 1.94E-05 NP 239 2.87E-08 2.82E-09 1.55E-09 HO DATA 8.75E-09 4.70E-06 1.49E-05

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~0 TABLE A.2-26

,,0 INHALATION DOSE FACTORS FOR TEENAGER g (MREM PER PCI INHALED)

U NUCLIDE BONE LIVER T DODY THYROID KIDNEY LUNG GI-LLI N

\ H 3 NO DATA 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07

g. C 14 3.25E-06 6.095-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 g NA 24 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 P 32 2.36E-04 1.37E-05 8.95E-06 NO DATA NO DATA NO DATA 1.16E-05 CR 51 NO DATA NO DATA 1.69E-08 9.37E-09 3.84E-09 2.62E-06 3.75E-07 MN 54 NO DATA 6.39E-06 1.05E-06 NO DATA 1.59E-06 2.48E-04 8.35E-06 KN 56 NO DATA 2.12E-10 3.15E-11 NO DATA 2.24E-10 1.90E-06 7.18E-06 FE 55 4.18E-06 2.98E-06 6.93E-07 NO DATA NO DATA 1.55E-05 7.99E-07 rE 59 1.99E-06 4.62E-06 1.79E-06 NO DATA NO DATA 1.91E-04 2.23E-05 CO 58 NO DATA 2.59E-07 3.47E-07 NO DATA NO DATA 1.68E-04 1.19E-05 CO 60 NO DATA 1.89E-06 2.40E-06 NO DATA NO DATA 1.09E-03 3.24E-05 NI 63 7.255-05 5.435-06 2.47E-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 4.59E-06 CU 64 NO DATA 2.54E-10 1.06E-10 NO DATA 8.01E-10 1.39E-06 7.68E-06 ZN 65 4.82E-06 1.67E-05 7.80E-06 NO DATA 1.08E-05 1.55E-04 5.83E-06 ZN 69 6.04E-12 1.15E-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 5.41E-08 NO DATA NO DATA NO DATA LT E-24 BR 85 NO DATA NO DATA 2.29M-09 NO DATA NO DATA NO DATA LT E-24 I RB 86 NO DATA 2.38E-05 1.05E-05 NO DATA NO DATA NO DATA 2.21E-06 l RB 88 NO DATA 6.82E-08 3.40E-08 NO CATA NO DATA NO DATA 3.65E-15 l RB 89 NO DATA 4.40E-08 2.91E-08 NO DATA NO DATA NO DATA 4.225-17 SR 89 5.43E-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 9.56E-05 SR 91 1.10E-08 NO DATA 4.39E-10 NO DATA NO DATA 7.59E-06 3.24E-05 SR 92 1.19E-09 NO DATA 5.08E-11 NO DATA NO DATA 3.43E-06 1.495-05 Y 90 3.73E-07 NO DATA 1.00E-08 NO DATA NO DATA 3.66E-05 6.99E-05 Y 91M 4.63E-11 NO DATA 1.77E-12 NO DATA NO DATA 4.00E-07 3.77E-09 Y 91 8.26E-05 NO DATA 2.21E-06 NO DATA NO DATA 3.67E-04 5.11E-05 Y 92 1.84E-09 NO DATA 5.36E-11 NO DATA NO DATA 3.35E-06 2.06E-05 Y 93 1.69E-08 NO DATA 4.65E-10 NO DATA NO DATA 1.04E-05 7.24E-05 !

ER 95 1.82E-05 5.73E-06 3.94E-06 NO DATA 8.42E-06 3.36E-04 1.86E-05 :

ZR 97 1.12E-08 3.40E-09 1.57E-09 NO DATA 5.15E-09 1.62E-05 7.88E-05 l i

NB 95 2.32E-06 1.29E-06 7.08E-07 NO DATA 1.25E-06 9.39E-05 1.21E-05 j MO 99 NO DATA 2.11E-08 4.03E-09 NO DATA 5.14E-08 1.92E-05 3.36E-05 .

TC 99M 1.73E-13 4.83E-13 6.24E-12 NO DATA 7.20E-12 1.44E-07 7.66E-07 l

Talen from Regulatory Guide 1.109 (Per.1)

Czrrett Crpy Proc:d re 99-0412 09;o7:01 H

3 Revision: 2 OFFSITE DOSE CALCULATION MANUAL AP 078-003 10 43 Reference Use Page 92 of 168 m

9 ATTACHMENT A (Page 87 of 163) 0FFSITE DOSE CALCULATION MANUAL 40 l

.0

TAala A.2-2* (cont' d) l D INHAI.ATION DOSE FACTORS FOR TEENAGER

\ (MREM PER PCI INHALED)

O NucLIoE sone t.IVER T DODY THYROID MIDNEY LUNG CI LLI N

\ TC 101 7.40E-15 1.05E-14 1.03E-13 NO DATA 1.90E-13 8.34E-08 1.09E-16 g RU 103 2.63E-07 NO DATA 1.12E-07 NO DATA 9.29E-07 9.79E-05 1.36E-05 g RU 105 1.40E-10 NO DATA 5.42E-11 NO DATA 1.76E-10 2.27E-06 1.13E-05 RU 106 1.23E-05 NO DATA 1.55E-06 NO DATA 2.38E-05 2.01E-03 1.20E-04 AG 110M 1.73E-06 1.64E-06 9.99E-07 NO DATA 3.13E-06 8.44E-04 3.41E-05 TE 125M 6.10E-07 2.80E-07 8.34E-08 1.75E-07 NO DATA 6.10E-05 9.38E-06 TE 127M 2.25E-06 1.02E-06 2.73E-07 5.48E-07 8.17E-06 2.07E-04 1.99E-05 TE 127 2.51E-10 1.14E-10 5.52E-11 1.77E-10 9,10E-10 1.40E-06 1.015-05 TE 129M 1.74E-06 8.23E-07 2.81E-07 5.72E-07 6.49E-06 2.47E-04 5.06E-05 TE 129 8.87E-12 4.22E-12 2.20E-12 6.48E-12 3.32E-11 4.12E-07 2.02E-07 TE 131M 1.23E-08 7.51E-09 5.03E-09 9.06E-09 5.49E-08 2.97E-05 7.76E-05 TE 131 1.97E-12 1.04E-12 6.30E-13 1.55E-12 7.72E-12 2.92E-07 1.89E-09 TE 132 4.50E-08 3.63E-08 2.74E-08 3.07E-08 2.44E-07 5.61E-05 5.79E-05 I 130 7.80E-07 2.24E-06 8.96E-07 1.86E-04 3.44E-06 NO DATA 1.14E-06 I 131 4.43E-06 6.14E-06 3.30E-06 1.83E-03 1.05E-05 NO DATA 8.11E-07 I 132 1.99E-07 5.47E-07 1.97E-07 1.89E-05 0.65E-07 NO DATA 1.59E-07 I 133 1.52E-06 2.56E-06 7.78E-07 3.65E-04 4.49E-06 NO DATA 1.29E-06 I 134 1.11E-07 2.90E-07 1.05E-07 4.94E-06 4.58E-07 NO DATA 2.55E-09 I 135 4.62E-07 1.18E-06 4.36E-07 7.76E-05 1.86E-06 NO DATA 8.69E-07 CS 134 6.288-05 1.41E-04 6.86E-05 NO DATA 4.69E-05 1.83E-05 1.22E-06 CS 136 6.44E-06 2.42E-05 1.71E-05 NO DATA 1.38E-05 2.22E-06 1.36E-06 CS 137 8.38E-05 1.06E-04 3.89E-05 NO DATA 3.80E-05 1.51E-05 1.06E-06 CS 138 5.82E-08 1.07E-07 5.58E-08 NO DATA 8.20E-08 9.84E-09 3.38E-11 BA 139 1.67E-10 1.18E-13 4.87E-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 BA 141 1.78E-11 1.32E-14 5.93E-13 NO DATA 1.23E-14 4.11E-07 9.33E-14 BA 142 4.62E-12 4.63E-15 2.84E-13 NO DATA 3.92E-15 2.39E-07 5.99E-20 LA 140 5.99E-08 2.95E-08 7.82E-09 NO DATA NO DATA 2.68E-05 6.09E-05 LA 142 1.20E-10 5.31E-11 1.32E-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 3.32E-08 2.42E-08 2.70E-09 NO DATA 1.08E-08 1.63E-05 3.19E-05 CE 144 6.11E-04 2.53E-04 3.28E-05 NO CATA 1.51E-04 1.67E-03 1.08E-04 PR 143 1.67E-06 6.64E-07 8.28E-08 NO CATA 3.86E-07 6.04E-05 2.67E-05 PR 144 5.37E-12 2.20E-12 2.72E-13 NO DATA 1.26E-12 2.19E-07 2.94E-14 ND 147 9.83E-07 1.07E-06 6.41E-08 NO DATA 6.20E-07 4.65E-05 2.28E-05

)

1 W 187 1.50E-09 1.22E-09 4.29E-10 NO CATA NO DATA 5.92E-06 2.21E-05 NP 239 4.23E-08 3.99E-09 2.21E-09 NO CATA 1.25E-08 8.11E-06 1.65E-05 1

l OtrroIt CIpy Proc:dzro 99-0412 09:07IO1 4

U Revision: 2 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 1

Reference Use 9 Page 93 of 168 m \

i p ATTACHMENT A )

(Page 88 of 163) !

.,D

,0 TAaLa A.2-3*

J INHALATION DOSE FACTORS FOR CHILD

_g (MREM PER PCI INHALED)

O NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI bJ g 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-06 1.02E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 O NA 24 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 Al 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-00 2.31E-08 6.57E-09 4.59E-06 2.93E-07 MN 54 NO DATA 1.16E-05 2.57E-06 NO DATA 2.71E-06 4.26E-04 6.19E-06 MN 56 NO DATA 4.48E-10 0.43E-11 NO DATA 4.52E-10 3.55E-06 3.33E-05 FE 55 1.28E-05 6.80E-06 2.10E-06 NO DATA NO DATA 3.00E-05 7.75E-07 FE 59 5.59E-06 9.04E-06 4.51E-06 NO DATA NO DATA 3.43E-04 1.91E-05 CO 58 NO DATA 4.79E-07 8.55E 07 NO DATA NO DATA 2.99E-04 9.29E-06 CO 60 NO DATA 3.55E-06 6.12E-06 NO DATA NO DATA 1.91E-03 2.60E-05 NI 63 2.22E-04 1.25E-05 1.56E-06 NO DATA NO DATA 7.43E-05 1.71E-06 NI 65 0.08E-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 EN 65 1.15E-05 3.06E-05 1.90E-05 NO DATA 1.93E-05 2.69E-04 4.11E-06 ZN 69 1.81E-11 2.61E-11 2.41E-12 NO DATA 1.58E-11 3.84E-07 2.75E-06 BR 83 NO DATA' HO DATA 1.28E-07 NO DATA NO DATA NO DATA LT E-24 BR 84 NO DATA NO DATA 1.48E-07 NO DATA NO DATA NO DATA LT E-24 BR 85 NO DATA NO DATA 6.84E-09 NO DATA NO DATA NO DATA LT E-24 RB 86 NO DATA 5.36E-05 3.09E-05 NO DATA NO DATA NO DATA 2.16E-06 RB 88 NO DATA 1.52E-07 9.90E-08 NO DATA NO DATA NO DATA 4.6eE-09 RB 89 NO DATA 9.33E-08 7.83E-08 NO DATA NO DATA NO DATA 5.11E-10 SR 89 1.62E-04 NO DATA 4.66E-06 NO DATA NO DATA 5.83E-04 4.52E-05 SR 90 2.73E-02 NO DATA 1.74E-03 NO DATA NO DATA 3.99E-03 9.28E-05 SR 91 3.28E-08 NO DATA 1.24E-09 NO DATA NO DATA 1.44E-05 4.70E-05 SR 92 3.54E-09 NO DATA 1.42E-10 NO DATA NO DATA 6.49E-06 6.55E-05 Y 90 1.11E-06 NO DATA 2.99E-00 NO DATA NO DATA 7.01E-05 7.24E-05 Y 91H 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 5.07E-08 7.34E-09 4.32E-09 NO DATA 1.05E-08 3.06E-05 9.49E-05 NB 95 6.35E-06 2.48E-06 1.77E-06 NO DATA 2.33E-06 1.66E-04 1.00E-05 HO 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 froan Regulatory Guide 1.109 (Rev. 1)

CYrre;t Copy ProcedIre 99-0412 09:07;01 D Revision: 2 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 3

N Reference Use Page 94 of 168 o

m C ATTACHMENT A (Page 89 of 163) 0FFSITE DOSE CALCULATION MANUAL

.0

.0 TABLE A.2-3* (cont' d)

.0 INHALATION DOSE FACTORS FOR CHILD (MREM PER PCI INHALED)

O N'JCLIDE BONE LIVER T DODY THYROID KIDNEY LONG GI-LLI W

g 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 O RU 105 4.13E-10 NO DATA 1.50E-10 NO DATA 3.G3E-10 4.30E-06 2.69E-05 W

RU 106 3.69E-05 NO DATA 4.57E-06 NO DATA 4.97E-05 3.87E-03 1.16E-04 AG 110M 4.56E-06 3.08E-06 2.47E-06 NO DATA 5.74E-06 1.48E-03 2.71E-05 TE 125M 1.82E-06 6.29E-07 2.47E-07 5.20E-07 NO DATA 1.29E-04 9.13E-06 TE 127M 6.72E-06 2.31E-06 8.16E-07 1.64E-06 1.72E-05 4.00E-04 1.93E-05 TE 127 7.49E-10 2.57E-10 1.655-10 5.30E-10 1.91E-09 2.71E-06 1.52E-05 TE 129M 5.19E-06 1.85E-06 8.22E-07 1.71E-06 1.36E-05 4.16E-04 4.91E-05 TE 129 2.64E-11 9.45E-12 6.44E-12 1.93E-11 6.94E-11 7.93E-07 6.89E-06l TE 131M 3.63E-08 1.60E-08 1.37E-08 2.64E-08 1.08E-07 5.56E-05 8.32E-05 TE 131 5.87E-12 2.28E-12 1.78E-12 4.59E-12 1.59E-11 5.55E-07 3.60E-07 TE 132 1.30E-07 7.36E-08 7.125-08 8.58E-08 4.19E-07 1.02E-04 3.72E-05 I 130 2.21E-06 4.43E-06 2.20E-06 4.99E-04 6.61E-06 NO DATA 1.38E-06 l I 131 1.30E-05 1.30E-05 7.37E-06 4.39E-03 2.13E-05 NO DATA 7.68E-07 '

I 132 5.72E-07 1.10E-06 5.07E-07 5.23E-05 1.69E-06 NO DATA 8.65E-07 I 133 4.48E-06 5.49E-06 2.00E-06 1.04E-03 9.13E-06 NO DATA 1.48E-06 I 134 3.17E-07 5.84E-07 2.69E-07 1.37E-05 8.92E-07 NO DATA 2.58E-07 I 135 1.33E-06 2.36E-06 1.12E-06 2.14E-04 3.62E-06 NO DATA 1.20E-06 i CS 134 1.76E-04 2.74E-04 6.07E-05 NO DATA 8.93E-05 3.27E-05 1.04E-06 l CS 136 1.76E-05 4.62E-05 3.14E-05 NO DATA 2.58E-05 3.93E-06 1.13E-06 CS 137 2.45E-04 2.23E-04 3.47E-05 NO DATA 1.63E-05 2.81E-05 9.78E-07 CS 138 1.71E-07 2.27E-07 1.50E-07 NO DATA 1.68E-07 1.84E-08 7.29E-08 BA 139 4.98E-10 2.66E-13 1.45E-11 NO DATA 2.33E-13 1.56E-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 BA 142 1. 3 5,E- 11 9.73E-15 7.54E-13 NO DATA 7.87E-15 4.44E-07 7.41E-10 LA 14C 1.74E-07 6.00E-08 2.04E-08 NO DATA NO DATA 4.94E-05 6.10E-05 LA 142 3.50E-10 1.11E-10 3.49E-11 NO DATA NO DATA 2.35E-06 2.05E-05 CE 141 1.06E-05 5.28E-06 7.83E-07 NO DATA 2.31E-06 1.47E-04 1.53E-05 CE 143 9.89E-08 5.37E-08 7.77E-09 NO DATA 2.26E-08 3.12E-05 3.44E-05 CE 144 1.83E-03 5.72E-04 9.77E-05 NO DATA 3.17E-04 3.23E-03 1.05E-04 PR 143 4.99E-06 1.50E-06 2.47E-07 NO DATA 8.11E-07 1.17E-04 2.63E-05 PR 144 1.61E-11 4.99E-12 8.10E-13 NO DATA 2.64E-12 4.23E-07 5.32E-08 ND 147 2.92E-06 2.36E-06 1.84E-07 NO DATA 1.30E-06 8.87E-05 2.22E-05 W 181 4.41E-09 2.61E-09 1.17E-09 NO DATA NO DATA 1.11E-05 2.46E-05 NP 239 1.26E-07 9.04E-09 6.35E-09 NO DATA 2.63E-08 1.5hE-05 1.73E-05 1/98

{ l Ccrrxt G:py ProcO2re 99-04-12 09.07iO1 '

D Revision: 2 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 3

N Reference Use Page 95 of 168 9

m 1 1

f> ATTACHMENT A (Page 90 of 163)

.0

..D TABLE A.2-46

,,g INHALATION DOSE FACTORS FOR INFANT (MREM PER PCI INHALED)

O N'JCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI W

g H 3 NO DATA 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.625-07 C 14 1.89E-05 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 O NA 24 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 h)

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 MN 56 NO DATA 1.10E-09 1.58E-10 NO DATA 7.86E-10 8.95E-06 5.12E-05 FE 55 1.41E-05 8.39E-06 2.38E-06 NO DATA NO DATA 6.11E-05 7.82E-07 FE 59 9.69E-06 1.68E-05 6.77E-06 NO DATA NO DATA 7.25E-04 1.77E-05 CO 58 NO DATA 8.71E-07 1.30E-06 NO DATA NO DATA 5.553-04 7.95E-06 CO 60 NO DATA 5.73E-06 8.41E-06 NO DATA NO DATA 3.2211-03 2.28E-05 NI 63 2.42E-04 1.46E-05 8.29E-06 NO DATA NO DATA 1.49E-04 1.73E-06 NI 65 1.71E-09 2.03E-10 8.79E-11 NO DATA NO DATA 5.80E-06 3.58E-05 CU 64 NO DATA 1.34E-09 5.53E-10 NO DATA 2.84E-09 6.64E-06 1.07E-05 ZN 65 1.38E-05 4.47E-05 2.22E-05 NO DATA 2.32E-05 4.62E-04 3.67E-05 ZN 69 3.85E-11 6.91E-11 5.13E-12 NO DATA 2.87E-11 1.0$E-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 1.36E-04 6.30E-05 NO DATA NO DATA NO DATA 2.17E-06 RB 88 NO DATA 3.98E-07 2.05E-07 NO DATA NO DATA NO DATA 2.42E-07 RB 89 NO DATA 2.29E-07 1.47E-07 NO DATA NO DATA NO DATA 4. 8 7E- 08 SR 89 2.84E-04 NO DATA 8.15E-05 NO DATA NO DATA 1.45E-03 4.57E-05 SR 90 2.92E-02 NO DATA 1.85E-03 NO DATA NO DATA 8.03E-03 0.36E-05 SR 91 6.83E-08 NO DATA 2.47E-09 NO DATA NO DATA 3.76E-05 5.24E-05 SR 92 1.50E-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+s6 Y 91 4.20E-04 NO DATA 1.12E-05 NO DATA NO DATA 1.75E-03 5.02E-05 Y 92 1.17E-08 NO DATA 3.29E-10 NO DATA NO DATA 1.75E-05 9.04E-05 Y 93 1.07E-07 NO DATA 2.91E-09 NO DATA NO DATA 5.46E-05 1.19E-04 l ZR 95 8.24E-05 1.99E-05 1.45E-05 NO DATA 2.22E-05 1.25E-03 1.55E-05 ZR 97 1.07E-07 1.83E-08 8.36E-09 NO DATA 1.85E-08 7.88E-05 1.00E-04 NB 95 1.12E-05 4.59E-06 2.7CE-06 NO DATA 3.37E-06 3.42E-04 9.05E-06 MO 99 NO DATA 1.18E-07 2.31E-08 NO DATA 1.89E-07 9.63E-05 3.40E-05 TC 99M 9.98E-13 2.06E-12 2.66E-11 NO DATA 2.22E-11 5.19E-07 1.45E-06

Taken from Regulatory Guide 1.109 (Rev. 1) 1/98

' CYrrext Copy Proc: dire 99 0442 09:07I01 Revision: 2 ;OFFSITE DOSE CALCULATION MANUAL AP 07B-003 Reference Use: Page 96 Of 168~

M.

-U ATTACHMENT A (Page 91 of 163)

~

.0

.0 TAala A.2-4* (cont' d)

.,0 : INHALATION DOSE FACTORS FOR INFANT g (MREM PER PCI INMALED)

'D 'NUCLIDE -BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI W

g TC 101 '4 . 6 5E-14 5.8BE-14 5.80E-13 NO DATA 6.99E-13 4.17E-07 6.03E-07

-RU 103 1.44E-06 .NO DATA 4.85E-07 NO DATA 3.03E-06 3.94E-04 1.15E-05

-N 8.74E-10 RU 105 NO DATA '2.93E NO DATA 6.42E-10 1.12E-05 3.46E-05 M

RU 106- '.20E 6 05 NO DATA 7.77E-06 NO DATA 7.61E-05 8.26E-03 1.17E-04 AG 110M 7.13E-06 5.16E-06 3.57E-06 NO DATA 7.80E-06 2.62E-03 2.36E-05

> TE 125M 3.40E-06 1.42E-06 4.70E-07 1'.16E-06 NO DATA 3.19E-04 9.22E-06

'TE 127M 1.19E-05 4.93E-06 1.48E 3.48E-06 2.68E-05 9.??E-04 1.95E-05 TE 127 1.59E 6.81E-10 3.49E-10 1.32E-09 3.47E-09 7.39E-06 1.74E-05 TE 129M 1.01E-05 4.35E 1.59E-06 3.91E-06 2.27E-05 1.20E-03 4.93E-05 TE 129 5.63E-11 2.48E 1.34E-11 4.82E-11 1.25E-10 2.14E-06 1.88E-05 TE '131M 1.62E-08 3.93E-08 2.59E-08 6.38E-08 1.89E-07 1.42E-04 8.51E-05

- TE 131 1.24E-11 5.87E-12 3.57E-12 1.13E-11 2.85E-11 1.47E-06 5.87E-06 TE . 132 2.66E-07 1.69E-07 1.26E-07 1.99E-07 7.39E-07 2.43E-04 3.15E-05 I 130 4.54E-06 9.91E-06 3.98E-06 1.14E-03 1.09E-05 NO DATA 1.42E-06 I 131 2.71E-05 3.17E-05 1.40E-05 1.06E-02 3.70E-05 NO DATA 7.56E-07 I- 132 -1.21E-06 2.53E-06 8.99E-07 1.21E-04 2.82E -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 1.98E-06 4.97E-04 6.0$E-06 NO DATA 1.31E-06 CS 134 2.83E-04 5.02E-04 5.32E-05 NO DATA 1.36E-04 5.69E-05 9.53E-07 CS '136 3.45E-05 9.61E-05 3.78E-05 NO DATA 4.03E-05 8.40E-06 1.02E-06 CS 13T 3.92E-04 4.37E-04 3.25E-05 NO DATA 1.23E-04 5.09E-05 9.53E-07

'CS 138 3.61E-07 5.58E-07 2.84E-07 NO DATA 2.93E-07 4.67E-08 6.26E-07

^ BA ' 139 1.06E-09 1.03E-13 3.07E-11 NO DATA 4.23E-13 4.25E-06 3.64E-05 BA ' 140 4.00E-05 4.00E-08 2.07E-06 NO DATA 9.59E-09 1.14E-03 2.74E-05 BA 141 1.12E-10 7.70E-14 3.55E-12 -NO DATA 4.64r-14 2.12E-06 3.39E-06 BA - 142 2.84E-11 2.36E-14 1.40E-12 NO DATA 1.36E-14 1.11E-06 4.95E-07 LA 140 3.61E-07 1.43E-07 3.68E NO DATA NO DATA 1.20E-04 6.06E-05 LA 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. 0 9E-07 -- 1.38E-07 1.58E-08 NO DATA 4.03E-08 8.30E-05 3.55E-05 CE 144 2.28E-03 8.65E-04 1.26E-04 NO DATA- 3.84E-04 7.03E-03 1.06E-04 PR 143 1.00E 3.74E-06 4.99E-07 NO DATA 1.41E-06 3.09E-04 2.66E-05 PR 144 3.42E-11 1.32E-11 1.72E-12 NO DATA 4.80E-12 1.15E-06 3.06E-06 ND 147 5.67E-06 5.81E-06 3.57E-07 NO DATA 2.25E-06 2.30E-04 2.23E-05 N 181 9.26E-09 6. 4 4E-0 9 2.23E-09 NO DATA NO DATA 2.83E-05 2.54E-05 NP- 239 2.65E-07 2.37E-08 1.34E-08 NO DATA 4.73E-08 4.25E-05 1.78E-05

OtrroIt Ospy ProcedIre 99-0412 09:07;01 D,5 Revision: 2 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 N Reference Use Page 97 of 168

$i)

M C ATTACHMENT A (Page 92 of 163)

.0

.0 TABLE A.2-5*

D EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND

( (mrem /hr per pCi/m')

O ELEMENT TOTAL BODY SKIN N

\ H-3 0.0 0.0 g C-14 0.0 0.0 Na-24 2.50E-08 2.90E-08 N P-32 0.0 0.0 Cr-51 2.20E-10 2.60E-10 Mn-54 5.80E-09 6.80E-09 Mn-56 1.10E-08 1.30E-08 Fe-55 0.0 0.0 re-59 8.00E-09 9.40E-09 Co-58 7.00E-09 8.20E-09 Co-60 1.70E-08 2.00E-08 Ni-63 0.0 0.0 Ni-65 3.70E-09 4.30E-09 Cu-64 1.50E-09 1.70E-09 En-65 4.00E-09 4.60E-09 Zn-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 1.50E-08 1.80E-08 Sr-89 5.60E-13 6.50E-13 Sr-91 7.10E-09 8.30E-09 Sr-92 9.00E-09 1.00E-08 Y-90 2.20E-12 2.60E-12 Y-91M 3.80E-09 4.40E-09 Y-91 2.40E-11 2.70E-11 Y-92 1.60E-09 '1.90E-09 Y-93 5.70E-10 7.80E-10 Er-95 5.00E-09 5.80E-09 Er-97 5.50E-09 6.40E-09 Nb-95 5.10E-09 6.00E-09 Mo-99 1.90E-09 2.20E-09 Tc-99M 9.60E-10 1.10E-09 Tc-101 2.70E-09 3.00E-09 Ru-103 3.60E-09 4.20E-09 Ru-105 4.50E-09 5.10E-09 Ru-106 1.50E-09 1.80E-09 Ag-110M 1.80E-08 2.10E-08 Te-125M 3.50E-11 4.80E-11 Te-127M 1.10E-12 1.30E-12 Te-127 1.00E-11 1.10E-11 Te-129M 7.70E-10 9.00E-10 Te-129 7.10E-10 8.40E-10

Taken from Regulatory Guide 1.109 (Rev. 1) .

I l

CIrrelt Capy Procedre 99-0412 09107101 iH 3 Revision: 2 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 h Reference Use Page 98 of 168 itn U ATTACHMENT A (Page 93 of 163)

."0 4 TABLE A.2-5* (cont' d)

J EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND

\ (mrem /hr per pCi/m')

O

.g ELEMENT TOTAL BODY SKIN Te-131M 8.40E-09 9.905-09 i

\ Te-131 2.20E-09 2.60E-06 l (3 Te-132 1.70E-09 2.00E-09 gj 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 l Cs-136 1.50E-08 1.70E-08 Cs-137 4.20E-09 4.905-09 i Cs-138 2.10E-00 2.40E-08 l Ba-139 2.40E-09 2.70E-09 Ba-140 2.10E-09 2.40E-09 !

Ba-141 4.30E-09 4.90E-09 Ba-142 7.90E-09 9.00E-09 La-140 1.50E-08 1.70E-08 La-142 1.50E-08 1.80E-08 Ce-141 5.50E-10 6.20E-10 Ce-143 2.20E-09 2.50E-09 Ce-144 3.20E-10 3.70E-10 i Pr-143 0.0 0.0 i 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

i

)

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&rrelt CIpy Proc 74hre 99 0412 09:07i01 N Revision: ' OFiSITE DOSE CALCULATION MANUAL AP 07B-003 I

Reference Use Page 99 of 168 Sn 9 ATTACHMENT A (Page 94 of 163) 0FFSITE DOSE CALCULATION MANUAL

.D D TAaLa A.3-1+

.0 INGESTION DOSE FACTORS FOR ADULTS

, (MREM PER PCI INGESTED)

C NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI N

ig H 3 NO DATA 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 C 14 2.84E-06 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 O NA 24 1.70s-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 U

P 32 1.93E-04 1.20E-05 7.46E-06 NO DATA NO DATA NO DATA 2.17E-05 CR 51 NO DATA NO DATA 2.66E-09 1.59E-09 5.86E-10 3.53E-09 6.69E-07 MN 54 NO DATA 4.57E-06 8.72E-07 NO DATA 1.36E-06 NO DATA 1.40E-05 HN 56 NO DATA 1.15E-07 2.04E-08 NO DATA 1.46E-07 NO DATA 3.67E-06 TE SS 2.15E-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 58 NO DATA 7.45E-07 1.67E-06 NO DATA NO DATA NO DATA 1.51E-05 CO 60 NO DATA 2.14E-06 4.72E-06 NO DATA NO DATA NO DATA 4.02E-05 NI 63 1.30E-04 9.01E-06 4.36E-06 NO DATA NO DATA NO DATA 1.88E-06 NI 65 5.28E-07 6.86E-08 3.13E-08 NO DATA NO DATA NO DATA 1.74E-06 CU 64 NO DATA 8.33E-08 3.91E-08 NO DATA 2.10E-07 NO DATA 7. ME-0 6 EN 65 4.84E-06 1.54E-05 6.96E-06 NO DATA 1.03E-05 NO DATA 9.70E-06 EN 69 1.03E-08 1.91E-08 1.37E-09 NO DATA 1.263-98 NO DATA 2.96E-09 BR 83 NO DATA NO DATA 4.02E-08 NO DATA NO DATA NO DATA 5.79E-08 BR 84 NO DATA NO DATA 5.21E-08 NO DATA NO DATA NO DATA 4.09E-13 BR 85 NO DATA NO DATA 2.14E-09 NO DATA NO DATA NO DATA LT E-24 RB 86 NO DATA 2.11E-05 9.83E-06 NO DATA NO DATA NO DATA 4.16E-06 RB 88 NO DATA 6.05E-09 3.21E-08 NO DATA NO DATA NO DATA 8.36E-19 RD 89 NO DATA 4.01E-08 2.82E-08 NO DATA NO DATA NO DATA 2.33E-21 SR 89 3.08E-04 NO DATA 8.84E-06 NO DATA NO DATA NO DATA 4.94E-05 SR 90 1.58E-03 NO DATA 1.86E-03 NO DATA NO DATA NO DATA 2.19E-04 l SR 91 5.67E-06 NO DATA 2.29E-07 NO DATA NO DATA NO DATA 2.70E-05 SR 92 2.15E-06 NO DATA 9.30E-08 NO DATA NO DATA NO DATA 4.26E-05 Y 90 9.62E-09 NO DATA 2.58E-10 NO DATA NO DATA NO DATA 1.02E-04 Y 91M 9.09E-11 NO DATA 3.52E-12 NO DATA NO DATA NO DATA 2.67E-10 Y 91 1.41E-07 NO DATA 3.778-09 NO DATA NO DATA *NO DATA 7.76E-05 Y 92 8.45E-10 NO DATA 2.47E-11 NO DATA NO DATA NO DATA 1.48E-05 Y 93 2.68E-09 NO DATA 7.40E-11 NO DATA NO DATA NO DATA 8.50E-05 ER 95 3.04E-08 9.75E-09 6.60E-09 NO DATA 1.53E-08 NO DATA 3.09E-05 ER 97 1.68E-09 3.39E-10 1.55E-10 NO DATA 5.12E-10 NO DATA 1.0$E-04 NB 95 6.22E-09 3.46E-09 1.86E-09 NO DATA 3.42E-09 NO DATA 2.10E-05 NO 99 NO DATA 4.31E-06 8.20E-07 NO DATA 9.76E-06 NO DATA 9.99E-06 TC 99M 2.47E-10 6.98E-10 8.89E-09 NO DATA 1.06E-08 3.42E-10 4.13E-07

Taken from stegulatory Guide 1.109 (Rev. 1) 2/98

Cirre;t Ospy Proc 5d re 99-0412 09:07iO1 H 1 Revision: 2 3 OFFSITE DOSE CALCULATION MANUAL AP 0~/B-003

$ Reference Use Page 100 Of 168 dn 9 ATTACHMENT A (Page 95 of 163) 0FFSITE DOSE CALCULATION MANUAL

.".0

.0 TAaLE A.3-1* (Cont' d) 0 INGESTION DOSE FACTORS FOR ADULTS g (MREM PER PCI INGESTED)

U NUCLIDE BONE LIVER T BODY THYROID KIDNEY LONG GI-LLI N

N TC 101 2.54E-10 3.66E-10 3.59E-09 NO DATA 6.59r.-09 1.87E-10 1.10E-21 g RU 103 1.85E-07 NO DATA 7.97E-08 NO DATA 7.06E-07 NO DATA 2.16E-05 RU 105 1.54E-08 NO DATA 6.0BE-09 NO DATA 1.99E-07 NO DATA 9.42E-06 RU 106 2.75E-06 NO DATA 3.48E-07 NO DATA 5.31E-06 NO DATA 1.78E-04 AG 110M 1.60E-07 1.48E-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 1.0?E-05 TE 127M 6.77E-06 2.42E-06 8.2bE-07 1.73E-06 2.75E-05 NO DATA 2.27E-05 TE 127 1.10E-07 3.95E-08 2.38E-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 4.00E-05 NO DATA 5.79E-05 TE 129 3.14E-08 1.18E-08 7.65E-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 8.57E-06 NO DATA 8.40E-05 TE 131 1.97E-08 8.23E-09 6.22E-09 1.62E-08 8.63E-08 NO DATA 2.19E-09 TE 132 2.52E-06 1.63E-06 1.53E-06 1.80E-06 1.57E-05 NO DATA 7.71E-05 I 130 7.56E-07 2.23E-06 8.80E-07 1.89E-04 3.48E-06 NO DATA 1.92E-06 I 131 4.16E-06 5.95E-06 3.41E-06 1.95E-03 1.02E-05 NO DATA 1.57E-06 I 132- 2.03E-07 5.43E-07 1.90E-07 1.90E-05 0.65E-07 NO DATA 1.02E-07 I 133 1.42E-06 2.47E-06 7.53E-07 3.63E-04 4.31E-06 NO DATA 2.22E-06 I 134 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 NO DATA 2.51E-10 I 135 4.43E-07 1.16E-06 4.28E-07 7.65E-05 1.86E-06 NO DATA 1.31E-06 CS 134 6.22E-05 1.48E-04 1.21E-04 NO DATA 4.79E-05 1.59E-05 2.59E-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 7.97E-05 1.09E-04 7.14E-05 NO DATA 3.70E-05 1.23E-05 2.11E-06 CS 138 5.52E-08 1.09E-07 5.40E-08 NO DATA 8.01E-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 BA 140 2.03E-05 2.55E-08 1.33E-06 NO DATA 8.67E-09 1.46E-08 4.18E-05 BA 141 4.71E-08 3.56E-11 1.59E-09 NO DATA 3.31E-11 2.02E-11 2.22E-17 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 LA 142 1.288-10 5.82E-11 1.45E-11 NO DATA NO DATA NO DATA .25E-07 CE 141 9.36E-09 6.33E-09 7.18E-10 NO DATA 2.94E-09 NO DATA 2.42E-05 CE 143 1.65E-09 1.22E-06 1.35E-10 NO DATA 5.37E-10 NO DATA 4.56E-05 CE 144 4.88E-07 2.04E-07 2.62E-08 NO DATA 1.21E-07 NO DATA 1.65E-04 PR 143 9.20E-09 3.69E-09 4.56E-10 NO DATA 2.13E-09 NO DATA 4.03E-05 PR 144 3.01E-11 1.25E-11 1.53E-12 NO DATA 7.05E-12 NO DATA 4.33E-18 ND 147 6.29E-09 7.27E-09 4.35E-10 NO DATA 4.25E-09 NO DATA 3.49E-05 W 187 1.03E-07 8.61E-08 3.01E-08 NO DATA NO DATA NO DATA 2.82E-05 t

l i

Ctrrert Capy Proc: dire 99 0412 09.07iO1 H-3 Revision: 2 OFFSITE DOSE CALCULATION MANUAL AP 078-003 Reference USe Page 101 of 168 m

9 ATTACHMENT A (Page 96 of 163) 0FFSITE DOSE CALCULATION MANUAL

,0

.0 TaaLa A 3-1* (cont *d) 0 INGESTION DOSE FACTORS FOR ADULTS

'fg (NREN FER PCI INGESTED) 0 NucLIDE BONE LIVER T BODY THYROID MIDNEY LUNG GI-LLI N-

'\

.g NP 239 1.19E-09 1.17E-10 6.45E-11 NO DATA 3.65E-10 NO DATA 2.40E-05 sb 124** 2.80E-06 5.29E-08 1.11E 6.79E-09 NO DATA 2.18E-06 7.95E-05 N Sb 125** 1.79E-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 7.05E-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 Degulatory Guide 1.109 (Rev. 0)

J I

l l

1 l

l l

i l

l.

1 i

l

f CIrrent Copy Procodrre 99-0412 09:07L01 I

l H !

Revision: 2 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 l J4 ,

9 l 'p Reference Use Page 102 Of 168 l on 9 ATTACHMENT A (Page 97 of 163)

'0 TAsIA A-3.2 0 INGESTION DOSE FACTORS FOR TEENAGERS

\ { MREM PER PCI INGESTED)

O NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI

W

\ N 3 NO DATA 1.06E-07 1.06E-07 1.06E-07 1.065-07 1.06E-07 1.06E-07 O C 14 ~- 4.06E-06 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 g NA 24 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 P 32 2.76E-04 1.71E-05 1.07E-05 NO DATA NO DATA NO DATA 2.32E-05 CR 51 NO DATA HO DATA 3.60E-09 2.00E-09 7.89E-10 5.14E-09 6.05E-07 MN 54 NO DATA 5.90E-06 1.17E-06 NO DATA 1.76E-06 NO DATA 1.21E-05 MN 56 NO DATA 1.b8E-07 2.81E-08 NO DATA 2.00E-07 NO DATA 1.04E-05 FE 55 3.78E-06 2.68E-06 6.25E-07 NO DATA NO DATA 1.70E-06 1.16E-06 FE 59 5.87E-06 1.37E-05 5.29E-06 NO DATA NO DATA 4.32E-06 3.24E-05 CO 58 NO DATA 9.72E-07 2.24E-06 NO DATA NO DATA NO DATA 1.34E-05 CO 60 NO DATA 2.81E-06 6.33E-06 NO DATA NO DATA NO DATA 3.66E-05 NI 63 1.77E-04 1.25E-05 6.00E-06 NO DATA NO DATA NO DATA 1.99E-06 NI 65 7.49E-07 9.57E-08 4.36E-08 NO DATA NO DATA NO DATA 5.19E-06 CU 64 NO DATA 1.15E-07 5.41E-08 NO DATA 2.91E-07 NO DATA 8.92E-06 EN 65 5.76E-06 2.00E-05 9.33E-06 NO DATA 1.28E-05 NO DATA 8.47E-06 (

EN 69 1.47E-08 2.80E-08 1.96E-09 NO DATA 1.33E-08 NCt DATA 5.16E-08 BR 83 NO DATA NO DATA 5.74E-08 NO DATA NO DATA NO DATA LT E-24 I BR 84 NO DATA NO DATA 7.22E-08 NO DATA NO DATA NO DATA LT E-24 l BR 85 NO DATA NO DATA 3.05E-09 NO DATA NO DATA NO DATA LT E-24 RB B6 NO DATA 2.98E-05 1.40E-05 NO DATA NO DATA NO DATA 4.41E-06 RB 88 NO DATA 8.52E-08 4.54E-08 NO DATA NO DATA NO DATA 7.30E-15 i

RB 89 NO DATA 5.50E-08 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 6.09E-09 Y 91 2.01E-07 NO DATA 5.39E-09 NO DATA NO DATA NO DATA 8.24E-05 Y 92 1.21E-09 NO DATA 3.50E-11 NO DATA NO DATA NO DATA 3.32E-05 Y 93 3.83E-09 NO DATA 1.05E-10 NO DATA NO DATA NO DATA 1.17E-04 ER 95 4.12E-08 1.30E-08 8.94E-09 NO DATA 1.91E-08 NO DATA 3.00E-05 2R 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 4.42E-09 NO DATA 1.95E-05 NO 99 NO DATA 6.03E-06 1.15E-06 NO DATA 1.38E-05 NO DATA 1.08E-05 TC 99M 3.32E-10 9.26E-10 1.20E-08 NO DATA 1.30E-08 5.14E-10 6.08E-07

Taken from Regulatory Guide 1.109 (Rev.1) l

1 C rrelt "opy PrecedIre 99-0412 09.07t01 l

H.7 Revision: 2- OFFSITE DOSE CALCULATION MANUAL AP 07B-003 y

Reference Use Page 103 of 168 M

D ATTACHMENT A (Page 98 of 163)

.0 D TAaLa A-3.2 (cont'd) 0 INGESTION DOSE FACTORS FOR TEENAGERS g (MREM PER PCI INGESTED)

O NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI W

\ TC 101 3.60E-10 5.12E-10 5.03E-09 NO DATA 9.26E-09 3.12E-10 8.75E-17 g RU 103 2.55E-07 NO DATA 1.09E-07 NO DATA 8.99E NO DATA 2.13E-05 g RU 105 2.18E-08 NO DATA 8.46E-09 NO DATA 2.75E-07 NO DATA 1.76E-05 RU 106 3.92E-06 NO DATA 4.94E-07 NO DATA 7.56E-06 NO DATA 1.88E-04 AG 110M 2.05E-07 1.94E-07 1.18E-07 NO DATA 3.70E-07 NO DATA 5.45E-05 TE 125M 3.83E-06 1.38E-06 5.12E-07 1.07E-06 NO DATA NO DATA 1.13E-05 TE 127M 9.67E-06 3.43E-06 1.15E-06 2.30E-06 3.92E-05 NO DATA 2.41E-05 TE 127 1.58E-07 5.60E-08 3.40E-08 1.09E-07 6.40E-07 NO DATA 1.22E-05 TE 129M 1.63E-05 6.0$E-06 2.58E-06 5.26E-06 6.82E-05 NO DATA 6.12E-05 TE 129 4.48E-08 1.67E-08 1.09E-08 3.20E-08 1.88E-07 NO DATA 2.45E-07 TE 131M 2.44E-06 1.17E-06 9.76E-07 1.76E-06 1.22E-05 NO DATA 9.39E-05 TE 131 2.79E-08 1.15E-08 8.72E-09 2.15E-08 1.22E-07 NO DATA 2.29E-09 TE 132 3.49E-06 2.21E-06 2.08E-06 2.33E-06 2.12E-05 NO DATA 7.00E-05 I 130 1.03E-06 2.98E-06 1.19E-06 2.43E-04 4.59E-06 NO DATA 2.29E-06 I 131 5.05E-06 0.19E-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-0) 2.46E-05 1.15E-06 NO DATA 3.18E-07 I 133 2.01E-06 3.41E-06 1.04E-06 4.76E-04 5.98E-06 NO DATA 2.58E-06 I 134 1.46E-07 3.87E-07 1.39E-07 6.45E-06 6.10E-07 NO DATA 5.10E-09 I 135 6.10E-07 1.57E-06 5.82E-07 1.01E-04 2.485-06 NO DATA 1.14E-06 CS 134 8.37E-05 1.97E-04 9.14E-05 NO DATA 6.26E-05 2.39E-05 2.45E-06 CS f 36 8.59E-06 3.38E-05 2.27E NO DATA 1.84E-05 2.90E-06 2.72E-06 CS 137 1.12E-04 1.49E-04 5.19E-05 NO DATA 5.07E-05 1.97E-05 2.12E-06 CS 138 7.76E-08 1.49E-07 7.45E-08 NO DATA 1.10E-07 1.28E-08 6.76E-11 BA 139 1.39E-07 9.78E-11 4.05E-09 NO DATA 9.22E-11 6.74E-11 1.24E-06 BA 140 2.84E-05 3.48E-08 1.83E-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-00 2.99E-11 1.84E-09 NO DATA 2.53E-11 1.995-11 9.18E-20 LA 140 3.48E-09 1.71E-09 4.55E-10 NO DATA NO DATA NO DATA 9.82E-05 LA 142 1.79E-10 7.95E-11 1.98E-11 NO DATA NO DATA NO DATA 2.42E-06 CE 141 1.33E-08 8.00E-09 1.02E-09 NO DATA 4.18E-09 NO DATA 2.54E-05 CE 143 2.35E-09 1.71E-06 1.91E-10 NO DATA 7.67E-10 NO DATA 5.14E-05 CE 144 6.96E-07 2.88E-07 3.74E-08 NO DATA 1.72E-07 NO DATA 1.75E-04 PR 143 1.31E-08 5.23E-09 6.52E-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 9.30E-09 1.02E-08 6.11E-10 NO DATA 5.99E-09 NO DATA 3.6BE-05 W 187 1.46E-07 1.19E-07 4.17E-08 NO DATA NO DATA NO DATA 3.22E-05 l

Q:rrent Copy Procodyre 99-0412 09:07iO1 H

3 Revision: 2 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 10 g Reference Use Page 104 of 168

~ 51 1 P ATTACHMENT A I (Page 99 of 163)

OFFSITE DOSE CALCULATION MANUAL 1

,o

-Q TAaLa A-3.2 (cont'd)

,0 - INGESTION DOSE FAGTORS FOR TEENAGERS

( (MREM PER PCI INGESTED)

NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI

\

O NP 239 1. "16E-09 1.66E-10 9.22E-11 NO DATA 5.21E-10 NO DATA 2.67E-05 y Sb 124** 3.87E-06 7.13E-08 1.51E-06 8.78E-09 NO DATA 3.38E-06 7.80E-05 Sb 125** 2.48E-06 2.71E-08 5.80E-07 2.37E-09 NO DATA 2.18E-06 1.93E-05 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 NO DATA NO DATA NO DATA 4.44E-06

- Taken from Regulatory Guide 1.109 (Rev. 0)

I

i Crrre:t Copy ProcedIre 99-04-12 09.07101

!f.

Revision: 2 OFFSITE DOSE CALCULATION MANUAL AP 07B-003

Reference Use m Page 105 of 168 )'

V1 O ATTACHMENT A ;

(Page 100 of 163) )

.0 l

,0 TABLE A.3-3

.,0 INGESTION DOSE FACTORS FOR CHILD (MREM PER PCI INGESTED)

\ ,

O NUCLIDE BONE LIVER 7 BODY THYROID KIDNEY LUNG CI-LLI W

\ H 3 NO DATA 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 C 14 1.21E-05 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 O NA 24 5.80E-06 5.80E-06 5.80E-06 5.00E-06 5.80E-06 5.80E-06 5.00E-06 M

P 32 8.25E-04 3.86E-05 3.18E-05 NO DATA NO DATA NO DATA 2.28E-05 CR 51 NO DATA NO DATA 8.90E-09 4.94E-09 1.35E-09 9.02E-09 4.72E-07 MN 54 NO DATA 1.07E-05 2.85E-06 NO DATA 3.00E-06 NO DATA 8.98E-06 MN 56 NO DATA 3.34E-07 7.54E-08 NO DATA 4.04E-07 NO DATA 4.845-05 TE 55 1.15E-05 6.10E-06 1.89E-06 NO DATA NO DATA 3.45E-06 1.13E-06 FE 59 1.65E-05 2.67E-05 1.33E-05 NO DATA NO DATA 7.74E-06 2.7BE-05 CO 58 NO DATA 1.80E-06 5.51E-06 NO DATA NO DATA NO DATA 1.0$E-05 CO 60 NO DATA 5.29E-06 1.56E-05 NO DATA NO DATA NO DATA 2.93E-05 NI 63 5.3BE-04 2.88E-05 1.83E-05 NO DATA NO DATA NO DATA 1.94E-06 NI 65 2.22E-06 2.09E-07 1.22E-07 NO DATA NO DATA NO DATA 2.56E-05 CU 64 NO DATA 2.45E-07 1.48E-07 NO DATA 5.92E-07 NO DATA 1.15E-05 ZN 65 1.37E-05 3.65E-05 2.27E-05 NO DATA 2.30E-05 NO DATA 6.41E-06 ZN 69 4.38E-08 6.33E-08 5.85E-09 NO DATA 3.84E-08 NO DATA 3.99E-0(

BR 83 NO DATA NO DATA 1.71E-07 NO DATA NO DATA NO DATA LT E-21 BR 84 NO DATk NO DATA 1.98E-07 NO DATA NO DATA NO DATA LT E-74_

BR 85 NO DATA NO DATA 9.12E-09 NO DATA NO DATA NO DATA LT E-24 RB 86 NO DATA 6.70E-05 4.12E-05 NO DATA NO DATA NO DATA 4.31E-06 RB BB NO DATA 1.90E-07 1.32E-07 NO DATA NO DATA NO DATA 9.32E-09 RB 89 NO DATA 1.17E-07 1.04E-07 NO DATA NO DATA NO DATA 1.02E-09 SR 89 1.32E-03 NO DATA 3.77E-05 NO DATA NO DATA NO DATA 5.11E-05 SR 90 1.70E-02 NO DATA 4.31E-03 NO DATA NO DATA NO DATA 2.29E-04 SR 91 2.40E-05 NO DATA 9.06E-07 NO DATA NO DATA NO DATA 5.30E-05 SR 92 9.03E-06 NO DATA 3.62E-07 NO DATA NO DATA NO DATA 1.71E-04 Y 90 4.11E-08 NO DATA 1.10E-09 NO DATA NO DATA NO DATA 1.17E-04 Y 91M 3.82E-10 NO DATA 1.39E-11 NO DATA NO DATA NO DATA 1.48E-07 Y 91 6.02E-07 NO DATA 1.61E-08 NO DATA NO DATA NO DATA 8.02E-05 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 2R 95 1.16E-07 2.55E-00 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 2.2SE-08 8.76E-09 6.26E-09 NO DATA B.23E-09 NO DATA 1.62E-05 MO 99 NO DATA 1.33E-05 3.29E-06 NO DATA 2.84E-05 NO DATA 1.10E-05 TC 99M 9.23E-10 1.81E-09 3.00E-08 NO DATA 2.63E-08 9.19E-10 1.03E-06

Taken from Regulatory Guide 1.109 (Rev. 1)

. 8e.. 4e..-.m... 2

.3. " . ' . Revision: 2. OFFSITE DOSE CALCULATION MANUAL AP 07B-003 Yp Reference Use Page 106 of 168 yri .

j t. ATTACHMENT A (Page 101 of 163) l.

- 0FFSITE DOSE CALCULATION MANUAL i D 0 ThaLE A.3-3 (ooet'd) g3 INGESTION DOSE FACTORS FOR CHILD (MREN PER PCI INGESTED)

LO NUCLIDE' ' BONE LIVER 7 BODY THYROID KIDNEY LUNG GI-LLI W-g TC 101 1.07E-09 1.12E-09 1.42E-08 NO DATA 1.91E-08 5.92E-10 3.56E-09

! RU 103 7.31E-07 NO DATA 2.81E-07 NO DATA 1.84E-06 NO DATA 1.89E-05 O. RU 105 6.45E-08 NO DATA 2.34E-08 NO DATA 5.67E-07 NO DATA 4.21E-05 M

RU 106 1.1?E-05 NO DATA' 1.46E-06 NO DATA 1.58E-05 NO DATA 1.825-04 AG 110M 5.39E-07 3.64E-07 2.91E-01 NO DATA 6.78E-07 NO DATA 4.33E-05 TE 125M 1.14E-054 3.09E-06 1.52E-06 3.20E-06 NO DATA NO DATA 1.10E-05 TE 127N 2.89E-05 7.78E-06 3.43E-06 6.91E-06 8.24E-05 No DATA 2.34E-05 TE 127 4.71E-07 1.27E-07 1.01E-07 3.26E-07 1.34E-06 NO DATA 1.84E-05 TE 129N' 4.87E-05 1.36E-05 7.56E-06 1.57E-05 1.43E-04 NO DATA 5.94E-05 TE 129 1.34E-07 3.74E-08 3.18E-08 9.56E-08 3.92E-07 NO DATA 8.34E-06 TE 131M 7.20E-06 2.49E-06 2.65E-06 5.12E-06 2.41E-05 NO DATA 1.01E-04 TE 131 8.30E-08 2.53E-08' 2.47E-08 6.35E-08 2.51E-07 NO DATA 4.36E-07 TE 132 1.01E-05 4.47E-06 5.40E-06 6.51E-06 4.15E-05 NO DATA 4.50E-05 I 130 2.92E-06 5.90E-06 3.04E-06 6.50E-04 8.82E-06 NO DATA 2.76E-06

'I 131 1.72E-05 1.73E-05 9.83E-06 5.72E-03 2.84E-05 NO DATA 1.54E-06 I '132 8.00E-07 1.47E-06 .6.76E-07 6.'82E-05 2.25E-06 NO DATA 1.73E-06 I 133 5.92E-06 7.32E-06 2.77E-06 1.36E-03 1.22E-05 NO DATA 2.95E-06 I 134 4.19E-07 7.78E-07 3.5BE-07 1.79E-05 1.19E-06 NO DATA 5.16E-07 I 135 1.75E-06 3.15E-06 1.49E-06 2.79E-04 4.83E-06 NO DATA 2.40E-06 CS 134 2.34E-04 3.84E-04 8.10E-05 NO DATA 1.19E-04 4.27E-05 2.07E-06 CS 136 2.35E-05 6.46E-05 4.18E-05 NO DATA 3.44E-05 5.13E-06 2.27E-06 CS 137 3.27E-04 3.13E-04 4.62E-05 NO DATA 1.02E-04 3.67E-05 1.96E-06 CS 138 2.20E-07 3.17E-07 2.01E-01 NO DATA 2.23E-07 2.40E-08 1.46E-07 BA 139 4.14E-07 2.21E-10 1.20E-08 NO DATA 1.93E-10 1.30E-10 2.39E-05 BA 140 8.31E-05 7.28E-08 4.85E-06 NO DATA 2.37E-08 4.34E-08 4.21E-05 BA 141 2.00E-07 1.12E-10 6.51E-09 NO DATA 9.69E-11 6.5BE-10 1.14E-07 BA 142 8.74E-08 6.29E-11 4.88E-09 NO DATA 5.09E-11 3.70E-11 1.14E-09 LA 140 1.01E-08 3.53E-09 1.19E-09' NO DATA NO DATA NO DATA 9.845-05 LA 142 5.24E-10 1.67E-10 5.23E-11 NO DATA NO DATA NO DATA 3.31E-05 CE 141 '3.97E-08 1.9BE-08 2.94E-09 NO DATA 8.68E-09 NO DATA 2.47E-05 CE 143 6.99E-09 3.79E-06 5.49E-10 NO DATA 1.59E-09 NO DATA 5.55E-05

' CE . 144 2.00E-06 6.52E-07 1.11E-07 NO DATA 3.61E-07 NO DATA 1.10E-04 PR 143 '3.93E-08 1.18E-08 1.95E-09 NO DATA 6.39E-09 NO DATA 4.24E-05 PR 144 '1.29E-10 3.99E-11 6.49E-12 NO DATA 2.11E-11 NO DATA 8.59E-08 ND- 147 2.79E-08 2.26E-08 1.75E-09 NO DATA 1.24E-08 NO DATA 3.58E-05 W 187 4.29E-07 2.54E-07 1.14E-07 NO DATA NO DATA NO DATA 3.57E-05

L O!rre;t Ocpy Procodrre 09-0412 09.07!01

} Revision: 2 OFFSITE DOGE CALCULATION MANUAL AP 078-003 l; .3 i N Reference Use Page 107 of 168 0

tri 9 ATTACHMENT A (Page 102 of 163) ;

i OFFSITE DOSE CALCULATION MANUAL l .0

.0 TAata A.3-3 (cont'd) {

'D INGESTION DOSE FACTORS FOR CHILD s (MREM PER PCI INGESTED)

O NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI W ,

s g NP 239 5.25E 3.77E-10 2.65E-10 NO DATA 1.09E-09 NO DATA 2.19E-05 j O

Sb 124** '1.11E-05 1.44E-07 3.89E-06 2.45E-08 NO DATA 6.16E-06 6.94E-05 ,

Sb 125** 7.16E-06 5.52E-08 1.50E-06 6.63E-09 NO DATA 3.99E-06 1.11E-05 I IJ l Sb 126** 4.40E-06 6.73E-08 1.58E-06 2.58E-08 NO DATA 2.10E-06 8.875-05 Co 57+* NO DATA 4.93E-07 9.98E-07 NO DATA NO DATA NO DATA 4.04E-06

- Taken from segulatory Guide 1.109 (mov. 0) l l

l t

i l

l l

l 1

1 9

Otrrent Copy Proced re 99-0412 09.07:01 H

y Revision: 2 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 Reference Use Page 108 of 168 M

P ATTACHMENT A (Page 103 of 163)

.0

.D yngLa a,3 4+

,0 INGESTION DOSE FACTORS FOR INFANT

\ (MREM PER PCI INGESTED)

O NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI N

\ H 3 NO DATA 3.08E-07 3.00E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 g C 14 2.37E-05 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 g NA 24 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 P 32 1.70E-03 1.00E-04 6.59E-05 NO DATA NO DATA NO DATA 2.30E-05 CR 51 NO DATA NO DATA 1.41E-08 9.20E-09 2.01E-09 1.79E-08 4.11E-07 MN 54 NO DATA 1.99E-05 4.51E-06 NO DATA 4.41E-06 NO DATA 7.31E-06 MN $6 NO DATA 8.18E-07 1.41E-07 NO DATA 7.03E-07 NO DATA 7.43E-05 FE 55 1.39E-05 8.98E-06 2.40E-06 NO DATA NO DATA 4.39E-06 1.14E-06 FE 59 3.08E-05 5.38E-05 2.12E-05 NO DATA NO DATA 1.59E-05 2.57E-05 CO 58 NO DATA 3.60E-06 8.98E-06 NO DATA NO DATA NO DATA 8.97E-06 CO 60 NO DATA 1.08E-05 2.55E-05 NO DATA NO DATA NO DATA 2.57E-05 NI 63 6.34E-04 3.92E-05 2.20E-05 NO DATA NO DATA NO DATA 1.95E-06 NI- 65 4.70E-06 5.32E-07 2.42E-07 NO DATA NO DATA NO DATA 4.05E-05 CU 64 NO DATA 6.09E-07 2.82E-07 NO DATA 1.03E-06 NO DATA 1.25E-05 ZN 65 1.84E-05 6.31E-05 2.91E-05 NO DATA 3.06E-05 NO DATA 5.33E-05 EN 69 9.33E-08 1.68E-07 1.25E-08 NO DATA 6.98E-08 NO DATA 1.37E-05 BR 83 NO DATA NO DATA 3.63E-07 NO DATA NO DATA NO DATA LT E-24 BR 84 NO DATA NO DATA 3.82E-07 NO DATA NO DATA NO DATA LT E-24 BR 85 NO DATA NO DATA 1.94E-08 NO DATA NO DATA NO DATA LT E-24 RB 86 NO DATA 1.70E-04 8.40E-05 NO DATA NO DATA NO DATA 4.35E-06 RB 88 NO DATA 4.90E-07 2.73E-07 NO DATA NO DATA NO DATA 4.85E-07 RB 89 NO DATA 2.86E-07 1.97E-07 NO DATA NO DATA NO DATA 9.74E-00 SR 89 2.51E-03 NO DATA 7.20E-05 NO DATA NO DATA NO DATA 5.16E-05 SR 90 1.85E-02 NO DATA 4.71E-03 NO DATA NO DATA NO DATA 2.31E-04 SR 91 5.00F 05 NO DATA 1.81E-06 NO DATA NO DATA NO DATA 5.92E-05 SR 92 1.9* -05 NO DATA 7.13E-07 NO DATA NO DATA NO DATA 2.07E-04 Y 90 8.f '.-0 8 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 DATA 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-C8 2.54E-09 1.16E-09 NO DATA 2.56E-09 NO DATA 1.62E-04 NB 95 4.20E-08 1.73E-08 1.00E-08 NO DATA 1.24E-08 NO DATA 1.46E-05 MO 99 NO DATA 3.40E-05 6.63E-06 NO DATA 5.00E-05 NO DATA 1.12E-05 TC 99M 1.92E-C9 3.96E-09 5.10E-08 NO DATA 4.26E-08 2.07E-09 1.15E-06

Taken frost mogulatory Guide 1.109 (may. 1)

Czrrent @opy Proc: dire 99-0412 09.07t01 1

Revision: 2 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 N Reference Use Page 109 of 168 9

m \

U ATTACHMENT A !

(Page 104 of 163)

..D

.0 TABLE A.3-48 (cont'd)

J INGESTION DOSE FACTORS FOR INFANT (MREM PEA PCI INGESTED)

O NUCLIDE DONE LIVER T BODY THYROID KIDNEY LUNG CI-LLI W

.g TC 101 2.27E-09 2.86E-09 2.83E-08 NO DATA 3.40E-08 1.56E-09 4.86E-07 l RU . ' 103 1.48E-06 NO DATA 4.95E-07 NO DATA 3.08E-06 NO DATA 1.80E-05 O

RU 105 1.36E-07 NO DATA 4.58E-08 NO DATA 1.00E-06 NO DATA 5.41E-05 N

RU 106 2.41E-05 NO DATA 3.01E-06 NO DATA 2.85E-05 NO DATA 1.83E-04 AG - 110M 9 96E-07 7.27E-07 4.81E-07 NO DATA 1.04E-06 NO DATA 3.77E-05 TE 125N 2.33E-05 7.79E-06 3.15E-06' 7.84E-06 NO DATA NO DATA 1.11E-05 TE 127M 5.85E-05 1.945-05 7.08E-06 1.69E-05 1.44E-04 NO DATA 2.36E-05 TE 127 1.00E-06 3.355-07 2.15E-07 8.14E-07 2.44E-06 NO DATA 2.10E-05 TE 129N 1.00E-04 3.43E-05 1.54E-05 3.84E-05 2.50E-04 NO DATA 5.97E-05 TE 129 2.84E-07 9.79E-08 6.63E-08 2.30E-07 7.07E NO DATA 2.27E-05 TE 131M 1.52E-05 6.12E-06 5.05E-06 1.24E-05 4.21E-05 NO DATA 1.03E-04 TE 131 1.76E-07 6.50E-08 4.94E-08 1.57E-07 4.50E-07 NO DATA 7.11E-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 6.00E-06 1.32E-05 5.30E 1.48E-03 1.45E-05 NO DATA 2.83E-06 I 131 3.59E-05 4.23E-05 1.86E-05 1.39E-02 4.94E-05 -NO DATA 1.51E-06 I 132' 1.66E-06 3.37E-06 1.20E-06 1.58E-04 3.76E-06 NO DATA 2.73E-06 I 133 1.25E-05 1.82E-05 5.33E-06 3.31E-03 2.14E-05 NO DATA 3.00E-06 I 134 8.69E-07 1.78E-06 6.33E-07 4.15E-05 1.99E-06 NO DATA 1.84E-06 I 135 3.64E-06 7.24E-06 2.64E-06 6.49E-04 8.07E-06 NO DATA 2.62E-06

}

CS 134 3.77E-04 7.03E-04 7.10E-05 NO DATA 1.81E-04 7.42E-05 1.31E-06 CS 136 4.59E-05 1.35E-04 5.04E-05 NO DATA 5.38E-05 1.10E-05 2.05E-06 CS 137 5.22E-04 6.11E-04 4.33E-05 NO DATA 1.64E-04 6.64E-05 1.91E-06 CS 138 4.81E-07 7.82E-07 3.79E-07 NO DATA 3.90E-07 6.09E-08 1.25E-06 BA 139 8.81E-07 5.84E-10 2.55E-08 NO DATA 3.51E-10 3.54E-10 5.58E-05 BA 140 1.71E-04 1.71E-07 8.81E-06 NO DATA 4.06E-00 1.05E-07 4.20E-05 BA 141 4.25E-07 2.91E-10 1.34E-08 NO DATA 1.75E-10 1.77E-10 5.19E-06 BA 142 1.04E-07 1.53E-10 9.06E NO DATA 8.81E-11 9.26E-11 7.59E-07 LA 140 2.11E-08 8.32E-09 2.14E-09 NO DATA NO DATA NO DATA 9.77E-05 LA 142 1.10E-09 4.04E-10 9.67E-11 NO DATA NO DATA NO DATA 6.86E-05 CE 141 7.87E-08 4.80E-08 5.65E-09 NO DATA 1.48E-08 NO DATA 2.48E-05 CE 143' 1.48E-08 9.82E-06 1.12E-09 NO DATA 2.86E-09 NO DATA 5.73E-05 CE- 144 2.98E-06 1.223-06 1.67E-07 NO DATA 4.935-07 NO DATA 1.71E-04 PR 143 8.13E-08 3.04E-08 4.03E-09 NO DATA 1.13E-08 NO DATA 4.29E-05 PR 144 2.74E-10 1.06E-10 1.38E-11 NO DATA' 3.84E-11 NO DATA 4.93E-06 ND 147 5.53E-08 5.68E-08 3.40E-09 NO DATA 2.19E-08 NO DATA 3.60E-05 N 187 9.03E-07 6.28E-07 2.17E-07 NO DATA NO DATA NO DATA 3.69E-05 i

Curre t Copy Procedire 99-0412 09:07;01 g

-H Revision: 2 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 Reference Use Page 110 of 168 in -

9' ATTACHMENT A (Page 105 of 163)

OFFSITE' DOSE CALCULATION MANUAL

.0 ;

,0 . TABLE A.3-4* (cont'd) 0 INGESTION DOSE FACTORS FT)R INFANT

-( (MREM PER PCI INGESTED)

'O NUCLIDE BONE LIVER 7 BODY THYROID KIDNEY LUNG GI-LLI N

\ NP 239 1.11E-08 9.93E 5.61E-10 NO DATA 1.98E-09 NO DATA 2.87E-05 g 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 sb 126** 8.06E-06 1.58E-07 2.91E-06 6.19E-08 NO DATA 5,07E-06 8.35E-06 Co 57** NO DATA 1.15E-06 1.87E-06 NO DATA NO DATA NO DATA 3.92E-06

- Taken from segulatory Guide 1.109 (mov. 0) l I

i 0

a

y Crrrent copy Procodrre 99-0412 09ic7:01 H

Revision: 2 .OFFSITE DOSE CALCULATION MANUAL AP 07B-003 3

$ Reference Use Page 111 of 168 50 9 ATTACHMENT A (Page 106 of,163)

..D 0

TABI2 A . 3-5 *

.0 STABLE ELEMENT TRANSFER DATA

\ -Element 96, r, (Cow)

Q Vea7 soil Milk (d/1) Meat [g (d /kg) bl

,\ H. 4.8E 00 1.0E-02 + 1.20E-02

'C 5.5E 00 1.2E-02 + 3.1E-02 U Na- 5.2E-02 4.0E-02 3.0E-02

)J P 1.1E 00 2.5E-02 4.6E-02 Cr 2.5E-04 2.2E-03 2.4E-03 Hn 2.9E-02 2.5E-04 8.0E-04 Fe 6.6E-04 .1.2E-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

' En 4.0E-01 3.9E-02 3.0E-02 Rb 1.3E-01 3.0E-02 3.1E-02 Sr 1.7E-02 0.0E-04 + 6.0E-04 Y 2.6E-03 1.0E-05 4.6E-03 Zr 1.7E-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 To 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 1 3E-03 W 1.8E-02 5.0E-04 1.3f '3s Np 2.5E-03 5.0E-06 2.0E-04

+ F. (Goat) values for milk (d/1)

Element Milk (d/1)

H 1.7E-01 C 1.0E-01 P 2.5E-01 Fe 1.3E-04 Cu 1.3E-02 5t 1.4E-02 I 6.0E-02 Cs 3.0E-01

Taken from megulatory Guide 1.109 (mov. 1)

E 1 C rrent Copy Proced:re 99 04-12 09.07;01 H 1 Revision: 2 3 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 9

g Reference Use Page 112 of 168 i m I 9 ATTACHMENT A (Page 107 of 163)

OFFSITE DOSS CALCULATION MANUAL l

.0 TAat.s A.4-1 l

..D SITE RELATED DOSE COMMITMENT FACTOR AIT g MREM /HR PER pCI/ML g ADULT W #10CLIDE BONE LIVER T BODY THYROID KIDNEY 1.UNG GI-LLI l

\ l g H 3 0.00E-01 8.96E 30 8.96E 00 8.96E 00 8.96E 00 8.96E 00 8.96E 00 l C 14 3.15E 04 6.30E 03 6.30E 03 6.30E 03 6.30E 03 6.30E 03 6.30E 03 N NA 24 5.48E 02 5.48E 32 5.48E 02 5.48E 02 5.48E 02 5.48E 02 5.48E 02 P 32 4.62E 07 2.87E 06 1.79E 06 0.00E-01 0.00E-01 0.00E-01 5.20E 06 CR 51 0.00E-01 0.00E-01 1.49E 00 8.94E-01 3.29E-01 1.90E 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 50 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 32 9.58E 02 0.00E-01 0.00E-01 0.00E-01 8.16E 03 NI 63 4.19E 04 2.94E 03 1.41E 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-01 0.00E-01 0.00E-01 5.61E 02 CU 64 0.00E-01 1.69E 01 7.93E 00 0.00E-01 4.26E-01 0.00E-01 1.44E 03 ZN 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 1.09E-15 RB 86 0.00E-01 1.03E 05 4.79E 04 0.00E-01 0.00E-01 0.00E-01 2.03E 04 RB 88 0.00E-01 2.95E 02 1.56E 02 0.00E-01 0.00E-01 0.00E-01 4.07E-09 RR 89 0.00E-01 1.95E 02 1.37E 02 0.00E-01 0.00E-01 0.00E-01 1.13E-11 3R 89 4.78E 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 SR 92 3.33E C2 0.00E-01 1.44E 01 0.00E-01 0.00E-01 0.00E-01 6.60E 03 Y 90 1.30E CD 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 C1 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 3.53E-03 0.00E-01 0.00E-01 0.00E-01 2.12E 03 Y 93 3.835-C1 0.00E-01 1.06E-02 0.00E-01 0.00E-01 0.00E-01 1.22E 04 ER 95 2.77E C0 8.88E-01 6.01E-01 0.00E-01 1.39E 00 0.00E-01 2.82E 03 ZR 97 1.53E-01 3.09E-02 1.41E-02 0.00E-01 4.67E-02 0.00E-01 9.57E 03 NB 95 4.47E C2 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 1.0?E 03 TC 99M 2.94E-C2 8.32E-02 1.06E 00 0.00E-01 1.26E 00 4.07E-02 4.92E 01

[ l l Czrror.t copy PrecedIre 99-0412 09:07:01 !

U I Revision: 2 0FFSITE DOSE CALCULATION MANUAL AP 07B-003

Reference Use 9 Page 113 of 168

$n p ATTACHMENT A (Page 108 of 163) 0FFSITE DOSE CALCULATION MANUAL D

1

.0 '

TARIA A.4-1 (coot'd) '

(D SITE REl.ATED DOSE COMMITMENT FAC'ICR AIT g MREM /HR PER pCI/ML )

ADULT }

0 4 8

W NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI g l U TC 101 3.03E-02 4.36E-02 4.20E-01 0.00E-01 7.85E-01 2.23E-02 1.31E-13 RU 103 1.98E 01 0.00E-01 8.54E 00 0.00E-01 7.57E 01 0.00E-01 2.31E 03 N RU 105 1.65E 00 0.00E-01 6.52E-01 0.00E-01 2.13E 01 0.00E-01 1.01E 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 2.58E 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 1.00E 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 0.00E-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 131M 1.80E 03 0.01E 02 7.34E 02 1.39E 03 8.92E 03 0.00E-01 8.74E 04 I TE 131 2.05E 01 8.57E 00 6.47E 00 1.69E 01 8.98E 01 0.00E-01 2.90E 00

)

TE 132 2.62E 03 1.70E 03 1.59E 03 1.07E 03 1.63E 04 0.00E-01 8.02E 04 I 130 9.01E 01 2.66E 02 1.05E 02 2.25E 04 4.15E 02 0.00E-01 2.29E 02 I 131 4.96E 02 7.09E 02 4.06E 02 2.32E 05 1.22E 03 0.00E-01 1.87E 02 I 132 2.42E 01 6.47E 01 2.26E 01 2.26E 03 1.03E 02 0.00E-01 1.22E 01 I 133 1.69E 02 2.94E 02 8.97E 01 4.32E 04 5.13E 02 0.00E-01 2.64E 02 I 134 1.26E 01 3.43E 01 1.03E 01 5.94E 02 5.46E 01 0.00E-01 2.99E-02 I 135 5.28E 01 1.38E 02 5.10E 01 9.11E 03 2.22E 02 0.00E-01 1.56E 02 CS 134 3.03E 05 7.21E 05 5.89E 05 0.00E-01 2.33E 05 7.75E 04 1.26E 04 i

CS 136 3.17E 04 1.25E 05 9.01E 04 0.00E-01 6.97E 04 9.55E 03 1.42E 04 I CS 137 3.8BE 05 5.31E 05 3.40E 05 0.00E-01 1.80E 05 5.99E 04 1.03E 04 I CS 138 2.69E 02 5.31E 02 2.63E 02 0.00E-01 3.90E 02 3.85E 01 2.27E-03 I BA 139 9.00E 00 6.41E-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 0.05E-01 1.35E 00 3.88E 03 BA 141 4.37E 00 3.30E-03 1.48E-01 0.00E-01 3.07E-03 1.87E-03 2.06E-09 BA 142 1.98E 00 2.03E-03 1.24E-01 0.00E-01 1.72E-03 1.15E-03 2.78E-18 1.A 140 3.58E-01 1.80E-01 4.76E-02 0.00E-01 0.00E-01 0.00E-01 1.32E 04 !

LA 142 1.83E-02 0.33E-03 2.07E-03 0. 0^' - 01 0.00E-01 0.00E-01 6.08E 01 j CE 141 8.01E-01 5.42E-01 6.15E-02 0.06E-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 3.90E 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 1.01E-03 0.00E-01 6.19E-10 1

-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 8.90E 01 0.00E-01 0.00E-01 0.00E-01 8.34E 04 1

]

i l

i

Octrent Copy ProcedIre 99-0412 09:07101 1

D Revision: 2 OFFSITE DOSE CALCULATION MANUAL AP 078-003 N Reference Use 9 Page 114 of 168 m

p. ATTACHMENT A (Page 109 of 163) 1 OFFSITE DOSE CALCULATION MANUAL l

,0 0 Tanta A.4-1 (cont'd)

D" SITE RELATED DOSE COMMITMENT FACTOR AIT i

MREM /HR PER pCI/ML ADULT N. NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI .

\ !

O NP 239 1.29E-01 1.25E-02 6.91E-03 0.00E-01 3.91E-02 0.00E-01 2.57E 03 '

Sb 124 2.40E 02- 4.53E 00 ?.50E 01 5.81E-01 0.00E-01 1.87E 02 6.81E 03 M sb 125 1.53E 02 1.71E 00 1.56E-01 3.65E 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 8.0$E 03 Co 57 0.00E-01 3.55E 01 5.90E 01 0.00E-01 0.00E-01 0.00E-01 9.01E 02

C rrent Ccpy ProcedZre 99-04-12 09:07;01

!H Revision: 2 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 3

N Reference Use Page 115 of 168 y

on O ATTACHMENT A (Page 110 of 163)

.0

.0 TAB 12 A.4-2

,A SITE RELATED DOSE COMMITMENT FACTOR AIT

\ MREM /HR PER pCI/HL g TEEN 14 nucLIDE sone liven T sooY TavRoID 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 6.8FE 03 6.86E 03 6.86E 03 6.86E 03 6.865 03 6.86E 03 N NA 24 5.53E 02 5.53E 02 5.53E 02 5.53E 02 5.53E 02 5.53E 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 TE 55 9.09E 02 6. 4 5E 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 0.00E-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 8.00E 00 0.00E-01 4.35E 01 0.00E-01 1.33E 03 ZN 65 2.13E 04 7.41E 04 3.46E 04 0.00E-01 4.74E 04 0.00E-01 3.14E 04 ZN 69 5.45E 01 1.04E 02 7.26E 00 0.00E-01 6.78E 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-01 0.00E-01 8.24E-16 i

BR 85 0.00E-01 0.00E-01 2.51E 00 0.00E-01 0.00E-01 0.00E-01 0.24E-16 i RB 86 0.00E-01 1.10E 05 5.19E 04 0.00E-01 0.00E-01 0.00E-01 1.63E 04 l 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 I SR 89 4.97E 04 0.00E-01 1.42E 03 0.00E-01 0.00E-01 0.00E-01 5.91E 03 SR 90 9.37E 05 0.00E-01 2.31E 05 0.00E-01 0.00E-01 0.00E-01 2.63E 04 3 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 0.00E-01 0.77E 03 Y 90 1.42E 00 0.00E-01 3.83E-01 0.00E-61 0.00E-01 0.00E-01 1.17E 04 Y 91H 1.34E-01 0.00E-01 5.11E-03 0.00E-01 0.00E-01 0.00E-01 6.32E-01 Y 91 2.09E 01 0.00E-01 5.59E-00 0.00E-01 0.00E-01 0.00E-01 8.55E 03 Y 92 1.26E-03 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 1.093-01 0.00E-01 0.00E-01 0.00E-01 1.21E 04 1 ER 95 2.64E 03 8.34E-01 5.74E-00 0.00E-01 1.23E 00 0.00E-01 1.92E 03 l

, ER 97 1.52E-00 3.01E-02 1.39E-01 0.00E-01 4.56E-01 0.00E-01 8.15E 03 l l

NB 95 4.50E 02 2.50E 02 1.37E 02 0.00E-01 2.42E 02 0.00E-01 1.07E 06 i 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 1.03E 00 0.00E-01 1.18E 00 4.39E-01 5.20E 01 l

l i

p Crrre!.t Copy Proced:re 99-0412 09:07.01 iH Revision: 2 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 7

Reference Use Page 116 of 168 M

f) ATTACHMENT A (Page 111 of 163) 4-0FFSITE DOSE CALCULATION MANUAL

..D

..D TABLE A.4-2 (cont' d) l

.D SITE RELATED DOSE COMMITMENT FACTOR AIT ;

g MREM /HR PER pCI/ML g TEEN id NUCLIOE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI

\

g TC 101 3.08E-01 4.38E-02 4.30E-00 0.00E-01 7.92E-00 2.67E-01 7.48E-09 RU 103 1.95E 01 0.00E-01 8.33E 00 0.00E-01 6.07E 01 0.00E-01 1.63E 03 N RU 105 1.67E 00 0.00E-01 6.46E-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 1.20E 01 1.21E 01 7.36E 00 0.00E-01 2.31E 01 0.00E-01 3.40E 03 TE 125M 3.02E 03 1.09E 03 4.03E 02 8.43E 02 0.00E-01 0.00E-01 8.90E 03 TE 127M 7.62E 03 2.70E 03 9.06E 02 1.81E 03 3.09E 04 0.00E-01 1.90E 04 TE 127 1.24E 02 4.41E 01 2.68E 01 8.59E 01 5.045 02 0.00E-01 9.61E 03 TE 129M 1.28E 04 4.77E 03 2.03E 03 4.14E 03 5.37E 04 0.00E-01 4.82E 04 TE 129 3.53E 01 1.32E 01 8.59E 00 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 1.67E 04 0.00E-01 5.51E 04 I 130 8.81E 01 2.55E 02 1.02E 02 2.00E 04 3.92E 02 0.00E-01 1.96E 02 I 131 5.00E 02 7.00E 02 3.76E 02 2.04E 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 1.72E 02 2.92E 02 8.89E 01 4.072 04 S.11E 02 0.00E-01 2.21E 02 I 134 1.25E 01 3.31E 01 1.19E 01 5.51E 92 5.22E 01 0.00E-01 4.36E-01 I 135 5.22E 01 1.34E 02 4.98E 01 8.64E 0.1 2.12E 02 0.00E-01 1.49E 02 CS 134 3.10E 05 7.30E 05 3.39E 05 0.00E-02 2.32E 05 8.86E 04 9.0BE 03 CS 136 3.18E 04 1.25E 05 8.41E 04 0.00E-01 6.02E 04 1.07E 04 1.01E 04 CS 137 4.15E 05 5.52E 05 1.92E 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 2.51E-01 BA 139 9.10E 00 6.40E-03 2.65E-00 0.00E-01 6.03E-02 4.41E-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 3.20E-03 1.47E-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 1.30E-02 6.01E-12 LA 140 3.61E-00 1.77E-01 4.72E-01 0.00E-01 0.00E-01 0.00E-01 1.02E 04 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 0.00E-01 2.51E-00 0.00E-01 1.52E 03 CE 143 1.41E-00 1.03E 02 1.15E-01 0.00E-01 4.60E-01 0.00E-01 3.00E 03 CE 144 4.17E 01 1.73E 01 2.24E 00 0.00E-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 2.26E-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 3.82E 03 W 187 3.285 02 2.67E 02 9.37E 01 0.00E-01 0.00E-01 0.00E-01 7.24E 04

C rrelt Copy Proced:re 99 0412 09.07iO1 I -

D Revision: 2 OFFSITE DOSE CALCULATION MANUAL AP 078-003 3

N Reference Use 9 Page 117 of 168 40 0 ATTACHMENT A (Page 112 of 163)

4 TARIE, A 4-2 (cont' d)

J SITE RElATED DOSE COMMITMENT TACTOR AIT l

g MREM /HR PER pCI/ML O TEEN l W NUCLIDE BONE LIVER 7 BODY THYROID KIDNEY LUNG GI-LLI

\

g NP 239 1.34E-00 1.27E-02 7.04E-02 0.00E-01 3.9BE-01 0.00E-01 2.04E 03 Sb 124 2.32E 02 4.2BE 00 9.05E 01 5.26E-00 0.00E-01 2.03E 02 4.68E 03 N Sb 125 1.49E 02 1.63E 00 3.48E 01 1.42E-00 0.00E-01 1.31E 02 1.16E 03 i

Sb 126 9.53E 01 1.95E 00 3.42E 01 5.39E-00 0.00E-01 6.84E 01 5.64E 03 Co 57 0.00E-01 3.55E 01 5.96E 01 0.00E-01 0.00E-01 0.00E-01 6.6'? 02 i

L

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m V ATTACHMENT A (Page 113 of 163) 0FFSITE DOSE CALCULATION MANUAL

.0

.0 TABLE A.4-3

.0 SITE RELATED DOSE COMMITHENT FACTOR AIT

\ MREM /HR PER HCi/ML g CHILD 14 NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI

\

O 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 8.90E 03 8.90E 03 8.90E 03 8.905 03 8.90E 03 8.90E 03 N NA 24 7.93E 02 7.93E 00 7.93E 02 7.93E 02 7.93E 02 7.93E 02 7.93E 02 P 32 6.49E 07 3.04E 06 2.50E 06 0.00E-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 HN 56 0.00E-01 1.25E 02 2.81E 01 0.00E-01 1.51E 02 0.00E-01 1.80E 04 rE 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 CO 58 0.00E-01 1.75E 02 5.37E 02 0.00E-01 0.00E-01 0.00E-01 1.02E 03 CO 60 0.00E-01 5.16E 02 1.52E 03 0.00E-01 0.00E-01 0.00E-01 2.86E 03 NI 63 7.36E 04 3.94E 03 2.50E 03 0.00E-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 0.00E-01 2.39E 01 1.44E 01 0.00E-01 5.77E 01 0.00E-01 1.12E 03 ZN 65 2.23E 04 5.95E 04 3.70E 04 0.00E-01 3.75E 04 0.00E-01 1.05E 04 ZN 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 7.69E 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 3.89E-16 RB 86 0.00E-01 1.09E 05 6.72E 04 0.00E-01 0.00E-01 0.00E-01 7.03E 03 RD 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 1.66E 00 SR 89 1.08E 05 0.00E-01 3.08E 03 0.00E-01 0.00E-01 0.00E-01 4.18E 03 SR 90 1.39E 06 0.00E-01 3.52E 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 0.56E-01 0.00E-01 0.00E-01 0.00E-01 9.10E 03 Y 91M 2.97E-01 0.00E-01 1.08E-02 0.00E-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 0.00E-01 0.00E-01 0.09E 03

/

Y 93 8.87E-00 0.00E-01 2.44E-01 0.00E-01 0.00E-01 0.00E-01 1.32E 04 ZR 95 7.05E 00 1.55E 00 1.38E 00 0.00E-01 2.22E 00 0.00E-01 1.62E 03 ZR 97 4.25E-00 6.13E-02 3.62E-01 0.00E-01 8.81E-01 0.00E-Oi 9.29E 03 ND 95 5.32E 02 2.07E 02 1.48E 02 0.00E-01 1.95E 02 0.00E-01 3.83E 05 MO 99 0.00E-01 8.78E 02 2.17E 02 0.00E-01 1.87E 03 0.00E-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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3 Revision: 2 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 p

g Reference Use Page 119 of 168 M

-U ATTACHMENT A (Page 114 of 163)

J TAkLE A.4-3 (cont'd) l 0 SITE RELATED DOSE CCHNITNENT FACTOR AIT

( MREM /HR PER pCi/ML CHILD g

W NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI

\ .

g TC 101 7.48E-01 7.83E-02 9.93E-00 0.00E-01 1.345 00 4.14E-01 2.49E-01 g RU 103 4.83E 01 0.00E-01 1.85E 01 0.00E-01 1.21E 02 0.00E-01 1.25E C3 ,

, RU 105 4.26E 00 0.00E-01 1.54E 00 0.00E-01 3.74E 01 0 00F.-01 2.78E 03 l

RU 106 7.72E 02 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 5.6?E 02 1.19E 03 0.00E-01 0.00E-01 4.10E 03 TE 127H 1.00E 04 2.90E 03 1.20E 03 2.58E 03 3.07E 04 0.00E-01 8.72E 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 9.43E 00 9.21E 00 2.37E 01 9.36E 01 0.00E-01 1.63E 02 l

TE 132 3.77E 03 1.67E 03 2.01E 03 2.43E 03 1.55E 04 0.00E-01 1.68E 04 I I- 130 2.04E 02 4.13E 02 2.13E 02 4.55E 04 6.17E 02 0.00E-01 1.93E 02 j I 131 1.20E 03 1.21E 03 6.88E 02 4.00E 05 1.99E 03 0.00E-01 1.00E 02 j I 132 5.60E 01 1.03E 02 4.73E 01 4.77E 03 1.57E 02 0.00E-01 1.21E 02 I 133 4.14E 02 5.12E 02 1.94E 02 9.51E 04 8.53E 02 0.00E-01 2.06E 02 I 134 2.93E 01 5.44E 01 2.50E 01 1.25E 03 8.32E 01 0.00E-01 3.61E 01 I 135 1.22E 02 2.20E 02 1.04E 02 1.95E 04 3.38E 02 0.00E-01 1.68E 02 CS 134 3.82E 05 6.26E 05 1.32E 05 0.00E-01 1.94E 05 6.97E 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 CS 137 5.33E 05 5.11E 05 7.54E 04 0.00E-01 1.66E 05 5.99E 04 3.20E 03 CS 138 3.72E 02 5.17E 02 3.28E 02 0.00E-01 3.64E 02 3.92E 01 2.38E C2 BA 139 2.54E 01 1.35E-02 7.35E-00 0.00E-01 1.18E-01 7.97E-02 1.4?E 03 BA 140 5.09E 03 4.46E 00 2.97E 02 0.00E-01 1.45E 00 2.66E 00 2.58E 03 RA 141 1.23E 01 6.86E-03 3.99E-00 0.00E-01 5.94E-02 4.03E-01 6.99E 00 BA 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 9.26E-01 0.00E-01 0.00E-01 0.00E-01 7.66E 03 LA 142 4.08E-01 1.30E-02 4.07E-02 -0.00E-01 0.00E-01 0.00E-01 2.58E 03 CE 141 2.34E 00 1.17E 00 1.73E-00 0.00E-01 5.11E-00 0.00E-01 1.46E 03' CE 143 4.12E-00 2.23E 02 3.24E-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 1.00E 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 0.00E-01 3.59E 04

c. .

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.( Reference Use. Page 120 of 168 Iri -

'O ATTACHMENT A (Page 115 of 163) 0FFSITE DOSE CALCULATION MANUAL

0 J TAata A.4-3 (cont'd)

J SITE RELATED DOSE COMMITMENT FACTOR AIT g MREM /HR PER pC1/ML D CHILD N NUCLIDE BONF. LIVER 7 BODY THYROID KIDNEY LUNG GI-LLI

.\

NP 239 3.47E-00 2.49E-02 1.75E-01 0.00E-01 7.19E-01 0.00E-01 1.84E 03 U sb 124 6.54E 02 8.49E 00 2.29E 02 1.44E 00 0.00E-01 3.63E 02 4.095 03 Sb 125 4.22E 02 3.25E 00 8.84E 01 3.91E-00 0.00r.-01 2.35E 02 1.01E 03_

Sb 126 2.59E 02 3.97E 00 9.31E 01 1.52E 00 0.00E-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

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Revision: 2 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 3

Reference Use Page 121 of 168 m

U ATTACHMENT A (Page 116 of 163) 0FFSITE DOSE CALCULATION MANUAL 0

.0 TAata A.4-4 D SITE RELATED DOSE COMMITHENT FACTOR AIT

\ HREM/HR PER pCI/ML g INFANT W NUCLIDE BONE LIVER T BODY THYROID s(IDNEY LONG GI-LLI

\

g H 3 0.00E-01 1.16E 01 1.16E 01 1.16E 01 1. N 0 ". 1.16E 01 1.16E 01 C 14 8.92E 02 1.90E 02 1.90E 02 1.90E 07 1.90E 02 1.90E 02 1.90E 02 N NA 24 3.80E 02 3.80E 02 3.80E 02 3.00E 02 3.80E 02 3.00Efj 3.80E 02 P 32 6.40E 04 3.76E 03 -2.48E 03 0.00E 0.00E-01 0.00E-01 8.65E 02 CR 51 0.00E-01 0.00E-01 5.30E-01 3.46E. .. 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 2.64E 01 0.00E-01 2.00E 03 FE 55 5.23E 02 3.38E 02 9.03E 01 0.00E-01 0.00E-01 1.65E 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 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 9.67E 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 6.92E 02 2.37E 03 1.09E 03 0.00E-01 1.15E 03 0.00E-01 2.01E 03 ZN 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 BR 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 0.00E-01 3.76E-17 RB 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 l 1

RB 89

0.00E-01 1.08E 01 7.41E 00 0.00E-01 0.00E-01 0.00E-01 3.66K 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 8.69E 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 7.19E 03 Y 90 3.27E 00 0.00E-01 8.77E-02 0.00E-01 0.00E-01 0.00E-01 4.51E 03 l Y 91M 3.0$E-02 0.00E-01 1.04E-03 0.00E-01 0.00E-01 0.00E-01 1.02E 02 Y 91 4.25E 01 0.00E-01 1.13E 00 0.00E-01 0.00E-01 0.00E-01 3.05E 03 Y 92 2.88E-01 0.00E-01 8.09E-03 0.00E-01 0.00E-01 0.00E-01 5.49E 03 Y 93 9.14E-01 0.00E-01 2.49E-02 0.00E-01 0.00E-01 0.00E-01 7.22E 03 i ER 95 7.75E 00 1.89E 00 1.34E 00 0.00E-01 2.04E 00 0.00E-01 9.41F. 02 {

ZR 97 5.57E-01 9.56E-02 4.36E-02 0.00E-01 9.63E-02 0.00E-01 6.09E 03 i NB 95 1.58E 00 6.51E-01 3.76E-01 0.00E-01 4.66E-01 0.00E-01 5.49E 02 MO 99 0.00E-01 1.20E 03 2.49E 02 0.00E-01 1.91E 03 0.00E-01 4.21E 02 TC 99M 7.22E-02 1.49E-01 1.92E 00 0.00E-01 1.60E 00 7.79E-02 4.33E 01 1 l

l i

i 4

r Ctrrent Copy Proced:re 99-0412 09:07iO1 ,

l H

3 Revision: 2 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 l 5

h Reference Use Page 122 of 168

'M D ATTACHMENT A (Page 117 of 163) 0FFSITE DOSE CALCULATION MANUAL A

0 TABLE A.4-4 (cont' d)

J SITE RELATED DOSE COMMITMENT FACTOR AIT

\ MREM /HR PER kCI/ML l g INTANT W NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI l

\ !

o TC 101 8.54E-02 1.08E-01 1.06E 00 0.00E-01 1.28E 00 5.87E-02 1.83E 01 g RU 103 5.57E 01 0.00E-01 1.86E 01 0.00E-01 1.16E 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 l RU 106 9.07E 02 0.00E-01 1.13E 02 0.00E-01 1.07E 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-0'1 1.42E 03 TE 125M 8.77E 02 2.93E 02 1.19E 02 2.95E 02 0.00E-01 0.00E-01 4.18E 02 TE 127N 2.20E 03 7.30E 02 2.66E 02 6.36E 02 5.42E 03 0.00E-01 8.88E 02 TE 127 3.76E 01 1.26E 01 0.09E 00 3.06E 01 9.18E 01 0.00E-01 7.90E 02 TE 129M 3.76E 03 1.29E 03 5.79E 02 1.44E 03 9.41E 03 0.00E-01 2.25E 03 TE 129 1.07E 01 3.68E 00 2.49E 00 8.95E 00 2.66E 01 0.00E-01 8.54E 02 TE 131H 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 7.82E 02 3.87E 02 3.62E 02 5.72E 02 2.42E 03 0.00E-01 1.43E 03 I 130 2.26E 02 4.97E 02 1.99E 02 5.57E 04 5.45E 02 0.00E-01 1.06E 02 l I 131 1.35E 03 1.59E 03 7.00E 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 0.00E-01 1.03E 02 I 133 4.70E 02 6.85E 02 2.01E 02 1.25E 05 0.05E 02 0.00E-01 1.16E 02 I 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 2.72E 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 7.19E 01 CS 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 0.00E-01 6.17E 03 2.50E 03 7.19E 01 CS 138 1.81E 01 2.94E 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 1.32E-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 BA 141 1.60E 01 1.09E-02 5.04E-01 0.00E-01 6.58E-03 6.66E-03 1.95E 02 BA 142 6.92E 00 5.76E-03 3.41E-01 0.00E-01 3.31E-03 3.48E-03 2.86E 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 2.13E-01 0.00E-01 5.57E-01 0.00E-01 9.33E 02 .

CE 143 5.57E-01 3.69E 02 4.21E-02 0.00E-01 1.08E-01 0.00E-01 2.16E 03 CE 144 1.12E 02 4.59E 01 6.28E 00 0.00E-01 1.85E 01 0.00E-01 6.43E 03 PR 143 3.06E 00 1.14E 00 1.52E-01 0.00E-01 4.25E-01 0.00E-01 1.61E 03 PR 144 1.03E-02 3.99E-03 5.19E-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 8.24E-01 0.00E-01 1.35E 03 W 187 3.40E 01 2.36E 01 8.16E 00 0.00E-01 0.00E-01 0.00E-01 1.39E 03

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f. Revision: 2 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 Reference Use Page 123 of 168 M

O ATTACHMENT A I (Page 118 of 163)

,,0

.0 TABLE A.4-4 (cont' d)

,0 SITE RELATED DOSE COMMITMENT FACTOR AIT 1 MREM /HR PER pCI/ML INFANT bJ NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI

\

g NP 239 4.18E-01 3.74E-02 2.11E-02 0.00E-01 7.455-02 0.00E-01 1.00E 03 Sb 124 0.05E 02- 1.19E 01 2.49E 02 2.14E 00 0.00E-01 5.04E 02 2.48E 03 N Sb 125 4.63E 02 4.48E 00 9.52E 01 5.19E-00 0.00E-01 2.90E 02 6.17E 02 Sb 126 3.03E 02 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 1.47E 02 l

i l

1

gr !

li Czerent Copy ProcedIro 99 0412 09:07;01 Revision: 2 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 f Reference Use Page 124 of 168 m

(J . ATTACHMENT A

-(Page 119=of'163)

,o A TABLE A.5-1

.J'* INMALATION DOSE' PARAMETER FOR THE CHILD, PI I

\ MREM /YR per pCi/M 3 il O

W. H-3 1.12E 03 RU-103 6.62E 05

\ C-14 3.59E 04 RU-105 9.95E 04 O NA-24 1.61E 04 RU-106 1.43E 07 I U P-32 2.60E 06 AG-110M 5.48E 06 CR-51 1.70E 04 TE-125M 4.77E 05 MN-54 1.58E 06 TE-127M- 1.48E 06 MN-56 1.23E 05 TE-127 5.62E 04 FE-55 1.11E 05 TE-129M 1.76E 06 FE-59 1.27E 06 TE-129 2.55E 04 CO-58 1.11E 06 TE-131M 3.08E 05 Co-60 7.07E 06 TE-131 2.05E 03 NI-63 8.21E 05 TE-132 3.77E 05 NI-65 8.40E 04 I-130 1.85E 06 CU-64 3.67E 04 I-131 1.62E 07 ZN 9.95E 05 I-132 1.94E 05-ZN-69 1.02E 04 I-133 3.85E 06 BR-83 4.74E 02 I-134 5.07E 04 BR-84 5.48E 02 .I-135 7.92E 05 BR-85 2.53E Ol' 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 Y-90 2.68E 05 LA-140 2.26E 05

.Y-91M 2.81E 03 LA-142 7.59E 04 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 l-l

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.0 Tanza A.5-2

0. INHALATION PATHWAY FACTOR

( MREM /YR-PER pCI/M 3 ADULT (RI FACTORS)

O N NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI

\

g H 3 0.005 01 1.26E 03 1.26E 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 N NA 24 1.02E 04 1.02E 04 1.02E 04 1.02E 04 1.02E 04 1.02E 04 1.02E 04 P 32 1.32E 06 7.71E 04 5.01E 04 0.00E-01 0.00E-01 0.00E-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 0.00E 01 1.24E 00 1.83E-00 0.00E-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 FE 59 1.18E 04 2.78E 04 1.06E 04 0.00E-01 0.00E-01 1.02E 06 1.88E 05 CO 58 0.00E 01 1.58E 03 2.07E 03 0.00E-01 0.00E-01 9.28E 05 1.06E 05 CO 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 0.00E 01 1.46E 00 6.15E-01 0.00E-01 4.62E 00 6.78E 03 4.90E 04 EN 65 3.24E 04 1.03E 05 4.66E 04 0.00E-01 6.90E 04 8.64E 05 5.34E 04 ZN 69 3.38E-02 6.51E-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 1.28E 01 0.00E-01 0.00E-01 0.00E-01 0.00E-15 RB 86 0.00E-01 1.35E 05 5.90E 04 0.00E-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 Ra 89 0.00E-01 2.56E 02 1.70E 02 0.00E-01 0.00E-01 0.00E-01 9.28E-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 0.00E-01 0.00E-01 1.65E 04 4.30E 04 Y 90 2.09E 03 0.00E-01 5.61E 01 0.00E-01 0.00E-01 1.70E 05 5.06E 05 Y 91M 2.61E-02 0.00E-01 1.02E-02 0.00E-01 0.00E-01 1.92E 03 1.33E 00 Y 91 4.62E 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 0.00E-01 1.57E 04 7.35E 04 Y . 93 9.44E 01 0.00E-01 2.61E 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 ,

2R 97 9.68E 01 1.96E 01 9.04E 00 0.00E-01 2.97E 01 7.87E 04 5.23E 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 0.00E-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

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'n g Reference Use Page 126 of 168 N

CI ATTACHMENT A (Page 121 of 163) 0FFSITE DOSE CALCULATION MANUAL l

..D ;

0 TAaLE A.5-2 (cont'd) l l J INHALATION PATHWAY FACTOR l ( MREM /YR PER pCI/M 3 ;

g ' ADULT (R1 FACTORS) l l

W NUCLIDE BONE LIVER T BODY THYROID KTDNEY LUNG GI-LLI ,

\ I O TC 101 4.18E-05 6.02E-05 5.90E-04 0.00E-01 1.08E-03 3.99E 02 1.09E-11 '

g 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 1 1

RU -106 6.91E 04 0.00E-01 8.'l2E 03 0.00E-01 1.34E 05 9.36E 06 9.12E 05 AG 110M 1.0BE 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 '1.0$E 03 1.24E 04 3.14E 05 7.06E 04 TE 127M 1.26E 04 5.77E 03 1.57E 03 3.29E 03 4.58E 04 9.60E 05 1.50E 05 TE 127 1.40E 00 6.42E-01 3.10E-01 1.06E 00 5.10E 00 6.51E 03 5.14E 04 TE 129M 9.76E 03 4.67E 03 1.58E 03 3.44E 03 3.66E 04 1.16E 06 3.83E 05 TE 129 4.90E-02 2.39E-02 1.24E-02 3.90E-02 1.87E-01 1.94E 03 1.57E 02 TE 131M 6.99E 01 4.36E 01 2.90E 01 5.50E 01 3.09E 02 1.46E 05 5.56E 05 TE 131 1.11E-02 5.95E-03 3.59E-03 9.36E-02 4.37E-02 1.39E-03 1.84E 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 4.58E 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 l

l I 132 1.16E 03 3.26E 03 1.16E 03 1.14E 05 5.18E 03 0.00E-01 4.06E 02 l I 133 8.64E 03 1.48E 04 4.52E 03 2.15E 06 2.58E 04 0.00E-01 8.88E 03 I 134 6.44E 02 1.73E 03 6.15E 02 2.9BE 04 2.75E 03 0.00E-01 1.01E 00 l

I 135 2.68E 03 6.98E 03 2.57E 03 4.48E 05 1.11E 04 0.00E-01 5.25E 03 CS 134 3.73E 05 0.4BE 05 7.28E 05 0.00E-01 2.87E 05 9.76E 04 1.04E 04 CS 136 3.90E 04 1.46E 05 1.10E 05 0.00E-01 8.56E 04 1.20E 04 1.17E 04 CS 137 4.78E 05 6.21E 05 4.28E 05 0.00E-01 2.22E 05 7.52E 04 8.40E 03 CS 138 3.31E 02 6.21E 02 3.24E 02 0.00E-01 4.80E 02 4.86E 01 1.86E-03 BA 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 2.57E 03 0.00E-01 1.67E 01 1.27E 06 2.18E 05 BA 141 1.00E-01 7.53E-05 3.36E-03 0.00E-01 7.00E-05 1.94E 03 1.16E-07 l

BA 142 2.63E-02 2.70E-05 1.66E-03 0.00E-01 2.29E-05 1.19E 03 1.57E-16 I

l LA 140 3.44E 02 1.74E 02 4.58E 01 0.00E-01 0.00E-01 1.36E 05 4.58E 05 l LA 142 6.83E-01 3.10E-01 7.72E-02 0.00E-01 0.00E-01 6.33E 03 2.11E 03 l CE 141 1.99E 04 1.35E 04 1.53E 03 0.00E-01 6.26E 03 3.62E 05 1.20E 05 l CE 143 1.86E 02 1.38E 02 1.53E 01 0.00E-01 6.08E 01 7.98E 04 2.265 05 i CE 144 3.43E 06 1.43E 06 1.84E 05 0.00E-01 8.4BE 05 7.788 06 8.16E 05 PR 143 9.36E 03 3.75E 03 4.64E 02 0.00E-01 2.16E 03 2.81E 05 2.00E 05 PR 144 3.10E-02 1.25E-02 1.53E-03 0.00E-01 1.05E-03 1.02E 03 2.15E-08 ND 147 5.27E 03 6.10E 03 3.65E 02 0.00E-01 3.56E 03 2.21E 05 1.73E 05 W 187 8.48E 00 7.08E 00 2.48E 00 0.00E-01 0.00E-01 2.905 04 1. 55E 05 NP 239 2.30E 02 2.26E 01 1.24E 01 0.00E-01 7.00E 01 3.76E 04 1.19E 05 l

i

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U ATTACHMENT A (Page 122 of 163)

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0FFSITE DOSE CALCULATION MANUAL j

".0 S TABLE A.5-3

.0 INHALATION PATHWAY FACTOR

\ HREM/YR PER pCI/M 3 g TEEN (RI FACTORS) f\ NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI l

(3 H 3 0.00E-01 1.27E 03 1.27E 03 1.27E 03 1.27E 03 1.27E 03 1.27E 03 y C 14 2.60E 04 4.87E 03 4.87E 03 4.87E 03 4.87E 03 4.87E 03 4.87E 03 NA 24 1.30E 04 1.38E 04 1.38E 04 1.38E 04 1.38E 04 1.38E 04 1.38E 04 P 32 1.89E 06 1.10E 05 7.16E 04 0.00E-01 0.00E-01 0.00E-01 9.28E 04 .

CR 51 0.00E-01 0.00E-01 1.35E 02 7.50E 01 3.07E 01 2.10E 04 3.00E 03 l MN $4 0.00E-01 5.11E 04 8.40E 03 0.00E-01 1.27E 04 1.90E 06 6.68E 04 MN 56 0.00E-01 1.70E 00 2.52E-01 0.00E-01 1.79E 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 j rt 59 1.59E 04 3.10E 04 1.43E 04 0.00E-01 0.00E-01 1.53E 06 1.78E 05 :

CO 58 0.00E-01 2.07E 03 2.78E 03 0.00E-01 0.00E-01 1.34E 06 9.52E 04 CO 60 0.00E-01 1.51E 04 1.98E 04 0.00E-01 0.00E-01 0.72E 06 2.59E 05 NI 63 5.80E 05 4.34E 04 1.98E 04 0.00E-01 0.00E-01 3.07E 05 1.42E 04 NI 65 2.18E 00 2.93E-01 1.27E-01 0.00E-01 0.00E-01 .36E 03 3.67E 04 CU 64 0.00E-01 2.03E 00 8.48E-01 0.00E-01 6.41E 00 1.11E 04 6.14E 04 I EN 65 3.86E 04 1.34E 05 6.24E 04 0.00E-01 8.64E 04 1.24E 06 4.66E 04 1 ZN 69 4.83E-02 9.20E-02 6.46E-03 0.00E-01 6.02E-02 1.58E 03 2.85E 02 BR 83 0.00E-01 0.00E-01 3.44E 02 0.00E-01 0.00E-01 0.00E-01 0.00E-15 BR 84 0.00E-01 0.00E-01 4.33E 02 0.00E-01 0.00E-01 0.00E-01 0. 00E- 15 BR 85 0.00E-01 0.00E-01 1.83E 01 0.00E-01 0.00E-01 0.00E-01 8.00E-15 RB 86 0.00E-01 1.90E 05 8.40E 04 0.00E-01 0.00E-01 0.00E-01 1.77E 04 RD 88 0.00E-01 5.46E 02 2.72E 02 0.00E-01 0.00E-01 0.00E-01 2.92E-05 RB 89 0.00E-01 3.52E 02 2.33E 02 0.00E-01 0.00E-01 0.00E-01 3.38E-07 SR 89 4.34E 05 0.00E-01 1.25E 04 0.00E-01 0.00E-01 2.42E 06 3.71E 05 SR 90 1.08E 08 0.00E-01 6.68E 06 0.00E-01 0.00E-01 1.65E 07 7.65E 05 SR 91 8.80E 01 0.00E-01 3.51E 00 0.00E-01 0.00E-01 6.07E 04 2.59E 05 SR 92 9.52E 00 0.00E-01 4.06E-01 0.00E-01 0.00E-01 2.74E 04 1.19E 05 Y 90 2.98E 03 0.00E-01 8.00E 01 0.00E-01 0.00E-01 2.93E 05 5.59E 05 Y 91M 3.70E-01 0.00E-01 1.42E-02 0.00E-01 0.00E-01 3.20E 03 3.02E 01 Y 91 6.61E 05 0.00E-01 1.77E 04 0.00E-01 0.00E-01 2.94E 06 4.09E 05 Y 92 1.47E 01 0.00E-01 4.29E-01 0.00E-01 0.00E-01 2.68E 04 1.65E 05 Y 93 1.35E 02 0.00E-01 3.72E 00 0.00E-01 0.00E-01 8.32E 04 5.79E 05 ZR 95 1.46E 05 4.58E 04 3.15E 04 0.00E-01 6.74E 04 2.69E 06 1.49E 05 ZR 97 1.30E 02 2.72E 01 1.26E 01 0.00E-01 4.12E 01 1.30E 05 6.30E 05 Na 95 1.86E 04 1.03E 04 5.66E 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 2.69E 05 TC 99M 1.38E-03 3.86E-03 4.99E-02 0.00E-01 5.76E-02 1.15E 03 6.13E 03

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p Reference Use Page 128 of 168 m

P ATTACHMENT A (Page 123 of 163)

OFFSITE DOSE CALC'ULATION MANUAL 0

40 TABIA A.5-3 (cont'd)

D INHALATION PATH 14AY FACTOR i

\ MREM /YR PER pCI/M'

]

g TEEN (RI FACTORS) i N NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI

\

C3 TC 101 5.92E-05 8.40E-05 8.24E-04 0.00E-01 1.52E-03 6.67E 02 8.72E-07 g 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 RU 106 9.84E 04 0.00E-01 1.24E 04 0.00E-01 1.90E 05 1.61E 07 9.60E 05 I AG - 110M 1.30E 04 1.31E 04 7.99E 03 0.00E-01 2.50E 04 6.75E 06 2.73E 05 i TE 125M 4.88E 03 2.24E 03 6.74E 02 1.40E 03 0.00E-01 5.36E 05 7.50E 04 ,

j TE 127M 1.80E 04 8.16E 03 2.18E 03 4.38E 03 6.54E 04 1.66E 06 1.59E 05 l 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 1.98E u6 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 2.30E 05 6.21E 05 TE 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 2.46E 02 1.95E 03 4.49E 05 4.63E 05 I 130 6.24E 03 1.79E 04 7.17E 03 1.49E 06 2.75E 04 0.00E-01 9.12E 03 I 131 3.54E 04 4.91E 04 2.64E 04 1.46E 07 8.40E 04 0.00E-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 l I 133 1.22E 04 2.05E 04 6.22E 03 2.92E 06 3.59E 04 0.005-01 1.03E 04 l 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 4.66E 02 8.56E 02 4.46E 02 0.00E-01 6.62E 02 7.87E 01 2.70E-01 BA 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 2.03r. 06 2.29E 05 l BA 141 1.42E-01 1.06E-04 4.74E-03 0.00E-01 9.84E-05 3.29E 03 7.46E-04 j BA 142 3.70E-02 3.10E-05 2.27E-03 0.00E-01 3.14E-05 1.91E 03 4.79E-10 l 1

LA 140 4.79E 02 2.36E 02 6.26E 01 0.00E-01 0.00E-01 2.14E 05 4.87E 05 i LA 142 9.60E-01 4.25E-01 1.06E-01 0.00E-01 0.00E-01 1.02E 04 1.20E 04 l Cr. 141 2.84E 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 2.16E 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 1 PR 143 1.34E 04 5.31E 03 6.62E 02 0.00E-01 3.09E 03 4.83E 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 0.56E 03 5.13E 02 0.V0E-01 5.02E 03 3.72E 05 1.82E 05 W 187 1.20E 01 9.76E 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 l

l l

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,~1 Revision: 2 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 10 g Reference Use Page 129 of 168 l VI D ATTACHMENT A L (Page 124 of 163) !

.0

.D TAaLa A.5-4 j

.0 INHALATION PATHWAY FACTOR g MREM /YR PER pCI/H' )

g CHILD (RI FACTORS) bJ NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI f

\

g 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 03 6.73E 03 l NA 24 1.61E 04 1.61E 04 1.61E 04 1.61E 04 1.61E 04 1.61E 04 1.61E 04

]

P 32 2.60E 06 1.14E 05 9.88E 04 0.00E-01 0.00E-01 0.00E-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 e 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 3.12E-01 0.00E-01 1.67E 00 1.31E 04 1.23E 05 FE 55 4.74E 04 2.52E 04 7.77E 03 0.00E-01 0.00E-01 1.11E 05 2.87E 03 j FE 59 2.07E 04 3.34E 04 1.67E 04 0.00E-01 0.00E-01 1.27E 06 7.07E 04 CO 50 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' j i

NI 65 2.99E 00 2.96E-01 1.64E-01 0.00E-01 0.00E-01 8.18E 03 8.40E 04 i CO 64 0.00E-01 1.99E 00 1.07E 00 0.00E-01 6.03E 00 9.58E 03 3.67E 04 l EN 65 4.26E 04 1.13E 05 7.03E 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 1.42E 03 1.02E 04 l BR 83 0.00E-01 0.00E-01 4.74E 02 0.00E-01 0.00E-01 0.00E-01 3.70E-15 1 BR 84 0.00E-01 0.00E-01 5.48E 02 0.00E-01 0.00E-01 0.00E-01 3.70E-15 l 1

BR 85 0.00E-01 0.00E-01 2.53E 01 0.00E-01 0.00E-01 0.00E-01 3.70E-15 i RB 86 0.00E-01 1.90E 05 1.14E 05 0.00E-01 0.00E-01 0.00E-01 7.99E 03 !

RB 88 0.00E-01 5.62E 02 3.66E 02 0.00E-01 0.00E-01 0.00E-01 1.72E 01 )

RB 89 0.00E-01 3.45E 02 2.90E 02 0.00E-01 0.00E-01 0.00E-01 1.89E 00 !

SR 89 5.99E 05 0.00E-01 1.72E 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 0.00E-01 1.40E 07 3.43E 05 SR 91 1.21E 02 0.00E-01 4.59E 00 0.00E-01 0.00E-01 5.33E 04 1.74E 05 SR 92 1.31E 01 0.00E-01 5.25E-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 9.14E 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 2.39E 05 Y 93 1.86E 02 0.00E-01 5.11E 00 0.00E-01 0.00E-01 7.44E 04 3.89E 05 ZR 95 1.90E 05 4.18E 04 3.70E 04 0.00E-01 5.96E 04 2.23E 06 6.11E 04 ZR 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 9.185 03 6.55E 03 0.00E-01 8.62E 03 6.14E 05 3.70E 04 MO 99 0.00E-01 1.72E 02 4.25E 01 0.00E-01 3.92E 02 1.35E 05 1.27E 05 i TC 99M 1.78E-03 3.48E-03 5.77E-02 0.00E-01 5.07E-02 9.51E 02 4.811 03 l I

l i

C:rre:t C py Proccd:re 99-0412 09:07iO1 4-1 3 Revision: 2 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 D

p Reference Use Page 130 of 168 l M

P ATTACFMENT A l (Page 125 of 163)

.OFFSITE DOSE CALCULATION MANUAL 0

.D 0 TABLE A.5-4 (cont' d)

..D INHALATION PATHWAY FACTOR

( MREM /YR PER pCI/M 3 CHILD (RI FACTORS) g W NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI

\

O TC 101 8.10E-05 8.51E-05 1.08E-03 0.00E-01 1.45E-03 5.85E 02 1.63E 01 g 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 0.00E-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 TE 127M 2.49E 04 8.55E 03 3.02E 03 6.07E 03 6.36E 04 1.48E 06 7.14E 04 TE 127 2.77E 00 9.51E-01 6.10E-01 1.96E 00 7.07E 00 1.00E 04 5.62E 04 TE 129M 1.92E 04 6.85E 03 3.04E 03 6.33E 03 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 9.77E 01 4.00E 02 2.06E 05 3.08E 05 TE 131 2.17E-02 8.44E-03 6.59E-03 1.70E-02 5.88E-02 2.05E 03 1.33E 03 TE 132 4.81E 02 2.72E 02 2.63E 02 3.17E 02 1.77E 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 1.62E 07 7.88E 04 0.00E-01 2.84E 03 I 132 2.12E 03 4.07E 03 1.88E 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 9.9!L 02 5.01E 04 3.30E 03 0.00E-01 9.55E 02 I 135 4.92E 03 8.73E 03 4.14E 03 7.92E 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 1.71E 05 1.16E 05 0.00E-01 9.55E 04 1.45E 04 4.18E 03 CS 137 9.0?E 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 02 BA 139 1.84E 00 9.84E-04 5.36E-02 0.00E-01 8.62E-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 BA 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 2.2SE 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 2.90E 03 0.00E-01 8.55E 03 5.44E 05 5.66E 04 CE 143 3.66E 02 1.99E 02 2.87E 01 0.00E-01 8.365 01 1.15E 05 1.27E 05 CE 144 6.77E 06 2.12E 06 3.61E 05 0.00E-01 1.175 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 3.00E-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 1.63E 01 9.66E 00 4.33E 00 0.00E-01 0.00E-01 4.11E 04 9.10E 04 NP 239 4.66E 02 3.34E 01 2.35E 01 0.00E-01 9.73E 01 5.81E 04 6.40E 04

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3 Revision: 2 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 Reference Use Page 131 of 168 i

N l l ATTACHMENT A (Page 126 of 163) 0FFSITE DOSE CALCULATION MANUAL

) ,

f TABLE A.5-5

.s INHALATION PATHWAY FACTOR 2

g MREM /YR PER kCI/M O INFANT (RI FACTORS)

W NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG CI-LLI

\

g. 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 5.31E 03 5.31E 03 5.31E 03 5.31E 03 5.31E 03

,h 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 1.12E 05 7.74E 04 0.00E-01 0.00E-01 0.00E-01 1.61E 04

CR 51 0.00E-01 0.00E-01 0.95E 01 5.75E 01 1.32E 01 1.28E 04 3.57E 02 MN 54 0.00E-01 2.53E 04 4.90E 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 7.17E 04 FE 55 1.97E 04 1.17E 04 3.33E 03 0.00E-01 0.00E-01 8.69E 04 1.09E 03 FE $9 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 1.82E 03 0.00E-01 0.00E-01 7.77E 05 1.11E 04 CO 60 0.00E-01 0.02E 03 1.18E 04 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 2.39E 00 2.84E-01 1.23E-01 0.00E-01 0.00E-01 8.12E 03 5.01E 04 CU 64 0.00E-01 1.88E 00 7.74E-01 0.00E-01 3.90E 00 9.30E 03 1.50E 04 ZN 65 1.93E 04 6.26E 04 3.11E 04 0.0CE-01 3.25E 04 6.47E G5 5.14E 04 ZN 69 5.39E-02 9.67E-02 7.18F-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 0.00E-01 1.40E-15 BR 84 0.00E-01 0.00E-01 4.00E 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 86 0.00E-01 1.90E 05 8.02E 04 0.00E-01 0.00E-01 0.00E-01 3.04E 03 RB 88 0.00E-01 5.57E 02 2.07E 02 0.00E-01 0.00E-01 0.00E-01 3.39E 02 RB 89 0.00E-01 3.21E 02 2.06E 02 0.00E-01 0.00E-01 0.00E-01 6.82E 01 SR 89 3.98E 05 0.00E-01 1.14E 04 0.0CE-01 0.00E-01 2.03E 06 6.40E 04 SR 90 4.09E 07 0.00E-01 2.59E 06 0.0CE-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 3.29E 03 0.00E-01 8.82E 01 0.00E-01 0.00E-01 2.69E 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 5.88E 05 0.00E-01 1.57E 04 0.00E-01 0.00E-01 2.45E 06 7.03E 04 Y 92 1.64E 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 2.17E 04 2R 91 1.50E 02 2.56E 01 1.17E 01 0.00E-C1 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 HO 99 0.0CE-01 1.65E 02 3.23E 01 0.00E-01 2.65E 02 -1.35E 05 4.87E 04 TC 99M 1.40E-04 2.88E-03 3.72E-02 0.00E-01 3.11E-02 8.11E 02 2.03E 03

m Czrroit Copy Procs41 Ire 99 0412 09:07:01 b' .

,1 Revision: 2 OFFSITE DOSE CALCULATION MANUAL AP 07B-003

?D '

p3 Reference Use Page 132 of 168 18 U. ATTACHMENT A

~~

.(Page 127 of 163)

0 TAnLa A.5-5 (cont'd)

' .0 INHALATION PATHWAY FACTOR

\ MREN/YR PER pCI/M' g INFANT (RI FACTORS)

N1 NUCLIDE' BONE LIVER 7 BODY THYROID KIDNEY LUNG GI-LLI t g.

C3 TC 101 6.51E-05 8.23E-05 8.12E-04 0.00E-01 9.79E-04 5.84E 02 8.44E 02 y . RU - 103 2.02E 03 0.00E-01 6.79E 02 0.00E-01 4.24E 03 5.52E 05 1.61E 04 RU 105- 1.22E 00 0.00E-01 4.10E-01 0.00E-01 8.99E-01 1.57E 04 4.84E 04 RD 106 8.68E 04- 0.00E-01 1.09E 04 0.00E-01 1.07E 05 1.16E 07 1.64E 05 AG 110M' 9.98E 03 7.22E 03 5.00E 03 0.00E-01 1.09E 04 3.67E 06 3.30E 04 TE 125M 4.76E 03 1.99E 03 6.58E 02 1.62E 03 0.00E-01 4.47E 05 1.29E 04 ,

TE 127M 1.67E 04 6.90E 03 2.07E 03 4.87E 03 3.75E 04 1.31E 06 2.73E 04 ;

-127 2.23E 00 9.53E-01 4.89E-01 1.85E 00 4.86E 00 1.03E 04 2.44E 04

=

TE TE 129M 1.41E 04 6.09E 03 2.23E 03 5.47E 03 3.18E 04 1.68E 06 6.90E 04 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 3.72E 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 2.24F. 04 0.00E-01 2.16E 03 I ~134 9.21E 02 1.88E 03 6.65E 02 4.45E 04 2.09E 03 0.00E-01 1.29E 03 I 135 3.86E 03 1.60E 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 CS '136 4.83E 04 1.35E 05 5.29E 04 0.00E-01 5.64E 04 1.18E 04 1.43E 03 CS 137 5.49E 05 6.12E 05 4.55E 04' O.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 LA 140 5.05E 02 2.00E 02 5.15E 01 0.00E-01 0.00E-01 1.68E 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 5.1?E 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 5.38E 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 1

Ctrrett Crpy Proc d:re 99 0412 09.07:01 14 3 Revisioni 2 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 j I

{'O 3 Reference Use Page 133 of 168 in D ATTACHMENT A (Page 128 of 163)

.D

,0 TAsLE A.5-6

,0 GRASS-CCW-MILK PATHWAY FRCTOR

\ MI MREM /YR PER pCI/SEC l ADULT (RI FACTORS) 43 DJ NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI

\

(3 H 3 0.00E-01 7.63E 02 7.63E 02 7.63E 02 7.63E 02 7.63E 02 7.63E 02 g) 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 0.00E-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 8.41E 06 1.61E 06 0.00E-01 0.00E-01 0.00E-01 2.58E 07 MN 56 0.00E-01 4.16E-03 7.38E-04 0.00E-01 5.28E-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 6.98E 07 2.68E 07 0.00E-01 0.00E-01 1.95E 07 2.33E 08 I

C0 58 0.00E-01 4.71E 06 1.06E 07 0.00E-01 0.00E-01 0.00E-01 9.56E 07 i CO 60 0.00E-01 1.64E 07 3.62E 07 0.00E-01 0.00E-01 0.00E-01 3.08E 08 j NI 63 6.73E 09 4.71E 08 2.26E 08 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 EN 65 1.37E 09 4.37E 09 1.97E 09 0.00E-01 2.92E 09 0.00E-01 2.75E 09 ZN 69 5.22E-12 9.99E-12 6.95E-13 0.00E-01 6.49E-12 0.00E-01 1.50E-12 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 0.00E-01 2.59E 09 1.21E 09 0.00E-01 0.00E-01 0.00E-01 5.12E 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-OL SR 89 1.45E 09 0.00E-01 4.16E 07 0.00E-01 0.00E-01 0.00E-01 2.33E 08 SR 90 4.68E 10 0.00E-01 1.15E 10 0.00E-01 0.00E-01 0.00E-01 1.35E 09 SR 91 2.87E 04 0.00E-01 1.16E 03 0.00E-01 0.00E-01 0.00E-01 1.37E 05 SR 92 4.90E-01 0.00E-01 2.12E-02 0.00E-01 0.00E-01 0.00E-01 9.70E 00 Y 90 7.0?E 01 0.00E-01 1.90E 00 0.00E-01 0.00E-01 0.00E-01 7.50E 05 Y 91M 6.03E-20 0.00E-01 2.34E-21 0.00E-01 0.00E-01 0.00E-01 1.77E-19 Y 91 8.59E 03 0.00E-01 2.30E 02 0.00E-01 0.00E-01 0.00E-01 4.73E 06 ;

Y 92 5.59E-05 0.00E-01 1.63E-06 0.00E-01 0.00E-01 0.00E-01 9.79E-01 I 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 9.44E 02 3.03E 02 2.05E 02 0.00E-01 4.75E 02 0.00c-01 9.59E 05 ER 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 i MO 99 0.00E-01 2.48E 07 4.71E 06 0.00E-01 5.61E 07 0.00E-01 5.74E 07 l TC 99M 3.33E 00 9.40E 00 1.20E 02 0.00E-01 1.43E 02 4.60E 00 5.56E 03 '

l

CIrre!t Copy Proced re 99 0412 09:07(01 H

3 Revision: 2 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 n l h Reference Use Page 134 of 168 km i U ATTACHMENT A I (Page 129 of 163)

~

..o

.0 TAsia A.5-6 (cont'd)

,0 GRASS-COW-MILK PATHWAY FACTOR l M2 MREM /YR PER pCI/SEC

\

g ADULT (RI TACTORS)

N NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI l

\ I o TC 101 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 g 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 0.58E-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 AG 110M 5.82E 07 5.39E 07 3.20E 07 0.00E-01 1.06E 08 0.00E-01 2.20E 10 TE 125M 1.63E 07 5.90E 06 2.18E 06 4.90E 06 6.63E 07 0.00E-01 6.50E 07 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 2.25E 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 TE 131M 3.61E 05 1.77E 05 1.47E 05 2.8CE 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 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 09 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 8.28E-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 l i

I 135 1.29E 04 3.37E 04 1.24E 04 2.22E 06 5.40E 04 0.00E-01 3.80E 04 )

C3 134 5.65E 09 1.35E 10 1.10E 10 0.00E-01 4.35E 09 1.45E 09 2.35E 08 CS 136 2.61E 08 1.03E 09 7.42E 08 0.00E-01 5.73E 08 7.868 07 1.17E 08 CS 137 7.38E 09 1.01E 10 6.61E 09 0.00E-01 3.43E 09 1.14E 09 1.95E 08 i 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 3.04E-11 1.84E-11 8.09E-08 [

W BA 140 2.69E 07 3.38E 04 1.76E 06 0.00E-01 1.15E 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 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 l LA 140 4.52E 00 2.28E 00 6.02E-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-01 0.00E-01 3.12E-08 CE 141 4.84E 03 3.28E 03 3.72E 02 0.00E-01 1.52E 03 0.00E-01 1.25E 07 CE 143 4.16E 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 8.87E 04 0.00E-01 1.21E 08 PR 143 1.58E 02 6.33E 01 7.83r 00 0.00E-01 3.66E 01 0.00E-01 6.92E 05 PR 144 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 NO 147 9.46E 01 1.09E 02 6.55E 00 0.00E-01 6.40E 01 0.00E-01 5.25E 05 W 187 6.56E 03 5.49E 03 1.92E 03 0.00E-01 0.00E-01 0.00E-01 1.80E 06 NP 239 3.67E 00 3.61E-01 1.99E-01 0.00E-01 1.13E 00 0.00E-01 7.41E 04

G rre:t Copy Proc:d:re 99 04 12 09.07:01 H

3 Revision: 2 OFFSITE DOSE CALCULATION MANUAL AP 078-003 D

g Reference Use Page 135 of 168 l VI P ATTACHMENT A (Page 130 of 163)

~ l OFFSITE DOSE CALCULATION MANUAL 0

J TABLE A.5-7 D GBASS-COW-MILK PATHWAY FACTOR

\ M8 MREM /YR PER pCI/SEC O TEEN (RI FACTORS)

W NUCLIOE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI

\

Q H 3 0.00E-01 9.94E 02 9.94E 02 9.94E 02 9.94E 02 9.94E 02 9.94E 02 g C 14 4.86E 08 9.72E 07 9.72E 07 9.72E 07 9.72E 07 9.72E 07 9.72E 07 NA 24 4.26E 06 4.26E 06 4.26E 06 4.26E 06 4.26E 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 8.39E 06 KN 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 4.455 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 09 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 C0 60 0.00E-01 2.78E 07 6.26E 07 0.00E-01 0.00E-01 0.00E-01 3.62E 08 NI 63 1.18E 10 8.35E 09 4.01E 08 0.00E-01 0.00E-01 0.00E-01 1.33E 08 NI 65 8.48E-01 1.08E-01 4.94E-02 0.00E-01 0.00E-01 0.00E-01 5.88E 00 CU 64 0.00E-01 4.25E 04 2.00E 04 0.00E-01 1.00E 05 0.00E-01 3.30E 06 ZN 65 f.11E 09 7.31E 09 3.41E 09 0.00E-01 4.68E 09 0.00E-01 3.10E 09 EN 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 i RB 86 0.00E-01 4.73E 09 2.22E 09 0.00E-01 0.00E-01 0.00E-01 7.00E 08 d RB 88 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 i RB 09 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 0.00E-01 7.66E 07 0.00E-01 0.00E-01 0.00E-01 3.19E 08 SR 90 6.61E 10 0.00E-01 1.63E 10 0.00E-01 0.00E-01 0.00E-01 1.P6E 09 SR 91 5.27E 04 0.00E-01 2.10E 03 0.00E-01 0.00E-01 0.00E-01 2.39E 05 SR 92 8.96E-01 0.00E-01 3.82E-02 0.00E-01 0.00E-01 0.00E-01 2.28E 01 ]

Y 90 1.30E 02 0.00E-01 3.50E 00 0.00E-01 0.00E-01 0.00E-01 1.07E 06 .

Y 91M 1.11E-19 0.00E-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 0.00E-01 0.00E-01 2.83E 00 Y 93 4.30E-01 0.00E-01 1.18E-02 0.005-01 0.00E-01 0.00E-01 1.31E 04 ZR 95 1.65E 03 5.21E 02 3.58E 02 0.00E-01 7.65E 02 0.00E-01 1.20E 06 ER 97 7.89E-01 1.56E-01 7.19E-02 0.00E-01 2.37E-01 0.00E-01 4.23E 04 N3 95 1.41E 05 7.81E 04 4.30E 04 0.00E-01 7.57E C4 0.00E-01 3.34E 08 l MO 99 0.00E-01 4.47E 07 8.53E 06 0.00E-01 1.02E 09 0.00E-01 0.01E 07 l TC 99M 5.77E 00 1.61E 01 2.08E 02 0.00E-01 2.40E 02 8.93E 00 1.06E 04 I

CYrrent Copy ProcMlre 99 04-12 09:07;01 I

k.4 3 Revision: 2 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 Reference Use Page 136 of 168 f3 m i 9 ATTACHMENT A (Page 131 of 163) l OFFSITE DOSE CALCULATION MANUAL i

".0

.0 TAnLE A.5-7 (con t;* d)

..D GRASS-COW-MILK PATHWAY FACTOR 1' 3

\ M MREM /YR PER MCI /SEC g TEEN (RI FACTORS)

N NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI ,

\ !

g TC 101 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 l g RU 103 1.81E 03 0.00E-01 7.74E 02 0.00E-01 6.38E 03 0.00E-01 1.51E 05 '

RU 105 1.57E-03 0.00E-01 6.08E-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 1.23E 04 0.00E-01 1.80E 06 AG 110M 9.63E 07 9.11E 07 5.54E 07 0.00E-01 1.74E 08 0.005-01 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 3.42E 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 3J55E 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 TE 132 4.29E 06 2.72E 06 2.56E 06 2.R7E 06 2.61E 07 0.00E-01 8.61E 07 I 130 7.39E 05 2.14E 06 8.54E 05 1.74E 08 3.26E 06 0.00E-01 1.64E 06 I 131 5.37E 08 7.52E 09 4.04E 08 2.20E 11 1.30E 09 0.00E-01 1.495 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 9.08L 06 I 134 3.61E-12 9.58E-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 3.18E 06 9.28E 04 0.00E-01 6.51E 04 CS 134 9.02E 09 2.31E 10 1.07E 10 0.00E-01 7.34E 09 2.80E 09 2.87E 08 CS 136 4.44E 08 1.75E 09 1.17E 09 0.00E-01 9.52E 08 1.50E 08 1.41E 08 CS 137 1.34E 10 1.78E 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 2.46E-09 0.00E-01 5.60E-11 4.00E-11 7.53E-07 BA 140 4.85E 07 5'.95E 04 3.13E 06 0.00E-01 2.02E 04 4.00E 04 7.48E 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 8.12E 00 3.99E 00 1.06E 00 0.00E-01 0.00E-01 0.00E-01 2.29E 05 LA 142 1.69E-11 7.52E-12 1.87E-12 0.00E-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 3.54E 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 0.00E-01 9.55E 05 PR 144 0.00E-01 0.00E-01 0.005-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 ND 147 1.82E 02 1.98E 02 1.19E 01 0.00E-01 1.16E 02 0.00E-01 7.15E 05 W 187 1.20E 04 9.78E 03 3.43E 03 0.00E-01 0.00E-01 0.00E-01 2.65E 06 NP 239 7.01E 00 6.61E-01 3.67E-01 0.00E-01 2.07E 00 0.00E-01 1.06E 05

GYrroit Capy Proc: dure 99-0412 09107i01 H

Revision: 2 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 3

Reference Use Page 137 of 168 m

p ATTACHMENT A (Page 132 of 163)

.0

..D TABLE A.5-8 0 GRASS-COW-MILK PATHWAY FACTOR g M2 MREM /YR PER pCI/SEC g CHILD (RI FACTORS)

W NUCLIDE BCNE LIVER T BODY THYROID KIDNEY LUNG GI-LLI

\

g3 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 OS 2.39E 08 2.39E 08 2.39E 08 2.39E 08 2.39E 08 N HA 24 8.06E 06 8.86E 06 8.86E 06 8.86E 06 8.86E 06 8.865 06 8.86E 06 P 32 7.77E 10 3.64E 09 3.005 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 0.00E-01 5.64E 07 2.02E 08 CO 58 0.00E-01 1.21E 07 3.71E 07 0.00E-01 0.00E-01 0.00E-01 7.07E 07 CC 60 0.00E-01 4.32E 07 1.27E 08 0.00E-01 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 0.00E-01 0.00E-01 2.39E 01 CU 64 0.00E-01 7.47E 04 4.51E 04 0.00E-01 1.81E 05 0.00E-01 3.51E 06 ZN 65 4.13E 09 1.10E 10 6.85E 09 0.00E-01 6.94E 09 0.00E-01 1.93E 09 ZN 69 2.36E-11 3.42E-11 3.16E-12 0.00E-01 2.07E-10 0.00E-01 2.15E-09 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 0.00E-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-51 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 Y 90 3.22E 02 0.00E-01 8.61E 00 0.00E-01 0.00E-01 0.00E-01 9.15E 05 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 0.00E-01 0.00E-01 5.20E 06 Y 92 2.54E-04 0.00E-01 7.26E-06 0.00E-01 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 ZR 95 3.83E 03 8.43E 02 7.50E 02 0.00E-01 1.21E 03 0.00E-01 8.79E 05 ZR 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 0.00E-01 3.77E 02 1.32E 01 1.48E 04 l

I

Mrre;t Copy Proc:dzre 99 0412 09:07:01 Revision: 2 OFFSITE DOSE CALCULATION MANUAL AP 078-003 39 10 Reference Use Page 138 of 168 93 in O ATTACHMENT A (Page 133 of 163) l 0FFSITE DOSE CALCULATION MANUAL l

.0 l

.0 TABLE A.5-8 (cont'd) l D GRASS-COW-MILK PATHWAY EACTOR I i\

8 M MREM /YR PER pCI/SEC CHILD (RI FACTORS) 0 (J NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI l

\

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 4.28E 03 0.00E-01 1.65E 03 0.00E-01 1.08E 04 0.00E-01 1.11E 05 Id RU 105 3.83E-03 0.00E-01 1.39E-03 0.00E-01 3.36E-02 0.00E-01 2.50E 00 l RU 106 9.24E 04 0.00E-01 1.15E 04 0.00E-01 1.25E 05 0.00E-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 TE 127M 2.08E 08 5.60E 07 2.47E 07 4.97E 07 5.93E 08 0.00E-01 1.68E 08 TE 127 2.98E 03 8.03E 02 6.39E 02 2.06E 03 8.47E 03 0.00E-01 1.16E 05 TE 129M 2.71E 08 7.58E 07 4.21E 07 8.7$E 07 7.97E 08 0.00E-01 3.31E 08 TE .129 1.29E-09 3.60E-10 3.06E-10 9.21E-10 3.78E-09 0.00E-01 8.03E-08 TE 131M 1.60E 06 5.53E 05 5.89E 05 1.14E 06 5.36E 06 0.00E-01 2.24E 07 TE 131 1.64E-32 5.01E-33 4.89E-33 1.26E-32 4.97E-32 0.00E-01 8.64E-32 TE 132 1.02E 07 4.54E 06 5.48E 06 6.61E 06 4.21E 07 0.00E-01 4.57E 07 I 130 1.73E 06 3.49E 06 1.80E 06 3.85E 08 5.225 06 0.00E-01 1.63E 06 I 131 1.30E 09 1.31E 09 7.45E 08 4.33E 11 2.15E 09 0.00E-01 1.17E 08 I 132 6.91E-01 1.27E 00 5.84E-01 5.89E 01 1.94E 00 0.00E-01 1.49E 00 I 133 1.72E 07 2.12E 07 8.04E 06 3.95E 09 3.54E 07 0.00E-01 8.56E 06 I 134 8.55E-12 1.59E-11 7.31E-12 3.65E-10 2.43E-11 0.00E-01 1.05E-11 I 135 5.41E 04 9.73E 04 4.60E 04 8.62E 06 1.49E 05 0.00E-01 7.41E 04 i 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 1.78E 09 0.00E-01 1.47E 09 2.19E 08 9.69E 07 l 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 BA 139 2.07E-07 1.11E-10 6.01E-09 0.00E-01 9.67E-11 6.51E-11 1.20E-05 BA 140 1.17E 08 1.03E 05 6.84E 06 0.00E-01 3.34E 04 6.12E 04 5.94E 07 BA 141 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 1 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 1.94E 01 6.80E 00 2.29E 00 0.00E-01 0.00E-01 0.00E-01 1.89E 05 LA 142 4.09E-11 1.30E-11 4.08E-12 0.00E-01 0.00E-01 0.00E-01 2.58E-06 CE 141 2.19E 04 1.09E 04 1.62E 03 0.00E-01 4.78E 03 0.00E-01 1.36E 07 CE 143 1.88E 02 1.02E 05 1.47E 01 0.00E-01 4.27E 01 0.00E-01 1.49E 06 CE 144 1.62E 06 5.09E 05 8.66E 04 0.00E-01 2.82E 05 0.00E-01 1.33E 08 PR 143 7.18E 02 2.16E 02 3.56E 01 0.00E-01 1.17E 02 0.00E-01 7.75E 05 PR 144 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 NO 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 NP 239 1.72E 01 1.24E 00 8.70E-01 0.00E-01 3.58E 00 0.00E-01 9.1CE 04

3 i

CYrrent Ospy Proced:re 99-0412 09i07i01 j i

.D Revision: 2 OFFSITE DOSE CALCULATION MANUAL

.) AP 078-003 !

\

@ Reference Use p Page 139 of 168 0 ATTACHMENT A (Page 134 of 163) 0FFSITE DOSE CALCULATION MANUAL

.0 1

..D TAaI2 A.5-9 0 GRASS-COW-MILK PATHWAY FACTOR M* MREM /YR PER pCI/SEC D INFANT (RI FACTORS)

W NUCLIDE BONE LIVER T BODY 1rtsROIC KIDNEY LUNG GI-LLI

\

O 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 5.005 08 5.00E 08 5.00E 08 5.00E 08 5.00E 08 5.00E 08 U NA 24 1.54E 07' 1.54E 07 1.54E 07 1.54E 07 1.54E 07 1.54E 07 1.54E 07 l

P 32 1.60E 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 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 rt 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 HI 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 zN 65 5.55E 09 1.90E 10 8.79E 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 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 2.23E 10 1.10E 10 0.00E-01 0.00E-01 0.00E-01 5.70E 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 '

i SR 89 1.26E 10 0.00E-01 3.61E 08 0.00E-01 0.00E-01 0.00E-01 2.59E 08

,y 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 0.00E-01 9.39E 05 Y 91M 5.72t-19 0.00E-01 1.95E-20 0.00E-01 0.00E-01 0.00E-01 1.91E-15 Y 91 7.33L 04 0.00E-01 1.95E 03 0.00E-01 0.00E-01 0.00E-01 5.25E 06 Y 92 5.39F-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 1.19E 03 0.00E-01 8.26E 05 ZR 97 4.06E 00 6.98E-01 3.19E-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.'1E 08 0.00E-01 6.85E 07 TC 99H 2.15E 01 5.68E 01 7.31E 02 0.00E-01 6.1.? 02 2.9?E 01 1.65E 04 4__

o CIrrent copy Proc dire 99-0412 09:07101 l

1 1

Revision: 2 0FFSITE DOSE CALCULATION MANUAL AP 07B-003 10 Reference Use Page 140 of 168 93 7n O ATTACHMENT A I (Page 135 of 163) i 0FFSITE DOSE CALCULATION MANUAL D

A TABLE A.5-9 (cont' d) j) GRASS-COW-MILK PATHWAY FACTOR i .M 8 MREM /YR PER pCI/SEC .

) INFANT (RI FACTORS) l LM NUCLIDE BONE LIVER T BODY TGYROID KIDNEY LUNG GI-LLI

\

g) 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 8.67E 03 0.00E-01 2.90E 03 0.00E-01 1.80E 04 0.00E-01 1.05E 05 Id RU 105 8.07E-03 0.00E-01 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 0.00E-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 0.00E-01 0.00E-01 1.18E 07 TE 127M 4.21E 08 1.40E 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 129H 5.57E 08 1.91E 08 8.58E 07 2.14E 08 1.39E 09 0.00E-01 3.33E 08 n'

TE 129 2.74E-09 9.43E-10 6.39E-09 2,29E-08 6.81E-08 0.00E-01 2.19E-07 TE 131M 3.38E 06 1.36E 06 1.12E 06 2.76E 06 9.36E 06 0.00E-01 2.29E 07 TE 131 3.49E-32 1.29E-32 9.78E-32 3.11E-31 8.91E-31 0.00E-01 1.41E-30 TE 132 2.11E 07 1.05E 07 9.75E 06 1.54E 07 6.53E 07 0.00E-01 3.87E 07 I 130 3.55E 06 7.81E 06 3.14E 06 8.76E OB 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 1.43E 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 9.47E-09 4.06E-10 0.00t-01 3.16E-11 I 135 1.12E 05 2.24E 05 8.15E 04 2.00E 07 2.49E 05 0.00E-01 8.09E 04 CS 134 3.65E 10 6.80E 10 6.87E 09 0.00E-01 1.75E 10 6.21E 09 1.85E 08 CS 136 1.96E 09 5.16E 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-01 1.62E 10 6.55E 09 1.88E 08 CS 138 0.50E-23 1.38E-22 6.70E-22 0.00E-01 6.89E-22 1.08E-23 2.21E-22 BA 139 4.41E-07 2.93E-10 1.28E-07 0.00E-01 1.76E-09 1.77E-10 2.80E-05 BA 140 2.41E 08 2.41E 08 1.24E 07 0.00E-01 5.72E 04 1.48E 05 5.92E 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 4.06E 01 1.60E 01 4.12E 00 0.00E-01 0.00E-01 0.00E-01 1.88E 05 LA 142 8.59E-11 3.15E-11 7.55E-11 0.00E-01 0.00E-01 0.00E-01 5.36E-06 CE 141 4.34E 04 2.64E 04 3.11E 03 0.00E-01 8.16E 03 0.00E-01 1.37E 07 CE 143 3.97E 02 2.63E 05 3.00E 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 3.15E 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 PR 144 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 NO 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

Gctreit Copy Pro 2cd:re 99 04-12 09.07iO1 3 Revision: 2 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 f Reference Use Page 141 of 168

.A \

Ul p ATTACHMENT A (Page 136 of 163) l 0FFSITE DOSE CALCULATION MANUAL l

,0 0 TAaLa A.5-10 g GRASS-COW-MEAT PATHWAY FACTOR M' MREM /YR PER p0I/SEC ADULT (RI FACTORS)

C (d NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI O

H 3 0.00E-01 3.2SE 02 3.25E 02 3.25E 02 3.25E 02 3.25E 02 3.25E 02 C 14 2.41E 08 4.83E 07 4.83E07 4.83E 07 4.83E 07 4.83E 07 4.83E 07 M NA 24 1.36E-03 1.36E-03 1.36E-03 1.36E-03 1.36E-03 1.36E-03 1.36E-03 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 7.0$E 03 4.21E 03 1.55E 03 9.35E 03 1.77E 06

>N 54 0.00E-01 9.18E 06 1.75E 06 0.00E-01 2.73E 06 0.00E-01 2.81E 07 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 03 4.72E 07 0.00E-01 0.00E-01 1.135 08 1.16E 08 FE 59 2.65E OB 6.24E 09 2.39r, 08 0.00E-01 0.00E-01 1.74E 08 2.08E 09 CO 58 0.00E-01 1.82E 07 4.09E 07 0.00E-01 0.00E-01 0.00E-01 3.70E 08 CO 60 0.00E-01 7.52E 07 1.66E 08 0.00E-01 0.00E-01 0.00E-01 1.41E 09 NI 63 1.89E 10 1.32E 03 6.33E OB 0.00E-01 0.00E-01 0.00E-01 2.73E 08 NI 65 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-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 7.57E 08 0.00E-01 7.13E 08 ZN 69 0.00E-01 0.00E-01 0.00E-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 0.00E-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 4.87E 08 2.27E 08 0.00E-01 0.00E-01 0.00E-01 9.61E 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 3.02E 08 0.00E-01 8.66E 06 0.00E-01 0.00E-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 3.59E 08 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 0.00E-01 0.00E-01 0.00E-01 1.13E 06 Y 91M 0.00E-01 0.00E-01 0.00E-91 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 0.00E-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 2.09E-07 ZR 95 1.87E 06 6.01E 05 4.07E 05 0.00E-01 9.43E 05 0.00E-01 1.90E 09 ZR 97 2.08E-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 HO 99 0.00E-01 9.99E 04 1.90E 04 0.00E-01 2.26E 05 0.00E-01 2.32E 05 TC 99M 4.50E-21 1.27E-20 1.62E-10 0.00E-01 1.93E-19 6.23E-21 7.53E-18 TC 101 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.005-01 0.00E-01 0.00E-01

C:rre;t C1py Proc: dire 99 0412 09:07iO1 U Revision: 2 OFFSITE DOSE CALCULATION MANUAL AP 07B-003

..I M Reference Use 0 Page 142 of 168 M i p ATTACHMENT A (Page 137 of 163) 4 OFFSITE DOSE CALCULATION MANUAL l

..o j

,D TABLE A.5-10 (cont'd) i

..o GRASS-COW-MEAT PATHWAY FACTOR q M3 MREM /YR PER pCI/SEC

\ .

ADULT (RI FACTORS) i W NUCLIDE DONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI

\

O RU 103 1.05E 08 0.00E-01 4.53E 07 !

0.00E-01 4.01E 08 0.00E-01 1.23E 10 ~

g RU 105 5.87E-28 0.00E-01 2.32E-20 0.00E-01 7.58E-27 0.00E-01 3.59E-25 i

RU 106 2.80E 09 0.00E-01 3.54E 08 0.00E-01 5.40E 09 0.00E-01 1.81E 11 AG 110M 6.68E 06 6.18E 06 3.67E 06 0.00E-01 1.22E 07 0.00E-01 2.52E 09 l TE 125M 3.59E 08 1.30E 08 4.81E 07 1.00E 08 1.46E 09 0.00E-01 1.43E 09 4 i

TE 127M 1. lie 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 0.00E-01 5.71E 09 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 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 U.'0E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 TE 132 1.42E 06 9.19E 05 8.63E 05 1.01E 06 8.85E 06 J.00E-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 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 3.67E-01 6.3BE-01 1.94E-01 9.3?E 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 7.73E-15 1.88E-16 0.00E-01 1.32E-16 CS 134 6.58E 08 1.56E 09 1.20E 09 0.00E-01 5.06E 08 1.68E 08 2.74E 07 CS 136 1.18E 07 4.66E 07 3.35E 07 0.00E-01 2.59E 07 3.55E 06 5.24E 06 CS 137 8.72E 08 1.19E 09 7.81E 08 0.00E-01 4.05E 08 1.35E 08 2.31E 07 CS 130 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 2.87E 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 0.00E-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 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 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 6.095 05 9.83E 04 0.00E-01 3.61E 05 0.00E-01 4.93E 08 PR 143 2.10E 04 8.41E 03 1.04E 03 0.00E-01 4.86E 03 0.00E-01 9.19E 07 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 7.17E 03 8.29E 03 4.968 02 0.00E-01 4.84E 03 0.00E-01 3.98E 07 W 187 2.17E-02 1.81E-02 6.33E-03 0.00E-01 0.00E-01 0.00E-01 5.93E 00 NP 239 2.59E-01 2.55E-02 1.40E-02 0.00E-01 7.94E-02 0.00E-01 5.22E 03

T C1rreit 01py Proc d!re 99 0412 09:07:01 M Revision: 2 OFFSITE DOSE CALCULATION MANUAL AP 078-003 3

D Reference Use p Page 143 of 168

'M O- ATTACHMENT A (Page 138 of 163) 0FFSITE DOSE CALCULATION MANUAL D

0 TAa!.s A.5-11

,,g GRASS-COW-MEAT PATHWAY FACTOR a

g M MREM /YR PER pCI/SEC TEEN (RI FACTORS)

O W NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI U

H 3 'O.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 4.08E 07 4.08E 07 4.00E 07 4.08E 07 4.08E 07 4.08E 07 N NA 24 1.09E-03 '1.09E-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 0.00E-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 1.39E 06 0.00E-01 2.09E 06 0.00E-01 1.44E 07 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 2.30E 08 1.69E 08 3.93E 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 0.00E-01 0.00E-01 0.00E-01 CU 64 0.00E-01 2.23E-07 1.05E-07 0.00E-01 5.64E-07 0.00E-01 1.73E-05 ZN 65 2.50E 08 8.69E 08 4.05E 08 0.00E-01 5.56E 08 0.00E-01 3.68E 08 0.00E-01 I ZN 69 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 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 i 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 4.07E 08 1.91E 08 0.00E-01 0.00E-01 0.00E-01 6.02E 07 RB BS 0.00E-01 0.00E-01 0.00E 0.00E-01 0.00E-01 0.00E-01 0.00E-01 l

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 2.55E 08 0.00E-01 7.29E 06 0.00E-01 0.00E-01 0.00E-01 3.03E 07 j SR 90 8.05E 09 0.00E-01 1.99E 09 0.00E-01 0.00E-01 0.00E-01 2.26E 08 :

I 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 0.00E-01 Y 91 9.54E 05 0.00E-01 2.56E 04 0.00E-01 0.00E-01 0.00E-01 3.91E 08 Y 92 0.00E-01 0.00E-01 0.00E-01 0.0CE-01 0.00E-01 0.00E-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 ZR 95 1.50E 06 4.73E 05 3.26r. 05 0.00E-01 6.96E 05 0.00E-01 1.09E 09 2R 97 1.73E-05 3.42E-06 1.58E-06 0.00E-01 5.19E-06 0.00E-01 9.27E-01 i

i 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 1.58E 04 0.00E-01 1.89E 05 0.00E-01 1.48E 05 TC 99M 3.58E-21' 9.975 1.29E-19 0.00E-01 1.49E-19 5.54E-21 6.55E-18 -

I l

4 j 1

)

f i

I

C"rrelt C:py Proc:d:re 99 0412 09:07.01 f

.,I Revision: 2 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 N Reference Use Page 144 of 168 ja Vi p ATTACHMENT A (Page 139 of 163)

0 TABLE A.5-11 (cont'd) 0 GRASS-COW-MEAT PATHWAY FACTOR M2 MREM /YR PER pCI/SEC

]\ TEEN (RI FACTORS)

O bJ NUCLIDE BONE LIVER 7 BODY THYROID KIDNEY LUNG GI-LLI

\

O 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 8.56E 07 0.00E-01 3.66E 07 0.00E-01 3.02E 08 0.00E-01 7.15E 09 N RU 105 4.91E-28 0.00E-01 1.91E-28 0.00E-01 6.91E-27 0.00E-01 3.96E-25 RU 106 2.36E 09 0.00E-01 2.97E 08 0.00E-01 4.55E 09 0.00E-01 1.13E 11 AG 110M 5.06E 06 4.79E 06 2.91E 06 0.00E-01 9.13E 06 0.00E-01 1.35E 09 TE 125M 3.03E 08 1.09E 08 4.05E 07 8.47E 07 0.00E-01 0.00E-01 8.94E 08 TE 127M 9.42E 08 3.34E 08 1.12E 08 2.24E 08 3.82E 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 TE 129M 9.50E 00 3.53E 08 1.50E 08 3.07E 08 3.97E 09 0.00E-01 3.57E 09 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 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 TE 132 1.16E 06 7.36E 05 6.93E 05 7.76E 05 7.06E 06 0.00E-01 2.33E 07 I 130 1.71E-06 4.94E-06 1.97E-06 4.03E-04 7.61E-06 0.00E-01 3.80E-06 I 131 8.93E 06 1.25E 07 6.72E 06 3.65E 09 2.15E 07 0.00E-01 2.47E 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 3.07E-01 5.20E-01 1.59E-01 7.26E 01 9.12E-01 0.00E-01 3.93E-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 3.64E-17 9.37E-17 3.47E-17 6.03E-15 1.48E-16 0.00E-01 1.04E-16 CS 134 5.23E OB 1.23E 09 5.71E 08 0.00E-01 3.91E 08 1.49E 08 1.53E 07 CS 136 9.20E 06 3.62E 07 2.43E 07 0.00E-01 1.97E 07 3.112 06 2.91E 06 CS 137 7.24E 08 9.63E 08 3.36E 08 0.00E-01 3.28E 08 1.27E 08 1.37E 07 CS 130 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 0.0CE-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 3 BA 142 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 J 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 9.05E 02 0.0CE-01 3.71E 03 0.00E-01 2.25E 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 7.0$E 03 8.78E 02 0.00E-01 4.10E 03 0.00E-01 5.81E 07 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 6.32E 03 6.87E 03 4.11E 02 0.00E-01 4.03E 03 0.00E-01 2.48E 07 W 187 1.81E-02 1.48E-02 5.16E-03 0.00E-01 0.00E-01 0.0cE-01 4.00E 00 NP 239 2.26E-01 2.13E-02 1.19E-02 0.00E-01 6.70E-07 0.00E-01 3.43E 03

C rre;t O!py Proc: dure 99 0412 09:07;01 D Revision: 2 OFFSITE DOSE CALCULATION MANUAL 3 AP 0~1B-003 O

p Reference Use Page 145 of 168 M

O ATTACHMENT A (Page 140 of 163)

~

.0

.D TABLE A.5-12

.,0 GRASS-COW-MEAT PATHWAY FACTOR

(

g 8

M MREM /YR PER pCI/SEC CHILD (RI FACTORS)

W NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUriG GI-LLI j

\ !

O H 3 0.00E-01 2.34E 02 2.34E 02 2.34E 02 2.34E 02 2.34E 02 2.34E 02 l C 14 3.83E 08 7.67E 07 7.67E 07 7.67E 07 7.67E 07 7.67E 07 7.67E 07 N NA 24 1.73E-03 1.73E-03 1.73E-03 1.73E-03 1.73E-03 1.73E-03 1.73E-03 l

{

P 32 7.41E 09 3.47E 08 2.86E 08 0.00E-01 0.00E-01 0.00E-01 2.05E 08 CR 51 0.00E-01 0.00E-01 8.79E 03 4.8BE 03 1.33E 03 8.91E 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 MN 56 0.00E-01 1.63E-53 3.67E-54 0.00E-01 1.97E-53 0.00E-01 2.36E-51 i FE 55 4.57E 08 2.42E 08 7.50E 07 0.00E-01 0.00E-C1 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 CO 58 0.00E-01 1.64E 07 5.03E 07 0.00E-01 0.00E-01 0.00E-01 9.58E 07 CO 60 0.00E-01 6.93E 07 2.04E 08 0.00E-01 0.00E-01 0.00E-01 3.84E 08 NI 63 2.91E 10 1.56E 09 9.91E 08 0.00E-01 0.00E-01 0.00E-01 1.05E 08 NI 65 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 CU 64 0.00E-01 3.00E-07 1.81E-07 0.00E-01 7.24E-07 0.00E-01 1.41E-05 ZN 65 3.75E 08 1.00E 09 6.22E 08 0.00E-01 6.30E OB 0.00E-01 1.76E 08 ZN 69 0.00E-01 0.00E-01 0.00E-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 0.00E-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 5.77E 08 3.55E 08 0.00E-01 0.00E-01 0.00E-01 3.71E 01 i RB 88 0.00E-01 0.00E-01 0.00E-01 0.0CE-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 4.82E 08 0.00E-01 l'.38E 07 0.00E-01 0.00E-01 0.00E-01 1.87E 07 i SR 90 1.04E 10 0.00E-01 2.64E 09 0.00E-01 0.00E-01 0.00E-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 0.00E-01 Y 90 1.70E 02 0.00E-01 4.55E 00 0.00E-01 0.00E-01 0.00E-01 4.84E 05 Y 91H 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 0.00E-01 2.40E 08 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 2R 95 2.66E 06 5.86E 05 5.21E 05 0.00E-01 8.30E 05 0.00E-01 6.11E 08 t 2R 97 3.22E-05 4.65E-06 2.74E-06 0.00E-01 6.68E-06 0.00E-01 7.05E-01 i l

NB 95 3.10E 06 1.21E 06 8.63E 05 0.00E-01 1.13E 06 0.00E-01 2.23E 09 MO 99 0.00E-01 1.15E 05 2.84E 04 0.00E-01 2.45E 05 0.00E-01 9.51E 04 6.27E-21 1.23E-20 l TC 99M 2.04E-19 0 ,00E-01 1.79E-19 6.24E-21 7.00E-18 :

}

1 f

CZrre:t Orpy Proc: dire 99-04 12 09:.07.01 1

d Revision: 2 3 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 i

D Reference Use Page 146 of 168 i D

M l c ATTACHMENT A I (Page 141 of 163) ,

0FFSITE DOSE CALCULATION MANUAL i

.0

.0 TABLE A.5-12 (cont'd) I 0 GRASS-COW-MEAT PATHWAY FACTCR I g M' MREM /YR PER pCI/SEC Ci!ILD (RI FACTORS)

D l

14 NUCLTDE BONE LIVER T BODY THYROID KIONEY LUNG GI-LLI

\

O TC 101 0.0CE-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 i RU 103 1.55E 08 0.00E-01 5.95E 07 0.00E-01 3.90E 08 0.00E-01 4.00E 09 !

IJ RU 105 9.16E-28 0.00E-01 3.32E-28 0.00E-01 8.05E-27 0.00E-01 5.98E-25 ,

i RU 106 4.44E 09 0.00E-01 5.54E 08 0.00E-01 5.99E 09 0.00E-01 6.90E 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 5.69E 08 1.54E 09 7.59E 07 1.60E 08 0.00E-01 0.00E-01 5.49E 08 i i

TE 127M 1.77E 09 4.78E 08 2.11E 08 4.24E OG 5.06E 09 0.00E-01 1.44E 09 TE 127 3.41E-10 9.20E-11 7.32E-11 2.36E-10 9.71E-10 0.00E-01 1.33E-08 TE 129M 1.79E 09 5.00E 09 2.78E 08 5.77E 08 5.26E 09 0.00E-01 2.18E 09 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 4.99E 02 2.35E 03 0.00E-01 9.84E 03 TE 131 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-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 6.17E-06 3.18E-06 6.80E-04 9.22E-06 0.00E-01 2.89E-06 j I 131 1.66E 07 1.67E 07 9.47E 06 5.53E 09 2.74E 07 0.00E-01 1.48E 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 5.70E-01 7.04E-01 2.66E-01 1.31E 02 1.17E 00 0.00E-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 1.82E-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 2.32E 07 3.46E 06 1.53E 06 !

CS 137 1.33E 09 1.28E 09 1.88E 08 0.00E-01 4.16E 08 1.50E 08 7.99E 06 CS 130 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 4.39E 07 3.84E 04 2.56E 06 0.00E-01 1.25E 04 2.29E 04 2.22E 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 0.00E-01 0.00E-01 0.00E-01 LA 140 5.66E-02 1.98E-02 6.66E-03 0.00E-01 0.00E-01 0.00E-01 5.51E 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 2.22E 04 1.11E 04 1.64E 03 0.00E-01 4.86E 03 0.00E-01 1.38E 07 CE 143 3.18E-02 1.72E 01 2.50E-03 0.00E-01 7.23E-03 0.00E-01 2.52E 02 CE 144 2.32E 06 7.26E 05 1.24E 05 0.00E-01 4.02E 05 0.005-01 1.89E 08 PR 143 3.34E 04 1.00E 04 1.66E 03 0.00E-01 5.43E 03 0.00E-01 3.60E 07 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 1.19E 04 9.60E 03 7.43E 02 0.00E-01 5.27E 03 0.00E-01 1.52E 07 W 187 3.36E-02 1.99E-02 8.94E-03 0.00E-01 0.00E-01 0.00E-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

Curext CCpy PrecedIre 99 0412 09:07i01 f Revision: 2 0FFSITE DOSE CALCULATION MANUAL AP 07B-003 3

3 Reference Use Page 147 of 168 D

U ATTACHMENT A (Page 142 of 163) i OFFSITE DOSE CALCULATION MANUAL l D l

.0 TAat.s A.5-13

.0 VEGETATION PATHWAY FACTOR

, M' MREM /YR PER pCI/SEC ADULT (RI FACTORS) 14 NUCLIDE BONE LIVER T BODY THYROID KIDNEY LONG GI-LLI

\

g H 3 0.00E-01 2.26E 03 2.26E 03 2.26E 03 2.26E 03 2.26E 03 2.26E 03 C 14 2.38E 08 4.55E 07 4.55E 07 4.55E 07 4.55E 07 4.55E 07 4.55E 07 N NA 24 2.69E 05 2.69E 05 2.69E 05 2.69E 05 2.69E 05 2.69E 05 2.69E 05 P 32 1.40E 09 8.73E 07 5.42E 07 0.00E-01 0.00E-01 0.00E-01 1.58E 08 CR 51 0.00E-01 0.00E-01 4.64E 04 2.7BE 04 1.02E 04 6.16E 04 1.17E 07 HN 54 0.00E-01 3.13E 08 5.97E 07 0.00E-01 9.31E 07 0.00E-01 9.58E 08 MN 56 0.00E-01 1.59E 01 2.82E 00 0.00E-01 2.02E 01 0.00E-01 5.08E 02 rE $5 2.09E 08 1.45E 08 3.37E 07 0.00E-01 0.005-01 8.06E 07 8.29E 07 PE 59 1.26E 08 2.96E 08 1.14E 08 0.00E-01 0.00E-01 8.28E 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 3.49E 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 CU 64 0.00E-01 9.21E 03 4.32E 03 0.00E-01 2.32E 04 0.00E-01 7.85E 05 ZN 65 3.17E 08 1.01E 09 4.56E 08 0.00E-01 6.75E 08 0.00E 6.36E 08 ZN 69 8.77E-06 1.68E-05 1.17E-06 0.00E-01 1.09E-05 0.00E-01 2.52E-06 BR 83 0.00E-01 0.00E-01 3.11E 00 0.00E-01 0.00E-01 0.00E-01 4.4BE 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 1.84E-22 0.00E-01 0. 0_0 E-01 0.00E-01 0.00E-01 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 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 8.46E 04 Y 90 1.33E 04 0.00E-01 3.56E 02 0.00E-01 0.00E-01 0.00E-01 1.41E 08 Y 91M' 5.24E-09 0.00E-01 2.03E-10 0.00E-01 0.00E-01 0.00E-01 1.54E-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 0.00E-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 2R 95 1.18E 06 3.77E 05 2.55E 05 0.00E-01 5.92E 05 0.00E-01 1.20E 09 2R 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 03 7.93E 04 4.26E 04 0.00E-01 7.84E 04 0.00E-01 4.81E 08 MO 99 0.00E-01 6.15E 06 1.17E 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

r Czrrent Copy Proc: dire 99 04 12 09.07101 Revision: 2 OFFSITE DOSE CALCULATION MANUAL AP 078-003

Reference Use p Page 148 of 168 m

CI ATTACHMENT A (Page 143 of 163)

~

D TABLE A.5-13 (cont'd)

,,0 VEGETATION PATHWAY FACTOR g M' MREM /YR PER pCI/SEC ADULT (RI FACTORS)

Q.

bJ NOCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI

\

g TC 101 8.34E-31 1.20E-30 1.18E-29 0.00E-01 2.16E-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 N RU 105 5.39E 01 0.00E-01 2.13E 01 0.00E-01 6.97E 02 0.00E-01 3.30E 04 RU 106 1.93E 08 0.00E-01 2.44E 07 0.00E-01 3.72E 08 0.00E-01 1.25E 10 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 0.00E-01 3.86E 08 TE 127M 3.49E 08 1.25E 08 4.26E 07 8.93E 07 1.42E 09 0.00E-01 1.17E 09 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 9.30E 07 3.98E-07 8.63E 07 1.05E 09 0.00E-01 1.27E 09 TE 129 7.65E-04 2.87E-04 1.86E-04 5.87E-04 3.22E-03 0.00E-01 5.77E-04 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 2.78E 06 2.61E 06 3.07E 06 2.68E 07 0.00E-01 1.32E 08 I 130 3.95E 05 1.16E 06 4.57E 05 9.81E 07 1.81E 06 0.00E-01 9.97E 05 I 131 8.08E 07 1.16E 08 6.62E 07 3.79E 10 1.98E 08 0.00E-01 3.05E 07 I 132 5.77E 01 1.54E 02 5.40E 01 5.40E 03 2.46E 02 0.00E-01 2.90E 01 I 133 2.09E 06 3.63E 06 1.11E 06 5.33E 00 6.33E 06 0.00E-01 3.26E 06 I 134 9.E9E-05 2.63E-04 9.42E-05 4.56E-03 4.19E-04 0.00E-01 2.30E-07 I 135 3.90E 04 1.02E 05 3.77E 04 6.74E 06 1.64E 05 0.00E-01 1.15E 05 CS 134 4.67E 09 1.11E 10 9.00E 09 0.00E-01 3.59E 09 1.19E 09 1.9 'l CS 136 4.20E 07 1.66E OB 1.19E 08 0.00E-01 9.22E 07 1.26E 07 1.88 s1 CS 137 6.36E 09 8.70E 09 5.70E 09 0.00E-01 2.95E 09 9.81E 08 1.68E 08 CS 138 3.94E-11 7.78E-11 3.86E-11 0.00E-01 5.72E-11 5.65E-12 3.32E-16 BA 139 2.90E-02 2.07E-05 8.50E-04 0.00E-01 1.93E-05 1.17E-05 5.15E-02 BA 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 5.47E-25 6.01E-31 BA 142 0.00E-01 3.00E-01 0.00E-0' O.00E-01 0.00E-01 0.00E-01 0.00E-01 LA 140 1.98E 03 9.99E 02 2.64E 02 0.00E-01 0.00E-01 0.00E-01 7.33E 07 LA 142 1.42E-04 6.44E-05 1.61E-05 0.00E-01 0.00E-01 0.00E-01 4.70E-01 CE 141 1.97E 05 1.33E 05 1.51E 04 0.00E-01 6.19E 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 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 0.00E-01 7.32E-27 0.00E-01 0.00E-01 NO 147 3.36E 04 3.89E 04 2.32E 03 0.00E-01 2.27E 04 0.00E-01 1.87E 08 W 187 3.82E 04 3.20E 04 1.12E 04 0.00E-01 0.00E-01 0.00E-01 1.05E 07 NP 239 1.43E 03 1.40E 02 7.74E 01 0.00E-01 4.30E 02 0.00E-01 2.88E 07

CC:rrelt 02py Proc fyre 99 0412 09:07101 Revision: 2 OFFSITE DOSE CALCULATION MANUAL AP 078-003 O

O Reference Use Page 149 of 168 Fl O ATTACHMENT A (Page 144 of 163) 0FFSITE DOSE CALCULATION MANUAL

..D

.0 TABIA A.5-14

.,g VEGETATION PATHWAY FACTOR 8

g M MREM /YR PER pCI/SEC g TEEN (RI FACTORS) i (Q NUCLIDE BCNE LIVER T BODY THYROID KIDNEY LUNG GI-LLI

\

O H 3 0.00E-01 2.59E 03 2.59E 03 2.59E 03 2.59E 03 2.59E 03 2.59E 03 C 14 3.69E 08 7.38E 07 7.38E 07 7.38E 07 7.38E 07 7.38E 07 7.38E 07 N NA 24 2.39E 05 2.39E 05 2.39E 05 2.39E 05 2.39E 05 2.39E 05 2.39E 05 P 32 1.61E 09 9.96E 07 6.23E 07 0.00E-01 0.00E-01 0.00E-01 1.35E 08 CR 51 0.00E-01 0.00E-01 6.17E 04 3.43E 04 1.35E 04 8.81E 04 1.04E 07 HN 54 0.00E-01 4.54E 09 9.01E 07 0.00E-01 1.36E 08 0.00E-01 9.32E 08 MN 56 0.00E-01 1.44E 01 2.55E 00 0.00E-01 1.82E 01 0.005-01 9.45E 02 FE 55 3.2bE 08 2.31E 08 5.38E 07 0.00E-01 0.00E-01 1.46E 08 9.98E 07 FE 59 1.19E 08 4.18E 08 1.62E 08 0.00E-01 0.00E-01 1.32E 08 9.90E 08 CO 58 0.00E-01 4.36E 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 0.00E-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 6.45E 01 8.24E 00 3.76E 00 0.00E-01 0.00E-01 0.00E-01 4.47E 02 CU 64 0.00E-01 8.34E 03 3.92E 03 0.00E-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 ZN 69 8.21E-06 1.56E 05 1.10E-06 0.0CE-01 1.02E-05 0.00E-01 2.88E-05 BR 83 0.00E-01 0.00E-01 2.92E 00 0.0CE-01 0.00E-01 0.00E-01 5.08E-16 BR 84 0.00E-01 0.00E-01 2.27E-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 0.00E-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 01 RB 88 0.00E-01 3.21E-22 1.71E-22 0.00E-01 0.00E-01 0.00E-01 2.75E-29 RB 89 0.00E-01 1.26E-26 8.94E-27 0.0CE-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 0.00E-01 0.00E-01 2.11E 10 SR 91 2.83E 05 0.00E-01 1.13E 04 0.00E-01 0.00E-01 0.00E-01 1.28E 06 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 0.00E-01 0.00E-01 1.02E 08 Y 91H 4.08E-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 0.00E-01 0.00E-01 3.21E 09 Y 92 8.61E-01 0.00E-01 2.49E-02 0.00E-01 0.00E-01 0.00E-01 2.36E 04 Y 93 1.63E 02 0.00E-01 4.47E 00 0.00E-01 0.00E-01 0.002-01 4.99E 06 ,

ZR 95 1.72E 06 5.44E 05 3.74E 05 0.00E-01 7.99E 05 0.00E-01 1.25E 09 2R 97 3.12E 02 6.18E 01 2.85E 01 0.00E-01 9.37E 01 0.00E-01 1.67E 07 NB 95 1.93E 05 1.07E 05 5.88E 04 0.00E-01 1.04E 05 0.00E-01 4.57E 08 Ho 99 0.00E-01 5.65E 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 0.00E-01 1.14E 02 4.24E 00 5.02E 03 l

7:

Carrent Copy ProcedIro 99 0412 09:07:01

'M -

,~,1 Revision: 2' 0FFSITE DOSE CALCULATION MANUAL AP 07B-003

. Reference Use. Page 150 of 168 M

P ATTACHMENT A (Page 145 of 163)

~

.D '

O. TABLE A.5-14 (cont' d)

'.0 VEGETATION PATHWAY TACTOR 1( M8 MREN/YR PER pCI/SEC

g. TEEN (RI FACTORS) l W NUCLIDE BONE- LIVER' T BODY THYROID KIDNEY LUNG GI-LLI

\ . i

'g TC 101 7.76E-31 1.10E-30 1.08E-29 0.00E-01 . 2.00E-29 6.72E-31 0.00E-01 N- RU 103- 6.81E 06 0.00E-01 2.91E 06 0.00E-01 2.40E 07 0.00E-01 5.69E 08 RU- 105 '5.01E 01 0.00E-01 1.94E 01 0.00E-01 6.32E 02 0.00E-01 4.04E 04' RU 106- .3.09E 08 0.00E-01 3.90E 07 0.00E-01 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 TE 125M 1.48E 08 5.34E 07 1.98E 07 4.14E 07 0.00E-01 0.00E-01 4.39E 08 .

J TE. 127M 5.52E 08 1.96E 08 6.56E 07 1.31E 08 2.24E 09 0.00E-01 1.37E 09 TE 127 5.34E 03 1.89E 03 1.15E 03 3.68E 03 2.16E 04 0.00E-01 4.12E 05 TE 129M 3.62E 08 1.34E 09 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 4.22E 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 0.00E-01 7.84E 07 I 130 3.51E 05 1.02E 06 4.05E 05- 8.28E 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 0.00E-01 2.13E 07 I 132 5.20E 01 1.36E 02 4.89E 01 4.59E 03 2.14E 02 0.00E-01 5.93E 01 I 133 1.94E 06 3.29E 06 1.00E 06 4.59E 08 5.77E 06 0.00E-01 2.49E 06 I' 134 8.76E-05 2.32E-04 8.34E-05 3.87E-03 3.66E-04 0.00E-01 3.06E-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 CS 136 4.20E 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 CS 138 3.64E-11 6.98E-11 3.49E-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 1.30E 08. 1.69E 05 8.91E 06 0.00E-01 5.74E 04 1.14E 05 2.13E OB 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 0.00E-01 0.00E-01 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 5.7BE-05 1.44E-05 0.00E-01 0.00E-01 0.00E-01 1.76E 00 CE 141 2.83E 05 1.89E 05 2.17E 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 0.00E-01 1.33E 10 PR- 143 7.014 04 2.80E 04 3.49E 03 0.00E-01 1.63E 04 0.00E-01 2.31E 08 PR 144 2.93E-26 1.20E-26 1.49E-27 0.00E-01 6.88E-27 0.00E-01 3.23E-29 NO 147 '3.66E 04 3.98E 04 2.38E 03 0.00E-01 2.34E 04 0.00E-01 1.44E 08 W 187 3.56E 04 2.90E 04 1.02E 04 0.00E-01 0.00E-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

C rrent Ccpy ProcedZre 99-0412 09.07t01 i

f Revision: 2 OFFSITE DOSE CALCULATION MANUAL AP 078-003 J

D Reference Use p Page 151 of 168 m I p ATTACHMENT A I (Page 146 of 163)

OETSITE DOSE CALCULATION MANUAL <

.0 j 0 T m z A.5-15 i VEGETATION PATHWAY TACTOR I

O M2 MREM /YR PER pCI/SEC

\

CHILO (RI FACTORS)

O j y NUCLIDE BONE LIVER T BODY THYROID KIDNEY LONG GI-LLI H 3 0.00E-01 4.01E 03 (.01E 03 4.01E 03 4.01E 03 4.01E 03 4.01E 03 O C 14 8.89E 08 1.78E 08 1.78E 08 1.78E 08 1.78E 08 1.78E 08 1.78E 08 ;

h) _ _ 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 9.30E 07 !

CR 51 0.00E-01 0.00E-01 1.17E 05 6.50E 04 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 5.58E DE MN 56 0.00E-01 1.88E 01 4.24E 00 0.005-01 2.27E 01 0.00E-01 2.72E 03 i FE 55 8.00C 08 4.24E 08 1.31E 08 0.00E-01 0.00E-01 2.40E 08 7.86E 07 i TE 59 3.97E 08 6.43E 08 3.20E 08 0.00E-01 0.00E-01 1.86E 08 6.69E 08 j CO 50 0.00E-01 6.44E 07 1.97E 08 0.00E-01 0.00E-01 0.00E-01 3.76E 08 CO 60 0.00E-01 3.78E 08 1.12E 09 0.00E-01 0.00E-01 0.00E-01 2.10E 09 <

NI 63 3.95E 10 2.11E 09 1.348 09 0.00E-01 0.00E-01 0.00E-01 1.42E 08 I NI 65 1.18E 02 1.11E 01 6.51E 00 0.00E-01 0.00E-01 0.00E-01 1.37E 03 CU 64 0.00E-01 1.10E 04 6.65E 03 0.00E-01 2.66E 04 0.00E-01 5.16E 05 ZN 65 8.12E 08 2.16E 09 1.35E 09 0.00E-01 1.36E 09 0.00E-01 3.80E 08 1 l

ZN 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 5.38E 00 0.00E-01 0.00E-01 0.00E-01 3.14E-17 BR 84 0.00E-01 0.00E-01 3.85E-11 0.00E-01 0.00E-01 0.00E-01 1.94E-28 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 4.52E 08 2.78E 08 0.00E-01 0.00E-01 0.00E-01 2.91E 07 RB 88 0.00E-01 4.43E-22 3.08E-22 0.00E-01 0.00E-01 0.00E-01 2.17E-23 i

RB 89 0.00E-01 1.67E-26 1.4BE-26 0.00E-01 0.00E-01 0.00E-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 1 SR 91 5.21E 05 0.00E-01 1.97E 04 0.00E-01 0.00E-01 0.00E-01 1.15E 06 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 6.56E 07 j 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 1.86E 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 Y 93 3.01E 02 0.00E-01 8.26E 00 0.00E-01 0.00E-01 0.00E-01 4.48E 06 ZR 95 3.86E 06 8.49E 05 1.56E 05 0.00E-01 1.22E 06 0.00E-01 8.85E 08 ZR 97 5.70E 02 8.24E 01 4.86E 01 0.00E-01 1.18E 02 0.00E-01 1.25E 07 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 0.90E-01 1.65E 07 0.00E-01 6.38E 06 TC 99N 4.71E 00 9.24E 00 1.51E 02 0.00E-01 1.34E 02 4.69E 00 5.26E 03

i C rrent Copy Prece41rre 99-0412 09:07i01 l m ;

Revision: ,2 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 j

Reference Use p Page 152 of 168 l 1

m D ATTACHMENT A

-(Page 147 of 163)

~. OFFSITE DOSE CALCULATION MANUAL 0

0 TAats A.5-15 (cont'd)

A VEGETATION PATHWAY FACTOR g Ma MREM /YR PER pCI/SEC

g. CHILD (RI FACTORS)

W NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI A

O TC 101 1.43E-30 1.49E-30 1.89E-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 08 N RU 105 9.17E 01 0.00E-01' 3.33E 01 0.00E-01 8.06E 02 0.00E-01 5.99E 04 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 2.58E 09 TE 125M 3.51E 08 9.50E 07 4.67E 07 9.84E 07- 0.00E-01 0.00E-01 3.38E 08 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 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 2.88E 07 0.00E-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 OS 1.44E 08 8.17E 07 4.76E 10 2.36E 08 0.00E-01 1.28E 07

~I 132 9.23E 01 1.70E 02 7.80E 01 7.87E 03 2.60E 02 0.00E-01 2.00E 02 I 133 3.53E 06 4.37E 06 1.65E 06 8.12E 08 7.20E 06 0.00E-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 135 6.26E 04 1.13E 05 5.33E 04 9.98E 06 1.73E 05 0.00E-01 8.59E 04 CS 134 1.60E 10 2.63E 10 5.55E 09 0.00E-01 0.15E 09 2.93E 09 1.42E 08 CS 136 8.04E 07 2.21E 08 1.43E 08 0.00E-01 1.18E 08 1.76E 07 7.77E 06 CS' 137 2.39E 10 2.29E 10 3.30E 09 0.00E-01 7.46E 09 2.68E 09 1.43E 08 CS 138 6.61E-11 9.20E-11 5.83E-11 0.00E-01 6.47E-11 6.96E-12 4.24E-11 BA 139 5.04E-02 2.69E-05 1.46E-03 0.00E-01 2.35E-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 7.168-23 0.00E-01 1.07E-24 7.248-24 1.25E-21 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. 3.25E 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 4.868 04 0.00E-01 1.43E 05 0.00E-01 4.08E 08 CE 143 1.72E 03 9.31E 05 .1.35E 02 0.00E-01 3.91E 02 0.00E-01 1.36E 07 i CE 144 1.27E 08 3.98E 07 6.78E 06 0.00E-01 2.21E 07~ 0.00E-01 1.04E 10 l 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 0.005-01 3.62E-23 ND - 147 7.24E 04 5.86E 04 4.54E 03' O.00E-01 .3.22E 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 I

Orrrent CCPy Proc:Cro 99 0412 09:07:01

', Revision: 2 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 l

Reference Use Page 153 of 168 l 41 o ATTACHMENT A (Page 148 of 163)

.0

.0 TABLE A.5-16 l D

GROUND PLANE PATHWAY FACTOR

\ 2 M MREM /YR PER pCI/SEC I (RI FACTOR)

\ H-3 0.00E 00 Y-91M 1.00E 05 0 CS-134 6.86E 09 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 4 P-32 0.00E 00 Y-93 1.85E 05 CS-138 3.59E 05 CR-51 4.66E 06 ZR-95 2.45E 08 BA-139 1.06E 05 MN-54 1.39E 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 FE-55 0.00E 00 MO-99 3.99E 06 BA-142 4.49E 04 FE-59 2.73E 08 TC-99M 1.84E 05 LA-140 1.92E 07 TC-101 2.04E 04 CO-58 3.79E 08 RU-103 1.08E 08 LA-142 7.37E 05 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 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 RB-88 3.31E 04 TE-132 4.23E 06 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 Y-90 4.49E 03 I-135 2.53E 06

Otrre t Copy Proc:d:re 99-04-12 09 07:01 U Revision: 2 OFFSITE DOSE CALCULATION MANUAL AP 078-003 1

P Reference Use ja Page 154 of 168 M

U ATTACHMENT A f (Page 149 of 163)

.0 0 TABLE A.5-17

.0 GRASS-GOAT-MILX PATHWAY FACTOR M2 MREM /YR PER pCI/SEC ADULT O

DJ NUCLIDE BONE LIVER T BODY THYROID KIDNEY LONG GI-LLI

\

O 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 N 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 0.00E-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 CO 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 0.0CE-01 1.17E 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 2.66E 03 1.25E 03 0.00E-01 6.70E 03 0.00E-01 2.27E 05 ZN 65 1.65E 08 5.24E 08 2.37E 08 0.00E-01 3.50E 08 0.00E-01 3.30E 08 ZN 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 0.00E-01 0.00E-01 0.00E-01 0.00E-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 0.00E-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 0.00E-01 0.00E-01 0.00E-01 9.00E 04 Y 91M 7.24E-21 0.00E-01 2.00E-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 3.2SE 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 f

l CrrroIt CTpy Proc dzre 99-04-12 09107101 ]

U

..I Revision: 2 OFFSITE DOSE CALCULATION MANUAL AP 078-003 4

g Reference Use Page 155 of 168 I M

V ATTACHMENT A l (Page 150 of 163) 0FFSITE DOSE CALCULATION MANUAL

.0 "

,0 TABLE A.5-17 (cont' d)

,0 GRASS-GOAT-MILK PATHWAY FACTOR g M8 MREM /YR PER pCI/SEC ,

ADU1.T O l W NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI

\

g 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 1.22E 02 0.00E-01 5.26E 01 0.00E-01 4.66E 02 0.00E-01 1.43E 04 N RU 105 1.03E-04 0.00E-01 4.07E-05 0.00E-01 1.33E-03 0.00E-01 6.30E-02 l RU 106 2.45E 03 0.03E-01 3.10E 02 0.00E-01 4.73E 03 0.00E-01 1.58E 05 AG 110M 6.99E 06 6.46E 06 3.84E 06 0.00E-01 1.27E 07 0.00E-01 2.64E 09 TE 125M 1.95E 06 7.00E 05 2.62E 05 5.88E 05 7.95E 06 0.00E-01 7.81E 06 TE 127M 5.49E 06 1.96E 06 6.70E 05 1.40E 06 2.23E 07 0.00E-01 1.84E 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 2.69E 06 1.14E 06 2.48E 06 3.02E 07 0.00E-01 3.64E 07 TE 129 3.41E-11 1.28E-11 8.31E-12 2.62E-11 1.43E-10 0.00E-01 2.57E-11 TE 131H 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 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 1.49E 06 5.87E 05 1.26E 08 2.32E 06 0.00E-01 1.20E 06 1 131 3.55E 08 5.08E 08 2.91E 08 1.67E 11 8.71E 08 0.00E-01 1.34E 08 I 132 1.98E-00 5.29E-00 1.85E-00 1.85E 01 8.43E-00 0.00E-01 9.94E-01 I 133 4.65E 06 0.08E 06 2.46E 06 1.19E 09 1.41E 07 0.00E-01 7.26E 06 I 134 2.44E-12 6.63E-12 2.37E-12 1.15E-10 1.05E-11 0.00E-01 5.78E-15 I 135 1.54E 04 4.04E 04 1.49E 04 2.66E 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 1.83E 08 3.09E 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 CS 138 2.75E-23 5.43E-23 2.69E-23 0.00E-01 3.99E-23 3.94E-24 2.32E-28 BA 139 5.48E-09 3.90E-12 1.60E-10 0.00E-01 3.65E-12 2.21E-12 9.71E-09 BA 140 3.23E 06 4.05E 03 2.11E 05 0.00E-01 1.38E 03 2.32E 03 6.64E 06 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 5.43E-01 2.73E-01 7.23E-02 0.00E-01 0.00E-01 0.00E-01 2.01E 04 LA 142 1.13E-12 5.12E-13 1.28E-13 0.00E-01 0.00E-01 0.00E-01 3.74E-09 CE 141 5.81E 02 3.93E 02 4.46E 01 0.00E-01 1.83E 02 0.00E-01 1.50E 06 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 9.39E-00 0.00E-01 4.39E 00 0.00E-01 8.30E 04 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 7.87E 02 6.58E 02 2.30E 02 0.00E-01 0.00E-01 0.00E-01 2.16E 05 NP 239 4.41E-01 4.33E-02 2.39E-02 0.00E-01 1.35E-01 0.00E-01 8.89E 03

{

C rrett C?py Proc d:re 99 0412 09i07i01

{

l U Revision: 2 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 3 ,

l D Reference Use Page 156 of 168 !

p !

m p ATTACHMENT A (Page 151 of 163)

OFFSITE DOSE CALCULATION MANUAL l 0

.0 TABI.E A.5-18 3 GRASS-GOAT-MILK PATHWAY FACTOR i M8 MREM /YR PER pCI/SEC A

TFEN O

14 NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG G1-LLI

\

O H 3 0.00E-01 2.03E 03 2.03E 03 2.03E 03 2.03E 03 2.03E 03 2.03E 03 C 14 4.86E 08 9.72E 07 9.72E 07 9.72E 07 9.72E 07 9.72E 07 9.72E 07 N NA 24 5.11E 05 5.11E 05 5.11E 05 5.11E 05 5.11E 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 HN 54 0.00E-01 1.68E 06 3.34E 05 0.00E-01 5.02E 05 0.00E-01 3.45E 06 HN 56 0.00E-01 8.85E-04 1.57E-04 0.00E-01 1.12E-03 0.00E-01 5.82E-02 I FE 55 5.79E 05 4.10E 05 9.57E 04 0.0CE-01 0.00E-01 2.60E 05 1.78E 05 I FE 59 6.74E 05 1.57E 06 6.01E 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 0.0CE-01 0.00E-01 0.00E-01 4.35E 07 NI 63 1.42E 09 1.00E 08 4.81E 07 0.0CE-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 7.05E-01 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 4.09E 08 0.00E-01 5.62E 08 0.00E-01 3.72E 08 ZN 69 1.15E-12 2.20E-12 1.54E-13 0.0CE-01 1.44E-12 0.00E-01 4.05E-12 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 0.0CE-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 5.67E 08 2.67E 08 0.00E-01 0.00E-01 0.00E-01 8.40E 07 RD 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 5.62E 09 0.00E-01 1.61E 08 0.00E-01 0.00E-01 0.00E-01 6.69E 08 SR 90 1.39E 11 0.00E-01 3.43E 10 0.00E-01 0.00E-01 0.00E-01 3.90E 09 SR 91 1.11E 05 0.00E-01 4.40E 03 0.0CE-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 0.0CE-01 0.00E-01 0.00E-01 6,26E-19 Y 91 1.90E 03 0.00E-01 5.00E 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.DCE-01 0.00E-01 0.00E-01 3.40E-01 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 2R 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 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 0.0CE-01 0.00E-01 0.00E-01 0.00E-01

0 rre;t Crpy Procedzre 99-0412 09:07101 U Revision: 2 OETSITE DOSE CALCULATION MANUAL AP 0?B-003 I

d Reference Use 0 Page 157 of 168 m

o ATTACHMENT A (Page 152 of 163)

.0

,0 TABLE A.5-18 (cont'd)

'D GRASS-GOAT-MILK PATHWAY FACTOR MI MREM /YR PER pCI/SEC TEEN o

W NUCLIDE BCNE LIVER T BODY THYROID KIDNEY LUNG GI-LLI O

RU 103 2.17E 02 0.00E-01 9.28E 01 0.00E-01 7.66E D2 0.00E-01 1.81E 04 RU 105 1.88E-04 0.00E-01 7.30E-05 0.00E-01 2.37E-03 0.00E-01 1.52E-01 M

RU 106 4.50E 03 0.00E-01 5.67E 02 0.00E-01 8.60E 03 0.00E-01 2.16E 05 AG 110M 1.16E 07 1.09E 07 6.65E 06 0.00E-01 2.08E 07 0.00E-01 3.07E 09 TE 125M 3.60E 06 1.30E 06 4.82E 05 1.01E 06 0.00E-01 0.00E-01 1.06E 07 ,

TE 127M 1.01E 07 3.59E 06 1.20E 06 2.41E 06 4.10E 07 0.00E-01 2.52E 07 TE 127 1.45E 02 5.15E 01 3.13E 01 1.00E 02 5.89E 02 0.00E-01 1.12E 04 TE 129M 1.32E 07 4.90E 06 2.09E 06 4.26E 06 5.53E 07 0.00E-01 4.96E 07 TE 129 6.28E-11 2.34E-11 1.53E-11 4.48E-11 2.63E-10 0.00E-01 3.43E-10 TE 131M 7.89E 04 3.78E 04 3.16E 04 5.69E 04 3.94E 05 0.00E-01 3.04E 06 TE 131 8.04E-34 3.31E-34 2.51E-34 6.19E-34 3.51E-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 0.00E-01 1.97E 06 I 131 6.45E 08 9.03E 08 4.85E 08 2.63E 11 1.55E 09 0.00E-01 1.79E 08 I 132 3.51E-01 9.18E-01 3.29E-01 3.09E 01 1.45E 00 0.00E-01 4.00E-01 I 133 8.49E 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 CS 134 2.94E 10 6.93E 10 3.22E 10 0.00E-01 2.20E 10 8.41E 09 8.62E 08 CS 136 1.33E 09 5.25E 09 3.52E 09 0.00E-01 2.86E 09 4.50E 08 4.22E 08 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 8.23E-24 4.34E-26 BA 139 1.01E-08 7.13E-12 2.95E-10 0.00E-01 6.72E-12 4.91E-12 9.04E-08 BA 140 5.82E 06 7.14E 03 3.75E 05 0.00E-01 2.42E 03 4.08E 03 8.98E 06 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 2.25E-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 00 0.00E-01 1.15E 05 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 2.19E 01 2.38E 01 1.42E 00 0.0CE-01 1.40E 01 0.00E-01 8.57E 04 W 187 1.44E 03 1.17E 03 4.11E 02 0.0CE-01 0.00E-01 0.00E-01 3.18E 05 NP 239 8.41E-01 7.93E-02 4.41E-02 0.0CE-01 2.49E-01 0.00E-01 1.28E 04 I

I

Crrrent Gopy Proced:re 99-04 12 09.07101 Revision: 2 OFFSITE DOSE CALCULATION MANUAL AP 0~7B-003 p Reference Use Page 158 of 168 sn O ATTACHMENT A (Page 153 of 163)

.D TABLE A.5-19 D GRASS-GOAT-MILK PATHWAY TACTOR g M8 MREM /YR PER p;I/SEC CHILO O

N HUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI

\

f 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 2.39E 08 N NA 24 1.06E 06 1.06E 06 1.06E 06 1.06E 06 1.06E 06 1.06E 06 1.06E 06 P 32 9.33E 10 4.37E 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 6.7BE 03 1.85E 03 1.24E 04 6.4BE 05 MN 54 0.00E-01 2.52E 06 6.70E 05 0.00E-01 7.06E OL 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 TE SS 1.45E 06 7.70E 05 2.39E 05 0.00E-01 0.000 31 4.36E 05 1.43E 05 TE 59 1.56E 06 2.53E 06 1.26E 06 0.00E-01 0.002-01 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 0.00E-01 0.00E-01 2.87E 07 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 2.37E 00 CU 64 0.00E-01 8.23E 03 5.03E 03 0.00E-01 2.01E 04 0.00E-01 3.91E 05 EN 65 4.96E 08 1.32E 09 8.22E OB 0.00E-01 0.33E 08 0.00E-01 2.32E 08 EN 69 2.84E-12 4.10E-12 3.79E-13 0.00E-01 2.49E-12 0.00E-01 2.5BE-10 BR P3 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 0.00E-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 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 1.39E 10 0.00E-01 3.97E 08 0.00E-01 0.00E-01 0.00E-01 5.38E 08 SR 30 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 1.02E 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 1.2SE 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 8.79E-01 Y 93 1.27E-01 0.00E-01 3.4BE-03 0.00E-01 0.00E-01 0.00E-01 1.89E 03 ER 95 4.60E 02 1.01E 02 9.00E 01 0.00E-01 1.45E 02 0.00E-01 1.05E 05 ER 97 2.30E-01 3.33E-02 1.96E-02 0.00E-01 4.7BE-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 2.71s 17 MO 99 0.00E-01 9.76E 06 2.42E 06 0.00E-01 2.0BE 07 0.00E-01 8.07c J6 TC 99M 1.59E 00 3.11E 00 5.16E 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

i Carrext Ospy prec:d re 99 0412 09:07:01 )

4 1

l Revision: 2 ~ OFFS,ITE DOSE CALCULATION MANUAL AP 07B-003

'O

) Reference Use Page 159 of 168

. $1 .

01 0- ATTACHMENT A (Page 154 of'163) l OFFSITE DOSE CALCULATION MANUAL D

0 TAata A.5-19 (cont'd)

,.0 : CRASS-GOAT-MILK PATHWAY FACTOR g 'M8 MREM /YR PER pCI/SEC g CHILD W- NUCLIDE BONE LIVER T B00Y THYROID KIDNEY LUNG GI-LLI j

.( .

I3 RU 103 5.14E'02 0.00E-01 1.97E 02 0.00E-01 1.29E 03 0.005-01 1.33E 04 N RU 105 4.59E-04 0.00E-01 1.67E-04 0.00E-01 4.04E-03 0.00E-01 3.00E-01 RU 106 1.11E 04 0.00E-01 1.38E 03 0.00E-01 1.50E 04 0.00E-01 1,72E 05 AG 110M 2.51E 07 1.69E 07 .1.35E 07 '0.00E-01 3.15E 07 0.00E-01 2.01E 09 TE 125M 8.85E 06 2.40E 06-- 1.18E 06 2.48E 06 0.00E-01 0.00E-01 8.54E 06 TE 12?M 2.50E 07 6.72E 06 2.96E.06 5.97E 06 1.12E 07 0.00E-01 2.02E 07 TE 127- 3.57E 02 9.64E 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 9.56E 07 0.00E-01 3.97E 07 TE 129 1.55E-10 4.32E-11 3.68E-11 1.11E-10 4.53E-10 0.00E-01 9.64E-09 TE 131M 1.92E 05 6.64E 04 7.07E 04 1.37E 05' 6.43E 05 0.00E-01 2.69E 06 TE 131 1.97E-33 6.01E-34 5.87E-34 1.51E-33 5.97E-33 0.00E-01 1.04E-32 TE 132 1.23E 06 5.44E 05 6.58E 05 7.93E 05 5.05E 06 0.00E-01 5.48E 06 I 130 2.07E 06 4.19E 06 2.16E 06 4.62E 00 6.27E 06 0.00E-01 1.96E 06 I 131 1.56Z 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'03 7.01E-01 7.07E 01 2.33E 00 0.00E-01 1.79E 00 I 133 2.06E'07 2.55E 07 9.65E 06 4.74E 09 4.2SE 07 0.00E-01 1.03E 07 I 134 '1.03E-11 1.91E 8.77E-12 4.39E-10 2.92E-11 0.00E-01 1.26E-11 I 135 6.49E 04 1.17E 05 5.52E 04 1.03E 07 1.79E 05 0.00E-01 8.90E 04 l CS 134- 6.79E 10 1.11E 11 2.35E 10 0.00E-01 3.45E 10 1.24E 10 6.01E 08 i CS 136 3.01E 09 '8.27E 09 5.35E 09 0.00E-01 4.40E 09 6.57E 08 2.91E 08 CS 137 9.67E 10 9.26E 10 1.37E 10 0.00E-01 3.02E 10 1.09E 10 5.80E 08 CS . 138 1.21E-22 1.68E-22 .1.07E-22 0.00E-01 1.18E-22 1.27E-23 7.74E-23 BA 139 2.49E-08 1.33E-11 7.21E-10 0.00E-01 1.16E-11 7.82E-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 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 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 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 CE 143 2.25E 01 .1.22E 04 1.77E 00 0.00E-01 5.12E 00 0.00E-01 1.79E 05 CE 144- 1.95E 05 6.11E 04 1.04E 04 0.00E-01 3.38E 04 0.00E-01 1.59E 07 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 0.00E-01 0.00E-01. 0.00E-01 0.00E-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 l W 187 3.49E 03- 2.07E 03 9.28E 02 0.00E-01 0.00E-01 0.00E-01 2.90E 05 NP 239 -2.07E 00 1.49E-01 1.04E-01 0.00E-01 4.30E-01 0.00E-01 1.10E 04

]

l l

o

Crrreet copy Precedtre 00 0412 00.07:01 l N Revision:.2 3 OFFSITE DOSE CALCULATION MANUAL AP 078-003 1 E' Reference Use Page 160 of 168 sQ M'

g ATTACHMENT-A '

I (Page 155 of 163)

'D

.,0 TABLE A.5-20

.GRRSS-CORT-MILK PATHWAY FACTOR f%- M' MREM /YR PER pCI/SEC INFANT O-14 HUCLIDE BONE LIVER 7 BODY THYROID KIDNEY LUNG GI-LLI N 3- 0.00E-01 4.86E 03 4.86E 03 4.86E 03 4.86E 03 4.86E 03 4.86E 03 D ' 14 2.34E 09 5.00E 08 5.00E 08 5.00E 08-C 5.00E 08 5.00E 08 5.00E 08 M 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~ 1.13E 10 7.45E 09 0.00E-01 0.00E-01 0.00E-01 2.60E 09 CR . 51 .

. 0.00E-01 0.00E-01 1.94E 04 1.26E 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 FE 55 1.76E 06 1.13E 06 3.03E 06 0.00E-01 0.00E-01 5.54E 05 1.44E 05 PE 59 2.92E 06- 5.09E 06 2.01E 06- 0.00E-01 0.00E-01 1.51E 06 2.43E 06 C0 58 0.00E-01 2.91E 06 7.26E 06 0.00E-01 0.00E-01 0.00E-01 7.25E 06 CO ' - 60 0.00E-01 1.06E 07 2.50E 07 0.00E-01 0.00E-01 0.00E-01 2.52E 01 NI 63 4.19E 09- 2.59E 08 1.45E 08 0.00E-01 0.00E-01 0.00E-01 1.29E 07 NI 65' 5.27E-01 5.96E-02 2.71E-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 '

EN 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 0.00E-01 4.52E-12 0.00E-01. B.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 0.00E-01 0.00E-01 0.00E-01 0.00E-01 RB 86 0.00E-01 2.67E 09 1.32E 09' O.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 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 SR 89 2.64E 10 0.00E 7.5BE 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 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 2.19E 00 0.00E-01 0.00E-01 0.00E-01 1.13E 05 Y 91M 6.87E-20 0.00E-01 2.34E-21 0.30E-01 0.00E-01 0.00E-01 2.29E-16 Y 91 8.79E 03 0.00E-01 2.345 02 0.00E-01 0.00E-01 0.00E-01 6.30E 05 Y 92 6.47E-05 0.00E-01 1.82E-06 0.00E-01 0.00E-01 0.00E-01 1.23E 00 Y 93 2.70E-01 0.00E-01 7.36E-03 0.00E-01 0.00E-01 0.00E-01 2.13E 03 2R 95 8.17E 02 1.99E 02 1.41E 02- 0.00E-01 2.14E 02 0.00E-01 9.91E 04 2R 97 4.88E-01 8.37E-02 3.82E-02 0.00E-01 8.44E-02 0.00E-01 5.34E 03 NB 95 7.12E 04 2.93E 04 1.70E 04 0.00E-01 2.10E 04 0.00E-01 2.48E 07 M0 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 0.00E-01 7.33E 01 3.56E 00 1.98E 03

C rroit CGpy Procedire 99-0412 09.07101 l

l l U Revision: 2 OFFSITE DOSE CALC,ULATION MANUAL AP 07B-003 J

@ Reference Use Page 161 of 168 01 m

D ATTACHMENT A (Page 156 of 163)

0 TABI.E A.5-20 (cont

d)

J GRASS-GOAT-MILK PATHWAY TACTOR g M3 MREM /YR PER pCI/SEC g INTANT 14 NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI

\

g 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 N RU 105 9.68E-04 0,00E-01 3.26E-04 0.00E-01 1.12E-03 0.00E-01 3.85E-01 l l RU 106 2.28E 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 4.03E 07 0.00E-01 1.75E 09 TE 125M 1.81E 07 6.05E 06 2.45E 06 6.09E 06 0.00E-01 0.00E-01 8.62E 06 I

TE 127M 5.05E 07 1.68E 07 6.12E 06 1.46E 07 1.24E 08 0.00E-01 2.04E 07 TE 127 7.59E 02 2.54E 02 1.63E 02 6.18E 02 1.85E 03 0.00E-01 1.59E 04 TE 129M 6.69E 07 2.29E 07 1.03E 07 2.57E 07 1.67E 08 0.00E-01 3.99E 07 TE 129 3.20E-10 1.13E-10 7.66E-11 2.75E-10 8.17E-10 0.00E-01 2.62E-08 TE 131M 4.0$E 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 1.69E-31 TE 132 2.53E 06 1.25E 06 1.17E 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 0.00E-01 2.01E 06 I 131 3.26E 09 3.85E 09 1.69E 09 1.26E 12 4.49E 09 0.00E-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 l 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 135 1.35E 05 2.68E 05 9.79E 04 2.41E 07 2.99E 05 0.00E-01 9.71E 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 1.73E 10 6.45E 09 0.00E-01 6.89E 09 1.41E 09 2.63E 09 l

CS 137 1.54E 11 1.81E 11 1.28E 10 0.00E-01 4.85E 10 1.96E 10 5.65E 08 l

CS 138 2.55E-22 4.15E-22 2.01E-22 0.00E-01 2.07E-22 3.23E-23 6.63E-22 BA 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 1.49E 06 0.00E-01 6.87E 03 1.78E 04 7.11E 06 BA 141 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 RA 142 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 l 1.A 140 4.88E 00 1.92E 00 4.94E-00 0.00E-01 0.00E-01 0.00E-01 2.26E 04 i LA 142 1.03E-11 3.78E-12 9.06E-13 0.00E-01 0.00E-01 0.00E-01 6.43E-07 l CE 141 5.20E 03 3.17E 03 3.74E 02 0.00E-01 9.79E 02 0.00E-01 1.64E 06 l .CE 143 4.76E 01 3.16E 04 3.61E 00 0.00E-01 9.21E 00 0.00E-01 1.04E 05 l 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 2.40E 01 0.00E-01 9.41E 04 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 1.06E 02 1.09E 02 6.69E 00 0.00E-01 4.21E 01 0.00E-01 6.92E 04 W 187 7.35E 03 5.11E 03 1.17E 03 0.00E-01 0.00E-01 0.00E-01 3.00E 05 NP 239 4.38E 00 3.91E-01 2.21E-01 0.00E-01 7.80E-01 0.00E-01 1.13E 04 l

CYrroit Ospy Procedure 99-0412 09:07101 Revision: 2 OFFSITE DOSE CALCULATION MANUAL AP 078-003 Reference Use Page 162 of 168 (fri 9 ATTACHMENT A (Page 157 of 163)

~

I

.D D

\

O

.W

\

O L1 APPENDIX B Meteorological Model

Otrroit C1py Proc: dure 99 04 12 09.07i01 ,

1 Revision: 2 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 Reference Use Page 163 of 168 M

U ATTACHMENT A (Page 158 of 163) l 0FFSITE DOSE CALCULATION MANUAL 4

,0 APPENDIX B

.D

\' PROPRIETARY INFORMATION SUPPLIED BY SAI O

N- The X/Q's and D/Q's are calculated using the guidance of Reg.

\ Guide 1.111.

O I'I The constant mean wind direction model, as defined in equation 3 of Reg. Guide 1.111, is used to calculated X/Q values.

2 2 2.032 S ng exp (-h , / 2 a ,j [x)]

(>vo)"- _

NxUiE(x) e Where:

h. = effective release height (m). (All releases from Wolf. Creek Generating Station are considered as ground releases therefore he = 0.)

ng = hours of valid data for weather conditions in given direction, windspeed class I, and atmospheric stability class j.

N = total house of valid data Ui = midpoint of windspeed class (m/s) x = distance downwind (m) co(x) = vertical plume spread without volumetric correction at distance x and stability class j. See Figure B.1.

Eq (x) = vertical plume spread with columetric correction for release within buildings wake cavity, at distance x and stability class j.

For ground level releases Eq(x) is the lesser of 2

2 2 (o s (x) + 0.5 D ,f y orf3og(x)

Orrrert Copy ProcedIre 99-04 12 09.07i01 3

,1 Revision: 2 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 i

Reference Use Page 164 of 168 FI O ATTACHMENT A (Page 159 of 163) 1 OFFSITE DOSE CALCULATION MANUAL D

A 0

APPENDIX B (CONT'D)

Where:

\

U Da = maximum adjacent building height either up- or down-wind from the release point U

2.032 = (2/n) " divided by width, in radians, of a 22.5 sector (X/Q)o = Average ef fluent 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 j

= O (X /Q)D _.

g g, x {[x) j U

l The calculation of the ralative disposition per unit area, D/0, 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:

Dy (x)

DEPLv (x)

D/Q =

(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)

r-Orrre:t Copy Proc'd:re 99-0412 09.07t01 Revision: 2 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 Reference Use Page 165 of 168 0 ATTACHMENT A (Page 160 of 163)

.OFFSITE DOSE CALCULATION MANUAL

A APPENDIX B (CONT'D)

A

\ DEPLu (x) = Reduction factor due to-plume depletion at distance x 0

for windspeed i and stability class j.

N O ,

Carrext Capy procrdure 99-0412 09.07te1 U Revision: 2 'OFFSITE DOSE CALCULATION MANUAL AP 07B-003 i X

N Reference Use Page 166 of 168 9

trt o ATTACHMENT A (Page 161 of.163)

..o

~D rigure s.1 0

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Czrroit Capy Procsitire 99-0412 09107&O1 j l

Y3 Revision: 2 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 D Reference Use Page 167 of 168 ta .

Qn

-0 ATTACHMENT A (Page 162 of 163) ,

OFFSITE DOSE CALCULATION MANUAL 1 D

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Revision: 2 OFFSITE DOSE CALCULATION MANUAL AP 078-003 Reference Use Page 168 of 168 Vri D ATTACHMENT A (Page 163 of 163)

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- END -

4

Attachment 11 to the Wolf Creek Generating Station 1999 Annual Radilogical EITluent Release Report 1

l 1

l

)

l l

ATTACHMENT II i WCNOC ' Administrative Procedure AP 07B-004, Revision 0, i "Offsite Dose Calculation Manual (Radiological Environmental

. Monitoring Program)" !

l 1

i l

1

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i l

i

2e Currett Cepy Prosedure 99-04-12 09:07:51 s

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i w W$LF CREEK NUCLEAR OPERATING CORPORATION

\

O l!J AP 07B-004 OFFSITE DOSE CALCUIATION MANUAL (RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM)

Responsible Manager Manager Resource Protection Revision Number 0 Use Category Reference Administrative Controls Procedure Yes Infrequently Performed Procedure No Program Number 07B DC4 03/02/1999 4

. Carrreit Czpy Proc:d:re 99-0412 09.07:51 U' Revision: 0 OFFSITE DOSE CALCULATION MANUAL AP 078-004 5

(RADIOLOGICAL ENVIRONMENTAL MONITORING Reference Use PROGRAM) Page 1 of 29 O

v1.

o , TABLE OF CONTENTS

- SECTION TITLE PAGE

.,0

.0~ 1.0 PURPOSE 2

.0 2. 0 - SCOPE 2

\

3.0 REFERENCES

AND COMMITMENTS 2 0 4.0 DEFINITIONS 2 W 5.0 RESPONSIBILITIES 2

\ 6.0 PROCEDURE '

3 O 7.0 RECORDS M- 4 8.0 FORMS- 4 I ATTACHMENT A OFFSITE DOSE CALCULATION MANUAL (REMP) 5

Otrrelt 0:py Procedure 99-0412 09:07151 Revision: 0 OFFSITE DOSE CALCULATION MANUAL AP 078-004

?

(RADIOLOGICAL ENVIRONMENTAL Reference Use MONITORING PROGRAM) Page 2 of 29 00 0 1.0 PURPOSE

~

1.1 This procedure contains the Offsite Dose Calculation Manual 40

.0 (ODCM) Radiological Environmental Monitoring Program (REMP) requirements.

.,0

\ 2.0 SCOPE O

W 2.1 Technical Specifications 6.8.4-f, 6.9.1.6 and 6.14 shall be fully implemented by this procedure.

N 2.2 Procedure AP 078-003, OFFSITE DOSE CALCULATION MANUAL has been split into two procedures. Requirements for the REMP are now contained in this procedure.

3.0 REFF.RENCES AND CONNITHENTS 3.1 References 3.1.1 AP 07B-003, OFFSITE DOSE CALCULATION MANUAL 3.1.2 Radiological Assessment Branch Technical Position on Environmental Monitoring, Revision 1, November 1979

{

3.1.3 PIR 98-0112, Revising the ODCM with an OTSC )

3.1.4 Technical Specification 6.14 3.1.5 Technical Specification 6.8.4-f 3.1.6 Technical Specification 6.9.1.6 3.2 Commitments l

3.2.1 None l

4.0 DEFINITIONS 4.1 None 5.0 RESPONSIBILITIES 5.1 Environmental Management 5.1.1 Ensures the REMP is established, implemented and maintained.

CIrre2.t CIpy Proc: dure 99-04-12 09.07 51 U Revision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-004 f (RADIOLOGICAL ENVIRONMENTAL j Reference Use MONITORING PROGRAM) Page 3 of 29 40 0 6.0 PROCEDURE

~

6.1 Revisions to This Procedure

.0 NOTE D

\ To comply with Technical Specification 6.14, revisions to this O procedure are not permitted via APF 15C-004-04, ON THE SPOT f\ CHANGE form (Reference Step 3.1.3) ,

O hl 6.1.1 Revisions to this procedure are to be submitted through the Manager Resource Protection via APr 15C-004-01, DOCUMENT REVISION REQUEST (DRR).

6.1.2 Changes to ATTACHMENT A shall include:

1. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month / year) the change was implemented. (Reference Step 3.1.4)

2. Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s) and (Reference Step 3.1.4)

NOTE Changes to the REMP will have no impact upon the level of radioactive affluent control nor will impact the accuracy or reliability of affluent dose or setpoint calculations.

3. A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.106, 40 CFR Part 190, 10 CFR 50.36A, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent dose, or setpoint calculations. (Reference Step 3.1.4) 6.1.3 The changes shall become effective after review and acceptance by the PSRC and the approval of the Plant Manager. (Reference Step 3.1.4)

i Orrreit 33py Proc: dire 99-04-12 09.07151 i i

1 f Revision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-004 !

3 (RADIOLOGICAL ENVIRONMENTAL W- Reference Use MONITORING PROGRAM) Page 4 of 29 0

m p 6.2 ODCM Submittal To NRC i

NOTE i

..D

.D To comply with Technical Specification 6.14, a copy of this j

.0 procedure must be substitted to the NRC with the Annual !

o

\ Radioactive Effluent Release Report. .

N !

\ 6.2.1 Changes to the ODCM shall be submitted to the 0 l Commission in the form of a complete, legible copy of j the entire ODCM as a part of or concurrent with the Annual Radioactive Effluent Release Report for the l period of the report in which any change to the ODCM j was made. (Reference Step 3.1.4) l

)

7.0 RECORDS 7.1 The following is a lifetime QA Record:

7.1.1 AP 07B-004, OFFSITE DOSE CALCULATION MANUAL (RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM) {

i 8.0 FORMS l 0.1 None

- END -

D

l Current Copy Prsccdure 99-0412 09:07:51

{

l Revision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-004 Reference Use (RADIOLOGICAL ENVIRONMENTAL )

MONITORING PROGRAM) Page 5 of 29

)

WI p ATTACHMENT A l

(Page 1 of 25) 4-OFFSITE DOSE CALCULATION MANUAL (REMP)

,0 0

Wolf Creek Generating Station a

W

\

o IJ

-\

1 l

l 5

Offsite Dose Calculation Manual Radiological Environmental Monitoring Program

r CYrrelt Copy ProctdIre 99-0412 09:07t51 d Revision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-004

>i D (RADIOLOGICAL ENVIRONMENTAL p Reference Use MONITORING PROGRAM) Page 6 of 29 m

p ATTACHMENT A (Page 2 of 25)

.0

.,0 TABLE OF CONTENTS

..D

\ Title Page O

N

1.0 INTRODUCTION

8

\

Q 2.0 LIQUID EFFLUENTS (CONTAINED IN AP 07B-003) -

U 3.0 GASEOUS EFFLUENTS (CONTAINED IN AP 07B-003) -

4.0 TOTAL DOSE (CONTAINED IN AP 07B-003) -

5.0 RADIOI4GICAL ENVIRotO4 ENTAL MONITORING PROGRAM 5.1 Monitoring Program 8 5.2 Land Use Census 9 l 5.3 Interlaboratory Comparison Program 9 )

5.4 Reporting Requirements 10 )

j 6.O BASES j Sections 2.0 through 4.0 (Contained in AP 078-003) -

j l

Section 5.0 Radiological Environmental Monitoring 27 )

Program Section 5.1 Monitoring Program 27 Section 5.2 Land Use Census 28 Section 5.3 Interlaboratory Comparison Program 28 7.0 REPORTS 7.1 Annual Radiological Environmental Operating Report 28 7.2 Annual Radioactive Effluent Release Report -

(Contained in AP 078-003)

APPENDIX A: Dose Conversion Factor Tables (Contained in -

AP 07B-003)

APPENDIX B: Meteorological Model (Contained in AP 07B-003) -

l l

l

Currelt CIpy ProcedIre 99 04 12 09.07:51 F Revision: 0 OFFSITE DOSE CALCULkTION MANUAL

'I AP 07B-004

(RADI0 LOGICAL ENVIRONMENTAL Reference USe Page 7 of 29 p MONITORING PROGRAM)

B o ATTACHMENT A (Page 3 of 25)

', LIST OF TABLES Table Title Pay h 5-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 11

, 5-2 SAMPLING LOCATION NUMBERS, DISTANCES (MILES) AND 17 g DIRECTIONS 5-3 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE 18 ANALYSIS 5-4 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN 21 ENVIRONMENTAL SAMPLES LIST OF FIGURES Figure Title P_aage 5.1 AIRBORNE PATHWAY SAMPLING LOCATIONS 22 5.2 DIRECT RADIATION PATHWAY SAMPLING LOCATIONS 23 5.3 WATERBORNE PATHWAY SAMPLING LOCATIONS 24 5.4 INGESTION PATHWAY SAMPLING LOCATIONS 25 5.5 DISTANT SAMPLING LOCATIONS 26 l

m ,,

Orrre;t Copy PrordIre 99-0412 09:07:51 U Revision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-004 (RADIOLOGICAL ENVIRONMENTAL Reference Use MONITORING PROGRAM) Page 8 of 29 tn p ATTACHMENT A (Page 4 of 25)

..o a 1.0 Introduction A

\ This attachment contains the ODCM for the Radiological a Environmental Monitoring Program which was previously contained 49 in AP 07B-003. This program is provided to monitor the

\ radiation and radionuclides in the environs of the plant. The 0 -

program provides (1) representative measurements of M radioactivity in the highest potential exposure pathways, and (2) verification of the accuracy of the effluent monitoring program and modeling of environmental exposure pathways. This l

, program conforms to the guidance of Appendix I to 10 CFR part 50 and includes the following: (Reference Step 3.1.5)

1. Monitoring, ' sampling, analysis and reporting of radiation and radionuclides in the environment. (Reference Step 3.1.5)

2. A Land Use Census to ensure that changes in the use of areas at and beyond the site boundary are identified and the modifications to the monitoring program are made if required by the results of this census, and (Reference Step 3.1.5)

3. Participation in an Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring. (Reference Step 3.1.5)

This attachment also provides a description of the information that should be included in the Annual Radiological Environmental Operating Report. 12/98 2.0 Liquid Effluents (Contained in AP 07B-003) 3.0 Gaseous Effluents (Contained in AP 07B-003) 4.0 Total Dose (Contained in AP 07B-003) 5.0 Radiological Environmental Monitoring Program This section describes the Radiological Environmental Monitoring Program specified in Section 6.8.4.f of the Wolf Creek Technical Specifications. 2/98 5.1 Monitoring Program Table 5-1 provides a schedule which describes the pathways, specific locations, sample collection frequencies, and analyses to be performed to implement the Radiological Environmental Monitoring Program.

Crrrelt C'$py Proc: dire 99-04 12 09.07:51 U Revision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-004 h (RADIOLOGICAL ENVIRONMENTAL Reference Use MONITORING PROGRAM) Page 9 of 29 m

o ATTACHMENT A (Page 5 of 25)

.0 Figures 5.1 through 5.5 contain maps depicting sampling A locations in relation to the WCGS site. Table 5-2 lists )

.0 distances and directions to these locations from the WCGS site.

\

c Table 5-3 lists regatred detection capabilities for the analyses l N performed. I

\

O 5.2 Land Use census i IJ '

A Land Use Census shall be conducted annually during the growing season to identify the nearest (1) milk animal, (2) residence, and (3) garden of greater than 500 square feet producing broadleaf vegetation in each of the 16 meteorological sections within five miles of the WCGS site. (Broadleaf vegetation sampling of available vegetation may be performed at the site boundary in each of two different direction sectors with the l highest predicted D/Qs in lieu of the garden census.

Specifications for broadleaf vegetation sampling in Table 5-1, Part 4.c. shall be followed, including analysis of control samples.) Methods shall be used in conducting the census that provide the best results, such as door-to-door surveys, telephone surveys, consulting the U.S.D.A. office in Burlington, inspection of aerial photographs of the area, or reviewing leasing records for area farms and residences. 5/96 If a location'(s) is identified which yields a calculated dose or dose commitment (via the same exposure pathway) 20% greater than at a lecation from which samples are currently being obtained, and the cooperator agrees, the new location (s) shall be added to the Radiological Environmental Monitoring Program. The indicator sampling location (s) having the lowest calculated dose or dose commitment may then be deleted from the monitoring program. 11/98 The results of the Land Use Census shall be included in the Annual Radiological Environmental Operating Report described in Section 7.1.

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

A summary of intercomparison results shall be included in the Annual Radiological Environmental Operating Report described in Section 7.1.

. &rrelt Crpy Procrd2re 99-0412 09:07151 f Revision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-004 4 (RADIOLOGICAL ENVIRONMENTAL

Reference Use Page 10 of 29 0 MONITORING PROGRAM) m p ATTACHMENT A (Page 6 of 25)

.0 5.4 Reporting Requirements D

J 5.4.1 Annual Radiological Environmental Operating Report

\

O To meet the requirements of Wolf Creek Technical Specification W 6.9.1.6,-the Annual Radiological Environmental Operating Report O

\ covering the operation of the unit during the previous calendar U

year shall be submitted to the NRC before May 1 of each year.

The content of this report is described in Section 7.1.

5.4.2 Special Reports 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) +. 21.0 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 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. (*The methodology and parameters used to estimate the potential annual dose to a member of the public shall be indicated in this report.) 5/96

. CIrrelt Cipy Proc #fre 99-0412 09i07151 H

Revision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-004

f. Reference USe (RADIOLOGICAL ENVIRONMENTAL g MONITORING PROGRAM) Page 11 of 29 tri 0 ATTACHMENT A (Page 7 of 25)

OFFSITE DOSE CALCULATION MANUAL (REMP) 0

.0 TABLE 5-1 D RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

\

Q Exposure Pathway / Number of Samples and Sample Collection Type and Frequency g gmple Type Sample Locations (1) Frequency of Analysis

\ 1. AIRBORNE FIGURES 5.1 & 5.5 O

gj Radioiodine and Samples from five locations Continuous sampler, Analyze radiciodine

Particulates operation with canister weekly for sample collection I-131 weekly, or more frequently if required, by dust loading Saciples from locations near the site boundary in three sectors having the highest calculated annual average D/O (Locations 2, 3 s 37 on Figure 5.1)s-Sample from the vicinity of Analyze particulate a community having the filter weekly for highest calculated annual gross beta activity

-' average D/Q (Location 32 on (2); perform Figure 5.1, New Strawn); quarterly gamma <

isotopic analysis !

(3) composite (by location).

3 Sample from a control location 10-20 miles ,

distant in a low D/Q sector (Location 40 on Figure 5.5). (11) j

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

An inner rir.g of stations, one in each meteorological sector 0-3 mile range from the site (Locations 1, 7-9, 11-13, 18, 26, 27, 29-31, 7/97 37, 38 4 47 on Figure 5.2). l i

q

OYrreIt CIpy Prec: dure 99-0412 09.07:51 H

7 Revision: 0 OFFSITE DOSE CALCULATION MANUAL AP 078-004 h (RADIOLOGICAL ENVIRONMENTAL p Reference Use MONITORING PROGRAM) Page 12 of 29 tn U ATTACHMENT A (Page 8 of 25) l OFFSITE DOSE CALCULATION MANUAL (REMP)

'.D 0 TABI.E 5-1 (Continued)

.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM l

\

O _ Exposure Pathway / Number of Samples and Sample Collection Type and Frequency of y Sample Type Sample Locations (1) Frequency Analysis l

\ DIRECT RADIATION An outer ring of ctations, O (4) (CONTINUED) one in each meteorological M sector in the 3 to 5 mile range from the site (Locations 4-6, 15-17, 19-25, and 33-36 on Figure 5.2). Five sectors (A, B, D, G & L} contain an additional station (Locations 2, 3, 10, 14 and 28)

The balance of the stations to be placed in special interest areas such as population centers (Locations 23 and 32),

nearby residences (r.a ny locations are near a residence), schools (Location 23), and in one or two areas to serve as control stations 10-20 miles distant from the site (Locations 39 and 40 on (/97 Figure 5.5) (11)

3. WATERBORNE FIGURE 5.3 Surface One sample upstream (5) Honthly grab sample Monthly gamma (Location MUSH on Figure isotopic analysis (3) 5.3) and one sample down- and composite for stream (Location DC on tritium analysis Figure 5.3) quarterly.

Ground Samples from one or two Quarterly grab Qua:terly gamma sources only if likely to sample isotopic analysis (3) be affected and tritium analysis.

6/97 Indicator samples at locations hydrologically down-gradient of the site (Locations C-10, C-49 and D-65 on Figure 5.3);

control sample at a location hydrologically upgradient of the site '

(Location B-12 on Figure

5. 3) (6)

Czrrett Ospy Proc'd:re 99-04 12 09:07151 H

Revision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-004 y7 (RADIOLOGICAL ENVIRONMENTAL j,3 Reference Use MONITORING PROGRAM) Page 13 of 29 F1 9 ATTACHMENT A {

i (Page 9 of 25) l OFFSITE DOSE CALCULATION MANUAL (REMP) )

.0 l D TABLE 5-1 (Continued) I J RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM l

\

Q Exposure Pathway / Number of Samples and Sample Collection Type and Frequency y Sample Type Sample Locations (1) Frequency of Analysis

\ 3. WATERBORNE Sample of municipal water Monthly composite Monthly gamma C (CONT.) supply at an indicator (7) isotopic analysis (3) h) Drinking location downstream of the and gross beta l site (Location LW-40 on analysis of composite {

Figure 5.5)s control sample sample. Quarterly from location upstream of tritium analysis of l the site (Location BW-15 on composites (8).

Figure 5.3)

Shoreline Sediment One sample from the Semiannually Semiannual gama vicinity of Wolf Creek isotopic analysis (3)

Cooling Lake discharge cove (Location DC on Figure 5.3)s control sample from John Redmond Reservoir.

4. INGESTION FIGURES 5.4 AND 5.5 Milk Samples from milking Semimonthly April to Gama isotopic animals at three indicator November; monthly analysis (3) and locations within 5 miles of December-March (9) I-131 analysis o'f the site having the highest each sample. 7/97 dose potential (currently there are no locations producing milk for human consumption within 5 miles of the site); one sample from a control location greater than 10 miles from the site if indicator locations are sampled. (11) I/87 Fish Indicator samples of 1 to 3 Somiartnually Gamma isotopic recreationally important analysis (3) on species from Wolf Creek edible portions cooling Lake (several sampling areas indicated in Figure 5.4); control samples of similar species from John Redmond Reservoir Spillway (indicated on Figure 5.4).

C rrert Ccpy Proced:re 99 0412 09:07151 I H

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..D

,0 TABLE 5-1 (Continued) l

,D RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM l

\

O Exposure Pathway / Number of Samples and Sample Collection Type and Frequency gg Sample Type Sample Locations (1) Frequency of Analysis

4. INGESTION Samples of available Monthly when Gamma isotopic O (CCNT.) broadleaf vegetation from available (9) analysis (3) on IJ rood Products two indicator locations edible portions.

with highest calculated annual average D/0 (Locations G-1 and F-1 and alternate Location E-1 on Figure 5.4); sample of similar broadleaf vegetation from a control location greater than 10 miles from the site in a low D/0 section (Location 2/98 S-4 on Figure 5.5) . (11)

Food Products Sample of crops irrigated At time of harvest Gamma isotopic with water from the Neosho (10) analysis (3) on River downstream of the edible portions Neosho River-Wolf Creek confluence (locations will vary from year to year, e.g., Location NR-D1 &

NR-D2 on Figure 5.5).

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(Page 11 of 25)

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4 TABLE 5-1 (Continued)

D TABLE NOTATIONS

\

O (1) Deviations are permitted from the required sampling schedule if W specimens are unobtainable due to hazardous conditions, seasonal

\ unavailability, malfunction of automatic campling equipment, and other a legitimate reasons. If specimens are unobtainable due to sampling h) equipment malfunction, every effort shall be made to complete corrective action prior to the end of the next sampling period. All I

deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report described in Section 7.1. 5/96 g 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. 11/98 (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 is 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 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 optimmn dose information with minimal fading. S/96

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A o- TABLE 5-1 (Continued)

J TABLE NOTATIONS

.. g c: -(5) The " upstream" sample is taken at a distance beyond significant

.W influence of the discharge.

A .

(6).

o- Ground water samples shall be taken when this source is. tapped for

)J drinking or irrigation purposes in areas where the hydraulic gradient 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 the liquid concentrate. In this program, composite sample aliquots shall be collected at time intervals that are very short (e.g., every two hours) relative to the compositing period (e.g., monthly) in ceder to assure obtaining a representative sample. 5/96 (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 and broadleaf vegetation samples are often temporarily, but not permanently, unavailable at the scheduled sample collection times.

Alternate sampling locations nay 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 pa+4ermed during each discrete harvest. If harvest occurs continuously, sampling shall be monthly. Attention shall be pai- to including samples of tuberous and root food products.

(11) The purpose of this sample is to cbtain 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.

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.,0 D TABLE 5-2 1

.0 SAMPLING LOCATION NUMBERS, DISTANCES (miles) AND DIRECTIONS

.\ Air Particulate Locatie. Distance /

g g Number Direction

\ 2 2.7/N O 3 3.0/NNE N 32 3.2/WNW 37 2.1/NNW 40 >15.0/WNW )

6/97, TLD E ation Distance / Location Distance / Location Distance / Location Distance /

Number Direction Number Direction Number Direction Number Direction 1 1.4/N 11 1.6/E 21 3.8/S 31 3.0/WNW 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/CE 24 4.1/WSW 34 4.0/NW I 5 4.0/NE 15 4.5/ESE 25 3.6/W 35 4.6/NNW i 6 4.4/ENE 16 4.2/E 26 2.6/WSW 36 4.2/N l 7 1.9/NE 17 3.6/SE 27 2.1/SW 37 2.1/NNW 8 1.6/NNE 18 3.0/SSE 28 2.8/SW 38 1.2/NW 6/97 '

9 2.0/ENE 19 4.0/SSE 29 1.G/SSW 39 13.0/N 10 2.4/ENE 20 3.3/S 30 2.2/W 40 >15.0/WNW 47 .16/S 7/97

)

Groundwater Drinking Water Surface Water l B-12 2.2/NNE BW-15 3.9/SW MUSH 3.6/W I C-10 2.8/W LW-40 >10/SSE DC 0.6/WNW C-49 2.9/SW 0-65 3.9/S Milk f. Food

. Products F-1 1.8/ESE G-1 1.6/SE S-4 >15.0/WNW 6/97 E-1 1.8/E 2/98 Fish Shoreline Sediments Irrigated Crops WCCL DC 0.6/WNW NR-D1 9.2/S JRR 4/W JRR 4/W NR-D2 >10/S l

)

~

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.0-o TABLE 5-3

,o DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS ct) 2i (3)

\ Lower Limit of Detection (LLD)

O N AIRBORNE FOOD

\ PARTICULATE FISH PRODUCTS SEDIMENT D ANALYSIS WATER OR GASES (pCi/kg, MILK (pCi/kg, (pCi/kg, IJ (pCi/l) (pCi/m 3) wet) (pCi/1) wet) dry)

Gross '

4 0.01 Beta H-3 2,000*

Mn-54 35 130 co-58 15 130 Fe-59 30 260

{

Co-60 15 130' Zn-65 30 260 Zr-Nb-95 15 I-131 1** 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 LLD for drinking water samples. If no drinking water pathway exists, a value of 3,000 pCi/1 may be used.

- LLD for drinking water samples. If no drinking water pathway exists, the LLD of gamma isotopic analysis may be used.

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,0

.,o TABLE 5-3 (Continued)

.,0 TABLE NOTATIONS

\

O W (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 O nuclides, shall also be analyzed and reported in the Annual U 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.

(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% l i

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

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

4.66 s, LLD = E. V e 2.22 e Y e exp(-A At)

Where:

LLD =

the "a priori" lower limit of detection (piccCuries 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 i 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, Y =

the fractional radiochemical yield, wt :n applicable, A = the radioactive decay constant for the particular radionuclide (sec-1), and at =

the elapsed time between sample collection, or end of the sample collection period, and time of counting (sec) .

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

t_m_-

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D D TABI2 5-3 (Continued) 0 TABLE NOTATIONS

\

-0 It should be recognized that the LLD is defined as an a_ priori (before w the fact) 1!.mit representing the capability of a measurement system

\ and not as an a posteriori (af ter the fact) limit for a particular a measurement. Analyses shall be performed in such a manner that the gj stated LLDs will be achieved under routine conditions. Occasionally {

background fluctuations, unavoidable small sample sizes, the presence !

of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report described in Section 7.1.

1 1

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.,0

,0 TABLE 5-4

.0 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES

\

O W AIRBORNE g WATER PARTICULATE OR FISH MILK TOOD PRODUCTS O ANALYSIS (pCi/1) GASES (poi /m') (pCi/kg, wet) (pCi/1) (pC1/kg, Wet)

N H-3 20,000*

Mn-54 1,000 30,000 Co-58 1,000 30,000 i 1

Fe-59 400 10,000 l 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.

- If no drinking water pathway exists, a value of 20 pC1/1 may be used.

11/96

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D a FIGURE 5.1

.O N

i [A i % J 0A ;y

\ $N ~

Nk y c 9' P y' v y%4 & ,

.p.g ..- .

}"[ } /( /\ D e ~

+ '

i- 4o N 4-E I

'-3g .)

%fg%r - 0 , ?# F[

_ f~ '

j ,

,..= \

\[N Jl

/ -) ( L f( ,

4 (; ,

,a 'F -

n.J

\ xW" pf >

)

AIRBORNE PATHWAY SAMPLING LOCATIONS S = AIRBORNE PARTICULATE AND RADIOIODINE

Orrrer.t Copy Proc: dure 99-04 12 09:07151 D Revision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-004

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MONITORING PROGRAM) Page 23 of 29 da p ATTACHMENT A (Page 19 of 25)

.D

,o FIGURE 5.2 0

\

c N

\ \ [A i \ J NhM * -

Nk

Y c

' o VAi]\

O .'ibws.4 ,' v 6' P g ,..i'p37hjj [ D

== p; ( '- -hw "'

N _ . 25 6 .ie E c/_ - 4'

~

3 '

2 g4 15 i

29 4

~

y g y r -l

\l \ !\

R..

.d / /

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n J- l DIRECT RADIATION PATHWAY SAMPLING LOCATIONS e = TLD LOCATIONS 7/97

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.0 0 FIGURE 5.3

\

\ [A i \ J 0

\$d --

-c

$ k C

l W xM W (y

e 7_g3 ; a- g /x o

+ ,

UJ' LA -

/- \ m N\ r '

.. 3 U " / E Yd F[

fkl [ s

\fN f y{ ..

.i N \

/L ) ( Q( '

s 4 ( ;)

5 /

r a.. >

WATERBORNE PATHWAY SAMPLING LOCATIONS 9- DRINKING WATER A= SURFACE WATER E= GROUND WATER 4= SHORELINE SEDIMENT

Cyrrez.t C3py Proced re 99 0412 09:07151

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..a

.o FIGURE 5.4

,0

\

o bJ N

i (A i \ J

!, ' oWil

\$N -

[b f X c

' Kl %f 11K4V P

Q .'~'>

(/ p/( [\ D

=

N ,,

A-3 6 i

'n j4 s

E 4/- '-

' - ex -

11 i

t.

g .)

4%f l*':.;.; *

%%5/

\

ef Jt%r /' -7Q=J 3\VN '

' f( , %< ,

A16.1 9n J P' 1 J

INGESTION PATHWAY SAMPLING LOCATIONS A= FISH (JRR) E = BROADLEAF VEGETATION /lRRIGATED CROPS D = FISH (WCL) 1/9e l

c:

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gri 9 ATTACHMENT A l (Page 22 of 25)

- l OFFSITE DOSE CALCULATION MANUAL (REMP) i

.0 0 FIGURE 5.5

.0

\

o bJ

\

D ' " '

o / #=% .1%=

m //A a= a a f

r ---

a 9 l

L e n.s s

+ *^

, - /

/

{ E.

.s 1 1 .x .

I of

~~

d W '

_, 2 6

om

Jg %'m

\

I f

il E

Eb y Q.

-O- )

ou / -

i e - .g(-

/)

DISTANT SAMPUNG LOCATIONS e TLD s = DRNKING WATER

= ARBORNE PNmCULATE & RAD 000lNE o= BROADLEAF VEGETATIOPY IRRKIATED CROPS 6/97

CIrre;t G4 py Proc'.dtre 99-04 12 09:07:51 D Revision: 0 OFFSITE DOSE CALCULATION MhNUAL AP 078-004 (RADIOLOGICAL ENVIRONMENTAL Reference Use MONITORING PROGRAM) Page 27 of 29 m

p ATTACHMENT A (Page 23 of 25)