Text

Rev 0 to Offsite Dose Calculation Manual
	ML20138F337
Person / Time
Site:	Wolf Creek
Issue date:	04/30/1997
From:	; WOLF CREEK NUCLEAR OPERATING CORP.
To:	;
Shared Package
ML20138E816	List: ML20138E811; ML20138F331; ML20138F337;
References
	AP-07B-003, AP-7B-3, NUDOCS 9705050360
	Download: ML20138F337 (200)
	v • d • e

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j If WA.F CREEK NUCLEAR OPERATitJG CORPORATION i

i l AP 07B-003 OFFSITE DOSE CALCULATION MANUAL

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j Responsible Manaaer j Superintendent Chemistry 1

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Revision Number o Use Category Reference Administrative Controls Procedure Yes Infrequently Performed Procedure No Program Number 07B 0012 4 sa %

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?J SECTION TITLE EAGE

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J 1.0 PURPOSE 2 i 2.0 SCOPE 2 g

3.0 REFERENCES

IJJD CCK1ITMENTS .~.

4.0 DEFINITIONS 2 5.0 RESPONSIBILITIES 2 I 6.O PROCEDURE 3 6.1 Revision Of The ODCM 3 ,

6.2 ODCM Submittal To NRC 3 i 7.0 RECORDS 4 8.O FORMS 4 ATTACHMENT A OFFSITE DOSE CALCULATION MANUAL 5 3

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\\ 1.1 This procedure contains the Offsite Dose Calculation Manual f.L- (ODCM) and the requirements for revision and submittal to the

~M NRC. I

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2.0 SCOPE i

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I 2.1 Technical Specification 6.14 shall be fully implemented by this I procedure.

3.0 REFERENCES

AND COMMITMENTS 3.1 References 1

3.1.1 Technical Specification 6.14 3.1.2 AP 15C-001, Procedure Writers Guide 3.1.3 AP 15C-004, Preparation, Review, and Approval of Documents 3.1.4 Regulatory Guide 1.109, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance'with 10CFRPart50, Appendix I 3.1.5 NUREG 0133, Preparation of Radiological Effluent ,

Technical Specifications for Nuclear Power plants I 3.2 Commitments 3.2.1 None 4.0 DEFINITIONS 4.1 None 5.0 RESPONSIBILITIES 5.1 The Superintendent Chemistry is responsible for the ODCM.

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lcy3 6.0 PROCEDURE

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\\ 6.1 Revisinn of The ODCM M-j -N 6.1.1 All revisions to the ODCM are to be submitted through i \\ the Superintendent Chemistry via a document revision f[ request (DRh).

) 6.1.2 The Superintendent Chemistry shall ensure the Document

, Revision Request -(DRR) package includes the following:

i

, 1. A copy of the revised pages including revision bars

and the date (e.g. , month / year) in the right column.

} 2. Sufficient information to support the change together with the appropriate analyses or

evaluations justifying the change (s) and

3. A determination that the change will maintain the li level of Radioactive Effluent Control required by 10 CFR 20.106, 40 CFR Part 190, 10 CFR 50.36A, and i Appendix I to 10 CFR Part 50 and not adversely j impact the accuracy or reliability of effluent j dose, or setpoint calculations. !

I

) 6.1.3 The ODCM revision shall become effective after review

{ and acceptance by the PSRC and the approval of the Vice President Plant _ Operations as documented on the

- Document Revision Request (DRR).

6.2 ODCM Snhmittal To NRC i

i 6.2.1 Changes to the ODCM shall be submitted to the

! Commission in the form of a complete, legible copy of i 3

the entire ODCM as a part of or concurrent with the i Annual Radioactive Effluent Release Report for the

period of the report in which any change to the ODCM l was made.

I

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) f.ne change was

implemented.

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_g 7.0 RECORDS UN i i

\\ 7.1 The following is a lifetime QA Record: '

M-M 7.1.1 AP 07B-003, Offsite Dose Calculation Manual

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u I,}, Wolf Creek Generating Station i er 1

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\ OFFSITE DOSE CALCULATION MANUAL ,

4 i pj TABLE OF CONTENTS l

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1.0 INTRODUCTION

9 2.0 LIQUID EFFLUENTS 10 1 2.1 CONCENTRATION - COMPLIANCE WITH 10 CFR 20 10 2.2 DOSE - COMPLIANCE WITH 10 CFR 50 APPEIIL1X I 16 2.3 PROJECTED DOSE 18 2.4 INSTRUMENTATION 19 3.0 GASEOUS EFFLUENTS 37 ,

3.1 DOSE RATE - COMPLIANCE WITH 10 CFR 20 37 3.2 DOSE - COMPLIANCE WITH 10 CFR 50 APPENDIX I 45 3.3 PROJECTED DOSE 55 3.4 INSTRUMENTATION S7 4.0 TOTAL DOSE 72 4.1 REMEDIAL ACTION 72 4.2 SURVEILLANCE REQUIREMENTS 73 )

5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 73 5.1 MONITORING PROGRAM 73 5.2 LAND USE CENSUS 74 5.3 INTERLABORATORY COMPARISON PROGRAM 74 l 5.4 REPORTING REQUIREMENTS 75 l 6.0 BASES 92 7.0 REPORTS 101 l 7.1 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING 101 REPORT l 7.2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 102 APPENDIX A DOSE CONVERSION FACTOR TABLES 106 )

APPENDIX B: METEOROLOGICAL MODEL 183

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LIST OF TABLES jg Table ERGR lJ

.p 2-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM 11 i l

i 2-2 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 21 i !

2-3 RADIOACTIVE LIQUID EFFLUENT MONI'IORING INSTRUMENTATION 24

{ SURVEILLANCE REQUIREMENTS l 4

3-1 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM 41 f

3-2 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 58 3-3 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 60

SURVEILLANCE REQUIREMENTS 1

[ 5-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 76 i

l 5-2 SAMPLING LOCATION NUMBERS, DISTANCES (MILES) AND 82 DIRECTIONS i l

! 5-3 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE 83 ANALYSIS 5-4 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN 86 t ENVIRONMENTAL SAMPLES u l A.1-1 BIOACCUMULATION FACTORS TO BE USED IN THE ABSENCE OF 107 SITE SPECIFIC DATA A.1-2 DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS 108 A.2-1 INHALATION DOSE FACTORS FOR ADULTS 109 j A.2-2 INHALATION DOSE FACTORS FOR TEENAGERS 111 A.2-3 INHALATION DOSE FACTORS FOR CHILD 113 A.2-4 INHALATION DOSE FACTORS FOR INFANT 115 A.2-5 EXTERNAL DOSE FACTOR FOR STANDING ON CONTAMINATED 117 GROUND A.3-1 INGESTION DOSE FACTOR FOR ADULTS 119

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\h OFFSITE DOSE CALCULATION MANUAL LIST OF TABLES gg Table Ragg

.l5 gr A.3-2 INGESTION DOSE FACTOR FOR TEENAGERS 122 A.3-3 INGESTION DOSE FACTOR FOR CHILD 125 A.3-4 INGESTION DOSE FACTOR FOR INFANT 128 A.3-5 STABLE ELEMidT TRANSFER DATA 131 A 4-1 SITE RELATED INGESTION DOSE COMMITMENT FOR ADULT 132 A.4-2 SITE RELATED INGESTION DOSE COMMITMENT FACTOR FOR 135 TEENAGER j l

A.4-3 SITE RELATED INGESTION DOSE COMMITPENT FACTOR FOR CHILD 138 A.4-4 SITE RELATED INGESTION DOSE COMMITMENT FACTOR FOR 141 INFANT A.5-1 INHALATION DOSE PARAMETER FOR THE CHILD 144 l A.5-2 INHALATION PATHWAY FACTOR FOR ADULT (RI FACTOR) 145 A.5-3 INHALATION PATHWAY FACTOR FOR TEENAGER (RI FACTOR) 147 A.5-4 INHALATION PATHWAY FACTOR FOR CHILD (RI FACTOR) 149 A.5-5 INHALATION PATHWAY FACTOR FOR INFANT (RI FACTOR) 151 A.5-6 GRASS-COW-MILK PATHWAY FACTOR ADULT (RI FACTOR) OF SITE 153 SPECIPIC DATA A.5-7 GRASS-COW-MILK PATHWAY FACTOR TEEN (RI FACTOR) 155 A.5-8 GRASS-COW-MILK PATHWAY FACTOR CHILD (RI FACTOR) 157 A.5-9 GRASS-COW-MILK PATHUAY FACTCR INFANT (RI FACTOR) 159 A.5-10 GRASS-COW-MEAT PATHWAY FACTOR ADULT (RI FACTOR) 161 A.5-11 GRASS-COW-MEAT PATHWAY FACTOR TEEN (RI FACTOR) 163 A.5-12 GRASS-COW-MEAT PATHWAY FACTOR INFANT (RI FACTOR) 165

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\ OFFSITE DOSE CALCULATION MANUAL 61.

.g LIST OF TABLES Table Ea92

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A gj- A.5-13 VEGETATION PATHWAY FAC"POR ADULT (RI FACTOR) 167 A.5-14 V,dBTATION PATHWAY FACTOR TEEN (RI FACTOR) 169 A.5-15 VEGBTATION PATHWAY FACTOR CHILD (R1 FACTOR) 171 l

A.5-16 GROUND PLANE PATHWAY FACTOR (RI FACTOR) 173 A.5-17 GRASS-GOAT-MILK PATHWAY FACTOR ADULT (RI FACTOR) 174 A.5-18 GRASS-GOAT-MILK PATHWAY FACTOR TEEN (RI FACTOR) 176 A.5-19 GRASS-GOAT-MILK PATHWAY FACTOR CHILD (RI FACTOR) 179 .

l A.5-20 GRASS-GOAT-MILK PATHWAY FACTOR INFANT (RI FACTOR) 181 LIST OF FIGURES Ficure Eaga 2.1 BOUNDARY FOR LIQUID EFFLUENTS 36 3.1 BOUNDARY FOR GASEOUS EFFLUENTS 71 5.1 AIRBORNE PATHWAY SAMPLING LOCATIONS 87 5.2 DIRECT RADIATION PATHWAY SAMPLING LOCATIONS 88 5.3 WATERBCPNB PATHWAY SAMPLING LOCATIONS 89 5.4 INGESTION PATHWAY SAMPLING LOCATIONS 90 5.5 DISTANT SAMPLING LOCATIONS 91 B-1 VERTICAL STANDARD DEVIATION OF MATERIAL IN A PLUME 186 B2 PLUME TRWEL DISTANCE VCESUS FRJ.CTICN P.E'fAINING IN 1837 PLUME B-3 PLUME TRAVEL DISTANCE VERSUS RELATIVE DEPOSITION RATE 188

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@ ATTACHMENT A i gg (Page 6 of 384) g OFFSITE DOSE CALCULATION MANUAL hb g 1.0 IntXQ4ur#. ion

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

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

Wolf Creek will continue to maintain the existing level of l effluent control (10CFR20.106) to comply with the new 1 requirements. This method of compliance has been determined by the NRC to be ALARA. 22/S3 l

l The ODCM describes the methodology and parameters used in the

! calculation of offsite doses due to radioactive liquid and l l gaseous effluents. The ODCM contents for calculation of dose l are based on " Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants (NUREG-0133)," and Regulatory Guide 1.109, Revision 1.

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

Adult age group for the liquid pathway, and the Child age group for gaseous effluent organ doses. 22/S5 i

l The ODCM provides the limitations on the operability of ]

radioactive liquid and gaseous monitoring instrumentation l including surveillance tests and setpoint determination. Each Surveillance Requirement shall be performed within the specified l surveillance interval with a maximum allowable extension not to l exceed 25% of the specified interval.

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

l The ODCM provides descriptions of the information that should be ;

l includsd in the Annual Radiological Environmental Operating and l Aunual Radioactive Effluent Release Reports.

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__2 2b Rsvision: 0 OFFSITE D03E CALCULATION MANUAL AP 07B-003 ml R3forcnca Us3 Page 11 of 188 g ATTACHMENT A i gg (Page 7 of 184) l g OFFSITE DOSE CALCULATION MANUAL !

ta fd 2.0 Liquid Effluents I l\ 2.1 l4 Correntratico- _rampU.arna 3ith_ J.0_ftF .20 l Of l The concentration of radioactive material released in liquid l l effluents to UNRESTRICTED AREAS (see Figure 2.1) shall be limited to the concentration specified in 10 CPR 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. j 2.1.1 n---44m1 Action l With the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS exceeding the above limits, immediately restore the concentration to within the above limits.

2.1.2 surveillanca necruir--nts 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 analyzed according to the sampling and analysis program of Table 2-1. 3/92 i

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{g OFFSITE DOSE CALCULATION MANUAL l TABLE 2-1 j RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM i

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, LOWER ;

g. MINIMUM TYPE OF ACTIVITY LIMIT OF '

i LIQUID RELEASE SAMPLING ANALYSIS ANALYSIS DETECTION TYPE FREQUENCY FREQUENCY (1) (LLD)

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( Ci/mL) :

1. B cla Waste P P E ncipal Garda 5x10'#~

Release (2) Each Batch Each Batch (3) Emitters Tanks 1x10' I-131

a. Waste P M Dissolved and 1x10' Monitor Tank One Entrained Gases Batch /M (Gamma Emitters) F

b. Secondary P M (4) H-3 1x10*

Liquid Waste Each Batch Composite Monitor Tank

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1x10 '

Gross Alpha P Q (4) Sx10' Each Batch Composite SR-89, Sr-90 1x10' Fe-55

2. Continuous (6) W (4) 5x10 (5) Releases Daily Grab Composite Principal Gamma Sample (3) Emitters 1x10' I-131 Steam Generator M M Dissolved and 1x10 '

Blowdown Grab Entrained Gases Sample (Gamma Emitters)

(6) M (4) 1x10 '"

Daily Grab Couposite H-3 Sample 1x10 '

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Gross Alpha (6) Q (4) Ex10' Daily Grab Composite SR-89, Sr-90 Sample 1x10' Fe-55 3/.9J (

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TABLE 2-1 (Continued)

TABLE NOTATIONS

,l (1) The LLD is defined, as the smallest concentration of radioactive y material in a sample that will yield a net count, above system ;

background, that will be detected with 95% probability with only 5% '

probability of falsely concluding that a blank observation represents I a "real" signal. l For a particular measurement system, which may include radiochemical separation:

LLD = s.

E x V x 2.22 x 10' x Y x Decay where: l 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 j as appropriate, (counts per minute), g = [s"/ LT Where: B = background sum (counts) l 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, I

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: I A) This decay factor corrects for decay from the time of sampling to the start of the analysis.

e"Mts, where:

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

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\\ OFFSITE DOSE CALCULATION MANUAL bk g TABLE 2-1 (contintied) l gg TABLE NOTATIONS

.w GT A = In2/ half-life B) This decay factor corrects for decay during the analysis, i

'*"I 1-c '

A x RT , ;

A= in2/ half-11fe !

RT = real time of counting C) This decay factor corrects for decay during sampling.

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Mtd A = In2/ half-life td = deposition time - sample time - deposition start time l

NOTE i 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 j and not as an a posterfori (after the fact) limit for a particular measurement.

(2) A batch release is the discharge of liquid wastes of a discrete l volume. Prior to sampling for analyses, each batch shall be isolated, i and then thoroughly mixed by a method described in plant procedures to assure representative sampling. 4/92 ;

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\ OFFSITE DOSE CALCULATION MANUAL ti TABLE 2-1 (Continued)

{ TABLE NOTATIONS yp (3) The principal gamma emitters for which the LLD specification applies include the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the semiannual Radioactive Effluent Release Report in the format outlined in Regulatory Guide 1.21, Appendix B, Revision 1, June 1974.

(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 relcared. 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.

(C) Samplia shall be taken at the initiation cf 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 NOTATTON 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.

3/91

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( OFFSITE DOSE CALCULATION MANUAL 2.2 Doce - Compliance With 10 CFR 50 Annendir T

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

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

b. During any calendar year to less than or equal to 3

mrems to the whole body and to less than or equal to 10 mrems to any organ.

I 2.2.1 Razaadial Ac. tion i

With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, j prepare and submit to the Commission within 30 days, pursuant to i I

Technical Specification 6.9.2, a Special Report 'aat 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. 3/91 2.2.2 Surveill=nna Reauir===nta 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.

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OFFSITE DOSE CALCULATION MANUAL g Where,

\ I j D7- the cumulative dose commitment to the total bcdy '

p or any organ, T, from the liquid effluent for the total time period f A tt ,in nuem L=1 At t = the length of the Lth time period over which Cn i and Fu are averaged for all liquid releases, in hours.

Cn=

i the average concentration of radionuclide, 'i', in undiluted liquid effluent flow during time period Ato, in pci/mL. l Ft = the near field average dilution factor for Cit during any liquid effluent release where:

f t

F = (hK {

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 Ci/mL. See Tables A.4-1 through A.4-4.

The limiting age group for liquid dose calculations is the Adult age group. 22/95 Ar-i 1.14E5 (U, / D, + U, x BF)DF, i

ec-1 2 l

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( OFFSITE DOSE CALCULATION MANUAL '

Where, l

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DW = Dilution factor from the near field area to the

[ potable water intake for water consumption, for Wolf

, Creek Generating Station this factor is 1 (one).

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BFi= Bioaccumulation factor for radionuclide 'i', in i 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, j 'i', in mrem /pci, from Table A.3-1 through A.3-4, from j Regulatory Guide 1.109 (Rev. 1).

i

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

1.109)

Up = Adult fish consumption, (21 kg/yr.from Reg. Guide

) 1.109) 22/95 i 10'pCi/ pCi x 105 ml/ Kg

1.14E5 = Units conversion factor =

1 8760 hr / yr The dose calculations are based on the actual isotopic analysis )

, of the radioactive liquid effluento, the radioactive liquid j effluent flow, and the dilution flow. ,

i I

! 2.3 ProiachmA Dona l

! j The Liquid Radwaste Treatment System shall be OPERABLE and appropriate portions of the system shall be used to reduce i

releases of radioactivity when the projected doses due the j liquid effluent, from each unit, to UNRESTRICTED AREAS (see i Figure 2.1) would exceed 0.06 mrem to the whole body or 0.2 mrem )

to any organ in a 31 day period. ,

i 2.3.1 namadini Acticn l l

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 ,

l to the Commission within 30 days pursuant to Technical Specification 6.9.2, a Special Report that includes the following information: 3/92 l

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OFFSITE DOSE CALCULATION MANUAL

a. Explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable a aquipment or subaystema, and the rcason for the r 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. 3/92 2.3.2 surve111=nna Raauir-- =tm 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 utilized.

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 22/95 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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ATTACHMENT A

.g (Page 16 of 184) g OFFSITE DOSE CALCULATION MANUAL 2.4.1 Remedigi Action td 2.4.1.1 With a radioactive liquid ef fluent monitoring

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

4 2.4.1.2 With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 2-2. Restore the inoperable instrumentation to OPERABLE status within the time specified in the ACTION, or explain in the next Annual Radioactive Effluent Release Report, why this inoperability was not corrected within the time specified. 9/93 ,

I'

, 2.4.2 Survaillanca Requirements j 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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ATTACHMENT A N (Page 17 of 184' OFFSITE DOSE CALCULATION MANUAL U TABLE 2-2 N

RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION

\ INSTRUMENT d#

MINIMIM ACTION CHANNELS OPERABLE

1. Radioactivity Monitors Providing Alarm and Automatic Termination of Release

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

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

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

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

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

2. Flow Rate Measurement Devices

a. Liquid Redwaate Diacharge Line

1) Waste Monitor Tank A Discharge Line 1 34

2) Waste Monitor Tank B Discharge Line 1 34

b. Steam Generator Blowdown Discharge Line 1 34

c. Secondary Liquid Waste System Discharge Line 1 34 3/9.1

,~

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,O g ATTACHMENT A y (Page 18 of 184)

OFFSITE DOSE CALCULATION MANUAL g TABLE 2-2 (Continued)

\ ACTION STATEMENTS j J l f Action 31 - With the number of channels OPERABLE less than raquired by ths j Minimum Channels OPERABLE requirement, effluent releases via this l pathway may continue for up to 14 days provided that prior to initiating a release:

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

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.

l 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 30 days provided that prior to initiating a releases

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.

3/93

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ATTACHMENT A O (Page 19 of 184)

OFFSITE DOSE CALCULATION MANUAL TABLE 2-2 (Continued)

ACTION STATEMENTS

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

3/91

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ATTACHMENT A 0

g (Page 20 of 184)

OFFSITE DOSE CALCULATION MANUAL TABLE 2-3 M RADIOACTIVE LIQUID EFFLUENT MpKITORIBAG INSTRIBEIDITATION

\ SURVIILLANCE REQUIREMEldTE U INSTRIStENT M SOURCE CHANMEL AMALOG f EdE;E CHECE CALIBRATION CH&tDIEL OPERATIQMAL ZESZ

1. Radioactivity Ponitors providing 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) Q (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) i Influent Monitor (HF-RE-95)

2. Flow Rate Measurement Devices i

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 3 /92 i !

l i

i ,

)

4

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

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N~ TABLE 2-3 (Continued) '

i TABLE NOTATIONS l (1) The ANALOG CHANNEL OPERATIONAL TEST shall also demonstrate that l 7 automatic isolation of this pathway and control room alarm q annunciation occur as appropriate if any of the following conditions l exists: i

a. Instrument indicates measured levels above the Alam/ Trip Setpoint (isolation and alam), or I

b. Circuit failure (alam only), or i

c. Instrument indicates a downscale failure (alarm only), or !i I

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

)

(2) The initial CHANNEL CALIBRATION shall be perfomed using one or more !

of the reference (gas or liquid and solid) standards certified by the l 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 i permit calibrating the system over its intended range or energy, l measurement range, and establish moni. tor response to a solid i calibration source. For subsequent CHANNEL CALIBRATION, NIST traceable standard (gas, liquid, or solid) may be used; or a gas, j liquid, or solid source that has been calibrated by relating it to '

equipment that was previously (within 30 days) calibrated by the same '

j geometry and type of source standard traceable to NIST.

l (3) CHANNEL CHECK shall consist of verifying indication of flow during l periods of release. CHANNEL CHECK shall be made at least once per 24 I hours on days on which continuous, periodic, or batch releases are made.

)

3/91 l l

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

2

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ATTACHMENT A I (P9ge 22 of 184) g OFFSITE DOSE CALCULATION MANUAL 4N 2.4.2 g id Monitor __ Calibration Methodolorvv

,M ,

The fiva monitors associated with liquid releases are listed l

} g. helow:

1

j. Mnnitor In Description -

0-BM-RE-52 Steam Generator Blowdown Discharge Monitor

! 0-LE-RE-59 Turbine Building Drain Monitor {

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

0-HB-RE-18 Liquid Radwaste Discharge Monitor j 0-HF-RE-95 Wastewater Treatment System Influent Monitor Liquid effluent streams are monitored by an NaI(Tl) Datector.

The detector operates in a gross counting mode and is gamma 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/ce, 1 x 10-5 pCi/cc, and 1 x 10-3 pCi/cc. The solutions shall be presented to the detector and t.he neter reading in counts por minuta shall be record:d. A j determination of linearity shall be produced using the counts per minute vs. concentration data. 5/s5 l 2,4,4 Limn 4d Ef fluent REanitor Batsointa 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 one order of magnitude below the High Alarm / Trip Setpoint. Since the high alarm / trip initiates isolation of the particular system and termination of the releace, this netpoint 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. )

l

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g ATTACHMENT A g (Page 23 of 184)

OFFSITE DOSE CALCULATION MANUAL g The calculated Alarm and Trip Action Setpoints for the Liquid g Effluent Line Monitors must satisfy the following equation:

A y c gg Where:

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

c = The Setpoint, in pCi/mL, of the Radioactivity Monitor measuring the radioactivity concentration in i 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 l Value, which if exceeded would result in concentrations 2 exceeding the limits of 10 CFR 20 in the restricted area.

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

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

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

cs C(F+ f) GACi/ ml) f 2.4.4.1. continuous Liquid Effluent Manitora The three monitors associated with continuous liquid releases are listed below:

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

pg l

-3 '

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. ATTACHMENT A ,

g (Page 24 of 184) g OFFSITE DOSE CALCULATION MANUAL u 4 g The Steam Generator Blowdown Discharge Effluent Monitor l

\ continuously monitors the Blowdown Discharge Pump l 4 Outlet to detect excess radioactivity due to System ; j F Demineralizer breakthrough or abnormal Primary to Secondary leakage. The Blowdown Discharge Monitor's High Alarm Setpoint initiates CLOSURE of the Blowdown Isolation Valves and the Blowdown Discharge Valve.

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

Monitor setpoints will be conservatively based on I-131, the most restrictive isotope expected to be present. This is particularly appropriate for the 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 2

activities, it will not be possible to select a radionuclide distribution on which taa base the monitor setpoint. Additionally, maximum effluent flows and minimum dilution flows will normally be assumed.

4 The High Alarm / Trip Setpoint will be set to correspond to the I-131 MPC limit at the boundary of the i 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 j release points that have dilution and to the High Alarm i value for those without dilution. This High Alarm / Trip i Setpoint assures the limits of Section 2.1 are not exceeded at the boundary of the restricted area. 12/95 1

In the event that an alarm is TRIPPED, an evaluation of l the system will be made by taking an actual isotepic

! and flow analysis of the discharge.

4 I

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AP 07B-003 69 gp Reference Use Page 29 of 188 0

ATTACHMENT A (Page 25 of 184)

OFFSITE DOSE CALCULATION MANUAL The above continuous liquid effluents are not radioactive effluents until activity has been detected As by tile Liquid Efflucnt Monitor, a Tritiu.a analysis cf dr the Secondary system, or a gross Beta analysis of the Secondary system. At that time an analysis of the effluent will be made to verify activity in the system effluent. During periods of time when the above liquid effluents are not radioactive the High Alarm / Trip Setpoint may be set to 1.5 times the background count rate.

2.4.4.1.1 Sta== Generator Blowdown Dinahmege vanitor SETPOINT(pCi/ml) = MPCi-m X l F. !

where, l

l MPC in = Maximum Permissible Concentration of I-131, I

3.0 E-7 pCi/mL.

Fm = 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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ATTACHMENT A C)

(p32e 26 o# 184)

OFFSITE DOSE CALCULATION MANUAL M

g 2.4.4.1.2 Turbine Euilding Drain Mnnitor and Wasta Water

( Trea&==nt Syntam Influant unnitor S

O' F, + F' SETPOINT( Ci/ml) = MPC im X T

MPC -m = 3.0 E-7 pCi/mL.

I 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 Effluant unnitor The two monitors associated with liquid batch releases are listed below:

Monitor ID Description 0-HF-RE-45 Secondary Liquid Waste System Monitor 0-HB-RE-18 Liquid Radwaste Discharge Monitor The setpoint is a function of dilution flow rate, tank flow rate, and isotopic composition. A laboratory isotopic analysis is made of each batch prior to discharge. Based on the isotopic analysis and existing flow condition, the setpoint will be calculated and set on the appropriate monitor to ensure the concentration limits of 10 CFR 20, Appendix B, Table II, Column 2 is not exceeded.

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,O ATTACHMENT A (Page 27 of 184)

OFFSITE DOSE CALCULATION MANUAL 4

u g The cetpoints are determined using the following methodology:

\

j, 1) Determine concentrations of radioactivity of the barrF r 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.

Eq - Ec, + c + c + ci + cr i s 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 c a of alpha emitting nue] ides observed by gross alpha analysis of the monthly composite sample.

Cs = The measured concentrations of Sr-83 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 as determined by analysi's of the monthly composite.

Cg = 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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ATTACHMENT A (Page 28 cf 184)

.) OFFSITE DOSE CALCULATION MANUAL u

g 2) The measured radionuclida concen: rations are used to g\ calculate a dilution factor, Fd , which is the ratio of 2 tocal dilution flow' rale to tank flow lata required te f assure that the limiting concentrations of Section 2.1 are met at the point of discharge. This is referred to as the required dilution factor and is determined according to:

r F, = E i C' ' x F*

( MPC g Where:

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

MPCi = MPC g , MPCa, MPCs, MPCt and MPC f , are limiting concentrations of the appropriate radionuclide from 10 CFR 20, Appendix B, Table II, Column 2. For dissolved or entrained noble gases, the concentration shall be limited to 2.0E-04, pCi/mL total activity.

Fs = The safety factor; a conservative factor used to I compensate for statistical fluctuations and errors of l measurement default value is 0.5. 12/95 ]

l

3) For the case Fa < 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 available dilution flow may be apportioned among j simultaneous discharge pathways. l F. o Fi / F, Where Fa is the allocation factor which will modify the required dilution factor so that simultaneous liquid releases may be made without exceeding 10 CFR 20 limits.

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ATTACHMENT A ,

(Page 29 of 104) !

OFFSITE DOSE CALCULATION MANUAL ;

g The most straight-forward determination of allocation g factor is: !

D l f F, = 1/ n Where:

l l

n = The number of liquid discharge pathways for.which Fd > 1 and which is planned for simultaneous release.

However, this value for Fa may be unnecessarily restrictive'in that all release pathways are

~

apportioned the same fraction of the available dilution stream, regardless of the relative concentrations of each of the sources.

i '

Since the radionuclide concentration of the two continuous sources is expected to be less than that of I the batch release source, it is acceptable to allocate l smaller portions of the dilution stream to the continuous releases and a larger portion to the batch releases. j 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 4 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, Fd n, and the effective dilution flow rate, F egg. 1 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 l an effective dilution flow rate as:

F,g = F,, 1-

3 R:vicion: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 G Reference Use Page 34 of 188 6

g ATTACHMENT A g (Page 30 of 194) y, OFFSITE DOSE CALCULATION MANUAL M

g Where:

k j Fm = The c:gacted minimum dilution water flow rete.

E :

LCi - Measured concentration of nuclide i in the !

cooling lake water sample. )

MPCi = 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 Fegg, the calculated maximum permissible waste tank flow rate is given by F# + f, F'"

f,, 5; for f,((Feff FL f.

Where f p if the expected effluent flow rate; normally the rated capacity of the effluent pump. Thus the pump flow rate is set at or below fmax. Even though the value of fmax may be larger than the actual effluent pump capacity, f, p it does represent the upper limit to the effluent flow rate, whereby the requirement of 10CFR20 may still be met. If Fd s 1, the effluent pump 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. Rrvigion: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 N g Reference Use Page 35 of 188 9 ATTACHMENT A O (Page 31 of 184) f OFFSITE DOSE CALCULATION MANUAL b

5) The liquid radiaticn monitor setpoint may now be determined based on the values of E,C1, i and fmax-p The monitor response is primariAy to gamma Taoiation,

& therefore, the actual setpoint is based on I g, C g. The calculated monitor setpoint concentration is determined as follows: c = A[C g( CUml) 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**" P 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 tc establish a monitor setpoint which will provide a.larm should the release concentration inadvertently exceed 10CFR10 limits. This can be accomplished by establishing the adjustment factor as follows: A = 1/ F,

^$-

p Revision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 ' 'O I gi Reference Use Page 36 of 188 l 6 ATTACHMENT A 8 (Page '32 of 184) OFFSITE DOSE CALCULATION MANUAL FIGURE 2.1 l BOUNDARY FOR LIQUID EFFLUENTS 5

1 5

E. !_

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                =\

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V l 5[ OFFSITE DO5E CALCULATION MANUAL AP 07B-003 ' p Rsvision: 0 sD Reference Use Pago 37 of 188 A g 0 ATTACHMENT A 0 (Page 33 of 184) OFFSITE DOSE CALCULATION MANUAL M 3.O Gas 9sua_Jfflunats td

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

Waste Gas Decay Tank releases and Containment Building releases are treated as batch releases. 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. Monitor identifications are as follows: Monitor ID Release Point Description 0-GT-RE-21 A and B Unit Vent (Fuel / Auxiliary Building, access control area, containment purge, condenser air dicchurje) l O-GH-RB-10 A and B Radwaste Building vent (Radwaste Building, waste gas decay tank discharge. Acts to isolate Waste Gas Decay Tank discharge) O-GT-RE-22 & 23 Containment Purge System Monitor (acts to isolate the purge; is not an effluent monitor) 0-GT-RE-31 & 32 Containment Atmosphere Monitor (acts to isolate purge; not an effluent monitor) The setpoint for monitors may be determined either based on total body dose or skin dose rate. The dose rate limits are for l dose rates at the unrestricted area boundary. The monitor setpoint is the lesser of the total body dose rate or akin dose j rate. l l l

15

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0

 ,qp R0forcnco U o                                                       Page 38 of 188    i t 9

! ATTACHMENT A b (Page 34 of 184) l OFFSITE DOSE CALCULATION MANUAL

g. 3.1 Dona "lato - C^mpliance With 10 CFR 20

'q The 6000 r:Atc due to r?dicrctt /a ratorials rc3 cased d n gase~1c 3 , f 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. , l 3.1.1 Ramadial Action With the dose rate (s) exceeding the above limits, immediately l restore the release to within the above limit (s) . 3.1.2 Surveillance Reauir===nts The dowe rate tes radionuclides in gaseous effluents chall Lc determined to be within the above limits in accordance with the methodology described below by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 3-1. 3/.92 i Based on the methodology of NUREG-0133; I

a. Release rate limit for nobles gases: i

[KdX / Qpi < 500 mrem / yr for the total body, i and l [(L + i 1.1 M )(X/ i Q)Qi < 3000 mrem / yr for the skin 8 i Where: l Ki = Total body dose factor due to gamma emissions for each identified noble gas radionuclide, in mrem /yr per pCi/m3, from Table A.1-2. l

l Revision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 j i Reference Use Page 39 of 188 l i AT6CHMENT A (Page 35 of 184) OFFSITE DOSE CALCULATION MANUAL _. (X/ Q) = 2.2E-06 sec/m3, the highest calculated annual I average relative concentration at the restricted area

boundary ir the. north ractor. 3/97 Qi = Release rate of radionuclide i from vent, in 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 pCi/m3 from Table A.1-2. 1.1 = Conversion constant of air dose to skin dose.

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

(P,)IN x (X / Q)x Qi)< 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 pCi/m3 - See Table A.5-1. (X/Q) = 2.2E-06 sec/m3 (the highest annual average). The highest calculated annual average relative concentration for estimating the dose to any individual at the unrestricted area boundary in the E sector. l l

I j Revision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 l Reference Use Page 40 of 188 iO I ATTACHMENT A

 'b                                     (Page 36 of 184)

OFFSITE DOSE CALCULATION MANUAL i All radionuclides are assumed to be released in elemental form. ] The limit io' applicable to the location-(unrestricted area ! boundary or beyond), characterized by the value of X/Q which i resu1La in the r.ia:;imum tctal body or skin doso 'ccan.itment.

The

factors K1, Li, and Mi relate the radionuclide airborne
. concentrations to various dose rates assuming a semi-infinite l cloud. These factors are taken from Table B-1 of the Regulatory i 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 :

1 ! P(i)IN (Inhalation); Pg = K' (BR) DFA (mrem i / yr per pCi/ m') Where: K' = a constant of unit conversion, 106 pCi/pCi. BR = the breathing rate of the child age group in 3 m /yr DFAi = the maximum organ inhalation dose factor for the child age group for the i th radionuclide, in mrem /pci. The total body is considered as an organ in the selection of 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 /pCi. Resolutions of the units yield: Pi (Inhalation) = 3.7 X 109 DFAi The Pi value for tritium is: Pi . (Inhalation) = 3.7 x 109 DFAi l i

                                                                      -.          .._. m -       ,

2 y Revision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003-M g Reforcnca UEn Page 41 of 188 9 ATTACHMENT A ,0 (Page 37 of 184) lW '.g OFFSITE DOSE CALCULATION MANUAL !M TABLE 3-1 { id RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM !\ GASEOUS, SAMPI.ING MINIMtml TYPE OF ACTIVITYI LOMP ! ! RELEASE TYPE FREQUENCY ANALYSIS ANALYSIS LIMIT OF ! FREQUENCY DETECTION (LLD) (1) (pCi/ML) Principal Gamma l P P 1x10' _

1. Waste Gas Each Tank Each Tank Emitters (2)

l. Decay Tank Grab Sample P P Principal Gamma 1x10

2. Containment Each Purge Bach Purge Emitters (2)

Purge or Vent (3) Grab (3) Sample M 1x10' H-3 (oxide) ~ M(3), (4) M(3) Principal Gamma 1x10 '

3. Unit Vent Grab Sample Emitters (2)

M(4) 1x10 ~' H-3 (oxide) M M Principal GanrE 1x10 '

5. Radwaste Grab Sample Emitters (2)

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

6. Release (6) W(7) I-131 Types as i

listed in 3. and 5. above Charcoal 1x10 '" Sample I-133 Continuous W(7) Principal Gamma 1x10'" (6) Particulate Emitters (2) Sample Continuous M Particulate 1x10 (6) Sample Gross Alpha Composite Continuous Q Composite 1x10 " (6) Particulate Sr-89, Sr-90 Sample 12/92 l

                                                                        =    ._.

Revision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 Raforenco Use Page 42 of 188 F3 ATTACHMENT A O (Page 38 of 184) OPPSITE DOSE CALCULATION MANUAL TADLE 3-1 (C.:ntinued) TABLE NOTATIONS

 -,  (1 )  "'ho LI.D 4.s defined, an the em?llest concentraticn of r dioTctiJe f           material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5%

probability of falsely concluding that a blank observation represents a 'real" signal. For a particular measurement system, which may include radiochemical separation-l 4.66 s6 LLD = 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), sd = the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate, (counts per minute), se - Jo / LT Where B = background sum (counts) LT = live time (minutes), E = the counting efficiency (counts per disintegration), V = the sample size (units of mass or volume) , 2.22E-6 = the number of disintegrations per minute per microcurie, Y = the fractional radiochemical yield, when applicable, Decay = decay factor (s), There are three decay factors that may be appropriate for use depending on the nature of the sample and the half life of the nuclide. Any combinatien cf the three may be used. The factors are as follows: A) This decay factor corrects for decay from the time of sampling to the start of the analysis. eMts, where: Ats = decay time = acquisition start time - sample time 4/S2

y R; vision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 g R3forcnca U:0 Page 43 of 188 9 ATTACHMENT A (Page 39 of 184) g OFFSITE DOSE CALCULATION MANUAL b TABLE 3-1 (Continued) fJ TABLE NOTATIONS 7 A = In2/ half-life B) This decay factor corrects for decay during the analysis. 1-e" A x RT A = In2/ half-life RT = real time of counting C) This decay factor corrects for decay during sampling. i' 1 - c '*d AAtd l A = In2/ half-life l I Atd = deposition time - sample time - deposition start time 4/92 NOTE All times used in decay calculations should be in the same units. Typical values of E, V, Y, t s, tg 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 ar a nosteriori (after the fact) limit for a particular measurement.

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  $  Reference Use                                                    Page 44 of188 o                                      A'ITACHMENT A u                                       (Page 40ofI84)
   \

tu OFFSITE DOSE CALCULATION MANUAL

   ~
  \                               TABLE 3-1 (Continued)

J TABLE NOTATIONS (2) The principal gansna emitters for which the LLD specification applies W include the following radionuclides: Kr-87, Xr-88, Xe-133, 133, Xe-133m, Xe-135, and Xe-138 in noble gas releases and Mn-54, Fe-59, Co-58, Co-60, 2n-65, Mo-99, I-131, Cs-134, Cs-137, Ce-141 and Ce-144 in iodine and particulate relaar,es. This list doao not mean that only these 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 semiannual Radioactive Effluent Release Report in the fortnat outlined in Regulatory Guide 1.21, Appendix B, Revision 1, June 1974. (3) Sampling and analysis shall also be performed following shutdown, startup, or a THERMAL POWER change exceeding 15% of RATED THERMAL POWER within 1 hour period. (4) Tritium grab samples shall be taken and analyzed at least once per 24 hours 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. (7) Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours after changing, or after removal from sampler. For unit vent, sampling shall also be performed at least once per 24 hours for a least 7 days following each shutdown, startup or THERMAL POWER change exceeding 15% of RATED THERMAL POWER within a 1-hour period, and analyses shall be completed within 48 hours of changing. When samples collected for 24 hours are analyzed, the corresponding LLD's may be increased by a factor of 10. This requiren ent does not apply if t (1) analysis shows that the DOSE EQUIVALEUT I-131 concentration in the reactor coolant has not increased more than a factor of 3, and (2) the noble gas Monitor shows that effluent activity has not increased more than a factor of 3.

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ATTACHMENT A 1 (Page 41 of 184)

  \                        OFFSITE DOSE CALCULATION MANUAL h    3.2   D_one - C<rpr:11ance with 10 cFR 50 Appendix I 9   3.2.1 Nobit G ues f

The air dose due to noble gases released in gaseous effluents, from each unit, to areas at and beyond the SITE BOUNDARY (see ) I Figure 3.1) shall be limited to the following: l

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 t

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. I 3.2.1.1 Ramadial Action i 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. ; 1 3.2.1.2 Surveillance neauir--nte Cumulative dose contributions for the current calendar quarter and calendar year for noble gases shall be determined in j accordance with the following methodology at least once per 31 j days. The dose calculations for the actual releases of l 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: 3/92 l

a. During any calendar quarter; For gamma radiation; D = 3.17E-8 [M, {A 7-Q)x Q,'s 5 mrad.

j i-i

,~ 3 y> Revision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 0 + m R3foranca Uma Page 46 of 188 O

ATTACHMENT A (Page 42 of 184) g OFFSITE DOSE CALCULATION MANUAL For beta radiation:

  \
 .d                           D = 3.17B-8 EN, ~(.t / G)x Q,'s 10 mrad.

r i-i

b. During any calendar year:

For gamma radiation; ! D = 3.17E-8 [M, (X / Q)x Qh 10 mrad. i=1 For beta radiation: D = 3.17E-8 [Ni (X / Q)x Q,f 20 mrad. ii Where: 3.17 E-8 = The inverse of the number of seconds in a year. Mi - The air dcce factor due to gamma emiocions fcz. each identified noble gas radionuclide, in mrad /yr per pCi/m3 from Table A.1-2 (Reg. Guide 1.109, Table B-1, Col. 4). Ni = The air dose factor due to beta emissions for each identified noble gas radionuclide, in mrad / year per pCi/m3 from Table A.1-2 (Reg. Guide 1.109, Table B-1, Column 2). (X/Q) = 2.2E-06 sec/m3, the highest calculated annual average relative concentration at the restricted area boundary in the north sector. Qi = The release of noble gas radionuclides, 'i', in gaseous effluents, in 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:

3 D Revision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 O (3 Rafarenca Ure Page 47 of 188 ATTACHMENT A (Page 43 of 184) g OFFSITE DOSE CALCULATION MANUAL h a. For gamma radiation i 1.6 mrad /mo.

   \
   ;                    For bot, red 4.ati0n 4 3.? nrad/mo.                         .

7 If the monthly average air doses for: (a) is exceeded, it should be noted that if the release is continued at the same (or 1 higher) frequencies or activities the quarterly limit of sectien 3.2.1.A will be exceeded.

b. For gamma radiation s 0.8 mrad /mo.

j For beta radiation s 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 Radiolodines, Particulates and Oehar n=A4nnualidas j 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: l

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 l mrems to any organ. {

i l

vu 3 1 3 Revision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 , O l A Reference U:e Page 48 of 188 O ATTACHMENT A l (Page 44 of 184) l g OFFSITE DOSE CALCULATION MANUAL ' 3.2.2.1 Remedial _&c.t1on

 )           With the calculated dose from tha release of Todine-131 end i??,                 I y           tritium, and radionuclides in particulate form with half-lives

{ greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a special report that identifies the cause(s) for exceeding the limits and defines the corrective actions that have been taken t,o 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 Surveill=nna Reauir---nts 1 cumulative dose contributions for the current calendar quarter I and current calendar year for Iodine-131 and 133, tritium, and radionuclides in particulate form with half-lives greater than 8 l l 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 I calculations will be performed:

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

b. D (mrem) = 3.17E-8 [R,[(WQ,)} s 15 mrem 3/92

( Where: 1 3.17 E-8 = The inverse of the number of seconds in a year. 4 4 a

3 D Revision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 0 pq Raforence USS Page 49 of 188 O ATTACHMENT A [ (Page 45 of 184) g OFFSITE DOSE CALCULATION MANUAL 1 t H 9 Qi = The release of radiciodines, radioactive 4 g materials in particulate form and radionuclides other at 8' than noble gases in gaseous effluents, 'i', in pCi. . Releases shall be cumulative over the calendar quarter or year as appropriate. The Qi value shall be determined as the product of the flow rate through the j release point and grab samples of the effluent analyzed in accordance with Table 3-1. ! ! W = The annual average dispersion parameter for estimating the dose to an individual at the controlling location. W = (X/Q), 2.2 x 10-6 sec/m3 for the inhalation I pathway. , W = (D/Q), 1.8 E-8 m-2, for the food and ground plane pathways. i 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) S R's [X / Q) = K' (BR),(DFA 3), (mrem / yr per pCi / m ) Where: K' = a constant of unit conversion, 10 6 pCi/pCi. (BR)a = The breathing rate of the receptor of age group (a), in m3/yr. The breathing rates (BR)a for the various age groups are tabulated below, as given in Regulatory Guide 1.109, Table E-5. AGR GROUP fa) BRRATHING RATE (ml/vrl Infant 1400 Child 3700 Teen 8000 Adult 8000

3 l 3' Ravision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 El m Raforenca USS Page 50 of 188 1 J O ATTACHMENT A 0 (Page 46 of 184)

I g OFFSITE DOSE CALCULATION MANUAL l _ (DFAi)a e-The maximum crgan inhalaticn dose factor g for the receptor of age group (a) for the i th

 .:                 ladd enuclide, in m::cn/pci.              The body la considered az; F                  an organ in the selection of (DFA1 )a.                      See Tables A.2-1, A.2-2, A.2-3, & A.2-4. From Regulatory Guide 1.109, Tables E-7,E-8, E-9 and E-10.

Ground Plane Pathway Factor, RGf[p/g) 0 R i(D/Q]= K'K"(SF)DFO .c4 ,'fl[ m xmrem/yrperpCi/sec) 2 Where: K' = A constant of unit conversion, 106 pCi/pCi. K" = A constant of unit conversion, 8760 hr/ year. Ai = The decay constant for the i th radionuclide, sec-1 I 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') . See Table A.2-5. (Regulatory Guide 1.109, Table E-6). SF = The shielding factor (dimensionless), 0.7 (Reg. Guide 1.109) Grass-Cow-Milk Pathway Factor, RC g[p/g) RCi (D / Q) - K' i mrem / yr per pCi / sec) F,(r)(DFLM/Y)-A 'fh* Where: K' = A constant of unit conversion, 106 pCi/pCi. 1 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 1.10r, Table E-5).

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@                                  (Page 47 of 184)

OFFSITE DOSE CALCULATION MANUAL

Infant a 330 1/yr Child = 330 1/yr )

$                             Tcan       u    GOO 1/yr r                             Adult      =    310 1/yr Yp   =   The agricultural productivity by unit area of pasture feed grass, in kg/m2, 0.7 kg/m2        (Reg. Guide 1.109, Table E-15)

Fm = The stable element transfer coefficients, in days / liter, see Table A.3-5. (Reg. Guide 1.109, Table E-1) r = Fraction of deposited activity retained on cow's feed grass, r=1 for radiciodine and ra 0.2 for particulates. (Reg. Guide 1.109, Table B-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 A.3-4. (Reg. Guide 1.109, Table E-11, E-12, E-13, and E-14) 11    =  The decay constant for the i th radionuclide, in sec-1 Aw    -  The decay constant for removal of activity on leaf and plant surfaces by weathering, 5.73 E-7 sec-1 (corresponding to a 14 day half-life).

HoTE 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).

l

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O ATTACHMENT A (Page 48 of 184) y OFFSITE DOSE CALCULATION MANUAL ] [ Grass-Goat-Milk Pathway Factor, R g# [D/Q)

'A Ret (D /Q) = K'           F,(t)(DFLi ),(/Y,[i'fh8mrom/yr perpCi/ uc) l Where:

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

tg = The transport time from pasture to goat, to milk, to receptor, in sec, 1,73 E5 sec (2 days). (Reg. Guide 1.109, Table E-15). all other terms are defined under the Grass-Cow-Milk-Pathway l Factor. aW ! The fraction of the year that the goat is on pasture and the fraction of the goat feed that is pasture grass is assuaned to be 1.0, which is the most restrictive case. l The concentration of tritium in milk is based on the airborne concentration rather than the deposition. Therefore, the R Ci is based on (X/g), C R i[X/Q) = K'K" ' F Q,U,,(DFLi )).75 (0.5/H)hrem/yr per pCi/m') Where: K"' = a constant of unit conversion, 103 gm/Kg. H = Absolute humidity of the atmosphere, 8 gm/m' (Reg. Guide 1.109) . 0.75 = The fraction of total feed that is water. (NUREG 0133) 0.5 = The ratio of the specific activity of the feed grass water to the atmospheric water. (NUREG 0133)

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O ATTACHMENT A

@                                            (Page 49 of 184)

N OFFSITE DOSE CALCULATION MANUAL .M

Grass-Cow-Meat Pathway Factor, RM i[D/Q) N b R"'[D/ Q) = K' P,(r) (DFLi ),(/Y,[i'f{m* mrem / yr per mci / sec) Where: Fg = 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 is based on (X/Q) : R"i[X/Q) = K'K" ' F,Q,U,,(DFL i ),p.75 (0.$/H))hlyr per pCi/m') Where: All terms defined above. Vegetation Pathway Factor, RVg[p/g)

         -Man is considered to consume two types of vegetation (fresh and stored) that differs only in the time period between harvest and consumption, therefore:

Ri [D / Q]= K' (DFL;),f'.ff k*i'L)+h8.{f,[*i'h)f8 t x mrem / yr per pCi/ sec) Where: l K' = A constant of unit conversion, 106 pCi/pCi. i b

Ravision 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 Reference Use- Page 54 of 188 g l 0 ,

ATTACHMENT A J (Page 50 of 184) i OFFSITE DOSE CALCULATION MANUAL , u UaL = The consumption rate of fresh leafy vegetation h by the receptor in age group (a) , in kg/yr. (Reg. Guide f tr 1.10S', Table E-5) . i Infant = 0 kg/yr l Child = 26 kg/yr Teen a 42 kg/yr j Adult = 64 kg/yr l l S Ua = The consumption rate of stored vegetation by the receptor in age group (a), Kg/yr. (Reg. Guide 1.109, Table E-5). Infant = 0 kg/yr Child - 520 kg/yr Teen = 630 kg/yr Adult = 520 kg/yr i fL = The fraction of the annual intake of fresh leafy vegetation grown locally. (default = 1.0) (Reg Guide ' 1.109). , fg - The fraction of the annual intake of stored vegetation grown locally (default = 0.76) (Reg. Guide 1.109). tL - The average time between harvest of leafy vegetation and its consumption, in seconds, 8.6 E4 sec (1 day). (Reg. Guide 1.109). th = The average time between harvest of stored vegetation and its consumption, in seconds, 5.18 E6 sec (60 days) (Reg. Guide 1.109, Table E-15). Yy = The vegetation area density, 2.0 kg/m2, (geg, Guide 1.109, Table E-15). All other factors previously defined.

 $                                                                                                l 1

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 ,                                        ATTACHMENT A I                                      (Page 51 of 184)

E OFFSITE DOSE CALCULATION MANUAL b C The concentration of tritium in vegetation is based on the f A airborne concentration rather than the deposition. Therefore, the T?#1 i; bloed on (X/Q) : R*i(X/Q] = K'K" ' [U'.fo + Us.f DFLa),@.75 (0.5/H)K=r ='rra rnci'=') I Where: !. All terms defined previously. All values indicated are default , values from Reg. Guide 1.109, Rev. 1. An average monthly dose schedule should be setup to ensure ; Section 3.2.2 is not exceeded. The average monthly dose due to ) radiciodines, particulates, and other radionuclides which are ^ i included in this section should be as follows: ]

a. < 2.5 mrem /mo.

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

b. < 1.25 mrem /mo.

If the monthly average dose for (b) is exceeded, it should be noted that if the release is continued at the same (or higher) frequencies or activities the yearly limit of Section 3.2.2.b will be exceeded. If any of the above monthly doses are exceeded, evaluation of the causes should be performed and steps taken to reduce the

activity or frequency of the release.

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

a. 0.2 mrad to air from gamma radiation, or 3/91

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b. 0.4 tarad to air from beta radiation, or C .3 re u:.. to any organ of a MEMEEF. CF T;IE TULLIC.

3.3.1 Emmedial_ 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. 3/91 3.3.2 surveillance R.equirements 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 A - Cumulative dose for previous three months T = Number of days that the cumulative dose occurred in A above 12/95 3.3.2.2 The installed VENTILATION EXHAUST TREATMENT SYSTEM and WASTE GAS HOLDUP SYSTEM shall be considered OPERABLE by meeting Section 3.1 and 3.2 limits.

m 3 y Revision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 l g Roference Use Page 57 of 188 9 ATTACHMENT A l (Page 53 of 184) OFFSITE DOSE CALCULATION MANUAL g 3.4 Inntre antation j The radioactive g ccous ef f1.: ant monitoring instrunv.mtat tor, f channels shown in Table 3-2 shall be OPERABLE with their Alarm / Trip Setpoints set to ensure that the limits of Section 3.1 are not exceeded. The Alarm / Trip Setpoints of these l channels meeting Section 3.1 shall be determined and adjusted in ; accordance with the methodology and parameters of Section 3.4.4 ) below. l l 1 3.4.1 Remedial Action 1

a. With a radioactive gaseous effluent monitoring ;

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

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

3/91

N y Rnvision: 0 OFFSITE DOSE CALCULATION MANUAL AP 078-003 ROfGrenco U;o Page 58 of 188 ATTACHMENT A 8 er (Page 54 of 184) hj OFFSITE DOSE CALCULATION MANUAL M ~ TABLE 3-2 RADIOACTIVE GASIOUS EFFLUENT MONITORING INSTRUMENTATION 4 INSTRUMENT MitilliUM APELI.CABILITY ACTIQR ~3 CHANNELS OPERABLE

1. Unit Vent System

a. Noble Gas Activit'/ 1

40 Monitor - Providing Alarm (GT-RE-212)

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

43 l

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

43 l

d. Flow Rate N.A.

45

e. Sampler Flow Rate 1

39 Monitor

2. Containment Purge System

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

Tornination of Rolcase (GT-RE-22, GT-RE-33)

b. Flow Rate N.A.

45 l

3. Radwaste Building Vent System

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

Termination of Release:

(GH-RE-10B)

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

43 l

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

43 l

d. Flow Rate N.A.

45

e. Sampler Flow Rate Monitor 1

39 12/95
At all times.

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i TABLE 3-2 (continued) ) TABLE NOTATIONS i ACTION STATEMENTS l ACTION 38 - With the number of channels OPERABLE less than required by the q minimum channels OPERABLE requirement, the contents of the tank (s) may

be released to the environment for up to 14 days provided that prior l to initiating the release

+

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

l b. At least two technically qualified members of the facility j staff independently verify the release rate calculations and j discharge valve lineup. j Otherwise, suspend release of radioactive effluents via this pathway. I ACTION 39 - With the number of channels OPERABLE less than required by the i minimum channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided the flow rate is j

estimated at least once per 4 hours.

ACTION 40 - With the number of channels OPERABLE leno 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 J
at least once per 12 hours and these samples are analyzed for l radioactivity within 24 hours.

i' 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.
ACTION 43 - With the number of channels OPERABLE less than required by the j i minimum channels OPERABLE requirement, effluent releases via the j 4 affected pathway may continue for up to 30 days provided samples are ;

j continuously collected with auxiliary sample equipment as required in l g Table 3-1. j j ACTION 45 - Flow rate for this system shall be based on fan status and operating curves or actual measurements. 3/91 i i i s 1 , . . _ . . , . --

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   \
 ,j     Reference Use                                                             Page 60 of 188 e

ATTACHMENT A (Page 56 of 184)

    ,                                OFFSITE DOSE CALCULATION MANUAL
   )

T&BM. 3 .3. RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE WEOUIREMENTS

IFRTPl?FTC Cu?"TEL 'C'.TCn CMEL TIL^O l'^DEC._f'?ll CHECK QIECK CALIBRATION CHANNEL WHICH Ci OPERATIONAL SURVEILLANCE TEST IS REOUIRED

1. Unit Vent System 1

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

Providing Alam (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. *

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

2. Contairunent Purge System i

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

Providi.1g Alarm and Auto-matic Tertaination of Re-lease (GT-RE-22, GT-RE-33)

b. Iodine Campler W N.A. N.A. N.A.

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

c. N.A.

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

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

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.

3/93 e *At all times.

N R:vicion: O CRFSITE DOSE CALCULATION MANUAL AP 07B-003 I4 RSforencs U 0 Page 61 of 188 6 g ATTACHMENT A ik (Page 57 of 184) OFFSITE DOSE CALCULATION MANUAL g TABLE 3-3 (Continued) O TABLE NOTATIONS k ' .S (1) The ANALOG CHANNEL OPERATIONAL TEST shall also demonstrate that automatic if isolation of this pathway and control room alarm annunciation as appropriate occur if any of the following conditions exists:

a. Instrument indicates measured levels above the Alarm / Trip Setpoint (isolation and alann) , 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 OPERATIONAL TI:ST 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. Inutzu:aent indicates a do'.<nscale failure

d. Instrument controls not set in operate mode.

(3) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference (gas or liquid and solid) standards certified by the National Institute of Standards and Technology (NIST) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards shall permit calibrating the system over its intended range of energy, measurement range, and establish monitor responce 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 traceable to NIST. (4) If flow rate is determined by exhaust fan status and fan performance curves, the following surveillance operations shall be performed at least once per 18 months:

a. The specific vent flows by direct measurement, or

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

c. The fan motor horsepower measured and vent flow established by the fan's " flow-horsepower" curve. 3/91

Revision: 0 OFFSITE DOSE CALCUIATION MANUAL AP 07B-003 Rsforance U:s Page 62 of 188 ATTACHMENT A (Pege 58 of 184) OFFSITE DOSE CALCULATION MANUAL 3.4.3 Airhorne._Endiation._MorMor Calibration Methsdoirw v_ _ M The following monitors are associated with gaseou= releanan Monitor ID Monitor Description Monitor Tyne i 1 0-GT-RE-21A Plant Unit Vent Particulate, Iodine 0-cH-U.r-10A Radweste Building I:ffluent Particulate, Iodins O-GT-RE-21B Plant Unit Vent Wide Range Gas 0-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 l 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, 4 Cs-137, Cl 35, and Rh-10G. Each cource shall be positioned in the filter paper retaining ring and counted separately. The count rates for each radionuclide source shall be recorded and the data plotted on a graph of cpm /pci versus average beta energy. This curve represents the detectors response characteristics over the range of beta energies observed. The efficiency for setpoint calculations shall be based on the efficiency of the detector for Cs-137. 4 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

chall be produced using the counts per minute vs. concentration data. At least three sources covering approximately M, M, and X of full scale shall be checked. 5/.95 3.4.3.2 loMna 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.

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

'l  Referenca Use                                                                               Page 63 of 188 ATTACHMENT A h                                       (Page 59 of 184) k                            OFFSITE DOSE CALCULATION MANUAL Because of its short half-life and the difficulty in handling h(_        gaseous iodine, barium sources shall be used for calibration.

- hi The photo peake of interect are as follo.m:

-f

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

b. I-131: 364 kev gamma is 0.82 efficient / disintegration Therefore, 63ch iodine disintegration will produce 0.82/0.69 x barium disintegrations. Assuming that the detector efficiency for 356 kev is the same as for the 364 kev, the sensitivity for I-131 equals 1,19 x Ba-133 (counts / min) pCi. The standard sources shall be constructed by impregnating a standard Ba-133 solution into the charcoal filter element. The geometry shall simulate the iodine retention on the first surface-of the charcoal. Sources shall be prepared to cover approximately M, M and M of full scale. The barium counts per minute.for each standard shall be adjusted-to iodine counts per minute as described above. A determination of linearity shall be produced using the corrected counts per minute vs. concentration data.

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

Rsvision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 Rnforence Use Page 64 of 188 y ATTACHMENT A 1 (Page 60 of 184) k OFFSITE DOSE CALCULATION MANUAL b Sources for all gas detectors shall be produced by evacuating

  ;         the sample chamber with a vacuum pump.      The sample chamber then g            chall be backfilled t.o the desired pressure with a soarce of g-           standard Xc-133. The source is then counted and the counts per minute recorded. A determination of linearity shall be produced using'the counts per minute vs. concentration data. Sources shall be prepared to cover approxitaately L M and M of full scale for the detectors associated with monitors 0-GT-RE-22 and 33, 0-GT-RE-31 and 32 and the low-range detectors of monitors O-GT-RE-21B and 0-GH-RE-10B. Sources shall be prepared for the        .

mid/high range detecto'- to cover two points on the mid-range j scale. For ALARA purposes, response for the high-range scale l shall be extrapolated using the data from the mid-range calibration. 5/95 3.4.4 Airha-na h 4 tee s=*=aine= 3.4.4.1 Total modv nona mata se*=aine cateu1=tiaa-The limit of the total body dose rate is 500 mrem /yr at the unrestricted area boundary. The monitor alarm /tr.lp setpoint based on total body done will be calculated as follows: S. s (SF x AF)x D. x R, Where: Sb= t The monitors alarm / trip setpoint based on the total body dose rate. (pci/cc) NOTE If the anonitor setpoint units needed are (pci/sec), multiply l (pci/co) calculated setpoint by the waste gas stream flow rate ! (cc/sec). 12/95 Dtb = Limit of 500 mrem /yr total body, conservatively ; interpreted as a continuous release over a one year ; period.

R3 vision: 0 OFFSITE DOSE CALCULATION MANUAL AP 078-003 1

;I   Raforance Use                                            Page 65 of 188 ATTACHMENT A (Page 61 of 184)

(, OFFSITE DOSE CALCULATION MANUAL M

~~.                 SF =   Normally will be aet to 0.05. This number is chosen since the gaseous monitors are set using Xe-133

. 7 energy level, le-135 comprises 85% of Local noble I gaseous activity expected. (See USAR Table 11.1-1). If necessary the 0.85 can be further modified to compensate for statistical fluctuations and errors of measurement. AF = Allocation factor for each release so that simultaneous releases can be made without exceeding the limit. Normally AF is calculated as follows: AF - TF Where: RF = Release flow rate of the release point under consideration. TF = Total flow rate of all release points including i release under consideration. Rt= monitor response per mrem /yr to the total body, determined according to: R =, , i s(C/IQ)[K i Qi s Where: c= The monitor response to the gaseous effluent noble gas (pci/cc) corresponding to grab sample radionuclide concentrations. (X/Q) = The highest calculated annual average atmospheric dispersion (sec/m3 ) at the restricted area boundary. Ki- The total body dose factor due to gamma emissions from isotope 1 (mrem /yr per pCi/m3) from Table A.1-2.

Ravicion: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 R0forance U::e Fage 66 of 188

ATTACHMENT A (Page 62 of 184) OFFSITE DOSE CALCULATION MANUAL ~ Qi = Rate of release of noble gas radionuclide i ( Ci/sec) (concentration of radionuclide i x release flow rate) 3.4.4.2 Sk4n Dose Rate Calculation The limit of the skin doce rate is 3000 mrem /yr at ti.e restricted area boundary. The monitor alarm / trip setpoint is calculated as follows: S, s (SF x AF)x D, x R, Where: Ss- The monitors alarm / trip setpoint based on the skin dose rate. ( Ci/cc) NOTE If the monitor setpoint unita needed are (pci/aec), multiply the pCi/cc), calculated setpoint by the waste gas stream flow rate (cc/sec). 12/95 Ds = Limit of 3000 mrem /yr to the skin of the body, conservatively interpreted as a continuous release over a one year period. R g = Monitor response per mrem /yr to the skin of the body. R,=, , 3 i i s(X/Q)E(L i + 1.lM )Qi s Where: Li - Skin dose factor due to beta emissions from isotope 1 (mrem /yr per pCi/m3) from Table A.1-2. 1.1 - Conversion factor to mrem skin dose per mrad air dose.

R: vision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003

Rafaranca U23 Page 67 of 188 ATTACHMENT A

   ,                                (Page 63 of 184)

OFFSITE DOSE CALCULATION MANUAL

 ~.                    Mi- Air dose factor due to gamma emissions from isotope i (mrad /yr per pCi/m3) from Table A.1-2.

The factors SF, AF, c, (Y/d)andQiareasdefinedinSection 3.4.4.1. The results of equations from Sections 3.4.4.1 and 3.4,4.2 are compared to determine the smaller setpoint. The actual monitor setpoint is the lower of the two values. I 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 Batpoint calculations The Noble Gas Alert Alarm for the Plant Unit Vent (0-GT-RE-21) and Radwaste Building Exhaust Monitor (0-GH-RE-10), is set to alert operators to that averagc concer.traticn which if maintained for a full year would result in the 10 CFR 50, l Appendix I Annual Dose Guidelines being reached. Section 3.2.1 l limits the annual dose due to noble gases to s 10 mrads for gamma radiation and s 20 mrado for beta radiation. Section l l 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 l effluents to s 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 Noble Gas Alert Alarm Setpoint calculation The alert alarm setpoint is the lesser of Sys (SF x AF) x Dy x Ry S3s (SF x AF) x Dp x R Where: Sy = Monitor setpoint based on gamma radiation.

Rsvision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 Reference Use Page 68 of 188 ATTACHMENT A O (Page 64 of 184) i OFFSITE DOSE CALCULATION MANUAL Dy = Limit of 10 mrad /yr conservatively interpreted as l a continuous release over a one year period. j h Ry = Monitor response per mrad /yr determined according to: l R, = , 3 ) ! <NEM xQi t i > l Where i Mi = Gamma air dose factor (mrad /yr per pCi/m3), See Table A.1-2. Sp = Moni"or setpoint based on beta radiation. Dp = Limit of 20 mrad /yr conservatively interpreted as a continuous release over a one year period. Rg = Monitor response per mrad /yr determined according to: )

i R,=, . 3 l

                               .(X/QK,   Ni x Qi,                                             j Where:

l Ni = Beta air dose factor (mrad /yr per pCi/m3}, See Table A.1-2. j A semi-fixed alert alarm setpoint for the Plant Unit Vent l Monitor (0-GT-RE-21) and Radwaste Building Vent Monitor ! (0-GH-RE-10) is calculated using the following: (10 mrad / yrX.85)(AF) Setpo.m t ( Ci/ cc) = , 3 i (X / Q)[P, x M, x Q u i h where: Pi = Fractional value of isotope expected, Ci/C T'

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

i Reference Uro Page 69 of 188 ATTACHMENT A k (Page 65 of 184) OFFSITE DOSE CALCULATION MANUAL Where: Ci = Concentraticn in pCi/cc of isotope, h CT = Total Gaseous Activity from USAR Table 11.1-1 l AF = Either unit vent flow or Radwaste Building vent flow divided by the combined flow of the unit vent and Radwaste Building vent. 0 - Vent flow rate in ec/sec. ; Isotopes used and Pi values are as follows: ISOTOPE Ei l Kr-85M .018 Kr-87 .010 Kr-88 .033 Xe-133M .017 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 1=d Iodina Alarm Satuoints 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. m t(pCi/cc) = (MPC,)(AF)(SF) (oXxio) Where: MPCi - 5 x 10" pCi/cc for Cs-137

                           =    1 x 10" pCi/cc for I-131

F4 h R3vicion: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 9 ip,1 pRafGrcnc3 Uzo Page 70 of 188 9 ATTACHMENT A O (Page 66 of 184) OFFSITE DOSE CALCULATION MANUAL AF = as defined pr.cviously j SF = .0C.'5 for I-131 + f = .9375 for Cs-137 *

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

Q = Vent flow in M3/sec This will provide the hi alarm setpoint. The alert alarm setpoint is 10% of the hi alarm setpoint.

y Revision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 0 g R"Jference Use Page 71 of 188 9 ATTACHMENT A (Page 67 of 184) OFFSITE DOSE CALCULATION MAIRJAL EIGURE 3.1 BOUNDARY FOR GASEOUS EFFLUElffS D [

i l k h , t _m===

                                       .        1
           -'N.

i , L.e4 s 4Xc

                                                                              .-- y kya                   ~
                    . _ .                       s N     .

J e -- x g.4. a -.

                                                                           "8 4                               i                     h                    7-.
        ~:           _~                      .
                                                                                 ,,.i a 63ye um-l    '
                                                                                          ,. u
                                                                                   **a.aer 'er '***** ( 8'1-**u
                                                  -e# eagre samme e, at A > T \ --

_C,

                                =. .              . Q ~~gn
                              .                                                     _  L _.m-60 3/91

TF[ 1

)8 Revision: 0           OFFSITE DOSE CALCULATION MANUAL      AP 07B-003 t

g R3ference Use Page 72 of 188 6 ATTACHMENT A b (Page 68 of 104) OFFSITE DOSE CALCULATION MANUAL 0 g 4.0 Total Dose Thc' annual (Calendar year l doca cr doce ccmmitment t.o any !C'm l f OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the whole body or any organ, except the thyroid, which chall be limited to lecc than or equal to 75 mrems. l l 4.1 Rashadial Action With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Section 2.2a, 2.2b, 3.2.la, 3.2.lb, 3.2.2.a and 3.2.2b calculation should be made including direct radiation i 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 i 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 31rita. This opse3al 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. 3/91

M + Revision: 0 OFFSITE DOSE CALCUIATION MANUAL AP 07B-003 g R3ference Use Page 73 of 188 6' ATTACHMENT A (Page C9 of 184) OFFSITE DOSE CALCULATION MANUAL 2 4.2 surveillance Raauira= ants 4.2.1 Cuaulative donc centributions frcm liquid and gaceous cfflue:ita l g shall be determined in accordance with the methodology of Sections 2.2 and 3.2 at least once per 31 days when the release of radioactive materials in liquid or gaseous effluents exceed twice the limits of Section 2.2a, 2.2b, 3.2.la, 3.2.lb, 3.2.22 and 3.2.2b. Otherwise, no further evaluation is required.3/91 4.2.2 Cumulative dose contribution from direct radiation from the ' reactor unit and from Radwaste storage tanks shall be determined utilizing the results of routine plane perimeter surveys, TLD data or a combination of both, when necessary. This requirement is applicable only under conditions set forth in the remedial action above. 5.0 nadiological Envirnn==ntal unnitoring Program This section describes the Radiological Environmental Monitoring Program g specified in Section 6.8.4 F of the Wolf Creek Technical-Specifidations. 5.1 Manitorina Progrga Table 5-1 provides a schedule which describes the pathways, specific locatione, sample collection frequencies, and analyses to be performed to implement the Radiological Environmental Monitoring Program. Figures 5.1 through 5.5 contain maps depicting sampling locations in relation to the WCGS site. Table 5-2 lists distances and directions to these locations from the WCGS site. Table 5-3 lists required detection capabilities for the analyses performed. 3/92 i l

p Revision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 8 Reference Use g Page 74 of 188 ATTACHMENT A (Page 70 of 184) OFFSITE DOSE CALCULATION MANUAL 5.2 Land Uso census a

         .T Lan1 Sas C',n:uc shall bc cor.ucted   annually during the grovi..g f         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 WCCS sitc. Methods shall be used in conducting the census that provides 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. 3/91 If a location (s) is identified which yields a calculated dose or dose commitment (via the same exposure pathway) 20% greater than l at a location from which samples are currently being obtained, l the new location (s) shall be added to the Radiological Environmental Monitoring Program within 30 days as described in Table 5-1, Note (1). The indicator sampling location (s) having the lowest calculated dose or dose commitment may then be deleted from the monitoring program. The revision to Table 5-1 and the wrresponding rigure (s) as a result of cuch substitutions shall be documented in accordance with Section 6.14 of the Wolf Creek Technical Specifications.

The results of the Land Use Census shall be included in the Annual Radiological Environmental Operating Report described in Section 7.1. 5.3 Interlaboratory comnarison ProgIAM The analysis laboratory contracted to analyze samples from the Radiological Environmental Monitoring Program participates in the EPA Laboratory Intercomparison Program or similar program. 12/95

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

p Rsvicion: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 1 dP gp Rsforcnca U23 Page 75 of 188 i dP ATTACHMENT A dk (Page 71 of 184) f OFFSITE DOSE CALCULATION MANUAL b A summary of intercomparison results shall be included in the b Annual Radiological Environmental Operating Report described in

Section 7.1.

M V 5.4 Reportina Reauir===nts l I 5.4.1 annumi nadioloaieml Enviran==ntal operatina nanort To meet the requirements of Wolf Creek Technical Specification 6.9.1.6, the Annual Radiological Environmental Operating Report covering the previous year of operation shall be submitted to , the NRC by May 1 of each year. The content of this report is ! described in Section 7.1. 12/94 l . 5.4.2 Special Reports A special report shall be prepared and submitted to the NRC l within 30 days if levels of radioactivity as a result of plant I I 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 l
the cause(s) for exceeding the limit (s) and define the corrective actions to be taken to reduce radioactive eifluence so that the potential annual dose

to a member of the public is less than the calendar year limits of Wolf Creek Technical 4 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 l be submitted if: Concentration (1) + Concentration (2) +..>1.0 Reporting Level (1) Reporting Level (2) When radionuclides other than those in Table 5-4 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose

to a member of the public from all radionuclideo 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.                                                       3/91

Rsvision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 i Reference Use j Page 76 of 188 ATTACHMENT A B (Page 72 of 184)

    $  ,                              OFFSITE DOSE CALCULATION MANUAL                                          I TABLE 5-1

{y RADIOLOGICAL ENVIRONMEN1'AL MONITORING PROGRAM t

     %I      Fwn^mura Dat hway/     Numher of Samelam and          Ramn1m (%11ection     Type anA Frecuency h          g e Tvre             Samnle Loca t irm n (1)           Fre ern ene y           of Analysis

1. AIRBORNE FIGURES 5.1 & 5.5 Radiciodius and Samples troia five locations Continuuus sarapler Analyze radioacdAne Particulates operation with canister weekly for sample collection I-131 weekly, or more fre-quently if required ;

by dust loading Sar?les from locations near the site boundary in three sectors having the highest calculated annual average D/Q (locations 2,3 & 37 on Figure 5.1); 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 quar-Figure 5.1, New Strawn); terly gamma isotopic analysis (3) compo-site (by location). Sample from a control location 10-20 miles dis-tant in a low D/0 sector (Location 40 on Figure 5.5). (11) i

2. DIRECT FIGURES 5.2 AND 5.5 RADIATION (4) 4 40 routine monitoring sta- Quarterly Gamma dose quarterly

! tions with two or more i dosimeters measuring dose } continuously, placed as followat i An inner ring of stations, 4 one in each meteorological sector 0-3 mile range from the site (Locations 1,7-i 9,11-13, 18, 26, 27, 29-31, 22/fd i 37, & 3B on Figure 5.2). 4

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   }                          RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM i   punamura path,av/        Numher of Ramelen anA                  Ammnle collection        Tvne M Frecrimnry

[ samnie Tvne gggt l e Locatinna (1) Frernmn cy ' ' of ana!_. gig DIRECT RADIATION An outer ring of stations, (4) (CONTINUED) one in each meteorological j sector in the 3 to 5 mile ' range from the site (Loca-tions 4-6, 15-17, 19-25, and 33-36 on Figure 5.2) . Five sectors (A,B,D,0 & L) contain an additional sta- I tion (Locations 2,3,10, 14 and 28) 22/H ) The balance of the stations to be placed in special interest areas such as

population centers (Loca-4 tions 23 and 32), nearby 1

residences (many locations are near a residence), schools (Location 23), and in one or two areas to serve as control stations 10-20 miles distant frem the site (Locations 39 and 40 on Figure 5.5) (11) a

3, WATERBORNE FIGURE 5.3 i Surface One sample upstream (5) Monthly grab sample Monthly gamma iso-l (Location MUSH on Figure topic analysis (3) l 5.3) and one rample down- and composite for stream (Location DC on tritium analysis Figure 5.3) quarterly.

3 Ground Samples from one or two Quarterly Quarterly gamma sources only if likely to isotopic analysis be affected (3) and tritium analysis.

;                           Indicator samples at loca.

tions hydrologically down-

,                           gradient cf the site (Loc.a-tions C-10, C-49 and D-65 on Figure 5.3); control sample at a location hydro-logically upgradient of the site (Location B-12 on Figure 5.3) (6)

TW

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ATTACHMENT A

'M (Pare 74 of 184)

OFFSITE DOSE CALCULATION MANUAL M TABLE 5-1 (Continued) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MI evnemura

pathwav/ Nn=har of cm-nies and samnie collection

Tyne and Precua n t-v

~~

-[ samnie Tvns nannie Lormeinns iH Exequency of an=1ysie

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

Drinking location downstream oi the and gross beca site (Location LW-40 on analysis of compo-Figure 5.5); control sample site sample. from location upstream of Quarterly tritium the site (Location BW-15 on analysis of Figure 5.3) composites (8). Shoreline Sediment one sample from the vic- Semiannually Semiannual gamma inity of Wolf creek Cooling isotopic analysis Lake discharge cove (Loca- (3) tion DC on Figure 5.3); control sample from John Redmond Reservoir. 11/fd

4. INGESTION FIGURES 5.4 AND 5.5 Milk Samples from milking Semimonthly while Gamma isotopic j animals at three indicator animals are on analysis (3) and I. '

locations within 5 miles of pasture (April to 131 analysis of each the site having the highest Novamber); monthly sample, , dose potential (currently at other times j there are no locations pro- (December-March) (9) ducing milk for human con- j sumption within 5 miles of l the site);one sample from a control location greater than 10 miles from the site . (Location S-3 on Figure 5.5). (11) Pish Indicator samples of 1 to 3 Semiannually Gamma isotopic recreationally important analysis (3) on species from Wolf Creek edible portions cooling Lake (several samp-ling areas indicated in Figure 5.4); control sam-ples of similar species from John Redmond Reservoir Spillway (indicated on Figure 5.4).

w 'N g) Rovialon: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 0 m Reference Use Page 79 of 188 O ATTACHMENT A 0 (Page 75 of 184) kl g OFFSITE DOSE CALCULATION MANUAL N TABLE 5-1 (Continued) M RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

d* Fvnomure Pathwav/ Simber of Emmnlem and Ammnie Collection Tyne and Fracrimne v ,v nnn-nle Tvna samnie incations (1) Fre mm nc v of Analysis 4 INGESTION Sanples of available Monthly when Gamma isotopic (CONT.) broadleaf vegetation from available (9) analysis (3) on rood Products two indicatur locationa edible portions, with highest calculated annual average D/Q (Loca-tions K-1 and G 1 and alternate Location C-1 on Figure 5.4); sample of similar broadleaf vegeta-tion from a control loca. tion greater than 10 miles from the site in a low D/O section (Location S-4 on 12/S5 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 down-stream 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). i

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OFFSITE DOSE CALCULATION MANUAL TABLE 5-1 (Continued)' TABLE NOTATIONS (1) Deviations are permitted from the required sanspling ' schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment, and other legitimate reasons. If specimens are unobtainable due to sampling equipment malfunction, every effort shall be made to complete corrective action prior to the end of the next sampling period. All deviations from the sampling schedule shall be documented in the-Annual Radiological Environmental Operating Report described in Section 7.1. It is recognized that, at times, it may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time. In these instances, suitabic specific alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days. Revisions to this Table and to the corresponding Figure (s) as a result of such substitutions shall be documented in accordance with section 6.14 of Wolf Creek Technical Specifications. This documentation shall ! provide information identifying the cause of the unavailability of ) samples for that pathway and justifying the selection of the new location (s) for obcaining samples. (2) Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours or more after sampling to allow for RN-220 and Rn-222 daughter decay. If gross beta activity in air particulate samples are greater than 10 times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples. (3) Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility. (4) One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place , of, or in addition to, integrating dosimeters. For the purposes of this table, a thermoluminescent dosimeter (TLD) is considered to be one phosphori 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 optimum dose information with minimal fading. 3/A2

h g R vision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 g ROforanc3 Uza page 81 of 188 ATTACHMENT A O (Page 77 of 194) f OFFSITE DOSE CALCULATION MANUAL M TABLR 5-1 (Contfnued) i TABLE NOTATIONS I M T (5) The

upstream" sample is taken at a distance beyond significant .

influence of the discharge. l (6) Ground water samples shall be taken when this source is tapped for drinking or irrigation purposes in ar.eas where the hydraulie gradienu 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 to assure obtaining a representative sample. (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 smrple enllection timer Alternate sampling locations may therefore be listed in the Table and used at these times to provide continued monitoring of these pathways. If samples are considered permanently unavailable at a location, another location will be selected (if available) as described in Note (1). (10) If harvest occurs more than once a year, sampling shall be performed during each discrete harvest. If harvest occurs continuously, sampling shall be monthly. Attention shall be paid to including samples of tuberous and root food products. (11) The purpose of this sample is to obtain background information. If it is not practical to establish control locations in accordance with the distance and wind direction criteria, other sites that provide valid background data may be substituted. 3/91

4 - Ravicion: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 Roforcnca Uzo itq Page 82 of 188 S ATTACHMENT A y (Page 78 of 184) OFFSITE DOSE CALCULATION MANUAL -I TABI E 5-2 fT SAMPLING LOCATION NUMBERS, DISTANCES (miles) AND DIRECTIONS

ail? articulate O Location Distance / [ N11mher Directic_n 2 2.7/N 3 3. 0/NtTE 32 3.2/WNW 37 2.1/NNW 40 >15.0/WNW

     .TLD Location Distance / Logaj;1on Disennen/       Location Distance / Location Distance /

1himber Direction Number Direction Nitmher 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/SE 24 4.1/WSW 34 4.0/NW 5 4.0/NE 15 4.5/ESE 25 3.6/W 35 4.6/NNW 6 4.4/ENE 16 4.2/E 26 2.6/WSW 36 4.2/N 7 1.9/NE 17 3.6/SE 27 2.1/SW 37 2.1/NNW 8 1.6/NNE 18 3.0/SSE 28 2.8/SW 38 1.2/NW l 9 2.0/ENE 19 4.0/SSE 29 2.6/SSW 39 13.0/N 10 2.4/ENE 20 3.3/S 30 2.2/W 40 >15.0/WNW Groundwater Drinkino Water Surface Water B-12 2.2/NNE BW-15 3.9/SW MUSH 3.6/W C-10 2.8/W LW-40 >10/SSE DC 0.6/WNW C-49 2.9/SW D-65 3.9/S Milk & Pond Products C-1 2.6/NE R-1 2.1/NNW G-1 1.6/SE S-3 >15.0/WNW l S-4 >15.0/WNW Fish Ahoreline sedimentn Trriented crope WCCL DC 0.6/WNW NR-D1 9.2/S l JRR 4/W JRR 4/W NR-D2 >10/S 12/9E

. ,. _ . _ . - . -- - -- - - . .= Ravisions' O OFFSITE DOSE CALCULATION MANUAL AP 07B-003

1 Raforcnca Ure Page 83 of 188 ATTACHMENT A (Page 79 of 184) OFFSITE DOSE CALCULATION MANUAL b T&pLE 5-3 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS

Lower Limit of Detection (LLD)

( AIRBORNE SEDIMENT PARTICULATE FOOD (pCi/kg, WATER OR GAS FISH MILK PRODUCTS dry) ANALYSIS (pCi/1) (pC1/m3 ) (pCi/kg, wet) (pCi/1) (pCi/kg, wet) Gross Beta 4 0.01 H-3 2000(4) Mn-54 15 130 l Fe-59 30 260 Co-58,60 15 130 Zn-65 30 260 Zr-Nb-95 15 I-131 1(5) 0.07 1 60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-La-140 15 15 3/s2

1

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OFFSITE DOSE CALCULATION MANUAL 1 TABLE 5-3 (Continued) TABLE NOTATIONS ' h)

(1) This list does not mean that only these nuclides are to be considered. other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report described in Section 7.1. (2) Required detection capabilities for thermoluminescent dosimeters used for environmental measurements shall be in accordance with the ! recommendations of Regulatory Guide 4.13, Revision 1, 1977. (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 95t probability with only 5% probability of falsely concluding that a blank observation represents a 'real" signal. For a particular measurement system, which may include radiochemical separation: 4.66 s6 LLD = E V 2.22 Y exp (-A At) Where LLD = the 'a priori" lower limit of detection (picoCuries per unit mass or volume), Sb = the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counta per minute), E = the counting efficiency (counts per disintegration), V = the sample size (units of mass or volume), j 2.22 = the number of disintegrations per minute por picocurie, Y = the fractional radiochemical yield, when applicable, A = the radioactive decay constant for the particular radionuclide (s-1) , and 3/93

) R vision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 S g Reference Use page 85 of 188 6 ATTACHMElff A (Page 81 of 184) 4 OFFSITE DOSE CALCULATION MANUAL TABLE 5-3 (Continued) N TABLE NOTATIONS \\ .d g.- At = the elapsed time between sample collection, or end of the sample collection period, and time of counting (s). Typical values of E, V, Y, and At should be used in the calculation. It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement. Analyses shall be performed in such a manner that the 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. (4) LLD for drinking water samples. If no drinking water pathway exists, a value of 3000 pCi/ liter may be used. (5) LLD for drinking water samples. If no drinking water pathway exists, the LLE of gan.u isotupic analysia may be used. S/M.

5 h Revision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 e g Roforence Uso Page 86 of 188 0 ATTACHMENT A ; O (Page 82 of 184) OFFSITE DOSE CALCULATION MANUAL TABLE 5-4 M REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES \\ h AIRBORNE FOOD WATER PARTICULATE OR FISH MILK PRODUCTS ; ANALYSIS (pCi/l) GAS (pCi/m') (pCi/kg, wet) (pCi/1) (pCi/kg, wet) H-3 20,000* l 1 Mn-54 1,000 30,000

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

    *For drinking water samples. This is 40 CFR Part 141 value. If no drinking water pathway exists, a value of 30,000 pCi/l may be used.                           3/91 i

l

R vision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 R3forcncD Uma Page 87 of 188 ATTACHMENT A g (Page 83 of 184) OFFSITE DOSE CALCULATION MANUAL Y_

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Rsvision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 1 R3farenca Use Page 89 of 188

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Rsvision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 f) M Referenco Use Page 90 of 187

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b 4 y Revision? 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 g Reference Ure Page 91 of 188

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M ? _- p Rovicion: 0 OFFSITE DOSE CALCULATION MANUAL AP 078-003 O Rcforenca Ura Page 92 of 188 ATTACHMENT A O (Page 88 of 184) OFFSITE DOSE CALCULATION MANUAL 6.0 Bases x l t The bases contained on the succeeding pages summarizes rho ' f general requirements of Section 2.0, 3.0, 4.0 and 5.0 of the ODCM. Section 2.0 Licuid 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 bodiec of water in UNRESTRICTED AREAS will result in exposurea within: (1) the Section II. A design , objective of Appendly I, 10 CFR Part 50, to a MEMBER OF THE l 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 detection limits can be found in HASL Procedures Manual, RASL-3DA (revised annually), currie, L.A., " Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry," Anal. Chem. 4 0. , 586-93 (1968), and Hartwell, J.K., " Detection Limits for Radioanalytical Counting Techniques,

          " Atlantic Richfield Hanford Company Report ARM-SA-215 (June
                                                                                )

1975). 3/92 , 1

R2 vision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 ;

g. Reference Use Page 93 of 188 0 .

t ATTACHMENT A k (Page 89 of 184) OFFSITE DOSE CALCULATION MANUAL u gestion 2.2 Dome This section is provided to implement the requirements of f Section II.A, III.A and IV.A of Appendix I, 10 CFR Part 50. The remedial action implements the guides set forth in Section II.A , of Appendix I and provides the required operating flexibility 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 I

          *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 doce 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        l equaticne spccificd in the ODO for calculating the deses due ta     1 the actual release rates of radioactive materials in liquid offluents are consistent with time methodology provided in          i Regulatory Guide 1.109, " Calculation of Annual Doses to Man from   l 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 Dippersion of Effluents from Accidental and Routine Reactor Roleases for the Purpose of Implementing Appendix I," April 1977.                                                        3/92   '

i

g Rnviolon: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 4 i N g R3for nca U:s Page 94 of 188 ATTACHMENT A i O (Page 90 of 184) OFFSITE DOSE CALCULATION MANUAL Section 2.3 Lirruid Radwante 'freaF==n t System j The OPERABILITY of the Liquid Radwasta Treatment Eyctema enuntaa y that this system will be available for use whenever liquid effluents require treatment prior to release to the environment. The requirement that the appropriate portions of this system be used when specified provides assurnnce that the releases of i radioactive materials in liquid effluents will be kept *as low as , is reasonably achieveable." This section implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 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 j l 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 Llauld Effluent Monitoring Instrumantation 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 reqcirements of General Design Criteria 60, j 63, and 64 of Appendix A to 10 CFR Part 50. 3/92 i l l l

p Ravicion: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 8 Reference Use g Page 95 of 188 i 9 ' ATTACHMENT A O (Page 91 of 184) OFFSITE DOSE CALCULATION MANUAL B Section 3.0 Gaseous Effluenta y scetien 1.1 rone nata 6 I This section is provided to ensure that the dose at any time at and beyond the SITE BOUNDARY from gaseous effluents from all i units on the site will be within the annual dose limitF 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 ct 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, RASL-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 ARM-SA-215 (June 1975). 3/92

 > Ravision: 0          OFFSITE DOSE CALCULATION MANUAL        AP 07B-003 Reference Use                                            Page 96 of 188 6

ATTACRMENT A O (Page 92 of 184) OFFSITE DOSE CALCULATION MANUAL ~ Section 3.2.1 Dome - Noble Cases y This coction ic provided to imple:.mnt the requiremonta uf 8' Section II.B, III.A and IV.A of Appendix I, 10 CFR Part 50. The remedial action implements the guides set forth in Section II.B of Appendix I and provides the required operating flexibility and at the came time implement the guidec 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 curveillance 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 '- CFR Part 50, Appendix 1," Revision 1, October 1977 and Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors," Revision 1, July 1977. The ODCM equations provided for determining the air doses at and beyond the SITE BOUNDARY are based upon either the historical average or real time atmospheric conditions. 3/91

Ravicion: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 R3forencs Uno Page 97 of 188 ATTACHMENT A (Page 93 of 184) OFFSITE DOSE CALCULATION MANUAL O Section 3.2.2 Dome - Todine-131 and 133. Tritium med Radioactive Material in Particulate Form 4 This section is provided t. .oplement the requirements of 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 Appendix I, and prov3de the reautred 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 Releason of Reactor Effluents for the Pirpece 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 subacquant cossumption by man, (3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, (4) deposition on the ground with subsequent exposure of man. 3/92

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

  &  R2forence Use gi                                                                Page 98 of 188 6'

ATTACHMENT A (Page 94 of 184) OFFSITE DOSE CALCULATION MANUAL '~IS Section 3.3 Ganeous Radwasta Treme==nt System

'f3 The OPEP. ABILITY of the WP.STE GAS I!OLDUP SYSTEM and the g         VENTILATION EXHAUST TREATMENT SYSTEM ensures that the systems will be available for use whenever gaseous effluents require l            treatment prior to release to the environment.          The requirement that the appropriate portions of thic system be used when specified provides reasonable assurance that the releases of l

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 Radioactiva ammeone Effluent Monitorina_ Tnatrn=antation The radioactive gaseous effluent instrumentation is previded 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 Ci/cc are measurable. 3/92

p R3vicion: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 R3ferCnca U:0 Page 99 of 188 ATTACHMENT A O (Page 95 of 184) OFFSITE DOSE CALCULATION MANUAL Section 4.0 Total Dgag

 ,        Thin section 39 providad te mnet the dose ?imitatirra of CO C"".

f Part 190 that have been incorporated into 10 CFR Part 20 by 46 FR 18525. The section requires the preparation and submittal of a special report whenever the calculated doses due to releases l of radicactivity and the radiation from urenium 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 the 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 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 olhar 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 CPR Part 20. An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle. 3/92

  > Revision: 0          OFFSITE DOSE CALCULATION MANUAL        AP 07B-003 Reference Use                                            Page 100 of 188 i

ATTACHMENT A (Page 96 of 184) OFFSITE DOSE CALCULATION MANUAL I C Section 5.0 mmdiolocical Enviran=="tal Manitorina Proaram I h{ , h; Otet'en 5.1 M5nitoring P?tgram h? l The Radiological Environmental Monitoring Program provides representative measurements of radiation and of radioactive rater 3als in those exposure pathways and for those radionuclidas l that lead to the highest potential radiation exposures of i MEMBERS OF THE PUBLIC resulting from the station operation. l This monitoring program implements Section IV.B.2 of Appendix I to 10 CFR Part 50 and thereby supplements the Radiological Effluent Monitoring Program by verifying that the measurable concentrations of radioactive materials and levels of radiation l are not higher than expected on the basis of the effluent measurements and the modeling of the envir", ntal exposure pathways. Guidance for this monitoring agram is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring, Revision 1, November 1979. The required detection capabilities for environmental sample analyses are tabulated in terms of the lower limits of detection (LLDs). Tha LLDs are considered optimum for routine environmental measurements in industrial laboratories. 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. Detailed discussion of the LLD, and other detection limits, can be found in HASL Procedures Manual, RASL-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). 3/92

Revision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 q RafGrcnca Uso Page 101 of 188 i ATTACHMENT A (Page 97 of 184)

  ,                        OFFSITE DOSE CALCULATION MANUAL
 -)        section 5.2 r. nA Uma cannum                                              ,

This section la provided to ensure that chan37.s in the ucc cf f areas at and beyond the SITE BOUNDARY are. identified and that modifications to the Radiological Environmental Monitoring ' Program given in the ODCM are made if required by the results of this census. Information that will provide LSc beat results, such as door-to-door survey, aerial survey, or consulting with local agricultural authorities, shall be used. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 i CFR Part 50. Restricting the census to gardens of greater than 50 m2 provides assurance that significant exposure pathways via l leafy vegetables will be identified and monitored since a garden j of this size is the minimum required to produce the quantity (26 kg/ year) of leafy vegetables assume in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were made (1) 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and (2) a vegetation yield of 2 kg/m 2, Section 5.3 Interl=Mratory Camnarison Proar== The requirement for participation in an approved Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are valid for the purposes of Section IV.B.2 of Appendix I to 10 CFR Part 50, 3/92

N' ,I g; R; vision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 L9 gi Reference Use Page 102 of 188 l gy l ATTACHMElff A l dh (Page 90 of 184) l OFFSITE DOSE CALCULATION MANUAL hJ

   ,.0    Renorts 7.1    Annuni Radio 1rgical Environwontal octrating n:gort               l The Annual Radiological Environmental Operating Report shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental eurveillance activities for the report period, including a comparison with preoperational studies, with operational controls and with previous environmental surveillance reports, and an assessment of the observed impacts of the plant operation on the environment. The reports shall also include the results of the Land Use Census described in Section 5.2.

The Annual Radiological Environmental Operating Report shull include the results of analysis of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in Table 5-1 as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Fevicion 3, Movember 1979. In the event that ecco individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report. The reports shall also include the following: a summary description of the Radiological Environmental Monitoring Program; legible maps covering all sampling locations keyed to a table giving distances and directions from the centerline of the reactor; the results of licensee participation in the Interlaboratory Comparison Program and the corrective actions being taken if the specified program is not being performed as required by Section 5.3; reasons for not conducting the Radiological Environmental Program as required by Section 5.1 with plans for preventing a recurrence and discussion of all deviations from the sampling schedule of Table 5-1; discussion of environmental sample measurements that exceed the reporting levels of Table 5-4 but are not the result of plant effluents, and discussions of all analyses in which the LLD required by Table 5-3 was not achievable.

Rovision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 S R3farsncs Usa gp Page 103 of 188 0 ATTACHMENT A EI . (Page 99 of 184) OFFSITE DOSE CALCULATION MANUAL 1"nuni nadioactiva Effin=nt 2minana Rapart 7.2 ' l , jp Tre Annual Radioactiva Effluent E21cas2 T.; pert shell inclu'- ' ' gr summary of the quantities of radioactive liquid and gaseous I effluents and solid waste released from the Unit as outlined in f Regulatory Guide 1.21, " Measuring, Evaluating, and Reporting.

Radioactivity in Solid Wactes and Releases of Radioactive l

, Materials in Liquid and Gaseous Effluents from Light water-i Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof. For solid wastes, the format for Table 3 in Appendix { B shall be supplemented with three additional categories: class ;

of solid waste (as defined by 10 CFR Part 60), type of container I i (e.g., LSA, Type A, Type B, Large Quantity), and SOLIDIFICATION l agent or absorbent (e.g., cement, urea formaldehyde). 9/93 i

The Annual Radioactive Effluent Release Report to be submitted before May 1 of each year shall also include a'n annual summary i of hourly meteorological data collected over the previous year. i- This annual summary may be either in the form of an hour-by-hour i listing on magnetic tape of wind epced, wind direction, and i atmospheric stability, and precipitation (if measured) , or in j 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 j location, shall be included in these reports. Historical average meteorological conditions or the meteorological conditions cone ;ent with the time of release of radioactive materials in Octaous effluents, as determined by sampling frequency and measurement, shall be used for determining the gaseous pathway doses. The assessment of radiation doses shall be performed in accordance with the methodology and parameters in the ODCM. 12/95 4

1

Revision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 Reference Use Page 104 of 188 ATTACHMENT A k (Page 100 of 184) J {D OFFSITE DOSE CALCULATION MANUAL ( The Annual Radioactive Effluent Release Report to be submi+ ~1 fj before May 1 of each year shall also include an assessment of radiatica dcses to the likely most exposed MEMBER OF Th3 PUBL1C f from reactor releases and other nearby uranium fuel cycle sources, including doses from primary effluent pathways and direct radiation, for the previous calendar year to show ccaformance with 40 CFR Part 190, " Environmental Radiation Protection Standards for N uclear Power Operation." Acceptable-methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev. 1, October 1977. The Annual Radioactive Effluent Release Report shall include: . 9/93

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

          *In lieu of submission with the Annual Radioactive Effluent             l Felease Report, the. licencee has the option cf retaining this summary of required meteorological data on site in a file that shall be provided to the NRC upon request.                      S/93

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

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

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

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

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

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4) An evaluation of'the change which shows the-
{

[ i predicted releases of radioactive materials in j liquid and gaaecut. eriluenca and/or quantity of ,f solid waste that differ from those previously predicted in the license application and amendments ! thereto; 4

5) An evaluation of the change, which shows the l I

expected maximum exposures to a MEMBER OF THE , PUBLIC in tha UNRESTRICTED AREA and to the general ] population that differ from those previously i estimated in the license application and amendments thereto;

6) A comparison of the predicted releases of j radioactive materials, in liquid and gaseous j' j 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 calcuh tions identified by the Land Use Census,; e. A description of the events leading to liquid holdup tanks or gas storage tanks exceeding the limits of Technical Specification 3.11.1.4 or 3.11.2.6 respectively.; f. An explanation as to why the inoperability of a liquid or gaseous effluent monitoring instrumentation was not corrected within the time specified.; g. A description of the events leading to a missed sample required by Table 2-1 or 3-1.

1 m Revision: 0 OFFSITE DOSE CALCUIATION MANUAL AP 07B-003 2 pg R3forence Una Page 106 of 188 O ATTACHMENT A (Page 102 of 184) g OFFSITE DOSE CALCULATION MANUAL M 4J

2 W i l APPENDIX A Dose Conversion Factor Tables I I

w Y p Rovision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 dE f{l Reference Use Page 107 of 188 0. ATTACHMENT A (Page 103 of 184) OFFSITE DOSE CALCULATION MANUAL h TAnr.E A.1 18 A ninAcetman.aTrom FAcrona To nr usan In -} g T:!E r.nsrice er sTTr-corrrrTrn nr.TA (pci/kg per pCi/ liter) ELEMENT FRESHWATER FISH H 9.0E-01 C 4.6E 03 Na 1.0E 02 P 1.0E 05 Cr 2.0E 02 Mn 4.0E 02 Fe 1.0E 02 Co 5.0E 01 Ni 1.0E 02 Cu 5.0E 01 Zn 2.0E 03 Br 4.2E 02 Rb 2.0E 03 Sr 3.0E 01 Y 2.5E 01 Zr 3.3E 00 Nb 3.0E 04 Mo 1.0E 01 Tc 1.5E 01 Ru 1.0E 01 Rh 1.0E 01 Te 4.0E 02 I 1.5E 01 Cs 2.0E 03 Ba 4.0E 00 La 2.5E 01 Ce 1.0E 00 Pr 2.5E 01 Nd 2.5E 01 i W- 1.2E 03 Np 1.0E 01

                                 **Ag                     2.3E 00
                                 **Sb                     1.0E 00 0

Taken from Regulatory Guide 1.109 (Rev.1)

           ** Taken from Regulatory Guide 1.109 (Rev. 0) i

w 3 y Revision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 pp Raforenco Une Page 108 of 188 0 * .D ATTACHMENT A g (Page 104 of 184) g OFFSITE DOSE CALCULATION MANUAL n y TARTR A.1-2 g DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS *

;    ET*frmi l td?
       -              . Tral _2ct      SMa no ~ ** * ~-  O m a tir        n :1 Cr y                    Dose Factor              Lg        Dome Factor     Dose Factor (mram/vr ner Eg                                Mi              N.

A (mram/vr ner ci/mli fmrad/vr oer fmrad/vr ner pci/m 2 y peg j,11 gggggl y 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-30 1.47E+04 2.37E+03 1.S2E404 2.93E+03 Kr-89 1.66E+04 1.01E+04 1.73E+04 1.06E+04 Kr-90 1.56E+04 7.29E+03 1.63E+04 7.83E+03 Xe-131M 9.15E+01 4.76E+02 1.56E+02 1.11E+03 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 7.11S+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)

    **7.56E-02 = 7.56 x 10 ~3 l

'W7 , p Revision::0 OFFSITE DOSE CALCUI.ATION MANUAL AP 07B-003 pp Rafaranca Uso Page 109 of 188 ATTACHMENT A W (Pacte 105 of 184) 4 OFFSITE DOSE CALCULATION MANUAL TABLE A.2-1* INHALATION DOSE FACTORS FOR ADULTS h (MREM PER PCI INHALED) 8 f NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI H 3 NO DATA 1.58E-07 1.585-07 1.5SE-07 1.58E-07 1.585-07 1.58E-07 C 14 2.27E-06 4.26E-07 4.265-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 NA 24 1.28H-06 1.295-06 1.2CS 05 1.28E-0C 1.222-C5 1.283-05 1."CR 06 P 32 1.65E-04 9.64E-06 6.26E-06 NO DATA NO DATA NO DATA 1.08E-05 i CR 51 NO DATA NO DATA 1.25E-08 7.44E-09 2.85E-09 1.80E-06 4.15E-07 PN 54 NO DATA 4.95E-06 7.87E-07 NO DATA 1.23E-06 1.75E-04 9.67E-0G NN 56 NO DATA 1.55E-10 2.29E-11 NO DATA 1.63E-10 1.188-06 2.53E-06 FE- 55 3.078-06 2.128-06 4.93E-07 NO DATA NO DATA 9.015-06 7.54E-07 FE 59 1.47E-06 3.47E-06 1.32E-06 NO DATA NO DATA 1.27E-04 2.35E-05 CO 58 NO DATA 1.98E-07 2.593-07 NO DATA liO DATA 1.1GE-04 1. 33 E-O t; 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 l NI 65 1.92E-10 2.62E-11 1.14E-11 NO DATA NO DATA 7.00E-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 1.295-05 5.82E-06 NO DATA 8.62E-06 1.08E-04 6.68E-06 ZN 69 4.23E-12 8.145-12 5.65E-13 NO DATA 5.275-12 1.15E-07 2.04E-09 I BR R3 NO DATA NO DATA 3.01E-08 NO DATA NO DATA NO DATA 2 . 90 E- 08t 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 2.00E-06 RB 88 NO DATA ~4.84E-00 2.41E-06 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 7.625-04 NO DATA NO DATA 1.20E-03 9.02M-05 SR 91 7.74E-09 NO DATA 3.13E-10 NO DATA NO DATA 4.56E-06 2.39E-05 SR 92 8.43E-10 NO DATA 3.64E-11 NO DATA NO DATA 2.06E-06 5.38E-06 Y 90 2.61E-07 NO DATA 7.01E-09 NO DATA NO DATA 2.12E-05 6.32E-05 Y 91M 3.26E-11 NO DATA 1.275-12 NO DATA NO DATA 2.40E-07 1.66E-10 Y 91 5.78E-05 NO DATA 1.55E-06 NO DATA NO DATA 2.135-04 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-06 5.27E-05 ZR 95 1.34E-05 4.30E-06 2.91E-06 NO DATA 6.77E-06 2.21E-04 1.888-05 ZR 97 1.21E-08 2.45E-09 1.138-09 NO DATA 3.71E-09 9.84E-06 6.54E-05 NB 95 1.76E 06 9.77E-07 5.26E-07 NO DATA 9.67E-07 6.31E-05 1.30E-05 NO 99 NO DATA 1.51E-08 2.87E-09 NO DATA 3.64E 08 1.14E-05 3.10E-05 TC 99M 1.295-13 3.64E-13 4.63E-12 NO DATA 5.52E-12 9.55E-08 5.20E-07

     *Taken from Regulator Guide 1.109 (Rev. 1)

'7 @_f. R; vision: 0 OFFSITE DOSE CALCULATION MANUAL cP AP 07B-003 pg] ROforenco U.e & Page 110 of 188 CP ATTACHMENT A g (Page 106 of 184) g OFFSITE DOSE CALCULATION MANUAL W ~ TABLE A.2-1* (cont'd) h INHALATION DOSE FACTORS FOR ADULTS 110 (MREM PER PCI INHALED) GT NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI TC 101 5.22E-15 7.52E-15 7.38E-14 NO DATA 1.35E-13 4.99E-08 1.36E-21 RU 103 1.91E-07 NO DATA 8.23E-08 NO DATA 7.29E-07 6.31B-05 RU 105 9.8BE-11 NO DATA 1.38E-05 3.89?-11 STO DA??i 1.270-10 1.37E-06 6.02E-06 RU 106 8.64E-06 Ne DATA 1.09E-06 AG NO DATA 1.67E-05 1.17E-03 1.14E-04 110M 1.35E-06 1.25E-06 7.43E-07 NO DATA 2.46E-06 TE 125M 4.27E-07 5.79B-04 3.78E-05 1.98E-07 5.84E-08 1.313-07 1.55E-06 3.92E-05 6.83E-06 TE 127M 1.58E-06 7.21E-07 1.96E-07 4.12E-07 5.72E-06 1.20E-04 1.87E-05 TE 127 1.75E-10 8.03E-11 3.87E-11 1.32E-10 6.3?E-10 8.14E-07 7.17E-06 TE 129M 1.22B-06 5.84E-07 1.98E-07 4.30E-07 4.57E-06 1.45E-04 4.79E-05 TM 119 6.22E-12 2.99E-12 1.55E-12 4.07E-12 2.34E-11 2.42E-07 1.96E-08 TE 131M B.74E-09 5.45E-09 3.63E-09 TE 6.88E-09 3.86E-08 1.82E-05 6.95E-05 131 1.39E-12 7.44B-13 4.49E-13 1.17E-12 5.46E-12 1.74E-07 2.30E-09 TE 132 3.25E-08 2.69E-08 2.02E-08 2.37E-08 1.82E-07 3.60E-05 6.37E-05 I 130 5.728-07 1.68B-06 6.60E-07 1.42E-04 2.61E-06 NO DATA 9.61E-07 I 131 3.15E-06 4.47E-06 2.56E-06 1.49E-03 7.66E-06 NO DATA 7.85E-07 I 132 1.45E-07 4.078-07 1.45E-07 1.43E-05 6.48E-07 NO DATA 5.08E-08 I 133 1.083-06 1.85E-06 5.65E-07 2.69E-04 3.23E-06 UO DATA 1.11E-06 1 134 8.05B-08 2.16E-07 7.698-08 3.73E-06 3.44E-07 NO DATA 1.26E-10 I 135 3.35E-07 8.73B-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 *,.59E-05 136 1.22E-05 1.30E-06 CS 4.88E-06 1.83E-05 1.38E-05 NO DATA 1.07E-05 1.50E-06 1.46E-06 l CS 137 5.9BB-05 7.76E-05 5.35E-05 NO DATA 2.78E-05 9.40E-06 1.05E-06 CS 138 4.14E-08 7.76E-08 4.05E-08 NO DATA 6.00E-08 BA 139 1.17E-10 6.07E-09 2.33E-13 B.32E-14 3.42E-12 NO DATA 7.78E-14 4.70E-07 1.12E-07 BA 140 4.88E-06 6.13E-09 BA 3.21E-07 NO DATA 2.093-09 1.59E-04 2.73E-05 141 1.25E-11 9.41E-15 4.20E-13 NO DATA B.75E-15 2.42E-07 1.45E-17 BA 142 3.29E-12 3.38E-15 2.07E-13 NO DATA 2.86E-15 1.49E-07 1.96E-26 LA 140 4.30E-08 2.17E-08 5.73E-09 NO DATA NO DATA 1.70E-05 5.73E-05 IA 142 8.54E-11 3.88M-11 9.65E-12 NO DATA CE 141 NO DATA 7.91E-07 2.64E-07 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-09 144 9.978-06 2.83E-05 CE 4.29E-04 1.79B-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 ~ .0E-07 3.51E-05 2.50E-05 PR 144 3.76E-12 1.56E-12 1.91E-13 NO DATA ND 8.81E-13 1.27E-07 2.69E-18 147 6.59E-07 7.62E-07 4.56E-06 NO DATA W 4.45E-07 2.76E-05 2.16E-05 187 1.068-09 8.85E-10 3.10E-10 NO DATA NO DATA 3.63E-06 1.94E-05 NP 239 2.87E-08 2.82E-09 1.55E-09 NO DATA 8.75E-09 4.70E-06 1.49E-05 l

~G yr Revision: 0 CE OFFSITE DOSE CALCULATION MANUAL AP 07B-003 mm Rsforenco Uma 03 Page 111 of 188 CD ATTACHMENT A g (Page 107 of 180 gg OFFSITE DOSE CALCULATION MANUAL 1& g T.13LE A.2-2* INHALATION DOSE FACTORS FOR TEE?UWER -m (MREM PER PCI INHALED) @' NUCLIDE DONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI H 3 NO DATA 1.59E-07 1.592-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 C 14 3.25E-06 6.09E-07 6.098-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 NA 24 1.72E-06 3.77F-06 1.7"E-36 1.72E-06 1. 72E-06 1.72E-04 1.72E-06 P 32 2.36E-04 1.37E-05 B.95E-06 NO DATA CR NO DATA NO DATA 1.16E-05 51 NO DATA NO DATA 1.69E-08 9. 3 7E- 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 MN 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 FE 59 1.99E-06 4.62E-06 1.795-06 NO DATA NO DATA 1.91E-04 2.23E-05 CO 59 EO DATA 2.59E-07 3.47E-07 IJO DATA NO DATA 1.68E-04 1.19E-05 CO 60 NO DATA 1.89E-06 2.485-06 NO DATA NO DATA 1.09E-03 3.24E-05 N1 63 7.25E-05 5.43E-06 2.47E-06 NO DATA NO DATA 3.84E-05 1.77E-06 NI 65 2.73E-10 3.66E-11 1.59E-11 NO DATA NO DATA 1.17B-06 4.59E-06 CU 64 NO DATA 2.54E-10 1.06E-10 NO DATA ZN 8.01E-10 1.39E-06 7.68E-06 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 BR NO DATA 7.53E-12 1.98E-07 3.56E-08 83 NO DATA NO DATA 4.30E-09 MO DATA PO DATA NO EATA 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 2.29E-09 NO DATA NO DATA NO DATA LT E-24 RB 86 NO DATA 2.38E-05 1.05E-05 NO DATA NO DATA NO DATA 2.21E-06 RB 88 NO DATA 6.82E-08 3.40E-08 NO DATA NO DATA NO DATA 3.65E-15 RE 89 NO DATA 4,40E-08 2.91E-08 NO DATA NO DATA NO DATA 4.22E-17 SR 89 5.43E-05 NO DATA 1.56E-06 NO DATA NO DATA SR 3.02E-04 4.64E-05 90 1.35E-02 NO DATA 8.35E-04 NO DATA NO DATA 2.063-03 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 1.49E-05 Y 90 3.73E-07 NO DATA 1.00E-08 NO DATA NO DATA 3.66E-05 6.998-05

      't    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     2.21B-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 ZR      95                                                                1.04E-05   7.24E-05 1.82E-05   5.73E-06     3.94E-06     NO DATA ZR      97 8.42E-06   3.36E-04   1.86E-05 1.72E-08   3.40E-09     1.57E-09     NO DATA      5.15E-09   1.62E-05   7.88E-05 NB      95   2.32E-06   1.29E-06     7.08E-07 MO NO DATA      1.2SE-06   9.39E-05   1.21E-05 99   NO DATA    2.11E-08     4.03E-09 TC NO DATA      5.14E-08   1.92E-05   3.36E-05 99M   1.73E-13   4.838-13     6.24E-12     NO DATA      7.20E-12   1.44E-07   7.66E-07
   *Taken from Regulator Guide 1.109 (Rev. 1)

3$ Revision: 0 OFFSITE DOSE' CALCUIATION MANUAL AP 07B-003 rgi Raforenca Use Page 112 of 188

@                                                                                                           {
@                                               ATTACHMENT A g                                           (Page 108 of 184)

g. OFFSITE DOSE CALCUIATION MANUAL t fd" g TA %E A.2-2* (coat'd) k INHAIATION DOSE FACTORS FOR TEENAGER

/b                                            (MREM PER PCI INHALED)

7. NUCLIDE BONE ' LIVER T BODY THYROID KIDetEY LUNG GI-LLI TC 101 7.40E-15 1.05E-14 1.03E-13 NO DATA 1.90E-13 8.34E-08

     'RU                                                                                          1.09E-16 103  2.63E-07   NO DATA       1.12E-07     NO DATA    9.29E-07            9.79E-05             '

RU 105 1.40E-10 1.36E-05 NO EATA 5.42E-11 UO LATA 1.76E-10 2.27E-06 1.13E- Wi ! 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 9.995-07 NO DATA 3.13E-06 8.44E-04 TE 3.41E-05 1*25M C.10E 07 2.80E-07 8.342 08 1.75E-07 NO DATA 6.703-05 9.38E-06 TE 127M 2.25E-06 1.02E-06 2.73E-07 5.48E-07 8.17E-06 2.075-04 TE 1.99E-05 127 2.51E-10 1.14E-10 5.52E-11 1.77E-10' 9.10E-10 1.40E-06 1.01E-05 TE 129M 1.74E-06 8.23E-07 2.81E-07 5.72E-07 6.498-06 2.478-04 5.06E-05 TE 12) 8.87E-12 4.22E-12 2.20E-12 6.48E-12 3.32E-11 4.12E-07 2.02E-07 TI 131M 1.23E-08 7.51E-09 5.03E-09 9.065 09 5.495-08 2.97E-05 7.76E-05 TE 131 1.975-12 1.04E-12 6.30E-13 1.55E-12 7.725-12 2.92E-07 1.89E-09 TE 132 4.50E-08 3.63E-08 2.74E-08 3.07E-08 2.448-07 5.61E-05 5.795-05 I 130 7.80E-07 2.24E-06 8.96E-07 1.865-04 3.44E-06 NO DATA 1.14E-06 I 131 4.43E-06 6.14E-06 3.30E-06 1.83E-03 1.05E-05 NO DATA 8.11E-07 I 132 1.99E-07 5.475-07 1.975-07 1.89E-05 8.65E-07 NO DATA 1.59E-07 I 133 1.52E-06 2.56E-06 7.78E-07 3.65E-04 4.495-06 NO DATA 1.23E-06' I 134 1.11E-07 2.90E-07 1.05E-07 4.94E-06 4.58E-07 NO DATA 2.55E-09 i i I 135 4.62E-07 1.18E-06 '4.36E-07 7.76E-05 1.06E-06 NO DATA 8.69E-07 I CS 134 6.28E-05 1.415-04 6.863-05 NO DATA 4.695 05 1.435-05 1.22E-06 CS 136 6.44E-06 2.425-05 1.71E-05 NO DATA 1.38E-05 2.22E-06 1.365-06 i CS 137 8.38E-05 1.06E-04 3.89E-05 NO DATA 3.80E 05 1.513-05 1.06E-06 CS 138 5.82E-08 1.07E-07 5.58E-08 NO DATA S.28E-08 9.84E-09 3.38E-11 ; BA 139 1.675-10 1.185-13 1.11E-13 4.87E-12 NO DATA 8.08E-07 8.06E-07 , BA 140 6.84E-06 8.385-09 4.40E-07 NO DATA 2.85E-09 2.54E-04 2.86E-05 ! BA 141 1.788-11 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 2.395-07 5.99E-20 LA 140 5.99E-08 2.95E-08 7.828-09 NO DATA NO DATA 2.68E-05 6.09E-05 LA 142 1.20E-10 5.31E-11 1.325-11 NO DATA NO DATA 1.27E-06 1.50E-06 CE 141 3.55E-06 2.37E-06 2.71E-07 NO DATA 1.118-06 7.67E-05 1.58E-05 CE 143 3.325-08 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 DATA 1.51E-04 1.67E-03 1.08E-04 PR 143 1.67E-06 6.64E-07 8.285-08 NO DATA 3.86E-07 6.04E-05 2.67E-05 PR 144 5.37E-12 2.20E-12 2.72E-13 NO DATA 1.26E-12 2.19E-07 2.94E-14 ND 147 9.835-07 1.07E-06 6.41E-08 NO DATA 6.28E-07 W 4.65E-05 2.28E-05 187 1.50E-09 1.22E-09 4.29E-10 NO DATA NO DATA 5.92E-06 2.21E-05 NP 239 4.23E-08 3.995-09 2.21E-09 NO DATA 1.25E-08 8.11E-06 1.65E-05

y Rsvision: 0 OFFSITE DOSE CALCUIATION MANUAL

 @                                                                                  AP 07B-003 pp Rafarsnca Uca                                                               Page 113 of 188 ATTACHMENT A (Page 109 of 184) g                           OFFSITE DOSE CALCULATION MANUAL M

y TABLE A.2-3* k INHALATION DOSE FACTORS FOR CHILD (MREM PER PCI INHALED)

 .A 7       NUCLIDE    BONE       LIVER       T BODY     THYROID      KIDNEY    LUNG      GI-LLI H      3  NO DATA   3.04E-07     3.04E-07    3.04E-07    3.04E-07 3.04E-07   3.045-07 C     14  9.70E-06  1.82E-06      1.82E-06   1.82E-06 NA 1.82E-06 1.82E-06   1.825-06 24 4.35E-06    1.35E-06    4.353 05    4.351-06    4.35E-Oc 4.35E-06   s.35h-06 P     32 7.04E-04   3.09E-05     2.67E-05    NO DATA      NO DATA CR     51 NO DATA   1.14E-05 NO DATA    NO DATA     4.17E-08    2.31E-08    6.57E-09 4.59E-06   2.935-07 Mt1    54  NO DATA   1.16E-05     2.57E-06    NO DATA     2.71E 06 4.26E-04   6.19h-06 MN     56  NO DATA   4.48E-10     8.43E-11    NO DATA     4.52E-10 3.55E-06   3.33E-05 FE     55 1.28E-05   6.80E-06     2.10E-06    NO DATA      NO DATA 3.00E-05   7.75E-07 FE     59 5.59E-06   9.04E-06     4.51E-06    NO DATA      NO DATA 3.43E-04   1.91E-05 CO     58  NO DATA   4.793-07     8.55E-07    NO DATA      NO DATA CO     60 2.99E-04   9.29E-06 NO DATA   3.55E-06     6.12E-06    NO DATA      NO DATA 1.91E-03   2.60E-05 NI     63 2.225-04   1.25E-05     7.56E-06    NO DATA      NO DATA 7.43E-05   1.71E-06 NI     65 8.085-10   7.99E-11     4.44E-11    NO DATA      NO DATA 2.215-06   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   4.41E-06 ZN     69 1.81E-11   2.61E-11     2.415-12    NO DATA     1.585-11 3.84E-07   2.75E-06 BR-    83  NO DATA    NO DATA     1.28E-07    NO DATA      NO DATA  NO DATA    LT E-24 BR     84  NO DATA    NO DATA     1.48E-07    NO DATA      NO DATA  NO DATA    LT E-24 BR     85  NO DATA    NO DATA     6.84E-09    NO DATA     NO DATA  NO DATA     LT E-24 RB     86  NO DATA   5.36E-05     3.09E-05    NO DATA      NO DATA  NO DATA-  2.16E-06 RB     88  NO DATA   1.52E-07     9.90E-08    NO DATA NO DATA  NO DATA   4.66E-09 RB     89  NO DATA   9.33E-08     7.83E-08    NO DATA     NO 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 2.735-02    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-08    NO DATA     NO DATA  7.07E-05   7.24E-05 Y    91M 1.37E-10   NO DATA      4.98E-12    NO DATA     NO DATA  7.605-07   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      1.578-10    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     1.615-05 6.03E-04   1.65E-05

___ ZR 97 5.07E-08 7.34E-09 4.325-09 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 1.665-04 1.00E-05 NO 99 NO DATA 4.66E-08 1.15E-08 1.06E-07 NO DATA 3.66E-05 3.42E-05 TC 99M 4.81E-13 9.41E-13 1.56E-11 NO DATA 1.37E-11 2.57E-07 1.30E-06

    *Taken from Regulator Guide 1.109 (Rev. 1)

3

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

f) Referenca Ugo Page 114 of 188 O O ATTACHMENT A y (Page 110 of 184). g, OFFSITE DOSE CALCULATION MANUAL n y TABLE A.2 3* (ccat'd) INHALATION DOSE FACTORS FOR CHILD (MREM PER PCI INHALED) JJ F, NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG OI-LLI TC 101 2.19E-14 2.30E-14 2.915-13 NO DATA 3.92E-13 1.58E-07 4.41E-09 RU 103 7.555-07 NO DATA 2.90E-07 NO DATA 1.90E-06 1.79E-04 1.21E-05 PU 105 4.132-10 NO Dt.TA 1.Z E-10 NO DATA 3.63E-10 4.30E-06 2.bE-sa RU 106 3.68E-05 NO DATA 4.575-06 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 12'.M 1.82E-06 6.29E-07 2.47E-07 5.20E-07 NO DATA 1.29E-04 9.13E-06 TB 127M 6.725-06 2.31E-06 8.16E-07 1.64E-06 1.72E-05 4.00E-04 1.93E-05 4 TE 127 7.49E-10 2.57E-10 1.65E-10 5.30E-10 1.91E-09 2.71E-06 1.52E-05 TE 129M 5.19E-06 1.85E-06 8.22E-07 1.71E 06 1.36E-05 4.76E-04 4.91E-05 TE 129 2.64E-11 9.45E-12 6.44E-12 1.93E-11 6.49E-11 7.93E-07 6.89E-06 ; TE 131M 3.63E-08 1.60E-08 1.37E-08 2.64E-08 1.08E-07 . 56E-05 8.32E-05 TE 131 5.87E-12 2.28E-12 1.78E-12 4.59E-12 1.59E-11 5.558-07 3.60E-07 TE 132 1.30E-07 7.36E-08 7.12K-08 8.58E-08 4.79E-07 1.02E-04 3.72E-05 I 130 2.215-06 4.43I-06 2.28E-06 4.99E-04 6.61E-06 NO DATA 1.38E-06 I 131 1.30E-05 1.30E-05 7.37E-06 4.39E-03 2.13E-05 NO DATA 7.685-07 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 2.0PE-06 1.04F-03 9.13E-M US DATA 1.4PE-CC l I 134 3.17E-07 5.84E-07 2.695-07 1.37E-05 8.925-07 NO DATA 2.58E-07 1 R I f I 135 1.33E-06 2.36E-06 1.12E-06 2.14E-04 3.62E-06 NO DATA 1.20E-06 CS 134 1.765-04 2.74E-04 6.07E-05 NO DATA 8.93E-05 3.275-05 1.04E-06 CS 136 1.76E-05 4.62E-05 3.145-05 NO DATA 2.58E-05 3.93E-06 1.13E-06 . CS 137 2.45E-04 2.23E 3.47E-05 NO DATA 7.63E-05 2.81E-05 9.78E-07 $ CS 138 1.71E-07 2.27E-07 1.50E-07 NO DATA 1.685-07 1.84E-08 7.295-08 i BA 139 4.98E-10 2.66E-13 1.45E-11 NO DATA 2.33E-13 1.56E-06 1.56E-05 j BA 140 2.00E-05 1.75E-08 1.17E-06 NO DATA 5.71E-09 4.71E-04 2.75E-05 ! BA 141' 5.298-11 2.95E-14 1.72E-12 NO DATA 2.56E-14 7.89E-07 7.44E-08 $ BA 142 1.35E-11 9.73E-15 7.54E-13 NO DATA 7.87E-15 4.44E-07 7.41E-10 l 1A 140 1.74E-07 6.08E-08 2.04E-08 NO DATA NO DATA 4.94E-05 6.10E-05

LA 142 3.50E-10 1.11E-10 3.49E-11 NO DATA NO DATA 2.35E-06 2.05E-05

{ CE 141 1.06E-05 5.285-06 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 2.265-08 3.12E-05 3.4(3-05 CE 144 1.83E-03 5.72E-04 9.77E-05 NO DATA 3.17E-04 3.23E-03 1.05E-04 PR 143 4.995-06 1.50E-06 2.47E-07 NO DATA 8.11E 07 1.17E-04 2.63E-05 i PR 144 1.61E-11 4.99E-12 8.10E-13 NO DATA 2.645-12 4.23E-07 5.325-08 3 ND 147 2.92E-06 2.36E-06 1.84E-07 NO DATA 1.30E-06 8.87E-05 2.22E-05 q N 187 4.41E-09 2.61E-09 1.175-09 NO DATA NO DATA 1.11E-05 2.46E-05 i [ NP 239 1.26E-07 9.04E-09 6.35E 09 NO DATA 2.63E-08 1.57E-05 1.73E-05 ?

w 3 D Ravisiont 0 OFFSITE DOSE CALCUIATION MANUAL AP 07B-003

.D.

pg Referenca-Uce Page 115 of 188 0 O ATTACHMENT A

g. (Page 111 of 184) g OFFSITE DOSE CALCULATION MANUAL

 .M g                                                TABLE A.2-4*                                    !

IMHALATI0tt DOSE FACTORS FOR INFANT Y (MtEN PER PCI INHALED) 4 0" - NUCLIDE BottE LIVER. T BODY ' THYROID KIDNEY LUNG GI-I.LI H 3 NO DATA 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 C 14 1.89E-05 3.795-06 3.793-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 FA 21 7 M45 05 7.54E-06 7.54E-06 7.542-06 7.54E-0G' 7.S4E-06 7.54H-06 P 32 1.45E-03 8.03E-05 5.53E-05 NO DATA NO DATA NO DATA 1.15E-05 CR- 51 NO DATA NO DATA 6.39E-08 4.11E-08 9.45E-09 9.17E-06 2.55E-07 MN 54 NO DATA 1.81E-05 3.56E-06 NO DATA 3.568-06 7.14E-04 5.04E-06 MN 56 'NO DATA 1.10E-09 1.58E-10 NO DATA 7.865-10 8.95E-06 5.12E-05 FE 55 1.41E-05 8.39E-06 2.38E-06 NO DATA NO DATA 6.21E-05 7 82E-07 FE 59 9.69E-06 1.68E-05 6.77E-06 NO DATA NO DATA 7.25E-04 1.77E-05 CO 58 NO DATA 8.715-07 1.30E-06 NO DATA No DATA 5.55E-04 7.95E-06 CO 60 NO DATA 5.735-06 8.41E-06 NO DATA NO DATA 3.22E-03 2.28E-05

         .NI    63   2.425-04  1.46E-05    8.29E-06      NO DATA  NO DATA   1.49E-04  1.73E-06     l NI    65   1.71E-09  2.03E-10    8.795-11      NO DATA  NO DATA   5.80E-06  3.58E-05     I 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  4.625-04  3.67E-05 ZN    69   3.85E-11  6.915-11    5.13E-12      NO DATA  2.87E-11  1.05E-06  9.44E-06 PR    A3    NO DATA  NO OPsTA    2,72E-07      NO DATA  NO DATA   NO DATA    LT R-M      !

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 I RB 86 NO DATA 1.36E-04 6.305-05 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 2.425 07 i l RB 89 NO DATA 2.29E-07 1.47E-07 NO DATA NO DATA NO DATA 4.87E-08 l SR 89 2.84E-04 NO DATA 8.15E-06 NO DATA NO DATA ' 1.458-03 4.575-05 I SR 90 2.925 NO DATA 1.85E-03 NO DATA NO DATA 8.03E-03 9.36E-05 ! SR 91 6.83E-08 NO DATA 2.47E-09 NO DATA NO DATA 3.76R-05 5.24E-05 SR 92 7.50E-09 NO DATA 2.79E-10 NO DATA NO DATA 1.70E-05 1.00E-04 Y 90 2.355-06 NO DATA 6.30E-08 NO DATA NO DATA 1.92E-04 7.435-05 Y 91M 2.91E-10 NO DATA 9.90E-12 NO DATA NO DATA 1.995-06 1.68E-06 Y 91 4.20E-04 NO DATA 1.12E-05 NO DATA NO DATA 1.75E-03 5.02E-05 Y 92 1.17E-08 NO DATA 3.29E-10 NO DATA NO DATA 1.75E-05 9.04E-05

          .Y      4  1.07E-07   NO DATA    2.91E-09      NO DATA   NO DATA  5.46E-05  1.19E-04 ZR     95  8.24E-05  1.995-05 ' 1.45E-05       NO DATA  2.22E-05  1.25E-03  1.55E-05     ;

ZR 97 1.07E-07 1.835-08 8.36E-09 NO DATA 1.85E-08 7.88E-05 1.00E-04 I I NB 95 1.125-05 4.59E-06 2.70E-06 NO DATA 3.37E-06 3.42E-04 9.05E-06 NO 99 NO DATA 1.18E-07 2.31E-08 NO DATA 1.89E-07 9.63E-05 3.48E-05 TC 99M 9.98E-13 2.06E-12 2.66E-11 NO DATA 2.22E-11 5.79E-07 1.45E-06 : 1

        *Taken from Regulator Guide 1.109 (Rev. 1)

3 p Ravicion: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 M j g Rofersnca Use Page 116 of 188 1 O i ATTACHMENT A I h (Page 112 of 184) I _y OFFSITE DOSE CALCULATION MANUAL TAELE A.2-4* (cant'd) INHALATION DOSE FACTORS FOR INFANT

\                                                   05 TEM PER PCI INHALED)
.h

(' NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG OI-LLI TC 101 4.65E-14 5.88E-14 -5.805-13 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 3.94E-04 1.15E-05 RU 105 8.74E-10 NO DATA 2.93E-10 DO DATA 6.42d-10 1.12E-Ob 3.46E-05 RU' 106 6.20E-05 NO DATA 7.77E-06 NO DATA 7.61B-05 8.265-03 1.17E-04 AG 110M 7.13E-06 5.16E-06 3.57E-06 NO DATA 7.803-06 2.62E-03 2.36E-05 TE 125M 3.40E-06 1.42E-06 4.70E-07 1.16E-06 NO DATA 3.1SE-04 9.22E-06 TE 127M 1.19E-05 4.93E-06 1.48E-06 3.48E-06 2.68E-05 9.37E-04 1.95E.05 TE 127 1.59E-09 6.81E-10 3.49E-10 1.32E 3.47E-09 7. 3 9E-06 1.745,05 TE 129M 1.01E-05 4.35E-06 1.59E-06 3.91E-06 2.27E-05 1.20E-03 4.93E-05 TE 129 5.63E-11 2.488-11 1.345-11 4.82E-11 1.25E-10 2.145-06 1.88E-05 TE 131M 7.625-08 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 2.855-11 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 1.095-05 NO DATA 1.42E-06 I 131 2.715-05 -3.17E-05 1.40E-05 1.06E-02 3.70E-05 NO DATA 7.56E-07 l I 132 1.21E-06 2.53E-06 8.99E-07 1.215-04 2.82E-06 NO DATA 1.36E-06 I 133 9.46E-06 1.37E-05 4.00E-06 2.54E-03 1.GOE-05 NO DATA *

                                                                                                              . 518-06 I    134  6.58E-07  1.34E-06               4.75E-07               3.18E-05  1.493-06    NO DATA        9.215-07 I    135  2.76E-06  5.435-06               1.98E-06               4.97E-04  6.05E-06    NO DATA        1.31E-06' CS    134  2.83E-04  5.02E-04               5.32E-05                NO DATA  1.365-04    5.69E-05       9.53E-07 CS    136  3.45E-05  9.61E-05              3.78E-05                 NO DATA  4.03E   8.40E-06       1.02E-06 C8    13'  3.92E-04  4.37E-04               3.25E-05                NO DATA  1.23E-04    5.09E-05       9.53E-07 C$    131  3.61E-07  5.58E-07              2.84E-07                 NO DATA  2.93E-07    4.67E-08       6.26E 07 BA    II)  1.065-09  7.03E-13               3.07E-11                NO DATA  4.23E-13    4.25E-06       3.64E-05 BA    140  4.00E-05  4.00E-00               2.07E-06                NO DATA  9.59E-09    1.14E-03       2.74E-05 BA    141  1.12E-10  7.70E-14               3.55E-12                NO DATA  4.64E-14    2.12E-06       3.39E-06 BA    142  2.84E-11  2.36E-14               1.40E-12                NO DATA  1.365-14    1.11E-06       4.95E 07 LA    140  3.61E-07  1.43E-07               3.68E-08                NO DATA   NO DATA    1.20E-04       6.06E-05        i 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  2.09E-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-05  3.74E-06               4.99E-07                NO DATA  1.41E-06    3.09E-04       2.66E 05        j PR    144  3.425-11  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 W    187  9.26E-09  6.44E-09               2.23E-09                NO DATA   NO DATA    2.83E-05       2.54E-05 NP    239  2.65E-07  2.37E-08               1.34E-08                NO DATA  4.73E-08    4.25E-05       1.78E-05

, . . - . . __ . - . . . . . ~ . -- - . ~ . - . . 3 D Revision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 D pl Rsforanca Usa Page 117 of 188 O O- ATTACHMENT A l y (Page 113 of 134) . I g OFFSITE DOSE CALCULATION MANUAL l M ' g TABLE A.2-5*

 \                      EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND (mrem /hr per pC1/m*)

1) f ELEMENT TOTAL BODY SEZE H-3 0.0 0.0 C-14 0.0 0.0 N3-21 2.50E-03 2.90E-Oo P-32 0.0 0.0 Cr-51 2.20E-10 2.60E-10 Mn-54 5.80E-09 6.90E-09 Ma-56 1.10E-08 1.30E-08 Fe-55 0.0 0.0 Fe-59 8.00E-09 9.40E-09 Co-58 7.00E-09 8.20E-09 Co-60 1.70E-08 2.00E-08 Ni-63 0.0 0.0 Ni-65 3.70E-09 4.30E-09 . Cu-64 1.50E-09 1.70E-09 Zn-65 4.00E-09 4.60E-09 1 Zn-69 0.0 0.0 j Br-83 6.40E-11 9.30E-11 l 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 S r-89 5.605-13 6.50E-13 Sr-91 7.10E-09 8.30E-09 Br-92 9.00E-09 1.00E-08 Y-90 2.205-12 2.60E-12 j Y-91M 3.80E-09 4.40E-09 Y-91 2.40E-11 2.70E-11 l Y-92 1.60E-09 1.90E-09 I Y-93 5.70E-10 7.80E-10 Zr-95 5.00E-09 5.80E-09 Zr-97 5,50E-09 6.40E-09 Nb-95 5.10E-09 6.00E-09 Mo-99 1.90E-09 2.20E-09 Tc-99M 9.60E-10 1.10E-09 Tc-101 2.70E-09 3.00E-09 Ru-103 3.605-09 4.20E-09 l Ru-105 4.50E-09 5.10E-09 Ru-106 1.50E-09 1 80E-09 Ag-110M 1.80E-08 2.10E-08 Tc-125M 3.50*3 11 4.80E-11 Te-127M 1.10E-12 1.30E-12 Te-127 1.005-11 1.10E-11 Te-129M 7.70E-10 9.00E-10 Te-129 7.10E 10 8.40E-10

     *Taken f rora Regulatory Guide 1.109 (Rev. 1)                                                        l

3 3 Ravitsion: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 Cli m Referenca Uso Page 118 of 188 0 O ATTACHMENT A g (Page 114 of 184) g OFFSITE DOSE CALCULATION MANUAL H g TABLE A.2-5+ (cont'd) EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND (mres/hr per pCi/ad)

 .3 F                   ELEMENT                TOTAL BODY                SKIH Te-131M                  8.40E-09              9.90E-09 Te-131                   2.20E-09              2.60E-06 Te-132                   1.70E-09              2.00E-09 I-130                  1.40E-08              1.70E-C3 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              1.00E-08 I-135                  1.20E-08              1.405-08 Cs-134                   1.20E-08              1.40E-08 Cs-136                   1.50E-08              1.70E-08 Cs-137                  4.20E-09              4.90E-09 Co-138                  2.10E-08              2.40E-08 Ba-139                  2.40E-09              2.70E-09 Ba-140                  2.10E-09              2.40E-09 Ba-141                  4.305-09              4.90E-09 Ba-142                  7.90E-09              9.003-09 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 Co-144                  3.20E-10              3.70E-10 Pr-143                     0.0                   0.0 Pr-144                  2.00E 10              2.30E-10 Nd-147                  1.00E-09              1.20E-09 N-187                  3.10E-09              3.60E-09 Np-239                  9.50E-10              1.10E-09

                                               -      -        -     . _ . . - = . - -
   .D  Rsvision: 0                OFFSITE DOSE CALCULATION MANUAL                               AP 07B-003
    #P g  Reference Use                                                                      Page 119 of 188 ATTACHMENT A O

g (Page 115 of 184)

   .g                             OFFSITH DOSE CALCULATION MANUAL u                                                 TALLE A.3-1*

N ING3STION DOSE FACIORS FOR ADULTS k (MREM PER PCI INOESTED)

    $7       NUCLIDE      BONE       LIVER        T BODY    THYROID         KIDNEY       LUNG       GI-LLI

, H 3 NO DATA 1.055-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 C 14 2.845-06 5.68E-07 5.68E-07 5.68E-07 5.685-07 5.68E-07 5.68E-07

NA 21 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.702-0G 1.70U.06 1.7C",00 4 P 32 1.93E-04 1.20E-05 7.46E-06 NO DATA NO DATA NO DATA 2.17E-05

'f CR 51 NO DATA NO DATA 2.66E-09 1.59E-09 5.86E-10 3.53E-09 6.69E-07 , NN 54 NO DATA 4.57E-06 8.72E-07 NO DATA 1.36E-06 NO DATA 1.40E-05 l i I MN 56 NO DATA 1.15E-07 2.04E-08 NO DATA 1.46E-07 NO DATA 3.67E-06 FE 55 2.753-06 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 i i i NI 65 5.285-07 6.06E-08 3.13E-08 NO DATA NO DATA NO DATA 1.74E-06 i CU 64 NO DATA 8.33F-08 3.91E-08 NO DATA 2.10E-07 NO DATA 7.10E-06 1 ZN 65 4.84E-06 1. 54 E- M 6.96E-06 NO DATA 1.03E-05 NO DATA 9.70E-06 e ZN 69 1.03E-08 1.97E-08 1.375-09 NO DATA 1.28E-08 NO DATA 2.96E-09 j BR e3 NO DATA NO DATA 4.02E-08 NO DATA NO DATA PO DAT.% 5.79T 08 j 1 BR 84 NO DATA NO DATA 5.21E-08 NO DATA NO DATA NO DATA 4.09E-13 l t 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-00 3.21E-08 NO DATA NO DATA NO DATA 8.36E-19 I RB 89 NO DATA 4.01E-08 2.82E-08 NO DATA NO DATA NO DATA 2.33E-21 SR 89 3.08E-04 NO DATA 8.845-06 NO DATA NO DATA NO DATA 4.945-05 SR 90 7.58E-03 NO DATA 1.86E-03 NO DATA NO DATA NO DATA 2.19E-05 SR 91 5.67E-06 NO DATA 2.29E-07 NO DATA NO DATA NO DATA 2.70E-05 l SR 92 2.15E-06 NO DATA 9.30E-08 NO DATA NO DATA NO DATA '4.26E-05 2 Y 90 9.62E-09 NO DATA 2.58E-10 NO DATA NO DATA NO DATA 1.02E-04 Y 91M 9.095-11 NO DATA 3.52E-12 NO DATA NO DATA NO DATA 2.67E-10 Y 91 1.41E-07 NO DATA 3.77E-09 NO DATA NO DATA NO DATA 7.76F-05

Y 92 8.453-10 NO DATA 2.47E-11 NO DATA NO DATA NO DATA 1.48E-05 4

1 Y 93 2.68E-09 NO DATA 7.40E-11 NO DATA NO DATA NO DATA 8.50E-05 l ZR 95 3.04E-08 9.75E-09 6.60E-09 NO DATA 1.53E-08 NO DATA 3.09E-05

,           ZR     97   1.685-09    3.39E-10      1.55E-10   NO DATA       5.12E-10     NO DATA     1.05E-04 NB     95   6.22E-09    3.465-09      1.86E-09   NO DATA       3.42E-09     NO DATA     2.10E-05 d

MO 99 NO DATA 4.31E-06 8.20E-07 NO DATA 9.76E-06 NO DATA 9.99E 06 TC 99M 2 47E-10 6.98E-10 8.89E-09 NO DATA 1.06E-08 3.42E-10 4.13E-07 <

         *Taken from Regulator Guide 1.109 (Rev. 1) 1 i

Revision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 S g Rsference Use Page 120 of 188 ATTACHMENT A l

 @                                         (Page 116 of 184)

OFFSITE DOSE CALCULATION MANUAL r TA515 A.3-1* (cent'd) INGESTION DOSE FACTORS FOR ADULTS 9 (MREM PER PCI INGESTED) 1 b [ NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG OI-LLI TC 101' 2.54E-10 3.66E-10 3.595-09 NO DATA 6.595-09 1.87E-10 1.10E-21 RU 103 1.85E-07 NO DATA 7.975-08 NO DATA 7.06E-07 NO DATA 2.16E-05 , RU 105 1.042-3b NO DATA 6.03E-09 l'O DATA 1.993-07 NO EATA 9.4.95-06 l 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 125!1 2.68E-04 9.71E-07 3.59E-07 8.06E-07 1.09E-05 NO DATA 1.07E-05 TB 127M 6.77E-06 2.42E-06 8.25E-07 1.73E-06 2.755-05 NO DATA 2.27E-05 TR 127 1.10E-07 3.955-08 2.30E-08 8.15E-08 4.48E-07 NO DATA 8.68E-06 TE 129M 1.15E-05 4.29E-06 1.825-06 3.95E-06 4.005-05 NO DATA 5.79E-05 TE 129 3.14E-08 1.185 08 7.65E-09 2.41E-08 1.325-07 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 2.79E-09 TB 132' 2.52E-06 1.6*E-06 1.53E-06 1.805-06 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 1.575-06 I 132 2.03E-07 5.43E-07 1.90E-07 1.908-05 8.65E-07 NO DATA 1.02E-07 I 133 1.42E-06 2.472-06 7.535-07 3.63E-04 4.31E-04 NO DATA 2.22E-06 I 134 1.045-07 2.88E-07 1.03E-07 4.998-06 4.58E-07 NO DATA 2.51E-10 I 135 4.43E-07 1.16E-06 4.28E-07 7.65B-05 1.86E-06 NO DATA 1.31E-06 CS 134 6.223-05 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 8.018-08 7.91E-09 4.65E-13 BA 139 9.70E-08 6.91E-11 2.845-09 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 1.28E-10 5.02E-11 1.455-11 NO DATA NO DATA NO DATA 4.25E-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 2.625-08 NO DATA 1.21E-07 NO DATA 1.65E-04 PR 143 9.20E-09 3.69E-09 4.565-10 NO DATA 2.13E-09 NO DATA 4.03E-05 PR 144 3.01E-11 1.25E-11 1.53I-12 NO DATA 7.05E-12 NO DATA 4.33E-18 ND 147 6.29E-09 7.27E-09 4.35E-10 NO DATA 4.255-09 NO DATA 3.49E-05 N 187 1.03E-07 8.61E-08 3.015-08 NO DATA NO DATA NO DATA 2.82E-05

OFFSITE DOSE CALCULATION MANUAL AP 07B-003 Ravision: 0 Reference Use Paga 121 of 188 ATTACrIMENT A l (Page 117 of 184) OFFSITE DOSE CALCULATION MANUAL b TABLE A.3-1* (cont'd) 7 INGESTION DOSE FACTORS FOR ADULTS i (MREM PER PCI INGESTED) k LIVER T BODY THYROID KIDNEY LUNG GI-LLI NUCLIDE BONE 1.195-09 1.17E-10 6.45E-11 NO DATA 3.65E-10 NODATA 2.40E-05 NP 239 E.29E-08 1.111 06 6.79E-03 NO DATi. 2.18E-06 7.9FE-05 Ob 124'* 2.0SE-06 ' 1.79E-06 2.00E-08 4.26E-07 1.82E-09 NO DATA 1.38E-06 1.97E-05 Sb 125** 1.15E-06 2.34E-08 4.15E-07 7.04E-09 NO DATA 7.05E-07 9.40E-05 Sb 126** 1.75E-07 2.91E-07 NO DATA NO DATA NO DATA 4.44E-06 Co b7** NO DATA

         **Taken from Regulator Ouide 1.109 (Rev. 0)

J l t l ! ,5 { l I l i

d' l 7 Rovicion: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 Reference Use Page 122 of 188 ; 3 ATTACHMENT A (Page 118 of 184) OFFSITE DOSE CALCULATION MANUAL M TABLE A-3.2 INGESTION DOSE FACTORS FOR TEENAGERS I

.                                          (MREM PER PCI INGESTED)

(f NUCLIDE BONE LTVER T BODY THYROID KIDNEY LUNG GI-LLI l H 3 NO DATA 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 C 14 4.06E-06 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.128-07 NA 24 2.30E-06 2.30E-L6 2.302-06 2.20E-0 2.30E-06 2.3CE-DE 2.300-CC l P 32 2.76E-04 1.71E-05 1.07E-05 NO DATA NO DATA NO DATA 2.32E-05 l CR 51 NO DATA NO DATA 3.60E-09 2.00E-09 7.89E-10 5.14E-09 6.05E-07 e4N 54 NO DATA 5.905-06 1.17E-06 NO DATA 1.76E-06 NO DATA 1.21E-05 MN 56 NO DATA 1.58E-07 2.81E-08 NO DATA 2.00E-07 NO D71TA 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 SS 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 l MI 63 1.77E-04 1.25E-05 6.00E-06 NO DATA NO DATA NO DATA 1.99E-06 ' NI 65 7.49E-07 9.57E-08 4.36E-08 NO DATA NO DATA NO DATA 5.19E-06 CU 64 NO DATA 1.15E-07 5.41E-08 NO DATA 2.91E-07 NO DATA 8.92E-06 ZN 65 5.763-06 2.00E-05 9.33E-06 NO DATA 1.285-05 NO DATA 8.47E-06 ZN 69 1.47E-08 2.80E-08 1.96E-09 NO DATA 1.835-08 NO DATA 5.16E-08 PR 01 MO DATA NO DATA 5.*F4F-08 NO DATA NO DATA NO DATA LT E-24 BR 84 NO DATA NO DATA 7.22E-08 NO DATA NO DATA NO DATA LT E-24 BR 85 NO DATA NO DATA 3.05E-09 NO DATA NO DATA NO DATA LT E-24 RB 86 NO DATA 2.985-05 1.40E-05 NO DATA NO DATA NO DATA 4.41E-06 RB 88 NO DATA 8.52E-08 4.54E-06 NO DATA NO DATA NO DATA 7.30E-15 RB 89 NO DATA 5.50E-08 3.89E-08 NO DATA NO DATA NO DATA 8.43E-17 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 7.772-M 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 B.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 ZR 95 4.12E-08 1.30E-08 8.94E-09 NO DATA 1.91E-08 NO DATA 3.00E-05 ER 97 2.37E-09 4.69E-10 ?.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 MO 99 NO DATA 6.03E-06 1.15E-06 NO DATA 1.38E-05 NO DATA 1.08E-05 TC 99M 3.32E-10 9.26E-10 1.20E-08 NO DATA 1.38E-08 5.14E-10 6.08E-07

      *Taken from Regulator Guide 1.109 (Rev. 1)

Revision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 Reference Use Page 123 of 188 l l ATTACHMENT A ! k (Page 119 of 184) OFFSITE DOSE CALCULATION MANUAL -b TABLE A-3.~4 (cont' d) INGESTION DOSE FACTORS FOR TEENAGERS ( (MREM PER PCI IMOESTED) NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNO CI.LLI TC 101 3.60E-10 5.12E-10 5.03E-09 NO DATA 9.26E-09 3.12E-10 8.75E-17 j RU 103 2.55E 07 NO DATA 1.09E-07 NO DATA 8.99E-07 NO DATA 2.13E-05 I RU 105 2.18E-Od NO CATA 8 . 4 tir;- 09 NO DATA 2.75E-07 NO DATA 1.16E- h l 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 l TE 125M 3.83E-06 1.38E-06 5.12E-07 1.07E-06 NO DATA NO DATA 1.13E-05 l TB 127M 9.67E-06 3.43E-06 1.15E-06 2.30E-06 3.92E-05 NO DATA 2.41E-05 TH 127 1.585-07 5.60E-08 3.40E-08 1.09E-07 6.40E-07 NO DATA 1.22E-05 TE 129M 1.63E-05 6.05E-06 2.58E-06 5.26E-06 6.825 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 1.225-05 NO DATA 9.39E-05 TE 131 2.79E-08 1.15E-08 8.72E-09 2.15E-08 1.22B-07 NO DATA 2.29E-09 i TB 132 3.49E-06 2.21E-06 2.08E-06 2.33E-06 2.125 05 NO DATA 7.00E-05 I 130 1.03E-06 2.98E-06 1.19E-06 2.43E-04 4.59E-06 NO DATA 2.29E-06 I 131 5.85E-06 8.19E-06 4.40E-06 2.39E-03 1.41E-05 NO DATA 1.62E-06 I 132 2.79E-07 7.30E-07 2.62E-07 2.46E-05 1.15E-06 NO DATA 3.18E-07 1 133 2.01r 06 3..*1D 06 1.043-06 1.76E-04 5. 983- M NO DATA 2.5cr-Cr 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 1.018-04 2.48E-06 NO DATA 1.74E-06 CS 134 8.37E-05 1.97E-04 9.14E-05 NO DATA 6.26E-05 2.39E-05 2.45E-06 CS 136 8.59E-06 3.38E-05 2.27E-05 NO DATA 1.84E-05 2.90E-06 2.72E-06 CS 137 1.12E-04 1.49E-04 5.19E-05 NO DATA 5.07E-05 1.97E-05 2.12E-06 CS 138 7.76E-08 1.49E-07 7.45E-08 NO DATA 1.10E-07 1.28E-08 6.76E-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 3.4BE-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 2.998-08 2.995-11 1.84E-09 NO DATA 2.53E-11 1.99E-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 7.958-11 1.98E-11 NO DATA NO DATA NO DATA 2.42E-06 CE 141 1.33E-08 8.88E-09 1.02E-09 NO DATA 4.18E-09 NO DATA 2.54E-05 l 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 3.74B-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 ; I PR 144 4.30E 11 1.76E-11 2.18E-12 NO DATA 1.01E-11 NO DATA 4.74E-14 ND 147 9.38E-09 1.02E-08 6.11E-10 NO DATA 5.99E-09 NO DATA 3.68E-05 i N 187 1.46E-07 1.19E-07 4.17E-08 NO DATA NO DATA NO DATA 3.22E-05

m 1 3 R2 vision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 D g R3forcnce Use Page 124 of 188 O ATTACHMENT A O M (Page 120 of 184)

\                            OFFSITE DOSE CALCULATION MANUAL N

N TABLE A-3.2 (cont'd) INGESTION DOSE FACTORS FOR TEENAGERS

\                                        (MREN PER PCI INGESTED)

J) G* NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI NP 239 1.76E-09 1.66E-10 9.22E-11 NO DATA 5.21E-10 NO DATA 2.67E-05 Su 124** 3.476-06 7.13E-Cd 1.51E-06 0.7eE-09 ho DATA 3.308-06 1.80d-05 Sb 125** 2.48E-06 2.71E-08 5.BOE-07 2.37E-09 NO DATA 2.185-06 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 l

    **Taken from Regulator Guide 1.109 (Rev. 0)                                              '

i

D Rtvision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 O m R3for:nca Use Page 125 of 188 9 ATTACHMENT A O (Page 121 of 184) N \ OFFSITE DOSE CALCULATION MANUAL TABLE A.3-3 M INGESTION DOSE FAC"rORS FOR CHILD \ (MREM PER PCI INGESTED) 4 y NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI H 3 NO DATA 2.03E-07 2.03E-07 2.03E-07 2.C3E-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 UA 24 5.00045 5.E0E-06 C.30E-05 5.ECE-06 5.80E-0G 5.80D-CG 5. t 'A u 6 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 0 _ _.9FE-06 MN 56 NO DATA 3.34E-07 7.54E-08 NO DATA 4.04E-07 NO DAT1. 4.843-05 FE 55 1.15E-05 6.10E-06 1.89E-06 NO DATA NO DATA 3.45E-06 1.13E-06 FE 59 1.65E-05 2.67E-05 1.33E-05 NO DATA NO DATA 7.74E-C6 2.78E-05 CO 58 NO DATA 1.80E-06 5.51E-06 NO DATA NO DATA NO DATA 1.05E-05 CO 60 NO DATA 5.29E-06 1.56E-05 NO DATA NO DATA NO DATA 2.93E-05 NI 63 5.38E-04 2.88H-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 1.375-05 3.65E-05 2.27E-05 NO DATA 2.30E-05 NO DATA 6.41E-06 l ZN 69 4.38E-08 6.33E-08 5.85E-09 NO DATA 3.84E 08 NO DATA 3.99E-06 BR 83 NO DATA NO DATA 1.71E-07 NO DATA FO DATA NO DATA LT E 4 4 BR 84 NO DATA NO DATA 1.98E-07 NO DATA NO DATA NO DATA LT E-24 BR 85 NO DATA NO DATA 9.12E-09 NO DATA NO DATA NO DATA LT E-24 RB 86 NO DATA 6.70E-05 4.12E-05 NO DATA NO DATA NO DATA 4.31E-06 RB 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 7.4BE-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 ZR 95 1.16E-07 2.55E-08 2.27E-08 NO DATA 3.65E-08 NO DATA 2.66E-05 ZR 97 6.99E-09 1.01E-09 5.96E-10 NO DATA 1.45E-09 NO DATA 1.53E-04 NB 95 2.25E-08 8.76E-09 6.26E-09 NO DATA 8.23E-09 NO DATA 1.62E-05 MO 99 NO DATA 1.33E-05 3.29E-06 NO DATA 2.84E-05 NO DATA 1.10E-05 TC 99M 9.23E-10 1.81E-09 3.00E-08 NO DATA 2.63E-08 9.19E-10 1.03E-06

  *Taken from Regulator Guide 1.109 (Rev. 1)

3 ! 3 Rsvision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 p Reference Use Page 126 of 188 ATTACHMENT A I o (Page 122 of 184) g { g OFFSITE DOSE CALCULATION MANUAL : M N TABLE A.3-3 (coat'd) i INGESTION DOSE FACTORS FOR CHILD \ (MREM PER PCI INOESTED) ; 4 (P- NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI l 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 PU 105 6.45E-OS KO t.* TA :: .3 4E-08 H3 DATA S.G7E-07 N3 DATA 4.21C 05 RU los 1.17E-05 NO DATA 1.465-06 NO DATA 1.58E-05 NO DATA 1.82E-04 AG 110M 5.39E-07 3.648-07 2.91E-07 NO DATA 6.78E-07 NO DATA 4.33E-05 TE 125M 1.14L-05 3.09E-06 1.52E-06 3.20E-06 NO DATA NO DATA 1.10E-05 l TE 127M 2.89E-05 7.78E-06 3.43E-06 0.31E-06 8.24E-05 NO DATA 2.34E-05 TE 127 4.71E-07 1.27E-07 1.01E-07 3.26E-07 1.34E-06 NO DATA 1.84E-05 TE 129M 4.87E-05 1.36E-05 7.56E-06 1.57E-05 1.43E-04 NO DATA 5.94E-05 TE 129 1.34E-07 3.74E-08 3.18E-08 9.56E-08 3.92E-07 NO DATA B.34E-06 TE 131M 7.20E-06 2.49E-06 2.655-06 5.12E-06 2.41E-05 NO DATA 1.01E-04 TE 131 8.305-00 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 6.515-06 4.15E-05 NO DATA 4.50E-05 I 130 2.92E.06 5.90E-06 3.04E-06 6.505-04 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 2.77R-06 1.363-03 1.22F-05 NO DATA 2.95E-of

      .I    134 4.19E-07 7.78E-07      3.58E-07       1.79E-05             1.19E-06 NO DATA    5.16E-07 I    135 1.75E-06 3.15E-06      1.49E-06      2.795-04              4.83E-06 No DATA    2.40E-06 CS    134 2.34E-04 3.84E-04      8.10E-05       NO DATA              1.193-04 4.27E-05   2.07E-06 CS    136 2.35E-05 6.46E-05      4.18E-05       NO DATA              3.44E-05 5.13E-06   2.27E-06 CS    137 3.27E-04 3.13E-04      4.62E-05        NO DATA             1.02E-04 3.67E-05   1.96E-06 CS    138 2.28E-07 3.17E-07      2.01E-07       NO DATA              2.23E-07 2.40E-08   1.46E-07 BA    139 4.14E-07 2.21E-10      1.20E-08       NO DATA              1.93E-10 1.30E-10   2.39E-05 BA    140 8.31E-05 7.28E-08      4.85E-06        NO DATA             2.37E-08 4.34E-08   4.21E-05 BA    141 2.00E-07 1.12E-10      6.51E-09        NO DATA             9.69E-11 6.58E-10   1.1 0-07 BA    142 8.74E-08 6.29E-11      4.88E-09        NO DATA             5.09E-11 3.70E-11   1.14E-09 LA    240 1.01E-08 3.53E-09      1.19E-09        NO DATA              NO DATA  NO DATA   9.84E-05 I LA    142 5.245-10 1.67E-10      5.23E-11        NO DATA              NO DATA NO DATA    3.315-05 CE    141 3.97E-08 1.98E-08      2.94E-09        NO DATA             8.688-09 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 2.08E-06 6.52E-07      1.11E-07        NO DATA             3.61E-07  NO DATA   1.70E-04 PR    143 3.93E-08 1.18E-08      1.95E-09        NO DATA             6.39E-09  NO DATA   4.24E-05 PR    144 1.29E-10 3.99E-11      f.198-12        NO DATA             2.11E-11  NO DATA   8.59E-08 ND    147 2.79E-08 2.26E-08      1.75E-0.1       NO DATA             1.24E-08  NO DATA   3.58E-05 N    187 4.29E-07 2.54E-07      1.14E-01        NO DATA              NO DATA NO DATA    3.57E-05

%J 3 D R3 vision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 l C m Reference Use Page 127 of 188 O ATTACHMENT A O (Page 123 of 184)

 \                         OFFSITE DOSE CALCULATION MANUAL                                    i l

TAELE A.3-3 (cont'd) N INGESTION DOSE FACTORS FOR CHILD j

\                                      (MREM PER PCI INGESTED)

',A F NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI NP 239 5.25E-09 3.77E-10 2.65E-10 NO DATA 1.09E-09 NO DATA 2.79E-05 Sb 124** 1.11E-05 1.44E-07 3.89E-06 2.45E-08 NO DATA 6.16E-06 6.94E-05 th 120** 7.1CE-06 5.51E-03 1.50E-06 6.63E-09 NO DATA 3.9SE-0, 1.71L-03 Sb 126** 4.40E-06 6.73E-08 1.588-06 2.58E-08 NO DATA 2.10E-06 8.87E-05 Co 57** NO DATA 4.93E-07 9.98E-07 NO DATA NO DATA NO DATA 4.04E-06

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

1 i I l

3 g) Revision: 0 OFFSITE DOSE CALCUIATION MANUAL AP 07B-003 l 0 g RDforance Use Page 128 of 188 9 ATTACHMENT A l 0 (Page 104 of 184) ! kl i 3 g OFFSITE DOSE CALCULATION MANUAL u l TABLE A.3 18 ! 3U INGESTION DOSE FACTORS FOR INFANT k j$ (NREN PER PCI INGESTED) 2 f NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG OI-LLI I i H 3 NO DATA 3.0BE-07 3.08E-07 3.085-07 3.08E-07 3.08E-07 3.08E-07 I j C 14 2.37E-05 5.065-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 1

         ! .i    24  1.01::-00  1.01E-05    1.01C-G3   1.01C-05    1.01E-05 1.01L'-03      1.01E-05 1

P 32 1.70E-03 1.00E-04 6.59E-05 NO DATA NO DATA NO DATA 2.305-05 CR 51 NO DATA NO DATA 1.41E-08 9.20E-09 2.01E-09 1.79E-08 4.11E-07 P21 54 NO DATA 1.99E-05 4.51E-06 NO DATA 4.41E-06 NO DATA 7.31E-06 MN 56 NO DATA 8.18E-07 1.41E-07 NO DATA 7.03E-07 NO DATA 7.43E-05 4 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 a

l CO 58 NO DATA 3.60E-06 8.98E-06 NO DATA NO DATA NO DATA 8.97E-06 4 CO 60 NO DATA 1.08E-05 2.55E-05 NO DATA NO DATA NO DATA 2.57E-05 4 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 4.058-05 CU 64 NO DATA 6.09E-07 2.82E-07 NO DATA 1.03E-06 NO DATA 1.25E-05 i j ZN 65 1.84E-05 6.31E-05 2.91E-05 NO DATA 3.06E-05 NO DATA 5.33E-05 l 4 l l EN 69 9.33E-08 1.68E-07 1.25E-08 NO DATA 6.98E-08 NO DATA 1.37E-05 I i DR 83 NO DATA FO DA'"A 3.63E-U7 NO DATA NO DATA NO DATA LT E-24 l j BR 84 NO DATA NO DATA 3.82E-07 NO DATA NO DATA NO DATA LT E-24 l I 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 4.98E-07 2.73E-07 NO DATA NO DATA NO DATA 4.85E-07 i i RB 89 NO DATA 2.86E-07 1.97E-07 NO DATA NO DATA NO DATA 9.745-08 l SR 89 2.518-03 NO DATA 7.20E-05 NO DATA NO DATA NO DATA 5.16E-05 j SR 90 1.85E-02 NO DATA 4.71E-03 NO DATA NO DATA NO DATA 2.31E-04 1 1 SR 91 5.00E-05 NO DATA 1.81E-06 NO DATA NO DATA NO DATA 5.92E-05 j SR 92 1.92E-05 NO DATA 7.13E-07 NO DATA NO DATA NO DATA 2.07E-04 Y 90 8.69E-08 NO DATA 2.33E-09 NO DATA NO DATA NO DATA 1.20E-04 i

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 8.105-05 ) Y 92 7.65E-09 NO DATA 2.15E-10 NO DATA NO DATA NO DATA 1.46E-04 2 Y 93 2.43E-08 NO DATA 6.62E-10 NO DATA NO DATA NO DATA 1.92E-04 .j ZR 95 2.06E-07 5.02E-08 3.56E-08 NO DATA 5.41E-08 NO DATA 2.50E-05 j 1 ZR 97 1.48E-08 2.54E-09 1.16E-09 NO DATA 2.56E-09 NO DATA 1.62E-04 1 4 NB 95 4.20E-08 1.735-08 1.00E-08 NO DATA 1.24E-08 NO DATA 1.46E-05 i , MO 99 NO DATA 3.40E-05 6.63E-06 NO DATA 5.00E-05 NO DATA 1.12E-05 i TC 99M 1.92E-09 3.96E-09 5.10E-08 NO DATA 4.26E-00 2.07E-09 1.15E-06

      *Taken from Regulator Guide 1.109 (Rev. 1)

.) Ravision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 g Reference Use Page 129 of 188 13 ATTACHMENT A O (Page 125 of 184) N OFFSITE DOSE CALCULATION MANUAL b TA3LE A.3-4* (cont'd) M INGESTION DOSE FACTORS FOR INFANT

k. (MREM PER PCI INGESTED) di ff NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI TC 101 2.27E-09 2.86E-09 2.83E-08 NO DATA 3.40E-08 1.56E-09 4.86E-07 RU 103 1.48E-06 NO DATA 4.95E-07 NO DATA 3.08E-06 NO DATA 1.80E-05 RU 105 1.30E-07 NO DATA 4.5LC-CJ NO DATA 1.00E-06 NO DATA 5. s iE - 0.,

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-C7 4.81E-07 NO DATA 1.04E-06 NO DATA 3.77E-05 TE 125M 2.33E-05 7.79E-06 3.15E-06 ).84E-06 NO DATA NO DATA 1.11E-05 TE 127M 5.85B-05 1.94E-05 7.08E-06 1.69E-05 1.44E-04 NO DATA 2.36E-05 TE 127 1.00E-06 3.35E-07 2.15E-07 8.14E-07 2.44E-06 NO DATA 2.10E-05 TR 129M 1.00E-04 3.43E-05 1.54E-05 3.84E-05 2.50E-04 NO DATA 5.97E-05 TE 129 2.84E-07 9.79E-08 6.63E-08 2.38E-07 7.07E-07 NO DATA 2.27E-05 TE 131M 1.52E-05 6.12E-06 5.05E-06 1.24E-05 4.21E-05 NO DATA 1.03E-04 TE 131 1.76E-07 6.50E-08 4.94E-08 1.57E-07 4.50E 07 NO DATA 7.11E-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-06 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 1.25R-09 1.92E 05 5.31E 0f 3.31E-01 2.147-05 NO DATA 3.0BF-Of 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 1.91E-06 CS 136 4.59E-05 1.35E-04 5.04E-05 NO DATA 5.38E-05 1.10E-05 2.05E-06 CS 137 5.22E-04 6.11E-04 4.332-05 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 1.25h-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 8.81H-06 NO DATA 4.06E-08 1.05H-07 4.20E-05 BA 141 4.25E-07 2.91E-10 1.34E-08 NO DATA 1.75E-10 1.77E-10 5.19E-06 BA 142 1.84E-07 1.53E-10 9.06E-09 NO DATA 8.81E-11 9.26E-11 7.59E-07 LA 140 2.11E-08 8.323-09 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 1.22E-06 1.67E-07 NO DATA 4.93E-07 NO DATA 1.71E-04 PR 143 8.13E-08 3.04E-08 4.03E-09 NO DATA 1.13E-08 NO DATA 4.29E-05 PR 144 2.74E-10 1.06E-10 1.38E-11 NO DATA 3.84E-11 NO DATA 4.93E-06 ND 147 5.53E-08 5.68E-08 3.48E-09 NO DATA 2.19E-08 NO DATA 3.60E-05 W 187 9.03E-07 6.28E-07 2.17E-07 NO DATA NO DATA NO DATA 3.69E-05

l p R vision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 0 R^;for nca U23 g) Page 130 of 188 8 ATTACHMENT A O (Page 126 of 184) OFFSITE DOSE CALCULATION MANUAL a TABLE A 3-(* (c:ont' d) N INOESTION DOSE FACTORS FOR INFANT k, (MREM PER PCI INGESTED) e , @ NUCLIDE BONE LIVER T BODY THYRO 1D KIDNEY LUNG GI-LLI NP 239 1.11E-08 9.93E-10 5.61E-10 NO DATA 1.98E-09 NO DATA 2.87E-05 Sb 124** 2.14E-05 3.15E-07 6.63E-06 5.68E-08 NO DATA 1.34E-05 6.60E-05 Sb 125** 1.23E-05 1.195-07 2.53E-Ou 1.54E-03 NO LNIA 7.72d-06 1.64E-OL l l Sb 126** 8.06E-06 1.58E-07 2.91E-06 6.19E-08 NO DATA 5.07E-06 8.35E-06 I Co 57** NO DATA 1.15E-06 1.87E-06 NO DATA NO DATA NO DATA 3.92E-06

   **Taken from Regulator Guide 1.109 (Rev. 0) i 1

m 3 3 Revision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 si g Rcforence Use Page 131 of 188 f) ATTACHMENT A EE (Page 127 of 184) N OFFSITE DOSE CALCULATION MANUAL

TABLE A.3-5* N STABLE ELEMENT TRANSFER DATA Elgmant By P; (Cow) F: d) vaa/ moil Milk (d /11 Mamt (d/kal - gx i H 4.8E 00 1.0E-02 + 1.20E-02 C 5.5E 00 1.2E-02 + 3.1E-02 Na 5.2E-02 4.0E-02 3.0E-02 P 1.1E 00 2.52-C2 4.GE-02 Cr 2.5E-04 2.2E-03 2.4E-03 Mn 2.9E-02 2.5E-04 B.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 + B.0E-03 2n 4.0E-01 3.9E-02 3.0E-02 Rb 1.3E-01 3.0E-02 3.1E-02 Sr 1.7E-02 8.0E-04 + 6.0E-04 i Y 2.6E-03 1.0E-05 4.6E-03 i Zr 1.7E-04 5.0E-06 3.4E-02 l Nb 9.4E-03 2.5E-03 2.8E-01 l Mo 1.2E-01 7.5E-03 8.0E-03 Tc 2.5E-01 2.5E-02 4.0E-01 Ru 5.0E-02 1.0E-06 4.0E-01 Rh 1.3E 01 1.0E-02 1.5E-03 Ag 1.5E-01 5.0E-02 1.7E-02 Te 1.3E 00 1.0E-03 7.7E-02 I 2.0E-02 6.0E-03 + 2.9E-03 Cs 1.0E-02 1.2E-02 + 4.0E-03 Ba 5.0E-03 4.0E-04 3.2E-03 La 2.5E-03 5.0E-06 2.0E-04 Ce 2.5E-03 1.0E-04 1.2E-03 Pr 2.5E-03 5.0E-06 4.7E-03 Nd 2.4E-03 5.0E-06 3.3E-03 W 1.8E-02 5.0E-04 1.3E-03 Np 2.5E-03 5.0E-06 2.0E-04

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

Element Milk (d/11 H 1.7E-01 C 1.0E-01 P 2.5E-01 Fe 1.3E-04 Cu 1.35-02 Sr 1.4E-02 I 6.0E-02 Cs 3.0E-01

      *Taken from Regulatory Guido 1.109 (Rev. 1)

Ej s y Rsvision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 l f} ' Reference Use Page 132 of 188 l ATTACHMENT A O (Page 120 of 184) OFFSITE DOSE CALCULATION MANUAL IABLE A.4-1 SITE RELATED DOSE CCM4ITMENT FACTOR AIT g MREM /HR PER pCI/ML ff ADULT S 1 NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI ! H 3 0.00E-01 8.96E 00 8.96E 00 8.96E 00 8.96E 00 8.96E 00 8.96E 00 C 14 3.15E 04 6.3GE 03 J.3sE 03 6.30E 03 6.302 03 6.30E 03 6.30U Oa NA 24 5.4BE 02 5.48E 02 5.48E 02 5.48E 02 5.48E 02 5.48E 02 5.48E 02 P 32 4.62E 07 2.87E 06 1.79E 06 0.00E-01 0.00E-01 0.00E-01 5.20E 06 Ch 51 0.00E-01 0.00E-01 1.49E 00 8.94E-01 3.29E-01 1.98E 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 l l MN 56 0.00E-01 1.20E 02 2.12E 01 0.00E-01 1.52E 02 0.00E-01 3.82E 03 l FE 55 8.87E 02 6.13E 02 1.43E 02 0.00E-01 0.00E-01 3.42E 02 3.52E 02 ) FE 59 1.40E 03 3.29E 03 1.26E 03 0.00E-01 0.00E-01 9.19E 02 1.10E 04 CO 58 0.002-01 1.51E 02 3.39E 02 0.00E-01 0.00E-01 0.00E-01 3.06E 03 CO 60 0.00E-01 4.34E 02 9.58E 02 0.00E-01 0.00E-01 0.00E-01 8.16E 03 NI 63 4.19B 04 2.94E 03 1.41E 03 0.005-01 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 l EN 65 2.36B 04 7.50E 04 3.39E 04 0.00E-01 5.02E 04 0.00E-01 4.73E 04 EN 69 5.022 01 9.60E 01 6.67R 00 0.002-01 6.24F-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 l BR 84 0.00E-01 0.00E-01 5.67E 01 0.00E-01 0.00E-01 0.005-01 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-15l 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 RB 89 0.00E-01 1.95E 02 1.37E 02 0.00E-01 0.00E-01 0.00E-01 1.13E-11 j SR 89 4.78E 04 0.00E-01 1.37E 03 0.005-01 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 0.002-01 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 l SR 92 3.33E 02 0.00E-01 1.44E 01 0.00E-01 0.00E-01 0.00E-01 6.60E 03 Y 90 1.38E 00 0.00E-01 3.69E-02 0.00E-01 0.00E-01 0.00E-01 1.46E 04 Y 91M 1.30E-02 0.00E-01 5.04E-04 0.00E-01 0.00E-01 0.00E-01 3.82E-02 Y 91 2.02E 01 0.00E-01 5.39E-01 0.00E-01 0 00E-01 0.00E-01 1.11B 04 Y 92 1.21E-01 0.00E-01 3.53E-03 0.00E-01 0.00E-91 0.00E-01 2.12E 03 Y 93 3.83E-01 0.00E-01 1.06E-02 0.00E-01 0.00E-01 0.00E-01 1.22E 04 I ZR 95 2.77E 00 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 02 2.49E 02 1.34E 02 0.00E-01 2.46E 02 0.00E-01 1.51E 06 MO 99 0.00E-01 4.62E 02 8.79E 01 0.00E-01 1.05E 03 0.00E-01 1.07E 03 TC 99M 2.94E-02 8.32E-02 1.06E 00 0.00E-01 1.26E 00 4.07E-02 4.92E 01 s/s2

' t? 4 f Revision 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 8 g Reforcnca Use Page 133 of 188 9 ATTACHMENT A Sf (Page 129 of 184) OFFSITE DOSE CALCULATION MANUAL ') TAST E A.4 -1 (cont'd) l U SITE REIATED DOSE C064tITMENT FACTOR AIT MREM /HR PER pCI/ML j

 .ff                                                   ALOLT W

NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI TC 201 3.03E-02 4.36E-02 4.28E-01 0.00E-01 7.85E-01 2.23E-02 1.31E-13 U 103 1.S8E 01 0.0Sg-01 0.545 00 0.00E-01 7.57E 01 0.00E-01 2.31E 03 1 105 1.65E 00 0.00E-01 6.52E-01 0.00F 01 2.13E 01 0.00E-01 1.01E 03 AU 106 2.95E 02 0.00E-01 3.73E 01 0.00E-01 5.695 02 0.00E-01 1.91E 04 AG 110M 1.42E 01 1.31E 01 7.60E 00 0.00E-01 2.58E 01 0.00E-01 S.36E C3 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 2.52R 03 8.59E 02 1.80E 03 2.86E 04 0.00E-01 2.36E 04 TE 127 1.14E 02 4.11E 01 2.48E 01 8,48E 01 4.66E 02 0.00E-01 9.03E 03 TE 129M 1.20E 04 4.47E 03 1.89E 03 4.11E 03 5.00E 04 0.00E-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 8.81E 02 7.34E 02 1.39E 03 8.92E 03 0.00E-01 8.74E 04 TE 131 2.05E 01 8.57E 00 6.47E 00 1.69E 01 8.98E 01 0.00E-01 2.90E 00 TE 132 2.62E 03 1.70E 03 1.59E 03 1.87E 03 1.63E 04 0.00E-01 8.02E 04 I 130 9.01E 01 2.66E 02 1.05E 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 112 2.47.E 01 6.47E 01 2.76E 01 2.2fB 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 1.23E 31 5.94E 02 5.46E 01 0.00E-01 2.995-02 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 CS 136 3.17E 04 1.25E 05 9.01E 04 0.00E-01 6.97E 04 9.55E 03 1.42R 04 CS 137 3.88E 05 5.31E 05 3.40E 05 0.00E-01 1.80E 05 5.99E 04 1.03E 04 CS 138 2.69E 02 5.31E 02 2.63E 02 0.00E-01 3.90E 02 3.85E 01 2.27E-03 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 0.005-01 8.058-01 1.35E 00 3.BBB 03. RA 141 4.37E 00 3.30E-03 1.48E-01 0.00E-01 3.07E-03 1.87E-03 2.06E-09 RA 142 1.98E 00 2.03E-03 1~24E 01 0.005-01 1.72E-03 1.155-03 2.78E-18 LA 140 3.58E-01 1.80E-01 4.76E-02 0.00E-01 0.00E-01 0.00E-01 1.325 04 LA 142 1.83E-02 8.33E-03 2.075-03 0.005-01 0.00E-01 0.00E-01 6.08B 01 i CE 141 8.01E-01 5.42E-01 6.155-02 0.00E-01 2.52E-01 0.00E-01 2.07E 03 CE 143 1.41E-01 1.04E 02 1.16E-02 0.00E-01 4 66d-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 3.058-01 0.00E-01 5.775 03 PR 144 4.31E-03 1.79E-03 2.19E-04 0.00E-01 1.018-03 0.00E-01 6.195-10 ND 147 9.00E-01 1.04E 00 6.223-02 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

p Revision: 0 OFFSITE DOSE CALCUIATION MANUAL AP 07B-003

 @  Refercnce Uro

.g Page 134 of 188 '.6 ATTACHMENT A E (Page 130 of 184) OFFSITE DOSE CALCULATION MANUAL TAB' E A. 4 -1 (ccat'd) l7 SITE RELATED DOSE COPB4IDEENT FACTOR AIT

 \\                                       MRId4/HR PER pCI/ML g                                               ADULT f      NUCLIDE      BONE     LIVER      T BODY     THYROID      KIDNEY    LUNG     GI-LLI NP    239   1.28E-01 1.25E-02    6.91E-03    0.00E-01    3.91E-02 0.00E-01  2.57E 03 Cb    124   2.40E 02 4.53E 00    9.30E C1    5.61E 01    U.002-01 1.87E 02  6.813 03 Sb    125   1.53E 02 1.71E 00    3.65E 01    1.56E-01    0.00E-01 1.185 02  1.69E 03 Sb    126   9.85E 01 2.00E 00    3.55E 01    6.03E-01    0.00E-01 6.04E 01  8.05E 03 Co     57   0.00E-01 3.558 01    5.90E 01    0.00E-01    0.005-01 0.00E-01  9.01E 02

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

Ravision: 0 OFFSITE DOSE CALCUIATION MANUAL AP 07B-003 l ' g Reference Use' Page 135 of 188 6 ATTACHMENT A f9 (Page 131 of 104) l OFFSITE DOSE CALCUIATION MANUAL i O.\SLE A.4-2 SITE REIATED DOSE C0091I7 MENT FACTOR AIT I

 \                                                             letEN/HR PER pCI/ML
                                                                                                                           ]
 )                                                                      na W

NUCLIDE BONE LIVER T BODY THYROID EIDNEY 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 0. G.062 03 6.66E 03 0.b6E C3 6.66E 03 6.b6E 03 d.o6E OJ NA 24 5.53E 02 5.535 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 bl 0.00E-01 0.00E-01 1.525 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 8.195 03 FE 55 9.09E 02 6.45E 02 1.50E 02 0.00E-01 0.00E-01 4.09E 02 2.79E 02 FE 59 1.41E 03 3.30B 03 1.275 03 0.00E-01 0.00E-01 1.04E 03 7.79E 03 CO 58 0.00E-01 1.45E 02 3.35E 02 0.005-01 0.00E-01 0.00E-01 2.00E 03 I 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 j a 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 0.003 00 0.00F-01 4.35E 01 0.00E-01 1.33E 03 ! EN - 65 2.13E 04 7.41E 04 3.465 04 0.00E-01 4.74E 04 0.00E-01 3.14E 04 ) I FM 61 5.45E 01 1 04E 02 7.?KE 00 0.00E-01 6.7PE 01 0.00F-01 1.91E 00 BR 83 0.00E-01 0.00E-01 4.735 01 0.00E-01 0.00E-01 0.00E-01 8.24E-16 ! BR 84 0.005-01 0.00E-01 5.95E 01 0.00E-01 0.00E-01 0.00E-01 8.24E-16 , BR 85 0.00E-01 0.00E-01 2.51E 00 0.00E-01 0.00E-01 0.00E-01 8.24E-16 RB 86 0.005-01 1.10E 05 5.19E 04 0.00E-01 0.00E-01 0.00E-01 1.63E 04 RB 88 0.00E 01 3.16E 02 1.68E 02 0.005-01 0.00E-01 0.00E-01 2.71E-05 l RB 89 0.00E-01 2.04E 02 1.44E 02 0.00E-01 0.00E-01 0.00E-01 3.12E-07 SR 89 4.973 04 0.00E-01 1.425 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 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 8.77E 03 j Y 90 1.42E 00 0.00E-01 3.835-01 0.005-01 0.00E-01 0.00E-01 1.17E 04 Y 91M 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 0.005-01 5.59E-00 0.00E-01 0.00E-01, 0.005-01 8.55E 03 Y 92 1.26E-00 0.00E-01 3.63E-02 0.00E-01 0.00E-01 0.00E-01 3.44E 03 , Y 93 3.97E-00 0.00E-01 1.09E-01 0.00E-01 0.00E-01 0.00E-01 1.215 04 ZR 95 2.64E 00 8.345-01 5.74B-00 0.00E-01 1.23E 00 0.00E-01 1.92E 03 ZR 97 1.52E-00 3.018-02 1.393-01 0.005 01 4.56E-01 0.00E-01 8.15E 03 NB 95 4.50E 02 2.50E 02 1.37E 02 0.00E-01 2.42E 02 0.00E-01 1.07E 06 MO 99 0.00E-01 4.61E 02 8.78E 01 0.00E-01 1.05E 03 0.00E-01 8.25E 02 TC 99M 2.845-01 7.92E-02 1.03E 00 0.00E-01 1.185 00 4.39E-01 5.20E 01

I Rsvision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 g RafGrcnca U e Page 136 of 188 i e ATTACHMENT A O (Page 133 of 184) ' OFFSITE DOSE CALCULATION MANUAL l TABLE A.4-2 (cont;'d) I Q SITE RELATED DOSE COMMITMENT FACTOR AIT l k j MREM /HR PER pCI/ML TEEN l W NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI 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 1.153 01 0.;CE-01 0.332 00 C.00E-01 6.87E 01 0.00E-01 1.6'aB OJ RU 105 1.67E 00 0.00E-01 6.46E-00 0.00E-01 2.10E 01 0.00E-01 1.34E 03 a RU 106 2.99E 02 0.00E-01 3.77E 01 0.00E-01 5.77E 02 0.00E-01 1.44E 04 AG 11GM 1.28E 01 1.21E 01 7.36E 00 0.00E-01 2.31E 01 0.00E-01 3.40E 03 TE 125M 3.02E 03 1.09E 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 4.41B 01 2.68E 01 8.59E 01 5.04E 02 0.00E-01 9.61E 03 TE 129M 1.2BE 04 4.77E 03 2.03E 03 4.14E 03 5.375 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 TB 131M 1.92E 03 9.22E 02 7.69E 02 1.39E 03 9.61E 03 0.00E-01 7.40E 04 TB 131 2.20E 01 9.06E 00 6.87E 00 1.69E 01 9.61E 01 0.003-01 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 2.08E 04 3.92E 02 0.00E-01 1.968 02 I 131 5.00E 02 7.00E 02 3.76E 02 2.04E 05 1.21E 03 0.00E-01 1.39E 02 T 112 2.39E 01 6.74E 01 2.24F 01 2.10E 03 9.81E 01 0.00E-01 2.72E 01 1 133 1.72E 02 2.92E 02 8.89E 01 4.07E 04 5.11E 02 0.00E-01 2.21E 02 I 134 1.25E 01 3.31E 01 1.198 01 5.51E 02 5.22E 01 0.00E-01 4.36E-01 I 135 5.22E 01 1.34E 02 4.98E 01 8.64E 03 2.12E 02 0.00E-01 1.49E 02 CS 134 3.10E 05 7.30E 05 3.39E 05 0.00E-01 2.32E 05 8.86E 04 9.08E 03 CS 136 3.18E 04 1.25E 05 8.41E 04 0.00E-01 6.82E 04 1.07E 04 1.01E 04 CS 137 4.15E 05 5.52E 05 1.92E 6) 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 2.873 03 BA 141 4.39E 00 3.28E-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 6.018-12 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 7.9BE-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 1.15H-01 0.00E-01 4.60E-01 0.00E-01 3.08E 03 I 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 6.765-01 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 1.06B 00 6.34E-01 0.00E-01 C.21E-00 0.00E-01 3.82E 03 W 187 3.28E 02 2.67E 02 9.37E 01 0.00E-01 0.00E-01 0.00E-01 7.24E 04

p Ravicion: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 6 R3ference Use g1 Page 137 of 188 9 ATTACHMENT A b (Page 133 of 184) OFFSITE DOSE CALCULATION MANUA.L id T.1BLE A.4-2 (cont' d) SITE RELATED DOSE COMMITMENT FACTOR AIT MREM /HR PER pCI/ML TEEN NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI 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 2.32C C2 4.20E 00 9.05E 01 C.2G2 00 0.00E-01 2.L3E O. 4.5dE GJ Sb 125 1.49E 02 1.63E 00 3.48E 01 1.42E-00 0.00E-01 1.31E 02 1.16E 03 Sb 126 9.53E 01 1.95E 00 3.42E 01 5.39E-00 0.00E-01 6.84E 01 5.64E 03 Co 57 0.00E-01 3.55E 01 5.96E 01 0.00E-01 0.00E-01 0.00E-01 6.63E 02 l l

p Revision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 g Reference Use Page 138 of 188 9 ATTACHMENT A O (Page 134 of 194) OFFSITE DOSE CALCULATION MANUAL TA3LU A.4 3 KI SITE REIATED DOSE COMMITMENT FACTOR AIT k MREM /HR PER pCi/ML d CHILD ff NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI H 3 0.00E-01 1.19E 01 1.19E 01 1.19E 01 1.19E 01 1.19B 01 1.198 01 L 14 4.4SC C4 U.Sbu C3 8.303 OJ 0.$JE 03 8.90E 03 0.908 03 d. 'JOE 03 NA 24 7.93E 02 7.93E 02 7.93E 02 7.93E 02 7.93E 02 7.93E 02 7.93E 02 P 32 6.49B 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 MN 56 0.00E-01 1.25E 02 2.81E 01 0.00E-01 1.51E 02 0.00E-01 1.80E 04 FE 55 1.57E 03 8.34E 02 2.59E 02 0.00E-01 0.00E-01 4.72E 02 1.55E 02 FE 59 2.26E 03 3.65E 03 1.82E 03 0.00E-01 0.00E-01 1.06E 03 3.80E 03 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 0.005-01 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.?4r 00 0.00E-01 E.2CE 01 D.0CE-01 6.51R 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 0.005-01 1.09E 05 6.72E 04 0.00E-01 0.00E-01 0.00E-01 7.03E 03 RB 88 0.00E-01 3.10E 02 2.15E 02 0.00E-01 0.00E-01 0.00E-01 1.52E 01 RB 89 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 8.56E-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 4.6BE 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 8.092 03 Y 93 8.87E-00 0.00E-01 2.445-01 0.00E-01 0.00E-01 0.00E-01 1.32E 04 2R 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-01 9.29E 03 NB 95 5.32E 02 2.07E 02 1.40E 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

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

1 Reference Use Page 139 of 188 ATTACHMENT A l k (Page 2 35 of 15M) l OFFSITE DOSE CALCULATION MANUAL M '~~, TA:'.LU A . 4 -3 (c,mt'd) l SITE RELATED DOSE COMMITMENT FACTOR AIT l

\,                                        MREM /HR PER pC1/ML                                  l

, CHILD NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI TC 101 7.48E-01 7.83E-02 9.93E-00 0.00E-01 1.34E 00 4.14E-01 2.49E-01 RJ 103 4.836 01 c.00E 01 1.0LE C1 c.00L-01 1.21E 02 0.002-01 1.c.3 03 RU 105 4.263 00 0.00E-01 1.54E 00 0.00E-01 3.74E 01 0.00E-01 2.78E 03 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 5.67E 02 1.19E 03 0.00E-01 0.00E-01 4.10E 03 TE 127M 1.08E 04 2.90E 03 1.28E 03 2.58E 03 3.07E 04 0.00E-01 8.72E 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 1.39B 01 1.19E 01 3.56E 01 1.46E 02 0.00E-01 3.11E 03 TE 131M 2.6BE 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 TE 132 3.77E 03

47E 03 2.01E 03 2.43E 03 1.55E 04 0.00E-01 1.68E 04 I 130 2.04E 02 4.13E 02 2.13E D2 4.55E 04 6.17E 02 0.00E-01 1.93E 02 I 131 1.20E 03 1.21E 03 6.88E 02 4.00E 05 1.99E 03 0.00E-01 1.08E 02 I 132 5.G99 03 1.03E 02 4.73R 6: 4.7?E 03 1.57E 01 0.00P-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 3.82C 05 6.26E 05 1.32E 05 0.00E-02 1.94E 05 6.97E 04 3.38E 03 CS 136 3.03E 04 1.05E 05 6.82E 04 0.00E-Oi 5.61E 04 8.37E 03 3.70E 03 CS 137 5.33B 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 2.3BE 02 BA 139 2.54E 01 1.35E-02 7.35E-00 0.00E-01 1.18E-01 7.97E-02 1.47E 03 BA 140 5.09E 03 4.46E 00 2.97E 02 0.00E-01 1.45E 00 2.66E 00 2.58E 03 BA 141 1.238 01 6.86E-03 3.998-00 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 0.005-01 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 1.175 00 1.73E-00 0.00E-01 5.11E-00 0.00E-01 1.46E 03 CE 143 4.125-00 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 3.5BE 04

'l

_ _f __ ., g Rsvicion: 0 OFFSITE D?9R CALCULATION MANUAL AP 07B-003 9 g R fortnc3 U;a Page 140 of 188 9 ATTACHMENT A O (Page 136 of 184) OFFSITE DOSE CALCULATION MANUAL TABLE A.4-3 (ccat'd) , FITE RELATED DOSE COMMITMENT FACTOR AIT ' s MREM /HR PER pCi/ML

,j                                                  CHILD NUCLIDE    BONE     LIVER       T BODY         THYROID     KIDNEY    LUNG      OI-LLI N2    239 3.4"E-00 2.49E-02     1.75E-01        0.00E-01   7.1DE-C1 0.00E-01 l

1.54E 03 Sb 124 6.54E 02 8.49E 00 2.29E 02 1.44E 00 0.00E-01 3.63E 02 4.09E 03 Sb 125 4.22E 02 3.2SE 00 8.84E 01 3.91E-00 0.00E-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 l Co 57 0.00E-01 4.81E 01 9.73E 01 0.00E-01 0.00E-01 0.00E-01 3.948 02 l

Revision:~0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 1 RofGrcnce Uso Page 141 of 188 ATTACHMENT A i (Page 137 of 184) ; l OFFSITE DOSE CALCULATION MANUAL i i

 --                                                                                                           i TABLE A.4-4 f                                 SITE RELATED DOSE Col #IITMENT FACTOR AIT                                  ,

MREN/HR PER pCI/ML INFANT NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI H 3 0.00E-01 1.16E 01 1.16E 01 1.16E 01 1.16E 01 1.16E 01 1.16E 01 0 14 8.920 02 1.!OE 02 1.700 02 1.90E 02 1.90E C2 1.90L 02 1.00E 02 NA 24 3.80E 02 3.80E 02 3.80E 02 3.80E 02 3.80E 02 3.80E 02 3.80E 02 P 32 6.40E 04 3.76E 03 2.4BE 03 0.00E-01 0.00E-01 0.00E-01 8.65E 02 CR 51 0.00E-01 0.00E-01 5.30E-01 3.46E-01 7.56E-02 6.73E-01 1.55E 01 MN 54 0.00E-01 7.49E 02 1.70E 02 0.00E-01 1.66E 02 0.00E-01 2.75E 02 MN 56 0.00E-01 3.0BE 01 5.30E 00 0.00E-01 2.64E 01 0.00E-01 2.80E 03 I FE 55 5.23E 02 3.38E 02 9.03E 01 0.00E-01 0.00E-01 1.65E 02 4.29E 01 i FE 59 1.16E 03 2.02E 03 7.985 02 0.00E-01 0.00E-01 5.98L' 02 9.67E 02 ! l CO 58 0.00E-01 1.35E 02 3.38E 02 0.00E-01 0.00E-01 0.00E-01 3.37E 02 l CO 60 0.00E-01 4.06E 02 9.59E 02 0.00E-01 0.00E-01 0.00E-01 9.67E 02 l 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 1.77B 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 2.61E 00 0.00E-01 5.15R 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 0.005-01 0.00E-01 1.44E 01 0.00E-01 0.00E-01 0.005-01 3.76E-17 1 i BR 85 0.00E-01 0.005-01 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 j RB 88 0.00E-01 1.87E 01 1.03E 01 0.00E-01 0.00E-01 0.00E-01 1.82B 01 RB 89 0.00E-01 1.088 01 7.41E 00 0.00E-01 0.00E 01 0.00E-01 3.66E 00 SR 89 9.44E 04 0.005-01 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 0.005-01 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 7.79E 03 Y 90 3.27E 00 0.00E-01 8.77E-02 0.005-01 0.00E-01 0.00E-01 4.51E 03 Y 91M 3.05E-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 2.885-01 0.00E-01 8.09E-03 0.00E-01 0.00E-01 0.005-01 5.49E 03 Y 93 9.14E-01 0.000-01 2.49E-02 0.00E-01 0.00E-01 0.00E-01 7.22E 03 ZR 95 7.75E 00 1.89E 00 1.348 00 0.00E-01 2.04E 00 0.00E-01 9.41E 02 ZR 97 5.57E-01 9.56E-02 4.36E-02 0.00E-01 9.63E-02 0.00E-01 6.09E 03 NB 95 1.58E 00 6.515-01 3.765-01 0.00E-01 4.66E-01 0.00E-01 5.49E 02 MO 99 0.00E-01 1.2BE 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

R;vicion: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 i R3ferenca U::n Page 142 of 188 ATTACHMENT A (Page 118 of 184) OFFSITE DOSE CALCULATION MANUAL

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

SITE REIATED DOSE COMMITMENT FACTOR AIT MREM /HR PER pCI/ML IN1AhT NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI TC 101 8.548-02 1.08E-01 1.06E 00 0.00E-01 1.28E 00 5.87E-02 1.83E 01 RU 103 5.57F 01 0.00E-01 1.86S 01 C.ZE-01 1.1% 02 0.001:-01 b.r/E 04 RU 105 5.12E 00 0.00E-01 1.72E 00 0.00E-01 3.76B 01 0.00E-01 2.04E 03 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-01 1.42E 03 TE 125M 8.77E 02 2.93E 02 1.19E 02 2.95E 02 0.00E-01 0.005-01 4.18E 02 TE 127M 2.20E 03 7.30E 02 2.66E 02 6.36E 02 5.42B 03 0.00E-01 8.88E 02 TE 127 3.76E 01 1.26E 01 0.09E 00 3.06B 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 TB 131M 5.72E 02 2.30E 02 1.90E 02 4.66E 02 1.58E 03 0.00E-01 3.87E 03 TE 131 6.62E 00 2.45E 00 1.86E 00 5.91E 00 1.69E 01 0.00E-01 2.67E 02 TE 132 7.82E 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 I 131 1.35E 03 1.59E 03 7.00E 02 5.232 05 1.86E 03 0.0v2 01 5.6BE 01 I 132 6.24E 01 1.27E 02 4.51R 01 5.94R 01 1.41F 02 0.00E-01 1.03R 02 I 133 4.70E 02 6.05E 02 2.01E 02 1.25E 05 8.05E 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 2.64B 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 3.31B 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 1.143 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 2.36B 01 8.16E 00 0.00E-01 0.00E-01 0.00E-01 1.39E 03

W p Revision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 g Reference Use Page 143 of 188 ATTACHMENT A 9; (Page 139 of 184) OFFSITE DOSE CALCULATION MANUAL TABLE A.4-4 (cont'd) SITE REIATED DOSE COMMITMENT FACTOR AIT MREM /HR PER pCI/ML INFANT F NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI NP 239 4.18E-01 3.74E-02 2.11E-02 0.00E-01 7.45E-02 0.00E-01 1.08E 03 SL 124 0.05E 02 1.19E 01 2.49E 02 2.14E 00 0.00"-01 5.04E 0; 1.48it 03 l Sb 125 4.63E 02 4.48E 00 9.52E 01 5.79E-00 0.00E-01 2.90E 02 6.17E 02 1 Sb 126 3.03E 02 5.94E 00 1.09E 02 2.33E 00 0.005-01 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 I l l l i l i I

p Rovicion: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 fl R3fcrcnce U e Page 144 of 188 ATTACHMENT A h (Page 140 of 184) OFFSITE DOSE CALCULATION MANUAL

     -o TABLE A.5-1 INHALATION DOSE PARAMETER FOR THE CHILD, PI MREM /YR per pCi/*1' l

H-3 1.12E 03 RU-103 6.62E 05 C-14 3.59E 04 RU-105 9.95E 04 NA-24 1.61E 04 RU-106 1.43E 07 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 5.62R 04 FE-55 1.11E 05 TE-129M 1.76E 05 FE-59 1.27E 06 TE-129 2.55E 04 CO-58 1.11E 06 TE-131M 3.08E On CO-60 7.07E 00 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-65 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 5.40E 02 I-135 7.92E 05 BR-85 2.53E 01 CS-134 1.01E 06 RB-86 1.98E 05 CS-136 1.71E 05 RB-88 5.62E 02 CS-137 9.07E 05 RB-89 3.45E 02 CS-138 8.40E 02 SR-89 2.16E 06 BA-139 5.77E 04 SR-90 1.01E 08 BA-140 1.74E 06 SR-91 1.74E 05 BA-141 2.92E 03 SR-92 2.42E 05 BA-142 1.64E 03 Y-90 2.68E 05 LA-140 2.26E 05 Y-91M 2.81E 03 LA-142 7.59E 04 Y-92 2.398 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 1C-99M 4.81E 03 NP-239 6.40E 04 TC-101 5.85E 02

     -1 Ravision: 0             OFFSITE DOSE CALCULATION MANUAL                     AP 07B-003 R;for;nca Ura                                                          Page 145 of 188 6

ATTACID4ENT A O (Page 141 of 184) f

     - - -$3 OFFSITE DOSE CALCULATION MANUAL TAs m s.5-2 Q

V INHALATION PATHWAY FACTOR MREM /YR PER pCI/M' AuuLT (RI FACrokS) NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI H 3 0.00E 01 1.26E 03 1.26E 03 1.26E 03 1.26E 03 1.26E 03 1.26E 03 C 1: 1.025 01 .41E 03 2.GIE 0's 3.413 03 3.41E 03 3.4r3 00 3.41E L3 NA 24 1.02E 04 1.02B 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 8.64B 04 CR 51 0.00E 01 0.00E 01 1.00E 02 5.95E 01 2.282 01 1.44E 04 3.32E 03 MN 54 0.005 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 1.5BE 03 2.07E 03 0.00E-01 0.00E-01 9.28E 05 1.06E 05 CO 60 0.00E 01 1.15E 04 1.4BE 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 ZN 65 3.24E 04 1.03E 05 4.66E 04 0.00E-01 6.90E 04 8.64E 05 5.34E 04 ZN 64 3.39F-02 6.51F-01 4.52E 03 0.00E-01 4.22E-02 9.20E 09 1.63E 01 BR 83 0.00E-01 0.00E-01 2.41E 02 0.00E-01 0.00E-01 0.00E-01 2.328 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 8.00E-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 s2 0.00E-01 0.00E-01 0.00E-01 3.34E-09 RB 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 BR 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-01 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 ZR 97 9.68E 01 1.96E 01 9.048 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

p Rr,vicion: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 & RCforrnca U2O g Page 146 of 188 9 ATTACHMENT A O (Page 142 of 184) OFFSITE DOSE CALCULATION MANUAL "IO TAELE A.5-2 (cont'd) INHALATION PATHWAY FACTOR

\                                      MREM /YR PER pCI/M' j

ADULT (RI FAL. TORS)

V NUCLIDE BONE LIVER T LODY THYROID KIDNEY LUNG GI-LLI TC 101 4.18E-05 6.02E-05 5.90E-04 0.00E-01 1.08E-03 3.99E 02 1.09E-11 G 03 1.!aE 03 0.00E-01 6.50E 02 0.COE-01 b.83E 03 5.0LE 05 1. hL 03 RU 105 7.90E-01 0.00E-01 3.11E-01 0.00E-01 1.02E 00 1.10E 04 4.82E 04 RU 106 6.91E 04 0.00E-01 8.72E 03 0.00E-01 1.34E 05 9.36E 06 9.12E 05 AG 110M 1.08E 01 1.00E 04 5.94E 03 0.00E-01 1.97L 04 4.63E 06 3.02E 05 TE 125M 3.42E 03 1.58E 03 4.67E 02 1.05E 03 1.24E 04 3.14E 05 7.06E 04 TE 127M 1.26E 04 5.77E 03 1.57E 03 3.29E 03 4.58E 04 9.60E 05 1.502 05 TB 127 1.40E 00 6.42E-01 3.10E-01 1.06E 00 5.10E 00 6.51E 03 5.74E 04 TE 129M 9.76E 03 4.67E 03 1.588 03 3.44E 03 3.66E 04 1.16E 06 3.83E 05 TE 129 4.98E-02 2.39E-02 1.24E-02 3.90E 02 1.87E-01 1.94E 03 1.57E 02 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 I 132 1.16E 03 3.2GE 03 1.1CE 03 ' ,14E 05 5.18R 01 0.00E 01 4.0EE 02 I 133 0.642 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 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 8.48E 05 7.28B 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 l BA 141 1.00E-01 7.53E-05 3.36E-03 0.00E-01 7.00E-05 1.94E 03 1.16E-07 l EA 142 2.63E-02 2.70E-05 1.66E-03 0.00E-01 2.29E-05 1.19E 03 1.57E-16 LA 140 3.44E 02 1.74E 02 4.58E 01 0.00E-01 0.00E-01 1.36E 05 4.58E 05 LA 142 6.83E-01 3.10E-01 7.72E-02 0.00E-01 0.00E-01 6.33E 03 2.11E 03 i 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 2.26E 05 CE 144 3.43E 06 1.43E 06 1.84E 05 0.00E-01 8.4BE 05 7.78E 06 8.16E 05 , PR 143 9.36E 03 3.75E 03 4.64E 02 0.00E-01 2.16E 03 2.81E 05 2.00E 05 J PR 144 3.10E-02 1.25E-02 1.53E-03 0.00E-01 7.05E-03 1.02E 03 2.15E-08 ND 147 5.27E 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 2.40E 00 0.00E-01 0.00E-01 2.90E 04 1.55E 05 l l NP 239 2.30E 02 2.26E 01 1.24E 01 0.00E-01 7.00E 01 3.76E 04 1.19E 05 l l

R2 vision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 g R3for nco Uzo Page 147 of 188 8 ATTACHMENT A k (Page 143 of 3 94 ) OFFSITE DOSE CALCULATION MANUAL TA3T3 A.5-3 9 INHALATION PATHNAY FACTOR ! MREM /YR PER pCI/M* ; g FEEN (RI FACTORS) W NUCLIDE BONE LIVER T BOY THYROID KIDNEY LUNG GI-LLI H 3 0.00E-01 1.27E 03 1.27E 03 1.27E 03 1.27B 03 1.278 03 1.27E 03 C 11 2.CO2 04 1.67E C3 4.B70 03 4.87E 03 4.a7E 01 *. 070 C3 4.8?b C3 NA 24 1.38E 04 1.38E 04 1.38E 04 1.38E 04 1.38E 04 1.38E 04 1.38E 04 P 32 1.89E 06 1.10E 05 7.16E 04 0.00E-01 0.00E-01 0.00E-01 9.20E 04 CR 51 0.00E-01 0.00U-01 1.35E 02 7.50E 01 3.07E 01 2.10E 04 3.003 03 MN 54 0.00E-01 5.11E 04 8.40E 03 0.00E-01 1.27E 04 1.98E 06 6.6BE 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 FE 59 1.59E 04 3.70E 04 1.43E 04 0.00E-01 0.00E-01 1.53E 06 1.78E 05 l 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 1.51B 04 1.98E 04 0.00E-01 0 00E-01 8.72E 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 1.278-01 0.00E-01 0.00E-01 9.36E 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 ZN 65 3.86E 04 1.34E 05 6.24E 04 0.00E-01 8.64E 04 1.248 06 4.66E 04 1 2N 69 4.83E-02 9.20E-02 E 4CE-03 0.00F-01 6.02E-02 1.58E 03 2.85R 07

BR 83 0.00E-01 0.00E-01 3.44E 02 0.00E-01 0.00E-01 0.00E-01 8.00E-15 BR 84 0.00E-01 0.00E-01 4.33E 02 0.00E-01 0.00E-01 0.00E-01 8.00E-15 BR 85 0.00E-01 0.00E-01 1.83E 01 0.00E-01 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 RB 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 3.3BE-07 SR 89 4.34B 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 i 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 j 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 1.38E 02 2.72E 01 1.26E 01 0.00E-01 4.12E 01 1.30E 05 6.30E 05 NB 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 1.695 02 3.22E 01 0.00E-01 4.11E 02 1.54B 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

y Rsvision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 i l N M Raforenca U:e Page 148 of 188 l El ATTACHMENT A EE (Page 144 of 184) b , t OFFSITE DOSE CALCULATION MANUAL TAMLB A.5-3 (cont'd) l7 INHALATION PATHWAY FACTOR k MREM /YR PER pCI/M3

f TEEN (RI FACTORS)

W NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI l TC 101 5.92E-05 8.40E-05 8.24E-04 0.00E-01 1.52E-03 6.67E 02 8.72E-07 RU 103 2.10" 03 0.00E-01 8.96L 02 0.0CE-01 7.43E C; 7.63L OS 1.0Sa 03 l RU 105 1.12E 00 0.00E-01 4.34B-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 AG 110M 1.38E 04 1.31E 04 7.99E 03 0.00E-01 2.50E 04 6.75E 06 2.738 05 TE 125M 4.88E 03 2.24E 03 6.74E 02 1.40E 03 0.00E-01 5.36E 05 7.50E 04 TE 127M 1.80E 04 8.16E 03 2.182 03 4.38E 03 6.54E 04 1.66E 06 1.59E 05 TE 127 2.01E 00 9.12E-01 4.42E-01 1.42E 00 7.28E 00 1.12E 04 8.08E 01 TE 129M 1.395 04 6.5BE 03 2.25E 03 4.58E 03 5.19E 04 1.98E 06 4.05E 05 TE 129 7.10E-02 3.38E-02 1.76E-02 5.18E-02 2.66E-01 3.30E 03 1.62E 03 TE 131H 9.84E 01 6.01E 01 4.20E 01 7.25E 01 4.39E 02 2.38E 05 6.21E 05 TE 131 1.5BE-02 8.32E-03 5.04E-03 1.24E-02 6.18E-02 2.34E 03 1.51B 01 TE 132 3.60E 02 2.90E 02 2.198 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 l I 132 1.59E 03 4.30E 03 1.58R 03 1.51R 05 6.92E 03 0.00E-01 3.27? 03 I 133 1.22E 04 2.05E 04 6.22E 03 2.92E 06 3.59E 04 0.00E-01 1.03E 04 I 134 8.88E 02 2.32E 03 8.40E 02 3.95E 04 3.66E 03 0.00E-01 2.04E 01 1 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 j l CS 137 6.70E 05 8.48E 05 3.11E 05 0.00E-01 3.04E 05 1.21E ?$ 8.4BE 03 CS 138 4.66E 02 b.56E 02 4.46E 02 0.00E-01 6.62B 02 7.87B 01 2.70E-01 I BA 139 1.34E 00 9.44E-04 3.908-02 0.00E-01 8.88E-04 6.465 03 6.45E 03 l l BA 140 5.47E 04 6.70E 01 3.52E 03 0.00E-01 2 28E 01 2.03E 06 2.29E 05 BA 141 1.42E-01 1.06E-04 4.74E-03 0.00E-01 9.84E-05 3.29E 03 7.46E-04 BA 142 3.70E-02 3.70E-05 2.27E-03 0.00E-01 3.14E-05 1.91E 03 4.79E-10 IA 140 4.79E 02 2.36E 02 6.26E 01 0.00E-01 0.00E-01 2.14E 05 4.87E 05 l LA 142 9.60E-01 4.25E-01 1.06E-01 0.00E-01 0.00E-01 1.02E 04 1.20E 04 CE 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 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 8.56E 03 5.13E 02

0.00E-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 3.38B 02 3.19E 01 1.77E 01 0.00E-01 1.00E 02 6.49E 04 1,32E 05 l

O p R vicion: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 & R;forence Use g Page 149 of 188 9 ATTACHMENT A O (Page 145 of 184) OFFSITE DOSE CALCULATION MANUAL TALLE A.5-4 INHALATION PATHWAY FACTOR ( MREM /YR PER pCI/M8 l 3 CHILD (RI FACTORS) If NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI I 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 3.398 0e 6.738 Da 6.73E 03 6.?au 03 6.13E 03 6.7JE 03 6. */JE 03 NA 24 1.61E 04 1.61E 04 1.61E 04 1.61E 04 1.61E 04 1.61E 04 1.61E 04 I 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 MN 54 0.00E-01 4.29E 04 9.51E 03 0.00E-01 1.00E 04 1.58B 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 7.77B 03 0.00E-01 0.00E-01 1.11E 05 2.87E 03 FE 59 2.07E 04 3.34E 04 1.67E 04 0.00E-01 0.00E-01 1.27E 06 7.07E 04 CO 58 0.00E-01 1.77E 03 3.16E 03 0.00E-01 0.00E-01 1.11E 06 3.44E 04 CO 60 0.00E-01 1.31E 04 2.26E 04 0.00E-01 0.00E-01 7.07E 06 9.62E 04 NI 63 8.21E 05 4.63E 04 2.80E 04 0.00E-01 0.00E-01 2.75E 05 6.33E 03 NI 65 2.99E 00 2.96E-01 1.64E-01 0.00E-01 0.00E-01 8.18E 03 8.40E 04 CU 64 0.00E-01 1.99E 00 1.07E 00 0.00E-01 6.03E 00 9.58E 03 3.67E 04 EN 65 4.26E 04 1.13E 05 7.03E 04 0.00E-01 7.14E 04 9.95E 05 1.63E 04 ZN 69 G.70E-02 9.6KE-02 8.92F-01 0.00E-01 5.85E-02 1.42E 03 1.02,7 04 BR 83 0.00E-01 0.00E-01 4.74E 02 0.00E-01 0.00E-01 0.00E-01 3.70E-15 BR 84 0.00E-01 0.00E-01 5.48E 02 0.00E-01 0.00E-01 0.00E-01 1-70E-15 BR 85 0.00E-01 0.00E-01 2.53E 01 0.00E-01 0.00E-01 0.00E-01 3.708-15 RB 86 0.00E-01 1.98E 05 1.14E 05 0.00E-01 0.00E-01 0.00E-01 7.99E 03 RB 88 0.00E-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 1.48E 07 3.438 05 SR 91 1.21E 02 0.00E-01 4.59E 00 0.00E-01 0.00E-01 5.33E 04 1.74E 05 l 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 5.078-01 0.00E-01 1.84E-02 0.00E-01 0.00E-01 2.81E 03 1.72E 03 Y 91 9.14F 05 0.00E-01 2.44E 04 0.00E-01 0.00E-01 2.63E 06 1.84B 05 Y 92 2.04E 01 0.00E-01 5.815-01 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 9.18E 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 1.358 05 1.27E 05 TC 99M 1.78E-03 3.48E-03 5.7?E-02 0.00E-01 5.07E-02 9.51B 02 4.81E 03 9/93

p Rnvicion: 0 OFFSITE DOSE CALCULATION MAN 4 AP 07B-003 S ROforcnco Use y Page 150 of 188 0 ATTACHMENT A O (Page 346 of 194) OFFSITE DOSE CALCULATION MANUAL TABLE A.5-4 { cont'd) INHALATION PATHWAY FACTOR MREM /YR PER pCI/M' [\ CHILD (RI FACTORS) F NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI 1 TC 101 8.10E-05 8.51E-05 1.08E-03 0.00E-01 1.45E-03 5.85E 02 1.635 01 12 10 2.73E C3 0.002 -C1 1.07E 03 0.00E-01 7.038 03 6.ti2E c5 4.etad 04 RU 105 1.53E 00 0.00E-01 5.55E-01 0.00E-01 1.34E 00 1.59E 04 9.95E 0( RU 106 1.36E 05 0.00E-01 1.69E 04 0.00E-01 1.84E 05 1.43E 07 4.29E 05 l AG 110M 1.69E 04 1.14E 04 9.14E 03 0.00E-01 2.12E 04 5.48E OG 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 TE 6.85E 03 5.62E 04 l 129M 1.92E 04 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 2.062 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 4.01E 02 2.72B 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.PBE 0? 1.94E 05 6.2SE 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 1.175 03 2.16E 03 9.95E 02 5.07E 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 9.07E 05 8.25E 05 1.28E 05 0.00E-01 2.82E 05 1.04E 05 3.62E 03 CS 138 6.33E 02 8.40E 02 5.55E 02 0.00E-01 6.22E 02 6.81E 01 2.70E 02 BA 139 1.84E 00 9.84E-04 5.36E-02 0.00E-01 8.62E-04 5.77E 03 5.77E 04 RA 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 4.995-02 3.60E-05 2.79E-03 0.00E-01 2.91E-05 1.64E 03 2.74E 00 LA 140 6.44E 02 2.25E 02 7.55E 01 0.00E-01 0.00E-01 1.83E 05 2.26E 05 LA 142 1.29E 00 4.11E-01 1.29E-01 0.00E-01 0.00E-01 8.70E 03 7.59E 04 CE 141 3.92E 04 1.95E 04 2.90E 03 0.00E-01 8.55E 02 5.44E 05 5.66E 04 CE 143 3.66E 02 1.998 02 2.87E 01 0.00E-01 8.36E 01 1.15E 05 1.27E 05 CE 144 6.77E 06 2.12E 06 3.61E 05 0.00E-01 1.17E 06 1.20B 07 3.89E 05 PR ?43 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 D3 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 6.40B 04 9/92

p Revision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 g Refersnca Use Page 151 of 188 ATTACHMENT A

 #                                   (Page 14*7 of 184)
 \\                         OFFSITE DOSE CALCULATION MANUAL A)

TABLE A.5-5 4 IMHAIATION PATHWAY FACTOR

 \\                                      MREM /YR PER pCI/M3 g                                      INFANT (RI FACE RS) f NUCLIDE   BONE       LIVER     T BODY                  THYROID  KIDN8 i;                     LUNG-                  GI-LLI H      3 0.00E-01   6.47E 02   6.475 02                6.47E 02 6.47E 02                    6.47E 02                6.47E 02 0    14 2.552 04   5.51E 03   L.31L 03                5.31E 03 5.31E 03                    5.31E 04                S.31d 03 i       NA    24 1.06E 04   1.065 04   1.06E 04                1.065 04 1.06E 04                    1.06E 04                1.06E 04 a

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 8.95E 01 5.758 01 1.32E 01 1.28E 04 3.57E 02 MN 54 0.00E-01 2.53E 04 4.98E 03 0.00E-01 4.98E 03 1.002 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 l FE 55 1.97E 04 1.17E 04 3.33E 03 0.00E-01 0.00E-01 8.69E 04 1.09E 03 j FE 59 1.36E 04 2.35E 04 9.48E 03 0.00E-01 0.00E-01 1.02E 06 -2.48E 04 i

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 8.02R 03 1.18E 04 0.00E-01 0.005-01 4.51E 06 3.19E 04 i 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 7.745-01 0.00E-01 3.98E 00 9.30E 03 1.50E 04 ZN 65 1.93E 04 6.26E 04 3.11E 04 0.00E-01 3.25E 04 6.47E 05 5.14E 04 I 7N 69 5.39E-02 0.67E-02 7.18F.01 0.003-01 4.02E-02 1.4?E 03 1.32F Cl BR 83 0.00E-01 0.00E-01 3.81E 02 0.00E-01 0.00E-01 0.00E-01 1.40E-15 i BR 84 0.00E-01 0.00E-01 4.00E 02 0.003-01 0.00E-01 0.00E-01~ 1.40E-15 j i , BR 85 0.00E-01 0.00E-01 2.04E 01 0.00E-01 0.00E-01 0.00E-01 1.40E-15 I RB 86 0.00E-01 1.90E 05 8.828 04 0.00E-01 0.00E-01 0.00E-01 3.04E 03 } RB 88 0.00E-01 S.57E 02 2.875 02 0.00E-01 0.00E-01 0.00E-01 3.393 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 0.00E-01 0.00E-01 2.03E 06 6.40E 04 , SR 90 4.095 07 0.00E-01 2.59E 06 0.00E-01 0.005-01 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 I SR 92 1.05E 01 0.00E-01 3.91E-01 0.00E-01 0.00E-01 2.38E 04 1.40E 05 i Y 90 3.29E 03 0.00E-01 4.82E 01 0.005-01 0.00E-01 2.69E 05 1.04E 05 i 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 l 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 ZR 97 1.50E 02 2.56E 01 1.17E 01 0.005-01 2.59E 01 1.105 05 1.40E 05 NB 95 1.57E 04 6.43E 03 3.78E 03 0.00E-01 4.72E 03 4.79E 05 1.27E 04 MO 99 0.00E-01 1.65E 02 3.23E 01 0.00E-01 2.65E 02 1.35E 05 4.87E 04

TC 99M 1.40E-04 2.88E-03 3.723-02 0.00E-01 3.11E-02 8.11E 02 2.03E 03 i

i

il p R: vision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 gi . R fer:nca Urs Page 152 of 188 dP ATTACHMENT A E (Page 148 of 184) OFFSITE DOSE CALCULATION MANUAL TA3'l.3 A.5-5 (cont'd) l' INHALATION PATHWAY FACTOR MREM /YR PER pCI/M 3 INFANT (RI EACTORS) f NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI l TC 101 6.51E-05 8.23E-05 8.12E-04 0.00E-01 9.79E-04 5.84E 02 8.44E 02 RU 10' 2.C2E 03 0.00E-01 C.753 02 0.00E-01 4.24E C3 S.52E 05 1.51E 04 l RU 105 1.22E 00 0.00E-01 4.10E-01 0.00E-01 8.99E-01 1.57E 04 4.64E 04 l RU 106 8.68E 04 0.00E-01 1.09E 04 0.00E-01 1.07E 05 1.16E 07 1.64E 05 AG 110M 9.90E 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 TE 127 2.232 00 9.53E-01 4.89E-01 1.85E 00 4.86E 00 1.03E 04 2.44E 04 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 3.003 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 5.006-03 1.58E-02 3.99E-02 2.06E 03 8.22E 03 TE 132 3.72E 02 2.378 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 1.998 03 I 131 3.79E 04 4.44E 04 1.96E 04 1.48E 07 5.188 04 0.00E-01 1.06E 03 I 132 1.69E 03 3.54E 01 1.26E 03 1.69E 05 3.95E 03 0.00E-01 1.60Y 03 I 133 1.325 04 1.92E 04 5.60E 03 3.56E 06 2.24E 04 0.00E-01 2.16E 03 I 134 $.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 7.60E 03 2.77E 03 6.96E 05 8.47E 03 0.00E-01 1.83E 03 CS 134 3.96E 05 7.03E 05 7.45E 04 0.00E-01 1.90E 05 7.97E 04 1.33E 03 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 6.125 05 4.55E 04 0.00E-01 1.72E 05 7.13E 04 1.33E 03 CS 138 5.05E 02 7.81E 02 3.98E 02 0.00E-01 4.10E 02 6.54E 01 8.76E 02 BA 139 1.48E 00 9.84E-04 4.30E 02 0.00E-01 5.92E-04 5.95E 03 5.10E 04 BA 140 5.60E 04 5.60E 01 2.908 03 0.00E-01 1.34E 01 1.60E 06 3.84E 04 BA 141 1.575-01 1.08E-04 4.978-03 0.00E-01 6.50E-05 2.97E 03 4.755 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 5.17E 05 2.16E 04 CE 143 2.93E 02 1.93E 02 2.21E 01 0.00E-01 5.64E 01 1.16E 05 4.97E 04 CE 144 3.19E 06 1.21E 06 1.76E 05 0.00E-01 5.38E 05 9.84E 06 1.488 05 PP 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 NO it' 7.94E 03 8.13E 03 5.00E 02 0.00E-01 3.15E 03 3.22E 05 3.12E 04 W 187 1.302 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 C1 0.00E-01 6.62E 01 5.95E 04 2.49E 04

f Revision: 0 OFFSITE DOSE CALCUIATION MANUAL AP 07B-003 ! I d9 i g Reference Use Page 153 of 188 ' 6 ATTACHMENT A O (Page M9 of 3 64) 69 + g OFFSITE DOSE CALCULATION MANUAL ! D : TABLE A.5-6 ? N GRASS-CON-MILK PATHNAY FACTOR .; M8 MREM /YR PER pCI/SEC ! M- ADULT (RI FACTORS) ; NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI ) 1 H 3 0.00E-01 7.63E 02 7.63E 02 7.63E 02 7.63E 02 7.63E 02 7.63E 02 , C 14 2.63E 08 5.27E 07 S.213 07 5.'47E 01 5.27d 07 5 27E 07 5.2/E 07 -{ NA 24 2.44E 06 2.44E 06 2.44E 06 2.44E 06 2.44E 06 2.44E 06 2.44E 06 l

P 32 1.71E 10 1.065 09 6.60E 08 0.005-01 0.00E-01 0.005-01 1.92E 09 l CR 51 0.005-01 0.SOE-01 2.86E 04 0.00E-01 6,30E 03 3.795 04 7.19E 06 l MN 54 0 00E-01 8.41E 06 1.61E 06 0.00E-01 0.005-01 0.00E-01 2.58E 07 ! i a l MN 56 0.00E-01 4.16E-03 7.38E-04 0.00E-01 5.2SE-03 0.00E-01 1.33E-01 FE 55 2.51E 07 1.73E 07 4.04E 06 0.00E-01 0.00E-01 9.67E 06 9.95E 06

FE 59 2.97E 07 6.90E 07 2.68E 07 0.00E-01 0.00E-01 1.95E 07 2.33E 08 [

I ! l 00 58 0.00E-01 4.71E 06 1.06E 07 0.00E-01 0.00E-01 0.00E-01 9.56E 07 l

. CO 60 0.00E-01 1.64E 07 3.62E 07 0.00E-01 0.00E-01 0.00E-01 3.08E 08 l t NI 63 6.73E 09 4.71E 08 2.26E 08 0.00E-01 0.00E-01 0.00E-01 9.73E 07 i

} NI 65 4.63E-01 6.02E-02 2.75E-02 0.00E-01 0.00E-01 0.00E-01 1.53E 00 j CU 64 0.00E-01 2.39E 04 1.12E 04 0.005-01 6.02E 04 0.00E-01 2.03E 06 j 7 EN 65 1.37E 09 4.37E 09 1.97E 09 0.005-01 2.92E 09 0.005-01 2.755 09 } 7't 69 5.22E-19 9. 09 E -12 6.9EE.13 0.00M-01 C.49F-12 0.00?-01 2.E00-12 } BR 83 0.00E-01 0.00E-01 0.005-01 0.00E=01 0.00E-01 0.00E-01 0.00E-01 BR 84 0.00E-01 0.00E-01 0.005-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 4 BR 85 0.00E-01 0.00E-01 0.005-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 RB 86 0.00E-01 2.59E 09 1.215 09 0.00E-01 0.00E-01 0.00E-01 5.12E 08 I 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 0.005-01 0.00E 01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 i SR 89 1.45E 09 0.005-01 4.16E 07 0.00E-01 0.00E-01 0.00E-01 2.33E 08 SR 90 4.685 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 1.375 05 SR 92 4.90E-01 0.00E-01 2.12E-02 0.00E-01 0.00E-01 0.00E-01 9.70E 00 i Y 90 7.075 01 0.00E-01 1.90E 00 0.00E-01 0.00E-01 0.00E-01 7.505 05 1 Y 91M 6.03E-20 0.00E-01 2.345-21 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 0.003-01 1.63E-06 0.00E-01 0.00E-01 0.00E-01 9.79E-01 e Y 93 2.33E-01 0.00E-01 6.44E-03 0.00E-01' O.00E-01 0.00E-01 7.39E 03 h ZR 95 9.44E 02 3.03E 02 2.05E 02 0.00E-01 4.75E 02 0.00E-01 9.59E 05 I ER 97 4.33E-01 8.75E-05 4.00E-02 0.00E-01 1.328-00 0.00E-01 2.71E 04 NB 95 0.26E 04 4.59E 04 2-47E

                                                                     . 04    0.00E-01           4.54E 04 0.00E-01   2.79E 08      ,

4 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 1 l T

g Rsvision: 0 OPPSITE DOSE CALCULATION MANUAL AP 07B-003 0 g Reference Use Page 154 of 188 9 ATTACHMENT A O M (Page 150 of 184) g OFFSITE DOSE CALCULATION MANUAL u U TABLE A.5-6 (conted) GRASS-CON-MILK PATHWAY FAC'IVR k 8 M MREM /YR PER pCI/SEC i lf ADULT (RI FACTORS) l V NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI TC 101 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 kU 103 1.02E 03 0.00E-01 4.38E 02 0.00E-01 3.88E 03 0.00E-01 1.19E 05 RU 105 8.58E-04 0.00E-01 3.39E-04 0.00E-01 1.11E-02 0.00E-01 5.25E-01 RU 106 2.045 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 0.005-01 3.03E 08 TE 129 2.84E-10 1.07E-10 C.29E-11 2.18E-10 1.19E-09 0.00E-01 2.14E-10 TE 131M 3.61E 05 1.772 05 1.47E 05 2.80E 05 1.79E 06 0.00E-01 1.73E 07 TE 131 3.67E-33 1.53E-33 1.16E-33 3.01E-33 1.61E-32 0.00E-01 0.00E-01 {

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 US 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 1.5C 01 7.02E 01 0.00E-01 8.281-02 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 5.525-12 1.98E-12 9.575-11 8.78E-12 0.00E-01 4.81E-15 l I 135 1.29E 04 3.375 04 1.24E 04 2.22E 06 5.40E 04 0.00E-01 3.00E 04 C8 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 1.038 09 7.42E 08 0.00E-01 5.73E 08 7.865 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 1.815-23 8.975-24 0.005-01 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 l 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 RA 142 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.005-01 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 241 4.84E 03 3.28E 03 1.72E 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 1.9?P P4 0.00E-01 8.87E 04 0.00E-01 1.21E 08 , PR 143 1.585 02 6.33E 01 7.83E 00 0.00E-01 3.66E 01 0.00E-01 6.92E 05 PR 144 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 ND 147 9.46E 01 1.095 02 6.55E 00 0.00E-01 6.40E 01 0.00E-01 5.25E 05 , W 187 6.56E 03 5.49E 03 1.928 03 0.00E-01 0.00E-01 0.00E-01 1.805 06 NP 239 3.67B 00 3.61E-01 1.99E-01 0.00E-01 1.13E 00 0.00E-01 7.41E 04

g Revision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 R Raforanca Ura g Page 155 of 188 U ATTACHMENT A O (Page 151 of 184) OFFSITE DOSE CALCULATION MANUAL TABLE A.5-7 P3 GRASS-CON-MILK PATHWAY FACTOR k 8 M MREM /YR PER kCI/SEC j TEEN (R1 FACTORS) $ N LIVER _ UCLIDE BONE T BODY THYROID KIDNEY LUNG GI-LLI N 3 0.00E-01 9.94E 02 9.94E 02 9.94E 02 9.94E 02 9.94E 02 9.94E 02 C li 4.EEE OC 9.72T. 07 9.72E 07 9.723 07 9.72E 07 9.72E C7 S.71E 07 NA 24 4.268 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 1.098 04 7.13E 04 8.39E 06 MN 54 0.00E-01 1.40E 07 2.78E 06 0.00E-01 4.18B 06 0.00E-01 2.87E 07 MN 56 0.00E-01 7.37E-03 1.31E-03 0.00E-01 9.33E-03 0.00E-01 4.85E-01 FE 55 4.45E 07 3.16E 07 7.36E 06 0.00E-01 0.00E-01 2.00E 07 1.37E 07 FE 59 5.18E 07 1.21E 08 4.67E 07 0.00E-01 0.00E-01 3.81E 07 2.86E 08 CO 58 0.005-01 7.94E 06 1.83E 07 0.00E-01 0.00E-01 0.00E-01 1.09E 08 CO 60 0.00E-01 2.78E 07 6.26E 07 0.00E-01 0.00E-01 0.00E-01 3.62E 08 NI 63 1.18E 10 8.35E 08 4.01E 08 0.00E-01 0.00E-01 0.005-01 1.33E 08 NI 65 8.48E-01 1.085-01 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 1.08E 05 0.00E-01 3.30E 06 EN 65 2.11E 09 7.31E 09 3.41E 09 0.005-01 4.68E 09 0.00E-01 3.10E 09 ZN 69 9.62E-12 1.83E-11 1.22E-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 l BR 84 0.00E-01 0.00E-01 0.005-01 0.00E-01 0.00E-01 0.005-01 0.00E-01 l BR 85 0.005-01. 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 RB 86 0.00E-01 4.73E 09 2.22E 09 0.00E-01 0.00E-01 0.00E-01 7.00E 09 RB 88 0.00E-01 0.00E-01 0.00E-01 0.005-01 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 0.005-01 0.005-01 ' 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 1.86E 09 j 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 j 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 4.225-21 0.00E-01 0.00E-01 0.005-01 5.228-18 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 1.185-02 0.00E-01 0.00E-01 0.00E-01 1.31E 04 2R 95 1.655 03 5.21E 02 3.58E 02 0.00E-01 7.65E 02 0.00E-01 1.20E 06 ZR 97 7.89E-01 1.56E-01 7.19E-02 0.00E-01 2.37E-01 0.005-01 4.23E 04 , NB 95 1.41E 05 7.81E 04 4.30E 04 0.00E-01 7.57E 04 0.005-01 3.34E 08 ; MO 99 0.00E-01 4.47E 07 8.53E 06 0.00E-01 1.02E 08 0.005-01 8.01E 07 TC 99M 5.77E 00 1.61E 01 2.08E 02 0.00E-01 2.40E 02 8.93E 00 1.068 04

N 3 Ravicion: 0 h OFFSITE DOSE CALCULATION MANUAL AP 07B-003 o " R;foranca U::3 6 Page 156 of 188 o o ATTACHMENT A O (Page 152 of 184) N OFFSITE DOSE CALCULATION MANUAL N TABLE A.5-7 (con t' d) y GRASS-COW-HILK PATHWAY FACTOR g) M' MREM /YR PER pCI/SEC 47 TEEN (RI FAC'10RS) T NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI TC 101 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 PU 103 1.912 03 0.00E 01 7.74E C2 C.003-01 E.3GE 03 0.00E-01 1.51E G5 RU 105 1.57E-03 0.00E-01 6.08E-04 0.00E-01 1.98E-02 0.00E-01 1.278 00 RU 106 3.75E 04 0.00E-01 4.73E 03 0.00E-01 7.23E 04 0.00E-01 1.80E 06 AG 110M 9.63E 07 9.11E 07 5.543 07 0.00E-01 1.74E 08 0.00E-01 2.56E 10 TE 125M 3.00E 07 1.08E 07 4.02E 06 8.39E 06 0.00E-01 0.00E-01 8.86E 07 . l TE 127M 8.44E 07 2.99B 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 3.55E 07 4.618 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 2.66E-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 TB 132 4.29E 06 2.72E 06 2.56E 06 2.87E 06 2.61E 07 0.00E-01 8.61E 07 I 130 7.39E 05 2.14E 06 8.54E 05 1.74E 08 3.26E 06 0.00E-01 1.64E 06 I 131 5.37E 08 7.52E 08 4.04E 08 2.20E 11 1.30E 09 0.00E-01 1.49E 08 I 132 2.92E-01 7.65E-01 2.74E-01 2.583 01 1.?0E 00 0.00E-01 3.13E-01 I 133 7.07E 06 1.20E 07 3.66E 06 1.67E 09 2.10E 07 0.00E-01 9.00E OG I 134 3.61E-12 9.582-12 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 3.73E 06 9.28E 04 0.00E-01 6.51E 04 CS 134 9.82E 09 2.31E 10 1.07E 10 0.00E-01 7.34E 09 2.80E 09 2.873 08 CS 136 4.44B 08 1.75E 09 1.17E 09 0.00E-01 9.52B 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 5.608-11 4.09E-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 RA 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 30 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 0.00E-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 1.063 05

T E R;vicion: 0 g w OFFSITE DOSE CALCULATION MANUAL AP 07B-003 M R2fercncs Une g Page 157 of 188 0

0 ATTACHMENT A Q (Pege 3 53 of 184) N OFFSITE DOSE CALCULATION MANUAL ra TABL3 A.5-8 N GRASS-COW-MILK PATHWAY FACTOR

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

T NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI l H 3 0.00E-01 1.57E 03 1.57E 03 1.57E 03 1.57E 03 1.57E 03 1.57E 03 C 14 1.133 09 2. 3 9'd 08 2.392 Od 2.330 06 2.39d OS 2.33E 08 2.39h Od NA 24 8.86E 06 8.86E 06 8.86E 06 8.86E 06 8.86E 06 8.86E 06 8.86E 06 i P 32 7.77E 10 3.64E 09 3.00E 09 0.00E-01 0.00E-01 0.00E-01 2.15E 09 CR 51 0.03E 01 0.00E-01 1.02E 05 5.G5E 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 1 MN 56 0.00E-01 1.29E-02 2.90E-03 0.00E-01 1.56E-02 0.00E-01 1.86E 00 i 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 CO 60 0.00E-01 4.32E 07 1.27E 08 0.00E-01 0.00E-01 0.00E-01 2.392 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 i CU 64 0.00E-01 7.47E 04 4.51E 04 0.00E-01 1.81E 05 0.00E-01 3.51E 06 I 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 2.073 *.0 0.003-01 2.2GE-09 l BR 83 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 i BR 84 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 ! 1 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 8.77E 09 5.39E 09 0.00E-01 0.00E-01 0.00E-01 5.64E 08 RB 88 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 I RB 89 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.005-01 0.00E-01 0.00E-01 SR 89 6.625 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 I SR 91 1.29E 05 0.00E-01 4.88E 03 0.00E-01 0.00E-01 0.00E-01 2.85E 05 SR 92 2.19E 00 0.00E-01 8.78E-02 0.00E-01 0.00E-01 0.00E-01 4.15E 01 l Y 90 3.22E 02 0.00E-01 8.61E 00 0.005-01 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 Y 92 2.54E-04 0.00E-01 5.20E 06 l 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 8.79B 05 ZR 97 1.92E 00 2.77E-01 1.643-01 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 0.005-01 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 9/92

l Revision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 ' i Roforenca Uso Page 158 of 188 . O ATTACHMENT A (Page 154 of 184) j OFFSITE DOSE CALCULATION MANUAL ; t 2" TABLE A.5 8 (cont'd) GRASS-COW-MILK PATHWAY FACTOR ! Pd MREM /YR PER pCI/SEC i

 ,                                         CHILD (;k i FACTORS)

O' NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI-TC 101 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 RU 103 4.203 02 0.00E-01 1.6CE 03 C.332-01 1.00E 04 0.00E-01 1.11E 05 RU 105 3.83E-03 0.00E-01 1.393-03 0.00E-01 3.36E-02 0.00E-01 2.505 00 RU 106 9.24E 04 0.00E-01 1.15E 04 0.00E-01 1.25E 05 0.00E-01 1.445 06 AG 110M 2.09E 08 1.41E 08 1.135 08 0.00E-01 2.63E 08 0.00E-01 1.68E 10 TE 125M 7.38E 07 2.00E 07 9.84E 06 2.07C 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 0.005-01 1.68E 08 TE 127 2.90E 03 8.03E 02 6.39E 02 2.06E () 8.47E 03 0.00E-01 1.16E 05 TE 129M 2.71E OS 7.58E 07 4.21E 07 8.75E 07 7.97E 08 0.005-01 3.31E 08 l 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 5.22E 06 0.00E-01 1.635 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 5.44E-01 5.89E 01 1.94E 00 0.00R-01 2 493 09 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 5.413 04 9.735 04 4.6*E 04 8.62E 06 1.49E 05 0.00E-01 7.41E 04 CS 134 2.27E 10 3.72E 10 7.84E 09 0.00E-01 1.15E 10 4.135 09 2.00E 08 ; CS 136 1.00E 09 2.76E 09 1.73B 09 0.00E-01 1.47E 09 2.19E 08 9.69E 07 I CS 137 3.22E 10 3.09E 10 4.55E 09 0.005-01 1.01E 10 3.625 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 : BA 139 2.075-07 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 06 6.12E 04 5.94E 07 BA 141 0.005-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 l RA 142 0.00E-01 0.00E-01 0.005 01 0.005-01' O.00E-01 0.00E-01 0.00E-01 i LA 140 1.94E 01 6.80E 00 2.29E 00 0.00E-01 0.00E-01 0.005-01 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 4.27N 01 0.00E-01 1.49E 06 CE 144 1.623 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 ND 147 4.475 02 3.62E 02 2.80E 01 0.00E-01 1.99E 02 0.00T,-01 5.73E 05 W 187 2.91E 04 1.72E 04 7.73E 03 0.00E-01 0.00E-01 0. ODE-01 2.42E 06 NP 239 1.72E 01 1.24E 00 8.70E-01 0.00E-01 3.58E 00 0.00E-01 9.16E 04 I 9/93

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                        .OFFSITE DOSE CALCULATION MANUAL TAIL:: A.5-9

@ GRASS-COW-MILK PATHNAY FACTOR $- 8 M MREM /YR PER pCI/SEC dj INFANT (RI FACTORS) ] E ; NUCLIDE BONE LIVER T BODY THYROID KIDNEY. LUNG GI-LLI H 3 0.005-01 2.38E 03 2.38E 03 2.385 03 2.385 03 2.38E 03 2.38E 03 { C 14 2.3tr 0* 5.00E 06 7.LJ: 06 5.00E 09 5.003 08 S 00E 05 5.00E Ou ) NA 24 1.54E 07 1.54E 07 1.54E 07 1.54E 07 1.54E 07 1.54E 07 1.54E 07 P 32 1.60E 11 9.42E 09 6.21E 09 0.00E-01 0.00E-01 0.00E-01 2.17E 09 CR 51 0.03E-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 0.005-01 2.715-02 0.005-01 2.86E 00 FE 55 1.35E 08 8.72E 07 2.33E 07 0.00E-01 0.005-01 4.26E 07 1.11E 07 FE 59 2.24E 08 3.92E 08 1.54E 08 0.00E-01 0.00E-01 1.16E 08 1.87E 08 CO 58 0.00E-01 2.43E 07 6.05E 07 0.00E-01 0.00E-01 0.00E-01 6.04E 07 CO 60 0.00E-01 8.82E 07 2.00E 08 0.00E-01 0.00E-01 0.00E-01 2.10E 08 NI 63 3.49E 10 2.16E 09 1.21E 09 0.00E-01 0.00E-01 0.00E-01 1.07E 08 NI 65 4.39E 00 4.97E-01 2.26E-01 0.005-01 0.00E-01 0.00E-01 3.78E 01 CU 64 0.00E-01 1.86E 05 8.60E 04 0.00E-01 3.145 05 0.00E-01 3.81E 06 ZN 65 5.55E 09 1.90E 10 8.78E 09 0.005-01 9.23E 09 0.005-01 1.61E 10 ZN 49 5.04E-11 9.07E-11 6.75P-12 0,00E-01 3.??E-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 0.005-01 0.00E-01 0.00E-01 0.00E-01 BR 85 0.005-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-31 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 RR 89 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 SR 89 1.26E 10 0.00E-01 3.61E 08 0.00M-01 0.00E-01 0.00E-01 2.59E 08 SR 90 1.22E 11 0.00E-01 3.10E 10 0.000-01 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. 3E 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 5.725-19 0.00E-01 1.95E-20 0.005-01 0.00E-01 0.00E-01 1.91E-15 Y 91 7.33E 04 0.00E-01 1.95E 03 0.00E-01 0.00E-01 0.00E-01 5.25E 06 Y 92 5.39E-04 0.00E-01 1.51E-05 0.00E-01 0.00E-01 0.00E-01 1.03E 01 s~ Y 93 2.25R 00 0.00E-01 6.135-02 0.00E-01 0.00E-01 0.00E-01 1.78E 04 ZR 95 6.811 03 1.66E 03 1.18E 03 0.00E-01 1.79E 03 0.00E-01 8.26E 05 ZR 97 4.06E 00 6.98E 01 3.195-01 0.00E-01 7.03E-01 0.00E-01 4.45E 04 NB 95 5.94E 05 2.45E 05 1.41E 05 0.00E-01 1.75E 05 0.00E-01 2.065 08 MO 99 0.00E-01 2.08E 08 4.06E 07 0.00E-01 3.11E 08 0.00E-01 6.85E 07 TC 99M 2.75E 01 5.68E 01 7.31E 02 0.00E-01 6.11E 02 2.97E 01 1.65E 04 I

g R3vicion: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 H q R;fGr nce U;o _ Page 160 of 188 D ATTACHMENT A h (Page 156 of 184) y OFFSITE DOSE CALCULATION MANUAL M TABLE A.5 9 (cont'd) () GRASS-COW-MILK PATHWAY FACTOR S M* MREM /YR PER pCI/SEC INFANT (RI FACTORS) NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI TC 101 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 FU 201 8.67E 03 0.00F-C1 2.302 C3 0.00C-01 1.bOE 04 0.00s-01 1.05d 05 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 00 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 7.18E 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 1.335 05 TE 129M 5.57E 08 1.91E 08 8.58E 07 2.14E 08 1.39E 09 0.00E-01 3.33E 08 TE 129 2.74E-09 9.43E-10 6.39E-09 2.29E-08 6.81E-CG 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 08 8.585 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 1.41E 00 2.91E 00 1.04R 00 1.17E 02 3.25E 00 0.0CR-01 7.15? 00 I 133 3.63E 07 5.20E 07 1.55E 07 9.61E 09 6.21E 07 0.00E-01 8.94E 06 I 134 1.77E-11 3.63E-11 1.29E-10 8.47E-09 4.06E-10 0.00E-01 3.76E-11 I 135 1.12E 05 2.24E 05 8.15E 04 2.00E 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 6.21B 09 1.85E 08 CS 136 1.96E 03 5.76E 09 2.15E 09 0.00E-01 2.30E 09 4.70E 08 8.75E 07 CS 137 5.15E 10 6.02E 10 4.27E 09 0.00E-01 1.62E 10 6.55E 09 1.88E 08 CS 138 8.50E-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 5.72R 04 1.48E 05 5.92E 07 BA 141 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.005-01 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 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 1=4 2.33E 06 9.52B 05 1.30E 05 0.00E-01 3.85E 05 0.00E-01 1.33E 08 PR 143 1.49E 03 5.56E 02 7.36E 01 0.00E-01 2.07E 02 0.00E-01 7.84E 05 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 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 2Js 3.65E 01 3.268 00 1.84E 00 0.00E-01 1.50E 00 0.00E-01 9.43E 04

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 ,g                                                                           Page 161 of 188 E

1 ATTACHMENT A ' O (Page 157 of 3 84) N

  \                          OFFSITE DOSE CALCULATION MANUAL u

TABLR A.5-10 f3 GRASS-COW-MEAT PATHWAY FACTOR

 \                                       M' MREM /YR PER pCI/SEC
 .@                                        ADULT (RI FAC7VRS)

V NUCLIDE DONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI H 3 0.00E-01 3.25E 02 3.25E 02 3.25E 02 3.25E 02 3.25B 02 3.25E 02 C 14 2.41E 08 4.300 07 4.83E07 4.53E 07 4.UJE 01 4.8JE 0 7 s . 8 J r. 07 NA 24 1.36E-03 1.36E-03 1.36E-03 1.36E-03 1.165-03 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 0.00R-01 0.00E-01 7.05E 03 4.21E 03 1.55E 03 9.35E 03 1.77B 06 MN 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 08 4.72E 07 0.00E-01 0.00E-01 1.13E 08 1.16E 08 FE 59 2.65E 08 6.24E 08 2.39E 08 0.00E-01 0.00E-01 1.74E 08 2.08E 09 CO 58 0.00E-01 1.02E 07 4.09E 07 0.00E-01 0.00E-01 0.00E-01 3.70E 08 CO 60 0.005-01 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 09 6.33E 08 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 0.003-01 2.33E-05 ZN 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 0.002-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00F-01 BR 83 0.00E-01 0.00E-01 0.005-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 BR 84 0.00E-01 0.00E-01 0.00E-01 0 00E-01 0.00E-01 0.005-01 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 RD 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 8.66B 06 0.00E-01 0.00E-01 0.00E-01 4.84B 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-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Y 91 1.13E 06 Or00E-01 3.03E 04 0.00E-01 0.00E-01 0.00E-01 6.23E 08 _Y 92 0.005-01 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 D6 1.28E 06 6.88E 05 0.00E-01 1.26E 06 0.00E-01 7.76E 09 MO 99 0.00E-01 9.995 04 1.90E 04 'O.00E-01 2.26E 05 0.00E-01 2.32B 05 TC 99M 4.50C-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 0.005-01 0.00E-01 0.00E-01 0.00E-01

m 3 D Ravicion: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 O yq R3fersnca U 3 Page 162 of 188 U ATTACHMENT A D (Pace 158 of 184)

 \                         OFFSITE DOSE CALCULATION MANUAL D                                     TA4!N A.5-10 (cont'd)

GRASS-COW-MEAT PATHWAY FACTOR l k Mf MREM /YR PER pCI/SEC

 .)                                      ADULT (RI FACTORS)                                  !

C' NUCLIDE \ BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI l RU 103 1.05E 08 0.00E-01 4.53E 07 0.00E-01 4.01E 08 0.00E-01 1.23E 10 to 105 L.6;E-28 0.004.ul 2.32E-20 0.00E-01 '/.588-27 0.00E-01 3.59E-25 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 TE 125M 3.59E 08 1.30E 08 4.818 07 1.08B 08 1.46E 09 0.00E-01 1.43E 09 TE 127M 1.12E 09 3.99E 08 1.36E 08 2.85E 08 4.53E 09 0.00E-01 3.74E 09 TB 127 2.14E-10 7.68E-11 4.63E-11 1.58E-10 8.71E-10 0.00E-01 1.693-08 TE 129M 1.13E 09 4.23E 08 1.80E 08 3.90E 08 4.73E 09 0.00E-01 5.71B 09 1 TE 129 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 TE 4.52E 02 2.21E 02 l 131M 1.84E 02 3.50E 02 2.24E 03 0.00E-01 2.20E 04 TE 131 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 TE 132 1.42E 06 9.19E 05 8.635 05 1.01E 06 8.85E 06 0.00E-01 4.35E 07 1 130 2.12E-06 6.26E-06 2.478-06 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 1 113 3.67E-01 C.18E-01 1.94E-01 9.37E 01 1.11E 00 0.00E-01 5.733-ci I 134 0.00E-01 0.00E-01 0.005-01 0.00E-01 0.00E-01 0.005-01 0.60E-01 1 135 4.47E-17 1.17E-16 4.32E-17 7.73E-15 1.8BE-16 0.00E-01 1.32E-16 CS 134 6.58E 08 1.56E 09 1.28E 09 0.00E-01 5.06E 08 1.68E 08 2.74E 07 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 138 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 BA 139 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 1 BA 140 2.87E 07 3.61E 04 1.885 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 3.768-02 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 0.005-01 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 6.09E 05 9.83B 04 0.00E-01 3.61H 05 0.00E-01 4.93E 08 PR 143 2.10E 04 8.41E 03 1.04E 03 0.00E-01 4.868 03 0.005-01 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 4.96E 02 0.00E-01 4.84E 03 0.00E-01 3.98E 07 W 187 2.17E-02 1.81E-02 6.338-03 0.005-01 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

w 3 3 Revision:'0 - OFFSITE DOSE CALCUIATION MANUAL AP 07B-003 g Raforance Use Page 163 of 188 8 ATTACHMENT A E (Page 159 of 184) M OFFSITE DOSE CALCUIATION MANUAL TABLE A.3-11 GRASS-COW-MEAT PATHWAY FACTDE M* MREM /YR PER pCI/SEC

                                         *IEEN (RI FACTORS) 5 NUCLIDE       BONE     LIVER      T BODY       THYROID    EIDNEY    ' LUNG     GI-LLI H      3   0.00E-01  1.94E 02    1.94E C2     1.94E 02   1.94E 02 1.94E 02    1.94E 02 C     14   2. 04E CE 4.00E 07    1.008 07     4.00E 07   4.DdE 07 4.08E 01    4.0aE 07 NA     24   1.09E-03  1.09E-03    1.098-03     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   0.005-01 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   0.005-01  7.00E 06    1.39E 06     0.005-01   2.09E 06 0.00E-01    1.44E 07 MN     56   0.00E-01  0.00E-01    0.005-01     0.00E-01   0.00E-01 0.00E-01    0.00E-01 FE     55   2.38E 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 1.56B 08    1.175 09 CO     58   0.00E-01  1.41E 07    3.243 07     0.00E-01   0.00E-01 0.00E-01    1.94E 08 CO     60   0.005-01  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 0.005-01    0.00E-01 CU     64   0.00E-01  2.23E-07    1.05E-07     0.00E-01   5.64E-07 0.005-01    1.735-05 EN     65   2.50E 08  8.695 08    4.05E 08     0.005-01   5.56E 08 0.00E-01    3.685 08 EN     69   0.00E-01  0.00E-01    0.00R-01     0.00E-01   0.00E-01 0.00E-01    0.00E-01 BR     63   0.00E-01  0.00E-01    0.00E-01     0.00E-01   0.00N-01 0.00E-01    0.00E-01 BR     84   0.00E-01  0.00E-01    0.005-01     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  4.07E 08    1.91E 08     0.00E-01   0.00E-01 0.00E-01   6.02E 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   2.55E 08  0.00E-01    7.29E 06     0.00E-01   0.00E-01 0.00E-01   3.03E 07 SR     90   8.05E 09  0.00E-01    1.99E 09     0.00E-01   0.00E-01 0.00E-01   2.26E 08 SR -   91   1.19E-10  0.00E-01    4.75E-12     0.00E-01   0.00E-01 0.00E-01    5.41E-10 SR     92   0.00E-01  0.005-01    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   0.005-01 0.005-01   0.00E-01 Y     91   9.54E 05  0.00E-01    2.565 04     0.00E-01   0.00E-01 0.00E-01   3.91E 08 Y     92   0.005-01  0.00E-01    0.00E-01     0.005-01   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 2R     95   1.50E 06  4.73E 05    3.26E 05     0.00E 01   6.96E 05 0.00E-01    1.09E 09 ER     97   1.73E-05  3.42E-06    1.58E-06     0.00E-01   5.19E-06 0.00E-01    9.27E-01 NB     95   1.80E 06  9.96E 05    5.48E 05     0.00E-01   9.66E 05 0.005-01    4.26E 09 MO     99   0.00E-01  8.26E 04    1.58E 04     0.00E-01   1.89E 05 0.005-01    1.48E 05 TC    99M   3.58E-21  9.975-21    1.29E-19     0.00E 01   1.49E-19 5.54E-21    6.55E-18 I

l

g Ravicion: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 B g) R3forcncs U20 Page 164 of 188 9 ATTACHMENT A 6 (Page 160 of 184) OFFSITE DOSE CALCULATION MANUAL TABLE A.5-11 (cont'd) GRASS-COW-MEAT PATHWAY FACTOR M' MREM /YR PER #CI/SEC y TEi N (HI FACTORS) W NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI TC 101 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 EU 103 8.56E 07 0.000-01 3.66S 07 0.003-03 3.00E 03 0.00E-01 7.15E 0)' RU 105 4.92E-28 0.00E-01 1.91E-28 0.00E-01 6.91E-27 0.00E-01 3.962-25 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 1.358 09 TE 125M 3.03E 08 1.095 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 08 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-02 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 0.005-01 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 08 1.23E 09 5.718 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 3.11E 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 138 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 BA 139 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 BA 140 2.38E 07 2.918 04 1.53E 06 0.00E-01 9.88E 03 1.96E 04 3.67E 07 BA 141 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 BA 142 0.00E-01 0.00E-01 0.00E-01 0.002-01 0.00E-01 0.00E-01 0.005-01 LA 140 3.09E-02 1.52E-02 4.04E-03 0.00E-01 0.00E-01 0.00E-01 8.72E 02 LA 142 0.003-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 CE 141 1.18E 04 7.8BE 03 9.05E 02 0.00E-01 3.71E 03 0.00E-01 2.25E 07 CE 143 1.692-02 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 7.058 03 0.78E 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 1.81B-02 1.48E-02 5.18E-03 0.00E-01 0.00E-01 0.00E-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

3 Ravicion: 0 3 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 0 g Rsfarenca UEQ Page 165 of 188 0 - ATTACHMENT A O N (Pa.ge 161 of 184) \ OFFSITE DOSE CALCULATION MANUAL N H TA3LE A.5-12 GRASS-COW-MEAT PATHWAY FACTOR -\ 8 M MREN/YR PER pCI/SEC 3 CHILD (RI FACTORS) W NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI H 3 0.00E-01 2.34E 02 2.34E 02 2.34E 02 2.34E 02 2.34E 02 2.34E 02 C 11 3.C3E 00 7.67E 07 7.61J 07 7.vJE 07 7.67E 07 7.6 /E 07 */.67n 07 NA 24 1.73E-03 1.73E-03 1.73E-03 1.73E-03 1.73E-03 1.73E-03 1.73E-03 P 32 7.415 09 3.47E 08 2.86E 08 0.00E-01 0.00E-01 0.00E-01 2.05E 08 CR 51 0.00h-01 0.00E-01 8.79E 03 4.88E 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 FE 55 4.57E 08 2.42E 08 7.50E 07 0.00E-01 0.00E-01 2.36E-51 l 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 08 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 9.915 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 0.005-01 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 KN 65 3.75E 08 1.00E 09 6.22E 08 0.00E-01 6.30E 08 0.00E-01 1.76E 08 7M 69 0.00E-01 0.00E 01 0.00F-01 0.00E-01 0.00E-01 C.00E-01 0.002-C1 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 0.005-01 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 0.005-01 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 07 RS 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 4.82E 08 0.00E-01 1.38E 07 0.00E-01 0.00E-01 0.00E-01 1.87E 07 SR 90 1.04E 10 0.00E-01 2.64E 09 0.00E-01 0.00E-01 0.00E-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-01 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 SIM 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Y 91 1.00E 06 0.00E-01 4.825 04 0.00E-01 0.00E-01 0.00E-01 Y 92 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 2.40E 08 l 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 ER 95 2.66E 06 5.86E 05 5.21E 05 0.00E-01 8.38E 05 0.00E-01 6.11E 08 ZR 97 3.22E-05 4.65E-06 2.74E-06 0.00E-01 6.68E-06 0.00E-01 7.05E-01 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 0.005-01 1.15E 05 2.84E 04 0.00E-01 2.45E 05 0.00E-01 9.51E 04 TC 99M 6.27E-21 1.23E-20 2.04E-19 0.00E-01 1.79E-19 6.24E-21 7.00E-18 9/s.1

Revision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 M g R3forenco Uca Page 166 of 188 0 ATTACHMENT A O (Page 162 of 3 M) N OFFSITE DOSE CALCULATION MANUAL t\ tar.LE A.3-12 (coat'd) t IQ GRASS-COM-MEAT PATHNAY FACTOR k M* MREM /YR PER pCI/SEC -jg CHILD (RI FACTORS) j E' NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG i GI-LLI TC 101 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 EU 10 1.558 08 c.00E-01 5.S'i1 OV

                                         .        J . W E- 01 3.!r0k 08 0.00E-01   4.008 09 RU     105 9.16E-28 0.005-01    3.32E-28     0.00E-01    8.05E-27  0.00E-01   5.98E-25 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 08    7.59E 07     1.60E 08    0.00E-01  0.00E-01   5.495 08 l

TE 127M 1.77E 09 4.78E 08 2.11E 08 4.24E 08 5.06E 09 0.00E-01 1.44E 09 l TR 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 08 2.78E 08 5.77E 08 5.26E 09 0.005-01 2.18E 09 l TE 129 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 1 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 l 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 0.005-01 9.46E 06 I 130 3.05E-06 6.17E-06 3.185-06 6.80E-04 9.22E-06 0.00E-01 2.89E-06 'l I 131 1.66E 07 1.67E 07 9.47E 06 5.51E 09 2.74E 07 0.00E-01 1.48E 06 l I 1?2 0.00E-01 0.00E-01 0.00C-01 0.00E-01 9.00E 01 0.0 5-01 0.00"-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 1 135 6.595 17 1.195-16 5.61E-17 1.055-14 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 l CS 136 1.59E 07 4.36E 07 2.823 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 4.165 08 1.50E 08 7.995 06 CS 138 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.005-01 0.005-01 0.00E-01 BA 139 0.00E-01 0.005-01 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 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 0.005-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 LA 140 5.66E-02 1.98E-02 6.66E-03 0.005-01 0.00E-01 0.00E-01 LA 142 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 5.51E02l 0.00E-01 CE 141 2.22E 04 1.115 04 1.64E 03 0.00E-01 4.86E 03 0.00E-01 1.3 8E 07 CE 143 3.18E-02 1.72E 01 2.50E-03 0.00E-01 7.235-03 0.00E-01 2.52E 02 CE 144 2.32R 06 7.26E 05 1.24E 05 0.00E-01 4.025 05 0.00E-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 5.278 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 l 9/93

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,s R; vision: 0 O                            OFFSITE DOSE CALCULATION MANUAL                     AP 078-003 O

g R3ferenca U:D Page 167 of 188 0 ATTACHMENT A O (Page 163 of 184) N OFFSITE DOSE CALCULATION MANUAL

N TA3L3 f. 5-13 h1 VEGBTATION PATHWAY FACTOR

\                                       M* MREM /YR PER pCI/SEC 3                                         ADULT (RI FACTORS)

T NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI H 3 0.00E-01 2.26E 03 2.26E 03 2.26E 03 2.26E 03 2.26E 03 2.26E 03 , C .! 4 2. Er 08 4.55E 07 4.53E 07 4.55U 07 4.35E 07 4.55E 01 e.55E 07 l NA 24 2.69E 05 2.698 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 2.78E 04 1.02E 04 6.16E 04 1.17E 07 I MN 54 0.00E-01 3.13E 08 5.97E 07 0.00E-01 9.31E 07 0.00E-01 9.58E 08 l MN 56 0.00E-01 1.59E 01 2.82E 00 0.00E-01 2.02E 01 0.00E-01 5.085 02 FE 55 2.09E 08 1.45E 08 3.37E 07 0.00E-01 0.00E-01 8.06E 07 8.29E 07 FE 59 1.26E 08 2.968 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 3.698 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-01 6.36E 08 2N 69 8.77F-06 1.6AM-05 1.178-06 0.00E-01 1.09E-05 0.n0E-01 2.592-06 BR 83 0.00E-01 0.00E-01 3.11E 00 0.00E-01 0.00E-01 0.00E-01 4.48E 00 BR 84 0.00E-01 0.00E-01 2.49E-11 0.00E-01 0.00E-01 0.00E-01 1.96E-16 BR 85 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 RB 86 0.00E-01 2.19E 08 1.02E 08 0.00E-01 0.00E-01 0.00E-01 4.33E 07 RB 88 0.00E-01 3.47E-22 1.84E-22 0.00E-01 0.00E-01 0.00E-01 0.00E-01 RB 89 0.00E-01 1.415-26 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 0.003-01 0.00E-01 1.75E 10 SR 91 3.03E 05 0.00E-01 1.22H 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 03 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 ZR 95 1.18E 06 3.77E 05 2.55E 05 0.00E-01 5.92E 05 0.00E-01 1.20E 09 ZR 97 3.37E 02 6.81E 01 3.11E 01 0.00E-01 1.03E 02 0.00E-01 2.11E 07 NB 95 1.43B 05 7.93E 04 4.26E 04 0.062-01 7.84E 04 0.00E-01 4.81E 08 MO 99 0.00E-01 6.15E 06 1.17E 06 0.C0E-11 1.39E 07 0.00E-01 1.43E 07 TC 99M 3.10E 00 8.77E 00 1.12E 02 0.0G2-01 1.33E 02 4.30E 00 5.19E 03

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  \                                    OFFSITE DOSE CALCULATION MANUAL N

T93LE A.5-13 (cent'd) fd VEGETATION PATHWAY FACTOR

  \                                                  8 M MREM /YR PER pCI/SEC                                  I 3                                                    ADULT (RI FACTORS)

W NUCLIDE BOBIE LIVER T BODY THYROID KIDNEY LUNG GI-LLI TC 101 8.34E-31 1.20E-30 1.18E-29 0.00E-01 2.16E-29 6.14E-31 0.00E-01 PU 103 4.7CE 06 0.J05-01 2.05E OG 0.00E-01 1.82h 01 0.00E-01 5.563 v6 RU 105 5.395 01 0.00E-01 2.13E 01 0.005-01 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 1.175 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 9.38E 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 1.515-15 6.32E-16 4.78E-16 1.24E-15 6.638-15 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 I 131 8.08E 07 1.16E 08 6.62E 07 3.79E 10 1.988 08 0.00E-01 3.05E 07 I I 132 5.775 01 1.54E 02 5.405 01 5.40E 03 2.44E 02 0.00E-01 2.f02 01 I 133 2.09E 06 3.63E 06 1.11E 06 5.33E 08 6.33E 06 0.00E-01 3.26E 06 I 134 9.69E-05 2.63E-04 9.425 05 4.56E-03 4.19E-04 0.00E-01 2.30E-07 l I 135 3.90E 04 1.02E 05 3.77E 04 6.74E 06 1.64E 05 0.003-01 1.15E 05 CS 134 4.675 09 1.11E 10 9.085 09 0.00E-01 3.59E 09 1.19E 09 1.94E 08 i CS 136 4.20E 07 1.66E 08 1.19E 08 0.00E-01 9.228 07 1.26E 07 1.88E 07 CS 137 6.36E 09 8.70E 09 5.70E 09 0.00E-01 2.95E 09 9.61E 08 1.68E 08 CS 138 3.94E-11 7.78E-11 3.86E-11 0.00E-01 5.72E-11 5.652-12 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 B P. ". 4 0 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 RA 142 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 LA 140 1.98E 03 9.99E 02 2.64E 02 0.00E-01 0.00E-01 0.005-01 7.33E 07 LA 142 1.42E-04 6.44E-05 1.615 05 0.00E-01 0.00E-01 0.00E-01 4.70E-01 CE 141 1.975 05 1.33E 05 1.51B 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 1.385 07 1.77E 06 0.00E-01 8.16E 06 0.00E-01 1.11E 10 PR 143 6.26E 04 2.51B 04 3.11E 03 0.00E-01 1.45E 04 0.005-01 2.74E 08 PR 144 3.135-26 1.30E-26 1.59E-27 0.00E-01 7.32E-27 0.00E-01 0.00E-01 ND 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 1.058 07 NP 239 1.43E 03 1.40E 02 7.74E 01 0.00E-01 4.38E 02 0.00E-01 2.88E 07 m~ e- -me v+ -., ,- y, ,-

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TABLE A.5 14 h VEGETATION PATIDfAY FACTOR

  \                                  M' MREM /YR PER pCI/SEC
  .h                                    TEEN (RI FACTORS)

C' NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI 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 3.65E G8 7.3ed 07 7.auE 01 7.10E 01 7.JdE 07 7.3dE 07 7.36d O 's 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 s CR 51 0.00E-01 0.00E-01 6.17E 04 3.43E 04 1.35E 04 8.81E 04 1.04E 07 MN 54 0.00E-01 4.54E 08 l 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 0.00E-01 9.45E 02 j FE 55 3.25E 08 2.318 08 5.38E 07 0.00E-01 0.002-01 1.46E 08 9.98E 07 j FE 59 1.79E 08 4.18E 08 1.62E 08 0.00E-01 0.00E-01 1.32E 08 9.90E 08 l Y CO 58 0.00E-01 4.36E 07 1.01E 08 0.00E-01 0.00E-01 0.00E-01 6.01E 08 l 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 l 8.345 03 3.92E 03 0.00E-01 2.11B 04 0.00E-01 6.47E 05 j ZN 65 4.248 08 1.47E 09 6.86E 08 0.00E-01 9.42E 08 0.00E-01 6.23E 08 I ZN 69 8.21E-06 1.*6E 05 1,10?-06 0.00E-01 1.02E-05 0.0nn-01 2. 00E. ca i BR 83 0.00E-01 0.00E-01 2.92E 00 0.00E-01 0.00E-01 0.00E-01 5.08E-16 ! BR 84 0.00E-01 0.00E-01 2.27E-11 0.00E-01 0.00E-01 0.00E-01 3.14E-28 I l BR 85 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 RB 86 0.005-01 2.745 08 1.29E 08 0.00E-01 0.00E-01 0.00E-01 4.05B 07 RB 88 0.00E-01 3.21E-22 1.71E-22 0.00E-01 0.00E-01 0.00E-01 2.75E-29 a l RB 09 0.00E-01 1.26E-26 8.94E-27 0.00E-01 0.00E-01 0.00E-01 1.94E-35 SR 89 1.53E 10 0.00E-01 4.34E 08 0.00E-01 0.00E-01 0.005-01 1.80E 09 Ek 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 1.13B 04 0.00E-01 0.00E-01 0.00E-01 1.28E 06 i 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 3.345 02 0.00E-01 0.00E-01 0.00E-01 1.02E 08 i Y 91M 4.88E-09 0.00E-01 1.87E-10 0.00E-01 0.00E-01 0.00E-01 2.30E-07 Y 91 7.84E 06 0.00E-01 2.10E 05 0.00E-01 0.00E-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 0.00E-01 4.99E 06 ZR 95 1.72E 06 5.44E 05 3.745 05 0.00E-01 7.99E 05 0.00E-01 1.25E 09 ZR 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 5.885 04 0.00E-01 1.04E 05 0.00E-01 4.57E 08 MO 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

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,  Raforanco Usa                                                         Page 170 of 188

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TABLE A.5-14 (cont'd) M VEGETATION PATHWAY FACTOR 8

\                                   M MREM /YR PER kCI/SEC J                                       TEEN (RI FACTORS)
                                                                                         ]

NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI TC 101 7.76E-31 1.10E-30 1.08E-29 0.00E-01 2.00E-29 6.72E-31 0.00E-01 PU 103 f.813 06 0.00E-01 2.91E 00 0.00E-01 2.40E C7 C.00E-01 d.69d Od 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 l TE 125M 1.48E 08 5.34E 07 1.98E 07 0.00E-01 4.14E 07 0.00E-01 4.39E 08 TE 127M 5.52E 08 1.968 08 6.56E 07 1.31E 08 2.24E 09 0.005-01 1.37E 09 l TE 127 5.34E 03 1.89E 03 1.15E 03 2.16E 04 3.685 03 0.00E-01 4.12E 05 TE 129M 3.62E 08 1.34E 08 5.73E 07 1.17E 08 1.51E 09 0.00E-01 1.36E 09 TE 129 7.16E-04 2.67E-04 1.74E-04 5.12E-04 3.01E-03 0.00E-01 3.92E-03 TE 131M 8.44E 05 4.05E 05 3.38E 05 4.22E 06 6.09E 05 0.00E-01 3.25E 07 TB 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 7,905 05 I 131 7.69E 07 1.00E 08 5.78E 07 3.14E 10 1.85E 08 0.00E-01 2.13E 07 I 132 5.20E 01 1.36E 02 4.89R 01 4.59E 03 2.14E 02 0.00E-01 5.93E 01 I 133 1.94E 06 3.295 06 1.00E 06 4.59E 08 5.778 06 0.005-01 2.49E 06 1 134 8.76E-05 2.32E-04 8.34E-05 3.875-03 3.66E-04 0.00E-01 3.06E-06 I 135 3.52E 04 9.07E 04 3.365 04 5.84E 06 1.43E 05 0.005-01 1.01E 05 CS 134 7.10E 09 1.675 10 7.75E 09 0.00E-01 5.31E 09 2.03E 09 2.08B 08 CS 136 4.285 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 130 3.64E 11 6.988-11 3.49E-11 0.005-01 5.155-11 6.00E-12 3.17E-14 BA 139 2.73E-02 1.925-05 7.96E-04 0.00E-01 1.81E-05 1.325-05 2.44E-01 i BA 140 1.38E 08 1.69E 05 8.91E 06 0.00E-01 5.74E 04 1.14E 05 2.13E 08 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 8.898 02 2.37E 02 0.00E-01 0.00E-01 0.00E-01 5.11E 07 LA 142 1.30E-04 5.78E 05 1.44E-05 0.00E-01 0.00E-01 0.00E-01 1.76E 00 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 5.278 07 2.18E 07 2.83E 06 0.00E-01 1.30E 07 0.00E-01 1.33E 10 PR 143 7.01E 04 2.80E 04 3.49B 03 0.00E-01 1.63E 04 0.00E-01 2.31E 08 PR 144 2.93B-26 1.20E-26 1.49E-27 0.00E-01 6.88E-27 0.00E-01 3.23E-29 ND 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 4.105 02 0.00E-01 2.10E 07

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ATTACHMENT A ! 0 (Page 167 of 1A4) l W OFFSITE DOSE CALCULATION MANUAL TABLE A.5-15 h VEGBTATION PATHNAY FACTOR l

   \                                       M' MREM /YR PER pCI/SEC jj -                                       CHILD (k1 PACToks)

O' NUCLIDE BONE LIVER T BODY THYROID EIDNEY LUNG GI-LLI H 3 0.00E-01 4.01E 03 4.01E 03 4.01E 03 4.01E 03 4.01E 03 4.01E 03 C 1: B.30E OS 1.7S2 08 1.78E G8 1.7;E 00 1.78L 04 1.70E Ou 1.78E Co FA 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 1.305 08 0.00E-01 0.00E-01 0.00E-01 CR 51 0.00C-01 0.00E-01 1.17E 05 6.50E 04 1.7eE 04 9.30E07l 1.198 05 6.21E 06 MN 54 0.00E-01 6.65E 08 1.77E 08 0.00E-01 1.86E 08 0.00E-01 5.58E 08 MN 56 0.00E-01 1.88E 01 4.245 00 0.00E-01 2.27E 01 0.00E-01 2.72E 03 FE 55 8.00E 08 4.24E 08 1.31E 08 0.00E-01 0.005-01 2.40E 08 7.86E 07 FE 59 3.97E 08 6.43E 08 3.20E 08 0.00E-01 0.00E-01 1.86E 08 6.69E 08 CO 58 0.00E-01 6.44E 07 1.97E 08 0.00E-01 0.00E-01 0.00E-01 3.76E 08 i CO 60 0.005-01 3.78E 08 1.12E 09 0.00E-01 0.00E-01 0.00E-01 2.10E 09 i NI 63 3.95E 10 2.11E 09 1.34E 09 0.00E-01 0.00E-01 0.00E-01 1.42E 08 I NI 65 1.18E 02 1.115 01 6.51E 00 0.005-01 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 EN 65 8.12E 08 2.16E 09 1.358 09 0.00E-01 1.36E 09 0.00E-01 3.80E 08 ZN 69 1.51E-05 7.19R-05 2.02R-06 0.00E-01 1.?3E-05 c.00E.03 1.38H-03 BR 83 0.00E-01 0.00E-01 5.38E 00 0.00E-01 0.00E-01 0.005-01 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 0.005-01 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 0.005-01 4.43E-22 3.08E-22 0.00E-01 0.00E-01 0.00E-01 2.17E-23 RB 89 0.00E-01 1.67E-26 1.48E-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 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 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 4.995 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 4.5BE 04 4 l Y 93 3.01E 02 0.00E-01 8.26E 00 0.00E-01 0.00E-01 0.00E-01 4.48E 06 ' 2R 95 3.86E 06 8.498 05 7.56E 05 0.00E-01 1.22E 06 0.00E-01 8.85E 08 j ZR 97 5.70E 02 8.248 01 4.86E 01 0.00E-01 1.18E 02 0.00E-01 1.25E 07 j 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 0.00E-01 1.65E 07 0.00E-01 6.38E 06 TC 99M 4.71H 00 9.24E 00 1.51E 02 0.00E-01 1.34E 02 4.69E 00 5.26E 03 l s/93

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      \                                                       OFFSITE DOSE CALCULATION MANUAL D

TABLE .L 3-15 (coat'd) t0 VEGETATION PATHWAY PACTOR k a M MREM /YR PRR pCI/SEC j) CHILD (RI FACTORS)

      %s NUCLIDE               BONE    LIVER           T BODY          THYROID  KIDNEY     LUNG     GI-LLI TC      101           1.43E-30 1.495-30        1.89E-29         0.00E-01 2.55E-29 7.90E-31   4.75E-30 EU      103           1.533 01 0.002 01        5.68E Co         u.094-01 3.obE 07 0.00E-01   3.96E 08 RU     105           9.17E 01 0.00E-01        3.33E 01         0.00E-01 8.06E 02 0.00E-01   5.99E 04 EU      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 i
.                             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         3.165 08 3.775 09 0.00E-01   1.07E 09         !

TE 127 9.855 03 2.66E 03 2.11E 03 6.92E 03 2.80E 04 0.00E-01 3.85E 05 l TE 12pH 8.41E 08 2.35E 08 1.308 08 2.71E 08 2.47E 09 0.00E-01 1.03E 09 l t

TE 129 1.33E-03 3.70E-04 3.15E-04 9.46E-04 3.885-03 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 i TE 131 2.59E-15 7.90E-16 7.71E-16 1.98E-15 7.84E-15 0.005-01 1.365-14 1

l TE 132 7.00E 06 3.10E 06 3.74E 06 4.515 06 2.885 07 0.00E 3.12E 07 I I 130 6.16E 05 1.24E 06 6.41B 05 1.373 08 1.86E 06 0.00E-01 5.82E 05 l I 131 1.43E 08 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 03 7.P03 01 7.P7? 03 2.60E 02 1.00E-01 2.00E C2: I 133 3.53E 06 4.37E 06 1.65E 06 8.12E 08 7.28E 06 0.00E-01 1.765 06 1 i I 134 1.56E-04 2.89E-04 1.33E-04 6.65E-04 4.42E-04 0.00E-01 1.92E-04 i

j I 135 6.26E 04 1.13E 05 5.335 04 9.985 06 1.73E 05 0.00E-01 8.59E 04

CS 134 1.60E 10 2.63E 10 5.55E 09 0.00E-01 8.15E 09 2.93E 09 1.42E 08

) CS 136 8.04E 07 2.21E 08 1.43B 08 0.00E-01 1.18E 08 1.76E 07 7.773 06 I CS 137 2.39E 10 2.29E 10 3.38E 09 0.00E-01 7.46E 09 2.68E 09 1.43I 08 CS 138 6.61E-11 9.20E-11 5.83E-11 0.00E-01 6.475-11 6.965-12 4.24E-11 i BA 139 5.04E-02 2.695-05 1.465-03 0.00E-01 2.35E-05 1.58E-05 2.91E 00 RA 140 2.77E 08 2.435 05 1.62E 07 0.00E-01 7.90E 04 1.45E 05 1.40E 08 j RA 141 2.20E-21 1.23E-24 7.16E-23 0.00E-01 1.07E-24 7.24E-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 3.835 02 0.00E-01 0.003-01 0.00E-01 3.17E 07 1 l LA- 142 2.36E-04 7.51E-05 2.358-05 0.00E-01 0.00E-01 0.00E-01 1.49E 01 ! CE 141 6.56E 05 3.27E 05 4.86E 04 0.00E-01 1.43E 05 0.00E-01 4.08E 08 CE 143 1.72E 03 9.313 05 1.35E 02 0.00E-01 3.91E 02 0.00E-01 1.36E 07 CE 144 1.27E 08 3.98E 07 6.78E 06 0.00E-01 2.21E 07 0.00E-01 1.04E 10 PR 143 1.46E 05 4.38E 04 7.23E 03 0.005-01 2.378 04 0.00E-01 1.57E 08 i I' PR 144 5.44E-26 1.68E-26 2.74E-27 0.00E-01 0.90E-27 0.00E-01 3.62E-23 l [ ND. 147 7.24E 04 5.86E 04 4.54E 03 0.00E-01 3.22E 04 0.00E-01 9.295 07 N 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 0.005-01 5.31E 02 0.00E-01 1.36E 07 R/DJ l

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k. M* MREM /YR PER pCI/SEC d (RI FACTOR) f H-3 0.00E 00 Y-91M 1.00E 05 CS-134 6.86E 09 C-14 0.00E 00 Y-91 1.07E 06 CS-136 1.49E 08 MA-24 1.15E 07 Y d3 1.833 05 CS-137 1.03U 13 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 2.058 07 MN-56 9.03E 05 NB-95 1.37E 08 BA-141 4.18E 04 FE-55 0.00E 00 HO-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 7.378 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 2.9BE 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 KL-66 8.99E 06 TE-131 2.92E 04 RB-88 3.31E 04 TE-132 4.23E 06 RB-89 1.218 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 9/93

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7?JL'8 A.5-17 ld GRASS-GOAT-MILE PATHWAY FACTOR

 \                                       M' MREM /YR PER pCI/SEC J                                                ADULT                                        !

F NUCLIDE BONE LIVER T BODY THYROID EIDNEY LUNG GI-LLI H 3- 0.00E-01 1.56E 03 1.56E 03 1.56E 03 1.56E 03 1.563 03 1.56E 03 i C 11 2.633 CD ~ 5.272 07 5.270 07 1.27E 07 5.27E 07 5.2/E 07 5.27h 0? NA 24 2.93E 05 2.93E 05 2.935 05 2.93E 05 2.93E 05 2.93E 05 2.93E 05 P 32 2.055 10 1.27E 09 7.93E 08 0.00E-01 0.00E-01 0.00E-01 2.31E 09 CR 51 0.00E-01 0.00U-01 3.43E 03 2.05E 03 7.55E 02 4.55E 03 8.62E 05 MN 54 0.00E-01 1.01E 06 1.93E 05 0.00E-01 3.005 05 0.00E-01 3.09E 06 MN 56 0.00E-01 4.99E-03 8.853-04 0.00E-01 f.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 3.06E 05 9.07E 05 3.40E 05 0.00E-01 0.00E-01 2.54E 05 3.03E 06 CO 58 0.005-01 5.66E 05 1.27E 06 0.00E-01 0.005-01 0.00E-01 1.15E 07 CO 60 0.00E-01 1.97E 06 4.34E 06 0.00E-01 0.00E-01' O.00E-01 3.70E 07 NI 63 8.07E 08 5.65E 07 2.71E 07 0.00E-01 0.00E-01 l 0.00E-01 1.17E 07 1 l NI 65 5.56E 7.22E-03 3.30E-03 0.00E-01 0.00E-01 0.00E-01 1.035-01 CU 64 0.00E-01 2.66E 03 1.25E 03 0.003-01 6.70E 03 0.00E-01 2.27E 05 ZN 65 1.65E 00 5.243 08 2.37E 08 0.00E-01 3.50E 08 0.005-01 3.30E 08 7N 69 6.27E-13 1.20E-12 8.34E-14 0.00E-01 7.79E-11 0.00E-01 1.4cc-13 BR 83 0.00E-01 0.00E-01 0.005-01 0.005-01 0.005-01 0.00E-01 0.00E-01 BR 84 0.005-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 BR 85 0.00E-01 0.005-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 RB 86 0.005-01 3.11E 08 1.455 08 0.005-01 0.00E-01 0.00E-01 6.14E 07 RB 88 0.00E-01 0.005-01 0.00E-01 0.005-01 0.005-01 0.00E-01 0.00E-01 RB 89 0.00E-01 0.00E-01 0.005-01 0.00E-01 0.00F-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 0.005-01 4.45E-01 0.00E-01 0.005-01 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 2.80E-22 0.00E-01 0.00E-01 0.00E-01 2.13E-20 Y -91 1.03E 03 0.00E-01 2.765 01 0.00E-01 0.00E-01 0.005-01 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 0.005-01 0.00E-01 0.00E-01 8.87E 02 l i 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 3.258 03 NB 95 9.91E 03 5.51E 03 2.965 03 0.00E-01 5.45E 03 0.00E-01 3.35E 07 MO 99 0.00E-01 2.97E 06 5.655 05 0.00E-01 6.73E 06 0.00E-01 6.89E 06 TC 99M 3.99E-01 1.135 00 1.44E 01 0.00E-01 1.715 01 5.535-01 6.67E 02 1 1 I

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\                                OFFSITE DOSE CALCULATION MANUAL' N-TABLE A.5-17 (cont'd)

M ORASS-GOAT-MILK PATHWAY FACTOR ( M' MREN/YR PER pCI/SEC 'A ADULT V NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI TC 101 0.00E-01 0.005-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 RU- 103 1.22E'02 0.00E-01 S.26E 61 0.00E-01 4.66E 02 0.00E-01 1.43E 04 RU 105 1.03E-04. 0.00E-01 4.07E-05 0.005-01 1.335-03 0.005-01 6.30E ' RU .106 2.455 03 0.00E-01 3.10E 02 0.005 01 4.73E 03 0.00E-01 1.58E 05 AG 11CM 6.90E 06 6.46E 06 3.84E 06 0.00E-01 1.27E 07 0.00E-01 2.64E 09 TE 125M 1.95E 06 7.08E 05 2.62E 05 5.88E 05 0.00E-01 7.95E 06 7.81E 06 TE 127M 5.495 06 1.96E 06 6.70E 05 1.40E 06 2.23E 07 0.003 01 1.84E 07 TE 127 7.84E 01 2.82B 01 1.70E 01 5.81E 01 3.19E 02 0.005-01 6.19E 03 TE 129M 7.22E 06 2.69E 06 1.14E 06 2.485 06 3.02E 07 0.005-01 3.64E 07 TE 129 3.41E-11 1.28E-11 8.31E-12 2.62E-11 1.438 10 0.00E-01 2.57E-11 TE 131M 4.33E 04 2.12E 04 1.77E 04 3.36E 04 2.15E 05 0.00E-01 2.105 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 1.28E 06 ! I 131 3.55E 08 5.08E 08 2.915 08 1.67E 11- 8.71E 08 0.00E-01 1.34E 08 I 132 1.993 00 5.29R-00 1.89F-00 1.R5E 01 8.43E-00 0.033-C1 9.340-01 I 133 4.65B 06 8.08E 06 2.46E 06 1.195 09 1.41E 07 0.005-01 7.26E 06 I 134 2.445-12 6.63E-12 2.37E-12 1.15E-10 1.05E-11 0.00E-01 5.785-15 i i I 135 1.54E 04 4.04E 04 1.49E 04 2.665 06 6.48E 04 0.00E-01 4.56E 04 i CS 134 1.70E 10 4.04E 10 3.30E 10 0.00E-01 1.31E 10 4.34E 09 7.06E 08 C8 136 7.83E 08 3.095 09 2.23E 09 0.00E-01 1.72E 09 2.36E 08 3.51E 08 CS 137 2.21E 10 3.035 10 1.90E 10 0.00E-01 1.03E 10 3.42E 09 5.86E 08 C8 138 2.75E-23 5.43E-23 2.69E-23 0.00E-01 3.99E-23 3.945-24 2.32E-28 RA 139 5.48E-09 3.90E-12 '1.605-10 0.00E-01 3.65E-12 2.21E-12 9.71E-09 BA 140 3.235 06 4.05E 03 2.11E 05 0.00E-01 1.38E 03 2.32E 03 6.64E 06 RA 141 0.00E-01 0.005-01 0.00E-01 0.00E-01 0.005-01 0.005-01 0.005-01 RA 142 0.005-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01

        - LA     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   1.285-13    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    1.835 02     0.003-01   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    i 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   9.398-00    0.00E-01    4.39E 00     0.005-01   8.305 04 PR     144  0.005 01  0.00E-01   0.00E-01    0.00E-01    0.00E-01     0.00E-01   0.00E-01 ND     147  1.14E 01  1.31E 01   7.85E-01    0.005-01    7.67E 00     0.005-01   6.30E 04 W      187  7.87E 02  6.58E 02   2.30E 02    0.0,0E-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

2-g Ravicion: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 0 g Raforanca Uma Page 176 of 188

D ATTACHMENT A O

M (Page 172 of 184) 'T OFFSITE DOSE CALCULATION MANUAL M TABLE A.5-18 M GRASS-GohT-MILK PATHNAY FACTOR 8

\                                    M MREM /YR PER pCI/SEC g                                             TE&h NUCLIDE    BONE     LIVER      T BODY       THYROID       KIDNEY                LUNG           GI-LLI 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 4.96E 09  9.725 07    9.721 07     9.7?       07 0.72C 37         S.7;E C7            5.72E 07 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 3.785 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   5.93E 03      3.33E 03      1.31E 03         8.55E 03            1.01E 06 MN     54 0.005-01  1.bdB 06   3.345 05      0.00E-01      5.02E 05         0.005-01            3.45E 06 i MN     56 0.00E-01  8.85E-04   1.57E-04      0.00E-01      1.12E-03        0.00E-01             5.82E-02 FE     55 5.79E 05  4.10E 05   9.57E 04      0.00E-01      0.00E-01        2.60E 05             1.78E 05 FE     59 6.74E 05  1.57E 06   6.07E 05      0.00E-01      0.00E-01        4.96E 05             3.72E 06 CO     58 0.00E-01  9.52E 05   2.19E OG      0.005-01      0.00E-01        0.00E-01             1.31E 07 !

CO 60 0.00E-01 3.34E 06 7.52E 06 0.00E-01 0.00E-01 0.005-01 4.35E 07 NI 63 1.42E 09 1.00E 08 4.81E 07 l 0.00E-01 0.00E-01 0.00E-01 1.59E 07 ; NI 65 1.02a-01 1.30E-02 5.92E-01 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 EN 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 1.548-13 0.00E-01 1.44E-12 0.00E-01 -4.05E-12 BR 83 0.00E-01 0.00E-01 0.005-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 ! BR 84 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 ! BR 85 0.00E-01 0.005-01 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 RB 88 0.005-01 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 1.3 9E 11 0.00E-01 3.43E 10 0.00E-01 0.00E-01 0.005-01 3.90E 09 SR 91 1.11E 05 0.00E-01 4.40E 03 0.00E-01 0.00E-01 0.00E-01 5.023 05 1 SR 92 1.88E 00 0.00E-01 8.02E-02 0.00E-01 0.00E-01 0.00E-01 4.80E 01 l Y 90 1.56E 01 0.00E-01 4.20E-00 0.00E-01 0.00E-01 0.00E-01 1.29E 05 Y 91M 1.33E-20 0.00E-01 5.07E-22 0.00E-01 0.005-01 0.00E-01 6.26E-19 Y 91 1.90E 03 0.00E-01 5.00E 01 0.005-01 0.00E-01 0.00E-01 7.77E 05 Y 92 1.24E-05 0.00E-01 3.59E-07 0.00E-01 0.00E-01 0.00E-01 3.40E-01 Y 93 5.16E-02 0.00E-01 1.41B-03 0.00E-01 0.00E-01 0.005-01 1.585 03 ZR 95 1.98E 02 6.25E 01 4.30E 01 0.00E 01 9.18E 01 0.00E-01 1.44E 05 ZR 97 9.47E-02 1.87E-02 8.63E-03 0.00E-01 2.84E-02 0.00E-01 5.07E 03 NB 95 1.69E 04 9.37E 03 5.163 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 0.00E-01 0.00E-01 0.00E-01 0.00E-01

g R'; vision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 bl ROfGrcnco Ur3 Prga 177 of 188 g 9 ATTACHMENT A O (Page 173 of 181) N OFFSITE DOSE CALCULATION MANUAL t TABLE A.5-19 (cont Y) M GRASS-GOAT-MILK PATHWAY FACTOR M' MREM /YR PER pCI/SEC k f Ti.hN W NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI RU 103 2.17E 02 0.00E-01 9.28E 01 0.00E-01 7.66E 02 0.00E-01 1.81E 04 FM 1*C 1. P fM"- 01 0.00E-01 7.33-05 0.0*2-01 J . 3i2 -C J 0.001:. 01 1. 32 E - L RU 106 4.50E 03 0.00E-01 5.67E 02 0.00E-01 8.68E 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 OG 1.30E 05 4.82E 05 1.01E 06 0.0CE-01 0.00E-01 3.06E 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 6.2BE-11 2.34E-11 1.53E-11 4.4BE-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-38, 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 0.0GE-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 113 8.495 06 1.44F 07 4 19E 06 ?.01E 09 7.52E 07 0.00R-01 1.03E 07 1 134 4.34E-12 1.15E-11 4.13E-12 1.92E-10 1.81E-11 0.00E-01 1.51E-13 I 135 2.748 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 lo 0.00E-01 2.20F 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 9.01E 13 2.25E-13 0.00E-01 0.00E-01 0.00E-01 2.75E-08 CE 141 1.07E 02 '7.13 0{ 8.18E 01 0.00E-01 3.35E 02 0.00E-01 2.04E 06 CE 143 9.17E 00 6.67E D3 7.45E-00 0.00E-01 2.99E 00 0.00E-01 2.01E 05 CE 144 7.90E 04 3.278 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 2.3BE 01 1.42E 00 0.00E-01 1.40E 01 0.00E-01 8.57E 04 W 187 1.44E 03 1.17E 03 4.11E 02 0.00E-01 0.00E-01 0.00E-01 3.18E 05 NP 239 8.41E-01 7,93E-02 4.41E-02 0.00E-01 2.49E-01 0.00E-01 1.28E 04

 !   R;vicion: 0 lg                           OFFSITE DOSE CALCULATION MANUAL                    AP 07B-003 E}

g RJforanca U;c Page 178 of 188 E) ,8 ATTACHMENT A (Page 3 74 of 184) JFFSITE DOSE CALCULATION MANUAL a TABLM A.5-19 p GRASS-GOAT-MILK PATHWAY FACTCR

 \                                       8 M MREM /YR PER pCI/SEC
 -),                                            CalILI) e       NUCLIDE    BONE     LIVER      T BODY      THYROID    KIDNEY    LUNG     GI-LLI H      3 0.00E-01  3.20E 03    3.20E 03    3.208 03  3.20E 03 3.20E 03   3.20E 03 C    14  1.19E 39 2.3]E 02    2.39E 33    2.3DE 03  2.05C 06 2.39E 08   2.39E 06 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-31  0.00E-01    1.22E 04    6.7BE 03  1.85E 03 1.24E 04   6.48E 05 MN     54 0.00E-01  2.52E 06   6.70E 05     0.00E-01  7.06E 05 0.00E-01   2.11E 06 MN     56 0.00E-01  1.54E-03   3.48E-04     0.00E-01  1.87E-03 0.00E-01   2.24E-01 FE     55 1.45E 06  7.70E 05   2.39E 05     0.00E-01  0.00E-01 4.36E 05   1.43E 05 FE     59 1.56E 06  2.53E 06   1.26E 06     0.00E-01  0.00E-01 7.33E 05   2.63E 06 CO     58 0.003-01  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   1.288 07 NI     65 2.49E-01  2.34E-02   1.37E-02     0.00E-01  0.00E-01 0.00E-01   2.87E 00 CU     64 0.00E-01  8.23E 03   5.03E 03     0.00E-01  2.01E 04 0.00E-01   3.91E 05   l ZN     65 4.96E 08  1.32E 09   8.22E 08     0.00E-01  8.33E 08 0.00E-01   2.32E 08 i

ZN 69 2.84E-12 4.10E-12 3.74E-23 0.00E-01 2.448-12 0.00E-31 .9.r8E-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 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 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 i 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 OR 90 2.35E 11 0.00E-01 5.95E 10 0.00E-01 0.00E-01 0.00E-01 3.16E 09 SR 91 2.71E 05 0.00E-01 1.02E 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 i Y 91M 3.24E-20 0.00E-01 1.18E-21 0.00E-01 0.00E-01 0.00E-01 6.34E-17 Y 91 4.68E 03 0.00E-01 1.25E 00 0.00E-01 0.00E-01 0.00E-01 6.24E 05 Y 92 3.04E-05 0.00E-01 8.71E-07 0.00E-01 0.00E-01 0.00E-01 8.79E-01 ! Y 93 1.27E-01 0.00E-01 3.48E-03 0.00E-01 0.00E-01 0.00E-01 1.89E 03 ER 95 4.602 02 1.01E 02 9.00E 01 0.00E-01 1.45E 02 0.00E-01 1.05E 05 l 2R 97 2.30E-01 3.33E-02 1.96E-02 0.00E-01 4.7BE-02 0.00E-01 5.04E 03 j NB 95 3.82E 04 1.49E 04 1.06E 04 0.00E-01 1.40E 04 0.00E-01 2.75E 07 l j MO 99 0.00E-01 9.76E 06 2.42E 06 0.00E-01 2.08E 07 0.00E-01 8.07E 06 l TC 99M 1.59E 00 3.11E 00 5.16E 01 0.00E-01 4.52E 01 1.58E 00 1.7 1 03 l TC 101 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 l I l

3 a Rovision: 0 OFFSITE DOSE CALCU1 ATION MMUAL AP 07B-003 U R3f rcnc3 U;a M Page 179 of 188 i t1 ATTACHMENT A O (Page 175 of L84) M j

  \                          OFFSITE DOSE CALCULAMON MANUAL                                          !

03 TABLE A.5-19 (cont' t) M GRASS-GOAT-MILK PATHWAY F/CTOR

  \                                      M? MREM /YR PER pCI/SEC g                                               CHILD NUCLIDE     BONE    LIVER      T BODY      THYROID       KIDNEY    LUNG     GI-LLI RU     103 5.14E 02 0.00E-01    1.978 02    0.00E-01     1.29E 01 0.00E-01   1.33E 04 I

kU 105 4.595-04 0.00E-01 1.67E-04 0.00E-01 4.04E-03 0.00E-01 3.00E-01 RU 106 1.118 04 0.00E-01 1.38B 03 0.00E-01 1.50E 04 0.00E-01 1.72E 05 AG 110M 2.51E 07 1.69E 07 1.353 07 0.00E-01 3.15E 07 0.00E-01 2.01E 09 TE 125M 8.85E 06 2.40E 06 1.18B 06 2.48E 06 0.00E-01 0.00E-01 8.54E 06 1 TB 127M 2.50E 07 6.72E 06 2.96E 06 5.97E 06 7.12E 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 1.40B 04 l TE 129M 3.26E 07 9.09E 06 5.05E 06 1.05E 07 9.56E 07 0.00E-01 3.97E 07 l 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 TB 132 1.23H 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 08 6.27E 06 0.00E-01 1.96E 06 I 131 1.56E 09 1.57E 09 8.94E 08 5.20E 11 2.58E 09 0.00E-01 1.40E 08 1 I 132 8.30E-01 1.52E 00 7.01E-01 7.07E 01 2.33E 00 0.00E-01 1.79E 00 l I 133 2.06E 07 2.55E 07 9.6b4 06 4.74E 09 4.2SE 07 0.00E-01 1.03E 07 ' I 134 1.03B-11 1.91E-11 8.77E-12 4.39E-10 2.923-11 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 CS 134 6.79E 10 1.11E 11 2.358 10 0.00E-01 3.45E 10 1.24E 10 6.01E 08 CS 136 3.01F 09 8.27h 09 5.358 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-12 4.90E-13 0.00E-01 0.00E-01 0.00E-01 3.10E-07 CE 141 2.63E 03 1.31E 03 1.94E 02 0.00E-01 5.74E 02 0.00E-01 1.63E 06 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 l 1.40E 01 0.00E 01 9.30E 04 l PR 144 0.00E-01 0.00E-01 0.00E 01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 i 147 5.36E 01 l ND 4.34E 01 3.36E 00 0.00E-01 2.38E 01 0.00E-01 6.BBE 04 W 187 3.49E 03 2.07E 03 9.28E 02 0.00E-01 0.00E-01 0.00E-01 2.90E 05 l NP 239 2.07E 00 1.49E-01 1.04E-01 0.00E-01 4.30E-01 0.00E-01 1.10E 04 9/92 l

R 5 Rovision g 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 0 Rsforcnca Use g Page 180 of 188 O ( ATTACHMENT A 0 (Page 176 of 1sc) { N OFFSITE DOSE CALCULATION MANUAL TABLE A.5-20 l0 GRMS-GOAT-MILK PATHWAY FACTOR \ M* MREM /YR PER pCI/SEC y INFANT j W NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI H 3 0.00E-01 4.865 03 4.86E 03 4.86E 03 4.86E 03 4.86E 03 4.86E 03 0 14 2.343 0) 5.00E CC 5.00E bd 5.00E Ga 5.003 08 5.003 06 5.004 06 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 2.45E 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 FE 59 2.92E 06 5.09E 06 2.01E 06 0.00E-01 0.00E-01 1.51E 06 2.43E 06 CO 58 0.00E-01 2.91E 06 7.26E 06 0.00E-01 0.00E-01 0.00E-01 7.25E 06 00 60 0.00E-01 1.06E 07 2.50E 07 0.00E-01 0.00E-01 0.00E-01 2.52E 07 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 ZN 65 6.66E 08 2.28E 09 1.05E 09 0.00E 01 1.11E 09 0.00E-01 1.93E 09 ZN 69 6.04E-12 1.093 11 8.162-13 0.00F-01 4.f2E-12 0.CCE-01 8.97E 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 1.328 09 0.00E-01 0.00E-01 0.00E-01 6.83E 07 RB 88 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 RB 89 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 SR 89 2.64E 10 0.00E-01 7.58E 08 0.00E-01 0.00E-01 0.00E-01 5.43E 08 SR 90 2.55E 11 0.00E-01 6.50E 10 0.00E-01 0.00E-01 0.00E-01 3.19E 09 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 1.055 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 0.00E-01 0.00E-01 0.00E-01 2.29E-16 Y 91 8.79E 03 0.00E-01 2.34E 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 ZA 95 8.17E 02 1.99E 02 1.41E 02 0.00E-01 2.14E 02 0.00E-01 9.91E 04 ZR 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 MO 99 0.00E-01 2.50E 07 4.87B 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 I

fW l ll Ravision! 0 lg OFFSITE DOSE CALCULATION MANUAL AP 07B-003 Rsforcnca U2O Page 181 of 188 ATTACHMENT A iO (Page 177 of 194) M l\ OFFSUfE DOSE CALCULATION MANUAL b) 4 LDLE A.5-20 (cont'd) M ORASS GOAT-MILE PATHWAY FACTOR

 \                                     M MREM /YR PER SCI /SEC 4                                              INFANT O'

NUCLIDE BONE LIVER T BODY THYROID KIDNEY LUNG GI-LLI TC 101 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 P.U 103 1.C4E C3 0.0]E-01 3.4SE J2 0.DUC-01 2.16E 03 0.00E-01 1.J66 04 RU 105 9.68E-04 0.00E-01 3.26E-04 0.00E-01 7.12E-03 0.00E-01 3.85E-01 RU 106 2.28E 04 0.00E-01 2.85E 03 0.00E-01 2.70E 04 0.00E-01 1.73E 05 AC 110H 4.63E 07 3.38E 07 2.248 07 0.00E-03 4.83E 07 0.00E-01 1.75E 09 TE 125M 1.81E 07 6.05E 06 2.45E 06 0.00E-01 E.0,9F 06 0.00E-01 8.62E 06 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 2.578 07 1.67E 08 1.03E 07 0.00E-01 3.99E 07 TE 129 3.28E-10 1.13E-10 7.66E-13 2.75E-10 8.17E-10 0.00E-01 2.62E-08 TE 131M 4.05E 05 1.63E 05 1.35E 0'i 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 332 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 1.055 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 3.49R 00 1.24F 06 1.64E 02 3.90E 00 0.097 01 2.012 00 2 133 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 0.005-01 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 08 CS 137 1.54E 11 1.81E 11 1.28E 10 0.00E-01 4.85E 10 1.96E 10 Sg65E 08 CS 138 2.S5E-22 4.15E 22 2.01E-22 0.00E-01 2.07E-22 3.23E-23 6.63E-22 RA 139 5.30E-08 3.51E-11 1.53E-09 0.00E-01 2.11E-11 2.13E-11 3.35E-06 BA 140 2.89E 07 2.89E 04 1.49E 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 __BA 142 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 LA 140 4.88E 00 1.92E 00 4.94E 00 0.00E-01 0.00E-01 0.00E-01 2.26E 04 LA 142 1.03E-11 3.78E-12 9.06E-13 0.00E-01 0.00E-01 0.00E-01 6.43E-07 CE 141 5.20E 03 3.17E 03 3.74E 02 0.00E-01 9.79E 02 0.00E-01 1.64E 06 i CE 143 4.76E 01 3.16E 04 3.61E 00 0.00E-01 9.21E 00 0.00E-01 1.84E 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 2.48E 01 0.00E-01 9.41E 04 l PR 144 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 i ND 147 1.06E 02 1.09B 02 6.6DE 00 0.00E-01 4.21E 01 0.00E-01 6.92E 04 i W 187 7.35E 03 5.11E 03 1.77E 03 0.00E-01 0.00E-01 0.00E-01 3.00E 05 NP 239 4.38E 00 3.91E-01 2.21E-01 0.00E-01 7.805-01 0.00E-01 1.13E 04

w _ . _ . _ _ . _ _ _ ____. . - - - - - - - - - R0 vision 0 .OFFSITE DOSE CALCULATION MANUAL AP 07B-003 Raforenca Uso Page 182 of 188 0 ATTACHMENT A O (Page 178 of 184) OFFSITE DOSE CALCULATION MANUAL M

 'kt
   \

E W APPENDIX B Meteorological Model 4

I R*; vision : 0 OFFSITE DOSE CALCULATION MAINAL AP 07B-003 R0fcrcnc3 U n Page 183 of 188 ATTACHMENT A 6 (Pa.ge 179 of 184) N OFFSITE DOSE CALCULATION MANUAL h) APSEl? DIX B PEOP.RIETIRLTNFERMETION.SIIEPFID_BY 9" E. The X/Q's and D/Q's are calculated using the guidance of Reg. l Guide 1.111. I The constant mean wind direction model, as defined in equation 3 of Reg. Guide 1.111, is used to calculated X/Q values. I i

                                                  ~2      2 2.032 Eny exp  -h ,/2 o ,j [x)]                 ;

(x/Q) - U 1 N x Ut E(x)

                                                    =J Where:

1 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 atmonpharic stability class j. N = total house of valid data Di - midpoint of windspeed class (m/s) x - distance downwind (m) og (x) = vertical plume spread without volumetric correction at distance x and stability class j. See Figure B.1. Eg(x) = vertical plume spread with columetric correction for release within buildings wake cavity, at distance x and stability class j. For ground level releases Eg (x) is the lesser of 2 2 (a e (x) + 0.5 D ,j,f2 or}3 o g (x)

w 3 y Rsvision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 M p; Rsforcnca Une Page 184 of 188 U ATTACHMENT A O N (Page 180 of 184) \ OFFSITE DOSE CALCULATION MANUAL N i APPENDIX B (CONT"D) l Where: J g D, = maximum adjacent building height either up- or < i down-wind from the release point ! 1 2.032 = (2/n) " divided by width, in radiana, of a 22.5 sector (X/Q)n = Average effluent concentration, X, normali zed to source strength, Q, at distance x in sector D. i For WCGS the above Meteorological Model will simplify to the following equation for X/Q: 2.032 ][ng

                             =        U (X / Qi)D     _

N Un x ][(x) U The calculation of the relative disposition per unit area, D/Q, is performed using the deposition rate graphs found in Reg. Guide 1.111. For c 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: 1 D/Q = Da (x) . DEPL (x) g (:2 n /16)x Where: Dy(x) = Relative deposition rate for windspeed class i and I stability class j at downwind distance x (1/m). See Figure B.3. (2n/16)x - length of are across sector at downwind distance x (m). D/0 = relative deposition per unit area (m)

j f l g R3 vision: 0 OFFSITE DOSE CALCUIATION MANUAL AP 07B-003 O RafSrznca Ua 5 Page 185 of 188 6 ATTACHMENT A 8'l (Page 181 cf 184) l OFFSITE DOSE CALCULATION MANUAL 1 f APPENDIX B (CONT'D) 7 ji DEPL33(x) = RedGction factor due to plume depletion at distance x g- for windspeed i and stability class j. l l l l l 1

W b Revision: 0 OFFSITE DOSE CALCUIATION MANUAL AP 078-003 9 ' 41P 8 Raforencs U30 Page 186 of 188 ATTACHMENT A ,O (Page 182 of 184) lN OFFSITE DOSE CALCULATION MANUAL ! lb Figure B.1 F

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i i I 0.1 1.0 10 100 PLUME TRAVEL DISTANCE (KILOMETERS) I Vertical Standard Deviation of Materist in a Plume (Letters denote Pasquilt Stability Class) i l l NOTE: THGSE ARE STANDARO REtAflONStilPS ANO MAY HAVE TO DE ( MOOtFIEO FOR CERTAIN TYPES OF TERRAIN AND/OR CLIMAflC l l CONO!TIONS(E.C. VAlt.EY OESERT OVER WATERI. ; I f 'B-4 ; ! I i

b! R;vicion: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 RafGrCnca U o Page 187 of 188 e ATTACID4ENT A & (Prige IR3 of 184) h/ o OFFSITE DOSE CALCULATION MAIR7AL Figure B.2 f3 4 .a (F . 8 l

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n. p Ravicion 0 OFFSITE DOSE CALCULATION MANUAL AP 073-003 M1 RafCrcnco U23 Page 188 of 188 9 ATTACHMENT A @ (Page 184 of 184) g 4 OFFSITE DOSE CALCULATION MANUAL 13 py Figura B.3 h 2 or 104 10-d x s W %

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204 N x l 10-7 0.1 1A 10.0 1003 200.0 PLUMG TRAVEL OtSTANCE (KtLOMETERS) R-6

                                        - END -

3 a 3 . gI " FORN,APF 15A-003-05, REV. 2 f fil O RECORD SUPPLEMENTAUCORRECTION SHEET lc I U:

  \      1.       AFFECTED RECORD h) l File No.:              h ~~) - dd )

i A Record Ti'.1.0/Reccrd C Numbers oppgyrg cp3g pAqfgj t Ayggy m A n,j A t ,) p p o g g

2. DESCRIPTION OF DATA BEING CHANGED, ANENDED, ETC.

CN q c notc S and 6 on pe,e y4 -to Ibte to and ~7, respective _ht,

3. REASON FOR SUPPLEMENT OR CORRECTION Stey m%-nunberi ccc.amA duivan last froaduM.

re- an& ceaM c. 4 APPROVAL SIGNATURES. THESE CHANGES HAVE RECEIVED THE APPROPRIATE REVIEW AND APPROVALS BY THE ORIGINATING ORGANIZATION. Ah0h k, Al10 Al W 6.5 S l-Or ator

                                           ~'      ~-

Date J r Approval Signatu'r6 ' ' Date Additional Signature (s) (if required) Date Does this Supplemental / Correction Sheet affect the Code QA Program? No YesO (If yes, complete the following with the appropriate signatures.) 't Yw M Manager flaintenance D. Aleux6 &11-44 Dato Supervisor Quality Control (QC Inspections) or Date Supervisor Quality Evaluations (Surveillances)

                        ~ ANII/ANI/AI                                           Date

l D .c lavision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 ; a ' m Reference Use Page 44 of 188 0 i a ATTACHMENTA a (Page 40 of 184) , \ OFFSITE DOSE CALCULATION MANUAL IM l .- TABLE 3-1 (Continued)

  \                                            TABLE NOTATIONS M       (M           The principal gamma emitters for which the LLD specification applies O'                   include the following radionuclides: Kr-87, Kr-88, Xe-133, 133,                  j Xe-133m, Xe-135, and Xe-138 in noble gas releases and Mn-54, Fe-59,              '

l Co-58, Co-60, Zn-65, Mo-99, I-131, Cs-134, Cs-137, Ce-141 and Ce-144 l in iodine and particulate releases. This list does not mean that only these nuclides are to be considered. Other ganna peaks that zo.e : identifiable, together with those of the above nuclides, shall also be analyzed and reported in the semiannual Radioactive Effluent Release l Report in the format outlined in Regulatory Guide 1.21, Appendix B, Revision 1, June 1974. l (3) Sampling and analysis shall also be performed following shutdown, I startup, or a THERMAL POWER change exceeding 15% of RATED THERMAL I POWER within 1 hour period. (4) Tritium grab samples shall be taken and analyzed at least once per 24 hours when the refueling canal is flooded. l (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 l calculation made in accordance with Sections 3.1, 3.2 and 3.3. , 1 (7) Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours after changing, or after removal from sampler. For unit vent, sampling shall also be performed at least l once per 24 hours for a least 7 days following each shutdown, startup or THERMAL POWER change exceeding 15% of RATED THERMAL POWER within a 1-hour period, and analyses shall be completed within 48 hours of changing. When samples collected for 24 hours are analyzed, the corresponding LLD's may be increased by a factor of 10. This l requirement does not apply if: (1) analysis shows that the DOSE I EQUIVALENT I-131 concentration in the reactor coolant has not l increased more than a factor of 3, and (2) the noble gas monitor i shows that effluent activity has not increased more than a factor of 3. l l t l

-~y

M 1 koR4f aPF 15C-004 04 arv 06 pg ) g gg 7 n Document Number: ON THE SPOT CHANGE (OTSC) OTSCs: % owq rri AP 07B-003 Current Revision Number: 0 O Document

Title:

Offsite Dose Calculation Manual I I O Originator: ) Teresa L. Rawlings 6/11/96 l 0* Print Name Date

  \   Reason For Change:(Erplain)             Attachment A, Figure 5.5 is being revised to more accurately depict milk location S-3. The M    change is being made due to a comment in Quality Evaluation Audit Report K15-002 K-458.

TJ

 \                                                                                                                      O Continued on attached OTSC SCREENING f                            (A YESanser to any ofthefollowing questions indicates an 015C cannot be performed)

1. la this a change to the intent of the procedure as defined in the purpose or scope? O YES g NO

2. Will this change decrease or modify a hold point requirement or Quality inspection point? O YES O NO

3. Will the change result in a reduction of personnel or equipment safety?

O YES S NO

4. Will the change involve a USQD? (Must perform a screening to determine) D YES g NO g A marked up copy of the proposed change is attached.

O Regulatory Screenings and/or Evaluations (APF 26A-003-1) has been completed and attached as required by AP 26A-003, SCREENING AND EVALUATING CHANGES, TESTS, AND EXPERIMENTS. APPROVAL FOR IMMEDIATE USE j Approved By:/fi" rIntYn~ dent

                                    //M           '

(for Ps nly) L/D te/1/k ' Approved By: _ M h/ / W 'OC StafMember* Print Name Date . 1 Approved By: l Cogyofant Supervisor

Q r-C V

                                                                                          ) PrintName d

h/d/b Date

For Operations Dehartm#t procedures, one must hold a Senior Reactor Operator license per TS 6.8.3.

The remainder of this form shall be completed within 14 days as required by Technical Specification 6.8.3. QUALIFIED REVIEW Cross-Disciplinary Review Required By: O NONE REQUIRED D QPCVM Matrix (Form APF 15C-004-08) M Quality Evaluations O QualityControl o Surveillance Coordinator a Other(specify)h Afd f-g PSRC review required.' O PSRC review and VP Plant Operations approval not requi

                                          * (Mandatoryfor all OTSC's to Administrative Control Procedures)                                   {

All cross-disciplinary reviews have been completed, reviewer comments have been resolved, and the recormaended disposition of this OTSC en identified n the JINA APPROVAL section of this form. ets ef t$antt*% (o /2$~/ % ()ualified Revicur Print Name Date FINAL APPROVAL

     % Approved:                                               O Disapproved, cancel, remove from OTSC file, and initiate PIR M Maintain in active OTSC file until incorporated into future revision.                    Incorporated by DRR number:

or OTSC number: O Maintain in active OTSC file until specified date / / (TMs sectionfor Administrative ControlP dures Only) roved O 717 - I/& N M Disapproved, lPSRC Meeting No:

                                                                                  ' *fSRCChairman(Initials)                         Date UN                    hwM/                                                                                 h/A?l$

Vice/residen' t P'lant' Operations Date

                                                                                                                           /     /

Responsible Manager (For all 07SC except ACP 's) Date DC34 (o-23-%

H 2 - p., Revision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 g 0T5( 96 04(:n ; m Reference Use Page 91 of 188 l O Pccu 1AA ATTACHMENT A C (Page 87 of 184) g OFFSITE DOSE CALCULATION MANUAL M \1 FIGURE 5.5 \ " ~~

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m 3 . h APF 26A-003-01, Rev.1 otsc Ct4 -04b'7 m REGULATORY SCREENING NO. 59 0 l USQD rev. Document Number: AP 078-003 Revision: O Page 1 of 4 r

 }. Description of Proposed Change: Attachment A, Figure 5.5 is being revised to more accurately y  d:pict milk location S-3. The change is being made due to a comment in Quality Evaluation Audit g  Report K15-002 K-458.
 .o T

Screening Questions: (Note: All questions must be answered except as provided in questions 1 and 2, all cvaluations shall be completed using forms APF 26A-003-02 and APF 26A-003-03 as appropriate.)

1. Has this change been previously 0 YES No further screening is required.

approved for WCNOC by the NRC or Document # covered by another Unreviewed Safety Justify in

Clarification
Section.

question Determination (APF 26A-003- B NO

03) See Note Below.

NOTE: If referencing a previously performed USQD: a) contact Licensing to update USQD log, b) review to ensure USDQ meets current procedural standards and expectttions (Reference step 6.5 of procedure AP 26A 003), c) ensure that it has been approved by the PSRC prior to implementing the change, and d) ensure no interim changes have been implemented which could affect the proposed change or conclusions of the screening or evaluations.

2. Would the change result in a revision O YES Change may NOT be implemented prior to to the Operating License including approval of a License Amendment (NOTE:

Appendices? (This includes the No further screening is required since Technical Spe :ifications) NRC approval must be obtained prior to implementing the change.) B NO

3. Identify the sections of the Updated Safety Analysis Report (including the Emergency Plan and Security Plans) which are related to or may be affected by the change. Identify the review by Chapter, Section, page or Figure (Reference the revision of the page if page number is used). It is important in this review to go beyond direct affects of a change and to document those sections.

Reviewed Reviewed and Affected Chapter 17 l Section 9.5.1 l Section 13.2.1.2 1

I- H 3 . ; D

     .APF 26A-003-01. Rev.1 6%<_  #N - 0 L(o 7
  $                                       REGULATORY SCREENING                            NO. 59           l c                                                                                       USQD rev.

i ; Document Number: AP 07B-003 Revision: O Page 2 of 4 l o l i F l \ 10 l 4. Could the change potentially result in a revision to: l \1 1

  \  a. The Physical Security Plan, A b. The Safeguards Contingency Plan, or                                                                 !

F l l c. The Security Training and Qualification Plan? I O Yes if Yes an evaluation must be O No completed in accordance with 10 CFR 50.54(p) prior to implementing the change. This evaluation must be approved by the Superintendent Security or the Manager Design Engineering l if yes to this question, the' proposed change may also require evaluation under 10 CFR 50.59 ! (question 11 on this form). (Security documents are safeguards documents. If unsure of the affect of the proposed change, contact Security or Engineering.)

5. Could the change potentially result in a revision to the Operating Quality Assurance Program described in Chapter 17 of the USAR. If Chapter 17 of the USAR was identified as affected in section 3 of this form, this block must be checked yes.

O Yes if yes, an evaluation must be E No approved in accordance with 10 CFR 50.54(a)(3) by the Manager Performance l Assessment ! If yes to this question, the proposed change may also require evaluation under 10 CFR 50.59 (question 11 on this form). I

6. Could the change potentially result in a revision to the Fire Protection Program described in USAR Section 9.5.1and 9.5 Appendices? If Chapter 9.5.1 or 9.5 Appendices of the USAR were identifed I

as affected in section 3 of this form, this block must be checked yes. O Yes If yes, an evaluation must be E No : approved in accordance with license NPF-42 paragraph 2.c(5) by the Superintendent Resource Protection or an Engineering Manager. If yes to this question, the proposed change may also require evaluation under 10 CFR 50.59 (question 11 on this form). l

3 D . APF 26A-003-01, Riv.1 MsC C4L-ObG,7

 $                                      REGULATORY SCREENING                       .

NO. 59 i o USQD rev. Document Number: AP 078-003 Revision: 0 Page 3 of 4 r

7. Could the change potentially result in a re'rision to the Radiological Emergency Response Plan?

v O Yes if yes, an evaluation must be approved E No

 \                                        in accordance with 10 CFR 50.54(q) by D

F the Manager Emergency Planning prior to implementation of the change. If yes to this question, the proposed change may also require evaluation under 10 CFR 50.59 (question 11 on this form).

8. Could the change potentially result in a revision to the Licensed Operator Re-qualification Program as described in USAR Section 13.2.1.27 If Chapter 13.2.1.2 of the USAR was identified as :

affected in section 3 of this form, this block must be checked yes. O Yes If yes, an evaluation must be approved E No : in accordance with 10 CFR 50.54 ) (1-1) by the Manager Training. If yes to this question, the proposed change may also require evaluation under 10 CFR 50.59 (question 11 on this form).

9. Could the change potentially result in a change to an NRC commitment?.

O Yes if yes, an evaluation must be E No coordinated by the Supervisor Regulatory Compliance.

10. Does the proposed change involve one or more of the following:

a. A change in the rate, volume, concentration, composition or flow path of nonradiological liquid or gaseous effluents?

b. A change in the volume, concentration or composition of nonradiological solid waste?

c. An increase in the thermal power above the current licensed level and/or an alteration in the magnitudes of thermally affected effluents?

d. A physical change in area outside of the owner controlled area boundary which was not disturbed by previous construction?

e. The addition of a new storage tank, or physical changes to the piping or capacity of an existing tank, that contains more than 660 gallons of chemical O Yes if yes, an environmental impact O No determination must be approved by the Superintendent- Resource Protection.

H i 3 - D APF 26A-003-01. R:v.1 OT5L CR, - O ldo7 n REGULATORY SCREENING NO. 59 a USQD rev. Document Number: AP 078-003 Revision: 0 Page 4 of 4 o r }y NOTE: For purposes of this question the Emergency Plan and Security Plans are considered part of the USAR.

3 11. Would the change involve one or more of the following: r a. a change to the plant structures, systems, components or equipment as outlined, summarized or described in the USAR such that accomplishment of the change could directly or indirectly make information in the USAR no longer true, complete or accurate, or would violate a requirement stated in the USAR? 1

b. a change to procedures or administrative controls as outlined, summarized , or described in the USAR such that accomplishment of the change could make information in the USAR no longer true, complete or accurate, or would violate requirement stated in the USAR?

c. Tests or experiments NOT described in the USAR?

O Yes A formal Unreviewed Safety Question El No 1 Determination using APF 26A-003-03 ' must be completed prior to implementing the change. Reminder: If es. evaluate need for a USAR Change Request in accordance with AP268-003 Ca . ed that step 11.a convey a broad and conservative interpretation of 10 CFR 50.59 as described in NSAC-125. An unreviewed safety question determination is required if the proposed change could alter the description of any SSC or equipment described in the USAR. This applies to the specific SSC being changed as well as any other equipment that could be affected directly or indirectly.

12. Clarification:

Prepared by: 4 ggg Date: (g _ 44 Approved by: fj Date: 4 ,74 % 7 .-

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Title:

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 .9 0-    Please retum completed Comment Control Form to:

Daniel Williamson Environmental Met. 4609 06-19-96 Print Name Pepartment Extension Date due No. - Comment number M = Mandatory G = General Step = Procedure step number COMMENTS RESOLUTION No.& Step & description No. M/G ! O This Comment Control Form is being utilized by the QR to document the distribution of and responses to OTSC 96-0667. The following individuals received copics: Birk, D. A. Moles, K. J. Blow, M. A. Moore, G. D. l Boyer, G. D. Morrill, T. S. Burchart, G. D. Neises, G. J. Conely, T. A. Norton, W. B. Dingler, M. E. Pippin, J. M. l Eales Jr., W. G. Schmotzer, E. W. I Flannigan, R. D. Sims, R. L. Garrett, T. J. Weatherford, T, M. Gerrelts, D. E. Weeks, J. D. Ilarvey, K. M. Williams, M. G. Iloadicy, N. W. Younie, C. R. Larson, M. S. Replies were not received from the following individuals: Boyer, G. D. Hoadley, N. W. Eales Jr., W. G. Pippin, J. M. Gerrelts, D. E. Weeks, J. D. Comments made?: X Yes No Comments made by: Daniel Williamson Environmental Met 4609 Print Name Department Extension Comments resolved by: Whff - =# Environmental Met 4609 Prmt Name Department Extemion

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                                                                                )           /

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OfTsite Dose Calculation Manual h) TJ Please perform for: O verification a walkdown O Compliance verification Matrix

  \                             O Validation            O Cross-Disciplinary Review                       g Other (Division Manager /PSRC J                                                                                                       Member) i (T

Pleasespero completed Comment Control Form.co: Den w8P'- - =. . hv6- - dMat. 4609 Q619 96 Print Name Department Extemion Date due No. - Comment number M = Mandatory G = General Step = Procedure step number COMMENTS RESOLUTION No.& Step & description No. M/G l l 1 i l l RECEIVED JUN 141996 M. G. Williams Comments made?; Yes Comments made by: Merlin Williams PrintName

                                                                                              #5e  Department ExteElon Commente resolved by:

Print Name Department Extension

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                   ,                                            COMMENT CONTROL FORM
                                               /                                                      DRR#______              OTSC#: 96-0667 O               Route to:.- C. R. YoumerffD-OP)

O Document Number: AP 07B-003 Revision Number:J IT

   \               Document

Title:

Offsite Dose Calculation Manual M 11 Please perform for: O venfication a walkdown a Compliance verification Matrix

\ O validation O Cross-Disciplinary Review gg Other(Division Manager /PSRC l

   .0                                                                                                                       Member) 0" I

Please return completed Comment Control Form to: q Dan Williame.on Environmental Mat. 4609 06-19-96 !. Print Name Department Extension Date due j No. = Comment number M = Mandatory G = General Sten = Procedure step number COMMENTS RESOLUTION

No.& Step & desenption No. l j M/G l ! l I< l ' i : 3 1 i i 2 d i 1 i 4 i Comments made?: Yes

                                                                                   % No

Comments made by: .M. bbar(I 06 N3 /

Print Name Department Extension Comments resolved by: Print Name Department Estension i i I i 4 0

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ON THE SPOT CHANGE (OTSC) OTSc #:c_. h- O(,0 9 tri Document Number: AP 07B-003 Current Revision Number: 0 0 Document

Title:

Ofreie, Dose calculation Manual O Originator: Teresa L Rawlin" 04-29-96 U1 PrintName Date

   \    Reason For Change: (Erplain) His procedure is being revised to incorporate the gardens to be sampled for the Radiological Environmental Monitoring Program. Location A-3 is being added, and location C-1 is being deleted. Thejustification for the 0"    changes is in the 1995 Land Use Census. He pages to be revised are 79 and 90 (Table 5-1 and Figure 5.4). Additionally, editorial N   changes were made to pages 74,75,80,81 and 102.
  .D (F                                                                                                               O Continued on attached OTSC SCREENING (A YES anrwer to any ofthefollowing questions indicates an OTSC cannot be performed.)

1. Is this a change to the intent of the procedure as defined in the purpose or scope? O YES S NO

2. Will this change decrease or modify a hold point requirement or Quality inspection point? O YES S NO

3. Will the change result in a reduction of personnel or equipment safety? O YES g NO

4. WllI the change involve a USQD1 (Must perform a screening to determine) O YES g NO g A marked up copy of the proposed change is attached, g Regulatory Screenings and/or Evaluations (APF 26A 003-1) has been completed and attached as required by AP 26A-003, SCREENING AND EVALUATING CHANGES, TESTS, AND EXPERIMENTS.

APPROVAL FOR IMMEDIATE USE Approved By: " g/1/g f -- C CP nly) e _ infnt(f Approved By: p , , HGS # )/

                                       'CNOC StafMember*                                   Print Name                     Date Approved By:                  O'*P                                             N--% b b                           /     /
                                  / fntSupervisor*                              '

Q PriIstName Date

For Operations Dghartment procedures, one must hold a Senior Reactor Operator license per TS 6.8.3.

The remainder of this form shall be completed within 14 days as required by Technical Specification 6.8.3. QUALIFIED REVIEW i Cross-Disciplinary Review Required By: O NONE REQUIRED

       % Quality Evaluations              O QualityControl                O Surveillance Coordinator             O Other(Specify)

All cross-disciplinary reviews have been completed, reviewer comments have been resolved, and the recommended disposition of this OTSC has be identified in he FINAL APPROVAL section of this fo f b 4" $//VIf4 hualipedReviewer Print Name Date FINAL APPROVAL D Approved: O Disapproved. cancel, remove from OTSC file, and initiate PIR M Maintain in active OTSC file until incorporated into future revision. Incorporated by DRR number: l or OTSC number: f O Maintain in active OTSC file until specified date / / / (this sectionfor Admmistrative Control Procedures O . Approved O Disapprov P C Meeting No: Ts .5 /15 /h 0 PSRC Chairmanfitials) Date US f t%sm / V/lb I 9b

                        ~ Vice-fresident Plansbperatiohi                                                                         Date M            kb                                                                       [ k/k Respontale AfaQe%rr all 07SC except ACP's)                                                            Date
                                                                                                              @2 Elb- 94

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3, , rua % 01 0 9 Ir Rsvision: 0 OFFSITE DOSE CALCULATION MANUAL O AP 07B-003 m Reference Use Gd7

O lPage 74 of 188 O EE A m (Page 70 of 184) l g OFFSITE DOSE CALCULATION MANUAL 5.2 L=nd Use cannum l 0- ;

2 A Land Use Census shall be conducted annually during the growing

r season to identify the nearest (1) milk animal, (2) residence, i

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. 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 location from which samples are currently being obtained, the new location (s) shall be added to the Radiological ,

Environmental Monitoring Program within 30 days as described in l Table 5-1, Note (1). The indicator sampling location (s) having the lowest calculated dose or dose commitment may then be deleted from the monitoring program. The revision to Table 5-1 and the corresponding Figure (s) as a result of such

substitutions shall be decumented in accordance with Section 6.14 of the Wolf Creek Technical Specifications. The results of the Land Use Census shall be included in the Annual Radiological Environmental Operating Report described in Section 7.1. 5.3 M erlaboratorv C - arison Proaram The analysis laboratory contracted to analyze samples from the Radiological Environmental Monitoring Program participates in the EPA Laboratory Intercomparison Program or similar program. 12/95

Broad leaf vegetation sampling of available vegetation may be performed at the site boundary in each of two different direction sectors with the highest predicted D/Qs in lieu of the garden census. Specifications for broad leaf vegetation sampling in Table 5-1, Part 4.c. shall be followed, including analysis of control samples. 3/92

H 3 . cer v - %-OMQ .y Revision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 g c) Reference Use OE3 Page 75 of 188 O O ATTACHMENT A (Page 71 of 184) OFFSITE DOSE CALCULATION MANUAL i T A summary of intercomparison res'ults shall be included in the Annual Radiological Environmental Operating Report described in Section 7.1. 5.4 Ranorting Raouir===nts I 5.4.1 Annual Radioloalcal Environ ==ntal Onaratina Renort To meet the requirements of Wolf Creek Technical Specification 6.9.1.6, the Annual Radiological Environmental Operating Report { covering the previous year of operation shall be submitted to ' the NRC by May 1 of each year. The content of this report is described in Section 7.1. 11/94 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 l 1 l 1

H 3-em. %- Obo9 .y Revision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 D m Reference Use NES Page 79 of 188 O O ATTACHMENT A tn (Page 75 of 184) g OFFSITE DOSE CALCULATION MANUAL

T TABLE 5-1 (Continued) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

9 Firnonure Pathway / Numher of Samnies and Samnle Collection Tyne and Preauency 7 Samnie Tvne Samnle Locations (1) Precruency of Analvain

4. INGESTION Samples of available Monthly when Gamma isotopic (CONT.) broadleaf vegetation from available (9) analysis (3) on Food Products two indicator locations edible portions, with highest calculated annual average D/Q (Loca-tions A-3 and R-1 and alternate Location G-1 on Figure S.4); sample of similar broadleaf vegeta-tion from a control loca-tion greater than 10 miles from the site in a low D/Q section (Location S-4 on 4/ss 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 down-stream 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).

H I 3, ' St%C. %.ObOS

 . IP      Ravision: 0             OFFSITE DOSE CALCULATION MANUAL o                                                                         AP 07B-003 A      Reference Use                                    5o%           Page 80 of 188 O

O ATTACHMENT A m (Page 76 of 184) OFFSITE DOSE CALCULATION MANUAL I TABLE 5-1 (Continued)

TABLE NOTATIONS

.D

g. (1) Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment, and other legitimate reasons. If specimens are unobtainable due to sampling equipment malfunction, every effort shall be made to complete corrective action prior to the end of the next sampling period. All deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report described in Section 7.1.

It is recognized that, at times, it may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time. In these instances, suitable specific alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days. Revisions to this Table and to the corresponding Figure (s) as a result of such substitutions shall be. documented in accordance with Section 6.14 of Wolf Creek Technical Specifications. This documentation shall provide information identifying the cause of the unavailability of samples for that pathway and justifying the selection of the new location (s) for obtaining samples. (2) Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours or more after sampling to allow for RN-220 and l 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. 1 (4) One or more instruments, such as a pressurized ion chamber, for ! measuring and recording dose rate continuously may be used in place i 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 chall not be used as dosimeters for t measuring direct radiation. The 40 stations are not an absolute number. The number of direct radiation monitoring stations may be reduced according to geographical limitations, e.g., some sectors are over water so that the number of dosimeters may be reduced accordingly.. The frequency or analysis or readout for the TLD system depends upon the characteristics of the specific system used and is selected to obtain optimum dose information with minimal fading. 5/96 1

n*TSC., %bOMi .y Revision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 O m Reference Use BEE page 81 of 188 O ATTACHMENT A (Page 77 of'184) y OFFSITE DOSE CALCULATION MANUAL F TABLE 5-1 (Continued) TABLE NOTATIONS

I (5) The

upstream" sample is taken at a distance beyond significant influence of the discharge.

(6) Ground water samples shall be taken when this source is tapped for 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 order 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. i (9) Milk and broadleaf vegetation samples are often temporarily, but not ' permanently, unavailable at the scheduled saa,le collection times. Alternate sampling locations may therefore be listed in the Table and used at these times to provide continued monitoring of these pathways. If samples are considered permanently unavailable at a location, another location will be selected (if available) as described in Note (1). (10) If harvest occurs more than once a year, sampling shall be performed during each discrete harvest. If harvest occurs continuously, sampling shall be monthly. Attention shall be paid to including samples of tuberous and root food products. (11) The purpose of this sample is to obtain background information. If it is not practical to establish contro. locations in accordance with the distance and wind direction criteria, other sites that provide valid background data may be substituted. 3/92 j

7

       '                                                                      6t% QL- OboQ Revision: 0             OFFSITE DOSE CALCULATION                   AL               AP 078-003 g       Reference Use                                                                 Page 90 of 188 O                                                 ATTACHMENT A (page 86 of 184)

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INGESTION PATHWAY SAMPLING LOCATIONS A= FISH (JRR) 15 -FOOD PRODUCTS D = FISH (WCCL) 4/96

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  .y     Revision: 0            OFFSITE DOSE CALCULATION MANUAL          Ap 07B-003 m

O Reference Use TES Page 102 of 188 O O ATTACHMENT A (Page 98 of 184) OFFSITE DOSE CALCUL$ TION MANUAL r [. 7.0 Reports

j 7.1 Annumi Radioloalcal Environ ==ntal Onarat4nn Renort o' The Annual Radiological Environmental Operating Report shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, with operational controls and with previous environmental surveillance reports, and an assessment of the observed impacts of the plant operation on the environment. The reports shall also include the results of the Land Use Census described in Section 5.2. The Annual Radiological Environmental Operating Report shall include the results of analysis of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in Table 5-1 as well as summarized and tabulated

.               results of these analyses and measurements in the format of the       :

i table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual

results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.

l The report shall also include the following: a summary description of the Radiological Environmental Monitoring Program; legible maps covering all sampling locations keyed to a table giving distances and directions from the centerline of the reactor; the results of licensee participation in the Interlaboratory Comparison Program and the corrective actions j being taken if the specified program is not being performed as required by Section 5.3; reasons for not conducting the { Radiological Environmental Program as required by Section 5.1 ) with plans for preventing a recurrence and discussion of all l deviations from the sampling schedule of Table 5-1; discussion l of environmental sample measurement's that exceed the reportin'g levels of Table 5-4 but are not the result of plant effluents, and discussions of all analyses in which the LLD required by Table 5-3 was not achieved. 5/96

H 1

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APF 26A 003 01. Riv.1 0 1rf. C K ,- & 0 9 m REGULATORY SCREENING NO. 59 o USOD rev. Document Number: AP 078-003 Revision: O Page 1 of 4 O Vi

\                                                                                                                 '

Description of Proposed Change: This procedure is being revised to incorporate the gardens to be sampled for the Radiological Environmental Monitoring Program. Location A-3 is being added, and location C-1 is (3 being deleted. Thejustification for the changes is in the 1995 La J Use Census. The pages to be revised nm 79 and 90 (Table 5-1 and Figum 5.4). Additionally, editorial changs were made to pages 74,75,80,81 and 102. cr Screening Questions: (Note: All questions must be answered except as provided in questions 1 and 2, all evaluations shall be completed using forms APF 26A-003-02 and APF 26A-003-03 as appropriate.)

1. Has this change been previously 0 YES No further screening is required.

approved for WCNOC by the NRC or Document # covered by another Unreviewed Safety Justify in " Clarification" Section. question Determination (APF 26A-003- 0 NO

03) See Note Below.

NOTE: If referencing a previously performed USQD: a) contact Licensing to update USQD log, b) review to ensure USDQ meets current procedural standards and expectations (Reference step 6.5 of procedure AP 26A-003), c) ensure that it has been approved by the PSRC prior to implementing the change, and d) ensure no interim changes have been implemented which could affect the proposed change or conclusions of the screening or evaluations.

2. Would the change result in a revision O YES Change may NOT be implemented prior to I to the Operating License including approval of a Ucense Amendment (NOTE: !

Appendices? (This includes the No further screening is required since Technical Specifications) NRC approval must be obtained prior to l implementing the change.) 8 NO

3. Identify the sections of the Updated Safety Analysis Report (including the Emergency Plan and Security Plans) which are related to or may be affected by the change. Identify the review by Chapter, Section, page or Figure (Reference the revision of the page if page number is used). It is <

important in this review to go beyond direct affects of a change and to document those sections. Reviewed Reviewed and Affected 9.5.1 13.2.1.2 Chapter 17

3 -1 ,

     * [ APF 26A-003-01. Rev.1                                                              OW 96 0(o09 l      m                                         REGULATORY SCREENING                               NO. 59

) .o USQD rev.

Document Number: AP 078-003 Revision: O Page 2 of 4

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4. Could the change potentially result in a revision to:

) (r

       \  a. The Physical Security Plan, l

j [ b c The The Safeguards Contingency Security Training Plan,Plan? and Qualification or i O Yes if Yes an evaluation must be E No j completed in accordance with 10 CFR 50.54(p) prior to implementing

the change. This evaluation must

! be approved by the Superintendent j Security or the Manager Design ! Engineering if yes to this question, the proposed change may also require evaluation under 10 CFR 50.59 I (question 11 on this form) (Security documents are safeguards documents. If unsure of the i j affect of the proposed change, contact Security or Engineering.) I i 4

5. Could the change potentially result in a revision to the Operating Quality Assurance Program i described in Chapter 17 of the USAR. If Chapter 17 of the USAR was identified as affected in i

section 3 of this form, this block must be checked yes. I i O Yes if yes, an evaluation must be E No l approved in accordance with 3 10 CFR 50.54(a)(3) by the j Manager Performance Assessment if yes to this question, the proposed change may also require evaluation under 10 CFR 50.59 (question 11 on this form).

6. Could the change potentially result in a revision to the Fire Protection Program described in USAR Section 9.5.1and 9.5 Appendices? If Chapter 9.5.1 or 9.5 Appendices of the USAR were identified as affected in section 3 of this form, this block must be checked yes.

O Yes if yes, an evaluation must be a No approved in accordance with license NPF-42 paragraph l 2.c(5) by the Superintendent Resource Protection or an ' Engineering Manager. If yes to this question, the proposed change may also require evaluation under 10 CFR 50.59 (question 11 on this form).

!   3           -

7 APF 26A-003-01. RIv.1 cTtsc %-t% M , m REGULATORY SCREENING NO. 59 I i o USQD rev. j Document Number: AP 078-003 a a Revision: O Page 3 of 4 j in

    }  7. Could the change potentially result in a revision to the Radiological Emergency Response Plan?

o- O Yes if yes, an evaluation must be approved B No l 3 \ in accordance with 10 CFR 50.54(q) by D l the Manager Emergency Planning prior C !t to implementation of the change. if yes to this question, the proposed change may also require evaluation under 10 CFR 50.59

(question 11 on this form).

j

8. Could the change potentially result in a revision to the Licensed Operator Re-qualification Program l as described in USAR Section 13.2.1.2? If Chapter 13.2.1.2 of the USAR was identified as l i affected in section 3 of this form, this block must be checked yes. l 1 O Yes if yes, an evaluation must be approved B No .

in accordance with 10 CFR 50.54 l l (1-1) by the Manager Training. l If yes to this question, the proposed change may also require evaluation under 10 CFR 50.59

(question 11 on this form).

l 9. Could the change potentially result in a change to an NRC commitment?. t j O Yes if yes, an evaluation - must be E No , coordinated by the Supervisor j Regulatory Compliance.

10. Does the proposed change involve one or more of the following:

a. A change in the rate, volume, concentration, composition or flow path of nonradiological

liquid or gaseous effluents?

I

b. A change in the volume, concentration or composition of nonradiological solid waste?

4

c. An increase in the thermal power above the current licensed level and/or an alteration in
the magr: itudes of thermally affected effluents? l; d. A physical change in area outside of the owner controlled area boundary which was not l
disturbed by previous construction?: e. The addition of a new storage tank, or physical changes to the piping or capacity of an existing tank, that contains more than 660 gallons of chemical l O Yes if yes, an environmental impact 8 No 2 determination must be approved by l

the Superintendent Resource ; Protection.

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$                                         REGULATORY SCREENING                               NO. 59 o                                                                                            USQD rev.

Document Number: AP 07B-003 Revision: 0 Page 4 of 4 o tn

\
   ' NOTE: For purposes of this question the Emergency Plan and Security Plans are considered part of g       the USAR.
\

2 11. Would the change involve one or more of the following: r a. a change to the plant structures, systems, components or equipment as outlined, summarized or described in the USAR such that accomplishment of the change could directly or indirectly make information in the USAR no longer true, complete or accurate, or would violate a requirement stated in the USAR?

b. a change to procedures or administrative controls as outlined, summarized , or described in the USAR such that accomplishment of the change could make information in the USAR no longer true, complete or accurate, or would violate requirement stated in the USAR?

c. Tests or experiments NOT described in the USAR?

O Yes A formal Unreviewed Safety Question E! No Determination using APF 26A-003-03 must be completed prior to implementing the change. Reminder: If es, evaluate need for a USAR Change Request in accordance with AP26B-003 Ca . ed that step 11.a convey a broad and conservative interpretation of 10 CFR 50.59 as described in NSAC-125. An unreviewed safety question determination is required if the proposed change could alter the description of any SSC or equipment described in the USAR. This applies to the specific SSC being changed as well as any other equipment that could be affected directly or indirectly.

12. Clarification:

Prepared by: g gJ Date: gg,g Approved by: g Date: f,.f 4/[j

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  \                                            O validation                     gCross-Disciplinary Review                     O Other D

7 Please return completed Comment Control Form to: .*- l Damon L. Stone Chemistry 5-13-% ' &JJ7 Print Name Department Extension Date due l No. = Comment number M = Mandatory G = General Step = Procedure step n'.imber COMMENTS RESOLUTION No. & Step & desenption No. M/G l Comments made?: O ves @ "o Comments made by: 41?+ Print Nar;{e r ___ _ [ Department

                                                                                                                                             .. h[

Extension Comments resolved by:

      )                                                              Print Name                                          Department            Extension l

i 1 l l

H , j 3- , Nam Apr ise-ooc-es nav os 4 o COMMENT CONTROL FORM pg DRR # ._., - OTSC#: %-0609 p MQSM AbVMY~\ MckY-3 o Document Number AP 07B 003 Revision Number: 0 1 U1

g Document

Title:

OFFalTE DOSE CALCULATION AMNUAL 4 j g- Please perform for: O venfication a walkdown O Compliance verification Matrix

N O validation pross-Disciplinary Review O Other a

r Please return completed Gomment Control Form to:

                                                                    -~~-.~.,.

Chemistry 4527 (~).~Ma=a= A-- ,,,L. Stone

                                  ;,,,,       - - ~- - ~~~~~DepwtmeM'                                       Extension 5-13-%

Date due No. = Comment ni.i.As M = Mandatory G = General Step = Procedure step number COMMENTS RESOLUTION No.& Step & description No. M/G Comments made?: O ves @ No Comments made by: ..... PrintName

                                                                               /A    #w Department
                                                                                                                                              .bExzension Comments resolved by:

Print Name Department Extension i l i I

l sFoRM APF 15e-004-02 REV 03 N[g COMMENT CONTROL FORM l DRR # _ _ _ _ _ _ OTSC#: 96-0609 o Route to: ,j]}}RC 4' ALDW AD- tJ/ O Document Number:AP 07B-003 Revision Number: 0 (G

          \      Document

Title:

OFFSITE DOSE CALCULATION MANUAL 0- Please perform for: O verification O walkdowr. O Compliance venfication Matrix

         \                          O validation             pross-Disciplinary Review                a other
        .D 0-Aeturg]leted Comment Control Form to-                                                                                  l Damon L Stone      )                  ('hemistry                          4527
            ]           Print Namf                             Department                    Extension 5-13-96 Date due Mo'mment number              M = Mandatory       G = General     Step = Procedure step number                          :

COMMENTS RES9LUTION No. & Step & desenption No. M/G I l l l l l l l l l Comments made?: Yes No Comments made by: b IM __ O 13 -- _Y4 '7/ Print Name Depbrtment Exterision Comments resolved by: Print Name Department Extension I

H 3 PhRM APF 15C 004-02 REV 03 'I. o COMMENT CONTROL FORM gy DRR # _ _ _ _ _ _ OTSC#: 96-0609 p Route to:___0 BAD #ff rD</ 68 -EAM c Document Nunberg 078-003 Revision Number. O tn Document

Title:

OFFSrm DOSE CALCULATION MANUAL

g. Please perform for: O Venfication O Walkdown O Compliance verification Matnx x, O Validation Ji3' Cross-Disciplinary Review O Other D

g- Please retum completed Comment Control Form to: Damon L Stone Chemistry 4527 5-13 96 Print Name Department Extension Date due No. = Comment number M = Mandatory G = General Step = Procedure step number COMMENTS RESOLUTION No.& Step & desenption No. I M/G l Comments made?: Yes No Conunents made by: 9c.caee, L . DEMTo^/ _____G C __B_o 3 6 Print Name Department Ertension Comments resolved by: Print Name Department Extension

H 3 soam att 1sc.ooe.o Aav os '- f. O COMMENT CONTROL FORM R DRR # _ _ _ _ _ _ OTSC#: 96-0609 Route to:___.fdf, Ji/EA 7 N ZA R W D dd-AES O Document Number:AP 078-n03 Revision Number. O m Document

Title:

OFFSITE DOSE CALCULATION MANUAL \ ~. Please perform for: O vmfication O walkdown O Compliance verification Matrix 0 validation $ross-Disciplinary Review O Other n p Please return completed Comment Control Form to: Damon L. Stone Chemistry 4527 5 13- % Print Name Department Extension Date due No. = Comment number M = Mandatory G = General Step = Procedure step number COMMENTS RESOLUTION No.& Step & description No. M/G l Comments made?: Yes No Comments made by-l Print Name Department Extension l Comments resolved by: Print Name Department Extenston

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, f F6R38 AFF 15e-004-02 REV 03 l F ! O COMMENT CONTROL FORM

g DRR # _ _ _ _ _ _ OTSC#: %-0609

) n Route to: __ fetRV GMAE1i - fA-MS i l O Document Number AP 07B-003 Revision Number: 0 I in g Document Titic;OFFSITE DOSE CALCULATION MANUAL

Please perfonn for: O venfication 0 O walkdown O Compliance venfication Matrix s O Validation pi[ Cross-Disciplinary Review O Other f ,n,

           ,,     M<* return compjeted         mment Control Form to:

s l h- Daman L. Stone Chemistry 4527 5-13-96 i Prin%e Dc artment Extension Date due

Ngmment number M = Mandatory G = General Step = Procedure step number j COMMENTS RESOLUTION
No.& Step & desenption No.

M/G 1 4 I 1 l l 5 l 3 i l l ) e. i 4 ] 4

                                                                             -    A Comments made?:
                                               ] Yes                        ] No Comments made by:                    ____9a                tt                             ____f,ur dervi               _fDf_V PrQ'ame                                             DSartmens)            Extension Comments resolved by:

Print Name Department Extension I

OEM APF 15e 004-02 REV 03 COMMENT CONTROL FORM U DRR # _ _ _ _ _ _ _ OTSC#: 96-0609 Route to:__/E S />74 cryt/ &gc Document NumberAP 07B-003 Revision Number 0 Document

Title:

OFFSITE DOSE CALCULATION MANUAL ~

 . Please perform for: O venfication                         o walkdown                        a Compliance venfication Marnx 0 validation             gCross-Disciplinary Review                     0 Other Please return completed Comment Control Form to:
                                                                      '[

A4) , M<y [,h . Damon L. Stone Chemistry 4527 512-pf Print Name Depart'hrent Extension _ Date due No. = Comment number M = Mandatory G = General Step = Procedure step number COMMENTS RESOLUTION No.& Step & desenption No. AUG Comments made?: Yes

                                                    $No Comments made by:                be-rk b t-s a,                               _ha. $er.hi.c3               __?I3T Prmt Name                                     Department           Extension Comments resolved by:

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' U' DRR # _ _ _ __ OTSC#: 2p6-0609 g Route to:_.,g($V.ZW /MGCES 46--5S D cument Nuanber:AP 07B-003 Revision Number: 0 O Document

Title:

OFFSITE DOSE CALCULATION MANUAL

Please perfonn for: O verification O walkdown a Compliance verification Matrix 0 validation @ss-Disciplinary Review O Other i

 .D 7      Please return completed Comment Control Form to:                                                                               !

Damon L. Stone Chemistry 4527 5-13-% Print Name Department Extension Date due No. = Comment number M = Mandatory G = General Step = Procedure step number COMMENTS RESOLUTION No.& Step & desenption No. M/G I l 1

i Conunents made?: Yes

                                                          @ No Comments made by:             _ _ _ _ _ _  o Cf60 b/b4R        "
                                                                                 ,         /8                 _____ 80 /0 Prin6'ame                             Department             Extension Comments resolved by:

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s ~

Sd '. mm Apr 1sc oc4-02 arv os o COMMENT CONTROL FORM A , DRR # _ _ _ _ __ _ _ _ OTSC#: 96-0609 o Route to:_ .[ftJA46) i FLAA/A/769A/ d h Alf

O Document Number:AP 07B-003 Revision Number: 0 in g Document

Title:

OFFSITE DOSE CALCULATION MANUAL h Please perform for: O venfication O walkdown O Compliance verification Matnx \ O Validation g Cross-Disciplinary Review O Other E <r Please return coWC6NtmeneContrgQorm to;s 1 Damon L. Stene Chemis 4527 S 13-96 Print Name Department h Ertension Date due s~' No. = Comment number M = Mandatory G = Gene 6- Step = Procedure step number

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                              -.-.{OMIMNTS ~ ~                                                      RESOLUTION No.&                        Step & desenption                        No.

M/G 1 1 l Comments made?: Yes No Comments made by: _ YdMul9 N NE _ woo

                                             ' Print Name Q                               Department            Ext'ension Comments resolved by:

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_!axAprisc-ooc-o2 azy os COMMENT CONTROL FORM e DRR # _ _ _ _ _.. OTSC#: 96-0609 v Route to:____7ft#1/ MIDg2IL/ AA-A h C Document Number:AP 07B-003 Revision Number 0

'n Document

Title:

OFFSITE DOSE CALCULATION MANUAL (T Please perform for: O venfication a walkdown O Compliance venfication Matrix

\.                        O validation            gross-Disciplinary Review                O Other
.D 7    Please return completed Comment Control Form to:

Damon L. Stone Chemistry 4527 5 13-96 Print Name Department Extension Date due No. = Comment number M = Mandatory G = General Step = Procedure step number COMMENTS RESOLUTION No.& Step & description No. M/G l Comments made?: Yes N No Comments made by: __ _ T8 No & ! fb bd __h 707 l Print Name department Extension 1 Comments resolved by: i Print Name Department Extension

5-t #

                                                                                           ,,                             . macr-
   ,]   ,'ronx Apr 15c-004-04 REV 07 PCg3 1 cf I

ON THE SPOT CHANGE (OTSC) OTSCu:%f80l Document Number: AP 07B-003 Current Revision Number: _Q Document

Title:

Offsite Dose calculation Manual Originator: Teresa L Rawlings 11-18-96 Print Name Date s Reason For Change:(Erplain) This procedure is being revised to incorporate the gardens to be sampled for the Radiological [ Environmental Monitoring Program. Location A-3 is being deleted, and location F-1 is being added. Thejustification for the change is in the 1996 Land Use Census Report. The pages to be revised are 79 and 90 (Table 5-1 and Figure 5.4).

O Continued on attached g OTSC SCREENING (A YES answer to any ofthefollowing questions indicates an 075C cannot be performed)

1. Is this a change to the intent of the procedure as deimed in the purpose or scope?

O YES S NO

2. Will this change decrease or modify a hold point requirement or Quality inspection point? O YES S NO

3. Will the change result in a reduction of personnel or equipment safety?

4. Will the change involve a USQD7 (Mustperform a screening to determine)

O YES S NO D YES g NO g A marked up copy of the proposed change is attached. O Regulatory Screenings and/or Evaluations (APF 26A-003-1) has been completed and attached as required by AP 26A-003, SCREENING AND EVALUAT!NG CHANGES, TESTS, AND EXPERIMENTS. APPROVAL FOR IMMEDIATE USE Approved By: CallSuperintendent (for ACPs only)

                                                                                /2-Date/ h /h Approved By:                  4                                           aA                         d o< N        / 2-/_[gf WCNOCStafMember*                                      Print Name                     Date Approved By:                    6m              ^_)                            QtW                 )               /ch f/

I

                                      / Cchnizant Supervisor

l Print Name Date
For Operation (Department procedures, one must hold a Senior Reactor Operator license per TS 6.8.3.

The remainder of this form aball be completed within 14 days as required by Technical Specification 6.8.3. QUALIFIED REVIEWp PSRf. MwL.s:Op Cross-Disciplinary Review Required By: O NONE REQUIRED / O Quality Evaluations (QPCVM Documents) g Quality Control O Surveillance Coordinator s Oth6(Specify) (Form APF 15C-004-08) p PSRC review required.' O PSRC review and Plant Manager approval not required.

                                                    * (Mandatoryfor all OTSC's to Administrative ControlProcedures)

All cross- 'pli ar) evi< ws ve been completed, reviewer comments have been resolved, and the recommended disposition of this OTSC has & n entiied nt ie FINAL APPROVAL section of this fo

                                      ' k       
                                                                                                     . eC9 %              \ *L i O /%

QuahphiReviewer ' Print N2the Date FINAL APPROVAL

          $ Approved:                                                   O Disapproved, cancel, remove from OTSC file, and initiate PIR p Maintain in active OTSC file until incorporated into future revision.                   Incorporated by DRR number:

or OTSC number: O Maintain in active OTSC file until specified date / / (nis section or Administrative Controllydures Only) q f Di( Approved O Disapproved PSRC Meeti .g No: 'NR W J_f_ ,/ PSR$U irman (Initials) Date

                                                    " Plantblahager ie                                                                b h/

_) Date Responsibth Afa&r (For all 075C except ACP 's) OC12 12. m .cw M/ [/ h Date

w ~. .. t

 .s. -                                                                  crst w o9ol              %

3 Revision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 C 7 Reference Use page 79 of 188 C ATTACHMENT A 7 hs (Page 75 of 184)

   \                              OFFSITE DOSE CALCULATION MANUAL TABLE 5-1 (Continued) l                            RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
  \

l Fvnnmure pathway / Number of Emmnlem and f wnle Collection Tyne and Praana n N O' A=="la Tvee Sansia Locatinna fil Fra mia n c-v of Analvain

4. INGESTION Samples of available Monthly when Gamma isotopic (CONT.) broadleaf vegetation from available (9) analysis (3) on Food Products two indicator locations edible portions.

with highest calculated annual average D/0 (Loca-tions G-1 and R-1 and a' M rnate Location F-1 on F. re 5.4); sample of a lar broadleaf vegeta-tion from a control loca-tion greater than 10 miles from the site in a low D/0 section (Location S-4 on 22/ss Figure 5.5) . (11) Food Products Sanple of crops irrigated At time of harvest Gamma isotopic with water from thy Neosho (10) analysis (3) on River down-stream 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).

OtSc %-096l (bs Ravicion: 0 OFFSITE DOSE CALCULATIO.N MANUAL AP 07B-003 d Reference Use Page 90 of 188 O ATTACHMENT A { (Page 86 of 184) g OFFSITE DOSE CALCULATION MANUAL

 }                                               FIGURE 5.4
  \
 .c s   (A       i    \   J
                                  \   "jfN           -

Bg {

                   !        oWO                                   X c.

I' o O &( r%d b o ' P

                            ;gg "py{/ /( f\

p e4N x (~ 4-

4" y# Vd' L[ d E _ sC ms

                                  \/          L jw )

A f Tj y? # F[ _rggy yp ngx < r h ki' it A+Mi

                                  .xq'#T_3 n d          VT        \  ll INGESTION PATHWAY SAMPLING LOCATIONS A-    FISH (JRR)     5 -FOOD PRODUCTS h5 - FISH (WCCL) 11/96

I w ' 1 ' l [ APF 26A-003-01, R:v.1 OTGC %-O90l m REGULATORY SCREENING NO. 59 o USQD rev. Document Number: AP 078-003 Revision: 0 Page 1 of 4 0

    \  Description of Proposed Change: This ,~9cedure is being revised to incorporate the gardens to be
   ~

l , simpled for the Radiological Environmemi Monitoring Program. Location A-3 is being deleted, and l g location F-1 is being added. The justification for the change is in the 1996 Land Use Census Report. 2, The pages to be revised are 79 and 90 (Table 5-1 and Figure 5.4).

   <r Screening Questions: (Note: All questions must be answered except as provided in questions 1 and 2, all svaluations shall be completed using forms APF 26A-003-02 and APF 26A-003-03 as appropriate.)

1. Has this change been previously 0 YES No further screening is required.

approved for WCNOC by the NRC or Document # covered by another Unreviewed Safety Justify in " Clarification" Section. question Determination (APF 26A-003- a NO

03) See Note Below.

NOTE: If referencing a previously performed USQD: a) contact Licensing to update USQD log, b) review to ensure USDQ meets current procedural standards and expectations (Reference step 6.5 of procedure AP 26A-003), c) ensure that it has been approved by the PSRC prior to implementing the change, and d) ensure no interim changes have been implemented which could affect the proposed change or conclusions of the screening or evaluations. 1

2. Would the change result in a revision O YES Change may NOT be implemented prior to to the Operating License including approval of a License Amendment (NOTE:

No further screening is required since Appendices? (This includes the NRC approval must be obtained prior to : Technical Specifications) implementing the change.) g NO -' j 1 l 1

3. Identify the sections of the Updated Safety Analysis Report (including the Emergency Plan and Security Plans) which are related to or may be affected by the change. Identify the review by Chapter, Section, page or Figure (Reference the revision of the page if page number is used). It is important in this review to go beyond direct affects of a change and to document those sections.

Reviewed Reviewed and Affected 9.5.1 l 13.2.1.2 i Chapter 17

i H . l l,1$ 'APF 26A-003-01, Rev.1 OTS C. %-O 101 , m REGULATORY SCREENING NO. 59 4 o USQD rev. Document Number: AP 078-003 Revision: 0 Page 2 of 4 M i \

4. Could the change potentially result in a revision to: j D

     \ c. The Physical Security Plan, 3 b. The Safeguards Contingency Plan, or                                     '

! c. The Security Training and Qualification Plan? l D Yes if Yes an evaluation must be E No

completed in accordance with 10 l

CFR 50.54(p) prior to implementing

the change. This evaluation must
be approved by the Superintendent i Security or the Manager Design Engineering 1

! If yes to this question, the proposed change may also require evaluation under 10 CFR 50.59 l (question 11 on this form). (Security documents are safeguards documents, if unsure of the i affect of the proposed change, contact Security or Engineering.) ) 5. Could the change potentially result in a revision to the Operating Quality Assurance Program l described in Chapter 17 of the USAR. If Chapter 17 of the USAR was identified as affected in j section 3 of this form, this block must be checked yes.

O Yes if yes, an evaluation must be E No approved in accordance with 10 CFR 50.54(a)(3) by the Manager Performance Assessment j If yes to this question, the proposed change may also require evaluation under 10 CFR 50.59 (question 11 on this form). !

6. Could the change potentially result in a revision to the Fire Protection Program described in USAR l Section 9.5.1and 9.5 Appendices? If Chapter 9.5.1 or 9.5 Appendices of the USAR were identified as affected in section 3 of this form, this block must be checked yes.

O Yes if yes, an evaluation must be B No ! approved in accordance with license NPF-42 paragraph 2.c(5) by the Superintendent Resource Protection or an Engineering Manager, if yes to this question, the proposed change may also require evaluation under 10 CFR 50.59 (question 11 on this form).

<     H      *
     ,1, kPF 26A-003-01, Rev.1                                                                          OTSC do-09OI j      $

, m REGULATORY SCREENING NO. 59 l c USQD rev.

Document Number: AP 07B-003 Revision: 0 Page 3 of 4

! M f)A j

7. Could the change potentially result in a revision to the Radiological Emergency Response Plan?

O Yes if yes, an evaluation must be approved B No

\ in accordance with 10 CFR 50.54(q) by 3 the Manager Emergency Planning prior i

to implementation of the change.

if yes to this question, the proposed change may also require evaluation under 10 CFR 50.59
(question 11 on this form).

J

8. Could the change potentially result in a revision to the Licensed Operator Re-qualification Program as described in USAR Section 13.2.1.27 If Chapter 13.2.1.2 of the USAR was identified as j affected in section 3 of this form, this block must be checked yes, i O Yes if yes, an evaluation must be approved 2 No j in accordance with 10 CFR 50.54 l (1-1) by the Manager Training.

i If yes to this question, the proposed change may also require evaluation under 10 CFR 50.59 i (question 11 on this form). 1 ) ) 9. Could the change potentially result in a change to an NRC commitment?. O Yes if yea, an evaluation must be O No coordinated by the Supervisor Regulatory Compliance:

10. Does the proposed change involve one or more of the following:

j a. A change in the rate, volume, concentration, composition or flow path of nonradiological j liquid or gaseous effluents? l b. A change in the volume, concentration or composition of nonradiological solid waste? l c. An increase in the thermal power above the current licensed level and/or an alteration in j the magnitudes of thermally affected effluents? ! d. A physical change in area outside of the owner controlled area boundary which was not disturbed by previous construction? ! e. The s,ddition of a new storage tank, or physical changes to the piping or capacity of an ! existing tank, that contains more than 660 gallons of chemical ) O Yes if yes, an environmental impact B No I determination must be approved by

the Superintendent Resource I Protection.

l

 ;                                                                                                o I                                                                                                                                                 l J

l

3 -

   ,[.,.hPF 26A-003-01, Rev.1                                                            OT$C @,,-09Ol

! m REGULATORY SCREENING NO.'59

O USQD rev.

Document Number: AP 078-003 Revision: 0 Page 4 of 4 ] tJ

     )  NOTE: For purposes of this question the Emergency Plan and Security Plans are considered part of
     ;       the USAR.
     \

A 11. Would the change involve one or more of the following: F a. a change to the plant structures, systems, components or equipment as outlined, summarized or described in the USAR such that accomplishment of the change could directly or indirectly make informatior, in the USAR no longer true, complete or accurate, or would violate a requirement stated in the USAR?

b. a change to procedures or administrative controls as outlined, summarized , or described in the USAR such that accomplishment of the change could make information in the USAR no longer true, complete or accurate, or would violate requirement stated in the USAR?

c. Tests or experiments NOT described in the USAR?

O Yes A formal Unreviewed Safety Question G5 No Determination using APF 26A-003-03 must be completed prior to implementing the change. Reminder: If yes, evaluate need for a USAR Change Request in accordance with AP26B-003 Caution: It is intended that step 11.a convey a broad and conservative interpretation of 10 CFR j 50.59 as described in NSAC-125. An unreviewed safety question determination is required if the l proposed change could alter the description of any SSC or equipment described in the USAR. This applies to the specific SSC being changed as well as any other equipment that could be affected directly or indirectly.

12. Clarification:

Prepared by: h -/,'S2ddyp Date: // J g Approved by:

                                                   /             Date:       q, g ,,9g i

l

H 2 3 Revision: 0 OFFSITE DOSE CALCULATION MANUAL AP 07B-003 Reference Use Page 44 of 188 O

ATTACHMENT A O

(Page 40 of 184) N

  \                                   OFFSITE DOSE CALCULATION MANUAL TABLE 3-1 (Continued) j TABLE NOTATIONS j           (2),      The principal gamma emitters for which the LLD specification applies 1                      include the following radionuclides:

y Kr-87, Kr-88, Xe-133, 133, Xe-133m, Xe-135, and Xe-138 in noble gas releases and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, I-131, Cs-134, Cs-137, Ce-141 and Ce-144 in iodine and particulate releases. This list does not mean that only these 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 semiannual Radioactive Effluent Release Report in the format outlined in Regulatory Guide 1.21, Appendix B, Revision 1, June 1974. (3) Sampling and analysis shall also be performed following shutdown, startup, or a THERMAL POWER change exceeding 15% of RATED THERMAL POWER within 1 hour period. (4) Tritium grab samples shall be taken and analyzed at least once per 24 hours when the refueling canal is flooded. (5) The ratio of the sample flow rate to the samp12d stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with Sections 3.1, 3.2 and 3.3. (6) Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours after changing, or after removal from sampler. For unit vent, sampling shall also be perfomed at least once per 24 hours for a least 7 days following each shutdown, startup or THERMAL POWER change exceeding 15% of RATED THERMAL POWER within a 1-hour period, and analyses shall be completed within 48 hours of changing. When samples collected for 24 hours are analyzed, the corresponding LLD's may be increased by a factor of 10. This requirement does not apply if: (1) analysis shows that the DOSE EQUIVALENT I-131 concentration in the reactor coolant has not increased more than a factor of 3, and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3. I l 1 l l 1 I}}

ML20138F337

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3.0 REFERENCES

3.0 REFERENCES

1.0 INTRODUCTION

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