"Wolf Creek Generating Station Annual Radioactive Effluent ...

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%o W@TzLF CREEK ,t' NUCLEAR OPERATING CORPORATION

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: Otto L Maynard ;* " . Vice President Plant Operations. ,

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Mar.ch 28, 1994

'WO 94-0035^

.U. S. Nuclear' Regulatory Commission*

' ATTN: Document' Control Desk. Mail Station P1-137 ,

Washington, D. C. 20555 |

Subject: Docket No. 50-482: Annual Radioactive Effluent-Release Report

Gentlemen:

Enclosed is the Wolf Creek Generating Station (WCGS) . Annual RadioactiveEffluent Relee.de Report' covering the period from January 1, 1993,'to December.

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31, 1993. This report is submitted pursuant to section 6. 9.1. 7 . of the WCGS. unit No. 1,. Technical Specifications.

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i Very truly yours,

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Otto L.LMaynard.

.OLM/jad,

Enclosure.,

cc: L. J. Ca3lan (VRC), w/a4

G. A. Pick -(KRC) , ' w/aW. D. Reckley (NRC), w/aL. A. Yandell (NRC) , w/a

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94033101 ~~ ---

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PDRr.v ,, ~. _ durlington, KS 66839 / Phone: (316) 364-8831 f ('

An Equal Opportunity Employer M/F/HC/ VET . . l -|'

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Faclosure to WO 94-0035Page 1 of 31

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Wolf Creek Nuclear Operating Corporation

Wolf Creek Generating Station

Docket No: 50-482Facility Operating License No: NPF-42

Annual Radioactive Ellluent Release Report

Report No.17

Reporting Period: January 1,1993 - December 31,1993

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' Enclosure to WO 94-0035.Page 2 of 31

Table of Contents

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DCf

Section I 4

Liquid Radioactive Ellluents 4

Dose Summary 8

- Airborne Radioactive Ellluents 10 i

Dose Summary 11

Section II .15 I

Offsite Dose Calculation Manual Limits 15

Maximum Permissible Concentrations 16

Measurements and Approximations of Total Reactivity 18 ;

Batch Releases 18

Continuous Releases 19

Solid Waste Shipments 21

Irradiated Fuel Shipments 22

Section ill 23 q

i Meteorological Data 22 ;

Section IV 31

iUnplanned or Abnormal Releases 31

OITsite Dose Calculation Manual 31

Major Changes to Liquid, Gascous or Solid Radwaste Systems 31 .;Land Use Census 31

Radioactive Shipments 31Inoperability of Airborne Efiluent Monitoring Instrumentation 31Storage Tanks . 31 )

Full and Low Pressure RCS Gas Sampic 31'

Attachment 1Liquid Effluent Change to Report No.16

Attachment 2 -

Offsite Dose Calculation Manual

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| Enclosure to WO 94-0035Page 3 of 31

EXECtITIVE St1MM ARY

The purpose of the Annual Radioactive EfIluent Release Report is to report on the quantities ofliquid andI gaseous effluents and solid waste released from Wolf Creek Generating Station (WCGS). This report

covers the period beginning on January 1,1993, and ending on December 31,1993.

' Section i provides a summary of the quantitics of radioactive liquid and gaseous efuuents for thisreporting period. The format is similar to that recommended in Regulatory Guide 1.21, Revision 1. Anelevated release pathway dose not exist at WCGS, therefore, all airborne releases are considered to beground level releases. The concurrent meteorological condition gaseous pathway dose determination ismet by the WCGS Offsite Dose Calculation Manual (ODCM) methodology of assigning all gaseouspathways to a hypothetical individual residing at the highest annual X/Q and D/Q location. This results .

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in a conservative estimate of dose to a member of the public rather than determining each pathway dosefor cach release condition. A conservative error of thirty percent has been estimated in effluent data.

Sections II, III and IV proside additional information required by Regulatory Guide 1.21, Rcvision 1 andODCM Section ~.2.

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Atteluvent i provides actual values to replace the estimated values for liquid elliuents provided inf eraiannual Radioactive Eilluent Release Report No.16. Analysis results for the Fourth Quarter ofReport No.16 were not completed prior to submission of the report. Actual results of the Fourth Quarter,

| liquid effluents mdicated the presence of Fe-55 and St-90 in the liquid batch composite. This correction

| resulted in very minor changes to the cumulative dose.

Attachment 2 provides the latest revision of the Offsite Dose Calculation Manual.

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Section 1 ,

Report of Radioactive Efiluents (199M: Lionial

hpe of Elliuent Mrlil - Ouarter 1 Ouarter 2

A. Fission and Activation Products :'

1. Total Release (not including tritium, gases, alpha) Ci 4.01E-01 2.74E-01 -2. Average Diluted Concentration During Period uCi/ml 6.32E-08 3.08E-083. Percent of Applicable Limit (1) % 8.03E+00 5.49E+00

B. Tritium1. TotalRelease Ci 4.87E+02 3.90E+012. Average Diluted Concentration During Period uCi/ml 7.67E-05 4.39E-063. Percent of Applicable Limit -(2) % 2.56E+00 1.46E-01

C. Dissolved and Entrained Gases1. Total Release Ci 1.67E+01 4.00E-032. Average Diluted Concentration During Period uCi/ml 2.62E-06 4.50E-103. Percent of Applicable Limit (3) % 1.31E+00 2.25E-04

D. Gross Alpha Radioactivity

1. Total Release Ci 7.41 E-05 4.13E-05!

E. Volume of Waste Rc! case 4rior to dilution) Liters 1.41E+08 1.14E+08

F. Volume of Dilution Water Used Liters 6.21E+09 8.78E+09

1. The applicable limit fbr the Wolf Creek Generating Station is 5 Curies per year. (Reference 10 CFR 50,Appendix I, " Guides on Design Objective For 1.ightJWater-Coolad Nwelear Power Reactors," paragraph A.2). Thevalue prin%1 here is derived by dividing the total released Curies by 5 Curies and then multiplying the result by 100.

2. This value is derived by the following fonnula:% of Applicable Limit _(Avegee Diluted Concentration)(100)=

*- (MPC, Appendix 13, Table 1110CFR20)

3. This value is derived by the following fonnula:% of Applicable 1,imit _(Atear ge Diluted ConcentrationM100)=

(2E-4 from ODCM Section 2.1)

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Page 5 of 31 |

Section I d

Report of Radioactive Efiluents (1993h Liquid

Tyr>c of Effluent Rnil Ouarter 3 Quarter 4n

A. Fission and . Activation Products1. Total Release (not including tritium, gases, alpha) Ci 2.23E4)2 8.55E-032. Average Diluted Concentration During Period uCi/ml 4.01E-09 2.53 E-093. Percent of Applicable Limit (1) % 4.46E-01 1,71 E-01

13. Tritium,

1. Total Release Ci 1.65E+02 3.08E+022. Average Diluted Concentration During Period uCi/ml 2.97E-05 9.12E-053. Percent of Applicable Limit (2) % 9.90E-01 3.04 E+00 '

C. Dissolved and Entrained Gases1. Total Release Ci 1.15E-03 1.45E-022. Average Diluted Concentration During Period uCi/ml 2.06E.10 4.28E-093. Percent of Applicable Limit (3) % l .03E-04 2.14E4)3 r

D. Gross Alpha Radioactivity

1. Total Release Ci 2.75E-05 1.35E-05

E. Volume of Waste Release (prior to dilution) Liters 4.60E+06 1.42E+08

F. Volume of Dilution Water Used Liters 5.55E+09 3.24 E+09

1. The applicable limit for the Wolf Creek Generating Station is 5 Curies per year. (Reference 10 CFR 50,Appendix I, " Guides on Design Objective for Light-Water-Cooled Nuclear Power Reactors " paragraph A.2). 'lhevalue printed here is derived by disiding the total released Curies by 5 Curies and then multiplying the result by 100,

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2. This value is derived by the following fannula:% of Applicable Limit _faverace Diluted ConcentrationM100)= >

(MPC, Appendix 13, Table II 10CFR20)

3. 'Ihis value is derived by the following fonnula:% of Applicable Limit fAverace Diluted ConcentrationM100)=


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Enclosure to WO 944)o35Page 6 of 31

1 OUlD EFF1 UENTS

Continuous Mode Batch Mode - '

Nudiden Released_l.] nil Quarter i Qllarter 2 Ouarter 1 Quarter 2

H-3 Ci 3.59E-01 5.61 E-01 4.86E+02 3.84EH)1Be-7 Ci 0.00E+00 0.00E+00 5.98E-04 0.00E+00Na-24 Ci 0.00E+00 0.00E+00 1.22E-05 0.00E+00Cr 51 Ci 0.00E+00 0.00E+00 6.46E-03 - 2.46E-02Mn-54 Ci <6.98E4)2 <5.66E-02 7.03E-03 3.40E-03Fe-55 Ci <l.40E-01 <l.31 E-01 1.55E-01 5.43E-02Fe-59 Ci <6.98E-02 <5.66E-02 5.96E-04 2.83E-03 jCo-57 Ci 0.00E+00 0.00E+00 1.00E-03 5.10E-04 .iCo-58 Ci <6.98E4)2 1.46E-05 2.58E-02 9.97E-02 !Co-60 Ci <6.98E-02 <5.66E4)2 1.06E4)1 2.98E-02 i

Zn-65 Ci <6.98E4)2 <5.66E-02 <8.91 E-04 <6.62 E-04 .

Sr-89 Ci <6.98E-03 <5.66E-03 <8.91 E-05 <6.62E-05 !Sr-90 Ci <6.98E-03 <5.66E-03 6.95E-05 2.25E-05 l

Sr-92 Ci 0.00E+00 0.00E+00 8.68E-06 0.00E+00 1

Zr-95 Ci 0.00E+00 0.00E+00 3.23E-04 4.64E-03 |Nb-95 Ci 0.00EH)0 0.00E+00 6.57E-04 8.24E4)3 i

Tc-99M Ci 0.00E+00 0.00E+00 2.10E-05 0.00E+00Mo-99 Ci <6.98E-02 <5.66E-02 <8.91 E-04 <6.62E-04Ru-103 Ci 0.00E+00 0.00E +00 1.27E-04 9.35E-04Ag-110M Ci 0.00E+00 0.00E+00 1.90E-03 8.02E-04

Sn-113 Ci 0.00E+00 0.00E+00 8.47E-05 1.69E-03Sn-ll7M Ci 0.00E+00 0.00E+00 2.87E414 2.43E-05Sb-124 Ci 0.00E+00 0.00E+00 2.04 E-03 1.23E-03

Sb-125 Ci 0.00E+00 0.00E+00 5.84E-02 1.90E-02Sb-126 Ci 0.00E+00 0.00E+00 1.49E-04 0.00EH)01-131 Ci 9.80E4)5 <l.31E4)1 4.21E-03 9.06E-041-132 Ci 0.00E+00 0.00E+00 9.35E-05 0.00E+001-133 Ci 7. l l E-05 0.00EH)0 0.00E+00 0.00E+ 00

Cs-134 Ci 4.15E-05 <5.66E-02 1.16E-02 9.28E-03Cs-136 Ci 0.00E+00 0.00E+00 0.00E+00 4.70E-05

Cs-137 Ci 2.30E-05 <5.66E-02 127E-02 8.95E-03La-140 Ci 0.00E+00 0.00E+00 2.43 E-04 4.14E-05Cc-141 Ci <6.98E-02 <5.66E-02 4.17E-05 1.94E-04Cc-144 Ci <6.98E-02 <5.66E-02 4.86E-03 2.61 E-03

Hf181 Ci 0.00E+00 0.00E+00 0.00E+00 3.71 E-04

Ar-41 Ci < l .40E+00 <l .31 E+ 00 <l .78E4)2 <l.32 E-02Kr-85M Ci <l .40E+00 <l .31E+00 <l.78E-02 4.64E-05 -Kr-85 Ci < l .40E+00 < l .3 ] E+00 4.03E-01 <l .32E-02Kr-87 Ci <l .40E+00 < l .31EM)0 <l .78E-02 1.32E-04 .

Kt-88 Ci < l.40E+00 <l .31 E+00 <l .78E-02 <l .32E-02Xc-131M Ci < l .40E+00 <l.31 E+00 2.48E-01 <l .32E-02Xc-133M Ci <l.40E+00 <l .31 E+00 1.15E-01 <! .32E-02Xc-133 Ci < l .40E400 <l .31 E+00 1.58E+01 3.82 E-03

Xe-135 Ci < l .40E+00 <l .31E+00 9.95E-03 <l .32E-02Xc-138 Ci <l .40E+00 <l.31E+00 <l .78E-02 <l .32E-02G-ALPHA Ci <l.40E-02 <l .31E-02 7.41E-05 4.13 E-05muGD f OTAl. Ci 3.59E-01 5.61E-01 5.03 E+02 3.87E+01NOTE: Less than values are calculated using the lower limit of detection (LLD) values listed in Table 2-1 of theODCM multiplied by the volume of waste discharged during the respective quaner. De less than values are notincluded in the summation for the total release values.

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1Enclosure to WO 94-0035Page 7 of 31

'lLIOUID EFFLUENTS -]

Continuous Mode Batch ModeNucti&s Released Unit Ouarter 3 Ouarter 4 Quarter 3 Ouarter 4. )H-3 Ci 1.84E-02 1,46E-02 .1.65E+02 3.08E+02 >

Be-7 Ci 0.00E+00 0.00E+00 0.00E+00 6.26E-05 .

Cr-51 Ci 0.00E+00 0.00E+00 3.04 E-04 0.00E+00Mn-54 Ci <l.77E413 <7.07E-02 3.53 E-04 1.61 E-04

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Fe-55 Ci <3.54E-03 < l .41E-01 1.16E4)2 2.05E-03Fe-59 Ci < l.77E-03 <7.07E4)2 1.73 E-05 <3.81E-04Co-57 Ci 0.00E+00 0.00E+00 2.88E-05 8.80E416 .

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Co-58 Ci < l .77E-03 <7.07E-02 4.32E-03 7.99E-04Co-60 Ci <l .77E-03 <7.07E-02 3.90E-03 1.92E-03Zn-65 Ci <l.77E-03 <7.07E-02 <5.30E-04 <3.81E-04Sr-89 Ci <l.77E4)4 <7.07E4)3 <5.30E-05 <3.81 E-05St-90 Ci < l .77E-04 <7.07E-03 <5.30E4)5 <3.81E4)5 ' |Zr-95 Ci 0.00F+00 0.00E400 1.29E-04 0.00E+00

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Nb-95 Ci 0.00E+00 0.00E+ 00 5.15E-04 9.10E-05Mo-99 Ci < l.77E-03 <7.07E-02 <5.30E-04 <3.81E-04Ru-103 Ci 0.00E+00 0.00E+00 4.58E-06 0.00E+00Ag 110M Ci 0.00E+00 0.00E+00 8.45E-05 0.00E+00Sn-ll3 Ci 0.00E+00 0.00E+00 9. l l E-05 0.00E+00Sb-125 Ci 0.00E+00 0.00E+00 6.84E-04 1.18E-04I-131 Ci <3.54E-03 <l .41E-01 1.73E-05 <7.62E-04Cs-134 Ci <l .77E-03 <7.07E-02 2.93E-05 1.55E-03 .Cs-137 Ci <l.77E-03 <7.07E-02 9.11E-05 1.75E-03

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La-140 Ci 0.00E+00 0.00E+00 1.23E-06 0.00E+00Cc-141 Ci <l .77E-03 <7.07E-02 <5.30E-04 <3.81 E-04 .Cc-144 Ci <! .77E-03 <7.07E-02 6.84E-05 1.74 E-05

Ar-41 Ci <3.54 E-02 <l.4 IE+00 - <l .06E-02 <7.62E-03 -Kr-85M Ci <3.54E-02 <l .41E+00 <1.06E-02 - 3.29E-06Kr-85 Ci . <3.54E-02 <l .41E+00 <l.06E412 5.04 E-03Xe-133M Ci <3.54E4)2 <l .41 E+00 <l .06E-02 4.65E-05Xe-133 Ci <3.54 E-02 <l .41E+00 1.14E-03 9.35E-03Xc-135 Ci <3.54E-02 <l .41 E+00 <l .06E-02 2.62E4)5Xc-138 Ci <3.54E-02 <l .41E+00 < l .06E-02 <7.62E-03G-ALPHA Ci <3.54 E-04 <l .4 ] E-02 2.75E-05 1.35E-05 -PElHOD TOTAL Ci 1.84E-02 1.46E-02 1.65E+02 3.08E+02

NOTE: Less ilum values are calculated using the lower limit of detection (LLD) values listed in Table 21 of the - '

ODCM multiplied by the volume of waste discharged during the respective quarter. The less than values are notincluded in the summation for the total release vahies.

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LIOUlD CUMULATIVE DOSE SUMMARY (1993) qTable 1 !

O|j. ODCM CALC. DOSE ODCM LIMIT (1) % OF LIMITQuarter 1 of1993TOTAL DOSE (mrem) FOR BONE 1.03 E-01 5.00E+00 2.07E+00.TOTAL DOSE (mrem) FOR LIVER 2.53E-01 5.00E+00 5.07E+00TOTAL DOSE (mrem)FOR TOTAL BODY 2.07E-01 1.50E+00 1.38E+01

|. TOTAL DOSE (mrem) FOR THYROID 8.29E-02 5.00E+00 1.65E+00

| TOTAL DOSE (mrem) FOR KIDNEY 1.30E-01 5.00E+00 2.61E+00

| TOTAL DOSE (mrem) FOR LUNG 9.15E-02 5.00E+00 1.83E+00i TOTAL DOSE (mrem) FOR GI-LLI 1.01 E-01 5.00E+00 2.03 E+00

Quarter 2 of1993TOTAL DOSE (mrem) FOR BONE 7.89E-02 5.00E+00 1.58E+00

|- TOTAL DOSE (mrem) FOR LIVER 1.64E-01 5.00E+00 3.288+00TOTAL DOSE (mrem) FOR TOTAL BODY 1.28E-01 1.50E+00 8.57E+00TOTAL DOSE (mrem) FOR TIIYROID 2.51E4)2 5.00E+00 5.03E-01

TOTAL l>OSE (mrem) FOR KIDNEY 6.80E-02 5.00E+00 1.36E+00 a

TOTAL DOSE (mrem) FOR LUNG 3.69E-02 5.00E+00 7.39E-01 |'

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TOTAL DOSE (mrem) FOR GI-LLI 163E-01 5.00E+00 3.26E+00

Quarter 3 of 1993TOTAL DOSE (mrem) FOR BONE 4.46E-04 5.00E+00 - 8.93E-03

TOTAL DOSE (mrem) FOR LIVER 1.99E-02 5.00E+00 3.99E-01 ;

TOTAL DOSE (mrem) FOR TOTAL BODY 1.97E-02 1.50E+00 L31E+00TOTAL DOSE (mrem) FOR THYROID 1.93E-02 .5.00E+00 3.86E-01

TOTAL DOSE (mrem) FOR KIDNEY 1.94 E-02 5.00E+00 3.89E-01

TOTAL DOSE (mrem) FOR LUNG L93E-02 5,00EM)0 3.87E-01

TOTAL DOSE (mrem) FOR GI-LLI 2.60E-02 5.00E+00 5.21E-01

Quarter 4 of 1993TOTAL DOSE (mrem) FOR BONE 9.72E-03 5.00E+00 1.94E-01 )TOTAL DOSE (mrem) FOR LIVER 5.29E-02 5.00EH)0 1.05E+00TOTAL DOSE (mrem) FOR TOTAL BODY 4.85E-02 1.50E+00 3.23E+00

TOTAL DOSE (mrem) FOR THYROID 3 56E-02 5.00E+00 7.12E-01 ;

TOTAL DOSE (mrem) FOR KIDNEY 4.13E-02 5.00E+00 8.26E-01 R

TOTAL DOSE (mrem) FOR LUNG. 3.75E-02 5.00E+00 7.50E-01


| TOTALS FOR 1993TOTAL DOSE (mrem) FOR BONE 192E-01 1.00E+01 1.92E+00

TOTAL DOSE (mrem) FOR LIVER 4.90E-01 1.00E401 4.90E+00

TOTAL DOSE (mrem) FOR TOTAL BODY 4.04E-01 3.00E+00 1.34E+01

TOTAL DOSE (arem) FOR THYROID 1.63E-01 1.00E+01 1.63E+00

TOTAL DOSE (rmem) FOR KIDNEY 2.59E-01 1.00E+01 2.59E+00

TOTAL DOSE (mrem) FOR LUNG 1.85E-01 1.00E+01 1.85E+00

TOTAL DOSE (mrem) FOR GI-LLI 3.28E-01 1.00E+01 3.28E+00 ;

i- 1. Based on ODCM Section 2.2 which restricts dose to the whole txxly to less than or equal to 1.5 mrem per quarterj and 3.0 mrem per year. Dose restriction to any organ is less tlum or equal to 5 mrem per qarter and 10 mrem per .

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. LIOUID CUMULATIVE DOSE SUMMARY (1993)Table 2

jOuarter 1 Ouarter 2 Quarter 3 Onarter 4 -TOTAL

A. Fission and Activation Products !

(not including H-3, gases, alpha)

1. Total Release -(Ci) 4.01E4)1 2.74E4)1 2.23E-02 8.55E-03 - 7.06E-012. Maximum Organ Dose (mrem) ' l.82E-01 1.43 E-01 6.78E4)3 - 1.73E-02 3.43 E-01 !,

3. Organ Dose Limit (mrem) 5.00E+00 5.00E+00 5.00E+00 5.00E+00 1.00E+01 I

4. Percent of Limit 3.65E+00 2.85E400 1.35E-01 3.46E-01 3.43 E+00,

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1. Total Release -(Ci) 4.87E+02 3.90E+01 1.65E+02 3.08E+02 9.99E+02J2. Maximum Organ Dose (mrem) 7.09E-02 2.10E-02 1.93E-02 3.56E-02 1.47E-01 i

3 Organ Dose Limit (mrem) 5.00E+00 5.00E+00 5.00E+00 5.00E+00 .1.00E+01 l

4. Percent of Limit 1.42E+00 4.21E-01 3.86E4)I 7.12E-01 1.47E+00 ']

This table is included to show the correlation between Curies released and the associated calculated maximum organdose. Wolf Creek ODCM methodology is used to calculate the maximum organ dose which assumes that anindividmd drinks the water and eats the fish from the discharge point. ODCM Section 2.2 organ dose limits are used.The less than values are not included in the summation for the total release values.

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Enclosure to WO 94-0035 i'

Page 10 of 31REPORT OF RADIOACTIVE EFFLUENT (1993h AIRBORNE

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jType of EfTluent Unit Ouarter.1 Ouarter 2 Ouatter.3 Ouarter 4A. Fission and Activation Gases i

1. Total Relcase Ci 5.10E+02 2.11E+00 3.87E+00 5.68E+00 ~

2. Average Release Rate for Period uCi/sec 6.56E+01 2.69E-01 4.87E-01 7.15E-01

3. Percent of ODCM Limit (1) % 3.87E-01 2.95E-03 9.67E-03 1.33E-02

B. Iodines (Iodine-131)1. Total Release Ci 5.37E-04 L1IE-04 3.39E-05 1.1 I E-05

2. Average Release Rate for Period uCi/sec 6.90E-05 1.42E-05 4.27E-06 1.39E-06 i

3. Percent of ODCM Limit (2) % 5.37E-02 1.1 IE-02 3.39E-03 1.11E-03

C. Particulates (Halflives > 8 days) ;

1. Total Release Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 )

2. Average Release Rate for Period uCi/sec 0.00E+00 0.00E+00 0 00E+00 0.00E+00 '

3. Percent of ODCM Limit (3) % 0.00E+00 0.00E+00 0.00E +00 0.00E+00 I

4. Gross Alpha Radioactivity Ci 0.00E+00 5.50E-08 5.02E-08 0.00E+00

D. Tritium1. Total Release Ci 5.53 E+00 4.72E+00 8.45E400 6.98E+00

2. Average Release Rate for Period uCi/sec 7.1 lE-01 6.00E-01 1.06E+00 8.78E-01

3. Percent of ODCM Litml (4) % 5.69E-02 4.68E-02 7.87E-02 6.20E-02

1. De percent of ODCM limit for fission and activation gases is calculated using the following methodelagt ,

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% of ODCM Limit = (Otrly Total Beta Airdosey100) or (OtrlyTotal Gamma AirdoseV100) )10 mrad 5 mrad ;

The largest value calculated between Gamma and Beta airdose is listed as the % of ODCM Limit.'

2. He percent of ODCM limit for iodine is calculated using the fallouing methodology:

_C[Fot_aj_guries oflodine-131 Y100)% of 0DCM Limit =

1 Curie

3. The percent of ODCM limit for particulates is calculated using the following methodology-

% of ODCM Limit 0lichest Organ Dose due to ParticulatesY100)=

7.5 miem

4. The percent of OIX'M limit for tritium is calculated using the following methodology:

Ofichest Orcan Dose Due to II-3Y100)% of ODCM Limit =

7.5 mremNOTE: Tlus type of methodology is used since the Wolf Creek ODCM ties relene limits to doses rather than Curierelease rates.

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GASEOUS EFFLUENTS'{l

Continuous Mode Batch ModsNuclides Released Rail Ouarter 1 Ouarter 2 Quarter i Ouarter 2 |

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l. FissionGases

Ar-41 Ci 0.00E+00 0.00E+00 1.12E-01 4.15E-02.

Kr-85M Ci 5.85E-01 0.00E+00 0.00E+00 0.00E+00Kr-85 Ci 0.00E+00 0.00E+00 2.02E+01 1.82E+00Kr-87 Ci <2.37E+01 <2.68E+01 <l .43 E+00 <4.05 E+00 t

Kr-88 Ci 4.54E411 <3.01E+01 <l .60E+00 <2.27E+00Xc-131M Ci 8.57E-01 0.00E+00 1.05E+01 1.69E4)2Xc-133M Ci 1.39E-01 <5.40E+0 i 2.b9E+00 <4.07E+00Xe-133 Ci 1.71E+02 1.12E-02 2.98E+02 1.81E-02Xe-135 Ci 3.79E+00 2.02E-01 2.56E4)1 4.04 E-04Xc-138 Ci <8.55E+01 <9.67E+01 <5.15E+00 <7.30E+00Total for ,

Period Ci 1.77E+02 2.13E-01 3.32E+02 1.90E+00

2. Iodines

1-131 Ci 5.36E-04 1.1IE-04 <l .43 E-05 <2.03E-05I-133 Ci 6.92E4)5 9.00E-06 <l .43 E-03 <2.03 E-03

Total forPeriod Ci 6.05E-04 1.20E-04 0.00E+00 0.00E+00

3. Particulates& Tritimn

H-3 Ci 5.04E+00 4.38E+00 ' 4.86E-01 3.31 E-01

Mn-54 Ci <2. 37E-03 <2.69E-03 <l .43E-04 <2.03 E-04Fe-59 Ci <2.37E4)3 <2.69E4)3 <l.43E414 <2.03 E-04Co-58 Ci <2.37E-03 <2.69E-03 <l.43 E-04 <2.03E-04Co-60 Ci <2.37E-03 <2.69E-03 <l.43E-04 <2.03 E-04Zn-65 Ci <2.37E-03 <2.69E-03 <l.43E4)4 <2.03 E-04Sr-89 Ci <2.37E4)3 <2.69E-03 < l.43 E-04 <2.03 E-04

Sr-90 Ci <2.3 7E-03 <2.69E-03 <l .43 E-04 <2.03 E-04

Mo-99 Ci <2.37E-03 <2.69E4)3 <l .43 E-04 <2.03 E-04

Cs-134 Ci <2.37E-03 <2.69E413 <l.43 E-04 <2.03 E-04Cs-137 Ci <2.37E-03 <2.69E4)3 < l .43 E4)4 <2.03 E-04

Cc-141 Ci <2.37E4)3 <2.69E-03 <l .43E-04 <2.03 E-04

Ce-144 Ci <2.37E-03 <2.69E-03 <l .43E-04 <2.03E-04G-Alpha Ci <2.37E-03 5.49E-08 <l.43E-0; <2.03E-04Total forPeriod Ci 5.04E+00 4.38E+00 4.86E-01 3.31E-01

NOTE: 1.ess than values for Noble Oases are calculated using the lower limit of detection (LLD) values obtained at - !

WCOS multiplied by the volume of air discharged during the respective quarter. For the Ilalogens and Particulatesthe ODCM LLD values are used. - The less than values are not included in the summation for the total release values.

|

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. . _ _

Enclosure to WO 94-0035Page 12 of 31

GASEOUS EFFLUENTS

Continuous Mods Batch ModeNuclide, Released Unit Ouarter 3 Ouarter 4 Ouartef 3 ' Ouarter 41. Fission

Gases

Ar-41. Ci 0.00E+00 0.00E+00 6.98E-02 1.23E-01

Kr-87 Ci <2.68E+01 <2.69E+01 <7.58E4)3 - < l .29E-02

Kr-88 Ci <3.01E+01 <3.02E+01 <8.51 E-03 <l .45E-02Xc-133 Ci 6.40E4)1 .1.44E+00 6.58E-03 1,58E-02

Xe-133:n Ci <5.40E+01 <5.43E+01 <l.53E-02 <2.61 E-02Xc-135 Ci 3.15E+00 4.10E+00 5.76E-05 1.70E-04 .

Xc-138. Ci <9.68E+01 <9.72 E+01 <2.74E4)2 <4.67E-02Total forPeriod Ci 3.79E+00 5.54E+00 7.65E-02 1.39E-01

2.lodines

I-131 Ci 3.39E-05 1.10E-05 <7.60E-08 <l.30E-071-133 Ci 1.32E-04 2.O l E-04 <7.60E416 < l.30E-05Total forPeriod Ci 1.66E-04 2.12E-04 0.00E+00 0.00E+00

3. Particulatesand Tritium

H-3 Ci 8.26E+00 6.73E+00 1.84 E-01 2.38E-01Mn-54 Ci <2.69E-03 <2.70E40 <7.60E-07 <l.30E-06Fe-59 Ci <2.69E-03 ' <2.70E-03 <7.60E-07 <l .30E-06Co-58 Ci <2.69E-03 <2.70E413 <7.60E-07 < l .30E-06

Co-60 Ci <2.69E-03 <2.70E-t J <7.60E-07 <l .30E-06 >

Zn-65 Ci <2.69E-03 <2.70E-03 <7.60E-07 <l .30E-06St-89 Ci <2.69E4)3 <2.70E-03 <7.60E-07 <l .30E-06Sr-90 Ci <2.69E-03 <2.70E-03 <7.60E-07 <l .30E-06Mo-99 Ci <2.69E4)3 <2.70E4)3 <7.60E4)7 <l .30E-06Cs-134 Ci <2.69E-03 <2.70E-03 <7.60E-07 <l .30E-06Cs-137 Ci <2.69E-03 <2.70E-03 <7.60E-07 <l .30E-06Cc-141 Ci <2.69 E4)3 <2.70E-03 <7.60E-07 <l.30E-06 I

Cc-144 Ci <2.69E-03 <2.70E-03 <7.60E-07 <l .30E-06 |

G-Alpha Ci 5.02 E4)8 <2.70E-03 <7.60E-07 <l.30E-06 - |

Total for ,

|Period Ci 8.26E+00 6.73 E+00 1.84E-01 2.38E-01

l

NOTE: Less than values ihr Noble Gases are calculated using the LLD values obtained at WCGS multiplied by the i

vohirne of air discharged during the respective quarter. For the Italogens and Particulates the ODCM LLD values areused. "lhe less than values are not included in the smranation for the total release values.

i

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Enclosure to WO 94 0035Page 13 of 31

GFEOUS CUMULATIVE DOSE SUMM ARY (1993)Tabic 1

,,-

ODCM CALC. DOSE ODCM LIMIT (D % OF LIMIT 1

Quarter 1 of 1993 ~.

TOTAL DOSE (mrem) FOR BONE 9.35E-04 7.50E+00 1.24E-02 -

TOTAL DOSE (mrem) FOR LIVER 4.85E-03 7.50E+00 6.46E-02 :

TOTAL DOSE (mrem) FOR TOTAL BODY 4.44 E-03 7.50EM)0 5.92E-02

TOTAL DOSE (mrem) FOR THYROID 3.13 E-01 7.50E+00 4.17E+00;- TOTAL DOSE (mrem) FOR KIDNEY 5.45E4)3 7.50E+00 ' 7.27E-02 -

TOTAL DOSE (mrem) FOR LUNG 3.91E-03 7.50E+00 5.22E-02

TOTAL DOSE (mrem) FOR GI-LLI 3.99E-03 7.50E+00 5.33 E-02

Quarter 2 of 1993TOTAL DOSE (mrem) FOR BONE 1.94E-04 7.50E+00 2.58E-03

TOTAL DOSE (mrem) FOR LIVER 3.53 E-03 7.50E+00 ' 4.70E-02TOTAL DOSE (mrem) FOR TOTAL BODY 3.44E-03 - 7.50Ev00 4.59E-02

TOTAL DOSE (mrem) FOR THYROID 6.74E4)2 7.50E+00 8.99E-01

TOTAL DOSE (mrem) FOR KIDNEY 3.65E-03 7.50E+00 - 4.87E-02 .

TOTAL DOSE (mrcm) FOR LUNG 3.33E-03 7.50E+00 4.44 E-02

TOTAL DOSE (mrem) FOR GI-LLI 3.35E-03 7.50E+00 4.47E412

Quarter 3 of 1993TOTAL DOSE (mrem) FOR BONE 6.24E415 - 7.50E+00 8.33E-04

TOTAL DOSE (mrem) FOR L1VER 6.03 E-03 7.50E+00 8.04E-02.

TOTAL DOSE (mrem) FOR TOTAL BODY 6.00E4)3 7.50E+00 8.01E-02 - ;

TOTAL DOSE (mrem) FOR THYROID 2.62E4)2 7.50E+00 3.50E-01 |

TOTAL DOSE (mrem) FOR KIDNEY 6.07E-03 7.50E+00 8.10E-02 -

TOTAL DOSE (mrem) FOR LUNO 5.97E-03 7.50E+00 7.96E-02

TOTAL DOSE (mrem) FOR GI-LLI 5.98E-03 7.50E+00 7,97E-02 '

Quarter 4 of 1993TOTAL DOSE (mrem) FOR BONE 2.45E415 7.50E+00 3.27E-04

TOTAL DOSE (mrem) FOR LIVER 4.95E-03 7.50E+00 6.61 E-02 ,

TOTAL DOSE (mrem) FOR TOTAL BODY 4.94E-03 - 7.50E+00 6.59E4)2 I

TOTAL DOSE (mrem) FOR THYROID 1.24E-02 7.50E+00 1.66E-01

TOTAL DOSE (mrem) FOR KIDNEY 4.97E-03 7.50E+00 6.63E-02

TOTAL DOSE (mrem) FOR LUNG 4.93E4)3 7.50E+00 6.57E-02 |

TOTAL DOSE (mrem) FOR Gl LLI 4.93E-03 7.50E+00 6.58E-02 !

|

TOTALS FOR 1993

TOTAL DOSE (mrem) FOR BONE 1.21E-03 1.50E+0! 8.llE4)3TOTAL DOSE (mrem) FOR LIVER 1.93E4)2 1.50E+01 1.29E-01

TOTAL DOSE (mrem) FOR TOTAL BODY 1.88E 02 1.50E+01 1.25E-01

TOTAL DOSE (mrem) FOR THYROID 4.19E-01 1.50E+0 ! 2.79E+00

TOTAL DOSE (mrem) FOR KIDNEY 2.01 E-02 1.50E+01 1.34E-01

TOTAL DOSE (mrem) FOR LUNG 1.81 E4)2 1.50E+01 1.2 iE-01

TOTAL DOSE (mrem) FOR GI-LLI 1.82 E-02 1.50E+01 1.21E-01

1. Based on ODCM Section 3.2.2 which restricts dose during any calendar quarter to less than or equal to 7.5 mremto any organ and during any calendar year to less than or equal to 15.0 mrem to any organ

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

.

- Enclosure to WO 94-0035Page 14 of 31

G ASEOllS CUMULATIVE DOSE SUMM ARY (1993)Table 2

0 :arter 4 TotalNuclides Released Quarter 1 Ouarter 2 Ouarter 3 2- A. Fission and Activation

1. Total Release (Ci) 5.10E+02 2.1 I E+00 3.87E+00 5.68E+00 5.21 E+ 02

2. Total Gamma Airdose (mrad) 1.28E-02 5.71 E-05 4.83E-04 6.64E-04 1.40E-02

3. Gamma Airdose Limit (mrad) 5.00E+00 5.00E+00 5.00E+00 5.00E+00 1.00E+01

4. Percent of Gamma Airdose Limit 2.57E-01 1.14E-03 9.67E-02 1.33 E-02 1.40E-01

5. Total Beta Airdose (mrad) 3.87E-02 2.95E-04 6.04E-04 8.38E-04 4.05E-02

6. Beta Airdose Limit (mrad) 1.00E+01 1.00E+01 1.00E+01 1.00E+01 2.00E+01

7. Percent of Beta Airdose Limit (mrad) 3.87E-01 2.95E-03 6.04E-03 8,38E-03 2.02E4)1

B. Particulates

1. Total Particulates (Ci) 0.00E+00 0.00E+00 0.00 E+00 0.00E+00 0.00E+002. Maximum Organ Dose (mrem) 0.00E 00 0.00E+00 0.00E+00 0.00E+00 0.00E+003. Org:m Dose Limit (mrem) 7.50E+00 7.50E+00 7.50E+00 7.50E+00 1.50E+01

4. Percent of Limit 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00

C. Tritium

1. Total Particulates (Ci) 5.53E+00 4.71 E+00 8.44 E+00 6.97E+00 2.56E+012. Maximum Organ Dose (mrem) 4.27E-03 3.51E-03 5.90E-03 4.65E-03 1.83E-023. Organ Dose Limit (mrem) 7.50E+00 7.50E+00 7.50E+00 7.50E+00 1.50E+01

4. Percent of Limit 5.69E-02 4.68E-02 7.87E-02 6.20E-02 1.22E-01

D. lodine

1. TotalI-131,1133 (Ci) 6.05E-04 1.20E-04 1.66E-04 2.12E-04 1.10E-032. Maximum Organ Dose (mrem) 3.67E411 5.86E-03 2.24 E-02 5.38E-03 4.0 l E-01

3. Organ Dose Limit (mrem) 7.50E+00 7.50E+00 7.50E+00 7.50E+00 1.50E+01. .

4. Percent of Limit 4.90E+00 7.82E-02 2.98E-01 7.18E-02 2.67E+00

This table is included to show the correlation between Curies released and the associated calculated maximum organdose. The maximum org m dose is calculated using Wolf Creek ODCM methodology which assumes that anindividual actually resides at the release point ODCM Section 3.2.2 organ dose limits are used.

1

!

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Section II,

Supplemental Information.

Facility: Wolf Creek Generatine Station License Number: NPF-42

1. ODCM Limits

A. For liouhl waste effluents

A.1 The concentration of radioactive material released in liquid emuents' toUNRESTRICTED AREAS shall be limited to the concentrations specified in 10CFR20,Appendix B Table II, Column 2, for radionuclides other than dissolved or entrainednoble gases. For dissolved or entrained noble gases, the concentration shall be limitedto 2 x 10 -4 microcurie /ml total activity.

A.2 The dose or dose commitment to MEMBER OF THE PUBLIC from radioactivematerials in liquid effluents released, from each unit, to UNRESTRICTED AREAS shallbe 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 svhole body

and to less than or equal to 10 mrems to any organ.

H. For caseous waste effluents

B.1 The dose rate due to radioactive material released in gaseous effluents fro the site to areaat and beyond the SITE BOU'NDARY 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, andb. For lodine-131, lodine 133, tritium, and all radionuclides in particulate form

with half-lives greater thank 8 days: Less than or equal to 1500 mrems/yr to anyorgan. !

B.2 The air dose due to noble gases released in gaseous effluents, from each unit, to areas atand beyond the SITE BOUNDARY shall be limited to the following:a. During any calendar quarter: Less than or equal to 5 mrads for gamma

radiation and less than or equal to 10 mrads for beta radiation, andb. 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.B.3 The dose from lodine-131, lodine-133, tritium, and a radionuclide in particulate form

w ch half-hves greater than 8 days in gaseous cPluents released to area at and beyondthe SITE BOUND ARY shall be limited to the following:a. During any calendar quarter: Less than or equal to 7.5 mrems to any organ,

andb. During any calendar year: Less than or equal to 15 mrems to any organ.

2. Maximum Permissible Concentrations (MPC's)

Water - covered in Section 1.A.Air - covered in Section 1.B.

3. Average energy of fission and activation gaseous effluents is not applicable. See ODCM Section3.1.2 for the methodology used in determining the release rate limits fro:n noble gas releases.

__

, .. - -- - .


4. Measurements and Approximations of Total Radioactivity

A. Liquid Efiluents

Liquid Release Sampling Method of Analysis Type of ActivityType Frequency Analysis

- P

1. Batch Waste Each Batch P.H. A. Principal Ganuna EmittersRelease Tank

P

Each Batch P.H. A. I-131

a. Waste Monitor Tank P P.H. A. Dissolved and EntrainedOne Batch /M Gases (Gamma

Emitters)

P L.5. H-3b. Secondarv Liquid Each Batch S.A.C. Gross Alpha

Waste MonitorP O.S L. St-89, Sr-90

Each Batch O.S.L. Fe-55

2. Continuous Releases Daily P.H.A. Principal Gamma EmittersGrab Sample i

1

|P.H. A. 1-131

a. Steam Generator M Dissolved and entrainedBloudown Grab Sample P.H.A. Gases (Gamma Emitters) .

!

|b. Turbine Building Daily L.S. H-3 |

Sump Grab Sample |4

l

S.A.C. Gross Alpha'

c. Lime Sludge Pond Daily O.S.L. Sr-89, Sr-90Grab Sample

;

i

O.S.L. Fe-55

P = prior to uch batch S AC. = scintillation a!phs counterM = monthly O.S.L = performed by an offsite laboratory

,LS. = Liquid scintillation detector P. IIA = gamma spectrum pulse height analysis using a iligh

j Purity Germanium detector

1

L

j +

- -

. _


Section IISupplemental Information

,

Facility: Wolf Creek Generatine Station License Number: NPF-42

1. ODCM Limits

A. For liquid waste effluents

A.1 The concentration of radioactive material released in liquid effluents toUNRESTRICTED AREAS shall be limited to the concentrations specified in 10CFR20,Appendix B, Table 11, Cohimn 2, for radionuclides other than dissolved or entrainednoble gases. For dissolved or entrained noble gases, the concentration shall be limitedto 2 x 10 -4 microCuric/mi total activity.

A.2 The dose or dose commitment to MEMBER OF THE PUBLIC from radioactivematerials in liquid emuents released, from each unit, to UNRESTRICTED AREAS shallbe 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.

B. For caseous waste efnuents

B.1 The dose rate due to radioactive material released in gaseous ellluents fro the site to areaat and beyond the SITE BOUNDARY shall be limited to the following: )a. For noble gases: Less than or equal to 500 mrems/yr to the whole body and less ' i

than or equal to 3000 mrems/yr to the skin, and )b. For lodine-131, lodine-133, tritium, and all radionuclides in particulate form

with half-lives greater thank 8 days: Less than or equal to 1500 mrems/yr to anyorgan. .

B.2 The air dose due to noble gases released in gaseous effluents, from each unit, to areas at -Iand beyond the SITE BOUNDA.RY shall be limited to the following:a. During any calendar quarter: Less than or equal to 5 mrads for gamma

radiation and less than or equal to 10 mrads for beta radiation, and |

b. During any calendar year: Less than or equal to 10 mrads for gamma radiationand less than or equal to 20 mreds for beta radiation.

B.3 The dose from Iodine-131, lodine-133, tritium, and a radionuclide in particulate formwith half-lives greater than 8 days in gaseous effluents released to area at and beyondthe SITE BOUNDARY shall be limited to the following:a. During any calendar quarter: Less than or equal to 7.5 mrems to any organ,

andb. During any calendar year: Less than or equal to 15 mrems to any organ.

2. Maximum Permissible Concentrations (MPC's)

Water - covered in Section 1 A.Air - covered in Section 1.B.

3. Average energy of Ossion and activation gaseous effluents is not applicable. See ODCM Section3.1.2 for the methodology used in determining the release rate limits from noble gas releases.

|q ]>

|

Enclosure to WO 94-0035 -Page 16 of 31

4. Measurements and Approximations of Total Radioactivity 'j1

A. Liquid Effluents

ui

Liquid Release Sampling Method of Analysis Type of Activity -Type Frequency Analysis

P

1. Batch Waste Each Batch P.H.A. Principal Gamma Emitters |

Release Tank ||P

Each Batch P.H.A. 1-131

a. Waste Monitor Tank P P.H. A. Dissolved and EntrainedOne Batch /M Gases (Gamma

Emitters)

F L.5. H-3b. Secondary Liquid Each Batch S.A.C. Gross Alpha

Waste Monitor i'

P O.S.L. St-89, Sr-90Each Batch O.S.L. Fe-55

2. Continuous Releases Daily P.H. A. Principal Gamma EmittersGrab Sample :

P.H.A. 1-131

a. Steam Generator M Dissolved and entrainedBlowdown Grab Sample P.H.A. Gases (Gamma Emitters)

"-

b. Turbine Building Daily L.S. H-3Sump Grab Sample

S.A.C. Gross Alpha

c. Lime Sludge Pond Daily O.S.L. Sr-89, Sr-90Grab Sample

_

O.S.L. Fe-55

P = prior to each batch S AC. = scintillation alpha counterM = monthly O.S.L. a performed by an olisite laboratoryLS. = Liquid scintillation detector P.llA = gamma spectrum pulse height analysis using a 1ligh

Purity Gennanium detector

-

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~ Enclosure to WO 94-0035Page 17 of 31.

11. Gaseous Waste Effluents1

-1.

uGaseous, Release Sampling Frequency- Melhod of Analysis Type of Activity

'

Type Analysis-|

P P.H.A. Principal Gamma EmittersWaste Gas Decay Tank Each Tank

Grab Sample |

|1

Containment Purge or P P.H.A. Principal Gamma Emitters '

Vent Each Purge Grab Sample 1

Gas Bubbler and L.S. H-3 (oxide)

Unite Vent M P.H.A. Principal Gamma Emitters IGrab Sampic

Gas Bubbler and L.S. H-3 (oxide)s

Radwaste Building M P.H.A Principal Gamma EmittersVent Grab Sample

For Unit Vent and Continuous P.ll. A. 1-131- I

Radwaste BuildingVent release types I-131listed above

Continuous P.H. A. Principal Gamma EmittersParticulateSample

Continuous S.A.C. Gross AlphaComposite Particulate

Sample

Continuous O.S.L. Sr-89, Sr-90CompositeParticulate Sample

P = prior to each batch S.A C. = scintillation alpha counterM = monthly O S.L = performed by an offsite laboratoryL.S. = Liquid scintillation detector P.H.A. = gamma spectrum pulse height

analysis using a Iligh PurityGennanium detector

J

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.jl

1

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~ Enclosure to WO 94-0035''

Page 18 of 31

5. Batch Releases

A batch release is the discontinuous release ofliquid ellluent which takes place over a finiteperiod of time usually hours or days.

There were 75 gaseous batch releases during the reporting period. The longest gaseous batchrelease lasted 10,262 minutes, while the shortest lasted 16 minutes. The average release lasted1,009 minutes with a total gascous batch release time of 75,692 minutes..

There were 116 liquid batch releases during the reporting period, The longest liquid batchrelease lasted 249 minutes, while the shortest lasted 37 minutes. The average release lasted 102minutes with a totalliquid batch release time of 11,797 minutes.

s

6. Continuous Releases

A continuous release is a release of gaseous or liquid ellluent which is essentially uninterruptedfor extended periods during normal operation of the facility. 1

There were three liquid release pathways designated as continuous releases during this reportingperiod. They were the Steam Generator Blowdown, Turbine Birilding Sump, and Lime SludgePond. There were two gas release pathways designated as continuous releases. These were the 1

Unit Vent and Radwaste Building Vent. 'l~I!

1,

'

I|

~

!>

j

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_. ._ _ , _ . . . . . .. . ,

-|


lIEFFLUENT AND WASTE DISPOSAL ANNUAL REPORT (1993)

. SOLID WASTE SillPMENTS

A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fud) ;j

1. Type of waste Unit I- Year Est. TotalPeriod Error %

|a. Spent resins, filter sludges, m3* 15.78E+00

| craporator bottoms, etc. Ci 7.59E+02 2.50E+01

b. Dry compressible waste, m3* $3 00E+00contaminated equip. etc. Ci 2.61 E+00 2.50E+01

c. Irradiated components, m3+ 0.00E+00control rods, etc. Ci 0.00E+00 0.00E+00

d. Other m3* 0.00E+00Ci 0.00E+00 0.00E+00

m3* = cubic meters

| 2. Estimate of major nuclide composition (by type of waste)l

l| a.. Spent resin, Eller sludges, craporator bottoms, etc.

Nuclide PercentName Abundance Curi?c

Fe-55 50.439 7.70E+00| Co-58 25.751 3.93 E+06! Ni-63 11.751 1.79E+00

Co-60 10.462 - 1.60E+00

| H-3 1.056 1.61E-01Cs-137 .272 4.15E-02C-14 .265 4.04 E-02St-90 .004 6.60E-04Cm-242 .000 0.00E+00Pu-241 .000 0.00E+001-129 .000 0.00E+00Tc-99 .000 0.00E+00Nb-94 .000 0.00E+00Ni-59 .000 0.00E +00

l

L

|.I!

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

.~,

.3

' Enclosure to 'WO 94-0035Page 20 of 31

b. Dry compressible waste, contaminated equipment etc.

Nuclide - PercentName Abundance -. Curies

Fe-55 ~ 82% 2,16

Co-58 7% 0.20Co-60 6% 0.16NM3 5% 0.137 ,

c. Irradiated components, control rods etc.

none

d. Other

Done *

3. Solid Waste Disposition

Number of Shioments Mode of Transportation Destination6 Truck Barnwell

South Carolina|

..la

1

4. Class of Solid Waste

a. Class A, Class B, Class C- Corresponding to 2ab. Class A - corresponding to 2bc. Not applicable |

d. Not applicable..n

T pe of container5. 3

a. LSA (Strong, light), Type A, Type B - corresponding to 2a I

b. LSA (Strong, tight) - corresponding ,o 2bc. Not applicabled. Not applicable

d

, w w~ , _ . . . - , _. 4 v.-

.. . .- . . - .- . . - - .

. Enclosure to WO 94-0035~ Page 21 of_31,

"

6. Solidification Agent

a. Not applicableb. Not applicablec. Not applicabled. Not applicable

B. IRRADI ATED FUEL SHIPMENTS (Disposition)

There were no irradiated fuel shipments during this period.

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Enclosure to WO 94.0035 |

Page 22 of 31

Section III

; 110URS AT EACII WIND SPEED AND DIRECTION|-I All gaseous releases at the WCGS are ground level releases. The meteorategical data supplied in these ,

tables covers the period from January 1,1993, through December 31,1993, and indicates the number of (hours at cach wind speed and direction for each stability class. !

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- - -


IIOURS AT EACH WIND SPEED AND DIRECTION

PERIOD OF RECORD: Jan 1 - Dec 31,1993

STABILITY CLASS: A

ELEVATION: 10 Meters

;

Wind Wind Speed (mph) at 10m LevelD.irac1LQn 1-3 4-2 8-12 13-18 19-24 >11 TOTAL

N 5 9 10 4 1 0 29

NNE O O O O O O O

NE O O O O 0 0 0

ENE O O 3 0 0 0 3 i

E O 0 1 0 0 0 1

ESE O 2 3 0 0 0 5 )

SE 1 12 3 2 0 0 18

SSE O 4 12 0 0- 0 16

S 0 2 3 4 0 0- 9

SSW 0 0 0 1 0 0 1

SW 0 1 3 0 0 0 4

WSW 0 1 1 1 0 0 3

i

TV 1 1 4 2 0 0 8

|

WNW 0 1 1 0 0 0 2

NW 0 1 3 2 0 0 6 )NNW 0 3 10 17 3 2 35

VARIABLE 0 0 0 0 0 0 0

TOTAL 7 37 57 33 4 2 140

IPeriod of calm (hours): 22

'

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_ _ ._ , , ..

.. . . . . - -. . _ . - . = .- _-- -

Enclomre to WO 94 0035Page 24 of 31

HOURS AT EACH WIND SPEED AND DIRECTION


STABILITY CLASS: B


Wlud Wind Spee 1 (mph) at 10m LevelDirection M M El4 13-18 J3-jl4 >lt IRTAL

N 32 70 135 87 21 0 345

NNE O O O O O O O

NT 0 0 2 0 0 0 2

ENE O 1 3 4 0 0 8

E O O O 2 1 0 3

ESE O 3 2 4 1 0 10

SE O 12 13 13 2 0 40

SSE 2 8 36 11 1 0 58

S 1 5 18 31 6 0 Gl' i

SSW 2 4 10 2 5 0 23 ]'

SW 2 6 11 0 0 0 19

|

WSW 0 10 15 4 0 0 20

W 2 7 8 6 0 0 23

WNW 2 0 18 20 14 0 63 |

NW l 8 40 50 20 4 123

NNW 7 17 47 56 23 1 151

VARIABLE O O 0 0 0 0 0

TOTAL. 51 100 358 290 94- 5 958

Period of calm (hours): 0

_ _ _-_ _ .- . _.

. ... . . . -. . _ . .. - - -. . - -.

Enclosure to WO 94-003$Page 25 of 31

HOURS AT EACil WIND SPEED AND DIRECTION;


STABILITY CLASS: C


1

Wind Wind Speed (mph) at 10m LevelDirectinn 1-3 1-1 E12 13-18 1E14 12_4 TOTAL

N 5 56 93 37 8 1 200

NNE O O O O O O O

NE O 2 5 0 0 0 7

ENE O 4 7 11 0 0 22

E O 2 5 2 1 0 10

ESE O 4 6 1 0 0 11

1SE O 3 6 6 0 0 15 '|4

SSE O 7 14 6 0 0 27

S 0 2 19 35 9 0 65'

lSSW 2 1 13 15 7 0 38 -)

.i

SW 2 3 4 0 0 0 0 I

:|WSW 0 1 2 0 0 0 3 |

!W 1 3 5 1 0 0 10 1

l

WNW 0 2 4 7 0 2 15 l

NW 0 4 21 10 5 7 47

NNW 3 6 19 16 22 1 67

VARIABLE O O O O O O O

TOTAL 13 100 223 147 52 11 546


. . _ . _ . . . ...

__. . _ . _ . __ . . . . .




STABILITY CLASS: D


Wind ' Wind Speed (mph) at 10m LevelDirection 1-4 4-1 8-12 13-18 19-24 >jM TOTAL_

N 31 160 230 103 23 1 54F

NNE O O 3 0 0 0 3

NE 5 6 2 1 0 0 14

ENE l '' 17 6 2 0 1 36

E 9 22 19 4 0 0 54 ,

ESE 4 27 16 5 0 0 52

SE 5 20 41 16 0 0 82

SSE 4 36 93 48 9 0 190

S 4 28 116 106 47 6 307,

SSW 0 24 89 94 21 2- 230

SW 5 37 33 15 1 0 91

WSW 6 19 26 13 2 0 66

W 4 20 34 17 3 2 80

WNW 3 16 26 14 2 3 64

NW 3 19 42 31 7 2 104

NNW 4 40 52 61 16 2 175

VARIABLE O O O O O O O' i

!

TOTAL 97 491 828 530 131 19 2006

Period of calm (hoursi: 2

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Enclosure to WO 944)035Page 27 of 3i



STABILITY CLASS: E


Wind Wind Speed (mph) at 10m Level_

Dittet19n 1-3 1-1 8-13 13-18 19-24 >jl4 TOTAL,

|N 113 301 177 85 21 2 699

NNE 1 4 1 0 0 0 6

NE 6 4 2 0 0 0 12

ENE 17 10 3 1 0 0 31

E 4 22 6 2 0 0 34

ESE 9 56 36 6 0- 0 -107

SE 12 70 69 16 0 0 167

SSE 10 82 203 130 32 1 458i

S 7 87 245 253 79 12 683

SSW 10 60 144 107 23 1 345

SW 7 56 34 11 1 0 109

WSW 7 25 22 9 1 1 65

W 4 35 50 12 4 1 106

WNW G 31 41 16 8 0 102

NW 4 48 61 69 23 .0- 205,

NNW 11 72 89 73 21 5 271


TOTAL 228 063 1183 790 213 23 3400


. . . - - - .

Enclosure to WO 94-0035' Page 28 of 31

HOURS AT EACII WIND SPEED AND DIRECTION


'

STABILITY CLASS: F.


Wind Wind Speed (mph) at 10m Level.pirection 1-3 4_-2 8-12 13-18 19-24 >14 TOTALS

N 43 111 45 1 0 0 200

NNE O 3 0 0 0 0 3

NE 6 2 0 0 0 0 8

EhT 7 IG 2 0 0 0 25

E 4 13 4 0 0 0 21

ESE 5- 41 5 0 0 0 51

SE 5 58 18 1 0 0 82

SSE 5 40 42 4 0 1 92

S 2 32 50 12 3 0 09 j

SSW 5 25 16 4 0 0 50. .|

SW 5 37 3 0 0 0 45 I

WSW 3 8 1 0 0 0 12

W 0 9 3 0 0 0 12

WNW 2 17 7 0 0 0 26

NW 8 37 20 1 0 0 66 1

NNW 7 37 23 0 0 0 67


TOTAL 107 486 239 23 3 1 859


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STABILITY CLASS: G


Wind Wind Speed (mph) at 10m Level '

Direction 1-a 1-2 8-12 13-18 19-24 >24 TOTAL

N 19 70 47 15 1 0 122 ,

NNE O 4 0 0 0 0 4

NE O 1 0 0 0 0 1

ENE 1 5 0 0 0 0 6 ,

E 1 19 4 0 0 0 24:

ESE 2 18 1 0 0 0 21

SE 2 20 0 0 0 0 22

SSE I 10 2 1 0 0 14

i

S 1 7 1 5 0 0 14

SSW 1 8 6 0 0 0 15 -|.)

SW 1 5 0 0 0 0 6

WSW 0 0 0 0 0 0 0

W 0 2 0 0 0 0 2

WNW 1 4 1 0 0 0 6|

STV 3 18 7 0 0 0 28

NhTV 2 11 4 5 0 0 22


i

TOTAL 35 202 43 26 1 0 307-


_ _ . _- . _ _ . _

Enclosure to WO 9441035Page 30 of 31



STABILITY CLASS: ALL

EL.EVATION: 10 Meters

Wind Wind Speed (mph) at 10m LevelDirection M M E-12 13-18 1E34 >23 TOTAL_

N 248 777 707 332 75 4 2143 ;

NNE I 11 4 0 0 0 16

NE 17 15 11 1 0 0 44

ENE 35 53 24 18 0 1 131.

E 18 78 39 10 2 0 147

|

ESE 20 151 69 16 1 0 257 .

l

SE 25 195 150 54 2 0 426

SSE 22 187 402 200 42 2 855

S 15 163 452 446 144 18 1238;-

SSW 20 122 278 223 56 3 702 ,

SW 22 145 88 26 2 0 283

WSW 16 64 67 27 3 1- 178

W 12 77 104 38 7 3 241

WNW 14 80 98 57 24 5 278

NW 19 135 194 163 55 13 579

NNW 34 186 244 228 85 11 788

VARIABLE O O O O O O 0

TOTAL 538 2439 2931 1839 498 61 8306


Hours of missing data: 368

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. .. _ , _ __ _. .

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. Section IVi

Additional Information.

1. Unplanned or Abnonnal Releases -

'There were no unplanned or abnormal releases during this time period.

2. Offsite Dose Calculation h1anual (ODCht)

Offsite Dose Calculation hianual , Revision 11, was approved this reporting period by the Plant - :

Safety Review Committee on December .22,1993. A complete copy of the revised ODCM isprovided in Attachment 2.

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3. hiajor Changes to Radwaste Treatment Systems

No plant modification to the radwaste treatment systems are currently reponable.

4. Land Use Census

There were no new location for dose calculation identified during this report period. +

5. Radioactive Shipment j

There were six shipments of radioactive radwaste during this report period. Six shipments wereto Barnwell. South Carolina. All six shipments were by truck. ,

,

6. Inoperability of Efiluent hionitoring Instrumentation

There were no events that irecolved inoperable liquid or gaseous effluent monitoringinstrumentation not being corrected within the time specified in Technical Specification3.3.3. I 1.

*

7. Storage Tanks i

There were no events leading to liquid holdup tanks or gas storage tanks exceeding the limits of jTechnical Specification 3.11.1.4 or 3.11,2.6. ;

:

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Attachment 1

Attachment 1 provides actual values to replace the estimated values for liquid emuents provided inSemiannual Radioactive Emuent Release Report 16. New values are denoted by bold face type,

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-- , y m. ,, . , , ,--- - '. - - - . ~ v s - -

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Section I

Report of Radioactive Ellluents (1992): Liquid

Lpe of Efilugn_t 1J. nil Qnarter 3 Ouarter 4

A. Fission and Activation Products1. Total Release (not including tritium, gases, alpha) Ci 8.15E-02 5.5 t E-02 (4) -2. Average Diluted Concentration During Period uCihul 2.05E-08 1.67E-083. Percent of Applicable Limit (1) % 1.70E+00 1.10 E+00 .

B. Tritium1. TotalRelease Ci 1.50E+02 1.70E+022. Average Diluted Concentration During Period uCi/mi ~ 3.62E4)5 5.13E-053. Percent of Applicable Limit (2) % 1.21E+00 1.71E400

.

,

C. Dissolved and Entrained Gases1. Total Release Ci 1.63E412 1.37E-01

2. Average Diluted Concentration During Period uCi/mi 3.93E-09 4.14E-083. Percent of Applicable Limit (3) % 1.97E-03 . 2.70E-02

D. Gross Alpha Radioactivity -

1. Total Release Ci - 1.02E4)5 9.89E-06 - ,

E. Volume of Waste Release (prior to dilution) Liters 8.74 E+05 1.38E+08

F. Volume of Dilution Water Used Liters 4.15E+09 3.17E+09

1. The applicable limit for the Wolf Creek Generating Station is 5 Curies per year. (Reference 10 CFR 50,Appendix 1, " Guides on Design Objective For Light-Water-Cooled Nuclear Power Reactors," paragraph A.2). Thevalue printed here is derived by dividing the total release Curies by 5 Curies and then multiplying the result by 100.

2. This value is derived by the following fannula:% ofApplicable Limit (Average Diluted Concentration)(100)=

(MPC, Appendix 11, Table 1110CFR20) '

3. This value is derived by the following formula:% of Applicable Limit (Averace Diluted Concentration)(100)=


4. Curies in the Fotuth Quarter are based on the October composite Fe-55 values, and the Third Quartercomposite Sr-89 and Sr-90 values. Estimated values for the Fourth Quarter have now been replaced with actualcomposite results.

.

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- . . , , - . - . , . . . # . _ . . - - . , .._.--1

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LIQUID EFFLUENTS (1992)

Continuous Release Batch ModeNitelidsBelcasgd 11.nli Ouarter 3 Ouarter 4 Ouarter 3 Quarter 4

'H-3 . Ci 1.40E-05 9.75 E-03 1.50E+02 1.70E+02Cr-51 Ci 0.00E+00 0.00E+00 0.00E+00 9.07E-05Mn 54 Ci 1.04E-07 <6 85E-02 7.35E-04 8.10E4)4Fe-55 Ci <4.92E-06 <l .37E-01 3.47E-02 2,79E-02 (1)Fe-59 Ci <2.46E-06 <6.85 E-02 <4.35E-04 <3.79E-04Co-57 Ci 0.00E+00 0.00E+00 3.73 E-04 9.44E-05Co-58 Ci 3.56E-07 <6.85E-02 1.47E-02 1.34E413Co-60 Ci 1.19E-06 <6.85E-02 1.79E-02 1.53E-02Zn-65 Ci <2.46E-06 <6.85E-02 <4.35E-04 <3.79E-04Sr-89 Ci <2.46E4)7 <6.85E4)3 1.65E4)3 <3.79 E-05 (1)Sr-90 Ci <2.46E-07 <6.85 E-03 4.61 E-05 4.01E-06 (1)Nb-95 Ci 1.17E-07 0.00E+00 2.55E-04 0.00E+00

Mo-99 Ci <2.46E-06 <6.85E-02 <4.35 E-04 <3.79E 04Te-99M Ci 0.00E+00 0.00E+00 1.06E-04 0.00E+00Ag-110M Ci 0.00E+00 0.00E+00 1.76E-04 2 06E-04Sn 113 Ci 0.00E+00 0.00E+00 0.00E+00 7.27E-06Sb-124 Ci 0.00E+00 0.00E+00 2.98E-05 0.00E+00Sb-125 Ci 3.50E-07 0.00E+00 1.01E-02 7.09E-031-131 Ci <4.92E-06 <l .37E-01 <3.69E-04 1.69E-04Cs-134 Ci 3.23 E-07 <6 85E-02 1.61E-03 6.82E-04Cs-137 Ci 3.12E-07 <6.85E-02 1.65E-03 6.70E4)4La-140 Ci 0.00E400 0.00Et00 1.79E-04 0.00E+00Ce-141 Ci <2.46E-06 <6.85E-02 <4.35E-04 <3.79E-04Ce-144 Ci 1.40E-07 <6.85E-02 9.09E-04 6.89E-04

GROSSALPHA Ci <4.92 E-07 <l.37E-02 3.02E4)5 9.89E-06Ar-41 Ci <4.92E-05 <! 37E+00 <8.69E-03 <7.57E-03 -|%-85 Ci <4.92E-05 <l.37E+00 <8.69E-03 1.21E-01Kr-85M Ci <4.92 E-05 <l.37E+00 <8.69E4)3 <7.57E-03Kr-87 Ci <4.92E-05 <l .37F+00 <8.69E-03 <7.57E-03Kr-88 Ci <4.92 E-05 <l .37E+00 <8.69E-03 <7.57E-03Xe-131M Ci <4.92E-05 <l.37E+00 <8.69E-03 1.92E-03Xe-133 Ci <4.92 E-05 < l.37E+00 1.62E-02 1.41E-02Xc-133M Ci <4.92E-05 <l .37E+00 <8.69E-03 4.42E-05Xe 135 Ci ' <4.92E-05 <l .37E+00 5.81E-05 7.34E415Xe-135M Ci <4.92E-05 < l .37E+00 <8.69E-03 <7.57E-03

NOTE: Less than values are calculated using the lower limit of detection (LLD) values listed in Table 2-1 of theODCM multiplied by the volume of waste discharged during the respective quarter.(1) The Fe-55 value for the Fourth Quarter is based on the October monthly composite value. The Sr.89 and St-90values for the Fomth Quarter are based on the Third Qwtrter composite values. Estimated values for the Fourth ,

Quarter have now been replaced with actual composite results. |

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!

LIQUID CUMULATIVE DOSE SUMMARY (1992)TABLE 1

ODCM CALC. DOSE ODCM LIMIT (1) % OF LIMIIQuarter 1 of 1992 i

TOTAL DOSE (mrem) FOR BONE 3.22E-02 5.00E+00 6.44E411

TOTAL DOSE (mrem) FOR LIVER 7.46E-02 5.00E+00 1.49E+00' TOTAL, DOSE (mrem) FOR TOTAL BODY 6.01E-02 1.50E +00 4.01 E+00

TOTAL DOSE (mrem) FOR TilYROID 1.68E4)2 5.00E+00 3.36E-01

TOTAL DOSE (mrem) FOR KIDNEY 3.58E4)2 5.00E+00 7.16E-01TOTAL DOSE (mrem) FOR LUNG 2.33E4)2 5.00E+00 4.66E-01TOTAL DOSE (mrem) FOR GI-LLI 5.03 E-02 5.00E+00 1.01 E+00 .

Quarter 2 of 1992TOTAL DOSE (mrem) FOR BONE 3.91E-03 5.00E+00 7.82E-02TOTA.L DOSE (mrem) FOR LIVER 1.83E-02 5.00E+00 3.66E-01

TOTAL DOSE (mrem) FOR TOTAL BODY 1.66E-02 1.50E+00 1llE+00TOTAL DOSE (mrem) FOR THYROID 1.16E-02 5.00E+00 2.32E-01

TOTAL DOSE (mrem) FOR KIDNEY 1.38E412 5.00E+00 2.76E-01TOTAL DOSE (mrem) FOR LUNG 1.24E-02 5.00E+ 00 2.48E-01

TOTAL DOSE (mrem) FOR GI-LLI 1.34E-02 5.00E+00 2.68E-01'

Quarter 3 of 1992TOTAL DOSE (mrem) FOR BONE 1.06E4)2 5.00E+00 2.12E-01

TOTAL DOSE (mrem) FOR LIVER 2.76E-02 5.00E+00 5.52E411

TOTAL DOSE (mrem) FOR TOTAL BODY 2.35 E-02 1.50E+00 1.57E+00

TOTAL DOSE (mrem) FOR THYROID 1.06E4)2 5.00E+ 00 2.12E-01

TOTAL DOSE (mrem) FOR KIDNEY 1.62E-02 ' 5.00E+00 3.24E-01

TOTAL DOSE (mrem) FOR LUNG 1.26E-02 5.00E+00 2.52E-01


Quarter 4 of 1992 (2)TOTAL DOSE (mrem) FOR BONE 4.79 E-03 5.00E+00 9.5N E-02

TOTAL DOSE (mrem) FOR LIVER 2.45E-02 5.00E+00 4.90 E-01

TOTAL DOSE (mrem) FOR TOTAL BODY 2.24 E-02 1.50E+00 1.49E400TOTAL DOSE (mrem) FOR THYROID 1.65E-02 5.00E+00 3.30E-01

TOTAL DOSE (mrem) FOR KIDNEY 1.88E-02 5.00E400 3,76E-01

TOTAL DOSE (mrem) FOR LUNG 1.71 E-02 5.00E+00 3.42E-01TOTAL DOSE (mrem) FOR GI-LLI * 1.82 E-02 5.00E+00 *3.64 E-01

TOTALS FOR 1992TOTAL DOSE (mrem) FOR BONE 5.16 E-02 1.00E+01 5.16 E-01

TOTAL DOSE (mrem) FOR LIVER * l.45 E-01 1.00E+01 *l.45E+00TOTAL DOSE (mrem) FOR TOTAL DODY a l.23 E-01 3.00E+00 *4.10 E+00

TOTAL DOSE (mrem) FOR THYROID 5.55E-02 1.00E+01 5.55 E-01

TOTAL DOSE (mrem) FOR KIDNEY 8,46E-02 1.00E+01 8.46E411

TOTAL DOSE (mrem) FOR LUNG 6.54 E-02 1.00E+01 6.54 E-01

TOTAL DOSE (mrem) FOR GI-LLI *9.82 E-02 1.00E+01 *9.82 E-01

1. Based on ODCM Section 2.2 whi h restricts dose to the whole body to less than or equal to 1.5 rnrem per quarter and 10 mrem peryear. Dose restriction to any wgan is less than or equal to 5 mrem per quarter and 10 mrem per year.2. De calculated doses for the fourth Quarter of 1992 given above ar e based on the October l'e.$5 composite resuhs, and the ThirdQuader St-89 and Sr-90 composite results. Estimated vehics for the Fourth Quar 1er hase now been replaced with actual compostteresults.* 1 here were na algumcant thangen to these Salues and they are therefore reported the same as the values in iteport 16.

_ _ _ _ __ _ _ _ _ _ _ _ ___ _ _

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

|

LIQUID CUMULATIVE DOSE SUMMARY (1992)TABLE 2

_ Quarter 1 Ouarter 2 Ouarter 3 Quarter 4 TOTAL

A. Fission and Activation Products(not including H-3, gases, alpha)

1. Total Release-(Ci) 1.19E-01 3.23E4)2 8.51E-02 5.51E-02 2.92 E-01

2. hLuimum Organ Dose (mrem) 5.78E-02 6.70E-03 1.69E-02 8.40E-03 *8 98E-02.

3. Organ Dose Limit (mrem) 5.00E+00 5.00E400 5.00E+00 5.00E+00 1.00E+01

4. Percent of Limit 1.16E+ 00 1.34E-01 3.38E-01 ' 1.68E-01 *N 98E-01

B. Tritium

1. Total Release -(Ci) 1.01E+2 3.01E+01 1.50E+02 1.70E+02 4.51E+02

2. Maximum Organ Dose (mrem) 1.68E-02 1.16E-02 1.07E-02 1.61E-02 5.52E-02

3. Organ Dose Limit (mrem) 5.00E+00 5.00E+00 5.00E+00 5.00E+00 1.00E+01

4. Percent of Limit 3.36E-01 2.32E-01 2.14E-Ol 3.22E-01 5.52E-01

'lhis table is included to show the correlation between Curies released and the associated calculated maximmn organdose. Wolf Creek OlX'M methodology is used to calculate the maximum organ dose ahich assumes that anindividual drinks the water and eats the nsh from the discharge point. OIX'M Section 2.2 organ dose limits are used.The less thtm values are not included in the summation for the total release values.

NOTE- The Fourth Quarter Category A values were calculated based on the October Fe-55 composite result, andthe Third Qua;ter Sr-89, Sr-90, composite results. Also the Second Quarter Category A values given above ditTer ifrom the values reported in Semiannual Radioactive Efiluent Release Report 15 due to adjustment for Fe-55, St-89,and Sr-90 composite data. Estimated values for the Fourth Quarter have now been replaced with actualcompoilte results.* There were no signlHcant changes to these values and they are therefore reported the same as the values inReport 16.

_ . t -

,s& 6 A . x _ .an o-+s- -.aa n = a t-,+a a m.= 1- .a m- m ~m -.m -re.s a ma u - = n .--;..

Attachment 2

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I

utrdnt; DOSE CAILEATICH MANUALi'

for

Wolf Cmek Nuclear Operating CorporationWolf Cmek Generating Station

Revision 11

NCCH-2

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APPROVED BY DATE: N i?Manacer Chanist)y '/

Y //hWA /)A $~ DATE: /2-DDA3APPROVED BYPSRC

APPROVED BY /Av6e DATE: /?- 7 @7-

5Vice Pmsident 11 ant Operations9 04 /95

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TABLE OF 00tEDES

Pace

1.0 INIRODUCTION 1

2.0 LIQUID EFFIUDES 12.1 00tCENIRATICN - CCMPLIAtCE WrIH 10 CFR 20 12.2 DOSE - C W PLIAICE WPIH 10 CFR 50 APPENDIX I 72.3 PRQ7 TTED DOSE 9

' 2.4 INSTRW ENITEION 10

3.0 GASEQUS EFF WENTS 263.1 DOSE RATE - COMPLIA?CE WTIH 10 CFR 20 273.2 - DOSE - CCHPLIANCE WPIH 10 CFR 50 APPDIDIX I 333.3 PROJETED DOSE 423.4 INSTRWDEATICN 43

4.0 'IUTAL DOSE 614.1 RmEDIAL ACTION 614.2 SURVEILIRCE REQUIREMENIS 61

,

5.0 RADIOWGICAL EtWIROtNENTAL FONTIORUG PROGRAM 625.1 NONTIORDG PROGRAM 625.2 IAND USE CD1 SUS 625.3 INTERIABORA'IORY CCNPARISON PROGRAM 635.4 REPORTDG RDQUIREMDES 63

6.0 BASES 81

7.0 REPORTS 897.1 ANNUAL RADIOWGICAL DWIRONMDEAL OPERATDG ,

REPORT 897.2 ANNUAL RADIOACTIVE EFFLUDE RELEASE REPORT 89 |

APPENDIX A: DOSE CONVERSION F.2CDOR TAEES A-1

APPENDIX B: METEORO WGICAL 10 DEL B-1

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9/93

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LISP & TABLES'Ibble Ibae

2-1 RADIOACTIVE LIQUID NASTE SAMPLD G AND ANALYSIS PROGRAM 3

2-2 RADIOACTIVE LIWID EFFLUENT MONI7mDG DGIRUEffATIN 11

2-3 RADIOACf1VE LIQUID EFFLUENT NCNPIIRDG INSTRUEffATIONSURVEILLANCE RDQUIREMENIS 14

3-1 RADIOACf1VE GASEOUS WASTE SMFLUG AND ANALYSIS PROGRAM 30

3-2 RADIOACfIVE GASEQUS EFFLUDir NONfitRDG INSTRUMENIATION 45

3-3 RADIOACTIVE GASEOUS EFFwENT FINFICRDG INSURIEDTIATIONSURVEILIRGE R10UIREMDTTS 48

5-1 RADIGILGICAL DNIRONME!TTAL FDfITIRDG PROGRAM 65

5-2 SAMPLDU IOCATIN NUMBERS, DISTANCES (MILES) AtoDIRECTIONS 71

5-3 DETECTION CAPABILITIES FTR DWIRONMENIAL SAMPLE ANALYSIS 72

5-4 REaumNG LEVELS FIR RADIOACTIVITY CONCENIRATIGG INDNIRCNEffAL SMFLES 75 !

|

A.1-1 BIOACCORATION FACIORS 70 BE USED IN 711E ABSDGEOF SITE SPECIFIC DATA A-2

A.1-2 DOSE FACIORS FIR NOBLE GASES AtO DAIGTTERS A-3

A.2-1 INHALATIN DOSE FACIORS FOR ADULTS A-4

A.2-2 INilAIATION DOSE FACIORS FOR TEENAGERS A-7.

:

A.2-3 DelAIATION DOSE FACICES FOR OIIID A-10 l

A.2-4 INIIAIATION DOSE FAC; ORS FTR INFANP A-13'i

A.2-5 FXTERNAL DOSE FAC70R FtR STA!GUG ON COtifAMINATEDGROUND A-16 j

A.3-1 HUESTION DOSE FACIm FOR ADUL'IS A-18

A.3-2 INGESTION DOSE FACIOR FIR TEENAGERS A-21

A.3-3 DGESTION DOSE FACIOR FOR OIIID A-24

A.3-4 DGESTION DOSE FACIOR FCR UFANT A-27

A.3-5 STABLE ELDeff TRANSFER DATA A-30

_113/91

LISP T TME2STable Rxp

A.4-1 SITE REIATED DGESTION DOSE COMIHERf FOR ADULT A-31

A.4-2 SITE RIIATED DGESTICN DOSE COMIDENP FMIOR IMTEENAGER A-34

A.4-3 SITE RELATED DUESTION DOSE COMI'IMENT FACIOR FOR OfILD A-37

A.4-4 SITE RELATED DGESTION DOSE COMI'IMENT FACIOR Em INFANT A-40

A.5-1 DalAIATION DOSE PARAMDTER FOR 'IHE CHIID A--43

A.5-2 INHAIATION PAHiWAY FAC'IOR FOR ADULT (RI F1CIOR) A-44

A.5-3 DEAIATION PA'IliRY FACIOR FOR TEENAGER (RI FICIOR) A-47

A.5-4 INHAIATION PA'IHRY F1CIm EM CHIID (RI FAC'IOR) A-50

A.5-5 HalAIATICN PAHlWAY F1CIOR FOR INFANT (RI FACIOR) A-53

A.5-6 GRASS-CON-MIII PATIiWAY F1CIM ADULT (RI FACIOR)OF SITE SPECIFIC DATA A-56

A.5-7 GRASS-CON-MIIE PA'IEWAY FICIOR TEEN (RI FICIOR) A-59

A.5-8 GRASS-CON-MIIE PA'11MY F1Clm CHIID (RI Factor) A-62

A.5-9 GRASS-CON-EUR PA'IHNAY FICIOR INFANT (RI FACIOR) A-65r

A.5-10 GRASS-COW-MEAT PA'IliWAY FAClm ADULT (RI Factor) A-68

A.5-11 GRASS-(XM-MEAT PAHIRY FACIOR TEEN (RI FICIOR) A-71

A.5-12 GRASS-COW-MFAT PADIRY F1CIOR INFANT (RI FACIOR) A-74 )i

A.5-13 VEUETATION PATIiWAY F1CIOR ADULT (RI FACIOR) A-77

A.5-14 VEGETATION PA'111WAY FACIOR TEEN (RI F1CIOR) A-80

A.5-15 VEGEIATION PAHEY F1CIOR CHIID (RI F1CIOR) A-83

A.5-16 GROUND PIANE PAHIRY F1CIOR (RI FICIOR) A-86

A.5-17 GRASS-GCAT-MIIE PA'IllWAY F1CIOR ADULT (RI F1CICR) A-87

A.5-18 GRASS-GOAT-MIII PA'IllWAY FACIOR TEEN (RI F1LM) A-90

A.5-19 GRASS-GCAT-MIIE PATIMY FICIOR CHIID (RI FACIOR) A-93

A.5-20 GRASS-GOAT-MIII PADIWAY F1CIOR INFANT (RI FACIOR) A-96

-111-

_ _

IJSP T FIGIIES

Fiqure Jhoo

2.1 BOUNDARY KR LIQUID EFFIDENIS 25

3.1 BOUNDARY KR GASECUS EFFUJEtus 60

5.1 AIRBORNE PATEDRY SAMPLlN3 IOCATIGE 76

5.2 DIRECT RADIATION PA'D5&Y SAMPLDG IDCATIONS 77

5.3 WATERBORNE PAMMAY SAMPLUG LOCATIONS 78

5.4 DGESTION PA35&Y SAMPIJPG IOCATIGE 79

5.5 DISTANT SAMPLDU IOCATIONS 80

B-1 VERTICAL S'IANDARD DEVIATION OF MATERIAL IN A PLUME B-4

B -2 PLUME 'IRAVEL DISTAIGE VERSUS FRALTICN RDRINDG IN B-5PLUME

B-3 PUJME TRAVEL DISTANCE VERSUS RELATIVE DEPOSITICN RATE B-6

-iv-

3/91

1.0 INnuxx;nCN

% e Offsite Dose Calculation Manual describes the RadioactiveEffluent Centrols F w pmu. % e impl m entation of this programensures empliance with the requirments of 10 CFR 50.36,10 CFR20.106, 10 CFR 50 Appendix I and 40 CFR 190.

On January 1, 1994, 10CFR20.1001-20.2402 shall be implmented.Wolf Creek will continue to maintain the existing level ofeffluent control (10CFR20.106) to cmply with the new require-ments. %is method of ccmfinnce has been determined by the NRCto be AIARA.

We ODCM describes the methodology and parameters used in thecalculation of offsite doses due to radioactive liquid and

;

gaseous effluents. % e CDCM contents for calculation of dose arebased on " Preparation of Radiological Effluent Technical Speci-fications' for Nuclear Power Plants (NUREG-0133)," and RegulatoryGuide 1.109, Revision 1.

%e ODCM provides the limitations on the operability of radio-active liquid and gaseous monitoring instrumentation includingsurveillance tests and setpoint determination. Each SurveillanceRequirment shall be perfomed within the specified surveillanceinterval with a mwimm allowable extension not to exceed 25% ofthe specified interval.

he ODCM provides the Radiological Enviremental Nonitoring Pro-gram. %e supmu consists of m:nitoring stations and sampling !

pupaum designed to confirm the dose estimates made under nonnali

or accident conditions, and conform to NRC requirements in 10 CFR jPart 50. 1

I%e ODCM provides descriptions of the infoImation that should be - -!included in the Annual Radiological Environmental Operating andAnnual Radioactive Effluent Release Reports.

2.0 IJOLTID EFFTUFNIS

2.1 Oc umLuition - Compliance With 10 CPR 20

me concentration of radioactive material released in liquid ef-fluents to UNRESTRICfED AREAS (see Figure 2.1) shall be' limitedto the concentration specified in 10 CFR Part 20, Appendix B,Table II, Column 2, for radionuclides other than dissolved orentrained noble gases. For dissolveci or entrthe m ncentration shall be limited to 2 x 10 p ed noble gases,microcurie /mltotal activity.

2.1.1 Itsnodial Acti90

With the mncentration of radioactive material released in liquideffluents to UNRESTRICTED AREAS ex*ing the above limits, im -mediately restore the concentration to within the above limits.

ODCM 1

12/93.

2.1.2 Surveillance arrmimaents

'Ib show emn14ance with this requimient, cancentrations of ac-tual liquid effluents will be detennined by performing IsotopicAnalyses. Radioactive liquid wastes shall be sampled andanalyzed according to the namniing and analysis program of Table-

2-1.

,

ODCM 2

3/91

__

TMER 2-1i

RADIOACTIVE LIQUID WASTE SAMPLDG AND AIRLYSIS PROGRAM

IDER LIMITOF DEI'ECTION

MINDM (1)LIQUID RELEASE SAMPLDG ANALYSIS TYPE OF JC1'IVITY (LLD)

TYPE FREQUENCY FREQUDCY ANALYSIS (uCi/ml)

1. Batch Wasta P PRelease Each Batch Each Batch Principal Camn 5x10~7

(2) (3)Tanks Dnitters

I-131 1x10-6a. Waste

Monitor P M Dissolved and -5Tank One Batch /M Entrained Gases 1x10(Ganina Dnitters)

b. SecondaryLiquid P M (4) H-3 -5Waste Mon- Each Batch Couposite 1x10itor Tank

Gross Alpha 1x10-7

P Q (4) Sr-89, Sr-90 ,

Each Batch Canposite 5x10~0 ||

Fe-551x10-6

2. Continuous (6) W (4) Principal Ganna~7

(5) Daily Camposite (3) 5x10Releases Grab Sample Dnitters

I-1311x10-6

SteamGenerator M M Dissolved andBlodown Grab Sample Entrained Gases 1x10~0 !

(Gantna Dnitters)

M (4) H-3(6) Canposite 1x10-5

Daily |

Grab Sample Gross Alpha |-

1x10~' '

|

(6) Q (4) Sr-89, Sr-90Daily Canposite 5x10~8 '

Grab SampleFe-55 -61x10

CDCM 3

3/91'

_ _ _

,

|

9mBIR 2-1 (Orttinued)

TABLE ?DIATIONS |1

)(1) %e IID is defined, as the smallest concentration of radio- |

active material in a sample that will yield a net count, above i

Isystem background, that will be detected with 95% probabilitywith only 5% prnM bility of falsely concluding that a blarjc !

observation represents a "real" signal.

For a particubr masurement systen, which my include radio-chenical separation |

4.66 sb '

IID = i

E * V * 2.22 x 106 . Y * DecayWhere:

IID = the "a priori" lower limit of detection (microCuries perunit m ss or volume),

the starxiard deviation of the background counting rates =b or of the counting rate of a blank sample as

/ LTapp us iate, (counts per minute), s =

B = background sum (counts)bwhere:LT = live time (minutes),

the counting efficiency (counts per disintegration),E =

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

62.22 x 10 the number of disintegrations per minute per=

microcurie,

the fractional rac"mhemical yield, when applicable,Y =

Decay = decay factor (s), here are three decay factors that maybe appropriate for use depending cn the nature of thesample and the half life of the nuclide. Anyc mbination of the three may be used. W e factors areas follows:

A) Wis decay factor corrects for decay frtxn the time ofsampling to the start of the analysis,

24te s, wh:Ats = decay time = acquisit m start tim - sample time

A = In2/ half-life

B) % is decay factor corrects for decay during the analysis.

1-e - # , wheretA . RT1= In2/ half-lifeRT = real tim of counting

ODCM 4

4/92

_ _ _ . _ _ _ _ _ _ _ . _ .

TAIYR 2-1 (Ocntinni)

TABLE NOIATIO3S (Continued)

C) 'Jhls decay factor corrects for decay during sampling.

1-e - td , where:1 Atd3=In2/ half-life

td = deposition tim = sample time - deposition start time

NOTE: All times used in decay calculations should be in thesame units.

Typical values of E, V, Y, t , t should be used in the m1mlation.g d

It should be recognized that the ILD is defined as an a priori (be-fore the fact) limit representing the caphility of a measurmentsystem and not as an a posteriori (after the fact) limit for a par-ticular measuranent.

(2) A batch release is the discharge of liquid wastes of a discretevolume. Prior to anmnling for analyses, each batch shall beisolated, and then thoroughly mixed by a method described inplant procedures to assure representative anmnling.

(3) 'Ihe principal ganna atitters for which the ILD specificationapplies include the following radionuclides: h 54, Fe-59, Co-58, Co-60, Zn-65, h 99, Cs-134, Cs-137, Ce-141 and Ce-144.This list does not mean that only these nuclides are to be con-sidered. Other ganun peaks that are identifiable, together withthose of the above nuclides, shall also be analyzed and reportedin the saniannual Radioactive Effluent Release Report in theformat outlined in Regulatory Guide 1.21, Appendix B, Revision1, June 1974.

(4) A composite sample is one in which the quantity of liquid sam-pled is suru11onal to the quantity of liquid waste dischargedand in which the methed of aampling employal results in a speci-nen that is representative of the liquids released. Prior toanalysis, all samples taken for the ccrnposite shall be thor-oughly mixed in order for the composite samples to be represen-tative of the effluent release.

(5) A continuous release is the discharge of liquid wastes of a non-discrete volume, e.g., frun a volume of a systen that has aninput ficw during the continuous release.

(6) Samples shall be taken at the initiation of effluent flow and atleast once per 24 hours thereafter while the release is occur-ring. To be representative of the liquid effluent, . the samplevolume shall be sugarLioned to the effluent stream' dischargevolume. 'Ihe ratio of sample volune to effluent discharge volumeshall be unintained constant for all samples taken for the ccm-posite sample.

ODCM 5

4/92

TPEIR 2-1 (Omtisned)

FRE00ENCY NCTfATIO1

IUPATIOJ FRE00ENCY

S At lease once per 12 hours.

D At least once per 24 hours.

W At least once per 7 days

M At least once per 31 days.

Q At least once per 92 days.

SA_ At lmst once per 184 days.

R At least once per 18 months.

S/U Prior to each zeactor startup.

N.A. Not applicable.

P Ccxnpleted prior to each release.

ODCM 6

3/91

2.2 Dono - Cbmplianm With 10 CFR 50 Amendix I

'Ihe dose or dose cmmitment to a MEMBER OF 'IHE PUBLIC frun radio-active materials in liquid effluents released, fran each unit, toUNRES'HUCTED AREAS (see Figure 2.1) shall be limited:

a. During any calendar quarter to less than or equal to1.5 mtuns to the whole body and to less than or equalto 5 mrms to any organ, and

b. During any calendar year to less than or equal to 3mrans to the whole body and to less than or equal to10 mmns to any organ.

2.2.1 Hrsnedial Action

With the calculated dose fran the release of radioactive mate-rials in liquid effluents ex W ing any of the above limits, pre-pare and subnit to the Conmission within 30. days, pursuant toTechnical Specification 6.9.2, a Special Report that identifiesthe cause(s) for exceeding the limit (s) and defines the correc-tive actions that have been taken to redu 'the releases and theproposed corrective actions to be taken to assure that subsequentreleases will be in mmmnce with the above limits. 'IhisSpecial Report shall also incitx3e: (1) the results of radio-logical analyses of the drinking water source, and (2) the radio-logical impact on finished drinking water supplies with regard tothe requirments of 40 CER Part 141, Clean Drinking Wdtar Act.'Ihis require:ent of (1) and (2) are applicable only if drinkingwater supply is taken fran the receiving body within 3 miles ofthe plant discharge.

2.2.2 Surveillance 1kratirements

Cumulative dose contributions frun liquid effluents for the cur-rent calendar quarter and the current calendar year shall be de-termined using the following methodology at least once per 31days.

mIA 1 At C F)D *iT g g 3T

lel

Nhere,

g = the cumulative dose comtitment to the total body orany organ, T, fran the liquid effluent for thetotal

mtime period E at , in man.

t171

% = and Fthe length of the Lth time period over which C

areaveragedforallliquidreleases,ihghours.

ODCM 7

3/91

.

l.|

| |

2.2.2 Surmillanco Haouirantets - Otmtinued I,

|'

Cg= the average concentration of radionuclide, 'i', in |urrilluted liquid effluent flow during tine period j

| A t , in uC1/ml.g

the near field average dilution factor for CF =L g

during any liquid effluent release where

f 1F =L l(7)p

where:

f= Liquid Radi, active Waste Flow l

i

F= Discharge Structure Exit Flow, the sum of the re- !lease and dilution flow. !

K= Applicable factor; the site dependent value for themixing effect of the discharge structure. Thisvalue is conservatively assurred to be 1 (one) forthis section.

he site related ingestion dose conmitment factor to IA =iT the total body or any organ, 'T', for each iden- ;

tified principal gamna and beta emitter, mrem /hr per i

uCi/ml. See Tables A.4-1 through A.4-4. |

|gg, = '1.14ES (U /g + U .BF ) MyA g p f

Nhere,

DW = Dilution factor frm the nar field area to thepotable water intake for water consumption, for Wolf i

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

y= Bioaccumulation factor for radionuclide, 'i', inBFfish, pCi/Kg per pCi/1, frm Table A.1-1 frm Regu-latory Guide 1.109 (Rev. 1).

DFy= Dose Conversion factor for radionuclide, 'i', innmem/pC1, frm Table A.3-1 through A.3-4, from Regu-latory Guide 1.109 (Rev. 1).

U, = Water consumption, in kg/yr.

Fish consumption, in kg/yr. )U =p6 31.14E5 = units conversion factor = 10 pC1/uCi x 10 ,1fgg

8760 hr/yr

ODCM 8

.-

|

1-

.

l

2.2.2 Surmillance amuiremonta - Otmtirnd I

I'1he dose calculations are based on the actual isotopic analysis Iof the radioactive liquid effluents, the radioactive liquid ef- |fluent flow, and the dilution flow,

l

2.3 Proiected Dono |

'Ihe Liquid Radeste Tmatnent Systs shall be OPERABLE arxi appro-priate portions of the systs shall be used to raluce releases ofradioactivity when the projected doses due the liquid effluent,frm each unit, to UNRES'IRlCTED AREAS (see Figum 2.1) would ex-ceed 0.06 mr m to the whole body or 0.2 mr m to any organ in a 31day period.

2.3.1 Remedial R:tice ;

With radioactive liquid e ste being discharged without treatmentand in excess of the above limits and any portion of the LiquidRadeste Treatment Systm not in operation, prepare and submit tothe Camtission within 30 days pursuant to 'Ibchnical Specification-6.9.2, a special Report that incitxles the following information:

A. Explanation of why liquid radwaste ma beirxy discharged with-out treatment, identification of any inoperable equipent orsubsystas, and the reason for the inornmhility,

B. Action (s) taken to restore the inoperable equipent toOPERABLE status, and

C. Sumary description of action (s) taken to prevent a recur-rence.

2.3.2 Surveillance amuirnments

2.3.2.1 Doses due to liquid releases frm each unit to UNRESTRICTED AREASshall be projected at least once per 31 days in accordance withthe following methodology when Liquid Badeste Trmtnent Systmsare not being fully utilized.

__

A 31D =.

31 T__

Where,

31 " 3 31 Y *D

A = Cumulative dose for current quarter

T = Current nunter of days in quarter

00CM 9

3/91

-

2.3.2.2 '1he installed Liquid Radwaste Treatment System shall be con-sidered OPERABLE by neeting the requirments of Sections 2.1 and2.2.

2.4 Inntnannntation

'Ihe radioactive liquid effluent monitoring instrumntation chan-nels shown in Table 2-2 shall be OPERABLE with their Alam/ TripSetpoints set to ensure that the limits of Section 2.1 are notexceeded. 'Ihe Alam/ Trip Setpoints of these channels shall bedetemined and adjusted in accordance with the nothodology andpirannters described in Section 2.4.4.

2.4.1 Ikmxlial Actioni'

2.4.1.1 With a radioactivo liquid effluent nonitoring instrunentationchannel Alam/ Trip Setpoint less conservative than required by ;

the above, inmxiiately suspend the release of radioactive 11guld ;

effluents nonitored by the affected channel, or declare the chan-i

Inel inoperable.

2.4.1.2 With less than the mLninum number of radioactive liquid effluent;

nonitoring instrumentation channels OPERABLE, take the EfIONshown in Table 2-2. Restore the inoperable instrunentation to - !

OPERABLE status within the time specified in the EfION, or ex-plain in the next Annual Radioactive Effluent Release Report, | )why this inoperability was not corrected within the tine speci- ifled.

|'2.4.2 Surveillance IVxndmments

Each radioactive liquid effluent nonitoring instrunentation chan-nel shall be dmonstratal OPERABLE by perfornance of the QiANNELOIIIK, SOURCE OIECK, CIANNEL CALIBRATIOT and ANAIOG OIANNELOPERATIONAL TEST at the frequencies shown in Table 2-3.

.

ODCM 10

9/93

.

.

W

TABLE 2-2

RADI0 ACTIVE LIQUID EFFLUENT. MONITORING INSTRUMENTATION

'

MINIMUMCHANNELS

INSTRUMENT- OPERABLE ACTION

1. Radioactivity Monitors Providing Alarm and AutomaticTermination of Release

.

.

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

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

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 (HF-RE-95) 1 32

2. Flow Rate Measurement Devices !

a. Liquid Radwaste Discharge Line

1) Waste Monitor Tank A Discharge Line 1 34 ,

2) Waste Monitor Tank B Discharge Line 1 34r

b. Steam Generator Blowdown Discharge Line 1 34

c. Secondary Liquid Waste System Discharge Line 1 34

ODCM 11

3/91 '

. - - _ _ _ _ _ _ _ . __ _______-__-__-__-_-__-__.__:-__-__ - - .

TAIIR 2-2 (Continued

ALTICN STATEMENIS

Action 31 - With the number of channels TERABLE less than requiredby the Minimum Channels @ERABLE requirement, effluentreleases via this pathway may continue for up to 14 daysprovided that prior to initiating a release

a. At least two independent sanples are analyzed inaccordanm with Section 2.1.2, and i

b. At least two technically qualified nanbers of thefacility staff independently verify the release ratecalculations and discharge line valving.

1

Otherwise, suspend release of rn h etive effluents via |Ithis pathway.J

Action 32 - With the number of channels OPERABLE less than required |by the Minimum Channels OPERABLE requirment, effluentreleases via this pathway may cantinue for up to 30 daysprovidai grab samples are analyzed for principle ganmaemitters and I-131 at a lower limit of detection as spe-cified in Table 2-1.

a. At least ance per 12 hours when the' specific acti-vity of the secondary coolant is greater than 0.01microcurie / gram DCSE EQUIVAT22e I-131, or

b. At least once per 24 hours when the specific acti-vity of the secondary coolant is less than or equalto 0.01 microcurie / gram DOSE EQUIVAIRC I-131.

Action 33 - With the number of channels OPERABLE less timn requiredby the Minimum Channels OPERABLE requirment, effluentreleases via this pathway may cantinue for up to 30 daysprovided that prior to initiating a releases

a. At least two independent samples are analyzal inaccordance with Section 2.1.2, and

b. At least two technically qmlified members of thefacility staff independently verify the release ratecalculations and discharge line valving.

Otherwise, suspend release of radioactive effluents viathis pathway.

ODCM 12

3/91

a - . _ . - - - _ .

. .

TNIR 2-2 (Contirmed)

1CTION STATENENTS

Action 34 - With the ntunber of channels OPERABLE less timn . Wby the Minimum Channels OPERABLE requirenent, effluentreleases via this pathway may continue for up to 30 daysprovided the flow rate is estimated at least once per 4hours during actual releases. Pump performance curvesgenerated in place may be used to estimate flow.

ODCM 13

3/91

.

I

TABLE 2-3

RADI0 ACTIVE LIOUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS

ANALOG-CHANNEL

CHANNEL SOURCE CHANNEL OPERATIONALINSTRUMENT CHECK CHECK CALIBRATION TEST

1. Radioactivity Monitors ProvidingAlarm and Automatic Terminationof Release

a. Liquid Radwaste Discharge Monitor(HB-RE-18) D P R(2) Q(1)

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

c. Turbine Building Drain Monitor(LE-RE-59) D M R(2) Q(1)

d. Secondary Liquid Waste SystemMonitor (HF-RE-45) D P R(2) Q(1)

e. Wastewater Treatment System InfluentMonitor (HF-RE-95) D M R(2) Q(1)

2. Flow Rate-Measurement Devices 14

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

b. Steam Generator Blowdown Discharge Line D(3) N.A. R N.A.

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

ODCM 14-

3/91

. .. .. . . . --

TAHLE 2-3 (Ctmtintni)

TABLE UPATIOE

(1) %e ANAII)G CHANNEL OPERATIONAL TEST shall also daranstrate thatautmatic isolation of this pathway and control rom alam an-nunciation occur as appropriate if any of the following condi-tions exists:

a. Instrumnt indicates measured levels above the Alam/ TripSetpoint (isolation and alam), or

b. Circuit failure (alarm only), or

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

d. Instrument controls not set in operate node (alam only).

(2) he initial CHANNEL CALIBRATION shall be ,rnrfnmwi using one ornore of the reference (gas or liquid and solid) standards wr-tified by the National Institute of Standards and Technology.(NIST) or using standards that have been obtained frm suppliersthat participate in measurment assurance activities with NIST.%ese standards shall pemit calibrating the systen over itsintended range or energy, measurment range, and establieh non-itor response to a solid calibration source. For subsequentCHANNEL CALIBRATIOi, NIST tmr'#able standard (gas, liquid, orsolid) may be used; or a gas, liquid, or solid source that hasbeen miihmted by relating it to equipnent that was previously(within 30 days) m1ibrated by the sane gemetry and type ofsource standard tmmable to NIST.

(3) CHANNEL CHECK shall consist of verifying indication of flow dur-ing periods of release. CHANNEL CHECK shall be made at leastonce per 24 hours on days on which ocntinuous, periodic, or <

batch releases are made.

ODCM 15

3/91

2.4.3 Lianid Mcmitar Calibmtian )ethodoloav

%e five nonitors associated with liquid releases are listed be-low:

Monitor ID Description

0-BM-RE-52 Steam Generator BlowdownDischarge Monitor

0-LE-RE-59 Turbine Building DrainMonitor

0-HF-RE-45 Secondary Liquid WasteSysten Monitor

0-HB-RE-18 Liquid Radwaste DischargeMonitor

0-HF-RE-95 Wastewater Treat m nt SystemInfluent Monitor

Liquid effluent streams are nonitored by an NaI(Tl) Detector.The detector operates in a gross counting node and is ganna sen-sitive.

Calibration of the liquid nanitors shall be performed using threestandard solutions of Cs-137. The solutions shall cover the ap-propriate range of pe detector and p ve concentrations of ap-proxinately 5 x 10~ uCi/cc, 1 x 10~ uCi/ce, and 1 x 10~uCi/cc. 'Ihe solutions shall be presented to the detector and theneter reading in counts per nunute shall be recorded. A graph ofcounts por minute versus concentration shall be produced frun thedata.

2.4.4 Liquid Effluent Martitor Setmints

'Ihe Alarm / Trip Setpoints for the Liquid Effluent Radiation Moni-tors are based on the instantaneous concentration limits of 10CFR 20, Appendix B, Table II, Column 2 applied at the boundary of I

the restricted area. Specifically, the High Alarm Setpoint will !

correspond to the 10 CFR Part 20 limita at the Boundary of the )restricted area; the Alert Alann Setpoint is set one order of !

nagnitude below the High Alann/ Trip Setpoint. Since the High |Alann/ Trip initiates isolation of the particular Systen and tenn- !ination of the release, this setpoint represents assurance thatthe instantaneous liquid release limit of 10 CFR Part 20 is notexceeded. Auditable records shall be maintained indicating the jactual setpoints used at all tines.

|,

ODCM 16

|1

1

The calculated Alarm and Trip Action Setpoints for the Liquid !Effluent Line Monitors nust satisfy the follwang equation _|

,

cf <C '

F+f

Where:

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

'

c = 2he Setpoint, in uC1/ml, of the Radioactivity Manitormeasuring the radioactivity concentration in the effluentline prior to dilution and subsequent release; the Set-point, which is inversely puru.Lianal to the VolumetricFlw of the effluent line and directly supu.Lianal to theVolumetric Fl w of the dilution stream plus the effluentstream, represents a value, which, if exceeded, would re-sult in cancentrations exceeding the limits of 10 CFR 20 inthe unrestricted area.

f = The Pump Flw Rate as Insasured at the Radiation MonitorIocation, in Volume per Unit Tine, but in the sane units asF, belw.

F = 7he Dilution Water Flw Rate as neasured prior to the re-lease point, in volume per Unit Time.

7hus, the expression for detennining the Setpoint on the LiquidRadwaste Effluent Line Monitor beoanes:-

c < "(F+f) (uCi/ml). f

,

OEDi 17

2.4.4.1 Ocritinuous Lianid Effluent Manitnra

%e three noni. tors associated with continuous 11guld releases arelisted below:

Monitor ID Description

0-BM-RE-52 Steam Generator BlowdownDischarge Monitor

0-LE-RE-59 Tnrhine Building Drain Monitor

0-HF-RE-95 Waste Water Treatment Syst aInfluent Monitor

%e Steam Generator Blowdown Discharge Effluent Monitor contin-uously nonitors the Blowdown Discharge Pump Outlet to detect ex-cess radioactivity due to Systs Demineralizer breakthrough or -abnormal Primary to Secondary leakage. The Blowdown DischargeMonitor's High Alam Setpoint initiates CIOSURE of the BlowdownIsolation valves and the Blowdown Discharge Valve. ' Similarly,the High Radiation Alarm on the Turbine Building Drain Monitorand Waste Water Treatment Monitor initiates CIDSURE of the DrainLine Isolation Valves to prevent the release of radioactive ef-fluents.

Monitor setpoints will be conservatively based on I-131, the mostrestrictive isotope expected to be present. his is particularlyanu.vs.iate for the Turbine Building Drain Line Monitor since themost probable source is the Secondary Steam Syst s which is ex-pected to have negligible activity unless.there is a significantPrimary to Secondary leak. Due to changing activities,-it willnot be possible to select a radionuclide distribution on which tobase the nonitor setpoint. Aiiitionally, maximum. effluent flowsand mininum dilution flows will normally be assumed.

The High Alarm / Trip Setroint will be set to correspond to the I-131 MPC limit at the boundary of the restricted area frm 10 CFRPart 20, Appendix B, Table II, Column 2. % e alert alarm is setone order of magnitude below the High Alarm / Trip Setpoint. %isHigh Alarm / Trip Setpoint assures the limits of Section 2.1 arenot exceeded at the bourdary of the restrictai area.

In the event that an alarm is TRIPPED, an evaluation of the sys-tem will be made by taking an actual isotopic and flow analysisof the discharge.

W e above continuous liquid effluents are not radioactive ef-fluents until activity has been detected by the Liquid EffluentMonitor, a Tritium analysis of the Secondary system, or a grossBeta analysis of the Secondary system. At that time an analysisof the effluent will be nade to verify activity in the systemeffluent. During periods of time when the above liquid effluentsare not radioactive the High Alarm / Trip Setpoint may be set to1.5 tines the background count rate.

ODCM 18

2.4.4.1.1 Steam Generntor Blow &wn Disdnroe Mmitnr

F +F'SEIPOINT (uCi/ml) = MPC X m BI-131

B

where,= == s le Concmuadm ofMPCI-131 I-131, 3.0 E-7 uC1/ml.

F = Dilution flow rate.m

F "*

B

% e setpoint calculation is based on the minimum dilution flowrate, the mwinn possible blowdown flow rate, and, due tochanging conditions, I-131 which is the most restrictive isotopeexpected to be present.

On the event that an niann is reched, the setpoint will be re-evaluated using the actual dilution f1w rate, the actual blw-down flow rate, and the actual isotopic analysis as outlined inSection 2.4.4.2. his evaluation will be used to ensure thelimit of Section 2.1 was not exceeded. We setpoint will stillbe based on the MPC of I-131 due to the changing conditions ofactivity and I-131 being the ucst restrictive isotope.

2.4.4.1.2 Turbine ndidirn Drain Mcnitor And msto eter TrmtamtSvatam Influent Ibnitor

F+F-Setpoint (uCi/ml) = MPC X m TI-131

T

where,MPC = 3.0 E-7 uCi/ml.I-131F = Dilution flow rate.m

F = Effluent flow rate.T

he setpoint is based on the minimum dilution flow rate, the max-imum possible effluent flow rate, and the nost restrictive iso-topo expected to be present, I-131.

On the event that an alarm is reached, the release will be eval-uated to see if the limit of Section 2.1 was exceeded by usingthe actual Dilution Flow Rate, the actual Effluent Flow Rate, andthe actual isotopic analysis as outlined in Section 2.4.4.2. hesetpoint will still be based on the MPC of I-131 due to the

changing conditions of activity and I-131 being the most restri-ctive isotope.

ODCM 19

.

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

.

. . . ,

2.4.4.2 Batdt Fr<iirwtive Liould Efflumt Itmitar -'The two nonitors associated with liquid batch releases are listed

below:

- Monitor ID Description

0-IT-RE-45 Secordary Liquid WasteSysten Monitor

0-HB-RE-18 Liquid Radwaste Discharge !Manitor ,

, % e setpoint is a function of dilution flow rate, tank flow rate,.and isotopic ccrrposition. ' A laboratory isotopic analysis is madeof each batch prior to discharge. Based on the isotopic analysis. '

and existing flow condition, the setpoint will be calculated andset on the apywytiate manitor to ensure the concentration 11ntitsof 10 CFR 20, Appendix B, Table II, Column 2 are not exceeded.

We setpoints are determined using the following methodology:' ,

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

h e isotopic canoentration of the batch is the sum ~of.the' '

concentratians for the isotopes present as detennined fran ,the analysis required in Table 2-1.

kCf= fC + C, + C +Cg+Cf ;g s

Where:

1 %e concentration of nuclide i as detennined by.C =,

the analysis of the waste sample.

he sum of the cancentrations C' of each measured'C =-

9 9ganma enitting nuclide observed by ganma-rayspectroscopy of the waste sample.

*C,= he measured cancentration C of alpha enittingnuclidesobservedbygrossafphaanalysisofthe;nunthly camposite sample.

te measured cancentrations of Sr-89 and Sr-90 in*C =s liquid waste as detennined by analysis of the-

quarterly camposite sanple.

ODCM 20

- _ _ - _ --

.

%e M cmcendon of H-3 in Wd wasta*C =g

as detemined by analysis of the. monthly campo-site.

*Cf= 'Ihe measumd concentration of Fe-55 in liquidwaste as detemined by analysis of the quarterlycmposite.

* Values for these concentrations will be based onprevious cmposite sample analysis as required byTable 2-1.

2) The measured radionuclide concentrations are used to calcu-late a dilution factor, F , which is the ratio of total di-lutionflowratetotankIlowraterequiredtoassurethat

,

the limiting concentrations of Section 2.1 are met at the .|point of discharge. This is referred to as the required di-lution factor and is detemined according to:

F = (A C. )xFd(1 idC ) j

8

1

Miere: ,

!

C1= Measured cancentrations of , C,C ,g,C

C ,f,C and C ,

as defined in Step 1. 1brms C,t fwill be included in the cal tio8 as aps vg iato.

MPC E,E,E,E E ,am gcm-=1 t Icen9_ ratio 8s of Ehe apsvgiate radianuclide fram 10 i

'CFR 20, Apperriix B, Table II, Colum 2. For dis-solved or entrained noble gases, the concentration- ,

shall be limited to 2.0E-04, uCi/ml. total activity. ~)i

'lhe safety factor; a conservative factor used toF =8

cmpensate for statistical fluctuations and errors !of measurement default value is 1.0. -

3) For the case Fg < 1, the waste tank effluent concentration lmeets the limits of 10 CFR 20 without dilution and the ef- '

fluent nay be released at any desired flow rate. For the icase F 1, a nodified dilution factor, F must be deter- |minedNo>thatavailabledilutionflowmayb, apportioned jamng simultaneous discharge pathways. l

ODCM 21

- ___ _-_

Fg=Fd a

Where F is the allocation factor which will modify the re-quired 811ution factor so that simultaneous liquid releasesmy be mde without exceeding 10 CFR 20 limits.

We nest straight-forward detemination of allocation factoris:

F = 1/na

Where

n = h e number of liquid discharge pathways for which Fd>and which are planned for sinultaneous release.

However, this value for F m y be unnecessarily restrictivein that all release pathw$ys are apportioned the sam frac-tion of the available dilution stream, regardless of the re-lative concentrations of each of the sources.

Since the radianuclide cencentration of the two continuoussources is expected to be less than that of the batch releasesource, it is acceptable to allocate smaller portions of thedilution stream to the continuous releases and a larger por-tion to the batch releases.

%erefore, F is defined as a flexible quantity with a de-faultvalue8f1/n. Prior to initiating sinultaneous re-lease, a check will be mde to assure that the sum of theallocation factors assigned to pathways for the sinultaneousrelease is < l.

4) ne calculated mvimn pemissible waste tank effluent flowrate, F , is based on the nodified dilution factor, Fg,and the"@ffective dilution flow rate, F

eff*

% e cooling lake into which the effluent is discharged isalso the source of the dilution stream. It is thereforenecessary to take into account the recirculation of pre-viously anitted radionuclides should they be detected by sam-ple analysis of the cooling lake water. his is acocznplishedby defining an effective dilution flow rate as:

#eff = F, 1I

ODCM 22 |

I

:

i

.. _

|

|

I

Where: |

e expected mininum dilution eter flow rate.F *m

IC = Measured concentration of nuclide i in the cooling !1 lake e ter sample.

MPCy = Idmiting concentration of radianuclide i frcm 10 CFR20, Appendix B, Table II, Column 2.

For the purpse of setpoint miculations the expected Irdninumdilution flow rate * assigned a value based upon the typeand number of ptmpe m WDG into the circulating ster pip-ing.

Having established the values of F and F , the calculatedmaximumpermissibleestetankflobrate18hivenby.

:I 5Feff + f #eff f#fnax p p " Feff

F fdn dn

Where f if the expected effluent flow rate; nozmally therated cEpacity of the effluent pump. Sus the pump flow rateis set at or below f Even though the value of f may.

belargerthanthea'dEdaleffluentpumpcapacity,f"*ftdoes9represent the upper limit to the effluent flow rate whereby

the requirement of 10 CFR 20 may still be met. If Fa 5 1,the effluent pump flow rate may be assigned any valuM sincethe este tank effluent cancentration meets the limits of 10CFR 20 without dilution and the release nay be made withoutregard to the setpoints for other release patheys. Forthose discharge pathways selected to be secured during therelease under consideratian, the pump flow rate should be setat as low a value as practicable to detect any inadvertentrelease.

A setpoint for the dilution stream flow rate is not appli-cable since the minimum flow rate is administratively set.

5) We liquid radiation non} tor setpoint nay now be determinedbased on the values of 4 , C , and f %e nonitor re-.

Isponse is prinarily to ghnnn mdiatiM* therefore, the actualsetpoint is based an 6, Cconcentration is detenVdne3. he calculated nonitor setpointas follows:

c=A C (uCi/ml)g

li

ODCM 23 j:|

|!

u

|

Where:

A= Adjustment factor which will allow the setpoint .tobe established in a practical manner for convenienceand to prevent spurious alanns,

f"A=fP

If A > 1, calculate c and determine the eximum value for theactual monitor setpoint (uci/ml).

If A < 1, no release my te mde.

If Fd< , no f e u n e m ease mybe m de without regard to available dilution or toother releases made sinultaneously. However, it isnecessary to establish a monitor sctpoint whichwill provide alarm should the release cancentrationinadvertently exceed 10 CFR 20 limits. 'Ihis can beacccmplished by establiahing the adjust 2nent factoras follows:

A = 1/Fd

11

l1

:

|

l

P

ODCM 24.

2 4 - ,Js 4 anEa--4'M , 4W-+p, y v 4w .

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BOUNDARY.FOR LIQUID EFFLUE T5(.

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WOLICREEK CfNERATWC STATION1 UNIT No t

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3.0 (ASHOUS FMDENTS i

l

Gaseous effluent releases frcm the Unit Vent and RadesteBillding Vent are nanitored continuously. Se Unit Vent is therelease point for the Fuel /Amiliary Billding, access control . !

area, containment purge, and condenser air discharge. Se Pad-m ate Building Vent is the release point for Waste Gas DecayTanks and the Radeste Building Ventilation System.

Waste Gas Decay Tank releases and Containment Building releasesare treated as 'aatch releases. Waste Gas Decay Tank releases aremonitored by the Radeste Building Exhaust Monitor. ContainmentBuilding releases (purges) are monitored by the Containment PurgeSysten nonitorrs 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 / AuxiliaryBillding, access control area,containment purge, condenserair discharge)

0-GI-RE-10 A and B Radwaste Building vent (Rad-waste Building, waste gas de-cay tank discharge. Acts toisolate Waste Gas Decay Tankdischarge)

0-GT-RE-22 & 23 Containment Purge System Moni 'tor (acts to isolate thepurge; is not an effluent man-itor)

0-GT-RE-31 & 32 Containment Atnosphere Monitor(acts to isolate purge; not aneffluent monitor)

he setpoint for nonitors Iray be determined either based on totalbody dose or skin dose rate. The dose rate limits are for doserates at the unrestricted area boundary. We nanitor setpoint isthe lesser of the total body dose rate or skin dose rate.

00CM 26

3.1 Done Rate - nrmnhnoe With 10 CFR 20

%e dose rate due to radioactive matenals released in gaseouseffluents frm 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 mrms/yr to thewhole body arx1 less than or equal to 3000 mmns/yr to theskin, and

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

3.1.1 Rmedial Action

With the dose rate (s) exceeding the above limits, ! = v h telyrestore the release to within the above limit (s).

3.1.2 Surveillanm Reaulu-An

h e dose rate to radionuclides in gaseous effluents shall be de-tennined to be within the above limits in accordance with themethodology described below by obtaining representative samplesand performing analyses in accordance with the sanpling and anal-ysis supcun specified in Table 3-1.

Based on the methodology of NUREG-0133;

a. Release rate limit for nobles gases

fK1 (X/Q) Of <500 mrm /yr for the total body,

and

f(L1 + 1.1 M ) (X/Q) Q1 <3000 mrm/yr for the skin.1

Where:

Total body dose factor due to gamma emissions forK =1 each ident,1fied noble gas radionuclide, in mrm/yr

per uCi/m", frm Table A.1-2.3

(X/Q) 2.2 E-06 sec/m , the highest calculated annual=

average relative concentration at the restrictedarea boundary in the north sector.

ODCM 27

3/91

- ... . . - . - - -- - - . -

.

5

3.1.2 Surwilla== Reauirasents (nmwima)i

Release rate of radionuclide i frun vent, in..Q =guC1/sec.

Skin dose factor due to beta emissions for eachL =I

identgfied noble gas radionuclide, in.mran/yr peruCi/m , from Table A.1-2.-

Air dose factor due to ganma emissions for' each .M =1

identgfied noble' gas radionuclide,:in mrad /yr per .uCi/m frun' Table ' A.1-2. ,

'

Conversion constant of air dose to' skin dose.1.1 =

b. Release rate limit for all radionuclides and radioactivematerials in particulate form and radionuclides other thannoble gases:

(P IN * (X/Q) * O ) <l500 mrun/yr to any organ.f

Where: '

f % e release rate of radionuclides, i, in gaseousO =,

effluent frtm all vent releases, in uCi/sec. I

,

II)IN %e dose parameter for radionuclides other thanP =;

noblesgapsfortheinhalationpathway,.-inmrem/yr iper uCi/m .' See Table'A.5-1. ''

]3-(X/Q) = 2.2 E-06 sec/m (the highest annual average). We

highest calculated relative concentration for es-timating the dose to an' individual at the unre-stricted area boundary in the N sector.

All radionuclides are assumed to be released in' elenental form. H%e limit is applicable to the locatico (unrestricted area boun- ,|dary or beyond), characterized by the value of X/O which results. 1

in the maximum total body or skin dose catmLtment. %e factorsK L and M. relate the radionuclide airborne concentrations .toykr,iobs,dosehatesassumingasemi-infinitecloud.'nesefactorsare taken f p Table B-1 of p Regug tory Guide 1.109 and multi-plied by 10 to convert pCi to uti and listed in Table A.1-2.

ODCM 28

~

,

f

r . - i% - .- -- , =-

3.1.2 Surveillanco Roauirunmts fotrrtinued)

% e following equation for P(i)IN ms en h m 0133:

1)g (Inhalation);P

P = K' (BR) DFAf (Wp par d/m )g)gNhere:

6a constant of unit conversion, 10 pCi/uCiK' =

tge breathing rate of the child age group inBR =

m /yr

the maximum organ inhalation dose factor forDFA =f the child age group for the i th radicnuclide,

in mmm/pC1. H e total body is considered asan organ in the selection of DFA .

1

Theagegroupconsideredistheegildgroup. Se child'sbreathing rate is taken as 3700 m /yr frun Table E-S ofRegulatory Guide 1.109. %e inhalation dose factors forthe child, DFA, are presented in Table E-9 of RegulatoryGaide 1.109,.t'n units of mrem /pC1.

Resolutions of the units yields:9

Py (Inhalation) = 3.7 X 10 DFAf ;

he P value for tritium is |y9

P1 ( h M on) = 3.7 x 10 DFAf

!

i

l

!I

i

l

ODCM 29

I

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!

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.

%

TABLE 3-1

RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM

MINIMUM LOWER LIMIT OFSAMPLING ANALYSIS TYPE OF DETECTION (LLD)(1)GASEOUS, RELEASE TYPE FREQUENCY FREQUENCY ACTIVITY ANALYSIS (uCi/ml)

P P1. Vaste Gas Decay Each Tank Each Tank Principal Gamma Emitters (2) 1x10-0

Tank Grab Sample

P P2. Containment Purge Each Purge (3) Each Purge (3) Principal Gamma Emitters (2) 1x10-0

or Vent GrabSample M

H-3 (oxide) 1x10-63. Unit. Vent M(3), (4) M(3)

Grab Principal Gamma Emitters (2) 1x10-4Sample

H-3 (oxide) 1x10-65. Radwaste Building M M

Vent Grab Sample Principal Gamma Emitters (2) 1x10-4i

M

H-3 (oxide) 1x10-66. Release Types Continuous

as listed in 3. (6) W(7) I-131 1x10-12and 5. above

Charcoal Sample I-133 1x10-10

Continuous W(7) Particulate(6) Sample Principal Gamma Emitters (2) 1x10-11

Continuous (6) M -Particu-Composite late Sample Gross Alpha 1x10-11

Continuous 'Q. .

.

1x10-11(6) Composite Parti- Sr-89, Sr-90culate Sample q

ODCM 30-12/91

-,

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

TAK E 3-1 (Continuedj

TAKE W TATIONS

(1) S e LT.D is defined, as the smallest concentration of radioactivematerial in a sanple that will yield a net count, above systembackground, that will be detected with 95% prooability with anly _5% prnhability of falsely canc1'xling that a blank observationrepresents a "real" signal.

For a particular measuranent system, which may include radio-chenical separation:

4.66 sb

E * V * 2.22 x 106 7 . DecayWhere:

IID = the "a priori" lower limit of detection (microCurles perunit mass or volume),

the standard deviation of the background counting rate ors =b of the counting rate of a blank sample as ae vsiate,

(counts per minute), = F / LTWhere: B = ba sum (counts)

LT = live time (minutes),

the counting efficiency (counts per disintegratian),E =

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

62.22 x 10 the number of disintegrations per minute per=

microcurie,l

the fractional radicchemimi yield, when applicable,Y =

Decay = decay factor (s), here are three decay factors that may |be agg.vg iate for use depending an the nature of the ;sample and the half life of the nuclide. Any ecnibination i

of the three may be used. S e factors are as follows:

A) Wis decay factor corrects for decay from the time of I

sampling to the start of the analysis,-3 ate 3, ,

Ats = decay time = acquisition start tine - sample time2 = In2/ half-life

B) mis decay factor corrects for decay during the analysis.O#1-e , where:

~)L. RTA = In2/ half-lifeRT = real time of counting

ODCM 31 4/92

.

1RBIE 3-1 (continmd1

TABLE NOIATIONS (Continuedi

C) h is decay factor corrects for decay during e mpling.td-

1-e , where:l Atd2 = In2/ half-lifetd = deposition tim = sanple tim - deposition start tim

NOPE: All times used in decay calculations should be in thesam units.

Typical values of E, V, Y, t , t us in the calculation.s d

'It should be recognized that the ILD is defined as an a priori (be-fore the fact) limit representing the capability of a masurmentsysten and not as an a posteriori (after the fact) limit for a par-ticular measurment.

(2) he principal gamma emitters for which the IID specification ap-plies include the following radionuclides: Kr-87, Kr-88, Xe-133,133, Xe-133m, Xe-135, and Xs-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-141and Ce-144 in iodine and particulate releases. B is list doesnot mean that'anly these nuclides are to be considered. Othergamna peaks that are identifiable, together with those of theabove nuclides, shall also be analyzed and reported in the semi-annual Radioactive Effluent Release Report in the format outlinedin Regulatory Guide 1.21, Appendix B, Revision 1, June 1974.

(3) hmnling and analysis shall also be performed following shutdown,startup, or a 'IHERMAL PONER change mmmaing 15% of RATED UIERMALPONER within 1 hour period.

(4) 'Ititium grab samples shall be taken and analyzed at least onceper 24 hours when the refueling canal is flooded.

(6) h e ratio of the sample flow rate to the sampled stream flow rateshall be known for the time period covered by each dose or doserate calculation made in accordance with Sections 3.1, 3.2 and3.3.

(7) Sanples shall be changed at least once per 7 days and analysesshall be ccrnpleted within 48 hours after changing, or after re-moval frm sanpler. For unit vent, m mnling shall also be per-fonted at least cnce per 24 hours for a least 7 days followingeach shutdown, startup or 2EERMAL POWER change exceeding 15% ofRATED 'IHERMAL POWER within a 1-hour period, and analyses shall becompleted within 48 hours of changing. When samples collectedfor 24 hours are analyzed, the corresponding ILD's my be in-creased by a factor of 10. his requirement does not apply if s(1) analysis shows that the DOSE EQUIVALENT I-131 concentrationin the reactor coolant has not increased nore than a factor of 3,and (2) the noble gas nonitor shows that effluent activity hasnot increased nore than a factor of 3.

ODCM 32 4/92

_ _ _ _ .._

3.2 Dose - nrunliance With 10 CPR 50 Ar-rwiir I

3.2.1 lenhkus Gases

n e air dose due to nobles gases released in gaseous effluents,fr a each unit, to areas at and beyond the SITE BOUNDARY (seeFigure 3.1) shall be lhnited to the followings

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

,

. >

b. During any calendar year: . Iass than or equal to 10 mrads forgama radiation and less than or equal to 20 mrads for beta .7radiation. !

3.2.1.1 n=mviial Actirm,

.

With the m1mlated air dose frun radioactive noble gases in: *

gaseous effluents e W ing any of the above limits,. prepare and '

subnit to the Ccmmission within 30 days, pursuant to TechnicalSpecificaticn 6.9.2, a special report that identifies the '

cause(s) for ex*ing the limit (s) and defines the correctiveactions that have been taken to reduce the releases and the pro-posal corrective actions to be taken to assure that subsequentreleases will be in emnliance with the above limits. .

'

3.2.1.2 Surveillance Reaui - im

Cumulative dose contributions for the current calendar quarterand calendar year for noble gases shall be detemined in aco r-dance with the following methodology at least once per 31 days.%e dose calculations for the actual releases of radioactivenoble gases in' gaseous' effluent will be consistent with the.methodology provided in Reg. Guide 1.109, Rev.~ 1. he followingdose mimlations will be performed:

a. During any calendar quarter;

For gamma radiation;

1 [(h0) * 0 ] 5 5 mrad.3.17E-8.f,yD M=1

For beta radiation;

f,y g [[/Q) * O J 5.10 mrad.'

3.17 E-8D = Nf

.

CDCM 33

3/91

- - .

3.2.1.2 Surveillance neauiremrrits (Omitirnwri)

b. During any calendar years

For ganma radiation:4

1 [(X/Q) * O ) 510 mrad.3.17 E-8 gy MD =y

For beta radiation:4

1 [(X/Q) * O ] 5 20 mrad.3.17 E-8 7,7 ND =f

Where:

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

The air dose factor due to ganna anissions for eachM =yidentjfied noble gas radionuclide, in Irrad/yr peruCi/m from Table A.1-2 (Reg. Guide 1.109, Table B-1, Col. 4).

The air dose factor due to beta enissions for eachN =1

identgfiednoblegasradionuclide,inmrad/yearperuCi/m fIun Table A.1-2 (Reg. Guide 1.109, Table B-1, Column 2).

2.2 E-6 sec/m . % e highest calculated annual ave- !(x/Q) =

rage relative concentration for any area at the un-restricted area boundary.

f h e release of noble gas radionuclides, 'i', in gas-O =

ecus effluents, in uCi. Releases shall be cumulative.over the calendar quarter or year as appropriate.

An average nonthly air dose schedule should be setup to ensuresection 3.2.1 is not exceeded. The average nonthly air doseshould be as follows:

a. For gamma radiation 51.6 mrad /no. !For beta radiation 5 3.3 mrad /no.

If the nonthly average air dose for: (a) is exceeded, it shouldbe noted that if the release is continued at the same (or higher)frequencies or activities the quarterly limit of Section 3.2.1.Awill be exceeded.

b. For gamma radiation 5 0.8 mrad /no.For beta radiation 51.6 mrad /no.

If the nonthly average air dose for: (b) is exceeded, it shouldbe noted that if the release is continued at the sane (or higher)frequencies or activities the annual limit of Section 3.2.1.Bwill be exceeded.

ODCM 34

_. _ . _ . . _ . _ _ . _

3.2.1.2 Surwillarm par =iin==aats (Cbutimed)

If any of the above monthly average air doses are exceeded, eval 3uation of the causes of the high air dose should be.perfomed andsteps 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 R=iinirviimus, Ihrticulates and Other B=iir== elides

'Ihe dose to a MEMBER OF 'mE PUBLIC frm Iodine-131 and 133, tri-tium, and all radionuclides in particulate fom with half-livesgreater .than 8 days in gaseous effluents released, frm eachunit, to areas at and beyond the SITE BOUNDARY (see Figure 3.1)shall be limited to the following:

a. During any calendar quarter: less than or equal to 7.5 mremsto any organ; and

b. During any calendar year Iess than or equal to 15 mr m s toany organ.

;

3.2.2.1 p-arlial Actim

With the calenlated dose frcm the release of Iodine-131 and 133,tritium, and radionuclides in particulate fom with-half-livesgreater than 8 days, in gaseous effluents exceeding any of theabove limits, prepare and submit to the Ccamissicn within 30days, pursuant to Technical Specification 6.9.2, a special reportthat. identifies the cause(s) for exceeding the limits and definesthe u.uaective actions that have bem taken to reduce the re-leases and the proposed corrective actions to be taken to assurethat subsequent releases will be in nnmnliance with the abovelimits.

3.2.2.2 Survaill- Heauituum=do

Cumulative dose contributions for the current calendar quarterand current calendar year for Iodine-131 and 133, tritium, and ,

radionuclides in particulate fom with half-lives greater than 8 |days shall be detemined in accordance with the following metho-dology at least once per 31 days. : To show emnliance, the dosecalculations for the actual releases of.the subject materials are-censistent with the methnriningy provided in Regulation Guide'1.109, Revision 1. 'Ihe follcwing dose calculations will be per-fomed:

a. D (mrm) = 3.17E-8 Ry [(WQ )] $ 7.5 mrmf

b. D (mtm) = 3.17E-8 R1 [@f)] 515 m

ODCM 35-3/91

. . .

- _ _ _ .

3.2.2.2 Surveillance Heauirumenbi (Omtinued)

Where:

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

he release of radiciodines, radioactive materialsO =f in particulate fann and radionuclides other than

noble gases in gaseous effluents, 'i', in uC1.Releases shall be cumulative over the calendarquarter or year as anavgiate. m e Q value shall

4be determined as the product of the flow ratethrough the release point and grab samples of theeffluent analyzed in armrrhnce with Table 3-1.

The annual average dispersion paraneter for esti-W =

mating the dose to an individual at the controllinglocation.

-6 3(X/Q), 2.2 x 10 sec/m for the inhalationW =pathway.

(D/Q), 1.8 E-8 m~ , for the food and groundW =

plane pathways.

nedosefactorforeachgdentifiedradionuclide,R. =1 'i', in mrem /yr per uCi/m . See Table A.5-2 through

Table A.5-20.

Where::

Inhalation Pathway Factor, R y [X/Q)3

R 1 [X/Q) = K' (BR)a (DFA )a (mIEm/Yr Per uC1/m )g

Where:

6a constant of unit conversion, 10 pC1/uC1.K' =

i

(BR)a gyo receptor of ageegroup (a), in m /yr.

We breathing rates (BR)hiven in Regulatory Guidefor the various age groups

i

are tabulated below, as i1.109, Table E-5.

E'E GROUP (a) BREA'DmG RATE (m /yr)Infant 1400Child 3700Teen 8000Adult 8000

ODCM 36

3.2.2.2 SurveL11ance notatiments (Oantirmed).

l

(DFA )8 = % e maximum organ inhalation dose factor forf the receptor of age group (a) for the i thradionuclide, in mrun/pci. he total bcdyis considerud as an organ in the selectionof (DFA )a. See Tables A.2-1, A.2-2, A.2-3, ;

f '& A.2-4. Frun Regulatory Guide 1.109,Tables E-7, E-8, E-9 and E-10.

Ground Plane Pathway Factor, R f[D/Q)

R y[D/Q]=K'K" (SF) DFGy[(1-ebi)/hi](m mram/yr per uCi/sec) .

-*

Where:

6A constant of unit uusvux.sion,10 pCi/uC1.K' =

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

Af % e_ p y constant for the i th radionuclide, |=

sLC .

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

y Thegroundplanedoseconversionfgetorforthei )DFG =

th radionuclide (mran/hr per pCi/m ). See TableA.2-5. (Regulatory Guide 1.109, Table E-6).

]

%e shielding factor (dimensionless), 0.7 (Reg.SF =

Guide 1.109)

Grass-Cow-Milk Pathway Factor, R f(D/Q]

1[D/Q) = K' Q F, (r) (DE )a ( Y ) (* f)y f p2(m .mrap/yr per uCi/sec)

Where:

6A constant of unit conversion, 10 pCi/uC1.K' =

The cow's consumption rate, in Kg/ day (wet weight),O =F

50 kg/ day. (Reg. Gaide 1.109, Table E-3).

n e receptor's milk consumption rate for age (a),U =

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

CDCM 37

.

. - , , . - . - . . . - . - . . - . . . - .

'

.

t

3.2.2.2 Surveillance Heaufzements (wi==i)

330 1/yr,Infant =

330 1/yrChild =

Teen = -400 1/yr.310 1/yrAdult =

Y = %e agricultural product {vity by un{t area of pas-P ture feed grass, in kg/m , 0.7 kg/m . (Reg. Guide1.109, Table E-15)

F" % e stable element transfer coefficients, in=

days / liter, see Table A.3-5. (Reg. Guide 1.109,Table E-1)

Fraction of deposited activity retained on cow'sr =

feed grass, r=1 for radioicxiine and r=0.2_ for par-ticulates. (Reg. Guide 1.109, Table E-15)

,

(DFL )a e h op 5 tim h fah for h i=f th radionuclide for the receptor in age group 'a',

in mrm/pC1. 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)

21 he, y constant for the i th radionuclide, in=

sec

Aw %e decay constant for ruoval of activity on lyf=

and plant surfaces by weathering, 5.73 E-7 sec(corresponding to a 14' day half-life),,

ne. transport time from pasture to cow, to milk, tot =f rewebr, in sec,1.73 E5 secs (2 days). - (Reg.'

Guide 1.109, Table E-15).'

NME: 'Ihe fractim of the year that the cow is an pasture andthe fractim of the cxw feed that is pasture <paaa isassumed to be 1.0, which is the most restrictive case.

Grass-Goat-Milk Pathway Factor, RC [D/Q)

R f[D/Q] = K' ( ) F ,(r) (DFL )a I /Y ) (8 )) t )-

ff p

(m *mram/yr per uCi/sec)

,

-

ODCM 38

i

|,

__ _ _ . . . _ . .__ . _ . _ _ . -

I|

|

3.2.2.2 Surveillance Ivxnti2mmts (ccritiran_t1 )|

MleIe!

h e g at's consumption rate, in Eg/ day (wat IQ =F weight), 6 Kg/ day. (Reg. Guide 1.109, Table E-3),

fhe transport time frun pasture to goat, to milk,t =

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 Fac-tor.

FOIE: 'Ite fracticut of the year that the goat la m pasture and ;

the fraction of the (pat feed that is pasture grass is I

asmmvi to be 1.0, whidt is the armt rmtrictivo caso.

We concentration of tritium in milk is based on the airborgeconcentration rather than the deposition. herefore, the R isybaaed on (X/ )'Q

R y [X/Q] = K'K"' F OUap (DE )a [0.75 (0.5/H]y7 p

3(mmn/yr par uC1/m )

Where:

3a constant of unit conversion, 10 gg,K"' = g

3Absolute humidity of the atnosphere, 8 gm/m ,H =

(Reg. Guide 1.109).

0.75 he fraction of total feed that is water. (NUREG=

0133)

"0.5 The ratio of the specific activity of the feed=

grass water to the atnespheric water. (NUREG 0133)

Grass-Cow-Meat Pathway Factor, R"f[D/Q)t

1[D/Q) = K' ( )Ff (r) (DFL )a I !Y ) (e~ i f)f p

(m 'mmn/yr per uC1/sec)

Where:

he stable element transfer coefficients, inF =f days /kg, Table A.3-5. (Reg. Guide 1.109, Table E-

1).

GDCM 39

I

_ _ _ _ _ _ _ - -

3.2.2.2 Surveinanan Reautremts (Oritinued), ,

U,P 'Ihe receptor's meat consumption rate for age (a),=

in kg/yr. (Reg. Guide 1.109, Table E-b).

Infant 0=

Child 41=

65Teen =

Mult 110=

g %e transport time frun pasture to recuptc12, int =

sec., 1.73 E6 (20 days) (Reg. Guide 1.109, Table E-15).

%e concentration of tritium in meat is based on its ahpconcentration rather than the deposition. %erefore, the Ir isybased on (X/Q):

[y[X/Q]=K'K"'F QU ap (DFL ),[0.75 (0.5/H)]f F 1

(mtm/yr per uCi/ra ),

Where:

All terms 'ine:1 above.

Vegetation Pathway Factor, R [D/Qj

Nan is considered to cnnsume two types of vegt4. ation (fresh andstored) that differs caly in the tine period betmen harvestand ora W on, therefore:

a)If )(e hi hR"g[D/Q]=K'[Qg+4))(DFL)a[(Ur IIf )(* )+IU gg L gYy 2(m , mr m/yr per uCi/sec)

Where:

6K' A constant of unit conversion, 10 [f.1/uCi.=

Lne consumption rate of fresh leafy vegetation byU =

athe receptor in age group (a), in kg/yr. (Reg.Guide 1.109, Table E-5).

Infant 0 kg/yr=

Child = 26 kg/yrTeen = 42 kg/yrMult = 64 kg/yr

{SU, h e consumption rate of stored vegetation by the=

receptor in age group (a), Kg/yr. (Reg. Guide1.109, Table E-5).

1

ODCM 40

i

_ _________ _

3.2.2.2 Surveillance knuiruments (Continmd)

0 kg/yrInfant =

Child = 520 kg/yrTeen = 630 kg/yrMult = 520 kg/yr

f h e fraction of the annual intake of fresh leaff=3 vegetation grown locally. (default = 1.0) (Reg.

Guide 1.109).

f ne fraction of the annual intake of stored vege-=

9 tation grown locally. (default = 0.76) (Reg. Guide1.109),

n e average time between harvest of leafy vegeta-t =g

tion and its consumptian, in seconds, 8.6 E4 secs(1 day). (Reg. Guide 1.109).

e average tine between harvest of stored vege-t =h tatlan and its consumptian, in seconds, 5.18 E6

secs (60 days) (Reg. Guide 1.109, Table E-15).2% e vegetation area density, 2.0 kg/m . (Reg. GuideY =

y3.109, Table E-15).

All other factors previously defined.

%e concentration of tritium in vegetation _is based an the air-bpe cancentration rather than the deposition. herefore, theR , is based an (X/Q):

-

1[X/Q] = K' K"' [h fL+ f ] (DFL ), [0.75 (0.5/H)]Rg 1a

3(mrun/yr per uCi/m )

Where:

All terms defined previously. All values indicated are defaultvalues frun Reg. Guide 1.109, Rev.1.

An average nonthly dose schedule should be setup to ensure Sec-tian 3.2.2 is not exceeded. %e average nonthly dose due toradiciodines, .particulates, and other radionuclides Mtich areincluded in this section should be as follows:

a. < 2.5 mran/no.

ODCM 41

l

i

3.2.2.2 Surveillance Iknuirunents (Omitinued)

If the Ironthly average dose for (a) is exceeded, it should benoted that if the release is continued at the same (or higher)frequencies or activities the quarterly limit of Section 3.2.2.awill be ex * ui.

b. < 1.25 m.sn/mo.

If the nanthly average dose for (b) is exceeded, it should benoted that if the release is continued at the same (or higher)frequencies or activities the yearly li2 nit of Section 3.2.2.bwill be exceeded.

If any of the above monthly dosos are exceeded, evaluation of thecauses should be performed and steps taken to reduce the activityor frequency of the release.

3.3 Prow Dose

'Ihe VENTIIATICN EEAUST 'IRETdMFNT SYSTEM and the WASTE GAS 10LDUPSYSTEM shall be OPERABLE ard appcapriate portions of these sys-tems shall be used to reduce releases of radioactivity when theprojected doses in 31 days due to gaseous effluent releases, fruneach unit, to areas at and beyond the SM'E BOUNDARY (see Fignm3-1) would exceed:

a. 0.2 mrad to air frm galma radiation, or

b. 0.4 mrad to air frun beta radiation, or

c. 0.3 mrun to any organ of a MEMBER OF '111E PUBLIC.

3.3.1 Ikmxii>tl rction

With radioactive gaseous waste being discharged without treatmentand in excess of the above limits, prepare and subnit to the Ccan-mission within 30 days, pursuant to h chnical Specification6.9.2, a special report that includes the follcwing information:

a. Identification of any inoperable equipment or subsystans, ardthe reason for the inoperability,

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

c. Sunnary descriptian of action (s) taken to prevent a recur-rence.

ODCM 42

3/91

3.3.2 Surveillanco Ikrs Lummw

3.3.2.1 Doses due to gaseous releases frun each unit to areas at and be-yond the SITE BOUNDARY shall be projected at least once per 31days in accordance with the following nethodology when GaseousRadeste Treatment Systans are not being fully utilized.

_ _ _ _

A 31D =.

31 T_ . _ .

Where:

D = Projectal 31 day dose31

A = Cunnlative dose for current quarter

T = Current number of days into quarter

3.3.2.2 he installed VENITEATIN EXHAUST 'IREA'INEtfr SYSTEM and NASTE GASHOLDUP SYSTEM shall be considered OPERABLE by neeting Section 3.1and 3.2 limits.

3.4 Instrmentatirm

'Ihe radioactive gaseous effluent nonitoring instrumentation chan-nels shom in Table 3-2 shall be OPERABLE with their Alann/ TripSetpoints set to ensure that the limits of Section 3.1 are notexceeded. 'Ihe Alaun/ Trip Setpoints of these channels meetingSection 3.1 shall be determined and adjusted in accordance withthe nethodology and parameters of Section 3.4.4 below.

3.4.1 Irmrifal Action

a. With a radioactive gaseous effluent nonitoring instnmenta-tion channel Alann/ Trip Setpoint less conservative than re-quiral by the above specification, immrHately suspend therelease of radioactive gaseous effluents nonitored by theaffected channel, or declare the clennel inoperable,

b. With less than the minixnum rurnber of radioactive gaseous ef-fluent nonitoring instrumentation channels OPERABLE take theACTION shown in Table 3-2. Restore the inoperable instru-nentation 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 correctedwithin the tine specified.

ODN 43

9/93

.

.

~

3.4.2 Surveillance Rxmin==mi.n <

Each radioactive gaseous effluent nonitoring instrumentationchannel shall be dm onstrated OPERABLE by performance of theCIANNEL OIECK, SOURCE OIECK, OIANNEL CALIBRATION and ANAILGOIANNEL OPERATIONAL TEST at the frequencies shown in Table 3-3.

|

|

1

,

ODCM 44;

''3/91|

1

|

1

I

.

*

TABLE 3-2

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION

MINIMUM CHANNELSINSTRUMENT OPERABLE APPLICABILITY ACTION

1. Unit Vent System

Noble Gas ActivitAlarm (GT-RE-21) y Monitor - Providing

a.1 * 40

b. Iodine Sampler 1 * 43

c. Particulate Sampler 1 * 43

d. Flow Rate N.A. *'

45

e. Sampler Flow Rate Monitor 1 * 39

2. Containraent Purge System

a. Noble Gas Activity Monitor - ProvidingAlarm and Automatic Termination ofRelease (GT-RE-22, GT-RE-33) 1 * 41

b. Iodine Sampler 1 * 43

c. Particulate Sampler- 1 * 43

d. Flow Rate N.A. * 45


ODCM 45

3/91.

_ _ _ - - _ _ _ _ - _ . . __ __ - _ __

TABLE 3-2 (Continued)

RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION

MINIMUM CHANNELSINSTRUMENT OPERABLE APPLICABILITY ACTION-

3. Radwaste Building Vent System

a. Noble Gas Activity Monitor - ProvidingAlarm and Automatic. Termination of ;

Release (GH-RE-10) 1 38,40*

b. Iodine Sampler 1* 43

c. Particulate Sampler 1 * 43

d. Flow Rate N.A. *'

.45


;

.

>

ODCM: 46 ~.

3/91-

_-

TAM E 3-2 (O mtinued)|

TABIE NrJTATIONS

* At all tines.

JCTION STATEMENTS

JCrION 38 -With the number of channels OPERAME less than mquiredby the mininum channels OPERAME Iequiranent, the con-tents of the tank (s) my be released to the environmentfor up to 14 days provided that prior to initiating therelease:

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

b. At least two technically qualified members of thefacility staff independently verify the release ratecalculations and discharge valve lineup.

Otherwise, suspend release of radioactive effluents viathis pathway.

ICTION 39 -With the number ef channels OPERAME less than requiredby the minimum enannels OPERAEE requ h at, effluentreleases via tFis pathey my continue for up to 30 daysprovided the fh.v rate is estimated at least once per 4hours.

ACTION 40 -With die number of channels OPERAME less than requiredby the minhnum channels OPERABLE requirment, effluentreleases via this pathway my continue for up to 30 daysprovided grab sanples are taken at least once per 12hours and these samples are analyzed for radioactivitywithin 24 hours.

1crION 41 -With the number of channels OPERABLE less than requiredby the minunum channels OPERAME requirment, immo-diately suspend PURGING of radioactive effluents viathis pathway.

JCTION 43 -With the number of channels OPERAME less than requiredby the minimum channels OPERAEE requiranent, effluentreleases via the affected pathey my continue for up to30 days provided samples are continuously collected withauxiliary sample equignent as required in Table 3-1.

ICTION 45 -Flow rate for this systan shall be based on fan statusand operating curves or actual n m surements.

ODCM47

3/91|

.

d'

TABLE 3-3

RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE RE0VIREMENTS

ANALOGCHANNEL MODES FOR WHICH

Ci!ANNEL SOURCE CHANNEL OPERATIONAL SURVEILLANCEINSTRUMENT CHECK CHECK CALIBRATION TEST IS RE0VIRED

1. Unit Vent System

Noble Gas ActivitProviding Alarm (y Monitor-

a.GT-RE-21) D M R(3) Q(2) *

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. Containment Purge' System

a. Nobic Gas Activity Monitor-Providing Alarm and AutomaticTermination of Release-(GT-RE-22,GT-RE-33) D P R(3) Q(1) *

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. *

;

00CM '48'

3/91

|. - _ _ _ _ _ _ _ _ - _ _ _ _ . - - - - _ - _ . _ _ _ __ . _.___. _

i

TABLE 3-3 (Continued)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE RE0VIREMENTS

ANALOGCHANNEL MODES FOR WHICH

CHANNEL SOURCE CHANNEL OPERATIONAL SURVEILLANCEINSTRUMENT CHECK CHECK CALIBRATION TEST IS REOUIRED

3. Radwaste Building Vent System

a. Noble Gas Activity Monitor-Providing Alarm and Auto-matic Termination of Release-(GH-RE-10) D,P up R(3) Q(1) *

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. *,

t

.

I

..

ODCM 49

3/91-_ _ _ _ _ - _ - _ - _ _ - _ _ _ _ _ _ . _ _ _ - . . _ . _ _ _ . - _ - _ _ _ _ - _ . _ _ _ _ - _ - - _ .

TMEE 3-3 (Otritinued)

TABLE FUPATIONS'

* At all tims.

(1) %e ANAIIG CHANNEL OPERATIONAL TEST shall also damstrate thatautomatic isolation of this pathway and centrol rocxn alaan an-nunciation as appropriate occur if any of the following condi-tions exists:

a. Instrumnt indicates masured levels above the Alam/ TripSetpoint (isolation and alam), or

b. Circuit failure (alam only), or

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

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

(2) he ANAIiX3 CHANNEL OPERATIONAL TEST shall also dmonstrate chatcontrol rocxn alann annunciation occurs if any one or ccrnbinationof the following conditions exists:

a. Instrument indicates measured levels above the alarm set-point

b. Circuit failure

c. Instrument indicates a downscale failure

d. Instrument cmtrols not set in operate mode.

(3) % e initial CHANNEL CALIBRATION shall be performed using cne ornore of the reference (gas 'r liquid and solid) standards cer-tified by the National Institute of- Standards arri Technology(NIST) or using standards that have been obtained from suppliersthat participate in masurment assurance activities with NIST.% ese standards shall permit calibrating the system over itsintended range of energy, masurenent range, and establish non-itor response to a solid calibration source. For subsequentCHANNEL CALIBRATION, NIST traceable standard (gas, liquid orsolid) may be used; or a gas, liquid, or solid source that hasbeen calibrated by relating it to equipTent that was previously(within 30 days) calibrated by the same gecxnetry and type of 'source traceable to NIST.

ODCM 50

3/91

A

:

|1

l

'INER 3-3 (Ctmtinue_d1 |InmE NC7fATIONS

(4) If flow rate is detemined by exhaust fan status arxi fan per-formance curves, the following surveillance operations shall beperfomed at least once per 18 months:

a. W e specific vent flows by direct measur m ent, or

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

c. he fan notor horsepower neasured and vent flow establishcxiby the fan's " flow-horsepower" curve.

CDCM 51

3/91

3.4.3 Airbame Radiatim Manitor Calibraticn Methodolcxw

he following nonitors are associated with gaseous releases.

Monitor ID Monitor Description Monitor Tvm !

O-GT-RE-21A Plant Unit Vent Particulate, Iodine

0-Gi-RE-10A Radweste Building Effluent Particulate, Iodine

O-GT-RE-21B Plant Unit Vent Wide Range Gas

O-GH-RE-10B Radwaste nni1 ding Effluent Wide Range Gas -

0-GT-RE-22 & 33 containment Purge Exhaust Particulate, Iodine, Gas

O-Gr-RE-31 & 32 Containment Atnosphere Particulate, Iodine, Gas !

3.4.3.1 Ihrticulate De^wetuc

Beta particulate is nonitored by a 50 mn diameter by 0.25 nmthick plastic scintillator optically coupled to a 50 nm diameterphotmultiplier tube. Bis detector shall be calibratal over its ,

range of energy and rate capabilities. 1

For energy range calibration four sources shall be used. Each i

source consists of a filter paper impregnated with a beta anit- |

ting radionuclide. %e radionuclides used should be Tc-99, Cs- I137, Cl-36, and Rh-106. Each source shall be positioned in the !

filter paper retaining ring and counted separately. We count I

rates for each radionuclide source shall be recorded and the data !plotted on a graph of cpn/uci versus average beta energy. Bis - 1

curve represents the detectors response characteristics over therange of beta energies observed. %e efficiency for setpoint |

'calculations shall be based on the efficiency of the detector forCs-137.

%e detector shall be calibrated for its rate capabilities usinga filter paper impregnated with standard activities of Cs-137. 1

Increasing anounts of a standard Cs-137 solution shall be impreg- I

nated on a filter paper. he counts per minute for each Cs-137standard shall be recorded and the data plotted on a graph of

.

counts per minute versus activity. At least three sources |

covering approximately 1/4, 1/2, and 3/4 of full scale shall bechecked.

ODCM 52

_ ______ ______ - _ _____________ _ - _ - _

|'

3.4.3.2 Iodine Dubxbur

Iodine gas is monitored by absorbing the gas on a charcoal filterelment. The charcoal filter is viewed by an NaI(Tl) integralline ganma scintillator assmbly.

Because of its short half-life and the difficulty in handlinggaseous ladine, barium sources shall be used for <w14hmtion.n e photo peaks of interest are as follows:

A. Ba-133: 356 kev game is 0.69 efficient / disintegration

B. I-131: 364 kev gamma is 0.82 efficient / disintegration

h erefore, each iodine disintegration will produce 0.82/0.69 xbarium disintegrations. Assuming that the detector efficiencyfor 356 kev is the sane as for the 364 Ke'v, the sensitivity forI-131 equals 1.19 x Ba-133 (counts / min)/uci. %e standardsources shall be constructed by impregnating a standard Ba-133solution into the charcoal filter element. We gecnetry shallsimulate the iodine retention on the first surface of the char-coal. Sources shall be prepared to cover approximately 1/4, 1/2and 3/4 of full scale. n e barium counts per minute for eachstandard shall be adjusted to iodine counts per minute as des-cribed above. W e adjusted counts per minute shall be plotted ona graph of counts per minute versus activity.

3.4.3.3 Gas Debx/wr

% e gas detectors associated with monitors O-GT-RE-22 & 33, o c -RE-31 & 32 and the low-range detectors of nonitors O-GT-RE-21Band O-GH-RE-10B are a plastic scintillator identical to the par-ticulate detector. The mid-range and high-range detectors ofntnitors O-GT-RE-21B and 0-GH-RE-10B are cadmium telluride, solidstate sensors.

1'

Sources for all gas detectors shall be produced by evacuating thesample chamber with a vacuum pump. The sample chamber then shallbe backfilled to the desired pressure with a source of standardXe-133. W e source is then counted ard the counts per minuterecorded. A graph of counts per minute versus concentration I

shall be produced frtm the data. Sources shall be prepared tocover approxhnately 1/4,1/2 and 3/4 of full scale for the de-tectors associated with nonitors O-GI-RE-22 and 33, 0-Gr-RE-31and 32 and the low-range detectors of nonitors O-GT-RE-21B and O-GH-RE-10B. . Sources shall be prepared for the mid/high rangedetector to cover two points on the mid-range scale. For AIARApurposes, response for the high-range scale shall be extrapolatedusing the data frta the mid-range calibration.

I

ODCM 53

1

_ ______--_ _________

3.4.4 Af2 borne Mtnitor Setrnints"3.4.4.1 'Ibtal Ibdv Dose Rate Setroint Calculations

'1he limit of the total body dose rate is 500 mrm/yr at the un-restricted area boundary. '1he monitor alarm / trip setpoint based -on total body dose will be calculated as follows:

Sg .< (SF x AF) x D xR (1)g t

Where

Sg= 'Ihe nonitor alarm / trip setpoint based on the totalbody dose rate.

g= Limit of 500 mrm /yr total body, conservativelyDinterpreted as a cantinuous release over a oneyear period.

SF = Normally will be set to 0.85. 'Ihis number ischosen since the gaseous nonitors are set usingXe-133 energy level. Xe-133 cmprises 85% oftotal noble gaseous activity expected. . (See USN1Table 11.1-1). If necessary the 0.85 can be fur-ther nodified to cmpensate for statistical fluc-tuations and errors of measurement.

AF = Allocation factor for each release so that simul-taneous releases can be made without exceeding thelimit. Nonrally AF is calculated as follows:

AF = _RFTF

Khere:

RF = Release flow rate of the release pointunder consideration.

TF = Total flow rate of all release points in-cluding release under consideration.

nonitor response per mrem /yr to the total body,R =

t determined accordLng to

cRt " ( (X/Q) y K

<Qf)g

ODCM 54

_ _ _ _ _ _ _ _ _. . . . . _ ..

3.4.4.1 'tutal Body Does Rate Setznint t'm1mlath (Qmtirmed)-

where

c= '1he manitor response to the gaseous effluent noblegas (uC1/cc) corresponding to grab sanple radio-nuclide concentrations.

(X/Q) = h highest calcugated annual average' atatosphericdispersion (sec/m ) at the restricted area boundary.

1= '1he total body dose factor due t 3 gamma enissionsKfran isotope 1 (mmn/yr per uCi/m ) fran Table A.1 :2.

Q. = Rate of release of noble gas radionuclide i1

(uC1/sec)(concentration of radionuclide i x releaseflow rate),

3.4.4.2 Skin Dose Rats t'm1mintica

h limit of the skin dose rate is 3000 mran/yr at the restricted;area boundary, h nonitor alarm / trip setpoint is calculated asfollows:

S # (SF x AF) x D xR (2)s- g g

Where:

S 'Ihe monitor alarm / trip setpoint based on the skin=g

dose rate.

Limit of 3000 mran/yr to the skin of the body, con-D =s servatively interpreted as a continuous. release overa one year period.

| R MW mp p Mg M & h M & '=g

body.c

| ( (X/Q) y(Lf + 1.1M ) Of)8

f.

where:

i L1= Skin dose factor due to b:t.a enissions frtm isotope -31 (mrem /yr per uC1/m ) fran Table A.1-2.

,

!1.1 = Conversion factor to mmn skin dose'per mrad air -)

dose. .j

Air dose factor due tp) ganna emissions frun isotopeM1= 1 (mrad /yr per uCi/m fran Table A.1-2.-

ODCM 55

.

_ - - . _ - . _ . _ _ _ _ _ _ . _

- - _ _ _ - _ _ _ _ _ _ _ -

.

3.4.4.2 Skin Ibse Rato Calculation (Continued)

he factors SF, AF, c, (X/Q) and O are as defined in Sectionf3.4.4.1.

%e results of equations frm Sections 3.4.4.1 and 3.4.4.2 areccmpared to detemine the snaller setpoint. %e actual monitorsetpoint is the lower of the two values.

A pre-release isotopic analysis is performd for batch releasesfrm Waste Gas Decay Tanks and Cantainment Billriing purges todetermine the identity and quantity of the principal radio-nuclides. %eam us.iate alarm / trip setpoint(s) are adjustedaccordingly to ensure that the limits of 3.1 are not exceeded.

3.4.4.3 Alert Alann Settnint Calculatims

he Noble Gas Alert Alarm for the Plant Unit Vent (0-GT-RE-21)and Radwaste Biiiding Exhaust Monitor (0-GH-RE-10), is set toalert operators to that average concentration which if maintainedfor a full year would result in the 10 CFR 50, Appendix I AnnualDose Guidelines being reached. Section 3.2.1 limits the annualdose due to noble gases to 510 mrads for ganrna radiation and 520 mrads for beta radiation. Section 3.2.2 limits the annualdose to a } EMBER OF ' HIE PUBLIC frm Iodine-131, Icdine-133, tri-tium and all radionuclides in particulate form with half-livesgreater than 8 days in gaseous effluents to 515 mrm to any or-gan. % ese two sections contain the annual dose limits due togaseous releases found in 10 CFR 50, Appeixlix I.

3.4.4.3.1 Noble Gas Alert Alarm Settnint Calculatirm

he alert alarm setpoint is the lesser of

Sy 5 (SF x AF) x Df x Ry

Sp$ (SF x AF) x Dp x Rp

|

i: I1

1

ODCM 56

_ ____________-__

3.4.4.3.1 lbble Gas Alert Alann Setznint Calculation (Omtinued)

Nhere:

Sg= Monitor setpoint based on ganna radiation.

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

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

C

R ]( = ( (X/Q) M xQf)y

Where: *

h 88 I"" I FMM =1 3

uCi/m ). See Table A.1-2.

Sp = Monitor setpoint based on beta radiation.'Df= Limit of 20 mrad /yr conservatively interpreted as a

continuous release over a one year period.

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

c

Rp = ( (X/Q) E-

N xQ1)f y

Where:

y Beta p dose factor (mrad /yr perN =

uCi/m ). See Table A.1-2.

A semi-fixed alert alann setpoint for the Plant Unit-Vent Monitor(0-GT-RE-21) and Radwaste Building Vent Monitor (0-Gi-RE-10) iscalculated using the following:

(10 mrad /vr) (.85)(AF)

Setpoint (uCi/cc) = ( (X/Q) P xM x Q) (5)g y

ODCM 57

3.4.4.3.1 mhle Gas Alert Alann Setroint Calculation (Carttirnni)

Where:

f Practionalvalueofisotopeexpected,C/g,P =f

Whexes

Concentration in uti/cc of isotope.C =1

'Ibtal Gaseous Activity frtra USAR Table 11.1-1C =T

Either unit vent flow or Radwaste 9diding ventAF =

flow divided by the cambined flow of the unit ventand Radwaste Bd1 ding vent.

Vent flow rate in cc/sec.0 =

Isotopes used and P values are as follows:y ,

ISOIOPE gKr-85M .018Kr-87 .010Kr-88 .033Xe-133M .017Xe-133 .851Xe-135 .051

Should this sani-fixed alert alana cause a continuous alann con-dition, then actual setpoints will be calculated.

3.4.4.4 Particulate And Iodine Alanu Setrnints

Setpoints for the gaseous effluent particulate and iodine chan-nels are set using Cs-137 MFC for particulates and I-131 MPC foriodines. 'Ihe following is the calculation used:

(MPC ) (AF) (SF)1

Setpoint (uC1/cc) (Q) (X/Q)=

,

1

ODCM 58 I11

.

.

3.4.4.4 Iurticulate And Iodine Alaun Setpoints (Cintinued)

Where:

-105 x 10 uC1/cc for Cs-137MPC =y

1 x 10-10 uC1/cc for I-131=

as definal pzwiouslyAF =

.0625 for I-131 *SF =

.9375 for Cs-137 *=

* derived fran ratio of isotope activity (either I-131 or Cs-137) to sum of activity of Cs-137.andI-131 found in USAR Table 11.1-1 for reactorcoolant.

3Vent flow in M /sec0 =

'Ihis will provide the hi alarm setpoint. 'Ihe alert alarm set-point is 10% of the hi alann setpoint.

1

Il

'

I|

|

ODCM 59

I|

i. . .

fIctmr 3.1

BOUNDARY FOR GASEOUS EFFLUENTS'l

.

/; 1

i :> a~

:- ~

j E 'E,

mese'

=mpcocEscocY---

eoe est.ows cw(tacn sth . a$tricted met

W

I ; 6 % r=74 aX.

.; }f _~_ x.

--_. .m ~.

***-,

7> >

\ .sama.c e=. e

j

eccane g

(*, 9"N aw ooo

.Q.

)-..

., . -. .

*. '

-.

**===c.*

I % 7 ..-

wCLF CREEK CENFJMTWC STATMNUntT No, t -

Cr4, , 3.1

mer far c s-s (tri-*swe> osas cosens tmet.

. - .(s ) 4 \ .

vy<.

= = , . . . . - .sg .aue

-

==.

, .__.4*"- *

60.

i

e

%

O

>

3/91,

4.0 4UIE DOSE

'Ihe annual (Calendar year) dose or dose cmmitrmnt to any MEMBEROF '1EE PUBLIC due to releases of radioactivity and to radiationfr m uranium fuel cycle sources shall be limited to less than orequal to 25 mmns to the whole body or any organ, except the thy-roid, which shall be limited to less than or equal to 75 mrems.

4.1 Hmrxfial Action

With the calculated doses frm the release of radioactive ma-terials in liquid or gaseous effluents m @ ng twice the limitsof Section 2.2a, 2.2b, 3.2.la, 3.2.lb, 3.2.2.a and 3.2.2b calcu-latian should be nede including direct radiation contributionsfrm the units and frm outside storage tanks to detemine whe-ther the above limits of Section 4.0 above have been exceeded.If such is the case, prepare and subnit to the Cmmissian within30 days, pursuant to Technical Specification 6.9.2, a specialreport that defines the corrective action to be taken to reducesubsequent releases to prevent recurrence of exceeding the abovelimits. 'lhis special report, as defined in 10 CFR 20.405c, shallinclude an analysis that estimates the radiatica exposure (dose)to a MEMBER OF 'IHE PUBLIC frm uranium fuel cycle sources, in-cluding all effluent pathways and direct radiation, for the ca-1endar year that includes the release (s) covered by this report.It shall also describe levels of radiation and cancentrations ofradioactive material involved, and the cause of the exposure le-vels or cancentrations. If the estimated dose (s) exceeds theabove limits, and if the release condition resulting in violationof 40 CFR Part 190 has not already been corrected, the specialreport shall incitrie a request for a variance in accordance withthe provisians of 40 CFR Part 190. Suhnittal of the report isconsidered a timely request, and a variance is granted untilstaff action an the request is emplete.

4.2 SurvallLince Requimacnts

.

4.2.1 Cumulative dose contributions frm liquid and gaseous effluentsshall be detemined in accordance with the methodology of Sec-tions 2.2 and 3.2 at least once per 31 days when the release ofradioactive naterials in liquid or gaseous effluents exceed twicethe limits of Section 2.2a, 2.2b, 3.2.la, 3.2.lb, 3.2.2a and3.2.2b. Otherwise, no further evaluation is required.

4.2.2 Cumulative dose contribution frm direct radiation frm the reac-tor unit and frm Radwaste storage tanks shall be determinedutilizing the results of routine plane perineter surveys, TIDdata or a cmbinatian of both, when necessary. 'Ihis requirmentis applicable only under ccnditions set forth in the Imedialaction above.

ODCM 61

3/91

.

. - - .. .. .-.

;

4

5.0 RADImmTCAL ENVIIOGGREE MMPITRDG PROGRAM

mis section describes the Radiological Envisuu=utal Monitoring i

[email protected] specified in Section 6.8.4 F of the Wolf Creek TechnicalSpecifications.

1

5.1 Manitrrirn Prua-. )

Table 5-1 provides a schedule which describes the pathways, spe-cific locations, sample collection frequencies, and analyses tobe perfonned to inplanent the Radiological Environmental Moni- 4

toring Fr%tcuu. |I

Figures 5.1 through 5.5 cantain maps depicting == ling locations j'

in relation to the NCES site. Table 5-2 lists distances and di-rections to these locations frun the NOGS site.

. i

Table 5_-3 lists required detection capabilities for the analyses -jperformed.

5.2 Iand Use census'

A land Use Census shall be conducted annually during the growing .season to identify the nearest (1) mi.lk animal,-(2) residence,and (3) garden of greater than 500 square feet producing broad-leaf vegetatian* in each of the 16 noteorological sections withinfive miles of the NOGS site. Methods-shall be used in conductingthe census that provide the best results,'such as docr-to-door.,

surveys, telephone surveys, censulting the U.S.D.A office in *

Burlingtm, inspection of aerial phovphs of the area, or re-viewing leasing records for area farms and residences.

If a location (s) is identified which yields a calculated dose or'

dose cmmitznent (via the same exposure pathway) 20% greater thanat a location frm which sanples are currently being obtained, ;

the new location (s) shall be added to the Radiological Environ- 1

mental ibnitoring Prwmn within 30 days as d='hi in Table 5-1, Note (1). We indicator sanpling location (s) having the -low-est calculated dose or dose cmmitment may then be deleted frmthe nonitoring pre . %e revision to Table 5-1 and the cor-responding Figure (s) as'a result of such substitutions shall be

,

hmmted in accordance with Section 6.14 of the Wolf Creek ;

Technical Specifications. i

ne results of the Iand Use Census shall be included in the An- i

nual Radiological Environmental Operating Report ~ described in ,

Section 7.1. |

:j

* Broad leaf vegetation mmling of available vegetation may be )perfonmd at the site boundary in each of two different direction |

sectors with the highest predicted D/Qs in lieu of the gardencensus. Specifications for broad leaf vegetation sampling inTable 5-1, Part 4.c. shall be followed, including analysis ofcontrol sanples. |

ODCM 62 1

3/91

|

_ _

5.3 Interhwhuy n= arf roi Puuu-

The analysis laboratory contracted to analyze samples frtxn theRadiological Enviromental Monitoring Prwuun participates in theEPA laboratory Interemparison Picquuu. Results of interun-parisons are provided to NCNOC saniannually in revisions to theanalysis laboratory's Quality Control manual, a controlled copyof which is maintained by the NCNOC Nuclear Services Division.

A summary of interrmmrison results shall be included in theAnnual Radiological Environmental Operating Report described inSection 7.1.

5.4 Heoortirri Recuirtwrits

5.4.1 Annual Buiinlmical Favim-mbd Operatirx2 Report

Ub neet the requiratents of Wolf Creek 7bchnical Specification6.9.1.3, the Annual Radiological Environ:tental Operating Reportcovering the previous year of operation shall be subnitted to theNRC by May 1 of each year. The centent of this report is des-cribed in Section 7.1.

5.4.2 Special Hrxxnts

A special report shall be prepared and subnitted to the NRCwithin 30 days if levels of radioactivity as a result of planteffluents detected in an environmental medium at a specified loc-ation exceed the reporting levels of Table 5-4 when averaged overany calendar quarter. The special report ehall identify thecause(s) for exceeding the limit (s) and define the corrective

|

actions to be taken to reduce radioactive effluents so that the I

potential annual dose * to a nember of the public is less than the !calendar year limits of Wolf Creek Technical Specification '

6.8.4.e. When one or nore of the radionuclides in Table 5-4 aredetected in the sampling nelium, this report shall be subnittedif:

4

'

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

.

When radionuclides other than those in Table 5-4 are detected and I

are the result of plant effluents, this report shall be subnitted I

if the potential annual dose * to a uuth of the public frun all i

radionuclides is equal to or greater than the calendar yar li-mits of 7bchnical Specification 6.8.4.e.

4

*7he methodology and parameters used to estimate the potential |annual dose to a uud;er of the public shall be indicated in thisreport.

ODCM 633/91

TABLE 5-1

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

Number of SamplesExposure Pathway / and Sample Type and Frequency

Sample Type Sample Locations (I) Collection Frecuency of Analysis

1. AIRBORNE FIGURES 5.1 & 5.5

Radiciodine and Samples fron. five locations Continuous sampler Analyze radiciodineParticulates operation with sample canister weekly for

Samples from locations near collection weekly, or I-131.the site boundary in three sec- more frequently iftors having the highest calcu- required by dustlated annual average D/Q (Loca- loading.tions 2,3 and 37 on Figure 5.1);

Analyze particulate fil-Sample from the vicinity of ter weekly for gross betaa community having the activity (2); performhighest calculated annual quarterly gamma isotopicaverage D/Q (Location 32 analysis (3) composite (byon Figure 5.1, New Strawn); location).Sample from a control loca-tion 10-20 miles distant ina low D/Q Sector (Location40 on Figure 5.5). (11)

ODCM 643/91

_-__- __ _________ ____-_ . - _ - _ _ . _. -

TABLE 5-1 (Con't.)

RADIOLOGICAL ENVIROMENTAL MONITCRING PROGRAM


Sample Type Sample Locations (1)_ Collection Frequency of Analysis

2. DIRECT RADIATION FIGURES 5.2 and 5.5(4)

40 routine monitoring sta- Quarterly Gama dose quarterlytions with two or more dosi-meters measuring dose contin-uously, placed as follows:

An inner ring of stations, onein each meteorological sector0 - 3 mile range from the site(Locations 1 - 14, 18, 26 -31,37, and 38 on Figure 5.2).

An outer ring of stations, onein each meteorological sectorin the 3 to 5 mile range fromthe site (Locatior.s 15, 16, 17,19 -22, 24, 25 and 32 - 36 onFigure 5.2).

The balance of the stations tobe placed in special interestareas such as population cen-ters (Locations 23 and 32),nearby residences (Many loca-tions are near a residence),schools (Location 23), and inone or two areas to serve ascontrol stations 10 - 20 milesdistant ~from the site (Loca-tions 39 and 40 on Figare 5.5).(11)

ODCM 653/91

TABLE 5-1 (Con't.)

_ RADIOLOGICAL ENVIROSENTAL MONITORING PROGRAM


Sample Type , Sample Locations (1) Collection Frecuency of Analysis

3. WATERBORNE FIGURE 5.3

Surface One sample upstream (5)(Loca- Monthly grab sample Monthly gamma isotopiction MUSH on Figure 5.3) and analysis (3) and com-one sample downstream (Loca- posite for tritiumtion DC on Figure 5.3). analysis quarterly.

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

analysis.Indicator samples at locationshydrologically downgradient ofthe site (Locations C-10, C-49and D-65 on Figure 5.3); con-trol sample at a location hydro-logically upgradient of the site(Location B-12 on Figure 5.3).(6)

Drinking Sample of :nunicipal water sup Monthly composite (7) Monthly gama isotopicply at an indicator location analysis (3) and grossdownstream of the site (Loca- beta analysis of compositetion LW-40 on Figure 5.5); con- sample. Quarterly tritiumtrol sample from location ep- analysis of composites (8).stream of the site (LocationBW-15 on Figure 5.3).

Shoreline One sample from the vicinity Semiannually Semiannual gama iso-Sediment of Wolf Creek Cooling Lake topic analysis (3)

discharge cove (Location DCon Figure 5.3).

03CM 66 i

3/91___ __ ____________ - _ _ _ ..

TABLE 5-1 (Con't.)

RADIOLOGICAL ENVIR0fffMTAL MONITORING PROGRAM

Number of Samples '

Exposure Pathway / :nd Sample Type atd FrequencySample Type Sample Locations (1) Collection Frecuency of Analysis

4. INGESTION FIIGURES 5.4 AND 5.5

Milk Samples from milking animals at Semimonthly while Gamma isotopic analysisthree indicatcr iocations with- animals are on pasture (3) and I-131 analysisin 5 miles of the site having (April to November); of each sample.the highest dose poter.tial (cur- monthly at other timesrently there are no locations (December-March)(9) ,

producing milk for human con-sumption within 5 miles of thesite); one sample from a ccntrollocation greater than 10 milesfrom the site (Location S-3 onFigure 5.5). (11).

Fish Indicator samples of 1 to 3 re- Semiannually Gamma isotopic analysiscreationally important species (3) on edible portions.from Wolf Creek Cooling Lake(several sampling areas indica-ted in Figure 5.4); control sam-*

ples of similar species from,

John Redmond Reservoir Spillway(indicated on Figure 5.4).

t

Food Products Samples of-available broadleaf Monthly when avail- Gamma isotopic analysisvegetation from two indicator able (9) (3) on edible portions.locations with highest calcu-lated annual average D/Q (Loca-tions A-1 and G-1 and alternateLocation R-1 on Figure 5.4); sam-ple of similar broadleaf vegeta-tion from a control locationgreater than 1G miles from thesite in a low D/Q sector (Loca-tion S-4 on Figure 5.5).(11)

ODCM 673/91

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - - _ _ - .. . . . . . . ..

|

l

TABLE 5-1 (Con't.)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

l

Number of SamplesiExposure Pathway / and Sample Type and Frequency i

Sample Tvoe Sample Locations (1) Collection Freauency of Analysis

4. INGESTION (cont'd) FIGURES 5.4 and 5.5

| Food Products Sample of crops irrigated with At time of harvest (10) Gamma isotopic analysis| water from the Neosho River (3) on edible portions.

downstream of the Neosho River-,

| Wolf Creek confluence (Loca-tions will vary from year toyear, e.g., location NR-D1 and

Iand NR-D2 on Figure 5.5).

:

ODCM 683/91.

_. __ __ _ _ - - - _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ = _ _ _ _ _ _ __

TNEE 5-1 (GN'T. )

TNH2 NCTlATIGE

(1) Deviations are permitted frm the required swnnling schedule ifspecimns are unobtainable due to hazardous canditions, seasonalunavailability, nalfunction of automatic sampling equipuent, andother legitJnate reasons. If sreimns are unobtainable due tosampling equipnent malfunction, every effort shall be nede tocmplete corrective action prior to the end of the next samplingperiod. All deviations frm the annUng schedule shall be do-cumnted in the Annual Radiological Environmental Operating Re-port described in Section 7.1. ,

It is recognized that, at tines, it nay not be possible orpracticable to continue to obtain samples of the media of choiceat the nost desired location or tim. In these instances,suitable specific alternative media and locations may be chosenfor the particular pathway in questian and appropriate substi-tutions nede within 30 days. Revisions to this Table and to thecouespculing Figure (s) as a result of such substitutions shallbe documnted in accordance with Section 6.14 of Wolf CreekTechnical Specifications. This devmmtation shall provide in-fornation identifying the cause of the unavailability of samplesfor that pathway and justifying the selection of the new loca-tion (s) for obtaining samples.

(2) Airborne particulate sample filters shall be analyzed for grossbeta radioactivity 24 hours or nore after sampling to allow forRn-220 and Rn-222 daughter decay. If gross beta activity in airparticulate samples is greater than 10 tines the yearly mean ofcontrol samples, ganna isotopic analysis shall be performed onthe individual samples.

(3) Ganna isotopic analysis means the identification and quan-tification of ganna-emitting radianuclides that nay be at-tributable to the effluents frm the facility.

(4) One or nere instruments, such as a pressurized ion chamber, formeasuring and recording dose rate continuously may be uscd inplace of, or in addition to, integrating dosimeters. For thepurposes of this table, a thernoluminescent dosimeter (TLD) isconsidered to be one phosphor; two or nore phosphors in a packetare considered as two or nore dosimeters. Film badges shall notbe used as dosimeters for measuring direct radiation. The 40stations is not an absolute number. The number of direct rad-iation natitoring stations nay be reduced according to geogra-phical limitations, e.g., sme sectors are over water so thatthe number of dosineters nay be reduced accordingly. The fre-quency of analysis or readout for the TLD syst m depends uponthe characteristics of the specific systm used and is selectedto obtain optinum dose infornation with minimal fading.

ODCM 69

3/91

TMER 5-1 (CDPT. )

TABLE ICIATIONS

(5) The " upstream" sample is taken at a distance beyond significantinfluence of the discharge.

(6) G mund water samples shall be taken when this source is tappedfor drinking or irrigaticn purposes in areas where the hydraulicgradient or recharge s uperties are suitable for contaminaticn.

(7) A composite sample is one in which the quantity (aliquot) ofliquid sampled is consistent over the n=nHng period and inwhich the method of sampling employed results in a srm4mn thatis representative of the liquid cancentrate. In this svguuu,cmposite sample aliquots shall be collected at time intervalsthat are very short (e.g., every two hours) relative to the cm-positing period (e.g., nanthly) in order to assure obtaining arepresentative sample.

(8) If the dose calculated for consumption of water (using ODCMmethodology and parameters) exceeds one milliran per year, cm-posite n=nling at the indicator location shall be perfonnedevery two weeks and I-131 analysis shall be performed on thecmposite samples.

(9) Milk and broadleaf vegetation samples are often tannrnrily, butnot pennanently, unavailable at the scheduled sample collectiontines. Alternate sampling locations may therefore be listed inthe Table and used at these times to provide continued moni-toring of these pathways. If samples are considered perrranentlyunavailable at a location, another location will be selected (ifavailable) as described in ?bte (1).

(10) If harvest occurs nore than once a year, sampling shall be per-fonned chring each discrete harvest. If harvest occurs contin-uously, sampling shall be monthly. Attention shall be paid toincluding sanples 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 accor-dance with the distance and wind direction criteria, other sitesthat provide valid background data may be substituted.

ODCM 70

3/91

TABLE 5-2

SAMPLING LOCATION NUMBERS, DISTANCES (miles) AND DIRECTIONS

TLD and Air Particulate

Location Distance / Location Distance / Location Distance / Location Distance /Number Direction Number Direction Number Direction Number Direction

1 1.4/N 11 1.5/E 21 3.8/S 31 3.0/WNW2 2.7/N 12 1.8/ESE 22 4.1/SSW 32 3.2/WNW3 3.0/NNE 13 1.5/SE 23 4.5/SW 33 3.7/WNW4 4.0/NNE 14 2.6/SE 24 4.1/WSW 34 4.0/NW5 4.0/NE 15 4.5/ESE 25 3.6/W 35 4.6/NNW6 4.4/ENE 16 4.2/E 26 2.6/WSW 36 4.2/N7 1.9/NE 17 3.6/SE 27 2.1/SW 37 2.1/NNW8 -1.6/NNE 18 3.2/SSE 26 2.8/SW 38 1.2/NW9 2.0/ENE 19 4.0/SSE 29 2.6/SSW 39 13.0/N

10 2.4/ENE 20 3.3/S 30 2.2/W 40 >15.0/WNW

Groundwater Drinkina Water Surface Water

B-12 2.2/NNE BW-15 3.9/SW MUSH 3.6/WC-10 2.8/W LW-40 10/SSE DC 0.6/WNWC-49 2.9/SWD-65 3.9/S

Milk and Food Products

A-1 1.4/N R-1 2.1/NNWG-1 1.6/SE S-3 >15.0/WNW

S-4 >15.0/WNW

Fish Shoreline Sediments Irriaated Crops

WCCL DC 0.6/WNW NR-01 9.2/5JRR .4/W NR-D2 >10/S

ODCM - 71

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

.

TABLE 5-3

DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS (1)

LOWER LIMIT OF DETECTION (LLD) (2,3)

.

ANALYSIS WATER AIRBORNEPARTIgULATE FISH MILK FOOD PRODUCTS SEDIMENT(pCi/1) OR GAS (pCi/m ) (pCi/kg, wet) (pCi/l)_ (pCi/kg, wet) .(pCi/kg. dry)

Gross Beta 4 0.01

H-3 2000(4)

Mn-54 15 130

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

4

I

ODCM. 72-3/91

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

_T_NG 5-3 (CIN'T. )

TABLE N7IATICIE

(1) '1his list does not mean that only these nuclides are to be cen-siderai. Other peaks that are identifiable, together with thoseof the above nuclides, shall also be analyzed and reported inthe Annual Radiological Environ e ntal Operating Report describedin Section 7.1.

(2) Required detection capabilities for thenroluminescent dosimetersused for ~nvirone ntal measurements shall be in~accordance withthe rectm mndations of RegulatorfGuide 4.13, Revision 1, 1977.

(3) 'Ihe IID is defined, as the smallest concentration of radioactivematerial in a sample that will yield a net count, above systanbackground, that will be detected with 95% prnhability with only5% probability of falsely concluding that a blank observationrepresents a "real" signal.

For a particular measurement systan, which may include radio-chanical separation:

4.66 Sb

E V 2.22 Y exp (- 2 4 t)

Where:

IID the "a priori" lower limit of detection (picoCuries per=

unit mass or volume),

b the standard deviation of the background counting rateS =

or of the counting rate of a blank sample as apywyriate(counts per minute),

the counting efficiency (counts per disintegration),E =

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

2.22 = the number of disintegrations per minute per picocurie,

the fractional radiochanical yield, when applicable,Y =

Jnuclide (s$)ve decay ccnstant for the pattimlar radio-the radica=

, and

At the elapsed time between sample collection, or end of=

the sample collection period, and tine of counting (s).

Typical values of E, V, Y, and 4. t should be usai in the cal-culation.

ODCM 733/91

.

TAME 5-3 (G N'T.)

TAEE WIATIGE

It should be recxx3nized that the UD is defined as an a priori(before the fact) limit representing the capability of a mea-sursent systan and not as an a posteriori (after the fact)limit for a particular measuratent. Analyses- shall be perfonmdin such a nenner that the statal HDs will be achieved underroutine conditions. Occasionally background fluctuations, un-avoidable small sample sizes, the presence of interfering nuc-lides, or other uncontrollable circumstances may render theseUDs unachievable. In such cases, the contributing factorsshall be identified and described in the Annual RadiologicalEnvironmental Operating Report described in Section 7.1.

(4) UD for drinking ster samples. If no drinking ster patheyexists, a value of 3000 pCi/ liter may be used.

(5) H D for drinking m ter samples. If no drinking m ter pathwayexists, the HD of ganma isotopic analysis may be used.

ODCM 74

3/91

TABLE 5-4

REPORTING LEVELS FOR RADI0 ACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES'

REPORTING LEVELS

ANALYSIS WATER AIRBORNEPARTIgULATE FISH MILK FOOD PRODUCTS(pCi/l) OR GAS (pCi/m ) (pCi/kg, wet) (pCi/1) (pCi/kg, wet)

H-3 20,000*

Mn-54 1,000 30,000

Fe-59 400 10,000

Co-58 1,000 30,000

Co-60 300 10,000

Zn-65 300 20,000

Zr-Nb-95 400

I-131 2 0.9 3 100

Cs-134 30 10 1,000 60 1,000

Cs-137 50 20 2,000 70 2,000

Ba-La-140 200 300

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

ODCM 753/91

1

y ws

FIGURE 5.1

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^

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.

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AIRBORNE PATHWAY SAMPLING LOCATIONS

+- AIRBORNE PARTICULATE. AND RADIOlODINE

.

ODCM 76

.. .

I

FIGURE-5.2

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!

DIRECT RADIATION PATHWAY ' SAMPLING LOCATIONS

*- TLD LOCATIONS

|

l1

OECM 77

.1

I

FIGURE 5.3

' \ {A h~-~-- - ~~~-

at B /, ,,

3 I- Xc- CP Q j'"| )

[ Dg----- ,

k,Ji: 3i ,A,_

i, s

'TEAbT '-,

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~

) L-- --

( 'K(_ }'

,

%fd !# I ?>// et4

cht w x syx "_

r ' -; f ppy \ wp-~~ ~

,..

'N;, K , .

___

3n ![ | bd

WATERBORNE PATHWAY SAMPLING LOCATIONS

*-DRINKING WATER A-SURFACE WATER

u-GROUND WATER v-SHORELINE SEDIMENT

ODCM 78

__ _ _ _ _ - _ _ _ _ _ _ .

. ..

FIGURE 5.4

\ {A h

\\ d_

|C'

i

..Th ' '

| p~J )P ' ^ ' ----

i_

, ,.

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j%e' h4 8 y/x g/'L N / rhe -

--- -~~

(G,~

/ \ j,

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----

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INGESTION PATHWAY SAMPLING LOCATIONS

a-FOOD PRODUCTS

E-FISH (WCCL) A-FISH (JRR)

|

ODCM 79

.

.

_ _ - . . _ ._

FIGURE'5.5. :

ph m - ; - - -

|-- - _= g

O*

OLD U.S.50

8 E l.!wavanthso wtr

I'

.

F AS 113 3

HM18 SUMMIT'

. E

J) gs-< . s u,ta

og i F..,,,!,

IS-3 s

E 3 ! |.E !I !< pwe,

$ ]'New

-. , -

"mEE|R*

6

k) EKFAS to F e

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I

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83 3I

un-ose *

M ONOLEY~

w .

{g .-

.

un-os f f'""**

DISTANT SAMPLING LOCATIONSe-TLD s-DRINKING . WATER l

i

A- MILK *-BROADLEAF VEGETATION /IRRIGATED CROPS

oDcM so

_ _ _ - _ _ _ _ _ _ _ - _ _ _ - _ - _ _ _ _ _ . -_ _ _ _ _ _ _ _ _ _

6.0 BASES

The bases cantained on the survmiing pages sumarizes the gen-eral requirements of Section 2.0, 3.0, 4.0 and 5.0 of the ODCM.

Sectim 2.0 Lianid Effluents|

Section 2.1 Caumdaation-

This section is provided to ensure that the concentration of rad-ioactive naterials released in liquid mate effluents to UN-RESTRICIED AREAS will be less than the concentration levels spe-!

cified in 10 CFR Part 20, Appendix B, Table II, Column 2. Thislimitation provides additional assurance that the levels of rad-ioactive e terials in bodies of e ter in UNRES7RICIED AREAS willresult in exposures within: (1) the Section II.A design objec-

| tives of Appendix I,10 CFR Part 50, to a MEMBER OF THE PUBLIC,and (2) the limits of 10 CFR Part 20.106(e) to the population.The concentration limit for dissolved or entrained nobles gasesis based upon the assumption that Xe-135 is the controlling rad-icisotope and its MFC in air (mhmian) ms converted to anequivalent concentration in ster using the methods described inInternational Ccumission on Radiological Protection (ICRP) Pub- .jlication 2. I

The required detection capabilities for radioactive naterials inliquid e ste samples are tabulated in terms of the lower limitsof detection (LIDS). Detailed discussion of the ILD, and otherdetection limits can be found in HASL Procedures Manual, HASL-300(revised annually), Currie, L.A., " Limits for Qualitative Detec- jtion and Quantitative Determination - Application to Radio- i

chmistry," Anal. Chm. 40, 586-93 (1968), and Harte ll, J.K., |" Detection Limits for Radioanalytical Counting Techniques, "At-lantic Richfield Hanford Cmpany Report ARH-SA-215 (June 1975).

ODCM 81

3/91

_ _ _ - _ - _ _ _ _ _ _ _ _ _ _ _

Secticrt 2.2 Dose

his section is provided to impleTent the requirunents of Section~

. II.A, III.A and IV.A of Appendix I,10 CFR Part 50. - %e renedialaction implements the guides set forth in Section II.A of Appen-dix I and provides the required operating flexibility and at thesame time implanent the guides set forth in Section IV.A of Ap-pendix I to assure that the releases of radioactive material inliquid effluents to UNRESTRICI'ED AREAS will be kept "as low as isreasonably achievable." Also, for fresh water sites with drink-ing water supplies that can be potentially affected by plant ope-rations ,there is reasonable assurance that the operation of thefacility will not result in radianuclide cancentrations in thefinished drinking water that are in excess of the requirements of40 CFR Part 141. % e dose calculation methodology and parametersin the ODCM implanant the requirements in Section III.A of Ap-pendix I which specify that conformance with the guides of Ap-pendix I be shown by calculational procedures based an models anddata, such that the actual exposure of a MmBER OF '1HE PUBLICthrough aw.vg.iate pathways is unlikely to be substantially un-derestimated. 'Ihe equations specified in the CDCM for calcu-lating the doses due to the actual release rates of radioactivematerials in liquid effluents are consistent with the methodologyprovided in Regulatory Guide 1.109, "Calculatian of Annual Dosesto Man fr m Routine Releases of Reactor Effluents for the Purposeof Evaluating crrmWnce with 10 CFR Part 50, Appendix I, "Revi-sian 1, October 1977 and Regulatory Guide 1.113, " Estimating-Aquatic Dispersion of Effluents frta Accidental and RoutineReactor Releases for the Purpose of Implementing Appendix I,"April 1977.

Sectirrt 2.3 Liquid Radwnste TMumsd, System

he OPERABILITY of the Liquid Radwaste Treatment Systems ensuresthat this systen will be available for use whenever liquid ef-fluents require treatment prior to release to the environment.We requiraient that the appropriate portlans of this systen beused when specified provides assurance that the releases of ra-dioactive materials in liquid effluents will be kept "as low asis reasonably achievable." his section implanents the require-ments of 10 CPR Part 50.36a, General Design Criterion 60 of Ap-pendix A to 10 CFR Part 50 and design objective given in Sect.ianII.D of Appendix I to 10 CFR Part 50. h e specified limits go-verning the use of appropriate portions of the Liquid RadwasteTreatment System were specified as a suitable fraction of thedose design objective set forth in Section II.A of Appendix I, 10CPR Part 50, for liquid effluents.

CDCM 82

3/91

_---_____ _ _ _ _ _ _ -

Section 2.4 Radirwtive Lianid Efflumt McmitrwirriInstnmambitim

he radioactive liquid effluent instnmentation is provided to -nonitor and control, as applicable, the releases of radioactivematerials in liquid effluents during actual or potential releasesof liquid effluents. %e Alann/ Trip Setpoints for these instru-ments shall be calculated and adjusted in accordance with thenethodology and parameters in the ODCM to ensure that the,

( alann/ trip will occur prior to ex eding the limits of 10 CFR! Part 20. W e OPERABILITY and use of this instrumentation is con-I sistent with the requirements of General Design Criteria 60, 63,

and 64 of Appendix A to 10 CFR Part 50.

Sectico 3.0 Gaseous Effluents

Sectim 3.1 Dose Rate

mis section is provided to ensure that the dose at any tine atand beyond the SITE BOUNDARY frtru gaseous effluents frtrn allunits on the site will be within the annual dose limits of 10 CFRPart 20 to UNRESTRICTED AREAS. %e annual dose limits are thedoses associated with the concentrations of 10 CFR Part 20, Ap-pendix B, Table II, Column 1. Rese limits provide reasonableassurance that radioactive naterial discharged in gaseous ef-fluents will not result in the exposure of a MEMBER OF THE PUBLICin an UNRESTRICTED AREA, either within or outside the SITEBOUNDARY, to annual average concentrations exceeding the limitsspecified in Appendix B, Table II of 10 CFR Part 20 (10 CFR20.106(b)). For MEMBERS OF 3HE PUBLIC who may at tines be withinthe SITE BOUNDARY, the e r ncy of that MEMBER OF THE PUBLICwill usually be sufficiently lcw to cmpensate for any increasein the atmospheric diffusion factor above' that-for the SITEBOUNDARY. We specified release rate limits restrict, at alltines, the corresponding ganna and beta dose rates above back-ground to a MEMBER OF THE PUBLIC at or beyond the SITE BOUNDARYto less than or equal to 500 mr m s/ year to the whole body or to-

less than or equal to 3000 mrms/ year to the skin. %ese releaserate limits also restrict, at all tines the corresponding thyroid ,

dose rate above background to a child via the inhalation pathwayto less than or equal to 1500 mrms/ year.

The required detection capabilities for radioactive nuterials ingaseous waste samples are tabulated in tenns of the lower limits

i

of detection (LIDS). Detailed discussion of the LLD, and other |detection limits can be found in HASL Procedures Manual, HAST-300 '

(revised annually), Currie, L.A., " Limits for Qualitative Detec-tion and Quantitative Detennination - Application to Radio-chemistry," Anal. Chm 40, 586-93 (1968), and Hartwell, J.K.,

,

" Detection Limits for Radioanalytical Counting Techniques," At- !

lantic Richfield Hanford Cmpany Report ARH-SA-215 (June 1975). ]1

ODCM 83

3/91

.

. ---

___.___________________m

- . _ _ _ _ _ _ _ _ _ _ _ _ _ _

Sectim 3.2.1 Dme - Noble Gasm

911s section is provided to implenent the requirments of SectionII.B, III.A and IV.A of Appendix I, 10 CFR Part 50. S e reuedialaction hnplanents the guides set forth in Section II.B of Ap-pendix I and provides the required operating flexibility and atthe same thne implanent the guides set forth in Section IV.A ofAppendix I to assure that the releases of radioactive material in

gaseous effluents to UNRESTRICTED AREAS will be kept "as low asis reasonably achievable." W e surveillance requiru ents imple-mnt the requirauents in Section III.A of Appendix I that con-fonrance with the guides of Appendix I be shown by calculationals uc.ulures based on models and data such that the actual exposureof a MEMBER OF DIE PUBLIC through a p ug iate pathways is un-likely to be substantially underestimated. %e dose calculationmethodology and parameters established in the ODCM for calcu-lating the doses due to the actual release rates of radioactivematerials in gaseous effluents are consistent with the metho-dology provided in Regulatory Guide 1.109, " Calculation of AnnualDoses to Man fran Routine Releases of Reactor Effluents for thePurpose of Evaluating Compliance with 10 CFR Part 50, AppendixI," Revision 1, October 1977 and Regulatory Guide 1.111, " Methodsfor Estimating Atmospheric Transport and Dispersion of GaseousEffluents in Routine Releases from Id.ght-Water Cooled Reactors,"Revision 1, July 1977. h e ODCM equations provided for deter-mining the air doses at and beyond the SITE BOUNDARY are basedupon either the historical average or real time atmospheric con-ditions.

!

Ii

|

ODCM 84

3/91

_ _ _ _ - _ _ _ _ _ _ _

1

I

I

Sectim 3.2.2 Dose - Iodine-131 and 133 Tritim and I'

Racilanctive Material in Particulate Fbra

his section is provided to implment the requirements of Sec- )tions II.C, III.A and IV.A of Appendix I, 10 CFR Part 50. We

1

remedial actions are the guides set forth in Section II.C of Ap- |pendix I, and provide the required operating flexibility and at |the sane tine impiment the guides set forth in Section IV.A ofAppendix I to assure that the releases of radioactive naterials |in gaseous effluents to UNRESTRICIED AREAS will be kept "as low l

as is reasonably achievable." The ODCM calmlational nethodsspecified in the surveillance requirements imp 1 ment the require-ments in Section III.A of Appendix I- that confomance with theguides of Appendix I be shown by calculational procedures basedon nodels and data, such that the actual exposure of a MEMBER OFTHE PUBLIC through appropriate pathways is unlikely to be sub-stantially underestinated. W e ODCM calculational methodologyand parameters for calculating the doses due to the actual re-lease rates of the subject mat wiala are consistent with thenethodology provided in Regulatory Guide 1.109, " Calculational of ,

Annual Doses to Man frm Routine Releases of Reactor Effluentsfor the Purpose of Evaluating cnmnliance with 10 CFR Part 50,Appendix I," Revision 1, Ocbfuer 1977 and Regulatory Guide 1.111, -

" Methods for Estimating Atmospheric Transport and Dispersion ofGaseous Effluents in Routine Releases fIm Light-Water-CooledReactors," Revi.sion 1, July 1977. These equations also providefor deteunining the actual doses based upon either the historicalaverage or real time conditions. The release rate limits forIodine-131 and 133, tritium, and radionuclides in particulateform with half lives greater that 8 days are dependent upon theexisting radionuclide pathways to nan, in the areas at and beyondthe SITE BOUNDARY. The pathways that were exandned in the de-velognent of these calculations were: (1) individual inhalationof airbome radionuclides, (2) deposition of radionuclides ontogreen leafy vegetation with subsequent consumption by nan, (3)deposition onto grassy areas where milk animals and neat pro-ducing animals graze with consumption of the milk and meat bynan, and (4) deposition on the ground with subsequent exposure ofman.

Section 3.3 Gaseous Radwaste Luab=2d, Systm

The OPERABILITY of the WASTE GAS HOLDUP SYSTEM and the VENTIIA-TION EXHAUST TREATMENT SYSTEM ensures that the systems will beavailable for use whenever gaseous effluents require treatnantprior to release to the environment. The requirement that theaygusiate portions of this system be used when specified pro-vides reasonable assurance that the releases of radioactive na-terials in gaseous effluents will be kept "as low as is reason-ably achievable." mis section implements the requirments of 10CFR 50.36a, General Design Criterion 60 of Appendix A to 10 CFRPart 50 and the design objectives given in Section II.D of Ap-pendix I to '10 CFR Part 50. The specified limits governing theuse of aps us iate portions of the syst m s were specified as asuitable fraction of the dose design objectives set forth in Sec-tion II.B and II.C of Appendix I, 10 CFR Part 50, for gaseouseffluents.

ODCM 853/91

.

Section 3.4 Rutimetive Gasoous Rffhxmt RmitnringInstnanrsitatlan

he radioactive gaseous effluent instnmentation is provided tonordtor and control, as applicable, the releases of radioactivematerials in gaseous effluents during actual or potential re-leases of gaseous effluents. Se Alarm / Trip Setpoints for theseinstruments shall be adjusted to values calculated in accordancewith the nothodology and parameters in the CDCM to ensure thatthe alarm / trip will occur prior to exceeding the limits of 10 CFRPart 20. %e OPERABILITY and use of this instrumentation is con-sistent with the rapirments of General Design Criteria 60, 63and 64 of Apperdix A to 10 CFR Part 50. % e sensitivity of anynoble gas activity rnanitor used to show mpliance with thegaseous effluent release requiranents of pan 3.2 shall besuch that concentrations as low as 1 x 10 uCi/cc are neasur-able.

Section 4.0 ibtal Ihm

his section is provided to meet the dose limitations of 40 CFRPart 190 that have been incorporated into 10 CFR Part 20 by 46 FR18525. We section requires the preparation and subnittal of aspecial report denever the calmlated doses due to releases ofradioactivity and the radiation frm uranium fuel cycle sourcesexceed 25 mrms to the whole body or any organ, except the thy-rold, which shall be limited to less than or equal to 75 nuxrns.For sites containing up to four reactors, it is highly unlikelythat the resultant dose to a MEMBER OF DE PUBLIC will exceed thedose limits of 40 CFR Part 190 if the individual reactors renninwithin twice the dose design objectives of Appendix I, and ifdirect radiation doses frun the reactor units and frm outsidestorage tanks are kept small. %e Special Report will describe acourse of action that should result in the limitation of the an-nual dose to a MDEER OF HIE PUBLIC to within the 40 CFR Part 190limits. For the purposes of the Special Report, it may be as-sunod that the dose cmmitnent to the MEMBER OF HE PUELIC frmother uranium fuel cycle sources is negligible, with the excep-tion that dose contributions frm other nuclear fuel cycle facil-ities at the same site or within a radius of 8 km must be con-sidered. If the dose to any MEMBER OF HIE PUBLIC is estimatal toexceed the requirments of 40 CFR Part 190, the Special Reportwith a request for a variance (provided the release conditionsresulting in violation of 40 CFR Part 190 have not already beencorrected), in accordance with the provisions of 40 CFR 190.11and 10 CFR 20.405c, is considered to be a tinely request ard ful-fills the requirments of 40 CFR Part 190 until NRC staff actionis completed. We variance only relates to the limits of 40 CFRPart 190, and does not apply in any way to the other requirmentsfor dose limitation of 10 CFR Part 20. An individual is not con-sidered a MDEER OF DE PUBLIC during any period in which he/sheis engaged in carrying out any operation that is part of thenuclear fuel cycle. -

ODCM 86

3/91

Section 5.0 Radioloniml Envirummial Mcnitorim P1Xutau

Section 5.1 Manitorim Pru4 nun

he Radiological Enviremental Monitoring Frcxgma provides re-presentative neasurments of radiation and of radioactivenaterials in those exposure patheys and for those radionuclidesthat lead to the highest potential radiation exposures of MEMBERSOF 'IEE PUBLIC resulting frm the station operation. his nani-toring sugma implments Section IV.B.2 of Appendix I to 10 CFRPart 50 and thereby supp1ments the Radiological Effluent Moni-toring Prcxgma by verifying that the neasurable concentrations ofradioactive naterials and levels of radiation are not higher thanexpected on the basis of the effluent neasurments and thenodeling of the envitummital exposure patheys. GMance forthis nanitoring pugma is provided by the Radiological Assess-nent Branch Technical Position on Environmental Monitoring, Re-vision 1, Evudux: 1979.

%e required detection capabilities for envirormental sample ana-lyses are tabulated in tenns of the lower limits of detection(LIDS). Se IIDs are considered optimum for routine environ-nental neasurments in industrial laboratories. It should berecognized that the LID is defined as an a priori (before thefact) limit representing the capability of a measurment systsand not as an an a posteriori (after the faq limit for a par-ticular measurment.

Detailed discussion of the LID, and other detection limits, canbe found in HASL Procedures Manual, HASIr-300 (revised annually),Currie, L.A., " Limits for Qualitative Detection and QuantitativeDetermination-Application to Radiochemistry," Anal. Chem. 40,586-93 (1968), and Hartwell, J.K., " Detection Limits for Radio-analytical Counting Techniques," Atlantic Richfield Hanford Cm-pany Report ARH-SA-215 (June 1975).

Sectim 5.2 Iarri Use Cbnsus

his section is providal to erumre that clmnges in the use ofareas at and beyond the SITE BOUNDARY are identified and thatmodifications to the Radiological Envitumuial Monitoring Pro-gram given in the ODCM are made if required by the results ofthis census. Infonnation that will provide the best results, i

such as door-to-door survey, aerial survey, or consulting withlocal agricultural authorities, shall be used. Bis census sa-tisfies the requirments of Section IV.B.3 of Appendix I to 10CFR3 art 50. Restricting the census to gardens of greater than-50 m provides assurance that significant exposure pathways vialeafy vegetables will be identified and monitored since a gardenof this size is the minimum required to produce the quantity (26kg/ year) of leafy vegetables assume in Regulatory Guide 1.109 forconsumption by a child.

ODCM 87

3/91

|2

Sectim 5.2 Iand Ilse Omsus (Continued)

'Ib detemine this minimum garden size, the following assumptionswere made: (1) 20% of the garden was used for growing broad leafvegetation (i.e., simily to lettuce and mhhage), and (2) a veg-etaticn yield of 2 kg/m .

Sectim S.3 Interial --Lu.y hvinon Fruumu

'Ibe requiranent for participation in an approved Intarinhnratory ,

hvien Frugtmu is provided to ensure that independent checksan the precision and accuracy of the measurenents of radioactivematerial in envitummial sample matrices are perfonmd as partof the quality assurance pru3tmu for environental nonitoring inorder to demonstrate that the results are valid for the purposesof Section IV.B.2 of Appendix I to 10 CFR Part 50.

ODCM 88

3/91

7.0 RFARIS

7.1 Anrnni Radiological Ehvitu=5dal Operating Heoort

%e Annual Radiningical Envisuuiudal Operating Report shall in-clude summaries, interpretations, and an analysis of trends ofthe results of the radiological envisuutudal surveillance ac-tivities for the report period, incitriing a cmparison with pre-operational studies, with operational controls and with previousenvinanimial surveillance reports, and an assessment of the ob--

served impacts of the plant operation an the environment. 'Ihereports -shall also include the results of the Iand Use Censusdescribed in Section 5.2.

The Annual Radiological Environmental Operating Report shall in-clude the results of analysis of all radiological environmentalsamples and of all envituniudal radiation nmsurements takenduring the period pursuant to the locations specified in Table 5-1 as well as sunnerized and tabulated results of these analysesand measurements in the fomat of the table in the RadiologicalAssessnent Branch Technical Position, Revision 1, November 1979.In the event that scrne individual results are not avniinhle forinclusian with the report, the report shall be subnitted notingand explaining the reasons for the missing results. h missingdata shall be subnitted as soon as possible in a supplementaryreport.

'1he septis shall also include the following: a sunnary de-scriptian of the Radiological Environmental Manitoring Ptugtcuu;legible maps covering all anmpling locations keyed to a tablegiving distances and directions frm the centerline of the reac-tor; the results of licensee participation in the InterlaboratoryComparison Pwgicuu and the corrective actions being taken if thespecified program is not being perfonned as required by Section5.3; reasons for not conducting the Radiological EnvironnentalProgram as required by Section 5.1 with plans for preventing arecurrence and discussion of all deviations frm the samplingschedule of Table 5-1; discussion of envirarmental sample nea-surements that exceed the reporting levels of Table 5-4 but arenot the result of plant effluents, and discussions of allanalyses in which the IID required by Tabic 5-3 was not achiev-able.

7.2 Anntal Radimetive Effluent Relaam Hepart

'Ihe Annual Radioactive Effluent Release Report shall-include asunnary of the quantities of radioactive liquid and gaseouseffluents and solid waste released frm the Unit-as outlined inRegulatory Guide 1.21, " Measuring, Evaluating, and ReportingRadioactivity in Solid Wastes and Releases of RadioactiveMaterials in Liquid and Gaseous Effluents frm Light-Water-cooledNuclear Power Plants," Revision 1, June 1974, with data

ODCM 899/93

7.2 Annual Radimetive Efflumt Ihlease Report Mbntinwxf) f

sunnarized on a quarterly basis following the fount of AppendixB thereof. For solid estes, the fontat for Table 3 in AppendixB shall be supplemented with three additional categories: classof solid e ste (as defined by 10 CFR Part 60), type of container(e.g., LSA, Type A, Type B, large Quantity), and SOLIDIFICATIONagent or eherbent (e.g., cement, urea formaldehyde).

7he Annual Radioactive Effluent Release Report to be subnittedbefore May 1 of each year shall also include an annual summary ofhourly noteorological data collected over the previous year.This annual sumary may be either in the fann of an hour-by-hourlisting an magnetic tape of wind speed, wind direction, andatnospheric stability, and precipitation (if measured), or in thefann of joint frequency distributions of wind speed, winddirection, and at:nospheric st ability.* This same report shallinclude an assessment of the radiation doses due to theradioactive liquid and gaseous effluents released frun the Unitor Station during the previous calendar year. This same reportshall also include an assessment of the radiation doses frunradioactive liquid and gaseous effluents to MEMBERS OF THE PUBLICdue to their activities inside the SITE BOUNDARY during thereport period using historical average atmosphere canditions.All assumptions used in making these assessments, i.e., specificactivity, exposure time and location, shall be included in thesereports. The neteorological conditions concurrent with the timeof release of radioactive mamrials in gaseous effluents, asdeternined by sampling frequency and neasurenent, shall be usedfor detennining the gaseous pathway doses. The assessment ofradiation doses shall be performed in accordance with themethodology and pauudu w in the ODCM.-

Uhe Annual Radioactive Effluent Release Report to be subnittedbefore May 1 of each year shall also include an assessment ofradiation doses to the likely nost exposed MEMBER OF 7EE PUBLICfrom reactor releases and other nearby uranium fuel cyclesources, including doses fran primary effluent pathways anddirect radiation, for the previous calendar year to showconfomance with 40 CFR Part 190, " Environmental RadiationProtection Standards for Nuclear Power Operation." Acceptable

,

methods for calculating the dose contribution frcan liquid and '

gaseous effluents are given in Regulatory Guide 1.109, Rev. 1,October 1977.

The Annual Radioactive Effluent Release Report shall include: |

a. A list and description of unplanned releases fran the site toUNRESTRICI'ED AREAS of radioactive materials in gaseous andliquid effluents made during the reporting period.

ODCM 90

9/93

7.2 Arnni Railoactive Effitrrit Iblonse Ikgrrrt (Cbntinued)

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

c. Major changes to the Radwaste Treatment Systens for theperiod in which the evaluation was reviewed and accepted bythe PSRC. 'Ihe discussion of each change shall cantain:

*In lieu of sutrnission with the Annual Radioactive EffluentRelease Report, the licensee has the option of retalning thissunnary of required meteorological data on site in a file thatshall be provided to the NRC upon request.

1) A sumary of the evaluation that led to the determinationthat the change could be made in accordance with 10 CFR50.59;

2) Sufficient detailed infonration to totally support thereason for the change without benefit of additional andsupplemntal infonnation;

3) A detailed description of the equiprent, ccrnponents, andprocesses involved and the interfaces with other plantsystans.

4) An evaluation of the change which shows the predictedreleases of radioactive eterials in liquid and gaseouseffluents and/or quantity of solid waste that differ frunthose previously predicted in the license application andamendments thereto;

5) An evaluation of the change, which shows the expectedmaximum exposures to a MEMBER OF ' ale PUBLIC in the UN-RESTRICTED AREA and to the general population that differfran those previously esthnated in the license appli-cation and cme nreits thereto;

6) A ccznparison of the predicted releases of radioactivemterials, in liquid and gaseous effluents and in solidwaste, to the actaaal releases for the period prior towhen the changes are to be made;

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

8) hmrmtation of the fact that the change was revieux!and found acceptable by the PSRC.

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

ODCM 91

9/93 i:

.

J

, ., .- , . - - . .

,

g

< '

17.2. Jlnrmaal Bartirwtive Effluent Dalaama psgrwt funrwh=ri)

e A' description of the events leading to liquid holdup' tanks.or:,

gas storage tanks exceeding the limits of Technical Speci- '

fication 3.11.1.4 or 3.11.2.6 respectively.

''f. An explanation as to why the' ferability of a liquid or

gaseous effluent nonitoring instrumentaticn was not corrected awithin the time specified.

g. - A description of the events laading to a missed sample re- -quired by Table 2-1 or 3-1.

~

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1

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ODCM 92

9/93

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APPEt0IX A

,

Dose Conversion Factor Tables

ODCM A-1

,

TABLE A.1-1*

BIOAOCIMEATION FACICRS '10 BE USED IN'IME ABSE2CE OF SITE-SPECIFIC DATA

(pCi/kg per );Ci/ liter)FRESH ATER

ELEMENP FISH

H 9.0E-01C 4.6E 03Na 1.0E 02P 1.0E 05Cr 2.0E 02Nh 4.0E 02Fe 1.0E 02Co 5.0E 01Ni 1.0E 02Cu 5.0E 01Zn 2.0E 03Br 4.2E 02Rb 2.0E 03Sr 3.0E 01Y 2.5E 01Zr 3.3E 00Nb 3.0E 04Mo 1.0E 01Tc 1.5E 01Ru 1.0E 01Rh 1.0E 01Tu 4.0E 02I 1.5E 01Cs 2.0E 03Ba 4.0E 00La 2.5E 01Co 1.0E 00Pr 2.5E 01Nd 2.5E 01W 1.2E 03Np 1.0E 01

**Ag 2.3E 00 i

I**Sb 1.0E 00

I,

*Taken frcm Regulatory Guide 1.109 (Rev. 1) I**Taken frca Regulatory Guide 1.109 (Rev. 0)

|

!

ODCM A-2

.

TABLE A.1-2

DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS *

Total Body Gamma Air Beta AirDose Factor Skin Dose Factor Dose Factor Dose Factor

K L M NI IRadionuclide (mrem /vr per uCi/m3) (mrem /vrher uCi/m3) (mrad /vr per uCi/m3) (mrad /vrber uCi/m3)Kr-83M 7.56E-02** --- 1.93E+01 2.88E+02

Kr-85M 1.17E+03 1.46E+03 1.23E+03 1.97E+03

Kr-85 1.61E+01 1.34E+03 1.72E+01 1.95E+03

Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04

Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03

Kr-89 1.66E+04 1.01E+04 1.73E+04 1.06E+04

Kr-90 1.56E+04 7.29E+03 1.63E+04 7.83E+03

Xe-131M 9.15E+01 4.76E+02 1.56E+02 1.11E+03

Xe-133 2.94E+02 3.06E+02 3.53E+02 1.05E+03

Xe-133M 2.51E+02 9.94E+02 3.27E+02 1.48E+03 !

Xe-135M 3.12E+03 7.11E+02 3.36E+03 7.39E+02

Xe-135 1.81E+03 1.86E+03 1.92E+03 2.46E+03

Xe-137 1.42E+03.g 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 -2

.

i ODCM. A-3

_ . _ - _ - _ _ _ _ _ _ - - _ _ _ _ - - _ _ - - - _ _ _ _ . _ _ _ - _ _

.

.

M BLE A.2-1*

INHAIATIN DOSE FACITS mR ADULTS(MRDi PER PCI INHALED)

NUCLIDE BONE LIVER T BODY '1BYROID KIDNEY IJJNG_ GI-LLI

H 3 10 DATA 1.588-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07C 14 2.27E-06 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07NA 24 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06

P 32 1.65E-04 9.64E-06 6.26E-06 10 DATA 10 DATA 10 DATA 1.08E-05CR 51 10 DATA 10 DATA 1.25E-08 7.44E-09 2.85E-09 1.80E-06 4.15E-07MN 54 10 DATA 4.95E-06 7.87E-07 10 DATA 1.23E-06 1.75E-04 9.67E-06

MN 56 NO DATA 1.55E-10 2.29E-11 10 DATA 1.63E-10 1.18E-06 2.53E-06FE 55 3.07E-06 2.12E-06 4.93E-07 NO DATA NO DATA 9.01E-06 7.54E-07FE 59 1.47E-06 3.47E-06 1.32E-06 10 DATA 10 DATA - 1.27E-04 2.35E-05

00 58 to DATA 1.98E-07 2.59E-07 10 DATA 10 DATA 1.16E-04 1.33E-05CO 60 10 DATA 1.44E-06 1.85E-06 NO DATA NO DATA 7.46E-04 3.56E-05NI 63 5.40E-05 3.93E-06 1.81E-06 10 DATA NO DATA 2.23E-05 1.67E-06

NI 65 1.92E-10 2.62E-11 1.14E-11 10 DATA 10 DATA 7.00E-07 1.54E-06'CU 64 10 DATA 1.83E-10 7.69E-11 NO DATA 5.78E-10 8.48E-07 6.12E-06ZN 65 4.05E-06 1.29E-05 5.82E-06 NO DATA 8.62E-06 1.08E-04 6.68E-06

ZN 69 4.23E-12 8.14E-12 5.65E-13 to DATA 5.27E-12 1.15E-07 2.04E-09BR 83 10 DATA NO DATA 3.01E-08 FO DATA 10 DATA 10 DATA 2.90E-08BR 84 10 DATA 10 DATA 3.91E-08 10 DATA NO DATA NO DATA 2.05E-13

BR 85 10 DATA NO DATA 1.60E-09 NO DATA NO DATA 10 DATA LT E-24RB 86 to DATA 1.69E-05 7.37E-06 10 DATA 10 DATA 10 DATA 2.08E-06RB 88 NO DATA 4.84E-08 2.41E-08 NO DATA 10 DATA 10 DATA 4.18E-19

RB 89 NO DATA 3.20E-08 2.12E-08 10 DATA 10 DATA 10 DATA 1.16E-21SR 89 3.80E-05 NO DATA 1.09E-06 10 DATA 10 DATA 1.75E-04 4.37E-05

'SR 90 1.24E-02 10 DATA 7.62E-04 10 DATA 10 DATA 1.20E-03 9.02E-05

SR 91 7.74E-09 10 DATA 3.13E-10 NO DATA 10 DATA 4.56E-06 2.39E-05SR 92 8.43E-10 10 DATA 3.64E-11 10 DATA 10 DATA 2.06E-06 5.38E-06Y 90 2.61E-07 NO DATA 7.01E-09 10 DATA 10 DATA 2.12E-05 6.32E-05 <

Y 91M 3.26E-11 NO DATA 1.27E-12 10 D M 10 DATA 2.40E-07 1.66E-10Y 91 5.78E-05 to DATA 1.55E-06 10 DATA 10 DATA 2.13E-04 4.81E-05 :Y 92 1.29E-09 10 DATA 3.77E-11 10 DATA NO DATA 1.96E-06 9.19E-06*Taken frcm Regulatory Guide 1.109 (Rev.1)

A-4

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'IRBLE A.2-1 (cont'd) ,

INHAIATION DOSE FICIORS ECR ADUUIS(NREH PER PCI INHAIED)

NUCLIDE BONE LIVER T BODY 'IHYROID KIDNEY IDG GI-ILI

Y 93 1.18E-08 10 DATA 3.26E-10 10 DATA 10 DATA 6.06E-06 5.27E-05ZR 95 1.34E-05 4.30E-06 2.91E-06 10 DATA 6.77E-06 2.21E-04 1.88E-05ZR 97 1.21E-08 2.45E-09 1.13E-09 10 DATA 3.71E-09 9.84E-06 6.54E-05

NB 95 1.76E-06 9.77E-07 5.26E-07 D DATA 9.67E-07 6.31E-05 -1.30E-05'

MD 99 10 DATA 1.51E-08 2.87E-G. DATA 3.64E-08 1.14E-05 3.10E-05'IC 59M 1.29E-13 3.64E-13 4.63E-12 / DATA 5.52E-12 9.55E-08 5.20E-07

'IC 101 5.22E-15 7.52E-15 7.38E-14 10 DATA 1.35E-13 4.99E-08 1.36E-21RU 103 1.91E-07 10 DATA 8.23E-08 NO DATA 7.29E-07 6.31E-05 1.38E-05RU 105 9.88E-11 NO DATA 3.8SE-11 10 DATA 1.27E-10 1.37E-06 6.02E-06

RU 106 8.64E-06 NO DATA 1.09E-06 NO DATA 57E-05 1.17E-03 1.14E-041G 110M 1.35E-06 1.25E-06 7.43E-07 10 DA'IA 46E-06 5.79E-04 ~3.78E-05TE 125M 4.27E-07 1.98E-07 5.84E-08 1.31E-07 1.55E-06 3.92E-05 8.83E-06

TE 127M 1.58E-06 7.21E-07 1.96E-07 4.11E-07 5.72E-06 1.20E-04 1.87E-05TE 127 1.75E-10 8.03E-11 3.87E-11 1.32E-10 6.37E-10 8.14E-07 7.17E-06 '

TE 129M 1.22E-06 5.84E-07 1.98E-07 4.30E-07 4.57E-06 1.45E-04 4.79E-05

TE 129 6.22E-12 2.99E-12 1.55E-12 4.87E-12 2.34E-11 2.42E-07 1.96E-08TE 131M 8.74E-09 5.45E-09- 3.63E-09 6.88E-0" 3.86E-08 1.82E-05 6.95E-05TE 131 1.39E-12 7.44E-13 4.49E-13 1.17E-1 J.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-05I 130 5.72E-07 1.68E-06 6.60E-07 1.42E-04 2.61E-06 to 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 2

I 132 1.45E-07 4.07E-07 1.45E-07 1.43E-05 6.48E-07 NO DATA 5.08E-08.I 133 1.08E-06 1.85E-06 5.65E-07 2.69E-04 3.23E-06 10 DATA :1.11E-06I 134 8.05E-08 2.16E-07 7.69E-08 3.73E-06 3.44E-07 NO DATA 1.26E-10

-I 135 3.35E-07 8.73E-07 3.21E-07 5.60E-05 1.39E-06 No DATA 6.56E-07 )CS 134 4.66E-05 1.06E-04 9.10E-05 10 DATA 3.59E-05 1.22E-05 1.30E-06 -1

CS 136 4.88E-06 1.83E-05 1.38E-05 10 DATA 1.07E-05 1.50E-06 1.46E-06 |,

CS 137 5.98E-05 7.76E-05 5.35E-05 NO DATA 2.78E-05 9.40E-06 1.05E-06CS 138 4.14E-08 7.76E-08 4.05E-08 10 DATA 6.00E-08 6.07E-09 2.33E-13,EA 139 1.17E-10 8.32E-14 3.42E-12 10 DATA 7.78E-14 4.70E-07 1.12E-07-

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A-5

,

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TABm A.2-1 (cartt'd) .

INHAIATION DOSE F1CICES Im ADULTS(MREM PER PCI DEALED)

i

NUCLIDE BOPE LIVER T BODY 'IHYROID KIDNtX IDG GI-ILI

PA 140 4.88E-06 6.13E-09 3.21E-07 10 dam 2.09E-09 1.59E-04 2.73E-05BA 141 1.25E-11 9.41E-15 4.20E-13 10 DATA 8.75E-15 2.42E-07 1.45E-17BA 142 3.29E-12 3.38E-15 2.07E-13 10 DATA 2.86E-15 1.49E-07 1.96E-26

IA 140 4.30E-08 2.17E-08 5.73E-09 10 DAR 10 dam 1.70E-05 5.73E-05IA 142 8.54E-11 3.88E-11 9.65E-12 10 DAM 10 DATA 7.91E-07 2.64E-07CE 141 2.49E-06 1.69E-06 1.91E-07 NO DATA 7.83E-07 4.52E-05 1.50E-05

CE 143 2.33E-08 1.72E-08 1.91E-09 to DATA 7.60E-09 9.97E-06 2.83E-05 ;

CE 144 4.29E-04 1.79E-04 2.30E-05 to DATA 1.06E-04 9.72E-04 1.02E-04'

PR 143 1.17E-06 4.69E-07 5.80E-08 NO DATA 2.70E-07 3.51E-05 2.50E-05,

PR 144 3.76E-12 1.56E-12 1.91E-13 NO DATA 8.81E-13 1.27E-07 2.69E-18ND 147 6.59E-07 7.62E-07 4.56E-08 NO DATA 4.45E-07 2.76E-05 2.16E-05

'

W 187 1.06E-09 8.85E-10 3.10E-10 10 DATA 10 DATA 3.63E-06 1.94E-QS i

NP 239 2.87E-08 2.82E-09 1.55E-09 10 DATA 8.75E-09 4.70E-06 1.49E-05

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A-6

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TAB m A.2-2*

INHAIATICN DOSE FACIGS FOR TEENIGER(MREM PER PCI INHALED)

NUCLIDE BONS LIVER T BODY 'IHYROID KIDNEY LUTO GI-LLI

H 3 10 DATA 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07C 14 3.25E-06 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 !NA 24 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06

<

P 32 2.36E-04 1.37E-05 8.95E-06 10 DATA 10 DATA 10 DATA 1.16E-05CR 51 10 DATA NO DATA 1.69E-08 9.37E-09 3.84E-09 2.62E-06 3.75E-07MN 54 10 DATA 6.39E-06 1.05E-06 10 DATA 1.59E-06 2.48E-04 8.35E-06

MN 56 10 DATA 2.12E-10 3.15E-ll 10 DATA 2.24E-10 1.90E-06 7.18E-06 ,

FE 55 4.18E-06 2.98E-06 6.93E-07 10 DATA 10 D M 1.55E-05 7.99E-07FE 59 1.99E-06 4.62E-06 1.79E-06 10 DATA 10 DATA 1.91E-04 2.23E-05 '

CO 58 10 DATA 2.59E-07 3.47E-07 10 DA'IA 10 DATA 1.68E-04 1.19E-0500 60 10 DATA 1.89E-06 2.48E-06 10 DATA 10 DATA 1.09E-03 3.24E-05NI 63 7.25E-05 5.43E-06 2.47E-06 10 DATA 10 DATA 3.84E-05 1.77E-06

NI 65 2.73E-10 3.66E-11 1.59E-11 10 DATA 10 DATA 1.17E-06 4.59E-06CU 64 10 DATA 2.54E-10 1.06E-10 NO DATA 8.01E-10 1.39E-06 7.68E-06 '

ZN 65 4.82E-06 1.67E-05 7.80E-06 10 DATA 1.08E-05 1.55E-04 5.83E-06

ZN 69 6.04E-12 1.15E-11 8.07E-13 10 DATA 7.53E-12 1.98E-07 3.56E-08BR 83 to DATA 10 DATA 4.30E-08 10 DATA 10 DATA 10 DATA LT E-24RR 84 10 DATA 10 DATA 5.41E-08 10 DATA 10 DATA 10 DATA LT E-24

BR 85 NO DATA 10 DATA 2.29E-09 10 DATA 10 DATA 10 DATA LT E-24RB 86 ?O DATA 2.38E-05 1.05E-05 10 DATA 10 DATA 10 DATA 2.21E-06RB 88 10 DATA 6.82E-08 3.40E-08 ?O DATA 10 DATA 10 DATA 3.65E-15

RB 89 10 DATA 4.40E-08 2.91E-08 10 DATA 10 DATA NO DATA 4.22E-17SR 89 5.43E-05 NO DATA 1.56E-06 10 DATA to DATA 3.02E-04 4.64E-05SR 90 1.35E-02 NO DATA 8.35E-04 NO DATA ?O DATA 2.06E-03 9.56E-05

SR 91 1.10E-08 to DATA 4.39E-10 10 DATA 10 DATA 7.59E-06 3.24E-05SR 92 1.19E-09 10 DATA 5.08E-11 NO DATA IO DATA 3.43E-06 1.49E-05Y 90 3.73E-07 10 DATA 1.00E-08 10 DATA 10 DATA 3.66E-05 6.99E-05

Y 91M 4.63E-11 10 DATA 1.77E-12 10 DATA 10 DATA 4.00E-07 3.77E-09 t

Y 91 8.26E-05 10 DATA 2.21E-06 10 DATA 10 DATA 3.67E-04- 5.11E-05Y 92 1.84E-09 to DATA 5.36E-11 NO DATA 10 DATA 3.35E-06 2.06E-05*Taken frun Regulatory Guide 1.109 (Rev.1)

A-7

TABER A.2-2 (cont'd)

nEAIATION DOSE DCITS mR TEEMGER(MRD4 PER PCI INHALED)

?FJCLIDE BONE LIVER T BODY 'IHYROID KIDNEY IRC GI-ILI

Y 93 1.69E-08 10 DATA 4.65E-10 10 DATA 10 DATA 1.04E-05 7.24E-05ZR 95 1.82E-05 5.73E-06 3.94E-06 10 DATA 8.42E-06 3.36E-04 1.86E-05ZR 97 1.72E-08 3.40E-09 1.57E-09 NO DATA 5.15E-09 1.62E-05 7.88E-05

IB 95 2.32E-06 1.29E-06 7.08E-07 10 DATA 1.25E-06 9.39E-05 1.21E-05MD 99 10 DATA 2.11E-08 4.03E-09 10 DATA 5.14E-08 1.92E-05 3.36E-05'IC 99M 1.73E-13 4.83E-13- 6.24E-12 to DATA 7.20E-12 1.44E-07 7.66E-07

'It 101 7.40E-15 1.05E-14 1.03E-13 10 DATA 1.90E-13 8.34E-08 1.09E-16RU 103 2.63E-07 to DATA 1.12E-07 No DATA 9.29E-07 9.79E-05 1.36E-05RU 105 1.40E-10 10 DATA 5.42E-11 NO DATA 1.76E-10 2.27E-06 1.13E-05

RU 106 1.23E-05 10 DATA 1.55E-06 NO DATA 2.38E-05 2.01E-03 1.20E-04AG 110M 1.73E-06 1.64E-06 9.99E-07 10 DATA 3.13E-06 8.44E-04 3.41E-05TE 125M 6.10E-07 2.80E-07 8.34E-08 1.75E-07 NO DATA 6.70E-05 9.38E-06

TE 127M 2.25E-06 1.02E-06 2.73E-07 5.48E-07 8.17E-06 2.07E-04 1.99E-05TE 127 2.51E-10 1.14E-10 5.52E-11 1.77E-10 9.10E-10 1.40E-06 1.01E-05TE 129M 1.74E-06 8.23E-07 2.81E-07 5.72E-07 6.49E-06 2.47E-04 5.06E-05

TE 129 8.87E-12 4.22E-12 2.20E-12 6.48E-12 3.32E-11 4.12E-07 .2.02E-07TE 131M 1.23E-08 7.51E-09 5.03E-09 9.06E-09 5.49E-08 2.97E-05 7.76E-05TE 131 1.97E-12 1.04E-12 6.30E-13 1.55E-12 7.72E-12 2.92E-07 1.89E-09

TE 132 4.50E-08 3.63E-08 2.74E-08 3.07E-08 2.44E-07 5.61E-05 5.79E-05I 130 7.80E-07 2.24E-06 8.96E-07 1.86E-04 3.44E-06 10 DATA 1.14E-06I 131 4.43E-06 6.14E-06 3.30E-06 1.83E-03 1.05E-05 NO DATA 8.11E-07

I 132 1.99E-07 5.47E-07 1.97E-07 1.89E-05 8.65E-07 NO DATA 1.59E-07I 133 1.52E-06 2.56E-06 7.78E-07 3.65E-04 4.49E-06 NO DATA 1.29E-06'I 134 1.11E-07 2.90E-07 1.05E-07 4.94E-06 4.58E-07 NO DATA 2.55E-09

I 135 4.62E-07 1.18E-06 4.36E-07 7.76E-05 1.86E-06 10 DATA 8.69E-07 -CS 134 6.28E-05 1.41E-04 6.86E-05 to DATA 4.69E-05 1.83E-05 1.22E-06CS 136 6.44E-06 2.42E-05 1.71E-05 to DATA 1.38E-05 2.22E-06 1.36E-06

CS 137 8.38E-05 1.06E-04 3.89E-05 10 DATA 3.80E-05- 1.51E-05 1.06E-06CS 138 5.82E-08 1.07E-07 5.58E-08 PO DATA 8.28E-08 9.84E-09 3.38E-11BA 139 1.67E-10 1.18E-13 4.87E-12 10 DATA 1.11E-13 8.08E-07 8.06E-07'

A-8

:

|

'mB[E A.2-2 (cont'd) j

IlamIATIm DOSE F/CImS ER TEEtFGER |

(MREM PER PCI IluRLED) ;I

NUCLIDE IDE LIVER T BODY 'IEYROID KIDtEY LUNG GI-LTI

BA 140 6.84E-06 8.38E-09 4.40E-07 10 DATA 2.85E-09 2.54E-04 2.86E-05BA 141 1.78E-11 1.32E-14 5.93E-13 to DATA 1.23E-14 4.11E-07 9.33E-14IM 142 4.62E-12 4.63E-15 2.84E-13 FD DATA 3.92E-15 2.39E-07 5.99E-20

IA 140 5.99E-08 2.95E-08 7.82E-09 10 DATA 10 DATA 2.68E-05 6.09E-05IA 142 1.20E-10 5.31E-11 1.32E-11 10 DATA 10 DATA 1.27E-06 1.50E-06CE 141 3.55E-06 2.37E-06 2.71E-07 10 DATA 1.11E-06 7.67E-05 1.58E-05

CE 143 3.32E-08 2.42E-08 2.70E-09 10 DATA 1.08E-08 1.63E-05 3.19E-05CE 144 6.11E-04 2.53E-04 3.28E-05 10 DATA 1.51E-04 1.67E-03 1.08E-04PR 143 1.67E-06 6.64E-07 8.28E-08 to 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-14ND 147 9.83E-07 1.07E-06 6.41E-08 10 DATA 6.28E-07 4.65E-05 2.28E-05W 187 1.50E-09 1.22E-09 4.29E-10 10 DATA NO DATA 5.92E-06 2.21E-05

NP 239 4.23E-08 3.99E-09 2.21E-09 to DATA 1.25E-08 8.11E-06 1.65E-05

A-9

,

. _ _ _ _ _ _ _ _ _

TAB 2 A.2-3*

INHAIATION DOSE FACIGS EDR CHIID(MREM PER PCI INHALED)

NUCLTDE BOtE LIVER T BODY 'IHYIOID -KIDNEY LUNG GI-LLI

H 3 10 DATA 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07C 14 9.70E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06NA 24 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06

P 32 7.04E-04 3.09E-05 2.67E-05 10 DATA 10 DATA 10 DATA 1.14E-05CR 51 10 DATA 10 DATA 4.17E-08 2.31E-08 6.57E-09 4.59E-06 2.93E-07MN 54 to DATA 1.16E-05 2.57E-06 to DATA 2.71E-06 4.26E-04 6.19E-06

MN 56 NO DATA 4.48E-10 8.43E-11 NO DATA 4.52E-10 3.55E-06 3.33E-05FE 55 1.28E-05 6.80E-06 2,10E-06 10 DATA 10 DATA 3.00E-05 7.75E-07FE 59 5.59E-06 9.04E-06 4.51E-06 10 DATA 10 DATA 3.43E-04 1.91E-05

CO 58 10 DATA 4.79E-07 8.55E-07 10 DATA 10 DATA 2.99E-04 9.29E-06CO 60 10 DATA 3.55E-06 6.12E-06 10 DATA 10 DATA 1.91E-03 2.60E-05NI 63 2.22E-04 1.25E-05 7.56E-06 10 DATA NO DATA 7.43E-05 1.71E-06

NI 65 8.08E-10 7.99E-11 4.44E-11 NO DATA ?O DATA 2.21E-06 2.27E-05 '

CU 64 to DATA 5.39E-10 2.90E-10 NO DATA 1.63E-09 2.59E-06 9.92E-06ZN 65 1.15E-05 3.06E-05 1.90E-05 10 DATA 1.93E-05 2.69E-04 4.41E-06

'

ZN 69 1.81E-11 2.61E-11 2.41E-12 NO DATA 1.58E-11 3.84E-07 2.75E-06-BR 83 to DATA 10 DATA 1.28E-07 NO DATA 10 DATA NO DATA LT E-24BR 84 ?O DATA 10 DATA 1.48E-07 10 DATA NO DATA 10 DATA LT E-24

BR 85 10 DATA 10 DATA 6.84E-09 10 DATA 10 DATA 10 DATA LT E-24' IRB 86 10 DATA 5.36E-05 3.09E-05 10 DATA 10 DATA 10 DATA 2.16E-06 .

RB 88 to DATA 1.52E-07 9.90E-08 10 DATA 10 DATA NO DATA 4.66E-09 )RB 09 10 DATA 9.33E-08 7.83E-08 10 DATA 10 DATA 10 DATA 5.11E-10SR 89 1.62E-04 10 DATA 4.66E-06 10 DATA 10 DATA 5.83E-04 4.52E-05 i

SR 90 2.73E-02 10 DATA 1.74E-03 to DATA 10 DATA 3.99E-03 9.28E-05 |l

SR 91 3.28E-08 to DATA 1.24E-09 NO DATA 10 DATA 1.44E-05 4.70E-05- jSR 92 3.54E-09 to DATA 1.42E-10 10 DATA 10 DATA 6.49E-06 6.55E-05 )Y 90 1.11E-06 to DATA 2.99E-08 10 DATA 10 DATA 7.07E-05 7.24E-05 i

Y 91M 1.37E-10 10 DATA 4.98E-12 10 DATA NO DATA 7.60E-07- 4.64E-07|Y 91 2.47E-04 to DATA 6.59E-06 10 DATA NO DATA 7.10E-04 4.97E-05

Y 92 5.50E-09 to DATA 1.57E-10 NO DATA 10 DATA 6.46E-06 6.46E-05*Taken frun Regulatory Guide 1.109 (Rev.1)

A-104

l. .

1

l1

i

nam A.2-3 (cont'd)

INHAIATION DOSE FAC1mS 10R CHIID(MREM PER PCI INHALED)

NUCLTDE BONE LIVER T BODY 'IHYROID KIDNEY IUf0 GT-ILI

Y 93 5.04E-08 10 dam 1.38E-09 10 dam to dam 2.01E-05 1.05E-04 IZR 95 5.13E-05 1.13E-05 1.00E-05 10 dam 1.61E-05 6.03E-04 1.65E-05ZR 97 5.07E-08 7.34E-09 4.32E-09 NO DATA 1.05E-08 3.06E-05 9.49E-05

NB 95 6.35E-06 2.48E-06 1.77E-06 NO DATA 2.33E-06 1.66E-04 1.00E-05MD 99 10 dam 4.66E-08 1.15E-08 No dam 1.06E-07 3.66E-05 3.42E-051'IC 99M 4.81E-13 9.41E-13 1.56E-11 10 DATA 1.37E-11 2.57E-07 1.30E-06

'IC 101 2.19E-14 2.30E-14 2.91E-13 10 dam 3.92E-13 1.58E-07 4.41E-09RU 103 7.55E-07 10 DATA 2.90E-07 10 dam 1.90E-06 1.79E-04 1.21E-05RU 105 4.13E-10 10 DATA 1.50E-10 NO DATA 3.63E-10 4.30E-06 2.69E-05

.

RU 106 3.68D-05 10 DAR 4.57E-06 No DATA 4.97E-05 3.87E-03 1.16E-04..AG 110M 4.56E-06 3.08E-06 2.47E-06 NO dam 5.74E-06 1.48E-03 2.71E-05TE 125M 1.82E-06 6.29E-07 2.47E-07 5.20E-07 10 DATA 1.29E-04 9.13E-06

TE 127M 6.72E-06 2.31E-06 8.16E-07 1.64E-06 1.72E-05 4.00E-04 1.93E-05TE 127 7.49E-10 2.57E-10 1.65E-10 5.30E-10 1.91E-09 2.71E-06 1.52E-05TE 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-06TE 131M 3.63E-08 1.60E-08 1.37E-08 2.64E-08 1.08E-07 5.56E-05 8.32E-05TE 131 5.87E-12 2.28E-12 1.78E-12 4.59E-12 1.59E-11 5.55E-07 3.60E-07

TE 132 1.30E-07 7.36E-08 7.12E-08 8.58E-08 4.79E-07 1.02E-04 3.72E-05I 130 2.21E-06 4.43E-06 2.28E-06 4.99E-04 6.61E-06 10 dam 1.38E-06I 131 1.30E-05 1.30E-05 7.37E-06 4.39E-03 2.13E-05- 10 DATA 7.68E-07

I 132 5.72E-07 1.10E-06 5.07E-07 5.23E-05 1.69E-06 NO DATA 8.65E-07I 133 4.48E-06 5.49E-06 2.08E-06 1.04E-03 9.13E-06 10 DATA 1.48E-06I 134 3.17E-07 5.84E-07 2.69E-07 1.37E-05 8.92E-07 No DATA 2.58E-07

I 135 1.33E-06 2.36E-06 1.12E-06 2.14E-04 3.62E-06 10 DATA 1.20E-06CS 134 1.76E-04 2.74E-04 6.07E-05 10 DATA 8.93E-05 3.27E-05 1.04E-06CS 136 1.76E-05 4.62E-05 3.14E-05 NO DATA 2.58E-05 3.93E-06 1.13E-06- !

CS 137 2.45E-04 2.23E-04 3.47E-05 NO DATA 7.63E-05 2.81E-05 9.78E-071CS 138 1.71E-07 2.27E-07 1.50E-07 NO DATA 1.68E-07- 1.84E-08. 7.29E-08 i

BA 139 4.98E-10 2.66E-13 1.45E-11 10 DATA 2.33E-13 1.56E-06 1.56E-05'

!

A-11

.

!

nBIE A.2-3 (cant'd) -

INHAIATION DOSE F1CIORS R]R CHIID(MREM PER PCI INHALED)

NLCLIDE BONE LIVER T BODY 'IYWROID KIDNEY LUNG GI-LLI

BA 140 2.00E-05 1.75E-08 1.17E-06 10 DATA 5.71E-09 4.71E-04 2.75E-05BA 141 5.29E-11 2.95E-14 1.72E-12 10 DATA 2.56E-14 7.89E-07 7.44E-08BA 142 1.35E-11 9.73E-15 7.54E-13 to DATA 7.87E-15 4.44E-07 7.41E-10

IA 140 1.74E-07 6.08E-08 2.04E-08 10 DATA 10 DATA 4.94E-05 6.10E-05IA 142 3.50E-10 1.11E-10 3.49E-11 10 DATA 10 DATA 2.35E-06 2.05E-05CE 141 1.06E-05 5.28E-06 7.83E-07 10 DATA 2.31E-06 1.47E-04 1.53E-05~

CE 143 9.89E-08 5.37E-08 7.77E-09 NO DATA 2.26E-08 3.12E-05 3.44E-05CE 144 1.83E-03 5.72E-04 9.77E-05 NO DATA 3.17E-04 3.23E-03 1.05E-04PR 143 4.99E-06 1.50E-06 2.47E-07 to DATA 8.11E-07 1.17E-04 2.63E-05

PR 144 1.61E-11 4.99E-12 8.10E-13 10 DATA 2.64E-12 4.23E-07 5.32E-08ND 147 2.92E-06 2.36E-06 1.84E-07 10 DATA 1.30E-06 8.87E-05 2.22E-05W 387 4.41E-09 2.61E-09 1.17E-09 NO DATA NO DATA 1,11E-05 2.46E-05

NP 239 1.26E-07 9.04E-09 6.35E-09 to DATA 2.63E-08 1.57E-05 1.73E-05-

A-12

. - __

|4

MBM A.2-4*

INHAIATICN DOSE FACIGS KR INFANT(MREM PER PCI INHALED)

NUCLIDE BONE LIVER T BODY 7HYROID KIDNEY IUfO GI-LLI

H 3 10 DATA 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07C 14 1.89E-05 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06fNA 24 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06

P 32 1.45E-03 8.03E-05 5.53E-05 10 DATA 10 DATA 10 DATA 1.15E-05CR 51 10 DATA 10 DATA 6.39E-08 4.11E-08 9.45E-69 9.17E-06 2.55E-07MN 54 10 DATA 1.81E-05 3.56E-06 NO DATA 3.56E-06 7.14E-04 5.04E-06

MN 56 to DATA 1.10E-09 1.58E-10 NO DATA 7.86E-10 8.95E-06 '5.12E-05FE 55 1.41E-05 8.39E-06 2.38E-06 NO DATA 10 DATA 6.21E-05 7.82E-07FE 59 9.69E-06 1.68E-05 6.77E-06 10 DATA NO DATA 7.25E-04 1.77E-05

00 58 10 DATA 8.71E-07 1.30E-06 NO DATA 10 DATA 5.55E-04 7.95E-06CO 60 to DATA 5.73E-06 8.41E-06 10 DATA NO DATA 3.22E-03 2.28E-05NI 63 2.42E-04 1.46E-05 8.29E-06 10 DATA 10 DATA 1.49E-04 1.73E-06

NI 65 1.71E-09 2.03E-10 8.79E-11 10 DATA 10 DATA 5.80E-06 3.58E-05CU 64 10 DATA 1.34E-09 5.53E-10 NO DATA 2.84E-09 6.64E-06 1.07E-05ZN 65 1.38E-05 4.47E-05 2.22E-05 10 DATA 2.32E-05 4.62E-04 3.67E-05

ZN 69 3.85E-11 6.91E-11 5.13E-12 10 DATA 2.87E-11 1.05E-06 9.44E-06BR 83 10 DATA 10 DATA 2.72E-07 NO DATA 10 DATA NO DATA LT E-24BR 84 10 DATA NO DATA 2.86E-07 10 DATA NO DATA 10 DATA LT E-24

BR 85 10 DATA 10 DATA 1.46E-08 10 DATA 10 DATA 10 DATA LT E-24RB 86 NO DATA 1.36E-04 6.30E-05 10 DATA NO DATA NO DATA 2.17E-06RB 88 10 DATA 3.98E-07 2.05E-07 NO DATA 10 DATA 10 DATA 2.42E-07

RB 89 NO DATA 2.29E-07 1.47E-07 10 DATA 10 DATA NO DATA 4.87E-08SR 89 2.84E-04 10 DATA 8.15E-06 10 DATA NO DATA 1.45E-03 4.57E-05SR 90 2.92E-02 10 DATA 1.85E-03 NO DATA 10 DATA 8.03E-03 9.36E-05

SR 91 6.83E-08 NO DATA 2.47E-09 10 DATA NO DATA 3.76E-05 5.24E-05SR 92 7.50E-09 10 DATA 2.79E-10 to DATA 10 DATA 1.70E-05 1.00E-04Y 90 2.35E-06 NO DATA 6.30E-08 10 DATA 10 DATA 1.92E-04 7.43E-05

Y 91M 2.91E-10 10 DATA 9.90E-12 NO DATA NO DATA 1.99E-06 1.68E-06Y 91 4.20E-04 NO DATA 1.12E-05 10 DATA 10 DATA 1.75E-03 5.02E-05Y 92 1.17E-08 ?O DATA 3.29E-10 10 DATA 10 DATA 1.75E-05 9.04E-05*Taken fmn Regulatory Guide 1.109 (Rev.1)

A-13

_ _ _ _ _ _ _ _ _ _

TABLE A.2-4 (crut'd)

INHAIATION DOSE FAC1DRS EDR INFANT

(MRDi PER PCI INHALED)

NCELIDE BONE LIVER T BODY 'IFIROID KIDNEl InfG GI-ILI

Y 93 1.07E-07 10 DATA 2.91E-09 10 DATA 10 DATA 5.46E-05 1.19E-04ZR 95 8.24E-05 1.99E-05 1.45E-05 NO DATA 2.22E-05 1.25E-03 1.55E-05ZR 97 1.07E-07 1.83E-08 8.36E-09 NO DATA 1.85E-08 7.88E-05 1.00E-04

NB 95 1.12E-05 4.59E-06 2.70E-06 10 DATA 3.37E-06 3.42E-04 9.05E-06MD 99 to DATA 1.18E-07 2.31E-08 NO DATA 1.89E-07 9.63E-05 3.48E-05'It 99M 9.98E-13 2.06E-12 2.66E-11 10 DATA 2.22E-11 5.79E-07 1.45E-06'

'IC 101 4.65E-14 5.88E-14 5.80E-13 NO DATA 6.99E-13 4.17E-07 6.03E-07RU 103 1.44E-06 NO DATA 4.85E-07 NO DATA 3.03E-06 3.94E-04 1.15E-05RU 105 8.74E-10 NO DATA 2.93E-10 10 DATA 6.42E-10 1.12E-05 3.46E-05

RU 106 6.20E-05 NO DATA 7.77E-06 NO DATA 7.61E-05 8.26E-03 1.17E-04AG 110M ' 13E-06 5.16E-06 3.57E-06 to DAut 7.80E-06 2.62E-03 2.36E-05.

TE 125M 3.40E-06 1.42E-06 4.70E-07 1.16E-06 10 DATA 3.19E-04 9.22E-06

TE 127M 1.19E-05 4.93E-06 1.48E-0: 3.48E-06 2.68E-05 9.37E-04 1.95E-05TE 127 1.59E-09 6.81E-10 3.49E-10 1.32E-09 3.47L-09 7.39E-06 1.74E-05TE 129M 1.01E-05 4.35E-06 1.59E-06 3.91E-06 2.27E-05 1.20E-03 4.93E-05

TE 129 5.63E-11 2.48E-11 1.34E-11 4.82E-11 1.25E-10 2.14E-06 1.88E-05TE 131M 7.62E-08 3.93E-08 2.59E-08 6.38E-08 1.89E-07 1.42E-04 .'8.51E-05TE 131 1.24E-11 5.87E-12 3.57E-12 1.13E-11 2.85E-11 1.47E-06 5.87E-06

TE 132 2.66E-07 1.69E-07 1.26E-07 1.99E-07 7.39E-07 2.43E-04 3.15E-05I 130 4.54E-06 9.91E-06 3.98E-06 1.14E-03 1.09E-05 10 DATA 1.42E-06I 131 2.71E-05 3.17E-05 1.40E-05 1.06E-02 3.70E-05 NO DATA 7.56E-07

I 132 1.21E-06 2.53E-06 8.99E-07 1.21E-04 2.82E-06 10 DATA 1.36E-06I 133 9.46E-06 1.37E-05 4.00E-06 2.54E-03 1.60E-05 NO DATA 1.54E-06 ;

I 134 6.58E-07 1.34E-06 4.75E-07 3.18E-05 1.49E-06 10 DATA 9.21E-07 |

|

I 135 2.76E-06 5.43E-06 1.98E-06 4.97E-04 6.05E-06 to DATA 1.31E-06 ICS 134 2.83E-04 5.02E-04 5.32E-05 10 DATA 1.36E-04 5.69E-05 9.53E-07CS 136 3.45E-05 9.61E-05 3.78E-05 10 DATA 4.03E-05 8.40E-06 1.02E-06

|CS 137 3.92E-04 4.37E-04 3.25E-05 10 DNIA 1.23E-04 5.09E-05 9.53E-07' .

CS 138 3.61E-07 5.58E-07 2.84E-07 10 DATA 2.93E-07 4.67E-08 6.26E-07 1PA 139 1.06E-09 7.03E-13 3.07E-11 10 DATA 4.23E-13 4.25E-06 3.64E-05

A-14

i

TMER A.2-4 (cant'd)

INHAIATION DOSE F1CIORS IOR INFANT(MRD4 PER PCI 1RIALED)

FRJCLTDE DONE LIVER T TODY 'IIIYROID KIDNEY IUto GT-ILI

BA 140 4.00E-05 4.00E-08 2.07E-06 10 DATA 9.59E-09 1.14E-03 2.74E-05BA 141 1.12E-10 7.70E-14 3.55E-12 10 DATA 4.64E-14 2.12E-06 3.39E-06BA 142 2.84E-11 2.36E-14 1.40E-12 10 DATA 1.36E-14 1,11E-06 4.95E-07

IA 140 3.61E-07 1.43E-07 3.68E-08 10 DATA 10 DATA 1.20E-04 6.06E-05IA 142 7.36E-10 2.69E-10 6.46E-11 10 DATA 10 DATA 5.87E-06 4.25E-05CE 141 1.98E-05 1.19E-05 1.42E-06 to DATA 3.75E-06 3.69E-04 1.54E-05

CE 143 2.09E-07 1.38E-07 1.58E-08 to DATA 4.03E-08 8.30E-05 3.55E-05CE 144 2.28E-03 8.65E-04 1.26E-04 10 DNTA 3.84E-04 7.03E-03 1.06E-04PR 143 1.00E-05 3.74E-06 4.99E-07 PO DATA 1.41E-06 3.09E-04 2.66E-05

PR 144 3.42E-11 1.32E-11 1.72E-12 to DATA 4.80E-12 1.15E-06 3.06E-06ND 147 5.67E-06 5.81E-06 3.57E-07 10 DATA 2.25E-06 2.30E-04 2.23E-05W 107 9.26E-09 6.44E-09 2.23E-09 10 DATA ?O DATA 2.83E-05 2.54E-05

NP 239 2.65E-07 2.37E-08 1.34E-08 10 DATA 4.73E-08 4.25E-05 1.78E-05

Eg

A-15

|

|

TlWLE A.2-5*

EXTERNAL DOSE FICIORS FOR S'IANDI!G Cg)CONIAMINATED GROU!O(mran/hr per pCi/m

Element 'Ibtal Body Skin

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

'

Cu-64 1.50E-09 1.70E-09-Zn-65 4.00E-09 4.60E-09Zn-69 0.0 0.0Br-83 6.40E-11 9.30E-11Br-84 1.20E-08 1.40E-08Br-85 0.0 0.0Rb-86 6.30E-10 7.20E-10Rb-88 3.50E-09 4.00E-09Rb-89 1.50E-08 1.80E-08Sr-89 5.60E-13 6.50E-13Sr-91 7.10E-09 8.30E-09Sr-92 9.00E-09 1.00E-08Y-90 2.20E-12 2.60E-12Y-91M 3.80E-09 4.40E-09Y-91 2.40E-11 2.70E-11Y-92 1.60E-09 1.90E-09Y-93 5.70E-10 7.80E-10Zr-95 5.00E-09 5.80E-09'Zr-97 5.50E-09 6.40E-09Nb-95 5.10E-09 6.00E-09Mo-99 1.90E-09 2.20E-09Tc-99M 9.60E-10 1.10E-09Tc-101 2.70E-09 3.00E-09Ru-103 3.60E-09 4.20E-09Ru-105 4.50E-09 5.10E-09h 106 1.50E-09 1.80E-09Ag-110M 1.80E-08 2.10E-08Te-125M 3.50E-11 4.80E-11Te-127M 1.10E-12 1.30E-12Te-127 1.00E-11- 1.10E-11h 129M 7.70E-10 9.00E-10Te-129 7.10E-10 8.40E-10

*Taken frun Regulatory Guide 1.109 (Rev.1)A-16 ;

!

I

!

:

, . . .

'mB[E A.2-5 (ant'd)

EXTERNAL DTE FAC'IORS ITR STANDDC g)CCNINiINATED GROUND( 6 per pCi/m

Element Total Body Skin

h 131M 8.40E-09 9.90E-09h 131 2.20E-09 2.60E-06h 132 1.70E-09 2.00E-09

- I-130 1.40E-08 1.70E-08I-131 2.80E-09 3.40E-09I-132 1.70E-08 2.00E-08I-133 3.70E-09 4.50E-09I-134 1.60E-08 1.90E-08I-135 1.20E-08 1.40E-08Cs-134 1.20E-08 1.40E-08Cs-136 1.50E-08 1.70E- 08Cs-137 4.20E-09 4.90E-09Cs-138 2.10E-08 2.40E-08Ba-139 2.40E-09 2.70E-09Ba-140 2.10E-09 2.40E-09Ba-141 4.30E-09 4.90E-09Ba-142 7.90E-09 9.00E-09Ia-140 1.50E-08 1.70E-08Ia-142 1.50E-08 1.80E-08Ce-141 5.50E-10 6.20E-10Ce-143 2.20E-09 2.50E-09Ce-144 3.20E-10 3.70E-10Pr-143 0.0 0.0Pr-144 2.00E-10 2.30E-10111-147 1.00E-09 1.20E-09W-187 3.10E-09 3.60E-09Np-239 9.50E-10 1.10E-09

A-17

.

l

TPR E A.3-1* ;

1

DOESTION DOSE FACImS KR ADULTS(MREM PER PCI DGESTED)

IU 1IDE BONE LIVER T BODY T!WROID KIDNEY IElO GI-ILI

H 3 to DATA 1.03E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07C 14 2.84E-06 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07NA 24 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06

P 32 1.93E-04 1.20E-05 7.46E-06 10 DATA 10 DATA NO DATA 2.17E-05CR 51 10 DATA 10 DATA 2.66E-09 1.59E-09 5.86E-10 3.53E-09 6.69E-07MN 54 10 DATA 4.57E-06 8.72E-07 NO DATA 1.36E-06 10 DATA 1.40E-05

MN 56 to DATA 1.15E-07 2.04E-08 10 DATA 1.46E-07 NO DATA 3.67E-06FE 55 2.75E-06 1.90E-06 4.43E-07 NO DATA NO DATA 1.06E-06 1.09E-06-FE 59 4.34E-06 1.02E-05 3.91E-06 NO DATA NO DATA 2.85E-06 3.40E-05

CO 58 NO DATA 7.45E-07 1.67E-06 NO DATA NO DATA 10 DATA 1.51E-05CO 60 NO DATA 2.14E-06 4.72E-06 10 DATA NO DNFA 10 DATA 4.02E-05NI 63 1.30E-04 9.01E-06 4.36E-06 to DATA 10 DATA NO DATA- 1.88E-06

NI 65 5.28E-07 6.86E-08 3.13E-08 NO DATA NO DATA 10 DATA 1.74E-06CU 64 NO DATA 8.33E-08 3.91E-08 10 DATA 2.10E-07 10 DATA 7.10E-06ZN 65 4.84E-06 1.54E-05 6.96E-06 NO DATA 1.03E-05 NO DATA 9.70E-06

ZN 69 1.03E-08 1.97E-08 1.37E-09 NO DATA 1.28E-08 10 DATA 2.96E-09ER 83 NO DATA 10 DATA 4.02E-08 NO DATA 10 DATA 10 DATA 5.79E-08BR 84 10 DATA 10 DATA 5.21E-08 NO DATA NO DATA 10 DATA 4.09E-13

BR 85 10 DATA N3 DATA 2.14E-09 10 DATA NO DATA 10 DATA LT E-24RB 86 10 DATA 2.11E-05 9.83E-06 NO DATA 10 DATA 10 DATA 4.16E-06RB 88 10 DATA 6.05E-08 3.21E-08 10 DATA 10 DATA 10 DATA 8.36E-19

RB 89 10 DATA 4.01E-08 2.82E-08 10 DATA 10 DATA 10 DATA 2.33E-21SR 89 3.08E-04 10 DATA 8.84E-06 10 DATA NO DATA 10 DATA 4.94E-05SR 90 7.58E-03 10 DATA 1.86E-03 10 DATA 10 DATA NO DATA 2 19E-04

SR 91 5.67E-06 NO DATA 2.29E-07 10 DATA 10 DATA NO DATA 2.70E-05SR 92 2.15E-06 NO DATA 9.30E-08 10 DATA 10 DATA 10 DATA 4.26E-05Y 90 9.62E-09 NO DATA 2.58E-10 10 DATA 10 DATA 10 DATA 1.02E-04

Y 91M 9.09E-11 10 DATA 3.52E-12 10 DATA NO DATA NO DATA 2.67E-10Y 91 1.41E-07 10 DATA 3.77E-09 10 DATA 10 DATA NO DATA 7.76E-05Y 92 8.45E-10 10 DATA 2.47E-11 10 DATA NO DATA 10 DATA' l.48E-05~ I

*Taken fran Regulatory Guide 1.109 (Rev.1)

i

A-18 I!

,

_ - _ _ _ _ _ _ _

BBLE A.3-1 (cxmt'd)

DOESTION DOSE F1CICRS ER ADUIIIS(MRDi PER PCI DGESTED)

!OCLIDE DONE LIVER T BODY THYROID KIDNEY LUFG GI-LLI

Y 93 2.68E-09 10 D m 7.40E-11 10 DATA 10 IATA 10 DATA 8.50E-05ZR 95 3.04E-08 9.75E-09 6.60E-09 10 DATA 1.53E-08 10 DATA 3.09E-05ZR 97 1.68E-09 3.39E-10 1.55E-10 10 DATA 5.12E-10 to DATA 1.05E-04

NB 95 6.22E-09 3.46E-09 1.86E-09 10 DATA 3.42E-09 10 DATA 2.10E-0510 99 to DATA 4.31E-06 8.20E-07 10 DATA 9.76E-06 10 DATA 9.99E-06T 99M 2.47E-10 6.98E-10 8.89E-09 10 DATA 1.06E-08 3.42E-10 4.13E-07

E 101 2.54E-10 3.66E-10 3.59E-09 10 DATA 6.59E-09 1.87E-10 1.10E-21RU 103 1.85E-07 NO DATA 7.97E-08 10 DATA 7.06E-07 10 DATA 2.16E-05RU 105 1.54E-08 10 DATA 6.08E-09 to DATA 1.99E-07 10 DATA 9.42E-06

RU 106 2.75E-06 NO DATA 3.48E-07 10 DATA 5.31E-06 10 DATA 1.78E-041G 110M 1.60E-07 1.48E-07 8.79E-08 10 DATA 2.91E-07 to DATA 6.04E-05TE 125M 2.68E-06 9.71E-07 3.59E-07 8.06E-07 1.09E-05 to DATA 1.07E-05

TE 127M 6.77E-06 2.42E-06 8.25E-07 1.73E-06 2.75E-05 to DATA 2.27E-05TE 127 1.10E-07 3.95E-08 2.38E-08 8.15E-08 4.48E-07 NO DATA 8.68E-06TE 129M 1.15E-05 4.29E-06 1.82E-06 3.95E-06 4.80E-05 NO DATA 5.79E-05

'TE 129 3.14E-08 1.18E-08 7.65E-09 2.41E-08 1.32E-07 10 DATA 2.37E-08TE 131M 1.73E-06 8.46E-07 7.05E-07 1.34E-06 8.57E-06 NO DATA 8.40E-05 i

TE 131 1.97E-08 8.23E-09 6.22E-09 1.62E-08 8.63E-08 NO DATA 2.79E-09;

|

TE 132 2.52E-06 1.63E-06 1.53E-06 1.80E-06 1.57E-05 10 DATA 7.71E-05 '|I 130 7.56E-07 2.23E-06 8.80E-07 1.89E-04 3.48E-06 10 DATA 1.92E-06 1

I 131 4.16E-06 5.95E-06 3.41E-06 1.95E-03 1.02E-05 to DATA 1.57E-06-

I 132 2.03E-07 5.43E-07 1.90E-07 1.90E-05 8.65E-07 10 DATA 1.02E-07I 133 1.42E-06 2.47E-06 7.53E-07 3.63E-04 4.31E-06 ' NO DATA 2.22E-06I 134 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 to DATA 2.51E-10

I 135 4.43E-07 1.16E-06 4.28E-07 7.65E-05 1.86E-06 to DATA 1.31E-06CS 134 6.22E-05 1.48E-04 1.21E-04 NO DATA 4.79E-05 1.59E-05 2.59E-06CS 136 6.51E-06 2.57E-05 1.85E-05 10 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 to DATA 8.01E-08 7.91E-09 4.65E-13-

BA 139 9.70E-08 6.91E-11 2.84E-09 NO DATA 6.46E-11 3.92E-11 1.72E-07

A-19

li

l

r

BBLE A.3-1 (cont'd)

IlGESTION DOSE F1CIGS IIR ADUUPS(MRD4 PER PCI IletdTw)

NUCLIDE BONE LIVER T BODY THYROID KIDNEY IU1C GI-ILI

BA 140 2.03E-05 2.55E-08 1.33E-06 10 DATA 8.67E-09 1.46E-08 4.18E-05BA 141 4.71E-08 3.56E-11 1.59E-09 10 DATA 3.31E-11 2.02E-11 2.22E-17'BA 142 2.13E-08 2.19E-11 1.34E-09 to DATA 1.85E-11 1.24E-11 3.00E-26

,

IA 140 2.50E-09 1.26E-09 3.33E-10 10 DATA 10 DATA 10 DATA 9.25E-05'IA 142 1.28E-10 5.82E-11 1.45E-11 10 IRTA 10 DATA 10 DATA 4.25E-07CE 141 9.36E-09 6.33E-09 7.18E-10 to DATA 2.94E-09 10 DATA 2.42E-05-

CE 143 1.65E-09 1.22E-06 1.35E-10 10 DATA 5.37E-10 10 DATA 4.56E-05CE 144 4.88E-07 2.04E-07 2.62E-08 NO DATA 1.21E-07 10 DATA 1.65E-04PR 143 9.20E-09 3.69E-09 4.56E-10 to DATA 2.13E-09 NO DATA 4.03E-05

PR 144 3.01E-11 1.25E-11 1.53E-12 10 DATA 7.05E-12 10 DATA 4.33E-18ND 147 6.29E-09 7.27E-09 4.35E-10 10 DATA 4.25E-09 10 DATA 3.49E-05W 187 1.03E-07 8.61E-08 3.01E-08 10 DATA NO DATA NO DATA 2.82E-05

NP 239 1.19E-09 1.17E-10 6.45E-11 10 DATA 3.65E-10 NODATA 2.40E-05Sb 124** 2.80E-06 5.29E-08 1.11E-06 6.79E-09 to DATA 2.18E-06 7.95E-05_Sb 125** 1.79E-06 2.00E-08 4.26E-07 1.82E-09 NO DATA 1.38E-06 1.97E-05

Sb 126** 1.15E-06 2.34E-08 4.15E-07 7.04E-09 to DATA 7.05E-07 9.40E-05Co 57** NO DATA 1.75E-07 2.91E-07 10 DATA NO DATA NO DATA 4.44E-06

**Taken frun Regulatory Guide 1.109 (Rev. 0)

l

i

I

I;

1

A-20

I

-I

_ _ _

URB W A.3-2*

INHAIATICN DOSE FACIORS IDR TEEtGGERS(MREM PER PCI INHALED)

FRCLIDE B0ffE LIVER T BODY 7HYIOID KIDNEY LU10 GI-ILI

H 3 10 DATA 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07C 14 4.06E-06 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07NA 24 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06

P 32 2.76E-04 1.71E-05 1.07E-05 10 DATA 10 DATA 10 DATA 2.32E-05CR 51 to DATA 10 DATA 3.60E-09 2.00E-09 7.89E-10 5.14E-09 6.05E-07MN 54 10 DATA 5.90E-06 1.17E-06 NO DATA 1.76E-06 10 DATA 1.21E-05

MN 56 10 DATA 1.58E-07 2.81E-08 to DATA 2.00E-07 10 DATA 1.04E-05FE 55 3.78E-06 2.685-06 6.25E-07 to DATA 10 DMA 1.70E-06 1.16E-06FE 59 5.87E-06 1.37E-05 5.29E-06 10 DATA 10 DATA 4.32E-06 3.24E-05

CO 58 10 DATA 9.72E-07 2.24E-06 10 DATA 10 DATA 10 DATA 1.34E-05CO 60 NO DATA 2.81E-06 6.33E-06 10 DATA 10 DATA 10 DATA 3.66E-05NI 63 1.77E-04 1.25E-05 6.00E-06 10 DATA 10 DATA 10 DATA 1.99E-06

NI 65 7.49E-07 9.57E-08 4.36E-08 10 DATA 10 DATA 10 DATA 5.19E-06CU 64 10 DATA 1.15E-07 5.41E-08 10 DATA 2.91E-07 10 DATA 8.92E-06 ,

ZN 65 5.76E-06 2.00E-05 9.33E-06 10 DATA 1.28E-05 to DATA 8.47E-06

ZN 69 1.47E-08 2.80E-08 1.96E-09 10 DATA 1.83E-08 10 DATA 5.16E-08 )BR 83 10 DATA 10 DATA 5.74E-08 10 DATA NO DATA NO DATA LT E-24BR 84 10 DATA NO DATA 7.22E-08 10 DATA 10 DATA NO DATA LT E-24

BR 85 10 DATA NO DATA 3.05E-09 NO DATA 10 DATA 10 DATA LT E-24RB 86 10 DATA 2.98E-05 1.40E-05 10 DATA NO DATA NO DATA 4.41E-06RB 88 to DATA 8.52E-08 4.54E-08 to DATA 10 DATA 10 DATA 7.30E-15

RB '89 to DATA 5.50E-08 3.89E-08 10 DATA 10 DATA NO DATA 8.43E-17SR 89 4.40E-04 10 DATA 1.26E-05 10 DATA NO DATA 10 DATA 5.24E-05SR 90 8.30E-03 NO DATA 2.05E-03 NO DATA 10 DATA 10 DATA 2.33E-04

SR 91 8.07E-06 NO DATA 3.21E-07 10 DATA 10 DATA 10 DATA 3.66E-05SR 92 3.05E-06 NO DATA 1.30E-07 10 DATA 10 DATA 10 DATA 7.77E-05Y 90 1.37E-08 10 DATA 3.69E-10 NO DATA 10 DATA 10 DATA 1.13E-04

Y 91M 1.29E-10 NO DATA 4.93E-12 10 DATA 10 DATA 10 DATA 6.09E-09Y 91 2.01E-07 10 DATA 5.39E-09 NO DATA NO DATA 10 DATA 8.24E-05Y 92 1.21E-09 10 DATA 3.50E-11 10 DATA 10 DATA IO DATA 3.32E-05*Taken finn Regulatory Guide 1.109 (Rev.1)

A-21

TnBm A.3-2 (Ctmt'd.)

INGESTION DOSE FACIGS MR TEENAGERS(MREM PER PCI Ilumw)

NUCLIDE BONE LIVER T BODY 'IHYROID KIDNEY LUlG GI-ILI

Y 93 3.83E-09 10 DATA 1.05E-10 10 DATA 10 DATA 10 DATA 1.17E-04ZR 95 4.12E-08 1.30E-08 8.94E-09 10 DATA 1.91E-08 NO DATA 3.00E-05ZR 97 2.37E-09 4.69E-10 2.16E-10 to DATA 7.11E-10 10 DATA 1.27E-04

NB 95 8.22E-09 4.56E-09 2.51E-09 10 DATA 4.42E-09 10 DATA 1.95E-0510 99 10 DATA 6.03E-06 1.15E-06 NO DATA 1.38E-05 10 DATA 1.08E-05'IC 99M 3.32E-10 9.26E-10 1.20E-08 lo DATA 1.38E-08 5.14E-10 6.08E-07

TC 101 3.60E-10 5.12E-10 5.03E-09 NO DATA 9.26E-09 3.12E-10 8.75E-17RU 103 2.55E-07 10 DATA 1.09E-07 10 DATA 8.99E-07 NO DATA 2.13E-05RU 105 2.18E-08 NO DATA 8.46E-09 10 DATA 2.75E-07 NO DATA 1.76E-05

RU 106 3.92E-06 10 DATA 4.94E-07 10 DATA 7.56E-06 10 DATA 1.88E-04AG 110M 2.05E-07 1.94E-07 1.18E-07 to DATA 3.70E-07 10 DATA 5.45E-05TE 125M 3.83E-06 1.38E-06 5.12E-07 1.07E-06 10 DATA 10 DATA 1.13E-05-

TE 127M 9.67E-06 3.43E-06 1.15E-06 2.30E-06 3.92E-05 10 DATA 2.41E-05TE 127 1.58E-07 5.60E-08 3.40E-08 1.09E-07 6.40E-07 NO DATA 1.22E-05 '

TE 129M 1.63E-05 6.05E-06 2.58E-06 5.26E-06 6.82E-05 NO DATA 6.12E-05 ;

TE 129 4.48E-08 1.67E-08 1.09E-08 3.20E-08 1.88E-07 NO DATA 2.45E-07 ,

TE 131M 2.44E-06 1.17E-06 9.76E-07 1.76E-06 1.22E-05 10 DATA 9.39E-05'

TE 131 2.79E-08 1.15E-08 8.72E-09 2.15E-08 1.22E-07 10 DATA 2.29E-09

TE 132 3.49E-06 2.21E-06 2.08E-06 2.33E-06 2.12E-05 to DATA 7.00E-05 !I 130' 1.03E-06 2.98E-06 1.19E-06 2.43E-04 4.59E-06 10 DATA 2.29E-06 |I 131 5.85E-06 8.19E-06 4.40E-06 2.39E-03 1.41E-05 to 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-07I 133 2.01E-06 3.41E-06 1.04E-06 4.76E-04 5.98E-06 10 DATA 2.58E-06I 134 1.46E-07 3.87E-07 1.39E-07 6.45E-06 6.10E-07 10 DATA 5.10E-09

I 135 6.10E-07 1.57E-06 5.82E-07 1.01E-04 2.488-06 10 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. iCS 136 8.59E-06 3.38E-05 2.27E-05 10 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-06CS 138 7.76E-08 1.49E-07 7.45E-08 NO DATA 1.10E-07 1.28E-08- 6.76E-11BA 139 1.39E-07 9.78E-11 4.05E-09 lo DATA 9.22E-11 6.74E-11 1.24E-06

A-22

.- . -. - .- -.. -. - -. .. = .

B B[E A.3-2-(Otmt'd.) 4

DGESTICN DOGE FACIORS FIR TEEt@GERS .

.(MREM PER PCI DGESTED)

NUCLIDE DONE LIVER T BODY 'IHYROID KIDNEY Ill?C GI-ILI,

'l- BA 140 2.84E-05 3.48E-08 1.83E-06 NO DATA 1.18E-08 2.34E-08 4.38E-05 ;

BA 141 6.71E-08 5.01E-11 2.24E-09 NO DATA 4.65E-11 3.43E-11 '1.43E-13 ';BA 142 2.99E-08 2.99E-11 1.84E-09 10 DATA 2.53E-11 1.99E-11 9.18E-20

IA 140 3.48E-09 1.71E-09 4.55E-10 NO DATA NO DATA 20 DATA 9.82E-05IA 142 1.79E-10 7.95E-11 1.98E-11 NO DATA NO DATA NO DATA 2.42E-06CE 141 1.33E-08 8.88E-09 1.02E-09 NO DATA 4.18E-09' NO DATA 2.54E-05 '

,

CE 143 2.35E-09 1.71E-06 1.91E-10 NO DATA 7.67E-10 NO DATA 5.14E-05 :CE 144 6.96E-07 2.88E-07 3.74E-08 NO DATA 1.72E-07 NO DATA 1.75E-04PR 143 1.31E-08 5.23E-09 6.52E-10 10 DATA 3.04E-09 NO DATA ~4.31E-05 ''!

PR 144 4.30E-11 1.76E-11 2.18E-12 NO DATA 1.01E-11 NO DATA 4.74E-14ND 147 9.38E-09 1.02E-08 6.11E-10 10 DATA 5.99E-09 NO DATA 3.68E-05' *

W 187 1.46E-07 1.19E-07 4.17E-08 NO DATA 10 DATA No DATA 3.22E-05

NP 239 1.76E-09 1.66E-10 9.22E-11 NO DATA '5.21E-10 NO DATA 2.67E-05Sb 124** 3.87E-06 7.13E-08 1.51E-06 8.78E-09 10 DATA 3.38E-06 7.80E-05Sb 125** 2.48E-06 2.71E-08 5.80E-07 2.37E-09 to DATA 2.18E-06 1.93E-05

:

Sb 126** 1.59E-06 3.25E-08 5.71E-07 8.99E-09 NO DATA 1.14E-06 9.41E-05Co 57** NO DATA 2.38E-07 3.99E-07 10 DATA NO DATA NO DATA 4.44E-06 '

**Taken frtra Regulatory Guide 1.109 (Rev. 0) ;

y;

:1

I

i

A-23

.

.~p 4 ,. n y a v- , - w '=

_ _ _ __ _ _ - _ . _ . . _ _ < _ _ . -

-

|

)~|

|

'IRBM A.3-3*

IIGESTIW DOSE FICIGS KR CHIID(MRD4 PER FCI IIGESTED) |

|

NUCLIDE BONE LIVER T BODY THYROID KIONEY LUfG GI-LLI

H 3 10 DATA 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07.C 14 1.21E-05 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06- 2.42E-06NA 24 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06

P 32 8.25E-04 3.86E-05 3.18E-05 NO DATA 10 DATA 10 DATA -2.28E-05CR 51 NO DATA 10 DATA 8.90E-09 4.94E-09 1.35E-09 9.02E-09 4.72E-07MN 54 NO DATA 1.07E-05 2.85E-06 NO DATA 3.00E-06 NO DATA 8.98E-06

MN 56 NO DATA 3.34E-07 7.54E-08 10 DATA 4.04E-07 NO DATA 4.84E-05-FE 55 1.15E-05 6.10E-06 1.89E-06 10 DATA 10 DATA 3.45E-06 1.13E-06' i

FE 59 1.65E-05 2.67E-05 1.33E-05 NO DATA 10 DATA 7.74E-06 ~2.78E-05

CO 58 NO DATA 1.80E-06 5.51E-06 NO DATA 10 DATA NO DATA 1.05E-05-CO 60 NO DATA 5.29E-06 1.56E-05 10 DATA 10 DATA NO DATA 2.93E-05-NT 63 5.38E-04 2.88E-05 1.83E-05 10 DATA NO DATA NO DATA- 1.94E-06

NI 65 2.22E-06 2.09E-07 1.22E-07 10 DATA NO DATA NO DATA 2.56E-05CU 64 NO DATA 2.45E-07 1.48E-07 NO DATA 5.92E-07 NO DATA 1.15E-05

'

ZN 65' 1.37E-05 3.65E-05 2.27E-05 NO DATA 2.30E-05 NO DATA 6.41E-06'

ZN 69 4.38E-08 6.33E-08 5.85E-09 NO DATA 3.84E-08 to DATA 3.99E-06BR 83 NO DATA 10 DATA 1.71E-07 10 DATA 10 DATA 10 DATA LT E-24'BR 84 NO DATA NO DATA 1.98E-07 10 DATA 10 DATA 10 DATA LT E-24

BR 85 NO DATA NO DATA 9.12E-09 10 DATA 'NO DATA NO DATA LT E-24 !RB 86 to DATA 6.70E-05 4.12E-05 NO DATA NO DATA NO DATA 4.31E-06 iRB 88 NO DATA 1.90E-07 1.32E-07 10 DATA NO DATA NO DATA 9.32E-09 ;

RB 89 10 DATA 1.17E-07 1.04E-07 NO DATA NO DATA 10 DATA 1.02E-09 jSR 89 1.32E-03 10 DATA 3.77E-05 NO DATA 10 DATA NO DATA ' 5.11E-05 -SR 90 1.70E-02 to DATA 4.31E-03 NO DATA NO DATA NO DATA 2.29E-04

SR 91 2.40E-05 10 DATA 9.06E-07 NO DATA 10 DATA- NO DATA 5.30E-05' USR 92 9.03E-06 NO DATA 3.62E-07 10 DATA NO DATA 10 DATA 1.71E-04 i

Y 90 4.11E-08 NO DATA 1.10E-09 10 DATA - NO DATA NO DATA 1.17E-04

Y 91M 3.82E-10 10 DATA 1.39E-11 10 DATA 10 DATA 10 DATA 7.48E-07 ;

Y 91 6.02E-07 10 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*Taken frun Regulatory Guide 1.109 (Rev.1)

A-24

l-. - _ _ .

1

_ _ _ _

!

TABm A.3-3 (Cbnt'd)

DEESTION DOSE FICIORS KR CHIID I

(MREM PER PCI DUtam)

NUCLIDE BONE LIVER T BODY 'IHYROID KIDNEY LU?G GI-ILI

Y 93 1.14E-08 to dam 3.13E-10 10 DATA 10 DAM NO dam 1.70E-04ZR 95 1.16E-07 2.55E-08 2.27E-08 to dam 3.65E-08 NO DATA 2.66E-05.ZR 97 6.99E-09 1.01E-09 5.96E-10 10 DATA 1.45E-09 to DATA 1.53E-04

NB 95 2.25E-08 8.76E-09 6.26E-09 NO dam 8.23E-09 10 dam 1.62E-05MO 99 NO DATA 1.33E-05 3.29E-06 10 DATA 2.84E-05 NO DATA 1.10E-05'IC 99M 9.23E-10 1.81E-09 3.00E-08 NO DATA 2.63E-08 9.19E-10 1.03E-06

'IC 101 1.07E-09 1.12E-09 1.42E-08 to DATA 1.91E-08 5.92E-10 3.56E-09RU 103 7.31E-07 10 DATA 2.81E-07 10 DATA 1.84E-06 NO DATA 1.89E-05RU 105 6.45E-08 10 DATA 2.34E-08 10 DATA 5.67E-07 10 DATA 4.21E-05 >

RU 106 1.17E-05 to DATA 1.46E-06 10 DATA 1.58E-05 NO DATA 1.82E-041G 110M 5.39E-07 3.64E-07 2.91E-07 to DATA 6.78E-07 10 DATA 4.33E-05TE 125M 1.14E-05 3.09E-06 1.52E-06 3.20E-06 10 DATA 10 DATA 1.10E-05

TE 127M 2.89E-05 7.78E-06 3.43E-06 6.91E-06 8 24E-05 NO DATA 2.34E-05 ,

TE 127 4.71E-07 1.27E-07 1.01E-07 3.26E-07 1.34E-06 10 DATA 1.84E-05TE 129M 4.87E-05 1.36E-05 7.56E-06 1.57E-05 1.43E-04 10 DATA 5.94E-05

TE 129 1.34E-07 3.74E-08 3.18E-08 9.56E-08 ~3.92E-07 NO DATA 8.34E-06TE 131M 7.20E-06 2.49E-06 2.65E-06 5.12E-06 2.41E-05 to DATA 1.01E-04TE 131 8.30E-08 2.53E-08 2.47E-08 6.35E-08 2.51E-07 10 DATA 4.36E-07

TE 132 1.01E-05 4.47E-06 5.40E-06 6.51E-06 4.15E-05 10 DATA 4.50E-05I 130 2.92E-06 5.90E-06 3.04E-06 6.50E-04 8.82E-06 NO DATA 2.76E-06I 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 10 DATA 1.73E-06 '

I 133 5.92E-06 7.32E-06 2.77E-06 1.36E-03 1.22E-05 10 DATA 2.95E-06I 134 4.19E-07 7.78E-07 3.58E-07 1.79E-05 1.19E-06 10 DATA 5.16E-07

I 135 1.75E-06 3.15E-06 1.49E-06 2.79E-04 4.83E-06 to DATA 2.40E-06CS 134 2.34E-04 3.84E-04 8.10E-05 to DATA 1.19E-04 4.27E-05 2.07E-06CS 136 2.35E-05 6.46E-05 4.18E-05 10 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-06CS 138 2.28E-07 3.17E-07 2.01E-07 10 DATA 2.23E-07 2.40E-08 1.46E-07 i

BA 139 4.14E-07 2.21E-10 1.20E-08 to DATA 1.93E-10 1.30E-10 2.39E-05

1

A-25

_.

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

B Bm A.3-3 (O mt'd),

1'

IlOESTION DOSE FACICRS KR OIIID(MRDi PER PCI INtam)

i|

NUCLIDE BONE LIVER T BODY '11NROID KIDNEY IUtG GI-LLI

BA 140 8.31E-05 7.28E-08 4.85E-06 10 DATA 2.37E-08 4.34E-08 4.21E-05BA 141 2.00E-07 1.12E-10 6.51E-09 to DATA 9.69E-11 6.58E-10 1.14E-07BA 142 8.74E-08 6.29E-11 4.88E-09 to DATA 5.09E-11 3.70E-11 1.14E-09

;

IA 140 1.01E-08 3.53E-09 1.19E-09 10 DATA NO DATA 10 DATA 9.84E-05 .

IA 142 5.24E-10 1.67E-10 5.23E-11 10 DATA 10 DATA NO DATA 3.31E-05'

CE 141 3.97E-08 1.98E-08 2.94E-09 NO DATA 8.68E-09 10 DATA 2.47E-05]

CE 143 6.99E-09 3.79E-06 5.49E-10 to DATA 1.59E-09 10 DATA 5.55E-05 !CE 144 2.08E-06 6.52E-07 1.11E-07 to DATA 3.61E-07 10 DATA 1.70E-04PR 143 3.93E-08 1.18E-08 1 & E-09 10 DAM 6.39E-09 10 DATA 4.24E-05

PR 144 1.29E-10 3.99E-11 6.49E-12 NO DATA 2.11E-11 10 DATA 8.59E-08ND 147 2.79E-08 2.26E-08 1.75E-09 to DATA 1.24E-08 to DATA 3.58E-05W 187 4.29E-07 2.54E-07 1.14E-07 to DATA 10 DATA NO DATA 3.57E-05

NP 239 5.25E-09 3.77E-10 2.65E-10 NO DATA 1.09E-09 10 DATA 2.79E-05Sb 124** 1.11E-05 1.44E-07 3.89E-06 2.45E-08 10 DATA 6.16E-06 .6.94E-05Sb 125** 7.16E-06 5.52E-08 1.50E-06 6.63E-09 NO DATA 3.99E-06 1.71E-05

Sb 126** 4.40E-06 6.73E-08 1.58E-06 2.58E-08 NO DATA 2.10E-06 8.87E-05_Co 57** 10 DATA 4.93E-07 9.98E-07 10 DATA NO DATA 10 DATA 4.04E-06

**Taken fmn Regulatory Guide 1.109 (Rev. 0)

,

A-26

.

.

t

TAB W A.3-4*

IIGESTICN DOSE FACIORS FOR INFANT(MRD4 PER PCI INumrw)

NUCLIDE BONE LIVER T BJDY 'IHYROID KIDNEY IRC GI-LLI

H 3 10 DATA 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 ,

C 14 2.37E-05 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06NA 24 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1iO1E-05

P 32 1.70E-03 1.00E-04 6.59E-05 10 DATA 10 DATA 10 DATA 2.30E-05CR 51 10 DATA 10 DATA 1.41E-08 9.20E-09 2.01E-09 1.79E-08 4.11E-07MN 54 10 DATA 1.99E-05 4.51E-06 10 DATA 4.41E-06 10 DATA 7.3]E-06

MN 56 10 DATA 8.18E-07 1.41E-07 to DATA 7.03E-07 10 DATA 7.43E-05FE 55 1.39E-05 8.98E-06 2.40E-06 10 DATA 10 DATA 4.39E-06 1.14E-06FE 59 3.08E-05 5.38E-05 2.12E-05 10 DATA 10 DATA 1.59E-05 2.57E-05

CO 58 10 DATA 3.60E-06 8.98E-06 10 DATA 10 DATA 10 DATA 8.97E-06CO 60 10 DATA 1.08E-05 2.55E-05 10 DATA 10 DATA 10 DATA 2.57E-05NI 63 6.34E-04 3.92E-05 2.20E-05 NO DATA 10 DATA 10 DATA 1.95E-06

NI 65 4.70E-06 5.32E-07 2.42E-07 10 DATA 10 DATA 10 DATA 4.05E-05CU 64 10 DATA 6.09E-07 2.82E-07 10 DATA 1.03E-06 10 DATA 1.25E-05ZN 6.5 1.84E-05 6. 31E- 05 2.91E-05 NO DATA 3.06E-05 10 DATA 5.33E-05

ZN 69 9.33E-08 1.68E-07 1.25E-08 10 DATA 6.98E-08 to DATA 1.37E-05BR 83 10 DATA 10 DATA 3.63E-07 10 DATA NO DATA 10 DATA LT E-24BR 84 NO DATA 10 DATA 3.82E-07 NO DATA 10 DATA 10 DATA LT E-24

BR 85 10 DATA 10 DATA 1.94E-08 10 DATA NO DATA NO DATA LT E-24RB 86 NO DATA 1.70E-04 8.40E-05 10 DATA NO DATA 10 DATA 4.35E-06RB 88 10 DATA 4.98E-07 2.73E-07 10 DATA 10 DATA 10 DATA 4. 85E-07

RB 89 NO DATA 2.86E-07 1.97E-07 NO DATA 10 DATA NO DATA 9.74E-08SR 89 2.51E-03 NO DATA 7.20E-05 10 DATA 10 DATA NO DATA 5.16E-05SR 90 1.85E-02 10 DATA 4.71E-03 10 DATA 10 DATA NO DATA 2.31E-04

SR 91 5.00E-05 NO DATA 1.81E-06 NO DATA NO DATA 10 DATA 5.92E-05SR 92 1.92E-05 10 DATA 7.13E-07 10 DATA 10 DATA 10 DATA 2.07E-04Y 90 8.69E-08 10 DATA 2.33E-09 10 DATA 10 DATA NO DATA 1.20E-04

Y 91M 8.10E-10 10 DATA 2.76E-11 NO DATA NO DATA 10 DATA 2.70E-06Y 91 1.13E-06 10 DATA 3.01E-08 10 DATA 10 DATA NO DATA 8.10E-05Y 92 7.65E-09 10 DATA 2.15E-10 10 DATA NO DATA 10 DATA 1.46E-04*Taken fraa Regulatory Guide 1.109 (Rev.10

A-27

TABLE A.3-4 (Cbnt'd)

IIGESTION DOSE FAC'IGS IOR INFAITT(MREM PER PCI INFaw)

NUCLIDE BONE LIVER T BODY '11EROID KIDNEY LUfC GI-ILI

Y 93 2.43E-08 10 DATA 6.62E-10 10 DATA 10 dam 10 DATA 1.92E-04ZR 95 2.06E-07 5.02E-08 3.56E-08 to DATA 5.41E-08 10 DATA 2.50E-05ZR 97 1.48E-08 2.54E-09 1.16E-09 10 DATA 2.56E-09 10 DATA 1.62E-04

NB 95 4.20E-08 1.73E-08 1.00E-08 -10 dam 1.24E-08 10 DATA 1.46E-05NO- 99 to DATA 3.40E-05 6.63E-06 10 DATA 5.08E-05 NO DATA 1.12E-05'IC 99M 1.92E-09 3.96E-09 5.10E-08 NO DATA 4.26E-00 2.07E-09 1.15E-06

'IC 101 2.27E-09 2.86E-09 2.83E-08 NO dam 3.40E-08 1.56E-09 4.86E-07RU 103 1.48E-06 NO dam 4.95E-07 to dam 3.08E-06 NO DATA 1.80E-05RU 105 1.36E-07 to DATA 4.58E-08 10 DATA 1.00E-06 NO DATA 5.41E-05

RU 106 2.41E-05 to DATA 3.01E-06 10 DATA 2.85E-05 10 DATA 1.83E-041G 110M 9 96E-07 7.27E-07 4.81E-07 10 DATA 1.04E-06 NO dam 3.77E-05TE 125M 2.33E-05 7.79E-06 3.15E-06 7.84E-06 NO DATA NO DATA 1.11E-05

TE 127M 5.85E-05 1.94E-05 7.08E-06 1.69E-05 1.44E-04 NO DATA 2.36E-05TE 127 1.00E-06 3.35E-07 2.15E-07 8.14E-07 2.44E-06 NO DATA 2.10E-05TE 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 10 DATA 2.27E-05TE 131M 1.52E-05 6.12E-06 5.05E-06 1.24E-05 4.21E-05 10 DATA 1.03E-04TE 131 1.76E-07 6.50E-08 4.94E-08 1.57E-07 4.50E-07 10 DATA 7.11E-06

TE 132 2.08E-05 1.03E-05 9.61E-06 1.52E-05 6.44E-05 10 DATA 3.81E-05I 130 6.00E-06 1.32E-05 5.30E-06 1.48E-03 1.45E-05 NO dam 2.83E-06 j

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 10 DATA 2.73E-06I 133 1.25E-05 1.82E-05 5.33E-06 3.31E-03 2.14E-05 NO DATA 3.08E-06I 134 8.69E-07 1.78E-06 6.33E-07 4.15E-05 1.99E-06 NO DATA 1.84E-06 i

;

I 135 3.64E-06 7.24E-06 2.64E-06 6.49E-04 8.07E-06 to dam 2.62E-06 ICS 134 3.77E-04 7.03E-04 7.10E-05 10 DATA 1.81E-04 7.42E-05 1.91E-06

'

CS 136 4.59E-.05 1.35E-04 5.04E-05 to DATA 5.38E-05 1.10E-05 2.05E-06i

CS 137 5.22E-04 6.11E-04 4.33E-05 10 DATA 1.64E-04 6.64E-05 1.91E-06 iCS 138 4.81E-07 7.82E-07 3.79E-07 10 dam 3.90E-07 6.09E-08 1.25E-06 '

BA 139 8.81E-07 5.84E-10 2.55E-08 to DATA 3.51E-10 3.54E-10 5.58E-05 1

A-28

- -

. _ _ _ . .

'mBLE A.3-4 (@nt'd)

DGESTICN DOSE F1CIORS FOR INFNfr(MRDi PER PCI D(itzirw)

10CLIDE BONE I,IVER T BODY 'IEYROID KIDNEY IRO GI-ILI .

BA 140 1.71E-04 1.71E-07 8.81E-06 to DATA 4.06E-08 1.05E-07 4.20E-05BA 141 4.25E-07 2.91E-10 1.34E-08 10 DATA 1.75E-10 1.77E-10 5.19E-06BA 142 1.84E-07 1.53E-10 9.06E-09 10 DATA 8.81E-11 9.26E-11 7.59E-07

IA 140 2.11E-08 8.32E-09 2.14E-09 10 DATA 10 DATA 10 DATA 9.77E-05IA 142 1.10E-09 4.04E-10 9.67E-11 10 DATA 10 DATA 10 DATA 6.86E-05CE 141 7.87E-08 4.80E-08 5.65E-09 10 DATA 1.48E-08 10 DATA 2.48E-05

CE 143 1.48E-08 9.82E-06 1.12E-09 10 DATA 2.86E-09 to DATA 5.73E-05CE 144 2.98E-06 1.22E-06 1.67E-07 to DATA 4.93E-07 10 DATA 1.71E-04PR 143 8.13E-08 3.04E-08 4.03E-09 FO DATA 1.13E-08 10 DATA 4.29E-05

PR 144 2.74E-10 1.06E-10 1.38E-11 to DATA 3.84E-11 10 DATA 4.93E-06-ND 147 5.53E-08 5.68E-08 3.48E-09 10 DATA 2.19E-08 to DATA 3.60E-05W 187 9.03E-07 6.28E-07 2.17E-07 PO DATA 10 DATA 10 DATA 3.69E-05

NP 239 1.11E-08 9.93E-10 5.61E-10 10 DATA 1.98E-09 10 DATA 2.87E-05Sb 124** 2.14E-05 3.15E-07 6.63E-06 5.68E-08 NO DATA 1.34E-05 6.60E-05Sb 125** 1.23E-05 1.19E-07 2.53E-06 1.54E-08 10 DATA 7.72E-06 1.64E-05

Sb 126** 8.06E-06 1.58E-07 2.91E-06 6.19E-08 10 DATA 5.07E-06 8.35E-06Co 57** 10 DATA 1.15E-06 1.87E-06 10 DATA NO DATA NO DATA 3.92E-06

1

**Taken fIun Regulatory Guide 1.109 (Rev. 0) |

|

|

A-29

.

. - -.._. __ . .

' MIKE A.3-5*

STABIE EIJMENP 'mANSFER DNm

B F, @) Ffy f

Elamnt Vec/Soll p(llk (d/1) Meat (d/ko)

H 4.8E 00 1.0E-02 + 1.2E-02C 5.5E 00 1.2E-02 + 3.1E-02

)Na 5.2E-02 4.0E-02 3.0E-02P 1.1E 00 2.5B-02 + 4.6E-02Cr 2.5E-04 2.2E-03 2.4E-03

|Mn 2.9E-02 2.5E-04 8.0E-04Fe 6.6E-04 1.2E-03 + 4.0E-02Co 9.4E-03 1.0E-03 1.3E-02N1 1.9E-02 6.7E-03 5.3E-02Cu 1.2E-01 1.4E-02 + 8.0E-03Zn 4.0E-01 3.9E-02 3.0E-02Rb 1.3E-01 3.0E-02 3.1E-02Sr 1.7E-02 8.0E-04 + 6.0E-04Y 2.6E-03 1.0E-05 4.6E-03Zr 1.7E-04 5.0E-06 '3.4E-02Nb 9.4 E-03 2.5E-03 2.8E-01Mo 1.2E-01 7.5E-03 8.0E-03Tc 2.5E-01 2.5E-02 4.0E-01Ru 5.0E-02 1.0E-06 4.0E-01Rh 1.3E 01 1.0E-02 1.5E-03 '|Ag 1.5E-01 5.0E-02 1.7E-02Tb 1.3E 00 1.0E-03 '7.7E-02I 2.0E-02 6.0E-03 + 2.9E-03Cs 1.0E-02 1.2E-02 + 4.0E-03 ,

Da 5.0E-03 4.0E-04 3.2E-03 iLa 2.5E-03 5.08-06 2.0E-04Ce 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 !

Fm (G at) values for milk (d/1)Elemnt Milk (d/1)H 1.7E-01C 1.0E-01 1P 2.5E-01Fe 1.3E-04Cu 1.3E-02Sr 1.4E-02I 6.0E-02Cs 3.0E-01

*Taken frun Regulatory Gulds 1.109 (Rev.1)A-30

. .

-.

TAIRE A.4-1

SITE RELATED DOSE OCMiI'DIENT F1CIOR AITMREM /IIR PER UCI/ML

ADUUr

NUCLIDE BONE LIVER T DODY '11!YROID KTDNEY UJNG GI-ILI

H 3 0.00E-01 8.96E 00 8.96E 00 8.96E 00 8.96E 00 8.96E 00 8.96E 00C 14 3.15E 04 6.30E 03 6.30E 03 6.30E 03 6.30E 03 6.30E 03 6.30E 03NA 24 5.488 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 06CR 51 0.00E-01 0.00E-01 1.49E 00 8.94E-01 3.29E-01 1.98E 00 3.76E 02MN 54 0.00E-01 4.76E 03 9.08E 02 0.00E-01 1.42E 03 0.00E-01 1.46E 04

MN 56 0.00E-01 1.20E 02 2.12E 01 0.00E-01 1.52E 02 0.00E-01 3.82E 03FE 55 8.87E 02 6.13E 02 1.43E 02 0.00E-01 0.00E-01 3.42E 02 3.52E 02FE 59 1.40E 03 3.29E 03 1.26E 03 0.00E-01 0.00E-01 9.19E 02 1.10E 04

CO 58 0.00E-01 1.51E 02 3.39E 02 0.00E-01 0.00E-01 0.00E-01 3.06E 0300 60 0.00E-01 4.34E 02 9.58E 02 0.00E-01 0.00E-01 0.00E-01 8.16E 03NI 63 4.19E 04 2.94E 03 1.41E 03 0.00E-01 0.00E-01 0.00E-01 6.07E 02

NI 65 1.70E 02 2.21E 01 1.01E 01 0.00E-01 0.00E-01 0.00E-01 5.61E 02CU 64 0.00E-01 1.69E 01 7.93E 00 0.00E-01 4.26E-01 0.00E-01 1.44E 03ZN 65 2.36E 04 7.50E 04 3.39E 04 0.00E-01 5.02E 04 0.00E-01 4.73E 04

ZN 69 5.02E 01 9.60E 01 6.67E 00 0.00E-01 6.24E-01 0.00E-01 1.44E 01BR 83 0.00E-01 0.00E-01 4.38E 01 0.00E-01 0.00E-01 0.00E-01 6.30E 01BR 84 0.00E-01 0.00E-01 5.67E 01 0.00E-01 0.00E-01 0.00E-01 4.45E-04

BR 85 0.00E-01 0.00E-01 2.33E 00 0.00E-01 0.00E-01 0.00E-01 1.09E-15 |RB 86 0.00E-01 1.03E 05 4.79E 04 0.00E-01 0.00E-01 0.00E-01 2.03E 04RB 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-11SR 89 4.78E 04 0.00E-01 1.37E 03 0.00E-01 0.00E-01 0.00E-01 7.66E 03FR 90 1.18E 06 0.00E-01 2.88E 05 0.00E-01 0.00E-01 0.00E-01 3.40E 04

SR 91 8.79E 02 0.00E-01 3.55E 01 0.00E-01 0.00E-01 0.00E-01 4.19E 03SR 92 3.33E 02 0.00E-01 1.44E 01 0.00E-01 0.00E-01 0.00E-01- 6.60E 03Y 90 1.38E 00 0.00E-01 3.69E-02 0.00E-01 0.00E-01 0.00E-01 1.46E 04

Y 91M 1.30E-02 0.00E-01 5.04E-04 0.00E-01 0.00E-01 0.00E-01 3.82E-02-Y 91 2.02E 01 0.00E-01 5.39E-01 0.00E-01 0.00E-01 0.00E-01 1.11E 04-Y 92 1.21E-01 0.00E-01 3.53E-03 0.00E-01 0.00E-01 0.00E-01 2.12E 03-

A-319/93

,

l,

'mBm A.4-1 (cont'd)

SITE REIATED DOSE OCNMI'IMEt7f FACIOR AltNREM/HR PER UCI/ML

ADULT

NUCLIDE DONE LIVER T BODY 'IHYROID KIDNEY IlltG GI-ILI

Y 93 3.83E-01 0.00E-01 1.06E-02 0.00E-01 0.00E-01 0.00E-01 1.22E 04ZR 95 2.77E 00 8.88E-01 6.01E-01 0.00E-01 1.39E 00 0.00E- 01 2.82E 03ZR 97 1.53F-01 3.09E-02 1.41E-02 0.00E-Cl 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 03TC 99M 2.94E-02 8.32E-02 1.06E 00 0.00E-01 1.26E 00 4.07E-02 4.92E 01

'IC 101 3.03E-02 4.36E-02 4.28E-01 0.00E-01 7.85E-01 2.23E-02 1.31E-13RU 103 1.98E 01 0.00E-01 8.54E 00 0.00E-01 7.57E 01 0.00E-01 2.31E 03RU 105 1.65E 00 0.00E-01 6.52E-01 0.00E-01 2.13E 01 0.00E-01 1.01E 03

RU 106 2.95E 02 0.00E-01 3.73E 01 0.00E-01 5.69E 02 0.00E-01 1.91E 04IG 110M 1.42E 01 1.31E 01 7.80E 00 0.00E-01 2.58E 01 0.00E-01 5.36E 03TE 125M 2.79E 03 1.01E 03 3.74E 02 8.39E 02 1.13E 04 0.00E-01 1.11E 04

TE 127M 7.05E 03 2.52E 03 8.59E 02 1.80E 03 2.86E 04 0.00E-01 2.36E 04TE 127 1.14E 02 4.11E 01 2.48E 01 8.48E 01 4.66E 02 0.00E-01 9.03E 03TE 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 01TE 131M 1.80E 03 8.81E 02 7.34E 02 1.39E 03 8.92E 03 0.00E-01 8.74E 04TE 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 04I 130 9.01E 01 2.66E 02 1.05E 02 2.25E 04 4.15E 02 0.00E-01 2.29E 02I 131 4.96E 02 7.09E 02 4.06E 02 2.32E 05 1.22E 03 0.00E-01 1.87E 02

I 132 2.42E 01 6.47E 01 2.26E 01 2.26E 03 1.03E 02 0.00E-01 1.22E 01I 133 1.69E 02 2.94E 02 8.97E 01 4.32E 04 5.13E 02 0.00E-01 2.64E 02I 134 1.26E 01 3.43E 01 1.23E 01 5.94E 02 5.46E 01 0.00E-01 2.99E-02

I 135 5.28E 01 1.38E 02 5.10E 01 9.11E 03 2.22E 02 0.00E-01 1.56E 02CS 134 3.03E 05 7.21E 05 5.89E 05 0.00E-01 2.33E 05 7.75E 04 1.26E 04CS 136 3.17E 04 1.25E 05 9.01E 04 0.00E-01 6.97E 04 9.55E 03 1.42E 04

1

CS 137 3.88E 05 5.31E 05 3.48E 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

i

A-32 |

)

|

~1

1

'IPELE A.4-1 (cont'd)

SITE RELATED DOSE CCEMI'IMENT F1CIOR AITMREM /HR PER IEI/ML

ADULT

FRELIDE BONE LIVER T BODY 'IIIYROID KIDNEY IUtG GI-LLI

BA 140 1.88E 03 2.37E 00 1.23E 02 0.00E-01 8.05E-01 1.35E 00 3.88E 03BA 141 4.37E 00 3.30E-03 1.48E-01 0.00E-01 3.07E-03 1.87E-03 2.06E-09BA 142 3.98E 00 2.03E-03 1.24E-01 0.00E-01 1.72E-03 1.15E-03 2.78E-18

IA 140 3.58E-01 1.80E-01 4.76E-02 0.00E-01 0.00E-01 0.00E-01 1.32E 04IA 142 1.83E-02 8.33E-03 2.07E-03 0.00E-01 0.00E-01 0.00E-01 6.08E 01CE 141 8.01E-01 5.42E-01 6.15E-02 0.00E-01 2.52E-01 0.00E-01 2.07E 03

CE 143 1.41E-01 1.04E 02 1.16E-02 0.00E-01 4.60E-02 0.00E-01 3.90E 03CE 144 4.18E 01 1.75E 01 2.24E 00 0.00E-01 1.04E 01 0.00E-01 1.41E 04PR 143 1.32E 00 5.288-01 6.52E-02 0.00E-01 3.05E-01 0.00E-01 5.77E 03 ,

PR 144 4.31E-03 1.79E-03 2.19E-04 0.00E-01 1.01E-03 0.00E-01 6.19E-10-ND 147 9.00E-01 1.04E 00 6.22E-02 0.00E-01 6.08E-01 0.00E-01 4.99E 03W 187 3.04E 02 2.55E 02 8.90E 01 0.00E-01 0.00E-01 0.00E-01 8.34E 04

NP 239 1.28E-01 1.25E-02 6-91E-03 0.00E-01 3.91E-02 0.00E-01 2.57E 03Sb 124 2.40E 02 4.53E 00 9.50E 01 5.81E-01 0.00E-01 1.87E 02 6.81E 03Sb 125 1.53E 02 1.71E 00 3.65E 01 1.56E-01 0.00E-01 1.18E 02 -1.69E 03

Sb 126 9.85E 01 2.00E 00 3.55E 01 6.03E-01 0.00E-01 6.04E 01 8.05E 03Co 57 0.00E-01 3.55E 01 5.90E 01 0.00E-01 0.00E-01 0.00E-01 9.01E 02

i

A-33 |

|

,

_.

.

'DMER A.4-2

SITE RELATED DOSE COMI'IMEN1 FACIOR AITMREM /HR PER UCI/ML

TEEN

NTLIDE BCNE LIVER T DODY 'IHYROID KIDNEY IDG GI-ILI

H 3 0.00E-01 6.34E 00 6.34E 00 6.34E 00 6.34E 00 6.34E 00 6.34E 00C 14 3.43E 04 6.86E 03 6.86E 03 6.86E 03 6.86E 03 6.86E 03 6.86E 03NA 24 5.53E 02 5.53E 02 5.53E 02 5.53E 02 5.53E 02 5.53E 02 5.53E 02

,

P 32 5.04E 07 3.12E 06 1.95E 06 0.00E-01 0.00E-01 0.00E-01 4.23E 06CR 51 0.00E-01 0.00E-01 1.52E 00 8.46E-01 3.34E-01 2.17E 00 2.56E 02MN 54 0.00E-01 4.65E 03 9.22E 02 0.00E-01 1.39E 03 0.00E-01 9.53E 03

MN 56 0.00E-01 1.24E 02 2.21E 01 0.00E-01 1.58E 02 0.00E-01 8.19E 03FE 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 3.30E 03 1.27E 03 0.00E-01 0.00E-C' __' % v3 7.79E 03

CO 58 0.00E-01 1.45E 02 3.35E 02 0.00E-01 0.00E-01 0.00E-01 2.00E 0300 60 0.00E-01 4.20E 02 9.45E 02 0.00E-01 0.00E-01 0.00E-01 5.47E 03NI 63 4.26E 04 3.01E 03 1.44E 03 0.00E-01 0.00E-01 0.00E-01 4.79E 02

NI 65 1.80E 02 2.30E 01 1.05E 01 0.00E-01 0.00E-01 0.00E-01 1.25E 03CU 64 0.00E-01 1.72E 01 8.08E 00 0.00E-01 4.35E 01 0.00E-01 1.33E 03ZN 65 2.13E 04 7.41E 04 3.46E 04 0.00E-01 4.74E 04 0.00E-01 3.14E 04

ZN 69 5.45E 01 1.04E 02 7.26E 00 0.00E-01 6.78E 01 0.00E-01 1.91E 02BR 83 0.00E-01 0.00E-01 4.73E 01 0.00E-01 0.00E-01 0.00E-01 8.24E-16BR 84 0.00E-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-16RB 86 0.00E-01 1.10E 05 5.19E 04 0.00E-01 0.00E-01 0.00E-01 1.63E 04RB 88 0.00E-01 3.16E 02 1.68E 02 0.00E-01 0.00E-01 0.00E-01 2.71E-05

RB 89 0.00E-01 2.04E 02 1.44E 02 0.00E-01 0.00E-01 0.00E-01 3.12E-07SR 89 4.97E 04 0.00E-01 1.42E 03 0.00E-01 0.00E-01 0.00E-01 5.91E 03SR 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 03SR 92 3.44E 02 0.00E-01 1.47E 01 0.00E-01 0.00E-01 0.00E-01 8.77E 03Y 90 1.42E 00 0.00E-01 3.83E-02 0.00E-01 0.00E-01 0.00E-01 1.17E 04

Y 91M 1.34E-02 0.00E-01 5.llE-04 0.00E-01 0.00E-01 0.00E-01 6.32E-01Y 91 2.09E 01 0.00E-01 5.59E-01 0.00E-01 0.00E-01 0.00E-01 8.55E 03Y 92 1.26E-01 0.00E-01 3.63E-03 0.00E-01 0.00E-01 0.00E-01 3.44E 03

A-34

TABM A.4-2 (cont'd)

SITE RE[ATED DOSE COMIUNEtTf FACIDR AITMREM /HR PER UCI/ML *

TEER

NLCLIDE DONE LIVER T BODY THYROID KIDNEY IUNG GI-ILI

Y 93 3.97E-01 0.00E-01 1.09E-02 0.00E-01 0.00E-01 0.00E-01 1.21E 04ZR 95 2.64E 00 8.34E-01 5.74E-01 0.00E-01 1.23E 00 0.00E-01 1.92E 03ZR 97 1.52E-01 3.01E-02 1.39E-02 0.00E-01 4.56E-02 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 06ND 99 0.00E-01 4.61E 02 8.78E 01 0.00E-01 1.05E 03 0.00E-01 8.25E 027C 99M 2.84E-02 '7.92E-02 1.03E 00 0.00E-01 1.18E 00 4.39E-02 5.20E 01

TC 101 3.08E-02 4.38E-02 4.30E-01 0.00E -01 7.92E-01 2.67E-02 7.48E-09-RU 103 1.95E 01 0.00E-01 8.33E 00 0.00E-01 6.87E 01 0.00E-01 1.63E 03RU 105 1.67E 00 0.00E-01 6.46E-01 0.00E-01 2.10E 01 0.00E-01 1.34E 03

RU 106 2.99E 02 0.00E-01 3.77E 01 0.00E-01 5.77E 02 0.00E-01 1.44E 041G 110M 1.20E 01 1.21E 01 7.36E 00 0.00E-01 2.31E 01 0.00E-01 3.40E 03TE 125M 3.02E_03 1.09E 03 4.03E 02 8.43E 02 0.00E-01 0.00E-01 8.90E 03


,

'TE 129 3.53E 01 1.32E 01 8.59E 00 2.52E 01 1.48E 02 0.00E-01 1.93E 02TE 131M 1.92E 03 9.22E 02 7.69E 02 1.39E 03 9.61E 03 0.00E-01 7.40E 04TE 131 2.20E 01 9.06E 00 6.87E 00 1.69E 01 9.61E 01 0.00E-01 1.80E 00

TE 132 2.75E 03 1.74E 03 1.64E 03 1.84E 03 1.67E 04 0.00E-01 5.51E 04I 130 8.81E 01 2.55E 02 1.02E 02 2.08E 04 3.92E 02 0.00E-01 1,96E 02 ,

I 131 5.00E p2 7.00E 02 3.76E 02 2.04E 05 1.21E 03 0.00E-01 1.39E 02 |

I 132 2.39E 01 6.24E 01 2.24E 01 2.10E 03 9.83E 01 0.00E-01 2.72E 01 |

I 133 1.72E 02 2.92E 02 8.89E 01 4.07E 04 5.11E 02 0.00E-01 2.21E 02 -iI 134 1.25E 01 3.31E 01 1.19E 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 02CS 134 3.10E 05 7.30E 05 3.39E 05 0.00E-01 2.32E 05 8.86E 04 9.08E 03 I

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 05 0.00E-01 1.88E 05 7.30E 04 7.86E 03CS 138 2.88E 02 5.52E 02 2.76E 02 0.00E-01 4.08E 02 4.74E 01 2.51E-01In 139 9.10E 00 6.40E-03 2.65E-01 0.00E-01 6.03E-03 4.41E-03 8.1]E 01

i

A-35

.

'EMEE A.4-2 (cont'd)

SITE RELATED DOSE CCIMID!EtE FACIDR AITMREM /HR PER UCI/ML

TEEN

NUCLIDE FX)NE LIVER T BODY 'IHYROID KIDNEY Ill!G GI-ILI

BA 140 1.86E 03 2.28E 00 1.20E 02 0.00E-01 7.72E-01 1.53E 00 2.87E 03BA 141 4.39E 00 3.28E-03 1.47E-01 0.00E-01 3.04E-03 2.24E-03 9.36E-06BA 142 1.96E 00 1.96E-03 1.20E-01 0.00E-01 1.66E-03 1.30E-03 6.01E-12'

IA 140 3.61E-01 1.77E-01 4,72E-02 0.00F-01 0.00E-01 0.00E-01 1.02E 04IA 142 1.86E-02 8.25E-03 2.05E-03 0.00E-01 0.00E-01 0.00E-01 2.51E 02 '

CE 141 7.98E-01 5.32E-01 6,12E-02 0.00E-01 2.51E-01 0.00E-01 1.52E 03

CE 143 1.41E-01 1.03E 02 1.15E-02 0.00E-01 4.60E-02 0.00E-01 3.08E 03CE 144 4.17E 01 1.73E 01 2.24E 00 0.00E-01 1.03E 01 0.00E-01 1.05E 04PR 143 1.36E 00 5.43E- 01 6.76E-02 0.00E-01 3.15E-01 0.00E-01 4.47E 03

PR 144 4.46E-03 1.83E-03 2.26E-04 0.00E-01 1.05E-03 0.00E-01 4.92E-06ND 147 9.73E-01 1.06E 00 6.34E-02 0.00E-01 6.21E-01 0.00E-01 3.82E 03W 187 3.28E 02 2.67E 02 9.37E 01 0.00E-01 0.00E-01 0.00E-01 7.24E 04

NP 239 1.34E-01 1.27E-02 7.04E-03 0.00E-01 3.98E-02 0.00E-01 2.04E 03Sb 124 2.32E 02 4.28E 00 9.05E 01 5.26E-01 0.00E-01 2.03E 02 4.68E 03Sb 125 1.49E 02 1.63E 00 3.48E 01 1.42E-01 0.00E-01 1.31E 02 1.16E 03

,

Sb 126 9.53E 01 1.95E 00 3.42E 01 5.39E-01 0.00E-01 6.84E 01 5.64E 03Co 57 0.00E-01 3.55E 01 5.96E 01 0.00E-01 0.00E-01 0.00E-01 6.63E 02

A-36

)

. . .

TAIRE A.4-3,

SITE RELATED DOSE CCIMI'IMENf F1CIOR AITNREM/PR PER UCI/ML

CHIID

NOCLIDE BONE LIVER T DODY 'I1WROID KIDNEY IIRG GI-ILI

H 3 0.00E-01 1.19E 01 1.19E 01 1.19E 01 1.19E 01 1.19E 01 1.19E 01-C 14 4.45E 04 8.90E 03 8.90E 03 8.90E 03 8.90E 03 8.90E 03 8.90E 03NA 24 7.93E 02 7.93E 02 7.93E 02 7.93E 02 7.93E 02 7.93E 02 7.93E 02

P 32 6.49E 07 3.04E 06 2.50E 06 0.00E-01 0.00E-01 0.00E-01 1.79E 06CR 51 0.00E-01 0.00E-01 1.92E 00 1.06E 00 2.91E-01 1.94E 00 1.02E 02MN 54 0.00E-01 3.99E 03 1.06E 03 0.00E-01 1.12E 03 0.00E-01 3.35E 03


00 58 0.00E-01 1.75E 02 5.37E 02 0.00E-01 0.00E-01 0.00E-01 1.02E 03CO 60 0.00E-01 5.16E 02 1.52E 03 0.00E-01 0.00E-01 0.00E-01 2.86E 03NI 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 03CU 64 0.00E-01 2.39E 01 1.44E 01 0.00E-01 5.77E 01 0.00E-01 1.12E 03ZN 65 2.23E 04 5.95E 04 3.70E 04 0.00E-01 3.75E 04 0.00E-01- 1.05E 04

ZN 69 7.15E 01 1.03E 02 9.54E 00 0.00E-01 6.26E 01 0.00E-01 6.51E 03BR 83 0.00E-01 0.00E-01 6.64E 01 0.00E-01 0.00E-01 0.00E-01 3.89E-16BR 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-16RB 86 0.00E-01 1.09E 05 6.72E 04 0.00E-01 0.00E-01 0.00E-01 7.03E 03RB 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 00SR 89 1.08E 05 0.00E-01 3.08E 03 0.00E-01 0.00E-01 0.00E-01 4.18E 03SR 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 03SR 92 7.38E 02 0.00E-01 2.96E 01 0.00E-01 0.00E-01 0.00E-01 -1.40E 04Y 90 3.20E 00 0.00E-01 8.56E-02 0.00E-01 0.00E-01 0.00E-01 9.10E 03

Y 91M 2.97E-02 0.00E-01 1.08E-03 0.00E-01 0.00E-01 0.00E-01 5.82E Ol'Y 91 4.68E 01 0.00E-01 1.25E-02 0.00E-01 0.00E-01 0.00E-01 6.24E 03Y 92 2.80E-01 0.00E-01 8.01E-03 0.00E-01 0.00E-01 0.00E-01 8.09E 03

A-37

|.

D BLE A.4-3 (cont'd)

SITE RELATED DOSE GEMIUMEtE FACTOR AITMREM /HR PER UCI/ML

CHIID

NUCLIDE BONE LIVER T BODY THYROID KIDNEY IUNG GI-ILI

Y 93 8.87E-01 0.00E-01 2.44E-02 0.00E-01 0.00E-01 0.00E-01 1.32E 04KR 95 7.05E 00 1.55E 00 1.38E 00 0.00E-01 2.22E 00 0.00E-01 1.62E 03 i

KR 97 4.25E-01 6.13E-02 3.62E-02 0.00E-01 8.81E-02 0.00E-01 9.29E 03

NB 95 5.32E 02 2.07E 02 1.48E 02 0.00E-01 1.95E 02 0.00E-01 3.83E 05MO 99 0.00E-01 8.78E 02 2.17E 02 0.00E-01 1.87E 03 0.00E-01 7.26E 02TC 99M 6.46E-02 1.27E-01 2.10E 00 0.00E-01 1.84E 00 6.43E-02 7.20E 01 j

TC 101 7.48E-02 7.83E-02 9.93E-01 0.00E-01 1.34E 00 4.14E-02 2.49E-01RU 103 4.83E 01 0.00E-01 1.85E 01 0.00E-01 1.21E 02 0.00E-01 1.25E 03RU 105 4.26E 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 04AG 110H 3.23E 01 2.18E 01 1.74E 01 0.00E-01 4.06E 01 0.00E-01 2.60E 03 i

TE 12SH 4.25E 03 1.15E 03 5.67E 02 1.19E 03 0.00E-01 0.00E-01 4.10E 03 j

TE 12ZH 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 1.39E 01 1.19E 01 3.56E 01 1.46E 02 0.00E-01 3.11E 03 :

TE 131M 2.68E 03 9.28E 02 9.88E 02 1.91E 03 8.98E 03 0.00E-01 3.77E'04 iTE 131 3.09E 01 9.43E 00 9.21E 00 2.37E 01 9.36E 01 0.00E-01 1.63E 02

1

TE 132 3.77E 03 1.67E 03 2.01E 03 2.43E 03 1.55E 04 0.00E-01 1.68E 04 I'

.I 130 2.04E 02 4.13E 02 2.13E 02 4.55E 04 6.17E 02 0.00E-01 1.93E 02-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 5.60E 01 1.03E 02 4.73E 01 4.77E 03 1.57E 02 0.00E-01 1.21E 02I 133 4.14E 02 5.12E 02 1.94E 02 9.51E 04 8.53E 02 0.00E-01 2.06E 02I 134 2.93E 01 5.44E 01 2.50E 01 1.2SE 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 02CS 134 3.82E 05 6.26E 05 1.32E 05 0.00E-01' 1.94E 05 6.97E 04 3.38E 03CS 136 3.83E 04 1.05E 05 6.82E 04 0.00E-01 5.61E 04 8.37E 03 3.70E 03

CS 137 5.33E 05 5.11E 05 7.54E 04 0.00E-01 1.66E 05 5.99E 04 3.20E 03 I

CS 138 3.72E 02 5.17E 02 3.28E 02 0.00E-01 3.64E 02 3.92E 01 2.38E 02BA 139 2.54E 01 1.35E-02 7.35E-01 0.00E-01 1.18E-02 7.97E-03 1.47E 03

i

||

A-38

TPELE A.4-3 (amt'd)

SITE RELATED DOSE CCNMI'IMENT FACIQ1 AITMREM /HR PER UCI/ML

CHIID

NUCLIDE BONE LIVER T BODY THYROID KIDtEY IDG GI-ILI

BA 140 5.09E 03 4.46E 00 2.97E 02 0.00E-01 1.45E 00 2.66E 00 2.58E 03BA 141 1.23E 01 6.86E-03 3.99E-01 0.00E-01 5.94E-03 4.03E-02 6.99E 00BA 142 5.36E 00 3.85E-03 2.99E-01 0.00E-01 3.12E-03 2.27E-03 6.99E-02

IA 140 7.86E-01 2.75E-01 9.26E-02 0.00E-01 0.00E-01 0.00E-01 7.66E 03IA 142 4.08E-02 1.30E-02 4.07E-03 0.00E-01 0.00E-01 0.00E-01 2.58E 03CE 141 2.34E 00 1.17E 00 1.73E-01 0.00E-01 5.11E-01 0.00E-01 1.46E 03

CE 143 4.12E-01 2.23E 02 3.24E-02 0.00E-01 9.37E-02 0.00E-01 3.27E 03CE 144 1.23E 02 3.84E 01 6.54E 00 0.00E-01 2.13E 01 0.00E-01 1.00E 04PR 143 3.06E 00 9.18E-01 1.52E-01 0.00E-01 4.97E-01 0.00E-01 3.30E 03

PR 144 1.00E-02 3.10E-03 5.05E-04 0.00E-01 1.64E-03 0.00E-01 6.68E 00ND 147 2.17E 00 1.76E 00 1.36E-01 0.00E-01 9.65E-01 0.00E-01 2.79E 03W 187 4.30E 02 2.55E 02 1.14E 02 0.00E-01 0.00E-01 0.00E-01 3.58E 04

NP 239 3.47E-01 2.49E-02 1.75E-02 0.00E-01 7.19E-02 0.00E-01 1.84E 03Sb 124 6.54E 02 8.49E 00 2.29E 02 1.44E 00 0.00E-01 3.63E 02 4.09E 03Sb 125 4.22E 02 3.25E 00 8.84E 01 3.91E-01 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-Co 57 0.00E-0] 4.81E 01 9.73E 01 0.00E-01 0.00E-01 0.00E-01 3.94E 02

|1

|

A-39

i.

||

|

I

'1%BW A.4-4 i

SITE RELATED DOSE COMI'IMENT FICIOR AITMREM /HR PER UCI/lO

INFANT

NUCLIDE BONE LIVER T BODY THYROID KIDNEY IJJtG GI-ILI


P 32 6.40E 04 3.76E 03 2.48E 03 0.00E-01 0.00E-01 0.00E-01 8.65E 02CR 51 0.00E-01 0.00E-01 5.30E-01 3.46E-01 7.56E-02 6.73E-01 1.55E 01MN 54 0.00E-01 7.49E 02 1.70E 02 0.00E-01 1.66E 02 0.00E-01 2.75E 02


CO 58 0.00E-01 1.35E 02 3.38E 02 0.00E-01 0.00E-01 0.00E-01 3.37E 02CO 60 0.00E-01 4.06E 02 9.59E 02 0.00E-01 0.00E-01 0.00E-01 9.67E 02NI 63 2.39E 04 1.47E 03 8.28E 02 0.00E-01 0.00E-01 0.00E-01 7.34E 01


ZN 69 3.51E 00 6.32E 00 4.70E-01 0.00E-01 2.63E 00 0.00E-01 5.15E 02BR 83 0.00E-01 0.00E-01 1.37E 01 0.00E-01 0.00E-01 0.00E-01 3.76E-17BR 84 0.00E-01 0.00E-01 1.44E 01 0.00E-01 0.00E-01 0.00E-01 3.76E-17

BR 85 0.00E-01 0.00E-01 7.30E-01 0.00E-01 0.00E-01 0.00E-01 3.76E-17RB 86 0.00E-01 6.40E 03 3.16E 03 0.00E-01 0.00E-01 0.00E-01 1.64E 02RB 88 0.00E-01 1.87E 01 1.03E 01 0.00E-01 0.00E-01 0.00E-01 1.82E 01

RB 89 0.00E-01 1.08E 01 7.41E 00 0.00E-01 0.00E-01 0.00E-01 3.66E 00SR 89 9.44E 04 0.00E-01 2.71E 03 0.00E-01 0.00E-01 0.00E-01 1.94E 03SR 90 6.96E 05 0.00E-01 1.77E 05 0.00E-01 0.00E-01 0.00E-01 8.69E 03

SR 91 1.88E 03 0.00E-01 6.81E 00 0.00E-01 0.00E-01 0.00E-01 2.23E 03SR 92 7.22E 02 0.00E-01 2.68E 01 0.00E-01 0.00E-01 0.00E-01 7.79E 03Y 90 3.27E 00 0.00E-01 8.77E-02 0.00E-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 02Y 91 4.25E 01 0.00E-01 1.13E 00 0.00E-01 0.00E-01 0.00E-01 3.05E 03Y 92 2.88E-01 0.00E-01 8.09E-03 0.00E-01 0.00E-01 0.00E-01 5.49E 03

A-40

_

7NIE A.4-4 (cortt'd)

SITE RELATED DOSE CXEMI'IMENT FNHOR AITMRD4/HR PER UCI/ML

INEANT |

NLCLIDE BONE LIVER T BODY THYROID KIDNEY IRE GI-ILI

Y 93 9.14E-01 0.00E-01 2.49E-02 0.00E-01 0.00E-01 0.00E-01 7.22E 03ZR 95 7.75E 00 1.89E 00 1.34E 00 0.00E-01 2.04E 00 0.00E-01 9.41E 02 )ZR 97 5.57E-01 9.56E-02 4.36E-02 0.00E-01 9.63E-02 0.00E-01 6.09E 03 1

NB 95 1.58E 00 6.51E-01 3.76E-01 0.00E-01 4.66E-01 0.00E-01 5.49E 02MD 99 0.00E-01 1.28E 03 2.49E 02 0.00E-01 1.91E 03 0.00E-01 4.21E 02TC 99M 7.22E-02 1.49E-01 1.92E 00 0.00E-01 1.60E 00 7.79E-02 4.33E 01 |

|TC 101 8.54E-02 1.08E-01 1.06E 00 0.00E-01 1.28E 00 5.87E-02 1.83E 01

'

RU 103 5.57E 01 0.00E-01 1.86E 01 0.00E-01 1.16E 02 0.00E-01 6.77E 02RU 105 5.12E 00 0.00E-01 1.72E 00 0.00E-01 3.76E 01 0.00E-01 2.04E 03

RU 106 9.07E 02 0.00E-01 1.13E 02 0.00E-01 1.07E 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 0.00E-01 4.18E 02

TE 127M 2.20E 03 7.30E 02 2.66E 02 6.36E 02 5.42E'03 0.00E-01 8.88E 02TE 127 3.76E 01 1.26E 01 8.09E 00 3.06E 01 9.18E 01 0.00E-01 7.90E 02 ,

TF 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 02TE 131M 5.72E 02 2.30E 02 1.90E 02 4.66E.02 1.58E 03 0.00E-01 3.87E 03TE 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 03I 130 2.26E 02 4.97E 02 1.99E 02 5.57E 04 5.45E 02 0.00E-01 1.06E 02 l

I 131 1.35E 03 1.59E 03 7.00E 02 5.23E 05 1~.86E 03 0.00E-01 5.68E 01 1

I 132 6.24E 01 1.27E 02 4.51E 01 5.94E 03 1.41E 02 0.00E-01 1.03E 02I 133 4.70E 02 6.85E 02 2.01E 02 1.25E 05 8.05E 02 0.00E-01 1.16E 02 jI 134 3.27E 01 6.70E 01 2.38E 01 1.56E 03 7.49E 01 0.00E-01 6.92E 01

1 135 1.37E 02 2.72E 02 9.93E 01 2.44E 04 3.04E 02 0.00E-01 9.86E 01CS 134 1.42E 04 2.64E 04 2.67E 03 0.00E-01 6.81E 03 2.42E 03 7.19E 01CS 136 1.73E 03 5.08E 03 1.90E 03 0.00E-01 2.02E 03 4.14E 02 7.7]E 01

CS 137 1.96E 04 2.30E 04 1.63E 03 0.00E-01 6.17E 03 2.50E 03 7.19E 01CS 138 1.81E 01 2.94E 01 1.43E 01 0.00E-01 1.47E 01 2.29E 00 4.70E 01BA 139 3.31E 01 2.20E-02 9.59E-01 0.00E-01 1.32E-02 1.33E-02 2.10E 03 l

i

!

A-41

.

MBLE A.4-4 (cmt'd)

SITE RELATED DGiB CCMEINEN1' F1CIER AITMREM /HR PER UCI/ML

INFANP

NUCLIDE BONE LIVER T BODY 'IHYROID hT24EY Il]NG GI-ILI

BA 140 6.43E 03 6.43E 00 3.31E 02 0.00E-01 1.53E 00 3.95E 00 1.58E 03BA 141 1.60E 01 1.09E-02 5.04E-01 0.00E-01 6.58E-03 6.66E-03 1.95E 02BA 142 6.92E 00 5.76E-03 3.41E-01 0.00E-01 3.31E-03 3.48E-03 2.86E 01

IA 140 7.94E-01 3.13E-01 8.05E-02 0.00E-01 0.00E-01 0.00E-01 3.68E 03.IA 142 4.14E-02 1.52E-02 3.64E-03 0.00E-01 0.00E-01 0,00E-01 2.58E 03CE 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 03CE 144 1.12E 02 4.59E 01 6.28E 00 0.00E-01 1.85E 01 0.00E-01 6.43E 03PR 143 3.06E 00 1.14E 00 1.52E-01 0.00E-01 4.25E-01 0.00E-01 1.61E 03

FR 144 1.03E-02 3.99E-03 5.19E-04 0.00E-01 1.44E-03 0.00E-01 1.85E 02ND 147 2.08E 00 2.14E 00 1.31E-01 0.00E-01 8.24E-01 0.00E-01- 1.35E 03W 187 3.40E 01 2.36E 01 8.16E 00 0.00E-01 0.00E-01 0.00E-01 1.39B 03

NP 239 4.18E-01 3.74E-02 2.11E-02 0.00E-01 7.45E-02 0.00E-01 1.08E 03Sb 124 8.05E 02 1.19E 01 2.49E 02 2.14E 00 0.00E-01 5.04E 02 2.48E 03Sb 125 4.63E 02 4.48E 00 9.52E 01 5.79E-01 0.00E-01 2.90E 02 6.17E 02

Sb 126 3.03E 02 5.94E 00 1.09E 02 2.33E 00 0.00E-01 1.91E 02 3.14E 03Co 57 0.00E-01 4.33E 01 7.03E 01 0.00E-01 0.00E-01 0.00E-01 1.47E 02

A-42

i

I;a

f

TABLE A.5-1

IMIAIATION DOSE PARAMETER KR ' HIE CHILD, PIMRDi/YR per uCi/M

i

H-3 1.12E 03 RU-103 6.62E 05C-14 3.59E 04 RU-105 9.95E 04NA-24 1.61E 04 RU-106 1.43E 07P-32 2.60E 06 1G-110M 5.48E 06CR-51 1.70E 04 TE-125M 4.77E 05MN-54 1.58E 06 TE-127M 1.48E 06MN-56 1.23E 05 TE-127 -5.62E 04FE-55 1.11E 05 TE-129M 1.76E 06FE-59 1.27E 06 TE-129 2.55E 04CO-58 1.11E 06 TE-131M 3.08E 05CO-60 7.07E 06 TB-131 2.05E 03NI-63 8.21E 05 TE-132 3.77E 05NI-65 8.40E 04 I-130 1.85E 06CU-64 3.67E 04 I-131 1.62E 07ZN-65 9.95E 05 I-132 1.94E 05ZN-69 1.02E 04 I-133 3.85E 06BR-83 4.74E 02 I-134 5.07E 04BR-84 5.48E 02 I-135 7.92E 05BR-85 2.53E 01 CS-134 1.01E 06RB-86 1.98E 05 CS-136 1.71E 05RB-88 5.62E 02 CS-137 9.07E 05RB-89 3.45E 02 CS-138 8.40E 02SR-89 2.16E 06 BA-139 5.77E 04SR-90 1.01E 08 BA-140 1.74E 06SR-91 1.74E 05 BA-141 2.92E 03 !

SR-92 2.42E 05 BA-142 1.64E 03 l

Y-90 2.68E 05 IA-140 2.26E 05Y-91M 2.81E 03 IA-142 7.59E 04Y-91 2.63E 06 CE-141 5.44E 05Y-92 2.39E 05 CE-143 1.27E 05Y-93 3.89E 05 CE-144 1.20E 07ZR-95 2.23E 06 PR-143 4.33E 05ZR-97 3.51E 05 PR-144 1.57E 03 {NB-95 6.14E 05 ND-147 3.28E 05MD-99 1.35E 05 W-187 9.10E 04'IC-99M 4.81E 03 NP-239 6.40E 04'IC-101 5.85E 02

A-43,

.

_

2 g e-- M L.

.

TABLE A.5-2

INHAIATION PATHWAY FpMRDVYR PER UCIn,r

ADULT (RI FACIORS)

NUCLIDE BONE LIVER T BODY THYROID KIDNEY IDG GI-ILI -

H 3 0.00E 01 1.26E 03 1.26E 03 1.26E 03 1.26E 03 1.26E 03 -1.26E 03C 14 1.82E 04 3.41E 03 3.41E 03 3.41E 03 3.41E 03 3.41E 03 3.41E 03NA 24 1.02E 04 1.02E 04 1.02E 04 1.02E 04 1.02E 04 1.02E 04 1.02E 04

P 32 1.32E 06 7.71E 04 5.01E 04 0.00E-01 0.00E-01 0.00E-01 8.64E 04CR 51 0.00E 01 0.00E 01 1.00E 02 5.95E 01 2.28E Ol' 1.44E 04 3.32E 03MN 54 0.00E 01 3.96E 04 6.30E 03 0.00E-01 9.84E 03 1.40E 06 7.74E 04

-bW 56 0.00E 01 1.24E 00 1.83E-01 0.00E-01 1.30E 00 9.44E 03 2.02E 04FE 55 2.46E 04 1.70E 04 3.94E 03 0.00E-01 0.00E-01 7.21E 04 6.03E 03FE 59 1.18E 04 2.78E 04 1.06E 04 0.00E-01 0.00E-01 1.02E 06 1.88E 05

00 58 0.00E 01 1.58E 03 2.07E 03 0.00E-01 0.00E-01 9.28E 05 1.06E 0500 60 0.00E 01 1.15E 04 1.48E 04 0.00E-01 0.00E-01 5.97E 06 2.85E 05NI 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 04CU 64 0.00E 01 1.46E 00 6.15E-01 0.00E-01 4.62E 00 6.78E 03 4.90E 04ZN 65 3.24E 04 1.03E 05 4.66E 04 0.00E-01 6.90E 04 8.64E 05 5.34E 04-

ZN 69 3.38E-02 6.51E-02 4.52E-03 0.00E-01 4.22E-02 9.20E 02 1.63E 01BR 83 0.00E-01 0.00E-01 2.41E 02 0.00E-01 0.00E-01 0.00E-01 2.32E 02BR 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-15RB 86 0.00E-01 1.35E 05 5.90E 04 0.00E-01 0.00E-01 0.00E-01 1.66E 04RB 88 0.00E-01 3.87E 02 1.93E 02 0.00E-01 0.00E-01 0.00E-01 3.34E-09-

RB 89 0.00E-01 2.56E 02 1.70E 02 0.00E-01 0.00E-01 0.00E-01 9.28E-12SR 89 3.04E 05 0.00E-01 8.72E 03 0.00E-01 0.00E-01 1.40E 06 3.50E 05SR 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 05SR 92 6.74E 00 0.00E-01 2.91E-01 0.00E-01 0.00E-01 1.65E 04 4.30E 04Y 90 2.09E 03 0.00E-01 5.61E 01 0.00E-01 0.00E-01 1.70E 05 5.06E 05

Y 9LH 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 05Y 92 1.03E 01 0.00E-01 3.02E-01 0.00E-01 0.00E-01 1.57E 04 7.35E 04

I

lA-44

1

I

|

.

|

TABLE A.5-2 (cont'd)

INHAIATICN PA71MAY F3 CITMREN/YR PER UCI/M'ADUUI' (RI FAC'ITS)

NUCLIDE BONE LIVER T BODY TiWROID KIDNEY IDG GI-ILI

Y 93 9.44E 01 0.00E-01 2.61E 00 0.00E-01 0.00E-01 -4.85E 04 4.22E 05ZR 95 1.07E 05 3.44E 04 2.33E 04 0.00E-01 5.42E 04 1.77E 06 1.50E 05ZR 97 9.68E 01 1.96E 01 9.04E 00 0.00E-01 2.97E 01 7.87E 04 5.23E 05

NB 95 1.41E 04 7.82E 03 4.21E 03 0.00E-01 7.74E 03 5.05E 05 1.04E 05-MD 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

TC 101 4.18E-05 6.02E-05 5.90E-04 0.00E-01 1.08E-03 3.99E 02 1.09E-11RU 103 1.53E 03 0.00E-01 6.58E 02 0.00E-01 5.83E 03 5.05E 05 1.10E 05RU 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 05AG 110M 1.08E 04 1.00E 04 5.94E 03 0.00E-01 1.97E 04 4.63E 06 3.02E 05TE 12SM 3.42E 03 1.58E 03 4.67E 02 1.05E 03 1.24E 04 3.14E 05 7.06E 04

TE 127H 1.26E 04 5.77E 03 1.57E 03 3.29E 03 4.58E 04 9.60E 05 1.50E 05TE 127 1.40E 00 6.42E-01 3.10E-01 1.06E 00 5.10E 00 6.51E 03 5.74E 04TE 129M 9.76E 03 4.67E 03 1.58E 6?. 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 02TE 131M 6.99E 01 4.36E 01 2.90E 01 5.50E 01 3.09E 02 1.46E 05 5.56E 05TE 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 05I 131 2.52E 04 3.58E 04 2.05E 04 1.19E 07 6.13E 04 0.00E-01 6.28E 03

I 132 1.16E 03 3.26E 03 1.16E 03 1.14E 05 5.18E 03 0.00E-01 4.06E 02I 133 8.64E 03 1.48E 04 4.52E 03 2.15E 06 2.58E 04 0.00E-01 8.88E 03I 134 6.44E 02 1.73E 03 6.15E 02 2.98E 04 2.75E 03 0.00E-01 1.01E 00

I 135 2.68E 03 6.98E 03 2.57E 03 4.48E 05 1.11E 04 0.00E-01 5.25E 03CS 134 3.73E 05 8.48E 05 7.28E 05 0.00E-01 2.87E 05 9.76E 04 1.04E 04.CS 336 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 03CS 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

|

A-45 I

|

|

1

!

TABM A.5-2 (cxmt'd)

IMIAIATICN PATH &Y FpMRDI/YR PER LCI/MAEXILT (RI F1CIGS)

1RCLIDE BONE LIVER T BODY 'IEYROID KITTEY IRC GI-ILI

BA 140 3.90E 04 4.90E 01 2.57E 03 0.00E-01 1.67E 01 1.27E 06 2.18E 05 '

BA 141 1.00E-01 7.53E-05 3.36E-03 0.00E-01 7.00E-05 1.94E 03 1.16E-07 '

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

IA 140 3.44E 02 1.74E 02 4.58E 01 0.00E-01 0.00E-01 1.36E 05 4.58E 05IA 142 6.83E-01 3.10E-01 7.72E-02 0.00E-01 0.00E-01 6.33E 03 2.11E 03CE 141 1.99E 04 1.35E 04 1.53E 03 0.00E-01 6.26E 03 3.62E 05 1.20E 05'

CE 143 1.86E 02 1.38E 02 1.53E 01 0.00E-01 6.08E 01 7.98E 04 2.26E 05CE 144 3.43E 06 1.43E 06 1.84E 05 0.00E-01 8.48E 05 7.78E 06 8.16E 05PR 143 9.36E 03 3.75E 03 4.64E 02 0.00E-01 2.16E 03 2.81E 05 2.00E 05

PR 144 3.10E-02 1.25E-02 1.53E-03 0.00E-01 7.05E-03 1.02E 03 2.15E-08ND 147 5.27E 03 6.10E 03 3.65E 02 0.00E-01 3.56E 03 2.21E 05 1.73E 05W 187 8.48E 00 7.08E 00 2.48E 00 0.00E-01 0.00E-01 2.90E 04 1.55E 05

NP 239 2.30E 02 2.26E 01 1.24E 01 0.00E-01 7.00E 01 3.76E 04 1.19E 05

A-46

____ _ - _ _ _ _ _ _ _ _ - _ _ _ - _ _ -

TAB m A.5-3

INHAIATION PA'IMAY FpMREM /YR PER UCI/r

TEEN (RI F1CIORS)

NUCLIDE BONE LIVER T BODY 'IHYROID KIDNEY IRG GI-ILI


P 32 1.89E 06 1.10E 05 7.16E 04 0.00E-01 0.00E-01 0.00E-01 9.28E 04CR 51 0.00E-01 0.00E-01 1.35E 02 7.50E 01 3.07E 01 2.10E 04 3.00E 03MN 54 0.00E-01 5.11E 04 8.40E 03 0.00E-01 1.27E_04 1.98E 06 6.68E 04

MN 56 0.00E-01 1.70E 00 2.52E-01 0.00E-01 1.79E 00 1.53E 04 5.74E 04FE 55 3.34E 04 2.38E 04 5.54E 03 0.00E-01 0.00E-01 1.24E 05 6.39E 03FE 59 1.59E 04 3.70E 04 1.43E 04 0.00E-01 0.00E-01 1.53E 06 1.78E 05

CO 58 0.00E-01 2.07E 03 2.78E 03 0.00E-01 0.00E-01 1.34E 06 9.52E 04CO 60 0.00E-01 1.51E 04 1.98E 04 0.00E-01 0.00E-01 8.72E 06 2.59E 05NI 63 5.80E 05 4.34E 04 1.98E 04 0.00E-01 0.00E-01 3.07E 05 1.42E 04

NI 65 2.18E 00 2.93E-01 1.27E-01 0.00E-01 0.00E-01 9.36E 03 3.67E 04CU 64 0.00E-01 2.03E 00 8.48E-01 0.00E-01 6.41E 00 1.11E 04 6.14E 04ZN 65 3.86E 04 1.34E 05 6.24E 04 0.00E-01 8.64E 04 1.24E 06 4.66E 04

ZN 69 4.83E-02 9.20E-02 6.46E-03 0.00E-01 6.02E-02 1.58E 03 2.85E 02BR 83 0.00E-01 0.00E-01 3.44E 02 0.00E-01 0.00E-01 0.00E-01 8.00E-15BR 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-15RB 86 0.00E-01 1.90E 05 8.40E 04 0.00E-01 0.00E-01 0.00E-01 1.77E 04RB 88 0.00E-01 5.46E 02 2.72E 02 0.00E-01 0.00E-01 0.00E-01 '2.92E-05

RB 89 0.00E-01 3.52E 02 2.33E 02 0.00E-01 0.00E-01 0.00E-01 3.38E-07SR 89 4.34E 05 0.00E-01 1.25E 04 0.00E-01 0.00E-01 2.42E 06 3.71E 05SR 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 05SR 92 9.52E 00 0.00E-01 4.06E-01 0.00E-01 0.00E-01' 2.74E 04 1.19E 05Y 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 01Y 91 6.61E 05 0.00E-01 1.77E 04 0.00E-01 0.00E-01 2.94E 06 4.09E 05Y 92 1.47E 01 0.00E-01 4.29E-01 0.00E-01 0.00E-01 2.68E 04 1.65E 05-

A-47

.

.

TAB m A.5-3 (cont'd)

INHAIATICN PA71MAY FMREM /YR PER UCL

TEEN (RI FACIORS)

NEX'LIDE BONE LIVER T BODY 'IHYROID KIDNEY IUNG GI-ILI

Y 93 1.35E 02 0.00E-01 3.72E 00 0.00E-01 0.00E-01 8.32E 04 5.79E 05ZR 95 1.46E 05 4.58E 04 3.15E 04 0.00E-01 6.74E 04 2.69E 06 1.49E 05ZR 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 04MD 99 0.00E-01 1.69E 02 3.22E 01 0.00E-01 4.11E 02 1.54E 05 2.69E 05TC 99M 1.38E-03 3.86E-03 4.99E-02 0.00E-01 5.76E-02 1.15E 03 6.13E 03

1C 101 5.92E-05 8.40E-05 8.24E-04 0.00E-01 1.52E-03 6.67E 02 8.72E-07.RU 103 2.10E 03 0.00E-01 8.96E 02 0.00E-01 7.43E 03 7.83E 05 1.09E 05RU 105 1.12E 00 0.00E-01 4.34E-01 0.00E-01 1.41E 00 1.82E 04 9.04E 04

RU 106 9.84E 04 0.00E-01 1.24E 04 0.00E-01 1.90E 05 1.61E 07 9.60E 05AG 11GM 1.38E 04 1.31E 04 7.99E 03 0.00E-01 2.50E 04 6.75E 06 2.73E 05TE 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 2.18E 03 4.38E 03 6.54E 04 1.66E 06 1.59E 05TE 127 2.01E 00 9.12E-01 4.42E-01 1.42E 00 7.28E 00 1.12E 04 8.08E 01TE 129M 1.39E 04 6.58E 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 03TE 13LM 9.84E 01 6.01E 01 4.20E 01 7.25E 01 4.39E 02 2.38E 05 6.21E 05TE 131 1.58E-02 8.32E-03 5.04B-03 1.24E-02 6.18E-02 2.34E 03 1.51E 01

TE 132 3.60E 02 2.90E 02 2.19E 02 2.46E 02 1.95E 03 4.49E 05 4.63E 05I 130 6.24E 03 1.79E 04 7.17E 03 1.49E 06 2.75E 04 0.00E-01 9.12E 03I 131 3.54E 04 4.91E 04 2.64E 04 1.46E 07 8.40E 04 0.00E-01 6.49E 03

I 132 1.59E 03 4.38E 03 1.5SE 03 1.51E 05 6.92E 03 0.00E-01 1.27E 03I 133 1.22E 04 2.05E 04 6.22E 03 2.92E 06 3.59E 04 0.00E-01 1.03E 04I 134 8.88E 02 2.32E 03 8.40E 02 3.95E 04 3.66E 03 0.00E-01 2.04E 01


CS 137 6.70E 05 8.48E 05 3.11E 05 0.00E-01 3.04E 05 1.21E 05 8.48E 03CS 138 4.66E 02 8.56E 02 4.46E 02 0.00E-01 6.62E 02 7.87E 01 2.70E-01BA 139 1.34E 00 9.44E-04 3.90E-02 0.00E-01 8.88E-04 6.46E 03 6.45E 03

A-48

I

I

TMER A.5-3 (cont'd)

DEIAIATION PA115%Y pFMREM /YR PER UCI/W

TEEN (RI FKJIORS)

NUCLIDE BONE LIVER T BODY THYROID KIDNEY IUtG GI-ILI

BA 140 5.47E 04 6.70E 01 3.52E 03 0.00E-01 2.28E 01 2.03E 06 2.29E 05BA 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

1A 140 4.79E 02 2.36E 02 6.26E 01 0.00E-01 0.00E-01 2.14E 05 4.87E 05IA 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


PR 144 4.30E-02 1.76E-02 2.18E-03 0.00E-01 1.01E-02 1.75E 03 2.35E-04ND 147 7.86E 03 8.56E 03 5.13E 02 0.00E-01 5.02E 03 a.72E 05 1.82E 05W 187 1.20E 01 9.76E 00 3.43E 00 0.00E-01 0.00E-01 4.74E 04 1.77E 05 i

NP 239 3.38E 02 3.19E 01 1.77E 01 0.00E-01 1.00E 02 6.49E 04 1.32E 05

!

1

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!

1

l

|A-49l

|

|l

I

I

I|l

!

'lTABLE A.5-4 j4

INHAIATION PATHWAY FpORMRDVYR PER UCI/M-

,

CHIID (RI FACTORS) )i

NUCLIDE BONE LIVER T BODY THYROID KIDNEY I13fC GI-ILI l

i

H 3 0.00E-01 1.12E 03 1.12E 03 1.12E 03 1.12E 03 1.12E 03 1.12E 03C 14 3.59E 04 6.73E 03 6.73E 03 6.73E 03 6.73E 03 6.73E 03 6.73E 03 JNA 24 1.61E 04 1.61E 04 1.61E 04 1.6]E 04 1.61E 04 1.61E 04 1.61E 04

P 32 2.60E 06 1.14E 05 9.88E 04 0.00E-01 0.00E-01 0.00E-01 4.22E 04CR 51 0.00E-01 0.00E-01 1.54E 02 8.55E 01 2.43E 01 1.70E 04 1.08E 03 -|101 54 0.00E-01 4.29E 04 9.51E 03 0.00E-01 1.00E 04 1.58E 06 2.29E 04

;

F23 56 0.00E-01 1.66E 00 3.12E-01 0.00E-01 1.67E 00 1.31E 04 1.23E 05FE 55 4.74E 04 2.52E 04 7.77E 03 0.00E-01 0.00E-01 1.11E 05 2.87E 03FE 59 2.07E 04 3.34E 04 1.67E 04 0.00E-01 0.00E-01 1.27E 06 7.07E 04

00 58 0.00E-01 1.77E 03 3.16E 03 0.00E-01 0.00E-01 1.11E 06 3.44E 0400 60 0.00E-01 1.31E 04 2.26E 04 0.00E-01 0.00E-01 7.07E 06 9.62E 04NI 63 8.21E 05 4.63E 04 2.80E 04 0.00E-01 0.00E-0? 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 04CU 64 0.00E-01 1.99E 00 1.07E 00 0.00E-01 6.03E 00 9.58E 03 3.67E 04ZN 65 4.26E 04 1.13E 05 7.03E 04 0.00E-01 7.14E 04 9.95E 05 1.63E 04



RB 89 0.00E-01 3.45E 02 2.90E 02 0.00E-01 0.00E-01 0.00E-01- 1.89E 00SR 89 5.99E 05 0.00E-01 1.72E 04 0.00E-01 0.00E-01 2.16E 06 1.67E 05SR 90 1.01E 08 0.00E-01 6.44E 06 0.00E-01 0.00E-01 1.48E 07 3.43E 05

SR 91 1.21E 02 0.00E-01 4.59E 00 0.00E-01 0.00E-01 5.33E 04 1.74E 05 |_SR 92 1.31E 01 0.00E-01 5.25E-01 0.00E-01 0.00E-01 2.40E 04 2.42E 05Y 90 4.11E 03 0.00E-01 1.11E 02 0.00E-01 0.00E-01 2.62E 05 2.68E 05

Y 91M 5.07E-01 0.00E-01 1.84E-02 0.00E-01 0.00E-01 2.81E 03 1.72E 03Y 91 9.14E 05 0.00E-01 2.44E 04 0.00E-01 0.00E-01 2.63E 06 1.84E 05Y 92 2.04E 01 0.00E-01 5.81E-01 0.00E-01 0.00E-01 2.39E 04 2.39E 05

A-509/93

1|

|

TABLE A.5-4 (cxmt'd),

|

INHAIATION PATHOLY F pMREM /YR PER UCI/M-OUID (RI FACIORS)

NtK'LIDE FONE LIVER T BODY THYROID KIDNEY IRC GI-ILI


NB 95 2.35E 04 9.18E 03 6.55E 03 0.00E-01 8.62E 03 6.14E 05 3.70E 04MD 99 0.00E-01 1.72E 02 4.25E 01 0.00E-01 3.92E 02 1.35E 05 1.27E 05TC 99M 1.78E-03 3.48E-03 5.77E-02 0.00E-01 5.07E-02 9.51E 02 4.81E 03

3C 101 8.10E-05 0.51E-05 1.08E-03 0.00E-01 1.45E-03 5.85E 02 1.63E 01RU 103 2.79E 03 0.00E-01 1.07E 03 0.00E-01 7.03E 03 6.62E 05 4.48E 04RU 105 1.53E 00 0.00E-01 5.55E-01 0.00E-01 1.34E 00 1.59E 04 9.95E 04

RU 106 1.36E 05 0.00E-01 1.69E 04 0.00E-01 1.84E 05 1.43E 07 4.29E 05AG 110M 1.69E 04 1.14E 04 9.14E 03 0.00E-01 2.12E 04 5.48E 06 1.00E 05

| TE 125M 6.73E 03 2.33E 03 9.14E 02 1.92E 03 0.00E-01 4.77E 05 3.38E 04

TE 127H 2.49E 04 8.55E 03 3.02E 03 6.07E 03 6.36E 04 1.48E 067.14E 04 | -TE 127 2.77E 00 9.51E-01 6.10E-01 1.96E 00 7.07E 00 1.00E 04 5.62E 04

7E 129M 1.92E 04 6.85E 03 3.04E 03 6.33E 03 5.03E 04 1.76E 06 1.82E 05

TE 129 9.77E-02 3.50E-02 2.38E-02 7.14E-02 2.57E-01 2.93E 03 2.55E 04TE 13EH 1.34E 02 5.92E 01 5.07E 01 9.77E 01 4.00E 02 2.06E 05 3.08E 05TE 131 2.17E-02 8.44E-03 6.59E-03 1.70E-02 5.88E-02 2.05E 03 1.33E 03

TE 132 4.81E 02 2.72E 02 2.63E 02 3.17E 02 1.77E 03- 3.77E 05 1.38E 05I 130 8.18E 03 1.64E 04 8.44E 03 1.85E 06 2.45E 04 0.00E-01 5.11E 03 ,

I 131 4.81E 04 4.81E 04 2.73E 04 1.62E 07 7.88E 04 0.00E-01 2.84E 03 '

I 132 2.12E 03 4.07E 03 1.88E 03 1.94E 05 6.2SE 03 0.00E-01 3.20E 03I 133 1.66E 04 2.03E 04 7.70E 03 3.85E 06 3.38E 04 0.00E-01 5.48E 03 i

I 134 1.17E 03 2.16E 03 9.95E 02 5.07E 04 3.30E 03 0.00E-01 9.55E 02

I 135 4.92E 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 i

A-519/93 1

|

i|

\

D B 2 A.5-4 (cont'd)'

DHiAIATICN PATiiWAY pMREM /YR PER UCI/rCHIID (RI FACIORS) I

NUC[JDE BOtJE LIVER T BODY 'HiYROID KIDNEY IDG GI-ILI

BA 140 7.40E 04 6.48E 01 4.33E 03 0.00E-01 2.11E 01 '1.74E 06 1.02E 05BA 141 1.96E-01 1.09E-04 6.36E-03 0.00E-01 9.47E-05 2.92E 03 2.75E 02BA 142 4.99E-02 3.60E-05 2.79E-03 0.00E-01 2.91E-05 1.64E 03 2.74E 00

IA 140 6.44E 02 2.25E 02 7.55E 01 0.00E-01 0.00E-01 1.83E 05 2.26E 051A 142 1.29E 00 4.11E-01 1.29E-01 0.00E-01 0.00E-01 8.70E 03 7.59E 04CE 141 3.92E 04 1.95E 04 2.90E 03 0.00E-01 8.55E 03 5.44E 05 5.66E 04


PR 144 5.96E-02 1.85E-02 3.00E-03 0.00E-01 9.77E-03 1.57E 03 1.97E 02ND 147 1.08E 04 8.73E 03 6.81E 02 0.00E-01 4.81E 03 3.28E 05 8.21E 04W 187 1.63E 01 9.66E 00 4.33E 00 0.00E-01 0.00E-01 4.11E 04 9.10E 04

NP 239 4.66E 02 3.34E 01 2.35E 01 0.00E-01 9.73E 01 5.81E 04 6.40E 04

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,

A-52 )ii|

I

I

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TAB 2 A S-5

INIMIATION PATIMAY F3 CITMRE24/YR PER UCI/M"INFAFTP (RI FACIGS)

~NUCLIDE BONE LIVER T DODY 'IUYROID KIDNEY IljtG GI-ILI

H 3 0.00E-01 6.47E 02 6.47E 02 6.47E 02 6.47E 02 6.47E 02 6.47E 02C 14 2.65E 04 5,31E 03 5.31E 03 5.31E 03 5.31E 03 5.31E 03 5.31E 03ta 24 1.06E 04 1.06E 04 1.06E 04 1.06E 04 1.06E 04 1.06E 04 1.06E 04

P 32 2.03E 06 1.12E 05 7.74E 04 0.00E-01 0.00E-01 0.00E-01 1.61E 04CR 51 0.00E-01 0.00E-01 8.95E 01 5.75E 01 1.32E 01 1.28E 04 3.57E 02MN 54 0.00E-01 2.53E 04 4.98E 03 0.00E-01 4.98E 03 1.00E 06 7.06E 03

MN 56 0.00E-01 1.54E 00 2.21E-01 0.00E-01 1.10E 00 1.25E 04 7.17E 04.FE 55 1.97E 04 1.17E 04 3.33E 03 0.00E-01 0.00E-01 8.69E 04 1.09E 03FE 59 1.36E 04 2.35E 04 9.48E 03 0.00E-01 0.00E-01 1.02E 06 2.48E 04

CO 58 0.00E-01 1.22E 03 1.82E 03 0.00E-01 0.00E-01 7.77E 05 1.11E 0400 60 0.00E-01 8.02E 03 1.18E 04 0.00E-01 0.00E-01 4.51E 06 3.19E 04NI 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 04CU 64 0.00E-01 1.88E 00 7.74E-01 0.00E-01 3.98E 00 9.30E 03 1.50E 04ZN 65 1.93E 04 6.26E 04 3.11E 04 0.00E-01 3.25E 04 6.47E 05 5.14E 04



RB 89 0.00E-01 3.21E 02 2.06E 02 0.00E-01 0.00E-01 0.00E-01 6.82E 01SR 89 3.98E 05 0.00E-01 1.14E 04 0.00E-01 0.00E-01 2.03E 06 6.40E 04SR 90 4.09E 07 0.00E-01 2.59E 06 0.00E-01 0.00E-01 1.12E 07 1.31E 05

SR 91 9.56E 01 0.00E-01 3.46E 00 0.00E-01 0.00E-01 5.26E 04 7.34E 04SR 92 1.05E 01 0.00E-01 3.91E-01 0.00E-01 0.00E-01 2.38E 04 1.40E 05Y 90 3.29E 03 0.00E-01 8.82E 01 0.00E-01 0.00E-01 2.69E 05 1.04E 05

Y 91M 4.07E-01 0.00E-01 1.39E-02 0.00E-01 0.00E-01 2.79E 03 2.35E 03Y 91 5.88E 05 0.00E-01 1.57E 04 0.00E-01 0.00E-01 2.45E 06 7.03E 04Y 92 1.64E 01 0.00E-01 4.61E-01 0.00E-01 0.00E-01 2.45E 04 1.27E 05

A-53

.

'mB 2 A.5-5 (cont'd)

INIAIATION PATHWAY FAgTORSMREM /YR PER UCI/WINFANT (RI FACIORS)

NUCLIDE BONE LIVER T BODY 4HYROID KIDNEY LUfG GI-IL_I


NB 95 1.57E 04 6.43E 03 3.78E 03 0.00E-01 4.72E 03 4.79E 05 1.27E 04HD 99 0.00E-01 1.65E 02 3.23E 01 0.00E-01 2.65E 02 1.35E 05 4.87E 04'IC 99M 1.40E-04 2.88E-03 3.72E-02 0.00E-01 3.11E-02 8.11E 02 2.03E 03

TC 101 6.51E-05 8.23E-05 8.12E-04 0.00E-01 9.79E-04 5.84E 02- 8.44E 02RU 103 2.02E 03 0.00E-01 6.79E 02 0.00E-01 4.24E 03 5.52E 05 1.61E 04RU 105 1.22E 00 0.00E-01 4.10E-01 0.00E-01 8.99E-01 1.57E 04 4.84E 04

RU 106 8.68E 04 0.00E-01 1.09E 04 0.00E-01 1.07E 05 1.16E 07 1.64E 051G 110M 9.98E 03 7.22E 03 5.00E 03 0.00E-01 1.09E 04 3.67E 06 3.30E 04TE 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 04TE 127 2.23E 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 3.00E 03 2.63E 04 i

TE 131M 1.07E 02 5.50E 01 3.63E 01 8.93E 01 2.65E 02 1.99E 05 1.19E 05 |TE 131 1.74E-02 8.22E-03 5.00E-03 1.58E-02 3.99E-02 2.06E 03 8.22E 03

TE 132 3.72E 02 2.37E 02 1.76E 02 2.79E 02 1.03E 03 3.40E 05 4.41E 04I 130 6.36E 03 1.39E 04 5.57E 03 1.60E 06 1.53E 04 0.00E-01 1.99E 03I 131 3.79E 04 4.44E 04 1.96E 04 1.48E 07 5.18E 04 0.00E-01 1.06E 03

I 132 1.69E 03 3.54E 03 1.26E 03 1.69E 05 3.95E 03 0.00E-01 1.90E 03 i

I 133 1.32E 04 1.92E 04 5.60E 03 3.56E 06 2.24E 04 0.00E-01 2.16E 03 II 134 9.21E 02 1.88E 03 6.65E 02 4.45E 04 2.09E 03 0.00E-01 1.29E 03


CS 137 5.49E 05 6.12E 05 4.55E 04 0.00E-01 1.72E 05 7.13E 04- 1.33E 03CS 138 5.05E 02 7.81E 02 3.98E 02 0.00E-01 4.10E 02 6.54E 01 8.76E 02BA 139 1.48E 00 9.84E-04 4.30E-02 0.00E-01 5.92E-04 5.95E 03 5.10E 04

A-54

.

t'

!

|

TABLE A.5-5 (cont'd) |

INHAIATICN PA'IHWAY F1QIORSMREM /YR PER UCI M.INFANI' (RI F1CIGS)

NUCLIDE BONE LIVER T BDDY THYROID KIDfEY LUNG GI-ILI

BA 140 5.60E 04 5.60E 01 2.90E 03 0.00E-01 1.34E 01 1.60E 06 3.84E 04BA 141 1.57E-01 1.08E-04 4.97E-03 0.00E-01 6.50E-05 2.97E 03 4.75E 03BA 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 04IA 142 1.03E 00 3.77E-01 9.04E-02 0.00E-01 0.00E-01 8.22E 03 5.95E 04CE 141 2.77E 04 1.67E 04 1.99E 03 0.00E-01 5.2SE 03 5.17E 05 2.16E 04


PR 144 4.79E-02 1.85E-02 2.41E-03 0.00E-01 6.72E-03 1.61E 03 4.28E 03ND 147 7.94E 03 8.13E 03 5.00E 02 0.00E-01 3.15E 03 3.22E 05 3.12E 04W 187 1.30E 01 9.02E 00 3.12E 00 0.00E-01 0.00E-01- 3.96E 05 3.56E 04

NP 239 3.71E 02 3.32E 01 1.88E 01 0.002-01 6.62E 01 5.95E 04 2.49E 04

A-55

_ - - _ _- .- _ - __.

. _ _

'mBLE A.5-6

GRASg-CON-MILK PA'li5RY F1CIORM MREM /YR PER UCI/SEC

ADULT (RI FAC' LGS)

NIX'LIDE BONE LIVER T BODY 'IHYROID KIDNEY LUNG GI-LLI

H 3 0.00E-01 7.63E 02 7.63E 02 7.63E 02 7.63E 02 '7.63E 02 7.63E 02 >

C 14 2.63E 08 5.27E 07 5.27E 07 5.27E 07 5.27E 07 5 27E 07 5.27E 07' ,

FR 24 2.44E 06 2.44E 06 2.44E 06 2.44E 06 2.44E 06 2.44E 06 2.44E 06.

P 32 1.71E 10 1.06E 09 6.60E 08 0.00E-01 0.00E-01 0.00E-01 1.92E 09CR 51 0.00E-01 0.00E-01 2.86E 04 0.00E-01 6.30E 03 3.79E 04 7.19E 06MN 54 0.00E-01 8.41E 06 1.61E 06 0.00E-01 0.00E-01 0.00E-01 2.58E 07

MN 56 0.00E-01 4.16E-03 7.38E-04 0.00E-01 5.28E-03 0.00E-01 1.33E-01FE 55 2.51E 07 1.73E 07 4.04E 06 0.00E-01 0.00E-01 9.67E 06 9.95E 06FE 59 2.97E 07 6.98E 07 2.68E 07 0.00E-01 0.00E-01 1.95E 07 2.33E 08

CO 58 0.00E-01 4.71E 06 1.06E 07 0.00E-01 0.00E-01 0.00E-01 9.56E 07CO 60 0.00E-01 1.64E 07 3.62E 07 0.00E-01 0.00E-01 0.00E-01 3.08E 08.NI 63 6.73E 09 4.71E 08 2.26E 08 0.00E-01 0.00E-01 0.00E-01 9.73E 07

NI 65 4.63E-01 6.02E-02 2.75E-02 0.00E-01 0.00E-01 0.00E-01 1.53E 00CU 64 0.00E-01 2.39E 04 1.12E 04 0.00E-01 6.02E 04 0.00E-01 2.03E 06 )ZN 65 1.37E 09 4.37E 09 1.97E 09 0.00E-01 2.92E 09 0.00E-01 2.75E 09 j

ZN 69 5.22E-12 9.99E-12 6.95E-13 0.00E-01 6.49E-12 0.00E-01 1.50E-12 IBR 83 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01- IBR 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-01RB 86 0.00E-01 2.59E 09 1.21E 09 0.00E-01 0.00E-01 0.00E-01 5.12E 08.RB 88 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01-

RB 89 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01SR 89 1.45E 09 0.00E-01 4.16E 07 0.00E-01 0.00E-01 0.00E-01 2.33E 08SR 90 4.68E 10 0.00E-01 1.15E 10 0.00E-01 0.00E-01 0.00E-01 1.35E 09

SR 91 2.87E 04 0.00E-01 1.16E 03 0.00E-01 0.00E-01 0.00E-01 1.37E 05SR 92 4.90E-01 0.00E-01 2.12E-02 0.00E-01 0.00E-01 0 00E-01 9.70E 00Y 90 7.07E 01 0.00E-01 1.90E 00 0.00E-01 0.00E-01 0.00E-01 7.50E 05

Y 91M 6.03E-20 0.00E-01 2.34E-21 0.00E-01 0.00E-01 0.00E-01 1.77E-19Y 91 8.59E 03 0.00E-01 2.30E 02 0.00E-01 0.00E-01 0.00E-01 4.73E 06Y 92 5.59E-05 0.00E-01 1.63E-06 0.00E-01 0.00E-01 0.00E-01 9.79E-01

A-56

. - - .

. .- - - . - -. .. .. . -. _ .. .. - . -

TRH 2 A.5-6 (cont'd)

GRASg NREM/YR PER UCI/SECCOW-MILK PATENAY FACIOR

,

M-ADULT (RI FACTORS)

NUCLIDE' BONE- LIVER T BODY 'IHYROID KIDNEY LUNG GI-ILI

Y 93 2.33E-01 0.00E-01 6.44E-03 0.00E-01 0.00E-01 0.00E-01 7.39E 03-ZR 95 9.44E 02 3.03E 02 2.05E 02 - 0.00E-01- 4.75E 02 0.00E-01 9.59E 05ZR 97 4.33E-01 8.75E-05 4.00E-02 0.00E-01 l.32E-01 0.00E-01 '2.71E 04-

NB 95 8.26E 04 4.59E 04 2.47E 04 0.00E-01 4.54E 04 0.00E-01 2.79E 08-ND 99 0.00E-01 2.48E 07 4.71E 06 0.00E-01 5.61E 07 0.00E-01 -5.74E 07:TC 99M 3.33E 00 9.40E 00 1.20E 02 0.00E-01 3.43E 02 4.60E 00 '5.56E 03:

TC 101 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01. 0.00E-01 0.00E-01- ,

RU 103 1.02E 03 0.00E-01 4.38E 02 0.00E-01 3.88E 03 0.00E-01 1.19E 05-RU 105 8.58E-04 0.00E-01 3.39E-04- 0.00E-01- 1.11E-02 0.00E-01 5.25E-01

'

RU 106 2.04E 04- 0.00E-01 2.58E 03 0.00E-01. 3.94E 04 0.00E-01 1.32E 06LAG 110M 5.82E 07 5.39E 07 3.20E 07 0.00E-01- 1.06E 08 0.00E-01 12.20E-101TE 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 04TE 129M- 6.02E 07 2.25E 07 9.53E 06 2.07E 07~ 2.51E 08 0.00E-01 '3.03E 08-

TE 129 2.84E-10 1.07E-10 6.29E-11 2.18E-10 1.19E-09 0.00E-01 2.14E-10-TE '13EH 3.6]E 05 1.77E 05- 1.47E 05 2.80E 05 1.79E 06 0.00E-01 1.73E 07TE 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 07JI 130 4.20E 05 1.24E 06 4.89E 05 1.05E 08 1.94E 06 -0.00E-01 1.07E 06 '

I 131 '2.96E 08 4.24E 08 2.43E 08 1.39E 11- 7.26E 08 0.00E-01 1.12E 08 :

I 132 1.65E-01 4.41E-01 1.54E-01 1.54E 01 7.02E-01 0.00E-01- 8.28E-02 '

I 133 3.87E 06 6.73E 06 2.05E 06 9.90E 08 1.18E 07 0.00E-01 6.05E 06-I 134 2.03E-12 5.52E-12 1.98E-12 9.57E-11 8.78E-12 0.00E-01 4.81E-15.

'

I 135 1.29E 04 3.37E 04 1.24E 04 2.22E 06 5.40E 04 0.00E-01 3.80E 04CS 134 5.65E 09 1.35E 10 1.10E 10 0.00E-01- 4.35E 09 1.45E 09 2.35E 08' |

CS 136 2.61E 08 1.03E 09 7.428 08 0.00E-01 ~5.73E 08 7.86E 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'CS 138 9.16E-24 1.81E-23 8.97E-24 0.00E-01 1.33E-23 1.31E-24 7.72E-29BA 139 4.56E-08 3.25E-11 1.34E-09 0.00E-01 3.04E-11 1.84E-11 8.09E-08.

A-57

|

]'

. . . - - . - -. - . . - - . .- - .-

TABLE A.5-6 (cxmt'd)

GRASg-COW-MILK PATHWAY FACIORM~ MREM /YR PER UCI/SEC

ADULT (RI FACIORS)

E UJDE BONE LIVER T BODY 'lHYROID KIDNEY LUNG GT-ILI

BA 140 2.69E 07 3.38E 04 1.76E 06 0.00E-01 1.15E 04 1.93E 04 5.54E 07BA 141 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00F-01 0.00E-01 0.00E-01BA 142 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01

LA 140 4.52E 00 2.28E 00 6.02E-01 0.00E-01 0.00E-01 0.00E-01 1.67E 05IA 142 9.39E-12 4.27E-12 1.06E-12 0.00E-01 0.00E-01 0.00E-01 3.12E-08CE 141 4.84E 03 3.28E 03 3.72E 02 0.00E-01 1.52E 03 0.00E-01 1.25E 07

CE 143 4.16E 01 3.07E 04 3.40E 00 0.00E-01 1.35E 01 0.00E-01 1.15E 06CE 144 3.58E 05 1.50E 05 1.92E 04 0.00E-01 8.07E 04 0.00E-01 1.21E 08PR 143 1.58E 02 6.33E 01 7.83E 00 0.00E-01 3.66E 01 0.00E-01 6.92E M

PR 144 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01ND 147 9.46E 01 1.09E 02 6.55E 00 0.00E-01 6.40E 01 0.00E-01 5.25E 05W 187 6.56E 03 5.49E 03 1.92E 03 0.00E-01 0.00E-01 0.00E-01 1.80E 06

NP 239 3.67E 00 3.61E-01 1.99E-01 0.00E-01 1.13E 00 0.00E-01 7.41E 04

i

-|

A-58

'

1

I.

'INEZ A.5--7 |

GRASg-COW-MIII PA'IfMAY FAC'KR 1

M MRfW YR PER UCI/SEC |

TEEN (RI FICIT S)

NUCLIDE BCNE LIVER T BODY 'IHYROID KIDNEY LUNG GI-ILI

iH 3 0.00E-01 9.94E 02 9.94E 02 9.94E 02 9.94E 02 9.94E 02 9.94E 02C 14 ;.86E 08 9.72E 07 9.72E 07 9.72E 07 9.72E 07 9.72E 07 9.72E 07NA 24 4.26E 06 4.26E 06 4.26E 06 4.26E 06 4.26E 06 4.26E 06 4.26E 06

P 32 3.15E 10 1.95E 09 1.22E 09 0.00E-01 0.00E-01 0.00E-01 2.65E 09|CR 51 0.00E-01 0.00E-01 4.99E 04 2.77E 04 1.09E 04 7.13E 04 8.39E 06

MN 54 0.00E-01 1.40E 07 2.78E 06 0.00E-01 4.18E 06 0.00E-01 2.87E 07

MN 56 0.00E-01 7.37E-03 1.31E-03 0.00E-01 9.33E-03 0.00E-01 4.85E-01FE 55 4.45E 07 3.16E 07 7.36E 06 0.00E-01 0.00E-01 2.00E 07 1.37E 07FE 59 5.18E 07 1.21E 08 4.67E 07 0.00E-01 0.00E-01 3,81E 07 2.86E 08

00 58 0.00E-01 7.94E 06 1.83E 07 0.00E-01 0.00E-01 0.00E-01 1.09E 0800 60 0.00E-01 2.78E 07 6.26E 07 0.00E-01 0.00E-01 0.00E-01 3.62E 08 l

NI 63 1.18E 10 8.35E 08 4.01E 08 0.00E-01 0.00E-01 0.00E-01 1.33E 08

NI 65 8.48E-01 1.08E-01 4.94E-02 0.00E-01 0.00E-01 0.00E-01 -5.88E 00 !CU 64 0.00E-01 4.25E 04 2.00E 04 0.00E-01 1,08E 05 0.00E-01 3.30E 06 ;KN 65 2.11E 09 7.31E 09 3.41E 09 0.00E-01 4.68E 09 0.00E-01 3.10E 09 )

|ZN 69 9.62E-12 1.83E-11 1.28E-12 0.00E-01 1.20E-11 0.00E-01 3.38E-11 ;

BR 83 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 I

BR 84 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 Il

BR 85 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01RB 86 0.00E-01 4.73E 09 2.22E 09 0.00E-01 0.00E-01 0.00E-01 7.00E 08 iRB 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' O.00E-01 -|SR 89 2.67E 09 0.00E-01 7.66E 07 0.00E-01 0.00E-01 0.00E-01 3.19E 08 l

SR 90 6.61E 10 0.00E-01 1.63E 10 0.00E-01 0.00E-01 0.00E-01 1.86E 09

SR 91 5.27E 04 0.00E-01 2.10E 03 0.00E-01 0.00E-01 0.00E-01 2.39E 05SR 92 8.96E-01 0.00E-01 3.82E-02 0.00E-01 0.00E-01 0.00E-01 2.28E 01Y 90 1.30E 02 0.00E-01 3.50E 00 0.00E-01 0.00E-01 0.00E-01 '1.07E 06

Y 91M 1.11E-19 0.00E-01 4.22E-21 0.00E-01 0.00E-01 0.00E-01 5.22E-18Y 91 1.58E 04 0.00E.01 4.24E 02 0.00E-01 0.00E-01 0.00E-01 6.48E 06Y 92 1.03E-04 0.00E-01 2.99E-06 0.00E-01 0.00E-01 0.00E-01 2.83E 00

A-59

.

_ _ _ _ __-_____ _ _________ _-_____- _ _ -_ _ _-_ - __-____ _ _-____ - __ - ______________

TM3LE A.5-7 (cxnt'd) ,

IGRASg-CON-MILK PA'1H&Y FICIOR

'

M MREM /YR PER UCI/SECTEEN (RI FACIORS)

NUCLIDE BONE LIVER T BODY 'IHYROID KIDNEY TIRG GI-IL_I

Y 93 4.30E-01 0.00E-01 1.18E-02 0.00E-01 0.00E-01 0.00E-01 1.31E 04 |ZR 95 1.65E 03 5.21E 02 3.58E 02 0.00E-01 7.65E 02 0.00E-01 1.20E 06ZR 97 7.89E-01 1.56E-01 7.19E-02 0.00E-01 2.37E-01 0.00E-01 4.23E 04

NB 95 1.41E 05 7.81E 04 4.30E 04 0.00E-01 7.57E 04 0.00E-01 3.34E 08MD 99 0.00E-01 4.47E 07 8.53E 06 0.00E-01 1.02E 08 0.00E-01 8.01E 07TC 99M 5.77E 00 1.61E 01 2.08E 02 0.00E-01 2.40E 02 8.93E 00 1.06E 04

'IC 101 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01RU 103 1.81E 03 0.00E-01 7.74E 02 0.00E-01 6.38E 03 0.00E-01 1.51E 05RU 105 1.57E-03 0.00E-01 6.08E-04 0.00E-01 1.98E-02 0.00E-01 1.27E 00

RU 106 3.75E 04 0.00E-01 4.73E 03 0.00E-01 7.23E 04 0.00E-01 1.80E 06AG 110M 9.63E 07 9.11E 07 5.54E 07 0.00E-01 1.74E 08 0.00E-01 2.56E 10TE 125M 3.00E 07 1.08E 07 4.02E 06 8.39E 06 0.00E-01 0.00E-01 8.86E 07

TE 127M 8.44E 07 2.99E 07 1.00E 07 2.01E 07 3.42E 08 0.00E-01 2.10E 08TE 127 1.21E 03 4.29E 02 2.61E 02 8.36E 02 4.91E 03 0.00E-01 9.35E 04TE 129M ).10E 08 4.09E 07 1.74E 07 3.55E 07 4.61E 08 0.00E-01 4.13E 08

TE 129 5.23E-10 1.95E-10 1.27E-10 3.74E-10 2.20E-09 0.00E-01 2.86E-09TE 131M 6.57E 05 3.15E 05 2.63E 05 4.74E 05 3.29E 06 0.00E-01 2.53E 07TE 131 6.70E-33 2.76E-33 2.09E-33 5.16E-33 2.93E-32 0.00E-01 5.50E-34


I 132 2.92E-01 7.65E-01 2.74E-01 2.588 01 1.20E 00 0.00E-01 3.33E-01I 133 7.07E 06 1.20E 07 3.66E 06 1.67E 09 2.10E 07 0.00E-01 9.08E 06I 134 3.61E-12 9.58E-12 3.44E-12 1.60E-10 1.51E-11 0.00E-01 1.26E-13


CS 137 1.34E 10 1.78E 10 6.20E 09 0.00E-01 6.06E 09 2.35E 09 2.53E 08CS 138 1.66E-23 3.19E-23 1.60E-23 0.00E-01 2.36E-23 2.74E-24 1.45E-26BA 139 8.44E-08 5.94E-11 2.46E-09 0.00E-01 5.60E-11 4.09E-11 7.53E-07

A-60

!,

. . . . .. - - - - - - - - - - - _

;

TMEE A.5-7 (cont'd)

GRASg-CON-MILK PA'1HRY F1CIORM MRDUYR PER UCI/SEC

TEEN (RI F1CICRS)

NUCLIDE BONE LIVER T IODY 'IHYROID KIDNEY LUtG GI-LLI

BA 140 4.85E 07 5.95E 04 3.13E 06 0.00E-01 2.02E 04 4.00E 04 7.48E 07BA 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

IA 140 8.12E 00 3.99E 00 1.06E 00 0.00E-01 0.00E-01 0.00E-01 2.29E 05IA 142 1.69E-11 7.52E-12 1.87E-12 0.00E-01 0.00E-01 0.00E-01 2.29E-07CE 141 8.88E 03 5.93E 03 6.81E 02 0.00E-01 2.79E 03 0.00E-01 1.70E 07

CE 143 7.64E 01 5.56E 04 6.21E 00 0.00E-01 2.49E 01 0.00E-01 1.67E 06CE 144 6.58E 05 2.72E 05 3.54E 04 0.00E-01 1.63E 05 0.00E-01 1.66E 08PR 143 2.90E 02 1.16E 02 1.44E 01 0.00E-01 6.73E 01 0.00E-01 9.55E 05


NP 239 7.01E 00 6.61E-01 3.67E-01 0.00E-01 2.07E 00 0.00E-01 1.06E 05

|

|

|

|

|

A-61

J

i

,

'mBLE A.5-8

GRASg-COR-MIII PA'IHWAY FACIORM MREM /YR PER UCI/SEC

CHILD (RI FACIORS)

NUCLIDE BONE LIVER T BODY THYROID KIDNEY IRC GI-ILI


P 32 7.77E 10 3.64E 09 3.00E 09 0.00E-01 0.00E-01 0.00E-01 2.15E 09CR 51 0.00E-01 0.00E-01 1.02E 05 5.65E 04 1.54E 04 1.03E 05 5.40E 06MN 54 0.00E-01 2.10E 07 5.59E 06 0.00E-01 5.88E 06 0.00E-01 1.76E 07-

MN 56 0.00E-01 1.29E-02 2.90E-03 0.00E-01 1.56E-02 0.00E-01 1.86E 00FE 55 1.12E 08 5.93E 07 1.84E 07 0.00E-01 0.00E-01 3.35E 07 1.10E 07FE 59 1.20E 08 1.94E 08 9.69E 07 0.00E-01 0.00E-01 5.64E 07 2.02E 08


NI 65 2.07E 00 1.95E-01 1.14E-01 0.00E-01 0.00E-01 0.00E-01 2.39E 01CU 64 0.00E-01 7.47E 04 4.51E 04 0.00E-01 1.81E 05 0.00E-01 3.51E 06ZN 65 4.13E 09 1.10E 10 6.85E 09 0.00E-01 6.94E 09 0.00E-01 1.93E 09

ZN 69 2.36E-11 3.42E-11 3.16E-12 0.00E-01 2.07E-11 0.00E-01 .2.15E-09BR 83 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01

3'

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-01RB 86 0.00E-01 8.77E 09 5.39E 09 0.00E-01 0.00E-01 0.00E-01 5.64E 08 iRB 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 0.0.0E- 01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 |SR 89 6.62E 09 0.00E-01 1.89E 08 0.00E-01 0.00E-01 0.00E-01 2.56E 08 i

SR 90 1.12E 11 0.00E-01 2.83E 10 0.00E-01 0.00E-01 0.00E-01 1.50E 09

SR 91 1.29E 05 0.00E-01 4.88E 03 0.00E-01 0.00E-01 0.00E-01 2.85E 05SR 92 2.19E 00 0.00E-01 8.78E-02 0.00F-01 0.00E-01 0.00E-01 4.15E 01 ^ !Y 90 3.22E 02 0.00E-01 8.61E 00 0.00E-01 0.00E-01 0.00E-01 9.15E 05 l

IY 91M 2.70E-19 0.00E-01 9.82E-21 0.00E-01 0.00E-01 0.00E-01 5.29E-16 i

Y 91 3.90E 04 0.00E-01 1.04E 03 0.00E-01 0.00E-01 0.00E-01 5.20E 06 | ||Y 92 2.54E-04 0.00E-01 7.26E-06 0.00E-01 0.00E-01 0.00E-01 7.33E 00.

A-629/93 |

'

_ _ _ _ _ _ _ _. .

'l|

TABLE A.5-8 (Ocut'd)

G-RASg-(IM-MILK PATHNAY FACIORM MRDVYR PER UCI/SEC

CHIID (RI FACIORS)

NO3 IDE BONE LIVER T BJDY THYROID KIDNEY IRG GI-ILI

Y 93 1.06E 00 0.00E-01 2.90E-02 0.00E-01 0.00E-01 0.00E-01 1.57E 04ZR 95 3.83E 03 8.43E 02 7.50E 02 0.00E-01 1.21E 03 0.00E-01 8.79E 05 :ZR 97 1.92E 00 2.77E-01 1.64E-01 0.00E-01 3.98E-01 0.00E-01 4.20E 04

NB 95 3.18E 05 1.24E 05 8.85E 04 0.00E-01 1.16E 05 0.00E-01 2.29E 08MO 99 0.00E-01 8.14E 07 2.01E 07 0.00E-01 1.74E 08 0.00E-01 6.73E 07TC 99M 1.32E 01 2.59E 01 4.30E 02 0.00E-01 3.77E 02 1.32E 01 1.48E 04

TC 101 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01,

RU 103 4.28E 03 0.00E-01 1.65E 03 .0.00E-01 1.08E 04 0.00E-01 1.11E 05'RU 105 3.83E-03 0.00E-01 1.39E-03 0.00E-01 3.36E-02 0.00E-01 2.50E 00

RU 106 9.24E 04 0.00E-01 1.15E 04 0.00E-01 '1.25E 05 0.00E-01- 1.44E 06AG 110M 2.09E 08 1.41E 08 1.13E 08 0.00E-01 2.63E 08 0.00E-01 1.68E 10TE 125M 7.38E 07 2.00E 07 9.84E 06 2.07E 07 0.00E-01 0.00E-01 7.12E 07 :

TE 127M 2.08E 08 5.60E 07 2.47E 07 4.97E 07 5.93E 08 0.00E-01 1.68E.08TE 127 2.98E 03 8.03E 02 6.39E 02 2.06E 03 8.47E 03 0.00E-01 1.16E 05TE 129M 2.71E 08 7.58E 07 4.21E 07 8.75E 07 7.97E 08 0.00E-01 3.31E 08 |

TE 129 1.29E-09 3.60E-10 3.06E-10 9.21E-10 3.78E-09 0.00E-01 8.03E-08TE 131M 1.60E 06 5.53E 05 5.89E 05 1.14E 06 5.36E 06 0.00E-01 2.24E 077E 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 071 130 1.73E 06 3.49E 06 1.80E 06 3.85E 08 5.22E 06 0.00E-01 .1.63E 06I 131 1.30E 09 1.31E 09 7.45E 08 4.33E 11 2.15E 09 0.00E-01 1.17E 08

I 132 6.91E-01 1.27E 00 5.84E-01 5.89E 01 1.94E 00 0.00E-01 1.49E 00I 133 1.72E 07 2.12E 07 0.04E 06 3.95E 09 3.54E 07 0.00E-01 8.56E 06I 134 8.55E-12 1.59E-11 7.31E-12 3.65E-10 2.43E-11 0.00E-01 1.05E-11

I 135 5.41E 04 9.73E 04 4.60E 04 8.62E 06 1.49E 05 0.00E-01 7,41E 04CS 134 2.27E 10 3.72E 10 7.84E 09 0.00E-01 1.15E 10 4.13E 09 2.00E 08CS 136 1.00E 09 2.76E 09 1.78E 09 0.00E-01 1.47E 09_ 2.19E 08 9,692 07

,

CS 137 3.22E 10 3.09E 10 4.55E 09 0.00E-01 1.01E 10 3.62E 09 1.93E 08CS 138 4.03E-23 5.60E-23 3.55E-23 0.00E-01 3.94E-23 4.24E-24 2.58E-23 i

BA 139 2.07E-07 1.11E-10 6.01E-09 0.00E-01 9.67E-11 6.51E-11 1~20E-05.

A-63 !

9/93

,

__ _

1

TABLE A.5-8 (cxmt'd)1

GRASg-CON-MILK PA'IHWAY FACIOR j

M MREM /YR PER UCI/SEC '

CHIID (RI FACIMS)

NUCLIDE BONE LIVER T BODY 'IHYROID KIDNEY IRG GT-LLI ;

BA 140 1.17E 08 1.03E 05 6.84E 06 0.00E-01 3.34E 04 6.12E 04 5.94E 07BA 141 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01BA 142 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01

LA 140 1.94E 01 6.80E 00 2.29E 00 0.00E-01 0.00E-01 0.00E-01 1.89E 05LA 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-02 4.27E 01 0.00E-01 1.49E 06CE 144 1.62E 06 5.09E 05 8.66E 04 0.00E-01 2.82E 05 0.00E-01 1.33E 08PR 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-01ND 147 4.47E 02 3.62E 02 2.80E 01 0.00E-01 1.99E 02 0.00E-01 5.73E 05W 187 2.91E 04 1.72E 04 7.73E 03 0.00E-01 0.00E-01 0.00E-01 2.42E 06-

NP 239 1.72E 01 1.24E 00 8.70E-01 0.00E-01 3.58E 00 0.00E-01 9.16E 04

A-64

. _

'mB2 A.5-9

GRASj-CON-MILK PA'lH&Y F1CIORM MREM /YER PER UCI/SEC

INFANT (RI FAC'IORS)

NTLTDE BCNE LIVER T BODY THYROID KIDNEY IRC GI-ILI


P 32 1.60E 11 9.42E 09 6.21E 09 0.00E-01 0.00E-01 0.00E-01 2.17E 09CR 51 0.00E-01 0.00E-01 1.61E 05 1.05E 05 2.30E 04 2.05E 05 4.70E 06MN 54 0.00E-01 3.90E 07 8.84E 06 0.00E-01 8.64E 06 0.00E-01 1.43E 07

MN 56 0.00E-01 3.15E-02 5.43E-03 0.00E-01 2.71E-02 0.00E-01 2.86E 00FE 55 1.35E 08 8.72E 07 2.33E 07 0.00E-01 0.00E-01 4.26E 07 1.11E 07FE 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 6.01E 07CO 60 0.00E-01 8.82E 07 2.08E 08 0.00E-01 0.00E-01 0.00E-01 2.109 08NI 63 3.49E 10 2.16E 09 1.21E 09 0.00E-01 0.00E-01 0.00E-01 1.07E 08

NI 65 4.39E 00 4.97E-01 2.26E-01 0.00E-01 0.00E-01 0.00E-01 3.78E 01CU 64 0.00E-01 1.86E 05 8.60E 04 0.00E-01 3.14E 05 0.00E-01 3.81E 06ZN 65 5.55E 09 1.90E 10 8.78E 09 0.00E-01 9.23E 09 0.00E-01 1.61E 10

ZN 69 5.04E-11 9.07E-11 6.75E-12 0.00E-01 3.77E-11 0.00E-01 7.40E-09BR 83 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01BR 84 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01

BR 85 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01"

RB 86 0.00E-01 2.23E 10 1.10E 10 0.00E-01 0.00E-01 0.00E-01 5.70E 08RB 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-01SR 89 1.26E 10 0.00E-01 3.61E 08 0.00E-01 0.00E-01 0.00E-01 2.59E 08SR 90 1.22E 11 0.00E-01 3.10E 10 0.00E-01 0.00E-01 0.00E-01 1.52E 09 l

iSR 91 2.69E 05 0.00E-01 9.75E 02 0.00E-01 0.00E-01 0.00E-01 3.19E'05 '

SR 92 4.66E 00 0.00E-01 1.73E-01 0.00E-01 0.00E-01 0.00E-01 5.02E 01Y 90 6.80E 02 0.00E-01 1.32E 01 0.00E-01 0.00E-01 0.00E-01 9.39E 05

Y 91M 5.72E-19 0.00E-01 1.95E-20 0.00E-01 0.00E-01 0.00E-01 1.91E-15Y 91 7.33E 04 0.00E-01 1.95E 03 0.00E-01 0.00E-01 0.00E-01 5.25E 06Y 92 5.39E-04 0.00E-01 1.51E-05 0.00E-01 0.00E-01 0.00E-01 1.03E 01 |

l

A-65

'.

. . . . , ,

. .. _ _ _

|

'mBLE A.5-9 (cont'd) -

Gq MREM /YR PER UCI/SIECOW-MILK PATHWAY FICIOR

MINFANI' (RI FICImS)

NUCLIDE BONE LIVER T BODY 11r/ROID KIDNEY IJJNG GT-ILI

Y 93 2.25E 00 0.00E-01 6.13E-02 0.00E-01 0.00E -01 0.00E-01 1.78E 04ZR 95 6.81E 03 1.66E 03 1.18E 03 0.00E-01 1.79E 03 0.00E-01 8.26E 05ZR 97 4.06E 00 6.98E-01 3.19E-01 0.00E-01 7.03E-01 0.00E-01 4.45E 04

NB 95 5.94E 05 2.45E 05 1.41E 05 0.00E-01 1.75E 05 0.00E-01 2.06E 08NO 99 0.00E-01 2.08E 08 4.06E 07 0.00E-01 3.11E 08 0.00E-01 6.85E 077C 99M 2.75E 01 5.68E 01 7.31E 02 0.00E-01 6.11E 02 2.97E 03 1.65E 04

7C 101 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01RU 103 8.67E 03 0.00E-01 2.90E 03 0.00E-01 1.80E 04 0.00E-01 1.05E 05RU 105 8.07E-03 0.00E-01 2.72E-03 0.00E-01 5.93E-02 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 06AG 110M 3.86E 08 2.82E 08 1.86E 08 0.00E-01 4.03E 08 0.00E-01 1.46E 10TE 125M 1.51E 08 5.04E 07 2.04E 07 5.07E 07 0.00E-01 0.00E-01 7.18E 07



TE 132 2.11E 07 1.05E 07 9.75E 06 1.54E 07 6.53E 07 0.00E-01 3.87E 07I 130 3.55E 06 7.81E 06 3.14E 06 8.76E 08 8.58E 06 0.00E-01 1.68E 06 1

1 131 2.72E 09 3.21E 09 1.41E 09 1.05E 12 3.74E 09 0.00E-01 1.14E 08'

I 132 1.43E 00 2.91E 00 1.04E 00 1.37E 02 3.25E 00 0.00E-01 2.36E 00I 133 3.63E 07 5.28B 07 1.55E 07 9.61E 09 6.21E 07 0.00E-01 8.94E 06 iI 134 1.77E-11 3. '33E-11 1.29E-11 8.47E-10 4.06E-11 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 04CS 134 3.65E 10 6.80E 10 6.87E 09 0.00E-01 1.75E 10 6.21E 09 1.85E 08 .

CS 136 1.96E 09 5.76E 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 G.55E 09 1.88E 08CS 138 8.50E-23 1.38E-22 6.70E-23 0.00E-01 6.89E-23 1.08E-23 2.21E-22BA 139 4.41E-07 2.93E-10 1.28E-08 0.00E-01 1.76E-10 1.77E-10 2.80E-05 l

A-66

.. .

|Il

l

'IBBM A.5-9 (carrt'd)

GRASj-CCW-MILK PA'IEWAY FACIORW MREM /YR PER UCI/S E

INFANI' (RI FACIORS)

NUCLIDE BCNE LIVER T BODY 'IHYROID KIDNEY Il3NG GI-ILI

BA 140 2.41E 08 2.41E 05 1.24E 07 0.00E-01 5.72E 04 1.48E 05 5.92E 07BA 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


CE 143 3 97E 02 2.63E 05 3.00E 01 0.00E-01 7.67E 01 0.00E-01 1.54E 06CE 144 2.33E 06 9.52E 05 1.30E 05 0.00E-01 3.85E 05 0.00E-01 1.33E 08PR 143 1.49E 03 5.56E 02 7.36E 01 0.00E-01 2.07E 02 0.00E-01 -7.84E 05


NP 239 3.65E 01 3.26E 00 1.84E 00 0.00E-01 1.50E 00 0.00E-01 9.43E 04

.

A-67

I

l

.)- _ _ _ . -

!

|

|1

B BLE A.5-10

Gq MREN/YR PER UCI/SEC )COR-MEAT PA'IENAY F1CIOR |

rADULT (RI F1CIORS)

!NUCLIDE BONE LIVER T BODY 'IEYROID KIDNEY LUNG GI-LLI !

H 3 0.00E-01 3.25E 02 3.25E 02 3.25E 02 3.25E 02 3.25E 02 3.25E 02 |C 14 2.41E 08 4.83E 07 4.83E 07 4.83E 07 4.83E 07 4.83E 07 4.83E 07 i

NA 24 1.36E-03 1.36E-03 1.36E-03 1.36E-03 1.36E-03 1.36E-03 1.36E-03'l

P 32 4.65E 09 2.89E 08 1.80E 08 0.00E-01 0.00E-01 0.00E-01 5.23E 08 ,

CR 51 0.00E-01 0.00E-01 7.05E 03 4.21E 03 1.55E 03 9.35E 03 1.77E 06 |'

MN 54 0.00E-01 9.18E 06 1.75E 06 0.00E-01 2.73E 06 0.00E-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 2.02E 08 4.72E 07 0.00E-01 0.00E-01 1.13E 08- 1.16E 08FE 59 2.65E 08 6.24E 08 2.39E 08 0.00E-01 0.00E-01 1.74E 08 2.08E 09

00 58 0.00E-01 1.82E 07 4.09E 07 0.00E-01 0.00E-01 0.00E-01 3.70E 08 )00 60 0.00E-01 7.52E 07 1.66E 08 0.00E-01 0.00E-01 0.00E-01 1.41E 09 :NI 63 1.89E 10 1.32E 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-01CU 64 0.00E-01 2.73E-07 1.28E-07 0.00E-01 6.89E-07 0.00E-01 2.33E-05

i

ZN 65 3.56E 08 1.13E 09 5.12E 08 0.00E-01 7.57E 08 0.00E-01 7.13E 08- .j|

ZN 69 0.00E-01 0.00E-01 0.00E -01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 |BR 83 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 iBR 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-01RB 86 0.00E-01 4.87E 08 2.27E 08 0.00E-01 0.00E-01 0.00E-01 9.61E 07RB 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-01SR 89 3.02E 08 0.00E-01 8.66E 06 0.00E-01 0.00E-01 0.00E-01 4.84E 07SR 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-10SR 92 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01Y 90 1.07E 02 0.00E-01 2.86E 00 0.00E-01 0.-00E-01 0.00E-01 1.13E 06

lY 91M 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 i

Y 91 1.13E 06 0.00E-01 3.03E 04 0.00E-01 0.00E-01 0.00E-01 6.23E 08Y 92 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 !

!

A-68

-- . _ . .

TABLE A.5-10 (Otmt'd)

GRASg-COW-MEAT PA'IB4AY FACITM~ MREM /YR PER UCI/SEC

ADULT (RI FICIGS)

_N_UCLIDE BONE LIVER T BODY 'IRYROID KIDNEY IDG GI-ILI

Y 93 6.59E-12 0.00E-01 1.82E-13 0.00E-01 0.00E-01 0.00E-01 2.09E-07ZR 95 1.87E 06 6.01E 05 4.07E 05 0.00E-01 9.43E 05 0.00E-01 1.90E 09ZR 97 2.08E-05 4.19E-06 1.92E-06 0.00E-01 6.33E-06 0.00E-01 1.30E 00

NB 95 2.30E 06 1.28E 06 6.88E 05 0.00E-01 1.26E 06 0.00E-01 7.76E 09ND 99 0.00E-01 9.99E 04 1.90E 04 0.00E-01 2.26E 05 0.00E-01 2.32E 05'IC 99M 4.50E-21 1.27E-20 1.62E-19 0.00E-01 1 93E-19 6.23E-21 7.53E-18'.

'IC 101 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01. 0.00E-01RU 103 1.05E 08 0.00E-01 4.53E 07 0.00E-01 4.01E 08 0.00E-01 1.23E 10RU 105 5.87E-28 G.00E-01 2.32E-28 0.00E-01 7.58E-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 11AG 110M 6.68E 06 6.18E 06 3.67E 06 0.00E-01 1.22E 07 0.00E-01 2.52E 09TE 125M 3.59E 08 1.30E 08 4.81E 07 1.08E 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 09TE 127 2.14E-10 7.68E-11 4.63E-11 1.58E-10 8.71E-10 0.00E-01 '1.69E-08TE 129M 1.13E 09 4.23E 08 1.80E 08 3.90E 08 4.73E 09 0.00E-01 5.71E 09

TE 129 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01-TE 131M 4.52E 02 2.21E 02 1.84E 02 3.50E 02 2.24E 03 0.00E-01 2.20E 04TE 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 8.63E 05 1.01E 06 8.85E 06 0.00E-01 4.35E 07I 130 2.12E-06 6.26E-06 2.47E-06 5.30E-04 9.76E-06 0.00E-01- 5.39E-06I 131 1.07E 07 1.54E 07 8.81E 06 5.04R 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-01I 133 3.67E-01 6.38E-0) 1.94E-01 9.37E 01 1.11E 00 0.00E-01 5.73E-01I 134 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01

I 135 4.47E-17 1.17E-16 4.32E-17 7.73E-15 1.88E-16 0.00E-01 1.32E-16CS 134 6.58E 08 1.56E 09 1.28E 09 0.00E-01 5.06E 08 1.68E 08 2.74E 07CS 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 ').00E-01 0.00E-01 0.00E-01

A-69

. - .- = .

!

|l

TAB 2 A.5-10 (Cbnt'd)

%"-COW-MEAT PATHWAY F1CIUt j

M MREN/YR PER UCI/SEC !

ADULT (RI F1CICRS) |

NUCIJDE BONE LIVER T BODY THYROID KIDNEY IDG GI-LLI

BA 140 2.87E 07 3.61E 04 1.88E 06 0.00E-01 1.23E 04 2.07E 04 5.92E 07In 141 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01Im 142 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01

LA 140 3.76E-02 1.89E-02 5.00E-03 0.00E-01 0.00E-01 0.00E-01 1.39E 03LA 142 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01CE 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 02CE 144 1.46E 06 6.09E 05 9.83E 04 0.00E-01 3.61E 05 0.00E-01 4.93E 08PR 143 2.10E 04 8.41E 03 1.04E 03 0.00E-01 4.86E 03 0.00E-01 9.19E 07

PR 144 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01ND 147 7.17E 03 8.29E 03 4.96E 02 0.00E-01 4.84E 03 'O.00E-01 3.98E 07W 187 '2.17E-02 1.81E-02 6.33E-03 0.00E-01 0.00E-01 0.00E-01 5.93E 00

,

NP 239 2.59E-01 2.55E-02 1.40E-02 0.00E-01 7.94E-02 0.00E-01- 5.22E 03

A-70

-

|

TABLE A.5-11

GRAS -CON-MEAT PATfDRY F1CIORJM MRDf/YR PER TI/SE

TEEN (RI F1CIORS)

NUCLIDE BONE LIVER T BODY 'IHYROID KIDNEY IRC GI-ILI

H 3 0.00E-01 1.94E 02 1.94E 02 1.94E 02 1.94E 02 1.94E 02 1.94E 02C 14 2.04E 08 4.08E 07 4.08E 07 4.08E 07 4.08E 07 4.08E 07 4.08E 07NA 24 1.09E-03 1.09E-03 1.09E-03 1.09E-03 1.09E-03 1.09E-03 1.09E-03


Fm 56 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01FE 55 2.38E 08 1.69E 08 3.93E 07 0.00E-01 0.00E-01 1.07E 08 7.30E 07FE 59 2.12E 08 4.95E 08 1.01E 08 0.00E-01 0.00E-01 1.56E 08 1.17E 09

00 58 0.00E-01 1.41E 07 3.24E 07 0.00E-01 0.00E-01 0.00E-01 1.94E 0800 60 0.00E-01 5.83E 07 1.31E 08 0.00E-01 0.00E-01 0.00E-01 7.60E 08NI 63 1.52E 10 1.07E 09 5.15E 08 0.00E-01 0.00E-01 0.00E-01 1.71E 08

NI 65 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01CU 64 0.00E-01 2.23E-07 1.05E-07 0.00E-01 5.64E-07 0.00E-01 1.73E-05ZN 65 2.50E 08 8.69E 08 4.05E 08 0.00E-01 5.56E 08 0.00E-01 3.68E 08

KN 69 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01BR 83 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01BR 84 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 0.006-01 0.00E-01 3.03E 07SR 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-10SR 92 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01Y 90 8.98E 01 0.00E-01 2.42E 00 0.00E-01 0.00E-01 0.00E-01 7.41E 05


A-71

.

. - .

'mBLE A.5-11 (Otmt'd)

GRASg-COR-MEAT PAENAY F1CIORM MREM /YR PER UCI/SEC

TEEN (RI F1CIORS)

NUCLIDE EONE LIVER T BODY 'IHYROID KIDNEY TJJPG GI-ILI

Y 93 5.56E-12 0.00E-01 1.53E-13 0.00E-01 0.00E-01 0.00E-01 1.70E-07ZR 95 1.50E 06 4.73E 05 3.26E 05 0.00E-01 6.96E 05 0.00E-01 1.09E 09-ZR 97 1.73E-05 3.42E-06 1.58E-06 0.00E-01 5.19E-06 0.00E-01 9.27E-01

NB 95 1.80E 06 9.96E 05 5.48E 05 0.00E-01 9.66E 05 0.00E-01. 4.26E 09-MD 99 0.00E-01 8.26E 04 1.58E 04 0.00E-01 1.89E 05 0.00E-01 1.48E 05-'IC 99M 3.58E-21 9.97E-21 1.29E-19 0.00E-01 1.49E-19 5.54E-21 6.55E-18

'IC 101 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01RU 103 8.56E 07 0.00E-01 3.66E 07 0.00E-01 3.02E 08 0.00E-01 7.15E 09'RU 105 4.91E-28 0.00E-01 1.91E-28 0.00E-01 6.91E-27 0.00E-01 3.96E-25

RU 106 2.36E 09 0.00E-01 2.97E 08 0.00E-01 4.55E 09 0.00E-01 1.13E 11IG 110M 5.06E 06 4.79E 06 2.91E 06 0.00E-01 9.13E 06 0.00E-01 1.35E 09_TE 125M 3.03E 08 1.09E 08 4.05E 07 8.47E 07 0.00E-01 0.00E-01 8.94E 08

TE 127M 9.42E 08 3.34E 08 1.12E 08 2.24E 08 3.82E 09 0.00E-01 .2.35E 09TE 127 1.81E-10 6.43E-11 3.91E-11 1.25E-10 7.35E-10 0.00E-01 1.40E-08TE 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-01TE 131M 3.77E 02 1.81E 02 1.51E 02 2.72E 02 1.88E 03 0.00E-01 1.45E 04TE 131 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01

TE 132 1.16E 06 7.36E 05 6.93E 05 7.76E 05 7.06E 06 0.00E-01 2.33E 07I 130 1.71E-06 4.94E-06 1.97E-06 4.03E-04 7.61E-06 0.00E-01 3.80E-06I 131 8.93E 06 1.25E 07 6.72E 06 3.d5E 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-01I 133 3.07E-01 5.20E-01 1.59E-01 7.26E 01 9.12E-01 0.00E-01 3.93E-01I 134 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01

1 135 3.64E-17 9.37E-17 3.47E-17 6.03E-15 1.40E-16 0.00E-01 1.04E-16CS 134 5.23E 08 1.23E 09 5.71E 08 0.00E-01 3.91E 08 1.49E 08 1.53E 07CS 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 07CS 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 'O.00E-01

A-72 I

. - -

TMER A.5-11 (Cant'd)

GRASg-CON-MEAT PAMiWAY F1CIORM MRDUYR PER UCI/SEC

TEE:N (RI F1CIORS)

NUCLIDE BCNE LIVER T DODY U1YROID KIDNEY ION 3 GI-ILI

m 140 2.38E 07 2.91E 04 1.53E 06 0.00E-01 9.88E 03 1.96E 04 3.67E 07m 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

1A 140 3.09E-02 1.52E-02 4.04E-03 0.00E-01 0.00E-01 0.00E-01 8.72E 02IA 142 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01CE 141 1.18E 04 7.88E 03 9.05E 02 0.00E-01 3.71E 03 0.00E-01 2.25E 07

CE 143 1.69E-02 1.23E 01 1.38E-03 0.00E-01 5.53E-03 0.00E-01 3.70E 02-CE 144 1.23E 06 5.08E 05 6.60E 04 0.00E-01 3.04E 05 0.00E-01 3.09E 08PR 143 1.77E 04 7.05E 03 8.78E 02 0.00E-01 4.10E 03 0.00E-01 5.81E 07

PR 144 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01ND 147 6.32E 03 6.87E 03 4.11E 02 0.00E-01 4.03E 03 0.00E-01 '2.48E 07W 187 1.81E-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

)

|

||

!

A-73,

1

|

|,

1

_. _.

TAB m A.5-12

GRASg-00N-MEAT PA'IIMAY FACIORM MREM /YR PER UCI/SEC )

CHIID (RI FACIORS)

NUCLIDE BONE LIVER T BODY 'IHYROID KIDtEY IAN3 GI-ILI

H 3 0.00E-01 2.34E 02 2.34E 02 2.34E 02 2.34E 02 2.34E 02 2.34E 02 |

C 14 3.83E 08 7.67E 07 7.67E 07 7.67E 07 7.67E 07 7.67E 07 7.67E 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 7.41E 09 3.47E 08 2.86E 08 0.00E-01 0.00E-01 0.00E-01 2.05E 08 iCR 51 0.00E-01 0.00E-01 8.79E 03 4.88E 03 1.33E 03 8.91E 03 4.66E 05 iMN 54 0.00E-01 8.01E 06 2.13E 06 0.00E-01 2.25E 06 0.00E-01 6.72E 06 |

MN 56 0.00E-01 1.63E-53 3.67E-54 0.00E-01 1.97E-53 0.00E-01 2.36E-51|'FE 55 4.57E 08 2.42E 08 7.50E 07 0.00E-01 0.00E-01 1.37E 08 4.49E 07 )FE 59 3.76E 08 6.09E 08 3.03E 08 0.00E-01 0.00E-01 1.76E 08 6.34E 08 !

l'

00 58 0.00E-01 1.64E 07 5.03E 07 0.00E-01 0.00E-01 0.00E-01 9.58E 0700 60 0.00E-01 6.93E 07 2.04E 08 0.00E-01 0.00E-01 0.00E-01 3.84E 08 i

NT 63 2.91E 10 1.56E 09 9.91E 08 0.00E-01 0.00E-01 0.00E-01 1.05E 08

NI 65 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 _lCU 64 0.00E-01 3.00E-07 1.81E-07 0.00E-01 7.24E-07 0.00E-01 1.41E-05 l

ZN 65 3.75E 08 1.00E 09 6.22E 08 0.00E-01 6.30E 08 0.00E-01 1.76E 08

ZN 69 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 -IBR 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 |

BR 85 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01RB 86 0.00E-01 5.77E 08 3.55E 08 0.00E-01 0.00E-01 0.00E-01 3.71E 07. aRB 88 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 '


SR 91 2.24E-10 0.00E-01 8.45E-12 0.00E-01 0.00E-01 0.00E-01 4.94E-10SR 92 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01Y 90 1.70E 02 0.00E-01 4.55E 00 0.00E-01 0.00E-01 0.00E-01 4.84E 05

Y 91M 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 )Y 91 1.80E 06 0.00E-01 4.82E 04 0.00E-01 0.00E-01 0.00E-01 2.40E 08 |Y 92 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01

A-749/93

TABLE A.5-12 (&rtt'd)

GRASj-CON-MEATPAniWAYF1CIORM MREM /YR PER UCI/SK'

CHILD (RI FAC'IORS)

NUCLIDE DONE LIVER T BODY MEROID KIDNEY IENG GT-LLI

Y 93 1.04E-11 0.00E-01 2.87E-13 0.00E-01 0.00E-01 0.00E-01 1.56E-07ZR 95 2.66E 06 5.86E 05 5.21E 05 0.00E-01 8.38E 05 0.00E-01 6.11E 08ZR 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 09MD 99 0.00E-01 1.15E 05 2.84E 04 0.00E-01 2.45E 05 0.00E-01 9.51E 04TC 99M 6.27E-21 1.23E-20 2.04E-19 0.00E-01 1.79E-19 6.24E-2] 7.00E-18

TC 101 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01RU 103 1.55E 08 0.00E-01 5.95E 07 0.00E-01 3.90E 08 0.00E-01 4.00E 09RU 105 9.16E-28 0.00E-01 3.32E-28 0.00E-01 8.05E-27 0.00E-01 5.98E-25

RU 106 4.44E 09 0.00E-01 5.54E 08 0.00E-01 5.99E 09 0.00E-01 6.90E 10IG 110M 8.34E 06 5.67E 06 4.53E 06 0.00E-01 1.06E 07 0.00E-01 6.74E 08TE 125M 5.69E 08 1.54E 08 7.59E 07 1.60E 08 0.00E-01 0.00E-01 5.49E 08

TE 127M 1.77E 09 4.78E 08 2.11E 08 4.24E 08 5.06E 09 0.00E-01 1.44E 09TE 127 3.41E-10 9.20E-11 7.32E-11 2.36E-10 9.71E-10 0.00E-01 1.33E-08TE 129M 1.79E 09 5.00E 08 2.78E 08 5.77E 08 5.26E 09 0.00E-01 2.18E 09 |

TE 129 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01TE 131M 7.01E 02 2.43E 02 2.58E 02 4.99E 02 2.35E 03 0.00E-01 9.84E 03TE 131 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 1

TE 132 2.12E 06 9.39E 05 1.13E 06 1.37E 06 8.72E 06 0.00E-01 9.46E 06I 130 3.05E-06 6.17E-06 3.18E-06 6.80E-04 9.22E-06 0.00E-01 2.89E-06I 131 1.66E 07 1.67E 07 9.47E 06 5.51E 09 2.74E 07 0.0CE-01 1.48E 06

I

I 132 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01I 133 5.70E-01 7.04E-01 2.66E-01 1.31E 02 1.17E 00 0.00E-01 2.84E-01I 134 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01

I 135 6.59E-17 1 19E-16 5. LYE-17 1.05E-14 1.82E-16 0.00E-01 9.04E-17CS 134 9.22E 08 1.51E 09 3.19E 08 0.00E-01 4.69E 08 1.68E 08 8.16E 06CS 136 1.59E 07 4.36E 07 2.82E 07 0.00E-01 2.32E 07 3.46E 06 1.53E 06


A-759/93

__ _

s

TABM A.5-12 (Corit'd)

GRAB'g-CON-MEAT PA'1HRY F1CIORM MRF2f/YR PER LCI/SEC

CHIID (RI F1CIORS)

NUCLIDE BONE LIVER T BODY 'nlYROID KIDNEY IRG GI-ILI


IA 140 5.66E-02 1.98E-02 6.66E-03 0.00E-01 0.00E-01 0.00E-01 5.51E 02 |IA 142 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01- 0.00E-01 0.00E-01CE 141 2.22E 04 1.11E 04 1.64E 03 0.00E-01 4.86E 03 0.00E-01 1.38E 07

CE 143 3.18E-02 1.72E 01 2.50E-03 0.00E-01 7.23E-03 0.00E-01 2.52E 02CE 144 2.32E 06 7.26E 05 1.24E 05 0.00E-01 4.02E 05 0.00E-01 1.89E 08PR 143 3.34E 04 1.00E 04 1.66E 03 0.00E-01 5.43E 03 0.00E-01 3.60E 07

PR 144 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01-ND 147 1.19E 04 9.60E 03 7.43E 02 0.00E-01 5.27E 03 0.00E-01 1.52E 07W 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 |

:

.

I

|

A-769/93

. . - _ . _

|

|,

||

'mB2 A.5-13

VDgEIATION PA'1HWAY F1CIORM MRD1/YR PER UCI/SEC

i

ADULT (RI F1CIORS) |NUCLIDE BONE LIVER T DODY 'IHYROID KIDNEY IRC GI-ILI

H 3 0.00E-01 2.26E 03 2.26E 03 2.26E 03 2.26E 03 2.26E 03 2.26E 03C 14 2.38E 08 4.55E 07 4.55E 07 4.55E 07. 4.55E 07 4.55E 07 4.55E 07NA 24 2.69E 05 2.69E 05 2.69E 05 2.69E 05 2.69E 05 2.69E 05 2.69E 03

P 32 1.40E 09 8.73E 07 5.42E 07 0.00E-01 0.00E-01 0.00E-01 1.58E 08CR 51 0.00E-01 0.00E-01 4.64E 04 2.78E 04 1.02E 04 6.16E 04 1.17E.07MN 54 0.00E-01 3.13E 08 5.97E 07 0.00E-01 9.31E 07 0.00E-01 9.58E 08




ZN 69 8.77E-06 1.68E-05 1.17E-06 0.00E-01 1.09E-05 0.00E-01 2.52E-06BR 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-01RB 86 0.00E-01 2.]9E 08 1.02E 08 0.00E-01 0.00E-01 0.00E-01 4.33E 07RB 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 1.41E-26 9.88E-27 0.00E-01 0.00E-01 0.00E-01 0.00E-01SR 89 9.97E 09 0.00E-01 2.86E 08 0.00E-01 0.00E-01 0.00E-01 1.60E 09SR 90 6.05E 11 0.00E-01 1.48E 11 0.00E-01 0.00E-01 0.00E-01 1.75E 10 )

|SR 91 3.03E 05 0.00E-01 1.22E 04 0.00E-01 0.00E-01 0.00E-01 1.44E 06. 1

SR 92 4.27E 02 0.00E-01 1.85E 01 0.00E-01 0.00E-01 0.00E-01 8.46E 03Y 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-08Y 91 5.11E 06 0.00E-01 1.37E 05 0.00E-01 0.00E-01 0.00E-01 2.81E 09Y 92 9.16E-01 0.00E-01 2.68E-02 0.00E-01 0.00E-01 0.00E-01 1.60E 04 j

A-77

Y.

l'

__ _ _

TAB 2 A.5-13 (cont'd)

VIgETATICN PA'IEWAY FAC'KRM~ MRDUYR PER UCI/SEC |

ADULT (RI FACIORS) l!

NUCLIDE BONE LIVER T BODY 'IHYROID KIDNEY IDG GI-ILI

Y 93 1.74E 02 0.00E-01 4.81E 00 0.00E-01 0.00E-01 0.00E-01 5.52E 06ZR 95 1.18E 06 3.77E 05 2.55E 05 0.00E-01 5.92E 05 0.00E-01 1.20E 09ER 97 3.37E 02 6.81E 01 3.11E 01 0.00E-01 1.03E 02 0.00E-01 2.11E 07

NB 95 1.43E 05' 7.93E 04 4.26E 04 0.00E-01 7.84E 04 0.00E-01 4.81E 0810 99 0.00E-01 6.15E 06 1.17E 06 0.00E-01 1.39E 07 0.00E-01 1.43E 077C 99M 3.10E 00 8.77E 00 1.12E 02 0.00E-01 1.33E 02 4.30E 00 5.19E 03

TC 101 8.34E-31 1.20E-30 1.18E-29 0.00E-01 2.16E-29 6.14E-31 0.00E-01RU 103 4.76E 06 0.00E-01 2.05E 06 0.00E-01 1.82E 07 0.00E-01 5.56E 08RU 105 5.39E 01 0.00E-01 2.13E 01 0.00E-01 6.97E 02 0.00E-01 3.30E 04

RU 106 1.93E 08 0.00E-01 2.44E 07 0.00E-01 3.72E 08 0.00E-01 1.25E 10AG 110M 1.05E 07 9.75E 06 5.79E 06 0.00E-01 1.92E 07 0.00E-01 3.98E 09TE 125M 9.66E 07 3.50E 07 1.29E 07 2.90E 07 3.93E 08 0.00E-01 3.86E 08

TE 127H 3.49E 08 1.2SE 08 4.26E 07 8.93E 07 1.42E 09 0.00E-01 1.17E 09'TE 127 5.66E 03 2.03E 03 1.23E 03 4.20E 03 2.31E 04 0.00E-01 4.47E 05TE 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-04TE 13DH 9.12E 05 4.46E 05 3.72E 05 7.07E 05 4.52E 06 0.00E-01 4.43E 07TE 131 1.51E-15 6.32E-16 4.78E-16 1.24E-15 6.63E-15 0.00E-01 2.14E-16


I 132 5.77E 01 1.54E 02 5.40E 01 5.40E 03 2.46E 02 0.00E-01 2.90E 01I 133 2.09E 06 3.63E 06 1.11E 06 5.33E 08 6.33E 06 0.00E-01 3.26E 06I 134 9.69E-05 2.63E-04 9.42E-05 4.56E-03 4.19E-04 0.00E-01 2.30E-07


CS 137 6.36E 09 8.70E 09 5.70E 09 0.00E-01 2.95E 09 9.81E 08 1.68E 08 -CS- 138 3.94E-11 7.78E-11 3.86E-11 0.00E-01 5.72E-11 5.65E-12 3.32E-16-BA 139 2.90E-02 2.07E-05 8.50E-04 0.00E-01 1.93E-05 1.17E-05 5.15E-02

A-78

1

|

li

TMILE A.5-13 (Cont'd)

WCN PRIHMY F1CITR |

M'' MREM /YR PER ICI/SEC l

ADULT (RI F1CIORS)

NUCLIDE BONE LIVER T BODY 'IYiYROID KIDtEY IUNG GI-ILI

BA 140 1.29E 08 1.61E 05 8.42E 06 0.00E-01 5.49E 04 9.25E 04 2.65E 08BA 141 1.28E-21 9.64E-25 4.31E-23 0.00E-01 8.96E-25 5.47E-25 6.01E-31'PA 142 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01



PR 144 3.13E-26 1.30E-26 1.59E-27 0.00E-01 7.32E-27 0.00E-01 0.00E-01ND 147 3.36E 04 3.89E 04 2.32E 03 0.00E-01 2.27E 04 0.00E-01 1.87E 08.W 187 3.82E 04 3.20E 04 1.12E 04 0.00E-01 0.00E-01 0.00E-01 1.05E 07

NP 239 1.43E 03 1.40E 02 7.74E 01 0.00E-01 4.38E 02 0.00E-01 2.88E 07

|

!

A-79

-

"mBIE A.5-14

TATICN PATI 5&Y FACKR'

MREM /YR PER UCI/SEC.,

TEEN (RI FAC'KRS)

NtIIIDE BONE LIVER T BODY THYROID KIDNEY IDNG GI-ILI

H 3 0.00E-01 2.59E 03 2.59E 03 2.59E 03 2.59E 03 2.59E 03 2.59E 03C 14 3.69E 08 7.38E 07 7.38E 07 7.38E 07 7.38E 07 7.38E 07 7.38E 07NA 24 2.39E 05 2.39E 05 2.39E 05 2.39E 05 2.39E 05 2.39E 05 2.39E 05 i

P 32 1.61E 09 9.96E 07 6.23E 07 0.00E-01 0.00E-01 0.00E-01 1.35E 08CR 51 0.00E-01 0.00E-01 6.17E 04 3.43E 04 1.35E 04 8.81E 04 1.04E 07MN 54 0.00E-01 4.54E 08 9.01E 07 0.00E-01 1.36E 08 0.00E-01- 9.32E 08


00 58 0.00E-01 4.36E 07 1.01E 08 0.00E-01 0.00E-01 0.00E-01 6.01E 0800 60 0.00E-01 2.49E 08 5.60E 08 0.00E-01 0.00E-01 0.00E-01 3.24E 09NI 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 02CU 64 0.00E-01 8.34E 03 3.92E 03 0.00E-01 2.11E 04 0.00E-01 6.47E 05EN 65 4.24E 08 1.47E 09 6.86E 08 0.00E-01 9.42E 08 0.00E-01 6.23E 08

ZN 69 8.21E-06 1.56E 05 1.10E-06 0.00E-01 1.02E-05 0.00E-01 2.88E-05BR 83 0.00E-01 0.00E-01 2.92E 00 0.00E-01 0.00E-01 0.00E-01 5.08E-17BR 84 0.00E-01 0.00E-01 2.27E-11 0.00E-01 0.00E-01 0.00E-01 3.14E-28



SR 91 2.83E 05 0.00E-01 1.13E 04 0.00E-01 0.00E-01 0.00E-01 1.28E 06SR 92 3.98E 02 0.00E-01 1.70E 01 0.00E-01 0.00E-01 0.00E-01 1.01E 04Y 90 1.24E 04 0.00E-01 3.34E 02 0.00E-01 0.00E-01 0.00E-01 1.02E 08

Y 91M 4.88E-09 0.00E-01 1.87E-10 0.00E-01 0.00E-01 0.00E-01 2.30E-07Y 91 7.84E 06 0.00E-01 2.10E 05 0.00E-01 0.00E-01 0.00E-01 3.21E 09Y 92 8.61E-01 0.00E-01 2.49E-02 0.00E-01 0.00E-01 0.00E-01 2.36E 04

,

A-80

!1

i

'mBIE A.5-14 (Cant'd)

VIgEIATIO1 PATIMAY FACIORM MREM /YR PER UCI/SEC

TEEN (RI FACITS)

NUCLIDE BONE LIVER T BODY 'IHYROID KIDNEY IDE GI-ILI

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 3.74E 05 0.00E-01 7.99E 05 0.00E-01 1.25E 09ZR 97 3.12E 02 6.18E 01 2.85E 01 0.00E-01 9.37E 01 0.00E-01 1.67E 07-

NB 95 1.93E 05 1.07E 05 5.88E 04 0.00E-01 1.04E 05 0.00E-01 4.57E 08-MD 99 0.00E-01 5.65E 06 1.08E 06 0.00E-01 1.29E 07 0.00E-01 1.01E 07TC 99M 2.74E 00 7.64E 00 9.90E 01 0.00E-01 1.14E 02 4.24E 00 5.02E 03

TC 101 7.76E-31 1.10E-30 1.08E-29 0.00E-01 2.00E-29 6.72E-31 0.00E-01RU 103 6.81E 06 0.00E-01 2.91E 06 0.00E-01 2.40E 07 0.00E-01 5.69E 08RU 105 5.01E 01 0.00E-01 1.94E 01 0.00E-01 6.32E 02 0.00E-01 4.04E 04


TE 127H 5.52E 08 1.96E 08 6.56E 07 1.31E 08 2.24E 09 0.00E-01 1.37E 09TE 127 5.34E 03 1.89E 03 1.15E 03 3.68E 03 2.16E 04 0.00E-01 4.12E 05TE 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-03TE 131M 8.44E 05 4.05E 05 3.38E 05 6.09E 05 4.22E 06 0.00E-01 3.25E 077E 131 1.41E-15 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 07I 130 3.51E 05 1.02E 06 4.05E 05 8.28E 07 1.56E 06 0.00E-01 7.80E 05 >

I 131 7.69E 07 1.08E 08 5.78E 07 3.14E 10 1.85E 08 0.00E-01 2.13E 07

I 132 5.20E 01 1.36E 02 4.89E 01 4.59E 03 2.14E 02 0.00E-01 5.93E 01I 133 1.94E 06 3.29E 06 1.00E 06 4.59E 08 5.77E 06 0.00E-01 2.49E 06I 134 8.76E-05 2.32E-04 8.34E-05 3.87E-03 3.66E-04 0.00E-01 3.06E-06-

I 135 3.52E 04 9.07E 04 3.36E 04 5.84E 06 1.43E 05 0.00E-01 1.01E 05 |CS 134 7.10E 09 1.67E 10 7.75E 09 0.00E-01 5.31E 09 2.03E 09 2.08E 08CS 136 4.28E 07 1.68E 08 1.13E 08 0.00E-01 9.16E 07 -1.44E 07 1.35E 07 i

!CS 137 1.01E 10 1.35E 10 4.69E 09 0.00E-01 4.59E 09 1.78E 09 1.92E 08 )CS 138 3.64E-11 6.98E-11 3.49E-11 0.00E-01 5.15E-11 6.00E-12 3.17E-14- '

BA 139 2.73E-02 1.92E-05 7.96E-04 0.00E-01 1.81E-05 1.32E-05 2. 44 E-01 -

1A-81

!

I

I

Il

- ..

TABM A.5-14 (corrt'd)

@MRD4/YR PER UCI/SEC'ICN PA'IHWAY F1CIOR

M-TEEN (RI F1CitRS)

NtK'LIDE BONE LIVER T BODY 'DEROID KIDNEY IRG GI-LLI


IA 140 1.81E 03 8.89E 02 2.37E 02 0.00E-01 0.00E-01 0.00E-01 5.11E 07'IA 142 1.30E-04 5.78E-05 1.44E-05 0.00E-01 0.00E-01 0.00E-01 1.76E 00CE 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 07CE 144 5.27E 07 2.18E 07 2.83E 06 0.00E-01 1.30E 07 0.00E-01 1.330 10PR 143 7.01E 04 2.80E 04 3.49E 03 0.00E-01 1.63E 04 0.00E-01 2.31E 28


NP 239 1.39E 02 1.31E 02 7.26E 01 0.00E-01 4.10E 02 0.00E-01 2.10E 07

A-82

.

.]

TEM A.5-15

pCN PA'11MAY F1CIORM MREM /YR PER UCI/SEC

CHILD (RI FICIORS)

NUCLIDE BONE LIVER T BODY 'IHYROID KIDNEY IRC GI-LLI


P 32 3.37E 09 1.58E 08 1.30E 08 0.00E-01 0.00E-01 0.00E-01 9.30E 07 |CR 51 0.00E-01 0.00E-01 1.17E 05 6.50E 04 1.78E 04 1.19E 05 6.21E 06MN 54 0.00E-01 6.65E 08 1.77E 08 0.00E-01 1.86E 08 0.00E-01 5.58E 08

,


00 58 0.00E-01 6.44E 07 1.97E 08 0.00E-01 0.00E-01 0.00E-01 3.76E 08C) 60 0.00E-01 3.78E 08 1.12E 09 0.00E-01 0.00E-01 0.00E-01 2.10E 09NI 63 3.95E 10 2.11E 09 1.34E 09 0.00E-01 0.00E-01 0.00E-01 1.42E 08

NI 65 1.18E 02 1.11E 01 6.51E 00 0.00E-01 0.00E-01 0.00E-01 1.37E 03CU 64 0.00E-01 1.10E 04 6.65E 03 0.00E-01 2.66E 04 0.00E-01 5.16E 05-ZN 65 8.12E 08 2.16E 09 1.35E 09 0.00E-01 1.36E 09 0.00E-01 3.80E 08

ZN 69 1.51E-05 2.19E-05 2.02E-06 0.00E-01 1.33E-05 0.00E-01 1.38E-03BR 83 0.00E-01 0.00E-01 5.38E 00 0.00E-01 0.00E-01 0.00E-01 3.143-17BR 84 0.00E-01 0.00E-01 3.85E-11 0.00E-01 0.00E-01 0.00E-01 1.94E-28


RB 89 0.00E-01 1.67E-26 1.48E-26 0.00E-01 0.00E-01- 0.00E-01 1.45E-28SR 89 3.60E 10 0.003-01 1.03E 09 0.00E-01 0.00E-01 0.00E-01 1.39E 09SR 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 06SR 92 7.29E 02 0.00E-01 2.92E 01 0.00E-01- 0.00E-01 0.00E-01 1.38E 04Y 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-05Y 91 1.86E 07 0.00E-01 4.99E 03 0.00E-01 0.00E-01 0.00E-01 2.48E 09

,

Y 92 1.59E 00 0.00E-01 4.54E-02 0.00E-01 0.00E-01 0.00E-01 4.58E 04 '

A-839/93

;

.

. _ . -- -

TABLE A.5-15 (Ckmt'd)

VEGETATION PA'HMLY FAC'IORr MRIN/YR PER UCI/SEC

CHIID (RI FACIORS)

1RX'LIDE BONE LIVER T BODY 'IHYROID KIDNEY IJJtG GI-ILI

Y 93 3.01E 02 0.00E-01 8.26E 00 0.00E-01 0.00E-01 0.00E-01 4.48E 06ZR 95 3.86E 06 8.49E 05 7.56E 05 0.00E-01 1.22E 06 0.00E-01 8.85E 08_ZR 97 5.70E 02 8.24E 01 4.86E 01 0.00E-01 1.18E 02 0.00E-01 1.25E 07

1B 95 4.11E 05 1.60E 05 1.14E 05 0.00E-01 1.50E 05 0.00E-01 2.96E 08HD 99 0.00E-01 7.71E 06 1.91E 06 0.00E-01 1.65E 07 0.00E-01 6.38E 06'IC 99M 4.71E 00 9.24E 00 1.51E 02 0.00E-01 1.34E 02 4.69E 00 5.26E 03 |

'IC 101 1.43E-30 1.49E-30 1.89E-29 0.00E-01 2.55E-29 7.90E-31 4.75E-30RU 103 1.53E 07 0.00E-01 5.88E 06 0.00E-01 3.85E 07 0.00E-01 3.96E 08RU 105 9.17E 01 0.00E-01 3.33E 01 0.00E-01 8.06E 02 0.00E-01 5.99E 04

RU- 106 7.45E 08 0.00E-01 9.30E 07 0.00E-01 1.01E 09 0.00E-01 1.16E 10IG 110M 3.21E 07 2.17E 07 1.73E 07 0.00E-01 4.04E 07 0.00E-01- 2.58E 09TE 125M 3.51E 08 9.50E 07 4.67E 07 9.84E 07 0.00E-01 0.00E-01 3.38E 08

TE 127M 1.32E 09 3.56E 08 1.57E 08 3.16E 08 3.77E 09 0.00E-01 1.07E 09TE 127 9.85E 03 2.66E 03 2.11E 03 6.82E 03 2.80E 04 0.00E-01 3.85E 05TE 129M 8.41E 08 2.35E 08 1.30E 08 2.71E 08 2.47E 09 0.00E-01 1.03E 09 |

TE 129 1.33E-03 3.70E-04 3.15E-04 9.46E-04 3.88E-03 0.00E-01 8.25E-02TE 131M 1.54E 06 5.33E 05' 5.68E 05 1.10E 06 5.16E 06 0.00E-01 2.16E 07TE 131 2.59E-15 7.90E-16 7.71E-16 1.98E-15 7.84E-15 0.00E-01 1.'36E-14 -



I 135 6.26E 04 1.13E 05 5.33E 04 9.98E 06 1.73E 05 0.00E-01 8.59E 04CS 134 1.60E 10- 2.63E 10 5.55E 09 0.00E-01 8.15E 09 2.93E 09 1.42E 08CS 136 8.04E 07 2.21E 08 1.43E 08 0.00E-01 1.18E 08 1.76E 07 7.77E 06

CS 137 2.39E 10 2.29E 10 3.38E 09 0.00E-01 7.46E 09 2.68E 09 1.43E 08CS 138 6.61E-11 9.20E-11 5.83E-11 0.00E-01 6.47E-11 6.96E-12 4.24E-11BA 139 5.04E-02 2.69E-05 1.46E-03 0.00E-01 2.35E-05 1.58E-05 2.91E 00

A-849/93

TABLE A.5-15 (Cont'd)

VEg= EI'ATIOf PAH1WAY F1CICRM MREM /YR PER UCI/SEC

CHIID (RI F1CIGS)

NUCEJDE BONE LIVER T BODY DIYHOID KIDNEY IIRE GI-ILI

BA 140 2.77E 08 2.43E 05 1.62E 07 0.00E-01 7.90E 04 1.45E 05 1.40E 08BA 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

IA 140 3.25E 03 1.14E 03 3.83E 02 0.00E-01 0.00E-01 0.00E-01 3.17E 07IA 142 2.36E-04 7.51E-05 2.35E-05 0.00E-01 0.00E-01 0.00E-01 1.49E 01CE 141 6.56E 05 3.27E 05 4.86E 04 0.00E-01 1.43E 05 0.00E-01 4.08E 08-



NP 239 2.56E 03 1.84E 02 1.29E 02 0.00E-01 5.31E 02 0.00E-01 1.36E 07

A-85

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

(

TABLE A.5-16

GROgND PIANE PKH5%Y F1CIORM MRDUYR PER UCI/SEC

(RI F1CIQ1)

H-3 0.00E 00 Y-91M 1.00E 05 CS-134 6.86E 09C-14 0.00E 00 Y-91 1.07E 06 CS-136 1.49E 08 |NA-24 1.19E 07 Y-92 1.80E 05 CS-137 1.03E 10P-32 0.00E 00 Y-93 1.85E 05 CS-138 3.59E 05CR-51 4.66E 06 ZR-95 2.45E 08 BA-139 1.06E 05MN-54 1.39E 09 ZR-97 2.96E 06 BA-140 2.05E 07MN-56' 9.03E 05 h 95 1.37E 08 BA-141 4.18E 04FE.-55 0.00E 00 6 99 3.99E 06 N 142 4.49E 04FE-59 2.73E 08 'IC-99M 1.84E 05 IA-140 1.92E 07

'IC-101 2.04E 04CO-58 3.79E 08 RU-103 1.08E 08 IA-142 7.37E 05CO-60 2.15E 10 RU-105 6.36E 05 CE-141 1.37E 07NI-63 0.00E 00 RU-106 4.21E 08 CE-143 2.31E 06NI-65 3.02E 05 G 110M 3.44E 09 CE-144 6.96E 07CU-64 6.07E 05 TE-125M 1.55E 06 PR-143 0.00E 00ZN-65 7.46E 08 TE-127M 9.17E 04 PR-144 1.83E 03ZN-69 0.00E 00 TE-127 2.98E 03 ND-147 8.46E 06BR-83 4.87E 03 TE-129M 1.98E 07 W-187 2.36E 06BR-84 2.03E 05 TE-129 2.62E 04 NP-239 1.71E 06BR-85 0.00E 00 TE-131M 8.03E 06RB-86 8.99E 06 TE-131 2.92E 04RB-88 3.31E 04 TE-132 4.23E 06RB-89 1.21E 05 I-130 5.51E 06SR-89 2.16E 04 I-131 1.72E 07SR-90 0.00E 00 I-132 1.25E 06SR-91 2.14E 06 I-133 2.45E 06SR-92 7.77E 05 I-134 4.47E 05Y-90 4.49E 03 I-135 2.53E 06

i

A-869/93

_

--_____ _ _ _ _______-__ _ - _ - -_ _ _ _ - __ _

TABLE A.5-17

GRASSp'4/YR PER UCI/SECMILK PA'1HRY F1CIU1

M MRDADULT

i! NUCLIDE BONE LIVER T BODY 'IHYROID KIDNEY IDG GI-LLI |


P 32 2.05E 10 1.27E 09 7.93E 08 0.00E-01 0.00E-01 0.00E-01 2.31E 09| CR 51 0.00E-01 0.00E-01 3.43E 03 2.05E 03 7.55E 02 4.55E 03 8.62E 05| MN 54 0.00E-01 1.01E 06 1.93E 05 0.00E-01 3.00E 05 0.00E-01 3.09E 06

121 56 0.00E-01 4.99E-04 8.85E-05 0.00E-01 6.34E-04 0.00E-01 1.59E-02FE 55 3.26E 05 2.25E 05 5.26E 04 0.00E-01 0.00E-01 1.26E 05 1.29E 05FE 59 3.86E 05 9.07E 05 3.48E 05 0.00E-01 0.00E-01 2.54E 05 3.02E 06

00 58 0.00E-01 5.66E 05 1.27E 05 0.00E-01 0.00E-01 0.00E-01 1.15E 0700 60 0.00E-01 1.97E 06 4.34E 06 0.00E-01 0.00E-01 0.00E-01 3.708 07NI 63 8.07E 08 5.65E 07 2.71E 07 0.00E-01 0.00E-01 0.00E-01 1.17E 07

NI 65 5.56E-02 7.22E-03 3.30E-03 0.00E-01 0.00E-01 0.00E-01 1.838-01CU 64 0.00E-01 2.66E 03 1.25E 03 0.00E-01 6.70E 03 0.00E-01 2.27E 05KN 65 1.65E 08 5.24E 08 2.37E 08 0.00E-01 3.50E 08 0.00E-01 3.30E 08



RB 89 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01.SR 89 3.05E 09 0.00E-01 8.75E 07 0.00E-01 0.00E-01 0.00E-01 4.89E 08 iSR 90 9.83E 10 0.00E-01 2.41E 10 0.00E-01 0.00E-01 0.00E-01 2.84E 09 i

i

SR 91 6.02E 04 0.00E-01 2.43E 03 0.00E-01 0.00E-01 0.00E-01 2.87E 05-SR 92 1.03E 00 0.00E-01 4.45E-02 0.00E-01 0.00E-01 0.00E-01 2.04E 01 !Y 90 8.49E 00 0.00E-01 2.28E-01 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-20Y 91 1.03E 03 0.00E-01 2.76E 01 0.00E-01 0.00E-01 0.00E-01 5.67E 05 3Y 92 6.71E-06 0.00E-01 1.96E-07 0.00E-01 0.00E-01 0.00E-01 1.18E-01

'A-87

!!

- _ _ _ - _ _ - - _ _ - _ . _ _ - _ _ _

_ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ___-_-__ _ _ - -.

BBER A.5-17 (Cbrit'd)

GRASS pOAT-MILK PA11MAY FICIORM~ MREM /YR PER UCI/SDC

ADULT

NUCLIDE BONE LIVER T DODY 7HYROID KIDNEY IRC GI-ILI

Y 93 2.80E-02 0.00E-01 7.73E-04 0.00E-01 0.00E-01 0.00E-01 8.87E 02ZR 95 1.13E 02 s.63E 01 2.46E 01 0.00E-01 5.70E 01 0.00E-01 1.15E 05ZR 97 5.20E-02 1.05E-02 4.80E-03 0.00E-01 1.58E-02 0.00E-01 3.25E 03

;

NB 95 9.91E 03 5.51E 03 2.96E 03 0.00E-01 5.45E 03 0.00E-01 3.35E 07NO 99 0.00E-01 2.97E 06 5.65E 05 0.00E-01 6.73E 06 0.00E-01 6.89E 067C 99M 3.99E-01 1.13E 00 1.44E 01 0.00E-01 1.71E 01 5.53E-01 6.67E 02

7C 101 0.00E-01 0.00E-01 0,00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01RU 103 1.22E 02 0.00E-01 5.26E 01 0.00E-01 4.66E 02 0.00E-01 1.43E 04RU 105 1.03E-04 0.00E-01 4.07E-05 0.00E-01 1.33E-03 0.00E-01 6.30E-02

RU 106 2.45E 03 0.00E-01 3.10E 02 0.00E-01 4.73E 03 0.00E-01 1.58E 05IG 110M 6.99E 06 6.46E 06 3.84E 06 0.00E-01 1.27E 07 0.00E-01 2.64E 09TE 125M 1.95E 06 7.08E 05 2.62E 05 5.88E 05 7.95E 06 0.00E-01 7.81E 06

TE 127M 5.49E 06 1.96E 06 6.70E 05 1.40E 06 2.23E 07 0.00E-01 1.84E 07TE 127 7.84E 01 2.82E 01 1.70E 01 5.81E 01 3.19E 02 0.00E-01 6.19E 03TP 129M 7.22E 06 2.69E 06 1.14E 06 2.48E 06 3.02E 07 0.00E-01 3.64E 07



I 132 1.98E-01 5.29E-01 1.85E-01 1.85E 01 8.43E-01 0.00E-01 9.94E-02I 133 4.65E 06 8.08E 06 2.46E 06 1.19E 09 1.41E 07 0.00E-01 7.26E 06I 134 2.44E-12 6.63E-12 2.37E-12 1.15E-10 1.05E-11 0.00E-01 5.78E-15



A-88

:

... _ _ _ _

i

i|

I!

!

'IRBLE A.5-17 (Cant'd)

GRASSp-MILK PATERY FAC70RM MREM /YR PER W I/S E

ADULT

NUCLIDE BONE LIVER T BODY 'IHYROID KIDhTY IDE GI-ILI

BA 140 3.23E 06 4.05E 03 2.11E 05 0.00E-01 1.38E 03 2.32E 03 .6.64E 06BA 141 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01BA 142 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01

IA 140 5.43E-01 2.73E-01 7.23E-02 0.00E-01 0.00E-01 0.00E-01 2.01E 04LA 142 1.13E-12 5.12E-13 1.28E-13 0.00E-01 0.00E-01 0.00E-01 3.74E-09CE 141 5.81E 02 3.93E 02 4.46E 01 0.00E-01 1.83E 02 0.00E-01 1.50E 06

CE 143 4.99E 00 3.69E 03 4.08E-01 0.00E-01 1.62E 00 0.00E-01 1.38E 05CE 144 4.29E 04 1.79E 04 2.30E 03 0.00E-01 1.06E 04 0.00E-01 1.45E 07PR 143 1.90E 01 7.60E 00 9.39E-01 0.00E-01 4.39E 00 0.00E-01 8.30E 04

PR 144 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01ND 147 1.14E 01 1.31E 01 7.85E-01 0.00E-01 7.67E 00 0.00E-01 6.30E 04 '

W 187 7.87E 02 6.58E 02 2.30E 02 0.00E-01 0.00E-01 0.00E-01 2.16E 05

NP 239 4.41E-01 4.33E-02 2.39E-02 0.00E-01 1.35E-01 0.00E-01 8.89E 03

i

J

l|

|!

!

!

!

A-89i|

||

l'

.

TMIR A.5-18

GRASS,pCAT-MILK PA'IIDIAY FICIORM MREM /YR PER UCI/SEC

TEEN

NUCLIDE DONE LIVER T BODY 'IHYROID KIDNEY I13tG GI-ILI


P 32 3.78E 10 2.34E 09 1.47E 09 0.00E-01 0.00E-01 0.00E-01 3.18E 09 ,

CR 51 0.00E-01 0.00E-01 5.99E 03 3.33E 03 1.31E 03 8.55E 03 1.01E 06MN 54 0.00E-01 1.68E 06 3.34E 05 0.00E-01 5.02E 05 0.00E-01 3.45E 06

MN 56 0.00E-01 8.85E-04 1.578-04 0.00E-01 1.12E-03 0.00E-01 5.829-02FE 55 5.79E 05 4.10E 05 9.57E 04 0.00E-01 0.00E-01 2.60E 05 1.78E 05FE 59 6.74E 05 1.57E 06 6.07E 05 0.00E-01 0.00E-01 4.96E 05' 3.72E 06

00 58 0.00E-01 9.52E 05 2.19E 06 0.00E-01 0.00E-01 0.00E-01 1.31E 07CO 60 0.00E-01 3.34E 06 7.52E 06 0.00E-01 0.00E-01 0.00E-01 4.35E 07NI 63 1.42E 09 1.00E 08 4.81E 07 0.00E-01 0.00E-01 0.00E-01 1.59E 07

NI 65 1.02E-01 1.30E-02 5.92E-03 0.00E-01 0.00E-01 0.00E-01 7.05E-01CU 64 0.00E-01 4.74E 03 2.23E 03 0.00E-01 1.20E 04 0.00E-01 3.67E 05ZN 65 2.53E 08 8.78E 08 4.09E 08 0.00E-01 5.62E 08 0.00E-01 3.72E 08




SR 91 1.11E 05 0.00E-01 4.40E 03 0.00E-01 0.00E-01 0.00E-01 5.02E 05SR 92 1.88E 00 0.00E-01 8.02E-02 0.00E-01 0.00E-01 0.00E-01 4.80E 01Y 90 1.56E 01 0.00E-01 4.20E-01 0.00E-01 0.00E-01 0.00E-01 1.29E 05


A-90 I

|

|

TBB m A.5-18 (Cont'd)

GRASS,fGCAT-MILK PA11MAY FACTCRM~ MRDf/YR PER UCI/SEC

TEEN

NUPLIDE BONE LIVER T BODY THYROID KIDNEY IDG GI-LLI

Y 93 5.16E-02 0.00E-01 1.41E-03 0.00E-01 0.00E-01 0.00E-01 1.58E 03ZR 95 1.98E 02 6.25E 01 4.30E 01 0.00E-01 9.18E 01 0.00E-01 1.44E 05.ZR 97 9.47E-02 1.87E-02 8.63E-03 0.00E-01 2.84E-02 0.00E-01 5.07E 03

NB 95 1.69E 04 9.37E 03 5.16E 03 0.00E-01 9.09E 03 0.00E-01. 4.01E 07-NO 99 0.00E-01 5.37E 06 1.02E 06 0.00E-01 1.23E 07 0.00E-01 9.61E 067C 99M 6.92E-01 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-01RU 103 2.17E 02 0.00E-01 9.28E 01 0.00E-01 7.66E 02 0.00E-01 1.81E 04RU 105 1.88E-04 0.00E-01 7.30E-05 0.00E-01 2.37E-03 0.00E-01 1.52E-01 #




TE 132 5.15E 05 3.26E 05 3.07E 05 3.44E 05 3.13E 06 0.00E-01 1.03E 07I 130 8.87E 05 2.57E 06 1.02E 06 2.09E 08 3.95E 06 0.00E-01 1.97E 06I 131 6.45E 08 9.03E 00 4.85E 08 2.63E 11- 1.55E 09 0.00E-01 1.79E 08

I 132 3.51E-01 9.18E-01 3.29E-01 3.09E 01 1.45E 00 0.00E-01 4.00E-01I 133 8.49E 06 1.44E 07 4.39E 06 2.01E 09 2.52E 07 0.00E-01 1.09E 07I 114 4.34E-12 1.15E-11 4.13E-12 1.92E-10 1.81E-11 0.00E-01 1.51E-13

I 135 2.74E 04 7.05E 04 2.61E 04 4.54E 06 1.11E 05 0.00E-01 7.82E.04CS 134 2.94E 10 6.93E 10 3.22E 10 0.00E-01 2.20E 10 8.41E 09 8.62E 08CS 135 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 08CS 138 4.99E-23 9.58E-23 4.79E-23 0.00E-01 7.07E-23 8.23E-24 4.34E-26Im 139 1.01E-08 7.13E-12 2.95E-10 0.00E-01 6.72E-12 4.91E-12 9.04E-08

A-91 l

;

I

!

_ .. . _ _ _ _ _ _ _

'lNEE A.5-18 (Otmt'd)

MILK PA'mWAY FICERGRASSpf/YR PER TJCI/SECM MRD

TEEN

NUCLIDE KNE LIVER T BODY 'IHYROID KIDNEY IDG GT-ILI


IA 140 9.75E-.01 4.79E-01 1.27E-01 0.00E-01 0.00E-01 0.00E-01 2.75E 041A 142 2.03E-12 9.03E 13 2.25E-13 0.00E-01 0.00E-01 0.00E-01' 2.75E-08CE 141 1.07E 03 7.12E 02 8.10E 01 0.00E-01 3.35E 02 0.00E-01- 2.04E 06

CE 143 9.17E 00 6.67E 03 7.45E-01 0.00E-01 2.99E 00 0.00E-01 2.01E 05CE 144 7.90E 04 3.27E 04 4.24E D3 0.00E-01 1.95E 04 0.00E-01 1.99E 07PR 143 3.48E 01 1.39E 00 1.73E 00 0.00E-01 8.08E 00 0.00E-01 1.15E g


NP 239 8.41E-01 7.93E-02 4.41E-02 0.00E-01 2.49E-01 0.00E-01 1.28E 04

A-92

# _A. .-w . 4

GRAS pS-MILK PA'IHWAY FACIORr MRIN/YR PER UCI/SEE

CHIID

NUCLIDE BONE LIVER T BODY 'IHYROID KIDNEY IRG GI-ILI

H 3 0.00E-01 3.20E 03 3.20E 03 3.20E 03 3.20E 03 3.20E 03 3.20E 03C 14 1.19E 09 2.39E 08 2.39E 08 2.39E 08 2.39E 08 2.39E 08 2.39E 08NA 24 1.06E 06 1.06E 06 1.06E 06 1.06E 06, 1.06E 06 1.06E 06 1.06E 06


MN 56 0.00E-01 1.54E-03 3.48E-04 0.00E-01 1.87E-03 0.00E-01 2.24E-01FE 55 1.45E 06 7.70E 05 2.39E 05 0.00E-01 0.00E-01 4.36E 05 1.43E 05FE 59 1.56E 06 2.53E 06 1.26E 06 0.00E-01 0.00E-01 7.33E 05 2.63E 06

CO 58 0.00E-01 1.46E 06 4.45E 06 0.00E-01 0.00E-01 0.00E-01 8.49E 06CO 60 0.00E-01 5.18E 06 1.53E 07 0.00E-01 0.00E-01- 0.00E-01 2.87E 07NI 63 3.56E 09 1.90E 08 1.21E 08 0.00E-01 0.00E-01 0.00E-01 1.28E 07

NI 65 2.49E-01 2.34E-02 1.37E-02 0.00E-01 0.00E-01 0.00E-01 2.87E 00CU 64 0.00E-01 8.23E 03 5.03E 03 0.00E-01 2.01E 04 -0.00E-01 3.91E 05 '

ZN 65 4.96E 08 1.32E 09 8.22E 08 0.00E-01 8.33E 08 0.00E-01 2.32E 08

ZN 69 2.84E-12 4.10E-12 3.79E-13 0,00E-01 2.49E-12 0.00E-01 2.58E-10BR 83 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01BR 84 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-01SR 89 1.39E 10 0.00E-01 3.97E 08 0.00E-01 0.00E-01 0.00E-01' 5.38E 08SR 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 05SR - 92 4.60E 00 0.00E-01 1.84E-01 0.00E-01 0.00E-01 0.00E-01 8.71E 01Y 90 3.86E 01 0.00E-01 1.03E-00 0.00E-01 0.00E-01 0.00E-01 1.10E 05.


A-93 )

:1

. _

.)

TABM A.5-19 (Cont'd)

GRAS pS-MILK PATHWAY FACIOR-

r MRD UYR PER UCI/SECCHIID

NUCLIDE BONE LIVER T BODY THYROID KIDNEY IRG GI-ILI

Y 93 1.27E-01 0.00E-01 3.48E-03 0.00E-01 0.00E-01 0.00E-01 1.89E 03ZR 95 4.60E 02 1.01E 02 9.00E 01 0.00E-01 1.45E 02 0.00E-01 1.05E 05ZR 97 2.30E-01 3.33E-02 1.96E-02 0.00E-01 4.78E-02 0.00E-01 5.04E 03 !

NB 95 3.82E 04 1.49E 04 1.06E 04 0.00E-01 1.40E 04 0.00E-01 2.75E 07 iMO 99 0.00E-01 9.76E 06 2.42E 06 0.00E-01 2.08E 07 0.00E-01 8.07E 06 !TC 99M 1.59E 00 3.11E 00 5.16E 01 0.00E-01 4.52E 01 1.58E 00 1.77E 03 |

TC 101 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 !RU 103 5.14E 02 0.00E-01 1.97E 02 0.00E-01 1.29E 03 0.00E-01 1.33E 04 I

RU 105 4.59E-04 0.00E-01 1.67E-04 0.00E-01 4.04E-03 0.00E-01 3.00E-01

RU 106 1.11E 04 0.00E-01 1.38E 03 0.00E-01 1.50E 04 0.00E-01 1.72E 05AG 110H 2.51E 07 1.69E 07 1.35E 07 0.00E-01 3.15E 07 0.00E-01 2.01E 09TE 125M 8.85E 06 2.40E 06 1.18E 06 2.48E 06 0.00E-01 0.00E-01 8.54E 06 !

TE 127M 2.50E 07 6.72E 06 2.96E 06 5.97E 06 7.12E 07 0.00E-01 2.02E 07TE 127 3.57E 02 9.64E 01 7.67E 01 2.47E 02 1.02E 03 0.00E-01 1.40E 04TE 129M 3.26E 07 9.09E 06 5.05E 06 1.05E 07 9.56E 07 0.00E-01 3.97E 07 |1



I 132 8.30E-01 1.52E 00 7.01E-01 7.07E 01 2.33E 00 0.00E-01 1.79E 00I 133 2.06E 07 2.55E 07 9.65E 06 4.74E 09 4.25E 07 0.00E-01 1.03E 07I 134 1.03E-11 1.91E-11 8.77E-12 4.39E-10 2.92E-11 0.00E-01 1.26E-11 .i

I 135 6.49E 04 1.17E 05 5.52E 04 1.03E 07 1.79E 05 0.00E-01 8.90E 04 I'CS 134 6.79E 10 1.11E 11 2.35E 10 0.00E-01 3.45E 10 1.24E 10 6.01E 08

CS 136 3.01E 09 8.27E 09 5.35E 09 0.00E-01 4.40E 09 6.57E 08 2.91E 08

CS 137 9.67E 10 9.26E 10 1.37E 10 0.00E-01 3.02E 10 1.09E 10 5.80E 08CS 138 1.21E-22 1.68E-22 1.07E-22 0.00E-01 1.18E-22 1.27E-23 7.74E-23BA 139 2.49E-08 1.33E-11 7.21E-10 0.00R-01 1.16E-11 7.82E-12 1.44 E-06

A-949/93

l

i

i

|

1

'1%B[E A.5-19 (Ctmt'd):

GRASS @-MIIK PA'1M%Y F1CIOR |

M~ MRH VYR PER UCI/S T j

CHIID li

NUCLIDE BJNE LIVER T BODY 'IEYROID KIDNEY IDG GI-ILI ;

I'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-01BA 142 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 ,

IA 140 2.33E 00 8.16E-01 2.75E-01 0.00E-01 0.00E-01 0.00E-01 2.27E 04IA 142 4.91E-12 1.56E-12 4.90E-13 0.00E-01 0.00E-01 0.00E-01 3.10E-07CE lal 2.63E 03 1.31E 03 1.94E 02 0.00E-01 5.74E 02 0.00E-01 1.63E 06


PR 144 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01ND 147 5.36E 01 4.34E 01 3.36E 00 0.00E-01 2.38E 01 0.00E-01 6.88E 04W 187 3.49E 03 2.07E 03 9.28E 0?. 0.00E-01 0.00E-01 0.00E-01 2.90E05I:

NP 239 2.07E 00 1.49E-01 1.04E-01 0.00E-01 4.30E-01 0.00E-01 1.10E 04

A-959/93

.

TAB 2 A.5-20

GRASS @'-MILK PA'IHWAY F1CIORM~ MREN/YR PER ICI/SEC

INFANI'

NIELIDE BONE LIVER T DODY 'IHYROID KIDNEY IDG GI-ILI

H 3 0.00E-01 4.86E 03 4.86E 03 4.86E 03 4.86E 03 4.863 03 4.86E 03C 14 2.34E 09 5.00E 08 5.00E 08 5.00E 08 5.00E 08 5.00E 08 5.00E 08NA 24 1.85E 06 1.85E 06 1.85E 06 1.85E 06 1.85E 06 1.85E 06 1.85E 06


MN 56 0.00E-01 3.78E-03 6.51E-04 0.00E-01 3.25E-03 0.00E-01 3.43E-01FE 55 1.76E 05 1.13E 06 3.03E 06 0.00E-01 0.00E-01 5.54E 05 1.44E 05FE 59 2.92E 06 f_;.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 06CO 60 0.00E-01 1.06E 07 2.50E 07 0.00E-01 0.00E-01 0.00E-01 2.52E 07NI 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 00CU 64 0.00E-01 2.07E 04 9.58E 03 0.00E-01 3.50E 04 0.00E-01 4.25E 05ZN 65 6.66E 08 2.28E 09 1.05E 09 0.00E-01 1.11E 09 0.00E-01 1.93E 09


BR 85 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01RB 86 0.00E-01 2.67E 09 1.32E 09 0.00E-01 0.00E-01 0.00E-01 6.83E 07RB 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-01SR 89 2.64E 10 0.00E-01 7.58E 08 0.00E-01 0.00E-01 0.00E-01 5.43E 08SR 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 05SR 92 9.78E 00 0.00E-01 3.63E-01 0.00E-01 0.00E-01 0.00E-01 1.05E 02Y 90 8.1M 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-16Y 91 8.79E 03 0.00E-01 2.34E 02 0.00E-01 0.00E-01 0.00E-01 6.30E 05Y 92 6.47E-05 0.00E-01 1.82E-06 0.00E-01 0.00E-01 0.00E-01 1.23E 00

|

|

A-96 )i

1

ii

!

|

TABM A.5-20 (Omt'd) 1

GRASS @ -MILK PATHNAY EACICRM MREN/YR PER UCI SEC

INFANI'

NUCLIDE BONE I,IVER T BODY THYROID KIDNEY IDG GI-ILI

Y 93 2.70E-01 0.00E-01 7.36E-03 0.00E-01 0.00E-01 0.00E-01 2.13E 03ZR 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 07MD 99 0.00E-01 2.50E 07 4.87E 06 0.00E-01 3.73E 07 0.00E-01 8.22E 06-7C 99M 3.30E 00 6.81E 00 8.77E 01 0.00E-01 7.33E 01 3.56E 00 1.98E 0J

7C 101 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00D-01 0.00E-01RU 103 1.04E 03 0.00E-01 3.48E 02 0.00E-01 2.16E 03 0.00E-01 1.26E 04RU 105 9.68E-04 0.00E-01 3.26E-04 0.00E-01 7.12E-03 0.00E-01 3.85E-01


TE 127M 5.05E 07 1.68E 07 6.12E 06 1.46E 07 1.24E 08 0.00E-01 2.04E 07TE 127 7.59E 02 2.54E 02 1.63E 02 6.18E 02 1.85E 03 0.00E-01 1.59E 04TE 129M 6.69E 07 2.29E 07 1.03E 07 2.57E 07 1.67E OP 0.00E-01 3.99E 07

TE 129 3.28E-10 1.13E-10 7.66E-11 2.75E-10 8.17E-10 0.00E-01 2.62E-08TE 131M 4.05E 05 1.63E 05 1.35E 05 3.31E 05 1.12E 06 0.00E-01 2.75E 06.TE 131 4.18E-33 1.54E-33 1.17E-33 3.73E-33 1.07E-32 0.00E-01 1.69E-31

TE 132 2.53E 06 1.25E 06 1.17E 06 1.85E 06 7.84E 06 0.00E-01 4.64E 06I 130 4.26E 06 9.38E 06 3.76E 06 1.05E 09 1.03E 07 0.00E-01 -2.01E 06I 131 3.26E 09 3.85E 09 1.69E 09 1.26E 12 4.49E 09 0.00E-01 1.37E 08



CS 137 1.54E 11 1.81E 11 1.28E 10 0.00E-01 4.85E 10 1.96E 10 5.65E 08CS 138 2.55E-22 4.15E-22 2.01E-22 0.00E-01 2.07E-22 3.23E-23 6.63E-22Im 139 5.30E-08 3.51E-11 1.53E-09 0.00E-01 2.11E-11 2.13E-11 3.35E-06

A-97

Iii

TABLE A.5-20 (Otut'd)

GRASSp-MIII PA'IEWAY F1CIORM~ MREM /YR PER UCI/SEC

INFANT

NUCLIDE BONE LIVER T BODY 'IHYROID KIDNEY IMG GI-ILI i

BA 140 2.89E 07 2.89E 04 1.49E 06 0.00E-01 6.87E 03 1.78E.04 7.11E 06 j

BA 141 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01BA 142 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01 0.00E-01

IA 140 4.88E 00 1.92E 00 4.94E-01 0.00E-01 0.00E-01 0.00E-01 2.26E 04 >

IA 142 1.03E-11 3.78E-12 9.06E-13 0.00E-01 0.00E-01 0.00E-01 6.43E-07CE 141 5.20E 03 3.17E 03 3.74E 02 0.00E-01 9.79E 02 0.00E-01 1.64E 06



NP 239 4.38E 00 3.91E-01 2.21E-01 0.00E-01 7.80E-01 0.00E-01 1.13E 04

.

A-98

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1

.

!

.

.

AMBOIX B

Meteorological Mcdel

i

M B-1

APPENDIX B

PROPRIETARY INFORMATICN SUPPLIED BY SAI

'Ihe X/Q's and D/Q's are calculated using the guidance of Reg. Guide1.111.

'Ihe constant nean wi2d direction nodel, as defined in equation 3 ofReg. Guide 1.111, is used to calculated X/Q values.

2 2

(X/Q)D 2.032{gfg exp [-he /2 & zj (x))= n

N x U ( (x)f

where:

h Effective release height (m). (All releases frun Wolf=e Creek Generating Station are considered as ground

releases therefore h = 0.)e

gg Hours of valid data for weather conditions in given-n =

direction, windspeed class 1, and atnespheric stabilityclass j.

'Ibtal hours of valid dataN =

U Midpoint of windspeed class.(m/s)=f

Distance downwird' (m)x =

&(x) Vertical plume spread without volumetric correction at=

*3 distance x and stability class j. See Figure B.1 j

Vertical plume spread with columetric correction for(x) =

release within buildings wake cavity, at distance x and .Istability class j. |

!

For ground level releases fj(x)isthelesserof

( o. 2 (x) + 0.5Dz/ 11- )1/2

gjor6 Fzj (X)

Where

Mwimn adjacent bd1dNg height either up- ID =* or down-wind frcxn the release point

ODCM B-2

__ . _.. _ -_ _ _ _ _ _ _ .

1/2.2.032 = (2/ ) divided by width, in radians, of.a 22.5 sector

(X/Q)D Average effluent concentration, .X, normalized=

to source strength, Q, at distance x insector D.

For NOGS the above Meteoregical Model will shnplify to thefollowing equation for X/Q: -

2.032 i n

(X/Q)D"

f) jx)N iJ xf

The calculation of the relative disposition per unit area, D/Q, is-performed using the deposition rate graphs found in Reg. Guide1.111. Ibr a 22.5 sector, since the effluent concentration is -assumed uniform across the sector, the relative deposition perunit area is assumed uniform across the sector.

The calculation of D/Q is determined frm relative deposition bythe following relationship:

D/Q fj (x) *D DE yj (x)=

(2 r/16) xf

Nhere:

D )(x) Relative deposition rate for windspeed class i and=f stability class j at downwind distance x (1/m).

See Figure B.3.

(2e/16)x Iangth of arc across sector at downwind distance x=

(m).

D/O Relative deposition per unit area.(m).=

DEPL )(x) =Reduction factor due to plume depletion at distancegx for windspeed i and stability class j.

|

s

1

!|

|

j

ODCM B-3 !

.

Figure B.1

(

10001 1

I

* ,</ / /> /

/ /'

// / /| ,/ /; /*, -

| | / ,/

/ / / // /

/ / -

/ / / /,

^ '/-

-- /100 ! ' '1 ,

, ,-/ / / f c / /"O/ j; f>

t / "

s "'s*

/ '/'/ / ,; i ;f f /s

/ / i7 / / / ---

,'

/ f | _ . -

// 'D / |'

h ||s/ /),/ / !,

s ,._. s /

,~/ / F /

~

.. o

V,

10 -/,/,

,

/ af,

,

/ / / / 'l/ / / // / / '

s/ / / / ~]_/ / / ,

// ;.

/ / '

/ '

//

1

0.1 1.0 10 100PLUME TRAVEL DISTANCE (KILOMETERS)

Vertical Standard Deviation of Materialin a Plume (Letters denote Pasquilt Stability Class)

NOTE:THESE ARE STANDARD RELATIONSHIPS AND MAY HAVE TO BEMOOtFIED FOR CERTAIN TYPES OF TERRAIN ANO/OR CLIMATICCONDITIONS (E.C., VALLE Y. 0ESERT. OVER WATERI.

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