Text

Rev 7 to 6610-PLN-4200.01, Odcm
	ML20059M230
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Site:	Crane
Issue date:	11/12/1993
From:	; GENERAL PUBLIC UTILITIES CORP.
To:	;
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{{#Wiki_filter:- Number bdear TMI Radiological Controis Departmental Procedure 6610-PLN-4200.01 Titte Revision No. Offsite Dose Calculation Manual (ODCM) 7 . Apphcabihty/ Scope Calculate OffSIts doses due to radioactive Responscle Office Ettective Date effluents fc ' aonstrating compliance with Site Technical Specifications 10 CFR 20 & 10 CFR 50 - Appendix 1 6610 This document is within OA plan scope X Yes No Safety Reviews Required X Yes No List of Effective Pages Pace Revision Pace Revision Paae Revision Paae Revision 1.0 7 21.0 7 41.0 7 61.0 3 2.0 7 22.0 3 42.0 7 62.0 3 3.0 7 23.0 3 43.0 7 63.0 3 4.0 7 24.0 4 44.0 7 64.0 3 5.0 7 25.0 3 45.0 3 65.0 3 6.0 7 26.0 3 46.0 3 66.0 3 7.0 7 27.0 3 47.0 3 67.0 3 8.0 7 28.0 3 48.0 3 68.0 3 9.0 7 29.0 3 49.0 3 69.0 3 10.0 7 30.0 7 50.0 3 70.0 3 11.0 4 31.0 7 51.0 3 71.0 3 12.0 3 32.0 3 52.0 3 72.0 3 13.0 7 33.0 3 53.0 7 73.0 3 14.0 7 34.0 7 54.0 7 74.0 3 15.0 7 35.0 3 55.0 3 75.0 3 16.0 7 36.0 7 56.0 3 76.0 3 17.0 7 37.0 7 57.0 3 77.0 3 18.0 7 38.0 7 58.0 3 78.0 3 19.0 7 39.0 7 59.0 3 79.0 3 20.0 7 40.0 7 60.0 3 80.0 3 ? Signature.] 3 Dats. i Radiological Engineer, TMI sI-i t -4 5 Env. Controls y // //6F(( Manager, Rad. Eng., TMi g_,g i 1 - g a - q '3 TMI Licensing Director gpp f gfjy/[/ jf ~/a f.3 Chairman, TMI.2 Plant Review Group fj/jf3 TMI-2 Site Operations Director ff fthy Rad Con Director, TMI gg g 1( -1&-R3 V J 9311280292 931112 DR ADOCK 05000320 PDR. i ~. ; y

= fdumber TMl Radiological Controls Departmental Procedure 6610-PLN-4200.01 Title Reviuon No. I Offsite Dose Calculation Manual (ODCM) 7 l List of Effective Pages (Cont'd) -l Page Revision Paae Revision Pace Revision Paae Revision 81.0 3 121.0 7 I 82.0 3 122.0 7 l 83.0 3 123.0 7 84.0 3 124.0 7 85,0 3 125.0 7 l 86.0 7 12S.O 7 87.0 7 127.0 7 88.0 7 128.0 7 + 89.0 4 129.0 7 90.0 7 130.0 7 91.0 3 131.0 7 92.0 3 132.0 7 93.0 3 133.0 7 94.0 3 134.0 7 95.0 3 31 1 3 96.0 4 E2-1 3 97.0 4 E3-1 3 98.0 3 E4-1 3 99.0 3 E4-2 3 100.0 3 E5-1 3 101.0 3 E6-1 3 102.0 3 E7-1 3 l 103.0 3 E7-2 3 -l 104.0 3 E7-3 3 105.0 3 E7-4 3 106.0 3 107.0 7 108.0 7 109.0 3 110.0 7 .111.0 7 112.0 3 113.0 7 114.0 3 115.0 7 116.0 7 117.0 7 'I 118.0 7 119.0 7 'i 120.0 7 I 2.0 v 7,, l

Number [r yJ1 Nuclear '" d 9'o"' c ""d' Departmental Procedure 6610-PLN-4200.01 T rtie Revision No. Offsite Dose Calculation Manual (ODCM) 7 INTRODUCTION The OFFSITE DOSE CALCULATION MANUAL (ODCM) is a supporting document of the GPUNC Three Mile Island Nuclear Station FMINS) Unit 1 and Unit 2 PDMS Technical Specifications. The ODCM describes the methodology and parameters to be used in the calculation of off site doses due to radioactive liquid and gaseous effluents. This document also describes the methodology used for calculation of the liquid and gaseous effluent monitoring instrumentation alarm / trip set points. Liquid and Gaseous Radwaste Treatment System configurations are also included. The ODCM also is used to define the requirements for the TMINS radiological environmental monitoring program (REMP) and contains a list and graphical description of the specific sample locations used in the REMP. The ODCM is maintained at the Three Mile Island GM!) site for use as a reference guide and training document of accepted methodologies and calculations. Changes in the calculation methods or parameters will be incorporated into the ODCM to ensure the ODCM represents the present methodology in all applicable areas. GPUNC initiated changes to the ODCM will be implemented in accordance with the TMI-1 and TMi-2 PDMS Technical Specifications. The ODCM follows the methodology and models suggested by NUREG-0133, and Regulatory Guide 1.109, Revision 1 for calcutation of aff-site doses due to plant effluent releases. Simplifying assumptions have been app!ied in this manual where applicable to provide a more workable document for implementation of the Radiological Effluent Controls requirements. GPUN implements the TMi Radiological Effluent Controls Program and Regulatory Guide 1.21. Revision 1 (Semiannual Radioactive Effluent Release Report) requirements by use of a computerized system used to determine TMI effluent releases and to update cumulative effluent doses. 1 2 30 rm.

Number Ic r., J] Nualear " " d' ' o'o^' "t * $ Departmental Procedure 6610-PLN-4200.01 Title Revision No. Offsite Dose Calculation Manual (ODCM) 7 TABLE OF CONTENTS Section Page PARTI EFFLUENT DATA AND CALCULATIONAL METHODOLOGIES 1.0 LIQUID EFFLUENT MONITORS 13.0 1.1 TMI-1 and TMI-2 Uguid Radiation Monitor Set Points 13.0 1.2 TMI Uguid Release Points and Liquid Radiation Monitor Data 14.0 1.3 Control of Liquid Releases 17.0 2.0 LIQUID EFFLUENT DOSE ASSESSMENT 22.0 2.1 Liquid Effluents - 10 CFR 50 Appendix i 22.0 2.2 TMI-1 Liquid Radwaste System Dose Cales Once per Month 24.0 2.3 Alternative Dose Calculational Methodology 25.0 3.0 UQUID EFFLUENT WASTE TREATMENT SYSTEM 30.0 3.1 TMI-1 Liquid Effluent Waste Treatment System 30.0 3.2 Operability of TMI-1 Liquid Effluent Waste Treatment System 31.0 3.3 TMI-2 Uquid Effluent Waste Treatment System 31.0 4.0 GASEOUS EFFLUENT MONITORS 34.0 4.1 TMI-1 Noble Gas Monitor Set Points 34.0 4.2 TMI-1 Particulate and Radiciodine Monitor Set Points 36.0 4.3 TMI-2 Gaseous Radiation Monitor Set Points 37.0 4.4 TMI-1 Gaseous Effluent Release Points and Gaseous Radiation Monitor Data 38.0 l 4.5 TMI 2 Gaseous Effluent Release Points and Gaseous Radiation Monitor Data 40.0 4.6 Control of Gaseous Effluent Releases 42.0 j l 5.0 GASEOUS EFFLUENT DOSE ASSESSMENT 54.0 j 5.1 Gaseous Effluents - Dose Rate Limits 54.0 5.1 1 Noble Gases 54.0 4.0 rm,

p Number (UClear m R di i si ai Controis Departmental Procedure 6610-PLN-4200.01 True Revision No. Offsite Dose Calculation Manual (ODCM) 7 i TABLE OF CONTENTS (Cont'd) PARTI EFFLUENT DATA AND CALCULATIONAL METHODOLOGIES Section Page 5.1.1.1 Total Body 54.0 5.1.12 Skin 55.0 5.1.2 lodines and Particulates 56.0 5.2 Gaseous Effluents - 10 CFR 50 Appendix l - 57.0 l 5.2.1 Noble Gases 57.0 6 5.2.2 lodines and Particulates 58.0 i 5.3 Gaseous Radioactive System Dose Calculations Once per Month 60.0 5.4 Alternative Dose Calculational Methodologies 61.0 l 6.0 GASEOUS EFFLUENT WASTE TREATMENT SYSTEM B3.0 6.1 Description of the TMI-1 Gaseous Radwaste Treatment System 83.0 j 6.2 Operability of the TMi-1 Gaseous Radwaste Treatment System 83.0 7.0 EFFLUENT TOTAL DOSE ASSESSMENT 85.0 f 8.0 TMINS RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) 86.0 8.1 Monitoring Program Requirements 86.0 8.2 Land Use Census 88.0 8.3 Intertaboratory Comparison Program 90.0 9.0 PART I REFERENCES 107.0 i IIII( 1 e >v1.-

.~ Number MUClear i R die gic i Contres Departmental Procedure 6610-PLN-4200.01 Tiu' Revision No. Offsite Dose Calculation Manual (ODCM) 7 TABLE OF CONTENTS (Cont'd) - t PARTI EFFLUENT DATA AND CALCUl.ATIONAL METHODOLOGIES Section Page i TABLES Table 1.1 TMI-1 Liquid Release Point and Liquid Radiation Monitor Data 18.0 l Table 1.2 TMl-2 Sump Capacities 19.0 Table 2.1 Liquid Dose Conversion Factors (DCF): DF; . 26.0 i 1 Table 2.2 Bioaccumulation Factors. BF 29.0 -l i Table 4.1 TMI-1 Gaseous Release Point & Gaseous Radiation Monitor Data 42.0 I Table 4.2 TMI-2 Gaseous Release Point & Gaseous Radiation Monitor Data 44.0 -l Table 4.3 Dose Factors for Noble Gases and Daughters 45.0 j l Tabic 4.4 Atmospheric Dispersion Factors for Three Mile island - Station Vent 46.0 Table 4.S Atmospheric Dispersion Factors for Three MHe Island - Ground Release 47.0 j s Table 4 6 Dose Parameters for Radiolodines and Radioactive Particulate, Gaseous, Effluents 48.0 i Table 5.2.1 Pathway Dose Factors, R - Infant, inhalation 62.0 l i l Table 5.2.2 Pathway Dose Factors, R - Child, inhalation 63.0 i Table 5.2.3 Pathway Dose Factors, R - Teen, Inhalation 64.0 i Table 5.2.4 Pathway Dose Factors, R; - Adu!t, Inhalation 65.0 Table 5.3.1 Pathway Dose Factors, R, - All Age Groups, Ground Plane 66.0 l I ] Table 5.4.1 Pathway Dose Factors, R; - Infant, Grass-Cow-Milk. 67.0 Table 5.4.2 Pathway Dose Factors, R - Child, Grass-Cow-Milk 68.0 i 3 i Table 5.4.3 Pathway Dose Factors, R - Teen, Grass-Cow-Milk 69.0 3 Table 5.4.4 Pathway Dose Factors, R, - Adult, Grass-Cow-Milk 70.0 ~ Table 5.5.1 Pathway Dose Factors R - Infant, Grass-Goat-Milk 71.0 i 6.0 u n.

5 Numbor j bdeM TMi R di I gi i Contro:s Departmental Procedure - 6610-PLN-4200.01 I htle Revision No. Offsite Dose Calculation Manual (ODCM) 7 i TABLE OF CONTENTS (Cont'd) PARTI EFFLUENT DATA AND CALCULATIONAL METHODOLOGIES Section Page TABLES i Table 5.5.2 Pathway Dose Factors, R, - Child, Grass-Goat-Milk 72.0 Table 5.5.3 Pathway Dose Factors, R; - Teen, Grass-Goat-Milk 73.0 Table 5.5.4 Pathway Dose Factors, R, - Adult, Grass-Goat-Milk 74.0 Table 5.6.1 Pathway Dose Factors, R - Infant, Grass-Cow-Meat 75.0 3 Table 5.6.2 Pathway Dose Factors, R - Child, Grass-Cow-Meat 76.0 3 Table 5.6.3 Pathway Dose Factors, R; - Teen, Grass-Cow-Meat 77.0 Table 5.6.4 Pathway Dose Factors, R, - Adult, Grass-Cow-Meat 78.0 Table 5.7.1 Pathway Dose Factors, R, - Infant, Vegetation 79.0 Table 5.7.2 Pathway Dose Factors, R; - Child, Vegetation 80.0 Table 5.7.3 Pathway Dose Factors, R, - Tecn, Vegetation 81.0 Table 5.7.4 Pathway Dose Factors, R, - Adult. Vegetation 82.0 Table 8.1 Sample Cofiection and Analysis Requirements 91.0 Table 8.2 Reporting Levels for Radioactivity Concentrations in Environmental Samples 96.0 Table 8.3 Detection Capabilities for Environmental Sample Aralysis 97.0 i Table 8.4 TMINS REMP Station Locations - Air Particulate and Air lodine 99.0 Table 8.5 TMINS REMP Station Locations - Direct Radiation (TLD) 99.0 i Table 8.6 TMINS REMP Station Lacations - Surface Water 101.0 i Table 8.7 TMINS REMP Station Locations - Aquatic Sediment 101.0 Table 8.8 TMINS REMP Station Locations - Milk 102.0 Table 0.9 TMINS REMP Station Locations - Fish 102.0 Table 8.10 TMINS REMP Station Locations - Food Products 103.0 i 7.0 ma i

Numtor AUClear i R di I gi ai Controls Departmental Procedure 6610-PLN-4200.01 - 3 Tatie Revision No. l } . Offsite Dose Calculation Manual (ODCM) 7 j l TABLE OF CONTENTS (Cont'd) PARTI EFFLUENT DATA AND CALCULATIONAL METHODOLOGIES l Section Page l l TABLES } MAP 8.1 Three Mile Island Nuclear Station Locations of Radiological Environmental 104.0 'i Monitoring Program Stations within 1 Mile of the Site MAP 8.2 Three Mile Island Nuclear Station Locations of Radiological Environmental 105.0 Monitoring Program Stations within 5 miles of the Site MAP 8.3 Three Mile Island Nuclear Station Locations of Radiological Environmental 106.0 Monitoring Program Stations Greater than 5 miles from the Site FIGURES Figure 1.1 TMl-1 Liquid Effluent Pathways 20.0 l Figure 1.2 TMI-2 Liquid Effluent Pathways 21.0 Figure 3.1 TMI-1 Liquid Radwaste 32.0 .i t Figure 3.2 TMI-1 Liquid Waste Evaporators 33.0 Figure 4.1 TMI-1 Gaseous Effluent Pathways 49.0 Figure 4.2 TMI-1 Auxiliary & Fuel Handling Buildings Effluent Pathways 50.0 i Figure 4.3 TMI-1 Reactor Building Effluent Pathway 51.0 t Figure 4.4 TMI-1 Condenser Offgas Effluent Pathway 52.0 Figure 4.5 TMI-2 Gaseous Effluent Pathways 53.0 { Figure 6.1 Waste Gas System 84.0 I 6 4 8.0 2m.

l Numbst j-ggy TMI Radiological Controls Depa11 mental Procedure 6610 PLN-4200.01 i Title Revision No. I Offsite Dose Calculation Manual (ODCM) 7 TABLE OF CONTENTS (Cont'd) PARTll TMI-2 RADIOLOGICAL EFFLUENT CONTROLS Section Page '[ t 1.0 DEFINITIONS 110.0 Table 1.1, Frequency Notation 112.0. 2.0 RADIOLOGICAL EFFLUENT REQUIREMENTS 115.0 = 2.1 Radioactive Discharges 115.0 l I 2.1.1 Liquid Effluents 115.0' 2.1.2 Gaseous Effluents 117.0 I 2.2 Radioactivo Gaseous Effluent Monitoring instrumentation 119.0 i Table 2.2-1, Radioactive Gaseous Effluent Monitoring Instrumentation 120.0 3.0 MONITORING REQUIREMENTS 121.0 3.1 Radioactive Discharges 121.0 l 3.1.1 Liquid Effit.ents 121.0 3.1.2 Gaseous Effluents 121.0 .l i 3.2 Radioactive Gaseous Effluent Monitoring Instrumentation 123.0 l l Table 3.1-1, Radioactive Liquid Waste Sampling and Analysis 124.0 Table 3.1-2, Radioactive Gaseous Waste Sampling and Analysis 125.0 ' I 9.0 un,

Numbat MUClear M Radiolgical Controls Departmental Procedure 6610-PLN-4200.01 noe necion No. i Offsite Dose Calculation Manual (ODCM) 7 TABLE OF CONTENTS (Cont'd) PART 11 TMI-2 RADIOLOGICAL EFFLUENT CONTROLS Section Page 4.0 - DESIGN FEATURES 128.0 t 4.1 SITE 128.0 4.1.1 Exclusion Area 128.0 0 4.1.2 Low Population Zone 128.0 3 4.1.3 Site Boundary for Gaseous Effluents 128.0 4.1.4 Site Boundary for Liquid Effluents 128.0 l 5.0 PART 11 REFERENCES 129.0 e -j J 1 o i 10.0 mi,

Nurr.ber Nuclear " "*di ' 9'a' o "t' 1 Departmental Procedure 6610-PLN-4200.01 j Trtie Revision No. i Offsite Dose Calculation Manual (ODCM) 4 l TABLE OF CONTENTS (Cont'd) P A R T lil REPORTING REQUIREMENTS Section Page j 1.0 TMl ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 141.0 1 2.0 TMI ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 142.0 l l 3.0 PART 111 REFERENCES 144.0 APPENDICES A. Pathway Dose Rate Parameter (P) E1-1 3 i B. Inhalation Pathway Dose Factor (R) E2-1 i C. Ground Plane Pathway Dose Factor (R;) E3-1 D. Grass-Cow-Ml!k Pathway Dose Factor (R;) E4-1 E. Cow-Meat Pathway Dose Factor (R,) E5-1 F. Vegetation Pathway Dose Factor (R) E6-1 3 APPENDIX A - F REFERENCES E7-1 1 'l l l j 11.0 raw

] Number (UCIGar-TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 Trtle Revision No. f Offsite Dose Calculation Manual (ODCM) 3 J L i P PARTI i EFFLUENT DATA AND CALCULATIONAL METHODOLOGIES t { j 1 i 'l 12 L sm j j

i Number { -(UClear MI Radiological Connois Departmental Procedure 6610-PLN-4200.01 True n vision ta Offsite Dose Calculation Manual (ODCM) 7 1 -l 1.0 LIQUID EFFLUENT MONITORS 1.1 TMl-1 and TMI-2 Liquid Radiation Monitor Set Points t The liquid effluent off-line monitors are set such that the concentration (s) of radionuclides in the liquid effluents will not exceed ten times the concentrations specified in 10 CFR 20 Appendix B Table 2, Col 2. Table 1.1 lists the Liquid Effluent Release Points and their parameters: Figure 1.1 provides a Liquid Release Pathway Diagram. To meet the above limit, the alarm / trip set points for liquid effluent monitors and flow measuring devices are set in accordance with the following equation: c

f,< C (eq 1.1) _

F+f where: l C= ten times the effluent concentration of 10 CFR 20 for the site, in pCi/mL l c= the set point, in Cl/ml, of the liquid effluent monitor measuring the radioactivity concentration in the effluent line prior to dilution and release. The set point is inversely l proportional to the maximum volumetric flow of the effluent line and proportional to the e minimal volumetric flow of the dilution stream plus the effluent stream. The alert set point value is set to ensure that advance waming occurs prior to exceeding any limits. The high i alarm set point value is such that if it were exceeded, it would result in concentrations exceeding ten times the 10 CFR 20 concentrations for the unrestricted area. t= flow set point as measured at the radiation monitor location, in vo'ume per unit time, but in the same units as F below. Discharge flow ranges and flow recorder designations are listed in Table 1.1. F= flow rate of dilution water measured prior to the release point, in volume per unit time. On site dilution minimal flows are listed in Table *.1. The set point concentration is reduced such that cor. centration contributions from multiple release points would not combine to exceed ten times 10 CFR 20 concentrations. The set point d concentration is converted to set point scale units using appropriate radiation monitor calibration factors. This section of the ODCM is implemented by the Radiation Monitor System Set Points procedure and, for batch releases, the Releasing Radioactive Uguid Waste procedure. 13.0 mi,

Number - AUClear i Radidogical Contds Departmental Prccedure 6610-PLN-4200.01 l Title Revision No. l Offsite Dose Calculation Manual (ODCM) 7 A f 1.2 TMI Licuid Effir nt Release Points and Liauld Radiation Monitor Data TMI-1 has two required liquid radiation monitors. These are RM-L6 and RM-L12.- These liquid release point radiation monitors and sample points are shown in Table 1.': (The TMI outfall radiation monitor, RM-L7, is also listed for information only.) l TMI-2 does not have any required liquid radiation monitors, but does utilizo RM-L12, and RM-L7 for release of non-accident water. TMI-2 does not release any processed water to the environment. i 1.2.1 RM-L6 RM-L6 is an off-line system, monitoring radioactive batch discharges from the TMI-1 liquid radwaste system (see Figure 1.1). These batch releases are sampled and analyzed per site procedures prior to release. The release rate is based on releasing one of twc Waste Evaporator Condensate Storage Tanks (WECST) at a flow which will add less than 10%, of i ten times the 10 CFR 20 concentrations to radionuclide concentrations in the unrestricted f area, including conservative default values for Sr-89, Sr-90, and Fe-55. { The release flow rate used is the most restrictive of threr flow rates calculated for each liquid j batch release, per the approved plant procedure. l i Three Dilution Factors (DF) are calculated to ultimately :.;culate the batch release flow rate. i These three DF's are calculated to: 1) insure each radionuclide released to the unrestricted i area is less than 10 percent of ten times the 10CFR20 radionuclide concentrations,2) ensure each liquid batch release boron concentration to the river will not exceed 0.7 ppm, and 3), ensure ten times the 10CFR20 concentration for Cesium-137 (1E-5 pCifml) will not be - exceeded based on the calculated high alarm set point and the expected response of RM-L6 to this concentration of Cs-137. l 1 The maximum release f;c~ rate is then calculated by dividing the ut restriptive (largest) DF into 90 percent of the current dilution flow rate of the Mechanm Draft Cooling Tower (MDCT). This conservative flow rate is then multiplied by 0.9 for tht allowable flow rate. j Calculation of 10 percent 10% of ten times the 10CFR20 concentration DF: DF, = z (SA,) + (10% of ten times the 10CFR20 concentration) SA = Specific Activity of each identified radionuclide i Calculation of Baron DF: l l DF, = Actual Tank Doron Concentration + 0.7. f Calculatior d Cs-137 Limit: l DF = HNh Marm Set Point + (IE-5 pCl/mi

7.16E7 cpm per pCi/mi) 3 Maximum release flow rate calculation:

Max Flow = [(MDCT flow gpm

0.9) + (Most Restrictive DF)]
0.9 t

i 14 0 nm. ) I

Number i bdeM TMl Radiological Controls ) Departmental Procedure 6610-PLN-4200.01 1 Title Revnion No. i Offsite Dose Calculation Manual (ODCM) 7 The dilution flow rate used is the current f!ow rate at the site. The minimum dilution flow rate is 5000 gpm per the TMI-1 FSAR. This ensures this batch release will meet the fo!!owing equation. l , _ 0.10, (eq 1.2) l I(C /X,) 3 where: Ci = diluted concentration of the i* radiort clide, i X= Ten times the concentration for that radionuclide in the unrestricted area 3 (10 CFR 20, App. B, Table 2, Col. 2). A value of 3E-3 pCi/mi for dissolved i and entrained nob!e gases shall be used. The set points for RM-L6 are set for each release based on the monitor response to each i radionuclide identified in the gamma scan sample results as follows: (1.5)* [Ei (pCi/cc),*(CPM /pCl/cc),] + (CPM,gg) = ALERT CPM j (2.0)* [El (pCi/cc), (CPM /pCi/cc),] + (CPfA,go) = WM MW @M i where: (pCl/cc), = positively identified radionuclides (CPM /pCl/cc), = RM-L6 sensitivity to radionuclide L l (CPMBKo)= RM-L6 background prior to batch release A high alarm on RM L6 will close valve WOL-V-257 and terminate any WECST releases to the environment. 4 1.2.2 RM-L12 I r RM-L12 is an off-line system, monitoring per%dic combined relm

from the Industrial j

Waste Treatment System / industrial Waste Filt Sn System (IWTS/.NFS). The input to i IWTS/lWFS originates in TMl-2 sumps, (see Figures 1.1 and 1.2) and the TMl-1 Turbine J Building sump (see Figure 1.1). The set points are based on the maximum release rate from l l both IWTS and (WFS simultaneously, (see Figure 1.1) a minimum dilution flow rate, and 50% l of ten times the 10CFR20 concentration for Cs-137, which is the most limiting radionuclide at a concentration of 1E-5 pCl/ml. These inputs are used in equation 1.1 to determine the l { RM-L12 High Alarm set point for all radionuclides being released. The minimum dilution flow l rate required per plant procedures during an IWTS/FS release is 10,000 gpm. A high alarm i on RM-L12 will close IWTS and IWFS release valves and trip release pumps to stop the release. 1.2.3 RM-L10 RM-L10 was a Nat detector submerged in the TMI-1 Turbine Building Sump. This detector l has been removed from service. l l 1 I 1 15.0 n n, l

i Numbor j '(UClear mi Radi i 9 ai connois i 1 Departmental Procedure 6610-PLN-4200.01 j Tm. nevision no. Offsite Dose Calculation Manual (ODCM) 7 i 1.2.4 RM-L7 RM-L7 is not a Tech. Spec. required liquid radiation monitor. RM-L7 is an off-line system, monitoring the TMINS outfall to the Susquehanna River (see Figures 1.1 and 1.2). RM-L7 has an associated proportional to flow compositor which ts used to collect composite r sampfes. This monitor is the final radiation monitor for TMI-1 and TMI-2 normal liquid effluent releases. I t i ( i k .l i t u h P 16.0 j u n. i -i

t Numbor (UClear mi R did gi ai Contres Departmental Procedure 6610-PLN-4200.01 Titie Revision No. l i Offsite Dose Calculation Manual (ODCM) 7' 1.3 Control of Liquid Releases l TMI liquid effluent releases are contro!!ed to less than ten times the 10CFR20 concentrations by limiting the percentage of this limit allowable from the two TMl liquid release points. RM-L6, and effluent sampling, limits batch releases to less than or equal to 10% for all radionuclides, and RM-L12. and effluent sampling, limits _ releases from TMI-1 and TMI-2 to less than or equal to 50% for Cs-137. These radiation monitor set points also include built in meter error factors to further ensure that TMI l liquid effluent re. eases are less than ten times the 10CFR20 concentrations to the environment. I The radioactivity content of each batch of radioactive liquid waste is determined prior to release by f sampling and analysis in accordance with TMI-1 Tech. Spec. Table 4.22-1. The results of pre-release analyses are used with the calculational methods in Section 1.1, to assure that the concentration at i the point of release is mcintained within the TMI-1 Tech. Spec. Section 3.22.1.1. Post-release analysis of samples composited from batch releases are performed in accordance with TMl-1 Tech. Spec. Table 4.22-1. The results of the previous post-release analysis shall be used with t the calculational methods in the ODCM to assure that the concentrations at the point of release were maintained within the TMI-1 Tech. Spec. Section 3.22.1.1. The radioactMty concentration of liquids discharged from continuous release points are determined by co!!ection and analysis of samples in accordance with TMI-1 Tech. Spec. Table 4.22-1. The results of the analysis are used with the calculational methods of the ODCM to assure that the concentration at the point of release is maintained within the TMI-1 Tech. Spec. Section 3.22.1.1. l t t i I i 17.0 sm. i

i Number - bdear TMI Radiological Controls { Departmental Procedure 6610-PLN-4200.01 t Tstle Revision No. i Offsite Dose Calculation Manual (ODCM) 7 l TABL8I 1.1 I TMI Liquid Release Point and Liquid Radiation Monitor Data i LIQUID (f) (F) (FR) (DF) RELEASE l LIQUID RELEASE DISCHARGE RADIATION TERMINATION 3 RADIATION POINT FLOW GPM ON SITE RNER FLOW NEAR FIELD MONITOR INTERLOCK MONITOR (Maximum (FLOW DILUTION RATE GPM DILUTION SENSITMTY (YES/NO) (DETECTOR) LOCATION Volume) RECORDER) GPM (Range) FACTOR (CPM /pCi/cc) VALVES r > = 5.000 YES (FT.t a6) WDL V257 l 281' Elevation WECST Batch Minimum l RM-L8 TML1 Auxihary Releases o-30 gpm flow per 2E7 AVE. Cs 137 l (Nal) Bldg (8000 gal.) (FT-84) FSAR (14E6 5.4E8) 5 7.16E7 j Station YES Discharge WDL-V257 'I RM-L7 TMi-1 and

WDL R-1311 (Nal)

South end of TMi 2 > = 5,000 2E7 AVE. Cs 137 TM11 MDCT Non AGW (FT-140) N.A. (1.4ES-5.4E8) 5 7.10E7 t YES IWTS/lWFS L131 IW V73, Contiruous o 200 gpm 4E8 IW-P16,17,18 Releases (FT-342)/ RM-L12 IWFS Building (300,000/ 0-100 gpm > = 10,000 2E7 AVE. Cs-137 '!W-V279, l (Naf) NW Comer 80,000 gni.) (FT 373) (FT 140) (1.4ES-5.4E8) 5 3E8 IW-P29,30

WDL-R 1311 has been flanged off as a T Ml 2 liquid outfall.

"RM-L7 is not a Tech. Spec. required liquid radiation monitor. i 4 d j f l i t i I i k 18.0 I nm. I

Number (EleM Tui R di i gi i Controls Departmental Procedure - 6610-PLN-4200.01 Title Revisiori No. Offsite Dose Calculation Manual (ODCM) 7 TABLE 1.2 TMI-2 Sump Capacities .i Total - Capacity Gations Sump Gallons perinch Turbine Building Sump 1346 22.43 3 ) Circulating Water Pump House Sump 572 10.59 - - Control Building Area Sump 718 9.96 7 l Tendon Access Galley Sump 538 9.96 Control to Service Building Sump 1346 22.43 Contaminated Drain Tank Room Sump 135 3.80 Chlorinator House Sump Water Treatment Sump" - 1615 22.43 Air intake Tunnel Normal Sump 700 Air intake Tunnel Emergency Sump 100000 766.00 Condensate Polisher Sump

2617 62.31 Studge Collection Sump" 1106 26.33 Heater Drain Sump Solid Waste Staging Facility Sump 1476 24.00 Auxiliary Building Sump 10102 202.00 Decay Heat Vault Sump 479 10.00 Building Spray Vault Sump 479 10.00 l

i Condensate Polisher Sump is deactivated and in PDMS cundition. The Water Treatment and Sludge Collection Sumps will be deactivated for PDMS. f l 19.0 j mm, j

Figure 1.1 g j,m*g,osito ({t) Radiation Monitor p TMl-1 Liquid Effluent Pathways as nadwa s Sample Fyf Disposal Pre-Operation Auxiliary Powdex Solids Graver Chemical Cleaning Boiler Vessels System r Basins (2) Blow down m i M SB00iesel SB0Dbsel TM!-2 i SEPA SupB SumDs Intermediate

l m

Building intermediate l S $,d",*',$*' o b Building Sump Turbine East Collection < ,r Build.ing 4 sump Intermediate Sump industrial v i wasto Building Sump r#I Treatrnont g N l Preeam Wa TMl-1 Y#'* f Condensate,_ j and TMl-2 Tane ,rO S%T

'*)

E L s i Effluent Co T1B Main Pumping ,r St^U "S -+bollection nk) N Secondary Waste Waste 3 Sump Plant Evaporator . Evaporator SeWa9eIfeatment w" d " * * ' ' " ' Condensatt Condensatt Neutralizer aste yg Storage Storage Tank Plant

"tratgn gg Tank A Tank B 8g Solids

~t m 4 fiIGI ,r y Component Mechanical Draft T Cooling Cooling Tower S ~* Water TMI-1 TMI-1

RIVER E

j 6610-PLN-4200.01 ) FIGURE 1.3 Revision 7 TMI-2 Liquid Effluent Pathways ( ) CONTROL CONTROL & J BUILDING E4 SERVICE SUMP AREA SUMP 'I i i TURBINE TENDON BUILDING ACCESS SUMP GALLERY SUMP t b IWTS SUMP 1 1 INDUSTRIAL WASTE TREATMENT SYSTEM v R ML-12 r v C RML-7 C - COMPOSITE SAMPLER i y i [ 21.0 ,m, i i

Numt>tr -gdgg_ TMl Radiological Controls Departmental Procedure 6610-PLN-4200.01 Tette Revision No. Offsite Dose Calculation Manual (ODCM) 3 i i 2.0 LIQUID EFFLUENT DOSE ASSESSMENT 2.1 Liquid Effluents 10 CFR 50 Appendix i The dose from liquid effluents results from the consumption of fish and drinking water. The location of the nearest potable water intake is PP&L Brunner Island Steam Electric Station located downstream of TML The use of the flow of the Susquehanna River as the dilution flow is justified based on the complete mixing in the river prior to the first potable water supply, adequately demonstrated by fiume tracer die stuoles and additionalliquid effluent release studies conducted l using actual TMI-1 tritium releases. Other pathways contribute negligibly at Three Mile Island. The dose contribution from all radionuclides in liquid effluents released to the unrestricted area is calculated using the following expression; AF,3 X X (eq 2.1} I Dose j = (b t) X ( C,) X A W,3 X + i where: Dose j = the cumulative dose commitment to the total body or any organ, j, from the liquid effluents for the total time period, in mrem. l At = the length of the time period of actual releases, over which C, and f are averaged for all l liquid releases, in hours. C, = the average concentration of radionuclide, i, in undiluted liquid effluent during time f period at from any liquid release, in pCl/ml. j NOTE For Fe-55, Sr-89, Sr-90, prior to batch releases conservative concentration values will be used in the initial dose calculation based i on similar past plant conditions. LLD values are not used in dose calculations. t f= undiluted liquid waste flow, in gpm. 4 FD = plant dilution water flowrate during the period of release, in gpm FR = actual river flowrate during the period of release or average river flowrate for the month ~ the release is occurring, in gpm. DF = dilution factor as a result of mixing effects in the near field of the discharge structure of 0.2 (Reg. Guide 1.109, Rev.1, Table A-2) or taken to be 5 based on the inverse of 0.2. AW, and AF, = the site-related ingestion dose commitment factor to the total body od any organ, j, for I each identified principle gamma and beta emitter, in mrem /hr per pCl/ml. AW is the factor for the waMr pathway and AF is the factor for the fish pathway. I 22.0 mu i

r h Number gggy . TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 r Tatie Revision No. q

t Offsite Dose Calculation Manual (ODCM) 3-Values for AW, are determined by the following equation:

AW, = (1.14E5) x (U,) x (DF,) (eq 2.2) where: 1.14E5 = (1.0E6 pCi/pCI) x (1.0E3 ml/kg) + (8760 hr/yr) f U, = Water consumption rate for adult is 730 kg/yr (Reg. Guide 1.109, Rev.1). i DF, - ingestion dose conversion factor for radionuclide,1, for adults total body and for Vorst case" organ, J, in mrem /pCl, from Table 2.1 (Reg. Guide 1.109) Values for AF, are determined by the following equation: AF, = (1.14E5) x (U,) x (DF) x (BF) (eq 2.2.2) +.1ere: 1... a = defined above U, = adult fish consumption, assumed to be 21 kg/yr (Reg. Guide 1.109, Rev.1). DF,= ingestion dose conversion factor for radionuclide, l. for adult total body and for " worst case" organ, J, in mrem /pCl, from Table 2.1 (Reg. Guide 1.109, Rev.1). BF,= Bioaccumulation factor for radionuclide, i, in fish, in pCi/kg per pCl/L from Table 2.2 (Reg. Guide 1.109, Rev.1). 5 T i I i l l 23.0 mm,

J NumbIf gggp TMI Radiological Controls I Departmental Procedure 6610-PLN-4200.01 Title Revsson No. l Offsite Dose Calculation Manual (ODCM) 4 l 2.2 TMI-1 Liauid Radwaste System Dose Cales Once/ Month TMI-1 Tech. Spec. Section 3.22,1.3 requires that appropriate portions of the liquid radwaste treatment system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the monthly projected doses due to the liquid effluent releases from each unit to unrestricted areas would exceed 0.06 mrem to the total body or 0.2 mrem to any organ in any calendar month. The following calculational method is provided for performing this dose projection. At least once per month, the total dose from all liquid releases for the quarter-to< fate will be divided by the number of days into the quarter and multiplied by 31. Also, this dose projection shall include the estimated dose due to any anticipated unusual releases during the period for which the i projection is made. If this projected dose exceeds 0.06 mrem total body or 0.2 mrem any organ, appropriate portions of the Liquid Radwaste Treatment System, as defined in Section 3.1, shall be used to reduce radioactMty levels prior to release. (This section does not apply to TMI-2.) s 1 L t i 9 V t 24.0 nm,

Number [r g J1 Nuclear Radiaogicai connas Departmental Procedure 6610-PLN-4200.01 j Titie Revision No. Offsite Doso Calculation Manual (ODCM) 3 2.3 Alternative Liquid Dose Calculational Methodology As an alternative, models in, or based upon, those presented in Regulatory Guide 1.109 (Rev.1) may be used to make a comprehensive dose assessment. Default parameter values from Reg. Guide 1.109 (Rev.1) and/or actual site specific data are used where applicable. As an alternative dose calculational methodology GPU Nuclear calculates doses using SEEDS (simplified environmental effluent dosimetry system). The onsite and SEEDS calculational rnodels use actual liquid release data with actual monthly Susquehanna River flow data to assess the dispersion of effluents in the river. l 1 ) 25 0 n n,

I Number j Nuclear ' "adi*9'a' co"t'* i Departmental Procedure 6610-PLN-4200.01 l Tdie Revision No. l Offsite Dose Calculation Manual (ODCM) 3 TABLE 2.1 i Liquid Dose Conversion Factors (DCF): DF, f Page 1 of 3 Ingestion Dose Factors for Adults

j (MREM Per PCI Ingested) j NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI t

H 3 NO DATA 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 - 1.05E-07 C 14 2.84 E-06 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E47 5.68E-07 NA 24 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E46 CR 51 NO DATA NO DATA 2.66E49 1.59E 09 5.86E-10 3.53E49 6.69E 07 MN 54 NO DATA 4.57E-06 8.72E-07 NO DATA 1.36E-06 NO DATA 1.40E-05 MN 56 NO DATA 1.15E-07 2.04 E-08 NO DATA 1.46E-07 NO DATA 3.67E46 l FE 55 2.75E-06 1.90E-06 4.43E-07 NO DATA NO DATA 1.06E-06 1.09E-06 ) FE 59 4.34E-06 1.02E-05 3.91 E-06 NO DATA NO DATA 2.85E-06 3.40E-05 CO 58 NO DATA 7.45E-07 1.67E-06 NO DATA NO DATA NO DATA 1.51E45 CO 60 NO DATA 2.14E-06 4.72E46 NO DATA NO DATA NO DATA 4.02E-05 NI 63 1.30E-04 9.01E46 4.36E-06 NO DATA NO DATA NO DATA 1.88E-06 NI 65 5.28E-07 6.86E-08 3.13E48 NO DATA NO DATA NO DATA 1,74E-06 CU 64 NO DATA 8.33E48 3.91 E-08 NO DATA 2.10E-07 NO DATA 7.10E-06 ZN 65 4.84E-06 1.54E-05 6.96E-06 NO DATA 1.03E-05 NO DATA 9.70E-06 ZN 69 1.03E48 1.97E 08 1.37E-09 NO DATA 1.28E 08 NO DATA 2.96E-09 BR 83 NO DATA NO DATA 4.02E-08 NO DATA NO DATA NO DATA 5.79E-08 BR 84 NO DATA NO DATA 5.21 E-08 NO DATA NO DATA NO DATA 4.09E-13 BR 85 NO DATA NO DATA 2.14E-09 NO DATA NO DATA NO DATA LT E-24 RB 86 NO DATA 2.11E45 9.83E46 NO DATA NO DATA NO DATA 4.16E-06 RB 88 NO DATA 6.05E-08 3.21 E-08 NO DATA NO DATA NO DATA 8.36E-19 i RS 89 NO DATA 4.01 E-08 2.82E-08 NO DATA NO DATA NO DATA 2.33E-21 SR 89 3.08E-04 NO DATA 8.84E-06 NO DATA ' NO DATA NO DATA 4.94E-05 SR 90 7.58E43 NO DATA 1.86E43 NO DATA NO DATA NO DATA 2.19E44 SR 91 5.67E 06 NO DATA 2.29E-07 NO DATA NO DATA NO DATA 2.70E SR 92 2.15E-06 NO DATA 9.30E-08 NO DATA .40 DATA NO DATA 4.26E-05 Y 90 9 G2E-09 NO DATA 2.58E-10 NO DATA NO DATA NO DATA 1.02E-04 26.0 m

Numbor Nuclear '" dd *a'o "t'd$ i Departmental Procedure 6610-PLN-4200.01 j . Title Revision No. Offsite Dose Calculation Manual (ODCM) 3 TABLE 2.1 (Cont'd) l Liquid Dose Conversion Factors (DCF): DF, P Page 2 of 3 Ingestion Dose Factors for Adults

i (MREM Per PCI Ingested)

NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LU 0 Y 91M 9.09E-11 NO DATA 3.52E-12 NO DATA NO DATA NO DATA 2.67E-10 i V 91 1.41 E-07 NO DATA 3.77E-09 NO DATA NO DATA NO DATA 7.76E-05 l Y 92 8.45E 10 NO DATA 2.47611 NO DATA NO DATA NO DATA 1.48E-05 Y 93 2.68E-09 NO DATA 7.40E-11 NO DATA NO DATA NO DATA - 8.50E-05 ZR 95 3.04E-08 9.75E-09 6.60E-09 NO DATA 1.53E-08 NO DATA 3.09E-05 ZR 97 1.68E-09 3.39E-10 1.55E-10 NO DATA 5.12E-10 NO DATA 1.05E-04 NB 95 6.22E-09 3.46E-09 1.86E-09 NO DATA 3.42E-09 NO DATA 2.10E-05 MO 99 NO DATA 4.31 E-06 8.20E-07 NO DATA 9.76E-06 NO DATA 9.99E-06 TC 99M 2.47E-10 6.98E-10 8.89E-09 NO DATA 1.06E-08 ' 3.42E-10 4.13E-07 TC 101 2.54E-10 3.66E-10 3.59E-09 NO DATA 6.59E-09 1.87E-10 1.10E-21 RU 103 1.85E-07 NO DATA 7.97E-08 NO DATA 7.06E-07 NO DATA 2.16E-05 RU 105 1.54E-08 NO DATA 6.08E-09 NO DATA 1.99E47 NO DATA 9.42E-06 l RU 106 2.75E-06 NO DATA 3.48E-07 NO DATA 5.31 E-06 NO DATA 1.78E-04 AG 110M 1.60E47 1.48E-07 8.79E-08 NO DATA 2.91E47 NO DATA 6.04E-05 SB 125 1.79E-06 2.00E-08 4.26E-07 1.82E-09 0.0 1.38E-06 1.97E-05 TE 125M 2.68E46 9.71 E-07 3.59E-07 8.06E-07 1.09E-05 NO DATA 1.07E-05 i TE 127M 6.77E-06 2.42E-06 8.25E-07 1.73E46 2.75E-05 NO DATA 2.27E-05 TE 127 1.10E-07 3.95E-08 2.38E-08 8.15E-08 4.48E-07 NO DATA 8.68E-06 TE 129M 1.15E45 4.29E-06 1.82E-06 3.95E-06 4.80ti-05 NO DATA 5.79E-05 TE 129 3.14E-08 1.18E-08 7.65E-09 2.41 E-08 1.32E-07 NO DATA 2.37E-08 TE 131M 1.73E-06 8.46E-07 7.05E-07 1.34E-06 8.57E-06 NO DATA 8.40E-05 TE 131 1.97E-08 8.23E-09 6.?2E-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 NO DATA 7.71E-05 i i 130 7.56E-07 2.23E-06 8.80E-07 1.89E-04 3.48E46 NO DATA 1.92E-06 1 131 4.16E-06 5.95E-06 3.41 E-06 1.95E-03 1.02E-05 NO DATA 1.57E-06 l 132 2.03E-07 5.43E-07 1.90E 07 1.90E-05 8.65E-07 NO DATA 1.02E-07 l 133 1.42E-06 2.47E-06 7.53E-07 3.63E-04 4.31 E-06 NO DATA 2.22E-06 1 134 1.06E-07 2.88E-07 1.03E-07 4.99E 06 4.58E-07 NO DATA 2.51 E-10 l 27.0 mu

Numb $r NUCISar TMI Radiological Controls Departmental procedure 6610-PLN-4200.01 Title Revision No. Offsite Dose Calculation Manual (ODCM) 3 i TABLE 2.1 - (Cont'd) Liquid Dose Conversion Factors (DCF): DF, l Page 3 of 3 Ingestion Dose Factors for Adults

t (MREM Per PCI Ingested) i NUCUDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI i

t i 135 4.43E-07 1.16E-06 4.28E-07 7.65E-05 1.86E-06 NO DATA 1.31E-06 CS 134 6.22E-05 1.48E-04 1.21 E-04 NO DATA 4.79E45 1.59E-05 2.59E-06 CS 136 6.51 E-06 2.57E-05 1.85E-05 NO DATA 1.43E-05 1.96E-06 2.92E-06 CS 137 7.97E-05 1.09E-04 7.14E-05 NO DATA 3.70E45 1.23E-05 2.11E-06 CS 138 5.52E-08 1.09E-07 5.40E-08 NO DATA 8.01 E-08 7.91E-09 4.65E-13 BA 139 9.70E-08 6.91 E-11 2.84E-09 NO DATA 6.46E-11 3.92E-11 1.72E BA 140 2.03E-05 2.55EO8 1.33E-06 NO DATA 8.67E-09 1.46E-08 4.18E45 i BA 141 4.71E 08 3.56E-11 1.59E-09 NO DATA 3.31E 11 2.02E-11 2.22E-17 BA 142 2.13E-08 2.19E-11 1.34E-09 NO DATA 1.85E-11 1.24E-11 3.00E-26 LA 140 2.50E-09 1.26E-09 3.33E-10 NO DATA NO DATA NO DATA 9.25E-05 ' LA 142 1.28E-10 5.82E-11 1.45E-11 NO DATA NO DATA NO DATA 4.25E-07 CE 141 9.36E-09 6.33E-09 7.18E-10 NO DATA 2.94E-09 NO DATA 2.42E-05 CE 143 1.65E-09 1.22E-06 1.35E-10 NO DATA 5.37E-10 NO DATA 4.56E-05 CE 144 4.88E-07 2.04E-07 2.62E-08 NO DATA 1.21E47 NO DATA 1.65E-04 PR 143 9.20E-09 3.69E-09 4.56E-10 NO DATA 2.13E-09 NO DATA 4.03E-05 l PR 144 3.01 E-11 1.25E-11 1.53E-12 NO DATA 7.05E 12 NO DATA 4.33E-18 ND 147 6.29E-09 7.27E-09 4.35E-10 NO DATA 4.25E-09 NO DATA 3.49E-05 W 187 1.03E-07 8.61 E-08 3.01 E-08 NO DATA NO DATA NO DATA 2.82E-05, NP 239 1.19E-09 1.17E-10 6.45E-11 NO DATA 3 65E-10 NO DATA 2.40E-05 Dose factors of internal exposure are for continuous intake over a one-year period and include the dose j commitment over a 50-year period; from Reg. Guide 1.109 (Rev.1). Additional dose factors for nuclides not included in this table may be obtained from NUREG-0172. 28.0 mu

'l Numt>2r l gdgy TMI Radiological Controls Departmental Precedure 6610-PLN-4200.01 i Tstie Revision No. Offsite Dose Calculation Manual (ODCM) l 3 l TABLE 2.2 Bioaccumulation Factors, BF, f Bioaccumulation Factors to be Used in the Absence of Site-Specific Data * (pCl/kg per pCl/ liter) FRESHWATER ELEMENT FISH INVERTEBRATE i H 9.0E-01 9.0E41 C 4.6E 4 03 9.1 E + 03 l NA 1.0E + 02 2.0E + 02 CR 2.0E + 02 2.0E + 03 i MN 4.0E + 02 9.0E + 04 ) FE 1.0E + 02 3.2E + 03 C0 5.0E + 01 2.0E + 02 l NI 1.0E + 02 1.0E + O2 l CU 5.0E + 01 4.0E + 02 1 ZN 2.0E + 03 1.0E + 04 BR 4.2E + 02 3.3E + 02 RB 2.0E + 03 1.0E + 03 SR 3.0E+01 1.0E + 02 I Y 2.5E + 01 1.0E + 03 l ZR 3.3E + 00 6.7E + 00 i NB 3.0E + 04 1.0E + O2 l MO 1.0E + 01 1.0E + 01 j TC 1.5E + 01 5.0E+00 RU 1.0E + 01 3.0E + 02 i RH 1.0E + 01 3.0E + 02 I

SB 1.0E + 00 1.0E + 00 TE 4.0E + 02 6.1 E + 03 i

i 1.5E+01 5.0E+00 CS 2.0E + 03 1.0E + 03 BA 4.0E + 00 2.0E + O2 LA 2.5E + 01 1.0E + 03 CE 1.0E + 00 1.0E + 03 PR 2.5E + 01 1.0E + 03 ND 2.5E + 01 1.0E 4 03 1 W 1.2E + 03 1.0E + 01 NP 1.0E + 01 4.0E + 02 l Bioaccumulation factor values are taken from Reg. Guide 1.109 (Rev.1), Table A-1j. Sb bioaccumulation factor value is taken from EPRI NP-3840. '.1 29.0 nn.

Numbst gggp TMl Radiological Controls Departmental Procedure 6610-PLN-4200.01 . Title Revision No. Offsite Dose Calculation Manual (ODCM) 7 3.0 TMi LlOUID EFFLUENT WASTE TREATMENT SYSTEMS 3.1 TMI-1 Liauid Effluent Waste Treatment System 3.1.1 Description of the Liquid Radioactive Waste Treatment System (see Figure 3.1) Reactor Coolant Train a. Water Sources - (3) Reactor Coolant Bleed Tanks (RCBT) - (1) Reactor Coolant Drain Tank (RCDT) b. Liquid Processing - Reactor Coolant Waste Evaporator (see Figure 3.2) - Demineralizers prior to release c. Liquid Effluent for Release - (2) Waste Evaporator Condensate Storage Tanks (WECST) d. Dilution - Mechanical Draft Cooling Tower (0-38k gpm) - River Flow (2E7 gpm average) Misce!!aneous Waste Train a. Water sources: Auxiliary Building Sump - Reactor Building Sump - Misco!!aneous Waste Storage Tank l - Laundry Waste Storage Tank - Neutralizer Mixing Tank - Neutralizer Feed Tank - ] - Used Precoat Tank - Borated Water Tank Tunnel Sump - Heat Exchanger Vault Sump i - Tendon Access Galley Sump - Spent Fuel Pool Room Sump b. Liquid Processing - Miscellaneous Waste Evaporator, MWE (see Figure 3.2) - Demineralizers prior to release c. Uquid Effluent for Release - (2) Waste Evaporator Condensate Storage Tanks (WECST) d. Dilution - Mechanical Draft Cooting Tower (0-38k gpm) River Flow (2E7 gpm average) e 30 0 sm, 1

Mumtor IUClear m nadid gi at Contres Departmental Procedure 6610-PLN-4200.01 Im. mason No. Offsite Dose Calculation Manual (ODCM) 7 "l 3.2 Operability of the TMI-1 Llauid Effluent Waste Treatment System j 3.2.1 The TMl-1 Liquid Waste Treatment System as described in Section 11 of the TMI-1 Final Safety Analysis Report is considered to be operable when one of each of the following pieces of equipment is available to perform its intended function: j a) Miscellaneous Waste Evaporator (WDL-Z18) or Reactor Coolant Evaporator (WDL-Z1A) i I b) Waste Evaporator Condensate Domineralizer (WDL-K3 A or B) } c) Waste Evaporator Condensate Storage Tank (WDL-T 11 A or B) d) Evaporator Condensate Pumps (WDL-P 14 A or B) 'l 3.2.2 TMI-1 Representative Sampling Prior to Discharge All liquid releases from the TMI-1 Liquid Waste Treatment System are made through the j Waste Evaporator Condensate Storage Tanks. To provide thorough mixing and a representative sample, the contents of the tank are recirculated using one of the Waste - i Evaporator Condensate Transfer Pumps. l 3.3 TMI-2 Llauid Effluent Waste Treatment System 3.3.1 Description of the TMI-2 Liquid Radioactive Waste Treatment System The TMI-2 Liquid Radioactive Waste Treatment System has been out of service since the TMI-2 Accident in 1979. TMI-2, however, releases water from various sumps and tanks to i the river (see Figures 1.1 and 1.2). This process is governed by plant procedures that encompass proper sampling, sample analysis, and radiation monitoring techniques. i i e b I i k t b 31.0 ma v

Numt:Or (UCIO8r TMI Radiological ControIS Departmental procedure 6610-PLN-4200.01 Title Nwslon No. Offsite Dose Calculation Manual (ODCM) 3 FIGURE 3.1 TMI-1 Liquid Radwaste RC BwST SUMP onAgg r l RE ACTOR l S.F. SUMP d MAKE ,8 LOG SUMP, TENDON BORIC ACID 7 RC DRAIN UF c^atY s,,,t, uix TANK TK ,oRv TANK l A I SAFTY _ MISC. ORAIN MU-V8 ' AUX BLDG & RELIEF r LJ LI.J _ VALVES sum 9 U t f If f IfI'I'l' dL MISC..vASTE RC BLEED AC BLEED RC BLEED STORACE TK TK A TK s TK C I I I I MISC. WASTE bb h h h TRANSFER PUMPSi i, i, TR SF M MM 3 \\ c bFQTER N I i LTER y V3 CE (1 OF 21 11 OF 26 f 6 t e e MISC. wAETE RC WASTg Dt%TILLAM 06TILLATE I l V JL j II CONCENTRATED Rf CLAIME D WASTE STORACE TK M AUX n SORIC ACID TK (1 DF 23 STE M (1 OF 21 1 I CONCENTRATED h b BORIC ACID RADWAKTE PUM% f RECYCLE PU HITTMAN EMERGANCY BORAtlON SOLIDIFICATION DOWNSTR E AM MU-V8 SYSTEM CONDENSATE DEMIN WASTE EV AP. It OF 26 MECHANICAL DRAFT CONDENSATE I COOLING TOWER

STORAGE TK EFFLUENT n oF m DEMINERALIZED RECLAIMED W ATE R h

EVAP. W ATE R (FWTl STORAGE TK - CONDENSATE p PUMrs 1r REttof8E0 WATER SYSTU1 yg P 32.0 rm. P c

9 I 5e ? A o - g. T O N2 ~ CC' v "= ^ CONC. ~9( 6 C k ,;g - MATER FLUSH -~, g g SEPARATOR o

== _U s. g gr,)3-SFAL o q g g 4, o -> g a = WATER I wsce n CC bMER g MM ,,,i OtsT. y 'M _4 p) C 'j[ j O = CONCENTRATOR ~ DW O h a5 w [C4W'-P-h- '*C L E 3 YM e C g I" w m R m H g gg mOOP0ENSATE U S -52 C ' = ) E m i E o e g6. OUT T. F P i % m y D TM L .f F U j s R E A X 3 E U E

5 2I J

Y ? ~ ~r. - d, - 8 go 'O C a E G gy 4 hn d ' ] ' i-d '

5R H

REKCT A8 n 5~T '% ( eh) _ WASTE FfLL 1. m I hh C(, 1 -( y FEED TANK g g ',, lo x , e pu@ r-CJ Z seu o .c O 4

Number gdgy TMI Radiological Controts Departmental Procedure 6610-PLN-4200.01 'f 1stle Revision No. i Offsite Dose Calculation Manual (ODCM) 7 i 4.0 GASEOUS EFFLUENT MONITORS 4.1 TMI-1 Noble Gas Monitor Set Points The gaseous effluent monitor set points are established for each gaseous effluent radiation monitor to assure concentrations of radionuclides in gaseous effluents do not exceed the limits set forth in Technical Specification 3.22.2.1. Table 4.1 lists Gaseous Effluent Release Points and their associated { parameters; Figure 4.1 provides a Gaseous Effluent Reicase Pathway Diagram. t The set points are established to satisfy the more restrictive set point concentration in the following two equations: 500 > I(c)(F)(K,)(Dv) (eq 4.1.1) 3 i and 3000 > I(c,)(13 + 1.1 M,)(Dv)(F) (eg 4.1.2) i ( where: c, = set point concentration based on Xe-133 equivalent, in pCl/cc F= gaseous effluent flowrate at the monitor, in cc/sec (reference Table 4.1) j i 3 K,= total body dose factor, in mrem /yr per pCi/m from Table 4.3 Dv = highest sector annual average gaseous atmospheric dispersion factor (X/0) at or 3 beyond the unrestricted area boundary, in sec/m, from Table 4.4 for station vent i releases and Table 4.5 for all other releases, (Condenser off gas, ESF FHB, and ground 3 releases). Maximum values presently used are 7.17E-7 sec/m at sector NNE for 3 station vent, and 1.16E-5 sec/m at sectors N and WNW for all other releases. l 3 h= skin dose factor due to beta emissions from radionuclide i, in mrem /yr per Cl/m i from Table 4.3. j f 3 M, = air dose factor due to gamma emissions from radionuclide I, in mrad /yr per pCl/m from Table 4.3. 1.1 = rarem skin dose per mrad air dose. i 500 = annual whole body dose rate limit for unrestricted areas, in mrem /yr. l t 3000 = annual skin dose rate limit for unrestricted areas, in mrem /yr. The set point concentration is further reduced such that the concentration contributions from I multiple release points would not combine to exceed Tech. Spec. limits. The set point concentration is converted to set point scale units on each radiation monitor using i appropriate calibration factors. i 34.0 rme

i Number AUClear. I Radiological Controls j Departmental Procedure 6610-PLN-4200.01 j -me nevison No. ' Offsite Dose Calculation Manual (ODCM) 3 j This section of the ODCM is implemented by the Radiation Monhor System Set Points procedure and the procedure for Releasing Radioactive Gaseous Waste, i i i I i ? L f i t 4 P i t e i i i l r i i i 35.0 mi. t i I

l Nurtibor.

(UCIO8r M Radiological Controls Departmental Procedure 6610-PLN-4200.01 Tn!e Revaion No. 1 Offsite Dose Calculation Manual (ODCM) 7 i I 4.2 TMI-1 Particulate and Radiolodine Monitor Set Points Set points for monitors which detect radionuclides other than noble gases are also estabilshed to. assure that concentrations of these radionuclides in gaseous effluents do not exceed the limits j T.S. 3.22.2.1. Set points are established so as to satisfy the following equations: _j 1500 > I(c,)(F)(P)(Dv) (eg 4.2) 3 I wherc: c= set point concentration based on 1-131 equivalent, in pCl/cc i F= gaseous effluent flow rate at the monitor, in cc/sec (Table 4.1) 3 P= pathway dose parameter, in mrem /yr per pCl/m for the inhalation pathway from i Table 4.6. The dose factors are based on the actual individual organ and most l restrictive age group (child) (NUREG-0133). NOTE Appendix A contains P, calculational methodology. 1500 = annual dose rate limit to any organ from particulates and radiolodines and radionuclides (other than noble gases) with half lives greater than eight days in mrem /yr. I Dv = highest sector annual average gaseous dispersion factor (X/O or D/O) at or beyond the unrestricted area boundary from Table 4.4 for releases from the station vent and Table 4.5 for all other releases. X/O is used for the inhalation pathway. Maximum 3 values of X/O gresently used are 7.17E-7 sec/m for station vent, at sector SE, and 1.16E-5 sec/m for all other releases, at sectors N and WNW. The set point concentration is further reduced such that concentration contributions from multiple release points would not combine to exceed Tech. Spec. limits. l The set point concentration is converted to set point scale units on each radiation monitor using ) appropriate calibration factors. i l This section of the ODCM is implemented by the Radiation Monitor Systems Set Points procedure and the procedure for Releasing Radioactive Gaseous Waste. i 36.0 nn,

i l Mumtor - ,l g ggggy TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 l ~ Title Revision No. l l Offsite Dose Calculation Manual (ODCM) 7 4.3 TMI-2 Gaseous Radiation Monitor Set Points i TMl-2 Gaseous Radiation Monitors have their set points described in TMI Plant Procedure 1101-2.1. l Figure 4.5 provides a gaseous effluent release pathway diagram. Table 4.2 provides TMI-2 Radiation j Monitor Data. l P These set points are set in accordance with the Controis defineated in Part L of this ODCM. l l 3 [ i I lq l l 1 i I t 1 i ) t 1 4 I l i 37.0 nn, 2

Number (UCIO8r TMI Radiological Controls s Departmental Procedure 6610-PLN-4200,01 Tale Revision No. i Offsite Dose Calculation Manual (ODCM) 7 i 4.4 TMI-1 Gaseous Effluent Release Points and Gaseous Radiation Monitor Data TMI-1 has eleven (11) required effluent gaseous radiation monitors. These are RM-A4, RM-AS, RM-A15, RM-A6, RM-A7, RM-AB, RM-A9, RM-A14, ALC-RMI-18, WHP-RIT-1, and RLM-RM-1. These gaseous release points, radiation monitors, and sample points are shown in Table 4.1. 4.4.1 RM-A4/RM-A6 Fuel Handlino and Auxiliary Buildina Exhaust i RM-A4 is the particulate, radiolodine and gaseous radiation monitor for the TMI-1 Fuel Handling Building Ventliation (see Figures 4.1 and 4.2). RM-A6 is the particulate, radioiodine, and gaseous radiation monitor for the TMI-1 Auxiliary Building Ventilation (see j Figures 4.1 and 4.2). High alarms on RM-A4 or RM-A6 noble gas channels will initiate shutdown of the related building ventilation air supply system. These two radiation monitors l concurrently will satisfy requirements for the Station Vent release point in place of RM-A8-4.4.2 RM-A8 Station Ventilation Exhaust RM-A8 is the particulate, radioiodine and gaseous radiation monitor for the TMl-1 Station - Ventilation (see Figures 4.1 and 4.2). This in plant effluent radiation monitor also has an associated sampling panel with sampling lines located before the sample filters. High alarm on RM-A8 noble gas low channel will initiate shutdown of the Station Ventilation air supply systems. (The Fuel Handling and Auxiliary Building Ventilation). This radiation monitor satisfies requirements for the Station Vent release point in place of RM-A4 and RM-A6. 4.4.3 RM-A5/RM.A15 Condenser Off Gas Exhaust f RM-A5 is the gaseous radiation monitor for the TMI-1 Condenser Off Gas exhaust (see Figures 4.1 and 4.4). RM-A15 is the back up gaseous radiation monitor for the TMI-1 Condenser Off Gas exhaust (see Figures 4.1 and 4.4). High alarms on RM-A5 low channel or RM-A15 noble gas channels will initiate the MAP-5 Radiciodine Processor Station. These i two radiation monhors together satisfy requirements for the Condenser Off Gas release i point. 4.4.4 RM-A7 Waste Gas Decay Tank Exhaust RM-A7 is the gaseous radiation monitor for the TMI-1 Waste Gas Decay tanks (see Figures 4.1 and 4.2). This in plant effluent radiation monitor also has an associated sampling panel. High alarm on RM-A7 noble gas channel willinitiate shutdown of the Waste Gas Decay Tank release in progress. This radiation monitor satisfies requirements for batch l gaseous releases to the Station Vent release point. 1 4.4.5 RM-A9 Reactor Buildina Purne Exhaust l l RM-A9 is the particulate, radiolodine and gaseous radiation monitor for the TMl-1 Reactor Building Purge system (see Figures 4.1 and 4 3). This in plant effluent radiation monitor also has an asso Nted sampling panel with sampling lines located before the sample filters. High alarm on RM-A9 noble gas low channel will initiate shutdown of the Reactor Building Purge System. This radiation monitor satisfies requirements for the Reactor Building Purge System release point. 38.0 m,

Numbor '} (UClear mi Radi i gi i Connois 1 Departmental Procedure 6610-PLN-4200.01 Tme nevisen No. Offsite Dose Calculation Manual (ODCM) 7 i 4.4.6 RM-A14 ESF FHB Ventilation System RM-A14 is the gaseous radiation monitor for the TMl-1 Emergency Safeguards Features 3 (ESF) Fuel Handling Building Exhaust system (see Figures 4.1 and 4.2). This in plant effluent radiation monitor also has an associated sampling panet with sampling lines located y before the sampler filters. High alarm on RM-A14 noble gas channel will initiate shutdown of the ESF Fuel Handling Bu!! ding Exhaust System. This radiation monitor satisfies requirements for the ESF Fuel Handling Building Exhaust System release point. 4.4.7 ALC-RMI-18 Chemical Clean!na Facility (CCF) Ventilation Exhaust ALC-RMI-18 is an Ebedine PING particulate. radiolodine, and gaseous radiation monitor for the Chemical Cleaning building exhaust. Presently, the radioiodine channel is not in use. This monitor is located in the Chemical Cleaning building on the ground floor, and has an associated sample pane!. Sampling for particulate actMty is performed off of the monitor. 4.4.8 WHP-RIT-1 Waste Handlina and Packaalna Facility (WHPF) Exhaust. WHP-RIT-1 is an Eberline AMS-3 particulate radiation monitor for the TMI WHPF. The monitor is located in the Mechanical Equipment Room in the WHPF. Sampling for i particulate actMty is performed off of the monitor. A high alarm will initiate shutdown of the ventilation air exhaust system. 4.4.9 RLM.RM-1 Respirator Cleanino and Laundry Maintenance (RLM) Facility l RLM-RM-1 is an Eberline AMS-3 particulate radiation monitor for the TMI RLM Facility. The monitor is located in the Mechanical Equipment Room in the RLM. Sampling for particulate activity is performed off of the monitor. l d b 39 0 nn. .a

Number (UCIO8r m R di i gi ai controis Departmental Procedure 6610-PLN-4200.01 Trtle Revision No. Offsite Dose Calculation Manual (ODCM) 7 4.5 TMI-2 Gaseous Efpaent Release Points and Gaseous Radiation Monitor Data TMl 2 has three (3) regulatory required gaseous effluent radiation monitors. These are HP-R 219. j HP-R-219A and HP-R-225. These gaseous release points, radiation monitors, and sample points are shown in Table 4.2, and various gaseous effluent pathways are depicted in Figure 4.5. 4.5.1 HP-R-219 Station Ventilation Exhaust HP-R-219 is a Victoreen particulate and gaseous radiation monitor for the TMl-2 ventilation exhaust. This in-plant effluent radiation monitor is located in the TMI-2 Auxiliary Building 328 I foot elevation and has an associated sample panel. A high alarm will initiate shutdown of I the ventilation air supply systems. 4.5.2 ,HP-R-219A Station Ventilation Exhaust HP-R-219A is a Victoreen particulate and gaseous radiation monitor for the TMI-2 ventilation exhaust. This in-plant effluent radiation monitor is located in the TMI-2 Auxiliary Building 328 foot elevation. A high alarm will initiate shutdown of the ventilation air supply systems. 4.5.3 HP-R-225 Reactor Buildina Purae Air Exhaust Duct *A* HP-R-225 is a Victoreen particulate and gaseous radiation monitor for the TMI-2 Reactor BuBGng Purge Air Exhaust System. This in-plant effluent radiation monitor is located in the TMi-2 Auxiliary Building 328' elevation area. A high alarm will initiate a shutdown of the TMI-2 Reactor Building Purge Exhaust System by tripping supply and exhaust dampers and actuating the recirculation mode. l l l l 40 0 ,m,

%mber gdgy TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 Trtle Revision No. Offsite Dose Calculation Manual (ODCM) 7 4.6 Control of Gaseous Effluent Releases TMI gaseous effluent combined releases are contro!!ed (per TMI-1 Tech. Spec. Section 3.22.2.1 and ODCM Part 11 for TMI-2) by effluent sampling and radiation monitor set points. These measures assure that releases from the various vents do not combine to produce dose rates at the site boundary exceeding the rnost restrictive of 500 mrem per year to the total body or 3000 mrem per year to the skin, and 1500 mrem per year to the thyroid. This is done by restricting simultaneous releases and by limiting the dose rates that may be contributed by the various vents at any time. The various vent radiation monitor set points are each based on fractions of the above limits and do not exceed the above limits when summed together. These effluent radiation monitor set points are calculated using the methodology described in equations 4.1.1, or 4.1.2 and 4.2. The actual set points are then listed in TMI-1 Operations Procedure 1101-2.1. The radioactive content of each batch of gaseous waste is determined prior to release by sampling and analyses in accordance with TMI-1 Tech. Spec. Table 4.22-2 and ODCM Part 11 for TMI-2. The results of pre-release analyses are used with the calculational methods in Sections 4.1 and 4.2 to assure that the dose rates at the site boundary are maintained below the limits in TMI-1 Tech. Spec. Section 3.22.2.1 and ODCM Part il for TMI-2. Post-release analyses of samples composited from batch and continuous releases are performed in accordance with TMi-1 Tech. Spec. Table 4.22-2 and ODCM Part 11 for TMI 2. The results of the analyses are used to assure that the dose rates at the site boundary are maintained within the limits of TMi-1 Tech. Spec. Section 3.22.2.1 and ODCM Part ll for TMI-2. 41.0 mu

1 NumtXar - bdeM Tui R di i gi ai controis Departmental Procedure 6610-PLN-4200.01 Title Revision No. Offsite Dose Calculation Manual (ODCM) 7 TABLE 4.1 TMI-1 Gaseous Release Point and Gaseous Radiation Monitor Data (F) RADIATION RADIATION RADATION RELEASE GASEOUS EXHAUST MONITOR MONTTOR = MONITOR TERMINATION l RAD!ATION GASEOUS FLOW CFM SENSITMTY SENSITMTY SENSITMTY INTERLOCK i MONITOR RELEASE (FLOW (CPM / MIN /pCi/cc) (CPM / MIN /pCi/cc) (CPM /pCi/cc) (YES/NO) (DETECTOR) LOCATION POINT RECORDER) PARTICULATE IODINE GAS VALVES i YES l AH-E-10 l Fuel Hand. AH-D 120 306' Elevation Building 0 50.000 1.30E10 122E9 3 96E7 AH-D 121 RM-A4 Auxiliary Bldg. Exhaust (FR-149) (Sr-90) (L131) (Xe-133) AH-D 122 I Auxiliary l 306' Elevation Building 0 100.000 1.30E10 1.2?E9 3 96E7 YES { RM-A6 Auxiliary Bldg. Exhaust (FR-150) (Sr-90) (L131) (Xe-133) AH-E-11 l YES 2 WDG-V47 i AH-E-10 s AH-E-11 RMA-8/9 Bldg. Starts MAP-5 Near BWST Station 0-150,000 1.60E10 1.30E9 369E7 Radioiodine RM-A8 Exhaust Vent (FR-151) (Sr-90) (L131) (Xe-133) Sampler e 4 4 00E7 YES 322' Elevation Condenser (Xe-133) Starts MAP-5 Second Floor Off Gas 0-200 8.70E7 Radioiodine l RM-A5 Turbine Bldg Exhaust FR-1113 (Kr-85) Sampler l 325E7 YES 322' Elevation Condenser (Xe-133) Starts MAP-5 t Second Floor Off Gas 0-200 9.11E7 Radiciodine RM-A15 Turbine Bldg. Exhaust FR-1113 (Kr 85) Sampler I Waste Gas 306' Elevation Decay Tanks 010 4.00E5 YES RM-A7 Auxiliary Bldg. sA.B.C) FR-123 (Xe-133) WDG V47 ( ) YES AH-V-1A/B/C/D l Reactor WDG-534/535 { Building 0 150,000 Starts MAP 5 l RMA 8/9 Bldg. Purge FR-909/ 1.80E10 1A0E9 3.96E7 Radioiodine i RM-A9 Near BWST Exhaust FR-148 (Sr-90) (L131) (Xe-133) Sampler 331' Devation ESF FHB ESF Fuel 1.05E7 Outside Handling (Xe-133) NO Chern. Building 07000 4 21E7 Manua! l RM-A14 Addition B!dg. Exhaust FR-1104A/B (Kr-85) Actions l I e f I 1 42.0 rm,

i i Number l l (UClear M Radidogical Contrds l Departrnental Procedure 6610-PLN-4200.01 i f II*Je Revision No. i Offsite Dose Calculation Manual (ODCM) 7 -l TABLE 4.1 (Cont'd) l f TMI-1 Gaseous Release Point and Gaseous Radiation Monitor Data i t (F) RADATION RADIATION RADIATION RELEASE GASEOUS EXHAUST MONITOR MONITOR MONITOR TERMINATION RADATION GASEOUS FLOW CFM SENSITMTY SENSITMTY SENSITMTY INTERLOCK MONITOR RELEASE (FLOW (CPM / MIN /pCi/cc) (CPM / MIN /pCi/cc) (CPM /pCi/ce) (YES/NO) [ (DETECTOR) - LOCATION POINT RECORDER) PARTICULATE LODINE GAS VALVES Chemical CCB l Cleaning Bldg. Exhaust 1.40ES CPM /pCi 2.06E7 i ALC-RMi-18 304' Elevation System B.000 (SR-90) (KR-85) NONE WHPF l Mechanical WHPF YES Equipme it Exhaust WHPF WHP-R:T 1 Room System 7,500 1 3.333E10 Ventitation Trips RLM-Mechanical Equipment RLM Exhaus' g RLM.RM-1 Room System 900 3.33E10 NONE + ~ f 1 l i i i l l f f i I i i t 43.0 mu

Number (ggy TMi Radiological Controls Departmental Procedure 6610-PLN-4200.01 Title Revision No. f Offsite Dose Calculation Manual (ODCM) 7 t TABLE 4.2 TMI-2 Gaseous Release Point and Gaseous Radiation Monitor Data i t RADIATION - RADATION FRDIATION i MONITOR MONITOR MONITOR RELEASE GASEOUS SENSITIV11Y SENSITMTY SENSITIVITY TERMINATION .l RADLATION GASEOUS EXHAUST (CPM / MIN /pCi/ce) (CPM / MIN /pCi/cc) (CPM /pCi/cc) INTERLOCK MONITOR RELEASE FLOW PARTICULATE BETA IODINE BETA GAS (YES/NO) (DETECTOR) LOCATION POINT CFM SCINTILLATOR SCINTILLATOR Nal DETECTOR VALVES YES Trips AH-E-23A/B, { 9A/B,7A/B l Closes D 5128A/D i* 328' Elevation Station D-5129A Auxiliary Vent 1.514E11 7.81E7 Opens HP R 219 Building Exhaust ' 140,000 (Sr 90) (KR45) D51290 328' Elevation YES Auxiliary Station Vent 1.514E11 7.81E7 Same as HP-R-219A Building Exhaust 140.000 (SR.90) (rA85) HP-R-219 f Reactor YES i Btdg Purge Closes D-5129A. f 328' Elevation Exhaust 1.514E11 7.81E7 5128A/D. HP R-225 Auxiliary Building Duct "A" 25,000 (SR-90) (KR-85) OPENS D-5129D t I i 4 1 i t f i f I I f 4 l' i I i t a. i I [ 44.0 mu f

Numts 1 -(UClear M Radiological Controls Departmental Procedure 6610-PLN-4200.01 Titie Revision No. ) I Offsite Doso Calculation Manual (ODCM) 3 TABLE 4.3 l Dose Factors for Noble Gases and Daughters

Gamma Beta Total Body Skin Dose Gamma Air Beta Air Dose Factor (a)

Factor (b) Dose Factor Dose Factor N 4 N, Radio-(mrem /yr per (mrem /yr per (mrad /yr per (mrad /yr per nuclide pCl/m') pCi/m') pCl/m') pCl/m') Kr-83m 7.56E42*

1.93E + 01 2.88E + 02 Kr-85m 1.17E + 03 1.46E + 03 1.23E + 03 1.97E + 03 l

Kr-85 1.61E + 01 1.34E + 03 1.72E + 01 1.95E + 03 Kr-87 5.92E + 03 9.73E 4 03 6.17E + 03 1.0]+04 Kr-88 1.47E+ 04 2.37E + 03 1.52E + 04 33 Kr-89 1.66E + 04 1.01E4 04 1.73E + 04 . 4 E < 04 Kr-90 1.56E + 04 7.29E+ 03 1.63E + 04 7.83E+ 03 i Xe-131m 9.15E + 01 4.76E 4 02 1.56E + 02 1.11E+ 03 Xe-133m 2.51 E + 02 9.94E + 02 3.27E + 02 1.48E + 03 Xe-133 2.94E + 02 3.06E + 02 3.53E + 02 1.05E + 03 Xe-135m 3.12E+ 03 7.11 E + 02 3.36E + 03 7.39E + 02 Xo-135 1.81 E + 03 1.86E 4 03 1.925 + 03 2.46E + 03 Xe-137 1.42E + 03 1.22E + 04 1.51 E + 03 1.27E + 04 Xe-138 8.83E + 03 4.13E + 03 9.21 E 4 03 4.75E + 03 Ar-41 8.84E + 03 2.69E + 03 9.30E + 03 3.28E + 03

Dose factors are for immersion exposure in uniform semi-infinite cloud of noble gas radionuclides that may be detected ingaseous effluents. Dose factor values are taken from Regulatory Guide 1.109 (Rev.1), Table B-1.
- 7.56E-02 = 7.56 x 10-2 i

(a) Total body dose factor for garnma penetration depth of 5 cm into the body. l l (b) Skin dose factor at a tissue depth or tissue density thickness of 7 mg/cm'. 45.0 n m. -n n

=. Number hdeM TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 Title Revision No. Offsite Dose Calculation Manual (ODCM) 3 l i i TABLE 4 4 Atmospheric Dispersion Factors for Three Mile Island e STATION VENT DISTANCE 3 e SECTOR AVERAGE X/O (IN SEC/M ) (IN METERS) SEASON. ANNUAL SECTOR 610 2413 4022 5631 7240 12067 24135 40225 56315 72405 N 1.18E-07 5.32E 07 2.95E-07 1.93E-07 1.39E-07 5.52E48 1.9f E48 5.02E-09 1.88E49 1.09E-09 NNE 1.70E 07 7.17E-07 3.45E-07 2.00E-0, 1.39E-07 5.58E-08 1.70E-08 4.77E-09 1.98E-09 9.69E-10 NE 1.12E47 1.75E-07 326E-07 1.86E 07 1.21E47 5.00E-08 1.67E 08 4.67E49 1.85E-09 9 93E-10 [ ENE 1.09E-07 2.13E-07 2.67E-07 1.53E-07 1.05E-07 4.31E4B 1.42E-08 4.42E49 1.59E-09 8.64E-10 l r E 2,31 E-07 1.71E-07 1.52E 07 1.49E-07 1.06E-07 4.63E 08 1.52E-08 5.19E-09 2.48E49 1.50E-09 ESE 3.50E-07 2.12E-07 2.50E 07 1.48E 07 9 48E-08 3.98E-08 1.50E-08 5.92E-09 2.92E-09 1.93E-09 [ i 4 SE 419E-07 3.79E-07 2.53E-07 1.55E-07 1.11E47 4.82E48 1.81E-08 6.84 E-09 3.30E-09 2.22E49 SSE 2.90E 07 3.62E-07 2.55E-07 1.49E47 1.11 E-Ut 5.02E-08 1.9BE-08 6.97E-09 2S4E49 1.70E 09 S 1.87E 07 6.47E-08 2.16E-07 1.30E 07 8.65E-08 4.09E-08 1.40E48 4 96E-09 1.99E49 1.04 E-09 h SSW 6.13E 08 4.16E-08 1.55E-07 1.03E-07 6.81 E-08 2.72E 08 9.74E-09 3.01E-09 1.50E-09 8.23E-10 SW 5.76E48 1.14E-07 1.70E 07 1.05E 07 6.93E-08 2.51E 08 9.34E49 2.72E-09 1.33E-09 8.33E-10 WSW 8.52E-08 3.75E-07 2.14E 07 126E-07 7.74 E-08 3 0BE-08 1.02E-08 328E-09 1.39E49 9.69E-10 i W 1.15E-07 5.80E 07 2.88E-07 1.63E-07 1.18E-07 523E-08 1.72E-08 5.06E-09 1.9BE49 125E-09 WNW 1.41 E-07 628E-07 3.30E-07 2.19E-07 148E47 5.68E-08 1.95E-08 6.32E-09 2.16E49 1.34E 09 NW 142E 07 5.67E-07 3.17E-07 1.93E-07 1.30E-07 5.67E-08 2.06E-08 5.90E 09 2.70E-09 1.45E49 NNW 1.00E47 5.77E-07 3.18E-07 1.80E-07 127E-07 5.20E48 1.77E48 4.82E-09 2.01E-09 122E-09 f j e STATION VENT DISTANCE j e SECTOR AVERAGE D/O (IN M-2) (IN METERS) SEASON-ANNUAL d f SECTOR 610 2413 4022 5631 7240 12067 24135 40225 56315 72405 N 2.51 E-09 A 72E-10 4.84E-10 2.98E-10 2.50E-10 8.57E-11 2.51E-11 4.98E-12 1.57E-12 7.84E 13 { NNE 3.89E-09 1.9BE49 9.54E-10 4.99E-10 3.3BE 10 1.10E 10 2.89E-11 6.06E-12 2.10E-12 8.89E 13 l NE 2.58E49 6.70E-10 9.13E-10 4.91E-10 2.97E-10 1.04E-10 2.87E 11 6.01 E-12 1.99E-12 9.23E-13 p ENE 2.15E-09 5.85E-10 5 54E-10 3.06E-10 2.08E-10 8.30E-11 2.32E-11 5.41 E-12 1.63E 12 7.64E-13 I i E 5.54E 09 123E 09 6.17E-10 4.59E-10 3.63E-10 1.34E-10 3 66E 11 9.44E-12 3.77E-12 1.97E-12 i f ESE 9.17E-09 2.05E-09 1.51E 09 8.66E-10 5.11E-10 1.82E-10 5.77E-11 1.72E-11 7.07E-12 4.07E-12 SE 122E48 2.88E49 1.84E-09 1.02E-09 6.85E 10 2.60E-10 8.30E-11 2.34E-11 9 42E.12 5.51E-12 [ SSE 7.50E-09 1.62E-09 1.08E49 5.89E-10 4 49E 10 1.87E-10 6.16E-11 1.61E-11 5.67E-12 2.83E-1? S 3 86E49 6.53E 10 6.27E-10 3.59E-10 2.32E 10 1.06E-10 3.05E-11 8.10E-12 2.73E 12 1.23E-12 f SSW 1.13E 09 2.94E-10 4.19E-10 2.53E-10 1.56E-10 5.38E-11 1.68E-11 3.91 E-12 1.64E-12 7.84E-13 SW 1.19E-09 3.84E-10 4.96E-10 2.80E-10 1.70E-10 524E-11 1.65E-11 3.62E-12 1.49E 12 8.12E 13 WSW 1.77E-09 8.31 E-10 6 49E-10 3.50E-10 1.99E-10 6.73E-11 1.89E-11 4.58E-12 1.63E-12 9.90E-13 l W 2 41E-09 129E49 6.81E-10 3.65E-10 2.96E-10 1.12E-10 311E-11 6.90E-12 226E-12 125E-12 WNW 320E 09 1.39E-09 7.73E-10 S.91E 10 3 66E-10 1.19E-10 3.43E-11 8.36E-12 2.39E-12 129E-12 NW 325E49 123E-09 7.39E-10 422E 10 2.77E-10 1.14E-10 72BE-11 7.61E-12 2.92E-12 1.36E 12 NNW 1.98E 09 9.88E-10 5.71 E-10 3.05E-10 223E-10 821E-11 2.41E-11 4 93E-12 172E-12 9.03E-13 i DATA FROM 1/1/78 THROUGH 12/31/86 USED IN CALCULATIONS l 46.0 m j .+.,... - .-9

.~ Number Nuclear =^dio'oa*a' co"tro's Departrnental Procedure 6610-PLN-4200.01 i Title Revision No. Offsite Doso Calculation Manual (ODCM) 3 i l i TABLE 4.5 l i Atmospheric Dispersion Factors for Three Mile Island I e GROUND RELEASE DISTANCE 3 e SECTOR AVERAGE X/O (IN SEC/M ) ON METERS) SEASON - ANNUAL SECTOR 610 2413 4022 5631 7240 12067 24135 40225 56315 72405 N 1.16E-05 1.13E-06 5 94E-07 3.80E-07 2.38E 07 9.74E-08 3.45E-08 9 2BE-09 3.52E 09 2.05E-09 NNE 1.08E-05 1.10E46 5f4E 07 3.41E-07 2.38E-07 9.55E48 3.11E4B B 94E-09 3.74E-09 1.84E-09 NE 7.02E 06 9.81 E-07 5.42E 07 3.17E-07 2.10E-07 9.01 E-08 3.10E48 8.87E49 3.54E49 1.91E-09 ENE 7.14E-06 9.64E 07 4 92E-07 2.85E 07 1.97E 07 7.82E-08 2.64E 08 8.38E49 3.04E-09 1.66E49 E 8.49E 06 1.09E-06 5.48E-07 2.91E 07 1.87E-07 8.40E 08 2.82E-08 9.85E49 4.75E 09 2.87E-09 ESE 6.91E-06 9.02E-07 4.49E-07 2.57E 07 1.67E-07 720E-08 2.77E-08 1.12E48 5.54E-09 3.68E 09 SE 6.70E-06 9.06E-07 4.53E-07 2.81E-07 2.03E-07 8.94E-08 3.33E-08 128E-08 6.19E 09 4.18E-09 SSE 726E-06 925E-07 4.91 E-07 2.87E-07 2.08E-07 9.18E-08 3.72E-08 1.32E-08 5.62E 09 326E-09 S 8.70E-06 9.08E-07 3.99E 07 2.41E-07 1.61 E-07 7.31E 08 2.57E 08 923E-09 3.74E-09 1.95E 09 SSW 6.05E-06 7.01 E-07 2.75E-07 1.86E-07 124E-07 5.06E48 1.82E 08 5.71E 09 2.87E-09 1.58E-09 SW 5 94E-06 5.71 E-07 2.86E-07 1.81E-07 1.22E-07 4.50E-08 1.72E-08 5.12E-09 2.53E49 1.59E-09 WCW 8.00E-06 7.02E-07 3.60E-07 2.15E 07 1.34E-07 5.50E-08 1.87E48 6.12E-09 2.62E-09 1.83E-09 W 1.02E45 1.07E-06 5.30E-07 3 02E47 2.05E-07 9.01 E-08 3.15E48 9.48E-09 3.74E-09 2.38E-09 WNW 1.16E-05 1.13E-06 5 98E-07 3 67E-07 2.53E-07 1.00E 07 3.56E48 1.18E48 4.07E-09 2.54E-09 NW 1.13E-05 1.06E 06 5.70E 07 3.53E-07 2.40E-07 1.02E-07 3 82E-08 1.11E4B 5.14 E-09 2.78E-09 NNW 1.08E-05 1.04E-06 5.72E-07 3.27E-07 2.22E-07 9.06E-08 320E-08 8.89E-09 3.75E-09 229E 09 eGROUND RELEASE DISTANCE o SECTOR AVERAGE D/O ON M-2) ON METERS) SEASON. ANNUAL SECTOR 610 2413 4022 5631 7240 12067 24135 40225 56315 72405 N 2.30E-08 1.88E-09 8 93E-10 4.82E 10 2.70E-10 8.9SE-11 2.53E-11 4.98E-12 1.57E-12 7.84E-13 NNe 2.66E-08 225E-09 1.06E-09 5 42E-10 3.38E-10 1.10E-10 2.89E-11 6.06E-12 2.10E-12 8.89E-13 NE 1.75E-08 2.00E49 1.01 E-09 5.04E-10 2.9BE-10 1.04E 10 2.88E-11 6.01E 12 1.99E-12 923E-13 ENE 168E-08 1.85E-09 8 65E-10 428E-10 2 65E-10 8.57E-11 2.33E-11 5 41E-12 1.63E-12 7.64 E-13 E 2.88E-08 2.99E-09 1.39E-09 6.34E-10 3.67E-10 1.35E-10 3.68E-11 9.42E-12 3.77E-12 1.97E-12 ESE 3.59E48 3.80E49 1.77E-09 8.79E-10 5.15E-10 1.83E-10 5.78E-11 1.71E-11 7.06E-12 4.06E-12 SE 4.12E48 4.55E-09 2.13E-09 1.15E-09 7.50E-10 2.72E-10 8.31E-11 2.34E-11 9.42E-12 5.50E-12 SSE 3.12E-08 323E-09 1.59E49 8.00E-10 520E-10 1.88E-10 6.18E-11 1.61 E-11 5.66E-12 2.83E-12 S 245E-08 221E 09 9.07E-10 4.75E-10 2.86E-10 1.07E 10 3.06E-11 8.10E-12 2.73E-12 1.23E-12 SSW 1.45E-08 1.30E-09 4.80E-10 2.82E-10 1.70E-10 5.71 E-11 1.69E-11 3.91E 12 1.64E-12 7.84E-13 SW 1.42E-08 1.10E-09 5.15E-10 2.82E-10 1.71 E-10 524E-11 1.65E-11 3E2E-12 1.49E-12 8.12E-13 WSW 2.01E48 1.41E-09 6.82E-10 3.54E-10 2.00E-10 6.76E 11 1.89E-11 4.58E-12 1.63E-12 9.90E-13 W 2.55E-08 2.16E-09 1.00E49 4 91E-10 3.01 E-10 1.12E-10 3.11E-11 6.90E-12 2.27E-12 125E-12 WNW 2.88E 08 2.30E-09 1.13E-09 5 93E-10 3 67E-10 1.19E-10 3.43E 11 8.36E 12 2.39E-12 129E 12 NW 2.78E48 2.15E-09 1.06E-09 5 58E-10 3.41 E-10 1.19E-10 3.57E-11 7.61 E-12 2.92E-12 1.36E-12 NNW 2.17E48 1.75E49 8.75E-10 424E-10 2.57E-10 8.55E-11 2.42E-11 4 93E-12 1.72E-12 9.03E-13 DATA FROM 1/1/78 THROUGH 12/31/86 USED IN CALCULATIONS 47.0 m

t 1 Number Nuclear ' aad'doo'c^' co"trd' Departmental Procedure 6610-PLN-4200.01 I latte Revision No. Offsite Dose Calculation Manual (ODCM) 3 TABLE 4.6 Dose Parameters for Radioiodines and Radioactive Particulate in Gaseous Effluents

CRITICAL ORGAN CRITICAL ORGAN NUCLIDE ORGAN FACTOR Pi"
NUCUDE ORGAN-FACTOR Pi"*

.{ H-3" TOTAL BODY 3.04E-07 1.12E + 03 RU-103 LUNG 1.79E-04 6.62E + 05 A 24 TO AL BODY .3 -06 6E U 10 G .3 7 P-32 BONE 7.04 E-04 2.60E + 06 AG-110M LUNG 1.48E-03 5.48E + 06 CR-51 LUNG 4.59E-06 1.70E + 04 TE-125M - LUNG 1.29E-04 4.77E + 05 MN-54 LUNG 4.26E-04 1.58E + 06 SB-125 LUNG 6.27E-04 2.32E + 06 MN-56 GI-LU 3.33E-05 1.23E + 05 TE-127M LUNG 4.00E-04 1.48E 4 06 l FE-55 LUNG 3.00E-05 1.11 E + 05 TE-127 GI-LU 1.52E-05 5.62E + 04 FE-59 LUNG 3.43E-04 1.27E + 06 TE-129M LUNG 4.76E-04 1.76E + 06 CO-58 LUNG 2.99E-04 1.11 E + 06 TE-129 GI-LU 6.89E-06 2.55E + 04 CO-60 LUNG 1.91 E-03 7.07E + 06 TE-131M GI-LU 8.32E-05 3.08E+ 05 i NI-63 BONE 2.22E-04 8.21E + 05 TE-131 LUNG 5.55F.-07 2.05E + 03 N1-65 GI-LU 2.27E-05 8.40E + 04 TE-132 LUNG 1.0212-04 3.77E + 05 CU-64 GI-LU 9.92E-06 3.67E + 04 l-130 TYHROID 4.P&E-04 1.85E + 06 ZN-65 LUNG 2.69E-04 9.95E + 05 I-131 THYROID 4.39E-03 1.62E + 07 ZN-69 GI-LU 2.75E-06 1.02E + 04 1-132 THYROID 5.23E-05 1.94E + 05 BR-83 TOTAL BODY 1.28E-07 4.74E + 02 1-133 THYROID 1.04E-03 3.85E + 06 BR-84 TOTAL BODY 1.48E-07 5.48E+02 1-134 THYROID 1.37E-05 5.07E+ 04 BR-85 TOTAL BODY 6.84E-09 2.53E + 01 1-135 THYROID 2.14E-04 7.92E + 05 l RB-86 UVER 5.36E-05 1.98E + 05 CS-134 LIVER 2.74E-04 1.01 E+ 06 RB-8B UVER 1.52E-07 5.62E + 02 CS-136 UVER 4.62E-05 1.71E 4 05 RB-39 UVER 9.33E-08 3.45E 4 02 CS-137 BONE 2.45E-04 9.07E + 05 1 SR-89 LUNG 5.89E-04 2.16E + 06 CS-138 LIVER 2.27E-07 8.40E + 02 SR-90 BONE 2.73E-02 1.01 E + 08 BA-139 GI-LU 1.56E-05 5.77E + 04 SR-91 GI-LU 4.70E-05 1.74E + 05 BA-140 LUNG 4.71 E-04 1.74E + 06 SR-92 GI-LU 6.55E-05 2.42E + 05 BA-141 LUNG 7.89E-07 2.92E + 03 Y-90 GI-LU 7.24E-05 2.68E + 05 BA-142 LUNG 4.44E-07 1.64E + 03 Y-91 M LUNG 7.60E-07 2.81E 4 03 LA-140 GI-LU 6.10E45 2.26E+ 05 Y-91 LUNG 7.10E-04 2.63E + 06 LA-142 GI-LU 2.05E-05 7.59E + 04 Y 92 Gl-LU 6.46E-05 2.39E + 05 CE-141 LUNG 1.47E-04 5.44E + 05 Y-93 GI-LU 1.05E-04 3.89E + 05 CE-143 GI-LU 3.44E-05 1.27E + 05 ZR-95 LUNG 6.03E-04 2.23E + 06 CE-144 LUNG 3.23E-03 1.20E + 07 ZR-97 GI-LU 9.49E-05 3.51E 4 05 PR-143 LUNG 1.17E-04 4.33E + 05 NB-95 LUNG 1.66E-04 6.14E + 05 PR-144 LUNG 4.23E-07 1.57E + 03 MO-99 LUNG 3.66E-05 1.35E + 05 ND-147 LUNG 8.87E-05 3.28E+ 05 TC-99M GI-LU 1.30E-06 4.81 E + 03 W-187 GI-LU 2.46E-05 9.10E + 04 TC-101 LUNG 1.58E-07 5.85E + 02 NP-239 GI-LLI 1.73E-05 6.40E + 04 i The listed dose parameters are for radionuclides, other than noble gases that may be dete'. A gaseous i effluents. Pi factors include all nonatmospheric pathway transport parameters, the receptor's usage of pathway media, and are based on the most restrictive age group (child) critical organ. Additional dose parameters for nuclides not included in this Table may be calculated using the methodology described in NUREG-0133. Tritium dose factors include an increase of 50% to account for the additional amount of this nuclide absorbed through the skin. mrem / year per pCl/m'. 48.0 m

Numhor (UClear TMl Radiological Controts Departmental Procedure 6610-PLN-4200.01 g, Revision No. Offsite Dose Calculation Manual (ODCM) 3 FIGURE 4.1 TMI-1 Gaseous Effluent Pathways t t 'i FIGURE 4.1 ORV" 0.u"STOS . no 2O""* %

"%T.

t = m

^

"t*

Y p Q l AUXILIARY BUILDING oc.mo em i nuo F 9 " ^ ^ " ~

43

,,,i WGDTS00o _l RM-AS l REAC*,0R su m a g i man C D 1RM-A14, fpp t 1 ED" " 7 N N ^ d FUEL co~os = sm i HANDLING l fifc0^* l BUILDING g-- .j ca, su.cz OW P-PRE FILTER 15*^5 '"^' 4 A-ABSOLUTE HEPA C-CHARCOAL FILTER HN 'V C0CN T 7 vuS { t m t 49.0 rme

Numbor l' Nuclear " "ad'*o'ca' c ""* Departmental Procedure 6610-PLN-4200.01 Revision No. Offsite Dose Calculation Manual (ODCM) 3 FIGURE 4.2 TMi-1 Auxiliary and Fuel Handling Buildings Effluent Pathways 1 WM I40,4 U R g "" yr we m RM-A8 uxlo ao a rtw P A C m rar /\\ es RM-A6 $WLE RM-A14 Ho a gg.A4 mr;u a m I ESFFUEL P A C AUXILIARY s HANDuns h-RM-A7 ? BUILDING m a a rts BUILDING 3-A n A FUEL HANDLING 3 1" v y'v y'v BUILDING q AUXILIARY AND TUEL HANDLING BUILDINGS EXHAUST RADIAT10N UEE MNITORS AND SAMPllNG STATIONS C = C** p i 50.0 1

%mtor NUCIear TMl Radic$ogical Controls Departmental Procedure 6610-PLN-4200.01 Title Revisiori No. i Offsite Dose Calculation Manual (ODCM) 3 'i FIGURE 4.3 TMI-1 Reactor Building Effluent Pathway-PFL 170 V4 ~ FEET i REACTOR BUILDING PURGE EXHAUST RADIAT10N HONITCRS AND

'8 "*

SAMPLING STAIl0NS w-s O f X M stata 1 FMT/ REACTOR N BUILDING mfes we ) A,' ^

5-88 CfM PAI flLV iDCi3t LU%

WRK SYSTD6 FGilCLLAE/ Tid 13 WLE W p : FGTDut A = A151UT[ C : OWG4. f 51.0 nm.

1 Numb 2r Nuclear 'M' "adi 'o9'ca' coatro'$ Departmental Procedure 6610-PLN-4200.01 i Tme Revision No. Offsite Dose Calculation Manual (ODCM) 3 i FIGURE 4.4 TMl-1 Condenser Offgas Effluent Pathway 1 i CONDENSER 0FF GAS STACK CONDENSER OFF GAS i 3 115 e -cts EXHAUST FEET RADIATION MONITORS AND SAMPLING STATIONS W"Ji'" i e.,-.s .gep l n en-ais MAIN gg g 3 CONDENSER i D 1 0 to 700 Cru =,- -o 7 l I 52.0 mu i +

? W O E h

==E E STATION VENT ,b A Q O 5 4 -i u= cm c H P-R-219 H P R-219 A C_ HP R.219 SAMPLE RACK RB8RE N A o "1 i s , _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - -- s.______________! g i a 4 ro.one em A ese em I bd cE

U L

- tm FILTERS wa.are wa.ese FILTERS O

5U D NG U REACTOR O 3 Oh BUILDING 5 Q v u, C 5n m o aw Po 3 m ga <s.o.e em c eq rutt 8 in Ro 4-st1Ah FILTERS -*.n-seis HANDLING BL 9. BUILDING g yO_ s 8o ^ 3 ag ,*. c. Iso esosnion j g e CONTROL AND SERVICE BUILDING e a E a S g 8 o a a 5 UNIT 2 EXHAUST AIR FLOW AND RMS SCHEMATIC E y .im ~ O j .Ooa m_ _ _ __.. _ _... _. _ _... ~... _ _ -___ -.-,- - ,m .-m .c ...r

1 hmber i -(UClear m sad d ai i Contres Departmental Procedure 6610-PLN-4200.01 Title - Revision No. I Offsite Dose Calculation Manual (ODCM) 7 5.0 GASEOUS EFFLUENT DOSE ASSESSMENT 5.1 3aseous Effluents -Instantaneous Release Limits 5.1.1 Noble Gases i For noble gases, the following equations apply for total body and skin dose rate at the unrestricted area boundary: l i 5.1.1.1 Total Body Dose Rateg = I(K;) x (Dv) x (Q) (eg 5.1.1.1) { 3 i i where: Dose Ratetb= instantaneous total body dose rate limit, at the site boundary, in mrem /yr. l K= total body dose factor due to gamma emissions for each identified noble i 3 gas radionuclide, in mrem /yr per pCi/m from Table 4.3. j Dv = highest sector annual average gaseous dispersicn factor (X/O) at or 3 beyond the unrestricted area boundary, in sec/m, from Table 4.4 for [ station vent releases; and Table 4.5 for all other releases (Condenser Off i Gas, ESF FHB, and ground releases). Maximum values presently in use 3 3 are 7.17E-7 sec/m at sector NNE for station vent, and 1,16E-5 sec/m p for all other releases, at sectors N and WNW. l O, = Release rate of radionuclide, i, in pCi/sec as determined by sampfing and analysis. Calculated using the concentration of noble gas radionuclide, I, in pCl/cc, times the release pathway flow rate, in cc/second. L t i 5 i ? i t i 54.0 una I

I Number -bdeM Tui R di r gi at Contrors - Departmental Procedure 6610-PLN-4200.01 l Idle Pevision No. .l Offsite Dose Calculation Manual (ODCM) 3 ) -l 5.1.1.2 Skin Dose Rate. = I(L, + 1.1 M,) X (Dv) X (0,) (eq 5.1.1.2) ) I t i where: Dose Rate = instantaneous mrem / year skin dose rate limit, at the site bcundary, in mrem /yr. L, = skin dose factor due to beta emissions for each identified noble gas - l radionuclide, in mrem /yr per pCl/m' from Table 4.3. M, = air dose factor due to gamma emissions for each identified noble gas - radionuclide, in mrad /yr per Cl/m' from Table 4.3. 1.1 - mrem skin dose per mrad air dose. Converts air dose to skin dose. I l O, = release rate of radionuclide, I, in pCl/sec, as determined by sampling and i analysis. Calculated using the concentration of noble gas radionuclide, i, in pCi/ce, times the release pathway flow rate, in cc/second. Dv = highest sector annual average gaseous dispersion factor (X/0) at or beyond the unrestricted area boundary, in sec/m', from Table 4.4 for l station vent releases; and Table 4.5 for all other releases (Condenser Off Gas ESF FHB, and ground releases). Maximum values presently in use i are 7.17E-7 sec/m' at sector NNE for station vent, and 1.16E-5 sec/m' for i all other releases, at sectors N and WNW. -1 ? 55.0 2 m, i

~_ - Number b'deM Tui R di i gi i Controis Departmental Procedure 6610-PLN-4200.01 Tette Revision No. Offsite Dose Calculation Manual (ODCM) 3 5.1.2 lodine-131. lodine-133. Tritium and Radionuclides in Particulate Form, with Half-Lives Greater than 8 Days I For 1-131,1-133, Tritium and Radionuclides in Particulate Form, with half-lives greater than 8 days, the following equation applies: .l l Dose Rate, = I (P) (Dv) (Q) (eq 5.1.2) l I where: = Dose Rate, = mrem / year organ dose rate. l i P, = dose parameter for 1-131,1-133, Tritium and Radionuclides in Particulate Form, with half-lives greater than 8 days, for the inhalation pathway, in - mrem /yr per pCi/m', from Table 4.6. The dose factors are based on the critical individual organ and most restrictive age group (child). .l r Dv = highest sector annual average gaseous dispersion factor (X/O or D/0) at or beyond the unrestricted area boundary, in sec/m' from Table 4.4 for l the station vent releases and Table 4.5.~or all other rcleases. X/O is used for the inhalation pathway. Maximum values of X/O presently used are 7.17E-7 sec/m' for station vent, at sector NNE, and 1.16E-5 sec/m' for all other releases, et sectors N and WNW. O, = release rate of each radionuclide, I, in pCl/sec. Calculated using the concentration of each radionuclide, I, in Ci/cc, times the release pathway i flow rats, in cc/second. 1 j i 1 i J 'I i .i a 56.0 mu

Number -(LIClear mi a di t gi ai Controis Departmental Procedure 6610-PLN-4200.01 Title Revision No. l Offsite Dose Cuculation Manual (ODCM) 3 5.2 Gaseous Effluents - 10 CFR 50 Appendix I 5.2.1 Noble Gases The air dose in an unrestricted area due to noble gases released in gaseous effluents from the site is determined using the following expressions: Dose r = (3.17E-8) x I(M,) x (Dv) x (Oi) (eg 5.2.1) i l and l Dose p = (3.17E-8) x I (N,) x (Dv) x (OI) (eg 5.2.2) where: ) Dose r = mrad gamma air dose due to gamma emissions from noble gas radionuclides. 1 Dose # = mrad beta air dose due to beta emissions from noble gas radionuclides. M, = air dose factor due to gamma emissions for each identified noble gas radionuclide, in mrad /yr per pCl/m', from Table 4.3. 4 N, = air dose factor due to beta emissions for each identified noble gas radionuclide, in mrad /yr per pCl/m', from Table 4.3. Dv = highest sector annual average gaseous dispersion factor, X/O, at or beyond the unrestricted area boundary, in sec/m'. Values may be read or interpolated from Table 4.4 for releases from the station vent and Table 4.5 for all other releases. Maximum values of X/O presently ue,ed are 7.17E-7 sec/m' for station vent at sector NNE, and 1.16E-5 sec/m' for all other releases at sectors N or WNW. O, = release of noble gas radionuclide, I, in pCl, over the specified time period, ( Ci/second

seconds).

3.17E4 = inverse of the number of seconds in a year. j NOTE if the methodology in this section is used in determining dose to an f individual, rather than air dose due to noble gases, substitute Ki, from Table 4.3, for Mi, and (U + 1.1 Mi) for Ni. i 1 57.0

m,

Wmber hdeM Tu R di i gi i Controis Departmental Procedure 6610-PLN-4200.01 Title Revision No. Offsite Dose Calculation Manual (ODCM) 3 5.2.2 lodine-131. lodine-133 Tritium and Radionuclides in Particulate Form, with Half-Uves Greater than 8 Days ? The dose to an individual from l-131,1-133, Tritium and Radionuclides in Particulate Form with half-lives greater than 8 days in gaseous effluents released from the site to an unrestricted area is determined by solving the following expression: Dose, = I(3.17E-8) x I (R,) (Dv) (Q,) (eq 5.2.2) I i where: l Dose, = dose to all real pathways, p, to organ, o, of an individual in age group, a, from I-131,1-133, Tritium and Radionuclides in Particulate Form, with half-lives greater than 8 days, in mrem, during any desired time period. R, = the dose factor for each identified radionuclide. I, pathway, p, age group, a, and organ, o, in mrem /yr per pCl/m' for the inhalation pathway and m' - mrem /yr per Cl/sec for other pathways, from Tables 5.2 to 5.7. NOTE Since there is minimal or no elemental lodine released from the condenser off-gas air ejector (see NUREG-0017) all lodine R, values for l all pathways, except the inhalation pathway, are considered to be zero when performing dose calculations for releases from the condenser off-gas air ejector. Only calculate the dose due to the inhalation pathway for condenser off-gas air ejector lodines. l NOTE Tritium, H-3, dose factor is mrem / year per pCI/m' for all pathways. Dv = highest sector annual average gaseous dispersion factor (X/0) at or beyond the unrestricted area boundary, in sec/m', for the inhalation pathway, and D/O, in m', for other pathways. Table 4.4 is used for station vent releases and Table 4.5 for a!! ether releases. Maximum values of X/O presently used are 7.17E-7 sec/m' lor station vent at sector NNE and 1.16E-5 sec/m' for all other releases at sectors N and WNW. Maximum i values of D/O in m for station vent is 1.22E-8/m' at sector SE, and for 2 ground releases,4.12E-8/m for sector SE. i i Dv(H-3) = In the case ' H-3 only the X/O's are used for all pathways from Table 4.4 for station vent releases and Table 4.5 for all other releases. e v 58.0 2nu i

- ~ _. I ams.r ~l -(UClear. M Radidogical Contrds j Departmental Procedure 6610-PLN-4200.01 4' Tette Revision No, Offsite Dose Calculation Manual (ODCM) 3 O, = release of I-131,1-133, Tritium and Radionuclides, I, in Particulate Form with [ half-lives greater than 8 days, in pCl, cumulative over the specified time i period (gCl/second

seconds).

3.17E-8 = inverse of the number of seconds in a year. 1 -t h I i b i F 'f l 59.0 2m,

Number gggy TMI Radiviogical Controls Departmental Procedure 6610-PLN-4200.01 Titie Revision No. Offsite Dose Calculation Manual (ODCM) 3 5.3 Gaseous Radioactive System Dose Calculations Once per Month TMI-1 Tech. Spec. Section 3.22.2.4 requires that appropriate subsystem of the Gaseous Radwaste Treatment System shall be used to reduce the radioactive materials in gaseous waste prior to their discharge. When the monthly projected doses due to the gaseous effluent releases from the site would exceed: i 0.2 mrad to air from gamma radiation; or 0.4 mrad to air from beta radiation; or l 0.3 mrem to any organ. The following calculational method is provided for performing this dose projection. At least once per month the gamma air dose, beta air dose and the maximum organ dose for the quarter-to4 ate will be divided by the number of days into the quarter and multiplied by 31. Also, _ t this dose projection shall include the estimated Jose due to any anticipated unusual release during the period for which the projection is made if these projected doses exceed any of the values listed j above, appropriate portions of the Gaseous Waste Processing System, as defined in Section 6.2, shall be used to reduce radioactivity levels prior to release. i l 0 i ( l ] I i .I 60.0 2m, l

1 I Number l Nuclear " ad'd

aiContras i

Departmental Procedure 6610-PLN-4200.01 Title Revision No. Offsite Dose Calculation Manual (ODCM) 3 l 5.4 Alternative Dose Calculadonal Methodolooles for Gaseous Effluents As an alternative to the methods described above, the models in/or based upon, those presented in 3 Regulatory Guide 1.109 (Rev.1) may be used to make a comprehensive dose assessment. Default parameter values from Regulatory Guide 1.109 (Rev.1) and/or actual site specific data can be used where applicable. r I The onsite, on-line computerized system for tracking gaseous effluent dose uses annual average gaseous dispersion factors. As an alternative dose calculational methodology. GPU Nuclear i calculates doses using an advanced class *A" dispersion model called SEEDS (simplified i environmental effluent dosimetry system). r t This model incorporates the guidelines and methodology set forth in USNRC Regulatory Guide 1.109, and uses actual hourly meteorological information matched to the time of releases to more i accurately assess the dispersion of effluents in the atmosphere. Combining this assessment of i dispersion with TMINS effluent data for each unit, postulated maximum hypothetical doses to the public are calculated. l L l 1 6 i i P ) 1 61.0 rme 1 1 ~

i Wmt:or (MClear TM Radiological Controls Departmental Procedure 6610-PLN-4200.01 Tme Revision No. I Offsite Dose Calculation Manual (ODCM) 3 l TABLE 5.2.1 Pathway Dose Factors, RI AGE GROUP: INFANT PATHWAY: INHALATION i ORGAN DOSE FACTORS; mrem / year per pCi/m' ' NUCUDE = - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - BONE UVER T. BODY THYROID KIDNEY LUNG GI-LU -= ....=-- H-3 0.00E + 00 6.47E + 02 6.47E + 02 6.47E + 02 6.47E + 02 6.47E + 02 6.47E + 02 8 C-14 2.65E + 04 5.31 E + 03 5.31E + 03 5.31 E + 03 5.31 E + 03 5.31E + 03 5.31E + 03 CR-51 0.00E + 00 0.00E + 00 8.95E + 01 5.75E + 01 1.32E + 01 1.28E + 04 3.57E+ 02 MN-54 bI005~00 5 53E + 04 4.'98Elb3 b'005~0O'~ i.00E + 06 7.06E +b!!~ ~ 4.98E+ 03 FE-55 1.97E + 04 1.17E + 04 3.33E + 03 0.00E + 00 0.00E + 00 8 69E + 04 1.09E + 03 FE-59 1.36E + 04 2.35E + 04 9.48E + 03 0.00E + 00 - 0.00E + 00 1.02E + 06 2.48E + 04 i CO-58 b.00E + 00 ~I.~225~03 5.~82E703~~b.~00 Ebb ~b.~bbEIO0 7.77E + 051.11 E + 04 l ~ ~ ~' ~ CO-60 0.00E + 00 8.02E + 03 1.18E + 04 0.00E + 00 0.00E + 00 4.51 E + 06 3.19E + 04 NI63 3.39E + 05 2.04E + 04 1.16E + 04 0.00E + 00 0.00E + 00 2.09E + 05 2.42E + 03 I =_...... ZN-65 1.93E + 04 6.26E + 04 3.11 E + 04 0.00E + 00 3.25E + 04 6.47E + 05 5.14E + 04 RB-86 0.00E + 00 1.90E + 05 8.82E + 04 0.00E 4 00 0.00E + 00 0.00E + 00 3.04E + 03 l SR 3.98E + 05 0.00E + 00 1.14E + 04 0.00E + 00 0.00E + 00 2.03E + 06 6.40E + 04 .._.-8 9.__._.....____.._....-= __-----_= -- _ _-_._.._. =- .= SR-90 4.09E + 07 0.00E + 00 2.59E + 06 0.00E + 00 0.00E + 00 1.12E + 07 1.31 E + 05 Y-91 5.88E + 05 0.00E + 00 1.57E + 04 0.00E + 00 0.00E + 00 2.45E + 06 7.03E + 04 ZR-95 1.15E + 05 2.79E + 04 2.03E + 04 0.00E + 00 3.11 E + 04 1.75E + 06 2.17E + 04 ...___.______.______..._...__.._...........____---.27E+04 i 6.43E + 03 3.78E + 03 0.00E +00 4.72E + 03 4.79E + 05 1 NB.95 1.57E 4 04 RU-103 2.02E + 03 0.00E + 00 6.79E 4 02 0.00E + 00 4.24E + 03 5.52E + 05 1.61 E + 04 RU 106 8.68E + 04 0.00E + 00 1.09E4 04 0.00E + 00 1.07E + 05 1.16E + 07 1.64E + 05 j = - -. _ - - - - _. AG-110M 9.98E + 03 7.22E + 03 5.00E + 03 0.00E + 00 1.09E + 04 3.67E + 06 3.30E + 04 TE-125M 4.76E + 03 1.99E + 03 6.58E + O2 1.62E + 03 0.00E + 00 4.47E + 05 1.29E + 04 TE-127M 1.67E + 04 6.90E + 03 2.07E + 03 4.87E + 03 3.75E + 04 1.31E + 06 2.73E + 04 i .. _. = = - - - _ TE-129M 1.41 E + 04 6.09E + 03 2.23E + 03 5.47E+03 3.18E + 04 1.68E + 06 6.90E + 04 1131 3.79E + 04 4.44E + 04 1.96E + 04 1.48E + 07 5.18E + 04 0.00E + 00 1.06E 4 03 a l133 1.32E + 04 1.92E+ 04 5.60E + 03 3.56E + 06 2.24E + 04 0.00E + 00 2.16E + 03 -_ =... CS-134 3.96E + 05 7.03E + 05 7.45E + 04 0.00E + 00 1.90E4 05 7.97E + 04 1.33E + 03 i l CS-136 4.83E + 04 1.35E + 05 5.29E + 04 0.00E + 00 5.64E + 04 1.18E + 04 1.43E + 03 CS-137 5.49E + 05 6.12E + 05 4.55E + 04 0.00E + 00 1.72E + 05 7.13E + 04 1.33E + 03 ~ ~ ~ ~ ~ ~ ~~~ ~bA 5~'O b.60504 5.~60503 250E703~~b.~00E 4 00 i.345bi1 1.60E + 06 3.84E + 04 4 CE-141 2.77E + 04 1.67E + 04 1.99E + 03 0.00E + 00 5.25E + 03 5.17E + 05 2.16E + 04 CE-144 3.19E + 06 1.21 E + 06 1.76E + 05 0.00E + 00 5.38E 4 05 9.84E + 06 1.48E + 05 _=__._.. ........___.......= PR-143 1.40E + 04 5.24E+03 6.99E + O2 0.00E + 00 1.97E + 03 4.33E + 05. 3.72E + 04 i ND-147 7.94E + 03 8.13E 4 03 5.00E + O2 0.00E 4 00 3.15E + 03 3.22E + 05 3.12E + 04 i ..... _ _ _.. _ _ _ _ _ _... _ = = - - - l I i 62.0 m

Ember (tJClear WI Radiotopcal Conkols Departmental Procedure 6610-PLN-4200.01 l Iltle Revision No. Offsite Dose Calculation Manual (ODCM) 3 l i r TABLE 5.2.2 Pathway Dose Factors, Ri { AGE GROUP: CHILD PATHWAY: INHALATION [ i ..... -. _ _ _. _ _ _ - _ _ _ _ _ _ _ _. = - - - - - = - - -

==.... ORGAN DOSE FACTOhs; mrem / year per pCi/m' NUCLIDE - - - - - - - - - - - - - - - - - = - =

==----- -

==-----------------.-ODY THYROID KIDNEY LUNG Gl-LU BONE LIVER TB H-3 0.00EI00 i.12E+ 03 i.12E +b3 1.12EIb3 1.12E + 03 5.125I03 5.12EIO3

~ ~ 4 C-14 3.59E + 04 6.73E + 03 - 6.73E + 03 6.73E + 03 6.73E + 03 6.73E + 03 6.73E + 03 j CR-51 0.00E + 00 0.00E + 00 1.54E + 02 8.55E + 01 2.43E + 01 1.70E + 04 1.08E + 03 5E-5I b.00Eb0 4.29E b4 b.51E + 03 0 00E 500 1.00E + 04 158E + 06 2.29E + 04 f ~ ~ FE-55 4.74E + 04 2.52E + 04 7.77E + 03 0.00E+ 00 0.00E+ 00 1.11 E + 05 2.87E + 03 FE-59 2.07E + 04 3.34E + 04 1.67E + 04 0.00E + 00 0.00E + 00 1.27E + 06 7.07E 4 04 l f ~ ~~ 5I5 bI005I00 i.775+ 03 3.16E+ b3 b.00E+b0 0.00E + b~0 5.~11E+~b6 3.44E + 04 5 CO-60 0.00E 4 00 1.31 E + 04 2.26E + 04 0.00E + 00 0.00E + 00 7.07E + 06 9.62E + 04 -l i __ -63 8.21 E + 05 4.63E + 04 2.80E + 04 0.00E + 00 0.00E + 00 2.75E + 05 6.33E + 03 NI ..____....-.........____....- _.....=-- ZN-65 4.26E + 04 1.13E + 05 7.03E + 04 0.00Ei 00 7.14E+ 04 9.95E + 05 1.63E + 04 RB-86 0.00E + 00 1.98E + 05 1.14E + 05 0.00E + 00 0.00E + 00 0.00E4 00 7.99E + 03 l SR-89 5.99E + 05 0.00E + 00 1.72E4 04 0.00E + 00 0.00E + 00 2.16E + 06 1.67E + 05 SR-90 1.01E + 08 0.00E + 00 6.44E + 06 0.00E + 00 0.00E + 00 1.48E + 07 3.43E + 05 Y-91 9.14E + 05 0.00E + 00 2.44E + 04 0.00E + 00 0.00E + 00 2.63E + 06 1.84E + 05 l ZR-95 1.90E + 05 4.18E + 04 3.70E + 04 0.00E + 00 5.96E + 04 2.23E + 06 6.11E + 04 l =.- NB-95 2.35E + 04 9.18E + 03 6.55E + 03 0.00E + 00 8.62E + 03 6.14E + 05 3.70E + 04 RU-103 2.79E + 03 0.00E + 00 1.07E + 03 0.00E + 00 7.03E + 03 6.62E + 05 4.48E + 04 i AG-110M 1.69E + 04~~i.~14E+ b~4 b.~14E + 03 0.00E + 00~~b.~12EI~04~~5.48EA06 15EIO5~ l RU-106 1.36E + 05 0.00E + 00 1.69E + 04 0.00E + 00 1.84E + 05 1.43E + 07 4.29E + 05 ~ ~ ~ TE-125M 6.73E+ 03 2.33E + 03 9.14E + O2 1.92E + 03 0.00E + 00 4.77E + 05 3,38E + 04 TE-127M 2.49E + 04 8.55E + 03 3.02E + 03 6.07E + 03 6.36E + 04 1.48E + 06 7.14E + 04 l TE-129M 1.92E + 04 6.85E + 03 3.04E + 03 6.33E + 03 5.03E + 04 1.76E + 06 1.82E 4 05 l l l-131 4.81 E + 04 4 81E + 04 2.73E + 04 1.62E + 07 7.88E + 04 0.00E + 00 2.84E + 03 l133 1.664404 2.03E + 04 7.70E + 03 3.85E + 06 3.38E + 04 0.00E + 00 - 5.48E + 03 i TSU34~ '~ 6IS1EIbb~i.~01EIOb~b.~25EIO5 UIO0Ed00 3I30E b~5~i.'21EIO5 3.85E + 03 ~ ~ ~ ~ ~ ~ CS-136 6.51 E + 04 1.71 E + 05 1.16E + 05 0.00E + 00 9.55E + 04 1.45E + 04 4.18E + 03 i CS-137 9.07E + 05 8.25E + 05 1.28E + 05 0.00E+ 00 2.82E+ 05 1.04E + 05 3.62E + 03 BA-140 7.40E + 04 6.48E + 01 4.33E + 03 0.00E + 00 2.11 E + 01 1.74E + 06 1.02E + 05 CE-141 3.92E + 04 1.95E + 04 2.90E + 03 0.00E + 00 8.55E+ 03 5.44E + 05 5.66E + 04 CE-144 6.77E 4 06 2.12E + 06 3.61E 4 05 0.00E + 00 1.17E + 06 1.20E + 07 3.89E + 05 j =._-_-_.--........-.. --...._..................__..___....-........_. PR-143 1.85E + 04 5.55E + 03 9.14E + O2 0.00E + 00 3.00E + 03 4.33E + 05 9.73E + 04 i ND-147 1.08E 4 04 8.73E + 03 6.81E4 02 0.0CE 00 4.81 E + 03 3.28E + 05 8.21 E + 04 ............. - _ =. _..... _... _ _ .=........ l 63.0 nm.

Wmbor (UClear M Radiological Controls Departmental Procedure 6610-PLN-4200.01 Titie. Revision No. Offsite Dose Calculation Manual (ODCM) 3 TABLE 5.2.3 l Pathway Dose Factors, Ri AGE GROUP: TEEN PATHWAY: INHALATION [ l = ---__=__._______________=-- = - - ORGAN DOSE FACTORS; mrem / year per pCi/m' t NUCLIDE t = =----- -- BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI f H-3 0.00E + 00 1.27E + 03 1.27E + 03 1.27E + 03 1.27E + 03 1.27E+ 03 1.27E+ 03 i C-14 2.60E 4 04 4.87E + 03 4.87E + 03 4.87E + 03 4.87E + 03 4.87E + 03 4.87E + 03 CR-51 0.00E + 00 0.00E + 00 1.35E + 02 7.50E + 01 3.07E + 01 2.10E + 04 3.00E + 03 ~il 54~~~ ~~b.~00E+~iO~~511E+i4~b.~40E+~ 03 b.~00E+~b0 1.27E + 04 1.98E + 06 6dE+b4 l ~ ~ ~ ~~ ~ FE-55 3.34E + 04 2.38E + 04 5.54E + 03 0.00E + 00 0.00E + 00 1.24E + 05 6.39E + 03 l FE-59 1.59E + 04 3.70E + 04 1.43E + 04 0.00E + 00 0.00E + 00 1.53E + 06 1.78E+ 05 CO-58 b.00E+~00 ~~ ~~E+~03~~b"78E + 03 b.00E + 00 OEE + 00 1.34E + 06 9.52E + 04 ~ ~~~~ ~~~ 2.07 CO-60 0.00E + 00 1.51 E + 04 1.98E + 04 0.00E + 00 0.00E + 00 8.72E + 06 2.59E + 05 l NI-63 5.80E + 05 4.34E + 04 1.98E + 04 0.00E + 00 0.00E + 00 3.07E + 05 1.42E + 04 ZN-65 3.86E + 04 1.34E + 05 6.24E + 04 0.00E + 00 8.64 E + 04 1.24E + 06 4.66E+ 04 ' RB-86 0.00E + 00 1.90E + 05 8.40E+ 04 0.00E + 00 0.00E + 00 0.00E + 00 1.77E + 04 f SR-89 4.34 E + 05 0.00E + 00 1.25E + 04 0.00E 4 00 0.00E + 00 2.42E + 06 3.71 E + 05 .._=- l SR-90 1.08E + 08 0.00E + 00 6.68E + 06 0.00E + 00 0.00E + 00 1.65E + 07 7.65E + 05 Y-91 6.61E + 05 0.00E+ 00 1.77E + 04 0.00E + 00 0.00E + 00 2.94E + 06 4.09E + 05 i ZR-95 1.46E + 05 4.58E + 04 3.15E + 04 0.00E + 00 6.74E + 04 2.69E + 06 1.49E + 05 ___________ __= NB-95 1.86E + 04 1.03E + 04 5.66E + 03 0.00E + 00 1.00E + 04 7.51E + 05 9.68E + 04 l RU-103 2.10E + 03 0.00E + 00 8.96E + 02 0.00E + 00 7.43E + 03 7.83E + 05 1.09E + 05 RU 106 9.84E + 04 0.00E + 00 1.24E + 04 0.00E + 00 1.90E+ 05 1.61 E + 07 9.60E+ 05 l .=_- AG-110M 1.38E + 04 1.31 E + 04 7.99E + 03 0.00E + 00 2.50E+ 04 6.75E + 06 2.73E + 05 t TE-125M 4.88E + 03 2.24E + 03 6.67E + 02 1.40E + 03 0.00E + 00 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 + 05 l TE-129M 1.39E + 04 6.58E + 03 2.25E + 03 4.58E + 03 5.19E + 04 1.98E + 06 4.05E 4 05 1131 3.54E + 04 4.91E 4 04 2.64E + 04 1.46E + 07 ' 8.40E + 04 0.00E + 00 6.49E + 03 j l__-133 1.22E + 04 2.05E + 04 6.22E + 03 2.92E + 06 3.59E + 04 0.00E + 00 1.03E+ 04 j = - = - - - - - - - - = - - - - =__... CS-134 5.02E 4 05 1.13E + 06 5.49E 4 05 0.00E + 00 3.75E + 05 1.46E + 05 9.76E4 03 CS-136 5.15E + 04 1.94E 4 05 1.37E + 05 ~ 0 n0E + 00 1.10E + 05 1.78E + 04 1.09E+ 04 l CS-137 6.70E + 05 8.48E + 05 3.11 E + 05 0voE+00 3.04E + 05 1.21 E + 05 8.48E + 03 r =___... -.___....__-_==- BA-140 5.47E + 04 6.70E + 01 3.52E + 03 0.00E + 00 2.28E + 01 2.03E + 06 2.29E+ 05 CE-141 - 2.84E + 04 1.90E + 04 2.17E + 03 0.00E + 00 8.88E + 03 6.14E + 05 1.26E + 05 i CE-144 4.89E + 06 2.02E 4 06 2.62E + 05 0.00E+ 00 1.21 E + 06 - 1.34E 4 07 8.64E + 05 PR-143 1.34E + 04 5.31 E + 03 6.62E + 02 0.00E + 00 3.09E + 03 4.83E + 05 2.14E + 05 j ND-147 7.86E + 03 8.56E + 03 5.13E+02 0.00E + 00 5.02E + 03 3.72E + 05 1.82E + 05 l --.._____._...._....___- = t i j 64 0 m i v

i Number ' ? (UCl Gar TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 A Tme Revision No. Offsite Dose Calculation Manual (ODCM) 3 h i' TABLE 5.2.4 Pathway Dose Factors, Ri l AGE GROUP: ADULT PATHWAY: INHALATION NUCUDE - - - - - - - - - = = i BONE UVER T. BODY THYROID KIDNEY LUNG GI-LLI - - - _ _ _ _ _ _ _ _ = = H-3 0.00E + 00 1.26E + 03 1.26E + 03 1.26E + 03 1.26E + 03 1.26E4 03 1.26E + 03 C-14 1.82E 4 04 3.41 E + 03 3.41 E + 03 3.41 E + 03 3.41 E + 03 ' 3.41 E + 03 3.41E+ 03 CR 51 0.00E + 00 0.00E + 00 1.00E + 02 5.95E + 01 2.28E + 01 1.44E + 04 3.32E + 03 MN-54 0.00E + 00 3.96E + 04 6.30E + 03 0.00E + 00 9.84E + 03 1.40E + 06 7.74E + 04 FE-55 2.46E + 04 1.70E + 04 3.94E + 03 0.00E + 00 0.00E + 00 7.21E + 04 6.03E + 03 FE-59 1.18E + 04 2.78E+ 04 1.06E4 04 0.00E + 00 0.00E + 00 1.02E + 06 1.88E + 05 UE0E+00 1.58E + 03 2.07EIOb b5d+'b0 bb5+"00 9.28E + 05 1.06E4 05 ~ CCh58 CO-60 0.00E + 00 1.15E + 04 1.48E + 04 0.00E + 00 0.00E + 00 5.97E +06 2.85E+ 05 NI63 4.32E + 05 3.14E + 04 1.45E + 04 0.00E + 00 0.00E 4 00 1.78E + 05 1.34E + 04 =__ __________ --=______________________________________.__=.90E+04 8.64E + 05 - 5.34E + 04 _ _ _ = ZN-65 3.24E + 04 1.03E + 05 4.66E + 04 0.00E + 00 6 RB-86 0.00E + 00 1.35E + 05 5.90E + 04 0.00E + 00 _ 0.00E + 00 0.00E + 00 1.66E + 04 i SR-89 3.04E + 05 0.00E + 00 8.72E + 03 0.00E + 00 0.00E + 00 1.40E + 06 3.50E + 05 ~ E b'6~ BEE +0O 0.00E + 00 9.60E + 06 7.225 b5' ~ kbb b.~92E+'07 b.00E + 00 '~' S 6.10 Y-91 4.62E + 05 0.00E + 00 1.24E + 04 0.00E + 00 0.00E + 00 1.70E + 06 3.85E + 05 ' [ ZR-95 1.07E + 05 3.44E + 04 2.33E + 04 0.00E + 00 5.42E + 04 1.77E + 06 1.50E + 05 i _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ = = _ _ = - - - NB-95 1.41 E + 04 7.82E + 03 4.21 E + 03 0.00E + 00 7.74E+ 03 5.05E + 05 1.04E + 05 j RU-103 1.53E + 03 0.00E + 00 6.58E + 02 0.00E + 00 5.83E + 03 5.05E + 05 1.10E + 05 l 2 RU 106 6.91 E + 04 0.00E + 00 8.72E + 03 0.00E + 00 1.34E + 05 9.36E + 06 9.12E + 05 . - - = _ _ _ _ _

=== = - = _ _ _ _ _ _ _ _. _ _ _ _ _ _ _ _ _ - - =-- AG-110M 1.08E + 04 1.00E + 04 5.94E + 03 0.00E + 00 1.97E + 04 4.63E + 06 3.02E + 05 TE-125M 3.42E + 03 1.5SE + 03 4.67E + 02 1.05E + 03 1.24E + 04 3.14E + 05 7.06E + 04 TE-127M 1.26E + 04 5.77E + 03 1.57E + 03 3.29E + 03 4.58E + 04 ' 9.60E + 05 1.50E + 05 I TE-129M 'b.~76EIbb~i67EIO3-1.58E5b3 3.44EAb3 3.66E504 1.16E +b~6 3.83E + 05~ l ~ ~ ~ l-131 2.52E + 04 3.58E + 04 2.05E + 04 1.19E + 07 6.13E + 04 0.00E4 00 6.28E + 03 i I133 8.64E + 03 1.48E + 04 4.52E + 03 2.15E + 06 2.58E + 04 0.00E + 00 8.88E+ 03 - - - = - - - CS-134 3.73E + 05 8.4 SE + 05 7.28E + 05 0.00E + 00 2.87E + 05. 9.76E + 04 1.04E + 04 CS-136 3.90E + 04 1.46E + 05 1.10E+ 05 0.00E + 00 8.56E + 04 1.20E + 04 1.17E 4 04 CS-137 4.78E 4 05 6.21 E + 05 4.28E + 05 0.00E + 00 ?*

05 7.52E + 04 8.40E + 03. -

BA-140 3.90E + 04 4.90E + 01 2.57E + 03 0.00E + 00 1.6. s1 1.27E + 06 2.18E + 05 CE-141 1.99E + 04 1.35E + 04 1.53E + 03 0.00E + 00 6 26E + 03 3.62E + 05 1.20E + 05 - J CE-144 3.43E + 06 1.43E + 06 1.84 E + 05 0.00E + 00 8.48E + 05 7.78E + 06 8.16E + 05 i PR-143 9.36E + 03 3.75E + 03 4.64E + 02 0.00E + 00 2.16E + 03 2.81E + 05 2.00E + 05 ND 147 5.27E + 03 6.10E + 03 3.65E + O2 0.00E4 00 3.56E + 03 2.21 E + 05 1.73E + 05 . _____________________________._____ ___ ___-=-- __ _=. d a i 65.0 nm i

~ Number gggg TMI Radiological Controls Depanmental Procedure 6610-PLN-4200.01 1 Title Revision No. .l Offsite Dose Calculation Manual (ODCM) 3 TABLE 5.3.1 Pathway Dose Factors, Ri i AGE GROUP: ALL PATHWAY: GROUND PLANE i ORGAN DOSE FACTORS

e 1NUCUDE

---I T. BODY SKIN p_ l H-3 0.00E + 00 0.00E + 00 l l C-14 0.00E + 00 0.00E + 00 ! l CR-51 4.65E + 06 5.50E + 06 l i p- - = = _ _ _.i j MN-54 1.39E + 09 1.62E+ 09 L l FE-55 0.00E + 00 0.00E + 00 l ! FE-59 2.73E + 08 3.21E + 08 : p- - _________4 l CO-58 3.79E + 08 4.44E+ 08 l l CO-60 2.15E 410 2.53E + 10 l I NI-63 0.00E + 00 0.00E+ 00 l ________4 p- -- l ZN-65 7.47E + 08 8.59E+ 08 l l RB-86 8.97E + 06 1.03E + 07 l [ I SR-89 2.16E + 04 2.51E + 04 l p-l' SR-90 0.00E + 00 0.00E + 00 ' lY-91 1.07E + 06 1.21E + 06 i ZR-95 2.45E + 08 2.84E + 08 o p-3 NB-95 1.37E + 08 1.61E + 08 l l RU-103 1.08E + 08 1.26E + 08 l i l RU-106 4.22E + 08 5.06E + 08 l -.{ p___ j AG-110M 3.44E + 09 4.01E + 09 ! j l TE-125M 1.55E + 06 2.13E + 06 i l l TE _127M 9.17E + 04 1.08E+ 05 's.; p_ _ _ -- _ - - - = = -

TE-129M 1.98E + 07 2.31E + 07 -l j

!l-131 1.72E + 07 2.09E + 07 l I l-133 2.45E + 06 2.98E + 06 ll i p--- ! CS-134 6.86E + 09 8.00E + 09 ' l l CS-136 1.51 E + 08 1.71E + 08. l CS _137 1.03E + 10 1.20E + 10 p_ _ _ _ = -- _4 l BA-140 2.06E + 07 2.36E + 07 : l CE-141 1.37E + 07 1.54E + 07 ! CE-144 6.96E + 07 8.05E + 07 k 4 r p- ' PR-143 0.00E + 00 0.00E+0b j i ND-147 8.39E + 06 1.01E+ 07 l c _- __________s

m'- mrem / year per Ci/sec.

66.0 twa I

Number 4tJClear i R di i g i connois Departmen'.at Procedure 6610-PLN-4200.01 j w.

a. vision no.

I Offsite Dose Calculation Manual (ODCM) 3 TABLE 5.4.1 ? .t Pathway Dose Factors, Ri AGE GROUP: INFANT PATHWAY: GRASS-COW-MILK l NUCLlDE i =. B O DY THYROID KIDNEY LUNG GI-LLI BONE LIVER T . - - - - - -, - - - = - H-3 0.00E4 00 2.38E + 03 2.38E + 03 2.38E + 03 2.38E + 03 2.38E + 03 2.38E + 03 C-14 2.34E 4 09 5.00E + 08 5.00E + 08 5.00E + 08 5.00E+ 08 5.00E + 08 5.00E + 08 CR 51 0.00E + 00 0.00E + 00 1.61 E + 05 1.05E + 05 2.30E + 04 2.05E + 05 4.70E + 06 i MN-54 0.00E + 00 3.91 E + 07 8.85E + 06 0.00E + 00 8.65E + 06 0.00E + 00 1.43E + 07 FE-55 1.35E + 08 8.74E + 07 2.34E + 07 0.00E + 00 0.00E + 00 4.27E + 07 1.11 E + 07 FE-59 2.25E + 08 3.93E + 08 1.55E + 08 0.00E + 00 0.00E + 00 1.16E + 08 1.88E + 08 ~~ ~~5+~07~~UEE + U"7~UIO5E+00~~~~UIO05+~00 0.00E + 00~ ~U.~055+~07~~ ~~ ~ ~ ~b'O58"~ UIO0E ~00 ~ ~ 2.43 CO.60 0.00E + 00 8.83E + 07 2.08E + 08 0.00E + 00 0.00E + 00 0.00E + 00 2.10E + 08 NI-63 3.50E + 10 2.16E + 09 1.21 E + 09 0.00E + 00 0.00E + 00 0.00E + 00 1.08E + 08 ZN45 5.56E 4 09 1.91 E + 10 8.79E + 09 0.00E + 00 9.24E + 09 0.00E + 00 1.61 E + 10 RB-86 0.00E + 00 2.23E + 10 1.10E + 10 0.00E + 00 0.00E + 00 0.00E + 00 5.70E + 08 SR-89 1.26E + 10 0.00E + 00 3.62E + 08 0.00E + 00 0.00E + 00 0.00E + 00 2.59E+ 08 SR 0 1[225 l1 bTO05 00 3105 50 b505 00 6.00b+b0 bT005+00 1.525+ 09 -l ~ ~ Y-91 7.34E + 04 0.00E + 00 1.95E + 03 0.00E + 00 0.00E + 00 0.00E + 00 5.26E 4 06 ZR-95 6.81 E + 03 166E + 03 1.18E + 03 0.00E + 00 1.79E + 03 0.00E + 00 8.27E + 05 =...---------... NB-95 5.94 E + 05 2.45E + 05 1.41 E + 05 0.00E + 00 1.75E + 05 0.00E + 00 2.07E + 08 RU-103 8.68E 4 03 0.00E + 00 2.90E + 03 0.00E + 00 1.81 E + 04 0.00E4 00 1.06E + 05 RU-106 1.91 E + 05 0.00E + 00 2.38E + 04 0.00E + 00 2.25E + 05 0.00E + 00 1.45E + 06 AG-110M 3.86E + 08 2.82E + 08 1.87E + 08 0.00E + 00 4.03E + 08 0.00E + 00 1.46E + 10 i TE-125M 1.51 E + 08 5.05E + 07 2.04E + 07 5.08E + 07 0.00E + 00 0.00E + 00 7.19E + 07 i TE-127M 4.22E + 08 1.40E + 08 5.10E + 07 1.22E + 08 1.04E + 09 0.00E 4 00 1.70E + 08 TE-129M 5.58E + 08 1.91 E + 08 8.59E + 07 2.14 E + 08 1.39E + 09 0.00E + 00 3.33E + 08 l-131 2.72E + 09 3.21 E + 09 1.41 E + 09 1.05E + 12 3.75E+ 09 0.00E + 00 1.15E + 08 i 1-133 3.63E + 07 ' 5.29E + 07 1.55E + 07 9.62E + 09 6.22E + 07 0.00E + 00 8.96E + 06 i - -... = - - CS-134 3.65E + 10 6.81 E + 10 6.88E + 09 0.00E+ 00 1.75E + 10 7.19E + 09 1.85E + 08 CS-136 1.98E + 09 5.83E + 09 2.18E + 09 0.00E + 00 2.32E + 09 4.75E + 08 8.85E + 07 i CS-137 5.15E+10 6.03E + 10 4.27E + 09 0.00E + 00 1.62E + 10 6.55E + 09 1.89E + 08 i' BA-140 2.42E 4 08 2.42E + 05 1.25E + 07 0.00E + 00 5.75E + 04 1.49E + 05 5.94E + 07 CE-141 4.34E + 04 2.65E + 04 3.12E + 03 0.00E + 00 8.17E + 03 0.00E + 00 1.37E + 07 i CE-144 2.33E + 06 9 53E + 05 1.30E + 05 0.00E + 00 3.85E + 05 0.00E + 00 1.34E + 08 l - -.. - - - -.... - -... - - - - - - - - - - - -.. - - - - - -... -... - - - - - - - _ - = = _.----------- PR-143 1.49E + 03 5.56E 4 02 7.37E 4 01 0.00E + 00 2.07E + 02 0.00E + 00 7.84E + 05 ND-147 8.83E + O2 9.07E + 02 5.55E + 01 0.00E + 00 3.50E + O2 0.00E + 00 5.75E + 05 -...-= J l i 67.0 mu

Number -(HClear M Radidopcal Contrds Departmental Procedure 6610-PLN-4200.01 Tme Revision No. Offsite Dose Calculation Manual (ODCM) 3 TABLE 5.4.2 Pathway Dose Factors, Ri AGE GROUP CHILD PATHWAY: GRASS-COW-MILK l

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

2 ORGAN DOSE FACTORS; m - mrem / year per pCl/sec NUCLIDE - - - - - - - - - - - - = - - - - - - - - - - - - - - = - - - - - - - - - - - - - - - -- - ---- --- -- --- -- -- -- ---. B O DY THYROID KIDNEY LUNG Gl-LLI BONE UVER T '4-3 0.00E + 00 1.57E + 03 1.57E+ 03 1.57E + 03 1.57E + 03 1.57E + 03 1.57E + 03 C-14 1.20E + 09 2.39E + 08 2.39E + 08 2.39E + 08 2.39E + 08 2.39E + 08 2.39E+ 08 CR-51 0.00E + 00 0.00E + 00 1.02E + 05 5.65E + 04 1.54E + 04 1.03E + 05 5.40E + 06 ~ E+E6 b.00E+00 5.89E+~06 0.00E + b~0 1.76d+~E7~ ~~ ~ ~~~ ~il5-54 BEE +~~0b 2.10E b'7 5.S9 FE-55 1.12E + 08 5.94E + 07 1.84E + 07 0.00E+ 00 0.00E + 00 3.36E + 07 1.10E + 07 FE-59 1.20E + 08 1.95E + 08 9.70E + 07 0.00E + 00 0.00E + 00 5.65E4 07 2.03E + 08 CO-58 0.00E + 00 1[21E+b7 3I72E+~07~~5.~00E + 00 b.00E+00 55E+~~00 7.08E + 07 ~~ ~ l CO-60 0.00E + 00 4.32E + 07 1.27E + 08 0.00E + 00 0.00E + 00 0.00E + 00 2.39E + 08 i NI-63 2.97E + 10 1.59E + 09 1.01E + 09 0.00E + 00 0.00E + 00 0.00E + 00 1.07E + 08 ZN-65 4.14E + 09 1.10E + 10 6.86E + 09 0.00E + 00 6.95E + 09 ' O.00E + 00 1.94E + 09 RB-86 0.00E + 00 8.78E + 09 5.40E + 09 0.00E + 00 0.00E + 00 0.00E + 00 5.65E + 08 SR-89 6.63E + 09 0.00E + 00 1.89E+ 08 0.00E + 00 0.00E,30 0.00E + 00 2.57E+ 08 _ = _ = - - - - - - - - - - - - - - - - - - - - - - - - - - - - -... = =-_=.......-- SR-90 1.12E + 11 0.00E + 00 2.84E + 10 0.00E + 00 0.00E + 00 0.00E + 00 1.51E+ 09 Y-91 3.91 E + 04 0.00E + 00 1.05E + 03 0.00E + 00 0.00E + 00 0.00E + 00 5.21E+ 06 ZR-95 3.84E + 03 8.43E+O2 7.51 E + 02 0.00E + 00 1.21E + 03 0.00E + 00 8.80E + 05 N %95 3.18E + 05 1.24E + 05 8.86E + 04 0.00E+00 1.16E+b5 0.50d+~~00 2.29E + 08 ~ ~~ RU-103 4.29E + 03 0.00E + 00 1.65F + n3 0.00E+ 00 1.08E + 04 0.00E + 00 1.11E + 05 = RU-106 9.25E + 04 0.00E + 00 1.15E + 04 0.00E + 0u 1.25E + 05 0.00E + 00 1.44E + 06 _ - = _ __ _ _ = - -...... - - - - -.... - _-= =....--. AG-110M 2.09E + 08 1.41 E + 08 1.13E + 08 0.00E + 00 2.63E+ 08 0.00E + 00 1.68E + 10 TE-125M 7.39E + 07 2.00E + 07 9.85E + 06 2.07E + 07 0.00E + 00 0.00E + 00 7.13E + 07 TE-127M 2.08E + r L61 E + 07 2.47E + 07 4.98E + 07 5.94E + 08 0.00E + 00 1.69E + 08 .3-TE-129M 2.72E + 0ts 7.59E + 07 4.22E + 07 8.76E + 07 7.98E + 08 0.00E+ 00 3.31E + 08 l-131 1.31 E + 09 1.31 E + 09 7.46E + 08 4.34E + 11 2.16E+ 09 0.00E + 00 1.17E + 08 ' l-133 1.72E + 07 2.13E + 07 8.05E + 06 3.95E + 09 3.55E 4 07 0.00E + 00 8.58E+06 ._==___......... CS-134 2.27E + 10 3.72E + 10 7.85E + 09 0.00E+ 00 1.15E + 10 4.14E + 09 2.01E + 08 CS-136 1.01 E + 09 2.79E + 09 1.80E + 09 0.00E + 00 1.49E + 09 2.21E+ 08 9.80E + 07 CS-137 3.23E + 10 3.09E + 10 4.56E + 09 0.00E + 00 1.01 E + 10 3.62E + 09 1.93E + 08 --....... _--=-- . =-------_-------. BA-140 1.18E + 08 1.03E 4 05 6.86E + 06 0.00E + 00 3.35E + 04 6.14E + 04 5.96E + 07 CE-141 2.19E + 04 1.09E + 04 1.62E + 03 0.00E + 00 4.79E + 03 0.00E + 00 1.36E + 07 CE-144 1.63E + 06 5.09E + 05 8.67E + 04 0.00E + 00 2.82E + 05 0.00E + 00 1.33E + 08 PR-143 7.18E + O2 2.16E + 02 3.56E + 01 0.00E + 00 1.17E + O2 0.00E + 00 7.75E + 05 ND-147 4.45E< 02 3.61 E + O2 2.79E + 01 0.00E + 00 1.98E + O2 0.00E + 00 5.71E + 05 -= 68.0 am

P Wmber --(UClear m a di i gi ai Controis Departrnental Procedure 6610-PLN-4200.01 f Title Reveon No. Ohsite Dose Calculation Manual (ODCM) 3 i -h TABLE 5.4.3 e l Pathway Dose Factors, R; AGE GROUP: TEEN PATHWAY: GRASS-COW-MILT ( . = - - -. - = =. _.... _ _ _. = -. NUCUDE =

= = - - - - - - - - - - - -

- - - - - - - - - - - - = = - = =......._......_... '.._.. LUNG _.......-LLI THYROID KIDNEY GI BONE LIVER T. BODY =.. - - - ._==_ H-3 0.00E + 00 9.93E + 02 9.93E + 02 9.93E + 02 9.93E + 02 9.93E + 02 9.93E + 02 C 14 4.86E + 08 9.73E + 07 9.73E + 07 9.73E + 07 9.73E + 07 9.73E + 07 9.73E + 07 CR-51 0.00E + 00 0.00E + 00 4.99E + 04 2.77E + 04 1.09E + 04 7.13E + 04 8.39E + 06 5 54 BOO 5 b0 1T40E b"7 2.78E+~ 06 U.~005 00 k19N+06 b.bOEIb0 2.88NIO7 ~ FE-55 4.46E + 07 3.16E + 07 7.37E + 06 0.00E + 00 0.00E + 00 2.01 E + 07 1.37E + 07 l FE-59 5.19E+07 1.21 E + 08 4.68E + 07 0.00E + 00 0.00E+00 3.82E + 07 2.86E + 08 l CO-58 0.00E + 00 7.94E + 06 1.83E + 07 0.00E + 00 0.00E + 00 0.00E + 00 1.10E + 08 CO-60 0.00E + 00 2.78E + 07 6.27E + 07 0.00E + 00 0.00E + 00 0.00E + 00 3.62E + 08 NI-63 1.18E + 10 8.36E + 08 4.01 E + 08 0.00E + 00 0.00E + 00 0.00E + 00 1.33E + 08 ......... _.... _ _ _ _ _ _.. _ _ _ _ _.. _.... = - - _ =...... ZN45 2.11 E + 09 7.32E + 09 3.42E + 09 0.00E + 00 4.69E + 09 0.00E + 00 3.10E + 09 RB-86 0.00E + 00 4.73E + 09 2.22E + 09 0.00E + 00 0.00E + 00 0.00E + 00 7.00E + 08 j SR 89 2.68E + 09 0.00E + 00 7.67E + 07 0.00E + 00 0.00E + 00 0.00E+ 00 3.19E + 08 ~~ $00EIb~0~b505 b0 1.86E + b~9 ~ ~ ~ SR-90 6.62E [0 0.005 ~00~~ '5E+lb~b.~00E+~00 ~ 0 1. Y-91 1.58E + 04 0.00E + 00 4.24E + 02 0.00E + 00 0.00E + 00 0.00E + 00 6.48E + 06 ZR-95 1.65E + 03 5.21 E + O2 3.58E + 02 0.00E + 00 7.65E + 02 0.00E + 00 1.20E + 06 i ___=-____-_ = NB-95 1.41 E + 05 7.82E + 04 4.30E + 04 0.00E + 00 7.58E + 04 0.00E + 00 3.34E + 08 RU-103 1.81 E + 03 0.00E + 00 7.75E + O2 0.00E + 00 6.39E + 03 0.00E + 00 1.51E + 05 RU 106 3.76E + 04 0.00E + 00 4.73E + 03 0.00E + 00 7.24E + 04 0.00E + 00 1.80E + 06 _=-_=.- = _ - - AG-110M 9.64E + 07 9.12E + 07 5.55E + 07 0.00E + 00 1.74E + 08 0.00E + 00 2.56E + 10 TE-125M 3.01 E + 07 1.08E + 07 4.02E + OS 8.40E + 06 0.00E+ 00 0.00E + 00 8.87E + 07 TE-127M 8.45E + 07 3.00E + 07 1.00E + 07 2.01E + 07 3.42E + 08 0.00E + 00 2.11 E + 08 -.10E+ 08_ _...... - - - - - - - - = _ - _.. - - - =__............ ___.. . -- =.. _ 1 4.09E + 07 1.74E + 07 3.56E + 07 4.61E + 08 0.00E + 00 4.14E + 08 TE-129M l-131 5.38E + 08 7.53E + 08 4.05E + 08 2.20E + 11 1.30E + 09 0.00E + 00 1.49E + 08 l-133 7.08E + 06 1.20E + 07 3.66E + 06 1.68E + 09 2.11 E + 07 0.00E + 00 9.09E + 06 ._.__.--.......---- =- CS-134 9.83E + 09 2.31 E + 10 1.07E + 10 0.00E + 00 7.35E + 09 2.81E + 09 2.88E + 08 CS-136 4.49E + 08 1.77E + 09 1.19E + 09 0.00E + 00 9.63E+ 08 1.52E + 08 1.42E 4 08 CS-137 1.34E + 10 1.78E + 10 6.21E + 09 0.00E + 00 6.06E + 09 2.36E4 09 2.54E + 08 1 . ___ - _ = ---== ___= BA-140 4.87E + 07 5.97E + 04 3.14E + 06 0.00E + 00 2.02E + 04 4.01 E + 04 7.51 E + 07 CE-141 8.89E + 03 5.94E + 03 6.82E + O2 0.00E + 00 2.80E + 03 0.00E + 00 1.70E + 07 lt44 e *E+ 5 223E+p_5._ 3.54E4p_4_ 0.00E 4 00 i.63E 405 0.00E 4 00 i.66e + 08 PR-143 2.90E + O2 1.16E + O2 1.44E + 01 0.00E + 00 6.73E + 01 0.00E + 00 9.55E + 05 i ND-147 1.81 E + 02 1.97E 4 02 1.18E + 01 0.00E + 00 1.16E + O2 0.00E + 00 7.12E + 05 i =- -- - - = = - - - -...... _ L F 69.0 m

Mumber ] bdeM Tui Radiot09 cai Controis i Departmental Procedure 6610-PLN-4200.01 - Title Rewsion No. j f Offsite Dose Calculation Manual (ODCM) 3 TABLE 5.4.4 i Pathway Dose Factors, Ri j r I AGE GROUP: -__.._ _ _ _ _ _...__ _ __ _ __ __._ _ _ _-COW-MILK ADULT PATHWAY: GRASS ---_.= 2 ORGAN DOSE FACTORS; m - mrem / year per pCl/sec NUCLIDE - - - - - - - - - - - - - - - - - - - - - - - - = - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - GI BONE UVER T. BODY THYROID KIDNEY LUNG _ ___ _-LLI ___________.___...... __. ___..._____._________.--= --= H-3 0.00E + 00 7.62E + 02 7.62E + O2 7.62E + 02 7.62E + O2 7.62E + G2 7.62E + 02 l C-14 2.63E + 08 5.26L + 07 5.26E+07 5.26E + 07 5.26E + 07 5.26E + 07 5.26E4 07 l CR-51 0.00E + 00 0.00E + 00 2.85E + 04 1,70E + 04 6.28E + 03 3.78E + 04 7.17E + 06 i ~ 5EIO6 b.00E+~00 2.57E + 07 ~ ~~~ Y[h-54 ~ b5E+00 ~~~~ ~~5 b~6~iE0h+ 06 b OE+b0 8.40 2 FE-55 2.51 E + 07 1.73E + 07 4.04E 4 06 0.00E+ 00 0.00E + 00 9.66E + 06 9.93E + 06 FE-59 2.97E + 07 6.97E + 07 2.67E+ 07 0.00E + 00 0.00E + 00 1.95E + 07 2.32E + 08 CO-58 b~00E+~00~ ~ I.~71E ~06~~i.~05E+~b~7~b5E + 00 6.00E+bb 6.00E + 00 9.54E A 07 f ~ ~ ~ ~~ ~~ 7 CO40 0.00E + 00 1.64E + 07 3.61 E + 07 0.00E + 00 0.00E + 00 0.00E + 00 3.08E + 08 Ni-63 6.72E + 09 4.65E + 08 2.25E + 08 0.00E + 00 0.00E + 00 0.00E + 00 9.71E + 07 l ZN45 1.37E + 09 4.36E + 09 1.97E + 09 0.00E + 00 2.91E+ 09 0.00E + 00 2.74E + 09 RB-86 0.00E 4 00 2.59E + 09 1.21 E + 09 0.00E + 00 0.00E + 00 0.00E+ 00 5.10E + 08 SR-89 1.45E 4 09 0.00E + 00 4.16E + 07 0.00E + 00 0.00E + 00 0.00E + 00 2.32E + 08 i ~ Erbb ~ I.~675I10 0.00E + 00~~~~I.~15EA 10 0.00E+~b0 5.00E + 00 0.00E +b~0~i.55E+09 f ~ ~ ~~ Y-91 8.57E + 03 0.00E + 00 2.29E 4 02 0.00E + 00 0.00E + 00 0.00E + 00 4.72E + 06 ZR-95 9.41E + 02 3.02E 4 02 2.04 E + 02 0.00E + 00 4.74E + 02 0 00E+ 00 9.57E + 05 i ~ ~ ~ ~I.58E+~04~~5.~46E +~04~~~b.~00EI~00~~d.53E+ b4 6.00EAb0 2.78E + 05 ~ ~ ~ NB-95 8.24E + 04 RU-103 1.02E + 03 0.00E 4 00 4.38E + O2 0.00E + 00 3.88E+ 03 0.00E4 00 1.19E + 05 RU-106 2.04E 4 04 0.00E + 00 2.58E + 03 0.00E + 00 3.93E+ 04 0.00E + 00 1.32E + 06 .... ___..._____ _ _- =.._____ _- AG-110M 5.81 E + 07 5.38E + 07 3.19E + 07 0.00E + 00 1.06E + 08 0.00E+ 00 2.19E + 10 TE-125M 1.63E + 07 5.89E + 06 2.18E 4 06 4.89E+ 06 6.61E+ 07 0.00E + 00 6.49E + 07 l - _ _{,,,p 1.53E 3,08,, j 1.63E 0],_,{,57E 4 06 ,,,,,,,,,,,,,,,1,0f-m b 08 1.17E ~ [.57E307 00 ,,,1, TE-129M 6.01E + 07 2.24E + 07 9.51 E+ 06 2.06E + 07 2.51E + 08 0.00E + 00 3.02E + 08 l 1-131 2.96E + 08 4.23E + 08 2.42E + 08 1.39E + 11 7.25E4 08 0.00E + 00 1.12E + 08 i 1-133 3.87E + 06 6.73E + 06 2.05E + 06 9.88E + 08 1.17E + 07 0.00E + 00 6.04E+ 06 ~ ~ ~ ~ ~' CS-134 55E709 i.54EI1b i.10E+10 b.005 ~00 4.34E 4 09 1.44E + 09 2.35E + b'8 l CS-136 2.63E + 08 1.04E 4 09 7.48E + 08 0.00E 4 00 5.78E + 08 7.92E + 0/ 1.18E + 08 CS 137 7.37E 4 09 1.01 E + 10 6.60E4 09 0.00E + 00 3.42E + 09 1.14E + 09 1.95E+ 08 BA-140 2.69E + 07 3.38E + 04 1.76E + 06 0.00E + 00 1.15E + 04 1.94E + 04 5.54E + 07 i CE-141 4.84E + 03 3.27E 4 03 3.71 E + O2 0.00E + 00 1.52E + 03 0.00E + 00 1.25E + 07 E CE-144 3.57E + 05 1.49E + 05 1.92E + 04 0.00E + 00 8.85F4 04 0.00E400 1.21E+ 08 i - - =.. _ _ _ - _ _ PR-143 1.57E 4 02 6.32E + 01 7.81 E + 00 0.00E + 00 3.65E + 01 0.00E + 00 6.90E + 05 i ND-147 9.40E + 01 1.09E + 02 6.50E + 00 0.00E + 00 6.35E+ 01 0.00E + 00 5.22E + 05 i i l 1 i 70.0 rm. j m

t Numbu 9 ai Connois i $UClear 1 m R di i Departmental Procedure 6610-PLN-4200.01 l Title Revision No. - f Offsite Dose Calculation' Manual (ODCM) 3 j i .l f TABLE 5.5.1 Pathway Dose Factors, Ri AGE GROUP: INFANT PATHWAY: GRASS-GOAT-MILK ~ URGAb~DE5EFACTORS; E Ne~rky~ar per pCl/sec ~~ ~ ~ ~~~ e ? t NUCLIDE - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - = = - = = - - - - - - - BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI l E5 b.~00E+E0 k.86EIO3 E.~86E+ 03 d56EIO3 ~ 4.86E + 03 4.86E 03 4.86E + 03 C-14 2.34E + 09 5.00E + 08 5.00E + 08 5.00E + 08 5.00E + 08 5.00E+ 08 5.00E+ 08 CR-51 0.00E + 00 0.00E + 00 1.94E + 04 1.26E + 04 2.76E + 03 2.46E + 04 5.64E + 05 y _ _ = _..._..._ MN-54 0.00E + 00 4.68E 4 06 1.06E + 06 0.00E+ 00 1.04E + 06 0.00E + 00 1.72E + 06 FE-55 1.7t E + 06 1.14E + 06 3.03E + 05 0.00E + 00 0.00E + 00 5.55E+ 05 1.44E+ 05 FE-59 2.92E + 06 5.10E+ 06 2.01E + 06 0.00E+ 00 0.00E+ 00 1.51E + 06 2.44E + 06 -t CO-58 0.00E + 00 2.91E 4 06 7.26E + 06 0.00E + 00 0.00E + 00 0.09E + 00 7.25E + 06 CO-60 0.00E + 00 1.06E 4 07 2.50E + 07 0.00E + 00 0.00E + 00 0.00E + 00 2.52E + 07 Ni-63 4.19E + ')9 2.59E + 08 1.46E + 08 0.00E + 00 0.00E+ 00 0.00E + 00 1.29E+ 07 --... _ - _.. _ _ _ _ _... _ _. - - - = = ..00 E + 00 1.11E + 09 0.00E + 00 1.93E + 09 l 6.67E 4 08 2.29E + 09 1.05E + 09 ZN-65 8 8-86 0.00E + 00 2.67E + 09 1.32E + 09 0.00E + 00 0.00E + 00 0.00E + 00 6.83E + 07 SR-89 2.65E + 10 0 00E + 00 7.59E + 08 0.00E + 00 0.00E + 00 0.00E + 00 5.44E + 08 SR.90 5IS5E+~il 0.00E I00 5IS05+~l0 0.00E700 0.00E + 00 b.~00E + 00 3.1Ed+~0i ~ ~ ~~ Y-91 8.80E + 03 0.00E + 00 2.34E + 02 0.00E + 00 0.00E + 00 0.00E + 00 6.31E + 05 i ZR-95 8.17E + O2 1.99E + 02 1.41 E 4 02 0.00E + 00 2.15E + O2 0.00E + 00 9.91E + 04 NB-95 7.13EIO4 2.93E + 04 1.70E + b4 050EI00 2.10E+ 04 0.00EI00 2.48dIO7 ~ ~ ~~ RU-103 1.04E + 03 0.00E + 00 3.48E + O2 0.00E + 00 2.17E + 03 0.00E + 00 1.27E + 04 { RU-106 2.28E + 04 0.00E + 00 2.85E + 03 0.00E + 00 2.70E + 04 0.00E + 00 1.73E + 05 t AG-110M 4.65IO7 3[38E + 07 dI24E407 b 00EIO0~'~k54E+07 0.00E + 00 1.75E+~i9 ~~~ TE-125M 1.81 E + 07 6.05E + 06 2.45E + 06 6.09E + 06 0.00E+ 00 0.00E+ 00 8.62E + 06 2 TE-127M 5.06E 4 07 L68E+07 6.12E + 06 1.46E + 07 1.24E + 08 0.00E + 00 2.04E+ 07 i, ---==_ __ _==...._ TE-129M 6.69E + 07 2.29E + 07 1.03E + 07 2.57E + 07 1.67E + 08 0.00E + 00 3.99E+ 07 l-131 3.27E + 09 3.85E + 09 1.69E + 09 1.27E + 12 4.50E + 09 0.00E + 00 1.37E + 08 I l-133 4.36E + 07 6.35E + 07 1.86E+ 07 1.15E + 10 7.46E + 07 0.00E + 00 1.07E + 07 j CS-134 1.09E + 11 2.04E + 11 2.06E + 10 0.00E + 00 5.26E + 10 2.15E + 10 5.55E + 08 l CS-136 .5.94E + 09 1.75E + 10 6.52E + 09 0.00E + 00 6.96E + 09 1.42E + 09 2.65E + 08 CS-137 1.54E + 11 1.81 E + 11 1.28E + 10 0.00E + 00 4.85E + 10 1.96E + 10 5.65E+ 08 [ - - - -. - _.. _ _ _. _. - = - BA-140 2.90E + 07 2.90E + 04 1.50E + 06 0.00E + 00 6.89E+ 03 1.78E + 04 7.13E 4 06 j CE-141 5.21 E 4 03 3.18E 4 03 3.74E 4 02 0.00E + 00 9.79E + 02 0.00E + 00 1.64E+ 06 CE 144 2.79E + 05 1.14E 4 05 1.56E + 04 0.00E+ 00 4.62E + 04 0.00E + 00 1.60E+07 i .===..... _......._..=- . - - = =..... -. _.. _... _ _.... l PR 143 1.78E + 02 6.66E + 01 8.83E4 00 0.00E + 00 2.48E + 01 0.00E+ 00 9.4CE + 04 ND-147 1.06E + 02 1.09E + 02 6.66E4 00 0.00E 4 00 4.15E + 01 0.00E 4 00 6.89E + 04 _== = l 71.0 ms 1 ) 4

i e Number l - -gdgy TMl Radiological Controls Departmental Procedure 6610-PLN-4200.01 .{ Tme Msion No. Offsite Dose Calculation Manual (ODCM) 3 [ TABLE 5.5.2 l Pathway Dose Factors, RI AGE GROUP: CHILD PATHWAY: GRASS-GOAT-MILK - -__=_ ORGAN DOSE FACTORS: m' - mrem / year per pCi/sec NUCLIDE - - - - - - - - - - - - = = - - - - - - - - - - - - - - - - - - - - - - - - - - - - = - - - - - - - - - - - - - - - = = BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI 7 H-3 0.00E+ 00 3.20E + 03 3.20E + 03 3.20E + 03 3.20E + 03 3.20E + 03 3.20E + 03 C-14 1.20E + 09 2.39E + 08 2.39E + 08 2.39E + 08 2.39E + 08 2.39E + 08 2.39E+ 08 CR 51 0.00E + 00 0.00E + 00 1.22E + 04 6.78E + 03 1.85E + 03 1.24E + 04 6.48E + 05 t .......... _ _..... - - _ _............... - - = =............_.--_--- I MN-54 0.00E + 00 2.52E + 06 6.71 E + 05 0.00E + 00 7.06E + 05 0.00E+ 00 2.11 E + 06 FE-55 1.45E + 06 7.71 E + 05 2.39E + 05 0.00E + 00 0.00E + 00 4.36E + 05 1.43E + 05 _, gE3pg_ 0.00E+00 7.34E + 05 2.64E + 06 j _,g,,3g,6,,,{.26E;g6 2 E FEj{,__,{pp06 0 CO-58 0.00E 4 00 1.46E + 06 4.46E + 06 0.00E + 00 0.00E4 00 0.00E + 00 8.49E + 06 CO-60 0.00E + 00 5.18E + 06 1.53E + 07 0.00E + 00 0.00E + 00 0.00E + 00 2.87E + 07 NI-63 3.56E + 09 1.91E + 08 1.21 E + 08 0.00E + 00 0.00E + 00 0.00E + 00 1.28E + 07 i =---... ---........ = - - ZN-65 4.96E 4 08 1.32E 4 09 8.22E + 08 0.00E + 00 8.33E + 08 0.00E + 00 2.32E + 08 RB-86 0.00E 4 00 1.05E + 09 6.47E + 08 0.00E + 00 0.00E + 00 0.00E + 00 6.77E + 07 ... -89 1.39E + 10 0.00E + 00 3.97E + 08 0.00E + 00 0.00E + 00 - 0.00E + 00 5.39E + 08 l SR .=z 3 SR-90 2.35E + 11 0.00E + 00 5.95E + 10 0.00E + 00 0.00E + 00 0.00E + 00 3.16E + 09 Y-91 4.69E + 03 0.00E + 00 1.25E + O2 0.00E + 00 0.00E + 00 0.00E + 00 6.24E + 05 ....-95=- __ - _= ( ZR 4.60E + 02 1.01E + 02 9.00E + 01 0.00E + 00 1.45E + 02 0.00E + 00 1.05E + 05 NB-95 3.82E + 04 1.'49E + 04 1.06E + 04 0.00E + 00 1.40E + 04 0.00E + 00 2.75E + 07 l RU-103 5.14E + O2 0.00E + 00 1.98E + 02 0.00E + 00 1.29E + 03 0.00E + 00 1.33E + 04 RU 106 1.11 E + 04 0.00E + 00 1.38E + 03 0.00E + 00 1.50E + 04 0.00E + 00 1.73E + 05 t .... = =-_.-- ---- - _. = = - AG-110M 2.51E + 07 1.69E + 07 1.35E + 07 0.00E + 00 3.15E + 07 0.00E + 00 2.01E + 09 TE-125M 8.86E + 06 2.40E + 06 1.18E + 06 2.49E + 06 0.00E + 00 0.00E + 00 8.55E + 06 TE-127M 2.50E + 07 6.72E + 06 2.96E + 06 5.97E + 06 7.12E + 07 0.00E + 00 2.02E +07 { .................==. _ - - - - = . - - - - - =. -....... _ _ _ - - - - _ TE-129M 3.2GE + 07 9.10E + 06 5.06E + 06 1.05E + 07 9.56E + 07 0.00E 4 00 3.97E + 07 l i 1131 1.57E + 09 1.57E + 09 8.95E + 08 5.21 E + 11 2 58E + 09 0.00E4 00 1.40E+ 08 l-133 2.06E + 07 2.55E 4 07 9.66Ea 06 4.74E + 09 4.23E+ 07 0.00E + 00 1.03E+ 07 .-....-. - _.... - -.. _ _ = _ CS-134 6.80E + 10 1.12E + 11 2.35E +10 0.00E + 00 3.46E + 10 1.24E + 10 6.01 E + 08 CS-136 3.04E 4 09 8.36E + 09 5.41E 4 09 0.00E 4 00 4.45E + 09 6.64E + 08 2.94E + 08 i CS-137 9 68E + 10 9.26E + 10 1.37E + 10 0.00E 4 00 3.02E + 10 1.09E + 10 5.80E + 08 j BA-140 1.41E 4 07 1.24E + 04 8.23E + 05 0.00E + 00 4.02E + 03 7.37E+ 03 7.15E 4 06 CE-141 2.63E 4 03 1.31 E + 03 1.95E 4 02 0.00E + 00 5.74E + O2 0.00E 4 00 1.63E + 06 ) CE-144 1.95E + 05 6.11 E + 04 1.04E + 04 0.00E + 00 3.38E + 04 0.00E + 00 1.59E + 07 i ...........--................._............--.......-_=_ PR-143 8 61E + 01 2.59E + 01 4.27E + 00 0.00E + 00 1.40E + 01 0.00E 4 00 9.29E + 04 i ND-147 5.34E 4 01 4.33E + 01 3.35E 4 00 0.00E + 00 2.37E 4 01 0.00E + 00 6.85E + 04 = 72.0 2m.

Numbor - (UClear m R di i 0 ai Connois 1 Departmental Procedure 6610-PLN-4200.01 Tme Revision No. Offsite Dose Calculation Manual (ODCM) 3 1 TABLE 5.5.3 l Pathway Dose Factors, Ri AGE GROUP: TEEN PATHWAY: GRASS _ GOAT-MILK r NUCLlDE t - - - - - - - - - - - - - - - - - - - =

-- -- --- -- --- ----. B O D Y THYROID KlDNEY LUNG GI-LLI BONE LIVER T

53 b.00E + 00 2.04E + 03 2.04E + 03 2.04E + 03 2.04E + 03 2.04E + 03 2.5E ~03I ~ C-14 4.86E + 08 9.72E + 07 9.72E + 07 9.72E + 07 9.72E + 07 9.72E + 07 9.72E + 07 CR-51 0.00E + 00 0.00E + 00 5.99E + 03 3.33E + 03 1.31E + 03 8.55E + 03 1.01 E + 06 ....._..........._--........_--_.._.._-..=___ - _ _ = _ -.. MN-54 0.00E + 00 1.68E + 06 3.34E + 05 0.00E + 00 5.02E + 05 0.00E + 00 3.45E + 06 FE-55 5.79E + 05 4.11 E + 05 9.58E + 04 0.00E+ 00 0.00E + 00 2.61E + 05 1.78E + 05 FE-59 6.74E 4 05 1.57E + 06 6.08E + 05 0.00E + 00 0.00E + 00 4.96E + 05 3.72E + 06 CO-58 0.00E + 00 9.53E + 05 2.20E 4 06 0.00E + 00 0.00d+ 00 0.00d ~00 1.315 07~~ ~ ~~~ CO-60 0.00E + 00 3.34E + 06 7.52E + 06 0.00E + 00 0.00E + 00 0.00E + 00 4.35E + 07 N!-63 1.42E 4 09 1.00E + 08 ' 4.81 E + 07 0.00E + 00 0.00E + 00 0.00E + 00 1.60E + 07 l =-- ZN-65 2.53E + 08 8.78E + 08 4.10E + 08 0.00E + 00 5.62E + 08 0.00E + 00 3.72E + 08 l RB-86 0.00E+ 00 5.67E+08 2.67E + 08 0.00E + 00 0.00E + 00 0.00E + 00 8.40E + 07 SR-89 5.62E + 09 0.00E + 00 1.61 E + 08 0.00E + 00 0.00E + 00 0.00E + 00 6.69E + 08 ~~ 1.395 il b.005 ~00 3.43E lb 6.5E+00~~~b.~00dA00 0.5dIO0 3.90E + 09 .. t ~~ SR-90 Y-91 1.90E + 03 0.00E + 00 5.09E + 01 0.00E + 00 0.00E + 00 0.00E + 00 7.78E + 05 ZR-95 1.98E + 02 6.25E + 01 4.30E + 01 0.00E + 00 9.18E + 01 0.00E + 00 1.44E + 05 'kB-95 1.695 04 U 38E403 5.16E+ 03 b Od+00 U.095+ 03 b.00d+~00 4.01d+ 07~~ ~~ ~ ~ ~~ ~ i RU-103 2.17E + O2 0.00E + 00 9.29E + 01 0.00E+ 00 7.66E + O2 0.00E + 00 1.82E + 04 l RU-106 4.50E + 03 0.00E + 00 5.68E + O2 0.00E + 00 8.69E + 03 0.00E + 00 2.16E + 05 i - =............ _ _ AG-110M 1.16E + 07 1.09E + 07 6.65E + 06 0.00E + 00 2.09E + 07 0.00E + 00 3.07E + 09 TE-125M 3.61E + 06 1.30E + 06 4.82E + 05 1.01E + 06 0.00E + 00 0.00E + 00 1.06E + 07 I TE-127M 1.01E + 07 3.59E + 06 1.20E + 06 2.41E + 06 4.11 E + 07 0.00h'+ 00 2.52E + 07 -=_ =-- ----- TE-129M - 1.32E + 07 4.90E + 06 2.09E + 06 4.26E + 06 5.53E+07 0.00E + 00 4.96E + 07 1-131 6.45E + 08 9.03E + 08 4.85E + 08 2.64E + 11 1.56E + 09 0.00E + 00 1.79E + 08 l133 8.49E + 06 1.44E + 07 4.40E + 06 2.01 E + 09 2.53E + 07 0.00E + 00 1.09E+ 07 CS-134 2.95E + 10 6.93E + 10 3.22E + 10 0.00E + 00 2.20E + 10 8.41E + 09 8.62E + 08 i CS-136 1.35E + 09 5.30E + 09 3.56E + 09 0.00E + 00 2.89E + 09 4.55E + 08 4.27E + 08 l CS-137 4.02E + 10 5.34E + 10 1.86E + 10 0.00E + 00 1.82E + 10 7.07E + 09 7.60E + 08 i = = _ _ _ - = - - _ _ _ _ _ _.. _ _ _.. _ _. _.... - _ _. _... _ _ _ _=-- i BA-140 5.84E 4 06 7.16E + 03 3.76E 4 05 0.00E4 00 2.43E + 03 4,81 E + 03 9.01 E + 06 CE-141 1.07E + 03 7.12E 4 02 8.18E + 01 0.00E 4 00 3.35E 4 02 0.00E + 00 2.04E + 06 CE-144 /.90E + 04 3.27E + 04 4.25E + 03 0.00E + 00 1.95E + 04 0.00E+ 00 1.99E + 07 -- -__= PR-143 3.48E + 01 1.39E + 01 1.73E + 00 0.00E 4 00 8.08E + 00 0.00E4 00 1.15E 4 05 i ND-147 2.18E + 01 2.37E + 01 1.42E + 00 0.00E + 00 1.39E + 01 0.00E + 00 8.54E + 04 = - - - -- a i 73.0 m i

fdumber l NUCIear '"' "* di ' 9' ^' i Departmental Procedure 6610-PLN-4200.01 .j hile Revision No. l 1 Offsite Dose Calculation Manual (ODCM) 3-j l TABLE 5.5.4 l Pathway Dose Factors, Ri i AGE GROUP: ADULT PATHWAY GRASS-GOAT-MILK NUCUDE - - - - - - - - - - = - - = = = - = - = = - - -==---- -- -- ------ --- ---- - ------. B O D Y -....' THYROID KIDNEY LUNG GI_LLI-= l BONE UVER T H-3 0.00E + 00 1.56E + 03 1.56E + 03 1.56E + 03 1.56E + 03 1.56E + 03 1.56E + 03 - C-14 2.64E + 08 5.27E + 07 5.27E + 07 5.27E + 07 5.27E + 07 5.27E + 07 5.27E+07 CR-51 0.00E + 00 0.00E + 00 3.43E + 03 2.05E + 03 7.56E + O2 4.55E + 03 8.63E + 05 MN-54 0_00E + 00 1.01E + 06 1.93E + 05 0.00E + 00 3.01E + 05 0.00E + 00 3.10E + 06 FE-55 3.27E + 05 2.26E + 05 5.26E + 04 0.00E + 00 0.00E + 00 1.26E + 05. 1.30E + 05 --..-59 3.87E + 05 9.09E + 05 3.48E + 05 0.00E + 00 0 00E + 00 2.54E + 05 3.03E + 06 FE ..-... ------.........=_- =...... CO-58 0.00E + 00 5.66E + 05 1.27E + 06 0D 0 00 0.00E + 00 0.00E + 00 1.15E + 07 CO-60 0.00E+ 00 1.97E + 06 4.35E ' % 0.00E + 00 0 00E+ 00 0.00E + 00 3.70E + 07 I NI-63 8.08E 4 08 5.60E + 07 2.71 E + 07 0.00E + 00 0.00E + 00 0.00E + 00 1.17E + 07 t

==.--. ZN-65 1.65E + 08 5.24E + 08 2.37E + 08 0.00E + 00 3.5'E+ 08 0.00E + 00 3.30E + 08 i RB-86 0.00E + 00 3.12E + 08 1.45E + 08 0.00E + 00 0.00E + 00 0.00E + 00 6.14E + 07 SR-89 3.05E + 09 0.00E + 00 8.76E4 07 0.00E + 00 0.00E + 00 0.00E + 00 4.89E + 08 SR-90 9.84d [0 b.00E$00 2.41E$i0 0.00N 00 b.00E + 00 b.00E5b0 2d4E+09 ~ ~ r ~ Y-91 1.03E + 03 0.00E + 00 2.76E + 01 0.00E + 00 0.00E + 00 0.00E + 00 5.68E + 05 ZR-95 1.13E + 02 3.63E + 01 2.46E + 01 0.00E 4 00 5.70E+ 01 0.00E + 00 1.15E + 05 NB-9b hT92EIO3 bI52E+ 03 b.'97E+ bb 0.00E + 00 5I45E403 0 00E + b~0~5I35d+07~~ ~ ~ ~ ~ ~ ~' j RU-103 1.22E + 02 0.00E + 00 5.27E + 01 0.00E + 00 4.67E 4 02 0.00E + 00 1.43E + 04 l RU-106 2.45E + 03 0.00E + 00 3.10E + O2 0.00E + 00 4.73E + 03 0.00E+ 00 1.59E+ 05 AG-110M 6.9dE + 06 UI47E+06 5.~84E + b6 0.00d + 00 1.27E + 07 050E+~00 5~64E + 09 ~ ~ ~ TE-125M 1.96E + 06 7.09E + 05 2.62E + 05 5.89E + 05 7.96E + 06 0.00E + 00 7.81E + 06 TE-127M 5.50E 4 06 1.97E + 06 6.70E + 05 1.41 E + 06 2.23E +07 0.00E + 00 1.84E + 07 [ = - = -.......... r TE-129M 7.23E + 06 2.70E + 06 1.14E + 06 2.48E + 06 3.02E + 07 0.00E + 00 3.64E + 07 l-131 3.56E + 08 5.09E + 08 2.92E + 08 1.67E + 11 8.73E + 08 0.00E + 00 1.34E + 08 l 4.65E + 06 8.10E + 06 2.47E + 06 1.19E + 09 1.41 E + 07 0.00E + 00 7 28E + 06 l .-133_ _ _ _ - _. CS-134 1.70E + 10 4.04E + 10 3.30E + 10 0.00E + 00 1.31E + 10 4.34E + 09 7.07E + 08 l CS-136 7.92E + 08 3.13E + 09 2.25E + 09 0.00E + 00 1.74E + 09 2.38E + 08 3.55E + 08 CS-137 2.22E + 10 3.03E + 10 1.99E + 10 0.00E + 00 1.03E + 10 3.42E + 09 5.87E + 08 ~~~IO75 b~3~E~12IdI05~~U.~00d+~00 1.38E + 03 2.33E+ 03 5.~67E+ 06 ~~ ~ ~' ~ ~~ Bh-140 3.24E706 4 CE-141 5.82E + 02 3.94E + 02 4.47E + 01 0.00E + 00 1.83E + 02 0.00E + 00 1.51E+ 06 CE-144 4.30E + 04 1.80E4 04 2,31 E + 03 0.00E + 00 1.07E + 04 0.00E + 00 1.45E + 07 PR-143 1.90E + 01 7.60E + 00 9.40e-01 0.00E h 00 4.39E + 00 0.00E + b0 bI30E+~04~~ ~~ ND-147 1.13E + 01 1.31 E + 01 7.82e41 0.00E + 00 7.65E + 00 0.00E + 00 6.28E + 04 l d 74.0 mm. l

a MumhOr bdeM TMi nadi i gi ai Controts Departmental Procedure 6610-PLN-4200.01 htie Revision No. Offsite Dose Calculation Manual (ODCM) .3' i TABLE 5.6.1 Pathway Dose Factors, Ri j -..._._g,,,g,j]NFANT PATHWAY: GRASS-C0W-MEAT j ^OE R0 P ORGAN DOSE FACTORS; m' - mrem / year per pCi/sec NUCUDE BONE UVER T. BODY THYROID KIDNEY LUNG GI-LLI EE b5E bc 0.00EdiO~550E + bb 0.00E + 00 0.00E + 00 O d E+~0b 0 5 E bi C-14 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 CR-51 0.00E + 00 0.00E+ 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E+ 00 5U~54 BIO 0E b0 b[00E bb 0.00E+b0 0.00E + 00 b.~00E+ 00 ode +b0 b.~00E+~b0 ~ ~ ~ ~ ~ ~ FE-55 0.00E + 00 0 00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 - 0.00E + 00 I FE-59 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 l CO-58 6IO0E+~00 b.005A00 U.00E+~b0 BIO 0E+~00~~5.~00E + 00 0.00E + 00 0[00E+ 0b~ { ~ ~ ~ ~ ~ CO-60 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 N!-63 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 - i ZN-65 BIO 0E+ 00 650E 00 0005IOb 0 OE+00~~ ~b50E+0b O dEh00 55E+~00~~ ~ ~ .t RB-86 0.00E 4 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E+ 00 SR-89 OLDE+00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 l TR 90 U.~00E Ob 5 5 E b0 UEEI'00 OIO0E b0 6.~00E5bb 0.00Edb0 b.00E + 00 f 5 ~ Y-91 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 _ t ZR 95 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 i 5B 9E BIO 5E bb BIO 0EIDO bdEIE0 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 RU-103 0.00E + 00 0.00E + 00 0.n0E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 l AG-110M 6[00E + 00 0.00E + 00 0.00EIb0 OIO0E+~00 b.00E + 00 55E+~E0~b.00E+TO~ l RU-106 0.00E + 00 - 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00. 0.00E + 00 ~ ~ ~ TE-125M 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 TE-127M 0.00E 4 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 l TE-129M 0.00E+C0 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 l-131 0.00E + 00 0.00E + 00 0.00E + 00 0.00E+ 00 0.00E + 00 0.00E+ 00. 0.00E+ 00 l-133 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E+ 00 0.00E + 00 ~ ~ ~ ~ ~ CS-134 0.00E I~00 6.00EAiO~ BIO 0E ~00 ~b[00AAb0 6.00E + 00 - 0.00E + 00 b.00d+ 00 CS-136 0.00E + 00 0.00E + 00 0.00E + 00 0.00E+ 00 0.00E4 00 0.00E+ 00 0.00E+ 00 CS 137 0.00E 4 00 0.00E+ 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E+ 00 0.00E+ 00 ..... = BA-140 0.00E + 00 0.00E+ 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 CE-141 0.00E + 00 0.00E 4 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 CE-144 0.00E 4 00 0.00E 4 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 . i N-143 OIDOE bb 6[00hA00 b.00EI00 b.00E bb 0.00E b0 b 5 EIbb 0.005I~00~~ ND-147 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E4 00 0.00E + 00 0.00E + 00 75.0 rm. J t

1 Numb $r - MUClear MI Radiological Connois Departmental Procedure 6610-PLN-4200.01 Tme Revision No. Offsite Dose Calculation Manual (ODCM) 3 i TABLE 5.6.2 i Pathway Dose Factors, Ri l AGE GROUP: CHILD PATHWAY: GRASS COW-_ MEAT _...... -..... = - = _ _ _............ -- ---=== = -ORGAN DOSE FACTORS; m' - mrem / year per pCi/sec i NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI 53 b[00E+00 2 34E + 02 E.~34E~02 554E+02 b.34E+02 2.34E + 02 h.34E b~2~ ~ ~ ~ C-14 3.84E + 08 7.S7E + 07 7.67E + 07 7.67E + 07 7.67E+ 07 7.67E + 07 7.67E + 07 i CR-51 0.00E + 00 0.00E + 00 8.78E + 03 4.88E + 03 1.33E + 03 8.90E + 03 4.66E + 05 - - -, = =... MN-54 0.00E + 00 8.01E + 06 2.13E + 06 0.00E + 00 2.25E + 06 0.00E + 00 6.73E + 06 i FE-55 4.57E + 08 2.43E + 08 7.52E + 07 0.00E + 00 0.00E + 00 1.37E + 08 4.49E + 07 FE-59 3.77E + 08 6.10E + 08 3.04E + 08 0.00E + 00 0.00E + 00 1.77E+ 08 6.35E + 08 i 558 b.00N b0 1EEI~07 b.~03E b'7~5.~00EI~00 b.00E + 00 b.00E + 00 9.58E + b[ ~ ~ ~ ~ CO-60 0.00E + 00 6.93E + 07 2.04E + 08 0.00E + 00 0.00E + 00 0.00E+ 00 ' 3.84E+ 08 N1-63 2.91 E + 10 1.56E + 09 9.91E + 08 0.00E + 00 0.00E + 00 0.00E+ 00 1.05E + 08 5N-65 5.76E 08 1.00EIO9 b.22E 08 b50E+00 6.31E 08 0.00EdOO i.76E+08 ~ ~~ RB-86 0.00E + 00 5.76E + 08 3.54E + 08 0.00E + 00 0.00E + 00 0.00E + 00 3.71 E + 07 SR-89 4.82E + 08 0.00E+ 00 1.38E + 07 0.00E + 00 0.00E+ 00 0.00E + 00 1.87E + 07 SR-90 1.04E + 10 0.00E + 00 2.64E + 09 0.0bE 00 b.00U+ 00 6.00E + 00 1.40E b8 Y-91 1.80E + 06 0.00E + 00 4.82E + 04 0.00E + 00 0.00E + 00 0.00E+ 00 2.40E + 08 1 ZR-95 2.66E + 06 5.86E + 05 5.21 E + 05 0.00E + 00 8.38E + 05 0.00E + 00 6.11 E + 08 NB-95 3.105 b6 1.21E+ 06 853E+05 bE0E+00 1.I3Ed06 0.00EI~00~~E.~23E + Oi ~~ ~ ~~ ~ RU-103 1.55E + 08 0.00E + 00 5.96E + 07 0.00E + 00 3.90E + 08 0.00E+ 00 4.01E + 09 RU 106 4.44E + 09 0.00E + 00 5.54E + 08 0.00E + 00 6.00E + 09 0.00E + 00 6.91E + 10 =...._ AG-110M 8.39E + 06 5.67E + 06 4.53E + 06 0.00E + 00 1.06E + 07 0.00E+ 00 6.74E + 08 TE-125M 5.69E + 08 1.54E + 08 7.59E + 07 1.60E + 08 0.00E + 00 0.00E + 00 5.49E 4 08 TE-127M 1.78E + 09 4.78E+ 08 2.11E + 08 4.25E + 08 5.06E + 09 0.00E + 00 1.44E + 09 ~ h~ih9M 1.79E h 09 5.00E + 08 2.78E + 08 5.77E + 08 5.26E+09 0.00E + 00 2.18E+ 09 T l-131 1.66E + 07 1.67E + 07 9.48E + 06 5.52E + 09 2.74E + 07 0.00E + 00 1.48E + 06 ^ l-133 5.720-01 7.08e-01 2.68e.01 1.31 E + 02 1.18E + 00 0.00E + 00 2.85e-01 CS-134 9%.I+ 08 1.51E + 09 3.19E + 08 0.00E + 00 4.69E 4 08 1.68E 4 08 8.16E + 06 CS-136 1.63E + 07 4.48E + 07 2.90E + 07 0.00E + 00 2.39E + 07 3.56E + 06 1.57E + 06 CS-137 1.33E + 09 1.28E + 09 1.89E + 08 0.00E + 00 4.16E + 08 1.50E + 08 8.00E + 06 BA-140 4A2E+07 3.87E + 04 2.58E + 06 0.00E + 00 1.26E + 04 2.31E + 04 2.24E + 07 CE-141 2.22E + 04 1.11 E + 04 1.65E + 03 0.00E + 00 4.86E + 03 0.00E + 00 1.38E + 07 CE _144_ 2.32E + 06 7.2SE + 05 1.24E + 05 0.00E+ 00 4 02E+ 05 0.00E + 00 1.89E + 08 ] PR-143 3.33E + 04 1.00E 4 04 1.65E + 03 0.00E + 00 5.42E + 03 0.00E + 00 3.60E + 07 ND-147 1.17E + 04 9.48E + 03 7.34E + O2 0.00E + 00 5.20E 4 03 0.00E + 00 1.50E + 07 1 76.0 n m,

Number { -gggg TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 Title Revision No. Offsite Dose Calculation Manual (ODCM). 3 l TABLE 5.6.3 Pathway Dose Factors, Ri j AGE GROUP: TEEN PATHWAY: GRASS-COW-MEAT 2 ORGAN DOSE FACTORS; m - mrem / year per pCl/sec NUCLlDE - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - = = =---- i BONE UVER T. BODY THYROID KIDNEY LUNG GI-LLI H-3 0.005 i,0~~i.53E + 02~i.535Ibb~I.~95EIbE2~i.~95E+b2~I.535Ib2 1.535563~ ~~ ~ ~ C-14 2.04E + 08 4.08E + 07 4.08E + 07 4.08E + 07 4.08E + 07 4.08E + 07 4.08E + 07 CR-51 0.00E + 00 0.00E + 00 5.63E + 03 3.13E + 03 1.23E + 03 8.03E + 03 9.46E + 05 i MN-54 0.00E + 00 7.00E + 06 1.39E + 06 0.00E + 00 2.09E5b6 - b.00E+00~~~i.~44E+~07~~' l ~ FE-55 2.38E + 08 1.69E + 08 3.94E + 07 0.00E + 00 0.00E + 00 1.07E+ 08 7.31 E + 07 l i FE-59 2.12E + 08 4.95E + 08 1.91 E + 08 0.00E + 00 0.00E + 00 1.56E + 08 - 1.17E+ 09 CO-58 U~00E+~00~~I.~40EI~07 3.24EIO7 6.00E + 00~~~~b.~00E + 0b~b.~00E+~~00 1.94E + 08 ~ ~ ~ ~ CO-60 0.00E + 00 5.83E + 07 1.31E + 08 0.00E + 00 0.00E + 00 0.00E + 00 7.60E + 08 Ni-63 1.52E + 10 1.07E + 09 5.15E + 08 0.00E + 00 0.00E + 00 0.00E + 00 ' 1.71 E + 08 - _ =. - _. - - -..... - - ZN-65 2.50E 4 08 8.68E + 08 4.05E + 08 0.00E + 00 5.56E+ 08 0.00E + 00 3.68E + 08 RB-86 0.00E + 00 4.06E + 08 1.91E + 08 0.00E + 00 0.00E + 00 0.00E + 00 6.00E + 07 i SR-89 2.55E + 08 0.00E + 00 7.29E + 06 0.00E + 00 0.00E + 00 0.00E + 00 3.03E + 07 _ = =.... _ - - _ __--- SR-90 8.04E + 09 0.00E 4 00 1.99E + 09. 0.00E + 00 0.00E + 00 0.00E + 00 2.26E + 08 Y-91 9.54E + 05 0.00E + 00 2.56E + 04 0.00E + 00 0.00E + 00 0.00E + 00 3.91E + 08 ZR-95 1.50E + 06 4.73E + 05 3.25E + 05 0.00E + 00 6.95E + 05 0.00E + 00 1.09E + 09 i . _ = - -...... -...... - - - - - -.... - - - = - = _ - - = -. NB-95 1.79E 4 06 9.95E + 05 5.48E + 05 0.00E + 00 9.64E + 05 0.00E + 00 4.25E + 09 RU-103 8.56E + 07 0.00E + 00 3.66E + 07 0.00E + 00 3.02E + 08 0.00E +00 7.15E + 09 j RU-106 2.36E + 09 0.00E + 00 2.97E + 08 0.00E + 00 4.54E + 09 0.00E + 00 1.13E + 11 ~ ~~ ~~ ~ ~~ ~ ~~~ AG-110M 106E+~06 178E+b6 2.915+ 06 b.00E + 00 9.13E+ 06 b 00E+ 00~~5.34E+09 TE-125M 3.03E + 08 1.09E + 08 4.05E + 07 8.46E + 07 0.00E + 00 0.00E + 00 8.94E+ 08 ....-127M 9.41 E + 08 3.34E 4 08 1.12E + 08 2.24E + 08 3.81 E + 09 0.00E + 00 2.35E+ 09 TE = TE-129M 9.49E + 08 3.52E 4 08 1.50E + 08 3.06E + 08 3.97E + 09 0.00E + 00 3.56E + 09 1 1-131 8.93E+06 1.25E + 07 6.72E + 06 3.65E + 09 2.15E + 07 0.00E + 00 2.47E + 06 l133 3.08e-01 5.22e-01 1.59e-01 7.29E + 01 9.16e-01 0.00E+ 00 3.95e-01 S[34 5.23E + 08 1.23E + 09 5.71E 4 08 0.00E + 00 351E+ 08 1.49E + 08 153E+ 07 I CS-136 9.43E+ 0S 3.71 E + 07 2.49E+ 07 0.00E + 00 2.02E+ 07 3.18E + 06 ' 2.99E + 06 7.24E + 08 9.63E + 08 3.35E + 08 0.00E + 00 3.28E + 08 1.27E+ 08 1.37E + 07 CS. _-137- =-.......--__-.__ _-...=- 1 BA-140 2.39E + 07 2.93E + 04 1.54E + 06 0.00E + 00 9.94E + 03 1.97E + 04 3.69E + 07 CE-141 1.18E + 04 7.87E + 03 9.05E + 02 0.00E + 00 3.71E+ 03 0.00E+ 00 2.25E + 07 CE-144 1.23E + 06 5.08E + 05 6.60E + 04 0.00E + 00 3.03E + 05 0.00E + 00 3.09E + 08 -=...---- = PR-143 1.76E + 04 7.03E + 03 8.76E + 02 0.00E + 00 4.08E + 03 0.00E+ 00 5.79E+ 07 ND 147 6.23E 4 03 6.78E + 03 4.06E + 02 0.00E + 00 3.98E + 03 0.00E + 00 2.44E + 07 i .-- =_-....------. 77.0 rm. 1

Numbsr bdeM Tuin dii 91 i Controis Copartmental Procedure 6610-PLN-4200.01 ) . Titie Rewsion No. 4 Offsite Dose Calculation Manual (ODCM) 3 f TABLE 5.6.4 Pathway Dose Factors, Ri j AGE GROUP: ADULT PATHWAY: GRASS-COW-MEAT -..._........._..=- _.. _ _ - _ _ - 2 ORGAN DOSE FACTORS; m - mrem / year per pCl/sec NUCLIDE - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - = - BONE UVER T. BODY THYROID KIDNEY LUNG GI-LLI ....... _ _ _ _..... _.. _.. _........ = H-3 0.00E + 00 3.24E + 02 3.24E + 02 3.24E + 02 3.24E + 02 3.24E 4 02 3.24E + 02 C-14 2.42E + 08 4.83E + 07 4.83E + 07 4.83E + 07 4.83E + 07 4.83E + 07 4.83E + 07 - CR 51 0.00E + 00 0.00E + 00 7.04E + 03 4.21 E + 03 1.55E + 03 9.35E + 03 1.77E + 06 .-=.. __........_......._. _...._......... MN-54 0.00E + 00 9.18E + 06 1.75E + 06 0.00E + 00 2.73E + 06 0.00E + 00 2.81 E + 07. FE-55 2.93E + 08 2.03E+ 08 4.73E + 07 0.00E + 00 0.00E + 00 1.13E + 08 1.16E + 08 i FE-59 2.66E + 08 6.25E + 08 2.39E + 08 0.00E + 00 0.00E + 00 1.75E + 08 2.08E + 09 CO-58 0.00E + 00 1.82E + 07 4.096 + 07 0.00E+ 00 0.00E + 00 0.00E+ 00 3.70E + 08 t CO-60 0.00E +00 7.52E + 07 1.665 + 08 0.00E + 00 0.00E + 00 0.00E + 00 1.41 E + 09 ...-63 1.89E + 10 1.31 E + 09 6.33E M8 0.00E + 00 0.00E + 00 0.00E + 00 2.73E + 08 - l Ni ZN-65 3.56E + 08 1.13E + 09 5.12E + 08 0.00E + 00 7.57E + 08 0.00E + 00 7.13E + 08 } RB-86 0.00E + 00 4.87E + 08 2.27E + 08 0.00E + 00 0 00E + 00 0.00E + 00 9.59E + 07 l SR-89 3.02E + 08 0.00E + 00 8.66E + 06 0.00E + 00 0.00E + 00 0.00E + 00 4.84E + 07 ......_........... = __ = l SR-90 1.24E + 10 0.00E + 00 3.05E + 09 0.00E + 00 0.00E + 00 0.00E + 00 3.60E+ 08 - Y-91 1.13E + 06 0.00E + 00 3.03E + 04 0.00E+ 00 0.00E + 00 0.00E + 00 6.24E + 08 i ZR-95 187E+ 06 6.01 E + 05 4.07E + 05 0.00E + 00 9.43E 4 05 0.00E + 00 1.90E+ 09 NB-95 2.30E + 06 1.28E 4 06 6.87E + 05 0.00E + 00 1.26E + 06 0.00E + 00 7.76E + 09 } RU-103 1.05E + 08 0.00E + 00 4.53E + 07 0.00E + 00 4.02E + 08 0.00E + 00 1.23E + 10 RU-106 2.80E + 09 0.00E + 00 3.54E + 08 0.00E + 00 5.41E + 09 0.00E + 00 1.81E + 11 AG-110M 6.68E + 06 6.18E + 06 3.67E + 06 0.00E + 00 1.22E 4 07 0.00E + 00 2.52E+ 09 TE-125M 3.59E + 08 1.30E + 08 4.81E + 07 1.08E + 08 1.46E + 09 0.00E + 00 1.43E + 09 TE-127M 1.12E + 09 3.99E + 08 1.36E + 08 2.85E + 08 4.53E + 09 0.00E + 00 3.74E + 09 -.__..___........... = TE-129M 1.13E + 09 4.23E + 08 1.79E + 08 3.89E + 08 4.73E+ 09 0.00E+ 00 5.71E + 09 1-131 1.08E + 07 1.54E + 07 8.82E + 06 5.04 E + 09 2.64E + 07 0.00E + 00 4.06E + 06 _-=_.._= _- _ = _. 5.76e.01 i l-133 3.68e 01 6.41 e-01 1.95e41 9.42E + 01 1.12E + 00 0.00E+ 00 =...... CS-134 6.58E + 08 1.57E + 09 1.28E + 09 0.00E 4 00 5.07E + 08 1.68E + 08 2.74E + 07 CS-136 1.21 E + 07 4.78E + 07 3.44E+ 07 0.00E + 00 2.66E + 07 3.65E + 06 5.43E + 06 CS-137 8.72E + 08 1.19E + 09 7.82E+ 08 0.00E + 00 4.05E + 08 1.35E + 08 2.31E+ 07 j .....____.........._____.. _.......__._..._.= BA-140 2.90E + 07 3.64E + 04 1.90E + 06 0.00E + 00 1.24E + 04 - 2.08E 4 04 5.90E + 07 i CE-141 1.41 E + 04 9.51 E + 03 1.08E + 03 0.00E + 00 4.42E + 03 0.00E + 00 3.64E + 07 i CE-144 1.46E + 06 6.10E + 05 7.83E + 04 0.00E + 00 3.62E + 05 0.00E + 00 4.93E + 08 ..._-_ - =-- =- PR-143 2.09E + 04 8.40E + 03 1.04E + 03 0.00E + 00 4.85E + 03 0.00E + 00 9.17E + 07 l ND-147 7.08E + 03 8.18E + 03 4.90E + O2 0.00E + 00 4.78E + 03 0.00E + 00 3.93E + 07 = ........ _..._-=-_ i I i I l 78.0 2m

i i Wumbor M Nuclear- ' "ad'***' coa"* i Departmental Procedure 6610-PLN-4200.01 1 Title Revision No. Offsite Dose Calculation Manual (ODCM) 3 j l TABLE 5.7.1 Pathway Dose Factors, Ri AGE GROUP: INFANT PATHWAY: VEGETATION 2 F ORGAN DOSE FACTORS; rn - mrem / year per pCl/sec NUCUDE - - - - - - - - - - - - - - - - - - - - - - - - - - = = - BONE UVER T. BODY THYROlD - KIDNEY LUNG Gl-LU s 3 = - -. _ H-3 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 C-14 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 CR-51 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00. 0.00E + 00 0.00E + 00 FIN-54 b5dI00 b.00E+0b OIO0E+~00 b.~005+~ 00 bI00E 00 0.00E[00 0.00E + 0b' ~ ~ ~ FE-55 0.00E + 00 0.00E + 00 0.00E + CO 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 FE 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 - _ _ _-59___ -= CO-58 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 CO-60 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 NI-63 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E+ 00 0.00E + 00 0.00E + 00 i 5f[ES bI0050b 6.00E+00 0.00E + 00 0.00E +0b 0.00E+b~0 b5d b'O b.~005+ 00 RB-86 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 SR-89 0.00E + 00 0.00E + 00 0.n0E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 SR 90 b.0bE + 00 b5E b0 0$00E+~03 BIO 0E b'O bI0OE+ 0O bI00E+~b'0~b5d+~00~' ~ ~ ' ~ ~ ~ ' Y-91 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E+ 00 ZR-95 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E+ 00 0 00E+ 00 NB-95 b'00EIb'O bE05$00 U.00EIb~0 UE0E b0 6.00E + 00 0.00E + 00 0.00E+ 00 { ~ ~' RU-103 0.00E+ 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E+ 00 0.00E + 00 RU-106 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 AG-110M 555$b'O bI0bE+00~b.00E+b'O bI00E+ 00 Uh0E+00 0 OE+00 ~ BIO 0E+~00 l ~ ~ TE-125M 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E+ 00 0.00E + 00 0.00E + 00 TE-127M 0.00E 4 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 i ~ ~ ~~' TE-129M 0.00E + 00 bI00E[00 b55 00 b5EIO0 0.00E + 00 6.00E+00 0.00E + 00 -i 1-131 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 1-133 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 CS-134 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E < 00 0.00d+ 00 ~b5EIOO CS-136 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 CS-137 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 B -[4b b50E+00 bT05EIO0 0.00E[00 bI00E+00 bI00E 00 0.00E + 00 b505+00 ~ ~ ~ CE-141 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E4 00 0.00E + 00 0.00E+ 00 CE-144 0.00E + 00 0.00E + 00 0.00E + 00 0.00E+ 00 0.00E + 00 0.00E + 00 0.00E + 00 7PII43 UE0EIbb b.~00E+00 0.00E 00 0.00E + 00 0.00E100 0.00E + 00 0.00E + 00 ND-147 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 19.0 mm. l - E

l I Number gdgy TMl Radiological Controls Departmental Procedure 6610-PLN-4200.01 l Tatie Revision No. Offsite Dose Calculation Manual (ODCM) 3 i i TABLE 5.7.2 Pathway Dose Factors, Ri AGE GROUP: CHILD PATHWAY: VEGETATION - 1 =-- -=.._- -- ORGAN DOSE FACTORS; m'- mrom/ year per pCl/sec r NUCLIDE _ _ _..-LLI GI BONE LIVER T. BODY THYROID KIDNEY LUNG .. _ _ _ _........ -... _..... _...... _ _ _.. _ _.... _. _ _ _... =. H-3 0.00E + 00 4.02E + 03 4.02E + 03 4.02E + 03 4.02E + 03 4.02E + 03 4.02E + 03 -i C-14 8.89E + 08 1.78E + 08 178E + 08 1.78E + 08 1.78E + 08 1.78E + 08 1.78E + 08 CR 51 0.00E + 00 0.00E + 00 1.17E + 05 6.49E + 04 1.77E + 04 1.18E + 05 6.20E + 06 + - _.... _ _...... _. _ = = - - - - - MN-54 0.00E + 00 6.65E+ 08 1.77E + 08 0.00E + 00 1.86E + 08 0.00E + 00 5.58E+08 FE-55 8.01 E + 08 4.25E 4 08 1.32E 4 08 0.00E + 00 0.00E + 00 2.40E + 08 7.87E + 07 l -_ _ _-5 9 3.98E + 08 6.44E + 08 3.21 E + 08 0.00E + 00 0.00E + 00 1.87E + 08 6.71E + 08 1 FE ...-_._______ ___....__==-

=.._ ____... ___.._---

CO-58 0.00E + 00 6.44E + 07 1.97E + 08 0.00E + 00 0.00E + 00 0.00E + 00 3.76E + 08 CO-60 0.00E + 00 3.78E + 08 1.12E + 09 0.00E + 00 0.00E + 00 0.00E + 00 2.10E + 09 i NI-63 3.95E + 10 2.11 E + 09 1.34E + 09 0.00E + 00 0.00E + 00 0.00E+ 00 1.42E + 08 - =-- -_.._... --...___.-. =.. _.... -....... ZN-65 8.12E + 08 2<16E + 09 1.35E + 09 0.00E+ 00 1.36E + 09 0.00E + 00 3.80E + 08 RB-86 0.00E + 00 4.51 E + 08 2.77E + 08 0.00E + 00 0.00E + 00 0.00E + 00 2.90E + 07 -l SR-89 3.60E + 10 0.00E 4 00 1.03E + 09 0.00E 4 00 0.00E 4 00 0.03E + 00 1.39E + 09 i SR-90 1.24E + 12 0.00E + 00 3.15E + 11 0.00E + 00 0.00E + 00 0.00E + 00 1.67E+ 10 Y-91 1.87E + 07 0.00E + 00 4.99E + 05 0.00E + 00 0.00E + 00 0.00E+00 2.49E+ 09 3.86E + 06 8.48E + 05 7.55E+ 05 0.00E + 00 1.21 E + 06 0.00E + 00 8.85E + 08 ZR._-95...- =

==-. - =.. _. -..... _..... _ _ - - - - - -.. _ _... NB-95 4.11 E + 05 1.60E + 05 1.14E + 05 0.00E + 00 1.50E + 05 0.00E + 00 2.96E + 08 RU-103 1.53E + 07 0.00E + 00 5.90E + 06 0.00E + 00 3.86E 4 07 0.00E + 00 3.97E + 08 .._ -106 7.45E + 08 0.00E + 00 9.30E + 07 0.00E + 00 1.01 E + 09 0.00E + 00. = =.- 1.16E + 10 RU .= AG-110M 3.21E + 07 2.17E + 07 1.73E + 07 0.00E + 00 4.04E + 07 0.00E + 00 2.58E + 09 TE-125M 3.51 E + 08 9.50E + 07 4.67E + 07 9.84E + 07 0.00E + 00 0.00E + 00 3.38E + 08 TE-127M 1.32E + 09 3.56E + 08 1.57E + 08 3.16E + 08 3.77E + 09 0.00E4 00 1.07E4 09 .......... _. _. _.... - _ _.... _.. _. - = = . - =.. ._..==- TE-129M 8.40E + 08 2.35E + 08 1.30E + 08 2.71 E + 08 2.47E + 09 0.00E + 00 1.02E + 09 l-131 1.43E 4 08 1.44E 4 08 8.18E + 07 4.76E + 10 2.36E + 08 0.00E+ 00 1.28E + 07 l-133 3.53E + 06 4.37E + 06 1.65E + 06 8.12E + 08 7.2SE + 06 0.00E + 00 1.76E + 06 i - - = =. _. _ _..... _. _. -.. _..... _ -.. _...... -. _ _ _ _ - -.. _ _.... _.......... CS-134 1.60E + 10 2.63E + 10 5.55E + 09 0.00E + 00 8.15E + 09 2.93E + 09 1.42E + 08 CS-136 8.28E + 07 2.28E + 08 1.47E + 08 0.00E + 00 1.21 E + 08 1.81E + 07 8.00E + 06 CS-137 2.39E + 10 2.29E + 10 3.38E + 09 0.00E + 00 7.46E + 09 2.68E + 09 1.43E + 08 ~ ~~ bA-140 2.79E + 08 2.44E + 05 1.63E + b7 0.'O0E+~00~~h.96E 4 04 I.46E + b5 1.41 E + 08 CE-141 6.57E 4 05 3.28E 4 05 4.86E + 04 0.00E + 00 1.44E + 05 0.00E+ 00 4.09E + 08 CE-144 1.27E 4 08 3.99E + 07 6.79E4 06 0.00E + 00 2.21 E 4 07 0.00E 4 00 1.04 E + 10 TR I43 5.~45E+~ ~05 4 36E+ 04 f.~215403 0.0dE + 00 2.365+"04 OE05+'((0~I.57E+08 l ~ ~ ~ ~ ~~ ~ ~ ~ ~~~ ~~ ND-147 7.15E 4 04 5.79E + 04 4.49E + 03 0.00E + 00 3.18E + 04 0.00E+ 00 9.18E + 07 . = - - - - -...... _ _........... - - M 80.0 rme

1 4 Number bdeM TMI Radiological Controls. j Departmental Procedure 6610-PLN-4200.01 . Tatie Revision No. ) l Offsite Dose Calculation Manual (ODCM) 3 i i TABLE 5.7.3 Pathway Dose Factors, RI l 3 AGE GROUP: TEEN PATHWAY: VEGETATION i _==- 2 ORGAN DOSE FACTORS; m - mrem / year per pCl/sec NUCLIDE ? _ _.-LLI - BONE LIVER T. BODY THYROID KIDNEY LUNG GI H-3 0.00E 4 00 2.59E + 03 2.59E + 03 2.59E + 03 2.59E + 03 2.59E + 03 2.59E + 03 C-14 3.69E + 08 7.38E + 07 7.38E + 07 7.38E + 07 7.38E + 07 7.38E + 07 7.38E + 07 l CR-51 0.00E + 00 0.00E + 00 6.16E + 04 ' 3.42E + 04 1.35E + 04 8.79E + 04 1.03E+ 07 MN-54 0.00E + 00 4.54E + 08 9.01E + 07 0.00E + 00 1.36E + 08 0.00E + 00 9.32E + 08 FE.55 3.26E + 08 2.31E + 08 5.39E + 0 / 0.00E + 00 0.00E + 00 1.47E + 00 1.00E + 08 ....-59 1.80E 4 08 4.19E + 08 1.62E+ 08 0.00E + 00 0.00E+ 00 1.32E + 08 9.91E + 08 i FE CO-58 0.00E + 00 4.36E + 07 1.01 E + 08 0.00E 4 00 0.00E + 00 0.00E + 00 6.01E + 08 i CO-60 0.00E + 00 2.49E + 08 5.60E + 08 0.00E + 00 0.00E + 00 0.00E + 00 3.24E + 09 l NI-63 1.61E + 10 1.13E + 09 5.45E + 08 0.00E + 00 0.00E + 00 0.00E + 00 1.81 E + 08 j, -_....= ZN-65 4.24E + 08 1.47E + 09 6.86E + 08 0.00E + 00 9.42E + 08 0.00E + 00 6.23E + 08 RB-86 0.00E + 00 2.73E + 08 1.28E + 08 0.00E + 00 0.00E + 00 0.00E + 00 4.04E + 07 SR-89 1.52E + 10 0.00E + 00 4.34E + 08 0.00E + 00 0.00E + 00 0.00E + 00 1.80E + 09 SR-90 7IS1E 1 UIO0EIO0 IIB 55k1 b[00E+~00 bI00EIO0 U.~00E+ 00 2.11E + 10 ~ ~ ~ ~ ~ ~ ~ ~ Y-91 7.84E + 06 0.00E + 00 2.10E + 05 0.00E + 00 0.00E + 00 0.00E + 00 3.226 + 09 i ..._-95 1.72E + 06 5.43E + 05 3.73E + 05 0.00E + 00 7.98E + 05 0.00E + 00 1.25E + 09 ? ZR . = - - -........... NB-95 1.92E + 05 1.07E + 05 5 87E + 04 0.00E + 00 1.03E + 05 0.00E + 00. 4.56E + 08 RU-103 6.82E + 06 0.00E + 00 2.92E + 06 0.006 + 00 2.41E + 07 0.00E +00 - 5.70E+08 RU-106 3.09E + 08 0.00E + 00 3.90E + 07 0.00E + 00 5.97E+08 0.00E + 00 1.48E + 10 j 1.43 + 07 852EIO6 b[00E+ 00 2.74E + 07 0.00E + 00 4.03E + 09 i Ah-[10M 1.52k+ 07 I TE-125M 1.48E + 08 5.34E + 07 1.98E + 07 4.14E + 07 0.00E + 00 0.00E + 00 4.37E + 08 ....-127M 5.52E + 08 1.96E + 08 6.56E + 07 1.31 E + 08 2.24E + 09 0.00E + 00 1.37E + 09 l TE TE-129M 3.61E + 08 1.34E + 08 5.72E + 07 1.17E + 08 1.51E + 09 0.00E + 00 1.36E + 09 ' 1-131 7.69E 4 07 1.08E + 08 5.78E + 07 3.14E + 10 1.85E + 08 0.00E + 00 2.13E + 07 l133 1.94E 4 06 3.29E + 06 1.00E + 06 4.59E + 08 5.77E + 06 0.00E + 00 2.49E + 06 i 4 . _...... _ _........ _.... _. _ _ _. _. _. = __ = CS-134 7.10E + 09 1.67E + 10 7.75E + 09 0.00E + 00 5.31E + 09 2.03E + 09 2.08E + 08 i CS-136 4 39E4 07 1.73E + 08 1.16E 4 08 0.00E + 00 9.41E + 07 1.48E + 07 1.39E + 07 i CS 137 1.01E + 10 1.35E + 10 4.69E + 09 0.00E + 00 4.59E + 09 1.78E + 09 1.92E+ 08 -..._ =_ 8A-140 1.39E + 08 1.71E + 05 8.97E + 06 0.00E + 00 5.78E 4 04 1.15E + 05 2.15E + 08 CE-141 2 83E + 05 1.89E + 05 2.17E+ 04 0.00E + 00 8.90E + 04 0.00E + 00 5.41 E + 08 CE-144 5.28E + 07 2.18E + 07 2.83E + 06 0.00E + 00 1.30E + 07 0.00E + 00 1.33E + 10 TRI43 b595I04 2.79E + 04 3I485IO3 b 00E + 00 IIG2EIO4 bI00EIO0 2E0E+b8~ ~ ~~ ~ ~~ ~ ~ ND-147 3.62E + 04 3.94 E + 04 2.36E + 03 0.00E + 00 2.31 E + 04 0.00E + 00 1.42E + 08 2 1 I l { 81.0 ame

~. i Numtor gggy TMI Radiological Controls i Departmental Procedure 6610-PLN-4200.01 j htte. Revision No. Offsite Dose Calculation Manual (ODCM) 3 i TABLE 5.7.4 t Pathway Dose Factors, Ri ? AGE GROUP: ADULT PATHWAY: VEGETATION NUCLIDE

------------. THYRO I D

.-=................--.-LLI.__ i LUNG GI BONE LIVER T. BODY KIDNEY ....._.....--......................= H-3 0.00E + 00 2.26E + 03 2.26E + 03 2.26E + 03 2.26E + 03. 2.26E + 03 2.26E + 03 C-14 2.28E + 08 4.55E + 07 4.55E + 07 4.55E+ 07 4.55E + 07 4.55E + 07 4.55E + 07 CR 51 0.00E + 00 0.00E + 00 4.64E + 04 2.77E + 04 1.02E 4 04 6.15E + 04 1.17E + 07 2 MN-54 0.00E + 00 3.13E + 08 5.97E + 07 0.00E + 00 9.31E + 07 0.00E + 00 9.58E + 08 ) FE-55 2.10E + 08 1.45E + 08 3.38E + 07 0.0CE + 00 0.00E + 00 8.08E + 07 8.31E + 07 FE 1.26E + 08 2.97E + 08 1.14E + 08 0.00E + 00 0.00E + 00 8.29E + 07 9.89E+ 08 ... -59.... CO-58 0.00E + 00 3 07E + 07 6.89E + 07 0.00E+ 00 0.00E + 00 0.00E + 00 6.23E + 08 CO-60 0.00E + 00 1.67E + 08 3.69E + 08 0.00E + 00 0.00E + 00 0.00E + 00 3.14E+ 09 N1-63 1.04 E + 10 7.21 E + 08 3.49E + 08 0.00E + 00 0.00E + 00 0.00E + 00 - : 1.50E + 08 i ~ 3.17E+~08 IO1E+09 4.56E + 08 d.00E[00 615E+08 0.00E + 00 - 6.36E + 08 1 ~~ ~ ~ ~ ZN-6 RB-86 0.00E + 00 2.19E + 08 1.02E + 08 0.00E + 00 0.00E + 00 0.00E + 00 4.32E + 07 l! SR-69 9.98E + 09 0.00E + 00 2.86E + 08 0.00E + 00 0.00E + 00 0.00E + 00 1.60E + 09 -- =... SR-90 6.05E + 11 0.00E 4 00 1.48E + 11 0.00E+ 00 0.00E + 00 0.00E 4 00 - 1.75E+ 10 Y 91 5.12E+06 0.00E + 00 1.37E + 05 0.00E + 00 0.00E + 00. 0.00E + 00 2.82E+ 09 l ZR-95 1.17E + 06 3.77E + 05 2.55E + 05 0.00E + 00 5.91 E + 05 0.00E + 00 1.19E + 09 ..- - _... _ -... = - - - - - - -

== NB-95 1.42E + 05 7.02E + 04 4.26E + 04. 0.00E + 00 7.83E + 04 0.00E + 00 4.81E + 08 RU-103 4.77E + 06 0.00E + 00 2.06E + 06 0.00E + 00 1.82E + 07 0.00E + 00 5.57E4 08 l RU-106 1.93E + 08 0.00E + 00 2.44E + 07 0.00E+ 00 3.72E + 08 0.00E+ 00 1.25E+ 10 i AG-110M 1.05E + 07 9.75E+ 06 5.79E + 06 0.00E+ 00 1.92E + 07 0.00E + 00 3.98E + 09 TE-125M 9.66E + 07 3.50E + 07 1.29E + 07 2.90E + 07 3.93E + 08 0.00E + 00 3.86E+ 08 TE-127M 3.49E + 08 1.25E + 08 4.26E + 07 8,93E + 07 1.42E + 09 0.00E + 00 1.17E + 09 - = =... - - = = - -...... - = TE-129M 2.51E + 08 9.37E + 07 3.97E + 07 8.63E + 07 1.05E + 09 0.00E + 00 1.26E+ 09 I l-131 8.08E + 07 1.16E + 08 6.62E + 07 3.79E + 10 1.98E + 08 0.00E + 00 3.05E+ 07 ) 1-133 2.09E + 06 3.63E + 06 1.11E + 06 5.34E + 08 6.33E + 06 0.00E + 00 3.26E + 06 - _ __ =............-...... CS-134 4.67E + 09 1.11 E + 10 9.08E + 09 0.00E+ 00 3.59E + 09 1.19E+ 09 1.94E + 08 CS-136 4.28E 4 07 1.69E + 08 1.22E + 08 0.00E + 00 9.41E + 07 1.29E + 07 1.92E+ 07 CS-1

7 6.36E 4 09 8.70E + 09 5.70E + 09 0.00E + 00 2.95E+09 9.81 E + 08 1.68E + 08 l

. _ - _ _ _....... - _........ _....... = - BA-140 1.29E + 08 1.62E + 05 8.47E + 06 0.00E + 00 5.52E 4 04 9.29E4 04 2.66E+ 08 CE-141 1.97E + 05 1.33E + 05 1.51 E + 04 0.00E + 00 6.20E + 04 0.00E + 00 5.10E+08 CE-144 3.29E + 07 1.38E + 07 1.77E + 06 0.00E + 00 8.16E + 06 0.00E + 00 1.11 E + 10 PR-143 6.25E + 04 2.51 E + 04 3.10E + 03 b.~00E+~ 00 1.45E + 04 0.00E+00 574E+~08~~ ~ ~ ~ ~ ~ ~ ~ ND-147 3.34E + 04 3.85E + 04 2.31 E + 03 0.00E + 00 2.25'E + 04 0.00E + 00 1.85E+ 08 _ _ _ _. - - - = - - - = 82.0 rm

l Number Nuclear- " "ad'S o'ca' c "t'd' i Departmental Procedure 6610-PLN-4200.01 - Ts11e Revision No. l Offsite Dose Calculation Manual (ODCM) 3 l l 6.0. TMI-1 GASEOUS WASTE TREATMENT SYSTEM l r 6.1 Description of the TMI-1 Gaseous Radwaste Treatment System (see Floure 6.1) { 6.1.1 Waste Gas System a. Reactor Building: - Reactor Coolant Drain Tank (RCDT) header j b. Auxillary Building: - Vent Header from 1 Miscellaneous Waste Storage Tank (MWST) 2. Three (3) Reactor Coolant Bleed Teoks (RCBT) - Waste Gas Delay Tank - Two (2) Waste Gas Compressors ? - Three (3) Wasto Gas Decay Tanks (WGDT) 8 c. Filtration and dilution provided by the Statior. Ventilation System. l 6.2 Operability { Operability of the Gaseous Waste Treatment System is defined as the ability to remove gas from the j vent header / tank gas spaces and store it under a higher pressure in the Waste Gas Decay Tanks for i subsequent release. 1' Except for initiating the make up tank sample and waste gas venting and the recycle or disposal of compressed waste gases stored in the waste gas decay tanks, the operation of the waste gas systern is entirely automatic. One waste gas compressor comes on automatically, removing gases from the vent header system as required, to maintain the pressure in the system at a maximum of i about 16.4 psia. l ? I p 1 5 I t 83.0 rm. r w

Number Nuclear ' "ad'd*^' coatro's Departmental Procedure 6610-PLN-4200.01 Title Revision No. Offsite Dose Calculation Manual (ODCM)- 3 FIGURE 6.1 ~ Waste Gas System i russeense uurw eeneses maass a s. esasus l 68 l 88 w w mases m ,-l. l 1r ir d i f k y 'F M D&am i '~ t u mue mue u mue a,ans e l eass a sans: ,,9,,, 1 ts - -.s .y,;,,=,,, * , e......e. $128 witti f uIteS 1 ' ts e a yA=== N e - ei ?" A od. C ""~ '" u o.i,t_i4 as t.i,s_ag t,asteine. mast w 48,5 6&8 t e E e a ..j0 g...,,p p.,,p +

,J i

i i t ) M.0

2373, l

Number -(UClear TMI Radiological Controls Departmental proenture 6610-PLN-4200.01 Title Revision No. f Offsite Dose Calculation Manual (ODCM) 3 l { 7.0 EFFLUENTTOTAL DOSE ASSESSMENT 7.1 Total Dose Calculation The annual (calendar year) dose or dose committment to any member of the public, due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrem to the total body or any organ except the thyroid, which sha!! be limited to less than or equal to 75 mrem. This control is provided in order to meet the dose limitations of 40 CFR 190. j The total dose from TMI-1 and TMI-2 (uranium fuel cycle facilities within 8 kilometers) is calculated i by summing the calculated annual doses to critical organs of a real individual for liquid effluent using Section 2.1 methodology, for gaseous effluent using Section 5.2.1 and 5.2.2 methodology, and the l direct radiation from the site from the environmental monitoring program's direct radiation (TLD) l monitors. e l t l t 4 l 2 85.0 t' "' j

Numtsr j g'dgy TMl Radiological Controls j Departmental Procedure 6610-PLN-4200.01 Title Revision No. Offsite Dose Calculation Manual (ODCM) 7 8.0 TMINS RADIO 1.OGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) 8.1 Monitorina Proaram Requirements 8.1.1 Controls in accordance with the TMI-1 Tech. Specs. and TMI-2 PDMS Tech. Specs., the radiological environmental monitoring program shall be conducted as specified in Table 8.1. 8.1.2 Applicability At a!! times. 8.1.3 Action a. With the radiological environmental monitoring program not being conducted as specified in l Table 8.1, prepare and submit to the Commission in the Annual Radiological Environmental l Operating Report, a description of the reasons for not conducting the program as required I and the plans for preventing a recurrence, b. With the level of radicactivity as the result of plant effluents in an environmental sampling i medium exceeding the reporting levels of Table 8.2 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days from the end of the affected - calendar quarter, a special report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose

to a member of the public is less than the calendar year limits of TMI-1 Tech.

Spec. Sections 3.22.1.2, 3.22.2.2, 3.22.2.3 and ODCM Part II, Sections 2.1.1.3F,2.1.2.3D, and 2.1.2.3E. When more than one of the radionuclides in Table 8.2 are detected as the result of plant effluents in the sampling medium, this report shall be submitted if: concentration (1) + concentration (2) +... a: 1.0 reporting level (1) reporting level (2) When radionuclides other than those in Table 8.2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose

to a member of the public is equal to or greater than the calendar year limits of TMI-1 Tech. Spec.

Sections 3.22.1.2, 3.22.2.2, 3.22.2.3 and ODCM Part II, Sections 2.1.1.3F,2.1.2.3D, and 2.1.2.3E. This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described i in the Annual Radiological Environmental Operating Report. The methodology and parameters used to estimate the potential annual dose 1o a member of the public shall be indicated in this report. 86.0 rm. i

_..-.~ Number bdeM Tui Radiorogicai Controts Departmental Procedure 6610-PLN-4200.01 True Revision No. Offsite Dose Calculation Manual (ODCM) 7 l c. With milk or fresh leafy vegetation samples unavailable from one or more of the sample locations required by Table 8.1, identify specific locations for obtaining replacement samples - and add them within 30 days to the Radiological Environmental Monitoring Program given in the ODCM. The specific locations from which samples were unavailable may then be deleted from the monitoring program. Pursuant to TMI-1 Tech. Spec. 6.14 and TMl-2 PDMS Tech. Spec. 6.12, submit in the next Annual Radioactive Effluent Release Report documentation for a change in the ODCM including a revised figure (s) and table for the - ODCM reflecting the new location (s) with supporting information identifying the cause of the unavailability of samples and justifying the selection of the new location (s) for obtaining l samples. i 8.1.4 Bases t The radiological monitoring program required by this control provides representative measurements of radiation and of radioactiv9 materials in those exposure pathways and for those radionuclides which lead to the highest potential radiation exposures c' r. ems of the general public resu!!ing from the station operation. This monitoring program implements Sectica IV B.2 of Appendix i to 10CFR50 and thereby supplements the radiological effluent monitoring program by verifying that the I measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the onvironmental exposure. pathways. Gu! dance for this monitoring is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring (Revision 1, November 1979). Program changes may be initiated based on operational experience. 8.1.5 Surveillance Reauirements l The radiological environmental monitoring samples shall be coller,ted pursuant to Table 8.1, from the i specific locations given in Tables 8.4 through 8.10 and Maps 8.1 through 8.3, and shall be analyzed pursuant to the requirements of Table 8.1 and the detection capabilities required by Table 8.3. r l i b i i 87.0 2nw

~ l Number bdeM TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 i Titie Revision No. l Offsite Dose Calculation Manual (ODCM) 7 -l l 8.2 Land Use Census 8.2.1 Controh I In accordance with the TMI-1 Tech. Specs. and TMI-2 PDMS Tech. Specs., a Land Use Census shall be conducted and shall identify within a distance of 8 km (5 miles) the location in each of the 16 meteorological sectors of the nearest milk animal, the nearest residence, and the nearest garden

2 2

of greater than 50 m (500 ft ) producing broad leaf vegetation. 8.2.2 Applicability i s' At all times. I 8.2.3 Action a. With a Land Use Census identifying a location (s) that yields a calculated dose or dose commitment greater than the values currently being calculated in TMI-1 Tech. Spec. 4.22.2.3, pursuant to ODCM, Part 111. Section 2.0, identify the new location (s) in the next Annual Radioactive Effluent Release Report. b. With a Land Use Census identifying a location (s) that yields a calculated dose or dose commitment (via the same exposure pathway) 20% greater than at a location from which samples are currently being obtained in accordance with Table 8.1, add the new location (s) within 30 days to the Radiological Environmental Monitoring Program given in the ODCM. The sampling location (s), excluding the control station location, having the lowest calculated dose or doso commitment (s), via the same exposure pathway, may be deleted from this -[ monitoring program after October 31 of the year in which this Land Use Census was conducted. Pursuant to TMI-1 Tech. Spec. 6.14 and TMI-2 PDMS Tech. Spec. 6.12, submit in the next Annual Radioactive Effluent Release Report documentation for a change in the ODCM inc:uding a revised figure (s) and table (s) for the ODCM reflecting the new location (s) with information supporting the change in sampling locations. 8.2.4 Bases This Control is provided to ensure that changes in the use of unrestricted areas are identified and modifications to the monitoring program are made if required by the results of this census. The best information from the door-to-door survey, aerial surveys, or consulting with local agricultural authoritie3 shall be used. This census satisfies the requirements of Section IV.B.3 of Appendix I to 2 10 CFR 50. Restricting the census to gardens of greater than 500 square feet (50 m ) provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/yr) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were used: 1) that 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and 2) a vegetation yield of 2 kg/ square meter. i Broad leaf vegetation r..npfing of at least three different kinds of vegetation may be performed at the site boundary in each L. two different sectors with the highest predicted D/Os in lieu of TFe garden census. Requiremente 'or broad leaf sampling in Table 8.1 shall be followed, including analysis ci control samples. 88.0 m i i

Number Numlear " "a* ' 9'oa' 1 Departmental Procedure 6610-PLN-4200.01 v Title Revision No. Offsite Dose Calculatlon Manual (ODCM) 4 8.2.5 Surveillance Reauirements The t.and Use Census shall be conducted during the growing season at least once per 12 months, using that information that will provide the best results, such as by a door-to4oor survey, aerial survey, or by consulting local agricultural authorities. The results of the land Use Census shall be included in the Annual Radiological Environmental Operating Report pursuant to ODCM, Part 111, l Section 1.0. p 1 t i c i l 89 0 am, i

Numbsr ( d ear Tui Radiologicai Controis Departmental Procedure _ 6610-PLN-4200.01 - Inte Revision No. Offsite Dose Calculation Manual (ODCM) 7 8,3 Intertaboratory Comparison Proaram i 8.3.1 Controls l i In accordance with the TMI-1 Tech. Specs. and TMl-2 PDMS Tech. Specs., analyses shall be l performed on radioactive materials supplied as part of an Interfaboratory Comparison Program i which has been approved by the Commission (NRC). Only those samples and analyses which are required by Table 8.1 shall be performed. 8.3.2 Applicability i At all times. I 8.3.3 Action j With analysis not being performed as required above, report the corrective action taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report. l t 8.3.4 Bases } The requirement for participation in an approved Interlaboratory Comparison Program is provided to ensure that independent checks on precision and accuncy of the measurements of radioacthe l material in environmental sample matrices are performed as part of a quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid for the i purpose of Section IV, B.2 of Appendix i to 10 CFR 50. { l 8.3.5 Surveillance Reauirements A summary of the Interlaboratory Comparison Program results shall be included in the' Annual I Radiological Environmental Operating Report. ] 1 M0 4 im,

Number - gggp TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 TUs. Rewston No. Offsite Dose Calculation Manual (ODCM) 3 4 TABLE 8.1 i i Sample Collection and Analysis Requirements

i t

Number of Samples Exposure Pathway and Sampling and Type and Frequency and/or Sample Sample Locations

Collection Frequency" of Analysis'

-l

1. Airborne i

Radiolodine and Samples from 5 location? Continuous sampler Radiolodine Canister: Particulates from Table 8.4. operation with sample Analyze weekly for 1-131. j collection weekly, or more Particulate Fi!!er: frequently if required by dust Analyze for gross beta j loading. radioactivity following filter change'. Perform gamma isotopic analysis' on composite (by location) sample quarterly.

2. Direct Samples from 40 Sample Quarterly Analyze for gamma dose Radiation' locations from Table 8.5 quarter 1y.

p (using either 2 l dosimeters or at least 1 -l t instrument for continuously measuring and recording dose rate l at each location). j i I ( i f i 6 I I i I i l 91.0 nm. i

-1 i Numto j jUClBar - TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 - htie Revision No.. Offsite Dose Calculation Manual (ODCM) 3 l TABLE 8.1 (Cont'd) i' Sample Collection and Analysis Requirements i Number of Samples l Exposure Pathway and Sampling and ' Type and Frequency and/or Sample Sample Locations' Collection Frequency *. of Analysis'

3. Waterborne

a. Surface' Samples from 2 locations Composite' sample over 1 Perform gamma isotopic

~j from Table 8.6. monthly period. analysis' monthly. Composite for tritium e 1 sample from analysis quarterly.- -li downstream (indicator) location e 1 sample from upstream i (control) location (or location not influenced by the station discharge)

b. Drinking Samples from 2 locations Composite' sample over 1 Perform gross beta and.

.i 'l from Table 8.6. monthly period. gamma isotopic analysis' monthly. Perform Sr-90 e 1 sample at the location analysis if gross beta of. of the nearest water monthly composite >10 { supply that could be times control. Composite affected by the station for tritium analysis discharge. quarterly.

1 sample from a control location.

c. Sediment from Samples from 2 locations Sample twice per year Perform gamma isotopic Shoreline (1 Control and 1 Indicator)

(Spring and Fall), the interval analysis' on each sample, i from Table 8.7. not to exceed 184 days. l l, I i 92.0 mu i O

~. i Numbst l (UClear m a diigi i Controis Departmental Procedure 6610-PLN-4200.01 i Title Revisiori No. i Offsite Dose Calculation Manual (ODCM) 3 l TABLE 8.1 (Cont'd) Sample Collection and Analysis Requirements i Number of Samples Exposure Pathway and Sampling and Type and Frequency 1 and/or Sample Sample Locations

Collection Frequency" of Analysis' j

4. Ingestion

{

a. Milk Samples from 4 locations Sample semimonthly when Perform gamma isotopic from Table 8.8.

animals are on pasture; analysis' and 1-131 i monthly at other times. analysis on each sample. l Composite for Sr-90 j analysis quarterly. {

b. Fish Samples from 2 locations Sampta Mice per year Perform gamma isotopic' from Table 8.9.

(Spring rd Fall), the interval and Sr-90 analysis on j not to exceed 184 days. edible portions.

1 sample of l

recreationally important bottom feeders and 1 sample of recreationally important predators in the vicinity of the station discharge.

1 sample of

.f recreationally important bottom feeders and 1 sample of recreationally important predators from an area not influenced by the station discharge. l t i i a 1 1 J 93.0 2m. i t [

Numbzr i bdeM' TMI Racilological Controls Departmental Procedure - 6610-PLN-4200.01_ l Tdle Revision No. Offsite Dose Calculation Manual (ODCM) 3 i TABLE 8.1 (Cont'd) i Sample Collection and Analysis Requirements i a Number of Samples Exposure Pathway and Sampling and Type and Frequency. and/or Sample Sample Locations' Collection Frequency" of Analysis'

c. Food Samples from 2 locations Sample at time of harvest.

Perform gamma isotopic', Products from Table 8.10 (when 1-131, and Sr-90 analysis available) on edible portions. e 1 sample of green leafy vegetables or leafy vegetation at a location in the immediate vicinity of the station. (indicator) o 1 sample of same species or graup from a location not influenced by the station discharge. Samples from 4 locations Sampfe fruits and Perform gamma isotopic - (3 indicator and 1 control) vegetables at time of analysis' on edible from Table 8.10 (when harvest. portions. available). { i i 1 j 94.0 nn,

l Numbsr 1 bdeM TM! Radiological Controls 1 Departmental Procedure 6610-PLN-4200.01 l Titie Revision No. l l Offsite Dose Calculation Manual (ODCM) 3 i TABLE 8.1 (Cont'd) Sample Collection and Analysis Requirements Table Notation Sampling locations are provided in Tables 8.4 the ough 8.10. They are depicted in Maps 8.1 through 8.3. a. Deviations are permitted from the required sampi'ng schedute if specimens are unobtainable due to hazardous conditions, seasonal unavailability, mafunction of automatic sampling equipment and other legitimate reasons. All deviations from the sampfi7g schedule shall be explained in the Annual Radiologica! l Environmental Operating Report. b. Frequency notation: weekly (7 days), semimonth!/ (15 days), monthly (31 days), and quarterly (92 days). All surveillance requirements shall be pedormed w: thin the specified time interval with a maximum allowable j extension not to exceed 25% of the surveillance interval. A total maximum combined interval time for any 4 consecutive tests shall not exceed 3.25 times the f.pecified collection or analysis interval. ? c. One or more instruments, such as a pressurized ion chamber for measuring and recording dose rate ' f continuously, may be used in place of, or in additian to, integrating dosimeters. For the purpose of this - table, a thermoluminescent dosimeter (TLD) is cor,sidered to be one phosphor; two or more phosphors in a packet are considered as two or more dosimeters. Film badges shall not be used as dosimeters for measuring direct radiation. I d. Airbome particulate sample fl!!ers shall be analyzed for gross beta radioactivity 24 hours or more after sampling to allow for radon and thoron daughter decay. If gross beta acth,'ity in an air particulate sample (s) is greater than ten times the calendar year mean of control samples, Sr-90 and gamma isotopic analysis { shall be performed on the individual sample (s). e. Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility. f. The " upstream sample" shall be taken at a distance beyond significant influence of the discharge. The ' " downstream sample" shall be taken in an area beyond but near the mixing zone. g. Composite sample aliquots shall be collected at time intervals that are short (e g., hourly) relative to the compositing period (e.g., monthly) in order to assure obtaining a representative samp!e. i i i I' 95.0 m i l

l Numt>tr Nuslear '"' "ad'o'oo'ca' contro'$ Departmental Procedure 6610-PLN-4200.01 nu. nemen no. Offsite Dose Calculation Manual (ODCM) 4 TABLE 8.2 Reporting Levels for Radioactivity Concentrations in Environmental Samples 1 Airbome Particulate Water or gas Fish Milk Food Products 3 Analysis (pCi/L) (pCi/m ) (.nCi/kg, wet) (pCl/L) (pCi/kg. wet) H-3 20,000(*) l Mn-54 1000 30,000 l Fe-59 400 10,000 l Co-58 1000 30,000 Co40 300 10.000 1 l Zn-65 300 20,000 Sr-90 8 0.1 100 8 100 l Zr-Nb-95 400 1-131 2 0.9 3 100 Cs-134 30 10 1000 60 1000 Cs-137 50 20 2000 70 2000 Ba-La-140 200 300 (*IFor drinking water samples. This is 40 CFR Part 141 value. l l l-l l 96.0 rin.

Numbst (UClOST m nadi i gi ai Controis Departmental Procedure 6610-PLN-4200.01 Tale Revision No. { i Offsite Dose Calculation Manual (ODCM) 4 t TABLE B.3 Detection Capabilities for Environmental Sample Analysis' j Lower Limit of Detection (lld)he Airborne l Particulate Fish I'o ad Sediment Water or Gas (pCi/kg. Milk Products (pCi/kg, Analysis (pCi/L) (pCi/m ) wet) (pCl/L) (pCl/kg, wet) dry) i 3 i Gross Beta 4 0.01 H-3 2000

f Mn-54 1b 130 i

Fe-59 30 260 f Co-58, 60 15 130 Zn-65 30 260 Zr-95 30 St90 2 0.01 10 2 10 Nb-95 15 d l-131 1 0.07 1 60 Cs-134 15 0.05 130 15 60 150 j Cs-137 18 0.06 150 18 80 180 i I Ba-140 60 60 La-140 15 15 i 97.0 nm s

Number gdgy TMI Radiological Controls Departmental Procedure 6610-PLN-4200,01 litle Revissort No. Offsite Dose Calculation Manual (ODCM) 3 i TABLE 8.3 (Cont'd) Detection Capabilities for Environmental Sample Analysis' - Table Notation a. This list does not mean that only these nuclides are to be considered. Other peaks that are identifiable, which may be related to punt operations, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report. ^ b. Required detection capabilities for thermoluminescent dosimeters used for environmental measurements are given in Regulatory Guide 4.13 (Rev.1). t c. The LLD is defined, for purposes of these controls, as the smallest concentration of radioactive material in a { sample that will yield a net count, above system background, that will be detected with 95% probability with i only 5% probability of falsely concluding that a blank observation represents a "real" signal. For a particular measurement system (which may include radiochemical separation):

.66 S 3

ttp. E V 2.22 Y exp (-Aat) Where: LLD is the "a priori" lower limit of detection as defined above, as picocuries per unit mass or vefume. i s,is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate, as counts per minute, t i E is the counting efficiency, as counts per disintegration, f V is the sample size in units of mass or volume, l d 2.22 is the number of disintegrations per minute per picocurie, Y is the fractional radiochemical yleid (when appilcable), 1 A is the radioactive decay constant for the particular radionuclide and at for environmental samples is the elapsed time between sample collection, or end of the sample collection . j period, and time of counting. Typical values of E, V, Y and at should be used in the calculation. it should be recognized that the Lt D is defined as an "a priori" (before the fact) limit representing the capability of a measurement system and not as an "a posteriori" (after the fact) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs will be achiewd under routine conditions. Occasionally background fluctuations, unavoidable small sampics sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report. d. LLD for drinking water. 98.0 2mi ]

nt=

v r m -. m m-. m mu - . r

._ ~ __ i Numbst (gggy TMI Radiological Controls j Departmental Procedure 6610-PLN-4200.01 ~ Title Revision No. Offsite Dose Calculation Manual (ODCM) 3 i TABLE 8.4 TMINS REMP Station Locations-Air Particulate an'd Air lodine I Station Code Distance (miles) Azimuth (*) MapNo. -l ? B1-4 0.8 28 60 El-2 0.4 95 2 l F1-3 0.6 105 70 -l G2-1 1,4 125 75 M2-1 1.3 253 3 A3-1 2.S 358 4 H3-1 2.3 159 5 l J3-2 2.9 181 71 04-1 3.5 325 92 G10-1 9.8 127 6 l J15-1 12.6 180 7-i 015-1 13.5 305 8 i TABLE 8.5 TMINS REMP STATION Locations-Direct Radiation (TLD) 'i i Station Code Distance (miles) Azimuth (*) MapNo. A1-1 0.4 0 1 A1 -4 0.3 5 9 B1-1 0.6 25 10 B1 -2 0.4 26-11 B1-3 0.5 15 12 C1-2 0.3 54-13 D1-1 0.2 74 14 ' E1-1 0.2 95 15 El-2 0.4 95 2 El-4 0.2 98 16 F1-2 0.2 109 17-G1-3 0.3 129 18 H1-1 0.5 167 .19 I H1-9 0.3 167 20 J1-1 0.8 184' 21 3 J1-3 0.3 189 22 J1-4 0.4 188 23 K1-4 0.2 208 24 i K1-5 0.2 202 . 25 L1-1 0.1 235 26- ] M1-1 0.1 249 27 N1-3 0.1 270 28 I P1-1 0.4 293 29 P1-2 0.2 290 30 99 0 nm.

smuu gdgp TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 i Tatte Revision No. Offsite Dose Calculation Manual (ODCM) 3 l i TABLE 8.5 (Cont'd) I TMINS REMP STATION Locations-Direct Radiation (TLD) Station Code Distance (nM Azimuth (*) MapNo. 01-2 0.2 318 31 i R1-1 0.2 335 32 [ C2-1 1.6 48 33 i K2-1 1.1 200 34 M2-1 1.3 253 3 A3-1 2.6 358 4 H31 2.3 159 5 R3-1 2.6 338 35 B5-1 - 4.8 18 36-C5-1 4.5 42 37 E5-1 4.6 81 38 FS-1 4.7 107 39 GS-1 4.8 131 40 ? H5-1 4.1 157 41 J5-1 4.9 182 42 K5-1 5.0 200 43 -l LS-1 4.1 228 44 MS-1 4.3 249 45 N5-1 4.9 2GB 46 PS-1 4.9 285 47 l 05-1 5.0 318 48 RS-1 4.9 339 49 D6-1 5.2 65 50 E71 6.8 86 51 09-1 8.5 308 52 j B10-1 9.4 21 53 G10-1 9.8 127 6 I G15-1 14.4 124 54 J15-1 12.6 180 7 015-1 13.5 305 8 R15-2 12.4 329 55 l l l l i I l t 100.0 un, 1 ~ -

Numbst (UClear M Radidogical Contrds Departmental Procedure 6610-PLN-4200.01 l Tce Revision No. Offsite Dose Calculation Manual (ODCM) 3 TABLE 8.6 i TMINS REMP Station Locations-Surface Water Station Code Distance (miles) Azimuth (*) MapNo. P1-3 (R) 0.1 284 56 J1-2 (R) 0.5 188 57 J2-1 (R) 1.5 182 58 l A3-2 (R) 2.5 335 59 l H5-2 (F) 4.2-157 61 09-1 (F) 8.5 308 52 ? 3' 5-1 (F) 14.4 124 54 G15-2 (F) 13.6 128 62 G15-3 (F) 14.8 124 63 J15-2 (F) 14.7 178 64 l F15-1 (R) 12.6 122 65 (R) = Raw Water (F) = Finished Water i .1 TABLE 8.7 i TMINS REMP Station Locations-Aquatic Sediment { 1 Station Code Distance (miles) Azimuth (*) MaoNo. t A1-2 0.8 6 66 l A1-3 0.5 0 67 G1-1 0.3 137 68 j K1-3 0.3 202 69 J2-1 1.5 182 58 j ) i I i i i 101.0 2m. r -,.. + - .-.4,

f Numhor (UClear M Radiological Contrds i Departmentai Procedure 6610-PLN-4200.01 Title Revision No. Offsite Dose Calculation Manual (ODCM) 3 f i TABLE 8.8 TMINS REMP Station Locations-Milk i Station Code Distance (miles) Arimuth (*) Map No. [ A2-1 (MG) 1.2 5 - 72 A15 2 (MG) 14.2 9 73 D2-1 (M) -1.1 65 74 G2-1 (M) 1.4 125 75 P7-1 (M) 6.7 293 76 K15-2 (M) 12.8 208 77 F3-1 (M) 2.3 104 78 i E2-2 (M) 1.1 93 79 i A4-1 (M) 3.3 10 93 l r (MG) = Goat Milk (M) = Cow Milk l TABLE 8.9 TMINS REMP Station Locations-Fish Station Code Station Loca' ion ' f TM-AOF-IND Downstream of Station Discharge l . TM-AOF-BKG Upstream of Station Discharge i AOF = Fish j ) l 102.0 rm.

Number i -(UClear iR diigi i controis - Departtmntal Procedure 6610-PLN-4200.01 Tatie Revision No. l l Offsite Dose Calculation Manual (ODCM) 3 i TABLE 8.10 i TMINS REMP Station Locations-Food Products l Azim, uth (*) MapNo. Station Code Distance (miles) l D2-1 1.1 65 74 l G2-1 1.4 126 75 l A9-2 9.3 357 80 i P3-1 2.6 293 - 81 A15-1 10.5 10 82 l El 3 0.7 90 83 j E2-1 1.1 80 84 i H1-2 0.9 150

85 E6-1 5.9 100 86 l

M15-2 13.6 253 87 D1-3 0.5 65 88 I A2-1 1.2 5 72 P7-1 6.7 293 76 K15-2 12.8 208 77 A15 2 14.2 9 73 i F3-1 2.3 104 78 j E2-2 1.1 93 79 B15-1 10.3 12 89 3 [1-2 0.4 95 2 R15-2 12.4 329 55 F1-1 0.5 117 91 J2-2 1.5 178 90 A4-1 3.3 10 93 i M2-2 1.3 252 94 1 N2-2 1.3 265 96 H1-3 0.7 150 96 [ 1 ) 103.0 nm. l i

Number - Nuclear " "ad' '**' coat

J Departmental Procedure 6610-PLN-4200.01

) Tatie Revisiori No. 1 Offsite Dose Calculation Manual (ODCM) 3 3 4 e. 7 5 . 33.75 320.25 A. g R j gL I, waar ',, 6 se.as we c 103. j s 5 0 ^ I ooqHoAN r. o 7e.7s p w q o, p ,e,.,..~ _< j jO E qcas 5%'" (<I & :, L,- A = gn O-;s, y,,,.,, .m F ise.7 ,,j u T [E WILE ' AN it / CN '0 s 2.7s H $ 4 14 213.7 5 I9t.t s .\\ e I MAP 1 THREE MILE ISLAND NUCLE!4R STATION LOCATIOk3 0F RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM STATIONS WITHIN 1 MILE OF THE SITE .l l MAP 8.1 THREE MILE ISLAND NUCLEAR STATION LOCATIONS OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM STATIONS WITHIN 1 MILE OF THE SITE 104.0 rm. i

wraver - Nuclear " "ad'd o'c"' o"" 1 Departmental Procedure 6610-PLN-4200.01 i Title Revision No ] Offsite Dose Calculation Manual (ODCM) 3 J i N 1 A / / o... e 'I 37 g 4+.,

If e

ton,o,o; raar i / j s 3 ..u 3 ) s 4 m oonos( i g g wi e 3 .u zu g 3! Sa u

5 r

t 66

F1 i

,a.... N C.W. RRY/ 'E L I o \\\\ + l t s l a MAP 2 THREE MILE ISLAND NUCLEAR STATION LOCATIONS DE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM STATIONS WITHIN 5 MILES OF THE $1TE I MAP 8.2 THREE MILE ISLAND NUCLEAR STATION LOCATIONS OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM STATIONS WITHIN 5 MILES OF THE SITE 105.0 em.

i Mumte Nuclear ' aad' ' 9*"' coa" '$ Departmental Procedure GG10-PLN-4200.01 Title. Revision No. [ -l Offsito Doso Calculation Manual (ODCM) 3 i i l e N I l o Il g e ., e' to

3,

== g gger P &LW fS4 L C'31"' so .u f s, ts== o f .u... me [, ' ' * = a so 7 s 33 t E 8' i a unautw ee. uu. sr '%,.m, ' ,== svts m W ,, as 'O nma 77 l vm t 'J i s= K n MAP 3 THREE MILE !$ LAND NUCLEAR STATION LOCATIONS OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM STATIONS GREATER THAN 5 MILES FROM THE SITE '? I i MAP 8.3 THREE MILE ISLAND NUCLEAR STATION LOCATIONS OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM STATIONS GREATER THAN 5 MILES FROM THE SITE -i 106.0 nm. g

i i %mbor FUl Nuclear " "adid o'c^'c "t'd* Departmental Procedure 6610-PLN 4200.01 - Titie Revision No. t Offsite Dose Calculation Manual (ODCM) 7 l 9.0 PART I REFERENCES 1. EPRI NP-3840, RP 1560-3 Final Report, " Environmental Radiation Doses From Difficult-To-Measure Nuclides," January 1985 2.

Evaluation of the Three Mile Island Nuclear Station Unit 1 to Demonstrate Conformance to the l

Design Objectives of 10 CFR 50, Appendix 1," Nuclear Safety Associates, May 1976 3. TMl-1 Final Safety Analysis Report (FSAR) 4. TMI-2 Final Safety Analysis Report (FSAR) r 5. MeteorologicalInformation and Dose Assessment System (MIDAS) ? ? 6. NUREG-0017. " Calculation of Releases of Radioactive Materials in Gaseous and Uquid Effluents from PWR," Revision 1,1985 7. NUREG-0133,

Preparation of Radiological Effluent Technical Specifications for Nuclear Power.

I Plants," October 1978 i 8. NUREG-0172 " Age-Specific Radiation Dose Commitment Factors For A One-Year Chronic intake," l November 1977 9. Regulatory Guide 1.21,

Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and l

Releases of Radioactive Materlats in Uquid and Gaseous Effluents from Ught-Water Cooled Nuclear. Power Plants," Revision 1, June 1974 i 10. Regulatory Guide 1.109, ' Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR 50, Appendix 1," Revision 1, i October 1977 11. Simplified Environmental Effluent Dosimetry System (SEEDS) i 12. TMI Recirculation Factor Memos, April 12,1988 and March 17,1988 -l -i 13. TMI-1 Operations Procedure, 11012.1, " Radiation Monitor Set Points' .j i 14. Title 10 Code of Federal Regulations, " Energy" l .i 15. TMI 1 Technical Specifications, attached to Facility Operating Ucense No. DPR-50 l 16. Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Ught. Water-Cooled Reactors," Revision 1, July 1977 l 17. TMI 2 PDMS Technical Specifications, attached to Facility Ucense No. DPR 73 18. Radiological Assessment Branch Technical Position on Environmental Monitoring, Revision 1.- .j November 1979 19. Title 40, Code of Federal Regulations, " Protection of Environment". 107.0 rm

i Number j -(UClear TMI Radiological Controls ] Departmental Procedure 6610-PLN-4200.01 ] we n vision no. Offsite Dose Calculation Manual (ODCM) 7 i 20. Regulatory Guide 4.13, " Performance, Testing and Procedural SpecifFations for Thermoluminescence Dosimetry: Environmental Applications," Revision 1, July 19'7 21. Post-Defueling Monitored Storage Safety Analysis Report (PDMS SAR) f a 5 i l l 1 j J 108.0 25m

Number Nuclear " "*did*^' ""d* Departmental Procedure 6610-PLN-4200.01 Title Revision No. Offsite Dose Calculation Manual (ODCM) 3 i PART11 TMI-2 RADIOLOG' CAL EFFLUENT CONTROLS 109.0 n2=

i Number - (UClear-TMl Radiological Controla f Departmental Procedure 6610-PLN-4200.01 Title Revition No. t I Offsite Dose Calculation Manual (ODCM) 7 PART!! Definitions [ 1.0 DEFINITIONS DEFINED TERMS a 1.1 The DEFINED TERMS of this section appear in capitalized type and are app!! cable throughout Part 11 of the ODCM. FACluTY MODE 3 1.2 Post-Defueling Monitored Storage (PDMS) is that condition where TMI-2 defueling has been completed, the core debris removed from the reactor during the clean-up period has been shipped off-site and the facility has been placed in a stable, safe and secure condition. ~ ACTION I .l 1.3 ACTION shall be those additional requirements specified as corollary statements to each control and shall be part of the controls. OPERABLE - OPERABILITY v 1.4 A system, subsystem, train, component or device shall be OPERABLE or have OPERABluTY when it is capable of performing its specified function (s). Implicit in this definition shall be the assumption that all necessary attendant instrumentation, controls, normal and emergency electrical power sources, cooling or seal water, lubrication or other auxiliary equipment, that are required for the system, subsystem, train, component or device to perform its function (s), are also capable of performing their related support function (s). 3 CHANNEL CAUBRATION [ 1.5 A CHANNEL CAUBRATION shall be the adjustment, as necessary, of the channel output such that it i responds with necessary range and accuracy to known values of the parameter which the channel [ monitors. The CHANNEL CAUBRATION shall encompass the entire channel including tho sensor y and alarm and/or trip functions, and shall include the CHANNEL FUNCTIONAL TEST. CHANNEL : [ CAUBRATION may be performed by any series of sequent!al, overlapping or total chann# steps such that the entire channel is calibrated. t CHANNEL CHECK i l 1.6 A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by [ observa:lon. This determination shall include, where possible, comparison of the channel indication j and/or status with other indications and/or status derived from independent instrument _ channels measuring the same parameter. i ~! I I 110.0 mm -i y v-r r s 1 e -e--

Numbst gdgp TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 Tde Revision No. Offsite Dose Calculation Manual (ODCM) 7 i i NOTE For radioactive effluent monitors, except for those in Table 2.2-1, this shall include a verification which provides a qualitative assessment of channel response when the channel sensor is exposed to a radioactive r source. CHANNEL FUNCTIONAL TEST [ t 1.7 A CHANNEL FUNCTIONAL TEST shall be: I a. Analog channels - the injection of a simulated signal into the channel as close to the primary f sensor as practicable to verify OPERABluTY including alarm and/or trip functions., b. Bistable channels - the injection of a simulated signal into the channel sensor to verify OPERABluTY including alarm and/or trip functions. FREOUENCY NOTATION 1.8 The FREQUENCY NOTATION specified for the perfortnance of Surveillance Requirements shall correspond to the intervals defined in Table 1.1. COMl=OSITE SAMPLE 1.9 A COMPOSITE SAMPLE is a combination of individual samples obtained at regular intervals over a time period. Elther the volume of each individual sample is proportional to the low rate discharge at I the time of sampling or the number of equal volume samples is proportional to the time period used to produce the composite. j GRAB SAMPLE -[ 1.10 A GRAB SAMPLE is an individual sample collected in less than fifteen minutes. .i BATCH RELEASE 1.11 A BATCH RELEASE is the discharge of fluid waste of a discrete volume. I _ CONTINUOUS RELEASE '{ 1.12 A CONTINUOUS RELEASE is the discharge of fluid waste of a non<liscrete volume, e.g., from a l volume or system that has an input flow during the CONTINUOUS RELEASE. I 111.0 me

i Number MUCIO8r TMl' Radiological Controls Departmental procedure 6610-PLN-4200.01 Tdle Revision No. Offsite Dose Calculation Manual (ODCM) 3 l TABLE 1.1 Frequency Notation NOT/ TION FREQUENCY S (Shiftly) At least once per 12 hours. D (Daily) At least once per 24 hours. W (Weekly) At least once per 7 days. M (Monthly) At least once per 31 days. 0 (Quarterly) At least once per 92 days. L ? SA (Semi-Annually) At least once per 184 days. A (Annually) At least once per 12 months.- R At least once per 18 months. N.A. Not applicable. l i i [ L i i i I 112.0 me

i Number i (UClear ml R di i gi ai Controls l Departmental Procedure 6610-PLN-4200.01 l Title Revision No. Offsite Dose Calculation Manual (ODCM) 7 l i SECTIONS 2.0,3.0 AND 4.0 Controls and Surveillance Requirements 2/3.0 APPLICABILITY t CONTROLS 2/3.0.1 Controls and ACTION requirements shall be applicable during the conditions specified for each control. 2/3.0.2 Adherence to the requirements of the Control and/or associated ACTION within the specified time interval shall constitute cornpliance with the control. In the event the Control is restored prior to expiration to the specified time interval, completion of the ACTION statement is not required. 2/3.0.3 in the event the Control and/or associated ACTION requirements cannot be satisfied because of ' circumstances in excess of those addressed in the Control, initiate appropriate actions to rectify the problem to the extent possible under the circumstances, and submit a special report to the Commission pursuant to TMI-2 PDMS Technical Specification (Tech. Spec.) Section 6 8.2 within 30 days unless otherwise specified. SURVEILLANCE REQUIREMENTS t t 4.0.1 Surveillance Requirements shall be applicable during the conditions specified for indMdual Controls unless otherwise stated in an Individual Surveillance Requirement. The Surveillance Requirements shall be performed to demonstrate compliance with the OPERABILITY requirements of the Control. 4 4.0.2 Each Surveillance Requirement shall be performed within the specified time interval with: I a. A maximum allowable extension not to exceed 25% of the surveillance interval, and I i b. A total maximum combined interval time for any 4 consecutive tests not to exceed 3.25 times the specified surveillance interval. 4.0.3 Performance of a Surveillance Requirement within the specified time interval shall constitute comp!!ance with OPERABILITY requirements for a Control and associateel ACTION statements unless otherwise required by the Control. J 113.0 ] nm ~-

Number gggy TMI Radiological Controls .l Departmental Procedure 6610-PLN-4200.01 Title Rewston No. j Offsite Dose Calculation Manual (ODCM) 3 i BASES The Controls of this serfors provide the general requirements applicable to each of the Control and Surveillance Requirements. 2/3.0.1 This Control defines the applicability of each Control in terms of the specified conditions and is provided to delineate specifically when each Control is applicable. 2/3.0.2 This Control defines those conditions necessary to constitute compliance with the terms of an individual Control and associated ACTION requirement. 2/3.0.3 This Control delineates the ACTION to be taken for circumstances not directly provided for in the { ACTION statements or when the provisions of the stated ACTION statement are not or cannot be complied with. The intent of this Control is to require that inoperable equipment be restored to an OPERABLE status in a prompt manner, that the unit be maintained in stable conditions, and that the Commission be promptly notified of such conditions. i 4.0.1 This Control provides that surveillance activities necessary to ensure the Controts are met and will be 1 performed during the FACluTY MODE or other conditions for which the Controls are applicable. 4.0.2 The provisions of this Control provide allowa5fe tolerances for performing surveillance activities beyond those specified in the normal surveillance interval. These tolerances are necessary to provide operational flexibility because of scheduling and performance considerations. The phrase "at least" associated with a i survei!!ance frequency does not negate this allowable tolerance value and permits the performance of more l frequent surveillance activities. The tolerance values, taken either individually or consecutively over 3 test intervals, are sufficiently restrictive to ensure that the reliability associated with the surveillance activity is not degraded beyond that obtained from the nominal specified interval. 4.0.3 The provisions of this Control set forth the criteria for determination of compliance with the OPERABluTY - requirements of the Control. Under this criteria, equipment, systems or components are assumed to be OPERABLE if the associated surveillance activities have been satisfactorily performed within the specified j time interval. Nothing in this provision is to be construed as defining equipment, systems or components OPERABLE, when such items are found or known to be inoperable although still meeting the Surveillance r Requirements. 4 1 i 'I i l i 114.0 me, m-- + -.. - - -. - ,,-n..

f0 umber bdeM' TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 htle Revision No. Offsite Dose Calculation Manual (ODCM) 7 2.0 RADIOLOGICAL EFFLUENT REQUIREMENTS .i 2.1 Radioactive Discharges .i 2.1.1 Liquid Effluents l 2.1.1.1 OBJECTIVES l To define the limits and conditions for the controlled release of liquid radioactive effluents to the environs to ensure that these re! eases are as low as practicable. These releases should not result 1.n radiation exposures to offsite areas greater than a few percent of background exposures..The-instantaneous release rate for all effluent discharges should be within ten times the concentrations specified in 10 CFR Part 20. To assure that the releases of radioactive liquids to offsite areas meet the *as low as practicable" concept, the fo!!owing objectives apply: A. The annual total quantity of radioactive materials in liquid waste, excluding tritium and 1 dissolved gases, should not exceed 5 curies per radioactive waste-producing reactor, and the annual dose to the whole body or any organ of an individual should not exceed 3 mrem to the total body and shall be less than or equal to 10 mrem to any orgart -{, B. The annual average concentration of radioactive materials in the effluent from the Mechanical Draft Cooling Towers prior to dilution in the Susquehanna River, excluding tritium and dissolved gases, should not exceed 2E-8 pCl/ml. i C. The annual average concentration of tritium in liquid waste prior to dilution in the environment should not exceed SE-6 pCl/ml. 2.1.1.2 APPLICABluTY Applies to the controlled release of radioactive liquids frcm TMl-2. 2.1.1.3 CONTROLS l t A. The radioactivity release concentration in liquid effluents from TMI-2 to the environment shall' not exceed ten times the values specified in 10 CFR 20, Appendix B, for unrestricted areas. B. The total release of radioactive liquid effluent from TMI-2, excluding tritium and noble gases, shall not exceed 10 curies during any calendar quarter. C. The equipment installed in the liquid radioactive waste system shall be maintained and shall be operated to process all radioactive liquid wastes prior to this discharge when the activity release rate will exceed 1.25 curies, excluding tritium and dissolved gases, during any j calendar quarter. 1 D. The maximum radioactivity to be contained in one liquid radwaste tank, excluding trillum ~ and dissolved gases, that can be discharged directly, to the environs, shall not exceed 10 curies. I I 115.0 j mm

hmbo: gggy TMl Radiological Controls Departmental Proceduro 6610-PLN-4200.01 1 Title Revision No. Offsite Dose Calculation Manual (ODCM) 7 7 E. When the average release rate of radioactive effluents, excluding tritium and dissolved gases, exceeds 2.5 curies per radioactive waste-producing reactor during any calendar quarter, the licensee shall notify the NRC within 30 days, identifying the causes and describing the proposed program of action to reduce such release rates. P F. The dose or dose commitment from liquid effluents shall be less than or equal to 3 mram total body and less than or equal to 10 mrem to any organ for the calendar year. t 2.1.1.4 BASES Liquid radioactive waste release levels to unrestricted areas should be kept *as low as practicable" and are not to exceed ten times the concentrations'specified in 10 CFR 20. The Controls provide reasonable assurance that the resulting annual exposure to an individual in off-site areas WHI not exceed the design objectives of Appendix 1 to 10 CFR Part 50, which were established as requirements for the cleanup of TMI-2 in the NRC's Statement of Policy of April 27,1981. This -l assurance is based on the fact that the Susquehanna River will dilute the liquid effluents upon their release from the site. The effluents will be diluted by a factor of about 250 in the region where finfish can exist (within a one-quarter mile radius of the discharge point). At the same time these Controls l permit flexibility under unusual conditions, which may temporarily result in higher than normal releases, but still within ten times the concentrations, specified in 10 CFR 20. It is expected that by l using this flexibility under unusual conditions, and exerting every effort to keep levels of radioactive material in liquid wastes as low as practicable, the annual releases will not exceed a small fraction of the annual average concentrations specified in 10 CFR 20. Contro! 2.1.1.3 A above requires the licensee to limit the concentration of radioactive materials in liquid effluents from TMI-2 to ten times the levels specified in 10 CFR 20, Appendix B, for unrestricted areas. This Control provides assurance that no member of the general public can be exposed to liquids containing radioactive materials in excess of limits considered permissible under l the Commission's rules and regulations. Control 2.1.1.3 B. above estab!!shes an upper limit for the release of radioactive liquid effluents, j excluding trbum and dissolved gases, of 10 curies during any calendar quarter. The intent of this Control is to permit the licensee flexibuity under unusual conditions, which may temporarily result in releases higher than the levels normally achievable when the unit and the liquid radwaste equipment are functioning as designed. Releases of up to 10 curies during any calendar quarter will result in concentrations of radioactive materials in liquid effluents at small percentages of the concentrations -l specified in 10 CFR 20. j Control 2.1.1.3 C. requires the licensee to maintain and operate the equipment installed in the liquid radioactive waste system to reduce the release of radioactive materials in liquid effluents to as low as practicable, consistent with the requirements of 10 CFR 50.36a. Normal use and maintenance of installed equipment in the liquid radioactive system is expected to result in releases of not more than about five curies per year, excluding tritium and dissolved gases during normal operations. In order to keep releases of radioactive materials as low as practicable, the Control requires, as a rr.inimum, operation of equipment whenever the rate of release exceeds 1.25 curies per quarter, excluding tritium and dissolved gases. .q 116.0 m 1 j

Namber [c g J1 Nuclear " " d' ' o'oa' c "t'd$ Departmental Procedure 6610-PLN-4200.01 i Title Rewsion No. Offsite Dose Calculation Manual (ODCM) 7 in addition to Control 2.1.1.3 B., the reporting requirements of Control 2.1.1.3 E. and Section 6.6 of the TMI-2 PDMS Tech. Specs., defineate that the licensee shall identify the cause whenever the rate of radioactive effluents, excluding tritium and noble gases, exceeds 2.5 curies during any calendar quarter and describe the proposed program o' action to reduce such release rates. This report must be filed within 30 days following the calendar quarter in which the 2.5 curie release occurred. Control 2.1.1.3 F. requires that the dose to offsite personnel be limited to the design objectives of Appendix I of 19 CFR Part 50. This will assure the dose received by the public during the cleanup is equivalent to c ;eds than that from a normal operating reactor. The limits also assure that the environmental impacts are consistent with those assessed in NUREG-0683, the TMI-2 Programmatic Environmental Impact Statement (PElS). 2.1 2 Gaseous Effluents 2.1.2.1 OBJECTIVES To define the limits and conditions for the controlled rel ease of radioactive gaseous effluents to the environs to ensure that these releases are as low as practicable. These releases should not result in radiation exposures in offsite areas greater than a few percent of background exposures. To assure that the release of radioactive gases to offsite areas meet the as low as practicable concept, the release rate of gaseous effluents shall not result in doses to the public exceeding the design objectives of Appendix I to 10 CFR Part 50. 2.12.2 APPLICABILITY Applies to the controlled release of radioactive gases from TMI-2. 2.1 'L3 GvNTROLS A. The instantaneous dose rate from release of gross gaseous activity except for halogens and particulates with half-lives longer than eight days shall not exceed 500 mrem / year to the total body and 3000 mrem / year to the skin. B. The instantaneous dose rate from release of particulates with half-lives greater than eight days, to the environs as part of the airborne effluents, shall not exceed 1500 mrem / year to any organ. C. Radioactive gases and particulates purged from the Reactor Building shall be filtered through the high efficiency particulate air filters. D. The air dose due to noble gases in gaseous effluents shall be less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation for the calendar year, and less than or cqual to 5 mrad for gamma radiation and 10 mrad for beta radiation for any calendar quarter. i E. The dose for radioactive (other than noble gaseous effluents) shall be less than or equal to 15 mrem to any organ for the calendar year, and 7.5 mrem to any organ for any calendar quarter. 117.0 m

h Number Nuclear ' "adi 'oo'ca' c "tr* Departmental Procedure 6610-PLN-4200.01 i Title Revision No. f Offsite Dose Calculation Manual (ODCM) 7 t F. When the release of radioactNe materials in gaseous wastes exceeds the values in Controls A, B. D or E, the licensee shall notify the NRC within 30 days, idenufying the causes and describing the proposed program of action to reduce such releases. 2.1.2.4 BASES The specified levels provide reasonable assurance that the resulting annual exposure rate from noble gases at any location at the site boundary will not exceed 10 millirems per year. At the same time, these Controls permit flexibility under unusual conditions, which may temporarily result in higher i than the design objective levels, but still within the dose limits specified in 10 CFR 20 and within the design objectives of Appendix 1 to 10 CFR 50. It is expected that using this flexibility under unusual i conditions, and by exerting every effort to keep levels of radioactive material in paseous wastes as low as practicable, the annual releases will not exceed a small fraction of the annual dose limits specified in 10 CFR 20 and will not result in doses which exceed the design objectives of Appendix I to 10 CFR 50, which were endorsed as limits for the cleanup of TMI-2 by the NRC's Statement of Policy of April 27,1981. These efforts should include consideration of meteorological corsditions during releases. ~ Control 2.1.2.3 A., requires the licensee to limit the concentration of noble gases from TMI-2 to unrestricted areas to levels such that no individual will receive dose at a rate greater than 500 l mrem /yr to the total body or 3000 mrem /yr to the skin. Control 2.1.2.3 B.., requires the licenseo to limit the concentratior, of particulates with half-lives greater than eight days, released from TMI-2 to unrestricted areas to levels such that no individual will receive dose at a rate greater than 1500 mrem /yr to any organ. The absence of iodine ensures that the corresponding thyroid dose rate above background to an infant via the cow-milk infant pathway is less than or equal to 1500 mrem /yr. A grazing period of 6 months has been applied to all radionuclides in particulate form with half-lives greater than 8 days, to allow for the milk exposure pathway. Control 2.1.2.3 C., limits the radioactivity that may be released to the environment to "as low as practic;ible * } In addition to the requirements of Controls 2.1.2.3 B., D. and E., the reporting requirements of Control 2.1.2.3 F. delineate that the licensee shall identify the cause whenever the radioactive gaseous releases exceed Control 2.1.2.3 D. or Control 2.1.2.3 E., and describe the proposed l program of action to reduce such releases. The report must be filed within 30 days following the l calendar quarter in which the release accurred. j 1 1 p 118.0 m

Mumber - (UCIO8r M Radiological Controls { Departmental Procedure 6610-PLN-4200.01 i Tme Revision No. i Offsite Dose Calculation Manual (ODCM) 7 l i 2.2 Radioactive Gaseous Effluent Monitoring instrumentation f i 2.2.1 OBJECTIVE The radioactive gaseous effluent monitoring instrumentation channels shown in Table 2.2-1 shall be OPERABLE. l 2.2.2 . APPLICABILITY j t As shown in Table 2.2-1. f 2.2.3 CONTROL i With less than the minimum number of radioactive gaseous effluent monitoring i instrumentation channels OPERABLE, take the ACTION shown in Table 2.2-1. 2.2.4 BASES The radioactive gaseous effluent instrumentation is provided to monitor and control, as - j applicable, the releases of radioactive materials in gaseous effluents during actual or f potential releases of gaseous effluents. The OPERABluTY and use of this instrumentation is ' l consistent with the requirements of General Design Criterion 64 of Appendix A to 10 CFR j Part 50. l i s b h I i l q 119.0 mm

l Numbor [r g JJ Nuclear ' "ad'#*^' co""d$ Departmental Procedure 6610-PLN-4200.01 istle Revissori No. Offsite Dose Calculation Manual (ODCM) 7 TABLE 2.2-1 Radioactive Gaseous Effluent Monitoring Instrumentation CHANNEL M:N MUM CHANNEL CHANNEL FUNCTIONAL CHANNELS INSTRUMENT CHECK CALIBRATION TEST OPERABLE APPLICABILITY ACTION HP-R-219 Gas D R M 1 Note 1 Note 2 HP-R-219 Particulate D R M 1 Note 1 Note 2 HP-R-219A Gas D R M 1 Note 1 Note 3 HP-R-219A Particufate D R M 1 Note 1 Note 3 HP-R-225 Gas D R M 1 Note 1 Note 4 HP-R-225 Particulate D R M 1 Note 1 Note 4 NOTES: l 1. During operation of the monitored system. 2. If the same channel on HP-R-219A is inoperable, secure Reactor Building Purge if in progress. 3. If the same channel on HP-R-219 is inoperable, secure Reactor Building Purge if in progress. 4. If channel is inoperable, secure Reactor Building Purge if in progress. l 120.0 me.

l %mber - gdgy TMI Radiological Controis Departmental Procedure GS10-PLN-4200.01 Title - Revmon No. l Offsite Dose Calculation Manual (ODCM) 7 I 3.0 MONITORING REQUIREMENTS I i 3.1 Radioactive Discharges { 3.1.1 Liquid Effluents j 3.1.1.1 OBJECTIVE I'i To ensure that radioactive liquid releases from the facility are within the limits of Controls 2.1.1.3 A. -l through F. 3.1.1.2 CONTROLS i During release of liquid radioactive wastes from Radioactive Waste-Miscellaneous Liquids Systemi ~i the following conditions shall be met: j A. Facility records shall be maintained of the radioactive concentrations and volume before j dilution of each batch of liquid effluent released, and the average dilution flow and length of j time over which each discharge occurred. Estimates of the error associated with each reported value should be included in facility records. l 1 B. Radioactive liquid waste sampling and activity analysis shall be performed in accordance 3 with Table 3.1 1. Prior to the release of each batch of liquid effluent, a sample shall be taken from that batch and analyzed for the concentration of each significant gamma emitter to demonstrate compilance with Control 2.1.1.3 A. using the flow into which the effluent is - discharged. 3.1.1.3 BASES These monitoring requirements provide the data for the licensee and the Commission to evaluate the station's performance relative to radioactive liquid wastes released to the environment. Reports on i the quantities of radioactive materials released in liquid effluents shall be fumished to the 'l l Commission on the basis of ODCM Part 111 Requirements. On the basis of such reports and any ) additional information obtained from the licensee or others, the Commission may require the licensee to take appropriate action. l 3.1.2 Gaseous Effluents j 3.1.2.1. OBJECTIVE To ensure that radioactive gaseous releases from the tacility are within the limits of Controls 2.1.2.3 A. through F. i 3.1.2.2 CONTROLS During release of radioactive gaseous wastes, the following conditions shall be met: i ~i b a 121.0 mm.

~ i Mumber (UClear i Radidogical Contrds f Departmental Procedure 6610 PLN-4200.01 Title nevisiori No. { Offsite Dose Calculation Manual (ODCM) 7 ' [ i A. During purge of the Reactor Building, the following conditions shall be met: 1. The Reactor Bu!! ding Purge Exhaust Monitors (HP-R-225 and HP-R-219 or similar device) shall be OPERABLE. 2. The Purge Exhaust Valves (D5129 A/D) shall be OPERABLE.- 3. The Purge Exhaust Valves (D5129 A/D) shall be Interlocked to recirculate on receipt of a high radiation signal from the Reactor Building Exhaust Monitor (HP-R-225). B. The flow rate for radioactive effluent streams and the Auxiliary and Fuel Handling Buildings and the Reactor Building, shall be monitored and recorded. Gaseous effluents from the j Reactor Building Purge Exhaust shall be continuously monitored and recorded. C. Radioactive gaseous waste sampling and activity analysis shall be performed in accordance l with Table 3.1-2. i i D. Facility records shall be maintained of radioactive concentration, release ratio and volume of r each batch of gaseous effluents released and the length of time over which release l occurred. Estimates of the error associated with each reported value should be included in facility records. E. The Unit Vent monitors (HP-R-219, HP-R-219A, and HP-R-225) shatt be CAllBRATED at least f every eighteen months by means of a known radioactive source. These detectors shall have ' a CHANNEL FUNCTIONAL TEST at least monthly, and a CHANNEL CHECK at least daily, to verify that the read-out device is indicated as expected. - j F. The release of radioactive materials, other than noble gases, in gaseous effluents shall be ' j determined to be within the limits calculated in accordance with this Control by obtaining representative samples and performing analyses in accordance with the sampling and analysis program, specified in Table 3.1-2. 3.1.2.3 BASES Controls 3.1.2.2 A. through E. require that suitable equipment to monitor the radioactive gaseous releases are operating during any period these releases are taking place. Control 3.1.2.2 F. is provided to ensure that the dose to a member of the public from gaseous effluents from TMI 2 will be within the limits of Control 2.1.2.3 D and Controt 2.1.2.3 E. These monitoring requirements provide assurance that radiaactive gaseous effluents from the station are properly controlled and monitored over the life of the station. These monitoring requirements provide the data for the licensee and the Commission to evaluate the station's performance relative to radioactive gaseous wastes released to the environment. Reports on the quantities of radioactive materials released in gaseous effluents shall be furnished to the Commission on the basis of ODCM Part Ill requirements. On the basis of such report and any additional information the Commission may obtain from the licensee or others, the Commission may from time to time require the licensee to take such action as the Commission deems appropriate. j i 122.0 mm -p p w. v .w,q--y+p-. 4 y w-- - - - -

n Number bdG8r TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 Ittle. Revisiori te. Offsite Dose Calculation Manual (ODCM) 7 l 3.2 Radioactive Gaseous Effluent Monitoring Instrumentation j Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL ) FUNCTIONAL TEST operations at the frequencies shown in Table 2.2-1 (per occupational exposure considerations and detector sensitMty in ambient radiation areas). i i t 5 f I i ~ l l f l l ~ I i ) 1 ) i \\ I j 123.0 mm .i I

Number -(UClear M Radiological Controls Departmental Procedure 6610-PLN-4200.01 Tnie Revision No. Offsite Dose Calculation Manual (ODCM) 7 TABLE 3.1-1 Radioactive Liquid Waste Sampling and Analysis (4,5) l A. Liouid Releaws Type of Detectable Sampling Frequency Activity Analysis Concentration (3) Each Batch IndMdual Gamma SE-7 pCi/ml (2) H-3 1E-5 pCl/ml Monthly Composite (1) Gross Alpha 1E-7 pCI/ml Sr-89 SE-8 pCi/ml Sr-90 SE-8 pCi/mi [ i NOTES: + (1) A COMPOSITE SAMPLE is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged from the plant. I r (2) For certain mixtures of gamma emitters, !! may not be possible to measure radionuclides in concentrations near this sensitivity limit when other nuclides are present in the sample in much greater concentrations. Under these circumstances, it will be more appropriate to calculate the concentrations of such radionuclides using measured ratios with those radionuclides which are routinely identified and measured. (3) The detectabHity limits for radioactivity analysis are based on the technical feasibility and on the potential significance in the environment of the quantitles released. For some nuclides, lower detection limits may be i readily achievable and when nuclides are measured below the stated limits, they should also be reported. (4) The results of these analyses should be used as the basis for recording and reporting the quantities of radioactive material released in liquid effluents during the sampling period. In estimating releases for a period when analyses were not performed, the average of the two adjacent data points spanning this period should be used. Such estimates should be included in the effluent records and reports; however, they -l should be clearly identified as estimates, and the method used to obtain these data should be described. (5) Deviations from the sampling / analysis regime will be noted in the report specified in ODCM Part 111. l 9 3 124.0 mm l

~. i Number hdeM Tui Radi i gi ai controis Departmental Procedure 6610-PLN-4200.01 T rtle Revision No. Offsite Doso Calculation Manual (ODCM) 7 1 TABLE 3.1-2 -[ Radioactive Gaseous Waste Sampling and Analysis (3) i SAMPLE SAMPLING TYPE OF DETECTABLE SAMPLE POINT TYPE FREQUENCY ACTIVITY ANALYSIS CONCENTRATION (1)(a) 'i Reactor Building Purge Releases Gas Each Purge H-3 1E4 pCi/cc Individual Gamma Emitters 1E-4 Ci/cc (2) j Unit Exhaust Vent Release Points Gas MontNy H-3 1E-6 pCl/cc indMdual Gamma Emitters 1E-4 pCl/cc (2) l IndMdual (b) Particulates Weekly Gamma Emitters 1E 10 pCi/cc (2) Monthly Composite Sr-90 1E-11 pCl/cc Monthly Gross Alpha j Composite Emitters 1E-11 pCi/cc Reactor Building Breather Particulates Semi-Annually indv. Gamma 1E-10 pCl/cc (2) Emitters (b) Sr-90 1E-11 pCi/cc Gross Alpha 1E-11 pCl/cc Emitters (1) The above detectah!!ity hmits are based on technical feasibility and on the potential significance in the environment of the quantitles released. For some nuclides, lower detection limits may be readily achievable and when nuclides are measured below the stated limits, they should also be reported. j i ' (2) For certain mixtures of gamma emitters, it may be possible to measure radionucli+s at levels near their sensitivity limits when other nuclides are present in the sample at much higher levels. Under these circumstances, it will be more appropriate to calculate the levels of such radionuclides using observed ratios in the gaseous component in the reactor coolant for those radionuclides which are measurabie. (3) Deviations from the sampling and analysis regime will be noted in the report specified in ODCM Part 111. 4 4 125.0 mm

i

l f

Number -(UClear i nadid gi al contres j Departmental Procedure - 6610-PLN-4200.01 j Tdle Revision No. ll Offsite Dose Calculation Manual (ODCM) 7 j TABLE 3.1-2 (Cont'd) { t Radicactive Gaseous Waste Sampling and Analysis Program Table Notation I a. The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% i probability with 5% probability of falsely concluding that a blank observation represents a "real" signal. j For a particular measurement system (which may include radiochemical separation): i t 4.66 Sb LLD = i S V

2. 22 Y exp (- A A t) i Where j

LLD is the lower limit of detection as defined above (as picocurie per unit mass or volume). S is the standard deviation of the background counting rate or of the counting rate of a blank i b sample as appropriate (as counts per minute). E is the counting efficiency (as counts per transformation), V is the sample size (in units of mass or volume), 2.22 is the number of transformations per minute per picocurie, Y is the fractional radiochemical yield (when applicable), A is the radioactive decay constant for the particular radionuclide, and i at is the elapsed time between midpoint of sample collection and time of counting (for plant effluents. not environmental samples), I The value of S used in the calculation of the LLD for a detection system shall be based on the l e actual observed variance of the background counting rate or of the counting rate of the blank i samples (as appropriate) rather than on an unverified theoretically predicted variance. In calculating the L!D for a radionuclide determined by gamma-ray spectrometry, the background shall include the j typical contributions of other radionuclides normally present in the samples. Typical values of E, V. Y, and at shall be used in the calculation. The background count rate is calculated from the i background counts that are determined to be with i one FWHM (Full-Width-at-Half-Maximum) energy band about the energy of the gamma-ray peak used for the quantitative analysis for that radionuclide. 126.0 m

I Numbzr MUCIO8r~ mi a di i ai ai Connors - i Departmental ProcMure 6610-PLN-4200.01 l ~ Title Revision No. cl i Offsite Dose Calculation Manual (ODCM) 7 i i TABLE 3.12 (Cont'd) Radioactive Gaseous Waste Sampling and Analysis Program Table Notation b. The principal gamma emitters for which the LLD specification applies exclusively are the following - radionuclides: Mn-54, Fe 59, Co-58, Co@, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 for particulate emissions. This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and t reported. Nuclides which are below the LLD for the analyses shall be reported as "less than" the nuclide's LLD and shall not be reported as being present at the LLD level for that nuclide. The "less than* values shall I not be used in the required dose calculations. I l l f i i l l k y 1 i I i 127.0 I ma

. ~. i l Numt:Or (UClear-Mi Radiological Conkols Departmental Procedure 6610-PLN-4200.01 -j f Title Revision No. i Offsite Dose Calculation Manual (ODCM) 7 I I SECTION 4.0 j Design Features 4.0 DESIGN FEATURES 4.1 SITE EXCLUSION AREA ) 4.1.1 The exclusion area is shown in Figure 5 t, TMl-1 Tech. Specs. i LOW POPULATION ZONE 4.1.2 The low population zone is shown in Figure 5-2, TMI-1 Tech. Specs. SITE BOUNDARY FOR GASEOUS EFFLUENTS t 4.1.3 The site boundary for gaseous effluents shall be as shown in Figure 5-3, TMI-1 Tech. Specs. i f SITE BOUNDARY FOR UOUID EFFLUENTS 4.1.4 The site boundary for liquid effluents shall be as shown in Figure 54. TMI-1 Tech. Specs. b t '? 9 i I =i I 4 i 'f 1 128.0 . mu I -v~- --a

Numbst. gdgg TMl Radiological Controls Departmental Procedure 6610-PLN-4200.01 Title Revision No. j i Otisite Dose Calculation Manual (ODCM)' 7 I 5.0 PART 11 REFERENCES 5.1 NUREG-0683, " Final Programmatic Environmental Impact Statement related to decontamination and disposal of radioactive wastes resulting from March 28,1979, accident Three Mile Island Nuclear Station, Unit 2,* March 1981, and its supplements. .j 5.2 TMI-2 PDMS Technical Specifications, attached to Facility License No. DPR-73 5.3 Title 10, Code of Federal Pegulations.

Energy
j 5.4
Statement of Policy Relative to the NRC Programmatic Environmental impact Statement on the f

Cleanup of Three Mile Island Unit 2,* dated April 27,1981 i 5.5 Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor -l Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50 Appendix 1,* Revision 1, October 1977 5.6 DOE / TIC-27601, Atmospheric Science and Power Reduction 5.7 TMI-1 Technical Specifications, attached to Facility Operating License No DPR-50 l 5.8 PDMS-SAR t i f i f l r ? l I i 129.0 mm L

t Number ~f - (UClear i nadid gicai contres Departrcental Procedure _ 6610-PLN-4200.01 Title Revision No, Offsite Dose Calculation Manual (ODCM) 7 i i i ..i i PARTlli REPORTING REQUIREMENTS P i t I r I L 130.0 me,

Number m R di i i ai Controts (UClear Departmental Procedure 6610-PLN-4200.01 Title Recon No. - Offsite Dose Calculation Manual (ODCM) 7 PART lil Reporting Requirements 1.0 TMI ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT

1.1 Routine Radiological Environmental Operating Reports covering the operation of the unit during the previous calendar year shall be submitted to the Commission prior to May 1 of each year.

1.2 The Annual Radiological Environmental Operating Reports shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental monitoring activities for the report period, including a comparison with pre-operational studies, with operational controls as appropriate, and with previous environmental monitoring reports, and an assessment of the observed impacts of the plant operation on the environment. The reports shall also include the results of Land Use Censuses required by Part I, Section 8.2. 1.3 The Annual Radiological Environmental Operating Reports shall include the summarized tabulated resu!!s of analysis of all radiological environmental samples and environmental radiation measurements required by Part i Table 8.1 taken during the period pursuant to the locations specified in the tables and figures in this ODCM, as well as summarized and tabulate ( :o

s of these analyses and measurements in a format similar to the table in the Radiological Acc. ; ment Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report, the report shall be submitted explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.

1.4 The reports sha!! also include the following: a summary description of the radiological environments monitoring program; a map (s) of all sampling locations keyed to a table giving distances and directions from a point that is midway between the Reactor Buildings of TMI-1 and TMI-2; the results of licensee participation in the interfaboratory Comparison Program, required by Part I, Section 8.3; discussion of all deviations from the sampling schedule of Part I, Table 8.1; discussion of all the required analyses in which the LLD required by Part I, Table 8.3 was not achievable. ' A singte submittal may be made for the station. 131.0 mm

y hbmtor itIClear-TMi Radiological Controls d Departmental Procedure 6G10-PLN-4200.01 ] Trtie Revision FJo. Offsite Dose Calculation Manual (ODCM) 7 2.0 TMl ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NOTE A single submittal may be made for the station. The submittal should combine those sect;ons that are common to both units at the station j however, for units with separate radwaste systems, the submittal shall specify the release of radioactive material from each unit. 2.1 Routine Radioactive Effluent Release Reports covering the operations of the unit during the previous 12 months of operation shall be submitted within 60 days after January 1 of each year for TMI-1 and prior to May 1 for TMI.2. 2.2 The following information shall be included in both Radioactive Effluent Release Reports to be submitted each year: The Radioactive Effluent Release Reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Reg. Guide 1.21, Rev.1, with data summarized on a quarteriy basis following the format of Appendix B thereof,' 2.3 The Radioactive Effluent Release Reports shall include the following information for each type of solid waste shipped offsite during the report period: a. container volume, b. total curie quantity (specify whether determined by measurement or estimate), c. principal radionuclides (specify whether deterrnined by measurement or estimate), d. type of waste (e.g., spent resin, compacted dry waste, evaporator bottoms), e. type of shipment (e g., LSA, Type A, Type B) and f. solidification agent (e g., cement). 2.4 The Radioactive Effluent Release Reports shall include a summary of unplanned releases from the site to unrestricted areas of radioactive materials in gaseous and liquid effluents made during the reporting period. 2.5 The Radioactive Effluent Release Reports shall include any changes made during the reporting period to the PROCESS CONTROL PROGRAM (PCP) documents and to the OFFSITE DOSE CALCULATION MANUAL (ODCM), as well as a listing of new locations for dose calculations and/or environmental monitoring identified by the land use census pursuant to Part i Section 8.2. 2.6 The Radioactive Effluent Release Reports shall include the instrumentation not returned to OPERABLE status within 30 days per TMI-1 Tech. Spec. Sections 3.21.1.b and 3.21,2.b. 132.0 mm

h Numbor (UCIO8r TMl Radiological Controls oepartmentai Procedure . 6610-PLN-4200.01 Revision No. j Tatte l - Offsite Dose Calculation Manual (ODCM)- 7 l u" i 2.7 The Radioactive Effluent Release Report to be submitted shallinclude an annual summary of hourly l meteorological data collected over the previous year. This annual summary may be either in the j form of an hour-by-hour listing of wind speed, wind direction, atmosphere stat N, and precipitation (if measured) on magnetic tape, or in the form of joint frequency distribution of wind speed, wind direction, and atmospheric stability. 2.8 The Radioactive Effluent Release Report shall include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous _j calendar year. s 2.9 The Radioactive Effluent Release Report shall include an assessment of the radiation doses from - radioactive liquid and gaseous effluents to MEMBERS OF THE PUBUC due to their activities inside j the site boundary (Figure 5-3, TMI-t Tech. Specs.) during the report period. All assumptions used in j making these assessments (i.e., specific actMty, exposure time and location) shall be included in these reports. The meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents (as determined by sampling frequency and measurement) shall be used for determining the gaseous pathway doses. The assessment of radiation doses shall be performed in accordance with this ODCM. 2.10 The Radioactive Effluent Release Report shall also include an assessment of radiation doses to the likely most exposed real individual from reactor releases and other nearby uranium fuel cycle sources including doses from primary effluent pathways and direct radiation for the previous 12 j consecutive months to show conformance with 40 CFR 190

Environmental Radiation Protection Standards for Nuclear Power Operation." Acceptable methods for calculating the dose contributions from liquid and gaseous effluents are given in Regulatory Guide 1.109 Rev.1.

i i i f I i l i I t i 133 0 m h

Mumber - (' UClear i Radidogical Contrds j Departmental Procedure. 6610-PLN-4200.01 Trtle Revision No. Offsite Dose Calculation Manual (ODCM) 7 .t 3.0 PART 111 REFERENCES { 3.1 Radiological Assessment Branch Technical Position, Revision 1. November 1979 3.2 Regulatory Guide 1.21, " Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and .l Releases of Radioactive Materials in Uguld and Gaseous Effluents from Light-Water-Cooled Nuclear t Power Plants," Revision 1, June 1974 3.3 TMI-1 Technical Specifications, attached to Facility Operating Ucense No. DPR-50 3.4 Title 40, Code of Federal Regulations, " Protection of Environment" 3.5 Regulatory Guide 1.109,' Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix 1," Revision 1, October 1977 3.6 Title 10, Code of Federal Regulations, " Energy" 3.7 . Regulatory Guide 1.111, " Methods of Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases frorn Ught-Water-Cooled Reactors," Revision 1, July 1977 3.8 Regulatory Guide 1.112. " Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Ught-Water-Cooled Power Reactors," Revision O-R, April 1976 - .j 3.9 Regulatory Guide 1.113,

Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of implementing Appendix 1," Revision 1. April 1977 l

.f i 134.0 222m

Number - Nualear

' "*d' ' 9'ca' c "o'$

Departmental Procedure 6610-PLN-4200.01 Title Revision No. Offsite Dose Calculation Manual (ODCM) 3. APPENDIX A P,- Pathway Dose Rate Parameter P,(inhalation) = k' (BR) DFA, (Eq A-1) Where: P, = the pathway dose rate parameter for radionuclide, I, (other than noble gases) for the inhalation pathway, in 8 mrem /yr per microcurie /m. The dose factors are based on the critical individual organ for the child age -. group. k' = conversion factor,1E6 pCi/ microcurie BR = 3700 m'/yr, breathing rate for child (Reg. Guido 1.109. Rev.1. Table E-5) DFA,= the maximum organ inhalation dose factor for the infant age group for the ith radionuclide (mrem /pCl).- Values are taken from Table E-10, Reg. Guide 1.109 (Rev.1). Resolution of the units yields: (ODCM Part i Table 4.6) P,(inhalation) = 3.7E9 DFA, (mrem /yr per pCl/m') (Eq A-2). NOTE The latest NRC Guidance has deleted the requirement to determine P, (ground plane) and P, (food). In addition, the critical age group has been changed from infant to child. E11 m.

Numbai I AUClear TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 Tme Revision No. { .Offsite Dose Calculation Manual (ODCM) 3 i l APPENDIX B Ri-Inhalation Pathway Dose Factor I R, = k' (BR) (DFAJ (mrem /yr per microcurie /m') (Eq B 1) Where: k' = conversion factor,1E6 pCl/ microcurie BR = breathing rate. 1400, 3700, 8000, 8000 m'/yr for infant, child, teenager, and adult age groups, respectively. (Reg. Guide 1.109, Rev.1 Table E-5) DFA,= the inhalation dose factor for organ, o, of the receptor of a given age group, a, and for the ith u radionuclide, in mrem /pCl. The total body is considered as an organ in the selection of DF%. Values are taken from Tables E-7 through C-10, Reg. Guide 1.109 (Rev.1). i Resolutions of the units yields: f Ri = (1.4E9) (DFA ) infant (ODCM Part i Table 5.2.1) j u i Ri = (3 7E9) (DFA ) child (ODCM Part i Table 5.2.2) u Ri = (8.0E9) (DFA,) teen and adult (ODCM Part i Tables 5.2.3 and 5.2.4) { l I i I i E2-1 me e, e

i i Numt:or gggy. - TMI Radiological Contro!s Departmental Procedure 6610-PLN-4200.01 Title Revision No. Offsite Dose Calculation Manual (ODCM) 3 APPENDIX C Ri - Ground Plane Pathway Dose Factor R, = k' k' (SF) (DFG) [(1-e 'i')/AJ (Eq C-1) Where: k' = conversion factor,1E6 pCl/ microcurie k" = conversion factor,8760 hr/yr 4 A, - decay constant for the i* radionuclide, sec t= the exposure time (this calculation assumes that decay is the only operating removal mechanism) 4.73 x 10'sec. (15 yrd Reg. Guide 1.109 (Rev.1), Appendix C 1 DFG,= the ground pir-conversion factor for the i* radionuclide (mrem /hr per pCl/m'). Values are taken from Table E4, Re .ulde 1.109 (Rev.1). These values apply to all ace aroups. SF = 0.7, shielding factor, from Table E-15 Reg. Guide 1.109 (Rev.1) Reference ODCM Part i Table 5.3.1 E3-1 mm

E mtcr^ Nuclear- " " d'd *^' "t' '$ Departmenta' Procedure 6610-PLN-4200.01 Tive - Revision No. i Offsite Dose Calculation Manual (ODCM) 3 i APPENDIX D Ri-Grass Cow-Milk Pathway Dose Factor R, = k' [(0, x U,) / (A, + A,,)] x (F ) x (r) x (DFV x [((f, x f)/Y,) + ((1-f, x f,) e 'Th)/Y,] e'ff (Eq D-1) l Where: k' = conversion factor,1ES picocurie / microcurie (pCl/pci) Q, = cow consumption rate, 50 kg/ day, (Reg. Guide 1.109, Rev.1) goat consumption rate,6 kg/ day, (Reg. Guide 1.109, Rev.1, Table E-2) U,, = Receptor's milk consumption rate; 330,330,400,310 liters /yr for infant, child, teenager, and adult I age groups, respectively (Reg. Guide 1.109, Rev.1) Y, = agricultural productivity by unit area of pasture feed grass,0.7 kg/m' (NUREG-0133) 2 Y, = agricultural productivity by unit area of stored feed,2.0 kg/m (NUREG-0133) F,,, = stable element transfer coefficient (Table E-1, Reg. Guide 1.109, Rev.1) r-fraction of deposited activity retained in cow's feed grass,0.2 for particulates,1.0 for radiolodine (Table E-15 Reg. Guide 1.109, Rev.1) .[ DFlw= the ingestion dose factor for organ, o, and the ith radionuclide for each respective age group, a [ (Tables E-11 to E-14, Reg. Guide 1.109, Rev.1) ? A, = decay constant for the ith radionuclide, sec' i A,, = decay constant for weathering,5.73 x 10'sec' (NUREG-0133); based on a 14 day half life 5 t, = 1,73 x 10 sec, the transport time from pasture to cow to milk to receptor (Table E-15, Reg. Guide 1.109 Rev.1), or 2 days t, = 7.78 x 10'sec, the transport time from pasture to harvest to cow to milk to receptor (Table E-15, Reg. Guide 1.109, Rev.1), or 90 days f, = 1.0, the fraction of the year that the cow is on pasture f, = 1.0, the fraction of the cow feed that is pacture grass while the cow is on pasture ) i l E4-1 me 'I i

r Numtor MUClear i Radidogical Contrds Departmental Procedure 6610-PLN-4200.01 Tetne Revision No. Offsite Dose Calculation Manual (ODCM) 3 j i APPENDIX D (Cont'd) i The concentration of tritium in milk is based on the airborne concentration rather than the deposition. Therefore, R, is based on (X/0): R*,,, = k'k"' F O, U,,DF(,, (.75 [.5/H]) (Eq D-2) Whole: k*" = 1E3 grams /kg H= 8 grams /m', absolute humidity of the atmosphere .75 = fraction of the total feed grass mass that is water .5 = ratio of the specific activity of the feed grass water to the atmospheric water (NUREG-0133) D F(,,, = the ingestion dose factor for tritium and organ, o, for each respective age group, a (Tables E-11 to E-14, Reg. Guide 1.109, Rev.1) All other parameters and values are as given above. NOTE Goat-milk pathway factor, R,, will be computed using the cow-milk pathway factor equation. F,, factor for goat-milk will be from Table E-2 Reg. Guide 1.109 Rev.1.

Reference:

ODCM Part i Tables 5.4.1 to 5.4.4 ? ? E4-2 me 6

y Numta. (UClear Radiological Controls l Departmental Procedure 6610-PLN-4200,01 Trtis Reviston No. Offsite Dose Calculation Manual (ODCM) 3 'I t APPENDIX E f Ri-Cow-Meat Patnway Dose Factor 'i R, = k' [(0, x U,) / (A, + A )] x (F,) x (r) x (DF(,) x [((f, x f,)/Y,) + ((1-f,f,) e 'i'h)/Y,] x e i'f (Eq E-1) d Where: k' = conversion factor,1E6 picoeurie/ microcurie (pCi/pci) -t O, = cow consumption rate,50 kg/ day, (Reg. Guide 1.109, Rev.1) l U, = Receptor's meat consumption rate; 0,41,65,110 kg/yr for infant, child, teenager, and adult age groups, respectively (Reg. Guide 1.109, Rev.1) l F, = the stabte element transfer coefficients, days /kg (Table E-1, Reg. Guide 1.109, Rev,1) r= fraction of deposited activity retained in cow's feed grass,0.2 for particulates,1.0 for radiolodine [ (Table E-15, Reg. Guide 1.109, Rev.1) DF( = the ingestion dose factor for organ, o, and the ith radionuclide for each respective age group, a - j (Tables E-11 to E-14. Reg. Guide 1.109, Rev.1) A, - decay constant for the radionuclide I, sec' [ A, = decay constant for weathering,5.73 x 10 sec' (NUREG-0133), based on a 14 day half life 4 t, = 1.73 x 10'sec, the transport time from pasture to receptor (NUREG-0133) i t, = 7.78 x 10'sec, the transport time from crop to receptor (NUREG-0133) 2 Y, = agricultural productivity by unit area of pasture feed grass,0.7 kg/m (NUREG-0133) 4 2 Y, = agricultural productivity by unit area of stored feed,2.0 kg/m (NUREG-0133) t f, = 1.0, the fraction of the year that the cow is on pasture f, = 1.0, the fraction of the cow feed that is pasture grass while the cow is on pasture The concentration of tritium in meat is based on the airbome concentration rather than the deposition. Therefore, l R,is based on (X/0): i R, = k'k'" F, Q, U, (DFV x 0.75 x (0.5/H]) (Eq E-2) l m Where: All terms are as defined above and in Appendix D.

Reference:

ODCM Part I, Tables 5.6.1 to 5.6.4 i i E5-1 mm e s-

r: q ' Numb @r -gdgy-TMI Radiological Controls Departmental Procedure 6610-PLN-4200.01 - l Title Rewsion No. Offsite Dose Calculation Manual (ODCM) 3 APPENDIX F Ri-Vegetation Pathway Dose Factor R, = k' x [r/ (Y, (A, + A,))] x (DFV x [(U',) f, e'fL + U', f, e'fh] (Eq F-1) Where: 1 f k' = 1E6 picoeurie/ microcurie (pCi/pci) U', = the consumption rate of fresh leafy vegetation,0,26,42,64 kg/yr for infant, child, teenager, or adult age s groups, respectively (Reg. Guide 1.109, Rev.1) U', = the consumption rate of stored vegetation,0,520,630,520 kg/yr for infant, child, teenager, or adult age groups respectively (Reg. Guide 1.109 Rev.1)

f. = the fraction of the annual intake of fresh leafy vegetation grown locally, = 1.0 (NUREG4)133) f, = the fraction of the stored vegetation grown locally = 0.76 (NUREG-0133) t=

the average time between harvest of leafy vegetation and its consumption, 8.6 x 10' seconds i [ Table E-15 Reg. Guide 1.109, Rev.1 (24 hrs)] t, = the average time between harvest of stored leafy vegetation and its consumption,5.18 x 10' seconds _, [ Table E 15, Reg. Guide 1.109 Rev.1 (60 days)] y, = the vegetation area density,2.0 kg/m' (Table E-15, Reg. Gulde 1.109, Rev.1) All other parameters are as previously defined. I The concentration of tritium in vegetation is based on the airborne concentration rather than the deposition. Therefore, R,is based on (X/0) R,., = k'k'" [U', f.

U', f,] (DF(,) (.75 [.5/H])

(Eq F-2) Where: All terms are as defined above and in Appendix D.

Reference:

ODCM Part I, Tables 5.7.1 to 5.7.4 i l ) i l EC 1 m.

r h! umber (UClear Mt Radiological Controls Departmental Procedure 6610-PLN-4200.01 Tme Revision No. Offsite Dose Calculation Manual (ODCM) 3 APPENDIX A-F REFERENCES (Page 1 of 4) Parameters Used in Dose Factor Calculations Origin of Value. Table in Section of Site-Parameter Value R.G.1.109 NUREG4133 Specific m "* For P, * *

DFA Each radionuclide E-9 Note 1 BR 3700 m'/yr (child)

E-5

- - For RI (Vegetation)*"

r Each element type E-1 Y, 2.0 kg/m' E-15 Aw 5.73 E-7 sec' 5.3.1.3 DFL Each age group and radionuclide E-11 thru E-14 Note 1 U,' Each age group E-5 f 1.0 5.3.1.5 i t 8.6 E + 4 seconds E-15 t U,' Each age group E-5 f, 0.76 5.3.1.5 t, 5.18 E + 6 seconds E-15 H 8.0 grams /kg 5.2.1.3

- - For Ri (Inhalation)***

BR Each age group E-5 DFA Each age group and E-7 thru E-10 Note 1 l nuclide E7-1 mu

3 Number ' "adid 9' "' c ""d$ le c'Ji Nuclear Departmental Procedure 6610-PLN-4200.01 w. Remion No. Offsite Dose Calculation Manual (ODCM) 3 APPENDIX A-F REFERENCES (Page 2 of 4) Parameters Used in Dose Factor Calculations I Origin of Value Table in Section of Site-Parameter Value R.G.1.109 NUREG4133 Specific

** For R, (Ground Plane) ***

SF 0.7 E-15

DFG, Each radionuctide E-6 t

4.73 E + 8 sec 5.3.1.2

- - For R1 (Grass / Animal / Meat) ***

O,(Cow) 50 kg/ day E-3 O, (Goat) 6 kg/ day E-3 Ref. Only U, Each age group E-5 Aw 5.73 E-7 sec' 5.3.1.3 F, (Both) Each element E-1 r Each element type E-15

DFL, Each age group and nuclide E-11 thru E-14 Note 1 f,

1.0 5.3.1.3 Note 2 f, 1.0 5.3.1.3 Note 2 Y, 0.7 kg/m' E-15 t,, 7.78 E + 6 sec E-15 Y, 2.0 kg/m' E-15 t, 1.73 E + 6 sec E-15 H 8 0 grams /kg 5.2.1.3 E7-2 mm

Numbr [r g'J J Nualear " " d' ' 9'oa' c "" '$ Departmental Procedure 6610-PLN-4200.01 Tnie Revision No. Offsite Dose Calculation Manual (ODCM) 3 APPENDIX A-F REFERENCES (Page 3 of 4) Parameters Uced in Dese Factor Calculations Origin of Value Table in Section of Site-Parameter Value R.G.1.109 NUREG-0133 Specific

- - For R, (Grass / Cow / Milk) ***

0, 50 kg/ day E-3 U, Each age group E-5 Aw 5.73 E-7 sec' 5.3.1.3 F, Each element E-1 r Each element type E-15

DFL, Each age group and nuclide E 11 thru E-14 Note 1 Y,

0.7 kg/m' E-15 t, 7.78 E + 6 sec E-15 Y, 2.0 kg/m' E-15 t, 1.73 E + 5 sec E-15 f, 1.0 5.3.1.3 f, 1.0 5.3.1.3 H 8.0 grams /kg 5.2.1.3 E7-3 2nu

.=_ Number Nualear " "ad"oa'c^' coat'o'$ Departmental Procedure 6610-PLN-4200.01 1 Title Revision No. I l Offsite Dose Calculation Manual (ODCM) 3 i APPENDIX A-F REFERENCES I i (Page 4 of 4) NOTES [ t inhalation and ingestion dose factors were taken from the indicated source. For each age group, for each. .[ nuclide, the organ dose factor used was the highest dose factor for that nuclide and age group in the referenced table. ( 'I 2. Typically beef cattle are raised all year on pasture. Annualland surveys have indicated that the small j number of goats raised within 5 miles typically are used for grass control and not food or milk.. Nevertheless, the goats can be treated as full meat sources where present, despite the fact that their numbers cannot sustain the meat consumption rates of Table E-5, NUREG-0133. 1 REFERENCES 1. Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix 1," Revision 1, October 1977, l 2. TMI-1 Technical Specifications, attached to Facility Operating License No. DPR-50. i 3. NUREG-0133,

Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants,"

October 1978. i I 6 -i ) l .- l l Y 1 ) E7-4 mm _ ~. _}}

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