Text

Calculation 6610-PLN-4200.01,Rev 24, Offsite Dose Calculation Manual.
	ML061320352
Person / Time
Site:	Three Mile Island
Issue date:	07/01/2003
From:	; AmerGen Energy Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	6610-PLN-4200.01, Rev 24
	Download: ML061320352 (196)
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Number AmerGen TMI - Unit 1 Radiological Controls Procedure 661 0-PLN-4200.DI Title Revision No.

Offsite Dose Calculation Manual (ODCM) __24 Applicability/Scope USAGE LEVEL Effective Date TMI Division 3 07/01/03 This document is within QA plan scope I I Yes No 50.59 Applicable I X I Yes No List of Effective Pages Page Revision Page Revision Page Revision Page Revision 1 24 41 24 81 24 121 24 2 24 42 24 82 24 122 24 3 24 43 24 83 24 123 24 4 24 44 24 84 24 124 24 5 24 45 24 85 24 125 24 6 24 46 24 86 24 126 24 7 24 47 24 87 24 127 24 8 24 48 24 88 24 128 24 9 24 49 24 89 24 129 24 10 24 50 24 90 24 130 24 11 24 51 24 91 24 131 24 12 24 52 24 92 24 132 24 13 24 53 24 93 24 133 24 14 24 54 24 94 24 134 24 15 24 55 24 95 24 135 24 16 24 56 24 96 24 136 24 17 24 57 24 97 24 137 24 18 24 58 24 98 24 138 24 19 24 59 24 99 24 139 24 20 24 60 24 100 24 140 24 21 24 61 24 101 24 141 24 22 24 62 24 102 24 142 24 .

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Number TMI - Unit I I Radiological Controls Procedure 661 O-PLN-4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 24 List of Effective Pages Pale Revision Pace Revision Page Revision Pace Revision 161 24 162 24 163 24 164 24 165 24 166 24 167 24 168 24 169 24 170 24 171 24 172 24 173 24 174 24 175 24 176 24 177 24 178 24 179 24 180 24 181 24 182 24 183 24 184 24 185 24 186 24 187 24 188 24 189 24 190 24 191 24 192 24 193 24 194 24 195 24 196 24 2

Number TMI- Unit 1 Radiological Controls Procedure I 6610-PLN-4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 24 INTRODUCTION The OFFSITE DOSE CALCULATION MANUAL (ODCM) is a supporting document of the Three Mile Island Nuclear Station (TMI) Unit I and Unit 2 PDMS Technical Specifications and implements TMI radiological effluent controls.

The ODCM contains the controls, bases, and surveillance requirements for liquid and gaseous radiological effluents.

In addition, 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 TMI 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 (TMI) 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. 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 I for calculation of off-site doses due to plant effluent releases. Simplifying assumptions have been applied in this manual where applicable to provide a more workable document for implementation of the Radiological Effluent Controls requirements.

TMI implements the TMI Radiological Effluent Controls Program and Regulatory Guide 1.21, Revision 1 (Annual Radioactive Effluent Release Report) requirements by use of a computerized system used to determine TMI effluent releases and to update cumulative effluent doses.

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i I I Number TMI - Unit 1 I Radiological Controls Procedure 661 O-PLN-4200.01 Title Revision No.

Offsite Dose C:alculation Manual (ODCM) 24 TABLE OF CONTENTS PART I TMI-1 RADIOLOGICAL EFFLUENT CONTROLS Section Page 1.0 DEFINITIONS 15 Table 1-1. Frequency Notation 19 2.0 RADIOLOGICAL EFFLUENT CONTROLS AND BASES 21 2.1 Radioactive Effluent Instrumentation 21 2.1.1 Radioactive Liquid Effluent Instrumentation 21 Table 2.1-1, Radioactive Liquid Effluent Instrumentation 22 2.1.2 Radioactive Gaseous Process and Effluent Monitoring Instrumentation 23 Table 2.1-2, Radioactive Gaseous Process and Effluent Monitoring Instrumentation 24 2.2 Radiological Effluent Controls 30 2.2.1 Liquid Effluent Controls . 30 2.2.2 Gaseous Effluent Controls 33 2.2.3 Total Radioactive Effluent Controls 39 3.0 SURVEILLANCES 41 3.1 Radioactive Effluent Instrumentation 41 3.1.1 Radioactive Liquid Effluent Instrumentation 41 Table 3.1-1, Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements . 42 3.1.2 Radioactive Gaseous Process and Effluent Monitoring Instrumentation 44 Table 3.1-2, Radioactive Gaseous Process and Effluent Monitoring Instrumentation 45 Surveillance Requirements 3.2 Radiological Effluents 49 3.2.1 Liquid Effluents 49 Table 3.2-1, Radioactive Liquid Waste Sampling and Analysis Program 50 4

Number tI TMI - Unit I Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 24 TABLE OF CONTENTS (Cont'd)

PART I TMI-1 RADIOLOGICAL EFFLUENT CONTROLS Section Page 3.2.2 Gaseous Effluents 53 Table 3.2-2, Radioactive Gaseous Waste Sampling and Analysis Program 55 3.2.3 Total Radioactive Effluents 59 4.0 PARTI REFERENCES 60 5

Number TMI- Unit I Radiological Controls Procedure 661 0-PLN-4200.Cil Title Revision No.

Offsite Dose Calculation Manual (ODCM) 24 TABLE OF CONTENTS (Cont'd)

PART II T&I-2 RADIOLOGICAL EFFLUENT CONTROLS Section Paoe 1.0 DEFINITIONS 62 Table 1.1, Frequency Notation 64 2.0 CONTROLS AND BASES 65 2.1 Radioactive Effluent Instrumentation 65 2.1.1 Radioactive Liquid Effluent Instrumentation 65 2.1.2 Radioactive Gaseous Process and Effluent Monitoring Instrumentation 65 Table 2.1.2, Radioactive Gaseous Process and Effluent Monitoring Instrumentation 67 2.2 Radioactive Effluent Controls 68 2.2.1. Liquid Effluent Controls 68 2.2.2 Gaseous Effluent Controls 71 2.2.3 Total Radioactive Effluent Controls 76 3.0 SURVEILLANCES 78 3.1 Radioactive Effluent Instrumentation 78 3.1.1 Radioactive Liquid Effluent Instrumentation 78 3.1.2 Radioactive Gaseous Process and Effluents Monitoring Instrumentation 78 Table 3.1-2, Radioactive Gaseous Process and Effluent Monitoring Instrumentation 79 Surveillance Requirements 3.2 Radiological Effluents 80 3.2.1 Liquid Effluents 80 Table 3.2-1, Radioactive Liquid Waste Sampling and Analysis Program 81 3.2.2 Gaseous Effluents 82 Table 3.2-2, Radioactive Gaseous Waste Sampling and Analysis Program 83 3.2.3 Total Radioactive Effluents 86 6

Number I *AtIJI~~f%

TMI - Unit I rCI nfrJIlc 5i Prne-ar5 rn55 nrzin..pI mI.A~flf nl Title Revision No.

Offsite Dose Calculation Manual (ODCM) 24 TABLE OF CONTENTS (Cont'd)

. PART 11 TMI-2 RADIOLOGICAL EFFLUENT CONTROLS Section Page 4.0 1PART 11REFERENCES 87 7

Number TMI - Unit I Radiological Controls Procedure I 6610-PLN-4200.01 Title Revision No.

Offsite Dose calculation Manual (ODCM) _ _24__

TABLE OF CONTENTS (Cont'd)

PART III EFFLUENT DATA AND CALCULATIONAL METHODOLOGIES Section Page 1.0 LIQUID EFFLUENT MONITORS 89 1.1 TMI-1 and TMI-2 Liquid Radiation Monitor Set Points 89 1.2 TMI Liquid Release Points and Liquid Radiation Monitor Data 90 1.3 Control of Liquid Releases 91 2.0 LIQUID EFFLUENT DOSE ASSESSMENT 97 2.1 Liquid Effluents - 10 CFR 50 Appendix I 97 2.2 TMI Liquid Radwaste System Dose Calcs Once per Month 98 2.3 Alternative Dose Calculational Methodology 99 3.0 LIQUID EFFLUENT WASTE TREATMENT SYSTEM 104 3.1 TMI-1 Liquid Effluent Waste Treatment System 104 3.2 Operability of TMI-1 Liquid Effluent Waste Treatment System 105 3.3 TMI-2 Liquid Effluent Waste Treatment System 105 4.0 GASEOUS EFFLUENT MONITORS 108 4.1 TMI-1 Noble Gas Monitor Set Points 108 4.2 7MI-1 Particulate and Radioiodine Monitor Set Points 110 4.3 7MI-2 Gaseous Radiation Monitor Set Points 111 4.4 TMI-1 Gaseous Effluent Release Points and Gaseous Radiation Monitor Data 112 4.5 TMI-2 Gaseous Effluent Release Points and Gaseous Radiation Monitor Data 114 4.6 Control of Gaseous Effluent Releases 115 8

Number TMI - Unit I Radiological Controls Procedure 661 O-PLN-4200.01 Title . Revision No.

Offsite Dose Calculation Manual (ODCM) 24 TABLE OF CONTENTS (Cont'd)

PART III EFFLUENT DATA AND CALCULATIONAL METHODOLOGIES Section Page 5.0 GASEOUS EFFLUENT DOSE ASSESSMENT 127 5.1 Gaseous Effluents - Instantaneous Release Limits 127 5.1.1 Noble Gases 127 5.1.1.1 Total Body 127 5.1.1.2 Skin 128 5.1.2 Iodines and Particulates 129 5.2 Gaseous Effluents - 10 CFR 50 Appendix I 130 5.2.1 Noble Gases 130 5.2.2 lodines and Particulates 131 5.3 Gaseous Radioactive System Dose Calculations Once per Month 133 5.4 Alternative Dose Calculational Methodologies 134 6.0 GASEOUS EFFLUENT WASTE TREATMENT SYSTEM 156 6.1 Description of the TMI-1 Gaseous Radwaste Treatment System 156 6.2 Operability of the TMI-1 Gaseous Radwaste Treatment System 156 7.0 EFFLUENT TOTAL DOSE ASSESSMENT 158 8.0 TMINS RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) 159 8.1 Monitoring Program Requirements 159 8.2 Land Use Census 161 8.3 Interlaboratory Comparison Program 163 9.0 PART IlIl REFERENCES 179 9

Number TMI - Unit 1 I Radiological Controls Procedure 661 0-PLN-4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 24 TABLE OF CONTENTS (Cont'd)

PART III EFFLUENT DATA AND CALCULATIONAL METHODOLOGIES Section Page TABLES Table 1.1 TMI-1 Liquid Release Point and Liquid Radiation Monitor Data 93 Table 1.2 TMI-2 Sump Capacities 94 Table 2.1 Liquid Dose Conversion Factors (DCF): DFj 100 Table 2.2 Bioaccumulation Factors, BFj 103 Table 4.1 TMI-1 Gaseous Release Point & Gaseous Radiation Monitor Data 116 Table 4.2 TMI-2 Gaseous Release Point & Gaseous Radiation Monitor Data 117 Table 4.3 Dose Factors for Noble Gases and Daughters 118 Table 4.4 Atmospheric Dispersion Factors for Three Mile Island - Station Vent 119 Table 4.5 Atmospheric Dispersion Factors for Three Mile Island - Ground Release 120 Table 4.6 Dose Parameters for Radioiodines and Radioactive Particulate In Gaseous Effluents 121 Table 5.2.1 Pathway Dose Factors, R - Infant, Inhalation 135 Table 5.2.2 Pathway Dose Factors, RI - Child, Inhalation 136 Table 5.2.3 Pathway Dose Factors, RI - Teen, Inhalation 137 Table 5.2.4 Pathway Dose Factors, R1 -Adult, Inhalation 138 Table 5.3.1 Pathway Dose Factors, R1 - All Age Groups, Ground Plane 139 Table 5.4.1 Pathway Dose Factors, RI - Infant, Grass-Cow-Milk 140 Table 5.4.2 Pathway Dose Factors, RI - Child, Grass-Cow-Milk 141 Table 5.4.3 Pathway Dose Factors, R1 - Teen, Grass-Cow-Milk 142 Table 5.4.4 Pathway Dose Factors, R1 - Adult, Grass-Cow-Milk 143 Table 5.5.1 Pathway Dose Factors, R1 - Infant, Grass-Goat-Milk 144 10

Number TMI- Unit 1 Radiological Controls Procedure 661 O-PLN-4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 24 TABLE OF CONTENTS (Cont'd)

PART III EFFLUENT DATA AND CALCULATIONAL METHODOLOGIES Section Page TABLES Table 5.5.2 Pathway Dose Factors, R,- Child, Grass-Goat-Milk 145 Table 5.5.3 Pathway Dose Factors, R,- Teen, Grass-Goat-Milk 146 Table 5.5.4 Pathway Dose Factors, R1 - Adult, Grass-Goat-Milk 147 Table 5.6.1 Pathway Dose Factors, RI - Infant, Grass-Cow-Meat 148 Table 5.6.2 Pathway Dose Factors, RI - Child, Grass-Cow-Meat 149 Table 5.6.3 Pathway Dose Factors, R1 - Teen, Grass-Cow-Meat 150 Table 5.6.4 Pathway Dose Factors, R,- Adult, Grass-Cow-Meat 151 Table 5.7.1 Pathway Dose Factors, RI - Infant, Vegetation 152 Table 5.7.2 Pathway Dose Factors, RI - Child, Vegetation 153 Table 5.7.3 Pathway Dose Factors, RI - Teen, Vegetation 154 Table 5.7.4 Pathway Dose Factors, R1 - Adult, Vegetation 155 Table 8.1 Sample Collection and Analysis Requirements 164 Table 8.2 Reporting Levels for Radioactivity Concentrations in Environmental Samples 168 Table 8.3 Detection Capabilities for Environmental Sample Analysis 169 Table 8.4 TMINS REMP Station Locations - Air Particulate and Air Iodine 171 Table 8.5 TMINS REMP Station Locations - Direct Radiation (TLD) 171 Table 8.6 TMINS REMP Station Locations - Surface Water 173 Table 8.7 TMINS REMP Station Locations - Aquatic Sediment 173.

Table 8.8 TMINS REMP Station Locations - Milk 174 Table 8.9 TMINS REMP Station Locations - Fish 174 Table 8.10 TMINS REMP Station Locations - Food Products 175 11

Number TMI- Unit 1 Radiological Controls Procedure 661 O-PLN-4200.01 Title JRevision No.

Offsite Dose Calculation Manual (ODCM) 24 TABLE OF CONTENTS (Cont'd)

PART IlIl EFFLUENT DATA AND CALCULATIONAL METHODOLOGIES Section Pagte TABLES MAP 8.1 Three Mile Island Nuclear Station Locations of Radiological Environmental 176 Monitoring Program Stations within I Mile of the Site MAP 8.2 Three Mile Island Nuclear Station Locations of Radiological Environmental 177 Monitoring Program Stations within 5 miles of the Site MAP 8.3 Three Mile Island Nuclear Station Locations of Radiological Environmental 178 Monitoring Program Stations Greater than 5 miles from the Site FIGURES Figure 1.1 TMI-1 Liquid Effluent Pathways 95 Figure 1.2 TMIA-2 Liquid Effluent Pathways 96 Figure 3.1 TrIll-1 Liquid Radwaste 106 Figure 3.2 TMIA-1 Liquid Waste Evaporators 107 Figure 4.1 TMI-1 Gaseous Effluent Pathways 122 Figure 4.2 TMI-1 Auxiliary & Fuel Handling Buildings Effluent Pathways 123 Figure 4.3 TMIVI-1 Reactor Building Effluent Pathway 124 Figure 4.4 TMIV1-1 Condenser Offgas Effluent Pathway 125 Figure 4.5 TM11-2 Gaseous Effluent Filtration System/Pathways 126 Figure 6.1 Waste Gas System 157 12

Number rlidu:Iu -- TMI - Unit I i~u lIuy~I~,rur ~ u CC u-F L A0n n4 I r-aU1o[Ugicd a~fLUb MULA:rol o Urceuru-rT-rvtuu.W I V'r Title Revision No.

Offsite Dose Calculation Manual (ODCM) 24 TABLE OF CONTENTS (Cont'd)

PART IV REPORTING REQUIREMENTS Section Page 1.0 TMI ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 182 2.0 TMI ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 183 3.0 PART IV REFERENCES 185 APPENDICES A. Pathway Dose Rate Parameter (Pi) 186 B. Inhalation Pathway Dose Factor (RI) 187 C. Ground Plane Pathway Dose Factor (Ri) 188 D. Grass-Cow-Milk Pathway Dose Factor (Re) 189 E. Cow-Meat Pathway Dose Factor (RI) 191 F. Vegetation Pathway Dose Factor (R1) 192 APPENDIX A - F REFERENCES 193 13

Number TMI - Unit I Radiological Controls Procedure 661 0-PLN-4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 24 PART I TMI-1 RADIOLOGICAL EFFLUENT CONTROLS 14

Number TM] - Unit I Radiological Controls Procedure I 661 0-PLN-4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 24 1.0 DEFINITIONS The following terms are defined for uniform interpretation of these controls and surveillances.

1.1 Reactor Operating Conditions 1.1.1 Cold Shutdown The reactor is in the cold shutdown condition when it is subcritical by at least one percent delta k/k and Tavg is no more than 200 0F. Pressure is defined by Technical Specification 3.1.2.

1.1.2 Hot Shutdown The reactor is in the hot shutdown condition when it is subcritical by at least one percent delta k/k and Tavg is at or greater than 5250F.

1.1.3 Reactor Critical The reactor is critical when the neutron chain reaction is self-sustaining and Keff = 1.0.

1.1.4 Hot Standby The reactor is in the hot standby condition when all of the following conditions exist:

a. Tavg is greater than 5250 F

b. The reactor is critical

c. Indicated neutron power on the power range channels is less than two percent of rated power. Rated power is defined in Technical Specification Definition 1.1.

1.1.5 Power Operation The reactor is in a power operating condition when the indicated neutron power is above two percent of rated power as indicated on the power range channels. Rated power is defined in Technical Specification Definition 1.1.

1.1.6 Refueling Shutdown The reactor is in the refueling shutdown condition when, even with all rods removed, the reactor would be subcritical by at least one percent delta k/k and the coolant temperature at the decay heat removal pump suction is no more than 140'F. Pressure is defined by Technical Specification 3.1.2. A refueling shutdown refers to a shutdown to replace or rearrange all or a portion of the fuel assemblies and/or control rods.

1.1.7 Refueling Operation An operation involving a change in core geometry by manipulation of fuel or control rods when the reactor vessel head is removed.

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A Number TMI -Unit I I Radiological Controls Procedure 661 O-PLN-4200.01 Title Revision No.

Offsite Dose C:alculation Manual (ODCM) 24 1.1.8 Refueling Interval Time between normal refuelings of the reactor. This is defined as once per 24 months.

1.1.9 Startup The reactor shall be considered in the startup mode when the shutdown margin is reduced with the intent of going critical.

1.1.10 Tave Tave is defined as the arithmetic average of the coolant temperatures in the hot and cold legs of the loop with the greater number of reactor coolant pumps operating, if such a distinction of loops can be made.

1.1.11 Heatup - Cooldown Mode The heatup-cooldown mode is the range of reactor coolant temperature greater than 200OF and less than 525 0F.

1.2 Operable A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function(s) and when all necessary attendant instrumentation, controls, electrical power, 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).

1.3 Instrument Channel An instrument channel is the combination of sensor, wires, amplifiers, and output devices which are connected for the purpose of measuring the value of a process variable for the purpose of observation, control, and/or protection. An instrument channel may be either analog or digital.

1.4 Instrumentation Surveillance 1.4.1 Channel Test A CHANNEL TEST shall be the injection of a simulated signal into the channel as close to the sensor as practical to verify OPERABILITY, including alarm and/or trip functions.

1.4.2 Channel Check A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation. This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrumentation channels measuring the same parameter.

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Number .

TMI - Unit I Radiological Controls Procedure 661 0-PLN-4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 24 1.4.3 Source Check A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.

1.4.4 Channel Calibration An instrument CHANNEL CALIBRATION is a test, and adjustment (if necessary), to establish that the channel output responds with acceptable range and accuracy to known values of the parameter which the channel measures or an accurate simulation of these values. Calibration shall encompass the entire channel, including equipment actuation, alarm, or trip and shall be deemed to include the channel test.

1.5 Dose Equivalent 1-131 The DOSE EQUIVALENT 1-131 shall be that concentration of 1-131 (microcurie/gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of 1-131, 1-132, 1-133, 1-134, and 1-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table Ill of TID 14844, "Calculation of Distance Factors for Power and Test Reactor Sites". [Or in Table E-7 of NRC Regulatory Guide 1.109, Revision 1, October 1977.]

1.6 Offsite Dose Calculation Manual (ODCM)

The OFFSITE DOSE CALCULATION MANUAL (ODCM) contains the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluent, in the calculation of gaseous and liquid effluent monitoring Alarm/Trip Setpoints, and in the conduct of the Radiological Environmental Monitoring Program. The ODCM also contains (1) the Radiological Effluent Controls, (2) the Radiological Environmental Monitoring Program and (3) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Annual Radioactive Effluent Release Reports.

1.7 Gaseous Radwaste Treatment The GASEOUS RADWASTE TREATMENT SYSTEM is the system designed and installed to reduce radioactive gaseous effluent by collecting primary coolant system off gases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.

1.8 Ventilation Exhaust Treatment System A VENTILATION EXHAUST TREATMENT SYSTEM is any system designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in effluent by passing ventilation or vent exhaust gases through charcoal absorbers and/or HEPA filters for the purpose of removing iodine or particulates from the gaseous exhaust system prior to the release to the environment.

Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEMS.

1.9 Purge - Purging PURGE or PURGING is the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating conditions in such a manner that replacement air or gas is required to purify the confinement.

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t Number TMI - Unit 1 Radiologaical Controls Procedure 661 0-PLN-4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 24 1.10 Venting VElNTING is the controlled process of discharging air as gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating conditions in such a manner that replacement air or gas is not provided. Vent used in system name does not imply a VENTING process.

1.11 Member(s) of the Public MEMBER OF THE PUBLIC means any individual except when that individual is receiving an occupational dose.

1.12 Site Boundary The SITE BOUNDARY used as the basis for the limits on the release of gaseous effluents is as defined in Section 2.1.2.2 and shown on Figure 2.1-3 of the TMI-1 FSAR. This boundary line includes portions of the Susquehanna River surface between the east bank of the river and Th -ee Mile Island and between Three Mile Island and Shelley Island.

The SITE BOUNDARY used as the basis for the limits on the release of liquid effluents is as shown in Figure 1.1 in Part I of this ODCM.

1.13 F'equency Notation The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1-1. All Surveillance Requirements shall be performed within the specified time interval with a maximum allowable extension not to exceed 25% of the surveillance interval. The 25% extension applies to all frequency intervals with the exception cf "F."

No extension is allowed for intervals designated "F."

1.14 Occupational Dose CCCUPATIONAL DOSE means the dose received by an individual in the course of employment in which the individual's assigned duties involve exposure to radiation or to radioactive material from licensed and unlicensed sources of radiation, whether in the possession of the licensee or other person. Occupational dose does not include doses received from background radiation, from any medical administration the individual has received, from exposure to individuals administered radioactive material and released under 10CFR35.75, from voluntary participation in medical research programs, or as a member of the public.

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Number TMI - Unit 1 Radiological Controls Procedure 661 O-PLN-4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) - 24 Table 1-1 Frequency Notation Notation Frequency S Shiftly (once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months )

D Daily (once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months )

W Weekly (once per 7 days)

M Monthly (once per 31 days)

Q Quarterly (once per 92 days)

S/A Semi-Annually (once per 184 days)

R Refueling Interval (once per 24 months)

P S/U Prior to each reactor startup, if not done during the previous 7 days P Completed prior to each release N/A (NA) Not applicable E Once per 18 months F Not to exceed 24 months Bases Section 1.13 establishes the limit for which the specified time interval for Surveillance Requirements may be extended. It permits an allowable extension of the normal surveillance interval to facilitate surveillance scheduling and consideration of plant operating conditions that may not be suitable for conducting the surveillance; e.g.,

transient conditions or other ongoing surveillance or maintenance activities. It also provides flexibility to accommodate the length of a fuel cycle for surveillances that are specified to be performed at least once each REFUELING INTERVAL. It is not intended that this provision be used repeatedly as a convenience to extend surveillance intervals beyond that specified for surveillances that are not performed once each REFUELING INTERVAL. Likewise, it is not the intent that REFUELING INTERVAL surveillances be performed during power operation unless it is consistent with safe plant operation. The limitation of Section 1.13 is based on engineering judgement and the recognition that the most probable result of any particular surveillance being performed is the verification of conformance with the Surveillance Requirements. This provision is sufficient to ensure that the reliability ensured through surveillance activities is not significantly degraded beyond that obtained from the specified surveillance interval.

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6610-PLN-4200.01 Revision 24 FIGURE 1.1 Gaseous Effluent Release Points and Liquid Effluent Outfall Locations A

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Number TM[ - Unit 1 Radiological Controls Procedure 661 O-PLN4200.O1 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 24 2.0 RADIOLOGICAL EFFLUENT CONTROLS AND BASES 2.1 Radioactive Effluent Instrumentation 2.1.1 Radioactive Liquid Effluent Instrumentation CONTROL:

The radioactive liquid effluent monitoring instrumentation channels shown in Table 2.1-1 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of Control 2.2.1.1 are not exceeded. The alarmltrip setpoints of these channels shall be determined in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM).

APPLICABILITY: At all times

ACTION:

a. With a radioactive liquid effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above control, immediately suspend the release of radioactive liquid effluent monitored by the affected channel or declare the channel inoperable.

b.With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 2.1-1. Exert best efforts to return the instrumentation to OPERABLE status within 30 days and, if unsuccessful, explain in the next Annual Effluent Release Report why the inoperability was not corrected in a timely manner.

For FT-84, and RM-L6, operability is not required when discharges are positively controlled through the closure of WDL-V257.

For RM-L12 and associated IWTS/1WFS flow interlocks, operability is not required when discharges are positively controlled through the closure of IW-V72, 75 and IW-V280, 281.

For FT-146, operability is not required when discharges are positively controlled through the closure of WDL-V257, IW-V72, 75 and IW-V280, 281.

BASES The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluent during actual or potential releases. The alarm/trip setpoints for these instruments shall be calculated in accordance with NRC approved methods in the ODCM to ensure that the alarm/trip will occur prior to exceeding ten times the effluent concentrations of 10 CFR Part 20.

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Number TMI- Unit I I Radiological Controls Procedure 661 O-PLN-4200.131 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 24 Table 2.1-1 Radioactive Liquid Effluent Instrumentation Minimum Channels Instrument Operable ACTION

1. Gross Radioactivity Monitors Providing Automatic Termination ol Release

a. Unit I Liquid Radwaste Effluent 1 18 Line (RM-L6)

b. IWTS/IWFS Discharge Line (RM-L12) 1 20

2. Flow Rate Measurement Devices

a. Unit I Liquid Radwaste Effluent I 21 Line (FT-84)

b. Station Effluent Discharge I 21 (FT-146)

Table Notation ACTION 18 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE rnquirement, effluent releases may continue, provided that prior to initiating a release:

1. At least two independent samples are analyzed in accordance with Surveillances 3.2.1.1.1 and 3.2.1.1.2 and;

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

C. The TMI Plant Manager shall approve each release.

Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 20 With the number of channels OPERABLE less than required by the Minimum Channels OPEFRABLE requirement, effluent releases via this pathway may commence or continue provided that grab samples are collected and analyzed for gross radioactivity (beta or gamma) at a limit of detection of at least 1x10 7 microcuries/ml, prior to initiating a release and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during release.

ACTION 21 W~ith the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, radioactive effluent releases via this pathway may continue, provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual releases. Pump curves may be used to estimate ilow.

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Number TMI - Unit 1 Radiological Controls Procedure I 661 0-PLN-4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 24 2.1.2 Radioactive Gaseous Process and Effluent Monitoring Instrumentation CONTROL:

The radioactive gaseous process and effluent monitoring instrumentation channels shown in Table 2.1-2 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of Control 2.2.2.1 are not exceeded. The alarm/trip setpoints of these channels shall be determined in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM).

APPLICABILITY: As shown in Table 2.1-2.

ACTION:

a. With a radioactive gaseous process or effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above control, immediately suspend the release of radioactive effluent monitored by the affected channel or declare the channel inoperable.

b. With less than the minimum number of radioactive gaseous process or effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 2.1-2. Exert best efforts to return the instrumentation to OPERABLE status within 30 days and, if unsuccessful, explain in the next Annual Effluent Release Report why the inoperability was not corrected in a timely manner.

BASES The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluent during actual or potential releases. The alarm/trip setpoints for these instruments shall be calculated in accordance with NRC approved methods in the ODCM to provide reasonable assurance that the annual releases are within the limits specified in 10 CFR 20.1301.

The low range condenser offgas noble gas activity monitors also provide data for determination of steam generator primary to secondary leakage rate. Channel operability requirements are based on an ASLB Order No. LBP-84-47 dated October 31, 1984, and as cited in 20 NRC 1405 (1984).

23

661 0-PLN-4200.01 Revision 24 Table 2.1-2 Radioactive Gaseous Process and Effluent Monitoring Instrumentation MINIMUM CHANNELS INSTRUMEN' T OPERABLE APPLICABILI1TY ACTION

1. Waste Gas Holdup System

a. Noble Gas Activity Monitor (RM-A7) 1 25

b. Effluent System Flow Rate Measuring Device (FT-123) 1 26

2. Waste Gas Holdup System Explosive Gas Monitoring System

a. Hydrogen Monitor 2 **

30

b. Oxygen Monitor 2 **

30

3. Containment Purge Monitoring System

a. Noble Gas Activity Monitor (RM-A9) 1 27

b. Iodine Sampler (RM-A9) 1 #t 31

c. Particulate Sampler (RM-A9) 1 31

d. Effluent System Flow Rate Measuring Device 1 #t 26 (FR-148A, FR-148B) 1 26

e. Sampler Flow Rate Monitor 24

661 0-PLN-4200.01 Revision 24 Table 2.1-2 (Cont'd)

Radioactive Gaseous Process and Effluent Monitoring Instrumentation MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION

4. Condenser Vent System

a. Low Range Noble Gas Activity Monitor (RM-A5Lo and 2(') 32 Suitable Equivalent)

NOTE (1): For one of the channels, an operable channel may be defined for purposes of this control and 3.1.2.1 only as a suitable equivalent monitoring system capable of being placed in service within one hour. A suitable equivalent system shall include instrumentation with comparable sensitivity and response time to the RM-A5Lo monitoring channel. When the equivalent monitoring system is in service, indication will be continuously available to the operator, either through indication and alarm in the Control Room or through communication with a designated individual continuously observing local indication.

25

661 0-PLN-4200.01 Revision 24 Table 2.1-2 (Cont'd)

Radioactive Gaseous Process and Effluent Monitoring Instrumentation

- MINIMUM CHANINELS INSTRUMENT OPERABLE APPLICABILI- TY ACTION

5. Auxiliary and Fuel Handling Building Ventilation System

'a. Noble Gas Activity Monitor (RM-A8) or (RM-A4 and RM-A6) I

27

b. Iodine Samples (RM-A8) or (RM-A4 and RM-A6) I 31

c. Particulate Sampler (RM-A8) or (RM-A4 and RM-A6) I 31

d. Effluent System Flow Rate Measuring Devices (FR-149 1 26 and FR-150)

e. Sampler Flow Rate Monitor 1

26

6. Fuel Handling Building ESF Air Treatment System

a. Noble Gas Activity Monitor (RM-A14 or Suitable Equivalent) 1 27, 33

b. Iodine Cartridge N/A(2) 31, 33 NIA(2)

c. Particulate Filter 31, 33

d. Effluent System Flow (UR-1 104A/B) 26, 33 1

e. Sampler Flow Rate Monitor 26, 33 NOTE 2: No instrumentation channel is provided. However, for determining operability, the equipment named must be installed and functional or the ACTION applies.

26

661 0-PLN-4200.01 Revision 24 Table 2.1-2 (Cont'd)

Radioactive Gaseous Process and Effluent Monitoring Instrumentation MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABIL1l ry ACTION

7. Chemical Cleaning Building Ventilation System j(3) 27

a. Noble Gas Activity Monitor (ALC RM-l-1 8)

.1(3)

b. Iodine Sampler (ALC RM-1-1 8) ##W 31

c. Particulate Sampler (ALC RM-1-18) I 31

8. Waste Handling and Packaging Facility Ventilation System

a. Particulate Sampler (WHP-RIT-1) 1 31

9. Respirator and Laundry Maintenance Facility Ventilation System

a. Particulate Sampler (RLM-RM-1) 1 31 NOTE 3: Channel only required when liquid radwaste is moved or processed within the facility.

27

Number TMI- Unit 1 Radiological Controls Procedure 661 0-PLN-4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 24 Table 2.1-2 Table Notation A* At all times.

- - During waste gas holdup system operation.

Operability is not required when discharges are positively controlled through the closure of WDG-V47 and where RM-A8 (or RM-A4 and RM-A6), FT-1 49, and FT-1 50 are operable.

During Fuel Handling Building ESF Air Treatment System Operation.

At all times during containment purging.

At all times when condenser vacuum is established.

During operation of the ventilation system.

ACTION 25 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the tank may be released to the environment provided that prior to initiating the release:

1. At least two independent samples of the tank's contents are analyzed in accordance with Table 3.2-2, Item A, and

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

3. The TMI Plant Manager shall approve each release.

Otherwise, suspend release of radioactive effluent via this pathway.

ACTION 26 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

ACTION 27 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are taken at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and the initial samples are analyzed for gross activity (gamma scan) within.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after the channel has been declared inoperable. If RM-A9 is declared inoperable, see also Technical Specification 3.5.1, Table 3-5.1, Item C.3.f.

ACTION 30 1. With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, a grab sample shall be collected and analyzed for the inoperable gas channel(s) at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . With both channels inoperable, a grab sample shall be collected and analyzed for the inoperable gas channel(s):

(a) at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during degassing operations.

(b) at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months during other operations (e.g. Feed and Bleed).

28

Number TMI - Unit I Radiological Controls Procedure 661 O-PLN-4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 24 Table 2.1-2

2. If the inoperable gas channel(s) is not restored to service within 14 days, a special report shall be submitted to the Regional Administrator of the NRC Region I Office and a copy to the Director, Office of Inspection and Enforcement within 30 days of declaring the channel(s) inoperable. The report shall describe (a) the cause of the monitor inoperability, (b) action being taken to restore the instrument to service, and (c) action to be taken to prevent recurrence.

ACTION 31 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that within four hours after the channel has been declared inoperable, samples are continuously collected with auxiliary sampling equipment.

ACTION 32 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 28 days, provided that one OPERABLE channel remains in service or is placed in service within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . After 28 days, or if one OPERABLE channel does not remain in service or is not placed in service within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , the provisions of Technical Specification 3.0.1 apply, as if this Control were a Tech Spec Limiting Condition for Operation.

ACTION 33 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, either restore the inoperable channel to OPERABLE status within 7 days, or prepare and submit a special report within 30 days outlining the action(s) taken, the cause of the inoperability, and plans and schedule for restoring the system to OPERABLE status.

29

K Number TMI - Unit 1 Radiological Controls Procedure 661 0-PLN-4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 24 2.2 Radioactive Effluent Controls 2 2.1 Liquid Effluent Controls 2.2.1.1 Liquid Effluent Concentration CONTROL:

The concentration of radioactive material released at anytime from the unit to unrestricted areas shall be limited to ten times the concentrations specified in 10 CFR Part 20.1001-20.2401, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 3 x 10-3 uCi/cc total activity.

APPLICABILITY: At all times ACTION:

With the concentration of radioactive material released from the unit to unrestricted areas exceeding the above limits, immediately restore concentrations within the above limits.

BASES This control is provided to ensure that the concentration of radioactive materials released in liquid waste effluent from the unit to unrestricted areas will be less than ten times the concentration levels specified in 10 CFR Part 20.1001-20.2401, Appendix B, Table 2. This limitation provides additional assurance that the levels of radioactive materials in bodies of water outside the site will not result in exposures with (1) the Section II.A design objectives of Appendix 1,10 CFR Part 50, to a MEMBER OF THE PUBLIC and (2, the limits of 10 CFR Part 20.1301 to the population. The concentration limit for noble gases is based upon the assumption the Xe-1 35 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2.

2.2.1.2 Liquid Effluent Dose CONTROL The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released from the unit to the SI-YE BOUNDARY shall be limited:

a. During any calendar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 mrem to any crgan.

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

30

Number TMI - Unit I a_ ._. _ . _ ._ en__ __ I eo rs. ha

.. n ran I Radiological Controls Procedure b00 U-rLrJ-'4&ZUU.U1 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 24 APPLICABILITY: At all times ACTION:

a. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the NRC Region I Administrator within 30 days, a Special Report which identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduce the releases of radioactive materials in liquid effluents during the remainder of the current calendar quarter and during the subsequent 3 calendar quarters so that the cumulative dose or dose commitment to any individual from such releases during these four calendar quarters is within 3 mrem to the total body and 10 mrem to any organ. This Special Report shall also include (1) the result of radiological analyses of the drinking water source, and (2) the radiological impact on finished drinking water supplies with regard to the requirements of 40 CFR 141, Safe Drinking Water Act.

BASES This control and associated action is provided to implement the requirements of Sections Il.A, III.A, and IV.A of Appendix 1,10 CFR Part 50. The Control implements the guides set forth in Section I.A of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents will be kept "as low as is reasonably achievable". Also, for fresh water sites with drinking water supplies which can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 10 CFR 20. The dose calculations in the ODCM implement The requirements in Section III.A. of Appendix I that conformance with the guides of Appendix I is to be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October, 1977, and Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April, 1977.

NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.113.

31

Number TMI- Unit 1 Radiologjical Controls Procedure 661 O-PLN-4200.01 Title Revision No.

Of fsite Dose Calculation Manual (ODCM) 24 2.2.1.3 Liquid Radwaste Treatment System CONTROL:

The 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 projected doses due to the liquid effluent from the unit to unrestricted areas would exceed 0.06 mrem to the total body or 0.2 mrem to any organ in any calendar month.

APPLICABILITY: At all times ACTION:

a. With radioactive liquid waste being discharged without treatment and in excess of the above limits, prepare and submit to thD NRC Region I Administrator within 30 days, a Special Report which includes the following information:

1. Explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reason for inoperability,

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

3. A summary description of action(s) taken to prevent a recurrence.

BASES The requirement that the appropriate portions of this system be used, when specified, provides assurance that the releases of radioactive materials in liquid effluents will be kept as low as is reasonably achievable. This control implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objective given in Section Il.D of Appendix I to 10 CFR Part 50. The intent of Section Il.D. is to reduce effluents to as low as is reasonably achievable in a cost effective manner. This control satisfies this intent by establishing a dose limit which is a small fraction (25%) of Section I.A of Appendix I, 10 CFR Part 50 dose requirements. This margin, a factor of 4, constitutes a reasonable reduction.

32

Number TMI - Unit I I Radiological Controls Procedure 661 0-PLN-4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 24 2.2.1.4 Liquid Holdup Tanks CONTROL The quantity of radioactive material contained in each of the following tanks shall be limited to less than or equal to 10 curies, excluding tritium and dissolved or entrained noble gases.

a. Outside temporary tank APPLICABILITY: At all times.

ACTION:

a. With the quantity of radioactive material in any of the above listed tanks exceeding the above limit, immediately suspend all additions of radioactive material to the tank and within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months reduce the tank contents to within the limit.

BASES Restricting the quantity of radioactive material contained in the specified tanks provides assurance that in the event of an uncontrolled release of the tanks' contents, the resulting concentrations would be less than the limits of 10 CFR Part 20.1001-20-20.2401, Appendix B, Table 2, Column 2, at the nearest potable water supply and the nearest surface water supply in an unrestricted area.

2.2.2 Gaseous Effluent Controls 2.2.2.1 Gaseous Effluent Dose Rate CONTROL:

The dose rate due to radioactive materials released in gaseous effluent from the site shall be limited to the following:

a. For noble gases: less than or equal to 500 mrem/yr to the total body and less than or equal to 3000 mrem/yr to the skin, and

b. For 1-131, 1-133, tritium and all radionuclides in particulate form with half lives greater than 8 days: less than or equal to 1500 mrem/yr to any organ.

APPLICABILITY: At all times.

ACTION:

With the release rate(s) exceeding the above limits, immediately decrease the release rate to comply with the above limit(s).

33

Number TMI - Unit I Radiological Controls Procedure 1 661 0-PLN-4200.01 Title D Revision No.

Offsite Dose Calculation Manual (ODCM) 24 BASES The control implements the requirement in Technical Specification (6.8.4.b(7).

This specification is provided to ensure that the dose from radioactive materials in gaseous effluents at and beyond the SITE BOUNDARY will be within the annual dose limits of 10 CFR Part 20. The annual dose limits are the doses associated with 10 times the concentrations of 10 CFR Part 20, Appendix B, Table 2, Column 1. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result i 1 the exposure of a MEMBER OF THE PUBLIC, either within or outside the SITE BOUNDARY, to annual average concentrations exceeding the limits specified in Appendix B, Table 2 of 10 CFR Part 20.1302. For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy of the MEMBER OF THE PUBLIC will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the exclusion area boundary. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to a MEMBER OF THE PUBLIC at or beyond the SITE BOUNDARY to less than or equal to 500 mrem/year to the total body or to less than or equal to 3000 mrem/year to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to a child via the inhalation pathway to less than or equal to 1500 mrem/year (NUREG 1301).

2.2.2.2 Gaseous Effluents Dose-Noble Gases CONTROL:

The air dose due to noble gases released in gaseous effluents from the unit to areas at and beyond the SITE BOUNDARY shall be limited to the following:

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

b. During any calendar year: less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.

APPLICABILITY: At all times.

ACTION:

a. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the NRC Region I Administrator within 30 days, a Special Report which identifies the cause(s) for exceeding the limit(s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance.

with the above limits.

34

Number TMI - Unit I I Radiological Controls Procedure 661 0-PLN-4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 24 BASES This control applies to the release of radioactive materials in gaseous effluents from TMI-1.

This control and associated action is provided to implement the requirements of Section Il.B, III.A and IV.A of Appendix I, 10 CFR Part 50. The Control implements the guides set forth in Section Il.B of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents will be kept "as low as is reasonably achievable." The Surveillance Requirements implement the requirements in Section II.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through the appropriate pathways is unlikely to be substantially underestimated. The dose calculation methodology and parameters established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Release of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.1 11, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors," Revision 1, July 1977. The ODCM equations provided for determining the air doses at and beyond the SITE BOUNDARY are based upon the historical average atmospheric conditions. NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.111.

2.2.2.3 Dose - lodine-1 31, lodine-1 33, Tritium, and Radionuclides In Particulate Form CONTROL:

The dose to a MEMBER OF THE PUBLIC from lodine-131, lodine-133, Tritium, and all radionuclides in particulate form with half lives greater than 8 days, in gaseous effluents released from the unit to areas at and beyond the SITE BOUNDARY shall be limited to the following:

a. During any calendar quarter: less than or equal to 7.5 mrem to any organ, and

b. During any calendar year: less than or equal to 15 mrem to any organ.

APPLICABILITY: At all times.

35

Number TMI - Unit I Radiological Controls Procedure 6610-PLN-4200.Di Title Revision No.

Offsite Dose Calculation Manual (ODCM) 24 ACTION:

With the calculated dose from the release of Iodine-131, Iodine-133, Tritium, and radionuclides in particulate form with half lives greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and submit to the NRC Region I Administrator within 30 days, a Special Report which identifies the cause(s) for exceeding the limit and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

BASES This control applies to the release of radioactive materials in gaseous effluents from TMI-1.

This control and associated action is provided to implement the requirements of Section II.C, III.A and IV.A of Appendix 1,10 CFR Part 50. The Controls are the guides set forth in Section I.C of Appendix I. The ACTION statement provides the required operating flexibility and at the same time implements the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." The ODCM calculational methods specified in the surveillance requirements implement the requirements in Section III.A Of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The ODCM calculational methodology and parameters for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluati ng Compliance with 10 CFR Part 50, Appendix I,"Revision 1, October, 1977 and Regulatory Guide 1.1 11, "Methods for Estimating Atmospheric Transpcrt and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July, 1977. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate controls for iodine-131, iodin-e-133, tritium and radionuclides in particulate form with half lives greater than B days are dependent upon the existing radionuclide pathways to man, in areas at and beyond the SITE BOUNDARY. The pathways that were examined in the development of these calculations were: 1) individual inhalation of airborne radionuclides, 2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man.

36

Number TMI- Unit 1 Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 24 2.2.2.4 Gaseous Radwaste Treatment System CONTROL The GASEOUS RADWASTE TREATMENT SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM shall be OPERABLE. The appropriate portions of the GASEOUS RADWASTE TREATMENT SYSTEM shall be used to reduce radioactive materials in the gaseous waste prior to their discharge when the monthly projected gaseous effluent air doses due to untreated gaseous effluent releases from the unit would exceed 0.2 mrad for gamma radiation and 0.4 mrad for beta radiation. The appropriate portions of the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the monthly projected doses due to gaseous effluent releases from the site would exceed 0.3 mrem to any organ.

APPLICABILITY: At all times.

ACTION:

a. With the GASEOUS RADWASTE TREATMENT SYSTEM and/or the VENTILATION EXHAUST TREATMENT SYSTEM inoperable for more than a month or with gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit to the NRC Region I Administrator within 30 days, a Special Report which includes the following information:

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

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

3. A summary description of action(s) taken to prevent a recurrence.

BASES The use of the GASEOUS RADWASTE TREATMENT SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM ensures that gaseous effluents are treated as appropriate prior to release to the environment. The appropriate portions of this system provide reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." This control implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objectives given in Section I1.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the guide set forth in Sections ll.B and IL.C of Appendix 1,10 CFR Part 50, for gaseous effluents.

37

Number TMI - Unit I Radiological Controls Procedure I 6610-PLN-4200.01 Title D l Revision No.

Offsite Dose tCalculation Manual (ODCM) 24 2.2.2.5 Explosive Gas Mixture CONTROL The concentration of oxygen in the Waste Gas Holdup System shall be limited to less than or equal to 2% by volume whenever the concentration of hydrogen in the Waste Gas Holdup System is greater than or equal to 4% by volume.

AVAILABILITY: At all times.

ACTION:

Whenever the concentration of hydrogen in the Waste Gas Holdup Syslem is greater than or equal to 4% by volume, and:

a. The concentration of oxygen in the Waste Gas Holdup System is greater than 2% by volume, but less than 4% by volume, without delay begin to reduce the oxygen concentration to within its limit.

b. The concentration of oxygen in the Waste Gas Holdup Syslem is greater than or equal to 4% by volume, immediately suspend additions of waste gas to the Waste Gas Holdup System and without delay begin to reduce the oxygen concentration to within its limit.

BASES:

Based on experimental data (Reference 1), lower limits of flammability for hydrogen is 5% and for oxygen is 5% by volume. Therefore, if the concentration of either gas is kept below it lower limit, the other gas may be present in higher amounts without the danger of an explosive mixture.

Maintaining the concentrations of hydrogen and oxygen such that an explosive mixture does not occur in the waste gas holdup system provides assurance that the release of radioactive materials will be controlled in conformance with the requirements of General Design Criterion 60 of Appendix A to 10 CFR 50.

REFERENCES (1) Bulletin 503, Bureau of Mines; Limits of Flammability of Gases and Vapors.

38

Number TMI - Unit I ocedur--

,adiologica .ontrols - .. ._U_.-1 I Radiological Controls Procedure 001 U1-VLN-4ZUCU.U11 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 24 2.2.2.6 Waste Gas Decay Tanks CONTROL:

The quantity of radioactivity contained in each waste gas decay tank shall be limited to less than or equal to 8800 curies noble gases (considered as Xe-133).

APPLICABILITY: At all times.

ACTION:

a. With the quantity of radioactive material in any waste gas decay tank exceeding the above limit, immediately suspend all additions of radioactive material to the tank and within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months reduce the tank contents to within the limit.

BASES Restricting the quantity of radioactivity contained in each waste gas decay tank provides assurance that in the event of an uncontrolled release of the tanks contents, the resulting total body exposure to a MEMBER OF THE PUBLIC at the nearest exclusion area boundary will not exceed 0.5 rem. This is consistent with Standard Review Plan 15.7.1, 'Waste Gas System Failure."

2.2.3 Total Radioactive Effluent Controls 2.2.3.1 Total Dose CONTROL:

The annual (calendar year) dose or dose commitment 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 shall be limited to less than or equal to 75 mrem.

APPLICABILITY: At all times.

ACTION:

With the calculated dose from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Controls 2.2.1.2.a, 2.2.1.2.b, 2.2.2.2.a, 2.2.2.2.b, 2.2.2.3.a, or, 2.2.2.3.b, calculations should be made including direct radiation contributions from the unit and from outside storage tanks to determine whether the above limits of Control 2.2.3.1 have been exceeded. If such is the case, prepare and submit to the NRC Region I Administrator within 30 days, a Special Report which defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits. This Special Report, as defined in 39

a Number TMI- Unit 1 Radiological Controls Procedure 661 0-PLN-4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 24 10 CFR Part 20.2203(b), shall include an analysis which estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release(s) covered by this report. It shall also describe levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations. If the estimated dose(s) exceed the above limits, and if the release condition resulting in violation of 40 CFR 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR 190. Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.

BASES This control is provided to meet the dose limitations of 40 CFR Part 190 that have been incorporated into 10 CFR Part 20.1301(d). This control requ res the preparation and submittal of a Special Report whenever the calculated doses from plant generated radioactive effluents and direct radiation exceed 25 mrem to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrem. For sites containing up to 4 reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR Part 190 if the individual reactors remain within twice the dose design objectives of Appendix I, and if direct radiation doses from the reactor units and outside storage tanks are kept small. The Special Report will describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the member of the public from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or vithin a radius of 8 km must be considered. If the dose to any member of the public is estimated to exceed the requirements of 40 CFR Part 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected), in accordance with the provisions of 40 CFR Part 190.11 and 10 CFR Part 20.2203(b), is considered to be a timely request and fulfills the requirements of 40 CFR Part 190 until NRC staff action is completed. The variance only relates to the limits of 40 CFR Part 190, and does not apply in any way to the other requirements for dose limitation of 10 CFR Part 20, as addressed in Controls 2.2.1.1 and 2.2.2.1. An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.

40

Number TMI - Unit I Radiological Controls Procedure 661 O-PLN-4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 24 3.0 SURVEILLANCES 3.1 Radioactive Effluent Instrumentation 3.1.1 Radioactive Liquid Effluent Instrumentation Surveillance Requirements 3.1.1.1 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, AND CHANNEL TEST operations during the MODES and at the frequencies shown in Table 3.1-1.

41

I I 661 0-PLN-4200.01 Revision 24 Table 3.1-1 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements CHANNEL SOURCE CHANNEL CHANNEL

_r--

INSTRUMENT CHECK CHECK CALiBRATiON Ico m

1. Radioactivity Monitors Providing Alarm and Automatic Isolation D P R(2) Q(1O)

a. Unit 1 Liquid Radwaste Effluents Line (RM-L-E5)

D P R(2) Q(1)

b. IWTSIiWFS Discharge Line (RM-L-12)

2. Flow Rate Monitors D(3) N/A R Q

a. Unit.1 Liquid Radwaste Effluent Line (FT-84)

D(3) N/A R Q

b. Station Effluent Discharge (FT-146)I

- I 42

Number TMI - Unit 1 I Radiological Controls Procedure 661 0-PLN-4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 24 Table 3.1-1 Table Notation (1) The CHANNEL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if the following condition exists:

1. Instrument indicates measured levels above the high alarm/trip setpoint. (Includes - circuit failure)

2. Instrument indicates a down scale failure. (Alarm function only.) (Includes - circuit failure)

3. Instrument controls moved from the operate mode (Alarm function only).

(2) The initial CHANNEL CALIBRATION for radioactivity measurement instrumentation shall be performed using one or more of the reference standards certified by the National Institute of Standards and Technology or using standards that have been obtained from suppliers that participated in measurement assurance activities with NIST. These standards should permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration should be used. (Operating plants may substitute previously established calibration procedures for this requirement)

(3) CHANNEL CHECK shall consist of verifying indication of flow during periods of release. CHANNEL CHECK shall be made at least once daily on any day on which continuous, periodic, or batch releases are made.

43

Number TMI - Unit I Radiological Controls Procedure 661 0-PLN-4200.01 Title DRevision No.

Offsite Dose c-alculation Manual (ODCM) 24 3.1.2 Radioactive Gaseous Process and Effluent Monitoring Instrumentation Surveillance Requirements 3.1.2.1 Each radioactive gaseous process or effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL TEST operations at the frequencies shown in Table 3.1-2.

44

661 0-PLN-4200.01 Revision 24 Table 3.1-2 Radioactive Gaseous Process and Effluent Monitoring Instrumentation Surveillance Requirements CHANNEL SOURCE CHANNEL CHANNEL INSTRUMENT CHECK CHECK CALIBRATION TEST APPLICABILITY

1. Waste Gas Holdup System

a. Noble Gas Activity Monitor (RM-A7) P P E(3) Q(1)

b. Effluent System Flow Rate Measuring Device (FT-123) P N/A E Q

2. Waste Gas Holdup System Explosive Gas Monitoring System

a. Hydrogen Monitor D N/A Q(4) M

b. Oxygen Monitor D N/A Q(5) M **

3. Containment Purge Vent System

a. Noble Gas Activity Monitor (RM-A9) D P E(3) M(1)

b. Iodine Sampler (RM-A9) W N/A N/A N/A U

c. Particulate Sampler (RM-A9) W N/A N/A N/A U

d. Effluent System Flow Rate Measuring Device (FR-148) D N/A E Q U

e. Sampler Flow Rate Monitor D N/A E N/A U

4. Condenser Vent System

a. Noble Gas Activity Monitor (RM-A5 and Suitable D M E(3) Q(2)

Equivalent -.See Table 2.1-2, Item 4.a) 45

661 0-PLN-4200.01 Revision 24 Table 3.1-2 Radioactive Gaseous Process and Effluent Monitoring Instrumentation Surveillance Requirements CHANNEL SOURCE CHANNEL CHANNEL INSTRUMENT CHECK CHECK CALIBRATION TEST APP~iiGAM~iTY'

5. Auxiliary and Fuel Handling Building Ventilation System

a. Noble Gas Activity Monitor (RM-A8) or (RM-A4 and D M E(3) Q(1)

RM-A6)

b. Iodine Sampler (RM-A8) or (RM-A4 and RM-A6) W N/A N/A N/A

c. Particulate Sampler (RM-A8) or (RM-A4 and RM-A6) W N/A N/A N/A

d. System Effluent Flow Rate Measurement Devices 0 N/A E Q (FR-149 and FR- 50)

e. Sampler Flow Rate Monitor D N/A E N/A *

6. Fuel Handling Building ESF Air Treatment System

a. Noble Gas Activity Monitor (RM-A14) D M R(3) Q(2)

b. System Effluent Flow Rate (UR-1104 A/B) 0 N/A R Q

c. Sampler Flow Rate Measurement Device D N/A R Q 46

661 0-PLN-4200.01 Revision 24 Table 3.1-2 Radioactive Gaseous Process and Effluent Monitoring Instrumentation Surveillance Requirements CHANNEL SOURCE CHANNEL CHANNEL INSTRUMENT CHECK CHECK CALIBRATION TEST APPLICABILITY

7. Chemical Cleaning Building Ventilation System

a. Noble Gas Activity Monitor (ALC RM-1-18) D M E(3) Q(2)

b. Iodine Sampler (ALC RM-1-18) W N/A N/A N/A

f##

c. Particulate Sampler (ALC RM-1-18) W. NIA NIA NIA

8. Waste Handling and Packaging Facility Ventilation System

a. Particulate Sampler (WHP-RIT-1) D w SA W

9. Respirator and Laundry Maintenance Ventilation System

a. Particulate Sampler (RLM-RM-1) D w SA W 47

Number TMI - Unit 1 I Radiological Controls Procedure 661 O-PLN-4200.J1 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 24 Table 3.1-2 Table Notation

At all times.

- During waste gas holdup system operation.

Operability is not required when discharges are positively controlled through the closure of VWDG-V47, and where RM-A8 (or RM-A4 and RM-A6), FT-149, and FT-150 are operable.

Curing Fuel Handling Building ESF Air Treatment System Operation.

At all times during containment purging.

At all times when condenser vacuum is established.

,#: CDuring operation of the ventilation system.

(1) The CHANNEL TEST shall also demonstrate that automatic isolation of this pathway for the Auxiliary and Fuel Handling Building Ventilation System, the supply ventilation is isolated and control room alarm annunciation occurs if the following condition exists:

1. Instrument indicates measured levels above the high alarm/trip setpoint (Includes circuit failure).

2. Instrument indicates a down scale failure (Alarm function only) (Includes circuit failure).

3. Instrument controls moved from the operate mode (Alarm function only).

(2) The CHANNEL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exist:

1 Instrument indicates measured levels above the alarm setpoint. (includes circuit failure)

2. Instrument indicates a down scale failure (includes circuit failure).

3. Instrument controls moved from the operate mode.

(3) The initial CHANNEL CALIBRATION for radioactivity measurement instrumentation shall be performed using one or more of the reference standards certified by the National Institute of Standards and Technology or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards should permit calibrating the system over its intended range of energy arid measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration should be used. (Operating plants may substitute previously established calibration procedures for this requirement.)

(4) The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal:

1. One volume percent hydrogen, balance nitrogen, and

2. Four volume percent hydrogen, balance nitrogen.

(5) The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal:

1. One volume percent oxygen, balance nitrogen, and

2. Four volume percent oxygen, balance nitrogen.

48

Number TMI- Unit 1 Radioloqical Controls Procedure 661 O-PLN-4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 24 3.2 Radiological Effluents 3.2.1 Liquid Effluents SURVEILLANCE REQUIREMENTS 3.2.1.1 Concentration 3.2.1.1.1 The radioactivity content of each batch of radioactive liquid waste shall be determined prior to release by sampling and analysis in accordance with Table 3.2-1. The results of pre-release analyses shall be used with the calculational methods in the ODCM to assure that the concentration at the point of release is maintained within the limits of Control 2.2.1.1.

3.2.1.1.2 Post-release analysis of samples composited from batch releases shall be performed in accordance with Table 3.2-1. The results of the previous post-release analysis shall be used with the calculational methods in the ODCM to assure that the concentrations at the point of release were maintained within the limits of Control 2.2.1.1.

3.2.1.1.3 The radioactivity concentration of liquids discharged from continuous release points shall be determined by collection and analysis of samples in accordance with Table 3.2-1. The results of the analysis shall be used with the calculational methods of the ODCM to assure that the concentration at the point of release is maintained within the limits of Control 2.2.1.1.

3.2.1.2 Dose Calculations 3.2.1.2.1 Cumulative dose contributions from liquid effluents shall be determined in accordance with the Offsite Dose Calculation Manual (ODCM) at least once a month.

3.2.1.3 Liquid Waste Treatment 3.2.1.3.1 Doses due to liquid releases shall be projected at least once a month, in accordance with the ODCM.

3.2.1.4 Liquid Holdup Tanks 3.2.1.4.1 The quantity of radioactive material contained in each of the tanks specified in Control 2.2.1.4 shall be determined to be within the limit by analyzing a representative sample of the tank's content weekly when radioactive materials are being added to the tank.

49

661 0-PLN-4200.01 Revision 24 Table 3.2-1 Radioactive Liquid Waste Sampling and Analysis Program II I

I I Lowe erLimit of Sampling I Minimum Analysis I Type of Activity Detec tion (LLD)

Liquid Release Type t Frequency I Frequency I

A.1 I

Analysis (.iCilmnl)(Note a)

Batch Waste Release Tanks (Note d) P I P

. I I H-3 1 x 10-*

I I Each Batch I Each Batch I I Principal Gamma 5 I I I

I I Emitters (Note f) iX 10-6 I

I I I I II I I I 1-131 1 X 10-4 I I I I f I

9 I I

Dissolved and Ix10 I I Entrained Gases I I I I (Gamma Emitters)

I I (Note a)

I I II I P Q I I Gross alpha x107 I Each Batch IC omposite (Note b) II I I Sr-89, Sr-90 I I x 10-8 I I I I I I Fe-55 I 1x 10.6 I

IW A.2 Continuous Releases (Note e) I Continuous I Principal Gamma 5x10-7 I

I (Note c) (Composite , Emitters (Note f)

(N I

I ote c)

, (

I 1-131 1x 104 I

I II I II Grab Sample M Dissolved and 1 x 10-M Entrained Gases (Gamma Emitters)

(Note g)

Continuous M

H-3 1 x lo0 (Note c) ' Composite (Notec) Gross alpha ' 1x107 Continuous ' Q . Sr-89, Sr-90 5 x 10-(Note c) Composite I (Notec) Fe-55 I x 1046 50

Number TMI - Unit I Radiological Controls Procedure 6610-PLN-4200.01 Title . Revision No.

Offsite Dose Calculation Manual (ODCM) 24 Table 3.2-1 Table Notation

a. The LLD is defined, for purposes of this surveillance, 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 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system (which may include radiochemical separation):

LLD =4.66 Sb ExVx2.22x 0 6 xYxexp(-XAt)

Where:

LLD is the "a priori" lower limit of detection as defined above (as microcurie per unit mass or volume),

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

E is the counting efficiency (as counts per disintegration),

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

2.22 x 106 is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield (when applicable),

X is the radioactive decay constant for the particular radionuclide, and At is the elapsed time between midpoint of sample collection and time of counting.

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

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

b. A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquids released.

c. To be representative of the quantities and concentrations of radioactive materials in liquid effluent, samples shall be collected continuously in proportion to the rate of flow of the effluent stream. Prior to analyses, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the effluent release.

51

Number TMI - Unit I Radiological Controls Procedure 661 O-PLN-4200.01 Title Revision No.

Offsite Dose calculation Manual (ODCM) 24 Table 3.2-1

d. A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for analyses, each batch shall be isolated, and be thoroughly mixed, by a method described in the ODCM, to assure representative sampling.

e. A,continuous release is the discharge of liquid wastes of a non- discrete volume; e.g., from a volume cr system that has an input flow during the continuous release.

f. The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144.

This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radioactive Effluent Release Report pursuant to TS 6.9.4.

9. The gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, and Xe-135. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those cf the above nuclides, shall also be analyzed and reported in the Annual Effluent Release Report pursuant to T.S. 6.9.4.

52

Number TMI- Unit I Radiological Controls Procedure I 661 0-PLN-4200.01 Title . Revision No.

Offsite Dose Calculation Manual (ODCM) 24 3.2.2 Gaseous Effluents SURVEILLANCE REQUIREMENTS 3.2.2.1 Dose Rates 3.2.2.1.1 The dose rate due to noble gases in gaseous effluents shall be determined to be within the limits of Control 2.2.2.1.a in accordance with the methods and procedures of the ODCM.

3.2.2.1.2 The dose rate of radioactive materials, other than noble gases, in gaseous effluents shall be determined to be within the limits of Control 2.2.2.1.b in accordance with methods and procedures of the ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program, specified in Table 3.2-2.

3.2.2.2 Dose, Noble Gas 3.2.2.2.1 Cumulative dose contributions from noble gas effluents for the current calendar quarter and current calendar year shall be determined in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM) monthly.

3.2.2.3 Dose, lodine-131, lodine-1 33, Tritium, and Radionuclides In Particulate Form 3.2.2.3.1 Cumulative dose contributions from lodine-131, lodine-1 33, Tritium, and radionuclides in particulate form with half lives greater than 8 days for the current calendar quarter and current calendar year shall be determined in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM) monthly.

3.2.2.4 Gaseous Waste Treatment 3.2.2.4.1 Doses due to gaseous releases from the unit shall be projected monthly in accordance with the ODCM.

3.2.2.5 Explosive Gas Mixture 3.2.2.5.1 The concentrations of hydrogen and oxygen in the waste gas holdup system shall be determined to be within the limits of Control 2.2.2.5 by monitoring the waste gases in the Waste Gas Holdup System with the hydrogen and oxygen monitors covered in Table 2.1-2 of Control 2.1.2.

53

Number TMI - Unit 1 Radiological Controls Procedure 661 0-PLN-4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 24 3.2.2.6 Waste Gas Decay Tank 3.2.2.6.1 The concentration of radioactivity contained in the vent header shall be determined weekly. If the concentration of the vent header exceeds 10.7 Ci/cc, daily samples shall be taken of each waste gas decay tank being added to, to determine if the tank(s) is less than or equal to 8800 Ci/tank.

54

661 0-PLN-4200.01 Revision 24 Table 3.2-2 Radioactive Gaseous Waste Sampling and Analysis Program Minimum Lower Limit of Gaseous Release Type Sampling : Analysis Type of Activity Detection (LLD)

Frequency Frequency X Analysis I4Ci/ml) (Note a)

A. Waste Gas P P Principal Gamma

, Each ach Tank Emitters (Note g) XW Decay Tank , Grab Sample E T B. Containment P(Noteb)

Purge H-3 1x10

' Each Purge Grab P (Note b) Each Principal Gamma ' 1x Sample Pre 'Emitters (Note g)

C. Auxiliary and M (Notes c, e) Grab Fuel Handling Building

' P 1x104 I

Air Treatment System a Sampe' a e Principal Gama x.le Emitters (Note g)

D. Fuel Handling Building ESF Air Treatment System

M (during System M (during : H--3 Operation) System ' Principal Gamma ' 1 x 106 a Grab Sample Operation) Emitters (Note q) 1 x 104 E. Condenser Vacuum M (Note h) M H-3 1x 106 Pumps Exhaust M (Note h) Grab Sample (Note h) M h)

(Note Principal a(oeg Gamma 1x1 x 104 Emttrs(Nteg F. Chemical Cleaning Building Air Treatment System M3(NoteI) M HG 1x104 GrbSapePrincipal Gamma ' 1X10-4 G p , Emitters (Note g)

G. Waste Handling and Packaging Facility ' See Section I See Section I '

' See Section I ' See Section I Air Treatment System of this table of this table a a of this table a of this table H. Respirator and Laundry Maintenance Facility Air Treatment System See Section I of this table See Section I : See Section I ' See Section I e of this table I of this table - of this table 55

6610 -PLN-4200.01 Revision 24 Table 3.2-2 Radioactive Gaseous Waste Sampling and Analysis Program Minimum , Lower Limit of Sampling Analysis Type of Aclivily Detection (LLD)

Gaseous Release Type Frequency Frequency ! Analysis ! (iiCifml) (Note a)

All Release Types as Listed Above in B, C, D, F, G, Connou and H (During System Operation) W (Note d)

Connuous Charcoal 1-131 1 x 10-12 (Note i)

Sample Continuous I

, W (Note d) ' Principal Gamma (Note f) Particulate Emitters (Note g) 1x

,(1-131, Others)

Continuous ' Composite ' G A (Note f) Particulate Sample

,* Q I Continuous Composite Sr-89, Sr-90 (Note f) : Particulate 1 x 10-"

Sample J. Condenser Vent Stack Continuous Iodine Sampler (Note j) W (Note d)

C(Note k)i Charcoal 1-131 1 x 10- 2 Sample .

56

Number TMI - Unit I Radiological Controls Procedure 1 661 O-PLN-4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 24 Table 3.2-2 Table Notation

a. The LLD is defined, for purposes of this surveillance, 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 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system (which may include radiochemical separation):

4.66 Sb LLD=

ExVx2.22x10 6 xYxexp(-XAt)

Where:

LLD is the "a priori" lower limit of detection as defined above (as microcurie per unit mass or volume),

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

E is the counting efficiency (as counts per disintegration),

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

2.22 x 106 is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield (when applicable),

X is the radioactive decay constant for the particular radionuclide, and At is the elapsed time between midpoint of sample collection and time of counting.

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

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

b. Sampling and analysis shall also be performed following shutdown, startup, or a THERMAL POWER change exceeding 15 percent of RATED THERMAL POWER within one hour unless (1)analysis shows that the DOSE EQUIVALENT 1-131 concentration in the primary coolant has not increased more than a factor of 3; and (2) the noble gas activity monitor shows that effluent activity has not increased by more than a factor of 3.

c. Tritium grab samples from the spent fuel pool area shall be taken at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the refueling canal is flooded.

57

.Number TMI - Unit 1 I Radiological Controls Procedure 661 O-PLN-4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 24 Table 3.2-2

d. Charcoal cartridges and particulate filters shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after changing (or after removal from sampler).

e. Tritium grab samples shall be taken weekly from the spent fuel pool area whenever spent fuel is in the spent fuel pool.

f. The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with Controls 2.2.2.1, 2.2.2.2, and 2.2.2.3.

9. The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135 and Xe-138 for gaseous emissions and An-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-1 37, Ce-141 and Ce-144 for particulate emissions.

This list does not mean that only these nuclides are to be considered. Other gamma peaks that are ifentifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radioactive Effluent Release Report pursuant to TS 6.9.4.

h. Applicable only when condenser vacuum is established. Sampling and analysis shall also be performed following shutdown, startup, or a THERMAL POWER change exceeding 15 percent of RATED THERMAL POWER within one hour unless (1) analysis shows that the DOSE EQUIVALENT 1-131 concentration in the primary coolant has not increased more than a factor of 3; and (2) the noble gas activity monitor shows that effluent activity has not increased by more t-an a factor of 3.

i. Gross Alpha, Sr-89, and Sr-90 analyses do not apply to the Fuel Handling Building ESF Air Treatment System.

j. If the Condenser Vent Stack Continuous Iodine Sampler is unavailable, then alternate sampling equipment will be placed in service within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or a report will be prepared and submitted within

30 days from the time the sampler is found or made inoperable which identifies (a) the cause Df the inoperability, (b) the action taken to restore representative sampling capability, (c) the action taken lo prevent recurrence, and (d) quantification of the release via the pathway during the period and comparison to the limits prescribed by Control 2.2.2.1.b.

k. Applicable only when condenser vacuum is established.

I. Applicable when liquid radwaste is moved or processed within the facility.

m. Iodine samples only required in the Chemical Cleaning Building when TMI-1 liquid radwaste i; stored or processed in the facility.

58

Number TM) - Unit 1 Pn II rfl^ Irn;aI Cr'^m*rrIc Or~r-or.~omm I . f-- ulJ IU -

nninl.PI

-- -l m-.A9Afln ni S ar.

Title Revision No.

Offsite Dose Calculation Manual (ODCM) 24 3.2.3 Total Radioactive Effluents 3.2.3.1 Dose Calculation 3.2.3.1.1 Cumulative annual dose contributions from liquid and gaseous effluents shall be determined in accordance with Surveillances 3.2.1.2.1, 3.2.2.2.1, and 3.2.2.3.1, including direct radiation contributions from the Unit and from outside storage tanks, and in accordance with the methodology contained in the ODCM.

59

Number TMI - Unit I Radiological Controls Procedure 661 O-PLN-4200.01 Title Revision No.

Offsite Dose C3alculation Manual (ODCM) 24 4.0 PART I REFERENCES 4.1 Title 10, Code of Federal Regulations, "Energy" 4.2 Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routing Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I, "Revision 1, October 1977 4.3 TMI-1 Technical Specifications, attached to Facility Operating License No. DPR-50 4.4 TMI-1 FSAR 60

Number TMI - Unit 1 Radiological Controls Procedure 661 0-PLN-4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 24 PART II TMI-2 RADIOLOGICAL EFFLUENT CONTROLS 61

Number TMI - Unit 1

-.- _.I _. % ..hal A Radiological Controls Procedure 001u-rLrd-/LN UU.U1 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 24 PART 11 Definitions 1.0 DEFINITIONS DEFINED TERMS 1.1 The DEFINED TERMS of this section appear in capitalized type and are applicable throughout Part 11of the ODCM.

PDMS 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 1.3 ACTION shall be those additional requirements specified as corollary statements to each control and shall be part of the controls.

OPERABLE - OPERABILITY 1.4 A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY 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).

CHANNEL CAL113RATION 1.5 A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds with necessary range and accuracy to known values of the parameter which the channel monitors. The CHANNEL CALIBRATION shall encompass the entire channel including the sensor and alarm and/or trip functions, and shall include the CHANNEL FUNCTIONAL TEST. CHANNEL CALIBRATION may be performed by any series of sequential, overlapping or total channel steps such that the entire channel is calibrated.

CHANNEL CHECK 1.6 A CHANNEL CHECK shall be the qualitative assessment of channel behavior during operation by observation. This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter.

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Number TMI - Unit I Radiological Controls Procedure I 661 0-PLN-4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 24 CHANNEL FUNCTIONAL TEST 1.7 A CHANNEL FUNCTIONAL TEST shall be:

a. Analog channels - the injection of a simulated signal into the channel as close to the primary sensor as practicable to verify OPERABILITY including alarm and/or trip functions.

b. Bistable channels - the injection of a simulated signal into the channel sensor to verify OPERABILITY including alarm and/or trip functions.

SOURCE CHECK 1.8 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.

COMPOSITE SAMPLE 1.9 A COMPOSITE SAMPLE is a combination of individual samples obtained at regular intervals over a time period. Either the volume of each individual sample is proportional to the flow rate discharge at the time of sampling or the number of equal volume samples is proportional to the time period used to produce the composite.

GRAB SAMPLE 1.10 A GRAB SAMPLE is an individual sample collected in less than fifteen minutes.

BATCH RELEASE 1.11 A BATCH RELEASE is the discharge of fluid waste of a discrete volume.

CONTINUOUS RELEASE 1.12 A CONTINUOUS RELEASE is the discharge of fluid waste of a non-discrete volume, e.g., from a volume or system that has an input flow during the CONTINUOUS RELEASE.

SITE BOUNDARY 1.13 The SITE BOUNDARY used as the basis for the limits on the release of gaseous effluents is as defined in Section 2.1.2.2 and shown on Figure 2.1-3 of the TMI-1 FSAR. This boundary line includes portions of the Susquehanna River surface between the east bank of the river and Three Mile Island and between Three Mile Island and Shelley Island.

The SITE BOUNDARY used as the basis for the limits on the release of liquid effluents is as shown in Figure 1.1 in Part I of this ODCM.

FREQUENCY NOTATION 1.14 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.1. All Surveillance Requirements shall be performed within the specified time interval with a maximum allowable extension not to exceed 25% of the surveillance interval.

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Offsite Dose Calculation Manual (ODCM) 24 TABLE 1.1 Frequency Notation NOTATION FREQUENCY S (Shiftly) At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

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

W (Weekly) At least once per 7 days.

M (Monthly) At least once per 31 days.

Q (Quarterly) At least once per 92 days.

SA (Semi-Annually) At least once per 184 days.

A (Annually) At least once per 12 months.

E At least once per 18 months.

N.A. Not applicable.

P Completed prior to each release 64

Number TMI - Unit I I Radiological Controls Procedure 661 O-PLN-4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 24 2.0 CONTROLS AND BASES 2.0.1 Controls and ACTION requirements shall be applicable during the conditions specified for each control.

2.0.2 Adherence to the requirements of the Control and/or associated ACTION within the specified time interval shall constitute compliance 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.

2.0.3 In the event the Control and 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.

2.1 Radioactive Effluent Instrumentation 2.1.1 Radioactive Liquid Effluent Instrumentation Radioactive Liquid Effluent Instrumentation is common between TMI-1 and TMI-2.

Controls, applicability, and actions are specified in ODCM Part I, Control 2.1.1 2.1.2 Radioactive Gaseous Process and Effluent Monitoring Instrumentation CONTROL:

The radioactive gaseous process and effluent monitoring instrumentation channels shown in Table 2.1-2 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of Control 2.2.2.1 are not exceeded. The alarm/trip setpoints of these channels shall be determined in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM).

APPLICABILITY: As shown in Table 2.1-2.

ACTION:

a. With a radioactive gaseous process or effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above control, immediately suspend the release of radioactive effluent monitored by the affected channel or declare the channel inoperable.

b. With less than the minimum number of radioactive gaseous process or effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 2.1-2. Exert best efforts to return the instrumentation to OPERABLE status within 30 days and, if unsuccessful, explain in the next Annual Effluent Release Report why the inoperability was not corrected in a timely manner.

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Number TMI - Unit 1

,al Controls Procedure 661 0-PLN-4200.01 Offsite Dose Calculation Manual (01 BASES The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluent during actual or potential releases. The alarm/trip setpoints for these instruments shall be calculated in accordance with NRC approved methods in the ODCM to provide reasonable assurance that the annual releases are within the limits specified in 10 CFR 20.1301.

66

6610-PLN-4200.O1 Revision 24 Table 2.1-2 Radioactive Gaseous Process and Effluent Monitoring Instrumentation MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION

1. Containment Purge Monitoring System

a. Noble Gas Activity Monitor (2HP-R-225) I NOTE I NOTE 2

b. Particulate Monitor (2HP-R-225) 1 NOTE 1 NOTE 2

c. Effluent System Flow Rate Measuring Device (2AH-FR-5907 Point 1) 1 NOTE 1. NOTE 3

2. Station Ventilation System

a. Noble Gas Activity Monitor (2HP-R-219) or (2HP-R-219A) 1 NOTE 1 NOTE 2

b. Particulate Monitor (2HP-R-219) or (2HP-R-219A) 1 NOTE 1 NOTE 2

c. Effluent System Flow Rate Monitoring Device (2AH-FR-5907 Point 6) 1 NOTE 1 NOTE 3 NOTES:

1. During operation of the monitored system.

2. With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, secure Reactor Building Purge if in progress.

3. With flow rate monitoring instrumentation out of service, flow rates from the Auxiliary (2AH-FR-5907 Point 2), Fuel Handling (2AH-FR-5907 Point 4), Soiled Exhaust System (2AH-FR-5907 Point 5), and Reactor Buildings (2AH-FR-5907 Point 1) may be summed individually. Under these conditions, the flow rate monitoring device Is considered operable. If the flow rates cannot be summed individually, they may be estimated using the maximum design flow for the exhaust fans, and the reporting requirements of Control 2.1.2.b are applicable.

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Offsite Dose Calculation Manual (ODCM) 24 2.2 Radioactive Effluent Controls 2.2.1 Liquid Effluent Controls 2.2.1.1 Liquid Effluent Concentration CONTROL:

The concentration of radioactive material released at anytime from the unit to unrestricted areas shall be limited to ten times the concentrations specifiad in 10 CFR Part 20.1001-20.2401, Appendix B, Table 2, Column 2.

APPLICABILITY: At all times ACTION:

With the concentration of radioactive material released from the unit to unrestricted areas exceeding the above limits, immediately restore concentrations within the above limits.

BASES This control is provided to ensure that the concentration of radioactive materials released in liquid waste effluent from the unit to unrestricted areas will be less than ten times the concentration levels specified in 10 CFR Part 20.1001-20.2401, Appendix B, Table 2. These Controls 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 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 Df the annual average concentrations specified in 10 CFR 20. As a result, this Control provides reasonable assurance that the resulting annual exposire to an individual in off-site areas will not exceed the design objectives of Section IL.A of Appendix I 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.

2.2.1.2 Liquid Effluent Dose CONTROL The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released from the unit to the SITE BOUNDARY shall be limited:

a. During any calendar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 mrem to any organ.

b. During any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any orclan.

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Number TMI - Unit 1 Radiological Controls Procedure 661 0-PLN-4200.01 Title .Revision No.

Offsite Dose Calculation Manual (ODCM) 24 APPLICABILITY: At all times ACTION:

a. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the NRC Region I Administrator within 30 days, a Special Report which identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduce the releases of radioactive materials in liquid effluents during the remainder of the current calendar quarter and during the subsequent 3 calendar quarters so that the cumulative dose or dose commitment to any individual from such releases during these four calendar quarters is within 3 mrem to the total body and 10 mrem to any organ. This Special Report shall also include (1) the result of radiological analyses of the drinking water source, and (2) the radiological impact on finished drinking water supplies with regard to the requirements of 40 CFR 141, Safe Drinking Water Act.

BASES This Control requires that the dose to offsite personnel be limited to the design objectives of Appendix I of 10 CFR Part 50. This will assure the dose received by the public during PDMS is equivalent to or less 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 (PEIS). The ACTION statements provide the required flexibility under unusual conditions and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents will be kept "as low as is reasonably achievable". The dose calculations in the ODCM implement the requirements in Section III.A. of Appendix I that conformance with the guides of Appendix I is to be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October, 1977, and Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April, 1977.

NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.113.

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Number TMI- Unit 1 Radiological Controls Procedure 661 O-PLN-4200.0O1 Title Revision No.

Mite Dose Calculation Manual (ODCM) 24 2.2.1.3 Liquid Radwaste Treatment System CONTROL:

The 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 projected doses due to the liquid effluent from the unit to unrestricted areas would exceed 0.06 mrem to the total body or 0.2 mrem to any organ in any calendar month.

APPLICABILITY: At all times ACTION:

a. With radioactive liquid waste being discharged without treatment and in excess of the above limits, prepare and submit to the NRC Region I Administrator within 30 days, a Special Report which includes the following information:

1. Explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reason for inoperability,

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

3. A summary description of action(s) taken to prevent a recurrence.

BASES The requirement that the appropriate portions of this system (shared with TMI-1) be used, when specified, provides assurance that the releases of radioactive materials in liquid effluents will be kept as low as is reasonEbly achievable. This control implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objective given in Section II.D of Appendix I to 10 CFR Part 50. The intent of Section II.D. is to reduce effluents to as low as is reasonably achievable in a cost effective manner. This control satisfies this intent by establishing a dose limit which is a small fraction (25%) of Section II.A of Appendix I, 10 CFR Part 50 dose requirements. This margin, a factor of 4, constitutes a reasonable reduction.

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Number TMI- Unit I Radiological Controls Procedure 661 O-PLN-4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 24 2.2.2 Gaseous Effluent Controls 2.2.2.1 Gaseous Effluent Dose Rate CONTROL:

The dose rate due to radioactive materials released in gaseous effluent from the site shall be limited to the following:

a. For noble gases: less than or equal to 500 mrem/yr to the total body and less than or equal to 3000 mrem/yr to the skin, and

b. For tritium and all radionuclides in particulate form with half lives greater than 8 days: less than or equal to 1500 mrem/yr to any organ.

APPLICABILITY: At all times.

ACTION:

With the release rate(s) exceeding the above limits, immediately decrease the release rate to comply with the above limit(s).

BASES The control provides reasonable assurance that the annual dose at the SITE BOUNDARY from gaseous effluent from all units on the site will be within the annual dose limits of 10 CFR Part 20 for unrestricted areas. At the same time, these Controls permit flexibility under unusual conditions, which may temporarily result in higher than the design objective levels, but still within the dose limits specified in 10 CFR 20 and within the design objectives of Appendix I to 10 CFR 50. It is expected that using this flexibility under unusual conditions, and by exerting every effort to keep levels of radioactive material in gaseous 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 gaseous release rates provide reasonable assurance that radioactive material discharged in gaseous effluent will not result in the exposure of a MEMBER OF THE PUBLIC in an unrestricted area, either within or outside the SITE BOUNDARY, to annual average concentrations exceeding the values specified in Appendix B, Table 2 of 10 CFR Part 20. For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy of the MEMBER OF THE PUBLIC will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the exclusion area boundary.

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Number TMI - Unit 1 Radiological Controls Procedure 6610-PLN-4200.0'1 TRevision No.

Offsite Dose Cdlculation Manual (ODCM) 24 The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to a MEMBER OF THE PUBLIC at or beyond the SITE BOUNDARY to less than or equal to 500 mrem/year to the total body or to less than or equal to 3000 mrem/year to the skin. The absence of iodine ensures that the corresponding thyroid dose rate above background to a child via the inhalation pathway is less than or equal to 1500 mrem/yr (NUREG 1301), thus there is no need to specify dose rate limits for these nuclides.

2.2.2.2 Gaseous Effluents Dose-Noble Gases CONTROL:

The air dose due to noble gases released in gaseous effluents from the unit to areas at and beyond the SITE BOUNDARY shall be limited to the following:

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

b. During any calendar year: less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.

APPLICABILITY: At all times.

ACTION:

a. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the NRC Region I Administrator within 30 days, a Special Report which identifies the cause(s) for exceeding Ihe limit(s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

BASES This control applies to the release of radioactive materials in gaseous effluents from TMI-2.

This control and associated action is provided to implement the requirements of Section IL.B, Il.A and IV.A of Appendix 1,10 CFR Part 50. The Con':rol implements the guides set forth in Section ll.B of Appendix 1. The ACTION statements provide flexibility under unusual conditions and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents will be kept "as low as is reasonably achievable." The Surveillance Requirements implement the requirements in Section lll.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through 72

Number TMI- Unit I rocedure Kadiologica!Cotrols I UL . .. . .U. U.-

I Radiological Controls Procedure bb 00U-ILN-4ZUU.U1 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 1 24 the appropriate pathways is unlikely to be substantially underestimated. The dose calculation methodology and parameters established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Release of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.1 11, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors," Revision 1, July 1977. The ODCM equations provided for determining the air doses at and beyond the SITE BOUNDARY are based upon the historical average atmospheric conditions. NUREG-01 33 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.111.

2.2.2.3 Dose - Iodine-131, lodine-133, Tritium, and Radionuclides In Particulate Form CONTROL:

The dose to a MEMBER OF THE PUBLIC from Tritium and all radionuclides in particulate form with half lives greater than 8 days, in gaseous effluents released from the unit to areas at and beyond the SITE BOUNDARY shall be limited to the following:

a. During any calendar quarter: less than or equal to 7.5 mrem to any organ, and

b. During any calendar year: less than or equal to 15 mrem to any organ.

APPLICABILITY: At all times.

ACTION:

With the calculated dose from the release of Tritium and radionuclides in particulate form with half lives greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and submit to the NRC Region I Administrator within 30 days, a Special Report which identifies the cause(s) for exceeding the limit and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

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Number TMI - Unit I Radiological Controls Procedure 6610-PLN-4200.01 Title DtRevision No.

Offsite Dose Calculation Manual (ODCM) 24 BASES This control applies to the release of radioactive materials in gaseous effluents from TMI-2.

This control and associated action is provided to implement the requirements of Section 11.C, II.A and IV.A of Appendix I, 10 CFR Part 50. The Controls are the guides set forth in Section I1.C of Appendix I. The ACTION statement provides flexibility during unusual conditions and at the same time implements the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." The ODCM calculational methods specified in the surveillance requirements implement the requirements in Section Ill.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The ODCM calculational methodology and parameters for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October, 1977 and Regulatory Guide 1.1 11, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July, 1977. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate controls for iodine-131, iodine-133, tritium and radionuclides in particulate form with half lives greater than 83days are dependent upon the existing radionuclide pathways to man, in areas at and beyond the SITE BOUNDARY. The pathways that were examined in the development of these calculations were: 1) individual inhalation of airborne radionuclides, 2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man. The absence of iodines at the site eliminates the need to specify dose limits for these nuclides.

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Number TMI - Unit 1 Radiological Controls Procedure 661 O-PLN-4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 24 2.2.2.4 Ventilation Exhaust Treatment System CONTROL The VENTILATION EXHAUST TREATMENT SYSTEM shall be OPERABLE.

The appropriate portions of the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the monthly projected doses due to gaseous effluent releases from the site would exceed 0.3 mrem to any organ.

APPLICABILITY: At all times.

ACTION:

a. With the VENTILATION EXHAUST TREATMENT SYSTEM inoperable for more than a month or with gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit to the NRC Region I Administrator within 30 days, a Special Report which includes the following information:

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

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

3. A summary description of action(s) taken to prevent a recurrence.

BASES The use of the VENTILATION EXHAUST TREATMENT SYSTEM ensures that gaseous effluents are treated as appropriate prior to release to the environment. The appropriate portions of this system provide reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable." This control implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design objectives given in Section Il.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the guide set forth in Sections ll.B and Il.C of Appendix 1,10 CFR Part 50, for gaseous effluents.

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Number TMI- Unit 1 gal Controls Procedure 661 0-PLN-4200.01 Qffsite Dose Calculation

-- - - - Manual (ODCM' 2.22.3 Total Radioactive Effluent Controls 2.2.3.1 Total Dose CONTROL:

The annual (calendar year) dose or dose commitment 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 shall be limited to less than Dr equal to 75 mrem.

APPLICABILITY: At all times.

ACTION:

With the calculated dose from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Controls 2.2.1.2.a, 2.2.1.2.b, 2.2.2.2.a, 2.2.2.2.b, 2.2.2.3.a, or, 2.2.2.3.b, calculations should be made including direct radiation contributions from the unit and from outside storage tanks to determine whether the above limits of Control 2.2.3.1 have been exceeded. If such is the case, prepare and submit to the NRC Region I Administrator within 30 days, a Special Report which defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits. This Special Report, as defined in 10 CFR Part 20.2203(b), shall include an analysis which estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release(s) covered by this report. It she-i also describe levels of radiation and concentrations of radioactive material involved, and the cause of the exposure levels or concentrations. If the estimated dose(s) exceed the above limits, and if the release condition resulting in violation of 40 CFR 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR 190. Submittal of the report is considered a time;y request, and a variance is granted until staff action on the request is complete.

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Number TMI - Unit I I Radiological Controls Procedure 6610-PLNN 4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 24 BASES This control is provided to meet the dose limitations of 40 CFR Part 190 that have been incorporated into 10 CFR Part 20.1301(d). This control requires the preparation and submittal of a Special Report whenever the calculated doses from plant generated radioactive effluents and direct radiation exceed 25 mrem to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrem. For sites containing up to 4 reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR Part 190 if the individual reactors remain within twice the dose design objectives of Appendix I, and if direct radiation doses from the reactor units and outside storage tanks are kept small. The Special Report will describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the member of the public from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 8 km must be considered. If the dose to any member of the public is estimated to exceed the requirements of 40 CFR Part 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected), in accordance with the provisions of 40 CFR Part 190.11 and 10 CFR Part 20.2203(b), is considered to be a timely request and fulfills the requirements of 40 CFR Part 190 until NRC staff action is completed. The variance only relates to the limits of 40 CFR Part 190, and does not apply in any way to the other requirements for dose limitation of 10 CFR Part 20, as addressed in Controls 2.2.1.1 and 2.2.2.1. An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.

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Number TMI - Unit 1 Radiological Controls Procedure 661 O-PLN-4200.0 1 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 24 3.0 SURVEILLANCES 3.0.1 Surveillance Requirements shall be applicable during the conditions specified for individual 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.

3.0.2 Each Surveillance Requirement shall be performed within the specified time interval with a maximum allowable extension not to exceed 25% of the surveillance interval.

3.0.3 Failure to perform a Surveillance Requirement within the time interval specified in Section 3.0.2 shall constitute non-compliance with OPERABILITY requirements for a Control. The time limits of the ACTION requirements are applicable at the time it is identified that a Surveillance Requirement has not been performed. The ACTION requirements may be delayed for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to permit completion of the surveillance when the allowab e outage time limits of the ACTION requirements are less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Surveillance Requirements do not have to be performed on inoperable equipment.

3.1 Radioactive Effluent Instrumentation 3.1.1 Radioactive Liquid Effluent Instrumentation Surveillance Requirements Radioactive Liquid Effluent Instrumentation is common between TMI-1 and TMI-2.

Surveillances for this instrumentation are specified in ODCM Part I, Surveillance 3.1.1.

8.1.2 Radioactive Gaseous Process and Effluent Monitoring Instrumentation SURVEILLANCE REQUIREMENTS 3.1.2.1 Each radioactive gaseous process or effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL TEST operations at the frequencies shown in Table 3.1-2.

78

6610-PLN-4200.01 Re!vision 24 Table 3.1-2 Radioactive Gaseous Process and Effluent Monitoring Instrumentation Surveillance Requirements CHANNEL CHANNEL CHANNEL FUNCTIONAL INSTRUMENT CHECK CALIBRATION TEST APPLICABILITY

1. Containment Purge Monitoring System

a. Noble Gas Activity Monitor (2HP-R-225) D E M NOTE 1

b. Particulate Sampler (2HP-R-225) w N/A N/A NOTE 1

2. Station Ventilation Monitoring System

a. Noble Gas Activity Monitor (2HP-R-219) and D E M NOTE I (2HP-R-21 9A)

b. Particulate Sampler (2HP-R-219) and (2HP-R-219A) w N/A NIA NOTE 1 NOTES:

1. During operation of the monitored system.

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Offsite Dose Calculation Manual (ODCM) 24 3.2 Radioactive Effluents 3.2.1 Liquid Effluents SURVEILLANCE REQUIREMENTS 3.2.1.1 Concentration 3.2.1.1.1 The radioactivity content of each batch of radioactive liquid waste shall be determined by sampling and analysis in accordance with Table 3.2-1. The results of analyses shall be used with the calculational methods in the ODCM to assure that the concentration at the point of release is maintained within the limits of Control 2.2.1.1.

3.2.1.1.2 Analysis of samples composited from batch releases shall be performed in accordance with Table 3.2-1. The results of the analysis shall be used with the calculational methods in the ODCM to assure that the concentrations at the point of release were maintained within the limits of Control 2.2.1.1.

3.2.1.1.3 The radioactivity concentration of liquids discharged from continuous release points shall be determined by collection and analysis of samples in accordance with Table 3.2-1. The results of the analysis shall be used with the calculational methods. of the ODCM to assure that the concentration at the point of release is maintained within the limits of Control 2.2.1.1.

3.2.1.2 Dose Calculations 3.2.1.2.1 Cumulative dose contributions from liquid effluents shall be determined in accordance with the Offsite Dose Calculation Manual (ODCM) at least once a month.

3.2.1.3 Dose Projections 3.2.1.3.1 Doses due to liquid releases shall be projected at least once a month, in accordance with the ODCM.

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Offsite Dose Calculation Manual (ODCM) 24 TABLE 3.2-1 Radioactive Liquid Waste Sampling and Analysis (4, 5)

A. Liquid Releases Sampling Frequency Type of Detectable lI_ Activity Analysis I Concentration (3) j P Individual Gamma 5E-7 pCi/ml (2)

Each Batch H-3IE-5 iCi/mI Q Gross Alpha I E-7 pCi/ml Quarterly Composite (1) Sr-90 5E-8 RCi/ml 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.

(2) For certain mixtures of gamma emitters, it 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 detectability limits for radioactivity analysis are based on the technical feasibility and on the potential significance in the environment of the quantities 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.

(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 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 IV.

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Offsite Dose Calculation Manual (ODCM) 24 3.2.2 Gaseous Effluents SURVEILLANCE REQUIREMENTS 3.2.2.1 Dose Rates 3.2.2.1.1 The dose rate due to noble gases in gaseous effluents shall be determined to be within the limits of Control 2.2.2.1.a in accordance with the methods and procedures of the ODCM.

3.2.2.1.2 The dose rate of radioactive materials, other than noble gases, in gaseous effluents shall be determined to be within the limits of Control 2.2.2.1.b in accordance with methods and procedures of the ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program, specified in Table 3.2-2.

3.2.2.2 Dose, Noble Gas 3.2.2.2.1 Cumulative dose contributions from noble gas effluents for the current calendar quarter and current calendar year shall be determined in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM) monthly.

3.2.2.3 Dose, Tritium and Radionuclides In Particulate Form 3.2.2.3.1 Cumulative dose contributions from Tritium and radionuclides in particulate form with half lives greater than 8 days for the current calendar quarter and current calendar year shall be determined in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM) monthly.

3.2.2.4 Ventilation Exhaust Treatment 3.2.2.4.1 Doses due to gaseous releases from the unit shall be projected monthly in accordance with the ODCM.

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Offsite Dose Calculation Manual (ODCM) 24 TABLE 3.2-2 Radioactive Gaseous Waste Sampling and Analysis (3)

DETECTABLE SAMPLE SAMPLING TYPE OF CONCENTRATION(1)(

SAMPLE POINT TYPE FREQUENCY ACTIVITY ANALYSIS a)

Reactor Building Purge Releases P H-3 I E-6 pCi/cc Gas Each Purge Gamma Emitters 1E-4 jiCi/cc (2)

Unit Exhaust Vent Release Points M H-3 1E-6 gCi/cc Gas Monthly GammaIndividual Emitters I E-4 iCi/cc (2)

W Individual (b)

Weekly Gamma Emitters 1E-1 0 p~Ci/cc; (2) l M Particulates Patclts Monthly Composite _____

Sr-90____

1E-1 1 jiCi/cc M

Monthly Gross Alpha Emitters 1E-1 I pCi/cc I_ Composite Reactor Building Breather Indv. Gamma IE-10 pCi/cc (2)

SA Emitters (b) I-Oiic 2 Particulates Semi-Annually Sr-90 1E-1 I pCi/cc Gross Alpha Emitters 1E-1 1 gCi/cc (1 ) The above detectability limits are based on technical feasibility and on the potential significance in the environment of the quantities 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.

(2) For certain mixtures of gamma emitters, it may be possible to measure radionuclides 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 measurable.

(3) Deviations from the sampling and analysis regime will be noted in the report specified in ODCM Part IV.

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Offsite Dose Calculation Manual (ODCM) 24 TABLE 3.2-2 Radioactive Gaseous Waste Sampling and Analysis Program Table Notation

a. The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system (which may include radiochemical separation):

4.66 sp E x V x 2.22 x 106 x Y x exp (-XAt)

Where LLD is the lower limit of detection as defined above (as picocurie per unit mass or volume).

Sb is the standard deviation of the background counting rate or of the counting rate of a blank 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),

I is the radioactive decay constant for the particular radionuclide, and At is the elapsed time between midpoint of sample collection and time of counting (for plant effluents, not environmental samples),

The value of Sb used in the calculation of the LLD for a detection system shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance. In calculating the LLD for a radionuclide determined by gamma-ray spectrometry, the background shall include the 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 background counts that are determined to be with +/- 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.

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Offsite Dose Calculation Manual (ODCM) 24 TABLE 3.2-2

b. The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, 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 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 not be used in the required dose calculations.

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Of fsite Dose Calculation Manual (ODCM) 24 3.2.3 Total Radioactive Effluents 3.2.3.1 Dose Calculation 3.2.3.1.1 Cumulative annual dose contributions from liquid and gaseous effluents shall be determined in accordance with Surveillances 3.2.1.2.1, 3.2.2.2.1, and 3.2.2.3.1, including direct radiation contributions from the Unit and from outside storage tanks, and in accordance with the methodology contained in the ODCM.

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Offsite Dose Calculation Manual (ODCM) 24 4.0 PART II REFERENCES 4.1 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.

4.2 TMI-2 PDMS Technical Specifications, attached to Facility License No. DPR-73 4.3 Title 10, Code of Federal Regulations, "Energy" 4.4 "Statement of Policy Relative to the NRC Programmatic Environmental Impact Statement on the Cleanup of Three Mile Island Unit 2," dated April 27, 1981 4.5 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 I," Revision 1, October 1977 4.6 DOEITIC-27601, Atmospheric Science and Power Reduction 4.7 TMI-1 Technical Specifications, attached to Facility Operating License No. DPR-50 4.8 PDMS - SAR 87

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Offsite Dose Calculation Manual (ODCM) 24 PART III EFFLUENT DATA AND CALCULATIONAL METHODOLOGIES 88

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Offsite Dose Calculation Manual (ODCM) 24 1.0 LIQUID EFFLUENT MONITORS 1.1 TMI-1 and TMI-2 Liquid Radiation Monitor Set Points 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) where:

C = ten times the effluent concentration of 10 CFR 20 for the site, in juCi/ml.

c = the set point, in pCi/ml, of the liquid effluent monitor measuring the radioactivity concentration in the effluent line prior to dilution and release. The set point is inversely proportional to the maximum volumetric flow of the effluent line and proportional to the minimal volumetric flow of the dilution stream plus the effluent stream. The alert set point value is set to ensure that advance warning occurs prior to exceeding any limits. The high 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.

f= flow set point as measured at the radiation monitor location, in volume per unit time, but in the same units as F below.

F = flow rate of dilution water measured prior to the release point, in volume per unit time.

The set point concentration is reduced such that concentration contributions from multiple release points would not combine to exceed ten times 10 CFR 20 concentrations. The set point 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 Liquid Waste procedure.

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Offsite Dose Calculation Manual (ODCM) 24 1.2 TMI Liquid Effluent Release Points and Liquid Radiation Monitor Data TMJI-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 1.1. (The TMI outfall radiation monitor, RM-L7, is also listed for information only.)

TM11-2 does not have any required liquid radiation monitors, but does utilize RM-L12, and RM-L7 for release of liquid waste.

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 two Waste Evaporator Condensate Storage Tanks (WECST) at a flow which will add less than 10%,

of ten times the 10 CFR 20 concentrations [20% for H-3] to radionuclide concentrations in the unrestricted area, including conservative default values for Sr-89, Sr-90, and Fe-55.

The release flow rate used is the most restrictive of two flow rates calculated for each liquid batch release, per the approved plant procedure.

Two Dilution Factors (DF) are calculated to ultimately calculate the batch release flow rate. These two DF's are calculated to insure each radionuclide released to the

.unrestricted area is less than 10 percent of ten times the 10CFR20 radionuclide concentrations, (20% for H-3), and to ensure each liquid batch release boron concentration to the river will not exceed 0.7 ppm.

The maximum release flow rate is then calculated by dividing the most restrictive (largest)

DF into 90 percent of the current dilution flow rate of the Mechanical Draft Cooling Tower (MDCT). This conservative flow rate is then multiplied by 0.9 for the allowable flow rate.

Calculation of the IOCFR20 concentration DF:

DF, = , (SAJ) (10% [20% for H-3] of ten times the I OCFR20 concentration)

SA = Specific Activity of each identified radionuclide

Calculation of Boron DF:

DF2 = Actual Tank Boron Concentration + 0.7.

Maximum release flow rate calculation:

Max Flow = [(MDCT flow gpm

0.9) + (Most Restrictive DF)]

0.9 The dilution flow rate used is the current flow 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 following equation.

£(Cl1X1) + (CH4/2XH4) < 0.1, (eq 1.2) 90

Number TMI- Unit I Radiological Controls Procedure I 6610-PLN-4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 24 where: Ci = diluted concentration of the ith radionuclide, other than H-3 X= Ten times the concentration for that radionuclide in the unrestricted area (10 CFR 20, App. B, Table 2, Col. 2). A value of 3E-3 jiCi/ml for dissolved and entrained noble gases shall be used.

CH.3 =diluted concentration of H-3 XH-3 =Ten times the concentration for H-3 in the restricted area (10 CFR 20, App. B, Table 2, Col. 2).

The set points for RM-L6 are based on the maximum release rate (30 gpm), a minimum dilution flow (5000 gpm), and 25% of ten times the 10CFR20 concentration for Cs-137, which is the most limiting radionuclide at a concentration of 1.OE-5 uCi/ml. These inputs are used in Equation 1.1 to determine the RM-L-6 High Alarm setpoint for all radionuclides being released. A high alarm on RM-L-6 will close valve WDL-V-257 and terminate any WECST releases to the environment.

1.2.2 RM-L12 RM-L12 is an off-line system, monitoring periodic combined releases from the Industrial Waste Treatment System/lindustrial Waste Filtration System (IWTS/IWFS). The input to IWTS/IWFS originates in TMI-2 sumps, (see Figures 1.1 and 1.2) and the TMI-1 Turbine Building sump (see Figure 1.1). The set points are based on the maximum release rate from both IWTS and IWFS simultaneously, (see Figure 1.1) a minimum dilution flow rate, and 50% of ten times the 10CFR20 concentration for Cs-1 37, which is the most limiting radionuclide at a concentration of 1E-5 itCi/ml. These inputs are used in equation 1.1 to determine the RM-L12 High Alarm set point for all radionuclides being released. A high alarm on RM-L12 will close IWTS and IWFS release valves and trip release pumps to stop the release.

1.2.3 RM--10 RM-L10 was a Nal detector submerged in the TMI-I Turbine Building Sump. This detector has been removed from service.

1.2.4 RM-L7 RM-L7 is not an ODCM required liquid radiation monitor. RM-L7 is an off-line system, monitoring the TMI outfall to the Susquehanna River (see Figures 1.1 and 1.2). This monitor is the final radiation monitor for TMI-1 and TMI-2 normal liquid effluent releases.

1.3 Control of Liquid Releases TMI liquid effluent releases are controlled to less than ten times the 10CFR20 concentrations by limiting the percentage of this limit allowable from the two TMI liquid release points. -RM-L6 and effluent sampling limit batch releases to less than or equal to 25% for all radionuclides, and RM-L12 and effluent sampling limit releases from TMI-1 and TMI-2 to less than or equal to 50% for Cs-1 37.

These radiation monitor set points also include built in meter error factors to further ensure that TMI liquid effluent releases are less than ten times the IOCFR20 concentrations to the environment.

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Mffite Dose Calculation Manual (ODCM) 24 The radioactivity content of each batch of radioactive liquid waste is determined prior to release by sampling and analysis in accordance with ODCM Part I Table 3.2-1 or ODCM Part II, Table 3.2-1.

The results of analyses are used with the calculational methods in Section 1.1, to assure that the concentration at the point of release is maintained within the ODCM Part I Control 2.2.1.1, and ODCM Part II Control 2.2.1.1.

Post-release analysis of samples composited from batch releases are performed in accordance with ODCM Part I Table 3.2-1 or ODCM Part II Table 3.2-1. The results of the previous post-release analysis shall be used with the calculational methods in the ODCM to assure that the concentrations at the point of release were maintained within the ODCM Part I Control 2.2.1.1, and ODCM Patt 11 Control 2.2.1.1.

Tne radioactivity concentration of liquids discharged from continuous release points are determined by collection and analysis of samples in accordance with ODCM Part I Table 3.2-1, or ODCM Part II Table 3.2-1. 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 ODCM Part I Control 2.2.1.1, and ODCM Part II Control 2.2.1.1.

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Offsite Dose Calculation Manual (ODCM) 24 TABLE 1.1 TMI Liquid Release Point and Liquid Radiation Monitor Data RELEASE LIQUID RADIATION LIQUID RELEASE TERMINATION MONITOR POINT (Maximum DISCHARGE FLOW INTERLOCK (DETECTOR) LOCATION Volume) RECORDER (YES/NO) VALVES RM-L6 281' Elevation WECST Batch YES (Nal) TMI-1 Auxiliary Bldg Releases (8000 gal.) FT84 WDL-V257 RM-1-7 SainDshreYES South end of TMI-1 StioDscae (Nal) DCT TMI-1 and FT-146 WDL-V257 TMI-2, *WDL-R-1311 YES IWTS/IWFS IW-V73, RM-L12 IWFS Building NW Continuous Releases FT-342/ IW-P16,17,18 (Nal) Corner (300,000/ FT-373 80,000 gal.) IW-V279, IW-P29,30

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

- RM-L7 is not an ODCM required liquid radiation monitor.

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Title 24 Offsite Dose Calculation Manual (ODCM)

TABLE 1.2 TMI-2 Sump Capacities Total Capacity l Gallons Sump l Gallons I per Inch 1346 22.43 Turbine Building Sump 572 10.59 Circulating Water Pump House Sump 718 9.96 Control Building Area Sump 538 9.96 Tendon Access Galley Sump 1346 22.43 Control to Service Building Sump 135 3.80 Contaminated Drain Tank Room Sump Chlorinator House Sump 1615 22.43 Water Treatment Sump**

700 -

Air Intake Tunnel Normal Sump 100000 766.00 Air Intake Tunnel Emergency Sump 2617 62.31 Condensate Polisher Sump*

1106 26.33 Sludge Collection Sump**

Heater Drain Sump 1476 24.00 Solid Waste Staging Facility Sump 10102 202.00 Auxiliary Building Sump 479 10.00 Decay Heat Vault Sump 479 10.00 Building Spray Vault Sump

Condensate Polisher Sump is deactivated and in PDMS condition. for PDMS.

- The Water Treatment and Sludge Collection Sumps will be deactivated 94

661O.PLN-4200.01 Revision 24 Figure 1.t1 Composite adiation Monitor TMI-1 Liquid Effluent Pathways Samlter Component - lMechanical Draft Cooling K Cooling Tower Water TMI-1 TMI-1 RIVER 95

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Offsite Dose Calculation Manual (ODCM) 24 FIGURE 1.2 TMI-2 Liquid Effluent Pathways CONTROL CONTROL &

BUILDING - SERVICE SUMP AREA SUMP IWTS SUMP INDUSTRIAL WASTE TREATMENT SYSTEM

( C -- COMPOSITE SAMPLER 96

Number TMdUU~y~I

-Unrrit1rcuwu uLItu~

&sfen ni I Aflnn nol Title Revision No.

Offsite Dose Calculation Manual (ODCM) 24 2.0 LIQUID EFFLUENT DOSE ASSESSMENT 2.1 Linuid 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 TMI. 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 flume tracer die studies and additional liquid effluent release studies conducted 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:

Dosej= (At)X (Ci) X [AWij X f ) + (AFij X f X F )] (eq 2.1) 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.

At = the length of the time period of actual releases, over which C1 and f are averaged for all liquid releases, in hours.

C,= the average concentration of radionuclide, i, in undiluted liquid effluent during time period At from any liquid release, in pCi/ml.

NOTE For Fe-55, Sr-89, Sr-90, prior to batch releases conservative concentration values will be used in the initial dose calculation based on similar past plant conditions. LLD values are not used in dose calculations.

f= undiluted liquid waste flow, in gpm.

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 (NUREG 0133) or taken to be 5 based on the inverse of 0.2.

AWij and AFij = the site-related ingestion dose commitment factor to the total body or any organ, j, for each identified principle gamma and beta emitter, in mrem/hr per PCi/ml. AW is the factor for the water pathway and AF is the factor for the fish pathway.

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Offsite Dose Calculation Manual (ODCM) 24 Values for AWij are determined by the following equation:

AW~j = (1.144E5) x (Uw) x (DFj) (eq 2.2) wnere:

1.1 4E5 = (1.OE6 pCi/lpCi) x (1.0E3 ml/kg) + (8760 hr/yr)

Uw = Water consumption rate for adult is 730 kglyr (Reg. Guide 1.109, Rev. 1).

DFij = ingestion dose conversion factor for radionuclide, i, for adults total body and for "worst case" organ, j, in mrem/pCi, from Table 2.1 (Reg. Guide 1.109)

Values for AF11 are determined by the following equation:

AFij = (1.14E5) x (Uf) x (DFij) x (BFi) (eq 2.2.2) where:

1.14E5 = defined above Uf = adult fish consumption, assumed to be 21 kg/yr (Reg. Guide 1.109, Rev. 1).

DFij = ingestion dose conversion factor for radionuclide, i, for adult total body and for "worst case" organ, j, in mrem/pCi, from Table 2.1 (Reg. Guide 1.109, Rev. 1).

BFi = Bioaccumulation factor for radionuclide, i, in fish, in pCi/kg per pCiIL from Table 2.2 (Reg.

Guide 1.109, Rev. 1).

2.2 TMI Liquid Radwaste System Dose Calcs Once/Month ODCM Part I Control 2.2.1.3 and TMI-2 PDMS Tech Spec Section 6.7.4.a.6 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-date 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 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 radioactivity levels prior to release.

At the discretion of Radiological Engineering, time periods other than the current quarter-to-date may be used to project doses if the dose per day in the current quarter-to-date is not believed to be representative of the dose per day projected for the next month.

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Offsite Dose Calculation Manual (ODCM) 24 2.3 Alternative Liquid Dose Calculational Methodolocy 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 TMI calculates doses using SEEDS (simplified environmental effluent dosimetry system).

The onsite and SEEDS calculational models use actual liquid release data with actual monthly Susquehanna River flow data to assess the dispersion of effluents in the river.

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Offsite Dose Calculation Manual (ODCM) 24 TABLE 2.1 Liquid Dose Conversion Factors (DCF): DF 1j Page 1 of 3 Ingestion Dose Factors for Adults*

(hMREM Per PCI Ingested)

NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI H 3 NO DATA 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 C 14 2.84E-06 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-.07 NA 24 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 CR 51 NO DATA NO DATA 2.66E-09 1.59E-09 5.86E-10 3.53E-09 6.69E*-07 MN 54 NO DATA 4.57E-06 8.72E-07 NO DATA 1.36E-06 NO DATA 1.40E.05 MN 56 NO DATA 1.15E-07 2.04E-08 NO DATA 1.46E-07 NO DATA 3.67E-06 FE 55 2.75E-06 1.90E-06 4.43E-07 NO DATA NO DATA 1.06E-06 1.09E-06 FE 59 4.34E-06 1.02E-05 3.91 E-06 NO DATA NO DATA 2.85E-06 3.40E-05 CO 58 ',JO DATA 7.45E-07 1.67E-06 NO DATA NO DATA NO DATA 1.51 E.-05 CO 60 NO DATA 2.14E-06 4.72E-06 NO DATA NO DATA NO DATA 4.02E-05 NI 63 1.30E-04 9.01 E-06 4.36E-06 NO DATA NO DATA NO DATA 1.88E-06 NI 65 5.28E-07 6.86E-08 3.13E-08 NO DATA NO DATA NO DATA 1.74E.-06 CU 64 NO DATA 8.33E-08 3.91 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 1.03E-08 1.97E-08 1.37E-09 NO DATA 1.28E-08 NO DATA 2.961--09 BR 83 NO DATA NO DATA 4.02E-08 NO DATA NO DATA NO DATA 5.791--08 BR 84 NO DATA NO DATA 5.21 E-08 NO DATA NO DATA NO DATA 4.091-z-13 BR 85 NO DATA NO DATA. 2.14E-09 NO DATA NO DATA NO DATA LT E-24 RB 86 NO DATA 2.11E-05 9.83E-06 NO DATA NO DATA NO DATA 4.16 E-06 RB 88 NO DATA 6.05E-08 3.21 E-08 NO DATA NO DATA NO DATA 8.36E-19 RB 89 NO DATA 4.01E-08 2.82E-08 NO DATA NO DATA NO DATA 2.33E-21 SR 89 3.08E-04 NO DATA 8.84E-06 NO DATA NO DATA NO DATA 4.94E-05 SR 90 7.58E-03 NO DATA 1.86E-03 NO DATA NO DATA NO DATA 2.19E-04 SR 91 5.67E-06 NO DATA 2.29E-07 NO DATA NO DATA NO DATA 2.70E-05 SR 92 2.15E-06 NO DATA 9.30E-08 NO DATA NO DATA NO DATA 4.2EE-05 Y 90 9.62E-09 NO DATA 2.58E-10 NO DATA NO DATA NO DATA 1.02E-04 100

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Offsite Dose Calculation Manual (ODCM) 24 TABLE 2.1 Liquid Dose Conversion Factors (DCF): DF1, Page 2 of 3 Ingestion Dose Factors for Adults*

(MREM Per PCI Ingested)

NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI Y 91M 9.09E-1 1 NO DATA 3.52E-12 NO DATA NO DATA NO DATA 2.67E-1 0 Y 91 1.41 E-07 NO DATA 3.77E-09 NO DATA NO DATA NO DATA 7.76E-05 Y 92 8.45E-10 NO DATA 2.47E-11 NO DATA NO DATA NO DATA 1.48E-05 Y 93 2.68E-09 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 1.99E-07 NO DATA 9.42E-06 RU 106 2.75E-06 NO DATA 3.48E-07 NO DATA 5.31 E-06 NO DATA 1.78E-04 AG 110M 1.60E-07 1.48E-07 8.79E-08 NO DATA 2.91 E-07 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 2.68E-06 9.71 E-07 3.59E-07 8.06E-07 1.09E-05 NO DATA 1.07E-05 TE 127M 6.77E-06 2.42E-06 8.25E-07 1.73E-06 2.75E-05 NO DATA 2.27E-05 TE 127 1.10E-07 3.95E-08 2.38E-08 8.15E-08 4.48E-07 NO DATA 8.68E-06 TE 129M 1.15E-05 4.29E-06 1.82E-06 3.95E-06 4.80E-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 6.22E-09 1.62E-08 8.63E-08 NO DATA 2.79E-09 TE 132 2.52E-06 1.63E-06 1.53E-06 1.80E-06 1.57E-05 NO DATA 7.71 E-05 130 7.56E-07 2.23E-06 8.80E-07 1.89E-04 3.48E-06 NO DATA 1.92E-06 131 4.16E-06 5.95E-06 3.41 E-06 1.95E-03 1.02E-05 NO DATA 1.57E-06 I 132 2.03E-07 5.43E-07 1.90E-07 1.90E-05 8.65E-07 NO DATA 1.02E-07 I 133 1.42E-06 2.47E-06 7.53E-07 3.63E-04 4.31 E-06 NO DATA 2.22E-06 I 134 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 NO DATA 2.51 E-10 101

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Offsite Dose Calculation Manual (ODCM) 24 TABLE 2.1 Liquid Dose Conversion Factors (DCF): DFjj Page 3 of 3 Ingestion Dose Factors for Adults*

(MREM Per PCI Ingested)

NUCLIDE 13ONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI 135 4.43E-07 1.16E-06 4.28E-07 7.65E-05 1.86E-06 NO DATA 1.31 E-06 Cs 134 6.22E-05 1.48E-04 1.21 E-04 NO DATA 4.79E-05 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 3.70E-05 1.23E-05 2.1IIE-36 Cs 138 5.52E-08 1.09E-07 5.40E-08 NO DATA 8.01 E-08 7.91 E-09 4.65E-13 BA 139 9.70E-08 6.91 E-11 2.84E-09 NO DATA 6.46E-11 3.92E-11 I1.72E-07 BA 140 2.03E-05 2.55E-08 1.33E-06 NO DATA 8.67E-09 1.46E-08 4.18E-05 BA 141 4.71 E-08 3.56E-1 I 1.59E-09 NO DATA 3.31 E-11 2.02E-1 1 2.22E 17 BA 142 2..13E-08 2.19E-11 1.34E-09 NO DATA 1.85E-11 1.24E-1 1 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 '..28E-10 5.82E-1 1 1.45E-1I 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 I1.65E-09 1.22E-06 1.35E-10 NO DATA 5.37E-1 0 NO DATA 4.56E-05 CE 144 4.88E-07 2.04E-07 2.62E-08 NO DATA 1.21 E-07 NO DATA 1.65E-04 PR 143 9.20E-09 3.69E-09 4.56E-10 NO DATA 2.13E-09 NO DATA 4.03E-05 PR 144 3.01E-11 1.25E-11 1.53E-12 NO DATA 7.05E-12 NO DATA 4.33E-18 ND 147 6.29E-09 7.27E-09 4.35E-10 NO DATA 4.25E-09 NO DATA 3.49E.-05 W 187 1.03E-07 8.61 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 commitment over a 50-year period; from Reg. Guide 1.109 (Rev. 1). Additional dose factors for nuclides not included in l:his table may be obtained from NUREG-0172.

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Offsite Dose Calculation Manual (ODCM) 24 TABLE 2.2 Bioaccumulation Factors, BF 1 Bioaccumulation Factors to be Used in the Absence of Site-Specific Data*

(pCi/kg per pCi/liter)

ELEMENT FRESHWATER FISH INVERTEBRATE H 9.OE-01 9.OE-01 C 4.6E+03 9.1 E+03 NA 1.OE+02 2.OE+02 CR 2.OE+02 2.OE+03 MN 4.OE+02 9.OE+04 FE 1.OE+02 3.2E+03 CO 5.OE+01 2.OE+02 NI 1.OE+02 1.OE+02 CU 5.OE+01 4.OE+02 ZN 2.OE+03 1.OE+04 BR 4.2E+02 3.3E+02 RB 2.OE+03 1.OE+03 SR 3.OE+01 1.OE+02 Y 2.5E+01 1.OE+03 ZR 3.3E+00 6.7E+OO NB 3.OE+04 1.OE+02 MO 1.OE+01 1.OE+01 TC 1.5E+01 5.OE+O0 RU 1.OE+01 3.OE+02 RH 1.0E+01 3.0E+02

AG-11Om 2.30E+1 7.70E+2

SB 1.OE+00 1.0E+OO TE 4.OE+02 6.1 E+03 I 1.5E+01 5.OE+OO CS 2.OE+03 1.OE+03 BA 4.OE+OO 2.OE+02 LA 2.5E+01 1.OE+03 CE 1.OE+OO 1.OE+03 PR 2.5E+01 1.OE+03 ND 2.5E+01 1.OE+03 W 1.2E+03 1.OE+01 NP 1.OE+01 4.OE+02

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.

- - Ag bioaccumulation factor value is taken from Reg. Guide 1.109 (Rev. 0), Table A-8.

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Offsite Dose Calculation Manual (ODCM) 24 3.0 TMI LIQUID EFFLUENT WASTE TREATMENT SYSTEMS 3.1 TMI-1 Liquid 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)

Miscellaneous Waste Train

a. Water sources: - Auxiliary Building Sump

- Reactor Building Sump

- Miscellaneous Waste Storage Tank

- Laundry Waste Storage Tank

- Neutralizer Mixing Tank

- Neutralizer Feed Tank

- Used Precoat Tank

- Borated Water Tank Tunnel Sump

- Heat Exchanger Vault Sump

- Tendon Access Galley Sump

- Spent Fuel Pool Room Sump

- TMI-2 Miscellaneous Waste Holdup Tank

b. Liquid Processing - Miscellaneous Waste Evaporator, MWE (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) 104

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Offsite Dose Calculation Manual (ODCM) 24 3.2 Operability of the TMI-1 Liquid Effluent Waste Treatment System 3.2.1 The TMI-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:

a) Miscellaneous Waste Evaporator (WDL-ZI B) or Reactor Coolant Evaporator (WDL-Z1A) b) Waste Evaporator Condensate Demineralizer (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) 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 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 Evaporator Condensate Transfer Pumps.

3.3 TMI-2 Liquid 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 Liquid Radioactive Waste is processed by the TMI-1 system described in Section 3.1 prior to release. In addition, TMI-2 releases water from various sumps and tanks to the river (see Figures 1.1 and 1.2). These processes are governed by plant procedures that encompass proper sampling, sample analysis, and radiation monitoring techniques.

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Offsite Dose Calculation Manual (ODCM) I24 FIGURE 3.1 TMI-1 Liquid Radwaste RC DRAIN lHITTMAN LaL w RECLAIMED WATER SYSTEM 106

6610-PLN-4200.01 Revision 24 FIGURE 3.2 TMI-1 Liquid Waste Evaporators 107

Number TMI- Unit I Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 24 4.0 GASEOU; 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 ODCM Part I Control 2.2.2.1. Table 4.1 lists Gaseous Effluent Release Points and their associated parameters; Figure 4.1 provides a Gaseous Effluent Release Pathway Diagram.

The set points are established to satisfy the more restrictive set point concentration in the following two equations:

500 > S (cj(F)(Kj)(Dv) (eq 4.1.1) aid 3000 > i (c1)(L1 + 1.1 M1)(Dv)(F) (eq 4.1.2) where:

c; = set point concentration based on Xe-133 equivalent, in pCi/cc F = gaseous effluent flowrate at the monitor, in cc/sec K,= total body dose factor, in mrem/yr per pCi/m3 from Table 4.3 Dv = highest sector annual average gaseous atmospheric dispersion factor (X/Q) at or beyond the unrestricted area boundary, in sec/M 3 , from Table 4.4 for station vent releases end Table 4.5 for all other releases, (Condenser off gas, ESF FHB, and ground releases).

Maximum values presently used are 7.17E-7 sec/M 3 at sector NNE for station vent, and 1.16E-5 sec/m3 at sectors N and WNW for all other releases.

L= skin dose factor due to beta emissions from radionuclide i, in mrem/yr per 1 iCi/m3 from Table 4.3.

M= air dose factor due to gamma emissions from radionuclide i, in mrad/yr per PCi/m3 from Table 4.3.

1.1 = mrem skin dose per-mrad air dose.

500 = annual whole body dose rate limit for unrestricted areas, in mrem/yr.

3000 = annual skin dose rate limit for unrestricted areas, in mremlyr.

The set point concentration is further reduced such that the concentration contributions from multiple release points would not combine to exceed ODCM Control limits.

The set point concentration is converted to set point scale units on each radiation monitor using appropriate calibration factors.

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Offsite Dose Calculation Manual (ODCM) 24 This section of the ODCM is implemented by the Radiation Monitor System Set Points procedure and the procedure for Releasing Radioactive Gaseous Waste.

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Offsite Dose (Cal culation Ma nual (ODCM) 24 4.2 TMI-I Particulate and Radioiodine Monitor Set Points Set points for monitors which detect radionuclides other than noble gases are also established to assure that concentrations of these radionuclides in gaseous effluents do not exceed the limits of ODCM Part I Control 2.2.2.1.

Set points are established so as to satisfy the following equations:

1500 > (c,)(F)(Pj)(Dv) (eq 4.2) where:

c; = set point concentration based on 1-131 equivalent, in ptCi/cc F = gaseous effluent flow rate at the monitor, in cc/sec Pi = pathway dose parameter, in mrem/yr per gCi/m3 for the inhalation pathway from Table 4.6. The dose factors are based on the actual individual organ and most restrictive age group (child) (NUREG-0133).

NOTE Appendix A contains Pi calculational methodology.

1500 = annual dose rate limit to any organ from particulates and radioiodines and radionuclides (other than noble gases) with half lives greater than eight days in mrem/yr.

Dv = highest sector annual average gaseous dispersion factor (X/Q or D/Q) 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/Q is used for the inhalation pathway. Maximum values of X/Q presently used are 7.17E-7 sec/m3 for station vent, at sector SE, and 1.16E-5 sec/m3 for all other releases, at sectors N and WNW.

The set point concentration is further reduced such that concentration contributions from mulkiple release points would not combine to exceed ODCM Control limits.

The set point concentration is converted to set point scale units on each radiation monitor us'ng appropriate calibration factors.

This section of the ODCM is implemented by the Radiation Monitor Systems Set Points procedure and the procedure for Releasing Radioactive Gaseous Waste.

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Offsite Dose Calculation Manual (ODCM) 24 4.3 TMI-2 Gaseous Radiation Monitor Set Points TMI-2 Gaseous Radiation Monitors have their set points described in TMI Plant Procedure 101-2.1.

Figure 4.5 provides a gaseous effluent release pathway diagram. Table 4.2 provides TMI-2 Radiation Monitor Data.

These set points are set in accordance with the Controls delineated in Part II of this ODCM.

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Offsite Dose (,calculation Manual (ODCM) 24 4.4 TMI-1 Gaseous Effluent Release Points and Gaseous Radiation Monitor Data TMI-1 has eleven (I1) required effluent gaseous radiation monitors. These are RM-A4, RM-A5, 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 Handling and Auxiliary Building Exhaust RM-A4 is the particulate, radioiodine and gaseous radiation monitor for the TMI-1 Fuel Handling Building Ventilation (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 Figures 4.1 and 4.2). High alarms on RM-A4 or RM-A6 noble gas channels wi'l initiate shutdown of the related building ventilation air supply system. These two radiation monitors 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 TMI-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-A1 5 Condenser Off Gas Exhaust RM-A5 is the gaseous radiation monitor for the TMI-1 Condenser Off Gas exhaust (see Figures 4.1 and 4.4). RM-A1 5 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 Radioiodine Processor Station. These two radiation monitors together satisfy requirements for the Condenser Off Gas release 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 (sea 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 will initiate shutdown of the Waste Gas Decay Tank release in progress. This radiation monitor satisfies requirements for batch gaseous releases to the Station Vent release point.

4.4.5 RM-A9 Reactor Building Purge Exhaust RM-A9 is the particulate, radioiodine and gaseous radiation monitor for the TMI-1 Reactor Building Purge system (see Figures 4.1 and 4.3). This in plant effluent radiation monitor also has an associated 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.

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Offsite Dose Calculation Manual (ODCM) 24 4.4.6 RM-A14 ESF FHB Ventilation System RM-A14 is the gaseous radiation monitor for the TMI-1 Emergency Safeguards Features (ESF) Fuel Handling Building Exhaust system (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 sampler filters. High alarm on RM-A14 noble gas channel will initiate shutdown of the ESF Fuel Handling Building Exhaust System. This radiation monitor satisfies requirements for the ESF Fuel Handling Building Exhaust System release point.

4.4.7 ALC-RMI-18 Chemical Cleaning Facility (CCF) Ventilation Exhaust ALC-RMI-18 is an Victoreen particulate, radioiodine, and gaseous radiation monitor for the Chemical Cleaning building exhaust. This monitor is located in the Chemical Cleaning building on the ground floor, and has an associated sample panel. Sampling for particulate activity is performed off of the monitor.

4.4.8 WHP-RIT-1 Waste Handling and Packaging 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 particulate activity 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 Cleaning and Laundry Maintenance (RLM) Facility 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.

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Offsite Dose C:alculation Manual (ODCM) 24 4.5 TMI-2 Gaseous Effluent Release Points and Gaseous Radiation Monitor Data TMI-2 has three (3) regulatory required gaseous effluent radiation monitors. These are HP-R-,219, 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 TMI-2 ventilation exhaust. This in-plant effluent radiation monitor is located in the TMI-2 Auxiliary Building 328 foot elevation and has an associated sample panel.

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.

L.5.3 HP-R-225 Reactor Building Purge Air Exhaust Duct "A" HP-R-225 is a Victoreen particulate and gaseous radiation monitor for the TMI-2 Reactor Building Purge Air Exhaust System. This in-plant effluent radiation monitor is located in the TMI-2 Auxiliary Building 328' elevation area.

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Offsite Dose Calculation Manual (ODCM) 24 4.6 Control of Gaseous Effluent Releases TMI gaseous effluent combined releases are controlled (per ODCM Part I for TMI-1 and ODCM Part II 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 most 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 ODCM Part I for TMI-1 and ODCM Part II 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 ODCM Part I for TMI-1 and ODCM Part II for TMI-2.

Post-release analyses of samples composited from batch and continuous releases are performed in accordance with ODCM Part I for TMI-1 and ODCM Part II 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 ODCM Part I for TMI-1 and ODCM Part II for TMI-2.

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Number TMI - Unit 1 Radiological Controls Procedure I 661 0-PLN-4200.01 Title Revision No.

Offsite Dose Coalculation Manual (ODCM) 24 TABLE 4.1 TMI-1 Gaseous Release Point and Gaseous Radiation Monitor Data GASEOUS RELEASE RADIATION GASEOUS (F) TERMINATION MONITOR RELEASE FLOW INTERLOCK

-(DETECTOR) LOCATION POINT RECORDER (YES/NO) VALVES YES AH-D-122 306' Elevation Auxiliary YES RM-A6 Auxiliary Bldg Building FR- 50 AH-E-11 Auxliay Bdg.ExhaustA--I YES WDG-V47 RMA-8/9 Bldg. Statio'n FR-I149 AH-E-1 0 RM-A8 Near BWST Vent & FR-150 AH-E-1 I Exhaust Starts MAP-5 Radioiodine I _ _ _Sampler YES 322' Elevation Condenser Starts MAP- I RM-A5 Second Floor Off Gas FR- 113 Radioiodine Turbine Bldg. Exhaust Sampler 322' Elevation Condenser SaSM RM-A15 Second Floor Off Gas FR-1113 Starts MAP-5 Turbine Bldg. Exhaust Radioiodine I . _ Sampler I Waste Gas RM-A7 306' Elevation Decay FR 123 YES Auxiliary Bldg. Tanks WDG-V47 YES Reactor AH-V-1A/B/C/D RMA-8/9 Bldg. Building FR-909/ WDG-534/535 RM-A9 Near BWST Purge FR-148 Starts MAP-5S Exhaust Radioiodine Sampler 331' Elevation ESF Fuel NO RM-A14 ESF FHB Handling FR-1104A/B Manual Outside Chem. Building Actions

[ ~~~~Addition Bldg2. Exhaust _ _ _ _ _ _ _ _ _ _ _ _ _ _

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Offsite Dose Calculation Manual (ODCM) 24 TABLE 4.1 TMI-1 Gaseous Release Point and Gaseous Radiation Monitor Data RELEASE GASEOUS TERMINATION RADIATION INTERLOCK MONITOR GASEOUS (YES/NO)

(DETECTOR) LOCATION RELEASE POINT VALVES Chma CCB Exhaust ALC-RMI-1 8 Cleaning Bldg. SytmN E 304' Elevation. (Typical flow rate is 10,000 cfm)

WHPF WHPF Exhaust YES WHP-RIT-1 Mechanical System WHPF Ventilation Equipmet Room(Typical flow rate Trp lEquipment Room is 7,500 cfm)Trips RLM Exhaust RLM-RM-1 RLM-Mechanical System NONE Equipment Room (Typical flow rate N is 900 cfm)

TABLE 4.2 TMI-2 Gaseous Release Point and Gaseous Radiation Monitor Data RELEASE GASEOUS TERMINATION RADIATION GASEOUS INTERLOCK' MONITOR . RELEASE (YESINO)

(DETECTOR) LOCATION POINT VALVES 328' Elevation Station HP-R-219 Auxiliary Vent NONE Building Exhaust 328' Elevation Station Vent NN HP-R-219A Auxiliary Exhaust NONE Building _____ ___ NONE 328' Elevation Reactor Bldg HP-R-225 Auiir uligPurge Exhaust NONE Auxliay BildngDuct "A"________

117

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Offsite Dose Calculation Manual (ODCM) 24 TABLE 4.3 Dose Factors for Noble Gases and Daughters*

Gamma Beta Total Body Skin Dose Gamma Air Dose Factor(a) Factor(b) Dose Factor Beta Air K. Li Mj Dose Factor (mremlyr per (mremlyr per (mrad/yr per N, Radionuc lide 3) ItCi/m 4iCi/m 3) iCi/m 3 ) (mrad/yr per iCi/m 3 )

Kr-83rn 7.56E-02** 1.93E+01 2.88E+02 Kr-85rn 1.17E+03 1.46E+03 1.23E+03 1.97E+03 Kr-85 1.61 E+01 1.34E+03 1.72E+01 1.95E+03 Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03 Kr-89 1.66E+04 1.01 E+04 1.73E+04 1.06E+04 Kr-9( 1.56E+04 7.29E+03 1.63E+04 7.83E+03 Xe-131 m 9.15E+01 4.76E+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 Xe-1 :S5 1.81 E+03 1.86E+03 1.92E+03 2.46E+03 Xe-137 1.42E+03 1.22E+04 1.51E+03 1.27E+04 Xe-138 8.83E+03 4.13E+03 9.21 E+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 in gaseous effluents. Dose factor values are taken from Regulatory Guide 1.109 (Rev. 1), Table B-1.

- 7.56E-02 = 7.56 x 10.2.

(a) Total body dose factor for gamma penetration depth of 5 cm into the body.

(b) Skin dose factor at a tissue depth or tissue density thickness of 7 mg/cm 2 .

118

Number TMI- Unit I Radiological Controls Procedure 661 O-PLN-4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 24 TABLE 4.4 Atmospheric Dispersion Factors for Three Mile Island

STATION VENT DISTANCE

SECTOR AVERAGE X/Q (IN SEC/M3) 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 5.52E-08 1.91 E-08 5.02E-09 1.88E-09 1.09E-09 NNE 1.70E-07 7.17E-07 3.45E-07 2.00E-07 1.39E-07 5.58E-08 1.70E-08 4.77E-09 1.98E-09 9.69E-10 NE 1.12E-07 1.75E-07 3.26E-07 1.86E-07 1.21 E-07 5.00E-08 1.67E-08 4.67E-09 1.85E-09 9.93E-10 ENE 1.09E-07 2.13E-07 2.67E-07 1.53E-07 1.05E-07 4.31E-08 1.42E-08 4.42E-09 1.59E-09 8.64E-10 E 2.31E-07 1.71 E-07 1.52E-07 1.49E-07 1.06E-07 4.63E-08 1.52E-08 5.19E-09 2.48E-09 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 SE 4.19E-07 3.79E-07 2.53E-07 1.55E-07 1.11E-07 4.82E-08 1.81 E-08 6.84E-09 3.30E-09 2.22E-09 SSE 2.90E-07 3.62E-07 2.55E-07 1.49E-07 1.11 E-07 5.02E-08 1.98E-08 6.97E-09 2.94E-09 1.70E-09 S 1.87E-07 6.47E-08 2.16E-07 1.30E-07 8.65E-08 4.09E-08 1.40E-08 4.96E-09 1.99E-09 1.04E-09 SSW 6.13E-08 4.16E-08 1.56E-07 1.03E-07 6.81E-08 2.72E-08 9.74E-09 3.01E-09 1.50E-09 8.23E-10 SW 5.76E-08 1.14E-07 1.70E-07 1.05E-07 6.93E-08 2.51E-08 9.34E-09 2.72E-09 1.33E-09 8.33E-10 WSW 8.52E-08 3.75E-07 2.14E-07 1.26E-07 7.74E-08 3.08E-08 1.02E-08 3.28E-09 1.39E-09 9.69E-10 W 1.15E-07 5.80E-07 2.88E-07 1.63E-07 1.18E-07 5.23E-08 1.72E-08 5.06E-09 1.98E-09 1.25E-09 WNW 1.41 E-07 6.28E-07 3.30E-07 2.19E-07 1.48E-07 5.68E-08 1.95E-08 6.32E-09 2.16E-09 1.34E-09 NW 1.42E-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 1.45E-09 NNW 1.OOE-07 5.77E-07 3.18E-07 1.80E-07 1.27E-07 5.20E-08 1.77E-08 4.82E-09 2.01E-09 1.22E-09

STATION VENT DISTANCE

SECTOR AVERAGE D/Q (IN M2) (IN METERS) SEASON - ANNUAL SECTOR 610 2413 4022 5631 7240 12067 24135 40225 56315 72405 N 2.51 E-09 8.72E-10 4.84E-10 2.98E-10 2.50E-10 8.57E-11 2.51 E-11 4.98E-12 1.57E-12 7.84E-13 NNE 3.89E-09 1.98E-09 9.54E-10 4.99E-10 3.38E-10 1.10E-10 2.89E-11 6.06E-12 2.10E-12 8.89E-13 NE 2.58E-09 6.70E-10 9.13E-10 4.91E-10 2.97E-10 1.04E-10 2.87E-11 6.01E-12 1.99E-12 9.23E-13 ENE 2.15E-09 5.85E-10 5.54E-10 3.06E-10 2.08E-10 8.30E-11 2.32E-11 5.41E-12 1.63E-12 7.64E-13 E 5.54E-09 1.23E-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 ESE 9.17E-09 2.05E-09 1.51 E-09 8.66E-10 5.11 E-10 1.82E-10 5.77E-11 1.72E-11 7.07E-12 4.07E-12 SE 1.22E-08 2.88E-09 1.84E-09 1.02E-09 6.85E-10 2.60E-10 8.30E-11 2.34E-11 9.42E-12 5.51 E-12 SSE 7.50E-09 1.62E-09 1.08E-09 5.89E-10 4.49E-10 1.87E-10 6.16E-11 1.61 E-11 5.67E-12 2.83E-12 S 3.86E-09 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 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 5.24E-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 W 2.41E-09 1.29E-09 6.81E-10 3.65E-10 2.96E-10 1.12E-10 3.11E-11 6.90E-12 2.26E-12 1.25E-12 WNW 3.20E-09 1.39E-09 7.73E-10 5.91E-10 3.66E-10 1.19E-10 3.43E-11 8.36E-12 2.39E-12 1.29E-12 NW 3.25E-09 1.23E-09 7.39E-10 4.22E-10 2.77E-10 1.14E-10 7.28E-11 7.61 E-12 2.92E-12 1.36E-12 NNW 1.98E-09 9.88E-10 5.71 E-10 3.05E-10 2.23E-10 8.21 E-11 2.41 E-11 4.93E-12 1.72E-12 9.03E-13 DATA FROM 1/1/78 THROUGH 12/31/86 USED IN CALCULATIONS 119

Number TMI - Unit I Radiological Controls Procedure 661 O-PLN-4200.01 Revision No.

Title Offsite Dose Calculation Manual (ODCM) 24 TABLE 4.5 Atmospheric Dispersion Factors for Three Mile Island

GROUND RELEASE DISTANCE

SECTOR AVERAGE X/O (IN SE ,/M) IN METERS) SEASON -ANNUAL 2413 4022 5631 7240 12067 24135 40225 56315 72405 SECTOR 61()

1.13E-06 5.94E-07 3.80E-07 2.38E-07 9.74E-08 3.45E-08 9.28E-09 3.52E-09 2.05E-09 N 1.16E-05 1.1OE-06 5.66E-07 3.41 E-07 2.38E-07 9.55E-08 3.11 E-08 8.94E-09 3.74E-09 1.84E-09 NNE 1.08E-05 9.81 E-07 5.42E-07 3.17E-07 2.1 OE-07 9.01 E-08 3.1 OE-08 8.87E-09 3.54E-09 1.G 1E-09 NE 7.02E-06 9.64E-07 4.92E-07 2.85E-07 1.97E-07 7.82E-08 2.64E-08 8.38E-09 3.04E-09 1.66E-09 ENE 7.14E-06 1.09E-06 5.48E-07 2.91 E-07 1.87E-07 8.40E-08 2.82E-08 9.85E-09 4.75E-09 2.E7E-09 E 8.49E.-06 9.02E-07 4.49E-07 2.57E-07 1.67E-07 7.20E-08 2.77E-08 1.12E-08 5.54E-09 3.E8E-09 ESE 6.91 E.-06 9.06E-07 4.53E-07 2.81 E-07 2.03E-07 8.94E-08 3.33E-08 1.28E-08 6.19E-09 4.18E-09 SE 6.70E-06 9.25E-07 4.91 E-07 2.87E-07 2.08E-07 9.18E-08 3.72E-08 1.32E-08 5.62E-09 3.26E-09 SSE 7.26E:-06 9.08E-07 3.99E-07 2.41 E-07 1.61 E-07 7.31 E-08 2.57E-08 9.23E-09 3.74E-09 1.E-5E-09 S 8.70E.-06 7.01 E-07 2.75E-07 1.86E-07 1.24E-07 5.06E-08 1.82E-08 5.71 E-09 2.87E-09 1.E8E-09 SSW 6.05E:06 5.71 E-07 2.86E-07 1.81E-07 1.22E-07 4.50E-08 1.72E-08 5.12E-09 2.53E-09 1.69E-09 SW 5.94E:-06 7.02E-07 3.60E-07 2.15E-07 1.34E-07 5.50E-08 1.87E-08 6.12E-09 2.62E-09 1.E,3E-09 WSW 8.00E-06 1.07E-06 5.30E-07 3.02E-07 2.05E-07 9.31 E-08 3.15E-08 9.48E-09 3.74E-09 2.'18E-09 W 102E: 05 1.13E-06 5.98E-07 3.67E-07 2.53E-07 1.OOE-07 3.56E-08 1.18E-08 4.07E-09 2.'i4E-09 WNW 1.16E. 05 1.06E-06 5.70E-07 3.53E-07 2.40E-07 1.02E-07 3.82E-08 1.11 E-08 5.14E-09 2.78E-09 NW 1.13E.-05 1.04E-06 5.72E-07 3.27E-07 2.22E-07 9.06E-08 3.20E-08 8.89E-09 3.75E-09 2.29E-09 NNW 1.08E' 05

GROUND RELEASE DISTANCE SE A S O N - A N NJUA L

_ (I N M E T E R S ) _ _ _

SECTOR AVERAGE D/Q (IN M _

2413 4022 5631 7240 12067 24135 40225 56315 72405 SECTOR 610 1.88E-09 8.93E-10 4.82E-10 2.70E-10 8.96E-11 2.53E-11 4.98E-12 1.57E-12 7.134E-13 N 2.30E-08 2.25E-09 1.06E-09 5.42E-10 3.38E-10 1.1OE-10 2.89E-11 6.06E-12 2.1OE-12 8.139E-13 NNE 2.66E--08 2.OOE-09 1.01E-09 5.04E-10 2.98E-10 1.04E-10 2.88E-11 6.01E-12 1.99E-12 9.23E-13 NE 1.75E- 08 1.85E-09 8.65E-10 4.28E-10 2.65E-10 8.57E-11 2.33E-11 5.41E-12 1.63E-12 7.64E-13 ENE 1.681E-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 E 2.881- 08 3.80E-09 1.77E-09 8.79E-10 5.15E-10 1.83E-10 5.78E-11 1.71 E-11 7.06E-12 4.I)6E-12 ESE 3.591_-08 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 SE 4.121- 08 3.23E-09 1.59E-09 8.OOE-10 5.20E-10 1.88E-10 6.18E-11 1.61 E-11 5.66E-12 2.;33E-12 SSE 3.121_-08 2.21 E-09 9.07E-10 4.75E-10 2.86E-10 1.07E-10 3.06E-11 8.1OE-12 2.73E-12 1.23E-12 S 2.651_-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 7.34E-13 SSW 1.451--08 1.10E-09 5.15E-10 2.82E-10 1.71E-10 5.24E-11 1.65E-11 3.62E-12 1.49E-12 8.12E-13 SW 1.42L-08 1.41 E-09 6.82E-10 3.54E-10 2.OOE-10 6.76E-11 1.89E-11 4.58E-12 1.63E-12 9.90E-13 WSW 2.01S'-08 2.16E-09 1.OOE-09 4.91E-10 3.01E-10 1.12E-10 3.11E-11 6.90E-12 2.27E-12 1.25E-12 W 2.55--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 1.29E-12 WNW 2.88E-08 2.15E-09 1.06E-09 5.58E-10 3.41E-10 1.19E-10 3.57E-11 7.61E-12 2.92E-12 1.36E-12 NW 2.78E-08 1.75E-09 8.75E-10 4.24E-10 2.57E-10 8.55E-11 2.42E-11 4.93E-12 1.72E-12 9.D3E-13 NNW 2.17E-08 DATA FROM 1/178 THROUGH 12/31/86 USED IN CALCULATIONS 120

Number TMI - Unit 1 Radioloqical Controls Procedure 661 O-PLN-4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 24 TABLE 4.6 Dose Parameters for Radioiodines and Radioactive Particulate in Gaseous Effluents*

CRITICAL ORGAN CRITICAL ORGAN NUCLIDE ORGAN FACTOR Pi*** NUCLIDE ORGAN FACTOR H-3** TorAL BODY 3.04E-07 1.12E+03 RU-1 03 LUNG 1.79E-04 6.62E+05 C-14 BONE 9.70E-06 3.59E+04 RU-1 05 GI-LLI 2.69E-05 9.95E+04 NA-24 TOTAL BODY 4.35E-06 1.61 E+04 RU-1 06 LUNG 3.87E-03 1.43E+07 P-32 BONE 7.04E-04 2.60E+06 AG-11 OM 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-LILI 3.33E-05 1.23E+05 TE-127M LUNG 4.00E-04 1.48E+06 FE-55 LUNG 3.OOE-05 1.11E+05 TE-127 GI-LLI 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-LLI 6.89E-06 2.55 E+04 CO-60 LUNG 1.91 E-03 7.07E+06 TE-131M GI-LLI 8.32E-05 3.08 --+05 NI-63 BONE 2.22E-04 8.21 E+05 TE-131 LUNG 5.55E-07 2.05 -+03 NI-65 GI-LILI 2.27E-05 8.40E+04 TE-132 LUNG 1.02E-04 3.77--+05 CU-64 GI-ILI 9.92E-06 3.67E+04 1-130 TYHROID 4.99E-04 1.85-+06 ZN-65 LUNG 2.69E-04 9.95E+05 1-131 THYROID 4.39E-03 1.622-+07 ZN-69 GI-ILI 2.75E-06 1.02E+04 1-132 THYROID 5.23E-05 1.94 --+05 BR-83 TOTAL BODY 1.28E-07 4.74E+02 1-133 THYROID 1.04E-03 3.85 --+06 BR-84 TOTAL BODY 1.48E-07 5.48E+02 1-134 THYROID 1.37E-05 5.07.-+04 BR-85 TOTAL BODY 6.84E-09 2.53E+01 1-135 THYROID 2.14E-04 7.92i--+05 RB-86 LIVER 5.36E-05 1.98E+05 CS-134 LIVER 2.74E-04 1.011-+06 RB-88 LIVER 1.52E-07 5.62E+02 CS-1 36 LIVER 4.62E-05 1.71I +05 RB-89 LIVER 9.33E-08 3.45E+02 CS-1 37 BONE 2.45E-04 9.071-+05 SR-89 LUNG 5.89E-04 2.16E+06 CS-138 LIVER 2.27E-07 8.40I-+02 SR-90 BONE 2.73E-02 1.Q1E+08 BA-139 GI-LLI 1.56E-05 5.77I--+04 SR-91 GI-ILI 4.70E-05 1.74E+05 BA-140 LUNG 4.71 E-04 1.741=+06 SR-92 G-l.LI 6.55E-05 2.42E+05 BA-141 LUNG 7.89E-07 2.921=+03 Y-90 GI-l.LI 7.24E-05 2.68E+05 BA-142 LUNG 4.44E-07 1.64I+03 Y-91 M LUNG 7.60E-07 2.81 E+03 LA-140 GI-LLI 6.1 OE-05 2.261-+05 Y-91 LUNG 7.10E-04 2.63E+06 LA-142 GI-LLI 2.05E-05 7.59I-+04 Y-92 GI-LLI 6.46E-05 2.39E+05 CE-141 LUNG 1.47E-04 5.441-+05 Y-93 GI-l.LI 1.05E-04 3.89E+05 CE-143 GI-LLI 3.44E-05 1.27I +05 ZR-95 LUNG 6.03E-04 2.23E+06 CE-144 LUNG 3.23E-03 1.20I--+07 ZR-97 GI-LLI 9.49E-05 3.51 E+05 PR-143 LUNG 1.17E-04 4.331-+05 NB-95 LUNG 1.66E-04 6.14E+05 PR-144 LUNG 4.23E-07 1.572-+03 MO-99 LUNG 3.66E-05 1.35E+05 ND-147 LUNG 8.87E-05 3.28E+05 TC-99M GI-LLI 1.30E-06 4.81 E+03 W-187 GI-LLI 2.46E-05 9.10I+04 TC-101 LUNG 1.58E-07 5.85E+02 NP-239 GI-LLI 1.73E-05 6.40E+04

The listed close parameters are for radionuclides, other than noble gases that may be detected in gaseous effluents. FPi 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-01 33.

Tritium dose factors include an increase of 50% to account for the additional amount of this nuclide abscrbed through the skin.

- - mrem/year per PCi/m3 .

121

-p Number TMI- Unit 1 As ^^^ XA PPA ^ "l Radiological Controls Procedure bb U-rLN-4ZUU.U1 Title Revision No.

OMsite Dose Calculation Manual (ODCM) 24 FIGURE 4.1 TMI-1 Gaseous Effluent Pathways 122

Number TMI - Unit 1 Radiological Controls Procedure 661 O-PLN-4200.01 Title Revision No.

Offsite Dose C-alculation Manual (ODCM) 24 FIGURE 4.2 TMI-1 Auxiliary and Fuel Handling Buildings Effluent Pathways 123

I0 Number TMI - Unit 1 Radiologqical Controls Procedure 661 O-PLN-4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 24 FIGURE 4.3 TMI-1 Reactor Building Effluent Pathway 170 REACTOR BUILDING PURGE EXHAUST RADIATION MONITORS AND SAMPLING STATIONS REACTOR BUILDING S"G-l R*G-13 FITERS crNPLmmInFM REACTOR BJLUM

$*tK SYSMD PARIDIAT/TRIIA IOD(/ I~K GA4S .F=PARUA ]

A=ABMUTE C=DW 124

Number TMI- Unit I Radioloqical Controls Procedure 661 O-PLN-4200.01 Title D Revision No.

Oftfite Dose Clalculation Manual (ODCM) 24 FIGURE 4.4 TMI-1 Condenser Offgas Effluent Pathway CONDENSER OFF GAS STACK CONDENSER OFF GAS EXHAUST RADIATION MONITORS AND SAMPLING STATIONS 125

661 0-PLN-4200.01 Revision 24 FIGURE 4.5 TMI-2 Gaseous Effluent Filtration System/Pathways STATION VENT 0 . -142.COO CM RB BREATHER I__ _ _ _ _ _ _ _ _ _ _ _

I UNIT 2 EXHAUST AIR FLOW AND RMS SCHEMATIC 126

Number TMI - Unit I Radioloqical Controls Procedure 661 O-PLN-4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 24 5.0 GASEOIJS EFFLUENT DOSE ASSESSMENT 5.1 Gaseous Effluents - Instantaneous Release Limits 5.1.1 Noble Gases For noble gases, the following equations apply for total body and skin dose rate at the unrestricted area boundary:

5.1.1.1 Total Body Dose Ratet, = A (Ka) x (Dv) x (Qu) (eq 5.1 .1.1) where:

Dose Ratet b = instantaneous total body dose rate limit, at the site boundary, in mrem/yr.

= total body dose factor due to gamma emissions for each identified noble gas radionuclide, in mrem/yr per PCi/M3 from Table 4.3.

Dv = highest sector annual average gaseous dispersion factor (X/Q) at or beyond the unrestricted area boundary, in sec/M 3 , from Table 4.4 for station vent releases; and Table 4.5 for all other releases (Condenser Off Gas, ESF FHB, and ground releases). Maximum values presently in use are 7.17E-7 sec/M 3 at sector NNE for station vent, and 1.16E-5 secIM3 for all other releases, at sectors N and WNW.

Qj= Release rate of radionuclide, i, in pCi/sec as determined by sampling and analysis. Calculated using the concentration of noble gas radionuclide, i, in pCi/cc, times the release pathway flow rate, in cc/second.

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Offsite Dose Calculation Manual (ODCM) 1 24 5.1.1.2 Skin Dose Ratesk = £ (Li + 1.1 MI) X (Dv) X (Q1) (eq 5.1.1.2) where:

Dose Ratesk = instantaneous mrem/year skin dose rate limit, at the site boundary, in mrem/yr.

L,= skin dose factor due to beta emissions for each identified noble gas radionuclide, in mrem/yr per pcCi/M 3 from Table 4.3.

Mi = air dose factor due to gamma emissions for each identified noble gas radionuclide, in mrad/yr per pCi/M 3 from Table 4.3.

1.1 = mrem skin dose per mrad air dose. Converts air dose to skin dose.

Qj = release rate of radionuclide, i, in iiCi/sec, as determined by sampling and analysis. Calculated using the concentration of noble gas radionuclide, i, in [tCi/cc, times the release pathway flow rate, in cc/second.

Dv = highest sector annual average gaseous dispersion factor (X/Q) at or beyond the unrestricted area boundary, in sec/M 3 , from Table 4.4 for station vent releases; and Table 4.5 for all other releases (Condenser Off Gas, ESF FHB, and ground releases). Maximum values presently in use are 7.17E-7 sec/iM3 at sector NNE for station vent, and 1.16E-5 sec/M 3 for all other releases, at sectors N and WNW.

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Number TMI - Unit 1 Radiological Controls Procedure 661 0-PLN-4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 24 5.1.2 lodine-131, Iodine-133, Tritium and Radionuclides in Particulate Form, with Half-Lives Greater than 8 Days For 1-131, 1-133, Tritium and Radionuclides in Particulate Form, with half-lives greater than 8 days, the following equation applies:

Dose Ratelp = (Pi) (Dv) (Qi) (eq 5.1.2) where:

Dose Ratelp = mrem/year organ dose rate.

Pi = 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 VICi/m 3, from Table 4.6. The dose factors are based on the critical individual organ and most restrictive age group (child).

Dv = highest sector annual average gaseous dispersion factor (X/Q or D,/Q) at or beyond the unrestricted area boundary, in sec/M 3 , from Table 4.4 for the station vent releases and Table 4.5 for all other releases. X/Q is used for the inhalation pathway. Maximum values of X/Q presently used are 7.17E-7 sec/M 3 for station vent, at sector NNE, and 1.1 6E-5 sec/M 3 for all other releases, at sectors N and WNW.

Qj= release rate of each radionuclide, i, in pCi/sec. Calculated using the concentration of each radionuclide, i, in pCi/cc, times the release pathway flow rate, in cc/second.

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Number TMI- Unit I Radioloqical Controls Procedure 6610-PLN-4200.01 Title . Revision No.

Offsite Dose Calculation Manual (ODCM) 24 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 (Mi) x (Dv) x (Qi) (eq 5.2.1) and Dose 3= (3.17E-8) x (N1) x (Dv) x (Qi) (eq 5.2.2) where:

Dose r = mrad gamma air dose due to gamma emissions from noble gas radionuclides.

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 iCil/m3 , from Table 4.3.

N1 = air dose factor due to beta emissions for each identified noble gas radionuclide, in mrad/yr per ACi/M 3 , from Table 4.3.

Dv = highest sector annual average gaseous dispersion factor, X/Q, at or beyond the unrestricted area boundary, in sec/m 3 . 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/Q presently used are 7.17E-7 sec/m 3 for station vent at sector NNE, and 1.1 6E-5 sec/m3 for all other releases at sectors N or WNW.

Qj = release of noble gas radionuclide, i, in gCi, over the specified time period, (pCi/second

seconds).

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

NOTE If the methodology in this section is used in determining dose to an individual, rather than air dose due to noble gases, substitute Ki, from Table 4.3, for Mi, and (Li + 1.1 Mi) for Ni.

130

r Number LUnitI[U TM[UII -~d [U.UIU E LEtU U C&4n ni LI A'Inn n4 I rlologIcalUd %ontrolsUZ mroceureU: Wu a W-r L_~reuV.W I Title Revision No.

Offsite Dose Calculation Manual (ODCM) 24 5.2.2 lodine-131, lodine-1 33, Tritium and Radionuclides in Particulate Form, with Half-Lives Greater than 8 Days The dose to an individual from 1-131, 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-C) x i (RI) (Dv) (Q1) (eq 5.2.2) where:

Dose, = dose to all real pathways, p, to organ, o, of an individual in age group, a, from 1-131,1-133, Tritium and Radionuclides in Particulate Form, with half-lives greater than 8 days, in mrem, during any desired time period.

Ri = the dose factor for each identified radionuclide, i, pathway, p, age group, a, and organ, o, in mrem/yr per IiCi/m3 for the inhalation pathway and m2 -

mrem/yr per pCi/sec for other pathways, from Tables 5.2 to 5.7.

NOTE Since there is minimal or no elemental iodine released from the condenser off-gas air ejector (see NUREG-0017) all Iodine R,values for 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 iodines.

I NOTE I Tritium, H-3, dose factor is mremiyear per PCi/M 3 for all pathways.

Dv = highest sector annual average gaseous dispersion factor (X/Q) at or beyond the unrestricted area boundary, in sec/M 3 , for the inhalation pathway, and D/Q, in M2, for other pathways. Table 4.4 is used to derive the values for station vent releases and Table 4.5 is used to derive the values for all other releases. The values used to calculate site bou idary and critical receptor doses are as follows:

Station Vent Releases - Boundary Inhalation X/Q 7.17 E-7 Meat D/Q 1.22 E-8 Ground D/Q. 1.22 E-8 Cow/Milk/Infant D/Q 1.22 E-8 Vegetation D/Q 1.22 E-8 Station Vent Releases - Critical Receptor Inhalation X/Q 7.2 E-7 Meat D/Q 4.6 E-9 Ground DIQ 7.8 E-9 Cow/Milk/Infant D/Q 3.1 E-9 Vegetation D/Q 8.9 E-9 131

Number TMI- Unit I Radiological Controls Procedure I 661 0-PLN-4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 24 Ground or Other Releases - Boundary Inhalation X/Q 1.16 E-5 Meat D/Q 4.12 E-8 Ground D/Q 4.12 E-8 Cow/Milk/Infant D/Q 4.12 E-8 Vegetation D/Q 4.12 E-8 Ground or Other Releases - Critical Receptor Inhalation X/Q 1.2 E-5 Meat D/Q 9.2 E-9 Ground D/Q 3.0 E-8 Cow/Milk/Infant D/Q 6.3 E-9 Vegetation DIQ 2.6 E-8 Dv(H-3) = In the case of H-3 only the X/Q's above are used for all pathways.

Qj = release of 1-131, 1-133, Tritium and Radionuclides, i, in Particulate Form with half-lives greater than 8 days, in ptCi, cumulative over the specified time period (pCi/second

seconds).

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

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Number TMI - Unit 1 Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 24 5.3 Gaseous Radioactive SVstem Dose Calculations Once per Month IDDCM Part I Control 2.2.2.4 and TMI-2 PDMS Tech Spec Section 6.7.4.a.6 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 closes due to the gaseous effluent releases from the site would exceed:

0.2 mrad to air from gamma radiation; or 0.4 mrad to air from beta radiation; or 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-to-date 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 release during the period for which the projection is made. If these projected doses exceed any of the values listed above, appropriate portions of the TMI-1 Gaseous Waste Treatment System, as defined in Section 6.0, or appropriate portions of the TMI-2 Gaseous Effluent Filtration System as shown on

igure 4.5, shall be used to reduce radioactivity levels prior to release.

At the discretion of Radiological Engineering, time periods other than the current quarter-to-date

-nay be used to project doses if the dose per day in the current quarter-to-date is not believed to be representative of the dose per day projected for the next month.

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Offsite Dose Calculation Manual (ODCM) 24 5.4 Alternative Dose Calculational Methodologies for Gaseous Effluents As an alternative to the methods described above, the 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 Regulatory Guide 1.109 (Rev. 1) and/or actual site specific data can be used where applicable.

The onsite, on-line computerized system for tracking gaseous effluent dose uses annual average gaseous dispersion factors. As an alternative dose calculational methodology. TMI calculates doses using an advanced class "A" dispersion model called SEEDS (simplified environmental effluent dosimetry system).

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 accurately assess the dispersion of effluents in the atmosphere. Combining this assessment of dispersion with TMI effluent data for each unit, postulated maximum hypothetical doses to the public are calculated.

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Offsite Dose Calculation Manual (ODCM) .24 TABLE 5.2.1 Pathway Dose Factors, Ri AGE GROUP: INFANT PATHWAY: INHALATION NUCLIDE -

1 ORGAN DOSE FACTORS; mrem/year per IICi/m3 BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 O.OOE+00 6.47E+02 6.47E+02 6.47E+02 6.47E+02 6.47E+02 6.47E+02 C-14 2.65E+04 5.31 E+03 5.31 E+03 5.31 E+03 5.31 E+03 5.31 E+03 5.31 E+03 CR-51 O.OOE+00 0.00E+00 8.95E+01 5.75E+01 1.32E+01 1.28E+04 3.57E+02 MN-54 O.OOE+00 2.53E+04 4.98E+03 0.OOE+00 4.98E+03 1.OOE+06 7.06E+03 FE-55 1.97E+04 1.17E+04 3.33E+03 0.OOE+00 0.OOE+00 8.69E+04 1.09E+03 FE-59 1.36E+04 2.35E+04 9.48E+03 0.OOE+00 0.OOE+00 1.02E+06 2.48E+04 CO-58 0.00E+00 1.22E+03 1.82E+03 0.OOE+00 0.OOE+00 7.77E+05 1.11E+04 CO-60 0.OOE+00 8.02E+03 1.18E+04 0.OOE+00 0.OOE+00 4.51 E+06 3.19E+04 Nl-63 3.39E+05 2.04E+04 1.16E+04 0.00OE+00 0.OOE+00 2.09E+05 2.42E+03 ZN-65 1.93E+04 6.26E+04X 3.11E+04 0.OOE+00 3.25E+04 6.47E+05 5.14E+04 RB-86 0.OOE+00 1.90E+05 ; 8.82E+04 0.OOE+00 0.OOE+00 0.OOE+00 3.04E+03 SR-89 3.98E+05 0.00E+0C 1.14E+04 0.OOE+00 0.OOE+00 2.03E+06 6.40E+04 SR-90 4.09E+07 0.OOE+00 ) 2.59E+06 0.OOE+00 0.OOE+00 1.12E+07 1.31E+05 Y-91 5.88E+05 0.00E+00) 1.57E+04 0.OOE+00 0.OOE+00 2.45E+06 7.03E+04 ZR-95 1.15E+05 2.79E+04 2.03E+04 0.OOE+00 3.11E+04 1.75E+06 2.17E+04 NB-95 1.57E+04 6.43E+03 3.78E+03 0.OOE+00 4.72E+03 4.79E+05 1.27E+04 RU-103 2.02E+03 0.OOE+00 6.79E+02 0.OOE+00 4.24E+03 5.52E+05 1.61E+04 RU-1 06 8.68E+04 0.OOE+00 1.09E+04 0.OOE+00 1.07E+05 1.16E+07 1.64E+05 AG-1i OM1 9.98E+03 7.22E+03 5.OOE+03 0.00E+00 1.09E+04 3.67E+06 3.30E+04 TE-1251\4 4.76E+03 1.99E+03 6.58E+02 1.62E+03 0.OOE+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 TE-1291\M 1.41E+04 6.09E+03 2.23E+03 5.47E+03 3.18E+04 1.68E+06 6.90E+04 1-131 3.79E+04 4.44E+04 I1.96E+04 1.48E+07 5.18E+04 0.OOE+00 1.06E+03 1-133 1.32E+04 1.92E+04 5.60E+03 3.56E+06 2.24E+04 0.OOE+00 2.16E+03 CS-1 34 3.96E+05 7.03E+05 7.45E+04 0.OOE+00 1.90E+05 7.97E+04 1.33E+03 CS-136 4.83E+04 1.35E+05 5.29E+04 0.OOE+00 5.64E+04 1.18E+04 1.43E+03 CS-1 37 5.49E+05 6.12E+05 4.55E+04 0.OOE+00 1.72E+05 7.13E+04 1.33E+03 BA-140 5.60E+04 5.60E+01 2.90E+03 0.OOE+00 1.34E+01 1.60E+06 3.84E+04 CE-141 2.77E+04 1.67E+04 1.99E+03 0.OOE+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+05 9.84E+06 1.48E+05 PR-143 1.40E+04 5.24E+03 6.99E+02 0.OOE+00 1.97E+03 4.33E+05 3.72E+04 ND-147 7.94E+03 8.13E+03 5.OOE+02 0.OOE+00 3.15E+03 3.22E+05 3.12E+04 135

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Offsite Dose Calculation Manual (ODCM) 24 TABLE 5.2.2 Pathway Dose Factors, Ri AGE GROUP: CHILD PATHWAY: INHALATION ORGAN DOSE FACTORS; mrem/year per piCi/m 3 NUCLIDE --_-----_----___---____---___---

_ BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 0.OOE+00 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 1.12E+03 C-14 3.59E+04 6.73E+03 6.73E+03 6.73E+03 6.73E+03 6.73E+03 6.73E+03 CR-51 0.OOE+00 0.00E+00 1.54E+02 8.55E+01 2.43E+01 1.70E+04 1.08E+03 MN-54 0.OOE+00 4.29E+04 9.51 E+03 0.OOE+00 1.00E+04 1.58E+06 2.29E+04 FE-55 4.74E+04 2.52E+04 7.77E+03 0.00E+00 0.00E+00 1.11E+05 2.87E+03 FE-59 2.07E+04 3.34E+04 1.67E+04 0.OOE+00 0.00E+00 1.27E+06 7.07E+04 CO-58 0.OOE+00 1.77E+03 3.16E+03 0.O0E+00 0.00E+00 1.11E+06 3.44E+04 CO-60 0.OOE+00 1.31 E+04 2.26E+04 0.OOE+00 0.00Eo00 7.07E+06 9.62E+04 NI-63 8.21 E+05 4.63E+04 2.80E+04 0.OOE+00 0.00E+00 2.75E+05 6.33E+03 ZN-65 4.26E+04 1.13E+05 7.03E+04 0.00E+00 7.14E+04 9.95E+05 1.63E+04 RB-86 0.00E+00 1.98E+05 1.14E+05 0.00E+OD 0.00E+0 0.OOE+00 7.99E+03 SR-89 5.99E+05 0.00E+00 1.72E+04 0.00E+00 0.00E+00 2.16E+06 1.67E+05 SR-90 1.01 E+08 0.OOE+00 6.44E+06 0.OOE+00 0.OOE+00 1.48E+07 3.43E+05 Y-91 9.14E+05 0.00E+O0 2.44E+04 0.OOE+00 0.OOE+00 2.63E+06 1.84E+05 ZR-95 1.90E+05 4.18E+04 3.70E+04 0.OOE+0O 5.96E+04 2.23E+06 6.11E+04 NB-95 2.35E+04 9.18E+03 6.55E+03 0.OOE+00 8.62E+03 6.14E+05. 3.70E+04 RU-103 2.79E+03 0.OOE+00 1.07E+03 0.OOE+00 7.03E+03 6.62E+05 4.48E+04 RU-106 1.36E+05 0.OOE+00 1.69E+04 0.OOE+00 1.84E+05 1.43E+07 4.29E+05 9.1

_4E_3 AG-I1 OM 1.69E+04 1.14E+04 9.14E+03 0.00E+00 2.12E+04 5.48E+06 1.OOE+05 TE-125M 6.73E+03 2.33E+03 9.14E+02 1.92E+03 0.O0E+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 TE-129M 1.92E+04 6.85E+03 3.04E+03 6.33E+03 5.03E+04 1.76E+06 1.82E+05 1-131 4.81 E+04 4.81 E+04 2.73E+04 1.62E+07 7.88E+04 0.OOE+00 2.84E+03 1-133 1.66E+04 2.03E+04 7.70E+03 3.85E+06 3.38E+04 0.OOE+00 5.48E+03 6.51 E_05 ________ _ _ _ _ _

CS-134 6.51 E+05 1.01 E+06 2.25E+05 0.00E+00 3.30E+05 1.21E+05 3.85E+03 CS-1 36 6.51 E+04 1.71 E+05 1.16E+05 0.O0E+00 9.55E+04 1.45E+04 4.18E+03 CS-137 9.07E+05 8.25E+05 1.28E+05 0.OOE+00 2.82E+05 1.04E+05 3.62E+03 BA-140 7.40E+04 6.48E+01 4.33E+03 0.OOE+00 2.11 E+01 1.74E+06 1.02E+05 CE-141 3.92E+04 1.95E+04 2.90E+03 0.OOE+00 8.55E+03 5.44E+05. 5.66E+04 CE-144 6.77E+06 2.12E+06 3.61 E+05 0.OOE+00 1.17E+06 1.20E+07 3.89E+05 PR-143 1.85E+04 5.55E+03 9.14E+02 0.OOE+00 3.OOE+03 4.33E+05 9.73E+04 ND-147 1.08E+04 8.73E+03 6.81E+02 0.OOE+00 4.81E+03 3.28E+05 8.21E+04 136

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Offsite Dose C alculation Manual (ODCM) 24 TABLE 5.2.3 Pathway Dose Factors, RI AGE GROUP: TEEN PATHWAY: INHALATION NUCLIDE 1---ORGAN DOSE FACTORS; mrem/year per pCi/m 3 J BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 0.OOE+00 1.27E+03 1.27E+03 1.27E+03 1.27E+03 1.27E+03 1.27E+03 C-14 2.60E+04 4.87E+03 4.87E+03 4.87E+03 4.87E+03 4.87E+03 4.87E+03 CR-51 0.OOE+00 0.O0E+00 1.35E+02 7.50E+01 3.07E+01 2.1OE+04 3.OOE+03 MN-54 0.OOE+00 5.11E+04 8.40E+03 0.OOE+00 1.27E+04 1.98E+06 6.68E+04 FE-55 3.34E+04 2.38E+04 5.54E+03 0.OOE+00 0.OOE+00 1.24E+05 6.39E+03 FE-59 1.59E+04 3.70E+04 1.43E+04 0.00E+00 0.OOE+00 1.53E+06 1.78E+05 CO-58 0.OOE+00 2.07E+03 2.78E+03 0.OOE+00 0.OOE+00 I1.34E+06 9.52E+04 CO-60 O.OOE+00 1.51 E+04 1.98E+04 0.OOE+00 0.OOE+00 8.72E+06 2.59E+05 Nl-63 5.80E+05 4.34E+04 1.98E+04 0.00E+00 0.OOE+00 3.07E+05 1.42E+04 ZN-65 3.86E+04 1.34E+05 6.24E+04 0.OOE+00 8.64E+04 1.24E+06 4.66E+04 RB-86 0.OOE+00 1.90E+05 8.40E+04 O.0OE+O0 0.OOE+00 0.00E+00 1.77E+04 SR-89 4.34E+05 0.OOE+00 1.25E+04 0.OOE+00 0.00E+00 2.42E+06 3.71 E+05 SR-90 1.08E+08 0.OOE+00 6.68E+06 0.OOE+00 0.OOE+00 1.65E+07 7.65E+05 Y-91 6.61 E+05 0.OOE+00 1.77E+04 0.OOE+00 0.OOE+00 2.94E+06 4.09E+05 ZR-95 1.46E+05 4.58E+04 3.15E+04 0.OOE+00 6.74E+04 2.69E+06 1.49E+05 NB-95 1.86E+04 1.03E+04 5.66E+03 0.OOE+O0 1.OOE+04 7.51 E+05 9.68E+04 RU-103 2.1 OE+03 0.OOE+00 8.96E+02 O.OOE+00 7.43E+03 7.83E+05 1.09E+05 RU-1 06 9.84E+04 0.OOE+00 1.24E+04 0.OOE+00 1.90E+05 1.61E+07 9.60E+05 AG-101bM 1.38E+04 1.31 E+04 7.99E+03 0.OOE+00 2.50E+04 6.75E+06 2.73E+05 TE-125M 4.88E+03 2.24E+03 6.67E+02 1.40E+03 0.OOE+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 TE-129M 1.39E+04 6.58E+03 2.25E+03 4.58E+03 5.19E+04 1.98E+06 4.05E+05 1-131 3.54E+04 4.91 E+04 2.64E+04 I1.46E+07 8.40E+04 0.00E+00 6.49E+03 1-133 1.22E+04 2.05E+04 6.22E+03 2.92E+06 3.59E+04 0.OOE+00 1.03E+04 CS-1 34 5.02E+05 1.13E+06 5.49E+05 0.OOE+00 3.75E+05 1.46E+05 9.76E+03 CS-1 36 5.15E+04 1.94E+05 1.37E+05 0.00 E+00 1.10E+05 1.78E+04 1.09E+04 CS-1 37 6.70E+05 8.48E+05 3.11E+05 0.00E+00 3.04E+05 1.21E+05 8.48E+03 BA-1 40 5.47E+04 6.70E+01 3.52E+03 0.OOE+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 CE-144 4.89E+06 2.02E+06 2.62E+05 0.OOE+00 1.21E+06 1.34E+07 8.64E+05 PR-143 1.34E+04 5.31 E+03 6.62E+02 0.OOE+00 3.09E+03 4.83E+05 2.14E+05 ND-147 7.86E+03 8.56E+03 5.13E+02 0.OOE+00 5.02E+03 3.72E+05 1.82E+05 137

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Offsite Dose Calculation Manual (ODCM) 24 TABLE 5.2.4 Pathway Dose Factors, RI AGE GROUP: ADULT PATHWAY: INHALATION NUCLIDE 1---ORGAN DOSE FACTORS; mrem/year per ptCi/m 3 BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 0.OOE+00 1.26E+03 1.26E+03 1.26E+03 1.26E+03 1.26E+03 1.26E+03 C-14 1.82E+04 3.41 E+03 3.41 E+03 3.41 E+03 3.41 E+03 3.41 E+03 3.41 E+03 CR-51 0.OOE+00 0.00E+00 1.OOE+02 5.95E+01 2.28E+01 1.44E+04 3.32E+03 MN-54 O.OE+00 3.96E+04 6.30E+03 0.OOE+00 9.84E+03 1.40E+06 7.74E+04 FE-55 2.46E+04 1.70E+04 3.94E+03 0.OOE+00 0.OOE+00 7.21 E+04 6.03E+03 FE-59 1.18E+04 2.78E+04 1.06E+04 0.OOE+00 0.0OE+0O 1.02E+06 1.88E+05 CO-58 O.OOE+00 I1.58E+03 2.07E+03 .0OOE+OO .0.OE-'-O 9.28E+ 05 1.06E+05 CO-60 0.00E+00 1.15E+04 1.48E+04 0.OOE+00 Q.OOE+00 5.97E+106 2.85E+05 NI-63 4.32E+05 3.14E+04 1.45E+04 0.OOE+00 .0.OE+OO I1.78E+~05 1.34E+04

E+--

ZN-65 3.24E+04 I1.03E+05 4.66E+04 6.90E+04 8.64E+I 05 5.34E+04 0.OOE+00 RB-86 0.00E+00 1.35E+05 5.90E+04 0.OOE+i 00 1.66E+04 0.00E+OO 0.OOE+OO SR-89 3.04E+05 8.72E+03 1.40E+106 3.50E+05 O.OOE+OD ________

.0QOE+OO 0.OOE+00 ___________.

SR-90 9.92E+07 6.1 OE+06 0.002+00 .9.60E+I06 7.22E+05 O.OOE+OD 0.OOE+00 Y-91 4.62E+05 1.24E+04 1.70E+106 3.85E+05 0.OOE+OO ZR-95 1.07E+05 3.44E+04 2.33E+04 5.42E+04 1.77E+106 1.50E+05 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 RU-1 03 1.53E+03 0.00E+00 6.58E+02 0.00E+00 5.83E+03 5.05E+( )5 1.10E+05 RU-106 6.91 E+04 O.OOE+00 8.72E+03 0.00E+00 1.34E+05 9.36E+( 06 9.12E+05 AG-I1 OM 1.08E+04 1.OOE+04 5.94E+03 0.00E+00 1.97E+04 4.63E+06 3.02E+05 TE-125M 3.42E+03 1.58E+03 4.67E+02 1.05E+03 1.24E+04 3.14E+05 7.06E+04 TE-127M 1.26E+04 5.77E+03 1.57E+03 3.29E+03 4.58E+04 9.60E+05 1.50E+05 TE-129M 9.76E+03 4.67E+03 1.58E+03 3.44E+03 3.66E+04 1.16E+06 3.83E+05 1-131 2.52E+04 3.58E+04 2.05E+04 1.19E+07 6.13E+04 0.00E+00 6.28E+03 1-133 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 8.48E+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 0.0OE+00 8.56E+04 1.20E+04 1.17E+04 CS-137 4.78E+05 6.21E+05 4.28E+05 0.00E+00 2.22E+05 7.52E+04 8.40E+03 BA-140 3.90E+04 4.90E+01 2.57E+03 0.00E+00 1.67E+01 1.27E+06 2.18E+05 CE-141 1.99E+04 1.35E+04 1.53E+03 0.OOE+00 6.26E+03 3.62E+05 1.20E+05 CE-144 3.43E+06 1.43E+06 1.84E+05 0.00E+00 8.48E+05 7.78E+06 8.16E+05 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+02 0.00E+00 3.56E+03 2.21E+05 1.73E+05 138

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Offsite Dose Calculation Manual (ODCM) 24 -

TABLE 5.3.1 Pathway Dose Factors, Ri AGE GROUP: ALL PATHWAY: GROUND PLANE

r------------------------------

ORGAN DOSE FACTORS*

,NUCLIDE -- -- -- -- -- -- --

T.BODY SKIN F -____ __ __ -- _--------t H-3 0.00E+00 0.OOE+00

,C-14 0.OOE+00 0.OOE+00 CR-51 4.65E+06 5.50E+06

,IMN-54 1.39E+09 1.62E+09 FE-55 0.OOE+00 0.O0E+00 FE-59 2.73E+08 3.21 E+08 CO-58 3.79E+08 4.44E+08

'CO-60 2.15E+10 2.53E+10 Nl-63 0.OOE+00 0.OOE+0O aZN-65 7.47E+08 8.59E+08 RB-86 8.97E+06 1.03E+07 SR-89 2.16E+04 2.51 E+04 SR-90 0.00E+00 0.00E+00

,Y-91 1.07E+06 1.21E+06 aZR-95 2.45E+08 2.84E+08 NB-95 1.37E+08 1.61E+08 aRU-103 1.08E+08 1.26E+08 a RU-106 4.22E+08 5.06E+08 a r------- ---------- -

aAG-1 1OM 3.44E+09 4.01 E+09 TE-125M 1.55E+06 2.13E+06 TE-127M 9.17E+04 1.08E+05 TE129M I.98E+07 2.31 E+07 a

,1-131 1.72E+07 2.09E+07 a1-133 2.45E+06 2.98E+06 a CS-134 6.86E+09 8.OOE+09 a CS-136 1.51 E+08 1.71 E+08 CS-137 1.03E+10 1.20E+10 r------------------_____

aBA-140 2.06E+07 2.36E+07 ;

CE-141 1.37E+07 1.54E+07

' CE-144 6.96E+07 8.05E+07 PR-143 0.OOE+00 0.OOE+00 aND-147 8.39E+06 1.01 E+07 a

m- mrem/year per pCi/sec.. 139

Number TMI - Unit 1 Radiological Controls Procedure 661 O-PLN-4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 24 TABLE 5.4.1 Pathway Dose Factors, Ri AGE GROUP: INFANT PATHWAY: GRASS-COW-MILK U ORGAN DOSE FACTORS; m2 - mrem/year per tCi/sec NUCLIDE BONE LIVER T.BODY THYROID KIDY LG G .--

BONE LIVER T.BODY THYROID KIDNEY LUNG Gl-LLI H-3 0.00E+00 2.38E+03 2.38E+03 2.38E+03 2.38E+03 2.38E+03 2.38E+03 C-14 2.34E+09 5.OOE+08 5.00E+08 5.00E+08 5.00E+08 5.00E+08 5.OOE+08 CR-51 0.OOE+00 0.00E+00 1.61 E+05 1.05E+05 2.30E+04 2.05E+05 4.70E+06 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.OOE+00 0.00E+00 4.27E+07 1.11E+07 FE-59 2.25E+08 3.93E+08 1.55E+08 0.OOE+00 0.00E+00 1.16E+08 1.88E+08 CO-58 0.00E+00 2.43E+07 7 6.06E+07 0.00E+00 0.00E+00 0.00E+00 6.05E+07 CO-60 0.00E+00 8.83E+07

2.08E+08 0.OOE+00 0.OOE+00 0.00E+00 2.10E+08 NI-63 3.50E+10 2.16E+09 3 1.21 E+09 0.OOE+00 0.OOE+00 0.00E+00 1.08E+08 ZN-65 5.56E+09 1.91E+10 8.79E+09 0.OOE+00 9.24E+09 0.00E+00 1.61E+10 RB-86 0.00E+00 2.23E+10 1.1OE+10 0.00E+00 0.00E+00 0.00E+00 5.70E+08 SR-89 1.26E+10 0.OOE+00 3.62E+08 0.00E+00 0.00E+00 0.00E+00 2.59E+08 SR-90 1.22E+11 0.00E+00 3.10E+10 0.00E+00 0.00E+00 0.OOE+00 1.52E+09 Y-91 7.34E+04 0.00E+00 1 .95E+03 0.00E+00 0.00E+00 0.00E+00 5.26E+06 ZR-95 6.81 E+03 1.66E+03 1.18E+03 0.00E+00 1.79E+03 0.00E+00 8.27E+05 NB-95 5.94E+05 2.45E+05 1.41 E+05 0.00E+00 1.75E+05 0.00E+00 2.07E+08 RU-103 8.68E+03 0.OOE+00 2.90E+03 0.00E+00 1.81 E+04 0.00E+00 1.06E+05 RU-106 1.91E+05 0.OOE+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 TE-125M 1.51E+08 5.05E+07 2.04E+07 5.08E+07 0.00E+00 0.OOE+00 7.19E+07 TE-127M 4.22E+08 1.40E+08 5.10E+07 1.22E+08 1.04E+09 0.00E+00 1.70E+08 TE-129M 5.58E+08 1.91E+08 8.59E+07 2.14E+08 1.39E+09 0.00E+00 3.33E+08 1-131 2.72E+09 3.21 E+09 1.41 E+09 1.05E+12 3.75E+09 0.OOE+00 1.15E+08 1-133 3.63E+07 5.29E+07 1.55E+07 9.62E+09 6.22E+07 0.00E+00 8.96E+06 CS-134 3.65E+10 6.81E+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.OOE+00 2.32E+09 4.75E+08 8.85E+07 CS-137 5.15E+10 6.03E+10 4.27E+09 0.OOE+00 1.62E+10 6.55E+09 1.89E+08 0.00E+00 ____ ___.

BA-140 2.42E+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 CE-144 2.33E+06 9.53E+05 1.30E+05 0.00E+00 3.85E+05 0.00E+00 1.34E+08 PR-143 1.49E+03 5.56E+02 7.37E+01 0.00E+00 2.07E+02 0.OOE+00 7.84E+05 ND-147 8.83E+02 9.07E+02 5.55E+01 0.00E+00 3.50E+02 0.00E+00 5.75E+05 140

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Offsite Dose Calculation Manual (ODCM) 24 TABLE 5.4.2 Pathway Dose Factors, Ri AGE GROUP: CHILD PATHWAY: GRASS-COW-MILK 1 ORGAN DOSE FACTORS; m2 rmrem/year per piCi/sec NUCLIOE ----------------------------------------------------------

BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 0.OOE+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.OOE+00 0.OOE+00 1.02E+05 5.65E+04 1.54E+04 1.03E+05 5.40E+06 MN-54 0.OOE+00 2.10E+07 5.59E+06 0.OOE+00 5.89E+06 0.0OE+00 1.76E+07 FE-55 1.12E+08 5.94E+07 1.84E+07 O.OOE+00 0.00E+00 3.36E+07 1.1OE+07 FE-59 1.20E+08 1.95E+08 9.70E+07 0.OOE+00 0.00E+00 5.65E+07 2.03E+08 CO-58 0.OOE+00 1.21E+07 3.72E+07 0.OOE+00 O.OOE+00 0.O0E+00 7.08E+07 CO-60 0.OOE+00 4.32E+07 1.27E+08 0.00E+00 0.OOE+00 0.OOE+00 2.39E+08 NI-63 2.97E+10 1.59E+09 1.01 E+09 0.OOE+00 0.OOE+00 0.0OE+00 1.07E+08 ZN-65 4.14E+09 1.1 OE+10 6.86E+09 0.OOE+O0 6.95E+09 0.OOE+00 1.94E+09 RB-86 0.00E+00 8.78E+09 5.40E+09 0.OOE+00 0.OOE+00 0.OOE+00 5.65E+08 SR-89 6.63E+09 0.O0E+0O 1.89E+08 O.OOE+00 0.OOE+00 0.OOE+00 2.57E+08 SR-90 1.12E+11 0.OOE+00 2.84E+10 0.OOE+00 0.O0E+00 0.OOE+00 1.51 E+09 Y-91 3.91 E+04 0.OOE+00 1.05E+03 0.OOE+00 0.OOE+00 .0.E+OO 5.21 E+06 ZR-95 3.84E+03 8.43E+02 7.51 E+02 0.OOE+00 1.21 E+03 8.80E+05 0.OOE40OO NB-95 3.18E+05 1.24E+05 8.86E+04

0.OOE+00 1.16E+05 2.29E+08 RU-103 4.29E+03 0.OOE+00 1.65E+03 0.OOE+00 1.08E+04 0.OOE+00 1.11E+05 RU-1 06 9.25E+04 0.00E+00 1.15E+04 O.OOE+O0 1.25E+05 0.OOE+00 1.44E+06 AG-Ib M 2.09E+08 1.41 E+08 1.13E+08

0.OOE+00 2.63E+08 0.00E+00 1.68E+10 TE-12510 7.39E+07 2.OOE+07 9.85E+06 2.07E+07 0.O0E+00 .0.E+O0. 7.13E+07 TE-1271M 2.08E+08 5.61 E+07 2.47E+07 4.98E+07 5.94E+08 .0.OE+OO 1.69E+08 TE-1291M 2.72E+08 7.59E+07 4.22E+07 8.76 E+07 7.98E+08 0.00E+00 3.31 E+08 1-131 1.31E+09 1.31E+09 7.46E+08 4.34E+1 1 2.16E+09 0.OOE+00 1.17E+08 1-133 1.72E+07 2.13E+07 8.05E+06 3.95E+09 3.55E+07 0.OOE+00 8.58E+06 0.OOE+00-CS-134 2.27E+10 3.72E+10 7.85E+09 0.OOE+00 1.15E+10 4.14E+09 2.01 E+08 CS-136 1.01 E+09 2.79E+09 1.80E+09 0.OOE+OO 1.49E+09 2.21E+08 9.80E+07 CS-1 37 3.23E+10 3.09E+10 4.56E+09 1.01E+10 3.62E+09 1.93E+08

_____..__________________________ 0.OOE+00 _________________________.

BA-140 1.18E+08 1.03E+05 6.86E+06 0.OOE+00 3.35E+04 6.14E+04 5.96E+07 CE-141 2.19E+04 1.09E+04 1.62E+03 0.OOE+OO 4.79E+03 0.0OE+00 1.36E+07 CE-144 1.63E+06 5.09E+05 8.67E+04 2.82E+05 0.OOE+00 1.33E+08 PR-143 7.18E+02 2.16E+02 3.56E+01 0.OOE+00 1.17E+02 0.OOE+00 7.75E+05 ND-147 4.45E+02 3.61 E+02 2.79E+01 0.OOE+00 1.98E+02 0.OOE+00 5.71 E+05 141

b.

Number TMI - Unit 1 Radiological Controls Procedure 6610-PLN-4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 24 TABLE 5.4.3 Pathway Dose Factors, Ri AGE GROUP: TEEN PATHWAY: GRASS-COW-MILK

_ _2 ORGAN DOSE FACTORS; mr mremfyear per pCi/sec NUCLIDE ----------------------------------------------------------- _ _ _ _ _ _ _ _ _ _

J BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 0.OOE+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.OOE+00 4.99E+04 2.77E+04 1.09E+04 7.13E+04 8.39E+06 MN-54 O.OOE+00 1.40E+07 2.78E+06 O.OOE+00 4.19E+06 O.OOE+00. 2.88E+07 FE-55 4.46E+07 3.16E+07 7.37E+06 0.OOE+OO 0.OOE+00 2.01 E+07 1.37E+07 FE-59 5.19E+07 1.21 E+08 4.68E+07 O.OOE+00 O.00E+00 3.82E+07 2.86E+08 C0-58 0.OOE+00 7.94E+06 1.83E+07 0.OOE+00 0.OOE+00 0.OOE+00 1.10E+08 C0-60 O.OOE+00 2.78E+07 6.27E+07 0.OOE400 0.OOE+00 0.OOE+00 3.62E+08 NI-63 1.18E+10 8.36E+08 4.01 E+08 0.00E+00 0.OOE+00 0.OOE+00 1.33E+08

--- OE---

ZN-65 2.11E+09 7.32E+09 3.42E+09 4.69E+09 3.10E+09 0.OOE+00 0.OOE+00 RB-86 0.00E+00 4.73E+09 2.22E+09 0.00E+00 0.OOE+00 0.OOE+00 7.00E+08 SR-89 2.68E+09 0.00E+00 7.67E+07 0.OOE+00 3.19E+08 0.OOE+OO SR-90 6.62E+10 0.OOE+00 1.63E+10 0.00 E+00 0.OOE+00 1.86E+09 Y-91 1.58E+04 0.OOE+00 4.24E+02 0.OOE+00 0.OOE+00 0.OOE+00 6.48E+06 ZR-95 1.65E+03 5.21 E+02 3.58E+02 0.00E+00 7.65E+02 0.OOE+00 1.20E+06 NB-95 1.41 E+05 7.82E+04 4.30E+04 0.OOE+00 7.58E+04 0.OOE+00 3.34E+08 RU-103 1.81 E+03 0.OOE+00 7.75E+02 0.00E+00 6.39E+03 0.OOE+00 1.51 E+05 RU-106 3.76E+04 0.OOE+00 4.73E+03 0.OOE+00 7.24E+04 0.OOE+00 1.80E+06 AG-i1 OM 9.64E+07 9.12E+07 5.55E+07 0.OOE+00 1.74E+08 0.OOE+00 2.56E+10 TE-125M 3.01 E+07 1.08E+07 4.02E+06 8.40E+06 0.OOE+00 0.OOE+00 8.87E+07 TE-127M 8.45E+07 3.OOE+07 1.OOE+07 2.01 E+07 3.42E+08 0.OOE+00 2.11 E+08 TE-129M 1.1OE+08 4.09E+07 1.74E+07 3.56E+07 4.61E+08 0.OOE+00 4.14E+08 1-131 5.38E+08 7.53E+08 4.05E+08 2.20E+11 1.30E+09 0.OOE+00 1.49E+08 1-133 7.08E+06 1.20E+07 3.66E+06 1.68E+09 2.11E+07 0.OOE+00 9.09E+06 CS-1 34 9.83E+09 2.31 E+1 1.07E+10 0.OOE+00 7.35E+09 2.81E+09 2.88E+08 CS-1 36 4.49E+08 I1.77E+09 1.19E+09 0.OOE+00 9.63E+08 1.52E+08 1.42E+08 CS-137 1.34E+10 1.78E+10 6.21 E+09 0.OOE+00 6.06E+09 2.36E+09 2.54E+08 0.OOE+00 BA-140 4.87E+07 5.97E+04 3.14E+06 2.02E+04 4.01E+04 7.51E+07 0.OOE+00 CE-141 8.89E+03 5.94E+03 6.82E+02 2.80E+03 0.OOE+00 1.70E+07 0.OOE+00 CE-144 6.59E+05 2.73E+05 3.54E+04 1.63E+05 0.OOE+00 1.66E+08 PR-143 2.90E+02 1.16E+02 1.44E+01 0.OOE+00 6.73E+01 0.OOE+00 9.55E+05 ND-147 1.81E+02 1.97E+02 1.18E+01 0.O0E+00 1.16E+02 0.OOE+00 7.12E+05 142

Number TMI - Unit 1 Radiological Controls Procedure 661 0-PLN-420C.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 24 TABLE 5.4.4 Pathway Dose Factors, Ri AGE GROUP: ADULT PATHWAY: GRASS-COW-MILK 1

NUCLIDE ------------------------------

ORGAN DOSE FACTORS; m2 rmrem/year per piCi/sec BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 0.OOE+00 7.62E+02 7.62E+02 7.62E+02 7.62E+0, Z 7.62E+02 7.62E+02 C-14 2.63E+08 5.26E+07 5.26E+07 5.26E+07 5.26E+0' 1' 5.26E+07 5.26E+07 CR-51 0.OOE+00 0.OOE+00 2.85E+04 1.70E+04 6.28E+0, 3 3.78E+04 7.17E+06

--. OOE+00 MN-54 0.QOE+00 8.40E+06 1.60E+06 0.OOE+00 2.50E+0( 3 0.OOE+00 2.57E+07 FE-55 2.51 E+07 1.73E+07 4.04E+06 0.OOE+00 0.QOE+0( ) 9.66E+06 9.93E+06 FE-59 2.97E+07 6.97E+07 2.67E+07 0.OOE+0( ) 1.95E+07 2.32E+08 0.OOE+00 0.OOE+00-CO-58 0.OOE+00 4.71 E+06 1.05E+07 0.OOE+00- O.OOE+OC 9.54E+07 0.OOE+00 CO-60 0.OOE+00 1.64E+07 3.61 E+07 0.OOE+00 0.OOE+OC 3.08E+08 0.OOE+00 Nl-63 6.72E+09 4.65E+08 2.25E+08 0.00E4-0C 9.71 E+07

) .OOE+00 _________.

ZN-65 I1.37E+09 4.36E+09 1.97E+09 0.OOE+00 2.91 E+O0 ) .OOE+00 2.74E+09 RB-86 0.OOE+00 2.59E+09 1.21 E+09 0.OOE+00 0.OOE+OC 5.1OE+08

)0.OOE+00 SR-89 1.45E+09 0.OOE+00 4.16E+07 0.OOE+00 0.OOE+OC 2.32E+08 SR-90 4.67E+10 0.00E+00 1.15E+10 0.OOE+00 0.OOE+00 0.OOE+00 1.35E+09 Y-91 8.57E+03 0.OOE+00 2.29E+02 0.OOE+00 0.OOE+00 0.OQE+00 4.72E+06 ZR-95 9.41 E+02 3.02E+02 2.04E+02 0.OOE+00 4.74E+02 0.OOE+00 9.57E+05 NB-95 8.24E+04 4.58E+04 2.46E+04 0.OOE+00 4.53E+04 0.OOE+00 2.78E+08 RU-1 03 1.02E+03 0.OOE+00 4.38E+02 0.OOE+00 3.88E+03 0.OOE+00 1.19E+05 RU-1 06 2.04E+04 0.OOE+00 2.58E+03 0.OOE+00 3.93E+04 0.OOE+00 1.32E+06 AG-I lOM1 5.81 E+07 5.38E+07 3.19E+07 0.OOE+00 1.06E+08 0.OOE+00 .2.19E+10 TE-125t1 1.63E+07 5.89E+06 2.18E+06 4.89E+06 6.61 E+07 0.00E+00 6.49E+07 TE-127M1 4.57E+07 1.63E+07 5.57E+06 1.17E+07 1.86E+08 0.OOE+00 1.53E+08 TE-129M1 6.01E+07 2.24E+07 9.51E+06 2.06E+07 2.51E+08 0.OOE+00 3.02E+08 1-131 2.96E+08 4.23E+08 2.42E+08 1.39E+11 7.25E+08 0.OOE+00 1.12E+08 1-133 3.87E+06 6.73E+06 2.05E+06 9.88E+08 1.17E+07 0.OOE+00 6.04E+06 CS-134 5.64E+09 1.34E+10 1.1OE+10 0.OOE+00 4.34E+09 1.44E+09 2.35E+08 CS-136 2.63E+08 1.04E+09 7.48E+08 0.OOE+00 5.78E+08 7.92E+07 1.18E+08 CS-1 37 7.37E+09 1.01E+10 6.60E+09 0.OOE+00 3.42E+09 1.14E+09 1.95E+08 BA-140 2.69E+07 3.38E+04 1.76E+06 0.OOE+00 1.15E+04 1.94E+04 5.54E+07 CE-141 4.84E+03 3.27E+03 3.71E+02 0.OOE+00 1.52E+03 0.00E+00 1.25E+07 CE-144 3.57E+05 1.49E+05 1.92E+04 0.OOE+00 8.85E+04 0.OOE+00 1.21E+08 PR-143 1.57E+02 6.32E+01 7.81E+00 0.OOE+00 3.65E+01 0.OOE+00 6.90E+05 ND-147 9.40E+01 1.09E+02 6.50E+00 0.OOE+00 6.35E+01 0.OOE+00 5.22E+05 143

Number TMI -Unit I IlRadiological Controls Procedure 661 O-PLN-4200.01 Title .Revision No.

Offsite Dose Calculation Manual (ODCM) - 24 TABLE 5.5.1 Pathway Dose Factors, Ri AGE GROUP: INFANT PATHWAY: GRASS-GOAT-MILK ORGAN DOSE FACTORS; m2- mrem/year per jpCi/sec N U CLID E - - - -- - -- -- - - -- - -- - - - - -- - - - - -- -- - - -- - -- - - - - - - - - - - - - - -- - - -

J BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 0.00E+00 4.86E+03 4.86E+03 4.86E+03 4.86E+03 4.86E+03 4.86E+03 C-14 2.34E+09 5.00E+08 5.OOE+08 5.OOE+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 MN-54 0.OOE+00 4.68E+06 1.06E+06 0.00E+00 1.04E+06 0.00E+00. 1.72E+06 FE-55 1.76E+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 CO-58 0.00E+00 2.91 E+06 7.26E+06 0.00E+00 0.00E+00 0.00E+00 7.25E+06 CO-60 0.OOE+00 1.06E+07 2.50E+07 O.OOE+00 O.OOE+0 0.OOE+00 2.52E+07 NI-63 4.19E+09 2.59E+08 1.46E+08 0.00E+00 0.00E+00 0.OOE+00 1.29E+07 ZN-65 6.67E+08 2.29E+09 1.05E+09 0.00E+00 1.11E+09 0.00E+00 1.93E+09 RB-86 0.00E+00 2.67E+09 1.32E+09 0.00E+00 0.OOE+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 2.55E+11 0.00E+00 6.50E+10 0.00E+00 0.00E+00 0.00E+00 3.19E+09 Y-91 8.80E+03 0.00E+00 2.34E+02 0.00E+00 0.00E+00 0.00E+00 6.31 E+05 ZR-95 8.17E+02 1.99E+02 1.41E+02 0.00E+00 2.15E+02 0.00E+00 9.91E+04 NB-95 7.13E+04 2.93E+04 1.70E+04 0.00E+00 2.10E+04 0.00E+00 2.48E+07 RU-103 1.04E+03 0.00E+00 3.48E+02 0.00E+00 2.17E+03 0.00E+00 1.27E+04 RU-1 06 2.28E+04 0.00E+00 2.85E+03 0.00E+00 2.70E+04 0.00E+00 1.73E+05 AG-110M 4.63E+07 3.38E+07 2.24E+07 0.00E+00 4.84E+07 0.00E+00 1.75E+09 TE-125M 1.81E+07 6.05E+06 2.45E+06 6.09E+06 0.00E+00 0.00E+00 8.62E+06 TE-127M 5.06E+07 1.68E+07 6.12E+06 1.46E+07 1.24E+08 0.00E+00 2.04E+07 TE-129M 6.69E+07 2.29E+07 1.03E+07 2.57E+07 1.67E+08 0.00E+00 3.99E+07 1-131 3.27E+09 3.85E+09 1.69E+09 1.27E+12 4.50E+09 0.00E+00 1.37E+08 1-133 4.36E+07 6.35E+07 1.86E+07 1.15E+10 7.46E+07 0.00E+00 1.07E+07 CS-134 1.09E+11 2.04E+11 2.06E+10 0.002+00 5.26E+10 2.15E+10 5.55E+08 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 1.81E+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 0.002+00 6.89E+03 1.78E+04 7.13E+06 CE-141 5.21E+03 3.18E+03 3.74E+02 0.00E+00 9.79E+02 0.00E+00 1.64E+06 CE-144 2.79E+05 1.14E+05 1.56E+04 0.00E+00 4.62E+04 0.00E+00 1.60E+07 PR-143 1.78E+02 6.66E+01 8.83E+00 0.00E+00 2.48E+01 0.00E+00 9.40E+04 ND-147 1.06E+02 1.09E+02 6.66E+00 0.00E+00 4.19E+01 0.00E+00 6.89E+04 144

la Number TMI - Unit I Radiological Controls Procedure 6610-PLN-4200.01 Title DoRevision No.

Offsite Dose Calculation Manual (ODCM) 24 _

TABLE 5.5.2 Pathway Dose Factors, Ri AGE GROUP: CHILD PATHWAY: GRASS-GOAT-MILK 1J BONE ORGAN DOSE FACTORS; m2 _-mrem/year per pCi/sec LIVER T.BODY THYROID KIDNEY LUNG GI-LLI 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.OOE+00 0.OOE+00 1.22E+04 6.78E+03 1.85E+03 1.24E+04 6.48E+05 MN-54 0.00E+00 2.52E+06 6.71 E+05 0.OOE+00 7.06E+05 0.OOE+00 2.11 E+06 FE-55 1.45E+06 7.71 E+05 2.39E+05 0.OOE+00 0.00E+00 4.36E+05 1.43E+05 FE-59 1.56E+06 2.53E+06 1.26E+06 0.OOE+00 0.OOE+00 7.34E+05 2.64E+06 0.OOE+00 CO-58 0.OOE+00 1.46E+06 4.46E+06 0.OOE+00 0.OOE+00 8.49E+06 0.OOE+00 CO-60 0.OOE+00 5.18E+06 1.53E+07 0.00E+00 0.OOE+00 2.87E+07 0.OOE+00 NI-63 3.56E+09 1.91 E+08 1.21 E+08 0.OOE+00 0.OOE+00 1.28E+07 0.OOE+00 ZN-65 4.96E+08 1.32E+09 8.22E+08 0.OOE+00 8.33E+08 0.OOE+00 2.32E+08 RB-86 0.OOE+00 1.05E+09 6.47E+08 0.OOE+00 0.OOE+00 0.OOE+00 6.77E+07 SR-89 1.39E+10 0.OOE+00 3.97E+08 0.OOE+00 0.00E+00 5.39E+08 SR-90 2.35E+11 0.OOE+00 5.95E+10 0.OOE+00 0.OOE+00 0.OOE+00 3.16E+09 Y-91 4.69E+03 0.OOE+00 1.25E+02 0.OOE+00 0.OOE+00 0.OOE+00 6.24E+05 ZR-95 4.60E+02 1.01 E+02 9.OOE+01 0.OOE+00 1.45E+02 0.OOE+00 1.05E+05 NB-95 3.82E+04 1.49E+04 1.06E+04 0.OOE+00 1.40E+04 0.OOE+00 2.75E+07 RU-103 5.14E+02 0.OOE+00 1.98E+02 0.OOE+00 1.29E+03 0.OOE+00 1.33E+04 RU-1 06 1.11E+04 0.OOE+00 1.38E+03 0.OOE+00 1.50E+04 0.OOE+00 1.73E+05

_ _ _ _ _ _ _ _ _ . _---E+0_

AG-1i1 OMA 2.51 E+07 1.69E+07 1.35E+07 0.OOE+00 3.15E+07 0.00E+00 2.01 E+09 TE-125MI 8.86E+06 2.40E+06 1.18E+06 2.49E+06 0.OOE+00 0.OOE+00 8.55E+06 TE-127A1 2.50E+07 6.72E+06 2.96E+06 5.97E+06 7.12E+07 0.00E+00 2.02E+07 TE-129A1 3.26E+07 9.1OE+06 5.06E+06 1.05E+07 9.56E+07 0.OOE+00 3.97E+07 1-131 1.57E+09 1.57E+09 8.95E+08 5.21E+11 2.58E+09 0.OOE+00 1.40E+08 1-133 2.06E+07 2.55E+07 9.66E+06 4.74E+09 4.25E+07 0.00E+00 1.03E+07 CS-1 34 6.80E+10 1.12E+11 2.35E+10 0.OOE+00 3.46E+10 1.24E+10 6.01 E+08 CS-136 3.04E+09 8.36E+09 5.41 E+09 0.OOE+00 4.45E+09 6.64E+08 2.94E+08 CS-1 37 9.68E+10 9.26E+1 0 1.37E+10 0.OOE+00 3.02E+1 0 1.09E+10 5.80E+08 BA-140 1.41 E+07 1.24E+04 8.23E+05 0.OOE+00 4.02E+03 7.37E+03 7.15E+06 CE-141 2.63E+03 1.31E+03 1.95E+02 0.OOE+00 5.74E+02 0.OOE+00 1.63E+06 CE-144 1.95E+05 6.11E+04 1.04E+04 0.OOE+00 3.38E+04 0.OOE+00 1.59E+07 PR-143 8.61E+01 2.59E+01 4.27E+00 0.OOE+00 1.40E+01 0.OOE+00 9.29E+04 ND-147 5.34E+01 4.33E+01 3.35E+00 0.OOE+00 2.37E+01 0.OOE+00 6.85E+04 145

Number TMI - Unit 1 Radiological Controls Procedure l 661 O-PLN-4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 24 TABLE 5.5.3 Pathway Dose Factors, RI AGE GROUP: TEEN PATHWAY: GRASS-GOAT-MILK ORGAN DOSE FACTORS; m2 mrem/year per iCi/sec N U C LID E - - --- --- --- - - -- - - -- - -- - - - - - - --- - - --- - -- - - - - - - - - - - - - - - - - - - -

BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 0.00E+00 2.04E+03 2.04E+03 2.04E+03 2.04E+03 2.04E+03 2.04E+03 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.OOE+00 0.OOE+00 5.99E+03 3.33E+03 1.31E+03 8.55E+03 1.01E+06 MN-54 0.OOE+00 1.68E+06 3.34E+05 0.OOE+00 5.02E+05 0.O0E+00 3.45E+06 FE-55 5.79E+05 4.11E+05 9.58E+04 0.OOE+00 0.OOE+00 2.61E+05 1.78E+05 FE-59 6.74E+05

. . ._ 1.57E+06 6.08E+05

_ O.OOE+00 0.00E+00 4.96E+05 3.72E+06 CO-58 0.OOE+00 9.53E+05 2.20E+06 0.00E+00 0.00E+00 0.OQE+00 1.31 E+07 CO-60 0.00E+00 3.34E+06 7.52E+06 0.00E+00 0.OOE+00 4.35E+07 0.OOE+00 Nl-63 1.42E+09 1.OOE+08 4.81 E+07 0.00E+00 0.OQE+00 1.60E+07 0.OOE+00 ZN-65 2.53E+08 8.78E+08 4.IOE+08 0.00E+00 5.62E+08 0.OOE+00- 3.72E+08 RB-86 0.OOE+00 5.67E+08 2.67E+08 0.00E+00 0.OOE+00 0.OOE+00 8.40E+07 SR-89 5.62E+09 0.00E+00 1.61 E+08 0.00E+00 0.00E+00 6.69E+08 SR-90 1.39E+11 0.00E+00 3.43E+10 0.OOE+00 0.OOE+00 0.OOE+00 3.90E+09 Y-91 1.90E+03 0.OOE+00 5.09E+01 0.OQE+00 0.00E+00 0.OOE+00 7.78E+05 ZR-95 1.98E+02 6.25E+01 4.30E+01 0.OOE+00 9.18E+01 0.OOE+00 1.44E+05 NB-95 1.69E+04 9.38E+03 5.16E+03 0.OOE+00 9.09E+03 0.OOE+00 4.01 E+07 RU-103 2.17E+02 0.OOE+00 9.29E+01 0.OOE+00 7.66E+02 0.OOE+00 1.82E+04 RU-1 06 4.50E+03 0.OOE+00 5.68E+02 0.OOE+00 8.69E+03 0.OOE+00 2.16E+05 AG- 1 OM 1.16E+07 1.09E+07 6.65E+06 0.OOE+00 2.09E+07 0.OOE+00 3.07E+09 TE-125M 3.61 E+06 1.30E+06 4.82E+05 1.01E+06 0.OOE+00 0.OOE+00 1.06E+07 TE-127M 1.01 E+07 3.59E+06 1.20E+06 2.41 E+06 4.11 E+07 0.OOE+00 2.52E+07 TE-129M 1.32E+07 4.90E+06 2.09E+06 4.26E+06 5.53E+07 0.OOE+00 4.96E+07 1-131 6.45E+08 9.03E+08 4.85E+08 2.64E+11 1.56E+09 0.OOE+00 1.79E+08 1-133 8.49E+06 1.44E+07 4.40E+06 2.01 E+09 2.53E+07 0.OOE+00 1.09E+07 0.0____ ________.

CS-134 2.95E+10 6.93E+10 3.22E+10 0.00E+00 2.20E+10 8.41 E+09 8.62E+08 CS-136 1.35E+09 5.30E+09 3.56E+09 0.OOE+00 2.89E+09 4.55E+08 4.27E+08 CS-137 4.02E+10 5.34E+10 1.86E+10 0.OOE+00 1.82E+10 7.07E+09 7.60E+08 BA-140 5.84E+06 7.16E+03 3.76E+05 0.OOE+00 2.43E+03 4.81 E+03 9.01 E+06 CE-141 1.07E+03 7.12E+02 8.18E+01 0.OOE+00 3.35E+02 0.OOE+00 2.04E+06 CE-144 7.90E+04 3.27E+04 4.25E+03 0.00E+00 1.95E+04 0.OOE+00 1.99E+07 PR-143 3.48E+01 1.39E+01 1.73E+00 0.OOE+00 8.08E+00 0.OOE+00 1.15E+05 ND-147 2.18E+01 2.37E+01 1.42E+00 0.OOE+00 1.39E+01 0.OOE+00 8.54E+04 146

Number TMI- Unit I Radiologjical Controls Procedure 661 0-PLN-4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 24 TABLE 5.5.4 Pathway Dose Factors, RI AGE GROUP: ADULT PATHWAY: GRASS-GOAT-MILK 1 -- ORGAN DOSE FACTORS; m2 - mrem/year per VCi/sec NUCLIDE-

_- - - J BONE LIVER T.BODY

_- - - - T . _

THYROID_~

KIDNEY LUNG

- L N___-

GI-LLI H-3 0.OOE+00 1.56E+03 1.56E+03 1.56E+03 I1.56E+03 1.56E+03 I1.56E+03 C-14 2.64E+08 5.27E+07 5.2 7E+07 5.27E+07 5.27E+07 5.27E+07 5.27E+07 CR-51 0.OOE+00 0.OOE+00 3.4 3E+03 2.05E+03 7.56E+02 4.55E+03 8.63E+05 MN-54 0.OOE+00 1.01 E+06 1.93E+05 0.00E+00 3.01 E+05 0.00E+00 3.10E+06 FE-55 3.27E+05 2.26E+05 5.26E+04 0.00E+00 O.OOE+00 I1.26E+05 1.30E+05 FE-59 3.87E+05 9.09E+05 3.48E+05 0.OOE+00 0.00E+00 2.54E+05 3.03E+06 0.OOE+00 ---- O-+-0 CO-58 0.00E+00 5.66E+05 1.27E+06 O.OOE+00 1.15E+07 0.00E+00 0.OOE+00 CO-60 0.OOE+00 1.97E+06 4.35E+06 O.OOE+OO 3.70E+07 0.OOE+00 0.OOE+00 NI-63 8.08E+08 5.60E+07 2.71 E+07 0.00E+00 1.1I7E+07

.O.00E+00 0.OOE+00 ZN-65 1.65E+08 5.24E+08 2.37E+08 3.51 E+08 3.30E+08 RB-86 0.00E+00 3.12E+08 1.45E+08 0.OOE+00 0.00E+00 0.00E+00 6.14E+07 SR-89 3.05E+09 0.00E+00 8.76E+07 0.OOE+00 0.OOE+00 0.OOE+00 4.89E+08 SR-90 9.84E+10 0.00E+00 2.41 E+10 0.OOE+00 0.OOE+00 0.OOE+00 2.84E+09 Y-91 1.03E+03 0.OOE+00 2.76E+01 0.OOE+00 0.00E+00 0.OOE+00 5.68E+05 ZR-95 1.13E+02 3.63E+01 2.46E+01 5.70E+01 1.15E+05 NB-95 9.92E+03 5.52E+03 2.97E+03 0.OOE+00 5.45E+03 0.OOE+00 3.35E+07 RU-1 03 1.22E+02 0.00E+00 5.27E+01 0.OOE+00 4.67E+02 0.OOE+00 1.43E+04 RU-1 06 2.45E+03 0.OOE+00 3.1 OE+02 0.OOE+00 4.73E+03 0.OOE+00 1.59E+05 AG-1101/1-AG-I1010 6.99E+06 6.47E+06 3.84E+06 0.OOE+00 1.27E+07 2.64E+09 TE-125M 1.96E+06 7.09E+05 2.62E+05 5.89E+05 7.96E+06 0.OOE+00 7.81 E+06 TE-127M 5.50E+06 1.97E+06 6.70E+05 1.41 E+06 2.23E+07 0.OOE+00. 1.84E+07 TE-129M 7.23E+06 2.70E+06 1.14E+06 2.48E+06 3.02E+07 0.OOE+00 3.64E+07 1-131 3.56E+08 5.09E+08 2.92E+08 1.67E+1 1 8.73E+08 0.OOE+00 1.34E+08 1-133 4.65E+06 8.10E+06 2.47E+06 1.19E+09 1.41 E+07 7.28E+06 0.OOE+00-CS-1 34 1.70E+10 4.04E+10 3.30E+10 0.OOE+00 1.31 E+10 4.34E+09 7.07E+08 CS-1 36 7.92E+08 3.13E+09 2.25E+09 1.74E+09 2.38E+08 3.55E+08 0.OOE+00 CS-1 37 2.22E+1 0 3.03E+10 1.99E+10 1.03E+10 3.42E+09 5.87E+08 BA-140 3.24E+06 4.07E+03 2.12E+05 0.00E+00 1.38E+03 2.33E+03 6.67E+06 CE-141 5.82E+02 3.94E+02 4.47E+01 0.OOE+00 1.83E+02 0.OOE+00 1.51E+06 CE-144 4.30E+04 1.80E+04 2.31 E+03 0.OOE+00 1.07E+04 0.OOE+00 1.45E+07 PR-143 1.90E+01 7.60E+00 9.40e-01 0.OOE+00 4.39E+00 0.OOE+00 8.30E+04 ND-147 1.13E+01 1.31E+01 7.82e-01 0.OOE+00 7.65E+00 0.OOE+00 6.28E+04 147

Number TMI- Unit 1 Radiological Controls Procedure 661 0-PLN-4200.01 Title - Revision No.

Offsite Dose Calculation Manual (ODCM) 24 TABLE 5.6.1 Pathway Dose Factors, Ri AGE GROUP: INFANT PATHWAY: GRASS-COW-MEAT 1 - - - - - - - - - - -_ - - _ - - - - - -2_-_ - - - - _ - -_- -_ -__- _ _ _.

ORGAN DOSE FACTORS; m2_ mrem/year per yCi/sec NUCLIDE BONE LIVER _NE TBOD- TYO LUNG G________

BONE LIVER - - - T.BODY THYROID KIDNEY- - - - - - -

LUNG Gl-LLI H-3 0.OOE+00 O.OOE+00 0.O0E+00 .0.E+OO 0.OOE+00 0.00E+00 0.OOE+00 C-14 O.OOE+OO O.O0E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+OO CR-51 O.OOE+00 O.OOE+00 0.OOE+00 .0OOE+OO 0.OOE+00 O.OOE+00 O.OOE+OO 0.OOE+00 MN-54 O.OOE+OO O.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 FE-55 0.OOE+00 O.OOE+00 0.00E+00 0.OOE+OO O.OOE+00 O.OOE+00 0.OOE+00 FE-59 0.OOE+00 0.00 E+O0 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 CO-58 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+OO .0OOE+00 0.OOE+00 CO-60 0.OOE+00 0.OOE+00 0O.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 NI-63 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O0.E+OO 0.OOE+00 0.OOE1+00 0.OOE+00 I--------

ZN-65 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 O.OOE+OO RB-86 O.OOE+00 0.00 E+OO 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 SR-89 0.OOE+00 0.OOE+OO 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 SR-90 0.OOE+00 --.0.OOE+00 O--+DO 0.OOE+00 0.OOE+00 0.OOE+OO 0.OOE+00 0.OOE+00-0.OQE+O0 Y-91 0.OOE+00 0.00E+00 0.OOE+0O

.0.OE+OO ZR-95 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OQE+00 0.OOE+00 NB-95 0.OOE+00 0.0E-----

0.OOE+00 0.OOE+00 RU-103 0.0OE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 RU-1 06 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 AG-1 OM .0.OE+0O 0.OOE+00 0.OOE+OO 0.OOE+00 0.OOE+00 .0.OE+OO .0OOE+OO TE-125M 0O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+OO 0.OOE+00 TE-127M O0.OE+DO 0.OOE+00 0.OOE+OO .0OOE+OO 0.OOE+00 .0.OE+OO 0.OOE+00 E-129_M_ _. O_O _EE+00 O-E _E 0 _ _ _E _ _ _ _E_ _ __ _ _ _ _ _ _ _ _ _E__ _ _ _ _ _ _ _ _ _.

TE-123M 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 1-131 0.OOE+00 0.OOE+00 0.O0E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1-133 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.0OE+00 0.OOE+00 CS-1 34 0.OOE+00 0.OOE+00 0.O0E+00 0.O0E+0O 0.OOE+00 0.OOE+00 0.0OE+00 CS-1 37 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.O0E+00 0.0OE+00 0.OOE+00 BA-1 40 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.0OE+00 0.OOE+00 CE-141 0.0OE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00. 0.OOE+00 CE-144 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.O0E+00 0.OOE+00 PR-143 0.00E+00 0.0OE+00 0.0OE+0O 0.O0E+00 0.OOE+00 0.O0E+00 0.OOE+00 ND-147 0.00E+00 0.0OE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.0OE+00 0.0OE+00 148

Number TMI - Unit 1 Radiological Controls Procedure 661 O-PLN-4200.01 Title DtRevision No.

MOfite Dose C"'alculation Manual (ODCM) 24 TABLE 5.6.2 Pathway Dose Factors, Ri AGE GROUP: CHILD PATHWAY: GRASS-COW-MEAT 1 ORGAN DOSE FACTORS; m2 _ mrem/year per pCi/sec NUCLIDE 1-------------------------------------------~~~~~~~~

- BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 0.OOE+00 2.34E+02 2.34E+02 2.34E+02 2.34E+02 2.34E+02 2.34E+02 C-14 3.84E+08 7.67E+07 7.67E+07 7.67E+07 7.67E+07 7.67E+07 7.67E+07 CR-51 O.OOE+00 0.OOE+00 8.78E+03 4.88E+03 1.33E+03 8.90E+03 4.66E+05 MN-54 0.OOE+00 8.01 E+06 2.13E+06 0.OOE+00 2.25E+06 O.OOE+00 6.73E+06 FE-55 4.57E+08 2.43E+08 7.52E+07 0.OOE+00 0.00E+00 1.37E+08 4.49E+07 FE-59 3.77E+08 6.10E+08 3.04E+08 0.OOE+00 0.OOE+00 1.77E+08 6.35E+08 C0-58 O.OOE+00 1.64E+07 5.03E+07 0.OOE+00 0.OOE+00 0.OOE+00 9.58E+07 C0-60 O.OOE+00 6.93E+07 2.04E+08 0.OQE+00 0.OOE+00 0.OOE+00 3.84E+08 NI-63 2.91E+10 1.56E+09 9.91 E+08 0.OOE+00 0.OOE+00 0.OOE+00 1.05E+08 ZN-65 3.76E+08 1.00E+09 6.22E+08 0.OOE+00 6.31 E+08 0.OOE+00 1.76E+08 RB-86 0.OOE+00 5.76E+08 3.54E+08 0.OQE+00 0.00E+00 0.OOE+00 3.71 E+07 SR-89 4.82E+08 0.OOE+00 1.38E+07 0.OQE+00 0.00E+00 0.OOE+00 1.87E+07 SR-90 1.04E+10 0.OOE+00 2.64E+09 0.00E+00 0.00 E+00 0.OOE+00 __.40E+08 Y-91 1.80E+06 0.00E+00 4.82E+04 0.OOE+00 0.00E+00 0.OOE+00 2.40E+08 ZR-95 2.66E+06 5.86E+05 5.21 E+05 0.00E+00 8.38E+05 0.OOE+00 6.11E+08 NB-95 3.10E+06 1.21E+06 8.63E+05 0.00E+00 1.13E+06 0.OOE+00 2.23E+09 RU-103 1.55E+08 0.OOE+00 5.96E+07 0.OOE+00 3.90E+08 0.OOE+00 4.01 E+09 RU-1 06 4.44E+09 0.OOE+00 5.54E+08 0.00E+00 6.OOE+09 0.00E+00 6.91 E+10 AG-110II 8.39E+06 5.67E+06 4.53E+06 0.OOE+00 1.06E-i07 0.OOE+00 6.74E+08 TE-1251v1 5.69E+08 1.54E+08 7.59E+07 I1.60E+08 0.OOE+00 0.OOE+00. 5.49E+08 TE-127191 1.78E+09 4.78E+08 2.11E+08 4.25E+08 5.06E+09 0.00E+00 1.44E+09 TE-1291\ 11.79E+09 5.OOE+08 2.78E+08 5.77E+08 5.26E+09 0.00E+00 2.18E+09 1-131 1.66E+07 1.67E+07 9.48E+06 5.52E+09 2.74E+07 0.OOE+00 1.48E+06 1-133 5.72e-01 7.08e-01 2.68e-01 1.31 E+02 1.18E+00 0.OOE+00 2.85e-01 CS-134 9.23E+08 1.51 E+09 3.19E+08 0.00E+00 4.69E+08 I1.68E+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-1 37 1.33E+09 1.28E+09 1.89E+08 0.00E+00 4.16E+08 1.50E+08 8.OOE+06 BA-140 4.42E+07 3.87E+04 2.58E+06 1.26E+04 2.31 E+04 2.24E+07 0.OOE+00 CE-141 2.22E+04 1.11E+04 1.65E+03 4.86E+03 0.00E+00 1.38E+07 0.OOE+00 CE-144 2.32E+06 7.26E+05 1.24E+05 4.02E+05 0.OOE+00 1.89E+08 PR-143 3.33E+04 1.00E+04 1.65E+03 0.00E+00 5.42E+03 0.OOE+00 3.60E+07 ND-147 1.17E+04 9.48E+03 7.34E+02 0.OOE+00 5.20E+03 0.00E+00 1.50E+07 149

Number TMI- Unit I Radioloqical Controls Procedure 661 0-PLN-4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 24 TABLE 5.6.3 Pathway Dose Factors, Ri AGE GROUP: TEEN PATHWAY: GRASS-COW-MEAT ORGAN DOSE FACTORS; m2 mrem/year per pCi/sec NUCLIDE------- ----------------

J BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 0.00E+00 I1.93E+02 1.93E+02 1.93E+02 1.93E+02 1.93E+02 1.93E+02 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.OOE+00 0.OOE+00 5.63E+03 3.13E+03 1.23E+03 8.03E+03 9.46E+05 0.OOE+00 MN-54 0.OOE+00 7.OOE+06 1.39E+06 0.OOE+00 2.09E+06 0.OOE+00 1.44E+07 FE-55 2.38E+08 1.69E+08 3.94E+07 0.OOE+00 0.OOE+00 1.07E+08 7.31 E+07 FE-59 2.12E+08 4.95E+08 1.91 E+08 0.00E+00 0.OOE+00 1.56E+08 1.17E+09 CO-58 0.00E+00 1.40E+07 3.24E+07 0.OOE+00 0.OOE+00 0.OOE+00 1.94E+08 CO-60 0.OOE+00 5.83E+07 1.31 E+08 0.OOE+00 0.OOE+00 0.OOE+00 7.60E+08 NI-63 1.52E+10 I1.07E+09 5.15E+08 0.00E+00 0.OOE+00 0.OOE+00 1.71 E+08 ZN-65 2.50E+08 8.68E+08 4 .05E+08 0.OOE+00 5.56E+08 0.OOE+00 3.68E+08 RB-86 0.OOE+00 4.06E+08 1.91 E+08 0.OOE+00 0.00E+00 0.OOE+00 6.OOE+07 SR-89 2.55E+08 0.OOE+00 7 .29E+06 0.OOE+00 0.OOE+00 0.OOE+00 3.03E+07 SR-90 8.04E+09 0.OOE+00 1.99E+09 0.OOE+00 0.OOE+00 0.OOE+00 2.26E+08 Y-91 9.54E+05 0.OOE+00 2 .56E+04 0.OOE+00 0.OOE+00 0.OOE+00 3.91 E+08 ZR-95 1.50E+06 4.73E+05 3 .25E+05 0.OOE+00 6.95E+05 0.OOE+00 1.09E+09 NB-95 1.79E+06 9.95E+05, 5 .48E+05 0.OOE+00 9.64E+05 0.OOE+00 4.25E+09 RU-1 03 8.56E+07 0.OOE+00 3 .66E+07 0.OOE+00 3.02E+08 0.OOE+00 7.15E+09 RU-106 2.36E+09 0.OOE+00 2 .97E+08 0.OOE+00 4.54E+09 0.OOE+00 1.13E+11 AG-1101 A 5.06E+06 4.78E+06 2 .91 E+06 0.OOE+00 9.13E+06 0.OOE+00 1.34E+09 TE-125!v 1 3.03E+08 1.09E+08 4 .05E+07 8.46E+07 0.OOE+00 0.OOE+00 8.94E+08 TE-127rv A 9.41 E+08 3.34E+08 1..12E+08 2.24E+08 3.81 E+09 0.OOE+00 2.35E+09 TE-129rv I 9.49E+08 3.52E+08 1,.50E+08 3.06E+08 3.97E+09 0.OOE+00 3.56E+09 1-131 8.93E+06 1.25E+07 6..72E+06 3.65E+09 2.15E+07 0.OOE+00 2.47E+06 1-133 3.08e-01 5.22e-01 1.,59e-01 7.29E+01 9.16e-01 0.OOE+00 3.95e-01 CS-1 34 5.23E+08 1.23E+09 5..71 E+08 0.OOE+00 3.91 E+08 1.49E+08 1.53E+07 CS-136 9.43E+06 3.71 E+07 2. !49E+07 0.OOE+00 2.02E+07 3.1 8E+06 2.99E+06 CS-137 7.24E+08 9.63E+08 3. 35E+08 0.OOE+00 3.28E+08 1.27E+08 1.37E+07 BA-140 2.39E+07 2.93E+04 1.54E+06 0.OOE+00 9.94E+03 I1.97E+04 3.69E+07 CE-141 1.18E+04 7.87E+03 9. 05E+02 0.OOE+00 3.71 E+03 0.OOE+00 2.25E+07 CE-144 1.23E+06 5.08E+05 6. 60E+04 0.OOE+00 3.03E+05 0.OOE+00 3.09E+08 PR-143 1.76E+04 7.03E+03 8.76E+02 0.OOE+00 4.08E+03 0.00E+00 5.79E+07 ND-147 6.23E+03 6.78E+03 4.06E+02 0.OOE+00 3.98E+03 0.OOE+00 2.44E+07 150

Number TMI - Unit I Radiological Controls Procedure 661 0-PLN-4200.01 Title .Revision No.

Offsite Dose 'Calculation Manual (ODCM) 24 TABLE 5.6.4 Pathway Dose Factors, Ri AGE GROUP: ADULT PATHWAY: GRASS-COW-MEAT 1 ORGAN DOSE FACTORS; m2 - mrem/year per pCilsec NUCLIDE ------------------------------

BONE LIVER 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+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.OOE+00 7.04E+03 4.21E+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.OOE+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 FE-59 2.66E+08 6.25E+08 2.39E+08 0.OOE+00 0.00E+00 1.75E+08 2.08E+09 4.09E+07 0.002+00_0__ OE+__

CO-58 0.OOE+00 1.82E+07 4.09E+07 0.00E+00 0.00E+00 0.00E+00 3.70E+08 CO-60 0.OOE+00 7.52E+07 1.66E+08 0.00E+00 0.00E+00 0.00E+00 1.41 E+09 NI-63 1.89E+10 1.31E+09 6.33E+08 0.00E+00 0.00E+00 0.00E+00 2.73E+08 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.OOE+00 0.00E+00 9.59E+07 SR-89 3.02E+08 0.OOE+00 8.66E+06 0.OOE+00 0.00E+00 0.00E+00 4.84E+07 SR-90 1.24E+10 0.OOE+00 3.05E+09 0.00E+00 0.00E+00 0.OOE+00 3.60E+08 Y-91 1.13E+06 0.00E+00 3.03E+04 0.OOE+00 0.OOE+00 O.OOE+00 6.24E+08 ZR-95 1.87E+06 6.01 E+05 4.07E+05 0.OOE+00 9.43E+05 0.00E+00 1.90E+09 NB-95 2.30E+06 1.28E+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 5.41 E+09 0.00E+00 1.81E+11 AG-b1 0M 6.68E+06 6.18E+06 3.67E+06 0.00E+00 1.22E+07 0.00E+00 2.52E+09 TE-1251VI 3.59E+08 1.30E+08 4.81 E+07 1.08E+08 1.46E+09 0.00E+00 1.43E+09 TE-127MvI 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 5.71 E+09 1-131 1.08E+07 1.54E+07 8.82E+06 5.04E+09 2.64E+07 0.00E+00 4.06E+06 1-133 3.68e-01 6.41 e-01 1.95e-01 9.42E+01 1.12E+00 0.00E+00 5.76e-01 C-I 34 _____ ___

CS-134 6.58E+08 1.57E+09 1.28E+09 0.00E+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-1 37 8.72E+08 1.19E+09 7.82E+08 0.00E+00 4.05E+08 1.35E+08 2.31 E+07 BA-140 2.90E+07 3.64E+04 1.90E+06 0.00E+00 1.24E+04 2.08E+04 5.96E+07 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 CE-144 1.46E+06 6.1 OE+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 ND-147 7.08E+03 8.18E+03 4.90E+02 0.00E+00 4.78E+03 0.00E+00 3.93E+07 151

Number TMI - Unit 1 Radiological Controls Procedure 661 0-PLN-4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 24 TABLE 5.7.1 Pathway Dose Factors, RI AGE GROUP: INFANT PATHWAY: VEGETATION NUCLIDEl ORGAN DOSE FACTORS; m2- mrem/year per jtCilsec J BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 0.00E+00 0.00E+00 0.00E+00 0.00E+00 .0.E+OO C-14 0.QOE+OO 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+OO 0.OOE+00 0.00E+OO 0.OOE+OO CR-51 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 .O.OE+OO MN-54 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00.

FE-55 0.OOE.00 0.OOE+00 0.00E+00 0.OOE+00 FE-59 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 CO-58 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 CO-60 0.OOE+OO 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.OQE+00 0.00E+OO 0.OOE+00 NI-63 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 ZN-65 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 RB-86 0.0OE+00 0.OOE+00 0.00E+00 0.OOE+OO 0.00E+00 0.OOE+00 0.OOE+00 SR-89 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00-SR-90 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Y-91 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 ZR-95 0.OOE+00 0.0OE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 NB-95 0.OOE+00 0.OOE+00 0.O0E+00 0.OOE+00- 0.OOE+00 0.OOE+00 0.OOE+00 RU-1 03 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 RU-1 06 0.OOE+00 0.O0E+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00

__OOE+0 ____OE_0_

0.OOE+00 0.OOE+OO _-------

__-- __E_ E+_.-0_ _ _ __ --_ __--_ _ __

AG-i1 OM 0.00E+00 0.0OE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 TE-125M 0.0OE+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 TE-127M 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.O___+0

_.OOE+00

_ ___---- _ .OOE+

___ _0 0- _0_______OE____ +___

TE-129M 0.OOE+00 0.O0E+00 1-131 0.0OE+0O 0.OOE+00 1-133 0.0OE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 CS-1 34 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+OO CS-1 36 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 CS-137 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.O0E+00 0.OOE+00

____E_- __OOE- _00 0_______- __O ___0 BA-140 0.OOE+00 0.OOE+00 0.OOE+O0 0.OOE+00 0.00E+00 0.OOE+00 O.OOE+00 0.00E+00 0.00E+00 CE-141 .0OOE+OO 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0 .00E+00 CE-144 0.OOE+OO 0.00E+00 0.00E+00 0.00E+00 0.00E+00 PR- 43 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 ND-147 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 152

Number TMI - Unit I Radiological Controls Procedure 661 O-PLN-4200.01 Title D Revision No.

Offsite Dose Calculation Manual (ODCM) 24 TABLE 5.7.2 Pathway Dose Factors, Ri AGE GROUP: CHILD PATHWAY: VEGETATION ORGAN DOSE FACTORS; m2 mrem/year per pCi/sec NUCLIC-E- - _ _----_------_ ---- __-_-__-_-

_ BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 0.00E+00 4.02E+03 4.02E+03 4.02E+03 4.02E+03 4.02E+03 4.02E+03 C-14 8.89E+08 1.78E+08 1.78E+08 1.78E+08 1.78E+08 1.78E+08 1.78E+08 CR-51 0.OOE+00 0.OOE+00 1.17E+05 6.49E+04 1.77E+04 1.18E+05 6.20E+06 MN-54 O.OOE+00 6.65E+08 1.77E+08 0.00E+00 I1.86E+08 0.OOE+00 5.58E+08 FE-55 8.01 E+08 4.25E+08 1.32E+08 0.OOE+00 0.OOE+00 2.40E+08 7.87E+07 FE-59 3.98E+08 6.44E+08 3.21 E+08 0.OOE+00 0.OOE+00 I1.87E+08 6.71 E+08

E---

CO-58 0.OOE+00 6.44E+07 1.97E+08 0.OOE+00 0.OOE+00 3.76E+08 0.OOE+00 CO-60 0.00E+00 3.78E+08 1.12E+09 0.OOE+00 0.OOE+00 2.1 0E+09 0.OOE+00 0.OOE+00 NI-63 3.95E+ 10 2.11 E+09 1.34E+09 0.OOE+00 1.42E+08 0.OOE+00 ZN-65 8.12E+08 2.16E+09 1.35E+09 0.OOE+00 I1.36E+09 0.OOE+00- 3.80E+08 RB-86 0.00E+00 4.51 E+08 2.77E+08 0.00E+00 0.00E+00 0.OOE+00 2.90E+07 SR-89 3.60E+10 0.OOE+00 1.03E+09 0.00E+00 0.OOE+00 1.39E+09

-. OO_+0_ _. _0_O_ 0

_-OOE+00 O_+_0_

SR-90 1.24E+12 0.OOE+00 3.15E+11 0.OOE+00 0.OOE+00 0.OOE+00 1.67E+10 Y-91 1.87E+07 0.00E+00 4.99E+05 0.OOE+00 0.00E+06 0.OOE+00 2.49E+09 ZR-95 3.86E+06 8.48E+05 7.55E+05 0.00E+00 1.21 E+06 0.00E+00 8.85E+08 NB-95 4.11E+05 1.60E+05 1.14E+05 0.OOE+00 1.50E+05 0.OOE+00 2.96E+08 RU-103 1.53E+07 0.OOE+00 5.90E+06 0.OOE+00 3.86E+07 0.OOE+00 3.97E+08 RU-I 06 7.45E+08 0.OOE+00 9.30E+07 0.OOE+00 1.01 E+09 0.OOE+00 1.16E+10 AG-I1 01M 3.21 E+07 2.17E+07 1.73E+07 0.OOE+00 4.04E+07 0.OOE+00 2.58E+09 TE-125M 3.51 E+08 9.50E+07 4.67E+07 9.84E+07 0.OOE+00 0.OOE+00 3.38E+08 TE-127fM 1.32E+09 3.56E+08 1.57E+08 3.16E+08 3.77E+09 0.OOE+00 1.07E+09 TE-129MA 8.40E+08 2.35E+08 1.30E+08 2.71 E+08 2.47E+09 0.OOE+00 1.02E+09 1-131 1.43E+08 1.44E+08 8.18E+07 4.76E+10 2.36E+08 0.OOE+00 1.28E+07 1-133 3.53E+06 4.37E+06 1.65E+06 8.12E+08 7.28E+06 0.OOE+00 1.76E+06 0.OOE+00 CS-1 34 1.60E+10 2.63E+10 5.55E+09 0.OOE+00 8.15E+09 2.93E+09 1.42E+08 CS-1 36 8.28E+07 2.28E+08 1.47E+08 0.OOE+00 1.21 E+08 1.81E+07 8.00E+06 CS-1 37 2.39E+10 2.29E+10 3.38E+09 0.OOE+00 7.46E+09 2.68E+09 1.43E+08 BA-140 2.79E+08 2.44E+05 1.63E+07 0.OOE+00 7.96E+04 1.46E+05 1.41E+08 CE-141 6.57E+05 3.28E+05 4.86E+04 0.OOE+00 1.44E+05 0.OOE+00 4.09E+08 CE-144 1.27E+08 3.99E+07 6.79E+06 0.00E+00 2.21 E+07 0.OOE+00 1.04E+10 PR-143 1.45E+05 4.36E+04 7.21 E+03 0.OOE+00 2.36E+04 0.OOE+00 1.57E+08 ND-147 7.15E+04 5.79E+04 4.49E+03 0.OOE+00 3.18E+04 0.OOE+00 9.18E+07 153

Number TMI - Unit 1 nmn-pi ki-Agnn m Title Revision No.

Offsite Dose Calculation Manual (ODCM) 24 TABLE 5.7.3 Pathway Dose Factors, Ri AGE GROUP: TEEN PATHWAY: VEGETATION 1

NUCLIDE ----------------------

ORGAN DOSE FACTORS; m2 rmremlyear per pCitsec J BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 O.OOE+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 CR-51 O.OOE+00 O.OOE+OO 6.16E+04 3.42E+04 1.35E+04 8.79E+04 1.03E+07 MN-54 O.OOE+OO 4.54E+08 9.01 E+07 O.OOE+00 1.36E+08 O.OOE+00 9.32E+08 FE-55 3.26E+08 2.31 E+08 5.39E+07 O.OOE+00 O.OOE+OO 1.47E+08 1.OOE+08 FE-59 1.80E+08 4.19E+08 1.62E+08 O.OOE+OO O.OOE+00 1.32E+08 9.91 E+08 C0-58 O.OOE+0O 4.36E+07 1.01 E+08 O.OOE+00 O.OOE+00 6.01 E+08 C0-60 O.OOE+00 2.49E+08 5.60E+08 O.OOE+00 O.oOE+00 O.OOE+OO 3.24E+09 NI-63 1.61E+10 1.1 3E+09 5.45E+08 0.00E+00 O.OOE+00 0.00E+00 1.81 E+08 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 O.OOE+00 2.73E+08 1.28E+08 0.00E+00 0.00E+00 0.00E+00 4.04E+07 SR-89 1.52E+10 O.OOE+00 4.34E+08 0.00E+00 0.00E+00 0.00E+00 1.80E+09 SR-90 7.51 E+11 0.OOE+OO 1.85E+11 0.O0E+00 0.00E+00 0.00E+00 2.11E+10 Y-91 7.84E+06 O.0OE+OO 2.1 OE+05 0.00E+00 0.00E+00 0.00E+00 3.22E+09 ZR-95 1.72E+06 5.43E+05 3.73E+05 0.00E+00 7.98E+05 0.00E+00 1.25E+09 NB-95 1.92E+05 1.07E+05 5.87E+04 0.00E+00 1.03E+05 0.00E+00 4.56E+08 RU-1 03 6.82E+06 O.OOE+00 2.92E+06 0.00E+00 2.41E+07 0.00E+00 5.70E+08 RU-106 3.09E+08 O.OOE+00 3.90E+07 0.00E+00 5.97E+08 0.00E+00 1.48E+10 AG-11OM 1.52E+07 1.43E+07 8.72E+06 0.00E+00 2.74E+07 0.00E+00 4.03E+09 TE-125M 1.48E+08 5.34E+07 1.98E+07 4.14E+07 0.00E+00 0.00E+00 4.37E+08 TE-127M 5.52E+08 1.96E+08 6.56E+07 1.31 E+08 2.24E+09 0.00E+00 1.37E+09 TE-129M 3.61 E+08 1.34E+08 5.72E+07 1.17E+08 1.51E+09 0.00E+00 1.36E+09 1-131 7.69E+07 1.08E+08 5.78E+07 3.14E+10 1.85E+08 0.00E+00 2.13E+07 1-133 1.94E+06 3.29E+06 1.00E+06 4.59E+08 5.77E+06 0.00E+00 2.49E+06 CS-1 34 7.1 OE+09 1.67E+10 7.75E+09 0.00E+00 5.31 E+09 2.03E+ 09 2.08E+08 CS-1 36 4.39E+07 1.73E+08 1.16E+08 0.00E+00 9.41 E+07 1.48E+I07 1.39E+07 CS-1 37 1.01E+10 1.35E+10 4.69E+09 0.00E+00 4.59E+09 1.78E+109 1.92E+08 BA-1 40 1.39E+08 1.71 E+05 8.97E+06 5.78E+04 1.15E+l 05 2.15E+08 CE-141 2.83E+05 1.89E+05 2.17E+04 0.00E+00 8.90E+04 0.00E+100 5.41 E+08 CE-144 5.28E+07 2.18E+07 2.83E+06 0.00E+00 1.30E+07 0.00E+100 1.33E+10 PR-143 6.99E+04 2.79E+04 3.48E+03 0.00E+00 1.62E+04 0.00E+00 2.30E+08 ND-147 3.62E+04 3.94E+04 2.36E+03 0.00E+00 2.31 E+04 0.00E+00 1.42E+08 154

AC Number TM -Unit 1 Radiological Controls Procedure 661 O-PLN-4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 24 TABLE 5.7.4 Pathway Dose Factors, Ri AGE GROUP: ADULT PATHWAY: VEGETATION ORGAN DOSE FACTORS; m2 - mrem/year per pCi/sec NUCLICE -----------------------------------------------------------

_ BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI 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.OOE+00 4.64E+04 2.77E+04 1.02E+04 6.15E+04 1.17E+07 MN-54 0.00E+00 3.13E+08 5.97E+07 0.OOE+00 9.31 E+07 0.00E+00 9.58E+08 FE-55 2.10E+08 1.45E+08 3.38E+07 O.00E+00 0.00E+00 8.08E+07 8.31E+07 FE-59 1.26E+08 2.97E+08 1.14E+08 0.OOE+00 0.00E+00 8.29E+07 9.89E+08 CO-58 0.00E+00 3.07E+07 6.89E+07 0.OOE+OC 0.OOE+00 0.OOE+00 6.23E+08 CO-60 0.00E+00 1.67E+08 3.69E+08 0.OOE+0( 0.00E+00 0.OOE+00 3.14E+09 NI-63 1.04E+10 7.21E+08 3.49E+08 0.00E+0C 0.00E+00 0.OOE+00 1.50E+08 ZN-65 3.17E+08 1.01 E+09 4.56E+08 0.OOE+OC 6.75E+08 0.OOE+00 6.36E+08 RB-86 0.00E+00 2.19E+08 1.02E+08 0.OQE+OC 0.00E+00 0.OOE+00 4.32E+07 SR-89 9.98E+09 0.00E+00 2.86E+08 0.00E+0C 0.00E+00 0.OOE+00 1.60E+09 SR-90 6.05E+11 0.00E+00 1.48E+11 0.OOE+OC 0.O0E+00 O.OOE+00 1.75E+10 Y-91 5.12E+06 0.O0E+00 1.37E+05 0.OOE+OC 0.OOE+00 O.OOE+00 2.82E+09 ZR-95 1.17E+06 3.77E+05 2.55E+05 O.OOE+00 5.91E+05 0.OOE+00 1.19E+09 NB-95 1.42E+05 7.92E+04 4.26E+04 0.OOE+00 7.83E+04 0.OOE+00 4.81 E+08 RU-1 03 4.77E+06 0.00E+00 2.06E+06 Q.OOE+00 1.82E+07 0.OOE+00 5.57E+08 RU-106 1.93E+08 0.OOE+00 2.44E+07 0.OOE+00 3.72E+08 0.00E+00 1.25E+10 AG-1101i 1.05E+07 9.75E+06 5.79E+06 0.OOE+00 1.92E+07 0.OOE+00 3.98E+09 TE-1251A 9.66E+07 3.50E+07 1.29E+07 2.90E+07 3.93E+08 0.OOE+00 3.86E+08 TE-1271A 3.49E+08 1.25E+08 4.26E+07 8.93E+07 1.42E+09 O.OOE+00 1.17E+09 TE-129M 2.51 E+08 9.37E+07 3.97E+07 8.63E+07 1.05E+09 0.OOE+00 1.26E+09 1-131 8.08E+07 1.16E+08 6.62E+07 3.79E+1 0 1.98E+08 0O.OOE+00 3.05E+07 1-133 2.09E+06 3.63E+06 1.11 E+06 5.34E+08 6.33E+06 0.OOE+00 3.26E+06 CS-134 4.67E+09 1.11E+10 9.08E+09 0.OOE+00 3.59E+09 1.19E+09 1.94E+08 CS-136 4.28E+07 1.69E+08 1.22E+08 0.00E+00 9.41 E+07 I1.29E+07 1.92E+07 CS-1 37 6.36E+09 8.70E+09 5.70E+09 0.OOE+00 2.95E+09 9.81 E+08 1.68E+08 BA-140 1.29E+08 1.62E+05 8.47E+06 0.OOE+00 5.52E+04 9.29E+04 2.66E+08 CE-141 1.97E+05 1.33E+05 1.51 E+04 0.OOE+00 6.20E+04 O.OQE+00 5.1 OE+08 CE-144 3.29E+07 1.38E+07 1.77E+06 0.OQE+00 8.16E+06 0.OOE+00 1.11 E+10 PR-143 6.25E+04 2.51E+04 3.10E+03 0.OOE+00 1.45E+04 0.OOE+00 2.74E+08 ND-147 3.34E+04 3.85E+04 2.31 E+03 0.OOE+00 2.25E+04 0.OOE+00 1.85E+08 155

Number TMI - Unit 16 Radiological Controls Procedure 661 O-PLN4200.O1 Title .Revision No.

Offsite Dose Calculation Manual (ODCM) 24 6.0 TMI-1 GASEOUS WASTE TREATMENT SYSTEM 6.1 Description of the TMI-1 Gaseous Radwaste Treatment System (see Figure 6.1) 6.1.1 Waste Gas System

a. Reactor Building:

- Reactor Coolant Drain Tank (RCDT) header

b. Auxiliary Building:

- Vent Header from

1. Miscellaneous Waste Storage Tank (MWST)

2. Three (3) Reactor Coolant Bleed Tanks (RCBT)

- Waste Gas Delay Tank

- Two (2) Waste Gas Compressors

- Three (3) Waste Gas Decay Tanks (WGDT)

c. Filtration and dilution provided by the Station Ventilation System.

6.2 Operability Operability of the Gaseous Waste Treatment System is defined as the ability to remove gas from the vent header/tank gas spaces and store it under a higher pressure in the Waste Gas Decay Tanks for subsequent release.

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 system 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 about 16.4 psia.

156

W Number TMI- Unit I Radiological Controls Procedure 661 O-PLN-4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 24 FIGURE 6.1 Waste Gas System POIswMAm WALK#$

157

Number TMI - Unit I Radiological Controls Procedure 661 0-PLN-4200.01 Title oClao a ln{No.

Offsite Dose Calculation Manual (ODCM) 24 7.0 EFFLUENT TOTAL DOSE ASSESSMENT 7.1 Total Dose Calculation The annual (calendar year) dose or dose commitment 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 shall 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.

The total dose from TMI-1 and TMI-2 (uranium fuel cycle facilities within 8 kilometers) is calculated 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 direct radiation from the site from the environmental monitoring program's direct radiation (TLD) monitors.

158

'~

Number TMI - Unit I Radiological Controls Procedure 661 O-PLN-4200.01 Title DuRevisaon No.

Offsite Dose Calculation Manual (ODCM) 24 8.0 TMINS RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) 8.1 Mvionitoring Proqram Requirements 83.1.1 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.

13.1.2 Applicability At all times.

13.1.3 Action

a. With the radiological environmental monitoring program not being conducted as specified in Table 8.1, prepare and submit to the Commission in the Annual Radiological Environmental Operating Report, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.

b. With the level of radioactivity as the result of plant effluents in an environmental sampling medium exceeding the reporting levels of Tabla 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 ODCM Part I Controls 2.2.1.2, 2.2.2.2 and 2.2.2.3 and ODCM Part II Controls 2.2.1.2, 2.2.2.2 and 2.2.2.3. 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) + 210 reportinglevel (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 ODCM Part I Controls 2.2.1.2, 2.2.2.2 and 2.2.2.3 and ODCM Part 11, Controls 2.2.1.2, 2.2.2.2 and 2.2.2.3. This report is not required if the measured level of radioactivity was not the result of plant effluents; hovwever, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report.

The method )logy and parameters used to estimate the potential annual dose to a member of the public shall be indicated in this report.

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Number TMI- Unit 1 Radiological Controls Procedure I 661 0-PLN-4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 24

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 TMI-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 samples.

8.1.4 Bases The radiological monitoring program required by this control provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides which lead to the highest potential radiation exposures of members of the general public resulting from the station operation. This monitoring program implementsSection IV B.2 of Appendix I to 10CFR50 and thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways. Guidance 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 Requirements The radiological environmental monitoring samples shall be collected pursuant to Table 8.1, from the 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.

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Offsite Dose Calculation Manual (ODCM) 24 8.2 L-and Use Census 3.2.1 Controls 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 of greater than 50 m2 (500 ft2 ) producing broad leaf vegetation.

.3.2.2 Applicability At all times.

3.2.3 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 ODCM Part I Surveillance 3.2.2.3.1, pursuant to ODCM, Part IV, 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 dose 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 including a revised figure(s) and table(s) for the ODCM reflecting the new location s) with information supporting the change in sampling locations.

Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the site boundary in each of two different sectors with the highest predicted D/Qs in lieu of the garden census.

Requirements for broad leaf sampling in Table 8.1 shall be followed, including analysis of control samples.

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Offsite Dose Calculation Manual (ODCM) 24 8.2.4 Bases This Control is provided to ensure that changes in th6 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 authorities shall be used. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR 50. Restricting the census to gardens of greater than 500 square feet (50 M2 ) provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/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.

8.2.5 Surveillance Requirements The Land 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-to-door 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 IV, Section 1.0.

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Offsite Dose Calculation Manual (ODCM) 24 8.3 Interlaboratory Comparison Program 8.3.1 Controls In accordance with the TMI-1 Tech. Specs. and TMI-2 PDMS Tech. Specs., analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program which has been approved by the Commission (NRC). Only tlose samples and analyses which are required by Table 8.1 shall be performed.

3.3.2 Applicability At all times.

8.3.3 Action 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.

8.3.4 Bases The requirement for participation in an approved Interlaboratory Comparison Program is provided to ensure that independent checks on precision and accuracy of the measurements of radioactive material in environmental sample matrices are perfonrned as part of a quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid for the purpose of Section IV, B.2 of Appendix I to 10 CFR 50.

B.3.5 Surveillance Requirements A summary of the Interlaboratory Comparison Program results shall be included in the Annual Radiological Environmental Operating Report.

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Offsite Dose Calculation Manual (ODCM) 24 TABLE 8.1 Sample Collection and Analysis Requirements Number of Samples Exposure Pathway and Sampling and Type and Frequency and/or Sample Sample Locations" Collection Frequencyb of Analysisb l1. Airbornel Radioiodine and Samples from 5 locations Continuous sampler operation Radioiodine Canister:

Particulates from Table 8.4. with sample collection weekly, Analyze weekly for 1-131 .

or more frequently if required Particulate Filter:

by dust loading. Analyze for gross beta radioactivity following filter changed. Perform gamma isotopic analysiso on composite (by location) sample quarterly.

2. Direct Radiationc Samples from 40 locations Sample Quarterly Analyze for gamma dose from Table 8.5 (using either quarterly.

2 dosimeters or at least 1 instrument for continuously measuring and recording dose rate at each location).

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Offsite Dose Calculation Manual (ODCM) _ 24I TABLE 8.1 Sample Collection and Analysis Requirements I, 11

a. Surface' Samples from 2 locations Compositeg sample over Perform gamma isotopic from Table 8.6. I monthly period. analysise monthly.

Composite for tritium

. 1 sample from analysis quarterly.

downstream (indicator) location

. 1 sample from upstream (control) location (or location not influenced by the station discharge)

b. Drinking Samples from 2 locations Compositeg sample over Perform gross beta and from Table 8.6. 1 monthly period. gamma isotopic analysis' monthly. Perform Sr-90

1sample at the location analysis if gross beta of of the nearest water monthly composite >.j0 supply that could be times control. Composite for affected by the station tritium analysis quarterly.

discharge.

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) analysise on each sample.

from Table 8.7.

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Offsite Dose Calculation Manual (ODCM) 24 TABLE 8.1 Sample Collection and Analysis Requirements l Number of Samples Exposure Pathway and Sampling and Type and Frequency and/or Sample Sample Locationsa Collection Frequencyb of Anal YSiSb

4. Ingestion

a. Milk Samples from 4 locations from Sample semimonthly when Perform gamma isotopic Table 8.8. animals are on pasture; analysise and 1-131 monthly at other times. analysis on each sample.

Composite for Sr-90 analysis quarterly.

b. Fish Samples from 2 locations from Sample twice per year Perform gamma isotopice Table 8.9. (Spring and Fall). and Sr-90 analysis on edible portions.

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

1 sample of recreationally important bottom feeders and 1 sample of recreationally important predators from an area not influenced by the station discharge.

c. Food Samples from 2 locations Sample at time of harvest. Perform gamma Products from Table 8.10 (when isotopice, 1-131, and available) Sr-90 analysis on edible portions.

. 1 sample of green leafy vegetables or leafy vegetation at a location in the immediate vicinity of the station. (indicator)

1 sample of same species or group from a location not influenced by the station discharge.

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Offsite Dose! Calculation Manual (ODCM) 24 TABLE 8.1 Sample Collection and Analysis Requirements Table Notation

a. Sampling locations are provided in Tables 8.4 through 8.10. They are depicted in Maps 8.1 through ;3.3.

Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment and other legitimate reasons. All deviations from the sampling schedule shall be explained in the Annual Radicological Environmental Operating Report.

b. Frequency notation: weekly (7 days), semimonthly (15 days), monthly (31 days), and quarterly (92 days).

All surveillance requirements shall be performed within the specified time interval with a maximum allowable 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 specified collection or analysis interval.

c. One or more instruments, such as a pressurized ion chamber for measuring and recording dose rate continuously, may be used in place of, or in addition to, integrating dosimeters. For the purpose of this table, a thermoluminescent dosimeter (TLD) is considered to be one phosphor; two or more phosphors in a packet are considered as two or more dosimeters. Film badges shall not be used as dosimeters for measur ng direct radiation.

d. Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in an air particulate samrple(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 sample.

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Offsite Dose Calculation Manual (ODCM) 24 TABLE 8.2 Reporting Levels for Radioactivity Concentrations in Environmental Samples I Airborne Particulate l Water or gas Fish Milk Food Products

___Analysis (pCi/L) (pCi/M 3) (pCi/kg,wet) (pCi/L) (pCi/kg, wet)

H-3 20,000(a)

Mn-54 1000 30,000 Fe-59 400 10,000 Co-58 1000 30,000 Co-60 300 10,000 Zn-65 300 20,000 Sr-90 8 0.1 100 8 100 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 (a) For drinking water samples. This is 40 CFR Part 141 value.

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Title Offsite Dose Calculation Manual (ODCM) 24 TABLE 8.3 Detection Capabilities for Environmental Sample Analysisa Lower Limit of Detection (LLD)b .

Airborne Particulate Fish Food Sediment Water or Gas (pCi/kg, Milk Products (pCilkg, Analysis (pCi/L) (pCi/m3) wet) (pCi/L) (pCi/kg,wet) dry)

Gross Beta 4 0.01 H-3 2000 Mn-54 15 130 Fe-59 30 260 Co-58, 60 15 130 Zn-65 30 260 Zr-95 30 Sr-90 2 0.01 10 2 10 Nb-95 15 1-131 1d 0.07 1 60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180.

Ba-140 60 60 La-140 15 15 169

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Offsite Dose Calculation Manual (ODCM) - 24 TABLE 8.3 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 maBy be related to plant 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).

c. The LLD is defined, for purposes of these controls, as the smallest concentration of radioactive material in a sample tiat will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system (which may include radiochemical separation):

lLD

=4.66 Sb ILD = 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 volume.

Sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate, as counts per minute, E is the counting efficiency, as counts per disintegration, V is the sample size in units of mass or volume, 2.22 is the number of disintegrations per minute per picocurie, Y is the fractional radiochemical yield (when applicable),

Xis 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 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 LLD is defined as an "a priori" (before the fact) limit representing the capability of a measurement system and not as an "a posteriori" (after the fact) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved urder routine conditions. Occasionally background fluctuations, unavoidable small samples 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.

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Offsite Dose Calculation Manual (ODCM) 24 TABLE 8.4 TMINS REMP Station Locations-Air Particulate and Air Iodine Station Code Distance (miles) Azimuth (1) Map No.

B114 0.8 28 60 El-2 0.4 95 2 F1l-3 0.6 105 70 G2-1 1.4 125 74

- M2-1 1.3 253 3 A3-1 2.6 358 4 H3-1 2.3 159 5 Q4-1 3.5 325 61 Q15-1 13.5 305 8 TABLE 8.5 TMINS REMP Station Locations-Direct Radiation (TLD)

Station Code Distance (miles) Azimuth (0) Map No.

A1-4 0.3 5 9 B1-1 0.6 25 10 B13-2 0.4 26 11 C1-2 0.3 54 13 D1-1 0.2 74 14 El-2 0.4 95 2 E1-4 0.2 98 16 F1-2 0.2 109 17 G1-3 0.3 129 18 HI-I 0.5 167 19 J,1-1 0.8 184 -21 J,1-3 0.3 189 22 K1-4 0.2 208 24 1-1I 0.1 235 26 M1-1 0.1 249 27 N1-3 0.1 270' 28 P1-1 0.4 293 29 P1-2 0.2 290 30 171

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Offsite Dose Calculation Manual (ODCM) 24 TABLE 8.5 TMINS REMP Station Locations-Direct Radiation (TLD)

Station Code Distance (miles) Azimuth (°) Map No.

QI-'2 0.2 318 31 Rl-'l 0.2 335 32 C2-l 1.6 48 33 K2-'i 1.1 200 34 M2-i 1.3 253 3 A3-1 2.6 358 4 H3-1 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 F5-1 4.7 107 39 G5-1 4.8 131 40 H5-1 4.1 157 41 J5-1 4.9 182 42 K5-1 5.0 200 43 L5-1 4.1 228 44 M5-1 4.3 249 45 N5-1 4.9 268 46 P5-1 4.9 285 47 Q5-1 5.0 318 48 R5-1 4.9 339 49 D6-1 5.2 65 50 E7-1 6.8 86 51 Q9-1 8.5 308 52 B10-1 9.4 21 53 G10-1 9.8 127 6 G15-1 14.4 124 54 J15-1 12.6 180 7 Q15-1 13.5 305 8 172

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Offsite Dose Calculation Manual (ODCM) 24 TABLE 8.6 TMINS REMP Station Locations-Surface Water Station Code Distance (miles) Azimuth (0) Map No.

JI-2 (R) 0.5 188 57 A3-2 (R) 2.5 355 59 Q9-1 (F) 8.5 308 52 Q9-1 (R) 8.5 308 52 G15-2 (F) 13.6 128 62 G15-3 (F) 14.8 124 63 F15-1 (R) 12.6 122 65 (R) = Raw Water (F) = Finished Water TABLE 8.7 TMINS REMP Station Locations-Aquatic Sediment Station Code Distance (miles) Azimuth (0) Man No.

Al-3 0.5 0 67 G1-1 0.3 137 68 KI -3 0.3 202 69 J2-1 1.5 182 58 J,1-2 0.5 188 57 173

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Offsite Dose Calculation Manual (ODCM) 24 TABLE 8.8 TMINS REMP Station Locations-Milk Station Code Distance (miles) Azimuth (0) Map No.

D2-1 1.1 65 72 E2-2 1.1 93 73 G2-l 1.4 125 74 P7-'S 6.7 293 77 KI 5-3 14.5 205 78 TABLE 8.9 TMINS REMP Station Locations-Fish Station Code Station Location IND Downstream of Station Discharge BKG Upstream of Station Discharge 174

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Offsite Dose Calculation Manual (ODCM) 24 TABLE 8.10 TMINS REMP Station Locations-Food Products Station Code Distance (miles) Azimuth (0) Map No.

Dl-3 0.5 65 79 El-2 0.4 95 2 Fl-I 0.5 117 80 Al 5-1 10.5 10 85 B10-2 10.1 28 55 175

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Offsite Dose Calculation Manual (ODCM) 24 MAP 8.1 THREE MILE ISLAND NUCLEAR STATION LOCATIONS OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM STATIONS WITHIN 1 MILE OF THE SITE 101.25' 176

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Offsite Dose Calculation Manual (ODCM) 24 MAP 8.2 THREE MILE ISLAND NUCLEAR STATION LOCATIONS OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM STATIONS WITHIN 5 MILES OF THE SITE 348.75' A I15 177

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Offsite Dose Calculation Manual (ODCM) 24 MAP 8.3 THREE MILE ISLAND NUCLEAR STATION LOCATIONS OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM STATIONS GREATER THAN 5 MILES FROM THE SITE 348.75- A 11.25-I 191.2S- j 168.75' 178

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Offsite Dose Calculation Manual (ODCM) - 24 9.0 PART lIl 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 I to Demonstrate Conformance to the Design Objectives of 10 CFR 50, Appendix I," Nuclear Safety Associates, May 1976

3. TMI-1 Final Safety Analysis Report (FSAR)

4. TMI-2 Final Safety Analysis Report (FSAR)

5. Meteorological Information and Dose Assessment System (MIDAS)

6. NUREG-0017, "Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from PWR," Revision 1, 1985

7. NUREG-0133, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," October 1978

8. NUREG-0172, "Age-Specific Radiation Dose Commitment Factors ForA One-Year Chronic Intake,"

November 1977

9. Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water Cooled Nuclear Power Plants," Revision 1, June 1974

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 I," Revision 1, October 1977

11. Simplified Environmental Effluent Dosimetry System (SEEDS)

12. TMI Recirculation Factor Memos, April 12, 1988 and March 17, 1988

13. TMI-1 Operations Procedure, 1101-2.1, "Radiation Monitor Set Points"

14. Title 10, Code of Federal Regulations, "Energy"

15. TMI-1 Technical Specifications, attached to Facility Operating License No. DPR-50

16. Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977

17. TMI-2 PDMS Technical Specifications, attached to Facility License No. DPR-73

18. Radiological Assessment Branch Technical Position on Environmental Monitoring, Revision 1, November 1979

19. Title 40, Code of Federal Regulations, "Protection of Environment" 179

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Offsite Dose Calculation Manual (ODCM) 24fo

20. Regulatory Guide 4.13, "Performance, Testing, and Procedural Specifications for Thermoluminescence Dosimetry: Environmental Applications," Revision 1, July 1977

21. Post-Defueling Monitored Storage Safety Analysis Report (PDMS SAR) 180

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Offsite Dose Calculation Manual (ODCM) 24 PART IV REPORTING REQUIREMENTS 181

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Offsite Dose Calculation Manual (ODCM) 24 PART IV 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 Es 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 III, Section 8.2.

1.3 The Annual Radiological Environmental Operating Reports shall include the summarized tabulated results of analysis of all radiological environmental samples and environmental radiation measurements required by Part liI 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 tabulated results of these analyses and measurements in a format similar to the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report, the report shall be submitted 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 shall 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 Interlaboratory Comparison Program, required by Part Ill, Section 8.3; discussion of all deviations from the sampling schedule of Part III, Table 8.1; discussion of all the required analyses in which the LLD required by Part 1II,Table 8.3 was not achievable.

A single submittal may be made for the station.

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Offsite Dose Calculation Manual (ODCM) 24 2.0 TMI ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NOTE A single submittal may be made for the station. The submittal should combine those sections that are common to both units at the station 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 prior to May 1 for TMI-1 and 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 quarterly 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 determined 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 IlIl Section 8.2.

2.6 The Radioactive Effluent Release Reports shall include the instrumentation not returned to OPERABLE status within 30 days per ODCM Part I Controls 2.1.1b and 2.1.2b, and ODCM Part II Control 2.1.2b.

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Offsite Dose Calculation Manual (ODCM) 24 2.7 The Radioactive Effluent Release Report to be submitted shall include an annual summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing of wind speed, wind direction, atmosphere stability, and precipitation (if measured) on magnetic tape, or in the form of joint frequency distribution of wind speed, "ind direction, and atmospheric stability.

2.8 The Radioactive Effluent Release Report shall include an assessment of the radiation doses to MEMBERS OF THE PUBLIC due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year. 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.

2.9 The Radioactive Effluent Release Report shall include an assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY during the report period, to verify compliance with the limits of 10CFR20.1301(a)(1). All assumptions used in making these assessments (i.e., specific activity, exposure time and location) shall be included in these reports.

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 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.

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Offsite Dose Calculation Manual (ODCM) 24 3.0 PART IV 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 Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974 3.3 TMI-1 Technical Specifications, attached to Facility Operating License 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 I," 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 from Light-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 Light-Water-Cooled Power Reactors," Revision O-R, April 1976 3.9 Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," Revision 1, April 1977 185

Number TMI - Unit 1 Radiological Controls Procedure I 6610-PLN-420'D.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 24 APPENDIX A Page 1 of 1 PI - Pathway Dose Rate Parameter Pi (inhalation):: k' (BR) DFA1 (Eq A-1)

Where:

PI = the pathway dose rate parameter for radionuclide, i, (other than noble gases) for the inhalation pathway, in mrem/yr per microcurie/m 3 . The dose factors are based on the critical individual organ for the child age group.

k'= conversion factor, I E6 pCi/microcurie BR = .3700 m3/yr, breathing rate for child (Reg. Guide 1.109, Rev. 1, Table E-5)

DFA1 = the maximum organ inhalation dose factor for the infant age group for the ith radionuclide (mRem/pCi).

Values are taken from Table E-10, Reg. Guide 1.109 (Rev. 1), or NUREG-01 72.

Resolut on of the units yields: (ODCM Part IlIl Table 4.6)

PI (inhalation) :: 3.7E9 DFA 1 (mremlyr per pCi/m 3) (Eq A-2)

NOTE The latest NRC Guidance has deleted the requirement to determine Pi (ground plane) and Pi (food). In addition, the critical age group has been changed from infant to child.

186

Number TMI - Unit 1 Radiological Controls Procedure 661 O-PLN-4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 24 APPENDIX B Page 1 of I Ri - Inhalation Pathway Dose Factor RI = k' (BR) (DFAia,o) (mremfyr per microcurielm 3 ) (Eq B-1)

Where:

k'= conversion factor, I E6 pCi/microcurie BR = breathing rate, 1400, 3700, 8000, 8000 m3 /yr for infant, child, teenager, and adult age groups, respectively. (Reg. Guide 1.109, Rev. 1, Table E-5)

DFAI,a,o = the inhalation dose factor for organ, o, of the receptor of a given age group, a, and for the ith radionuclide, in mrem/pCi. The total body is considered as an organ in the selection of DFA,18 O.

Values are taken from Tables E-7 through E-10, Reg. Guide 1.109 (Rev. 1), or NUREG 0172.

Resolutions of the units yields:

RI = (1.4E9) (DFA, 8 0) infant (ODCM Part IlIl Table 5.2.1)

RI = (3.7E9) (DFA-,.,,) child (ODCM Part III Table 5.2.2)

Ri = (8.0E9) (DFA-a o) teen and adult (ODCM Part IlIl Tables 5.2.3 and 5.2.4) 187

Number TMI - Unit 1 I Radiological Controls Procedure 661 0-PLN-4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 24 APPENDIX C Page 1 of Ri - Ground Plane Pathway Dose Factor Ri k' k" (SF) (DFGj) [(1-e xit)/IXi] (Eq C-1)

Where:

k' = conversion factor, I E6 pCi/microcurie k" = conversion factor, 8760 hr/yr

%I= decay constant for the ith radionuclide, sec 1 t = the exposure time (this calculation assumes that decay is the only operating removal mechanism) 4.73 x 108 sec. (15 yrs), Reg. Guide 1.109 (Rev. 1), Appendix C DFGI = the ground plane dose conversion factor for the ijh radionuclide (mrem/hr per pCi/M 2 ). Values are taken from Table E-6, Reg. Guide 1.109 (Rev. 1), or NUREG 0172. These values applv to al age groups.

SF = 0.7, shielding factor, from Table E-15 Reg. Guide 1.109 (Rev. 1)

Reference ODCM Part IlIl Table 5.3.1 188

Number TMI- Unit I Radiological Controls Procedure I 661 0-PLN-4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 24 APPENDIX D Page 1 of 2 Ri - Grass Cow-Milk Pathway Dose Factor R= +

k' [(QF X UAP) I (Xi 4X) x (Fm) X (r) x (DFLiao) x IMp x f.)IYp) + ((I-fp x fQ)e -Lth)1Y 5 ] e-itf (Eq D-1)

Where:

kw = conversion factor, I E6 picocurie/microcurie (pCi/lici)

QF = 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)

UAP = Receptor's milk consumption rate; 330, 330, 400, 310 liters/yr for infant, child, teenager, and adult age groups, respectively (Reg. Guide 1.109, Rev. 1)

Yp = agricultural productivity by unit area of pasture feed grass, 0.7 kg/iM2 (NUREG-0133)

Y, = agricultural productivity by unit area of stored feed, 2.0 kg/m2 (NUREG-0133)

Fm = 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 radioiodine (Table E-15, Reg. Guide 1.109, Rev. 1)

DFL1,8,0 = 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), or NUREG 0172.

X,= decay constant for the ith radionuclide, sec' X, = decay constant for weathering, 5.73 x 10-7 seeI (NUREG-0133); based on a 14 day half life tf = 1.73 x 105 sec, the transport time from pasture to cow to milk to receptor (Table E-15, Reg.

Guide 1.109, Rev. 1), or 2 days th = 7.78 x 106 sec, the transport time from pasture to harvest to cow to milk to receptor (Table E-1 5, Reg. Guide 1.109, Rev. 1), or 90 days fp = 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 189

-Number TMI - Unit 1 I Radiological Controls Procedure 661 0-PLN-4200.01)

Title Revision No.

Offsite Dose Calculation Manual (ODCM) 24 _

APPENDIX D Page 2 of 2 The concentration of tritium in milk is based on the airborne concentration rather than the deposition. Therefore, R, is based on (X/C?):

Rcta.o = k'k." Fm OF UApDFLt,a,o (.75 [.5/H]) (Eq D-2)

Where:

k"' = 1E3 grams/kg H = B grams/M 3 , 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)

DFLtao = the ingestion dose factor for tritium and organ, o, for each respective age group, a (Tables E-il 1 to E-14, Reg. Guide 1.109, Rev. 1), or NUREG 0172.

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. Fm factor for goat-milk will be from Table E-2 Reg. Guide 1.109, Rev. 1.

Reference:

ODCM Part IlIl Tables 5.4.1 to 5.4.4 190

Number TMI - Unit 1 Radiological Controls Procedure I 661 0-PLN-4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 24 APPENDIX E Ri - Cow-Meat Pathway Dose Factor RI k' [(QF X UAP) / (Xi + XW)] x (Ff) x (r) x (DFLrao) x

[((fp x f)JYNp) + ((I-fpfQ) e 4 ith)/YNJ x e*tf (Eq E-1)

Where:

k'= conversion factor, 1 E6 picocurie/microcurie (pCi/[tci)

QF = cow consumption rate, 50 kgfday, (Reg. Guide 1.109, Rev. 1)

UAP = 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)

Ff = the stable 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 radioiodine (Table E-15, Reg. Guide 1.109, Rev. 1)

DFL1,2,0 = 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), or NUREG 0172.

X,= decay constant for the radionuclide i, sec' Xw = decay constant for weathering, 5.73 x 10-7 sec' (NUREG-0133), based on a 14 day half life tt = 1.73 x 106 sec, the transport time from pasture to receptor (NUREG-01 33) th = 7.78 x 106 sec, the transport time from crop to receptor (NUREG-0133)

Yp = agricultural productivity by unit area of pasture feed grass, 0.7 kg/m2 (NUREG-0133)

Y. = agricultural productivity by unit area of stored feed, 2.0 kg/m2 (NUREG-0133) fp = 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 airborne concentration rather than the deposition. Therefore, R1 is based on (X/Q):

Rtao = k'k"' Ff QF UAP (DFLt, ,) 0 x 0.75 x (0.51H]) (Eq E-2)

Where:

All terms are as defined above and in Appendix D.

Reference:

ODCM Part l1l, Tables 5.6.1 to 5.6.4 191

I Number TMI - Unit 1 Radiological Controls Procedure 661 0-PLN-4201).O1 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 24 APPENDIX F Ri - Vegetation Pathway Dose Factor R= k' x [rl (4Y (X + X.))] x (DFLi,a,o) x [(ULA) fL e-"i'L + USA fu e-lith] (Eq F-1)

Where:

k'= 1E6 picocurie/microcurie (pCi/pci)

ULA = the consumption rate of fresh leafy vegetation, 0, 26, 42, 64 kg/yr for infant, child, teenager, or adult age groups, respectively (Reg. Guide 1.109, Rev. 1)

USA = 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) fL = the fraction of the annual intake of fresh leafy vegetation grown locally, = 1.0 (NUREG-0133) fg = the fraction of the stored vegetation grown locally = 0.76 (NUREG-0133) tL = Ihe average time between harvest of leafy vegetation and its consumption, 8.6 x 104 seconds ITable E-15, Reg. Guide 1.109, Rev.1 (24 hrs)]

th = the average time between harvest of stored leafy vegetation and its consumption, 5.18 x 106 seconds, [Table E-15, Reg. Guide 1.109, Rev.1 (60 days)]

Yv = Ihe vegetation area density, 2.0 kg/m2 (Table E-15, Reg. Guide 1.109, Rev. 1)

All other parameters are as previously defined.

The concentration of tritium in vegetation is based on the airborne concentration rather than the deposition.

Therefore, R1 is based on (X/Q)

Rtao = k'k"' [ULA fL + USA fgj (DFLtao) (.75 [.5/H]) (Eq F-2)

Where:

All terms are as defined above and in Appendix D.

Reference:

ODC:M Part IlIl, Tables 5.7.1 to 5.7.4 192

Number TMI - Unit I Radiological Controls Procedure 661 0-PLN-4200.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 24 APPENDIX A-F REFERENCES (Page 1 of 4)

Parameters Used in Dose Factor Calculations l__ _ Origin of Value l Table in Section of Site-Parameter Value R.G. 1.109 NUREG-0133 Specific For Pi DFA; Each radionuclide E-9 Note 1 BR 3700 m3 /yr (child) E-5

- - For Ri (Vegetation)***

r Each element type E-1 Y v 2.0 kg/rm2 E-1 5 xw 5.73 E-7 sec' 5.3.1.3 DFLI Each age group and radionuclide E-11 thru E-14 Note 1 Ua Each age group E-5l fL 1.0 5.3.1.5 tL 8.6 E + 4 seconds E-15 UaS Each age group E-5 fg 0.76 5.3.1.5 th5.18 E + 6 seconds E-15 H 8.0 grams/kg 5.2.1.3

'For Ri (Inhalation)'**

BR Each age group E-5 Each age group and E-7 thru E-10 Note 1

~nuclide DF _ __ _ _ I__ _ _ _ _ _ I__ I_ _ _ __ _

193

Number TMI - Unit I Radiological Controls Procedure 661 O-PLN-4200.01 Revision No.

Title 24 Offsite Dose Calculation Manual (ODCM)

APPENDIX A-F REFERENCES (Page 2 of 4)

Parameters Used in Dose Factor Calculations Origin of Value Table in Section of Site-Parameter Value R.G. 1.109 NUREG-0133 Specific For RI (Ground Plane)

SF 0.7 E-1 5 DFGj Each radionuclide E-6 t 4.73 E + 8 sec 5.3.1.2 For Ri (GrasslAnimal/Meat)

QF(COW) 50 kg/day E-3 6 kg/day E-3 Ref. Only QF (Goat)

Uap Each age group E-5 xw 5.73 E-7 sec1 5.3.1.3 F.(Both) Each element E-1 r Each element type E-15 Each age group and nuclide E-1 1 thru E-14 Note 1 DFL4 5.3.1.3 Note 1.0 fp 1.0 5.3.1.3 Note 2 YP 0.7 kg/m3 E-1 5 th 7.78 E + 6 sec E-15 2.0 kg/M 2 E-15 _

1.73 E + 6 sec E-15 H 8.0 grams/kg 5.2.1.3 194

Number TMI - Unit 1 Radiological Controls Procedure 661 0-PLN-4200.01 Revision No.

Title Offsite Dose Calculation Manual (ODCM) 24 APPENDIX A-F REFERENCES (Page 3 of 4)

Parameters Used in Dose Factor Calculations

]___ _ lOrigin of Value l Table in Section of Site-P Parameter Value R.G. 1.109 NUREG-0133 Specific l For RI (Grass/Cow/Milk)

Qf 50 kg/day E-3 Uap Each age group E-5 l 5.73 E-7 sec' 5.3.1.3 Fm Each element E-1 r Each element type E-1 5 DFL, Each age group and nuclide E-1 1 thru E-14 Note 1 Yp 0.7 kg/M2 E-1 5 th 7.78 E + 6 sec E-15 Y, 2.0 kg/iM2 E-1 5 If1.73 E + 5 sec E-15 fp 1.0 5.3.1.3 I's 1.0 5.3.1.3 H 8.0 grams/kg 5.2.1.3 195

Number TMI - Unit 1 Radiological Controls Procedure 661 0-PLN-420D.01 Title Revision No.

Offsite Dose Calculation Manual (ODCM) 24 APPENDIX A-F REFERENCES (Page 4 of 4)

NOTES

1. 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.

2. Typically beef cattle are raised all year on pasture. Annual land surveys have indicated that the small 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 cannDt sustain the meat consumption rates of Table E-5, NUREG-0133.

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 I," Revision 1, October 1977.

2. TMI-1 Technical Specifications, attached to Facility Operating License No. DPR-50.

3. NUREG..0133, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants,"

October 1978.

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