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ODCM Change for TMI, Offsite Dose Calculation Manual, Revision 3, CY-TM-170-300
	ML15126A391
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Site:	Three Mile Island
Issue date:	04/30/2015
From:	Haaf T; Exelon Generation Co
To:	; Document Control Desk, Office of Nuclear Material Safety and Safeguards
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ML15126A376	List: ML15126A389; ML15126A390; TMI-15-052, ODCM Change for TMI, Offsite Dose Calculation Manual, Revision 3, CY-TM-170-300;
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	TMI-15-052 CY-TM-170-300, Rev. 3
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2014 Annual Radioactive Effluent Release Report for TMI Enclosure I - Page I of I ODCM Change for TMI Offsite Dose Calculation Manual, Revision 3 CY-TM-170-300 (Revision 3 was issued on May 23, 2012)

CY-TM-1 70-300 Revision 3 En Page 1of 209 Nuclear Level 3 - Information Use OFFSITE DOSE CALCULATION MANUAL (ODCM)

INTRODUCTION The OFFSITE DOSE CALCULATION MANUAL (ODCM) is a supporting document of the Three Mile Island Nuclear Station (TMI) Unit 1 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 1 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.

This procedure replaces 6610-PLN-4200.01.

CY-TM-1 70-300 Revision 3 Page 2 of 209 TABLE OF CONTENTS PART I TMI-1 RADIOLOGICAL EFFLUENT CONTROLS Section Page 1.0 DEFINITIONS 13 Table 1-1, Frequency Notation 18 Mapl.1, Gaseous Effluent Release Points and Liquid Effluent Outfall Locations 19 2.0 RADIOLOGICAL EFFLUENT CONTROLS AND BASES 20 2.1 Radioactive Effluent Instrumentation 20 2.1.1 Radioactive Liquid Effluent Instrumentation 20 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 Radioactive Effluent Controls 30 2.2.1 Liquid Effluent Controls 30 2.2.2 Gaseous Effluent Controls 34 2.2.3 Total Radioactive Effluent Controls 41 3.0 SURVEILLANCES 44 3.1 Radioactive Effluent Instrumentation 44 3.1.1 Radioactive Liquid Effluent Instrumentation 44 Table 3.1-1, Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements 45 3.1.2 Radioactive Gaseous Process and Effluent Monitoring Instrumentation 47 Table 3.1-2, Radioactive Gaseous Process and Effluent Monitoring Instrumentation Surveillance Requirements 48

CY-TM-1 70-300 Revision 3 Page 3 of 209 TABLE OF CONTENTS (Cont'd)

PART I TMI-1 RADIOLOGICAL EFFLUENT CONTROLS Section Paqe 3.2 Radiological Effluents 53 3.2.1 Liquid Effluents 53 Table 3.2-1, Radioactive Liquid Waste Sampling and Analysis Program 55 3.2.2 Gaseous Effluents 58 Table 3.2-2, Radioactive Gaseous Waste Sampling and Analysis Program 60 3.2.3 Total Radioactive Effluents 64 4.0 PART I REFERENCES 65

CY-TM-1 70-300 Revision 3 Page 4 of 209 TABLE OF CONTENTS (Cont'd)

PART II TMI-2 RADIOLOGICAL EFFLUENT CONTROLS Section Page 1.0 DEFINITIONS 67 Table 1.1, Frequency Notation 70 2.0 CONTROLS AND BASES 71 2.1 Radioactive Effluent Instrumentation 71 2.1.1 Radioactive Liquid Effluent Instrumentation 71 2.1.2 Radioactive Gaseous Process and Effluent Monitoring Instrumentation 71 Table 2.1-2, Radioactive Gaseous Process and Effluent Monitoring Instrumentation 73 2.2 Radioactive Effluent Controls 74 2.2.1 Liquid Effluent Controls 74 2.2.2 Gaseous Effluent Controls 78 2.2.3 Total Radioactive Effluent Controls 85 3.0 SURVEILLANCES 87 3.1 Radioactive Effluent Instrumentation 87 3.1.1 Radioactive Liquid Effluent Instrumentation 87 3.1.2 Radioactive Gaseous Process and Effluent Monitoring Instrumentation 87 Table 3.1-2, Radioactive Gaseous Process and Effluent Monitoring Instrumentation Surveillance Requirements 88 3.2 Radioactive Effluents 89 3.2.1 Liquid Effluents 89 Table 3.2-1, Radioactive Liquid Waste Sampling and Analysis Program 90 3.2.2 Gaseous Effluents 91

CY-TM-1 70-300 Revision 3 Page 5of 209 TABLE OF CONTENTS (Cont'd)

PART II TMI-2 RADIOLOGICAL EFFLUENT CONTROLS Section Page Table 3.2-2, Radioactive Gaseous Waste Sampling and Analysis Program 92 3.2.3 Total Radioactive Effluents 95 4.0 PART II REFERENCES 96

CY-TM-1 70-300 Revision 3 Page 6 of 209 TABLE OF CONTENTS (Cont'd)

PART III EFFLUENT DATA AND CALCULATIONAL METHODOLOGIES Section Page 1.0 LIQUID EFFLUENT MONITORS 98 1.1 TMI-1 and TMI-2 Liquid Radiation Monitor Set Points 98 1.2 TMI Liquid Effluent Release Points and Liquid Radiation Monitor Data 99 1.3 Control of Liquid Releases 101 2.0 LIQUID EFFLUENT DOSE ASSESSMENT 106 2.1 Liquid Effluents - 10 CFR 50 Appendix I 106 2.2 TMI Liquid Radwaste System Dose Calcs Once Per Month 107 2.3 Alternative Liquid Dose Calculational Methodology 108 3.0 TMI LIQUID EFFLUENT WASTE TREATMENT SYSTEM 113 3.1 TMI-1 Liquid Effluent Waste Treatment System 113 3.2 Operability of the TMI-1 Liquid Effluent Waste Treatment System 114 3.3 TMI-2 Liquid Effluent Waste Treatment System 114 4.0 GASEOUS EFFLUENT MONITORS 117 4.1 TMI-1 Noble Gas Monitor Set Points 117 4.2 TMI-1 Particulate and Radioiodine Monitor Set Points 119 4.3 TMI-2 Gaseous Radiation Monitor Set Points 120 4.4 TMI-1 Gaseous Effluent Release Points and Gaseous Radiation Monitor Data 121 4.5 TMI-2 Gaseous Effluent Release Points and Gaseous Radiation Monitor Data 123 4.6 Control of Gaseous Effluent Releases 124

CY-TM-1 70-300 Revision 3 Page 7 of 209 TABLE OF CONTENTS (Cont'd)

PART III EFFLUENT DATA AND CALCULATIONAL METHODOLOGIES Section Page 5.0 GASEOUS EFFLUENT DOSE ASSESSMENT 136 5.1 Gaseous Effluents - Instantaneous Release Limits 136 5.1.1 Noble Gases 136 5.1.1.1 Total Body 136 5.1.1.2 Skin 137 5.1.2 lodines, Tritium and Particulates 138 5.2 Gaseous Effluents - 10 CFR 50 Appendix I 139 5.2.1 Noble Gases 139 5.2.2 lodines, Tritium and Particulates 140 5.3 Gaseous Radioactive System Dose Calculations Once per Month 142 5.4 Alternative Gaseous Dose Calculational Methodology 143 6.0 TMI-1 GASEOUS EFFLUENT WASTE TREATMENT SYSTEM 165 6.1 Description of the TMI-1 Gaseous Radwaste Treatment System 165 6.2 Operability of the TMI-11 Gaseous Radwaste Treatment System 165 7.0 EFFLUENT TOTAL DOSE ASSESSMENT 167 8.0 TMINS RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) 168 8.1 Monitoring Program Requirements 168 8.2 Land Use Census 171 8.3 Interlaboratory Comparison Program 173 9.0 PART Ill REFERENCES 191

CY-TM-1 70-300 Revision 3 Page 8 of 209 TABLE OF CONTENTS (Cont'd)

PART III EFFLUENT DATA AND CALCULATIONAL METHODOLOGIES Section Page TABLES Table 1.1 TMI Liquid Release Point and Liquid Radiation Monitor Data 102 Table 1.2 TMI-2 Sump Capacities 103 Table 2.1 Liquid Dose Conversion Factors (DCF): DFij 109 Table 2.2 Bioaccumulation Factors, BF1 112 Table 4.1 TMI-1 Gaseous Release Point and Gaseous Radiation Monitor Data 125 Table 4.2 TMI-2 Gaseous Release Point and Gaseous Radiation Monitor Data 126 Table 4.3 Dose Factors for Noble Gases and Daughters 127 Table 4.4 Atmospheric Dispersion Factors for Three Mile Island - Station Vent 128 Table 4.5 Atmospheric Dispersion Factors for Three Mile Island - Ground Release 129 Table 4.6 Dose Parameters for Radioiodines and Radioactive Particulate In Gaseous Effluents 130 Table 5.2.1 Pathway Dose Factors, Ri - Infant, Inhalation 144 Table 5.2.2 Pathway Dose Factors, Ri - Child, Inhalation 145 Table 5.2.3 Pathway Dose Factors, Ri - Teen, Inhalation 146 Table 5.2.4 Pathway Dose Factors, Ri- Adult, Inhalation 147 Table 5.3.1 Pathway Dose Factors, Ri - All Age Groups, Ground Plane 148 Table 5.4.1 Pathway Dose Factors, Ri - Infant, Grass-Cow-Milk 149 Table 5.4.2 Pathway Dose Factors, Ri - Child, Grass-Cow-Milk 150 Table 5.4.3 Pathway Dose Factors, Ri - Teen, Grass-Cow-Milk 151 Table 5.4.4 Pathway Dose Factors, Ri - Adult, Grass-Cow-Milk 152 Table 5.5.1 Pathway Dose Factors, Ri - Infant, Grass-Goat-Milk 153

CY-TM-1 70-300 Revision 3 Page 9 of 209 TABLE OF CONTENTS (Cont'd)

PART III EFFLUENT DATA AND CALCULATIONAL METHODOLOGIES Section Paqe TABLES Table 5.5.2 Pathway Dose Factors, R1 - Child, Grass-Goat-Milk 154 Table 5.5.3 Pathway Dose Factors, R1 - Teen, Grass-Goat-Milk 155 Table 5.5.4 Pathway Dose Factors, Ri - Adult, Grass-Goat-Milk 156 Table 5.6.1 Pathway Dose Factors, Ri - Infant, Grass-Cow-Meat 157 Table 5.6.2 Pathway Dose Factors, R1 - Child, Grass-Cow-Meat 158 Table 5.6.3 Pathway Dose Factors, Ri - Teen, Grass-Cow-Meat 159 Table 5.6.4 Pathway Dose Factors, R1 - Adult, Grass-Cow-Meat 160 Table 5.7.1 Pathway Dose Factors, Ri - Infant, Vegetation 161 Table 5.7.2 Pathway Dose Factors, R - Child, Vegetation 162 Table 5.7.3 Pathway Dose Factors, Ri - Teen, Vegetation 163 Table 5.7.4 Pathway Dose Factors, Ri - Adult, Vegetation 164 Table 8.1 Sample Collection and Analysis Requirements 174 Table 8.2 Reporting Levels for Radioactivity Concentrations in Environmental Samples 180 Table 8.3 Detection Capabilities for Environmental Sample Analysis 181 Table 8.4 TMINS REMP Station Locations - Air Particulate and Air Iodine 184 Table 8.5 TMINS REMP Station Locations - Direct Radiation 184 Table 8.6 TMINS REMP Station Locations - Surface Water 186 Table 8.7 TMINS REMP Station Locations - Aquatic Sediment 186 Table 8.8 TMINS REMP Station Locations - Milk 187 Table 8.9 TMINS REMP Station Locations - Fish 187 Table 8.10 TMINS REMP Station Locations - Food Products 187

CY-TM-1 70-300 Revision 3 Page 10 of 209 TABLE OF CONTENTS (Cont'd)

PART III EFFLUENT DATA AND CALCULATIONAL METHODOLOGIES Section Paqe MAPS MAP 8.1 Three Mile Island Nuclear Station Locations of Radiological Environmental Monitoring Program Stations within 1 Mile of the Site 188 MAP 8.2 Three Mile Island Nuclear Station Locations of Radiological Environmental Monitoring Program Stations within 5 miles of the Site 189 MAP 8.3 Three Mile Island Nuclear Station Locations of Radiological Environmental Monitoring Program Stations Greater than 5 miles from the Site 190 FIGURES Figure 1.1 TMI-1 Liquid Effluent Pathways 104 Figure 1.2 TMI-2 Liquid Effluent Pathways 105 Figure 3.1 TMI-1 Liquid Radwaste 115 Figure 3.2 TMI-1 Liquid Waste Evaporators 116 Figure 4.1 TMI-1 Gaseous Effluent Pathways 131 Figure 4.2 TMI-1 Auxiliary and Fuel Handling Buildings Effluent Pathways 132 Figure 4.3 TMI-1 Reactor Building Effluent Pathway 133 Figure 4.4 TMI-1 Condenser Offgas Effluent Pathway 134 Figure 4.5 TMI-2 Gaseous Effluent Filtration System/Pathways 135 Figure 6.1 Waste Gas System 166

CY-TM-1 70-300 Revision 3 Page 11 of 209 TABLE OF CONTENTS (Cont'd)

PART IV REPORTING REQUIREMENTS Section Paqe 1.0 TMI ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 194 2.0 TMI ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 195 3.0 PART IV REFERENCES 197 APPENDICES A. Pathway Dose Rate Parameter (Pi) 198 B. Inhalation Pathway Dose Factor (Ri) 199 C. Ground Plane Pathway Dose Factor (Ri) 200 D. Grass-Cow-Milk Pathway Dose Factor (R1) 201 E. Cow-Meat Pathway Dose Factor (Ri) 203 F. Vegetation Pathway Dose Factor (R) 205 APPENDIX A - F REFERENCES 206

CY-TM-1 70-300 Revision 3 Page 12 of 209 PART I TMI-1 RADIOLOGICAL EFFLUENT CONTROLS

CY-TM-1 70-300 Revision 3 Page 13 of 209 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 2000 F. 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 5250 F.

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 525 0 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.

CY-TM-1 70-300 Revision 3 Page 14 of 209 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 0 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.

1.1.8 Refueling Interval The 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 5250 F.

1.2 Operable A system, subsystem, train, component or device, shall be OPERABLE or have OPERABILITY when it is capable of performing it's 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

CY-TM-1 70-300 Revision 3 Page 15 of 209 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.

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 III 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.]

CY-TM-1 70-300 Revision 3 Page 16 of 209 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.

1t8 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.

1t9 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.

1.10 Venting VENTING 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.

CY-TM-1 70-300 Revision 3 Page 17 of 209 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 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.

1.13 Frequency 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 of "F." No extension is allowed for intervals designated "F."

1.14 Occupational Dose OCCUPATIONAL 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.

CY-TM-1 70-300 Revision 3 Page 18 of 209 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 judgment 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.

CY-TM-1 70-300 Revision 3 Page 19 of 209 Map 1.1 Gaseous Effluent Release Points and Liquid Effluent Outfall Locations

CY-TM-170-300 Revision 3 Page 20 of 209 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 alarm/trip 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 WDL-FT-84, and RM-L-6, operability is not required when discharges are positively controlled through the closure of WDL-V-257.

For RM-L-12 and associated IWTS/IWFS flow interlocks, operability is not required when discharges are positively controlled through the closure of IW-V-72, 75 and IW-V-280, 281.

For SR-FT-146, operability is not required when discharges are positively controlled through the closure of WDL-V-257, IW-V-72, 75 and IW-V-280, 281.

CY-TM-1 70-300 Revision 3 Page 21 of 209 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.

CY-TM-1 70-300 Revision 3 Page 22 of 209 Table 2.1-1 Radioactive Liquid Effluent Instrumentation Minimum Channels Instrument Operable ACTION

1. Gross Radioactivity Monitors Providing Automatic Termination of Release

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

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

2. Flow Rate Measurement Devices

a. Unit 1 Liquid Radwaste Effluent Line (WDL-FT-84) 1 21

b. Station Effluent Discharge (SR-FT-146) 1 21 Table Notation ACTION 18 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, 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.

3. 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 OPERABLE 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 lx107 microcuries/mI, 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 With 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 flow.

CY-TM-1 70-300 Revision 3 Page 23 of 209 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 AmerGen letter

5928-06-20449, "Request to Revise Condenser Vent System Low Range Noble Gas Monitor Operability Requirements", Pamela B. Cowan to U.S.N.R.C., May 25, 2006.

CY-TM-1 70-300 Revision 3 Page 24 of 209 Table 2.1-2 Radioactive Gaseous Process and Effluent Monitoring Instrumentation MINIMUM CHANNEL INSTRUMENT OPERABLE APPLICABILITY ACTION

1. Waste Gas Holdup System

a. Noble Gas Activity Monitor (RM-A-7) 1 25 B. Effluent System Flow Rate Measuring Device (WDG-FT-123) 1 261

2. Waste Gas Holdup System Explosive Gas Monitoring System

a. Hydrogen Monitor (CA-G-1A/B) 2 ** 30

b. Oxygen Monitor (CA-G-1AIB) 2 ** 30

3. Containment Purge Monitoring System

a. Noble Gas Activity Monitor (RM-A-9) 1 # 27

b. Iodine Sampler (RM-A-9) 1 # 31

c. Particulate Sampler (RM-A-9) 1 # 31

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

e. Sampler Flow Rate Monitor (RM-FI-1231) 1 # 26

4. Condenser Vent System

a. Low Range Noble Gas Activity Monitor (RM-A-5Lo or RM-A-15) 1 # 32

CY-TM-1 70-300 Revision 3 Page 25 of 209 Table 2.1-2 (Cont'd)

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

5. Auxiliary and Fuel Handling Building Ventilation System

a. Noble Gas Activity Monitor (RM-A-8) or (RM-A-4 and RM-A-6) 1

27

b. Iodine Sampler (RM-A-8 or (RM-A-4 and RM-A-6) 1

31

c. Particulate Sampler (RM-A-8 or (RM-A-4 and RM-A-6) 1

31

d. Effluent System Flow Rate Measuring Devices (AH-FR-149 and 1

26 AH-FR-150)

e. Sampler Flow Rate Monitor (RM-FI-1230 or RM-A-4\FI and RM-A-6\FI) 1 26

6. Fuel Handling Building ESF Air Treatment System

a. Noble Gas Activity Monitor (RM-A-14 or suitable equivalent) 1 .... 27,33

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

c. Particulate Filter N/A(2) .... 31,33

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

e. Sampler Flow Rate Monitor (RM-A-14FI14) 1 .... 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.

CY-TM-1 70-300 Revision 3 Page 26 of 209 Table 2.1-2 (Cont'd)

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

7. Chemical Cleaning Building Ventilation System

a. Noble Gas Activity Monitor (ALC RM-1-18) 1(3) 27

b. Iodine Sampler (ALC RM-1-18) 1(3) 31

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

CY-TM-1 70-300 Revision 3 Page 27 of 209 Table 2.1-2 (Cont'd)

Table Notation At all times

- ** During waste gas holdup system operation

- *** Operability is not required when discharges are positively controlled through the closure of WDG-V-47 or where RM-A-8, AH-FT-149 and AH-FT-150 are operable and RM-A-8 is capable of automatic closure of WDG-V-47 S**** 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-A-9 is declared inoperable, see also Technical Specification 3.5.1, Table 3-5.1, Item C.3.f.

CY-TM-1 70-300 Revision 3 Page 28 of 209 Table 2.1-2 Notations (Cont'd)

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).

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 14 days, provided that grab samples are taken and analyzed.

If the primary-to-secondary leak rate was unstable*, or was indicating an increasing trend at the initial time when there was no operable channel of the Condenser Vent System Low Range Noble Gas Activity Monitor, analyze grab samples of the reactor coolant system and Condenser OffGas once every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months to provide an indication of primary-to-secondary leakage. Subsequent sample frequency shall be in accordance with Table 1 based on the last sample result. Otherwise, analyze grab samples of the reactor coolant system and Condenser OffGas to provide an indication of primary-to-secondary leakage at the minimum frequency indicated in Table 1, below:

CY-TM-1 70-300 Revision 3 Page 29 of 209 Table 2.1-2 Notations (Cont'd)

Table I Minimum Frequency of Grab Samples When No Condenser Vent System Low Range Noble Gas Activity Monitor is Operable Existing Total Primary-to-Secondary Leak Rate Frequency of Grab Samples (based on last monitor reading or sample result) 0 to < 5 GPD Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 5 to < 30 GPD Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 30 to < 75 GPD Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 75 GPD or greater Place the unit in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and at least COLD SHUTDOWN within the subsequent 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Unstable is defined as > 10% increase during a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period, as stated in the EPRI Guidelines.

Condenser Vent System Low Range Noble Gas Activity Monitor inoperable channels should be restored to operability as rapidly as practical.

After 14 days, if one OPERABLE channel is not returned to service, within I hour, 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.

CY-TM-170-300 Revision 3 Page 30 of 209 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 3E-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.

CY-TM-1 70-300 Revision 3 Page 31 of 209 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 organ.

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 radio!ogical impact on finished drinking water supplies with regard to the requirements of 40 CFR 141, Safe Drinking Water Act.

CY-TM-170-300 Revision 3 Page 32 of 209 BASES This control and associated action is provided to implement the requirements of Sections II.A, IIl.A, and IV.A of Appendix I, 10 CFR Part 50. The Control implements the guides set forth in Section II.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 .,"

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.

CY-TM-1 70-300 Revision 3 Page 33 of 209 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 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 II.D of Appendix I to 10 CFR Part 50. The intent of Section ll.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 1,10 CFR Part 50 dose requirements. This margin, a factor of 4, constitutes a reasonable reduction.

CY-TM-1 70-300 Revision 3 Page 34 of 209 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

CY-TM-1 70-300 Revision 3 Page 35 of 209 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 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 in 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,

CY-TM-1 70-300 Revision 3 Page 36 of 209

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.

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

This control and associated action is provided to implement the requirements of Section 1I.B, III.A and IV.A of Appendix I, 10 CFR Part 50. The Control implements the guides set forth in Section II.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 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 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 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in

CY-TM-1 70-300 Revision 3 Page 37 of 209 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 - Iodine-1 31, Iodine-1 33, Tritium, and Radionuclides in Particulate Form CONTROL:

The dose to a MEMBER OF THE PUBLIC from Iodine-131, Iodine-133, Tritium, and all radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents 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 Iodine-131, Iodine-1 33, 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-I.

This control and associated action is provided to implement the requirements of Section II.C, III.A and IV.A of Appendix I, 10 CFR Part 50. The Controls are the guides set forth in

CY-TM-170-300 Revision 3 Page 38 of 209 Section II.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 Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October, 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors" Revision 1, July, 1977. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate controls for iodine-1 31, iodine-1 33, tritium and radionuclides in particulate form with half lives greater than 8 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.

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

CY-TM-170-300 Revision 3 Page 39 of 209 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 II.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the guide set forth in Sections II.B and II.C of Appendix 1,10 CFR Part 50, for gaseous effluents.

CY-TM-1 70-300 Revision 3 Page 40 of 209 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 System 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 System 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

CY-TM-1 70-300 Revision 3 Page 41 of 209 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-1 33).

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

CY-TM-1 70-300 Revision 3 Page 42 of 209 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 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 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

CY-TM-170-300 Revision 3 Page 43 of 209 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.

CY-TM-1 70-300 Revision 3 Page 44 of 209 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.

CY-TM-1 70-300 Revision 3 Page 45 of 209 Table 3.1-1 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements CHANNEL SOURCE CHANNEL CHANNEL INSTRUMENT CHECK CHECK CALIBRATION TEST

1. Radioactivity Monitors Providing Alarm and Automatic Isolation

a. Unit 1 Liquid Radwaste Effluents Line (RM-L-6) D P R(2) Q(1)

b. IWTS/IWFS Discharge Line (RM-L-12) D P R(2) Q(1)

2. Flow Rate Monitors

a. Unit 1 Liquid Radwaste Effluent Line (WDL-FT-84) D(3) N/A R Q

b. Station Effluent Discharge (SR-FT-146) D(3) N/A R Q

CY-TM-170-300 Revision 3 Page 46 of 209 Table 3.1-1 (Cont'd)

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.

CY-TM-170-300 Revision 3 Page 47 of 209 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.

CY-TM-170-300 Revision 3 Page 48 of 209 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 (WDG-FT-123) P N/A E Q

2. Waste Gas Holdup System Explosive Gas Monitoring System

a. Hydrogen Monitor (CA-G-1A/B) D N/A Q(4) M **

b. Oxygen Monitor (CA-G-1A/B) 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 #

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

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

e. Sampler Flow Rate Monitor (RM-FI-1231) D N/A E N/A #

4. Condenser Vent System

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

See Table 2.1-2, Item 4.a)

CY-TM-170-300 Revision 3 Page 49 of 209 Table 3.1-2 (Cont'd)

Radioactive Gaseous Process and Effluent Monitoring Instrumentation Surveillance Requirements CHANNEL SOURCE CHANNEL CHANNEL INSTRUMENT CHECK CHECK CALIBRATION TEST APPLICABILITY

5. Auxiliary and Fuel Handling Building Ventilation System

a. Noble Gas Activity Monitor (RM-A8) or (RM-A4 and RM-A6) D M E(3) Q0(1)

k

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 (AH-FR-149 and D N/A E Q AH-FR-150)

D N/A E N/A

e. Sampler Flow Rate Monitor (RM-FI-1230 or RM-A-4\FI and RM-A-6\FI)

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 (AH-UR-1104 A/B) D N/A R Q

c. Sampler Flow Rate Measurement Device (RM-A-14FI14) D N/A R Q

CY-TM-1 70-300 Revision 3 Page 50 of 209 Table 3.1-2 (Cont'd)

Radioactive Gaseous Process and Effluent Monitoring Instrumentation Surveillance Requirements CHANNEL SOURCE CHANNEL CHANNEL INSTRUMENT CHECK CHECK CALIBRATION TEST AlPPLICABILITY

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

c. Particulate Sampler (ALC RM-1-18) W N/A N/A N/A

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

CY-TM-1 70-300 Revision 3 Page 51 of 209 Table 3.1-2 (Cont'd)

Table Notation

At all times

- During waste gas holdup system operation Operability is not required when discharges are positively controlled through the closure of WDG-V-47, or where RM-A-8, AH-FT-149, and AH-FT-150 are operable and RM-A-8 is capable of automatic closure of WDG-V-47 During Fuel Handling Building ESF Air Treatment System Operation

At all times during containment purging

1. At all times when condenser vacuum is established

1. 1. During 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.

CY-TM-170-300 Revision 3 Page 52 of 209 Table 3.1-2 NOTATIONS (Cont'd)

(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 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.)

(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

CY-TM-1 70-300 Revision 3 Page 53 of 209 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.

CY-TM-1 70-300 Revision 3 Page 54 of 209 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.

CY-TM-1 70-300 Revision 3 Page 55 of 209 Table 3.2-1 Radioactive Liquid Waste Sampling and Analysis Program Lower Limit of Sampling Minimum Analysis Detection (LLD)

Liquid Release Type Frequency Frequency Type of Act ivity Analysis (gCi/ml) (Note a)

A.1 Batch Waste Release Tanks (Note d) P P H---3 1 x 10-5 7

Each Batch Each Batch Principal Gammaa Emitters (Note f) 5 x 10-I-"131 1 x 106 Dissolved and Entrained Gases 1 x 0-5 (Gamma Em itters) (Note g)

P M Gross alpha 1 x 10-Each Batch Composite (Note b)

P , Q Sr-89 ,Sr-90 5 x 10.8 Each Batch Composite (Note b) Fe ~-55 1 x 10-A.2 Continuous Releases (Note e) Continuous W Principal Gamma Emitters (Note f) 5 x 10.7 (Note c) Composite (Note c) Ill1 I ý1 flI-6 I- I4,I I I A il.

Grab Sample M Dissolved and Entrained Gases 1 x 105 M (Gamma Emitters) (Note g)

Continuous M H-3 i x 10.5 (Note c) Composite (Note c) Gross alpha 1x 10-7 Continuous Q Sr-89, Sr-90 5 x 10-8 (Note c) Composite (Note c) Fe-55 1 x 106

CY-TM-1 70-300 Revision 3 Page 56 of 209 Table 3.2-1 (Cont'd)

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 =

E x V x 2.22 x 106 x Y x exp (-A At)

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 E6 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

CY-TM-1 70-300 Revision 3 Page 57 of 209 Table 3.2-1 Notations (Cont'd)

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

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 or 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.

g. 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 of the above nuclides, shall also be analyzed and reported in the Annual Effluent Release Report pursuant to T.S.

6.9.4.

CY-TM-170-300 Revision 3 Page 58 of 209 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, Iodine-131, Iodine-133, Tritium, and Radionuclides in Particulate Form 3.2.2.3.1 Cumulative dose contributions from lodine-131, Iodine-133, 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.

CY-TM-1 70-300 Revision 3 Page 59 of 209 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.

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 jiCi/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.

CY-TM-1 70-300 Revision 3 Page 60 of 209 Table 3.2-2 Radioactive Gaseous Waste Sampling and Analysis Program Minimum Lower Limit of Sampling Analysis Type of Activity Detection (LLD)

Gaseous Release Type Frequency Frequency Analysis , iCi/ml) (Note a)

Each TankP Principal Gamma 1x 10-4 A. Waste Gas Decay Tank Grab Sample Each Tank Emitters (Note g)

B. Containment Purge H-3 1x 10-6 P (Note b)Each P (Note b) Each Principal1Gamma Purge Grab Sample Purge Emitters (Note g)' 1 X 10-1 C. Auxiliary and Fuel Handling Building H-3 1 x 10-6 Air Treatment System M(Notes c, e) Grab Sample M Principal Gamma Emitters (Note g) 1 x 10 D. Fuel Handling Building ESF Air Treatment System M (during System M (during H-3 1 x 106 Operation) System Principal Gamma ',

Grab Sample Operation) Emitters (Note g) "x 10

H-3 1 x10.6 E. Condenser Vacuum Pumps Exhaust (Note h) M(Note h) M Principal Gamma Grab Sample (Note h) Emitters (Note g) 1x F. Chemical Cleaning Building Air Treatment System M(Note I) M Pr Hi3GX10a Grab Sample MPrincipal (Note Gamma 1X1-Grab___ ___Sample____

_Emitters g) 1x 1 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 of this table of this table H. Respirator and Laundry Maintenance Facility See Section I See Section I See Section I See Section I Air Treatment System of this table of this table of this table of this table

CY-TM-1 70-300 Revision 3 Page 61 of 209 Table 3.2-2 (Cont'd)

Radioactive Gaseous Waste Sampling and Analysis Program Lower Limit of Sampling Minimum Analysis Type of Activity Detection (LLD)

Gaseous Release Type Frequency Frequency Analysis (gCi/ml) (Note a)

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

(Note f) Charcoal Sample 1-131" 1 X 1012 (Note i) (Note iPrincipal Gamma

, Continuous W (Note d) Emitters (Note g) lx101" (Note f) Particulate (1-131, Others)

Q Continuous Composite Gross Alpha 1 x 1011 (Note f) Particulate Sample Q

Continuous Composite Sr-89, Sr-90 1 x 1011 (Note f) Particulate Sample Continuous Noble Gas ',

(Note f Beta or Gamma Noble Gases , 1 x 106 J. Condenser Vent Stack Continuous Iodine Continuous W (Note d) 1-131 1 X10-12 Sampler (Note j) (Note k) Charcoal Sample

CY-TM-1 70-300 Revision 3 Page 62 of 209 Table 3.2-2 (Cont'd)

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 =

E xV x2.22x106 xY xexp(-?At)

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 E6 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 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.

CY-TM-1 70-300 Revision 3 Page 63 of 209 Table 3.2-2 Notations (Cont'd)

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.

g. 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-1 38 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-137, 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 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.

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 than a factor of 3.

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 of the inoperability, (b) the action taken to restore representative sampling capability, (c) the action taken to 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.

1. 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 is stored or processed in the facility.

CY-TM-170-300 Revision 3 Page 64 of 209 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.

CY-TM-1 70-300 Revision 3 Page 65 of 209 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

CY-TM-1 70-300 Revision 3 Page 66 of 209 PART II TMI-2 RADIOLOGICAL EFFLUENT CONTROLS

CY-TM-1 70-300 Revision 3 Page 67 of 209 PART II Definitions 1.0 DEFINITIONS DEFINED TERMS 1.1 The DEFINED TERMS of this section appear in capitalized type and are applicable throughout Part II of 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 CALIBRATION 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.

CY-TM-1 70-300 Revision 3 Page 68 of 209 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.

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.

CY-TM-1 70-300 Revision 3 Page 69 of 209 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.

CY-TM-1 70-300 Revision 3 Page 70 of 209 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

CY-TM-170-300 Revision 3 Page 71 of 209 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.

CY-TM-1 70-300 Revision 3 Page 72 of 209

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.

CY-TM-1 70-300 Revision 3 Page 73 of 209 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) 1 NOTE 1 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.

CY-TM-1 70-300 Revision 3 Page 74 of 209 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.

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 of the annual average concentrations specified in 10 CFR 20. As a result, this Control provides reasonable assurance that the resulting annual exposure to an individual in off-site areas will not exceed the design objectives of Section II.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.

CY-TM-1 70-300 Revision 3 Page 75 of 209 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 organ.

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.

CY-TM-1 70-300 Revision 3 Page 76 of 209 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.

CY-TM-1 70-300 Revision 3 Page 77 of 209 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 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 II.D of Appendix I to 10 CFR Part 50. The intent of Section ll.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 1,10 CFR Part 50 dose requirements.

This margin, a factor of 4, constitutes a reasonable reduction.

CY-TM-170-300 Revision 3 Page 78 of 209 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).

CY-TM-1 70-300 Revision 3 Page 79 of 209 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. 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.

CY-TM-1 70-300 Revision 3 Page 80 of 209 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.

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

CY-TM-1 70-300 Revision 3 Page 81 of 209 This control and associated action is provided to implement the requirements of Section II.B, III.A and IV.A of Appendix I, 10 CFR Part 50. The Control implements the guides set forth in Section II.B of Appendix I. 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 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 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 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors,"

Revision 1, July 1977. The ODCM equations provided for determining the air doses at and beyond the SITE BOUNDARY are based upon 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 - Iodine-131, Iodine-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.

CY-TM-1 70-300 Revision 3 Page 82 of 209 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.

CY-TM-1 70-300 Revision 3 Page 83 of 209 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 II.C, III.A and IV.A of Appendix I, 10 CFR Part 50. The Controls are the guides set forth in Section II.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 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 Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October, 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July, 1977. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate controls for iodine-1 31, iodine-1 33, tritium and radionuclides in particulate form with half lives greater than 8 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. The absence of iodines at the site eliminates the need to specify dose limits for these nuclides.

CY-TM-1 70-300 Revision 3 Page 84 of 209 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 II.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the systems were

CY-TM-170-300 Revision 3 Page 85 of 209 specified as a suitable fraction of the guide set forth in Sections 1I.B and 11.0 of Appendix 1,10 CFR Part 50, for gaseous effluents.

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 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.

CY-TM-170-300 Revision 3 Page 86 of 209 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.

CY-TM-1 70-300 Revision 3 Page 87 of 209 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 allowable 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 3.1.1.1 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.

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.

CY-TM-1 70-300 Revision 3 Page 88 of 209 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 (2HP-R-219A) D E M NOTE 1

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

1. During operation of the monitored system.

CY-TM-1 70-300 Revision 3 Page 89 of 209 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.

CY-TM-170-300 Revision 3 Page 90 of 209 TABLE 3.2-1 Radioactive Liquid Waste Sampling and Analysis Program (4, 5)

A. Liquid Releases Sampling Frequency Type of Detectable Activity Analysis Concentration (3)

P Individual Gamma 5E-7 pjCi/ml (2)

Each Batch H-3 1E-5 lCi/ml Q Gross Alpha 1E-7 jiCi/ml Quarterly Composite (1) Sr-90 5E-8 }ICi/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.

CY-TM-1 70-300 Revision 3 Page 91 of 209 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.

CY-TM-1 70-300 Revision 3 Page 92 of 209 TABLE 3.2-2 Radioactive Gaseous Waste Sampling and Analysis Program (3)

SAMPLING TYPE OF DETECTABLE SAMPLE FREQUENC ACTIVITY CONCENTRATION SAMPLE POINT TYPE Y ANALYSIS (1)(a)

P H-3 1E-6 itCi/cc Reactor Building Purge Gas Individual 1E-4 tCi/cc (2)

Releases Each Purge Gamma Emitters M H-3 1E-6 iCi/cc Unit Exhaust Vent Release Gas Individual Points Monthly Gamma Emitters 1E-4 ptCi/cc (2)

W Individual (b) 1E-10 gCi/cc (2)

Weekly Gamma Emitters M

Particulate Monthly Sr-90 1 E-1 1 pCi/cc s Composite M Gross Alpha 1E-1 I.Ci/cc Monthly Emitters Composite Reactor Building Breather SA Indv.Gamma Emittersm b) 1E-1 0 p.Ci/cc (2)

P Semi-Annual Sr-90 1E-11 giCi/cc ly Gross Alpha 1E-1 1 gCi/cc Emitters 1_E-11___i/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.

CY-TM-170-300 Revision 3 Page 93 of 209 TABLE 3.2-2 (Cont'd)

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):

LLD = 4.66 sp E xV x 2.22 x 106 x Y xexp(-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),

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 (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.

CY-TM-1 70-300 Revision 3 Page 94 of 209 TABLE 3.2-2 Notation (Cont'd)

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-1 34, Cs-1 37, 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.

CY-TM-1 70-300 Revision 3 Page 95 of 209 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.

CY-TM-1 70-300 Revision 3 Page 96 of 209 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 DOE/TIC-27601, Atmospheric Science and Power Reduction 4.7 TMI-1 Technical Specifications, attached to Facility Operating License No.

DPR-50 4.8 PDMS-SAR

CY-TM-1 70-300 Revision 3 Page 97 of 209 PART III EFFLUENT DATA AND CALCULATIONAL METHODOLOGIES

CY-TM-170-300 Revision 3 Page 98 of 209 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:

f CC (eq 1.1)

F+f -

Where:

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

c = the set point, in jtCi/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.

CY-TM-1 70-300 Revision 3 Page 99 of 209 1.2 TMI Liquid Effluent Release Points and Liquid Radiation Monitor Data TMI-1 has two required liquid radiation monitors. These are RM-L6 and RM-L12.

These liquid release point radiation monitors and sample points are shown in Table 1.1. (The TMI outfall radiation monitor, RM-L7, is also listed for information only.)

TMI-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 10CFR20 concentration DF:

DF1 = El (SA1 ) + (10% [20% for H-3] of ten times the 10CFR20 concentration)

SA = Specific Activity of each identified radionuclide Calculation of Boron DF:

DF2 = Actual Tank Boron Concentration - 0.7.

CY-TM-1 70-300 Revision 3 Page 100 of 209

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.

Y.(C 1 /Xi) + (CH-3/2XH-3) <0.1, (eq 1.2)

Where: Ci = diluted concentration of the ith radionuclide, other than H-3 Xi= 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 p[Ci/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-1 37, which is the most limiting radionuclide at a concentration of 1.0E-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/Industrial Waste Filtration System (IWTS/IWFS). The input to IWTS/IWFS originates in TMI-2 sumps, (see Figures 1.1 and 1.2) and the TM I-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 jiCi/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.

CY-TM-1 70-300 Revision 3 Page 101 of 209 1.2.3 RM-L10 RM-L1 0 was a Nal detector submerged in the TMI-1 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 10CFR20 concentrations to the environment.

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 Part II Control 2.2.1.1.

The 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.

CY-TM-1 70-300 Revision 3 Page 102 of 209 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.) WDL-V257 RM-L7 South end of TMI-1 Station Discharge YES (Nal) MDCT TMI-1 and SR-FT-146 WDL-V257

- TMI-2, *WDL-R-1 311 YES IWTS/IWFS IW-V73, RM-L12 (Nal)

IWFS Building NW Continuous Releases Corner (300,000/

80,000 gal.)

IW-FT-342/

IW-FT-373 IW-P16,17,18 IW-V279, I

I_ I_ I I IW-P29,30

WDL-R-1 311 has been flanged off as a TMI-2 liquid outfall.

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

CY-TM-1 70-300 Revision 3 Page 103 of 209 TABLE 1.2 TMI-2 Sump Capacities Total Capacity Gallons Sump Gallons per Inch Turbine Building Sump 1346 22.43 Circulating Water Pump House Sump 572 10.59 Control Building Area Sump 718 9.96 Tendon Access Galley Sump 538 9.96 Control to Service Building Sump 1346 22.43 Contaminated Drain Tank Room Sump 135 3.80 Chlorinator House Sump ----.....

Water Treatment Sump** 1615 22.43 Air Intake Tunnel Normal Sump 700 ----

Air Intake Tunnel Emergency Sump 100000 766.00 Condensate Polisher Sump* 2617 62.31 Sludge Collection Sump** 1106 26.33 Heater Drain Sump ----.....

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

Condensate Polisher Sump is deactivated and in PDMS condition.

- The Water Treatment and Sludge Collection Sumps will be deactivated for PDMS.

CY-TM-170-300 Revision 3 Page 104 of 209 FIGURE 1-1 TMI-1 Liquid Effluent Pathways Page 1 of 1 Component Cooling Mechanical Draft Cooling Tower Basin Water 'M 1' TMI-1

CY-TM-1 70-300 Revision 3 Page 105 of 209 FIGURE 1.2 TMI-2 Liquid Effluent Pathways CONTROL CONTROL &

BUILDING SERVICE SUMP AREA SUMP INDUSTRIAL WASTE TREATMENT SYSTEM C -- COMPOSITE SAMPLER

CY-TM-1 70-300 Revision 3 Page 106 of 209 2.0 LIQUID EFFLUENT DOSE ASSESSMENT 2.1 Liquid Effluents - 10 CFR 50 Appendix I The dose from liquid effluents results from the consumption of fish and drinking water. The location of the nearest potable water intake is PP&L Brunner Island Steam Electric Station located downstream of 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:

Dose j= i (At) X (Ci) X AWij X FRFD + ( AFij ED X DF (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 Ci and f are averaged for all liquid releases, in hours.

Ci = the average concentration of radionuclide, i, in undiluted liquid effluent during time period At from any liquid release, in 0Ci/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 lowrate 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 piCi/ml. AW is the factor for the water pathway and AF is the factor for the fish pathway.

CY-TM-170-300 Revision 3 Page 107 of 209 Values for AWij are determined by the following equation:

AWj = (1.14E5) x (U,) x (DFy) (eq 2.2)

Where:

1.14E5 = (1.0E6 pCil/Ci) x (1.0E3 mllkg) + (8760 hr/yr)

Uw = Water consumption rate for adult is 730 kg/yr (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 AFij 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 pCi/L from Table 2.2 (Reg. Guide 1.109, Rev. 1).

2.2 TMI Liquid Radwaste System Dose Calcs Once Per 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. Ifthis projected dose exceeds 0.06 mrem total body or 0.2 mrem any organ, appropriate portions of the Liquid Radwaste Treatment System, as

CY-TM-1 70-300 Revision 3 Page 108 of 209 defined in Section 3.1, shall be used to reduce radioactivity levels prior to release.

At the discretion of the ODCM Specialist, 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.

2.3 Alternative Liquid Dose Calculational Methodology As an alternative, models in, or based upon, those presented in Regulatory Guide 1.109 (Rev. 1) may be used to make a comprehensive dose assessment.

Default parameter values from Reg. Guide 1.109 (Rev. 1) and/or actual site specific data are used where applicable.

As an alternative dose calculational methodology 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.

CY-TM-1 70-300 Revision 3 Page 109 of 209 TABLE 2.1 Liquid Dose Conversion Factors (DCF): DF1 I Page 1 of 3 Ingestion Dose Factors for Adults*

(MREM 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 3.91E-06 NO DATA NO DATA 2.85E-06 3.40E-05 CO 58 NO DATA 7.45E-07 1.67E-06 NO DATA NO DATA NO DATA 1.51 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 9.01E-06 4.36E-06 NO DATA NO DATA NO DATA 1.88E-06 NI 65 5.28E-07 6.86E-08 3.13E-08 NO DATA NO DATA NO DATA 1.74E-06 CU 64 NO DATA 8.33E-08 3.91 E-08 NO DATA 2.1OE-07 NO DATA 7.1OE-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 2.96E-09 BR 83 NO DATA NO DATA 4.02E-08 NO DATA NO DATA NO DATA 5.79E-08 BR 84 NO DATA NO DATA 5.21E-08 NO DATA NO DATA NO DATA 4.09E-13

....85 ....... N D - -N . ....... N D N . .DATA A' ..... LT . E-24 RB 86 NO DATA 2.11E-05 9.83E-06 NO DATA NO DATA NO DATA 4.16E-06 RB 88 NO DATA 6.05E-08 3.21 E-08 NO DATA NO DATA NO DATA 8.36E-19 RB -9 NO DATA 4.01 E-08 2.82E-08 NO DATA NO DATA NO DATA 2.33E-21 SR 89 3.08E-04 NO DATA 8.84E-06 NO DATA NO DATA NO DATA 4.94E-05 SR 90 7.58E-03 NO DATA 1.86E-03 NO DATA NO DATA NO DATA 2.19E-04

.........-9 -.1. 5-.... .67E- 6 ... N0...... .......

.......... 2."2-9.. E"-.0.7- N D....

... ........... .....O... ........A .............. D...A

............. 720........

E"-.0"5".

SR 92 2.15E-06 NO DATA 9.30E-08 NO DATA NO DATA NO DATA 4.26E-05 Y 90 9.62E-09 NO DATA 2.58E-10 NO DATA NO DATA NO DATA 1.02E-04

CY-TM-1 70-300 Revision 3 Page 110 of 209 TABLE 2.1 Liquid Dose Conversion Factors (DCF): DFij 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-11 NO DATA 3.52E-12 NO DATA NO DATA NO DATA 2.67E-10 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--.------E, ........3 6"19 ........ 1 686E-09 -- N..... DXT:f T.A....... ...E:*"9 ...... O.34.2*N ATA ... - 2' 1 E-'5 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 TO 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 -06 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 1.1OE-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 7.71E-05 I 130 7.56E-07 2.23E-06 8.80E-07 1.89E-04 3.48E-06 NO DATA 1.92E-06 I 131 4.16E-06 5.95E-06 3.41E-06 1.95E-03 1.02E-05 NO DATA 1.57E-06 I 132 2.03E-07 5.43E-07 1.90E-07 1.90E-05 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

CY-TM-170-300 Revision 3 Page 111 of 209 TABLE 2.1 Liquid Dose Conversion Factors (DCF): DFij Page 3 of 3 Ingestion Dose Factors for Adults*

(MREM Per PCI Ingested)

NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLI I 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 2.11E-06 CS 138 5.52E-08 1.09E-07 5.40E-08 NO DATA 8.01E-08 7.91E-09 4.65E-13 BA 139 9.70E-08 6.91E-11 2.84E-09 NO DATA 6.46E-11 3.92E-11 1.72E-07

.. . . . .. .. . .. --. -.. --2.....3E

. .. . 0

. . 5- .. -. --- ............---

-2 5 5 E ...-08 - - - - -1....................................- "A'T-A"......... 8............ 0"9'......... 1.................. .... 4....................

BA 140 2.03E-05 2.55E-08 1.33E-06 NO DATA 8.67E-09 1.46E-08 4.18E-05 BA 141 4.71E-08 3.56E-11 1.59E-09 NO DATA 3.31E-11 2.02E-11 2.22E-17 BA 142 2.13E-08 2.19E-11 1.34E-09 NO DATA 1.85E-11 1.24E-11 3.OOE-26 LA 140 2.50E-09 1.26E-09 3.33E-10 NO DATA NO DATA NO DATA 9.25E-05 LA 142 1.28E-10 5.82E-11 1.45E-11 NO DATA NO DATA NO DATA 4.25E-07 CE 141 9.36E-09 6.33E-09 7.18E-10 NO DATA 2.94E-09 NO DATA 2.42E-05 CE 143 1.65E-09 1.22E-06 1.35E-10 NO DATA 5.37E-10 NO DATA 4.56E-05 CE 144 4.88E-07 2.04E-07 2.62E-08 NO DATA 1.21 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 3.01 E-11 1.25E-11 1.53E-12 NO DATA 7.05E-12 NO DATA 4.33E-18 ND 147 6.29E-09 7.27E-09 4.35E-10 NO DATA 4.25E-09 NO DATA 3.49E-05 W 187 1.03E-07 8.61E-08 3.01E-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 this table may be obtained from NUREG-0172.

CY-TM-170-300 Revision 3 Page 112 of 209 TABLE 2.2 Bioaccumulation Factors, BF, Bloaccumulation 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 9.1E+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+00 NB 3.OE+04 1.OE+02 MO 1.OE+01 1.OE+01 TC 1.5E+01 5.OE+00 RU 1.OE+01 3.OE+02 RH 1.OE+01 3.OE+02

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

- SB 1.OE+00 1.OE+00 TE 4.OE+02 6.1 E+03 I 1.5E+01 5.OE+00 CS 2.OE+03 1.OE+03 BA 4.OE+00 2.OE+02 LA 2.5E+01 1.OE+03 CE 1.OE+00 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-lj.

- 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.

CY-TM-1 70-300 Revision 3 Page 113 of 209 3.0 TMI LIQUID EFFLUENT WASTE TREATMENT SYSTEM 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

- Demineralizers prior to release (see Figure 3.2)

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

CY-TM-1 70-300 Revision 3 Page 114 of 209

b. Liquid Processing - Miscellaneous Waste Evaporator, MWE

- Demineralizers prior to release (see Figure 3.2)

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) 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-Z1 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.

CY-TM-170-300 Revision 3 Page 115 of 209 FIGURE 3.1 TMI-1 Liquid Radwaste RECLAIMED WATER SYSTEM

CY-TM-1 70-300 Revision 3 Page 116 of 209 FIGURE 3.2 TMI-1 Liquid Waste Evaporators

CY-TM-1 70-300 Revision 3 Page 117 of 209 4.0 GASEOUS EFFLUENT MONITORS 4.1 TMI-1 Noble Gas Monitor Set Points The gaseous effluent monitor set points are established for each gaseous effluent radiation monitor to assure concentrations of radionuclides in gaseous effluents do not exceed the limits set forth in 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 > i (c1)(F)(Ki)(Dv) (eq 4.1.1) and 3000 > (ci)(Li + 1.1 Mi)(Dv)(F) (eq 4.1.2)

Where: ci = set point concentration based on Xe-133 equivalent, in LCi/cc F =gaseous effluent flowrate at the monitor, in cc/sec Ki =total body dose factor, in mrem/yr per PtCi/m 3 from Table 4.3 Dv = highest sector annual average gaseous atmospheric dispersion factor (X/Q) at or beyond the unrestricted area boundary, in sec/m3 , 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 used are 1.27E-6 sec/m 3 at sector SE for station vent, and 1.40E-5 sec/m 3 at sector E for all other releases.

L= skin dose factor due to beta emissions from radionuclide i, in mrem/yr per ptCi/m 3 from Table 4.3.

Mi= air dose factor due to gamma emissions from radionuclide i, in mrad/yr per pCi/m 3 from Table 4.3.

1.1 = nrem 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 mrem/yr.

CY-TM-170-300 Revision 3 Page 118 of 209 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.

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

CY-TM-1 70-300 Revision 3 Page 119 of 209 4.2 TMI-1 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>* (ci)(F)(Pi)(Dv) (eq 4.2)

Where: ci = set point concentration based on 1-131 equivalent for radioiodine monitor and Sr-90 for particulate monitor, in LCi/cc F = gaseous effluent flow rate at the monitor, in cc/sec Pi = pathway dose parameter, in mrem/yr per jiCi/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 1.27E-6 sec/m3 for station vent, at sector SE, and 1.40E-5 sec/m3 for all other releases, at sector E.

The set point concentration is further reduced such that 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.

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

CY-TM-1 70-300 Revision 3 Page 120 of 209 4.3 TMI-2 Gaseous Radiation Monitor Set Points TMI-2 Gaseous Radiation Monitors have their set points described in TMI Plant Procedure 1101-2.1. 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.

CY-TM-1 70-300 Revision 3 Page 121 of 209 4.4 TMI-1 Gaseous Effluent Release Points and Gaseous Radiation Monitor Data TMI-1 has eleven (11) required effluent gaseous radiation monitors. These are RM-A4, RM-A5, RM-A15, RM-A6, RM-A7, RM-A8, 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 radiation monitor for the TMI-l Fuel Handling Building Ventilation (see Figures 4.1 and 4.2). RM-A6 is the 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 will 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-A15 is the back up gaseous radiation monitor for the TMI-1 Condenser Off Gas exhaust (see Figures 4.1 and 4.4). High alarms on RM-A5 low channel or RM-A15 noble gas channels will initiate the MAP-5 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 (see Figures 4.1 and 4.2). This in plant effluent radiation monitor also has an associated sampling panel. High alarm on RM-A7 noble gas channel 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.

CY-TM-1 70-300 Revision 3 Page 122 of 209 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.

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.

CY-TM-1 70-300 Revision 3 Page 123 of 209 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.

4.5.3 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.

CY-TM-170-300 Revision 3 Page 124 of 209 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 IIfor 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 IIfor 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.

CY-TM-1 70-300 Revision 3 Page 125 of 209 TABLE 4.1 TMI-1 Gaseous Release Point and Gaseous Radiation Monitor Data GASEOUS RELEASE RADIATION GASEOUS (F) TERMINATION MONITOR RELEASE FLOW INTERLOCK (YES/NO)

(DETECTOR) LOCATION POINT RECORDER VALVES YES 306' Elevation Fuel Hand. AH-E-10 RM-A4 Auxiliary Bldg Building AH-FR-149 AH-D-120 Exhaust AH-D-121 AH-D-1 22 306' Elevation Auxiliary YES RM-A6 Auxiliary Bldg. Building AH-FR-150 AH-E-11 Exhaust YES WDG-V47 RMA-8/9 Bldg. Station AH-FR-149 AH-E-10 RxNar Exhaust Vent & AH-FR-150 AH-E-1 1 Starts MAP-5 I Radioiodine Sampler 322' Elevation Condenser YES RM-A5 Second Floor Off Gas VA-FR-1 113 Starts MAP-5 Turbine Bldg. Exhaust Radioiodine Sampler 322' Elevation Condenser YES RM-A1 5 Second Floor Off Gas VA-FR-1 113 Starts MAP-5 Turbine Bldg. Exhaust Radioiodine Sampler Waste Gas RM-A7 306' Elevation Decay WDG-FR-1 23 YES Auxiliary Bldg. Tanks WDG-V47 (A, B,C)

Reactor YES ReactorAH-V-1AIB/C/D RM-A9 RMA-8/9 Bldg. Building AH-FT-909/ WDG-534/535 Near BWST Purge AH-FR-148 Exhaust Starts MAP-5 Exhaust_ Radioiodine Sampler 331' Elevation ESF Fuel NO RM-A14 ESF FHB Handling AH-UR-1 104A/B Manual Outside Chem. Building Actions Addition Bldg. Exhaust

CY-TM-1 70-300 Revision 3 Page 126 of 209 TABLE 4.1 (Cont'd)

TMI-1 Gaseous Release Point and Gaseous Radiation Monitor Data RELEASE GASEOUS TERMINATION RADIATION INTERLOCK MONITOR GASEOUS (YES/NO)

(DETECTOR) LOCATION RELEASE POINT VALVES Chemical CCB Exhaust SytmNE ALC-RMI-18 Cleaning Bldg. System NONE 304' Elevation (Typical flow rate is 10, 000 cfm)

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

TABLE 4.2 TMI-2 Gaseous Release Point and Gaseous Radiation Monitor Data RELEASE GASEOUS TERMINATION RADIATION GASEOUS INTERLOCK MONITOR RELEASE (YES/NO)

(DETECTOR) LOCATION POINT VALVES 328' Elevation Station HP-R-219 Auxiliary Vent NONE Building Exhaust 328' Elevation Station Vent HP-R-219A Auxiliary Exhaust NONE Building 328' Elevation Reactor Bldg HP-R-225 Auxiliary Building Purge Duct "A"Exhaust NONE

CY-TM-170-300 Revision 3 Page 127 of 209 TABLE 4.3 Dose Factors for Noble Gases and Daughters*

Gamma Beta Total Body Skin Dose Dose Factor(b) Gamma Air Beta Air Factor(a) Li Dose Factor Dose Factor Ki (mrem/yr Mi Ni (mrem/yr per per (mrad/yr per (mrad/yr per Radionuclide itCi/m 3 ) jiCi/m3) tci/m3) ptCi/n 3)

Kr-83m 7.56E-02** --- 1.93E+01 2.88E+02 Kr-85m 1.17E+03 1.46E+03 1.23E+03 1.97E+03 Kr-85 1.61 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-90 1.56E+04 7.29E+03 1.63E+04 7.83E+03 Xe-131m 9.15E+01 4.76E+02 1.56E+02 1.11E+03 Xe-1 33m 2.51 E+02 9.94E+02 3.27E+02 1.48E+03 Xe-1 33 2.94E+02 3.06E+02 3.53E+02 1.05E+03 Xe-135m 3.12E+03 7.11E+02 3.36E+03 7.39E+02 Xe-135 1.81 E+03 1.86E+03 1.92E+03 2.46E+03 Xe-137 1.42E+03 1.22E+04 1.51 E+03 1.27E+04 Xe-138 8.83E+03 4.13E+03 9.21 E+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-I.

- 7.56E-02 = 7.56 x 102.

(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 .

CY-TM-1 70-300 Revision 3 Page 128 of 209 TABLE 4.4 Atmospheric Dispersion Factors for Three Mile Island STATION VENT DISTANCE SFC.TO)R AVFRAGF X/Q (IN SEC/M3 (iN MF:TIFRR 5RFARON - ANNI JAL SECTOR 610 2413 4022 5631 7240 12067 24135 40225 56315 72405 N 1.63E-07 5.69E-07 3.62E-07 2.19E-07 1.63E-07 7.31E-08 2.99E-08 1.55E-08 1.00E-08 7.28E-09 NNE 4.06E-07 1.10E-06 5.84E-07 3.42E-07 2.17E-07 9.35E-08 3.58E-08 1.84E-08 1.20E-08 8.68E-09 NE 3.45E-07 3.48E-07 2.54E-07 3.86E-07 2.56E-07 1.14E-07 4.33E-08 2.22E-08 1.44E-08 1.05E-08 ENE 2.24E-07 4.54E-07 6.55E-07 3.61E-07 2.35E-07 1.20E-07 4.79E-08 2.45E-08 1.59E-08 1.15E-08 E 4.48E-07 3.99E-07 3.46E-07 4.25E-07 3.06E-07 1.31E-07 4.95E-08 2.52E-08 1.62E-08 1.17E-08 ESE 8.35E-07 5.29E-07 6.22E-07 4.00E-07 2.53E-07 1.08E-07 4.03E-08 2.03E-08 1.31E-08 9.41E-09 SE 1.27E-06 8.28E-07 5.96E-07 3.20E-07 2.05E-07 9.14E-08 3.90E-08 1.98E-08 1.28E-08 9.22E-09 SSE 7.20E-07 7.10E-07 4.94E-07 2.74E-07 1.83E-07 8.96E-08 3.36E-08 1.71E-08 1.10E-08 7.90E-09 S 1.58E-07 1.09E-07 3.71E-07 1.98E-07 1.27E-07 6.15E-08 2.29E-08 1.15E-08 7.39E-09 5.31E-09 SSW 4.16E-08 5.78E-08 2.69E-07 1.41E-07 8.94E-08 3.88E-08 1.53E-08 7.70E-09 4.93E-09 3.54E-09 SW 5.06E-08 1.75E-07 2.59E-07 1.43E-07 8.94E-08 3.82E-08 1.42E-08 7.12E-09 4.55E-09 3.27E-09 WSW 9.31E-08 4.71E-07 3.22E-07 1.73E-07 1.1OE-07 4.68E-08 1.76E-08 8.89E-09 5.71E-09 4.12E-09 W 1.41E-07 3.31E-07 3.69E-07 2.11E-07 1.47E-07 6.90E-08 2.58E-08 1.31E-08 8.38E-09 6.03E-09 WNW 1.96E-07 2.55E-07 3.94E-07 2.75E-07 1.72E-07 7.34E-08 2.77E-08 1.41E-08 9.09E-09 6.57E-09 NW 1.37E-07 5.23E-07 3.49E-07 1.92E-07 1.26E-07 6.31E-08 2.46E-08 1.33E-08 8.62E-09 6.25E-09 NNW 8.38E-08 5.25E-07 3.32E-07 1.87E-07 1.28E-07 6.44E-08 2.47E-08 1.26E-08 8.19E-09 5.94E-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 5.65E-09 1.02E-09 4.24E-10 3.24E-10 2.60E-10 9.41E-11 3.05E-11 1.27E-11 6.85E-12 4.26E-12 NNE 1.28E-08 2.15E-09 1.16E-09 5.85E-10 3.44E-10 1.21E-10 3.71E-11 1.51E-11 8.14E-12 5.06E-12 NE 1.04E-08 1.37E-09 4.64E-10 6.47E-10 3.87E-10 1.44E-10 4.41E-11 1.79E-11 9.65E-12 6.00E-12 ENE 6.91E-09 1.16E-09 8.68E-10 4.20E-10 2.59E-10 1.36E-10 4.46E-11 1.82E-11 9.78E-12 6.09E-12 E 1.45E-08 2.46E-09 8.77E-10 9.16E-10 5.97E-10 2.13E-10 6.55E-11 2.68E-11 1.45E-11 9.06E-12 ESE 2.76E-08 4.35E-09 2.30E-09 1.29E-09 7.48E-10 2.64E-10 8.11E-11 3.31E-11 1.79E-11 1.12E-11 SE 4.09E-08 5.28E-09 2.54E-09 1.19E-09 6.95E-10 2.65E-10 9.22E-11 3.75E-11 2.02E-11 1.26E-11 SSE 2.28E-08 2.80E-09 1.17E-09 6.39E-10 4.60E-10 2.09E-10 6.42E-11 2.66E-11 1.43E-11 8.91E-12 S 5.17E-09 7.98E-10 8.66E-10 4.10E-10 2.45E-10 1.16E-10 3.61E-11 1.48E-11 7.94E-12 4.93E-12 SSW 1.17E-09 2.90E-10 5.61E-10 2.61E-10 1.51E-10 5.53E-11 1.88E-11 7.64E-12 4.12E-12 2.56E-12 SW 1.78E-09 4.57E-10 5.62E-10 2.78E-10 1.59E-10 5.77E-11 1.77E-11 7.17E-12 3.86E-12 2.40E-12 WSW 2.87E-09 6.37E-10 6.40E-10 2.99E-10 1.78E-10 6.27E-11 1.92E-11 7.89E-12 4.25E-12 2.64E-12 W 5.54E-09 1.06E-09 6.25E-10 3.84E-10 2.91E-10 1.17E-10 3.60E-11 1.46E-11 7.87E-12 4.89E-12 WNW 6.71E-09 1.21E-09 7.72E-10 5.81E-10 3.32E-10 1.18E-10 3.60E-11 1.46E-11 7.86E-12 4.89E-12 NW 4.25E-09 7.99E-10 4.43E-10 2.16E-10 1.35E-10 7.25E-11 2.30E-11 1.OOE-11 5.38E-12 3.34E-12 NNW 2.61E-09 6.15E-10 3.47E-10 I1.70E-10 1.25E-10 6.32E-1I 2.02E-11 8.24E-12 4.43E-12 2.75E-12 DATA FROM 2006 -2010 USED IN CALCULATIONS

CY-TM-1 70-300 Revision 3 Page 129 of 209 TABLE 4.5 Atmospheric Dispersion Factors for Three Mile Island GROUND RELEASE 3 DISTANCE 4=(rTr)0 A\I~pAt.Ir V/IA 1IlK 4arlA N lKII IPt* Q1 QPAAM1 - AKIKIHAI UJIAJ,1%

'.d*/ /-la *vxl\/'-. 1 11 .I1 I i I- L..

.- 1J,/U . .. lJ.',./*JiI -- f ,t~lt.,I SECTOR 610 2413 4022 5631 7240 12067 24135 40225 56315 72405 N 8.15E-06 1.01E-06 5.06E-07 3.22E-07 2.31E-07 1.18E-07 4.79E-08 2.50E-08 1.63E-08 1.19E-08 NNE 9.69E-06 1.19E-06 5.97E-07 3.81E-07 2.73E-07 1.39E-07 5.69E-08 2.97E-08 1.94E-08 1.42E-08 NE 1.19E-05 1.47E-06 7.38E-07 4.70E-07 3.36E-07 1.71E-07 6.94E-08 3.61E-08 2.36E-08 1.72E-08 ENE 1.31E-05 1.65E-06 8.26E-07 5.25E-07 3.75E-07 1.91E-07 7.72E-08 4.OOE-08 2.61E-08 1.90E-08 E 1.40E-05 1.78E-06 8.83E-07 5.57E-07 3.96E-07 2.00E-07 7.98E-08 4.11E-08 2.66E-08 1.93E-08 ESE 1.19E-05 1.50E-06 7.35E-07 4.61E-07 3.26E-07 1.63E-07 6.44E-08 3.29E-08 2.12E-08 1.54E-08 SE 1.16E-05 1.43E-06 6.99E-07 4.38E-07 3.10E-07 1.55E-07 6.18E-08 3.18E-08 2.06E-08 1.49E-08 SSE 9.94E-06 1.26E-06 6.16E-07 3.86E-07 2.73E-07 1.37E-07 5.41E-08 2.77E-08 1.79E-08 1.29E-08 S 6.77E-06 8.87E-07 4.33E-07 2.71E-07 1.91E-07 9.50E-08 3.73E-08 1.90E-08 1.22E-08 8.79E-09 SSW 4.47E-06 5.88E-07 2.87E-07 1.80E-07 1.27E-07 6.33E-08 2.49E-08 1.27E-08 8.15E-09 5.87E-09 SW 4.18E-06 5.44E-07 2.66E-07 1.66E-07 1.17E-07 5.83E-08 2.29E-08 1.16E-08 7.48E-09 5.39E-09 WSW 5.06E-06 6.49E-07 3.19E-07 2.01E-07 1.42E-07 7.12E-08 2.83E-08 1.45E-08 9.35E-09 6.76E-09 W 7.42E-06 9.56E-07 4.70E-07 2.96E-07 2.1OE-07 1.05E-07 4.16E-08 2.13E-08 1.37E-08 9.93E-09 WNW 7.75E-06 9.78E-07 4.85E-07 3.07E-07 2.19E-07 1.1OE-07 4.42E-08 2.28E-08 1.48E-08 1.08E-08 NW 7.07E-06 8.80E-07 4.41E-07 2.81E-07 2.01E-07 1.02E-07 4.15E-08 2.16E-08 1.41E-08 1.03E-08 NNW 6.67E-06 8.33E-07 4.18E-07 2.66E-07 1.90E-07 9.70E-08 3.94E-08 2.05E-08 1.34E-08 9.74E-09 GROUND RELEASE DISTANCE SECTOR AVERAGE D/Q (IN M-2 (IN METERS) SEASON - ANNUAL SECTOR 610 2413 4022 5631 7240 12067 24135 40225 56315 72405 N 1.40E-08 1.41E-09 5.78E-10 3.18E-10 2.03E-10 8.23E-11 2.61E-11 1.06E-11 5.70E-12 3.54E-12 NNE 1.92E-08 1.94E-09 7.96E-10 4.39E-10 2.80E-10 1.13E-10 3.60E-11 1.46E-11 7.85E-12 4.88E-12 NE 1.96E-08 1.98E-09 8.11E-10 4.47E-10 2.85E-10 1.16E-10 3.67E-11 1.49E-11 8.01E-12 4.97E-12 ENE 1.93E-08 1.95E-09 7.99E-10 4.40E-10 2.81E-10 1.14E-10 3.61E-11 1.46E-11 7.88E-12 4.89E-12 E 2.95E-08 2.98E-09 1.22E-09 6.74E-10 4.30E-10 1.74E-10 5.53E-11 2.24E-11 1.21E-11 7.49E-12 ESE 3.81E-08 3.85E-09 1.58E-09 8.69E-10 5.55E-10 2.25E-10 7.13E-11 2.89E-11 1.56E-11 9.66E-12 SE 4.25E-08 4.29E-09 1.76E-09 9.70E-10 6.19E-10 2.51E-10 7.96E-11 3.23E-11 1.74E-11 1.08E-11 SSE 2.94E-08 2.97E-09 1.22E-09 6.70E-10 4.28E-10 1.73E-10 5.50E-11 2.23E-11 1.20E-11 7.46E-12 S 1.57E-08 1.59E-09 6.52E-10 3.59E-10 2.29E-10 9.28E-11 2.94E-11 1.20E-11 6.43E-12 3.99E-12 SSW 8.14E-09 8.22E-10 3.37E-10 1.86E-10 1.19E-10 4.80E-11 1.52E-11 6.18E-12 3.33E-12 2.07E-12 SW 7.89E-09 7.97E-10 3.27E-10 1.80E-10 1.15E-10 4.65E-11 1.48E-11 5.99E-12 3.22E-12 2.OOE-12 WSW 9.38E-09 9.47E-10 3.88E-10 2.14E-10 1.37E-10 5.53E-11 1.75E-11 7.12E-12 3.83E-12 2.38E-12 W 1.57E-08 1.59E-09 6.52E-10 3.59E-10 2.29E-10 9.28E-11 2.94E-11 1.19E-11 6.43E-12 3.99E-12 WNW 1.62E-08 1.64E-09 6.71E-10 3.70E-10 2.36E-10 9.56E-11 3.03E-11 1.23E-11 6.62E-12 4.11E-12 NW 1.09E-08 1.1OE-09 4.49E-10 2.48E-10 1.58E-10 6.40E-11 2.03E-11 8.24E-12 4.43E-12 2.75E-12 NNW 9.23E-09 9.33E-10 3.82E-10 2.11E-10 1.34E-10 5.45E-11 1.73E-11 7.01E-12 3.77E-12 2.34E-12 DATA FROM 2006 - 2010 USED IN CALCULATIONS

CY-TM-1 70-300 Revision 3 Page 130 of 209 TABLE 4.6 Dose Parameters for Radioiodines and Radioactive Particulate in Gaseous Effluents*

CRITICAL ORGAN 1 CRITICAL ORGAN NUCLIDE ORGAN FACTOR Pi** NUCLIDE ORGAN FACTOR P***

TOTAL BODY 3.04E-07 1.12E+03 RU-103 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-106 LUNG 3.87E-03 1.43E+07 P-32 BONE 7.04E-04 2.60E+06 AG-11iM LUNG 1.48E-03 5.48E+06 CR-51 LUNG 4.59E-06 1.70E+04 TE-1 25M 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-LLI 3.33E-05 1.23E+05 TE-1 27M 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-1 29M LUNG 4.76E-04 1.76E+06 CO-58 LUNG 2.99E-04 1.11E+06 TE-129 GI-LLI 6.89E-06 2.55E+04 CO-60 LUNG 1.91 E-03 7.07E+06 TE-131M GI-LLI 8.32E-05 3.08E+05 NI-63 BONE 2.22E-04 8.21 E+05 TE-131 LUNG 5.55E-07 2.05E+03 NI-65 GI-LLI 2.27E-05 8.40E+04 TE-132 LUNG 1.02E-04 3.77E+05 CU-64 GI-LLI 9.92E-06 3.67E+04 1-130 THYROID 4.99E-04 1.85E+06 ZN-65 LUNG 2.69E-04 9.95E+05 1-131 THYROID 4.39E-03 1.62E+07 ZN-69 GI-LLI 2.75E-06 1.02E+04 1-132 THYROID 5.23E-05 1.94E+05 BR-83 TOTAL BODY 1.28E-07 4.74E+02 1-133 THYROID 1.04E-03 3.85E+06 BR-84 TOTAL BODY 1.48E-07 5.48E+02 1-134 THYROID 1.37E-05 5.07E+04 BR-85 TOTAL BODY 6.84E-09 2.53E+01 1-135 THYROID 2.14E-04 7.92E+05 RB-86 LIVER 5.36E-05 1.98E+05 CS-1 34 LIVER 2.74E-04 1.01 E+06 RB-88 LIVER 1.52E-07 5.62E+02 CS-1 36 LIVER 4.62E-05 1.71 E+05 RB-89 LIVER 9.33E-08 3.45E+02 CS-1 37 BONE 2.45E-04 9.07E+05 SR-89 LUNG 5.89E-04 2.16E+06 CS-1 38 LIVER 2.27E-07 8.40E+02 SR-90 BONE 2.73E-02 1.01E+08 BA-1 39 GI-LLI 1.56E-05 5.77E+04 SR-91 GI-LLI 4.70E-05 1.74E+05 BA-140 LUNG 4.71 E-04 1.74E+06 SR-92 GI-LLI 6.55E-05 2.42E+05 BA-141 LUNG 7.89E-07 2.92E+03 Y-90 GI-LLI 7.24E-05 2.68E+05 BA- 142 LUNG 4.44E-07 1.64E+03 Y-91M LUNG 7.60E-07 2.81 E+03 LA-140 GI-LLI 6.1 OE-05 2.26E+05 Y-91 LUNG 7.10E-04 2.63E+06 LA-142 GI-LLI 2.05E-05 7.59E+04 Y-92 GI-LLI 6.46E-05 2.39E+05 CE-141 LUNG 1.47E-04 5.44E+05 Y-93 GI-LLI 1.05E-04 3.89E+05 CE-143 GI-LLI 3.44E-05 1.27E+05 ZR-95 LUNG 6.03E-04 2.23E+06 CE-144 LUNG 3.23E-03 1.20E+07 ZR-97 GI-LLI 9.49E-05 3.51 E+05 PR-143 LUNG 1.17E-04 4.33E+05 NB-95 LUNG 1.66E-04 6.14E+05 PR-144 LUNG 4.23E-07 1.57E+03 MO-99 LUNG 3.66E-05 1.35E+05 ND-147 LUNG 8.87E-05 3.28E+05 TC-99M GI-LLI 1.30E-06 4.81E+03 W-187 GI-LLI 2.46E-05 9.1OE+04 TC-101 LUNG 11.58E-07 5.85E+02 NP-239 GI-LLI 1.73E-05 6.40E+04

The listed dose parameters are for radionuclides, other than noble gases that may be detected in gaseous effluents. Pi factors include all nonatmospheric pathway transport parameters, the receptor's usage of pathway media, and are based on the most restrictive age group (child) critical organ. Additional dose parameters for nuclides not included in this Table may be calculated using the methodology described in NUREG-0133.

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

mrem/year per p.Ci/m 3.

CY-TM-1 70-300 Revision 3 Page 131 of 209 FIGURE 4.1 TMI-1 Gaseous Effluent Pathways FIGURE 4.1.

00.0m0 or" C NOUNSE" OFF (3^

STACK 0-40 CFM ~

P-PRE FILTER A-ABSOLUTE HEPA C-CHARCOAL FILTER VACUUM PUMPS

CY-TM-1 70-300 Revision 3 Page 132 of 209 FIGURE 4.2 TMI-1 Auxiliary and Fuel Handling Buildings Effluent Pathways

CY-TM-1 70-300 Revision 3 Page 133 of 209 FIGURE 4.3 TMI-1 Reactor Building Effluent Pathway

CY-TM-1 70-300 Revision 3 Page 134 of 209 FIGURE 4.4 TMI-1 Condenser Offgas Effluent Pathway

CY-TM-1 70-300 Revision 3 Page 135 of 209 FIGURE 4.5 TMI-2 Gaseous Effluent Filtration System/Pathways STATION VENT 0 - -14*,000 CFN RB BREATHER I - - - - - - - - - - - - - -

UNIT 2 EXHAUST AIR FLOW AND RMS SCHEMATIC

CY-TM-170-300 Revision 3 Page 136 of 209

.5.0 GASEOUS 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 Ratetb = z (KI) x (Dv) x (Q1) (eq 5.1.1.1)

Where:

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

Ki = total body dose factor due to gamma emissions for each 3 identified noble gas radionuclide, in mrem/yr per ýLCi/m 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 1.27E-6 sec/m 3 at sector SE for station vent, and 1.40E-5 sec/m 3 for all other releases at sector E.

Qi = Release rate of radionuclide, i, in jLCi/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.

CY-TM-1 70-300 Revision 3 Page 137 of 209 5,1.1.2 Skin Dose Ratesk = f (Li + 1.1 M1) 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.

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

Mi = air dose factor due to gamma emissions for each 3

identified noble gas radionuclide, in mrad/yr per jiCi/m from Table 4.3.

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

Qi = release rate of radionuclide, i, in jiCi/sec, as determined by sampling and analysis. Calculated using the concentration of noble gas radionuclide, i, in IiCi/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 1.27E-6 sec/m 3 at sector SE for station vent, and 1.40E-5 sec/m 3 for all other releases at E.

CY-TM-1 70-300 Revision 3 Page 138 of 209 5.1.2 Iodine-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 = f (Pi) (Dv) (Qi) (eq 5.1.2)

Where:

Dose Rateip = 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 pCi/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 1.27E-6 sec/m 3 for station vent, at sector SE, and 1.40E-5 sec/m 3 for all other releases at sector E.

Q= release rate of each radionuclide, i, in pCi/sec.

Calculated using the concentration of each radionuclide, i, in ýtCi/cc, times the release pathway flow rate, in cc/second.

CY-TM-1 70-300 Revision 3 Page 139 of 209 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 F = (3.17E-8) x z (Mi) x (Dv) x (Qi) (eq 5.2.1) and Dose P3 = (3.17E-8) x i (Ni) x (Dv) x (Qi) (eq 5.2.2)

Where:

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

Dose P3= mrad beta air dose due to beta emissions from noble gas radionuclides.

Mi = air dose factor due to gamma emissions for each identified noble gas radionuclide, in mrad/yr per jiCi/m3 ,

from Table 4.3.

Ni = air dose factor due to beta emissions for each identified noble gas radionuclide, in mrad/yr per giCi/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 1.27E-6 sec/m 3 for station vent at sector SE, and 1.40E-5 sec/m 3 for all other releases at sector E.

Q= release of noble gas radionuclide, i, in jiCi, over the specified time period, (ftCi/second

seconds).

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

CY-TM-1 70-300 Revision 3 Page 140 of 209 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.

5.2.2 Iodine-131, Iodine-133, 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. = * (3.17E-8) x z (Ri) (Dv) (Q1) (eq 5.2.2)

Where:

Doseo = 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 itCi/m 3 for the inhalation pathway and m 2 - mrem/yr per jiCi/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 Ri 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.

NOTE: Tritium, H-3, dose factor is mrem/year per ýtCi/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 boundary and critical receptor doses are as follows:

CY-TM-1 70-300 Revision 3 Page 141 of 209 Station Vent Releases - Boundary - all in sector SE Inhalation X/Q 1.27E-6 Meat D/Q 4.09E-8 Ground D/Q 4.09E-8 Cow/Milk/Infant D/Q 4.09E-8 Vegetation D/Q 4.09E-8 Station Vent Releases - Critical Receptor Inhalation X/Q 1.13E-6 in sector SE Meat D/Q 5.93E-9 Ground D/Q 2.25E-8 in sector SE in sector SE Cow/Milk/Infant D/Q 5.93E-9 Vegetation D/Q 1.34E-8 in sector SE in sector E Ground or Other Releases - Boundary Inhalation X/Q 1.40E-5 in sector E all in sector SE:

Meat D/Q 4.25E-8 Ground D/Q 4.25E-8 Cow/Milk/Infant D/Q 4.25E-8 Vegetation D/Q 4.25E-8 Ground or Other Releases - Critical Receptor - all in sector E Inhalation X/Q 1.12E-5 Meat D/Q 4.94E-9 Ground D/Q 2.37E-3 Cow/Milk/Infant D/Q 4.94E-9 Vegetation D/Q 1.92E-8 Dv(H-3) = In the case of H-3 only the X/Q's above are used for all pathways.

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

seconds).

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

CY-TM-1 70-300 Revision 3 Page 142 of 209 5.3 Gaseous Radioactive System Dose Calculations Once per Month ODCM 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 doses 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 Figure 4.5, shall be used to reduce radioactivity levels prior to release.

At the discretion of the ODCM Specialist, 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.

CY-TM-1 70-300 Revision 3 Page 143 of 209 5.4 Alternative Gaseous Dose Calculational Methodologqy 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.

CY-TM-1 70-300 Revision 3 Page 144 of 209 TABLE 5.2.1 Pathway Dose Factors, R1 AGE GROUP: INFANT PATHWAY: INHALATION 3

NUC LID E - - - - - - - ORGAN - DOSE - - - - -mrem/year

- - - FACTORS; - -gCi/m

- - - - per - - - - -- - - - -

BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 0.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 5.31E+03 5.31E+03 5.31E+03 5.31E+03 5.31E+03 5.31E+03 CR-51 0.OOE+00 0.OOE+00 8.95E+01 5.75E+01 1.32E+01 1.28E+04 3.57E+02 MN-54 0.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 0.00E+00 O.00E+00 8.69E+04 1.09E+03 FE-59 1.36E+04 2.35E+04 9.48E+03 0.OOE+00 O.OOE+00 1.02E+06 2.48E+04 CO-58 0.OOE+00 1.22E+03 1.82E+03 0.OOE+00 0.OOE+00 7.77E+05 1.11E+04 CO-60 O.OOE+00 8.02E+03 1.18E+04 0.OOE+00 0.OOE+00 4.51E+06 3.19E+04 NI-63 3.39E+05 2.04E+04 1.16E+04 0.OOE+00 0.OOE+00 2.09E+05 2.42E+03 ZN-65 1.93E+04 6.26E+04 3.11E+04 O.OOE+00 3.25E+04 6.47E+05 5.14E+04 RB-86 0.OOE+00 1.90E+05 8.82E+04 O.OOE+00 0.OOE+00 0.OOE+00 3.04E+03 SR-89 3.98E+05 O.OOE+00 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.OOE+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-1 03 2.02E+03 O.OOE+00 6.79E+02 0.OOE+00 4.24E+03 5.52E+05 1.61 E+04 RU-106 8.68E+04 O.OOE+00 1.09E+04 O.OOE+00 1.07E+05 1.16E+07 1.64E+05 AG-110M 9.98E+03 7.22E+03 5.OOE+03 0.OOE+00 1.09E+04 3.67E+06 3.30E+04 TE-125M 4.76E+03 1.99E+03 6.58E+02 1.62E+03 O.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-129M 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 1.96E+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-1 36 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-1 44 3.19E+06 1.21E+06 1.76E+05 0.OOE+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

CY-TM-1 70-300 Revision 3 Page 145 of 209 TABLE 5.2.2 Pathway Dose Factors, R, AGE GROUP: CHILD PATHWAY: INHALATION 3

NUCLIDE [ ORGAN DOSE FACTORS; mrem/year per p.Ci/m

[ 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.OOE+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.OOE+04 1.58E+06 2.29E+04 FE-55 4.74E+04 2.52E+04 7.77E+03 0.OOE+00 0.OOE+00 1.11E+05 2.87E+03 FE-59 2.07E+04 3.34E+04 1.67E+04 O.OOE+00 0.OOE+00 1.27E+06 7.07E+04 CO-58 O.OOE+00 1.77E+03 3.16E+03 0.OOE+0O 0.OOE+00 1.11E+06 3.44E+04 CO-60 0.OOE+00 1.31E+04 2.26E+04 0.OOE+0O 0.OOE+00 7.07E+06 9.62E+04 NI-63 8.21 E+05 4.63E+04 2.80E+04 0.OOE+0O 0.OOE+00 2.75E+05 6.33E+03 ZN-65 4.26E+04 1.13E+05 7.03E+04 0.OOE+0O 7.14E+04 9.95E+05 1.63E+04 RB-86 0.OOE+00 1.98E+05 1.14E+05 O.OOE+O0 0.OOE+00 O.OOE+00 7.99E+03 SR-89 5.99E+05 0.OOE+00 1.72E+04 O.OOE+00 O.OOE+00 2.16E+06 1.67E+05 SR-90 1.01E+08 0.OOE+00 6.44E+06 0.OOE+00 O.OOE+00 1.48E+07 3.43E+05 Y-91 9.14E+05 0.OOE+00 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+OO 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-1 03 2.79E+03 O.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 AG-110M 1.69E+04 1.14E+04 9.14E+03 0.OOE+00 2.12E+04 5.48E+06 1.OOE+05 TE-1 25M 6.73E+03 2.33E+03 9.14E+02 1.92E+03 0.OOE+00 4.77E+05 3.38E+04 TE- 27M 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 4.81E+04 4.81E+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 CS-134 6.51E+05 1.01E+06 2.25E+05 O.OOE+00 3.30E+05 1.21E+05 3.85E+03 CS-136 6.51E+04 1.71E+05 1.16E+05 O.OOE+00 9.55E+04 1.45E+04 4.18E+03 CS-137 9.07E+05 8.25E+05 1.28E+05 O.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 2.11E+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 3.61E+05 O.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

CY-TM-1 70-300 Revision 3 Page 146 of 209 TABLE 5.2.3 Pathway Dose Factors, R, AGE GROUP: TEEN PATHWAY: INHALATION 3

N ORGAN DOSE FACTORS; mrem/year per ý.Ci/m NUCLIDE 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.OOE+00 1.35E+02 7.50E+01 3.07E+01 2.10E+04 3.OOE+03 MN-54 O.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 O.OOE+00 0.OOE+00 1.53E+06 1.78E+05 CO-58 0.OOE+00 2.07E+03 2.78E+03 O.OOE+00 0.OOE+00 1.34E+06 9.52E+04 CO-60 0.OOE+00 1.51E+04 1.98E+04 0.OOE+00 0.OOE+00 8.72E+06 2.59E+05 NI-63 5.80E+05 4.34E+04 1.98E+04 0.OOE+00 O.OOE+00 3.07E+05 1.42E+04 ZN-65 3.86E+04 1.34E+05 6.24E+04 O.OOE+00 8.64E+04 1.24E+06 4.66E+04 RB-86 O.OOE+00 1.90E+05 8.40E+04 0.OOE+00 0.OOE+00 0.OOE+00 1.77E+04 SR-89 4.34E+05 O.OOE+00 1.25E+04 0.OOE+00 0.OOE+00 2.42E+06 3.71 E+05 SR-90 1.08E+08 O.OOE+00 6.68E+06 0.OOE+00 O.OOE+00 1.65E+07 7.65E+05 Y-91 6.61E+05 O.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 O.OOE+00 1.OOE+04 7.51 E+05 9.68E+04 RU-103 2.10E+03 0.OOE+00 8.96E+02 O.OOE+00 7.43E+03 7.83E+05 1.09E+05 RU-106 9.84E+04 O.OOE+00 1.24E+04 0.OOE+00 1.90E+05 1.61 E+07 9.60E+05 AG-110M 1.38E+04 1.31E+04 7.99E+03 O.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 4.91E+04 2.64E+04 1.46E+07 8.40E+04 0.OOE+00 6.49E+03 1-133 1.22E+04 2.05E+04 6.22E+03 2.92E+06 3.59E+04 O.OOE+00 1.03E+04 CS-134 5.02E+05 1.13E+06 5.49E+05 O.OOE+00 3.75E+05 1.46E+05 9.76E+03 CS-136 5.15E+04 1.94E+05 1.37E+05 O.OOE+00 1.10E+05 1.78E+04 1.09E+04 CS-137 6.70E+05 8.48E+05 3.11E+05 O.OOE+00 3.04E+05 1.21 E+05 8.48E+03 BA-140 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.OOE+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 5.31E+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

CY-TM-170-300 Revision 3 Page 147 of 209 TABLE 5.2.4 Pathway Dose Factors, R, AGE GROUP: ADULT PATHWAY: INHALATION 3

U ORGAN DOSE FACTORS; mrem/year per pCi/m NUCLI 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 3.41E+03 3.41E+03 3.41E+03 3.41E+03 3.41E+03 3.41E+03 CR-51 0.OOE+00 0.OOE+00 1.OOE+02 5.95E+01 2.28E+01 1.44E+04 3.32E+03 MN-54 0.OOE+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 O.OOE+00 O.OOE+00 7.21E+04 6.03E+03 FE-59 1.18E+04 2.78E+04 1.06E+04 0.00E+00 0.OOE+00 1.02E+06 1.88E+05 0.OOE+00 CO-58 0.OOE+00 1.58E+03 2.07E+03 0.OOE+00 O.OOE+00 9.28E+05 1.06E+05 CO-60 O.OOE+00 1.15E+04 1.48E+04 O.OOE+00 0.OOE+00 5.97E+06 2.85E+05 NI-63 4.32E+05 3.14E+04 1.45E+04 0.OOE+00 1.78E+05 1.34E+04 0.OOE+00 ZN-65 3.24E+04 1.03E+05 4.66E+04 O.OOE+00 6.90E+04 8.64E+05 5.34E+04 RB-86 0.OOE+00 1.35E+05 5.90E+04 0.OOE+00 0.OOE+00 0.OOE+00 1.66E+04 SR-89 3.04E+05 O.OOE+00 8.72E+03 O.OOE+00 1.40E+06 3.50E+05 O.OOE+00 SR-90 9.92E+07 O.OOE+00 6.10E+06 0.OOE+00 0.OOE+00 9.60E+06 7.22E+05 Y-91 4.62E+05 O.OOE+00 1.24E+04 0.OOE+00 0.OOE+00 1.70E+06 3.85E+05 ZR-95 1.07E+05 3.44E+04 2.33E+04 5.42E+04 1.77E+06 1.50E+05 O.OOE+00 7.74E+03 5.05E+05 1-.04E+05 NB-95 1.41E+04 7.82E+03 4.21E+03 O.OOE+00 5.83E+03 5.05E+05 1.10E+05 RU-1 03 1.53E+03 0.OOE+00 6.58E+02 0.OOE+00 RU-1 06 6.91E+04 0.OOE+00 8.72E+03 1.34E+05 9.36E+06 9.12E+05 0.00E+00 AG-11 OM 1.08E+04 1.OOE+04 5.94E+03 1.97E+04 4.63E+06 3.02E+05 TE-1 25M 3.42E+03 1.58E+03 4.67E+02 1.05E+03 1.24E+04 3.14E+05 7.06E+04 TE-1 27M 1.26E+04 5.77E+03 1.57E+03 3.29E+03 4.58E+04 9.60E+05 1.50E+05 TE-1 29M 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.OOE+00 6.28E+03 1-133 8.64E+03 1.48E+04 4.52E+03 2.15E+06 2.58E+04 0.OOE+00 8.88E+03 CS-1 34 3.73E+05 8.48E+05 7.28E+05 0.OOE+00 2.87E+05 9.76E+04 1.04E+04 CS-1 36 3.90E+04 1.46E+05 1.10E+05 O.OOE+00 8.56E+04 1.20E+04 1.17E+04 CS-137 4.78E+05 6.21E+05 4.28E+05 O.OOE+00 2.22E+05 7.52E+04 8.40E+03 BA-140 3.90E+04 4.90E+01 2.57E+03 O.OOE+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.OOE+00 8.48E+05 7.78E+06 8.16E+05 PR-143 9.36E+03 3.75E+03 4.64E+02 0.OOE+00 2.16E+03 2.81E+05 2.00E+05 ND-147 5.27E+03 6.10E+03 3.65E+02 0.OOE+00 3.56E+03 2.21E+05 1.73E+05

CY-TM-1 70-300 Revision 3 Page 148 of 209 TABLE 5.3.1 Pathway Dose Factors, R, AGE GROUP: ALL PATHWAY: GROUND PLANE ORGAN DOSE FACTORS*

NUCLIDE T.BODY SKIN I----------------------------------------

H-3 0.OOE+00 0.OOE+00 C-14 0.OOE+00 0.OOE+00 CR-51 4.65E+06 5.50E+06 MN-54 1.39E+09 1.62E+09 FE-55 0.OOE+00 0.OOE+00 FE-59 2.73E+08 3.21E+08 CO-58 3.79E+08 4.44E+08 CO-60 2.15E+10 2.53E+10 NI-63 0.OOE+00 O.OOE+00 ZN-65 7.47E+08 8.59E+08 RB-86 8.97E+06 1.03E+07 SR-89 2.16E+04 2.51E+04 I--------------------- --------------------

, SR-90 O.OOE+00 O.OOE+00 Y-91 1.07E+06 1.21 E+06 ZR-95 2.45E+08 2.84E+08 NB-95 1.37E+08 1.61 E+08 RU-103 1.08E+08 1.26E+08

-RU-106 4.22E+08 5.06E+08

, AG-1l OM 3.44E+09 4.01E+09

TE-125M 1.55E+06 2.13E+06

,TE-127M 9.17E+04 1.08E+05 TE-129M 1.98E+07 2.31E+07

1-131 1.72E+07 2.09E+07 1-133 2.45E+06 2.98E+06 CS-1 34 6.86E+09 8.OOE+09 CS-136 1.51E+08 1.71E+08 CS-1 37 1.03E+10 1.20E+10 BA-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 O.00E+00 0.OOE+00 ND-147 8.39E+06 1.01E+07

m2 _ mrem/year per pCi/sec.

CY-TM-1 70-300 Revision 3 Page 149 of 209 TABLE 5.4.1 Pathway Dose Factors, R, AGE GROUP: INFANT PATHWAY: GRASS-COW-MILK NUCLIDE ORGAN DOSE FACTORS; m2 - mrem/year per pCi/sec

-BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 0.OOE+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.OOE+08 5.OOE+08 5.OOE+08 5.OOE+08 5.OOE+08 CR-51 0.OOE+00 O.OOE+00 1.61 E+05 1.05E+05 2.30E+04 2.05E+05 4.70E+06 MN-54 0.OOE+00 3.91 E+07 8.85E+06 0.OOE+00 8.65E+06 0.OOE+00 1.43E+07 FE-55 1.35E+08 8.74E+07 2.34E+07 0.OOE+00 O.OOE+00 4.27E+07 1.11E+07 FE-59 2.25E+08 3.93E+08 1.55E+08 0.OOE+00 0.OOE+00 1.16E+08 1.88E+08 CO-58 O.OOE+00 2.43E+07 6.06E+07 0.OOE+00 0.OOE+00 0.OOE+00 6.05E+07 CO-60 O.OOE+00 8.83E+07 2.08E+08 0.OOE+00 O.OOE+00 0.OOE+00 2.10E+08 NI-63 3.50E+10 2.16E+09 1.21E+09 0.OOE+00 O.OOE+00 O.OOE+00 1.08E+08 ZN-65 5.56E+09 1.91E+10 8.79E+09 0.00E+00 9.24E+09 0.OOE+00 1.61E+10 RB-86 0.00E+00 2.23E+10 1.10E+10 0.00E+O0 O.OOE+00 0.OOE+00 5.70E+08 SR-89 1.26E+10 0.OOE+00 3.62E+08 0.00E+O0 0.OOE+00 0.OOE+00 2.59E+08 SR-90 1.22E+1 1 0.OOE+00 3.10E+10 0.OOE+00 0.OOE+00 0.OOE+00 1.52E+09 Y-91 7.34E+04 0.OOE+00 1.95E+03 0.OOE+00 0.OOE+00 0.OOE+00 5.26E+06 ZR-95 6.81E+03 1.66E+03 1.18E+03 0.OOE+O0 1.79E+03 0.OOE+00 8.27E+05 NB-95 5.94E+05 2.45E+05 1.41E+05 0.OOE+00 1.75E+05 0.00E+00 2.07E+08 RU-1 03 8.68E+03 O.OOE+00 2.90E+03 0.OOE+00 1.81 E+04 O.OOE+00 1.06E+05 RU-1 06 1.91E+05 O.OOE+00 2.38E+04 0.OOE+00 2.25E+05 0.OOE+00 1.45E+06 AG-110M 3.86E+08 2.82E+08 1.87E+08 0.OOE+00 4.03E+08 0.00E+00 1.46E+10 TE-125M 1.51E+08 5.05E+07 2.04E+07 5.08E+07 O.00E+00 0.00E+00 7.19E+07 TE-127M 4.22E+08 1.40E+08 5.1OE+07 1.22E+08 1.04E+09 0.OOE+00 1.70E+08 TE-129M 5.58E+08 1.91E+08 8.59E+07 2.14E+08 1.39E+09 0.OOE+00 3.33E+08 1-131 2.72E+09 3.21E+09 1.41E+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.OOE+00 8.96E+06 CS-134 3.65E+10 6.81E+10 6.88E+09 0.OOE+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 BA-140 2.42E+08 2.42E+05 1.25E+07 0.OOE+00 5.75E+04 1.49E+05 5.94E+07 CE-141 4.34E+04 2.65E+04 3.12E+03 0.OOE+00 8.17E+03 0.OOE+00 1.37E+07 CE-144 2.33E+06 9.53E+05 1.30E+05 0.OOE+00 3.85E+05 0.OOE+00 1.34E+08 PR-143 1.49E+03 5.56E+02 7.37E+01 0.OOE+00 2.07E+02 0.OOE+00 7.84E+05 ND-147 8.83E+02 9.07E+02 5.55E+01 0.OOE+00 3.50E+02 O.OOE+00 5.75E+05

CY-TM-1 70-300 Revision 3 Page 150 of 209 TABLE 5.4.2 Pathway Dose Factors, Ri AGE GROUP: CHILD PATHWAY: GRASS-COW-MILK 2

ORGAN DOSE FACTORS; m - mrem/year per pCi/sec NUCLIDE

[BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 0.00E+00 1.57E+03 1.57E+03 1.57E+03 1.57E+03 1.57E+03 1.57E+03 C-14 1.20E+09 2.39E+08 2.39E+08 2.39E+08 2.39E+08 2.39E+08 2.39E+08 CR-51 0.00E+00 O.OOE+00 1.02E+05 5.65E+04 1.54E+04 1.03E+05 5.40E+06 MN-54 O.OOE+00 2.1OE+07 5.59E+06 0.OOE+00 5.89E+06 0.OOE+00 1.76E+07 FE-55 1.12E+08 5.94E+07 1.84E+07 0.OOE+00 0.00E+00 3.36E+07 1.10E+07 FE-59 1.20E+08 1.95E+08 9.70E+07 0.OOE+00 0.OOE+00 5.65E+07 2.03E+08 CO-58 0.OOE+00 1.21E+07 3.72E+07 0.OOE+00 0.OOE+00 0.OOE+00 7.08E+07 CO-60 0.OOE+00 4.32E+07 1.27E+08 0.OOE+00 0.OOE+00 0.OOE+00 2.39E+08 NI-63 2.97E+10 1.59E+09 1.01E+09 0.OOE+00 0.OOE+00 0.OOE+00 1.07E+08 ZN-65 4.14E+09 1.10E+10 6.86E+09 0.00E+00 6.95E+09 0.OOE+00 1.94E+09 RB-86 0.OOE+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.OOE+00 1.89E+08 0.OOE+00 0.OOE+00 0.OOE+00 2.57E+08 SR-90 1.12E+11 0.OOE+00 2.84E+10 0.00E+00 0.OOE+00 0.OOE+00 1.51E+09 Y-91 3.91 E+04 O.OOE+00 1.05E+03 0.OOE+00 0.00E+00 0.OOE+00 5.21E+06 ZR-95 3.84E+03 8.43E+02 7.51 E+02 0.00E+00 1.21E+03 0.OOE+00 8.80E+05 NB-95 3.18E+05 1.24E+05 8.86E+04 0.00E+00 1.16E+05 0.OOE+00 2.29E+08 RU-1 03 4.29E+03 0.00E+00 1.65E+03 0.OOE+00 1.08E+04 0.OOE+00 1.11E+05 RU-106 9.25E+04 0.00E+00 1.15E+04 0.OOE+00 1.25E+05 0.OOE+00 1.44E+06 AG-110M 2.09E+08 1.41 E+08 1.13E+08 0.OOE+00 2.63E+08 0.OOE+00 1.68E+10 TE-1 25M 7.39E+07 2.OOE+07 9.85E+06 2.07E+07 0.OOE+00 0.OOE+00 7.13E+07 TE-1 27M 2.08E+08 5.61 E+07 2.47E+07 4.98E+07 5.94E+08 0.OOE+00 1.69E+08 TE-129M 2.72E+08 7.59E+07 4.22E+07 8.76E+07 7.98E+08 0.OOE+00 3.31E+08 1-131 1.31 E+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 CS-1 34 2.27E+÷ 0 3.72E+10 7.85E+09 0.OOE+00 1.15E+10 4.14E+09 2.01E+08 CS-1 36 1.01E+09 2.79E+09 1.80E+09 0.OOE+00 1.49E+09 2.21E+08 9.80E+07 CS-1 37 3.23E+10 3.09E+10 4.56E+09 0.OOE+00 1.01E+10 3.62E+09 1.93E+08 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+00 4.79E+03 0.OOE+00 1.36E+07 CE-144 1.63E+06 5.09E+05 8.67E+04 0.OOE+00 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 3.61E+02 2.79E+01 0.OOE+00 1.98E+02 0.OOE+00 5.71E+05

CY-TM-1 70-300 Revision 3 Page 151 of 209 TABLE 5.4.3 Pathway Dose Factors, R, AGE GROUP: TEEN PATHWAY: GRASS-COW-MILK NUCLIDE - - -FACTORS;

- - --DOSE

-- - - - - -ORGAN mz-- mrem/year

- - - -;- pe pCi/sec r m y a per t is c- -- - - - -

[ 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 O.OOE+00 4.99E+04 2.77E+04 1.09E+04 7.13E+04 8.39E+06 MN-54 0.OOE+00 1.40E+07 2.78E+06 0.OOE+00 4.19E+06 0.OOE+00 2.88E+07 FE-55 4.46E+07 3.16E+07 7.37E+06 O.OOE+00 O.OOE+00 2.01E+07 1.37E+07 FE-59 5.19E+07 1.21E+08 4.68E+07 O.OOE+00 O.00E+00 3.82E+07 2.86E+08 CO-58 0.OOE+00 7.94E+06 1.83E+07 O.OOE+00 0.OOE+00 0.OOE+00 1.10E+08 CO-60 0.OOE+00 2.78E+07 6.27E+07 O.OOE+00 O.OOE+00 0.OOE+00 3.62E+08 NI-63 1.18E+10 8.36E+08 4.01E+08 O.OOE+00 O.OOE+00 0.OOE+00 1.33E+08 ZN-65 2.11 E+09 7.32E+09 3.42E+09 O.OOE+00 4.69E+09 0.OOE+00 3.10E+09 RB-86 0.OOE+00 4.73E+09 2.22E+09 O.OOE+00 O.OOE+00 0.OOE+00 7.OOE+08 SR-89 2.68E+09 O.OOE+00 7.67E+07 O.OOE+00 O.OOE+00 0.OOE+00 3.19E+08 SR-90 6.62E+10 0.OOE+00 1.63E+10 O.OOE+00 O.OOE+00 0.OOE+00 1.86E+09 Y-91 1.58E+04 0.OOE+00 4.24E+02 0.00E+00 O.OOE+00 0.OOE+00 6.48E+06 ZR-95 1.65E+03 5.21E+02 3.58E+02 0.OOE+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-1 03 1.81 E+03 0.OOE+00 7.75E+02 0.OOE+00 6.39E+03 0.OOE+00 1.51E+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-11OM 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 O.OOE+00 0.OOE+00 8.87E+07 TE-1 27M 8.45E+07 3.OOE+07 1.OOE+07 2.01E+07 3.42E+08 0.OOE+00 2.11E+08 TE-1 29M 1.10E+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+10 1.07E+10 0.OOE+00 7.35E+09 2.81E+09 2.88E+08 CS-136 4.49E+08 1.77E+09 1.19E+09 0.OOE+00 9.63E+08 1.52E+08 1.42E+08 CS-1 37 1.34E+10 1.78E+10 6.21E+09 0.OOE+00 6.06E+09 2.36E+09 2.54E+08 BA-140 4.87E+07 5.97E+04 3.14E+06 0.OOE+00 2.02E+04 4.01E+04 7.51E+07 CE-141 8.89E+03 5.94E+03 6.82E+02 0.00E+00 2.80E+03 O.OOE+00 1.70E+07 CE-144 6.59E+05 2.73E+05 3.54E+04 O.OOE+00 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 O.OOE+00 1.16E+02 0.OOE+00 7.12E+05

CY-TM-1 70-300 Revision 3 Page 152 of 209 TABLE 5.4.4 Pathway Dose Factors, R, AGE GROUP: ADULT PATHWAY: GRASS-COW-MILK NUC LID E -- - - - - --ORGAN DOSE FACTORS; m 2-- -mrem/year - p.Ci/sec

- - - -per - - - - -- - - - -

[ BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 O.OOE+00 7.62E+02 7.62E+02 7.62E+02 7.62E+02 7.62E+02 7.62E+02 C-14 2.63E+08 5.26E+07 5.26E+07 5.26E+07 5.26E+07 5.26E+07 5.26E+07 CR-51 O.OOE+00 O.OOE+00 2.85E+04 1.70E+04 6.28E+03 3.78E+04 7.17E+06 MN-54 O.OOE+00 8.40E+06 1.60E+06 O.OOE+00 2.50E+06 O.OOE+00 2.57E+07 FE-55 2.51 E+07 1.73E+07 4.04E+06 O.OOE+00 O.OOE+00 9.66E+06 9.93E+06 FE-59 2.97E+07 6.97E+07 2.67E+07 O.OOE+00 O.OOE+00 1.95E+07 2.32E+08 CO-58 O.OOE+00 4.71E+06 1.05E+07 O.OOE+00 O.OOE+00 O.OOE+00 9.54E+07 CO-60 O.OOE+00 1.64E+07 3.61E+07 O.OOE+00 O.OOE+00 O.OOE+00 3.08E+08 NI-63 6.72E+09 4.65E+08 2.25E+08 O.OOE+00 O.OOE+00 O.OOE+00 9.71 E+07 ZN-65 1.37E+09 4.36E+09 1.97E+09 O.OOE+00 2.91E+09 O.OOE+00 2.74E+09 RB-86 O.OOE+00 2.59E+09 1.21E+09 O.OOE+00 O.OOE+00 O.OOE+00 5.10E+08 SR-89 1.45E+09 O.OOE+00 4.16E+07 O.OOE+00 O.OOE+00 O.OOE+00 2.32E+08 SR-90 4.67E+1 0 0.OOE+00 1.15E+10 O.OOE+00 O.OOE+00 0.OOE+00 1.35E+09 Y-91 8.57E+03 0.OOE+00 2.29E+02 O.OOE+00 0.OOE+00 0.OOE+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-103 1.02E+03 O.OOE+00 4.38E+02 O.OOE+00 3.88E+03 0.OOE+00 1.19E+05 RU-106 2.04E+04 O.OOE+00 2.58E+03 0.OOE+00 3.93E+04 0.OOE+00 1.32E+06 AG-110M 5.81E+07 5.38E+07 3.19E+07 0.OOE+00 1.06E+08 0.OOE+00 2.19E+10 TE-125M 1.63E+07 5.89E+06 2.18E+06 4.89E+06 6.61E+07 0.OOE+00 6.49E+07 TE-127M 4.57E+07 1.63E+07 5.57E+06 1.17E+07 1.86E+08 0.OOE+00 1.53E+08 TE-129M 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 O.OOE+00 6.04E+06 CS-134 5.64E+09 1.34E+10 1.10E+10 O.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-137 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 O.OOE+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 O.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

CY-TM-1 70-300 Revision 3 Page 153 of 209 TABLE 5.5.1 Pathway Dose Factors, R, AGE GROUP: INFANT PATHWAY: GRASS-GOAT-MILK NUCLIDE NUCLI

[ BONE ORGAN DOSE FACTORS; m2 - mrem/year per pCi/sec 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.OOE+08 5.00E+08 5.OOE+08 5.OOE+08 5.OOE+08 5.00E+08 CR-51 O.00E+00 0.OOE+00 1.94E+04 1 .26E+04 2.76E+03 2.46E+04 5.64E+05 MN-54 0.00E+00 4.68E+06 1.06E+06 O.OOE+00 1 .04E+06 0.OOE+00 1.72E+06 FE-55 1.76E+06 1.14E+06 3.03E+05 0.OOE+00 O.00E+00 5.55E+05 1.44E+05 FE-59 2.92E+06 5.10E+06 2.01E+06 0.OOE+00 0.00E+0O 1.51 E+06 2.44E+06 CO-58 0.00E+00 2.91E+06 7.26E+06 0.OOE+00 O.00E+O0 0.OOE+00 7.25E+06 CO-60 0.00E+00 1.06E+07 2.50E+07 O.00E+00 0.OOE+00 0.00E+00 2.52E+07 0.OOE+00 NI-63 4.19E+09 2.59E+08 1.46E+08 0.00E+00 O.00E+O0 1.29E+07 0.OOE+00 ZN-65 6.67E+08 2.29E+09 1.05E+09 0.OOE+00 1.11E+09 0.OOE+00 1.93E+09 RB-86 0.00E+00 2.67E+09 1.32E+09 0.OOE+00 0.00E+00 0.00E+00 6.83E+07 SR-89 2.65E+10 0.OOE+00 7.59E+08 0.OOE+O0 0.00E+O0 5.44E+08 SR-90 2.55E+11 0.OOE+00 6.50E+10 0.OOE+00 O.00E+00 0.OOE+00 3.19E+09 Y-91 8.80E+03 0.OOE+00 2.34E+02 0.00E+00 0.00E+00 0.OOE+00 6.31E+05 ZR-95 8.17E+02 1.99E+02 1.41E+02 0.00E+00 2.15E+02 0.OOE+00 9.91E+04 NB-95 7.13E+04 2.93E+04 1.70E+04 0.OOE+00 2.10OE+04 0.OOE+00 2.48E+07 RU-103 1.04E+03 0.OOE+00 3.48E+02 0.OOE+00 2.17E+03 0.00E+00 1.27E+04 RU-1 06 2.28E+04 0.OOE+00 2.85E+03 0.OOE+00 2.70E+04 O.OOE+00 1.73E+05 AG-110M 4.63E+07 3.38E+07 2.24E+07 0.OOE+00 4.84E+07 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 0.00E+00 1.24E+08 2.04E+07 TE-129M 6.69E+07 2.29E+07 1.03E+07 2.57E+07 1.67E+08 0.OOE+00 3.99E+07 1-131 3.27E+09 3.85E+09 1.69E+09 1.27E+1 2 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 1.07E+07 CS-1 34 1.09E+11 2.04E+11 2.06E+10 0.OOE+00 5.26E+10 2.15E+10 5.55E+08 CS-1 36 5.94E+09 1.75E+10 6.52E+09 0.00E+00 6.96E+09 1.42E+09 2.65E+08 CS-1 37 1.54E+11 1.81E+11 1.28E+10 0.OOE+00 4.85E+10 1.96E+10 5.65E+08 BA-140 2.90E+07 2.90E+04 1.50E+06 0.OOE+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.OOE+00 1.64E+06 CE-144 2.79E+05 1.14E+05 1.56E+04 0.OOE+00 4.62E+04 0.OOE+00 1.60E+07 PR-143 1.78E+02 6.66E+01 8.83E+00 0.OOE+00 2.48E+01 0.OOE+00 9.40E+04 ND-147 1.06E+02 1.09E+02 6.66E+00 0.00E+00 4.19E+01 O.OOE+00 6.89E+04

CY-TM-1 70-300 Revision 3 Page 154 of 209 TABLE 5.5.2 Pathway Dose Factors, R, AGE GROUP: CHILD PATHWAY: GRASS-GOAT-MILK ORGAN DOSE FACTORS; M2 _ mrem/year per ýtCi/sec NUCLIDE ORA-OS-A TOS- ------------ per---i-se-BONE 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 0.00E+00 0.00E+00 1.22E+04 6.78E+03 1.85E+03 1.24E+04 6.48E+05 MN-54 0.OOE+00 2.52E+06 6.71E+05 0.OOE+00 7.06E+05 0.00E+00 2.11E+06 FE-55 1.45E+06 7.71E+05 2.39E+05 0.OOE+00 0.OOE+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 CO-58 0.OOE+00 1.46E+06 4.46E+06 0.OOE+00 0.OOE+00 0.OOE+00 8.49E+06 CO-60 0.OOE+00 5.18E+06 1.53E+07 0.OOE+00 0.OOE+00 0.00E+00 2.87E+07 NI-63 3.56E+09 1.91E+08 1.21E+08 0.OOE+00 0.OOE+00 0.00E+00 1.28E+07 ZN-65 4.96E+08 1.32E+09 8.22E+08 O.OOE+00 8.33E+08 0.OOE+00 2.32E+08 RB-86 0.00E+00 1.05E+09 6.47E+08 0.00E+00 0.00E+00 0.OOE+00 6.77E+07 SR-89 1.39E+10 0.00E+00 3.97E+08 0.OOE+00 0.OOE+00 0.OOE+00 5.39E+08 SR-90 2.35E+l 1 0.OOE+00 5.95E+10 0.00E+00 0.OOE+00 0.OOE+00 3.16E+09 Y-91 4.69E+03 0.OOE+00 1.25E+02 0.00E+00 0.OOE+00 0.OOE+00 6.24E+05 ZR-95 4.60E+02 1.01E+02 9.OOE+01 0.00E+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-1 03 5.14E+02 0.00E+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 AG-11iM 2.51 E+07 1.69E+07 1.35E+07 0.OOE+00 3.15E+07 0.00E+00 2.01E+09 TE-1 25M 8.86E+06 2.40E+06 1.18E+06 2.49E+06 0.00E+00 0.OOE+00 8.55E+06 TE-127M 2.50E+07 6.72E+06 2.96E+06 5.97E+06 7.12E+07 0.OOE+00 2.02E+07 TE- 29M 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 5.21 E+i 1 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.OOE+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 6.01E+08 CS-1 36 3.04E+09 8.36E+09 5.41 E+09 0.OOE+00 4.45E+09 6.64E+08 2.94E+08 CS-137 9.68E+1 0 9.26E+10 1.37E+10 0.OOE+00 3.02E+10 1.09E+10 5.80E+08 BA-140 1.41E+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 6.11 E+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 0.00E+00 1.40E+01 0.OOE+00 9.29E+04 ND-147 5.34E+01 4.33E+01 3.35E+00 0.00E+00 2.37E+01 0.00E+00 6.85E+04

CY-TM-1 70-300 Revision 3 Page 155 of 209 TABLE 5.5.3 Pathway Dose Factors, R, AGE GROUP: TEEN PATHWAY: GRASS-GOAT-MILK NUCLIDE - ORGAN DOSE FACTORS; m 2 - mrem/year per IiCi/sec BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 0.OOE+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 1.31 E+03 8.55E+03 1.01E+06 MN-54 0.OOE+00 1.68E+06 3.34E+05 O.OOE+00 5.02E+05 0.OOE+00 3.45E+06 FE-55 5.79E+05 4.11E+05 9.58E+04 O.OOE+00 0.OOE+00 2.61 E+05 1.78E+05 FE-59 6.74E+05 1.57E+06 6.08E+05 O.OOE+00 0.OOE+00 4.96E+05 3.72E+06 CO-58 0.OOE+00 9.53E+05 2.20E+06 O.OOE+00 0.OOE+00 0.OOE+00 1.31E+07 CO-60 0.OOE+00 3.34E+06 7.52E+06 O.OOE+00 0.OOE+00 0.OOE+00 4.35E+07 NI-63 1.42E+09 1.OOE+08 4.81E+07 O.00E+00 0.OOE+00 O.OOE+00 1.60E+07 ZN-65 2.53E+08 8.78E+08 4.10E+08 O.OOE+00 5.62E+08 O.OOE+00 3.72E+08 RB-86 0.OOE+00 5.67E+08 2.67E+08 0.OOE+00 0.OOE+00 0.OOE+00 8.40E+07 SR-89 5.62E+09 0.OOE+00 1.61E+08 0.OOE+00 0.00E+00 O.OOE+00 6.69E+08 SR-90 1.39E+11 O.OOE+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 O.OOE+00 0.00E+00 0.OOE+00 7.78E+05 ZR-95 1.98E+02 6.25E+01 4.30E+01 O.OOE+00 9.18E+01 0.OOE+00 1.44E+05 NB-95 1.69E+04 9.38E+03 5.16E+03 O.OOE+00 9.09E+03 0.OOE+00 4.01E+07 RU-103 2.17E+02 0.00E+00 9.29E+01 0.OOE+00 7.66E+02 0.OOE+00 1.82E+04 RU-1 06 4.50E+03 O.00E+00 5.68E+02 0.OOE+00 8.69E+03 0.OOE+00 2.16E+05 AG-110M 1.16E+07 1.09E+07 6.65E+06 0.OOE+00 2.09E+07 0.OOE+00 3.07E+09 TE-125M 3.61E+06 1.30E+06 4.82E+05 1.01E+06 O.OOE+OO 0.OOE+00 1.06E+07 TE-1 27M 1.01E+07 3.59E+06 1.20E+06 2.41E+06 4.11lE+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 2.01E+09 2.53E+07 .0.00E+00 1.09E+07 CS-134 2.95E+10 6.93E+10 3.22E+10 O.OOE+00 2.20E+1 0 8.41 E+09 8.62E+08 CS-1 36 1:35E+09 5.30E+09 3.56E+09 O.OOE+00 2.89E+09 4.55E+08 4.27E+08 CS-137 4.02E+10 5.34E+10 1.86E+1i 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 4.81E+03 9.01E+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.OOE+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

CY-TM-1 70-300 Revision 3 Page 156 of 209 TABLE 5.5.4 Pathway Dose Factors, R, AGE GROUP: ADULT PATHWAY: GRASS-GOAT-MILK NUCLIDE ------- ORGAN -DOSE FACTORS; -m - mrem/year per p.Cilsec -------

__ __~_____ BONE -_

__~ -LIVER -_ T. BODY -- THYROID -- KIDNEY --- LUING- . GI-LLI_

H-3 O.OOE+00 1.56E+03 1.56E+03 1.56E+03 1.56E+03 1.56E+03 1.56E+03 C-14 2.64E+08 5.27E+07 5.27E+07 5.27E+07 5.27E+07 5.27E+07 5.27E+07 CR-51 O.OOE+00 0.OOE+00 3.43E+03 2.05E+03 7.56E+02 4.55E+03 8.63E+05

--.- OE+0-MN-54 O.00E+00 1.01E+06 1.93E+05 3.01 E+05 0.OOE+00 3.1OE+06 0.OOE+00 0.OOE+00 1.26E+05 1.30E+05 FE-55 3.27E+05 2.26E+05 5.26E+04 O.00E+00 2.54E+05 3.03E+06 FE-59 3.87E+05 9.09E+05 3.48E+05 0.OOE+00 0.OOE+OO-- 0.OOE+00 CO-58 5.66E+05 1.27E+06 0.OOE+00 0.OOE+00 1.15E+07 0.OOE+00 0.OOE+00 0.OOE+00 3.70E+07 CO-60 1.97E+06 4.35E+06 0.OOE+00 0.OOE+O0 1.17E+07 NI-63 8.08E+08 5.60E+07 2.71 E+07 0.OOE+00 0.OOE+00 0.00E+00 ZN-65 1.65E+08 5.24E+08 2.37E+08 3.51 E+08 0.OOE+00 3.30E+08 0.OOE+0O 6.14E+07 RB-86 0.OOE+00 3.12E+08 1.45E+08 0.OOE+00 0.OOE+00 O.00E+00 4.89E+08 SR-89 3.05E+09 0.00E+00 8.76E+07 0.OOE+00 0.OOE+00 SR-90 9.84E+10 0.OOE+00 2.41E+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.OOE+00 0.OOE+00 5.68E+05 ZR-95 1.13E+02 3.63E+01 2.46E+01 0.OOE+00 5.70E+01 0.OOE+00 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.OOE+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 3.10E+02 0.OOE+00 4.73E+03 0.OOE+00 1.59E+05 0.OOE+00-AG-110M 6.99E+06 6.47E+06 3.84E+06 0.OOE+00 1.27E+07 2.64E+09 7.96E+06 0.OOE+00 7.81 E+06 TE-125M 1.96E+06 7.09E+05 2.62E+05 5.89E+05 2.23E+07 0.OOE+00 1.84E+07 TE-127M 5.50E+06 1.97E+06 6.70E+05 1.41E+06 0.OOE+00 TE-129M 7.23E+06 2.70E+06 1.14E+06 2.48E+06 3.02E+07 0.OOE+00- 3.64E+07 M-131 3.56E+08 5.09E+08 2.92E+08 1.67E+i 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 CS-134 1.70E+10 4.04E+10 3.30E+10 0.OOE+00 1.31E+10 4.34E+09 7.07E+08 CS-1 36 7.92E+08 3.13E+09 2.25E+09 0.OOE+00 1.74E+09 2.38E+08 3.55E+08 CS-1 37 2.22E+10 3.03E+10 1.99E+10 0.OOE+00 1.03E+10 3.42E+09 5.87E+08 BA-140 3.24E+06 4.07E+03 2.12E+05 0.OOE+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 2.31E+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

CY-TM-1 70-300 Revision 3 Page 157 of 209 TABLE 5.6.1 Pathway Dose Factors, R, AGE GROUP: INFANT PATHWAY: GRASS-COW-MEAT NUCLIDE ORGAN DOSE FACTORS; m2 - mrem/year per pCi/sec BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 0.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 C-14 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 CR-51 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 MN-54 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 FE-55 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 FE-59 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 CO-58 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.00E+00 0.00E+00 CO-60 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 NI-63 O.OOE+00 0.OOE+00 0.OOE+00 0.0OE+00 0.OOE+00 0.OOE+00 O.OOE+00 ZN-65 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+O0O .OOE+00 0.OOE+00 O.OOE+00 RB-86 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 SR-89 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 SR-90 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+0O O.OOE+00 Y-91 0.OOE+00 0.OOE+O0 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 ZR-95 0.OOE+00 0.OOE+00 0.OOE+OO 0.OOE+00 0.OOE+O0 0.OOE+00 O.OOE+0O NB-95 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 RU-103 .0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 RU-106 0.OOE+00 0.OOE+O0 O.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 AG-110M 0.OOE+00 Q.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 TE-125M 0.OOE+00 0.OOE+O0 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 TE-127M 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00

°

) 0.OOE+00 0.OOE+00 TE-129M 0.OOE+00 0.OOE+OO ) O.OOE+00 0.OOE+O0 O.OOE+O0 0.OOE+00 0.OOE+00 1-131 O.OOE+00 0.OOE+00 ) 0.OOE+00 O.OOE+O0 O.OOE+00 0.00E+00 0.00E+00 1-133 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 CS-1 34 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 CS-1 36 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 CS-1 37 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 BA-140 0.OOE+00 O.OOE+00 0.0OE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 CE-141 O.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 CE-1 44 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 PR-1 43 O.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 ND-147 0.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00

CY-TM-170-300 Revision 3 Page 158 of 209 TABLE 5.6.2 Pathway Dose Factors, R, AGE GROUP: CHILD PATHWAY: GRASS-COW-MEAT NUCLIDE ORGAN DOSE FACTORS; m - mrem/year per ýtCi/sec

[LBONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 0.00E+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 0.OOE+00 0.OOE+00 8.78E+03 4.88E+03 1.33E+03 8.90E+03 4.66E+05 MN-54 O.00E+00 8.01E+06 2.13E+06 0.OOE+00 2.25E+06 O.00E+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 0.00E+00 1.77E+08 6.35E+08 CO-58 0.OOE+00 1.64E+07 5.03E+07 0.OOE+00 0.00E+00 O.OOE+00 9.58E+07 CO-60 0.OOE+00 6.93E+07 2.04E+08 O.OOE+00 0.00E+00 O.OOE+00 3.84E+08 NI-63 2.91E+10 1.56E+09 9.91E+08 O.00E+00 0.00E+00 0.OOE+00 1.05E+08 ZN-65 3.76E+08 1.OOE+09 6.22E+08 O.OOE+00 6.31E+08 0.OOE+00 1.76E+08 RB-86 0.OOE+00 5.76E+08 3.54E+08 0.OOE+00 0.00E+00 0.OOE+00 3.71E+07 SR-89 4.82E+08 0.OOE+00 1.38E+07 0.OOE+00 0.00E+00 0.OOE+00 1.87E+07 SR-90 1.04E+10 0.OOE+00 2.64E+09 0.OOE+00 0.00E+00 0.OOE+00 1.40E+08 Y-91 1.80E+06 0.OOE+00 4.82E+04 0.00E+00 O.00E+00 0.OOE+00 2.40E+08 ZR-95 2.66E+06 5.86E+05 5.21E+05 0.00E+00 8.38E+05 O.OOE+00 6.11E+08 NB-95 3.1OE+06 1.21 E+06 8.63E+05 0.OOE+00 1.13E+06 0.OOE+00 2.23E+09 RU-1 03 1.55E+08 0.OOE+00 5.96E+07 0.OOE+00 3.90E+08 0.OOE+00 4.01E+09 RU-1 06 4.44E+09 0.OOE+00 5.54E+08 0.OOE+00 6.OOE+09 0.OOE+00 6.91E+10 AG-i1 OM 8.39E+06 5.67E+06 4.53E+06 0.OOE+00 1.06E+07 0.OOE+00 6.74E+08 TE-125M 5.69E+08 1.54E+08 7.59E+07 1.60E+08 0.OOE+00 0.OOE+00 5.49E+08 TE- 127M 1.78E+09 4.78E+08 2.11E+08 4.25E+08 5.06E+09 0.OOE+00 1.44E+09 TE-129M 1.79E+09 5.OOE+08 2.78E+08 5.77E+08 5.26E+09 0.OOE+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 I-133 5.72E-01 7.08E-01 2.68E-01 1.31E+02 1.18E+00 0.OOE+00 2.85E-01 CS-134 9.23E+08 1.51E+09 3.19E+08 0.OOE+00 4.69E+08 1.68E+08 8.16E+06 CS-136 1.63E+07 4.48E+07 2.90E+07 0.OOE+00 2.39E+07 3.56E+06 1.57E+06 CS-137 1.33E+09 1.28E+09 1.89E+08 0.OOE+00 4.16E+08 1.50E+08 8.OOE+06 BA-140 4.42E+07 3.87E+04 2.58E+06 0.OOE+00 1.26E+04 2.31E+04 2.24E+07 CE-141 2.22E+04 1.11E+04 1.65E+03 0.OOE+00 4.86E+03 0.OOE+00 1.38E+07 CE-144 2.32E+06 7.26E+05 1.24E+05 0.OOE+00 4.02E+05 0.OOE+00 1.89E+08 PR-143 3.33E+04 1.OOE+04 1.65E+03 0.OOE+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.OOE+00 1.50E+07

CY-TM-1 70-300 Revision 3 Page 159 of 209 TABLE 5.6.3 Pathway Dose Factors, R, AGE GROUP: TEEN PATHWAY: GRASS-COW-MEAT NUCLIDE ORGAN DOSE FACTORS; m2 - mrem/year per pCi/sec NUCLI BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 0.OOE+00 1.93E+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 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 7.31E+07 FE-59 2.12E+08 4.95E+08 1.91E+08 0.OOE+00 0.OOE+00 1.56E+08 1.17E+09 CO-58 0.OOE+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 1.31E+08 0.OOE+00 0.OOE+00 0.OOE+00 7.60E+08 NI-63 1.52E+10 1.07E+09 5.15E+08 0.OOE+00 0.OOE+00 0.OOE+00 1.71E+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 1.91E+08 0.OOE+00 0.OOE+00 0.OOE+00 6.OOE+07 SR-89 2.55E+08 O.00E+00 7.29E+06 0.OOE+00 0.OOE+00 0.OOE+00 3.03E+07 SR-90 8.04E+09 0.00E+00 1.99E+09 0.00E+00 0.00E+00 0.OOE+00 2.26E+08 Y-91 9.54E+05 O.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 0.OOE+00-NB-95 1.79E+06 9.95E+05 5.48E+05 0.OOE+00 9.64E+05 4.25E+09 3.02E+08 0.OOE+00 7.15E+09 RU-1 03 8.56E+07 0.OOE+00 3.66E+07 0.OOE+00 0.OOE+00 1.13E+11 RU-1 06 2.36E+09 O.OOE+00 2.97E+08 0.OOE+00 4.54E+09 O.OOE+0O AG-110M 5.06E+06 4.78E+06 2.91E+06 0.OOE+00 9.13E+06 0.OOE+0O- 1.34E+09 TE-125M 3.03E+08 1.09E+08 4.05E+07 8.46E+07 0.OOE+00 0.OOE+00 8.94E+08 TE-127M 9.41E+08 3.34E+08 1.12E+08 2.24E+08 3.81 E+09 2.35E+09 0.OOE+00 TE-129M 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 3.95E-01 CS-134 5.23E+08 1.23E+09 5.71E+08 0.OOE+00 3.91 E+08 1 .49E+08 1.53E+07 CS-1 36 9.43E+06 3.71 E+07 2.49E+07 0.OOE+00 2.02E+07 3.18E+06 2.99E+06 CS-1 37 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 1.97E+04 3.69E+07 CE-141 1.18E+04 7.87E+03 9.05E+02 0.OOE+00 3.71E+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.OOE+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

CY-TM-1 70-300 Revision 3 Page 160 of 209 TABLE 5.6.4 Pathway Dose Factors, R, AGE GROUP: ADULT PATHWAY: GRASS-COW-MEAT ORGAN DOSE FACTORS; m 2 - mrem/year per 1pCi/sec NUCLIDE LIVER T--D-THROD -KDNY-UN-G-LL-

_____ _ _ _ BONE -_ -LIVER T.BODY -- THYROID - KIDNEY _ -LUNG- . GI-LLI--

H-3 0.OOE+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.OOE+00 0.OOE+00 7.04E+03 4.21E+03 1.55E+03 9.35E+03 1.77E+06 MN-54 O.OOE+00 9.18E+06 1.75E+06 0.OOE+00 2.73E+06 0.OOE+00 2.81E+07 FE-55 2.93E+08 2.03E+08 4.73E+07 O.OOE+00 O.OOE+00 1.13E+08 1.16E+08 FE-59 2.66E+08 6.25E+08 2.39E+08 0.OOE+00 O.OOE+00 1.75E+08 2.08E+09 CO-58 0.OOE+00 1.82E+07 4.09E+07 0.OOE+00 O.OOE+00 O.OOE+00 3.70E+08 CO-60 O.OOE+00 7.52E+07 1.66E+08 0.OOE+00 O.OOE+00 O.OOE+00 1.41E+09 NI-63 1.89E+10 1.31E+09 6.33E+08 0.OOE+00 0.OOE+00 0.OOE+00 2.73E+08 ZN-65 3.56E+08 1.13E+09 5.12E+08 0.00E+00 7.57E+08 O.OOE+00 7.13E+08 RB-86 O.OOE+00 4.87E+08 2.27E+08 0.00E+00 0.OOE+00 0.OOE+00 9.59E+07 SR-89 3.02E+08 0.OOE+00 8.66E+06 0.00E+00 0.OOE+00 0.OOE+00 4.84E+07 SR-90 1.24E+10 0.OOE+00 3.05E+09 0.00E+00 0.OOE+00 0.OOE+00 3.60E+08 O.OOE+00 Y-91 1.13E+06 0.OOE+00 3.03E+04 0.OOE+00 O.OOE+00 O.OOE+00 6.24E+08 ZR-95 1.87E+06 6.01E+05 4.07E+05 9.43E+05 0.OOE+00 1.90E+09 O.OOE+00 NB-95 2.30E+06 1.28E+06 6.87E+05 0.OOE+00 1.26E+06 0.OOE+00 7.76E+09 RU-103 1.05E+08 0.OOE+00 4.53E+07 0.OOE+00 4.02E+08 O.OOE+00 1.23E+10 RU-1 06 2.80E+09 0.OOE+00 3.54E+08 5.41 E+09 O.OOE+00 1.81E+11 0.OOE+00 AG-110M 6.68E+06 6.18E+06 3.67E+06 1.22E+07 O.OOE+00 2.52E+09 TE-1 25M 3.59E+08 1.30E+08 4.81 E+07 1.08E+08 1.46E+09 O.OOE+00 1.43E+09 TE-1 27M 1.12E+09 3.99E+08 1.36E+08 2.85E+08 4.53E+09 0.OOE+00 3.74E+09 TE-1 29M 1.13E+09 4.23E+08 1.79E+08 3.89E+08 4.73E+09 0.OOE+00 5.71E+09 1-131 1.08E+07 1.54E+07 8.82E+06 5.04E+09 2.64E+07 0.OOE+00 4.06E+06 1-133 3.68E-01 6.41 E-01 1.95E-01 9.42E+01 1.12E+00 0.OOE+00 5.76E-01 O.OOE+00 CS-1 34 6.58E+08 1.57E+09 1.28E+09 0.OOE+00 5.07E+08 1.68E+08 2.74E+07 CS-1 36 1.21E+07 4.78E+07 3.44E+07 0.OOE+00 2.66E+07 3.65E+06 5.43E+06 CS-1 37 8.72E+08 1.19E+09 7.82E+08 4.05E+08 1.35E+08 2.31E+07 0.OOE+00 BA-140 2.90E+07 3.64E+04 1.90E+06 0.08E+08 1.24E+04 2.08E+04 5.96E+07 CE-141 1.41E+04 9.51 E+03 1.08E+03 2.85E+08 4.42E+03 O.OOE+00 3.64E+07 CE-144 1.46E+06 6.1OE+05 7.83E+04 3.62E+05 0.OOE+00 4.93E+08 PR-143 2.09E+04 8.40E+03 1.04E+03 O.OOE+00 4.85E+03 0.OOE+00 9.17E+07 ND-147 7.08E+03 8.18E+03 4.90E+02 0.OOE+00 4.78E+03 O.OOE+00 3.93E+07

CY-TM-170-300 Revision 3 Page 161 of 209 TABLE 5.7.1 Pathway Dose Factors, R, AGE GROUP: INFANT PATHWAY: VEGETATION NUCLIDE [ -BONE LIVER T.BODY 2

ORGAN DOSE FACTORS; m - mrem/year per jiCi/sec THYROID KIDNEY LUNG GI-LLI H-3 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 C-14 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 CR-51 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 MN-54 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 FE-55 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 FE-59 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 CO-58 O.OOE+00 O.00E+O0 O.OOE+O0 O.OOE+OO 000OE+0O 0.OOE+00O O.OOE+OO O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+O0 CO-60 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 NI-63 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 ZN-65 RB-86 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 O.OE+00 SR-89 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 SR-90 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.0OE+00 Y-91 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 ZR-95 NB-95 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.00E+OO O.OOE+OO RU-1 0 3 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+OO O.OOE+OO RU-1 OE3 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.00E+OO O.OOE+OO O.OOE+00 O.OOE+00 AG-110M O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 TE-125M O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 TE-127M O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 TE-129M O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 000OE+00 O.OOE+00 O.OOE+00 1-131 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1-133 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 CS-1 34 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 CS-1 36 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 CS-1 37 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 BA-140 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 CE-141 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 CE-144 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 000OE+00 PR-1 43 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 ND-147 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OE+00 O.OOE+00

CY-TM-1 70-300 Revision 3 Page 162 of 209 TABLE 5.7.2 Pathway Dose Factors, R, AGE GROUP: CHILD PATHWAY: VEGETATION NUCLIDE ORGAN DOSE LIVER FACTORS; m 2 - mrem/year per pCi/sec T-BD-THROD DNY-UN----

___-____ _ BONE -_ -LIVER T.BODY- -THYROID- -KIDNEY _ -LUNG- . -GI-LLI-- -

H-3 0.OOE+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 O.OOE+00 O.OOE+00 1.17E+05 6.49E+04 1.77E+04 1.18E+05 6.20E+06 MN-54 0.OOE+00 6.65E+08 1.77E+08 0.OOE+00 1.86E+08 0.0OE+00 5.58E+08 FE-55 8.01E+08 4.25E+08 1.32E+08 0.OOE+00 0.00E+00 2.40E+08 7.87E+07 FE-59 3.98E+08 6.44E+08 3.21E+08 0.00E+00 O.OOE+00 1.87E+08 6.71E+08 CO-58 0.OOE+00 6.44E+07 1.97E+08 0.00E+00 0.OOE+00 O.OOE+00 3.76E+08 CO-60 0.OOE+00 3.78E+08 1.12E+09 0.00E+00 0.OOE+00 0.OOE+00 2.10E+09 NI-63 3.95E+10 2.11E+09 1.34E+09 O.00E+00 0.OOE+00 0.OOE+00 1.42E+08 ZN-65 8.12E+08 2.16E+09 1.35E+09 O.OOE+00 1.36E+09 O.OOE+00 3.80E+08 RB-86 O.OOE+00 4.51E+08 2.77E+08 0.00E+00 0.OOE+00 0.OOE+00 2.90E+07 SR-89 3.60E+10 0.00E+00 1.03E+09 O.OOE+00 0.OOE+00 O.OOE+00 1.39E+09 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+00 0.00E+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 0.00E+O0 2.96E+08 RU-103 1.53E+07 0.OOE+00 5.90E+06 0.00E+00 3.86E+07 0.00E+00 3.97E+08 RU-106 7.45E+08 0.00E+00 9.30E+07 0.00E+O0 1.01 E+09 0.OOE--00 1.16E+10 AG-110M 3.21 E+07 2.17E+07 1.73E+07 O.OOE+00 4.04E+07 0.OOE+00 2.58E+09 TE-1 25M 3.51 E+08 9.50E+07 4.67E+07 9.84E+07 0.OOE+00 0.OOE+00 3.38E+08 TE-1 27M 1.32E+09 3.56E+08 1.57E+08 3.16E+08 3.77E+09 0.OOE+00 1.07E+09 TE- 29M 8.40E+08 2.35E+08 1.30E+08 2.71E+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 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 1.21E+08 1.81E+07 8.OOE+06 CS-1 37 2.39E+1 0 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.OOE+00 2.21E+07 0.OOE+00 1.04E+10 PR-143 1.45E+05 4.36E+04 7.21E+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

CY-TM-170-300 Revision 3 Page 163 of 209 TABLE 5.7.3 Pathway Dose Factors, R, AGE GROUP: TEEN PATHWAY: VEGETATION NUCLIDE ORGAN DOSE FACTORS; m2 - mrem/year per pCi/sec

-BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI H-3 0.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 0.OOE+00 0.OOE+00 6.16E+04 3.42E+04 1.35E+04 8.79E+04 1.03E+07 MN-54 0.OOE+00 4.54E+08 9.01E+07 0.00E+00 1.36E+08 0.OOE+00 9.32E+08 FE-55 3.26E+08 2.31 E+08 5.39E+07 0.OOE+00 0.OOE+00 1.47E+08 1.OOE+08 FE-59 1.80E+08 4.19E+08 1.62E+08 0.OOE+00 0.OOE+00 1.32E+08 9.91E+08 CO-58 0.OOE+00 4.36E+07 1.01E+08 0.00E+00 0.OOE+00 0.OOE+00 6.01E+08 CO-60 0.OOE+00 2.49E+08 5.60E+08 0.00E+00 0.OOE+00 0.OOE+00 3.24E+09 NI-63 1.61 E+10 1.13E+09 5.45E+08 0.OOE+00 0.OOE+00 0.OOE+00 1.81E+08 ZN-65 4.24E+08 1.47E+09 6.86E+08 0.00E+00 9.42E+08 0.OOE+00 6.23E+08 RB-86 O.OOE+00 2.73E+08 1.28E+08 0.00E+00 0.OOE+00 0.OOE+00 4.04E+07 SR-89 1.52E+10 0.00E+00 4.34E+08 0.OOE+00 0.OOE+00 0.00E+00 1.80E+09 SR-90 7.51E+i1 O.OOE+00 1.85E+l1 0.OOE+00 0.OOE+00 0.OOE+00 2.11E+10 Y-91 7.84E+06 0.OOE+00 2.10E+05 0.OOE+00 0.OOE+00 0.OOE+00 3.22E+09 ZR-95 1.72E+06 5.43E+05 3.73E+05 0.OOE+00 7.98E+05 0.OOE+00 1.25E+09 NB-95 1.92E+05 1.07E+05 5.87E+04 0.OOE+00 1.03E+05 0.00E+00 4.56E+08 RU-103 6.82E+06 0.OOE+00 2.92E+06 0.OOE+00 2.41E+07 0.00E+00 5.70E+08 RU-106 3.09E+08 O.OOE+00 3.90E+07 0.OOE+00 5.97E+08 O.OOE+00 1.48E+10 AG-110M 1.52E+07 1.43E+07 8.72E+06 0.OOE+00 2.74E+07 O.OOE+00 4.03E+09 TE-1 25M 1.48E+08 5.34E+07 1.98E+07 4.14E+07 0.OOE+00 0.OOE+00 4.37E+08 TE-1 27M 5.52E+08 1.96E+08 6.56E+07 1.31E+08 2.24E+09 0.OOE+00 1.37E+09 5.72E+07 TE-129M 3.61 E+08 1.34E+08 5.78E+07 1.17E+08 1.51E+09 0.OOE+00 1.36E+09 1-131 7.69E+07 1.08E+08 3.14E+10 1.85E+08 0.OOE+00 2.13E+07 1-133 1.94E+06 3.29E+06 1.OOE+06 4.59E+08 5.77E+06 0.OOE+00 2.49E+06 CS-1 34 7.1OE+09 1.67E+10 7.75E+09 0.OOE+00 5.31E+09 2.03E+09 2.08E+08 CS-1 36 4.39E+07 1.73E+08 1.16E+08 0.OOE+00 9.41E+07 1.48E+07 1.39E+07 CS-1 37 1.01E+10 1.35E+10 4.69E+09 0.OOE+00 4.59E+09 1.78E+09 1.92E+08 BA-140 1.39E+08 1.71E+05 8.97E+06 O.OOE+00 5.78E+04 1.15E+05 2.15E+08 CE-141 2.83E+05 1.89E+05 2.17E+04 0.OOE+00 8.90E+04 0.OOE+00 5.41E+08 CE-144 5.28E+07 2.18E+07 2.83E+06 0.OOE+00 1.30E+07 0.OOE+00 1.33E+10 PR-143 6.99E+04 2.79E+04 3.48E+03 0.OOE+00 1.62E+04 O.OOE+00 2.30E+08 ND-147 3.62E+04 3.94E+04 2.36E+03 0.OOE+00 2.31E+04 0.OOE+00 1.42E+08

CY-TM-1 70-300 Revision 3 Page 164 of 209 TABLE 5.7.4 Pathway Dose Factors, R, AGE GROUP: ADULT PATHWAY: VEGETATION NORGAN DOSE FACTORS; M2 - mrem/year per pCi/sec NUCLIDE jBONE ORGAN DOSE LIVER FACTORS T.BODY THYROID --- DEY p p-G/sec m KIDNEY LUNG GI-LLI H-3 0.OOE+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.OOE+00 0.OOE+00 4.64E+04 2.77E+04 1.02E+04 6.15E+04 1.17E+07 MN-54 0.OOE+00 3.13E+08 5.97E+07 0.OOE+00 9.31E+07 0.OOE+00 9.58E+08 FE-55 2.1OE+08 1.45E+08 3.38E+07 0.OOE+00 0.OOE+00 8.08E+07 8.31E+07 FE-59 1.26E+08 2.97E+08 1.14E+08 0.OOE+00 0.OOE+00 8.29E+07 9.89E+08 CO-58 0.OOE+00 3.07E+07 6.89E+07 0.OOE+00 0.OOE+00 0.OOE+00 6.23E+08 CO-60 0.OOE+00 1.67E+08 3.69E+08 0.OOE+00 0.OOE+00 0.OOE+00 3.14E+09 NI-63 1.04E+10 7.21 E+08 3.49E+08 0.OOE+00 0.OOE+00 0.OOE+00 1.50E+08

OE+-O ZN-65 3.17E+08 1.01E+09 4.56E+08 6.75E+08 0.OOE+00 6.36E+08 0.OOE+00 0.OOE+00 0.OOE+00 4.32E+07 RB-86 O.OOE+00 2.19E+08 1.02E+08 0.OOE+00 SR-89 9.98E+09 0.OOE+00 2.86E+08 0.OOE+00 0.OOE+00 1.60E+09 0.OOE+0O SR-90 6.05E+1 1 0.OOE+00 1.48E+11 ----- E+-- 0.OOE+00 0.OOE+00 1.75E+10 Y-91 5.12E+06 O.OOE+00 1.37E+05 0.OOE+00 0.OOE+00 0.OOE+00 2.82E+09 ZR-95 1.17E+06 3.77E+05 2.55E+05 5.91E+05 0.OOE+00 1.19E+09 0.OOE+00 NB-95 1.42E+05 7.92E+04 4.26E+04 O.OOE+00 7.83E+04 0.OOE+00 4.81E+08 RU-1 03 4.77E+06 0.OOE+00 2.06E+06 0.OOE+O0 1.82E+07 0.OOE+00 5.57E+08 RU-1 06 1.93E+08 0.OOE+00 2.44E+07 3.72E+08 0.OOE+00 1.25E+10 O.OOE+00 AG-110M 1.05E+07 9.75E+06 5.79E+06 1.92E+07 0.OOE+00 3.98E+09 TE-125M 9.66E+07 3.50E+07 1.29E+07 2.90E+07 3.93E+08 0.OOE+00 3.86E+08 TE-127M 3.49E+08 1.25E+08 4.26E+07 8.93E+07 1.42E+09 0.OOE+00 1.17E+09 TE-129M 2.51E+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 0.OOE+00 3.05E+07 1-133 2.09E+06 3.63E+06 1.11E+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.OOE+00 9.41E+07 1.29E+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 1.51E+04 0.OOE+00 6.20E+04 O.OOE+00 5.1OE+08 CE-144 3.29E+07 1.38E+07 1.77E+06 0.OOE+00 8.16E+06 0.OOE+00 1.11E+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 2.31E+03 O.OOE+00 2.25E+04 0.OOE+00 1.85E+08

CY-TM-1 70-300 Revision 3 Page 165 of 209 6.0 TMI-1 GASEOUS EFFLUENT 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 of the TMI-1 Gaseous Radwaste Treatment System 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.

CY-TM-1 70-300 Revision 3 Page 166 of 209 FIGURE 6.1 Waste Gas System

&SaUMi KACIU &MO U.-

CY-TM-1 70-300 Revision 3 Page 167 of 209 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 monitors.

CY-TM-1 70-300 Revision 3 Page 168 of 209 8.0 TMINS RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) 8.1 Monitoring Program Requirements 8.1.1 Controls In accordance with the TMI-1 Tech. Specs. and TMI-2 PDMS Tech.

Specs., the radiological environmental monitoring program shall be conducted as specified in Table 8.1.

8.1.2 Applicability At all times.

8.1.3 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 Table 8.2 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days from the end of the affected calendar quarter, a special report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose to a member of the public is less than the calendar year limits of 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) + >_1.0 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 The methodology and parameters used to estimate the potential annual dose to a member of the public shall be indicated in this report.

CY-TM-1 70-300 Revision 3 Page 169 of 209 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 II, 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; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report.

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

CY-TM-170-300 Revision 3 Page 170 of 209 to the requirements of Table 8.1 and the detection capabilities required by Table 8.3.

CY-TM-1 70-300 Revision 3 Page 171 of 209 8.2 Land Use Census 8.2.1 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.

8.2.2 Applicability At all times.

8.2.3 Action

a. With a Land Use Census identifying a location(s) that yields a calculated dose or dose commitment greater than the values currently being calculated in 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.

CY-TM-1 70-300 Revision 3 Page 172 of 209 8.2.4 Bases This Control is provided to ensure that changes in the use of unrestricted areas are identified and modifications to the monitoring program are made if required by the results of this census. The best information from the door-to-door survey, aerial surveys, or consulting with local agricultural 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.

CY-TM-1 70-300 Revision 3 Page 173 of 209 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 those samples and analyses which are required by Table 8.1 shall be performed.

8.3.2 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 performed 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.

8.3.5 Surveillance Requirements A summary of the Interlaboratory Comparison Program results shall be included in the Annual Radiological Environmental Operating Report.

CY-TM-1 70-300 Revision 3 Page 174 of 209 TABLE 8.1 Sample Collection and Analysis Requirements Number of Samples Exposure Pathway and Sampling and Type and Frequency and/or Sample Samle Locationsa Collection Frequencyb of Analysis

1. Airborne 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:

Three of these samples by dust loading. Analyze for gross beta should be close to the Site radioactivity following filter Boundary, in different changed. Perform gamma sectors, of the highest isotopic analysise on calculated annual average composite (by location) ground level D/Q. sample quarterly.

One of the samples should be from the vicinity of a community having the highest calculated annual average ground level D/Q.

And one sample should be from a control location 15 to 30 km distant in a less prevalent wind direction.

CY-TM-170-300 Revision 3 Page 175 of 209 TABLE 8.1 (Cont'd)

Sample Collection and Analysis Requirements Number of Samples Exposure Pathway and Sampling and Type and Frequency Locationsa Collection Frequencyb of Analysisb and/or Sample Sample

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).

Placed as follows:

An inner ring of stations, one in each meteorological sector in the general area of the site boundary; An outer ring of stations, one in each meteorological sector in the 6 to 8 km from the site; and the balance of the stations to be placed in special interest areas such as population centers, nearby residences, schools, and in at least one or two areas to serve as control stations.

CY-TM-170-300 Revision 3 Page 176 of 209 TABLE 8.1 (Cont'd)

Sample Collection and Analysis Requirements Number of Samples Exposure Pathway and Sampling and Type and Frequency and/or Sample Sample Locationsa Collection Frequencyb of Analysisb

3. Waterborne

a. Surfacef Samples from 2 locations Composite' sample over Perform gamma isotopic from Table 8.6. 1 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 analysise monthly. Perform Sr-90

1 sample at the location analysis if gross beta of of the nearest water monthly composite >10 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.

1from Table 8.7. 1 1

CY-TM-1 70-300 Revision 3 Page 177 of 209 TABLE 8.1 (Cont'd)

Sample Collection and Analysis Requirements Number of Samples Exposure Pathway and Sampling and Typeofand Frequency Analysisb and/or Sample Sample Locationsa Collection Frequencyb

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.

Samples should be from Composite for Sr-90 milking animals in three analysis quarterly.

locations within 5 km distance having the highest dose potential. If there are none, then one sample from milking animals in each of three areas between 5 to 8 km distant where doses are calculated to be greater than 1 mrem per year.

One sample from milking animals at a control location 15 to 30 km distant in a less prevalent wind direction.

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.

CY-TM-1 70-300 Revision 3 Page 178 of 209 TABLE 8.1 (Cont'd)

Sample Collection and Analysis Requirements Number of Samples Exposure Pathway and Sampling and Type and Frequency and/or Sample Sample Locationsa Collection Frequencyb of Analysisb

4. Ingestion (contd)

c. Food Samples from 2 locations Sample at time of harvest. Perform gamma Products from Table 8.10 (when isotopice, and 1-131, available) analysis on edible portions. Sr-90 analysis

1 sample of each principle on green leafy class of food products at a vegetables or vegetation location in the immediate only.

vicinity of the station.

(indicator)

1 sample of same species or group from a location not influenced by the station discharge.

Samples of three different Monthly during growing Perform gamma kinds of broad leaf vegetation season isotopice 1-131 analysis.

grown nearest each of two different offsite locations of highest predicted annual average ground level D/Q if milking sampling is not performed.

One sample of each of the similar broad leaf vegetation grown 15 to 30 km distant in a less prevalent wind direction if milk sampling is not performed.

CY-TM-170-300 Revision 3 Page 179 of 209 TABLE 8.1 (Cont'd)

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 8.3. 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 Radiological 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 dosimeter is considered to be one phosphor; two or more phosphors in a packet are considered as two or more dosimeters. Film badges shall not be used as dosimeters for measuring direct radiation.

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 sample(s) is greater than ten times the calendar year mean of control samples, Sr-90 and gamma isotopic analysis shall be performed on the individual sample(s).

e. Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility.

f. The "upstream sample" shall be taken at a distance beyond significant influence of the discharge. The "downstream sample" shall be taken in an area beyond but near the mixing zone.

g. Composite sample aliquots shall be collected at time intervals that are short (e.g., hourly) relative to the compositing period (e.g., monthly) in order to assure obtaining a representative sample.

CY-TM-1 70-300 Revision 3 Page 180 of 209 TABLE 8.2 Reporting Levels for Radioactivity Concentrations in Environmental Samples Airborne Particulate 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.

CY-TM-1 70-300 Revision 3 Page 181 of 209 TABLE 8.3 Detection Capabilities for Environmental Sample Analysisa Lower Limit of Detection (LLD)b'c Airborne Particulate Fish Food Sediment Water or Gas (pCi/kg, Milk Products (pCi/kg, Analysis (pCi/L) (pCi/m 3) wet) (pCi/L) (pCi/kgwet) 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

CY-TM-1 70-300 Revision 3 Page 182 of 209 TABLE 8.3 (Cont'd)

Detection Capabilities for Environmental Sample Analysisa Table Notation

a. This list does not mean that only these nuclides are to be considered. Other peaks that are identifiable, which may be related to 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 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 that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.

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

LLD =4.66 Sb E e V e 2.22 9 Y o exp (-XAt)

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),

X is the radioactive decay constant for the particular radionuclide and At for environmental samples is the elapsed time between sample collection, or end of the sample collection period, and time of counting.

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

CY-TM-1 70-300 Revision 3 Page 183 of 209 TABLE 8.3 (Cont'd)

Detection Capabilities for Environmental Sample Analysis' Table Notation It should be recognized that the LLD is defined as an "a priori" (before the fact) limit representing the capability of a measurement system and not as an "a posteriori" (after the fact) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidable small 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.

CY-TM-1 70-300 Revision 3 Page 184 of 209 TABLE 8.4 TMINS REMP Station Locations-Air Particulate and Air Iodine Station Code Distance (miles) Azimuth (0) Map No.

E1-2 0.4 97 8.1 F1 -3 0.6 112 8.1 G2-1 1.4 126 8.2 M2-1 1.3 256 8.2 A3-1 2.7 357 8.2 H3-1 2.2 160 8.2 Q15-1 13.4 309 8.3 TABLE 8.5 TMINS REMP Station Locations-Direct Radiation Station Code Distance (miles) Azimuth (0) Map No.

A1-4 0.3 6 8.1 B1-1 0.6 25 8.1 81-2 0.4 23 8.1 C1-2 0.3 50 8.1 D1-1 0.2 76 8.1 E1-2 0.4 97 8.1 E1-4 0.2 97 8.1 F1-2 0.2 112 8.1 G1-3 0.2 130 8.1 H1-1 0.5 167 8.1 J1-1 0.8 176 8.1 J1-3 0.3 189 8.1 K1-4 0.2 209 8.1 LU-1 0.1 236 8.1 M1-1 0.1 250 8.1 N1-3 0.1 274 8.1 P1-1 0.4 303 8.1 P1-2 0.1 292 8.1

CY-TM-1 70-300 Revision 3 Page 185 of 209 TABLE 8.5 (Cont'd)

TMINS REMP Station Locations-Direct Radiation Station Code Distance (miles) Azimuth (0) Map No.

Q1-2 0.2 321 8.1 0.2 335 8.1 C2-1 1.5 44 8.2 K2-1 1.2 200 8.2 M2-1 1.3 256 8.2 A3-1 2.7 357 8.2 H3-1 2.2 160 8.2 R3-1 2.6 341 8.2 A5-1 4.4 3 8.2 B5-1 4.9 19 8.2 C5-1 4.7 43 8.2 E5-1 4.7 82 8.2 F5-1 4.7 109 8.2 G5-1 4.8 131 8.2 H5-1 4.1 158 8.2 J5-1 4.9 181 8.2 K5-1 4.9 202 8.2 L5-1 4.1 228 8.2 M5-1 4.3 249 8.2 N5-1 5.0 268 8.2 P5-1 5.0 284 8.2 Q5-1 5.0 317 8.2 R5-1 4.9 339 8.2 D6-1 5.2 66 8.3 E7-1 6.7 88 8.3 Q9-1 8.5 310 8.3 B10-1 9.2 21 8.3 G10-1 9.7 128 8.3 G15-1 14.4 126 8.3 J15-1 12.6 183 8.3 Q15-1 13.4 309 8.3

CY-TM-1 70-300 Revision 3 Page 186 of 209 TABLE 8.6 TMINS REMP Station Locations-Surface Water Station Code Distance (miles) Azimuth (0) Map No.

J1-2 (SW) 0.5 188 8.1 A3-2 (SW) 2.7 356 8.2 Q9-1 (DW) 8.5 310 8.3 Q9-1 (SW) 8.5 310 8.3 G15-2 (DW) 13.3 129 8.3 G15-3 (DW) 15.7 124 8.3 (SW) = Surface Water (DW) = Drinking Water TABLE 8.7 TMINS REMP Station Locations-Aquatic Sediment Station Code Distance (miles) Azimuth (0) Map No.

A1-3 0.5 359 8.1 K1-3 0.2 212 8.1 J2-1 1.4 179 8.2

CY-TM-170-300 Revision 3 Page 187 of 209 TABLE 8.8 TMINS REMP Station Locations-Milk Station Code Distance (miles) Azimuth (0) Map No.

E2-2 1.1 96 8.2 F4-1 3.2 104 8.2 G2-1 1.4 126 8.2 P4-1 3.7 295 8.2 K15-3 14.4 205 8.3 TABLE 8.9 TMINS REMP Station Locations-Fish Station Code Station Location IND Downstream of Station Discharge BKG Upstream of Station Discharge TABLE 8.10 TMINS REMP Station Locations-Food Products Station Code Distance (miles) Azimuth (0) Map No.

E1-2 0.4 97 8.1 H11-2 1.0 151 8.1 B10-2 10.0 31 8.3

CY-TM-170-300 Revision 3 Page 188 of 209 MAP 8.1 THREE MILE ISLAND NUCLEAR STATION LOCATIONS OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM STATIONS WITHIN I MILE OF THE SITE MAP 8.1 Three Mile Island Nuclear Station Locations of Radiological Environmental Monitoring Program Stations Within I Mile of the Site

CY-TM-1 70-300 Revision 3 Page 189 of 209 MAP 8.2 THREE MILE ISLAND NUCLEAR STATION LOCATIONS OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM STATIONS WITHIN 5 MILES OF THE SITE MAP 8.2 Three Mile Island Nuclear Station Locations of Radiological Environmental Monitoring Program Stations Within 5 Miles of the Site

CY-TM-170-300 Revision 3 Page 190 of 209 MAP 8.3 THREE MILE ISLAND NUCLEAR STATION LOCATIONS OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM STATIONS GREATER THAN 5 MILES FROM THE SITE MAP 8.3 Three Mile Island Nuclear Station Locations of Radiological Environmental Monitoring Program Stations Greater Than 5 Miles from the Site

CY-TM-1 70-300 Revision 3 Page 191 of 209 9.0 PART III REFERENCES

1. EPRI NP-3840, RP 1560-3 Final Report, "Environmental Radiation Doses From Difficult-To-Measure Nuclides," January 1985

2. "Evaluation of the Three Mile Island Nuclear Station Unit 1 to Demonstrate Conformance to the 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 For A 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

CY-TM-170-300 Revision 3 Page 192 of 209

18. Radiological Assessment Branch Technical Position on Environmental Monitoring, Revision 1, November 1979

19. Title 40, Code of Federal Regulations, "Protection of Environment"

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)

CY-TM-1 70-300 Revision 3 Page 193 of 209 PART IV REPORTING REQUIREMENTS

CY-TM-1 70-300 Revision 3 Page 194 of 209 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 as appropriate, and with previous environmental monitoring reports, and an assessment of the observed impacts of the plant operation on the environment.

The reports shall also include the results of Land Use Censuses required by Part 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 III 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 III, Table 8.3 was not achievable.

A single submittal may be made for the station.

CY-TM-170-300 Revision 3 Page 195 of 209 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., Isa, 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 III Section 8.2.

CY-TM-1 70-300 Revision 3 Page 196 of 209 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.lb and 2.1.2b, and ODCM Part II Control 2.1.2b.

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, wind 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.

CY-TM-1 70-300 Revision 3 Page 197 of 209 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, Ccde 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

CY-TM-1 70-300 Revision 3 Page 198 of 209 APPENDIX A Page 1 of 1 P, - Pathway Dose Rate Parameter P, (inhalation) = k' (BR) DFAI (Eq A-I)

Where:

P, = 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, 1E6 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 adionuclide (mRem/pCi). Values are taken from Table E-10, Reg. Guide 1.109 (Rev. 1), or NUREG-01 72.

Resolution of the units yields: (ODCM Part III Table 4.6)

Pi (inhalation) = 3.7E9 DFA1 (mrem/yr per iiCilm 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.

CY-TM-1 70-300 Revision 3 Page 199 of 209 APPENDIX B Page 1 of 1 R, - Inhalation Pathway Dose Factor R, = k' (BR) (DFAi,a,o) (mrem/yr per microcurie/m 3) (Eq B-i)

Where:

k' = conversion factor, 1E6 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 DFAia,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:

R, = (1.4E9) (DFAi,a,o) infant (ODCM Part III Table 5.2.1)

R, = (3.7E9) (DFAi,a,o) child (ODCM Part II!Table 5.2.2)

Ri = (8.0E9) (DFAi,a,o) teen and adult (ODCM Part III Tables 5.2.3 and 5.2.4)

CY-TM-1 70-300 Revision 3 Page 200 of 209 APPENDIX C Page 1 of I R, - Ground Plane Pathway Dose Factor R, = k' k" (SF) (DFG1 ) [(1 -e "*it)1 ,i] (Eq C-1)

Where:

k' = conversion factor, 1E6 pCi/microcurie k" = conversion factor, 8760 hr/yr

), = decay constant for the ith radionuclide, sec 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 DFG1 = the ground plane dose conversion factor for the ith 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 apply to all age groups.

SF = 0.7, shielding factor, from Table E-15 Reg. Guide 1.109 (Rev. 1)

Reference ODCM Part III Table 5.3.1

CY-TM-1 70-300 Revision 3 Page 201 of 209 APPENDIX D Page 1 of 2

- Grass Cow-Milk Pathway Dose Factor R = k' [(QF X UAP) / (,i + )w)] X (Fm) x(r) x (DFLi,a ,o)x

[((fp x fs)/Yp) + ((I-fp x fs) e Xith)/Ys] E-ýitf (Eq D-1)

Where:

k' = conversion factor, 1E6 picocurie/microcurie (pCi/lpci)

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) 2 Yp = agricultural productivity by unit area of pasture feed grass, 0.7 kg/M (NUREG-0133)

Ys = agricultural productivity by unit area of stored feed, 2.0 kg/mr2 (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)

DFLi,a,o = 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.

ki = decay constant for the ith radionuclide, sec1

= decay constant for weathering, 5.73 x 10-7 sec1 (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), or2 days th = 7.78 x 106 sec, the transport time from pasture to harvest to cow to milk to receptor (Table E-15, Reg. Guide 1.109, Rev. 1), or 90 days 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

CY-TM-1 70-300 Revision 3 Page 202 of 209 APPENDIX D Page 2 of 2 The concentration of tritium in milk is based on the airborne concentration rather than the deposition. Therefore, Ri is based on (X/Q):

RCt,a,o = k'k'" Fm QF UApDFLt,a,o (.75 [.51H]) (Eq D-2)

Where:

k'" = 1E3 grams/kg H = 8 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)

DFLt,a,o = the ingestion dose factor for tritium and organ, o, for each respective age group, a (Tables E-11 to E-14, Reg. Guide 1.109, Rev. 1), or NUREG 0172.

All other parameters and values are as given above.

NOTE: Goat-milk pathway factor, Ri, 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 III Tables 5.4.1 to 5.4.4

CY-TM-1 70-300 Revision 3 Page 203 of 209 APPENDIX E Page 1 of 2 R, - Cow-Meat Pathway Dose Factor R = k' [(QF X UAP) / (Xi1+*w) x(Ff) x (r) x (DFLi,a,o) x

[((fp x f,)/Yp) + ((I-fpfs) e -"ith)/Ys] x E-xitf (Eq E-1)

Where:

k' = conversion factor, 1 E6 picocurie/microcurie (pCi/ýtci)

QF = cow consumption rate, 50 kg/day, (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)

DFLi,a,o = 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.

%i= decay constant for the radionuclide i, sec1 Xw = decay constant for weathering, 5.73 x 10-7 sec1 (NUREG-0133), based on a 14 day half life tf = 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-01 33) 2 Yp = agricultural productivity by unit area of pasture feed grass, 0.7 kg/m (NUREG-0133)

Ys = agricultural productivity by unit area of stored feed, 2.0 kg/M 2 (NUREG-01 33) fp = 1.0, the fraction of the year that the cow is on pasture fs = 1.0, the fraction of the cow feed that is pasture grass while the cow is on pasture

CY-TM-1 70-300 Revision 3 Page 204 of 209 APPENDIX E PAGE 2 OF 2 The concentration of tritium in meat is based on the airborne concentration rather than the deposition. Therefore, Ri is based on (X/Q):

Rta,o = k'k'"Ff QF UAP (DFLt,a,o) x 0.75 x (0.5/H]) (Eq E-2)

Where:

All terms are as defined above and in Appendix D.

Reference:

ODCM Part Ill, Tables 5.6.1 to 5.6.4

CY-TM-1 70-300 Revision 3 Page 205 of 209 APPENDIX F PAGE 1 OF 1 R - Vegetation Pathway Dose Factor R= k' x [r/ (Y, (ki + X,))] x (DFLI,a,o) X [(ULA) fL E'-itL + USA fg E-ith] (Eq F-I)

Where:

k' = 1E6 picocurie/microcurie (pCi/lci) 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 = the average time between harvest of leafy vegetation and its consumption, 8.6 x 104 seconds [Table 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 10 seconds, [Table E-15, Reg. Guide 1.109, Rev. 1 (60 days)]

y, = the vegetation area density, 2.0 kg/mi2 (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, Ri is based on (X/Q)

Rt,a,o = k'k"' [ULA fL + UsA fg] (DFLt,a,o) (.75 [.5/H]) (Eq F-2)

Where:

All terms are as defined above and in Appendix D.

Reference:

ODCM Part III, Tables 5.7.1 to 5.7.4

CY-TM-1 70-300 Revision 3 Page 206 of 209 APPENDIX A-F REFERENCES (Page 1 of 4)

Parameters Used in Dose Factor Calculations Origin of Value Table in Section of SitE-Parameter Value R.G. 1.109 NUREG-0133 Specific For Pi ***

DFA, Each radionuclide E-9 Note 1 3

BR 3700 m /yr (child) E-5

- - For R1 (Vegetation)***

r Each element type E-1 Y, 2.0 kg/mi2 E-1 5 1

xw 5.73 E-7 sec 5.3.1.3 DFLi Each age group and radionuclide E-1 1 thru E-14 Note 1 UaL Each age group E-5 fL 1.0 5.3.1.5 tL 8.6 E + 4 seconds E-15 Uas Each age group E-5 f9 0.76 5.3.1.5 th 5.18 E + 6 seconds E-15 H 8.0 grams/kg 5.2.1.3

- - For R, (inhalation)***

BR Each age group E-5 DFAj Each age group and nuclide E-7 thru E-10 Note 1

CY-TM-1 70-300 Revision 3 Page 207 of 209 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 QF (Goat) 6 kg/day E-3 Ref. Only Uap Each age group E-5 1

xw 5.73 E-7 sec 5.3.1.3 Ff (Both) 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 fp 1.0 5.3.1.3 Note 2

f. 1.0 5.3.1.3 Note 2 Yp 0.7 kg/m 3 E-1 5 th 7.78 E + 6 sec E-15 Yý 2.0 kg/M 2 E-1 5 tf 1.73 E + 6 sec E-15 H 8.0 grams/kg 5.2.1.3

CY-TM-1 70-300 Revision 3 Page 208 of 209 APPENDIX A-F REFERENCES (Page 3 of 4)

Parameters Used in Dose Factor Calculations Origin of Value Parameter Value Table R.G. in 1.109 Section of NUREG-0133 SitE-Specific For R, (Grass/Cow/Milk) ***

Qf 50 kg/day E-3 Uap Each age group E-5

%w 5.73 E-7 sec1 5.3.1.3 Fm Each element E-1 r Each element type E-1 5 DFL1 Each age group and nuclide E-11 thru E-14 Note 1 Yp 0.7 kg/M 2 E-1 5 th 7.78 E + 6 sec E-15 Ys 2.0 kg/M 2 E-1 5 tf 1.73 E + 5 sec E-15 fp 1.0 5.3.1.3

f. 1.0 5.3.1.3 H 8.0 grams/kg 5.2.1.3

CY-TM-1 70-300 Revision 3 Page 209 of 209 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 cannot 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 Facifity Operating License No. DPR-50.

3. NUREG-0133, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," October 1978.

2014 Annual Radioactive Effluent Release Report for TMI - Page I of I Process Control Program for Radioactive Wastes, Revision 10 RW-AA-100 (Revision 10 was issued on April 16, 2014)

1 vJ Exeton Generation,. RW-AA-1 00 Revision 10 Page 1 of 12 Level 3 - Information Use PROCESS CONTROL PROGRAM FOR RADIOACTIVE WASTES

1. PURPOSE 1.1. The purpose of the Process Control Program (PCP) is to:

1.1.1. Establish the process and boundary conditions for the preparation of specific procedures for processing, sampling, analysis, packaging, storage, and shipment of solid radwaste in accordance with local, state, and federal requirements. (CM-1) 1.1.2. Establish parameters which will provide reasonable assurance that all Low Level Radioactive Wastes (LLRW), processed by the in-plant waste process systems on-site OR by on-site vendor supplied waste processing systems, meet the acceptance criteria to a Licensed Burial Facility, as required by 10CFR Part 20, 10CFR Part 61, 10CFR Part 71, 49CFR Parts 171-172, "Technical Position on Waste Form (Revision 1)" [1/91], "Low-Level Waste Licensing Branch Technical Position on Radioactive Waste Classification" [5/83], and the Station Technical Specifications, as applicable.

1.1.3. Provide reasonable assurance that waste placed in "on-site storage" meets the requirements as addressed within the Safety Analysis Reports for the low level radwaste storage facilities for dry and/or processed wet waste.

2. TERMS AND DEFINITIONS 2.1. Process Control Program (PCP): The program which contains the current formulas, sampling, analysis, tests, and determinations to be made to ensure that processing and packaging of solid radioactive waste based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure the waste meets the stabilization criteria specified in 10CFR Parts 20, 61 and 71, state regulations, and burial site requirements.

2.2. Solidification

Liquid waste processed to either an unstable or stable form per 10CFR61 requirements. Waste solidified does not have to meet the 300-year free standing monolith criteria. Approved formulas, samples and tests do not have to meet NRC approval for wastes solidified in a container meeting stability criteria (e.g.

High Integrity Container).

2.3. Stabilization

Liquid waste processed to a "stable state" per 10CFR61 Requirements. Established formulas, samples, and tests shall be approved by the NRC in order to meet solidification "stabilization" criteria. This processing method is currently not available, because the NRC recognizes that waste packed in a High Integrity Container meets the 300-year stabilization criteria. In the event that this processing method becomes an acceptable method, then the NRC shall approve the stabilization formulas, samples, tests, etc.

RW-AA-100 Revision 10 Page 2 of 12 2.4. Solidification Media: An approved media (e.g. Barnwell - vinyl ester styrene, cement, bitumen) when waste containing nuclides with greater than 5-year half lives is solidified in a container with activity greater than 1 micro curie/cc. Waste solidified in a HIC is approved by the commission meeting the 10CFR61 stabilization criteria, including 1% free standing liquids by volume when the waste is packaged to a "stable" form and < 0.5% when waste is packaged to an "unstable" form. The formulas, sampling, analysis, and test do not require NRC approval, because the HIC meets the stability criteria.

2.4.1. Solidification to an unstable or stable state is performed by vendors, when applicable. Liquid waste solidified to meet stabilization criteria (10CFR61 and 01-91 Branch Technical Requirements) shall have documentation available that demonstrates that the process is approved by the NRC or disposal facility.

2.5. Dewatering

The process of removing fluids from liquid waste streams to produce a waste form that meets the requirements of 10CFR Part 61 and applicable burial site criteria, <0.5% by volume when the waste is packaged to an "unstable" state, or

<1% by volume when the waste is packaged to a "stable" form.

2.6. High Integrity Container (HIC): A disposable container that is approved to the Requirements of 10CFR61. The use of HIC's is an alternative to solidification or encapsulation in a steel container to meet burial stability. HIC's are used to package dewatered liquid wastes, (e.g. filter cartridges, filter media, resin, sludges, etc), or dry active waste.

2.7. Liquid Waste Processing Systems: In-plant or vendor supplied processing systems consisting of equipment utilized for evaporation, filtration, demineralization, dewatering, compression dewatering, solidification, or reverse osmosis (RO) for the treatment of liquid wastes (such as Floor Drains, Chemical Drains and Equipment Drain inputs).

2.8. Incineration. RVR, and/or Glass Vitrification of Liquid or Solid: Dry or wet waste processed via incineration and/or thermal processing where the volume is reduced by thermal means meets 10CFR61 requirements.

2.9. Compaction

When dry wastes such as paper, wood, plastic, cardboard, incinerator ash, and etc. are volume reduced through the use of a compactor.

RW-AA-100 Revision 10 Page 3 of 12 2.10. Waste Streams: Consist of but are not limited to

- Filter media (powdered, bead resin and fiber),

- Filter cartridges,

- Pre-coat body feed material,

- Contaminated charcoal,

- Fuel pool activated hardware,

- Oil Dry absorbent material added to a container to absorb liquids

- Fuel Pool Crud

- Sump and tank sludges,

- High activity filter cartridges,

- Concentrated liquids,

- Contaminated waste oil,

- Dried sewage or wastewater plant waste,

- Dry Active Waste (DAW): Waste such as filters, air filters, low activity cartridge filters, paper, wood, glass, plastic, cardboard, hoses, cloth, and metals, etc, which have become contaminated as a consequence of normal operating, housekeeping and maintenance activities.

- Other radioactive waste generated from cleanup of inadvertent contamination.

2.11. Concentration Averaging: Concentration averaging is either: a) the mathematical averaging of waste concentrations, based on the size, geometry, type of radioactive emission, and observed dose rates, or b) the combining of radioactive components in a single container and how their radioactivity may be averaged over the volume of the container. Concentration averaging is subject to constraints identified in the NRC's Branch Technical Position on Concentration Averaging and Encapsulation and may also be constrained by Agreement States or Disposal Facilities.

2.12. Encapsulation: Encapsulation is the surrounding of a radioactive source or component with a nonradioactive material. Encapsulation involves a radioactive core surrounded by a non-radioactive matrix.

2.13. Blending: The intentional mixing of different, but miscible waste streams (such as resins, filter media, etc.) from different batches or systems for the purpose of operational efficiency or ALARA. Blending applies to LLRW streams only. The addition of non-radioactive materials or fillers is not considered blending.

3. RESPONSIBILITIES 3.1. Implementation of this Process Control Program (PCP) is described in procedures at each station and is the responsibility of the each site to implement.

RW-AA-100 Revision 10 Page 4 of 12

4. MAIN BODY 4.1. Process Control Program Requirements 4.1.1. A change to this PCP (Radioactive Waste Treatment Systems) may be made provided that the change is reported as part of the annual radioactive effluent release report, Regulatory Guide 1.21, and is approved by the Plant Operations Review Committee (PORC).

4.1.2. Changes become effective upon acceptance per station requirements.

4.1.3. A solidification media, approved by the burial site, may be REQUIRED when liquid radwaste is solidified to a stable/unstable state.

4.1.4. When processing liquid radwaste to meet solidification stability using a vendor supplied solidification system:

1. If the vendor has its own Quality Assurance (QA) Program, then the vendor shall ADHERE to its own QA Program and shall have SUBMITTED its process system topical report to the NRC or agreement state.

2. If the vendor does not HAVE its own Quality Assurance Program, then the vendor shall ADHERE to an approved Quality Assurance Topical Report standard belonging to the Station or to another approved vendor.

4.1.5. The vendor processing system(s) is/are controlled per the following:

1. A commercial vendor supplied processing system(s) may be USED for the processing of LLRW streams.

2. Vendors that process liquid LLRW at the sites shall MEET applicable Quality Assurance Topical Report and Augmented Quality Requirements.

4.1.6. Vendor processing system(s) operated at the site shall be OPERATED and CONTROLLED in accordance with vendor approved procedures or station procedures based upon vendor approved documents.

4.1.7. All waste streams processed for burial or long term on-site storage shall MEET the waste classification and characteristics specified in 10CFR Part 61.55, Part 61.56, the 5-83 Branch Technical Position for waste classification, and the applicable burial site acceptance criteria (for any burial site operating at the time the waste was processed).

4.1.8. An Exelon Nuclear plant may store waste at another Exelon Nuclear plant, provided formal NRC approval has been RECEIVED for the transfer of waste.

RW-AA-100 Revision 10 Page 5 of 12 4.2. General Waste Processinq Requirements NOTE: On-site resin processing involves tank mixing and settling, transferring to the station or vendor processing system via resin water slurry or vacuuming into approved waste containers, and, when applicable, dewatering for burial.

4.2.1. Vendor resin beds may be USED for decontamination of plant systems, such as, SFP (Spent Fuel Pool), RWCU (reactor water cleanup), and SDC (Shut Down Cooling). These resins are then PROCESSED via the station or vendor processing system.

4.2.2. Various drains and sump discharges will be COLLECTED in tanks or suitable containers for processing treatment. Water from these tanks may be SENT through a filter, demineralizer, concentrator or vendor supplied processing systems.

4.2.3. Process waste (e.g. filter media, sludges, resin, etc) will be periodically DISCHARGED to the station or vendor processing system for onsite waste treatment or PACKAGED in containers for shipment to offsite vendor for volume reduction processing.

4.2.4. Process water (e.g. chemical, floor drain, equipment drain, etc.) may be SENT to either the site waste processing systems or vendor waste processing systems for further filtration, demineralization for plant re-use, or discharge.

4.2.5. All dewatering and solidification/stabilization will be PERFORMED by either utility site personnel or by on-site vendors or will be PACKAGED and SHIPPED to an off-site vendor low-level radwaste processing facility.

4.2.6. Dry Active Waste (DAW) will be HANDLED and PROCESSED per the following:

1. DAW will be COLLECTED and SURVEYED and may be SORTED for compactable and non-compactable wastes.

2. DAW may be packaged in containers to facilitate on-site pre-compaction and/or off-site vendor contract requirements.

3. DAW items may be SURVEYED for release onsite or offsite when applicable.

4. Contaminated filter cartridges will be PLACED into a HIC or will be ENCAPSULATED in an in-situ liner for disposal or SHIPPED to an offsite waste processor in drums, boxes or steel liners per the vendor site criteria for processing and disposal.

RW-AA-100 Revision 10 Page 6 of 12 4.2.7. Filtering devices using pre-coat media may be USED for the removal of suspended solids from liquid waste streams. The pre-coat material or cartridges from these devices may be routinely REMOVED from the filter vessel and discharged to a Filter Sludge Tank or Liner/HIC. Periodically, the filter sludge may be DISCHARGED to the vendor processing system for waste treatment onsite or PACKAGED in containers for shipment to offsite vendor for volume reduction processing.

4.2.8. Activated hardware stored in the Spent Fuel Pools will be PROCESSED periodically using remote handling equipment and may then be PUT into a container for shipment or storage in the pool or loading the processed activated hardware into the Dry Cask storage system.

4.2.9. High Integrity Containers (HIC):

1. For disposal at Barnwell, vendors supplying HIC's to the station shall PROVIDE a copy of the HIC Certificate of Compliance, which details specific limitations on use of the HIC.

2. For disposal at Clive or WCS, vendors supplying HIC's to the station shall PROVIDE a copy of the HIC Certificate of Conformance, which details specific limitations on use of the HIC.

3. Vendors supplying HIC's to the station shall PROVIDE a handling procedure which establishes guidelines for the utilization of the HIC. These guidelines serve to protect the integrity of the HIC and ensure the HIC is handled in accordance with the requirements of the Certificate of Compliance or Certificate of Conformance.

4.2.10. Lubricants and oils contaminated as a consequence of normal operating and maintenance activities may be PROCESSED on-site (by incineration, for oils meeting 10CFR20.2004 and applicable state requirements, or by an approved vendor process) or SHIPPED offsite (for incineration or other acceptable processing method).

4.2.11. Former in-plant systems GE or Stock Drum Transfer Cart and Drum Storage Areas may be USED for higher dose DAW storage at Clinton, Dresden, Quad Cities, Braidwood and Byron.

4.2.12. Certain waste, including flowable solids from holding pond, oily waste separator, cooling tower basin and emergency spray pond, may be disposed of onsite under the provisions of a 10CFR20.2002 permit. Specific requirements associated with the disposal shall be incorporated into station implementing procedures. (CM-2)

RW-AA-100 Revision 10 Page 7 of 12 4.2.13. Concentration averaging may be PERFORMED to combine LLRW having different concentrations of radionuclides to form a homogeneous mixture in accordance with the guidance in the NRC's Branch Technical Position on Concentration Averaging and Encapsulation-1995:

- For homogeneous waste types such as resins and filter media, the concentration of the mixture for classification purposes may be based on either the highest radionuclide concentration in any of the individual waste types contributing to the mixture or the volumetric or weight-averaged nuclide concentrations in the mixture provided that the concentrations of the individual waste type contributors to the mixture are within a factor of 10 of the average concentration of the resulting mixture. (NOTE: a designed collection of homogeneous waste types (from different sources within a facility) is not considered 'mixing' and the concentration for classification purposes may be the average concentration of the combination).

- For non-homogeneous waste types such as activated metals, cartridge filters or components incorporating radioactivity in their design, the concentration should be determined from the total weight or displaced volume (excluding major void spaces) of the component. Mixtures of components in a disposal container is permissible. Concentration averaging of a mixture of components of similar types can be performed in accordance with the NRC's Branch Technical Position on Concentration Averaging and Encapsulation and any State or Disposal Site specific requirements.

4.2.14. Blending may be PERFORMED for routine LLRW such as resins and filter media in accordance with the guidance in the NRC's Branch Technical Position on Concentration Averaging and Encapsulation as further clarified in SECY 2010-0043.

The concentration of the mixture may be determined based on the total activity of all components in the mixture divided by the total volume or mass of the mixture.

Reasonable effort should be made to mix blended LLRW so that activity is evenly distributed.

4.2.15. Encapsulation may be PERFORMED for routine wastes such as filters, filter cartridges, or sealed sources centered in an encapsulated mass, in accordance with the guidance in the NRC's Branch Technical Position on Concentration Averaging and Encapsulation. Classification may be based on the overall volume of the final solidified mass provided that;

- The minimum solidified volume or mass should be reasonably difficult to move by hand.

- The maximum solidified volume or mass used for determining concentration for any single discrete source should be no more than 0.2 m3 or 500Kg (typically 55-gallon drum).

- The maximum amount of gamma-emitting radioactivity or radioactive material is <0.02 mrem/hr on the surface of the encapsulation over a 500-year decay period.

RW-AA-100 Revision 10 Page 8 of 12 The maximum amount of any radionuclide in a single encapsulation, when averaged over the waste and encapsulating media, does not exceed the maximum concentration limits for Class C waste.

Written procedures should be established to ensure that the radiation source(s) is reasonably centered (or distributed) within the encapsulating media.

All other disposal facility requirements for encapsulated material are met.

4.3. Burial Site Requirements 4.3.1. Waste sent directly to burial shall COMPLY with the applicable parts of 49CFR1 71-172, 10CFR61, 10CFR71, and the acceptance criteria for the applicable burial site.

4.4. Shipping and Inspection Requirements 4.4.1. All shipping/storage containers shall be INSPECTED, as required by station procedures, for compliance with applicable requirements (Department of Transportation (DOT), Nuclear Regulatory Commission (NRC), station, on-site storage, and/or burial site requirements) prior to use.

4.4.2. Containers of solidified liquid waste shall be INSPECTED for solidification quality and/or dewatering requirements per the burial site, offsite vendor acceptance, or station acceptance criteria, as applicable.

4.4.3. Shipments sent to an off site processor shall be INSPECTED to ensure that the applicable processor's waste acceptance criteria are being met.

4.4.4. Shipments sent for off site storage shall MEET the storage site's waste acceptance criteria.

4.5. Inspection and Corrective Action 4.5.1. Inspection results that indicate non-compliance with applicable NRC, State, vendor, or site requirements shall be IDENTIFIED and TRACKED through the Corrective Action Program.

4.5.2. Administrative controls for preventing unsatisfactory waste forms from being released for shipment are described in applicable station procedures. If the provisions of the Process Control Program are not satisfied, then SUSPEND shipments of defectively packaged radioactive waste from the site. (CM-1) 4.5.3. If freestanding water or solidification not meeting program requirements is observed, then samples of the particular series of batches shall be TAKEN to determine the cause. Additional samples shall be TAKEN, as warranted, to ensure that no freestanding water is present and solidification requirements are maintained.

RW-AA-100 Revision 10 Page 9 of 12 4.6. Procedure and Process Reviews 4.6.1. The Exelon Nuclear Process Control Program and subsequent changes (other than editorial/minor changes) shall be REVIEWED and APPROVED in accordance with the station procedures, plant-specific Technical Specifications (Tech Spec),

Technical Requirements Manual (T&RM), Operation Requirements Manual (ORM),

as applicable, for the respective station and LS-AA-1 06. Changes to the Licensees Controlled Documents, UFSAR, ORM, or TRM are controlled by the provisions of 10CFR 50.59.

4.6.2. Any changes to the PCP shall be reviewed to determine if reportability is required in the Annual Radiological Effluent Release Report (ARERR). The Radwaste Specialist shall ensure correct information is SUBMITTED to the ODCM program owner prior to submittal of the ARERR.

4.6.3. Procedures shall be IMPLEMENTED as follows:

- Station processes or other vendor waste processing/operating procedures shall be technically reviewed and approved per RM-AA-102-1006.

- Procedures related to waste manifests, shipment inspections, and container activity determinations are CONTROLLED by Radiation Protection Standard Procedures (RP-AA-600 Series).

- Site waste processing IS CONTROLLED by site operating procedures.

- Liquid processed by vendor equipment shall be PERFORMED in accordance with vendor procedures.

- The dewatering procedures implemented by Vendor for the purpose of compliance to the Process Control Program SHALL BE REVIEWED and APPROVED in accordance with the plant specific TRM or ORM (either Current Technical Specifications (CTS) or Improved Technical Specifications (ITS), as applicable for the respective stations).

4.7. Waste Types, Point of Generation, and Processing Method Methods of processing and individual vendors may CHANGE due to changing financial and regulatory options. The table below is a representative sample. It is not intended be all encompassing.

RW-AA-100 Revision 10 Page 10 of 12 AVAILABLE WASTE POEING ME WASTE STREAM POINTS OF GENERATION PROCESSING METHODS Bead Resin Systems - Fuel Pool, Condensate, Dewatering, solidification to an Reactor Water Cleanup, Blowdown, unstable/stable state Equipment Drain, Chemical and Thermal Processing Volume Control Systems, Floor Drain, Maximum Recycle, Blowdown, Boric Free Release to a Land Fill Acid Recycling System, Vendor Supplied Processing Systems, and Portable Demin System Powdered Resin Systems - (Condensate System, Floor Dewatering, solidification to an Drain/Equipment Drain filtration, Fuel unstable/stable state Pool) Thermal Processing Concentrated Waste Waste generated from Site Solidification to an unstable/stable Evaporators resulting typically from the state Floor Drain and Equipment Drain Thermal Processing Systems Sludge Sedimentation resulting from various Dewatering, solidification to an sumps, condensers, tanks, cooling unstable/stable state tower, emergency spray pond, holding Thermal Processing pond, and oily waste separators Evaporation on-site or at an offsite processor On-site disposal per 10CFR20.2002 permit Filter cartridges Systems - Floor/Equipment Drains, Dewatering, solidification to an Fuel Pool; cartridge filters are typically unstable/stable state generated from clean up activities Processed by a vendor for volume within the fuel pool, torus, etc reduction Dry Active Waste Paper, wood, plastic, rubber, glass, Decon/Sorting for Free Release metal, and etc. resulting from daily Compaction/Super-compaction plant activities Thermal Processing by Incineration or glass vitrification Sorting for Free Release Metal melting to an ingot Contaminated Oil Oil contaminated with radioactive Solidification unstable state materials from any in-plant system. Thermal Processing by Incineration Free Release for recycling Drying Bed Sludge Sewage Treatment and Waste Water Free release to a landfill or burial Treatment Facilities Metals See DAW See DAW Irradiated Hardware Fuel Pool, Reactor Components Volume Reduction for packaging efficiencies

RW-AA-100 Revision 10 Page 11 of 12

5. DOCUMENTATION 5.1. Records of reviews performed shall be retained for the duration of the unit operating license. This documentation shall contain:

1. Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change, and

2. A determination which documents that the change will maintain the overall conformance of waste products to Federal (10CFR61 and the Branch Technical Position), State, or other applicable requirements, including applicable burial site criteria.

6. REFERENCES 6.1. Technical Specifications:

6.1.1. The details contained in Current Tech Specs (CTS) or Improved Technical Specifications (ITS), as applicable, in regard to the Process Control Program (PCP),

are to be relocated to the Licensee Controlled Documents. Some facilities have elected to relocate these details into the Operational Requirements Manual (ORM).

Relocation of the description of the PCP from the CTS or ITS does not affect the safe operation of the facility. Therefore, the relocation details are not required to be in the CTS or the ITS to provide adequate protection of the public health and safety.

6.2. Writers'

References:

6.2.1. Code of Federal Regulations: 10 CFR Part 20, Part 61, Part 71, 49 CFR Parts 171-172 6.2.2. Low Level Waste Licensing Branch Technical Position on Radioactive Waste Classification, May 1983 6.2.3. Technical Position on Waste Form (Revision 1), January 1991 6.2.4. USNRC Branch Technical Position on Concentration Averaging and Encapsulation, January 1995 6.2.5. 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 6.2.6. I.E. Circular 80.18, 10CFR 50.59 Safety Evaluation for Changes to Radioactive Waste Treatment Systems 6.2.7. Amendment No. 202 to Facility Operating License No. NPF-1 1 and Amendment No.

189 to Facility Operating License (FOL) No. NPF-18 for the LaSalle County Station (LSCS), Units 1 and 2

RW-AA-100 Revision 10 Page 12 of 12 6.2.8. NRC Branch Technical Position on Blending of Low-Level Radioactive Waste, SECY-10-0043 6.3. Users'

References:

6.3.1. Quality Assurance Program (QATR) 6.3.2. LS-AA-1 06, Plant Operations Review Committee 6.3.3. RM-AA-102-1006, Processing Vendor Documents 6.3.4. RP-AA-600 Series, Radioactive Material/Waste Shipments 6.3.5. CY-AA-170-2000, Annual Radioactive Effluent Release Report 6.4. Station Commitments:

6.4.1. Peach Bottom CM-1, T03819, Letter from G.A. Hunger, Jr., dated Sept. 29 1994, transmitting TSCR 93-16 (Improved Technical Specifications). (Step 1.1.1,4.5.2) 6.4.2. Limerick CM-2, T03896, 10CFR20.2002 permit granted to Limerick via letter dated July 10, 1996. (Step 4.2.12)

7. ATTACHMENTS - None

TMI-15-052, ODCM Change for TMI, Offsite Dose Calculation Manual, Revision 3, CY-TM-170-300

Contents

Text

Reference:

Reference:

Reference:

2.2. Solidification

2.3. Stabilization

2.5. Dewatering

2.9. Compaction

References:

References:

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TMI-15-052, ODCM Change for TMI, Offsite Dose Calculation Manual, Revision 3, CY-TM-170-300

Text

Reference:

Reference:

Reference:

2.2. Solidification

2.3. Stabilization

2.5. Dewatering

2.9. Compaction

References:

References:

Navigation menu

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