ML14120A337

CY-TM-170-300, Rev. 3, Offsite Dose Calculation Manual

ML14120A337
Person / Time
Site:	Three Mile Island
Issue date:	04/25/2014
From:	Exelon Generation Co, Exelon Nuclear
To:	NRC/FSME, Office of Nuclear Reactor Regulation
References
CY-TM-170-300, Rev 3
Download: ML14120A337 (225)

Text

CY-TM-1 70-300Exelon. Revision 3Page 1 of 209Nuclear Level 3 -Information UseOFFSITE DOSE CALCULATION MANUAL (ODCM)INTRODUCTION The OFFSITE DOSE CALCULATION MANUAL (ODCM) is a supporting document of theThree Mile Island Nuclear Station (TMI) Unit 1 and Unit 2 PDMS Technical Specifications andimplements TMI radiological effluent controls.

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

In addition, the ODCMdescribes the methodology and parameters to be used in the calculation of off-site doses dueto radioactive liquid and gaseous effluents.

This document also describes the methodology used for calculation of the liquid and gaseous effluent monitoring instrumentation alarm/trip setpoints. 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 specificsample locations used in the REMP.The ODCM is maintained at the Three Mile Island (TMI) site for use as a reference guide andtraining 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 inaccordance 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 moreworkable 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 acomputerized system used to determine TMI effluent releases and to update cumulative effluent doses.This procedure replaces 6610-PLN-4200.01.

CY-TM-1 70-300Revision 3Page 2 of 209TABLE OF CONTENTSPART I TMI-1 RADIOLOGICAL EFFLUENT CONTROLSSection Page1.0 DEFINITIONS 13Table 1-1, Frequency Notation 18Map1.1, Gaseous Effluent Release Points and Liquid Effluent Outfall Locations 192.0 RADIOLOGICAL EFFLUENT CONTROLS AND BASES 202.1 Radioactive Effluent Instrumentation 202.1.1 Radioactive Liquid Effluent Instrumentation 20Table 2.1-1, Radioactive Liquid Effluent Instrumentation 222.1.2 Radioactive Gaseous Process and Effluent Monitoring Instrumentation 23Table 2.1-2, Radioactive Gaseous Process and Effluent Monitoring Instrumentation 242.2 Radioactive Effluent Controls 302.2.1 Liquid Effluent Controls 302.2.2 Gaseous Effluent Controls 342.2.3 Total Radioactive Effluent Controls 413.0 SURVEILLANCES 443.1 Radioactive Effluent Instrumentation 443.1.1 Radioactive Liquid Effluent Instrumentation 44Table 3.1-1, Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements 453.1.2 Radioactive Gaseous Process and Effluent Monitoring Instrumentation 47Table 3.1-2, Radioactive Gaseous Process and Effluent Monitoring Instrumentation Surveillance Requirements 48 CY-TM-170-300 Revision 3Page 3 of 209TABLE OF CONTENTS (Cont'd)PART I TMI-1 RADIOLOGICAL EFFLUENT CONTROLSSection Page3.2 Radiological Effluents 533.2.1 Liquid Effluents 53Table 3.2-1, Radioactive Liquid Waste Sampling and Analysis Program 553.2.2 Gaseous Effluents 58Table 3.2-2, Radioactive Gaseous Waste Sampling and Analysis Program 603.2.3 Total Radioactive Effluents 644.0 PART I REFERENCES 65 CY-TM-1 70-300Revision 3Page 4 of 209TABLE OF CONTENTS (Cont'd)PART II TMI-2 RADIOLOGICAL EFFLUENT CONTROLSSection Page1.0 DEFINITIONS 67Table 1.1, Frequency Notation 702.0 CONTROLS AND BASES 712.1 Radioactive Effluent Instrumentation 712.1.1 Radioactive Liquid Effluent Instrumentation 712.1.2 Radioactive Gaseous Process and Effluent Monitoring Instrumentation 71Table 2.1-2, Radioactive Gaseous Process and Effluent Monitoring Instrumentation 732.2 Radioactive Effluent Controls 742.2.1 Liquid Effluent Controls 742.2.2 Gaseous Effluent Controls 782.2.3 Total Radioactive Effluent Controls 853.0 SURVEILLANCES 873.1 Radioactive Effluent Instrumentation 873.1.1 Radioactive Liquid Effluent Instrumentation 873.1.2 Radioactive Gaseous Process and Effluent Monitoring Instrumentation 87Table 3.1-2, Radioactive Gaseous Process and Effluent Monitoring Instrumentation Surveillance Requirements 883.2 Radioactive Effluents 893.2.1 Liquid Effluents 89Table 3.2-1, Radioactive Liquid Waste Sampling and Analysis Program 903.2.2 Gaseous Effluents 91 CY-TM-170-300 Revision 3Page 5 of 209TABLE OF CONTENTS (Cont'd)PART II TMI-2 RADIOLOGICAL EFFLUENT CONTROLSSection PaqeTable 3.2-2, Radioactive Gaseous Waste Sampling and Analysis Program 923.2.3 Total Radioactive Effluents 954.0 PART II REFERENCES 96 CY-TM-170-300 Revision 3Page 6 of 209TABLE OF CONTENTS (Cont'd)PART III EFFLUENT DATA AND CALCULATIONAL METHODOLOGIES Section Pagqe1.0 LIQUID EFFLUENT MONITORS 981.1 TMI-1 and TMI-2 Liquid Radiation Monitor Set Points 981.2 TMI Liquid Effluent Release Points and Liquid Radiation Monitor Data 991.3 Control of Liquid Releases 1012.0 LIQUID EFFLUENT DOSE ASSESSMENT 1062.1 Liquid Effluents

-10 CFR 50 Appendix I 1062.2 TMI Liquid Radwaste System Dose Calcs Once Per Month 1072.3 Alternative Liquid Dose Calculational Methodology 1083.0 TMI LIQUID EFFLUENT WASTE TREATMENT SYSTEM 1133.1 TMI-1 Liquid Effluent Waste Treatment System 1133.2 Operability of the TMI-1 Liquid Effluent Waste Treatment System 1143.3 TMI-2 Liquid Effluent Waste Treatment System 1144.0 GASEOUS EFFLUENT MONITORS 1174.1 TMI-1 Noble Gas Monitor Set Points 1174.2 TMI-1 Particulate and Radioiodine Monitor Set Points 1194.3 TMI-2 Gaseous Radiation Monitor Set Points 1204.4 TMI-1 Gaseous Effluent Release Points and Gaseous Radiation MonitorData 1214.5 TMI-2 Gaseous Effluent Release Points and Gaseous Radiation MonitorData 1234.6 Control of Gaseous Effluent Releases 124 CY-TM-1 70-300Revision 3Page 7 of 209TABLE OF CONTENTS (Cont'd)PART III EFFLUENT DATA AND CALCULATIONAL METHODOLOGIES Section Page5.0 GASEOUS EFFLUENT DOSE ASSESSMENT 1365.1 Gaseous Effluents

-Instantaneous Release Limits 1365.1.1 Noble Gases 1365.1.1.1 Total Body 1365.1.1.2 Skin 1375.1.2 lodines, Tritium and Particulates 1385.2 Gaseous Effluents

-10 CFR 50 Appendix I 1395.2.1 Noble Gases 1395.2.2 lodines, Tritium and Particulates 1405.3 Gaseous Radioactive System Dose Calculations Once per Month 1425.4 Alternative Gaseous Dose Calculational Methodology 1436.0 TMI-1 GASEOUS EFFLUENT WASTE TREATMENT SYSTEM 1656.1 Description of the TMI-1 Gaseous Radwaste Treatment System 1656.2 Operability of the TMI-1 Gaseous Radwaste Treatment System 1657.0 EFFLUENT TOTAL DOSE ASSESSMENT 1678.0 TMINS RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) 1688.1 Monitoring Program Requirements 1688.2 Land Use Census 1718.3 Interlaboratory Comparison Program 1739.0 PART III REFERENCES 191 CY-TM-1 70-300Revision 3Page 8 of 209TABLE OF CONTENTS (Cont'd)EFFLUENT DATA AND CALCULATIONAL METHODOLOGIES PART IIISectionTABLESTable 1.1Table 1.2Table 2.1Table 2.2Table 4.1Table 4.2Table 4.3Table 4.4Table 4.5Table 4.6Table 5.2.1Table 5.2.2Table 5.2.3Table 5.2.4Table 5.3.1Table 5.4.1Table 5.4.2Table 5.4.3Table 5.4.4Table 5.5.1PaqeTMI Liquid Release Point and Liquid Radiation Monitor DataTMI-2 Sump Capacities Liquid Dose Conversion Factors (DCF): DFijBioaccumulation

Factors, BFiTMI-1 Gaseous Release Point and Gaseous Radiation Monitor DataTMI-2 Gaseous Release Point and Gaseous Radiation Monitor DataDose Factors for Noble Gases and Daughters Atmospheric Dispersion Factors for Three Mile Island -Station VentAtmospheric Dispersion Factors for Three Mile Island -Ground ReleaseDose Parameters for Radioiodines and Radioactive Particulate In GaseousEffluents Pathway Dose Factors, Ri -Infant, Inhalation Pathway Dose Factors, Ri -Child, Inhalation Pathway Dose Factors, Ri -Teen, Inhalation Pathway Dose Factors, Ri -Adult, Inhalation Pathway Dose Factors, Ri -All Age Groups, Ground PlanePathway Dose Factors, Ri -Infant, Grass-Cow-Milk Pathway Dose Factors, R -Child, Grass-Cow-Milk Pathway Dose Factors, Ri -Teen, Grass-Cow-Milk Pathway Dose Factors, Ri -Adult, Grass-Cow-Milk Pathway Dose Factors, Ri -Infant, Grass-Goat-Milk 102103109112125126127128129130144145146147148149150151152153 CY-TM-1 70-300Revision 3Page 9 of 209TABLE OF CONTENTS (Cont'd)EFFLUENT DATA AND CALCULATIONAL METHODOLOGIES PART IIISectionTABLESTable 5.5.2Table 5.5.3Table 5.5.4Table 5.6.1Table 5.6.2Table 5.6.3Table 5.6.4Table 5.7.1Table 5.7.2Table 5.7.3Table 5.7.4Table 8.1Table 8.2Table 8.3Table 8.4Table 8.5Table 8.6Table 8.7Table 8.8Table 8.9Table 8.10PaaqePathway Dose Factors, Ri -Child, Grass-Goat-Milk Pathway Dose Factors, Ri -Teen, Grass-Goat-Milk Pathway Dose Factors, Ri -Adult, Grass-Goat-Milk Pathway Dose Factors, Ri -Infant, Grass-Cow-Meat Pathway Dose Factors, Ri -Child, Grass-Cow-Meat Pathway Dose Factors, Ri -Teen, Grass-Cow-Meat Pathway Dose Factors, Ri -Adult, Grass-Cow-Meat Pathway Dose Factors, Ri -Infant, Vegetation Pathway Dose Factors, R1 -Child, Vegetation Pathway Dose Factors, Ri -Teen, Vegetation Pathway Dose Factors, Ri -Adult, Vegetation Sample Collection and Analysis Requirements Reporting Levels for Radioactivity Concentrations in Environmental SamplesDetection Capabilities for Environmental Sample AnalysisTMINS REMP Station Locations

-Air Particulate and Air IodineTMINS REMP Station Locations

-Direct Radiation TMINS REMP Station Locations

-Surface WaterTMINS REMP Station Locations

-Aquatic SedimentTMINS REMP Station Locations

-MilkTMINS REMP Station Locations

-FishTMINS REMP Station Locations

-Food Products154155156157158159160161162163164174180181184184186186187187187 CY-TM-1 70-300Revision 3Page 10 of 209TABLE OF CONTENTS (Cont'd)EFFLUENT DATA AND CALCULATIONAL METHODOLOGIES PART IIISectionMAPSPaqeMAP 8.1 Three Mile Island Nuclear Station Locations of Radiological Environmental Monitoring Program Stations within 1 Mile of the SiteMAP 8.2 Three Mile Island Nuclear Station Locations of Radiological Environmental Monitoring Program Stations within 5 miles of the SiteMAP 8.3 Three Mile Island Nuclear Station Locations of Radiological Environmental Monitoring Program Stations Greater than 5 miles from the Site188189190FIGURESFigure 1.1Figure 1.2Figure 3.1Figure 3.2Figure 4.1Figure 4.2Figure 4.3Figure 4.4Figure 4.5Figure 6.1TMI-1 Liquid Effluent PathwaysTMI-2 Liquid Effluent PathwaysTMI-1 Liquid RadwasteTMI-1 Liquid Waste Evaporators TMI-1 Gaseous Effluent PathwaysTMI-1 Auxiliary and Fuel Handling Buildings Effluent PathwaysTMI-1 Reactor Building Effluent PathwayTMI-1 Condenser Offgas Effluent PathwayTMI-2 Gaseous Effluent Filtration System/Pathways Waste Gas System104105115116131132.133134135166 CY-TM-1 70-300Revision 3Page 11 of 209TABLE OF CONTENTS (Cont'd)PART IV REPORTING REQUIREMENTS Section Page1.0 TMI ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 1942.0 TMI ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1953.0 PART IV REFERENCES 197APPENDICES A. Pathway Dose Rate Parameter (Pi) 198B. Inhalation Pathway Dose Factor (Ri) 199C. Ground Plane Pathway Dose Factor (Ri) 200D. Grass-Cow-Milk Pathway Dose Factor (R1) 201E. Cow-Meat Pathway Dose Factor .(Ri) 203F. Vegetation Pathway Dose Factor (Ri) 205APPENDIX A -F REFERENCES 206 CY-TM-1 70-300Revision 3Page 12 of 209PART ITMI-1 RADIOLOGICAL EFFLUENT CONTROLS CY-TM-170-300 Revision 3Page 13 of 2091.0 DEFINITIONS The following terms are defined for uniform interpretation of these controls andsurveillances.

1.1 Reactor Operating Conditions 1.1.1 Cold ShutdownThe reactor is in the cold shutdown condition when it is subcritical by atleast one percent delta k/k and Tavg is no more than 2000F. Pressure isdefined by Technical Specification 3.1.2.1.1.2 Hot ShutdownThe reactor is in the hot shutdown condition when it is subcritical by atleast one percent delta k/k and Tavg is at or greater than 5250F.1.1.3 Reactor CriticalThe reactor is critical when the neutron chain reaction is self-sustaining and Keff = 1.0.1.1.4 Hot StandbyThe reactor is in the hot standby condition when all of the following conditions exist:a. Tavg is greater than 5250Fb. The reactor is criticalc. Indicated neutron power on the power range channels is lessthan two percent of rated power. Rated power is defined inTechnical Specification Definition 1.1.1.1.5 Power Operation The reactor is in a power operating condition when the indicated neutronpower is above two percent of rated power as indicated on the powerrange channels.

Rated power is defined in Technical Specification Definition 1.1.

CY-TM-1 70-300Revision 3Page 14 of 2091.1.6 Refueling ShutdownThe reactor is in the refueling shutdown condition when, even with allrods removed, the reactor would be subcritical by at least one percentdelta k/k and the coolant temperature at the decay heat removal pumpsuction is no more than 1400F. Pressure is defined by Technical Specification 3.1.2. A refueling shutdown refers to a shutdown toreplace or rearrange all or a portion of the fuel assemblies and/or controlrods.1.1.7 Refueling Operation An operation involving a change in core geometry by manipulation offuel or control rods when the reactor vessel head is removed.1.1.8 Refueling IntervalThe time between normal refuelings of the reactor.

This is defined asonce per 24 months.1.1.9 StartupThe reactor shall be considered in the startup mode when the shutdownmargin is reduced with the intent of going critical.

1.1.10 TaveTave is defined as the arithmetic average of the coolant temperatures inthe hot and cold legs of the loop with the greater number of reactorcoolant pumps operating, if such a distinction of loops can be made.1.1.11 Heatup -Cooldown ModeThe heatup-cooldown mode is the range of reactor coolant temperature greater than 200OF and less than 5250F.1.2 OperableA system, subsystem, train, component or device, shall be OPERABLE or haveOPERABILITY when it is capable of performing it's specified function(s),

andwhen all necessary attendant instrumentation,

controls, electrical power, coolingor seal water, lubrication or other auxiliary equipment that are required for thesystem, subsystem, train, component, or device to perform its function(s),

arealso capable of performing their related support function(s).

1.3 Instrument ChannelAn instrument channel is the combination of sensor, wires, amplifiers, and outputdevices, which are connected for the purpose of measuring the value of a CY-TM-1 70-300Revision 3Page 15 of 209process variable, for the purpose of observation,

control, and/or protection.

Aninstrument channel may be either analog or digital.1.4 Instrumentation Surveillance 1.4.1 Channel TestA CHANNEL TEST shall be the injection of a simulated signal into thechannel as close to the sensor as practical to verify OPERABILITY, including alarm and/or trip functions.

1.4.2 Channel CheckA CHANNEL CHECK shall be the qualitative assessment of channelbehavior during operation by observation.

This determination shallinclude, where possible, comparison of the channel indication and/orstatus with other indications and/or status derived from independent instrumentation channels measuring the same parameter.

1.4.3 Source CheckA SOURCE CHECK shall be the qualitative assessment of channelresponse when the channel sensor is exposed to a radioactive source.1.4.4 Channel Calibration An instrument CHANNEL CALIBRATION is a test, and adjustment (ifnecessary),

to establish that the channel output responds withacceptable range and accuracy to known values of the parameter, whichthe 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 1-131The DOSE EQUIVALENT 1-131 shall be that concentration of 1-131(microcurie/gram),

which alone would produce the same thyroid dose as thequantity and isotopic mixture of 1-131, 1-132, I-133, 1-134, and 1-135 actuallypresent.

The thyroid dose conversion factors used for this calculation shall bethose listed in Table III of TID 14844, "Calculation of Distance Factors for Powerand Test Reactor Sites". [Or in Table E-7 of NRC Regulatory Guide 1.109,Revision 1, October, 1977.]

CY-TM-170-300 Revision 3Page 16 of 2091.6 Offsite Dose Calculation Manual (ODCM)The OFFSITE DOSE CALCULATION MANUAL (ODCM) contains themethodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluent, in the calculation of gaseous andliquid effluent monitoring Alarm/Trip Setpoints,.

and in the conduct of theRadiological 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 theAnnual Radiological Environmental Operating and Annual Radioactive EffluentRelease Reports.1.7 Gaseous Radwaste Treatment The GASEOUS RADWASTE TREATMENT SYSTEM is the system designedand installed to reduce radioactive gaseous effluent by collecting primary coolantsystem off gases from the primary system and providing for delay or holdup forthe purpose of reducing the total radioactivity prior to release to the environment.

1.8 Ventilation Exhaust Treatment SystemA VENTILATION EXHAUST TREATMENT SYSTEM is any system designed andinstalled to reduce gaseous radioiodine or radioactive material in particulate formin effluent by passing ventilation or vent exhaust gases through charcoalabsorbers 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 notconsidered to be VENTILATION EXHAUST TREATMENT SYSTEMS.1.9 Purge -PurgingPURGE or PURGING is the controlled process of discharging air or gas from aconfinement to maintain temperature,

pressure, humidity, concentration or otheroperating conditions in such a manner that replacement air or gas is required topurify the confinement.

1.10 VentingVENTING 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.

Ventused in system name does not imply a VENTING process.1.11 Member(s) of the PublicMEMBER OF THE PUBLIC means any individual except when that individual isreceiving an occupational dose.

CY-TM-170-300 Revision 3Page 17 of 2091.12 Site BoundaryThe SITE BOUNDARY used as the basis for the limits on the release of gaseouseffluents is as defined in Section 2.1.2.2 and shown on Figure 2.1-3 of the TMI-1FSAR. This boundary line includes portions of the Susquehanna River surfacebetween the east bank of the river and Three Mile Island and between Three MileIsland and Shelley Island.The SITE BOUNDARY used as the basis for the limits on the release of liquideffluents is as shown in Figure 1.1 in Part I of this ODCM.1.13 Frequency NotationThe FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1-1. AllSurveillance Requirements shall be performed within the specified time intervalwith 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 DoseOCCUPATIONAL DOSE means the dose received by an individual in the courseof employment in which the individual's assigned duties involve exposure toradiation or to radioactive material from licensed and unlicensed sources ofradiation, 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 toindividuals administered radioactive material and released under 10CFR35.75, from voluntary participation in medical research

programs, or as a member of thepublic.

CY-TM-1 70-300Revision 3Page 18 of 209Table 1-1Frequency NotationNotation Frequency S Shiftly (once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />)D Daily (once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />)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 doneduring the previous 7 daysP Completed prior to each releaseN/A (NA) Not applicable E Once per 18 monthsF Not to exceed 24 monthsBasesSection 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 thatmay not be suitable for conducting the surveillance; e.g., transient conditions or other ongoingsurveillance or maintenance activities.

It also provides flexibility to accommodate the length ofa fuel cycle for surveillances that are specified to be performed at least once eachREFUELING INTERVAL.

It is not intended that this provision be used repeatedly as aconvenience to extend surveillance intervals beyond that specified for surveillances that arenot performed once each REFUELING INTERVAL.

Likewise, it is not the intent thatREFUELING INTERVAL surveillances be performed during power operation unless it isconsistent 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.

Thisprovision is sufficient to ensure that the reliability ensured through surveillance activities is notsignificantly degraded beyond that obtained from the specified surveillance interval.

CY-TM-1 70-300Revision 3Page 19 of 209Map 1.1Gaseous Effluent Release Points and Liquid Effluent Outfall Locations CY-TM-1 70-300Revision 3Page 20 of 2092.0 RADIOLOGICAL EFFLUENT CONTROLS AND BASES2.1 Radioactive Effluent Instrumentation 2.1.1 Radioactive Liquid Effluent Instrumentation CONTROL:The radioactive liquid effluent monitoring instrumentation channelsshown 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.

Thealarm/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 bythe above control, immediately suspend the release ofradioactive liquid effluent monitored by the affected channel ordeclare the channel inoperable.

b. With less than the minimum number of radioactive liquideffluent monitoring instrumentation channels

OPERABLE, take the ACTION shown in Table 2.1 -1. Exert best efforts toreturn the instrumentation to OPERABLE status within 30days and, if unsuccessful, explain in the next Annual EffluentRelease Report why the inoperability was not corrected in atimely manner.For WDL-FT-84, and RM-L-6, operability is notrequired when discharges are positively controlled through the closure of WDL-V-257.

For RM-L-12 and associated IWTS/IWFS flowinterlocks, operability is not required whendischarges are positively controlled through theclosure of IW-V-72, 75 and IW-V-280, 281.For SR-FT-146, operability is not required whendischarges are positively controlled through theclosure of WDL-V-257, IW-V-72, 75 and IW-V-280, 281.

CY-TM-1 70-300Revision 3Page 21 of 209BASESThe radioactive liquid effluent instrumentation is provided to monitor andcontrol, as applicable, the releases of radioactive materials in liquideffluent during actual or potential releases.

The alarm/trip setpoints forthese instruments shall be calculated in accordance with NRC approvedmethods in the ODCM to ensure that the alarm/trip will occur prior toexceeding ten times the effluent concentrations of 10 CFR Part 20.

CY-TM-170-300 Revision 3Page 22 of 209Table 2.1-1Radioactive Liquid Effluent Instrumentation MinimumChannelsOperableInstrument ACTION1. Gross Radioactivity MonitorsProviding Automatic Termination of Releasea. Unit 1 Liquid Radwaste Effluent Line (RM-L6)b. IWTS/IWFS Discharge Line (RM-L12)2. Flow Rate Measurement Devicesa. Unit 1 Liquid Radwaste Effluent Line (WDL-FT-84)

b. Station Effluent Discharge (SR-FT-146) 111820112121Table NotationACTION 18With the number of channels OPERABLE less than required by the MinimumChannels OPERABLE requirement, effluent releases may continue, provided thatprior to initiating a release:1. At least two independent samples are analyzed in accordance withSurveillances 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.With the number of channels OPERABLE less than required by the MinimumChannels OPERABLE requirement, effluent releases via this pathway maycommence or continue provided that grab samples are collected and analyzedfor gross radioactivity (beta or gamma) at a limit of detection of at least lx10-7microcuries/ml, prior to initiating a release and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> duringrelease.With the number of channels OPERABLE less than required by the MinimumChannels OPERABLE requirement, radioactive effluent releases via this pathwaymay continue, provided the flow rate is estimated at least once per 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />sduring actual releases.

Pump curves may be used to estimate flow.ACTION 20ACTION 21 CY-TM-1 70-300Revision 3Page 23 of 2092.1.2 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 withtheir alarm/trip setpoints set to ensure that the limits of Control 2.2.2.1are not exceeded.

The alarm/trip setpoints of these channels shall bedetermined in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM).APPLICABILITY:

As shown in Table 2.1-2ACTION:a. With a radioactive gaseous process or effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above control, immediately suspend therelease of radioactive effluent monitored by the affectedchannel or declare the channel inoperable.

b. With less than the minimum number of radioactive gaseousprocess or effluent monitoring instrumentation channelsOPERABLE, take the ACTION shown in Table 2.1-2. Exertbest efforts to return the instrumentation to OPERABLE statuswithin 30 days and, if unsuccessful, explain in the next AnnualEffluent Release Report why the inoperability was notcorrected in a timely manner.BASESThe radioactive gaseous effluent instrumentation is provided to monitorand control, as applicable, the releases of radioactive materials ingaseous effluent during actual or potential releases.

The alarm/trip setpoints for these instruments shall be calculated in accordance withNRC approved methods in the ODCM to provide reasonable assurance that the annual releases are within the limits specified in 10 CFR20.1301.The low range condenser offgas noble gas activity monitors also providedata for determination of steam generator primary to secondary leakagerate. Channel operability requirements are based on an AmerGen letter#5928-06-20449, "Request to Revise Condenser Vent System LowRange Noble Gas Monitor Operability Requirements",

Pamela B. Cowanto U.S.N.R.C.,

May 25, 2006.

CY-TM-1 70-300Revision 3Page 24 of 209Table 2.1-2Radioactive Gaseous Process and Effluent Monitoring Instrumentation MINIMUMCHANNELINSTRUMENT OPERABLE APPLICABILITY ACTION1. Waste Gas Holdup Systema. Noble Gas Activity Monitor (RM-A-7) 1 25B. Effluent System Flow Rate Measuring Device (WDG-FT-123) 1 2612. Waste Gas Holdup System Explosive Gas Monitoring Systema. Hydrogen Monitor (CA-G-1A/B) 2 ** 30b. Oxygen Monitor (CA-G-1A/B) 2 ** 303. Containment Purge Monitoring Systema. Noble Gas Activity Monitor (RM-A-9) 1 # 27b. Iodine Sampler (RM-A-9) 1 # 31c. Particulate Sampler (RM-A-9) 1 # 31d. Effluent System Flow Rate Measuring Device (AH-FR-148A, AH-FR-148B) 1 # 26e. Sampler Flow Rate Monitor (RM-FI-1231) 1 # 264. Condenser Vent Systema. Low Range Noble Gas Activity Monitor (RM-A-5Lo or RM-A-15) 1## 32 CY-TM-1 70-300Revision 3Page 25 of 209Table 2.1-2 (Cont'd)Radioactive Gaseous Process and Effluent Monitoring Instrumentation MINIMUMCHANNELINSTRUMENT OPERABLE APPLICABILITY ACTION5. Auxiliary and Fuel Handling Building Ventilation Systema. Noble Gas Activity Monitor (RM-A-8) or (RM-A-4 and RM-A-6) 1

• 27b. Iodine Sampler (RM-A-8 or (RM-A-4 and RM-A-6) 1

• 31c. Particulate Sampler (RM-A-8 or (RM-A-4 and RM-A-6) 1

• 31d. Effluent System Flow Rate Measuring Devices (AH-FR-149 and 1

• 26AH-FR-1 50)e. Sampler Flow Rate Monitor (RM-FI-1230 or RM-A-4\FI and RM-A-6\FI) 1 266. Fuel Handling Building ESF Air Treatment Systema. Noble Gas Activity Monitor (RM-A-14 or suitable equivalent) 1 .... 27,33b. Iodine Cartridge N/A(2) .... 31,33c. Particulate Filter N/A(2) .... 31,33d. Effluent System Flow (AH-UR-1 104A/B) 1 .... 26,33e. Sampler Flow Rate Monitor (RM-A-14FI14) 1 26,33NOTE 2: No instrumentation channel is provided.

However, for determining operability, the equipment named must beinstalled and functional or the ACTION applies.

CY-TM-1 70-300Revision 3Page 26 of 209Table 2.1-2 (Cont'd)Radioactive Gaseous Process and Effluent Monitoring Instrumentation MINIMUMCHANNELINSTRUMENT OPERABLE APPLICABILITY ACTION7. Chemical Cleaning Building Ventilation Systema. Noble Gas Activity Monitor (ALC RM-1-18) 1(3) 27b. Iodine Sampler (ALC RM-1-18) 1(3) 31c. Particulate Sampler (ALC RM-1-18) 1 318. Waste Handling and Packaging Facility Ventilation Systema. Particulate Sampler (WHP-RIT-1) 1 319. Respirator and Laundry Maintenance Facility Ventilation Systema. Particulate Sampler (RLM-RM-1) 1 31NOTE 3: Channel only required when liquid radwaste is moved or processed within the facility.

CY-TM-1 70-300Revision 3Page 27 of 209Table 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 whereRM-A-8, AH-FT-149 and AH-FT-150 are operable andRM-A-8 is capable of automatic closure of WDG-V-47During Fuel Handling Building ESF Air Treatment SystemOperation

-# At all times during containment purging-# At all times when condenser vacuum is established

-### During operation of the ventilation systemACTION 25With the number of channels OPERABLE less than required by the MinimumChannels OPERABLE requirement, the contents of the tank may be released tothe environment provided that prior to initiating the release:1. At least two independent samples of the tank's contents are analyzed inaccordance with Table 3.2-2, Item A, and2. 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.With the number of channels OPERABLE less than required by the MinimumChannels OPERABLE requirement, effluent releases via this pathway maycontinue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.With the number of channels OPERABLE less than required by the MinimumChannels OPERABLE requirement, effluent releases via this pathway maycontinue provided grab samples are taken at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and theinitial samples are analyzed for gross activity (gamma scan) within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> afterthe channel has been declared inoperable.

If RM-A-9 is declared inoperable, seealso Technical Specification 3.5.1, Table 3-5.1, Item C.3.f.ACTION 26ACTION 27 CY-TM-1 70-300Revision 3Page 28 of 209Table 2.1-2Notations (Cont'd)ACTION 30 1.With the number of channels OPERABLE less than required by theMinimum Channels OPERABLE requirement, a grab sample shall becollected and analyzed for the inoperable gas channel(s) at least onceper 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. With both channels inoperable, a grab sample shall becollected and analyzed for the inoperable gas channel(s):

ACTION 31ACTION 32(a) at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during degassing operations.

(b) at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> during other operations (e.g. Feedand 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 theNRC Region I Office and a copy to the Director, Office of Inspection andEnforcement within 30 days of declaring the channel(s) inoperable.

Thereport shall describe (a) the cause of the monitor inoperability, (b) actionbeing taken to restore the instrument to service, and (c) action to betaken to prevent recurrence.

With the number of channels OPERABLE less than required by the MinimumChannels OPERABLE requirement, effluent releases via this pathway maycontinue provided that within four hours after the channel has been declaredinoperable, samples are continuously collected with auxiliary samplingequipment.

With the number of channels OPERABLE less than required by the MinimumChannels OPERABLE requirement, effluent releases via this pathway maycontinue 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 anincreasing trend at the initial time when there was no operable channel of theCondenser Vent System Low Range Noble Gas Activity

Monitor, analyze grabsamples of the reactor coolant system and Condenser OffGas once every4 hours to provide an indication of primary-to-secondary leakage.

Subsequent sample frequency shall be in accordance with Table 1 based on the last sampleresult. Otherwise, analyze grab samples of the reactor coolant system andCondenser OffGas to provide an indication of primary-to-secondary leakage atthe minimum frequency indicated in Table 1, below:

CY-TM-170-300 Revision 3Page 29 of 209Table 2.1-2Notations (Cont'd)Table 1Minimum Frequency of Grab Samples When No Condenser Vent System Low RangeNoble Gas Activity Monitor is OperableExisting TotalPrimary-to-Secondary Leak Rate Frequency of Grab Samples(based on last monitor readingor sample result)0 to < 5 GPD Once per 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s5 to < 30 GPD Once per 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />s30 to < 75 GPD Once per 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />s75 GPD or greater Place the unit in at least HOT STANDBY within thenext 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and at least HOT SHUTDOWN withinthe following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and at least COLDSHUTDOWN within the subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.*Unstable is defined as > 10% increase during a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period, as stated in the EPRIGuidelines.

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 Ihour, the provisions of Technical Specification 3.0.1 apply, as if thisControl were a Tech Spec Limiting Condition for Operation.

ACTION 33With the number of channels OPERABLE less than required by the MinimumChannels OPERABLE requirement, either restore the inoperable channel toOPERABLE status within 7 days, or prepare and submit a special report within30 days outlining the action(s) taken, the cause of the inoperability, and plansand schedule for restoring the system to OPERABLE status.

CY-TM-170-300 Revision 3Page 30 of 2092.2 Radioactive Effluent Controls2.2.1 Liquid Effluent Controls2.2.1.1 Liquid Effluent Concentration CONTROL:The concentration of radioactive material released at anytimefrom the unit to unrestricted areas shall be limited to ten timesthe concentrations specified in 10 CFR Part 20.1001-20.2401, Appendix B, Table 2, Column 2 for radionuclides other thandissolved or entrained noble gases. For dissolved orentrained noble gases, the concentration shall be limited to3E-3 uCi/cc total activity.

APPLICABILITY:

At all timesACTION:With the concentration of radioactive material released fromthe unit to unrestricted areas exceeding the above limits,immediately restore concentrations within the above limits.BASESThis control is provided to ensure that the concentration ofradioactive materials released in liquid waste effluent from theunit to unrestricted areas will be less than ten times theconcentration levels specified in 10 CFR Part20.1001-20.2401, 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 inexposures with (1) the Section II.A design objectives ofAppendix 1, 10 CFR Part 50, to a MEMBER OF THE PUBLICand (2) the limits of 10 CFR Part 20.1301 to the population.

The concentration limit for noble gases is based upon theassumption the Xe-1 35 is the controlling radioisotope and itsMPC in air (submersion) was converted to an equivalent concentration in water using the methods described inInternational Commission on Radiological Protection (ICRP)Publication

2.

CY-TM-170-300 Revision 3Page 31 of 2092.2.1.2 Liquid Effluent DoseCONTROLThe dose or dose commitment to a MEMBER OF THEPUBLIC from radioactive materials in liquid effluents releasedfrom the unit to the SITE BOUNDARY shall be limited:a. During any calendar quarter to less than or equal to1.5 mrem to the total body and to less than or equalto 5 mrem to any organ.b. During any calendar year to less than or equal to3 mrem to the total body and to less than or equal to10 mrem to any organ.APPLICABILITY:

At all timesACTION:a. With the calculated dose from the release ofradioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to theNRC Region I Administrator within 30 days, aSpecial Report, which identifies the cause(s) forexceeding the limit(s),

and defines the corrective actions to be taken to reduce the releases ofradioactive materials in liquid effluents during theremainder of the current calendar quarter andduring the subsequent 3 calendar quarters so thatthe cumulative dose or dose commitment to anyindividual from such releases during these fourcalendar quarters is within 3 mrem to the total bodyand 10 mrem to any organ. This Special Reportshall also include (1) the result of radiological analyses of the drinking water source, and (2) theradiological impact on finished drinking watersupplies with regard to the requirements of 40 CFR141, Safe Drinking Water Act.

CY-TM-1 70-300Revision 3Page 32 of 209BASESThis control and associated action is provided to implement the requirements of Sections II.A, Ill.A, and IV.A of Appendix I,10 CFR Part 50. The Control implements the guides set forthin Section II.A of Appendix I. The ACTION statements providethe required operating flexibility and at the same timeimplement the guides set forth in Section IV.A of Appendix I toassure that the releases of radioactive material in liquideffluents will be kept "as low as is reasonably achievable".

Also, for fresh water sites with drinking water supplies whichcan be potentially affected by plant operations, there isreasonable assurance that the operation of the facility will notresult in radionuclide concentrations in the finished drinkingwater that are in excess of the requirements of 10 CFR 20.The dose calculations in the ODCM implement therequirements 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 actualexposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated.

Theequations specified in the ODCM for calculating the doses dueto the actual release rates of radioactive materials in liquideffluents are consistent with the methodology provided inRegulatory Guide 1.109, "Calculation of Annual Doses to Manfrom Routine Releases of Reactor Effluents for the Purpose ofEvaluating 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 ofImplementing Appendix I," April, 1977. NUREG-0133 provides methods for dose calculations consistent withRegulatory Guides 1.109 and 1.113.

CY-TM-170-300 Revision 3Page 33 of 2092.2.1.3 Liquid Radwaste Treatment SystemCONTROL:The appropriate portions of the liquid radwaste treatment system shall be used to reduce the radioactive materials inliquid wastes prior to their discharge when the projected dosesdue to the liquid effluent from the unit to unrestricted areaswould exceed 0.06 mrem to the total body or 0.2 mrem to anyorgan in any calendar month.APPLICABILITY:

At all timesACTION:a. With radioactive liquid waste being discharged without treatment and in excess of the above limits,prepare and submit to the NRC Region IAdministrator within 30 days, a Special Reportwhich includes the following information:

1. Explanation of why liquid radwaste wasbeing discharged without treatment, identification of any inoperable equipment or subsystems, and the reason forinoperability,

2. Action(s) taken to restore the inoperable equipment to OPERABLE status, and,3. A summary description of action(s) takento prevent a recurrence BASESThe requirement that the appropriate portions of this systembe used, when specified, provides assurance that the releasesof radioactive materials in liquid effluents will be kept as low asis reasonably achievable.

This control implements therequirements 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. Theintent of Section ll.D. is to reduce effluents to as low as isreasonably achievable in a cost effective manner. This controlsatisfies this intent by establishing a dose limit which is a smallfraction (25%) of Section II.A of Appendix 1, 10 CFR Part 50dose requirements.

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

CY-TM-1 70-300Revision 3Page 34 of 2092.2.1.4 Liquid Holdup TanksCONTROLThe quantity of radioactive material contained in each of thefollowing tanks shall be limited to less than or equal to 10curies, excluding tritium and dissolved or entrained noblegases.a. Outside temporary tankAPPLICABILITY:

At all times.ACTION:a. With the quantity of radioactive material in any ofthe above listed tanks exceeding the above limit,immediately suspend all additions of radioactive material to the tank and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce thetank contents to within the limit.BASESRestricting the quantity of radioactive material contained in thespecified tanks provides assurance that in the event of anuncontrolled release of the tanks' contents, the resulting concentrations would be less than the limits of 10 CFR Part20.1001-20-20.2401, Appendix B, Table 2, Column 2, at thenearest potable water supply and the nearest surface watersupply in an unrestricted area.2.2.2 Gaseous Effluent Controls2.2.2.1 Gaseous Effluent Dose RateCONTROL:The dose rate due to radioactive materials released ingaseous effluent from the site shall be limited to the following:

a. For noble gases: less than or equal to 500 mrem/yrto the total body and less than or equal to 3000mrem/yr to the skin, andb. For 1-131, 1-133, tritium and all radionuclides inparticulate 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 70-300Revision 3Page 35 of 209ACTION:With the release rate(s) exceeding the above limits,immediately decrease the release rate to comply with theabove limit(s).

BASESThe control implements the requirement in Technical Specification (6.8.4.b (7). This specification is provided toensure that the dose from radioactive materials in gaseouseffluents at and beyond the SITE BOUNDARY will be withinthe annual dose limits of 10 CFR Part 20. The annual doselimits are the doses associated with 10 times theconcentrations of 10 CFR Part 20, Appendix B, Table 2,Column 1. These limits provide reasonable assurance thatradioactive material discharged in gaseous effluents will notresult in the exposure of a MEMBER OF THE PUBLIC, eitherwithin or outside the SITE BOUNDARY, to annual averageconcentrations exceeding the limits specified in Appendix B,Table 2 of 10 CFR Part 20.1302.

For MEMBERS OF THEPUBLIC who may at times be within the SITE BOUNDARY, the occupancy of the MEMBER OF THE PUBLIC will besufficiently low to compensate for any increase in theatmospheric diffusion factor above that for the exclusion areaboundary.

The specified release rate limits restrict, at alltimes, the corresponding gamma and beta dose rates abovebackground to a MEMBER OF THE PUBLIC at or beyond theSITE BOUNDARY to less than or equal to 500 mrem/year tothe total body, or to less than or equal to 3000 mrem/year tothe skin. These release rate limits also restrict, at all times,the corresponding thyroid dose rate above background to achild via the inhalation pathway to less than or equal to 1500mrem/year (NUREG 1301).2.2.2.2 Gaseous Effluents Dose-Noble GasesCONTROL:The air dose due to noble gases released in gaseous effluents from the unit to areas at and beyond the SITE BOUNDARYshall be limited to the following:

a. During any calendar quarter:

less than or equal to 5mrad for gamma radiation and less than or equal to10 mrad for beta radiation

and, CY-TM-1 70-300Revision 3Page 36 of 209b. During any calendar year: less than or equal to 10mrad for gamma radiation and less than or equal to20 mrad for beta radiation.

APPLICABILITY:

At all timesACTION:a. With the calculated air dose from radioactive noblegases in gaseous effluents exceeding any of theabove limits, prepare and submit to the NRC RegionI Administrator within 30 days, a Special Reportwhich identifies the cause(s) for exceeding thelimit(s) and defines the corrective actions that havebeen taken to reduce the releases and the proposedcorrective actions to be taken to assure thatsubsequent releases will be in compliance with theabove limits.BASESThis control applies to the release of radioactive materials ingaseous effluents from TMI-I.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 forthin Section 1l.B of Appendix I. The ACTION statements providethe required operating flexibility and at the same timeimplement the guides set forth in Section IV.A of Appendix I toassure that the releases of radioactive material in gaseouseffluents will be kept "as low as is reasonably achievable."

The Surveillance Requirements implement the requirements inSection III.A of Appendix I that conformance with the guides ofAppendix I be shown by calculational procedures based onmodels and data such that the actual exposure of a MEMBEROF THE PUBLIC through the appropriate pathways is unlikelyto be substantially underestimated.

The dose calculation methodology and parameters established in the ODCM forcalculating the doses due to the actual release rates ofradioactive 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 ofReactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in CY-TM-170-300 Revision 3Page 37 of 209Routine Releases from Light-Water Cooled Reactors",

Revision 1, July 1977. The ODCM equations provided fordetermining the air doses at and beyond the SITEBOUNDARY are based upon the historical averageatmospheric conditions.

NUREG-0133 provides methods fordose calculations consistent with Regulatory Guides 1.109and 1.111.2.2.2.3 Dose -Iodine-131, Iodine-133,

Tritium, and Radionuclides inParticulate FormCONTROL:The dose to a MEMBER OF THE PUBLIC from Iodine-1 31,Iodine-133,

Tritium, and all radionuclides in particulate formwith half-lives greater than 8 days, in gaseous effluents released from the unit to areas at and beyond the SITEBOUNDARY shall be limited to the following:

a. During any calendar quarter:

less than or equal to7.5 mrem to any organ, andb. During any calendar year: less than or equal to 15mrem to any organ.APPLICABILITY:

At all timesACTION:.With the calculated dose from the release of Iodine-131, Iodine-1 33, Tritium, and radionuclides in particulate form withhalf-lives greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and submit to the NRCRegion I Administrator within 30 days, a Special Report whichidentifies the cause(s) for exceeding the limit and defines thecorrective actions that have been taken to reduce the releasesand the proposed corrective actions to be taken to assure thatsubsequent releases will be in compliance with the abovelimits.BASESThis control applies to the release of radioactive materials ingaseous 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-1 70-300Revision 3Page 38 of 209Section II.C of Appendix I. The ACTION statement providesthe required operating flexibility and at the same timeimplements the guides set forth in Section IV.A of Appendix Ito assure that the releases of radioactive materials in gaseouseffluents 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 ofAppendix I that conformance with the guides of Appendix I beshown by calculational procedures based on models and datasuch that the actual exposure of a MEMBER OF THE PUBLICthrough appropriate pathways is unlikely to be substantially underestimated.

The ODCM calculational methodology andparameters for calculating the doses due to the actual releaserates of the subject materials are consistent with themethodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of ReactorEffluents for the Purpose of Evaluating Compliance with 10CFR Part 50, Appendix I," Revision 1, October, 1977 andRegulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in RoutineReleases from Light-Water-Cooled Reactors" Revision 1, July,1977. These equations also provide for determining the actualdoses based upon the historical average atmospheric conditions.

The release rate controls for iodine-131, iodine-133, tritium and radionuclides in particulate form withhalf lives greater than 8 days are dependent upon the existingradionuclide pathways to man, in areas at and beyond theSITE BOUNDARY.

The pathways that were examined in thedevelopment of these calculations were: 1) individual inhalation of airborne radionuclides,

2) deposition ofradionuclides onto green leafy vegetation with subsequent consumption by man, 3) deposition onto grassy areas wheremilk animals and meat producing animals graze withconsumption 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 SystemCONTROLThe GASEOUS RADWASTE TREATMENT SYSTEM and theVENTILATION EXHAUST TREATMENT SYSTEM shall beOPERABLE.

The appropriate portions of the GASEOUSRADWASTE TREATMENT SYSTEM shall be used to reduceradioactive materials in the gaseous waste prior to theirdischarge when the monthlyprojected gaseous effluent airdoses due to untreated gaseous effluent releases from the unit CY-TM-1 70-300Revision 3Page 39 of 209would exceed 0.2 mrad for gamma radiation and 0.4 mrad forbeta radiation.

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

At all timesACTION:a. With the GASEOUS RADWASTE TREATMENT SYSTEM and/or the VENTILATION EXHAUSTTREATMENT SYSTEM inoperable for more than amonth or with gaseous waste being discharged without treatment and in excess of the above limits,prepare and submit to the NRC Region IAdministrator within 30 days, a Special Reportwhich includes the following information:

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

2. Action(s) taken to restore the inoperable equipment to OPERABLE status, and3. A summary description of action(s) takento prevent a recurrence BASESThe use of the GASEOUS RADWASTE TREATMENT SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM ensures that gaseous effluents are treated asappropriate prior to release to the environment.

Theappropriate portions of this system provide reasonable assurance that the releases of radioactive materials ingaseous effluents will be kept "as low as is reasonably achievable."

This control implements the requirements of 10CFR Part 50.36a, General Design Criterion 60 of Appendix Ato 10 CFR Part 50, and the design objectives given in SectionII.D of Appendix I to 10 CFR Part 50. The specified limitsgoverning the use of appropriate portions of the systems werespecified as a suitable fraction of the guide set forth inSections II.B and II.C of Appendix 1, 10 CFR Part 50, forgaseous effluents.

CY-TM-1 70-300Revision 3Page 40 of 2092.2.2.5 Explosive Gas MixtureCONTROLThe concentration of oxygen in the Waste Gas Holdup Systemshall be limited to less than or equal to 2% by volumewhenever the concentration of hydrogen in the Waste GasHoldup System is greater than or equal to 4% by volume.AVAILABILITY:

At all timesACTION:Whenever the concentration of hydrogen in the Waste GasHoldup System is greater than or equal to 4% by volume, and:a. The concentration of oxygen in the Waste GasHoldup System is greater than 2% by volume, butless than 4% by volume, without delay, begin toreduce the oxygen concentration to within its limit.b. The concentration of oxygen in the Waste GasHoldup System is greater than or equal to 4% byvolume, immediately suspend additions of wastegas to the Waste Gas Holdup System and withoutdelay, begin to reduce the oxygen concentration towithin its limit.BASES:Based on experimental data (Reference 1), lower limits offlammability for hydrogen is 5% and for oxygen is 5% byvolume. Therefore, if the concentration of either gas is keptbelow it lower limit, the other gas may be present in higheramounts without the danger of an explosive mixture.Maintaining the concentrations of hydrogen and oxygen suchthat an explosive mixture does not occur in the waste gasholdup system provides assurance that the release ofradioactive materials will be controlled in conformance with therequirements of General Design Criterion 60 of Appendix A to10 CFR 50.REFERENCES (1) Bulletin 503, Bureau of Mines; Limits of Flammability of Gasesand Vapors CY-TM-1 70-300Revision 3Page 41 of 2092.2.2.6 Waste Gas Decay TanksCONTROL:The quantity of radioactivity contained in each waste gasdecay tank shall be limited to less than or equal to 8800 curiesnoble gases (considered as Xe-1 33).APPLICABILITY:

At all timesACTION:a. With the quantity of radioactive material in anywaste gas decay tank exceeding the above limit,immediately suspend all additions of radioactive material to the tank and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce thetank contents to within the limit.BASESRestricting the quantity of radioactivity contained in eachwaste gas decay tank provides assurance that in the event ofan uncontrolled release of the tanks contents, the resulting total body exposure to a MEMBER OF THE PUBLIC at thenearest exclusion area boundary will not exceed 0.5 rem.This is consistent with Standard Review Plan 15.7.1, "WasteGas System Failure."

2.2.3 Total Radioactive Effluent Controls2.2.3.1 Total DoseCONTROL:The annual (calendar year) dose or dose commitment to anyMEMBER OF THE PUBLIC, due.to releases of radioactivity and to radiation from uranium fuel cycle sources shall belimited to less than or equal to 25 mrem to the total body orany organ except the thyroid, which shall be limited to lessthan or equal to 75 mrem.APPLICABILITY:

At all timesACTION:With the calculated dose from the release of radioactive materials in liquid or gaseous effluents exceeding twice thelimits 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 70-300Revision 3Page 42 of 209direct radiation contributions from the unit and from outsidestorage tanks to determine whether the above limits of Control2.2.3.1 have been exceeded.

If such is the case, prepare andsubmit to the NRC Region I Administrator within 30 days, aSpecial Report which defines the corrective action to be takento reduce subsequent releases to prevent recurrence ofexceeding the above limits and includes the schedule forachieving conformance with the above limits. This SpecialReport, as defined in 10 CFR Part 20.2203(b),

shall include ananalysis which estimates the radiation exposure (dose) to aMEMBER OF THE PUBLIC from uranium fuel cycle sources,including all effluent pathways and direct radiation, for thecalendar year that includes the release(s) covered by thisreport. It shall also describe levels of radiation andconcentrations of radioactive material

involved, and the causeof 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 beencorrected, the Special Report shall include a request for avariance in accordance with the provisions of 40 CFR 190.Submittal of the report is considered a timely request, and avariance is granted until staff action on the request iscomplete.

BASESThis control is provided to meet the dose limitations of 40 CFRPart 190 that have been incorporated into 10 CFR Part20.1301(d).

This control requires the preparation andsubmittal of a Special Report whenever the calculated dosesfrom plant generated radioactive effluents and direct radiation exceed 25 mrem to the total body or any organ, except thethyroid, which shall be limited to less than or equal to 75mrem. For sites containing up to 4 reactors, it is highlyunlikely that the resultant dose to a MEMBER OF THEPUBLIC will exceed the dose limits of 40 CFR Part 190 if theindividual reactors remain within twice the dose designobjectives of Appendix I, and if direct radiation doses from thereactor units and outside storage tanks are kept small. TheSpecial Report will describe a course of action that shouldresult in the limitation of the annual dose to a MEMBER OFTHE PUBLIC to within the 40 CFR Part 190 limits. For thepurposes of the Special Report, it may be assumed that thedose commitment to the member of the public from otheruranium 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 3Page 43 of 209considered.

If the dose to any member of the public isestimated to exceed the requirements of 40 CFR Part 190, theSpecial Report with a request for a variance (provided therelease conditions resulting in violation of 40 CFR Part 190have not already been corrected) in accordance with theprovisions of 40 CFR Part 190.11 and 10 CFR Part20.2203(b),

is considered to be a timely request and fulfills therequirements of 40 CFR Part 190 until NRC staff action iscompleted.

The variance only relates to the limits of 40 CFRPart 190, and does not apply in any way to the otherrequirements for dose limitation of 10 CFR Part 20, asaddressed in Controls 2.2.1.1 and 2.2.2.1.

An individual is notconsidered a MEMBER OF THE PUBLIC during any period inwhich he/she is engaged in carrying out any operation that ispart of the nuclear fuel cycle.

CY-TM-1 70-300Revision 3Page 44 of 2093.0 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 ofthe CHANNEL CHECK, SOURCE CHECK, CHANNELCALIBRATION, AND CHANNEL TEST operations during theMODES and at the frequencies shown in Table 3.1-1.

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

1. Radioactivity Monitors Providing Alarm and Automatic Isolation

a. Unit 1 Liquid Radwaste Effluents Line (RM-L-6)b. IWTS/IWFS Discharge Line (RM-L-12)

2. Flow Rate Monitorsa. Unit 1 Liquid Radwaste Effluent Line (WDL-FT-84)

b. Station Effluent Discharge (SR-FT-146)

DDD(3)D(3)PPN/AN/AR(2)R(2)RRCHANNELTESTQ(1)Q(1)QQ CY-TM-1 70-300Revision 3Page 46 of 209Table 3.1-1 (Cont'd)Table Notation(1) The CHANNEL TEST shall also demonstrate that automatic isolation of this pathwayand 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 theNational Institute of Standards and Technology or using standards that have beenobtained from suppliers that participated in measurement assurance activities withNIST. These standards should permit calibrating the system over its intended range ofenergy and measurement range. For subsequent CHANNEL CALIBRATION, sourcesthat have been related to the initial calibration should be used. (Operating plants maysubstitute 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 3Page 47 of 2093.1.2 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 OPERABLEby 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 70-300Revision 3Page 48 of 209Table 3.1-2Radioactive Gaseous Process and Effluent Monitorinq Instrumentation Surveillance Requirements CHANNEL SOURCE CHANNEL CHANNELINSTRUMENT CHECK CHECK CALIBRATION TEST APPLICABILITY

1. Waste Gas Holdup Systema. 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 Q2. Waste Gas Holdup System Explosive Gas Monitoring Systema. 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 Systema. 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 Systema. 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-1 70-300Revision 3Page 49 of 209Table 3.1-2 (Cont'd)Radioactive Gaseous Process and Effluent Monitoring Instrumentation Surveillance Requirements CHANNEL SOURCE CHANNEL CHANNELINSTRUMENT

5. Auxiliary and Fuel Handling Building Ventilation Systema. Noble Gas Activity Monitor (RM-A8) or (RM-A4 and RM-A6)b. Iodine Sampler (RM-A8) or (RM-A4 and RM-A6)c. Particulate Sampler (RM-A8) or (RM-A4 and RM-A6)d. System Effluent Flow Rate Measurement Devices (AH-FR-149 andAH-FR-1 50)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 Systema. Noble Gas Activity Monitor (RM-A14)b. System Effluent Flow Rate (AH-UR-1104 A/B)c. Sampler Flow Rate Measurement Device (RM-A-14FI14)

CHECK CHECK CALIBRATION TESTDWWDDDDDMN/AN/AN/AN/AMN/AN/AE(3)N/AN/AEER(3)RRQ(1)N/AN/AQN/AAPPLICABILITY Q(2)QQ CY-TM-1 70-300Revision 3Page 50 of 209Table 3.1-2 (Cont'd)Radioactive Gaseous Process and Effluent Monitoring Instrumentation Surveillance Requirements CHANNEL SOURCE CHANNEL CHANNELINSTRUMENT

7. Chemical Cleaning Building Ventilation Systema. Noble Gas Activity Monitor (ALC RM-1-18)b. Iodine Sampler (ALC RM-1-18)c. Particulate Sampler (ALC RM-1-18)8. Waste Handling and Packaging Facility Ventilation Systema. Particulate Sampler (WHP-RIT-1)

9. Respirator and Laundry Maintenance Ventilation Systema. Particulate Sampler (RLM-RM-1)

CHECK CHECK CALIBRATION TEST AlPPLICABILITY DWWDMN/AN/AWE(3)N/AN/ASAQ(2)N/AN/AWD WSA W CY-TM-170-300 Revision 3Page 51 of 209Table 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 theclosure of WDG-V-47, or where RM-A-8, AH-FT-149, and AH-FT-150 areoperable and RM-A-8 is capable of automatic closure of WDG-V-47During Fuel Handling Building ESF Air Treatment System Operation

1. At all times during containment purging## At all times when condenser vacuum is established

1. 1. 1. During operation of the ventilation system(1) The CHANNEL TEST shall also demonstrate that automatic isolation of this pathway forthe Auxiliary and Fuel Handling Building Ventilation System, the supply ventilation isisolated 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 circuitfailure).

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

3. Instrument controls moved from the operate mode.

CY-TM-170-300 Revision 3Page 52 of 209Table 3.1-2NOTATIONS (Cont'd)(3) The initial CHANNEL CALIBRATION for radioactivity measurement instrumentation shall be performed using one or more of the reference standards certified by theNational Institute of Standards and Technology or using standards that have beenobtained from suppliers that participate in measurement assurance activities with NIST.These standards should permit calibrating the system over its intended range of energyand measurement range. For subsequent CHANNEL CALIBRATION, sources thathave been related to the initial calibration should be used. (Operating plants maysubstitute previously established calibration procedures for this requirement.)

(4) The CHANNEL CALIBRATION shall include the use of standard gas samplescontaining a nominal:1. One volume percent hydrogen, balance nitrogen, and2. Four volume percent hydrogen, balance nitrogen(5) The CHANNEL CALIBRATION shall include the use of standard gas samplescontaining a nominal:1. One volume percent oxygen, balance nitrogen, and2. Four volume percent oxygen, balance nitrogen CY-TM-170-300 Revision 3Page 53 of 2093.2 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 ofradioactive liquid waste shall be determined prior torelease, 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 theconcentration 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 frombatch releases shall be performed in accordance with Table 3.2-1. The results of the previouspost-release analysis shall be used with thecalculational methods in the ODCM to assure thatthe concentrations at the point of release weremaintained 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 shallbe used with the calculational methods of theODCM to assure that the concentration at the pointof release is maintained within the limits of Control2.2.1.1.3.2.1.2 Dose Calculations 3.2.1.2.1 Cumulative dose contributions from liquid effluents shall be determined in accordance with the OffsiteDose Calculation Manual (ODCM) at least once amonth.3.2.1.3 Liquid Waste Treatment 3.2.1.3.1 Doses due to liquid releases shall be projected atleast once a month, in accordance with the ODCM.

CY-TM-170-300 Revision 3Page 54 of 2093.2.1.4 Liquid Holdup Tanks3.2.1.4.1 The quantity of radioactive material contained ineach of the tanks specified in Control 2.2.1.4 shallbe determined to be within the limit by analyzing arepresentative sample of the tank's content weeklywhen radioactive materials are being added to thetank.

CY-TM-170-300 Revision 3Page 55 of 209Liquid Release TypeA.1 Batch Waste Release Tanks (NoteTable 3.2-1Radioactive Liquid Waste Sampling and Analysis ProgramSampling Minimum AnalysisFrequency Frequency Type of Actid) P P HEach Batch Each Batch Principal GammEII-1Dissolved and F(Gamma EmiP M GrossEach Batch Composite (Note b)P Q Sr-89IiEach Batch Composite (Note b) FeContinuous W Principal Gamma(Note c) Composite (Note c) I1Grab Sample M Dissolved and ErM (Gamma EmitterContinuous M H(Note c) Composite (Note c) GrossContinuous Q Sr-89(Note c) Composite (Note c' FeA.2 Continuous Releases (Note e)ivity Analysis-3Emitters (Note f)131Entrained Gasestters) (Note g)alphaSr-90-55Emitters (Note f)31 Gases;) (Note g)-3alphaSr-90-55ILower Limit ofDetection (LLD)(p.Ci/ml)

(Note a)1 xl0-55 x 10-71 x 1061 xl0s1 x10-75 x 10-81 x 1065 X10-7I x 101 x 10-51 x 10-1 x l0i75 x 1081 x 106.1-I..... r. ..... \ ......

• CY-TM-170-300 Revision 3Page 56 of 209Table 3.2-1 (Cont'd)Table Notationa. The LLD is defined, for purposes of this surveillance, as the smallestconcentration of radioactive material in a sample that will yield a net count abovesystem 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 SbLLD =E x V x 2.22 x 106 x Y x exp (-AAt)Where:LLD is the "a priori" lower limit of detection as defined above (as microcurie perunit mass or volume)Sb is the standard deviation of the background counting rate or of the countingrate 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, andAt is the elapsed time between midpoint of sample collection and time of countingTypical 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 "aposteriori" (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 samplingemployed results in a specimen which is representative of the liquids released CY-TM-1 70-300Revision 3Page 57 of 209Table 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 rateof flow of the effluent stream. Prior to analyses, all samples taken for thecomposite shall be thoroughly mixed in order for the composite sample to berepresentative of the effluent released. A batch release is the discharge of liquid wastes of a discrete volume. Prior tosampling for analyses, each batch shall be isolated, and be thoroughly mixed, bya 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 thesenuclides are to be considered.

Other gamma peaks that are identifiable, togetherwith those of the above nuclides, shall also be analyzed and reported in theAnnual Radioactive Effluent Release Report pursuant to TS 6.9.4.g. The gamma emitters for which the LLD specification applies exclusively are thefollowing radionuclides:

Kr-87, Kr-88, Xe-133, Xe-133m, and Xe-135. This listdoes not mean that only these nuclides are to be considered.

Other gammapeaks that are identifiable, together with those of the above nuclides, shall alsobe analyzed and reported in the Annual Effluent Release Report pursuant to T.S.6.9.4.

CY-TM-1 70-300Revision 3Page 58 of 2093.2.2 Gaseous Effluents SURVEILLANCE REQUIREMENTS 3.2.2.1 Dose Rates3.2.2.1.1 The dose rate due to noble gases in gaseouseffluents shall be determined to be within the limitsof Control 2.2.2.1 .a in accordance with the methodsand procedures of the ODCM.3.2.2.1.2 The dose rate of radioactive materials, other thannoble gases, in gaseous effluents shall bedetermined to be within the limits of Control2.2.2.1.b in accordance with methods andprocedures of the ODCM by obtaining representative samples and performing analyses inaccordance with the sampling and analysisprogram, specified in Table 3.2-2.3.2.2.2 Dose, Noble Gas3.2.2.2.1 Cumulative dose contributions from noble gaseffluents for the current calendar quarter and currentcalendar year shall be determined in accordance with the OFFSITE DOSE CALCULATION MANUAL(ODCM) monthly.3.2.2.3 Dose, Iodine-131, Iodine-1 33, Tritium, and Radionuclides inParticulate Form3.2.2.3.1 Cumulative dose contributions from Iodine-1 31,Iodine-133,

Tritium, and radionuclides in particulate form with half lives greater than 8 days for thecurrent calendar quarter and current calendar yearshall be determined in accordance with theOFFSITE 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 shallbe projected monthly in accordance with the ODCM.

CY-TM-170-300 Revision 3Page 59 of 2093.2.2.5 Explosive Gas Mixture3.2.2.5.1 The concentrations of hydrogen and oxygen in thewaste gas holdup system shall be determined to bewithin the limits of Control 2.2.2.5 by monitoring thewaste gases in the Waste Gas Holdup System withthe hydrogen and oxygen monitors covered in Table2.1-2 of Control 2.1.2.3.2.2.6 Waste Gas Decay Tank3.2.2.6.1 The concentration of radioactivity contained in thevent header shall be determined weekly. If theconcentration of the vent header exceeds10.7 gCi/cc, daily samples shall be taken of eachwaste gas decay tank being added to, to determine if the tank(s) is less than or equal to 8800 Ci/tank.

CY-TM-170-300 Revision 3Page 60 of 209Table 3.2-2Radioactive Gaseous Waste Sampling and Analysis ProgramMinimum Lower Limit ofSampling Analysis Type of Activity Detection (LLD)Gaseous Release Type Frequency Frequency Analysis piCi/ml)

(Note a)PEhaP Principal Gamma 1A. Waste Gas Decay Tank Grab Sample Each Tank Emitters (Note g)B. Containment Purge H-3 1 x 10-6P (Note b)Each P (Note b) Each Principal GammaPurge Grab Sample Purge Emitters (Note g) 1 X 10.C. Auxiliary and Fuel Handling Building H-3 1 x10.6Air Treatment System M (Notes c, e) GrabSample M Principal Gamma 1Emitters (Note g) 1 x 10D. Fuel Handling Building ESF Air Treatment System M (during System M (during H-3 1 x 10-6Operation)

System Principal GammaGrab Sample Operation)

Emitters (Note g) 1 x 10-4Ex as Nt )H-3 1 x10-6E. Condenser Vacuum Pumps Exhaust (Note h) M (Note h) M Principal GammaGrab Sample (Note h) Emitters (Note g) 1 x 10-4F. Chemical Cleaning Building Air Treatment System MH-3 1 x 1r0iM (Notel1)

M Principal GammaGrab Sample Emitters (Note g) 1x 10-4G. Waste Handling and Packaging Facility See Section I See Section I See Section I See Section IAir Treatment System of this table of this table of this table of this tableH. Respirator and Laundry Maintenance Facility See Section I See Section I See Section I See Section IAir Treatment System of this table of this table of this table , of this table CY-TM-170-300 Revision 3Page 61 of 209Table 3.2-2 (Cont'd)Radioactive Gaseous Waste Sampling and Analysis ProgramLower Limit ofI Sampling Minimum Analysis Type of Activity Detection (LLD)Gaseous Release Type Frequency Frequency Analysis (pCi/ml)

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

Continuous W (Note d) 1-131 1 X 10-12(Note f) Charcoal Sample : 1 0(Note i) ___Principal GammaContinuous W (Note d) Emitters (Note g) 1x1011(Note f) Particulate (1-131, Others)QContinuous Composite Gross Alpha 1 x .10"11(Note f) Particulate SampleQContinuous Composite Sr-89, Sr-90 1 x 10-11(Note f) Particulate SampleContinuous Noble Gas 1 X,(Note f) Beta or Gamma Noble Gases , 1 x 10.6J, Condenser Vent Stack Continuous Iodine Continuous W (Note d) 1-131 1 x 10-12Sampler (Note j) (Note k) Charcoal Sample CY-TM-1 70-300Revision 3Page 62 of 209Table 3.2-2 (Cont'd)Table Notationa. The LLD is defined, for purposes of this surveillance, as the smallestconcentration of radioactive material in a sample that will yield a net count abovesystem 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):

4.66SbLLD =E xV x2.22 x 106 x Y xexp(-kAt)

Where: LLD is the "a priori" lower limit of detection as defined above (as microcurie perunit mass or volume)Sb is the standard deviation of the background counting rate or of the countingrate 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, andAt is the elapsed time between midpoint of sample collection and time ofcounting.

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 "aposteriori" (after the fact) limit for a particular measurement.

b. Sampling and analysis shall also be performed following

shutdown, startup, orTHERMAL POWER change exceeding 15 percent of RATED THERMALPOWER within one hour, unless (1) analysis shows that the DOSEEQUIVALENT 1-131 concentration in the primary coolant has not increased morethan a factor of 3; and (2) the noble gas activity monitor shows that effluentactivity 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 onceper 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the refueling canal is flooded.

CY-TM-170-300 Revision 3Page 63 of 209Table 3.2-2 Notations (Cont'd)d. Charcoal cartridges and particulate filters shall be changed at least once per 7days and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing (or afterremoval from sampler).

e. Tritium grab samples shall be taken weekly from the spent fuel pool areawhenever spent fuel is in the spent fuel pool.f. The ratio of the sample flow rate to the sampled stream flow rate shall be knownfor the time period covered by each dose or dose rate calculation made inaccordance 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-1 33, Xe-1 33m, Xe-1 35 andXe-1 38 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99,Cs-1 37, Ce-141 and Ce-144 for particulate emissions.

This list does not meanthat only these nuclides are to be considered.

Other gamma peaks that areidentifiable, together with those of the above nuclides, shall also be analyzed andreported in the Annual Radioactive Effluent Release Report pursuant to TS 6.9.4.h. Applicable only when condenser vacuum is established.

Sampling and analysisshall also be performed following

shutdown, startup, or a THERMAL POWERchange exceeding 15 percent of RATED THERMAL POWER within one hourunless (1) analysis shows that the DOSE EQUIVALENT 1-131 concentration inthe primary coolant has not increased more than a factor of 3; and (2) the noblegas activity monitor shows that effluent activity has not increased by more than afactor of 3.Gross Alpha, Sr-89, and Sr-90 analyses do not apply to the Fuel HandlingBuilding ESF Air Treatment System.j. If the Condenser Vent Stack Continuous Iodine Sampler is unavailable, thenalternate sampling equipment will be placed in service within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or a reportwill be prepared, and submitted within 30 days from the time the sampler is foundor made inoperable, which identifies (a) the cause of the inoperability, (b) theaction taken to restore representative sampling capability, (c) the action taken toprevent recurrence, and (d) quantification of the release via the pathway duringthe 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-1liquid radwaste is stored or processed in the facility.

CY-TM-1 70-300Revision 3Page 64 of 2093.2.3 Total Radioactive Effluents 3.2.3.1 Dose Calculation 3.2.3.1.1 Cumulative annual dose contributions from liquid andgaseous effluents shall be determined in accordance withSurveillances 3.2.1.2.1, 3.2.2.2.1, and 3.2.2.3.1, including direct radiation contributions from the Unit and fromoutside storage tanks, and in accordance with themethodology contained in the ODCM.

CY-TM-170-300 Revision 3Page 65 of 2094.0 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 RoutingReleases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR Part 50, Appendix I, "Revision 1, October 19774.3 TMI-1 Technical Specifications, attached to Facility Operating License No.DPR-504.4 TMI-1 FSAR CY-TM-1 70-300Revision 3Page 66 of 209PART IITMI-2 RADIOLOGICAL EFFLUENT CONTROLS CY-TM-1 70-300Revision 3Page 67 of 209PART IIDefinitions

1.0 DEFINITIONS

DEFINED TERMS1.1 The DEFINED TERMS of this section appear in capitalized type and areapplicable throughout Part II of the ODCM.PDMS1.2 Post-Defueling Monitored Storage (PDMS) is that condition where TMI-2defueling has been completed, the core debris removed from the reactor duringthe clean-up period has been shipped off-site, and the facility has been placed ina stable, safe, and secure condition.

ACTION1.3 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 haveOPERABILITY when it is capable of performing its specified function(s).

Implicitin 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 requiredfor 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 thechannel output such that it responds with necessary range and accuracy toknown values of the parameter, which the channel monitors.

The CHANNELCALIBRATION shall encompass the entire channel including the sensor andalarm 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 70-300Revision 3Page 68 of 209CHANNEL CHECK1.6 A CHANNEL CHECK shall be the qualitative assessment of channel behaviorduring operation by observation.

This determination shall include, wherepossible, comparison of the channel indication and/or status with otherindications and/or status derived from independent instrument channelsmeasuring the same parameter.

CHANNEL FUNCTIONAL TEST1.7 A CHANNEL FUNCTIONAL TEST shall be:a. Analog channels

-the injection of a simulated signal into the channel asclose 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 channelsensor to verify OPERABILITY including alarm and/or trip functions.

SOURCE CHECK1.8 A SOURCE CHECK shall be the qualitative assessment of channel responsewhen the channel sensor is exposed to a radioactive source.COMPOSITE SAMPLE1.9 A COMPOSITE SAMPLE is a combination of individual samples obtained atregular intervals over a time period. Either the volume of each individual sampleis proportional to the flow rate discharge at the time of sampling or the number ofequal volume samples is proportional to the time period used to produce thecomposite.

GRAB SAMPLE1.10 A GRAB SAMPLE is an individual sample collected in less than fifteen minutes.BATCH RELEASE1.11 A BATCH RELEASE is the discharge of fluid waste of a discrete volume.CONTINUOUS RELEASE1.12 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 theCONTINUOUS RELEASE.

CY-TM-170-300 Revision 3Page 69 of 209SITE BOUNDARY1.13 The SITE BOUNDARY used as the basis for the limits on the release of gaseouseffluents is as defined in Section 2.1.2.2 and shown on Figure 2.1-3 of the TMI-1FSAR. This boundary line includes portions of the Susquehanna River surfacebetween the east bank of the river and Three Mile Island and between Three MileIsland and Shelley Island.The SITE BOUNDARY used as the basis for the limits on the release of liquideffluents is as shown in Figure 1.1 in Part I of this ODCM.FREQUENCY NOTATION1.14 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.1. AllSurveillance Requirements shall be performed within the specified time intervalwith a maximum allowable extension not to exceed 25% of the surveillance interval.

CY-TM-170-300 Revision 3Page 70 of 209TABLE 1.1Frequency NotationNOTATIONFREQUENCY S (Shiftly)

D (Daily)W (Weekly)M (Monthly)

Q (Quarterly)

SA (Semi-Annually)

A (Annually)

EN.A.At least once per 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />sAt least once per 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />sAt least once per 7 daysAt least once per 31 daysAt least once per 92 daysAt least once per 184 daysAt least once per 12 monthsAt least once per 18 monthsNot applicable Completed prior to each releaseP CY-TM-170-300 Revision 3Page 71 of 2092.0 CONTROLS AND BASES2.0.1 Controls and ACTION requirements shall be applicable during theconditions 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 tothe specified time interval, completion of the ACTION statement is notrequired.

2.0.3 In the event the Control and associated ACTION requirements cannotbe satisfied because of circumstances in excess of those addressed inthe Control, initiate appropriate actions to rectify the problem to theextent possible under the circumstances, and submit a special report tothe 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-1and TMI-2. Controls, applicability, and actions are specified in ODCMPart I, Control 2.1.12.1.2 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 withtheir alarm/trip setpoints set to ensure that the limits of Control 2.2.2.1are not exceeded.

The alarm/trip setpoints of these channels shall bedetermined in accordance with the OFFSITE DOSE CALCULATION MANUAL (ODCM).APPLICABILITY:

As shown in Table 2.1-2ACTION:a. With a radioactive gaseous process or effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above control, immediately suspend therelease of radioactive effluent monitored by the affectedchannel or declare the channel inoperable.

CY-TM-1 70-300Revision 3Page 72 of 209b. With less than the minimum number of radioactive gaseousprocess or effluent monitoring instrumentation channelsOPERABLE, take the ACTION shown in Table 2.1-2. Exertbest efforts to return the instrumentation to OPERABLE statuswithin 30 days and, if unsuccessful, explain in the next AnnualEffluent Release Report why the inoperability was notcorrected in a timely manner.BASESThe radioactive gaseous effluent instrumentation is provided to monitorand control, as applicable, the releases of radioactive materials ingaseous effluent during actual or potential releases.

The alarm/trip setpoints for these instruments shall be calculated in accordance withNRC approved methods in the ODCM to provide reasonable assurance that the annual releases are within the limits specified in 10 CFR20.1301.

CY-TM-170-300 Revision 3Page 73 of 209Table 2.1-2Radioactive Gaseous Process and Effluent Monitoring Instrumentation MINIMUMCHANNELSINSTRUMENT OPERABLE APPLICABILITY ACTION1. Containment Purge Monitoring Systema. Noble Gas Activity Monitor (2HP-R-225) 1 NOTE 1 NOTE 2b. Particulate Monitor (2HP-R-225) 1 NOTE 1 NOTE 2c. Effluent System Flow Rate Measuring Device (2AH-FR-5907 Point 1) 1 NOTE 1 NOTE 32. Station Ventilation Systema. Noble Gas Activity Monitor (2HP-R-219) or (2HP-R-219A) 1 NOTE 1 NOTE 2b. Particulate Monitor (2HP-R-219) or (2HP-R-219A) 1 NOTE 1 NOTE 2c. Effluent System Flow Rate Monitoring Device (2AH-FR-5907 Point 6) 1 NOTE 1 NOTE 3NOTES:1. During operation of the monitored system.2. With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, secureReactor Building Purge if in progress.

3. With flow rate monitoring instrumentation out of service, flow rates from the Auxiliary (2AH-FR-5907 Point 2), FuelHandling (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.

Ifthe flow rates cannot be summed individually, they may be estimated using the maximum design flow for the exhaustfans, and the reporting requirements of Control 2.1.2.b are applicable.

CY-TM-170-300 Revision 3Page 74 of 2092.2 Radioactive Effluent Controls2.2.1 Liquid Effluent Controls2.2.1.1 Liquid Effluent Concentration CONTROL:The concentration of radioactive material released at anytimefrom the unit to unrestricted areas shall be limited to ten timesthe concentrations specified in 10 CFR Part 20.1001-20.2401, Appendix B, Table 2, Column 2.APPLICABILITY:

At all timesACTION:With the concentration of radioactive material released fromthe unit to unrestricted areas exceeding the above limits,immediately restore concentrations within the above limits.BASESThis control is provided to ensure that the concentration ofradioactive materials released in liquid waste effluent from theunit to unrestricted areas will be less than ten times theconcentration levels specified in 10 CFR Part20.1001-20.2401, Appendix B, Table 2. These Controlspermit flexibility under unusual conditions, which maytemporarily result in higher than normal releases, but stillwithin ten times the concentrations, specified in 10 CFR 20. Itis expected that by using this flexibility under unusualconditions, and exerting every effort to keep levels ofradioactive material in liquid wastes as low as practicable, theannual releases will not exceed a small fraction of the annualaverage 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 notexceed the design objectives of Section II.A of Appendix I to10 CFR Part 50, which were established as requirements forthe cleanup of TMI-2 in the NRC's Statement of Policy of April27, 1981.

CY-TM-1 70-300Revision 3Page 75 of 2092.2.1.2 Liquid Effluent DoseCONTROLThe dose or dose commitment to a MEMBER OF THEPUBLIC from radioactive materials in liquid effluents releasedfrom the unit to the SITE BOUNDARY shall be limited:a. During any calendar quarter to less than or equal to1.5 mrem to the total body and to less than or equalto 5 mrem to any organ.b. During any calendar year to less than or equal to 3mrem to the total body and to less than or equal to10 mrem to any organ.APPLICABILITY:

At all timesACTION:a. With the calculated dose from the release ofradioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to theNRC Region I Administrator within 30 days, aSpecial Report which identifies the cause(s) forexceeding the limit(s) and defines the corrective actions to be taken to reduce the releases ofradioactive materials in liquid effluents during theremainder of the current calendar quarter andduring the subsequent 3 calendar quarters so thatthe cumulative dose or dose commitment to anyindividual from such releases during these fourcalendar quarters is within 3 mrem to the total bodyand 10 mrem to any organ. This Special Reportshall also include (1) the result of radiological analyses of the drinking water source, and (2) theradiological impact on finished drinking watersupplies with regard to the requirements of 40 CFR141, Safe Drinking Water Act.

CY-TM-1 70-300Revision 3Page 76 of 209BASESThis Control requires that the dose to offsite personnel belimited to the design objectives of Appendix I of 10 CFR Part50. This will assure the dose received by the public duringPDMS is equivalent to or less than that from a normaloperating reactor.

The limits also assure that theenvironmental impacts are consistent with those assessed inNUREG-0683, the TMI-2 Programmatic Environmental ImpactStatement (PEIS). The ACTION statements provide therequired flexibility under unusual conditions and at the sametime implement the guides set forth in Section IV.A ofAppendix I to assure that the releases of radioactive materialin liquid effluents will be kept "as low as is reasonably achievable".

The dose calculations in the ODCM implement the requirements in Section lIlA.. of Appendix I thatconformance with the guides of Appendix I is to be shown bycalculational procedures based on models and data such thatthe actual exposure of a MEMBER OF THE PUBLIC throughappropriate pathways is unlikely to be substantially underestimated.

The equations specified in the ODCM forcalculating the doses due to the actual release rates ofradioactive materials in liquid effluents are consistent with themethodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of ReactorEffluents for the Purpose of Evaluating Compliance with 10CFR Part 50, Appendix I," Revision 1, October, 1977, andRegulatory Guide 1.113, "Estimating Aquatic Dispersion ofEffluents from Accidental and Routine Reactor Releases forthe 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 70-300Revision 3Page 77 of 2092.2.1.3 Liquid Radwaste Treatment SystemCONTROL:The appropriate portions of the liquid radwaste treatment system shall be used to reduce the radioactive materials inliquid wastes prior to their discharge when the projected dosesdue to the liquid effluent from the unit to unrestricted areaswould exceed 0.06 mrem to the total body or 0.2 mrem to anyorgan in any calendar month.APPLICABILITY:

At all timesACTION:a. With radioactive liquid waste being discharged without treatment and in excess of the above limits,prepare and submit to the NRC Region IAdministrator within 30 days, a Special Reportwhich includes the following information:

1. Explanation of why liquid radwaste wasbeing discharged without treatment, identification of any inoperable equipment or subsystems, and the reason forinoperability,

2. Action(s) taken to restore the inoperable equipment to OPERABLE status, and,3. A summary description of action(s) takento prevent a recurrence.

BASESThe requirement that the appropriate portions of this system(shared with TMI-1) be used, when specified, providesassurance that the releases of radioactive materials in liquideffluents will be kept as low as is reasonably achievable.

Thiscontrol implements the requirements of 10 CFR Part 50.36a,General Design Criterion 60 of Appendix A to 10 CFR Part 50and the design objective given in Section II.D of Appendix I to10 CFR Part 50. The intent of Section ll.D. is to reduceeffluents to as low as is reasonably achievable in a costeffective manner. This control satisfies this intent byestablishing a dose limit which is a small fraction (25%) ofSection II.A of Appendix 1, 10 CFR Part 50 dose requirements.

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

CY-TM-1 70-300Revision 3Page 78 of 2092.2.2 Gaseous Effluent Controls2.2.2.1 Gaseous Effluent Dose RateCONTROL:The dose rate due to radioactive materials released ingaseous effluent from the site shall be limited to the following:

a. For noble gases: less than or equal to 500 mrem/yrto the total body and less than or equal to 3000mrem/yr to the skin, andb. For tritium and all radionuclides in particulate formwith half lives greater than 8 days: less than orequal 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 theabove limit(s).

CY-TM-1 70-300Revision 3Page 79 of 209BASESThe control provides reasonable assurance that the annualdose at the SITE BOUNDARY from gaseous effluent from allunits on the site will be within the annual dose limits of 10 CFRPart 20 for unrestricted areas. At the same time, theseControls permit flexibility under unusual conditions, which maytemporarily result in higher than the design objective levels,but still within the dose limits specified in 10 CFR 20 andwithin the design objectives of Appendix I to 10 CFR 50. It isexpected 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 annualreleases will not exceed a small fraction of the annual doselimits specified in 10 CFR 20 and will not result in doses whichexceed the design objectives of Appendix I to 10 CFR 50,which were endorsed as limits for the cleanup of TMI-2 by theNRC's Statement of Policy of April 27, 1981. These gaseousrelease rates provide reasonable assurance that radioactive material discharged in gaseous effluent will not result in theexposure of a MEMBER OF THE PUBLIC in an unrestricted area, either within or outside the SITE BOUNDARY, to annualaverage concentrations exceeding the values specified inAppendix B, Table 2 of 10 CFR Part 20. For MEMBERS OFTHE PUBLIC who may at times be within the SITEBOUNDARY, the occupancy of the MEMBER OF THEPUBLIC will be sufficiently low to compensate for any increasein the atmospheric diffusion factor above that for the exclusion area boundary.

The specified release rate limits restrict, at alltimes, the corresponding gamma and beta dose rates abovebackground to a MEMBER OF THE PUBLIC at or beyond theSITE BOUNDARY to less than or equal to 500 mrem/year tothe total body or to less than or equal to 3000 mrem/year tothe skin. The absence of iodine ensures that thecorresponding thyroid dose rate above background to a childvia the inhalation pathway is less than or equal to 1500mrem/yr (NUREG 1301), thus there is no need to specify doserate limits for these nuclides.

CY-TM-170-300 Revision 3Page 80 of 2092.2.2.2 Gaseous Effluents Dose-Noble GasesCONTROL:The air dose due to noble gases released in gaseous effluents from the unit to areas at and beyond the SITE BOUNDARYshall be limited to the following:

a. During any calendar quarter:

less than or equal to 5mrad for gamma radiation and less than or equal to10 mrad for beta radiation and,b. During any calendar year: less than or equal to 10mrad for gamma radiation and less than or equal to20 mrad for beta radiation.

APPLICABILITY:

At all times.ACTION:a. With the calculated air dose from radioactive noblegases in gaseous effluents exceeding any of theabove limits, prepare and submit to the NRC RegionI Administrator within 30 days, a Special Reportwhich identifies the cause(s) for exceeding thelimit(s) and defines the corrective actions that havebeen taken to reduce the releases and the proposedcorrective actions to be taken to assure thatsubsequent releases will be in compliance with theabove limits.BASESThis control applies to the release of radioactive materials ingaseous effluents from TMI-2.

CY-TM-1 70-300Revision 3Page 81 of 209.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 forthin Section II.B of Appendix I. The ACTION statements provideflexibility under unusual conditions and at the same timeimplement the guides set forth in Section IV.A of Appendix I toassure that the releases of radioactive material in gaseouseffluents will be kept "as low as is reasonably achievable."

The Surveillance Requirements implement the requirements inSection III.A of Appendix I that conformance with the guides ofAppendix I be shown by calculational procedures based onmodels and data such that the actual exposure of a MEMBEROF THE PUBLIC through the appropriate pathways is unlikelyto be substantially underestimated.

The dose calculation methodology and parameters established in the ODCM forcalculating the doses due to the actual release rates ofradioactive 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 ofReactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents inRoutine Releases from Light-Water Cooled Reactors,"

Revision 1, July 1977. The ODCM equations provided fordetermining the air doses at and beyond the SITEBOUNDARY are based upon the historical averageatmospheric conditions.

NUREG-0133 provides methods fordose calculations consistent with Regulatory Guides 1.109and 1.111.2.2.2.3 Dose -Iodine-131, Iodine-133,

Tritium, and Radionuclides InParticulate FormCONTROL:The dose to a MEMBER OF THE PUBLIC from Tritium and allradionuclides in particulate form with half lives greater than 8days, in gaseous effluents released from the unit to areas atand beyond the SITE BOUNDARY shall be limited to thefollowing:

a. During any calendar quarter:

less than or equal to7.5 mrem to any organ, andb. During any calendar year: less than or equal to 15mrem to any organ.

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

At all times.ACTION:With the calculated dose from the release of Tritium andradionuclides in particulate form with half lives greater than 8days, in gaseous effluents exceeding any of the above limits,prepare and submit to the NRC Region I Administrator within30 days, a Special Report which identifies the cause(s) forexceeding the limit and defines the corrective actions thathave been taken to reduce the releases and the proposedcorrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

CY-TM-1 70-300Revision 3Page 83 of 209BASESThis control applies to the release of radioactive materials ingaseous 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 inSection II.C of Appendix I. The ACTION statement providesflexibility during unusual conditions and at the same timeimplements the guides set forth in Section IV.A of Appendix Ito assure that the releases of radioactive materials in gaseouseffluents 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 ofAppendix I that conformance with the guides of Appendix I beshown by calculational procedures based on models and datasuch that the actual exposure of a MEMBER OF THE PUBLICthrough appropriate pathways is unlikely to be substantially underestimated.

The ODCM calculational methodology andparameters for calculating the doses due to the actual releaserates of the subject materials are consistent with themethodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of ReactorEffluents for the Purpose of Evaluating Compliance with 10CFR Part 50, Appendix I," Revision 1, October, 1977 andRegulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in RoutineReleases from Light-Water-Cooled Reactors,"

Revision 1,July, 1977. These equations also provide for determining theactual doses based upon the historical average atmospheric conditions.

The release rate controls for iodine-131, iodine-133, tritium and radionuclides in particulate form withhalf lives greater than 8 days are dependent upon the existingradionuclide pathways to man, in areas at and beyond theSITE BOUNDARY.

The pathways that were examined in thedevelopment of these calculations were: 1) individual inhalation of airborne radionuclides,

2) deposition ofradionuclides onto green leafy vegetation with subsequent consumption by man, 3) deposition onto grassy areas wheremilk animals and meat producing animals graze withconsumption of the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man. Theabsence of iodines at the site eliminates the need to specifydose limits for these nuclides.

CY-TM-1 70-300Revision 3Page 84 of 2092.2.2.4 Ventilation Exhaust Treatment SystemCONTROLThe VENTILATION EXHAUST TREATMENT SYSTEM shallbe OPERABLE.

The appropriate portions of theVENTILATION EXHAUST TREATMENT SYSTEM shall beused to reduce radioactive materials in gaseous waste prior totheir discharge when the monthly projected doses due togaseous effluent releases from the site would exceed 0.3mrem to any organ.APPLICABILITY:

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

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

2. Action(s) taken to restore the inoperable equipment to OPERABLE status, and3. A summary description of action(s) takento prevent a recurrence.

BASESThe use of the VENTILATION EXHAUST TREATMENT SYSTEM ensures that gaseous effluents are treated asappropriate prior to release to the environment.

Theappropriate portions of this system provide reasonable assurance that the releases of radioactive materials ingaseous effluents will be kept "as low as is reasonably achievable."

This control implements the requirements of 10CFR Part 50.36a, General Design Criterion 60 of Appendix Ato 10 CFR Part 50, and the design objectives given in SectionII.D of Appendix I to 10 CFR Part 50. The specified limitsgoverning the use of appropriate portions of the systems were CY-TM-170-300 Revision 3Page 85 of 209specified as a suitable fraction of the guide set forth inSections II.B and II.C of Appendix 1, 10 CFR Part 50, forgaseous effluents.

2.2.3 Total Radioactive Effluent Controls2.2.3.1 Total DoseCONTROL:The annual (calendar year) dose or dose commitment to anyMEMBER OF THE PUBLIC, due to releases of radioactivity and to radiation from uranium fuel cycle sources shall belimited to less than or equal to 25 mrem to the total body orany organ except the thyroid, which shall be limited to lessthan 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 thelimits 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 outsidestorage tanks to determine whether the above limits of Control2.2.3.1 have been exceeded.

If such is the case, prepare andsubmit to the NRC Region I Administrator within 30 days, aSpecial Report which defines the corrective action to be takento reduce subsequent releases to prevent recurrence ofexceeding the above limits and includes the schedule forachieving conformance with the above limits. This SpecialReport, as defined in 10 CFR Part 20.2203(b),

shall include ananalysis which estimates the radiation exposure (dose) to aMEMBER OF THE PUBLIC from uranium fuel cycle sources,including all effluent pathways and direct radiation, for thecalendar year that includes the release(s) covered by thisreport. It shall also describe levels of radiation andconcentrations of radioactive material

involved, and the causeof 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 beencorrected, the Special Report shall include a request for avariance in accordance with the provisions of 40 CFR 190.Submittal of the report is considered a timely request, and avariance is granted until staff action on the request iscomplete.

CY-TM-1 70-300Revision 3Page 86 of 209BASESThis control is provided to meet the dose limitations of 40 CFRPart 190 that have been incorporated into 10 CFR Part20.1301(d).

This control requires the preparation andsubmittal of a Special Report whenever the calculated dosesfrom plant generated radioactive effluents and direct radiation exceed 25 mrem to the total body or any organ, except thethyroid, which shall be limited to less than or equal to 75mrem. For sites containing up to 4 reactors, it is highlyunlikely that the resultant dose to a MEMBER OF THEPUBLIC will exceed the dose limits of 40 CFR Part 190 if theindividual reactors remain within twice the dose designobjectives of Appendix I, and if direct radiation doses from thereactor units and outside storage tanks are kept small. TheSpecial Report will describe a course of action that shouldresult in the limitation of the annual dose to a MEMBER OFTHE PUBLIC to within the 40 CFR Part 190 limits. For thepurposes of the Special Report, it may be assumed that thedose commitment to the member of the public from otheruranium 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 beconsidered.

If the dose to any member of the public isestimated to exceed the requirements of 40 CFR Part 190, theSpecial Report with a request for a variance (provided therelease conditions resulting in violation of 40 CFR Part 190have not already been corrected),

in accordance with theprovisions of 40 CFR Part 190.11 and 10 CFR Part20.2203(b),

is considered to be a timely request and fulfills therequirements of 40 CFR Part 190 until NRC staff action iscompleted.

The variance only relates to the limits of 40 CFRPart 190, and does not apply in any way to the otherrequirements for dose limitation of 10 CFR Part 20, asaddressed in Controls 2.2.1.1 and 2.2.2.1.

An individual is notconsidered a MEMBER OF THE PUBLIC during any period inwhich he/she is engaged in carrying out any operation that ispart of the nuclear fuel cycle.

CY-TM-170-300 Revision 3Page 87 of 2093.0 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 beperformed 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% ofthe surveillance interval.

3.0.3 Failure to perform a Surveillance Requirement within the time intervalspecified in Section 3.0.2 shall constitute non-compliance withOPERABILITY requirements for a Control.

The time limits of theACTION requirements are applicable at the time it is identified that aSurveillance Requirement has not been performed.

The ACTIONrequirements may be delayed for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to permit completion ofthe surveillance when the allowable outage time limits of the ACTIONrequirements are less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Surveillance Requirements do nothave 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 commonbetween TMI-1 and TMI-2. Surveillances for thisinstrumentation 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 byperformance of the CHANNEL CHECK, SOURCE CHECK,CHANNEL CALIBRATION, and CHANNEL TEST operations at the frequencies shown in Table 3.1-2.

CY-TM-1 70-300Revision 3Page 88 of 209Table 3.1-2Radioactive Gaseous Process and Effluent Monitoring Instrumentation Surveillance Requirements CHANNELCHECKINSTRUMENT

1. Containment Purge Monitoring Systema. Noble Gas Activity Monitor (2HP-R-225)

b. Particulate Sampler (2HP-R-225)

CHANNELCALIBRATION EN/ACHANNELFUNCTIONAL TESTMN/AAPPLICABILITY NOTE 1NOTE 1Dw2. Station Ventilation Monitoring Systema. Noble Gas Activity Monitor (2HP-R-219) and (2HP-R-219A)

b. Particulate Sampler (2HP-R-219) and (2HP-R-219A)

NOTES:1. During operation of the monitored system.DwEN/AMN/ANOTE 1NOTE 1 CY-TM-170-300 Revision 3Page 89 of 2093.2 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 ofradioactive liquid waste shall be determined bysampling and analysis in accordance with Table3.2-1. The results of analyses shall be used withthe calculational methods in the ODCM to assurethat the concentration at the point of release ismaintained within the limits of Control 2.2.1 .1.3.2.1.1.2 Analysis of samples composited from batchreleases shall be performed in accordance withTable 3.2-1. The results of the analysis shall beused with the calculational methods in the ODCM toassure that the concentrations at the point ofrelease were maintained within the limits of Control2.2.1.1.3.2.1.1.3 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 shallbe used with the calculational methods of theODCM to assure that the concentration at the pointof release is maintained within the limits of Control2.2.1.1.3.2.1.2 Dose Calculations 3.2.1.2.1 Cumulative dose contributions from liquid effluents shall be determined in accordance with the OffsiteDose Calculation Manual (ODCM) at least once amonth.3.2.1.3 Dose Projections 3.2.1.3.1 Doses due to liquid releases shall be projected atleast once a month, in accordance with the ODCM.

CY-TM-170-300 Revision 3Page 90 of 209TABLE 3.2-1Radioactive Liquid Waste Sampling and Analysis Program (4, 5)A. Liquid ReleasesSampling Frequency Type of Detectable Activity Analysis Concentration (3)P Individual Gamma 5E-7 ýLCi/ml (2)Each Batch H-3 1 E-5 ýtCi/mlQ Gross Alpha 1 E-7 JLCi/mlQuarterly Composite (1) Sr-90 5E-8 jtCi/mlNOTES:(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 measureradionuclides in concentrations near this sensitivity limit when other nuclides arepresent in the sample in much greater concentrations.

Under these circumstances, itwill be more appropriate to calculate the concentrations of such radionuclides usingmeasured 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.

Forsome nuclides, lower detection limits may be readily achievable and when nuclides aremeasured 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 samplingperiod. In estimating releases for a period when analyses were not performed, theaverage of the two adjacent data points spanning this period should be used. Suchestimates should be included in the effluent records and reports;

however, they shouldbe clearly identified as estimates, and the method used to obtain these data should bedescribed.

(5) Deviations from the sampling/analysis regime will be noted in the report specified inODCM Part IV.

CY-TM-1 70-300Revision 3Page 91 of 2093.2.2 Gaseous Effluents SURVEILLANCE REQUIREMENTS 3.2.2.1 Dose Rates3.2.2.1.1 The dose rate due to noble gases in gaseouseffluents shall be determined to be within the limitsof Control 2.2.2.1 .a in accordance with the methodsand procedures of the ODCM.3.2.2.1.2 The dose rate of radioactive materials, other thannoble gases, in gaseous effluents shall bedetermined to be within the limits of Control2.2.2.1.b in accordance with methods andprocedures of the ODCM by obtaining representative samples and performing analyses inaccordance with the sampling and analysisprogram, specified in Table 3.2-2.3.2.2.2 Dose, Noble Gas3.2.2.2.1 Cumulative dose contributions from noble gaseffluents for the current calendar quarter and currentcalendar year shall be determined in accordance with the OFFSITE DOSE CALCULATION MANUAL(ODCM) monthly.3.2.2.3 Dose, Tritium and Radionuclides In Particulate Form3.2.2.3.1 Cumulative dose contributions from Tritium andradionuclides in particulate form with half livesgreater than 8 days for the current calendar quarterand current calendar year shall be determined inaccordance with the OFFSITE DOSECALCULATION MANUAL (ODCM) monthly.3.2.2.4 Ventilation Exhaust Treatment 3.2.2.4.1 Doses due to gaseous releases from the unit shallbe projected monthly in accordance with the ODCM.

CY-TM-1 70-300Revision 3Page 92 of 209TABLE 3.2-2Radioactive 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 1 E-6 pCi/ccReactor Building Purge Gas Individual Releases Each Purge Gamma Emitters 1E-4 tCi/cc (2)M H-3 1E-6 gCi/ccUnit Exhaust Vent Release Gas Individual Points Monthly Gamma Emitters 1 E-4 gtCi/cc (2)W Individual (b) 1E-10 pCi/cc (2)Weekly Gamma EmittersMParticulate Monthly Sr-90 1 E-1 1 p.Ci/ccs Composite MMonthly Gross AlphaMnhy Emitters 1 E-1 1 gCi/ccComposite Indv. Gam ma 1E 10 g ic 2Reactor Building Breather SA Emitters (b) E- Ci/cc (2)Particulate SAEitr(bSemi-Annual Sr-90 1 E-1 1 gCi/ccly Gross Alpha 1 E-1 1 pCi/ccEmitters 1E-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, lowerdetection limits may be readily achievable and when nuclides are measured below thestated limits, they should also be reported.

(2) For certain mixtures of gamma emitters, it may be possible to measure radionuclides atlevels near their sensitivity limits when other nuclides are present in the sample at muchhigher levels. Under these circumstances, it will be more appropriate to calculate thelevels of such radionuclides using observed ratios in the gaseous component in thereactor coolant for those radionuclides which are measurable.

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

CY-TM-1 70-300Revision 3Page 93 of 209TABLE 3.2-2 (Cont'd)Radioactive Gaseous Waste Sampling and Analysis ProgramTable Notationa. The LLD is the smallest concentration of radioactive material in a sample that willbe detected with 95% probability with 5% probability of falsely concluding that ablank observation represents a "real" signal.For a particular measurement system (which may include radiochemical separation):

4.66 spLED =E x V x 2.22 x 106 x Y x exp (-XAt)WhereLLD is the lower limit of detection as defined above (as picocurie per unit mass orvolume).Sb is the standard deviation of the background counting rate or of the countingrate 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, andAt 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 bebased on the actual observed variance of the background counting rate or of thecounting 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 typicalcontributions of other radionuclides normally present in the samples.

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

The background countrate 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 thegamma-ray peak used for the quantitative analysis for that radionuclide.

CY-TM-170-300 Revision 3Page 94 of 209TABLE 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-1 44 for particulate emissions.

This list does notmean that only these nuclides are to be detected and reported.

Other peakswhich are measurable and identifiable, together with the above nuclides, shallalso be identified and reported.

Nuclides which are below the LLD for theanalyses shall be reported as "less than" the nuclide's LLD and shall not bereported 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-170-300 Revision 3Page 95 of 2093.2.3 Total Radioactive Effluents 3.2.3.1 Dose Calculation 3.2.3.1.1 Cumulative annual dose contributions from liquidand gaseous effluents shall be determined inaccordance 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 inaccordance with the methodology contained in theODCM.

CY-TM-1 70-300Revision 3Page 96 of 2094.0 PART II REFERENCES 4.1 NUREG-0683, "Final Programmatic Environmental Impact Statement related todecontamination and disposal of radioactive wastes resulting from March 28,1979, accident Three Mile Island Nuclear Station, Unit 2," March 1981, and itssupplements.

4.2 TMI-2 PDMS Technical Specifications, attached to Facility License No. DPR-734.3 Title 10, Code of Federal Regulations, "Energy"4.4 "Statement of Policy Relative to the NRC Programmatic Environmental ImpactStatement on the Cleanup of Three Mile Island Unit 2," dated April 27, 19814.5 Regulatory Guide 1.109, "Calculation of Annual Doses to Man from RoutineReleases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR Part 50, Appendix I," Revision 1, October 19774.6 DOE/TIC-27601, Atmospheric Science and Power Reduction 4.7 TMI-1 Technical Specifications, attached to Facility Operating License No.DPR-504.8 PDMS-SAR CY-TM-170-300 Revision 3Page 97 of 209PART IIIEFFLUENT DATA AND CALCULATIONAL METHODOLOGIES CY-TM-170-300 Revision 3Page 98 of 2091.0 LIQUID EFFLUENT MONITORS1.1 TMI-1 and TMI-2 Liquid Radiation Monitor Set PointsThe liquid effluent off-line monitors are set such that the concentration(s) ofradionuclides 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 LiquidEffluent Release Points and their parameters; Figure 1.1 provides a LiquidRelease Pathway Diagram.To meet the above limit, the alarm/trip set points for liquid effluent monitors andflow measuring devices are set in accordance with the following equation:

• f< C (eq 1.1)F+f -Where:C = ten times the effluent concentration of 10 CFR 20 for the site, in giCi/ml.c = the set point, in giCi/ml, of the liquid effluent monitor measuring theradioactivity concentration in the effluent line prior to dilution and release.The set point is inversely proportional to the maximum volumetric flow of theeffluent line and proportional to the minimal volumetric flow of the dilutionstream plus the effluent stream. The alert set point value is set to ensurethat advance warning occurs prior to exceeding any limits. The high alarmset point value is such that if it were exceeded, it would result inconcentrations exceeding ten times the 10 CFR 20 concentrations for theunrestricted area.f = flow set point as measured at the radiation monitor location, in volume perunit time, but in the same units as F below.F = flow rate of dilution water measured prior to the release point, in volume perunit time.The set point concentration is reduced such that concentration contributions frommultiple release points would not combine to exceed ten times 10 CFR 20concentrations.

The set point concentration is converted to set point scale unitsusing appropriate radiation monitor calibration factors.This section of the ODCM is implemented by the Radiation Monitor System SetPoints procedure and, for batch releases, the Releasing Radioactive LiquidWaste procedure.

CY-TM-1 70-300Revision 3Page 99 of 2091.2 TMI Liquid Effluent Release Points and Liquid Radiation Monitor DataTMI-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 inTable 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 utilizeRM-L12, and RM-L7 for release of liquid waste.1.2.1 RM-L6RM-L6 is an off-line system, monitoring radioactive batch discharges from the TMI-1 liquid radwaste system (see Figure 1.1). These batchreleases 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 than10%, of ten times the 10 CFR 20 concentrations

[20% for H-3] toradionuclide 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 ratescalculated for each liquid batch release, per the approved plantprocedure.

Two Dilution Factors (DF) are calculated to ultimately calculate the batchrelease flow rate. These two DF's are calculated to insure eachradionuclide released to the unrestricted area is less than 10 percent often times the 10CFR20 radionuclide concentrations, (20% for H-3), andto ensure each liquid batch release boron concentration to the river willnot exceed 0.7 ppm.The maximum release flow rate is then calculated by dividing the mostrestrictive (largest)

DF into 90 percent of the current dilution flow rate ofthe Mechanical Draft Cooling Tower (MDCT). This conservative flowrate is then multiplied by 0.9 for the allowable flow rate.* Calculation of the 10CFR20 concentration DF:DFI = :-Y (SA1) -(10% [20% for H-3] often times the IOCFR20concentration)

SA = Specific Activity of each identified radionuclide

• Calculation of Boron DF:DF2= Actual Tank Boron Concentration

+ 0.7.

CY-TM-170-300 Revision 3Page 100 of 209Maximum release flow rate calculation:

Max Flow = [(MDCT flow gpm

• 0.9) -(Most Restrictive DF)] *0.9The dilution flow rate used is the current flow rate at the site. Theminimum dilution flow rate is 5000 gpm per the TMI-1 FSAR. Thisensures this batch release will meet the following equation.

YX(CI/Xi)

+ (CH-3/2XH-3)

< 0.1, (eq 1.2)Where: Ci = diluted concentration of the ith radionuclide, other than H-3Xi= Ten times the concentration for that radionuclide in theunrestricted area (10 CFR 20, App. B, Table 2, Col. 2). Avalue of 3E-3 jtCi/ml for dissolved and entrained noble gasesshall be used.CH.3 = diluted concentration of H-3XH-3 = Ten times the concentration for H-3 in the restricted area (10CFR 20, App. B, Table 2, Col. 2).The set points for RM-L6 are based on the maximum release rate (30gpm), a minimum dilution flow (5000 gpm), and 25% of ten times the1OCFR20 concentration for Cs-1 37, which is the most limitingradionuclide at a concentration of 1.OE-5 uCi/ml. These inputs are usedin Equation 1.1 to determine the RM-L-6 High Alarm setpoint for allradionuclides being released.

A high alarm on RM-L-6 will close valveWDL-V-257 and terminate any WECST releases to the environment.

1.2.2 RM-L12RM-L12 is an off-line system, monitoring periodic combined releasesfrom the Industrial Waste Treatment System/Industrial Waste Filtration System (IWTS/IWFS).

The input to IWTS/IWFS originates in TMI-2sumps, (see Figures 1.1 and 1.2) and the TMI-1 Turbine Building sump(see Figure 1.1). The set points are based on the maximum release ratefrom both IWTS and IWFS simultaneously, (see Figure 1.1) a minimumdilution flow rate, and 50% of ten times the 10CFR20 concentration forCs-1 37, which is the most limiting radionuclide at a concentration of1E-5 ýtCi/ml.

These inputs are used in equation 1.1 to determine theRM-L12 High Alarm set point for all radionuclides being released.

Ahigh alarm on RM-L12 will close IWTS and IWFS release valves and triprelease pumps to stop the release.

CY-TM-1 70-300Revision 3Page 101 of 2091.2.3 RM-L1ORM-L1O was a Nal detector submerged in the TMI-1 Turbine BuildingSump. This detector has been removed from service.1.2.4 RM-L7RM-L7 is not an ODCM required liquid radiation monitor.

RM-L7 is anoff-line system, monitoring the TMI outfall to the Susquehanna River(see Figures 1.1 and 1.2). This monitor is the final radiation monitor forTMI-1 and TMI-2 normal liquid effluent releases.

1.3 Control of Liquid ReleasesTMI liquid effluent releases are controlled to less than ten times the 1OCFR20concentrations by limiting the percentage of this limit allowable from the two TMIliquid release points. RM-L6 and effluent sampling limit batch releases to lessthan or equal to 25% for all radionuclides, and RM-L12 and effluent samplinglimit 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 tofurther ensure that TMI liquid effluent releases are less than ten times the1OCFR20 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 Table3.2-1 or ODCM Part II, Table 3.2-1. The results of analyses are used with thecalculational methods in Section 1.1, to assure that the concentration at the pointof release is maintained within the ODCM Part I Control 2.2.1.1, and ODCM PartII 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. Theresults 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 releasewere maintained within the ODCM Part I Control 2.2.1.1, and ODCM Part IIControl 2.2.1.1.The radioactivity concentration of liquids discharged from continuous releasepoints are determined by collection and analysis of samples in accordance withODCM Part I Table 3.2-1, or ODCM Part II Table 3.2-1. The results of theanalysis are used with the calculational methods of the ODCM to assure that theconcentration at the point of release is maintained within the ODCM Part IControl 2.2.1.1, and ODCM Part II Control 2.2.1.1.

CY-TM-170-300 Revision 3Page 102 of 209TABLE 1.1TMI Liquid Release Point and Liquid Radiation Monitor DataRELEASELIQUID RADIATION LIQUID RELEASE TERMINATION MONITOR POINT (Maximum DISCHARGE FLOW INTERLOCK (DETECTOR)

LOCATION Volume) RECORDER (YES/NO)

VALVESRM-L6 281' Elevation WECST Batch YES(Nal) TMI-1 Auxiliary Bldg Releases (8000 gal.) WDL-V257RM-L7 South end of TMI-1 Station Discharge YES(Nal) MDCT TMI-1 and SR-FT-146 WDL-V257** TMI-2, *WDL-R-1 311YESIWTS/IWFS IW-V73,RM-L12 IWFS Building NW Continuous Releases IW-FT-342/

IW-P16,17,18 (Nal) Corner (300,000/

IW-FT-373 80,000 gal.) IW-V279,I_ IW-P29,30

• WDL-R-1311 has been flanged off as a TMI-2 liquid outfall.** RM-L7 is not an ODCM required liquid radiation monitor.

CY-TM-170-300 Revision 3Page 103 of 209TABLE 1.2TMI-2 Sump Capacities TotalCapacity GallonsSump Gallons per InchTurbine Building Sump 1346 22.43Circulating Water Pump House Sump 572 10.59Control Building Area Sump 718 9.96Tendon Access Galley Sump 538 9.96Control to Service Building Sump 1346 22.43Contaminated Drain Tank Room Sump 135 3.80Chlorinator House Sump ........Water Treatment Sump** 1615 22.43Air Intake Tunnel Normal Sump 700 ----Air Intake Tunnel Emergency Sump 100000 766.00Condensate Polisher Sump* 2617 62.31Sludge Collection Sump** 1106 26.33Heater Drain Sump ----.....

Solid Waste Staging Facility Sump 1476 24.00Auxiliary Building Sump 10102 202.00Decay Heat Vault Sump 479 10.00Building 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-1 70-300Revision 3Page 104 of 209FIGURE 1-1TMI-1 Liquid Effluent PathwaysPage 1 of 1 CY-TM-1 70-300Revision 3Page 105 of 209FIGURE 1.2TMI-2 Liquid Effluent PathwaysCONTROL CONTROL &BUILDING SERVICESUMP AREA SUMPINDUSTRIAL WASTETREATMENT SYSTEMC -- COMPOSITE SAMPLER CY-TM-1 70-300Revision 3Page 106 of 2092.0 LIQUID EFFLUENT DOSE ASSESSMENT 2.1 Liquid Effluents

-10 CFR 50 Appendix IThe dose from liquid effluents results from the consumption of fish and drinkingwater. The location of the nearest potable water intake is PP&L Brunner IslandSteam Electric Station located downstream of TMI. The use of the flow of theSusquehanna River as the dilution flow is justified based on the complete mixingin the river prior to the first potable water supply, adequately demonstrated byflume tracer die studies and additional liquid effluent release studies conducted using actual TMI-1 tritium releases.

Other pathways contribute negligibly atThree Mile Island. The dose contribution from all radionuclides in liquid effluents released to the unrestricted area is calculated using the following expression:

Dose j (At) X () X AW ij X- + (AF ij X f X 1 (eq 2.1)Doej. AtX(C) LAWJFR) FD DFWhere:Dose j = the cumulative dose commitment to the total body or any organ, j, fromthe liquid effluents for the total time period, in mrem.At = the length of the time period of actual releases, over which Ci and f areaveraged for all liquid releases, in hours.C = the average concentration of radionuclide, i, in undiluted liquid effluentduring time period At from any liquid release, in ýLCi/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 usedin dose calculations.

f = undiluted liquid waste flow, in gpm.FD = plant dilution water flowrate during the period of release, in gpmFR = actual river flowrate during the period of release or average riverlowrate for the month the release is occurring, in gpm.DF = dilution factor as a result of mixing effects in the near field of thedischarge structure of 0.2 (NUREG 0133) or taken to be 5 based on theinverse of 0.2.AWij and AFij = the site-related ingestion dose commitment factor to the totalbody or any organ, j, for each identified principle gamma andbeta emitter, in mrem/hr per pCi/ml. AW is the factor for thewater pathway and AF is the factor for the fish pathway.

CY-TM-1 70-300Revision 3Page 107 of 209Values for AWij are determined by the following equation:

AWij = (1.14E5) x (Uw) x (DFij) (eq 2.2)Where:1.14E5 = (1.0E6 pCilpjCi) x (1.0E3 mi/kg) + (8760 hrlyr)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 bodyand 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 aboveUf = 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 bodyand 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/Lfrom Table 2.2 (Reg. Guide 1.109, Rev. 1).2.2 TMI Liquid Radwaste System Dose Calcs Once Per MonthODCM 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 shallbe used to reduce the radioactive materials in liquid wastes prior to theirdischarge when the monthly projected doses due to the liquid effluent releasesfrom each unit to unrestricted areas would exceed 0.06 mrem to the total body or0.2 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 thequarter-to-date will be divided by the number of days into the quarter andmultiplied by 31. Also, this dose projection shall include the estimated dose dueto any anticipated unusual releases during the period for which the projection ismade. If this projected dose exceeds 0.06 mrem total body or 0.2 mrem anyorgan, appropriate portions of the Liquid Radwaste Treatment System, as CY-TM-170-300 Revision 3Page 108 of 209defined in Section 3.1, shall be used to reduce radioactivity levels prior torelease.At the discretion of the ODCM Specialist, time periods other than the currentquarter-to-date may be used to project doses if the dose per day in the currentquarter-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 sitespecific data are used where applicable.

As an alternative dose calculational methodology TMI calculates doses usingSEEDS (simplified environmental effluent dosimetry system).The onsite and SEEDS calculational models use actual liquid release data withactual monthly Susquehanna River flow data to assess the dispersion of effluents in the river.

CY-TM-1 70-300Revision 3Page 109 of 209TABLE 2.1Liquid Dose Conversion Factors (DCF): DF1jPage 1 of 3Ingestion Dose Factors for Adults*(MREM Per PCI Ingested)

NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLIH 3 NO DATA 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07C 14 2.84E-06 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07NA 24 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06CR.51 NO DATA NO DATA 2.66E-09 1.59E-09 5.86E-10 3.53E-09 6.69E-07MN 54 NO DATA 4.57E-06 8.72E-07 NO DATA 1.36E-06 NO DATA 1.40E-05............... ....... .. .. .. ...........

..... ..........

... ... .........

.. .. .................

..... .. ..........

.. ...... .............

......... ....MN 56 NO DATA 1.151E-07 2.04E-08 NO DATA 1.46E-07 NO DATA 3.67E-06FE 55 2.75E-06 1.90E-06 4.43E-07 NO DATA NO DATA 1.06E-06 1.09E-06FE 59 4.34E-06 1.02E-05 3.91E-06 NO DATA NO DATA 2.85E-06 3.40E-05CO-58 NO DATA 7.45E-07 1.67E-06 NO DATA NO DATA NO DATA 1.51E-05CO 60 NO DATA 2.14E-06 4.72E-06 NO DATA NO DATA NO DATA 4.02E-05NI 63 1.30E-04 9.011E-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-06CU 64 NO DATA 8.33E-08 3.91 E-08 NO DATA 2.1OE-07 NO DATA 7.1OE-06ZN 65 4.84E-06 1.54E-05 6.96E-06 NO DATA 1.03E-05 NO DATA 9.70E-06.. .............................................................................................................................................................................

ZN 69 1.03E-08 1.97E-08 1.37E-09 NO DATA 1.28E-08 NO DATA 2.96E-09BR 83 NO DATA NO DATA 4.02E-08 NO DATA NO DATA NO DATA 5.79E-08BR 84 NO DATA NO DATA 5.21E-08 NO DATA NO DATA NO DATA 4.09E-13..............

..............

.............

..............

.............

..............

..............

.............

..............

.............

..............

.............

BR-85 NO DATA NO DATA 2.14E-09 NO DATA NO DATA NO DATA LT E-24RB 86 NO DATA 2.11E-05 9.83E-06 NO DATA NO DATA NO DATA 4.16E-06RB 88 NO DATA 6.05E-08 3.21 E-08 NO DATA NO DATA NO DATA 8.36E-19RB.89 NO DATA 4.01E-08 2.82E-08 NO DATA NO DATA NO DATA 2.33E-21SR 89 3.08E-04 NO DATA 8.84E-06 NO DATA NO DATA NO DATA 4.94E-05SR 90 7.58E-03 NO DATA 1.86E-03 NO DATA NO DATA NO DATA 2.19E-04..R. .1 0-6E- .. -NO DATA' 2.29E-07 NO DATA NO DATA NO DATA 2.70E-05-----------------------------------------

2;2 9-f *...........---......

...... ..........*- -------SR 92 2.15E-06 NO DATA 9.30E-08 NO DATA NO DATA NO DATA 4.26E-05Y 90 9.62E-09 NO DATA 2.58E-10 NO DATA NO DATA NO DATA 1.02E-04 CY-TM-1 70-300Revision 3Page 110 of 209TABLE 2.1Liquid Dose Conversion Factors (DCF): DF=jPage 2 of 3Ingestion Dose Factors for Adults*(MREM Per PCI Ingested)

NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLIY 91M 9.09E-11 NO DATA 3.52E-12 NO DATA NO DATA NO DATA 2.67E-10Y 91 1.41 E-07 NO DATA 3.77E-09 NO DATA NO DATA NO DATA 7.76E-05Y 92 8.45E-10 NO DATA 2.47E-11 NO DATA NO DATA NO DATA 1.48E-05Y 93 2.68E-09 NO DATA 7.40E-11 NO DATA NO DATA NO DATA 8.50E-05ZR 95 3.04E-08 9.75E-09 6.60E-09 NO DATA 1.53E-08 NO DATA 3.09E-05ZR 97 1.68E-09 3.39E-10 1.55E-10 NO DATA 5.12E-10 NO DATA 1.05E-04NB.95 6.22E-09 3.46E-09 1.86E-09 NO DATA 3.42E-09 NO DATA 2.10E-05MO 99 NO DATA 4.31E-06 8.20E-07 NO DATA 9.76E-06 NO DATA 9.99E-06TC 99M 2.47E-10 6.98E-10 8.89E-09 NO DATA 1.06E-08 3.42E-10 4.13E-07.. .............................................................................................................................................................................

TC 101 2.54E-10 3.66E-10 3.59E-09 NO DATA 6.59E-09 1.87E-10 1.1OE-21RU 103 1.85E-07 NO DATA 7.97E-08 NO DATA 7.06E-07 NO DATA 2.16E-05RU 105 1.54E-08 NO DATA 6.08E-09 NO DATA 1.99E-07 NO DATA 9.42E-06RU 106 2.75E-06 NO DATA 3.48E-07 NO DATA 5.31 E-06 NO DATA 1.78E-04AG 110M 1.60E-07 1.48E-07 8.79E-08 NO DATA 2.91 E-07 NO DATA 6.04E-05SB 125 1.79E-06 2.00E-08 4.26E-07 1.82E-09 0.0 1.38E-06 1.97E-05TE 125M 2.68E-06 9.71 E-07 3.59E-07 8.06E-07 1.09E-05 NO DATA 1.07E-05TE.127M 6.77E-06 2.42E-06 8.25E-07 1.73E-06 2.75E-05 NO DATA 2.27E-05TE 127 1.10E-07 3.95E-08 2.38E-08 8.15E-08 4.48E-07 NO DATA 8.68E-06TE 129M 1.15E-05 4.29E-06 1.82E-06 3.95E-06 4.80E-05 NO DATA 5.79E-05.. .............................................

.................................

• ..............................................................................................

TE 129 3.14E-08 1.18E-08 7.65E-09 2.41 E-08 1.32E-07 NO DATA 2.37E-08TE 131M 1.73E-06 8.46E-07 7.05E-07 1.34E-06 8.57E-06 NO DATA 8.40E-05TE 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-05I 130 7.56E-07 2.23E-06 8.80E-07 1.89E-04 3.48E-06 NO DATA 1.92E-06I 131 4.16E-06 5.95E-06 3.41E-06 1.95E-03 1.02E-05 NO DATA 1.57E-06I. 132 2.03E-07 E-07 5.ZE-07 1.90E-07 1.90E-05 8.65E-07 NO DATA 1.02E-07I 133 1.42E-06 2.47E-06 7.53E-07 3.63E-04 4.31 E-06 NO DATA 2.22E-06I 134 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 NO DATA 2.51 E-10 CY-TM-1 70-300Revision 3Page 111 of 209TABLE 2.1Liquid Dose Conversion Factors (DCF): DFIjPage 3 of 3Ingestion Dose Factors for Adults*(MREM Per PCI Ingested)

NUCLIDE BONE LIVER T. BODY THYROID KIDNEY LUNG GI-LLII 135 4.43E-07 1.16E-06 4.28E-07 7.65E-05 1.86E-06 NO DATA 1.31 E-06CS 134 6.22E-05 1.48E-04 1.21E-04 NO DATA 4.79E-05 1.59E-05 2.59E-06CS 136 6.51 E-06 2.57E-05 1.85E-05 NO DATA 1.43E-05 1.96E-06 2.92E-06CS.137 7.97E-05 1.09E-04 7.14E-05 NO DATA 3.70E-05 1.23E-05 2.11E-06CS 138 5.52E-08 1.09E-07 5.40E-08 NO DATA 8.01E-08 7.91E-09 4.65E-13BA 139 9.70E-08 6.91E-11 2.84E-09 NO DATA 6.46E-11 3.92E-11 1.72E-07BA 140 2.03E-05 2.55E-08 1.33E-06 NO DATA 8.67E-09 1.46E-08 4.18E-05BA 141 4.71E-08 3.56E-11 1.59E-09 NO DATA 3.31E-11 2.02E-11 2.22E-17BA 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-05LA 142 1.28E-10 5.82E-11 1.45E-11 NO DATA NO DATA NO DATA 4.25E-07CE 141 9.36E-09 6.33E-09 7.18E-10 NO DATA 2.94E-09 NO DATA 2.42E-05CE-143 1.65E-09 1.22E-06 1.35E-10 NO DATA 5.37E-10 NO DATA 4.56E-05CE 144 4.88E-07 2.04E-07 2.62E-08 NO DATA 1.21 E-07 NO DATA 1.65E-04PR 143 9.20E-09 3.69E-09 4.56E-10 NO DATA 2.13E-09 NO DATA 4.03E-05PR.144 3.01 E-11 1.25E-11 1.53E-12 NO DATA 7.05E-12 NO DATA 4.33E-18ND 147 6.29E-09 7.27E-09 4.35E-10 NO DATA 4.25E-09 NO DATA 3.49E-05W 187 1.03E-07 8.61 E-08 3.01E-08 NO DATA NO DATA NO DATA 2.82E-05N-.23 9 ... --- ........ 1" .......-E.. .D , ....3"."... E'"0 NO D A -.6E- ., ...NO... D T *0E"-"5Dose factors of internal exposure are for continuous intake over a one-year period andinclude 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 fromNUREG-0172.

CY-TM-1 70-300Revision 3Page 112 of 209TABLE 2.2Bloaccumulation

Factors, BF,Bioaccumulation Factors to be Used in the Absence of Site-Specific Data*(pCi/kg per pCi/liter)

ELEMENT FRESHWATER FISH INVERTEBRATE H 9.OE-01 9.OE-01C 4.6E+03 9.1E+03NA 1.OE+02 2.OE+02CR 2.OE+02 2.OE+03MN 4.OE+02 9.OE+04FE 1.OE+02 3.2E+03CO 5.OE+01 2.OE+02NI 1.OE+02 1.OE+02CU 5.OE+01 4.OE+02ZN 2.OE+03 1.OE+04BR 4.2E+02 3.3E+02RB 2.OE+03 1.OE+03SR 3.OE+01 1.OE+02Y 2.5E+01 1.OE+03ZR 3.3E+00 6.7E+00NB 3.OE+04 1.OE+02MO 1.OE+01 1.OE+01TC 1.5E+01 5.OE+00RU 1.OE+01 3.OE+02RH 1.OE+01 3.OE+02***AG-110m 2.30E+1 7.70E+2**SB 1.OE+00 1.OE+00TE 4.OE+02 6.1 E+03I 1.5E+01 5.OE+00CS 2.OE+03 1.OE+03BA 4.OE+00 2.OE+02LA 2.5E+01 1.OE+03CE 1.OE+00 1.OE+03PR 2.5E+01 1.OE+03ND 2.5E+01 1.OE+03W 1.2E+03 1.OE+01NP 1.OE+01 4.OE+02* Bioaccumulation factor values are taken from Reg. Guide 1.109 (Rev. 1), Table A-1j.** Sb bioaccumulation factor value is taken from EPRI NP-3840.Ag bioaccumulation factor value is taken from Reg. Guide 1.109 (Rev. 0), Table A-8.

CY-TM-170-300 Revision 3Page 113 of 2093.0 TMI LIQUID EFFLUENT WASTE TREATMENT SYSTEM3.1 TMI-1 Liquid Effluent Waste Treatment System3.1.1 Description of the Liquid Radioactive Waste Treatment System (seeFigure 3.1)Reactor Coolant Traina. 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 Traina. 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 70-300Revision 3Page 114 of 209b. 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 System3.2.1 The TMI-1 Liquid Waste Treatment System as described in Section 11of the TMI-1 Final Safety Analysis Report is considered to be operablewhen one of each of the following pieces of equipment is available toperform its intended function:

a) Miscellaneous Waste Evaporator (WDL-Z1 B) or Reactor CoolantEvaporator (WDL-Z1 A)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 aremade through the Waste Evaporator Condensate Storage Tanks. Toprovide thorough mixing and a representative sample, the contents ofthe tank are recirculated using one of the Waste Evaporator Condensate Transfer Pumps.3.3 TMI-2 Liquid Effluent Waste Treatment System3.3.1 Description of the TMI-2 Liquid Radioactive Waste Treatment SystemThe TMI-2 Liquid Radioactive Waste Treatment System has been out ofservice since the TMI-2 Accident in 1979. TMI-2 Liquid Radioactive Waste is processed by the TMI-1 system described in Section 3.1 priorto release.

In addition, TMI-2 releases water from various sumps andtanks to the river (see Figures 1.1 and 1.2). These processes aregoverned by plant procedures that encompass proper sampling, sampleanalysis, and radiation monitoring techniques.

CY-TM-1 70-300Revision 3Page 115 of 209FIGURE 3.1TMI-1 Liquid Radwaste CY-TM-170-300 Revision 3Page 116 of 209FIGURE 3.2TMI-1 Liquid Waste Evaporators DIST.

CY-TM-1 70-300Revision 3Page 117 of 2094.0 GASEOUS EFFLUENT MONITORS4.1 TMI-1 Noble Gas Monitor Set PointsThe gaseous effluent monitor set points are established for each gaseouseffluent radiation monitor to assure concentrations of radionuclides in gaseouseffluents 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 pointconcentration in the following two equations:

500> >. (c1)(F)(K1)(Dv) (eq 4.1.1)and3000 > I (cq)(LI + 1.1 Mi)(Dv)(F)

(eq 4.1.2)Where: ci = set point concentration based on Xe-1 33 equivalent, in iCi/ccF =gaseous effluent flowrate at the monitor, in cc/secKi =total body dose factor, in mrem/yr per p.Ci/m3 from Table 4.3Dv = highest sector annual average gaseous atmospheric dispersion factor(X/Q) at or beyond the unrestricted area boundary, in sec/m3, fromTable 4.4 for station vent releases and Table 4.5 for all other releases, (Condenser off gas, ESF FHB, and ground releases).

Maximum valuespresently used are 1.27E-6 sec/m3 at sector SE for station vent, and1.40E-5 sec/M3 at sector E for all other releases.

Li= skin dose factor due to beta emissions from radionuclide i, in mrem/yrper jLCi/m3 from Table 4.3.MI = air dose factor due to gamma emissions from radionuclide i, in mrad/yrper p.Ci/m3 from Table 4.3.1.1 = mrem skin dose per mrad air dose.500 = annual whole body dose rate limit for unrestricted areas, in mrem/yr.3000 = annual skin dose rate limit for unrestricted areas, in mrem/yr.

CY-TM-1 70-300Revision 3Page 118 of 209The set point concentration is further reduced such that the concentration contributions from multiple release points would not combine to exceed ODCMControl 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 SetPoints procedure and the procedure for Releasing Radioactive Gaseous Waste.

CY-TM-170-300 Revision 3Page 119 of 2094.2 TMI-1 Particulate and Radioiodine Monitor Set PointsSet points for monitors which detect radionuclides other than noble gases arealso established to assure that concentrations of these radionuclides in gaseouseffluents 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)(P 1)(Ov) (eq 4.2)Where: c1 = set point concentration based on 1-131 equivalent for radioiodine monitorand Sr-90 for particulate

monitor, in VLCi/ccF = gaseous effluent flow rate at the monitor, in cc/secPi = pathway dose parameter, in mrem/yr per p.Ci/m3 for the inhalation pathway from Table 4.6. The dose factors are based on the actualindividual 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 thaneight days in mrem/yr.Dv = highest sector annual average gaseous dispersion factor (X/Q or D/Q) ator beyond the unrestricted area boundary from Table 4.4 for releasesfrom the station vent and Table 4.5 for all other releases.

X/Q is used forthe inhalation pathway.

Maximum values of X/Q presently used are1.27E-6 sec/m3 for station vent, at sector SE, and 1.40E-5 sec/m3 for allother releases, at sector E.The set point concentration is further reduced such that concentration contributions from multiple release points would not combine to exceed ODCMControl 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 SetPoints procedure and the procedure for Releasing Radioactive Gaseous Waste.

CY-TM-1 70-300Revision 3Page 120 of 2094.3 TMI-2 Gaseous Radiation Monitor Set PointsTMI-2 Gaseous Radiation Monitors have their set points described in TMI PlantProcedure 1101-2.1.

Figure 4.5 provides a gaseous effluent release pathwaydiagram.

Table 4.2 provides TMI-2 Radiation Monitor Data.These set points are set in accordance with the Controls delineated in Part II ofthis ODCM.

CY-TM-170-300 Revision 3Page 121 of 2094.4 TMI-1 Gaseous Effluent Release Points and Gaseous Radiation Monitor DataTMI-1 has eleven (11) required effluent gaseous radiation monitors.

These areRM-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 ExhaustRM-A4 is the radiation monitor for the TMI-1 Fuel Handling BuildingVentilation (see Figures 4.1 and 4.2). RM-A6 is the radiation monitor forthe TMI-1 Auxiliary Building Ventilation (see Figures 4.1 and 4.2). Highalarms on RM-A4 or RM-A6 noble gas channels will initiate shutdown ofthe related building ventilation air supply system. These two radiation monitors concurrently will satisfy requirements for the Station Ventrelease point in place of RM-A8.4.4.2 RM-A8 Station Ventilation ExhaustRM-A8 is the particulate, radioiodine and gaseous radiation monitor forthe TMI-1 Station Ventilation (see Figures 4.1 and 4.2). This in planteffluent radiation monitor also has an associated sampling panel withsampling lines located before the sample filters.

High alarm on RM-A8noble gas low channel will initiate shutdown of the Station Ventilation airsupply systems.

(The Fuel Handling and Auxiliary Building Ventilation).

This radiation monitor satisfies requirements for the Station Vent releasepoint in place of RM-A4 and RM-A6.4.4.3 RM-A5/RM-A15 Condenser Off Gas ExhaustRM-A5 is the gaseous radiation monitor for the TMI-1 Condenser OffGas exhaust (see Figures 4.1 and 4.4). RM-A15 is the back up gaseousradiation monitor for the TMI-1 Condenser Off Gas exhaust (seeFigures 4.1 and 4.4). High alarms on RM-A5 low channel or RM-A15noble gas channels will initiate the MAP-5 Radioiodine Processor Station.

These two radiation monitors together satisfy requirements forthe Condenser Off Gas release point.4.4.4 RM-A7 Waste Gas Decay Tank ExhaustRM-A7 is the gaseous radiation monitor for the TMI-1 Waste Gas Decaytanks (see Figures 4.1 and 4.2). This in plant effluent radiation monitoralso has an associated sampling panel. High alarm on RM-A7 noblegas channel will initiate shutdown of the Waste Gas Decay Tank releasein progress.

This radiation monitor satisfies requirements for batchgaseous releases to the Station Vent release point.

CY-TM-1 70-300Revision 3Page 122 of 2094.4.5 RM-A9 Reactor Building Purge ExhaustRM-A9 is the particulate, radioiodine and gaseous radiation monitor forthe TMI-1 Reactor Building Purge system (see Figures 4.1 and 4.3).This in plant effluent radiation monitor also has an associated samplingpanel with sampling lines located before the sample filters.

High alarmon RM-A9 noble gas low channel will initiate shutdown of the ReactorBuilding Purge System. This radiation monitor satisfies requirements forthe Reactor Building Purge System release point.4.4.6 RM-A14 ESF FHB Ventilation SystemRM-A14 is the gaseous radiation monitor for the TMI-1 Emergency Safeguards Features (ESF) Fuel Handling Building Exhaust system (seeFigures 4.1 and 4.2). This in plant effluent radiation monitor also has anassociated sampling panel with sampling lines located before thesampler filters.

High alarm on RM-A14 noble gas channel will initiateshutdown of the ESF Fuel Handling Building Exhaust System. Thisradiation monitor satisfies requirements for the ESF Fuel HandlingBuilding Exhaust System release point.4.4.7 ALC-RMI-18 Chemical Cleaning Facility (CCF) Ventilation ExhaustALC-RMI-18 is an Victoreen particulate, radioiodine, and gaseousradiation monitor for the Chemical Cleaning building exhaust.

Thismonitor is located in the Chemical Cleaning building on the ground floor,and has an associated sample panel. Sampling for particulate activity isperformed off of the monitor.4.4.8 WHP-RIT-1 Waste Handlinq and Packaging Facility (WHPF) ExhaustWHP-RIT-1 is an Eberline AMS-3 particulate radiation monitor for theTMI WHPF. The monitor is located in the Mechanical Equipment Roomin the WHPF. Sampling for particulate activity is performed off of themonitor.

A high alarm will initiate shutdown of the ventilation air exhaustsystem.4.4.9 RLM-RM-1 Respirator Cleaning and Laundry Maintenance (RLM)FacilityRLM-RM-1 is an Eberline AMS-3 particulate radiation monitor for theTMI RLM Facility.

The monitor is located in the Mechanical Equipment Room in the RLM. Sampling for particulate activity is performed off ofthe monitor.

CY-TM-1 70-300Revision 3Page 123 of 2094.5 TMI-2 Gaseous Effluent Release Points and Gaseous Radiation Monitor DataTMI-2 has three (3) regulatory required gaseous effluent radiation monitors.

These are HP-R-219, HP-R-219A and HP-R-225.

These gaseous releasepoints, radiation

monitors, and sample points are shown in Table 4.2, and variousgaseous effluent pathways are depicted

-in Figure 4.5.4.5.1 HP-R-219 Station Ventilation ExhaustHP-R-219 is a Victoreen particulate and gaseous radiation monitor forthe TMI-2 ventilation exhaust.

This in-plant effluent radiation monitor islocated in the TMI-2 Auxiliary Building 328 foot elevation and has anassociated sample panel.4.5.2 HP-R-219A Station Ventilation ExhaustHP-R-219A is a Victoreen particulate and gaseous radiation monitor forthe TMI-2 ventilation exhaust.

This in-plant effluent radiation monitor islocated 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 forthe TMI-2 Reactor Building Purge Air Exhaust System. This in-planteffluent radiation monitor is located in the TMI-2 Auxiliary Building 328'elevation area.

CY-TM-170-300 Revision 3Page 124 of 2094.6 Control of Gaseous Effluent ReleasesTMI gaseous effluent combined releases are controlled (per ODCM Part I forTMI-1 and ODCM Part II for TMI-2) by effluent sampling and radiation monitor setpoints. These measures assure that releases from the various vents do notcombine to produce dose rates at the site boundary exceeding the mostrestrictive of 500 mrem per year to the total body or 3000 mrem per year to theskin, 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 bythe various vents at any time. The various vent radiation monitor set points areeach based on fractions of the above limits and do not exceed the above limitswhen summed together.

These effluent radiation monitor set points arecalculated 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 torelease by sampling and analyses in accordance with ODCM Part I for TMI-1 andODCM Part II for TMI-2. The results of pre-release analyses are used with thecalculational methods in Sections 4.1 and 4.2 to assure that the dose rates at thesite boundary are maintained below the limits in ODCM Part I for TMI-1 andODCM Part II for TMI-2.Post-release analyses of samples composited from batch and continuous releases are performed in accordance with ODCM Part I for TMI-1 and ODCMPart II for TMI-2. The results of the analyses are used to assure that the doserates at the site boundary are maintained within the limits of ODCM Part I forTMI-1 and ODCM Part II for TMI-2.

CY-TM-170-300 Revision 3Page 125 of 209TABLE 4.1TMI-1 Gaseous Release Point and Gaseous Radiation Monitor DataGASEOUS RELEASERADIATION GASEOUS (F) TERMINATION MONITOR RELEASE FLOW INTERLOCK (YES/NO)(DETECTOR)

LOCATION POINT RECORDER VALVESYES306 Elevation Fuel Hand. AH-E-1 0RM-A4 Auxiliary Bldg. Building AH-FR-149 AH-D-120Exhaust AH-D-121AH-D-122306' Elevation Auxiliary YESRM-A6 Auxiliary Bldg. Building AH-FR-150 AH-E-11ExhaustYESWDG-V47RMA-8/9 Bldg. Station AH-FR-149 AH-E-10RA Nar Vent & AH-FR-1 50 AH-E-1 1Exhaust Starts MAP-5Radioiodine Sampler322' Elevation Condenser YESRM-A5 Second Floor Off Gas VA-FR-1 113 Starts MAP-5Turbine Bldg. Exhaust Radioiodine Sampler322' Elevation Condenser YESRM-A1 5 Second Floor Off Gas VA-FR-1 113 Starts MAP-5Turbine Bldg. Exhaust Radioiodine SamplerWaste GasRM-A7 306' Elevation Decay WDG-FR-123 YESAuxiliary Bldg. Tanks WDG-V47(A,B,C)Reactor YESReactor AH-V-1AINB/C/D RM-A9 RMA-8/9 Bldg. Building AH-FT-909/

WDG-534/535 Near BWST Purge AH-FR-148 Starts4MAP-ExhaustStarts MAP-5Exhaust Radioiodine Sampler331' Elevation ESF Fuel NORM-A14 ESF FHB Handling AH-UR-1104A/B ManualOutside Chem. Building ActionsAddition Bldg. Exhaust CY-TM-1 70-300Revision 3Page 126 of 209TABLE 4.1 (Cont'd)TMI-1 Gaseous Release Point and Gaseous Radiation Monitor DataRELEASEGASEOUS TERMINATION RADIATION INTERLOCK MONITOR GASEOUS (YES/NO)(DETECTOR)

LOCATION RELEASE POINT VALVESChemical CCB ExhaustALC-RMI-18 Cleaning Bldg. System NONE304' Elevation (Typical flow rateis 10,000 cfm)WHPF WHPF Exhaust YESWHP-RIT-1 Mechanical System WHPF Ventilation Equipment Room (Typical flow rate Tripsis 7,500 cfm)RLM ExhaustRLM-RM-1 RLM-Mechanical System NONEEquipment Room (Typical flow rateI is 900 cfm)TABLE 4.2TMI-2 Gaseous Release Point and Gaseous Radiation Monitor DataRELEASEGASEOUS TERMINATION RADIATION GASEOUS INTERLOCK MONITOR RELEASE (YES/NO)(DETECTOR)

LOCATION POINT VALVES328' Elevation StationHP-R-219 Auxiliary Vent NONEBuilding Exhaust328' Elevation Station VentHP-R-219A Auxiliary Exhaust NONEBuilding328' Elevation Reactor BldgHP-R-225 Auxiliary Building Purge Exhaust NONEDuct "A" CY-TM-170-300 Revision 3Page 127 of 209TABLE 4.3Dose Factors for Noble Gases and Daughters*

Gamma BetaTotal Body Skin DoseDose Factor(b)

Gamma Air Beta AirFactor(a)

Li Dose Factor Dose FactorKi (mrem/yr Mi Ni(mrem/yr per per (mrad/yr per (mrad/yr perRadionuclide pci/m3) ýLCi/m3) gCi/m3) ýiCi/m3)Kr-83m 7.56E-02**

--- 1.93E+01 2.88E+02Kr-85m 1.17E+03 1.46E+03 1.23E+03 1.97E+03Kr-85 1.61 E+01 1.34E+03 1.72E+01 1.95E+03Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03Kr-89 1.66E+04 1.01 E+04 1.73E+04 1.06E+04Kr-90 1.56E+04 7.29E+03 1.63E+04 7.83E+03Xe-131 m 9.15E+01 4.76E+02 1.56E+02 1.11E+03Xe-133m 2.51 E+02 9.94E+02

.3.27E+02 1.48E+03Xe-133 2.94E+02 3.06E+02 3.53E+02 1.05E+03Xe-135m 3.12E+03 7.11 E+02 3.36E+03 7.39E+02Xe-135 1.81 E+03 1.86E+03 1.92E+03 2.46E+03Xe-137 1.42E+03 1.22E+04 1.51 E+03 1.27E+04Xe-138 8.83E+03 4.13E+03 9.21E+03 4.75E+03Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03Dose factors are for immersion exposure in uniform semi-infinite cloud of noble gasradionuclides that may be detected in gaseous effluents.

Dose factor values are takenfrom Regulatory Guide 1.109 (Rev. 1), Table B-1.7.56E-02

= 7.56 x 10-2.(a) Total body dose factor for gamma penetration depth of 5 cm into the body.(b) Skin dose factor at a tissue depth or tissue density thickness of 7 mg/cm2.

CY-TM-1 70-300Revision 3Page 128 of 209TABLE 4.4Atmospheric Dispersion Factors for Three Mile IslandSTATION VENTSECTOR AVERAGE X/Q (IN SEC/M3)DISTANCE(IN SEASON -ANNUAlSECTOR 610 2413 4022 5631 7240 12067 24135 40225 56315 72405N 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.OOE-08 7.28E-09NNE 4.06E-07 1.1OE-06 5.84E-07 3.42E-07 2.17E-07 9.35E-08 3.58E-08 1.84E-08 1.20E-08 8.68E-09NE 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-08ENE 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-08E 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-08ESE 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-09SE 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-09SSE 7.20E-07 7.10E-07 4.94E-07 2.74E-07 1.83E-07 8.96E-08 3.36E-08 1.71E-08 1.1OE-08 7.90E-09S 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-09SSW 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-09SW 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-09WSW 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-09W 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-09WNW 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-09NW 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-0911 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-09STATION VENT DISTANCESECTOR AVERAGE D/Q (IN M2) (IN METERS) SEASON -ANNUALSECTOR 610 2413 4022 5631 7240 12067 24135 40225 56315 72405N 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-12NNE 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-12NE 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.OOE-12ENE 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-12E 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-12ESE 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-11SE 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-11SSE 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-121 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-12SSW 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-12SW 1.78E-09 4.57E-10 5.62E-10 2.78E-10 1.59EA10 5.77E-11 1.77E-11 7.17E-12 3.86E-12 2.40E-12WSW 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-12W 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-12WNW 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-12NW 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 TNNW 2.61E-09 6.15E-10 3.47E-10 1.70E-10 1.25E-10 6.32E-11 2.02E-11 8.24E-12 4.43E-12 2.75E-12DATA FROM 2006-2010 USED IN CALCULATIONS CY-TM-1 70-300Revision 3Page 129 of 209TABLE 4.5Atmospheric Dispersion Factors for Three Mile IslandGROUND RELEASE0rf'-TrD AIr'DAfr-C VIt' I1M ccr-IRA3\DISTANCEIlkI IjACT C ZMeAr 1MI AKIKIHAlSECTOR 610 2413 4022 5631 7240 12067 24135 40225 56315 72405N 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-08NNE 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-08NE 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-08ENE 1.31E-05 1.65E-06 8.26E-07 5.25E-07 3.75E-07 1.91E-07 7.72E-08 4.00E-08 2.61E-08 1.90E-08E 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-08ESE 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-08SE 1.16E-05 1.43E-06 6.99E-07 4.38E-07 3.1OE-07 1.55E-07 6.18E-08 3.18E-08 2.06E-08 1.49E-08SSE 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-08S 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-09SSW 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-09SW 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-09WSW 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-09W 7.42E-06 9.56E-07 4.70E-07 2.96E-07 2.10E-07 1.05E-07 4.16E 2.13E-08 1.37E-08 9.93E-09WNW 7.75E-06 9.78E-07 4.85E-07 3.07E-07 2.19E-07 1.10E-07 4.42E-08 2.28E-08 1.48E-08 1.08E-08NW 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-08NNW 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-09GROUND RELEASE DISTANCESECTOR AVERAGE D/Q (IN M2 (IN METERS) SEASON -ANNUALSECTOR 610 2413 4022 5631 7240 12067 24135 40225 56315 72405N 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-12NNE 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-12NE 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-12ENE 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-12E 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-12ESE 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-12SE 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-11SSE 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-12S 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-12SSW 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-12SW 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-12WSW 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-12W 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-12WNW 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-12NW 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-12NNW 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-12DATA FROM 2006 -2010 USED IN CALCULATIONS CY-TM-1 70-300Revision 3Page 130 of 209TABLE 4.6Dose Parameters for Radioiodines and Radioactive Particulate in Gaseous Effluents*

CRITICAL ORGAN CRITICAL ORGANNUCLIDE ORGAN FACTOR Pi** NUCLIDE ORGAN FACTORH-3**C-14NA-24P-32CR-51MN-54MN-56FE-55FE-59CO-58CO-60NI-63NI-65CU-64ZN-65ZN-69BR-83BR-84BR-85RB-86RB-88RB-89SR-89SR-90SR-91SR-92Y-90Y-91MY-91Y-92Y-93ZR-95ZR-97NB-95MO-99TC-99MTC-101TOTAL BODYBONETOTAL BODYBONELUNGLUNGGI-LLILUNGLUNGLUNGLUNGBONEGI-LLIGI-LLILUNGGI-LLITOTAL BODYTOTAL BODYTOTAL BODYLIVERLIVERLIVERLUNGBONEGI-LLIGI-LLIGI-LLILUNGLUNGGI-LLIGI-LLILUNGGI-LLILUNGLUNGGI-LLILUNG3.04E-079.70E-064.35E-067.04E-044.59E-064.26E-043.33E-053.OOE-053.43E-042.99E-041.91 E-032.22E-042.27E-059.92E-062.69E-042.75E-061.28E-071.48E-076.84E-095.36E-051.52E-079.33E-085.89E-042.73E-024.70E-056.55E-057.24E-057.60E-077.1OE-046.46E-051.05E-046.03E-049.49E-051.66E-043.66E-051.30E-061.58E-071.12E+033.59E+041.61 E+042.60E+061.70E+041.58E+061.23E+051.11E+051.27E+061.11E+067.07E+068.21 E+058.40E+043.67E+049.95E+051.02E+044.74E+025.48E+022.53E+011.98E+055.62E+023.45E+022.16E+061.01 E+081.74E+052.42E+052.68E+052.81 E+032.63E+062.39E+053.89E+052.23E+063.51 E+056.14E+051.35E+054.81 E+035.85E+02RU-103RU-105RU-106AG-110MTE-125MSB-125TE-127MTE-127TE-129MTE-129TE-131MTE-131TE-1321-1301-1311-1321-1331-1341-135CS-1 34CS-1 36CS-1 37CS-138BA-1 39BA-140BA-141BA-142LA-140LA-142CE-141CE-143CE-144PR-143PR-144ND-147W-187NP-239LUNGGI-LLILUNGLUNGLUNGLUNGLUNGGI-LLILUNGGI-LLIGI-LLILUNGLUNGTHYROIDTHYROIDTHYROIDTHYROIDTHYROIDTHYROIDLIVERLIVERBONELIVERGI-LLILUNGLUNGLUNGGI-LLIGI-LLILUNGGI-LLILUNGLUNGLUNGLUNGGI-LLIGI-LLI1.79E-042.69E-053.87E-031.48E-031.29E-046.27E-044.OOE-041.52E-054.76E-046.89E-068.32E-055.55E-071.02E-044.99E-044.39E-035.23E-051.04E-031.37E-052.14E-042.74E-044.62E-052.45E-042.27E-071.56E-054.71 E-047.89E-074.44E-076.1 OE-052.05E-051.47E-043.44E-053.23E-031.17E-044.23E-078.87E-052.46E-051.73E-056.62E+059.95E+041.43E+075.48E+064.77E+052.32E+061.48E+065.62E+041.76E+062.55E+043.08E+052.05E+033.77E+051.85E+061.62E+071.94E+053.85E+065.07E+047.92E+051.01E+061.71 E+059.07E+058.40E+025.77E+041.74E+062.92E+031.64E+032.26E+057.59E+045.44E+051.27E+051.20E+074.33E+051.57E+033.28E+059.1 OE+046.40E+04GI-LLI 9.10E+04LUNG 6.40E+04

-I .1.The listed dose parameters are for radionuclides, other than noble gases that may be detected in gaseouseffluents.

Pi factors include all nonatmospheric pathway transport parameters, the receptor's usage ofpathway media, and are based on the most restrictive age group (child) critical organ. Additional doseparameters for nuclides not included in this Table may be calculated using the methodology described inNUREG-0133.

Tritium dose factors include an increase of 50% to account for the additional amount of this nuclideabsorbed through the skin.mrem/year per piCi/m3.

CY-TM-170-300 Revision 3Page 131 of 209FIGURE 4.1TMI-1 Gaseous Effluent Pathways CY-TM-1 70-300Revision 3Page 132 of 209FIGURE 4.2TMI-1 Auxiliary and Fuel Handling Buildings Effluent Pathways CY-TM-1 70-300Revision 3Page 133 of 209FIGURE 4.3TMI-1 Reactor Building Effluent PathwayRcl170FEET7--REACTOR BUILDING PURGE EXHAUSTRADIATION MONITORS ANDSAMPLING STATIONSREACTORBUILDINGIW3-"m4.0-a2II I I IJ K"w =MFILTMR CR MH FIXFREACTER NUJNSmfltG SYSTENSPARTICULATUTITRHRM COMI&~E GASC A:oIpmI CY-TM-170-300 Revision 3Page 134 of 209FIGURE 4.4TMI-1 Condenser Offgas Effluent PathwayCONDENSER OFF GAS STACKCONDENSER OFF GASEXHAUSTRADIATION MONITORSAND SAMPLING STATIONS CY-TM-1 70-300Revision 3Page 135 of 209FIGURE 4.5TMI-2 Gaseous Effluent Filtration SystemlPathways STATION VENT0o ~ 0.0 -12,oo M1RD BREATHER--4,I --------------0 .-AM crmUNIT 2 EXHAUST AIR FLOW AND RMS SCHEMATIC CY-TM-1 70-300Revision 3Page 136 of 2095.0 GASEOUS EFFLUENT DOSE ASSESSMENT 5.1 Gaseous Effluents

-Instantaneous Release Limits5.1.1 Noble GasesFor noble gases, the following equations apply for total body and skindose rate at the unrestricted area boundary:

5.1.1.1 Total BodyDose Ratetb = z (Ki) x (Dv) x (Q1) (eq 5.1.1.1)Where:Dose Rate b = instantaneous total body dose rate limit, at the siteboundary, in mrem/yr.Ki = total body dose factor due to gamma emissions for eachidentified noble gas radionuclide, in mrem/yr per jiCi/m3from Table 4.3.Dv = highest sector annual average gaseous dispersion factor(X/Q) at or beyond the unrestricted area boundary, insec/m3, from Table 4.4 for station vent releases; andTable 4.5 for all other releases (Condenser Off Gas, ESFFHB, and ground releases).

Maximum values presently inuse are 1.27E-6 sec/m3 at sector SE for station vent, and1.40E-5 sec/m3 for all other releases at sector E.Qi = Release rate of radionuclide, i, in p.Ci/sec as determined by sampling and analysis.

Calculated using theconcentration of noble gas radionuclide, i, in ýtCi/cc, timesthe release pathway flow rate, in cc/second.

CY-TM-1 70-300Revision 3Page 137 of 2095.1.1.2 SkinDose Ratesk = (Li + 1.1 Mi) X (Dv) X (Qi) (eq 5.1.1.2)Where:Dose Ratesk = instantaneous mrem/year skin dose rate limit, at the siteboundary, in mrem/yr.Li = skin dose factor due to beta emissions for each identified noble gas radionuclide, in mrem/yr per JLCi/m3 fromTable 4.3.Mi = air dose factor due to gamma emissions for eachidentified noble gas radionuclide, in mrad/yr per ýtCi/m3from Table 4.3.1.1 = mrem skin dose per mrad air dose. Converts air dose toskin dose.Qi = release rate of radionuclide, i, in gCi/sec, as determined by sampling and analysis.

Calculated using theconcentration of noble gas radionuclide, i, in p.Ci/cc, timesthe release pathway flow rate, in cc/second.

Dv = highest sector annual average gaseous dispersion factor(X/Q) at or beyond the unrestricted area boundary, insec/m3, from Table 4.4 for station vent releases; andTable 4.5 for all other releases (Condenser Off Gas, ESFFHB, and ground releases).

Maximum values presently inuse are 1.27E-6 sec/m3 at sector SE for station vent, and1.40E-5 sec/m3for all other releases at E.

CY-TM-1 70-300Revision 3Page 138 of 2095.1.2 Iodine-131, Iodine-133, Tritium and Radionuclides in Particulate Form,with Half-Lives Greater than 8 DaysFor 1-131, 1-133, Tritium and Radionuclides in Particulate Form, withhalf-lives greater than 8 days, the following equation applies:Dose Rateip = (P1) (Dv) (Qi) (eq 5.1.2)Where:Dose Rateip = mrem/year organ dose rate.Pi = dose parameter for 1-131, 1-133, Tritium andRadionuclides in Particulate Form, with half-lives greaterthan 8 days, for the inhalation

pathway, in mrem/yr perPtCi/m3, from Table 4.6. The dose factors are based onthe critical individual organ and most restrictive agegroup (child).Dv -highest sector annual average gaseous dispersion factor(X/Q or D/Q) at or beyond the unrestricted areaboundary, in sec/M3, from Table 4.4 for the station ventreleases and Table 4.5 for all other releases.

X/Q isused for the inhalation pathway.

Maximum values of X/Qpresently used are 1.27E-6 sec/m3 for station vent, atsector SE, and 1.40E-5 sec/m3 for all other releases atsector E.Q= release rate of each radionuclide, i, in pCi/sec.Calculated using the concentration of each radionuclide, i, in pCi/cc, times the release pathway flow rate, incc/second.

CY-TM-1 70-300Revision 3Page 139 of 2095.2 Gaseous Effluents

-10 CFR 50 Appendix I5.2.1 Noble GasesThe air dose in an unrestricted area due to noble gases released ingaseous effluents from the site is determined using the following expressions:

Dose F = (3.17E-8) x (MI) x (Dv) x (Qi) (eq 5.2.1)andDose p = (3.17E-8) x f (NI) x (Dv) x (Qi) (eq 5.2.2)Where:Dose F = mrad gamma air dose due to gamma emissions fromnoble gas radionuclides.

Dose P = mrad beta air dose due to beta emissions from noble gasradionuclides.

MI = air dose factor due to gamma emissions for eachidentified noble gas radionuclide, in mrad/yr per gCi/m3,from Table 4.3.Ni = air dose factor due to beta emissions for each identified noble gas radionuclide, in mrad/yr per VLCi/m3, fromTable 4.3.Dv = highest sector annual average gaseous dispersion factor,X/Q, at or beyond the unrestricted area boundary, insec/m3.Values may be read or interpolated fromTable 4.4 for releases from the station vent and Table 4.5for all other releases.

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.Qi= release of noble gas radionuclide, i, in ýtCi, over thespecified time period, (jiCi/second

• seconds).

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

CY-TM-1 70-300Revision 3Page 140 of 209NOTE: If the methodology in this section is used in determining dose toan 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 DaysThe dose to an individual from 1-131, 1-133, Tritium and Radionuclides inParticulate Form with half-lives greater than 8 days in gaseous effluents released from the site to an unrestricted area is determined by solvingthe following expression:

Dose. = z (3.17E-8) x ý (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 andRadionuclides in Particulate Form, with half-lives greaterthan 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 perýtCi/m3 for the inhalation pathway and m2 -mrem/yr perýtCi/sec for other pathways, from Tables 5.2 to 5.7.NOTE: Since there is minimal or no elemental iodine released from thecondenser off-gas air ejector (see NUREG-0017) all Iodine Rivalues for all pathways, except the inhalation

pathway, areconsidered to be zero when performing dose calculations forreleases from the condenser off-gas air ejector.

Only calculate the dose due to the inhalation pathway for condenser off-gas airejector iodines.NOTE: Tritium, H-3, dose factor is mrem/year per pLCi/m3 for all pathways.

Dv = highest sector annual average gaseous dispersion factor(X/Q) at or beyond the unrestricted area boundary, insec/m3, for the inhalation

pathway, and D/Q, in m , forother pathways.

Table 4.4 is used to derive the valuesfor station vent releases and Table 4.5 is used to derivethe values for all other releases.

The values used tocalculate site boundary and critical receptor doses are asfollows:

CY-TM-1 70-300Revision 3Page 141 of 209Station Vent Releases

-Boundary

-all in sector SEInhalation X/Q 1.27E-6Meat D/Q 4.09E-8 Ground D/QCow/Milk/Infant D/Q 4.09E-8 Vegetation D/Q4.09E-84.09E-8Station Vent Releases

-Inhalation X/QMeat D/QCow/Milk/Infant D/QCritical Receptor1.13E-6 in sector SE5.93E-9 Ground D/Qin sector SE5.93E-9 Vegetation D/Qin sector SE2.25E-8in sector SE1.34E-8in sector EGround or Other Releases

-BoundaryInhalation X/Q 1.40E-5 in sector Eall in sector SE:Meat D/Q 4.25E-8 Ground D/QCow/Milk/Infant D/Q 4.25E-8 Vegetation D/Q4.25E-84.25E-8Ground or Other Releases

-CriticalInhalation X/Q 1.12E-5Meat D/Q 4.94E-9Cow/Milk/Infant D/Q 4.94E-9Receptor

-all in sector EGround D/Q 2.37E-8Vegetation D/Q 1.92E-8Dv(H-3) = In the case of H-3 only the X/Q's above are used for allpathways.

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

• seconds).

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

CY-TM-170-300 Revision 3Page 142 of 2095.3 Gaseous Radioactive System Dose Calculations Once per MonthODCM 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 priorto their discharge.

When the monthly projected doses due to the gaseouseffluent releases from the site would exceed:0.2 mrad to air from gamma radiation; or0.4 mrad to air from beta radiation; or0.3 mrem to any organ.The following calculational method is provided for performing this doseprojection.

At least once per month the gamma air dose, beta air dose and the maximumorgan dose for the quarter-to-date will be divided by the number of days into thequarter and multiplied by 31. Also, this dose projection shall include theestimated dose due to any anticipated unusual release during the period forwhich the projection is made. If these projected doses exceed any of the valueslisted above, appropriate portions of the TMI-1 Gaseous Waste Treatment System, as defined in Section 6.0, or appropriate portions of the TMI-2 GaseousEffluent Filtration System as shown on Figure 4.5, shall be used to reduceradioactivity levels prior to release.At the discretion of the ODCM Specialist, time periods other than the currentquarter-to-date may be used to project doses if the dose per day in the currentquarter-to-date is not believed to be representative of the dose per day projected for the next month.

CY-TM-1 70-300Revision 3Page 143 of 2095.4 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 acomprehensive dose assessment.

Default parameter values from Regulatory Guide 1.109 (Rev. 1) and/or actual site specific data can be used whereapplicable.

The onsite, on-line computerized system for tracking gaseous effluent dose usesannual 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 USNRCRegulatory Guide 1.109, and uses actual hourly meteorological information matched to the time of releases to more accurately assess the dispersion ofeffluents in the atmosphere.

Combining this assessment of dispersion with TMIeffluent data for each unit, postulated maximum hypothetical doses to the publicare calculated.

CY-TM-1 70-300Revision 3Page 144 of 209TABLE 5.2.1Pathway Dose Factors, R,AGE GROUP: INFANTPATHWAY:

INHALATION NUCLIDE ORGAN DOSE FACTORS; mrem/year per iCi/m3NUCL _ BONI --BONE .... -LIVER- .. T.BODY " THYROID --- KIDNEY ---- LLING- G" .... GI-LLII--

H-3C-14CR-51MN-54FE-55FE-590.OOE+002.65E+040.OOE+000.OOE+001.97E+041.36E+046.47E+02 6.47E+025.31E+03 5.31E+030.OOE+00 8.95E+01-----------.---------

2.53E+04 4.98E+031.17E+04 3.33E+032.35E+04 9.48E+036.47E+025.31 E+035.75E+010.OOE+000.OOE+000.00E+006.47E+025.31 E+031.32E+014.98E+030.OOE+000.OOE+006.47E+02 6.47E+025.31E+03 5.31E+031.28E+04 3.57E+02......................

1.OOE+06 7.06E+038.69E+04 1.09E+031.02E+06 2.48E+04---------..-----------

7.77E+05 1.11E+044.51E+06 3.19E+042.09E+05 2.42E+036.47E+05 5.14E+040.OOE+00 3.04E+032.03E+06 6.40E+04CO-58 0.OOE+00 1.22E+03 1.82E+03 0.OOE+00 0.OOE+00CO-60 0.OOE+00 8.02E+03 1.18E+04 0.OOE+00 0.OOE+00NI-63 3.39E+05 2.04E+04 1.16E+04 0.OOE+00 0.OOE+00ZN-65 1.93E+04 6.26E+04 3.11E+04 0.OOE+00 3.25E+04RB-86 0.OOE+00 1.90E+05 8.82E+04 0.OOE+00 0.OOE+00SR-89 3.98E+05 0.OOE+00 1.14E+04 0.OOE+00 0.OOE+00SR-90Y-91ZR-95NB-95RU-1 03RU-106AG-110MTE-125MTE-127MTE-129M1-1311-1334.09E+075.88E+051.15E+050.OOE+000.OOE+002.79E+042.59E+06I1.57E+04 2.03E+041.57E+04 6.43E+03 3.78E+032.02E+03 0.OOE+00 6.79E+028.68E+04 0.OOE+00 1.09E+049.98E+03 7.22E+03 5.OOE+034.76E+03 1.99E+03 6.58E+021.67E+04 6.90E+03 2.07E+030.OOE+000.OOE+000.OOE+00--.--E+--0.OOE+000.OOE+000.OOE+00I1.62E+03 4.87E+035.47E+031.48E+073.56E+060.OOE+00 1.12E+07 1.31E+050.OOE+00 2.45E+06 7.03E+043.11E+04 1.75E+06 2.17E+044.72E+034.24E+031.07E+051.09E+040.OOE+003.75E+043.18E+045.18E+042.24E+041.41E+043.79E+041.32E+046.09E+034.44E+041.92E+042.23E+031.96E+045.60E+034.79E+05 1.27E+045.52E+05 1.61 E+041.16E+07 1.64E+053.67E+06 3.30E+044.47E+05 1.29E+041.31E+06 2.73E+041.68E+06 6.90E+040.OOE+00 1.06E+030.OOE+00 2.16E+03---------..-----------

7.97E+04 1.33E+031.18E+04 1.43E+037.13E+04 1.33E+031.60E+06 3.84E+045.17E+05 2.16E+049.84E+06 1.48E+05CS-134 3.96E+05CS-1 36 4.83E+04CS-1 37 5.49E+05BA-140 5.60E+04CE-141 2.77E+04CE-144 3.19E+067.03E+05 7.45E+04 0.OOE+001.35E+05 5.29E+04 0.OOE+006.12E+05 4.55E+04 0.OOE+005.60E+01 2.90E+03 0.OOE+001.67E+04 1.99E+03 0.OOE+001.21EE+06 1.76E+05 0.OOE+001.90E+055.64E+041.72E+051.34E+015.25E+035.38E+05PR-143 1.40E+04 5.24E+03 6.99E+02 0.OOE+00 1.97E+03 4.33E+05 3.72E+04ND-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 70-300Revision 3Page 145 of 209TABLE 5.2.2Pathway Dose Factors, R,AGE GROUP: CHILD PATHWAY:

INHALATION ORGAN DOSE FACTORS; mrem/year per p.Ci/m3-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+03C-14 3.59E+04 6.73E+03 6.73E+03 6.73E+03 6.73E+03 6.73E+03 6.73E+03CR-51 0.OOE+00 0.OOE+00 1.54E+02 8.55E+01 2.43E+01 1.70E+04 1.08E+03MN-54 0.OOE+00 4.29E+04 9.51E+03 0.OOE+00 1.OOE+04 1.58E+06 2.29E+04FE-55 4.74E+04 2.52E+04 7.77E+03 0.OOE+00 0.OOE+00 1.11E+05 2.87E+03FE-59 2.07E+04 3.34E+04 1.67E+04 O.OOE+00 0.OOE+00 1.27E+06 7.07E+04CO-58 0.OOE+00 1.77E+03 3.16E+03 0.OOE+00 0.OOE+00 1.11E+06 3.44E+04CO-60 0.OOE+00 1.31E+04 2.26E+04 0.OOE+00 0.OOE+00 7.07E+06 9.62E+04NI-63 8.21E+05 4.63E+04 2.80E+04 0.OOE+00 O.OOE+00 2.75E+05 6.33E+03................................................................................

ZN-65 4.26E+04 1.13E+05 7.03E+04 0.OOE+00 7.14E+04 9.95E+05 1.63E+04RB-86 0.OOE+00 1.98E+05 1.14E+05 0.OOE+00 O.OOE+00 0.OOE+00 7.99E+03SR-89 5.99E+05 O.OOE+00 1.72E+04 0.OOE+00 O.OOE+00 2.16E+06 1.67E+05SR-90Y-91ZR-95NB-95RU-103RU-1 06AG-110MTE-125MTE-127MTE-129M1-1311-133CS-1 34CS-136CS-137BA-140CE-141CE-1441.01E+08 O.OOE+009.14E+05 O.OOE+001.90E+05 4.18E+046.44E+062.44E+043.70E+040.OOE+000.OOE+000.OOE+00O.OOE+O00.OOE+O05.96E+041.48E+072.63E+062.23E+063.43E+051.84E+056.11 E+042.35E+042.79E+031.36E+051.69E+046.73E+032.49E+041.92E+044.81E+041.66E+046.51 E+056.51 E+049.07E+057.40E+043.92E+046.77E+069.18E+03 6.55E+030.OOE+00 1.07E+030.OOE+00 1.69E+041.14E+04 9.14E+032.33E+03 9.14E+028.55E+03 3.02E+036.85E+03 3.04E+034.81 E+04 2.73E+042.03E+04 7.70E+031.01E+06 2.25E+051.71E+05 1.16E+058.25E+05 1.28E+056.48E+01 4.33E+031.95E+04 2.90E+032.12E+06 3.61 E+050.OOE+00 8.62E+030.OOE+00 7.03E+030.OOE+00 1.84E+05O.OOE+00 2.12E+041.92E+03 0.OOE+006.07E+03 6.36E+046.33E+03 5.03E+041.62E+07 7.88E+043.85E+06 3.38E+04O.OOE+00 3.30E+050.OOE+00 9.55E+04O.OOE+00 2.82E+050.OOE+00 2.11E+010.OOE+00 8.55E+030.OOE+00 1.17E+066.14E+05 3.70E+046.62E+05 4.48E+041.43E+07 4.29E+055.48E+06 1.OOE+054.77E+05 3.38E+041.48E+06 7.14E+041.76E+06 1.82E+05O.OOE+00 2.84E+03O.OOE+00 5.48E+031.21E+05 3.85E+031.45E+04 4.18E+031.04E+05 3.62E+031.74E+065.44E+051.20E+071.02E+055.66E+043.89E+05PR-143 1.85E+04 5.55E+03 9.14E+02 O.OOE+00 3.OOE+03 4.33E+05 9.73E+04ND-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 70-300Revision 3Page 146 of 209TABLE 5.2.3Pathway Dose Factors, R,AGE GROUP: TEENPATHWAY:

INHALATION NUCLIDE [.ORGAN DOSE FACTORS; mrem/year per _iCi/m3[ BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLIH-3 0.00E+00 1.27E+03 1.27E+03 1.27E+03 1.27E+03 1.27E+03 1.27E+03C-14 2.60E+04 4.87E+03 4.87E+03 4.87E+03 4.87E+03 4.87E+03 4.87E+03CR-51 0.00E+00 0.00E+00 1.35E+02 7.50E+01 3.07E+01 2.10E+04 3.OOE+03MN-54FE-55FE-59CO-58CO-60NI-63ZN-65RB-86SR-89SR-90Y-91ZR-95O.00E+003.34E+041.59E+045.11 E+042.38E+043.70E+042.07E+031.51 E+044.34E+040.OOE+000.00E+005.80E+053.86E+04 1.34E+050.OOE+00 1.90E+054.34E+05 0.00E+001.08E+08 0.00E+006.61E+05 0.00E+001.46E+05 4.58E+048.40E+03 0.00E+005.54E+03 0.00E+001.43E+04 0.00E+002.78E+03 0.00E+001.98E+04 0.00E+001.98E+04 0.00E+006.24E+04--.....E.....

6.24E+04 0.00E+008.40E+04 0.00E+001.25E+04 0.00E+006.68E+06 0.OOE+001.77E+04 0.00E+003.15E+04 0.00E+005.66E+03 0.OOE+008.96E+02 0.00E+001.24E+04 O.00E+007.99E+03 0.00E+006.67E+02 1.40E+032.18E+03 4.38E+031.27E+040.00E+000.OOE+00O.00E+000.OOE+00O.OOE+008.64E+04O.OOE+00O.OOE+000.OOE+00O.OOE+006.74E+041.OOE+047.43E+031.90E+052.50E+040.OOE+006.54E+045.19E+048.40E+043.59E+043.75E+051.10E+053.04E+051.98E+06 6.68E+041.24E+05 6.39E+031.53E+06 1.78E+051.34E+06 9.52E+048.72E+06 2.59E+053.07E+05 1.42E+04-----------.----------

1.24E+06 4.66E+040.OOE+00 1.77E+042.42E+06 3.71 E+051.65E+07 7.65E+052.94E+06 4.09E+052.69E+06 1.49E+057.51E+05 9.68E+047.83E+05 1.09E+051.61E+07 9.60E+056.75E+06 2.73E+055.36E+05 7.50E+041.66E+06 1.59E+051.98E+06 4.05E+050.00E+00 6.49E+030.00E+00 1.03E+041.46E+05 9.76E+031.78E+04 1.09E+041.21E+05 8.48E+03NB-95RU-1 03RU-106AG-110MTE-125MTE-127MTE-129M1-1311-133CS-134CS-136CS-1371.86E+2.1 0E+9.84E-+1 .38E+4.88E+1 .80E+1 .39E+3.54E-'1 .22E+5.02E-+5.15E+6.70E+-04 1.03E+04-03 0.00E+00-04 0.00E+00-04 1.31 E+04-03 2.24E+03-04 8.16E+03-04 6.58E+03-04 4.91E+04-04 2.05E+04-05 1.13E+06-04 1.94E+05-05 8.48E+052.25E+032.64E+046.22E+035.49E+051.37E+053.11 E+054.58E+031.46E+072.92E+060.OOE+000.OOE+000.OOE+00BA-140 5.47E+04 6.70E+01 3.52E+03 0.OOE+00 2.28E+01 2.03E+06 2.29E+05CE-141 2.84E+04 1.90E+04 2.17E+03 0.OOE+00 8.88E+03 6.14E+05 1.26E+05CE-144 4.89E+06 2.02E+06 2.62E+05 0.OOE+00 1.21E+06 1.34E+07 8.64E+05PR-143 1.34E+04 5.31E+03 6.62E+02 0.OOE+00 3.09E+03 4.83E+05 2.14E+05ND-147 7.86E+03 8.56E+03 5.13E+02 0.OOE+00 5.02E+03 3.72E+05 1.82E+05 CY-TM-1 70-300Revision 3Page 147 of 209TABLE 5.2.4Pathway Dose Factors, R1AGE GROUP: ADULTPATHWAY:

INHALATION ORGAN DOSE FACTORS; mrem/year per iLCi/m3NUCLIDE T---D- THYROID KIDNEY L -LL-___ _ ___-___ _ BONE -_ -LIVER -._T.13ODY

--THYROID --KIDNEY --LUNG ----GI-LLI_H-3 O.OOE+00 1.26E+03 1.26E+03 1.26E+03C-14 1.82E+04 3.41E+03 3.41E+03 3.41E+03CR-51 0.OOE+00 O.OOE+00 1.OOE+02 5.95E+01MN-54 0.OOE+00 3.96E+04 6.30E+03 0.OOE+00FE-55 2.46E+04 1.70E+04 3.94E+03 O.OOE+00FE-59 1.18E+04 2.78E+04 1.06E+04 O.OOE+001.26E+033.41 E+032.28E+019.84E+030.OOE+000.OOE+000.OOE+000.00E+000.OOE+006.90E+040.OOE+000.OOE+001.26E+03 1.26E+033.41E+03 3.41E+031.44E+04 3.32E+031.40E+06 7.74E+047.21E+04 6.03E+031.02E+06 1.88E+05---------..-----------

9.28E+05 1.06E+055.97E+06 2.85E+051.78E+05 1.34E+04-----------.----------

8.64E+05 5.34E+040.OOE+00 1.66E+041.40E+06 3.50E+05CO-58CO-60NI-63ZN-65RB-86SR-89SR-90Y-91ZR-95NB-95RU-1 03RU-106AG-110MTE-125MTE-127MTE-129M1-1311-1330.OOE+000.OOE+004.32E+053.24E+040.OOE+003.04E+059.92E+074.62E+051.07E+051.41 E+041.53E+036.91 E+041.08E+043.42E+031.26E+049.76E+032.52E+048.64E+031.58E+031.15E+043.14E+041.03E+051.35E+050.OOE+002.07E+031.48E+041.45E+044.66E+045.90E+048.72E+030.OOE+000.OOE+000.OOE+000.OOE+00-0.OOE+000.OOE+000.OOE+00 6.10E+060.OOE+00 1.24E+043.44E+04 2.33E+047.82E+03 4.21 E+030.OOE+00 6.58E+020.OOE+00 8.72E+031.OOE+04 5.94E+031.58E+03 4.67E+025.77E+03 1.57E+034.67E+03 1.58E+033.58E+04 2.05E+041.48E+04 4.52E+038.48E+05 7.28E+051.46E+05 1.10E+056.21E+05 4.28E+054.90E+01 2.57E+031.35E+04 1.53E+031.43E+06 1.84E+050.OOE+00 0.OOE+000.OOE+00 0.OOE+000.OOE+00 5.42E+040.OOE+00 7.74E+030.OOE+00 5.83E+030.OOE+00 1.34E+050.OOE+00 1.97E+041.05E+03 1.24E+043.29E+03 4.58E+043.44E+03 3.66E+041.19E+07 6.13E+042.15E+06 2.58E+040.OOE+00 2.87E+050.OOE+00 8.56E+040.OOE+00 2.22E+050.OOE+00 1.67E+010.OOE+00 6.26E+030.OOE+00 8.48E+059.60E+061.70E+061.77E+065.05E+055.05E+059.36E+064.63E+063.14E+059.60E+051.16E+060.OOE+000.OOE+009.76E+041.20E+047.52E+041.27E+063.62E+057.78E+067.22E+053.85E+051.50E+051.04E+051.1OE+059.12E+053.02E+057.06E+041.50E+053.83E+056.28E+038.88E+031.04E+041.17E+048.40E+03CS-1 34CS-1 36CS-1 37BA-140CE-141CE-1443.73E+053.90E+044.78E+053.90E+041.99E+043.43E+062.18E+051.20E+058.16E+05PR-143 9.36E+03 3.75E+03 4.64E+02 0.OOE+00 2.16E+03 2.81E+05 2.OOE+05ND-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 70-300Revision 3Page 148 of 209TABLE 5.3.1Pathway Dose Factors, R,AGE GROUP: ALL PATHWAY:

GROUND PLANEORGAN DOSEFACTORS*NUCLIDE -- ----------T.BODY SKINH-3 0.OOE+00 O.OOE+00C-14 O.OOE+00 0.OOE+00CR-51 4.65E+06 5.50E+06MN-54 1.39E+09 1.62E+09FE-55 O.OOE+00 0.OOE+00FE-59 2.73E+08 3.21 E+08CO-58 3.79E+08 4.44E+08CO-60 2.15E+10 2.53E+10NI-63 0.OOE+00 O.OOE+00-------------------------.

ZN-65 7.47E+08 8.59E+08RB-86 8.97E+06 1.03E+07SR-89 2.16E+04 2.51 E+04---------------------------

---

1SR-90 0.OOE+00 0.OOE+00Y-91 1.07E+06 1.21 E+06ZR-95 2.45E+08 2.84E+08NB-95 1.37E+08 1.61 E+08RU-103 1.08E+08 1.26E+08RU-106 4.22E+08 5.06E+08AG-1i1M 3.44E+09 4.01"E+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+06CS-134 6.86E+09 8.OOE+09CS-136 1.51E+08 1.71E+08CS-137 1.03E+10 1.20E+10---------------------

BA-140 2.06E+07 2.36E+07CE-141 1.37E+07 1.54E+07CE-144 6.96E+07 8.05E+07-------------------------

PR-143 0.OOE+00 0.OOE+00ND-147 8.39E+06 1.01E+07* m2-mrem/year per ýiCi/sec.

CY-TM-1 70-300Revision 3Page 149 of 209TABLE 5.4.1Pathway Dose Factors, R,AGE GROUP: INFANT PATHWAY:

GRASS-COW-MILK N ORGAN DOSE FACTORS; m2 -mrem/year per pCi/secNU----- BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLIH-3C-14CR-51MN-54FE-55FE-59CO-58CO-60NI-63ZN-65RB-86SR-89SR-90Y-91ZR-950.OOE+002.34E+090.OOE+00O.OOE+001.35E+082.25E+080.OOE+000.OOE+003.50E+105.56E+090.OOE+001.26E+101.22E+117.34E+046.81 E+032.38E+03 2.38E+03 2.38E+03 2.38E+035.OOE+08 5.OOE+08 5.OOE+08 5.OOE+080.OOE+00 1.61E+05 1.05E+05 2.30E+04-----------.----------------------------

3.91E+07 8.85E+06 O.OOE+00 8.65E+068.74E+07 2.34E+07 0.OOE+00 0.OOE+003.93E+08 1.55E+08 0.OOE+00 0.OOE+002.43E+07 6.06E+07 O.OOE+00 O.OOE+008.83E+07 2.08E+08 O.OOE+00 0.OOE+002.16E+09 1.21E+09 0.OOE+00 0.OOE+00-----------.----------------------------

1.91E+10 8.79E+09 0.OOE+00 9.24E+092.23E+10 1.10E+10 0.OOE+00 0.OOE+000.OOE+00 3.62E+08 O.OOE+00 0.OOE+000.OOE+00 3.10E+10 0.OOE+00 0.OOE+000.OOE+00 1.95E+03 0.OOE+00 0.OOE+001.66E+03 1.18E+03 0.OOE+00 1.79E+032.38E+03 2.38E+035.OOE+08 5.OOE+082.05E+05 4.70E+06......................

0.OOE+00 1.43E+074.27E+07 1.11E+071.16E+08 1.88E+08O.OOE+00 6.05E+07O.OOE+00 2.10E+080.OOE+00 1.08E+08......................

O.OOE+00 1.61E+10O.OOE+00 5.70E+080.OOE+00 2.59E+08O.OOE+00 1.52E+09O.OOE+00 5.26E+06O.OOE÷00 8.27E+05NB-95RU-103RU-1 06AG-11iMTE-125MTE-127MTE-129M1-1311-133CS-134CS-1 36CS-1 37BA-140CE-141CE-1445.94E+058.68E+031.91E+053.86E+081.51 E+084.22E+085.58E+082.72E+093.63E+073.65E+101.98E+095.15E+102.42E+084.34E+042.33E+062.45E+05 1.41 E+050.OOE+00 2.90E+030.OOE+00 2.38E+04-----------.---------

2.82E+08 1.87E+085.05E+07 2.04E+071.40E+08 5.1OE+07-----------.---------

1.91E+08 8.59E+073.21E+09 1.41E+095.29E+07 1.55E+07-----------.---------

6.81E+10 6.88E+095.83E+09 2.18E+096.03E+10 4.27E+09O.OOE+00 1.75E+05O.OOE+00 1.81E+040.OOE+00 2.25E+050.OOE+00 4.03E+085.08E+07 0.OOE+001.22E+08 1.04E+092.14E+08 1.39E+091.05E+12 3.75E+099.62E+09 6.22E+070.OOE+00 1.75E+100.OOE+00 2.32E+09O.OOE+00 1.62E+100.OOE+00 2.07E+080.OOE+00 1.06E+050.OOE+00 1.45E+060.OOE+00 1.46E+100.OOE+00 7.19E+07O.OOE+00 1.70E+080.OOE+00 3.33E+08O.OOE+00 1.15E+080.OOE+00 8.96E+067.19E+09 1.85E+084.75E+08 8.85E+076.55E+09 1.89E+081.49E+05 5.94E+070.OOE+00 1.37E+07O.OOE+00 1.34E+082.42E+05 1.25E+07 0.OOE+00 5.75E+042.65E+04 3.12E+03 0.OOE+00 8.17E+039.53E+05 1.30E+05 0.OOE+00 3.85E+05PR-143 1.49E+03 5.56E+02 7.37E+01 O.OOE+00 2.07E+02 O.OOE+00 7.84E+05ND-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 70-300Revision 3Page 150 of 209TABLE 5.4.2Pathway Dose Factors, R,AGE GROUP: CHILDPATHWAY:

GRASS-COW-MILK N ORGAN DOSE FACTORS; m2 -mrem/year per giCi/secNUCLI BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLIH-3C-14CR-51MN-54FE-55FE-59CO-58CO-60NI-63ZN-65RB-86SR-89O.OOE+00 1.57E+03 1.57E+031.20E+09 2.39E+08 2.39E+08O.00E+00 0.OOE+00 1.02E+05O.OOE+00 2.1OE+07 5.59E+061.12E+08 5.94E+07 1.84E+071.20E+08 1.95E+08 9.70E+070.OOE+00 1.21E+07 3.72E+070.00E+00 4.32E+07 1.27E+082.97E+10 1.59E+09, 1.01E+094.14E+09 1.10E+10 6.86E+090.OOE+00 8.78E+09 5.40E+096.63E+09 O.OOE+00 1.89E+081 .57E+032.39E+085.65E+04O.00E+0O0.OOE+0OO.00E+0O0.OOE+OO0.OOE+OO0.OOE+OO0.OOE+OO0.OOE+0O0.OOE+00SR-90Y-91ZR-95NB-95RU-1 03RU-1061.12E+113.91 E+043.84E+033.18E+054.29E+039.25E+04AG-110M 2.09E+08TE-125M 7.39E+07TE-127M 2.08E+08TE-129M 2.72E+081-131 1.31E+091-133 1.72E+07CS-1 34 2.27E+10CS-1 36 1.01 E+09CS-1 37 3.23E+100.OOE+00 2.84E+100.OOE+00 1.05E+038.43E+02 7.51 E+021.24E+05 8.86E+040.OOE+00 1.65E+030.OOE+00 1.15E+041.41E+08 1.13E+082.OOE+07 9.85E+065.61 E+07 2.47E+07-----------.---------

7.59E+07 4.22E+071.31E+09 7.46E+082.13E+07 8.05E+063.72E+10 7.85E+092.79E+09 1.80E+093.09E+10 4.56E+090.OOE+000.OOE+000.OOE+O00.OOE+000.OOE+000.OOE+O00.OOE+002.07E+074.98E+078.76E+074.34E+i 13.95E+09--.--E+--O.OOE+000.OOE+001.57E+03 1.57E+032.39E+08 2.39E+081.54E+04 1.03E+055.89E+06 0.OOE+00O.OOE+00 3.36E+07O.OOE+00 5.65E+070.OOE+00 0.OOE+000.OOE+00 0.OOE+000.OOE+00 O.OOE+006.95E+09 0.OOE+000.OOE+00 0.OOE+00O.OOE+00 0.OOE+000.OOE+00 0.OOE+000.OOE+00 O.OOE+001.21 E+03 0.OOE+001.16E+05 0.OOE+001.08E+04 0.OOE+001.25E+05 0.OOE+002.63E+08 0.OOE+000.OOE+00 0.OOE+005.94E+08 0.OOE+007.98E+08 0.OOE+002.16E+09 0.OOE+003.55E+07 0.OOE+001.15E+10 4.14E+091.49E+09 2.21E+081.01E+10 3.62E+091.57E+032.39E+085.40E+061.76E+071.1OE+072.03E+087.08E+072.39E+081.07E+081.94E+095.65E+082.57E+081.51 E+095.21 E+068.80E+052.29E+081.11E+051.44E+061.68E+107.13E+071.69E+083.31 E+081.17E+088.58E+062.01 E+089.80E+071.93E+08BA-140 1.18E+08 1.03E+05 6.86E+06 0.OOE+00 3.35E+04 6.14E+04 5.96E+07CE-141 2.19E+04 1.09E+04 1.62E+03 0.OOE+00 4.79E+03 0.OOE+00 1.36E+07CE-144 1.63E+06 5.09E+05 8.67E+04 0.00E+00 2.82E+05 0.OOE+00 1.33E+08PR-143 7.18E+02 2.16E+02 3.56E+01 0.OOE+00 1.17E+02 0.OOE+00 7.75E+05ND-147 4.45E+02 3.61E+02 2.79E+01 0.OOE+00 1.98E+02 0.OOE+00 5.71E+05 CY-TM-170-300 Revision 3Page 151 of 209TABLE 5.4.3Pathway Dose Factors, R,AGE GROUP: TEENPATHWAY:

GRASS-COW-MILK NULIEORGAN DOSE FACTORS; M2_ mrem/year per gCilsecBONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLIH-3 0.00E+00 9.93E+02 9.93E+02 9.93E+02 9.93E+02 9.93E+02 9.93E+02C-14 4.86E+08 9.73E+07 9.73E+07 9.73E+07 9.73E+07 9.73E+07 9.73E+07CR-51 0.OOE+00 0.OOE+00 4.99E+04 2.77E+04 1.09E+04 7.13E+04 8.39E+06MN-54FE-55FE-590.OOE+004.46E+075.19E+071.40E+073.16E+071.21E+082.78E+067.37E+064.68E+07O.OOE+00 4.19E+060.OOE+00 0.OOE+000.OOE+00 0.OOE+000.OOE+002.01 E+073.82E+072.88E+071.37E+072.86E+08CO-58 O.OOE+00CO-60 0.OOE+00NI-63 1.18E+10ZN-65 2.11 E+09RB-86 O.OOE+00SR-89 2.68E+097.94E+06 1.83E+072.78E+07 6.27E+078.36E+08 4.01 E+08-----------.---------

7.32E+09 3.42E+094.73E+09 2.22E+090.OOE+00 7.67E+070.00E+000.00E+000.OOE+000.OOE+000.OOE+000.00E+000.OOE+00 0.OOE+00 1.1OE+080.OOE+00 O.OOE+00 3.62E+080.00E+00 0.00E+00 1.33E+084.69E+09 0.00E+00 3.10E+090.OOE+00 0.OOE+00 7.OOE+080.OOE+00 0.OOE+00 3.19E+080.OOE+00 0.00E+00 1.86E+090.00E+00 0.00E+00 6.48E+067.65E+02 0.00E+00 1.20E+06--------------------.----------

7.58E+04 0.OOE+00 3.34E+086.39E+03 0.OOE+00 1.51E+057.24E+04 0.00E+00 1.80E+06SR-90 6.62E+10Y-91 1.58E+04ZR-95 1.65E+03NB-95 1.41 E+05RU-103 1.81E+03RU-106 3.76E+040.OOE+00 1.63E+100.OOE+00 4.24E+025.21 E+02 3.58E+02.....................

7.82E+04 4.30E+040.OOE+00 7.75E+020.OOE+00 4.73E+039.12E+07 5.55E+071.08E+07 4.02E+063.OOE+07 1.OOE+070.00E+000.OOE+000.00E+000.OOE+000.OOE+000.00E+000.00E+008.40E+062.01 E+07AG-110MTE-125MTE-127M9.64E+073.01 E+078.45E+071.74E+080.00E+003.42E+080.00E+00 2.56E+100.OOE+00 8.87E+070.OOE+00 2.11E+08TE-129M1-1311-133CS-1 34CS-1 36CS-1 37BA-140CE-141CE-1441.10E+08 4.09E+075.38E+08 7.53E+087.08E+06 1.20E+079.83E+09 2.31E+104.49E+08 1.77E+091.34E+10 1.78E+104.87E+07 5.97E+048.89E+03 5.94E+036.59E+05 2.73E+051.74E+07 3.56E+074.05E+08 2.20E+113.66E+06 1.68E+09-.-------------------

1.07E+10 0.OOE+001.19E+09 0.OOE+006.21E+09 0.OOE+003.14E+06 0.OOE+006.82E+02 0.00E+003.54E+04 0.OOE+004.61E+08 0.OOE+00 4.14E+081.30E+09 0.O0E+00 1.49E+082.11E+07 0.00E+00 9.09E+067.35E+09 2.81E+09 2.88E+089.63E+08 1.52E+08 1.42E+086.06E+09 2.36E+09 2.54E+082.02E+04 4.01E+04 7.51E+072.80E+03 0.OOE+00 1.70E+071.63E+05 0.OOE+00 1.66E+08PR-143 2.90E+02 1.16E+02 1.44E+01 0.OOE+00 6.73E+01 0.OOE+00 9.55E+05ND-147 1.81E+02 1.97E+02 1.18E+01 0.00E+00 1.16E+02 0.OOE+00 7.12E+05 CY-TM-170-300 Revision 3Page 152 of 209TABLE 5.4.4Pathway Dose Factors, R,AGE GROUP: ADULTPATHWAY:

GRASS-COW-MILK NUCLIDE ---- ORGAN DOSE FACTORS; M2_ mrem/year per p.Cilsec[-BONE -_ -LIVER -_ T.BODY --THYROID -KIDNEY --LUNG ----GI-LLI--H-3C-14CR-51MN-54FE-55FE-590.OOE+002.63E+080.OOE+000.OOE+002.51 E+072.97E+077.62E+02 7.62E+025.26E+07 5.26E+070.OOE+00 2.85E+048.40E+06 1.60E+061.73E+07 4.04E+066.97E+07 2.67E+077.62E+025.26E+071.70E+040.OOE+000.OOE+000.OOE+00CO-58 0.OOE+00CO-60 0.00E+00NI-63 6.72E+09ZN-65 1.37E+09RB-86 0.OOE+00SR-89 1.45E+09SR-90 4.67E+10Y-91 8.57E+03ZR-95 9.41 E+02NB-95 8.24E+04RU-103 1.02E+03RU-106 2.04E+04AG-110M 5.81E+07TE-125M 1.63E+07TE-127M 4.57E+07TE-129M 6.01E+071-131 2.96E+081-133 3.87E+06CS-1 34 5.64E+09CS-1 36 2.63E+08CS-1 37 7.37E+094.71E+06 1.05E+07 0.00E+001.64E+07 3.61E+07 0.00E+004.65E+08 2.25E+08 0.OOE+00-----------.-------------------

4.36E+09 1.97E+09 0.00E+002.59E+09 1.21E+09 0.00E+000.OOE+00 4.16E+07 0.00E+000.00E+00 1.15E+10 0.OOE+000.00E+00 2.29E+02 0.OOE+003.02E+02 2.04E+02 0.OOE+004.58E+04 2.46E+04 0.00E+000.00E+00 4.38E+02 0.00E+000.00E+00 2.58E+03 O.00E+00-----------.-------------------

5.38E+07 3.19E+07 0.00E+005.89E+06 2.18E+06 4.89E+061.63E+07 5.57E+06 1.17E+077.62E+02 7.62E+025.26E+07 5.26E+076.28E+03 3.78E+042.50E+06 0.OOE+000.00E+00 9.66E+060.00E+00 1.95E+070.OOE+00 0.00E+000.OOE+00 0.00E+000.00E+00 0.00E+002.91 E+09 0.00E+000.00E+00 0.OOE+000.00E+00 0.00E+000.OOE+00 0.00E+000.OOE+00 0.00E+004.74E+02 0.00E+004.53E+04 0.00E+003.88E+03 0.00E+003.93E+04 0.00E+007.62E+025.26E+077.17E+062.57E+079.93E+062.32E+089.54E+073.08E+089.71E+072.74E+095.10E+082.32E+081.35E+094.72E+069.57E+052.78E+081.19E+051.32E+062.24E+07 9.51 E+064.23E+08 2.42E+086.73E+06 2.05E+06-----------.----------

1.34E+10 1.10E+101.04E+09 7.48E+081.01E+10 6.60E+092.06E+071.39E+119.88E+080.00E+000.00E+000.00E+000.OOE+000.OOE+000.OOE+001.06E+086.61 E+071.86E+082.51 E+087.25E+081.17E+074.34E+095.78E+083.42E+091.15E+041.52E+038.85E+040.OOE+000.OOE+000.OOE+000.OOE+000.OOE+000.00E+001.44E+097.92E+071.14E+091.94E+040.OOE+000.OOE+002.19E+106.49E+071.53E+083.02E+081.12E+086.04E+062.35E+081.18E+081.95E+085.54E+071.25E+071.21E+08BA-140CE-141CE-1442.69E+074.84E+033.57E+053.38E+043.27E+031.49E+051.76E+063.71 E+021.92E+04PR-143 1.57E+02 6.32E+01 7.81E+00 0.OOE+00 3.65E+01 0.OOE+00 6.90E+05ND-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 70-300Revision 3Page 153 of 209TABLE 5.5.1Pathway Dose Factors, R,AGE GROUP: INFANT PATHWAY:

GRASS-GOAT-MILK S .ORGAN DOSE FACTORS; M2 _ mrem/year per jCi/secNU LI E -- -- -- ..-L- ------ ----- ---------6 ..G ---...-- -- --- ---------

BONE -_ -LIVER T. BODY --THYROID --KIDNEY -LUNG- .GI-LLI_H-3 0.00E+00 4.86E+03 4.86E+03 4.86E+03 4.86E+03 4.86E+03 4.86E+03C-14 2.34E+09 5.00E+08 5.OOE+08 5.00E+08 5.OOE+08 5.OOE+08 5.00E+08CR-51 0.00E+00 0.OOE+00 1.94E+04 1.26E+04 2.76E+03 2.46E+04 5.64E+05................................................................................

MN-54 0.OOE+00FE-55 1.76E+06FE-59 2.92E+06CO-58 0.OOE+00CO-60 0.OOE+00NI-63 4.19E+09ZN-65 6.67E+08RB-86 0.00E+00SR-89 2.65E+l0SR-90 2.55E+1 1Y-91 8.80E+03ZR-95 8.17E+02NB-95 7.13E+04RU-1 03 1.04E+03RU-106 2.28E+044.68E+06 1.06E+061.14E+06 3.03E+055.10E+06 2.01E+06-----------.----------

2.91 E+06 7.26E+061.06E+07 2.50E+072.59E+08 1.46E+08-........

1.....E......

2.29E+09 1.05E+092.67E+09 1.32E+090.00E+00 7.59E+080.OOE+00 6.50E+10O.00E+00 2.34E+021.99E+02 1.41E+022.93E+04 1.70E+04O.OOE+00 3.48E+020.00E+00 2.85E+03O.OOE+000.OOE+0O0.00E+001 .04E+060.00E+00O.00E+000.00E+005.55E+051.51 E+060.00E+00O.OOE+00O.OOE+000.00E+OO0.00E+000.00E+000.OOE+000.OOE+000.OOE+000.OOE+000.OOE+000.00E+O00.00E+006.09E+061 .46E+070.OOE+00 0.OOE+000.OOE+00 0.OOE+00O.00E+00 O.00E+001.11E+09 O.OOE+000.OOE+00 0.OOE+000.OOE+00 0.00E+000.00E+00 0.00E+00O.00E+00 O.OOE+002.15E+02 O.OOE+002.10E+04 0.00E+002.17E+03 0.00E+002.70E+04 O.00E+004.84E+07 0.OOE+000.OOE+00 0.00E+001.24E+08 0.00E+001.72E+061.44E+052.44E+067.25E+062.52E+071.29E+071.93E+096.83E+075.44E+083.19E+096.31 E+059.91 E+042.48E+071.27E+041.73E+051.75E+098.62E+062.04E+07AG-110M 4.63E+07 3.38E+07TE-125M 1.81E+07 6.05E+06TE-127M 5.06E+07 1.68E+07TE-129M 6.69E+07 2.29E+071-131 3.27E+09 3.85E+091-133 4.36E+07 6.35E+07............................

CS-134 1.09E+11 2.04E+11CS-136 5.94E+09 1.75E+10CS-137 1.54E+11 1.81E+11BA-140 2.90E+07 2.90E+04CE-141 5.21E+03 3.18E+03CE-144 2.79E+05 1.14E+052.24E+072.45E+066.12E+061.03E+07 2.57E+07 1.67E+08 0.OOE+00 3.99E+071.69E+09 1.27E+12 4.50E+09 0.OOE+00 1.37E+081.86E+07 1.15E+10 7.46E+07 0.00E+00 1.07E+07-.---------------------------------------.----------

2.06E+10 0.OOE+00 5.26E+10 2.15E+10 5.55E+086.52E+09 0.00E+00 6.96E+09 1.42E+09 2.65E+081.28E+10 0.00E+00 4.85E+10 1.96E+10 5.65E+081.50E+063.74E+021.56E+04O.OOE+0O0.OOE+000.00E+006.89E+039.79E+024.62E+041.78E+040.00E+000.OOE+007.13E+061.64E+061.60E+07PR-143 1.78E+02 6.66E+01 8.83E+00 0.OOE+00 2.48E+01 0.OOE+00 9.40E+04ND-147 1.06E+02 1.09E+02 6.66E+00 0.OOE+00 4.19E+01 0.OOE+00 6.89E+04 CY-TM-1 70-300Revision 3Page 154 of 209TABLE 5.5.2Pathway Dose Factors, R,AGE GROUP: CHILD PATHWAY:

GRASS-GOAT-MILK NUCLIDE ORGAN DOSE

-mrem/year per jiCi/secBONE LIVER T.BODY -THYROID KIDNEY LN- G I-LLIH-3 0.00E+00 3.20E+03 3.20E+03 3.20E+03 3.20E+03C-14 1.20E+09 2.39E+08 2.39E+08 2.39E+08 2.39E+08CR-51 0.OOE+00 0.OOE+00 1.22E+04 6.78E+03 1.85E+03MN-54 0.OOE+00 2.52E+06 6.71E+05 0.OOE+00 7.06E+05FE-55 1.45E+06 7.71E+05 2.39E+05 0.OOE+00 0.OOE+00FE-59 1.56E+06 2.53E+06 1.26E+06 0.OOE+00 0.OOE+00CO-58 0.OOE+00 1.46E+06 4.46E+06 0.00E+00 0.OOE+00CO-60 0.OOE+00 5.18E+06 1.53E+07 0.00E+00 0.OOE+00NI-63 3.56E+09 1.91E+08 1.21E+08 0.OOE+00 0.OOE+003.20E+03 3.20E+032.39E+08 2.39E+081.24E+04 6.48E+050.00E+00 2.11E+064.36E+05 1.43E+057.34E+05 2.64E+060.OOE+00 8.49E+060.OOE+00 2.87E+070.OOE+00 1.28E+07.

ZN-65 4.96E+08 1.32E+09 8.22E+08 0.OOE+00 8.33E+08 O.OOE+00 2.32E+08RB-86 0.OOE+00 1.05E+09 6.47E+08 0.OOE+00 0.OOE+00 0.OOE+00 6.77E+07SR-89 1.39E+10 O.OOE+00 3.97E+08 0.OOE+00 0.OOE+00 0.OOE+00 5.39E+08SR-90 2.35E+11 0.OOE+00 5.95E+10Y-91 4.69E+03 0.OOE+00 1.25E+02ZR-95 4.60E+02 1.01E+02 9.OOE+01NB-95 3.82E+04 1.49E+04 1.06E+04RU-103 5.14E+02 0.OOE+00 1.98E+02RU-106 1.11E+04 0.OOE+00 1.38E+03AG-110M 2.51E+07 1.69E+07 1.35E+07TE-125M 8.86E+06 2.40E+06 1.18E+06TE-127M 2.50E+07 6.72E+06 2.96E+06.......................................

TE-129M 3.26E+07 9.10E+06 5.06E+061-131 1.57E+09 1.57E+09 8.95E+081-133 2.06E+07 2.55E+07 9.66E+06.......................................

CS-1 34 6.80E+10 1.12E+11 2.35E+10CS-1 36 3.04E+09 8.36E+09 5.41 E+09CS-137 9.68E+10 9.26E+10 1.37E+100.OOE+000.OOE+000.OOE+00--.--E+--OO.OOE+000.OOE+000.OOE+002.49E+065.97E+061 .05E+075.21 E+l114.74E+090.OOE+00 0.OOE+00 3.16E+090.OOE+00 0.OOE+00 6.24E+051.45E+02 0.OOE+00 1.05E+05...............................

1.40E+041.29E+031.50E+043.15E+07O.OOE+007.12E+079.56E+072.58E+094.25E+070.OOE+00 2.75E+070.OOE+00 1.33E+040.OOE+00 1.73E+050.OOE+00 2.01E+090.OOE+00 8.55E+06O.00E+00 2.02E+07......................

0.00E+00 3.97E+070.OOE+00 1.40E+080.00E+00 1.03E+070.OOE+00 3.46E+10 1.24E+10 6.01E+080.OOE+00 4.45E+09 6.64E+08 2.94E+080.OOE+00 3.02E+10 1.09E+10 5.80E+08BA-140 1.41E+07 1.24E+04 8.23E+05 0.OOE+00 4.02E+03 7.37E+03 7.15E+06CE-141 2.63E+03 1.31E+03 1.95E+02 0.OOE+00 5.74E+02 0.00E+00 1.63E+06CE-144 1.95E+05 6.11E+04 1.04E+04 0.OOE+00 3.38E+04 0.OOE+00 1.59E+07PR-143 8.61E+01 2.59E+01 4.27E+00 0.OOE+00 1.40E+01 0.00E+00 9.29E+04ND-147 5.34E+01 4.33E+01 3.35E+00 0.OOE+00 2.37E+01 0.OOE+00 6.85E+04 CY-TM-170-300 Revision 3Page 155 of 209TABLE 5.5.3Pathway Dose Factors, R,AGE GROUP: TEENPATHWAY:

GRASS-GOAT-MILK N ORGAN DOSE FACTORS; m -mrem/year per jiCi/secNUCLIDE BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLIH-3 0.OOE+00 2.04E+03C-14 4.86E+08 9.72E+07CR-51 0.OOE+00 0.OOE+00MN-54 0.00E+00 1.68E+06FE-55 5.79E+05 4.11E+05FE-59 6.74E+05 1.57E+062.04E+039.72E+075.99E+033.34E+059.58E+046.08E+052.04E+039.72E+073.33E+030.00E+000.00E+000.OOE+002.04E+03 2.04E+039.72E+07 9.72E+071.31E+03 8.55E+035.02E+05 0.OOE+000.OOE+00 2.61E+050.OOE+00 4.96E+052.04E+039.72E+071.01 E+063.45E+061.78E+053.72E+06CO-58CO-60NI-63ZN-65RB-86SR-89SR-90Y-91ZR-95NB-95RU-1 03RU-1060.00E+00 9.53E+050.OOE+00 3.34E+061.42E+09 1.00E+082.53E+08 8.78E+080.OOE+00 5.67E+085.62E+09 0.OOE+001.39E+11 0.00E+001.90E+03 0.OOE+001.98E+02 6.25E+011.69E+04 9.38E+032.17E+02 0.00E+004.50E+03 0.00E+002.20E+06 0.OOE+007.52E+06 O.00E+004.81E+07 O.00E+004.10E+08 O.00E+002.67E+08 0.00E+001.61 E+08 0.00E+003.43E+10 0.00E+005.09E+01 0.OOE+004.30E+01 0.OOE+005.16E+03 O.00E+009.29E+01 0.OOE+005.68E+02 O.00E+000.OOE+00 0.OOE+00 1.31E+070.OOE+00 0.00E+00 4.35E+070.OOE+00 0.00E+00 1.60E+075.62E+08 0.00E+00 3.72E+080.00E+00 0.OOE+00 8.40E+070.00E+00 0.00E+00 6.69E+080.OOE+00 0.OOE+00 3.90E+090.OOE+00 0.OOE+00 7.78E+059.18E+01 0.OOE+00 1.44E+059.09E+03 0.00E+00 4.01E+077.66E+02 0.00E+00 1.82E+048.69E+03 0.00E+00 2.16E+05AG-110M 1.16E+07 1.09E+07 6.65E+06 0.00E+00 2.09E+07 0.00E+00 3.07E+09TE-125M 3.61E+06 1.30E+06 4.82E+05 1.01E+06 0.OOE+00 0.OOE+00 1.06E+07TE-127M 1.01E+07 3.59E+06 1.20E+06 2.41E+06 4.11E+07 0.00E+00 2.52E+07TE-129M 1.32E+07 4.90E+06 2.09E+06 4.26E+06 5.53E+07 0.OOE+00 4.96E+071-131 6.45E+08 9.03E+08 4.85E+08 2.64E+11 1.56E+09 0.00E+00 1.79E+081-133 8.49E+06 1.44E+07 4.40E+06 2.01E+09 2.53E+07 0.00E+00 1.09E+07CS-1 34CS-1 36CS-1 372.95E+l 01.35E+094.02E+l 06.93E+105.30E+095.34E+1 03.22E+103.56E+091.86E+l00.00E+000.00E+000.OOE+002.20E+1 02.89E+091.82E+108.41 E+094.55E+087.07E+098.62E+084.27E+087.60E+08BA-140 5.84E+06 7.16E+03 3.76E+05 0.OOE+00 2.43E+03 4.81E+03 9.01E+06CE-141 1.07E+03 7.12E+02 8.18E+01 0.OOE+00 3.35E+02 0.00E+00 2.04E+06CE-144 7.90E+04 3.27E+04 4.25E+03 0.OOE+00 1.95E+04 0.00E+00 1.99E+07PR-143 3.48E+01 1.39E+01 1.73E+00 0.OOE+00 8.08E+00 0.OOE+00 1.15E+05ND-147 2.18E+01 2.37E+01 1.42E+00 0.00E+00 1.39E+01 0.OOE+00 8.54E+04 CY-TM-1 70-300Revision 3Page 156 of 209TABLE 5.5.4Pathway Dose Factors, R,AGE GROUP: ADULTPATHWAY:

GRASS-GOAT-MILK NUCLIDE I::::::-

ORGAN DOSE FACTORS; m2 -mrem/year per gCi/secBONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLIH-3 0.00E+00 1.56E+03C-14 2.64E+08 5.27E+07CR-51 0.OOE+00 0.00E+00MN-54 0.00E+00 1.01E+06FE-55 3.27E+05 2.26E+05FE-59 3.87E+05 9.09E+051.56E+03 1.56E+035.27E+07 5.27E+073.43E+03 2.05E+031.93E+05 0.OOE+005.26E+04 0.OOE+003.48E+05 O.OOE+001.56E+03 1.56E+035.27E+07 5.27E+077.56E+02 4.55E+033.01E+05 0.00E+00O.00E+00 1.26E+050.00E+00 2.54E+051.56E+035.27E+078.63E+053.1OE+061.30E+053.03E+06CO-58 0.OOE+00 5.66E+05 1.27E+06 O.OOE+00 0.OOE+00 0.00E+00 1.15E+07CO-60 0.OOE+00 1.97E+06 4.35E+06 0.00E+00 0.OOE+00 0.OOE+00 3.70E+07NI-63 8.08E+08 5.60E+07 2.71E+07 O.00E+00 0.OOE+00 0.OOE+00 1.17E+07................................................................................

ZN-65RB-86SR-89SR-90Y-91ZR-95NB-95RU-1 03RU-1 061.65E+08 5.24E+08 2.37E+080.OOE+00 3.12E+08 1.45E+083.05E+09 0.00E+00 8.76E+079.84E+10 0.00E+00 2.41E+101.03E+03 0.00E+00 2.76E+011.13E+02 3.63E+01 2.46E+019.92E+03 5.52E+03 2.97E+031.22E+02 0.00E+00 5.27E+012.45E+03 0.00E+00 3.10E+020.00E+000.00E+000.00E+000.00E+000.OOE+000.00E+000.00E+000.00E+000.00E+003.51 E+080.OOE+000.OOE+000.00E+000.OOE+000.OOE+003.30E+086.14E+074.89E+080.OOE+00 0.OOE+000.OOE+00 0.OOE+005.70E+01 0.OOE+005.45E+03 0.OOE+004.67E+02 0.OOE+004.73E+03 0.OOE+002.84E+095.68E+051.15E+053.35E+071.43E+041.59E+052.64E+097.81 E+061.84E+073.64E+071.34E+087.28E+06AG-110M 6.99E+06 6.47E+06TE-125M 1.96E+06 7.09E+05TE-127M 5.50E+06 1.97E+06TE-129M 7.23E+06 2.70E+061-131 3.56E+08 5.09E+081-133 4.65E+06 8.10E+06CS-134 1.70E+10 4.04E+10CS-136 7.92E+08 3.13E+09CS-1 37 2.22E+10 3.03E+103.84E+06 0.00E+00 1.27E+072.62E+05 5.89E+05 7.96E+066.70E+05 1.41E+06 2.23E+071.14E+06 2.48E+06 3.02E+072.92E+08 1.67E+ 1I 8.73E+082.47E+06 1.19E+09 1.41E+073.30E+10 0.00E+00 1.31E+102.25E+09 0.00E+00 1.74E+091.99E+10 0.00E+00 1.03E+100.OOE+000.OOE+000.00E+000.OOE+000.00E+000.00E+004.34E+092.38E+083.42E+097.07E+083.55E+085.87E+08BA-140 3.24E+06 4.07E+03 2.12E+05 0.OOE+00 1.38E+03 2.33E+03 6.67E+06CE-141 5.82E+02 3.94E+02 4.47E+01 0.00E+00 1.83E+02 0.OOE+00 1.51E+06CE-144 4.30E+04 1.80E+04 2.31E+03 0.00E+00 1.07E+04 0.OOE+00 1.45E+07PR-143 1.90E+01 7.60E+00 9.40E-01 0.00E+00 4.39E+00 0.OOE+00 8.30E+04ND-147 1.13E+01 1.31E+01 7.82E-01 0.OOE+00 7.65E+00 0.OOE+00 6.28E+04 CY-TM-170-300 Revision 3Page 157 of 209TABLE 5.6.1Pathway Dose Factors, R1AGE GROUP: INFANT PATHWAY:

GRASS-COW-MEAT NUCLIDE ORGAN DOSE FACTORS; M -mrem/year per piCisecSIBONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLIH-3C-14CR-51MN-54FE-55FE-59CO-58CO-60NI-630.OOE+000.OOE+000.OOE+000.OOE+00---

0.OOE+000.OOE+000.OOE+000.OOE+000.OOE+000.00E+000.OOE+000.OOE+000.00E+000.OOE+000.OOE+00----- ---+ --00.OOE+000.OOE+000.00E+000.OOE+000.OOE+000.OOE+000.OOE+000.OOE+000.00E+000.OOE+000.OOE+00 0.OOE+00 0.OOE+000.OOE+00 0.OOE+00 0.OOE+000.00E+00 0.00E+00 0.00E+000.OOE+00 0.OOE+00 0.OOE+000.OOE+00 0.OOE+00 0.OOE+000.OOE+00 0.OOE+00 0.OOE+000.00E+00 0.OOE+00 0.OOE+000.OOE+00 0.OOE+00 0.OOE+000.OOE+00 0.OOE+00 0.00E+000.OOE+000.00E+000.OOE+000.OOE+000.OOE+000.OOE+000.OOE+000.OOE+000.00E+00ZN-65 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00RB-86 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00SR-89 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00SR-90Y-91ZR-95NB-95RU-103RU-106AG-110MTE-125MTE-127MTE-129M1-1311-133CS-1 34CS-136CS-137BA-140CE-141CE-1440.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+000.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+000.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00.................................................

0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+000.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+000.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+000.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+000.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+000.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+000.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+000.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+000.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+000.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+000.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+000.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+000.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+000.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+000.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+000.OOE+000.00E+000.OOE+000.OOE+000.OOE+000.00E+000.OOE+00 0.OOE+000.OOE+00 0.OOE+000.OOE+00 0.OOE+000.00E+00 0.00E+000.00E+00 0O.E+000.00E+00 0.00E+000.00E+00 0.00E+000.00E+00 0.00E+000.OOE+00 0.OOE+000.OOE+00 0.00E+000.OOE+00 0.OOE+000.00E+00 0.00E+000.OOE+000.OOE+000.OOE+000.OOE+000.OOE+000.OOE+00PR-1 43 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00ND-147 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 CY-TM-1 70-300Revision 3Page 158 of 209TABLE 5.6.2Pathway Dose Factors, R,AGE GROUP: CHILDPATHWAY:

GRASS-COW-MEAT

[ULD ------ ORGAN DOSE FACNULD-----------------------------

j BONE LIVER T.BODYH-3 0.OOE+00 2.34E+02 2.34E+02C-14 3.84E+08 7.67E+07 7.67E+07CR-51 0.OOE+00 O.00E+00 8.78E+03MN-54 0.OOE+00 8.01E+06 2.13E+06FE-55 4.57E+08 2.43E+08 7.52E+07FE-59 3.77E+08 6.10E+08 3.04E+08CO-58 0.00E+00 1.64E+07 5.03E+07CO-60 0.00E+00 6.93E+07 2.04E+08NI-63 2.91E+10 1.56E+09 9.91E+08.......................................

ZN-65 3.76E+08 1.OOE+09 6.22E+08RB-86 0.00E+00 5.76E+08 3.54E+08SR-89 4.82E+08 0.OOE+00 1.38E+07SR-90 1.04E+10 O.OOE+00 2.64E+09Y-91 1.80E+06 0.OOE+00 4.82E+04ZR-95 2.66E+06 5.86E+05 5.21E+05TORS; mrem/year per iiCi/secTHYROID KIDNEY LUNG GI-LLI2.34E+02 2.34E+02 2.34E+02 2.34E+027.67E+07 7.67E+07 7.67E+07 7.67E+074.88E+03 1.33E+03 8.90E+03 4.66E+050.OOE+00 2.25E+06 0.00E+00 6.73E+06O.OOE+00 O.00E+00 1.37E+08 4.49E+07O.00E+00 O.00E+00 1.77E+08 6.35E+080.00E+00 O.00E+00 O.00E+00 9.58E+07O.00E+00 O.00E+00 0.OOE+00 3.84E+08O.00E+00 O.OOE+00 O.00E+00 1.05E+080.00E+00 6.31E+08 O.OOE+00 1.76E+08O.00E+00 0.OOE+00 O.00E+00 3.71E+070.00E+00 0.OOE+00 O.OOE+00 1.87E+07O.00E+00 0.OOE+00 0.0OE+00 1.40E+080.00E+00 0.OOE+00 O.OOE+00 2.40E+080.00E+00 8.38E+05 0.OOE+00 6.11E+08NB-95RU-1 03RU-106AG-11iMTE-125M.TE-127MTE-129M1-1311-133CS-1 34CS-1 36CS-1 37BA-140CE-141CE-1443.1OE+06 1.21E+06 8.63E+051.55E+08 0.OOE+00 5.96E+074.44E+09 0.OOE+00 5.54E+080.OOE+00 1.13E+060.OOE+00 3.90E+080.00E+00 6.OOE+098.39E+06 5.67E+06 4.53E+06 0.OOE+005.69E+08 1.54E+08 7.59E+07 1.60E+081.78E+09 4.78E+08 2.11E+08 4.25E+081.79E+09 5.OOE+08 2.78E+08 5.77E+081.66E+07 1.67E+07 9.48E+06 5.52E+095.72E-01 7.08E-01 2.68E-01 1.31 E+029.23E+08 1.51E+09 3.19E+08 O.OOE+001.63E+07 4.48E+07 2.90E+07 0.00E+001.33E+09 1.28E+09 1.89E+08 0.OOE+004.42E+07 3.87E+04 2.58E+06 0.OOE+002.22E+04 1.11 E+04 1.65E+03 0.OOE+002.32E+06 7.26E+05 1.24E+05 0.OOE+001.06E+070.OOE+005.06E+095.26E+092.74E+071.18E+004.69E+082.39E+074.16E+081.26E+044.86E+034.02E+050.OOE+00 2.23E+090.00E+00 4.01E+090.OOE+00 6.91E+100.00E+00 6.74E+080.OOE+00 5.49E+080.00E+00 1.44E+090.OOE+00 2.18E+090.00E+00 1.48E+060.OOE+00 2.85E-011.68E+08 8.16E+063.56E+06 1.57E+061.50E+08 8.OOE+062.31 E+040.00E+000.00E+002.24E+071.38E+071.89E+08PR-143 3.33E+04 1.00E+04 1.65E+03 0.OOE+00 5.42E+03 0.00E+00 3.60E+07ND-147 1.17E+04 9.48E+03 7.34E+02 0.OOE+00 5.20E+03 0.00E+00 1.50E+07 CY-TM-1 70-300Revision 3Page 159 of 209TABLE 5.6.3Pathway Dose Factors, R,AGE GROUP: TEENPATHWAY:

GRASS-COW-MEAT NUCLIDE ORGAN DOSE FACTORS; m2 -mrem/year per !tCi/sec_ BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLIH-3 0.OOE+00C-14 2.04E+08CR-51 0.OOE+00MN-54 0.00E+00FE-55 2.38E+08FE-59 2.12E+08CO-58 0.OOE+00CO-60 0.OOE+00NI-63 1.52E+10ZN-65RB-86SR-89SR-90Y-91ZR-95NB-95RU-103RU-106AG-11OMTE-125MTE-127M2.50E+080.00E+002.55E+088.04E+099.54E+051.50E+061.79E+068.56E+072.36E+095.06E+063.03E+089.41 E+081.93E+02 1.93E+024.08E+07 4.08E+070.OOE+00 5.63E+037.OOE+06 1.39E+061.69E+08 3.94E+074.95E+08 1.91 E+081.40E+07 3.24E+075.83E+07 1.31E+081.07E+09 5.15E+08---------..----------

8.68E+08 4.05E+084.06E+08 1.91E+080.OOE+00 7.29E+060.00E+00 1.99E+090.OOE+00 2.56E+044.73E+05 3.25E+05---------------------

9.95E+05 5.48E+050.00E+00 3.66E+070.OOE+00 2.97E+084.78E+06 2.91 E+061.09E+08 4.05E+073.34E+08 1.12E+081.93E+02 1.93E+02 1.93E+024.08E+07 4.08E+07 4.08E+073.13E+03 1.23E+03 8.03E+030.00E+00 2.09E+06 0.OOE+000.OOE+00 0.OOE+00 1.07E+080.OOE+00 0.OOE+00 1.56E+080.00E+00 0.00E+00 0.00E÷000.OOE+00 0.OOE+00 0.OOE+000.OOE+00 0.OOE+00 0.OOE+000.00E+00 5.56E+08 0.00E+000.OOE+00 0.OOE+00 0.OOE+000.OOE+00 0.56E+00 0.OOE+000.OOE+00 0.00E+00 0.OOE+000.OOE+00 0.OOE+00 0.00E+000.OOE+00 6.95E+05 0.00E+001.93E+024.08E+079.46E+051.44E+077.31 E+071 .17E+091.94E+087.60E+081.71 E+083.68E+086.OOE+073.03E+072.26E+083.91 E+081.09E+094.25E+097.15E+091.13E+111.34E+098.94E+082.35E+093.56E+092.47E+063.95E-011.53E+072.99E+061.37E+070.OOE+000.OOE+000.OOE+000.OOE+008.46E+072.24E+089.64E+05 0.OOE+003.02E+08 0.OOE+004.54E+09 0.OOE+009.13E+06 0.00E+000.OOE+00 0.OOE+003.81E+09 0.OOE+00TE-129M 9.49E+081-131 8.93E+061-133 3.08E-01CS-1 34 5.23E+08CS-1 36 9.43E+06CS-1 37 7.24E+083.52E+081.25E+075.22E-011.23E+093.71 E+079.63E+081.50E+086.72E+061.59E-015.71 E+082.49E+073.35E+083.06E+083.65E+097.29E+010.00E+000.OOE+000.OOE+003.97E+092.15E+079.16E-013.91 E+082.02E+073.28E+080.OOE+000.OOE+000.00E+001.49E+083.18E+061 .27E+08BA-140 2.39E+07 2.93E+04 1.54E+06 0.OOE+00 9.94E+03 1.97E+04 3.69E+07CE-141 1.18E+04 7.87E+03 9.05E+02 0.OOE+00 3.71E+03 0.OOE+00 2.25E+07CE-144 1.23E+06 5.08E+05 6.60E+04 0.OOE+00 3.03E+05 0.OOE+00 3.09E+08PR-143 1.76E+04 7.03E+03 8.76E+02ND-147 6.23E+03 6.78E+03 4.06E+020.OOE+00 4.08E+03 0.OOE+00 5.79E+070.OOE+00 3.98E+03 0.OOE+00 2.44E+07 CY-TM-1 70-300Revision 3Page 160 of 209TABLE 5.6.4Pathway Dose Factors, R,AGE GROUP: ADULTPATHWAY:

GRASS-COW-MEAT NUCLIDE ORGAN DOSE FACTORS; m _ mrem/year per _Ci/_sec( BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLIH-3 0.OOE+00 3.24E+02 3.24E+02 3.24E+02 3.24E+02 3.24E+02 3.24E+02C-14 2.42E+08 4.83E+07 4.83E+07 4.83E+07 4.83E+07 4.83E+07 4.83E+07CR-51 0.OOE+00 O.OOE+00 7.04E+03 4.21E+03 1.55E+03 9.35E+03 1.77E+06................................................................................

MN-54FE-55FE-59CO-58CO-60NI-63ZN-65RB-86SR-89SR-90Y-91ZR-950.OOE+00 9.18E+062.93E+08 2.03E+082.66E+08 6.25E+08.....................

0.OOE+00 1.82E+07O.OOE+00 7.52E+071.89E+10 1.31E+09---------------------

3.56E+08 1.13E+090.OOE+00 4.87E+083.02E+08 O.OOE+001.24E+10 O.OOE+001.13E+06 0.OOE+001.87E+06 6.01E+051.75E+06 0.OOE+004.73E+07 0.OOE+002.39E+08 O.OOE+00-.-------------------

4.09E+07 0.OOE+001.66E+08 0.OOE+006.33E+08 0.OOE+00-.-------------------

5.12E+08 O.OOE+002.27E+08 0.OOE+00.8.66E+06 O.OOE+003.05E+09 0.OOE+003.03E+04 0.OOE+004.07E+05 O.OOE+006.87E+05 0.OOE+004.53E+07 0.OOE+003.54E+08 O.OOE+00-.-------------------

3.67E+06 0.OOE+004.81 E+07 1.08E+081.36E+08 2.85E+082.73E+06 0.OOE+00 2.81E+070.OOE+00 1.13E+08 1.16E+080.OOE+00 1.75E+08 2.08E+09...............................

O.OOE+00 0.OOE+00 3.70E+080.OOE+00 0.OOE+00 1.41 E+090.OOE+00 0.OOE+00 2.73E+087.57E+08 O.OOE+00 7.13E+080.OOE+00 0.OOE+00 9.59E+070.OOE+00 0.OOE+00 4.84E+070.OOE+000.OOE+009.43E+05O.OOE+O00.OOE+00O.OOE+003.60E+086.24E+081.90E+09NB-95 2.30E+06 1.28E+06RU-103 1.05E+08 0.OOE+00RU-106 2.80E+09 0.OOE+00............................

AG-110M 6.68E+06 6.18E+06TE-125M 3.59E+08 1.30E+08TE-127M 1.12E+09 3.99E+081.26E+06 O.OOE+004.02E+08 0.OOE+005.41E+09 0.OOE+001.22E+07 0.OOE+001.46E+09 0.OOE+004.53E+09 0.OOE+00TE-129M1-1311-133CS-1 34CS-1 36CS-1 371.13E+091.08E+073.68E-016.58E+081.21E+078.72E+082.90E+071.41 E+041.46E+064.23E+081.54E+076.41 E-011.57E+094.78E+071.19E+-09 3.64E+049.51 E+036.1OE+051.79E+08 3.89E+088.82E+06 5.04E+091.95E-01 9.42E+011.28E+09 0.OOE+003.44E+07 0.OOE+007.82E+08 O.OOE+004.73E+09 0.OOE+002.64E+07 0.OOE+001.12E+00 0.OOE+005.07E+08 1.68E+082.66E+07 3.65E+064.05E+08 1.35E+081.24E+04 2.08E+044.42E+03 O.OOE+003.62E+05 0.OOE+007.76E+091.23E+101.81 E+I 12.52E+091.43E+093.74E+095.71 E+094.06E+065.76E-012.74E+075.43E+062.31E+075.96E+073.64E+074.93E+08BA-140CE-141CE-1441.90E+061.08E+037.83E+04O.OOE+000.OOE+00O.OOE+00PR-143 2.09E+04 8.40E+03 1.04E+03 O.OOE+00 4.85E+03 O.OOE+00 9.17E+07ND-147 7.08E+03 8.18E+03 4.90E+02 0.OOE+00 4.78E+03 0.OOE+00 3.93E+07 CY-TM-1 70-300Revision 3Page 161 of 209TABLE 5.7.1Pathway Dose Factors, R,AGE GROUP: INFANTPATHWAY:

VEGETATION NUCLIDE ORGAN DOSE FACTORS; m2 -mrem/year per piCi/sec-BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLIH-3 0.OOE+00C-14 O.OOE+00CR-51 0.00E+00MN-54 0.00E+00FE-55 0.00E+00FE-59 O.OOE+00CO-58 0.OOE+00CO-60 0.00E+00NI-63 0.OOE+00ZN-65 0.OOE+00RB-86 0.OOE+00SR-89 0.OOE+000.O0E+00 O.OOE+00O.00E+00 O.OOE+000.00E+00 0.00E+00O.OOE+00 O.OOE+000.OOE+00 O.OOE+00O.OOE+00 O.OOE+00O.OOE+00 O.OOE+000.00E+00 0.00E+000.00E+00 0.00E+00O.OOE+00 O.OOE+00O.OOE+00 0.00E+000.OOE+00 0.OOE+00O.OOE+00 O.OOE+00O.OOE+00 O.OOE+00O.00E+00 O.00E+00Q.OOE+00O.OOE+00O.OOE+OO0.00E+O0O.00E+00O.OOE+000.OOE+00O.OOE+0O0.00E+0OO.OOE+000.OOE+0OO.OOE+000.OOE+0O0.OOE+00O.OOE+00O.OOE+00 0.OOE+000.OOE+00 O.00E+000.OOE+00 O.OOE+000.00E+00 0.00E+00O.OOE+00 0.00E+00O.00E+00 0.OOE+000.OOE+00 0.OOE+00O.OOE+00 O.00E+000.OOE+OO O.OOE+000.00E+00 0.OOE+00O.OOE+00 0.00E+000.OOE+00 0.OOE+00O.OOE+00O.OOE+O00.OOE+OOO.OOE+OO--

O.OOE+000.OOE+0OO.OOE+00O.OOE+00O.OOE+00O.OOE+OO0.OOE+000.OOE+00O.OOE+0O0.00 E+00--0.OOE+000.OOE+000.OOE+000.OOE+00SR-90Y-91ZR-950.OOE+000.OOE+000.OOE+000.OOE+000.OOE+000.OOE+00O.OOE+000.00E+00O.00E+O0NB-95 0.00E+00RU-1 03 0.OOE+00RU-1 06 O.00E+00AG-110M 0.OOE+00TE-125M 0.00E+00TE-127M 0.00E+000.00E+000.OOE+000.00E+000.OOE+000.00E+000.OOE+00 0.OOE+000.OOE+00 0.00E+000.OOE+00 0.00E+000.00E+00 0.00E+000.00E+00 0.00E+000.OOE+00 0.OOE+000.OOE+00 0.00E+000.00E+00 0.OOE+000.00E+00 0.OOE+000.OOE+00 0.OOE+000.00E+00 O.00E+000.00E+00 0.OOE+000.OOE+00 0.OOE+000.OOE+00 0.OOE+000.OOE+00 0.OOE+000.00E+00 0.OOE+000.OOE+00 0.00E+000.OOE+00 0.OOE+00TE-129M1-1311-133CS-1 34CS-1 36CS-1370.OOE+00 0.OOE+000.OOE+00 0.00E+000.OOE+00 0.00E+000.00E+00 0.OOE+000.00E+00 0.OOE+000.OOE+00 0.OOE+000.OOE+000.00E+000.00E+000.OOE+O00.OOE+000.00E+000.OOE+00 0:OOE+000.00E+00 0.OOE+000.00E+00 0.OOE+000.OOE+00 0.00E+000.OOE+00 0.OOE+000.00E+00 0.OOE+00BA-140 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00CE-141 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00CE-1 44 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00PR-143 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00ND-147 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 CY-TM-1 70-300Revision 3Page 162 of 209TABLE 5.7.2Pathway Dose Factors, R,AGE GROUP: CHILDPATHWAY:

VEGETATION N ORGAN DOSE FACTORS; m2 -mrem/year per ipCi/secNUCLI BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLIH-3C-14CR-51MN-54FE-55FE-59CO-58CO-60NI-63ZN-65RB-86SR-89SR-90Y-91ZR-95NB-95RU-103RU-1060.OOE+00 4.02E+03 4.02E+038.89E+08 1.78E+08 1.78E+080.OOE+00 0.00E+00 1.17E+05...............................

O.OOE+00 6.65E+08 1.77E+088.01 E+08 4.25E+08 1.32E+083.98E+08 6.44E+08 3.21E+080.00E+00 6.44E+07 1.97E+080.00E+00 3.78E+08 1.12E+093.95E+10 2.11E+09 1.34E+09-------------------------------

8.12E+08 2.16E+09 1.35E+090.00E+00 4.51E+08 2.77E+083.60E+10 0.OOE+00 1.03E+09---------------------.---------

1.24E+12 O.OOE+00 3.15E+111.87E+07 0.OOE+00 4.99E+053.86E+06 8.48E+05 7.55E+054.02E+031 .78E+086.49E+04--.--E+---0.OOE+000.OOE+000.OOE+000.00E+00O.00E+000.00E+000.OOE+004.02E+031.78E+081.77E+041.86E+080.OOE+00O.00E+000.00E+000.OOE+000.00E+001.36E+090.OOE+000.OOE+004.02E+03 4.02E+031.78E+08 1.78E+081.18E+05 6.20E+06......................

0.00E+00 5.58E+082.40E+08 7.87E+071.87E+08 6.71E+080.OOE+00 3.76E+080.00E+00 2.10E+090.00E+00 1.42E+08...E..................

0.00E+00 3.80E+080.00E+00 2.90E+070.00E+00 1.39E+09......................

0.00E+00 1.67E+100.OOE+00 2.49E+090.OOE+00 8.85E+08...E..................

0.OOE+00 2.96E+080.00E+00 3.97E+080.OOE+00 1.16E+10......................

0.00E+00 2.58E+090.00E+00 3.38E+080.00E+00 1.07E+090.00E+00 1.02E+090.OOE+00 1.28E+070.00E+00 1.76E+064.11E+051.53E+077.45E+081.60E+050.OOE+000.OOE+001.14E+055.90E+069.30E+070.00E+000.OOE+000.OOE+00--.---+--0.OOE+000.OOE+000.OOE+009.84E+073.16E+082.71 E+084.76E+1 08.12E+080.00E+000.00E+001.21 E+061.50E+053.86E+071.01E+094.04E+070.00E+003.77E+092.47E+092.36E+087.28E+06AG-110M 3.21E+07 2.17E+07 1.73E+07TE-125M 3.51E+08 9.50E+07 4.67E+07TE-127M 1.32E+09 3.56E+08 1.57E+08TE-129M 8.40E+08 2.35E+08 1.30E+081-131 1.43E+08 1.44E+08 8.18E+071-133 3.53E+06 4.37E+06 1.65E+06CS-134 1.60E+10 2.63E+10 5.55E+09 0.00E+00 8.15E+09 2.93E+09 1.42E+08CS-136 8.28E+07 2.28E+08 1.47E+08 0.00E+00 1.21E+08 1.81E+07 8.OOE+06CS-137 2.39E+10 2.29E+10 3.38E+09 0.OOE+00 7.46E+09 2.68E+09 1.43E+08BA-140 2.79E+08 2.44E+05 1.63E+07 0.00E+00 7.96E+04 1.46E+05 1.41E+08CE-141 6.57E+05 3.28E+05 4.86E+04 0.00E+00 1.44E+05 0.00E+00 4.09E+08CE-144 1.27E+08 3.99E+07 6.79E+06 0.00E+00 2.21E+07 0.00E+00 1.04E+10PR-143 1.45E+05 4.36E+04 7.21E+03ND-147 7.15E+04 5.79E+04 4.49E+030.OOE+00 2.36E+04 0.00E+00 1.57E+080.00E+00 3.18E+04 0.00E+00 9.18E+07 CY-TM-1 70-300Revision 3Page 163 of 209TABLE 5.7.3Pathway Dose Factors, R,AGE GROUP: TEENPATHWAY:

VEGETATION NUCL-DE [ -- ORGAN DOSE FACTORS; m2 -mrem/year per --Ci/secNUCLIDE LIV E TO RO-D K eY LUNG -- L-___ _ ___-___ _ BONE -_ -LIVER -_ T.BODY --THYROID --KIDNEY -LUNG- .GI-LLI--H-3C-14CR-51MN-54FE-55FE-59O.OOE+00 2.59E+03 2.59E+033.69E+08 7.38E+07 7.38E+070.OOE+00 0.OOE+00 6.16E+040.OOE+00 4.54E+08 9.01E+073.26E+08 2.31E+08 5.39E+071.80E+08 4.19E+08 1.62E+082.59E+037.38E+073.42E+04--.-OE+--O.OOE+000.OOE+002.59E+037.38E+071.35E+041.36E+080.OOE+000.OOE+002.59E+03 2.59E+037.38E+07 7.38E+078.79E+04 1.03E+070.OOE+00 9.32E+081.47E+08 1.OOE+081.32E+08 9.91E+08......................

0.OOE+00 6.01E+080.OOE+00 3.24E+090.00E+00 1.81E+08CO-58 0.OOE+00 4.36E+07 1.01E+08 0.OOE+00 0.OOE+00CO-60 0.OOE+00 2.49E+08 5.60E+08 0.OOE+00 0.OOE+00NI-63 1.61E+10 1.13E+09 5.45E+08 0.OOE+00 0.OOE+00ZN-65RB-86SR-89SR-90Y-91ZR-95NB-95RU-103RU-1064.24E+080.OOE+001.52E+107.51E+117.84E+061.72E+061.92E+056.82E+063.09E+081.47E+092.73E+080.OOE+006.86E+081.28E+084.34E+080.OOE+00 1.85E+110.OOE+00 2.10E+055.43E+05 3.73E+051.07E+05 5.87E+040.OOE+00 2.92E+06O.OOE+00 3.90E+071 .43E+07 8.72E+065.34E+07 1.98E+071.96E+08 6.56E+071.34E+08 5.72E+071.08E+08 5.78E+073.29E+06 1.OOE+060.OOE+00 9.42E+08 0.OOE+000.OOE+00 0.OOE+00 0.00E+000.OOE+00 0.OOE+00 0.00E+000.OOE+00 0.OOE+00 0.OOE+000.OOE+00 0.OOE+00 0.OOE+000.OOE+00 7.98E+05 0.OOE+000.OOE+00 1.03E+05 0.OOE+000.OOE+00 2.41E+07 0.OOE+000.OOE+00 5.97E+08 0.OOE+000.OOE+00 2.74E+07 0.OOE+004.14E+07 0.OOE+00 0.00E+001.31E+08 2.24E+09 0.OOE+001.17E+08 1.51E+09 0.OOE+003.14E+10 1.85E+08 0.00E+004.59E+08 5.77E+06 0.OOE+000.OOE+00 5.31E+09 2.03E+090.OOE+00 9.41 E+07 1.48E+070.OOE+00 4.59E+09 1.78E+096.23E+084.04E+071.80E+092.11E+103.22E+091.25E+094.56E+085.70E+081.48E+104.03E+094.37E+081.37E+091.36E+092.13E+072.49E+062.08E+081 .39E+071.92E+08AG-110MTE-125MTE-127MTE-129M1-1311-1331.52E+071.48E+085.52E+083.61 E+087.69E+071.94E+067.1OE+094.39E+071.01E+10CS-1 34CS-1 36CS-1 371.67E+101.73E+081.35E+107.75E+091. 16E+084.69E+09BA-140 1.39E+08 1.71E+05 8.97E+06 0.OOE+00 5.78E+04 1.15E+05 2.15E+08CE-141 2.83E+05 1.89E+05 2.17E+04 0.OOE+00 8.90E+04 0.OOE+00 5.41E+08CE-144 5.28E+07 2.18E+07 2.83E+06 0.00E+00 1.30E+07 0.OOE+00 1.33E+10PR-143 6.99E+04 2.79E+04 3.48E+03 0.OOE+00 1.62E+04 0.OOE+00 2.30E+08ND-147 3.62E+04 3.94E+04 2.36E+03 0.OOE+00 2.31E+04 O.OOE+00 1.42E+08 CY-TM-1 70-300Revision 3Page 164 of 209TABLE 5.7.4Pathway Dose Factors, R,AGE GROUP: ADULTPATHWAY:

VEGETATION SORGAN DOSE FACTORS; M2-mrem/year per GCi-sec__~ ~ ___ __ __ __ BONE -_ -LIVER T.BODY --THYROID --KIDNEY -LUNG- .GI-LLI_H-3 0.OOE+00C-14 2.28E+08CR-51 O.OOE+00MN-54 0.OOE+00FE-55 2.1OE+08FE-59 1.26E+08CO-58 0.OOE+00CO-60 0.OOE+00NI-63 1.04E+10ZN-65 3.17E+08RB-86 0.OOE+00SR-89 9.98E+09SR-90 6.05E+11Y-91 5.12E+06ZR-95 1.17E+06NB-95 1.42E+05RU-1 03 4.77E+06RU-106 1.93E+08AG-110M 1.05E+07TE-125M 9.66E+07TE-127M 3.49E+08TE-129M 2.51E+081-131 8.08E+071-133 2.09E+06CS-1 34 4.67E+09CS-1 36 4.28E+07CS-1 37 6.36E+092.26E+03 2.26E+034.55E+07 4.55E+07O.OOE+00 4.64E+04-----------.----------

3.13E+08 5.97E+071.45E+08 3.38E+072.97E+08 1.14E+083.07E+07 6.89E+071.67E+08 3.69E+087.21 E+08 3.49E+08-----------.----------

1.01E+09 4.56E+082.19E+08 1.02E+080.OOE+00 2.86E+08......................

0.OOE+00 1.48E+1 10.OOE+00 1.37E+053.77E+05 2.55E+05-----------.----------

7.92E+04 4.26E+040.OOE+00 2.06E+06O.OOE+00 2.44E+079.75E+06 5.79E+063.50E+07 1.29E+071.25E+08 4.26E+07-----------.----------

9.37E+07 3.97E+071.16E+08 6.62E+073.63E+06 1.11E+061.11E+10 9.08E+091.69E+08 1.22E+088.70E+09 5.70E+092.26E+034.55E+072.77E+040.OOE+0O0.OOE+000.OOE+O00.OOE+000.OOE+000.OOE+000.OOE+00O.OOE+00O.OOE+00O.OOE+0O0.OOE+0OO.OOE+000.OOE+000.OOE+000.OOE+000.OOE+002.90E+078.93E+078.63E+073.79E+1 05.34E+080.OOE+000.OOE+000.OOE+002.26E+03 2.26E+03 2.26E+034.55E+07 4.55E+07 4.55E+071.02E+04 6.15E+04 1.17E+07---------------------.----------

9.31E+07 0.OOE+00 9.58E+080.OOE+00 8.08E+07 8.31E+070.OOE+00 8.29E+07 9.89E+08O.OOE+00 0.OOE+00 6.23E+080.OOE+00 0.OOE+00 3.14E+090.OOE+00 O.OOE+00 1.50E+08---------------------.----------

6.75E+08 O.OOE+00 6.36E+080.OOE+00 0.OOE+00 4.32E+070.OOE+00 0.OOE+00 1.60E+090.OOE+00 0.OOE+00 1.75E+100.OOE+00 0.OOE+00 2.82E+095.91E+05 O.OOE+00 1.19E+097.83E+04 0.OOE+00 4.81E+081.82E+07 O.OOE+00 5.57E+083.72E+08 0.OOE+00 1.25E+101.92E+07 0.OOE+00 3.98E+093.93E+08 0.OOE+00 3.86E+081.42E+09 0.OOE+00 1.17E+091.05E+09 O.OOE+00 1.26E+091.98E+08 0.OOE+00 3.05E+076.33E+06 0.OOE+00 3.26E+06---------------------.----------

3.59E+09 1.19E+09 1.94E+089.41E+07 1.29E+07 1.92E+072.95E+09 9.81E+08 1.68E+08BA-140 1.29E+08 1.62E+05 8.47E+06 O.OOE+00 5.52E+04 9.29E+04 2.66E+08CE-141 1.97E+05 1.33E+05 1.51E+04 0.00E+00 6.20E+04 0.OOE+00 5.10E+08CE-144 3.29E+07 1.38E+07 1.77E+06 O.OOE+00 8.16E+06 0.OOE+00 1.11E+10PR-143 6.25E+04 2.51E+04ND-147 3.34E+04 3.85E+043.10E+03 O.OOE+00 1.45E+04 0.OOE+00 2.74E+082.31E+03 O.OOE+00 2.25E+04 0.OOE+00 1.85E+08 CY-TM-1 70-300Revision 3Page 165 of 2096.0 TMI-1 GASEOUS EFFLUENT WASTE TREATMENT SYSTEM6.1 Description of the TMI-1 Gaseous Radwaste Treatment System (see Figure 6.1)6.1.1 Waste Gas Systema. Reactor Building:

-Reactor Coolant Drain Tank (RCDT) headerb. Auxiliary Building:

-Vent Header from1. 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 SystemOperability of the Gaseous Waste Treatment System is defined as the ability toremove gas from the vent header/tank gas spaces and store it under a higherpressure in the Waste Gas Decay Tanks for subsequent release.Except for initiating the make up tank sample and waste gas venting and therecycle or disposal of compressed waste gases stored in the waste gas decaytanks, the operation of the waste gas system is entirely automatic.

One wastegas compressor comes on automatically, removing gases from the vent headersystem as required, to maintain the pressure in the system at a maximum ofabout 16.4 psia.

CY-TM-1 70-300Revision 3Page 166 of 209FIGURE 6.1Waste Gas SystemAd LawpI -"Mi a___L CY-TM-1 70-300Revision 3Page 167 of 2097.0 EFFLUENT TOTAL DOSE ASSESSMENT 7.1 Total Dose Calculation The annual (calendar year) dose or dose commitment to any member of thepublic, due to releases of radioactivity and to radiation from uranium fuel cyclesources shall be limited to less than or equal to 25 mrem to the total body or anyorgan 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 within8 kilometers) is calculated by summing the calculated annual doses to criticalorgans of a real individual for liquid effluent using Section 2.1 methodology, forgaseous effluent using Section 5.2.1 and 5.2.2 methodology, and the directradiation from the site from the environmental monitoring program's directradiation monitors.

CY-TM-170-300 Revision 3Page 168 of 2098.0 TMINS RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP)8.1 Monitorinq Program Requirements 8.1.1 ControlsIn accordance with the TMI-1 Tech. Specs. and TMI -2 PDMS Tech.Specs., the radiological environmental monitoring program shall beconducted as specified in Table 8.1.8.1.2 Applicability At all times.8.1.3 Actiona. With the radiological environmental monitoring program notbeing conducted as specified in Table 8.1, prepare and submitto the Commission in the Annual Radiological Environmental Operating Report, a description of the reasons for notconducting the program as required and the plans forpreventing a recurrence.

b. With the level of radioactivity as the result of plant effluents inan 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 fromthe end of the affected calendar

quarter, a special report thatidentifies the cause(s) for exceeding the limit(s) and definesthe corrective actions to be taken to reduce radioactive effluents so that the potential annual dose to a member of thepublic is less than the calendar year limits of ODCM Part IControls 2.2.1.2, 2.2.2.2 and 2.2.2.3 and ODCM Part IIControls 2.2.1.2, 2.2.2.2 and 2.2.2.3.

When more than one ofthe radionuclides in Table 8.2 are detected as the result ofplant effluents in the sampling medium, this report shall besubmitted if:concentration (1) concentration (2) + > 1.0reportinglevel (1) reporting level (2) +When radionuclides other than those in Table 8.2 are detectedand are the result of plant effluents, this report shall beThe methodology and parameters used to estimate the potential annual dose to a member of the public shallbe indicated in this report.

CY-TM-1 70-300Revision 3Page 169 of 209submitted if the potential annual dose* to a member of thepublic is equal to or greater than the calendar year limits ofODCM Part I Controls 2.2.1.2, 2.2.2.2 and 2.2.2.3 and ODCMPart II, Controls 2.2.1.2, 2.2.2.2 and 2.2.2.3.

This report is notrequired if the measured level of radioactivity was not theresult of plant effluents;

however, in such an event, thecondition shall be reported and described in the AnnualRadiological Environmental Operating Report.c. With milk or fresh leafy vegetation samples unavailable fromone or more of the sample locations required by Table 8.1,identify specific locations for obtaining replacement samplesand add them within 30 days to the Radiological Environmental Monitoring Program given in the ODCM. Thespecific locations from which samples were unavailable maythen be deleted from the monitoring program.

Pursuant toTMI-1 Tech. Spec. 6.14 and TMI-2 PDMS Tech. Spec. 6.12,submit in the next Annual Radioactive Effluent Release Reportdocumentation for a change in the ODCM including a revisedfigure(s) and table for the ODCM reflecting the new location(s) with supporting information identifying the cause of theunavailability of samples and justifying the selection of thenew location(s) for obtaining samples.8.1.4 BasesThe radiological monitoring program required by this control providesrepresentative measurements of radiation and of radioactive materials inthose exposure pathways and for those radionuclides which lead to thehighest potential radiation exposures of members of the general publicresulting from the station operation.

This monitoring programimplementsSection IV B.2 of Appendix I to 10CFR50 and therebysupplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels ofradiation are not higher than expected on the basis of the effluentmeasurements 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 onoperational 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 8.4through 8.10 and Maps 8.1 through 8.3, and shall be analyzed pursuant CY-TM-170-300 Revision 3Page 170 of 209to the requirements of Table 8.1 and the detection capabilities requiredby Table 8.3.

CY-TM-170-300 Revision 3Page 171 of 2098.2 Land Use Census8.2.1 ControlsIn accordance with the TMI-1 Tech. Specs. and TMI-2 PDMS Tech.Specs., a Land Use Census shall be conducted and shall identify withina distance of 8 km (5 miles) the location in each of the 16 meteorological sectors of the nearest milk animal, the nearest residence, and thenearest garden* of greater than 50 m2 (500 ft2) producing broad leafvegetation.

8.2.2 Applicability

At all times.8.2.3 Actiona. With a Land Use Census identifying a location(s) that yields acalculated dose or dose commitment greater than the valuescurrently being calculated in ODCM Part I Surveillance 3.2.2.3.1, pursuant to ODCM, Part IV, Section 2.0, identify thenew location(s) in the next Annual Radioactive EffluentRelease Report.b. With a Land Use Census identifying a location(s) that yields acalculated dose or dose commitment (via the same exposurepathway) 20% greater than at a location from which samplesare currently being obtained in accordance with Table 8.1, addthe new location(s) within 30 days to the Radiological Environmental Monitoring Program given in the ODCM. Thesampling location(s),

excluding the control station location, having the lowest calculated dose or dose commitment(s),

viathe same exposure

pathway, may be deleted from thismonitoring program after October 31 of the year in which thisLand Use Census was conducted.

Pursuant to TMI-1 Tech.Spec. 6.14 and TMI-2 PDMS Tech. Spec. 6.12, submit in thenext Annual Radioactive Effluent Release Reportdocumentation for a change in the ODCM including a revisedfigure(s) and table(s) for the ODCM reflecting the newlocation(s) with information supporting the change in samplinglocations.

Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the siteboundary 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 70-300Revision 3Page 172 of 2098.2.4 BasesThis Control is provided to ensure that changes in the use of unrestricted areas are identified and modifications to the monitoring program aremade if required by the results of this census. The best information fromthe door-to-door survey, aerial surveys, or consulting with localagricultural authorities shall be used. This census satisfies therequirements 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) providesassurance that significant exposure pathways via leafy vegetables willbe identified and monitored since a garden of this size is the minimumrequired to produce the quantity (26 kg/yr) of leafy vegetables assumedin Regulatory Guide 1.109 for consumption by a child. To determine thisminimum garden size, the following assumptions were used: 1) that20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage),

and 2) a vegetation yield of2 kg/square meter.8.2.5 Surveillance Requirements The Land Use Census shall be conducted during the growing season atleast once per 12 months, using that information that.will provide thebest results, such as by a door-to-door survey, aerial survey, or byconsulting local agricultural authorities.

The results of the Land UseCensus shall be included in the Annual Radiological Environmental Operating Report pursuant to ODCM, Part IV, Section 1.0.

CY-TM-1 70-300Revision 3Page 173 of 2098.3 Interlaboratory Comparison Program8.3.1 ControlsIn accordance with the TMI-1 Tech. Specs. and TMI-2 PDMS Tech.Specs., analyses shall be performed on radioactive materials suppliedas part of an Interlaboratory Comparison Program which has beenapproved by the Commission (NRC). Only those samples and analyseswhich are required by Table 8.1 shall be performed.

8.3.2 Applicability

At all times.8.3.3 ActionWith analysis not being performed as required above, report thecorrective action taken to prevent a recurrence to the Commission in theAnnual Radiological Environmental Operating Report.8.3.4 BasesThe requirement for participation in an approved Interlaboratory Comparison Program is provided to ensure that independent checks onprecision and accuracy of the measurements of radioactive material inenvironmental sample matrices are performed as part of a qualityassurance program for environmental monitoring in order to demonstrate that the results are reasonably valid for the purpose of Section IV, B.2 ofAppendix I to 10 CFR 50.8.3.5 Surveillance Requirements A summary of the Interlaboratory Comparison Program results shall beincluded in the Annual Radiological Environmental Operating Report.

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

1. AirborneRadioiodine 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 betashould be close to the Site radioactivity following filterdBoundary, in different change .Perform gammasectors, of the highest isotopic analysise oncalculated annual average composite (by location) ground level D/Q. sample quarterly.

One of the samples shouldbe from the vicinity of acommunity having thehighest calculated annualaverage ground level D/Q.And one sample should befrom a control location 15to 30 km distant in a lessprevalent wind direction.

CY-TM-170-300 Revision 3Page 175 of 209TABLE 8.1 (Cont'd)Sample Collection and Analysis Requirements Number of SamplesExposure Pathway and Sampling and Type and Frequency

____ S m Cy oAnlysisb and/or Sample Sample Locationsa CollectionFrequency_

of Analysis

_2. Direct Radiationc Samples from 40 locations Sample Quarterly Analyze for gamma dosefrom Table 8.5 (using either quarterly.

2 dosimeters or at least 1instrument 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 areaof the site boundary; An outer ring of stations, one in each meteorological sector in the 6 to 8 km fromthe site; and the balance ofthe stations to be placed inspecial interest areas suchas population centers,nearby residences,

schools, and in at least oneor two areas to serve ascontrol stations.

CY-TM-1 70-300Revision 3Page 176 of 209TABLE 8.1 (Cont'd)Sample Collection and Analysis Requirements Number of SamplesExposure Pathway and Sampling and Type and Frequency and/or Sample Sample Locationsa Collection Frequencyb of Analysisb

3. Waterborne

a. Surface' Samples from 2 locations Compositeg sample over Perform gamma isotopicfrom Table 8.6. 1 monthly period. analysis' monthly.Composite for tritium* 1 sample from analysis quarterly.

downstream (indicator) location* 1 sample from upstream(control) location (orlocation not influenced bythe station discharge)

b. Drinking Samples from 2 locations Composite 0 sample over Perform gross beta andfrom Table 8.6. 1 monthly period, gamma isotopic analysise monthly.

Perform Sr-90* 1 sample at the location analysis if gross beta ofof the nearest water monthly composite

>10supply that could be times control.

Composite foraffected by the station tritium analysis quarterly.

discharge.

• 1 sample from a controllocation.

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

(Spring and Fall) analysise on each sample.from Table 8.7. 1 1 CY-TM-1 70-300Revision 3Page 177 of 209TABLE 8.1 (Cont'd)Sample Collection and Analysis Requirements Number of SamplesExposure Pathway and Sampling and Type and Frequency and/or Sample Sample Locationsa Collection Frequencyb of Analysisb

4. Ingestion

a. Milkb. FishSamples from 4 locations fromTable 8.8.Samples should be frommilking animals in threelocations within 5 km distancehaving the highest dosepotential.

If there are none,then one sample from milkinganimals in each of three areasbetween 5 to 8 km distantwhere doses are calculated tobe greater than 1 mrem peryear.One sample from milkinganimals at a control location 15to 30 km distant in a lessprevalent wind direction.

Samples from 2 locations fromTable 8.9.* 1 sample of recreationally important bottom feeders and1 sample of recreationally important predators in thevicinity of the stationdischarge.

• 1 sample of recreationally important bottom feeders and1 sample of recreationally important predators from anarea not influenced by thestation discharge.

Sample semimonthly whenanimals are on pasture;monthly at other times.Sample twice per year(Spring and Fall).Perform gamma isotopicanalysise and 1-131analysis on each sample.Composite for Sr-90analysis quarterly.

Perform gamma isotopic' and Sr-90 analysis onedible portions.

CY-TM-1 70-300Revision 3Page 178 of 209TABLE 8.1 (Cont'd)Sample Collection and Analysis Requirements Number of SamplesExposure Pathway and Sampling and Type and Frequency and/or Sample Sample Locationsa Collection Frequencyb of Analysisb

4. Ingestion (contd)c. FoodProductsSamples from 2 locations from Table 8.10 (whenavailable)

• 1 sample of each principle class of food products at alocation in the immediate vicinity of the station.(indicator)

• 1 sample of same speciesor group from a locationnot influenced by thestation discharge.

Samples of three different kinds of broad leaf vegetation grown nearest each of twodifferent offsite locations ofhighest predicted annualaverage ground level D/Q ifmilking sampling is notperformed.

One sample of each of thesimilar broad leaf vegetation grown 15 to 30 km distant ina less prevalent winddirection if milk sampling isnot performed.

Sample at time of harvest.Monthly during growingseasonPerform gammaisotopice, and 1-131,analysis on edibleportions.

Sr-90 analysison green leafyvegetables or vegetation only.Perform gammaisotopice 1-131 analysis.

CY-TM-170-300 Revision 3Page 179 of 209TABLE 8.1 (Cont'd)Sample Collection and Analysis Requirements Table Notationa. Sampling locations are provided in Tables 8.4 through 8.10. They are depicted inMaps 8.1 through 8.3. Deviations are permitted from the required sampling schedule ifspecimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment and other legitimate reasons.

Alldeviations 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), andquarterly (92 days). All surveillance requirements shall be performed within thespecified time interval with a maximum allowable extension not to exceed 25% of thesurveillance 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 andrecording 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 onephosphor; two or more phosphors in a packet are considered as two or moredosimeters.

Film badges shall not be used as dosimeters for measuring directradiation.

d. Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />sor more after sampling to allow for radon and thoron daughter decay. If gross betaactivity in an air particulate sample(s) is greater than ten times the calendar year meanof control samples, Sr-90 and gamma isotopic analysis shall be performed on theindividual 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 thedischarge.

The "downstream sample" shall be taken in an area beyond but near themixing 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 assureobtaining a representative sample.

CY-TM-1 70-300Revision 3Page 180 of 209TABLE 8.2Reporting Levels for Radioactivity Concentrations in Environmental SamplesAirborneParticulate Water or gas Fish Milk Food ProductsAnalysis (pCi/L) _(pCi/m3) (pCi/kg,wet)

(pCi/L) (pCi/kg, wet)H-3 20,000(a)

Mn-54 1000 30,000FE-59 400 10,000Co-58 1000 30,000Co-60 300 10,000Zn-65 300 20,000Sr-90 8 0.1 100 8 100Zr-Nb-95 4001-131 2 0.9 3 100Cs-134 30 10 1000 60 1000Cs-1 37 50 20 2000 70 2000Ba-La-140 200 300(a) For drinking Water samples.

This is 40 CFR Part 141 value.

CY-TM-1 70-300Revision 3Page 181 of 209TABLE 8.3Detection Capabilities for Environmental Sample Analysisa Lower Limit of Detection (LLD)b'cAirborneParticulate Fish Food SedimentWater or Gas (pCi/kg, Milk Products (pCi/kg,Analysis (pCi/L) (pCi/m3) wet) (pCi/L) (pCi/kg,wet) dry)Gross Beta 4 0.01H-3 2000Mn-54 15 130FE-59 30 260Co-58, 60 15 130Zn-65 30 260Zr-95 30Sr-90 2 0.01 10 2 10Nb-95 151-131 1d 0.07 1 60Cs-134 15 0.05 130 15 60 150Cs-137 18 0.06 150 18 80 180Ba-140 60 60La-140 15 15 CY-TM-1 70-300Revision 3Page 182 of 209TABLE 8.3 (Cont'd)Detection Capabilities for Environmental Sample Analysisa Table Notationa. This list does not mean that only these nuclides are to be considered.

Other peaks thatare identifiable, which may be related to plant operations, together with those of theabove 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 ofradioactive 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 SbE & V

• 2.22

• Y

• exp (-X At)Where:LLD is the "a priori" lower limit of detection as defined above, as picocuries per unitmass or volume.Sb is the standard deviation of the background counting rate or of the counting rate of ablank 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 andAt for environmental samples is the elapsed time between sample collection, or end ofthe sample collection period, and time of counting.

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

CY-TM-1 70-300Revision 3Page 183 of 209TABLE 8.3 (Cont'd)Detection Capabilities for Environmental Sample Analysisa Table NotationIt should be recognized that the LLD is defined as an "a priori" (before the fact) limitrepresenting the capability of a measurement system and not as an "a posteriori" (afterthe fact) limit for a particular measurement.

Analyses shall be performed in such amanner 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 AnnualRadiological Environmental Operating Report.d. LLD for drinking water.

CY-TM-170-300 Revision 3Page 184 of 209TABLE 8.4TMINS REMP Station Locations-Air Particulate and Air IodineStation CodeDistance (miles)E1-2F1-3G2-1M2-1A3-1H3-1Q15-10.40.61.41.32.72.213.4Azimuth (0)971121262563571603098.18.18.28.28.28.28.3Map No.TABLE 8.5TMINS REMP Station Locations-Direct Radiation Station CodeDistance (miles)A1-4B1-1B1-2C1-2D1-1E1-2E1-4F1-2G1-3H1-1J1-1J1-3K1 -4L1-1M1-1N1-3P1-1P1-20.30.60.40.30.20.40.20.20.20.50.80.30.20.10.10.10.40.1Azimuth (0)6252350769797112130167176189209236250274303292Map No.8.18.18.18.18.18.18.18.18.18.18.18.18.18.18.18.18.18.1 CY-TM-1 70-300Revision 3Page 185 of 209TABLE 8.5 (Cont'd)TMINS REMP Station Locations-Direct Radiation Station CodeDistance (miles)Q1-2C2-1K2-1M2-1A3-1H3-1R3-1A5-1B5-1C5-1E5-1F5-1G5-1H5-1J5-1K5-1L5-1M5-1N5-1P5-1Q5-1R5-1D6-1E7-1Q9-1B10-1G10-1G15-1J15-1Q1 5-10.20.21.51.21.32.72.22.64.44.94.74.74.74.84.14.94.94.14.35.05.05.04.95.26.78.59.29.714.412.613.4Azimuth (0)321335442002563571603413194382109131158181202228249268284317339668831021128126183309Map No.8.18.18.28.28.28.28.28.28.28.28.28.28.28.28.28.28.28.28.28.28.28.28.28.38.38.38.38.38.38.38.3 CY-TM-1 70-300Revision 3Page 186 of 209TABLE 8.6TMINS REMP Station Locations-Surface WaterStation Code Distance (miles) Azimuth (0) Map No.J1-2 (SW) 0.5 188 8.1A3-2 (SW) 2.7 356 8.2Q9-1 (DW) 8.5 310 8.3Q9-1 (SW) 8.5 310 8.3G15-2 (DW) 13.3 129 8.3G15-3 (DW) 15.7 124 8.3(SW) = Surface Water(DW) = Drinking WaterTABLE 8.7TMINS REMP Station Locations-Aquatic SedimentStation Code Distance (miles) Azimuth (0) Map No.A1-3 0.5 359 8.1K1-3 0.2 212 8.1J2-1 1.4 179 8.2 CY-TM-1 70-300Revision 3Page 187 of 209Station CodeE2-2F4-1G2-1P4-1K15-3TABLE 8.8TMINS REMP Station Locations-Milk Distance (miles) Azimuth (0)1.1 963.2 1041.4 1263.7 29514.4 205Map No.8.28.28.28.28.3TABLE 8.9TMINS REMP Station Locations-Fish Station Code Station LocationIND Downstream of Station Discharge BKG Upstream of Station Discharge Station CodeE1-2H11-2B10-2TABLE 8.10TMINS REMP Station Locations-Food ProductsDistance (miles) Azimuth (0)0.4 971.0 15110.0 31Map No.8.18.18.3 CY-TM-170-300 Revision 3Page 188 of 209MAP 8.1THREE MILE ISLAND NUCLEAR STATIONLOCATIONS OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAMSTATIONS WITHIN I MILE OF THE SITEU U.Z U.4 U _ _ _ _ _MAP 8.1Three Mile Island Nuclear StationLocations of Radiological Environmental Monitoring Program StationsWithin I Mile of the Site CY-TM-170-300 Revision 3Page 189 of 209MAP 8.2THREE MILE ISLAND NUCLEAR STATIONLOCATIONS OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAMSTATIONS WITHIN 5 MILES OF THE SITEMAP 8.2Three Mile Island Nuclear StationLocations of Radiological Environmental Monitoring Program StationsWithin 5 Miles of the Site CY-TM-170-300 Revision 3Page 190 of 209MAP 8.3THREE MILE ISLAND NUCLEAR STATIONLOCATIONS OF RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAMSTATIONS GREATER THAN 5 MILES FROM THE SITEMAP 8.3Three Mile Island Nuclear StationLocations of Radiological Environmental Monitoring Program StationsGreater Than 5 Miles from the Site CY-TM-1 70-300Revision 3Page 191 of 2099.0 PART Ill REFERENCES

1. EPRI NP-3840, RP 1560-3 Final Report, "Environmental Radiation Doses FromDifficult-To-Measure Nuclides,"

January 19852. "Evaluation of the Three Mile Island Nuclear Station Unit 1 to Demonstrate Conformance to the Design Objectives of 10 CFR 50, Appendix I," NuclearSafety Associates, May 19763. 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 andLiquid Effluents from PWR," Revision 1, 19857. NUREG-0133, "Preparation of Radiological Effluent Technical Specifications forNuclear Power Plants,"

October 19788. NUREG-01 72, "AgE-Specific Radiation Dose Commitment Factors For A OnE-Year Chronic Intake,"

November 19779. Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity inSolid Wastes and Releases of Radioactive Materials in Liquid and GaseousEffluents from Light-Water Cooled Nuclear Power Plants,"

Revision 1, June 197410. Regulatory Guide 1.109, "Calculation of Annual Doses to Man from RoutineReleases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR 50, Appendix I," Revision 1, October 197711. Simplified Environmental Effluent Dosimetry System (SEEDS)12. TMI Recirculation Factor Memos, April 12, 1988 and March 17, 198813. 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 LicenseNo. DPR-5016. Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport andDispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors,"

Revision 1, July 197717. TMI-2 PDMS Technical Specifications, attached to Facility License No. DPR-73 CY-TM-1 70-300Revision 3Page 192 of 20918. Radiological Assessment Branch Technical Position on Environmental Monitoring, Revision 1, November 197919. Title 40, Code of Federal Regulations, "Protection of Environment"

20. Regulatory Guide 4.13, "Performance,

Testing, and Procedural Specifications forThermoluminescence Dosimetry:

Environmental Applications,"

Revision 1, July197721. Post-Defueling Monitored Storage Safety Analysis Report (PDMS SAR)

CY-TM-170-300 Revision 3Page 193 of 209PART IVREPORTING REQUIREMENTS CY-TM-1 70-300Revision 3Page 194 of 209PART IVReporting Requirements 1.0 TMI ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT1.1 Routine Radiological Environmental Operating Reports covering the operation ofthe 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 includesummaries, interpretations, and an analysis of trends of the results of theradiological environmental monitoring activities for the report period, including acomparison with prE-operational

studies, with operational controls asappropriate, and with previous environmental monitoring

reports, and anassessment of the observed impacts of the plant operation on the environment.

The reports shall also include the results of Land Use Censuses required by PartIII, Section 8.2.1.3 The Annual Radiological Environmental Operating Reports shall include thesummarized tabulated results of analysis of all radiological environmental samples and environmental radiation measurements required by Part IIITable 8.1 taken during the period pursuant to the locations specified in the tablesand figures in this ODCM, as well as summarized and tabulated results of theseanalyses and measurements in a format similar to the table in the Radiological Assessment Branch Technical

Position, Revision 1, November 1979. In theevent that some individual results are not available for inclusion with the report,the report shall be submitted explaining the reasons for the missing results.

Themissing 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 theradiological environments monitoring program; a map(s) of all sampling locations keyed to a table giving distances and directions from a point that is midwaybetween the Reactor Buildings of TMI-1 and TMI-2; the results of licenseeparticipation 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 byPart III, Table 8.3 was not achievable.

A single submittal may be made for the station.

CY-TM-1 70-300Revision 3Page 195 of 2092.0 TMI ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORTNOTE: A single submittal may be made for the station.

The submittal should combine those sections that are common to both units atthe station however, for units with separate radwaste systems,the submittal shall specify the release of radioactive materialfrom each unit.2.1 Routine Radioactive Effluent Release Reports covering the operations of the unitduring the previous 12 months of operation shall be submitted prior to May 1 forTMI-1 and TMI-2.2.2 The following information shall be included in both Radioactive Effluent ReleaseReports to be submitted each year:The Radioactive Effluent Release Reports shall include a summary of thequantities of radioactive liquid and gaseous effluents and solid waste releasedfrom the unit as outlined in Reg. Guide 1.21, Rev. 1, with data summarized on aquarterly 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 volumeb. Total curie quantity (specify whether determined by measurement orestimate)

c. Principal radionuclides (specify whether determined by measurement orestimate)

d. Type of waste (e.g., spent resin, compacted dry waste, evaporator bottoms)e. Type of shipment (e.g., Isa, type a, type b) andf. 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 gaseousand liquid effluents made during the reporting period.2.5 The Radioactive Effluent Release Reports shall include any changes madeduring the reporting period to the PROCESS CONTROL PROGRAM (PCP)documents and to the OFFSITE DOSE CALCULATION MANUAL (ODCM), aswell 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 70-300Revision 3Page 196 of 2092.6 The Radioactive Effluent Release Reports shall include the instrumentation notreturned to OPERABLE status within 30 days per ODCM Part I Controls 2.1.1 band 2.1.2b, and ODCM Part II Control 2.1.2b.2.7 The Radioactive Effluent Release Report to be submitted shall include an annualsummary of hourly meteorological data collected over the previous year. Thisannual summary may be either in the form of an hour-by-hour listing of windspeed, wind direction, atmosphere stability, and precipitation (if measured) onmagnetic tape, or in the form of joint frequency distribution of wind speed, winddirection, and atmospheric stability.

2.8 The Radioactive Effluent Release Report shall include an assessment of theradiation doses to MEMBERS OF THE PUBLIC due to the radioactive liquid andgaseous effluents released from the unit or station during the previous calendaryear. The meteorological conditions concurrent with the time of release ofradioactive 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 thisODCM.2.9 The Radioactive Effluent Release Report shall include an assessment of theradiation doses from radioactive liquid and gaseous effluents to MEMBERS OFTHE PUBLIC due to their activities inside the SITE BOUNDARY during the reportperiod, to verify compliance with the limits of 1OCFR20.1301 (a)(1). Allassumptions used in making these assessments (i.e., specific

activity, exposuretime and location) shall be included in these reports.2.10 The Radioactive Effluent Release Report shall also include an assessment ofradiation doses to the likely most exposed real individual from reactor releases, and other nearby uranium fuel cycle sources, including doses from primaryeffluent pathways and direct radiation for the previous 12 consecutive months, toshow conformance with 40 CFR 190 "Environmental Radiation Protection Standards for Nuclear Power Operation."

Acceptable methods for calculating thedose contributions from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev. 1.

CY-TM-1 70-300Revision 3Page 197 of 2093.0 PART IV REFERENCES 3.1 Radiological Assessment Branch Technical

Position, Revision 1, November 19793.2 Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity inSolid Wastes and Releases of Radioactive Materials in Liquid and GaseousEffluents from Light-Water-Cooled Nuclear Power Plants,"

Revision 1, June 19743.3 TMI-1 Technical Specifications, attached to Facility Operating License No.DPR-503.4 Title 40, Code of Federal Regulations, "Protection of Environment" 3.5 Regulatory Guide 1.109, "Calculation of Annual Doses to Man from RoutineReleases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR Part 50, Appendix I," Revision 1, October 19773.6 Title 10, Code of Federal Regulations, "Energy"3.7 Regulatory Guide 1.111, "Methods of Estimating Atmospheric Transport andDispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors,"

Revision 1, July 19773.8 Regulatory Guide 1.112, "Calculation of Releases of Radioactive Materials inGaseous and Liquid Effluents from Light-Water-Cooled Power Reactors,"

Revision O-R, April 19763.9 Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents fromAccidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," Revision 1, April 1977 CY-TM-1 70-300Revision 3Page 198 of 209APPENDIX APage 1 of 1P, -Pathway Dose Rate Parameter P, (inhalation)

= k' (BR) DFAI (Eq A-I)Where:Pi = the pathway dose rate parameter for radionuclide,-

i, (other than noble gases) for theinhalation

pathway, in mrem/yr per microcurie/m 3.The dose factors are based onthe critical individual organ for the child age group.k' = conversion factor, 1 E6 pCi/microcurie BR = 3700 m3/yr, breathing rate for child (Reg. Guide 1.109, Rev. 1, Table E-5)DFA= = the maximum organ inhalation dose factor for the infant age group for the ithadionuclide (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 DFAI (mrem/yr per PCi/m3) (Eq A-2)NOTE: The latest NRC Guidance has deleted the requirement todetermine Pi (ground plane) and Pi (food). In addition, thecritical age group has been changed from infant to child.

CY-TM-1 70-300Revision 3Page 199 of 209APPENDIX BPage 1 of IR, -Inhalation Pathway Dose FactorR1 = k' (BR) (DFAi,a,o)

(mrem/yr per microcurie/m

3) (Eq B-I)Where:k' = conversion factor, 1 E6 pCi/microcurie BR = breathing rate, 1400, 3700, 8000, 8000 m3/yr for infant, child, teenager, and adultage 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 anorgan in the selection of DFAi,ao.

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)R1 = (3.7E9) (DFAi,a,o) child (ODCM Part III Table 5.2.2)Rj = (8.0E9) (DFAi,ao) teen and adult (ODCM Part III Tables 5.2.3 and 5.2.4)

CY-TM-1 70-300Revision 3Page 200 of 209APPENDIX CPage 1 of 1R, -Ground Plane Pathway Dose FactorR, = k' k" (SF) (DFGj) [(1-e "it)/X1] (Eq C-1)Where:k' = conversion factor, 1 E6 pCi/microcurie k" = conversion factor, 8760 hr/yr= decay constant for the ith radionuclide, sect = 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 CDFG1 = the ground plane dose conversion factor for the ith radionuclide (mrem/hr perpCi/m2). Values are taken from Table E-6, Reg. Guide 1.109 (Rev. 1), orNUREG 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-170-300 Revision 3Page 201 of 209APPENDIX DPage 1 of 2R, -Grass Cow-Milk Pathway Dose FactorRim k' [(QF X UAP) / (Xi + Xw)] x (Fo) x (r) x (DFLi,a,o) x[((fp x fs)/Yp) + ((I-fp x fs) e -ith)IYs]

E-Xitf (Eq D-1)Where:k' = conversion factor, 1 E6 picocurie/microcurie (pCi/lgci)

QF = cow consumption rate, 50 kg/day, (Reg. Guide 1.109, Rev. 1)goat consumption rate, 6 kg/day, (Reg. Guide 1.109, Rev. 1, Table E-2)UAP = Receptor's milk consumption rate; 330, 330, 400, 310 liters/yr for infant, child,teenager, and adult age groups, respectively (Reg. Guide 1.109, Rev. 1)Yp = agricultural productivity by unit area of pasture feed grass, 0.7 kg/M2(NUREG-0133)

Ys = agricultural productivity by unit area of stored feed, 2.0 kg/M2 (NUREG-0133)

Fm = stable element transfer coefficient (Table E-1, Reg. Guide 1.109, Rev. 1)r = fraction of deposited activity retained in cow's feed grass, 0.2 for particulates, 1.0for 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, sec-1;L, = decay constant for weathering, 5.73 x 10-7 sec-1 (NUREG-0133);

based on a 14day half lifetf = 1.73 x 105 sec, the transport time from pasture to cow to milk to receptor (TableE-15, Reg. Guide 1.109, Rev. 1), or 2 daysth = 7.78 x 106 sec, the transport time from pasture to harvest to cow to milk toreceptor (Table E-15, Reg. Guide 1.109, Rev. 1), or 90 daysfp = 1.0, the fraction of the year that the cow is on pasturefs = 1.0, the fraction of the cow feed that is pasture grass while the cow is on pasture CY-TM-1 70-300Revision 3Page 202 of 209APPENDIX DPage 2 of 2The concentration of tritium in milk is based on the airborne concentration rather than thedeposition.

Therefore, Ri is based on (X/Q):Rct,a,o = k'k"' Fm QF UApDFLt,a,o

(.75 [.5/HI) (Eq D-2)Where:k"' = 1E3 grams/kgH = 8 grams/m3, 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 thecow-milk pathway factor equation.

Fm factor for goat-milk will befrom Table E-2 Reg. Guide 1.109, Rev. 1.

Reference:

ODCM Part III Tables 5.4.1 to 5.4.4 CY-TM-1 70-300Revision 3Page 203 of 209APPENDIX EPage 1 of 2R, -Cow-Meat Pathway Dose FactorRi= k' [(QF X UAP) I (Xi+ X (Ff) x (r) x (DFLi,a,o) x[((fp x fs)/Yp) + ((I-fpfs) e "'ith)/Ys]

x E-xitf (Eq E-1)Where:k' = conversion factor, 1 E6 picocurie/microcurie (pCi/gci)

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, 1.0for 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.XI = decay constant for the radionuclide i, sec1X, = decay constant for weathering, 5.73 x 10- sec1 (NUREG-0133),

based on a 14day half lifetf = 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)Yp = agricultural productivity by unit area of pasture feed grass, 0.7 kg/M2(NUREG-0133)

Ys = agricultural productivity by unit area of stored feed, 2.0 kg/M2 (NUREG-0133) fp = 1.0, the fraction of the year that the cow is on pasturefs = 1.0, the fraction of the cow feed that is pasture grass while the cow is on pasture CY-TM-1 70-300Revision 3Page 204 of 209APPENDIX EPAGE 2 OF 2The concentration of tritium in meat is based on the airborne concentration rather than thedeposition.

Therefore, Ri is based on (X/Q):Rt,a,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 III, Tables 5.6.1 to 5.6.4 CY-TM-170-300 Revision 3Page 205 of 209APPENDIX FPAGE 1 OF IR, -Vegetation Pathway Dose FactorR, k' x [r/ (Y, (k, + kw))] x (DFLi,a,o)

X [(ULA) fL E'XitL + USA fg E-'ith] (Eq F-1)Where:k' = 1 E6 picocurie/microcurie (pCi/jLci)

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 x104 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)]yv = 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 thanthe deposition.

Therefore, Ri is based on (X/Q)Rt,a,o = k'k"' [ULA fL + USA fg] (DFLt,a,o)

(.75 [.5/1H])

(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 70-300Revision 3Page 206 of 209APPENDIX A-F REFERENCES (Page 1 of 4)Parameters Used in Dose Factor Calculations Origin of ValueTable in Section of SitE-Parameter Value R.G. 1.109 NUREG-0133 SpecificFor Pi ***DFA, Each radionuclide E-9 Note 1BR 3700 m3/yr (child) E-5***For Ri (Vegetation)***

r Each element type E-1Yv 2.0 kg/m2 E-15kw 5.73 E-7 sec' 5.3.1.3DFL1 Each age group and radionuclide E-1 1 thru E-14 Note 1UaL Each age group E-5fL 1.0 5.3.1.5tL 8.6 E + 4 seconds E-15Uas Each age group E-5fg 0.76 5.3.1.5th 5.18 E + 6 seconds E-15H 8.0 grams/kg 5.2.1.3***For Ri (Inhalation)***

BR Each age group E-5DFA, Each age group and nuclide E-7 thru E-10 Note 1 CY-TM-1 70-300Revision 3Page 207 of 209APPENDIX A-F REFERENCES (Page 2 of 4)Parameters Used in Dose Factor Calculations Origin of ValueTable in Section of SitE-Parameter Value R.G. 1.109 NUREG-0133 SpecificFor Ri (Ground Plane)SF 0.7 E-1 5DFGj Each radionuclide E-6t 4.73 E + 8 sec 5.3.1.2For R1 (Grass/Animal/Meat)

QF(COW) 50 kg/day E-3QF (Goat) 6 kg/day E-3 Ref. OnlyUap Each age group E-5xw 5.73 E-7 sec1 5.3.1.3Ff (Both) Each element E-1r Each element type E-15DFLI Each age group and nuclide E-1 1 thru E-14 Note 1fp 1.0 5.3.1.3 Note 2f 1.0 5.3.1.3 Note 2Yp 0.7 kg/m3 E-15th 7.78 E + 6 sec E-15Ys 2.0 kg/m2 E-15tf 1.73 E + 6 sec E-15H 8.0 grams/kg 5.2.1.3 CY-TM-1 70-300Revision 3Page 208 of 209APPENDIX A-F REFERENCES (Page 3 of 4)Parameters Used in Dose Factor Calculations Origin of ValueTable in Section of SitE-Parameter Value R.G. 1.109 NUREG-0133 SpecificFor R, (Grass/Cow/Milk)

• • • Q, 50 kg/day E-3Uap Each age group E-5Xw 5.73 E-7 sec1 5.3.1.3Fm Each element E-1r Each element type E-1 5DFL1 Each age group and nuclide E-1 1 thru E-14 Note 1Yp 0.7 kg/mi2 E-15th 7.78 E + 6 sec E-15Ys 2.0 kg/M2 E-15tf 1.73 E + 5 sec E-15fp 1.0 5.3.1.3s 1.0 5.3.1.3H 8.0 grams/kg 5.2.1.3 CY-TM-1 70-300Revision 3Page 209 of 209APPENDIX A-F REFERENCES (Page 4 of 4)NOTES1. Inhalation and ingestion dose factors were taken from the indicated source. For eachage group, for each nuclide, the organ dose factor used was the highest dose factor forthat 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 controland not food or milk. Nevertheless, the goats can be treated as full meat sources wherepresent, despite the fact that their numbers cannot sustain the meat consumption ratesof Table E-5, NUREG-01 33.REFERENCES

1. Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases ofReactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50,Appendix I," Revision 1, October 1977.2. TMI-1 Technical Specifications, attached to Facility Operating License No. DPR-50.3. NUREG-01 33, "Preparation of Radiological Effluent Technical Specifications for NuclearPower Plants,"

October 1978.

50.59 APPLICABILITY REVIEW FORMActivity/Document Number: i -Revision Number:Title: .QC$ _ VZ(:_V ~/ ~IoLS-AA-104-1002 Revision 4Page I of IIAddress the questions below for all aspects of the Activity.

If the answer is yes for any portion of the Activity, apply the identified process(es) to that portion of the Activity.

Note that it is not unusual to have more than one process apply to a given Activity.

SeeSection 4 of the Resource Manual (RM) for additional guidance.

1. Does the proposed Activity involve a change:I. Technical Specifications or Facility Operating License (1OCFR50.90)?

I NO [I YES See Section 4.2.1.1 of the RM2. Conditions of LicenseQuality Assurance program (1 OCFR50.54(a))?

XNO C1 YESSecurity Plan (I OCFR50.54(p))?

NO E] YES See Section 4.2.1.2 of the RMEmergency Plan (IOCFR50.54(q))?

I NO [] YES3. Codes and Standards IST Program Plan (IOCFR50.55a(O)?

[NO Dl YES See Section 4.2.1.3 of the RMISI Program Plan (IOCFR50.55a(g))?

'NO El YES4. ECCS Acceptance Criteria (IOCFR50.46)?

PqNO El YES See Section 4.2.1.4 of the RM5. Specific Exemptions (IOCFR50.12)?

25NO E] YES See Section 4.2.1.5 of the RM6. Radiation Protection Program (IOCFR20)?

KNO [I YES See Section 4.2.1.6 of the RM7. Fire Protection Program (applicable UFSAR or operating license EgNO 0l YES See Section 4.2.1.7 of the RMcondition)?

8. Programs controlled by the Operating License or the Technical ANO [: YES See Section 4.2.1.7 of the RMSpecifications (such as the ODCM).9. Environmental Protection Program [NO E] YES See Section 4.2.1.7 of the RM10. Other programs controlled by other regulations.

toa.p.(,

I ,l0 El NO K"YES See Section 4.2.1 of the RMII. Does the proposed Activity involve maintenance which restores SSCs totheir original condition or involve a temporary alteration supporting D(NOmaintenance that will be in effect during at-power operations for 90 days orless?Ill. Does the proposed Activity involve a change to the:I1. UFSAR (including documents incorporated by reference) that is limitedto reformatting, simplification, removing excessive detail, or minor XNO Cl YES See Section 4.2.3 of the RMeditorial changes as discussed in NEI 96-07 or NEI 98-03?2. Managerial or administrative procedures governing the conduct of [E NO rMYES See Section 4.2.4 of the RMfacility operations (subject to the control of IOCFR50, Appendix B)3. Procedures for performing maintenance activities (subject to IOCFR50,

[I"NO C1 YES See Section 4.2.4 of the RMAppendix B)?4. Regulatory commitment not covered by another regulation based change KNO 0l YES See Section 4.2.3/4.2.4 of the RMprocess (see NEI 99-04)?IV. Does the proposed Activity involve a change to the Independent Spent Fuel (NO El YES See Section 4.2.6 of the RMStorage Installation (ISFSI) (subject to control by 10 CFR 72.48)Check one of the following:

• If all asoects of the Activity are controlled by one or more of the above processes, then a 50.59 Screening is not required andthe Activity may be implemented in accordance with its governing procedure.

El If any portion of the Activity is not controlled by one or more of the above processes, then process a 50.59 Screening for theportion not covered by any of the above processes.

The remaining portion of the activity should be implemented inaccordance with its governing procedure.

0.59 S _ Sign: I Date:(Circle One) (Print name) (Signature)

C 50.59 REVIEW COVERSHEET FORM LS-AA-104-1001 Revision 3Page 1 of 1Station/Unit(s):

TMI -1Activity/Document Number: RW-AA-100 Revision Number: 8Title: Process Control Program for Radioactive WastesNOTE: For 50.59 Evaluations, information on this form will provide the basis for preparing the biennial summary reportsubmitted to the NRC in accordance with the requirements of 10 CFR 50.59(d)(2).

Description of Activity:

(Provide a brief, concise description of what the proposed activity involves.)

Issue rev 8 of corporate procedure RW-AA- 100, Process Control Program for Radioactive Wastes which describes theadministrative program requirements for the Process Control Program (PRP).Rev 8 changes include:* (step 4.1.8) Allow an Exelon Nuclear plant to store radioactive waste from another Exelon Nuclear plant providedformal NRC approval is granted for the transfer of waste.0 (step 4.2.8) modify statement to include " in the pool or loading the processed activated hardware into Dry Casestorage system."* (step 4.4.4) Add statement that Shipment sent off-site storage shall meet the storage site's waste acceptance criteria.

• Minor editorial changes and grammatical error corrections to improve readability of the document.

Reason for Activity:

(Discuss why the proposed activity is being performed.)

RW-AA- 100 rev 8 steps 4.1.8 and 4.4.4 are added to address transfer and storage of radioactive waste from one Exelon Nuclearplant to another Exelon Nuclear plant provided formal NRC approval is granted.

Step 4.2.8 is amended to further clarify thestorage of activated hardware.

Effect of Activity:

(Discuss how the activity impacts plant operations, design bases, or safety analyses described in the UFSAR.)The activity is a change to an administrative procedure and has no impact on plant operations, design basis, or safety analysisdescribed in the UFSAR.Summary of Conclusion for the Activity's 50.59 Review:(Provide justification for the conclusion, including sufficient detail to recognize and understand the essential arguments leadingto the conclusion.

Provide more than a simple statement that a 50.59 Screening, 50.59 Evaluation, or a License Amendment Request; as applicable, is not required.).

.... .... ......The Process Control Program is a tech spec required program to ensure processed Radioactive Wastes meets applicable criteriafor disposal.

RW-AA-100 is an admihistrative procedure governing the conduct of facility operation and is not subject toIOCFR50.59 review in accordance with LS-AA-104-1000 section 4.2.4, Exelon 50.59 Resource Manual.Attachments:

Attach all 50.59 Review forms completed, as appropriate.

Forms Attached:

(Check all that apply.)0 Applicability ReviewE0 50.59 Screening 50.59 Screening No. Rev.EJ 50.59 Evaluation 50.59 Evaluation No. Rev.

Fleet Standard Document

-Corporate Approval Form AD-AA-101-F-09 Page 2 of 2 Revision

01. Step 4.1.8 suggested wording should read: "An Exelon Nuclear plant may store wasteat another Exelon Nuclear plant, provided formal NRC approval has been received forthe transfer of waste."2. Add a step under section 4.4 "Shipment sent for off site storage shall meet the storagesite's waste acceptance criteria3. Add step 4.1.8 "It also possible to store waste from one nuclear plant at another nuclearplant, if formal NRC approval has been received."

4. Modify step 4.2.8 by adding the following words at the end of sentence "in the pool orloading the processed activated hardware into Dry Case storage system.

Fleet Standard Document

-Corporate Approval FormPage 1 of 2AD-AA-101-F-09 Revision 0See AD-AA- 101 for the procedural requirements associated with this Form.Desktop Instruction available on Intranet or through AD functional area.Document Number: RW-AA-100 Revision:

8Title: Process Control Program for Radioactive WastesSuperseded Fleet Standard Documents:

NIA 0 or List:Batch -Are multiple document creations/revisions/cancelations being issued to add/revise/cancel them for similarreouirements?

No M or Yes fl If Yes, then identify the hiohest level Document and Issue Type below.Check only one Document Tvoe: Check only one Issue Type: Incorporated Fleet Items:Level 1 -Continuous Use Procedure El New ElLevel 2 -Reference Use Procedure 0 Revision 0Level 3 -Information Use Procedure 0 Editorial Revision 0T&RM 0 Cancel Document

[Form E] Cancel Revision

__Revision Summary:

See attached Summary of Changes.(Attach additional descdption iR rewuired)

CONFIRM that no commitments (i.e., those steps annotated with CM-X) have been changed or deleted unlessevaluated via completion of LS-AA-1 10 commitment change/deletion form and INITIAL [Preparer]:

RMCPreparer Robert Class 03/07/12 canterwafs0372829 Print Date Location and EUtSite Applicability and Contacts

-Check box and provide name:BRW 0 Michael Gorap DRE 0 Sandy Uvecchl OYS 0 Gonzalo Lamena TMI 0 Tamara HanlonBYR 0 Norma Gordon LAS [ Lynn Kofold-Durden PEA 0 George Tharpe ZIN 0CPS 0 Anthony KllbUm LIM 0 Unda Knapp QDC Debra Cline Other 0Affected Functional Area (FA) -Check box & provide Corporate contact name if FA is affected by this revision:

AD [I ER [] NO C_ RW [IAR [I_ HRO [ OP 0_ SA [IB1O [1 HUO _ OUO _ _SM []Cc [] IT _ _3. PC 0_ SY 0_CY []_ LR [-_ PI _ _ TO []El 0 LS 0_ PL [I WC 0_ENO MAO [ RM 0 -__EP []_ NF I" RP [] -__I___'Validation

-Is substantiating this document's usability via mockup, simulated performance, field walkdown, orbench top review required?

No 0 or Yes [] ff Yes, then attach validation documentation.

If Yes, then print name & sign for completed validation:

4-NOS Review -Excluding NDE, ISI, Peer Inspection or Independent Verification, is this document used to performindependent inspection for acceptance (including field installation inspections, fabrication inspections, receiptinspections, new fuel inspection, etc.), or for certification of Inspection personnel?

No 0 or Yes C0If Yes, then NOS Reviewer to print name & sign for acceptance:

Common Training

-Is common training material being provided?

(Document in the change management how thecommon training material will be developed and pmvided to the sites or attach.)

No 0 or Yes 01Change Management provided in: HU-AA-)4'1 CPaWge Checklist Attached

[I or: As directed by SFAM Zr CFAM Approval Miguel Azar/ /j .03/07/12 Cantera/3240 EPd -V Date Location and ExtSRRS Number 1B.100 Document Site Approval FormPage 2 of 2AD-AA-101-F-O1 Revision 4Continuation B -Is this a T&RM, or Form? NodS or Yes [] If yes, then skip the following section and goContinuation C.PORC R quired: If yes, then enter PORC Numr r (a er P Approved):

Plant Manager Print and Si (whn regu)e by procedure)

_ _,, b _,ateContinuation C -Is this an Editorial Revision;,No]%,or es If yes, then skip the following section and go toContinuation D.Applicable Site. Contact/Site Change Agents (SME): -1 C *-Responsible for Change Management information in---his form or E] HU-AA-1 101 Checklist (attached)

-Responsible to shepherd the document through site review, approval/authorization, and implementation.

Affected Functional Area(s) or Individuals:

-j) Pit ,, U Signature Date Af e FAPrint Signature Date Affected FAPrnt Signature Date Affected FAAttach additional if recfdResources needed to Implement Change: "At rOnly list, if other than Level of Effort.)For ongoing impacts, estimate number of Full Time Equivalents (FTE). If additional resources are needed go to HU-AA-1101.Communication Plan: (e.g., e-mail, Site Paper, Supervisor

Briefing, Voice Mail, etc.)Training Required I Qualifications affected: El Yes If yes, list:(e.g., Supervisory

Briefing, Tailgate

Briefing, Required

Reading, Formal Training, recertification etc.)Update to information infrastructure (e.g. PassPort, PIMS, EDMS w9flows, etc.) required to supportimplementation (including updated forms loaded into PassPort):

AVControlled Document distribution (ref. RM-AA-1 02) or Records Retention Schedule (ref. RM-AA-1 01-1004)impacted:

$No 0l Yes If yes, describe change and list Records Manager contacted:

IContinuation D -If all procedurally required activities associated with this document revision have been completed and the document is ready for implementatio4, then SFAM to print name, sign & date for authorization to implement.

Provide implementation date or, if the Implementation Date is blank or N/A then implementation will be upon theissuance by Records Management per RM requirements.

Authorization below indicates the SFAM or a designee ofthe SFAM has verified the document does not alter or negatively impact compliance with regulatory requirements orL#tOGln ý^mnlfmmnfa IInterim Chg # 01Authorization:

A1/... /4L..L'Z_____

i-PPrintaate Imi, Date Exp. DateSRRS Number 1 B.160 Document Site Approval Form Page 1 of 2AD-AA-1 01 -F-01Revision 4See AD-AA-101 for the procedural requirements associated with this Form.Desktop Instruction available on Intranet or through AD functional area. ý Facility:

DocumetNumber:

P,),.) G (00 Revision:

WTitle: a-F-S, C a cr V .o XcA' ASuperseded Documents:

N/AKor List: WE] Check this box if superseding a document containing commitments,

'notify the Commitment TrabkingCoordinator per LS-AA-1 10 so the CTD can be updated as appropriate.

Environmental Review Applicability

-Is an Environmental Review ap5plicable per EN-AA-1 03? Noj or Yes E]If Yes, then attach Environmental Review documentation required per EN-AA-103.

, IIs this a Fleet Standard Document being pirocessed with form AD-AA-1O1-F-09?

No E] or Yes K If yes, thenattach the completed form AD-AA- 10.-F-09, skip the following

section, and go to Continuation A. 41Qth -Are multiple document creations/revisionslcancelations being issued to add/revise/cancel them for similarredbizements?

No M- or Yes -- If Yes. then identify the hiahest level Document and Issue Tvne belowCheck oni e Document Type: Check only one Issue Type: Incorporated Site ItemsML, AR,Level 1 -Con i us Use Procedure El .New E] PCR, etc):,ýn~ usRevision ELevel 2 -Referenc se Procedure E]Cancel DocumentLevel 3 -Information Us rocedure El Cancel Revision E]RM Non-Permanent ElFo Editorial RevisionRevision Summary:

ý 7(Attach additional description if CONFIRM that no commitments (i.e., those steps CM-X) have been changed or deleted unlessevaluated via completion of LS-AA-1 10 commitmenJ, eiange~deaietion form and INITIAL [Preparer]:

PreprerPrintJ Date Extension Validation

-Is substantiating this cument's usability via mockup, simulatedl*.

ormance, field walkdown, orbench top review required?

NeU or Yes n ] m f Yes, then attach validation documeen.

If Yes, then print narneWgn for completed validation:

NOS Review -_.ý.-'1ding NDE, ISI, Peer Inspection or Independent Verification, is this docurne'ht, sed to perform for acceptance (including field installation inspections, fabrication inspecJ~ts, new fuel inspection, etc.), or for certification of Inspection personnel?No E] or Yes Elthen NOS Reviewer to print name & sign for acceptance: Continuation A -Is this a T&RM, Form, or Editorial Revision?

No PS or Yes L] If yes, then skip the following section and go Continuation B.Impact on Operating and Design Margins -N/A~jor explain:(Attach additional description if required)

No [] Yes I0CFR50.59 Applicable?

Tracking Number (/A,.KNo [] Yes 10CFR72.48 Applicable?

9No El Yes Other Regulatory Process Applicable?

Other Regulatory Process Number: (/u/4[] Yes Potential security impact per SY-AA-500-127?

If Yes, then Security Reviewer acceptance documented bycross discipline review belowNo 0i Yes Surveillance Coordinator Review Required?

If Yes, then Surveillance Coordinator Review documented by cross discipline review belowCross Discipline Reviews:

(list below)-z, f.4,vt.,PrintPrintPrintSignature Data(~I2

_i__ReODate Discipline or Org.Date Discipline or Org.Date Discipline or Org.Signature Signature 1-l auu-nlll "T IQ USQR Approval indicates that all required Cross-Disciplinary reviews have been performed and the reviewers have signed this form. Thisprocedure is technically and functionally accurate f r all functional area /(See ADAA-102)

SOR Approval:ad

/0n --i 2a -Print end Sign Date Dsiln 2013 Annual Radioactive Effluent Release Report for TMIEnclosure 2 -Page 1 of 1Process Control Program for Radioactive Wastes, Revision 8RW-AA-100 (Revision 8 was issued on March 20, 2013) 1RW-AA-1 00e lamRevision 8Ex l " Page 1 of 9Nuclear Level 3 -Information UsePROCESS CONTROL PROGRAM FOR RADIOACTIVE WASTES1. PURPOSE1.1. The purpose of the Process Control Program (PCP) is to:1.1.1. Establish the process and boundary conditions for the preparation of specificprocedures for processing,

sampling, analysis, packaging,

storage, and shipment ofsolid radwaste in accordance with local, state, and federal requirements.

(CM-1)1.1.2. Establish parameters which will provide reasonable assurance that all Low LevelRadioactive Wastes (LLRW), processed by the in-plant waste process systemson-site OR by on-site vendor supplied waste processing

systems, meet theacceptance criteria to a Licensed Burial Facility, as required by 10CFR Part 20,1OCFR Part 61, 10CFR Part 71, 49CFR Parts 171-172, "Technical Position onWaste 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 therequirements as addressed within the Safety Analysis Reports for the low levelradwaste storage facilities for dry and/or processed wet waste.2. TERMS AND DEFINITIONS 2.1. Process Control Program (PCP): The program which contains the currentformulas,

sampling, analysis, tests, and determinations to be made to ensure thatprocessing and packaging of solid radioactive waste based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such away as to assure the waste meets the stabilization criteria specified in 10CFR Parts20, 61 and 71, state regulations, and burial site requirements.

2.2. Solidification:

Liquid waste processed to either an unstable or stable form per1OCFR61 requirements.

Waste solidified does not have to meet the 300-year freestanding monolith criteria.

Approved

formulas, samples and tests do not have tomeet 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 1OCFR61Requirements.

Established

formulas, samples, and tests shall be approved by theNRC in order to meet solidification "stabilization" criteria.

This processing method iscurrently not available, because the NRC recognizes that waste packed in a HighIntegrity Container meets the 300-year stabilization criteria.

In the event that thisprocessing method becomes an acceptable method, then the NRC shall approve thestabilization

formulas, samples, tests, etc.

IRW-AA-100 Revision 8Page 2 of 92.4. Solidification Media: An approved media (e.g. Barnwell

-vinyl ester styrene,cement, bitumen) when waste containing nuclides with greater than 5-year half livesis 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. Theformulas,

sampling, analysis, and test do not require NRC approval, because theHIC meets the stability criteria.

2.4.1. Solidification to an unstable or stable state is performed by vendors, whenapplicable.

Liquid waste solidified to meet stabilization criteria (1OCFR61 and 01-91Branch Technical Requirements) shall have documentation available thatdemonstrates 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 awaste form that meets the requirements of 10CFR Part 61 and applicable burial sitecriteria,

<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 theRequirements of 10CFR61.

The use of HIC's is an alternative to solidification orencapsulation in a steel container to meet burial stability.

HIC's are used to packagedewatered liquid wastes, (e.g. filter cartridges, filter media, resin, sludges, etc), ordry active waste.2.7. Encapsulation:

The process of placing a component (e.g. cartridge filters ormechanical components) into a special purpose disposable container and thencompletely surrounding the waste material with an approved stabilization media,such as cement.2.8. 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 thetreatment of liquid wastes (such as Floor Drains, Chemical Drains and Equipment Drain inputs).2.9. Incineration, RVR, and/or Glass Vitrification of Liquid or Solid: Dry or wetwaste processed via incineration and/or thermal processing where the volume isreduced by thermal means meets 1OCFR61 requirements.

2.10. Compaction:

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

2.11. 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, RW-AA-100 Revision 8Page 3 of 9-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 activitycartridge

filters, paper, wood, glass, plastic, cardboard, hoses, cloth, andmetals, etc, which have become contaminated as a consequence of normaloperating, housekeeping and maintenance activities.

Other radioactive waste generated from cleanup of inadvertent contamination.

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

4. MAIN BODY4.1. Process Control Proqram Requirements 4.1.1. A change to this PCP (Radioactive Waste Treatment Systems) may be madeprovided that the change is reported as part of the annual radioactive effluentrelease 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 liquidradwaste is solidified to a stable/unstable state.4.1.4. When processing liquid radwaste to meet solidification stability using a vendorsupplied solidification system:1. If the vendor has its own Quality Assurance (QA) Program, then the vendorshall ADHERE to its own QA Program and shall have SUBMITTED itsprocess system topical report to the NRC or agreement state.2. If the vendor does not HAVE its own Quality Assurance

Program, then thevendor shall ADHERE to an approved Quality Assurance Topical Reportstandard belonging to the Station or to another approved vendor.

RW-AA-100 Revision 8Page 4 of 94.1.5. The vendor processing system(s) is/are controlled per the following:

1. A commercial vendor supplied processing system(s) may be USED for theprocessing of LLRW streams.2. Vendors that process liquid LLRW at the sites shall MEET applicable QualityAssurance Topical Report and Augmented Quality Requirements.

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

4.1.7. All waste streams processed for burial or long term on-site storage shall MEET thewaste classification and characteristics specified in 1 OCFR Part 61.55, Part 61.56,the 5-83 Branch Technical Position for waste classification, and the applicable burialsite acceptance criteria (for any burial site operating at the time the waste wasprocessed).

4.1.8. An Exelon Nuclear plant may store waste at another Exelon Nuclear plant, providedformal NRC approval has been RECEIVED for the transfer of waste.4.2. General Waste Processing Requirements NOTE: On-site resin processing involves tank mixing and settling, transferring to the station or vendor processing system via resinwater 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 DownCooling).

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 suitablecontainers for processing treatment.

Water from these tanks may be SENT througha 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 wastetreatment or PACKAGED in containers for shipment to offsite vendor for volumereduction processing.

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

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

RW-AA-100 Revision 8Page 5 of 94.2.6. Dry Active Waste (DAW) will be HANDLED and PROCESSED per the following:

1. DAW will be COLLECTED and SURVEYED and may be SORTED forcompactable 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 beENCAPSULATED in an in-situ liner for disposal or SHIPPED to an offsitewaste processor in drums, boxes or steel liners per the vendor site criteria forprocessing and disposal.

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 thesedevices may be routinely REMOVED from the filter vessel and discharged to a FilterSludge Tank or Liner/HIC.

Periodically, the filter sludge may be DISCHARGED tothe vendor processing system for waste treatment onsite or PACKAGED incontainers 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 forshipment or storage in the pool or loading the processed activated hardware into theDry Cask storage system.4.2.9. High Integrity Containers (HIC):1. For disposal at Barnwell, vendors supplying HIC's to the station shallPROVIDE a copy of the HIC Certificate of Compliance, which details specificlimitations on use of the HIC.2. For disposal at Clive, vendors supplying HIC's to the station shall PROVIDE acopy 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 inaccordance with the requirements of the Certificate of Compliance orCertificate of Conformance.

4.2.10. Lubricants and oils contaminated as a consequence of normal operating andmaintenance activities may be PROCESSED on-site (by incineration, for oils meeting10CFR20.2004 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 Areasmay be USED for higher dose DAW storage at Clinton,

Dresden, Quad Cities,Braidwood and Byron.

FRW-AA-100 Revision 8Page 6 of 94.2.13 Certain waste, including flowable solids from holding pond, oily waste separator, cooling tower basin and emergency spray pond, may be disposed of onsite underthe provisions of a 10CFR20.2002 permit. Specific requirements associated with thedisposal shall be incorporated into station implementing procedures.

(CM-2)4.3. Burial Site Requirements 4.3.1. Waste sent directly to burial shall COMPLY with the applicable parts of49CFR171-172,

10CFR61, 10CFR71, and the acceptance criteria for the applicable burial site.4.4. Shippingq and Inspection Requirements 4.4.1. All shipping/storage containers shall be INSPECTED, as required by stationprocedures, for compliance with applicable requirements (Department ofTransportation (DOT), Nuclear Regulatory Commission (NRC), station, on-sitestorage, and/or burial site requirements) prior to use.4.4.2. Containers of solidified liquid waste shall be INSPECTED for solidification qualityand/or dewatering requirements per the burial site, offsite vendor acceptance, orstation acceptance

criteria, as applicable.

4.4.3. Shipments sent to an off site processor shall be INSPECTED to ensure that theapplicable 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 Action4.5.1. 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 beingreleased for shipment are described in applicable station procedures.

If theprovisions of the Process Control Program are not satisfied, then SUSPENDshipments 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 thecause. Additional samples shall be TAKEN, as warranted, to ensure that nofreestanding water is present and solidification requirements are maintained.

4.6. Procedure and Process Reviews4.6.1. The Exelon Nuclear Process Control Program and subsequent changes (other thaneditorial/minor changes) shall be REVIEWED and APPROVED in accordance withthe 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-106.

Changes to the Licensees Controlled Documents, UFSAR, ORM, or TRM are controlled by the provisions of10CFR 50.59.

RW-AA-100 Revision 8Page 7 of 94.6.2. Any changes to the PCP shall be reviewed to determine if reportability is required inthe Annual Radiological Effluent Release Report (ARERR).

The RadwasteSpecialist shall ensure correct information is SUBMITTED to the ODCM programowner prior to submittal of the ARERR.4.6.3. Station processes, applicable site-specific cask manual procedures, or other vendorwaste processing/operating procedures shall be approved per RM-AA-1 02-1006.Procedures related to waste manifests, shipment inspections, and container activitydeterminations are CONTROLLED by Radiation Protection Standard Procedures (RP-AA-600 Series).1. Site waste processing IS CONTROLLED by site operating procedures.

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

4.7. Waste Types, Point of Generation, and Processing MethodMethods of processing and individual vendors may CHANGE due to changingfinancial and regulatory options.

The table below is a representative sample. It isnot intended be all encompassing.

AVAILABLE WASTEWASTE STREAM POINTS OF GENERATION POEING M EPROCESSING METHODSBead Resin Systems -Fuel Pool, Condensate, Dewatering, solidification to anReactor Water Cleanup,

Blowdown, unstable/stable stateEquipment Drain, Chemical and Thermal Processing Volume Control Systems, Floor Drain,Maximum Recycle,

Blowdown, Boric Free Release to a Land FillAcid Recycling System, VendorSupplied Processing

Systems, andPortable Demin SystemPowdered Resin Systems -(Condensate System, Floor Dewatering, solidification to anDrain/Equipment Drain filtration, Fuel unstable/stable statePool) Thermal Processing Concentrated Waste Waste generated from Site Solidification to an unstable/stable Evaporators resulting typically from the stateFloor Drain and Equipment Drain Thermal Processing Systems ThermalProcessing Sludge Sedimentation resulting from various Dewatering, solidification to ansumps, condensers, tanks, cooling unstable/stable statetower, emergency spray pond, holding Thermal Processing pond, and oily waste separators Evaporation on-site or at an offsiteprocessor On-site disposal per 10CFR20.2002 I permit RW-AA-100 Revision 8Page 8 of 9AVAILABLE WASTEWASTE STREAM POINTS OF GENERATION POEING MEPROCESSING METHODSFilter cartridges Systems -Floor/Equipment Drains, Dewatering, solidification to anFuel Pool; cartridge filters are-typically unstable/stable stategenerated from clean up activities Processed by a vendor for volumewithin the fuel pool, torus, etc reduction Dry Active Waste Paper, wood, plastic, rubber, glass, Decon/Sorting for Free Releasemetal, and etc. resulting from daily Compaction/Super-compaction plant activities Thermal Processing by Incineration or glass vitrification Sorting for Free ReleaseMetal melting to an ingotContaminated Oil Oil contaminated with radioactive Solidification unstable statematerials 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 burialTreatment Facilities Metals See DAW See DAWIrradiated Hardware Fuel Pool, Reactor Components Volume Reduction for packaging efficiencies

5. DOCUMENTATION 5.1.1. 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, and2. A determination which documents that the change will maintain the overallconformance of waste products to Federal (10CFR61 and the BranchTechnical Position),

State, or other applicable requirements, including applicable burial site criteria.

6.6.1.REFERENCES 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 haveelected 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 thesafe operation of the facility.

Therefore, the relocation details are not required to bein the CTS or the ITS to provide adequate protection of the public health and safety.

RW-AA-100 Revision 8Page 9 of 96.2. Writers'

References:

6.2.1. Code of Federal Regulations:

10 CFR Part 20, Part 61, Part 71, 49 CFRParts 171-1726.2.2. Low Level Waste Licensing Branch Technical Position on Radioactive WasteClassification, May 19836.2.3. Technical Position on Waste Form (Revision 1), January 19916.2.4. Branch Technical Position on Concentration Averaging and Encapsulation, January 19956.2.5. Regulatory Guide 1.21, Measuring Evaluating, and Reporting Radioactivity in SolidWastes and Releases of Radioactive materials in Liquid and Gaseous Effluents fromLight-Water-Cooled Nuclear Power Plants6.2.6. I.E. Circular 80.18, 1OCFR 50.59 Safety Evaluation for Changes to Radioactive Waste Treatment Systems6.3. Users'

References:

6.3.1. Quality Assurance Program (QATR)6.3.2. LS-AA-106, 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 Report6.4. Station Commitments:

6.4.1. Peach BottomCM-1, T03819, Letter from G.A. Hunger, Jr., dated Sept. 29 1994, transmitting TSCR 93-16 (Improved Technical Specifications).

6.4.2. LimerickCM-2, T03896, 1OCFR20.2002 permit granted to Limerick via letter datedJuly 10, 1996.7. ATTACHMENTS

-None