ML14121A451

Enclosure 2, CY-QC-170-301, Revision 11, Offsite Dose Calculation Manual, Quad Cities, Units 1 and 2

ML14121A451
Person / Time
Site:	Quad Cities
Issue date:	04/29/2014
From:	Exelon Nuclear
To:	Office of Nuclear Reactor Regulation
Shared Package
ML14121A448	List: ML14121A450 ML14121A451 SVP-14-031, Radioactive Effluent Release Report for 2013
References
SVP-14-031 CY-QC-1 70-301, Revision 11
Download: ML14121A451 (308)

Text

{{#Wiki_filter:Enclosure 2 CY-QC-1 70-301, Revision 11, Offsite Dose Calculation Manual

CY-QC-1 70-301 Exelokn Revision 11 Page 1 of 307 Nuclear Level 3 - Information Use January 2013 Offsite Dose Calculation Manual Quad Cities Station Units 1 and 2 Effective: January 2013

CY-QC-170-301 Revision 11 Page 2 of 307 January 2013 ODCM TABLE OF CONTENTS PART I - RADIOLOGICAL EFFLUENT CONTROLS (RECS) PAGE 1.0 USE AND APPLICATION .......................................................................................... 11 1 .1 De fin itio n s ................................................................................................................. 11 1.2 Lo g ica l C o n ne cto rs ........................................................................................................ 16 1 .3 C o m p le tio n T im e s .......................................................................................................... 19 1 .4 F re q u e n cy ................................................................................................................. 30 1.5 REC and RSR Implementation .................................................................................. 35 2.0 through 11.0 NOT USED 12.0 RADIOLOGICAL EFFLUENT CONTROL (REC) and RADIOLOGICAL EFFLUENT SURVEILLANCE REQUIREMENT (RSR) APPLICABILITY ..................................... 37 12.1 NOT USED 12.2 INSTRUMENTATION ................................................................................................ 42 12.2.1 Radioactive Liquid Effluent Monitoring Instrumentation ............................. 42 12.2.2 Radioactive Gaseous Effluent Monitoring Instrumentation ....................... 46 12.3 LIQUID EFFLUENTS ................................................................................................. 52 12.3.1 Liquid Effluent Concentration ..................................................................... 52 12.3.2 Dose From Liquid Effluents ........................................................................ 58 12.3.3 Liquid Radwaste Treatment Systems ........................................................ 60 12.4 GASEOUS EFFLUENTS .......................................................................................... 62 12.4.1 Gaseous Effluent Dose Rates .................................................................... 62 12.4.2 Dose from Noble Gases ............................................................................ 66 12.4.3 Dose From Iodine -131, Iodine -133, Tritium, Carbon - 14, and Radioactive Materials in Particulate Form ..................................................................... 68 12.4.4 Gaseous Radwaste Treatment System .................................................... 69 12.4.5 Ventilation Exhaust Treatment System .................................................... 71 12.4.6 Mark I Containment .................................................................................. 73 12 .5 T O T A L D O S E ................................................................................................................ 74 12 .5 .1 T ota l D ose .............................................................................................. . . 74 12.5.2 Dose Limits for MEMBERS OF THE PUBLIC ............................................ 76 Quad Cities ODCM Table of Contents

CY-QC-170-301 Revision 11 Page 3 of 307 January 2013 ODCM TABLE OF CONTENTS PART I - RADIOLOGICAL EFFLUENT CONTROLS (RECS) PAGE 12.6 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ............................ 78 12.6.1 Radiological Environmental Monitoring Program ....................................... 78 12.6.2 Land Use Census ...................................................................................... 92 12.6.3 Interlaboratory Comparison Program ......................................................... 94 12.6.4 Meteorological Monitoring Instrumentation ................................................ 95 12.7 ADMINISTRATIVE REQUIREMENTS ....................................................................... 97 12.7.1 Station Operating Records ........................................................................ 97 12.7.2 Annual Radiological Environmental Operating Report ............................... 98 12.7.3 Annual Radioactive Effluent Release Report ............................................ 99 12.7.4 Off site Dose Calculation Manual (ODCM) .................................................. 101 12.7.5 Major Changes to Radioactive Waste Treatment Systems (Liquid and G a s e ou s ) ..................................................................................................... 10 2 12 .8 O DC M BA S E S ............................................................................................................. 10 3 PART 11- ODCM

1.0 INTRODUCTION

- ODCM GENERAL INFORMATION ...............................................                                                 133 1.1    S tructure of the O DC M......................................................................................                   133 1.2    R e g u la tio n s .......................................................................................................       13 4 1.2.1        Code of Federal Regulations ...............................................................                         134 1.2.2        Radiological Effluent Technical Standards ..........................................                                137 1.2.3        Offsite Dose Calculation Manual ..........................................................                          137 1.2.4       Overlapping Requirements ..................................................................                         138 1.2.5       Dose Receiver Methodology ................................................................                          138 1.3    Offsite Dose Calculation Parameters ................................................................                             142 1.4    R e fe re nce s ........................................................................................................         14 2 2.0    INSTRUMENTATION AND SYSTEMS ........................................................................                                    155 2 .1   Liqu id R e le a se s .................................................................................................          15 5 2 .1.1       S ystem D escriptio n ..............................................................................                155 2 .1.2       R adiatio n Monitors ...............................................................................                155 2.1.3        Alarm and Trip Setpoints .....................................................................                      156 2.1.4        D ischarge Flow R ates ..........................................................................                   158 Quad Cities ODCM Table of Contents

CY-QC-1 70-301 Revision 11 Page 4 of 307 January 2013 ODCM TABLE OF CONTENTS PART II - ODCM PAGE 2.1.5 Release Limits ..................................................................................... 159 2.1.6 Solidification of W aste/Process Control Program ................................ 160 2.2 Airborne Releases ............................................................................................. 160 2.2.1 System Description .............................................................................. 160 2.2.2 Radiation Monitors ............................................................................... 161 2.2.3 Alarm and Trip Setpoints ..................................................................... 163 2.2.4 Allocation of Effluents from Common Release Points .......................... 165 2.2.5 Dose Projections .................................................................................. 166 3.0 LIQUID EFFLUENTS ................................................................................................... 171 3.1 Liquid Effluent Releases - General Information ................................................ 171 3.2 Liquid Effluent Concentrations .......................................................................... 172 3.3 Liquid Effluent Dose Calculation Requirements ................................................ 174 3.4 Dose Methodology ............................................................................................ 175 3.4.1 Liquid Effluent Dose Method: General ................................................. 175 3.4.2 Potable W ater Pathway ....................................................................... 176 3.4.3 Fish Ingestion Pathway ........................................................................ 177 3.4.4 Offsite Doses ....................................................................................... 177 3.4.5 Drinking W ater ..................................................................................... 178 4.0 GASEOUS EFFLUENTS ............................................................................................. 198 4.1 Gaseous Effluents - General Information ......................................................... 198 4.2 Gaseous Effluents - Dose and Dose Rate Calculation Requirements .............. 199 4.2.1 Instantaneous Dose Rates ................................................................... 199 4.2.2 Time Averaged Dose from Noble Gas ................................................. 202 4.2.3 Time Averaged Dose from Non-Noble Gas Radionuclides .................. 205 5.0 TOTAL DOSE .............................................................................................................. 288 5.1 Total Dose Calculation Requirements ............................................................... 288 5.1.1 Total Effective Dose Equivalent Limits; 10CFR20, 40CFR1 90, and 10 C F R 7 2 ............................................................................................. 28 8 5 .1 .2 IS F S I .................................................................................................... 28 9 5.1.3 Total Dose Calculation Methodology ................................................... 289 5.1.4 BW R Skyshine ..................................................................................... 290 Quad Cities ODCM Table of Contents

CY-QC-170-301 Revision 11 Page 5 of 307 January 2013 ODCM TABLE OF CONTENTS PART II - ODCM PAGE 5.2 BW R Skyshine Calculation ................................................................................ 290 5.3 Onsite Radwaste and Rad Material Storage Facilities ...................................... 292 5.3.1 Process Waste Storage Facilities ........................................................ 292 5.3.2 DAW Storage Facilities ........................................................................ 292 5 .3 .3 IS F S I F acilitie s ..................................................................................... 293 5 .4 M e th o d o log y ...................................................................................................... 293 5 .5 T o ta l D o se ......................................................................................................... 294 5.6 Compliance to Total Dose Limits ....................................................................... 294 5.6.1 Total Effective Dose Equivalent Limit - 10CFR20 Compliance ............ 294 5.6.2 Dose to a MEMBER OF THE PUBLIC in the UNRESTRICTED A R E A ................................................................................................... 29 5 5.6.3 Dose to a MEMBER OF THE PUBLIC in the RESTRICTED AREA .... 295 5.6.4 Total Dose Due to the Uranium Fuel Cycle (40CFR190) ..................... 295 5.7 When Compliance Assessment is Required ..................................................... 296 6.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ............................... 297 6 .1 G e nera l Info rm atio n .......................................................................................... 29 7 6 .2 M o n ito rin g ......................................................................................................... 2 97 6 .3 La nd Use C e nsus .............................................................................................. 29 8 6.4 Interlaboratory Comparison Program ................................................................ 298 Quad Cities ODCM Table of Contents

CY-QC-170-301 Revision 11 Page 6 of 307 January 2013 ODCM TABLE OF CONTENTS LIST OF TABLES PART I - RADIOLOGICAL EFFLUENT CONTROLS (RECS) PAGE Table 1-1 Compliance Matrix ....... 15 Table 12.2.1-1 Radioactive Liquid Effluent Monitoring Instrumentation ............................. 45 Table 12.2.2-1 Radioactive Gaseous Effluent Monitoring Instrumentation ....................... 51 Table 12.3.1-1 Allowable Concentration of Dissolved or Entrained Noble Gases Released from the Site to UNRESTRICTED AREAS in Liquid W a ste ........................................................................................................ . .54 Table 12.3.1-2 Radioactive Liquid Waste Sampling and Analysis Program ....................... 55 Table 12.4.1-1 Radioactive Gaseous Waste Sampling and Analysis Program .................. 63 Table 12.6.1-1 Radiological Environmental Monitoring Program ....................................... 82 Table 12.6.1-2 Reporting Levels for Radioactivity Concentrations in Environmental Samples ........................................................................... 88 Table 12.6.1-3 Detection Capabilities for Environmental Sample Analysis Lower Lim it of D etection ...................................................................................... 89 Table 12.6.4-1 Meteorological Monitoring Instrumentation ................................................ 96 PART II - ODCM Table 1-1 Regulatory Dose Limit Matrix ....................................................................... 139 Table 1-2 Dose Assessment Receivers ....................................................................... 140 Table 1-3 Miscellaneous Dose Assessment Factors: Environmental Parameters ....... 150 Table 1-4 Stable Element Transfer Data ...................................................................... 151 Quad Cities ODCM Table of Contents

CY-QC-170-301 Revision 11 Page 7 of 307 January 2013 ODCM TABLE OF CONTENTS LIST OF TABLES PART II - ODCM PAGE Table 3-1 Bioaccumulation Factors (Bfi) to be Used in the Absence of S ite -S pecific D ata ........................................................................................ 17 9 Table 3-2 Nearest Downstream COMMUNITY WATER SYSTEM ............................... 182 Table 3-3 Aquatic Environmental Dose Parameters .................................................... 183 Table 3-4 Site Specific Potable Water Dose Factors ................................................... 184 Table 3-5 Site Specific Fish Ingestion Dose Factors .................................................... 192 Table 4-1 C ritica l R a ng e s ............................................................................................ 2 16 Table 4-2 Average W ind Speeds ................................................................................. 217 Table 4-3 Maximum Offsite Gamma X/Q ..................................................................... 218 Table 4-4 x/Q and D/Q Maxima at or Beyond the UNRESTRICTED AREA B o u n d a ry ..................................................................................................... 2 19 Table 4-5 X/Q and D/Q Maxima at or Beyond the RESTRICTED AREA Boundary ..... 220 Table 4-6 Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the UNRESTRICTED AREA Boundary for Various N u c lid e s ....................................................................................................... 221 Table 4-7 Parameters for Calculations of N-16 Skyshine Radiation F ro m Q uad C itie s ......................................................................................... 235 Table 4-8 Elevated Joint Frequency Distribution Table Summaries 296 Foot E levatio n D ata ............................................................................................. 2 36 Table 4-9 Mixed Mode Joint Frequency Distribution Table Summaries 196 Foot E le va tio n D a ta ............................................................................................. 2 39 Ground Level Joint Frequency Distribution Table Summaries 33 Foot Table 4-10 E le va tio n D a ta ............................................................................................. 24 2 Table 4-11 S tation C haracteristics ................................................................................. 245 Quad Cities ODCM Table of Contents

CY-QC-170-301 Revision 11 Page 8 of 307 January 2013 ODCM TABLE OF CONTENTS LIST OF TABLES PART 11- ODCM PAGE Table 4-12 Dose Factors for Noble Gases ..................................................................... 246 Table 4-13 External Dose Factors for Standing on Contaminated Ground D FG ij (m rem /hr per pC i/ m 2) ....................................................................... 247 Table 4-14 Ground Plane Dose Factors ........................................................................ 250 Table 4-15 Inhalation D ose Factors ............................................................................... 252 Table 4-16 Vegetation Dose Factors ............................................................................. 260 Table 4-17 Grass-Cow-Milk Dose Factors ..................................................................... 266 Table 4-18 Grass-Goat-Milk Dose Factors .................................................................... 274 Table 4-19 Grass-Cow-Meat Dose Factors ................................................................... 282 Table 6-1 Radiological Environmental Monitoring Program ......................................... 299 Quad Cities ODCM Table of Contents

CY-QC-1770-301 Revision 11 Page 9 of 307 January 2013 ODCM TABLE OF CONTENTS LIST OF FIGURES PART I - RADIOLOGICAL EFFLUENT CONTROLS PAGE None PART II - ODCM Figure 1-1 Radiation Exposure Pathways to Humans ................................................... 141 Figure 1-2 UNRESTRICTED AREA Boundary .............................................................. 153 Figure 1-3 RESTRICTED AREA Boundary ................................................................... 154 Figure 2-1 Simplified Gaseous Radwaste and Gaseous Effluent Flow Diagram ........... 167 Figure 2-2 Simplified Liquid Radwaste Processing Diagram ......................................... 168 Figure 2-3 Simplified Liquid Effluent Flow Diagram ....................................................... 169 Figure 2-4 Simplified Solid Radwaste Processing Diagram .......................................... 170 Figure 4-1 Graphical Representation of Deposition Rate and Joint Frequency D a ta - 2 9 6'. ................................................................................................. 2 38 Figure 4-2 Graphical Representation of Deposition Rate and Joint Frequency D a ta - 19 6 '. ................................................................................................. 24 1 Figure 4-3 Graphical Representation of Deposition Rate and Joint Frequency D a ta - 3 3'. ................................................................................................... 24 4 Figure 6-1 REMP Sample Locations Mile Radius ................................................... 306 Figure 6-2 REMP Sample Locations - 9.3 Mile Radius ................................................ 307 Quad Cities ODCM Table of Contents

CY-QC-170-301 Revision 11 Page 10 of 307 January 2013 I PART I RADIOLOGICAL EFFLUENTS CONTROLS FOR QUAD CITIES STATION UNITS 1 AND 2 Quad Cities ODCM Part I

CY-QC-170-301 Revision 11 Page 11 of 307 January 2013 1.0 USE AND APPLICATION 1.1 Definitions

---------------------------------           NOTE-------------------------------

The defined terms of this section appear in capitalized type and are applicable throughout these OFFSITE DOSE CALCULATION MANUAL Specifications and Bases. Term Definition ACTIONS ACTIONS shall be that part of a Specification that prescribes Required Actions to be taken under designated Conditions within specified Completion Times. ACTUAL DOSE Refers to using known release data to project the dose to the public for the previous month. These data are stored in the database and used to demonstrate compliance with the reporting requirements of RECS. BATCH RELEASE A BATCH RELEASE is the discharge of liquid wastes of a discrete volume. CHANNEL A CHANNEL CALIBRATION shall be the adjustment, as necessary, CALIBRATION of the channel output such that it responds within the necessary range and accuracy to known values of the parameter that the channel monitors. The CHANNEL CALIBRATION shall encompass all devices in the channel required for channel OPERABILITY and the CHANNEL FUNCTIONAL TEST. Calibration of instrument channels with resistance temperature detector (RTD) or thermocouple sensors may consist of an inplace qualitative assessment of sensor behavior and normal calibration of the remaining adjustable devices in the channel. The CHANNEL CALIBRATION may be performed by means of any series of sequential, overlapping, or total channel steps. CHANNEL CHECK A CHANNEL CHECK shall be the qualitative assessment, by observation, of channel behavior during operation. This determination shall include, where possible, comparison of the channel indication and status to other indications or status derived from independent instrument channels measuring the same parameter. Quad Cities ODCM Part I

CY-QC-170-301 Revision 11 Page 12 of 307 January 2013 CHANNEL A CHANNEL FUNCTIONAL TEST shall be the injection of a FUNCTIONAL TEST simulated or actual signal into the channel as close to the sensor as practicable to verify OPERABILITY of all devices in the channel required for channel OPERABILITY. The CHANNEL FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total channel steps. COMMUNITY WATER A public water system which serves at least 15 service connections SYSTEM used by year-round residents or regularly serves at least 25 year-round residents. This definition is per 40CFR141, National Primary Drinking Water Regulations. For purposes of the ODCM, COMMUNITY WATER SYSTEM is further defined as water taken from rivers, lakes or reservoirs (not well water) which is used for drinking. CONTINUOUS A CONTINUOUS RELEASE is the discharge of liquid wastes of a RELEASE non-discrete volume; e.g., from a volume or system that has an input flow during the release. CONTINUOUS Uninterrupted sampling with the exception of sampling SAMPLING interruptions of short duration (no longer than 2 hours) for required surveillances. DOSE EQUIVALENT DOSE EQUIVALENT 1-131 shall be that concentration of 1-131 1-131 (microcuries/gram) that alone would produce the same dose as the quantity and isotopic mixture of 1-131, 1-132, 1-133, 1-134, and 1-135 actually present. The dose conversion factors used for this calculation shall be the inhalation committed dose conversion factors in Federal Guidance Report 11, "Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion," 1989. GASEOUS Any system designed and installed to reduce RADWASTE radioactive gaseous effluents by collecting primary coolant TREATMENT system offgases from the primary system and providing for SYSTEM delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment. IMMEDIATELY IMMEDIATELY means that the required action should be pursued without delay in a controlled manner. LOWER LIMIT OF The LOWER LIMIT OF DETECTION (LLD) is the smallest DETECTION concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal. Quad Cities ODCM Part I

CY-QC-1 70-301 Revision 11 Page 13 of 307 January 2013 MEMBERS OF THE Any individual except when that individual is receiving an PUBLIC OCCUPATIONAL DOSE. MODE A MODE shall correspond to any one inclusive combination of MODE switch position, average reactor coolant temperature, and reactor vessel head closure bolt tensioning specified in Technical Specifications with fuel in the reactor vessel. OCCUPATIONAL The dose received by an individual in the course of DOSE employment in which the individual's assigned duties involve exposure to radiation and/or to radioactive material from licensed and unlicensed sources of radiation, whether in the possession of the licensee or other person. OCCUPATIONAL DOSE does not include dose from background radiation, as a patient from medical practices, from voluntary participation in medical research programs, or as a MEMBER OF THE PUBLIC. OFFSITE DOSE The ODCM shall contain the methodology and parameters used CALCULATION in the calculation of offsite doses resulting from radioactive gaseous MANUAL (ODCM) and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm/Trip Setpoints, and in the conduct of the Environmental Radiological Monitoring Program. The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Radioactive Effluent Release Reports. OPERABLE - A system, subsystem, division, component, or device shall be OPERABILITY OPERABLE or have OPERABILITY when it is capable of performing its specified safety function(s) and all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, division, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s). PROCESS CONTROL Contains the current formulas, sampling, analyses, tests, PROGRAM (PCP) and determinations to ensure that processing and packaging of solid radioactive wastes based on demonstrated processing of ACTUAL or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR 20, 10 CFR 61, and 10 CFR 71, State regulations, burial ground requirements, and other requirements governing the disposal of solid radioactive waste. Quad Cities ODCM Part I

CY-QC-1 70-301 Revision 11 Page 14 of 307 January 2013 PROJECTED DOSE Refers to using known release data from the previous month or estimated release data to forecast a future dose to the public. These data are NOT incorporated into the database. PURGE-PURGING Any controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration, or other operating condition, in such a manner that replacement air or gas is required to purify the confinement. RATED THERMAL RTP shall be a total reactor core heat transfer rate to the reactor POWER (RTP) coolant as defined in Technical Specifications. RADIOLOGICAL A compilation of the various regulatory requirements, EFFLUENT CONTROLS surveillance and bases, commitments and/or components of (RECS) the radiological effluent and environmental monitoring programs for Quad Cities Station. To assist in the understanding of the relationship between effluent regulations, ODCM equations, RECS and related Technical Specification requirements, Table 1-1 is a matrix that relates these various components, as well as the Radiological Environmental Monitoring Program fundamental requirements. SITE BOUNDARY That line beyond which the land is not owned, leased, or otherwise controlled by licensee as defined in ODCM Part II Figure 1-3. SOURCE CHECK The qualitative assessment of channel response when the channel sensor is exposed to a radioactive source. UNRESTRICTED An area, access to which is neither limited nor controlled by the AREA licensee. VENTILATION EXHAUST Any System designed and installed to reduce gaseous radioiodine TREATMENT SYSTEM or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment. Such a system is not considered to have any effect on noble gas effluents. Engineered Safety Features Atmospheric Cleanup Systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components. VENTING The controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration, or other operating condition, in such a manner that replacement air or gas is not provided or required. Vent, used in system names does not imply a VENTING process. Quad Cities ODCM Part I

CY-QC-170-301 Revision 11 Page 15 of 307 January 2013 I Table 1-1 COMPLIANCE MATRIX ODCM Technical Regulation Dose Component Limit Equation RECS Specification 10 CFR 50 1. Gamma air dose and beta air dose due to airborne 4-4 REC 12.4.2 5.5.4.h Appendix I radioactivity in effluent plume. 4-5

a. Total body and skin dose due to airborne 4-6 N/A N/A radioactivity in effluent plume are reported 4-7 only if certain gamma and beta air dose criteria are exceeded.

2. Dose for all organs and all four age groups due to 4-8 REC 12.4.3 5.5.4.i iodines and particulates in effluent plume. All pathways are considered.

3. Dose for all organs and all four age groups due to 3-3 REC 12.3.2 5.5.4.d radioactivity in liquid effluents.

10 CFR 20 1. Total Dose, totaling all external dose components 5-3 REC 12.5.2 5.5.4.c (direct, ground and plume shine) and internal dose (all pathways, both airborne and liquid-borne). 40 CFR 190 1. Total body dose due to direct dose, ground and 5-2 REC 12.5.1 5.5.4.j (now by plume shine from all sources at a station. reference, also part of 2. Organ doses to an adult due to all pathways. 5-3 10 CFR 20) Technical 1. "Instantaneous" whole body, skin, and organ dose 4-1 REC 12.4.1 5.5.4.g Specifications rates due to radioactivity in airborne effluents. For 4-2 the organ dose, only child inhalation is considered. 4-3

2. "Instantaneous" concentration limits for liquid 3-1 REC 12.3.1 5.5.4.b effluents.

10CFR50 1. Implement environmental monitoring program. N/A REC 12.6.1 N/A Appendix I Section IV.B.2 10CFR50 1. Land Use Census N/A REC 12.6.2 N/A Appendix I Section IV.B.3 10CFR50 1. Interlaboratory Comparison Program N/A REC 12.6.3 N/A Appendix I Section IV.B.2 Technical 1. Radioactive Effluent Release Report NA 12.7.3 5.6.3 Specifications 10CFR50 1. Annual Radiological Environmental Operating N/A 12.7.2 N/A Appendix I Report Section IV.B.2 and Technical Specifications Quad Cities ODCM Part I

CY-QC-1 70-301 Revision 11 Page 16 of 307 January 2013 1.0 USE AND APPLICATION 1.2 Logical Connectors PURPOSE The purpose of this section is to explain the meaning of logical connectors. Logical connectors are used in ODCM to discriminate between, and yet connect, discrete Conditions, Required Actions, Completion Times, Surveillances, and Frequencies. The only logical connectors that appear in ODCM are AND and OR. The physical arrangement of these connectors constitutes logical conventions with specific meanings. BACKGROUND Several levels of logic may be used to state Required Actions. These levels are identified by the placement (or nesting) of the logical connectors and by the number assigned to each Required Action. The first level of logic is identified by the first digit of the number assigned to a Required Action and the placement of the logical connector in the first level of nesting (i.e., left justified with the number of the Required Action). The successive levels of logic are identified by additional digits of the Required Action number and by successive indentations of the logical connectors. When logical connectors are used to state a Condition, Completion Time, Surveillance, or Frequency, only the first level of logic is used, and the logical connector is left justified with the statement of the Condition, Completion Time, Surveillance, or Frequency. EXAMPLES The following examples illustrate the use of logical connectors. (continued) Quad Cities ODCM Part I

CY-QC-1 70-301 Revision 11 Page 17 of 307 January 2013 1.2 Logical Connectors EXAMPLE 1.2-1 EXAMPLES (continued) ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. REC not met. A.1 Verify... AND A.2 Restore... In this example, the logical connector AND is used to indicate that, when in Condition A, both Required Actions A.1 and A.2 must be completed. (continued) Quad Cities ODCM Part I

CY-QC-170-301 Revision 11 Page 18 of 307 January 2013 1.2 Logical Connectors EXAMPLES EXAMPLE 1.2-2 (continued) ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. REC not met. A.1 Trip... OR A.2.1 Verify... AND A.2.2.1 Reduce... OR A.2.2.2 Perform... OR A.3 Align This example represents a more complicated use of logical connectors. Required Actions A.1, A.2 and A.3 are alternate choices, only one of which must be performed as indicated by the use of the logical connector OR and the left justified placement. Any one of these three ACTIONS may be chosen. IfA.2 is chosen, then both A.2.1 and A.2.2 must be performed as indicated by the logical connector AND. Required Action A.2.2 is met by performing A.2.2.1 or A.2.2.2. The indented position of the logical connector OR indicates that A.2.2.1 and A.2.2.2 are alternative choices, only one of which must be performed. Quad Cities ODCM Part I

CY-QC-170-301 Revision 11 Page 19 of 307 January 2013 1.0 USE AND APPLICATION 1.3 Completion Times PURPOSE The purpose of this section is to establish the Completion Time convention and to provide guidance for its use. BACKGROUND ODCM Radiological Effluent Controls (RECs) specify minimum requirements for ensuring safe operation of the unit. The ACTIONS associated with a REC state Conditions that typically describe the ways in which the requirements of the REC can fail to be met. Specified with each stated Condition are Required Action(s) and Completion Times. DESCRIPTION The Completion Time is the amount of time allowed for completing a Required Action. It is referenced to the time of discovery of a situation (e.g., inoperable equipment or variable not within limits) that requires entering an Actions Condition unless otherwise specified, providing the unit is in a MODE or specified condition stated in the Applicability of the REC. Required Actions must be completed prior to the expiration of the specified Completion Time. An Actions Condition remains in effect and the Required Actions apply until the Condition no longer exists or the unit is not within the REC Applicability. If situations are discovered that require entry into more than one Condition at a time within a single REC (multiple Conditions), the Required Actions for each Condition must be performed within the associated Completion Time. When in multiple Conditions, separate Completion Times are tracked for each Condition starting from the time of discovery of the situation that required entry into the Condition. Once a Condition has been entered, subsequent divisions, subsystem, components or variables expressed in the Condition, discovered to be inoperable or not within limits, will not result in separate entry into the Condition unless specifically stated. The Required Actions of the Condition continue to apply to each additional failure, with Completion Times based on initial entry into the Condition. (continued) Quad Cities ODCM Part I

CY-QC-1 70-301 Revision 11 Page 20 of 307 January 2013 1.3 Completion Times DESCRIPTION However, when a subsequent division, subsystem, component, or (continued) variable expressed in the Condition is discovered to be inoperable or not within limits, the Completion Time(s) may be extended. To apply this Completion Time extension, two criteria must first be met. The subsequent inoperability:

a. Must exist concurrent with the first inoperability; and

b. Must remain inoperable or not within limits after the first inoperability is resolved.

The total Completion Time allowed for completing a Required Action to address the subsequent inoperability shall be limited to the more restrictive of either:

a. The stated Completion Time, as measured from the initial entry into the Condition, plus an additional 24 hours; or

b. The stated Completion Time as measured from discovery of the subsequent inoperability.

The above Completion Time extension does not apply to those RECs that have exceptions that allow completely separate re-entry into the Condition (for each division, subsystem, component, or variable expressed in the Condition) and separate tracking of Completion Times based on this re-entry. These exceptions are stated in individual RECs. The above Completion Time extension does not apply to a Completion Time with a modified "time zero." This modified "time zero" may be expressed as a repetitive time (i.e., "once per 8 hours," where the Completion Time is referenced from a previous completion of the Required Action versus the time of Condition entry) or as a time modified by the phrase "from discovery . . ." example 1.3-3 illustrates one use of this type of Completion Time. The 10 day Completion Time specified for Condition A and B in example 1.3-3 may not be extended. EXAMPLES The following examples illustrate the use of Completion Times with different types of Conditions and changing Conditions. (continued) Quad Cities ODCM Part I

CY-QC-170-301 Revision 11 Page 21 of 307 January 2013 1.3 Completion Times EXAMPLES EXAMPLE 1.3-1 (continued) ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and B.1 Be in MODE 3. 12 hours associated Completion Time not met. AND B.2 Be in MODE 4. 36 hours Condition B has two Required Actions. Each Required Action has its own separate Completion Time. Each Completion Time is referenced to the time that Condition B is entered. The Required Actions of Condition B are in to be in MODE 3 within 12 hours AND in MODE 4 within 36 hours. A total of 12 hours is allowed for reaching MODE 3 and a total of 36 hours (not 48 hours) is allowed for reaching MODE 4 from the time that Condition B was entered. If MODE 3 is reached within 6 hours, the time allowed for reaching MODE 4 is the next 30 hours because the total time allowed for reaching MODE 4 is 36 hours. If Condition B is entered while in MODE 3, the time allowed for reaching MODE 4 is the next 36 hours. (continued) Quad Cities ODCM Part I

CY-QC-170-301 Revision 11 Page 22 of 307 January 2013 1.3 Completion Times EXAMPLES EXAMPLE 1.3-2 (continued) ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One monitor A. 1 Restore monitor to 7 days inoperable. OPERABLE status. B. Required Action and B.1 Be in MODE 3. 12 hours associated Completion Time not met. AND B.2 Be in MODE 4. 36 hours When a monitor is declared inoperable, Condition A is entered. If the monitor is not restored to OPERABLE status within 7 days, Condition B is also entered and the Completion Time clocks for Required Action B.1 and B.2 start. If the inoperable monitor is restored to OPERABLE status after Condition B is entered, Condition A and B are exited, and therefore, the Required Actions of Condition B may be terminated. When a monitor is declared inoperable while the first monitor is still inoperable, Condition A is not re-entered for the second monitor. REC 12.0.3 is entered, since the ACTIONS do not include a Condition from more than one inoperable monitor. The Completion Time clock for Condition A does not stop after REC 12.0.3 is entered, but continues to be tracked from the time Condition A was initially entered. While in REC 12.0.3, if one of the inoperable monitors is restored to OPERABLE status and the Completion Time for Condition A has not expired, REC 12.0.3 may be exited and operation continued in accordance with Condition A. (continued) Quad Cities ODCM Part I

CY-QC-170-301 Revision 11 Page 23 of 307 January 2013 1.3 Completion Times EXAMPLES EXAMPLE 1.3-2 (continued) While in REC 12.0.3, if one of the inoperable monitors is restored to OPERABLE status and the Completion Time for Condition A has expired, REC 12.0.3 may be exited and operation continued in accordance with Condition B. The Completion Time for Condition B is tracked from the time the Condition A Completion Time expired. On restoring one of the monitors to OPERABLE status, the Condition A Completion Time is not reset, but continues from the time the first monitor was declared inoperable. This Completion Time may be extended if the monitor restored to OPERABLE status was the first inoperable monitor. A 24 hour extension to the stated 7 days is allowed, provided this does not result in the second monitor being inoperable for > 7 days. (continued) Quad Cities ODCM Part I

CY-QC-1770-301 Revision 11 Page 24 of 307 January 2013 1.3 Completion Times EXAMPLES EXAMPLE 1.3-3 (continued) ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One Function X A.1 Restore Function X 7 days subsystem subsystem to inoperable. OPERABLE status. AND 10 days from discovery of failure to meet the REC B. One Function Y B.1 Restore Function Y 72 hours subsystem subsystem to inoperable. OPERABLE status. AND 10 days from discovery to meet REC C. One Function X C.1 Restore Function X 72 hours subsystem subsystem to inoperable. OPERABLE status. AND OR One Function Y subsystem C.2 Restore Function Y 72 hours inoperable, subsystem to OPERABLE status. (continued) Quad Cities ODCM Part I

CY-QC-1 70-301 Revision 11 Page 25 of 307 January 2013 1.3 Completion Times EXAMPLES EXAMPLE 1.3-3 (continued) When one Function X subsystem and one Function Y subsystem are inoperable, Condition A and Condition B are concurrently applicable. The Completion Times for Condition A and Condition B are tracked separately for each subsystem, starting from the time each subsystem was declared inoperable and the Condition was entered. A separate Completion Time is established for Condition C and tracked from the time the second subsystem was declared inoperable (i.e., the time the situation described in Condition C was discovered). If Required Action C.2 is completed within the specified Completion Time, Conditions B and C are exited. If the Completion Time for Required Action A.1 has not expired, operation may continue in accordance with Condition A. The remaining Completion Time in Condition A is measured from the time the affected subsystem was declared inoperable (i.e., initial entry into Condition A). The Completion Times of Conditions A and B are modified by a logical connector, with a separate 10 day Completion Time measured from the time it was discovered the REC was not met. In this example, without the separate Completion Time, it would be possible to alternate between Conditions A, B, and C in such a manner that operation could continue indefinitely without ever restoring systems to meet the REC. The separate Completion Time modified by the phrase "from discovery of failure to meet the Control" is designed to prevent indefinite continued operation while not meeting the REC. This Completion Time allows for an exception to the normal "time zero" for beginning the Completion Time "clock." In this instance, the Completion Time "time zero" is specified as commencing at the time the associated Condition was entered. (continued) Quad Cities ODCM Part I

CY-QC-170-301 Revision 11 Page 26 of 307 January 2013 1.3 Completion Times EXAMPLES EXAMPLE 1.3-4 (continued) ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more A.1 Restore 4 hours instruments instrument(s) to inoperable. OPERABLE status. B. Required Action and B.1 Be in MODE 3. 12 hours associated Completion Time not met. AND B.2 Be in MODE 4. 36 hours A single Completion Time is used for any number of instruments inoperable at the same time. The Completion Time associated with Condition A is based on the initial entry into Condition A and is not tracked on a per instrument basis. Declaring subsequent instruments inoperable, while Condition A is still in effect, does not trigger the tracking of separate Completion Times. Once one of the instruments has been restored to OPERABLE status, the Condition A Completion Time is not reset, but continues from the time the first instrument was declared inoperable. The Completion Time may be extended if the instrument restored to OPERABLE status was the first inoperable instrument. The Condition A Completion Time may be extended for up to 4 hours provided this does not result in any subsequent instrument being inoperable for > 4 hours. If the Completion Time of 4 hours (plus the extension) expires while one or more instruments are still inoperable, Condition B is entered. (continued) Quad Cities ODCM Part I

CY-QC-1 70-301 Revision 11 Page 27 of 307 January 2013 1.3 Completion Times EXAMPLES EXAMPLE 1.3-5 (continued) ACTIONS

                    ---------------------------      NOTE ------------------------------------

Separate Condition entry is allowed for each inoperable instrument. CONDITION REQUIRED ACTION COMPLETION TIME A. One or more A.1 Restore 4 hours instruments instrument(s) to inoperable. OPERABLE status. B. Required Action and B.1 Be in MODE 3. 12 hours associated Completion Time not met. AND B.2 Be in MODE 4. 36 hours The Note above the Actions Table is a method of modifying how the Completion Time is tracked. If this method of modifying how the Completion Time is tracked was applicable only to a specific Condition, the Note would appear in that Condition rather than at the top of the Actions Table. The Note allows Condition A to be entered separately for each inoperable instrument, and Completion Times tracked on a per instrument basis. When an instrument is declared inoperable, Condition A is entered and its Completion Time starts. If subsequent instruments are declared inoperable, Condition A is entered for each instrument and separate Completion Times start and are tracked for each instrument. If the Completion Time associated with an instrument in Condition A expires, Condition B is entered for that instrument. If the Completion Times associated with subsequent instruments in Condition A expire, Condition B is entered separately for each instrument and separate Completion Times start and are tracked for each instrument. If a instrument that caused entry into Condition B is restored to OPERABLE status, Condition B is exited for that instrument. Since the Note in this example allows multiple Condition entry and tracking of separate Completion Times, Completion Time extensions do not apply. (continued) Quad Cities ODCM Part I

CY-QC-1770-301 Revision 11 Page 28 of 307 January 2013 1.3 Completion Times EXAMPLES EXAMPLE 1.3-6 (continued) ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One channel A.1 Perform RSR 12.x.x.x. Once per 8 inoperable, hours OR A.2 Reduce THERMAL 8 hours POWER to < 50% RTP. B. Required Action and B. 1 Be in MODE 3. 12 hours associated Completion Time not met. Entry into Condition A offers a choice between Required Action A.1 or A.2. Required Action A.1 has a "once per" Completion Time, which qualifies for the 25% extension, per RSR 12.0.2 to each performance after the initial performance. The initial 8 hour interval of Required Action A.1 begins when Condition A is entered and the initial performance of Required Action A.1 must be completed within the first 8 hour interval. If Required Action A.1 is followed and the Required Action is not met within the Completion Time (plus the extension allowed by RSR 12.0.2), Condition B is entered. If Required Action A.2 is followed and the Completion Time of 8 hours is not met, Condition B is entered. If after entry into Condition B, Required Action A.1 or A.2 is met, Condition B is exited and operation may then continue in Condition A. (continued) Quad Cities ODCM Part I

CY-QC-1 70-301 Revision 11 Page 29 of 307 January 2013 1.3 Completion Times EXAMPLE 1.3-7 EXAMPLES (continued) ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One subsystem A.1 Verify affected 1 hour inoperable, subsystem isolated. AND AND Once per 8 hours thereafter A.2 Restore subsystem to 72 hours OPERABLE status. B. Required Action and B.1 Be in MODE 3. 12 hours associated Completion Time not met. AND B.2 Be in MODE 4. 36 hours Required Action A.1 has two Completion Times. The 1 hour Completion Time begins at the time the Condition is entered and each "Once per 8 hours thereafter" interval begins upon performance of Required Action A.1. If after Condition A is entered, Required Action A.1 is not met within either the initial 1 hour or any subsequent 8 hour interval from the previous performance (plus the extension allowed by RSR 12.0.2), Condition B is entered. The Completion Time clock for Condition A does not stop after Condition B is entered, but continues from the time Condition A was initially entered. If Required Action A. 1 is met after Condition B is entered, Condition B is exited and operation may continue in accordance with Condition A, provided the Completion Time for Required Action A.2 has not expired. IMMEDIATE When "Immediately" is used as a Completion Time, the Required Action COMPLETION should be pursued without delay and in a controlled manner. TIME Quad Cities ODOM Part I

CY-QC-1 70-301 Revision 11 Page 30 of 307 January 2013 1.0 USE AND APPLICATION 1.4 Frequency PURPOSE The purpose of this section is to define the proper use and application of Frequency requirements. DESCRIPTION Each ODCM Radiological Effluent Surveillance Requirement (RSR) has a specified Frequency in which the Surveillance must be met in order to meet the associated ODCM REC. An understanding of the correct application of the specified Frequency is necessary for compliance with the RSR. The "specified Frequency" is referred to throughout this section and each of the Requirements of Section 12.0, ODCM Surveillance Requirement (RSR) Applicability. The "specified Frequency" consists of the requirements of the Frequency column of each RSR, as well as certain Notes in the Surveillance column that modify performance requirements. Sometimes special situations dictate when the requirements of a Surveillance are to be met. They are "otherwise stated" conditions allowed by RSR 12.0.1. They may be stated as clarifying Notes in the Surveillance, as part of the Surveillance, or both. Example 1.4-4 discusses these special situations. Situations where a Surveillance could be required (i.e., its Frequency could expire), but where it is not possible or not desired that it be performed until sometime after the associated REC is within its Applicability, represent potential RSR 12.0.4 conflicts. To avoid these conflicts, the RSR (i.e., the Surveillance or the Frequency) is stated such that it is only "required" when it can be and should be performed. With a RSR satisfied, RSR 12.0.4 imposes no restriction. The use of "met" or "performed" in these instances conveys specified meanings. A Surveillance is "met" only when the acceptance criteria are satisfied. Known failure of the requirements of a Surveillance, even without a Surveillance specifically being "performed," constitutes a Surveillance not "met." "Performance" refers only to the requirement to (continued) Quad Cities ODCM Part I

CY-QC-170-301 Revision 11 Page 31 of 307 January 2013 1.4 Frequency DESCRIPTION specifically determine the ability to meet the acceptance criteria. (continued) RSR 12.0.4 restrictions would not apply if both the following conditions are satisfied:

a. The Surveillance is not required to be performed; and

b. The Surveillance is not required to be met or, even if required to be met, is not known to be failed.

EXAMPLES The following examples illustrate the various ways that Frequencies are specified. In these examples, the Applicability of the REC (REC not shown) is MODES 1, 2, and 3. EXAMPLE 1.4-1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Perform CHANNEL CHECK 12 hours Example 1.4-1 contains the type of RSR most often encountered in the ODCM. The Frequency specifies an interval (12 hours) during which the associated Surveillance must be performed at least one time. Performance of the Surveillance initiates the subsequent interval. Although the Frequency is stated as 12 hours, an extension of the time interval to 1.25 times the interval specified in the Frequency is allowed by RSR 12.0.2 for operational flexibility. The measurement of this interval continues at all times, event when the RSR is not required to be met per RSR 12.0.1 (such as when the equipment is inoperable, a variable is outside specified limits, or the unit is outside the Applicability of the REC). If the interval specified by RSR 12.0.2 is exceeded while the unit is in a MODE or other specified condition in the Applicability of the REC, (continued) Quad Cities ODCM Part I

CY-QC-170-301 Revision 11 Page 32 of 307 January 2013 1.4 Frequency EXAMPLES EXAMPLE 1.4-1 (continued) and the performance of the Surveillance is not otherwise modified (refer to Examples 1.4-3 and 1.4-4), then RSR 12.0.3 becomes applicable. If the interval as specified by RSR 12.0.2 is exceeded while the unit is not in a MODE or other specified condition in the Applicability of the REC for which performance of the RSR is required, the Surveillance must be performed within the Frequency requirements of RSR 12.0.2 prior to entry into the MODE or other specified condition. Failure to do so would result in a violation of RSR 12.0.4. EXAMPLE 1.4-2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Verify flow is within limits. Once within 12 hours after > 25% RTP AND 24 hours thereafter Example 1.4-2 has two Frequencies. The first is a one time performance Frequency, and the second is of the type shown in Example 1.4-1. The logical connector "AND" indicates that both Frequency requirements must be met. Each time reactor power is increased from a power level

                     < 25% RTP to > 25% RTP, the Surveillance must be performed within 12 hours.

(continued) Quad Cities ODCM Part I

CY-QC-170-301 Revision 11 Page 33 of 307 January 2013 1.4 Frequency EXAMPLES EXAMPLE 1.4-2 (continued) The use of "once" indicates a single performance will satisfy the specified Frequency (assuming no other Frequencies are connected by "AND"). This type of Frequency does not qualify for the extension allowed by RSR 12.0.2.

                    "Thereafter" indicates future performances must be established per RSR 12.0.2, but only after a specified condition is first met (i.e., the "once" performance in this example). If reactor power decreases to < 25% RTP, the measurement of both intervals stops. New intervals start upon reactor power reaching 25% RTP.

EXAMPLE 1.4-3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

                    ------------------ NOTE -------------------------

Not required to be performed until 12 hours after > 25% RTP. Perform channel adjustment. 7 days The interval continues whether or not the unit operation is < 25% RTP between performances. As the Note modifies the required performance of the Surveillance, it is construed to be part of the "specified Frequency." Should the 7 day interval be exceeded while operation is < 25% RTP, this Note allows 12 hours after power reaches > 25% RTP to perform the Surveillance. The Surveillance is still considered to be within the "specified Frequency." Therefore, if the Surveillance were not performed within the 7 day interval (plus the extension allowed by RSR 12.0.2), but operation was

                     < 25% RTP, (continued)

Quad Cities ODCM Part I

CY-QC-1770-301 Revision 11 Page 34 of 307 January 2013 1.4 Frequency EXAMPLES EXAMPLE 1.4-3 (continued) it would not constitute a failure of the RSR or failure to meet the REC. Also, no violation of RSR 12.0.4 occurs when changing MODES, even with the 7 day Frequency not met, provided operation does not exceed 12 hours with power > 25% RTP. Once the unit reaches 25% RTP, 12 hours would be allowed for completing the Surveillance. If the Surveillance were not performed within this 12 hour interval, there would then be a failure to perform a Surveillance within the specified Frequency, and the provisions of RSR 12.0.3 would apply. EXAMPLE 1.4-4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

                     ------------------- NOTE       --------------

Only required to be met in MODE 1. Verify leakage rates are within limits. 24 hours Example 1.4-4 specifies that the requirements of this Surveillance do not have to be met until the unit is in MODE 1. The interval measurement for the Frequency of this Surveillance continues at all times, as described in Example 1.4-1. However, the Note constitutes an "otherwise stated" exception to the Applicability of this Surveillance. Therefore, if the Surveillance were not performed within the 24 hour interval (plus the extension allowed by RSR 12.0.2), but the unit was not in MODE 1, there would be no failure of the RSR nor failure to meet the REC. Therefore, no violation of RSR 12.0.4 occurs when changing MODES, even with the 24 hour Frequency exceeded, provided the MODE change was not made into MODE 1. Prior to entering MODE 1 (assuming again that the 24 hour Frequency were not met), RSR 12.0.4 would require satisfying the RSR. Quad Cities ODCM Part I

CY-QC-1770-301 Revision 11 Page 35 of 307 January 2013 1.0 USE AND APPLICATION 1.5 REC and RSR Implementation The ODCM provides those limitations upon plant operations which are part of the licensing basis for the station but do not meet the criteria for continued inclusion in the Technical Specifications. It also provides information which supplements the Technical Specifications by implementing the requirements of Technical Specification Sections 5.5.1, 5.5.4, 5'6.2, and 5.6.3. Nothing in the ODCM shall supersede any Technical Specification requirement. RECs and RSRs are implemented the same as Technical Specifications (see ODCM 12.0 Applicability). However, RECs and RSRs are treated as plant procedures and are not part of the Technical Specifications. Therefore the following exceptions apply:

a. Violations of the Action or Surveillance requirements in a REC are not reportable as conditions prohibited by, or deviations from, the Technical Specifications per 10 CFR 50.72 or 10 CFR 50.73.

b. Power reduction or plant shutdowns required to comply with the Actions of a REC are not reportable per 10 CFR 50.72 or 10 CFR 50.73.

Quad Cities ODCM Part I

CY-QC-1 70-301 Revision 11 Page 36 of 307 January 2013 2.0 through 11.0 NOT USED INTENTIONALLY BLANK Sections 2.0 through 11.0 are not used in the ODCM in order to maintain the Original ODCM numbering convention Quad Cities ODCM Part I

CY-QC-1770-301 Revision 11 Page 37 of 307 January 2013 12.0 RADIOLOGICAL EFFLUENT CONTROL (REC) and RADIOLOGICAL EFFLUENT SURVEILLANCE REQUIREMENT (RSR) APPLICABILITY REC 12.0.1 RECs shall be met during the MODES or other specified conditions in the Applicability, except as provided in REC 12.0.2. REC 12.0.2 Upon discovery of a failure to meet a REC, the Required Actions of the associated Conditions shall be met, except as provided in REC 12.0.5. If the REC is met or is no longer applicable prior to expiration of the specified Completion Time(s), completion of the Required Action(s) is not required, unless otherwise stated. REC 12.0.3 When a REC is not met and the associated ACTIONS are not met, an associated ACTION is not provided, or if directed by the associated ACTIONS, action shall be initiated within 1 hour to:

a. Implement appropriate compensatory actions as needed;

b. Verify that the plant is not in an unanalyzed condition(s) or that a required safety function is not compromised by the inoperabilities; and

c. Within 12 hours, obtain Shift Manager or designee approval of the compensatory actions and the plan for exiting REC 12.0.3.

Exceptions to this REC are stated in the individual RECs. Where corrective measures are completed that permit operation in accordance with the REC or ACTIONS, completion of the actions required by REC 12.0.3 is not required. REC 12.0.3 is only applicable in MODES 1, 2, and 3. REC 12.0.4 When a REC is not met, entry into a MODE or other specified condition in the Applicability shall not be made except when the associated ACTIONS to be entered permit continued operation in the MODE or other specified condition in the Applicability for an unlimited period of time. This REC shall not prevent changes in (continued) Quad Cities ODCM Part I

CY-QC-1 70-301 Revision 11 Page 38 of 307 January 2013 12.0 RADIOLOGICAL EFFLUENT CONTROL (REC) and RADIOLOGICAL EFFLUENT SURVEILLANCE REQUIREMENT (RSR) APPLICABILITY REC 12.0.4 MODES or other specified conditions in the Applicability that are (continued) required to comply with ACTIONS or that are part of a shutdown of the unit. Exceptions to this REC are stated in the individual RECs. REC 12.0.4 is only applicable for entry into a MODE or other specified condition in the Applicability in MODES 1, 2, and 3. REC 12.0.5 Equipment removed from service or declared INOPERABLE to comply with ACTIONS may be returned to service under administrative control solely to perform testing required to demonstrate its OPERABILITY or the OPERABILITY of other equipment. This is an exception to REC 12.0.2 for the system returned to service under administrative control to perform the testing required to demonstrate OPERABILITY. REC 12.0.6 RECs, including associated ACTIONS, shall apply to each unit individually, unless otherwise indicated. Whenever the REC refers to a system or component that is shared by both units, the ACTIONS will apply to both units simultaneously. Quad Cities ODCM Part I

CY-QC-170-301 Revision 11 Page 39 of 307 January 2013 12.0 RADIOLOGICAL EFFLUENT CONTROL (REC) and RADIOLOGICAL EFFLUENT SURVEILLANCE REQUIREMENT (RSR) APPLICABILITY RSR 12.0.1 RSRs shall be met during the MODES or other specified conditions in the Applicability for individual RECs, unless otherwise stated in the RSR. Failure to meet a RSR, whether such failure is experienced during the performance of the RSR or between performances of the RSR, shall be failure to meet the REC. Failure to perform a RSR within the specified Frequency shall be failure to meet the REC except as provided in RSR 12.0.3. RSRs do not have to be performed on inoperable equipment or variables outside specified limits. RSR 12.0.2 The specified Frequency for each RSR is met if the RSR is performed within 1.25 times the interval specified in the Frequency, as measured from the previous performance or as measured from the time a specified condition of the Frequency is met. For Frequencies specified as "once," the above interval extension does not apply. If a Completion Time requires periodic performance on a "once per..." basis, the above Frequency extension applies to each performance after the initial performance. Exceptions to this RSR are stated in the individual RSRs. RSR 12.0.3 If it is discovered that a RSR was not performed within its specified Frequency, then compliance with the requirement to declare the REC not met may be delayed, from the time of discovery, up to 24 hours or up to the limit of the specified Frequency, whichever is greater. This delay period is permitted to allow performance of the RSR. A risk evaluation shall be performed for any Surveillance delayed greater than 24 hours and the risk impact shall be managed. If the RSR is not performed within the delay period, the REC must immediately be declared not met, and the applicable Condition(s) must be entered. When the RSR is performed within the delay period and the RSR is not met, the REC must immediately be declared not met, and the applicable Condition(s) must be entered. (continued) Quad Cities ODCM Part I

CY-QC-1 70-301 Revision 11 Page 40 of 307 January 2013 12.0 RADIOLOGICAL EFFLUENT CONTROL (REC) and RADIOLOGICAL EFFLUENT SURVEILLANCE REQUIREMENT (RSR) APPLICABILITY RSR 12.0.4 Entry into a MODE or other specified condition in the Applicability of a REC shall not be made unless the REC's RSRs have been met within their specified Frequency. This provision shall not prevent entry into MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit. RSR 12.0.4 is only applicable for entry into a MODE or other specified condition in the Applicability in MODES 1, 2, and 3. RSR 12.0.5 RSRs shall apply to each unit individually, unless otherwise indicated. Quad Cities ODCM Part I

CY-QC-170-301 Revision 11 Page 41 of 307 January 2013 I 12.1 NOT USED INTENTIONALLY BLANK Quad Cities ODCM Part I

CY-QC-1 70-301 Revision 11 Page 42 of 307 January 2013 12.2 INSTRUMENTATION 12.2.1 Radioactive Liquid Effluent Monitoring Instrumentation REC 12.2.1 The effluent monitoring instrumentation in Table 12.2.1-1 shall be OPERABLE with alarm setpoints set to ensure the limits of REC 12.3.1 are not exceeded. The instrument alarm setpoints shall be determined in accordance with the ODCM. APPLICABILITY: When flow is present in the system.

            -------- NOTE ------------------------------------

1. Separate Condition entry is allowed for each inoperable instrument channel.

2. The provisions of REC 12.0.4 are not applicable.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Required instrument A.1 Suspend release of radioactive Immediately channel alarm /trip liquid effluents monitored by the setpoint less instrument channel. conservative than required. OR A.2 Enter the Condition referenced Immediately in Table 12.2.1-1 for the instrument channel. B. One or more required B.1 Enter the Condition referenced in Immediately instrument channels with Table 12.2.1-1 for the instrument less than the minimum channel number of OPERABLE channels for reasons other than Condition A. C. Service Water Effluent C.1 Collect and analyze grab Once per 12 hours Gross Activity Monitor samples for beta or gamma with less than the activity at an LLD < 1 E-07 minimum number of PCi/ml. OPERABLE channels. AND C.2 Restore the instrument 30 days channel to OPERABLE status. (continued) Quad Cities ODCM Part I

CY-QC-1 70-301 Revision 11 Page 43 of 307 January 2013 CONDITION REQUIRED ACTION COMPLETION TIME D. Liquid Radwaste Effluent D.1 Perform RSR 12.3.1.1 on at least Prior to each release Gross Activity Monitor two independent samples of the with less than the tank's contents. minimum number of OPERABLE channels. AND D.2 Perform independent verification Prior to each release of the release rate calculations and discharge line valve line-up using at least two technically qualified members of the facility staff. AND D.3 Return instrument channel to 30 days OPERABLE status. E. Required Action and E.1 Suspend release of radioactive Immediately Completion Time of effluents via this pathway. Condition D not met F. Liquid Radwaste Flow -------------- NOTE ------------ Rate Monitor with less Pump curves may be used to than the minimum estimate flow. number of OPERABLE channels. F.1 Estimate flow rate for the Once per 4 hours release in progress via the affected pathway. AND F.2 Return instrument channel to 30 days OPERABLE status.

          -NOTE ----------------  G.1 Explain why the inoperability was    In accordance with Required Action G.1 shall            not corrected in a timely manner   Section 12.7.3 be completed if this                 in the next Radioactive Effluent Condition is entered.                Release Report.

G. Required Action C.2, or D.3, or F.2 and associated Completion Time not met. Quad Cities ODCM Part I

CY-QC-170-301 Revision 11 Page 44 of 307 January 2013 SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENT FREQUENCY RSR 12.2.1.1 Perform CHANNEL CHECK. 24 hours RSR 12.2.1.2 Perform CHANNEL CHECK. The test shall verify flow 24 hours during periods of release. RSR 12.2.1.3 Perform CHANNEL FUNCTIONAL TEST. The test shall 92 days also demonstrate that the control room alarm annunciates if any of the following conditions exist, where applicable:

a. Instrument indicates measured levels above the alarm setpoint.

b. Circuit failure.

c. Instrument indicates a downscale failure.

d. Instrument controls not set in the normal operating mode.

RSR 12.2.1.4 Perform SOURCE CHECK. For instrument 3, the test 24 months shall include observing instrument response during a discharge. RSR 12.2.1.5 Perform CHANNEL CALIBRATION. For instruments 1, 24 months 2, and 3, the test shall also include a SOURCE CHECK per RSR 12.2.1.4. Quad Cities ODCM Part I

CY-QC-170-301 Revision 11 Page 45 of 307 January 2013 Table 12.2.1-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION CONDITION MINIMUM REFERENCED NUMBER FROM OF REQUIRED OPERABLE ACTION A.2 SURVEILLANCE INSTRUMENT CHANNELS AND B.1 REQUIREMENTS

1. Service Water Effluent RSR 12.2.1.1 RSR 12.2.1.3 Gross Activity Monitor 1 C RSR 12.2.1.4 (Unit 1) RSR 12.2.1.4 RSR 12.2.1.5

2. Service Water Effluent RSR 12.2.1.1 RSR 12.2.1.3 Gross Activity Monitor 1 C RSR 12.2.1.4 (Unit 2) RSR 12.2.1.4 RSR 12.2.1.5

3. Liquid Radwaste RSR 12.2.1.3 Effluent Gross Activity 1 D RSR 12.2.1.4 Monitor RSR 12.2.1.5 RSR 12.2.1.5

4. Liquid Radwaste RSR 12.2.1.2 Effluent Flow Rate 1 F RSR 12.2.1.5 Monitor Quad Cities ODCM Part I

CY-QC-170-301 Revision 11 Page 46 of 307 January 2013 12.2 INSTRUMENTATION 12.2.2 Radioactive Gaseous Effluent Monitoring Instrumentation REC 12.2.2 The Radioactive Gaseous Effluent Monitoring Instrumentation in Table 12.2.2-1 shall be OPERABLE with alarm/trip setpoints set to ensure the limits of REC 12.4.1, REC 12.4.2, and REC 12.4.3 are not exceeded. The alarm trip/setpoints shall be determined in accordance with the ODCM. APPLICABILITY: According to Table 12.2.2-1.

              -------- NOTE          ---------------------

1. Separate Condition entry is allowed for each inoperable instrument channel.

2. The provisions of REC 12.0.4 are not applicable.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Required instrument A.1 Suspend release of Immediately channel alarm /trip setpoint radioactive gaseous effluents less conservative than monitored by the instrument required. channel. OR A.2 Enter the Condition Immediately referenced in Table 12.2.2-1 for the instrument channel. B. One or more required B.1 Enter the Condition Immediately instrument channels with referenced in Table 12.2.2-1 less than the minimum for the instrument channel. number of OPERABLE channels for reasons other than Condition A. C. Steam Jet Air Ejector C.1 Verify at least one Main Immediately Radiation Monitors with Chimney Noble Gas Activity less than the minimum Monitor OPERABLE. number of OPERABLE channels. AND C.2 Restore at least one 72 hours instrument channel to OPERABLE status. (continued) Quad Cities ODCM Part I

CY-QC-1770-301 Revision 11 Page 47 of 307 January 2013 CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Be in MODE 2 with all main 12 hours associated Completion steam lines isolated. Times of Required Action C.1 or C.2 not met. AND D.2 Restore instrument channel 30 days to OPERABLE status. E. Main Chimney Noble Gas E.1 Obtain grab samples. Once per 8 hours Activity Monitor with less than the minimum number AND of OPERABLE channels. E.2 Analyze grab samples for Within 24 hours noble gas emitters. following each grab sample AND E.3 Restore instrument channel 30 days to OPERABLE status. F. Main Chimney High Range F.1 Establish the preplanned 72 hours Noble Gas Monitor with alternate method of less than the minimum monitoring the appropriate number of OPERABLE parameters. channels. AND F.2 Restore instrument channel 7 days to OPERABLE status. G. Main Chimney Iodine G.1 Establish CONTINUOUS Immediately Sampler with less than the SAMPLING with auxiliary minimum number of sampling equipment as OPERABLE channels. required in Table 12.4.1-1. AND G.2 Restore instrument channel 30 days to OPERABLE status. (continued) Quad Cities ODCM Part I

CY-QC-170-301 Revision 11 Page 48 of 307 January 2013 CONDITION REQUIRED ACTION COMPLETION TIME H. Main Chimney Particulate H.1 Establish CONTINUOUS Immediately Sampler with less than the SAMPLING with auxiliary minimum number of sampling equipment as OPERABLE channels. required in Table 12.4.1-1. AND H.2 Restore instrument channel 30 days to OPERABLE status.

1. Main Chimney Sampler 1.1 Estimate sample flow rate. Once per 4 hours Flow Rate Monitor with less than the minimum number AND of OPERABLE channels.

1.2 Restore instrument channel 30 days to OPERABLE status. J. Main Chimney Flow Rate J.1 Estimate flow rate. Once per 4 hours Monitor with less than the minimum number of AND OPERABLE channels. J.2 Restore instrument channel 30 days to OPERABLE status. K. Reactor Building Vent K.1 Suspend release of Immediately Noble Gas Monitor with radioactive effluents via this less than the minimum pathway. number of OPERABLE channels. AND K.2 Restore instrument channel 30 days to OPERABLE status. L. Reactor Building Vent L.1 Establish CONTINUOUS Immediately Iodine Sampler with less SAMPLING with auxiliary than the minimum number sampling equipment as of OPERABLE channels. required in Table 12.4.1-1. AND L.2 Restore instrument channel 30 days to OPERABLE status. (continued) Quad Cities ODCM Part I

CY-QC-170-301 Revision 11 Page 49 of 307 January 2013 CONDITION REQUIRED ACTION COMPLETION TIME M. Reactor Building Vent M.1 Establish CONTINUOUS Immediately Particulate Sampler with SAMPLING with auxiliary less than the minimum sampling equipment as number of OPERABLE required in Table 12.4.1-1. channels. AND M.2 Restore instrument channel 30 days to OPERABLE status. N. Reactor Building Vent N.1 Estimate sample flow rate. Once per 4 hours Sampler Flow Rate Monitor with less than the minimum AND number of OPERABLE channels. N.2 Restore instrument channel 30 days to OPERABLE status.

----- --NOTE --------

Required Action 0.1 shall be completed if this Condition is entered.

0. Required Action and 0.1 Submit Special Report to 30 days associated Completion NRC outlining the action(s)

Time of Required Action taken, the cause of the F.2 not met. inoperability, and the plans and schedule for restoring the system to OPERABLE status.

-------     NOTE--------

Required Action P.1 shall be completed if this condition is entered. P. Required Action and P.1 Explain why the inoperability In accordance with associated Completion was not corrected in a timely Section 12.7.3 Time of Required Action manner in the next D.2, or E.3, or G.2, or H.2, Radioactive Effluent Release or 1.2, or J.2, or K.2, or L.2, Report. or M.2, or N.2 not met. Quad Cities ODCM Part I

CY-QC-170-301 Revision 11 Page 50 of 307 January 2013 SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENT FREQUENCY RSR 12.2.2.1 Perform CHANNEL CHECK. 24 hours RSR 12.2.2.2 Perform CHANNEL CHECK. The test shall verify that 7 days the instrument is in place and functioning properly. RSR 12.2.2.3 Perform SOURCE CHECK. 31 days RSR 12.2.2.4 Perform SOURCE CHECK. 92 days RSR 12.2.2.5 Perform SOURCE CHECK. 24 months

              -------- NOTE ------------------------------------

For instruments 2.e and 3.d, the test shall be performed on local switches providing low flow alarm. RSR 12.2.2.6 Perform CHANNEL FUNCTIONAL TEST. The test shall 92 days also demonstrate that the control room alarm annunciates if any of the following conditions exist, where applicable:

a. Instrument indicates measured levels above the alarm setpoint.

b. Circuit failure.

c. Instrument indicates a downscale failure.

d. Instrument controls not set in the normal operating mode.

RSR 12.2.2.7 Perform CHANNEL CALIBRATION. The test shall 24 months include a CHANNEL FUNCTIONAL TEST per RSR 12.2.2.6. Quad Cities ODCM Part I

CY-QC-1 70-301 Revision 11 Page 51 of 307 January 2013 Table 12.2.2-1 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION CONDITION APPLICABLE REFERENCED MODES OR MINIMUM FROM OTHER NUMBER OF REQUIRED SPECIFIED OPERABLE ACTION A.2 SURVEILLANCE INSTRUMENT CONDITIONS CHANNELS AND B.1 REQUIREMENTS RSR 12.2.2.1

1. Steam Jet Air Ejector RSR 12.2.2.5 Radiation Monitor (a) C RSR 12.2.2.6 RSR 12.2.2.7

2. Main Chimney Monitoring System RSR 12.2.2.1 2.a. Main Chimney Noble RSR 12.2.2.3 Gas Activity Monitor At all times (b) E RSR 12.2.2.6 RSR 12.2.2.7 2.b. Main Chimney High RSR 12.2.2.1 Range Noble Gas At all times (b) F RSR 12.2.2.6 Monitor RSR 12.2.2.6 RSR 12.2.2.7 2.c. Main C At all times (b) G RSR 12.2.2.2 Sampler 2.d. Main Chimney H RSR 12.2.2.2 Particulate Sampler At all times (b) 1 2.e. Main Chimney RSR 12.2.2.1 Sampler Flow Rate At all times (b) 1 1 RSR 12.2.2.6 Monitor RSR 12.2.2.7 2.f. Main Chimney Flow RSR 12.2.2.1 Rate Monitor At all times (b) 1 RSR 12.2.2.7

3. Reactor Building Vent Monitoring System per Unit) 3.a. Reactor Building Vent RSR 12.2.2.1 Noble Gas Activity At all times (b) 1 K RSR 12.2.2.6 Monitor RSR 12.2.2.6 RSR 12.2.2.7 3.b. Reactor B At all times (b) L RSR 12.2.2.2 Iodine Sampler 3-c. Reactor B At all times (b) M RSR 12.2.2.2 Particulate Sampler 3.d. Reactor Building Vent RSR 12.2.2.1 Sampler Flow Rate At all times (b) 1 N RSR 12.2.2.6 Monitor RSR 12.2.2.7 (a) Modes 1, 2, and 3 with any main steam line not isolated and steam jet air ejector in operation.

(b) Required when Actual or Potential discharge is in progress (see Bases Section 12.8: 12.2.2 page 116) Quad Cities ODCM Part I

CY-QC-1 70-301 Revision 11 Page 52 of 307 January 2013 12.3 LIQUID EFFLUENTS 12.3.1 Liquid Effluent Concentration REC 12.3.1 The concentration of radioactive material released from the site to areas at or beyond the SITE BOUNDARY shall be limited to:

a. 10 times the concentration specified in 10 CFR 20.1001-20.2402 Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases; and

b. the values listed in Table 12.3.1-1 for total activity concentration for all dissolved or entrained noble gases.

APPLICABILITY: At all times.

                    ----------------------- NOTE        --------------------

The provisions of REC 12.0.4 are not applicable. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Concentration of radioactive A.1 Decrease the release rate Immediately material released to areas at of radioactive materials to or beyond the SITE restore concentration to BOUNDARY exceeding within limits. limits. OR A.2 Increase the dilution flow Immediately rate to restore concentration within limits. OR A.3 Decrease the release rate Immediately of radioactive materials and increase the dilution flow rate to restore concentration within limits. Quad Cities ODCM Part I

CY-QC-170-301 Revision 11 Page 53 of 307 January 2013 SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENT FREQUENCY RSR 12.3.1.1 Determine radioactivity content of batch release tanks In accordance with using calculational methods described in the ODCM to Table 12.3.1-2 determine that the concentration of radioactive material in UNRESTRICTED AREAS is within the limits of REC 12.3.1. RSR 12.3.1.2 Determine radioactivity content of plant continuous In accordance with releases using calculational methods described in the Table 12.3.1-2 ODCM to determine that the concentration of radioactive material in UNRESTRICTED AREAS is within the limits of REC 12.3.1. Quad Cities ODCM Part I

CY-QC-170-301 Revision 11 Page 54 of 307 January 2013 Table 12.3.1-1 ALLOWABLE CONCENTRATION OF DISSOLVED OR ENTRAINED NOBLE GASES RELEASED FROM THE SITE TO UNRESTRICTED AREAS IN LIQUID WASTE NUCLIDE ALLOWABLE CONCENTRATION (PCi/ml)* Kr-85m 2 x 10-4 Kr-85 5 x 10-4 Kr-87 4 x 10-5 Kr-88 9 x 10-5 Ar-41 7 x 10-5 Xe-1 31 m 7 x 10-4 Xe-133m 5 x 10-4 Xe-133 6 x 104 Xe-1 35m 2 x 10-4 Xe-135 2 x 10-4 Computed from Equation 20 of ICRP Publication 2 (1959), adjusted for infinite cloud submersion in water, and R = 0.01 rem/week, density = 1.0 g/cc and Pw/Pt = 1.0. Quad Cities ODCM Part I

CY-QC-1770-301 Revision 11 Page 55 of 307 January 2013 Table 12.3.1-2 (Page 1 of 3) RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM LOWER LIMIT LIQUID RELEASE SAMPLING MINIMUM ANALYSIS TYPE OF ACTIVITY OF DETECTION TYPE FREQUENCY FREQUENCY ANALYSIS (LLD)(a) (pCi/ml) Principal Gamma 5x10-7 BATCH RELEASE A. Tanks Prior to each Prior to each Batch Emitters(e) Batch"d) 1-131 1x10-6 Prior to each 31 days Gross Alpha x10.7 Batch(d) Composite(b) H-3 1x10-5 Prior to each 92 days Fe-55 1x1,0 Batch(d) Composite (b) Sr-89, Sr-90 5x10 8 Prior to one Dissolved & 5 Batch per 31 days Entrained Gases (f) 1x10 month d) (Gamma Emitters) B. Plant 1-131 lx10-CONTINUOUS 31 days(c) 311daysx1O RELEASEs (Grab Sample) 31 days(c) 31 days(c) Principal Gamma 5x10-7 (Grab Sample) Emitters(e) 31 days(c) Dissolved & 1x10-5 t 3a Sample) 31 days(c) Entrained Gases~ ) (Grab Sample) (Gamma Emitters) 31 days(c) 31 days(c) H-3 1X10 (Grab Sample) Gross Alpha lx10i7 92 days(c) Sr-89, Sr-90 5x10 8 (Grab Sample) 92 days(c) Fe-55 1xlo0 Quad Cities ODCM Part I

CY-QC-170-301 Revision 11 Page 56 of 307 January 2013 Table 12.3.1-2 (Page 2 of 3) RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION (a) LOWER LIMIT OF DETECTION is defined as an a priori(before the fact) limit representing the capabilities of a measurement system, and not as an a posteriori(after the fact) limit for a particular measurement. For a particular measurement system, which may include radiochemical separation: LLD - 4"66Sb E. V 2.22E + 06. Y. e(-') Where: LLD = the a priori LOWER LIMIT OF DETECTION (microcuries per unit mass or volume), S= the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute), (TotalCounts) tb E = the counting efficiency (counts per disintegration), V = the sample size (units of mass or volume), 2.22E+06 = the number of disintegrations per minute per microcurie, Y = the fractional radiochemical yield, when applicable, tb = counting time of the background or blank (minutes) X= the radioactive decay constant for the particular radionuclide (sec -1), and At = the elapsed time between the midpoint of sample collection and the time of counting (sec). Typical values of E, V,Y, and At should be used in the calculation. (b) A composite sample is one in which the quantity of liquid samples is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen that is representative of the liquids released. (c) Ifthe alarm setpoint of the service water effluent monitor as determined in the ODCM is exceeded, the FREQUENCY of analysis shall be increased to daily until the condition no longer exists. (d) Prior to sampling for analyses, each batch shall be isolated and then thoroughly mixed to assure representative sampling. Quad Cities ODCM Part I

CY-QC-1770-301 Revision 11 Page 57 of 307 January 2013 Table 12.3.1-2 (Page 3 of 3) RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION (e) The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Mn-54, Fe-59, Co-60, Zn-65, Co-58, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144. Ce-144 shall be measured with an LLD of 5x106. Other peaks that are measurable and identifiable by gamma ray spectrometry together with the above nuclides shall be also identified and reported when the ACTUAL analysis is performed on a sample. Nuclides that are below the LLD for the analyses shall not be reported as being present at the LLD level for that nuclide. (f) The dissolved and entrained gases (gamma emitters) for which the LOWER LIMIT OF DETECTION specification applies exclusively are the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-1 33m, Xe-1 35, and Xe-1 38. Other dissolved and entrained gases (gamma emitters) that are measurable and identifiable by gamma ray spectrometry, together with the above nuclides, shall also be identified and reported when an ACTUAL analysis is performed on a sample. Nuclides that are below the LOWER LIMIT OF DETECTION for the analyses shall not be reported as being present at the LOWER LIMIT OF DETECTION level for that nuclide. Quad Cities ODCM Part I

CY-QC-1 70-301 Revision 11 Page 58 of 307 January 2013 12.3 LIQUID EFFLUENTS 12.3.2 Dose From Liquid Effluents REC 12.3.2 The dose or dose commitment above background to a MEMBER OF THE PUBLIC from radioactive material in liquid effluent releases from each unit to the areas at or beyond the SITE BOUNDARY shall be limited to:

a. < 1.5 mrem to the whole body and < 5.0 mrem to any organ during any calendar quarter; and

b. < 3.0 mrem to the whole body and < 10.0 mrem to any organ during any calendar year, and

c. < 1.0 mrem projected annual dose to the total body or any internal organ calculated at the nearest downstream COMMUNITY WATER SYSTEM.

APPLICABILITY: At all times. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME

         -NOTE ------------           A.1 Submit a Special Report to the --------NOTE -----------

Required Action A.1 shall NRC that identifies cause(s) for This action is in lieu be completed if this exceeding limits, actions taken of an LER. condition is entered. to reduce releases of radioactive materials in liquid effluents, and proposed actions 30 days A. Calculated dose not to ensure future releases are in within limits of compliance with REC 12.3.2.a REC 12.3.2.a. or and REC 12.3.2.b. REC 12.3.2.b. B. Calculated dose B.1 Enter Condition A of Immediately exceeds two times (2x) REC 12.5.1. the limits of REC 12.3.2.a or REC 12.3.2.b. (continued) Quad Cities ODCM Part I

CY-QC-170-301 Revision 11 Page 59 of 307 January 2013 CONDITION REQUIRED ACTION COMPLETION TIME

         -NOTE ----------------   C.1   Submit a Special Report to the --------NOTE -----------

Required Action C.1 shall COMMUNITY WATER This action is in lieu be completed if this SYSTEM operator, with copy to of an LER. condition is entered. the NRC, to assist the operator in meeting 40 CFR 141, EPA C. PROJECTED dose Primary Drinking Water 30 days computed at the nearest Standards. downstream COMMUNITY WATER SYSTEM exceeds limits of REC 12.3.2.c. SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENT FREQUENCY RSR 12.3.2.1 Calculate whole body and organ dose contribution -------- NOTE ----- from measured quantities of radioactive material. Provisions of RSR 12.0.2 are not applicable. 31 days RSR 12.3.2.2 Determine cumulative whole body and organ dose --------- NOTE ----- contributions for the current calendar quarter and Provisions of current calendar year. RSR 12.0.2 are not applicable. 31 days RSR 12.3.2.3 Determine PROJECTED DOSES at the nearest 92 days COMMUNITY WATER SYSTEM considering only the drinking water pathway using the methods prescribed in the ODCM. Quad Cities ODCM Part I

CY-QC-170-301 Revision 11 Page 60 of 307 January 2013 12.3 LIQUID EFFLUENTS 12.3.3 Liquid Radwaste Treatment Systems REC 12.3.3 Liquid effluent releases shall be processed prior to being discharged when the PROJECTED DOSE from liquid effluent releases from each unit to UNRESTRICTED AREAS exceeds < 0.06 mrem to the whole body or

                      < 0.20 mrem to any organ when averaged over 31 days.

APPLICABILITY: At all times.

                     ----------------------NOTE              --------------------

The provisions of REC 12.0.4 are not applicable. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME

          -NOTE ----------------    ----- - ---------------

NOTE ----------- Required Action A.1 shall IF limited and/or associated ACTION be completed if this requirements cannot be satisfied condition is entered. because of circumstances in excess of this section, THEN no changes in plant operational condition are A. Liquid waste discharged required, and entry into any without required OPERATING MODE is not processing. prohibited. AND A.1 Submit a Special Report to the 30 days PROJECTED DOSE NRC that includes: limits of REC 12.3.3 exceeded. (i) Identification and cause of defective equipment. (ii)Action taken to restore the INOPERABLE equipment to OPERABLE status (iii) Length of time OPERABILITY was not satisfied. (iv) Waste discharge volume and curie content. (v) Explanation of why liquid radwaste was discharged without required processing. (vi) Action(s) taken to prevent recurrence. Quad Cities ODCM Part I

CY-QC-170-301 Revision 11 Page 61 of 307 January 2013 SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENT FREQUENCY RSR 12.3.3.1 Determine PROJECTED DOSES due to liquid --------- NOTE --------- releases at or beyond the SITE BOUNDARY in Provisions of accordance with the ODCM. RSR 12.0.2 are not applicable. 31 days Quad Cities ODCM Part I

CY-QC-170-301 Revision 11 Page 62 of 307 January 2013 12.4 GASEOUS EFFLUENTS 12.4.1 Gaseous Effluent Dose Rates REC 12.4.1 The dose rate at or beyond the SITE BOUNDARY due to radioactive materials in gaseous effluents released from the site shall be limited to the following:

a. For noble gases, < 500 mrem/year to the whole body and < 3000 mrem/year to the skin

b. For iodine-131, iodine-133, tritium, carbon-14, and all radionuclides in particulate form with half-lives > 8 days, < 1500 mrem/year.

APPLICABILITY: At all times. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME

         -NOTE ----------------               A.1    Decrease release           Immediately Required Action A.2 shall be                       rates to comply with completed if this condition is                     limits.

entered. AND A. Dose rate(s) not within limits. A.2 Describe in next In accordance with Radioactive Effluent Section 12.7.3. Report. SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENT FREQUENCY RSR 12.4.1.1 Verify dose rates due to noble gases, iodine-1 31, In accordance with iodine-133, tritium, carbon-14, and all radionuclides Table 12.4.1-1. in particulate form with halflives > 8 days in gaseous effluents are within limits using methods prescribed in the ODCM by obtaining and analyzing representative samples. Quad Cities ODCM Part I

CY-QC-1 70-301 Revision 11 Page 63 of 307 January 2013 Table 12.4.1-1 (Page 1 of 3) RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM LOWER LIMIT MINIMUM OF GASEOUS SAMPLING ANALYSIS TYPE OF ACTIVITY DETECTION RELEASE TYPE FREQUENCY FREQUENCY ANALYSIS (LLD)(a) (pCi/ml) A. Main 31 days )Principal Gamma 10-4 Chimney and (Grab Sample) 31 days(b) Emitters (e) Reactor Bldg. Vent Stack 31 days Tritium lx10-B. All Release Continuous(d) 12 Types as 7 days(c) 1-131 lx10 Listed in A Charcoal Sample above 1-133 1x10-1° Continuous(d) 7 M Principal Gamma 7 days Emitters (e) (1-131, lxl 011 Particulate Sample others) Continuous(d) 92 days Sr-89 lx1011 Composite Particulate Sample Sr-90 lx10-11 Continuous(d) 31 days Composite Gross Alpha lx10-11 Particulate Sample C. Main Cotnos()6 Chimney Continuous Noble Gas Monitor Noble Gases 1x106 D. Reactor Bldg. Continuous(d) N Gs 0-4 Vent Stack Noble Gas Monitor Noble Gases E. Main N/A Chimney NN/A C14(f) N/A Quad Cities ODCM Part I

CY-QC-1 70-301 Revision 11 Page 64 of 307 January 2013 Table 12.4.1-1 (Page 2 of 3) RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION (a) LOWER LIMIT OF DETECTION is defined as an a priori(before the fact) limit representing the capabilities of a measurement system, and not as an a posteriori(after the fact) limit for a particular measurement. For a particular measurement system, which may include radiochemical separation: 4 66 LLD = . Sb E- V 2.22E + 06. Y- e Where: LLD = the a priori LOWER LIMIT OF DETECTION (microcuries per unit mass or volume), Sb= the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute), _/(TotalCounts) tb E = the counting efficiency (counts per disintegration), V = the sample size (units of mass or volume), 2.22E+06 = the number of disintegrations per minute per microcurie, Y = the fractional radiochemical yield, when applicable, tb = counting time of the background or blank (minutes)

               ;X= the radioactive decay constant for the particular radionuclide (sec 1), and At = the elapsed time between the midpoint of sample collection and the time of counting (sec).

Typical values of E, V, Y, and At should be used in the calculation. (b) Sampling and analyses shall also be performed following shutdown, startup, or a thermal power change exceeding 20% rated thermal power 1 hour unless (1) analysis shows that the DOSE EQUIVALENT 1-131 concentration in the primary coolant has not increased more than a factor of 5, and (2) the noble gas activity monitor shows that effluent activity has not increased by more than a factor of 3. (c) Samples shall be changed at least once per 7 days and the analyses completed within 48 hours after removal from the sampler. Sampling shall also be performed within 24 hours following each shutdown, startup, or thermal power level change exceeding 20% RTP in one hour. This requirement does not apply if 1) analysis shows that the DOSE EQUIVALENT 1-131 concentration in the primary coolant has not increased more than a factor of 5, and 2) the noble gas activity monitor shows that effluent activity has not increased by more than a factor of 3. When samples collected for 24 hours are analyzed, the corresponding LLDs may be increased by a factor of 10. Quad Cities ODCM Part I

CY-QC-1 70-301 Revision 11 Page 65 of 307 January 2013 Table 12.4.1-1 (Page 3 of 3) RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM TABLE NOTATION (d) The ratio of sample flow rate to the sampled stream flow rate shall be known. (e) 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, and Xe-1 38 for gaseous emissions, and Mn-54, Fe-59, Co-60, Zn-65, Co-58, Mo-99, Cs-1 34, Cs-1 37, Ce-141, and Ce-144 for particulate emissions. Other peaks that are measurable and identifiable by gamma ray spectrometry, together with the above nuclides, shall be also identified and reported when an ACTUAL analysis is performed on a sample. Nuclides that are below the LLD for the analyses shall not be reported as being present at the LLD level for the nuclide. (f) Per NRC guidance: If using estimated C-14 values based on scaling factors and fission rates, sampling is not required. Quad Cities ODCM Part I

CY-QC-1 70-301 Revision 11 Page 66 of 307 January 2013 12.4 GASEOUS EFFLUENTS 12.4.2 Dose from Noble Gases REC 12.4.2 The air dose at or beyond the SITE BOUNDARY due to noble gases in gaseous effluents released from each unit at the site shall be limited to the following:

a. For gamma radiation, < 5 mrad during any calendar quarter;

b. For beta radiation, _<10 mrad during any calendar quarter;

c. For gamma radiation, < 10 mrad during any calendar year;

d. For beta radiation, _<20 mrad during any calendar year.

APPLICABILITY: At all times. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME

         -NOTE --------------          A.1 Submit a Special Report to    -------- NOTE Required Action A.1 shall be             the NRC that identifies        This is in lieu of an completed if this condition is            causes for exceeding limits,   LER entered.                                 corrective actions taken to reduce the releases, and       30 days corrective actions to ensure A. Calculated air dose not                that future releases are within limits,                         within limits.

B. Calculated air dose B.1 Enter Condition A of Immediately exceeds two times (2x) the REC 12.5.1. limits of REC 12.4.2. Quad Cities ODCM Part I

CY-QC-170-301 Revision 11 Page 67 of 307 January 2013 SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENT FREQUENCY RSR 12.4.2.1 Determine the cumulative dose contributions due to -------- NOTE----- noble gases released in gaseous effluents for the Provisions of current calendar quarter and current calendar year RSR 12.0.2 are not in accordance with the ODCM. applicable. 31 days RSR 12,4.2.2 Determine effluents allocation between units having -------- NOTE----- shared effluent control systems per the ODCM. Provisions of RSR 12.0.2 are not applicable. 31 days Quad Cities ODCM Part I

CY-QC-1 70-301 Revision 11 Page 68 of 307 January 2013 12.4 GASEOUS EFFLUENTS 12.4.3 Dose From Iodine -131, Iodine -133, Tritium, Carbon - 14, and Radioactive Materials in Particulate Form REC 12.4.3 The dose to a MEMBER OF THE PUBLIC at or beyond the SITE BOUNDARY from iodine-131, iodine-133, tritium, carbon-14, and all radionuclides in particulate form, with half-lives > 8 days, in gaseous effluents released from each unit at the site shall be limited to:

a. < 7.5 mrem to any organ during any calendar quarter; and

b. _ 15 mrem to any organ during any calendar year.

APPLICABILITY: At all times. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME

          -NOTE ----------------      A.1 Submit a Special Report to -------- NOTE ---------

Required Action A.1 shall be the NRC that identifies This is in lieu of an completed if this condition is causes for exceeding limit(s), LER entered. corrective action(s) taken, and proposed corrective 30 days action(s) to ensure that A. Calculated dose not within subsequent releases are limits, within limits. B. Calculated dose exceeds B.1 Enter Condition A of Immediately two times (2x) the limits. REC 12.5.1. SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENT FREQUENCY RSR 12.4.3.1 Determine the cumulative dose for the current .------- NOTE----- calendar quarter and current calendar year to a Provisions of MEMBER OF THE PUBLIC due to releases of RSR 12.0.2 are not iodine-131, iodine-133, tritium, carbon-14, and applicable. radionuclides in particulate form with half-lives

                 > 8 days using methodology and parameters in the            31 days ODCM.

Quad Cities ODCM Part I

CY-QC-170-301 Revision 11 Page 69 of 307 January 2013 12.4 GASEOUS EFFLUENTS 12.4.4 Gaseous Radwaste Treatment System REC 12.4.4 Process and control equipment shall be operated during processing for discharge to the environs to reduce the amount or concentration of radioactive materials released at or beyond the SITE BOUNDARY.

a. The release rate of the sum of activities from noble gases measured at the Main Condenser air ejector shall be limited to

                            < 251,100 pCi/sec after 30 minutes decay.

b. The Off-Gas Charcoal Adsorber beds shall be in operation above 30% rated thermal power.

APPLICABILITY: MODES 1, 2, and 3 with any main steam line not isolated and steam jet air ejector in operation. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME

         -NOTE ----------------      A.1  Submit a Special Report to       30 days Required Action A.1 shall be           the NRC that includes:

completed if this condition is entered. (i) identification and cause of defective equipment (ii) actions taken to restore A. All charcoal beds bypassed the INOPERABLE for more than 7 days in a equipment to OPERABLE calendar quarter while status OPERATING above 30% (iii) length of time REC 12.4.4 was not met (iv) waste discharge volume and curie content that was not processed but required processing, (v) actions taken to prevent recurrence of equipment failures. B. Release rate of B.1 Restore release rate to 72 hours REC 12.4.4.a exceeded. within limits. (continued) Quad Cities ODCM Part I

CY-QC-1 70-301 Revision 11 Page 70 of 307 January 2013 J CONDITION REQUIRED ACTION COMPLETION TIME C. Required ACTIONS and C.1 Refer to Technical Immediately associated Completion Specification 3.7.6. Time of Condition B not met. SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENT FREQUENCY RSR 12.4.4.1 Monitor noble gas radioactivity rate at (near) the Continuously per Main Condenser air ejector outlet. REC 12.2.2.

              ---------------     NOTE         -------------------------    31 days Not required to be performed until 31 days after any Main Steam line not isolated and SJAE in operation.                                         AND RSR 12.4.4.2      Perform isotope analysis of a representative              Once within 4 hours sample of gases taken at either the recombiner            after a > 50%

outlet, or at the air ejector outlet if the recombiner is increase in nominal bypassed, to determine if the release rate of the steady state fission noble gas sum of the activities is within REC 12.4.4 gas release after limits. factoring out increases due to changes in thermal power level. Quad Cities ODCM Part I

CY-QC-170-301 Revision 11 Page 71 of 307 January 2013 12.4 GASEOUS EFFLUENTS 12.4.5 Ventilation Exhaust Treatment System REC 12.4.5 The appropriate portions of the VENTILATION EXHAUST TREATMENT SYSTEM shall be OPERABLE and be used to reduce releases of radioactivity when the PROJECTED DOSES in 31 days due to gaseous effluents at or beyond the SITE BOUNDARY would exceed:

a. 0.2 mrad to air from gamma radiation, or

b. 0.4 mrad to air from beta radiation, or

c. 0.3 mrem to any organ of a MEMBER OF THE PUBLIC APPLICABILITY: At all times.

---

--------- NOTE---------------------

1. The provisions of REC 12.0.4 are not applicable.

2. Separate Condition entry is allowed for each VENTILATION EXHAUST TREATMENT system pathway.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME

 ----- NOTE-------                  ----------------- NOTE ------------     30 days Required Action A.1 shall be          IF limited and/or associated completed if this condition is        ACTION requirements cannot be entered.                              satisfied because of circumstances in excess of this section, THEN no changes in A. Gaseous waste being                  plant operational condition are discharged without                required, and entry into any treatment,                        OPERATING MODE is not prohibited.

AND PROJECTED DOSE limits A.1 Submit a Special Report to of REC 12.4.5 exceeded. the NRC that includes INOPERABLE equipment or subsystem identification and reason, actions taken to restore the INOPERABLE equipment to OPERABLE status, and summary description of actions taken to prevent a recurrence. Quad Cities ODCM Part I

CY-QC-1770-301 Revision 11 Page 72 of 307 January 2013 SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENT FREQUENCY RSR 12.4.5.1 Project doses due to treated gaseous effluent -------- NOTE ---------- releases at and beyond the SITE BOUNDARY in Provisions of accordance with the ODCM. RSR 12.0.2 are not applicable. 31 days Quad Cities ODCM Part I

CY-QC-1 70-301 Revision 11 Page 73 of 307 January 2013 12.4 GASEOUS EFFLUENTS 12.4.6 Mark I Containment REC 12.4.6 VENTING or PURGING of the Drywell Containment shall be:

a. Through the Reactor Building Ventilation Exhaust System or Standby Gas Treatment System when:

i. Drywell noble gas activity < 3.2 x 10-3 iLCi/cc, AND ii. Drywell iodine and particulate activity < 3.9 x 10-5 [Ci/cc OR

b. Through the Standby Gas Treatment System.

APPLICABILITY: During drywell VENTING or PURGING in MODES 1, 2, or 3.

                   ---------------------- NOTE ------------------------------------

The provisions of REC 12.0.4 are not applicable. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of REC A.1 Suspend drywell VENTING Immediately 12.4.6 not met. or PURGING B. Required actions and B.1 Perform RSR 12.4.1.1, Immediately Completion Time of RSR 12.4.2.1, Condition A not met. RSR 12.4.3.1, and RSR 12.4.5.1. SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENT FREQUENCY RSR 12.4.6.1 Determine Containment Drywell VENTING or Prior to Containment PURGING pathway. Drywell VENTING or PURGING Quad Cities ODCM Part I

CY-QC-1 70-301 Revision 11 Page 74 of 307 January 2013 12.5 TOTAL DOSE 12.5.1 Total Dose REC 12.5.1 The dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and radiation from all uranium fuel cycle sources over 12 consecutive months shall be limited to:

a. < 25 mrem to the total body; and

b. _ 75 mrem to the thyroid; and

c. < 25 mrem to any other organ (except thyroid).

APPLICABILITY: At all times. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME

         -NOTE ---------------          A.1    Submit a report to the NRC -------- NOTE ----------

Required Action A.1 and A.2 that defines the corrective This is in lieu of an shall be completed if this action to be taken to reduce LER. condition is entered. subsequent releases to prevent recurrence of 30 days exceeding the limits to A. As required by Required include estimates of Action B.1 of REC 12.3.2, radiation exposure to a REC 12.4.2, or REC 12.4.3. MEMBER OF THE PUBLIC from uranium fuel cycle OR sources, including all effluent pathways and direct Calculated Total Dose not radiation, for a 12 within limits, consecutive month period that includes the release(s) covered by this report. AND (continued) Quad Cities ODCM Part I

CY-QC-1 70-301 Revision 11 Page 75 of 307 January 2013 CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) NOTE---------- Only applicable if the release condition resulting in violation of 40 CFR 190 has not been corrected. A.2 Submit a request for a 30 days variance in accordance with 40 CFR 190, including the specified information of 40 CFR 190.11. SURVEILLANCE REQUIREMENTS

---

NOTE ---------------------------------

Cumulative dose contributions from liquid and gaseous effluents are determined per RSR 12.3.2.2, RSR 12.4.2.1, and RSR 12.4.3.1. None. Quad Cities ODCM Part I

CY-QC-170-301 Revision 11 Page 76 of 307 January 2013 12.5 TOTAL DOSE 12.5.2 Dose Limits for MEMBERS OF THE PUBLIC REC 12.5.2 Operations shall be conducted such that:

a. TEDE to individual MEMBERS OF THE PUBLIC does not exceed 100 mrem/year;

b. The dose rate in any UNRESTRICTED AREA from external sources does not exceed 2 mrem in any one hour, and;

c. The Effluents Program shall implement monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10CFR20.1302 and the methodology and parameters in the ODCM.

APPLICABILITY: At all times. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME

         -NOTE ----------------       A.1    Submit a report to the NRC     30 days Required Action A.1 shall be               in accordance with completed if this condition is             1 OCFR20.2203.

entered. A. Dose limit of REC 12.5.2.a exceeded.

         -NOTE ----------------       B.1    Submit a report to the NRC     30 days Required Action B.1 shall be               in accordance with completed if this condition is             10CFR20.2203.

entered. B. Dose rate limit of REC 12.5.2.b exceeded. Quad Cities ODCM Part I

CY-QC-170-301 Revision 11 Page 77 of 307 January 2013 SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENT FREQUENCY RSR 12.5.2.1 Calculate the total dose to individual MEMBERS 12 months OF THE PUBLIC to determine compliance with REC 12.5.2.a limits in accordance with the ODCM. RSR 12.5.2.2 Determine and/or evaluate if direct radiation 12 months exposures exceed the cumulative dose contribution from direct radiation REC 12.5.2.b limits. Quad Cities ODCM Part I

CY-QC-170-301 Revision 11 Page 78 of 307 January 2013 12.6 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 12.6.1 Radiological Environmental Monitoring Program REC 12.6.1 The Radiological Environmental Monitoring Program (REMP) shall be conducted as specified in Table 12.6.1-1. APPLICABILITY: At all times.

                    ----------------------- NOTE          -----------------------

The provisions of REC 12.0.3 and REC 12.0.4 are not applicable. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME

         -NOTE --------------        A.1   Initiate action to identify      Immediately Required Action A.2 shall be            suitable, alternative completed if this condition is          sampling media and/or entered.                                specific locations for the pathway of interest and add them to the Radiological A. Sample type or location(s)           Environmental Monitoring required by Table 12.6.1-1           Program as soon as permanently unavailable,             practical. Delete locations from which samples are unavailable.

AND A.2 Prepare and submit In accordance with controlled revision of the Section 12.7.2. ODCM, including revised figures and tables reflecting the new location(s) with supporting information identifying the sample unavailability cause and justification of the new sampling location(s). (continued) Quad Cities ODCM Part I

CY-QC-1)70-301 Revision 11 Page 79 of 307 January 2013 CONDITION REQUIRED ACTION COMPLETION TIME

          -NOTE --------------      B.1 Submit a Special Report to  30 days Required Action B.1 shall be         the NRC that identifies the completed if this condition is       cause(s) for exceeding the entered.                             limits and defines the corrective actions to be taken to reduce radioactive B. Level of radioactivity in an      effluents so that the environmental sampling            potential annual dose to a medium at an ODCM                 MEMBER OF THE PUBLIC specified location exceeds        is less than the calendar the reporting levels of           year reporting level of Table 12.6.1-2 when               REC 12.3.2, REC 12.4.2, or averaged over any                 REC 12.4.3. The calendar quarter.                 methodology and parameters used to estimate the potential annual dose to a MEMBER OF THE PUBLIC shall be indicated in this report.

C. More than one radionuclide C.1 Submit a Special Report to 30 days in Table 12.6.1-2 is the NRC that identifies the detected in the sampling cause(s) for exceeding the medium, limits and defines the corrective actions to be AND taken to reduce radioactive C1 C2 effluents so that the

              +         + ... > 1.0     potential annual dose to a RL1       RL 2                    MEMBER OF THE PUBLIC is less than the calendar where;                            year reporting level of C = concentration                  REC 12.3.2, REC 12.4.2, or RL = reporting level.              REC 12.4.3. The methodology and parameters used to estimate the potential annual dose to a MEMBER OF THE PUBLIC shall be indicated in this report.

(continued) Quad Cities ODCM Part I

CY-QC-1 70-301 Revision 11 Page 80 of 307 January 2013 CONDITION REQUIRED ACTION COMPLETION TIME

          -NOTE ----------------  --------------------------

NOTE-------- Required Action D.1 and D.2 Only required if the radionuclides shall be completed if this detected are the result of plant condition is entered. effluents. D. Radionuclides other than D.1 Submit a Special Report to 30 days those in Table 12.6.1-2 are the NRC that identifies the detected cause(s) for exceeding the limits and defines the AND corrective actions to be taken to reduce radioactive The potential annual dose effluents so that the potential to a MEMBER OF THE annual dose to a MEMBER PUBLIC is greater than or OF THE PUBLIC is less than equal to the calendar year the calendar year reporting limits of REC 12.3.2, level. The methodology and REC 12.4.2, or REC 12.4.3. parameters used to estimate the potential annual dose to a MEMBER OF THE PUBLIC shall be indicated in this report. AND NOTE-------- Only required if the radionuclides detected are not the result of plant effluents. D.2 Describe the condition in the In accordance with Annual Radiological Section 12.7.2. Environmental Operating Report.

          -NOTE ----------------  E.1 Prepare and submit to the          In accordance with Required Action E.1 shall be          NRC, in the Annual              Section 12.7.2.

completed if this condition is Radiological Environmental entered. Operating Report, a description of the reasons for not conducting the program E. Requirements of as required and the plans for RSR 12.6.1.1 not met. preventing a recurrence. Quad Cities ODCM Part I

CY-QC-1 70-301 Revision 11 Page 81 of 307 January 2013 SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENT FREQUENCY

---

NOTE ----------------------

Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal availability, malfunction of sampling equipment, if a person/business who participates in the program goes out of business or can no longer provide a sample, or contractor omission which is corrected as soon as discovered. If the equipment malfunctions, corrective actions shall be completed as soon as practical. If a person/business supplying samples goes out of business, a replacement supplier shall be found as soon as possible. All deviations from the sampling schedule will be described in the Annual Radiological Environmental Operating Report. RSR 12.6.1.1 Collect and analyze samples in accordance with Table In accordance with 12.6.1-1 to the detection capabilities required by Table Table 12.6.1-1 12.6.1-3. Quad Cities ODCM Part I

CY-QC-170-301 Revision 11 Page 82 of 307 January 2013 Table 12.6.1-1 (Page 1 of 6) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLES AND SAMPLING AND COLLECTION TYPE AND FREQUENCY 1 AND/ OR SAMPLE SAMPLE LOCATIONS" ) FREQUENCY"1 ') OF ANALYSIS"1 ")

1. Airborne Radioiodine and Samples from a total of nine locations:

Particulates

a. Indicator- Near Field Radioiodine Canister:

Four samples from locations within 4.0 km (2.5 mi) in Sampler Operation Continuous 1-131 analysis on each different sectors. sample.

b. Indicator- Far Field Particulate Sample:

Four additional locations within 4.0 to 10 km (2.5 to 6.2 mi) Gross beta analysis on in different sectors. Filter change 7 days or more each sample.

c. Control frequently as required due to Gamma isotopic analysis( 4 )

dust loading, once per 92 days on One sample from a control location within 10 to 30 km (6.2 composite filters by to 18.6 mi). I location. Quad Cities ODCM Part I

CY-QC-170-301 Revision 11 Page 83 of 307 January 2013 Table 12.6.1-1 (Page 2 of 6) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLES AND SAMPLING AND COLLECTION TYPE AND AND/ OR SAMPLE SAMPLE LOCATIONS"1 ) FREQUENCY"11" FREQUENCY OF ANALYSIS' 1 )

2. Direct Radiation(b Forty routine monitoring stations, either with a dosimeter 92 days Gamma dose on each or with one instrument for measuring dose rate dosimeter once per 92 continuously, placed as follows: days.

a. Indicator- Inner Ring One in each meteorological sector, in the general area of the SITE BOUNDARY (0.1 to 3 miles);

b. Indicator- Outer Ring One in each meteorological sector, within 6.0 to 8.0 km (3.7 to 5.0 mi); and

c. Other One at each Airborne location given in part 1.a. and 1.b.

The balance of the dosimeters to be placed at special interest locations in the UNRESTRICTED AREA where either a MEMBER OF THE PUBLIC or Exelon Nuclear employees have routine access.

d. Control One at each airborne control location given in part 1.c.

Quad Cities ODCM Part I

CY-QC-170-301 Revision 11 Page 84 of 307 January 2013 Table 12.6.1-1 (Page 3 of 6) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLES AND SAMPLING AND COLLECTION TYPE AND FREQUENCY AND/ OR SAMPLE SAMPLE LOCATIONS"1 ) FREQUENCY"11 ) OF ANALYSIS(11 )

3. Waterborne

a. Ground/ Well a. Indicator 92 days Gamma isotopic(4) and tritium analysis on each Samples from two sources only if likely to be sample.

affected .(6)

b. Drinking(7) a. Indicator Grab samples once per 7 days. Gross beta and gamma isotopic analyses(4) on 31-One Sample from each COMMUNITY WATER day composite(2); tritium SYSTEM that could be affected by the station analysis on 92-day discharge within 8 km (5.0 mi) downstream of composite(2 ).

discharge. 1-131(9) on 14-day composite(2) when calculated dose > 1 mrem/year.

c. Surface Water(7) If no COMMUNITY WATER SYSTEM (Drinking Water) Grab samples once per 7 days. Gross beta and gamma exists within 10 km downstream of discharge then surface isotopic analyses(4) on 31-water sampling shall be performed. day composite(2); tritium analysis on 92-day

a. Indicator composite(2'.

One sample downstream

b. Control One sample upstream of discharge Quad Cities ODCM Part I

CY-QC-1 70-301 Revision 11 Page 85 of 307 January 2013 Table 12.6.1-1 (Page 4 of 6) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLES AND SAMPLING AND COLLECTION TYPE AND FREQUENCY AND/ OR SAMPLE SAMPLE LOCATIONS"1 ' FREQUENCY&11 ' OF ANALYSIS"1 ")

3. Waterborne (continued)

d. Sediment a. Indicator 184 days Gamma isotopic analysis")

on each sample. At least one sample from downstream(7) area within 10 Km (6.2 mi).

b. Control One sample upstream(7) of discharge

4. Ingestion

a. Milk( 8 ) a. Indicator Once per 14 days when animals Gamma isotopic(4) and are on pasture (May through 1-131(9) analysis on each Samples from milking animals from a maximum of October), 31 days at other times sample.

three locations within 8.0 km (5 mi) distance. (November through April).

b. Control One sample from milking animals at a control location within 15 to 30 km (9.3 to 18.6 mi).

b. Fish a. Indicator 184 days Gamma isotopic analysis(4)

Representative samples of commercially and on edible portions of each recreationally important species in discharge area. sample.

b. Control Representative samples of commercially and recreationally important species in control locations upstream of discharge.

Quad Cities ODCM Part I

CY-QC-170-301 Revision 11 Page 86 of 307 January 2013 Table 12.6.1-1 (Page 5 of 6) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE PATHWAY NUMBER OF REPRESENTATIVE SAMPLES AND SAMPLING AND COLLECTION TYPE AND FREQUENCY AND/ OR SAMPLE SAMPLE LOCATIONS"1 ) FREQUENCY(11 ) OF ANALYSISý 1

                                                                                                                                               )

4. Ingestion (continued)

c. Food Products a. Indicator 12 months Gamma isotopic(4) analysis Two representative samples from the principal food on each sample.

pathways grown in each of four major quadrants within 8 km (5 mi): 0 At least one root vegetable sample(1 ) At least one broad leaf vegetable (or vegetation)(10 )

b. Control Two representative samples similar to indicator samples grown within 15 to 30 km (9.3 to 18.6 mi).

d. Vegetation -------------------------- NOTE ------------------------------------ 31 days during the growing Gamma isotopic(4) on each These vegetation samples are only required if milk season (May through October). sample.

sampling is not performed.

a. Indicator Samples of 3 different types of broadleaf vegetation within 8 Km (5 miles) in the highest D/Q sector.

b. Control Sample of 3 different types of broadleaf vegetation 15 to 30 Km (9.4 to 18.7 miles) in the lowest D/Q sector.

Quad Cities ODCM Part I

CY-QC-170-301 Revision 11 Page 87 of 307 January 2013 Table 12.6.1-1 (Page 6 of 6) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM TABLE NOTATIONS (1) Specific parameters of distance and direction from the centerline of the midpoint of the two units and additional description where pertinent, shall be provided for each and every sample location in Table 6-1 of the ODCM. Refer to NUREG-0133, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," October 1978, and to Radiological Assessment Branch Technical Position, Revision 1, November 1979. (2) A composite sample is one in which the aliquot of liquid sampled is proportional to the quantity of flowing liquid and in which the method of sampling results in a representative sample. (3) Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in air particulate samples is greater than 10 times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples. (4) Gamma isotopic analysis means the identification and quantification of gamma emitting radionuclides that may be attributable to the effluents from the station. (5) One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters. Film badges shall not be used as dosimeters for measuring direct radiation. The 40 locations is not an absolute number. The number of direct radiation monitoring stations may be reduced according to geographical limitations; e.g., ifa station is adjacent to a lake, some sectors may be over water thereby reducing the number of dosimeters that could be placed at the indicated distances. The FREQUENCY of analysis or readout for dosimeter systems will depend upon the characteristics of the specific system used and should be selected to obtain optimum dose information with minimal fading. (6) Groundwater samples shall be taken when this source is tapped for drinking or irrigation purposes in areas where the hydraulic gradient or recharge properties are suitable for contamination. (7) The "downstream" sample shall be taken in an area beyond but near the mixing zone. The "upstream sample" shall be taken at a distance beyond significant influence of the discharge. Upstream samples in an estuary must be taken far enough upstream to be beyond the station influence. (8) If milking animals are not found in the designated indicator locations, or ifthe owners decline to participate in the REMP, all milk sampling may be discontinued. (9) 1-131 analysis means the analytical separation and counting procedure are specific for this radionuclide. (10) One sample shall consist of a volume/weight of sample large enough to fill contractor specified container. (11) The provisions of RSR 12.0.3 are not applicable to the REMP. Quad Cities ODCM Part I

CY-QC-1 70-301 Revision 11 Page 88 of 307 January 2013 Table 12.6.1-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES AIRBORNE PARTICULATE FOOD PRODUCTS ANALYSIS WATER (pCi/I) OR GASES (pCi/m 3) FISH (pCi/kg, wet) MILK (pCi/I) (pCi/kg, wet) H-3 20,000(1) Mn-54 1,000 30,000 Fe-59 400 10,000 Co-58 1,000 30,000 Co-60 300 10,000 Zn-65 300 20,000 Zr-Nb-95 400 1-131 2(2) 0.9 3 100 Cs-134 30 10 1,000 60 1,000 Cs-1 37 50 20 2,000 70 2,000 Ba-La-140 200 300 (1) For drinking water samples. This is 40 CFR 141 value. If no drinking water pathway exists, a value of 30,000 pCi/I may be used. (2) If no drinking water pathway exists, a value of 20 pCi/I may be used. Quad Cities ODCM Part I

CY-QC-170-301 Revision 11 Page 89 of 307 January 2013 Table 12.6.1-3 (Page 1 of 3) DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS(1 ) LOWER LIMIT OF DETECTION (LLD)(2)(3) AIRBORNE PARTICULATE FISH FOOD PRODUCTS SEDIMENT ANALYSIS WATER (pCi/I) OR GASES (pCi/m 3) (pCi/kg, wet) MILK (pCi/I) (pCi/kg, wet) (pCi/kg, dry) Gross Beta 4 0.01 H-3 2,000 Mn-54 15 130 Fe-59 30 260 Co-58 15 130 Co-60 15 130 Zn-65 30 260 Zr-95 30 Nb-95 15 1-131 1(4) 0.07 1 60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-140 60 60 La-140 15 15 Quad Cities ODCM Part I

CY-QC-170-301 Revision 11 Page 90 of 307 January 2013 Table 12.6.1-3 (Page 2 of 3) DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS(1 ) LOWER LIMIT OF DETECTION (LLD)(2)(3) TABLE NOTATIONS (1) The nuclides on this list are not the only nuclides intended to be considered. Other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report. (2) Required detection capabilities for thermoluminescent dosimeters used for environmental measurements shall be in accordance with the recommendations of Regulatory Guide 4.13. (3) The LOWER LIMIT OF DETECTION (LLD) is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal. For a particular measurement system, which may include radiochemical separation, the LLD is defined as follows: LLD= 466Sb E. V- 2.22. Y. e where: LLD = the "a priori" LOWER LIMIT OF DETECTION (picocuries per unit mass or volume), Sb= the standard deviation of the background counting rate or of the counting rate of a blank sample, as appropriate (counts per minute),

                              /TotalCoounts tb E =          the counting efficiency (counts per disintegration),

V = the sample size (units of mass or volume), 2.22 = the number of disintegrations per minute per picocurie, Y = the fractional radiochemical yield, when applicable, X = the radioactive decay constant for the particular radionuclide (sec1 ), tb = counting time of the background or blank (minutes), and At = the elapsed time between sample collection or end of the sample collection period, and the time of counting (sec). Quad Cities ODCM Part I

CY-QC-170-301 Revision 11 Page 91 of 307 January 2013 Table 12.6.1-3 (Page 3 of 3) DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS(1 ) LOWER LIMIT OF DETECTION (LLD)(2)(3) TABLE NOTATIONS Typical values of E, V, Y, and At should be used in the calculation. It should be recognized that the LLD is defined as a before the fact limit representing the capability of a measurement system and not as an after the fact limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally, background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report. (4) If no drinking water pathway exists, the value of 15 pCi/L may be used. Quad Cities ODCM Part I

CY-QC-1 70-301 Revision 11 Page 92 of 307 January 2013 12.6 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 12.6.2 Land Use Census REC 12.6.2 A Land Use Census shall be conducted and shall identify within a distance of 8.0 km (5.0 miles) the location in each of the 16 meteorological sectors of the nearest milk animal and the nearest residence. The Land Use Census shall also identify all milk animals within a distance of 5.0 km (3.0 miles). For dose calculation, a garden will be assumed at the nearest residence. APPLICABILITY: At all times.

---

NOTE ---------------------------------

1. The 16 meteorological sectors requirement may be reduced according to geographical limitations; e.g. at a lake site where some sectors will be over water.

2. The nearest industrial facility shall also be documented if closer than the nearest residence.

3. REC 12.0.3 and REC 12.0.4 are not applicable.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME

           -NOTE-------------             A. 1    Add the new location to the Required Action A.1 and A.2                    Radiological Environmental       30 days shall be completed if this                     Monitoring Program.

condition is entered. AND A. Land use census identifies a location which yields a calculated dose or dose commitment, via the same exposure pathway, that is at least 20% greater than at a location from which samples are currently being obtained in accordance with REC 12.6.1. (continued) Quad Cities ODCM Part I

CY-QC-1 70-301 Revision 11 Page 93 of 307 January 2013 ACTIONS (Continued) CONDITION REQUIRED ACTION COMPLETION TIME (continued) A. Land use census identifies ----------- NOTE---------- a location which yields a The indicator sampling location calculated dose or dose having the lowest calculated commitment, via the same dose or dose commitment, via exposure pathway, that is the same exposure pathway, at least 20% greater than may be deleted from the at a location from which radiological environmental samples are currently monitoring program after being obtained in October 31 of the year in accordance with which Land Use Census was REC 12.6.1. conducted. A.2 Submit the documentation for In accordance with a change in the ODCM in the Section 12.7.2 Annual Radiological Environmental Operating Report and include the revised figures and tables for the ODCM reflecting the new location(s) with information supporting the change in sampling locations. SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENT FREQUENCY RSR 12.6.2.1 Conduct a land use census during the growing NOTE------ season, between June 1 and October 1, using RSR 12.0.2 and information that will provide the best results, such as RSR 12.0.3 are not by a door-to-door survey, aerial survey, or by applicable. consulting local agriculture authorities or by some other appropriate means. 12 months Quad Cities ODCM Part I

CY-QC-1 70-301 Revision 11 Page 94 of 307 January 2013 12.6 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 12.6.3 Interlaboratory Comparison Program REC 12.6.3 Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program that is traceable to the National Institute of Standards and Technology. NOTE ---------------------- REC 12.0.3 and REC 12.0.4 are not applicable. APPLICABILITY: At all times. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME

         -NOTE -------------        A.1    Report corrective actions to   In accordance with Required Action A.1 shall be            prevent recurrence to the NRC  Section 12.7.2.

completed if this condition is in the Annual Radiological entered. Environmental Operating Report. A. Requirements of REC 12.6.3 not met. SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENT FREQUENCY RSR 12.6.3.1 Include a summary of the results of the Interlaboratory In accordance with Comparison Program in the Annual Radiological Section 12.7.2. Environmental Operating Report. Quad Cities ODCM Part I

CY-QC-1 70-301 Revision 11 Page 95 of 307 January 2013 12.6 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 12.6.4 Meteorological Monitoring Instrumentation REC 12.6.4 The meteorological monitoring instrumentation channels shown in Table 12.6.4-1 shall be OPERABLE such that the Annual Data recovery is > 90%. APPLICABILITY: At all times.

                             ----------------------   NOTE REC 12.0.3 and REC 12.0.4 are not applicable.

ACTIONS

                   ---------------------- NOTE                 --------------------

Separate condition entry is allowed for each instrument. CONDITION REQUIRED ACTION COMPLETION TIME A. Annual data recovery less A.1 Report reasons for instrument In accordance with than 90% for any INOPERABILITY in next Section 12.7.2. instrument in Table Radiological Environmental 12.6.4-1. Operating Report. SURVEILLANCE REQUIREMENTS SURVEILLANCE REQUIREMENT FREQUENCY RSR 12.6.4.1 Perform CHANNEL CALIBRATION of instrumentation 6 months shown in Table 12.6.4-1. Quad Cities ODCM Part I

CY-QC-170-301 Revision 11 Page 96 of 307 January 2013 Table 12.6.4-1 METEOROLOGICAL MONITORING INSTRUMENTATION CONDITION I CONDTIONSURVEILLANCE Instrument REFERENCED FROM SURVENCE REQUIRED ACTION A.1

1. 33 foot elevation 1.a Wind Speed A RSR 12.6.4.1 1.b Wind Direction A RSR 12.6.4.1 1.c Air Temperature A RSR 12.6.4.1

2. 196 foot elevation 2.a Wind Speed A RSR 12.6.4.1 2.b Wind Direction A RSR 12.6.4.1 2.c Air Differential Temperature A RSR 12.6.4.1

3. 296 foot elevation 3.a Wind Speed A RSR 12.6.4.1 3.b Wind Direction A RSR 12.6.4.1 3.c Air Differential Temperature A RSR 12.6.4.1 Quad Cities ODCM Part I

CY-QC-1 70-301 Revision 11 Page 97 of 307 January 2013 12.7 ADMINISTRATIVE REQUIREMENTS 12.7.1 Station Operating Records 12.7.1.1 Records and/or logs relative to the following items shall be kept in a manner convenient for review and shall be retained for at least five years. 12.7.1.1.1 Records and periodic checks, inspection and/or calibrations performed to verify the surveillance requirements (See the applicable surveillance in the Instrumentation, Liquid Effluents, Gaseous Effluents, and Radiological Environmental Monitoring Sections) are being met. All equipment failing to meet surveillance requirements and the corrective action taken shall be recorded. 12.7.1.1.2 Records of radioactive shipments. 12.7.1.2 Records and/or logs relative to the following items shall be recorded in a manner convenient for review and shall be retained for the life of the plant. 12.7.1.2.1 Records of offsite environmental monitoring surveys. 12.7.1.2.2 Records of radioactivity in liquid and gaseous wastes released to the environment. 12.7.1.2.3 Records of reviews performed for changes made to the ODCM. Quad Cities ODCM Part I

CY-QC-170-301 Revision 11 Page 98 of 307 January 2013 12.7.2 Annual Radiological Environmental Operating Report

                   --------------------- NOTE          ------------------

A single submittal may be made for a multiple unit station. The submittal should combine sections common to all units at the station. 12.7.2.1 The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted prior to May 15 of each year. 12.7.2.2 The report shall include summaries, interpretations, and an analysis of trends of the results of The Radiological Environmental Monitoring Program for the report period. The material provided shall be consistent with the objectives outlined in the ODCM, and in 10CFR50, Appendix I, Sections IV.B.2, IV.B.3, and IV.C. The report shall include a comparison with preoperational studies, with operational controls as appropriate, and with previous environmental surveillance reports, and an assessment of the observed impacts of the plant operation on the environment. 12.7.2.3 The report shall include the results of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the tables and figures in ODCM Part II Section 6.0, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report. 12.7.2.4 The report shall also include the following:

1. A summary description of the Radiological Environmental Monitoring Program

2. At least two maps covering all sampling locations keyed to a table giving distances and directions from the midpoint between the two units

3. A discussion of all deviations from the sampling schedule described in Section 12.6.1

4. Discussion of environmental sample measurements that exceed the reporting levels of Table 12.6.1-2 but are not the result of plant effluents

5. Discussion of all analyses in which the LLD required by Table 12.6.1-3 was not achievable

6. Result of the Land Use Census required by Section 12.6.2

7. The results of the licensee participation in an Interlaboratory Comparison Program and the corrective actions being taken if the specified program is not being performed as required by Section 12.6.3.

Quad Cities ODCM Part I

CY-QC-1 70-301 Revision 11 Page 99 of 307 January 2013 12.7.3 Annual Radioactive Effluent Release Report

                    -------------------- NOTE          ------------------

A single submittal may be made for a multiple unit station. The submittal should combine sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit. 12.7.3.1 The report covering the operation of the unit during the previous calendar year of operation shall be submitted in accordance with 10CFR50.36.9 prior to May 1 of each year. 12.7.3.2 The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be consistent with the objectives outlined in the ODCM and the PCP and in accordance with 10CFR50.36 and 10CFR50, Appendix I, Section IV.B.1 The report shall be outlined consistent with Regulatory Guide 1.21, "Measuring Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and -Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof. 12.7.3.3 The report shall include a list and description of unplanned releases from the site to UNRESTRICTED AREAS of radioactive materials in gaseous and liquid effluents made during the reporting period. 12.7.3.4 The report shall include any changes made during the reporting period to the PCP as well as any major changes to Liquid, Gaseous or Solid Radwaste Treatment Systems, pursuant to Section 12.7.5. 12.7.3.5 The report shall also include the following: an explanation as to why the INOPERABILITY of liquid or gaseous effluent monitoring instrumentation was not corrected within the specified time and description of the events leading to liquid holdup tanks or gas storage tanks exceeding the limits of Technical Specifications. 12.7.3.6 The report shall also include an annual summary of hourly meteorological data collected over the applicable year. This annual summary may be either in the form of an hour-by-hour listing on magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured), or in the form of joint FREQUENCY distributions of wind speed, wind direction, and atmospheric stability. In lieu of submission with the Annual Radioactive Effluent Release Report, the licensee has the option of retaining this summary of required meteorological data on site in a file that shall be provided to the NRC upon request (continued) Quad Cities ODCM Part I

CY-QC-170-301 Revision 11 Page 100 of 307 January 2013 12.7.3.7 The report shall also include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the Unit or Station during the previous calendar year. This report shall also include an assessment of the radiation doses to the most likely exposed MEMBER OF THE PUBLIC from reactor releases and other near-by uranium fuel cycle sources including doses from primary effluent pathways and direct radiation for the previous calendar year. The assessment of radiation doses shall be performed in accordance with the methodology and parameters in the ODCM, and in compliance with 10CFR20 and 40 CFR 190, "Environmental Radiation Protection Standards for Nuclear Power Operation." Quad Cities ODCM Part I

CY-QC-170-301 Revision 11 Page 101 of 307 January 2013 12.7.4 Off site Dose Calculation Manual (ODCM) 12.7.4.1 The ODCM shall contain the methodology and parameters used in the calculation of offsite doses due to radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm and trip setpoints, and in the conduct of the Radiological Environmental Monitoring Program. 12.7.4.2 The ODCM shall also contain the radioactive effluent controls and radiological environmental monitoring activities (described in Sections 12.2 - 12.6) and descriptions of the information that should be included in the Annual Radioactive Effluent Release and Radiological Environmental Operating Reports required by Sections 12.7.2 and12.7.3, and Technical Specifications 5.6.2 and 5.6.3. 12.7.4.3 Licensee initiated changes to the ODCM: 12.7.4.3.1 Shall be documented and records of reviews performed shall be retained as required by the Quality Assurance (QA) Manual. This documentation shall contain: 12.7.4.3.1.1 Sufficient information to support the change together with appropriate analyses or evaluations justifying the change(s); and 12.7.4.3.1.2 A determination that the change(s) will maintain the level of radioactive effluent control required by 10 CFR 20.1302, 40 CFR 190, 10 CFR 50.36a, and 10 CFR 50, Appendix I, and do not adversely impact the accuracy or reliability of effluent, dose, or set point calculations. 12.7.4.3.2 Shall become effective after approval of the Station Manager on the date specified by the Onsite Review and Investigative Function. 12.7.4.3.3 Shall be submitted to the NRC in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made effective. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (i.e. month and date) the change was implemented. Quad Cities ODCM Part I

CY-QC-170-301 Revision 11 Page 102 of 307 January 2013 12.7.5 Major Changes to Radioactive Waste Treatment Systems (Liquid and Gaseous) 12.7.5.1 Licensee initiated major changes to the radioactive waste systems may be made provided: 12.7.5.1.1 The change is reported in the Monthly Operating Report for the period in which the evaluation was reviewed by Onsite Review Function. The discussion of each change shall contain: 12.7.5.1.1.1 A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR 50.59; 12.7.5.1.1.2 Sufficient detailed information to support the reason for the change; 12.7.5.1.1.3 A detailed description of the equipment, components, and process involved and the interfaces with other plant systems; 12.7.5.1.1.4 An evaluation of the change which shows the predicted releases of radioactive materials in liquid and gaseous effluents ( or quantity of solid waste that differ from those previously predicted in the license application and amendments); 12.7.5.1.1.5 A comparison of the predicted releases of radioactive materials in liquid and gaseous effluents and in solid waste to the ACTUAL releases for the period in which the changes were made; 12.7.5.1.1.6 An estimate of the exposure to plant OPERATING personnel as a result of the change; and 12.7.5.1.1.7 Documentation of the fact that the change was reviewed and found acceptable by Onsite Review Function. 12.7.5.2 The change shall become effective upon review and acceptance by Onsite Review Function. Quad Cities ODCM Part I

CY-QC-1 70-301 Revision 11 Page 103 of 307 January 2013 12.8 ODCM BASES General It is expected that releases of radioactive material in effluents will be kept at small fractions of the limits specified in 10 CFR 20.1302. At the same time, the licensee is permitted the flexibility of operation, compatible with consideration of health and safety, to assure that the public is provided a dependable source of power even under unusual OPERATING conditions which may temporarily result in releases higher than such small fractions, but still within the limits specified in 10 CFR 20.1302. It is expected that in using this operational flexibility under unusual OPERATING conditions the licensee will exert his best efforts to keep levels of radioactive material in effluents as low as practicable. RECs REC 12.0.1 through REC 12.0.6 establish the general requirements applicable to all RECs in Sections 12.1 through 12.6 and apply at all times, unless otherwise stated. RSRs RSR 12.0.1 through RSR 12.0.5 establish the general requirements applicable to all Requirements in 12.1 through 12.5 and apply at all times, unless otherwise stated. REC 12.0.1 REC 12.0.1 establishes the Applicability statement within each individual REC as the requirement for when the REC is required to be met (i.e., when the unit is in the MODES or other specified conditions of the Applicability statement of each Requirement). RSR 12.0.1 RSR 12.0.1 establishes the requirement that RSRs must be met during the MODES or other specified conditions in the Applicability for which the requirements of the REC apply, unless otherwise specified in the individual RSRs. This REC is to ensure that RSRs are performed to verify the OPERABILITY of systems and components, and that variables are within specified limits. Failure to meet a RSR within the specified Frequency, in accordance with RSR 12.0.2, constitutes a failure to meet a REC. Systems and components are assumed to be OPERABLE when the associated RSRs have been met. Nothing in this RSR, however, is to be construed as implying that systems or components are OPERABLE when: (continued) Quad Cities ODCM Part I

CY-QC-1 70-301 Revision 11 Page 104 of 307 January 2013 12.8 ODCM BASES (continued) RSR 12.0.1 a. The systems or components are known to be INOPERABLE, (continued) although still meeting the RSRs; or

b. The requirements of the RSR(s) are known to be not met between required RSR performances.

RSR do not have to be performed when the unit is in a MODE or other specified condition for which the requirements of the associated REC are not applicable, unless otherwise specified. Unplanned events may satisfy the requirements (including applicable acceptance criteria) for a given RSR. In this case, the unplanned event may be credited as fulfilling the performance of the RSR. RSRs, including RSRs invoked by Required Actions, do not have to be performed on INOPERABLE equipment because the ACTIONS define the remedial measures that apply. RSRs have to be met and performed in accordance with RSR 12.0.2, prior to returning equipment to OPERABLE status. Upon completion of maintenance, appropriate post maintenance testing is required to declare equipment OPERABLE. This includes ensuring applicable RSRs are not failed and their most recent performance is in accordance with RSR 12.0.2. Post maintenance testing may not be possible in the current MODE or other specified conditions in the Applicability due to the necessary unit parameters not having been established. In these situations, the equipment may be considered OPERABLE provided testing has been satisfactorily completed to the extent possible and the equipment is not otherwise believed to be incapable of performing its function. This will allow operation to proceed to a MODE or other specified condition where other necessary post maintenance tests can be completed. REC 12.0.2 REC 12.0.2 establishes that upon discovery of a failure to meet a REC, the associated ACTIONS shall be met. The Completion Time of each Required Action for an ACTIONS Condition is applicable from the point in time that an ACTIONS Condition is entered. The Required Actions establish those remedial measures that must be taken within specified Completion Times when the requirements of a REC are not met. This Requirement establishes that:

a. Completion of the Required Actions within the specified Completion Times constitutes compliance with a REC; and (continued)

Quad Cities ODCM Part I

CY-QC-1 70-301 Revision 11 Page 105 of 307 January 2013 12.8 ODCM BASES (continued) REC 12.0.2 b. Completion of the Required Actions is not required when a (continued) REC is met within the specified Completion Time, unless otherwise specified. There are two basic types of Required Actions. The first type of Required Action specifies a time limit in which the REC must be met. This time limit is the Completion Time to restore an INOPERABLE system or component to OPERABLE status or to restore variables to within specified limits. Ifthis type of Required Action is not completed within the specified Completion Time, a shutdown may be required to place the unit in a MODE or condition in which the REC is not applicable. (Whether stated as a Required Action or not, correction of the entered Condition is an action that may always be considered upon entering ACTIONS.) The second type of Required Action specifies the remedial measures that permit continued operation of the unit that is not further restricted by the Completion Time. In this case, compliance with the Required Actions provides an acceptable level of safety for continued operation. Completing the Required Actions is not required when a REC is met or is no longer applicable, unless otherwise stated in the individual RECs. The nature of some Required Actions of some Conditions necessitates that, once the Condition is entered, the Required Actions must be completed even though the associated Condition no longer exists. The individual REC's ACTIONS specify the Required Actions where this is the case. An example of this is in REC 12.4.2, "Dose from Noble Gases." The Completion Times of the Required Actions are also applicable when a system or component is removed from service intentionally. The reasons for intentionally relying on the ACTIONS include, but are not limited to, performance of Surveillances, preventive maintenance, corrective maintenance, or investigation of operational problems. Entering ACTIONS for these reasons must be done in a manner that does not compromise safety. Intentional entry into ACTIONS should not be made for operational convenience. Additionally, if intentional entry into ACTIONS would result in redundant equipment being INOPERABLE, alternatives should be used instead. Doing so limits the time both subsystems/divisions of a function are INOPERABLE and limits the time conditions exist which may result in REC 12.0.3 being entered. Individual RECs may (continued) Quad Cities ODCM Part I

CY-QC-1770-301 Revision 11 Page 106 of 307 January 2013 12.8 ODCM BASES (continued) REC 12.0.2 specify a time limit for performing a RSR when equipment is (continued) removed from service or bypassed for testing. In this case, the Completion Times of the Required Actions are applicable when this time limit expires, if the equipment remains removed from service or bypassed. When a change in MODE or other specified condition is required to comply with Required Actions, the unit may enter a MODE or other specified condition in which another REC becomes applicable. In this case, the Completion Times of the associated Required Actions would apply from the point in time that the new REC becomes applicable and the ACTIONS Condition(s) are entered. RSR 12.0.2 RSR 12.0.2 establishes the requirements for meeting the specified Frequency for RSRs and any Required Action with a Completion Time that requires the periodic performance of the Required Action on a "once per..." interval. RSR 12.0.2 permits a 25% extension of the interval specified in the Frequency. This extension facilitates RSR scheduling and considers plant operating conditions that may not be suitable for conducting the RSR (e.g., transient conditions or other ongoing RSR or maintenance activities). The 25% extension does not significantly degrade the reliability that results from performing the RSR at its specified Frequency. This is based on the recognition that the most probable result of any particular RSR being performed is the verification of conformance with the RSRs. As stated in RSR 12.0.2, the 25% extension also does not apply to the initial portion of a periodic Completion Time that requires performance on a "once per..." basis. The 25% extension applies to each performance after the initial performance. The initial performance of the Required Action, whether it is a particular RSR or some other remedial action, is considered a single action with a single Completion Time. One reason for not allowing the 25% extension to this Completion Time is that such an action usually verifies that no loss of function has occurred by checking the status of redundant or diverse components or accomplishes the function of the INOPERABLE equipment in an alternative manner. (continued) Quad Cities ODCM Part I

CY-QC-1 70-301 Revision 11 Page 107 of 307 January 2013 12.8 ODCM BASES (continued) RSR 12.0.2 The provisions of RSR 12.0.2 are not intended to be used repeatedly (continued) merely as an operational convenience to extend RSR intervals (other than those consistent with refueling intervals) or periodic Completion Time intervals beyond those specified. REC 12.0.3 REC 12.0.3 establishes the actions that must be implemented when a REC is not met and:

a. An associated Required Action and Completion Time is not met and no other Condition applies; or

b. The condition of the unit is not specifically addressed by the associated ACTIONS. This means that no combination of Conditions stated in the ACTIONS can be made that exactly corresponds to the actual condition of the unit. Sometimes, possible combinations of Conditions are such that entering REC 12.0.3 is warranted; in such cases, the ACTIONS specifically state a Condition corresponding to such combinations and also that REC 12.0.3 be entered immediately.

Upon entering REC 12.0.3, 1 hour is allowed to implement appropriate compensatory actions and verify the plant is not in an unanalyzed condition or that a required safety function is not compromised. Within 12 hours, Shift Operations Superintendent or designee approval of the compensatory actions and the plan for exiting REC 12.0.3 must be obtained. The use and interpretation of specified times to complete the actions of REC 12.0.3 are consistent with the discussion of Section 1.3, Completion Times. The actions required in accordance with REC 12.0.3 may be terminated and REC 12.0.3 exited if any of the following occurs:

a. The REC is now met.

b. A Condition exists for which the Required Actions have now been performed.

c. ACTIONS exist that do not have expired Completion Times.

These Completion Times are applicable from the point in time that the Condition is initially entered and not from the time REC 12.0.3 is exited. (continued) Quad Cities ODCM Part I

CY-QC-170-301 Revision 11 Page 108 of 307 January 2013 12.8 ODCM BASES (continued) REC 12.0.3 In MODES 1, 2, and 3, REC 12.0.3 provides actions for Conditions (continued) not covered in other Requirements. The requirements of REC 12.0.3 do not apply in MODES 4 and 5 because the unit is already in the most restrictive Condition. The requirements of REC 12.0.3 do not apply in other specified conditions of the Applicability (unless in MODE 1, 2, or 3) because the ACTIONS of individual RECs sufficiently define the remedial measures to be taken. RSR 12.0.3 RSR 12.0.3 establishes the flexibility to defer declaring affected equipment INOPERABLE or an affected variable outside the specified limits when a RSR has not been completed within the specified Frequency. A delay period of up to 24 hours or up to the limit of the specified Frequency, whichever is greater, applies from the point in time it is discovered that the RSR has not been performed in accordance with RSR 12.0.2, and not at the time that the specified Frequency was not met. This delay period provides adequate time to complete RSRs that have been missed. This delay period permits the completion of a RSR before complying with Required Actions or other remedial measures that might preclude completion of the RSR. The basis for this delay period includes consideration of unit conditions, adequate planning, availability of personnel, the time required to perform the RSR, the safety significance of the delay in completing the required RSR, and the recognition that the most probable result of any particular RSR being performed is the verification of conformance with the requirements. When a RSR with a Frequency based not on time intervals, but upon specified unit conditions, operating situations, or requirements of regulations (e.g., prior to each release, or in accordance with the Radioactive Liquid Waste Sampling and Analysis Program, etc.) is discovered to not have been performed when specified, RSR 12.0.3 allows for the full delay period of up to the specified Frequency to perform the RSR. However, since there is not a time interval specified, the missed RSR should be performed at the first reasonable opportunity. RSR 12.0.3 provides a time limit for, and allowances for the performance of, RSRs that become applicable as a consequence of MODE changes imposed by Required Actions. (continued) Quad Cities ODCM Part I

CY-QC-170-301 Revision 11 Page 109 of 307 January 2013 12.8 ODCM BASES (continued) RSR 12.0.3 Failure to comply with specified Frequencies for RSRs is expected to (continued) be an infrequent occurrence. Use of the delay period established by RSR 12.0.3 is a flexibility which is not intended to be used as an operational convenience to extend RSR intervals. While up to 24 hours or the limit of the specified Frequency is provided to perform the missed RSR, it is expected that the missed RSR will be performed at the first reasonable opportunity. The determination of the first reasonable opportunity should include consideration of the impact on plant risk (from delaying the RSR as well as any plant configuration changes required or shutting the plant down to perform the RSR) and impact on any analysis assumptions, in addition to unit conditions, planning, availability of personnel, and the time required to perform the RSR. This risk impact should be managed through the program in place to implement 10 CFR 50.65(a)(4) and its implementation guidance, NRC Regulatory Guide 1.160, "Monitoring the Effectiveness of Maintenance at Nuclear Power Plants". This Regulatory Guide addresses consideration of temporary and aggregate risk impacts, determination of risk management action thresholds, and risk management action up to and including plant shutdown. The missed RSR should be treated as an emergent condition as discussed in the Regulatory Guide. The risk evaluation may use quantitative, qualitative, or blended methods. The degree of depth and rigor of the evaluation should be commensurate with the importance of the component. Missed RSRs for important components should be analyzed quantitatively. If the results of the risk evaluation determine the risk increase is significant, this evaluation should be used to determine the safest course of action. All missed RSRs will be placed in the station's Corrective Action Program. If a RSR is not completed within the allowed delay period, then the equipment is considered INOPERABLE or the variable then is considered outside the specified limits and the Completion Times of the Required Actions for the applicable REC Conditions begin immediately upon expiration of the delay period. If a RSR is failed within the delay period, then the equipment is INOPERABLE, or the variable is outside the specified limits and the Completion Times of the Required Actions for the applicable REC Conditions begin immediately upon the failure of the RSR. Completion of the RSR within the delay period allowed by this RSR, or within the Completion Time of the ACTIONS, restores compliance with RSR 12.0.1. Quad Cities ODCM Part I

CY-QC-170-301 Revision 11 Page 110 of 307 January 2013 12.8 ODCM BASES (continued) REC 12.0.4 REC 12.0.4 establishes limitations on changes in MODES or other specified conditions in the Applicability when an REC is not met. It precludes placing the unit in a MODE or other specified condition stated in that Applicability (e.g., Applicability desired to be entered) when the following exist:

a. Unit conditions are such that the requirements of the REC would not be met in the Applicability desired to be entered; and

b. Continued noncompliance with the REC requirements, if the Applicability were entered, would result in the unit being required to exit the Applicability desired to be entered to comply with the Required Actions.

Compliance with Required Actions that permit continued operation of the unit for an unlimited period of time in a MODE or other specified condition provides an acceptable level of safety for continued operation. This is without regard to the status of the unit before or after the MODE change. Therefore, in such cases, entry into a MODE or other specified condition in the Applicability may be made in accordance with the provisions of the Required Actions. The provisions of this REC should not be interpreted as endorsing the failure to exercise the good practice of restoring systems or components to OPERABLE status before entering an associated MODE or other specified condition in the Applicability. The provisions of REC 12.0.4 shall not prevent changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS. In addition, the provisions of REC 12.0.4 shall not prevent changes in MODES or other specified conditions in the Applicability that result from any unit shutdown. Exceptions to REC 12.0.4 are stated in the individual RECs. The exceptions allow entry into MODES or other specified conditions in the Applicability when the associated ACTIONS to be entered do not provide for continued operation for an unlimited period of time. Exceptions may apply to all the ACTIONS or to a specific Required Action of a REC. Surveillances do not have to be performed on the associated INOPERABLE equipment (or on variables outside the specified limits), as permitted by RSR 12.0.1. Therefore, changing MODES or (continued) Quad Cities ODCM Part I

CY-QC-170-301 Revision 11 Page 111 of 307 January 2013 12.8 ODCM BASES (continued) REC 12.0.4 other specified conditions while in an ACTIONS Condition, either in (continued) compliance with REC 12.0.4, or where an exception to REC 12.0.4 is stated, is not a violation of RSR 12.0.1 or RSR 12.0.4 for those Surveillances that do not have to be performed due to the associated INOPERABLE equipment. However, RSRs must be met to ensure OPERABILITY prior to declaring the associated equipment OPERABLE (or variable within limits) and restoring compliance with the affected REC. REC 12.0.4 is only applicable when entering MODE 3 from MODE 4, MODE 2 from MODE 3 or 4, or MODE 1 from MODE 2. Furthermore, REC 12.0.4 is applicable when entering any other specified condition in the Applicability only while operating in MODE 1, 2, or 3. The requirements of REC 12.0.4 do not apply in MODES 4 and 5, or in other specified conditions of the Applicability (unless in MODE 1, 2, or 3) because the ACTIONS of individual Requirements sufficiently define the remedial measures to be taken. RSR 12.0.4 RSR 12.0.4 establishes the requirement that all applicable RSRs must be met before entry into a MODE or other specified condition in the Applicability. This RSR ensures that system and component OPERABILITY requirements and variable limits are met before entry into MODES or other specified conditions in the Applicability for which these systems and components ensure safe operation of the unit. The provisions of this RSR should not be interpreted as endorsing the failure to exercise the good practice of restoring systems or components to OPERABLE status before entering an associated MODE or other specified condition in the Applicability. However, in certain circumstances, failing to meet a RSR will not result in RSR 12.0.4 restricting a MODE change or other specified condition change. When a system, subsystem, division, component, device, or variable is INOPERABLE or outside its specified limits, the associated RSR(s) are not required to be performed per RSR 12.0.1 which states that RSRs do not have to be performed on INOPERABLE equipment. When equipment is INOPERABLE, RSR 12.0.4 does not apply to the associated RSR(s) since the requirement for the RSR(s) to be performed is removed. Therefore, failing to perform the RSRs within the specified Frequency, on equipment that is INOPERABLE, does not result in a RSR 12.0.4 (continued) Quad Cities ODCM Part I

CY-QC-170-301 Revision 11 Page 112 of 307 January 2013 12.8 ODCM BASES (continued) RSR 12.0.4 restriction to changing MODES or other specified conditions of the (continued) Applicability. However, since the REC is not met in this instance, RSR 12.0.4 will govern any restrictions that may (or may not) apply to MODE or other specified condition changes. The provisions of RSR 12.0.4 shall not prevent changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS. In addition, the provisions of RSR 12.0.4 shall not prevent changes in MODES or other specified conditions in the Applicability that result from any unit shutdown. The precise requirements for performance of RSRs are specified such that exceptions to RSR 12.0.4 are not necessary. The specific time frames and conditions necessary for meeting the RSRs are specified in the Frequency, in the RSR, or both. This allows performance of RSRs when the prerequisite condition(s) specified in a RSR procedure require entry into the MODE or other specified condition in the Applicability of the associated REC prior to the performance or completion of a RSR. A RSR that could not be performed until after entering the REC Applicability would have its Frequency specified such that it is not "due" until the specific conditions needed are met. Alternately, the RSR may be stated in the form of a Note as not required (to be met or performed) until a particular event, condition, or time has been reached. Further discussion of the specific formats of RSRs' annotation is found in Section 1.4, Frequency. RSR 12.0.4 is only applicable when entering MODE 3 from MODE 4, MODE 2 from MODE 3 or 4, or MODE 1 from MODE 2. Furthermore, RSR 12.0.4 is applicable when entering any other specified condition in the Applicability only while operating in MODE 1, 2, or 3. The requirements of RSR 12.0.4 do not apply in MODES 4 and 5, or in other specified conditions of the Applicability (unless in MODE 1, 2, or

3) because the ACTIONS of individual Controls sufficiently define the remedial measures to be taken.

REC 12.0.5 REC 12.0.5 establishes the allowance for restoring equipment to service under administrative controls when it has been removed from service or declared INOPERABLE to comply with ACTIONS. The sole purpose of this Requirement is to provide an exception to REC 12.0.2 (e.g., to not comply with the applicable Required Action(s)) to allow the performance of required testing to demonstrate: (continued) Quad Cities ODCM Part I

CY-QC-1770-301 Revision 11 Page 113 of 307 January 2013 12.8 ODCM BASES (continued) REC 12.0.5 a. The OPERABILITY of the equipment being returned to (continued) service; or

b. The OPERABILITY of other equipment.

The administrative controls ensure the time the equipment is returned to service in conflict with the requirements of the ACTIONS is limited to the time absolutely necessary to perform the required testing to demonstrate OPERABILITY. This Requirement does not provide time to perform any other preventive or corrective maintenance. An example of demonstrating the OPERABILITY of other equipment is taking an INOPERABLE channel or TRIP SYSTEM out of the tripped condition to prevent the trip function from occurring during the performance of required testing on another channel in the other TRIP SYSTEM. A similar example of demonstrating the OPERABILITY of other equipment is taking an INOPERABLE channel or TRIP SYSTEM out of the tripped condition to permit the logic to function and indicate the appropriate response during the performance of required testing on another channel in the same TRIP SYSTEM. RSR 12.0.5 RSR 12.0.5 establishes the applicability of each RSR to both Unit 1 and Unit 2 operation. Whenever a requirement applies to only one unit, or is different for each unit, this will be identified with parenthetical reference, Notes, or other appropriate presentation within the RSR. REC 12.0,6 REC 12.0.6 establishes the applicability of each REC to both Unit 1 and Unit 2 operation. Whenever a requirement applies to only one unit, or is different for each unit, this will be identified in the appropriate section of the REC (e.g., Applicability, RSR, etc.) with parenthetical reference, Notes, or other appropriate presentation within the body of the requirement. Quad Cities ODCM Part I

CY-QC-170-301 Revision 11 Page 114 of 307 January 2013 12.8 ODCM BASES (continued) 12.1 NOT USED Quad Cities ODCM Part I

CY-QC-170-301 Revision 11 Page 115 of 307 January 2013 12.8 ODCM BASES (continued) 12.2 INSTRUMENTATION 12.2.1 Radioactive Liquid Effluent Monitoring Instrumentation BASES The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the release of radioactive materials in liquid effluents during ACTUAL or potential release of liquid effluents. The alarm setpoints shall be calculated in accordance with the methodology and parameters in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of RECS and 10CFR20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR 50. Quad Cities ODCM Part I

CY-QC-170-301 Revision 11 Page 116 of 307 January 2013 12.8 ODCM BASES (continued) 12.2 INSTRUMENTATION 12.2.2 Radioactive Gaseous Effluent Monitoring Instrumentation BASES The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during ACTUAL or potential releases of gaseous effluents. The alarm/trip setpoints shall be calculated in accordance with the methodology and parameters in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of RECS and 10CFR20. The OPERABILITY and use of instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR 50. Quad Cities ODCM Part I

CY-QC-1 70-301 Revision 11 Page 117 of 307 January 2013 12.8 ODCM BASES (continued) 12.3 LIQUID EFFLUENTS 12.3.1 Liquid Effluent Concentration BASES This specification is provided to ensure that the concentration of radioactive materials released in liquid waste effluents to areas at and beyond the SITE BOUNDARY will be less than 10 times the concentration levels specified in 10 CFR 20.1001-20.2402, Appendix B, Table 2, Column 2. The concentration limit for noble gases was converted to an equivalent concentration in water using the International Commission on Radiological Protection (ICRP) Publication 2. Quad Cities ODCM Part I

CY-QC-1 70-301 Revision 11 Page 118 of 307 January 2013 12.8 ODCM BASES (continued) 12.3 LIQUID EFFLUENTS 12.3.2 Dose From Liquid Effluents BASES This specification is provided to implement the requirements of Sections II.A, III.A and IV.A of Appendix 1, 10 CFR 50. Control REC 12.3.2 implements the guidance set forth in Section II.A of Appendix I. The statements provide the required OPERATING flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents will be kept "as low as reasonably achievable." The dose calculations in the ODCM implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the ACTUAL exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The equations described in the ODCM for calculating the doses due to the ACTUAL release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April 1977. NUREG-01 13 provides methods for dose calculations consistent with Reg. Guide 1.109 and 1.113. Quad Cities ODCM Part I

CY-QC-170-301 Revision 11 Page 119 of 307 January 2013 12.8 ODCM BASES (continued) 12.3 LIQUID EFFLUENTS 12.3.3 Liquid Radwaste Treatment Systems BASES The liquid radwaste treatment system OPERABILITY ensures the system will be available for use whenever liquid effluents require treatment prior to release to the environment. The requirement that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as reasonably achievable." This specification implements the requirements of 10 CFR 50.36a, General Design Criterion 60 of Appendix A to 10 CFR 50 and design objective Section II.D of Appendix I to 10 CFR 50. Quad Cities ODCM Part I

CY-QC-1 70-301 Revision 11 Page 120 of 307 January 2013 12.8 ODCM BASES (continued) 12.4 GASEOUS EFFLUENTS 12.4.1 Gaseous Effluent Dose Rates BASES This specification provides reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC in an UNRESTRICTED AREA, either at or beyond the SITE BOUNDARY in excess of the design objectives of Appendix I to 10CFR50. This specification is provided to ensure that gaseous effluents from all units on the site will be appropriately controlled. It provides operational flexibility for releasing gaseous effluents to satisfy the Section II.A design objectives of appendix I to 10 CFR 50. For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy will usually be sufficiently low to compensate for the reduced atmospheric dispersion of gaseous effluents relative to that for the SITE BOUNDARY. Examples of calculations for such MEMBERS OF THE PUBLIC, with appropriate occupancy factors, shall be given in the ODCM. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to an individual at or beyond the UNRESTRICTED AREA boundary to less than or equal to a dose rate of 500 mrem/year to the total body or to not less than or equal to a dose rate of 3000 mrem/year to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to a child via the inhalation pathway to not less than or equal to a dose rate of 1500 mrem/year. For purposes of calculating doses resulting from airborne releases the main chimney is considered to be an elevated release point, and the reactor vent stack is considered to be a mixed MODE release point. Quad Cities ODCM Part I

CY-QC-1 70-301 Revision 11 Page 121 of 307 January 2013 12.8 ODCM BASES (continued) 12.4 GASEOUS EFFLUENTS 12.4.2 Dose from Noble Gases BASES This specification is provided to implement the requirements of Sections II.B, III.A and IV.A of Appendix 1,10 CFR 50. The Limiting Conditions for Operation implements the guides set forth in Section II.B of Appendix I. The statements provide the required OPERATING flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents will be kept "as low as is reasonably achievable." The surveillance requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I is to be shown by calculational procedures based on models and data such that the ACTUAL exposure of a MEMBER OF THE PUBLIC through the appropriate pathways is unlikely to be substantially underestimated. The dose calculations established in the ODCM for calculating the doses due to the ACTUAL release rates of radioactive noble gases in gaseous effluents will be consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors," Revision 1, July 1977. The ODCM equations provide for determining the air doses at the unrestricted boundary based upon the historical average atmospheric conditions. NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.111. Quad Cities ODCM Part I

CY-QC-170-301 Revision 11

                                                                                  .Page 122 of 307 January 2013 12.8   ODCM BASES (continued) 12.4                GASEOUS EFFLUENTS 12.4.3              Dose From Iodine -131, Iodine -133, Tritium, Carbon- 14, and Radioactive Materials in Particulate Form BASES This specification is provided to implement the requirements of Sections II.C, III.A and IV.A of Appendix 1,10 CFR 50. The Limiting Conditions for Operation are the guides set forth in Section II.C of Appendix I. The statements provide the required OPERATING flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents will be kept "as low as reasonably achievable." The ODCM calculational methods specified in the surveillance requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the ACTUAL exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated.

The ODCM calculational methods approved by NRC for calculating the doses due to the ACTUAL release rates of the subject materials are required to be consistent with the methodology provided in Regulatory Guide 1.109. "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR 50, Appendix I", Revision 1, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977. These equations also provide for determining the ACTUAL DOSES based upon the historical average atmospheric conditions. The release rate limits for radioiodine, radioactive material in particulate form and radionuclides other than noble gases are dependent on the existing radionuclide pathways to man in the areas at and beyond the SITE BOUNDARY. The pathways that were examined in the development of these specifications were: 1) individual inhalation of airborne radionuclides, 2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man and 3) deposition onto grassy areas where milk animals graze with consumption of the milk by man. Quad Cities ODCM Part I

CY-QC-1770-301 Revision 11 Page 123 of 307 January 2013 12.8 ODCM BASES (continued) 12.4 GASEOUS EFFLUENTS 12.4.4 Gaseous Radwaste Treatment System BASES The OPERABILITY of the gaseous waste treatment (off-gas) system that reduces amounts or concentrations of radioactive materials ensures that the system will be available for use whenever gaseous effluents require treatment prior to release to the environment. The requirement that the appropriate portions of this system be OPERABLE when specified provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as reasonably achievable". This specification implements the requirements of 10 CFR 50.36a, General Design Criterion 60 of Appendix A to 10 CFR 50, and the design objectives given in Section 11.0 of Appendix I to 10 CFR 50. The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in Sections 11.3 and 11.0 of Appendix I, 10CFR50, for gaseous effluents. To determine if gaseous effluents shall be processed through installed treatment equipment, the average PROJECTED DOSE will be determined. For gaseous effluent pathways other than the specified unmonitored exhausts, treatment and monitoring will only be required for pathways that are significant. Regulatory Guide 1.109, "Calculations of Annual Doses to Man From Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR 50, Appendix I", states that a pathway is considered significant if a conservative evaluation yields an additional dose increment equal to or more than 10 percent of the total from all pathways. Therefore, the total dose from all release pathways that do not require treatment or monitoring can not exceed 10 percent of the limit specified in Section II.C of Appendix 1,10 CFR 50. Quad Cities ODCM Part I

CY-QC-170-301 Revision 11 Page 124 of 307 January 2013 12.8 ODCM BASES (continued) 12.4 GASEOUS EFFLUENTS 12.4.5 Ventilation Exhaust Treatment System BASES The OPERABILITY of the VENTILATION EXHAUST TREATMENT SYSTEM ensures that the system will be available for use whenever gaseous effluents require treatment prior to release to the environment. The requirement that the appropriate portions of these systems be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable". This specification implements the requirements of 10 CFR 50.36a, General Design Criterion 60 of Appendix A to 10 CFR 50, and the design objectives given in Section II.D of Appendix I to 10 CFR 50. The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in Sections 1I.B and II.C of Appendix 1,10 CFR 50, for gaseous effluents. Quad Cities ODCM Part I

CY-QC-1 70-301 Revision 11 Page 125 of 307 January 2013 12.8 ODCM BASES (continued) 12.4 GASEOUS EFFLUENTS 12.4.6 Mark I Containment BASES During normal conditions, drywell VENTING and PURGING is normally performed directly to the Reactor Building Ventilation System. The provisions of this REC provide reasonable assurance that the requirements of REC 12.4.1, REC 12.4.2, and REC 12.4.3 are met. The noble gas activity limit is based on not exceeding the alarm trip setpoint of the Reactor Building Vent Noble Gas Activity monitors assuming a Containment Drywell purge flow rate of 9500 cfm and one Reactor Building Ventilation Exhaust fan in operation. The iodine and particulate activity limit is based on not exceeding the requirements of REC 12.4.1 or REC 12.4.3. Quad Cities ODCM Part I

CY-QC-1 70-301 Revision 11 Page 126 of 307 January 2013 12.8 ODCM BASES (continued) 12.5 TOTAL DOSE 12.5.1 Total Dose BASES This Control is provided to meet the dose limitations of 40 CFR 190 that have been incorporated into 10 CFR 20 by 46 FR 18525. The Control requires the preparation and submittal of a Special Report whenever the calculated doses due to releases of radioactivity and to radiation from uranium fuel cycle sources exceed 25 mrems to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems. For sites containing up to four reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR 190 if the individual reactors remain within twice the dose design objectives of Appendix I, and if direct radiation doses from the reactor units and outside storage tanks are kept small. The Special Report will describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 8 km must be considered. If the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFR 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR 190 have not already been corrected), in accordance with the provisions of 40 CFR 190.11 and 10 CFR 20.2203, is considered to be a timely request and fulfills the requirements of 40 CFR 190 until NRC staff action is completed. The variance only relates to the limits of 40 CFR 190, and does not apply in any way to the other requirements for dose limitation of 10 CFR 20, as addressed in Sections 12.3.1 and 12.4.1. An individual is not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle. Quad Cities ODCM Part I

CY-QC-1 70-301 Revision 11 Page 127 of 307 January 2013 12.8 ODCM BASES (continued) 12.5 TOTAL DOSE 12.5.2 Dose Limits for MEMBERS OF THE PUBLIC BASES This section applies to direct exposure of radioactive materials as well as radioactive materials released in gaseous and liquid effluents. 1 OCFR20.1301 sets forth the 100 mrem/year dose limit to MEMBERS OF THE PUBLIC; 2 mrem in any one-hour limit in the UNRESTRICTED AREA; and reiterates that the licensee is also required to meet the 40CFR190 standards. 10CFR20.1302 provides options to determine compliance to 10CFR20.1301. Compliance to the above OPERABILITY requirement is based on 10CFR20, 40CFR190 and Quad Cities Station Technical Specification 5.5.4.j. Quad Cities ODCM Part I

CY-QC-1770-301 Revision 11 Page 128 of 307 January 2013 12.8 ODCM BASES (continued) 12.6 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 12.6.1 Radiological Environmental Monitoring Program BASES The Radiological Environmental Monitoring Program required by this specification provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposures of MEMBERS OF THE PUBLIC resulting from the station operation. This monitoring program implements Section IV.B.2 of Appendix I to 10 CFR 50 and thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and the modeling of the environmental exposure pathways. Guidance for this monitoring program is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring. The initially specified monitoring program will be effective for at least the first 3 years of commercial operation. Following this period, program changes may be initiated based on operational experience. The required detection capabilities for environmental sample analyses are tabulated in terms of the lower limits of detection (LLDs). The LLDs required by Table 12.6.1-3 are considered optimum for routine environmental measurements in industrial laboratories. It should be recognized that the LLD is defined as a before the fact limit representing the capability of a measurement system and not as an after the fact limit for a particular measurement. Detailed discussion of the LLD, and other detection limits, can be found in HASL Procedures Manual, HASL-300 (revised annually), Currie, LA, "Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry," Anal. Chem. 40, 586-93 (1968), and Hartwell, J.K., "Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975). Table 12.6.1-1 requires "one sample of each COMMUNITY WATER SYSTEM downstream of the plant within 10 kilometers." Drinking water supply is defined as water taken from rivers, lakes, or reservoirs (not well water) that is used for drinking. Quad Cities ODCM Part I

CY-QC-170-301 Revision 11 Page 129 of 307 January 2013 12.8 ODCM BASES (continued) 12.6 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 12.6.2 Land Use Census BASES This specification is provided to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the Radiological Environmental Monitoring Program given in the ODCM are made if required by the results of this census. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR 50. An annual garden census will not be required since the licensee will assume that there is a garden at the nearest residence in each sector for dose calculations. Quad Cities ODCM Part I

CY-QC-1770-301 Revision 11 Page 130 of 307 January 2013 12.8 ODCM BASES (continued) 12.6 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 12.6.3 Interlaboratory Comparison Program BASES The requirement for participation in an Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices, are performed as part of the quality assurance program for environmental monitoring, in order to demonstrate that the results are reasonably valid for the purposes of Section IV.B.2 of Appendix I to 10 CFR 50. Quad Cities ODCM Part I

CY-QC-1 70-301 Revision 11 Page 131 of 307 January 2013 12.8 ODCM BASES (continued) 12.6 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 12.6.4 Meteorological Monitoring Instrumentation BASES The OPERABILITY of the meteorological monitoring instrumentation ensures that sufficient meteorological data is available for estimating potential radiation doses to the public as a result of routine or accidental release of radioactive materials to the atmosphere. This capability is required to evaluate the need for initiating measures to protect the health and safety of the public. These requirements are consistent with the recommendations of Regulatory Guide 1.23 "Onsite Meteorological Programs," February, 1972. Quad Cities ODCM Part I

CY-QC-1 70-301 Revision 11 Page 132 of 307 January 2013 PART II OFFSITE DOSE CALCULATION MANUAL QUAD CITIES STATION UNITS 1 AND 2 Quad Cities ODCM Part II

CY-QC-170-301 Revision 11 Page 133 of 307 January 2013

1.0 INTRODUCTION

- ODCM GENERAL INFORMATION The Offsite Dose Calculation Manual (ODCM) presents a discussion of the following:

• The basic concepts applied in calculating offsite doses from plant effluents.
• The regulations and requirements for the ODCM and related programs.
• The methodology and parameters for the offsite dose calculations to assess impact on the environment and compliance with regulations.

The methodology detailed in this manual is intended for the calculation of radiation doses during routine (i.e., non-accident) conditions. The calculations are normally performed using a computer program. Manual calculations may be performed in lieu of the computer program. The dose effects of airborne radioactivity releases predominately depend on meteorological conditions (wind speed, wind direction, and atmospheric stability). For airborne effluents, the dose calculations prescribed in this manual are based on historical average atmospheric conditions. This methodology is appropriate for estimating annual average dose effects and is stipulated in the Bases Section of the Radiological Effluents Controls (RECS). 1.1 Structure of the ODCM Part I of the ODCM is considered to be the Radiological Effluents Controls (RECS), and contains the former Radiological Effluent Technical Specifications that have been removed from the Technical Specifications. Part I is organized as follows: 1.0 USE AND APPLICATION 2.0-11.0 Not Used 12.0 RADIOLOGICAL EFFLUENT CONTROL (REC) and RADIOLOGICAL EFFLUENT SURVEILLANCE REQUIREMENT (RSR) APPLICABILITY 12.1 NOT USED 12.2 INSTRUMENTATION 12.2.1 Radioactive Liquid Effluent Monitoring Instrumentation 12.2.2 Radioactive Gaseous Effluent Monitoring Instrumentation 12.3 LIQUID EFFLUENTS 12.3.1 Liquid Effluent Concentration 12.3.2 Dose From Liquid Effluents 12.3.3 Liquid Radwaste Treatment Systems 12.4 GASEOUS EFFLUENTS 12.4.1 Gaseous Effluent Dose Rates 12.4.2 Dose from Noble Gases 12.4.3 Dose From Iodine -131, Iodine -133, Tritium, Carbon - 14, and Radioactive Materials in Particulate Form Quad Cities ODCM Part II

CY-QC-170-301 Revision 11 Page 134 of 307 January 2013 12.4.4 Gaseous Radwaste Treatment System 12.4.5 Ventilation Exhaust Treatment System 12.4.6 Mark I Containment 12.5 TOTAL DOSE 12.5.1 Total Dose 12.5.2 Dose Limits for MEMBERS OF THE PUBLIC 12.6 RADIOLOGICAL ENVIRONMENTAL MONITORING 12.6.1 Radiological Environmental Monitoring 12.6.2 Land Use Census 12.6.3 Interlaboratory Comparison Program 12.6.4 Meteorological Monitoring Instrumentation 12.7 ADMINISTRATIVE REQUIREMENTS 12.7.1 Station Operating Records 12.7.2 Annual Radiological Environmental Operating Report 12.7.3 Annual Radioactive Effluent Release Report 12.7.4 Off site Dose Calculation Manual (ODCM) 12.7.5 Major Changes to Radioactive Waste Treatment Systems (Liquid and Gaseous) 12.8 ODCM BASES Part II of the ODCM is considered to be the Offsite Dose Calculation Manual (ODCM), and contains methods, equations, assumptions, and parameters for calculation of radiation doses from plant effluents. Part II is organized as follows:

1.0 INTRODUCTION

- ODCM GENERAL INFORMATION 2.0     INSTRUMENTATION AND SYSTEMS 3.0     LIQUID EFFLUENTS 4.0     GASEOUS EFFLUENTS 5.0     TOTAL DOSE 6.0     RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 1.2     Regulations This section serves to illustrate the regulations and requirements that define and are applicable to the ODCM. Any information provided in the ODCM concerning specific regulations are not a substitute for the regulations as found in the Code of Federal Regulations (CFR) or Technical Specifications.

1.2.1 Code of Federal Regulations Various sections of the Code of Federal Regulations (CFR) require nuclear power stations to be designed and operated in a manner that limits the radiation exposure to members of the public. These sections specify limits on offsite radiation doses and on effluent radioactivity concentrations and they also require releases of radioactivity to be "As Low As Reasonably Achievable". These requirements are contained in Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 135 of 307 January 2013 10CFR20, 10CFR50 and 40CFR190. In addition, 40CFR141 imposes limits on the concentration of radioactivity in drinking water provided by the operators of public water systems.

• 10CFR20, Standards for Protection Against Radiation This revision of the ODCM addresses the requirements of 10CFR20.

The 10CFR20 dose limits are summarized in Table 1-1.

• Design Criteria (Appendix A of 10CFR50)

Section 50.36 of 10CFR50 requires that an application for an operating license include proposed Technical Specifications. Final Technical Specifications for each station are developed through negotiation between the applicant and the NRC. The Technical Specifications are then issued as a part of the operating license, and the licensee is required to operate the facility in accordance with them. Section 50.34 of 10CFR50 states that an application for a license must state the principal design criteria of the facility. Minimum requirements are contained in Appendix A of 10CFR50.

• ALARA Provisions (Appendix I of 10CFR50)

Sections 50.34a and 50.36a of 10CFR50 require that the nuclear plant design and the station RECS have provisions to keep levels of radioactive materials in effluents to UNRESTRICTED AREAS "As Low As Reasonably Achievable" (ALARA). Although 10CFR50 does not impose specific limits on releases, Appendix I of 10CFR50 does provide numerical design objectives and suggested limiting conditions for operation. According to Section I of Appendix I of 10CFR50, design objectives and limiting conditions for operation, conforming to the guidelines of Appendix I "shall be deemed a conclusive showing of compliance with the "As Low As Reasonably Achievable" requirements of 10CFR50.34a and 50.36a." An applicant must use calculations to demonstrate conformance with the design objective dose limits of Appendix I. The calculations are to be based on models and data such that the actual radiation exposure of an individual is "unlikely to be substantially underestimated" (see 10CFR50 Appendix I, Section III.A.1). The guidelines in Appendix I call for an investigation, corrective action and a report to the NRC whenever the calculated dose due to the radioactivity released in a calendar quarter exceeds one-half of an annual design objective. The guidelines also require a surveillance Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 136 of 307 January 2013 program to monitor releases, monitor the environment and identify changes in land use.

• 40CFR1 90, Environmental Radiation Protection Standards for Nuclear Power Operations Under an agreement between the NRC and the EPA, the NRC stipulated to its licensees in Generic Letter 79-041 that "Compliance with Radiological Effluent Technical Specifications (RETS), NUREG-0473 (Rev.2) for BWR's, implements the LWR provisions to meet 40CFR190". (See Reference 103 and 49.)

The regulations of 40CFR1 90 limit radiation doses received by members of the public as a result of operations that are part of the uranium fuel cycle. Operations must be conducted in such a manner as to provide reasonable assurance that the annual dose equivalent to any member of the public due to radiation and to planned discharges of radioactive materials does not exceed the following limits: o 25 mrem to the total body o 75 mrem to the thyroid o 25 mrem to any other organ An important difference between the design objectives of 10CFR50 and the limits of 40CFR190 is that 10CFR50 addresses only doses due to radioactive effluents. 40CFR190 limits doses due to effluents and to radiation sources maintained on site. See Section 1.2.4 for further discussion of the differences between the requirements of 10CFR50 Appendix I and 40CFR1 90.

• 40CFR141, National Primary Drinking Water Regqulations The following radioactivity limits for COMMUNITY WATER SYSTEMS were established in the July, 1976 Edition of 40CFR141:

o Combined Ra-226 and Ra-228: < 5 pCi/L. o Gross alpha (particle activity including Ra-226 but excluding radon and uranium): < 15 pCi/L. o The average annual concentration of beta particle and photon radioactivity from man-made radionuclides in drinking water shall not produce an annual dose equivalent to the total body or any internal organ greater than 4 mrem/yr. The regulations specify procedures for determining the values of annual average radionuclide concentration that produce an annual dose equivalent of 4 mrem. Radiochemical analysis methods are also specified. The responsibility for monitoring radioactivity in a Quad Cities ODCM Part II

CY-QC-170-301 Revision 11 Page 137 of 307 January 2013 COMMUNITY WATER SYSTEM falls on the supplier of the water. There are no drinking water supplies affected by the operation of the Quad Cities Station. Therefore Quad Cities has no requirements related to 40CFR141 in the RECS.

• 10CFR72, Licensingq Requirements for the Independent Storage of Spent Nuclear Fuel, High-Level Radioactive Waste, and Reactor-Related Greater Than Class C Waste 10CFR72.104 states that annual dose to any real individual located beyond the controlled area must not exceed the following:

o 25 mrem to the total body o 75 mrem to the thyroid o 25 mrem to any other critical organ as a result of planned discharges of radioactive material to the environment, direct radiation from ISFSI operation, and other radiation from uranium fuel cycle operation (40CFR190). These requirements are consistent with the requirements of 40CFR190. 1.2.2 Radiological Effluent Technical Standards The Radiological Effluent Technical Standards (RETS) were formerly a subset of the Technical Specifications. They implement provisions of the Code of Federal Regulations aimed at limiting offsite radiation dose. The NRC published Standard RETS for BWRs (Reference 3) as guidance to assist in the development of technical specifications. These documents have undergone frequent minor revisions to reflect changes in plant design and evolving regulatory concerns. The RETS have been removed from the Technical Specifications and placed in the ODCM as the RECS (see Reference 90). The RECS are similar but not identical to the guidance of the Standard Radiological Effluent Technical Specifications. 1.2.3 Offsite Dose Calculation Manual The NRC in Generic Letter 89-01 defines the ODCM as follows (not verbatim) (see Reference 90): The Offsite Dose Calculation Manual (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm/Trip Setpoints, and in the conduct of the Radiological Environmental Monitoring Program. The ODCM shall also contain (1) the Radioactive Effluent Controls and Quad Cities ODCM Part II

CY-QC-170-301 Revision 11 Page 138 of 307 January 2013 Radiological Environmental Monitoring Programs and (2) descriptions of the Information that should be included in the Annual Radiological Environmental Operating and Annual Radioactive Effluent Release Reports. Additional requirements for the content of the ODCM are contained throughout the text of the RECS. 1.2.4 Overlapping Requirements In 10CFR20, 10CFR50 and 40CFR190, there are overlapping requirements regarding offsite radiation dose and dose commitment to the total body. In 10CFR20.1301, the total effective dose equivalent (TEDE) to a member of the public is limited to 100 mrem per calendar year. In addition, Appendix I to 10CFR50 establishes design objectives on annual total body dose or dose commitment of 3 mrem per reactor for liquid effluents and 5 mrem per reactor for gaseous effluents (see 10CFR50 Appendix I, Sections II.A and II.B.2(a)). Finally, 40CFR190 limits annual total body dose or dose commitment to a member of the public to 25 mrem due to all uranium fuel cycle operations. While these dose limits/design objectives appear to overlap, they are different and each is addressed separately by the RECS. Calculations are made and reports are generated to demonstrate compliance to all regulations. Refer to Table 1-1 and Table 1-2 for additional information regarding instantaneous effluent limits, design objectives and regulatory compliance. 1.2.5 Dose Receiver Methodology Table 1-2 lists the location of the dose recipient and occupancy factors, if applicable. Dose is assessed at the location in the UNRESTRICTED AREA where the combination of existing pathways and receptor age groups indicates the maximum potential exposures. The dose calculation methodology is consistent with the methodology of Regulatory Guide 1.109 (Reference 6) and NUREG 0133 (Reference 14). Dose is therefore calculated to a maximum individual. The maximum individual is characterized as "maximum" with regard to food consumption, occupancy and other usage of the area in the vicinity of the plant site. Such a "maximum individual" represents reasonable deviation from the average for the population in general. In all physiological and metabolic respects, the maximum individual is assumed to have those characteristics that represent averages for their corresponding age group. Thus, the dose calculated is very conservative compared to the "average" (or typical) dose recipient who does not go out of the way to maximize radioactivity uptakes and exposure. The dose limits of 40CFR1 90 and 10CFR72.104 are the same. Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 139 of 307 January 2013 Table 1-1 Regulatory Dose Limit Matrix REGULATION DOSE1 TYPE 1 DOSE LIMIT(s) [ Section O0CM Airborne Releases: (quarterly) (annual) 10CFR50 App. I' Gamma Dose to Air due to Noble Gas 5 mrad 10 mrad 4.2.2.1 Radionuclides (per reactor unit) Beta Dose to Air Due to Noble Gas 10 mrad 20 mrad 4.2.2.2 Radionuclides (per reactor unit) Organ Dose Due to Specified Non-Noble 7.5 mrem 15 mrem 4.2.3 Gas Radionuclides (per reactor unit) Total Body and Skin Total Body 2.5 mrem 5 mrem 4.2.2.3 Dose (if air dose is exceeded) Skin 7.5 mrem 15 mrem 4.2.2.4 Technical Specifications Total Body Dose Rate Due to Noble Gas Radionuclides (instantaneous limit, per 500 mrem/yr 4.2.1.1 site) Skin Dose Rate Due to Noble Gas Radionuclides (instantaneous limit, per 3,000 mrem/yr 4.2.1.2 site) Organ Dose Rate Due to Specified Non-Noble Gas Radionuclides (instantaneous 1,500 mrem/yr 4.2.1.3 limit, per site) Liquid Releases: (quarterly) (annual) 10CFR50 App. I' Whole (Total) Body Dose 1.5 mrem 3 mrem 3.4 (per reactor unit) Organ Dose (per reactor unit) 5 mrem 10 mrem 3.4 Technical Specifications The concentration of radioactivity in liquid Ten times the values effluents released to UNRESTRICTED listed in 10CFR20 AREAS Appendix B; Table 2, 3.2 Column 2, and in note 5 below for Noble Gases Total Doses 1. 10 CFR 20.1301 (a)(1) Total Effective Dose Equivalent 4 100 mrem/yr 5.2 10CFR20.1301 (d) Total Body Dose 25 mrem/yr 5.2 And 40CFR190 Thyroid Dose 75 mrem/yr 5.2 1 Other Oraan Dose 25 mrem/vr 5.2 4 mrem/yr 1 3.4 3.4 1 4 mrem/yr 1 These doses are calculated considering all sources of radiation and radioactivity in effluents. 2 These limits are not directly applicable to nuclear power stations. They are applicable to the owners or operators of public water systems. However, the Quad Cities RECS requires assessment of compliance with these limits. 3 Notethat 10CFR50 provides design objectives, not limits. 4 Compliance with 10CFR20.1301(a)(1) is demonstrated by compliance with 40CFR190. Note that it may be necessary to address dose from on-site activity by members of the public as well. 5 Kr-85m, Kr-85, Kr-87, Kr-88, Ar-41, Xe-131m, Xe-133m, Xe-133, Xe-135m and Xe-135 allowable concentration is 2E-4, 5E-4, 4E-5, 9E-5, 7E-5, 7E-4, 5E-4, 6E-4, 2E-4 and 2E-4 pCi/ml, respectively, computed from Equation 17 of ICRP Publication 2 adjusted for infinite cloud submersion in water, and R = 0.01 rem/wk, Pw = 1.0 g/cm3, and Pw/Pt = 1.0. Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 140 of 307 January 2013 Table 1-2 Dose Assessment Receivers Location; Occupancy if Dose Component or Pathway Different than 100%

"Instantaneous" dose rates from            UNRESTRICTED AREA boundary location airborne radioactivity                     that results in the maximum dose rate "Instantaneous" concentration limits in    Point where liquid effluents enter the liquid effluents                           UNRESTRICTED AREA Annual average concentration limits for    Point where liquid effluents enter the liquid effluents                           UNRESTRICTED AREA Receiver spends part of this time in the Direct dose from contained sources         controlled rsdneoareaihn     and the remainder ery     cuac at his residence or fishing nearby; occupancy factor is considered and is site-specific.

Receiver is at the UNRESTRICTED AREA Direct dose from airborne plume boundary location that results in the maximum dose. Dose due to radioiodines, tritium and Receiver is at the location in the particulates with half-lives greater than UNRESTRICTED AREA where the 8 days for inhalation, ingestion of combination of existing pathways and vegetation, milk and meat, and ground receptor age groups indicates the highest plane exposure pathways. potential exposures. The drinking water pathway is considered as an additive dose component in this Ingestion dose from drinking water assessment only if the public water supply serves the community immediately adjacent to the plant. Ingestion dose from eating fishboyfwae The receiver eats fish from the receiving body of water Total Organ Doses Summation of ingestion/inhalation doses Summation of above data (Note it may also Total Dose be necessary to address dose from on-site activity by members of the public.) Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 141 of 307 January 2013 Figure 1-1 illustrates some of the potential radiation exposure pathways to humans due to routine operation of a nuclear power station. Figure 1-1 Radiation Exposure Pathways to Humans Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 142 of 307 January 2013 1.3 Offsite Dose Calculation Parameters This section contains offsite dose calculation parameter factors, or values not specific only to one of the gas, liquid, or total dose chapters. Additional parameters are provided in the Sections 2.0, 4.0, and 5.0 of the ODCM. 10CFR50 Dose Commitment Factors With the exception of H-3, the dose commitment factors for 1 OCFR50 related calculations are exactly those provided in Regulatory Guide 1.109 (Reference 6). The following table lists the parameters and the corresponding data tables in the RG 1.109: PATHWAY ADULT TEENAGER CHILD INFANT Inhalation RG 1.109: RG 1.109: RG 1.109: RG 1.109: Table E-7 Table E-8 Table E-9 Table E-10 Ingestion RG 1.109: RG 1.109: RG 1.109: RG 1.109: Table E-11 Table E-12 Table E-13 Table E-14 These tables are contained in Regulatory Guide 1.109 (Reference 6). Each table (E-7 through E-14) provides dose factors for seven organs for each of 73 radionuclides, and Table E-5 lists Miscellaneous Dose Assessment Factors - Consumption Parameters. For radionuclides not found in these tables, dose factors will be derived from ICRP 2 (Reference 50) or NUREG-0172 (Reference 51). The values for H-3 are taken from NUREG-4013 (Reference 107). 1.4 References The references listed below were transferred from the previous ODCM revision that was common to all former Commonwealth Edison nuclear stations. The references not applicable to Quad Cities Station have been deleted, however the numbering has been preserved for ease of reference management throughout the ODCM document; therefore, reference numbering is not sequential.

3. U.S. Nuclear Regulatory Commission, Standard Radiological Effluent Technical Specifications for Boilinq Water Reactors, NUREG-0473, Rev. 3, Draft, September 1982 (frequently revised).

4. U.S. Nuclear Regulatory Commission, Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants, Regulatory Guide 1.21. Revision 1, June 1974.

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5. U.S. Nuclear Regulatory Commission, Onsite Meteorological Programs, Regulatory Guide 1.23, Safety Guide 23, February 17, 1972.

6. U.S. Nuclear Regulatory Commission, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50 Appendix I, Regulatory Guide 1.109, Rev.

1, October 1977.

7. U.S. Nuclear Regulatory Commission, Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors, Regulatory Guide 1.111, Rev. 1, July 1977.

8. U.S. Nuclear Regulatory Commission, Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Li-ght-Water-Cooled Power Reactors, Regulatory Guide 1.112, Rev. 0-R, April 1976; reissued May 1977.

9. U.S. Nuclear Regulatory Commission, Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I, Regulatory Guide 1.113, Rev. 1, April 1977.

10. U.S. Nuclear Regulatory Commission, Programs for Monitoring Radioactivity in the Environs of Nuclear Power Plants, Regulatory Guide 4.1, Rev. 1, April 1975.

11. U.S. Nuclear Regulatory Commission, Preparation of Environmental Reports for Nuclear Power Stations, Regulatory Guide 4.2, Rev. 2, July 1976.

12. U.S. Nuclear Regulatory Commission, Environmental Technical Specifications for Nuclear Power Plants, Regulatory Guide 4.8, Rev. 1, December 1975. (See also the related Radiological Assessment Branch Technical Position, Rev. 1, November 1979.)

13. U.S. Nuclear Regulatory Commission, Quality Assurance for Radiological Monitoring Programs (Normal Operations)--Effluent Streams and the Environment, Regulatory Guide 4.15, Rev. 1, February 1979.

14. U.S. Nuclear Regulatory Commission, Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants, edited by J. S. Boegli et al. NUREG-0133, October 1978.

15. U.S. Nuclear Regulatory Commission, XOQDOQ: Computer Program for the Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations, J. F. Sagendorf et al. NUREG/CR-2919, PNL-4380, September 1982.

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16. U.S. Nuclear Regulatory Commission, Radiological Assessment, edited by J. E. Till and H. R. Meyer, NUREG/CR-3332, ORNL-5968, September 1983.

17. U.S. Nuclear Regulatory Commission, Standard Review Plan, NUREG-0800, July 1981.

18. U.S. Atomic Energy Commission, Meteorology and Atomic Energy 1968, edited by D. H. Slade, TID-21940, July 1968.

19. U.S. Atomic Energy Commission, Plume Rise, G. A. Briggs, TID-25075, 1969.

20. U.S. Atomic Energy Commission, The Potential Radiological Implications of Nuclear Facilities in the Upper Mississippi River Basin in the Year 2000, WASH 1209, January 1973.

21. U.S. Atomic Energy Commission, HASL Procedures Manual, Health and Safety Laboratory, HASL-300 (revised annually).

22. U.S. Department of Energy, Models and Parameters for Environmental Radiological Assessments, edited by C- W. Miller, DOE/TIC-I 1468,1984.-

23. U.S. Department of Energy, Atmospheric Science and Power Production, edited by D. Randerson, DOE/TIC-27601, 1984.

24. U.S. Environmental Protection Agency, Workbook of Atmospheric Dispersion Estimates, D. B. Turner, Office of Air Programs Publication No.

AP-26, 1970.

25. U.S. Environmental Protection Agency, 40CFR190 Environmental Radiation Protection Requirements for Normal Operations of Activities in the Uranium Fuel Cycle, Final Environmental Statement, EPA 520/4-76-016, November 1,1976.

26. U.S. Environmental Protection Agency, Environmental Analysis of the Uranium Fuel Cycle, EPA-520/9-73-003-C, November 1973.

27. American Society of Mechanical Engineers, Recommended Guide for the Prediction of the Dispersion of Airborne Effluents, 1973.

28. Eisenbud, M., Environmental Radioactivity, 3rd Edition, (Academic Press, Orlando, FL, 1987).

29. Glasstone, S., and Jordan, W. H., Nuclear Power and Its Environmental Effects (American Nuclear Society, LaGrange Park, IL, 1980).

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30. International Atomic Energy Agency, Generic Models and Parameters for Assessing the Environmental Transfer of Radionuclides from Routine Releases, Safety Series, No. 57, 1982.

31. National Council on Radiation Protection and Measurements, Radiological Assessment: Predicting the Transport, Bioaccumulation, and Uptake by Man of Radionuclides Released to the Environment, NCRP Report No. 76, March 15, 1984.

32. American National Standards Institute, Guide to Sampling Airborne Radioactive Materials in Nuclear Facilities, ANSI N13.1-1969, February 19, 1969.

33. Institute of Electrical and Electronics Engineers, Specification and Performance of On-Site Instrumentation for Continuously Monitoring Radioactivity in Effluents, ANSI N13.10-1974, September 19, 1974.

34. American National Standards Institute, Testing and Procedural Specifications for Thermoluminescence Dosimetry (Environmental Applications), ANSI N545-1975, August 20, 1975.

35_-AmericanNuclear Insurers, Effluent MonitorinqANI/MAELU Engineering - Inspection Criteria for Nuclear Liability Insurance, Section 5.1, Rev. 2, October 24, 1986.

36. American Nuclear Insurers, Environmental Monitoring, ANI/MAELU Engineering Inspection Criteria for Nuclear Liability Insurance, Section 5.2, Rev. 1, March 23, 1987.

37. American Nuclear Insurers, Environmental Monitoring Programs, ANI/MAELU Information Bulletin 86-1, June 9, 1986.

39. Electric Power Research Institute, Guidelines for Permanent BWR Hydrogen Water Chemistry Installations--1987 Revision, EPRI NP-5283-SR-A, Special Report, September 1987.

41. U.S. Nuclear Regulatory Commission, Branch Technical Position, Radiological Assessment Branch, Revision 1, November 1979. (This is a branch position on Regulatory Guide 4.8.)

44. U.S. Nuclear Regulatory Commission, Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Boiling Water Reactors (BWR-GALE Code), NUREG-0016, April 1976.

45. Sargent & Lundy, N-16 Skyshine from BWR Turbine Systems and Piping, NSLD Calculation No. D2-2-85, Rev. 0, 2/1/85.

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48. Sargent & Lundy Calculation ATD-0140, Rev. 0, N-16 Skyshine Ground Level Dose from Quad Cities Turbine Systems and Piping., July 28, 1992.

49. U.S. Nuclear Regulatory Commission, Methods for Demonstrating LWR Compliance with the EPA Uranium Fuel Cycle Standard (40 CFR Part 190),

NUREG-0543, February 1980.

50. International Commission on Radiological Protection, Report of Committee Two on Permissible Dose for Internal Radiation, Recommendations of the International Commission on Radiological Protection, ICRP Publication 2, 1959.

51. U.S. Nuclear Regulatory Commission, Age-Specific Radiation Dose Commitment Factors for a One-Year Chronic Intake, Battelle Pacific Northwest Laboratories, NUREG-01 72, 1977.

52. W. C. Ng, Transfer Coefficients for Prediction of the Dose to Man via the Forage-Cow-Milk Pathway from Radionuclides Released to the Biosphere, UCRL-51939.

53. E. C. Eimutis and M. G. Konicek, Derivations of Continuous Functions for the Lateral and Vertical Atmospheric Dispersion Coefficients, Atmospheric Environment 6, 859 (1972).

54. D. C. Kocher, Editor, Nuclear Decay Data for Radionuclides Occurring in Routine Releases from Nuclear Fuel Cycle Facilities, ORNL/NUREG/TM-102, August 1977.

55. R. L. Heath, Gamma-Ray Spectrum Catalog, Aerojet Nuclear Co.,

ANCR-1000-2, third or subsequent edition.

56. S. E. Thompson, Concentration Factors of Chemical Elements in Edible Aquatic Organisms, UCRL-50564, Rev. 1, 1972.

57. U.S. Nuclear Regulatory Commission, Instruction Concerning Risks from Occupational Radiation Exposure, Regulatory Guide 8.29, July 1981.

62. Sargent & Lundy Calculation ATD-0175, Rev. 0, 9/21/92, Annual Dose to Members of the Public Due to the Quad Cities IRSF.

70. D. C. Kocher, Radioactivity Decay Data Tables, DOE/TIC-1 1026, 1981.

71. J. C. Courtney, A Handbook of Radiation Shieldinq Data, ANS/SD-76/14, July 1976.

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74. Commonwealth Edison Company, Information Relevant to Keeping Levels of Radioactivity in Effluents to Unrestricted Areas As Low As Reasonably Achievable, Quad Cities Station, Units 1 and 2, June 4, 1976.

75. Sargent & Lundy, METWRSUM, S&L Program Number 09.5.187-1.0.

76. Sargent & Lundy, Comments on CECo ODCM and List of S&L Calculations, Internal Office Memorandum, P. N. Derezotes to G. R. Davidson, November 23, 1988.

77. Sargent & Lundy, AZAP, A Computer Program to Calculate Annual Average Offsite Doses from Routine Releases of Radionuclides in Gaseous Effluents and Postaccident X/Q Values, S&L Program Number 09.8.054-1.7.

78. National Oceanic and Atmospheric Administration, A Program for Evaluating Atmospheric Dispersion from a Nuclear Power Station, J.. F. Sagendorf, NOAA Technical Memorandum ERL ARL-42, Air Resources Laboratory, Idaho Falls, Idaho, May 1974.

79. G. P. Lahti, R. S. Hubner, and J. C. Golden, Assessment of Gamma-Ray Exposures Due to Finite Plumes, Health Physics 41, 319 (1981).

80. National Council of Radiation Protection and Measurements, Ionizing Radiation Exposure of the Population of the United States, NCRP Report No. 93, September 1, 1987.

82. W. R. Van Pelt (Environmental Analysts, Inc.), Letter to J. Golden (Exelon Nuclear) dated January 3, 1972.

83. Electric Power Research Institute, Radiological Effects of Hydrogen Water Chemistry, EPRI NP-4011, May 1985.

84. U.S. Nuclear Regulatory Commission, Draft Generic Environmental Impact Statement on Uranium Milling, NUREG-0511, April 1979.

85. U.S. Environmental Protection Agency, Environmental Analysis of the Uranium Fuel Cycle, Part I - Fuel Supply, EPA-520/9-73-003-B, October 1973.

86. U.S. Nuclear Regulatory Commission, Final Generic Environmental Statement on the Use of Recycle Plutonium in Mixed Oxide Fuel in Light Water Cooled Reactors, NUREG-0002, August 1976.

87. U.S. Nuclear Regulatory Commission, Demographic Statistics Pertaining to Nuclear Power Reactor Sites, NUREG-0348, Draft, December 1977.

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89. General Electric Company, Irradiated Fuel Storagqe at Morris Operation, Operating Experience Report, January 1972 through December 1982, K. J.

Eger, NEDO-20969B.

90. U.S. Nuclear Regulatory Commission, Generic Letter 89-01, "Guidance For The Implementation of Programmatic Controls For RETS In The Administrative Controls Section of Technical Specifications and the Relocation of Procedural Details of Current RETS to the Offsite Dose Calculation Manual or Process Control Program", January 1989.

92. NRC Safety Evaluation Report (SER)/Idaho Notional Engineering Laboratory Technical Evaluation Report (TER) of the Commonwealth Edison Offsite Dose Calculation Manual (ODCM), Revision O.A, December 2, 1991.

95. U.S. Nuclear Regulatory Commission, Standards for Protection Against Radiation (10CFR20).

96. U.S. Nuclear Regulatory Commission, Licensing of Production and Utilization Facilities (10CFR50).

98. Miller, Charles W., Models and Parameters for Environmental Radiological Assessments, U.S. Dept. of Energy, DE8102754, 1984, pages 32, 33, 48, and 49.

99. Kocher, D. C., "Dose-Rate Conversion Factors For External Exposure To Photons and Electrons", Health Physics Vol. 45, No. 3 (September), pp.

665-686, 1983. 100. U.S. Department of Health, Education and Welfare Public Health Service, Radiological Health Handbook, January 1970. 101. ODCM Bases and Reference Document, rev. 0, November, 1998. 102. G. Moran, D. Goff, Quad Cities Nuclear Power Station; 1993 Hydrogen Water Chemistry Stress Corrosion Monitoring Test - Unit 2, 9/17-23/93. 103. U.S. Nuclear Regulatory Commission, Generic Letter 79-041, September 17, 1979. 104. Federal Register, Vol. 56, No. 98, Tuesday, May 21, 1991, page 23374, column 3. 106. U.S. Nuclear Regulatory Commission, Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Boiling Water Reactors, NUREG-1302, April 1991. Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 149 of 307 January 2013 107. U.S. Nuclear Regulatory Commission, LADTAP II - Technical Reference and Users Guide, NUREG-4013, April 1986. 108. 10CFR72, Licensinq Requirements for the Independent Storage of Spent Nuclear Fuel, High-Level Radioactive Waste, and Reactor-Related Greater Than Class C Waste 109. Holtec Report No. Hi-2053404, Dose Versus Distance From a Single Cask at the Quad Cities ISFSI. Holtec International, 07/15/05. 110. Quad Cities UFSAR Section 2.3, Meteorology. 111. U.S. Nuclear Regulatory Commission, Safety Guide 23, On-Site Meteorological Programs, 02-17-72. Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 150 of 307 January 2013 Table 1-3 Miscellaneous Dose Assessment Factors: Environmental Parameters Parameter Value Comment Equation Basisa f__ 0.76 4-11, 4-12a, 4-12b A fL 1.0 4-11,4-12a, 4-12b A f, 1.0 4-13,4-15 A f, 1.0 4-13,4-15 A tb 262,800 30 years 4-9 C hrs tf 48 hrs Cow Milk Pathway 4-13 A tf 480 hrs Cow Meat Pathway 4-15 A th 1440 hrs 60 days for produce human 4-11 A consumption th 2160 hrs 90 days for produce animal 4-13,4-15 A consumption tL 24 hrs 1 day for leafy vegetables 4-11 A QF 50 Cow Consumption Rate 4-13, 4-14a, 4-15, B Kg/day 4-16a r 1.0 For lodines 4-11,4-13, 4-15 A r 0.2 For Particulates 4-11,4-13, 4-15 A YP 0.7 2 4-13, 4-15 A Kg/M YS 2.0 2 4-13,4-15 A Kg/M Yv 2.0 2 4-11 A Kg/M 0.0021 4-11, 4-13, 4-15 A hr 1 H 8 gm/mi Absolute Atmospheric Humidity 4-12a, 4-14a, 4-16a D p 1.0 fractional equilibrium ratio (4400 4-12b, 4-14b, 4-16b E hrs/8760 hrs). The ratio of the total annual release time (for C-14 atmospheric releases) to the total annual time during photosynthesis occurs (taken to be 4400 hrs), under the condition that the value of p should never exceed unity. For continuous C-14 releases, p is taken to be unity. aBasis key: A: Reference 6, Table E-15. B: Reference 6, Table E-3. C: The parameter tb is taken as the midpoint of plant operating life (based upon an assumed 60 year plant operating lifetime). D: Reference 14, Section 5.3.1.3. E: Reference 6, Appendix C Section 3 Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 151 of 307 January 2013 Table 1-4 (Page 1 of 2) Stable Element Transfer Data Ff FM(COw) Element Meat (d/kq) Milk (d/L) Reference H 1.2E-02 1.OE-02 6 Be 1.5E-03 3.2E-03 Footnote 1 C 3.1 E-02 1.2E-02 6 F 2.9E-03 1.4E-02 Footnote 2 Na 3.OE-02 4.OE-02 6 Mg 1.5E-03 3.2E-03 Footnote 1 Al 1.5E-02 1.3E-03 Footnote 3 P 4.6E-02 2.5E-02 6 Cl 2.9E-03 1.4E-02 Footnote 2 Ar NA NA NA K 1.8E-02 7.2E-03 16 Ca 1.6E-03 1.1E-02 16 Sc 2.4E-03 7.5E-06 Footnote 4 Ti 3.4E-02 5.OE-06 Footnote 5 V 2.8E-01 1.3E-03 Footnote 6 Cr 2.4E-03 2.2E-03 6 Mn 8.OE-04 2.5E-04 6 Fe 4.OE-02 1.2E-03 6 Co 1.3E-02 1.OE-03 6 Ni 5.3E-02 6.7E-03 6

             -Cu        8.OE-03               1.4E-02                 6                -*

Zn 3.OE-02 3.9E-02 6 Ga 1.5E-02 1.3E-03 Footnote 3 Ge 9.1 E-04 9.9E-05 Footnote 7 As 1.7E-02 5.OE-04 Footnote 8 Se 7.7E-02 1.OE-03 Footnote 9 Br 2.9E-03 2.2E-02 Ff Footnote 2 ;FM from Ref. 16 Kr NA NA NA Rb 3.1 E-02 3.OE-02 6 Sr 6.OE-04 8.OE-04 6 Y 4.6E-03 1.OE-05 6 Zr 3.4E-02 5.OE-06 6 Nb 2.8E-01 2.5E-03 6 Mo 8.OE-03 7.5E-03 6 Tc 4.OE-01 2.5E-02 6 Ru 4.OE-01 1.OE-06 6 Rh 1.5E-03 1.OE-02 6 Pd 5.3E-02 6.7E-03 Footnote 10 Cd 3.OE-02 2.OE-02 Footnote 11 In 1.5E-02 1.3E-03 Footnote 3 Sn 9.1 E-04 9.9E-05 Footnote 7 Sb 5.OE-03 2.OE-05 98 Ag 1.7E-02 5.OE-02 6 Te 7.7E-02 1.OE-03 6 I 2.9E-03 6.OE-03 6 Xe NA NA NA Cs 4.OE-03 1.2E-02 6 Ba 3.2E-03 4.OE-04 6 La 2.OE-04 5.OE-06 6 Ce 1.2E-03 1.OE-04 6 Pr 4.7E-03 5.OE-06 6 Nd 3.3E-03 5.OE-06 6 Quad Cities ODCM Part II

CY-QC-170-301 Revision 11 Page 152 of 307 January 2013 Table 1-4 (Page 2 of 2) Stable Element Transfer Data Ff FM (Cow) Element Meat (d/kcq) Milk (d/L) Reference Pm 2.9E-04 2.OE-05 16 Sm 2.9E-04 2.OE-05 16 Eu 2.9E-04 2.OE-05 16 Gd 2.9E-04 2.OE-05 16 Dy 2.9E-04 2.OE-05 16 Er 2.9E-04 2.OE-05 16 Tm 2.9E-04 2.OE-05 16 Yb 2.9E-04 2.OE-05 16 Lu 2.9E-04 2.OE-05 16 Hf 3.4E-02 5.OE-06 Footnote 5 Ta 2.8E-01 1.3E-03 FM - Ref. 16; Ff -Footnote 6 W 1.3E-03 5.OE-04 6 Re 1.0E-01 1.3E-03 FM - Ref. 16; Ff -Footnote 12 Os 2.2E-01 6.OE-04 Footnote 13 Ir 7.3E-03 5.5E-03 Footnote 14 Pt 5.3E-02 6.7E-03 Footnote 10 Au 1.3E-02 3.2E-02 Footnote 15 Hg 3.OE-02 9.7E-06 FM - Ref. 16; Ff -Footnote 11 TI 1.5E-02 1.3E-03 FM - Ref. 16; Ff -Footnote 3 Pb 9.1E-04 9.9E-05 98 Bi 1.7E-02 5.OE-04 98 Ra 5.5E-04 5.9E-04 98 Th 1.6E-06 5.OE-06 98 U 1.6E-06 1.2E-04 98 Np 2.OE-04 5.OE-06 6 Am 1.6E-06 2.OE-05 98 Notes:

1. NA = It is assumed that noble gases are not deposited on the ground.

2. Elements listed are those considered for 10CFR20 assessment and compliance.

Footnotes: There are numerous Ff and FM values that were not found in published literature. In these cases, the periodic table was used in conjunction with published values. The periodic table was used based on a general assumption that elements have similar characteristics when in the same column of the periodic table. The values of elements in the same column of the periodic table, excluding atomic numbers 58-71 and 90-103, were averaged then assigned to elements missing values located in the same column of the periodic table. This method was used for all columns where there were missing values except column 3A, where there was no data, hence, the average of column 28 and 4A were used.

1. Values obtained by averaging Reference 6 values of Ca, Sr, Ba and Ra.

2. Ff value obtained by assigning the Reference 6 value for I. FM value obtained by averaging I (Ref. 6) and Br (Ref.16).

3. Ff values obtained by averaging Zn (Ref. 6) and Pb (Ref. 98); there were no values for elements in the same column; an average is taken between values of columns 2B and 4A on the periodic table. FM values obtained by using the value for TI from Reference 16.

4. Values obtained by averaging Reference 6 values of Y and La.

5. Values obtained by assigning the Reference 6 value for Zr.

6. Ff values obtained from Ref. 6 value for Nb. FM values obtained by averaging values for Nb (Ref. 6) and Ta (Ref. 16).

7. Values obtained from the Reference 6 values for Pb.

8. Values obtained from the Reference 6 values for Bi.

9. Values obtained from the Reference 6 values for Te.

10. Values obtained from the Reference 6 values for Ni.

11. Ff values obtained from Ref. 6 values for Zn. FM values obtained by averaging the Reference 6 values for Zn and Hg.

12. Values obtained by averaging Reference 6 values for Mn, Tc, Nd and Reference 98 value for U.

13. Values obtained by averaging Reference 6 values from Fe and Ru.

14. Values obtained by averaging Reference 6 values from Co and Rh.

15. Values obtained by averaging Reference 6 values from Cu and Ag.

Quad Cities ODCM Part II

70-301 CY-QC-1 Revision 11 Page 153 of 307 January 2013 Figure 1-2 Part II Quad Cities ODCM

CY-QC-1 70-301 Revision 11 Page 154 of 307 January 2013 Figure 1-3

• c*Restricted Area Bouncary OSITDOECLUAINMUL OFFSITE DOSE CALCULATION MANUAL T mC3I zIt QUAD CITIES STATION Iow a! 1l00I 20M FEET I

RESTRICTED AREA BOUNOARY GRAPHIC SCALE Quad Cities ODCM Part II

CY-QC-170-301 Revision 11 Page 155 of 307 January 2013 SYSTEMS 2.0 INSTRUMENTATION AND 2.1 Liquid Releases 2.1.1 System Description Simplified liquid radwaste and liquid effluent flow diagrams are provided in Figure 2-2 & Figure 2-3. The liquid radwaste treatment system is designed and installed to reduce radioactive liquid effluents by collecting the liquids, providing for retention or holdup, and providing for treatment by demineralizer for the purpose of reducing the total radioactivity prior to release to the environment. The system is described in Section 11.2 of the Quad Cities UFSAR. 2.1.1.1 River Discharge Tank There is one river discharge tank (65,000 gallons capacity) that receives water for discharge to the Mississippi River. This is the only release path in use. 2.1.2 Radiation Monitors 2.1.2.1 Liquid Radwaste Effluent Monitor Monitor 1/2-1799-01 is used to monitor all releases from the river discharge tank. On high alarm the release is terminated manually. Pertinent information on the monitor and associated control devices is provided in Quad Cities UFSAR Sections 11.5.2 and 11.5.3. 2.1.2.2 Service Water Effluent Monitors Monitors 1(2)-1799-01 continuously monitor the service water effluent. These monitors initiate no control device. Pertinent information on these monitors is provided in Quad Cities UFSAR 11.5.3. Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 156 of 307 January 2013 Trip Setpoints 2.1.3 Alarm and 2.1.3.1 Setpoint Calculations Alarm and trip setpoints of liquid effluent monitors at the principal release points are established to ensure that the limits of RECS are not exceeded in the UNRESTRICTED AREA. Currently these setpoints are based on the most conservative releases during the previous 18 months. If it is determined that this is no longer conservative, the setpoints are reevaluated. 2.1.3.1.1. Liquid Radwaste Effluent Monitor The monitor setpoint is found by solving equation 2.0-1 for the total isotopic activity. (x ______ C ]x[(0.5F",: ;+ F'~ 1+B (2.0-1) P Release Setpoint [cpm] C T Concentration of radionuclide "i" in [pCi/ml] the release tank. Frmax Maximum Release Tank Discharge Flow Rate [gpm] The flow rate from the radwaste discharge tank. K Calibration constant [cpm/jiCi/ml] DWC1 Derived Water Concentration of radionuclide "i" ((Ci/ml] From Appendix B, Table 2, Column 2 to 10CFR20. 1001-20.2402. 10 Multiplier granted in Technical Specifications applied to the DWC FdAVG Average dilution flow of initial dilution [gpm] stream B Background Count Rate [cpm] Quad Cities ODCM Part II

CY-QC-170-301 Revision 11 Page 157 of 307 January 2013 2.1.3.1.2. Service Water Effluent Monitors The monitor setpoint is found by solving equation 2.0-2. (K)x [ _-5 C ] [(Fd"'+F'..) ] +B (2.0-2) Ci Concentration of radionuclide "i" in service water If there is no detectable activity then pCi/1Ci/1 0*DWCi) is assumed to bel x 10-5 pCi/ml. Frmax Maximum discharge rate of service water for one unit. [gpm] All other terms are as defined in equation 2.0-1. Quad Cities ODCM Part II

CY-QC-1770-301 Revision 11 Page 158 of 307 January 2013 2.1.4 Discharge Flow Rates 2.1.4.1 Release Tank Discharge Flow Rate Prior to each BATCH RELEASE, a grab sample is obtained. The results of the analysis of the sample determine the discharge rate of each batch as follows: F,,= 01 UP(2.0-3) The summation is over radionuclides "i". 0.1 Reduction factor for conservatism. Frmax Maximum Permitted Discharge Flow Rate [gpm] The maximum permitted flow rate from the radwaste discharge tank. Fd Dilution Flow [gpm] C1 Concentration of Radionuclide "i"in the Release Tank [PtCi/ml] The concentration of radioactivity in the radwaste discharge tank based on measurements of a sample drawn from the tank. DWCj Derived Water Concentration of radionuclide "i" [1iCi/ml] From Appendix B, Table 2, Column 2 to 10CFR20.1001-0.2402. 10 Multiplier granted in Technical Specifications applied to the DWC Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 159 of 307 January 2013 2.1.5 Release Limits Release limits are determined from RECS. Calculated maximum permissible discharge rates are divided by 10 and dilution flows are divided by 2 to ensure that releases are well below applicable limits. (The factor of 2 used in the dilution flows accounts for discharging the RDT tank to the south diffuser pipe). 2.1.5.1 Release Mixture For the liquid radwaste effluent monitor the release mixture used for the setpoint determination is the radionuclide mix identified in the grab sample gamma isotopic analysis. H-3, Sr-89, Sr-90, and Fe-55 are not used in this calculation since the monitor cannot detect pure beta emitters. 2.1.5.2 Conversion Factors The readout for the liquid radwaste effluent monitor is in CPM. The calibration constant is based on the detector sensitivity to Cs-1 37. 2.1.5.3 Liquid Dilution Flow Rates The dilution flow is determined using equation 2.0-4 below. F" = (N"' x Fl""+ Nslt' x F"" - F ICE) (2.0-4) Fd = Dilution flow [gpm] NCW = Number of circulating water pumps on. FCW = 157000 [gpm] Flow with one circulating water pump on. NSW = Number of service water pumps on Fsw = 13800 [gpm] Flow with one service water pump on FICE = Deicing flow Quad Cities ODCM Part II

CY-QC-1770-301 Revision 11 Page 160 of 307 January 2013 2.1.5.4 Allocation of Effluents from Common Release Points Radioactive liquid effluent released from the release tank is comprised of contributions from both units. Allocation of waste is achieved by comparing the pump timer totals for each unit's floor drain and equipment drain pumps to the amount of waste sent to the river discharge tank from the floor drain and waste collector storage tanks. Liquid effluents from laundry and chemical waste are allocated evenly between units. During extended unit shutdown or periods of significant plant input differences, the apportionment is adjusted accordingly. The allocation of the effluents is made on a monthly basis. 2.1.5.5 Projected Concentrations for Releases If I 0DCi prior to dilution is greater than 25, the PROJECTED DOSE due to liquid effluent releases is calculated. Otherwise, the releases from the previous month are used to estimate the PROJECTED DOSE for the coming month using the methodology in ODCM Part II, Section 3.4. 2.1.6 Solidification of Waste/Process Control Program The Process Control Program (PCP) contains the current formulas, sampling, analysis, test, and determinations to be made to ensure that processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20, 61, and 71, State regulations, burial ground requirements, and other requirements governing the disposal of solid radioactive waste. Figure 2-4 is a simplified diagram of solid radwaste processing. 2.2 Airborne Releases 2.2.1 System Description A simplified gaseous radwaste and gaseous effluent flow diagram is provided in Figure 2-1. Each airborne release point is classified as stack, vent, or ground level in accordance with the definitions in Section 4.1.4. The principal release points for potentially radioactive airborne effluents and their classifications are as follows: Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 161 of 307 January 2013

• The ventilation chimney (a stack release point).
• The reactor building ventilation stack (a vent release point).

2.2.1.1 Condenser Offgas Treatment System The condenser offgas treatment system is designed and installed to reduce radioactive gaseous effluents by collecting non-condensable off-gases from the condenser and providing for holdup to reduce the total radioactivity via decay prior to release to the environment. Charcoal and HEPA filters retain the daughter products. The system is described in Section 11.3.2.1.1 of the Quad Cities UFSAR. 2.2.1.2 Ventilation Exhaust Treatment System Ventilation exhaust treatment systems are designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in selected effluent streams by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters prior to release to the environment. Such a system is not considered to have any effect on noble gas effluents. The ventilation exhaust treatment systems are shown in Figure 2-1. Engineered safety features atmospheric cleanup systems are not considered to be ventilation exhaust treatment system components. 2.2.2 Radiation Monitors 2.2.2.1 Plant Chimney Monitor Monitors 1(2)-1730A/B continuously monitor the final effluent from the chimney. The monitor system has isokinetic sampling, gaseous grab sampling, iodine and particulate sampling, and tritium sampling capability. The chimney effluent is also monitored by a separate particulate, iodine, and noble gas (SPING-4) system and a Victoreen system. The SPING/Victoreen system has high range capabilities to deal with accident conditions including post accident sampling capability. The Victoreen sampling system automatically begins taking samples after a high signal has been received on the SPING-4 low range noble gas monitor. Output from the SPING/Victoreen system is obtainable in the control room. These monitors perform no automatic isolation or control functions. Pertinent information on these monitors is provided in the Quad Cities UFSAR Section 11.5.2.3. Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 162 of 307 January 2013 2.2.2.2 Reactor Building Vent Stack Effluent Monitor The combined reactor building ventilation is also monitored by a SPING-4. This monitor has high range capabilities to deal with accident conditions. The SPING-4 noble gas detectors have ranges that envelope the range for the reactor building vent effluent trip point. The vent stack monitor has isokinetic sampling and iodine and particulate sampling capability. This monitor performs no automatic isolation or control functions. Pertinent information on this monitor is provided in the Quad Cities UFSAR Section 11.5.2.4. 2.2.2.3 Reactor Building Ventilation Monitors Monitors 1(2)-1735A/B continuously monitor the effluent from the Unit 1(2) reactor building. On high high alarm, the monitors automatically initiate closure of valves A01 (2)A-5741, A01 (2)B-5741, A01 (2)A-5742, and A01 (2)B-5742 thus isolating the Unit 1(2) reactor building, and initiate startup of the Unit 1(2) standby gas treatment system, and isolates control room HVAC. In addition to the above monitors, there is continuous iodine and particulate sampling of the reactor building exhaust. Pertinent information on these monitors is provided in Quad Cities UFSAR Section 11.5.2.4. The requirement to declare both channels INOPERABLE when the Reactor Building Vent Exhaust is isolated on one unit is discussed in Technical Specifications. 2.2.2.4 Condenser Air Ejector Monitors Monitors 1(2)-1733A/B continuously monitor gross gamma activity downstream of the steam jet air ejector and prior to release to the main chimney. On high high alarm the monitors automatically activate an interval timer which in turn initiates closure of air operated valve A01 (2)-5406, thus terminating the release. Monitors 1(2)-1741 continuously monitor the final offgas effluent prior to entering the chimney. These monitors initiate no control device and are not ODCM related monitors. Quad Cities ODCM Part II

CY-QC-170-301 Revision 11 Page 163 of 307 January 2013 Monitors 1(2)-1738 (flux tilt monitors) also continuously monitor gross gamma activity downstream of the steam jet air ejector. These monitors are not ODCM related monitors. Pertinent information on these monitors is found in Quad Cities UFSAR Sections 11.5.2.1 and 11.5.2.2. 2.2.3 Alarm and Trip Setpoints 2.2.3.1 Setpoint Calculations 2.2.3.1.1. Reactor Building Vent Stack Monitors The setpoint for the reactor building vent stack monitor is conservatively set at 2 mr/hr above background. The reactor building ventilation stack release rate, Qt,, at 2 mr/hr is calculated to be 14,400 .tCi/sec. Qt, is then substituted into Equations 2.0-5 and 2.0-6 to determine Qt,. 2.2.3.1.2. Condenser Air Ejector Monitors The high-high trip setpoint is established at <100 [tCi/sec per MWt (L2.5E5 [.Ci/sec) and the SJAE monitor high alarm setpoints are selected at 1.5 times normal full power background with hydrogen addition to satisfy the licensing commitments associated with the main steam line monitor Tech Spec amendment. 2.2.3.1.3. Plant Chimney Radiation Monitor The setpoints for the plant chimney radiation monitor are conservatively set at 10,000 [tCi/sec and 20,000 ptCi/sec (high and high-high alarms respectively). At this level the combined release from chimney and vent is approximately 10% of the RECS limit. This is determined by solving Equations 2.0-5 and 2.0-6 below. 2.2.3.2 Release Limits Alarm and trip setpoints of gaseous effluent monitors are established to ensure that the release rate limits of RECS are not exceeded. The release limit Qts is found by solving Equations 2.0-5 and 2.0-6. ZK .f {(XIQYQ,, +(XIQ/Q,)IQ< 500 mrem/ yr (2.0-5) Quad Cities ODCM Part II

CY-QC-170-301 Revision 11 Page 164 of 307 January 2013 _f{ ~L[ (x/Q)XQs+(X/Q).Q,]+ (1. (I) M[(/QQ,. +(x/Q( Qj}< 3 3 0 00 nme,,lyr (2.0-6) The summations are over noble gas radionuclides "i". fi Fractional Radionuclide Composition The release rate of noble gas radionuclide "i" divided by the total release rate of all noble gas radionuclides. Qts Total Allowed Release Rate, Stack Release [LCi/sec] The total Allowed release rate of all noble gas radionuclides released as stack releases. Qt, Total Allowed Release Rate, Vent Release [ptCi/sec] The total allowed release rate of all noble gas radionuclides released as vent releases. The remaining parameters in Equation 2.0-5 have the same definitions as in ODCM Part II, Section Equation 4-1. The remaining parameters in Equation 2.0-6 have the same definition as in Equation 4-2. Equation 2.0-5 is based on Equation 4-1 of ODCM Part II and the RECS restriction on whole body dose rate (500 mrem/yr) due to noble gases released in gaseous effluents (see Section 4.2.1.1 of ODCM Part II). Equation 2.0-6 is based on Equation 4-2 and the RECS restriction on skin dose rate (3000 mrem/yr) due to noble gases released in gaseous effluents (see ODCM Part II, Section 4.2.1.2). Equation 2.0-5 is used as the limiting noble gas release rate. Calibration methods and surveillance frequency for the monitors will be conducted as specified in the RECS. 2.2.3.3 Release Mixture In the determination of alarm and trip set points the radioactivity mixture in the exhaust air is assumed to be the same as the calculated effluent during the calendar quarter in which the monitor is recalibrated. 2.2.3.4 Conversion Factors The conversion factors used to establish gaseous effluent monitor setpoints are obtained as follows. Quad Cities ODCM Part II

CY-QC-170-301 Revision 11 Page 165 of 307 January 2013 2.2.3.4.1. Reactor building vent effluent monitor. The monitor setpoint is established at 2 mr/hr above background. For the purpose of setpoint determination it is assumed that the background is 1 mr/hr. There is sufficient conservatism in the setpoint calculation to accommodate routine variations in the background. However, the isotopic analysis in Section 2.2.3.3 is used to confirm that the setpoint is conservative. 2.2.3.4.2. Condenser air ejector monitor. The isotopic analysis in Section 2.2.3.3 and the flow and monitor reading at the time of the analysis are used to establish the conversion factor. 2.2.3.4.3. Plant chimney monitor. Calibration of the plant chimney monitor consists of recirculating an amount of off-gas (see 2.2.3.3) through the noble gas monitors and a Marinelli beaker. After readings have stabilized, the Marinelli beaker is removed and gamma isotopic analysis performed. The efficiency is determined from a plot of average gamma energy of the off-gas sample and net monitor readings. 2.2.3.5 HVAC Flow Rates The HVAC exhaust flow rates may be obtained from the process computers, indication in the control room, or fan combinations. Setpoints were calculated using the following values: Chim ney Air Flow ..................................................... 350,000 cfm Combined Reactor Vent* (1 fan) ............................... 48,000 cfm Combined Reactor Vent* (2 fans) ............................ 96,000 cfm

• per unit 2.2.4 Allocation of Effluents from Common Release Points Radioactive gaseous effluents released from the main chimney are comprised of contributions from both units. Under normal operating conditions, it is difficult to allocate the non-noble gaseous radioactivity between units due to fuel performance, in-plant leakage, power history, and other variables. Consequently, allocation is normally made evenly between the units. During extended unit shutdowns or periods of known differences, the apportionment is adjusted accordingly. The noble gaseous radioactivity is more easily allocated since the samples used for the calculations are unit specific. The allocation of effluents is estimated on a monthly basis.

Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 166 of 307 January 2013 2.2.5 Dose Projections Because the gaseous releases are continuous, the doses are routinely calculated in accordance with the RECS. Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 167 of 307 January 2013 Figure 2-1 11 DIAMETER Gn310' ABOVE GRADE M-.no... 57.OOOCFM 17 4 F ID 1-1730A 157.OSCF. TRITIUM

                                                                                                          '*               *,4E-7839 EDIAMETER 159'2AOVE GRADE P           I I

[VENTILATIO

                                                                                ~UNIT             -

2 OFF GAIASG RXBLDG SVENTILATOR EXHAUST STACK Ea-nOo 594.5. rO TE M.L LEGED AND NOTES OFFSITE DOSE CACLULATION MANUAL

                        -EEPAFTF                                                                                     QUAD-CITIES STATION UNITS 1 & 2 P. S-E                       R-OOO DMOTEOOR
                                 ~H5 IOODoES-LE                       NOWOLLYC        LOW ROT.CUOOF P*O                                       FIGURE 2-1 FLOW-,FOOOOOR-OOUTMO.oT11:       OoosI otFLOW Por P=POATcOL                    FEE FOOWELOTE                                       SlMPDLIFIED GASEOUS RADWASTE LO I=IOR.Je
                                                  **,NOTE                 :ALF-OROTOAT
                                                .. RNLo.&W~OH-N-L    CoOT FL-woTONOT c-A AND GASEOUS EFFLUENT FLow DIAGRAM CT tO Quad Cities ODCM Part II

CY-QC-170-301 Revision 11 Page 168 of 307 January 2013 Figure 2-2 RECYCLE To CONTAMNATED CONDENSATE SYSTEM FIGURE 2-2 SIMPLIFIED LIQUID RADWASTE PROCESSING DIAGRAM Quad Cities ODCM Part II

CY-QC-170-301 Revision 11 Page 169 of 307 January 2013 Figure 2-3 FLOW MISSISSIPPI RIVER NORTH CRIB HOUSE FIT-O-2002-140 (ABANDONED IN PLACE) L I Figure 2-3 Sti.LF1ED Liamu EFFLUENT FLOW DIAGRAM Quad Cities ODCM Part II

CY-QC-170-301 Revision 11 Page 170 of 307 January 2013 Figure 2-4 WASTE OFFSITE DISPOSAL DISPOSAL CONTAINER 4 DRUM SYSTEM NORrMALLY NOT USED MIXER USED ONLY WITH CEMENT SOLIDIFICATION . NOT USED WHEN DETWATER USING HIGH INTEGRITY CONTAINERS FIGURE 2-4 SIMPUFIED SOUD RADWASTE PROCESSING DIAGRAM Quad Cities ODCM Part II

CY-QC-1770-301 Revision 11 Page 171 of 307 January 2013 3.0 LIQUID EFFLUENTS 3.1 Liquid Effluent Releases - General Information 3.1.1 The design objectives of 10CFR50, Appendix I and RECS provide the following limits on the dose to a member of the public from radioactive materials in liquid effluents released from each reactor unit to RESTRICTED AREA boundaries:

• During any calendar quarter, less than or equal to 1.5 mrem to the total body and less than or equal to 5 mrem to any organ.
• During any calendar year, less than or equal to 3 mrem to the total body and less than or equal to 10 mrem to any organ.

3.1.2 The organ doses due to radioactivity in liquid effluents are also used as part of the 40CFR1 90 compliance and are included in the combination of doses to determine the total dose used to demonstrate 10CFR20 compliance. (See Section 5.0, TOTAL DOSE) 3.1.3 Dose assessments for 10CFR50 Appendix I compliance are made for four age groups (adult, teenager, child, infant) using NUREG 0133 (Reference

14) methodology and Regulatory Guide 1.109 (Reference 6) dose conversion factors.

3.1.4 To limit the consequences of tank overflow, the RECS/Technical Specifications may limit the quantity of radioactivity that may be stored in unprotected outdoor tanks. Unprotected tanks are tanks that are not surrounded by liners, dikes, or walls capable of holding the tank contents and that do not have tank overflows and surrounding area drains connected to the liquid radwaste treatment system. The specific objective is to provide assurance that in the event of an uncontrolled release of a tank's contents, the resulting radioactivity concentrations beyond the UNRESTRICTED AREA boundary, at the nearest potable water supply and at the nearest surface water supply, will be less than the limits of 10CFR20 Appendix B, Table 2; Column 2. The Technical Specifications and RECS may contain a somewhat similar provision. For most nuclear power stations, specific numerical limits are specified on the number of curies allowed in affected tanks. Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 172 of 307 January 2013 3.1.5 Cases in which normally non-radioactive liquid streams (such as the Service Water) are found to contain radioactive material are non-routine will be treated on a case specific basis if and when this occurs. Since the station has sufficient capacity to delay a liquid release for reasonable periods of time, it is expected that planned releases will not take place under these circumstances. Therefore, the liquid release setpoint calculations need not and do not contain provisions for treating multiple simultaneous release pathways. 3.2 Liquid Effluent Concentrations 3.2.1 One method of demonstrating compliance to the requirements of 10CFR20.1301 is to demonstrate that the annual average concentrations of radioactive material released in gaseous and liquid effluents do not exceed the values specified in 10CFR20 Appendix B, Table 2, Column 2. (See 10CFR 20.1302(b)(2).) However, as noted in Section 5.6.1, this mode of 10CFR20.1301 compliance has not been elected. As a means of assuring that annual concentration limits will not be exceeded, and as a matter of policy assuring that doses by the liquid pathway will be ALARA; RECS provides the following restriction:

                             "The concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS shall be limited to ten times the concentration values in Appendix B, Table 2, Column 2 to 10CFR20.1001-20.2402."

This also meets the requirement of Station Technical Specifications and RECS. Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 173 of 307 January 2013 3.2.2 According to the footnotes to 10CFR20 Appendix B, Table 2, Column 2, if a radionuclide mix of known composition is released, the concentrations must be such that E, -1 ___1 (3-1) 1 1lOECLi)- where the summation is over radionuclide i. C1 Radioactivity Concentration in Liquid Effluents to the UNRESTRICTED AREA [p.Ci/ml] Concentration of radionuclide i in liquid released to the UNRESTRICTED AREA. ECLI Effluent Concentration Limit in Liquid Effluents Released to the UNRESTRICTED AREA [pCi/ml] The allowable annual average concentration of radionuclide '"T in liquid effluents released to the UNRESTRICTED AREA. This concentration is specified in 10CFR20 Appendix B, Table 2, Column 2. Concentrations for noble gases are different and are specified in the stations' Technical Specifications/RECS. 10 Multiplier to meet the requirements of Technical Specifications. If either the identity or concentration of any radionuclide in the mixture is not known, special rules apply. These are given in the footnotes in 10CFR20 Appendix B, Table 2, Column 2. Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 174 of 307 January 2013 3.2.3 When radioactivity is released to the UNRESTRICTED AREA with liquid discharge from a tank (e.g., a radwaste discharge tank), the concentration of a radionuclide in the effluent is calculated as follows:

                                       = C tWaste Flow Dilution Flow C1      Concentration in Liquid effluent to the UNRESTRICTED AREA.

[1iCi/ml] Concentration of radionuclide "i" in liquid released to the UNRESTRICTED AREA. Cit Concentration in the Discharge Tank [ptCi/ml] Measured concentration of radionuclide i in the discharge tank. Waste Flow Liquid Radioactive Waste Flow [gpm] The average flow during disposal from the discharge structure release point into the receiving water body. Dilution Flow Dilution Water Flow During Period of Interest [gpm] The RECS and Technical Specifications require a specified sampling and analysis program to assure that liquid radioactivity concentrations at the point of release are maintained within the required limits. To comply with this provision, samples are analyzed in accordance with the radioactive liquid waste (or effluent) sampling and analysis program in ODCM Part I, Section 12.3.1. Radioactivity concentrations in tank effluents are determined in accordance with Equation 3-2. Comparison with the Effluent Concentration Limit is made using Equation 3-1. 3.3 Liquid Effluent Dose Calculation Requirements 3.3.1 RECS require determination of cumulative and PROJECTED DOSE contributions from liquid effluents for the current calendar quarter and the current calendar year at least once per 31 days. (See Section 12.3.2 of Part I, RECS.) For a release attributable to a processing or effluent system shared by more than one reactor unit, the dose due to an individual unit is obtained by proportioning the effluents among the units sharing the system. Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 175 of 307 January 2013 3.3.2 Operability and Use of the Liquid Radwaste Treatment System The design objectives of 10CFR50, Appendix I and RECS/Technical Specifications require that the liquid radwaste treatment system be operable and that appropriate portions be used to reduce releases of radioactivity when PROJECTED DOSES due to the liquid effluent from each reactor unit to RESTRICTED AREA boundaries exceed either of the following (see Section 12.3.3 of Part I, RECS);

• 0.12 mrem to the total body in a 31-day period.
• 0.4 mrem to any organ in a 31-day period.

3.4 Dose Methodology 3.4.1 Liquid Effluent Dose Method: General The dose from radioactive materials in liquid effluents considers the contributions for consumption of fish and potable water. All of these pathways are considered in the dose assessment unless demonstrated not to be present. While the adult is normally considered the maximum individual, the methodology provides for dose to be calculated for all four age groups. The dose to each organ (and to the total body) is calculated by the following expression: DLtq = F At AaipjC (3-3) aj =(F-3t p i The summation is over exposure pathways "p" and radionuclides "i". Duq Organ and Total Body Dose Due to Liquid Effluents [mrem] Dose to organ "j" (including total body) of age group "a" due to radioactivity in liquid effluents. F Near Field Average Dilution Factor [dimensionless] Dilution in the near field averaged over the period of interest. Defined as: F= Waste Flow (3-4) Dilution Flow x Z Z Discharge Structure Mixing Factor [dimensionless] Site-specific factor to account for the mixing effect of the discharge structure. The factor addresses the dilution that occurs in the near Quad Cities ODCM Part II

CY-QC-170-301 Revision 11 Page 176 of 307 January 2013 field between the discharge structure and the body of water containing the fish in the liquid ingestion pathway. At Duration of Release [hrs] Ci Average Radionuclide Concentration [piCi/ml] Average concentration of radionuclide i, in the undiluted liquid effluent during time period At. Aaipj Site-Specific Liquid Dose Factor [(mrem/hr)/([LCi/ml)] Site-specific dose factor for age group "a", nuclide "i", liquid pathway "p" and organ "j". The pathways included are potable water and fish ingestion. Aaipj is defined for these pathways in the following sections. All other terms have been previously defined. 3.4.2 Potable Water Pathway The site-specific potable water pathway dose factor is calculated by the following expression: A ai(PW)j = ko{_--I} DFLij (3-5) Where: Aai(PW)j Site-Specific Dose Factor for Potable Water Pathway [(mrem/hr)/( [tCi/ml)] Site-specific potable water ingestion dose factor for age group "a", nuclide "i" and organ "j". k, Conversion Constant (1.14E05) [(yr-pCi-ml)/(hr-jiCi-l)] Units constant to convert years to hours, pCi to ptCi and liters to ml. Uaw Potable Water Consumption Rate [l/yr] Potable water consumption rate for age group "a". Taken from Table E-5 of Regulatory Guide 1.109. Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 177 of 307 January 2013 Dw Potable Water Dilution Factor [dimensionless] Dilution factor from the near field area within one-quarter mile of the release point to the potable water intake. DFLaij Ingestion Dose Conversion Factor [mrem/pCi] Ingestion dose conversion factor for age group "a", nuclide "i" and organ "j". Converts pCi ingested to mrem. Taken from Tables E-11 though E-14 of Regulatory Guide 1.109. The value for H-3 and Sr-90 are taken from NUREG 4013 (Reference 107). 3.4.3 Fish Ingestion Pathway The site-specific fish ingestion pathway dose factor is calculated by the following expression: Aai(Fish)j - koUFBFiDFLaij (3-6) Where: Aai(Fish)j Site-Specific Dose Factor for Potable Water Pathway [(mrem/hr)/(V.tCi/mI)] Site-specific fish ingestion dose factor for age group "a", nuclide "i" and organ "j". UaF Fish Consumption Rate [kg/yr] Fish consumption rate for age group "a". Taken from Table E-5 of Regulatory Guide 1.109. BF 1 Bioaccumulation Factor [(pCi/kg)/(pCi/l)] Bioaccumulation factor for nuclide "i" in fresh water fish. Taken from Table 3-1. All other terms have been previously defined. 3.4.4 Offsite Doses Offsite doses due to projected releases of radioactive materials in liquid effluents are calculated using Equation 3-3. Projected radionuclide release concentrations are used in place of measured concentrations, Ci. Quad Cities ODCM Part II

CY-QC-170-301 Revision 11 Page 178 of 307 January 2013 3.4.5 Drinking Water Quad Cities has requirements for calculation of drinking water dose that are related to 40CFR141, the Environmental Protection Agency National Primary Drinking Water Regulations. These are discussed in Section 1.2.1. Table 3-2 provides specific information on the closest down stream COMMUNITY WATER SYSTEM. Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 179 of 307 January 2013 Table 3-1 (Page 1 of 3) Bioaccumulation Factors (BFi) to be Used in the Absence of Site-Specific Data Element BFi for Freshwater Fish Reference (pCi/kg per pCi/L) H 9.OE-01 6 Be 2.8E+01 Footnote 2 C 4.6E+03 6 F 2.2E+02 Footnote 16 Na 1.OE+02 6 Mg 2.8E+01 Footnote 2 Al 2.2E+03 Footnote 13 P 1.OE+05 6 Cl 2.2E+02 Footnote 16 Ar NA NA K 1.OE+03 Footnote 1 Ca 2.8E+01 Footnote 2 Sc 2.5E+01 Footnote 3 Ti 3.3E+00 Footnote 4 V 3.OE+04 Footnote 5 Cr 2.OE+02 6 Mn 4.OE+02 6 Fe 1.OE+02 6 Co 5.OE+01 6 Ni 1.OE+02 6 Cu 5.OE+01 6 Zn 2.OE+03 6 Ga 2.2E+03 Footnote 13 Ge 2.4E+03 Footnote 12 As 3.3E+04 Footnote 14 Se 4.OE+02 Footnote 15 Br 4.2E+02 6 Kr NA NA Rb 2.OE+03 6 Sr 3.OE+01 6 Y 2.5E+01 6 Zr 3.3E+00 6 Nb 3.OE+04 6 Mo 1.OE+01 6 Tc 1.5E+01 6 Ru 1.OE+01 6 Rh 1.OE+01 6 Pd 1.OE+02 Footnote 9 Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 180 of 307 January 2013 Table 3-1 (Page 2 of 3) Bioaccumulation Factors (BF1 ) to be Used in the Absence of Site-Specific Data Cd 2.OE+03 Footnote 11 In 2.2E+03 Footnote 13 Sn 2.4E+03 Footnote 12 Sb 1.OE+00 98 Ag 2.3E+00 56 Te 4.OE+02 6 I 1.5E+01 6 Xe NA NA Cs 2.OE+03 6 Ba 4.OE+00 6 La 2.5E+01 6 Ce 1.OE+00 6 Pr 2.5E+01 6 Nd 2.5E+01 6 Pm 3.OE+01 98 Sm 3.OE+01 Footnote 3 Eu 1.OE+02 Footnote 3 Gd 2.6E+01 Footnote 3 Dy 2.2E+03 Footnote 3 Er 3.3E+04 Footnote 3 Tm 4.OE+02 Footnote 3 Yb 2.2E+02 Footnote 3 Lu 2.5E+01 Footnote 3 Hf 3.3E+00 Footnote 4 Ta 3.OE+04 Footnote 5 W 1.2E+03 6 Re 2.1E+02 Footnote 6 Os 5.5E+01 Footnote 7 Ir 3.OE+01 Footnote 8 Pt 1.OE+02 Footnote 9 Au 2.6E+01 Footnote 10 Hg 2.OE+03 Footnote 11 TI 2.2E+03 Footnote 13 Pb 3.OE+02 98 Bi 2.OE+01 98 Ra 5.OE+01 98 Th 3.OE+01 98 U 1.OE+01 98 Np 1.OE+01 6 Am 3.OE+01 98 Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 181 of 307 January 2013 Table 3-1 (Page 3 of 3) Bioaccumulation Factors (BFi) to be Used in the Absence of Site-Specific Data Footnotes: NA = It is assumed that noble gases are not accumulated. In Reference 6, see Table A-1. A number of bioaccumulation factors could not be found in literature. In this case, the periodic table was used in conjunction with published element values. This method was used for periodic table columns except where there were no values for column 3A so the average of columns 2B and 4A was assigned.

1. Value is the average of Reference 6 values in literature for H, Na, Rb and Cs.

2. Value is the average of Ref. 6 values in literature for Sr, Ba and Ref. 98 values for Ra.

3. Value is the same as the Reference 6 value used for Y.

4. Value is the same as the Reference 6 value used for Zr.

5. Value is the same as the Reference 6 value used for Nb.

6. Value is the average of Reference 6 values in literature for Mn and Tc.

7. Value is the average of Reference 6 values in literature for Fe and Ru.

8. Value is the average of Reference 6 values in literature for Co and Rh.

9. Value is the same as the Reference 6 value used for Ni.

10. Value is the average of Reference 6 values in literature for Cu and Reference 56 value for Ag.

11. Value used is the same as the Reference 6 value used for Zn.

12. Value is the average of Reference 6 value in literature for C and Reference 98 value for Pb.

13. Value is the average of columns 2B and 4A, where column 2B is the "Reference 6 value for Zn" and column 4A is the average of "Reference 6 value for C and Reference 98 value for Pb".

14. Value is the average of Ref. 6 value found in literature for P and the Ref. 98 values for Bi and Sb.

15. Value is the same as the Reference 6 value used for Te.

16. Value is the average of Reference 6 values found in literature for Br and I.

Quad Cities ODCM Part II

CY-QC-170-301 Revision 11 Page 182 of 307 January 2013 Table 3-2 Nearest Downstream COMMUNITY WATER SYSTEM Exelon Nuclear Location and distance Other Exelon Nuclear Station facilities upstream of of closest Stations upstream of Quad Cities COMMUNITY water supply ___ ______ ____ ___ ___ ___ WATER SYSTEM (a) _ _ _ _ _ _ _ _ Quad Cities None East 16 Moline river miles I None (a) ODCM Bases and Table 0-2 and 0-6 of Reference 101 provide the bases of the location and distance data. Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 183 of 307 January 2013 Table 3-3 Aquatic Environmental Dose Parameters General Informationa Existence of irrigation not mentioned in Quad Cities Final Safety Analysis Report (FSAR), UFSAR, or Plant Design Analysis Recreation includes one or more of the following: boating, water skiing, swimming, and sport fishing. The station liquid discharge flows into the Mississippi River. Mississippi River Lock and Dam Number 14 is located between the station discharge and the E. Moline intake (see Figure 12 of the Quad Cities Unit 1 Plant Design Analysis, Volume II, and Figure 2.4.1 of the Quad Cities Safety Analysis Report.) Water and Fish Ingestion Parameters Parameterb Value Dw 10 Z 16 Limits on Radioactivity in Unprotected Outdoor Tanks c Outside Storage Tank < 10 Ci per Tank d Per Technical Specification 5.5.8.b a Quad Cities Updated Final Safety Analysis Report (USFAR) updated through Amendment 5. (9-3-87) Section 1.5.2 and Quad Cities Plant Design Analysis, Section 4.4 b The parameters are defined in ODCM Part II Section 3.1 c Refer to ODCM Part II Section 3.1 d Tritium and dissolved or entrained noble gasses are excluded from this limit. Quad Cities ODCM Part II

CY--QC-1 70-301 Revision 11 Page 184 of 307 January 2013 Table 3-4 (Page 1 of 8) Site Specific Potable Water Dose Factors Adult Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI H-3 O.OOE+00 4.98E-01 4.98E-01 4.98E-01 4.98E-01 4.98E-01 4.98E-01 Na-24 1.41E+01 1.41E+01 1.41E+01 1.41E+01 1.41E+01 1.41E+01 1.41E+01 Cr-51 O.OOE+00 O.OOE+00 2.21 E-02 1.32E-02 4.88E-03 2.94E-02 5.57E+00 Mn-54 O.OOE+00 3.80E+01 7.26E+00 O.OOE+00 1.13E+01 O.OOE+00 1.17E+02 Mn-56 O.OOE+00 9.57E-01 1.70E-01 O.OOE+00 1.22E+00O.OOE+00 3.05E+01 Fe-55 2.29E+01 1.58E+01 3.69E+00 O.OOE+00 O.OOE+00 8.82E+00 9.07E+00 Fe-59 3.61 E+01 8.49E+01 3.25E+01 O.OOE+00 O.OOE+00 2.37E+01 2.83E+02 Co-58 O.OOE+00 6.20E+00 1.39E+01 O.OOE+00 O.OOE+00 O.OOE+00 1.26E+02 Co-60 O.OOE+00 1.78E+01 3.93E+01 O.OOE+00 O.OOE+00 O.OOE+00 3.35E+02 Ni-63 1.08E+03 7.50E+01 3.63E+01 O.OOE+00 O.OOE+00 O.OOE+00 1.56E+01 Ni-65 4.39E+00 5.71E-01 2.60E-01 O.OOE+00 O.OOE+00 O.OOE+00 1.45E+01 Cu-64 O.OOE+00 6.93E-01 3.25E-01 O.OOE+00 1.75E+00 O.OOE+00 5.91E+01 Zn-65 4.03E+01 1.28E+02 5.79E+01 O.OOE+00 8.57E+01 O.OOE+00 8.07E+01 Zn-69 8.57E-02 1.64E-01 1.14E-02 O.OOE+00 1.07E-01 O.OOE+00 2.46E-02 Br-83 O.OOE+00 O.OOE+00 3.35E-01 O.OOE+00 O.OOE+00 O.OOE+00 4.82E-01 Br-84 O.OOE+00 O.OOE+00 4.34E-01 O.OOE+00 O.OOE+00 O.OOE+00 3.40E-06 Br-85 O.OOE+00 O.OOE+00 1.78E-02 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Rb-86 O.OOE+00 1.76E+02 8.18E+01 O.OOE+00 O.OOE+00 O.OOE+00 3.46E+01 Rb-88 O.OOE+00 5.03E-01 2.67E-01 O.OOE+00 O.OOE+00 O.OOE+00 6.96E-12 Rb-89 O.OOE+00 3.34E-01 2.35E-01 O.OOE+00 O.OOE+00 O.OOE+00 1.94E-14 Sr-89 2.56E+03 O.OOE+00 7.36E+01 O.OOE+00 O.OOE+00 O.OOE+00 4.11E+02 Sr-90 7.25E+04 O.OOE+00 1.46E+03 O.OOE+00 O.OOE+00 O.OOE+00 1.82E+03 Sr-91 4.72E+01 O.OOE+00 1.91E+00 O.OOE+00 O.OOE+00 O.OOE+00 2.25E+02 Sr-92 1.79E+01 O.OOE+00 7.74E-01 O.OOE+00 O.OOE+O0 O.OOE+00 3.55E+02 Y-90 8.01E-02 O.OOE+00 2.15E-03 O.OOE+00 O.OOE+00 O.OOE+00 8.49E+02 Y-91M 7.56E-04 O.OOE+00 2.93E-05 O.OOE+00 O.OOE+00 O.OOE+00 2.22E-03 Y-91 1.17E+00 O.OOE+00 3.14E-02 O.OOE+00 O.OOE+00 O.OOE+00 6.46E+02 Y-92 7.03E-03 O.OOE+00 2.06E-04 O.OOE+00 O.OOE+00 O.OOE+00 1.23E+02 Y-93 2.23E-02 O.OOE+00 6.16E-04 O.OOE+00 O.OOE+00 O.OOE+00 7.07E+02 Zr-95 2.53E-01 8.11E-02 5.49E-02 O.OOE+00 1.27E-01 O.OOE+00 2.57E+02 Zr-97 1.40E-02 2.82E-03 1.29E-03 O.OOE+00 4.26E-03 O.OOE+00 8.74E+02 Nb-95 5.18E-02 2.88E-02 1.55E-02 O.OOE+00 2.85E-02 O.OOE+00 1.75E+02 Mo-99 O.OOE+00 3.59E+01 6.82E+00 O.OOE+00 8.12E+01 O.OOE+00 8.31E+01 Tc- 99M 2.06E-03 5.81 E-03 7.40E-02 O.OOE+00 8.82E-02 2.85E-03 3.44E+00 Tc-101 2.11E-03 3.05E-03 2.99E-02 O.OOE+00 5.48E-02 1.56E-03 9.15E-15 Ru-103 1.54E+00 O.OOE+00 6.63E-01 O.OOE+00 5.88E+00 O.OOE+00 1.80E+02 Ru-105 1.28E-01 O.OOE+00 5.06E-02 O.OOE+00 1.66E+00 O.OOE+00 7.84E+01 Ru-106 2.29E+01 O.OOE+00 2.90E+00 O.OOE+00 4.42E+01 O.OOE+00 1.48E+03 Ag-110M 1.33E+00 1.23E+00 7.32E-01 O.OOE+00 2.42E+00 O.OOE+00 5.03E+02 Te-125M 2.23E+01 8.08E+00 2.99E+00 6.71E+00 9.07E+01 O.OOE+00 8.90E+01 Quad Cities ODCM Part II

CY-QC-170-301 Revision 11 Page 185 of 307 January 2013 Table 3-4 (Page 2 of 8) Site Specific Potable Water Dose Factors Adult Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI Te-127M 5.63E+01 2.01E+01 6.87E+00 1.44E+01 2.29E+02 0.OOE+00 1.89E+02 Te-127 9.15E-01 3.29E-01 1.98E-01 6.78E-01 3.73E+00 0.OOE+00 7.22E+01 Te-129M 9.57E+01 3.57E+01 1.51E+01 3.29E+01 3.99E+02 0.OOE+00 4.82E+02 Te-129 2.61E-01 9.82E-02 6.37E-02 2.01E-01 1.10E+00 O.OOE+00 1.97E-01 Te-131M 1.44E+01 7.04E+O0 5.87E+00 1.12E+01 7.13E+01 0.OOE+00 6.99E+02 Te-131 1.64E-01 6.85E-02 5.18E-02 1.35E-01 7.18E-01 O.OOE+00 2.32E-02 Te-132 2.10E+01 1.36E+01 1.27E+01 1.50E+01 1.31EE+02 O.OOE+00 6.42E+02 1-130 6.29E+00 1.86E+01 7.32E+00 1.57E+03 2.90E+01 0.OOE+00 1.60E+01 1-131 3.46E+01 4.95E+01 2.84E+01 1.62E+04 8.49E+01 0.OOE+00 1.31E+01 1-132 1.69E+00 4.52E+00 1.58E+00 1.58E+02 7.20E+00 0.OOE+00 8.49E-01 1-133 1.18E+01 2.06E+01 6.27E+00 3.02E+03 3.59E+01 0.OOE+00 1.85E+01 1-134 8.82E-01 2.40E+00 8.57E-01 4.15E+01 3.81E+00 0.OOE+00 2.09E-03 1-135 3.69E+00 9.65E+00 3.56E+00 6.37E+02 1.55E+01 0.OOE+00 1.09E+01 Cs-134 5.18E+02 1.23E+03 1.01E+03 0.OOE+00 3.99E+02 1.32E+02 2.16E+01 Cs-136 5.42E+01 2.14E+02 1.54E+02 0.OOE+00 1.19E+02 1.63E+01 2.43E+01 Cs-137 6.63E+02 9.07E+02 5.94E+02 0.OOE+00 3.08E+02 1.02E+02 1.76E+01 Cs-1 38 4.59E-01 9.07E-01 4.49E-01 O.OOE+00 6.67E-01 6.58E-02 3.87E-06 Ba-139 8.07E-01 5.75E-04 2.36E-02 O.OOE+00 5.38E-04 3.26E-04 1.43E+00 Ba-140 1.69E+02 2.12E-01 1.11E+01 0.OOE+00 7.22E-02 1.22E-01 3.48E+02 Ba-141 3.92E-01 2.96E-04 1.32E-02 0.00E+00 2.75E-04 1.68E-04 1.85E-10 Ba-142 1.77E-01 1.82E-04 1.12E-02 0.OOE+00 1.54E-04 1.03E-04 2.50E-19 La-140 2.08E-02 1.05E-02 2.77E-03 0.OOE+00 0.OOE+00 0.OOE+00 7.70E+02 La-142 1.07E-03 4.84E-04 1.21E-04 0.OOE+00 0.OOE+00 0.OOE+00 3.54E+00 Ce-141 7.79E-02 5.27E-02 5.98E-03 O.00E+00 2.45E-02 0.OOE+00 2.01EE+02 Ce-143 1.37E-02 1.02E+01 1.12E-03 0.OOE+00 4.47E-03 0.OOE+00 3.79E+02 Ce-144 4.06E+00 1.70E+00 2.18E-01 0.OOE+00 1.01E+00 0.OOE+00 1.37E+03 Pr-143 7.66E-02 3.07E-02 3.79E-03 0.OOE+00 1.77E-02 0.OOE+00 3.35E+02 Pr-144 2.50E-04 1.04E-04 1.27E-05 0.OOE+00 5.87E-05 0.OOE+00 3.60E-11 Nd-147 5.23E-02 6.05E-02 3.62E-03 O.OOE+00 3.54E-02 O.OOE+00 2.90E+02 W-187 8.57E-01 7.17E-01 2.50E-01 0.OOE+00 0.OOE+0( 0.OOE+00 2.35E+02 Np-239 9.90E-03 9.74E-04 5.37E-04 0.OOE+00 3.04E-03 0.OOE+00 2.00E+02 Notes:

1) Units are mrem/hr per itCi/ml.

Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 186 of 307 January 2013 Table 3-4 (Page 3 of 8) Site Specific Potable Water Dose Factors Teen Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI H-3 O.OOE+00 3.51 E-01 3.51 E-01 3.51E-01 3.51E-01 3.51 E-01 3.51E-01 Na-24 1.34E+01 1.34E+01 1.34E+01 1.34E+01 1.34E+01 1.34E+01 1.34E+01 Cr-51 O.OOE+00 O.OOE+00 2.09E-02 1.16E-02 4.59E-03 2.99E-02 3.52E+00 Mn-54 O.OOE+00 3.43E+01 6.80E+00 O.OOE+00 1.02E+01 O.OOE+00 7.03E+01 Mn-56 O.OOE+00 9.19E-01 1.63E-01 O.OOE+00 1.16E+00 O.OOE+00 6.05E+01 Fe-55 2.20E+01 1.56E+01 3.63E+00 O.OOE+00 O.OOE+00 9.88E+00 6.74E+00 Fe-59 3.41E+01 7.97E+01 3.08E+01 O.OOE+00 O.OOE+00 2.51E+01 1.88E+02 Co-58 O.OOE+00 5.65E+00 1.30E+01 O.OOE+00 O.OOE+00 O.OOE+00 7.79E+01 Co-60 O.OOE+00 1.63E+01 3.68E+01 O.OOE+00 O.OOE+00 O.OOE+00 2.13E+02 Ni-63 1.03E+03 7.27E+01 3.49E+01 O.OOE+00 O.OOE+00 O.OOE+00 1.16E+01 Ni-65 4.35E+00 5.56E-01 2.53E-01 O.OOE+00 O.OOE+00 O.OOE+00 3.02E+01 Cu-64 O.OOE+00 6.69E-01 3.15E-01 O.OOE+00 1.69E+00 O.OOE+00 5.19E+01 Zn-65 3.35E+01 1.16E+02 5.42E+01 O.OOE+00 7.44E+01 O.OOE+00 4.92E+01 Zn-69 8.55E-02 1.63E-01 1.14E-02 O.OOE+00 1.06E-01 O.OOE+00 3.OOE-01 Br-83 O.OOE+00 O.OOE+00 3.34E-01 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Br-84 O.OOE+00 O.OOE+00 4.20E-01 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Br-85 O.OOE+00 O.OOE+00 1.77E-02 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Rb-86 O.OOE+00 1.73E+02 8.14E+01 O.OOE+00 0.OOE+00 O.OOE+00 2.56E+01 Rb-88 O.OOE+00 4.95E-01 2.64E-01 O.OOE+00 O.OOE+00 O.OOE+00 4.24E-08 Rb-89 O.OOE+00 3.20E-01 2.26E-01 O.OOE+00 O.OOE+00 O.OOE+00 4.90E-10 Sr-89 2.56E+03 O.OOE+00 7.33E+01 O.OOE+00 O.OOE+00 O.OOE+00 3.05E+02 Sr-90 5.93E+04 O.OOE+00 1.19E+03 O.OOE+00 O.OOE+00 O.OOE+00 1.35E+03 Sr-91 4.69E+01 O.OOE+00 1.87E+00 O.OOE+00 O.OOE+00 O.OOE+00 2.13E+02 Sr-92 1.77E+01 O.OOE+00 7.56E-01 O.OOE+00 O.OOE+00 O.OOE+00 4.52E+02 Y-90 7.97E-02 O.OOE+00 2.15E-03 O.OOE+00 O.OOE+00 O.OOE+00 6.57E+02 Y-91M 7.50E-04 O.OOE+00 2.87E-05 O.OOE+00 O.OOE+00 O.OOE+00 3.54E-02 Y-91 1.17E+00 O.OOE+00 3.13E-02 O.OOE+00 O.OOE+00 O.OOE+00 4.79E+02 Y-92 7.03E-03 O.OOE+00 2.03E-04 O.OOE+00 O.OOE+00 O.OOE+00 1.93E+02 Y-93 2.23E-02 O.OOE+00 6.10E-04 O.OOE+00 O.OOE+00 O.OOE+00 6.80E+02 Zr-95 2.40E-01 7.56E-02 5.20E-02 O.OOE+00 1.11E-01 O.OOE+00 1.74E+02 Zr-97 1.38E-02 2.73E-03 1.26E-03 O.OOE+00 4.13E-03 O.OOE+00 7.38E+02 Nb-95 4.78E-02 2.65E-02 1.46E-02 O.OOE+00 2.57E-02 O.OOE+00 1.13E+02 Mo-99 O.OOE+00 3.51E+01 6.69E+00 O.OOE+00 8.02E+01 O.OOE+00 6.28E+01 Tc- 99M 1.93E-03 5.38E-03 6.98E-02 O.OOE+00 8.02E-02 2.99E-03 3.53E+00 Tc-101 2.09E-03 2.98E-03 2.92E-02 O.OOE+00 5.38E-02 1.81E-03 5.09E-10 Ru-103 1.48E+00 O.OOE+00 6.34E-01 O.OOE+00 5.23E+00 O.OOE+00 1.24E+02 Ru-105 1.27E-01 O.OOE+00 4.92E-02 O.OOE+00 1.60E+00 O.OOE+00 1.02E+02 Ru-106 2.28E+01 O.OOE+00 2.87E+00 O.OOE+00 4.40E+01 O.OOE+00 1.09E+03 Ag-1IOM 1.19E+00 1.13E+00 6.86E-01 O.OOE+00 2.15E+00 O.00E+00 3.17E+02 Te-125M 2.23E+01 8.02E+00 2.98E+00 6.22E+00 O.OOE+00 O.OOE+00 6.57E+01 Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 187 of 307 January 2013 Table 3-4 (Page 4 of 8) Site Specific Potable Water Dose Factors Teen Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI Te-127M 5.62E+01 1.99E+01 6.69E+00 1.34E+01 2.28E+02 0.OOE+00 1.40E+02 Te-127 9.19E-01 3.26E-01 1.98E-01 6.34E-01 3.72E+00 0.OOE+00 7.09E+01 Te-129M 9.48E+01 3.52E+01 1.50E+01 3.06E+01 3.97E+02 0.OOE+00 3.56E+02 Te-129 2.60E-01 9.71E-02 6.34E-02 1.86E-01 1.09E+00 0.OOE+00 1.42E+00 Te-131M 1.42E+01 6.80E+00 5.67E+00 1.02E+01 7.09E+01 O.OOE+00 5.46E+02 Te-131 1.62E-01 6.69E-02 5.07E-02 1.25E-01 7.09E-01 0.OOE+00 1.33E-02 Te-132 2.03E+01 1.28E+01 1.21E+01 1.35E+01 1.23E+02 0.OOE+00 4.07E+02 1-130 5.99E+00 1.73E+01 6.92E+00 1.41E+03 2.67E+01 0.OOE+00 1.33E+01 1-131 3.40E+01 4.76E+01 2.56E+01 1.39E+04 8.20E+01 0.OOE+00 9.42E+00 1-132 1.62E+00 4.24E+00 1.52E+00 1.43E+02 6.69E+00 0.OOE+00 1.85E+00 1-133 1.17E+01 1.98E+01 6.05E+00 2.77E+03 3.48E+01 0.OOE+00 1.50E+01 1-134 8.49E-01 2.25E+00 8.08E-01 3.75E+01 3.55E+00 0.OOE+00 2.97E-02 1-135 3.55E+00 9.13E+00 3.38E+00 5.87E+02 1.44E+01 0.OOE+00 1.01E+01 Cs-134 4.87E+02 1.15E+03 5.31E+02 0.OOE+00 3.64E+02 1.39E+02 1.42E+01 Cs-136 4.99E+01 1.97E+02 1.32E+02 O.OOE+00 1.07E+02 1.69E+01 1.58E+01 Cs-137 6.51E+02 8.66E+02 3.02E+02 O.OOE+00 2.95E+02 1.15E+02 1.23E+01 Cs-138 4.51E-01 8.66E-01 4.33E-01 O.OOE+00 6.40E-01 7.44E-02 3.93E-04 Ba-1 39 8.08E-01 5.69E-04 2.35E-02 0.OOE+00 5.36E-04 3.92E-04 7.21 E+00 Ba-140 1.65E+02 2.02E-01 1.06E+01 0.OOE+00 6.86E-02 1.36E-01 2.55E+02 Ba-141 3.90E-01 2.91 E-04 1.30E-02 0.OOE+00 2.70E-04 1.99E-04 8.31 E-07 Ba-142 1.74E-01 1.74E-04 1.07E-02 O.OOE+00 1.47E-04 1.16E-04 5.34E-13 La-140 2.02E-02 9.94E-03 2.65E-03 0.OOE+00 0.OOE+00 0.OOE+00 5.71E+02 La-142 1.04E-03 4.62E-04 1.15E-04 0.OOE+0O 0.OOE+00 0.OOE+00 1.41E+01 Ce-141 7.73E-02 5.16E-02 5.93E-03 O.OOE+00 2.43E-02 0.OOE+00 1.48E+02 Ce-143 1.37E-02 9.94E+00 1.11E-03 0.OOE+00 4.46E-03 0.OOE+00 2.99E+02 Ce-144 4.05E+00 1.67E+00 2.17E-01 O.OOE+00 1.OOE+00 0.OOE+00 1.02E+03 Pr-143 7.62E-02 3.04E-02 3.79E-03 0.OOE+00 1.77E-02 0.OOE+00 2.51E+02 Pr-144 2.50E-04 1.02E-04 1.27E-05 0.OOE+00 5.87E-05 0.OOE+00 2.76E-07 Nd-147 5.45E-02 5.93E-02 3.55E-03 0.OOE+00 3.48E-02 0.OOE+00 2.14E+02 W-187 8.49E-01 6.92E-01 2.42E-01 0.OOE+00 0.OOE+00 O.OOE+00 1.87E+02 Np-239 1.02E-02 9.65E-04 5.36E-04 0.10E+0 3.03E-03 O.OOE+00 1.55E+02 Notes:

1) Units are mrem/hr per ýtCi/ml.

Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 188 of 307 January 2013 Table 3-4 (Page 5 of 8) Site Specific Potable Water Dose Factors Child Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI H-3 O.OOE+00 6.74E-01 6.74E-01 6.74E-01 6.74E-01 6.74E-01 6.74E-01 Na-24 3.37E+01 3.37E+01 3.37E+01 3.37E+01 3.37E+01 3.37E+01 3.37E+01 Cr-51 O.OOE+00 O.OOE+00 5.17E-02 2.87E-02 7.85E-03 5.24E-02 2.74E+00 Mn-54 O.OOE+00 6.22E+01 1.66E+01 O.OOE+00 1.74E+01 O.OOE+00 5.22E+01 Mn-56 O.OOE+00 1.94E+00 4.38E-01 O.OOE+00 2.35E+00 O.OOE+00 2.81E+02 Fe-55 6.69E+01 3.55E+01 1.10E+01 O.OOE+00 0.OOE+00 2.01E+01 6.57E+00 Fe-59 9.59E+01 1.55E+02 7.73E+01 O.OOE+00 O.OOE+00 4.50E+01 1.62E+02 Co-58 O.00E+00 1.05E+01 3.20E+01 O.OOE+00 O.OOE+00 O.OOE+00 6.10E+01 Co-60 O.OOE+00 3.08E+01 9.07E+01 O.O0E+O0 O.00E+00 O.OOE+00 1.70E+02 Ni-63 3.13E+03 1.67E+02 1.06E+02 O.OOE+00 O.OOE+00 O.OOE+00 1.13E+01 Ni-65 1.29E+01 1.22E+00 7.09E-01 O.OOE+00 O.OOE+00 O.OOE+00 1.49E+02 Cu-64 O.OOE+00 1.42E+00 8.60E-01 O.OOE+00 3.44E+00 O.OOE+00 6.69E+01 Zn-65 7.97E+01 2.12E+02 1.32E+02 O.OOE+00 1.34E+02 O.OOE+00 3.73E+01 Zn-69 2.55E-01 3.68E-01 3.40E-02 O.OOE+00 2.23E-01 O.OOE+00 2.32E+01 Br-83 O.OOE+00 O.OOE+00 9.94E-01 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Br-84 O.OOE+00 O.OOE+00 1.15E+00 O.00E+O0 O.OOE+00 O.OOE+00 O.OOE+00 Br-85 O.OOE+00 O.OOE+00 5.30E-02 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Rb-86 O.OOE+00 3.90E+02 2.40E+02 O.OOE+OO O.OOE+00 O.OOE+00 2.51E+01 Rb-88 O.OOE+00 1.10E+00 7.67E-01 O.OOE+00 O.OOE+00 O.OOE+00 5.42E-02 Rb-89 O.OOE+00 6.80E-01 6.05E-01 O.OOE+00 O.OOE+00 O.OOE+00 5.93E-03 Sr-89 7.67E+03 O.OOE+00 2.19E+02 O.OOE+00 O.OOE+00 O.OOE+00 2.97E+02 Sr-90 1.49E+05 O.OOE+00 2.99E+03 O.OOE+00 O.OOE+00 O.OOE+00 1.33E+03 Sr-91 1.40E+02 O.OOE+00 5.27E+00 O.OOE+00 O.OOE+00 O.OOE+00 3.08E+02 Sr-92 5.25E+01 0.OOE+00 2.1OE+00 O.OOE+00 O.00E+00 O.OOE+00 9.94E+02 Y-90 2.39E-01 O.OOE+00 6.40E-03 O.OOE+00 O.OOE+00 O.OOE+00 6.80E+02 Y-91M 2.22E-03 O.OOE+00 8.08E-05 O.OOE+00 O.OOE+00 O.OOE+00 4.35E+00 Y-91 3.50E+00 O.OOE+00 9.36E-02 O.OOE+00 O.OOE+00 O.OOE+00 4.66E+02 Y-92 2.09E-02 O.OOE+00 5.99E-04 O.OOE+OO O.OOE+00 O.OE+00 6.05E+02 Y-93 6.63E-02 O.OOE+00 1.82E-03 O.OOE+00 O.OOE+00 O.OOE+00 9.88EE+02 Zr-95 6.74E-01 1.48E-01 1.32E-01 O.OOE+00 2.12E-01 O.OOE+00 1.55E+02 Zr-97 4.06E-02 5.87E-03 3.47E-03 O.OOE+00 8.43E-03 O.00E+00 8.90E+02 Nb-95 1.31 E-01 5.09E-02 3.64E-02 O.OOE+00 4.78E-02 O.OOE+00 9.42E+01 Mo-99 O.OOE+00 7.73E+01 1.91E+01 O.OOE+00 1.65E+02 O.OOE+00 6.40E+01 Tc- 99M 5.37E-03 1.05E-02 1.74E-01 O.OOE+00 1.53E-01 5.34E-03 5.99E+00 Tc-101 6.22E-03 6.51E-03 8.26E-02 O.OOE+00 1.11E-01 3.44E-03 2.07E-02 Ru-103 4.25E+00 O.OOE+00 1.63E+00 O.OOE+00 1.07E+01 O.OOE+00 1.1OE+02 Ru-105 3.75E-01 O.OOE+00 1.36E-01 O.OOE+00 3.30E+00 O.OOE+00 2.45E+02 Ru-106 6.80E+01 O.OOE+00 8.49E+00 O.OOE+00 9.19E+01 O.OOE+00 1.06E+03 Ag-110M 3.13E+00 2.12E+00 1.69E+00 O.OOE+O0 3.94E+00 O.OOE+00 2.52E+02 Te-125M 6.63E+01 1.80E+01 8.84E+00 1.86E+01 O.OOE+00 O.OOE+00 6.40E+01 Quad Cities ODCM Part II

CY-QC-170-301 Revision 11 Page 189 of 307 January 2013 Table 3-4 (Page 6 of 8) Site Specific Potable Water Dose Factors Child A e Group

        'Nuclide    Bone        Liver    T Body    Thyroid    Kidney      Lung      GI-LLI Te-127M     1.68E+02 4.52E+01      1.99E+01  4.02E+01   4.79E+02  O.OOE+00 1.36E+02 Te-127      2.74E+00 7.38E-01       5.87E-01 1.90E+00   7.79E+00  0.OOE+00 1.07E+02 Te-129M     2.83E+02 7.91E+01      4.40E+01  9.13E+01   8.31E+02  0.OOE+00 3.45E+02 Te-129       7.79E-01    2.17E-01   1.85E-01  5.56E-01  2.28E+00  0.OOE+00 4.85E+01 Te-131M     4.19E+01 1.45E+01      1.54E+01  2.98E+01   1.40E+02  0.OOE+00 5.87E+02 Te-131       4.83E-01    1.47E-01   1.44E-01  3.69E-01  1.46E+00  0.OOE+00 2.53E+00 Te-132      5.87E+01 2.60E+01      3.14E+01  3.78E+01   2.41E+02  0.OOE+00 2.62E+02 1-130       1.70E+01 3.43E+01      1.77E+01  3.78E+03   5.13E+01  0.OOE+00 1.60E+01 1-131       1.OOE+02 1.01E+02      5.72E+01  3.33E+04   1.65E+02  0.OOE+00 8.95E+00 1-132       4.65E+00 8.55E+00      3.93E+00  3.97E+02   1.31E+01  0.OOE+00 1.01E+01 1-133       3.44E+01 4.26E+01      1.61E+01  7.91EE+03  7.09E+01  0.OOE+00 1.72E+01 1-134       2.44E+00 4.52E+00      2.08E+00  1.04E+02   6.92E+00  O.00E+00 3.OOE+00 1-135       1.02E+01 1.83E+01      8.66E+00  1.62E+03   2.81E+01  0.OOE+00 1.40E+01 Cs-134      1.36E+03 2.23E+03      4.71E+02  O.OOE+00   6.92E+02  2.48E+02 1.20E+01 Cs-136      1.37E+02 3.76E+02      2.43E+02  0.OOE+00   2.OOE+02  2.98E+01 1.32E+01 Cs-137      1.90E+03 1.82E+03      2.69E+02  O.OOE+00   5.93E+02  2.13E+02 1.14E+01 Cs-138       1.33E+00 1.84E+00     1.17E+00  0.OOE+00   1.30E+00   1.40E-01   8.49E-01 Ba-139      2.41E+00 1.28E-03       6.98E-02 0.OOE+00    1.12E-03  7.56E-04 1.39E+02 Ba-140      4.83E+02 4.23E-01      2.82E+01  O.OOE+00    1.38E-01  2.52E-01 2.45E+02 Ba-141       1.16E+00 6.51E-04      3.78E-02 O.OOE+00    5.63E-04  3.83E-03 6.63E-01 Ba-142      5.08E-01    3.66E-04   2.84E-02 0.OOE+00    2.96E-04  2.15E-04 6.63E-03 La-140      5.87E-02 2.05E-02      6.92E-03 0.OOE+00   0.OOE+00  0.OOE+00 5.72E+02 La-142      3.05E-03 9.71 E-04     3.04E-04 0.OOE+00   0.OOE+00  O.OOE+00 1.92E+02 Ce-141       2.31E-01    1.15E-01   1.71E-02 0.OOE+00    5.05E-02 0.OOE+00 1.44E+02 Ce-143       4.06E-02 2.20E+01      3.19E-03 O.OOE+00    9.24E-03 O.OOE+00 3.23E+02 Ce-144       1.21E+01 3.79E+00      6.45E-01 O.OOE+00   2.1OE+00  0.OOE+00 9.88E+02 Pr-143      2.28E-01    6.86E-02   1.13E-02 O.OOE+00    3.72E-02 0.OOE+00 2.47E+02 Pr-144      7.50E-04 2.32E-04      3.77E-05 0.OOE+00    1.23E-04 0.OOE+00 4.99E-01 Nd-147      1.62E-01    1.31E-01   1.02E-02 0.OOE+00    7.21E-02 0.OOE+00 2.08E+02 W-187       2.49E+00 1.48E+00       6.63E-01 0.OOE+00   0.OOE+0O  0.OOE+00 2.081E+02 Np-239      3.05E-02 2.19E-03      1.54E-03 O.OOE+00    6.34E-03 0.OOE+00 1.62E+02 Notes:

1) Units are mrem/hr per [tCi/ml.

Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 190 of 307 January 2013 Table 3-4 (Page 7 of 8) Site Specific Potable Water Dose Factors Infant Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI H-3 O.OOE+00 6.62E-01 6.62E-01 6.62E-01 6.62E-01 6.62E-01 6.62E-01 Na-24 3.80E+01 3.80E+01 3.80E+01 3.80E+01 3.80E+01 3.80E+01 3.80E+01 Cr-51 O.OOE+00 O.OOE+00 5.30E-02 3.46E-02 7.56E-03 6.73E-02 1.55E+00 Mn-54 O.OOE+00 7.49E+01 1.70E+01 O.OOE+00 1.66E+01 O.OOE+00 2.75E+01 Mn-56 O.OOE+00 3.08E+00 5.30E-01 O.OOE+00 2.64E+00 O.OOE+00 2.80E+02 Fe-55 5.23E+01 3.38E+01 9.03E+00 O.00E+00 O.OOE+00 1.65E+01 4.29E+00 Fe-59 1.16E+02 2.02E+02 7.98E+01 O.OOE+00 O.OOE+00 5.98E+01 9.67E+01 Co-58 0.00E+00 1.35E+01 3.38E+01 O.OOE+00 O.OOE+00 O.OOE+00 3.37E+01 Co-60 O.OOE+00 4.06E+01 9.59E+01 O.OOE+00 O.OOE+00 O.OOE+00 9.67E+01 Ni-63 2.39E+03 1.47E+02 8.28E+01 O.OOE+00 O.OOE+00 O.OOE+00 7.34E+00 Ni-65 1.77E+01 2.OOE+00 9.10E-01 O.OOE+00 O.OOE+00 O.OOE+00 1.52E+02 Cu-64 O.OOE+00 2.29E+00 1.06E+00 O.OOE+00 3.87E+00 O.OOE+00 4.70E+01 Zn-65 6.92E+01 2.37E+02 1.09E+02 O.OOE+00 1.15E+02 O.OOE+00 2.01E+02 Zn-69 3.51E-01 6.32E-01 4.70E-02 O.OOE+00 2.63E-01 O.OOE+00 5.15E+01 Br-83 O.OOE+00 O.OOE+00 1.37E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Br-84 O.OOE+00 O.OOE+00 1.44E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Br-85 O.OOE+00 O.OOE+00 7.30E-02 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Rb-86 O.OOE+00 6.40E+02 3.16E+02 O.OOE+00 O.OOE+00 O.OOE+00 1.64E+01 Rb-88 O.00E+00 1.87E+00 1.03E+00 O.00E+00 O.OOE+00 O.OOE+00 1.82E+00 Rb-89 O.OOE+00 1.08E+00 7.41 E-01 O.OOE+00 O.OOE+00 O.OOE+00 3.66E-01 Sr-89 9.44E+03 O.OOE+00 2.71E+02 O.OOE+00 O.OOE+00 O.OOE+00 1.94E+02 Sr-90 1.06E+05 O.OOE+00 2.16E+03 O.OOE+00 O.OOE+00 O.OOE+00 8.69E+02 Sr-91 1.88E+02 O.00E+00 6.81 E+00 O.OOE+00 O.OOE+00 O.OOE+00 2.23E+02 Sr-92 7.22E+01 0.OOE+00 2.68E+00 O.OOE+00 O.OOE+00 O.OOE+00 7.79E+02 Y-90 3.27E-01 O.OOE+00 8.77E-03 O.OOE+00 O.OOE+00 O.OOE+00 4.51E+02 Y-91M 3.05E-03 O.OOE+00 1.04E-04 O.OOE+00 O.OOE+00 O.OOE+00 1.02E+01 Y-91 4.25E+00 O.OOE+00 1.13E-01 O.OOE+00 O.OOE+00 O.OOE+00 3.05E+02 Y-92 2.88E-02 O.OOE+00 8.09E-04 O.OOE+00 O.OOE+00 O.OOE+00 5.49E+02 Y-93 9.14E-02 O.OOE+00 2.49E-03 O.OOE+00 O.OOE+00 O.OOE+00 7.22E+02 Zr-95 7.75E-01 1.89E-01 1.34E-01 O.OOE+00 2.04E-01 O.OOE+00 9.41EE+01 Zr-97 5.57E-02 9.56E-03 4.36E-03 O.00E+00 9.63E-03 O.00E+00 6.09E+02 Nb-95 1.58E-01 6.51 E-02 3.76E-02 O.OOE+00 4.66E-02 O.OOE+00 5.49E+01 Mo-99 O.OOE+00 1.28E+02 2.49E+01 0.OOE+00 1.91E+02 O.OOE+00 4.21E+01 Tc- 99M 7.22E-03 1.49E-02 1.92E-01 O.OOE+00 1.60E-01 7.79E-03 4.33E+00 Tc-101 8.54E-03 1.08E-02 1.06E-01 O.OOE+00 1.28E-01 5.87E-03 1.83E+00 Ru-103 5.57E+00 O.OOE+00 1.86E+00 O.OOE+00 1.16E+01 O.OOE+00 6.77E+01 Ru-105 5.12E-01 O.OOE+00 1.72E-01 0.00E+00 3.76E+00 O.OOE+00 2.04E+02 Ru-106 9.07E+01 O.OOE+00 1.13E+01 O.OOE+00 1.07E+02 O.OOE+00 6.88E+02 Ag-110M 3.75E+00 2.73E+00 1.81E+00 O.OOE+00 3.91E+00 O.OOE+00 1.42E+02 Te-125M 8.77E+01 2.93E+01 1.19E+01 2.95E+01 O.OOE+00 O.OOE+00 4.18E+01 Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 191 of 307 January 2013 Table 3-4 (Page 8 of 8) Site Specific Potable Water Dose Factors Infant Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI Te-127M 2.20E+02 7.30E+01 2.66E+01 6.36E+01 5.42E+02 0.OOE+00 8.88E+01 Te-127 3.76E+00 1.26E+00 8.09E-01 3.06E+00 9.18E+00 0.OOE+00 7.90E+01 Te-129M 3.76E+02 1.29E+02 5.79E+01 1.44E+02 9.41E+02 0.OOE+00 2.25E+02 Te-129 1.07E+00 3.68E-01 2.49E-01 8.95E-01 2.66E+00 0.OOE+00 8.54E+01 Te-131M 5.72E+01 2.30E+01 1.90E+01 4.66E+01 1.58E+02 0.OOE+00 3.87E+02 Te-131 6.62E-01 2.45E-01 1.86E-01 5.91E-01 1.69E+0O 0.OOE+00 2.67E+01 Te-132 7.82E+01 3.87E+01 3.62E+01 5.72E+01 2.42E+02 0.OOE+00 1.43E+02 1-130 2.26E+01 4.97E+01 1.99E+01 5.57E+03 5.45E+01 O.OOE+00 1.06E+01 1-131 1.35E+02 1.59E+02 7.OOE+01 5.23E+04 1.86E+02 o.o0E+00 5.68E+00 1-132 6.24E+00 1.27E+01 4.51E+00 5.94E+02 1.41E+01 O.OOE+00 1.03E+01 1-133 4.70E+01 6.85E+01 2.01E+01 1.25E+04 8.05E+01 0.OOE+00 1.16E+01 1-134 3.27E+00 6.70E+00 2.38E+00 1.56E+02 7.49E+0O 0.OOE+00 6.92E+00 1-135 1.37E+01 2.72E+01 9.93E+00 2.44E+03 3.04E+01 0.OOE+00 9.86E+00 Cs-134 1.42E+03 2.64E+03 2.67E+02 0.OOE+00 6.81E+02 2.79E+02 7.19E+00 Cs-136 1.73E+02 5.08E+02 1.90E+02 0.OOE+00 2.02E+02 4.14E+01 7.71E+00 Cs-137 1.96E+03 2.30E+03 1.63E+02 0.OOE+00 6.17E+02 2.50E+02 7.19E+00 Cs-138 1.81E+00 2.94E+00 1.43E+00 0.OOE+00 1.47E+00 2.29E-01 4:70E+00 Ba-139 3.31E+00 2.20E-03 9.59E-02 0.OOE+00 1.32E-03 1.33E-03 2.10E+02 Ba-140 6.43E+02 6.43E-01 3.31E+01 0.OOE+00 1.53E-01 3.95E-01 1.58E+02 Ba-141 1.60E+00 1.09E-03 5.04E-02 0.OOE+00 6.58E-04 6.66E-04 1.95E+01 Ba-142 6.92E-01 5.76E-04 3.41E-02 0.OOE+00 3.31E-04 3.48E-04 2.86E+00 La-140 7.94E-02 3.13E-02 8.05E-03 O.OOE+00 O.OOE+00 0.OOE+00 3.68E+02 La-142 4.14E-03 1.52E-03 3.64E-04 0.OOE+00 0.OOE+00 0.OOE+00 2.58E+02 Ce-141 2.96E-01 1.81E-01 2.13E-02 0.OOE+00 5.57E-02 0.OOE+00 9.33E+01 Ce-143 5.57E-02 3.69E+01 4.21E-03 0.OOE+00 1.08E-02 0.OOE+00 2.16E+02 Ce-144 1.12E+01 4.59E+00 6.28E-01 0.OOE+00 1.85E+00 O.OOE+00 6.43E+02 Pr-143 3.06E-01 1.14E-01 1.52E-02 0.OOE+00 4.25E-02 0.OOE+00 1.61EE+02 Pr-144 1.03E-03 3.99E-04 5.19E-05 O.OOE+00 1.44E-04 0.OOE+00 1.85E+01 Nd-147 2.08E-01 2.14E-01 1.31E-02 O.OOE+00 8.24E-02 0.OOE+00 1.35E+02 W-187 3.40E+00 2.36E+00 8.16E-01 O.OOE+00 0.OOE+00 O.OOE+00 1.39E+02 Np-239 4.18E-02 3.74E-03 2.11E-03 0.OOE+00 7.45E-03 0.OOE+00 1.08E+02 Notes:

1) Units are mrem/hr per pCi/ml.

Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 192 of 307 January 2013 Table 3-5 (Page 1 of 6) Site Specific Fish Ingestion Dose Factors Adult Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI H-3 0.OOE+00 1.29E-01 1.29E-01 1.29E-01 1.29E-01 1.29E-01 1.29E-01 Na-24 4.07E+02 4.07E+02 4.07E+02 4.07E+02 4.07E+02 4.07E+02 4.07E+02 Cr-51 0.OOE+0O 0.OOE+00 1.27E+00 7.61 E-01 2.81E-01 1.69E+00 3.20E+02 Mn-54 0.OOE+00 4.38E+03 8.35E+02 0.OOE+00 1.30E+03 0.OOE+00 1.34E+04 Mn-56 0.OOE+00 1.10E+02 1.95E+01 0.OOE+00 1.40E+02 0.OOE+00 3.51E+03 Fe-55 6.58E+02 4.55E+02 1.06E+02 0.OOE+00 O.OOE+00 2.54E+02 2.61E+02 Fe-59 1.04E+03 2.44E+03 9.36E+02 0.OOE+0O 0.OOE+00 6.82E+02 8.14E+03 Co-58 0.OOE+00 8.92E+01 2.OOE+02 O.OOE+00 0.OOE+00 0.OOE+00 1.81 E+03 Co-60 O.OOE+00 2.56E+02 5.65E+02 O.OOE+00 O.OOE+00 0.OOE+00 4.81E+03 Ni-63 3.11E+04 2.16E+03 1.04E+03 O.OOE+00 0.OOE+00 0.OOE+00 4.50E+02 Ni-65 1.26E+02 1.64E+01 7.49E+00 0.OOE+00 0.OOE+00 0.OOE+00 4.17E+02 Cu-64 0.OOE+00 9.97E+00 4.68E+00 0.OOE+00 2.51E+01 0.OOE+00 8.50E+02 Zn-65 2.32E+04 7.37E+04 3.33E+04 0.OOE+00 4.93E+04 0.OOE+00 4.64E+04 Zn-69 4.93E+01 9.43E+01 6.56E+00 0.OOE+00 6.13E+01 0.OOE+00 1.42E+01 Br-83 O.OOE+00 O.OOE+00 4.04E+01 0.OOE+00 0.OOE+00 0.OOE+00 5.82E+01 Br-84 0.OOE+0O 0.OOE+00 5.24E+01 0.OOE+00 0.OOE+00 0.OOE+00 4.11E-04 Br-85 O.OOE+00 0.OOE+00 2.15E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Rb-86 0.OOE+00 1.011E+05 4.71 E+04 0.OOE+00 0.OOE+00 0.OOE+00 1.99E+04 Rb-88 0.OOE+00 2.90E+02 1.54E+02 O.OOE+00 O.OOE+00 0.OOE+00 4.OOE-09 Rb-89 0.OOE+00 1.92E+02 1.35E+02 0.OOE+00 0.OOE+00 O.OOE+00 1.12E-11 Sr-89 2.21E+04 0.OOE+00 6.35E+02 0.OOE+00 0.OOE+00 0.OOE+00 3.55E+03 Sr-90 6.26E+05 0.OOE+00 1.26E+04 0.OOE+00 0.OOE+0O 0.OOE+00 1.57E+04 Sr-91 4.07E+02 0.OOE+00 1.64E+01 0.OOE+00 0.O0E+00 0.OOE+00 1.94E+03 Sr-92 1.54E+02 0.OOE+00 6.68E+00 0.OOE+00 0.OOE+00 0.OOE+00 3.06E+03 Y-90 5.76E-01 0.OOE+00 1.54E-02 0.OOE+00 0.OOE+00 0.OOE+00 6.1OE+03 Y-91 M 5.44E-03 0.OOE+00 2.11 E-04 0.OOE+00 0.OOE+00 0.OOE+00 1.60E-02 Y-91 8.44E+00 0.OOE+00 2.26E-01 O.OOE+00 0.OOE+00 0.OOE+00 4.64E+03 Y-92 5.06E-02 0.OOE+00 1.48E-03 0.OOE+00 0.OOE+00 0.OOE+00 8.86E+02 Y-93 1.60E-01 O.OOE+00 4.43E-03 0.OOE+00 0.OOE+00 0.OOE+00 5.09E+03 Zr-95 2.40E-01 7.70E-02 5.21E-02 O.OOE+00 1.21E-01 0.OOE+00 2.44E+02 Zr-97 1.33E-02 2.68E-03 1.22E-03 0.OOE+00 4.04E-03 O.OOE+00 8.30E+02 Nb-95 4.47E+02 2.48E+02 1.34E+02 O.OOE+00 2.46E+02 0.OOE+00 1.51E+06 Mo-99 0.OOE+00 1.03E+02 1.96E+01 O.OOE+00 2.34E+02 0.OOE+00 2.39E+02 Tc- 99M 8.87E-03 2.51E-02 3.19E-01 0.OOE+00 3.81E-01 1.23E-02 1.48E+01 Tc-101 9.12E-03 1.31E-02 1.29E-01 0.OOE+00 2.37E-01 6.72E-03 3.95E-14 Ru-103 4.43E+00 O.OOE+00 1.91E+00 0.OOE+00 1.69E+O1 0.OOE+00 5.17E+02 Ru-105 3.69E-01 0.OOE+00 1.46E-01 0.OOE+00 4.76E+00 0.OOE+00 2.26E+02 Ru-106 6.58E+01 0.OOE+00 8.33E+00 0.OOE+00 1.27E+02 0.OOE+00 4.26E+03 Ag-i1M 8.81E-01 8.15E-01 4.84E-01 0.OOE+00 1.60E+00 0.0OE+00 3.33E+02 Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 193 of 307 January 2013 Table 3-5 (Page 2 of 6) Site Specific Fish Ingestion Dose Factors Adult Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI Te-125M 2.57E+03 9.30E+02 3.44E+02 7.72E+02 1.04E+04 0.OOE+00 1.02E+04 Te-127M 6.48E+03 2.32E+03 7.90E+02 1.66E+03 2.63E+04 0.OOE+00 2.17E+04 Te-127 1.05E+02 3.78E+01 2.28E+01 7.80E+01 4.29E+02 0.OOE+00 8.31E+03 Te-129M 1.10E+04 4.11EE+03 1.74E+03 3.78E+03 4.60E+04 0.OOE+00 5.54E+04 Te-129 3.01E+01 1.13E+01 7.33E+00 2.31E+01 1.26E+02 0.OOE+00 2.27E+01 Te-131M 1.66E+03 8.1OE+02 6.75E+02 1.28E+03 8.21E+03 0.OOE+00 8.04E+04 Te-131 1.89E+01 7.88E+00 5.96E+00 1.55E+01 8.26E+01 0.OOE+00 2.67E+00 Te-132 2.41E+03 1.56E+03 1.47E+03 1.72E+03 1.50E+04 0.OOE+00 7.38E+04 1-130 2.71E+01 8.01E+01 3.16E+01 6.79E+03 1.25E+02 0.OOE+00 6.89E+01 1-131 1.49E+02 2.14E+02 1.22E+02 7.OOE+04 3.66E+02 O.OOE+00 5.64E+01 1-132 7.29E+00 1.95E+01 6.82E+00 6.82E+02 3.11E+01 O.OOE+00 3.66E+00 1-133 5.1OE+01 8.87E+01 2.70E+01 1.30E+04 1.55E+02 0.OOE+00 7.97E+01 1-134 3.81E+00 1.03E+01 3.70E+00 1.79E+02 1.64E+01 0.OOE+00 9.01E-03 1-135 1.59E+01 4.17E+01 1.54E+01 2.75E+03 6.68E+01 O.OOE+00 4.70E+01 Cs-1 34 2.98E+05 7.09E+05 5.79E+05 0.OOE+00 2.29E+05 7.61E+04 1.24E+04 Cs-136 3.12E+04 1.23E+05 8.86E+04 0.OOE+00 6.85E+04 9.38E+03 1.40E+04 Cs-137 3.82E+05 5.22E+05 3.42E+05 O.OOE+00 1.77E+05 5.89E+04 1.01E+04 Cs-1 38 2.64E+02 5.22E+02 2.59E+02 0.OOE+00 3.84E+02 3.79E+01 2.23E-03 Ba-139 9.29E-01 6.62E-04 2.72E-02 0.OOE+00 6.19E-04 3.75E-04 1.65E+00 Ba-140 1.94E+02 2.44E-01 1.27E+01 0.OOE+00 8.30E-02 1.40E-01 4.OOE+02 Ba-141 4.51E-01 3.41E-04 1.52E-02 O.OOE+00 3.17E-04 1.93E-04 2.13E-10 Ba-142 2.04E-01 2.10E-04 1.28E-02 0.OOE+00 1.77E-04 1.19E-04 2.87E-19 La-140 1.50E-01 7.54E-02 1.99E-02 O.OOE+00 0.OOE+00 0.OOE+00 5.54E+03 La-142 7.66E-03 3.48E-03 8.68E-04 0.OOE+00 0.OOE+00 0.OOE+00 2.54E+01 Ce-141 2.24E-02 1.52E-02 1.72E-03 0.OOE+00 7.04E-03 0.OOE+00 5.79E+01 Ce-143 3.95E-03 2.92E+00 3.23E-04 0.OOE+00 1.29E-03 0.OOE+00 1.09E+02 Ce-144 1.17E+00 4.88E-01 6.27E-02 0.OOE+00 2.90E-01 0.OOE+00 3.95E+02 Pr-143 5.51E-01 2.21E-01 2.73E-02 O.OOE+00 1.27E-01 0.OOE+00 2.41E+03 Pr-144 1.80E-03 7.48E-04 9.16E-05 O.OOE+00 4.22E-04 0.OOE+00 2.59E-10 Nd-147 3.76E-01 4.35E-01 2.60E-02 0.OOE+00 2.54E-01 0.OOE+00 2.09E+03 W-187 2.96E+02 2.47E+02 8.65E+01 0.OOE+001 0.OOE+00 0.OOE+00 8.1OE+04 Np-239 2.85E-02 2.80E-03 1.54E-03 O.OOE+00 8.74E-03 0.OOE+00 5.75E+02 Notes:

1) Units are mrem/hr per ýtCi/ml.

Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 194 of 307 January 2013 Table 3-5 (Page 3 of 6) Site Specific Fish Ingestion Dose Factors Teen Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI H-3 O.OOE+00 9.92E-02 9.92E-02 9.92E-02 9.92E-02 9.92E-02 9.92E-02 Na-24 4.20E+02 4.20E+02 4.20E+02 4.20E+02 4.20E+02 4.20E+02 4.20E+02 Cr-51 O.OOE+00 O.OOE+00 1.31E+OO 7.30E-01 2.88E-01 1.88E+00 2.21E+02 Mn-54 O.OOE+00 4.30E+03 8.54E+02 O.OOE+00 1.28E+03 O.OOE+00 8.83E+03 Mn-56 O.OOE+00 1.15E+02 2.05E+01 O.OOE+00 1.46E+02 O.OOE+00 7.59E+03 Fe-55 6.89E+02 4.89E+02 1.14E+02 O.OOE+00 O.OOE+00 3.1OE+02 2.12E+02 Fe-59 1.07E+03 2.50E+03 9.65E+02 O.OOE+00 O.OOE+00 7.88E+02 5.91EE+03 Co-58 O.OOE+00 8.86E+01 2.04E+02 O.OOE+00 O.00E+00 O.OOE+00 1.22E+03 Co-60 O.OOE+00 2.56E+02 5.77E+02 O.OOE+00 O.OOE+00 O.OOE+00 3.34E+03 Ni-63 3.23E+04 2.28E+03 1.09E+03 O.OOE+00 O.OOE+00 O.OOE+00 3.63E+02 Ni-65 1.37E+02 1.75E+01 7.95E+00 O.OOE+00 O.OOE+00 O.OOE+00 9.47E+02 Cu-64 O.OOE+00 1.05E+01 4.93E+00 O.OOE+00 2.65E+01 O.OOE+00 8.14E+02 Zn-65 2.10E+04 7.30E+04 3.40E+04 O.OOE+00 4.67E+04 O.OOE+00 3.09E+04 Zn-69 5.36E+01 1.02E+02 7.15E+00 O.OOE+00 6.68E+01 O.OOE+00 1.88E+02 Br-83 O.OOE+00 O.OOE+00 4.40E+01 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Br-84 O.OOE+00 O.OOE+00 5.53E+01 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Br-85 O.OOE+00 O.OOE+00 2.34E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Rb-86 O.OOE+00 1.09E+05 5.11E+04 O.OOE+00 O.OOE+00 O.OOE+00 1.61E+04 Rb-88 O.OOE+00 3.11E+02 1.66E+02 O.OOE+00 O.OOE+00 O.OOE+00 2.66E-05 Rb-89 O.OOE+00 2.01E+02 1.42E+02 O.OOE+00 O.OOE+00 O.OOE+00 3.08E-07 Sr-89 2.41E+04 O.OOE+00 6.89E+02 O.OOE+00 O.OOE+O0 O.OOE+00 2.87E+03 Sr-90 5.58E+05 O.OOE+00 1.12E+04 O.OOE+00 O.OOE+00 O.OOE+00 1.27E+04 Sr-91 4.42E+02 O.OOE+00 1.76E+01 O.OOE+00 O.OOE+00 O.OOE+00 2.OOE+03 Sr-92 1.67E+02 O.OOE+00 7.11E+00 O.OOE+00 O.OOE+00 O.OOE+00 4.25E+03 Y-90 6.25E-01 O.OOE+00 1.68E-02 O.OOE+00 0.OOE+00 O.OOE+00 5.15E+03 Y-91M 5.88E-03 O.OOE+00 2.25E-04 O.OOE+0 0.00E+00 O.OOE+00 2.78E-01 Y-91 9.17E+00 O.OOE+00 2.46E-01 O.OOE+00 O.OOE+00 O.OOE+00 3.76E+03 Y-92 5.52E-02 O.OOE+00 1.60E-03 O.OOE+00 O.OOE+00 O.OOE+00 1.51EE+03 Y-93 1.75E-01 O.OOE+00 4.79E-03 O.OOE+00 O.OOE+00 O.OOE+00 5.34E+03 Zr-95 2.48E-01 7.82E-02 5.38E-02 O.OOE+00 1.15E-01 O.OOE+00 1.81E+02 Zr-97 1.43E-02 2.82E-03 1.30E-03 O.OOE+00 4.28E-03 O.OOE+00 7.64E+02 Nb-95 4.50E+02 2.50E+02 1.37E+02 O.OOE+00 2.42E+02 O.OOE+00 1.07E+06 Mo-99 O.OOE+00 1.10E+02 2.10E+01 O.OOE+00 2.52E+02 O.OOE+00 1.97E+02 Tc- 99M 9.08E-03 2.53E-02 3.28E-01 O.OOE+00 3.78E-01 1.41E-02 1.66E+01 Tc-101 9.85E-03 1.40E-02 1.38E-01 O.OOE+00 2.53E-01 8.54E-03 2.39E-09 Ru-103 4.65E+00 O.OOE+00 1.99E+00 O.OOE+00 1.64E+01 O.OOE+00 3.89E+02 Ru-105 3.98E-01 O.OOE+00 1.54E-01 O.OOE+00 5.02E+00 O.OOE+00 3.21E+02 Ru-106 7.15E+01 O.OOE+00 9.01E+00 O.OOE+00 1.38E+02 O.OOE+00 3.43E+03 Ag-11M 8.60E-01 8.14E-01 4.95E-01 O.OOE+00 1.55E+00 O.OOE+00 2.29E+02 Te-125M 2.79E+03 1.01E+03 3.74E+02 7.81E+02 O.OOE+00 O.OOE+00 8.24E+03 Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 195 of 307 January 2013 Table 3-5 (Page 4 of 6) Site Specific Fish Ingestion Dose Factors Teen Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI Te-127M 7.06E+03 2.50E+03 8.39E+02 1.68E+03 2.86E+04 0.OOE+00 1.76E+04 Te-127 1.15E+02 4.09E+01 2.48E+01 7.95E+01 4.67E+02 O.OOE+00 8.90E+03 Te-129M 1.19E+04 4.41E+03 1.88E+03 3.84E+03 4.98E+04 0.OOE+00 4.47E+04 Te-129 3.27E+01 1.22E+01 7.95E+00 2.33E+01 1.37E+02 0.OOE+00 1.79E+02 Te-131M 1.78E+03 8.54E+02 7.12E+02 1.28E+03 8.90E+03 0.OOE+00 6.85E+04 Te-131 2.04E+01 8.39E+00 6.36E+00 1.57E+01 8.90E+01 O.OOE+00 1.67E+00 Te-132 2.55E+03 1.61E+03 1.52E+03 1.70E+03 1.55E+04 0.OOE+00 5.11EE+04 1-130 2.82E+01 8.15E+01 3.26E+01 6.65E+03 1.26E+02 O.OOE+00 6.27E+01 1-131 1.60E+02 2.24E+02 1.20E+02 6.54E+04 3.86E+02 O.00E+00 4.43E+01 1-132 7.63E+00 2.OOE+01 7.17E+00 6.73E+02 3.15E+01 0.OOE+00 8.70E+00 1-133 5.50E+01 9.33E+01 2.85E+01 1.30E+04 1.64E+02 O.OOE+00 7.06E+01 1-134 3.99E+00 1.06E+01 3.80E+00 1.76E+02 1.67E+01 O.OOE+00 1.40E-01 1-135 1.67E+01 4.30E+01 1.59E+01 2.76E+03 6.79E+01 O.OOE+00 4.76E+01 Cs-134 3.05E+05 7.19E+05 3.33E+05 0.OOE+00 2.28E+05 8.72E+04 8.94E+03 Cs-136 3.13E+04 1.23E+05 8.28E+04 0.OOE+00 6.71E+04 1.06E+04 9.92E+03 Cs-137 4.09E+05 5.44E+05 1.89E+05 0.OOE+00 1.85E+05 7.19E+04 7.73E+03 Cs-1 38 2.83E+02 5.44E+02 2.72E+02 O.OOE+00 4.01E+02 4.67E+01 2.47E-01 Ba-139 1.01E+00 7.14E-04 2.95E-02 0.OOE+00 6.73E-04 4.92E-04 9.05E+00 Ba-140 2.07E+02 2.54E-01 1.34E+01 0.OOE+00 8.61E-02 1.71E-01 3.20E+02 Ba-141 4.90E-01 3.66E-04 1.63E-02 0.00E+00 3.39E-04 2.50E-04 1.04E-06 Ba-142 2.18E-01 2.18E-04 1.34E-02 0.OOE+00 1.85E-04 1.45E-04 6.70E-13 La-140 1.59E-01 7.80E-02 2.07E-02 0.OOE+00 O.OOE+00 0.OOE+00 4.48E+03 La-142 8.16E-03 3.63E-03 9.03E-04 0.OOE+00 0.OOE+00 0.OOE+00 1.10E+02 Ce-141 2.43E-02 1.62E-02 1.86E-03 O.OOE+00 7.62E-03 0.OOE+00 4.63E+01 Ce-143 4.29E-03 3.12E+00 3.48E-04 O.OOE+00 1.40E-03 0.OOE+00 9.38E+01 Ce-144 1.27E+00 5.25E-01 6.82E-02 0.OOE+00 3.14E-01 0.OOE+00 3.19E+02 Pr-143 5.97E-01 2.38E-01 2.97E-02 0.OOE+00 1.39E-01 0.OOE+00 1.97E+03 Pr-144 1.96E-03 8.03E-04 9.94E-05 O.OOE+00 4.61E-04 O.OOE+00 2.16E-06 Nd-147 4.28E-01 4.65E-01 2.79E-02 0.O0E+00 2.73E-01 0.OOE+00 1.68E+03 W-187 3.20E+02 2.60E+02 9.13E+01 O.OOE+00 0.OOE+00 0.00E+000 7.05E+04 Np-239 3.21 E-021 3.03E-03 1.68E-03 0.OOE+00 9.50E-03 0.OOE+00 4.87E+02 Notes:

1) Units are mrem/hr per pLCi/mI.

Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 196 of 307 January 2013 Table 3-5 (Page 5 of 6) Site Specific Fish Ingestion Dose Factors Child Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI H-3 0.OOE+00 8.21 E-02 8.21 E-02 8.21E-02 8.21 E-02 8.21 E-02 8.21 E-02 Na-24 4.56E+02 4.56E+02 4.56E+02 4.56E+02 4.56E+02 4.56E+02 4.56E+02 Cr-51 0.OOE+00 0.OOE+00 1.40E+00 7.77E-01 2.12E-01 1.42E+00 7.43E+01 Mn-54 0.OOE+00 3.37E+03 8.97E+02 0.00E+00 9.44E+02 0.OOE+00 2.83E+03 Mn-56 0.OOE+00 1.05E+02 2.37E+01 0.OOE+00 1.27E+02 0.OOE+00 1.52E+04 Fe-55 9.05E+02 4.80E+02 1.49E+02 0.OOE+00 0.OOE+00 2.71E+02 8.89E+01 Fe-59 1.30E+03 2.1OE+03 1.05E+03 0.OOE+00 0.OOE+00 6.09E+02 2.19E+03 Co-58 0.OOE+00 7.08E+01 2.17E+02 0.OOE+00 0.OOE+00 0.00E+00 4.13E+02 Co-60 0.OOE+00 2.08E+02 6.14E+02 0.OOE+00 0.OOE+00 0.OOE+00 1.15E+03 Ni-63 4.23E+04 2.27E+03 1.44E+03 0.OOE+00 O.OOE+00 0.OOE+00 1.53E+02 Ni-65 1.75E+02 1.64E+01 9.60E+00 0.OOE+00 0.OOE+00 O.OOE+00 2.01E+03 Cu-64 0.OOE+00 9.64E+00 5.82E+00 0.OOE+00 2.33E+01 0.OOE+00 4.52E+02 Zn-65 2.16E+04 5.74E+04 3.57E+04 0.OOE+00 3.62E+04 0.OOE+00 1.01E+04 Zn-69 6.89E+01 9.96E+01 9.20E+00 0.OOE+00 6.04E+01 0.OOE+00 6.28E+03 Br-83 0.OOE+00 0.OOE+00 5.65E+01 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Br-84 O.OOE+00 0.OOE+00 6.54E+01 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 Br-85 O.OOE+00 0.OOE+00 3.01E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Rb-86 0.OOE+00 1.05E+05 6.48E+04 0.OOE+00 0.OOE+00 0.OOE+00 6.78E+03 Rb-88 0.OOE+00 2.99E+02 2.08E+02 0.OOE+00 0.OOE+00 0.OOE+00 1.47E+01 Rb-89 0.OOE+00 1.84E+02 1.64E+02 0.OOE+00 0.OOE+00 0.OOE+00 1.60E+00 Sr-89 3.11 E+04 0.OOE+00 8.90E+02 0.OOE+00 0.OOE+00 0.OOE+00 1.21 E+03 Sr-90 6.04E+05 0.OOE+00 1.22E+04 0.OOE+00 0.OOE+00 0.00E+00 5.40E+03 Sr-91 5.66E+02 0.OOE+00 2.14E+01 0.OOE+00 O.OOE+00 0.OOE+00 1.25E+03 Sr-92 2.13E+02 O.OOE+00 8.54E+00 0.OOE+00 0.OOE+00 0.OOE+00 4.04E+03 Y-90 8.08E-01 0.OOE+00 2.16E-02 O.OOE+00 0.00E+00 0.OOE+00 2.30E+03 Y-91M 7.51E-03 0.OOE+00 2.73E-04 0.OOE+00 0.OOE+00 0.OOE+00 1.47E+01 Y-91 1.18E+01 0.OOE+00 3.17E-01 0.OOE+00 0.OOE+00 0.OOE+00 1.58E+03 Y-92 7.08E-02 0.OOE+00 2.03E-03 O.OOE+00 0.OOE+00 0.00E+00 2.05E+03 Y-93 2.24E-01 0.00E+00 6.16E-03 0.OOE+00 0.OOE+00 0.OOE+00 3.34E+03 Zr-95 3.01E-01 6.62E-02 5.89E-02 O.00E+00 9.47E-02 0.OOE+00 6.90E+01 Zr-97 1.81E-02 2.62E-03 1.55E-03 0.OOE+00 3.76E-03 0.00E+00 3.97E+02 Nb-95 5.31E+02 2.07E+02 1.48E+02 0.OOE+00 1.94E+02 0.00E+00 3.82E+05 Mo-99 0.OOE+00 1.05E+02 2.59E+01 0.00E+00 2.23E+02 0.00E+00 8.65E+01 Tc- 99M 1.09E-02 2.14E-02 3.54E-01 0.OOE+00 3.10E-01 1.08E-02 1.22E+01 Tc-101 1.26E-02 1.32E-02 1.68E-01 0.OOE+00 2.25E-01 6.99E-03 4.20E-02 Ru-103 5.75E+00 0.OOE+00 2.21E+00 0.OOE+00 1.45E+01 0.00E+00 1.49E+02 Ru-105 5.07E-01 0.OOE+00 1.84E-01 O.00E+00 4.46E+00 0.OOE+00 3.31E+02 Ru-106 9.20E+01 0.00E+00 1.15E+01 0.OOE+00 1.24E+02 0.OOE+00 1.43E+03 Ag-110M 9.75E-01 6.59E-01 5.26E-01 O.OOE+00 1.23E+00 0.OOE+00 7.83E+01 Te-125M 3.59E+03 9.72E+02 4.78E+02 1.01E+03 0.OOE+00 0.00E+00 3.46E+03 Quad Cities ODCM Part II

CY-QC-170-301 Revision 11 Page 197 of 307 January 2013 Table 3-5 (Page 6 of 6) Site Specific Fish Ingestion Dose Factors Child Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI Te-127M 9.09E+03 2.45E+03 1.08E+03 2.17E+03 2.59E+04 0.OOE+00 7.36E+03 Te-127 1.48E+02 4.OOE+01 3.18E+01 1.03E+02 4.22E+02 0.OOE+00 5.79E+03 Te-129M 1.53E+04 4.28E+03 2.38E+03 4.94E+03 4.50E+04 0.OOE+00 1.87E+04 Te-129 4.22E+01 1.18E+01 1.OOE+01 3.01E+01 1.23E+02 0.OOE+00 2.62E+03 Te-131M 2.27E+03 7.83E+02 8.34E+02 1.61E+03 7.58E+03 0.OOE+00 3.18E+04 Te-131 2.61E+01 7.96E+00 7.77E+00 2.OOE+01 7.90E+01 0.OOE+00 1.37E+02 Te-132 3.18E+03 1.41E+03 1.70E+03 2.05E+03 1.31E+04 0.OOE+00 1.42E+04 1-130 3.45E+01 6.96E+01 3.59E+01 7.67E+03 1.04E+02 0.OOE+00 3.26E+01 1-131 2.03E+02 2.04E+02 1.16E+02 6.75E+04 3.35E+02 0.OOE+00 1.82E+01 1-132 9.44E+00 1.73E+01 7.98E+00 8.05E+02 2.65E+01 O.OOE+00 2.04E+01 1-133 6.99E+01 8.64E+01 3.27E+01 1.60E+04 1.44E+02 0.OOE+00 3.48E+01 1-134 4.94E+00 9.18E+00 4.22E+00 2.11E+02 1.40E+01 O.OOE+00 6.09E+00 1-135 2.06E+01 3.72E+01 1.76E+01 3.29E+03 5.70E+01 O.OOE+00 2.83E+01 Cs-134 3.68E+05 6.04E+05 1.27E+05 0.OOE+00 1.87E+05 6.72E+04 3.26E+03 Cs-136 3.70E+04 1.02E+05 6.58E+04 O.OOE+00 5.41E+04 8.07E+03 3.57E+03 Cs-137 5.14E+05 4.92E+05 7.27E+04 0.OOE+00 1.60E+05 5.77E+04 3.08E+03 Cs-138 3.59E+02 4.99E+02 3.16E+02 0.OOE+00 3.51E+02 3.78E+01 2.30E+02 Ba-139 1.30E+00 6.95E-04 3.78E-02 0.OOE+00 6.07E-04 4.09E-04 7.52E+01 Ba-140 2.61 E+02 2.29E-01 1.53E+01 O.00E+00 7.46E-02 1.37E-01 1.32E+02 Ba-141 6.29E-01 3.52E-04 2.05E-02 O.00E+00 3.05E-04 2.07E-03 3.59E-01 Ba-142 2.75E-01 1.98E-04 1.54E-02 0.OOE+00 1.60E-04 1.16E-04 3.59E-03 La-140 1.99E-01 6.94E-02 2.34E-02 0.OOE+00 0.OOE+00 0.OOE+00 1.94E+03 La-142 1.03E-02 3.28E-03 1.03E-03 0.OOE+00 0.OOE+00 0.OOE+00 6.51E+02 Ce-141 3.12E-02 1.56E-02 2.31E-03 0.OOE+00 6.83E-03 0.OOE+00 1.94E+01 Ce-143 5.50E-03 2.98E+00 4.32E-04 0.OOE+00 1.25E-03 O.OOE+00 4.37E+01 Ce-144 1.64E+00 5.13E-01 8.73E-02 0.OOE+00 2.84E-01 0.OOE+00 1.34E+02 Pr-143 7.73E-01 2.32E-01 3.83E-02 0.OOE+00 1.26E-01 O.OOE+00 8.34E+02 Pr-144 2.54E-03 7.85E-04 1.28E-04 0.OOE+00 4.15E-04 0.OOE+00 1.69E+00 Nd-147 5.49E-01 4.44E-01 3.44E-02 0.OOE+00 2.44E-01 0.OOE+00 7.04E+02 W-187 4.05E+02 2.40E+02 1.08E+02 0.OOE+00 0.OOE+00 0.OOE+00 3.37E+04 Np-239 4.13E-02 2.97E-03 2.08E-03 O.OOE+00 8.57E-03 0.OOE+00 2.19E+02 Notes:

1) Units are mrem/hr per [tCi/ml.

2) The infant age group is assumed to receive no dose through the fish ingestion pathway, therefore no dose factors are supplied.

Quad Cities ODCM Part II

CY-QC-170-301 Revision 11 Page 198 of 307 January 2013 4.0 GASEOUS EFFLUENTS 4.1 Gaseous Effluents - General Information This section reviews the offsite radiological limits applicable to the Quad Cities Station and presents in detail the equations and procedures used to assess compliance with these limits. This approach uses the methodology of NUREG-0133 (Reference 14), and incorporates certain simplifications such as the use of average meteorology. 4.1.1 Pre-calculated atmospheric transport parameters are based on historical average atmospheric conditions. These historical meteorological conditions have resulted in the dispersion parameters shown in Table 4-3 through Table 4-5. Since Land Use Census data may vary yearly, dispersion factors for cow milk, cow meat, and nearest resident are in site specific procedures. 4.1.2 The equations and parameters of this section are for use in calculating offsite radiation doses during routine operating conditions. They are not for use in calculating doses due to non-routine releases (e.g., accident releases). 4.1.3 An overview of the required compliance is given in Table 1-1. The dose components are itemized and referenced, and an indication of their regulatory application is noted. Additionally, the locations of dose receivers for each dose component are given in Table 1-2. 4.1.4 Airborne Release Point Classifications The pattern of dispersion of airborne releases is dependent on the height of the release point relative to adjacent structures. Each release point is classified as one of the following three height-dependent types:

• Stack (or Elevated) Release Point (denoted by the letter S or subscript s). Quad Cities Main Chimney release point is a stack release.
• Ground Level Release Point (denoted by the letter G or subscript g).

Quad Cities does not have any ground level release points.

• Vent (or Mixed Mode) Release Point (denoted by the letter V or subscript v). Quad Cities Reactor Building Ventilation Exhaust is a vent release.

Quad Cities ODCM Part II

CY-QC-170-301 Revision 11 Page 199 of 307 January 2013 4.1.5 Operability and Use of Gaseous Effluent Treatment Systems 10CFR50 Appendix I and ODCM Part I (RECS) require that the ventilation exhaust treatment system and the waste gas holdup system be used when projected offsite doses in 31 days, due to gaseous effluent releases, from each reactor unit, exceed any of the following limits:

• 0.2 mrad to air from gamma radiation.
• 0.4 mrad to air from beta radiation.
• 0.3 mrem to any organ of a member of the public.

The station must project doses due to gaseous releases from the site at least once per 31 days. The calculational methods shown in sections 4.2.2.1, 4.2.2.2, and 4.2.3 are used for this dose projection. 4.1.6 For a release attributable to a processing or effluent system shared by more than one reactor unit, the dose due to an individual unit is obtained by proportioning the effluents among the units sharing the system. 4.2 Gaseous Effluents - Dose and Dose Rate Calculation Requirements 4.2.1 Instantaneous Dose Rates 4.2.1.1 Noble Gas: Total Body Dose Rate RECS limits the total body dose rate due to noble gases in gaseous effluents released from a site to areas at and beyond the site boundary to less than or equal to 500 mrem/yr at all times. The total body dose rate due to noble gases released in gaseous effluents is calculated by the following expression: DTB =*ZK 1 {(X/Q)sQis + (X/Q)y Qiv + (X/Q)gQig} (4-1) i The summation is over noble gas radionuclides i. DTB Total Body Dose Rate [mrem/yr] Dose rate to the total body due to gamma radiation from noble gas radionuclides released in gaseous effluents. Qis, Qiv, Qig Release Rate ((tCi/sec] Measured release rate of radionuclide i from a stack, vent or ground level release point, respectively. Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 200 of 307 January 2013 Ki Gamma Total Body Dose Conversion Factor [(mrem/yr)/(uCi/m 3 )] Gamma total body dose factor due to gamma emissions for noble gas radionuclide i. K values are taken from Table 4-12. (XIQ)s Relative Concentration Factor [sec/m 3] (x/Q)v (XjQ)g Radioactivity concentration based on semi-infinite cloud methodology at a specified location per unit of radioactivity release rate for a stack, vent, or ground level release, respectively. See Table 4-4. To comply with this specification, the effluent radiation monitor has a setpoint corresponding to an offsite total body dose rate at or below the limit (see Part II Section 2.2.3). In addition, compliance is assessed by calculating offsite total body dose rate based on periodic samples obtained per station procedures. 4.2.1.2 Noble Gas: Skin Dose Rate RECS limits the skin dose rate due to noble gases in gaseous effluents released from a site to areas at and beyond the site boundary to less than or equal to a dose rate of 3000 mrem/yr at all times. (See Part I Section 12.4.1.) The skin dose rate due to noble gases released in gaseous effluents is calculated by the following expression: IKI L[ (X/Q).Qi. + (X/Q)vQ,v + (X/Q)gQg] (4-2)

                                               + (X/Q)}Qi
                                                 ÷Q,.      +
                         +  (1.11) M,[ (X/Q)

The summation is over noble gas radionuclides i. DSK Skin Dose Rate [mrem/yr] Dose rate to skin due to beta and gamma radiation from noble gas radionuclides released in gaseous effluents. Li Beta Skin Dose Conversion Factor [(mrem/yr)/(uCi/m 3 )] Skin dose factor due to beta emissions for noble gas radionuclide i. L values are taken from Table 4-12. 1.11 Conversion Constant (rads in air to rem in tissue) [mrem/mrad] Quad Cities ODCM Part II

CY-QC-170-301 Revision 11 Page 201 of 307 January 2013 Mi Gamma Air Dose Conversion Factor [(mradlyr)l(ýtCilm 3 )] Gamma air dose rate factor per unit of radioactivity release rate for radionuclide i. See Table 4-12 for Gamma Air Dose conversion factors (From Table B-1 of Regulatory Guide 1.109). All other terms have been previously defined. To comply with this specification, gaseous effluent radiation monitors have setpoints corresponding to an offsite skin dose rate at or below the limit (see Part II Section 2.2.3). In addition, compliance is assessed by calculating offsite skin dose rate based on periodic samples obtained per station procedures. 4.2.1.3 Non-Noble Gas Radionuclides: Organ Dose Rate RECS limits the dose rate to any organ, due to radioactive materials in gaseous effluents released from a site to areas at and beyond the site boundary, to less than or equal to a dose rate of 1500 mrem/yr (See Part I Section 12.4.1). Typically the child is considered to be the limiting receptor in calculating dose rate to organs due to inhalation of non-noble gas radionuclides in gaseous effluents. The dose rate to any child organ due to inhalation is calculated by the following expression: NNG D(Child)i(Inhal)j = Z R(cihid)i(inhal)jj(X/Q)sQis + (x/Q)vQi, + (X/Q)gQig} (4-3) i The summation is over non-noble gas radionuclides i.

                  . NNG D(chi~d)i(,nha,)j           Inhalation Dose Rate            [mrem/yr]

Dose rate to the child age group from radionuclide i, via the inhalation pathway to organ j due to non-noble gas radionuclides. R(child)i(Inhal)j Inhalation Dose Factor [(mrem/yr)/( .tCi/m3)] Inhalation dose factor for child age group for radionuclide i, and organ j. All other terms have been previously defined. Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 202 of 307 January 2013 RECS requires the dose rate due to non-noble gas radioactive materials in airborne effluents be determined to be within the above limit in accordance with a sampling and analysis program specified in Part I Table 12.4.1-1. The child organ dose rate due to inhalation is calculated in each sector at the location of the highest offsite 7/Q (see Table 4-4). The result for the sector with the highest organ inhalation dose rate is compared to the limit. 4.2.2 Time Averaged Dose from Noble Gas 4.2.2.1 Gamma Air Dose RECS limits the gamma air dose due to noble gas effluents released from each reactor unit to areas at and beyond the UNRESTRICTED AREA boundary to the following:

• Less than or equal to 5 mrad per calendar quarter.
• Less than or equal to 10 mrad per calendar year.

The gamma air dose due to noble gases released in gaseous effluents is calculated by the following expression: D, = (3.17E-8)1M,{(x/Q)rA,5 + (X/Q)vAv + (X/Q) Ai, } (4-4) The summation is over noble gas radionuclides i. DY Gamma Air Dose [mrad] Dose to air due to gamma radiation from noble gas radionuclides released in gaseous effluents. 3.17E-8 Conversion Constant (seconds to years) [yr/sec] (X/Q)~I (X/Q)yv, (X/Q) Gamma-X/Q Factor [sec/m 3] Radioactivity concentration based on finite cloud methodology at a specific location per unit of radioactivity release rate from a stack, vent or ground level release, respectively. See Table 4-3 for Gamma-X/Q Factors. Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 203 of 307 January 2013 Ai., Ai,, Aig Cumulative Radionuclide Release [ktCi] Measured cumulative release of radionuclide i over the time period of interest from a stack, vent, or ground level release point, respectively. All other terms have been previously defined. RECS Section 12.4 requires determination of cumulative and projected gamma air dose contributions due to noble gases for the current calendar quarter and the current calendar year at least once per 31 days. Gamma air dose is calculated for the sector with the highest offsite (X/Q)Y and is compared with the RECS limits on gamma air dose. For a release attributable to a processing or effluent system shared by more than one reactor unit, the dose due to an individual unit is obtained by proportioning the effluents among the units sharing the system. 4.2.2.2 Beta Air Dose RECS limits beta air dose due to noble gases in gaseous effluents released from each reactor unit to areas at and beyond the UNRESTRICTED AREA boundary to the following:

• Less than or equal to 10 mrad per calendar quarter.
• Less than or equal to 20 mrad per calendar year.

The beta air dose due to noble gases released in gaseous effluents is calculated by the following expression: D, = (3.17E - 8)E {N11(X/Q)9 Al. + (X/Q)vAv + (X/Q)gAlJ. } (4-5) i The summation is over noble gas radionuclides i. Dp3 Beta Dose [mrad] Dose to air due to beta radiation from noble gas radionuclides released in gaseous effluents. Ni Beta Air Dose Conversion Factor [(mrad/yr)/([tCi/m 3)] Beta air dose rate per unit of radioactivity concentration for radionuclide i. See Table 4-12 for Beta Air Dose conversion factors (From Table B-1 of Regulatory Guide 1.109). Quad Cities ODCM Part II

CY-QC-170-301 Revision 11 Page 204 of 307 January 2013 All other terms have been previously defined. RECS Section 12.4 requires determination of cumulative and projected beta air dose contributions due to noble gases for the current calendar quarter and the current calendar year at least once per 31 days. Beta air dose is calculated for the sector with the highest offsite (7/Q) and is compared with the RECS limit on beta air dose. For a release attributable to a processing or effluent system shared by more than one reactor unit, the dose due to an individual unit is obtained by proportioning the effluents among the units sharing the system. 4.2.2.3 Total Body Dose The total body dose, to any receiver is due, in part, to gamma radiation emitted from radioactivity in airborne effluents. This component is added to others to demonstrate compliance to the requirements of 40CFR190 and 10CFR20. The total body dose component due to gamma radiation from noble gases released in gaseous effluents is calculated by the following expression: DTB = (3.17E - 8)1 Ki {(,/Q) .Ai.J+ (X/Q)fvAiv + (X/Q)'gAig } (4-6) i The summation is over noble gas radionuclides i. DTB Total Body Dose [mrem] Dose to the total body due to gamma radiation from noble gas radionuclides released in gaseous effluents. Ki Gamma Total Body Dose Conversion Factor [(mrem/yr)/(uCi/m 3 )] Gamma total body dose factor due to gamma emissions for noble gas radionuclide i released from a stack, vent or ground level release point, respectively. See Table 4-12 for Gamma total body dose conversion factors. (From Table B-1 of Regulatory Guide 1.109) All other terms have been previously defined. Quad cities ODCM Part II

CY-QC-170-301 Revision 11 Page 205 of 307 January 2013 The total body dose is also calculated for the 40CFR1 90 and 10CFR20 compliance assessments. In some cases, the total body dose may be required in 10CFR50 Appendix I assessments (See Part II Table 1-1). 4.2.2.4 Skin Dose There is no regulatory requirement to evaluate skin dose. However, this component is evaluated for reference as there is skin dose design objective contained in 10CFR50 Appendix I. Note that in the unlikely event that if beta air dose guideline is exceeded, then the skin dose will require evaluation. The part of skin dose due to noble gases released in gaseous effluents is calculated by the following expression: DSK = (3.17E-8) I{L,[ (X/Q).A, + (X/Q),A,v + ( A/Q),gAg]

                                                                                     }(4             7)

Ai, v+ (x/Q) gAig]

                                   + (1.11)M, [ (X/Q).Ai s+-(X/Q)

The summation is over noble gas radionuclides i. DSK Skin Dose [mrem] Dose to the skin due to beta and gamma radiation from noble gas radionuclides released in gaseous effluents. All other terms have been previously defined. The skin dose is calculated for reference only. 4.2.3 Time Averaged Dose from Non-Noble Gas Radionuclides RECS provides the following limits, based on 10CFR50 Appendix I, on the dose to a member of the public from specified non-noble gas radionuclides in gaseous effluents released from each reactor unit to areas at and beyond the UNRESTRICTED AREA boundary:

• Less than or equal to 7.5 mrem to any organ during any calendar quarter
• Less than or equal to 15 mrem to any organ during any calendar year The individual dose components are also required as part of the 40CFR1 90 assessments and combined as part of the 10CFR20 assessment (Part II Table 1-1). The dose due to radionuclides deposited on the ground is considered to be a component of the deep dose Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 206 of 307 January 2013 equivalent for 1 OCFR20 compliance and an organ (and total body) dose component for 10CFR50 Appendix I and 40CFR190 compliance. The dose is calculated for releases in the time period under consideration. Specifically, the dose is calculated as follows: DNNG (3.17E Rpj + WvRaipjAiv + WR.Aipj.] (4-8) p i The summation is over pathways p and non-noble gas radionuclides i. DalN"G Dose Due to Non-Noble Gas Radionuclides [mrem] Dose due to non-noble gases (radioiodines, tritium and particulates) to age group a, and to organ j. Ws, Wv, Wg Relative Concentration Factor Radioactive concentration at a specific location per unit of radioactivity release rate or concentration for stack, vent or ground level release, respectively. Ws, Wv, or Wg = (x/Q)., (XIQ)v or (TIQ)g for immersion, inhalation and all tritium pathways. WM, Wv, or Wg = (D/Q)s, (D/Q)v or (D/Q)g for ground plain and all ingestion pathways. (D/Q)s, (D/Q)v, (D/Q)g Relative Deposition Factor [1/M 2] Radioactivity concentration at a specified location per unit of radioactivity release concentration for a stack, vent, or ground level release, respectively. See Table 4-4 through Table 4-6. Deposition factors for cow milk, cow meat and nearest resident are in site specific procedures. Raipj Site-Specific Dose Factor [(M2 mrem/yr)/([tCi/sec)] or [(mrem/yr)/(ýICi/m 3 )] Site-specific dose factor for age group a, nuclide i, pathway p and organ j. Pathways included are ground plane exposure, inhalation, vegetation ingestion, milk ingestion and meat ingestion. Quad Cities ODCM Part II

CY-QC-170-301 Revision 11 Page 207 of 307 January 2013 A1 s, Air, Aig Cumulative Radionuclide Release ((tCi] Measured cumulative release of radionuclide i over the time period of interest from a stack, vent, or ground level release point, respectively. All other terms have been previously defined. RECS Section 12.4 require cumulative and PROJECTED DOSE contributions for the current calendar quarter and the current calendar year for the specified non-noble gas radionuclides in airborne effluents to be determined at least once per 31 days. To comply with this specification, Quad Cities Station obtains and analyzes samples in accordance with the radioactive gaseous waste or gaseous effluent sampling and analysis program (RECS Table 12.4.1-1). In accordance with NUREG 0133 (Reference 14), dose due to non-noble gases is assessed at the location in the UNRESTRICTED AREA where the combination of existing pathways and receptor age groups indicates the maximum potential exposure. The inhalation and ground plane exposure pathways are considered to exist at all locations. The food ingestion pathways at a specific location are considered based on their existence as determined by land use census. The values used for (Y/Q) and (D/Q) are shown in Table 4-4 through Table 4-6 and correspond to the applicable pathway location. X/Q and D/Q values for cow milk, cow meat and nearest resident are in site specific procedures. For a release attributable to a processing or effluent system shared by more than one reactor, the dose due to an individual unit is obtained by proportioning the effluents among the units sharing the system. The dose evaluated is also included as part of the 10CFR20 and 40CFR190 assessment (See Part II Section 5.0). 4.2.3.1 Ground Plane The site-specific dose factor for ground deposition of radioactivity is considered to be a total body dose component and is calculated by the following expression: R.i(GP)j[D/Q] = K'K" (0.7)DFG,[1- -2'tb (4-9) R3 (GP)j[D/Q] Ground Plane Deposition Dose Factor [(M2 mrem/yr)/([.Ci/sec)] Quad Cities ODCM Part II

CY-QC-170-301 Revision 11 Page 208 of 307 January 2013 Site-specific ground plane dose factor for age group a, nuclide i and organ j. The ground plane dose is calculated using (D/Q). K' Conversion Constant (1 E6 pCi per P.Ci) [pCi/pLCi] K" Conversion Constant (8760 hr/yr) [hr/yr] 0.7 Shielding Factor; a factor that accounts for dimensionless shielding due to occupancy of structures. DFGj Ground Plane Dose Conversion Factor [(mrem/hr)/(pCi/m 2 )] Dose rate to the total body per unit of surface radioactivity concentration due to standing on ground uniformly contaminated with radionuclide i. Ground Plane Dose Factors are shown in Table 4-13. Note that ground plane dose factors are only given for the total body and no age group. Doses to other organs are assumed to be equal to the total body dose. All age groups are assumed to receive the same dose. Xi Radiological Decay Constant [hr-1] Radiological decay constant for radionuclide i. tb Time Period of Ground Deposition [hr] Time period during which the radioactivity on the ground is assumed to have been deposited (see Part II Table 1-3). All other terms have been previously defined. The ground plane exposure pathway is considered to exist at all locations. Quad Cities ODCM Part II

CY-QC-170-301 Revision 11 Page 209 of 307 January 2013 4.2.3.2 Inhalation The site-specific dose factor for inhalation is calculated by the following expression: Rai(Inhal)j [X/Qa]= K'BRa DFAaij (4-10) Ra(Inhal)j [X/Q] Inhalation Pathway Dose Factor [(mrem/yr)/(ý1Ci/m 3 )] Site-specific inhalation dose factor for age group a, nuclide i and organ j. The inhalation dose is calculated using (X/Q). BRa Individual Air Inhalation Rate [m 3/yr] The air intake rate for individuals in age group a. See Table E-5 of Reg. Guide 1.109. DFAaij Inhalation Dose Conversion Factor [mrem/pCi] Dose commitment to an individual in age group a to organ j per unit of activity of radionuclide i inhaled. Taken from Tables E-7 through E-10 of Regulatory Guide 1.109. The value for H-3 is taken from NUREG 4013 (Reference 107). All other terms have been previously defined. The inhalation exposure pathway is considered to exist at all locations. 4.2.3.3 Ingestion: Vegetation Food ingestion pathway doses are calculated at locations indicated by the land use census survey. If no real pathway exists within 5 miles of the station, the cow-milk pathway is assumed to be located at 5 miles. Food pathway calculations are not made for sectors in which the offsite regions near the station are over bodies of water. The dose factor for consumption of vegetables is calculated by the following expression: Rai(veg)j [D/Q] = K'[Y (r w)1 (DFL.ij)[U.fLexitL + Usf ge_ .Lth] (4-11) R i(veg)j[D/Q] Vegetation Ingestion Pathway Dose Factor [(M2 mrem/yr)/([tLCi/sec)] Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 210 of 307 January 2013 Site-specific vegetation ingestion dose factor for age group a, nuclide i and organ j. With the exception of H-3 and C-14, the vegetation dose is calculated using (D/Q). r Vegetation Retention Factor [dimensionless] Yv Agricultural Productivity Yield [kg/ M 2 ] Xw Weathering Decay Constant [1/sec] Removal constant for physical loss of activity by weathering. See ODCM Part II Table 1-3. DFLaij Ingestion Dose Conversion Factor [mrem/pCi] Ingestion dose conversion factor for age group a, nuclide i and organ j. Converts pCi ingested to mrem. Taken from Tables E-1 1 though E-14 of Regulatory Guide 1.109. The value for H-3 is taken from NUREG 4013 (Reference 107). UaL Consumption Rate for Fresh Leafy Vegetation [kg/yr] Consumption rate for fresh leafy vegetation for age group a. Uas Consumption Rate for Stored Vegetation [kg/yr] Consumption rate for stored vegetation for age group a. fL Local Leafy Vegetation Fraction [dimensionless] Fraction of the annual intake of fresh leafy vegetation that is grown locally. fg Local Stored Vegetation Fraction [dimensionless] Fraction of the annual intake of stored vegetation that is grown locally. tL Environmental Transport Time - Fresh Vegetation [sec] Average time between harvest of leafy vegetation and its consumption. th Environmental Transport Time - Stored Vegetation [sec] Average time between harvest of stored vegetation and its consumption. Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 211 of 307 January 2013 All other terms have been previously defined. The tritium and carbon-14 dose from the vegetation pathway must be considered separately as the transport mechanism is based on airborne concentration rather than ground deposition. The dose factors for the tritium and carbon-14 vegetation pathways are: Ra(H-3)(Veg)j [l,/Q] = K'K" (uL + Uafg )DFLa(H 3 )j[0.75(0.5/H)] (4-12a) Ra(H_3)(veg)j[X/Q] Tritium Vegetation Ingestion Pathway Dose Factor [(mrem/yr)/( [Ci/m3)] Site-specific tritium vegetation ingestion dose factor for age group a and organ j. The tritium vegetation dose is calculated using yjQ. K"' Conversion Constant (1E3 gm per Kg) [gm/Kg] H Absolute Atmospheric Humidity [gm/m 3] 0.75 Water Fraction [dimensionless] The fraction of total vegetation that is water. 0.5 Specific Activity Ratio [dimensionless] All other terms have been previously defined. R,,(c_)(v*)J [x/Q] = K' K"(U~fL + uafg )DFLa(C_,4)jP[0.11/0.16] (4-12b) Site-specific carbon-14 vegetation ingestion dose factor for age group a and organ j. The carbon-14 vegetation dose is calculated using z/Q. 0.11 the fraction of total plant mass that is natural carbon [dimensionless] 0.16 the concentration of natural carbon in the atmosphere [gm/m 3] P fractional equilibrium ratio of total annual C-14 release time to annual time during which photosynthesis occurs. Assumed to be unity for continuous releases. All other terms have been previously defined. Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 212 of 307 January 2013 4.2.3.4 Ingestion: Milk The dose factor for consumption of milk is calculated by the following expressions: Rai(Milk)j[D/Q] = K' QF(Uam) Fm(r)(DFLj + (1-ff)e+ extf (4-13) X!+ ký I Ya Y. I Ri(Mik)j[D/Q] Milk Ingestion Pathway Dose Factor [(M2 mrem/yr)/(p.tCi/sec)] Site-specific milk ingestion dose factor for age group a, nuclide i and organ j. With the exception of H-3 and C-14, the milk dose factor is calculated using (D/Q). QF Feed Consumption [Kg/da] Amount of feed consumed by milk animal each day. See ODCM Part II Table 1-3. Uam Milk Consumption Rate [I/yr] Milk consumption rate for age group a. Fm Stable Element Transfer Coefficient for Milk [da/I] Fraction of animal's daily intake of a particular chemical element that appears in each liter of milk (pCi/I in milk per pCi/da ingested by animal). See ODCM Part II Table 1-4. fp Pasture Time Fraction [dimensionless] Fraction of year that animal is on pasture. fS Pasture Grass Fraction [dimensionless] Fraction of animal feed that is pasture grass while animal is on pasture. Yp Agricultural Productivity Yield - Pasture Grass [kg/M 2] The agricultural productivity by unit area of pasture feed grass. YS Agricultural Productivity Yield - Stored Feed [kg/m 2] The agricultural productivity by unit area of stored feed. Quad Cities ODCM Part II

CY-QC-170-301 Revision 11 Page 213 of 307 January 2013 th Environmental Transport Time - Stored Feed [sec] Average time between harvest to consumption of stored feed by milk animal. tf Environmental Transport Time - Pasture to Consumption [sec] Average time from pasture, to milk animal, to milk, to consumption. All other terms have been previously defined. The tritium and carbon-14 dose from the milk pathway must be considered separately as the transport mechanism is based on airborne concentration rather than ground deposition. The dose factors for the tritium and carbon-14 milk pathways are: R a(H-3)(Milk)j [X/Q] = K'K" Fm QFUamDFLa(H- 3)j[0.75(0.5/H)] (4-14a) Ra(H-3)(Milk)j [X/Q] Tritium Milk Ingestion Pathway Dose Factor [(m rem/yr)/( [LCi/m3)] Site-specific tritium milk ingestion dose factor for age group a and organ j. The tritium and carbon-14 milk dose is calculated using X/Q. H Absolute Atmospheric Humidity [gm/m 3 ] All other terms have been previously defined. Ra(c_ 4 )(Mik)j [Xz/Q ]= K' K" F,,, QFU,.,DFL.(c_,4 )jP[O.11/ 0.16] (4-14b) Rc-,4)(Mi~k~j [X/Q] Carbon-14 Milk Ingestion pathway dose factor [(mrem/yr)/( ýCi/mn)] Site-specific carbon-14 milk ingestion dose factor for age group a and organ j. The carbon-14 milk dose is calculated using y{/Q. All other terms have been previously defined. Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 214 of 307 January 2013 4.2.3.5 Ingestion: Meat The dose factor for consumption of meat is calculated by the following expression: Rai(Meat)j[D/Q] = K' QF(Uaf) Ff(r)(DFLaij) +f( e-+t (4-15) Rai(Meat)j [D/Q] Meat Ingestion Pathway Dose Factor [(M2 mrem/yr)/([tCi/sec)] Site-specific meat ingestion dose factor for age group a, nuclide i and organ j. With the exception of H-3 and C-14, the meat dose factor is calculated using (D/Q). Uaf Meat Consumption Rate [kg/yr] Meat consumption rate for age group a. Ff Stable Element Transfer Coefficient for Meat [da/Kg] Fraction of animal's daily intake of a particular chemical element that appears in each liter of meat (pCi/Kg in meat per pCi/da ingested by animal). See ODCM Part II Table 1-4. tf Environmental Transport Time - Pasture to Consumption [sec] Average time from pasture, to meat animal, to meat, to consumption. All other terms have been previously defined. The tritium and carbon-14 dose from the meat pathway must be considered separately as the transport mechanism is based on airborne concentration rather than ground deposition. The dose factors for the tritium and carbon-14 meat pathways are: Ra(H_3XMeat)j[x/Q] = K'K"'Ff QFUafDFLa(H_ 3)j [0.75(0.5/H)] (4-16a) Ra(H_3XMeat)j[X/Q] Tritium Meat Ingestion Pathway Dose Factor [(m rem/yr)/( [,Ci/m3)] Site-specific tritium meat ingestion dose factor for age group a and organ j. The tritium meat dose is calculated using 7,/Q. Quad Cities ODCM Part II

CY-QC-170-301 Revision 11 Page 215 of 307 January 2013 All other terms have been previously defined. Ra(C_,4)(M,,t)j [X/Q] = K' K" F, QFUc.,.DFL,(C_14).iP[O.11/0.16] (4-16b) R,,(C_,4)(Mf,,,)j [X/Q] Carbon-14 Meat Ingestion Pathway Dose Factor [(m rem/yr)/(ýtCi/m3)] Site-specific carbon-14 meat ingestion dose factor for age group a and organ j. The carbon-14 meat dose is calculated using X/Q. All other terms have been previously defined. Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 216 of 307 January 2013 Table 4-1 Critical Ranges UNRESTRICTED RESTRICTED Nearest Nearest Dairy Direction AREA Boundarya AREA Resident (m) Farm within 5 W() Boundaryb (m) milesd (M) N 864 219 800 note ' NNE 1029 224 note d note d NE 1212 265 note d note d ENE 1367 393 note d note d E 1170 867 noted T note d ESE 1170 924 note d note d SE 1189 1010 noted T note d SSE 1422 1059 note ý note d S 1198 762 note d note d SSW 2140 335 note d note d SW 1372 232 note d note d WSW 823 189 note d note d W 713 189 note d note d WNW 713 183 note d note d NW 823 210 note d note d NNW 1481 224 note d note d a Nearest land in UNRESTRICTED AREA. Used in calculating the meteorological dose factors in Table 4-3 through Table 4-5 and Table 4-6. b These values are to the edge of the Mississippi River, where applicable. c The distances are rounded to the nearest conservative 100 meters. d Current census data is contained in site specific procedures. Quad Cities ODCM Part II

CY-QC-170-301 Revision 11 Page 217 of 307 January 2013 Table 4-2 Average Wind Speeds Downwind Average Wind Speed (mlsec)* Direction Elevated Mixed Mode Ground Level N 6.4 5.5 2.1 NNE 6.4 5.5 2.4 NE 5.9 4.8 2.6 ENE 5.7 4.6 2.6 E 6.2 5.3 2.8 ESE 6.6 5.9 3.0 SE 6.1 5.1 2.7 SSE 5.3 4.5 2.5 S 5.2 4.4 2.7 SSW 5.0 4.4 2.6 SW 5.5 4.8 2.6 WSW 5.4 4.6 2.5 W 4.9 4.3 2.3 WNW 5.9 5.2 2.2 NW 5.7 4.8 2.1 NNW 5.9 5.1 2.0 Based on Quad Cities site meteorological data, January 1998 through December 2007. Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 218 of 307 January 2013 Table 4-3 Maximum Offsite Gamma-X/Q Downwind Radius Ground Stack Vent Direction Gamma-X/Q Gamma-X/Q Gamma-X/Q (meters) (sec/m3) (sec/m-3 ) (sec/m 3 ) N 864 9.34E-07 8.96E-08 2.52E-07 NNE 1029 6.54E-07 8.96E-08 2.23E-07 NE 1212 5.84E-07 5.79E-08 1.36E-07 ENE 1367 4.34E-07 4.19E-08 1.03E-07 E 1170 7.95E-07 6.76E-08 1.82E-07 ESE 1170 7.83E-07 7.11E-08 2.OOE-07 SE 1189 5.94E-07 7.08E-08 1.73E-07 SSE 1422 2.75E-07 4.20E-08 8.60E-08 S 1198 3.71E-07 4.28E-08 9.60E-08 SSW 2140 1.24E-07 2.11E-08 3.80E-08 SW 1372 3.65E-07 3.93E-08 9.40E-08 WSW 823 9.78E-07 6.61 E-08 1.76E-07 W 713 1.74E-06 8.53E-08 2.19E-07 WNW 713 2.39E-06 7.99E-08 2.56E-07 NW 823 1.36E-06 7.06E-08 1.98E-07 NNW 1481 4.36E-07 4.54E-08 1.10E-07 Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 219 of 307 January 2013 Table 4-4

                                          /n -A    rfun K A                D~.      A fke  HIMDC:Q-DIrIC'Tr) A~-A                  Q^HnAn X      l IU      IVIOAII CI.1 1  i    UI UI   UI IU LIIZ UI'II\I--J    I I\I' I L-I-/ /- 1 l.---    LUI IUC~4Ily Downwind                     Elevated (Stack) Release                            Mixed Mode (Vent) Release                                  Ground Level Release Direction Radius           x/Q          Radius           D/Q            Radius                X/Q            D/Q             Radius            7JQ          D/Q (meters)       (sec/m 3)      (meters)            m"2 )       (meters)      (sec/m 3 )             (M-2)           (meters)         (sec/m 3 )    (M-2)

N 4400 1.086E-08 864 1.360E-09 864 3.459E-07 3.605E-09 864 4.552E-06 8.720E-09 NNE 4023 1.458E-08 1029 2.079E-09 1029 2.828E-07 4.005E-09 1029 2.650E-06 8.121E-09 NE 4828 1.215E-08 1212 1.044E-09 1212 1.439E-07 1.824E-09 1212 2.285E-06 7.495E-09 ENE 4400 1.095E-08 1367 8.648E-10 1367 1.082E-07 1.507E-09 1367 1.795E-06 5.049E-09 E 3600 1.767E-08 1170 1.458E-09 1170 1.939E-07 3.345E-09 1170 3.154E-06 1.001E-08 ESE 3600 1.976E-08 1170 1.597E-09 1170 2.137E-07 3.806E-09 1170 3.168E-06 9.945E-09 SE 4023 1.881E-08 1189 1.513E-09 1189 1.789E-07 3.084E-09 1189 2.196E-06 7.816E-09 SSE 4023 1.195E-08 1422 8.501E-10 1422 8.928E-08 1.335E-09 1422 1.199E-06 3.331E-09 S 4400 9.854E-09 1198 6.592E-10 1198 9.098E-08 1.318E-09 1198 1.723E-06 4.442E-09 SSW 4400 8.037E-09 2140 3.622E-10 2140 4.944E-08 5.494E-10 2140 6.896E-07 1.299E-09 SW 4400 1.072E-08 1372 6.892E-10 1372 1.006E-07 1.409E-09 1372 1.669E-06 4.062E-09 WSW 4400 1.053E-08 823 7.839E-10 823 1.581E-07 2.243E-09 823 4.439E-06 1.048E-08 W 4828 1.075E-08 713 7.649E-10 713 1.837E-07 2.274E-09 713 9.933E-06 1.468E-08 WNW 4828 9.579E-09 713 8.161E-10 713 3.134E-07 3.276E-09 713 1.323E-05 1.947E-08 NW 4828 8.454E-09 823 8.376E-10 823 2.422E-07 2.243E-09 823 7.154E-06 1.137E-08 NNW 4400 9.806E-09 1481 8.183E-10 1481 1.394E-07 1.431E-09 1481 2.339E-06 3.972E-09 Quad Cities Site Meteorological Data 1998-2007 Based on Sargent & Lundy, Nuclear Safeguards and Licensing Division, Quad Cities calculation no. ATD-01 39, "N-1 6 Skyshine Ground Level Doses from Quad Cities Turbine Systems & Piping, Revision 0. Used for beta air, beta skin, and inhalation dose pathways. See ODCM part IIsections 4.2.2.2, 4.2.2.4, and 4.2.3.2. Used for produce and leafy vegetable pathways. See ODCM part IIsection 4.2.3. Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 220 of 307 January 2013 Table 4-5 X/Q and D/Q Maxima at or Beyond the RESTRICTED AREA Boundary Downwind Elevated (Stack) Release Mixed Mode (Vent) Release Ground Level Release Direction Radius X/Q Radius D/Q Radius X/Q D/Q Radius x'Q D/Q (meters) (sec/m3) (meters) (m-2) (meters) (sec/m3 ) (m-2) (meters) (sec/m 3) (m-2) N 4400 1.086E-08 420 1.893E-09 219 3.308E-06 1.840E-08 219 4.884E-05 7.042E-08 NNE 4800 1.388E-08 420 3.429E-09 224 3.039E-06 2.153E-08 224 3.519E-05 8.428E-08 NE 4828 1.215E-08 420 1.830E-09 265 1.189E-06 9.162E-09 265 2.785E-05 8.053E-08 ENE 4400 1.095E-08 420 1.587E-09 393 4.868E-07 5.882E-09 393 1.308E-05 3.718E-08 E 3600 1.767E-08 867 1.750E-09 867 2.648E-07 4.812E-09 867 5.047E-06 1.639E-08 ESE 3600 1.976E-08 924 1.814E-09 924 2.696E-07 5.044E-09 924 4.610E-06 1.467E-08 SE 4023 1.881E-08 1010 1.695E-09 1010 2.080E-07 3.760E-09 1010 2.828E-06 1.028E-08 SSE 4023 1.195E-08 1059 1.015E-09 1059 1.141E-07 1.898E-09 1059 1.887E-06 5.477E-09 S 4400 9.854E-09 1500 6.013E-10 762 1.435E-07 2.136E-09 762 3.587E-06 9.328E-09 SSW 4400 8.037E-09 420 9.631E-10 335 3.952E-07 4.066E-09 335 1.335E-05 2.610E-08 SW 4400 1.072E-08 1500 6.705E-10 232 1.058E-06 8.380E-09 232 3.244E-05 6.512E-08 WSW 4400 1.053E-08 1500 6.242E-10 189 1.477E-06 9.670E-09 189 5.598E-05 9.618E-08 W 4828 1.075E-08 1500 5.875E-10 189 1.484E-06 8.482E-09 189 1.026E-04 1.069E-07 WNW 4828 9.579E-09 420 9.604E-10 183 2.926E-06 1.550E-08 183 1.465E-04 1.483E-07 NW 4828 8.454E-09 420 1.096E-09 210 2.287E-06 9.946E-09 210 7.783E-05 9.OOOE-08 NNW 4400 9.806E-09 420 1.781E-09 224 2.504E-06 1.358E-08 224 5.713E-05 7.621E-08 Quad Cities Site Meteorological Data 1998-2007 Quad Cities ODCM Part II

CY-QC-170-301 Revision 11 Page 221 of 307 January 2013 Table 4-6 (Page 1 of 14) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the UNRESTRICTED AREA Boundary for Kr-83m Downwind UNRESTRICTED Elevated (Stack) Release Mixed Mode (Vent) Release Ground Level Release Direction AREA Boundary Radius S I Radius V V Radius G (meters) (meters) (mrad/yr)/(pCi/sec) (meters) (mrad/yr)/(pCi/sec) (meters) (mrad/yr)/(pCi/sec) N 864 864 4.010E-07 3.024E-07 864 8.570E-06 6.462E-06 864 1.790E-04 1.350E-04 NNE 1029 1029 6.710E-07 5.060E-07 1029 7.260E-06 5.474E-06 1029 1.040E-04 7.842E-05 NE 1212 1212 3.880E-07 2.961E-07 1212 3.760E-06 2.835E-06 1212 8.290E-05 6.250E-05 ENE 1367 1367 3.200E-07 2.413E-07 1367 2.920E-06 2.203E-06 1367 6.320E-05 4.769E-05 E 1170 1170 4.840E-07 3.649E-07 1170 5.580E-06 4.208E-06 1170 1.190E-04 8.973E-05 ESE 1170 1170 4.770E-07 3.596E-07 1170 6.300E-06 4.750E-06 1170 1.190E-04 8.971E-05 SE 1189 1189 4.700E-07 3.543E-07 1189 5.1OOE-06 3.845E-06 1189 8.190E-05 6.173E-05 SSE 1422 1422 3.130E-07 2.360E-07 1422 2.420E-06 1.825E-06 1422 4.060E-05 3.061E-05 S 1198 1198 2.250E-07 1.697E-07 1198 2.460E-06 1.855E-06 1198 5.970E-05 4.501E-05 SSW 2140 2140 2.130E-07 1.606E-07 2140 1.320E-06 9.954E-07 2140 1.760E-05 1.327E-05 SW 1372 1372 2.390E-07 1.802E-07 1372 2.770E-06 2.089E-06 1372 5.730E-05 4.320E-05 WSW 823 823 2.31OE-07 1.742E-07 823 4.350E-06 3.281E-06 823 1.720E-04 1.297E-04 W 713 713 2OOOE-07 1.508E-07 713 4.850E-06 3.656E-06 713 3.700E-04 2.790E-04 WNW 713 713 2.190E-07 1.651E-07 713 8.120E-06 6.123E-06 713 5.070E-04 3.823E-04 NW 823 823 2.740E-07 2.066E-07 823 5.940E-06 4.479E-06 823 2.790E-04 2.104E-04 NNW 1481 1481 3.010E-07 2.270E-07 1481 3.400E-06 2.563E-06 1481 7.820E-05 5.897E-05 Quad Cities Site Meteorological Data 1998-2007 Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 222 of 307 January 2013 Table 4-6 (Page 2 of 14) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the UNRESTRICTED AREA Boundary for Kr-85m Downwind UNRESTRICTED Elevated (Stack) Release Mixed Mode (Vent) Release Ground Level Release Direction AREA Boundary Radius S S Radius V V Radius G (meters) (meters) (mrad/yr)/(pCi/sec) (meters) (mrad/yr)/(pCi/sec) (meters) (mrad/yr)/(pCi/sec) N 864 864 1.040E-04 1.006E-04 864 3.980E-04 3.834E-04 864 2.890E-03 2.767E-03 NNE 1029 1029 1.070E-04 1.034E-04 1029 3.610E-04 3.482E-04 1029 1.920E-03 1.840E-03 NE 1212 1212 6.970E-05 6.742E-05 1212 2.330E-04 2.247E-04 1212 1.710E-03 1.640E-03 ENE 1367 1367 5.130E-05 4.961E-05 1367 1.820E-04 1.755E-04 1367 1.420E-03 1.362E-03 E 1170 1170 8.180E-05 7.910E-05 1170 3.030E-04 2.919E-04 1170 2.380E-03 2.283E-03 ESE 1170 1170 8.630E-05 8.347E-05 1170 3.310E-04 3.191E-04 1170 2.320E-03 2.225E-03 SE 1189 1189 8.550E-05 8.271E-05 1189 2.890E-04 2.787E-04 1189 1.690E-03 1.621E-03 SSE 1422 1422 5.150E-05 4.980E-05 1422 1.540E-04 1.485E-04 1422 9.070E-04 8.703E-04 S 1198 1198 5.090E-05 4.924E-05 1198 1.650E-04 1.592E-04 1198 1.180E-03 1.131E-03 SSW 2140 2140 2.780E-05 2.688E-05 2140 7.820E-05 7.539E-05 2140 4.840E-04 4.645E-04 SW 1372 1372 4.780E-05 4.624E-05 1372 1.640E-04 1.581E-04 1372 1.220E-03 1.170E-03 WSW 823 823 7.480E-05 7.239E-05 823 2.770E-04 2.669E-04 823 2.780E-03 2.615E-03 W 713 713 9.400E-05 9.096E-05 713 3.380E-04 3.256E-04 713 5.140E-03 4.916E-03 WNW 713 713 8.930E-05 8.642E-05 713 3.940E-04 3.790E-04 713 6.650E-03 6.357E-03 NW 823 823 8.040E-05 7.779E-05 823 3.120E-04 3.005E-04 823 4.180E-03 3.999E-03 NNW 1481 1481 5.580E-05 5.396E-05 1481 1.960E-04 1.889E-04 1481 1.660E-03 1.591E-03 Quad Cities Site Meteorological Data 1998-2007 Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 223 of 307 January 2013 Table 4-6 (Page 3 of 14) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the UNRESTRICTED AREA Boundary for Kr-85 Downwind UNRESTRICTED Elevated (Stack) Release Mixed Mode (Vent) Release Ground Level Release Direction AREA Boundary Radius S S Radius V V Radius G (meters) (meters) (mrad/yr)/(pCi/sec) (meters) (mrad/yr)/(pCi/sec) (meters) (mrad/yr)/(pCi/sec) N 864 864 1.670E-06 1.615E-06 864 5.110E-06 4.941E-06 864 3.680E-05 3.558E-05 NNE 1029 1029 1.680E-06 1.624E-06 1029 4.640E-06 4.487E-06 1029 2.460E-05 2.379E-05 NE 1212 1212 1.100E-06 1.064E-06 1212 3.050E-06 2.949E-06 1212 2.210E-05 2.137E-05 ENE 1367 1367 8.080E-07 7.814E-07 1367 2.400E-06 2.320E-06 1367 1.890E-05 1.828E-05 E 1170 1170 1.280E-06 1.238E-06 1170 3.930E-06 3.800E-06 1170 3.090E-05 2.986E-05 ESE 1170 1170 1.340E-06 1.296E-06 1170 4.270E-06 4.129E-06 1170 3.OOOE-05 2.901E-05 SE 1189 1189 1.340E-06 1.295E-06 1189 3.740E-06 3.616E-06 1189 2.170E-05 2.098E-05 SSE 1422 1422 8.080E-07 7.813E-07 1422 2.030E-06 1.963E-06 1422 1.220E-05 1.180E-05 S 1198 1198 8.170E-07 7.901E-07 1198 2.170E-06 2.099E-06 1198 1.570E-05 1.518E-05 SSW 2140 2140 4.320E-07 4.177E-07 2140 1.050E-06 1.015E-06 2140 7.350E-06 7.108E-06 SW 1372 1372 7.580E-07 7.330E-07 1372 2.150E-06 2.078E-06 1372 1.640E-05 1.586E-05 WSW 823 823 1.230E-06 1.189E-06 823 3.630E-06 3.510E-06 823 3.500E-05 3.385E-05 W 713 713 1.580E-06 1.529E-06 713 4.460E-06 4.313E-06 713 6.440E-05 6.227E-05 WNW 713 713 1.470E-06 1.421E-06 713 5.100E-06 4.932E-06 713 8.250E-05 7.978E-05 NW 823 823 1.310E-06 1.310E-06 823 4.050E-06 3.917E-06 823 5.300E-05 5.123E-05 NNW 1481 1481 8.780E-07 8.490E-07 1481 2.550E-06 2.466E-06 1481 2.310E-05 2.233E-05 Quad Cities Site Meteorological Data 1998-2007 Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 224 of 307 January 2013 Table 4-6 (Page 4 of 14) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the UNRESTRICTED AREA Boundary for Kr-87 Downwind UNRESTRICTED Elevated (Stack) Release Mixed Mode (Vent) Release Ground Level Release Direction AREA Boundary Radius S Radius V I Radius G (meters) (meters) (mrad/yr)/(pCi/sec) (meters) (mrad/yr)/(pCi/sec) (meters) (mrad/yr)/(pCi/sec) N 864 864 5.250E-04 5.101E-04 864 1.490E-03 1.447E-03 864 7.540E-03 7.321E-03 NNE 1029 1029 5.240E-04 5.091E-04 1029 1.350E-03 1.311E-03 1029 5.060E-03 4.913E-03 NE 1212 1212 3.400E-04 3.303E-04 1212 8.670E-04 8.421E-04 1212 4.450E-03 4.320E-03 ENE 1367 1367 2.470E-04 2.400E-04 1367 6.750E-04 6.556E-04 1367 3.460E-03 3.361E-03 E 1170 1170 3.960E-04 3.847E-04 1170 1.130E-03 1.097E-03 1170 6.150E-03 5.972E-03 ESE 1170 1170 4.160E-04 4.042E-04 1170 1.230E-03 1.195E-03 1170 6.010E-03 5.835E-03 SE 1189 1189 4.150E-04 4.032E-04 1189 1.070E-03 1.039E-03 1189 4.480E-03 4.351E-03 SSE 1422 1422 2.470E-04 2.400E-04 1422 5.680E-04 5.516E-04 1422 2.170E-03 2.108E-03 S 1198 1198 2.520E-04 2.449E-04 1198 6.170E-04 5.992E-04 1198 2.920E-03 2.836E-03 SSW 2140 2140 1.260E-04 1.224E-04 2140 2.770E-04 2.691E-04 2140 9.270E-04 9.001E-04 SW 1372 1372 2.320E-04 2.253E-04 1372 6.080E-04 5.904E-04 1372 2.910E-03 2.826E-03 WSW 823 823 3.880E-04 3.770E-04 823 1.060E-03 1.029E-03 823 7.510E-03 7.291E-03 W 713 713 5.010E-04 4.868E-04 713 1.310E-03 1.272E-03 713 1.380E-02 1.340E-02 WNW 713 713 4.690E-04 4.557E-04 713 1.500E-03 1.457E-03 713 1.830E-02 1.777E-02 NW 823 823 4.140E-04 4.022E-04 823 1.180E-03 1.146E-03 823 1.100E-02 1.068E-02 NNW 1481 1481 2.680E-04 2.603E-04 1481 7.150E-04 6.943E-04 1481 3.660E-03 3.553E-03 Quad Cities Site Meteorological Data 1998-2007 Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 225 of 307 January 2013 Table 4-6 (Page 5 of 14) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the UNRESTRICTED AREA Boundary for Kr-88 Downwind UNRESTRICTED Elevated (Stack) Release Mixed Mode (Vent) Release Ground Level Release Direction AREA Boundary Radius S Radius V V Radius G (meters) (meters) (mrad/yr)/(pCi/sec) (meters) (mrad/yr)/(pCi/sec) (meters) (mrad/yr)/(pCi/sec) N 864 864 1.340E-03 1.304E-03 864 3.790E-03 3.686E-03 864 2.680E-02 2.602E-02 NNE 1029 1029 1.350E-03 1.314E-03 1029 3.470E-03 3.375E-03 1029 1.770E-02 1.720E-02 NE 1212 1212 8.940E-04 8.701E-04 1212 2.320E-03 2.257E-03 1212 1.570E-02 1.525E-02 ENE 1367 1367 6.610E-04 6.435E-04 1367 1.830E-03 1.780E-03 1367 1.310E-02 1.273E-02 E 1170 1170 1.040E-03 9.927E-04 1170 2.960E-03 2.879E-03 1170 2.190E-02 2.128E-02 ESE 1170 1170 1.080E-03 1.051E-03 1170 3.200E-03 3.112E-03 1170 2.130E-02 2.069E-02 SE 1189 1189 1.080E-03 1.051E-03 1189 2.820E-03 2.743E-03 1189 1.550E-02 1.506E-02 SSE 1422 1422 6.590E-04 6.414E-04 1422 1.550E-03 1.507E-03 1422 8.370E-03 8.131E-03 S 1198 1198 6.690E-04 6.513E-04 1198 1.650E-03 1.605E-03 1198 1.090E-02 1.059E-02 SSW 2140 2140 3.570E-04 3.475E-04 2140 8.090E-04 7.869E-04 2140 4.370E-03 4.248E-03 SW 1372 1372 6.200E-04 6.035E-04 1372 1.640E-03 1.595E-03 1372 1.120E-02 1.088E-02 WSW 823 823 1.010E-03 9.835E-04 823 2.720E-03 2.646E-03 823 2.550E-02 2.477E-02 W 713 713 1.300E-03 1.265E-03 713 3.340E-03 3.248E-03 713 4.760E-02 4.622E-02 WNW 713 713 1.200E-03 1.168E-03 713 3.780E-03 3.676E-03 713 6.11OE-02 5.931E-02 NW 823 823 1.060E-03 1.032E-03 823 3.020E-03 2.937E-03 823 3.880E-02 3.768E-02 NNW 1481 1481 7.150E-04 6.960E-04 1481 1.930E-03 1.877E-03 1481 1.540E-02 1.496E-02 Quad Cities Site Meteorological Data 1998-2007 Quad Cities ODCM Part II

CY-QC-170-301 Revision 11 Page 226 of 307 January 2013 Table 4-6 (Page 6 of 14) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the UNRESTRICTED AREA Boundary for Kr-89 Downwind UNRESTRICTED Elevated (Stack) Release Mixed Mode (Vent) Release Ground Level Release Direction AREA Boundary Radius S S Radius V V Radius G (meters) (meters) (mrad/yr)/(pCi/sec) (meters) (mrad/yr)/(pCi/sec) (meters) (mrad/yr)/(pCi/sec) N 864 864 9.340E-04 9.077E-04 864 2.140E-03 2.080E-03 864 2.900E-03 2.817E-03 NNE 1029 1029 8.730E-04 8.485E-04 1029 1.760E-03 1.709E-03 1029 2.260E-03 2.195E-03 NE 1212 1212 4.940E-04 4.801E-04 1212 9.520E-04 9.248E-04 1212 2.040E-03 1.981E-03 ENE 1367 1367 3.270E-04 3.177E-04 1367 6.780E-04 6.586E-04 1367 1.260E-03 1.224E-03 E 1170 1170 6.010E-04 5.841E-04 1170 1.340E-03 1.302E-03 1170 2.740E-03 2.663E-03 ESE 1170 1170 6.580E-04 6.395E-04 1170 1.500E-03 1.457E-03 1170 2.770E-03 2.692E-03 SE 1189 1189 6.360E-04 6.181E-04 1189 1.260E-03 1.224E-03 1189 2.170E-03 2.108E-03 SSE 1422 1422 3.210E-04 3.119E-04 1422 5.470E-04 5.314E-04 1422 7.760E-04 7.537E-04 S 1198 1198 3.510E-04 3.411E-04 1198 6.690E-04 6.498E-04 1198 1.190E-03 1.156E-03 SSW 2140 2140 1.160E-04 1.127E-04 2140 1.900E-04 1.846E-04 2140 2.11OE-04 2.050E-04 SW 1372 1372 3.080E-04 2.993E-04 1372 6.240E-04 6.063E-04 1372 1.020E-03 9.906E-04 WSW 823 823 6.470E-04 6.288E-04 823 1.470E-03 1.428E-03 823 3.660E-03 3.555E-03 W 713 713 8.580E-04 8.338E-04 713 1.920E-03 1.865E-03 713 5.690E-03 5.527E-03 WNW 713 713 8.530E-04 8.290E-04 713 2.300E-03 2.235E-03 713 8.230E-03 7.993E-03 NW 823 823 7.210E-04 7.006E-04 823 1.660E-03 1.612E-03 823 4.070E-03 3.953E-03 NNW 1481 1481 3.540E-04 3.440E-04 1481 7.1OOE-04 6.897E-04 1481 8.070E-04 7.838E-04 Quad Cities Site Meteorological Data 1998-2007 Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 227 of 307 January 2013 Table 4-6 (Page 7 of 14) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the UNRESTRICTED AREA Boundary for Xe-1 31 m Downwind UNRESTRICTED Elevated (Stack) Release Mixed Mode (Vent) Release Ground Level Release Direction AREA Boundary Radius S S Radius V V Radius G (meters) (meters) (mrad/yr)/(pCi/sec) (meters) (mrad/yr)/(pCi/sec) (meters) (mrad/yr)/(p Ci/sec) N 864 864 2.560E-05 2.335E-05 864 1.320E-04 1.062E-04 864 1.410E-03 1.098E-03 NNE 1029 1029 2.790E-05 2.501E-05 1029 1.200E-04 9.796E-05 1029 9.160E-04 7.156E-04 NE 1212 1212 1.810E-05 1.636E-05 1212 7.530E-05 6.173E-05 1212 8.080E-04 6.318E-04 ENE 1367 1367 1.360E-05 1.209E-05 1367 5.930E-05 4.820E-05 1367 6.850E-04 5.369E-04 E 1170 1170 2.150E-05 1.902E-05 1170 1.000E-04 8.070E-05 1170 1.140E-03 8.918E-04 ESE 1170 1170 2.260E-05 2.003E-05 1170 1.100E-04 8.904E-05 1170 1.110E-03 8.684E-04 SE 1189 1189 2.230E-05 1.995E-05 1189 9.500E-05 7.738E-05 1189 7.920E-04 6.200E-04 SSE 1422 1422 1.360E-05 1.207E-05 1422 5.010E-05 4.455E-05 1422 4.450E-04 3.488E-04 S 1198 1198 1.290E-05 1.180E-05 1198 5.270E-05 4.323E-05 1198 5.810E-04 4.544E-04 SSW 2140 2140 7.710E-06 6.713E-06 2140 2.620E-05 2.127E-05 2140 2.620E-04 2.057E-04 SW 1372 1372 1.240E-05 1.122E-05 1372 5.390E-05 4.378E-05 1372 6.020E-04 4.708E-04 WSW 823 823 1.820E-05 1.701E-05 823 8.770E-05 7.091E-05 823 1.340E-03 1.043E-03 W 713 713 2.220E-05 2.059E-05 713 1.040E-04 8.369E-05 713 2.530E-03 1.965E-03 WNW 713 713 2.140E-05 2.001E-05 713 1.280E-04 1.017E-04 713 3.270E-03 2.537E-03 NW 823 823 1.970E-05 1.804E-05 823 1.OOOE-04 8.024E-05 823 2.060E-03 1.601E-03 NNW 1481 1481 1.450E-05 1.290E-05 1481 6.450E-05 5.195E-05 1481 8.560E-04 6.684E-04 Quad Cities Site Meteorological Data 1998-2007 Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 228 of 307 January 2013 Table 4-6 (Page 8 of 14) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the UNRESTRICTED AREA Boundary for Xe-1 33m Downwind UNRESTRICTED Elevated (Stack) Release Mixed Mode (Vent) Release Ground Level Release Direction AREA Boundary Radius S S Radius V V Radius G (meters) (meters) (mrad/yr)/(pCi/sec) (meters) (mrad/yr)/(pCi/sec) (meters) (mrad/yr)/(pCi/sec) N 864 864 2.060E-05 1.971E-05 864 1.060E-04 9.493E-05 864 1.190E-03 1.013E-03 NNE 1029 1029 2.240E-05 2.133E-05 1029 9.630E-05 8.752E-05 1029 7.700E-04 6.604E-04 NE 1212 1212 1.450E-05 1.383E-05 1212 6.020E-05 5.491E-05 1212 6.760E-04 5.808E-04 ENE 1367 1367 1.090E-05 1.036E-05 1367 4.740E-05 4.292E-05 1367 5.700E-04 4.913E-04 E 1170 1170 1.720E-05 1.632E-05 1170 8.060E-05 7.249E-05 1170 9.510E-04 8.176E-04 ESE 1170 1170 1.810E-05 1.718E-05 1170 8.870E-05 7.998E-05 1170 9.300E-04 8.002E-04 SE 1189 1189 1.790E-05 1.703E-05 1189 7.620E-05 6.913E-05 1189 6.620E-04 5.702E-04 SSE 1422 1422 1.100E-05 1.044E-05 1422 4.010E-05 3.645E-05 1422 3.700E-04 3.193E-04 S 1198 1198 1.040E-05 9.960E-06 1198 4.210E-05 3.843E-05 1198 4.860E-04 4.175E-03 SSW 2140 2140 6.200E-06 5.848E-06 2140 2.100E-05 1.900E-05 2140 2.160E-04 1.869E-04 SW 1372 1372 9.970E-06 9.519E-06 1372 4.320E-05 3.909E-05 1372 5.020E-04 4.312E-04 WSW 823 823 1.470E-05 1.414E-05 823 7.OOOE-05 6.307E-05 823 1.130E-03 9.624E-04 W 713 713 1.790E-05 1.723E-05 713 8.300E-05 7.423E-05 713 2.160E-03 1.829E-03 WNW 713 713 1.720E-05 1.654E-05 713 1.030E-04 9.090E-05 713 2.790E-03 2.356E-03 NW 823 823 1.580E-05 1.513E-04 823 8.030E-05 7.176E-05 823 1.750E-03 1.484E-03 NNW 1481 1481 1.160E-05 1.102E-05 1481 5.170E-05 4.638E-05 1481 7.140E-04 6.118E-04 Quad Cities Site Meteorological Data 1998-2007 Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 229 of 307 January 2013 Table 4-6 (Page 9 of 14) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the UNRESTRICTED AREA Boundary for Xe-133 Downwind UNRESTRICTED Elevated (Stack) Release Mixed Mode (Vent) Release Ground Level Release Direction AREA Boundary Radius S 1 Radius V V Radius G (meters) (meters) (mrad/yr)/(pCi/sec) (meters) (mrad/yr)/(pCi/sec) (meters) (mrad/yr)/(pCi/sec) N 864 864 1.950E-05 1.879E-05 864 1.140E-04 1.049E-04 864 1.250E-03 1.107E-03 NNE 1029 1029 2.180E-05 2.092E-05 1029 1.030E-04 9.575E-05 1029 8.120E-04 7.237E-04 NE 1212 1212 1.410E-05 1.355E-05 1212 6.460E-05 6.020E-05 1212 7.170E-04 6.530E-03 ENE 1367 1367 1.070E-05 1.025E-05 1367 5.090E-05 4.718E-05 1367 6.070E-04 5.432E-04 E 1170 1170 1.680E-05 1.608E-05 1170 8.640E-05 7.971E-05 1170 1.010E-03 9.022E-04 ESE 1170 1170 1.770E-05 1.695E-05 1170 9.530E-05 8.809E-05 1170 9.840E-04 8.795E-04 SE 1189 1189 1.750E-05 1.679E-05 1189 8.180E-05 7.841E-05 1189 7.030E-04 6.289E-04 SSE 1422 1422 1.070E-05 1.025E-05 1422 4.300E-05 3.997E-05 1422 3.940E-04 3.532E-04 S 1198 1198 9.960E-06 9.608E-06 1198 4.520E-05 4.214E-05 1198 5.150E-04 4.597E-04 SSW 2140 2140 6.150E-06 5.863E-06 2140 2.250E-05 2.083E-05 2140 2.320E-04 2.083E-04 SW 1372 1372 9.680E-06 9.314E-06 1372 4.640E-05 4.298E-05 1372 5.330E-04 4.759E-04 WSW 823 823 1.370E-05 1.327E-05 823 7.500E-05 6.927E-05 823 1.190E-03 1.054E-03 W 713 713 1.640E-05 1.589E-05 713 8.890E-05 8.160E-05 713 2.250E-03 1.982E-03 WNW 713 713 1.590E-05 1.540E-05 713 1.100E-04 9.997E-05 713 2.900E-03 2.548E-03 NW 823 823 1.480E-05 1.394E-05 823 8.600E-05 7.893E-05 823 1.830E-03 1.615E-03 NNW 1481 1481 1.130E-05 1.083E-05 1481 5.560E-05 5.121E-05 1481 7.580E-04 6.752E-04 Quad Cities Site Meteorological Data 1998-2007 Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 230 of 307 January 2013 Table 4-6 (Page 10 of 14) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the UNRESTRICTED AREA Boundary for Xe-1 35m Downwind UNRESTRICTED Elevated (Stack) Release Mixed Mode (Vent) Release Ground Level Release Direction AREA Boundary Radius S S Radius V V Radius G I - (meters) (meters) (mrad/yr /(pCi/sec) (meters) (mrad/yr)/(pCi/sec) (meters) (mrad/yr)/(pCi/sec) N 864 864 2.81E-04 2.717E-04 864 8.08E-04 7.802E-04 864 1.78E-03 1.715E-03 NNE 1029 1029 2.78E-04 2.687E-04 1029 7.09E-04 6.848E-04 1029 1.34E-03 1.291E-03 NE 1212 1212 1.72E-04 1.662E-04 1212 4.24E-04 4.096E-04 1212 1.21E-03 1.166E-03 ENE 1367 1367 1.20E-04 1.161E-04 1367 3.19E-04 3.081E-04 1367 7.87E-04 7.587E-04 E 1170 1170 2.03E-04 1.962E-04 1170 5.72E-04 5.523E-04 1170 1.60E-03 1.542E-03 ESE 1170 1170 2.17E-04 2.098E-04 1170 6.29E-04 6.074E-04 1170 1.59E-03 1.532E-03 SE 1189 1189 2.14E-04 2.069E-04 1189 5.42E-04 5.235E-04 1189 1.27E-03 1.224E-03 SSE 1422 1422 1.21E-04 1.170E-04 1422 2.64E-04 2.550E-04 1422 4.86E-04 4.685E-04 S 1198 1198 1.25E-04 1.208E-04 1198 3.OOE-04 2.897E-04 1198 6.82E-04 6.573E-04 SSW 2140 2140 5.40E-05 5.220E-05 2140 1.1OE-04 1.062E-04 2140 1.46E-04 1.407E-04 SW 1372 1372 1.13E-04 1.093E-04 1372 2.91E-04 2.810E-04 1372 6.29E-04 6.062E-04 WSW 823 823 2.02E-04 1.954E-04 823 5.65E-04 5.456E-04 823 2.06E-03 1.984E-03 W 713 713 2.62E-04 2.533E-04 713 7.11E-04 6.864E-04 713 3.46E-03 3.331E-03 WNW 713 713 2.51E-04 2.427E-04 713 8.27E-04 7.977E-04 713 5.08E-03 4.890E-03 NW 823 823 2.19E-04 2.117E-04 823 6.35E-04 6.130E-04 823 2.60E-03 2.504E-03 NNW 1481 1481 1.31E-04 1.266E-04 1481 3.40E-04 3.283E-04 1481 5.73E-04 5.522E-04 Quad Cities Site Meteorological Data 1998-2007 Quad Cities ODCM Part I1

CY-QC-1 70-301 Revision 11 Page 231 of 307 January 2013 Table 4-6 (Page 11 of 14) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the UNRESTRICTED AREA Boundary for Xe-1 35 Downwind UNRESTRICTED Elevated (Stack) Release Mixed Mode (Vent) Release Ground Level Release Direction AREA Boundary Radius S S Radius V V Radius G (meters) (meters) (mrad/yr)/(pCi/sec) (meters) (mrad/yr)/(pCi/sec) (meters) (mrad/yr)/(pCi/sec) N 864 864 1.720E-04 1.664E-04 864 6.060E-04 5.860E-04 864 4.430E-03 4.278E-03 NNE 1029 1029 1.760E-04 1.703E-04 1029 5.500E-04 5.320E-04 1029 2.950E-03 3.729E-03 NE 1212 1212 1.150E-04 1.113E-04 1212 3.570E-04 3.453E-04 1212 2.640E-03 2.549E-03 ENE 1367 1367 8.430E-05 8.158E-05 1367 2.800E-04 2.708E-04 1367 2.220E-03 2.146E-03 E 1170 1170 1.340E-04 1.297E-04 1170 4.630E-04 4.477E-04 1170 3.680E-03 3.555E-03 ESE 1170 1170 1.410E-04 1.365E-04 1170 5.050E-04 4.884E-04 1170 3.580E-03 3.459E-03 SE 1189 1189 1.400E-04 1.355E-04 1189 4.410E-04 4.265E-04 1189 2.600E-03 2.511E-03 SSE 1422 1422 8.460E-05 8.187E-05 1422 2.370E-04 2.293E-04 1422 1.430E-03 1.382E-03 S 1198 1198 8.430E-05 8.159E-05 1198 2.530E-04 2.447E-04 1198 1.850E-03 1.787E-03 SSW 2140 2140 4.550E-05 4.403E-05 2140 1.210E-04 1.171E-04 2140 8.100E-04 7.827E-04 SW 1372 1372 7.890E-05 7.636E-05 1372 2.520E-04 2.438E-04 1372 1.920E-03 1.854E-03 WSW 823 823 1.250E-04 1.210E-04 823 4.250E-04 4.11OE-04 823 4.230E-03 4.086E-03 W 713 713 1.580E-04 1.529E-04 713 5.200E-04 5.028E-04 713 7.800E-03 7.531E-03 WNW 713 713 1.500E-04 1.452E-04 713 6.020E-04 5.820E-04 713 1.OOOE-02 9.652E-03 NW 823 823 1.340E-04 1.297E-04 823 4.760E-04 4.603E-04 823 6.390E-03 6.170E-03 NNW 1481 1481 9.170E-05 8.874E-05 1481 3.OOOE-04 2.900E-04 1481 2.660E-03 2.569E-03 Quad Cities Site Meteorological Data 1998-2007 Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 232 of 307 January 2013 Table 4-6 (Page 12 of 14) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the UNRESTRICTED AREA Boundary for Xe-1 37 Downwind UNRESTRICTED Elevated (Stack) Release Mixed Mode (Vent) Release Ground Level Release Direction AREA Boundary Radius S S Radius V V Radius G (meters) (meters) (mrad/yr)/(pCi/sec) (meters) (mrad/yr)/(pCi/sec) (meters) (mrad/yr)/(pCi/sec) N 864 864 8.120E-05 7.860E-05 864 1.920E-04 1.859E-04 864 1.680E-04 1.626E-04 NNE 1029 1029 7.510E-05 8.301E-05 1029 1.530E-04 1.480E-04 1029 1.400E-04 1.354E-04 NE 1212 1212 4.070E-05 3.940E-05 1212 7.680E-05 7.433E-05 1212 1.280E-04 1.238E-04 ENE 1367 1367 2.630E-05 2.546E-05 1367 5.220E-05 5.051E-05 1367 7.280E-05 7.044E-05 E 1170 1170 5.060E-05 4.899E-05 1170 1.130E-04 1.093E-04 1170 1.740E-04 1.684E-04 ESE 1170 1170 5.610E-05 5.431E-05 1170 1.270E-04 1.229E-04 1170 1.810E-04 1.751E-04 SE 1189 1189 5.350E-05 5.179E-05 1189 1.040E-04 1.006E-04 1189 1.390E-04 1.345E-04 SSE 1422 1422 2.550E-05 2.468E-05 1422 4.11OE-05 3.978E-05 1422 4.450E-05 4.306E-05 S 1198 1198 2.840E-05 2.749E-05 1198 5.360E-05 5.187E-05 1198 7.750E-05 7.499E-05 SSW 2140 2140 7.940E-06 7.686E-06 2140 1.130E-05 1.094E-05 2140 9.630E-06 9.317E-06 SW 1372 1372 2.480E-05 2.401E-05 1372 4.870E-05 4.713E-05 1372 5.980E-05 5.786E-05 WSW 823 823 5.490E-05 5.315E-05 823 1.290E-04 1.249E-04 823 2.430E-04 2.351E-04 W 713 713 7.260E-05 7.028E-05 713 1.720E-04 1.665E-04 713 3.310E-04 3.203E-04 WNW 713 713 7.380E-05 7.145E-05 713 2.11OE-04 2.042E-04 713 4.720E-04 4.567E-04 NW 823 823 6.200E-05 6.001E-05 823 1.480E-04 1.432E-04 823 2.180E-04 2.11OE-04 NNW 1481 1481 2.840E-05 2.749E-05 1481 5.440E-05 5.265E-05 1481 3.380E-05 3.271E-05 Quad Cities Site Meteorological Data 1998-2007 Quad Cities ODCM Part II

CY-QC-170-301 Revision 11 Page 233 of 307 January 2013 Table 4-6 (Page 13 of 14) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the UNRESTRICTED AREA Boundary for Xe-1 38 Downwind UNRESTRICTED Elevated (Stack) Release Mixed Mode (Vent) Release Ground Level Release Direction AREA Boundary Radius S S Radius V V Radius G (meters) (meters) (mrad/yr /(pCi/sec) (meters) (mrad/yr /(pCi/sec) (meters) (mrad/yr)/(pCi/sec) N 864 864 8.32E-04 1.027E-03 864 2.38E-03 2.311E-03 864 9.47E-03 9.192E-03 NNE 1029 1029 8.32E-04 8.086E-04 1029 2.14E-03 2.079E-03 1029 6.45E-03 6.261E-03 NE 1212 1212 5.38E-04 5.229E-04 1212 1.36E-03 1.321E-03 1212 5.64E-03 5.474E-03 ENE 1367 1367 3.89E-04 3.780E-04 1367 1.06E-03 1.030E-03 1367 4.07E-03 3.950E-03 E 1170 1170 6.27E-04 6.093E-04 1170 1.79E-03 1.739E-03 1170 7.70E-03 7.475E-03 ESE 1170 1170 6.60E-04 6.413E-04 1170 1.95E-03 1.893E-03 1170 7.56E-03 7.338E-03 SE 1189 1189 6.57E-04 6.384E-04 1189 1.70E-03 1.652E-03 1189 5.78E-03 5.610E-03 SSE 1422 1422 3.90E-04 3.789E-04 1422 8.88E-04 8.624E-04 1422 2.51E-03 2.436E-03 S 1198 1198 3.97E-04 3.857E-04 1198 9.70E-04 9.422E-04 1198 3.44E-03 3.337E-03 SSW 2140 2140 1.95E-04 1.894E-04 2140 4.20E-04 4.080E-04 2140 8.68E-04 8.427E-04 SW 1372 1372 3.65E-04 3.547E-04 1372 9.54E-04 9.265E-04 1372 3.33E-03 3.231E-03 WSW 823 823 6.14E-04 5.967E-04 823 1.69E-03 1.641E-03 823 9.85E-03 9.558E-03 W 713 713 7.93E-04 7.707E-04 713 2.1OE-03 2.040E-03 713 1.81E-02 1.756E-02 WNW 713 713 7.42E-04 7.211E-04 713 2.39E-03 2.321E-03 713 2.46E-02 2.387E-02 NW 823 823 6.56E-04 6.375E-05 823 1.89E-03 1.835E-03 823 1.40E-02 1.359E-02 NNW 1481 1481 4.21E-04 4.091E-04 1481 1.12E-03 1.088E-03 1481 3.76E-03 3.649E-03 Quad Cities Site Meteorological Data 1998-2007 Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 234 of 307 January 2013 Table 4-6 (Page 14 of 14) Maximum Offsite Finite Plume Gamma Dose Factors Based on 1 cm Depth at the UNRESTRICTED AREA Boundary for Ar-41 Downwind UNRESTRICTED Elevated (Stack) Release Mixed Mode (Vent) Release Ground Level Release Direction AREA Boundary Radius S S Radius V V Radius G (meters) (meters) (mrad/yr)/(pCi/sec) (meters) (mrad/yr /(pCi/sec) (meters) (mrad/yr)/(pCi/sec) N 864 864 9.99E-04 9.670E-04 864 2.72E-03 2.633E-03 864 1.48E-02 1.433E-02 NNE 1029 1029 9.94E-04 9.622E-04 1029 2.47E-03 2.391E-03 1029 9.93E-03 9.611E-03 NE 1212 1212 6.48E-04 6.273E-04 1212 1.60E-03 1.549E-03 1212 8.79E-03 8.509E-03 ENE 1367 1367 4.71E-04 4.559E-04 1367 1.25E-03 1.210E-03 1367 7.01E-03 6.786E-03 E 1170 1170 7.54E-04 7.299E-04 1170 2.08E-03 2.013E-03 1170 1.22E-02 1.181E-02 ESE 1170 1170 7.90E-04 7.647E-04 1170 2.25E-03 2.178E-03 1170 1.19E-02 1.152E-02 SE 1189 1189 7.88E-04 7.628E-04 1189 1.98E-03 1.917E-03 1189 8.78E-03 8.498E-03 SSE 1422 1422. 4.71E-04 4.559E-04 1422 1.06E-03 1.026E-03 1422 4.44E-03 4.297E-03 S 1198 1198 4.82E-04 4.665E-04 1198 1.14E-03 1.103E-03 1198 5.89E-03 5.701E-03 SSW 2140 2140 2.42E-04 2.343E-04 2140 5.23E-04 5.063E-04 2140 2.07E-03 2.004E-03 SW 1372 1372 4.43E-04 4.288E-04 1372 1.13E-03 1.094E-03 1372 5.94E-03 5.750E-03 WSW 823 823 7.42E-04 7.183E-04 823 1.95E-03 1.888E-03 823 1.46E-02 1.413E-02 W 713 713 9.61E-04 2.922E-03 713 2.41E-03 2.334E-03 713 2.69E-02 2.603E-02 WNW 713 713 8.94E-04 8.654E-04 713 2.74E-03 2.652E-03 713 3.52E-02 3.407E-02 NW 823 823 7.89E-04 7.638E-04 823 2.17E-03 2.101E-03 823 2.16E-02 2.090E-02 NNW 1481 1481 5.11E-04 1.432E-04 1481 1.32E-03 1.277E-03 1481 7.72E-03 7.474E-03 Quad Cities Site Meteorological Data 1998-2007 Quad Cities ODCM Part II

CY-QC-170-301 Revision 11 Page 235 of 307 January 2013 Table 4-7 Parameters for Calculations of N-16 Skyshine Radiation From Quad Cities Location Occupancy Occupancy Shielding Distance Number Activity Hours Factor Factor Rk K OHka OFk SFk (m) Living at home 1 (nearest 8616 0.9836 0.7 800b resident) 2 Fishing 36 0.00410 1.0 2330 3 Fishing 51 0.00586 1.0 344c 4 Fishing 31 0.00351 1.0 361c 5 Fishing 26 0.00293 1.0 680c Mh = 3' K = 3.80 E-5 mrem / (MWe-hr) These parameters are used to obtain an initial estimate of skyshine dose to the maximally exposed member of the public using ODCM Part II, Section 5.0, Equation 5-1. If desired, more realistic parameters could be used in place of these to refine the estimate. For example, one could determine whether the nearest resident really fishes the specified number of hours at the specified location. Notes: a The amount of time in a year that a maximally exposed fisherman would spend fishing near the site is estimates as 12 hours per week for 8 months per year. This yields an estimate of: C 12 Hours ",.er Week

                                                       ,,months 1

weeks ear )

                                                                            =6 y~(otis~K hours ear b        Distance to nearest residence. (See Table 4-1) c        Estimated from drawings of the site.

d The OFk is the quotient of the number of hours a location is occupied and the number of hours in a year. Thus, OHk /8760 hours = OFk rounded to the nearest 0.01 digit. e Multiplication factor for hydrogen addition from Reference 6. Refer to equation 5-1. Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 236 of 307 January 2013 Table 4-8 (page 1 of 2) Elevated Joint Frequency Distribution Table Summaries 296 Foot Elevation Data

SUMMARY

TABLE OF PERCENT BY DIRECTION AND CLASS CLASS N NNE NE ENE E ESE SE SSE 5 SSW SW WSW W WNW NW NNW ITOTAL A 0.196 0.186 0.181 0.177 0.144 0.163 0.263 0.512 0.647 1.194 0.452 0.393 0.566 0.592 0.592 0.350 6.608 B 0.220 0.221 0.255 0.219 0.190 0.226 0.252 0.354 0.334 0.609 0.394 0.330 0.481 0.521 0.489 0.340 5.473

-C       0.301 0.274      0.309 0.291    0.289  0.288 0.262 0.403 0.367 ,0.644 0.454      0.403 0.611   0.634  0.620 0.411      6.562 D     2.068 1.620      2.517 2.364    2.317  2.078 1.603 1.589 1.807 2.139 2.179       2.208 3.828   4.737  4.276 12.362    39.693 E      1.070 0.865     0.951 1.149   _1.267   1.507'1.468    1.889 2.607 3.044 2.224   1.405 ,1.669  1.578  1.720 1.327     25.738 F     0.397 0.456      0.478 0.411    0.562  0.823 1.072 1.185 1.444 1.244 0.579       0.387 0.457   0.430  0.488 0.449     10.861 G    10.178 0.158      0.169 0.171    0.214  0.262 10.498 0.629 .0.743 0.769 .0.389    0.193 0.202   0.200  0.176 0.147      5.100 TOTAL 14.430 3.780         4.859 14.783   4.983  5.3461 5.418 6.562 17.949 19.645 66.72    5.319 7.813   8.692  8.362 5.386   100.000

SUMMARY

TABLE OF PERCENT BY DIRECTION AND SPEED SPEED N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL 0.5 0.001 0.003 0.001 0.001 0.000 0.001 0.002 0.001 0.001 0.000 0.000 0.000 0.002 0.000 0.001 0.000 0.016 1.0 10.030 0.037 0.031 0.042 0.042 0.034 0.024 0.038 0.040 0.028 0.027 0.041 0.047 0.033 0.028 0.021 0.543

-1.5     0.082 0.083 0.072 0.105 0.140 0.117 0.084              0.075 0.090 0.098 0.115 0.125 0.106     0.091  0.086  0.089     1.556 2.0    0.147 0.149 0.146 0.131 0.226 0.151 0.141              0.155 0.156 0.191 0.230 0.223 0.235     0.195 10.186  0.1551    2.816 3.0    0.491 0.461 0.485 0.565 0.682 0.498 0.474              0.500 0.482 0.648 0.653 0.495 0.608     0.578  0.672  0.591     8.883 4.0     0.667 0.593 0.671 0.658 0.766 0.604 0.627              0.694 0.623 0.813 0.721 0.567 0.747     0.650  0.776  0.733    10.911 5.0    0.815 0.743 0.760 0.718 0.999 0.684 0.784              1.037 0.951 1.150 0.916 0.774 1.011     0.968  1.032  0.833    14.175
-6.0     0.827 0.662 0.827 0.872 0.825 0.830 0.946              1.193 1.253 1.531 0.987 0.894 1.247     1.264  1.563  1.022    16.742 7.0    1.004 0.712 1.150 1.066 0.915 1.404 1.537              1.791 2.572 2.912 1.782 1.383 12.065    2.506  2.378  1.404    26.582 8.0     0.281 0.251 0.488 0.413 0.306 0.667 0.615              0.722 1.184 1.461 0.880 0.524 1.042     1.433  1.116  0.396    11.780 99.0    0.086 0.085 0.227 0.213 0.083 0.358 0.183              0.354 0.598 0.812 0.362 0.294 0.703     0.973  0.522  0.142     5.995 TOTAL 14.430 3.780 14.859 14.783 14.983 15.346 15.418           16.562 7.949 9.645 6.672 5.319 7.813     8.692  8.362  5.386  100d.000-R-QUAD CITIES METEOROLOGICAL DATA 1998-2007 NOTE: WIND DIRECTIONS IN TABLES ARE PRESENTED IN "WIND FROM" AND NOT "WIND TO" DIRECTIONS Quad Cities ODOM Part 11

CY-QC-1 70-301 Revision 11 Page 237 of 307 January 2013 Table 4-8 (page 2 of 2) Elevated Joint Frequency Distribution Table Summaries 296 Foot Elevation Data Summary Table of Percent by Speed and Class Class Speed A B C D E F G 0.5 0.000 0.000 0.000 0.003 0.005 0.005 0.003 1.0 0.000 0.000 0.007 0.199 0.094 0.127 0.115 1.5 0.009 0.042 0.097 0.677 0.294 0.217 0.220 2.0 0.092 0.195 0.337 1.170 0.440 0.357 0.226 3.0 0.593 0.813 1.117 3.209 1.526 0.944 0.679 4.0 0.907 0.809 1.034 3.809 2.303 1.283 0.768 5.0 1.113 0.957 0.954 4.743 3.651 1.894 0.865 6.0 1.192 0.785 0.816 6.003 4.760 2.237 0.949 7.0 1.670 1.032 1.244 10.123 8.165 3.204 1.143 8.0 0.727 0.545 0.614 5.950 3.259 0.555 0.129 99.0 0.305 0.259 0.341 3.807 1.241 0.040 0.002 Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 238 of 307 January 2013 Figure 4-1 Graphical Representation of Deposition Rate and Joint Frequency Data - 296' N 25 NNW NNE 20 NW., NE 15 WNW ,. . ENE W E WSW,- ESE SW " /S

                                               //                             SE 55 SSE S                              .--AD0O (E-10)

Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 239 of 307 January 2013 Table 4-9 (Page 1 of 2) Mixed Mode Joint Frequency Distribution Table Summaries 196 Foot Elevation Data S~~~~

SUMMARY

TABLE OF PERCENT BY DIRECTION AND CLASS ______ CLASS N NNE NE ENE E ESE SE SSE S SSW ISW WSW IW WNW NW INNW TOTAL A 0.385 0.400 0.424 0.393 0.291 0.385 0.430 0.881 0.899 1.678 0.663 0.532 1.001 1.064 1.049 0.640 11.111 B 0.107 0.114 0.118 0.127 0.083 0.122 0.130 0.166 0.138 0.284 0.183 0.147 0.283 0.264 0.266 0.161 2.693 C 0.285 0.249 0.309 0.234 0.258 0.295 0.251 0.323 0.309 0.549 0.387 0.397 0.618 0.569 0.540 0.352 5.928 D 1.823 1.449 12.347 2.090 12.050 1.877 1.308 11.252 1.397 1.740 1.816 2.141 3.732 4.577 3.635 1.896 35.130 E 1.053 0.728 1.053 1.316 1.358 1.741 1.401 1.766 2.453 2.765 2.263 ,1.661 1.938 1.978 1.920 1.235 26.629 F 0.367 0.414 0.451 0.451 0.571 0.923 0.944 1.182 1.363 1.075 0.438 0.323 0.402 0.453 0.437 0.407 10.201 1 0.258 0.287 0.298 0.292 0.428 0.627 0.988 1.126 1.183 0.976 0.499 0.294 0.329 0.26 0.2 023 839 TOTAL 14.278 3.640 5.001 14.903 5.039 15.970 5.453 6.696 17.742 9.066 6.249 5.497 ý8.303 19.167 8.070 4.9271 100.000.

SUMMARY

TABLE OF PERCENT BY DIRECTION AND SPEED SPEED N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL 0.5 0.000 0.001 0.001 0.000 0.002 0.003 0.001 0.000 0.002 0.000 0.007 0.002 0.00 1 0.000 0.003 0.003 0.029 1.0 0.057 0.056 0.048 0.045 0.050 0.054 0.044 0.054 0.054 0.045 0.063 0.067 0.063 0.058 0.050 0.057 0.864 1.5 0.115 0.115 0.127 0.146 0.158 0.132 0.134 0.120 0.130 0.123 0.175 0.176 0.171 0.156 0.144 0.111 2.234

-2.0      0.178  0.183 10.216 0.217 10.305 0.219 0.205 10.195 0.188 10.264 0.304 0.305 0.330           10.299    0.257  0.238     3.901 3.0     0.675  0.586 0.680 0.757 0.875 0.666 0.720 0.750 0.699 0.861 0.930 10.770 0.932               0.870    0.967  0.819    12.557 4.0      0.859  0.717 0.897 0.927 1.131 0.949 0.977 1.220 1.007 1.302 1.057 0.999 1.302                1.308    1.308  0.934    16.893 5.0     0.938  0.758 0.985 0.991 0.927 1.094 1.140 1.345 1.358 1.624 1.096 1.084 1.578                1.532    1.678  1.015    19.143
-6.0      0.740  0.599 0.847 0.775 0.700 1.052 0.983 1.170 1.433 1.600 0.940 0.893 1.310                1.491    1.336  0.841    16.711 7.0     0.532  0.436 10.804 0.678 10.635 1.133 0.890 1.179 1.792 2.066 1.203 0.827 ,1.538             1.992    1.550  0.706    17.960 8.0     0.165  0.158 0.311 0.2801 0.203 0.436 0.271          0.460 0.742 0.848 0.373 0.233 0.659      0.987    0.599  0.167     6.890 99.0     0.019  0.032 0.086 0.088 0.054 0.232 0.088 0.202 0.337 0.333 0.102 0.139 0.418                0.474    0.177  0.036     2.817 TOTAL      4.278  3.640 5.001 4.903 15.03-9 5905436967429.066                       6.249 5.497 8.303    9.6      807    492     1000 QUAD CITIES METEOROLOGICAL DATA 1998-2007 NOTE: WIND DIRECTIONS IN TABLES ARE PRESENTED IN "WIND FROM" AND NOT "WIND TO" DIRECTIONS Quad Cities 00CMV Part 11

CY-QC-1 70-301 Revision 11 Page 240 of 307 January 2013 Table 4-9 (Page 2 of 2) Mixed Mode Joint Frequency Distribution Table Summaries 196 Foot Elevation Data Summary Table of Percent by Speed and Class Class Speed A B C D E F G 0.5 0.000 0.000 0.000 0.003 0.008 0.003 0.014 1.0 0.000 0.000 0.009 0.269 0.152 0.131 0.304 1.5 0.041 0.022 0.096 0.891 0.372 0.294 0.518 2.0 0.189 0.098 0.381 1.548 0.682 0.394 0.608 3.0 1.151 0.491 1.335 3.805 2.660 1.451 1.665 4.0 1.835 0.507 0.966 4.567 4.580 2.386 2.051 5.0 2.068 0.466 0.881 5.500 5.763 2.634 1.832 6.0 1.992 0.355 0.742 5.799 5.117 1.740 0.967 7.0 2.519 0.481 0.913 7.684 4.952 1.073 0.338 8.0 0.959 0.183 0.446 3.454 1.748 0.088 0.012 99.0 0.358 0.089 0.159 1.609 0.594 0.007 0.000 Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 241 of 307 January 2013 Figure 4-2 Graphical Representation of Deposition Rate and Joint Frequency Data - 196' N NNW,, 10 /"NNE VNW- . , . N..

                                                                           ./*E   N NW                                          N      ENE
                                                                                           .7"- %Time
                        'A
                                                                                           -o-  D/Q (E-09) 5W II                                                ESE SW                                       SE SSW"ý                     SS5E S

Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 242 of 307 January 2013 Table 4-10 (Page 1 of 2) Ground Level Joint Frequency Distribution Table Summaries 33 Foot Elevation Data CHRIMMADV TA921 C nC DCDfCK1T 1V FlIDEITifKM AKIn t'I A4Z CLASS N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL A 0.423 0.401 0.418 0.462 0.308 0.417 0.508 0.886 0.660 1.377 1.141 0.613 1.151 1.014 0.983 0.628 11.391 B 0.131 0.114 0.114 0.140 0.097 0.137 0.147 0.137 0.108 0.225 0.256 0.188 0.317 0.250 0.252 0.145 2.758 C 0.314 0.225 0.304 0.295 0.277 0.314 0.288 0.303 0.243 0.429 0.546 0.441 0.691 0.523 0.543 0.345 6.080 D 2.092 1.387 2.311 2.311 2.192 2.000 1.471 1.124 1.036 1.403 2.238 2.561 4.180 4.655 3.453 1.708 36.122 E 0.894 0.704 1.190 1.569 1.453 1.843 1.735 1.649 1.914 2.009 2.846 1.959 2.296 2.056 1.876 1.131 27.124 F 0.325 0.385 0.464 0.486 0.791 1.464 1.071 0.951 0.659 0.603 0.390 0.327 0.618 0.589 0.422 0.309 9.853 G 0.191 0.195 0.227 0.287 0.894 1.851 0.682 0.458 0.327 0.190 0.189 0.164 0.306 0.404 0.169 0.138 6.672 TOTAL 4.370 3.411 5.029 5.551 6.012 8.025 5.902 5.507 4.946 6.236 7.606 6.254 9.559 9.490 7.698 4.404 100.000

SUMMARY

TABLE OF PERCENT BY DIRECTION AND SPEED SPEED N NNE NE ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW TOTAL 0.5 0.048 0.051 0.049 0.038 0.054 0.045 0.036 0.024 0.039 0.030 0.024 0.036 0.027 0.034 0.043 0.054 0.630 1.0 0.457 0.468 0.535 0.648 1.184 1.265 1.081 0.986 0.810 0.526 0.526 0.610 0.768 0.710 0.460 0.397 11.429 1.5 0.421 0.448 0.691 0.723 1.049 1.792 1.250 1.080 0.775 0.812 0.867 0.889 1.202 1.185 0.864 0.510 14.557 2.0 0.572 0.399 0.724 0.876 0.833 1.423 1.009 0.992 0.900 0.984 1.252 1.044 1.420 1.277 1.198 0.669 15.574 3.0 1.226 0.904 1.359 1.625 1.345 1.839 1.454 1.581 1.588 2.242 2.776 1.889 2.637 2.191 2.475 1.453 28.585 4.0 0.967 0.644 0.902 0.937 0.811 0.835 0.722 0.649 0.636 1.271 1.509 0.989 1.801 1.767 1.494 0.845 16.779 5.0 0.426 0.300 0.441 0.432 0.477 0.443 0.260 0.166 0.161 0.295 0.476 0.485 0.946 1.299 0.742 0.350 7.698 6.0 0.196 0.141 0.251 0.204 0.190 0.220 0.064 0.026 0.034 0.068 0.118 0.165 0.459 0.699 0.333 0.092 3.261 7.0 0.058 0.055 0.077 0.067 0.069 0.153 0.026 0.004 0.002 0.008 0.044 0.113 0.265 0.326 0.086 0.034 1.387 8.0 0.001 0.000 0.000 0.001 0.001 0.010 0.000 0.000 0.000 0.000 0.014 0.033 0.033 0.001 0.002 0.000 0.097 99.0 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.000 0.001 0.000 0.000 0.000 0.000 0.000 0.001 TOTAL 4.370 3.411 5.029 5.551 6.012 8.025 5.902 5.507 4.946 6.236 7.606 6.254 9.559 9.490 7.698 4.404 100.000 f'.l IA r* f'lI~r--o F hAlT*- l'l f'*BI* P"*'*I' l l*AIr"A A ..W rf '*,"* rvP"7

                                            *UMJ      LI I I-3   IVlE I          J' L   U      M1L/-*L UM IM'*   I  O--UU/

NOTE: WIND DIRECTIONS IN TABLES ARE PRESENTED IN "WIND FROM" AND NOT "WIND TO" DIRECTIONS Quad Cities ODCM Part II

CY-QC-170-301 Revision 11 Page 243 of 307 January 2013 Table 4-10 (Page 2 of 2) Ground Level Joint Frequency Distribution Table Summaries 33 Foot Elevation Data Summary Table of Percent by Speed and Class Class Speed A B C D E F G 0.5 0.000 0.000 0.000 0.014 0.052 0.147 0.416 1.0 0.002 0.000 0.012 0.867 2.767 3.859 3.922 1.5 0.101 0.080 0.320 3.212 5.544 3.595 1.705 2.0 0.813 0.385 1.183 4.980 6.187 1.550 0.474 3.0 4.476 1.172 2.289 11.357 8.488 0.654 0.150 4.0 3.777 0.623 1.257 8.180 2.896 0.043 0.004 5.0 1.490 0.341 0.612 4.404 0.850 0.001 0.000 6.0 0.594 0.087 0.296 2.040 0.243 0.001 0.000 7.0 0.136 0.069 0.111 0.973 0.097 0.001 0.001 8.0 0.001 0.001 0.001 0.094 0.000 0.000 0.000 99.0 0.000 0.000 0.000 0.001 0.000 0.000 0.000 Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 244 of 307 January 2013 Figure 4-3 Rate and Joint Frequency Data - 33' Graphical Representation of Deposition N T%of "me 20 D/Q (E-09) NNW "NNE - NW. 15,. NE

                                                                             /

WNW

""-,. \ 10 / /

ENE W5W WSW ENE WSW <- ESE SW' SE SSE S Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 245 of 307 January 2013 Table 4-11 Station Characteristics STATION: Quad Cities LOCATION: Cordova, Illinois CHARATERISTICS OF ELEVATED RELEASE POINT

1) Release Height = 94.49 m 2) Diameter = 3.35 m

3) Exit Speed = 16.0 m/s 4) Heat Content = 68 Kcal/s CHARATERISTICS OF VENT STACK RELEASE POINT: NOT APPLICABLE

1) Release Height = 48.5 ma Diameter = 2.74 m

3) Exit Speed = 14.8 m/sa CHARATERISTICS OF GROUND LEVEL RELEASE

1) Release Height = 0 m

2) Building Factor (D) = 43.46 ma METEOROLOGICAL DATA A 296 foot tower is located 1623 meters SSE of elevated release point.

Release Point Wind Speed & Direction Differential Temperature Elevated 296 ft I 296 - 33 ft Vent 196 ft 196 - 30 ft Ground 33 ft 196 - 30 ft a Used in calculating the meteorological and dose factors in Table 4-3 through Table 4-6. Also used in calculating dispersion and deposition factors for cow milk, cow meat, and nearest resident data in site specific procedures. Quad Cities ODCM Part II

CY-QC-170-301 Revision 11 Page 246 of 307 January 2013 Table 4-12 Dose Factors for Noble Gases Beta Air Beta Skin Gamma Air Gamma Total Dose Factor Dose Factor Dose Factor Body Dose Factor Ni Li Mi Ki Nuclide (mrad/yr per (mrem/yr per (mrad/yr per (mrem/yr per uCi/m 3 ) uCi/m 3) uCi/m 3 ) uCi/m 3) Kr-83m 2.88E+02 1.93E+01 7.56E-02 Kr-85m 1.97E+03 1.46E+03 1.23E+03 1.17E+03 Kr-85 1.95E+03 1.34E+03 1.72E+01 1.61 E+01 Kr-87 1.03E+04 9.73E+03 6.17E+03 5.92E+03 Kr-88 2.93E+03 2.37E+03 1.52E+04 1.47E+04 Kr-89 1.06E+04 1.01 E+04 1.73E+04 1.66E+04 Kr-90 7.83E+03 7.29E+03 1.63E+04 1.56E+04 Xe-1 31m 1.11E+03 4.76E+02 1.56E+02 9.15E+01 Xe-1 33m 1.48E+03 9.94E+02 3.27E+02 2.51 E+02 Xe-1 33 1.05E+03 3.06E+02 3.53E+02 2.94E+02 Xe-1 35m 7.39E+02 7.11 E+02 3.36E+03 3.12E+03 Xe-1 35 2.46E+03 1.86E+03 1.92E+03 1.81 E+03 Xe-137 1.27E+04 1.22E+04 1.51 E+03 1.42E+03 Xe-138 4.75E+03 4.13E+03 9.21 E+03 8.83E+03 Ar-41 3.28E+03 2.69E+03 9.30E+03 8.84E+03 Source: Table B-1 of Reference 6. Quad Cities ODCM Part II

CY-QC-170-301 Revision 11 Page 247 of 307 January 2013 Table 4-13 (Page 1 of 3) External Dose Factors for Standing on Contaminated Ground DFGij (mrem/hr per pCi/m 2 ) Whole Body Element Dose Factor Reference Element Dose Factor Reference H-3 0.00E+00 6 Be-7 5.95E-10 99 C-14 0.00E+00 6 F-18 1.19E-08 99 Na-22 2.42E-08 99 Na-24 2.50E-08 6 Mg-27 1.14E-08 99 Mg-28 1.48E-08 99 AI-26 2.95E-08 99 AI-28 2.OOE-08 99 P-32 0.OOE+00 6 C0-38 1.70E-08 99 Ar-41 1.39E-08 99 K-40 2.22E-09 99 K-42 4.64E-09 99 K-43 1.19E-08 99 Ca-47 1.14E-08 99 Sc-44 2.50E-08 99 Sc-46m 1.21E-09 99 Sc-46 2.24E-08 99 Sc-47 1.46E-09 99 Ti-44 1.95E-09 99 V-48 3.21 E-08 99 Cr-51 2.20E-10 6 Mn-52m 2.79E-08 99 Mn-52 3.80E-08 99 Mn-54 5.80E-09 6 Mn-56 1.10E-08 6 Fe-52 9.12E-09 99 Fe-55 0.00E+00 6 Fe-59 8.00E-09 6 Co-57 1.65E-09 99 Co-58 7.OOE-09 6 Co-60 1.70E-08 6 Ni-63 0.OOE+00 6 Ni-65 3.70E-09 6 Cu-64 1.50E-09 6 Cu-67 1.52E-09 99 Cu-68 8.60E-09' -- Zn-65 4.00E-09 6 Zn-69m 5.06E-09 99 Zn-69 0.OOE+00 6 Ga-66 2.70E-08 99 Ga-67 1.89E-09 99 Ga-68 1.24E-08 99 Ga-72 3.001-08 99 Ge-77 1.34E-08 99 As-72 2.23E-08 99 As-73 1.16E-10 99 As-74 9.41 E-09 99 As-76 6.46E-09 99 As-77 1.79E-10 99 Se-73 1.38E-08 99 Se-75 4.98E-09 99 Br-77 3.84E-09 99 Br-80 2.01 E-09 99 Br-82 3.00E-08 99 Br-83 6.40E-1 1 6 Br-84 1.20E-08 6 Br-85 0.OOE+00 6 Kr-79 3.07E-09 99 Kr-81 1.59E-10 99 Kr-83m 1.42E-1 1 99 Kr-85m 2.24E-09 99 Kr-85 1.35E-10 99 Kr-87 1.03E-08 99 Kr-88 2.07E-08 99 Kr-90 1.56E-08 99 Rb-84 1.07E-08 99 Rb-86 6.30E-10 6 Rb-87 0.OOE+00 99 Rb-88 3.50E-09 6 Rb-89 1.50E-08 6 Sr-85 6.16E-09 99 Sr-87m 3.92E-09 99 Sr-89 5.60E-13 6 Sr-90 1.84E-11 99 Sr-91 7.10E-09 6 Sr-92 9.OOE-09 6 Y-86 4.00E-08 99 Y-87 5.53E-09 99 Y-88 2.88E-08 99 Y-90 2.20E-12 6 Y-91m 3.80E-09 6 Y-91 2.40E-11 6 Y-92 1.60E-09 6 Y-93 5.70E-10 6 Zr-95 5.OOE-09 6 Zr-97 5.50E-09 6 Nb-94 1.84E-08 99 Nb-95 5.1OE-09 6 Nb-97m 8.57E-09 99 Nb-97 8.48E-09 99 Mo-99 1.90E-09 6 Tc-99m 9.60E-10 6 Tc-101 2.70E-09 6 Tc-104 1.83E-081 -- Ru-97 2.99E-09 99 Ru-103 3.60E-09 6 Ru-105 4.50E-09 6 Ru/Rh-106 5.76E-09 3 6, 99 Pc-109 3.80E-10 99 Cc-109 1.12E-10 99 In-111 5.11E-09 99 In-115m 2.01E-09 99 In-116 0.00E+002 -- Sn-113 1.15E-09 99 Sn-117m 1.96E-08 99 Sn-119m 7.05E-11 99 Sb-117 0.00E+002 -- Sb-122 2.71 E-091 -- Sb-124 1.16E-081 -- Sb-125 4.56E-09 99 Sb-126 7.13E-10 99 Ag-108m 1.92E-08 99 Ag-108 1.14E-09 99 Ag-110m 1.80E-08 6 Ag-111 6.75E-10 99 Te-121m 2.65E-09 99 Te-121 6.75E-09 99 Quad Cities ODCM Part II

CY-QC-170-301 Revision 11 Page 248 of 307 January 2013 Table 4-13 (Page 2 of 3) External Dose Factors for Standing on Contaminated Ground DFGij (mrem/hr per pCi/ M2 ) Whole Body Element Dose Factor Reference Element Dose Factor Reference Te-123m 1.88E-09 99 Te-125m 3.50E-11 6 Te-125 0.OOE+00 2 -- Te-127m 1.10E-12 6 Te-127 1.OOE-11 6 Te-129m 7.70E-10 6 Te-129 7.10E-10 6 Te-131m 8.40E-09 6 Te-131 2.20E-09 6 Te-1-132 3.40E-09' 6 Te-134 1.05E-08 99 1-123 2.12E-09 99 1-124 1.23E-08 99 1-125 2.89E-10 99 1-130 1.40E-08 6 1-131 2.80E-09 6 1-133 3.70E-09 6 1-134 1.60E-08 6 1-135 1.20E-08 6 Xe-127 3.44E-09 99 Xe-129m 5.57E-10 99 Xe-131m 2.13E-10 99 Xe-133m 4.81E-10 99 Xe-133 5.91E-10 99 Xe-135m 5.23E-09 99 Xe-135 3.36E-09 99 Xe-137 4.26E-09 99 Xe-138 1.30E-08 99 Cs-129 3.39E-09 99 Cs-132 8.40E-09 99 Cs-134 1.20E-08 6 Cs-136 1.50E-08 6 Cs-137/Ba-137m 1.14E-08 4 6, 99 Cs-138 2.1OE-08 6 Cs-139 5.15E-09 99 Ba-131 5.74E-09 99 Ba-133m 8.10E-10 99 Ba-133 4.85E-09 99 Ba-135m 7.26E-10 99 Ba-137m 7.17E-09 99 Ba-137 0.OOE+00 2 -- Ba-139 2.40E-09 6 Ba-La-140 1.71E-08 6 6 Ba-141 4.30E-09 6 Ba-142 7.90E-09 6 La-142 1.50E-08 6 Ce-139 2.04E-09 99 Ce-141 5.50E-10 6 Ce-143 2.20E-09 6 Ce-Pr-144 5.20E-10 7 6 Pr-142 1.84E-09 99 Pr-143 0.OOE+00 6 Nc-147 1.OOE-09 6 Nc-149 5.32E-09 99 Pm-145 3.38E-10 99 Pm-148m 2.35E-08 99 Pm-148 7.22E-09 99 Pm-149 5.32E-10 99 Sm-153 8.95E-10 99 Eu-152 1.30E-08 99 Eu-154 1.41E-08 99 Eu-155 8.27E-10 99 Gc-153 1.46E-09 99 Dy-157 4.39E-09 99 Er-169 6.12E-14 99 Er-171 5.11E-09 99 Tm-170 3.41E-10 99 Yb-169 4.12E-09 99 Yb-175 4.94E-10 99 Lu-177 4.60E-10 99 Hf-181 6.67E-09 99 Ta-182 1.42E-08 99 Ta-183 2.93E-091 -- W-187 3.10E-09 6 Re-188 1.89E-09 99 Os-191 9.83E-10 99 Ir-194 2.31E-09 99 Pt-195m 9.79E-10 99 Pt-197 3.57E-10 99 Au-195m 2.54E-09 99 Au-195 1.14E-09 99 Au-198 5.19E-09 99 Au-199 1.18E-09 99 Hg-197 9.33E-10 99 Hg-203 2.89E-09 99 TI-201 1.24E-09 99 TI-206 0.OOE+00 2 -- TI-208 3.58E-08 99 Pb-203 3.88E-09 99 Pb-210 3.57E-11 99 Pb-212 1.91E-09 99 Pb-214 3.18E-09 99 Bi-206 3.74E-08 99 Bi-207 1.77E-08 99 Bi-214 1.71E-08 99 Ra-226 8.78E-11 99 Th-232 8.14E-12 99 U-238 7.98E-12 99 Np-239 9.50E-10 6 Am-241 3.48E-10 99 Valued derived by comparing the percentage and MeV of the nuclide's gammas and then comparing to Cesium-137, as a value was not available in the literature. 2 0.0 due to low yield and short half-life. A value was not available in the literature. Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 249 of 307 January 2013 Table 4-13 (Page 3 of 3) External Dose Factors for Standing on Contaminated Ground DFGij (mrem/hr per pCi/ 2) Value is the sum of Ru-1 06 (1.50E-9) and Rh-106 (4.26E-9). The Rh-1 06 value is from Reference 99 and the Ru-106 value is from Reference 6. 4 Value is the sum of Cs-137 (4.20E-9) and Ba-137m (7.17E-9). The values are from references 6 and 99, respectively. 5 Value is the sum of Te-1 32 (1.70E-9) and 1-132 (1.70E-9). 6 Value is the sum of Ba-140 (2.10E-9) and La-140 (1.50E-8) from reference 6. In Reference 6, see Table E-6. 7 Value is the sum of Ce-144 (3.20E-10) and Pr-144 (2.OOE-10) from reference 6. Note: Dose assessments for 10CFR20 and 40CFR1 90 compliance are made for an adult only. Dose assessments for 10CFR50 Appendix are made using dose factors of Regulatory Guide 1.109 (Reference 6) for all age groups. Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 250 of 307 January 2013 Table 4-14 (Page 1 of 2) Ground Plane Dose Factors (Same for all age groups) Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI H-3 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+0O 0.OOE+00 0.OOE+00 0.00E+00 C-14 O.00E+00 0.00E+00 0.0E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 Na-24 1.20E+07 1.20E+07 1.20E+07 1.20E+07 1.20E+07 1.20E+07 1.20E+07 Cr-51 4.65E+06 4.65E+06 4.65E+06 4.65E+06 4.65E+06 4.65E+06 4.65E+06 Mn-54 1.38E+09 1.38E+09 1.38E+09 1.38E+09 1.38E+09 1.38E+09 1.38E+09 Mn-56 9.03E+05 9.03E+05 9.03E+05 9.03E+05 9.03E+05 9.03E+05 9.03E+05 Fe-55 0.00E+00 0.00E+00 0.00E+00 0.00E+00 O.00E+00 0.00E+00 0.OOE+00 Fe-59 2.73E+08 2.73E+08 2.73E+08 2.73E+08 2.73E+08 2.73E+08 2.73E+08 Co-58 3.80E+08 3.80E+08 3.80E+08 3.80E+08 3.80E+08 3.80E+08 3.80E+08 Co-60 2.45E+10 2.45E+10 2.45E+10 2.45E+10 2.45E+10 2.45E+10 2.45E+10 Ni-63 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ni-65 2.97E+05 2.97E+05 2.97E+05 2.97E+05 2.97E+05 2.97E+05 2.97E+05 Cu-64 6.05E+05 6.05E+05 6.05E+05 6.05E+05 6.05E+05 6.05E+05 6.05E+05 Zn-65 7.46E+08 7.46E+08 7.46E+08 7.46E+08 7.46E+08 7.46E+08 7.46E+08 Zn-69 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-83 4.87E+03 4.87E+03 4.87E+03 4.87E+03 4.87E+03 4.87E+03 4.87E+03 Br-84 2.03E+05 2.03E+05 2.03E+05 2.03E+05 2.03E+05 2.03E+05 2.03E+05 Br-85 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 9.01 E+06 9.01 E+06 9.01 E+06 9.01 E+06 9.01 E+06 9.01 E+06 9.01 E+06 Rb-88 3.31E+04 3.31E+04 3.31E+04 3.31E+04 3.31E+04 3.31E+04 3.31E+04 Rb-89 1.23E+05 1.23E+05 1.23E+05 1.23E+05 1.23E+05 1.23E+05 1.23E+05 Sr-89 2.16E+04 2.16E+04 2.16E+04 2.16E+04 2.16E+04 2.16E+04 2.16E+04 Sr-90 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 Sr-91 2.14E+06 2.14E+06 2.14E+06 2.14E+06 2.14E+06 2.14E+06 2.14E+06 Sr-92 7.76E+05 7.76E+05 7.76E+05 7.76E+05 7.76E+05 7.76E+05 7.76E+05 Y-90 4.50E+03 4.50E+03 4.50E+03 4.50E+03 4.50E+03 4.50E+03 4.50E+03 Y-91M 1.OOE+05 1.OOE+05 1.OOE+05 1.OOE+05 1.OOE+05 1.OOE+05 1.OOE+05 Y-91 1.07E+06 1.07E+06 1.07E+06 1.07E+06 1.07E+06 1.07E+06 1.07E+06 Y-92 1.80E+05 1.80E+05 1.80E+05 1.80E+05 1.80E+05 1.80E+05 1.80E+05 Y-93 1.83E+05 1.83E+05 1.83E+05 1.83E+05 1.83E+05 1.83E+05 1.83E+05 Zr-95 2.45E+08 2.45E+08 2.45E+08 2.45E+08 2.45E+08 2.45E+08 2.45E+08 Zr-97 2.96E+06 2.96E+06 2.96E+06 2.96E+06 2.96E+06 2.96E+06 2.96E+06 Nb-95 1.37E+08 1.37E+08 1.37E+08 1.37E+08 1.37E+08 1.37E+08 1.37E+08 Mo-99 3.99E+06 3.99E+06 3.99E+06 3.99E+06 3.99E+06 3.99E+06 3.99E+06 Tc- 99M 1.84E+05 1.84E+05 1.84E+05 1.84E+05 1.84E+05 1.84E+05 1.84E+05 Tc-101 2.03E+04 2.03E+04 2.03E+04 2.03E+04 2.03E+04 2.03E+04 2.03E+04 Ru-103 1.08E+08 1.08E+08 1.08E+08 1.08E+08 1.08E+08 1.08E+08 1.08E+08 Ru-105 6.36E+05 6.36E+05 6.36E+05 6.36E+05 6.36E+05 6.36E+05 6.36E+05 Ru-1 06 4.22E+08 4.22E+08 4.22E+08 4.22E+08 4.22E+08 4.22E+08 4.22E+08 Ag-110M 3.45E+09 3.45E+09 3.45E+09 3.45E+09 3.45E+09 3.45E+09 3.45E+09 Quad Cities ODCM Part II

CY-QC-170-301 Revision 11 Page 251 of 307 January 2013 Table 4-14 (Page 2 of 2) Ground Plane Dose Factors (Same for all age groups) Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI Te-125M 1.56E+06 1.56E+06 1.56E+06 1.56E+06 1.56E+06 1.56E+06 1.56E+06 Te-127M 9.16E+04 9.16E+04 9.16E+04 9.16E+04 9.16E+04 9.16E+04 9.16E+04 Te-127 2.99E+03 2.99E+03 2.99E+03 2.99E+03 2.99E+03 2.99E+03 2.99E+03 Te-129M 1.98E+07 1.98E+07 1.98E+07 1.98E+07 1.98E+07 1.98E+07 1.98E+07 Te-129 2.62E+04 2.62E+04 2.62E+04 2.62E+04 2.62E+04 2.62E+04 2.62E+04 Te-131M 8.02E+06 8.02E+06 8.02E+06 8.02E+06 8.02E+06 8.02E+06 8.02E+'06 Te-131 2.92E+04 2.92E+04 2.92E+04 2.92E+04 2.92E+04 2.92E+04 2192E+04 Te-132 4.22E+06 4.22E+06 4.22E+06 4.22E+06 4.22E+06 4.22E+06 4.22E+06 1-130 5.50E+06 5.50E+06 5.50E+06 5.50E+06 5.50E+06 5.50E+06 5.50E+06 1-131 1.72E+07 1.72E+07 1.72E+07 1.72E+07 1.72E+07 1.72E+07 1.72E+07 1-132 1.25E+06 1.25E+06 1.25E+06 1.25E+06 1.25E+06 1.25E+06 1.25E+06 1-133 2.45E+06 2.45E+06 2.45E+06 2.45E+06 2.45E+06 2.45E+06 2.45E+06 1-134 4.46E+05 4.46E+05 4.46E+05 4.46E+05 4.46E+05 4.46E+05 4.46E+05 1-135 2.53E+06 2.53E+06 2.53E+06 2.53E+06 2.53E+06 2.53E+06 2.53E+06 Cs-1 34 6.94E+09 6.94E+09 6.94E+09 6.94E+09 6.94E+09 6.94E+09 6.94E+09 Cs-136 1.50E+08 1.50E+08 1.50E+08 1.50E+08 1.50E+08 1.50E+08 1.50E+08 Cs-137 1.76E+10 1.76E+10 1.76E+10 1.76E+10 1.76E+10 1.76E+10 1.76E+10 Cs-1 38 3.59E+05 3.59E+05 3.59E+05 3.59E+05 3.59E+05 3.59E+05 3.59E+05 Ba-1 39 1.06E+05 1.06E+05 1.06E+05 1.06E+05 1.06E+05 1.06E+05 1.06E+05 Ba-140 2.05E+07 2.05E+07 2.05E+07 2.05E+07 2.05E+07 2.05E+07 2.05E+07 Ba-141 4.17E+04 4.17E+04 4.17E+04 4.17E+04 4.17E+04 4.17E+04 4.17E+04 Ba-142 4.44E+04 4.44E+04 4.44E+04 4.44E+04 4.44E+04 4.44E+04 4.44E+04 La-140 1.92E+07 1.92E+07 1.92E+07 1.92E+07 1.92E+07 1.92E+07 1.92E+07 La-142 7.60E+05 7.60E+05 7.60E+05 7.60E+05 7.60E+05 7.60E+05 7.60E+05 Ce-141 1.37E+07 1.37E+07 1.37E+07 1.37E+07 1.37E+07 1.37E+07 1.37E+07 Ce-143 2.31E+06 2.31iE+06 2.31E+06 2.31E+06 2.31E+06 2.31E+06 2.31E+06 Ce-144 6.96E+07 6.96E+07 6.96E+07 6.96E+07 6.96E+07 6.96E+07 6.96E+07 Pr-143 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Pr-144 1.84E+03 1.84E+03 1.84E+03 1.84E+03 1.84E+03 1.84E+03 1.84E+03 Nd-147 8.48E+06 8.48E+06 8.48E+06 8.48E+06 8.48E+06 8.48E+06 8.48E+06 W-187 2.35E+06 2.35E+06 2.35E+06 2.35E+06 2.35E+06 2.35E+06 2.35E+06 Np-239 1.71E+06 1.71iE+06 1.71E+061 1.71E+06 1.71E+06 1.71E+06 1.71E+06 Notes:

1) Units are m2 mrem/yr per [tCi/sec.

2) All age groups are assumed to receive the same dose.

Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 252 of 307 January 2013 Table 4-15 (Page 1 of 8) Inhalation Dose Factors Adult Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI H-3 O.OOE+00 7.18E+02 7.18E+02 7.18E+02 7.18E+02 7.18E+02 7.18E+02 C-14 1.82E+04 3.41E+03 3.41E+03 3.41E+03 3.41E+03 3.41E+03 3.41E+03 Na-24 1.02E+04 1.02E+04 1.02E+04 1.02E+04 1.02E+04 1.02E+04 1.02E+04 Cr-51 O.OOE+00 O.OOE+00 1.OOE+02 5.95E+01 2.28E+01 1.44E+04 3.32E+03 Mn-54 O.OOE+00 3.96E+04 6.30E+03 O.OOE+00 9.84E+03 1.40E+06 7.74E+04 Mn-56 O.OOE+00 1.24E+00 1.83E-01 O.OOE+00 1.30E+00 9.44E+03 2.02E+04 Fe-55 2.46E+04 1.70E+04 3.94E+03 O.OOE+00 O.OOE+00 7.21E+04 6.03E+03 Fe-59 1.18E+04 2.78E+04 1.06E+04 O.OOE+00 O.OOE+00 1.02E+06 1.88E+05 Co-58 O.OOE+00 1.58E+03 2.07E+03 O.OOE+00 O.OOE+00 9.28E+05 1.06E+05 Co-60 O.OOE+00 1.15E+04 1.48E+04 O.OOE+00 O.OOE+00 5.97E+06 2.85E+05 Ni-63 4.32E+05 3.14E+04 1.45E+04 O.OOE+00 O.OOE+00 1.78E+05 1.34E+04 Ni-65 1.54E+00 2.10E-01 9.12E-02 O.OOE+00 O.OOE+00 5.60E+03 1.23E+04 Cu-64 O.OOE+00 1.46E+00 6.15E-01 O.OOE+00 4.62E+00 6.78E+03 4.90E+04 Zn-65 3.24E+04 1.03E+05 4.66E+04 O.OOE+00 6.90E+04 8.64E+05 5.34E+04 Zn-69 3.38E-02 6.51E-02 4.52E-03 O.OOE+00 4.22E-02 9.20E+02 1.63E+01 Br-83 O.OOE+00 O.OOE+00 2.41E+02 O.OOE+00 O.OOE+00 O.OOE+00 2.32E+02 Br-84 O.OOE+00 O.OOE+00 3.13E+02 O.OOE+00 O.OOE+00 O.OOE+00 1.64E-03 Br-85 O.OOE+00 O.OOE+00 1.28E+01 O.OOE+00 O.00E+00 O.OOE+00 O.OOE+00 Rb-86 O.OOE+00 1.35E+05 5.90E+04 O.OOE+00 O.OOE+00 O.OOE+00 1.66E+04 Rb-88 O.OOE+00 3.87E+02 1.93E+02 O.OOE+00 O.OOE+00 O.OOE+00 3.34E-09 Rb-89 O.OOE+00 2.56E+02 1.70E+02 O.OOE+00 O.OOE+00 O.OOE+00 9.28E-12 Sr-89 3.04E+05 O.OOE+00 8.72E+03 O.OOE+00 O.OOE+00 1.40E+06 3.50E+05 Sr-90 2.87E+07 O.OOE+00 5.77E+05 O.00E+00 O.OOE+00 9.60E+06 7.22E+05 Sr-91 6.19E+01 O.OOE+00 2.50E+00 O.OOE+00 O.OOE+00 3.65E+04 1.91EE+05 Sr-92 6.74E+00 O.OOE+00 2.91E-01 O.OOE+00 O.OOE+00 1.65E+04 4.30E+04 Y-90 2.09E+03 O.00E+00 5.61E+01 O.OOE+00 O.OOE+00 1.70E+05 5.06E+05 Y-91M 2.61E-01 O.OOE+00 1.02E-02 O.OOE+00 O.OOE+00 1.92E+03 1.33E+00 Y-91 4.62E+05 O.OOE+00 1.24E+04 O.OOE+00 O.OOE+00 1.70E+06 3.85E+05 Y-92 1.03E+01 O.OOE+00 3.02E-01 O.OOE+00 O.OOE+00 1.57E+04 7.35E+04 Y-93 9.44E+01 O.OOE+00 2.61E+00 O.OOE+00 O.OOE+00 4.85E+04 4.22E+05 Zr-95 1.07E+05 3.44E+04 2.33E+04 O.OOE+00 5.42E+04 1.77E+06 1.50E+05 Zr-97 9.68E+01 1.96E+01 9.04E+00 O.OOE+00 2.97E+01 7.87E+04 5.23E+05 Nb-95 1.41E+04 7.82E+03 4.21E+03 O.OOE+00 7.74E+03 5.05E+05 1.04E+05 Mo-99 O.OOE+00 1.21E+02 2.30E+01 O.OOE+00 2.91E+02 9.12E+04 2.48E+05 Tc- 99M 1.03E-03 2.91E-03 3.70E-02 O.OOE+00 4.42E-02 7.64E+02 4.16E+03 Tc-101 4.18E-05 6.02E-05 5.90E-04 O.OOE+00 1.08E-03 3.99E+02 1.09E-11 Ru-103 1.53E+03 O.OOE+00 6.58E+02 O.OOE+00 5.83E+03 5.05E+05 1.10E+05 Ru-105 7.90E-01 O.OOE+00 3.11E-01 O.OOE+00 1.02E+00 1.10E+04 4.82E+04 Ru-106 6.91E+04 O.OOE+00 8.72E+03 O.OOE+00 1.34E+05 9.36E+06 9.12E+05 Ag-i 1 OM 1.08E+04 1.OOE+04 5.94E+03 O.OOE+00 1.97E+04 4.63E+06 3.02E+05 Quad Cities ODCM Part II

CY-QC-170-301 Revision 11 Page 253 of 307 January 2013 Table 4-15 (Page 2 of 8) Inhalation Dose Factors Adult Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI Te-125M 3.42E+03 1.58E+03 4.67E+02 1.05E+03 1.24E+04 3.14E+05 7.06E+04 Te-127M 1.26E+04 5.77E+03 1.57E+03 3.29E+03 4.58E+04 9.60E+05 1.50E+05 Te-127 1.40E+00 6.42E-01 3.10E-01 1.06E+00 5.1OE+00 6.51E+03 5.74E+04 Te-129M 9.76E+03 4.67E+03 1.58E+03 3.44E+03 3.66E+04 1.16E+06 3.83E+05 Te-129 4.98E-02 2.39E-02 1.24E-02 3.90E-02 1.87E-01 1.94E+03 1.57E+02 Te-131M 6.99E+01 4.36E+01 2.90E+01 5.50E+01 3.09E+02 1.46E+05 5.56E+05 Te-131 1.11E-02 5.95E-03 3.59E-03 9.36E-03 4.37E-02 1.39E+03 1.84E+01 Te-132 2.60E+02 2.15E+02 1.62E+02 1.90E+02 1.46E+03 2.88E+05 5.1OE+05 1-130 4.58E+03 1.34E+04 5.28E+03 1.14E+06 2.09E+04 O.00E+00 7.69E+03 1-131 2.52E+04 3.58E+04 2.05E+04 1.19E+07 6.13E+04 0.OOE+00 6.28E+03 1-132 1.16E+03 3.26E+03 1.16E+03 1.14E+05 5.18E+03 O.OOE+00 4.06E+02 1-133 8.64E+03 1.48E+04 4.52E+03 2.15E+06 2.58E+04 0.OOE+00 8.88E+03 1-134 6.44E+02 1.73E+03 6.15E+02 2.98E+04 2.75E+03 O.OOE+00 1.01E+00 1-135 2.68E+03 6.98E+03 2.57E+03 4.48E+05 1.11E+04 0.OOE+00 5.25E+03 Cs-134 3.73E+05 8.48E+05 7.28E+05 O.OOE+00 2.87E+05 9.76E+04 1.04E+04 Cs-136 3.90E+04 1.46E+05 1.1OE+05 O.OOE+00 8.56E+04 1.20E+04 1.17E+04 Cs-137 4.78E+05 6.21E+05 4.28E+05 0.OOE+00 2.22E+05 7.52E+04 8.40E+03 Cs-138 3.31E+02 6.21E+02 3.24E+02 0.OOE+00 4.80E+02 4.86E+01 1.86E-03 Ba-1 39 9.36E-01 6.66E-04 2.74E-02 0.OOE+00 6.22E-04 3.76E+03 8.96E+02 Ba-140 3.90E+04 4.90E+01 2.57E+03 0.OOE+00 1.67E+01 1.27E+06 2.18E+05 Ba-141 1.OOE-01 7.53E-05 3.36E-03 0.OOE+00 7.OOE-05 1.94E+03 1.16E-07 Ba-142 2.63E-02 2.70E-05 1.66E-03 0.OOE+00 2.29E-05 1.19E+03 1.57E-16 La-140 3.44E+02 1.74E+02 4.58E+01 0.OOE+00 O.OOE+00 1.36E+05 4.58E+05 La-142 6.83E-01 3.10E-01 7.72E-02 0.00E+00 O.OOE+00 6.33E+03 2.11E+03 Ce-141 1.99E+04 1.35E+04 1.53E+03 0.OOE+00 6.26E+03 3.62E+05 1.20E+05 Ce-143 1.86E+02 1.38E+02 1.53E+01 0.OOE+00 6.08E+01 7.98E+04 2.26E+05 Ce-144 3.43E+06 1.43E+06 1.84E+05 0.OOE+00 8.48E+05 7.78E+06 8.16E+05 Pr-143 9.36E+03 3.75E+03 4.64E+02 0.OOE+00 2.16E+03 2.81E+05 2.OOE+05 Pr-144 3.01E-02 1.25E-02 1.53E-03 0.OOE+O0 7.05E-03 1.02E+03 2.15E-08 Nd-147 5.27E+03 6.1OE+03 3.65E+02 0.OOE+00 3.56E+03 2.21E+05 1.73E+05 W-187 8.48E+00 7.08E+00 2.48E+00 O.OOE+00 0.OOE+00 2.90E+04 1.55E+05 Np-239 2.30E+02 2.03E+02 1.24E+01 O.OOE+00 7.OOE+01 3.76E+04 1.19E+05 Notes:

1) Units are mrem/yr per lLLCi/m 3 .

Quad Cities ODCM Part II

CY-QC-170-301 Revision 11 Page 254 of 307 January 2013 Table 4-15 (Page 3 of 8) Inhalation Dose Factors Teen Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI H-3 O.OOE+OO 7.25E+02 7.25E+02 7.25E+02 7.25E+02 7.25E+02 7.25E+02 C-14 2.60E+04 4.87E+03 4.87E+03 4.87E+03 4.87E+03 4.87E+03 4.87E+03 Na-24 1.38E+04 1.38E+04 1.38E+04 1.38E+04 1.38E+04 1.38E+04 1.38E+04 Cr-51 O.OOE+00 O.OOE+00 1.35E+02 7.50E+01 3.07E+01 2.1OE+04 3.OOE+03 Mn-54 O.OOE+00 5.11E+04 8.40E+03 O.OOE+00 1.27E+04 1.98E+06 6.68E+04 Mn-56 O.OOE+00 1.70E+00 2.52E-01 O.OOE+00 1.79E+00 1.52E+04 5.74E+04 Fe-55 3.34E+04 2.38E+04 5.54E+03 O.OOE+00 O.OOE+00 1.24E+05 6.39E+03 Fe-59 1.59E+04 3.70E+04 1.43E+04 O.OOE+00 O.OOE+00 1.53E+06 1.78E+05 Co-58 O.OOE+00 2.07E+03 2.78E+03 O.OOE+00 O.OOE+00 1.34E+06 9.52E+04 Co-60 O.OOE+00 1.51E+04 1.98E+04 O.OOE+00 O.OOE+00 8.72E+06 2.59E+05 Ni-63 5.80E+05 4.34E+04 1.98E+04 O.OOE+00 O.OOE+00 3.07E+05 1.42E+04 Ni-65 2.18E+00 2.93E-01 1.27E-01 O.OOE+00 O.OOE+00 9.36E+03 3.67E+04 Cu-64 O.OOE+00 2.03E+00 8.48E-01 O.OOE+00 6.41E+00 1.11E+04 6.14E+04 Zn-65 3.86E+04 1.34E+05 6.24E+04 O.OOE+00 8.64E+04 1.24E+06 4.66E+04 Zn-69 4.83E-02 9.20E-02 6.46E-03 O.OOE+00 6.02E-02 1.58E+03 2.85E+02 Br-83 O.OOE+00 O.OOE+00 3.44E+02 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Br-84 O.OOE+00 O.OOE+00 4.33E+02 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Br-85 O.OOE+00 O.OOE+00 1.83E+01 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Rb-86 O.OOE+00 1.90E+05 8.40E+04 O.OOE+00 O.OOE+00 0.00E+00 1.77E+04 Rb-88 O.OOE+00 5.46E+02 2.72E+02 O.OOE+00 O.OOE+00 O.OOE+00 2.92E-05 Rb-89 O.OOE+00 3.52E+02 2.33E+02 O.OOE+00 O.OOE+00 O.OOE+00 3.38E-07 Sr-89 4.34E+05 O.OOE+00 1.25E+04 O.OOE+00 O.OOE+00 2.42E+06 3.71 E+05 Sr-90 3.31E+07 O.OOE+00 6.66E+05 O.OOE+00 O.OOE+00 1.65E+07 7.65E+05 Sr-91 8.80E+01 O.OOE+00 3.51E+00 O.OOE+00 O.OOE+00 6.07E+04 2.59E+05 Sr-92 9.52E+00 O.OOE+00 4.06E-01 O.OOE+00 O.OOE+00 2.74E+04 1.19E+05 Y-90 2.98E+03 O.OOE+00 8.OOE+01 O.OOE+00 O.OOE+00 2.93E+05 5.59E+05 Y-91M 3.70E-01 O.OOE+00 1.42E-02 O.OOE+00 O.OOE+00 3.20E+03 3.02E+01 Y-91 6.61E+05 O.OOE+00 1.77E+04 O.OOE+00 O.OOE+00 2.94E+06 4.09E+05 Y-92 1.47E+01 O.OOE+00 4.29E-01 O.OOE+00 O.OOE+00 2.68E+04 1.65E+05 Y-93 1.35E+02 O.00E+00 3.72E+00 O.OOE+00 O.OOE+00 8.32E+04 5.79E+05 Zr-95 1.46E+05 4.58E+04 3.15E+04 O.OOE+00 6.74E+04 2.69E+06 1.49E+05 Zr-97 1.38E+02 2.72E+01 1.26E+01 O.OOE+00 4.12E+01 1.30E+05 6.30E+05 Nb-95 1.86E+04 1.03E+04 5.66E+03 O.OOE+00 1.OOE+04 7.51 E+05 9.68E+04 Mo-99 O.OOE+00 1.69E+02 3.22E+01 O.OOE+00 4.11E+02 1.54E+05 2.69E+05 Tc-99M 1.38E-03 3.86E-03 4.99E-02 O.OOE+00 5.76E-02 1.15E+03 6.13E+03 Tc-101 5.92E-05 8.40E-05 8.24E-04 O.OOE+00 1.52E-03 6.67E+02 8.72E-07 Ru-103 2.10E+03 O.OOE+00 8.96E+02 O.OOE+00 7.43E+03 7.83E+05 1.09E+05 Ru-105 1.12E+00 O.OOE+00 4.34E-01 O.OOE+00 1.41E+00 1.82E+04 9.04E+04 Ru-106 9.84E+04 O.OOE+00 1.24E+04 O.OOE+00 1.90E+05 1.61E+07 9.60E+05 Ag-11OM 1.38E+04 1.31E+04 7.99E+03 O.OOE+00 2.50E+04 6.75E+06 2.73E+051 Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 255 of 307 January 2013 Table 4-15 (Page 4 of 8) Inhalation Dose Factors Teen Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI Te-125M 4.88E+03 2.24E+03 6.67E+02 1.40E+03 0.OOE+00 5.36E+05 7.50E+04 Te-127M 1.80E+04 8.16E+03 2.18E+03 4.38E+03 6.54E+04 1.66E+06 1.59E+05 Te-127 2.01E+00 9.12E-01 4.42E-01 1.42E+00 7.28E+00 1.12E+04 8.08E+04 Te-129M 1.39E+04 6.58E+03 2.25E+03 4.58E+03 5.19E+04 1.98E+06 4.05E+05 Te-129 7.1OE-02 3.38E-02 1.76E-02 5.18E-02 2.66E-01 3.30E+03 1.62E+03 Te-131M 9.84E+01 6.01E+01 4.02E+01 7.25E+01 4.39E+02 2.38E+05 6.21E+05 Te-131 1.58E-02 8.32E-03 5.04E-03 1.24E-02 6.18E-02 2.34E+03 1.51E+01 Te-132 3.60E+02 2.90E+02 2.19E+02 2.46E+02 1.95E+03 4.49E+05 4.63E+05 1-130 6.24E+03 1.79E+04 7.17E+03 1.49E+06 2.75E+04 0.OOE+00 9.12E+03 1-131 3.54E+04 4.91E+04 2.64E+04 1.46E+07 8.40E+04 O.OOE+00 6.49E+03 1-132 1.59E+03 4.38E+03 1.58E+03 1.51EE+05 6.92E+03 0.OOE+00 1.27E+03 1-133 1.22E+04 2.05E+04 6.22E+03 2.92E+06 3.59E+04 0.OOE+00 1.03E+04 1-134 8.88E+02 2.32E+03 8.40E+02 3.95E+04 3.66E+03 0.OOE+00 2.04E+01 1-135 3.70E+03 9.44E+03 3.49E+03 6.21 E+05 1.49E+04 O.OOE+00 6.95E+03 Cs-134 5.02E+05 1.13E+06 5.49E+05 0.OOE+00 3.75E+05 1.46E+05 9.76E+03 Cs-136 5.15E+04 1.94E+05 1.37E+05 0.OOE+00 1.10E+05 1.78E+04 1.09E+04 Cs-137 6.70E+05 8.48E+05 3.11E+05 0.OOE+00 3.04E+05 1.21E+05 8.48E+03 Cs-138 4.66E+02 8.56E+02 4.46E+02 0.00E+00 6.62E+02 7.87E+01 2.70E-01 Ba-1 39 1.34E+00 9.44E-04 3.90E-02 O.OOE+00 8.88E-04 6.46E+03 6.45E+03 Ba-140 5.47E+04 6.70E+01 3.52E+03 0.OOE+00 2.28E+01 2.03E+06 2.29E+05 Ba-141 1.42E-01 1.06E-04 4.74E-03 0.OOE+00 9.84E-05 3.29E+03 7.46E-04 Ba-142 3.70E-02 3.70E-05 2.27E-03 0.OOE+00 3.14E-05 1.91E+03 4.79E-10 La-140 4.79E+02 2.36E+02 6.26E+01 0.OOE+00 0.OOE+00 2.14E+05 4.87E+05 La-142 9.60E-01 4.25E-01 1.06E-01 O.OOE+00 0.OOE+00 1.02E+04 1.20E+04 Ce-141 2.84E+04 1.90E+04 2.17E+03 0.OOE+00 8.88E+03 6.14E+05 1.26E+05 Ce-143 2.66E+02 1.94E+02 2.16E+01 0.OOE+00 8.64E+01 1.30E+05 2.55E+05 Ce-144 4.89E+06 2.02E+06 2.62E+05 0.OOE+00 1.21E+06 1.34E+07 8.64E+05 Pr-143 1.34E+04 5.31E+03 6.62E+02 0.OOE+00 3.09E+03 4.83E+05 2.14E+05 Pr-144 4.30E-02 1.76E-02 2.18E-03 0.OOE+00 1.01E-02 1.75E+03 2.35E-04 Nd-147 7.86E+03 8.56E+03 5.13E+02 O.OOE+00 5.02E+03 3.72E+05 1.82E+05 W-187 1.20E+01 9.76E+00 3.43E+00 0.OOE+00 0.OOE+00 4.74E+04 1.77E+05 Np-239 3.38E+02 2.88E+02 1.77E+01 O.OOE+00 1.OOE+02 6.49E+04 1.32E+05 Notes:

1) Units are mrem/yr per [iCi/m 3 .

Quad Cities ODCM Part II

CY-QC-170-301 Revision 11 Page 256 of 307 January 2013 Table 4-15 (Page 5 of 8) Inhalation Dose Factors Child Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI H-3 0.OOE+00 6.40E+02 6.40E+02 6.40E+02 6.40E+02 6.40E+02 6.40E+02 C-14 3.59E+04 6.73E+03 6.73E+03 6.73E+03 6.73E+03 6.73E+03 6.73E+03 Na-24 1.61E+04 1.61E+04 1.61E+04 1.61E+04 1.61E+04 1.61E+04 1.61E+04 Cr-51 0.OOE+00 0.OOE+00 1.54E+02 8.55E+01 2.43E+01 1.70E+04 1.08E+03 Mn-54 0.OOE+00 4.29E+04 9.51E+03 O.OOE+00 1.OOE+04 1.58E+06 2.29E+04 Mn-56 0.OOE+00 1.66E+00 3.12E-01 O.OOE+00 1.67E+00 1.31E+04 1.23E+05 Fe-55 4.74E+04 2.52E+04 7.77E+03 0.OOE+00 0.OOE+00 1.11E+05 2.87E+03 Fe-59 2.07E+04 3.34E+04 1.67E+04 0.OOE+00 0.OOE+00 1.27E+06 7.07E+04 Co-58 O.OOE+00 1.77E+03 3.16E+03 O.OOE+00 0.OOE+00 1.11E+06 3.44E+04 Co-60 0.OOE+00 1.31 E+04 2.26E+04 O.OOE+00 O.OOE+00 7.07E+06 9.62E+04 Ni-63 8.21E+05 4.63E+04 2.80E+04 O.OOE+00 O.OOE+00 2.75E+05 6.33E+03 Ni-65 2.99E+00 2.96E-01 1.64E-01 0.OOE+00 0.OOE+00 8.18E+03 8.40E+04 Cu-64 0.OOE+00 1.99E+00 1.07E+00 O.OOE+00 6.03E+00 9.58E+03 3.67E+04 Zn-65 4.26E+04 1.13E+05 7.03E+04 0.OOE+00 7.14E+04 9.95E+05 1.63E+04 Zn-69 6.70E-02 9.66E-02 8.92E-03 0.OOE+00 5.85E-02 1.42E+03 1.02E+04 Br-83 0.OOE+00 0.OOE+00 4.74E+02 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 Br-84 0.OOE+00 0.OOE+00 5.48E+02 0.OOE+00 0.OOE+00 O.OOE+00 0.00E+00 Br-85 0.OOE+00 0.00E+00 2.53E+01 O.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 Rb-86 0.OOE+00 1.98E+05 1.14E+05 0.OOE+00 0.OOE+00 0.OOE+00 7.99E+03 Rb-88 0.OOE+00 5.62E+02 3.66E+02 0.OOE+00 0.OOE+00 0.OOE+00 1.72E+01 Rb-89 0.OOE+00 3.45E+02 2.90E+02 0.OOE+00 0.OOE+00 0.OOE+00 1.89E+00 Sr-89 5.99E+05 0.OOE+00 1.72E+04 O.OOE+00 O.OOE+00 2.16E+06 1.67E+05 Sr-90 3.85E+07 0.00E+00 7.66E+05 0.OOE+00 0.OOE+00 1.48E+07 3.43E+05 Sr-91 1.21E+02 0.OOE+00 4.59E+00 0.OOE+00 0.OOE+00 5.33E+04 1.74E+05 Sr-92 1.31E+01 0.OOE+00 5.25E-01 O.OOE+00 0.OOE+00 2.40E+04 2.42E+05 Y-90 4.11E+03 O.OOE+00 1.11E+02 O.OOE+00 0.OOE+00 2.62E+05 2.68E+05 Y-91M 5.07E-01 0.OOE+00 1.84E-02 0.OOE+00 0.OOE+00 2.81E+03 1.72E+03 Y-91 9.14E+05 0.OOE+00 2.44E+04 0.OOE+00 0.OOE+00 2.63E+06 1.84E+05 Y-92 2.04E+01 O.OOE+00 5.81E-01 0.OOE+00 O.OOE+00 2.39E+04 2.39E+05 Y-93 1.86E+02 0.OOE+00 5.11E+00 0.OOE+00 0.00E+00 7.44E+04 3.89E+05 Zr-95 1.90E+05 4.18E+04 3.70E+04 0.OOE+00 5.96E+04 2.23E+06 6.11E+04 Zr-97 1.88E+02 2.72E+01 1.60E+01 O.OOE+00 3.89E+01 1.13E+05 3.51E+05 Nb-95 2.35E+04 9.18E+03 6.55E+03 O.OOE+00 8.62E+03 6.14E+05 3.70E+04 Mo-99 0.OOE+00 1.72E+02 4.26E+01 0.OOE+00 3.92E+02 1.35E+05 1.27E+05 Tc- 99M 1.78E-03 3.48E-03 5.77E-02 0.OOE+00 5.07E-02 9.51 E+02 4.81 E+03 Tc-101 8.1OE-05 8.51E-05 1.08E-03 0.OOE+00 1.45E-03 5.85E+02 1.63E+01 Ru-103 2.79E+03 0.OOE+00 1.07E+03 0.OOE+00 7.03E+03 6.62E+05 4.48E+04 Ru-105 1.53E+00 0.OOE+00 5.55E-01 0.OOE+00 1.34E+00 1.59E+04 9.95E+04 Ru-106 1.36E+05 0.OOE+00 1.69E+04 0.OOE+00 1.84E+05 1.43E+07 4.29E+05 Ag-110M 1.69E+04 1.14E+04 9.14E+03 0.OOE+00 2.12E+04 5.48E+06 1.OOE+05 Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 257 of 307 January 2013 Table 4-15 (Page 6 of 8) Inhalation Dose Factors Child Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI Te-125M 6.73E+03 2.33E+03 9.14E+02 1.92E+03 O.OOE+00 4.77E+05 3.38E+04 Te-127M 2.49E+04 8.55E+03 3.02E+03 6.07E+03 6.36E+04 1.48E+06 7.14E+04 Te-127 2.77E+00 9.51E-01 6.11E-01 1.96E+00 7.07E+00 1.OOE+04 5.62E+04 Te-129M 1.92E+04 6.85E+03 3.04E+03 6.33E+03 5.03E+04 1.76E+06 1.82E+05 Te-129 9.77E-02 3.50E-02 2.38E-02 7.14E-02 2.57E-01 2.93E+03 2.55E+04 Te-131M 1.34E+02 5.92E+01 5.07E+01 9.77E+01 4.OOE+02 2.06E+05 3.08E+05 Te-131 2.17E-02 8.44E-03 6.59E-03 1.70E-02 5.88E-02 2.05E+03 1.33E+03 Te-132 4.81E+02 2.72E+02 2.63E+02 3.17E+02 1.77E+03 3.77E+05 1.38E+05 1-130 8.18E+03 1.64E+04 8.44E+03 1.85E+06 2.45E+04 0.OOE+00 5.11E+03 1-131 4.81E+04 4.81E+04 2.73E+04 1.62E+07 7.88E+04 0.OOE+00 2.84E+03 1-132 2.12E+03 4.07E+03 1.88E+03 1.94E+05 6.25E+03 0.OOE+00 3.20E+03 1-133 1.66E+04 2.03E+04 7.70E+03 3.85E+06 3.38E+04 O.OOE+00 5.48E+03 1-134 1.17E+03 2.16E+03 9.95E+02 5.07E+04 3.30E+03 0.OOE+00 9.55E+02 1-135 4.92E+03 8.73E+03 4.14E+03 7.92E+05 1.34E+04 0.OOE+00 4.44E+03 Cs-134 6.51E+05 1.01E+06 2.25E+05 0.OOE+00 3.30E+05 1.21E+05 3.85E+03 Cs-136 6.51EE+04 1.71E+05 1.16E+05 0.OOE+00 9.55E+04 1.45E+04 4.18E+03 Cs-137 9.07E+05 8.25E+05 1.28E+05 0.OOE+00 2.82E+05 1.04E+05 3.62E+03 Cs-138 6.33E+02 8.40E+02 5.55E+02 O.00E+00 6.22E+02 6.81E+01 2.70E+02 Ba-1 39 1.84E+00 9.84E-04 5.37E-02 O.OOE+00 8.62E-04 5.77E+03 5.77E+04 Ba-140 7.40E+04 6.48E+01 4.33E+03 0.OOE+00 2.11E+01 1.74E+06 1.02E+05 Ba-141 1.96E-01 1.09E-04 6.36E-03 0.OOE+00 9.47E-05 2.92E+03 2.75E+02 Ba-142 5.OOE-02 3.60E-05 2.79E-03 0.OOE+00 2.91E-05 1.64E+03 2.74E+00 La-140 6.44E+02 2.25E+02 7.55E+01 O.OOE+00 0.OOE+00 1.83E+05 2.26E+05 La-142 1.30E+00 4.11E-01 1.29E-01 0.OOE+00 0.OOE+00 8.70E+03 7.59E+04 Ce-141 3.92E+04 1.95E+04 2.90E+03 O.OOE+00 8.55E+03 5.44E+05 5.66E+04 Ce-143 3.66E+02 1.99E+02 2.87E+01 0.OOE+00 8.36E+01 1.15E+05 1.27E+05 Ce-144 6.77E+06 2.12E+06 3.61E+05 Q.OOE+00 1.17E+06 1.20E+07 3.89E+05 Pr-143 1.85E+04 5.55E+03 9.14E+02 O.OOE+00 3.OOE+03 4.33E+05 9.73E+04 Pr-144 5.96E-02 1.85E-02 3.OOE-03 O.OOE+00 9.77E-03 1.57E+03 1.97E+02 Nd-147 1.08E+04 8.73E+03 6.81EE+02 O.OOE+00 4.81E+03 3.28E+05 8.21EE+04 W-187 1.63E+01 9.66E+00 4.33E+00 0.OOE+00 O.OOE+0 4.11E+04 9.1OE+04 Np-239 4.66E+02 3.01E+02 2.35E+01 O.OOE+00 9.73E+01 5.81E+04 6.40E+04 Notes:

1) Units are mrem/yr per [.Ci/m 3 .

Quad Cities ODCM Part II

CY-QC-170-301 Revision 11 Page 258 of 307 January 2013 Table 4-15 (Page 7 of 8) Inhalation Dose Factors Infant Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI H-3 O.OOE+00 3.68E+02 3.68E+02 3.68E+02 3.68E+02 3.68E+02 3.68E+02 C-14 2.65E+04 5.31E+03 5.31E+03 5.31E+03 5.31E+03 5.31E+03 5.31E+03 Na-24 1.06E+04 1.06E+04 1.06E+04 1.06E+04 1.06E+04 1.06E+04 1.06E+04 Cr-51 O.OOE+00 O.OOE+00 8.95E+01 5.75E+01 1.32E+01 1.28E+04 3.57E+02 Mn-54 O.OOE+00 2.53E+04 4.98E+03 O.OOE+00 4.98E+03 1.OOE+06 7.06E+03 Mn-56 O.OOE+00 1.54E+00 2.21E-01 O.OOE+00 1.10E+00 1.25E+04 7.17E+04 Fe-55 1.97E+04 1.17E+04 3.33E+03 O.OOE+00 O.OOE+00 8.69E+04 1.09E+03 Fe-59 1.36E+04 2.35E+04 9.48E+03 O.OOE+00 O.OOE+00 1.02E+06 2.48E+04 Co-58 O.OOE+00 1.22E+03 1.82E+03 O.OOE+00 O.OOE+00 7.77E+05 1.11E+04 Co-60 O.OOE+00 8.02E+03 1.18E+04 O.OOE+00 O.OOE+00 4.51E+06 3.19E+04 Ni-63 3.39E+05 2.04E+04 1.16E+04 O.OOE+00 O.OOE+00 2.09E+05 2.42E+03 Ni-65 2.39E+00 2.84E-01 1.23E-01 O.OOE+00 O.OOE+00 8.12E+03 5.01E+04 Cu-64 O.OOE+00 1.88E+00 7.74E-01 O.OOE+00 3.98E+00 9.30E+03 1.50E+04 Zn-65 1.93E+04 6.26E+04 3.11E+04 O.OOE+00 3.25E+04 6.47E+05 5.14E+04 Zn-69 5.39E-02 9.67E-02 7.18E-03 O.OOE+00 4.02E-02 1.47E+03 1.32E+04 Br-83 O.OOE+00 O.OOE+00 3.81E+02 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Br-84 O.OOE+00 O.OOE+00 4.OOE+02 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Br-85 O.OOE+00 O.OOE+00 2.04E+01 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Rb-86 O.OOE+00 1.90E+05 8.82E+04 O.OOE+00 O.OOE+00 O.OOE+00 3.04E+03 Rb-88 O.OOE+00 5.57E+02 2.87E+02 O.OOE+00 O.OOE+00 O.OOE+00 3.39E+02 Rb-89 O.OOE+00 3.21E+02 2.06E+02 O.OOE+00 O.OOE+00 O.OOE+00 6.82E+01 Sr-89 3.98E+05 O.OOE+00 1.14E+04 O.OOE+00 O.OOE+00 2.03E+06 6.40E+04 Sr-90 1.55E+07 O.OOE+00 3.12E+05 O.OOE+00 O.OOE+00 1.12E+07 1.31E+05 Sr-91 9.56E+01 O.OOE+00 3.46E+00 O.OOE+00 O.OOE+00 5.26E+04 7.34E+04 Sr-92 1.05E+01 O.OOE+00 3.91E-01 O.OOE+00 O.OOE+00 2.38E+04 1.40E+05 Y-90 3.29E+03 O.OOE+00 8.82E+01 O.00E+00 O.OE+00 2.69E+05 1.04E+05 Y-91M 4.07E-01 O.OOE+00 1.39E-02 O.OOE+00 O.OOE+0 2.79E+03 2.35E+03 Y-91 5.88E+05 O.OOE+00 1.57E+04 O.OOE+00 O.OOE+0 2.45E+06 7.03E+04 Y-92 1.64E+01 O.OOE+00 4.61E-01 O.OOE+00 O.OOE+0 2.45E+04 1.27E+05 Y-93 1.50E+02 O.OOE+00 4.07E+00 O.OOE+00 O.OOE+0 7.64E+04 1.67E+05 Zr-95 1.15E+05 2.79E+04 2.03E+04 O.OOE+00 3.11E+04 1.75E+06 2.17E+04 Zr-97 1.50E+02 2.56E+01 1.17E+01 O.OOE+00 2.59E+01 1.10E+05 1.40E+05 Nb-95 1.57E+04 6.43E+03 3.78E+03 O.OOE+00 4.72E+03 4.79E+05 1.27E+04 Mo-99 O.OOE+00 1.65E+02 3.23E+01 O.OOE+00 2.65E+02 1.35E+05 4.87E+04 Tc-99M 1.40E-03 2.88E-03 3.72E-02 O.OOE+00 3.11E-02 8.11E+02 2.03E+03 Tc-101 6.51E-05 8.23E-05 8.12E-04 O.OOE+00 9.79E-04 5.84E+02 8.44E+02 Ru-103 2.02E+03 O.OOE+00 6.79E+02 O.OOE+00 4.24E+03 5.52E+05 1.61E+04 Ru-105 1.22E+00 O.OOE+00 4.1OE-01 O.OOE+00 8.99E-01 1.57E+04 4.84E+04 Ru-106 8.68E+04 O.OOE+00 1.09E+04 O.OOE+00 1.07E+05 1.16E+07 1.64E+05 Ag-110M 9.98E+03 7.22E+03 5.OOE+03 O.OOE+00 1.09E+04 3.67E+06 3.30E+04 Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 259 of 307 January 2013 Table 4-15 (Page 8 of 8) Inhalation Dose Factors Infant Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI Te-125M 4.76E+03 1.99E+03 6.58E+02 1.62E+03 0.OOE+00 4.47E+05 1.29E+04 Te-127M 1.67E+04 6.90E+03 2.07E+03 4.87E+03 3.75E+04 1.31E+06 2.73E+04 Te-127 2.23E+00 9.53E-01 4.89E-01 1.85E+00 4.86E+00 1.03E+04 2.44E+04 Te-129M 1.41E+04 6.09E+03 2.23E+03 5.47E+03 3.18E+04 1.68E+06 6.90E+04 Te-129 7.88E-02 3.47E-02 1.88E-02 6.75E-02 1.75E-01 3.OOE+03 2.63E+04 Te-131M 1.07E+02 5.50E+01 3.63E+01 8.93E+01 2.65E+02 1.99E+05 1.19E+05 Te-131 1.74E-02 8.22E-03 5.OOE-03 1.58E-02 3.99E-02 2.06E+03 8.22E+03 Te-132 3.72E+02 2.37E+02 1.76E+02 2.79E+02 1.03E+03 3.40E+05 4.41E+04 1-130 6.36E+03 1.39E+04 5.57E+03 1.60E+06 1.53E+04 0.OOE+00 1.99E+03 1-131 3.79E+04 4.44E+04 1.96E+04 1.48E+07 5.18E+04 0.OOE+00 1.06E+03 1-132 1.69E+03 3.54E+03 1.26E+03 1.69E+05 3.95E+03 0.OOE+00 1.90E+03 1-133 1.32E+04 1.92E+04 5.60E+03 3.56E+06 2.24E+04 0.OOE+00 2.16E+03 1-134 9.21E+02 1.88E+03 6.65E+02 4.45E+04 2.09E+03 O.OOE+00 1.29E+03 1-135 3.86E+03 7.60E+03 2.77E+03 6.96E+05 8.47E+03 0.OOE+00 1.83E+03 Cs-134 3.96E+05 7.03E+05 7.45E+04 0.OOE+00 1.90E+05 7.97E+04 1.33E+03 Cs-136 4.83E+04 1.35E+05 5.29E+04 O.OOE+00 5.64E+04 1.18E+04 1.43E+03 Cs-137 5.49E+05 6.12E+05 4.55E+04 0.OOE+00 1.72E+05 7.13E+04 1.33E+03 Cs-138 5.05E+02 7.81E+02 3.98E+02 0.OOE+00 4.10E+02 6.54E+01 8.76E+02 Ba-139 1.48E+00 9.84E-04 4.30E-02 0.OOE+00 5.92E-04 5.95E+03 5.1OE+04 Ba-140 5.60E+04 5.60E+01 2.90E+03 0.OOE+00 1.34E+01 1.60E+06 3.84E+04 Ba-141 1.57E-01 1.08E-04 4.97E-03 0.OOE+00 6.50E-05 2.97E+03 4.75E+03 Ba-142 3.98E-02 3.30E-05 1.96E-03 0.OOE+00 1.90E-05 1.55E+03 6.93E+02 La-140 5.05E+02 2.OOE+02 5.15E+01 O.OOE+00 O.OOE+00 1.68E+05 8.48E+04 La-142 1.03E+00 3.77E-01 9.04E-02 0.OOE+00 0.OOE+00 8.22E+03 5.95E+04 Ce-141 2.77E+04 1.67E+04 1.99E+03 O.OOE+00 5.25E+03 5.17E+05 2.16E+04 Ce-143 2.93E+02 1.93E+02 2.21E+01 0.OOE+00 5.64E+01 1.16E+05 4.97E+04 Ce-144 3.19E+06 1.21E+06 1.76E+05 0.OOE+00 5.38E+05 9.84E+06 1.48E+05 Pr-143 1.40E+04 5.24E+03 6.99E+02 0.OOE+00 1.97E+03 4.33E+05 3.72E+04 Pr-144 4.79E-02 1.85E-02 2.41E-03 0.OOE+00 6.72E-03 1.61E+03 4.28E+03 Nd-147 7.94E+03 8.13E+03 5.OOE+02 0.OOE+00 3.15E+03 3.22E+05 3.12E+04 W-187 1.30E+01 9.02E+00 3.12E+00 0.OOE+00 0.OOE+00 3.96E+04 3.56E+04 Np-239 3.71EE+02 2.98E+02 1.88E+01 0.OOE+00 6.62E+01 5.95E+04 2.49E+04 Notes:

1) Units are mrem/yr per pLCi/m 3 .

Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 260 of 307 January 2013 Table 4-16 (Page 1 of 6) Vegetation Dose Factors Adult Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI H-3 O.OOE+00 1.29E+03 1.29E+03 1.29E+03 1.29E+03 1.29E+03 1.29E+03 C-14 8.97E+05 1.79E+05 1.79E+05 1.79E+05 1.79E+05 1.79E+05 1.79E+05 Na-24 2.69E+05 2.69E+05 2.69E+05 2.69E+05 2.69E+05 2.69E+05 2.69E+05 Cr-51 O.OOE+00 O.OOE+00 4.64E+04 2.77E+04 1.02E+04 6.15E+04 1.17E+07 Mn-54 O.OOE+00 3.13E+08 5.97E+07 O.OOE+00 9.31E+07 O.OOE+00 9.58E+08 Mn-56 O.OOE+00 1.54E+01 2.73E+00 O.OOE+00 1.95E+01 O.OOE+00 4.91E+02 Fe-55 2.1OE+08 1.45E+08 3.38E+07 O.OOE+00 O.OOE+00 8.08E+07 8.31E+07 Fe-59 1.26E+08 2.96E+08 1.13E+08 O.OOE+00 O.OOE+00 8.27E+07 9.87E+08 Co-58 O.OOE+00 3.08E+07 6.90E+07 O.OOE+00 O.OOE+00 O.OOE+00 6.24E+08 Co-60 O.OOE+00 1.67E+08 3.69E+08 O.OOE+00 O.OOE+00 O.OOE+00 3.14E+09 Ni-63 1.04E+10 7.21E+08 3.49E+08 O.OOE+00 O.OOE+00 O.OOE+00 1.50E+08 Ni-65 5.97E+01 7.75E+00 3.54E+00 O.OOE+00 O.OOE+00 O.OOE+00 1.97E+02 Cu-64 O.OOE+00 9.09E+03 4.27E+03 O.OOE+00 2.29E+04 O.OOE+00 7.75E+05 Zn-65 3.17E+08 1.01E+09 4.56E+08 O.OOE+00 6.75E+08 O.OOE+00 6.36E+08 Zn-69 4.95E-06 9.48E-06 6.59E-07 O.OOE+00 6.16E-06 O.OOE+00 1.42E-06 Br-83 O.OOE+00 O.OOE+00 3.OOE+00 O.OOE+00 O.00E+00 O.OOE+00 4.32E+00 Br-84 O.OOE+00 O.OOE+00 2.20E-11 O.OOE+00 O.OOE+00 O.OOE+OO 1.72E-16 Br-85 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.00F+00 O.OOE+00 O.OOE+00 Rb-86 O.OOE+00 2.20E+08 1.03E+08 O.OOE+00 O.OOE+00 O.OOE+00 4.34E+07 Rb-88 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 Rb-89 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Sr-89 9.95E+09 O.OOE+00 2.86E+08 O.OOE+00 O.OOE+00 O.OOE+00 1.60E+09 Sr-90 6.95E+11 O.OOE+00 1.40E+10 O.OOE+00 O.OOE+00 O.OOE+00 1.75E+10 Sr-91 3.01E+05 O.OOE+00 1.22E+04 O.OOE+00 O.OOE+00 O.OOE+00 1.43E+06 Sr-92 4.12E+02 O.OOE+00 1.78E+01 O.OOE+00 O.OOE+00 O.OOE+00 8.17E+03 Y-90 1.33E+04 O.OOE+00 3.57E+02 O.OOE+00 O.OOE+00 O.OOE+00 1.41E+08 Y-91M 4.93E-09 O.OOE+00 1.91E-10 O.OOE+00 O.OOE+00 O.OOE+00 1.45E-08 Y-91 5.12E+06 O.00E+00 1.37E+05 Q.OOE+00 O.OOE+00 O.OOE+00 2.82E+09 Y-92 8.95E-01 O.OOE+00 2.62E-02 O.OOE+00 O.OOE+00 O.OOE+00 1.57E+04 Y-93 1.67E+02 O.OOE+00 4.62E+00 O.OOE+00 O.OOE+00 O.OOE+00 5.31E+06 Zr-95 1.18E+06 3.77E+05 2.55E+05 O.OOE+00 5.92E+05 O.OOE+00 1.20E+09 Zr-97 3.35E+02 6.77E+01 3.09E+01 O.OOE+00 1.02E+02 O.OOE+00 2.10E+07 Nb-95 1.43E+05 7.95E+04 4.27E+04 O.OOE+00 7.86E+04 O.OOE+00 4.83E+08 Mo-99 O.OOE+00 6.14E+06 1.17E+06 O.OOE+00 1.39E+07 O.OOE+O0 1.42E+07 Tc-99M 3.06E+00 8.64E+00 1.10E+02 O.OOE+00 1.31E+02 4.23E+00 5.11E+03 Tc-101 O.OOE+00 O.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ru-103 4.77E+06 O.OOE+00 2.05E+06 O.OOE+00 1.82E+07 O.OOE+00 5.57E+08 Ru-105 5.27E+01 O.OOE+00 2.08E+01 O.OOE+00 6.81E+02 O.OOE+00 3.23E+04 Ru-106 1.93E+08 O.OOE+00 2.44E+07 O.OOE+00 3.72E+08 O.OOE+00 1.25E+10 Ag-110M 1.05E+07 9.75E+06 5.79E+06 O.OOE+00 1.92E+07 O.OOE+00 3.98E+09 Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 261 of 307 January 2013 Table 4-16 (Page 2 of 6) Vegetation Dose Factors Adult A e Group Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI Te-125M 9.67E+07 3.50E+07 1.30E+07 2.91E+07 3.93E+08 O.OOE+00 3.86E+08 Te-127M 3.49E+08 1.25E+08 4.26E+07 8.92E+07 1.42E+09 0.OOE+00 1.17E+09 Te-127 5.68E+03 2.04E+03 1.23E+03 4.21E+03 2.31E+04 0.OOE+00 4.48E+05 Te-129M 2.51E+08 9.37E+07 3.97E+07 8.62E+07 1.05E+09 0.OOE+00 1.26E+09 Te-129 7.14E-04 2.68E-04 1.74E-04 5.48E-04 3.OOE-03 O.OOE+00 5.39E-04 Te-131M 9.09E+05 4.45E+05 3.71E+05 7.04E+05 4.50E+06 0.OOE+00 4.41E+07 Te-131 1.26E-15 5.26E-16 3.97E-16 1.03E-15 5.51E-15 0.OOE+00 1.78E-16 Te-132 4.28E+06 2.77E+06 2.60E+06 3.06E+06 2.67E+07 0.OOE+00 1.31E+08 1-130 3.89E+05 1.15E+06 4.52E+05 9.72E+07 1.79E+06 0.OOE+00 9.87E+05 1-131 8.07E+07 1.15E+08 6.62E+07 3.78E+10 1.98E+08 0.OOE+00 3.05E+07 1-132 5.58E+01 1.49E+02 5.22E+01 5.22E+03 2.38E+02 0.OOE+00 2.80E+01 1-133 2.08E+06 3.62E+06 1.IOE+06 5.32E+08 6.31EE+06 O.OOE+00 3.25E+06 1-134 8.55E-05 2.32E-04 8.31E-05 4.02E-03 3.69E-04 0.OOE+00 2.02E-07 1-135 3.87E+04 1.01E+05 3.74E+04 6.68E+06 1.62E+05 0.OOE+00 1.14E+05 Cs-134 4.67E+09 1.11E+10 9.08E+09 0.OOE+00 3.59E+09 1.19E+09 1.94E+08 Cs-136 4.25E+07 1.68E+08 1.21E+08 0.OOE+00 9.33E+07 1.28E+07 1.90E+07 Cs-137 6.36E+09 8.70E+09 5.70E+09 O.OOE+00 2.95E+09 9.81E+08 1.68E+08 Cs-138 3.32E-11 6.56E-11 3.25E-11 0.OOE+00 4.82E-11 4.76E-12 2.80E-16 Ba-139 2.71E-02 1.93E-05 7.92E-04 0.OOE+00 1.80E-05 1.09E-05 4.80E-02 Ba-140 1.29E+08 1.61EE+05 8.42E+06 O.OOE+00 5.49E+04 9.24E+04 2.65E+08 Ba-141 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 O.OOE+00 Ba-142 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 La-140 1.98E+03 9.97E+02 2.63E+02 0.OOE+00 O.OOE+00 0.OOE+00 7.32E+07 La-142 1.94E-04 8.83E-05 2.20E-05 O.OOE+00 0.OOE+00 0.OOE+00 6.45E-01 Ce-141 1.97E+05 1.33E+05 1.51E+04 0.OOE+00 6.19E+04 0.OOE+00 5.09E+08 Ce-143 9.94E+02 7.35E+05 8.13E+01 0.OOE+00 3.24E+02 O.OOE+00 2.75E+07 Ce-144 3.29E+07 1.38E+07 1.77E+06 0.OOE+00 8.16E+06 O.OOE+00 1.11E+10 Pr-143 6.27E+04 2.51EE+04 3.11E+03 0.OOE+00 1.45E+04 O.OOE+00 2.75E+08 Pr-144 0.OOE+00 O.OOE+00 O.OOE+0( 0.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 Nd-147 3.37E+04 3.90E+04 2.33E+03 0.OOE+00 2.28E+04 0.OOE+00 1.87E+08 W-187 3.79E+04 3.17E+04 1.11E+04 0.OOE+00 0.OOE+00 0.OOE+00 1.04E+07 Np-239 1.42E+03 1.40E+02 7.72E+01 O.OOE+00 4.37E+02 0.OOE+00 2.87E+07 Notes:

1) Units are m2 mrem/yr per pCi/sec with the exception of H-3 and C-14.

2) For H-3 and C-14, the units are mrem/yr per [iCi/m 3 .

Quad Cities ODCM Part II

CY-QC-1770-301 Revision 11 Page 262 of 307 January 2013 Table 4-16 (Page 3 of 6) Vegetation Dose Factors Teen Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI H-3 0.OOE+00 1.47E+03 1.47E+03 1.47E+03 1.47E+03 1.47E+03 1.47E+03 C-14 1.45E+06 2.91E+05 2.91EE+05 2.91E+05 2.91E+05 2.91E+05 2.911E+05 Na-24 2.39E+05 2.39E+05 2.39E+05 2.39E+05 2.39E+05 2.39E+05 2.39E+05 Cr-51 0.OOE+00 0.OOE+00 6.16E+04 3.42E+04 1.35E+04 8.79E+04 1.03E+07 Mn-54 0.OOE+00 4.54E+08 9.01E+07 0.OOE+00 1.36E+08 0.OOE+00 9.32E+08 Mn-56 0.OOE+00 1.39E+01 2.47E+00 O.OOE+00 1.76E+01 O.OOE+00 9.13E+02 Fe-55 3.26E+08 2.31 E+08 5.39E+07 0.OOE+00 0.OOE+00 1.47E+08 1.OOE+08 Fe-59 1.79E+08 4.18E+08 1.61E+08 0.OOE+00 O.OOE+00 1.32E+08 9.89E+08 Co-58 0.OOE+00 4.37E+07 1.01E+08 O.OOE+00 O.OOE+00 0.OOE+00 6.02E+08 Co-60 0.OOE+00 2.49E+08 5.60E+08 O.00E+00 0.OOE+00 0.OOE+00 3.24E+09 Ni-63 1.61E+10 1.13E+09 5.45E+08 O.OOE+00 O.OOE+00 0.OOE+00 1.81E+08 Ni-65 5.55E+01 7.1OE+00 3.23E+00 0.OOE+00 0.OOE+00 0.OOE+00 3.85E+02 Cu-64 0.OOE+00 8.24E+03 3.87E+03 0.OOE+00 2.08E+04 0.OOE+00 6.39E+05 Zn-65 4.24E+08 1.47E+09 6.86E+08 0.OOE+00 9.411E+08 0.OOE+00 6.23E+08 Zn-69 4.64E-06 8.84E-06 6.19E-07 0.OOE+00 5.78E-06 0.OOE+00 1.63E-05 Br-83 0.OOE+00 0.OOE+00 2.81EE+00 0.OOE+00 0.OOE+00 0.OOE+0O 0.OOE+00 Br-84 0.OOE+00 0.OOE+00 2.OOE-1 1 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 Br-85 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Rb-86 0.OOE+00 2.75E+08 1.29E+08 0.OOE+00 0.OOE+00 O.OOE+00 4.06E+07 Rb-88 0.OOE+00 0.OOE+00 O.00E+0O 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 Rb-89 O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Sr-89 1.51E+10 0.OOE+00 4.33E+08 O.OOE+00 O.OOE+00 0.OOE+00 1.80E+09 Sr-90 9.22E+11 O.OOE+00 1.84E+10 O.OOE+00 O.OOE+00 O.0OE+00 2.11E+10 Sr-91 2.81E+05 O.OOE+00 1.12E+04 O.OOE+00 O.OOE+00 O.OOE+00 1.27E+06 Sr-92 3.84E+02 O.OOE+00 1.64E+01 O.OOE+00 O.OOE+00 O.00E+00 9.78E+03 Y-90 1.24E+04 O.OOE+00 3.35E+02 O.OOE+00 O.OOE+00 O.OOE+00 1.02E+08 Y-91M 4.59E-09 O.OOE+00 1.75E-10 O.00E+00 O.OOE+00 O.OOE+00 2.17E-07 Y-91 7.84E+06 O.OOE+00 2.10E+05 O.OOE+00 O.OOE+00 O.OOE+00 3.21E+09 Y-92 8.41E-01 0.OOE+00 2.43E-02 O.OOE+00 O.OOE+00 O.OOE+00 2.31E+04 Y-93 1.57E+02 0.OOE+00 4.30E+00 O.OOE+00 0.OOE+00 O.OOE+00 4.80E+06 Zr-95 1.72E+06 5.44E+05 3.74E+05 O.OOE+00 7.99E+05 O.OOE+00 1.26E+09 Zr-97 3.10E+02 6.14E+01 2.83E+01 0.OOE+00 9.31E+01 O.OOE+00 1.66E+07 Nb-95 1.93E+05 1.07E+05 5.90E+04 0.OOE+00 1.04E+05 O.OOE+00 4.58E+08 Mo-99 O.OOE+00 5.63E+06 1.07E+06 0.OOE+00 1.29E+07 0.OOE+00 1.01E+07 Tc-99M 2.70E+00 7.52E+00 9.75E+01 0.OOE+00 1.12E+02 4.17E+00 4.94E+03 Tc-101 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 Ru-103 6.82E+06 0.OOE+00 2.91E+06 0.OOE+00 2.40E+07 O.OOE+00 5.69E+08 Ru-105 4.90E+01 0.OOE+00 1.90E+01 0.OOE+00 6.18E+02 O.OOE+00 3.95E+04 Ru-106 3.09E+08 0.OOE+00 3.90E+07 0.00E+00 5.97E+08 0.OOE+00 1.48E+10 Ag-110M 1.52E+07 1.44E+07 8.73E+06 0.OOE+00 2.74E+07 O.OOE+00 4.03E+09 Quad Cities ODCM Part II

CY-QC-170-301 Revision 11 Page 263 of 307 January 2013 Table 4-16 (Page 4 of 6) Vegetation Dose Factors Teen Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI Te-125M 1.49E+08 5.35E+07 1.99E+07 4.15E+07 O.OOE+00 O.OOE+00 4.38E+08 Te-127M 5.51EE+08 1.96E+08 6.56E+07 1.31E+08 2.24E+09 O.OOE+00 1.37E+09 Te-127 5.36E+03 1.90E+03 1.15E+03 3.70E+03 2.17E+04 O.OOE+00 4.14E+05 Te-129M 3.61E+08 1.34E+08 5.72E+07 1.17E+08 1.51E+09 O.OOE+00 1.36E+09 Te-129 6.68E-04 2.49E-04 1.63E-04 4.77E-04 2.80E-03 O.OOE+00 3.65E-03 Te-131M 8.42E+05 4.04E+05 3.37E+05 6.07E+05 4.21E+06 O.OOE+00 3.24E+07 Te-131 1.17E-15 4.82E-16 3.66E-16 9.01E-16 5.11E-15 O.OOE+00 9.60E-17 Te-132 3.89E+06 2.46E+06 2.32E+06 2.60E+06 2.36E+07 O.OOE+00 7.81E+07 1-130 3.47E+05 1.01E+06 4.01E+05 8.20E+07 1.55E+06 O.OOE+00 7.73E+05 1-131 7.68E+07 1.08E+08 5.78E+07 3.14E+10 1.85E+08 O.OOE+00 2.13E+07 1-132 5.03E+01 1.32E+02 4.72E+01 4.43E+03 2.07E+02 O.OOE+00 5.73E+01 1-133 1.93E+06 3.28E+06 1.OOE+06 4.58E+08 5.75E+06 0.OOE+00 2.48E+06 1-134 7.73E-05 2.05E-04 7.36E-05 3.41E-03 3.23E-04 O.OOE+00 2.70E-06 1-135 3.49E+04 8.99E+04 3.33E+04 5.78E+06 1.42E+05 0.OOE+00 9.97E+04 Cs-134 7.10E+09 1.67E+10 7.75E+09 0.OOE+00 5.31E+09 2.03E+09 2.08E+08 Cs-136 4.35E+07 1.71E+08 1.15E+08 0.OOE+00 9.31E+07 1.47E+07 1.38E+07 Cs-137 1.01E+10 1.35E+10 4.69E+09 0.OOE+00 4.59E+09 1.78E+09 1.92E+08 Cs-138 3.07E-11 5.89E-11 2.94E-11 O.OOE+00 4.35E-11 5.06E-12 2.67E-14 Ba-139 2.55E-02 1.79E-05 7.42E-04 0.OOE+00 1.69E-05 1.23E-05 2.27E-01 Ba-140 1.38E+08 1.69E+05 8.90E+06 0.OOE+00 5.74E+04 1.14E+05 2.13E+08 Ba-141 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Ba-142 0.OOE+00 0.00E+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 La-140 1.81E+03 8.88E+02 2.36E+02 0.OOE+00 O.OOE+00 O.OOE+00 5.1OE+07 La-142 1.78E-04 7.92E-05 1.97E-05 0.OOE+00 O.OOE+00 0.OOE+00 2.41E+00 Ce-141 2.83E+05 1.89E+05 2.17E+04 0.OOE+00 8.89E+04 0.OOE+00 5.40E+08 Ce-143 9.29E+02 6.76E+05 7.55E+01 O.OOE+00 3.03E+02 0.OOE+00 2.03E+07 Ce-144 5.27E+07 2.18E+07 2.83E+06 0.OOE+00 1.30E+07 0.OOE+00 1.33E+10 Pr-143 7.01E+04 2.80E+04 3.49E+03 0.OOE+00 1.63E+04 0.OOE+00 2.31E+08 Pr-144 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+0O 0.OOE+00 Nd-147 3.67E+04 4.OOE+04 2.39E+03 0.OOE+00 2.35E+04 0.00E+00 1.44E+08 W-187 3.53E+04 2.87E+04 1.01E+04 O.OOE+00 0.OOE+00 O.OOE+00 7.78E+06 Np-239 1.38E+03 1.30E+02 7.24E+01 0.OOE+00 4.09E+02 0.OOE+00 2.1OE+07 Notes:

1) Units are m 2 mrem/yr per [tCi/sec with the exception of H-3 and C-14.

2) For H-3 and C-14, the units are mrem/yr per i.Ci/m 3.

Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 264 of 307 January 2013 Table 4-16 (Page 5 of 6) Vegetation Dose Factors Child Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI H-3 0.OOE+00 2.29E+03 2.29E+03 2.29E+03 2.29E+03 2.29E+03 2.29E+03 C-14 3.50E+06 7.01E+05 7.01E+05 7.01E+05 7.01E+05 7.01E+05 7.01E+05 Na-24 3.73E+05 3.73E+05 3.73E+05 3.73E+05 3.73E+05 3.73E+05 3.73E+05 Cr-51 0.OOE+00 0.OOE+00 1.17E+05 6.49E+04 1.77E+04 1.18E+05 6.20E+06 Mn-54 0.OOE+00 6.65E+08 1.77E+08 0.OOE+00 1.86E+08 0.00E+00 5.58E+08 Mn-56 0.OOE+00 1.82E+01 4.1OE+00 0.OOE+00 2.20E+01 0.OOE+00 2.63E+03 Fe-55 8.01 E+08 4.25E+08 1.32E+08 0.OOE+00 0.OOE+00 2.40E+08 7.87E+07 Fe-59 3.97E+08 6.42E+08 3.20E+08 0.OOE+00 O.OOE+00 1.86E+08 6.69E+08 Co-58 0.00E+00 6.45E+07 1.97E+08 0.OOE+00 0.OOE+00 O.OOE+00 3.76E+08 Co-60 0.OOE+00 3.78E+08 1.12E+09 O.OOE+00 O.OOE+00 O.OOE+00 2.10E+09 Ni-63 3.95E+10 2.11E+09 1.34E+09 0.OOE+00 O.OOE+00 O.OOE+00 1.42E+08 Ni-65 1.02E+02 9.59E+00 5.60E+00 0.OOE+00 0.OOE+00 0.OOE+00 1.18E+03 Cu-64 O.OOE+00 1.09E+04 6.56E+03 O.OOE+00 2.62E+04 O.OOE+00 5.10E+05 Zn-65 8.12E+08 2.16E+09 1.35E+09 0.OOE+00 1.36E+09 O.OOE+00 3.80E+08 Zn-69 8.56E-06 1.24E-05 1.14E-06 0.OOE+00 7.50E-06 O.OOE+00 7.80E-04 Br-83 0.OOE+00 0.OOE+00 5.18E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Br-84 0.OOE+00 0.OOE+00 3.39E-11 0.OOE+00 O.OOE+0 0.OOE+00 0.00E+00 Br-85 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+0O 0.OOE+00 Rb-86 0.OOE+00 4.54E+08 2.79E+08 0.OOE+00 O.OOE+00 0.OOE+00 2.92E+07 Rb-88 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Rb-89 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 Sr-89 3.59E+10 0.OOE+00 1.03E+09 0.OOE+00 0.OOE+00 0.OOE+00 1.39E+09 Sr-90 1.87E+12 0.OOE+00 3.77E+10 0.OOE+00 0.OOE+00 0.OOE+00 1.67E+10 Sr-91 5.17E+05 0.OOE+00 1.95E+04 0.OOE+00 0.OOE+00 0.OOE+00 1.14E+06 Sr-92 7.04E+02 0.OOE+00 2.82E+01 0.OOE+00 0.OOE+00 0.OOE+00 1.33E+04 Y-90 2.31E+04 0.OOE+00 6.18E+02 0.OOE+00 0.OOE+00 O.OOE+00 6.57E+07 Y-91M 8.42E-09 O.OOE+00 3.06E-10 O.OOE+00 O.OOE+00 O.OOE+00 1.65E-05 Y-91 1.87E+07 0.OOE+00 4.99E+05 0.OOE+00 0.OOE+00 0.OOE+00 2.49E+09 Y-92 1.55E+00 0.OOE+00 4.43E-02 O.OOE+00 0.OOE+0 0.OOE+00 4.47E+04 Y-93 2.89E+02 0.OOE+00 7.94E+00 0.OOE+00 0.OOE+00 0.OOE+00 4.31E+06 Zr-95 3.86E+06 8.50E+05 7.56E+05 0.OOE+00 1.22E+06 O.OOE+00 8.86E+08 Zr-97 5.67E+02 8.19E+01 4.83E+01 o.0OE+00 1.18E+02 0.OOE+00 1.24E+07 Nb-95 4.12E+05 1.61E+05 1.15E+05 0.OOE+00 1.51E+05 0.OOE+00 2.97E+08 Mo-99 0.OOE+00 7.69E+06 1.90E+06 0.OOE+00 1.64E+07 0.OOE+00 6.36E+06 Tc-99M 4.64E+00 9.1OE+00 1.51E+02 O.OOE+00 1.32E+02 4.62E+00 5.18E+03 Tc-101 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 Ru-103 1.53E+07 O.OOE+00 5.89E+06 0.OOE+00 3.86E+07 0.OOE+00 3.96E+08 Ru-105 8.97E+01 0.OOE+00 3.25E+01 0.OOE+00 7.89E+02 0.00E+00 5.86E+04 Ru-106 7.45E+08 0.OOE+0O 9.30E+07 0.OOE+00 1.01E+09 0.OOE+00 1.16E+10 Ag-110M 3.21E+07 2.17E+07 1.74E+07 0.00E+00 4.04E+07 0.OOE+00 2.58E+09 Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 265 of 307 January 2013 Table 4-16 (Page 6 of 6) Vegetation Dose Factors Child Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI Te-125M 3.51E+08 9.52E+07 4.68E+07 9.86E+07 0.00E+00 0.OOE+00 3.39E+08 Te-127M 1.32E+09 3.56E+08 1.57E+08 3.16E+08 3.77E+09 0.OOE+00 1.07E+09 Te-127 9.89E+03 2.67E+03 2.12E+03 6.84E+03 2.81E+04 0.OOE+00 3.86E+05 Te-129M 8.40E+08 2.35E+08 1.30E+08 2.71E+08 2.47E+09 0.OOE+00 1.02E+09 Te-129 1.24E-03 3.45E-04 2.94E-04 8.83E-04 3.62E-03 0.OOE+00 7.70E-02 Te-131M 1.54E+06 5.32E+05 5.66E+05 1.09E+06 5.15E+06 0.OOE+00 2.16E+07 Te-131 2.15E-15 6.57E-16 6.41E-16 1.65E-15 6.51E-15 0.OOE+00 1.13E-14 Te-132 6.97E+06 3.09E+06 3.73E+06 4.49E+06 2.86E+07 0.OOE+00 3.11E+07 1-130 6.1OE+05 1.23E+06 6.35E+05 1.36E+08 1.84E+06 0.OOE+00 5.76E+05 1-131 1.43E+08 1.44E+08 8.17E+07 4.75E+10 2.36E+08 0.OOE+00 1.28E+07 1-132 8.93E+01 1.64E+02 7.54E+01 7.61E+03 2.51E+02 0.OOE+00 1.93E+02 1-133 3.52E+06 4.36E+06 1.65E+06 8.09E+08 7.26E+06 0.OOE+00 1.76E+06 1-134 1.37E-04 2.55E-04 1.17E-04 5.86E-03 3.90E-04 O.OOE+00 1.69E-04 1-135 6.20E+04 1.12E+05 5.28E+04 9.89E+06 1.71E+05 0.OOE+00 8.51E+04 Cs-134 1.60E+10 2.63E+10 5.55E+09 0.OOE+00 8.16E+09 2.93E+09 1.42E+08 Cs-136 8.18E+07 2.25E+08 1.46E+08 0.OOE+00 1.20E+08 1.79E+07 7.90E+06 Cs-137 2.39E+10 2.29E+10 3.38E+09 0.OOE+00 7.46E+09 2.68E+09 1.43E+08 Cs-138 5.58E-11 7.75E-11 4.92E-11 0.OOE+00 5.45E-11 5.87E-12 3.57E-11 Ba-139 4.69E-02 2.51E-05 1.36E-03 0.OOE+00 2.19E-05 1.47E-05 2.71E+00 Ba-140 2.77E+08 2.43E+05 1.62E+07 O.OOE+00 7.90E+04 1.45E+05 1.40E+08 Ba-141 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+0O 0.00E+00 0.OOE+00 0.OOE+00 Ba-142 0.OOE+00 0.OOE+00 O.OOE+00 0. OOE+00 0.00E+0O 0.OOE+00 0.OOE+00 La-140 3.25E+03 1.13E+03 3.82E+02 0.00E+00 0.OOE+00 0.OOE+00 3.16E+07 La-142 3.23E-04 1.03E-04 3.22E-05 O.OOE+00 0.00E+00 0.OOE+00 2.04E+01 Ce-141 6.55E+05 3.27E+05 4.85E+04 O.OOE+00 1.43E+05 0.OOE+00 4.08E+08 Ce-143 1.71E+03 9.28E+05 1.34E+02 0.OOE+00 3.89E+02 0.0OE+00 1.36E+07 Ce-144 1.27E+08 3.98E+07 6.78E+06 O.OOE+00 2.21E+07 0.OOE+00 1.04E+10 Pr-143 1.46E+05 4.38E+04 7.24E+03 0.OOE+00 2.37E+04 0.OOE+00 1.57E+08 Pr-144 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 Nd-147 7.27E+04 5.89E+04 4.56E+03 0.OOE+00 3.23E+04 0.OOE+00 9.33E+07 W-187 6.41E+04 3.80E+04 1.70E+04 0.OOE+00 0.OOE+00 0.OOE+00 5.34E1:+06 Np-239 2.55E+03 1.83E+02 1.29E+02 0.OOE+00 5.30E+02 0.OOE+00 1.36E+07 Notes:

1) Units are m 2 mrem/yr per [tCi/sec with the exception of H-3 and C-14.

3

2) For H-3 and C-14, the units are mrem/yr per i.LCi/m .

3) The infant age group is assumed to receive no due through the vegetation ingestion pathway therefore no dose factors are supplied.

Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 266 of 307 January 2013 Table 4-17 (Page 1 of 8) Grass-Cow-Milk Dose Factors Adult Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI H-3 O.OOE+00 4.35E+02 4.35E+02 4.35E+02 4.35E+02 4.35E+02 4.35E+02 C-14 3.63E+05 7.26E+04 7.26E+04 7.26E+04 7.26E+04 7.26E+04 7.26E+04 Na-24 2.46E+06 2.46E+06 2.46E+06 2.46E+06 2.46E+06 2.46E+06 2.46E+06 Cr-51 O.OOE+00 O.OOE+00 2.86E+04 1.71E+04 6.29E+03 3.79E+04 7.18E+06 Mn-54 O.OOE+00 8.41E+06 1.61EE+06 O.OOE+00 2.50E+06 O.OOE+00 2.58E+07 Mn-56 O.OOE+00 4.13E-03 7.32E-04 O.OOE+00 5.24E-03 O.OOE+00 1.32E-01

          -Fe-55    2.51E+07  1.74E+07  4.05E+06 O.OOE+00   O.OOE+00  9.68E+06 9.95E+06 Fe-59     2.97E+07  6.98E+07  2.67E+07 O.OOE+00   O.OOE+00  1.95E+07 2.33E+08 Co-58     O.OOE+00  4.72E+06   1.06E+07 O.OOE+00  O.OOE+00  O.OOE+00 9.56E+07 Co-60     O.OOE+00  1.64E+07  3.62E+07 O.OOE+00   O.OOE+00  O.00E+00 3.08E+08 Ni-63     6.73E+09  4.66E+08  2.26E+08 O.OOE+00   O.OOE+00  O.OOE+00 9.73E+07 Ni-65      3.70E-01  4.81E-02  2.19E-02 O.OOE+00  O.OOE+00  O.OOE+00 1.22E+00 Cu-64     O.OOE+00  2.36E+04   1.11E+04 O.OOE+00  5.95E+04  O.OOE+00 2.01E+06 Zn-65     1.37E+09  4.36E+09   1.97E+09 O.OOE+00  2.92E+09  O.OOE+00 2.75E+09 Zn-69      2.01E-12  3.84E-12  2.67E-13 O.OOE+00   2.50E-12 O.OOE+00  5.78E-13 Br-83     O.OOE+00  O.OOE+00   9.65E-02 O.OOE+00  O.OOE+00  O.OOE+00  1.39E-01 Br-84     O.OOE+00  O.OOE+00  O.OOE+00 O.OOE+00   O.OOE+00  O.OOE+00 O.OOE+00 Br-85     O.OOE+00  O.OOE+00  O.OOE+00 O.00E+00   O.OOE+00  O.OOE+00 O.OOE+00 Rb-86     O.OOE+00  2.60E+09   1.21EE+09 O.OOE+00 O.OOE+00  O.OOE+00 5.12E+08 Rb-88     O.OOE+00  O.OOE+00   O.OOE+00 O.OOE+00  O.OOE+00  O.OOE+00 O.OOE+00 Rb-89     O.OOE+00  O.OOE+00   O.OOE+00 O.OOE+00  O.OOE+00  O.OOE+00 O.OOE+00 Sr-89     1.45E+09  O.OOE+00  4.16E+07 O.OOE+00   O.OOE+00  O.OOE+00 2.33E+08 Sr-90     5.38E+10  O.OOE+00   1.08E+09 O.OOE+00  O.OOE+00  O.OOE+00 1.35E+09 Sr-91     2.87E+04  O.OOE+00   1.16E+03 O.OOE+00  O.OOE+00  O.OOE+00 1.37E+05 Sr-92      4.84E-01 O.OOE+00   2.09E-02 O.OOE+00  O.OOE+00  O.OOE+00 9.58E+00 Y-90      7.1OE+01  O.OOE+00   1.90E+00 O.OOE+00  O.OOE+00  O.OOE+00 7.52E+05 Y-91M      6.42E-20 O.OOE+00  O.OOE+00 O.OOE+00   O.OOE+00  O.OOE+00  1.89E-19 Y-91      8.59E+03  O.OOE+00  2.30E+02 O.OOE+00   O.OOE+00  O.OOE+00 4.73E+06 Y-92       5.57E-05 O.OOE+00   1.63E-06 O.OOE+00  O.OOE+00  O.OOE+00  9.75E-01 Y-93       2.22E-01 O.00E+00   6.12E-03 O.OOE+00  O.OOE+00  O.OOE+00 7.03E+03 Zr-95     9.44E+02  3.03E+02  2.05E+02 O.OOE+00   4.75E+02  O.OOE+00 9.59E+05 Zr-97      4.32E-01  8.72E-02  3.99E-02 O.OOE+00   1.32E-01 O.OOE+00 2.70E+04 Nb-95     8.26E+04  4.60E+04  2.47E+04 O.OOE+00   4.54E+04  O.00E+00 2.79E+08 Mo-99     O.OOE+00  2.47E+07  4.70E+06 O.OOE+00   5.60E+07  O.OOE+00 5.73E+07 Tc- 99M   3.31EE+00 9.35E+00  1.19E+02 O.OOE+00   1.42E+02  4.58E+00 5.53E+03 Tc-101    O.00E+00  O.OOE+00  O.OOE+00 O.OOE+00   O.OOE+00  O.OOE+00 0.00E+00 Ru-103    1.02E+03  O.OOE+00  4.39E+02 O.00E+00   3.88E+03  O.OOE+00 1.19E+05 Ru-105     8.51E-04 O.OOE+00   3.36E-04 O.OOE+00   1.10E-02 O.OOE+00  5.20E-01 Ru-106    2.04E+04  O.OOE+00  2.58E+03 O.OOE+00   3.94E+04  O.OOE+00 1.32E+06 Ag-110M   5.82E+07  5.39E+07  3.20E+07 O.OOE+00   1.06E+08  O.OOE+00 2.20E+10 Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 267 of 307 January 2013 Table 4-17 (Page 2 of 8) Grass-Cow-Milk Dose Factors Adult Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI Te-125M 1.63E+07 5.91EE+06 2.18E+06 4.90E+06 6.63E+07 O.OOE+00 6.51E+07 Te-127M 4.58E+07 1.64E+07 5.58E+06 1.17E+07 1.86E+08 0.OOE+00 1.54E+08 Te-127 6.66E+02 2.39E+02 1.44E+02 4.94E+02 2.71E+03 0.OOE+00 5.26E+04 Te-129M 6.02E+07 2.24E+07 9.52E+06 2.07E+07 2.51E+08 O.OOE+00 3.03E+08 Te-129 2.83E-10 1.06E-10 6.88E-11 2.17E-10 1.19E-09 0.OOE+00 2.13E-10 Te-131M 3.61E+05 1.76E+05 1.47E+05 2.79E+05 1.79E+06 0.OOE+00 1.75E+07 Te-131 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 Te-132 2.39E+06 1.55E+06 1.45E+06 1.71E+06 1.49E+07 0.OOE+00 7.32E+07 1-130 4.18E+05 1.23E+06 4.86E+05 1.04E+08 1.92E+06 0.OOE+00 1.06E+06 1-131 2.96E+08 4.23E+08 2.43E+08 1.39E+11 7.26E+08 0.OOE+00 1.12E+08 1-132 1.65E-01 4.40E-01 1.54E-01 1.54E+011 7.02E-01 0.OOE+00 8.27E-02 1-133 3.88E+06 6.74E+06 2.06E+06 9.91E+08 1.18E+07 0.OOE+00 6.06E+06 1-134 1.89E-12 5.13E-12 1.83E-12 8.89E-11 8.16E-12 0.OOE+00 4.47E-15 1-135 1.29E+04 3.38E+04 1.25E+04 2.23E+06 5.42E+04 0.OOE+00 3.82E+04 Cs-134 5.65E+09 1.35E+10 1.10E+10 O.OOE+00 4.35E+09 1.45E+09 2.35E+08 Cs-136 2.63E+08 1.04E+09 7.46E+08 0.OOE+00 5.77E+08 7.91E+07 1.18E+08 Cs-137 7.38E+09 1.01E+10 6.61E+09 0.OOE+00 3.43E+09 1.14E+09 1.95E+08 Cs-138 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 Ba-139 4.43E-08 3.16E-11 1.30E-09 0.OOE+00 2.95E-11 1.79E-11 7.86E-08 Ba-140 2.69E+07 3.38E+04 1.76E+06 0.OOE+00 1.15E+04 1.93E+04 5.54E+07 Ba-141 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 Ba-142 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 La-140 4.52E+00 2.28E+00 6.02E-01 0.OOE+00 0.OOE+00 O.OOE+00 1.67E+05 La-142 1.89E-11 8.59E-12 2.14E-12 0.OOE+00 0.OOE+00 O.OOE+00 6.28E-08 Ce-141 4.84E+03 3.28E+03 3.72E+02 O.OOE+00 1.52E+03 0.OOE+00 1.25E+07 Ce-143 4.15E+01 3.07E+04 3.39E+00 0.OOE+00 1.35E+01 O.OOE+00 1.15E+06 Ce-144 3.58E+05 1.50E+05 1.92E+04 0.OOE+00 8.87E+04 O.OOE+00 1.21E+08 Pr-143 1.58E+02 6.34E+01 7.83E+00 0.OOE+00 3.66E+01 0.OOE+00 6.92E+05 Pr-144 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Nd-147 9.48E+01 1.10E+02 6.56E+00 0.OOE+00 6.41E+01 0.OOE+00 5.26E+05 W-187 6.51E+03 5.44E+03 1.90E+03 O.OOE+00 0.OOE+00 0.OOE+00 1.78E+06 Np-239 3.67E+00 3.61E-01 1.99E-01 0.00E+00 1.12E+00 0.OOE+00 7.40E+04 Notes:

1) Units are m 2 mrem/yr per pCi/sec with the exception of H-3 and C-14.

2) For H-3 and C-14, the units are mrem/yr per jiCi/m3 .

Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 268 of 307 January 2013 Table 4-17 (Page 3 of 8) Grass-Cow-Milk Dose Factors Teen Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI H-3 O.OOE+00 5.66E+02 5.66E+02 5.66E+02 5.66E+02 5.66E+02 5.66E+02 C-14 6.70E+05 1.34E+05 1.34E+05 1.34E+05 1.34E+05 1.34E+05 1.34E+05 Na-24 4.29E+06 4.29E+06 4.29E+06 4.29E+06 4.29E+06 4.29E+06 4.29E+06 Cr-51 O.OOE+00 O.OOE+00 4.99E+04 2.77E+04 1.09E+04 7.12E+04 8.38E+06 Mn-54 O.OOE+00 1.40E+07 2.78E+06 O.OOE+00 4.18E+06 O.OOE+00 2.87E+07 Mn-56 O.OOE+00 7.32E-03 1.30E-03 O.OOE+00 9.27E-03 O.OOE+00 4.82E-01 Fe-55 4.45E+07 3.16E+07 7.36E+06 O.OOE+00 O.OOE+00 2.OOE+07 1.37E+07 Fe-59 5.18E+07 1.21E+08 4.67E+07 O.OOE+00 O.OOE+00 3.81E+07 2.86E+08 Co-58 O.OOE+00 7.94E+06 1.83E+07 O.OOE+00 O.OOE+00 O.OOE+00 1.09E+08 Co-60 O.OOE+00 2.78E+07 6.26E+07 O.OOE+00 O.OOE+00 O.OOE+00 3.62E+08 Ni-63 1.18E+10 8.35E+08 4.01E+08 O.OOE+00 O.OOE+OO O.OOE+oO 1.33E+08 Ni-65 6.78E-01 8.66E-02 3.94E-02 O.OOE+00 O.OOE+00 O.OOE+00 4.70E+00 Cu-64 O.OOE+00 4.21E+04 1.98E+04 O.OOE+00 1.06E+05 O.OOE+00 3.26E+06 Zn-65 2.11E+09 7.31E+09 3.41E+09 O.OOE+00 4.68E+09 O.OOE+00 3.1OE+09 Zn-69 3.70E-12 7.05E-12 4.94E-13 O.OOE+00 4.61E-12 O.OOE+00 1.30E-11 Br-83 O.OOE+00 O.OOE+00 1.78E-01 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+0O Br-84 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+0O Br-85 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+0O Rb-86 O.OOE+00 4.73E+09 2.22E+09 O.OOE+00 O.OOE+00 O.OOE+00 7.01E+08 Rb-88 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Rb-89 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Sr-89 2.67E+09 O.OOE+00 7.66E+07 O.OOE+00 O.OOE+00 O.OOE+00 3.18E+08 Sr-90 8.13E+10 O.OOE+00 1.63E+09 O.OOE+00 O.OOE+00 O.OOE+00 1.86E+09 Sr-91 5.27E+04 O.OOE+00 2.1OE+03 O.OOE+00 0.00E+00 O.OOE+00 2.39E+05 Sr-92 8.85E-01 O.OOE+00 3.77E-02 O.OOE+00 O.OOE+00 O.OOE+00 2.26E+01 Y-90 1.30E+02 O.OOE+00 3.51E+00 O.OOE+00 O.OOE+00 O.OOE+00 1.08E+06 Y-91M 1.18E-19 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 5.55E-18 Y-91 1.58E+04 O.OOE+00 4.24E+02 O.OOE+00 O.OOE+00 Q.OOE+00 6.48E+06 Y-92 1.03E-04 O.OOE+00 2.98E-06 O.OOE+00 O.OOE+00 O.OOE+00 2.82E+00 Y-93 4.09E-01 O.OOE+00 1.12E-02 O.OOE+00 O.OOE+00 O.OOE+00 1.25E+04 Zr-95 1.65E+03 5.21E+02 3.58E+02 O.OOE+00 7.65E+02 O.OOE+00 1.20E+06 Zr-97 7.87E-01 1.56E-01 7.17E-02 O.OOE+00 2.36E-01 O.00E+00 4.22E+04 Nb-95 1.41EE+05 7.82E+04 4.30E+04 O.OOE+00 7.58E+04 O.OOE+00 3.34E+08 Mo-99 O.OOE+00 4.46E+07 8.51E+06 O.OOE+00 1.02E+08 O.OOE+00 8.OOE+07 Tc-99M 5.74E+00 1.60E+01 2.07E+02 O.OOE+00 2.39E+02 8.89E+00 1.05E+04 Tc-101 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ru-103 1.81E+03 O.OOE+00 7.74E+02 O.OOE+00 6.38E+03 O.OOE+00 1.51E+05 Ru-105 1.55E-03 O.OOE+00 6.03E-04 O.OOE+00 1.96E-02 O.OOE+00 1.25E+00 Ru-106 3.75E+04 O.OOE+00 4.73E+03 O.OOE+00 7.24E+04 O.OOE+00 1.80E+06 Ag-110M 9.63E+07 9.11EE+07 5.54E+07 O.OOE+00 1.74E+08 O.OOE+00 2.56E+10 Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 269 of 307 January 2013 Table 4-17 (Page 4 of 8) Grass-Cow-Milk Dose Factors Teen Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI Te-125M 3.01E+07 1.08E+07 4.02E+06 8.40E+06 0.OOE+00 O.OOE+00 8.87E+07 Te-127M 8.44E+07 2.99E+07 1.OOE+07 2.01E+07 3.42E+08 0.o0E+00 2.1OE+08 Te-127 1.24E+03 4.38E+02 2.66E+02 8.52E+02 5.OOE+03 O.OOE+00 9.54E+04 Te-129M 1.10E+08 4.09E+07 1.74E+07 3.55E+07 4.61E+08 0.OOE+00 4.13E+08 Te-129 5.20E-10 1.94E-10 1.27E-10 3.72E-10 2.18E-09 0.OOE+00 2.84E-09 Te-131M 6.57E+05 3.15E+05 2.63E+05 4.74E+05 3.28E+06 O.OOE+00 2.53E+07 Te-131 O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Te-132 4.27E+06 2.71E+06 2.55E+06 2.85E+06 2.60E+07 0.OOE+00 8.57E+07 1-130 7.35E+05 2.13E+06 8.49E+05 1.73E+08 3.27E+06 0.OOE+00 1.63E+06 1-131 5.37E+08 7.52E+08 4.04E+08 2.19E+11 1.29E+09 0.OOE+00 1.49E+08 1-132 2.92E-01 7.64E-01 2.74E-01 2.57E+01 1.20E+00 0.OOE+00 3.33E-01 1-133 7.08E+06 1.20E+07 3.66E+06 1.68E+09 2.11E+07 O.OOE+00 9.09E+06 1-134 3.35E-12 8.89E-12 3.19E-12 1.48E-10 1.40E-11 0.OOE+00 1.17E-13 1-135 2.29E+04 5.91E+04 2.19E+04 3.80E+06 9.33E+04 O.OOE+00 6.54E+04 Cs-134 9.82E+09 2.31E+10 1.07E+10 0.OOE+00 7.34E+09 2.80E+09 2.87E+08 Cs-136 4.47E+08 1.76E+09 1.18E+09 0.OOE+00 9.58E+08 1.51E+08 1.42E+08 Cs-137 1.34E+10 1.78E+10 6.20E+09 0.OOE+00 6.06E+09 2.35E+09 2.53E+08 Cs-138 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 Ba-139 8.20E-08 5.77E-11 2.39E-09 0.OOE+00 5.44E-11 3.98E-11 7.31E-07 Ba-140 4.85E+07 5.95E+04 3.13E+06 0.OOE+00 2.02E+04 4.OOE+04 7.49E+07 Ba-141 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+0O 0.OOE+00 0.OOE+00 Ba-142 O.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 La-140 8.12E+00 3.99E+00 1.06E+00 0.OOE+00 0.OOE+00 0.OOE+00 2.29E+05 La-142 3.41E-11 1.51E-11 3.77E-12 0.OOE+00 0.OOE+00 0.OOE+00 4.61 E-07 Ce-141 8.88E+03 5.93E+03 6.81 E+02 0.OOE+00 2.79E+03 0.OOE+00 1.70E+07 Ce-143 7.62E+01 5.55E+04 6.20E+00 0.OOE+00 2.49E+01 0.OOE+00 1.67E+06 Ce-144 6.58E+05 2.72E+05 3.54E+04 0.OOE+00 1.63E+05 0.OOE+00 1.66E+08 Pr-143 2.90E+02 1.16E+02 1.44E+01 0.OOE+00 6.74E+01 0.OOE+00 9.55E+05 Pr-144 O.OOE+00 O.OOE+00 0.OOE+O0 O.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 Nd-147 1.82E+02 1.98E+02 1.19E+01 0.OOE+00 1.17E+02 O.OOE+00 7.16E+05 W-187 1.19E+04 9.71E+03 3.40E+03 0.OOE+00 0.OOE+00 0.OOE+00 2.63E+06 Np-239 7.OOE+00 6.60E-01 3.67E-01 0.OOE+00] 2.07E+00 0.OOE+00 1.06E+05 Notes:

1) Units are m2 mrem/yr per [tCi/sec with the exception of H-3 and C-14.

2) For H-3 and C-14, the units are mrem/yr per pCi/m 3 .

Quad Cities ODCM Part II

CY-QC-170-301 Revision 11 Page 270 of 307 January 2013 Table 4-17 (Page 5 of 8) Grass-Cow-Milk Dose Factors Child Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI H-3 O.OOE+00 8.97E+02 8.97E+02 8.97E+02 8.97E+02 8.97E+02 8.97E+02 C-14 1.65E+06 3.29E+05 3.29E+05 3.29E+05 3.29E+05 3.29E+05 3.29E+05 Na-24 8.93E+06 8.93E+06 8.93E+06 8.93E+06 8.93E+06 8.93E+06 8.93E+06 Cr-51 O.OOE+00 O.OOE+00 1.02E+05 5.65E+04 1.54E+04 1.03E+05 5.39E+06 Mn-54 O.OOE+00 2.10E+07 5.59E+06 O.OOE+00 5.88E+06 O.OOE+00 1.76E+07 Mn-56 O.OOE+00 1.28E-02 2.88E-03 O.OOE+00 1.54E-02 O.OOE+00 1.85E+00 Fe-55 1.12E+08 5.93E+07 1.84E+07 O.OOE+00 O.OOE+00 3.35E+07 1.10E+07 Fe-59 1.20E+08 1.94E+08 9.69E+07 O.OOE+00 O.OOE+00 5.64E+07 2.02E+08 Co-58 O.OOE+00 1.21E+07 3.71E+07 O.OOE+00 O.OOE+00 O.OOE+00 7.08E+07 Co-60 O.OOE+00 4.32E+07 1.27E+08 O.OOE+00 O.OOE+00 O.OOE+00 2.39E+08 Ni-63 2.96E+10 1.59E+09 1.01E+09 O.OOE+00 O.OOE+00 O.OOE+00 1.07E+08 Ni-65 1.66E+00 1.56E-01 9.11E-02 O.OOE+00 O.OOE+00 O.OOE+00 1.91E+01 Cu-64 O.OOE+00 7.39E+04 4.47E+04 O.OOE+00 1.79E+05 O.OOE+00 3.47E+06 Zn-65 4.13E+09 1.10E+10 6.85E+09 O.OOE+00 6.94E+09 O.OOE+00 1.93E+09 Zn-69 9.10E-12 1.32E-11 1.22E-12 O.OOE+00 7.98E-12 O.OOE+00 8.29E-10 Br-83 O.OOE+00 O.OOE+00 4.37E-01 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Br-84 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Br-85 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Rb-86 O.OOE+00 8.78E+09 5.40E+09 O.OOE+00 O.OOE+00 O.OOE+00 5.65E+08 Rb-88 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Rb-89 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+O0 O.OOE+00 O.OOE+00 Sr-89 6.62E+09 O.OOE+00 1.89E+08 O.OOE+00 O.OOE+00 O.OOE+00 2.56E+08 Sr-90 1.68E+11 O.OOE+00 3.38E+09 O.OOE+00 O.OOE+00 O.OOE+00 1.51E+09 Sr-91 1.29E+05 O.OOE+00 4.88E+03 O.OOE+00 O.OOE+00 O.OOE+00 2.86E+05 Sr-92 2.16E+00 O.OOE+00 8.67E-02 O.OOE+00 O.OOE+00 O.OOE+00 4.09E+O1 Y-90 3.23E+02 O.OOE+00 8.64E+00 O.OOE+00 O.OOE+00 O.OOE+00 9.19E+05 Y-91M 2.87E-19 O.OOE+00 1.04E-20 O.OOE+00 O.OOE+00 O.OOE+00 5.62E-16 Y-91 3.90E+04 O.OOE+00 1.04E+03 O.OOE+00 O.OOE+00 O.OOE+00 5.20E+06 Y-92 2.53E-04 O.OOE+00 7.23E-06 O.OOE+00 O.OOE+00 O.OOE+00 7.30E+00 Y-93 1.OOE+00 O.OOE+00 2.75E-02 O.OOE+00 O.OOE+00 O.OOE+00 1.50E+04 Zr-95 3.83E+03 8.43E+02 7.50E+02 O.OOE+00 1.21E+03 O.OOE+00 8.79E+05 Zr-97 1.91E+00 2.77E-01 1.63E-01 O.OOE+00 3.97E-01 O.OOE+00 4.19E+04 Nb-95 3.18E+05 1.24E+05 8.85E+04 O.OOE+00 1.16E+05 O.OOE+00 2.29E+08 Mo-99 O.OOE+00 8.12E+07 2.01EE+07 O.OOE+00 1.73E+08 O.OOE+00 6.72E+07 Tc-99M 1.32E+01 2.58E+01 4.28E+02 O.OOE+00 3.75E+02 1.31E+01 1.47E+04 Tc-101 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00O.OOE+00 Ru-103 4.28E+03 O.OOE+00 1.65E+03 O.OOE+00 1.08E+04 O.00E+00 1.11E+05 Ru-105 3.79E-03 O.OOE+00 1.38E-03 O.OOE+00 3.33E-02 O.OOE+00 2.48E+00 Ru-106 9.24E+04 O.OOE+00 1.15E+04 O.OOE+00 1.25E+05 O.OOE+00 1.44E+06 Ag-110M 2.09E+08 1.41E+08 1.13E+08 O.OOE+00 2.63E+08 O.OOE+00 1.68E+10 Quad Cities ODCM Part II

CY-QC-170-301 Revision 11 Page 271 of 307 January 2013 Table 4-17 (Page 6 of 8) Grass-Cow-Milk Dose Factors Child Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI Te-125M 7.38E+07 2.OOE+07 9.84E+06 2.07E+07 0.OOE+00 0.OOE+00 7.12E+07 Te-127M 2.08E+08 5.60E+07 2.47E+07 4.97E+07 5.93E+08 O.OOE+00 1.68E+08 Te-127 3.04E+03 8.19E+02 6.51E+02 2.10E+03 8.64E+03 0.OOE+00 1.19E+05 Te-129M 2.71EE+08 7.58E+07 4.21EE+07 8.75E+07 7.97E+08 0.OOE+00 3.31E+08 Te-129 1.28E-09 3.58E-10 3.05E-10 9.16E-10 3.75E-09 0.OOE+00 7.99E-08 Te-131M 1.60E+06 5.53E+05 5.88E+05 1.14E+06 5.35E+06 0.OOE+00 2.24E+07 Te-131 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Te-132 1.02E+07 4.52E+06 5.46E+06 6.58E+06 4.19E+07 0.OOE+00 4.55E+07 1-130 1.72E+06 3.47E+06 1.79E+06 3.82E+08 5.19E+06 O.OOE+00 1.62E+06 1-131 1.30E+09 1.31E+09 7.45E+08 4.33E-'+11 2.15E+09 0.OOE+00 1.17E+08 1-132 6.91E-01 1.27E+00 5.84E-01 5.89E+01 1.94E+00 O.OOE+00 1.49E+00 1-133 1.72E+07 2.13E+07 8.05E+06 3.95E+09 3.55E+07 0.OOE+00 8.57E+06 1-134 7.94E-12 1.47E-11 6.79E-12 3.39E-10 2.26E-11 0.OOE+00 9.78E-12 1-135 5.43E+04 9.78E+04 4.62E+04 8.66E+06 1.50E+05 0.OOE+00 7.45E+04 Cs-134 2.26E+10 3.72E+10 7.84E+09 0.OOE+00 1.15E+10 4.13E+09 2.OOE+08 Cs-136 1.01E+09 2.77E+09 1.80E+09 0.OOE+00 1.48E+09 2.20E+08 9.75E+07 Cs-137 3.22E+10 3.09E+10 4.55E+09 O.OOE+00 1.01E+10 3.62E+09 1.93E+08 Cs-1 38 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Ba-139 2.01E-07 1.08E-10 5.84E-09 O.OOE+00 9.39E-11 6.33E-11 1.16E-05 Ba-140 1.17E+08 1.03E+05 6.84E+06 0.OOE+00 3.34E+04 6.12E+04 5.94E+07 Ba-141 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 Ba-142 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 La-140 1.95E+01 6.80E+00 2.29E+00 0.OOE+00 0.OOE+00 O.OOE+00 1.90E+05 La-142 8.24E-11 2.63E-11 8.22E-12 O.OOE+00 0.OOE+00 0.OOE+00 5.20E-06 Ce-141 2.19E+04 1.09E+04 1.62E+03 0.OOE+00 4.78E+03 O.OOE+00 1.36E+07 Ce-143 1.87E+02 1.01E+05 1.47E+01 O.OOE+00 4.26E+01 0.OOE+00 1.49E+06 Ce-144 1.62E+06 5.09E+05 8.66E+04 0.OOE+00 2.82E+05 0.OOE+00 1.33E+08 Pr-143 7.18E+02 2.16E+02 3.57E+01 0.OOE+00 1.17E+02 O.OOE+00 7.75E+05 Pr-144 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 O.OOE+00 Nd-147 4.48E+02 3.63E+02 2.81E+01 O.OOE+00 1.99E+02 0.OOE+00 5.75E+05 W-187 2.89E+04 1.71EE+04 7.67E+03 0.OOE+00 0.OOE+00 O.OOE+00 2.40E+06 Np-239 1.72E+01 1.24E+00 8.69E-01 0.OOE+00 3.58E+00 0.OOE+00 9.15E+04 Notes:

1) Units are m2 mrem/yr per [tCi/sec with the exception of H-3 and C-14.

2) For H-3 and C-14, the units are mrem/yr per [tCi/m 3.

Quad Cities ODCM Part II

CY-QC-170-301 Revision 11 Page 272 of 307 January 2013 Table 4-17 (Page 7 of 8) Grass-Cow-Milk Dose Factors Infant Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI H-3 O.00E+00 1.36E+03 1.36E+03 1.36E+03 1.36E+03 1.36E+03 1.36E+03 C-14 3.23E+06 6.89E+05 6.89E+05 6.89E+05 6.89E+05 6.89E+05 6.89E+05 Na-24 1.56E+07 1.56E+07 1.56E+07 1.56E+07 1.56E+07 1.56E+07 1.56E+07 Cr-51 O.OOE+00 O.OOE+00 1.61E+05 1.05E+05 2.30E+04 2.05E+05 4.70E+06 Mn-54 O.OOE+00 3.90E+07 8.84E+06 O.OOE+00 8.64E+06 O.OOE+00 1.43E+07 Mn-56 O.OOE+00 3.13E-02 5.39E-03 O.OOE+00 2.69E-02 O.OOE+00 2.84E+00 Fe-55 1.35E+08 8.73E+07 2.33E+07 O.OOE+00 O.OOE+00 4.27E+07 1.11EE+07 Fe-59 2.24E+08 3.92E+08 1.54E+08 O.OOE+00 O.OOE+00 1.16E+08 1.87E+08 Co-58 O.OOE+00 2.43E+07 6.05E+07 O.OOE+00 O.OOE+00 O.OOE+00 6.04E+07 Co-60 O.00E+00 8.82E+07 2.08E+08 O.OOE+00 O.OOE+00 O.OOE+00 2.10E+08 Ni-63 3.49E+10 2.16E+09 1.21E+09 O.OOE+00 O.OOE+00 O.OOE+00 1.07E+08 Ni-65 3.51E+00 3.97E-01 1.81E-01 O.OOE+00 O.OOE+O0 O.OOE+00 3.02E+01 Cu-64 O.OOE+00 1.84E+05 8.51E+04 O.OOE+00 3.11E+05 O.OOE+00 3.77E+06 Zn-65 5.55E+09 1.90E+10 8.78E+09 O.OOE+00 9.23E+09 O.OOE+00 1.61E+10 Zn-69 1.94E-11 3.49E-11 2.60E-12 O.OOE+00 1.45E-11 O.OOE+00 2.85E-09 Br-83 O.OOE+00 O.OOE+00 9.27E-01 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Br-84 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Br-85 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.00E+00 Rb-86 O.OOE+00 2.23E+10 1.10E+10 O.OOE+00 O.OOE+00 O.OOE+00 5.70E+08 Rb-88 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Rb-89 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Sr-89 1.26E+10 O.OOE+00 3.61E+08 O.OOE+00 O.00E+00 O.OOE+00 2.59E+08 Sr-90 1.86E+1 1 O.OOE+00 3.77E+09 O.OOE+00 O.OOE+00 O.OOE+00 1.52E+09 Sr-91 2.70E+05 O.OOE+00 9.76E+03 O.OOE+00 O.OOE+00 O.OOE+00 3.19E+05 Sr-92 4.60E+00 O.OOE+00 1.71E-01 O.OOE+00 O.OOE+OO O.OOE+00 4.96E+01 Y-90 6.82E+02 O.OOE+00 1.83E+01 O.OOE+00 O.OOE+00 O.OOE+00 9.42E+05 Y-91M 6.09E-19 O.OOE+00 2.07E-20 O.OOE+00 O.OOE+00 O.OOE+00 2.03E-15 Y-91 7.33E+04 O.OOE+00 1.95E+03 O.OOE+00 O.OOE+00 O.OOE+00 5.25E+06 Y-92 5.37E-04 O.OOE+00 1.51E-05 O.OOE+O0 O.OOE+00 O.OOE+00 1.02E+01 Y-93 2.14E+00 O.OOE+00 5.83E-02 O.OOE+00 O.OOE+00 O.OOE+00 1.69E+04 Zr-95 6.81E+03 1.66E+03 1.18E+03 O.OOE+00 1.79E+03 O.OOE+00 8.26E+05 Zr-97 4.05E+00 6.96E-01 3.18E-01 O.OOE+00 7.01E-01 O.OOE+00 4.44E+04 Nb-95 5.94E+05 2.45E+05 1.41E+05 O.OOE+00 1.75E+05 O.OOE+00 2.07E+08 Mo-99 O.OOE+00 2.08E+08 4.05E+07 O.OOE+00 3.1OE+08 O.OOE+00 6.84E+07 Tc- 99M 2.74E+01 5.65E+01 7.27E+02 O.OOE+00 6.08E+02 2.95E+01 1.64E+04 Tc-101 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ru-103 8.67E+03 O.OOE+00 2.90E+03 O.OOE+00 1.80E+04 O.OOE+00 1.05E+05 Ru-105 8.OOE-03 O.OOE+00 2.69E-03 O.OOE+00 5.88E-02 O.OOE+00 3.18E+00 Ru-106 1.90E+05 O.OOE+00 2.38E+04 O.OOE+00 2.25E+05 O.OOE+00 1.44E+06 Ag-110M 3.86E+08 2.82E+08 1.86E+08 O.OOE+00 4.03E+08 O.OOE+00 1.46E+10 Quad Cities ODCM Part II

CY-QC-170-301 Revision 11 Page 273 of 307 January 2013 Table 4-17 (Page 8 of 8) Grass-Cow-Milk Dose Factors Infant Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI Te-125M 1.51E+08 5.04E+07 2.04E+07 5.08E+07 0.OOE+00 0.00E+00 7.19E+07 Te-127M 4.21E+08 1.40E+08 5.10E+07 1.22E+08 1.04E+09 0.OOE+00 1.70E+08 Te-127 6.45E+03 2.16E+03 1.39E+03 5.25E+03 1.57E+04 0.OOE+00 1.35E+05 Te-129M 5.57E+08 1.91E+08 8.58E+07 2.14E+08 1.39E+09 0.OOE+00 3.33E+08 Te-129 2.72E-09 9.38E-10 6.35E-10 2.28E-09 6.77E-09 0.OOE+00 2.17E-07 Te-131M 3.37E+06 1.36E+06 1.12E+06 2.75E+06 9.35E+06 O.OOE+00 2.29E+07 Te-131 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 Te-132 2.1OE+07 1.04E+07 9.71E+06 1.54E+07 6.51E+07 0.OOE+00 3.85E+07 1-130 3.53E+06 7.77E+06 3.12E+06 8.71E+08 8.53E+06 0.OOE+00 1.67E+06 1-131 2.72E+09 3.20E+09 1.41E+09 1.05E+12 3.74E+09 O.OOE+00 1.14E+08 1-132 1.43E+00 2.91E+00 1.04E+00 1.36E+02 3.25E+00 O.OOE+00 2.36E+00 1-133 3.63E+07 5.29E+07 1.55E+07 9.62E+09 6.22E+07 0.OOE+00 8.95E+06 1-134 1.65E-11 3.37E-11 1.20E-11 7.87E-10 3.77E-11 0.OOE+00 3.49E-11 1-135 1.13E+05 2.25E+05 8.19E+04 2.01E+07 2.50E+05 0.OOE+00 8.13E+04 Cs-134 3.65E+10 6.80E+10 6.87E+09 0.OOE+00 1.75E+10 7.18E+09 1.85E+08 Cs-136 1.97E+09 5.80E+09 2.16E+09 O.OOE+00 2.31E+09 4.72E+08 8.80E+07 Cs-137 5.15E+10 6.02E+10 4.27E+09 0.OOE+00 1.62E+10 6.55E+09 1.88E+08 Cs-1 38 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Ba-139 4.29E-07 2.84E-10 1.24E-08 0.OOE+00 1.71E-10 1.72E-10 2.72E-05 Ba-140 2.41E+08 2.41E+05 1.24E+07 0.OOE+00 5.72E+04 1.48E+05 5.92E+07 Ba-141 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 Ba-142 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 La-140 4.06E+01 1.60E+01 4.12E+00 0.OOE+00 0.OOE+00 0.OOE+00 1.88E+05 La-142 1.73E-10 6.35E-11 1.52E-11 0.OOE+00 0.00'E+00 0.OOE+00 1.08E-05 Ce-141 4.34E+04 2.64E+04 3.11E+03 0.OOE+00 8.15E+03 0.OOE+00 1.37E+07 Ce-143 3.96E+02 2.63E+05 3.OOE+01 0.OOE+00 7.65E+01 0.OOE+00 1.53E+06 Ce-144 2.33E+06 9.52E+05 1.30E+05 0.OOE+00 3.85E+05 0.OOE+00 1.33E+08 Pr-143 1.49E+03 5.56E+02 7.37E+01 0.OOE+00 2.07E+02 O.OOE+00 7.84E+05 Pr-144 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 Nd-147 8.88E+02 9.12E+02 5.59E+01 0.OOE+00 3.51E+02 O.OOE+00 5.78E+05 W-187 6.08E+04 4.23E+04 1.46E+04 0.OOE+00 0.OOE+00 0.OOE+00 2.48E+06 Np-239 3.64E+01 3.26E+00 1.84E+00 0.OOE+00 6.50E+00 O.OOE+00 9.42E+04 Notes:

1) Units are m2 mrem/yr per [tCi/sec with the exception of H-3 and C-14.

2) For H-3 and C-14, the units are mrem/yr per ýLCi/m 3 .

Quad Cities ODCM Part II

CY-QC-170-301 Revision 11 Page 274 of 307 January 2013 Table 4-18 (Page 1 of 8) Grass-Goat-Milk Dose Factors Adult Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI H-3 O.OOE+00 8.88E+02 8.88E+02 8.88E+02 8.88E+02 8.88E+02 8.88E+02 C-14 3.63E+05 7.26E+04 7.26E+04 7.26E+04 7.26E+04 7.26E+04 7.26E+04 Na-24 2.95E+05 2.95E+05 2.95E+05 2.95E+05 2.95E+05 2.95E+05 2.95E+05 Cr-51 O.OOE+00 O.OOE+00 3.43E+03 2.05E+03 7.55E+02 4.55E+03 8.62E+05 Mn-54 O.OOE+00 1.01E+06 1.93E+05 O.OOE+00 3.OOE+05 O.OOE+OO 3.09E+06 Mn-56 O.OOE+00 4.95E-04 8.79E-05 O.OOE+00 6.29E-04 O.OOE+00 1.58E-02 Fe-55 3.26E+05 2.26E+05 5.26E+04 O.OOE+00 O.OOE+00 1.26E+05 1.29E+05 Fe-59 3.86E+05 9.07E+05 3.48E+05 O.OOE+o0 O.OOE+O0 2.53E+05 3.02E+06 Co-58 O.OOE+00 5.66E+05 1.27E+06 O.OOE+00 O.OOE+00 O.OOE+00 1.15E+07 Co-60 O.OOE+00 1.97E+06 4.34E+06 O.OOE+00 O.OOE+00 O.OOE+00 3.70E+07 Ni-63 8.07E+08 5.60E+07 2.71E+07 O.OOE+00 O.OOE+00 O.OOE+00 1.17E+07 Ni-65 4.44E-02 5.77E-03 2.63E-03 O.OOE+00 O.OOE+00 O.OOE+00 1.46E-01 Cu-64 O.OOE+00 2.63E+03 1.23E+03 O.OOE+00 6.63E+03 O.OOE+00 2.24E+05 Zn-65 1.65E+08 5.24E+08 2.37E+08 O.OOE+00 3.50E+08 O.OOE+00 3.30E+08 Zn-69 2.41E-13 4.61E-13 3.21E-14 O.OOE+00 3.OOE-13 O.OOE+00 6.93E-14 Br-83 O.OOE+00 O.OOE+00 1.16E-02 O.OOE+00 O.OOE+00 O.OOE+00 1.67E-02 Br-84 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 Br-85 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Rb-86 0.00E+00 3.12E+08 1.45E+08 O.OOE+00 O.OOE+00 O.OOE+00 6.15E+07 Rb-88 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Rb-89 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 Sr-89 3.05E+09 O.OOE+00 8.74E+07 O.OOE+00 O.OOE+00 O.OOE+00 4.88E+08 Sr-90 1.13E+11 O.OOE+00 2.27E+09 O.OOE+00 O.OOE+00 O.OOE+00 2.84E+09 Sr-91 6.03E+04 O.OOE+00 2.44E+03 O.OOE+00 O.OOE+00 O.OOE+00 2.87E+05 Sr-92 1.02E+00 O.OOE+00 4.39E-02 O.OOE+00 O.OOE+00 O.OOE+00 2.01E+01 Y-90 8.52E+o0 O.OOE+00 2.28E-01 O.OOE+00 O.OOE+00 O.OOE+00 9.03E+04 Y-91M O.OOE+00 O.OOE+00 O.OOE+00 O.O0E+00 O.OOE+00 O.OOE+O0 2.26E-20 Y-91 1.03E+03 O.OOE+00 2.76E+01 O.OOE+00 O.OOE+00 O.OOE+00 5.67E+05 Y-92 6.68E-06 O.0OE+00 1.95E-07 O.OOE+00 O.OOE+00 O.OOE+00 1.17E-01 Y-93 2.66E-02 O.OOE+00 7.34E-04 O.OOE+00 O.OOE+00 O.OOE+00 8.43E+02 Zr-95 1.13E+02 3.63E+01 2.46E+01 O.OOE+00 5.70E+01 O.OOE+00 1.15E+05 Zr-97 5.19E-02 1.05E-02 4.79E-03 O.OOE+00 1.58E-02 O.OOE+00 3.24E+03 Nb-95 9.92E+03 5.52E+03 2.97E+03 O.OOE+00 5.45E+03 O.OOE+00 3.35E+07 Mo-99 O.OOE+00 2.97E+06 5.65E+05 O.OOE+00 6.72E+06 O.OOE+00 6.88E+06 Tc-99M 3.97E-01 1.12E+00 1.43E+01 O.OOE+00 1.70E+01 5.50E-01 6.64E+02 Tc-101 o.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 Ru-103 1.22E+02 O.OOE+00 5.26E+01 O.OOE+00 4.66E+02 O.OOE+00 1.43E+04 Ru-105 1.02E-04 O.OOE+00 4.03E-05 O.OOE+00 1.32E-03 O.OOE+00 6.25E-02 Ru-106 2.45E+03 O.OOE+00 3.1OE+02 O.OOE+00 4.73E+03 O.OOE+00 1.58E+05 Ag-11OM 6.99E+06 6.46E+06 3.84E+06 O.OOE+00 1.27E+07 O.OOE+00 2.64E+09 Quad Cities ODCM Part II

CY-QC-170-301 Revision 11 Page 275 of 307 January 2013 Table 4-18 (Page 2 of 8) Grass-Goat-Milk Dose Factors Adult Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI Te-125M 1.96E+06 7.09E+05 2.62E+05 5.88E+05 7.95E+06 0.OOE+00 7.81E+06 Te-127M 5.49E+06 1.96E+06 6.69E+05 1.40E+06 2.23E+07 0.OOE+00 1.84E+07 Te-127 8.OOE+01 2.87E+01 1.73E+01 5.92E+01 3.26E+02 0.OOE+00 6.31E+03 Te-129M 7.22E+06 2.69E+06 1.14E+06 2.48E+06 3.01E+07 0.OOE+00 3.64E+07 Te-129 3.39E-11 1.27E-11 8.26E-12 2.60E-11 1.43E-10 0.OOE+00 2.56E-11 Te-131M 4.33E+04 2.12E+04 1.76E+04 3.35E+04 2.14E+05 0.OOE+00 2.10E-+06 Te-131 O.OOE+0O 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 Te-132 2.87E+05 1.86E+05 1.74E+05 2.05E+05 1.79E+06 0.OOE+00 8.78E+06 1-130 5.01EE+05 1.48E+06 5.84E+05 1.25E+08 2.31E+06 0.OOE+00 1.27E+06 1-131 3.55E+08 5.08E+08 2.91EE+08 1.67E+11 8.71E+08 0.OOE+00 1.34E+08 1-132 1.98E-01 5.29E-01 1.85E-01 1.85E+01 8.42E-01 0.OOE+00 9.93E-02 1-133 4.65E+06 8.09E+06 2.47E+06 1.19E+09 1.41E+07 O.OOE+00 7.27E+06 1-134 2.27E-12 6.15E-12 2.20E-12 1.07E-10 9.79E-12 O.OOE+00 5.36E-15 1-135 1.55E+04 4.06E+04 1.50E+04 2.68E+06 6.51E+04 O.OOE+00 4.58E+04 Cs-134 1.70E+10 4.04E+10 3.30E+10 0.OOE+00 1.31E+10 4.34E+09 7.06E+08 Cs-136 7.88E+08 3.11E+09 2.24E+09 0.OOE+00 1.73E+09 2.37E+08 3.53E+08 Cs-137 2.21E+10 3.03E+10 1.98E+10 0.OOE+00 1.03E+10 3.42E+09 5.86E+08 Cs-1 38 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Ba-139 5.32E-09 3.79E-12 1.56E-10 0.OOE+00 3.54E-12 2.15E-12 9.44E-09 Ba-140 3.23E+06 4.05E+03 2.11E+05 0.OOE+00 1.38E+03 2.32E+03 6.64E+06 Ba-141 0.OOE+00 O.OOE+00 0.OOE+0O 0.OOE+0O 0.OOE+00 0.OOE+00 0.OOE+00 Ba-142 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 La-140 5.43E-01 2.74E-01 7.23E-02 0.OOE+00 0.OOE+00 0.OOE+00 2.01E+04 La-142 2.27E-12 1.03E-12 2.57E-13 0.OOE+00 0.OOE+00 0.OOE+00 7.53E-09 Ce-141 5.81E+02 3.93E+02 4.46E+01 O.OOE+00 1.83E+02 O.OOE+00 1.50E+06 Ce-143 4.98E+00 3.68E+03 4.07E-01 0.OOE+00 1.62E+00 0.OOE+00 1.38E+05 Ce-144 4.29E+04 1.79E+04 2.30E+03 0.OOE+00 1.06E+04 0.OOE+00 1.45E+07 Pr-143 1.90E+01 7.60E+00 9.40E-01 0.OOE+00 4.39E+00 0.OOE+00 8.31E+04 Pr-144 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 Nd-147 1.14E+01 1.32E+01 7.87E-01 0.OOE+00 7.69E+00 0.OOE+00 6.31E+04 W-187 7.82E+02 6.53E+02 2.28E+02 0.OOE+00 0.OOE+00 O.OOE+00 2.14E+05 Np-239 4.40E-01 4.33E-02 2.39E-02 0.OOE+00 1.35E-01 0.OOE+00 8.88E+03 Notes:

1) Units are m 2 mrem/yr per ýtCi/sec with the exception of H-3 and C-14.

2) For H-3 and C-14, the units are mrem/yr per pLCi/m 3 .

Quad Cities ODCM Part II

CY-QC-170-301 Revision 11 Page 276 of 307 January 2013 Table 4-18 (Page 3 of 8) Grass-Goat-Milk Dose Factors Teen Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI H-3 O.OOE+00 1.16E+03 1.16E+03 1.16E+03 1.16E+03 1.16E+03 1.16E+03 C-14 6.70E+05 1.34E+05 1.34E+05 1.34E+05 1.34E+05 1.34E+05 1.34E+05 Na-24 5.15E+05 5.15E+05 5.15E+05 5.15E+05 5.15E+05 5.15E+05 5.15E+05 Cr-51 O.OOE+00 O.OOE+00 5.99E+03 3.33E+03 1.31E+03 8.55E+03 1.01E+06 Mn-54 O.OOE+00 1.68E+06 3.34E+05 O.OOE+00 5.02E+05 O.OOE+00 3.45E+06 Mn-56 O.OOE+00 8.78E-04 1.56E-04 O.OOE+00 1.11E-03 O.OOE+00 5.78E-02 Fe-55 5.79E+05 4.11E+05 9.57E+04 O.OOE+00 O.OOE+00 2.60Ei+05 1.78E+05 Fe-59 6.74E+05 1.57E+06 6.07E+05 O.OOE+00 0.00E+00 4.96E+05 3.72E+06 Co-58 O.OOE+00 9.53E+05 2.20E+06 O.OOE+00 0.00E+00 O.OOE+00 1.31E+07 Co-60 O.OOE+00 3.34E+06 7.52E+06 O.OOE+00 O.OOE+00 O.OOE+00 4.35E+07 Ni-63 1.42E+09 1.OOE+08 4.81E+07 O.OOE+00 O.OOE+00 O.OOE+00 1.59E+07 Ni-65 8.13E-02 1.04E-02 4.73E-03 O.OOE+00 O.OOE+00 O.OOE+00 5.63E-01 Cu-64 0.OOE+00 4.69E+03 2.20E+03 O.00E+00 1.19E+04 O.OOE+00 3.64E+05 Zn-65 2.53E+08 8.78E+08 4.09E+08 O.OOE+00 5.62E+08 O.OOE+00 3.72E+08 Zn-69 4.44E-13 8.46E-13 5.92E-14 O.OOE+00 5.53E-13 O.OOE+00 1.56E-12 Br-83 O.OOE+00 O.OOE+O0 2.13E-02 O.OOE+00 O.OOE+OO O.OOE+00 O.OOE+00 Br-84 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Br-85 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Rb-86 O.OOE+00 5.68E+08 2.67E+08 O.OOE+00 O.OOE+00 O.OOE+00 8.41E+07 Rb-88 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+OO O.OOE+00 O.OOE+00 Rb-89 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.00E+00 O.OOE+00 O.OOE+00 Sr-89 5.61E+09 O.OOE+00 1.61E+08 O.OOE+00 O.OOE+00 O.OOE+00 6.69E+08 Sr-90 1.71E+11 O.OOE+00 3.41E+09 O.OOE+00 O.0OE+00 O.OOE+00 3.90E+09 Sr-91 1.11E+05 O.OOE+00 4.41E+03 O.OOE+00 O.OOE+00 O.OOE+00 5.02E+05 Sr-92 1.86E+00 O.OOE+00 7.92E-02 O.OOE+00 O.OOE+00 O.OOE+00 4.74E+01 Y-90 1.56E+01 O.OOE+00 4.21E-01 O.OOE+00 O.OOE+00 O.OOE+00 1.29E+05 Y-91M 1.41E-20 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 6.66E-19 Y-91 1.90E+03 O.OOE+00 5.08E+01 O.OOE+00 O.OOE+00 O.OOE+00 7.77E+05 Y-92 1.23E-05 Q.OOE+00 3.57E-07 O.OOE+00 O.OOE+00 O.OOE+00 3.39E-01 Y-93 4.90E-02 O.OOE+00 1.34E-03 O.OOE+00 O.OOE+00 O.OOE+00 1.50E+03 Zr-95 1.98E+02 6.25E+01 4.30E+01 O.OOE+00 9.18E+01 O.OOE+00 1.44E+05 Zr-97 9.44E-02 1.87E-02 8.61E-03 O.OOE+00 2.83E-02 O.OOE+00 5.06E+03 Nb-95 1.69E+04 9.38E+03 5.16E+03 O.OOE+00 9.09E+03 O.OOE+00 4.01E+07 Mo-99 O.OOE+00 5.36E+06 1.02E+06 O.OOE+00 1.23E+07 O.OOE+00 9.59E+06 Tc-99M 6.89E-01 1.92E+00 2.49E+01 O.OOE+00 2.86E+01 1.07E+00 1.26E+03 Tc-101 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ru-103 2.17E+02 O.OOE+00 9.29E+01 O.OOE+00 7.66E+02 O.OOE+00 1.81E+04 Ru-105 1.86E-04 O.OOE+00 7.24E-05 O.OOE+00 2.35E-03 O.OOE+00 1.51E-01 Ru-106 4.50E+03 O.OOE+00 5.67E+02 O.OOE+00 8.68E+03 O.OOE+00 2.16E+05 Ag-11OM 1.16E+07 1.09E+07 6.65E+06 O.OOE+00 2.09E+07 O.OOE+00 3.07E+09 Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 277 of 307 January 2013 Table 4-18 (Page 4 of 8) Grass-Goat-Milk Dose Factors Teen Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI Te-125M 3.61E+06 1.30E+06 4.82E+05 1.01E+06 0.OOE+00 0.OOE+00 1.06E+07 Te-127M 1.01E+07 3.59E+06 1.20E+06 2.41E+06 4.10E+07 0.OOE+00 2.52E+07 Te-127 1.48E+02 5.25E+01 3.19E+01 1.02E+02 6.OOE+02 0.00E+00 1.14E+04 Te-129M 1.32E+07 4.90E+06 2.09E+06 4.26E+06 5.53E+07 O.OOE+00 4.96E+07 Te-129 6.24E-11 2.33E-11 1.52E-11 4.46E-11 2.62E-10 0.OOE+00 3.41E-10 Te-131M 7.88E+04 3.78E+04 3.15E+04 5.68E+04 3.94E+05 0.OOE+00 3.03E+06 Te-131 0.00E+00 0.OOE+00 0.OOE+0O 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 Te-132 5.13E+05 3.25E+05 3.06E+05 3.42E+05 3.12E+06 0.OOE+00 1.03E+07 1-130 8.82E+05 2.55E+06 1.02E+06 2.08E+08 3.93E+06 0.OOE+00 1.96E+06 1-131 6.45E+08 9.02E+08 4.85E+08 2.63E+11 1.55E+09 O.OOE+00 1.78E+08 1-132 3.50E-01 9.17E-01 3.29E-01 3.09E+01 1.44E+0O 0.OOE+00 3.99E-01 1-133 8.50E+06 1.44E+07 4.40E+06 2.01E+09 2.53E+07 0.OOE+00 1.09E+07 1-134 4.03E-12 1.07E-11 3.83E-12 1.78E-10 1.68E-11 0.OOE+00 1.41E-13 1-135 2.75E+04 7.09E+04 2.63E+04 4.56E+06 1.12E+05 0.OOE+00 7.85E+04 Cs-134 2.94E+10 6.93E+10 3.22E+10 0.OOE+00 2.20E+10 8.41E+09 8.62E+08 Cs-136 1.34E+09 5.28E+09 3.54E+09 0.OOE+00 2.87E+09 4.53E+08 4.25E+08 Cs-137 4.02E+10 5.34E+10 1.86E+10 0.OOE+00 1.82E+10 7.06E+09 7.60E+08 Cs-138 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Ba-139 9.84E-09 6.92E-12 2.87E-10 0.OOE+00 6.53E-12 4.77E-12 8.78E-08 Ba-140 5.82E+06 7.14E+03 3.75E+05 0.OOE+00 2.42E+03 4.80E+03 8.98E+06 Ba-141 O.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.O0E+00 0.OOE+00 0.OOE+00 Ba-142 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+0O 0.OOE+00 0.OOE+00 La-140 9.75E-01 4.79E-01 1.27E-01 0.OOE+00 0.OOE+00 O.OOE+00 2.75E+04 La-142 4.09E-12 1.82E-12 4.53E-13 0.OOE+00 0.OOE+00 O.OOE+00 5.53E-08 Ce-141 1.07E+03 7.12E+02 8.17E+01 0.OOE+00 3.35E+02 O.OOE+00 2.04E+06 Ce-143 9.15E+00 6.66E+03 7.44E-01 0.OOE+00 2.99E+00 O.OOE+00 2.OOE+05 Ce-144 7.90E+04 3.27E+04 4.24E+03 O.OOE+00 1.95E+04 0.OOE+00 1.99E+07 Pr-143 3.48E+01 1.39E+01 1.73E+00 0.OOE+00 8.08E+00 O.OOE+00 1.15E+05 Pr-144 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Nd-147 2.19E+01 2.38E+01 1.43E+00 0.00E+00 1.40E+01 O.OOE+00 8.59E+04 W-187 1.43E+03 1.17E+03 4.08E+02 0.OOE+00 0.OOE+00 0.OOE+00 3.15E+05 Np-239 8.40E-01 7.92E-02 4.40E-02 0.OOE+00 2.49E-01 0.OOE+00 1.27E+04 Notes:

1) Units are m 2 mrem/yr per [tCi/sec with the exception of H-3 and C-14.

2) For H-3 and C-14, the units are mrem/yr per [LCi/m 3 .

Quad Cities ODCM Part II

CY-QC-170-301 Revision 11 Page 278 of 307 January 2013 Table 4-18 (Page 5 of 8) Grass-Goat-Milk Dose Factors Child Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI H-3 O.OOE+00 1.83E+03 1.83E+03 1.83E+03 1.83E+03 1.83E+03 1.83E+03 C-14 1.65E+06 3.29E+05 3.29E+05 3.29E+05 3.29E+05 3.29E+05 3.29E+05 Na-24 1.07E+06 1.07E+06 1.07E+06 1.07E+06 1.07E+06 1.07E+06 1.07E+06 Cr-51 O.OOE+00 O.OOE+00 1.22E+04 6.78E+03 1.85E+03 1.24E+04 6.47E+05 Mn-54 O.OOE+00 2.52E+06 6.70E+05 O.OOE+00 7.06E+05 O.OOE+00 2.11EE+06 Mn-56 O.OOE+00 1.53E-03 3.46E-04 O.OOE+00 1.85E-03 O.OOE+00 2.22E-01 Fe-55 1.45E+06 7.71E+05 2.39E+05 O.OOE+00 O.OOE+00 4.36E+05 1.43E+05 Fe-59 1.56E+06 2.53E+06 1.26E+06 O.OOE+00 O.OOE+00 7.33E+05 2.63E+06 Co-58 O.OOE+00 1.46E+06 4.46E+06 O.OOE+00 O.OOE+00 O.OOE+00 8.49E+06 Co-60 O.OOE+00 5.18E+06 1.53E+07 O.OOE+00 O.OOE+00 O.OOE+00 2.87E+07 Ni-63 3.56E+09 1.90E+08 1.21E+08 O.OOE+00 O.OOE+00 O.OOE+00 1.28E+07 Ni-65 1.99E-01 1.87E-02 1.09E-02 O.OOE+00 O.OOE+00 O.OOE+00 2.29E+00 Cu-64 O.OOE+00 8.24E+03 4.98E+03 O.OOE+00 1.99E+04 O.OOE+00 3.87E+05 Zn-65 4.96E+08 1.32E+09 8.22E+08 O.OOE+00 8.33E+08 O.OOE+00 2.32E+08 Zn-69 1.09E-12 1.58E-12 1.46E-13 O.OOE+00 9.57E-13 O.OOE+00 9.95E-11 Br-83 O.OOE+00 O.OOE+00 5.24E-02 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Br-84 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Br-85 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Rb-86 O.OOE+00 1.05E+09 6.48E+08 O.OOE+00 O.OOE+00 O.OOE+00 6.78E+07 Rb-88 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Rb-89 O.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Sr-89 1.39E+10 O.OOE+00 3.97E+08 O.OOE+00 O.OOE+00 O.OOE+00 5.38E+08 Sr-90 3.53E+11 O.OOE+00 7.11E+09 O.OOE+00 O.OOE+00 O.OOE+00 3.16E+09 Sr-91 2.72E+05 O.OOE+00 1.03E+04 O.OOE+00 O.OOE+00 O.OOE+00 6.O0E+05 Sr-92 4.54E+00 O.OOE+00 1.82E-01 O.OOE+00 O.OOE+00 O.OOE+00 8.60E+01 Y-90 3.87E+01 O.OOE+00 1.04E+00 O.OOE+00 O.OOE+00 O.OOE+00 1.10E+05 Y-91M 3.45E-20 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 6.75E-17 Y-91 4.68E+03 O.OOE+00 1.25E+02 O.OOE+00 O.OOE+00 O.OOE+00 6.24E+05 Y-92 3.03E-05 O.OOE+00 8.67E-07 O.OOE+00 O.OOE+00 O.OOE+00 8.75E-01 Y-93 1.20E-01 O.OOE+00 3.31E-03 O.OOE+00 O.OOE+00 O.OOE+00 1.80E+03 Zr-95 4.60E+02 1.01E+02 9.OOE+01 O.OOE+00 1.45E+02 O.OOE+00 1.05E+05 Zr-97 2.30E-01 3.32E-02 1.96E-02 O.OOE+00 4.77E-02 O.OOE+00 5.03E+03 Nb-95 3.82E+04 1.49E+04 1.06E+04 O.OOE+00 1.40E+04 O.OOE+00 2.75E+07 Mo-99 O.OOE+00 9.75E+06 2.41E+06 O.OOE+00 2.08E+07 O.OOE+00 8.06E+06 Tc- 99M 1.58E+00 3.10E+00 5.14E+01 O.OOE+00 4.50E+01 1.57E+00 1.76E+03 Tc-101 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ru-103 5.14E+02 O.OOE+00 1.97E+02 O.OOE+00 1.29E+03 O.OOE+00 1.33E+04 Ru-105 4.55E-04 O.OOE+00 1.65E-04 O.OOE+00 4.OOE-03 O.OOE+00 2.97E-01 Ru-106 1.11E+04 O.OOE+00 1.38E+03 O.OOE+00 1.50E+04 O.OOE+00 1.72E+05 Ag-11OM 2.51EE+07 1.69E+07 1.35E+07 O.OOE+0O 3.15E+07 O.OOE+00 2.01E+09 Quad Cities ODCM Part II

CY-QC-170-301 Revision 11 Page 279 of 307 January 2013 Table 4-18 (Page 6 of 8) Grass-Goat-Milk Dose Factors Child Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI Te-125M 8.86E+06 2.40E+06 1.18E+06 2.49E+06 0.OOE+00 0.OOE+00 8.55E+06 Te-127M 2.50E+07 6.72E+06 2.96E+06 5.97E+06 7.12E+07 O.OOE+00 2.02E+07 Te-127 3.64E+02 9.83E+01 7.82E+01 2.52E+02 1.04E+03 0.OOE+00 1.42E+04 Te-129M 3.26E+07 9.09E+06 5.05E+06 1.05E+07 9.56E+07 0.OOE+00 3.97E+07 Te-129 1.54E-10 4.30E-11 3.66E-11 1.10E-10 4.51E-10 0.OOE+00 9.59E-09 Te-131M 1.92E+05 6.63E+04 7.06E+04 1.36E+05 6.42E+05 0.00E+00 2.69E+06 Te-131 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Te-132 1.22E+06 5.42E+05 6.55E+05 7.89E+05 5.03E+06 0.OOE+00 5.46E+06 1-130 2.06E+06 4.17E+06 2.15E+06 4.59E+08 6.23E+06 0.OOE+00 1.95E+06 1-131 1.56E+09 1.57E+09 8.94E+08 5.20E+11 2.58E+09 0.OOE+00 1.40E+08 1-132 8.29E-01 1.52E+00 7.OOE-01 7.07E+01 2.33E+00 0.OOE+00 1.79E+00 1-133 2.06E+07 2.55E+07 9.66E+06 4.74E+09 4.25E+07 O.OOE+00 1.03E+07 1-134 9.53E-12 1.77E-11 8.14E-12 4.07E-10 2.71E-11 0.OOE+00 1.17E-11 1-135 6.52E+04 1.17E+05 5.55E+04 1.04E+07 1.80E+05 0.OOE+00 8.94E+04 Cs-134 6.79E+10 1.11E+11 2.35E+10 0.OOE+00 3.45E+10 1.24E+10 6.01E+08 Cs-136 3.03E+09 8.32E+09 5.39E+09 0.00E+00 4.43E+09 6.61E+08 2.92E+08 Cs-137 9.67E+10 9.26E+10 1.37E+10 0.OOE+00 3.02E+10 1.09E+10 5.80E+08 Cs-138 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+0O 0.OOE+00 O.OOE+00 Ba-139 2.42E-08 1.29E-11 7.01E-10 O.OOE+00 1.13E-11 7.59E-12 1.40E-06 Ba-140 1.41E+07 1.23E+04 8.21E+05 0.OOE+00 4.01E+03 7.34E+03 7.12E+06 Ba-141 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 Ba-142 0.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 La-140 2.33E+00 8.16E-01 2.75E-01 0.OOE+00 0.OOE+00 0.OOE+00 2.27E+04 La-142 9.88E-12 3.15E-12 9.87E-13 0.OOE+00 0.OOE+00 O.OOE+00 6.24E-07 Ce-141 2.62E+03 1.31E+03 1.94E+02 0.OOE+00 5.74E+02 O.OOE+00 1.63E+06 Ce-143 2.25E+01 1.22E+04 1.76E+00 0.OOE+00 5.11E+00 O.0OE+00 1.78E+05 Ce-144 1.95E+05 6.11E+04 1.04E+04 0.OOE+00 3.38E+04 O.OOE+00 1.59E+07 Pr-143 8.62E+01 2.59E+01 4.28E+00 O.OOE+00 1.40E+01 O.OOE+00 9.30E+04 Pr-144 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Nd-147 5.37E+01 4.35E+01 3.37E+00 O.OOE+00 2.39E+01 0.OOE+00 6.89E+04 W-187 3.47E+03 2.05E+03 9.21E+02 0.OOE+00 0.OOE+00 0.OOE+00 2.88E+05 Np-239 2.07E+00 1.48E-01 1.04E-01 O.OOE+00 4.29E-01 0.OOE+00 1.10E+04 Notes:

1) Units are m2 mrem/yr per ýiCi/sec with the exception of H-3 and C-14.

2) For H-3 and C-14, the units are mrem/yr per [iCi/m 3 .

Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 280 of 307 January 2013 Table 4-18 (Page 7 of 8) Grass-Goat-Milk Dose Factors Infant Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI H-3 O.OOE+00 2.78E+03 2.78E+03 2.78E+03 2.78E+03 2.78E+03 2.78E+03 C-14 3.23E+06 6.89E+05 6.89E+05 6.89E+05 6.89E+05 6.89E+05 6.89E+05 Na-24 1.87E+06 1.87E+06 1.87E+06 1.87E+06 1.87E+06 1.87E+06 1.87E+06 Cr-51 O.OOE+00 O.OOE+00 1.93E+04 1.26E+04 2.76E+03 2.46E+04 5.64E+05 Mn-54 O.OOE+00 4.68E+06 1.06E+06 O.OOE+00 1.04E+06 O.OOE+00 1.72E+06 Mn-56 O.OOE+00 3.75E-03 6.47E-04 O.OOE+00 3.22E-03 O.OOE+00 3.41E-01 Fe-55 1.76E+06 1.13E+06 3.03E+05 O.OOE+00 O.OOE+O0 5.55E+05 1.44E+05 Fe-59 2.92E+06 5.09E+06 2.01E+06 O.OOE+00 O.OOE+00 1.51E+06 2.43E+06 Co-58 O.OOE+00 2.91E+06 7.26E+06 O.OOE+00 O.OOE+00 O.OOE+00 7.25E+06 Co-60 O.00E+00 1.06E+07 2.50E+07 O.OOE+00 O.OOE+00 O.OOE+00 2.52E+07 Ni-63 4.19E+09 2.59E+08 1.45E+08 O.OOE+00 O.OOE+00 O.OOE+00 1.29E+07 Ni-65 4.21E-01 4.77E-02 2.17E-02 O.OOE+00 O.OOE+00 O.OOE+00 3.63E+00 Cu-64 O.OOE+00 2.05E+04 9.48E+03 O.OOE+00 3.46E+04 O.OOE+00 4.20E+05 Zn-65 6.66E+08 2.28E+09 1.05E+09 O.OOE+00 1.11E+09 O.OOE+00 1.93E+09 Zn-69 2.33E-12 4.19E-12 3.12E-13 O.OOE+00 1.74E-12 O.OOE+00 3.42E-10 Br-83 O.OOE+00 O.OOE+00 1.11E-01 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Br-84 O.OOE+00 O.OOE+00 O.OOE+00 O.00E+00 O.OOE+00 O.OOE+00 0.00E+00 Br-85 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Rb-86 O.OOE+00 2.67E+09 1.32E+09 O.OOE+00 O.OOE+00 O.OOE+00 6.84E+07 Rb-88 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Rb-89 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+O0 O.OOE+00 Sr-89 2.64E+10 O.OOE+00 7.58E+08 O.OOE+00 O.OOE+00 O.OOE+00 5.43E+08 Sr-90 3.91E+11 O.OOE+00 7.92E+09 O.OOE+00 O.OOE+00 O.OOE+00 3.19E+09 Sr-91 5.66E+05 O.OOE+00 2.05E+04 O.OOE+00 O.OOE+00 O.OOE+00 6.70E+05 Sr-92 9.65E+00 O.OOE+00 3.59E-01 O.OOE+00 O.OOE+00 O.OOE+00 1.04E+02 Y-90 8.19E+01 O.OOE+00 2.20E+00 O.OOE+00 O.OOE+00 O.OOE+00 1.13E+05 Y-91M 7.31E-20 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 2.44E-16 Y-91 8.79E+03 O.OOE+00 2.34E+02 O.OOE+00 O.OOE+00 O.OOE+00 6.30E+05 Y-92 6.44E-05 O.OOE+00 1.81E-06 O.OOE+00 O.OOE+00 O.OOE+0 1.23E+00 Y-93 2.57E-01 O.OOE+00 6.99E-03 O.OOE+00 O.OOE+00 O.OOE+0O 2.03E+03 Zr-95 8.17E+02 1.99E+02 1.41E+02 O.OOE+00 2.15E+02 O.OOE+0 9.91E+04 Zr-97 4.87E-01 8.35E-02 3.81E-02 O.OOE+00 8.42E-02 O.OOE+0 5.33E+03 Nb-95 7.13E+04 2.94E+04 1.70E+04 O.OOE+00 2.10E+04 O.OOE+0 2.48E+07 Mo-99 O.OOE+00 2.49E+07 4.86E+06 O.OOE+00 3.72E+07 O.OOE+0 8.21E+06 Tc- 99M 3.29E+00 6.78E+00 8.73E+01 O.OOE+00 7.29E+01 3.54E+00 1.97E+03 Tc-101 O.OOE+00 Q.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+0 O.OOE+00 Ru-103 1.04E+03 O.OOE+00 3.48E+02 O.OOE+00 2.16E+03 O.OOE+00 1.27E+04 Ru-105 9.60E-04 O.OOE+00 3.23E-04 O.OOE+00 7.06E-03 O.OOE+0 3.82E-01 Ru-106 2.28E+04 O.OOE+00 2.85E+03 O.OOE+00 2.70E+04 O.OOE+0 1.73E+05 Ag-11OM 4.63E+07 3.38E+07 2.24E+07 O.OOE+00 4.84E+07 O.OOE+0O 1.75E+09 Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 281 of 307 January 2013 Table 4-18 (Page 8 of 8) Grass-Goat-Milk Dose Factors Infant Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI Te-125M 1.81E+07 6.05E+06 2.45E+06 6.09E+06 0.OOE+00 0.OOE+00 8.62E+06 Te-127M 5.05E+07 1.68E+07 6.12E+06 1.46E+07 1.24E+08 O.OOE+00 2.04E+07 Te-127 7.74E+02 2.59E+02 1.66E+02 6.30E+02 1.89E+03 O.OOE+00 1.63E+04 Te-129M 6.68E+07 2.29E+07 1.03E+07 2.57E+07 1.67E+08 0.OOE+00 3.99E+07 Te-129 3.26E-10 1.13E-10 7.62E-11 2.74E-10 8.13E-1O 0.OOE+00 2.61E-08 Te-131M 4.05E+05 1.63E+05 1.35E+05 3.30E+05 1.12E+06 0.OOE+00 2.74E+06 Te-131 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Te-132 2.52E+06 1.25E+06 1.17E+06 1.84E+06 7.81EE+06 0.OOE+00 4.62E+06 1-130 4.24E+06 9.32E+06 3.74E+06 1.04E+09 1.02E+07 0.OOE+00 2.OOE+06 1-131 3.26E+09 3.85E+09 1.69E+09 1.26E+12 4.49E+09 0.OOE+00 1.37E+08 1-132 1.72E+00 3.49E+00 1.24E+00 1.64E+02 3.90E+00 0.OOE+00 2.83E+00 1-133 4.36E+07 6.35E+07 1.86E+07 1.15E+10 7.46E+07 O.OOE+00 1.07E+07 1-134 1.98E-11 4.05E-11 1.44E-11 9.44E-10 4.53E-11 O.OOE+00 4.19E-11 1-135 1.36E+05 2.70E+05 9.83E+04 2.42E+07 3.01E+05 0.00E+00 9.76E+04 Cs-134 1.09E+11 2.04E+11 2.06E+10 0.OOE+00 5.25E+10 2.15E+10 5.54E+08 Cs-136 5.91E+09 1.74E+10 6.49E+09 O.OOE+00 6.93E+09 1.42E+09 2.64E+08 Cs-137 1.54E+11 1.81E+11 1.28E+1O 0.OOE+00 4.85E+10 1.96E+10 5.65E+08 Cs-138 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 Ba-139 5.14E-08 3.41E-11 1.49E-09 0.OOE+00 2.05E-11 2.07E-11 3.26E-06 Ba-140 2.89E+07 2.89E+04 1.49E+06 0.OOE+00 6.87E+03 1.78E+04 7.11E+06 Ba-141 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Ba-142 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 O.00E+00 0.OOE+00 La-140 4.88E+00 1.92E+00 4.95E-01 O.OOE+00 0.OOE+00 0.OOE+00 2.26E+04 La-142 2.08E-11 7.62E-12 1.82E-12 0.OOE+00 0.OOE+00 0.OOE+00 1.29E-06 Ce-141 5.20E+03 3.17E+03 3.73E+02 O.OOE+00 9.78E+02 0.OOE+00 1.64E+06 Ce-143 4.75E+01 3.15E+04 3.60E+00 0.OOE+00 9.19E+00 0.OOE+00 1.84E+05 Ce-144 2.79E+05 1.14E+05 1.56E+04 O.OOE+00 4.62E+04 O.OOE+00 1.60E+07 Pr-143 1.78E+02 6.67E+01 8.84E+00 0.OOE+00 2.48E+01 0.OOE+00 9.41E+04 Pr-144 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 Nd-147 1.07E+02 1.09E+02 6.70E+00 0.OOE+00 4.22E+01 0.OOE+00 6.93E+04 W-187 7.29E+03 5.07E+03 1.75E+03 0.OOE+00 0.OOE+00 0.OOE+00 2.98E+05 Np-239 4.37E+00 3.91E-01 2.21E-01 0.OOE+00 7.80E-01 0.OOE+00 1.13E+04 Notes:

1) Units are m 2 mrem/yr per [LCi/sec with the exception of H-3 and C-14.

2) For H-3 and C-14, the units are mrem/yr per [tCi/m 3 .

Quad Cities ODCM Part II

CY-QC-1770-301 Revision 11 Page 282 of 307 January 2013 Table 4-19 (Page 1 of 6) Grass-Cow-Meat Dose Factors Adult Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI H-3 O.OOE+00 1.85E+02 1.85E+02 1.85E+02 1.85E+02 1.85E+02 1.85E+02 C-14 3.33E+05 6.66E+04 6.66E+04 6.66E+04 6.66E+04 6.66E+04 6.66E+04 Na-24 1.45E-03 1.45E-03 1.45E-03 1.45E-03 1.45E-03 1.45E-03 1.45E-03 Cr-51 O.OOE+00 O.OOE+00 7.04E+03 4.21E+03 1.55E+03 9.34E+03 1.77E+06 Mn-54 O.OOE+00 9.18E+06 1.75E+06 O.OOE+00 2.73E+06 O.OOE+00 2.81E+07 Mn-56 O.OOE+00 O.OOE+00 O.OOE+00 O.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 Fe-55 2.93E+08 2.03E+08 4.72E+07 O.OOE+00 O.OOE+00 1.13E+08 1.16E+08 Fe-59 2.65E+08 6.24E+08 2.39E+08 O.OOE+00 O.OOE+00 1.74E+08 2.08E+09 Co-58 O.OOE+00 1.82E+07 4.09E+07 O.OOE+00 O.OOE+00 O.OOE+00 3.70E+08 Co-60 O.OOE+00 7.52E+07 1.66E+08 O.OOE+00 O.OOE+00 O.OOE+00 1.41E+09 Ni-63 1.89E+10 1.31E+09 6.33E+08 O.OOE+00 O.OOE+00 O.OOE+00 2.73E+08 Ni-65 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Cu-64 O.OOE+00 2.52E-07 1.18E-07 O.OOE+00 6.36E-07 O.OOE+00 2.15E-05 Zn-65 3.56E+08 1.13E+09 5.12E+08 O.OOE+00 7.57E+08 o.0OE+00 7.13E+08 Zn-69 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Br-83 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Br-84 O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+O0 O.OOE+00 O.OOE+00 O.OOE+00 Br-85 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.00E+00 O.OOE+00 Rb-86 O.OOE+00 4.88E+08 2.28E+08 O.OOE+00 O.OOE+00 O.OOE+00 9.63E+07 Rb-88 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Rb-89 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 Sr-89 3.01E+08 O.OOE+00 8.65E+06 O.OOE+00 O.OOE+00 O.OOE+00 4.83E+07 Sr-90 1.43E+10 O.OOE+00 2.87E+08 O.OOE+00 O.OOE+00 O.OOE+00 3.59E+08 Sr-91 1.43E-10 O.OOE+00 5.79E-12 O.OOE+00 O.OOE+00 O.OOE+00 6.83E-10 Sr-92 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Y-90 1.08E+02 O.OOE+00 2.91E+00 O.OOE+00 O.OOE+00 O.OOE+00 1.15E+06 Y-91M O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Y-91 1.13E+06 O.OOE+00 3.03E+04 O.OOE+00 O.OOE+0 O.OOE+00 6.23E+08 Y-92 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+0 O.OOE+00 O.OOE+00 Y-93 4.39E-12 O.OOE+00 1.21E-13 O.OOE+00 O.OOE+0 O.OOE+00 1.39E-07 Zr-95 1.87E+06 6.01E+05 4.07E+05 O.OOE+00 9.43E+05 O.OOE+00 1.91EE+09 Zr-97 2.04E-05 4.12E-06 1.88E-06 O.OOE+00 6.22E-06 O.OOE+00 1.28E+00 Nb-95 2.30E+06 1.28E+06 6.89E+05 O.OOE+00 1.27E+06 O.OOE+00 7.78E+09 Mo-99 O.OOE+00 9.93E+04 1.89E+04 O.OOE+00 2.25E+05 O.OOE+00 2.30E+05 Tc-99M O.OOE+00 1.22E-20 1.56E-19 O.OOE+00 1.85E-19 O.OOE+00 7.23E-18 Tc-101 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ru-103 1.05E+08 O.OOE+00 4.53E+07 O.OOE+O0 4.01E+08 O.OOE+00 1.23E+10 Ru-105 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Ru-106 2.80E+09 O.OOE+00 3.54E+08 O.OOE+00 5.40E+09 O.OOE+00 1.81E+11 Ag-110M 6.68E+06 6.18E+06 3.67E+06 O.OOE+00 1.22E+07 O.OOE+00 2.52E+09 Quad Cities ODCM Part II

CY-QC-170-301 Revision 11 Page 283 of 307 January 2013 Table 4-19 (Page 2 of 6) Grass-Cow-Meat Dose Factors Adult Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI Te-125M 3.59E+08 1.30E+08 4.81E+07 1.08E+08 1.46E+09 0.OOE+00 1.43E+09 Te-127M 1.12E+09 3.99E+08 1.36E+08 2.85E+08 4.53E+09 0.OOE+00 3.74E+09 Te-127 2.50E-10 8.98E-11 5.41E-11 1.85E-10 1.02E-09 0.OOE+00 1.97E-08 Te-129M 1.13E+09 4.23E+08 1.79E+08 3.89E+08 4.73E+09 0.OOE+00 5.71E+09 Te-129 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 Te-131M 4.49E+02 2.20E+02 1.83E+02 3.48E+02 2.23E+03 0.OOE+00 2.18E+04 Te-131 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+0O 0.OOE+0O 0.OOE+00 Te-132 1.40E+06 9.03E+05 8.48E+05 9.98E+05 8.70E+06 0.OOE+00 4.27E+07 1-130 2.03E-06 5.98E-06 2.36E-06 5.07E-04 9.33E-06 0.OOE+00 5.15E-06 1-131 1.07E+07 1.54E+07 8.80E+06 5.03E+09 2.63E+07 0.OOE+00 4.05E+06 1-132 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 1-133 3.70E-01 6.43E-01 1.96E-01 9.45E+01 1.12E+00 0.OOE+00 5.78E-01 1-134 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+0O 0.OOE+00 O.OOE+00 1-135 4.66E-17 1.22E-16 4.50E-17 8.04E-15 1.95E-16 0.OOE+00 1.38E-16 Cs-134 6.58E+08 1.57E+09 1.28E+09 0.OOE+00 5.07E+08 1.68E+08 2.74E+07 Cs-136 1.20E+07 4.73E+07 3.40E+07 O.00E+00 2.63E+07 3.61EE+06 5.37E+06 Cs-137 8.72E+08 1.19E+09 7.81E+08 O.OOE+00 4.05E+08 1.35E+08 2.31E+07 Cs-1 38 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 Ba-139 O.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.00E-+00 0.OOE+00 0.OOE+00 Ba-140 2.88E+07 3.61E+04 1.88E+06 0.OOE+00 1.23E+04 2.07E+04 5.92E+07 Ba-141 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 Ba-142 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 La-140 3.76E-02 1.90E-02 5.01E-03 0.OOE+00 0.OOE+00 0.OOE+00 1.39E+03 La-142 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 Ce-141 1.40E+04 9.49E+03 1.08E+03 0.OOE+00 4.41E+03 0.00E+00 3.63E+07 Ce-143 1.99E-02 1.47E+01 1.63E-03 0.OOE+00 6.47E-03 0.OOE+00 5.49E+02 Ce-144 1.46E+06 6.09E+05 7.83E+04 0.OOE+00 3.61E+05 0.OOE+00 4.93E+08 Pr-143 2.10E+04 8.42E+03 1.04E+03 O.OOE+00 4.86E+03 0.OOE+00 9.20E+07 Pr-144 0.OOE+00 0.OOE+0O 0.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 Nd-147 7.21E+03 8.33E+03 4.98E+02 O.OOE+00 4.87E+03 0.OOE+00 4.OOE+07 W-187 2.07E-02 1.73E-02 6.04E-03 0.OOE+00 0.OOE+00 O.OOE+00 5.66E+00 Np-239 2.57E-01 2.53E-02r 1.40E-02 0.OOE+00 7.90E-02 O.OOE+00 5.19E+03 Notes:

1) Units are m2 mrem/yr per [pCi/sec with the exception of H-3 and C-14.

2) For H-3 and C-14, the units are mrem/yr per pCi/m 3.

Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 284 of 307 January 2013 Table 4-19 (Page 3 of 6) Grass-Cow-Meat Dose Factors Teen Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI H-3 0.OOE+00 1.10E+02 1.1OE+02 1.10E+02 1.10E+02 1.10E+02 1.10E+02 C-14 2.81E+05 5.62E+04 5.62E+04 5.62E+04 5.62E+04 5.62E+04 5.62E+04 Na-24 1.16E-03 1.16E-03 1.16E-03 1.16E-03 1.16E-03 1.16E-03 1.16E-03 Cr-51 0.OOE+00 0.OOE+00 5.63E+03 3.13E+03 1.23E+03 8.04E+03 9.46E+05 Mn-54 0.OOE+00 7.OOE+06 1.39E+06 0.OOE+00 2.09E+06 0.OOE+00 1.44E+07 Mn-56 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 O.OOE+00 O.OOE+0O 0.OOE+00 Fe-55 2.38E+08 1.69E+08 3.94E+07 O.00E+00 0.OOE+00 1.07E+08 7.31E+07 Fe-59 2.12E+08 4.95E+08 1.91E+08 O.OOE+00 0.OOE+00 1.56E+08 1.17E+09 Co-58 0.OOE+00 1.41 E+07 3.24E+07 0.OOE+00 O.OOE+00 O.OOE+00 1.94E+08 Co-60 0.OOE+00 5.83E+07 1.31E+08 0.OOE+00 0.OOE+00 0.OOE+00 7.60E+08 Ni-63 1.52E+10 1.07E+09 5.15E+08 0.OOE+00 0.OOE+00 O.OOE+00 1.71E+08 Ni-65 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 Cu-64 0.OOE+00 2.06E-07 9.68E-08 0.OOE+00 5.21E-07 0.OOE+00 1.60E-05 Zn-65 2.50E+08 8.69E+08 4.05E+08 O.OOE+00 5.56E+08 0.OOE+00 3.68E+08 Zn-69 0.OOE+0O 0.OOE+0O 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 Br-83 0.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 Br-84 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 Br-85 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 Rb-86 0.OOE+00 4.08E+08 1.91E+08 O.OOE+00 O.OOE+00 O.OOE+00 6.03E+07 Rb-88 0.OOE+00 O.OOE+0O 0.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 Rb-89 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 Sr-89 2.54E+08 0.OOE+00 7.28E+06 0.OOE+00 O.OOE+0O 0.OOE+00 3.03E+07 Sr-90 9.89E+09 0.OOE+00 1.98E+08 0.OOE+00 0.OOE+00 O.OOE+00 2.26E+08 Sr-91 1.21E-10 0.OOE+00 4.80E-12 O.OOE+00 O.OOE+00 O.00E+00 5.47E-10 Sr-92 O.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 Y-90 9.13E+01 0.OOE+00 2.46E+00 O.OOE+00 0.OOE+00 O.OOE+00 7.53E+05 Y-91M O.OOE+00 O.OOE+0O 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Y-91 9.54E+05 0.OOE+00 2.56E+04 0.OOE+00 0.OOE+00 0.OOE+00 3.91E+08 Y-92 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 Y-93 3.71E-12 0.OOE+00 1.02E-13 0.OOE+00 O.OOE+00 O.OOE+00 1.13E-07 Zr-95 1.50E+06 4.74E+05 3.26E+05 O.OOE+00 6.96E+05 0.OOE+00 1.09E+09 Zr-97 1.70E-05 3.37E-06 1.55E-06 O.OOE+00 5.1OE-06 0.OOE+00 9.11E-01 Nb-95 1.80E+06 9.98E+05 5.49E+05 O.OOE+00 9.67E+05 O.OOE+00 4.27E+09 Mo-99 0.OOE+00 8.21 E+04 1.57E+04 O.OOE+00 1.88E+05 0.OOE+00 1.47E+05 Tc-99M 0.OOE+00 O.00E+00 1.24E-19 0.OOE+00 1.43E-19 O.OOE+00 6.29E-18 Tc-101 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Ru-103 8.56E+07 0.OOE+00 3.66E+07 O.OOE+00 3.02E+08 0.OOE+00 7.15E+09 Ru-1 05 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.00E+00 O.OOE+00 Ru-106 2.36E+09 0.00E+00 2.97E+08 O.OOE+00 4.55E+09 0.OOE+00 1.13E+11 Ag-110M 5.06E+06 4.79E+06 2.91E+06 O.OOE+00 9.13E+06 0.00E+00 1.35E+09 Quad Cities ODCM Part II

CY-QC-170-301 Revision 11 Page 285 of 307 January 2013 Table 4-19 (Page 4 of 6) Grass-Cow-Meat Dose Factors Teen Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI Te-125M 3.03E+08 1.09E+08 4.06E+07 8.47E+07 0.OOE+00 0.OOE+00 8.95E1:+08 Te-127M 9.41E+08 3.34E+08 1.12E+08 2.24E+08 3.82E+09 0.OOE+00 2.35E+09 Te-127 2.12E-10 7.53E-11 4.57E-11 1.46E-10 8.60E-10 0.OOE+00 1.64E-08 Te-129M 9.49E+08 3.52E+08 1.50E+08 3.06E+08 3.97E+09 0.OOE+00 3.56E+09 Te-129 O.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Te-131M 3.75E+02 1.80E+02 1.50E+02 2.70E+02 1.87E+03 0.OOE+00 1.44E+04 Te-131 0.OOE+0O 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 Te-132 1.14E+06 7.24E+05 6.811E+05 7.63E+05 6.94E+06 0.OOE+00 2.29E+07 1-130 1.63E-06 4.72E-06 1.88E-06 3.85E-04 7.27E-06 O.OOE+00 3.63E-06 1-131 8.92E+06 1.25E+07 6.71E+06 3.64E+09 2.15E+07 0.OOE+00 2.47E+06 1-132 0.00E+00 O.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1-133 3.09E-01 5.25E-01 1.60E-01 7.32E+01 9.20E-01 0.OOE+00 3.97E-01 1-134 0.OOE+00 O.OOE+0O 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 1-135 3.79E-17 9.75E-17 3.61E-17 6.27E-15 1.54E-16 0.oOE+00 1.08E-16 Cs-134 5.23E+08 1.23E+09 5.71E+08 O.OOE+00 3.91E+08 1.49E+08 1.53E+07 Cs-136 9.34E+06 3.68E+07 2.47E+07 0.OOE+00 2.OOE+07 3.15E+06 2.96E+06 Cs-1 37 7.24E+08 9.63E+08 3.36E+08 O.OOE+00 3.28E+08 1.27E+08 1.37E+07 Cs-1 38 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 Ba-1 39 O.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Ba-140 2.38E+07 2.91E+04 1.53E+06 0.OOE+00 9.88E+03 1.96E+04 3.67E+07 Ba-141 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 Ba-142 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 La-140 3.09E-02 1.52E-02 4.04E-03 0.OOE+00 0.OOE+00 0.OOE+00 8.73E+02 La-142 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 Ce-141 1.18E+04 7.87E+03 9.04E+02 0.OOE+00 3.70E+03 0.OOE+00 2.25E+07 Ce-143 1.67E-02 1.22E+01 1.36E-03 0.OOE+00 5.46E-03 0.OOE+00 3.66E+02 Ce-144 1.23E+06 5.08E+05 6.60E+04 O.OOE+00 3.04E+05 O.OOE+00 3.09E+08 Pr-143 1.77E+04 7.05E+03 8.79E+02 O.OOE+00 4.10E+03 0.OOE+00 5.81E+07 Pr-144 O.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Nd-147 6.35E+03 6.90E+03 4.14E+02 0.OOE+00 4.05E+03 0.OOE+00 2.49E+07 W-187 1.73E-02 1.41E-02 4.94E-03 0.OOE+00 0.OOE+0O 0.OOE+00 3.82E+00 Np-239 2.25E-01 2.12E-02 1.18E-02 0.OOE+00 6.66E-02 0.OOE+00 3.41iE+03 Notes:

1) Units are m2 mrem/yr per .lpCi/sec with the exception of H-3 and C-14.

2) For H-3 and C-14, the units are mrem/yr per [,Ci/m 3 .

Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 286 of 307 January 2013 Table 4-19 (Page 5 of 6) Grass-Cow-Meat Dose Factors Child Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI H-3 0.OOE+00 1.34E+02 1.34E+02 1.34E+02 1.34E+02 1.34E+02 1.34E+02 C-14 5.29E+05 1.06E+05 1.06E+05 1.06E+05 1.06E+05 1.06E+05 1.06E+05 Na-24 1.84E-03 1.84E-03 1.84E-03 1.84E-03 1.84E-03 1.84E-03 1.84E-03 Cr-51 0.OOE+00 0.OOE+00 8.78E+03 4.87E+03 1.33E+03 8.90E+03 4.66E+05 Mn-54 0.OOE+00 8.01E+06 2.13E+06 O.OOE+00 2.25E+06 0.OOE+00 6.72E+06 Mn-56 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 Fe-55 4.57E+08 2.42E+08 7.51 E+07 0.OOE+00 O.00E+00 1.37E+08 4.49E+07 Fe-59 3.76E+08 6.08E+08 3.03E+08 0.OOE+00 O.OOE+00 1.76E+08 6.34E+08 Co-58 O.OOE+00 1.64E+07 5.03E+07 O.OOE+00 0.OOE+00 0.OOE+00 9.59E+07 Co-60 0.OOE+00 6.93E+07 2.04E+08 0.OOE+00 0.OOE+00 0.OOE+00 3.84E+08 Ni-63 2.91E+10 1.56E+09 9.91E+08 O.OOE+00 0.OOE+00 0.OOE+00 1.05E+08 Ni-65 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Cu-64 O.OOE+00 2.77E-07 1.67E-07 O.OOE+00 6.68E-07 0.OOE+00 1.30E-05 Zn-65 3.75E+08 1.OOE+09 6.22E+08 0.OOE+00 6.30E+08 0.OOE+00 1.76E+08 Zn-69 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 Br-83 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 Br-84 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 Br-85 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Rb-86 O.OOE+00 5.78E+08 3.55E+08 O.OOE+00 0.OOE+00 0.OOE+00 3.72E+07 Rb-88 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 Rb-89 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 Sr-89 4.81E+08 O.OOE+00 1.37E+07 0.OOE+00 0.OOE+00 0.OOE+00 1.86E+07 Sr-90 1.57E+10 O.OOE+00 3.15E+08 0.OOE+00 0.OOE+00 0.OOE+00 1.40E+08 Sr-91 2.26E-10 0.OOE+00 8.54E-12 O.OOE+00 0.OOE+00 0.OOE+00 5.OOE-10 Sr-92 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Y-90 1.73E+02 0.OOE+00 4.62E+00 O.OOE+00 O.OOE+00 0.OOE+00 4.92E+05 Y-91M 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 Y-91 1.80E+06 0.OOE+00 4.82E+04 O.00E+00 0.OOE+00 0.OOE+00 2.40E+08 Y-92 0.OOE+00 0.OOE+00 0.OOE+0O 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 Y-93 6.97E-12 0.OOE+00 1.91E-13 O.OOE+00 0.OOE+00 0.OOE+00 1.04E-07 Zr-95 2.67E+06 5.86E+05 5.22E+05 0.OOE+00 8.39E+05 O.OOE+00 6.11E+08 Zr-97 3.16E-05 4.57E-06 2.70E-06 0.O0E+00 6.56E-06 0.OOE+00 6.93E-01 Nb-95 3.11E'+06 1.21E+06 8.64E+05 0.OOE+00 1.14E+06 O.OOE+00 2.24E+09 Mo-99 O.OOE+00 1.14E+05 2.82E+04 0.OOE+00 2.44E+05 O.OOE+00 9.44E+04 Tc- 99M O.OOE+00 1.18E-20 1.96E-19 0.OOE+00 1.72E-19 0.OOE+00 6.72E-18 Tc-1 01 O.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 Ru-103 1.55E+08 0.OOE+00 5.95E+07 0.OOE+00 3.90E+08 0.OOE+00 4.00E+09 Ru-1 05 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Ru-1 06 4.44E+09 0.OOE+00 5.54E+08 O.OOE+00 5.99E+09 0.OOE+00 6.90E+10 Ag-11iM 8.39E+06 5.67E+06 4.53E+06 O.OOE+00 1.06E+07 0.OOE+00 6.74E+08 Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 287 of 307 January 2013 Table 4-19 (Page 6 of 6) Grass-Cow-Meat Dose Factors Child Age Group Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI Te-125M 5.70E+08 1.54E+08 7.59E+07 1.60E+08 0.00E+00 0.OOE+00 5.50E+08 Te-127M 1.77E+09 4.78E+08 2.11E+08 4.24E+08 5.06E+09 O.OOE+00 1.44E+09 Te-127 3.99E-10 1.08E-10 8.56E-11 2.76E-10 1.14E-09 0.00E+00 1.56E-08 Te-129M 1.79E+09 5.OOE+08 2.78E+08 5.77E+08 5.25E+09 O.OOE+00 2.18E+09 Te-129 O.OOE+00 0.OOE+00 O.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 Te-131M 6.97E+02 2.41E+02 2.57E+02 4.96E+02 2.33E+03 0.OOE+00 9.78E+03 Te-131 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Te-132 2.09E+06 9.23E+05 1.12E+06 1.34E+06 8.57E+06 0.OOE+00 9.30E+06 1-130 2.92E-06 5.89E-06 3.04E-06 6.49E-04 8.81E-06 O.OOE+00 2.76E-06 1-131 1.65E+07 1.66E+07 9.45E+06 5.50E+09 2.73E+07 O.OOE+00 1.48E+06 1-132 0.OOE+0O 0.OOE+0O 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1-133 5.75E-01 7.1OE-01 2.69E-01 1.32E+02 1.18E+00 0.OOE+00 2.86E-01 1-134 0.OOE+0O O.00E+0O 0.00E+00 O.00E+00 0.OOE+0O 0.O0E+00 0.OOE+00 1-135 6.86E-17 1.23E-16 5.84E-17 1.09E-14 1.89E-16 0.OOE+00 9.40E-17 Cs-134 9.22E+08 1.51E+09 3.19E+08 O.OOE+00 4.69E+08 1.68E+08 8.16E+06 Cs-136 1.61E+07 4.43E+07 2.87E+07 0.OOE+00 2.36E+07 3.52E+06 1.56E+06 Cs-137 1.33E+09 1.28E+09 1.88E+08 0.OOE+00 4.16E+08 1.50E+08 7.99E+06 Cs-1 38 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 O.OOE+00 0.OOE+00 Ba-1 39 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 Ba-140 4.39E+07 3.84E+04 2.56E+06 0.00E+00 1.25E+04 2.29E+04 2.22E+07 Ba-141 0.00E+00 0.00E+00 0.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 Ba-142 Q.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 La-140 5.66E-02 1.98E-02 6.67E-03 0.00E+00 0.00E+00 0.O0E+00 5.52E+02 La-142 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 Ce-141 2.22E+04 1.11iE+04 1.64E+03 0.OOE+00 4.85E+03 0.OOE+00 1.38E+07 Ce-143 3.14E-02 1.70E+01 2.46E-03 0.OOE+00 7.14E-03 0.OOE+00 2.49E+02 Ce-144 2.32E+06 7.26E+05 1.24E+05 0.00E+00 4.02E+05 0.OOE+00 1.89E+08 Pr-143 3.34E+04 1.OOE+04 1.66E+03 0.OOE+00 5.44E+03 0.OOE+00 3.61E+07 Pr-144 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+0O 0.OOE+00 O.OOE+00 Nd-147 1.19E+04 9.65E+03 7.47E+02 0.OOE+00 5.29E+03 0.OOE+00 1.53E+07 W-187 3.21E-02 1.90E-02 8.52E-03 0.OOE+00 0.OOE+00 0.OOE+00 2.67E+00 Np-239 4.23E-01 3.04E-02 2.14E-02 0.OOE+00 8.79E-02 0.OOE+00 2.25E+03 Notes:

1) Units are m2 mrem/yr per [LCi/sec with the exception of H-3 and C-14.

2) For H-3 and C-14, the units are mrem/yr per ýtCi/m 3 .

3) The infant age group is assumed to receive no dose through the meat ingestion pathway therefore no dose factors are supplied.

Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 288 of 307 January 2013 5.0 TOTAL DOSE Radioactivity contained within tanks, pipes or other systems and contained radioactive material or waste stored on site can produce radiation at offsite locations. Annual offsite radiation doses near the stations due to such sources were judged to be negligible in comparison with applicable limits except for doses due to BWR turbine skyshine and potential doses due to radioactive waste storage facilities (excludes radioactive material storage). Changes or modifications to the power station that may impact the offsite dose through increases to the direct radiation levels need to be evaluated on a case-by-case basis and added to the Radiological Effluent Controls (RECS) to the ODCM when applicable. 5.1 Total Dose Calculation Requirements 5.1.1 Total Effective Dose Equivalent Limits; 10CFR20, 40CFR190, and 10CFR72 The Quad Cities Station is required to determine the total dose to a member of the public due to all uranium fuel cycle sources in order to assess compliance with 40CFR1 90 as part of demonstrating compliance with 10CFR20. The total dose for the uranium fuel cycle is the sum of doses due to radioactivity in airborne and liquid effluents and the doses due to direct radiation from contained sources at the nuclear power station. When evaluation of total dose is required for a station, the following contributions are summed:

• Doses due to airborne and liquid effluents from the station.
• Doses due to liquid effluents from nuclear power stations upstream.
• Doses due to any onsite radioactive waste storage facilities, if applicable.

                     " Doses due      to N-16 skyshine.

10CFR20 requires compliance to dose limits expressed as "Total Effective Dose Equivalent" (TEDE). Although annual dose limits in 10CFR20 are now expressed in terms of TEDEs, 40CFR1 90 limits remain stated as organ dose. The NRC continues to require 10CFR50 Appendix I and 40CFR1 90 doses to be reported in terms of organ dose and not TEDE. Due to the fact that organ dose limits set forth in 40CFR190 are substantially lower than those of 10CFR20 (25 mrem/yr vs. 100 mrem/yr), the NRC has stated that demonstration of compliance with the dose limits in 40CFR190 will be deemed as demonstration of compliance with the dose limits of 10CFR20 for most facilities (Reference 104). In addition to compliance with 40CFR190, it may be necessary for a nuclear power plant to address dose from on-site activity by members of the public. Quad Cities ODCM Part II

CY-QC-170-301 Revision 11 Page 289 of 307 January 2013 5.1.2 ISFSI 10CFR72.104 dose limits are the same as those specified by 40CFR190. Even a fully loaded ISFSI is not expected to become the prominent contributor to the limits in this section. ISFSI dose contribution is in the form of direct radiation as no liquid or gas releases are expected to occur. The 10CFR72.212 report prepared in accordance with ISFSI requirements assumes a certain array of casks exists on the pad. The dose contribution from this array of casks in combination with historical uranium fuel cycle operations (e.g. QCNPS 1 & 2) prior to ISFSI operations was analyzed to be within the 40CFR190 and 10CFR72.104 limits. If the dose limits of 40CFR190 or 10CFR72.104 are exceeded, a special report to the NRC as well as an appropriate request for exemption/variance is required to be submitted to the NRC. The requirement that the dose limits of 10CFR72.104 apply to "any real individual" is controlled for ISFSI activities in the ISFSI 72.212 report. Therefore, for the purposes of analyzing dose in the south end of the site, the member of the public as defined in 40CFR1 90 at this area is the same as the "real individual" identified in the 72.212 report. However, the location for the real individual identified in the ISFSI 72.212 report is not the limiting individual for calculating dose. The real individual that lives 800 meters north of QCNPS will remain the limiting individual, even with a fully loaded ISFSI. 5.1.3 Total Dose Calculation Methodology There are presently two types of contained sources of radioactivity that are of concern in Quad Cities Station's offsite radiological dose assessments. The first source is that due to gamma rays from nitrogen-1 6 ( 16 N) carried over to the turbine in BWR (boiling water reactor) steam. The second source is that due to gamma rays associated with radioactive material resident in onsite radwaste storage facilities. Gamma radiation from these sources contributes to the whole total body dose (deep dose equivalent). In addition to the total body, skin and single organ dose assessments previously described, an additional assessment is required. The additional assessment addresses radiation dose due to radioactivity contained within the nuclear power station and its structures. Quad Cities ODCM Part II

CY-QC-170-301 Revision 11 Page 290 of 307 January 2013 5.1.4 BWR Skyshine The most significant dose component to members of the public produced by "contained sources" is nitrogen-16 ( 16 N) within the turbine building of BWRs. Although primary side shielding is around the turbine and its piping, 16 N gamma rays scattered by air molecules in the overhead air space above the turbine and piping cause a measurable "skyshine" radiation dose in the local power plant environs. Equation 5-1 is used to evaluate skyshine dose. Quad Cities adds hydrogen to reactor coolant to improve coolant chemistry. The addition of hydrogen can increase the dose rate due to skyshine up to a factor of 10 times expected levels depending on injection rates and power levels (Reference 39). Increasing the hydrogen injection rate will increase the dose rates even further. (See Reference 102) The skyshine dose determined by Equation 5-1 depends on the following factors:

• The distance of the dose recipient location from the turbine.
• The number of hours per year that the location is occupied by a dose recipient.

                      " The total energy [MWe-hr] generated by the nuclear power station with hydrogen addition.
                      " The total energy [MWe-hr] generated by the nuclear power station without hydrogen addition.

5.2 BWR Skyshine Calculation The contained onsite radioactivity source that results in the most significant offsite radiation levels at Quad Cities Station is skyshine resulting from 16N decay inside turbines and steam piping. The 16 N that produces the skyshine effect is formulated through neutron activation of the oxygen atoms (oxygen-16, or 160) in reactor coolant as the coolant passes through the operating reactor core. The 16 N travels with the steam produced in the reactor to the steam driven turbine. While the 16 N is in transport, it radioactively decays with a half-life of about 7 seconds and produces 6 to 7 MeV gamma rays. Typically, offsite dose points are shielded from a direct view of components containing 16 N, but there can be skyshine radiation at offsite locations due to scattering of gamma rays off the mass of air above the steamlines and turbine. The offsite dose rate due to skyshine has been found to have the following dependencies:

• The dose rate decreases as distance from the station increases.

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CY-QC-170-301 Revision 11 Page 291 of 307 January 2013

• The dose rate increases non-linearly as the power production level increases.
• The dose rate increases when hydrogen is added to the reactor coolant, an action taken to improve reactor coolant chemistry characteristics (see Reference 39).

To calculate offsite dose due to skyshine in a given time period due to skyshine, Quad Cities Station must track the following parameters:

• The total gross energy Eh produced with hydrogen being added.
• The total gross energy E. produced without hydrogen being added.

The turbines at the site are sufficiently close to each other that energy generated by the two operating units at may be summed. An initial estimate of skyshine dose is calculated per the following equation: Dsky = (K)(Eo +MhEh)-{OFk SFk e-0 °° 7 Rk } (5-1) k The summation is over all locations "k" occupied by a hypothetical maximally exposed member of the public characterized by the parameters specified in ODCM Part IITable 4-7. The parameters in Equation 5-1 are defined as follows: DSsky Dose Due to N-16 Skyshine [mrem] Gamma External direct gamma dose (deep dose equivalent) due to BWR N-1 6 skyshine for the time period of interest. K Empirical Constant [mrem/(MWe-hr)] A constant determined by fitting data measured at the each station. E, Electrical Energy Generated Without Hydrogen Addition [MWe-hr] Total gross electrical energy generated without hydrogen addition in the time period of interest. Eh Electrical Energy Generated with Hydrogen Addition [MWe-hr] Total gross electrical energy generated with hydrogen addition in the period of interest. Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 292 of 307 January 2013 Mh Multiplication Factor for Hydrogen Addition [dimensionless] Factor applied to offsite dose rate when skyshine is present. Hydrogen addition increases main steam line radiation levels typically up to a factor of approximately 5 (see Page 8-1 of Reference 39). Mh is station specific and is given in ODCM, Part II Table 4-7. OFk Occupancy Factor [dimensionless] The fraction of time that the dose recipient spends at location "k" during the period of interest. See ODCM Part II Table 4-7. SFk Shielding Factor [dimensionless] A dimensionless factor that accounts for shielding due to occupancy of structures. SFk = 0.7 if there is a structure at location "k" SFk = 1.0 otherwise. See ODCM Part II, Table 4-7. 0.007 Empirical Constant [m-1] A constant determined by fitting data measured at the Quad Cities station (see Reference 45). Rk Distance [im] Distance from the turbine to location "k". See ODCM Part II, Table 4-7. 5.3 Onsite Radwaste and Rad Material Storage Facilities A 10CFR50.59 analysis is required for radwaste storage facilities. 5.3.1 Process Waste Storage Facilities 0 Interim Radwaste Storage Facility (IRSF) structure 0 Concrete vaults containing radwaste liners 5.3.2 DAW Storage Facilities

• Dry Active Waste (DAW) facilities (may include Butler buildings/warehouses)
• Seavans or other temporary warehouses Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 293 of 307 January 2013 5.3.3 ISFSI Facilities 0 Independent spent fuel storage installation facilities. 5.4 Methodology The external total body dose is comprised of the following parts: 5.4.1 Total body dose due to noble gas radionuclides in gaseous effluents (Section 4.2.2), 5.4.2 Dose due to 16N skyshine (section 5.2) and other contained sources (section 5.3) and 5.4.3 Total body dose due to radioactivity deposited on the ground (Section 4.2.3.1). The external total body dose due to radioactivity deposited on the ground is accounted for in the determination of the non-noble gas dose and is considered in section 4.2.3 and 4.2.3.1. The total external total body dose, DEx, is given by: DEx= DTBwb + Dsky + DOSF (5-2) DEx Total External Total Body Dose [mrem] Total external total body dose due to irradiation by external sources at the location of interest. DTB Noble Gas Total Body Dose [mrem] External total body dose due to gamma radiation from noble gas radionuclides released in gaseous effluents at the location of interest. See Section 4.2.2.3. DSky Dose Due to N-16 Skyshine Total Body Dose [mrem] External total body dose due to N-16 skyshine for the period and location of interest. See Equation 5-1. DOSF Dose From On-Site Storage Facilities [mrem] External total body dose due to gamma radiation from on-site storage facilities at the location of interest. See Section 5.3. Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 294 of 307 January 2013 5.5 Total Dose The total dose, DT t, in the UNRESTRICTED AREA to a member of the public due to plant operations is given by: DEx + DLiq + DNNG (5-3) where: DTot Total Dose To Member of Public [mrem] Total off-site dose to a member of public due to plant operations. DEx Total External Total Body Dose [mrem] Total body dose due to external exposure to noble gases, N-1 6 skyshine and on-site storage facilities. DLiquid Effluent Dose [mrem] ajLiudEfunDoe[rm Dose due to liquid effluents to age group "a" and organ "J". The age group and organ with the highest dose from liquid effluents is used. DjNG Non-Noble Gaseous Effluent Dose [mrem] Dose due to non-noble gaseous effluents to age group "a" and organ "j". The age group and organ with the highest dose from non-noble gas effluents is used. 5.6 Compliance to Total Dose Limits 5.6.1 Total Effective Dose Equivalent Limit - 10CFR20 Compliance Quad Cities' RECS limits the Total Effective Dose Equivalent (TEDE) to an annual limit of 100 mrem, as required by 10CFR20.1301 (a)(1). Demonstration of compliance with the limits of 40CFR1 90 (per Section 5.1.1) will be considered to demonstrate compliance with the 100 mrem/year limit. Quad Cities ODCM Part II

CY-QC-1770-301 Revision 11 Page 295 of 307 January 2013 5.6.2 Dose to a MEMBER OF THE PUBLIC in the UNRESTRICTED AREA The NRC has stated that demonstration of compliance with the limits of 40CFR1 90 or with the design objectives of Appendix I to 10CFR50 will be deemed to demonstrate compliance with the limits of 10CFR20.1301(a)(1). Power reactors that comply with Appendix I may also have to demonstrate that they are within the 25 mrem limit of 40CFR190 (See Reference 104). 5.6.3 Dose to a MEMBER OF THE PUBLIC in the RESTRICTED AREA In August of 1995, a revision to 10CFR20 was implemented that changed the definition of a member of the public. As a result, estimated doses were calculated for a member of the public who enters the site boundary, but is not authorized for unescorted access to the protected area of the site and does not enter any radiologically posted areas on the site. Realistic assumptions were made for occupancy times and locations visited while within the site boundary. These evaluations indicate that the doses estimated for these members of the public are well within the 10CFR20 limits. These dose evaluations will be performed annually and if necessary, a model will be developed and included in the ODCM. Evaluation of the 40CFR1 90 dose is used to demonstrate compliance to 10CFR20 and satisfy station RECS and Technical Specifications (see ODCM Part I). 5.6.4 Total Dose Due to the Uranium Fuel Cycle (40CFR190) RECS, 40CFR1 90, and 10CFR72 limit the annual (calendar year) dose or dose commitment to any member of the public due to releases of radioactivity and to radiation from uranium fuel cycle sources to the following:

• Less than or equal to 25 mrem to the total body.
• Less than or equal to 25 mrem to any organ except the thyroid.
• Less than or equal to 75 mrem to the thyroid.

Total Dose Components This requirement includes the total dose from operations at the nuclear power station. This includes doses due to radioactive effluents (airborne and liquid) and dose due to direct radiation from non-effluent sources (e.g., sources contained in systems on site). It also includes dose due to Quad Cities ODCM Part II

CY-QC-170-301 Revision 11 Page 296 of 307 January 2013 plants under consideration, neighboring plants and dose due to other facilities in the uranium fuel cycle. The operations comprising the uranium fuel cycle are specified in 40CFR1 90.02(b). The following are included to the extent that they directly support the production of electrical power for public use utilizing nuclear energy:

                     "   Milling of uranium ore.

• Chemical conversion of uranium.
• Isotopic enrichment of uranium.
• Fabrication of uranium fuel.

                     "   Generation of electricity by a light-watered-cooled nuclear power plant using uranium fuel.

• Reprocessing of spent uranium fuel.

Excluded are:

• Mining operations.
• Operations at waste disposal sites.
• Transportation of any radioactive material in support of these operations.
• The re-use of recovered non-uranium special nuclear and by-product materials from the cycle.

5.7 When Compliance Assessment is Required Compliance with the 40CFR190 regulations is required as part of demonstration of compliance to 1 OCFR20 regulations per 1 OCFR20.1301 (d). The dose due to the uranium fuel cycle is determined by equation 5-3. Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 297 of 307 January 2013 PROGRAM 6.0 RADIOLOGICAL ENVIRONMENTAL MONITORING 6.1 General Information 6.1.1 The Radiological Environmental Monitoring Program (REMP) supplements the results of station radiological effluent monitoring by verifying that the measurable concentration of radioactive material and levels of radiation present in the surrounding environment are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways. 6.1.2 The REMP program consists of the following components:

                    " Monitoring direct radiation and radionuclides in the environment surrounding the site.

• Performing a Land Use Census annually during the growing season to identify changes in land use. Changes in land use may require changing the monitoring program.
• Participation in an Interlaboratory Comparison Program to ensure independent checks on the precision and accuracy of radioactive material measurement in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring.

6.2 Monitoring 6.2.1 The REMP program monitors the following exposure pathways:

• Airborne
• Direct radiation
• Waterborne
• Ingestion 6.2.2 Specific sampling and analysis requirements of the REMP program are described in ODCM Part II Table 6-1 and ODCM Part I Section 12.6.

ODCM Part II Figure 6-1 and Figure 6-2 shows the specific location of each monitoring locations. 6.2.3 In addition to the monitoring locations described in ODCM Part II Table 6-1 and ODCM Part I Section 12.6, additional direct radiation monitoring is performed. These monitoring locations are described in station procedures and may vary. Reporting dose received from these monitoring locations in the Radiological Environmental Operating Report is not required. Quad Cities ODCM Part II

CY-QC-1770-301 Revision 11 Page 298 of 307 January 2013 6.2.4 Deviations from the sampling requirements of the REMP program are permitted. Refer to ODCM Part I Section 12.6.1 for requirements when required samples are not obtained. 6.3 Land Use Census 6.3.1 A Land Use Census is performed annually to identify changes in land use surrounding the site. Specific requirements of the Land Use Census are described in Table 6-1 and ODCM Part I Section 12.6.2. The results of the Land Use Census are reviewed and the monitoring program modified as necessary. 6.4 Interlaboratory Comparison Program 6.4.1 The laboratory performing the REMP analyses shall participate in an Interlaboratory Comparison Program as described in ODCM Part I Section 12.6.3. Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 299 of 307 January 2013 Table 6-1 (Page 1 of 7) Radiological Environmental Monitoring Program Exposure Pathway Sampling or Type and Frequency and/or Sample Sample or Monitoring Location Collection Frequency of Analysis

1. Airborne Radioiodine and a. Indicators-Near Field Particulates Q-01 Onsite No. 1 0.5 mi N (0.8 km)

Q-02 Onsite No. 2 0.4 mi ENE Radioiodine Canister: (0.7 km) Sampler Operation 1-131 analysis on each Q-03 Onsite No. 3 0.6 mi S (1.0 km) Continuous sample. Q-04 Nitrin, IL 1.7 mi NE (2.7 km)

b. Indicators-Far Field Q-13 Princeton, IA 4.7 mi SW (7.6 km)

Q-16 Low Moor, IA 5.7 mi NNW (9.2 km) Q-37 Meredosia Road, IL 4.4 mi ENE Particulate Sample: (7.1 km) Gross beta analysis on Q-38 Fuller Road, IL 4.7 mi E (7.6 km) Filter change 7 days or each sample. Q-41 Camanche, IA 4.3 mi NNE (6.9 km) more frequently as

c. Control required due to dust Gamma isotopic loading. analysis(3) once per 92 Q-42 LeClaire, IA 8.7 mi SSW (14.1 km) days on composite filters by location.

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CY-QC-1 70-301 Revision 11 Page 300 of 307 January 2013 Table 6-1 (Page 2 of 7) Radiological Environmental Monitoring Program Exposure Pathway Sampling or Type and Frequency and/or Sample Sample or Monitoringq Location Collection Frequency of Analysis

2. Direct Radiation a.lndicators-lnner Ring* 92 days Gamma dose on each Q-101-1, 0.6 mi N (0.9 km) dosimeter once per 92 days Q-101-2, 0.9 mi N (1.4 km)

Q-102-1, 1.3 mi NNE (2.2 km) Q-102-3, 1.4 mi NNE (2.3 km) Q-103-1, 1.2 mi NE (1.9 km) Q-103-2, 1.2 mi NE (1.9 km) Q-104-1, 1.1 mi ENE (1.9 km) Q-104-2, 0.9 mi ENE (1.4 km) Q-105-1, 0.8 mi E (1.2 km) Q-105-2, 0.8 mi E (1.2 km) Q-106-2, 0.7 mi ESE (1.1 km) Q-106-3, 0.7 mi ESE (1.2 km) Q-107-2, 0.7 mi SE (1.2 km) Q-107-3, 0.8 mi SE (1.2 km) Q-108-1, 1.0 mi SSE (1.5 km) Q-108-2, 0.9 mi SSE (1.4 km) Q-109-1, 0.9 mi S (1.4 km) Q-109-2, 1.2 mi S (1.9 km), Q-111-1, 2.6 mi SW (4.2 km) Q-111-2, 2.5 mi SW (4.0 km) Q-112-1, 2.5 mi WSW (4.0 km) Q-1 12-2, 2.2 mi WSW (3.6 km) Q-113-1, 2.5 miW (4.1 km) Q-113-2, 2.5 mi W (4.1 km) Q-114-1, 2.1 mi WNW (3.5 km) Q-114-2, 2.5 mi WNW (4.0 km) Q-115-1, 2.6 mi NW (4.2 km) Q-115-2, 2.3 mi NW (3.6 km) Q-116-1, 2.3 mi NNW (3.7 km) Q-116-3, 2.4 mi NNW (3.9 km)

                         * = Inner Ring dosimeters are not placed within SSW sector because of the river at this range.

J ___________________________________________________ L_________________________ .1. __________________________ Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 301 of 307 January 2013 Table 6-1 (Page 3 of 7) Radiological Environmental Monitoring Program Exposure Pathway Sampling or Type and Frequency and/or Sample Sample or Monitoring Location Collection Frequency of Analysis

2. Direct Radiation b. Indicators-Outer Ring (Cont'd) Q-201-1, 4.2 mi N (6.7 km)

Q-201-2, 4.2 mi N (6.7 km) Q-202-1, 4.4 mi NNE (7.0 km) Q-202-2, 4.8 mi NNE (7.7 km) Q-203-1, 4.7 mi NE (7.5 km) Q-203-2, 5.0 mi NE (8.0 km) Q-204-1, 4.7 mi ENE (7.5 km) Q-204-2, 4.5 mi ENE (7.2 km) Q-205-1, 4.7 mi E (7.5 km) Q-205-4, 4.8 mi E (7.7 km) Q-206-1, 4.8 mi ESE (7.7 km) Q-206-2, 4.8 mi ESE (7.7 km) Q-207-1, 4.7 mi SE (7.6 km) Q-207-4, 4.7 mi SE (7.6 km) Q-208-1, 4.3 mi SSE (6.8 km) Q-208-2, 4.9 mi SSE (7.9 km) Q-209-1, 4.7 mi S (7.6 km) Q-209-4, 4.7 mi S (7.6 km) Q-210-1, 4.1 mi SSW (6.5 km) Q-210-5, 3.3 mi SSW (5.3 km) Q-211-1, 4.5 mi SW (7.3 km) Q-211-2, 4.5 mi SW (7.3 km) Q-212-1, 4.9 mi WSW (7.9 km) Q-212-2, 4.4 mi WSW (7.2 km) Q-213-1, 4.3 mi W (6.9 km) Q-213-2, 4.8 mi W (7.8 km) Q-214-1, 4.7 mi WNW (7.5 km) Q-214-2, 4.4 mi WNW (7.1 km) Q-215-1, 5.0 mi NW (8.0 km) Q-215-2, 4.2 mi NW (6.7 km) Q-216-1, 4.6 mi NNW (7.4 km) Q-216-2, 4.3 mi NNW (7.0 km) Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 302 of 307 January 2013 4 of 7) Table 6-1 (Page Radiological Environmental Monitoring Program Exposure Pathway Sampling or Type and Frequency and/or Sample Sample or Monitorinq Location Collection of Analysis Frequency

2. Direct Radiation c. Other (Cont'd)

Indicators One at each of the airborne location given in part 1.a and 1.b.

d. Controls One at airborne control location given in part 1.c.

3. Waterborne

a. Ground/Well a. Indicators 92 days Gamma isotopic(3) and tritium analysis on each Q-35, McMillan Well, IL 1.5 mi S (2.4 km) sample.

Q-36, Cordova Well, IL 3.3 mi SSW (5.3 km)

b. Drinkinq Water a. Indicator Grab samples once Gross beta and gamma There are no drinking water pathways within 5.0 mi per 7 days. isotopic analyses(3) on downstream of Station. 31-day composite; tritium analysis on 92-day composite.

1-131(4) on 14-day composite when calculated dose > 1 mrem/year. Quad Cities ODCM Part II

CY-QC-170-301 Revision 11 Page 303 of 307 January 2013 Table 6-1 (Page 5 of 7) Radiological Environmental Monitoring Program Exposure Pathway Sampling or Type and Frequency and/or Sample Sample or Monitoring Location Collection of Analysis Frequency

3. Waterborne (Con't)

c. Surface Water a. Indicator Grab samples once Gross beta and gamma per 7 days. isotopic analyses(3) on Q-33 Cordova, IL 3.1 mi SSW (5.0 km) 31-day composite; tritium analysis on 92-day

b. Control composite.

Q-34 Camanche, IA 4.4 NNE (7.1 km)

d. Sediments a. Indicators 184 days Gamma isotopic analysis(3)

Q-39 Cordova, IL Downstream on Mississippi on each sample. River 0.8 mi SSW (1.3 km)

b. Control Q-40 North of Albany, IL Upstream on Mississippi River 8.9 mi NE (14.3 km)

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CY-QC-1 70-301 Revision 11 Page 304 of 307 January 2013 Table 6-1 (Page 6 of 7) Radiological Environmental Monitoring Program Exposure Pathway Sampling or Type and Frequency and/or Sample Sample or Monitoring Location Collection Frequency of Analysis

4. Ingestion

a. Milk a. Indicators Once per 14 days when Gamma isotopic(3) and animals are on pasture 1-131(9) analysis on each Q-26 Bill Stanley Dairy, IL 3.5 mi ESE (4.8 km) (May through October), sample.

31 days at other times There are no other participating dairies within (November through 5.0 miles. April).

b. Controls There are no participating control dairies within 9.3 to 18.6 miles.

b. Fish a. Indicator 184 days Gamma isotopic analysis(3) on edible Q-24 Pool #14 of Mississippi River, 0.5 mi SW portions of each sample.

(0.8 km)

b. Control Q-29 Mississippi River-Upstream 1.0 mi N (1.6 km)

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CY-QC-170-301 Revision 11 Page 305 of 307 January 2013 Table 6-1 (Page 7 of 7) Radiological Environmental Monitoring Program Exposure Pathway Sampling or Type and Frequency and/or Sample Sample or Monitoring Location Collection Frequency of Analysis

4. Inqestion (Cont'd)

a. Indicators 12 months Gamma isotopic(3)

c. Food Products analysis on each sample.

Two sample locations from each of the four major quadrants within 5.0 mi. Sample locations for food products may vary based on availability and therefore are not required to be identified here but shall be taken.

b. Controls Two samples grown within 9.3 to 18.6 mi.

1 Deleted. 2 Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in air particulate samples is greater than 10 times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples. 3 Gamma isotopic analysis means the identification and quantification of gamma emitting radionuclides that may be attributable to the effluents from the station. 4 1-131 analysis means the analytical separation and counting procedure are specific for this radionuclide. Quad Cities ODCM Part II

CY-QC-1 70-301 Revision 11 Page 306 of 307 January 2013 Figure 6-1 REMP Sample Locations Mile Radius I Z iM i" M, WNW West 2 mi wsw RE~ YP NN Quad Cities ODCM Part II

CY-QC-170-301 Revision 11 Page 307 of 307 January 2013 Figure 6-2 REMP Sample Locations - 9.3-Mile Radius Quad Cities ODCM Part II}}