Enclosure 2, Offsite Dose Calculation Manual (ODCM ... · The manual also details the methodology...

ENCLOSURE 2

Offsite Dose Calculation Manual (ODCM)Revision 17

Issued August 2005

* I

123 pages follow

ODCM .

OFFSITE DOSE CALCULATIONMANUAL

DOCUMENT TYPE: Controlled Reference

CLASSIFICATION: N/A

REVISION: 17

EFFECTIVE DATE: August 29, 2005

REVIEVER: Plant Operation's Review Committee

APPROVAL AUTHORITY: Plant Manager

PROCEDURE OWNER (title): Group Head

OWNER GROUP: Chemistry

Verified Current Copy:

List pages used for Partial Performance

Signature Date Time

Controlling Work Document Numbers

-

POINT BEACH NUCLEAR PLANT ODCMOFFSITE DOSE CALCULATION MANUAL Revision 17

August 29, 2005OFFSITE DOSE CALCULATION MANUAL

TABLE OF CONTENTS

SECTION TITLE PAGE

1.0 OFFSITE DOSE CALCULATION MANUAL ADMINISTRATION ................. ....... 15

1.1 Purpose ....................................................... 151.2 General Responsibilities ...................................................... 161.3 Manual Revisions ...................................................... 181.4 Audits ....................................................... 19

2.0 RADIATION MONITORING SYSTEM AND RELEASE ACCOUNTING ............. 19

3.0 METHODOLOGY FOR DETERMINING ALARM SET POINTS ............................ 28

3.1 Introduction ....................................................... 283.2 Objective ...................................................... 283.3 Alert Set Point Guidelines ...................................................... 293.4 Alarm or Trip Set Point Guidelines ...................................................... 293.5 Monitor Calibration and Calibration Constant Determination ...................................... 303.6 Determination of the Effective Maximum Effluent Concentration (EMEC)

for Liquid Releases ...................................................... 333.7 Determination of Liquid Effluent Monitor Alarm Set Point ......................................... 383.8 Determination of EMEC for Atmospheric Releases... ...... 453.9 Determination of Gaseous Effluent Monitor Alarm Set points ............................... I...... 473.10 Determination of Maximum Release Rates .52

4.0 DEMONSTRATING COMPLIANCE WITH 10 CFR 50, APPENDIX I .61

4.1 Introduction .614.2 ...........Dose Limits.624.3 Release Limits .644.4 EPA Regulations .66

5.0 CALCULATION AND COMPARISON OF EFFLUENT RELEASESTO RELEASE LIMITS ...................................................... 67

5.1 Appendix I Dose Calculations ...................................................... 685.1.1 Liquid Release Mode ...................................................... 685.1.2 Atmospheric Release Mode: Radioiodine, Tritium, and Particulates ............. 1095.1.3 Atmospheric Release Mode: Noble Gases ...................................................... 149

6.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM .................... 152

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TABLE OF CONTENTS

SECTION TITLE PAGE

7.0 RADIOLOGICAL EFFLUENT CONTROLS PROGRAM .152

8.0 RADIOLOGICAL IMPACT EVALUATION OF SEWAGE TREATMENTSLUDGE DISPOSAL .152

8.1 Basis, Commitments, and Actions .1538.1.1 Basis .1538.1.2 Basis for NRC Commitment Modification .1548.1.3 Modification .1558.1.4 Exposure Evaluations .156

8.2 Procedure ........................................................ 158

8.3 Administrative Requirements .. 1618.3.1 Complete records of each contaminated disposal shall be kept as follows: .161

APPENDIX A, DERIVATION OF LIQUID RELEASE PATHWAYEFFECTIVE MAXIMUM EFFLUENT CONCENTRATION .167

A. 1.0 Derivation of Liquid Release Effective Maximum Effluent Concentration ................ 167A.1.1 Source Term .................................................................. 167A.1.2 Effective Maximum Effluent Concentration .................................................... 167

APPENDIX B DERIVATION OF ATMOSPHERIC RELEASE MODEEFFECTIVE MAXIMUM EFFLUENT CONCENTRATION ................................ 178

B.1.0 Derivation of Atmospheric Release Effective Maximum Effluent Concentration ...... 178B1.1 SourceTerm ............................................................. 178B1.2 Effective Maximum Effluent Concentration .................................................... 178

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TABLE OF CONTENTS

SECTION TITLE PAGE

APPENDIX C CALCULATION OF TOTAL DOSE FACTORS USINGREGULATORY GUIDE 1.109, REV. 1 .. ....................................................... 189

C.1.0 Calculation of Total Dose Factors Using Regulatory Guide 1.109 Methodology ....... 189C.1.1 Liquid Release Dose Factors .......................................................... 189

C1.1.1 Aquatic Foods ............................................ 190C1.1.2 Irrigated Foods (Meat From Watered Cattle) ................................. 197C1.1.3 Irrigated Foods (Milk From Watered Cattle) ................................. 203C1.1.4 Potable Water ............................................ 209C1.1.5 Shoreline Deposits ............................................ 214

C1.2 Atmospheric Release Dose Factors: Non-Gaseous . .222C1.2.1 Inhalation of Nuclides In Air .......................... .................. 223C1.2.2 Annual Organ Dose From External Irradiation From Nuclides

Deposited On the Ground ............................................ 226C1.2.3 Annual Organ Dose From Atmospherically Released

Nuclides In Milk .231C1.2.4 Annual Organ Dose From Atmospherically Released

Nuclides In Meat .238C1.2.5 Annual Organ Dose From Atmospherically Released

Nuclides In Produce ..................................... 245C1.2.6 Annual Organ Dose From Atmospherically Released

Nuclides In Leafy Vegetables .............. ....................... 251C1.2.7 Doses from Airborne Tritium other than Inhalation ...................... 256C1.2.8 Annual Organ Dose from Atmospherically Released

Tritium in Produce .259C1.2.9 Annual Organ Dose from Atmospherically Released

Tritium in Milk .261C1.2.10 Annual Organ Dose from Atmospherically Released

Tritium in Meat .265

C1.3 Atmospheric Release Dose Factors: Noble Gases .269C1.3.1 Annual Gamma and Beta Air Dose From All Noble

Gas Releases .269C1.3.2 Annual Skin Dose From All Noble Gas Releases .275C1.3.3 Annual Total Body Dose From All Noble Gas Releases ............... 279

IPage 4 of 123 REFERENCE USE

POINT BEACH NUCLEAR PLANTOFFSITE DOSE CALCULATION MANUAL

OFFSITE DOSE CALCULATION MANUAL

ODCM :Revision 17August 29, 2005

TABLE OF CONTENTS

SECTION TITLE PAGI

APPENDIX D DERIVATION OF DILUTION FACTORS USINGREGULATORY GUIDE 1.113 ............................. ................................... 283

D1.0 Liquid Effluent Dilution Factor Calculations ............................................................... 283D1.1 Methodology ................................................................ 283D1.2 Dilution Factor Twelve Miles Downstream: Two Rivers Water Intake .......... 290

E

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OFFS1TE DOSE CALCULATION MANUAL

ODCMRevision 17August 29, 2005

-

LIST OF TABLES AND FIGURES

SECTION TITLE PAGE

SECTION 2.0

TABLE 2-1TABLE 2-2FIGURE 2-2

RADIOACTIVE LIQUID WASTE EFFLUENT MONITORS .................... 21RADIOACTIVE GASEOUS WASTE EFFLUENT MONITORS ............... 23RADIOACTIVE GASEOUS WASTE EFFLUENT MONITORS ............... 27

SECTION 3.0

TABLE 3.7-1

TABLE 3.7-2

TABLE 3.9-1

TABLE 3.9-2

Table 3.10-1Table 3.10-2Table 3.10-3Table 3.10-4

Table 3.10-5Table 3.10-6

SUMMARY OF LIQUID DILUTION AND EFFLUENTPATHWAY FLOW RATES .................................................. 41LIQUID PATHWAY MONiTOR CALCULATED DEFAULTSET POINTS .................................................. 44SUMMARY OF GASEOUS EFFLUENT PATHWAY DISCHARGEDEFAULT .................................................. 48ATMOSPHERIC PATHWAY MONITOR DEFAULTRMS SET POINTS .................................................. 49mrem from all radionuclides (1985 - 1991 average) ...................................... 54mrem from I-131 and I-133 (2.42E-03 Ci) .................................................. 55mrem from H-3 (116.3 Ci) .................................................. 55mrem from all radionuclides except H-3and radioiodines (2.15E-03 Ci) .................................................. 56mrem from Cs-134 and Cs-137 (1.84E-03 Ci) ................................................ 57mrem from Co-57, Co-58, and Co-60 (1.93E-04 Ci) ..................................... 57

SECTION 5.0

TABLE 5.1-1TABLE 5.1-2TABLE 5.1-3

LIQUID EFFLUENT DOSE FACTOR .............................. 72AIRBORNE EFFLUENT DOSE FACTOR .............................. 112ACTIVITY TO DOSE CONVERSION FACTORS FOR NOBLE GASES 151

APPENDIX A

TABLE A-iTABLE A-2

CURIES RELEASED IN LIQUIDS ................................. 171FRACTIONAL MEC IN LIQUID EFFLUENT ................................. 174

APPENDIX B

TABLE B-1TABLE B-2

CURIES IN ATMOSPHERIC EFFLUENT ......................................... 181FRACTIONAL MEC FOR ATMOSPHERIC EFFLUENT ......................... 185

APPENDIX D

TABLE D-1

FIGURE D-1

SURFACE DILUTION FACTORS LIQUID EFFLUENTSIN A LARGE LAKE ......................................... 285DILUTION FACTOR AT SURFACE ......................................... 288

,Page 6 of 123 REFERENCE USE



1.0 OFFSITE DOSE CALCULATION MANUAL ADMINISTRATION

1.1 Purpose

The PBNP Offsite Dose Calculation Manual contains the current methodology andparameters for the calculation of offsite doses due to radioactive gaseous and liquideffluents. This manual describes a methodology for demonstrating compliance with10 CFR 50, Appendix I dose limits. Compliance with Appendix I is demonstrated byperiodic calculation of offsite doses based on actual plant releases and comparison toAppendix I dose limits.

The manual also details the methodology for the determination of gaseous and liquideffluent monitor alarm set points. The PBNP Radiation Monitoring System (RMS)effluent monitor alarm set points are established to ensure that controlled releases ofliquid and gaseous radioactive effluents are maintained as low as is reasonablyachievable. The setpoints also are established to ensure that concentrations of radioactivematerial released in effluents to the atmosphere do not exceed the values of Table 2,Column 1, of Appendix B to 10 CFR 20.1001-20.2402 at or beyond the site boundary andto ensure that the concentrations of radioactive materials released in liquid effluents tothe unrestricted area conform to (do not exceed) 10 times the concentration values inTable 2, Column 2 of Appendix B to 10 CFR 20.1001-20.2402.

The manual also details the methodology for evaluating the radiological impact ofsewage treatment sludge disposal. This methodology addresses the commitments madeto the United States Nuclear Regulatory Commission in our application datedOctober 8, 1987 (NRC-87-104) and accepted by the USNRC in a letter datedJanuary 13, 1988. This application was submitted in accordance with the provisions of10 CFR 20.302(a). Dose limits are established in the application to ensure the health andsafety of the maximally exposed member of the general public and the inadvertentintruder. 10 CFR 50, Appendix I dose limits do not apply to sewage treatment sludgedisposal.

1.2 General Responsibilities

The primary responsibility for the implementation of the PBNP offsite dose calculationprogram and for any actions required by the program resides with Chemistry. Chemistrywill provide the technical, regulatory, licensing, and administrative support necessary tofulfill the requirements of this manual. The calculation of offsite doses and analysis ofdata are Chemistry responsibilities.

The Manager, PBNP is responsible for assuring that Radiation Monitoring System alarmset points are established and maintained in accordance with the methodologies outlinedin this manual. The Manager, PBNP is also responsible for assuring the performance ofperiodic release summaries for the purpose of demonstrating compliance with PBNPeffluent release limits.


POINT BEACH NUCLEAR PLANT ODCMOFFS1TE DOSE CALCULATION MANUAL Revision 17


1.3 Manual Revisions

Per TS 5.5.1.C, licensee initiated changes to the Offsite Dose Calculation Manual(ODCM) shall be documented and records of reviews performed shall be retained. Thisdocumentation shall contain sufficient information to support the changes(s) togetherwith the appropriate analyses or evaluations justifying the changes(s), and adetermination that the change(s) maintain the levels of radioactive effluent controlrequired 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 setpointcalculations. These changes shall become effective after receiving concurrence from thePlant Operations Review Committee (PORC) and approval of the Plant Manager, andshall be submitted to the NRC in the form of a complete, legible copy of the entireODCM as a part of or concurrent with the Annual Monitoring Report for the period of thereport in which any change in the ODCM was made. Each change shall be identified bymarkings in the affected pages, clearly indicating the area of the page that was changed,and shall indicate the date (i.e. month and year) the change was implemented.

1.4 Audits

Audits of the activities encompassed by the ODCM, the Radiological Effluent ControlProgram, and the Radiological Environmental Monitoring Program and its implementingprocedures shall be scheduled, performed, and reported in accordance with NMC-1,Quality Assurance Topical Report.

2.0 RADIATION MONITORING SYSTEM AND RELEASE ACCOUNTING

A computerized Radiation Monitoring System (RMS) is installed at Point Beach NuclearPlant (PBNP). The RMS includes area, process, and effluent monitors. A description of thosemonitors used for liquid and gaseous effluents is presented in Tables 2-1 and 2-2. The liquid andgaseous waste processing flow paths, equipment, and monitoring systems are depicted inFigures 2-1 and 2-2. Calibration of the RMS detectors is accomplished in accordance withprocedures contained in the PBNP Health Physics Calibration Manual. The set pointmethodology is described in Section 3 of this manual.

The RMS is designed to detect and measure liquid and gaseous releases from the plant effluentpathways. The RMS will initiate isolation and control functions on certain effluent streamsidentified in Tables 2-1 and 2-2. Complete monitoring and accounting of nuclides released inliquid and gaseous effluents is accomplished with the RMS together with the characterization ofnuclide distributions by laboratory analysis of grab samples. Sampling frequencies and analysisrequirements are described in Tables 6-1 and 6-2 of the Radiological Effluent Control Manual.The various aspects of grab sampling and release accountability are described in the PBNPRelease Accountability Manual.





-------

TABLE 2-1RADIOACTIVE LIQUID WASTE EFFLUENT MONITORS

1 (2) RE-216 Containment Fan Coolers Liquid None ScintillationMonitors

RE-218 Waste Disposal System Liquid Monitor Shuts waste liquid overboard Scintillation1 (2) RE-219 Steam Generator Blowdown Liquid Shuts steam generator blowdown isolation valves, Scintillation

Monitors blowdown tank outlet valves and steam generatorsample valves

RE-220 Spent Fuel Pool Liquid Monitor None ScintillationRE-223 Waste Distillate Overboard Liquid Shuts waste distillate overboard isolation valve Scintillation

Monitor1 (2) RE-229 Service Water Discharge Monitors None ScintillationRE-230 Waste Water Effluent Monitor None Scintillation1 (2) RE-222 Steam Generator Blowdown Tank Shuts steam generator blowdown isolation valves GM Tube[ Outlet Monitor and blowdown tank outlet valves _





TABLE 2-2RADIOACTIVE GASEOUS WASTE EFFLUENT MONITORS

C arNl NUMBER `NME< CONTROL FUNTO. D Acto TYP1 (2) RE-212 Containment Noble Gas Monitor Actuates containment ventilation isolation ScintillationRE-214 Auxiliary Building Exhaust Ventilation Shuts gas release valve and shifts auxiliary Scintillation

Noble Gas Monitor building exhaust through carbon filters1 (2) RE-215 Condenser Air Ejector Noble Gas None Scintillation

MonitorsRE-225 Combined Air Ejector Low-Range None Scintillation

Noble Gas MonitorRE-221 Drumming Area Vent Noble Gas None Scintillation

MonitorRE-224 Gas Stripper Building Exhaust Noble None Scintillation

Gas Monitor1 (2) RE-305 Unit 1 and 2 Purge Exhaust Noble Gas Containment ventilation isolation Scintillation

Monitors (Channel 5 on SPING UnitsNo. 21 and No. 22)

RE-315 Auxiliary Building Exhaust Ventilation None ScintillationNoble Gas Monitor (Channel 5 onSPING Unit No. 23) __

RE-325 Drumming Area Ventilation Noble Gas None ScintillationMonitor (Channel 5 on SPING Unit No.24)





FIGURE 2-1RADIOACTIVE LIQUID WASTE EFFLUENT MONITORS

Sp" Fuw Poo so%4 Ww p4a

ll 2 OCwhhu. Fun Coo* ABU"

: U2 TuVm WSW Frt a beP

U*2T~.tki*SyRO.CFekW0Ihk1i &2 I Sc.y Idsifta *. Tu

Nu.~ ._....

Raftcim Uquld WasteEaut Monitor

Page II of 123 REFERENCE USE




FIGURE 2-2RADIOACTIVE GASEOUS WASTE EFFLUENT MONITORS

Units I & 2 Tuibirne Ventilation ..- - Turbine BulklinG -1PM= I Root Exhausten. I

To Atmoe*hereChamistry Laboratorv (Variablel

------------.' m� xi�oaIF40O

F-21 MService BRulino VernilationxTnl- i - -. -.

A kF-29

A-11-inE D.,iiii,- Vriintin-1-17 -.-

Auxiliary BuiMing Ventilation (Low Radiation Areas) F-25

(~E)-Aux~lalBuilding

Vent

306 Unit IContairnmenT urge Vent

SPING2l

UnitI& 2 Steam Generator Blowdown Tank Vert Condensers I D

unn I a 2 Liss Ecay rIanx Emuenr

Unit 1 Air Ejector Effluent

I |inent Storagne|I . i j II

F-30 u

Deca-rd~-- y Duct TUUnit 2 Air Ejector Effluent

tnit I Volume ControlTnk

nit 2 Volume Controlank

Unit 1 & 2 Hydogen and Noble Gases From Letdowi GTanks

Unit I Containment Continuous Vent I P16 -IRE ' .............~~*T

V I _ FMI --Unit I Containment Purae

I -11FAiA1_1G 1

F -t~ttB

_ -. Unit 2

Purge Vent

SPN | iim22Unit 2 Containment Continuous Vent 2RE- ........................:

212

2F-11BUnit1& 2 Gas Skippger Buldina Ventilation ( I I

_

(E22 Onanmmng :Are heVent0

| [SPINS 24Unit 1 & 2 Spent Fuel Pool Surface Exhaust F-25

Unit 1 & 2 Drumming and Truck Access Area

Roughing HEPA CharcoalFiter Fiter Fiiter

0 - ...................

NormfalRoute

OpRoute




3.0 METHODOLOGY FOR DETERMINING ALARM SET POINTS

3.1 Introduction

The selection and maintenance of alert and alarm set points for each effluent monitor ofthe PBNP radiation monitoring system will be accomplished within the guidelines of thissection. The computerized PBNP radiation monitoring system permits each effluentradiation monitor to be programmed to alarm at two distinct set-points. The alert setpoint, typically twice the steady-state reading, is intended to delineate a changing plantcondition which may warrant corrective action. The high alarm or trip set point eitherwill actuate a control function as applicable or will require corrective action to beinitiated.

3.2 Objective

The effluent monitor set points are established to ensure that controlled releases of liquidand gaseous radioactive effluents are maintained as low as is reasonably achievable, toensure releases result in concentrations to unrestricted areas within specified limits and toensure that the dose limits of 10 CFR 50, Appendix I are not exceeded.

3.3 Alert Set Point Guidelines

The alert set point of each effluent monitor generally will be set to alarm at two times theestablished steady-state reading. The alert set point is normally set at concentrations wellbelow the alarm set point value and is never to be set in excess of the alarm set point. Inthe course of plant operations, certain situations may require a deviation from the twotimes steady-state guideline. The intent of the alert set point is to warn of changing plantconditions which may warrant an evaluation of the cause of the increased radiation. Ifthe increased reading is actually due to an increased radiation inventory within the systembeing monitored, as opposed to an increased background radiation field in the vicinity ofthe detector, an evaluation should be made to determine the impact of the release. Thealert set point may be adjusted with the approval of the Duty Shift Superintendent. Alertset point adjustments are to be made in accordance with the PBNP RMS Alarm Set Pointand Response Book.

3.4 Alarm or Trip Set Point Guidelines

Pursuant to regulatory and TS requirements as stated in Section 5 of the RadiologicalEffluent Control Manual, the alarm or trip set point for effluent monitors shall beestablished to annunciate at radiation levels which would result in an unrestricted areaconcentration equal to or less than the applicable maximum effluent concentration (MEC)for a single radionuclide. However, for a mixture of radionuclides, the set point shall beestablished so that the summation of fractions, as defined in Appendix B of 10 CFR 20(see Section 3.6), is less than or equal to one (1). If the calculated setpoint is above thesaturation level of the monitor, a setpoint value below the saturation level (70% or lower)may be used. The appropriate detailed response to an effluent alarm is described in thePBNP RMS Alarm Set Point and Response Book





3.5 Monitor Calibration and Calibration Constant Determination

Calibration of the RMS effluent detectors is accomplished in accordance with procedurescontained in the PBNP Health Physics Calibration Manual. Noble gas effluent monitorsapply the calibration constant to standardize all gaseous releases to the 1985-1991average isotopic noble gas distribution. The calibration constants are based on thecalculated monitor response to the beta energy distribution in the 1985-1991 averageisotopic noble gas distribution.

Noble gas effluent monitor calibration constants are derived from the following formulae:

Cal. Constant =i

Sensitivityand

Sensitivity = Monitor ResponseZ (microCi/ccj)

where:

Monitor response

1(gCi/cci)

= the calculated counts per minute registered by monitorexposed to the 1985-1991 average noble gas isotopicdistribution

= total concentration of isotopes in the 1985-1991 averagenoble gas isotopic distribution

The liquid effluent monitors apply the derived calibration constant to standardize allliquid releases to the total concentration in the release path. The calibration constants arebased on the monitor response to the 1985-1991 average liquid isotopic distribution.Each liquid monitor channel displays the effluent concentration in terms of a total releaseconcentration.

Liquid effluent monitor calibration constants are derived from the following formulae:

Cal. Constant =Sensitivity

and

Sensitivity =MonitorRe sponse

2xPoIcc, )


POINT BEACH NUCLEAR PLANT ODCMOFFSIm E DOSE CALCULATION MANUAL Revision 17


where:

Monitor Response = the counts per minute registered by monitor exposed tocalibration source

I(ACi/cci) = total concentration on radionuclides in the 1985-1991average liquid effluent isotopic distribution

The QAD computer program may be utilized to predict or determine monitor calibrationconstants. Application of the QAD program may be appropriate for determining monitorresponse for accident source terms or other instances when the use of a calibration sourceis impracticable. The methodology for determination of calibration constants using theQAD program is maintained by Radiation Protection.

3.6 Determination of the Effective Maximum Effluent Concentration (EMEC) for LiquidReleases

Pursuant to PBNP TS, the concentration of radioactive materials in liquid effluent maynot exceed 10 times the values of Column 2, Table 2, of Appendix B to10 CFR 20.1001-20.2402. However, as a conservative measure, the followingdetermination of the EMEC and the subsequent setpoint determination for liquid effluent(Section 3.7) do not employ the augmented concentration values.

In order to fulfill the requirements of 10 CFR 20, the RMS set point must be a valuewhich will alarm when a liquid effluent would contain enough radionuclides to cause theeffluent concentration limit of 10 CFR 20, Appendix B, Table 2, Column 2 for a singleradionuclide to be exceeded, or for a mixture of radionuclides, the summation offractions (SOF), as defined in Appendix B, to exceed one (1). Dividing the averageisotopic concentrations for the years 1985-1991 by the SOF scales the total of individualconcentrations up to the value where the SOF equals one. This total concentration iscalled the effective maximum effluent concentration (EMEC) and its calculation isdescribed below. (For a complete discussion of the EMEC derivation, see Appendix A.)

The SOF is calculated using the formula found in the revised 10 CFR 20, Appendix B,Note 4:

SOF = v C1/MEC1

where:

Ci = concentration of radionuclide "i" (giCi/ml) in effluent (annualdischarge/total volume of discharge)

MECQ = maximum effluent concentration for unrestricted areas fromAppendix B, Table 2, Column 2 of the revised 10 CFR 20.


POINT BEACH NUCLEAR PLANT ODCM -OFFSITE DOSE CALCULATION MANUAL Revision 17


The SOF for radionuclides in liquid effluent for the years 1985 through 1991 wereaveraged and applied to the average of the isotopic concentrations for the same years.Na-24 and H-3 were not used in the calculations (see Appendix A for details).

Next, the "effective MEC" or EMEC is calculated using the formula:

EMEC = Ci / £ (Ci/MECi) or lCi * 1/SOF

where the variables are the same as defined above.

The average EMEC, based on 1985-1991 data is 4.29E-06 glCi/cc. This is the maximumnon H-3 radionuclide mixture concentration that could be released in liquid effluentwithout the SOF exceeding one (1).

However, the 10 CFR 20, Appendix B criterion is that the SOF for all radionuclides,including H-3 which cannot be measured by the liquid effluent NaI RMS monitors, beless than or equal to one (1). Therefore, the above equation modified by a factor of 0.70(see Appendix A) to account for H-3 becomes

EMEC = 0.70 i / 7; (Ci/MECQ) or Wi * 0.70/SOF.

The EMEC becomes

EMEC = 0.70 * 4.29E-06 = 3.OOE-06 glCi/cc.

Only three radionuclides identified in PBNP liquid effluent have a lower MEC(10 CFR 20, Appendix B, Table 2). They are I-131 (1E-06), Cs-134 (9E-07), and Cs-137(lE-06).

Note that the use of the 0.7 modifying factor sets the SOF for non-tritium radionuclides to0.7 and allows an SOF of 0.3 for H-3. A SOF of 0.3 limits the discharge concentration ofH-3 to 0.3 MEC or 3E-04 gCi/cc. The factor of 0.3 may be changed as needed forreleases for which the isotopic mixture and concentrations are known as long as the totalSOF<1.




3.7 Determination of Liquid Effluent Monitor Alarm Set Point

The alarm set point for each liquid monitor is based upon the 1985-1991 averageradionuclide concentration in the effluent discharged to the unrestricted area. Theradionuclide concentration in the release is calculated assuming a minimum circulatingwater flow rate of 206,000 gpm and the maximum flow rate of the individual liquideffluent waste stream. The isotopic distribution of the waste stream is obtained from thehistorical PBNP release data for the seven years mentioned above. Set points aredetermined such that the sum of all radionuclides in the mixture, when released into thecirculating water system, will be maintained at or below the unrestricted area EMEC.

Set points are calculated using the formula

SP EMEC * Circ water flow rate (gpm)Waste Discharge Flow Rate (gpm)

where

SP = RMS alarm set point in gCi/cc

EMEC = effective maximum effluent concentration

Circ water flow rate = total flow from Unit 1 + Unit 2

Waste discharge flow rate = flow rate for effluent line on which themonitor is located

Maximum waste discharge flow rates and monitors associated with each liquid effluentpathway are described in Table 3.7-1.

Default alarm set points normally are established based upon the maximum wastedischarge flow rate and the minimum circulation water flow rate. The liquid releasemonitor default set points are listed in Table 3.7-2. Alarm set points may be adjusted forbatch releases, when actual flow rates are known. Alarm set point adjustments which arehigher than default values, are to be made in accordance with the provisions andmethodologies of this section and requires approval of the PORC . Lower alarm set pointvalues maybe used without PORC approval if the default values lie outside the upperrange of the monitor or if compliance with applicable limits will not be compromised.





TABLE 3.7-1SUMMARY OF LIQUID DILUTION AND EFFLUENT PATHWAY FLOW RATES

. A: h WAY I (GPM RAE PT AlOIORECIRCULATION WATER

1 pump, either unit 206,000 None2 pumps, either unit 350,000

1 pump, each unit 392,0001 pump, one unit & 530,0002 pumps, other unit2 pumps, each unit 680,000

SERVICE WATER RETURN 1 (2) RE-229(normal cooldown per pump

2 pumps @ 7500 gpm 15,0003 pumps @ 6300 gpm 18,900 l

4 pumps @ 5100 gpm 20,4005 pumps @ 4300 gpm 21,5006 pumps @ 3700 gpm 22,200

STEAM GENERATOR 1 (2) RE-219 & 1 (2) RE-222BLOWDOWN

Max flow 200WASTE WATER EFFLUENT RE-230

Max Flow Rate 600(both filter skids running in

parallel)


POINT BEACH NUCLEAR PLANTOFFS1TE DOSE CALCULATION MANUAL



TABLE 3.7-1, contSUMMARY OF LIQUID DILUTION AND EFFLUENT PATHWAY FLOW RATES

ALIQUID EFLU ENT' SCHARO. FLOW RT PATHWAY MONITOR 4

SPENT FUEL POOL RE-220Max Flow Rate 700

WASTE DISTILLATE & RE-218 & RE-223CONDENSATE TANKDISCHARGE

Max Flow Rate 100CONTAINMENT FAN 1 (2) RE-216COOLER RETURN

Max Flow Rate per 4000Containment


POINT BEACH NUCLEAR PLANTOFFSiTE DOSE CALCULATION MANUAL

OFFSIT`E DOSE CALCULATION MANUAL


TABLE 3.7-2LIQUID PATHWAY MONITOR

CALCULATED DEFAULT SET POINTS

MONITOR

1 (2) RE-229

1 (2) RE-219 &1 (2) RE-222

RE-230

RE-220

RE-218 &RE-223

FLOWRATE (gpm)

6 @ 37001

200

600

700

100

SET POINT (gCi/cc)

2.78E-05

3.09E-03

1.03E-03

8.83E-04

6.18E-03

1 (2) RE-216 4000 1.55E-04

I six service water pumps at normal cooldown flow rates

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August 29, 2005OFFS1TE DOSE CALCULATION MANUAL

3.8 Determination of EMEC for Atmospheric Releases

The maximum concentration of the mixture of radionuclides that is allowable at the siteboundary is called the effective maximum effluent concentration (EMEC). The EMECfor an effluent mixture is defined by the equation

EMEC = IQ / X(Cj / MECQ)

where

Ci = concentration of radionuclide "i"

MECi = maximum effluent concentration for radionuclide i from 10 CFR 20,Appendix B, Table 2

£ (Ci I MECQ) = summation of fractions (SOF), as discussed in Section 3.6, applied toatmospheric releases

The EMEC is calculated from the reference radionuclide mixture. This mixture isobtained from the 1985 - 1991 average annual atmospheric releases and thecorresponding concentrations determined from the highest annual average X1Q. (Detailsof the EMEC calculation are found in Appendix B.)

The calculated EMEC, corrected for H-3, of 1.92E-08 ,uCi/cc was obtained to be used inthe set point calculations.

I'




ODCM - - -Revision 17August 29, 2005

3.9 Determination of Gaseous Effluent Monitor Alarm Set points

The alarm set point for each monitor is based upon maintaining the concentration of thereference radionuclide mixture at or below the EMEC. The set point is calculated usingthe formula

whereSP

SP

2.12E+03

EMEC

= 2.12E+03 * EMEC / (xIQ * FR)

= set point in pCi/cc

= conversion factor for ft3/min to m3 /sec

= 1.92E-08 pCi/cc

X/Q = highest site boundary annual average 1.5E-06 sec/M3

FR = the flow rate in ft3/min of the effluent pathway being monitored.

Combining the above numerical values yields

SP(pLCi/cc) = 2.71E + 01 / FR

Gaseous effluent pathway discharge flow rates and monitors associated with eachpathway are summarized in Table 3.9-1.

TABLE 3.9-1SUMMARY OF GASEOUS EFFLUENT PATHWAY DISCHARGE FLOW RATES

DISCHARGE FLOW RATE MONITOR(S)GASEOUS EFFLUENT PATHWAY CFM IN EFFLUENT PATHWAY

a. Auxiliary Building Vent 66,400 RE-214 & SPING 23b. Combined Air Ejector 20 RE-225c. Unit Air Ejector 10 1 (2) RE-215d. Containment Purge Vent

1) 1 fan operating2) 2 fans operating

e. Gas Stripper Buildingf. Drumming Area Vent

12,50025,000

13,00043,100

1 (2) RE-212 &SPNGS 21 & 22

RE-224RE-221 & SPING 24

.Page 22 of 123 REFERENCE USE



Alarm set points are to be normally established based upon maximum waste discharge flow rates and thehighest annual average X/Q value at the site boundary. The alarm set points may be adjusted for releaseperiods if actual flow rates are reduced to less than maximum values or actual XIQ values are calculated.Alarm set point adjustments to higher values are to be made in accordance with the provisions andmethodologies of this section and require PORC approval. Default set point values obtained using theflow rates in Table 3.9-1 are presented in Table 3.9-2. An additional reduction factor of 1/4 has beenapplied to the four release point monitors so that the maximum allowable site boundary concentrationswill not be exceeded in the event simultaneous releases from these points occur. Lower set point valuesmay be used for any of the monitors without PORC approval if the default value is outside the upperrange of the monitor or if compliance with applicable release limits will not be compromised. The setpoint values for the SPINGs will be the same as the corresponding release point monitor; RE-214(SPING 23), 1(2)RE-212 (SPINGS 21 and 22) or RE-221 (SPING 24).

TABLE 3.9-2ATMOSPHERIC PATHWAY MONITOR

DEFAULT RMS SET POINTS

MONITOR FLOW RATE SET POINT(ft3/min) (MCi/cc)

RE-214 66,400 1.02E-04RE-225 20 1.36E+001RE-215 10 2.71E+002RE-215 10 2.71E+001RE-212 25,000' 2.73E-042RE-212 38,000& 1.78E-04

1/2RE-2123 30 2.26E-01RE-224 13,000 2.09E-03RE-221 43,000 1.58E-04

'2 fans (with 1 fan the flow rate is 12,500 cubic feet/minute)

22 fans + 13,000 cfm from the gas stripper building 3 Forced vent with nominal 30 cfm flow rate

The individual 1/2RE-212 setpoints are based on purge flow rates. During operational modes 1-4, thepurge valves are locked shut. Therefore, forced vent alarm setpoints are calculated based on the nominal30 cfm flow rate. This yields, upon applying the 1/4 reduction factor, a setpoint of 2.26E-01 pCi/cc.Because this is an order of magnitude above the monitors' saturation or fail high levels, the MSSapproved (MSSM No. 93-01) the use of a setpoint which is higher than the individual RE-212 Table 3.9-2 values and set at 570% of the monitor's fail high level. This approval applies to those monitors forwhich the calculated setpoint falls above the fail high level. The current alarm setpoint levels arerecorded in the RMS Alarm Set Point and Response Book.

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POINT BEACH NUCLEAR PLANT ODCMOFFSiTE DOSE CALCULATION MANUAL Revision 17


3.10 Determination of Maximum Release Rates

Technical specifications restrict the rate of release of radionuclides to the atmosphere tothat value, which if continued for one year, would result in the following annual doserates at or beyond the site boundary: 500 mrem/yr to the whole body and 3000 mrem/yrto the skin from noble gases; and, 1500 mrem/yr to any organ from I-131, 1-133, H-3, andparticulates with a half-life >8 days.

3.10.1 Noble gas release rate

The release rate for noble gases are calculated using the Reg. Guide 1.109dose factors and the annual average isotopic noble gas release for the years1985 - 1991 as shown in Table B-I. Following the methodology inSection 5.1.3, the calculated annual skin dose from the average 1985 - 1991isotopic mixture with a total of 4.5 1E+01 curies is 1.03E-02 mrem. Thereforethe maximum release rate is calculated from the formula

Ci/sec = total Ci * dose limit / (sec/yr * dose from total Ci).

Based on skin dose, the release rate formula

Ci/sec = 4.51E+01 Ci * 3000 mrem/yr/ (3.15E+07 sec/yr * 1.03E-02 mrem)yields a release rate of 4.17E-01 Ci/sec.

Using the same total curies with the same isotopic mixture but with the wholebody dose of 5.89E-03 mrem/yr and the whole body dose limit of500 mrem/yr, the release rate becomes 1.22E-01 Ci/sec.

Therefore the whole body dose rate is limiting and the maximum allowablePBNP noble gas release rate is 1.22E-01 Ci/sec. This rate is higher than anyPBNP noble gas release rate from 1985 - 1991 based on the highest reportedhourly average release rates of approximately 4.3E-02 Ci/sec.

1 PageaL 24 of 123 REFERENCE USE



3.10.2 Release rate for I-131, 1-133, H-3, and particulates released to the atmospherewith half-lives >8 days

During the time period of 1985 - 1991, PBNP released an annual average of116.30457 Ci to the atmosphere consisting of I-131, I-133, H-3, andparticulates whole half-life >8 days. Of this quantity, 116.30 was H-3 and4.57E-03 was I-131, I-133, and particulates whose half-life was >8 days. Thedoses from this mixture, calculated using ODCM methodology are shown inTable 3.10.1.

Table 3.10-1 mrem from all radionuclides (1985 - 1991 average)

mrem from all radionuclides (1985 - 1991 average)Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Sidn

ADULT 1.66E-02 3.68E-02 5.74E-02 5.44E-02 2.01E-02 1.42E-02 1.23E-02 3.27E-02TEEN 2.69E-02 5.25E-02 5.57E-02 4.64E-02 2.56E-02 1.72E-02 1.29E-02 3.27E-02CHILD 6.3 1E-02 8.30E-02 5.48E-02 7.70E-02 3.73E-02 2.31E-02 1.60E-02 3.27E-02INFANT 5.04E-02 6.77E-02 3.58E-02 1.04E-01 2.00E-02 9.39E-03 2.59E-03 3.27E-02

If the 1985 - 1991 average isotopic effluent mixture released to the atmosphere is brokendown into the following grouping: H-3, 1-131 and I-133, and the remainingradionuclides, the groups contribution to the various organ doses are revealed(Tables 3.10-2 - 3.10-4).

Table 3.10-2 mrem from I-131 and I-133 (2.42E-03 Ci)

mrem from 1-131 AND 1-133Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin

ADULT 9.26E-05 1.32E-04 1.1OE-04 4.31E-02 2.29E-04 0.OOE+00 3.66E-05 4.20E-05TEEN 8.52E-05 1.20E-04 9.82E-05 3.44E-02 2.06E-04 0.OOE+00 2.50E-05 4.20E-05CHILD 1.86E-04 1.88E-04 1.41E-04 6.17F-02 3.09E-04 0.OOE+00 1.79E-05 4.20E-05INFANT 2.63E-04 3.1OE-04 1.71E-04 1.01E-01 3.62E-04 0.00E+00 1.17E-05 4.20E-05

Table 3.10-3 mrem from H-3 (116.3 Ci)

mrem from H-3Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin

ADULT 0.OOE+00 1.13E-02 1.13E-02 1.13E-02 1.13E-02 1.13E-02 1.13E-02 0.OOE+00TEEN 0.00E+00 l.19E-02 l.19E-02 1.19E-02 1.19E-02 1.19E-02 1.19E-02 0.00E+00CHILD 0.00E+00 1.53E-02 1.53E-02 1.53E-02 1.53E-02 1.53E-02 1.53E-02 0.OOE+00INFANT 0.OOE+00 2.35E-03 2.35E-03 2.35E-03 2.35E-03 2.35E-03 2.35E-03 0.OOE+00

Page 25 of 123 REERENCE USE



ODCM - ..- >Revision 17August 29, 2005

Table 3.10-4 mrem from all radionuclides except H-3 and radioiodines (2.15E-03 Ci)

ADULTTEENCHILDINFANT

Bone1.65E-022.68E-026.29E-025.01E-02

Liver2.53E-024.04E-026.75E-026.51E-02

mrem from all radionuclides except H-3 and radioiodinesT. Body Thyroid Kidney Lungs GI-LLI Skin4.59E-02 2.08E-09 8.49E-03 2.84E-03 9.41E-04 3.27E-024.37E-02 2.64E-09 1.35E-02 5.25E-03 9.76E-04 3.27E-023.94E-02 4.94E-09 2.16E-02 7.81E-03 6.72E-04 3.27E-023.32E-02 1.88E-09 1.73E-02 7.04E-03 2.27E-04 3.27E-02

As evident from Tables 3.10-1 through 3.104, H-3 contributes a significant portion of thethyroid dose for all age groups for the 1985 - 1991 mixture of radionuclides released to theatmosphere. Comparison of Tables 3.10-5 and 3.10-6 to Table 3.104 reveals that the majorportion of the organ doses from radionuclides other than H-3 and radioiodines results from cobaltand cesium. Cs-134 and Cs-137 are the major dose contributors to the bone, liver, skin andkidneys whereas cobalt is the major contributor to the GI-LLI dose. Therefore, the dose resultsobtained from the 1985 - 1991 radionuclide mixture is consistent with the dose results fromcurrent effluents.

Table 3.10-5 mrem from Cs-134 and Cs-137 (1.84E-03 Ci)


Bone1.62E-022.64E-026.22E-025.01E-02

Liver2.53E-024.04E-026.74E-026.50E-02

mrem from Cs-134 and Cs-137T. Body Thyroid Kidney4.21E-02 0.OOE+00 8.48E-033.98E-02 0.OOE+00 1.35E-023.54E-02 0.OOE+00 2.16E-022.95E-02 0.OOE+00 1.73E-02

Lungs2.82E-035.22E-037.78E-037.02E-03

GI-LLI4.76E-045.52E-044.05E-041 .96E-04

Skin2.84E-022.84E-022.84E-022.84E-02

Table 3.10-6 mrem from Co-57, Co-58, and Co-60 (1.93E-04 Ci)


Bone0.OOE+000.OOE+000.OOE+000.OOE+00

Liver2.24E-052.97E-054.35E-057.75E-06

mrem from cobaltsT. Body Thyroid3.72E-03 0.OOE+003.73E-03 0.OOE+003.80E-03 0.OOE+003.69E-03 0.OOE+00

KidneyO.OOE+000.00E+000.OOE+000.OOE+00

Lungs2.32E-053.40E-052.76E-051.78E-05

GI-LLI Skin4.26E-04 4.32E-033.88E-04 4.32E-032.43E-04 4.32E-031.86E-05 4.32E-03

Based on these results, the release rates for various radionuclide mixture can be determined usingthe methodology in Section 3.10.1.

For the total radionuclide mixture, the maximum release rate is

Ci/sec =1.16E+02 Ci *1500 mrem/yr/ (1.04E-01 nmrem * 3.15E+07 sec/yr)

or 5.33E-02 Ci/sec,

Page 26 of 1234� REFERENCE USE



For radioiodines (1-131 and I-133), the maximum release rate is

Ci/sec =2.42E-03 Ci *1500 mremlyrl (1.O1E-01 mrem * 3.15E+07 sec/yr)

or 1.14E-06 Ci/sec,

For H-3, the maximum release rate is

Ci/sec =1.16E+02 Ci *1500 mremlyr/ (1.53E-02 mrem * 3.15E+07 sec/yr)

or 3.62E-01 Ci/sec,

For all radionuclides (other than H-3 and radioiodines) with a half-life > 8 days, the maximumrelease rate is

Ci/sec =2.15E-03 Ci *1500 mrem/yr/ (6.75E-02 mrem * 3.15E+07 sec/yr)

or 1.52E-06 Ci/sec,

For cesium (Cs-134, -137), the maximum release rate is


or 1.30E-06 Ci/sec,

For cobalt (Co-57, -58, -60), the maximum release rate is


or 2.16E-05 Ci/sec,

Finally, for the total of all radionuclides in the mixture except H-3, the maximum releaserate is

Ci/sec =4.57E-03 Ci *1500 mrem/yr/ (1.O1E-01 mrem * 3.15E+07 sec/yr)

or 2.15E-06 Ci/sec.

Because the limiting release rate is that of the radioiodines, a mixture of radionuclides whosehalf-lives is >8 days should be restricted to 1.14E-06 Ci/sec. However, if there is no I-131 andI-133, the cesium doses become limiting and the release rate limit may be raised to1.30E-06 Ci/sec.

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4.0 DEMONSTRATING COMPLIANCE WITH 10 CFR 50. APPENDIX I

4.1 Introduction

Maintaining effluents within the dose objectives of Appendix I is demonstrated at PBNPby periodic calculations. Compliance with Appendix I limits is demonstrated byperiodically calculating doses to the maximum exposed individual using the methodologyset forth in Regulatory Guide 1.109, Rev. 1, October 1977 and in other recognizedsources such as ICRP publications.

In order to aid in the dose calculations, the formulae in Reg Guide 1.109 were rearrangedto calculate the dose per curie released (mrem/Ci) to the environment. For each pathwaygiven in Reg Guide 1.109, a radionuclide's mrem/Ci values for the whole body and theorgans were calculated for each of the two release modes, liquid and atmospheric. All ofthe pathway doses for a radionuclide via the release mode under consideration weresummed to obtain the radionuclide's total mrem/Ci released. These values, called totaldose factors (TDFs), are listed in Tables 5.1.1 and 5.1.2. The application of TDFs aregiven in Section 5; the calculations used to obtain them, in Appendix C.

4.2 Dose Limits

To define the limits and conditions for the controlled release of radioactive materials inliquid and gaseous effluents to the environment, to ensure that these releases are as low asis reasonably achievable in conformance with 10 CFR Parts 50.34a and 50.36a, to ensurethat these releases result in concentrations of radioactive materials in liquid and gaseouseffluents released to unrestricted areas that are within the limits specified in 10 CFR 20,and to ensure that the releases of radioactive material above background to unrestrictedareas are as low as is reasonably achievable, the following design release limits asdefined in Appendix I to 10 CFR 50 apply:

A. The calculated annual total quantity of all radioactive material abovebackground that may be released from each light-water-cooled nuclear powerreactor to unrestricted areas should not result in an annual dose or dosecommitment from liquid effluents for any individual in an unrestricted areafrom all pathways of exposure in excess of 3 millirems to the total body or 10millirems to any organ.

B. The calculated annual total quantity of all radioactive material abovebackground that may be released from each light-water-cooled nuclear powerreactor to the atmosphere should not result in an annual air dose from gaseouseffluents at any location near ground level which could be occupied byindividuals in unrestricted areas in excess of 10 millirads for gamma radiationor 20 millirads for beta radiation, or that this quantity should not result in anannual external dose from gaseous effluents to any individual in unrestrictedareas in excess of 5 millirems to the total body or 15 millirems to the skin.

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C. The calculated annual total quantity of all radioactive iodine and radioactivematerial in particulate form above background that may be released from eachlight-water-cooled nuclear power reactor in effluents to the atmosphere shouldnot result in an annual dose or dose commitment from such radioactive iodineand radioactive material in particulate form for any individual in anunrestricted area from all pathways of exposure in excess of 15 millirems toany organ.

D. Pursuant to NRC interpretation as stated in PBNP TS 5.5.4.i, the doseguideline of Section 4.2.C, above, applies only to I-131, 1-133, H-3, and allparticulate material released to the atmosphere which has a half-life >8 days.Particulates with shorter half-lives are not considered because of theirnegligible dose contribution.

4.3 Release Limits

Based on the Appendix I dose limits, Point Beach, being a two (2) unit nuclear plant, mayrelease into the environment the quantities of radionuclides above background that fulfillthe criteria listed below.

A. Pursuant to Section 4.2.A, the doses from radionuclides in the unrestrictedarea in liquids shall not exceed

1. Six (6) millirem to the whole body, or

2. Twenty (20) millirem to any organ.

B. Pursuant to Section 4.2.B, the doses from gaseous radionuclides in theunrestricted area shall not exceed

1. Twenty (20) millirads to the air from gamma radiation,

2. Forty (40) millirads to the air from beta radiation,

3. Ten (10) millirem to the whole body, or

4. Thirty (30) millirem to the skin.

C. Pursuant to Section 4.2.d, the dose from radioiodine and radioactive materialin particulate form relea.sed to the atmosphere in the unrestricted area shall notexceed thirty (30) millirem to any organ.

D. Quarterly release limits are defined as % the annual limits.




4.4 EPA Regulations

Compliance with the provisions of Appendix I to 10 CFR 50 is adequate demonstrationof conformance to the standards set forth in 40 CFR 190 regarding the dose commitmentto individuals from the uranium fuel cycle. For 40 CFR 190 compliance, quarterly dosecalculations shall include exposures from effluent pathways and direct radiationcontributions from the reactor units and from any outside storage tanks.

The above calculations do not include contributions from the Kewaunee Nuclear PowerPlant (KNPP) which is some four miles north of PBNP. Under normal operations usingthe PBNP annual average X/Q and assuming that the KNPP source term is identical toeither PBNP unit, the greatest KNPP dose contribution occurs at the north sector PBNPboundary. However, the total KNPP-PBNP dose at that point is less than the dose in thehighest sector (south boundary) from PBNP alone. The KNPP contribution in this sectoradds only 1 percent to 8 percent to the total dose depending upon the release mode. Evenin the highly unlikely event that PBNP and KNPP operated for an entire year at twice theAppendix I levels, the small percentage contribution from KNPP would be insufficient toyield doses exceeding 40 CFR 190 limits.

5.0 CALCULATION AND COMPARISON OF EFFLUENT RELEASES TO RELEASE LIMITS

Technical Specification 5.5.4.e requires that an effluent release summary and dose calculationsbe performed periodically. This section describes the methodology for the calculation of dosesfor comparison to the corresponding dose limits. For Appendix I compliance, the organ andwhole body doses shall be calculated for the maximally exposed individual in each age groupusing the appropriate total dose factors in mrem/Ci released which were obtained usingRegulatory Guide 1.109 and other documented methodologies.

5.1 Appendix I Dose Calculations

5.1.1 Liquid Release Mode

The dose calculations for demonstration of compliance with the 10 CFR 50,Appendix I dose limits will be accomplished by Chemistry. Doses will becalculated for each month to track compliance with effluent and dose goals.The doses from each radionuclide will be calculated for each age group andfor each organ, including the whole body, and summed over all the identifiedradionuclides released. The total dose is compared to the corresponding liquidrelease mode Appendix I dose limit for the organ in question. Noble gasesreleased in liquids are added to the atmospherically released noble gases forAppendix I dose compliance calculations.

The doses are calculated using the following formula:

API = I Doseaomi = X (TDFaomi x Ci) < Kom mrem

-".IPage 30 of 123 REFERENCE USE



where

API = the Appendix I dose for compliance evaluation in mrem

Doseaomi = the dose to the specific age group (a) and organ (o) viarelease mode (m) from radionuclide (i)

TDFaomi = total dose factor for the specific age group (a) and organ (o)via release mode (m) from radionuclide (i) fromTable 5.1-1 in mrem/Ci

Ci = curies of radionuclide (i) released

Kom = the Appendix I dose limit for organ (o) and releasemode (m) for which the calculation is being made.

The methodology and the values used to obtain the TDFaomi values are givenin Appendix C.

It is recognized that some of the release quantities may not be available at theend of the month because the samples from these release paths are sent to avendor for analysis. Usually, the only radionuclides affected by these delaysare Sr-89 and Sr-90. Because the quantities of these two radionuclides are buta small fraction of the total release, the absence of their dose contributionsfrom the initial monthly dose calculation will not significantly affect the totaldose obtained from the remaining radionuclides. The dose for the month willbe updated upon the receipt of the vendor isotopic results and upon the receiptof any corrections to previous release quantities.

Note that all of the liquid release dose calculations assume that the dischargerate is 677,000 gpm. Whenever the average discharge rate for the month oryear differs, the final dose calculated must be multiplied by the correctionfactor CF where:

CF = 677,000 gpm / actual average discharge gpm

This correction will produce a greater change during the winter months whenthe circ water flow rates are lower.




ODCM -Revision 17August 29, 2005

i ,

Table 5.1-1

TABLE 5.1-1LIQUID EFFLUENT DOSE FACTOR

Summation of dose per curie released factor calculations over the pathways: potable water, aquatic food,shoreline deposit, irrigated foods (milk), and irrigated foods (meat).

Dose factor - liquid release pathway (mrem/Ci released)H-3

____ J Bone, L Kd ney Lungs | GI-L

Adult O.OOE+OO 4.46E-06 4.46E-06 4.46E-06 4.46E-06 4.46E-06 4.46E-06Teen X O.OOE+OO 4.04E-06 4.04E-06 4.04E-06 4.04E-06 4.04E-06 4.04E-06Child O.OOE+OO 6.67E-06 6.67E-06 6.67E-06 6.67E-06 6.67E-06 6.67E-06Infant O.OOE+OO 7.79E-06 7.79E-06 7.79E-06 7.79E-06 7.79E-06 7.79E-06

Dose factor - liquid release pathway (mrem/Ci released)F-18

i& Bo Liver Ti1 .LVBody fTrd Ki Lungs . 1-LU

;Adult - 1.15E-07 9.12E-89 1.28E-08 O.OOE+OO 5.14E-89 O.OOE+O0 3.40E-09Teen 1.21E-07 7.59E-89 1.35E-08 O.OOE+OO 4.35E-89 O.OOE+OO 1.09E-08Child 1.51E-07 1.08E-88 l.50E-08 O.OOE+OO 5.74E-89 O.OOE+OO 4.08E-08Infaht, 2.05E-12 O.OOE+OO 1.75E-13 O.OOE+OO O.OOE+OO O.OOE+OO 4.83E-13

Dose factor - liquid release pathway (mrem/Ci released)Na-22

_ B .on~e Liver 7 Body Thiyroid t J@ KEidney Lungs GLAdult i >'-, 4.71E-03 4.71E-03 4.82E-03 4.71E-03 4.71E-03 4.71E-03 4.71E-03Teen 5.48E-03 5.48E-03 6.07E-03 5.48E-03 5.48E-03 5.48E-03 5.48E-03Child 8.32E-03 8.32E-03 8.45E-03 8.32E-03 8.32E-03 8.32E-03 8.32E-03Infant 7.21E-03 7.21E-03 7.21E-03 7.21E-03 7.21E-03 7.21E-03 7.21E-03

Dose factor - liquid release pathway (mrem/Ci released)Na-24

Bo eL v rT o YU Th yro d id ne Lunj 31 LAdult-s7 1.85E-04 1.85E-04 1.85E-04 1.85E-04 1.85E-04 1.85E-04 1.85E-04,Teen < 1.98E-04 1.98E-04 1.98E-04 |.98E-04 1.98E-04 1.98E-04 1.98E-04Child 2.40E-04 2.40E-04 2.40E-04 2.40E-04 2.40E-04 2.40E-04 2.40E-04Infant 8.06E-05 8.06E-05 8.06E-05 8.06E-05 8.06E-05 8.06E-05 8.06E-05


POINT BEACH NUCLEAR PLANTOFF$1TE DOSE CALCULATION MANUAL



Table 5.1-1

Dose factor - liquid release pathway (mrern/Ci released)Sc-46

Adult 1.70E-07 3.31E-07 8.92E-06 O.OOE+OO 3.09E-07 O.OOE+OO 1.61E-03Teen - 1.52E-07 2.97E-07 4.94E-05 O.OOE+OO 2.84E-07 O.OOE+OO l.OlE-03Child 3.54E-07 4.85E-07 l.05E-05 O.OOE+OO 4.29E-07 O.OOE+OO 7.09E-04infant J ' 3.42E-07 4.94E-07 1.54E-07 O.OOE+OO 3.25E-07 O.OOE+OO 3.22E-04

Dose factor - liquid release pathway (mrem/Ci released)Mn-54

^Bone iver T.y 2Bi Kidney4 L ngsG LAdult' O.OOE+OO 3.28E-03 6.34E-04 O.OOE+OO 9.75E-04 O.OOE+OO l.OOE-02Teen- O.OOE+OO 3.22E-03 6.86E-04 O.OOE+OO 9.59E-04 O.OOE+OO 6.60E-03Child O.OOE+OO 2.60E-03 7.04E-04 O.OOE+OO 7.30E-04 O.OOE+OO 2.19E-03infant - O.OOE+OO 1.92E-04 4.34E-05 O.OOE+OO 4.25E-05 O.OOE+OO 7.04E-05

Dose factor - liquid release pathway (mrem/Ci released)Cr-51

_ _ _ _ _ M B o n L v °. B-d; T hBy o Ki eL (3kL LIAdult & O.OOE+OO O.OOE+OO 1.01E-06 5,84E-07 2.15E-07 1.30E-06 2.46E-04Tcee . O.OOE+OO O.OOE+OO 1.17E-06 5.60E-07 2.21E-07 1.44E-06 1.70E-04Child O.OOE+OO O.OOE+OO 1.19E-06 6.44E-07 1.76E-07 1.18E-06 6.15E-05Infant O.OOE+OO O.OOE+OO 1.72E-07 1.12E-07 2.45E-08 2.18E-07 5.O1E-06

Dose factor - liquid release pathway (mrern/Ci released)Mn-56

Adult O.OOE+OO 3.18E-06 5.65E-07 | O.OOE+OO 4.04E-06 JO.OOE+OO 1.02E-04Ten O.OOE+OO 3.33E-06 5.94E-07 O.OOE+OO 4.22E-06 O.OOE+OO 2.19E-04Child O.OOE+OO 3.04E-06 6.86E-07 j O.OOE+OO 3.67E-06 j O.OOE+OO 4.40E-04Ihfant O.OOE+OO 1.97E- 11 3.39E-12 7 O.OOE+00 1.69E-11 7 O.OOE+000 1.79E-09

Dose factor - liquid release pathway (mrem/Ci released) -

Fe-55 - |Bone Li ver T. B d yod yni

Adult 5.98E-04 4.13E-04 9.63E-05 O.OOE+00 O.OOE+OO 2.31E-04 2.37E-04Teen 6.11E-04 4.33E-04 1.01E-04 O.OOE+00 O.OOE+OO 2.75E-04 L1.88E-04Child'. 9.35E-04 4.96E-04 1.54E-04 O.OOE+00 O.OOE+00 2.80E-04 9.19E-05Infant | 1.55E-04 1.OOE-04 2.68E-05 O.OOE+00 O.OOE+00 4.91E-05 1.28E-05




ODCM , . .Revision 17August 29, 2005

Table 5.1-1

Dose factor - liquid release pathway (mrern/Ci released)Fe-59

___ oe'" ie'" .Bd ') ThyroidX Kine Lugs GT-LLirAdult 9.12E-04 2.14E-03 8.23E-04 O.OOE+00 O.OOEi+00- 5.99E-04 7.14E-03Te 9.22E-04 2.15E-03 8.40E-04 O.OOE+00 O.OOE+00 6.79E-04 5.09E-03Child 1.29E-03 2.09E-03 1.04E-03 O.OOE+00 O.OOE+00 6.07E-04 2.18E-03_nfant 3.34E-04 5.84E-04 2.30E-04 O.OOE+00 O.OOE+00 1.73E-04 2.79E-04

Dose factor - liquid release pathway (mrem/Ci released)Co-57

2 1(.l B<orne Liv..er J T. Body. "Thyroie 2d . idn.ey Lungws ..................... =GI-L.L IAdult ^O.OOE+00 2.02E-05 3.57E-05 O.OOE+OO O.OOE+00 O.OOE+00 5.13E-04Teen O.OOE+00 2.06E-05 4.62E-05 O.OOE+00 O.OOE-0O O.OOE+00 3.83E-04Childa < O.OOE+00 2.3 1E-05 4.93E-05 O.OOE+00 O.OOE+00 O.OOE+00 1.89E-04Infant"' ... j O.OOE+00 1.24E-05 2.02E-05 O.OOE+00 O.OOE+0 O.OOE-i+00 4.24E-05

Dose factor - liquid release pathway (mrem/Ci released)Co-58

Boe' 'Liver T. Bod 'CTyrd Kine Lug (iZ I1-L.0 0 0;l' .

Adut O.OOE+00 8.49E-05 1.93E-04 O.OOE+00 O.OOE+00 O.OOE+00 1.72E-03Teen O.OOE+00 8.30E-05 2.04E-04 O.OOE+00 O.OOE+00 O.OOE+00 1.14E-03

)Chid' O.OOE+oo 8.32E-05 2.57E-04 O.OOE+00 O.OOE+00 O.OOE+00 4.85E-04Infant O.OOE+00 3.84E-05 9.58E-05 O.OOE+00 O.OOE+00 O.OOE+00 9.57E-05

Dose factor - liquid release pathway (rnrern/Ci released)Co-60 i

;Jiv8>-ZBon Live ',T.Body Th Foi - 0 wLungs GI-L|Adult O.OOE+00 2.48E-04 6.82E-04 O.OOE+00 O.OOE+00 O.OOE+00 4.66E-03Teen ;.<. O.OOE+00 2.44E-04 1.30E-03 O.OOE+00 O.OOE+00 O.OOE+00 3.17E-03Child'| O.OOE+00 2.49E-04 8.92E-04 O.OOE+00 O.OOE+00 O.OOE+0| 1.38E-03Infantll O.OOE+00 1.17E-04 2.77E-04 O.OOE+00 O.OOE+00 O.OOE+00 2.79E-04

Dose factor - liquid release pathway (mrem/Ci released) |

Ni-63 I

I~ ~ 'Bn Z'Z-,.'r '-,'' BodyMB2Z Thy|2Z#al~lro<id' idne~y ) Lungs 'Z LGI-It_Adult 3.03E-02 2.10E-03 1.02E-03 O.OOE+00 O.OOE+00 O.OOE+00 | 4.38E-04Teen,~ g 3.13E-02 12.21E-03 1.06E-03 O.OOE+00 O.OOE+00C O.OOE+00 j 3.52E-04Chld 5.00E-02 2.67E-03 1.70E-03 O.OOE+00 O.OOE+00 I O.OOE+00 I 1.80E-04Infant l 1.27E-02 7.85E-04 4.41E-04 O.OOE+00 O.OOE+00 O.OOE+00 | 3.91E-05

I Page 34 of 123 REFERENCE USE

POINT BEACH NUCLEAR PLANTOFPSITE DOSE CALCULATION MANUAL



Table 5.1-1

Dose factor - liquid release pathway (mrem/Ci released)Ni-65

Bone \ 'Li e T. B y T hy r d K id ney Lu g s 0 -,l U

Adult 3.39E-06 4.40E-07 2.01E-07 O. O.OOE+O .OOE+00 0.OOE+OO 1.12E-05T - 3.66E-06 4.68E-07 2.13E-07 O.OOE+OO. 00OOE+OO 0.00E+00 2.54E-05Child 4.68E-06 4.41E-07 2.57E-07 -O.OOE+00 O.OOE+OO O.00E+00 5.40E-05

1Infant 1.74E-10 1.97E-11 8.95E-12 O.OOE+00 O.OOE+O0 O.OOE+00 1.50E-09

Dose factor - liquid release pathway (mrem/Ci released)Cu-64 _

B o n J L >i vB . t ';4er : fr T .B o d y T y r i K i<td n e L u nQ :Cgsr ( 3Adult" 0.002+00 4.02E-06 1.89E-06 0.OOE+OO 1.01E-05 O.OOE+OO 3.43E-04

Te O.OOE+O0 4.31E-06 2.04E-06 O.OOE+O0 1.09E-05 O.00E+OO 3.34E-04Child; O.OOE+00 4.30E-06 2.60E-06 O.OOE+OO 1.04E-05 O.OOE+OO 2.02E-04-Infant O.OOE+00 1.41E-06 6.52E-07 O.OOE+00 2.38E-06 O.OOE+00 2.89E-05

Dose factor - liquid release pathway (mrem/Ci released)Zn-65

, ; B one LiveS> r X T. Bod y~l oThyod Ki 5 d nkey Lungs.E GI-LL'Adult 1.73E-02 5.50E-02 2.49E-02 O.OOE+00 3.68E-02 O.OOE+O0 3.46E-02

eien 1.58E-02 5.50E-02 2.57E-02 O.OOE+00 3.52E-02 O.OOE+O0 2.33E-02Child 1.68E-02 4.47E-02 2.78E-02 O.OOE+00 2.82E-02 0.OOE+0O 7.85E-03

Infant 1.32E-03 4.51E-03 2.08E-03 O.OOE+OO 2.19E-03 O.OOE+00 3.81E-03

Dose factor - liquid release pathway (mrem/Ci released)Zn-69 _ _

B o n e L i v e r ,. B o dy'4 I T h r i * K i n e , L n s IAdult1 1.97E-05 O 3.76E-05 2.62E-06 O.OOE+00 | 2.44E-05 O.OOE+00 | 5.65E-06

Teen J 2.14E-05 4.08E-05 2.86E-06 O.OOE+00 2.67E-05 O.OOE+O0 7.52E-05Child 2.77E-05 4.00-E-S 3.70E-06 O.OOE+00 2.43E-05 0.OOE+|00 2.52E-03Infant 5.98E-07 1.08E-06 8.01E-08 O.OOE+00 4.47E-07 O.OOE+O0 8.78E-05

Dose factor - liquid release pathway (mrem/Ci released) lZn-69m I

_ _ _ B o n e: ;: | . S..L iv e r : T S d J T h y o i Ki d e L u g J GfEI- L IAdult J 3.25E-04 7.79E-04 | 7.12E-05 O.OOE+00 4.72E-04 0.00E+00 4.76E-02

Ten 43.50E-04 8.252-04 j7.57E-05 J .002+00 5.012-04 j .OOE+00 j4.53E-02!Child [4.49E-04 7.65E-04 |9.04E-05 7 0.00+00 4.44E-04 7 O.OOE+00 | 2.49E-02

Ifant 9.61E-06 1.96E-05 1.79E-06 | 0.002+00 7.94E-06 | O.OOE+00 [2.72E-04




ODCMRevision 17 -August 29, 2005

Table 5.1-1

Dose factor - liquid release pathway (mrem/Ci released)Br-82

_ _ _ _ B o eL veX_ T.''" ' B ody T hyroid0 N fg Ki ne L ung s .,. -L U~* Adilt O.OOE+OO O.OOE+OO 1.39E-03 | O.OOE+OO |O.OOE+00 O.OOE+OO 1.59E-03Teen 'O.OOE+OO O.OOE+OO 1.47E-03 O.OOE+OO O. O.OOE+00 O.OOE+OO O.OOE+OOChild O.OOE+OO O.OOE+OO 1.71E-03 O.OOE+OO O. O.OOE+00 O.OOE+OO O.OOE+OOInfant ' O.OOE+OO O.OOE+OO 4.43E-04 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO


' B o .. L ve....T.' o d J T h y r o d J ' d n yL u n s f_"- L

Adult O.OOE+OO O.OOE+OO 9.06E-07 O.OOE+OO JO.OOE+OO O.OOE+OO 1.30E-06Teen - O.OOE+OO O.OOE+OO 9.85E-07 jO.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OOChild', Z O.OOE+OO O.OOE+OO 1.27E-06 _O.OOE+OO _.OOE+OO O.OOE+00 jO.OOE+OOInfanit" O.OOE+OO O.OOE+OO 2.93E-11 O.OOE+OO O.OOE+OO O.OOE+OO jO.OOE+OO

Dose factor - liquid release pathway (mremlCi released)Br-84

_ _B o n e - -' J L v e T . B o y . T y o dK d n yL-sGR > /4'i',t5, T;"-"" w`YBb TW"" i$d 2 k~Xidi . ^; GAdult O.OOE+00 O.OOE+OO 3.12E-05 O.OOE+OO O.OOE-+OO O.OOE+OO 2.44E-10Teen' O.OOE+OO O.OOE+OO 3.43E-05 O.OOE+OO O.OOE-0O O.OOE+OO O.OOE+OO

Child ' 0.00O+O00 O.OOE+OO 4.33E-05 O.OOE-0O O.OOE+00 O.OOE1+OO O.OOE+OOInfant O.OOE+OO O.OOE+OO 1.20E-05 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO


Bone 'L iv r T'. od y T r K n Lungs GI-LLI s

Adult'. O.OOE+OO O.OOE+OO 4.24E-82 O.OOE+OO O.OOE+OO f O.OOE+OO O.OOE+OOT O.OOE+OO O.OOE+OO 4.60E-82 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OOChild" A O.OOE+OO O.OOE+OO 5.94E-82 O.OOE+OO | O.OOE+OO O.OOE+OO O.OOE+OObInfant 'j I O.OOE+OO O.OOE+OO 9.35E-309 O.OOE+OO O.OOE+OO j O.OOE+OO O.OOE-+OO


Rb-86 1B o n e L i v e r T . B o d y T h y r o i'd K d e u g - L

Adult O.OOE+OO | 7.36E-02 3.43E-02 7O.OOE+OO 7 O.OOE+OO O.OOE+OO 1.45E-02Teen O.OOE+OO 7.98E-02 3.75E-02 O.OOE+OO O.OOE+OO O.OOE+OO 1.18E-02Child&:- O.OOE+OO | 7.93E-02 4.88E-02 |O.OOE+OO 7O.OOE-+OO |O.OOE-+OO | 5.10E-03Infat O.OOE+OO 9.07E-03 4.48E-03 O.OOE+OO O.OOE+OO O.OOE+OO 2.32E-04

age 36 of 123 REFERENCE USE




Table 5.1-1

Dose factor - liquid release pathway (mrem/Ci released)Rb-88

I p B: o n e L i e . B o yT y o dK i n y f L n sG L LAdltU O.OOE+00 1.41E-16 7.46E-17 O.OOE+00 O.OOE+J00 O.OOE+00 1.94E-27Teen O.OOE+00 1.51E-16 8.04E-17 O.OOE+00 O.OOE+00 O.OOE+00 1.29E-23Child O.OOE+0o 1.45E-16 1.O1E-16 O.OOE+00 O.OOE+00 O.OOE+00 7.12E-18

nfant O.OOE+00 5.68E-54 3.12E-54 O.OOE+00 O.OOE+00 O.OOE+00 5.54E-54

Dose factor - liquid release pathway (mrem/Ci released)Rb-89

ult 0O.OOE+00 1.28E-18 8.99E-19 O.OOE+00 O.OOE-+00 O.OOE+00 7.42E-32O.OOE+00 1.34E-18 9.45E-19 O.OOE+00 O.OOE+00 O.OOE+00 2.05E-27

Childs O.OOE+00 1.23E-18 1.09E-18 O.OOE+00 O.OOE+00 O.OOE+00 1.07E-20Infant. O.OOE+00 1.15E-61 7.93E-62 O.OOE+00 O.OOE+00 O.OOE+00 3.92E-62

Dose factor - liquid release pathway (mrern/Ci released)Sr-89

Aut 2.26E-02 JO.OOE+00 6.48E-04 [O.OOE+00 O.OOE+00 O.OOE+00 3.62E-03Teen 2.43E-02 O.OOE+00 6.95E-04 O.OOE+00 O O.OOE+00 O.OOE+J00 2.89E-03Child 4.27E-02 O.OOE+00 1.22E-03 jO.OOE+00 O. O.OOE+00 O.OOE+00 1.65E-03lnfant j: 2.58E-02 jO.OOE+00 7.40E-04 O.OOE+00 O.OOE+00 O.OOE+j00 5.30E-04

Dose factor - liquid release pathway (mrem/Ci released)Sr-90

Adult 5.63E-01 O.OOE+00 1.38E-01 O.OOE-+00 [O.OOE+00 O.OOE+00 1.63E-02T 4.64E-01 O.OOE+00 1.15E-01 O.OOE+00 | O.OOE+00 O.OOE+00 1.30E-02

Child 5.59E-01 O.OOE+00 1.42E-01 O.OOE+00 | O.OOE+00 |.OOE+00 7.53E-03Infant 1.95E-01 O.OOE+00 4.97E-02 O.OOE+00 | O.OOE+00 O.OOE+00 | 2.44E-03

Dose factor- liquid release pathway (mrecn/Ci released)Sr-91

Adult 1.27E-04 7O.OOE+00 5.14E-06 7O.OOE+00 O.OOE+00 O.OOE+00 [6.05E1-04,.Teen 1.38E-04 |O.OOE+00 5.51E-06 O.OOE+00 O.OOE+00 | O.OOE+00 | 6.24E-04Child 1.83E-04 7O.OOE+00 6.91E-06 7O.OOE+00 O.OOE+00 O.OOE+00| 4.04E-04Infant 1.59E-05 O.OOE+00 5.76E-07 O.OOE+00 O.OOE+00 O.OOE+00 _ 1.88E-05





Table 5.1-1

Dose factor - liquid release pathway (rnrem/Ci released)S r-9 2 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

J Bon-eB Trd , Kiney Lgs d |

Adul 5.21E-06 O.OOE+00 2.26E-07 O.OOE+00 O.OOE+00 O.OOE+00 1.03E-04Teer 5.64E-06 0.OOE+0O 2.42E-07 O.OOE+00 O.OOE+00 O.OOE+00 1.44E-04Child 7.20E-06 0.OOE+00 2.89E-07 O.OOE+00 O.OOE+00 O.OOE+00 1.36E-04liifan t 9.41E-10 O.OOE+00 3.50E-l l O.OOE+00 0.OOE+00 0.OOE+00 l.O1E-08

Dose factor - liquid release pathway (rnrern/Ci released)Y-90

fn Bone ' Lie d T id Kd Lungs ^ GI-LL

Adult [SW 4.85E-07 O.OOE+00 1.30E-08 O.OOE+00 O.OOE+00 O.OOE+0O 5.15E-03Teen X 5.16E-07 O.OOE+0O 1.40E-08 O.OOE+00 O.OOE+00 0.OOE+00 4.26E-03Child j 8.67E-07 O.OOE+00 2.32E-08 O.OOE+00 O.OOE+00 O.OOE+00 2.47E-03Infant 4 j 4.80E-07 O.OOE+00 1.29E-08 O.OOE+00 O.OOE+00 O.OOE+00 6.63E-04

Dose factor - liquid release pathway (rnrem/Ci released)Y-91

____ '7 oe,>,6; WLiver', T. Boy Fhridj iF,;0dne Lu,.'ngs J2.29.: =GI." 'Adult ,,g 9.20E-06 O.OOE+O0 2.53E-07 O.OOE+00 O.OOE+00 O.OOE+00 5.06E-03Teen 9.68E-06 O.OOE+00 2.97E-07 O.OOE+00 O.OOE+00 O.OOE+00 3.97E-03Cild 1.74E-05 O.OOE+00 4.74E-07 O.OOE+00 O.OOE+00 O.OOE+00 2.32E-03Infait 1.03E-05 O.OOE+00 2.73E-07 O.OOE+00 O.OOE+00 O.OOE+00 7.35E-04

Dose factor - liquid release pathway (mrem/Ci released)Y-91m I_ _ _ _Bone Liver' iT B od y T hyroid' _ _ _ _ _ _ _ _ _ _ __i_ _|

Adult' J, 1.71E-13 O.OOE+O0 5.10E-14 O.OOE+00 O.OOE+00 O.OOE+00 5.02E-13Teen J 1.85E-13 O.OOE+O0 2.55E-13 O.OOE+00 O.OOE+00 O.OOE+00 - 8.72E-12Child | 2.36E-13 O.OOE+00 6.04E-14 O.OOE+00 O.OOE+00 O.OOE+00 4.62E-10Infant J 2.62E-26 O.OOE+00 8.92E-28 O.OOE+OO O.OOE+00 O.OOE+00 8.72E-23

Dose factor - liquid release pathway (mrem/Ci released) iY-92 I

I__ ni Boy T d J Kd Lu'ngs I I-LIAdult ' 3.51E-09 O.OOE+00 2.88E-10 O.OOE+00 O.OOE+00 I O.OOE+00 6.15E-05

ITeen J 3.83E-09 O.OOE+00 l.15E-09 O.OOE+00 O.OOE+00 O.OOE+00 1.05E-04Child I 4.92E-09 O.OOE+00 3.57E-10 0.OOE-00 O.OOE+00 O.OOE+00 I.42E-04Infnt 5.88E-12 | O.OOE+OO |.6.OOE+0 O.OOE+O O.OOE+00 O.OOE+00 1.12E-07

I � ! : Page 38 of 123 REFERENCE USE


,E D MANU

IIOFFSITE DOSE CALCULATION MANUAL


Table 5.1-1

Dose factor - liquid release pathway (mrern/Ci released)Y-93

g : B o n e L iv er T . B o d T h y oi B 1i d n e Lg 0 1 -L 1i:I Adultf 5.32E-08 O.OOE+OO 2.33E-09 O.OOE+OO O.OOE+O0 O.OOE+OO 1.69E-03Teen 5.77E-08 O.OOE+OO 6.38E-09 O.OOE+OO O.OOE+OO O.OOE+OO 1.76E-03

7.75E-08 O.OOE+OO 3.13E-09 O.OOE+OO O.OOE+OO O.OOE+OO 1.16E-03Infant 8.33E-09 O.OOE+OO 2.27E-10 O.OOE+OO O.OOE+OO O.OOE+OO 6.58E-05

Dose factor - liquid release pathway (mrem/Ci released)Zr-95 _

_ _ _ _ _ _ B o n e L i e J T & B d yU T hy r i K i n y L g s ; Iy- L L I<Aduilt . 1.23E-06 3.94E-07 1.79E-06 O.OOE+OO 6.19E-07 O.OOE+OO 1.25E-03Teen6E 1.1 lE-06 3.52E-07 8.74E-06 O.OOE+OO 5.17E-07 O.OOE+OO 8.1 lE-04CChild.- 2.48E-06 5.45E-07 2.26E-06 O.OOE+OO 7.80E-07 O.OOE+OO 5.69E-04Infant 1.87E-06 4.56E-07 3.23E-07 O.OOE+OO 4.91E-07 O.OOE+OO 2.27E-04

Dose factor - liquid release pathway (mrem/Ci released)Zr-97_ _ _ _ o n i v e r. B o y T h r i d K i e L u n s ; & I -L I dlf

Adult 1 .07E-08 2.16E-09 1.23E-08 O.OOE+OO 3.27E-09 O.OOE+OO 6.70E-04Teen . I.l1lE-08 2.19E-09 6.42E-08 O.OOE+OO 3.33E-09 O.OOE+OO 5.94E-04Chi d 2.21E-08 3.19E-09 E.51E-08 O.OOE+OO 4.58E-09 O.OOE+OO 4.83E-04

Infant 1.92E-08 3.29E-09 l.50E-09 O.OOE+OO 3.32E-09 O.OOE+OO 2.10E-04

Dose factor - liquid release pathway (mrem/Ci released)b95 J S E \ - ' = u -iBo n e ' -| T L i v e f . B o d y f T h y r o i d K i d e | L u n s G -

At ; 3.23E-04 1.79E-04 | 9.73E-05 [O.OOE+OO T 1.77E-04 O.OOE+0O 1.09E+OOTeen I 3.25E-04 1.80E-04 1 1.04E-04 I O.OOE+OO 1 1.75E-04 O.OOE+OO 7.70E-O1

Child 3.84E-04 1.49E-04 1.08E-04 | O.OOE+OO 1.40E-04 O.OOE+OO 2.76E-01Infant 5.36E-07 2.21E-07 1.28E-07 O.OOE+OO 1.58E-07 O.OOE+OO 1.86E-04

Dose factor - liquid release pathway (mrem/Ci released) |Nb-97 _

B o n e L i v e r T . B o d y T h y r o i dK i d n e uts i. LAdult 2.69E-09 6.81E-10 2.51E-10 O.OOE+OO | 7.95E-10 O.OOE+OO 2.51E-06Teen 2.90E-09 7.20E-10 2.73E-10 O.OOE+OO | 8.41E-10 O.OOE+OO 1.72E-05Child"' 3.68E-09 6.65E-10 3.12E-10 O.OOE+OO 7.38E-10 O.OOE+O0O 2.05E-04Infant 5.81E-21 l .24E-10 4.47E-22 |O.OOE+OO 9.68E-22 |O.OOE+OO 3.91E-16

. I Page 39 of 123 REFERENCE USE




Table 5.1-1

Dose factor - liquid release pathway (mrem/Ci released)Mo-99

Adult O.OOE+00 1.49E-04 2.84E-05 O.OOE+00 3.38E-04 O.OOE+00 3.46E-04Teen V O.OOE+00 1.76E-04 3.36E-05 O.OOE+00 4.03E-04 O.OOE+00 3.15E-04Child j, O.OOE+00 2.79E-04 6.91E-05 0.OOE+00 5.96E-04 O.OOE+00 2.31E-041Infant I O.OOE+00 4.38E-04 8.54E-05 O.OOE-+00 6.54E-04 O.OOE+00 1.44E-04

Dose factor - liquid release pathway (mrem/Ci released)Tc-99m _ _ _ _,__ _ _ _.

B on *2 Liv 5e r T.;B od y T h r id 'K d e 1F' f L u n g s GIU-L;,Adult 1.68E-09 4.74E-09 6.07E-08 O.OOE+00 7.20E-08 2.32E-09 2.81E-06Ten 1.74E-09 4.86E-09 6.46E-08 O.OOE+OO 7.24E-08 2.70E-09 3.19E-06

Child 2.19E-09 4.29E-09 7.15E-08 O.OOE+0O 6.24E-08 2.18E-09 2.44E-06Infafnt 3.78E-10 7.79E-10 1.OOE-08 O.OOE+00 8.38E-09 4.07E-10 2.26E-07

Dose factor - liquid release pathway (mrem/Ci released)Tc-101

'B o ne ' 'Lee T .B d B d -Th yroid 'K d e Lungs' O -L LIAdult 3.60E-24 5.19E-24 5.10E-23 0.OOE+00 9.34E-23 2.65E-24 1.56E-35

Te 3.89E-24 5.53E-24 5.49E-23 O.OOE+00 1.OOE-22 3.37E-24 9.45E-31Chid 4.98E-24 5.22E-24 6.63E-23 O.OOE+00 8.90E-23 2.76E-24 1.66E-23

Infant 9.73E-69 1.23E-68 1.21E-67 0.OOE+00 1.46E-67 6.69E-69 2.08E-66

Dose factor - liquid release pathway (mrem/Ci released)Ru-103

Bone,, L ' T o T Kidne Lungs. ' GI LLILAdult 3.47E-05 O.OOE+00 1.56E-05 O.OOE+00 1.32E-04 01.OOE+00 4.05E-03

Teen ' 2.96E-05 0.OOE+O0O 1.64E-05 0.OOE+|00 1.04E-04 |O.OOE+00 2.47E-03Child ' 5.53E-05 0.OOE+O0O 2.20E-05 0.OOE+|00 1.39E-04 0.OOE+O0O 1.43E-03Ian 1.33E-05 0.OOE+|00 4.43E-06 O.OOE+O0 2.76E-05 0.OOE+700 1.61E-04

Dose factor - liquid release pathway (mrem/Ci released) IRu-105 - I

B o e "iv er i. B'd u ng1 s (lIAl t 4.13E-08 0.OOE+|00 1.75E-08 | 0.OOE+00 5.34E-07 0.OOE+|00 2.53E-05

Teen =' 4.45E-08 |.OOE+O | 2.42E-08 O.OOE+00 5.62E-07 0.OOE+|00 3.59E-05|Child 5.71E-08 0.OOE+|00 2.22E-08 0.OOE+T00 5.02E-07 O.OOE+00 3.73E-05Infant I 6.98E-10 O.OOE+OO 2.35E-10 O.OOE+OO 5.13E-09 O.OOE+O0 2.78E-07

� I Page 40 of 123 REFERENCE USE

POINT BEACH NUCLEAR PLANTOFFS1ITE DOSE CALCULATION MANUAL - '


ODCMRevision 17-August 29, 2005

Table 5.1-1

Dose factor - liquid release pathway (mrem/Ci released)Ru-106

_ _ _ _ B o4Lv e1Bo yT y 'r o i K i n e u n s0 1 4 LAdult - 6.71E-04 O.OOE+00 8.76E-05 0.OOE+00 1.30E-03 O.OOE+00 4.34E-02

vTeen 5.86E-04 0.OOE+00 | 8.85E-05 O.OOE+00 1.13E-03 O.OOE+00 2.81E-02Child 1.13E-03 0.OOE+700 1.44E-04 0.OOE+00 1.53E-03 jO.OOE+00 1.76E-02Inffnt 2.23E-04 O.OOE+00 2.78E-05 O.OOE+00 2.63E-04 0.OOE+00 1.69E-03

Dose factor - liquid release pathway (mrem/Ci released)Rh-105

Bone Lie T= BOdy Tyid Updney Ls ^ ,Adult - 3.35E-06 2.45E-06 1.62E-06 0.OOE+00 1.04E-05 O.OOE+00 3.90E-04Teen - 4.IOE-06 2.96E-06 1.97E-06 O.OOE+O0 1.26E-05 O.OOE+00 3.77E-04-Child 8.43E-06 4.52E-06 3.88E-06 O.OOE+O0 1.80E-05 0.OOE+00 2.80E-04Infant 1.08E-05 7.05E-06 4.74E-06 O.OOE+0 1.96E-05 O.OOE+00 1.75E-04

Dose factor - liquid release pathway (mrem/Ci released)

AdiltZ 3.06E-05 2.83E-05 3.83E-05 O.OOE+O0 5.56E-05 0.OOE+0O 1.15E-02Teen 3.74E-05 3.54E-05 1.41E-04 O.OOE+00 6.75E-05 O.OOE+00 9.94E-03Child. 6.78E-05 4.58E-05 6.17E-05 0.OOE+00 8.53E-05 O.OOE+00 5.45E-03Infantiiiv 8.87E-05 6.47E-05 4.28E-05 0.OOE+O0 9.26E-05 O.OOE+0O 3.36E-03

Sn-I 13 and Sn- 17m - liquid release pathway (mrem/Ci released)Boi S L ne< Live JX W, oy Th r i K2id e Lu gs01

Adult J 6.40E-03 2.17E-04 6.78E-04 | 1.26E-04 O.OOE+00 O.OOE-+00 1.32E-01Teen j 6.96E-03 2.33E-04 7.33E-04 |1.28E-04 O.OOE+00 O.OOE+00 1.08E-01

-Child- - 9.03E-03 2.28E-04 9.44E-04 1.66E-04 0.OOE+00 j 0.OOE+00 4.61E-02Infant 1.42E-04 4.43E-06 1.47E-05 1 3.07E-06 0.OOE+00 I.OOE+X 0 3.50E-04

Dose factor -.liquid release pathway (mrem/Ci released)Sb-124

Adult 5.42E-04 1.02E-05 2.21E-04 1.32E-06 0.OOE+0OO 4.22E-04 1.54E-02Teen 5.66E-04 1.04E-05 2.53E-04 1.28E-06 0.OOE+|00 4.94E-04 1.14E-02Child 7.89E-04 1.02E-05 2.83E-04 1.74E-06 |O.OOE+0O 4.38E-04 4.94E-03Infant 1.95E-04 2.86E-06 6.03E-05 5.17E-07 O.OOE+O0 1.22E-04 6.00E-04



OFFS1ITE DOSE CALCULATION MANUAL

ODCM - +-,Revision 17August 29, 2005

Table 5.1-1

Dose factor - liquid release pathway (mrem/Ci released)Sb-125___ j on Livr' 'T.'uE .Bdy Tyod 'C idne J1 Lug | GI-LLJAdut 3.49E-04 3.90E-06 1.07E-04 3.55E-07 O.OOE+00 2.69E-04 3.85E-03

Teen 3.65E-04 3.99E-06 2.19E-04 3.49E-07 O.OOE+00 3.21E-04 2.84E-03Child 5.14E-04 3.96E-06 1.35E-04 4.76E-07 O.OOE+00 2.86E-04 1.23E-03nfant 1.14E-04 1 .1 1E-06 2.35E-05 1.43E-07 O.OOE+00 7.17E-05 1.52E-04

Dose factor - liquid release pathway (mrern/Ci released)Te-125m

_ BBonee T Body Thyroid' Mde Lngsm GI-LL

Adult J 3.30E-04 1.20E-04 4.43E-05 9.93E-05 1.34E-03 O.OOE+00 1.32E-03T 3.36E-04 1.21E-04 4.53E-05 9.39E-05 O.OOE+OO O.OOE+OO 9.92E-04

Chld 5.74E-04 1.56E-04 7.67E-05 1.61E-04 O.OOE+OO O.OOE+OO 5.54E-04infanlt 2.47E-04 8.27E-05 3.35E-05 8.33E-05 O.OOE+OO O.OOE+OO 1.18E-04

Dose factor - liquid release pathway (mrem/Ci released)Te-127'____ 'B~on'e g ~ Liv T. ,B'ody 'T,,, Thyr i Lgs, ' 'G"I LI

Adult 3.15E-05 1.13E-05 6.83E-06 2.34E-05 1.28E-04 O.OOE+OO 2.49E-03Teen'6` 3.45E-05 _ 1.22E-05 7.43E-06 2.38E-05 1 1.40E-04 O.OOE+OO 2.67E-03Child 4.45E-05 1.20E-05 9.54E-06 3.08E-05 1.27E-04 O.OOE+OO 1.74E-03Infant 'A 3.10E-07 1.04E-07 6.67E-08 2.52E-07 7.56E-07 O.OOE+OO 6.51E-06

Dose factor - liquid release pathway (mrem/Ci released)Te-127m

1 Bone Lise'T B',d`y Thyri Kidney Lungs 'GI-LLI

AdultW 8.63E-04 3.08E-04 1.05E-04 2.21E-04 3.51E-03 O.OOE+OO 2.89E-03T'' 8.74E-04 3.10E-04 1.04E-04 2.08E-04 3.54E-03 O.OOE+OO 2.18E-03.Child"' l.50E-03 4.05E-04 | 1.79E-04 3.60E-04 4.29E-03 O.OOE+OO 1.22E-03

Ihnfan't' J 6.28E-04 2.08E-04 7.61E-05 1.82E-04 1.55E-03 O.OOE+OO- 2.54E-04

Dose factor - liquid release pathway (mrem/Ci released)Te-129 _ _

|;,'on Lier -. B l , 0| To~dy Thyroid Kine <.;|.^.,,.Lungs GEI-LLIC'Adult 1 1.68E-08 6.32E-09 4.10E-09 1.29E-08 7.07E-08 O.OOE+OO 1.27E-08"Ten 8 .83E-08 6.82E-09 4.45E-09 1.31E-08 7.68E-08 O.OOE+OO l.OOE-07Child 2.36E-08 6.58E-09 5.60E-09 1.68E-08 6.90E-08 O.OOE+OO 1.47E-06Infant . | 1.08E-18 3.73E-19 2.53E-19 9.07E-19 2.69E-18 O.OOE+OO 8.65E-17

I . Page 42 of 123 PREFERENCE USE




Table 5.1-1

Dose factor - liquid release pathway (mrem/Ci released)Te-129m____:J. 00Bone Liver. T.$ Bodyt j....... Thyroid }, Kidney Lungs }f GJ-LAdult J 1.35E-03 5.04E-04 2.14E-04 4.64E-04 5.63E-03 O.OOE+OO 6.80E-03Teen 1.37E-03 5.1OE-04 2.18E-04 4.43E-04 5.75E-03 O.OOE+OO 5.16E-03Child j 2.34E-03 6.54E-04 3.64E-04 7.55E-04 6.88E-03 O.OOE+OO 2.86E-03Infant 1.04E-03 3.58E-04 1.61E-04 4.01E-04 2.61E-03 O.OOE+OO 6.23E-04

Dose factor - liquid release pathway (mrem/Ci released)Te-131m

______ Bone T.By Thri iny Lgs G-IAdult- 1.04E-04 5.08E-05 4.24E-05 8.05E-05 5. 15E-04 0O.OOE+OO 5.05E-03Teen 1.1 IE-04 5.34E-05 4.49E-05 8.03E-05 5.56E-04 -O.OOE-+O 4.28E-03Child 1.63E-04 5.63E-05 6.00E-05 1.16E-04 5.45E-04 O.OOE+OO 2.28E-03Infant .- 5.46E-05 2.20E-05 1.8 1E-05 4.45E-05 1.5 IE-04 O.OOE+OD 3.70E-04

Dose factor - liquid release pathway (mrem/Ci released)Te-131

Adultu 2.97E-15 1.24E-15 9.40E-16 2.44E-15 1.30E-14 O.OOE+OO 4.21E-16Teen ^ 3.21E-15 1.32E-15 1.O1E-15 2.47E-15 1.40E-14 O.OOE+OO 2.63E-16Child 4.12E-15 1.25E-15 1.23E-15 3.15E-15 1.24E-14 O.OOE+OO 2.16E-14Infant j 4.22E-41 1.56E-41 1.18E-41 3.77E-41 1.08E-40 O.OOE+OO 1.71E-39

Dose factor - liquid release pathway (mrem/Ci released)Te-132

Adult J 1.96E-04 [ 1.26E-04 | 1.19E-04 1.40E-04 1.22E-03 |O.OOE+OO 5.98E-03T 2.05E-04 1.30E-04 | 1.22E-04 1.37E-04 1.24E-03 O.OOE+OD 4.11E-03

Child 3.15E-04 1.39E-04 J 1.69E-04 2.03E-04 1.29E-03 O.OOE+OO T 1.40E-03Infant J 1.48E-04 7.32E-05 6.83E-05 1.08E-04 j 4.58E-04 O.OOE+OO 2.71E-04


I-131 I

| 2.09E-04 2.99E-04 1.71E-04 9.78E-02 5.12E-04 |O.OOE+OO 7.88E-05Teen 2.41E-04 3.37E-04 1.81E-04 9.83E-02 5.80E-04 O.OOE+OO 6.66E-05

Child 4.90E-04 4.93E-04 2.80E-04 1.63E-01 8.09E-04 |O.OOE+OO 4.39E-05Infan t | 5.71E-04 6.73E-04 2.96E-04 2.21E-01 7.86E-04 TO.OOE+OO 2.40E-05





Table 5. 1-1

Dose factor - liquid release pathway (mrem/Ci released)I-132

-__-rd. B oid } Ki gs

Adult 1.43E-07 3.81E-07 1.34E-07 1.33E-05 6.07E-07 O.OOE+00 7.16E-08Teen 1.49E-07 3.90E-07 1.41E-07 1.32E-05 6.15E-07 O.OOE+00 1.70E-07

Child-- 1.85E-07 3.39E-07 1.56E-07 1.57E-05 5.19E-07 O.OOE+00 3.99E-07Infant 1.64E-11 3.32E-11 1.18E-11 1.56E-09 3.71E-11 O.OOE+00 2.69E-11

Dose factor - liquid release pathway (mrem/Ci released)1-133

Bon e .e . .B o .T hyroid. I ^Ki d ey L ung GAdult 3.33E-05 j 5.80E-05 1.77E-05 8.52E-03 7 l.O1E-04 |O.OOE+00 5.21E-05Teen 3.74E-05 | 6.34E-05 1.94E-05 8.85E-03 1.1 1E-04 O.OOE+OO 4.80E-05Child 6.27E-05 7.75E-05 2.94E-05 1.44E-02 1.29E-04 O.OOE1+OO 3.13E-05Infant 4.77E-05 6.95E-05 2.04E-05 1.26E-02 8.17E-05 O.OOE+OO 1.18E-05

Dose factor - liquid release pathway (mrem/Ci released)1-134

_ _ _ B n Li e r T . d - iT h y r o idKi d y L ng s (3 -L UAdutd 2.09E-10 5.69E-10 2.04E-10 9.85E-09 9.04E-10 O.OOE+OO 4.96E-13Teen 2.20E-10 5.82E-10 2.10E-10 9.70E-09 9.18E-10 O.OOE+OO 7.67E-12Chfld 2.72E-10 5.05E-10 2.33E-10 1.16E-08 7.72E-10 O.OOE+OO 3.35E-10Infant 5.37E-22 1.1OE-21 3.91E-22 2.56E-20 1.23E-21 O.OOE+OO 1.14E-21

Dose factor - liquid release pathway (mrem/Ci released)1-135__ _ B one Liver T B od y Thyroid ,| KBoidney Lung G -h L ^Adul}tY- 3.37E-06 8.83E-06 3.26E-06 5.82E-04 1.42E-05 |O.OOE+OO 9.97E-06Teen 3.55E-06 9.14E-06 3.41E-06 5.88E-04 1.44E-05 O.OOE+OO 1.O1E-05

Child \ 4.54E-06 8.17E-06 3.87E-06 7.24E-04 1.25E-05 O.OOE+OO 6.23E-06Infant 4.48E-07 8.92E-07 3.25E-07 7.99E-05 9.94E-07 O.OOE+OO | 3.23E-07

Dose factor - liquid release pathway (mrem/Ci released)Cs-134 |

BIn L i e T' B o dy~ y ." T h r i ' 'n e L u g s & .(j , 3 1 -' " h S L U ;Adult 2.19E-01 5.21E-01 4.26E-O1 |O.OOE+OO | 1.69E-01 |5.60E-02 7 9.12E-03| T 1een1..` 2.25E-01 5.30E-01 2.46E-O1 O.OOE+OO 1.68E-01 | 6.43E-02 6.59E-03| nChid7 2.76E-01 4.520E-01 9.55E-02 7 O.OOE+OO 1.40E-01 5.0311E-02 2.44E-03Infant 1.071E-02 2.001E-02 2.021E-03 J .OOE3+00 5.16E-03 2.1 IE-03 5.441E-05

;-, � . Page 44 of 123 REFERENCE USE

POINT BEACH NUCLEAR PLANTOFFSlTE DOSE CALCULATION MANUAL



Table 5.1-1

Dose factor - liquid release pathway (mrem/Ci released)Cs-134m_ _ _ _ _ _ $ , f ' 9 ' B o n e L i v ' : :Jerss T . i. B o d y T h y o i dK i d L '

lAdult 4.21E-06 8.85E-06 4.52E-06 O.OOE+OO 4.80E-06 7.56E-07 3.12E-06Teen 4.42E-06 9.16E-06 4.71E-06 O.OOE+OO 5.10E-06 8.95E-07 6.OE-06

Child 5.48E-06 8.1 IE-06 5.29E-06 O.OOE+OO 4.28E-06 7.07E-07 1.03E-05Infant 5.19E-11 8.64E-11 4.37E-11 O.OOE+OO 3.33E-11 7.67E-12 6.84E- Il


Cs-136

Adult 2.23E-02 8.8 1E-02 6.34E-02 O.OOE+OO 4.90E-02 6.72E-03 1.OOE-02Teen j 2.25E-02 8.85E-02 5.95E-02 O.OOE+OO 4.82E-02 7.59E-03 7.12E-03

'Childf 2.69E-02 7.40E-02 4.79E-02 O.OOE+OQ 3.94E-02 5.87E-03 2.60E-03Infant [1.18E-03 3.47E-03 1.29E-03 O.OOE+OQ 1.38E-03 2.83E-04 5.27E-05


Cs-137

}Adultn - 2.81E-01 3.84E-01 2.52E-O1 O.OOE+OO 1.30E-01 4.33E-02 7.43E-03Tien 3.02E-01 4.01E-01 1.40E-O1 O.OOE+OQ 1.36E-01 5.30E-02 5.71E-03

Child 3.85E-01 3.69E-01 5.45E-02 O.OOE+QQ 1.20E-01 4.33E-02 2.31E-031in4t 1.l9E-02 1.74E-02 1.24E-03 O.OOE+OQ 4.68E-03 1.89E-03 5.45E-05


Cs-138B o n e.D ¢ L i e I T B o d yT y o i i n e y I , / ' > , L u n g s , = G 1 .1 ' .3I- L L

Adult 3.57E-11 7.04E-11 3.49E-l I1 O.OOE+OO 5.18E-11 5.11E-12 3.QOE-16Teen 3.82E-11 7.34E-11 3.67E-1 I O.OOE+OO 5.42E-11 6.30E-12 3.33E-14Child 4.84E-11 6.73E-11 4.27E-l I | O.OOE+OO 4.73E-11 5.10E-12 3.10E-11Infant 1.63E-32 2.65E-32 1 .28E-32 O.OOE+QO | 1.32E-32 2.06E-33 4.23E-32


Ba-139

I = I;=N-22S&}3 si 0l NoI P M10W1I WPAdult 1.67E-09 1. 19E-12 4.93E-l I T O.OOE+QQ0 | 1.12E-12 6.77E-13 2.97E-09

Teen 1.83E-09 1.29E-12 5.50E-1 | O.OOE+00 1.21E-12 8.87E-13 1.63E-08Child 2.35E-09 1.25E-12 6.84E-l |1 O.OOE+Q | 1.09E-12 7.37E-13 1.36E-07

Infant 3.30E-16 7 2.19E-19 9.55E-18 O.OOE+OQ 1.31E-19 1.33E-19 2.09E-14




ODCMRevision 1'7 ,August 29, 2005

Table 5.1-1

Dose factor - liquid release pathway (mrem/Ci released)Ba-140

-~ B o e-iv r od Th rod - -K id ney - L un sO - LAdult ,^ 5.34E-04 6.71E-07 3.51E-05 O.OOE+00 2.28E-07 3.84E-07 l.lOE-03

ee 5.41E-04 6.63E-07 3.56E-05 O.OOE+00 2.25E-07 4.46E-07 8.35E-04

Child '-k 1.32E-03 1.16E-06 7.72E-05 O.OOE+00 3.76E-07 6.89E-07 6.69E-04

4finhfantj 1.52E-03 1.52E-06 7.84E-05 -O.OOE+00 3.61E-07 9.34E-07 3.74E-04

Dose factor - liquid release pathway (mremnCi released)Ba-141______J__ 'Bone . Body Thyroid Kildey j ,L ngs OI-LLI

AdIlt 4.57E-19 3.45E-22 1.63E-20 -O.OOE+00 3.21E-22 1.96E-22 2.15E-28

T 4.96E-19 3.70E-22 2.14E-20 -O.OOE+00 3.44E-22 2.53E-22 1.06E-24

Child,, 6.37E-19 3.57E-22 2.18E-20 O.OOE+OO 3.09E-22 2.10E-21 3.63E-19

Infant 1.58E-53 1.08E-56 4.99E-55 - 1O.OOE+OO 6.52E-57 L6.60E-57 1.93E-52

Dose factor - liquid release pathway (mrem/Ci released)La-140 _

B O ne ' L e ' T ; BB d T K idney Lun |s G I-L L

Adult 3.66E-08 1.84E-08 1.03E-07 O.OOE+OO O.OOE+OO O.OOE-+OO 1.35E-03

Teen 3.68E-08 1.81E-08 5.51E-07 O.OOE+OO O.OOE+OO O.OOE+OO 1.04E-03

Clhildff 8.21E-08 2.87E-08 1.24E-07 -O.OOE+OO -O.OOE+OO O.OOE+OO 8.00E-04

Infant 8.56E-08 3.38E-08 8.69E-09 O.OOE+OO O.OOE+OO O.OOE+OO 3.97E-04

Dose factor - liquid release pathway (mrenmCi released)La-142

_ _ ' _ _ j B o n ~e .,,' , J L v e ~r', fT I Xt B d tyT y o d | K i n e L u n. T~g s 0 G V L| L I9:5Adult J 2.92E-11 1.33E-11 | 4.94E- 1 O.OOE+OO |O.OOE+OO O.OOE+OO 9.71E-08Teen 3.12E-11 1.38E-11 2.61E-10 O.OOE+OO [O.OOE+OO O.OOE+OO 4.21E-07

'Child 3.93E-11 1.25E-11l 5.77E- 1 O.OOE-1+OO O.OOE+OO O.OOE+OO 2.48E-06

Infant 7.74E-18 2.84E-18 6.81E-19 O.OOE+OO |O.OOE+OO |O.OOE+OO 4.83E-13

Dose factor - liquid release pathway (mrem/Ci released) -_

I Ce-141 4

| Ad`/`t''..| 2.05E-07 .. 1.39E-07 2.4213-07 | .OOE3+OO0 6.45E-08 r O.OOE+OO0 5.31E3-04| en;|2.06E-07 |1.37E3-07 |4.88E3-07 | .OOE3+OO0 6.47E3-08 | .OOE3+OO 3.93E-04 |

| Child ''|5.80E3-07 |2.89E2-07 |1.42E3-07 | .OOE3+OO 1.27E3-07 | O.OOE+OO0 3.61E-04t' 7.11IE-07 4.34E-07 5.11IE-08 O.OOE+OO0 1.34E3-07 1 O.OOE+OO 2.24E-04 W





Table 5. 1-1

Dose factor - liquid release pathway (mrem/Ci released)Ce-143

B o n e } L i v e r T . B o d y T h y r o d " M K id e yL n sG L I

Adlt 1.47E-08 1.09E-05 1.78E-08 O.OOE+OO 4.78E-09 O.OOE+OO 4.06E-04__ 1.49E-08 1.08E-05 9.40E-08 O.OOE+OO 4.86E-09 O.OOE+OO 3.26E-04

eChi 4.01E-08 2.17E-05 2.25E-08 O.OOE+OO 9.12E-09 O.OOE+OO 3.18E-04Infant 5.1OE-08 3.38E-05 3.86E-09 O.OOE+OO 9.85E-09 O.OOE+OO 1.97E-04

Dose factor - liquid release pathway (mrem/Ci released)Cc-144

Bone Liver 1 T. Bod y Th y o Ki ne L nsr (I-L L- . 4s

Au lt 1.12E-05 4.67E-06 1.04E-06 O.OOE+OO 2.77E-06 O.OOE+OO 3.78E-03T 1.12E-05 4.65E-06 3.03E-06 O.OOE+OO 2.78E-06 O.OOE+OO 2.82E-03

-Child" 3.17E-05 9.92E-06 2.20E-06 O.OOE+OO 5.50E-06 O.OOE+OO 2.59E-03Infant 2.80E-05 1.15E-05 O 1.57E-06 O.OOE1+OO 4.63E-06 -O.OOE+O0 1.61E-03

Dose factor - liquid release pathway (mrem/Ci released)Pr-143

= B one Liver, T. Body= } Thyroid.. . .. .. . .. .Kidn, Lung G I-lLLAdult 5.69E-07 2.28E-07 2.82E-08 O.OOE+OO 1.32E-07 | O.OOE+OO 2.49E-03

Te^n6.OOE-07 2.40E-07 2.99E-08 JO.OOE+OO 1.39E-07 O.OOE+OO 1.97E-03Child 1 1.07E-06 3.21E-07 5.31E-08 0O.OOE+00 .74E-07 O.OOE+OO 1.15E-03

Infant: 6.81E-07 2.55E-07 3.38E-08 O.OOE+O0 9.47E-08 O.OOE+OO 3.60E-04

Dose factor - liquid release pathway (mrem/Ci released)Pr-144

Adult 3.76E-22 1.56E-22 2.24E-23 O.OOE+O0 8.80E-23 O.OOE+OO 5.41E-29en 4.09E-22 1.67E-22 3.91E-23 O.OOE+O0 9.61E-23 O.OOE+OO 4.5 1E-25

id 5.29E-22 l1.64E-22 3.05E-23 O.OOE+OO 8.66E-23 O.OOE+OO 3.52E-19Infant- 1.72E-59 6.66E-60 8.67E-61 O.OOE+QO 2.41E-60 O.OOE+OO 3.10E-55

Dose factor - liquid releas pathway (mrem/Ci released)Nd-147 |

Adult, Jl 3.82E-07 4.42E-07 1.13E-07 O.OOE+OO | 2.58E-07 O.OOE+OO 2.12E-03Teen J 4.23E-07 4.60E-07 5.09E-07 O.OOE+OO r 2.70E-07 O.OOE+OO 1.66E-03

Child J 7.45E-07 6.03E-07 1.47E-07 O.OOE+OO 7 3.31E-07 O.OOE+OO 9.55E-04Infant _ 4.53E-07 4.65E-07 2.85E-08 |O.OOE+OO 1.79E-07 O.OOE+OO 2.95E-04


POINT BEACH NUCLEAR PLANTOFFS1TE DOSE CALCULATION MANUAL ;


ODCMI I Revision 17

August 29, 2005

.

Table 5.1-1


Adul 152 Eu- lE-05 2.99E-04 1 .6 3 E-0 4 O.OOE+00 1.85E-05 L. 00 +0 0 1.72E-03

Teenh, 1.21E-05 2.92E-06 9.OOE-04 O.OOE+00 1.35E-05 O.OOE+00 1.07E-03Child j 1.84E-05 3.34E-06 1.91E-04 O.OOE+00 1.41E-05 O.OOE+00 5.49E-04-Ifant 6.27E-06 1.67E-06 1.40E-06 O.OOE+00 4.67E-06 O.OOE+00 1.48E-04

Dose factor - liquid release pathway (mrem/Ci released)W-187

B o e L v e ~ . B d y I T h r id I K id - L u ns11 L

Adult 1' .52E-04 1.27E-04 4.45E-05 [O.OOE+00 O.OOE+00 O.OOE+00 4.17E-02Teen" 1.65E-04 1.34E-04 4.71E-05 fO.OOE+OO O.OOE+OO O.OOE1+OO 3.63E-02Child 2.09E-04 1.24E-04 5.57E-05 [O.OOE1+OO O.OOE+OO jO.OOE+OO 1.74E-02Infant 2.25E-06 1.57E-06 5.41E-07 O.OOE+OO jO.OOE+OO jO.OOE+OO 9.21E-05

Dose factor - liquid release pathway (mrem/Ci released)Np-239

l Bone TZ ;-Liver T . B ody T h oid u - Kidne y 'L ungs G I L LT;

Adult 3.15E-08 3.09E-09 2.30E-08 O.OOE+OO 9.65E-09 O.OOE+OO 6.34E-04Teen` 3.42E-08 3.22E-09 1.21E-07 O.OOE+OO 1.O1E-08 O.OOE+OO 5.19E-04Child 6.77E-08 4.86E-09 2.83E-08 O.OOE+OO 1.41E-08 O.OOE+OO 3.60E-04lfan 5.72E-08 5.12E-09 2.89E-09 jO.OOE+OO 1.02E-08 O.OOE+OO 1.48E-04

Dose factor - liquid release pathway (mrem/Ci released)U-235

-Liyei- 'BoneLd Kidney ' Lns Gl-LLIAdul`t ZO. 3.05E-02 O.OOE+OO 1.89E-03 O.OOE+OO 7.13E-03 O.OOE+OO 2.98E-03

Teen 3.17E-02 O.OOE+O0 2.13E-03 O.OOE+O0 7.43E-03 O.OOE+O0 2.30E-03Child 6.92E-02 O.OOE+O0 4.23E-03 O.OOE+OO 1.14E-02 O.OOE+OO | 1.63E-03Jnfant 4.42E-02 O.OOE+OO 3.37E-03 O.OOE+OO 9.40E-03 O.OOE+OO | 7.67E-04

Dose factor - liquid release pathway (mrem/Ci released) -_

U-238 H_ _A'B n 'L i v e '' T .'Body ~ hy oi IM d n "'L u s I L

',Adult ] 2.92E-02 |O.OOE+OO 1.73E-03 O.OOE+OO 6.67E-03 | O.OOE+OO 2.1OE-03Teen | 3.03E-02 |O.OOE+OO | 1.81E-03 |O.OOE+OO 6.96E-03 O.OOE+OO 1.62E-03Child \ 6.62E-02 |O.OOE+OO 3.93E-03 O.OOE+OO 1.06E-02 |O.OOE+OO 1. 15E-03Ihfant J8.| 4.23E-02 O.OOE+OO I 3.15E-03 |O.OOE+OO I 8.78E-03 O.OOE+OO 5.41E-04

. I ; , i Page 48 of 123 REFERENCE USE


OFFISITE DOSE CALCULATION MANUAL


Table 5.1-1

Dose factor - liquid release pathway (mrem/Ci released)Am-241

.Bone Lungs 01L -

Adult 5.25E-02 1.85E-02 3.47E-03 O.OOE+00 2.61E-02 O.OOE+00 4.75E-03Teen 4.10E-02 1.56E-02 2.77E-03 O.OOE+00 2.05E-02 O.OOE+00 3.74E-03Child 4.10E-02 1.83E-02 2.93E-03 O.OOE+00 1.79E-02 O.OOE+00 2.19E-03Infant 1.42E-02 6.68E-03 1.01lE-03 O.OOE+00 6.10E-03 O.OOE+00 7.17E-04

�i




5.1.2 Atmospheric Release Mode: Radioiodine, Tritium, and Particulates

The dose calculations for demonstration of compliance with the 10 CFR 50,Appendix I dose limits for radioiodines, tritium, and particulate radionuclidesreleased to the atmosphere will be done in the manner similar to the liquidrelease dose calculations described in Section 5.1.1. The total dose iscompared to the corresponding atmospheric release mode Appendix I doselimit for the organ in question.


API = Y Doseaomi = I (TDFaomi X Ci) 5 Kom mrem

Where

API = the Appendix I dose for compliance evaluations in mrem

Doseaomi = the dose to the specific age group (a) and organ (o) viarelease mode (m) from radionuclide (i)

TDFaomi = total dose factor for the specific age group (a) and organ (o)via release mode (m) from radionuclide (i) fromTable 5.1-2 in mrem/Ci

C, = curies of radionuclide (i) released

Kom = the Appendix I dose limit for organ (o) and releasemode (m) for which the calculation is being made.

The methodology and the values used to obtain the TDFaomi values aregiven in Appendix C.

It is recognized that some of the release quantities may not be available atthe end of the month because the samples from these release paths are sentto a vendor for analysis. Usually, the only radionuclides affected by thesedelays are Sr-89 and Sr-90. Because the quantities of these tworadionuclides are but a small fraction of the total release, the absence oftheir dose contributions from the initial monthly dose calculation will notsignificantly affect the total dose obtained from the remainingradionuclides. The dose for the month will be updated upon the receipt ofthe vendor isotopic results and upon the receipt of any corrections toprevious release quantities.

Instead of using the precalculated total dose factors, the Appendix I dosecalculation may be modified to reflect the actual X/Q during the releaseperiod using the methodology of Appendix C.


POINT BEACH NUCLEAR PLANTOFFSITE DOSE CALCULATION MANUAL I



Table 5.1-2

TABLE 5.1-2AIRBORNE EFFLUENT DOSE FACTOR

Summations of dose per curie released were made for calculations over the pathways: ingestion ofproduce, leafy vegetables, milk, meat; inhalation of airborne radionuclides, and direct exposure todeposited radioactivity.

Dose factor - airborne release pathway (mrern/Ci released)H-3- -11-3 °B one f ;; Liver < T~ o y Thyroi Kidny Luns ' GI-LLI ; 1 Ski

Adult O.OOE-+O0 2.34E-04 2.34E-04 2.34E-04 2.34E-04 2.34E-04 2.34E-04 0.OOE+00Teen O.OOE+00 2.69E-04 2.69E-04 2.69E-04 2.69E-04 2.69E-04 2.69E-04 O.OOE+00Child O.OOE+OO 3.93E-04 3.93E-04 3.93E-04 3.93E-04 3.93E-04 3.93E-04 O.OOE+O0Infat ^ 1 O.OOE+O0 1.73E-04 1.73E-04 1.73E-04 1.73E-04 1.73E-04 1.73E-04 0.OOE+O0

Dose factor - airborne release pathway (mrern/Ci released)F-18______ t-.S=Bone Lver Body Thy id Kid ney' L ungs GILLi n^ S inAdultt 1.12E-04 0.OOE1+O0O 9.61E-04 O.OOE+O0 O.OOE+O0 O.OOE+O0 2.19E-06 2.23E-03

'. "'f 1.55E-04 O.OOE+O0 9.65E-04 O.OOE+OO O.OOE+O0 O.OOE+O0 9.23E-06 2.23E-03Chl 2.06E-04 O.OOE+00 9.69E-04 O.OOE+00 O.OOE+0O O.OOE+O0 3.70E-05 2.23E-03

Inf 1.63E-04 O.OOE-+O0 9.62E-04 O.OOE+OO .OOE+O0 O.OOE+O0 2.53E-05 2.23E-03

Dose factor - airborne release pathway (mrem/Ci released)Na-22

Ad> t B oe Liver; T .Bo y T hyrid j Kine L ung *GI- L LIn __ _ .I 4.83E+00 4.83E+00 2.89E+01 T4.83E+O0 4.83E+00| 4.83E+O0O 4.83E+00 3.79E+01

Teen `Et 7.41E+00 741E+00 3.15E+01 7.41E+00 7.41E+O0 7.41E+00 7.41E+00 3.79E+O1Child 1.SOE+01 1.50E+01 3.90E+01 1.SOE+01 1.50E+01 1.50E+01 1.50E+01 3.79E1+01Infant 1.81E+01 1.81E+01 4.21E+01 1.81E+01 1.81E+01 1.81E+01 1.81E+01 3.79E+01

Dose factor - airborne release pathway (mrern/Ci released)Na-24

Adult 9.48E-04 9.48E-04 1.77E-02 [9.48E-04 9.48E-04 J 9.48E-04 9.48E-04 7.64E-02Teen 1.36E-03 | 1.36E-03 1.81E-02 j1.36E-03 1.36E-03 | 1.36E-03 1.36E-03 7.64E-02

d ^ 2.37E-03 2.37E-03 1.91E-02 2.37E-03 2.37E-03 | 2.37E-03 |2.37E-03 7.64E-02Infant j 3.14E-03 T 3.14E-03 1.99E-02 3.14E-03 3.14E-03 3.14E-03 13.14E-03 7.64E-02





Table 5.1-2

Dose factor - airborne release pathway (mrem/Ci released)Sc-46

Bone' Le Bodyy Thyd Kide Lungs - } SkinAdult-/H 1.33E-02 2.59E-02 2.OOE+00 O.OOE+00 2.42E-02 O.OOE+00 2.40E+00 2.69E+00Teen . 1.75E-02 3.41E-02 2.OOE+00 O.OOE+00 3.26E-02 O.OOE+00 2.09E+00 2.69E+00Child 2.23E-02 3.05E-02 2.OOE+00 O.OOE+00 2.70E-02 O.OOE+00 1.32E+00 2.69E+00Infant 1.56E-02 2.25E-02 2.OOE+00 O.OOE+00 1.48E-02 O.OOE+00 1.35E-03 2.69E+00

Dose factor - airborne release pathway (mrem/Ci released)Mn-54

>-Bone Liver 1> Body Thyroid Kidney ns dI nyLI. SinAdult - O.OOE+00 2.32E-01 1.99E+00 O.OOE+00 6.89E-02 4.15E-02 7.08E-01 2.28E+00Ten O.OOE+00 3.34E-01 2.01E+00 O.OOE+00 9.95E-02 5.89E-02 6.83E-01 2.28E+00Child O.OOE+00 4.86E-01 2.07E+00 O.OOE+00 1.36E-01 4.68E-02 4.08E-01 2.28E+00Infant O.OOE+00 2.03E-02 1.95E+00 O.OOE+00 4.47E-03 2.97E-02 7.38E-03 2.28E+00

Dose factor - airborne release pathway (mrem/Ci released)Cr-Sl

_____}__Bone L .Body Thyroid Kdney -Ln d- , -LLI kin

AdultCA, O.OOE+00 O.OOE+00 6.59E-03 2.68E-05 9.86E-06 4.83E-04 1.07E-02 7.73E-03Teen jt'-. O.OOE+00 O.OOE+00 6.60E-03 3.39E-05 1.34E-05 7.03E-04 9.66E-03 7.73E-03Child O.OOE+00 O.OOE+00 6.66E-03 6.30E-05 1.72E-05 6.14E-04 5.81E-03 7.73E-03Inant O.OOE+00 O.OOE+00 6.58E-03 2.42E-05 5.31E-06 4.25E-04 1.02E-03 7.73E-03

Dose factor - airborne release pathway (mrem/Ci released)Mn-56 1

'B)o4ne' Liver'''dy V yr; Thyrod J idne J 'nGI-LLI Skin iAdult O.OOE+00 4.81E-08 1.27E-03 O.OOE+00 J5.31E-08 T2.80E-04 6.01E-04 1.50E-03Teen' O.OOE+00 6.05E-08 1.27E-03 O.OOE+00 j 6.61E-08 j4.5 1E-04 J 1.70E-03 1.50E-03Child. O.OOE+00 6.26E-08 1.27E-03 O.OOE+00 | 6.58E-08 3.90E-04 | 3.66E-03 1.50E-03Infant . O.OOE+00 4.57E-08 1.27E-03 O.OOE+00 | 3.27E-08 3.72E-04 7 2.13E-03 1.50E-03

Dose factor - airborne release pathway (mrem/Ci released)Fe-55 _

___ one Lie-XBod hrid Kde Luns' ILI SAdut 3.20E-01 2.21E-01 5.15E-02 O.OOE+00 O.OOE+00 | 1.25E-01 1.27E-01 O.OOE+00Teen . . 3.80E-01 2.70E-01 6.29E-02 O.OOE+00 O.OOE+00 1.74E-01 1.17E-01 O.OOE+00Child 8.65E-01 4.59E-01 1.42E-01 O.OOE+00 O.OOE+00 2.62E-01 8.49E-02 O.OOE+00Infant A 7.36E-02 4.75E-02 1.27E-02 O.OOE+00 O.OOE+00 2.56E-02 6.02E-03 O.OOE+00


POINT BEACH NUCLEAR PLANTOFFSlTE DOSE CALCULATION MANUAL ; 3



Table 5.1-2

Dose factor - airborne release pathway (mrem/Ci released)Fe-59

Adult 2.01E-01 4.73E-01 5.65E-O1 O.OOE+0 O.OOE--+OO 1.62E-01 1.58E+00 4.50E-O1Teen 2.25E-01 5.24E-01 5.86E-O1 O.OOE+OO O.OOE-+OO 2.10E-01 1.24E+00 4.50E-01Child 4.62E-01 7.48E-01 7.56E-O1 O.OOE+00 O.OOE+OO 2.54E-01 7.80E-01 4.50E-01Ihfant I 6.14E-02 1.07E-01 4.26E-O1 OOO.OOE+00 O.OOE+OO 6.16E-02 5.16E-02 4.50E-Ol

Dose factor - airborne release pathway (mrem/Ci released)Co-57

;__ __ B o e - L i 'T. B od y j Thy Lungs G1-LLIS kinAdult AO.QOQ 0E+0 1.17E-02 4.93E-O1 O.OOE+QO O.OOE+OQ l.lOE-02 2.97E-01 6.13E-O1Te n O.OOE,+OO 1.59E-02 5.OOE-O1 O.OOE+OO Q.OOE+OO 1.74E-02 2.97E-01 6.13E-01Child .O.OOE1+OO 2.57E-02 5.26E-O1 O.OOE+QQ O.OOE+OO 1.50E-02 2.11E-O1 6.13E-OlInfant O.OOE+OQ 4.38E-03 4.8 lE-Ol O.OOE+OO O.OOE+OO 1.13E-02 1.E50-02 6.13E-Ol

Dose factor - airborne release pathway (mrem/Ci released)Co-58_ _ _ _ _ _ JC - 1 4 B o n e } Liver T . B ody T yr i ; uK idn y L u ;n gsG - L S in

Adult J O.OOE+QQ 3.14E-02 6.02E-O1 O.OOE+OO O.OOE+OO 2.75E-02 6.38E-01 6.23E-O1Teen O.OOE+OO 4.OOE-02 6.24E-O1 O.OOE+OO O.OOE+OO 3.99E-02 5.53E-01 6.23E-O1

ChildW O.OOE+0O 5.73E-02 7.07E-O1 O.OOE+OO O.OOE+OO 3.28E-02 3.35E-01 6.23E-O1Infant I O.OOE+OO 9.90E-03 5.57E-O1 O.OOE+OO O.OOE+OO 2.31E-02 2.49E-02 6.23E-Ol

Dose factor - airborne release pathway (mrem/Ci released) ICo-60 I

= o n L ̂ v e r . - o d T h r i d ? ' X i n e ; .L u n ;g s , ' I 1 -I # 1 S k i nAdult; |O.OQE+OO 1.68E-01 3.06E1+Q1 |O.QOE+OO |O.QOE+O0 1.77E-01 3.16E+00 |3.56E+01Teen j O.O-E+O0 2.23E-01 3.07E+01 |O.OOE+OO O.OOE+OO 2.59E-01 2.90E+OO 3.56E+O1

ChildD; |O.OOE+OQ 3.28E-01 3.12E+O1 O.OOE+0 O.OOE+OO |2.10E-01 T 1.82E+00 3.56E+O1Infant |0.OOE+OO 5.86E-02 |3.04E+O1 |O.OOE+OO 0.QQE+QO0 1.34E-01 1.40E-01 3.56E+O1

Dose factor - airborne release pathway (mrem/Ci released) - INi-63 _ _

BoI S S° LO t i ve ) T. Body Ty rod J | i ne 0L ng |. 0 -LU 'S kin.Adult 2.39E+01 1.65E+00 8.00E-O1 |.OOE+00 O.OOE+.OO 5.29E-03 3.45E-41 | O.OOE+OO

Teen 2.93E+O1 2.07E1+00| 9.92E-O1 O.OOE+OO O.OOE+OO | 9.11E-03 3.29E-O1 |O.OOE+OOChild 6.73E+01 3.60E+00 | 2.29E+OO |O.OOE+OQ O.OOE+OO 8.16E-03 2.43E-Q1 O.OOE+OOInfant 2.11E+01 | 1.30E+00 | 7.32E-O1 O.OOE-0O I.OOE+OO | 6.19E-03 6.49E-02 |O.OOE+OQ |



OFFSITE DOSE CALCULATION MANUAL ;

ODCM !!' ' -Revision 17August 29, 2005

- Table 5.1-2

Dose factor - airborne release pathway (mrem/Ci released)Ni-65

_ _ _ _ _ _ B o e ' iv e W T B od y' - - T h yro id "'K id ne -L u gG I Iki 1Adult 8.95E-08 1.19E-08 4.17E-04 O.OOE+00 O.OOE+00 1.66E-04 3.66E-04 4.85E-04Teen 1.06E-07 1.39E-08 4.17E-04 O.OOE+00 O.OOE+00 2.78E-04 1.09E-03 4.85E-04Child 1.64E-07 1.58E-08 4.17E-04 JO.OOE+00 O.OOE+00 2.43E-04 2.49E-03 4.85E-04Infant 7.17E-08 8.5 lE-09 4.17E-04 O.OOE+00 O.OOE+00 2.41E-04 1.49E-03 4.85E-04

Dose factor - airborne release pathway (mrem/Ci released)Cu-64

o n e L r T. Bd K id n e L u n s G = L L S nAdult O.OOE+00 1.12E-05 8.57E-04 O.OOE+00 2.82E-05 2.01E-04 2.40E-03 9.65E-04Teen -: O.OOE+OO 1.40E-05 8.58E-04 O.OOE+OO 3.54E-05 3.30E-04 2.90E-03 9.65E-04Child O.OOE+OO 2.19E-05 8.65E-04 O.OOE+OO 5.28E-05 2.84E-04 2.1 IE-03 9.65E-04Infant O.OOE+OO 3.42E-05 8.68E-04 O.OOE+OO 5.79E-05 2.76E-04 1.15E-03 9.65E-04

Dose factor - airborne release pathway (mrem/Ci released)Zn-65

' B n i er T. Body Th y roiid dn ey Lungs GI- LT' S kinAdultm: 1.21E+00 3.85E+00 2.79E+OO O.OOE+OO 2.57E+00 2.56E-02 2.42E+00 1.21E+OOTe 1.63E+00 5.67E+00 3.69E+OO O.OOE+OO 3.63E+00 3.68E-02 2.40E+00 1.21E+OOChild 3.12E+00 8.31E+OO 6.22E+OO O.OOE+OO 5.24E+00 2.95E-02 1.46E+00 1.21E+OOInfant 2.95E+OO l.O1E+Ol 5.71E+oo O.OOE+OO 4.91E+OO 1.92E-02 8.54E+00 1.21E+OO

Dose factor - airborne release pathway (mrem/Ci released)Zn-69 _

B o ne | i e T 6o d y ' K id L u n gs G J-L LI S kinAdult 3.01E-06 5.76E-06 4.01E-07 O.OOE+OO 3.74E-06 2.73E-05 1.35E-06 O.OOE+OO

Teen 4.64E-06 8.83E-06 |6.18E-07 O.OOE+OO 5.77E-06 4.70E-05 2.47E-05 O.OOE+OOChild | 1.08E-05 1.56E-05 1.45E-06 O.OOE+OO 9.49E-06 4.22E-05 1.29E-03 |O.OOE+OO |Infant | 1.93E-05 3.48E-05 2.59E-06 |O.OOE1+OO 1.45E-05 4.36E-05 3.23E-03 O.OOE+OO

Dose factor - airborne release pathway (mrem/Ci released)

Zn-69m

__ _ '^65t s Bone e L~tiver, l T. Bo Thyroid Kidn y Lungs 1 Si nAdult | 4.99E-05 1.20E-04 3.07E-03 O.OOE+OO 7.26E-05 5.65E-04 1.13E-02 5.74E-03

Teen 7.60E-05 1.79E-04 3.07E-03 O.OOE+OO 1.09E-04 9.30E-04 1.49E-02 5.74E-03Child 1.76E-04 3.00E-04 3.09E-03 O.OOE+OO 1.74E-04 8.08E-04 1.27E-02 5.74E-03Infant j 3.1 1E-04 6.35E-04 3.12E-03 O.OOE+OO 2.57E-04 7.93E-04 | .OOE-02 5.74E-03

. I Page 54 of 123 REFERENCE USE




.

Table 5.1-2

Dose factor - airborne release pathway (mrern/Ci released)Br-82_______. Bone Lif,| Sv'e'r', }l :T.~ Bod',;ytd |J, Thyrid Kidy LugS (I I Skin"1Adult O.OOE+OO O.OOE+OO 5.44E-02 O.OOE+OO O.OOE+OO O.OOE+OO 8.47E-03 6.41E-02Tee O.OOE+OO O.OOE+OO 5.89E-02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 6.41E-02Child O.OOE+OO O.OOE+OO 7.04E-02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 6.41E-02,nant O.OOE+OO O.OOE+OO 8.32E-02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 6.41E-02

Dose factor - airborne release pathway (mrem/Ci released)Br-83

'Bone Lier = T ,Bo d Thyidg -LL Skit J O.OOE+OO O.OOE+OO 1.65E-05 O.OOE+OO O.OOE+OO O.OOE+OO 6.89E-06 2.84E-03

Teen O.OOE+OO O.OOE+OO 1.96E-05 O.OOE+00 O.OOE+OO ._OOE+OO O.OOE+OO 2.84E-03Child O.OOE+OO O.OOE+OO 2.34E-05 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.84E-03Infant j O.OOE+OO O.OOE+OO 2.07E-05 O.OOE+OO O.OOE+0_ O.OOE+OO O.OOE+OO 2.84E-03

Dose factor -.airborne release pathway (mrern/Ci released)Br-84 _

7>>?xl f t E> Bone5 Liver T. Boy ThyroTidw Kidne Lungs............. -- GI-LLIE E SkinSAdltt i O.OOE+OO O.OOE+OO 2.59E-02 O.OOE1+OO O.OOE+OO O.OOE+OO 1.1 lE-09 2.49E-01Teen;.; O.OOE+OO O.OOE+OO 2.60E-02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.49E-01Child jO.OOE+OO O.OOE+OO 2.63E-02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.49E-O1Infant J O.OOE+OO O.OOE+OO 2.66E-02 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.49E-O1

Dose factor - airborne release pathway (mrem/Ci released)Br-85

D XBne_}_Livr . Bod TVyri ;x} |K > idne LunX rA g sW GILL gSkAdult J O.OOE+OO O.OOE+OO 4.95E-06 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.63E-04

Teen O.OOE+OO O.OOE+OO 7.06E-06 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.63E-04Chil&1d f O.OOE+OO O.OOE+OO 2.02E-05 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.63E-04Infant O.OOE+OO O.OOE+OO 4.21E-05 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.63E-04

Dose factor - airborne release pathway (mrem/Ci released)Rb-86 I

Adult - O.OOE+OO 8.21E-01 3.95E-O1 - O.OOE+OO O.OOE+OO O.OOE+OO 1.61E-01 1.44E-02Teen . .><ES | O.OOE+OO 1.23E+00 5.92E-O1 O.OOE+OO O.OOE+OO O.OOE+OO | L.82E-01 1.44E-02Child^ O.OOE+OO 2.18E+00 1.35E+OO O.OOE+OO O.OOE+OO | O.OOE+O 1.40E-01 1.44E-02Infant ^ O.OOE+OO 4.17E+O0 | 2.07E+OO O.OOE+OO0 | O.OOE+OO O.OOE+OOJ 1.07E-01 1.44E-02





Table 5.1-2

Dose factor - airborne release pathway (mrem/Ci released)Rb-88

Bonec 1 Live T- Body Tyroid "'Kidn L -L

Adidlt O.OOE+OO 1. l5E-05 5.22E-05 O.OOE--+OO O.OOE+OO O.OOE+OO 9.92E-17 5.31E-05T een ,M =O.OOE+OO 1.62E-05 5.45E-05 O.OOE+OO O.OOE+OO O.OOE+OO 8.66E-13 5.31E-05Child . O.OOE+OO 1.67E-05 5.73E-05 O.OOE+OO O.OOE+OO O.OOE+OO 5.12E-07 5.31 lE-05Infant O.OOE+OO 1.65E-05 5.50E-05 O.OOE+OO O.OOE+OO O.OOE1+OO 1.O1E-05 5.3 1E-05

Dose factor - airborne release pathway (mrem/Ci released)Rb-89 ,j s

Bone "'Liver T. Bo dy ThKyid " ; L f Skin

Adult O.OOE+OO 7.60E-06 1.78E-04 O.OOE+OO JO.OOE+OO O.OOE1+OO 2.75E-19 2.07E-04Teen O.OOE+OO 1.04E-05 1.80E-04 O.OOE+00 O. OOE+OO O.OOE-I0O 1.OOE-14 2.07E-04Child O.OOE+OO 1.02E-05 11.8 1E-04 O.OOE+OO O.OOE+OO O.OOE+OO 5.61E-08 2.07E-04Infant O.OOE+OO 9.51E-06 1.79E-04 JO.OOE+OO O. O.OOE-0O O.OOE+OO 2.02E-06 2.07E-04

Dose factor - airborne release pathway (mrem/Ci released)Sr-89

1'T""B Bone. Live T Bod .. d -"Kid I0 Iung "I Skin (Adult 7.63E+OO O.OOE+OO 2.19E-O1 O.OOE+OO jO.OOE+OO 4.15E-02 1.23E+00 3.53E-05Teen, 1.16E+O1 O.OOE+OO 3.34E-O1 O.OOE+OO O.OOE+OO 7.17E-02 1.40E+00 3.53E-05Child 2.77E+O1 jO.OOE+OO 7.90E-O1 O.OOE+OO O.OOE+OO 6.40E-02 1.08E+00 3.53E-05Infantt 3.66E+OO O.OOE+OO 1.05E-O1 O.OOE+OO O.OOE+OO 6.02E-02 7.69E-02 3.53E-05

Dose factor - airborne release pathway (mrem/Ci released)Sr-90

f -Bo ne J iver T. Bd Thyroi Kidny Lungs GvI-LLI Kdi L Sidn

Adult .5.10E+02 |O.OOE+OO 1.25E+02 O.OOE+OO j O.OOE+OO [2.85E-01 J 1.47E+O1 J O.OOE+OOT6een 6.33E+02 1 O.OOE+OO 1.56E+02 O.OOE+OO | O.OOE+OO | 4.89E-01 1.77E+O1 |O.OOE+OO|Child 1.05E+03 O.OOE+OO 2.65E+02 O.OOE+0 j.OOE+OO | 4.38E-01 1.41E+O1 |O.OOE+OOInfabft Jj 7.33E+O1 O.OOE+OO 1.84E+O1 O.OOE+OO | O.OOE+OO |3.34E-O1 9.04E-01 10.00E+OO

Dose factor - airborne release pathway (mren/Ci released) I

Sr-91 |

I.,..,,. ,Bone' Liver ~.. Bod.y Thyrid Kidnefy, S' GILL 00LlSkn s|Adult 2.29E-04 O.OOE+OO 3.03E-03 O.OOE+00 O.OOE+OO 1.08E-03 6.76E-03 3.53E-03Teen . 2.20E-04 | O.OOE+OO 3.03E-03 O.OOE+OO O.OOE+OO 1.80E-03 8.68E-03 3.53E-03Childf 4.09E-04 |O.OOE+OO 3.03E-03 O.OOE+0 O.OOE+OO| 1.58E-03 6.06E-03 3.53E-03Infant 5.29E-05 |O.OOE+OO 3.02E-03 O.OOE+0 O.OOE+OO| 1.56E-03 2.24E-03 3.53E-03


POINT BEACH NUCLEAR PLANTOFFSITE DOSE CALCULATION MANUAL.



Table 5.1-2

Dose factor - airborne release vathwav (rnrem/Ci released)Sr-92 _

2-g'DoneBw $ L iver T.B od yt Thyroid il idne - 'L ng ILL SkiAdult - 5.04E-07 O.OOE+00 1.65E-03 O.OOE+00 O.OOE+00 4.89E-04 1.28E-03 3.15E-03Teen I 5.66E-07 O.OOE+00 1.65E-03 O.OOE+00 O.OOE-+00 8.14E-04 3.54E-03 3.15E-03Child 9.08E-07 O.OOE+00 1.65E-03 O.OOE-+00 O.OOE+00 7.12E-04 7.20E.-03 3.15E-03Infant 3.12E-07 O.OOE+00 1.65E-03 O.OOE+00 O.OOE+00 7.06E-04 4.15E-03 3.15E-03


Y-90

Adult . 7.17E-05 O.OOE+00 8.23E-06 . .O.OOE+00 O.OOE+00 5.03E-03 1.19E-01 7.45E-06Teen 9.77E-05 J O.OOE+00 8.93E-06 _.OOE+00 [O.OOE-+00 8.69E-03 9.20E-02 7.45E-06Child [1.39E-04 O.OOE+00 1.00E-05 O.OOE-+00 O.OOE--+00 7.76E-03 5.63E-02 7.45E-06Infant 9.77E-05 O.OOE+00 8.93E-06 O.OOE+00 O.OOE+00 7.98E-03 3.26E-03 7.45E-06

Dose factor - airborne release pathway (mremi/Ci released)Y-91

B o n J L i e T B o d y : S : T h y o i K i n e L u i g s O - L S k 6 |, 'i nAdult, 1.78E-02 [O.OOE+OO 1.98E-03 |O.OOE+OO |O.OOE+OO 5.06E-02 2.26E+00 1.70E-03Teen J 2.55E-02 O.OOE+OO 2.19E-03 - O.OOE+OO O.OOE+OO 8.7 lE-02 2.44E+00 1.70E-03

Child, 64.l10E-02 O.OOE+OO 2.60E-03 O.OOE+OO O.OOE+OO 7.79E-02 1.86E1+00 1.70E-03Infant 1.75E-02 jO.OOE+OO 1.97E-03 O.OOE+OO O.OOE+OO 7.27E-02 3.72E-03 1.70E-03

Dose factor - airborne release pathway (mrem/Ci released)Y-9lm

t;5 5- § i Bo nie Lie r 1 ;6 T. Bod =Th roi Ki ne Lu g (3 US k

Aut 3.5E-0 O.OOE+ | 2.31E-04 O.OOE+OO |O.OOE+OO | 5.70E-05 58iOE-OS | 4.33E-04Ten .6.15E-06 O.OOE+OO 2.31E-04 O.OOE+OO O.OOE+OO 9.49E-0 2.95E-,-04 T 4.33E-04Chidn 1.50E-0 O.OOE+OO 4 2.31E-04 O.OOE+00 O.OOE+OO 8.34E-0 2.94E-02 | 4.33E-04Infant -1.21E-08 |O.OOE+OO 2.31E-04 O.OOE+OO TO.OOE+OO 8.27E-05 6.98E-05 74.33E-04

iDose factor - airborne release pathway (mrem/Ci released)Y-92 7 L1

| Aultt. | 3.35E-05 0.OE1+00 4.38E3-04 | O.OOE+OO | .OOE+OO T4.65E3-04 |5.83E3-01 |2.90E3-02ITeen" 1~:5.80E3-05 1 .OOE+OO 14-39E3-04 1 .OOE3+OO I .OOE3+OO 17.9E-04 11.58E3+OO 12.901302Chidld -| 1.42E3-04 | .OOE3+OO0 4.41E-04 | .OOE3+OO | .OOE3+OO 7.09E3-04 |4.09E3+OO0 2.90E-02 |

|Infanlt 4.86E-07 |O.OOE+OO0 4.37E3-04 | .OOE3+OO | .OOE3+OO 7.27E3-04 |3.76E3-03 |2.90E-02 |

. Page 57 of 123 REFERENCE USE




Table 5.1-2

Dose factor - airborne release pathway (mrem/Ci released)Y-93

JBoneIPW^$ Lvr 'YJ.'d T i Kidney `" ng 0-LU 'Skin

Adult J 1.08E-04 O.OOE+00 4.43E-04 O.OOE+00 O.OOE+00 1.44E-03 3.35E+00 6.58E-02Teen 1 1.86E-04 O.OOE+00 4.45E-04 O.OOE+00 O.OOE+00 2.47E-03 5.59E+00 6.58E-02Child j 4.53E-04 O.OOE+00 4.52E-04 O.OOE+00 O.OOE+00 2.21E-03 6.69E+00 6.58E-02

Infant 4.45E-06 O.OOE+00 4.40E-04 O.OOE+00 O.OOE+00 2.27E-03 4.95E-03 6.58E-02

Dose factor - airborne release pathway (mrem/Ci released)Zr-95

_ _ _ _ _ ; > B o n L i v r * F . 0 mB o d y X s y o d K i d n e ' L u n g G -L L S k i>n ,

Adult 4.79E-03 1.54E-03 3.45E-01 O.OOE+00 2.42E-03 5.25E-02 1.64E+00 3.98E-01

Teen 6.16E-03 1.94E-03 3.45E-01 O.OOE+00 2.85E-03 7.98E-02 1.35E+00 3.98E-01Child;, 9.47E-03 2.08E-03 3.45E-01 O.OOE+00 2.97E-03 6.62E-02 8.8lE-01 3.98E-01

Infant 3.43E-03 8.27E-04 3.44E-01 O.OOE+00 9.23E-04 5.19E-02 9.12E-04 3.98E-01


Zr-97

'J Bjone } Liver"'T.B ody d K n J Lungs 1 - S kinAdult 3.12E-06 6.31E-07 4.16E-03 O.OOE+00 9.56E-07 2.34E-03 3.09E-02 4.84E-03

Teen 4.31E-06 8.52E-07 4.16E-03 O.OOE+00 1.29E-06 3.85E-03 j 3.09E-02 4.84E-03Child f 5.98E-06 8.66E-07 4.16E-03 O.OOE+00 1.24E-06 3.36E-03 1.95E-02 4.84E-03

Infant ; 4.45E-06 7.60E-07 4.16E-03 O.OOE+00 7.69E-07 3.27E-03 4.16E-03 4.84E-03


Nb-95

-; Tf r .4B| XY= 1 _d,,_____ __==_ L_ ;| _ E

Adult ,. l 1.39E-03 7.75E-04 1.92E-01 O.OOE+00 7.67E-04 1.50E-02 3.30E+00 | 2.26E-01B o n . ~ L e ' T..B d T h r i i n y .1 L u g 1 L .S iTeenm-| 1.39E-03 7.72E-04 1.92E-01 O.OOE+00 | 7.48E-04 |2.23E-02 l.99E+00 | 2.26E-01

Child 2.22E-03 8.65E-04 1.93E-01 O.OOE+00 8.13E-04 1.82E-02 1T1 lOE+00 2.26E-01

Inant | 6.08E-04 2.49E-04 1.92E-01 O.OOE+00 1.82E-04 |1.42E-02 4.99E-02 2.26E-01


Nb-97 I

B o n L isv e r> F T . B o d T h r i -; K i n y L n s l ( - L I S i nAdultl~U 2.05E-06 5.17E-07 4.17E-04 O.OOE+00 | 6.03E-07 7.12E-05 l.91E-03 3.20E-03

Teen N 3.50E-06 8.68E-07 4.17E-04 O.OOE+00 1.02E-06 1.17E-04 2.07E-02 3.20E-03Child 8.49E-06 1.53E-06 4.17E-04 | O.OOE+00| 1.70E-06 l.OlE-04 4.73E-01 3.20E-03

|Ifant l.OlE-08 2.16E-09 4.17E-04 O.OOE+00 1.69E-09 9.84E-05 7.98E-04 3.20E-03


POINT BEACH NUCLEAR PLANTOFFSITE DOSE CALCULATION MANUAL -


ODCMRevision 17

-- - August 29, 2005

Table 5.1-2

Dose factor - airborne release pathway (rnremrCi released)Mo-99

d . one Li e T B od y ; T hyro d Kid L s 0 1-L Sk.nAdult O.OOE+00 9. 1OE-03 7.34E-03 O.OOE+O0 2.06E-02 2.71E-03 2.85E-02 6.50E-03Teen O.OOE+O0 1.24E-02 7.97E-03 O.OOE+O0 2.84E-02 4.56E-03 3.02E-02 6.50E-03Child O.OOE+O0 2.06E-02 1.07E-02 O.OOE+00 4.41E-02 4.02E-03 2.08E-02 6.50E-03Infant O.OOE+0O 3.82E-02 1.31E-02 0.OOE+00 5.70E-02 4.OOE-03 1.40E-02 6.50E-03

Dose factor - airborne release pathway (mremtCi released)Tc-99m

B Liver T , ' ^ ..oy dB OT yroid K id ney L: ns& 0 - Sk in

Ad;t 2.92E-09 8.24E-09 2.59E-04 O.OOE+OO 1.25E-07 2.27E-05 1.28E-04 2.96E-04Te 3.1 IE-09 8.68E-09 2.59E-04 O.OOE+O0 1.29E-07 3.42E-05 1.87E-04 2.96E-04Child 5.95E-09 1.17E-08 2.59E-04 O.OOE+O0 1.69E-07 2.82E-05 1.49E-04 2.96E-04Infant . 5.14E-09 1.06E-08 2.59E-04 O.OOE+OO 1.14E-07 2.41E-05 6.33E-05 2.96E-04

Dose factor - airborne release pathway (mremtCi released)Tc-101 _

Adult 1.16E-05 1.67E-05 2.08E-04 O.OOE+00 3.01E-04 2.04E-05 5.06E-17 | 5.80E-04Ten 3 1.99E-05 2.83E-05 3.23E-04 O.OOE+00 5.12E-04 3.71E-05 4.87E-12 5.80E-04

Child 4.89E-05 5.12E-05 6.93E-04 O.OOE+0O 8.72E-04 4.44E-05 1.63E-04 5.80E-04Infant 1.93E-12 2.44E-12 4.44E-05 O.OOE+00 2.90E-11 1.73E-05 2.50E-05 j 5.80E-04

Dose factor - airborne release pathway (rnrem/Ci released)Ru-103

Adlit 4.36E-02 TO.OOE+O0 1.71E-01 O.OOE+00 1.66E-01 1.50E-02 5.08E+00 1.77E-01Te 3.76E-02 1 O.OOE+O0 1.68E-01 O.OOE+00 1.33E-01 2.32E-02 3.14E1+00 1.77E-O1

Child ; 7.01E-02 O.OOE+O0 1.79E-01 O.OOE+00 1.77E-01 1.97E-02 1.81E+00 1.77E-O1Infat 6.20E-05 O.OOE+00 1.52E-01 O.OOE+00 1.30E-04 1.64E-02 5.05E-04 1.77E-Ol

Dose factor - airborne release pathway (mrerntCi released) -

Ru-105 _

0 Bone Liver T.~ Body T hy odi n,, L s | G IS kin

Adult 6.19E-04 O.OOE+O0 2.07E-03 O.OOE+0O 7.99E-03 3.25E-04 3.80E-01 1.02E-02Teen 1.06E-03 0.OOE+O0 2.23E-03 O.OOE+O0 1.34E-02 5.39E-04 | 8.59E-01 1.02E-02Child < 2.59E-03 0.OOE+O0 | 2.76E-03 O.OOE+O0 2.28E-02 4.72E-04 1.69E+00 1.02E-02Infaht| 3.63E-08 O.OOE+00 1.82E-03 | O.OOE+00 2.67E-08 4.65E-04 1.44E-03 1.02E-02

Page 59 of 123 REFERENCE USE l-




Table 5.1-2

Dose factor - airborne release pathway (mremJCi released)Ru-106

_ _ _ _ ' o n , ' i vfe rt T. .. . ... B o d y T h... o i d ' 0 K id n ey 0 L u nmg s . = 0 1 -'(L U I, , , , , iSn 2;^Adult , 1.65E+00 0.OOE+00 8.01E-01 O.OOE+00 3.18E+00 2.78E-01 1.06E+02 7.11E-01Teen 1.49E+00 0.OOE+00 7.81E-01 O.OOE+00 2.88E+00 4.77E-01 7.16E+01 7.11E-01Child 2.93E+00 O.OOE+00 9.58E-01 O.OOE+00 3.96E+00 4.25E-01 4.55E+01 7.11E-01Infant . 2.67E-03 O0.OOE+00 5.93E-01 O.OOE+00 3.28E-03 3.43E-01 5.60E-03 7.11lE-0l

Dose factor - airborne release pathway (mrem/Ci released)Rh-105

. -- 'Bd Rne'A| iv~eir VilW -- Aa hS h Mdf n-.. LAdult 4.81E-02 3.52E-02 2.47E-02 [0.OOE+00 1.50E-01 5.72E-04. 5.61E1+00 7.74E-03Teen 8.33E-02 6.02E-02 4.10E-02 O.OOE+00 2.56E-01 9.711E-04 7.66E+00 7.74E-03ChildM 2.04E-01 1.1OE-01 9.53E-02 O0.OOE+00 4.37E-01 8.59E-04 6.80E+00 7.74E-03Infant 7.15E-04 4.68E-04 1.83E-03 jO.OOE+00 1.30E-03 8.64E-04 1.22E-02 7.74E-03

Dose factor - airborne release pathway (mrem/Ci released)Ag-l lOm

oe Le TBod Th |yrd " Kidn^ey LuGLkinAdult, [4.1OE-02 3.80E-02 4.85E+00 O.OOE+00 7.47E-02 1.37E-01 1.54E+01 5.63E+00

Teen 6.28E-02 5.94E-02 4.86E+00 O.OOE+00 1.13E-01 2.OOE-01 1.66E+01 5.63E+00Child = .1.34E-01 9.04E-02 4.90E+00 O.OOE+00 1.68E-01 1.62E-01 1.07E+01 5.63E+00

Ina 1.93E-01 1.41E-01 4.92E+00 0.OOE+00 2.02E-01 1.09E-01 7.31E+-00 5.63E+00

Dose factor - airborne release athwa (mrem/Ci released)Sb-124_BLT B o d y T h y r o i d K i n e ' L u n g 0 1 - L U ' S k i nAdult 1.44E-01 2.73E-03 1.36E+00 3.50E-04 |O.OOE+00 1.85E-01 4.09E+00 4.02E+00Teen'- 2.22E-01 4.09E-03 1.39E1+00 5.03E-04 O.OOE+00 3.07E-01 4.46E+00 4.02E+00Child 5.1 IE-01 6.63E-03 1.48E+00 1.13E-03 0.OOE+00 3.79E-01 3.19E+00 4.02E+00lnfat 6.72E-02 9.90E-04 1.32E+00 1.78E-04 0.OOE+|00 1.20E-01 2.06E-01 '4.02E+00

Dose factor - airborne release pathway (mrem/Ci released)Sb-125 1

I ~ ~ B n L iv er * r ~ l 5 f' ^ ' T.;>~ B o d T h yroid 'Ki ne L ungss ' -L US kiAdulf 1.07E-011 1.20E-03 5.38E+0O 1.09E-04 O.OOE+OO00 1.33E-01 1.17E+00 9.E11E+00

11.61E-01 1.76E-03 5.39E+00 1.54E-04 O.OOE+00 2.21E-01 1.24E+00 9.11E+00|Chld | 3.69E-01| 2.84E-03 5.43E+00 3.42E-04 | 0.OOE+00 2.73E-01 8.75E-01 9.11E+|00lffantfiC ,'l 8.33E-02 8.05E-04 | 5.37E+00 - 1.04E-04 0.OOE+|00 9.99E-02 1.09E-01 9.11E+00

I � � , 'Page 60 of 123 REFERENCE USE

POINT BEACH NUCLEAR PLANTOFESITE DOSE CALCULATION MANUAL



Table 5.1-2

Dose factor - airborne release pathway (mrem/Ci released)Te-125m[ J B o Liver T dyk T K n L= g C, -LL S kin

Adult J 3.87E-01 1.40E-01 6.67E-02 1.16E-01 1.57E+00 | 9.30E-03 1.55E+00 3.96E-02Teen 5.1IE-01 1.84E-01 8.32E-02 1.43E-01 O.OOE+00 T 1.59E-02 1.511E+00 3.96E-02I Child 1.17E+00 3.16E-01 1.70E-01 3.27E-01 O.OOE+O00 1.42E-02 1.13E+00 3.96E-02Infant ' 5.10E-02 1.71E-02 2.18E-02 1.72E-02 O.OOE-+00 1.33E-02 2.46E-02 3.96E-02

Dose factor - airborne release pathway (mrem/Ci released)Te-127 ,

B o n e~ L i e r T . B o y T h r iCi n Y ' j L n s0 - US iAdul-t -; i, |4.47E-06 1.61E-06 5.15E-06 3.31E-06 1.82E-05 1.93E-04 2.05E-03 4.60E-06

Chnild 4.34E-06 l.55E-06 5.12E-06 3.00E-06 12.76E-05 3.32E-04 2.73E-03 4.60E-06ThiM"n 8.131E-06 2.20E-06 5.93E-06 5.63E-06 2.31lE-05 2.98E-04 1,98E-03 4.60E-06

Infant 1.25E-06 4.25E-07 4.45E-06 1.02E-06 3.03E-06 3.07E-04 7,48E-04 4.60E-06

Dose factor - airborne release pathway (mrem/Ci released)Te-127m

'B L T B ody T I Kid n L S kin

Adult ' 1.19E+00 4.26E-01 1.54E-01 3.05E-01 4.84E+00 2.85E-02 4.OOE+00 6.16E-02en 1.48E+00 5.26E-01 1.85E-01 3.52E-01 6.01E+00 4.91E-02 3.70E+00 6.16E-02

thld 3.32E+00 8.94E-01 4.03E-01 7.94E-01 9.47E+00 4.39E-02 2.69E+00 6.16E-021 Infant - 1.96E-01 6.50E-02 3.26E-02 5.66E-02 4.82E-01 3.89E-02 7.96E-02 6.16E-02

Dose factor - airborne release pathway (mrem/Ci released)Te- 129 _ _ _ _ _

.,i,,j>g2; ' Dg<'~, B one . Liver T. Bod y Thyrod K<7 idney f L ung :0 rL Skin $Adult 1.48E-09 7.10E-10 3.68E-05 1.16E-09 5.56E-09 5.74E-05 4.65E-06 4.36E-05Tn = 2.1 1E-09 l.OOE-09 3.68E-05 1.54E-09 7.88E-09 9.78E-05 4.79E-05 4.36E-05Chid 2.90E-09 1.04E-09 3.68E-05 2.12E-09 7.62E-09 8.71E-05 7.56E-04 4.36E-05Ifant 2.34E-09 1.03E-09 3.68E-05 2.00E-09 5.19E-09 8.89E-05 7.81E-04 4.36E-05

Dose factor - airborne release pathway (mrem/Ci released) |Te-129m -_

Adultv ;1 1.39E+00 5.19E-01 2.35E-01 4.78E-01 1 5.80E+00 3.44E-02 7.01E+00 9.07E-O1Ten 1.94E+00 7.20E-01 3.22E-01 6.26E-01 8.12E+00 5.86E-02 7.30E1+00 9.07E-01

Child 4.53E+00 1.26E+00 7.18E-01 1.46E+00 1.33E+01 5.23E-02 | 5.53E+00 9.07E-01Infant 1.39E-01 4.77E-02 3.66E-02 5.34E-02 3.48E-01 4.98E-02 8.46E-02 9.07E-O1

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Table 5.1-2

Dose factor - airborne release pathway (mrem/Ci released)Te-131

B,1 4 Liv e _ _ '. B y T hyr.'id J K 0 iL u 0 L U S in

Adult 1.47E-03 6.14E-04 | 5.56E-04 1.21E-03 6.43E-03 4.13E-05 2.09E-04 1.63E-03Teen 2.52E-03 1.04E-03 8.80E-04 1.94E-03 1.10E-02 6.93E-05 2.07E-04 1.63E-03C;hildC ' 6.19E-03 1.89E-03 T 1.93E-03 4.73E-03 1.87E-02 6.09E-05 3.25E-02 1.63E-03

nf, - 5.15E-10 2.44E-10 9.27E-05 4.69E-10 1.18E-09 6.1 1E-05 2.44E-04 1.63E-03

Dose factor - airborne release pathway (mrem/Ci released)Te-131m

d_ B Liv TB o d y Thyroid K id y ...- L....I .k i nAdult . 1.30E-01 6.34E-02 7.45E-02 1.OOE-O1 6.43E-01 4.32E-03 6.32E+00 3.77E-02Tee Y- 2.21E-01 1.06E-O1 l.lOE-O1 1.60E-O1 1.IIE+OO 7.05E-03 8.53E+00 3.77E-02Chid 5.38E-01 1.86E-01 2.20E-01 3.83E-01 1.80E+00 6.10E-03 7.56E+00 3.77E-02Infantf 6.34E-04 2.56E-04 2.18E-02 5.18E-04 1.76E-03 5.90E-03 7.8 lE-03 3.77E-02

Dose factor - airborne release pathway (mrem/Ci released)Te-132

B o eL i e T o d 'y ~ T h y r oid, K id nyJ u n gs G I L Ik nAdult 1.92E-01 1.24E-01 1.27E-01 1.37E-01 1.20E+00 8.55E-03 5.89E+00 1.32E-02Teenh- j- 3.19E-01 2.02E-01 2.OOE-01 2.13E-01 1.94E+00 1.33E-02 6.42E+00 1.32E-02Child; , 7.61E-01 3.37E-01 4.17E-01 4.91E-01 3.13E+00 1.12E-02 3.39E+00 1.32E-02Infant 3.94E-03 1.95E-03 1.17E-02 2.88E-03 1.22E-02 1.OlE-02 8.50E-03 1.32E-02

Dose factor - airborne release pathway (mrem/Ci released)I-131_ _ _ _ _ B o n L i e }l T. B o d T y o id ' id n e 9 4L u n g0 |s J G I L L S@ k in ̂ -0Adult i iyi7.16E-02 f 1.02E-01 | 8.29E-02 3.36E+01 1.76E-O1 O.OOE+O | 2.69E-02 2.93E-02

Teen~hv 6.57E-02 | 9.19E-02 7.35E-02 2.68E+01 1.58E-01 O.OOE+0O 11.81E-02 2.93E-02Child 1.44E-01 1.45E--1 1.07E-01 4.80E-01 2.38E-O1 0.OOE+00 1.29E-02 2.93E-02Infainti.> 2.04E-01 2.40E-01 1.30E-01 7.89E+01 2.80E-O1 |O.OOE+O0 8.56E-03 2.93E-02

Dose factor - airborne release pathway (mrem/Ci released) j

1-132

Ad|&ult 3.44E-OS 9.67E-05 1.78E-03 |3.40E-03 1.54E-04 0.OOE+|00 1.21E-05 2.06E-03Teen 4.73E-05 1.30E-04 1.80E-03 4.49E-03 2.05E-04 |O.OOE+|00 3.78E-05 2.06E-03Child 6.28E-05 1.21E-04 1.80E-03 5.74E-03 1.86E-04 O.OOE+00 9.50E-05 2.06E-03Infant 5.03E-05 1.05E-04 1.79E-03 5.03E-03 1.17E-04 O.OOE+00 5.65E-05 2.06E-03

I , � Page 62 of 123 REFERENCE USE

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Table 5.1-2

Dose factor - airborne release pathway (mrem/Ci released)1-133

9''Bone Live 1q T,.Body Th i | Kidney J| Lungs 1 GILI Si

Adult 1.46E-03 2.53E-03 4.21E-03 3.71E-01 4.41E-03 JO.OOE+00 2.14E-03 4.19E-03Teen 1.49E-03 2.52E-03 4.21E-03 3.53E-01 4.42E-03 O.OOE+00 1.75E-03 4.19E-03Child 2.87E-03 3.55E-03 4.78E-03 6.61E-01 5.91E-03 O.OOE+00 1.35E-03 4.19E-03Infant 3.16E-03 4.59E-03 4.79E-03 8.37E-01 5.40E-03 O.OOE+00 7.45E-04 4.19E-03

Dose factor - airborne release pathway (rnreni/Ci released)I-134

t ̂ ;Bone Liver T. Body Thyroid Kidy Lns TLU SkinAdult 1.91E-05 5.13E-05 6.45E-04 8.85E-04 8.17E-05 .O.OOE+00 2.99E-08 7.45E-04Teen 2.63E-05 6.88E-05 6.52E-04 1.17E-03 1.0O9E-04 O.OOE+00 6.05E-07 7.45E-04Child 3.48E-05 6.411E-05 6.57E-04 1.50E-03 9.79E-05 O.OOE+00 2.83E-05 7.45E-04Tnfant 2.73E-05 5.57E-05 6.47E-04 1.32E-03 6.19E-05 .O.OOE+00 3.83E-05 7.45E-04


Adult 9.3 IE-05 2.43E-04 3.64E-03 1.56E-02 3.87E-04 -O.OOE+00 1.96E-04 4.14E-03Teen 1.22E-04 3.12E-04 3.66E-03 2.05E-02 4.92E-04 O.OOE+00 2.41E-04 4.14E-03Child 1.69E-04 3.00E-04 3.69E-03 2.72E-02 4.61E-04 O.OOE-+00 1.63E-04 4.14E-03Infant 1.23E-04 I 2.43E-04 I 3.64E-03 2.22E-02 2.70E-04 I O.OOE+00 6.06E-05 4.14E-03

Dose factor - airborne release pathway (mrem/Ci released) I

Cs-134 -

Adult;S 6.68E+00 1.59E+01 2.26E+01 |O.OOE+00 5.15E1+00T 1.71E+00 2.78E-O1 1.12E+01T 1.06E+01 2.49E1+011 2.12E+01 O.OOE+00 7.90E+00 3.02E+00 3.09E-01 1.12E+01Child Xl 2.39E+01 3.93E+01 1.79E+01 O.OOE+00 1.22E+01 4.37E+00 2.12E-01 1.12E1+01 |Iant 1.96E+01 3.66E+01 1.33E+01 O.OOE+00 9.42E+00 | 3.86E+00 | 9.94E-02 1.12E+01

Dose factor - airborne release pathway (mrem/Ci released) I

Cs-134m _

_______,' |'Bone< ,|~Liv~er''j T~a. Boy} hrietd' idne ungi~s~ 01L SkinAdult 8.36E-04 1.76E-03 | 9.41E-04 |O.OOE-+00 9.54E-04 1.50E-04 6.19E-04 6.90E-05Teen- R 1.40E-03 2.89E-03 1.53E-03 | O.OOE+00 1.61E-03 2.83E-04 1.92E-03 6.90E-05Child 3.30E-03 4.897E-03 3.247E-03 O.OOE+00 2.58E-03 4.271E-04 6.18E-03 6.90E-05.Infant:, 5.481E-06 8.721E-06 4.70E3-05__I O.OOE-i-O 3.531E-06__ 8.3 1E-07 4.82E-06 6.90E-05


POINT BEACH NUCLEAR PLANTOFFSITE DOSE-CALCULATION MANUAL



Table 5.1-2

Dose factor - airborne release pathway (mrem/Ci released)Cs-136______ none Live |T+.d Bod Tr Kidney L -L SkinAdult 3.3 lE-01 1.31E+00 1.28E+00 O.OOE+00 7.27E-01 9.97E-02 1.48E-01 4.73E-01Teeni 5.12E-01 2.02E+00 1.70E+00 O.OOE+00 l0 .1OE+00 1.73E-01 1.62E-01 4.73E-01

ld 1.14E+00 3.14E+00 2.38E+00 O.OOE+00 1.67E+00 2.49E-01 1.lOE-01 4.73E-01a 3.54E-01 1.04E1+00 7.33E-01 O.OOE+00 4.15E-01 8.48E-02 1.58E-02 4.73E-01

Dose factor - airborne release pathway (mrem/Ci released)Cs-137

Bne iver, :TB dy Thyoid Kidney Lgs GL SkinAdult 9.52E+00 1.30E+01 2.30E1+01 0.00E+00 4.42E+00 1.47E+00 2.52E-01 1.69E+01Teen 1.57E+01 2.09E+01 2.18E+01 O.OOE+00 7.12E1+00 2.77E+00 | 2.97E-01 1.69E+01Child 3.73E+01 3.57E+01 1.97E+01 O.OOE+00 1.16E+01 4.18E+00 2.23E-01 1.69E+01Infant 2.99E+01 3.49E+01 1.70E+01 O.OOE+00 9.38E+o0 3.80E+00 1.09E-01 1.69E+01

Dose factor - airborne release pathway (mrem/Ci released)Cs-138

... "Bone Liver T. . | i d Th yrod K ideye U 'SknAdult 2.17E-03 4.28E-03 2.70E-03 O.OOE+00 3.14E-03 3.10E-04 1.82E-08 4.39E-03Teen .._,5 3.69E-03 7.08E-03 4.13E-03 O.OOE+00 5.23E-03 6.08E-04 3.21E-06 4.39E-03Child 8.93E-03 1.24E-02 8.46E-03 O.OOE+00 8.73E-03 9.40E-04 5.71E-03 4.39E-03Ifant - .50E-05 2.32E-05 5.97E-04 O.OOE+00 1.22E-05 1.94E-06 2.60E-05 4.39E-03

Dose factor - airborne release pathway (mrem/Ci released) --

Ba-139 ||

_____A ,Boiez |'_'Liver| T. BoyXhyd Kdney, |Luns ' (HLE 'G Sk|in>Adult 3.78E-03 [2.69E-06 1.38E-04 O.OOE+00 2.52E-06 4.62E-05 6.71E-03 6.76E-03Teen 6.56E-03 j4.61E-06 2.18E-04 O.OOE+00 4.35E-06 8.OOE-05 5.86E-02 6.76E-03Child 1.61E-02 | 8.60E-06 4.95E-04 O.OOE+00 7.51E-06 7.37E-05 9.31E-01 6.76E-03Infant 1.76E-08 | 1.17E-1 1 2.75E-05 O.OOE+O0 7.04E-12 7.07E-05 6.06E-04 6.76E-03

Dose factor - airborne release pathway (mrem/Ci released) |

Ba-140

_V_ .Bn Lier'. Body T d| ' dney, L GI-LLI SkinAdult l.O9E-01 1.37E-04 3.60E-02 O.OOE+00 4.67E-05 3.78E-02 2.29E-01 3.29E-02TeenI 1.19E-01 1.46E-04 3.65E-02 O.OOE+00 4.94E-05 | 6.04E-02 1.88E-01 3.29E-02Child 2.39E-01 2.10E-04 f4.28E-02 O.OOE+00 6.83E-05 J 5.18E-02 1.23E-01 3.29E-02Infant 4.46E-02 4.46E-05 3.1 IE-02 O.OOE+00 1.06E-05 | 4.74E-02 1.17E-02 3.29E-02

, Page 64 of 123 REFERENCE USE




Table 5.1-2

Dose factor - airborne release pathway (mrem/Ci released)Ba-141

1.83E-03 1.39E-06 2.01E-04 O.OOE+00 1.29E-06 2.38E-05 8.66E-13 1.55E-03Teen 3.16E-03 2.36E-06 2.45E-04 O.OOE+00 2.19E-06 4.07E-05 6.75E-09 1.55E-03Chi l: iix 7.79E-03 4.36E-06 3.92E-04 O.OOE+00 3.77E-06 6.03E-05 4.44E-03 l.55E-03

nfant 1.86E-09 1.28E-12 1.39E-04 O.OOE+00 7.72E-13 3.53E-05 5.64E-05 1.55E-03

Dose factor - airborne release pathway (mrem/Ci released)La-140-_ _ _ _ _ B oLi ver`W ^y B odyi T K L > L . Skin

Adlt 1.17E-05 5.91E-06 2.70E-02 O.OOE+00 O.OOE+00 4.04E-03 6.96E-02 3.06E-02Tee 1.57E-05 7.71E-06 2.70E-02 O.OOE+00 O.OOE+0O 6.36E-03 5.51E-02 3.06E-02Child 2.18E-05 7.60E-06 2.70E-02 O.OOE+00 O.OOE+OO 5.42E-03 3.26E-02 3.06E-02bInfan t 1.56E-05 6.17E-06 2.70E-02 O.OOE+00 O.OOE+0O 4.98E-03 5.27E-03 3.06E-02

Dose factor - airborne release pathway (mrern/Ci released)La-142, _< _ _ _ _; B o n e -0 L i v e r _ _ T . B o d T h r i . i d eL n sG I L - S nAdl 4.98E-06 2.27E-06 1.97E-03 O.OOE+00 O.OOE+00 7.52E-OS 1.65E-02 9.71E-03

Teen R 8.44E-06 3.75E-06 1.97E-03 O.OOE+00 O.OOE+OO 1.21E-04 1.14E-01 9.71E-03Child 2.04E-05 6.50E-06 1.97E-03 O.OOE+00 O.OOE+00 1.03E-04 1.29E+00 9.71E-03Itfant 1.22E-08 4.48E-09 1.97E-03 O.OOE+00 O.OOE+O0 9.77E-05 7.07E-04 9.71E-03

Dose factor - airborne release pathway (mrem/Ci released) 11

Ce-141 _

. f L ;;y-tL-|xiiv~er T o Thr|diT~ide '.Lns [0~ . |'tGI-L k kinAdul ,J 7.38E-04 | 5.01E-04 1,93E-02 O.OOE+0 | 2.32E-04 | 1.07E-02 | 3.84E-01 2.16E-02Teen 1.05E-03 7.02E-04 1.93E-02 f O.OOE+00 3.29E-04 1.82E-02 ' 4.02E-01 2.16E-02ChIld | 1.65E-03 8.20E-04 1.93E-02 0.|OOE+00 3.59E-04 1.61E-02 3.02E-01 2.16E-02Infant 8.32E-04 5.OOE-04 1.92E-02 | O.OOE+00 1.58E-04 1.53E-02 J 3.79E-03 2.16E-02

Dose factor - airborne release pathway (rnren/Ci released)

Ce-143T| ''B, C.>~t.id "'L "0015 ./'Bi Sa|a;|$

_ _ _ B n e L i e rT B d T h r i ' K d e ' ~ t i s0 - U J , S k i n .Adult 6.71E-05 4.80E-02 - 4.80E-03 O.OOE+OO 2.18E-05 9.48E-04 1.80E+00 | 6.60E-02Teen l.15E-04 8.10E-02 4.81E-03 O.OOE+00 3.74E-05 1.55E-03 2.44E+00 6.60E-02Child 2.77E-04 1.48E-01 4.82E-03 O.OOE+00 6.31E-05 1.37E-03 2.17E+00 6.60E-02|Infant - 3.55E-06 5.06E-05 4.80E-03 O.OOE+00 6.85E-07 1.38E-03 8.73E-04 6.60E-02





Table 5.1-2

Dose factor - airborne release pathway (mrem/Ci released)Ce-144

B - n I L i e I T . :}3 B o d y . T h r o i K i d n e L u n s ' ̂ 'aGI - L S k i n ,1 ......,,Adult 1.26E-01 5.24E-02 1.04E-O1 O.OOE+OO 3.10E-02 2.31E-O1 8.05E+00 1.13E-O1Teen 1 .83E-01 7.56E-02 1.07E-O1 O.OOE+OO 4.5 1E-02 3.96E-01 9.46E+00 1.13E-O1Child 2.91E-O1 9.1OE-02 1.13E-O1 O.OOE+OO 5.04E-02 3.55E-01 7.37E+00 1.13E-Olbifvti2Lj 9.58E-02 3.64E-02 1.03E-O1 O.OOE+OO 1.61E-02 2.92E-01 6.97E-02 1. 13E-Ol

Dose factor - airborne release pathway (mrem/Ci released)Pr-143

Z; B one Z Liver __A T. B ody Thyroid Kidne LungsZ 0 L U Skin

AdultV 5.1 1E-04 2.05E-04 2.53E-05 O.OOE+OO 1.18E-04 3.34E-03 1.75E+00 3.77E-O1Tten 8.14E-04 3.25E-04 4.05E-05 O.OOE+OO 1.89E-04 5.74E-03 2.16E+00 3.77E-O1

Child ;j 1.82E-03 5.46E-04 9.02E-05 O.OOE+OO 2.96E-04 5.15E-03 1.73E+00 3.77E-O1Infant 1.67E-04 6.23E-05 8.32E-06 O.OOE+OO 2.35E-05 5.14E-03 5.83E-04 3.77E-O1

Dose factor - airborne release pathway (mrem/Ci released)Pr-144 p way

Adult4 8.93E-10 3.70E-10 2.58E-06 O.OOE+OO 2.09E-10 3.01E-05 6.39E-16 2.96E-06Ten 1.27E-09 5.22E-10 2.58E-06 O.OOE+OO 2.99E-10 5.20E-05 6.98E-12 2.96E-06C 1.77E-09 5.48E-10 2.58E-06 O.OOE+OO 2.90E-10 4.64E-05 5.84E-06 2.96E-06Ifant 1.42E-09 5.48E-10 2.58E-06 O.OOE+OO 1.99E-10 4.78E-05 1.27E-04 2.96E-06

Dose factor - airborne release pathway (mrem/Ci released)Nd-147 B

- W"x' l T w 1 - = R'!V00_ _ _ _ _ _ _ -__ _ _ _ _ _ _ _ _ _ _ y o d " T K i n yL n s"-S k i n

Aidult 8.95E-05 1.03E-04 2.OOE-02 O.OOE+00 6.04E-05 -2.62E-03 1.51E-01 2.OOE-01Teen 1.22E-04 | 1.33E-04 2.OOE-02 O.OOE+OO | 7.80E-05 4.42E-03 1.15E-01 2.00E-O1Child | 1.85E-04 1.49E-04 2.OOE-02 O.OOE+OO 8.22E-05 3.90E-03 7.33E-02 2.OOE-O1Infant ,| 9.45E-05 9.69E-05 2.OOE-02 O.OOE+OO 3.75E-05 3.83E-03 | 4.73E-04 |2.OOE-O1

Dose factor - airborne release pathway (mrem/Ci released) -

E u - 1 5 2 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

_ _ _ I _ B n eL v r " T B o d y I T h yroi2Zd K idne y . 'L u n g |- Z. GI -L L= S kinAdult J 3.32E-02 2.45E-01 3.62E+O1 O.OOE+OO 4.67E-02 3.26E-02 1.38E+00 6.86E+O1|Teen 4.20E-02 1.02E-02 3.62E+O1 O.OOE+OO 4.73E-02 4.76E-02 1.23E+00 6.86E+01,Child 6.02E-02 1.1OE-02 3.62E+O1 O.OOE+OO 4.64E-02 3.96E-02 8.25E-01 6.86E+O1

nfant J 1.30E-02 2.95E-03 3.62E-O1 O.OOE+00 9.90E-03 2.46E-02 5.3 1E-04 6.86E+01


POINT BEACH NUCLEAR PLANTOFFS1TE DOSE CALCULATION MANUAL -

OFESITE DOSE CALCULATION MANUAL

ODCM: Revision 17

August 29, 2005

Table 5.1-2

Dose factor - airborne release pathway (mrem/Ci released)W-187_ _ _ _ _ _, ,. '' B one Live T., B ody T hyroid e L g I S knAidt 4.08E-03 3.41E-03 7.22E-03 O.OOE+OO O.OOE+OO 3.45E-04 1.12E+00 2.79E-02

Teen 6.98E-03 5.69E-03 8.03E-03 O.OOE+OO O.OOE+OO 5.63E-04 1.54E+00 2.79E-02Child 1.69E-02 1.OOE-02 1.05E-02 O.OOE+OO O.OOE+OO 4.88E-04 1.41E+00 2.79E-02Infant - 1.13E-05 7.88E-06 6.04E-03 O.OOE+OO O.OOE+OO 4.7 1E-04 8.79E-04 2.79E-02

Dose factor - airborne release pathway (mrem/Ci released)U-235

i.___|_J0, Bon~e Lie T.W't<<.lD Bod Thyrid>t- [1 KinyLns|iTSiAdult , 4.06E+O1 O.OOE+OO 1.04E+O1 O.OOE+OO |9.47E+00 4.66E+00 | 3.87E+00 | 1.06E+01Tene [ 6.45E+O1 O.OOE+OO 1.19E+O1 O.OOE+OO 1.5 1E+O1 8.03E+00 4.59E+00 1.06E+01Child 1.54E+02 O.OOE+OO 1.73E+O1 O.OOE+OO 2.53E+01 7.17E+00 3.58E+OO 1.06E+01Infant 1.17E+O1 O.OOE+OO 8.84E+OO O.OOE+OO 2.49E+00 5.46E+OO 1.90E-01 1.06E+01

Dose factor - airborne release pathway (mrem/Ci released)U-238

_ _ _ B 0 $ Von e L i e r T . B o d h y o d K i d n e ry L u n g G I L L 2 " 6Sk:ND, i$ ..........,8n LAAdult ' 3.88E+O1 O.OOE+OO 2.33E+OO O.OOE+OO 8.86E+00 4.36E+00 2.72E+00 2.47E-01Teen j 6.17E+O1 O.OOE+OO 3.70E+OO O.OOE+OO 1.41E+01 7.50E+00 3.23E+00 2.47E-O1Clild 1.48E+02 O.OOE+OO 8.79E+OO O.OOE+OO 2.37E+01 6.73E+00 2.53E+00 2.47E-01

Infanit 1.12E+O1 O.OOE+OO 18.63E-O1 I O.OOE+OO 2.33E+00 5.09E+00 1.34E-01 2.47E-01

Dose factor - airborne release pathway (mrem/Ci released)No-239

: B o nLi eT B ody T hyroid Ki nedL nsiI L | S kin t

tAdtt l 5.00E-05 4.92E-06 5.54E-03 O O.OOE+OO 1.53E-05 54.47E-04 489.55E-01 9.52E-03T 18.79E-05 8.29E-06 5.55E-03 O.OOE+OO 2.60E-05 7.71E-04 41.27E+00 9.52E-03

Child l2.1E-04 1.52E-05 5.55E-03 O.OOE+OO 4.39E-05 16.91E-04 11.10E+00 9.52E-03Irfant 4.42E-06 1 3.95E-07 5.54E-03 O.OOE+OO 7.88E-07 |7.07E-04 |3.14E-04 | 9.52E-03

IDose factor - airborne release pathway (mrem/Ci released) 1.Am-241 l

|'>t,'',i'6|t B l'Y,,= ,"od^ '|4* l;oadAD^ kill

|Adult .^ 1.34E+02 |4.76E+01 |1.03E+O1 |O.OOE+OO0 6.70E+01 |5.76E+00 |3.48E+00 :|2.94E+OO0|T666x; 1.46E+02 |5.59E+O1 |1.llE+O1 70.00E+00 7.31E+01 |9.99E+00 74.12E+00 2.94E+00CHU, 0 1.37E+02 |6.14E+01 1. I IE0 ;OE 5.9E0 .8; 13.2+0 29E0

! fnt~,3.07E+01 |11.41E+1 L~3.56E+OO | O.OOE+OO |11.32E+01 I 6.76E+00 I 2.58E-03 I 2.94E+OO0


POINT BEACH NUCLEAR PLANTOFFSITE DOSE-CALCULATION MANUAL



5.1.3 Atmospheric Release Mode:' Noble Gases

The dose calculations for demonstration of compliance with the 10 CFR 50,Appendix I dose limits for noble gases released to the atmosphere will bedone in the manner similar to the liquid release dose calculations described inSection 5.1.1. The total doses to the air, skin, and whole body resulting fromthe release of noble gases is compared to the corresponding Appendix limits.Noble gases released in liquids are to be added to the atmospherically releasednoble gases for Appendix I dose compliance calculations.


API = X Doseti = I (TTDFti x Ci ) < Kt mrem

where

API = the Appendix I dose for compliance evaluation in mrem

Doseti = the dose to the applicable target (t) from radionuclide (i)

TDFtd = total dose factor from Table 5.1-3 in mrem/Ci for the specifictarget (t) from radionuclide (i) based on the maximum annualaverage X/Q at the site boundary

Ci = curies of radionuclide (i) released

Kt = the noble gas Appendix I dose limit for target (t)

The methodology used to obtain the TDF values are given in Appendix C.

Instead of using the precalculated total dose factors, the Appendix I dosecalculation may be modified to reflect actual X/Q values during the releaseusing the methodology of Appendix C.

� -1 II �- � -:-k page 68 of 123 REFERENCE USE




TABLE 5.1-3ACTIVITY TO DOSE CONVERSION FACTORS FOR NOBLE GASES

(Highest Annual Average X/Q)Nulide Beta Air 'GammaifiAirfSifWoeBd

(ninrdci) (mradCi) nrmC) nrn/iAR-41 1.56E-04 4.42E-04 6.19E-04 4.20E-04

KR-83M 1.37E-05 9.18E-07 1.02E-06 3.59E-09KR-85M 9.37E-05 5.85E-05 1.34E-04 5.56E-05

KR-85 9.27E-05 8.18E-07 6.46E-05 7.66E-07KR-87 4.90E-04 2.93E-04 7.88E-04 2.81E-04KR-88 1.39E-04 7.23E-04 9.15E-04 6.99E-04KR-89 5.04E-04 8.23E-04 1.39E-03 7.89E-04KR-90 3.72E-04 7.75E-04 1.21E-03 7.42E-04

XE-131M 5.28E-05 7.42E-06 3.09E-05 4.35E-06XE-133M 7.04E-05 1.55E-05 6.45E-05 1.19E-05XE-133 4.99E-05 1.68E-05 3.32E-05 1.40E-05

XE-135M 3.51E-05 1.60E-04 2.11E-04 1.48E-04XE-135 1.17E-04 9.13E-05 1.90E-04 8.61E-05XE-137 6.04E-04 7.18E-05 6.60E-04 6.75E-05XE-138 2.26E-04 4.38E-04 6.82E-04 4.20E-04

I




6.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

Technical Specification 5.5.1.b requires the ODCM to contain the radiological environmentalmonitoring activities. A complete description of the PBNP radiological environmentalmonitoring program, including procedures and responsibilities, is contained in the PBNPEnvironmental Manual. The latter is hereby incorporated into the Offsite Dose CalculationManual (ODCM) by reference.

7.0 RADIOLOGICAL EFFLUENT CONTROLS PROGRAM

Technical Specifications 5.5.1.b and 5.5.4 require the ODCM to contain the radiological effluentcontrols program. A complete description of the PBNP radiological effluent controls program iscontained in the PBNP Radiological Effluent Control Manual. The latter is hereby incorporatedin the ODCM by reference.

8.0 RADIOLOGICAL IMPACT EVALUATION OF SEWAGE TREATMENT SLUDGEDISPOSAL

The methodology for determining the radiological impact of contaminated sewage treatmentsludge is presented in this section. The evaluation must be made prior to every land applicationof sewage treatment plant (STP) sludge that contains licensed material. Sludge and other STPmaterial which does not contain licensed materials may be disposed of by any legal methodwithout prior radiological analysis.

8.1 Basis. Commitments, and Actions

8.1.1 Basis

With the discovery that the PBNP STP sludge contained licensed material,Wisconsin Electric applied for NRC approval to dispose of the sludge by landapplication on land within the PBNP site boundary pursuant to10 CFR 20.302(a). Wisconsin Electric committed to gamma isotopic analysis(GIA) of the sludge to measure the concentrations of licensed material in theSTP sludge and to compare the results to concentration limits prior to eachdisposal [letter dated October 8, 1987 (VPNPD-87-430, NRC-87-104)]. Inaddition, the dose to the maximally exposed individual of the general publicand to the inadvertent intruder would be evaluated for the appropriateexposure pathways.

8.1.2 Basis for NRC Commitment Modification

Pursuant to NRC guidance, the sludge is clean if no licensed materials arefound when analyzed under conditions necessary to achieve the environmentalLLDs (NRC HPPOS 221). Clean sludge is not under NRC jurisdiction andmay be disposed of by any legal method without prior radioanalyses.Therefore, if the sludge is clean and there is no pathway to the STP from theRCA, or pathways are administratively controlled to prevent the transfer oflicensed materials to the STP, there is no need to analyze the sludge prior toany disposal.

-Page 70 of 123 REFERENCE USE



Since the 1987 commitment, engineering modifications and administrativecontrols have eliminated the pathways from the RCA to the STP. Threesubsequent sludge GIAs (a total of eight STP samples) utilizing the analyticalparameters required to achieve environmental lower limit of detection (LLD)found only naturally occurring radionuclides. In each analysis, the licensedmaterials were below the minimum detectable activity for the particularmeasurement and below the required LLDs. These results verify theefficiency of the modifications and administrative controls in eliminatingpathways from the RCA to the STP. Therefore, because there is no longer anyreason to believe that the PBNP STP sewage contains licensed material andthere are no pathways from the RCA to the STP, the sewage may be disposedof by any legal method without GIA prior to each disposal.

8.1.3 Modification

Periodic gamma isotopic analyses (GIA) of the STP sludge shall occur at afrequency set forth in the Chemistry Analytical Methods & Procedures(CAMP). This may include analyses prior to disposal depending on theresults from the periodic analyses. The GIA of the STP sludge shall meet theLLD criteria of normal liquid effluents. The detection of any licensedmaterial in the sludge during the periodic GIA shall necessitate returning tothe GIA prior to disposal in order to evaluate the radiological consequences ofthe disposal. The GIA prior to each disposal shall continue until such timethat the sludge can be shown, using environmental LLD criteria, not to containlicensed material.

Also, re-initiation of the 1987 commitment to analyze the STP sludge prior toeach disposal shall be required if plant conditions change in a manner whichwould lead one to believe that the STP sludge may be contaminated. Anexample of such a condition is the opening of valve STP-009 which iscontrolled by a danger tag. Again, reversion to a CAMP controlled frequencycan occur only upon verification that no licensed material is in the sludgepursuant to the environmental LLD criteria.

8.1.4 Exposure Evaluations

If the sludge contains licensed material, the 1987 commitment requires thatthe appropriate exposure pathways be evaluated prior to each application ofsludge to insure that the dose to the maximally exposed member of the generalpublic is maintained at less than 1 mrem/year and that to the inadvertentintruder, at less than 5 mrem/year. Also, the measured concentration shall becompared to the liquid maximum effluent concentrations of Appendix B to10 CFR 20.

The exposure pathways evaluated for the maximally exposed individual are thefollowing:

1. External whole body exposure due to a ground plane source of radionuclides.

2. Milk ingestion pathway from cows fed alfalfa grown on plot.

3. Meat ingestion pathway from cows fed alfalfa grown on plot.


POINT BEACH NUCLEAR PLANT ODCMOFFSMiT DOSE CALCULATION MANUAL Revision 17


4. Vegetable ingestion pathway from vegetables grown on plot.

5. Inhalation of radioactivity resuspended in air above plot.

6. Pathways associated with a release to Lake Michigan. These pathways areingestion of potable water at the Two Rivers, Wisconsin municipal water supply,ingestion of fish from edge of initial mixing zone of radionuclide release,ingestion of fresh and stored vegetables irrigated with water from Lake Michigan,ingestion of milk and meat from cows utilizing Lake Michigan as drinking watersource, swimming and boating activities at the edge of the initial mixing zone,and shoreline deposits.

The exposure pathways evaluated for the inadvertent intruder are the same as items 1, 4,5, and 6 identified above for the maximally exposed individual.

8.2 Procedure

The following steps are to be performed by the responsible Chemistry Specialist for eachcontaminated sewage treatment sludge disposal:

8.2.1 Determine the radionuclide concentrations in each representative sewagetreatment sludge sample. The minimum number of representative samplesrequired is three from each sludge storage tank. The average of allstatistically valid concentration determinations will be utilized in determiningthe sludge storage tank concentration values.

8.2.2 Verify that the concentration of each radionuclide meets the concentration andactivity limit criteria. The methodology for determining compliance with theconcentration and activity limit criteria are contained in Wisconsin Electricletter VPNPD 87-430.

8.2.3 Verify that the proposed disposal of the sewage treatment sludge will maintaindoses within the applicable limits. This calculation will include radionuclidesdisposed of in previous sludge applications. The activity from these priordisposals will be corrected for radiological decay prior to performing dosecalculations for the meat, milk, and vegetable ingestion pathways, theinhalation of resuspended radionuclides, and all pathways associated with apotential release to Lake Michigan. The residual radioactivity will becorrected, if applicable, for the mixing of radionuclides in the soil prior toperforming external exposure calculations.

QAD, a nationally recognized computer code, will be used to calculate thedose rate due to standing on a plot of land utilized for sludge disposal inwhich the radionuclides from prior disposals have been incorporated into theplot by plowing. This calculated dose rate will be used to assess theradiological consequences from prior disposals with the consequences ofproposed future disposals. The total radiological dose consequence of the pastand the proposed disposal will be compared to the applicable limits to insurethe dose is maintained at or below the limits.

The methodology for calculating the radiological impact of the sewagetreatment sludge disposal is contained in Wisconsin Electric letter VPNPD87430.




8.2.4 Inform the appropriate Chemistry Specialist that the sewage treatment sludgedisposal may proceed after verifying that the sewage treatment sludge meetsthe concentration, activity, and dose limits.

8.2.5 All calculations shall be included with the sewage treatment sludge disposalrecord.

8.3 Administrative Requirements

8.3.1 Complete records of each contaminated disposal shall be kept as follows:

a. Radionuclide concentration of the sludge.

b. Total volume of sludge disposed.

c. The identity of the plot used for the disposal.

d. Dose calculation results.

e. Results of annual chemical composition determination.

8.3.2 Modifications to the WE application as documented in the October 8, 1987,letter shall be processed in accordance with NP 5.1.7, "RegulatoryCommitment Management." (CCE 2001-013)

a. Commitment Change -1

Section 3.2 of Attachment II of the submittal states that physical andchemical properties of the sludge would be determined prior the each landapplication. Pursuant to a change in the PBNP WPDES Permit,non-radiological properties are now determined annually instead of perapplication. The frequency for radiological characterization did notchange. (See CCE 2002-002)

b. Commitment Change -2

In Section 3.3 of Attachment II of the submittal letter, the annual disposalrate was... " limited to 4,000 gallons/acre, provided WDNR chemicalcomposition, NRC dose guidelines and activity limits are maintained...."Modification 2 removes the 4,000 gallon limit and makes the applicationunlimited provided the WDNR and NRC constraints are met.(See CCE 2002-004)


POINT BEACH NUCLEAR PLANT ODCMOFFSITE DOSE CALCULATION MANUAL Revision 17 -


c. Commitment Change -3

In Section 3.2 of Attachment II of NRC submittal letter datedOctober 8, 1987, Wisconsin Electric committed to gamma isotopicanalysis (GIA) to determine the concentration of licensed material insewage treatment plant (STP) sludge prior to each disposal. Pursuant toNRC HPPOS-221 guidance, the sludge has been shown to be clean onthree different occasions after pathways from the RCA to the STP wereeliminated by plant modifications and administrative controls. Pursuant toHPPOS, the sludge analyses were done under the conditions necessary toachieve the environmental LLDs. Only naturally occurring radionuclideswere found and licensed material was below the minimum detectableconcentration. This indicates that the former pathways from the RCA tothe STP had been eliminated. Therefore, there is not need to continue theanalyses because there is no RCA to STP pathway and there is no reasonto believe that the sewage contains licensed material. Hence, thecommitment to analyze STP sludge prior to every disposal is modified andreplaced with periodic analyses at a frequency set by CAMP 914.However, if plant conditions change in a manner which places the STPsewage outside the guidance parameters which allowed for thediscontinuance of analyses, the sewage must be analyzed prior to eachdisposal until it again is shown not to contain licensed material.(See CCE-2002-3)




APPENDIX A

DERIVATION OF LIQUID RELEASE PATHWAY

EE;CTIVE MAXIMUM EFFLUENT CONCENTRATION

A. 1.0 Derivation of Liquid Release Effective Maximum Effluent Concentration

A.1.1 Source Term

The effective maximum effluent concentration is calculated from the annualreleases via liquids for the years 1985-1991 (Table A-1). Although Na-24was discharged in 1985, it was excluded from the isotopic mixture because itis not a radionuclide which would be normally found in PBNP effluent.Na-24 appears in the effluent because it was used for tests run on the steamsystem. Tritium also was omitted from the initial calculation because itsproduction is largely independent from the appearance of the fission productsin the effluent.

A.1.2 Effective Maximum Effluent Concentration

The effective maximum effluent concentration (EMEC) was calculated usingthe formula given in Section 3.6

EMEC - Ci / (Ci/MECi) or lCi * 1/SOF

where:

SOF = X Ci/MECi is the summation of fractions for the annualeffluent isotopic release

C1 = concentration of radionuclide "i" (pCi/ml) in effluent(annual discharge/total volume of discharge)

MECi = maximum effluent concentration for unrestricted areas fromAppendix B, Table 2, Column 2 of the revised 10 CFR 20.

The SOF for radionuclides in liquid effluent for the years 1985 through 1991were calculated with and without H-3 and used to calculate the EMEC for thesame years (Table B-2). The average EMEC without H-3 is 4.29E-06 ,uCi/cc.This is the maximum concentration of non H-3 radionuclides in a mixture thatcould be released in liquid effluent without the SOF exceeding one (1).

However, the 10 CFR 20 Appendix B criterion is that the SOF for allradionuclides, including H-3 which can not be measured by the liquid effluentNaI RMS monitors, be less than or equal to one (1). Therefore, the aboveequation, modified by a factor of 0.70 to account for H-3, becomes

EMEC = 0.70 Ci / Z (Ci/MECi) or Y.Ci * 0.70/SOF.




The EMEC becomes

EMEC = 0.70 * 4.29E-06 = 3.OOE-06 gCi/cc.

Only three radionuclides identified in PBNP liquid effluent have a lower MEC(10 CFR 20, Appendix B, Table 2). They are I-131 (lE-06), Cs-134 (9E-07),and Cs-137 (1E-06).

By restricting the non-tritium radionuclides to 70% of their calculated EMEC,the H-3 concentration can be discharged at 30% of its MEC or3.OOE-04 [tCi/cc without exceeding the SOF criterion of 10 CFR 20,Appendix B for the total liquid effluent isotopic mixture.





TABLE A-iCURIES RELEASED IN LIQUIDS

El��UULWL', I - i 4hW;U','�ll I , � 191Z � I , , m �m

�0� I �� I �� I . , � � � � 7

, , I ��K:A - i V � I � - 11 I � ; �r�-i � IMT � ME 1161, � E MM M 1",

H-3 I 00EO 3 8.05E+02 8.11IE+02 7.09E+02 3.57E+02 5.59E+02 8.7M2E+0 787E402

1-13 1 1.OOE-06 1.02E-01 3.74E-02 1.04E-02 1.40E-03 1.77E-03 1.53E-04 1.83E-03

1-132 1 .OOE-04 6.15E-02 7.25E-02 5.82E-02 1.03E-03 8.15E-04 4.45E-05 9AI1E-03

I-133 7.OOE-06 1.27E-01 1.49E-01 T1.04E-01 1.21E-02 T8.11E-03 3.01E-03 1.O1E-02

1-134 J4.OOE-04 3.18E-02 J4.39E-02 3.97E-02 2.29E-04 6.83E-04I-135 j3.OOE-05 J1.04E-01 J1.34E-01 1.23E-01 4.48E-04 J8.21E-04 __________

AG-i11OM 6.OOE-06 2.55E-05 2.84E-04 3.09E-03 9.85E-04 4.70E-04 1.7 1E-04 4.06E-04

BA-133 2.OOE-05BA-139 2.OOE-04 8.63E-06 2.47E-04

BA-140 8.OOE-06 6.90E-06 4.45E-05 6.13E-05

CD-109 6.OOE-06 6.33E-05 1.31E-04CE-139 7.OOE-05CE-141 3.OOE-05 1.31E-03 7.50E-04CE-144 3.OOE-06 1.37E-03 2.08E-03 4.76E-04 1.59E-04 9.47E-06 9.64E-06

CO-56 6.OOE-06CO-57 6.OOE-05 2.52E-03 1.33E-04 3.21E-04 5.07E-05 6.90E-07 4.08E-06

CO-58 2.OOE-05 4.05E-01 9.02E-03 3.36E-02 6.81E-03 3.12E-03 3.25E-04 2.93E-03

CO-60 3.OOE-06 2.88E-01 2.85E-02 6.34E-02 2.04E-02 1.54E-02 IAI1E-03 5.53E-03

CR-51 5.OOE-04 2.71E-02 3.16E-04 1.58E-02 5.31E-05 4.44E-04 8.71E-05

CS-134 9.OOE-07 4.76E-02 6.92E-03 1.18E-03 4.96E-04 1.49E-03

CS-134M 2.OOE-03 3.59E-04 5.97E-06 4.67E-04

CS-136 6.OOE-06 ____

CS-137 1.OOE-06 9.60E-02 2.11E-02 7.54E-03 8.63E-03 2.80E-03 1.94E-03 8.93E-03

CS-138 4.OOE-04 1.11E-03 5.48E-03 3.24E-03F-18 7.OOE-04 1.OOE-02 1.67E-02 7.56E-04 1.66E-03 2.26E-03 4.06E-04

FE-59 1.OOE-05 2.76E-04LA-140 9.OOE-06MN-54 3.OOE-05 7.46E-03 1.18E-03 4.68E-03 1.54E-04 2.68E-04 3.10E-05 1.96E-04

MO-99 2.OOE-05 3.70E-05N-5 3.OOE-05 6.28E-03 6.5E-04 3.21E-03 1.61E-04 2.33E-06 8.68E-05

NB-97 3.OOE-04 1.35E-03 5.22E-04 6.16E-5 1.06E-05 3.-90E-06 -8.80E-06 5.3GE-06

RB-88 4.OOE-04 8A46E-05 L.1E-02 3.33E-3RB-89 9.OOE-04 7.98E-04 2.34E-04RU-103 3.OOE-05 3.59E-03 1.68E-06 8.41E-04 5.86E.-05_____RU-106 3.OOE-06 8.07E-04 2.88E-03 7.33E-03 1.04E-04SB-124 7.OOB-06 3.86E-02 2.96E-04 1.42E-04 2.34E-04SB-125 3.OOE-05 1.12E-02 1.20E-03 1.95E-03 1.OOE-03 2.12E-02 1.28E-05 1.08E-02

SN-113 3.OOE-O5 1.07E-03 4.20B-05 5.13E-04 3.21E-04 3.07E-06

SR-89 8.OOE-06 2.27E-04 3.46E-05 3.8~9E03 2.68E-03 8.69E-06

SR-90 5.OOE-07 1.29E-03 2.28E-04 2.80E-04 3.50E-04 2.55E-04TC-99M 1.OOE-03 1.75E-05 3.75E-06 3.30E-05T-!-101 2.OOE-03 1.1OE-05TE-131 8.OOE-05 7.98E-05

TE-132 9.OOE-06 5.83E-07 6.94E-05 2.7~4E05 7.19E-06 1.74E-04

W-187 3.OOE-05 3.41E-05

Y~-91M 2.OOE-03ZN-65 5.OOE-06 5.15E-05ZR-95 2.OOE-05 7.95E-05 2.61E-04 2.45E-03 1.58E-05

ZR-97 9.OOE-06 1A49E-06 3.09E-06 1.74E-05

TOTAILC I I,~ I 8.06E+02 I 8.12E+02 I 7.10E+02 I 3.57E+02 I 5.59E+02 I 8.72E+02 I 7.87E+02TOTAL WiOG H-3 ~ ~ 1.37E+00O 5.39E-01 5.12E-011 5.9E-02 I5.65E-02 9.57E-03 5.42E-02

Page 77 of 123 Page77 o 123REFERENCE USE



ODCMRevision17:August 29, 2005

TABLE A-2FRACTIONAL MEC IN LIQUID EFFLUENT

'UC'LID C 19 1819871198811989190 |1991

H-3 .OOE-03 1.27E-03 1.25E-03 1.04E-03 |5.17E-04 8.36E-04 | 1.26E-03 |1.22E-03

1-131 1.OOE-06 1.61E-04 5.75E-05 1.52E-05 2.03E-06 2.65E-06 2.21E-07 2.84E-061-132 1.OOE-04 9.70E-07 1.12E-06 8.53E-07 1.49E-08 1.22E-08 6.43E-10 1.46E-071-133 7.OOE-06 2.86E-05 3.27E-05 2.18E-05 2.51E-06 1.73E-06 6.21E-07 2.24E-061-134 4.OOE-04 1.25E-07 1.69E-07 1.46E-07 8.30E-10 2.65E-091-135 3.00E-05 5.47E-06 6.87E-06 6.01E-06 2.16E-08 4.24E-08

AG-110M 6.00E-06 6.70E-09 7.28E-08 7.55E-07 2.38E-07 1.17E-07 4.12E-08 1.05E-07BA-133 2.OOE-05 1 1 _ 7 _ 1 1 1 1BA-139 2.00E-04 6.33E-11 1.79E-09BA-140 8.00E-06 1.36E-09 O.OOE+00 8.16E-09 1.11E-08

CD-109 6.00E-06 1.62E-08 3.16E-08

CE-139 7.00E-05CE-141 3.00E-05 6.89E-08 3.67E-08

CE-144 3.OOE-06 7.03E-07 1.02E-06 2.30E-07 7.92E-08 4.56E-09 4.98E-09CO-56 6.00 46 _ _____=_

CO-57 6.00E-05 6.62E-08 3.41E-09 7.84E-09 I.22E-09 I.72E-11 9.83E-11

CO-58 2.OOE-05 3.19E-O5 6.94E-07 2.46E-06 4.93E-07 2.33E-07 2.35E-08 2.27E-07

CO-60 3.00E-06 1.51E-04 1.46E-05 3.10E-05 9.86E-06 7.67E-06 6.79E-07 2.86E-06

CR-51 5.00E-04 8.55E-08 9.72E-10 4.63E-08 1.54E-10 1.33E-09 2.52E-10

CS-134 9.OOE-07 8.34E-05 1.18E-05 1.92E-06 7.99E-07 2.57E-06

CS-134M 2.00E-03 _ 2.60E-10 4.46E-12 3.62E-10

CS-136 6.00E-06

CS-137 1.OOE-06 1.51E-04 3.25E-05 1.11E-05 1.25E-05 4.19E-06 2.80E-06 1.38E-05

CS-138 4.00E-04 4.38E-09 2.11E-08 1.19E-08 _

F-18 7.00E-04 2.20E-08 3.50E-08 1.57E-09 3.54E-09 4.67E-09 8.99E-10

FE-59 1.OOE-05 4.05E-08

LA-140 9.00E-06

MN-54 3.00E-05 3.92E-07 6.05E-08 2.29E-07 7.44E-09 1.34E-08 1.49E-09 1.01E-08

MO-99 2.00E-05 2.68E-09

NB-95 3.00E-05 3.30E-07 3.41E-08 1.57E-07 7.78E-09 1.16-10 4.18-09 .1E

NB-97 3.00E-04 7.10E-09 2.68E-09 3.01E-10 5.12E-11 1.94E-11 4.24E-11 2.74E-1I

RB-88 4.00E-04 3.34E-10 4.27E-08 1.22E-08

RB-89 9.00E-04 1.36E-09 3.81E-10 _

RU-103 3.OOE-05 1.89E-07 8.62E-11 4.11E-08 2.83E-09 _

RU-106 3.OOE-06 4.24E-07 1.48E-06 3.58E-06 5.02E-08

SB-12A 7.00E-06 8.70E-06 6.51E-08 2.97E-08 4.84E-08

SB-125 3.00E-05 5.89E-07 6.155-08 9.53E-08 4.83E-08 1.06E-06 6.17E-10 5.58E-07

SN-113 3.OOE-05 5.63E-08 2.15E-09 2.515-08 1.55E-08 1.59E-10

SR-89 8.00E-06 448E-08 6.65E-09 7.13E-07 4.86E-07 1.62E-09

SR-90 5.OOE-07 4.07E-06 7.02E-07 8.21E-07 1.01E-06 7.62E-07

TC-99M 1.00E-03 2.76E-11 5.77E-12 4.78E-11

TC-101 2.00E-03 8.06E-12

TS-131 8.00E-05 1.45E-09

TE-132 9.OOE-06 1.02E-10 1.19E-08 4.46E-09 1.16E-09 3.OOE-08

W-187 3.00E-05 1.65E-09

Y-91M 2.00E-03 _ _

ZN-65 5.00E-06 1.51E-08

ZR-95 2.00E-05 6.27E-09 2.01E-08 1.80E-07 _ _ 1.14E-09

ZR-97 9.00E-06 2.61E-10 5.28E-10 2.80E-09

:Page 78 of 123 REFERENCE USE

POINT BEACH NUCLEAR PLANTOFFSITE DOSE CALCULATION MANUAL t, .S , C U. MANU



TABLE A-2, (cont.)FRACTIONAL MEC IN LIQUID EFFLUENT

ANNUAL VOL(CCs) 6.34E+14 6.50E+14 6.82E+14 6.90E+14 6.69E+14 6.92E+14 6.45E+14TOTFRACTION 1.90E-03 1.41E-03 1.14E-03 5A8E-04 8.54E-04 1.26E-03 1.25E-03FRACT W/O H-3 6.29E-04 1.61E-04 9.83E-05 3.04E-05 1.85E-05 4.41E-06 2.55E-05

TOTALCI 18.06E+402 | 8.12E+02 7.10E+02 3.57E+02 5.59+02 8.72E+02 7.87E+02TOTAL W/O H-3 1.37E+00 5.39B-01 5.12E-01 5.99B-02 5.65B-02 19.57B-03 5.42B-02

TOT CONC(uCiCC) 1.27B-06 1.25E-06 1.04E-06 5.17E-07 8.36E-07 1.26B-06 1.22B-06TCON W/O H-3 2.161-09 8.30E-10 7.51E-10 8.69E-11 8.44E-11 1.38E-11 8.40E-l 1-EMEC 6.70E-04 8.86E-04 9.14E-04 9.45E-04 9.78E-04 9.97E-04 9.80E-04EMEC W/O H-3 3.43E-06 5.14E-06 7.64E-06 2.85E-06 4.56E-06 3.14E-06 3.30B-06


POINT BEACH NUCLEAR PLANT ODCM - -OFFSITE DOSE CALCULATION MANUAL Revision 17 -


APPENDIX B

DERIVATION OF ATMOSPHERIC RELEASE MODE

EFFECTIVE MAXIMUM EFFLUENT CONCENTRATION

B.1.0 Derivation of Atmospheric Release Effective Maximum Effluent Concentration

B1.1 Source Term

The effective maximum effluent concentration (EMEC) for atmosphericeffluents is calculated from the annual releases for the years 1985-1991(Table B-i). Unlike liquid releases, tritium was not omitted from the EMECcalculation. Instead, the EMEC was calculated with H-3 and then modified bythe fraction of non-tritium radionuclides in the effluent.

B1.2 Effective Maximum Effluent Concentration

The maximum concentration of a radionuclide mixture that is allowable at thesite boundary is called the effective maximum effluent concentration (EMEC).The EMEC for an effluent mixture is defined by the equation

EMEC = IC /.S(Ci /MEC)

where

Ci= concentration of radionuclide "i"

MECi = maximum effluent concentration for radionuclide "i" from10 CFR 20, Appendix B, Table 2, Column 1

. (Ci I MECQ) = summation of fractions (SOF), as discussed in Section 3.6,applied to atmospheric releases

The EMEC is calculated from the reference radionuclide mixture which is theradionuclides released during the years 1985 - 1991. The average annual siteboundary concentration for each year was calculated using the highest annualaverage XiQ of 1.56E-06 sec/m3. Then the total EMEC was calculated foreach year (Table C-2). The average total EMEC is8.04E-08±1.31E-08 iiCi/cc with a range of 5.84E-08 to 9.50E-08 plCi/cc.Next, the annual EMEC was modified for the presence of H-3, which is notdetected by the atmospheric RMS, by multiplying each EMEC by the ratio ofthe non H-3 concentration to the total concentration. The annual H-3corrected EMECs were averaged to obtain a value of1.92E-08±1.23E-08 ,uCi/cc with a range of 5.02E-09 to 3.70E-08 gCi/cc.





-

TABLE B-1CURIES IN ATMOSPHERIC EFFLUENT

NULD E 1985! 196.1.. 18< 18 991990. 11

_ _ _ u i3/mi <. _ _ j . I9 _ _ 1 _ _ _ _ I , _ _ _ _ 0A I 991

H-3 1.00E-07 6.71E+01 I 1.20E+02 1.18E+02 1.26E+02 1.42E+02 1.28E+02 1.13E+02

AR-41 1.00E-08 1.27E+00 6.81E-01 2.17E+00 1.96E+00 1.57E+00 1.11+00 1.07E+00

KR-85M 1.00l-07 1.84E+01 6.77E-01 1.18E+00 7.31E-01 2.24E-01 1.85E-01 1.03E-01

KR-85 7.00E-07 1.67E+01 1.32E+00 7.1 1E-01 9.84E-01 3.58E-01 1.78E-01 2.74E-01

KR-87 2.OOE-08 4.78E+00 1.01E+00 2.37E+00 I.48E+00 4.94E-01 4.05E-01 2.31E-01

KR-88 9.00E-09 5.73E+00 1.30E+00 2.72E+00 I.69E+00 5.64E-01 4.49E-01 2.56E-0O

XE-131M 2.00E-06 8.54E-02 _

XE-133M 6.00E-07 3.30E-01 1.38E-01 2.12E-01 3.35E-01 4.94E-03 2.06E-02 3.97E-02

XE-133 5.00E-07 3.45E+01 1.53E+01 2.06E+01 6.04E+01 7.54E+00 1.96E+00 1.60E+01

XE-135M 4.00E-08 5.76E+00 1.27E+00 3.68E+00 2.54E+00 7.37E-01 6.49E-01 3.44E-01

XE-135 7.00E-08 1.19E+01 3.21E+00 5.64E+00 3.53E+00 1.08E+00 1.09E+00 6.03E-01

XE-138 2.00E-08 1.65E+01 2.91E+00 8.87E+00 7.19E+00 2.45E+00 1.99E+00 1.06E+00

AG-IIOM 1.00-10 2.31E-07

BA-133 9.00E-10

BA-139 4.00E-08 _ 1.17E-07

BA-140 2.00E-09 3AIE-07

CD-109 2.00E-10 8.92E-06 1.26E-06 2.28E-04

CE-139 9.00E-10

CE-141 8.00E-10 8.48E-09 _ _

CE-144 2.00E-11 2.04E-06 3.92E-07 3.94E-09

CO-57 9.OOE-10 2.10E-07 2.52E-11 1.13E-08 1.23E-06 4.80E-07

CO-58 1.00E-09 1.57E-04 1.33E-05 1.01-04 3.59E-05 1.69E-04 2.74E-05 3.85E-06

CO-60 5.00E-11 7.94E-05 1.11E-04 1.18E-05 3.64E-04 1.63E-04 3.56E-06 1.06E-04

CR-51 3.00E-08 5.28E-04 7.58E-09

CS-134 2.00E-10 1.18E-03 9.49E-04 5.86E-05 7.27E-05 IJ _OE-03

CS-136 9.00E-10

CS-137 2.00E-10 4.02E-03 2.94E-04 3.08E-04 6.74E-04 2.10E-03 1.91E-04 1.90E-03

CS-138 8.00E-08 9.64E-07 1.92E-06 1.85E-03 1.26E-07 3.44E-06 1.92E-02

F-18 I.OOE-07 1.08E-05 2.52E-04 3.87E-05 3.31E-04 1.10E-05 6.60E-04

FE-59 7.OOE-1O _ 4._7E__9

MN-54 1.00E-09 1.99E-06 1.70E-06 4.86E-05

MO-99 2.00E-09 7.27E-09 2.71E-08

NA-24 7.00E-09 1.39E-04 4.32E-04 4.29E-04

NB-95 2.00E-09 2.52E-06 7.70E-07 5.97E-07 6.25E-08 9.56E-10

NB-97 1.OOE-07 1.60E-08 1.65E-09

RB-88 9.00E-08 4.63E-05 3.46E-05 1.03E-02 4.00E-06 1.81E-05 1.62E-01

RB-89 2.00E-07 4.30E-09

RU-103 9.008-10 1.918-08 1.89E-05

SB-125 7.00E-10 1.25E-07 3.68E-06 9.39E-08

SN-113 8.00E-10 2.16E-08 4.80E-10 _

SR-89 2.00E-10 4.87E-08 1.54E-06 7.70E-07 3.71E-06

SR-90 6.00E-12 1.68E-10 4.30E-06

SR-91 5.OOE-09 _ _

TC-99M 3.00E-07 _ 6.43E-08 2.20E-07 9.24E-07

TC-101 5.00E-07 _ _ _

TE-132 9.00E-10 3.07E-06 7.33E-08 2.34E-06

Y-88 3.008-10 _ 1.28E-10 _

ZN-65 4.00E-10 9.27E-06

ZR-95 4.00E-10 1.31E-06 3.568-09 7A3E-lO

ZR-97 2.008-09 2.97E-10

.IPage 81 of 123 REFERENCE USE




TABLE B-1, (cont.)CURIES IN ATMOSPHERIC EFFLUENT

NULJE IM; ''l 1/985g 1986. -1987 >18S8 ;=X 198R9 - 199 = 01 . 1991

1-131 2.OOE-10 3.44E-03 1.1 IE-03 3.08E-03 5.43E-04 3.18E-04 7.85E-05 3.46E-04

1-132 2.OOE-08 3.75E-03 1.79E-03 2.42E-03 4.78E-04 4.20E-05 1.09E-05 2.95E-05

1-133 1.OOE-09 1.37E-03 6.80E-04 3.04E-03 1.53E-03 1.19E-03 1.13E-04 1.13E-04

1-134 6.OOE-08 1.33E-05 9.32E-041-135 6.OOE-09 5.79E-04 1.09E-04 2.19E-03 9.18E-05 1.26E-05 3.15E-08 1.58E-05

Page~ 82 of 123 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCMOFFSITE DOSE CALCULATION MANUAL :- Revision 17


TABLE B-2FRACTIONAL MEC FOR ATMOSPHERIC EFFLUENT

NUCULE DWjit98753 v MO 11.. m A J990 iJi991H-3 I 3.20E-05 I 5.71E-05 I 5.62E-05 I 6.OOE-05 I 6.76E-05 I 6.iOE-05 I 5.38E-05

AR-41 6.05E-06 3.24E-06 1.03E-05 9.33E-06 7.48E-06 5.29E-06 5.10E-06

KR-85M 8.76E-06 3.22E-07 5.62E-07 3.48E-07 1.07E-07 8.81E-08 4.90E-08

KR-85 1.14E-06 8.98E-08 4.84E-08 6.69E-08 2.44E-08 1.21E-08 I.86E-08

KR-87 I.14E-05 2.40E-06 5.64E-06 3.52E-06 1.18E-06 9.64E-07 5.50E-07

KR-88 3.03E-05 6.88E-06 1.44E-05 8.94E-06 2.98E-06 2.38E-06 1.35E-06

XE-131M 2.03E-09

XE-133M 2.62E-08 I.lOE-08 1.68E-08 2.66E-08 3.92E-10 1.63E-09 3.15E-09

XE-133 3.29E-06 1.46E-06 1.96E-06 5.75E-06 7.18E-07 1.87E-07 1.52E-06

XE-135M 6.86E-06 1.5 1E-06 4.38E-06 3.02E-06 8.77E-07 7.73E-07 4.10E-07

XE-135 8.10E-06 2.18E-06 3.84E-06 2.40E-06 7.35E-07 7.41E-07 4.10E-07

XE-138 3.93E-05 6.93E-06 2.1 lE-05 1.71E-05 5.83E-06 4.74E-06 2.52E-06

AG-llOM |.lOE-10

BA-139 1.39E-13

BA-140 8.12E-12

CD-109 2.12E-09 3.OOE-10 5.43E-08 |_r

CE-141 5.05E-13 _ _________

CE-144 4.86E-09 9.33E-10 9.38E-12

CO-57 i.11E-11 1.33E-15 5.98E-13 6.51E-11 2.54E-1i

CO-58 7.48E-09 6.33E-10 4.81E-09 1.71E-09 8.05E-09 1.30E-09 1.83E-10

CO-60 7.56E-08 1.06E-07 1.12E-08 3.47E-07 1.55E-07 3.39E-09 l.OlE-07

CR-51 8.38E-10 1.20E-14

CS-134 2.81E-07 2.26E-07 1.40E-08 1.73E-08 2.62E-07

CS-136

CS-137 9.57E-07 7.OOE-08 7.33E-08 1.60E-07 5.OOE-07 4.55E-08 4.52E-07

CS-138 5.74E-13 1.14E-12 1.1OE-09 7.50E-14 2.05E-12 1.14E-08

F-18 5.14E-12 1.20E-10 1.84E-11 1.58E-10 5.24E-12 3.14E-10

FE-59 3.31E-13

MN-54 9.48E-11 8.10E-11 _ 2.31E-09

MO-99 1.73E-13 6.45E-13

NA-24 9.46E-10 2.94E-09 2.92E-09

NB-95 6.OOE-11 1.83E-11 1.42E-11 1.49E-12 2.28E-14

NB-97 7.62E-15 7.86E-16

RB-88 2.45E-11 1.83E-11 5.45E-09 2.12E-12 9.58E-12 8.57E-08

RB-89 1.02E-15

RU-103 l.O1E-12 l.OOE-09

SB-125 8.50E-12 2.50E-10 6.39E-12

SN-1 13 1.29E-12 2.86E-14 _

SR-89 1.16E-11 3.67E-10 1.83E-10 8.83E-10

SR-90 1.33E-12 3.41E-08 _

SR-91

TC-99M 1.02E-14 3.49E-14 1.47E-13

TC-IOI I

TE-132 _ _ 1.62E-10 3.88E-12 1.24E-10

Y-88 2.03E-14

ZN-65 1 .1OE-09

ZR-95 1.56E-10 4.24E-13 8.85E-14

ZR-97 7.07E-15 I




ODCM -Revision 17August 29, 2005

TABLE B-2, (cont.)FRACTIONAL MEC FOR ATMOSPHERIC EFFLUENT

NUCUDE -| 1985 1986 ' 1987 1988 . 1989 1990 19911-131 8.19E-07 2.64E-07 7.33E-07 1.29E-07 7.57E-08 1.87E-08 8.24E-081-132 8.93E-09 4.26E-09 5.76E-09 1.14E-09 1.OOE-I0 2.60E-11 7.02E-I11-133 6.52E-08 3.24E-08 1.45E-07 7.29E-08 5.67E-08 5.38E-09 5.38E-091-134 1.06E-11 7.40E-101-135 4.60E-09 8.65E-10 1.74E-08 7.29B-10 I.OOE-10 2.50E-13 1.25E-10

TOTALFRAC 1.49E-04 8.29E-05 1.20E-04 1.11E-04 8.83E-05 7.62E-05 6.67E-05TOTALH3 L17E-04 2.57E-05 6.34E-05 5.13E-05 2.07E-05 1.52E-05 1.29E-05EFF bMEC 5.84E-08 8.49E-08 6.62E-08 8.85E-08 8.46E-08 8.50E-08 9.50E-08W/O H-3 3.70E-08 1.60E-08 1.92E-08 3.46E-08 A8.1E-09 5.02E-09 1.44E-08




APPENDIX C

CALCULATION OF TOTAL DOSE FACTORS

USING

REGULATORY GUIDE 1.109, REV. 1

C.1.0 Calculation of Total Dose Factors Using Regulator Guide 1.109 Methodology

C.1.1 Liquid Release Dose Factors

The equations and values used to calculate the total dose to the maximumexposed individual for each of the liquid release mode pathways evaluatedaccording to Regulatory Guide 1.109, Rev. 1, 1977 methodology is shownbelow. The total dose factor in mrem/Ci released is the sum of all pathwaydoses in mrem/Ci for the following pathways: milk, meat, fish, potable water,and shoreline deposits. The results for an organ is summed for each pathwayand the total presented by age group and target organ in a matrix format foreach radionuclide in Section 5, Table 5.1.1. The derivation of dilution factorsused in the calculations is presented in Appendix D. The highest dose in eachmatrix is used as the dose tracking factor to be used for the monthly trackingof release doses. These values are found in Section 5, Table 5.2.

Note that all of the liquid release dose calculations assume that the dischargerate is 677,000 gpm. Whenever the average discharge rate for the month oryear differs, the final dose calculated must be multiplied by the correctionfactor CF where:

CF = 677,000 gpm / actual average discharge gpm

This correction will produce a greater change during the winter months whenthe circ water flow rates are lower.

C1.1.1 Aquatic Foods

The dose from the eating of fresh fish caught at the edge of the initialmixing zone was calculated using the equation:

Doseapj 1100 MY a QjBipD j eF




where:

Doseapj = the dose to the organ j of an individual of age groupa from all of the nuclides i in pathway p, inmrem/year;

1100 = a factor to convert from Ci-sec/yr-ft to pCi/liter;

Mp = the mixing ratio (reciprocal of the dilution factor) atthe point of harvest of aquatic food, dimensionless;

Uap = a usage factor that specifies the intake rate for anindividual of age group a associated withpathway p, in kg/year;

F = the flow rate of the liquid effluent, in ft3 /sec;

Qi = the release rate of nuclide i, in Ci/year;

Bip = the equilibrium bioaccumulation factor for nuclide iin pathway p, expressed as the ratio of theconcentration in biota (in pCi/kg) to theradionuclide concentration in water (in pCi/1), inliters/kg;

Daipj = the dose factor, specific to a given age group a,nuclide i, pathway p, and organ j, which is used tocalculate the radiation dose from an intake of anuclide, in mrem/pCi;

Xj = the radioactive decay constant of nuclide i, in day1 ;

tp = the average transit time required for nuclides toreach the point of exposure. For internal dose, tp isthe total time elapsed between release of thenuclides and the ingestion of the water, in days.

To calculate the dose per curie released, the equation above wasrearranged and the calculation performed for each nuclide. Therearranged equation is shown below:

Dose.I 1p= 1100 Mp Up BipDeipjeAitP

The values used in the equation above are:




Mp = 0.1136 (Point of harvest of the fresh fish is taken at apoint 1000 m downstream. The plume centerlinedilution factor at this location is 8.8 using RG 1.111methodology. The dilution factor calculations areattached. The factor of 2 allowed for current reversalswas not used.);

Uap = Infant - 0, Child - 6.9, Teen - 16, andAdult - 21 kg/year;

F = 1507 ft3/sec. (677000 gpm);

Bip = Values used are taken from Table A-1 of RG 1.109;

Daipj = Values used are taken from Tables E-l 1 through E-14of RG 1.109;

tp = 0.5 days.

C1.1.2 Irrigated Foods (Meat From Watered Cattle)

The dose from the ingestion of meat from cattle which have beengiven contaminated water was calculated using the equation:

Doseapj, 1100 UpQw A QFiA Daipje-A'ts

where:

Doseapj = the dose to the organ j of an individual of age group afrom all of the nuclides i in pathway p, in mrem/year;

1100 = factor to convert from Ci-sec/yr-ft3 to pCi/liter;

Uap = a usage factor that specifies the intake rate for anindividual of age group a associated with pathway p, inkg/year;

Mp = the mixing ratio (reciprocal of the dilution factor) at thepoint of exposure, dimensionless;

QAW = consumption rate of contaminated water by an animal,in liters/day;




F = the flow rate of the liquid effluent, in ft3l/sec;


FiA = the stable element transfer coefficient that relates thedaily intake rate by an animal to the concentration in anedible portion of animal product, in pCi/liter of meatper pCi/day;

Daipj = the dose factor, specific to a given age group a,nuclide i, pathway p, and organ j, which is used tocalculate the radiation dose from an intake of a nuclide,in mrem/pCi;

Xi = the radioactive decay constant of nuclide i, in day-1

ts = the average time from slaughter to consumption, indays.


osQe = 1100 FUapQA FiA D je-A't'


Mp = 0.1111 (Point at which water is taken from the lake istaken as plume centerline 1 mile downstream. Theplume centerline dilution factor at this location is 9using RG 1.111 methodology.);

Uap = Infant - 0, Child - 41, Teen - 65, andAdult - 110 kg/year;

QAW = 60 liters/day;

F = 1507 ft3/sec. (677000 gpm);

FiA = Values used are taken from Table E-1 of RG 1.109;

Daipj = Values used are taken from Tables E-1 1 through E-14of RG 1.109;

ts = 20 days.




C1.1.3 Irrigated Foods (Milk From Watered Cattle)

The dose from the ingestion of milk from cows which have beengiven contaminated water was calculated using the equation:

Dosepj =1 100MP`UaPUQAWj Q. Fi Daipj eAitt

where:


1100 = factor to convert from Ci-sec/yr-ft3 to pCi/liter;

MP = the mixing ratio (reciprocal of the dilution factor) atthe point of exposure, dimensionless;

Uap = a usage factor that specifies the intake rate for anindividual of age group a associated with pathway p, inliters/year;

QAw = consumption rate of contaminated water by an animal,in liters/day;

F = the flow rate of the liquid effluent, in ft3/sec;

Qi ii= the release rate of nuclide i, in Ci/year;

FiA = the stable element transfer coefficient that relates thedaily intake rate by an animal to the concentration inan edible portion of animal product, in pCi/liter ofmilk per pCi/day;

Daipj = the dose factor, specific to a given age group a,nuclide i, pathway p, and organ j, which is used tocalculate the radiation dose from an intake of anuclide, in mrem/pCi;

= the radioactive decay constant of nuclide i, in day-1

tf = the average transport time of the activity from the feedinto the milk and to the receptor, in days.

'Page 89 of 123 REFERENCE USE

N


August 29, 2005OFFSTE DOSE CALCULATION MANUAL

To calculate.the dose per curie released, the equation above wasrearranged and the calculation performed for each nuclide. Therearranged equation is shown below:

Doseaipj = 1 10 0 Mp Up QAW FA DFipjeAitf

QI F


Mp = 0.1111 (Point at which water is taken from the lakeis taken as plume centerline 1 mile downstream. Theplume centerline dilution factor at this location is 9using RG 1.111 methodology. the dilution factorcalculations are attached. The factor of 2 allowedfor current reversals was not used. This is aconservative assumption.);

Uap = Infant - 330, Child - 330, Teen - 400, andAdult - 310 liters/year;

QAW = 60 liters/day;

F = 1507 ft3 /sec. (677000 gpm);

FiA = Values used are taken from Table E-1 of RG 1.109;

Daipj = Values used are taken from Tables E-1 1 throughE-14 of RG 1.109;

tf = 2 days.

IIPage 90 of 123 REFERENCE USE



C1.1.4 Potable Water

The dose from ingestion of water was calculated using the equation:

Doseapj = 1100 MPU I ZQDipje-t1e

where:

Doseapj = the dose to the organ j of an individual of age groupa from all of the nuclides i in pathway p, inmremniyear;

1100 = a factor to convert from Ci-sec/yr-ft3 to pCi/liter;

MP = the mixing ratio (reciprocal of the dilution factor) atthe point of withdrawal of drinking water,dimensionless;

Uap = a usage factor that specifies the intake rate for anindividual of age group a associated with pathway p,in 1/year;

F = the flow rate of the liquid effluent, in ft3/sec;

Q = the release rate of nuclide i, in Ci/year;

Daipj = the dose factor, specific to a given age group a,nuclide i, pathway p, and organ j, which is used tocalculate the radiation dose from an intake of anuclide, in mrremn/pCi;

Xi= the radioactive decay constant of nuclide i, in day-1

tp = the average transit time required for nuclides toreach the point of exposure. For internal dose, tp isthe total time elapsed between release of the nuclidesand the ingestion of the water, in days.

I.I Page 91 of 123 REFERENCE USE




DoseXip =1100 MPF Daipj e-itPQiF


MP = 0.0384 (Withdrawal point is taken as the Two Riversmunicipal water intake located a distance of 12 milesdownstream. The plume centerline dilution factor atthis location is 26 using RG 1.111 methodology andthe factor of 2 allowed for current reversals. Thedilution factor calculations are attached.);

Uap = Infant - 330, Child - 510, Teen - 510, and Adult - 730liters/year;

F = 1507 ft3 /sec. (677000 gpm);

Daipj = Values used are taken from Tables E-1 1 through E-14of RG 1.109

tp = 2 days (This was calculated using a current speed of12.2 cm/s plus 12 hours to reflect the transport of thewater through the water purification plant anddistribution system.)

C1.1.5 Shoreline Deposits

The dose from exposure to radioactive materials deposited on theshoreline of the lake was calculated using the equation:

Doseapj = 110000 MUpW Q, Ti Daipj eAitp (i - e-'itb)F

where:


110000 = a factor to convert from Ci-sec/yr-ft3 to pCi/liter andto account for the proportionality constant used in thesediment radioactivity model;

. Page 92 of 123 REFERENCE USE




= the mixing ratio (reciprocal of the dilution factor) atthe point of exposure, dimensionless;

Uap = a usage factor that specifies the exposure time for anindividual of age group a associated with pathway p,in hours/year;

W = shoreline width factor, dimensionless;

F = the flow rate of the liquid effluent, in ft3 /sec;


Ti = the radioactive half life of nuclide i, in days;

Daipi = the dose factor, specific to a given age group a,nuclide i, pathway p, and organ j, which is used tocalculate the radiation dose from an intake of anuclide, in mrem/pCi;

= the radioactive decay constant of nuclide i, in dayl;

tp = the average transit time required for nuclides to reachthe point of exposure. For internal dose, tp is the totaltime elapsed between release of the nuclides and theingestion of the water, in days;

tb = the period of time for which the sediment or soil isexposed to the contaminated water, in days.


.;




DQseiF = I110000 Pl F Ti Daipj eAItP(i- e'Aitb)


Mp = 0.01821 (Point of exposure is taken as the Point BeachState Park beach which is located 8000 metersdownstream. The plume shoreline dilution factor atthis location is 54.9 using RG 1.111 methodology.The dilution factor calculations are attached. Thefactor of 2 allowed for current reversals was notused.);

Uap = Infant - 0, Child - 14, Teen - 67, andAdult - 12 hours/year;

W = 0.3;

F = 1507 ft3/sec. (677000 gpm);

Daipj = Values used are taken from Table E-6 of RG 1.109;

= 0.5 day;

tb = 5458 days.

,Page 94 of 123 REFERENCE USE



C1.2 Atmospheric Release Dose Factors: Non-Gaseous

The equations and values used to calculate the total dose to the maximumexposed individual factors for non-gaseous radionuclides released to theatmosphere using Regulatory Guide 1.109, Rev. 1, 1977 is shown below. Thetotal dose factor in mrem/Ci released is the sum of all airborne effluent dosesin mrem/Ci for the following pathways: milk, meat, leafy vegetables, potablewater, and shoreline deposits. A summary of totals is presented by age groupand target organ in matrix format for each radionuclide in Section 5,Table 5-1. The highest dose in each matrix is used as the dose tracking factorto be used for the monthly tracking of release doses. These values are foundin Section 5, Table 5-2.

Note that Section C1.2.1 applies to both tritium and particulates.Sections C 1.2.2 through C 1.2.6 apply only to particulates released to theatmosphere. Atmospheric tritium releases are treated differently.Sections C1.2.7 through C1.2.10 apply to tritium.

C1.2.1 Inhalation of Nuclides In Air

The dose from the inhalation of nuclides in the air was calculatedusing the equation:

Doseia = 3.17E+04Ra(,JZQDR-ja

where:

Dose a = the annual dose to organ j of an individual of age groupa due to inhalation, in mrem/year;

3.17E+04 = the number of pCi/Ci divided by the number ofsec/year;

Ra = the annual air intake for individuals in the age group a,in m3/year;

X/Q = the annual average atmosphere dispersion factor, insec/m (The location at which the dose was calculatedwas the site boundary in the south sector - a distance of1270 meters.);





DFlija = the inhalation dose factor for radionuclide i, organ j,and age group a, mrem/pCi.


DoQea = 3.17 E+ 04 Ra ( DFLj.


Ra = Infant - 1400, Child - 3700, Teen - 8000, and3

Adult - 8000 m /year;

X/Q = 9.36E-07 seconds/m3 (This value taken fromTable I.4-2 of the FSAR, release mode 1B, annualaverage, site boundary.);

DFIija = Values used are taken from Tables E-7 through E-10of RG 1.109.

C1.2.2 Annual Organ Dose From External Irradiation From NuclidesDeposited On the Ground

The organ dose from external irradiation from nuclides deposited onthe ground was calculated using the equation:

Dosej = 1E+ 12(8760)6i SF e DFGij

where:

Dosej = the annual dose to the organ j, in mrem/year;

1E+12 = the number of pCi per Ci;

8760 = the number of hours in a year;

Si = the annual average relative deposition of nuclide i,considering depletion of the plume during transport, inm2, (The location at which the dose is calculated is thesite boundary in the south sector - a distance of1300 meters.);

:Page 96 of 123 REFERENCE USE



Sp = the attenuation factor that accounts for the dosereduction due to shielding provided by residentialstructures, dimensionless;


Xi = the radioactive decay constant of nuclide i, in day-

tb - the time period over which the accumulation isevaluated, in days;

DFGij = the open field ground plane dose conversion factor fororgan j from nuclide i, in mrem-m2/pCi-hour.


Doseij = 1E+ 12 (8760) Ai SF DFGij


= 3 1E-09 m2 (This value taken from Table I.4-2 of theFSAR, release mode 1B, annual average, siteboundary.);

SF = 1 (No structural shielding is assumed.);

tb = 5479 days (15 years);

DFGQj = Values used are taken from Table E-6 of RG 1.109.

V Page 97 of 123 REFERENCE USE



C1.2.3 Annual Organ Dose From Atmospherically Released Nuclides InMilk

The organ dose from atmospherically released nuclides in milk wascalculated using the equation:

Doseja = 2.7 E+ 09 Ua QF8 i Q FnmDFIija e'Aitf {fpfs + eA90i (1 - fpf }

x.fl i + e-A (1 e))1YVAEi PAJ

where:

Doseja = the annual dose to the organ j of an individual in age group afrom a dietary intake of atmospherically released nuclides, inmrem/year;

2.7E+09 = the number of pCi per Ci divided by the number of days peryear;

Ua = the ingestion rate of milk for individuals in age group a, inliters/year;

QF = the amount of feed consumed by a cow per, in kg/day;

= the annual average relative deposition of nuclide i,considering depletion of the plume during transport, in m-2,(The location at which the dose is calculated is the nearestanimal location in the south-southeast sector - a distance of1300 meters.);


xi = the radioactive decay constant of nuclide i, in day-1

tb = the time period over which the accumulation is evaluated, indays;

DFIija = the dose conversion factor for the ingestion of nuclide i,organ j, and age group a, in mrem/pCi;




Fim = the average fraction of the animal's daily intake of nuclide iwhich appears in each liter of milk, in days/liter;

tf = the average transport time of the activity from the feed intothe milk and to the receptor, in days;

fp = the fraction of the year that the animals graze on pasture,dimensionless;

fs = the fraction of the daily feed that is pasture grass when theanimal grazes on pasture, dimensionless;

r = the fraction of the deposited activity retained on crops,dimensionless;

XEi = the effective removal rate constant for nuclide i from crops, indays , where XEi = Xi + XW, and X, is the removal rateconstant for physical loss by weathering;

Xw = 0.0504 day 1;

te = the time period that crops are exposed to contamination duringthe growing season, in days;

Yv = the agricultural productivity, in kg (wet weight)/m ;

Biv = the concentration factor for the uptake of nuclide i inpathway p, expressed as the ratio of the concentration in biota(in pCi/kg) to the nuclide concentration in water (in pCi/liter),in liters/kg;

P = the effective surface density for soil, in kg (dry soil)/m2

For iodines, this factor is changed to 1.4E+09.




ODCM ;Revision 1-7August 29, 2005

To calculate the dose per curie released, the equation above was rearrangedand the calculation performed for each nuclide. The rearranged equation isshown below:

Doseij = 2.7E+9 UaQFi ZFimDFLja&e-A"' {f ,f5 + e '(1 - fpf5 )}Qii

r( - e") + Biv (1- e-itb){

YV'li Pi 'L


Ua = Infant - 330, Child - 330, Teen - 400, and Adult - 310 liters/year;

QF = 50 kg/day;

-2i = 18.8E-09 m (This value taken from Table 1.4-2 of the FSAR,

release mode 1B, grazing season, site boundary.);

Fim = Values used are taken from Table E-1 of RG 1.109;

DFIija = Values used are taken from Tables E-1 1 through E-14 ofRG 1.109;

tf = 2 days;

fp = 0.5;

fs = 0.5;

r = 0.25, 1.0 for iodines, and 0.20 for noble gases, tritium, andcarbon-14;

te = 30 days;

Yv = 0.7 kg/m2;

Biv = Values used are taken from Table E-1 of RG 1.109;

2P = 240 kg/mr;

tb = 5458 days (15 years).




C1.2.4 Annual Organ Dose From Atmospherically Released Nuclides InMeat

The organ dose from atmospherically released nuclides in meat wascalculated using the equation:

Doseja = 2.7 E+ 9 U QF 6i XQIFif DFIija e-At {fIf, + e-90Ai(1 - f(pi f

{ r(I - e-nt) Bi, (1 -1e sib)xs +

t YVAN PA1 J

where:



Ua = the ingestion rate of meat for individuals in age group a, inliters/year;

QF = the amount of feed consumed by a cow per, in kg/day;

8 j = the annual average relative deposition of nuclide i,considering depletion of the plume during transport, in mi2 ,(he location at which the dose is calculated is the nearestanimal location in the south-southeast sector - a distance of1300 meters.);


= the radioactive decay constant of nuclide i, in day






Fif = the average fraction of the animal's daily intake of nuclide iwhich appears in each kilogram of flesh, in days/kg;

ts = the average time from slaughter to consumption, in days;

fp = the fraction of the year that the animals graze on pasture,dimensionless;

fs = the fraction of the daily feed that is pasture grass when theanimal grazes on pasture, dimensionless;


XEi = the effective removal rate constant for nuclide i from crops,in days , where XEi = Xi + , and Xw is the removal rateconstant for physical loss by weathering;

te = the time period that crops are exposed to contaminationduring the growing season, in days;

Yv = the agricultural productivity, in kg (wet weight)/m2;

Biv = the concentration factor for the uptake of nuclide i inpathway p, expressed as the ratio of the concentration in biota(in pCi/kg) to the nuclide concentration in water (inpCi/liter), in liters/kg;

P = the effective surface density for soil, in kg (dry soil)/m2.



POINT BEACH NUCLEAR PLANT ODCMOFFSITE DOSE CALCULATION MANUAL * Revision 17



Doseija = 2.7 E+ 9 Ua QFii XFif DFlija eA'ts {fpf. + e-" 9(1- fpf.)}Qii

f Yvr I PIJ }


Ua = Infant -0, Child -41, Teen - 65, and Adult - 110 kg/year;

QF = 50 kg/day;

Si = 18.8E-09 m2 (This value taken from Table I.4-2 of the FSAR,release mode 1B, grazing season, site boundary.);

Fif = Values used are taken from Table E-1 of RG 1.109;

DFIija = Values used are taken from Tables E- II through E-14 ofRG 1.109;

ts = 20 days;

fp = 0.5;

fs = 1.0;


te = 30 days;


2Yv = 0.7 kg/mr;

P = 240 kg/rm;

-1'?'w = 0.0504 day-;


Page. 103 of 123 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCMOFFSITE DOSE CALCULATION MANUAL, Revision 17


C1.2.5 Annual Organ Dose From Atmosphericallv Released Nuclides InProduce

The organ dose from atmospherically released nuclides in producewas calculated using the equation:

Doseja = 2.7E+9UUfg.jQi DFIjDae1"h {(1 - e)t+ ) (I e-Aitb)l

where:



Ua = the ingestion rate of produce for individuals in age group a, inkg/year;

fg = fraction of produce ingested grown in garden of interest,dimensionless;

= the annual average relative deposition of nuclide i, consideringdepletion of the plume during transport, in m 2, (The location atwhich the dose is calculated is the nearest garden location inthe south-southwest sector - a distance of 1460 meters.);


Xi = the radioactive decay constant of nuclide i, in day-;



th = the holdup time that represents the time interval betweenharvest and consumption of the food, in days;





XEi = the effective removal rate constant for nuclide i from crops, indays , where XEi = Xi + , and XA is the removal rateconstant for physical loss by weathering;


Y = the agricultural productivity, in kg (wet weight)/m ;


P = the effective surface density for soil, in kg (dry soil)/m2


Page, 105 of 123 REFERENCE USE




Doseija = 2.7E+9 Uafgsi EDFijaeih P r(} ) )Qi Yi 1 P2,j


Ua = Infant - 0, Child - 520, Teen - 630, and Adult - 520 kg/year;

fg = 0.76;

i = 18.8E-09 m72 (This value taken from Table I.4-2 of the FSAR,release mode IB, growing season, site boundary.);


th = 60 days;


Xw = 0.0504 dayj;

te = 60 days;

Y = 0.7 kg/m2;


P = 240 kg/m;


Page- 106 of 123 REFERENCE USE



C1.2.6 Annual Organ Dose From Atmospherically Released Nuclides InLeafy Vegetables

The organ dose from atmospherically released nuclides in leafyvegetables was calculated using the equation:

Doseja = 2.7E+9 Uaf 1Si EQDFIija&eAIt r({ ) + eI-}t-YV AEI P21

where:



Ua = the ingestion rate of produce for individuals in age group a, inkg/year;

f = fraction of leafy vegetables ingested grown in garden ofinterest, dimensionless;

= the annual average relative deposition of nuclide i, consideringdepletion of the plume during transport, in rn 2, (The location atwhich the dose is calculated is the nearest garden location inthe south-southwest sector - a distance of 1460 meters.);


= the radioactive decay constant of nuclide i, in day-1



th = the holdup time that represents the time interval betweenharvest and consumption of the food, in days;


POINT BEACH NUCLEAR PLANT ODCMOFFS1ITE DOSE CALCULATION MANUAL Revision 17



XEi = the effective removal rate constant for nuclide i from crops, indays , where XEi = Xi + XW, and Xw is the removal rateconstant for physical loss by weathering;


Yv = the agricultural productivity, in kg (wet weight)/m2;


P = the effective surface density for soil, in kg (dry soil)/m2.



Doseija = 2.7E+9 Uafi1i XDFL-jaeA ith f eAzt-) +Qi IiYvA PAi


Ua = Infant - 0, Child - 26, Teen - 42, and Adult - 64 kg/year;

fi = 1;

Si = 18.8E-09 m72 (This value taken from Table I.4-2 of the FSAR,release mode IB, growing season, site boundary.);


th = 1day;



August 29, 2005OFESITE DOSE CALCULATION MANUAL


xW = 0.0504 dayj;

te = 60 days;

Yv = 0.7 kg/mr;

BiV = Values used are taken from Table E-1 of RG 1.109;

2P = 240 kg/rm;


C1.2.7 Doses from Airborne Tritium other than Inhalation

The calculation methodology for doses from airborne H-3 via themeat, milk and vegetation pathways is different from that ofparticulates because tritium is a vapor and not a particle. Theconcentrations of tritium in vegetation are based on theconcentrations found in the air surrounding the vegetation; and, allother vegetation based pathway doses are calculated from thisquantity. The concentration in vegetation (forage, produce and leafyvegetables) is calculated from the formula (Reg. Guide 1.109, Rev.1, p.1.109-27):

Ct= 3.17E+07 QT[X/Q](0.75)(0.5/H)

where:

QT = annual release rate of tritium in i2i/year;

[x/Q] = annual average atmosphere dispersion factor, In sec/m3 (Thelocation at which the dose was calculated was the site boundaryin the south sector, a distance of 1270m);

3.17E+07 = (1.OE+12 pCj/Ci) (1.OE+03 gAig) / (3.1SE+07 sec/yr)

0.75 = fraction of plant mass which is water;

0.5 = fraction of concentration of tritium in plant water to concentrationof tritium in atmospheric water;

H = absolute humidity of atmosphere in g/m3





Inserting the following values into the formula:

[X/Q] = 9.36E-07 sec/m3 (from Table I.4-2 of the FSAR, releasemode IB, annual average site boundary);

H = 5.5 g/m3 (from E. L. Entier (1980), Health Physics 39:318-320).

yields

Ct, = 2.0230 QT

which then is used to calculate doses from leafy vegetables and produce aswell as from milk and meat results for cattle ingestion of vegetation with theH-3 concentration.

C1.2.8 Annual Organ Dose from Atmospherically Released Tritium inProduce

Concentrations of tritium in vegetation are based on its concentrationin the air surrounding the vegetation as defined above in C1.2.7. Thedoses are calculated using the equation:

Doseja = DFIjaUafgCt,

where:

Doseja = the annual dose to the organ j of an individual in age group afrom a dietary intake of atmospherically released nuclides inmrem/yr,

DF~ja = the dose conversion factor for the ingestion of tritium inorgan j and age group a in mrem/yr;

Ua = ingestion rate for produce for individuals in age group a;

fg = fraction of produce ingested;

Ct, = concentration of tritium in vegetation, defined as 2.023 QT.

IPage 1 10 of 123 REFERENCE USE



To calculate the dose per curie released, the equation above is rearranged andthe calculation performed. The rearranged equation is shown below:

Doseja = 2.023 DFljaUafgQT


DFIja = values taken from Tables E-ll through E-14 of RG 1.109;

Ua = Infant-0, Child-520, Teen-630, Adult-520;

fg = 0.76;

C1.2.9 Annual Organ Dose from Atmospherically Released Tritium in Milk

The organ dose is calculated using the equation:

Doseja = DFIjaUaCtm

where Ctm is the concentration of tritium in milk which is calculatedusing the formula:

Ctm = FmCtvQexp(-Xttf).

Substituting Ct. into the dose formula, the following equationresults:

Doseja = DFIjaUBFmCtvQF exp(-Xttf)

where:

Doseja = the annual dose to the organ j of an individual in age group afrom a dietary intake of atmospherically released nuclides inmrem/yr;

DPIja = the dose conversion factor for the ingestion of tritium inorgan j and age group a in mrem/yr;


Fm = average fraction of animal's daily intake of tritium which appearsin milk (days/liter);

Ctv, = concentration of tritium in animal's feed (since the formula for theconcentration of tritium in vegetation does not depend on time,there is no distinction made between pasture grass and storedfeeds);

QF = amount of feed consumed by animal per day;

Page 1 11 of 123 REFERENCE USE



tf = average transport time from feed into milk and to receptor;

Xt = radiological decay constant for tritium.


__4ja = 2.023 DFIjaUaFmQF exp(-Xttf)QT

The values used in the above equation are:

DFIja = values taken from Tables E-l l through E-14 of RG 1.109;


Fm = 1.OE-02 days/liter (from RG 1.109 Table E-1);

Ctv = 2.0230 QT pCilg;

QF = 50 kg/day;

tf = 2 days;

Xt = 0.000154 days-.

C1.2.10 Annual Organ Dose from Atmospherically Released Tritium in Meat

The organ dose is calculated using the equation:

Doseja = DFljaUaCtf

where Ctf is defined as the concentration of tritium in meat which iscalculated using the formula:

Ctf = Ff CtvQF exp(-"ttS)

When this is inserted into the dose formula, the following equationresults:

Doseja = DFIjaUaFf CtVQF exp(-Xtt3)

where:

Doseja = the annual dose to the organ j of an individual in age group afrom a dietary intake of atmospherically released nuclides inmrem/yr;

DFIja = the dose conversion factor for the ingestion of tritium in organ jand age group a in mrem/yr;

Page 1 12 of 123 REFERENCE USE


IOFFSITE DOSE CALCULATION MANUAL



Ff = fraction of animal's daily intake of tritium which appears in eachkilogram of flesh (days/kg);

Ctv = concentration of tritium in animal's feed (since the formula for theconcentration of tritium in vegetation does not depend on time,there is no distinction made between pasture grass and storedfeeds);

QF = amount of feed consumed by animal per day;

t, = average time from slaughter to consumption;

Xt = radiological decay constant for tritium.


Doseia = 2.023 DFIjaUaFfQFexp(-Xtts)QT


DFIja = valuestakenfromTablesE-ll throughE-14ofRG 1.109;


Ff = 1.2E-02 days/kg;

Ct, = 2.0230 Qr pCi/g;

QF = 50 kg/day;

ts= 20 days;

Xt = 0.000154 days- .





C1.3 Atmospheric Release Dose Factors: Noble Gases

The equations and values used to calculate the total dose factors for noblegases released to the atmosphere using Regulatory Guide 1.109, Rev. 1, 1977is shown below. The dose factor in mrem/Ci and mrad/Ci released for eachradionuclide is presented in Section 5, Table 5-1.

C1.3.1 Annual Gamma and Beta Air Dose From All Noble Gas Releases

The dose from the submersion of individuals in air containing noblegases was calculated using the equation:

DoseyorDose-8 = 3.17E+04( ZQ(Fir or DFIP)

where:

Dosey orDosep

3.17E+04

XIQ

Qi

the annual gamma and beta air dose, inmrad/year;

the number of pCi/Ci divided by the number ofsec/year;

the annual average atmosphere dispersionfactor, in sec/m 3 (The location at which the dosewas calculated was the site boundary in thesouth sector-a distance of 1270 meters.);

the release rate of nuclide i, in Ci/year;

DFrorDF-8 = the gamma and beta air dose factors for auniform semi-infinite cloud of radionuclide i, inmrad-m3/pCi-year.

.IIPage 114 of 123 REFERENCE USE





DoserorDosef'- 3.17E+04(i-DF, orDF{)


X/Q = 9.36E-07 seconds/m3 (This value taken fromTable I.4-2 of the FSAR, release mode 1B,intermittent, annual average, site boundary.);

DEf orDF1 ' = Values used are taken from Table B-I of

RG 1.109.

C1.3.2 Annual Skin Dose From All Noble Gas Releases

The skin dose from the submersion of individuals in air containingnoble gases was calculated using the equation:

Dose = 3.I7E+ 04 ( 1 -1.1 SF XQ DFr + FQ DFSiJ

where:

Dose - the annual skin dose due to immersion in a semi-infinitecloud, in mren/year;

3.17E+04 = the number of pCi/Ci divided by the number of sec/year;

1.11 = the average ratio of tissue to air energy absorptioncoefficients;

Sp = the attenuation factor that accounts for the dose reductiondue to shielding provided by residential structures,dimensionless;

X/Q = the annual average atmosphere dispersion factor, insec/m3 (The location at which the dose was calculatedwas the site boundary in the south sector - a distance of1270 meters.);


POINT BEACH NUCLEAR PLANT ODCM -OFFSITE DOSE CALCULATION MANUAL Revision 17



DFj7 = the annual gamma air dose factor for a uniform

semi-infinite cloud of nuclide i, in mrad-m3/pCi-year;

DFSi = the beta skin dose factor for a semi-infinite cloud of2nuclide i, which includes the attenuation by 7 mg/cm of

3skin, in mrem-m /pCi-year.


Dosei =3.17E+04 (zJ(i.I 1SFDFIr + DFSi)Qi



X/Q = 9.36E-07 seconds/m 3 (This value taken fromTable I.4-2 of the FSAR, release mode IB, annualaverage, site boundary.);

DFY = Values used are taken from Table B-I of RG 1.109;

DFSi = Values used are taken from Table B-I of RG 1.109.

C1.3.3 Annual Total Body Dose From All Noble Gas Releases

The total body dose from the submersion of individuals in aircontaining noble gases was calculated using the equation:

Dose = 3.17E+04SF( JXQiDFBi

where:

Dose = the annual total body dose due to immersion in asemi-infinite cloud, in mrem/year;

3.17E+04 = the number of pCi/Ci divided by the number ofsec/year;

IIPage 116 of 123 REFERENCE USE



SF = the attenuation factor that accounts for the dosereduction due to shielding provided by residentialstructures, dimensionless;

XIQ = the annual average atmosphere dispersion factor, insec/m3 (The location at which the dose was calculatedwas the site boundary in the south sector - a distanceof 1270 meters.);


DFBj = the total body dose factor for a uniform semi-infinitecloud of nuclide i, which includes the attenuation of5 glcm of tissue, in mrem-m3/pCi-year.


Dose1 = 3.17E+04SF(, KJDFBiQi Q



/Q = 9.36E-07 seconds/m 3 (This value taken fromTable 1.4-2 of the FSAR, release mode 1B, annualaverage, site boundary.);

DFBi = Values used are taken from Table B-I of RG 1.109.




APPENDIX D

DERIVATION OF DILUTION FACTORS

USING

REGULATORY GUIDE 1.113

D1.0 Liquid Effluent Dilution Factor Calculations

D1.1 Methodology

The dilution factors used for calculating the doses from liquid effluentreleased to Lake Michigan were calculated using the methodology ofRegulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents fromAccidental and Routine Reactor Releases for the Purpose of ImplementingAppendix I." The parameters used in the calculation and the results of thecalculation are given in Table D-1. The results are presented graphically inFigure D-1.

The centerline and shoreline values were calculated using Reg Guide 1.113formulae 17 and 18 which apply to discharges to the Great Lakes. (Theformulae are not presented here. See Section 5 of the PBNP FSAR for theformulae and origin of values used.) These results are applied as calculatedfor fish caught near PBNP. But for other pathways, an extra factor of two (2)is applied to account for current reversals which occur in Lake Michigan asdescribed in the Appendix L Section 5, of the PBNP FSAR.

Page,118 of 123 REFERENCE USE



TABLE D-1SURFACE DILUTION FACTORS

LIQUID EFFLUENTS IN A LARGE LAKE

Downstream Distance Plume Centerline Shoreline(meters)

10 8.8120 8.8130 8.8140 8.8150 8.8160 8.8170 8.8180 8.8190 8.81

100 8.81200 8.81300 8.81400 8.81500 8.81600 8.81700 8.81800 8.81900 8.81

1000 8.81 1220002000 8.86 17583000 9.01 4014000 9.25 1865000 9.53 1166000 9.85 83.87000 10.2 65.98000 10.5 54.99000 10.8 47.4

10000 11.1 42.120000 14.0 2430000 16.1 20.140000 17.7 18.750000 18.8 18.360000 19.6 18.270000 20.3 18.380000 20.9 18.690000 :21.4 18.9

100000 21.9 19.2200000 25.9 23.2300000 29.2 26.9400000 32.3 30.3500000 35.2 33.3600000 37.8 36.0700000 40.2 38.6800000 42.6 41.0900000 44.8 43.3

1000000 46.9 [ 45.5

NOTE: These values were calculated using the equation described In Section 5.2 of the PBNP FSAR and the following values:

21E = 900 cm/sec zs = 0 meters

x = 2 cm2/sec d = 10 metersU = 12.2 cm/sec h = 10metersy 152.5 meters b = 305 meters

and a discharge rate of 42.2 m3lsec.


Dilution Factor at SurfaceLiquid Effluents in a Large Lake

1.OE+06

1 .OE+05

1.OE+04

1 .OE+03

I.OE+02

1.OE+O 1

DF per Unit Release Rate

zQ T1.P.t V

a t0 e

0 t

E tO

>t'0

9 '(

5 I

8Lo

) -0�jJ �:) R471

P.4

1)

=3

I

9 vZ:9:

4:-I

;:5.880- Q

-a

I

tri

1.OE+OO'1.OE+01 1.OE+02 1.OE+03 1.OE+04 1.OE+05 1.OE+06

Downstream Distance (in meters)Area source, width 305 m and height 10 m I



D1.2 Dilution Factor Twelve Miles Downstream: Two Rivers Water Intake

The dilution factor used at the Two Rivers water intake twelve milesdownstream from PBNP included the factor of two described in Section D1.1.However, instead of using the straight centerline dilution factor shown inTable 1, the weighted average dilution factor calculated over the width of theplume was used.

This approach was used for the following reasons. First, the path that thecurrent takes to reach the Two Rivers water intake is not straight. In order toreach Two Rivers, the water must flow southeast around Point Beach StatePark, which juts into Lake Michigan, and then curves back 90 degrees towardsTwo Rivers. As a result of this deviation from straight line flow, any part ofthe plume or possibly none of the plume would impinge upon the intakestructure.

Second, there is a difference in the distance offshore of the PBNP dischargeand the Two Rivers water intake. The Two Rivers water intake is located5080 feet offshore. By contrast, PBNP discharges close to the shorelinethrough two flumes, one directed north and one directed south, and is modeledas a source that extends 1000 feet out into the lake from the shoreline.

Based on these two considerations, it was concluded that the weighted averagedilution across the width of the plume as it diverges while flowing southwould constitute a better estimate of the dilution factor instead of thecalculated for the centerline of an area source as is assumed for the FSARcalculation. The calculation and the values used are shown below.

The average dilution factor at 12 miles downstream was calculated in thefollowing manner:

1. The standard deviation of the radionuclide concentration in the ydirection at 12 miles downstream on the surface of the lake wascalculated. This calculation used the following formula:

2 xexxay u

where.2

e Y = lateral turbulent diffusion coefficient in cm 2/sec

x = the downstream distance in cm

u = current in cm/sec




ODCM- Revision 17

August 29, 2005

Substituting the values for E Y, x, and u of 900 cm 2/sec, 19308 m, and12.2 cm/sec, respectively, into the equation yields

2 c2x90cm x19308mx100-

sec m

1 0 0 cmm

= 168.8 meters

2. At distances of 0.1a, 0.2a, etc., off the plume centerline, the dilutionfactor was calculated using the equation shown in Section 5.2 of thePBNP FSAR. The distances off the plume centerline, the calculateddilution factor, and the fraction of the area under the normal distributioncurve is listed below.

Distance Off Plume Centerline

Fraction ofStandard

Deviation

EquivalentDistance

(m)

Fraction of TotalArea Under the

Curve for Interval Dilution Factor

0.1c0.2cy0.3cy0.4c0.5cr0.6cr0.7cr0.8cr0.9crL.ocr1.1cr1.2cr1.3cr1.4cr1.5cr

1.75cr2.0Oc

2.25cr2.5cr3.0c

16.933.850.667.584.4

101.3118.1135.0151.9168.8185.6202.5219.4236.3253.2295.4337.6379.8421.9506.3

0.0800.0800.0780.0750.0720.0680.0650.0600.0560.0510.0460.0420.0370.0320.0280.0530.0350.0210.0120.010

13.814.014.314.715.215.816.617.618.820.221.923.926.329.232.644.764.798.4

158.4482

Totals 1.00

Page.122 of 123 REFERENCE USE




* It is assumed that the standard deviation of the radionuclide concentrationsacross the plume can be represented by a normal distribution curve. The fractionof the total area under the curve is that fraction of the area under the curve thatlies between, for example, the interval 0.la and 0.2a which also includes thearea of the curve in the interval -0.1 a and -0.2a.

The average dilution factor over the width of the plume was calculated bymultiplying the dilution factor at each of the locations off of the plume centerlineby the fraction of the total area of the curve occupied by that interval and thensumming over all the intervals. An average dilution actor of 29 was calculated.


ENCLOSURE 3

Environmental Manual (EM)Revision 18

Issued September 2005

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