ML051580487

Offsite Dose Calculation Manual, Revision 16

ML051580487
Person / Time
Site:	Point Beach
Issue date:	10/29/2004
From:	Nuclear Management Co
To:	Office of Nuclear Reactor Regulation
References
Download: ML051580487 (123)

Text

.~ (I ODCM OFFSITE DOSE CALCULATION MANUAL DOCUMENT TYPE: Controlled Reference CLASSIFICATION: N/A REVISION: 16 EFFECTIVE DATE: October 29, 2004 REVIEWER: Plant Operations Review Committee (PORC)

APPROVAL AUTHORITY: Plant Manager PROCEDURE OWNER (title): Group Head OWNER GROUP: Chemistry Verified Current Copy:

Signature Date Time List pages used for Partial Performance Controlling Work Document Numbers

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL " Revision 16 .,,

October 29, 2004i OFFSITE DOSE CALCULATION MANUAL 2 2004 TABLE OF CONTENTS SECTION TITLE PAGE 1.0 OFFSITE DOSE CALCULATION MANUAL ADMINISTRATION ......................... 7 1.1 Purpose ......................................................... 7 1.2 General Responsibilities ....................................................... 7 1.3 Manual Revisions ....................................................... 8 1.4 Audits ...................................................... 8 2.0 RADIATION MONITORING SYSTEM AND RELEASE ACCOUNTING .............. 8 3.0 METHODOLOGY FOR DETERMINING ALARM SET POINTS ............................ 13 3.1 Introduction ....................................................... 13 3.2 Objective ...................................................... 13 3.3 Alert Set Point Guidelines ....................................................... 13 3.4 Alarm or Trip Set Point Guidelines ...................................................... 13 3.5 Monitor Calibration and Calibration Constant Determination ...................................... 14 3.6 Determination of the Effective Maximum Effluent Concentration (EMEC) for Liquid Releases ............ 15 3.7 Determination of Liquid Effluent Monitor Alarm Set Point. 17 3.8 Determination of EMEC for Atmospheric Releases ......................................... .......... 21 3.9 Determination of Gaseous Effluent Monitor Alarm Set points ..................................... 22 3.10 Determination of Maximum Release Rates ................................................... 24 4.0 DEMONSTRATING COMPLIANCE WITH 10 CFR 50, APPENDIX I ................... 28 4.1 Introduction .................................................... 28 4.2 Dose Limits ..................... 28 4.3 Release Limits .29 4.4 EPA Regulations .30 5.0 CALCULATION AND COMPARISON OF EFFLUENT RELEASES TO RELEASE LIMITS .30 5.1 Appendix I Dose Calculations ...................... 30 5.1.1 Liquid Release Mode .30 5.1.2 Atmospheric Release Mode: Radioiodine, Tritium, and Particulates .50 5.1.3 Atmospheric Release Mode: Noble Gases .68 6.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM .70 Page 2 of 123 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM' OFFSITE DOSE CALCULATION MANUAL 'Revision 16

-.'October 29, 2004 OFFSITE DOSE CALCULATION MANUAL '

TABLE OF CONTENTS SECTION TITLE PAGE 7.0 RADIOLOGICAL EFFLUENT CONTROLS PROGRAM .70 8.0 RADIOLOGICAL IMPACT EVALUATION OF SEWAGE TREATMENT SLUDGE DISPOSAL .............. 70 8.1 Basis, Commitments, and Actions ................................... 70 8.1.1 Basis ................. .. 70 8.1.2 Basis for NRC Commitment Modification .70 8.1.3 Modification . 71 8.1.4 Exposure Evaluations .................... 71

'- 8.2 Procedure .... ';72 8.2 r c d r .. .. .......................... .. .............................................. 72

- 8.3 Administrative Requirements.; ...................... 73 Complete records of eachcontaminated -8.3.1 disposal shall be kept as follows: ..... 73 APPENDIX A, DERIVATION OF LIQUID RELEASE PATHWAY

- EFFECTIVE MAXIMUM EFFLUENT CONCENTRATION ................................. 75 A.1.0 Derivation of Liquid Release Effective Maxim'um Effluent Concentration ................. 75 A.1.1 SourceTerm ............... . 75 A.1.2 Effective Maximum Effluent Concentration .................................... 75 APPENDIX B 'DERIVATION OF ATMOSPHERIC RELEASE MODE EFFECTIVE MAXIMUM EFFLUENT CONCENTRATION ................................. 80 B.1.0 Derivation of Atmospheric Release Effective Maximum Effluent Concentration ....... 80 B-' -SourceTerm ................  ; 80 B 1.2, Effective Maximum Effluent Concentration .................................... 80

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_.. 114 POINT BEACH NUCLEAR PLANT ODCM- . -

OFFSITE DOSE CALCULATION MANUAL Revision 16--a October 29, 2004 OFFSITE DOSE CALCULATION MANUALDO,.

TABLE OF CONTENTS SECTION TITLE PAGE APPENDIX C CALCULATION OF TOTAL DOSE FACTORS USING-REGULATORY GUIDE 1.109, REV. 1......................................................... 85 C.1.0 Calculation of Total Dose Factors Using Regulatory Guide 1.109 Methodology ........ 85 C.1.1 Liquid Release Dose Factors ......................................................... 85 C1.1.1 Aquatic Foods ................. ........................................ 85 C1.1.2 Irrigated Foods (Meat From Watered Cattle) .................................. 87 C1.1.3 Irrigated Foods (Milk From Watered Cattle) .................................. 89 C1.1.4 Potable Water ......................................................... 91 C1.1.5 Shoreline Deposits ......................................................... 92 C1.2 Atmospheric Release Dose Factors: Non-Gaseous . 95 C1.2.1 Inhalation of Nuclides In Air ...................... ...................... 95 C1.2.2 Annual Organ Dose From External Irradiation From Nuclides Deposited On the Ground ............................................ 96 C1.2.3 Annual Organ Dose From Atmospherically Released Nuclides In Milk .98 C1.2.41 Annual Organ Dose From Atmospherically Released Nuclides In Meat .101 C1.2.5 Annual Organ Dose From Atmospherically Released Nuclides In Produce .104 C1.2.6 Annual Organ Dose From Atmospherically Released Nuclides In Leafy Vegetables .................................. 107 C1.2.7 Doses from Airborne Tritium other than Inhalation ...................... 109 C1.2.8 Annual Organ Dose from Atmospherically Released Tritium in Produce .110 C1.2.9 Annual Organ Dose from Atmospherically Released Tritium in Milk .111 C1.2.10 Annual Organ Dose from Atmospherically Released Tritium in Meat .112 C1.3 Atmospheric Release Dose Factors: Noble Gases . .114 C1.3.1 Annual Gamma and Beta Air Dose From All Noble Gas Releases .114 C1.3.2 Annual Skin Dose From All Noble Gas Releases .115 C1.3.3 Annual Total Body Dose From All Noble Gas Releases ............... 116 I Page 4 of 123 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL i - '. IRevision 16

'I, October 29, 2004 OFFSITE DOSE CALCULATION MANUAL TABLE OF CONTENTS SECTION TITLE PAGE APPENDIX D DERIVATION OF DILUTION FACTORS USING REGULATORYGUIDE1.113 ................................ 118 D1.0 Liquid Effluent Dilution Factor Calculations ..................................... 118 D1.1 Methodology .................................... 118 D1.2 Dilution Factor Twelve Miles Downstream: Two Rivers Water Intake .......... 121

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I C . . ..

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POINT BEACH NUCLEAR PLANT - ODCM-- .-

OFFSITE DOSE CALCULATION MANUAL ..X,(. Revision 16.X 20 4 . .

October 29, 2004 OFFSITE DOSE CALCULATION MANUAL .- I ~;

LIST OF TABLES AND FIGURES SECTION TITLE PAGE SECTION 2.0 TABLE 2-1 RADIOACTIVE LIQUID WASTE EFFLUENT MONITORS ..................... 9 TABLE 2-2 RADIOACTIVE GASEOUS WASTE EFFLUENT MONITORS ............... 10 l FIGURE 2-2 RADIOACTIVE GASEOUS WASTE EFFLUENT MONITORS ............... 12 SECTION 3.0 TABLE 3.7-1

SUMMARY

OF LIQUID DILUTION AND EFFLUENT PATHWAY FLOW RATES .................................................. 18 TABLE 3.7-2 LIQUID PATHWAY MONITOR CALCULATED DEFAULT SET POINTS .................................................. 20 TABLE 3.9-1

SUMMARY

OF GASEOUS EFFLUENT PATHWAY DISCHARGE DEFAULT .................................................. 22 TABLE 3.9-2 ATMOSPHERIC PATHWAY MONITOR DEFAULT RMS SET POINTS .................................................. 23 Table 3.10-1 mrem from all radionuclides (1985 - 1991 average) ...................................... 25 Table 3.10-2 mrem from I-131 and I-133 (2.42E-03 Ci) .................................................. 25 Table 3.10-3 mrem from H-3 (116.3 Ci) .................................................. 25 Table 3.104 mrem from all radionuclides except H-3 and radioiodines (2.15E-03 Ci) .................................................. 26 Table 3.10-5 mrem from Cs-134 and Cs-137 (1.84E-03 Ci) ............................................... 26 Table 3.10-6 mrem from Co-57, Co-58, and Co-60 (1.93E-04 Ci) ..................................... 26 SECTION 5.0 TABLE 5.1-1 LIQUID EFFLUENT DOSE FACTOR .................................................. 32 TABLE 5.1-2 ........ AIRBORNE EFFLUENT DOSE FACTOR 51 TABLE 5.1-3 ACTIVITY TO DOSE CONVERSION FACTORS FOR NOBLE GASES. 69 APPENDIX A TABLE A-1 CURIES RELEASED IN LIQUIDS ................................. 77 TABLE A-2 FRACTIONAL MEC IN LIQUID EFFLUENT ................................. 78 APPENDIX B TABLE B-I CURIES IN ATMOSPHERIC EFFLUENT ......................................... 81 TABLE B-2 FRACTIONAL MEC FOR ATMOSPHERIC EFFLUENT .......................... 83 APPENDIX D TABLE D-1 SURFACE DILUTION FACTORS LIQUID EFFLUENTS IN A LARGE LAKE ......................................... 119 FIGURE D-1 DILUTION FACTOR AT SURFACE .......................................... 120 Page 6 of 123 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 16

October 29, 2004 OFFSITE DOSE CALCULATION MANUAL 1.0 OFFSITE DOSE CALCULATION MANUAL ADMINISTRATION 1.1 Purpose The PBNP Offsite Dose Calculation Manual contains the current methodology and parameters for the calculation of offsite doses due to radioactive gaseous and liquid effluents. This manual describes' a methodology for demonstrating compliance with 10 CFR 50, Appendix I dose limits. Compliance with Appendix I is demonstrated by periodic calculation of offsite doses based on actual plant releases and comparison to Appendix I dose limits.

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

The manual also details the methodology for evaluating the radiological impact of sewage treatment sludge disposal. This methodology addresses the commitments made to the United States Nuclear Regulatory Commission in our application dated October 8, 1987 (NRC-87-104) and accepted by the USNRC in a letter dated January 13, 1988. This application was submitted in accordance with the provisions of 10 CFR 20.302(a). Dose limits are established in the application to ensure the health and safety of the maximally exposed memb6r of the general public and the inadvertent intruder. 10 CFR 50, Appendix I dose limits do not apply to sewage treatment sludge disposal.

1.2 General Responsibilities' The primary responsibility for the implementation of the PBNP offsite dose calculation program and for any actions required by the program resides with Chemistry. Chemistry will provide the technical, regulatory, licensing, and administrative support necessary to fulfill the requirements of this'm'anual. The calculation of offsite doses and analysis of l data are Chemistr'y responsibilities.

The'Manager, PBNP is'res'po'nsible for assuring that Radiation Monitoring System alarm set points are established and maintained in accordance with the methodologies outlined in this manual. The Manager, PBNP is also responsible for assuring the performance of periodic release summaries for the purpose of demonstrating compliance with PBNP effluent release limits.

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EAL POINT BEACH NUCLEAR PLANT ODCM OFFS1TE DOSE CALCULATION MANUAL Revision.16 October 29, 2004 OFFSITE DOSE CALCULATION MANUAL 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. This documentation shall contain sufficient information to support the changes(s) together with the appropriate analyses or evaluations justifying the changes(s), and a determination that the change(s) maintain the levels of radioactive effluent control required by 10 CFR 20.1302,40 CFR 190, 10 CFR 50.36a, and 10 CFR 50, Appendix I, and do not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations. These changes shall become effective after receiving concurrence from the Plant Operations Review Committee (PORC) and approval of the Plant Manager, and shall be submitted to the NRC in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Annual Monitoring Report for the period of the report in which any change in the ODCM was made. Each change shall be identified by markings 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 An audit of the activities encompassed by the ODCM, the Radiological Effluent Control Program, and the Radiological Environmental Monitoring Program and its implementing procedures shall be performed. Planning and scheduling of audits of the ODCM shall be performed in accordance with site Quality Assurance Program procedures. The results of the audit shall be transmitted to the Chief Nuclear Officer and the Chairman of the Offsite Review Committee.

2.0 RADIATION MONITORING SYSTEM AND RELEASE ACCOUNTING A computerized Radiation Monitoring System (RMS) is installed at Point Beach Nuclear Plant (PBNP). The RMS includes area, process, and effluent monitors. A description of those monitors used for liquid and gaseous effluents is presented in Tables 2-land 2-2. The liquid and gaseous waste processing flow paths, equipment, and monitoring systems are depicted in Figures 2-1 and 2-2. Calibration of the RMS detectors is accomplished in accordance with procedures contained in the PBNP Health Physics Calibration Manual. The set point methodology is described in Section 3 of this manual.

The RMS is designed to detect and measure liquid and gaseous releases from the plant effluent pathways. The RMS will initiate isolation and control functions on certain effluent streams identified in Tables 2-1 and 2-2. Complete monitoring and accounting of nuclides released in liquid and gaseous effluents is accomplished with the RMS together with the characterization of nuclide distributions by laboratory analysis of grab samples. Sampling frequencies and analysis requirements 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 PBNP Release Accountability Manual.

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POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 16 October 29, 2004 OFFSITE DOSE CALCULATION MANUAL TABLE 2-1 RADIOACTIVE LIQUID WASTE EFFLUENT MONITORS CHANNEL NumBER NAME- CONTROL FUNCTION DETECCTOR TYPE 1 (2) RE-216 Containment Fan Coolers Liquid None Scintillation

._______________ _ .Monitors .,_ _ _ _ _ _ _ _ _ _ _ _ . _ . _:

RE-218 - Waste Disposal System Liquid Monitor Shuts waste liquid overboard 'Scintillation 1 (2) RE-219 Steam Generator Blowdown Liquid Shuts steam generator blowdown isolation valves, Scintillation .

Monitors blowdown tank outlet valves and steam generator sample valves . . . .

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

... ,. ., -. .Monitor -......

1 (2) RE-229 Service Water Discharge Monitors None Scintillation RE-230 --- - Waste Water Effluent Monitor - None . - Scintillation 1 (2) RE-222 Steam Generator Blowdown Tank Shuts steam generator blowdown isolation valves GM Tube Outlet Monitor  : and blowdown tank outlet valves Page 9 of 123 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 16 October 29, 2004 OFFSITE DOSE CALCULATION MANUAL TABLE 2-2 RADIOACTIVE GASEOUS WASTE EFFLUENT MONITORS CHANNELNuMBER l NAME CONTROLFUNCTION TDETECrORTYPE 1 (2) RE-212 Containment Noble Gas Monitor Actuates containment ventilation isolation Scintillation RE-214 Auxiliary Building Exhaust Ventilation Shuts gas release valve and shifts auxiliary Scintillation Noble Gas Monitor building exhaust through carbon filters 1 (2) RE-215 Condenser Air Ejector Noble Gas None Scintillation Monitors RE-225 Combined Air Ejector Low-Range None Scintillation Noble Gas Monitor RE-221 Drumming Area Vent Noble Gas None Scintillation Monitor RE-224 Gas Stripper Building Exhaust Noble None Scintillation Gas Monitor 1 (2) RE-305 Unit 1 and 2 Purge Exhaust Noble Gas Containment ventilation isolation Scintillation Monitors (Channel 5 on SPING Units No. 21 and No. 22)

RE-315 Auxiliary Building Exhaust Ventilation None Scintillation Noble Gas Monitor (Channel 5 on SPING Unit No. 23)

RE-325 Drumming Area Ventilation Noble Gas None Scintillation Monitor (Channel 5 on SPING Unit No.

)

24_ _

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POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 16 October 29, 2004 OFFSITE DOSE CALCULATION MANUAL FIGURE 2-1 RADIOACTIVE LIQUID WASTE EFFLUENT MONITORS To >6a1*S W - Dil&lm A A A- --

I .

I . -;'.: ' I .

ok Ulk I Tutw &*q Flow she 2 TubW Da Floo Dfb'u

• th.4l I & 2 S-.~.y Sd. S.* .w A 0 - I I. . . t Radoactive Lklud Waste

. . . Effluet Monitors Page 11 of 123 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 16 October 29, 2004 OFFSITE DOSE CALCULATION MANUAL FIGURE 2-2 RADIOACTIVE GASEOUS WASTE EFFLUENT MONITORS Units 1 & 2 Turbine Ventilation I Turbine Bukiing - 1o To Atmnosphere Chemistry Laboratory (Variable) Ro Etks F-20

=r (E i)- Auxiliary Buikling Service Building Vemtilation F"21 _ Vent V

P&-*------ 1 - z- r I k A .1A 6 ,

F-29 Auxiliary Buildino Ventilation lSPtNG 23 l Auxiliary Buildim Ventilation (Low Radiation Areas)

Unit I Contda inme nt Purge Vent Unit 1& 2 Steam Generator Blowdoa Tank Vent Condensers I 3 Unit 1& 2 Gas Decay Tank Effluent lPermanentStrol I'RE- I I G2 Unit I Air Ejector Effluent F-30 Unit 1 Volume Control e Duryogenict C - Tank Unit 2 Air Ejector Effluent as Unit 1 & 2 Hydrogen and Noble Gases From Letdown G, Strpper

-I Cr Tanks Dey I

Unit 2 Volume Control lank Unit 1 Containment Continuous Vent ..........

I IIv A Unit I Containment Pume It UrIit2 Janment IF-t Purp a Vent tFttB T 7,}....2....................I Unit 2 Containment Continuous Vent

-w I mu lSPttsG 22 l I

Unit 2 Containment Purge A VI Drumming 2F.11B Area Vent Unit 1 & 2 Gas Strioer Buildina Ventilation Unit I & 2 Spent Fuel Pool Surface Exhaust F28 SPitG24 I M Unit I & 2 Drummina and Truck Access Area I Fugehing HEPA Charcoal Normal Optional Filter filter Filter Route Route Page 12 of 123 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 16

'October 29, 2004 OFFSITE DOSE CALCULATION MANUAL 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 of the PBNP radiation monitoring system will be accomplished within the guidelines of this section.' The computerized PBNP radiation monitoring system permits each effluent radiation monitor to be programmed to alarm at two distinct set-points. The alert set point, typically twice the steady-state reading, is intended to delineate a changing plant condition which may warrant corrective action. The high alarm or trip set point either will actuate a control function 'as applicable or will require corrective action to be initiated.

3.2 Objective The effluent monitor set points are established to ensure that controlled releases of liquid and gaseous radioactive effluents are maintained as low as is reasonably achievable, to ensure releases result in concentrations to unrestricted areas within specified limits and to ensure 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 the established steady-state reading. The alert set point is normally set at concentrations well below the alarm set point vahie and is never to be set in excess of the alarm set point. In the course of plant operations, certain situations may require a deviation from the two times steady-state guideline.: The intent of the alert set point is to warn of changing plant conditions which may warrant an evaluation of the cause of the increased radiation.-If the increased reading is actually due to an increased radiation inventory within the system being monitored, as opposed to an increased background radiation field in the vicinity of the detector, an evaluation should be made to determine the impact of the release. The alert set point may be adjusted with the approval of the Duty Shift Superintendent. Alert set point adjustments are to be made in accordance with the PBNP RMS Alarm Set Point and Response Book.

3.4 Alarm or Trip Set Point'Guidelines' Pursuant to regulatory and TS requirements as stated in Section 5 of the Radiological Effluent Control Manual, the alarm or trip set point for effluent monitors shall be established to annunciate at radiation levels which would result in an unrestricted area concentration 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 be established 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 the saturation 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 the PBNP RMS Alarm Set Point and Response Book I' "' -Pigd 13 of 123 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 16 October 29, 2004 OFFS1TE DOSE CALCULATION MANUAL 3.5 Monitor Calibration and Calibration Constant Determination Calibration of the RMS effluent detectors is accomplished in accordance with procedures contained in the PBNP Health Physics Calibration Manual. Noble gas effluent monitors apply the calibration constant to standardize all gaseous releases to the 1985-1991 average isotopic noble gas distribution. The calibration constants are based on the calculated monitor response to the beta energy distribution in the 1985-1991 average isotopic noble gas distribution.

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

1 Cal. Constant -

Sensitivity and Monitor Response Sensitivity =

Z (microCi/cci) where:

Monitor response = the calculated counts per minute registered by monitor exposed to the 1985-1991 average noble gas isotopic distribution 2:(gpici/) = total concentration of isotopes in the 1985-1991 average noble gas isotopic distribution The liquid effluent monitors apply the derived calibration constant to standardize all liquid releases to the total concentration in the release path. The calibration constants are based 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 release concentration.

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

Cal. Constant = 1 Sensitivity and MonitorRe sponse Sensitivity =

(UCi/cc1 )

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POINT BEACH NUCLEAR PLANT ODCM' OFFSITE DOSE CALCULATION MANUAL - Revision 16 October 29, 2004 OFFSITE DOSE CALCULATION MANUAL where:

Monitor Response = the counts per minute registered by monitor exposed to calibration source X(gCikccj) = total concentration on radionuclides in the 1985-1991 average liquid effluent isotopic distribution The QAD computer program may be utilized to predict or determine monitor calibration constants. Application of the QAD program may be appropriate for determining monitor response for accident source ferms or other instances when the use of a calibration source is impracticable. The methodology for determination of calibration constants using the QAD program is maintained by Radiation Protection.

3.6 Determination of the Effective Maximum Effluent Concentration (EMEC) for Liquid Releases Pursuant to PBNP TS, the concentration of radioactive materials in liquid effluent may not exceed 10 times the values of Column 2, Table 2, of Appendix B to 10 CFR 20.1001-20.2402. However, as a conservative measure, the following determination 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 value which will alarm when a liquid effluent would contain enough radionuclides to cause the effluent concentration limit of 10 CFR 20, Appendix B, Table 2, Column 2 for a single radionuclide to be exceeded, or for a mixture of radionuclides, the summation of fractions (SOF), as defined in Appendix B, to exceed one (1). Dividing the average isotopic concentrations for the years 1985-1991 by the SOF scales the total of individual concentrations up to the value where the SOF equals one. This total concentration is called the effective maximum effluent concentration (EMEC) and its calculation is described 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 = F CiJMECi where:

Ci = concentration of radionuclide "i" (gCirml) in effluent (annual discharge/total volume of discharge)

MEC, = maximum effluent concentration for unrestricted areas from Appendix B, Table 2, Column 2 of the revised 10 CFR 20.

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POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 16 October 29, 2004 OFFSITE DOSE CALCULATION MANUAL The SOF for radionuclides in liquid effluent for the years 1985 through 1991 were averaged 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 = -C;/I (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 pCi/cc. This is the maximum non H-3 radionuclide mixture concentration that could be released in liquid effluent without 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 Nal RMS monitors, be less 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 XCi / E (Ci/MECi) or XCi

• 0.70/SOF.

The EMEC becomes EMEC = 0.70

• 4.29E-06 = 3.00E-06 pCi/cc.

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

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

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POINT BEACH NUCLEAR' PLANT ODCM' OFFSITE DOSE CALCULATION MANUAL ' Revision 16

' October

' 29, 2004 OFFSITE DOSE CALCULATION MANUAL 3.7 Determination of Liquid Effluent Monitor Alarm Set Point The alarm set point for each liquid monitor is based upon the 1985-1991 average radionuclide concentration in the effluent discharged to the unrestricted area. The radionuclide concentration'in the release is calculated assuming a minimum circulating water flow rate of 206,000 gpm and the maximum flow rate of the individual liquid effluent waste stream. The isotopic distribution of the waste stream is-obtained from the

'historical PBNP release data for the seven years mentioned above. Set points are determined such that the sum of all radionuclides in the mixture, when released into the circulating water system, will be maintained at or below the unrestricted area EMEC.

.. Set points are calculated using the formula

= EMEC

• Circ water flow rate (gpm)

Waste Discharge Flow Rate (gpm) where SP = RMS alarm set point in jiCi/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 the monitor is located Maximum waste discharge flow rates and monitors associated wvith each liquid effluent pathway are described in Table 3.7-1.

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

.Vn 1;7 .%f 111 RPPFiFRNTCF.ITT4F.

I age & I .JL &.rJ - -.-. I -- - --

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 16 October 29, 2004 OFFSITE DOSE CALCULATION MANUAL TABLE 3.7-1

SUMMARY

OF LIQUID DILUTION AND EFFLUENT PATHWAY FLOW RATES LIQUID EFFLUENT DISCHARGE FLOW RATE PATHWAY MONITOR PATHWAY .J (GPM)

RECIRCULATION WATER _________

1 pump, either unit 206,000 None 2 pumps, either unit 350,000 1 pump, each unit 392,000 1 pump, one unit & 530,000 2 pumps, other unit .

2 pumps, each unit 680,000 SERVICE WATER RETURN 1 (2) RE-229 (normal cooldown per pump 2 pumps @ 7500 gpm 15,000 3 pumps @ 6300 gpm 18,900 4 pumps @ 5100 gpm 20,400 5 pumps @ 4300 gpm 21,500 6 pumps @ 3700 gpm 22,200 STEAM GENERATOR 1 (2) RE-219 & 1 (2) RE-222 BLOWDOWN Max flow 200 WASTE WATER EFFLUENT RE-230 Max Flow Rate 600 (both filter skids running in parallel)

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POINT BEACH NUCLEAR PLANT ' ' ODCM '.;

OFFSITE DOSE CALCULATION MANUAL - :Revision 16

,FTD CA L . lIO.

. MANU

'-' ' October 29, 2004

.. OFFSITE DOSE CALCULATION MANUAL

...... *1 . .  !

TABLE 3.7-1, cont

SUMMARY

OF LIQUID DILUTION 'AND EFFLUENT PATHWAY FLOW RATES

'..LIQUID EFFLUENT DISCHARGE FLOW RATE,.' PATHWAY MONiTOR PATHWAY - - 2.:> GP)

SPENT FUEL POOL . RE-220 Max Flow Rate 700 WASTE DISTILLATE & RE-218 & RE-223 CONDENSATE TANK DISCHARGE Max Flow Rate -. . 100 CONTAINMENT FAN 1 (2) RE-216 COOLER RETURN ._l Max Flow Rate per 4000 Containment

• '***j*

'. - - Page 19 of 123 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 16 October 29, 2004 OFFSLTE DOSE CALCULATION MANUAL TABLE 3.7-2 LIQUID PATHWAY MONITOR CALCULATED DEFAULT SET POINTS MONITOR FLOWRATE (gpm) SET POINT (iiCi/cc) 1 (2) RE-229 6 @ 3700' 2.78E-05 1 (2) RE-219 & 200 3.09E-03 1 (2) RE-222 RE-230 600 1.03E-03 RE-220 700 8.83E-04 RE-218 & 100 6.18E-03 RE-223 1 (2) RE-216 4000 1.55E-04 Xsix service water pumps at normal cooldown flow rates Page 20 of 123 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM- '

OFFSITE DOSE CALCULATION MANUAL

• IRevision 16

.-October 29, 2004

..-... OFFSITE DOSE CALCULATION MANUAL 3.8 Determination of EMEC for Atmospheric Releases The maximum concentration'of the mixture of radionuclides that is allowable at the site boundary is called the effective maximum effluent concentration (EMEC). The EMEC for an effluent mixture is defined by the equation EMEC = IQ /I(C I MECG) where C; = concentration of radionuclide "i" MEC' = maximum effluent concentration for radionuclide i from 10 CFR 20, Appendix B, Table 2 Z (C; / MECi) = summation of fractions (SOF), as discussed in Section 3.6, applied to atmospheric releases The EMEC is calculated from the reference radionuclide mixture. This mixture is obtained from the 1985 - 1991 average annual atmospheric releases and the corresponding concentrations determined from the highest annual average X/Q. (Details of the EMEC calculation are found in Appendix B.)

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

I!I

- :*, .,, , '.A- i' -Pige21of 123 REFERENCE USE

PLAN POINT EACH UCLEA POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 16 October 29, 2004 OFFSITE DOSE CALCULATION MANUAL 3.9 Determination of Gaseous Effluent Monitor Alarm Set points The alarm set point for each monitor is based upon maintaining the concentration of the reference radionuclide mixture at or below the EMEC. The set point is calculated using the formula SP = 2.12E+03

• EMEC / (X/Q

• FR) where SP = set point in jtCi/cc 2.12E + 03 = conversion factor for ft3 /min to m3 /sec EMEC = 1.92E-08 liCi/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(p.Ci/cc) = 2.71E+01 /FR Gaseous effluent pathway discharge flow rates and monitors associated with each pathway are summarized in Table 3.9-1.

TABLE 3.9-1

SUMMARY

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 23

b. Combined Air Ejector 20 RE-225

c. Unit Air Ejector 10 1 (2) RE-215

d. Containment Purge Vent

1) 1 fan operating 12,500 1 (2) RE-212 &

2) 2 fans operating 25,000 SPINGS 21 & 22

e. Gas Stripper Building 13,000 RE-224

f. Drumming Area Vent 43,100 RE-221 & SPING 24 Page 22 of 123 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 16 October 29, 2004 OFFSITE DOSE CALCULATION MANUAL ' ' '

Alarm set points are to be normally established based upon maximum waste discharge flow rates and the highest annual average X/Q value at the site boundary. The alarm set points may be adjusted for release periods if actual flow rates are reduced to less than maximum values or actual X/Q values are calculated.

Alarm set point adjustments to higher values'are to be made in accordance with the provisions and methodologies of this section' and require PORC approval. Default set point values obtained using the flow rates in Table 3.9-1 are presented in Table 3.9-2. An additional reduction factor of 1/4 has been applied to the four release point monitors so that the maximum allowable site boundary concentrations will not be exceeded in the event simultaneous releases from these points occur. Lower set point values may be used for any of the monitors without PORC approval if the default value is outside the upper range of the monitor or if compliance with applicable release limits will not be compromised. The set point 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 3.9-2 ATMOSPHERIC PATHWAY MONITOR DEFAULT RMS SET POINTS MONITOR FLOW RATE SET POINT

.-(ft3/min) ([!Ci/cc)

RE-214 66,400 1.02E-04 RE-225 20 1.36E+00 IRE-215 10 2.71E+00 2RE-215 10 2.71E+00 1RE-212 25,0001 2.73E-04 2RE-212 38,0002 1.78E-04 1/2RE-212 3 ' 30 2.26E-01 RE-224  : 13,000 2.09E-03 RE-221 43,000 1.58E-04

'2 fans (with I fan the flow rate is 12,500 cubic feet/minute) 22 fans + 13,000 cfm from the gas stripper building 3Forced vent with nominal 30 cfm flow rate The individual 1/2RE-212 setpoints are based on purge flow rates. During operational modes 14, the purge valves are locked shut. Therefore, forced vent alarm setpoints are calculated based on the nominal 30 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 MSS approved (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 *70% of the monitor's fail high level. This approval applies to those monitors for which the calculated setpoint falls above the fail high level. The current alarm setpoint levels are recorded in the RMS Alarm Set Point and Response Book.

-. L ... 1' TDT XT T TT!

iralgezz) (I

.i JLI..3 A1zr11%1NLr Uar

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 16 October 29, 2004 OFFSITE DOSE CALCULATION MANUAL 3.10 Determination of Maximum Release Rates Technical specifications restrict the rate of release of radionuclides to the atmosphere to that value, which if continued for one year, would result in the following annual dose rates at or beyond the site boundary: 500 mrem/yr to the whole body and 3000 mremlyr to the skin from noble gases; and, 1500 mrem/yr to any organ from I-131, 1-133, H-3, and particulates 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 1.109 dose factors and the annual average isotopic noble gas release for the years 1985 - 1991 as shown in Table B-1. Following the methodology in Section 5.1.3, the calculated annual skin dose from the average 1985 - 1991 isotopic mixture with a total of 4.51E+01 curies is 1.03E-02 mrem. Therefore the 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 = 4.5 1E+0I 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 whole body dose of 5.89E-03 mrem/yr and the whole body dose limit of 500 mrem/yr, the release rate becomes 1.22E-01 Ci/sec.

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

Page 24 of 123 REFERENCE USE

POINT BEACH NUCLEAR PLANT , ODCM OFFSITE DOSE CALCULATION MANUAL Revision 16

- -October 29, 2004

- -- OFFSlTE DOSE CALCULATION MANUAL 3.10.2 Release rate for I-131, I-133, H-3, and particulates released to the atmosphere with half-lives >8 days During the time period of 1985 - 1991, PBNP released an annual average of 116.30457 Ci to the atmosphere consisting of I-131, I-133, H-3, and particulates whole half-life >8 days. Of this quantity, 116.30 was H-3 and 4.57E-03 was I-131, I-133, and particulates whose half-life was >8 days. The doses from this mixture, calculated using ODCM methodology are shown in Table 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 Skin

.ADULT 1.66E-02 3.68E-02 5.74E-02 5.44E-02 2.01E-02 1.42E-02 1.23E-02 3.27E-02

'TEEN 2.69E-02 5.25E-02 5.57E-02 4.64E-02 2.56E-02 1.72E-02 1.29E-02 3.27E-02 CHILD 6.3 1E-02 8.30E-02 5.48E-02 7.70E-02 3.73E-02 2.3 1E-02 1.60E-02 3.27E-02 INFANT 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 broken down into the following grouping: H-3, I-131 and 1-133, and the remaining radionuclides, the groups contribution to the various organ doses are revealed (Tables 3.10 3.10-4).

- Table 3.10-2 mrem from 1-131 and I-133 (2.42E-03 Ci) mrem from 1-131 AND 1-133 Bone 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 O.OOE+00 3.66E-05 4.20E-05 TEEN 8.52E-05 1.20E-04 9.82E-05 3.44E-02 2.06E-04 0.OOE+00 2.50E-05 4.20E-05 CHILD .1.86E-04 1.88E-04 1.41E-04 6.17E-02 3.09E-04 0.OOE+00 1.79E-05 4.20E-05 INFANT 2.63E-04 3.1OE-04 1.71E-04; 1.O1E-01 3.62E-04 -O.OOE+00 1.17E-05 4.20E-05 Table 3.10-3 mrem from H1-3 (116.3 Ci)

." :mrem

' from H-3 Bone Liver T. Body Thyroid Kidney Lungs- GI-LLI Skin ADULT O.OOE+00 1.13E-02 1.13E-02 1.13E-02 1.13E-02 1.13E-02 1.13E1-02 O.OOE+00 TEEN O.OOE+00 1. 19E-02 l.l19E-02 ,1.19E-02 l.l9E3-02 1.19E-02 1.19E-02 O.OOE+00 CHILD 0.OOE+00 1.53E-02 1.53E-02 1.53E-02 1.53E-02 1.53E-02 1.53E3-02 O.OOE+00 INFANT O.OOE+00 2.35E-03 2.35E-03 2.35E-03 2.35E-03 2.35E-03 2.35E-03 O.OOE+00 z I. I t

• I .- ' . , ( ,

'Page 25 of 123 REFERENCE USE

L POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 16 October 29, 2004 OFFSITE DOSE CALCULATION MANUAL Table 3.10-4 mrem from all radionuclides except H-3 and radioiodines (2.15E-03 Ci) mrem from all radionuclides except H-3 and radioiodines Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin ADULT 1.65E-02 2.53E-02 4.59E-02 2.08E-09 8.49E-03 2.84E-03 9.41E-04 3.27E-02 TEEN 2.68E-02 4.04E-02 4.37E-02 2.64E-09 1.35E-02 5.25E-03 9.76E-04 3.27E-02 CHILD 6.29E-02 6.75E-02 3.94E-02 4.94E-09 2.16E-02 7.81E-03 6.72E-04 3.27E-02 INFANT 5.01E-02 6.51E-02 3.32E-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 the thyroid dose for all age groups for the 1985 - 1991 mixture of radionuclides released to the atmosphere. Comparison of Tables 3.10-5 and 3.10-6 to Table 3.104 reveals that the major portion of the organ doses from radionuclides other than H-3 and radioiodines results from cobalt and cesium. Cs-134 and Cs-137 are the major dose contributors to the bone, liver, skin and kidneys whereas cobalt is the major contributor to the GI-LLI dose. Therefore, the dose results obtained from the 1985 - 1991 radionuclide mixture is consistent with the dose results from current effluents.

Table 3.10-5 mrem from Cs-134 and Cs-137 (1.84E-03 Ci) mrem from Cs-134 and Cs-137 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin ADULT 1.62E-02 2.53E-02 4.21E-02 0.OOE+00 8.48E-03 2.82E-03 4.76E-04 2.84E-02 TEEN 2.64E-02 4.04E-02 3.98E-02 0.00E+00 1.35E-02 5.22E-03 5.52E-04 2.84E-02 CHILD 6.22E-02 6.74E-02 3.54E-02 0.00E+00 2.16E-02 7.78E-03 4.05E-04 2.84E-02 INFANT 5.01E-02 6.50E-02 2.95E-02 0.00E+00 1.73E-02 7.02E-03 1.96E-04 2.84E-02 Table 3.10-6 mrem from Co-57, Co-58, and Co-60 (1.93E-04 Ci) mrem from cobalts Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin ADULT 0.OOE+00 2.24E-05 3.72E-03 0.00E+00 0.00E+00 2.32E-05 4.26E-04 4.32E-03 TEEN 0.OOE+00 2.97E-05 3.73E-03 0.OOE+00 0.OOE+00 3.40E-05 3.88E-04 4.32E-03 CHILD 0.00E+00 4.35E-05 3.80E-03 0.OOE+00 0.OOE+00 2.76E-05 2.43E-04 4.32E-03 INFANT 0.OOE+00 7.75E-06 3.69E-03 0.00E+00 0.00E+00 1.78E-05 1.86E-05 4.32E-03 Based on these results, the release rates for various radionuclide mixture can be determined using the 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 mrem

• 3.15E+07 sec/yr) or 5.33E-02 Ci/sec, Page 26 of 123 REFERENCE USE

POINT BEACH NUCLEAR PLANT ' 'ODCM OFFSITE DOSE CALCULATION MANUAL ' 'Revision 16

', 'October 29, 2004 OFFSITE DOSE CALCULATION MANUAL '

For radioiodines (I-131 and I-133), the maximum release rate is Ci/sec =2.42E-03 Ci *1500 mrem/yr/ (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 mrem/yr/ (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 maximum release rate is Ci/sec =2.15E-03 Ci *1500 mrern/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 Ci/sec =1.84E-03 Ci *1500 inrem/yr/ (6.74E-02 mrem

• 3.15E+07 sec/yr) or 1.30E-06 Ci/sec, For cobalt (Co-57, -58, -60), the maximum release rate is Ci/sec =1.93E-04 Ci *1500 mremlyr/ (4.26E-02 mrem

• 3.15E+07 sec/yr) or 2.16E-05 Ci/sec, Finally, for the total of all radionuclides in'the mixture except H-3, the maximum release rate is Ci/sec =4.57E-03 Ci *1500 'mrem/yr/ (1.01E-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 whose half-lives is>'8 days'should be restricted to 1.14E-06 Ci/sec. -However, if there is no 1-131 and I-133, the cesium doses become limiting and the release rate limit may be raised to 1.30E-06 Ci/sec.':

' ";'Piae27of 123 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 16 October 29, 2004 OFFSITE DOSE CALCULATION MANUAL 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 PBNP by periodic calculations. Compliance with Appendix I limits is demonstrated by periodically calculating doses to the maximum exposed individual using the methodology set forth in Regulatory Guide 1.109, Rev. 1, October 1977 and in other recognized sources such as ICRP publications.

In order to aid in the dose calculations, the formulae in Reg Guide 1.109 were rearranged to calculate the dose per curie released (mrem/Ci) to the environment. For each pathway given in Reg Guide 1.109, a radionuclide's mrem/Ci values for the whole body and the organs were calculated for each of the two release modes, liquid and atmospheric. All of the pathway doses for a radionuclide via the release mode under consideration were summed to obtain the radionuclide's total mrem/Ci released. These values, called total dose factors (TDFs), are listed in Tables 5.1.1 and 5.1.2. The application of TDFs are given 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 in liquid and gaseous effluents to the environment, to ensure that these releases are as low as is reasonably achievable in conformance with 10 CFR Parts 50.34a and 50.36a, to ensure that these releases result in concentrations of radioactive materials in liquid and gaseous effluents 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 unrestricted areas are as low as is reasonably achievable, the following design release limits as defined in Appendix I to 10 CFR 50 apply:

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

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

Page 28 of 123 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL 'Revision 16

?,, *  ;,October 29, 2004 OFFSITE DOSE CALCULATION MANUAL C. The calculated annual total quantity of all radioactive iodine and radioactive material in particulate form above background that may be released from each light-water-cooled nuclear power reactor in effluents to the atmosphere should not result in an annual dose'or dose commitment from such radioactive iodine

'and radioactive material in particulate form for any individual in an unrestricted area'from all pathways of exposure in excess of 15 millirems to any organ.

D. Pursuant to NRC interpretation as stated in PBNP TS 5.5.4.i, the dose guideline of Section 4.2.C, above, applies only to I-131, I-133, H-3, and all particulate material released to the atmosphere which has a half-life >8 days.

Particulates with shorter half-lives are not considered because of their negligible dose contribution.

4.3 Release Limits Based on the Appendix I dose limits, Point Beach, being a two (2) unit nuclear plant, may release into the environment the quantities of radionuclides above background that fulfill the criteria listed below.

A. Pursuant to Section 4.2.A, the doses from radionuclides in the unrestricted area 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 the unrestricted 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.C, the dose from radioiodine and radioactive material in particulate'form released to the atmosphere in the unrestricted area shall not exceed thirty (30) nmillirem to any organ.

D. Quarterly release'limits are defined as 1/2 the annual limits.

Page 29 of 123 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 16 October 29, 2004 OFFSITE DOSE CALCULATION MANUAL 4.4 EPA Regulations Compliance with the provisions of Appendix I to 10 CFR 50 is adequate demonstration of conformance to the standards set forth in 40 CFR 190 regarding the dose commitment to individuals from the uranium fuel cycle. For 40 CFR 190 compliance, quarterly dose calculations shall include exposures from effluent pathways and direct radiation contributions from the reactor units and from any outside storage tanks.

The above calculations do not include contributions from the Kewaunee Nuclear Power Plant (KNPP) which is some four miles north of PBNP. Under normal operations using the PBNP annual average X/Q and assuming that the KNPP source term is identical to either PBNP unit, the greatest KNPP dose contribution occurs at the north sector PBNP boundary. However, the total KNPP-PBNP dose at that point is less than the dose in the highest sector (south boundary) from PBNP alone. The KNPP contribution in this sector adds only 1 percent to 8 percent to the total dose depending upon the release mode. Even in the highly unlikely event that PBNP and KNPP operated for an entire year at twice the Appendix I levels, the small percentage contribution from KNPP would be insufficient to yield 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 calculations be performed periodically. This section describes the methodology for the calculation of doses for comparison to the corresponding dose limits. For Appendix I compliance, the organ and whole body doses shall be calculated for the maximally exposed individual in each age group using the appropriate total dose factors in mrem/Ci released which were obtained using Regulatory 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 be calculated for each month to track compliance with effluent and dose goals.

The doses from each radionuclide will be calculated for each age group and for each organ, including the whole body, and summed over all the identified radionuclides released. The total dose is compared to the corresponding liquid release mode Appendix I dose limit for the organ in question. Noble gases released in liquids are added to the atmospherically released noble gases for Appendix I dose compliance calculations.

The doses are calculated using the following formula:

API =  : Doseaomi = E: (TDFaomi x C;) < Kom mrem Page 30 of 123 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 16

-October 29, 2004 OFFSITE DOSE CALCULATION MANUAL where API = the Appendix I dose for compliance evaluation in mrem Doseaomi = the dose to the specific age group (a) and organ (o) via release mode (m) from radionuclide (i)

TDFaom =' total dose factor for the specific age group (a) and organ (o) via release mode (m) from radionuclide (i) from Table 5.1-1 in mrem/Ci C; =. curies of radionuclide (i) released Kom = the Appendix I dose limit for organ (o) and release mode (m) for which the calculation is being made.

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

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

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

CF = 677,000 gpm / actual average discharge gpm

s. .. er..a.g.d.r..

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

l' ;"; Page'31 of 123 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 16 October 29, 2004 OFFSITE DOSE CALCULATION MANUAL Table 5.1-1 TABLE 5.1-1 LIQUID 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 I Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult O.OOE+OO [ 4.46E-06 4.46E-06 4.46E-06 4.46E-06 4.46E-06 4.46E-06 Teen O.OOE+OO 4.04E-06 4.04E-06 4.04E-06 4.04E-06 4.04E-06 4.04E-06 Child O.OOE+OO 6.67E-06 6.67E-06 6.67E-06 6.67E-06 6.67E-06 6.67E-06 Infant O.OOE+OO I 7.79E-06 7.79E-06 7.79E-06 7.79E-06 7.79E-06 7.79E-06 Dose factor - liquid release pathway (rnremlCi released) lF-18 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 1.15E-07 9.12E-89 1.28E-08 O.OOE+OO 5.14E-89 JO.OOE+OO 3.40E-09 Teen 1.21 E-07 7.59E-89 1.35E-08 O.OOE+OO 4.35E-89 jO.OOE+OO 1.09E-08 Child 1.51E-07 1.08E-88 1.50E-08 O.OOE+OO 5.74E-89 O.OOE+OO 4.08E-08 Infant 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 (mremlCi released) l Na-22 l Bone Liver T. Body Thyroid Kidney l Lungs GI-LLI Adult 4.71E-03 4.71E-03 4.82E-03 4.71E-03 4.71E-03 4.71E-03 4.71E-03 Teen 5.48E-03 5.48E-03 6.07E-03 5.48E-03 5.48E-03 5.48E-03 5.48E-03 Child C I 8.32E-03 8.32E-03 8.45E-03 8.32E-03 8.32E-03 8.32E-03 - 8.32E-03 Infant 7.21E-03 l 7.21E-03 7.21E-03 7.21E-03 7.21E-03 7.21E-03 7.21E-03 Dose factor - liquid release pathway (mremlCi released) -_

Na-24 __

Bone Liver T. Body l Thyroid Kidney Lungs GI-LLI Adult l 1.85E-04 1.85E-04 1.85E-04 1.85E-04 1.85E-04 1.85E-04 1.85E-04 Teen j 1.98E-04 1.98E-04 1.98-04 l 1.98E-04 1.98E-04 1.982-04 1.98E-04 Child l 2.402-04 2.40E-04 2.40E-04 l 2.40E-04 2.40E-W04 2.40E-04 2.40E-04 Infant l 8.06E-05 8.06E-05 8.06E-05 l 8.06E-05 8.062-05 8.06E-05 8.06E-05 Page 32 of 123 REFERENCE USE

i POINT BEACH NUCLEAR PLANT ODCM - .

OFFSITE DOSE CALCULATION MANUAL Revision 16

. October 29, 2004

-- .. OFFSITE DOSE CALCULATION MANUAL Table 5.1-1 Dose factor - liquid release pathway (mrernCi released)

Sc46

,Bone Liver ',-T. .Body, , Thyroid :_Kidney, Lungs GI-LLI Adult 1.70E-07. 3.3 1E-07 8.92E-06 0.OOE+00 3.09E-07 0.OOE+00 1.61E-03 Teen . 1.52E-07 2.97E-07 4.94E-05 0.OOE+00 2.84E-07 0.OOE+00 1.0 1E-03 Child 3.54E-07 4.85E-07 l.OSE O.OOE+00 4.29E-07 0.OOE+'00 7.09E-04 Infant 3.42E-07 4.94E-07 1.54E-07 0.OOE+00 3.25E-07 0.OOE+00 3.22E-04 Dose factor - liquid release pathway (rnrern/Ci released)

Mn-54 Bone Liver . "T. Body Thyroid ,Kidney- Lungs GI-LLI Adult 0.OOE+00 3.28E-03 6.34E-04 0.OOE+00 9.75E-04 0.OOE+00 1.OOE-02 Teen - O.OOE+00 3.22E-03 6.86E-04 0.OOE+00 9.59E-04 0.OOE+00 6.60E-03 Child 0.OOE+00 2.60E-03 7.04E-04 -O.OOE+00 7.30E-04 O.OOE+00 2.19E-03 Infant 0.OOE+00 1.92E-04 4.34E-05 O.OOE+00 4.25E-05 0.OOE+00 7.04E-05 Dose factor - liquid release pathway (mreni/Ci released)

Cr 5 Cr-S5l1 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

.,Bone._,  ;. ~Liver,,: Body .

BT ,:Thyroid .. Kidney,,. Lungs.,,: GI-LLI Adult 0.OOE+00 0.OOE+00 1.0lE-06 5.84E-07 2.15E-07 1.30E-06 2.46E-04 Teen :O.OOE+00 0 1.OOE+O0 1.17E-06 5.60E-07 2.211E-07 1.44E-06 1.70E-04 Child 0.OOE+00 0.OOE+00 1.19E-06 6.44E-07 L.76E-07 1.1&E-06 6.15E-05 Infant 0.OOE+00 0.OOE+00 1.72E-07. 1.12E-07 2.45E-08 2.18E-07 5.01E-06 Dose factor - liquid release pathway (mrerntCi released) -_-

Mn-56 - ,

lBone.'- , Liver ,T. ,Body. ,. Thyroid lKidney ',,,:'Lungs ,iGI-LLI lAdult 0.OOE+l00 3.18E-06 - 5.65E-07' 0.OOE+00 l 4.04E-06 0.OOE+l00 1.02E-04

'Teen-- 0.OOE+l00 3.33E-06 5.94E-07 O.OOE+00 l 4.22E-06 0.OOE+l00 2.19E-04 Child 0.OOE+00 3.04E 6.86E-07 0.OOE+00 l 3.67E-06 0.OOE+l00 4.40E-04 Infant 0.OOE+l00 1.97E-11 -l 3.39E-12 O.OOE+00 1.69E-1l 0.OOE+00 1.79E-09 Dose factor - liquid release pathway (mrem/Ci released)

Fe-55 -, - . . - -

l,.- Bone - Liver T. Body .. Thyroid ,Kidney Lungs_',, GI-LLI Adult 5.98E-04 4.13E-04 9.63E 0.OOE+00 O.OOE+00 2.31E-04 2.37E-04 Teen 6.1IE 4.33E-04 1.01E-04 0.OOE+0O 0.OOE+00 2.75E-04 1.88E-04 Child 9.35E-04 4.96E-04 -1.54E-04 l O.OOE+00 0.OOE+l00 2.80E-04 9.19E-05 Infant 1.55E-04 -1 l.OOE-04 2.68E-05 O.OOE+00 I O.OOE+00 4.91E-05 1.28E-05

.- Page 33 of 123 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 16 October 29, 2004 OFFSITE DOSE CALCULATION MANUAL Table 5.1-1 Dose factor - liquid release pathway (mrem/Ci released)

Fe-59 I l Bone Liver T. Body Thyroid Kidney Lungs GI-LLI 1 Adult 9.12E-04 2.14E-03 8.23E-04 0.00E+00 0.OOE+OO 5.99E-04 7.14E-03 J Teen 9.22E-04 2.15E-03 8.40E-04 0.00E+00 0.OOE+0O 6.79E-04 5.09E-03 Child 1.29E-03 2.09E-03 1.04E-03 0.00+00 0.00E+00 6.07E-04 2.182-03 Infant I 3.34E-04 5.84E-04 2.30E-04 0.00E+00 0.00E+0O 1.73E-04 2.792E-04 Dose factor - liquid release pathway (mrem/Ci released)

Co-57 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 0.OOE+0O 2.02E-05 3.57E-05 O0.OOE+0O 0.00E+00 0.OOE+0OO 5.13E-04 Teen 0.002+00 2.06E-05 4.62E-05 0.002+00 0.00E+00 0.00E+00 3.832-04 Child 0.002+00 2.3 1E-05 4.93E-05 0.00E+00 0.00E+00 O.OOE+00 1.89E-04 Infant O.OOE+00 1.24E-05 2.02E-05 0.OOE+00 0.00E+00 0.00E+00 4.242-05 Dose factor - liquid release pathway (mrem/Ci released)

Co-58 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 0.OOE+00 8.49E-05 1.93E-04 0.OOE+00 0.002+00 0.OOE+00 1.72E-03 Teen O.OOE+00 8.302-05 2.042-04 O.OOE+00 O.OOE+00 0.002+00 1.14E-03 Child 0.002+00 8.322-05 2.572-04 0.002+00 0.002+00 0.002+00 4.85E-04 Infant O.OOE+00 3.84E-05 9.582-05 O.OOE+00 0.002+00 0.002+00 9.572-05 Dose factor - liquid release pathway (mremlCi released)

Co-60 Bone Liver T. Body l Thyroid l Kidney Lungs GI-LLI Adult 0.002+00 2.482-04 6.822-04 j0.00+00 0.00+00 0.002+00 4.662-03 Teen 0.0023+00 2.442-04 1.30E-03 l 0.002+00 0.002+00 0.002+00 3.17E-03 Child 0.002+00 2.492-04 8.922-04 0.002+00 l 0.002+00 O.OOE+000 1.382-03 Infant 0.002+00 I 1.172-04 2.772-04 JO.00+00 0.002+00 0.002+00 2.79E-04 Dose factor - liquid release pathway (mrem/Ci released) _

Ni-63 D Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 3.032-02 2. 1OE-03 1.02E-03 0.002+00 0.002+00 0.l002+00 4.382-04 Teen 3.132-02 2.212-03 1.062-03 0.002+00 0.00+00 l 0.002+00 3.522-04 Child 5.002-02 2.672-03 1.702-03 0.002++00 0.00+00 O.OOE+0200 1.802-04 Infant 1.27E-02 7.852-04 4.41E-04 O 2OOE+00 O.OOE+00 O.OOE+00 3.912-05 Page 34 of 123 REFERENCE USE

POINT BEACH NUCLEAR PLANT O ODC .C

.I OFFSITE DOSE CALCULATION MANUAL IRevision 16 TDECL Ck M U  ! 4 ::October 29, 2004

..-OFFSllTE DOSE CALCULATION MANUAL Table 5.1-1 Dose factor - liquid release pathway (mrem/Ci released) lNi-65 Bone r Liver  :; T.,:Body , ,:Thyroid Kidney.; Lungs - GI-LLI Adult 3.39E-06 4.40E-07 2.01E-07 0 .OOE+00 0.OOE+00 0.OOE+00 1.12E-05 Teen - 3.66E-06 4.68E-07 2.13E 0.00E+00 0.OOE+00 0.OOE+00 - -2.54E-05 Child' 4.68E-06 4.41E-07 2.57E-07 O.OOE+00 O.OOE+00 O.OOE+00 5.40E-05 Infant 1.74E-10 1.97E-1 8.95E-12 0.00E+00 0.00E+00 O.OOE+00 1.50E-09 Dose factor - liquid release pathway (mrem/Ci released)

Cu - ' - - -

Bone - Liver -^l T. Body. ,Thyroid Kidney ' Lungs GI-LLI Adult 0.OOE+00 4.02E-06 1.89E-06 O.OOE+00 1.0 IE-05 0.00E+00 3.43E-04 Teen O.OOE+00 4.3 1E-06 2.04E-06 O.OOE+00 1.09E-05 0.00E+00 3.34E-04 Child . O.OOE+00 4.30E-06 2.60E-06 -O.OOE+00 1.04E-05 O.OOE+00 2.02E-04 Infant 0.00E+00 1.41E-06 I 6.52E-07 I 0.OOE+OO 2.38E-06 0.00E+00 2.89E-05 Dose factor - liquid release pathway (rnrem/Ci released)

Zn-65 - - - -- - - -_-_- --- - - -

Bone -  : -,-Liver- ',,T.-Body Thyroid -- Kidney Lungs l, GI-LLI Adult 1.73E-02 5.50E-02 2.49E-02 l O.OOE+00 3.68E-02 O.OOE+00 3.46E-02 Teen-: 1.58E-02 5.50E-02 2.57E-02 l 0.OOE+l00 3.52E-02 O.OOE+00 2.33E-02 Child 1.68E-02 4.47E-02 2.78E-02 O.OOE+00 2.82E-02 0.OOE+0OO 7.85E-03 Infant 1.32E-03 4.51E-03 2.08E-03 O.OOE+00 2.19E-03 0.OOE+!00 3.81E-03 Dose factor - liquid release pathway (mremlCi released)

Zn-69 - - - __

lBone.--l -:-Liver ,' T.,-,Body ,; Thyroid - -- Kidney -l -Lungs -lGI-LLI

-Adult 11.97E-05 -3.76E-05 - 2.62E-06 O.OOE+OO 2.44E-05 O.OOE+0O 5.65E-06 Teen - 2.14E-05 4.08E-05 2.86E 0.OOE+00 2.67E-05 O.OOE+00 7.52E-05 Child 2.77E-05 4.00E-05 -3.70E 0.00E+00 2.43E-05 0.OOE+00 2.52E-03 Infant ! 5.98E-07 1.08E-06 8.01E 0.OOE+00 4.47E-07 0.00E+O0O 8.78E-05 Dose factor -liquid release pathway (rnrem/Ci released)

Zn-69m - - - ^ - -_-_ _

, Liver . ,l,Bonel vT.Body,<,l T-hyroid .- Kidney.

l  ; Lungs l ,GI-LLI

'Adult 3.25E-04 7.79E 7.12E O.OOE+00 4.72E-04 lO.OOE+ 00 4.76E-02 Teen 3.50E 8.25E-04 7.57E-05 l O.OOE+00 5.01E-04 0.OOE+00 4.53E-02 Child 4.49E-04 7.65E-04 9.04E-05 0.OOE+00 4.44E-04 O.OOE+00 2.49E-02 Infant 9.61E-06 l 1.96E-05 1.79E-06 0.00E+00 7.94E-06 O.OOE+00 2.72E-04 I i- - . i -t- 1-A'g`e- 5'5 of 123 REFERENCE USE

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Br-82 Bone Liver T. Body Thyroid Kidney Lungs Gl-LLI Adult 0.OOE+00 O.OOE+00 1.39E-03 0.002+00 0.OOE+00 O.OOE+00 1.59E-03 Teen 0.002+00 0.0012+00 1.47E-03 0.OOE+00 0.OOE+00 0.OOE+00 0.00+00 Child 0.00+00 O.OOE+00 1.71 E-03 0.002+00 0.OOE+00 0.OOE+00 0.OOE+00 Infant 0.00+00 O.OOE+00 4.43E-04 0.OOE+00 0.00+00 0.OOE+00 0.OOE+00 Dose factor - liquid release pathway (mrem/Ci released)

Br-83 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 0.OOE+00 0.OOE+00 9.06E-07 0.OOE+00 O.OOE+00 0.00+00 1.30E-06 Teen 0.OOE+00 0.OOE+00 9.85E-07 0.OOE+00 0.00E+00 O0.OOE+00 0.OOE+00 Child O0.OOE+00 O0.OOE+00 1.27E-06 0.OOE+00 0.OOE+00 O0.OOE+00 0.00+00 Infant 0.002+00 I 0.OOE+00 2.93E- I I 0.00+00 0.OOE+030 O.OOE+00 0.002+00 Dose factor - liquid release pathway (mrem/Ci released)

Br-84 Bone Liver T. Body Thyroid l Kidney Lungs GI-LLI Adult 0.00E+00 l 0.002+00 3.122-05 0.00O+00 [0.00E+00 0.00E+00 2.44E-10 Teen O.OOE+00 J O.OOE+00 3.432-05 0.002+00 l 0.00E+00 0.002+00 0.00O+00 Child 0.002+00 J 0.00E+00 4.33E-05 0.002+00 0.001E+00 0 .00E+00 0.002+00 Infant 0.0023+00 j0.00E3+00 ,1.2023-05 0.0023+00 j0.0023+00 0. OOE+00 0.0023+00 Dose factor - liquid release pathway (mrem/Ci released)

Br-85 Bone Liver T. Body Thyroid Kidney Lungs l_GI-LLI Adult 0.002+00 O.OOE+00 4.242-82 0.00E+00 0.002+00 l 0.002+00 l0.00O+00 Teen 0.002+00 O.OOE+00 4.602-82 0.00O+00 0.OOE+00 l 0.002+00 l 0.002+00 Child 0.002+00 0.00O+00 5.94E-82 0.00O+00 O.OOE+00 0.OOE+00 0.00O+00 Infant I 0.00E+00 O.OOE+00 I 9.35E-309 I 0.002+00 0.002+00 0.00O+00 0.00E+00 Dose factor - liquid release pathway (mrem/Ci released) _

Rb-86 11 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 0.00E+00 7.362-02 l 3.432-02 0.00O+00 0.002+00 0.002+00 1.452-02 Teen 0.002+00 7.982-02 l 3.75E-02 0.002+00 0.00O+00 O.OOE+00 1.18E-02 Child 0.00O+00 7.93E-02 4.882-02 0.002+00 0.00E+00 O.OOE+00 5.10-03 Infant O.OOE+00 I 9.07E-03 4.482-03 0.002+00 0.002+00 0.002+00 2.322-04 Page 36 of 123 REFERENCE USE

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$" ,. 'j.October 4 29, 2004 OFFSITE DOSE CALCULATION MANUAL  ;

Table 5.1-1 Dose factor - liquid release pathway (mrern/Ci released)

Rb -.

Bone, Liver,, ,T. Body,' 'Thyroid Kidney_ Lungs GILLI Adult - O.OOE+OO 1.41lE-16 7.46E-17 O.OOE+OO O.OOE+00 O.OOE+OO 1.94E-27 Teen 'O.OOE+OO 1.51 E-16 -8.04E- 17. O.OOE+OO O.OOE+OO O.OOE+OO 1.29E-23 Child - O.OOE+OO 1.45E-16 1.OlE O.OOE+OO O.OOE1+OO O.OOE+OO 7.12E-18 Infant O.OOE+OO. 5.68E-54 3.12E-54 O.OOE+OO O.OOE+OO O.OOE+OO 5.54E-54 Dose factor - liquid release pathway (mremi/Ci released) -______-______

Rb-89 ase_ p . .

Bone Liver .T. Bodyl. - -,Thyroid ' Kidney ,Lungs- GI-LLI Adult O.OOE+OO 1.28E-18 8.99E-19 O.OOE+OO JO.OOE+OO O.OOE+OO 7.42E-32

Teen O.OOE+OO - 1.34E-18 9.45E O.OOE+OO JO.OOE+OO O.OOE+OO 2.05E-27 Child O.OOE+OO 1.23E-18 1.09E-18 O.OOE+OO O.OOE+OO O.OOE+OO 1.07E-20 Infant .O.OOE+OO 1.151E-61 7.93E-62 O.OOE+OO O.OOE+OO O.OOE+OO 3.92E-62 Dose factor - liquid release pathway (mrern/Ci released)

Sr-89

,, , Bone, .. , Liver :.,T.',Bodyl ', Thyroid Kidney . _;,Lungs_,, GI-LLI Adult 2.26E-02 O.OOE+OO 6.48E-04 O.OOE+OO -O.OOE+OO O.OOE+OO 3.62E-03 Teen 2.43E-02 -O.OOE+OO. 6.95E O.OOE+00 0.OOE+00 O.OOE+OO 2.89E-03 Child - 4.27E-02 O.OOE+OO 1.22E-03 O.OOE+OO O.OOE+OO O.OOE+OO 1.65E-03 Infant. 2.58E-02 O.OOE+OO 7.40E-04 O.OOE+OO O.OOE+OO O.OOE+OO 5.30E-04 Dose factor - liquid release pathway (mrem/Ci released)

Sr-90 . _ _. - -. - 11

.,,,Bone.:.... l.

Liver,. .

T.,,Body,. :,.Thyroid l;',Kidney l',,Lungs , GI-LLI

,Adult 5.63E-O1 -TO.OOE+OO- 1.38E-O1 O.OOE+00 O.OE+00 O.OOE+OO -l 1.63E-02 Teen - 4.64E-O1 lO.OOE+OO l1.15E-01 :O.OOE+OO lO.OOE+OO lO.OOE+OO 1.30E-02 Child- 5.59E-O1 O.OOE+OO- 1.42E O.OOE+0 O.OOE.+OO lO.OOE+OO 7.53E-03 Infant 1.95E-O1 O.OOE+OO l 4.97E-02 'O.OOE+OO O.OOE+OO lO.OOE+OO 2.44E-03 Dose factor - liquid release pathway (mrern/Ci released)

Sr-91 . . _______.,,

-- .'. Bone_ - Liver '; l,T; .Body- 'Thyroid . Kidney,.l ', Lungs_'.', ,GI-LLI lAdult ' -1.27E-04 O.OOE+OO -5.14E O.OOE+OO lO.OOE+OO O.OOE+OO 6.05E-04 lTeen l.' 1.38E-04 O.OOE+OO- 5.51E-06: O.OOE+OO O.OOE+OO lO.OOE+OO 6.24E-04 Child - l 1.83E-04 rO.OOE+OO 6.91E-06 O.OOE+OO lO.OOE1+OO O.OOE+OO l 4.04E-04 Infant l1.59E-05 O.OOE+OO- 5.76E-07 O.OOE+00 O.OOE+00 O.OOE+OO 1.88E-05

!.i 'i ,. "P;4 e 37 of 123 REFERENCE USE

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Sr-92 Bone Liver T. Body l Thyroid Kidney Lungs GI-LLI Adult 5.21E-06 0.00+00 2.26E-07 JO.OOE+00 O0.OOE+00 O.OOE+00 1.03E-04 Teen 5.64E-06 0.OOE+00 2.42E-07 l 0.00+00 O.OOE+00 O.OOE+00 1.442-04 Child 7.20E-06 O.OOE+00 2.89E-07 l O.OOE+00 O.OOE+00 0.00E+00 1.36E-04 Infant I 9.41E-10 O.OOE+00 3.50E-1I1I O.OOE+00 O.OOE+00 0.OOE+00 1.O1E-08 Dose factor - liquid release pathway (mrem/Ci released)

Y-90 I Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 4.85E-07 O.OOE+00 1.30E-08 O.OOE+00 O.OOE+00 O.OOE+00 5.15E-03 Teen 5.162-07 0.00+00 1.40E-08 0.002+00 O.OOE+00 O.OOE+00 4.26E-03 Child 8.67E-07 O.OOE+00 2.32E-08 O.OOE+00 O0.OOE+00 0.OOE+00 2.472-03 Infant , 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 (mremlCi released)

Y -9 1 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 9.20E-06 0.OOE+00 2.53E-07 0.002+00 0.002+00 0.00+00 5.062-03 Teen [9.682-06 0.00O+00 2.97E-07 O.OOE+00 0.00O+00 0.002+00 3.97E-03 Child 1.742-05 0.002+00 4.74E-07 O.OOE+00 0.002+00 0.002+00 2.322-03 Infant 1.032-05 0.00+00 J 2.732-07 0.00E+00 0.00E+00 O.OOE+00 7.352-04 Dose factor - liquid release pathway (mrem/Ci released)

Y-91m _

l Bone Liver T. Body l Thyroid l Kidney Lungs GI-LLI Adult T1.71E-13 0.00O+00 5.10E-14 l O.OOE+00 T 0.002+00 0.002+00 5.022-13 Teen 11.852-13 0O.OOE+00 2.55E-13 0.002+00 0.002+00 O.OOE+008 8.722-12 Child 2.362-13 0.002+00 6.042-14 0.002+00 0.002+00 O.OOE+00 4.622-10 Infant j2.622-26 O.OOE+00 , 8.92E-28 0.002+00 0.002+00 O.OOE+00 8.722-23 Dose factor - liquid release pathway (mrem/Ci released)

Y-92 _

Bone Liver T. Body Thyroid l Kidney Lungs GI-LLI Adult 3.51E-09 O.OOE+00 2.882-10 0.002+00 O.OO+00 7 0.002+00 6.152S-05 Teen 3.832-09 O.OOE+00 1.152-09 0.002+00 O.OOE+00 l O.OOE+00 1.05E-04 Child 4.92E-09 0.002+00 3.572-10 0.002+00 0.002+00 T O.OOE+00 1.422-04 Infant 5.882-12 0.002+00 1.652-13 0.002+00 O.OOE+00 l O.OOE+00 1.122-07 Page 38 of 123 REFERENCE USE

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October 29, 2004 OFFSITEDOSECALCULATIONMANUAL  ;

Table 5.1-1 Dose factor - liquid release pathway (rnren/Ci released)

Y-93

.Bone': 'Liver , ' T. Body ,Thyroid ,,,Kidney, Lungs GI-LLI Adult,, 5.32E-08 0.00+00 2.33E-09 0.OOE+O0 O.OOE+00 0.00+00 1.692-03 Teen 5.77E-08= O.OOE+00 6.38E-09 0.002+00 O.OOE+0+00 0.002+00 1.76E-03 Child 7.75E-08 0.00+00 3.13E-09 0.00+00 O.OOE+0O 0.00+00 1.16E-03 Infant 8.33E-09 0.002+00 2.27E-10 O.OOE+00 0.0E+00 0.002E+00 6.58E-05 Dose factor - liquid release pathway (rnrern/Ci released)

Zr-95 - ..

Bone ,:,,Liver' T. .,Body ',,Thyroid ' Kidney_.; -',Lungs GI-LLI Adult- 1.23E-06 3.94E-07 1.79E-06 0.00+00 6.19E-07 0.OOE+0O 1.25E-03 Teen-- 1.1 lE-06 3.52E-07 8.74E-06 0.00+00 5.17E-07 '0.00+00 8.11 E-04 Child 2.48E-06 5.45E-07 2.26E-06 O.OOE+00 7.80E-07 0.002+00 5.69E-04 Infant 1.87E-06 4.562-07 3.23E-07 O.OOE+00 4.91E-07 O.OOE+00 2.27E-04 Dose factor - liquid release pathway (mrern/Ci released)

Zr-97

,Bone , - Liver . T.-Body, .,-,,Thyroid, ,-Kidney_ .,-"'Lungs lGI-LLI Adult'- 1.07E-08 2.16E-09 1.23E-08 0.00+00 3.27E-09 0.00+00 6.70E-04 Teen - 1.112l-08 2.192-09 6.42E-08 O.OOE+00 3.33E-09 0.OOE+l00 5.94E-04 Child - 2.21E-08 3.19E-09 1.51E-08 O.OOE+00 4.58E-09 0.OOE+00 4.83E-04 Infant- 1.92E-08 3.29E-09 1.50E-09 O.OOE+00 3.32E-09 O.OOE+00 2.10E-04 Dose factor - liquid release pathway (mrern/Ci released)

Nb ._,_,_ __

_______ Bone .l Liver-, 2.'Bl ody, l.,_Thyroid l,-, ,Kidney.,

. Lungs, , GI-LLI Adult 3.23E-04 1.79E-04 9.73E-05 .OOE+00 1.77E-04 O.OOE+00 1.09E+00 lTeen 3.25E-04 1.80E-04 1.04E-04 O.OOE+00 1.75E-04 O.OOE+00 7.70E-0I Child 3.84E-04 1.492-04 1.08E-04 0.00+00 1.40E-04 J 0.002+00 2.762--01 Infant 5.362-07 2.2 12-07 1.282-07 0.002+00 -. 1.582-07 j .002+00 1.862-04

• Dosefactor - liquid release pathway (rnrern/Ci released)

Nb-97. - _

l____}__Bone .. -. Liver-,'-1 .' T. Body l Thyroid_ - Kidney,, lLungs, ,, GI-LLI Adult7 2.69E-09 6.81E-10 l2.51E-10 O.OOE+00 7.95E-10 0.002+00 2.51E-06 Teen ' 2.902-09 7.20E-10 - 2.73E-10 O.OOE+00 8.412-10 0.002+00 1.72E-05 Child ' 3.68E-09.- 6.65E-10 . .3.122-10 O.OOE+00 7.38E-10 O.OOE+00 2.05E-04 Infant 5.81E-21 1.24E-10 4.47E-22 0.OOE+00 9.68E-22 0.002+00 3.91E-16

I , ._, ;-., _. ..

- , " -page 39 of 123 REFERENCE USE

AL POINT BEACH NUCLEAR PLANT ODCM OFFS1TE DOSE CALCULATION MANUAL Revision 16 October 29, 2004 OFFSITE DOSE CALCULATION MANUAL Table 5.1-1 Dose factor - liquid release pathway (mrem/Ci released)

Mo-99 IBone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult O.OOE+00 1.49E-04 2.84E-05 O.00E+00 3.38E-04 O.OOE+00 3.46E-04 Teen O.OOE+00 1.76E-04 3.36E-05 0.OOE+00 4.03E-04 O.OOE+00 3.15E-04 Child O.OOE+00 2.79E-04 6.9 1E-05 0.OOE+00 5.96E-04 O.OOE+00 2.3 1E-04 Infant 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 (mrenlCi released)

T c -9 9 m _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 1.68E-09 4.74E-09 J6.07E-08 O.OOE+00 7.20E-08 2.32E-09 2.81 E-06 Teen 1.74E-09 4.86E-09 6.46E-08 O.OOE+00 7.24E-08 2.70E-09 3.19E-06 Child 2.19E-09 4.29E-09 7.15E-08 JO.OOE+00 6.24E-08 2.18E-09 2.44E-06 Infant 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 (nrem/Ci released)

T c - 10 1 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

Bone Liver T. Body Thyroid Kidney Lungs l GI-LLI Adult 3.60E-24 5.19E-24 5.IOE-23 O.OOE+00 9.34E-23 2.65E-24 1.56E-35 Teen 3.89E-24 5.53E-24 5.49E-23 0.00E+00 1.00E-22 3.37E-24 9.45E-31 Child 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 O.OOE+00 1.46E-67 6.69E-69  ! 2.08E-66 Dose factor - liquid release pathway (mrem/Ci released)

Ru- 103 _ _

Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 3.47E-05 O.OOE+00 1.56E-05 O.OOE+00 1.32E-04 O.OOE+00 4.05E-03 Teen 2.96E-05 O.OOE+00 1.64E-05 O.OOE+00 1.04E-04 O.OOE+00 l 2.47E-03 Child 5.53E-05 O.OOE+00 2.20E-05 O.OOE+00 1.39E-04 O.OOE+00 1.43E-03 Infant 1.33E-05 0.OOE+00 I 4.43E-06 O.OOE+00 2.76E-05 O.OOE+00 1.61E-04 Dose factor - liquid release pathway (mrem/Ci released)

Ru-105 11 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 4.13E-08 O.OOE+00 1.75E-08 0.OOE+00 5.34E-07 O.OOE+00 2.53E-05 Teen 4.45E-08 0.OOE+00 2.42E-08 0.OOE+00 5.62E-07 O.OOE+00 3.59E-05 Child 5.71E-08 O.OOE+00 2.22E-08 0.OOE+00 5.02E-07 O.OOE+00 3.73E-05 Infant 6.98E-10 O.OOE+00 I 2.35E-10 0.OOE+00 5.13E-09 O.OOE+00 I 2.78E-07 Page 40 of 123 REFERENCE USE

POINT BEACH NUCLEAR C L U . PLANT

.D IIOMAA ODCM OFFSITE DOSE CALCULATION MANUAL Revision 16

",October29, 2004

-OFFSITE DOSE CALCULATION MANUAL Table 5.1-1 Dose factor - liquid release pathway (mnrem/Ci released)

Ru-106 - - -- - ,

Bone . Liver ,T. Body, Thyroid 'Kidney 'Lungs. GI-LLI Adult'- 6.712-04 0.00+00 8.76E-05 0.OOE+l00 1.30E-03 0.OOE+l00 4.34E-02 Teen - - 5.86E-04 0.00E+00 8.85E 0.00+00 1.132-03 0.002+00 2.81E-02 Child 1.132-03 0.002+00 1.44E-04 0.002+00 1.53E-03 0.OOE+00 1.76E-02

-Infant 2.23E-04 0.OOE+00 2.78E-05 0.002+00 2.63E-04 0.O2O+00 1.69E-03 Dose factor - liquid release pathway (mrem/Ci released)

Rh-105 l.Bone ... Liver. :__T. Body:l, Thyroid l.Kidney, ,Lungs GI-LLI Adult 3.352-06 2.452-06 1.62E-06 0.002+00 1.042-05 0.00E+00 3.90E-04 Teen 4.10E-06 2.96E-06 1.97E-06 0.002+00 1.26E-05 0.002+00 3.77E-04 Child '- 8.43E-06 4.522-06 3.88E-06 0.002E+00 1.802-05 0.002+00 2.802-04 Infant 1.082-05 7.052-06 4.74E-06 0.002+00 1.962-05 0.002+00 1.75E-04 Dose factor - liquid release pathway (mremn/Ci released)

Ag-10 - - - - - -- -- _

Bone Liver B:yTBody>- Thyroid - .. Kidney Lungs. GI-LLI Adult -. 3.06E-05 2.832-05 3.83E-05 . 0.002+00 5.56E-05 0.002+00 1.152-02 Teen: 3.742-05 3.542-05 1.41E-04 0.002+00 6.752-05 0.002+00 9.942-03 Child 6.78E-05 4.58E-05 6.17E-05 0.002+00 8.53E-05 0.002+00 5.45E-03 Infant 8.872-05 6.47E-05 4.282-05 0.002+00 9.262-05 0.002+00 3.36E-03 Sn-1 13 and Sn-1 17m - liquid release pathway (mrem/Ci released) _ .- :

..... ^ --

Bone - -l;:,,Liver - :W.-Body:, - Thyroid Kidney,,, . Lungs ' GI-LLI Adult 7 6.402-03 2.172-04 6.782-04 -1.26E-04 0.002+00 0.002+00 1.322-01

-.Teen 6.962-03 2.332-04 7.33E-04---l 1.282-04 l 0.00E+00 0.002+00 1.082--01 lChild..-: 9.032-03 2.282-04 -9.44E --. 1.662-04 0.002+00 0.002+00 4.612-02 Infant- -J 1.42E-04 4.43E-06 1.472-05-- - 3.07E 0.00+00 0.002+00 3.502-04 Dose factor - liquid release pathway (mrem/Ci released)

Sb-124 .

- Bone Liver - -T.--J;B ody - Thyroid - Kidney ..-...Lungs GI-LLI Adult 5.422-04 1.022-05 2.21E - 1.322-06 0.002++00 4.222-04 1.542-02 Teen l 5.662-04 1.042-05 - 2.532 1.28E-06 0.002+00 4.942-04 l 1.142-02 "I . :Child 7 7.892-04-- 1.02E 2.832 1.74E-06 0.002+00 4.382-04 4.942-03

.IInfant; 1.95E-04 -- -1I 2.86E-06 6.03E-05 II 5.177E-07 dl 0.002+00 1.22E-04 6.00E-04

... .. B...

P*--e41of12 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 16 October 29, 2004 OFFSITE DOSE CALCULATION MANUAL Table 5.1-1 Dose factor - liquid release pathway (mrenmCi released)

Sb-125 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 3.49E-04 3.90E-06 1.07E-04 3.55E-07 0.OOE+00 2.69E1-04 3.85E-03 Teen 3.65E-04 3.99E-06 2.19E-04 3.49E-07 0.00+00 3.21E-04 2.84E-03 Child 5.14E-04 3.96E-06 1.35E-04 4.76E-07 O.OOE+00 2.86E-04 1.23E-03 Infant I 1.14E-04 1.1 lE-06 2.35E-05 1.43E-07 O.OOE+00 7.17E-05 1.52E-04 Dose factor - liquid release pathway (mrem/Ci released)

Te-125m Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult l 3.30E-04 1.20E-04 4.43E-05 9.93E-05 1.34E-03 0.00+00 1.32E-03 Teen J 3.36E-04 1.21E-04 4.53E-05 9.39E-05 O.OOE+00 O.OOE+00 9.92E-04 Child l 5.74E-04 1.56E-04 7.67E-05 1.611E-04 0.OOE+0O O.OOE+00 5.54E-04 Infant I 2.47E-04 8.27E-05 3.35E-05 8.33E-05 0.00+00 0.OOE+0O 1.18E-04 Dose factor - liquid release pathway (mrem/Ci released)

Te-127 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 3.15E-05 1.13E-05 6.83E-06 2.34E-05 1.28E-04 O.OOE+00 2.49E-03 Teen 3.45E-05 1.22E-05 7.43E-06 2.38E-05 1.40E-04 0.00+00 2.67E-03 Child 4.45E-05 1.20E-05 9.54E-06 3.08E-05 1.27E-04 0.00+00 1.74E-03 Infant 3.1OE-07 1.04E-07 6.67E-08 2.52E-07 7.56E-07 O.OOE+00 6.5 1E-06 Dose factor - liquid release pathway (mrem/Ci released)

Te-127m __

Bone Liver l T. Body Thyroid Kidney Lungs GI-LLI Adult l 8.63E-04 3.08E-04 l 1.05E-04 J 2.21E-04 3.51E-03 0.OOE+l00 2.89E-03 Teen l 8.74E-04 3.10E-04 l 1.04E-04 l 2.08E-04 3.54E-03 0.OOE+l00 2.18E-03 Child l 1.502-03 4.05E-04 1.79E-04 J 3.60E-04 4.29E-03 0.OOE+00 1.22E-03 Infant I 6.282-04 2.08E-04 7.61E-05 4 1.82E-04 1.55E-03 O.OOE+00 2.54E-04 Dose factor - liquid release pathway (mrem/Ci released)

Te- 129 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult J 1.68E-08 6.322-09 4.10E-09 J 1.29E-08 7.072-08 0.002+00 1.27E-08 Teen l 1.83E-08 6.82E-09 4.45E-09 l 1.31E-08 7.68E-08 O.OOE+00 l.OOE-07 Child ' 2.36E-08 6.58E-09 5.60E-09 4 1.68E-08 6.90E-08 0.002+00 1.47E-06 Infant I 1.08E-18 3.73E-19 2.532-19 I 9.072-19 2.692-18 O.OOE+00 I 8.652-17 Page 42 of 123 REFERENCE USE

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OFFSITE DOSE CALCULATION MANUAL Revision 16

.T DS C M October 29, 2004 OFFSITE DOSE CALCULATION MANUAL

• 1iV-Table 5.1-1 Dose factor - liquid release pathway (mremnCi released)

Te-129m

., , Bone,,,, l:,:'::Liver ,T.'Body,, Thyroid Kidney Lungs GI-LLI Adult 1.35E-03 5.04E-04 2.14E-04 4.64E-04 5.63E-03 O.OOE+OO ;6.80E-03 Teen 1.37E-03 -- 5.10E-04 2.18E-04 4.43E-04 5.75E-03 O.OOE+OO 5.16E-03 Child 2.34E-03 6.54E-04 3.64E-04 7.55E-04 6.88E-03 O.OOE+OO 2.86E-03 Infant 1.04E-03 3.58E-04 1.61E-04 4.01E-04 2.61E-03 _.___+00__ 6.23E-04 Dose factor - liquid release pathway (mrem/Ci released) ' '

Te-131m - ' -

, .,,'Bone Liver TT. 'Body, Thyroid 'Kidney Lungs GI-LLI Adult 1.04E-04 5.08E-05 4.24E-05 8.05E-05 5.15E-04 O.OOE+OO 5.05E-03 Teen - 1.1IE-04 5.34E-05 4.49E-05 8.03E-05 5.56E-04 O.OOE+OO 4.28E-03 Child .-. 1.63E-04 - 5.63E-05 6.00E-05 1.16E-04 5.45E-04 - O.OOE+OO 2.28E-03 Infant 5.46E-05 2.20E-05 1.8 1E-05 4.45E-05 1.5 1E-04 O.OOE+OO 3.70E-04 Dose factor - liquid release pathway (mremlCi released) ' -

Te-131

- 'Bone ,,;:,Liver. ,,,T. Body' , Thyroid ,Kidney,, Lungs GI-LLI

'Adult 2.97E-15 1.24E-15 9.40E-16 2.44E-15 1.30E-14 ' O.OOE+OO 4.21E-16 Teen . 3.21E-15 1.32E-15 1.O1E-15 2.47E-15 1.40E-14 O.OOE+OO 2.63E-16 Child 4.12E-15 - 1.25E-15 1.23E-15 3.15E-15 1.24E-14 -O.OOE+OO 2.16E-14 Infant 4.22E-41 1.56E-41 1.18E-41 3.77E-41 1.08E-40 0.00E+OO 1.71E-39 Dose factor - liquid release pathway (mrem/Ci released)

Te-132 - - - --- --- -- - '

l .',, Bone '  :,.Liver,-, ,, T. Body' Thyroid ., ,:Kidney ",Lungs 1_GI-LLI' Adult. 1.96E-04 1.26E-04 1.19E-04 1.40E-04 1.22E-03 lO.OOE+OO l 5.98E-03 Teenu 2.05E-04 1.30E-04 1.22E-04 1.37E-04 71.24E-03 rO.OOE+OO 4.1 1E-03 Child 3.15E-04 J 1.39E-04 1.69E-04 2.03E-04 1.29E-03 O.OOE+l0 1.40E-03

'Infant 1.481E-04 J7.321E-05 6.83E3-05 1.08E3-04 4.58E3-04 O.OOE3+00 2.71E-04 Dose factor - liquid release pathway (mrem/Ci released)

I-131 *  :- . , , 11 Bone, :l,-,Liver , T._Body_ . Thyroid, Kidney Lungs. GI-LLI lAdult - 2.09E-04 - 2.99E-04 1.71E-04 9.78E-02 5.12E-04 O.OOE+OO l 7.88E-05 Teen. -, 2.41E-04 3.37E-04 1.81E-04 9.83E-02 5.80E-04 O.OOE+OO 6.66E-05 Child .l 4.90E-04 l 4.93E-04 2.80E-04 1.63E-01 8.09E-04 O.OOE+OO l 4.39E-05 Infant -' 5.71E 6.73E-04 2.96E-04 l2.21E-O1 7.86E-04 O.OOE+OO 2.40E-05

. f '. , I - -

.. I . ) . age 43 of 123 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSLTE DOSE CALCULATION MANUAL Revision 16 October 29, 2004 OFFSITE DOSE CALCULATION MANUAL Table 5.1-1 Dose factor - liquid release pathway (mrem/Ci released) 1-132 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 1.43E-07 3.81E-07 1.34E-07 1.33E-05 6.07E-07 O.OOE+OO 7.16E-08 Teen 1.49E-07 3.901E-07 1.41E-07 1.323E-05 6.15E-07 O.OOE+OO 1.70E-07 Child 1.85E-07 3.39E-07 I.56E-07 1.57E-05 5.19E-07 O.OOE+OO 3.99E-07 Infant I .64E-11 3.32E-11 1.18E-II 1.56E-09 3.71E-11 O.OOE+OO 2.69E-II Dose factor - liquid release pathway (mrem/Ci released)

I-133 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 3.33E-05 5.80E-05 1.77E-05 8.52E-03 1.O1E-04 O.OOE+OO 5.21E-05 Teen 3.74E-05 6.34E-05 1.94E-05 8.85E-03 1.I IE-04 O.OOE+OO 4.80E-05 Child 6.27E-05 7.75E-05 2.94E-05 1.44E-02 1.29E-04 O.OOE+OO 3.13E-05 Infant 4.77E-05 6.95E-OS 0 2.04E-05 1.26E-02 8.17E-O5 O.OOE+OO 1.18E-05 Dose factor - liquid release pathway (mremlCi released) 1-134 Bone Liver l T. Body Thyroid Kidney Lungs l_GI-LLI Adult l 2.09E-10 5.69E-10 2.04E-10 9.85E-09 9.04E-10 O.OOE+OO 4.96E-13 Teen j 2.20E-10 5.82E-10 2.10E-10 9.70E-09 9.18E-10 O.OOE+OO 7.67E-12 Child 2.72E-10 5.05SE-IO l2.33E-10 1.16E-08 7.72E-10 O.OOE+OO l3.35E-10 Infant T 5.37E-22 l.IOE-21 3.91E-22 2.56E-20 I.23E-21 O.OOE+OO 1. 14E-21 Dose factor - liquid release pathway (mrem/Ci released) 1-135 _

l Bone Liver T. Body Thyroid Kidney Lungs l GI-LLI Adult l 3.37E-06 8.83E-06 3.26E-06 l5.82E-04 1.42E-05 O.OOE+OO l9.97E-06 Teen l 3.55E-06 9.14E-06 3.41E-06 l5.88E-04 l 1.44E-05 O.OOE+OO 1.O1E-05 Child T 4.54E-06 8.17E-06 3.87E-06 T 7.24E-04 T 1.25E-05 O.OOE+OO T 6.23E-06 Infant l 4.48E-07 8.92E-07 3.25E-07 7.99E-05 O 9.94E-07 O.OOE+OO l3.23E-07 Dose factor - liquid release pathway (mrernlCi released)

Cs- 134 11 Bone Liver T. Body Thyroid l Kidney, Lungs GI-LLI Adult 2.19E-O1 5.21E-01 4.26E-O1 O.OOE+OO l 1.69E-O1 5.60E-02 9.12E-03 Teen 2.25E-O1 5.30E-01 2.46E-O1 O.OOE+OO T 1.68E-01 6.43E-02 6.59E-03 Child 2.76E-01 4.52E-01 9.55E-02 O.OE+l00 1.40E-01 5.03E-02 2.44E-03 Infant I 1.07E-02 2.00E-02 2.02E-03 O.OOE+00 5.16E-03 2.1 1E-03 5.44E-05 Page 44 of 123 REFERENCE USE

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OFFSITE DOSE CALCULATION MANUAL - Revision 16 '

DC .AL MA , ,October 29, 2004 OFFSITE DOSE CALCULATION MANUAL- '.'

Table 5.1-1 Dose factor - liquid release pathway (mrem/Ci released)

Cs-134m

"-:,' Bone Liver  ;:,XT. Body . .. Thyroid;.  ::Kidney ',Lungs ,', GI-LLI Adult - 4.21E-06 8.85E-06 -4.52E O.OOE+OO 4.80E-06 7.56E-07 3.12E-06 Teen ' 4.42E 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 O.OOE+OO 4.28E-06 7.07E-07 1.03E-05 Infant - 5.19E-11 8.64E-11 4.37E-11 O.OOE+OO 3.33E-11 7.67E-12 6.84E-1 IJ Dose factor - liquid release pathway (mremnCi released)

Cs-136 - - - --' -_--_-_-_

' 1.' "lBone - . 'Liver , ',,T.;Body Thyroid Kidney . Lungs -,,GI-LLI Adult - 2.23E-02 8.81 E-02 6.34E-02 O.OOE+OO 4.90E-02 6.72E-03 1.OOE-02 7Teen - 2.25E-02 8.85E-02 5.95E-02 -O.OOE+OO 4.82E-02 7.59E-03 7.12E-03 Child 2.69E-02 7.40E-02 4.79E-02 -O.OOE+OO 3.94E-02 5.87E-03 2.60E-03 Infant ' 1.18E-03 3.47E-03 1.29E-03 O.OOE+OO 1.38E-03 2.83E-04 5.27E-05 Dose factor - liquid release pathway (mrern/Ci released)

Cs-137 -

. . ,Bone. Liver- . T. .B Thyroid ':Kidney- .- "Lungs GI-LLI Adult 2.81E-01 3.84E-01 2.52E-O1 O.OOE+OO 1.30E-01 4.33E-02 7.43E-03 Teen - 3.02E-01 4.01E-O1 1.40E-O1 O.OOE+OO 1.36E-01 5.30E-02 5.71E-03 Child 3.85E-01 3.69E-01 5.45E-02 O.OOE+OO 1.20E-01 - 4.33E-02 2.31E-03 Infant 1.49E-02 1.74E-02 1.24E-03 O.OOE+OO 4.68E-03 1.89E-03 5.45E-05 Dose factor - liquid release pathway (mreinCi released)

Cs-138 - - - _

Bone '->.Liver ': :4 xT.aBody .. Thyroid Kidney . Lungs', -GI-LLI

.Adult . 3.57E-11 7.04E-11 3.49E-1l O.OOE+OO 5.18E-111 5.11E-12 3.OOE-16 Teen 3.82E-11 l 7.34E-11 l 3.67E-l O.OOE+OO l 5.42E-11 6.30E-12 3.33E-14 Child 4.84E-11 6.73E-11 l 4.27E-ll l O.OOE+OO 4.73E-11 5.10E-12 3.10E-11 lInfant 1.63E-32 2.65E-32 1 .28E O.OOE+OO 1.32E-32 2.06E-33 4.23E-32 Dose factor - liquid release pathway (mremlCi released)

Ba-139 - - - - - -- --- '-

l Bone l .Liver

'.  :. T., Body . Thyroid Kidney. .1l Lungs

. - GI-LLI Adult 1.67E 1.19E-12 - 4.93E- I O.OOE+OO l 1.12E-12 J6.77E-13 2.97E-09 Teen 1.83E-09 1.29E-12 5.50E-11 O.OOE+OO l 1.21E-12 J8.87E-13 1.63E-08 Child - l-2.35E-09 1.25E-12 6.84E-11 l O.OOE+OO l 1.09E-12 l7.37E-13 1.36E-07 Infant -- 3.30E 2.19E-19 9.55E-18 O.OOE+OO 1.31E-19 1.33E-19 2.09E-14 I ,7 . 1.i -,I .'.SI

.. .. , ,71- _."

h":' Page45 of 123 REFERENCE USE

-l POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 16 October 29, 2004 OFFSITE DOSE CALCULATION MANUAL Table 5.1-1 Dose factor - liauid release tathwav (mrem/Ci released)

Ba-140 l Bone Liver T. Body l Thyroid Kidney Lungs GI-LLI Adult 5.34E-04 6.71E-07 3.5 1E-05 O.OOE+00 2.28E-07 3.84E-07 1.10E-03 Teen 5.41E-04 6.63E-07 3.56E-05 0.00+00 2.25E-07 4.46E-07 8.35E-04 Child 1.32E-03 1.16E-06 7.72E-05 0.OOE+00 3.76E-07 6.89E-07 6.69E-04 Infant 1.52E-03 I1.52E-06 7.84E-05 0.OOE+00 3.61 E-07 9.34E-07 3.742-04 Dose factor- liquid release pathway (mrem/Ci released)

Ba-141 Bone Liver l T. Body Thyroid l Kidney Lungs GI-LLI Adult 4.57E- 19 3.452-22 1.63E-20 0.00+00 3.21 E-22 1.96E-22 2.15E-28 Teen 4.96E-19 3.702-22 2.142-20 0.002+00 3.442-22 2.53E-22 1.06E-24 Child 6.37E-19 3.57E-22 2.18E-20 0.00E+00 3.09E-22 2.10E-21 3.63E-19 Infant 1.58E-53 1.08E-56 4.99E-55 0.002+00 6.52E-57 6.602-57 1.93E-52 Dose factor - liquid release pathway (mremlCi released)

La- 140 l Bone Liver T. Body l Thyroid Kidney Lungs GI-LLI Adult 3.66E-08 1.84E-08 1.032-07 E0.002+00 l 0.00+00 0.002+00 1.35E-03 Teen 3.68E-08 1.812E-08 5.51 E-07 0.00E+00 l 0.00+00 0.00+00 1.04E-03 Child j 8.21E-08 2.87E-08 1.24E-07 O.OOE+00 O.OOE+00 O.OOE+00 8.00E-04 Infant 8.562-08 3.38E-08 8.69E-09 O.00O+00 J 0.00+00 0.00+00 3.97E-04 Dose factor - liquid release pathway (mrem/Ci released)

La- 142 __

Bone Liver T. Body Thyroid l Kidney Lungs GI-LLI Adult 2.92E-11 l 1.33E-11 l 4.94E-1I1I 0.002+00 O.OOE+00 0.00+00 9.71E-08 Teen 3.12E-l11 1.38E-11 l 2.61E-10 0.00E+00 0.00+00 0.002+00 4.21E-07 Child 3.93E-11 1.252-11 5.77E-1II 0.002++00 0.00+00 O.OOE+00 2.48E-06 l Infant I 7.74E-18 2.84E-18 6.81E-19 0.00O+00 O.OOE+00 O.OOE+00 4.832-13 Dose factor - liquid release pathway (mrem/Ci released)

Ce- 141 __

Bone Liver;, T. Body l Thyroid Kidney- Lungs - GI-LLI Adult 2.05E-07 1.39E-07 2.42E-07 0.00E+00 6.45E-08 0.00E+00 5.3 1E-04 Teen 2.06E-07 1.37E-07 4.88E-07 0.00+00 6.47E-08 0.002+00 3.93E-04 Child 5.80E-07 2.89E-07 1.422-07 O.OOE+00 1.27E-07 O 2OOE+003.61E-04 Infant 7.1 1E-07 4.342-07 5.1IE-08 0.002+00 1.34E-07 0.00E+00 2.242-04 Page 46 of 123 REFERENCE USE

POINT BEACH NUCLEAR PLANT  ; . . . .

ODCM I I . . :, 1 OFFSITE DOSE CALCULATION MANUAL - -Revision 16

.. October 29, 2004 I . - s.' .

OFFSITE DOSE CALCULATION MANUAL --

Table 5.1-1 Dose factor - liquid release pathway (mrem/Ci released)

Ce-143 Bone Liver ' T. Body Thyroid Kidney Lungs,',., GI-LLI

-Adult 1.47E 1.09E-05 1.78E-08 O.OOE+00 4.78E-09 0.00+00 4.06E-04 Teen 1.49E-08 1.08E-05 9.40E-08 0.00+00 4.86E-09 O.OOE+00 3.26E-04 Child - 4.01E-08 2.17E-05 2.25E-08 O.OOE+00 9.12E-09 O.OOE+00 3.18E-04 Infant; 5.10E-08 3.38E-05 3.86E-09 O.OOE+00 9.85E-09 0.00E+00 1.97E-04 Dose factor - liquid release pathway (mrem/Ci released)

Ce-144 - --- -_-_-- ---

__._'l Bone,:. ' Liver T."Body.-' Thyroid ' Kidney 'Lungs GI-LLI

-Adult. 1.12E-05 4.67E-06 1.04E-06 0.OOE+00 l 2.77E-06 0.00+00 3.78E-03 Teen ' 1.12E-05 4.65E-06. 3.03E-06 O.OOE+00 2.78E-06 O.OOE+00 :2.82E-03 Child 3.17E-05 9.92E-06 2.20E-06 0.002+00 5.50-06 0.OOE+00 2.59E-03 Infant - 2.80E-05 I 1.151-05 1.57E 0.00E+00 4.632-06 0.OOE+00 1.61E-03 Dose factor - liquid release pathway (mrem/Ci released)

Pr-143 - --

Bone 7 .. KLiver.:: iT.~ Body-, ,:Thyroid

. J Kidney ,-Lungs,

. GI-LLI Adult 5.69E-07 2.28E-07 2.82E-08 0.002+00 1.322-07 0.00E+00 2.49E-03 Teen, 6.00E-07 2.40E-07 2.99E-08 0.002+00 1.392-07 0.00+00 1.97E-03 Child 1.072-06 3.212-07 5.31E-08 - 0.002+00 1.74E-07 O.OOE+00 1.152-03 Infant- 6.812-07 2.552-07 3.38E-08 O.OOE+00 9.47E-08 0.002+00 3.60E-04 Dose factor - liquid release pathway (mremlCi released)

Pr-144 - - - -- -_-_-___

.Bone .Liver,

'. .T. .Body. Thyroid '-: Kidney". Lungs - GI-LLI lAdult 3.76E-22 1.56E-22 2.242 0.002+00 8.802-23 0.002+00 5.412-29 Teen 4.09E-22 1.67E-22 3.91E-23 0.002+00 l 9.612-23 O.OOE+00 4.512-25 lChild- 5.292-22 1.64E-22 3.05E-23 0.002+00 l 8.66E-23 0.002+00 3.522--19 Infant' 1.72E-59 6.662-60 8.67E-61 0.002O+00 I 2.41E-60 0.002+00 3.102-55

• Dosefactor - liquid release pathway (mremlCi released)

INd-147 -- - -

Bone . l -'Liver. '-T..Body - Thyroid l -Kidney, -, Lungs .: 'GI-LLI lAdult - 3.82E-07 4.42E-07 1;.13E O.OOE+00 2.582-07 0.002+00 2.12E-03 Teen -. 4.23E - 4.60E-07 - 5.09E-07 0.002+00 2.70E-07 0.002+00 1.662-03 Child -'- 7.45E-07 6.032-07 - -1.47E - 0.002+00 l3.31E-07 0.002++00 9.552-04

-Infant 4.53E-07 4.65E-07 2.85E-08 0.002+00 l 1.792-07 0.002+00 l2.95E-04

~Page47 of 123 REFERENCE USE

- aL POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 16 October 29, 2004 OFFSITE DOSE CALCULATION MANUAL Table 5.1-1 Dose factor - liquid release pathway (mrem/Ci released)

Eu-152 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 1.31E-05 2.99E-04 1.63E-04 O.OOE+00 1.85E-05 O.OOE+00 1.72E-03 Teen 1.211E-05 2.92E-06 9.00E-04 O.OOE+00 1.35E-05 O.OOE+00 1.07E-03

-Child 1.84E-05 3.34E-06 1.911E-04 O.OOE+00 1.41E-05 -O.OOE+00 5.49E-04 Infant 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 (mreriiCi released)

W-187 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 1.52E-04 1.27E-04 4.45E-05 O.OOE+00 O.OOE+00 O.OOE+00 4.17E-02 Teen 1.65E-04 1.34E-04 4.71 E-05 O.OOE+00 O.OOE+00 O.OOE+00 3.63E-02 Child 2.09E-04 1.24E-04 5.57E-05 O.OOE+00 O.OOE+00 O.OOE+00 1.74E-02 Infant 2.25E-06 1.57E-06 _ 5.4 1E-07 O.OOE+00 O.OOE+00 O.OOE+00 9.2 1E-05 Dose factor - liquid release pathway (mrem/Ci released)

Np-239 _

Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 3.15E-08 3.09E-09 J 2.30E-08 O.OOE+00 9.65E-09 O.OOE+00 6.34E-04 Teen 3.42E-08 3.22E-09 l 1.21E-07 lO.OOE+00 1.01E-08 O.OOE+00 5.19E-04 Child 6.77E-08 4.86E-09 J 2.83E-08 O.OOE+00 1.41E-08 O.OOE+00 3.60E-04 Infant 5.72E-08 5.12E-09 l 2.89E-09 lO.OOE+00 1.02E-08 lO.OOE+00 1.48E-04 Dose factor - liquid release pathway (mrem/Ci released)

U-235 _

Bone Liver 7 T. Body 7 Thyroid Kidney Lungs 7_GI-LLI Adult [ 3.05E-02 O.OOE+00 1.89E-03 lO.OOE+00 7.13E-03 O.OOE+00 l 2.98E-03 Teen l 3.17E-02 lO.OOE+00 2.13E-03 O.OOE+00 7.43E-03 lO.OOE+00 2.30E-03 Child J 6.92E-02 0.OOE+00 4.23E-03 0.OOE+00 1.14E-02 O.OOE+00 1.63E-03 Infant 4.42E-02 0..OOE+00 I 3.37E-03 O.OOE+00 9.40E-03 0.OOE+00 7.67E.-04 Dose factor - liquid release pathway (mrenmCi released)

U-238 __

Bone Liver l T. Body l Thyroid Kidney Lungs l_GI-LLI Adult 7 2.92E-02 0.OOE+00 l 1.73E-03 7O.OOE+00 6.67E-03 lO.OOE+00 J2.1OE-03 Teen J 3.03E-02 0.OOE+00 l 1.81E-03 O.OOE+00 6.96E-03 O.OOE+00 1.62E-03 Child l 6.62E-02 lO.OOE+00 3.93E-03 O.OOE+00 1.06E-02 O.OOE+00 1.15E-03 Infant j 4.23E-02 O.OOE+00 I 3.15E-03 O.OOE+00 I 8.78E-03 O.OOE+00 l 5.4 1E-04 Page 48 of 123 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL i Revision 16

.I ,>. October 29, 2004

.- OFFSITE-DOSE CALCULATION MANUAL, 11 I s. . ....

Table 5.1-1 Dose factor - liquid release vathwav (mrem/Ci released)

Am-241

-. Bone - Liver "--T.'- Body" Thyroid Kidney Lungs GI-LLI Adult 5.25E-02 1.85E-02 3.47E-03 O.OOE+00 2.61E-02 0.002+00 4.75E-03

-Teen 4.102-02 1.56E-02 2.77E-03 0.002+00 2.05E-02 O.OOE+00 3.74E-03 Child - 4.10E-02 1.83E-02 2.93E-03 :. 0.00+00 1.79E-02 O.OOE+00 2.19E-03 Infant  : 1.42E-02 6.68E-03 1.O1E-03 O.OOE+00 6.10E-03 O.OOE+00 7.17E-04 E..i I  ; 7 _ - ' ,

. . - I I I I ", r -

. I

. - i 1  : . ' .- , . - .7 .

I .

I -

• I - of Page`49 o 2 REFERENCE USE

J-u-POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 16 October 29, 2004 OFFSITE DOSE CALCULATION MANUAL Table 5.1-2 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 radionuclides released to the atmosphere will be done in the manner similar to the liquid release dose calculations described in Section 5.1.1. The total dose is compared to the corresponding atmospheric release mode Appendix I dose limit for the organ in question.

The doses are calculated using the following formula:

API = Z Doseaomi = E (TDFaomi X C) < 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) via release 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) from Table 5.1-2 in mrem/Ci C; = curies of radionuclide (i) released Kom = the Appendix I dose limit for organ (o) and release mode (m) for which the calculation is being made.

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

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

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

Page 50 of 123 REFERENCE USE

• It'~~, %'

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 16 D.O 3 ,.

I I . ..

.. October 29, 2004 OFFSITE DOSE CALCULATION MANUAL Table 5.1-2 TABLE 5.1-2 AIRBORNE EFFLUENT DOSE FACTOR Summations of dose per curie released were made for calculations over the pathways: ingestion of produce, leafy.vegetables, milk, meat; inhalation of airborne radionuclides, and direct exposure to deposited radioactivity.

Dose factor - airborne release pathway (mrernlCi released)

H-3 - _ ' '

,one Liver T. 'Body" 'Thyroid Kidney^- 'Lungs', -GI-LLI '<-,Skin Adult O.OOE+00 2.34E-04 2.34E-04 2.34E-04 2.34E-04 2.34E-04 2.34E-04 O.OOE+00 Teen 0.00E+00 2.69E-04 2.69E 2.69E-04 2.69E-04 2.69E-04 2.69E O.OOE-+00 Child 0.OOE+00 3.93E-04 3.93E 3.93E-04 3.93E-04 3.93E-04 3.93E-04 0.0E+00 Infant 0.OOE+00 1.73E-04 1.73E-04 1.73E-04 1.73E-04 1.73E-04 1.73E-04 -O.OE+00 Dose factor - airborne release pathway (mrernlCi released) _____ __________

F '..Bone - n Liver, T.' Bodye -,Thyroid ' Kidney Lungs'-` GI-LLI Skin Adult 1.12E-04 0.OOE+00 9.61E-04 O.OOE+00 -O.OOE+00 0.OOE+00 2.19E-06 2.23E-03 Teen l.55E-04 0.OOE+00 9.65E-04 0.00E+00 0.00E+00 0.OOE+00 9.23E-06 2.23E-03 Child - 2.06E-04 O.OOE+00 9.69E-04 O.OOE+00 O0.OOE+00 O.OOE+00 3.70E-05 2.23E-03 Infant 1.63E-04 O.OOE+00 9.62E O.OOE+00 O.OOE+00 O.00E+00 2.53E-05 2.23E-03 Dose factor - airborne release pathway (mrern/Ci released)

Na-22 -- - --

Bone l-Liver T.-Body,:-Thyroid Kidney .Lungs GI-LLI '-, ,Skin-Adult' 4.83E+00 4.83E+00 2.89E+01 - 4.83E+00 4.83E+00 4.83E+00 4.83E+00 3.79E+01 Teen ' 7.41E+00 7.41E+00 3.15E+01 7.41E+00 7.41E+00 7.41E+00 7.41E+00 7 3.79E+01 Child 1.50E+01 1.50E+01 3.90E+01 1.50E+01 1.50E+01 1.50E+01 1.50E+01 3.79E+01 Infant 1.81E+01 1.81E+01 4.21E+01 1.81E+01 1.81E+01 1.81E+01 1.81E+01 j 3.79E+01 Dose factor - airborne release pathway (mrern/Ci released)

Na-24 ' - - -- - - -_ _ __ _

lBone" - 'Liver - T.- Body 'Thyroid Kidney, l,^'Lungs - GI-LLI,-, Skin, Adult - 9.48E-04 J 9.48E-04l 1.77E-02 9.48E-04 9.48E-04 9.48E-04 9.48E-04 7.64E-02

.Teen -- 1.36E-03-- 1.36E-03 1.81E-02 -l 1.36E-03 1.36E-03 1.36E 1.36E-03 7.64E-02 Child,- - 2.37E-031- 2.37E-03 1.91E 2.37E-03 2.37E-03 2.37E-03 2.37E-03 7.64E-02 Infant.= 3.1403 3.14103 -1.99E-02 3.141E03 3.14E 03 3.14E 03 3.14E-03 7.64E-02

, . . - . I .

I. I I I. I I

-, 1 , '

. *-.- I* . s f I @:. ..

.8 . .. . ... ..  !. .. I - I

' '" Page 51 of 123 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 16 October 29, 2004 OFFSITE DOSE CALCULATION MANUAL Table 5.1-2 Dose factor - airborne release pathway (mrem/Ci released)

Sc-46 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 1.332-02 2.59E-02 2.00E+00 [0.002+00 2.42E-02 0.002+00 2.40E+00 2.69E+00 Teen 1.75E-02 3.41 E-02 2.00E+00 O.OOE+00 3.26E-02 0.OOE+00 2.09E+00 2.69E+00 Child 2.232-02 3.052-02 2.00E+00 O0.OOE+00 2.70E-02 0.OOE+00 1.32E+00 2.69E+00 Infant 1.56E-02 2.25E-02 I 2.00E+00 I 0.OOE+00 1.48E-02 0.002+00 1.35E-03 2.69E+00 Dose factor - airborne release pathway (mremlCi released)

Mn-54 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 0.OOE+00 2.32E-01 1.99E+00 0.00+00 6.89E-02 4.15E-02 7.08E-01 2.282+00 Teen 0.OOE+00 3.34E-01 2.O1E+00 0.00+00 9.95E-02 5.89E-02 6.83E-01 2.28E+00 Child 0.OOE+00 4.86E-01 2.07E+00 0.00E+00 1.36E-01 4.68E-02 4.08E-01 2.28E+00 l Infant 0.00E+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-51 __

Bone Liver T. Body Thyroid Kidney 7 Lungs GI-LLI Skin Adult O.OOE+00 O.OOE+00 6.592-03 [2.68E-05 9.86E-06 4.83E-04 1.072-02 7.73E-03 Teen O.OOE+00 O.OOE+00 6.60E-03 3.392-05 1.34E-05 7.03E-04 9.66E-03 7.73E-03 Child 0.002+00 0.002+00 6.66E-03 J 6.302-05 1.72E-05 6.14E-04 5.812-03 7.732-03 Infant l O.OOE+00 O.OOE+00 I 6.58E-03 1 2.422-05 j5.312-06 I 4.252-04 I 1.022-03 I 7.732-03 Dose factor - airborne release pathway (mrem/Ci released)

Mn-56

__ l_ Bone Liver l T.Body Thyroid Kidney Lungs GI-LLI Skin Adult 0.002+00 4.81E-08 l 1.27E-03 0.002+00 [5.31E-08 [2.802-04 6.012-04 1.502-03 Teen 0.002+00 6.05E-08 11.272-03 1O.OOE+00 16.612-08 14.51E-04 1.70E-03 1.502-03 Child 0.002+00 6.262-08 1.272-03 10.002+00 16.58E-08 1 3.902-04 3.662-03 1.502-03 Infant 0.002+00 l 4.57E-08 1 1.272-03 1 0.002+00 l 3.272-08 3.72E-04 l2.13E-03 l1.2-03 Dose factor - airborne release pathway (mrem/Ci released)

Fe-55 Bone Liver T. Body Thyroid Kidney l Lungs GI-LLI Skin Adult 3.202-01 2.21E-01 5.15E-02 0.002+00 0.002+00 l 1.252-01 l 1.272-01 O.OOE+00 Teen 3.80E-01 2.70E-01 16.29E-02 O.OOE+00 0.002+00 1.74E-01 1.172-01 0.002+00 Child 8.65E-01 4.59E-01 1.42E-01 O.OOE+00 O.OOE+00 12.622-01 1 8.492-02 0.002+00 Infant 7.362-02 I 4.752-02 I 1.272-02 I 0.00E+00 O.OOE+00 12.56E-02 1 6.022-03 O.OOE+00 Page 52 of 123 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM  ;-

OFFSITE DOSE CALCULATION MANUAL Revision 16

• '. October 29, 2004 OFFSITE DOSE CALCULATION MANUAL Table 5.1-2 Dose factor - airborne release pathway (mremlCi released)

Fe - - -

l-Bone l Liver l T. Body,. 'Thyroid l Kidney. . Lungs ,-.. GI-LLI . . ;Skin Adult - 2.01E-01 4.73E-01 5.65E 0.OOE+00 0.00+00 1.62E-01 - 1.58E+00 4.50E-01 Teen 2.25E-01 5.24E-01 5.86E 0.OOE+00 0.OOE+00 2.10E-01 1.24E+00 4.50E-01 Child 4.62E-01 7.48E-01 7.56E-01 : .OOE+00 0.00+00 2.54i-01 7.80E-01 4.50E-01 Infant 6.14E-02 1.07E-01 4.26E O.OOE+O0 O.OOE+00 6.16E-02 5.16E-02 4.50E-01 Dose factor - airborne release pathway (mrem/Ci released)

Co-57 _

"Bone, -'Liver T. Body -Thyroid Kidney.. Lungs -: GI-LLI "Skin, Adult 0.002+00 1.17E-02 4.932-01 O.OOE+00 0.002+00 1.IOE-02 2.97E-01 6.13E-01 Teen O.OOE+00 - 1.59E-02 5.00E-01 0.00+00 0.OOE+00 1.74E-02 2.97E-01 6.13E-01 Child O.OOE+00 2.57E-02 5.26E0-1 O.OOE+00 0.002+00 1.502-02 2.1 lE-Ol 6.13E-01 Infant OO.E+00 4.38E-03 4.81E-01 O.OOE+00 0.002+00 1.13E-02 1.50L-02 6.13E-01 Dose factor - airborne release pathway (mrem/Ci released) - - -

Co-58 - --

Bone Liver T. Bodytl Thyroid l Kidney -Lungs 'GI-LL Skin Adult 0.002+00 3.142-02 6.02E-01 0.002++00 l0.00+00 l 2.75E-02 6.382-01 6.232-01 Teen O.OOE+00 4.00E-02 6.2421-01I 0.00E+00 0.002+00 3.99E 5.53E-01 6.232-01 Child 0.OOE+l00 5.73E-02 7.07E O.OOE+00 0.00+00 3.28E-02 3.35E 6.23E-01 Infant 0.002+00 T9.90E-03 5.57E 0.002+00 0.0023+00 2.312-02 2.49E-02 6.23E-01 Dose factor - airborne release pathway (mrenlCi released)

Co - _ -_ _ - =_-=___-_

-Bone .l- Liver' T. Body -l,Thyroidl Kidney -'..Lungs.,: GI-LLI. l - .LSkin Adult O.OOE+00 T 1.682-01 3.06E+01 O.OOE+00 0.002+00 1.77E-01 3.16E+00 l 3.56E+01 Teen 0.002.+00 2.232-01 3.07E+01 - 0.002+00 0.002+00 2.592-01 2.902+00 3.56E+01 Child O.OOE+00 3.282 3.12E+01- 0.002+00 0.002+00 2.102-01 1.822+00 3.56E+01 Infant 0.00E+00 5.862-02 3.04E+01 - 0.00E+00 0.00E+00 1.34E-01 1.402-01 3.562+01 Dose factor - airborne release pathway (mrenlCi released)

Ni-63 - - -__- -_- -__

i;-. l;.Bone. ,,Liver,':. -T. Body  !' Thyroid, Kidney.-.' 7Lungs GI-LLI l ._ Skin Adult 2.392+01 1.65E+00 8.OOE-01 --l 0.00E+00 0.002+00 5.292-03 -3.45E-01 0.002+00 Teen 2.93E+01 2.07E+00 9.92E-01 -- 0.002+00 0.00+00 l9.1 1E-03 3.29E 0.002+00 Child -- 6.73E+01 3.602+00 2.29E+00 - 0.002+00 0.002+00 8.162-03 2.432-01 0.002+00 Infant 2.112+01 1.302+00 7.32E-01 0.002+00 0.00+00 6.19E-03 6.49E 0.002+00 1 ,. !:"-! : !,.

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Ni-65

_ Bone Liver T. Body Thyroid Kidney Lungs GI-LLI 1 Skin Adult 8.95E-08 1.19E-08 4.17E-04 O.OOE+0O O.OOE+00 1.66E-04 3.66E-04 4.85E-04 Teen 1.06E-07 1.39E-08 4.17E-04 O.OOE+000 .OOE+00 2.78E-04 1.09L-03 j 4.85E-04 Child 1.64E-07 1.58E-08 4.17E-04 O.OOE+0O O.OOE+00 2.43E-04 2.49E-03 4.85E-04 Infant 7.17E-08 18.5 1E-09 J 4.17E-04 W O.OOE+00 0.OOE+00 2.4 1E-04 1.49E-03 l 4.85E-04 Dose factor - airborne release pathway (mrem/Ci released)

Cu-64

_ Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult O.OOE+00 1.12E-05 8.57E-04 0.OOE+00 2.82E-05 2.01E-04 2.40E-03 9.65E-04 Teen O.OOE+00 1.40E-05 8.58E-04 0.00E+0O 3.54E-05 3.30E-04 2.90E-03 9.65E-04 Child 0.00E+00 2.19E-05 8.65E-04 O.OOE+OO 5.28E-05 2.84E-04 2.1 IE-03 9.65E-04 Infant O.OOE+00 I 3.42E-05 I 8.68E-04 O.OOE+00 5.79E-05 2.762-04 1.15E-03 9.65E-04 Dose factor - airborne release pathwayr (mrerniCi released) -_____ _____-_____ _____

Zn-65 __

Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 1.21E+00 3.85E+00 2.79E+00 l 0.OOE+00 l 2.57E+00 l 2.56E-02 2.42E+00 1.212+00 Teen 1.63E+00 5.67E+00 3.69E+00 O.OOE+00 l 3.63E+00 l 3.68E-02 2.40E+00 1.212E+00 Child 3.12E+00 8.3 1E+00 l 6.22E+00 O.OOE+00 l 5.24E+00 l 2.95E-02 1.46E+00 1.21E+00 Infant l 2.95E+00 1.01E+01 5.71E+00 I.OOE+OO J 4.91E+00 1.92E-02 8.54E+00 l1.21E+00 Dose factor - airborne release pathway (mremlCi released) -

Zn-69 -

Bone Liver T. Body Thyroid Kidney Lungs - GI-LLI Skin Adult 3.01E-06 5.762-06 4.01E-07 0.0012+00 3.74E-06 2.73E-05 l 1.35E-06 O.OOE+00 Teen 4.64E-06 8.832-06 6.18E-07 O.OOE+00 5.77E-06 4.70E-05 2.47E-05 O.OOE+00 Child 1.08E-05 1.56E-05 1.45E-06 O.OOE+00 9.49E-06 4.22E-05 1.29E-03 O.OOE+OO Infant 1.93E-05 I 3.48E-05 I 2.59E-06 I 0.OOE+0OO 1.45E-05 4.36E-05 3.23E-03 O.OOE+00 Dose factor - airborne release pathwvay (mren/Ci released)

Zn-69m __

I Bone Liver T. Body Thyroid l Kidney Lungs GI-LLI l Skin Adult 4.99E-05 1.20E-04 3.07E-03 1O.OOE+00 7.26E-05 5.65E-04 J 1.132-02 5.74E-03 Teen 7.60E-05 1.79E-04 3.07E-03 0.00E+00 1.09E-04 9.30E-04 11.49-02 5.74E-03 Child 1.76E-04 3.00E-04 3.09E-03 l O.OOE+00 l 1.74E-04 l 8.08E-04 1.27E-02 5.74E-03 Infant 3.1IE-04 l6.35E-04 l3.122-03 O.OOE+00 l2.57E-04 7.93E-04 l.OOE-02 l5.74E-03 Page 54 of 123 REFERENCE USE

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POINT BEACH NUCLEAR PLANT ODCM  ! . ... .I OFFSITE DOSE CALCULATION MANUAL Revision 16 i,..

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.-.-. . _OFFSITE DOSE CALCULATION MANUAL Table 5.1-2 Dose factor - airborne release pathway (mrenmCi released)

Br-82 ' - - - - -

'Bone - Liver,:,, T. Bodyz Thyroid Kidney Lungs. GI-LLI - Skin'.

Adult O.OOE+00 O.OOE+OO 5.44E-02 O.OOE+OO O.OOE+OO O.OOE+OO 8.47E-03 6.4 1E-02 Teen - O.OOE+OO -O.OOE+OO 5.89E .OOE+00 O.OOE+OO O.OOE-i-O O.OOE+OO 6.4 IE-02 Child.- O.OOE+OO O.OOE1+OO 7.04E-02 O.OOE+OO OO.OOE+00 O.OOE+OO O.OOE+OO 6.41E_-02 Infant_.'. O.OOE+OO O.OOE+OO 8.32E02 O.OOE+OO O.OOE+OO O.O O.OOE O.OOE+OO 6.41E-02 Dose factor - airborne release pathway (mrem/Ci released)

Br-83 Bone ,,Liver. 'T.,Body,.: ,,,Thyroid', Kidney, - Lungs GI-LLI Skin Adult ,.,, O.OOE+OO O.OOE+OO 1.65E-05 O.OOE+OO O.OOE+OO O.OOE1+OO 6.89E-06 2.84E-03 Teen O.OOE+OO O.OOE+OO 1.96E-05 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.84E-03 Child O.OOE+OO O.OOE+OO 2.34E-05 O.OOE+OO O.OOE+00 O O.OOE+OO O.OOE--+OO 2.84E-03

. Infant . I O.OOE+OO O.OOE+OO 2.07E-05 '.OOE+OO O.OOE+OOOO O.OOE+OO 'O.OOE+OO 2.84E-03 Dose factor - airborne release pathway (mrem/Ci released)

Br-84--

- Bone .:Liver T.,.Body ' ,,Thyroid -,Kidney Lungs., l GI-LLI Skin Adult O.OOE+OO lO.OOE+OO 2.59E O.OOE+OO 1l 0OOE+00 0lO.OE+00 1.llE-09.. 2.49E-01 Teen ' O.OOE+00 O.OOE+00 2.60E-02 O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 2.49E-01 Child O.OOE+00 O.OOE+00 2.63E-02 - O.OOE+00 O.OOE+O0 O.OOE+O0 O.OOE+00 2.49E-01 Infant . . O.OOE+00

. 0.OOE+00 2.66E-021 O.OOE+00 - 0.OOE+00 - 0.OOE+00 0.OOE+00 2.49E-01

. - - .. . U - S S Dose factor - airborne release pathway (mreffiCi released).

Br-85 -- -- -- _ __ _F .__

lBone,:., .. Liver., ;T.1,Body Thyroid - Kidney ,.-., Lungs GI-LLI,

-,: Skin

'Adult- ^- 0.OOE+00 O.OOE+00 4.95E-06 O.OOE+00 O.OOE+00 0.OOE+l00 O.OOE+00 2.63E-04 Teen -' 0.OOE+00 0.OOE+l00 7.06E-06 0.OOE+00 7 0.OOE+00 0.OOE+00 0.OOE+00 2.63E-04 Child --- O.OOE+00 O.OOE+00 2.02E-05 0l.OOE+l00 O.OOE+00 O.OOE+00 0.OOE+00 2.63E-04 Infant -^ O.OOE+00 0.00E+00 4.21E-05 O.OE+00 S I 0.OOE+00

- S -

0.OOE+I00 a

O.OOE+00 -

2.63E-04 S , _

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

Rb-86 -- . - - . ,

________,: .Bone .Liver '.T.1,Body *:.Thyroid, ,Kidney .' 'Lungs,. ,GI-LLI, i, Skin Adult -- 0.OOE+00 8.21E-01 3.95E-O1- O.OOE+00 O.OOE+00 O.OOE+00 1.61E-01 1.44E-02 Teen- O.OOE+00 1.23E+00 5.92E O.OOE+00 0.OOE+00 0.OOE+00 1.82E-01 1.44E-02 Child - O.OOE+00 2.18E+00 1.35E++00 0.OOE+00 O.OOE+00 O.OOE+00 1.40E-01 1.44E-02 Infant .' 0.OOE+00 I 4.17E+00 . 2.07E+00 I O.OOE+00 I 0.OOE+00 I 0.OOE+00 71.07E-01 l 1.44E-02 i t t ., , I . - ,

. t-i

,. . .. . , %1 1 -

. 1

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Rb-88 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult O.OOE+00 1.15E-05 5.22E-05 0.002+00 0.00+00 0.OOE+00 9.92E- 17 5.3 1E-05 Teen 0.002+00 1.62E-05 5.45E-05 0.00E+00 0.002+00 0.OOE+00 8.662- 13 5.31E-05 Child 0.OOE+00 1.67E-05 5.73E-05 JO.OOE+00 .1OOE+00 0.002+00 5.122-07 5.3 1E-05 Infant O.OE+00I 1.65E-05 I 5.50E-05 _O.OOE+00 O.OOE+00 I 0.002+00 I1.01E-05 5.3 1E-05 Dose factor - airborne release pathway (mremlCi released)

Rb-89 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult O.OOE+00 7.602-06 1.78E-04 0.002+00 0.002+00 0.002+00 2.752-19 2.072-04 Teen O.OOE+00 1.04E-05 1.80E-04 0.002+00 10.002+00 0O.OOE+00 1.00E- 14 2.072-04 Child O.OOE+00 1.022-05 1.81 E-04 0.00+00 0.002E+00 10.002+00 5.612-08 2.072-04 Infant O.OOE+00 9.51 E-06 I 1.792-W04 0.00+00 10.002+00 10.00O+00 2.02E-06 2.072-04 Dose factor - airborne release pathway (mrem/Ci released)

Sr-89 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 7.632+00 0.002+00 2.192-01 0.002+00 0.00O+00 4.152-02 1.232+00 3.53E-05 Teen 1.162+01 0.002+00 3.34E-01 O.OOE+00 10.002+00 7.172-02 1.402+00 3.532-05 Child 2.77E+01 O.OOE+00 7.90E-01 O.OOE+00 10.002+00 6.402-02 1.08E+00 3.53E-05 Infant 13.66E+00 I O.OOE+00 I1.052-01 0.002+00 O.OOE+00 6.02E-02 7.69E-02 3.53E-05 Dose factor - airborne release pathway (mrem/Ci released)

Sr-90 U Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 5.10E+02 O.OOE+00 1.252+02 0.002+00 0.002+00 2.852-01 1.47E+01 O.OOE+00 Teen 6.33E+02 0.002+00 1.562+02 0.00OE+00 0.002+00 4.892-01 1.77E+01 0.00E+00 Child 1.0525+03 O.OOE+00 2.65E+02 O.OOE+00 0.002+00 4.38E-01 1.41E+01l O.OOE+00 l Infant - 7.332+01 I 0.002+00 I 1.84E+01 0.002+00 I 0.00O+00 l3.34E-01 l 9.04E-01 0.002+00 Dose factor - airborne release pathway (mrenlCi released)______ _____

Sr-91 __

Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 2.29E-04 O.OOE+00 3.032-03 O.OOE+00 0.002+00 1.082613-03 3.53E-03 Teen 2.202-04 0.002+00 3.032-03 0.002+00 0.002+00 1.802-03 8.68E-03 3.532-03 Child 4.092-04 0.002+00 3.03E-03 0.002+00 0.002+00 1.582-03 6.06E-03 l3.53E-03 Infant 5.292-05 O.OOE+00 3.02E-03 3 0.2+00 O.OE+00 1.562-03 l2.24E-03 3.532-033 Page 56 of 123 REFERENCE USE

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OFFS1TE DOSE CALCULATION MANUAL - Revision 16

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OFFSITE DOSE CALCULATION MANUAL Table 5.1-2 Dose factor - airborne release pathway (rnren/Ci released)

Sr-92 -_'_'

',Bone.

..- ,Liver, T. ,Body' IThyroid, ,,Kidney ,, .Lungs ,,'GI-LLI Skin Adult 5.04E-07 O.OOE+00 1.65E-03 O.OOE+00 O.OOE+00 4.89E-04 1.28E-03 3.15E-03 Teen -- 5.66E-07 O.OOE+00 1.65E-03 O.OOE+00 O.OOE+00 8.14E-04 3.54E-03 3.15E-03 Child - 9.08E-07 O.OOE+00 1.65E-03 O.OOE+00 O.OOE+00 7.12E-04 7.20E-03 3.15E-03 Infant: *'3.12E-07 O.OOE+00 1.65E-03 0O.OOE+00 O.OOE+00 7.06E-04 4.15E-03 3.15E-03 Dose factor - airborne release pathway (mrernCi released)

Y-90 ' - - _ .

_____Bone- lLiver -T. Body ;Thyroid - Kidney ' Lungs " . GI-LLI ,Skin Adult '-'[ 7.17E-05 O.OOE+00 8.23E-06 O.OOE+00 JO.OOE+00 5.03E-03 1.19E-01 7.45E-06 Teen . 9.77E-05 O.OOE+00 8.93E O.OOE+00 O.OOE+00 8.69E-03 9.20E-02 7.45E-06 Child - 1.39E-04 0.OOE+00 l.OOE O.OOE+00 0.OOE+00 7.76E-03 5.63E-02 7A5E-06 Infant ' 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 (mrem/Ci released)

Y-91 -_-_'_-. - ' _

-Bone,'l Liver " T., Bodyl - Thyroid ' Kidney  :, Lungs.. :.GI-LLI .- ':Skin Adult 1.78E-02 O.OOE+00 1.98E-03 O.OOE+00 O.OOE+00 5.06E-02 2.26E+00 1.70E-03 Teen- 2.55E-02 1O.OOE+00 2.19E-03 O.OOE+00 O.OOE+00 8.71E-02 2.44E+00 1.70E-03 Child 4.10E-02 O.OOE+00 2.60E-03 O.OOE+00 O.OOE+00 7.79E-02 1.86E+00 1.70E-03 Infant 1.75E-02 O.OOE+00 1.97E-03 O.OOE+00 O.OOE+00 7.271E02 3.72E-03 1.70E-03 Dose factor - airborne release pathway (mremlCi released)

Y-91m - . 11

, ,Bone l, Liver_ T., Body " Thyroidl Kidney Lungs',:lGI-LLID Skin

Adult 3.58E-06 O.OOE+00 2.31E-04 O.OOE+00 O.OOE+00 5.70E-05 1.05E-05 4.33E-04 Teen 6.15E-06 0.OOE+00 2.31E-04 - O.OOE+00 O.OOE+00 9.49E-05 2.91E-04 4.33E-04 lChild l.50E-05 1 O.OOE+00 2.31E-04 O.OOE+00 0.OOE+00 8.34E-05 2.94E-02. 4.33E-04 Infant 1.21E-08 O.OOE+00 2.31E-04 O.OOE+00 O.OOE+00 8.27E-05 6.98E-05 4.33E-04 Dose factor - airborne release pathway (mrernCi released) - -- ____

Y-92

. . Bone Liver T. Body' ,.Thyroid' Kidney,."' Lungs., GI-LLI;' 'l .. Skin Adult;: 3.35E-05 O.OOE+00 4.38E-04 - O.OOE+00 O.OOE+00 4.65E-04 5.83E-01 l 2.90E-02

-Teen 5.80E-05 l O.OOE+00 4.39E-04 -- O.OOE+00 O.OOE+00 7.95E-04 1.58E+00 2.90E-02 Child '1.42E - O.OOE+00 - 4.41E-04 O.OOE+00 O.OOE+00 7.09E-04 4.09E+00' 2.90E-02 Infant.. 4.86E-07 0.OOE+00 4.37E-04 0.OOE+00OI0.OOE+00 ,7.27E-04 3.76E-03 I2.90E-02

.I I 4 - i - It7'5 REFERENCE USE

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Y-93 P y Bone Liver T. Body JThyroid Kidney Lungs GI-LLI Skin Adult 1.08E-04 O.OOE+00 4.43E-04 0.OOE+00 0.OOE+00 1.44E-03 l 3.35E+00 6.58E-02 Teen 1.86E-04 0.00+00 4.45E-04 0.002+00 0.OOE+00 2.47E-03 5.59E+00 6.582-02 Child 4.53E-04 0.00+00 4.52E-04 O.OOE+00 0.002+00 2.21E-03 6.69E+00 6.58E-02 Infant 4.45E2-06 0.002+00 - 4.40E-04 10.00O+00 0.00+00 2.27E-03 4.952-03 6.58E-02 Dose factor - airborne release pathway (mremtCi released)

Zr-95 l Bone Liver T. Body l Thyroid Kidney Lungs GI-LLI Skin Adult 4.792-03 1.54E-03 3.45E-01 0.0023+00 l 2.42E-03 5.25E-02 1.64E+00 3.98E-01 Teen 6.162-03 1.94E-03 3.45E-01 0.002+00 2.852-03 7.982-02 1.352+00 3.982-01 Child 9.472-03 2.08E-03 3.45E-01 10.002+00 12.97E-03 6.62E-02 8.81E-01 3.982-01 Infant 3.43E-03 8.272-04 3.44E-01 O.OOE+00 1 9.23E-04 5.19E-02 9.12E-04 3.98E-01 Dose factor - airborne release pathway (mremtCi released)

Zr-97 l Bone Liver T. Body Thyroid Kidney JLungs GI-LLI Skin Adult 13.12E-06 6.31E-07 l4.16E-03 _0.00+00 l 9.56E-07 l2.34E-03 3.09E-02 4.84E-03 Teen j 4.31E-06 8.52E-07 4.162-03 10.002+00 11.29E-06 3.85E-03 3.092-02 4.84E-03 Child 5.982-06 8.662-07 4.162-03 0.002+00 1.24E-06 3.362-03 1.95E-02 4.84E-03 Infant J4.452-06 I 7.60E-07 I 4.162-03 _ 0.002+00 7.69E-07 13.27E-03 4.162-03 4.84E-03 Dose factor - airborne release pathway (mremtCi released)

Nb-95 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 1.39E-03 7.75E-04 1.922-01 O.OOE+00 7.67E-04 1.50E-02 3.30E+00 12.26E-01 Teen 1.392-03 7.722-04 1.922-01 O.OOE+00 7.482-04 2.23E-02 1.99E+00 2.262-01 Child l 2.222-03 8.652-04 1.93E-01 O.OOE+00 8.13E-04 1.82E-02l 1.102+00 12.262-01 Infant 6.08E-04 2.49E-04 l 1.92E-01 l 0.OOE+00 1.82E-04 1.42E-02 14.992-02 12.26E-01 Dose factor - airborne release pathway (mrenmCi released)

Nb-97 __

Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 2.052-06 l 5.17E-07 4.17E-04 0.002+00 6.032-07 7.122-05 1.91E-03 3.20E-03 Teen 3.502-06 l 8.68E-07 4.17E-04 O.OOE+00 1.02E-06 1.17E-04 2.072-02 3.202-03 Child 8.49E-06 1.532-06 4.172-04 0.002+00 1.70E-06 1.01E-04 4.732-01 3.20E-03 Infant 1.01E-08 I 2.162-09 I 4.17E2-4 0.00+00 1.692-09 I 9.84E-05 l 7.982-04 l 3.20E-03 Page 58 of 123 REFERENCE USE

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Table 5.1-2 Dose factor - airborne release pathway (mrem/Ci released)

Mo-99 '_'_'_'

Bone. Liver "T.' Body," 'Thyroid' ,,Kidney,:, Lungs ' GI-LLI 'Skin Adult 0.OOE+00 9.10E-03 7.34E-03 0.00E+00 2.06E-02 2.71IE-03 2.85E-02 6.50E-03 Teen 0.OOE+00 1.24E-02 7.97E-03 0.OOE+00 2.84E-02 4.56E-03 3.02E-02 6.50E-03 Child 0'.OOE+00 2.06E-02 1.07E-02 0.OOE+00 4.41E-02 4.02E-03 2.08E-02 6.50E-03 Infant 0.OOE+00 3.82E-02 1.3 IE-02 0.OOE-+00 5.70E-02 4.00E-03 1.40E-02 6.50E-03 Dose factor - airborne release pathway (mremtCi released)

Tc-99m - - - -

- Bone. Liver. T. Body  :,,, Thyroid Kidney -Lungs - -GI-LLI ,, ,' Skin Adult 2.92E-09 8.24E-09 2.59E-04 0.OOE+00 1.25E-07 2.27E-05 1.28E-04 2.96E-04 Teen - 3.1 1E-09 8.68E-09 2.59E-04 0.OOE+00 1.29E-07 3.42E-05 1.87E1.04 2.96E-04 Child 5.95E-09 1.17E-08 2.59E-04 O.OOE+00 1.69E-07 2.82E-05 1.49E-04 2.96E-04 Infant ' 5.14E-09 1.06E-08 2.59E-04 0.OOE+00 1.14E-07 2.41E-05 6.33E-05 2.96E-04 Dose factor - airborne release pathway (mrem/Ci released)

Tc-101 - .

Bone 'Liver ,T. Body, ' :-Thyroid Kidney,' Lungs _GI LLI ,,'Skin,:,

Adult 1.16E-05 1.67E-05 2.08E-04 0.OOE+00 3.01E-04 2.04E-05 5.06E-17 5.80E-04 Teen 1.99E-05 2.83E-05 3.23E-04 0.OOE+00 5.12E-04 3.71E-05 4.87E-12 5.80E-04 Child 4.89E-05 5.12E-05 6.93E-04 0.OOE+00 8.72E-04 4.44E-05 1.63E-04 5.80E-04 Infant - 1.93E-12 2.44E-12 4.44E-05 0.OOE+00 2.90E-11 l 1.73E-05 2.50E-05 5.80E-04 Dose factor - airborne release pathway (mrem/Ci released) - _ -

Ru-103 , , ,, , _ _

Bone -'Liver T Body+ Thyroid' Kidney Lungs GI-LLI Skin Adult 4.36E-02 0.OOE+00 1.71E-01 O.OOE+00 0: 1.66E-01 1.50E-02 l 5.08E+00 1.77E-01 Teen - 3.76E-02 0.OOE+00- 1.68E-01 O.OOE+00 1.33E-01 2.32E-02 3.14E+00 1.77E-01 Child- '- 7.01E-02 lO.OOE+00 1.79E-01 -- .OOE+00 1.77E-01 1R97E 02 1 81E+00 1.77E-01 Infant - 6.20E-05 0.OOE+00 1.52E-01, 0.OOE+00 1.30E-04 1.64E-02 5.05E-04 1.77E-01 Dose factor - airborne release pathway (mrem/Ci released) - -

Ru-105 - , - -

lBone ' ~Liver lT. Body ., hyroid, Kidney, -. Lungs GI-LLI -,Skin Adult; 1 6.19E-04 0.OOE+000 2.07E O.OOE+00 7.99E-03 3.25E-04 3.80E-01 1.02E-02 Teen: 1.06E-03 0.OOE+00 2.23E-03 O.OOE+00 1.34E-02 5.39E-04 8.59E-01 1.02E-02 Child 2.59E-03 0.OOE+00 2.76E-03 0.OOE--+00 2.28E-02 4.72E-04 1.69E+00 1.02E-02 Infant ' 3.63E-08 0.OOE+00l 1.82E-03 0.OOE+00 2.67E-08 4.65E-04 1.44E-03 1.02E-02 1 ,"`

..- . -)~ i ;~ i !. I -1 ,4

' Ng'e. . 59:

of 123 REFERENCE USE

- __ , iSJ POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 16 October 29, 2004 OFFSITE DOSE CALCULATION MANUAL Table 5.1-2 Dose factor - airborne release pathway (mremlCi released)

Ru-106 Bone Liver _ T. Body Thyroid Kidney l Lungs GI-LLI Skin Adult 1.65E+0O 0.OOE+00 8.01E-01 0.OOE+0O 3.18E+00 2.78E-01 1.06E+02 7.11E-01 Teen 1.49E+00 0.OOE+00 7.81E-O1 0.OOE+OO 2.88E+00 4.77E-01 7.16E+01 7.11E -0l Child 2.93E+0O O.OOE+0O 9.58E-01 O.OOE+00 3.96E+00 4.25E-01 4.55E+01 7.1 lE-Ol Infant 2.67E-03 0.OOE+0O 5.93E-O1 O.OOE+00 3.28E-03 3.43E-01 5.60E-03 7.11 E-O I Dose factor - airborne release pathway (mrem/Ci released)

Rh- 105 r Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 4.8 lE-02 3.52E-02 2.47E-02 0.OOE+0OO 1.50E-01 5.72E-04 5.61E+00 7.74E-03 Teen 8.33E-02 6.02E-02 4.10E-02 O.OOE+0O 2.56E-01 9.71 E-04 7.66E+00 7.74E-03 Child 2.04E-01 1.IOE-0l 9.53E-02 0.00E+OO 4.37E-01 8.59E-04 6.80E+00 7.74E-03 Infant 7.15E-04 4.68E-04 11.83E-03 I 0.OOE+00 1.30E-03 8.64E-04 1.22E-02 7.74E-03 Dose factor - airborne release pathway (mremtCi released)

Ag-I lOm Bone Liver T. Body JThyroid Kidney Lungs GI-LLI Skin Adult 4.10E-02 3.80E-02 4.85E+0O O.OOE+0O 7.47E-02 J1.37E-01 1.54E+01 5.63E+OO Teen 6.28E-02 5.94E-02 l 4.86E+00 O.OOE+00 1. 13E-01 2.00E-01 1.66E+01 5.63E+00 Child 1.34E-01 9.04E-02 j4.90E+OO O.OOE+OO 1.68E-0 1.62E-01 1.07E+01 5.63E+OO l Infant 1.93E-01 l 1.41E-01 l 4.92E+0O l 0.OOE+l00 2.02E-01 1.09E-01 7.31E+00 5.63E+00 Dose factor - airborne release pathway (mremtCi released) -

Sb-124 11 Bone Liver _ T. Body Thyroid Kidney l Lungs l_GI-LLI Skin Adult 1.44E-01 2.73E-03 1.36E+00 3.50E-04 0.OOE+0OO 1.85E-01 l 4.09E+00 4.02E+OO Teen 2.22E-01 4.09E-03 1.39E+00 5.03E-04 0.OOE+00 3.07E-01 J 4.46E+00 4.02E+OO Child 5.1 1E-01 6.63E-03 j 1.48E+00 1.13E-03 0.OOE+0OO 3.79E-01 l 3.19E+00 4.02E+00 Infant 6.72E-02 - 9.90E-04 l 1.32E+00 - 1.78E-04 0.OOE+0 r 1.20E-01 2.06E-0OI 4.02E+00 Dose factor - airborne release pathway (mremtCi released)

Sb-125 _

l Bone Liver T. Body Thyroid Kidney Lungs l GI-LLI Skin Adult J 1.07E-01 1.20E-03 5.38E+0O 1.09E-W04 0.OOE+l00 1.33E-01 11.17E+00 9.11E+00 Teen 7 l.61E-01 1.76E-03 5.39E+00 1.54E-04 O.OOE+00 2.21E-01 T 1.24E+00 9.1 1E+00 Child l 3.69E-01 2.84E-03 5.43E+00 3.42E-04 0.OOE+0 l 2.73E-01 8.75E-01 9.1 1E+00 Infant l 8.33E-02 l 8.05E-04 5.37E+OO l 1.04E-04 0.OOE+OO 9.99E-02 l.09E-01 9.1 1E+00 Page 60 of 123 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM .. ..

OFFSITE DOSE CALCULATION MANUAL £ ' - Revision 16  :-

,.. .October 29, 2004

. - . OFFSITE DOSE CALCULATION MANUAL , II : . .. . i Table 5.1-2 Dose factor - airborne release pathway (mrem/Ci released)

Te-125m Bone , ,,Liver T.' Body,", ,.Thyroid - Kidney,  :.,'Lungs GI-LLI, Skin Adult 3.87E-01 1.40E-01 6.67E-02 1.16E-01 1.57E+00 9.30E-03 1.55E+OO 3.96E-02 Teen 5.1 1E-Ol 1.84E-01 8.32E-02 1.43E-O1 O.OOE+OO 1.59E-02 1.51E+OO 3.96E-02 Child 1.17E+00 3.16E-01 1.70E-01. 3.27E-01 O.OOE+OO 1.42E-02 1.13E+00 3.96E-02 Infant 5.10E-02 1.71E-02 2.18E-02 I 1.72E-02 I O.OOE+OO 1.33E-02 2.46E-02 3.96E-02 Dose factor - airborne release pathway (mrem/Ci released)

Te-127 Bone -, Liver ,T. Body,- '.Thyroid , Kidney,,%- Lungs GI-LLI Skin Adult-' 4.47E-06 1.61E-06 5.15E-06 3.3 lE-06 1.82E 1.93E-04 2.05E-03 4.60E-06 Teen 4.34E-06 1.55E-06 5.12E-06 3.OOE-06 1.76E-05 3.32E-04 2.73E-03 4.60E-06 Child . 8.13E-06 2.20E-06 5.93E-06 5.63E-06 2.31E-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 (mrenmCi released)

Te-127m Bone - .',Liver. l ,T. Body_l ,;Thyroid, Kidney 'Lungs

,,l :l`GI-LLI, -Skin Adult: l.19E+00 4.26E-01 1.54E-01 3.05E-01 4.84E+00 2.85E-02 4.OOE+OO 6.16E-02 Teen' 1.48E+00 5.26E-01 1.85E-01 3.52E-01 6.01E+00 4.91E-02 3.70E+00 6.16E-02 Child - 3.32E+00 8.94E-01 4.03E-01 7.94E-01 9.47E+00 4.39E-02 2.69E+00 6.16E-02 Infant 1.96E-01 6.50E-02 3.26E-02 5.66E-02 4.82E-OI 7.96E-02 6.16E-02

• Dose factor - airborne release pathway (mremlCi released) 1 Te-129 - , , , 11

' Bone Liver 'T. Body,l,', Thyroid,l, Kidney,.,,, -'Lungs lGLLI, Skin Adult Teen

' 1.48E-09 2.11E-09 7.10E-10 1.OOE-09 3.68E 1.16E-09 3.68E-05 ' 1.54E-09 5.56E-09 7.88E-09 5.74E-05 9.78E-05 4.65E-06 4.79E-05 4.36E-05 4.36E-05 Child 2.90E-09 1.04E-09 .3.68E-05 2.12E-09 7.62E-09 8.71E-05 7.56E-04 4.36E-05 Infant 2.34E-09 1.03E-09 3.68E-05l 2.00E-09 5.19E-09 8.89E-05 7.81E-04 4.36E-05 Te-129m .

B poatn w.

Dose factor - airborne release pathway (mrenmCi released)1

. . .*I *---

'lBone'_ l,;'Liver;.., T. ,Body..`, - Thyroid Kidney, Lungs GI-LLI Skin Adult - 1.39E+00 5.19E 2.35E-01 4.78E-01 5.80E+00 3.44E-02 7.01E+00 79.07E-01 Teen- 1.94E+00 7.20E-01 3.22E-01 6.26E-01 8.12E+00 5.86E-02 7.30E+O0 9.07E1-01 Child 4.53E+00 1.26E+00 7.18E-01 1.46E+00 1.33E1+01 5.23E-02 5.53E+00 9.07E-01 Infant l 1.39E-01 4.77E-02 3.66E-02 5.34E-02 3.48E- 1 4.98E-02 8.46E-02 9.07E-01 i -1 --Page'61 of 123 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 16 October 29, 2004 OFFSITE DOSE CALCULATION MANUAL Table 5.1-2 Dose factor - airborne release pathway (mremlCi released)

Te-131 Bone Liver T. Body Thyroid Kidney Lungs Gl-LLI Skin Adult 1.47E-03 6.14E-04 5.56E-04 1.21 E-03 6.43E-03 4.13E-05 2.09E-04 1.63E-03 Teen 2.52E-03 1.04E-03 8.80E-04 1.94E-03 1.1 OE-02 6.93E-05 2.07E-04 1.63E-03 Child 6.19E-03 1.89E-03 1.93E-03 4.73E-03 1.87E-02 6.09E-05 3.25E-02 1.63E-03 Infant 5.15E-10 2.44E-10 9.27E-05 4.69E-10 1.18E-09 6.1 IE-05 2.44E-04 1.63E-03 Dose factor - airborne release pathway (mrem/Ci released)

Te-131m -

l Bone Liver l T. Body l Thyroid Kidney Lungs GI-LLI Skin Adult 1.30E-01 6.34E-02 7.45E-02 1.OOE-01 6.43E-01 4.32E-03 l 6.32E+00 3.77E-02 Teen 2.21E-01 1.06E-01 11.10E-01 1.60E-01 1.1 1E+00 7.05E-03 8.53E+00 3.77E-02 Child 5.38E-01 1.86E-01 2.20E-01 3.83E-01 1.80E+00 6.10E-03 7.56E+00 3.77E-02 Infant 6.34E-04 2.56E-04 12.18E-02 15.18E-04 1.76E-03 5.90E-03 7.81E-03 3.77E-02 Dose factor - airborne release pathway (mrem/Ci released)

Te-132 __

_ Bone Liver lT. Body Thyroid Kidney l Lungs GI-LLI Skin Adult 1.92E-01 1.24E-01 1.27E-01 1.37E-01 1.20E+00 8.55E-03 T5.89E+00 l1.32E-02 Teen 3.19E-01 2.02E-01 2.002-01 2.13E-01 1.94E+00 1.33E-02 6.422+001 1.32E-02 Child 7.61E-01 3.37E-01 l 4.17E-01 14.91E-01 13.13E+00 1.12E-02 13.392+00 11.32E-02 Infant 3.94E-03 l1.95E-03 l 1.17E-02 , 2.88E-03 _1.22E-02 1.01E-02 8.50E-03 1 1.32E-02 Dose factor - airborne release pathway (mrem/Ci released) 1-131 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 7.16E-02 1.02E-01 8.29E-02 3.36E+01 1.76E-01 O.OOE+00 2.69E-02 2.93E-02 Teen 6.57E-02 9.19E-02 7.35E-02 2.68E+01 1.58E-01 O.OOE+00 1.812-02 2.93E-02 Child 1.442-01 1.45E-01 1.07E-01 4.80E+01 2.38E-01 0.002+00 1.29E-02 2.93E-02 lnfant 2.04E-01 2.402-01I 1.302-01 I 7.89E+01 l 2.80E-01 O.OOE+00 8.56E-03 2.93E-02 Dose factor - airborne release pathway (mremlCi released) 1-132 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult l 3.44E-05 9.67E-05 1.782-03 3.40E-03 1.54E-04 O.OOE+00 1.21E-05 2.06E-03 Teen 14.73E-05 1.30E-04 1.80E-03 4.49E-03 2.05E-04 0.002+00 13.78E-05 2.06E-03 Child l 6.28E-05 1.21E-04 1.802-03 5.74E-03 1.86E-04 O.OOE+00 19.50E-05 2.06E-03 Infant 5.03E-05 1.05E-04 I 1.79E-03 I 5.03E-03 1.17E-04 O.OOE+00 5.65E-05 2.06E-03 Page 62 of 123 REFERENCE USE

POINT BEACH NUCLEAR PLANT ,,

OFFSITE DOSE CALCULATION MANUAL -' ' Revision 16'  :

'October 29, 2004

._.. OOFFSITE DOSE CALCULATION MANUAL Table 5.1-2 Dose factor - airborne release pathway (mremnCi released)11-133 l l33 -Bone .-Liver T. Body 1 1Thyroid Kidney .'Lungs l:GI-LLI Skin Adult 1.46E-03 2.53E-03 4.21E-03 3.71E-01 4.41E-03 O.OOE+00 2.14E-03 4.19E-03 Teen 1.49E-03 2.52E-03 4.21E-03 3.53E-01 4.42E-03 O.OOE+00 1.75E-03 4.19E-03 Child - 2.87E-03 3.55E-03 4.78E-03 6.612-01 5.911-03 O.OOE+00 1.35E-03 4.19E-03 Infant 3.16E-03 4.59E-03 4.79E-03 8.37E-01 5.40E-03 O.OOE+O0 7.45E-04 4.19E-03 Dose factor - airborne release pathway (mrem/Ci released) 1-134 -

Bone-.- Liver T. Body Thyroid Kidney Lungs GI-LLI ;Skin Adult 1.91E-05 5.13E-05 6.45E-04 8.85E-04 8.17E-05 0.OOE+00 2.99E-08 7.45E-04 Teen -- 2.63E-05 6.88E-05 6.52E-04'. 1.17E-03 1.09E-04 O.OOE+00 6.05E-07 7.45E-04 Child 3.48E-05 6.4 1E-05 6.57E-04 1.50-03 9.79E-05 O.OOE+00 2.83E-05 7.45E-04 Infant 2.73E-05 5.57E-05 6.47E-04 1.32E-03 6.192-05 O.OOE+00 3.83E-05 7.45E-04 Dose factor - airborne release pathway (mrem/Ci released) 1-135

Bone 'Liver lT. Body ' Thyroid Kidney, Lungs, GI-LLI ,Skin Adult 9.31E-05 2.43E-04 3.64E-03 1.562-02 3.87E-04 O.OOE+00 1.96E-04 4.14E-03 Teen- 1.22E-04 3.12E-04 3.66E-03 2.05E-02 4.92E-04 ' 0.OOE+0O 2.4 1E-04 4.14E-03 Child 1.69E-04 3.00E-04 3.69E-03 2.72E-02 4.61E-04 O.00E+00 1.63E-04 4.14E-03 Infant 1.23E-04 2.43E-04 3.64E-03 2.22E-02 2.70E-04 0.00O+00 6.06E-05 4.144E-03 Dose factor - airborne release pathway (rnrem/Ci released)

Cs-134 - - - .

l lBone 'Liver lT. Bodyg, .'Thyroid Kidney l,'Lungs GI-LLI l Skin Adult 6.68E+00 1.59E+01 2.26E+01 . O.OOE+00 5.15E+00 1.71E+00 2.78E-01 1.12E+01 Teen : l 1.06E+01 2.49E+01 2.12E+01 0.OOE+l00 7.90E+00 3.02E+00 3.09E-01 1.12E+01 Child 2.39E+01 3.93E+01 1.79E+01 O.OOE+00 1.22E+01 4.37E+00 2.12E-01 1.12E+OI l Infant 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) -_

C s-134m ' _ _ _ _ _ _ _ _ _ _ -_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

ll;_.__ Bone _:' Liver T. Body JThyroid Kidney Lungs GI-LLI - Skin Adult ' 8.36E-04 1.76E-03 9.41E-04 O.OOE+00 9.54E-04 1.50E-04 6.19E-04 6.90E-05 Teen: 1.40E-03 2.89E-03 1.53E-03:l O.OOE+00 1.61E-03 2.83E-04l 1.92E-03 6.90E-05 Child 3.30E-03 4.89E-03 3.24E-03 O.OOE+00 2.58E-03l 4.27E-04 6.18E-03 6.90E-05 Infant 5.48E-06 8.72E-06 4.70E-05 0.002+00 3.53E-06 8.3 IE-07 4.82E-06 6.90E-05

.1 ":. ,I ,.1," ;I ,. '4.:; .,, "',

I . ...

'Page 63 of 123 REFERENCE USE

Ian!

POINT BEACH NUCLEAR PLANT - ,-' - .ODCM A I !I ihr I 'I OFFSITE DOSE CALCULATION MANUAL ' 'K'.I-, ' , Revision 16 ; *. ,

October 29, 2004 OFFS1TE DOSE CALCULATION MANUAL I I, . I ,: - - I - ,iI

," , i . . .-

Table 5.1-2 Dose factor - airborne release pathway (mremnCi released)

Cs-136 ' ' ' ' '

l, ,Bone':1 'Liver. T.' Body. Thyroid T' Kidney' ,l.'.Lungs GI-LLI ' Skin Adult ' 3.3 1E-01 1.31E+00 1.28E+00 0.OOE+00 7.27E-01 9.97E-02 1.48E-01 4.73E-01 Teen - 5.12E-01 2.02E+00 1.70E+00 0.OOE+00 1.IOE+00 1.73E-01 1.62E-01 4.73E-01 Child 1.14E+00 3.14E+00 2.38E+00 0.OOE+00 1.67E+00 2.49E-01 I.lOE-01 4.73E-O1 Infant 3.54E-01 1.04E+00 7.33E-01 O.OOE+00 4.15E-01. 8.48E-02 1.58E-02 4.73E-01 Dose factor - airborne release pathway (mremlCi released) '__

Cs-137 - - - - - - . ,,

Bone '-.; Liver' T.- Body,- ' Thyroid: ' Kidney'; Lungs ^ GI-LLI.' Skin Adult 9.52E+00 1.30E+01 2.30E+01 O.OOE-+00 4.42E+00 1.47E+00 2.52E-01 1.69E+01 Teen' 1.57E+01 2.09E+01 2.18E+01 O.OOE+00 7.12E+00'" 2.77E+00 2.97E-01 1.69E+01 Child'. 3.73E+01 3.57E+01 1.97E+01 0.OOE+00' 1.16E+O1: -4.18E+00 ' 2.23E-01' 1.69E+01 Infant 2.99E+01 3.49E+01 1.70E+01 0l.OOE+00 9.38E+00 3.80E+00 1.09E-01 L69E+01 Dose factor - airborne release pathway (mrem/Ci released)

Cs-138 - - - - - -

' Bone' ' :Live T. Body' Thyroids,, 'KidneyS' Lungs',` GI-LLI' r Skin Adult 2.17E-03 4.28E-03 ' 2.70E-03 0.OOE+00 3.14E-03. 3.10E-04 1.82E-08 4.39E-03 Teenr 3.69E-03 7.08E-03: 4.13E-03' 0.OOE+00 5.23E-03 6.08E-04 3.21E-06' 4.39E-03 Child 8.93E-03 1.24E-02 8.46E-03 O.OOE+00 8.73E-03, 9.40E-04-' 5.71E-03 4.39E-03 Infant 1.50E-05 2.32E-05 5.97E-04 0.OOE+00 1.22E 1.94E-06 2.60E-05 4.39E-03 Dose factor - airborne release pathway (mrem/Ci released)

Ba-139 11 l Bone' , Liver' ',T. Body ':Thyroid-, '-' Kidney':'. Lungs -,GI-LLIl- Skin Adult 3.78E-03 2.69E-06 1.38E-04 O.OOE+00 2.52E-06l 4.62E-05 6.711E-03 6.76E-03 Teen' 6.56E-03 4.61E-06 2.18E 0.OOE+00. 4.35E-06 8.00E-05 . 5.86E-02 6.76E-03 Child" 1.61E3-02 8.60E3-06 j4.951E 04 0.OOE3+00 7.5 1E-06 7.37E-05 9.3 E-0 I 6.76E-03 Infant 1.76E-08 l1.17E-1 1 12.75E-05 10.00E+00 l7.04E-12: l7.07E-05 6.06E-04 6.76E-03 Dose factor - airborne release pathway (mrem/Ci released) ,

Ba-140 - '

,:Bone ' Liver:. ' T. Body l'Thyroid -, Kidney , Lungs,' .l:',GIULLI Skin Adult ' 1.09E-01 1.37E-04 l3.60E-02 0.OOE+00 4.67E-05 3.78E-02-' 2.29E-01 3.29E-02 Teenw'- 1.19E-01 1.46E-04 3.65E-02 0.OOE+00- 4.94E-05, 6.04E-02 1.88E-01 3.29E-02 Child '. 2.39E-01 2.10E-04 l4.28E-02 0.OOE+00 6.83E-05 5.18E-02 1 23E 3.29E-02 Infant ,l14.46E-02 l4.46E-05 I 3.11E-02 l0.OOE+00 l 1.06E-05 4.74E-02 1.17E-02 3.29E-02

- , I I . . I . I K.' Page 64 of 123 REFERENCE USE

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i POINT BEACH NUCLEAR PLANT ODCM:

OFFSITE DOSE CALCULATION MANUAL Revision 16 October 29, 2004 OFFSITE DOSE CALCULATION MANUAL I

Table 5.1-2 Dose factor - airborne release pathway (mrem/Ci released)

Ba-141 Bone 'Liver, "T. Body,' Thyroid, -Kidney.,', Lungs,,, ,,'GI-LLI Skin Adult 1.83E-03 1.39E-06 2.01E-04 O.OOE-+00 1.29E-06 2.38E-05 8.66E-13 1.55E-03 Teen- 3.16E-03 2.36E-06 2.45E-04 _.OOE+00 2.19E-06 4.07E 6.75E-09 1.55E-03 Child 7.79E-03 4.36E-06 3.92E-04 0.OOE+00 3.77E-06 6.03E-05 4.44E-03 1.55E-03 Infant 1.86E-09 1.28E-12 1.39E-04 0.OOE+00 7.72E-13 3.53E-05 5.64E-05 1.55E-03 Dose factor - airborne release pathway (mrenmlCi released)

La-140 1 Bone :Liver T. Body, Thyroid Kidney;, Lungs L GI-LLI Skin Adult ' [1.17E-05 5.91E-06 2.70E-02 0.OOE+00 O.OOE+00 4.04E-03 6.96E-02 3.06E-02 Teen'. 1.57E-05 7.7 1E-06 2.70E-02 0.00E+00 O.OOE+00 6.36E-03 5.5 1E-02 3.06E-02 Child. - 2.18E-05 7.60E-06 2.70E-02 O.OOE+00 O.OOE+00 5.42E-03 3.26E-02 3.06E-02 Infant 1.56E-05 6.17E-06 2.70E-02 O.OOE+00 O.OOE+00 4.98E-03 5.27E-03 3.06E-02 Dose factor - airborne release pathway (mnremlCi released)

La14 La-142-- _____ ______

one -Liver ' T. Body ' Thyroid Kidney tLungs . *GI-LLI -Skin Adult 4.98E-06 2.27E-06 1.97E 0.OOE+00 lO.OOE+00 7.52E-05 1.65E-02 9.71E-03 Teen 8.44E-06 3.75E-06 1.97E-03 .O.OOE+00 O.OOE+00 1.21E 1.14E-01 9.71E-03 Child 2.04E-05 6.50E-06 1.97E-03 0.OOE+00 0.OOE+00l 1.03E-04 1.29E+00 9.71E-03 Infant 1.22E-08 4.48E-o 1.97E-03 O.OOE+00 O.OOE+00 9.77E-05 7.07E-04 9.71E-03 Dose factor - airborne release pathway (mrem/Ci released) -

Ce-141 - - .- - - -. : - :--__' _

'-Bone',, l. 'Liver- -T.-.Body ",lThyroid,, Kidney ' Lungs - GI-LLI., - '-Skin Adult 7.38E-04 5.01E-04 1.93E-02 O.OOE+00 2.32E-04 1.07E-02 3.84E-01 2.16E-02 Teen 1.05E-03 7.02E-04 1.93E-02: O.OOE+00l 3.29E-04 1.82E-02 4.02E-01 2.16E-02 Child 1.65E-03 8.20E-04 1.93E-02 -- O.OOE+00 3.59E-04 1.61E-02 3.02E-01 2.16E-02 Infant 8.32E-04 5.OOE-04 1.92E-02 -O.OOE+00 ! 1.581E-04 1.533E-02 3.79E-03 2.16E-02 Dose factor - airborne release pathway (mrern/Ci released) - - _ :_'_-

Ce-143 - -- - - - - - - ---- -

. .:Bone ,.;Liver .. Body',l Thyroid l Kidney,_ Lungs ,;,GI-LLI: -:Skin Adult 6.71E-05 4.80E-02 4.80E-03 O.OOE+00 [2.18E-05 9.48E-04 1.80E+00l 6.60E-02 Teen,: 1.15E-04 8.10E-02 4.81E 0.OOE+00 3.74E-05 1 55E 03 2.44E+OOl 6.60E-02 Child 2.77E-04 1.48E-01 4.82E-03 O.OOE+00 J6.31E-05 0* 1.37E-03 2.17E+00 6.60E-02 Infant,-:- 3.55E-06 5.06E-05 4.80E , 0.OOE+00 j 6.85E-07 1.38E-03 8.73E-04 6.60E-02  !

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OFFSITE DOSE CALCULATION MANUAL . ;;,: Revision 16 l ,;  :%,

E Cj October 29, 2004 OFFSITE DOSE CALCULATION MANUAL Table 5.1-2 Dose factor - airborne release pathway (mreni/Ci released)

Ce-144 Bone .'l. Liver , T.'Body , Thyroid", Kidney - Lungs, GI-LLI, Skin Adult 1.26E-01 5.24E-02 1.04E-01 O.OOE+00 3.1OE-02 2.31E-01 8.05E+00: 1.13E-01 Teen' ' .1.83E-01 7.56E-02 1.07E-01 O.OOE+00 4.51E-02 3.96E-01 9.46E+00 1.13E-01 Child"'. 2.91E-01 9.10E-02 1.13E-01 0.OOE+00 5.04E-02 3.55E-01 7.37E+00 1.13E-01 Infant~'- 9.58E-02 3.64E-02 1.03E-01 0.0OE+00 1.61E-02 2.92E-01 6.97E-02 .1.13E-01 Dose factor - airborne release pathway (mremlCi released) _ '

Pr- 143 - -- - -

TBone Body'!

', Thyroid L. , Kidney ,"-'Lungs,- ", GI-LLI'J' " Skin Adult 5.1 1E-04 2.05E-04' -' 2.53E-05 O.OOE+00 1.18E-04 3.34E-03 1.75E+00 3.77E-01 Teen 8.14E-04 3.25E-04 4.05E-05 . 0.OOE+00 1.89E-04 5.74E-03 2.16E+00 3.77E-01 Child'-' : 1.82E 5.46E-04 9.02E-05 O.OOE+00 2.96E -04 5.15E-03 1.73E+00 3.77E-01 Infant'"';' 1.67E-04 6.23E-05 8.32E-06 O.OOE+00 2.35E-05 5.14E 03 5.83E-04 3.77E-01 Dose factor - airborne release pathway (mrem/Ci released) ' l Pr-144 - - --- - , ,,_,,,_

,,,, ,. Bone""; Liver: T. Bodyt '"Thyroid,l Kidney, , Lungs GI-LLI ? Skin Adult'.7 8.93E-10 l 3.70E 2.58E-06 0.OOE+00 2.09E-10 3.01E-05 6.39E-16 2.96E-06 Teenl ' 1.27E 5.22E 2.58E-06

? - 0.OOE+00 2.99E-10 5.20E-05 6.98E-12l 2.96E-06 Child'-',., 1.77E-09 5.48E 2.58E-06 0.OOE+00' 2.90E-10 4.64E-05. 5.84E-06 2.96E-06 Infant'L, 1.42E-09 5.48E-10 2.58E-06 O.OOE+00 I 1.99E-10 I 4.78E-05 I1.27E-04 2.96E-06 Dose factor - airborne release pathway (mremlCi released)

Nd- 147 . . , __

Bone ":Liver T Body-. Thyroid' l Kidney, -:; ,Lungs,- GI-LLIPl ,,Skin, Adult- 8.95E-05 1.03E-04 2.00E-02 O.OOE+00 6.04E-05 2.62E-03 l 1.51E-01 2.00E-01 Teen' 1.22E-04 1.33E-04 2.00E O.OOE+00 7.80E-05 4.42E-03 l.15E-01 2.00E-01 Child':' ' 1.85E-04 1.49E-04 2.00E-02 0.OOE--+00 8.22E-05 3.90E 7.33E-02 2.00E-01 Infant '-'l 9.45E 9.69E-05 2.00E-02 l O.OOE+00 3.75E-05 3.83E-03 4.73E-04 l 2.00E-01 Dose factor - airborne release pathway (mrem/Ci released) '

Eu-152 - ,

Bone '"l ' Liver"' lT.' Body-- Thyroid;. Kidney ,,, -,Lungs l-,,GI-LLI" l ' Skin Adult -- ' 3.32E-02 l2.45E-01 3.62E+01 0.OOE+00 4.67E-02. 3.26E-02 1.38E+00 6.86E+01

,Teen"' ';' 4.20E-02 1.02E-02 3.62E1+01; 0.OOE-1+00 4.73E-02 4.76E-02 ' 1.23E+00 6.86E+01 Child' ' 6.02E-02 1.10E-02 3.62E+01 O.OOE+00 4.64E-02: 3.96E-02 - 8.25E-01 6.86E+01 Infant 1.30E02 295E03 362E+01 0.OOE-i00 9.90E-03 *2.46E-02 5.31E-04 6.86E+0I

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-... OFFSITE DOSE CALCULATION MANUAL ' ' .i 1' 1  :' ' '

Table 5.1-2 Dose factor - airborne release pathway (mrem/Ci released)

W-187 -

. Bone Liver T Body Thyroid Kidney ","Lungs - 'GI-LLI ,- ,Skin Adult 4.08E-03 3.41E-03 7.22E-03 i 0.00+00 0.00+00 3.45E-04 1.12E+00 2.79E-02 Teen 6.98E-03 5.69E-03 8.032-03 O.OOE+00 0.002+00 5.632-04 1.542+00 2.79E-02 Child 1.69E-02 1.00-02 1.05E-02 0.OOE+00 0.00+00 4.88E-04 1.41lE+00 2.79E-02 Infant 1.13E-05 7.88E-06 6.04E-03 O.OOE+00 0.OOE+00 4.7 1E-04 8.79E-04 2.792-02 Dose factor - airborne release pathway (rnremlCi released)

U-235

. Bone, Liver. T.- Body,- ,~.Thyroid; Kidney., Lungs GI-LLI -Skin Adult 4.062+01 0.00E+00 1.042+01 0.OOE+00 9.47E+00 4.66E+00 3.872+00 1.06E+01 Teen 6.45E+01 0.00E+00 1.19E+01 0.00E+00 1.5 IE+O I 8.03E+00 4.592+00 1.06E+01 Child 1.54E+02 0.00E+00 1.73E+01 0.00+00 2.53E+01 7.17E+00 3.58E+00 1.06E+O1 Infant 1.171E+01 0.00E+00 8.842+00 0.002+00 2.49E+00 5.46E+00 1.90E-01 1.06E+O1 Dose factor - airborne release pathway (rnrem/Ci released)

U-238

-Bone, Liver, T.Bodyl  ;,Thyroid Kidney- -l-Lungs GI-LLI Skin Adult 3.88E+01 0.00+00 2.33E+00 0.00+00 8.86E+00 4.36E+00 2.72E+00 2.47E-01 Teen 6.17E+01 0.002+00 3.70E+00 0.00+00 1.41E+01 7.502+00 3.23E+00 2.47E-01 Child 1.482+02 0.00+00 8.792+00 0.002+00 2.37E+01 6.732+00 2.53E+00 72A7E-01 Infant 1.12E+01 0.002+00 8.63E-01 0.OOE+!00 2.33E+00 L5.09E+00 1.34E-01 I2.47E-01 Dose factor - airborne release pathway (rnrern/Ci released) _

Np-239 - l

,'{.Bone: .:'.Liver, T. -Bodyj , Thyroid 'Kidney, ;F"Lungs . GI-LLI Skin Adult 5.002-05 4.92E-06 5.542-03 0.002+00 1.53E-05 4.47E-04 9.552-01 9.522-03 Teen 8.792-05 8.292-06 5.55 0.002.+00 2.60E-05 7.71E-04 1.27E+00 9.522-03 Child 2.11E-04 1.522-05 5.55E-03 l 0.002+00 4.39E-05 6.912-04 1.102+00 9.522-03 Infant 4.422-06 3.95E-07 5.54E-03 . 0.002+00  ! 7.88-07 7.07E-04 3.142-04 9.522-03 Dose factor - airborne release pathway (mrem/Ci released)

Am-241 -___

Bone Liver T. Body lThyroid Kidney Lungs GI-LLI  ::..Skin Adult 1.34E+02 4.76E+01 1.03E+01 O.OOE+00 6.702+01 5.762+00

• 3.48E+00 2.94E+00 Teen 1.46E+02 5.592+01 1.11E+01 0.002+00 7.312+01 9.992+00 4.122+00 2.942+00 Child 1.372+02 6.142+01 1.112+01 0.002+00 5.982+01 8.882+00 3.222+00 2.942+00 Infant 3.072+01 1.41E+01 3.56E+00 0.002+00 1.322+01 6.76E+00 2.58E-03 2.942+00

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. .1 POINT BEACH NUCLEAR PLANT '- ODCM -I -, .1 ",. "', . f. , . iI OFFSITE DOSE CALCULATION MANUAL Revision 16, October 29, 2004 OFFSITE 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 'willbe done in the manner similar to the liquid release dose calculations described in Section 5.1.1. The total doses to the air, skin, and whole body resulting from the release of noble gases is compared to the corresponding Appendix limits.

Noble gases released in liquids'are to be added to the atmospherically released noble gases for Appendix I dose compliance calculations.

The doses are calculated using the following formula:

API = Z Doseti = :(TDFt X Ci) < Ktmrem where API = the Appendix I dose for compliance evaluation in mrem Doseti = the dose to the applicabletarget (t) from radionuclide (i)

TDFt; = total dose factor from Table 5.1-3 in mrem/Ci for,the specific target (t) from radionuclide (i) based on the maximum annual average XIQ at the site boundary C; = 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 dose calculation may be modified to reflect actual XIQ values during the release using the methodology of Appendix C.

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-. . OFFSITE DOSE CALCULATION MANUAL - I - ,vI

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

' (Highe st Annual Avera e /Q)

Nuclide - -Beta Air.; Gamna'Air 'Skin _Whole Body

- (rnradiCi) " (mrad/Ci) ' (rnre'rn/Ci) ;,Y(rnrerii/Ci)

AR-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-09 KR-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-07

-KR-87 4.90E-04,' - 2.93E-04 7.88E-04 2.8 1E-04 KR-88 1.39E-04 7.23E-04 9.15E-04 :6.99E-04 KR-89 5.04E-04 8.23E-04 1.39E-03 7.89E-04 KR-90 3.72E-04 7.75E-04 1.2 1E-03 7.42E-04 XE-131M 5.28E 7.42E-06 3.09E-05 4.35E-06 XE-133M 7.04E-05 1.55E-05 6.45E-05 1.19E-05 XE-133 ' 4.99E-05 1.68E-05 3.32E-o5 ' 1.40E-05 XE-135M 3.51E-05, 1.60E-04 2.11E-04 1.48E-04 XE-135 1.17E-04 9.13E-05 1.90E-04 8.61E-05 XE-137 6.04E-04 7.18E-05 6.60E-04 6.75E-05 XE-138 2.26E-04 4.38E-04 6.82E-04 4.20E-04

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October 29, 2004 OFFSITE DOSE CALCULATION MANUAL 6.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Technical Specification 5.5.1.b requires the ODCM to contain the radiological environmental monitoring activities. A complete description of the PBNP radiological environmental monitoring program, including procedures and responsibilities, is contained in the PBNP Environmental Manual. The latter is hereby incorporated into the Offsite Dose Calculation Manual (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 effluent controls program. A complete description of the PBNP radiological effluent controls program is contained in the PBNP Radiological Effluent Control Manual. The latter is hereby incorporated in the ODCM by reference.

8.0 RADIOLOGICAL IMPACT EVALUATION OF SEWAGE TREATMENT SLUDGE DISPOSAL The methodology for determining the radiological impact of contaminated sewage treatment sludge is presented in this section. The evaluation must be made prior to every land application of sewage treatment plant (STP) sludge that contains licensed material. Sludge and other STP material which does not contain licensed materials may be disposed of by any legal method without 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 land application on land within the PBNP site boundary pursuant to 10 CFR 20.302(a). Wisconsin Electric committed to gamma isotopic analysis (GIA) of the sludge to measure the concentrations of licensed material in the STP sludge and to compare the results to concentration limits prior to each disposal [letter dated October 8, 1987 (VPNPD-87430, NRC-87-104)]. In addition, the dose to the maximally exposed individual of the general public and to the inadvertent intruder would be evaluated for the appropriate exposure pathways.

8.1.2 Basis for NRC Commitment Modification Pursuant to NRC guidance, the sludge is clean if no licensed materials are found when analyzed under conditions necessary to achieve the environmental LLDs (NRC HPPOS 221). Clean sludge is not under NRC jurisdiction and may 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 the RCA, or pathways are administratively controlled to prevent the transfer of licensed materials to the STP, there is no need to analyze the sludge prior to any disposal.

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POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 16 s . . * , *October 29, 2004 OFFSITE DOSE CALCULATION MANUAL O 220 Since the 1987 commitment, engineering modifications and administrative controls have eliminated the pathways from the RCA to the STP. Three subsequent sludge GIAs (a total of eight STP samples) utilizing the analytical parameters required to achieve environmental lower limit of detection (LLD) found only naturally occurring radionuclides. In each analysis, the licensed materials were below the minimum detectable activity for the particular measurement and below the required LLDs. These results verify the efficiency of the modifications and administrative controls in eliminating pathways from the'RCA' to the STP. Therefore, because there is no longer any reason to believe that the PBNP STP sewage contains licensed material and there are no pathways from the RCA to the STP, the sewage may be disposed of 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 a frequency set forth in the Chemistry Analytical Methods & Procedures (CAMP). This may include analyses prior to disposal depending on the results from the periodic analyses. The GIA of the'STP sludge shall meet the LLD criteria of normal liquid effluents. The detection of any licensed material in the sludge during the periodic GIA shall necessitate returning to the GIA prior to'disposal in order to evaluate the radiological consequences of the disposal. The GIA prior to each disposal shall continue until such time that the sludge can be shown, using environmental LLD criteria, not to contain licensed material.

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

8.1.4 Exposure Evaluations, If the sludge contains licensed material, the 1987 commitment requires that the appropriate exposure pathways be evaluated prior to each application of

'sludge to insure that the dose to the maximally exposed member of the general public is maintained at less than 1 mrem/year and that to the inadvertent intruder, at lesilthan'5 mreml/year. Also, the measured concentration shall be compared to the liquid maximum effluent concentrations of Appendix B to 10 CFR 20.

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

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.

. - amp -DT T ' 71oT; I ' TTO rg II Ui 1iL. rcU13I.;n

POINT BEACH NUCLEAR PLANT ODCM ,-

OFFSITE DOSE CALCULATION MANUAL . Revision 16 .; -

October 29, 2004 OFFSITE DOSE CALCULATION MANUAL

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 are ingestion 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 water source, 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 each contaminated sewage treatment sludge disposal:

8.2.1 Determine the radionuclide concentrations in each representative sewage treatment sludge sample. The minimum number of representative samples required is three from each sludge storage tank. The average of all statistically valid concentration determinations will be utilized in determining the sludge storage tank concentration values.

8.2.2 Verify'that the concentration of each radionuclide meets the concentration and activity limit criteria. The methodology for'determining compliance with the concentration and activity limit criteria are contained in Wisconsin Electric letter VPNPD 87430.

8.2.3 Verify that the proposed disposal of the sewage treatment sludge will maintain doses within the applicable limits. This calculation will include radionuclides disposed of in previous sludge applications. The activity from these prior disposals will be corrected for radiological decay prior to performing dose calculations for the meat, milk, and vegetable ingestion pathways, the inhalation of resuspended radionuclides, and all pathways associated with a potential release to Lake Michigan. The residual radioactivity will be corrected, if applicable, for the mixing of radionuclides in the soil prior to performing external exposure calculations.

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

The methodology for calculating the radiological impact of the sewage treatment sludge disposal is contained in Wisconsin Electric letter VPNPD 87430.

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OFFSITE DOSE CALCULATION MANUAL Revision 16 October 29, 2004 OFSITE DOSE CALCULATION. MANUAL 8.2.4 Inform the appropriate Chemistry Specialist that the sewage treatment sludge disposal may proceed after verifying that the sewage treatment sludge meets the concentration, activity, and dose limits.

8.2.5 All calculations sh'all be included with the sewage treatment sludge disposal record.'

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, "Regulatory Commitment Management." (CCE 2001-013)

a. Commitment Change -1 Section 3.2 of Attachment II of the submittal states that physical and chemical properties of the sludge would be determined prior the each land application. Pursuant to a change in the PBNP WPDES Permit, non-radiological properties are now determined annually instead of per application: The frequency for radiological characterization did not change. (See CCE 2002-002)

b. Commitment Change -2 In Section 3.3 of Attachment II of the submittal letter, the annual disposal rate was..." limited to 4,000 gallons/acre, provided WDNR chemical composition, NRC dose guidelines and activity limits are maintained...."

Modification 2 removes the 4,000 gallon limit and makes the application unlimited provided the WDNR and NRC constraints are met.

(See CCE 2002-004)

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c. Commitment Change -3 In Section 3.2 of Attachment II of NRC submittal letter dated October 8, 1987, Wisconsin Electric committed to gamma isotopic analysis (GIA) to determine the concentration of licensed material in sewage treatment plant (STP) sludge prior to each disposal. Pursuant to NRC HPPOS-221 guidance, the sludge has been shown to be clean on three different occasions after pathways from the RCA to the STP were eliminated by plant modifications and administrative controls. Pursuant to HPPOS, the sludge analyses were done under the conditions necessary to achieve the environmental LLDs. Only naturally occurring radionuclides were found and licensed material was below the minimum detectable concentration. This indicates that the former pathways from the RCA to the STP had been eliminated. Therefore, there is not need to continue the analyses because there is no RCA to STP pathway and there is no reason to believe that the sewage contains licensed material. Hence, the commitment to analyze STP sludge prior to every disposal is modified and replaced with periodic analyses at a frequency set by CAMP 914.

However, if plant conditions change in a manner which places the STP sewage outside the guidance parameters which allowed for the discontinuance of analyses, the sewage must be analyzed prior to each disposal until it again is shown not to contain licensed material.

(See CCE-2002-3)

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APPENDIX A DERIVATION OF LIQUID RELEASE PATHWAY EFFECTIVE MAXIMUM EFFLUENT CONCENTRATION A.1.0 Derivation of Liquid Release Effective Maximum Effluent Concentration

,A.1.1 Source Term I 1, The effective maxiimum effluent concentration is calculated from the annual I . I ' .!

releases via liquids for'the years 1985-1991 (Table A-1). Although Na-24 was' discharged in 1985, it was excluded from the isotopic mixture because it is 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 steam system. Tritium also was omitted from the initial calculation because its production is largely independent from the appearance of the fission products in the effluent.

A. 1.2 Effective Maximum Effluent Concentration The effective maximum effluent concentration (EMEC) was calculated using the formula given in Section 3.6 EMEC = 2:C I/ (Ci/MECi) or SC;

• 1/SOF where:

SOF = 2; Ci/MECi is the summation of fractions for the annual effluent isotopic release C, = concentration of radionuclide "i" (gCi/ml) in effluent (annual discharge/total volume of discharge)

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

The SOF for radionuclides in liquid effluent for the years 1985 through 1991 were calculated with and without H-3 and used to calculate the EMEC for the same years (Table B-2). The average EMEC without H-3 is 4.29E-06 gCi/cc.

This is the maximum concentration of non H-3 radionuclides in a mixture that could be released in liquid effluent without the SOF exceeding one (1).

However, the 10 CFR 20 Appendix B criterion is that the SOF for all radionuclides, including H-3 which can not be measured by the liquid effluent Nal RMS monitors, be less than or equal to one (1). Therefore, the above equation, modified by a factor of 0.70 to account for H-3, becomes EMEC = 0.70 XCi / X,(Ci/MECi) or ZCi

• 0.70/SOF.

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October 29, 2004 OFFSITE DOSE CALCULATION MANUAL The EMEC becomes EMEC - 0.70

• 4.29E-06 = 3.OOE-06 PCi/cc.

Only three radionuclides identified in PBNP liquid effluent have a lower MEC (10 CFR 20, Appendix B, Table 2). They are 1-131 (1E-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 or 3.OOE-04 IiCi/cc without exceeding the SOF criterion of 10 CFR 20, Appendix B for the total liquid effluent isotopic mixture.

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'TABLE A-1 CURIES RELEASED IN LIQUIDS LIQUID RELEASES I _ _ _ __ . - '. I, ___I .I , - -,',- I NUCLIDET l MEC .1985 j. 1986: -- .1987 . 1988 .- 1989 1990 . 199 R *-'uCi/cc *j' I ' '  : '. . _ _

H-3 l 1.OOE-03 8.05E+02 8.11E+02 . 7.09E+02 3.57E+02 5.59E+02 8.72E+02 7.87E+02 1-131 1.OOE-06 I1.02E-01 3.74E-02 I.04E-02 IAOE-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 9.41E-03 1-133 7.00E-06 .l1.27E-OI1 . IA9E-01 . 1.04E-01 11.21E-02 _ 8.1 1E-03 3.01E-03 1.OIE-02 1-_134 . 4.OOE-04 3.18E-02 4.39E-02 . 3.97E-02 2.29E-04 6.83E-W4 1-135 3.00E-05 1.04E-01 1.34E-01 1.23E-01 4.48E-04 8.21 E-04 AG-I IOM 6.OOE-06 2.55E-05 2.84E-04 --v 3.09E-03 9.85E-04 4.70E-04 1.71E-04 4.06E-04 BA-133 2.OOE-05 . .

BA-139 2.00E-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 13 1E-04 CE-139 7.OOE-05 .

CE-141 3.00E-05 1.31E-03 7.50E-04 CE-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-06 . -. . . . .

CO-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 IA.IE-03 5.53E-03 CR-51 5.OOE-04 2.71 E-02 3.16E-04 1.58E-02 5.31E-05 4.44E-04 8.71 E-05 CS-134 9.OOE-07 4.76E-02 6.92E-03 - 1.18E-03 4.96E-04 1.49E-03 CS-134M 2.00E-03 3.59E-04 5S.97E-06 4.67E-04 CS-136 6.OOE-06 CS-137 I.OOE-06 9.60E-02 2.11 E-02 7.54E-03 8.63E-03 2.80E-03 1.94E-03 8.93E-03 CS-138 4.OOE-04 1. IE-03 S.48E 3.24E-03 F-18 7.OOE-04 I.OOE-02 1.67E-02 7.56E-04 1.66E-03 2.26E-03 4.06E-04 FE-59 1.OOE-05 2.76E-04 j.

LA-140 9.OOE-06 MN-54 3.00E-05 7A6E-03 1.18E-03 4.68E-03 1.54E-04 2.68E-04 3.1OE-05 1.96E-04 MO-99 2.OOE-05 3.70E-05 NB-95 3.OOE-05 6.28E-03 6.65E-04 3.21E-03 . 1.61 E-04 2.33E-06 8.68E-05 NB-97 3.OOE-04 1.35E-03 5.22E-04 6.16E-05 1.06E-05 3.90E-06 8.80E-06 5.30E-06 RB-88 4.OOE-04 8.46E-05 1.I IE-02 3.33E-03 RB-89 9.OOE-04 7.98E-04 2.34E-04 RU-103 3.00E-05 3.59E-03 1.68E-06 -. 8AI4E-04 5.86E-05 RU-106 3.OOE-06 8.07E-04 2.88E-03 7.33E-03 1.04E-04 SB-124 7.00E-06 3.86E-02 2.96E-04 1.42E-04 2.34E-04 SB-125 3.OOE-05 1.12E-02 1.20E403 1.9SE-03 1.OOE-03 2.12E-02'. 1.28E-05 1.08E-02 SN-113 3.OOE-05 1.07E-03 4.20E-05 - 5.13E104 3.21 E-04 . 3.07E-06 SR-89 8.OOE-06 2.27E-04 3.46E-45 3.89E-03 2.68E-03 8.69E-06 SR-90 S.OOE-07 1.29E-03 2.28E-04 2.80E-04 3.50E44 2.55E-04 TC-99M I.OOE-03 1.75E-05 3.75E-06 3.30E-05 TC-1O1 2.OOE-03 1.1OE-05_.

TE-131 8.OOE-05 7.98E-05 TE-132 9.OOE-06 5.83E-07 6.94E-05 2.74E-05 7.19E-06 . 1.74E-04 W-187 3.00-05 3.41E4-05 Y-91M 2.OOE-03 ZN-65 S.OOE-06 S.IS E-OS ___

ZR-95 2.OOE-05 7.95E-05 2.61 E-04. 2.45E-03 1.58E-US ZR-97 9.00E-06 I .49E-06 3.09E406 I .74E-OS TOTAL Cl - 8.06E+02 8.122E+02 7.10E+02 3.57E+02 S59E+02 8.72E+02 7.87E+02 TOTAL W/O H-3 1.37E+00 S.39E-01 (5.12E-01 5.99E-02 S.65E-02 9.57E-03 15A2E-02

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OFFSITE DOSE CALCULATION MANUAL Revision 16, October 29, 2004 OFFSITE DOSE CALCULATION MANUAL TABLE A-2 FRACTIONAL MEC IN LIQUID EFFLUENT NUCLIDEB. MEC v "1985 1986 1987 . 98 :1989 . 1990

- 1991 H-3 001-03 IJ2 1.27E-03 1.25E-03 1.042-03 5.17E-04 8.36E-W j 1.26E-03 1.22E-03 1-131 l.OOE-06 1.61E-04 5.75E-05 1.52E-05 2.032-06 2.65E-06 _ 2.21E-07 2.84E-06 1-132 1.00E-04 9.70E-07 1.12E-06 8.532-07 1.49E-08 1.22E-08 6.43E-10 1.46E-07 7 00 06 1-133 . E- 2.86E-05 3.27E-05 2.18E-05 2.51 E-06 1.732-06 6.21E-07 2.24E-06 1-134 4.00E-04 1.25E-07 1.69E-07 1.46E-07 8.302-.10 - 2.652-09 1-135 3.00-O05 5.47E-06 6.87E-06 6.01E-06 2.16E-08 4.24E-08 AG-IIOM 6.00E-06 6.70E-09 7.28E-08 7.55E-07 2.38E-07 1.17E-07 4.122-08 1.05E-07 BA-133 2.00E-05 _

BA-139 2.OOE-04 6.33E-11 1.79E BA-140 8.OOE-06 1.362-09 0.002+00 8.16E-09 1.11E-08 CD-109 6.002-06 1.62E-08 3.16E CE-139 7.00E-05 CE-141 3.002-05 6.89E-08 3.67E-08 .

CE-144 3.002-06 7.032-07 1.02E-06 2.30E-07 7.92E-08 4.56E-09 4.982-09 CO-56 6.00E-06 . .

CO-57 6.002-05 6.62E-08 3.41 E-09 7.84E-09 1.22E-09 1.72E-11 9.83E-11 l CO-58 2.002-05 3.19E-05 6.942-07 2.462-06 4.93E-07 2.332-07 2.35E-08 2.272-07 CO-60 3.002-06 1.51E-04 1.46E-05 3.10E-05 9.862-06 7.67E-06 6.79E-07 2.86E-06 CR-51 5.OO-W04 8.552-08 9.722-10 4.632-08 1.54E-10 1.33E-09 2.52E-10 CS-134 9.002-07 8.34E-05 1.182-05 1.922-06 7.992-07 ll 2.57E-06 CS-134M 2.00E-03 2.602-10 4.462-12 3.622-10 CS-136 6.00E-06 _

CS-137 1.00E-06 1.512-04 3.25E-05 1.IIE-05 1.252-05 4.192-06 2.802-06 1.382S-05 CS-138 4.002-04 4.38E-09 2.11E-08 1.192-08 F-18 7.00E-04 2.202-08 3.502-08 1.572-09 3.542-09 4.67E-09 8.99E-10 FE-59 1.002-05 4.05E-08 LA-140 9.002-06 MN-54 3.002-05 3.92E-07 6.052-08 2.29E-07 7.44E-09 1.342-08 1.492-09 1.012-08 MO-99 2.00E-05 2.68E-09 _ _ _

NB-95 3.00E-05 3.30-07 3.412-08 1.572-07 7.78E-09 1.16E-10 4.182-O09 NB-97 3.00-E04 7.10E-09 2.682-09 3.01E-10 5.122-11 1.942-11 l 4.242-11 l 2.742-II RB-88 4.002-04 3.34E- 10 4.27E-08 1.222-08 RB-89 9.00E-04 1.362-09 3.81E-10 RU-103 3.00E-05 1.89E-07 8.62E-I1 4.11 E-08 2.832-09 RU-106 3.002-06 4.242-07 1.48E-06 3582-06 5.022-08 SB-124 7.002-06 8.70E-06 6.512-08 2.972-08 4.84E-08 SB-125 3.00E-05 5.89E-07 6.152-08 9.532-08 4.832-08 1.062-06 6.17E-10 5.582-07 SN-113 3.002-05 5.63E-08 2.15-09 2.51E-08 1.552-08 1.592-10 SR-89 8.002-06 4.48E-08 6.652-09 7.132-07 4.86E-07 1.622-09 SR-90 5.002-07 4.072-06 7.022-07 8.21E-07 1.OIE-06 7.622-07 l TC-99M 1.OO-03 2.76E-11 5.772-12 4.78E-11 TC-101 2.00E-03 8.06E-12 TE-131 8.00E-05 1.45E-09 l l . i TE-132 9.00E-06 1.022-10 1.192-08 4.462-09 1.162-09 3.00E-08 NV-187 3.00E-05 1.65E-09 .

Y-91M 2.00E-03 . .

ZN-65 5.00E-06 1.5 1E-08 ZR-95 2.00E-05 6.272-09 2.01E-08 1.80E-07 _ 1.142-09 ZR-97 9.002-06 2.61E-10 5.28E-10 2.80E-09

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TABLE A-2, (cont.)

FRACTIONAL MEC IN LIQUID EFFLUENT 1985 1986- .. 1987 1988 1989 1990 1991 ANNUAL VOL(CCs) 6.34E+14 6.50E+14 6.82E+14 6.90E+14 6.69E+14 6.92E+14 6.45E+14 TOT FRACTION 1.90E-03 1IAlE-03 1.14E-03 5.48E-04 8.54E-04 1.26E-03 1.25E-03 FRACT 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 TOTAL C! 8.06E+02 8.12E+02Z 7.10E+02 13.57E+02 5.59E+02 8.72E+02 1 7.87E+02 TOTAL W/O H-3 1.37E+00 5.39E-01 5.12E-01 5.99E-02 l5.65E-02 9.57E-03 5.42E-02 TOT CONC(UCU/CC) 1.27E-06 1.25E-06 1.04E406 I5.17E-07 8.36E-07 1.26E-06 1.22E-06 TCONW/OH-3 2.16E-09 830E-10 7.51E-10 8.69E-1I 8.44E-1 I 1.38E-11I 8.40E-1I EMEC 6.70E-04 8.86E-04 9.14E-04 9.45E-04 9.78E-04 9.97E-04 9.80E-04 EMEC W/O H-3 3.43E-06 5.14E-06 7.64E-06 2.85E-06 4.56E-06 3.14E-06 330E-06

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OFFSITE DOSE CALCULATION MANUAL Revision 16 October 29, 2004 OFFSITE DOSE CALCULATION MANUAL 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 atmospheric effluents is calculated from the annual releases for the years 1985-1991 (Table B-i). Unlike liquid releases, tritium was not omitted from the EMEC calculation. Instead, the EMEC was calculated with H-3 and then modified by the fraction of non-tritium radionuclides in the effluent.

B 1.2 Effective Maximum Effluent Concentration The maximum concentration of a radionuclide mixture that is allowable at the site boundary is called the effective maximum effluent concentration (EMEC).

The EMEC for an effluent mixture is defined by the equation EMEC = Y-Ci /I(Ci / MECi) where C; = concentration of radionuclide "i" MECi = maximum effluent concentration for radionuclide "i" from 10 CFR 20, Appendix B, Table 2, Column 1 Y,(C; 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 the radionuclides released during the years 1985 - 1991. The average annual site boundary concentration for each year was calculated using the highest annual average X/Q of 1.56E-06 sec/m 3. Then the total EMEC was calculated for each year (Table C-2). The average total EMEC is 8.04E-08+/-1.31E-08 p.Ci/cc with a range of 5.84E-08 to 9.50E-08 ,uCi/cc.

Next, the annual EMEC was modified for the presence of H-3, which is not detected by the atmospheric RMS, by multiplying each EMEC by the ratio of the non H-3 concentration to the total concentration. The annual H-3 corrected EMECs were averaged to obtain a value of 1.92E-08+/-1.23E-08 ,uCi/cc with a range of 5.02E-09 to 3.70E-08 p.Ci/cc.

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'CURIES IN ATMOSPHERIC EFFLUENT NUCLIDE MEC 1985 1986 1987 1988 1989 1990 1 1991

.:."'uC..,.  : . - : .,;. ,:1 '1,_- . I _.0 lH-3 I.O-07 6.71E+01 1.20E+02 1.18E+02 1.26E+02 1.42E+02 1.28E+02 1.13E+02 AR-41 1.00-08 1.27E+00 6.81E-01 2.17E+00 1.96E+00 1.57E+00 l I.IE+00 1.07E+00 KR-85M 1.00I-07 1.84E+01 6.77E-01 1.18E+00 7312E-01 2.24E-01 1.85E-01 1.03E-01 KR-85 7.00E-07 1.67E+01 1.32E+00 7.11E-01 9.84E-01 3.58E-01 1.78E-01 2.74E-01 KR-87 2.00E-08 4.78E+00 1.01E+00 2.37E+00 1.48E+00 4.94E-01 4.05E-01 2.31E-01 KR-88 9.OOE-09 5.73E+00 1.30E+00 2.72E+00 1.69E+00 5.64E-41 4.49E-01 2.56E-0I XE-131M 2.00-E06 854E-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.OOE-07 3.45E+01 153E+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 1.002-10 231E-07 _ .

BA-133 9.00E-10 _

BA-139 4.00E-08 1.17E-07 BA-140 2.00E-09 3.41E-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 9.00E-10 2.10E-07 2.52E-11 1.13E-08 1.23E-06 4.80E-07 CO-58 1.002-09 1.57E-04 1.33E-05 1.01E-04 3.59E-05 1.69E-04 2.74E-05 3.85E-06 CO-60 5.00E-1 1 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 758E-09 CS-134 2.00E-10 1.18E-03 9.49E-04 5.86E-05 7.27E-05 _1.1OE-03 CS-136 9.00E-10 ,

CS-137 2.00E-10 4.02E-03 - 2.94E-04 3.08E-04 6.742-04 2.1OE-03 1.91 E-04 1.90E-03 CS-138 8.00E-08 9.64E-07 1.92E-06 1.85E-03 1.26E-07 3.44E-06 I S2E-02 F-18 1.00E-07 1.08E-05 2.52E-04 3.87E-05 3.31 E-04 1.1OE-05 6.60E-04 FE-59 7.00E-10 . - 4.87E-09 MN-54 1.002-09 1.99E-06 1.70E-06 4.86E-05 MO-99 2.00E-09 7.27E-09 2.71 E-08 NA-24 7.00E-09 139E-04 432E-04 4.29E-04 NB-95 2.00E-09 252E-06 7.70E-07 5.97E-07 6.25E-08 956E-10 NB-97 1.00E-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 430E-09 RU-103 9.00E-10 1.91E-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 7.702-07 3.71E-06 SR-90 6.00E 1.68E-10 4.30E-06 SR-91 5.00E-09 TC-99M 3.OOE-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 3.00E-10 1.28E-10 .

ZN-65 4.OOE-10 9.27E-06 .

ZR-95 4.00E-10 1.3 1E-06 3.56E-09 743E-10 ZR-97 2.002-09 2.97E-10

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OFFS1TE DOSE CALCULATION MANUAL - Revision 16; . . . 't October 29, 2004 OFFSITE DOSE CALCULATION MANUAL TABLE B-1, (cont.)

CURIES IN ATMOSPHERIC EFFLUENT l NUCLIDE MECX 1985 1986 OY 1987 1988 - 1989- 1990 1991-1-131 2.00e-10 3.44E-03 1.I11-03 3.08E-03 5.43E-04 3.18E-04 7.85E-05 3.46e-04 1-132 2.OOe-08 3.75e-03 1.792-03 2.42E-03 4.78-04 4.20e-05 1.09E-05 2.95E-05 1-133 I.002-09 1.37E-03 6.80e-04 3.04e-03 1.53E-03 1.19E-03 1.13E-04 1.13E-04 1-134 6.00e-08 1.33E-05 . 9.32e-04 IwI I 1 1-135 6.002-09 5.79E-04 1.09E 04 2.19E-03 9.18E-05 1 .26E-05 3.15E-08 I 1.58E-05

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... OFFSITE DOSE CALCULATION MANUAL

- - TABLE B-2 FRACTIONAL MEC FOR ATMOSPHERIC EFFLUENT NUCLIDE 1985 1986 :---s.l1987> : 1988 - 1989. 19900 1991 H-3 . 3.20E-05 5.71E-05 s.62E-05 6.O0E-05 6.76E-05 6.10E-05 5.38E-05 AR-41 6.05E-06 3.24E-06 1.03E-05 9.33E-06 l7A8E-06 5.29E-06 5.IOE-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 i 4.84E-08 6.69E-08 2.44E-08 1.21E-08 1.86E-08 KR-87 1.14E-05 2.40E-06 5.64E-06 3.52E-06 1.18E-06 9.64E-07 S.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 I.. - ._  :. .

XE-133M . 2.62E-08 I.IOE-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 1.51E-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 735E-07 7.41E-07 4.10E-07 XE-138 3.93E-05 6.93E-06 2.11E-05 1.71E-05 5.83E-06 4.74E-06 2.52E-06 AG-IIOM I.IOE-10 BA-139 1.39E-13 BA-140 8.12E-12 CD-109 2.12E-09 3.OOE-10 5A3E-08 CE-141 5.05E-13 .

CE-144 4.86E-09 9.33E-10 938E-12 CO-57 I.11E-11 133E-15 5.98E-13 6.51E-11 2.54E-1I CO-58 7A8E-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 I.01E-07 CR-SI . 838E-10 1.20E-14 CS-134 2.8 1E-07 2.26E-07 I.AOE-08 1.73E-08 2.62E-07 CS- 136 _ _ _ _ __ _ _ _ _

CS-137 9.57E-07 7.OOE-08 733E-08 1.60E-07 5.OOE-07 455E-08 4.52E-07 CS-138 5.74E-13 1.14E-12 1.10E-09 7.50E-14 2.05E-12 1.14E-08 F-18 5.14E-12 1.20E-10 1.84E-11 158E-10 5.24E-12 3.14E-10 FE 331E-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-1I IA2E-II IA9E-12 2.28E-14 NB-97 7.62E-15 7.86E-16 RB-88 2.45E-11 1.83E-1I SA5E-09 2.12E-12 9.58E-12 8.57E-08 RB-89 1.02E-15 RU-103 I.01E-12 1.OOE-09 SB-125 8.50E-12 2.50E-10 639E-12 SN-113 1.29E-12 2.86E-14 SR-89 1.16E-11 3.67E-10 1.83E-10 8.83E-10 SR-90 133E-12 3.41E-08 SR-91 TC-99M 1.02E-14 3A9E-14 IA7E-13 TC-101 _ _

TE-132 1.62E-10 3.88E-12 1.24E-10 Y-88 2.03E-14 ZN-65 I.IOE-09 ZR-95 1.56E-10 4.24E-13 8.85E-14 ZR-97 7.07E-15

- I Page

' of83123 e REFERENCE USE

1L51-POINT BEACH NUCLEAR PLANT I ODCM. A -. 7 "T' :. f- . I OFFSITE DOSE CALCULATION MANUAL Revision 16 October 29, 2004 OFFSITE DOSE CALCULATION MANUAL TABLE B-2, (cont.)

FRACTIONAL MEC FOR ATMOSPHERIC EFFLUENT NucLlDe 1985 1986 1987 1988 1989 1-990 1991 1-131 8.19E-07 2.64E-07 7.33E-07 1.29E-07 7.57E-08 1.87E-08 s.24E-os 1

1-132 8.93e-09 4.26E-09 5.76E-09 1.14E-09 1.00-10 2.60E-1 1 7.02E-11 1-133 6.52E-08 3.24e-08 1.45E-07 7.29e-08 5.67E-08 5.38e-09 5.38e-09 1-134 1.06E-1 I 7.402-10 1-135 4.60E-09 8.65E-10 1.74E-08 7.29E-10 1.002-10 2.50E-13 1.25E-10 TOTALFRAC 1.49E 8.29E-05 1.20E-04 1.11E-04 8.83E-05 7.62e-05 6.67E-05 TOTAL-H3 1.17E-04 2.57-05 6.34e-05 5.13E-05 2.07e-05 1.522-05 1.29E-05 EFF MEC 5.84E-08 8.49e-08 6.62e-08 8.85e-08 8.46E-08 8.5008 s9.50e-08 H-3 11/0 3.70e-08 1.602-08 1 922-08 3.46e-08 8.10-09 5.022-09 1.44E-08

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POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL ' Revision 16 October 29, 2004

.. OFFSITE DOSE CALCULATION MANUAL -

APPENDIX C CALCULATION OF TOTAL DOSE FACTORS USING REGULATORY GUIDE 1.109, REV. 1 C.1.0 Calculation of Total Dose Factors Using Regulatorv Guide 1.109 Methodology C.1.1 Liquid Release Dose Factors The equations and values used to calculate the total dose to the maximum exposed individual for each of the liquid release mode pathways evaluated according to Regulatory Guide 1.109, Rev. 1, 1977 methodology is shown below. The total dose factor in mrem/Ci released is the sum of all pathway doses in mrem/Ci for the following pathways: milk, meat, fish, potable water, and shoreline deposits. The results for an organ is summed for each pathway and the total presented by age group and target organ in a matrix format for each radionuclide in Section 5, Table 5.1.1. The derivation of dilution factors used in the calculations is presented in Appendix D. The highest dose in each matrix is used as the dose tracking factor to be used for the monthly tracking of release doses. These values are found in Section 5, Table 5.2.

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

CF = 677,000 gpm / actual average discharge gpm This correction will produce a greater change during the winter months when the 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 initial mixing zone was calculated using the equation:

'Do se'p;=-' 1100 rF azP QjBjpje AX

- -; '- U' '+ ¢T 't '~t^PA C F inTTTTTEED1OE

.i.

oJi: ~~J:J1NLL ~L ragu 0j Ul 140 Or =15 In U an

rLML-POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 16 October 29, 2004 OFFSITE DOSE CALCULATION MANUAL where:

Doseapi = the dose to the organ j of an individual of age group a from all of the nuclides i in pathway p, in mrem/year; 1100 = a factor to convert from Ci-sec/yr-ft to pCi/liter; Mp = the mixing ratio (reciprocal of the dilution factor) at the point of harvest of aquatic food, dimensionless; ap = a usage factor that specifies the intake rate for an individual of age group a associated with pathway 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; Bp = the equilibrium bioaccumulation factor for nuclide i in pathway p, expressed as the ratio of the concentration in biota (in pCi/kg) to the radionuclide concentration in water (in pCi/1), in liters/kg; Daipj = the dose factor, specific to a given age group a, nuclide i, pathway p, and organ j, which is used to calculate the radiation dose from an intake of a nuclide, in mrem/pCi;

= the radioactive decay constant of nuclide i, in dayj tp = the average transit time required for nuclides to reach the point of exposure. For internal dose, tp is the total time elapsed between release of the nuclides and the ingestion of the water, in days.

To calculate the dose per curie released, the equation above was rearranged and the calculation performed for each nuclide. The rearranged equation is shown below:

,Dose,jpj -110 MP UaP B D p D°S'ii=100 PF Bip]DaipjjeA' The values used in the equation above are:

Page 86 of 123 REFERENCE USE

POINT BEACH NUCLEAR'PLANT . ODCM' OFFSITE DOSE CALCULATION MANUAL Revision 16 October 29, 2004 OFFSITE DOSE CALCULATION MANUAL MP = 0.1136 (Point of harvest of the fresh fish is taken at a point 1000 m downstream. The plume centerline dilution factor at this location is 8.8 using RG 1.111 methodology. The dilution factor calculations are attached. The factor of 2 allowed for current reversals was not used.);

Ua.

'Uap = Infant - 0, Child - 6.9, Teen - 16, and

- Adult - 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-1 1 through E-14 of RG 1.109; t 0.5 days.

C1.1.2 Irrigated Foods (Meat From Watered Cattle)

The dose from the ingestion of meat from cattle which have been given contaminated water was calculated using the equation:

Doseap D 'iOMPU3PQAW

=1 ~FoMA E Qi FA Daipj eA~-Alt, where:

Dose'~~ = the dose to the organ j of an individual of age group a from all of the nuclides i in pathway p, in mrem/year; 1100 - factor to convert from Ci-sec/yr-ft 3 to pCifliter; Uap = a usage factor that specifies the intake rate for an individual of age group a associated with pathway p, in kglyear; Mp = the mixing ratio (reciprocal of the dilution factor) at the point of exposure, dimensionless; QAw = consumption rate of contaminated water by an animal,

- in liters/day;

-i;Ta- *,: .vnx Q7 -fC I Tn=nTDT;KTf- T1Qn

- - - . ragr- 0 1 Ul lzo r...r ur

ILML POINT BEACH NUCLEAR PLANT ODCM ,

OFFSITE DOSE CALCULATION MANUAL Revision 16 October 29, 2004 OFFSITE DOSE CALCULATION MANUAL F = the flow rate of the liquid effluent, in ft3/sec; Qi = the release rate of nuclide i, in Ci/year; FiA = the stable element transfer coefficient that relates the daily intake rate by an animal to the concentration in an edible portion of animal product, in pCiAiter of meat per pCi/day; Daipj = the dose factor, specific to a given age group a, nuclide i, pathway p, and organ j, which is used to calculate the radiation dose from an intake of a nuclide, in mrem/pCi; xA = the radioactive decay constant of nuclide i, in day-ts = the average time from slaughter to consumption, in days.

To calculate the dose per curie released, the equation above was rearranged and the calculation performed for each nuclide. The rearranged equation is shown below:

Dose~ipj = 1 0 0 MgUap QAW RADaipjelit, QI F The values used in the equation above are:

Mp = 0.1111 (Point at which water is taken from the lake is taken as plume centerline I mile downstream. The plume centerline dilution factor at this location is 9 using RG 1.111 methodology.);

Uap Infant - 0, Child - 41, Teen - 65, and Adult - 110 kg/year; QAW = 60 liters/day; F = 1507 ft 3/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-14 of RG 1.109; ts = 20 days.

, Page 88 of 123 REFERENCE USE

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.October 29, 2004

. OFFSITE DOSE CALCULATION MANUAL -

C1.1.3 Irrigated Foods (Milk From Watered Cattle)

The dose from the ingestion of milk from cows which have been given contaminated water was calculated using the equation:

Doseapj =1100 Mp Up QAW E Qj FiA Daipj e A"t where:

'- .  :;;f Doseap :- = the dose to the organ j of an individual of age group a from all of the nuclides i in pathway p, in mrem/year; 7 , .I l

1i100 '! ; = factor to convert from Ci-sec/yr-ft 3 to pCi/liter; M

P the mixing ratio (reciprocal of the dilution factor) at the point of exposure, dimensionless; Uap = a usage factor that specifies the intake rate for an individual of age group a associated with pathway p, in liters/year; Qii - - = consumption rate of contaminated water by an animal, in liters/day; F = the flow rate of the liquid effluent, in ft3fsec;

• = the release rate of nuclide i, in Ci/year; FiA = the stable element transfer coefficient that relates the daily intake rate by an animal to the concentration in an edible portion of animal product, in pCi/liter of milk per pCi/day; Daipj = the dose factor, specific to a given age group a, nuclide i, pathway p, and organ j, which is used to calculate the radiation dose from an intake of a nuclide, in mrem/pCi; Xi = the radioactive decay constant of nuclide i, in days; tf = the average transport time of the activity from the feed into the milk and to the receptor, in days.

-, I- .2; "-,

-.. I 0- . Pagee,89 of 123

, ia-. 2EC REFERENCE USE

11mL POINT BEACH NUCLEAR PLANT ODCM ,

OFFSITE DOSE CALCULATION MANUAL Revision 16 October 29, 2004 OFFSITE DOSE CALCULATION MANUAL To calculate the dose per curie released, the equation above was rearranged and the calculation performed for each nuclide. The rearranged equation is shown below:

Dose.ipj = 1100 MP UaP QAW FRADaipjeA' Q F The values used in the equation above are:

Mp = 0.1111 (Point at which water is taken from the lake is taken as plume centerline 1 mile downstream. The plume centerline dilution factor at this location is 9 using RG 1.111 methodology. the dilution factor calculations are attached. The factor of 2 allowed for current reversals was not used. This is a conservative assumption.);

Uap = Infant - 330, Child - 330, Teen - 400, and Adult - 310 liters/year; QAW = 60 liters/day; F = 1507 ft 3 /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 I through E-14 of RG 1.109; tf = 2 days.

Page 90 of 123 REFERENCE USE

, I : "' !

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL 1 Revision 16

-October 29, 2004 OFFSITE DOSE CALCULATION MANUAL C1.1.4 Potable Water The dose'from ingestion of water was calculated using the equation:

Doseapj 1 10 0M P, ZQjDaipje6tP F8

. :1. i . , i I.

where:

Doseap - the dose to the organ j of an individual of age group a from all of the nuclides i in pathway p, in mrem/year; 1100 a factor to convert from Ci-sec/yr-ft to pCi/liter; the mixing ratio (reciprocal of the dilution factor) at the point of withdrawal of drinking water, dimensionless; Uap a usage factor that specifies the intake rate for an individual of age group a associated with pathway p, in 1/year; F the flow rate of the liquid effluent, in ft3 /sec; Qi the release rate of nuclide i, in Ci/year;

. I I Daipj = the dose factor, specific to a given age group a,

'.- nuclide i, pathway p, and organ j, which is used to calculate the radiation dose from an intake of a i' - ' 'nuclide, in mrem/pCi; Xi = the radioactive decay constant of nuclide i, in day 1 t= the average transit time required for nuclides to reach the point of exposure. For internal dose, t is the total time'elapsed between release of the nuclides and the ingestion of the water, in days.

'. ':1 ' I 'I 1 li. ' I1.

- "i ' -Page 91 of 123 REFERENCE USE

- -ILALL- - -- -

POINT BEACH NUCLEAR PLANT ODCM ,

OFFSITE DOSE CALCULATION MANUAL Revision 16 October 29, 2004 OFFSITE DOSE CALCULATION MANUAL To calculate the dose per curie released, the equation above was rearranged and the calculation performed for each nuclide. The rearranged equation is shown below:

Doseaipj =1100 MP pDaipjeAtP The values used in the equation above are:

MP = 0.0384 (Withdrawal point is taken as the Two Rivers municipal water intake located a distance of 12 miles downstream. The plume centerline dilution factor at this location is 26 using RG 1.111 methodology and the factor of 2 allowed for current reversals. The dilution factor calculations are attached.);

Uap = Infant - 330, Child - 510, Teen - 510, and Adult - 730 liters/year; F = 1507 f1/sec. (677000 gpm);

Daipj = Values used are taken from Tables E-1 1 through E-14 of RG 1.109 tp = 2 days (This was calculated using a current speed of 12.2 cm/s plus 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to reflect the transport of the water through the water purification plant and distribution system.)

C1.1.5 Shoreline Deposits The dose from exposure to radioactive materials deposited on the shoreline of the lake was calculated using the equation:

Doseapj = 110000 MpUapW QiTiDaipj elt'(1 - eAAtb)

F where:

Doseapj = the dose to the organ j of an individual of age group a from all of the nuclides i in pathway p, in mremlyear; 110000 = a factor to convert from Ci-sec/yr-ft3 to pCi/liter and to account for the proportionality constant used in the sediment radioactivity model;

.. Page 92 of 123 REFERENCE USE

POINT BEACH NUCLEAR PLANT

• ODCM I:

OFFSITE DOSE CALCULATION MANUAL l ' Revision 16  ;-

October 29, 2004

.il I. . R. ,;. . . .

.. .OFFSITE DOSE CALCULATION MANUAL p; - the mixing ratio (reciprocal of the dilution factor) at the point of exposure, dimensionless; Uap = a usage factor that specifies the exposure time for an individual 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;

. -1

.Q i .. 7 -...

the release rate of nuclide i, in Ci/year;

. . .r . -i 11.,

Ti ., - the radioactive half life of nuclide i, in days; Daipj = the dose factor, specific to a given age group a,

. .nuclide i, pathway p, and organ j, which is used to

.. calculate the radiation dose from an intake of a nuclide, in mrem/pCi; Xi = the radioactive decay constant of nuclide i, in day tp = the average transit time required for nuclides to reach the point of exposure. For internal dose, tp is the total time elapsed between release of the nuclides and the ingestion of the water, in days; tb ':; - .the period of time for which the sediment or soil is exposed to the contaminated water, in days.

'! - t -Page 93 of 123 REFERENCE USE

-- - - ajlL-POINT BEACH NUCLEAR PLANT ODCM , '

OFFSITE DOSE CALCULATION MANUAL Revision 16 October 29, 2004 OFFSITE DOSE CALCULATION MANUAL To calculate the dose per curie released, the equation above was rearranged and the calculation performed for each nuclide. The rearranged equation is shown below:

Doseaipj = 1 1 0 0 0 0 MP F'8 WeAA)

TiDUpj elp The values used in the equation above are:

MP = 0.01821 (Point of exposure is taken as the Point Beach State Park beach which is located 8000 meters downstream. The plume shoreline dilution factor at this location is 54.9 using RG 1.111 methodology.

The dilution factor calculations are attached. The factor of 2 allowed for current reversals was not used.);

Uap = Infant - 0, Child - 14, Teen - 67, and Adult - 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />s/year; W = 0.3; F = 1507 ft3 /sec. (677000 gpm);

Daipj = Values used are taken from Table E-6 of RG 1.109; tp = 0.5 day; tb = 5458 days.

Page 94 of 123 REFERENCE USE

POINT BEACH NUCtEARPLANT ' ODCM' OFFSITE DOSE CALCULATION MANUAL Revision 16

FFST .D October 29, 2004

.OFFSTE DOSE CALCULATION MANUAL.

C1.2 Atmospheric Release Dose Factors: Non-Gaseous The equations and values used to calculate the total dose to the maximum exposed individual factors for non-gaseous radionuclides released to the atmosphere using Regulatory Guide 1.109, Rev. 1, 1977 is shown below. The total dose factor in'mreni/Ci released is the sum of all airborne effluent doses in mrem/Ci for the following pathways: milk, meat, leafy vegetables, potable water, and shoreline deposits. A summary of totals is presented by age group and 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 factor to be used for the monthly tracking of release doses. These values are found in Section 5, Table 5-2.

Note that SectioffCl.2.1 applies to both tritium and particulates.

Sections C1.2.2 through C1.2.6 apply only to particulates released to the atmosphere. 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 calculated

' using the equation:

Doseja 3.17E+04Ra(JZQiDFIija where:

Doseja - the annual dose to organ j of an individual of age group a due to inhalation, in mrem/year; 3.17E+04 = the number of pCi/Ci divided by the number of sec/year; Ra - the annual air intake for individuals in the age group a, 3

in m /year;

-XQ the annual average atmosphere dispersion factor, in sec/m 3 (The location at which the dose was calculated was the site boundary in the south sector - a distance of 1270 meters.);

Qi the release rate of nuclide i, in Ci/year;

Tj1Y!'r_=T~

-. . n L-E_

rare YJ VI iz-1 lS~l~z N >tU itrt

HJLL-POINT BEACH NUCLEAR PLANT ODCM *,

OFFSITE DOSE CALCULATION MANUAL Revision 16 October 29, 2004 OFFSITE DOSE CALCULATION MANUAL DFIija = the inhalation dose factor for radionuclide i, organ j, and age group a, mrem/pCi.

To calculate the dose per curie released, the equation above was rearranged and the calculation performed for each nuclide. The rearranged equation is shown below:

Doseija = 3.17 E+ 04 R (- D1Tja Qi Q The values used in the equation above are:

Ra = Infant - 1400, Child - 3700, Teen - 8000, and Adult - 8000 mr3/year;

/Q = 9.36E-07 seconds/m 3 (This value taken from Table 1.4-2 of the FSAR, release mode 1B, annual average, site boundary.);

DFIija = Values used are taken from Tables E-7 through E-10 of RG 1.109.

C 1.2.2 Annual Organ Dose From External Irradiation From Nuclides Deposited On the Ground The organ dose from external irradiation from nuclides deposited on the ground was calculated using the equation:

Dosej = 1E+ 12 (8760) Sf SF E Q1( DFG) i Ai 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;

= the annual average relative deposition of nuclide i, considering depletion of the plume during transport, in m2, (The location at which the dose is calculated is the site boundary in the south sector - a distance of 1300 meters.);

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POINT BEACH NUCLEAR PLANT. ' I . ODCM . . .

OFFSITE DOSE CALCULATION MANUAL 7 - "IRevision i . 16 . . . . I I October 29, 2004

-. OFFSITE DOSE CALCULATION MANUAL SF -' the attenuation factor that accounts for the dose reduction due to shielding provided by residential structures, dimensionless; Qi the release rate of nuclide i, in Ci/year;

-A; = the radioactive decay constant of nuclide i, in day tb the time period over which the accumulation is evaluated, in days; DFGij = the open field ground plane dose conversion factor for 2

organ j from nuclide i, in mrem-m /pCi-hour.

To calculate the dose per curie released, the equation above was rearranged and the calculation performed for each nuclide. The rearranged equation is shown below:

Doseij _ +E12 (8760)8,1 SF DFGjj Qi Ai The values used in the equation above are:

-= 3E-09 m 2 (This value taken from Table I.4-2 of the FSAR, release mode 1B, annual average, site boundary.);

SF J1 (No structural shielding is assumed.);

tb

• 5479 days (15 years);

DFGij - Values used are taken from Table E-6 of RG 1.109.

'I' , -*,;

rF '! "n," Page 97 of 123 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM ;.

OFFSITE DOSE CALCULATION MANUAL Revision 16 October 29, 2004 OFFSITE DOSE CALCULATION MANUAL C1.2.3 Annual Organ Dose From Atmospherically Released Nuclides In Milk The organ dose from atmospherically released nuclides in milk was calculated using the equation:

Doseja = 2.7 E+ 09 Ua QF i Qi Fim DFlija eA-tf {fpf1 + e90A' - f pf 1)}

x f r(Ie ) + B1v( e t YvAA PA; J where:

Doseja = the annual dose to the organ j of an individual in age group a from a dietary intake of atmospherically released nuclides, in mrem/year; 2.7E+09 = the number of pCi per Ci divided by the number of days per year; Ua = the ingestion rate of milk for individuals in age group a, in liters/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 m2, (The location at which the dose is calculated is the nearest animal location in the south-southeast sector - a distance of 1300 meters.);

Qi = the release rate of nuclide i, in Ci/year; A; = the radioactive decay constant of nuclide i, in day-1 tb = the time period over which the accumulation is evaluated, in days; DFI1 ja = the dose conversion factor for the ingestion of nuclide i, organ j, and age group a, in mrem/pCi; I.!Page 98 of 123 REFERENCE USE

POINT BEACH NUCLEAR PLANT bDCM OFFS=T DOSE CALCULATJON MANUAL 1'Revsion 16 OFFSITE DOSE CALCULATION MANUAL.Otbr2,20 Fim ' the average fraction of the animal's daily intake of nuclide i

'which appears in each liter of milk, in days/liter; tf = the average transport time of the activity from the feed into the milk and to the receptor, in days;

= the fraction of the year that the animals graze on pasture, dimensionless;

= the fraction of the daily feed that is pasture grass when the animal 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, in days , where XEi = Xi + X~,and Xw is the removal rate constant for physical loss by weathering; Xw 0.0504 day te the time period that crops are exposed to contamination during the growing season, in days; YV the agricultural productivity, in kg (wet weight)Im2

=ivthe concentration factor for the uptake of nuclide i in pathway 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.

00 nok'f. C411)2 DT7DT7?JCXTOT7MM JL- arv, 77 U1 LC.-p AXA-JL-A-LA-1'1%-JL. %JIJAI

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 16 October 29, 2004 OFFSITE DOSE CALCULATION MANUAL To calculate the dose per curie released, the equation above was rearranged and the calculation performed for each nuclide. The rearranged equation is shown below:

Doseija = 2.7E+9 UaQFSi ZFimDFIijaeAh" {fpfJ + el'9' (I - fPf X QI Xfr(I - e-e ) + Bi, (1-eAtb)l I YvAS PAIJ The values used in the equation above are:

Ua = Infant - 330, Child - 330, Teen - 400, and Adult - 310 liters/year; QF = 50 kg/day; 5i = 18.8E-09 m-2 (This value taken from Table 1.4-2 of the FSAR, release mode LB, 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 of RG 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, and carbon-14; te = 30 days; Yv = 0.7 kg/mr; Biv = Values used are taken from Table E-1 of RG 1.109; P = 240kg/mr; tb = 5458 days (15 years).

. Page 100 of 123 REFERENCE USE

POINT BEACH NUCLEAR PLANT 'ODCM OFFSITEDOSE CALCULATIONMANUAL Revision 16 October 29, 2004

.......OFFSITE DOSE CALCULATION MANUAL'................. - ,!:

C1.2.4 Annual Organ Dose From Atmospherically Released Nuclides In Meat The organ dose from atmospherically released nuclides in meat was calculated using the equation:

Doseja = 2.7 E+ 9 Ua QF5i ZQ; Fif DFIija e-Ait {fpfs + e90-A (I- fPf1)}

{r(1- eAEte) (-

(I+ et)}

YvA PA, where:

Doseja = the annual dose to the organ j of an individual in age group a from a dietary intake of atmospherically released nuclides, in rnrem/year; 2.7E+9 = the number of pCi per Ci divided by the number of days per year;,

Ua . the ingestion rate of meat for individuals in age group a, in liters/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 in2 ,

(The location at which the dose is calculated is the nearest animal location in the south-southeast sector - a distance of 1300 meters.);

Q= the release rate of nuclide i, in Ci/year; A; = the radioactive decay constant of nuclide i, in day tb = the time period over which the accumulation is evaluated, in days; DFIija = the dose conversion factor for the ingestion of nuclide i, organ j, and age group a, in mrem/pCi;

• ci .. I i

-s z..n l u uiw i

n.L. L~LL '..L rwt FT UFFF

• ----rage-Lul Ul 1 Zj rnXLJOuLn

ILALL-POINT BEACH NUCLEAR PLAN r ODCM .. :

-. , i OFFSITE DOSE CALCULATION IMANUAL Revision 16 October 29, 2004 OFFSITE DOSE CALCULATION I VIANUAL Fif the average fraction of the animal's daily intake of nuclide i which 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; the fraction of the daily feed that is pasture grass when the animal 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, in days , where XEi = Xi + Xw, and Xw is the removal rate constant for physical loss by weathering; te the time period that crops are exposed to contamination during the growing season, in days; the agricultural productivity, in kg (wet weight)/m2 the concentration factor for the uptake of nuclide i in pathway 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)/mr2 For iodines, this factor is changed to 1.4E+09.

- Page 102 of 123 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 16 October 29, 2004 OFFSITE DOSE CALCULATION MANUAL-t To calculate the'd6se per curie released, the equation above was rearranged and the calculation performed for each nuclide. The rearranged equation is shown below:

D:o.e;j:

Doseija

- 2.7E+9UaQFiSiFirDFIifaj {fepfs+"+e"' (1-fpf5)}

Qii xf r( -e"')+ Bi,(1-e'l l YVIan PAiJ The values used in the equation above are:

Ua = Infant,- 0, Child - 41, Teen - 65, and Adult - 110 kg/year; QF = 50 kg/day;

= 18.8E-09 m (This value taken from Table 1.4-2 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-11 through E-14 of RG 1.109; ts = 20 days; fP = 0.5; -

fs = 1.0;:-

r = 0.25, 1.0 for iodines, and 0.20 for noble gases, tritium, and carbon-14; t = 30 days; Biv = Values used are taken from Table E-1 of RG 1.109;

.. 0.7kg/rn; P 240kg/rn xw = 0.0504 day '

tb = 5458 days (15 years).

t 7 no t i o0ly an 1no M=s;T 7Xjf-T7wsTTQT

--. rageZ LU Ul 14i D..;Lrcr,1%L.;1%%1 uuon_

MALL-POINT BEACH NUCLEAR PLANT ODCM -

OFFSITE DOSE CALCULATION MANUAL Revision 16 October 29, 2004 OFFSITE DOSE CALCULATION MANUAL C1.2.5 Annual Organ Dose From Atmospherically Released Nuclides In Produce The organ dose from atmospherically released nuclides in produce was calculated using the equation:

Doseja = 2.7 E+ 9 U. f gSi QPDFIija e-[s + P/i )}

where:

Doseja = the annual dose to the organ j of an individual in age group a from a dietary intake of atmospherically released nuclides, in mrem/year; 2.7E+9 = the number of pCi per Ci divided by the number of days per year; Ua = the ingestion rate of produce for individuals in age group a, in kg/year; fg = fraction of produce ingested grown in garden of interest, dimensionless;

= 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 nearest garden location in the south-southwest sector - a distance of 1460 meters.);

Qi = the release rate of nuclide i, in Ci/year;

= the radioactive decay constant of nuclide i, in dayl tb = the time period over which the accumulation is evaluated, in days; DFlija = the dose conversion factor for the ingestion of nuclide i, organ j, and age group a, in mremlpCi; th = the holdup time that represents the time interval between harvest and consumption of the food, in days;

..... Page 104 of 123 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM I OFFSITE DOSE 'CALCULATION MANUAL ' Revision 16 October 29, 2004

.. ... . .. . OFSTTF TOSE CATCUTLATTON MANTTAT: . .

r '= th6 fraction of the deposited activity retained on crops, dimensionless; XEi = the effective removal rate constant for nuclide i from crops, in I

days , where XEi = Xi + Xw, and Xw is the removal rate constant for physical loss by weathering; te = the time period that crops are exposed to contamination during the'growing season, in days; I. ,

I  :- -:. . 2 V = the agricultural productivity, in kg (wet weight)/m Biv = the concentration factor for the uptake of nuclide i in pathway 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; UP =the effective 'surface density for soil, in kg (dry soil)/m 2 For iodines, this factor is changed to 1.4E+09.

I . . . " ,

I I;

. i2 Pa 1 5 o 2

• rb Page'105 of 123 REFERENCE USE

lILL POINT BEACH NUCLEAR PLANT ODCM , . . -*, .

OFFSITE DOSE CALCULATION MANUAL Revision 16 October 29, 2004 OFFSLTE DOSE CALCULATION MANUAL To calculate the dose per curie released, the equation above was rearranged and the calculation performed for each nuclide. The rearranged equation is shown below:

i = 2.7E+9 U. fgi6 DFija e-A" { r(1 )+

QT i abo e aA The values used in the equation above are:

Ua = Infant - 0, Child - 520, Teen - 630, and Adult - 520 kg/year; fg = 0.76;

= 18.8E-09 mr2 (This value taken from Table 1.4-2 of the FSAR, release mode 1B, growing season, site boundary.);

DFIija = Values used are taken from Tables E-1 1 through E-14 of RG 1.109; th = 60 days; r = 0.25, 1.0 for iodines, and 0.20 for noble gases, tritium, and carbon-14; Xw = 0.0504 dayI; t = 60 days; Y = 0.7 kg/M2; Biv = Values used are taken from Table E-1 of RG 1.109; P = 240 kg/m2; tb = 5458 days (15 years).

. Page 106 of 123 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 16 October 29, 2004

-OFFSITE DOSE CALCULATION MANUAL. -

C1.2.6 Annual Organ Dose From Atmospherically Released Nuclides In Leafy Vegetables -

The organ dose from atmospherically released nuclides in leafy vegetables was calculated using the equation:

Doseja = 2.7 E+ 9 U. f S. EQ DFIaeAith e + (-

I J

- :where:

. Doseha = the annual dose to the organ j of an individual in age group a Dfrom a dietary intake of atmospherically released nuclides, in

-mrer^/year; 2.7E+9 = the number of pCi per Ci divided by the number of days per year; -

Ua = the ingestion rate of produce for individuals in age group a, in kg/year; f =- fraction of leafy vegetables ingested grown in garden of interest, dimensionless; 81 = 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 nearest garden location in the south-southwest sector - a distance of 1460 meters.);

Q = the release rate of nuclide i, in Ci/year;

= the radioactive decay constant of nuclide i, in day; tb = the time period over which the accumulation is evaluated, in dais; DFIija = the dose conversion factor for the ingestion of nuclide i, organ j, and age group a, in mrem/pCi; th = the holdup time that represents the time interval between harvest and consumption of the food, in days;

-; i Page '107 of 123 REFERENCE USE

1LfL1 POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 16 October 29, 2004 OFFSITE DOSE CALCULATION MANUAL r = the fraction of the deposited activity retained on crops, dimensionless; XEi = the effective removal rate constant for nuclide i from crops, in days , where XEi = Xi + X~,and Xw is the removal rate constant for physical loss by weathering; te = the time period that crops are exposed to contamination during the growing season, in days; Yv = the agricultural productivity, in kg (wet weight)/m2 Biv = the concentration factor for the uptake of nuclide i in pathway p, expressed as the ratio of the concentration in biota (in pCi/kg) to the nuclide concentration in water (in pCiAiter),

in liters/kg; P = the effective surface density for soil, in kg (dry soil)/m 2 For iodines, this factor is changed to 1.4E+09.

To calculate the dose per curie released, the equation above was rearranged and the calculation performed for each nuclide. The rearranged equation is shown below:

Doseija = 2.7-E+9eUatfSZDF' jaeh r + Bi-( -ei)

Qi L YVAS P,?1 The values used in the equation above are:

Ua = Infant - 0, Child - 26, Teen - 42, and Adult - 64 kg/year; f = 1;

= 18.8E-09 m-2 (This value taken from Table 1.4-2 of the FSAR, release mode 1B, growing season, site boundary.);

DFIija = Values used are taken from Tables E-1 1 through E-14 of RG 1.109; th = 1day;

. .IPage108 of 123 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE 'CALCULATION MANUAL Revision 16 October 29, 2004 OFFSITE DOSE CALCULATION MANUAL  ;

r 0.25, 1.0 for iodines, and 0.20 for noble gases, tritium, and carbon-14;

= 0.0504 dayj; te = 60 days; Yv = 0.7 kg/m2; Biv = Values used are taken from Table E-1 of RG 1.109; P = 240 kg/m2; tb = 5458 days (15 years).

C1.2.7 Doses from Airborne Tritium other than Inhalation The caik6lation methodology for doses from airborne H-3 via the meat, milk and vegetation pathways is different from that of particulates because tritium is a vapor and not a particle. The concentrations of tritium in vegetation are based on the concentrations found in the air surrounding the vegetation; and, all other vegetation based pathway doses are calculated from this quantity. The concentration in vegetation (forage, produce and leafy vegetables) is calculated from the formula (Reg. Guide 1.109, Rev.

1, p.1.109-27):

c= 3.17E+07 QT[X/Q](0.75)(0.5/H) where:

QT annual release rate of tritium in Ci/year;

[X/Q] =. annual average atmosphere dispersion factor, in sec/r 3 (The location at which the dose was calculated was the site boundary in the south sector, a distance of 1270m);

3.17E+07 = (1.OE+12'pCi/Ci) (1.OE+03 g/Kg) / (3.15E+07 sec/yr) 0.75 fraction of plant mass which is water; 0.5 = fraction of concentration of tritium in plant water to concentration of tritium in atmospheric water; H = absolute humidity of atmosphere in g/M3

-  ! ". t Page'109 of 123 ,REFERENCE USE

CULL POINT BEACH NUCLEAR PLANT ODCM - -

OFFSITE DOSE CALCULATION MANUAL Revision 16 October 29, 2004 OFFSITE DOSE CALCULATION MANUAL Inserting the following values into the formula:

[X/Q] = 9.36E-07 sec/M3 (from Table I.4-2 of the FSAR, release mode 1B, annual average site boundary);

H = 5.5 g/m3 (from E. L. Entier (1980), Health Physics 39:318-320).

yields Ctv = 2.0230 QT which then is used to calculate doses from leafy vegetables and produce as well as from milk and meat results for cattle ingestion of vegetation with the H-3 concentration.

C1.2.8 Annual Organ Dose from Atmospherically Released Tritium in Produce Concentrations of tritium in vegetation are based on its concentration in the air surrounding the vegetation as defined above in C1.2.7. The doses are calculated using the equation:

Doseja = DFljaUafgCtv where:

Doseja = the annual dose to the organ j of an individual in age group a from a dietary intake of atmospherically released nuclides in mrem/yr; DF~ja = the dose conversion factor for the ingestion of tritium in organ 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.

- Page I l0 of 123 REFERENCE USE

POINT BEACH NUCLEAR PLANT 1'

• ODCM OFFS1TE DOSE CALCULATION MANUAL Revision i6 October 29, 2004

. OFFSITE DOSE CALCULATION MANUAL' -

To calculate the dose per curie released, the equation above is rearranged and the calculation performed. The rearranged equation is shown below:

Doseja = 2.023 DFIjaUafg Q,

The values used in the equation above are:

DFIja = values taken from Tables E-11 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 Cm is the concentration of tritium in milk which is calculated using the formula:

Ctm = FmCtvQFexp(-Xttf).

Substituting Cm into the dose formula, the following equation results:'-

DoSeja = DFIjaUaFmCtvQF exp(-Xttf) where:

Doseja - the'annual dose to the organ j of an individual in age group a from a dietary intake of atmospherically released nuclides in mem/yr;

,mre DFIja .= the dose conversion factor for the ingestion of tritium in organj and age group a in mremlyr; Ua .=, ingestion rate for produce for individuals in age group a; Fm = average fraction of animal's daily intake of tritium which appears in milk (days/liter);

Ct, = concentration of tritium in animal's feed (since the formula for the concentration of tritium in vegetation does not depend on time, there is no distinction made between pasture grass and stored feeds);

QF = amount of feed consumed by animal per day;

'-'" Page' 111 of 123 REFERENCE USE

- A-Lal POINT BEACH NUCLEAR PLANT ODCM -

OFFSITE DOSE CALCULATION MANUAL Revision 16 October 29, 2004 OFFSITE DOSE CALCULATION MANUAL tf = average transport time from feed into milk and to receptor; Xt = radiological decay constant for tritium.

To calculate the dose per curie released, the equation above is rearranged and the calculation performed. The rearranged equation is shown below:

Doseja = 2.023 DFIjaUaFmQF exp(-Xttf)

QT The values used in the above equation are:

DFIj 3 = values taken from Tables E-11 through E-14 of RG 1.109; Ua = Infant-330, Child-330, Teen-400, Adult-310; Fm = 1.OE-02 days/liter (from RG 1.109 Table E-1);

Ct, = 2.0230 QT pCi/g; QF = 50 kg/day; tf = 2 days; A, = 0.000154 days'.

C1.2.10 Annual Organ Dose from Atmospherically Released Tritium in Meat The organ dose is calculated using the equation:

Dosej, = DFIjaUaCtf where Ctf is defined as the concentration of tritium in meat which is calculated using the formula:

Ctf = Ff CtVQF exp(-Xtt5 )

When this is inserted into the dose formula, the following equation results:

Dosej. = DFIjaUaFf CtvQF exp(-Xtt,)

where:

Doseja = the annual dose to the organ j of an individual in age group a from a dietary intake of atmospherically released nuclides in mrem/yr; DFIz, = the dose conversion factor for the ingestion of tritium in organ j and age group a in mrem/yr; Page 112 of 123 REFERENCE USE

POINT BEACH NUCLEAR' PLANT i ODCM OFFSITE DOSE CALCULATION MANUAL -' Revision 16 October 29, 2004 OFFSITE DOSE CALCULATION MANUAL

'Ua = iigesii6ni rate for produce for individuals in age group a; Ff =' fraction of animal's daily intake of tritium which appears in each kilogram of flesh (days/kg);

= concentration of tritium in animal's feed (since the formula for the concentration of tritium in vegetation does not depend on time, there is no distinction made between pasture grass and stored feeds);

QF= amount of feed consumed by animal per day; t= average time from slaughter to consumption; t= radiological decay constant for tritium.

To calculate the dose per curie released, the equation above is rearranged and the calculation performed. The rearranged equation is shown below:

Doseja = 2.023 DFIjaUaFfQFexp(-Xtts)

QT The values used in the equation above are:

DFIja = values taken from Tables E-1 1 through E-14 of RG 1.109; Ua = Infant-0, Child-41, Teen-65, Adult-1 10; Ff = 1.2E-02 days/kg;

-Cv = 2.0230 QT pCi/g; QF 50 kg/day;.

= 20 days; xt = 0.000154 days' .

'.-' - "tPage'1 13 of 123 REFERENCE USE

It POINT BEACH NUCLEAR PLANT ODCM OFFSLTE DOSE CALCULATION MANUAL Revision 16 October 29, 2004 OFFSITE DOSE CALCULATION MANUAL C1.3 Atmospheric Release Dose Factors: Noble Gases The equations and values used to calculate the total dose factors for noble gases released to the atmosphere using Regulatory Guide 1.109, Rev. 1, 1977 is shown below. The dose factor in mrem/Ci and mrad/Ci released for each radionuclide is presented in Section 5, Table 5-1.

C1.3.1 Annual Gamma and Beta AirDose From All Noble Gas Releases The dose from the submersion of individuals in air containing noble gases was calculated using the equation:

DoseyorDose1 = 3.17E+04( 2zQi(DFr or DFr) where:

Dosey or Dose 3 the annual gamma and beta air dose, in mrad/year;

3. 17E+04 the number of pCi/Ci divided by the number of sec/year; XIQ the annual average atmosphere dispersion factor, in sec/m 3 (The location at which the dose was calculated was the site boundary in the south sector-a distance of 1270 meters.);

the release rate of nuclide i, in Ci/year; DF,rorDF,4= the gamma and beta air dose factors for a uniform semi-infinite cloud of radionuclide i, in mrad-m 3/pCi-year.

-Page 114 of 123 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM i OFFSITE DOSE CALCULATION MANUAL Revision 16  ;

October 29, 2004

..,.......OFFSITE DOSE CALCULATIONMANUAL To calculate the dose per-curie released, the equation above was rearranged and the calculation performed for each nuclide. The rearranged equation is shown below:

DoserDoser = 3.17E+04 (-)(DFrorDFf )

QI Q The values used in the equation above are:

X/ . = 9.36E-07 seconds/m 3 (This value taken from Table I.4-2 of the FSAR, release mode 1B, intermittent, annual average, site boundary.);

DEr orDF" = Values used are taken from Table B-1 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 containing noble gases was calculated using the equation:

Dose="-3.17 E+04 (X~~11 SF I QiDF +IZQ DFSiJ where:

Dose = the annual skin dose due to immersion in a semi-infinite cloud, in mrem/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 absorption coefficients; SF = the attenuation factor that accounts for the dose reduction due to shielding provided by residential structures, dimensionless; YJQ the annual average atmosphere dispersion factor, in sec/m (The location at which the dose was calculated

, was the site boundary in the south sector - a distance of 1270 meters.);

As i Page 115 of 123 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM^

OFFSITE DOSE CALCULATION MANUAL Revision 16 October 29, 2004 OFFSITE DOSE CALCULATION MANUAL Qi = the release rate of nuclide i, in Ci/year; DF/Y = the annual gamma air dose factor for a uniform semi-infinite cloud of nuclide i, in mrad-m 3 /pCi-year; DFSi = the beta skin dose factor for a semi-infinite cloud of nuclide i, which includes the attenuation by 7 mg/cm2 of skin, in mrem-m /pCi-year.

To calculate the dose per curie released, the equation above was rearranged and the calculation performed for each nuclide. The rearranged equation is shown below:

Dse =3.17E+04 (.J(1F.11sFDFir+DFS i )

Qi Q The values used in the equation above are:

SF = I (No structural shielding is assumed.);

X/Q = 9.36E-07 seconds/m 3 (This value taken from Table 1.4-2 of the FSAR, release mode 1B, annual average, site boundary.);

DF/ = 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.

C 1.3.3 Annual Total Body Dose From All Noble Gas Releases The total body dose from the submersion of individuals in air containing noble gases was calculated using the equation:

Dose = 3.17E+ 04 SF{-) Qj DFBi where:

Dose = the annual total body dose due to immersion in a semi-infinite cloud, in mrem/year; 3.17E+04 = the number of pCi/Ci divided by the number of sec/year;

.- Page 116 of 123 REFERENCE USE

PON . PLANT N

POINT BEACH NUCL~EA'R PLANT " " ODCM OFFS1TE DOSE CALCULATION MANUAL  ; .1 Revision 16 -

October 29, 2004

. .I OFFSITE DOSE CALCULATION MANUAL SF the attenuation factor that accounts for the dose reduction due to shielding provided by residential Istructures, dimensionless; XIQ = the annual average atmosphere dispersion factor, in

- , sec/m 3 (Thelocationatwhichthedosewascalculated was the site boundary in the south sector - a distance of 1270 meters.);

Q = the release rate of nuclide i, in Ci/year; DFBI = the total body dose factor for a uniform semi-infinite cloud of nuclide i, which includes the attenuation of 2 3

5 g/cm of tissue, in mrem-m /pCi-year.

To calculate the dose per curie released, the equation above was rearranged and the calculation performed for each nuclide. The rearranged equation is shown below:

Dose =3.17E+04SF DFBi The values used in the equation above are:

SF = 1 (No structural shielding is assumed.);

X/Q = 9.36E-07 seconds/m 3 (This value taken from Table I.4-2 of the FSAR, release mode 1B, annual average, site boundary.);

DFBj = Values used are taken from Table B-1 of RG 1.109.

Page 117 of 123 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM A, OFFSITE DOSE CALCULATION MANUAL Revision 16 October 29, 2004 OFFSITE DOSE CALCULATION MANUAL 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 effluent released to Lake Michigan were calculated using the methodology of Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I." The parameters used in the calculation and the results of the calculation are given in Table D-1. The results are presented graphically in Figure D-1.

The centerline and shoreline values were calculated using Reg Guide 1.113 formulae 17 and 18 which apply to discharges to the Great Lakes. (The formulae are not presented here. See Section 5 of the PBNP FSAR for the formulae and origin of values used.) These results are applied as calculated for 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 as described in the Appendix I, Section 5, of the PBNP FSAR.

Page 118 of 123 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM  ;

OFFSITE DOSE CALCULATION MANUAL Revision 16  :

October 29, 2004 OFFSlITE DOSE CALCULATION MANUAL

-;  :. TABLED-1 SURFACE DILUTION FACTORS LIQUID EFFLUENTS IN A LARGE LAKE Downstream Distance Plume Centerline Shoreline (meters) 10 8.81 20 8.81 30 8.81 40 8.81 50 8.81 60 8.81 70 8.81 80 8.81 90 8.81 100 8.81 200 8.81 300 8.81 400 8.81 500 8.81 600 8.81 700 8.81 800 8.81 900 8.81 1000 8.81 122000 2000 8.86 1758 3000 9.01 401 4000 9.25 186 5000 9.53

• 116 6000 9.85 83.8 7000 10.2 65.9 8000 10.5 54.9 9000 10.8 47.4 10000 11.1 42.1 20000 14.0 24 30000 16.1 20.1 40000 17.7 18.7 50000 18.8 18.3 60000 19.6 18.2 70000 20.3 18.3 80000 20.9 18.6 90000 21.4 18.9 100000 21.9 19.2 200000 25.9 23.2 300000 29.2 26.9 400000 32.3

• 30.3 35.2 33.3 600000 600000t 37.8 36.0 700000 40.2 38.6

-800000 -:-. ' 42.6 41.0 900000 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:

I = 900 cm2 /sec zs = 0 meters

= 2 cm 2/sec d = 10 meters u = 12.2 cm/sec h = 10 meters S = 152.5 meters b 305 meters and a discharge rate of 42.2 m3 /sec.

-; ' ';Page 119 of 123 REFERENCE USE

o o~

o qr Dilution Factor at Surface M- M tz Liquid Effluents in a Large Lake Cn W DF per Unit Release Rate -L ~

1.OE+06 03 q "

1.OE+05 z

1.OE04 n0 1.OE+03 o i 1.OE+02 C-,

O< g (D0 z 1.OE+O 1 " _ ,-

Q'Ob C%

1.OEOO' 1.OE+O1 1.OE+02 1.OE+03 1.OE+04 I 1.0E+05 1.OE+06 Downstream Distance (in meters)

Area source, width 305 m and height 10 m

i POINT BEACH NUCLEAR PLANT ,< -- ODCM- '  :

OFFSITE DOSE CALCULATION MANUAL Revision 16 October 29, 2004 OFFSITE' DOSE CALCULATION MANUAL

' D1.2 Dilution Factor Twelve Miles Downstream: Two Rivers Water Intake The dilution factor used at the Two Rivers water intake twelve miles downstream from PBNP included the factor of two described in Section D 1.1.

However, instead of using the straight centerline dilution factor shown in Table 1, the weighted average dilution factor calculated over the width of the plume was used. -

This approach'was used for the following reasons. First, the path that the current takes to reach the Two Rivers water intake is not straight. In order to reach Two Rivers, the water must flow southeast around Point Beach State Park, which juts'into Lake Michigan, and then curves back 90 degrees towards Two Rivers. As'a result of this deviation from straight line flow, any part of the plume or possibly none of the plume would impinge upon the intake structure.

Second, there is a difference in the distance offshore of the PBNP discharge and the Two Rivers water intake. The Two Rivers water intake is located 5080 feet offshore. By contrast, PBNP discharges close to the shoreline through'two flumes, one directed north and one directed south, and is modeled as a source that extends 1000 feet out into the lake from the shoreline.

Based on these two considerations, it was concluded that the weighted average dilution across the width of the plume as it diverges while flowing south would constitute a better estimate of the dilution factor instead of the calculated for the centerline of an area source as is assumed for the FSAR calculation. The calculation and the values used are shown below.

The average dilution factor at 12 miles downstream was calculated in the following manner:

1. The standard deviation of the radionuclide concentration in the y direction at'12 miles downstream on the surface of the lake was calculated. This calculation used the following formula:

. . .X

= 2x s xx ay:

where E = lateral turbulent diffusion coefficient in cm2/sec x = the downstream distance in cm U = - current in cm/sec

- 'mPa 121 of 123 REFERENCE USE

lulLi POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 16 October 29, 2004 OFFSITE DOSE CALCULATION MANUAL Substituting the values for E Y.x, and u of 900 cm 2 /sec, 19308 m, and 12.2 cm/sec, respectively, into the equation yields I 2 x 900 cm~

sec x 19308 m x 100-m ay V 12.2-cm sec 100 cm 168.8 meters m

2. At distances of 0.1c, 0.2c, etc., off the plume centerline, the dilution factor was calculated using the equation shown in Section 5.2 of the PBNP FSAR. The distances off the plume centerline, the calculated dilution factor, and the fraction of the area under the normal distribution curve is listed below.

Distance Off Plume Centerline Fraction of Equivalent Fraction of Total Standard Distance Area Under the Deviation (m) Curve for Interval Dilution Factor 0.1cr 16.9 0.080 13.8 0.2c 33.8 0.080 14.0 0.3cr 50.6 0.078 14.3 0.4c 67.5 0.075 14.7 0.5cr 84.4 0.072 15.2 0.6cr 101.3 0.068 15.8 0.7cr 118.1 0.065 16.6 0.8cr 135.0 0.060 17.6 0.9cr 151.9 0.056 18.8 1.0cr 168.8 0.051 20.2 1.1cr 185.6 0.046 21.9 1.2a 202.5 0.042 23.9 1.3c 219.4 0.037 26.3 1.4c 236.3 0.032 29.2 1.5cr 253.2 0.028 32.6 1.75cr 295.4 0.053 44.7 2.0cr 337.6 0.035 64.7 2.25c 379.8 0.021 98.4 2.5cr 421.9 0.012 158.4 3.0cr 506.3 0.010 482 Totals 1.00 Page 122 of 123 REFERENCE USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 16 October 29, 2004 OFFSITE DOSE CALCULATION MANUAL

• It is assumed that the standard deviation of the radionuclide concentrations across the plume can be represented by a normal distribution curve. The fraction of the total area under the curve is that fraction of the area under the curve that lies between, for example, the interval 0. 1c and 0.2a which also includes the area of the curve in the interval -0.1c and -0.2cy.

The average dilution factor over the width of the plume was calculated by multiplying the dilution factor at each of the locations off of the plume centerline by the fraction of the total area of the curve occupied by that interval and then summing over all the intervals. An average dilution actor of 29 was calculated.

Page 123 of 123 REFERENCE USE