ML20108A035

Offsite Dose Calculation Manual

ML20108A035
Person / Time
Site:	Point Beach
Issue date:	01/26/1996
From:	WISCONSIN ELECTRIC POWER CO.
To:
Shared Package
ML20107N199	List: ML20107N195 ML20108A001 ML20108A012 ML20108A019 ML20108A022 ML20108A035
References
PROC-960126, NUDOCS 9605020068
Download: ML20108A035 (193)

Text

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POINT BEACH NUCLEAR PLANI' l UNITS 1 AND 2 i

OFFSITE DOSE CALCULATION MANUAL l

WISCONSIN ELECTRIC POWER COMPANY O

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l January 26,1996 1 Revision 10 DRAFT O

9605020068 960424 PDR ADOCK 05000266 P PDR

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 TABLE OF CONTENTS Page 1

1 1.0 OFFSITE DOSE CALCULATION MANUAL ADMINISTRATION . . . . . . . . . . . . 7

, 1.1 Pu rpo se . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 1.2 General Responsibilities . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 1.3 Manual Revisions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 l 2.0 RADIATION MONITORING SYSTEM AND RELEASE ACCOUNTING . . . . . . . . 8 3.0 METHODOLOGY FOR DETERMINING ALARM SET POINTS ............. 13 3.1 Introduction .........................................13 3.2 Obj ective . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13 3.3 Alert Set Point Guidelines . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ?

l 3.4 Alarm or Trip Set Point Guidelines . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14 3.5 Monitor Calibration and Calibration Constant Determination . . . . . . . . . . . . . . ?

l 3.6 Determination of the Effective Maximum Effluent Concentration (EMEC) for Liquid Releases . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15 3.7 Determination of Liquid Effluent Monitor Alarm Set Points . . . . . . . . . . . . . 17 3.8 Detennination of EMEC for Atmospheric Releases .................. 21 ;

1 3.9 Determination of Gaseous Effluent Monitor Alarm Set Points . . . . . . . . . . . . 21 4.0 DEMONSTRATING COMPLIANCE WITH 10 CFR 50, APPENDIX I . . . . . . . . . . 25 4.1 Introduction ................................... . . . . . 25 4.2 Dose Limits .........................................25 l 4.3 Release Lim it s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 26 4.4 EPA Regulations ......................................27

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 O

Page l 5.0 CALCULATION AND COMPARISON OF EFFLUENT RFI EASES TO RFI.FASE .

LIMITS ................................................27 1

5.1 Appendix I Dose Calculations ..............................27 l 5.1.1 Liquid Release Mode . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 27 4

5.1.2 Atmospheric Release Mode: Radioiodine, Tritium, and Particulates . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

57 5.1.3 Atmospheric Release Mode: Noble Gases . . . . . . . . . . . . . . . . . 86 l 6.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ........... 88 4 l RADIOLOGICAL IMPACT EVALUATIONS OF SEWAGE TREATMENT

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S LUDGE DIS POS AL . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 88 7.1 Ba sis . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 88

. i 7.2 Procedu re . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 89 7.3 Administrative Requirements . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 90 Apoen d i x A . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 91 A1.0 Derivation of Liquid Release Effective Maximum Effluent Concentation ... ..... 92 A1.1 S ou rce Te rm . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 92 A1.2 Effective Maximum Effluent Concentration . . . . . . . . . . . . . . . . . . . . . 92 Apoend i x B . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 97 Bl.0 Derivation of Atmospheric Release Effective Maximum Effluent Concentation . . . . . . 98 Bl .1 S ou rce Te rm . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 98 4

4 Bl.2 Effective Maximum Effluent Concentration ......................98 d

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POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996

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l Page 4 Appe n d i x C . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 103 C1.0 Calculation of Total Dose Factors Using Regulatory Guide 1.109 Methodology . . . . . 104 C1.1 Liquid Release Dose Factors . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 104 C1.1.1 Aquatic Foods . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 104 C1.1.2 Irrigated Foods (Meat from Watered Cattle) . . . . . . . . . . . . . . . 105 1

C1.1.3 Irrigated Foods (Milk from Watered Cattle) ............... 107 I 1

l C1.1.4 Potable Water .................................109 i

C1.1.5 S horeline Deposits . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 111 C1.2 Atmospheric Release Dose Factors: Non-Gaseous . . . . . . . . . . . . . . . . . . 113 j C1.2.1 Inhalation of Nuclides in Air ........................ 113 C1.2.2 Annual Organ Dose fmm External Irradiation From Nuclides Deposited on the Ground . . . . . . . . . . . . . . . . . . . . . 114 C1.2.3 Annual Organ Dose from Atmospherically Released Nuclides in Milk . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 116 C1.2.4 Annual Organ Dose from Atmospherically Released Nuclides in Meat . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 119 C1.2.5 Annual Organ Dose from Atmospherically Released Nuclides in Produce . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 122 C1.2.6 Annual Organ Dose from Atmospherically Released Nuclides in Leafy Vegetables . . . . . . . . . . . . . . . . . . . . . . . . 124 C1.3 Atmospheric Release Dose Factors: Noble Gases . . . . . . . . . . . . . . .. . 126 C1.3.1 Annual Gamma and Beta Dose from All Noble Gas Rel eases . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12 6 C1.3.2 Annual Skin Dose from All Noble Gas Releases ............ 127 Cl.3.3 Annual Total Body Dose from All Noble Gas Releases ........ 128

l POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFI' OFFSITE DOSE CALCULATION MANUAL January 26,1996 Eagg Append ix D . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13 0 DI.0 Liquid Effluent Dilution Factor Calculations . . . . . . . . . . . . . . . . . . . . . . . . . . 131 l

DI .1 Methodology . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 131 DI.2 Dilution Factor Twelve Miles Downstream: Two Rivers Water Intake . . . . . 134 Appendix E NRC Submittal: Radiological Impact l Evaluation of Sewage Treatment Sludge . . . . . . . . . . . . . . . . . . . . . . . . . E-1 l Appendix F Modification #1 to NRC Submittal . . . . . .. .. . . . . . . . . . .. . . . . . .. . F-1 l Appendix G Modification #2 to NRC Submittal ............................G-1

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1 POINT BEACH NUCLEAR PLANT ODCM l OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL March 13,1996 l LIST OF TABLES AND FIGURES Page SECTION 2.0 Table 2-1 Radioactive Liquid Waste Effluent Monitors ......................9 Table 2-2 Radioactive Gaseous Waste Effluent Monitors .................... 10 Figure 2-1 Radioactive Liquid Waste Effluent Monitors ................. .... 10  ;

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 Flow Rates . . . . . . . . . . . . 22 Table 3.9-2 Atmospheric Pathway Monitor Default RMS Set Points . . . . . . . . . . . . ... 24 l SECTION 5.0 l Table 5.1-1 Liquid Effluent Dose Factors . . ...... ................... . 29 q Table 5.1-2 Airborne Effluent Dose Factors ............................. 58 b Table 5.1-3 Activity to Dose Conversion Factors for Noble Gases . . . . . . . . . . . . . . . . . 87 APPENDIX A Table A-1 Curies Released in Liquids .. ...... ...................94 Table A-2 Fractional MEC in Liquid Effluent . .............. . . . . . . . . . . 95 APPENDIX B Table B-1 Curies in Atmospheric Effluent ..... .......................99 i Table B-2 Fractional MEC for Atmospheric Effluent . . . . . . . . . . . . . . . . . . . . . . . 101 i

APPENDIX D Table D-1 Surface Dilution Factors, Liquid Effluent in a Large Lake . . . . . ..... . 132 Figure D-1 Dilution Factor at Surface . ... ....... ... . . . . . . . . . . . . 13 3 O

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4 POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 m

1.0 OFFSITE DOSE CALCULATION MANUAL ADMINISTRATION i 1.1 Purpose i

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 demonstmting 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 and to ensure releases result in concentrations to unrestricted areas within 4

limits specified in 10 CFR 20.

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

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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). A copy of the submittal and subsequent modifications is l contained in Appendices E,F, and G. Dose limits are established in the application to ensure the health and safety of the maximally exposed member of the general public and the inadvertent intmder. 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 the Manager and the staff of the Nuclear Industry and Regulatory Services Section (IRSS). IRSS will provide the technical, regulatory, licensing, and administrative support necessary to fulfill the requirements of this manual. The calculation of offsite doses and analysis of data are IRSS responsibilities.

l The Manager-PBNP is responsible for assuring that Radiation Monitoring System alarm set points are established and maintained in accordance with the methodologies l 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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POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 1.3 Manual Revisions This manual describes the current scope of the PBNP offsite dose calculation l program. The program and the manual are maintained by IRSS. Program items or procedums may be periodically updated or changed, either to reflect new parameters or to improve program effectiveness. This manual may be revised at the discretion ofIRSS with the concurrence of the PBNP Manager's Supervisory Staff (MSS).

2.0 RADIATION MONITORING SYSTEM AND RELEASE ACCOUNTING A computerized Radiation Monitoring System (RMS) is installed at Point Beach Nuclear l Plant (PBNP). The RMS includes area, process, and effluent monitors. A description of those monitors used for liquid and gaseous effluents is pmsented in Tables 2-1 and 2-2. The liquid and gaseous waste processing flow paths, equipment, and monitoring systems are i 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 f'} released in liquid and gaseous effluents is accomplished with the RMS together with the N> 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 l Radiological Effluent Control Manual (RECM). The various aspects of grab sampling and release accountability are described in the PBNP Release Accountability Manual.

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fl POINT BEACH NUCLEAR PLANT ODCM d OFFSITE DOSE CALCULATION MANUAL f]J L

l MAJOR

{'N Revision 10 DRAFT January 26,1996 OFFSITE DOSE CALCULATION MANUAL TABLE 2-1 RADIOACTIVE LIQUID WASTE EFFLUENT MONITORS CHANNEL NUMBER NAME CONTROL FUNCTION DETECTOR TYPE 1 (2) RE-216 Containment Fan Coolers Liquid None Scintillation Monitors RE-218 Waste Disposal System Liquid Shuts waste liquid overboard Scintillation Monitor 1 (2) RE-219 Steam Generator Blowdown Liquid Shuts steam generator blowdown isolation Scintillation Monitors valves, 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 Retention Pond Discharge Liquid None Scintillation Monitor 1 (2) RE-222 Steam Generator Blowdown Tank Shuts steam generator blowdown isolation GM Tube Outlet Monitor valves and blowdown tank outlet valves Page 9 of 136 A -_- - - _ - _

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3 POINT BEACH NUCLEAR PLANT ('N ODCM (V OFFSITE DOSE CALCULATION MANUAL d l MAJOR Revision 10 DRAFI' January 26, 1996 OFFSITE DOSE CALCULATION MANUAL TABLE 2-2 RADIOACTIVE GASEOUS WASTE EFFLUENT MONITORS CHANNEL NUMBER NAME CONTROL FUNCmON DETECTOR TYPE 1 (2) RE-212 Containment Noble Gas Monitor Actuates containment ventilation isolation Scintillation RE-214 Auxiliary Building Exhaust Ventilation Shuts gas miease 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 Dmmming Area Vent Noble Gas None Scintillation Monitor RE-224 Gas Stripper Building Exhaust Noble None Scintillation Gas Monitor 1 (2) RE-305 Unit I and 2 Purge Exhaust Noble Containment ventilation isolation Scintillation Gas 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 Dmmming Area Ventilation Noble None Scintillation Gas Monitor (Channel 5 on SPING Unit No. 24)

Page 10 of 136

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POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 f3 d 3.0 METHODOLOGY FOR DETERMINING ALARM SET POINTS 3.1 Introduction The selection and maintenance of alen 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 Obiective 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 mieases result in concentrations to unrestricted areas within

limits specified in 10 CFR 20, and to ensum that the dose limits of 10 CFR 50, Appendix I are not exceeded.

G 3.3 Alen Set Point Guidelines The aled set point of each effluent monitor generally will be set to alarm at two times the established steady-state reading. The aled set point is normally set at concentrations well below the alarm set point value and is never to be set in excess of the alarm set point. In the course of plant operations, cenain situations may require a deviation from the two times steady-state guideline. The intent of the alen 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 e adjusted with the approval of the Duty Shift Superintendent. Aled set point adjustments are to be made in accordance with the PBNP RMS Alarm Set Point and

, Response Book.

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POINT EEACH NUCLEAR PLANT ODCM l OFFSITll DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 3.4 Alarm or Trin Set Point Guidelines l In accordance with the requirements of Sections 5.2 and 5.4 of the RECM, 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 equd to or less than the applicable maximum effluent concentration (MEC) specified in 10 CFR 20, Appendix B, 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 is less than or equal to one (1). The appropriate detailed response to an effluent alarm is described in the PBNP RMS Alarm Set Point and Response Book.

3.5 Monitor Calibration and Calibration Constant Determination Calibration of the RMS effluent detectors is accomplished in accordance with 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 fonnulae:

1 Cal. Constant =

)

Sensitivity and Sensitivity - Monitor Response l

E (microCi/cc) i where:

Monitor response = the calculated counts per minute registered by monitor exposed to the 1985-1991 average noble gas isotopic distribution I(pCi/cci) = total concentration of isotopes in the 1985-1991 average noble ,

gas isotopic distribution l 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 tenns of a total release concentration.

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POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 Liquid effluent monitor calibrction constants are derived from the following formulae:

I Cal. Constant =

Sensitivity and tor Response Sensitivity -

E ( Ci/cc)i where:

Monitor Response = the counts per minute registered by monitor exposed to calibration source E( Ci/cci) = 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

.g calibration constants. Application of the QAD program may be appropriate for determining monitor response for accident source terms 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 the staff of the IRSS.

3.6 Determination of the Effective Maximum Effluent Concentration (EMEC) for Liquid Releases In order to fulfill the requirements of 10 CFR 20, the RMS set point must be a value j 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 4

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.)

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POINT BEACH NUCLEAR PLANT ODCM IOFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 O The SOF is calculated using the formula found in 10 CFR 20, Appendix B, Note 4:

i SOF = E C;/MECi i

where:

Ci = concentration of radionuclide "i" (pCi/ml) in effluent (annual

] discharge / total volume of discharge) f MECi = maximum effluent concentration for unrestricted areas from l Appendix B, Table 2, Column 2 of 10 CFR 20.

l 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 = ECi / E (C;/MEC)i or EC;

• 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 concentation 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 NaI 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 ECi / E (C;/MEC) i or ECi

• 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 I-131 (IE-%), Cs-134 (9E-07), and 4 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 pCi/cc. 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 sl.

Page 16 of 136

POINT BEACH NUCLEAR PLANT ODCM l OFFSITE DOSE CALCULATION MANUAL l MAJOR l Revision 10 DRAFT l OFFSITE DOSE CALCULATION MANUAL January 26,1996 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 ama. 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 j

, mixture, when released into the circulating water system, will be maintained at or l below the unrestricted area EMEC.

Set points are calculated using the formula 1

i c water now rate (gpm)

SP = EMEC

• Waste Discharge Flow Rate (gpm) 4 1 where SP = RMS alarm set point in pCi/cc EMEC = effective maximum effluent concentration Cire 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 with 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 MSS.

Lower alarm set point values maybe used without MSS approval if the default values lie outside the upper range of the monitor or if compliance with applicable limits will not be compromised.

O Page 17 of 136

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR I Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 TABLE 3.7-1

SUMMARY

OF LIOUID DILUTION AND EFFLUENT PATHWAY FIDW RATES LIQUID EFFLUENT DISCHARGE FLOW RATE PATHWAY -

PATHWAY MONITOR (GPM) l RECarULATION WATER None

_ 1 pas;,, either unit 206,000 2 pumps, either unit 350,000 1 pump, each unit 392,000 1 pump, one unit & 2 530,000 pumps, other unit  !

2 pumps, each unit 680,000 SERVICE WATER RETURN 1 (2) RE-229 (normal cooldown per pump O 2 pumps @ 7500 gpm 15,900 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 RETENTION POND PI-230 Max Flow R2 te (2 pumps) 360 (sliding gate open) 1670 I l i

1 i

Page 18 of 136

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 TABLE 3.7-1 (continued)

SUMMARY

OF LIOUID DILUTION AND EFFLUENT PATHWAY FLOW RATFS LIQUID EFFLUENT _ DISCHARGE FLOW RATE PATHWAY MONITOR PATHWAY (GPM)

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

~

O Page 19 of 136

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT I OFFSITE DOSE CALCULATION MANUAL January 26,1996 TABLE 3.7-2

LIQUID PATHWAY MONITOR CALCULATED DEFAULT SET POINTS I

MONITOR FLOWRATE (com) SET POINT (uCi/cc) ;

I (2) RE-229 6 @ 3700' 2.78E-05 1 (2) RE-219 & 200 3.09E-3 l 1 (2) RB-222 RB-230 1670 3.70E-04 RE-220 700 8.83E-04 RE-218 & 100 6.18E-03 RE-223 1 (2) RE-216 4000 1.55E-04 O

' six service water pumps at normal cooldown flow rates O

Page 20 of 136

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 b

V 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 = [C i/ E(C; / MEC)i  ;

where i C=

i concentration of radionuclide "i" 1

MECi = maximum effluent concentration for radionuclide i from 10 CFR 20, l Appendix B, Table 2 l E (Ci / MEC) i = 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 pCi/cc was obtained to be l used in the set point calculations.

3.9 Determination of Gaseous Effluent Monitor Alarm Set ooints 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 pCi/cc 2.12E+03 = conversion factor for ft 3/ min to m 3/sec EMEC = 1.92E-08 pCi/cc x/Q = highest site boundary annual average 1.5E-06 sec/m3 FR = the flow rate in ft 3/ min of the effluent pathway being monitored.

Combining the above numerical values yields SP(pCi/cc) = 2.71E+01/ FR k Gaseous effluent pathwa discharge Dow rates and monitors associated with each pathway are summarize in Table 3.9-1.

Page 21 of 136

1 POINT BEACH NUCLEAR PLANT ODCM OR9 SITE DOSE CALCULATION MANUAL l MAJOR l Revision 10 DRAFT l OFFSITE DOSE CALCULATION MANUAL January 26,1996 I TABLE 3.9-1

SUMMARY

OF GASEOUS EFFLUENT PATHWAY DISCHARGE FLOW RATFS 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 ,

, i

d. Containment Purge Vent

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

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

j

e. Gas Stripper Building 13,000 RE-224

f. Dmmming Area Vent 43,100 RE-221 & SPING 24 O

V O

Page 22 of 136

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 O

IO 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 MSS 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. Iower set point values may be used for any of the monitors without MSS 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 RB-221 (SPING 24).

l i

l

! U tO i

4 O

Page 23 of 136

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 i TABLE 3.9-2 ATMOSPHERIC PATHWAY MONITOR l

1 DEFAULT RMS SET POINTS FLOW RATE SET POINT i MONITOR (ft /mir,L_

3 (uCi/cc)

RE-214 66,400 1.02E-04 3

RE-225 20 1.36E+00 i 1RE-215 10 2.71E+00

{' 2RE-215 10 2.71E+00 1RE-212 25,000 2.73E-04 2RE-212 38,0002 1.78E-04 l

RE-224 13,000 2.09E-03 RE-221 43,000 1.58E-04

.O

' 2 fans (with I fan the flow rate is 12,500 cubic feet / minute) 2 2 fans + 13,000 cfm from the gas stripper building i

i

O Page 24 of 136

i POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996  ;

O l U 4.0 DEMONSTRATING COMPLIANCE WITH 10 CFR 50. APPENDIX I l 4.1 Introduction Maintr'ning effluents within the dose objectives of Appendix I is demonstrated at PBNP by periodic calculations. Compliance with Appendix I limits is demonstrated l 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 l 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 yia the release mode under considention 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 l n in liquid and gaseous effluents to the environment, to ensure that these releases are as l V 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:

l 4.2.1 The calculated annual total quantity of all radioactive material above ,

background that may be released from each light-water-cooled nuclear l power reactor to unrestricted amas should not result in an estimated 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.

l 4.2.2 The calculated annual total quantity of all radioactive material above background that may be released from each light-water-cooled nuclear l power reactor to the atmosphere should not result in an estimated 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 l this quantity should not result in an estimated 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 25 of 136

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 O

l 4.2.3 The calculated annual total quantity cf all radioactive iodine and radioactive material in particulate fotm above background that may be i released from each light-water-cooled nuclear power reactor in effluents to l the atmosphere should not result in an estimated annual dose or dose  !

commitment from such radioactive iocline and radioactive material in ,

particulate form for any individual in en unrestricted area from all )

pathways of exposure in excess of 15 niillirems to any organ.

J 4.3 Release Limits i

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.

l 4.3.1. Pursuant to Section 4.2.1, the estimated doses from radionuclides in the unrestricted area in liquids shall not exceed

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

b. Twenty (20) millimm to any organ.

I l 4.3.2 Pursuant to Section 4.2.2, the estimated doses from gaseous radionuclides in the unrestricted area shall not exceed

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

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

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

d. Thirty (30) millirem to the skin.

l 4.3.3. Pursuant to Section 4.2.3, the estimated dase from radioiodine and radioactive material in particulate form r: leased to the atmosphere in the unrestricted area shall not exceed thirty (30) millirem to any organ.

l 4.3.4. Quarterly release limits are defined as % the annual limits.

Page 26 of 136

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT

, OFFSITE DOSE CALCULATION MANUAL January 26,1996 4.4 EPA Regulations Compliance with the provisions of Appendix I to 10 CFR 50 is adequate demonstration of confonnance 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 contributicas frora 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 O

Q) l Sections 5.3,5.5, and 5.6 of the RECM require that an effluent release summary or dose calculation be performed quarterly. 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 maximumly exposed individual in each age group using the appropriate total dose factors in mn:m/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 l 10 CFR 50, Appendix I dose limits will be accomplished by the l Radiological Engineering Group of IRSS. These calculations will be done i monthly, within fifteen (15) days of receipt of the final effluent curie l values from the cognizant IRSS engineer. The doses from each  ;

radionuclide will be calculated for each age group and for each organ, )

including the whole body, ad 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.

O Page 27 of 136

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 The doses are calculated using the following formula:

API = E Dose.om; = E (TDF,om; X C) i s K om mrem where ,

API = the Appendix I dose for compliance evaluation in mrem

Dose om; = the dose to the specific age group a) and organ (o) via release mode (m) from radionuclide (i) l TDF,omi = total dose factor for the specific age group (a) and  !

organ (o) via release mode (m) from radionuclide (i) from l Table 5.1-1 in mrem /C  ;

Ci =

curies of radionuclide (i) released j l

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 TDF,om; values are given in Appendix C.  !

It is recognized that some of the release quantities may not be available at O 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 liquid discharge volume during the release period using the methodology in Appendix C.

)

(3 L)

Page 28 of 136

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996

'v 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 Bone ljver T. Body Thyroid Kidney Lungs GI-LLI Adult 0.00E+ 00 4.57E-06 4.57E-06 4.57E-06 4.57E-06 4.57E-06 4.57E-06 Teen 0.00E + 00 4.11 E-06 4.11 E-06 4.11E-06 4.11E-06 4.11E-06 4. l l E-06 Child 0.00E+ 00 6.76E-06 6.76E-06 6.76E 06 6.76E-06 6.76E-06 6.76E-06 i

Infant 0.00E+ 00 7.80E-06 7.80E-06 7.80E-06 7.80E-06 7.80E-06 7.80E-06 Dose factor - liquid release pathway (mrem /Ci released)

F-18 i

Q Bone Liver T. Body Thyroid ' Kidn'ey 12mgs GI-LLI Adult 1.15E-07 9.12E-89 1.28E-08 0.00E + 00 5.14E-89 0.00E+ 00 3.40E-09 Teen 1.21E-07 7.59E-89 1.35E-08 0.00E+ 00 4.35E-89 0.00E+ 00 1.09E-08 Child 1.51E-07 1.08E-88 1.50E-08 0.00E+00 5.74E-89 0.00E+ 00 4.08E-08 Infant 2.05E-12 0.00E + 00 1.75E-13 0.00E+ 00 0.00E+ 00 0.00E+ 00 4.83E-13 Dose factor - liquid release pathway (mrem /Ci released)

Na-22 Bone Liver T. Body . Thyroid - Kidney Lungs GI-LLI Adult 4.71 E-03 4.71 E-03 4.82E-03 4.71E-03 4.71E-03 4.71E-03 4.71 E-03 Teen 5.48E-03 5.48E-03 6.07E-03 5.48E-03 5.48E-03 5.48E-03 5.48E-03 Child 8.32E-03 8.32E-03 8.45E43 8.32E-03 8.32E-03 8.32E-03 8.32E-03 Infant 7.21E-03 7.21E-03 7.21 E-03 7.21E-03 7.21 E-03 7.21E-03 7.21E-03 On U

Page 29 of 136

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT  ;

OFFSITE DOSE CALCULATION MANUAL January 26,1996  !

i'3 V Table 5.1-1 (continued) l Dose factor - liquid release pathway (mrem /Ci released)

, Na-24 I

Bone - Liver T. Body R yroid - Kidney Lungs GI-LLI Adult 1.85E-04 1.85E-04 1.85E-04 1.85E-04 1.85E-04 1.85E-04 1.85E-04 Teen 1.98E-04 1.98E-04 1.98E-04 1.98E 04 1.98E-04 1.98E-04 1.98E-04 Child 2.40E-04 2.40E-04 2.40E-04 2.40E-04 2.40E-04 2.40E-04 2.40E-04 Infant 8.06E-05 8.06E-05 8.06E-05 8.06E-05 8.06E-05 8.06E-05 8.06E-05 Dose factor - liquid release pathway (mrem /Ci released)

Sc-46 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 1.70E-07 3.31 E-07 8.92E-06 0.00E+00 3.09E-07 0.00E + 00 1.61E-03 Teen 1.52E-07 2.97E-07 4.94E-05 0.00E+ 00 2.84E-07 0.00E+00 1.01E43 Child 3.54E-07 4.85E-07 1.05E-05 0.00E+00 4.29E-07 0.00E+00 7.09E-04 Infant 3.42E-07 4.94 E-07 1.54E-07 0.00E+00 3.25E-07 0.00E+ 00 3.22E-04 Dose factor - liquid release pathway (mrem /Ci released)

Mn-54 Bone Liver T. Body  % yroid Kidney Lungs GI-LLI Adult 0.00E+ 00 3.28E-03 6.34E-04 0.00E+00 9.75E-04 0.00E+00 1.00E-02 Teen 0.00E+ 00 3.22E-03 6.86E-04 0.00E + 00 9.59E-04 0.00E + 00 6.60E-03 Child 0.00E+ 00 2.60E-03 7.04E-04 0.00E+00 7.30E-04 0.00E + 00 2.19E-03 Infant 0.00E + 00 1.92E-04 4.34E-05 0.00E + 00 4.25E-05 0.00E+00 7.04E-05 (O)

Page 30 of 136

I POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 Table 5.1-1 (continued)

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

Cr-51 Bone Liver T. Body Thyroid Kidney Lungs GI-111 Adult 0.00E +00 0.00E+00 1.01E-06 5.84E-07 2.15E-07 1.30E-06 2.46E-04 Teen 0.00E+00 0.00E+00 1.17E-06 5.60E-07 2.21 E-07 1.44E-06 1.70E-04 Child 0.00E+ 00 0.00E + 00 1.19E-06 6.44E-07 1.76E-07 1.18E-06 6.15E-05 Infant 0.00E + 00 0.00E+ 00 1.72E-07 1.12E-07 2.45E-08 2.18E-07 5.01E-06 Dose factor - liquid release pathway (mrem /Ci released)

Mn-56 Bone Liver- T. Body H yroid lL Kidney Ltmgs GI-Lil f

Adult 0.00E+00 3.18E-06 5.65E-07 0.00E+00 l 4.04E 06 0.00E+ 00 1.02E-04 Teen 0.00E+00 3.33 E-06 5.94E-07 0.00E + 00 4.22E-06 0.00E+ 00 2.19E-04 Child 0.00E+00 3.04E-06 6.86E-07 0.00E + 00 3.67E-06 0.00E+00 4.40E-04 Infant 0.00E +00 1.97E-11 3.39E-12 0.00E + 00 1.69E-11 0.00E+00 1.79E-09 l

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

Fe-55 Bone Liver T. Body Hyroid Kidney Lungs GI-LLI Adult 5.98E-04 4.13 E-04 9.63E-05 0.00E + 00 0.00E + 00 2.31E-04 2.37E-04 Teen 6.11E-04 4.33 E-04 1.01E-04 0.00E + 00 0.00E+00 2.75E-04 1.88E-04 Child 9.35E-04 4.96E-04 1.54E-04 0.00E+00 0.00E+00 2.80E-04 9.19E-05 Infant 1.55E-04 1.00E-04 2.68E45 0.00E+00 0.00E+00 4.91E-05 1.28E-05 0) e Page 31 of 136

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR I Revision 10 DRAFT l OFFSITE DOSE CALCULATION MANUAL January 26,1996 Table 5.1-1 (continued)

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

Fe-59 1 Bone Liver T. Body Thyroid Kidney Lungs- GI-LLI Adult 9.12E-04 2.14E-03 8.23 E-04 0.00E+00 0.00E+00 5.99E-04 7.14E-03 Teen i 9.22E-04 2.15E-03 8.40E-04 0.00E +00 0.00E+00 6.79E-04 5.09E-03 Child 1.29E-03 2.09E-03 1.04E-03 0.00E+00 0.00E+00 6.07E-04 2.18E-03 Infant 3.34E-04 5.84E-04 2.30E-04 0.00E+ 00 0.00E+ 00 1.73E-04 2.79E-04 Dose factor - liquid release pathway (mrem /Ci released)

Co-57 Bone Liver T. Body Thyroid Kidney Lungs GI LLI Adult 0.00E+ 00 2.02E-05 3.57E45 0.00E+00 0.00E+ 00 0.00E+00 5.13 E-04 j Teen 0.00E + 00 2.06E-05 4.62E-05 0.00E+00 0.00E+ 00 0.00E + 00 3.83 E-04 l I

('T 0.00E+ 00 4.93 E-05 0.00E+00 0.00E+00 0.00E+00 1.89E-04 V Child . 2.31E-05  !

Infant 0.00E+00 1.24E-05 2.02E-05 0.00E+ 00 0.00E +00 0.00E+ 00 4.24E-05 I

l I

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

Co-58 Bone ' Liver T. Body Thyroid Kidney- ' Lungs ' GI-LLI i Adult - 0.00E+00 8.49E-05 1.93 E-04 0.00E+00 0.00E+ 00 0.00E+ 00 1.72E-03  ;

1 Teen 0.00E+00 8.30E-05 2.04E-04 0.00E+00 0.00E+ 00 0.00E+ 00 1.14E-03 Child. 0.00E + 00 8.32E-05 2.57E-04 0.00E+ 00 0.00E+ 00 0.00E + 00 4.85E-04 Infant 0.00E + 00 3.84E-05 9.58E-05 0.00E+00 0.00E+ 00 0.00E+00 9.57E-05 O

V Page 32 of 136

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFUSITE DOSE CALCULATION MANUAL January 26,1996

/h ^

Table 5.1-1 (continued) j l

1 l

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

Co-60 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI 4

Adult 0.00E + 00 2.48E-04 6.82E-04 0.00E+ 00 0.00E+00 0.00E+00 4.66E-03 Teen 0.00E +00 2.44E-04 1.30E-03 0.00E+00 0.00E+00 0.00E+00 3.17E-03 Child 0.00E+00 2.49E-04 8.92E-04 0.00E+00 0.00E +00 0.00E+ 00 1.38E-03 Infant 0.00E + 00 1.17E-04 2.77E-04 0.00E+00 0.00E +00 0.00E + 00 2.79E-04 Dose factor - liquid release pathway (mrem /Ci released)

Ni-63 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 3.03 E-02 2.10E-03 1.02E-03 0.00E+ 00 0.00E+00 0.00E+00 4.38E-04 Teen 3.13 E-02 2.21 E-03 1.06E-03 0.00E + 00 0.00E+00 0.00E +00 3.52E-04 Child - 5.00E-02 2.67E-03 1.70E-03 0.00E+00 0.00E+ 00 0.00E+00 1.80E-04 Infant 1.27E-02 7.85E-04 4.41E-04 0.00E+ 00 0.00E+ 00 0.00E+ 00 3.91 E-05 l

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

Ni-65 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 3.39E-06 4.40E-07 2.01 E-07 0.00E+00 0.00E+ 00 0.00E + 00 1.12E-05 Teen 3.66E-06 4.68E-07 2.13 E-07 0.00E+ 00 0.00E+ 00 0.00E +00 2.54E-05 Child 4.68 E-06 4.41E-07 2.57E-07 0.00E +00 0.00E+00 0.00E +00 5.40E-05 Infant 1.74E-10 1.97E-11 8.95E-12 0.00E+00 0.00E + 00 0.00E + 00 1.50E-09 O

's- /

Page 33 of 136

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/~N V Table 5.1-1 (continued)

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

Cu-64 i

Bone Liver T. Body H yroid- Kidney- Lungs GI-LLI Adult 0.00E + 00 4.02E-06 1.89E-06 0.00E+00 1.01E-05 0.00E+00 3.43E-04 Teen- 0.00E+00 4.31E-06 2.04E-06 0.00E+ 00 1.09E-05 0.00E +00 3.34E-04 Child - 0.00E+00 4.30E-06 2.60E-06 0.00E+00 1.04E-05 0.00E+00 2.02E-04 1

3Snt 0.00E+00 1.41E-06 6.52E-07 0.00E + 00 2.38E-06 0.00E+00 2.89E-05 l

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

Zn-65 1 1

Bone Liver T. Body Thyroid Kidney' Lungs GI-LLI Adult 1.73 E-02 5.50E-02 2.49E-02 0.00E + 00 3.68E 02 0.00E + 00 3.46E-02 j 4

Teen 1.58E 02 5.50E-02 2.57E-02 0.00E + 00 3.52E-02 0.00E+00 2.33 E-02 Child 1.68E-02 4.47E-02 2.78E-02 0.00E +00 2.82E-02 0.00E + 00 7.85E-03 Infant 1.32E-03 4.51 E-03 2.08E-03 0.00E+00 2.19E-03 0.00E+00 3.81E-03  ;

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

Zn-69 Bone Liver T. Body H yroid Kidney - Lungs GI-LLI Adult 1.97E-05 3.76E-05 2.62E-06 0.00E+00 2.44E-05 0.00E + 00 5.65E-06 Teen 2.14 E-05 4.08E-05 2.86E-06 0.00E+00 2.67E-05 0.00E+ 00 7.52E-05 Child 2.77E-05 4.00E-05 3.70E-06 0.00E+00 2.43 E-05 0.00E+00 2.51E-03 Infant 5.98E-07 1.08E-06 8.01 E-08 0.00E+00 4.47E-07 0.00E + 00 8.78E45 i

4

\.J ,

1 Page 34 of 136

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR l Revision 10 DRAFT

! OFFSITE DOSE CALCULATION MANUAL January 26,1996 Table 5.1-1 (continued) l Dose factor - liquid release pathway (mrem /Ci released)

Zn-69m Bone- Liver T. Body . Thyroid Kidney Lungs GI-LLI Adult 3.25E-04 7.79E-04 7.12E-05 0.00E+00 4.72E-04 0.00E+00 4.76E-02 Teen 3.50E-04 8.25E-04 7.57E-05 0.00E+ 00 5.01 E-04 0.00E + 00 4.53E-02 Child 4.49E-04 7.65E-04 9.04E-05 0.00E+00 4.44E-04 0.00E + 00 2.49E-02 Infant 9.61E-06 1.%E-05 1.79E-06 0.00E+00 7.94E-06 0.00E + 00 2.72E-04 Dose factor - liquid release pathway (mrem /Ci released)

Br-82 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI -

Adult 0.00E+00 0.00E+00 1.39E-03 0.00E + 00 0.00E +00 0.00E+00 1.59E-03 Teen 0.00E+ 00 0.00E+ 00 1.47E4)3 0.00E+00 0.00E+00 0.00E+ 00 0.00E+00 p)

( Child 0.00E + 00 0.00E+00 1.71E-03 0.00E+00 0.00E+ 00 0.00E+ 00 0.00E+00 Infant 0.00E + 00 0.00E+ 00 4.43 E-04 0.00E+00 0.00E+ 00 0.00E +00 0.00E+00 Dose factor - liquid release pathway (mrem /Ci released) l Br-83 j Bone Liver T. Body Thyroid Kidney Lungs ' CI-LLI Adult 0.00E+00 0.00E +00 9.06E-07 0.00E+00 0.00E+00 0.00E + 00 1.30E-06 Teen 0.00E+00 0.00E + 00 9.85E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Child 0.00E+00 0.00E + 00 1.27E-06 0.00E + 00 0.00E + 00 0.00E + 00 0.00E+00 l Infant 0.00E+00 0.00E+00 2.93E-11 0.00E+00 0.00E-F00 0.00E+ 00 0.00E+ 00 lO V

Page 35 of 136

. = . ,_- -

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 f3 Table 5.1-1 (continued)

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

Br-84 Bone . Liver' T. Body 'Ihyroid Kidney -Imngs GI-LLI Adult 0.00E+00 0.00E + 00 3.12E-05 0.00E+00 0.00E+00 0.00E+00 2.44E-10 Teen 0.00E +00 0.00E+ 00 3.43E-05 0.00E+00 0.00E+00 0.00E+00 0.00E + 00

. Child 0.00E+00 0.00E+00 4.33E-05 0.00E+ 00 0.00E +00 0.00E+ 00 0.00E + 00 Infant 0.00E+00 0.00E +00 1.20E-05 0.00E +00 0.00E + 00 0.00E + 00 0.00E+ 00 3 Dose factor - liquid release pathway (mrem /Ci released)  :

i Br-85 Bone Liver T. Body Thyroid Kidney Ltmgs GI-LLI Adult 0.00E+ 00 0.00E + 00 4.24E-82 0.00E+00 0.00E + 00 0.00E+00 0.00E + 00 Teen 0.00E + 00 0.00E+00 4.60E-82 0.00E+00 0.00E+00 0.00E+00 0.00E + 00

, O, 0.00E+00 0.00E+00 0.00E +00 0.00E+00 V Child 0.00E + 00 5.94E-82 0.00E + 00 Infant 0.00E+ 00 0.00E + 00 9.35E-309 0.00E+00 0.00E +00 0.00E+00 0.00E+00 Dose factor - liquid release pathway (mrem /Ci released)

Rb-86 Bone Liver T. Body - Thyroid Kidney Lungs GI-LLI Adult 0.00E+00 7.36E-02 3.43 E-02 0.00E+ 00 0.00E+00 0.00E+00 1.45E-02 Teen 0.00E+00 7.98 E-02 3.75E-02 0.00E + 00 0.00E+00 0.00E+00 1.18E-02 Child 0.00E + 00 7.93E-02 4.88E-02 0.00E+00 0.00E + 00 0.00E+ 00 5.10E-03 Infant 0.00E+ 00 9.07E-03 4.48E-03 0.00E+00 0.00E+00 0.00E + 00 2.32E-04 4

O Page 36 of 136

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,O J V Table 5.1-1 (continued) l Dose factor - liquid release pathway (mrem /Ci released)

Rb-88 1

Bone - Liver T. Body Thyroid . Kidney Lungs GI-LLI j Adult 0.00E +00 1.41 E-16 7.46E-17 0.00E+ 00 0.00E +00 0.00E+00 1.94E-27 Teen 0.00E+00 1.51E-16 8.04E-17 0.00E+00 0.00E + 00 0.00E +00 1.29E-23 Child 0.00E +00 1.45E-16 1.01E-16 0.00E + 00 0.00E +00 0.00E +00 7.12E-18 Infant 0.00E+00 5.68E-54 3.12E-54 0.00E+ 00 0.00E+ 00 0.00E + 00 5.54E-54 Dose factor - liquid release pathway (mrem /Ci released)

Rb-89 Bone Liver T. Body  % yroid- Kidney- Lungs GI-LLI I Adult 0.00E+ 00 1.28E-18 8.99E-19 0.00E+00 0.00E+00 0.00E +00 7.42E-32 ,

1 l Teen 0.00E+00 1.34E-18 9.45E-19 0.00E +00 0.00E+00 0.00E+00 2.05E-27 Child 0.00E + 00 1.23E-18 1.09E-18 0.00E+00 0.00E + 00 0.00E+00 1.07E-20 i 4

Infant 0.00E +00 1.15E-61 7.93 E-62 0.00E+00 0.00E+00 0.00E+00 3.92E-62 Dose factor -liquid release pathway (mrem /Ci released) r Sr-89 Bone Liver T. Body n yroid Kidney Lungs GI-Lil Adult 2.26E-02 0.00E+00 6.48E-04 0.00E + 00 0.00E+00 0.00E+00 3.62E-03 Teen 2.43 E-02 0.00E + 00 6.95E-04 0.00E + 00 0.00E+ 00 0.00E+ 00 2.89E 03 Child 4.27E-02 0.00E + 00 1.22E-03 0.00E + 00 0.00E+00 0.00E+00 1.65E-03 Infant 2.58E-02 0.00E + 00 7.40E-04 0.00E+00 0.00E + 00 0.00E+00 5.30E-04 i

4 O

Page 37 of 136

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 f

L Table 5.1-1 (continued)

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

St-90 Bone Liver T. Body 'lhyroid Kidney Ixngs - GI-111 Adult 5.63E-01 0.00E + 00 1.38E41 0.00E+00 0.00E+ 00 0.00E +00 1.63 E-02 Teen 4.64 E-01 0.00E+00 1.15E-01 0.00E+00 0.00E+00 0.00E+00 1.30E-02 Child 5.59E-01 0.00E +00 1.42E-01 0.00E+ 00 0.00E + 00 0.00E+ 00 7.53 E-03 Infant 1.95E-01 0.00E +00 4.97E-02 0.00E + 00 0.00E + 00 0.00E+ 00 2.44E-03 Dose factor - liquid release pathway (mrem /Ci released)

Sr-91 Bone Liver T. Body Thyroid Kidney Lungs- GI-Lil Adult 1.27E 04 0.00E + 00 5.14E-06 0.00E+ 00 0.00E + 00 0.00E+ 00 6.05 E-04 Teen 1.38E-04 0.00E+00 5.51E-06 0.00E+ 00 0.00E+00 0.00E + 00 6.24E-04 Child 1.83 E-04 0.00E+00 6.91 E-06 0.00E+00 0.00E + 00 0.00E + 00 4.04E44 Infant 1.59E-05 0.00E+00 5.76E-07 0.00E +00 0.00E+00 0.00E+ 00 1.88E-05 Dose factor - liquid release pathway (mrem /Ci released)

Sr-92 Bone 'Ijver T. Body Thyroid Kidney Lungs- GI-LLI Adult 5.21E-06 0.00E+00 2.26E-07 0.00E +00 0.00E+ 00 0.00E + 00 1.03 E-04 Teen 5.64E-06 0.00E+00 2.42E-07 0.00E+00 0.00E + 00 0.00E+00 1.44E-04 Child 7.20E-06 0.00E+00 2.89E-07 0.00E + 00 0.00E+00 0.00E + 00 1.36E-04 Infant 9.41 E-10 0.00E+00 3.50E-11 0.00E + 00 0.00E+ 00 0.00E+ 00 1.01 E-08 Page 38 of 136

I POINT BEACH NUCLEAR PLANT ODCM i OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 )

/3

(_/ i Table 5.1-1 (continued) l I

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

Y-90 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 4.85E-07 0.00E+00 1.30E-08 0.00E+00 0.00E+00 0.00E+00 5.15E-03 Teen 5.16E-07 0.00E+00 1.40E-08 0.00E + 00 0.00E + 00 0.00E+00 4.26E-03 Child 8.67E-07 0.00E+00 2.32E-08 0.00E+ 00 0.00E +00 0.00E+00 2.47E-03 Infant 4.80E47 0.00E + 00 1.29E 08 0.00E + 00 0.00E +00 0.00E+00 6.63 E-04 Dose factor - liquid release pathway (mrem /Ci released)

Y-91 Bone Liver T. Body "

Ihyroid ' Kidney Lungs- GI-LLI -

Adult 9.20E-06 0.00E+00 2.53 E-07 0.00E+00 0.00E+00 0.00E+ 00 5.06E-03 Teen 9.68E-06 0.00E+00 2.97E-07 0.00E +00 0.00E+00 0.00E + 00 3.97E-03 Child 1.74E-05 0.00E+00 4.74E 07 0.00E+00 0.00E+ 00 0.00E+00 2.32E-03 Infant 1.03 E-05 0.00E+00 2.73 E-07 0.00E+00 0.00E+ 00 0.00E+00 7.35E-04 _

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

Y-91m Bone Liver T. Body Thyroid ' Kidney Lun'gs GI-LLI Adult 1.71 E-13 0.00E + 00 5.10E-14 0.00E+00 0.00E + 00 0.00E+00 5.02E-13 Teen 1.85E-13 0.00E + 00 2.55E-13 0.00E+00 0.00E+00 0.00E+00 8.72E-12 <

Child 2.36E-13 0.00E+00 6.04E-14 0.00E+ 00 0.00E+ 00 0.00E+ 00 4.62E-10 Infant 2.62E-26 0.00E +00 8.92E-28 0.00E + 00 0.00E+00 0.00E+ 00 8.72E-23 Page 39 of 136

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996

~J Table 5.1-1 (continued) i Dose factor - liquid release pathway (mrem /Ci released) -

Y-92 Bone Liver T. Body R yroid Kidney Lungs ' GI-LLI '

Adult 3.51E-09 0.00E+00 2.88E-10 0.00E + 00 0.00E+00 0.00E+00 6.15E-05 Teen 3.83E-09 0.00E +00 1.15E-09 0.00E + 00 0.00E + 00 0.00E+00 1.05E-04 Child 4.92E49 0.00E+00 3.57E-10 0.00E+00 0.00E +00 0.00E + 00 1.42E-04 Infant 5.88E-12 0.00E+ 00 1.65E-13 0.00E+ 00 0.00E + 00 0.00E+ 00 1.12E-07 Dose factor - liquid release pathway (mrem /Ci released)

Y-93 Bone Liver T. Body - Thyroid Kidney Lungs ' GI-LLI Adult 5.32E-08 0.00E+ 00 2.33E-09 0.00E + 00 0.00E+00 0.00E +00 i.69E43 4 Teen- 5.77E-08 0.00E+ 00 6.38E-09 0.00E + 00 0.00E+00 0.00E + 00 1.76E-03 Child 7.75E-08 0.00E+00 3.13E-09 0.00E + 00 0.00E+00 0.00E+ 00 1.16E-03 Infant 8.33E-09 0.00E+00 2.27E-10 0.00E+ 00 0.00E + 00 0.00E+00 6.58E-05 Dose factor - liquid release pathway (mrem /Ci released)

Zr-95 Bone' Uver T. Body h yroid Kidney Lungs GI-LLI Adult 1.23 E-06 3.94E-07 1.79E-06 0.00E+00 6.19E-07 0.00E + 00 1.25E-03 Teen 1.11 E-06 3.52E-07 8.74E-06 0.00E+ 00 5.17E-07 0.00E+00 8.11E-04 Child 2.48 E-06 5.45E-07 2.26E-06 0.00E+ 00 7.80E-07 0.00E+00 5.69E-04 Infant 1.87E-06 4.56E-07 3.23E-07 0.00E+00 4.91 E-07 0.00E + 00 2.27E-04 O

Page 40 of 136

POINT BEACH NUCLEAR PLANT ODCM  !

, OFFSITE DOSE CALCULATION MANUAL l MAJOR f Revision 10 DRAFT l OFFSITE DOSE CALCULATION MANUAL January 26,1996 i

(

Table 5.1-1 (continued) l Dose factor - liquid release pathway (mrem /Ci released) l Zr-97 Bone Liver T. Body Thyroid Kidney Lungs- GI-LIJ Adult 1.07E-08 2.16E-09 1.23E-08 0.00E +00 3.27E-09 0.00E+ 00 6.70E-04 Teen 1.11E-08 2.19E-09 6.42E-08 0.00E +00 3.33 E-09 0.00E+ 00 5.94E-04 I Child 2.21E-08 3.19E-09 1.51E-08 0.00E + 00 4.58E-09 0.00E + 00 4.83E-04 Infant ~ 1.92E-08 3.29E-09 1.50E-09 0.00E +00 3.32E-09 0.00E+ 00 2.10E-04 l

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

Nb-95 Bone- Liver T. Body Thyroid Kidney Lungs GI-LLI ,

Adult 3.23E-04 1.79E-04 9.73E-05 0.00E + 00 1.77E-04 0.00E+ 00 1.09E + 00 Teen 3.25E-04 1.80E44 1.04E-04 0.00E+ 00 1.75E-04 0.00E+00 7.70E-01 Child 3.84E-04 1.49E-04 1.08E-04 0.00E+00 1.40E 04 0.00E+00 2.76E-01 In fant 5.36E-07 2.21E-07 1.28E-07 0.00E+00 1.58E-07 0.00E+00 1.86E-04 Dose factor - liquid release pathway (mrem /Ci released)

Nb-97 Bone- Liver T. Body 'Ihyroid ' Kidney ' Lungs ~ GI-LLI Adult 2.69E-09 6.81E-10 2.51E-10 0.00E +00 7.95E-10 0.00E + 00 2.51 E-06 Teen 2.90E-09 7.20E-10 2.73E-10 0.00E+00 8.41E-10 0.00E + 00 1.72E-05 Child 3.68E-09 6.65E-10 3.12E-10 0.00E+00 7.38E-10 0.00E + 00 2.05E-04 Infant 5.81 E-21 1.24E-10 4.47E-22 0.00E+00 9.68E-22 0.00E+ 00 3.91E-16 Page 41 of 136

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 O

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

Mo-99 Bone Uver T. Body ' Thyroid Kidney ' Lungs GI-111 Adult 0.00E+ 00 1.49E-04 2.84E-05 0.00E +00 3.38E-04 0.00E +00 3.46E-04 Teen 0.00E + 00 1.76E-04 3.36E-05 0.00E+ 00 4.03 E-04 0.00E+ 00 3.15E-04 Child 0.00E+00 2.79E-04 6.91E-05 0.00E+00 5.% E-04 0.00E+ 00 2.31E-04 Infant 0.00E +00 4.38E-04 8.54E-05 0.00E +00 6.54E-04 0.00E+ 00 1.44E-04 Dose factor - liquid release pathway (mrem /Ci released)

Tc-99m l Bone Liver T. Body Thyroid Kidney Lungs' GI-LLI Adult a 68E-09 4.74E-09 6.07E-08 0.00E+00 7.20E-08 2.32E-09 2.81 E-06 Teen 1.74E-09 4.86E-09 6.46E-08 0.00E+00 7.24E-08 2.70E-09 3.19E-06 i Child 2.19E-09 4.29E-09 7.15E-08 0.00E+00 6.24E-08 2.18E-09 2.44E-06 Infant 3.78E-10 7.79E-10 1.00E-08 0.00E+00 8.38E-09 4.07E-10 2.26E-07 Dose factor - liquid release pathway (mrem /Ci released)

Tc-101 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 3.60E-24 5.19E-24 5.10E-23 0.00E+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 i Child 4.98E-24 5.22E-24 6.63 E-23 0.00E+ 00 8.90E-23 2.76E-24 1.66E-23 Infant 9.73 E-69 1.23 E-68 1.21E-67 0.00E+00 1.46E-67 6.69E-69 2.08E-66 O

Page 42 of 136

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 Table 5.1-1 (continued)

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

Ru-103 Bone-- ' Liver T. Body Thyroid - Kidney Lungs GI-LLI Adult 3.47E-05 0.00E+ 00 1.56E-05 0.00E+ 00 1.32E-04 0.00E+00 4.05E-03 Teen 2.96E-05 0.00E+00 1.64E-05 0.00E+00 1.04E-04 0.00E+00 2.47E-03 Child 5.53E-05 0.00E+ 00 2.20E-05 0.00E+ 00 1.39E-04 0.00E+ 00 1.43E-03 Infant 1.33E-05 0.00E +00 4.43E-06 0.00E+00 2.76E-05 0.00E +00 1.61E-04 Dose factor - liquid release pathway (mrem /Ci released)

Ru-105 Bone Liver T. Body Thyroid - Kidney Lungs GI-LLI Adult 4.13E-08 0.00E+ 00 1.75E-08 0.00E+ 00 5.34E-07 0.00E+00 2.53 E-05 Teen 4.45E-08 0.00E + 00 2.42E-08 0.00E+ 00 5.62E-07 0.00E+ 00 3.59E-05 m

() Child Infant 5.71E-08 6.98E-10 0.00E+ 00 0.00E +00 2.22E-08 2.35E-10 0.00E + 00 0.00E+ 00 5.02E-07 5.13 E-09 0.00E+00 0.00E + 00 3.73E-05 2.78E-07 Dose factor - liquid release pathway (mrem /Ci released)

Ru-106

~

Bone- Liver T. Body Thyroid Kidney ' Lungs GI-LLI Adult 6.71E44 0.00E+ 00 8.76E-05 0.00E+ 00 1.30E-03 0.00E + 00 4.34E42 Teen 5.86E-04 0.00E+ 00 8.85E-05 0.00E + 00 1.13 E-03 0.00E+ 00 2.81E-02 Child 1.13E-03 0.00E+00 1.44E-04 0.00E+ 00 1.53E-03 0.00E+ 00 1.76E-02 Infant 2.23 E-04 0.00E+ 00 2.78E-05 0.00E+00 2.63 E-04 0.00E+00 1.69E-03 O

Page 43 of 136

POINT BEACH NUCLEAR PLANT ODCM l OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 i

Table 5.1-1 (continued)

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

Rh-105 Bone Liver- T. Body Thyroid .- Kidney Lungs GI LLI Adult 3.35E-06 2.45E-06 1.62E-06 0.00E+00 1.04E-05 0.00E + 00 3.90E-04 Teen 4.10E4)6 2.%E-06 1.97E-06 0.00E+00 1.26E-05 0.00E+ 00 3.77E-04 Child 8.43E-06 4.52E-06 3.88E-06 0.00E + 00 1.80E-05 0.00E +00 2.80E-04 Infant - 1.08E-05 7.05E-06 4.74E-06 0.00E + 00 1.%E-05 0.00E+00 1.75E-04 1

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

1 Ag-110m Bone -Liver T. Body ' Thyroid Kidney- Lungs GI LLI

, Adult - 3.06E-05 2.83E-05 3.83E-05 0.00E+00 5.56E-05 0.00E+ 00 1.15E-02 Teen 3.74E-05 3.54E-05 1.41 E-04 0.00E+ 00 6.75E-05 0.00E+00 9.94E-03 Child 6.78E-05 4.58E-05 6.17E-05 0.00E + 00 8.53E-05 0.00E+ 00 5.45E-03 Infant 8.87E-05 6.47E-05 4.28E-05 0.00E + 00 9.26E-05 0.00E+00 3.36E-03 Dose factor - liquid release pathway (mrem /Ci released)

Sb-124 i Bone Liver T. Body ' Thyroid Kidney Lungs GI-LLI Adult 5.42E-04 1.02E-05 2.21 E-04 1.32E-06 0.00E+00 4.22E-04 1.54E-02 l Teen 5.66E-04 1.04E-05 2.53E-04 1.28E-06 0.00E+00 4.94E-04 1.14E-02 Child 7.89E-04 1.02E-05 2.83E-04 1.74E-06 0.00E+00 4.38E-04 4.94E-03 Infant 1.95E-04 2.86E-06 6.03E-05 5.17E-07 0.00E+00 1.22E-04 6.00E-04 i

Page 44 of 136

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 A

Table 5.1-1 (continued)

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

Sb-125 Bone Liver T. Body 'Ihyroid Kidney- Lungs GI-LLI Adult 3.49E-04 3.90E-06 1.07E-04 3.55E-07 0.00E+ 00 2.69E-04 3.85E-03 Teen 3.65E-04 3.99E-06 2.19E-04 3.49E47 0.00E+00 3.21E-04 2.84E-03 Child - 5.14E-04 3.96E-06 1.35E-04 4.76E-07 0.00E+00 2.86E-04 1.23 E-03 4

Infant 1.14E-04 1.11 E-06 2.35E-05 1.43 E-07 0.00E+00 7.17E-05 1.52E-04 i

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

Te-125m Bone- Liver ' T. Body - Thyroid Kidney Lungs- GI-LLI Adult 3.30E-04 1.20E-04 4.43 E-05 9.93E-05 1.34E-03 0.00E+00 1.32E-03

. Teen 3.36E-04 1.21E-04 4.53E-05 9.39E-05 0.00E+ 00 0.00E+00 9.92E-04 Child 5.74E-04 1.56E-04 7.67E-05 1.61E-04 0.00E + 00 0.00E+00 5.54E-04 4

Infant 2.47E-04 8.27E-05 3.35E-05 8.33E-05 0.00E+ 00 0.00E + 00 1.18E-04 l Dose factor - liquid release pathway (mrem /Ci released)

Te-127 Bone Liver T. Body - Thyroid - Kidney Lungs GI-LLI Adult 3.15E-05 1.13 E-05 6.83 E-06 2.34E-05 1.28E-04 0.00E+00 2.49E-03 Teen- 3.45E-05 1.22E 05 7.43 E-06 2.38E-05 1.40E-04 0.00E+00 2.67E-03 Child 4.45E-05 1.20E-05 9.54E-06 3.08E-05 1.27E-04 0.00E+00 1.74E-03

~

Infant 3.10E-07 1.04E-07 6.67E-08 2.52E-07 7.56E-07 0.00E+00 6.51 E-06 4

4 O

a Page 45 of 136

._ =

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 Table 5.1-1 (continued)

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

Te-127m Bone Liver T. Body Thyroid Kidney Lungs GI-111 Adult 8.63E-04 3.08E-04 1.05E-04 2.21E-04 3.51E-03 0.00E + 00 2.89E-03 Teen 8.74E-04 3.10E-04 1.04E-04 2.08E-04 3.54E-03 0.00E +00 2.18E-03 Child 1.50E-03 4.05E-04 1.79E-04 3.60E-04 4.29E-03 0.00E+00 1.22E-03 Infant 6.28E44 2.08E-04 7.61E-05 1.82E44 1.55E-03 0.00E+ 00 2.54E-04 i

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

Te-129 Bone Liver T. Body Thyroid Kidney Lungs- -- GI-LU Adult 1.68E-08 6.32E-09 4.10E-09 1.29E-08 7.07E-08 0.00E +00 1.27E-08 Teen 1.83E-08 6.82E-09 4.45E-09 1.31 E-08 7.68E-08 0.00E+00 1.00E-07 Child 2.36E-08 6.58E-09 5.60E-09 1.68E-08 6.90E-08 0.00E+ 00 1.47E-06 Infant 1.08E-18 3.73 E-19 2.53E-19 9.07E-19 2.69E-18 0.00E+ 00 8.65E-17 Dose factor - liquid release pathway (mrem /Ci released)

Te-129m Bone Uver T. Body Thyroid Kidney - Lungs GI-LLI I Adult 1.35E-93 5.04E-04 2.14E44 4.64E-04 5.63 E-03 0.00E+00 6.80E-03 Teen 1.37E-03 5.10E-04 2.18E-04 4.43E-04 5.75E-03 0.00E + 00 5.16E-03 Child 2.34E-03 6.54E-04 3.64E44 7.55E-04 6.88E43 0.00E + 00 2.86E-03 Infant 1.04E-03 3.58E44 1.61 E-04 4.01 E-04 2.61E43 0.00E +00 6.23 E-04 O

Page 46 of 136

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 Table 5.1-1 (continued)

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

Te-131m _

E.* 6 Liver T. Body ' Thyroid Kidney Lungs GI-111 Adult 1.04E-04 5.08E-05 4.24E-05 8.05E-05 5.15E-04 0.00E+00 5.05E-03 Teen 1.11E-04 5.34E-05 4.49E-05 8.03E45 5.56E-04 0.00E +00 4.28E-03 Child 1.63E-04 5.63E-05 6.00E-05 1.16E-04 5.45 E-04 0.00E+00 2.28E-03 Infant 5.46E-05 2.20E-05 1.81E 05 4.45E-05 1.51E-04 0.00E+ 00 3.70E-04 Dose factor - liquid release pathway (mrem /Ci released)

Te-131 Bone Liver T. Body Thyroid Kidney Lungs GI-Lil Adult 2.97E-15 1.24E-15 9.40E-16 2.44E-15 1.30E-14 0.00E + 00 4.21 E-16 Teen 3.21E-15 1.32E-15 1.01E-15 2.47E-15 1.40E-14 0.00E + 00 2.63 E-16 Child 4.12E-15 1.25E-15 1.23E-15 3.15E-15 1.24E-14 0.00E +00 2.16E-14 Infant 4.22E-41 1.56E-41 1.18E-41 3.77t?-41 1.08E-40 0.00E+00 1.71E-39 Dose facter - liquid release pathway (mrem /Ci released)

Te-132 Bone Liver T. Body Thyroid Kidney Lungs l GI-Lil Adult 1.96E-04 l 1.26E-04 1.19E44 1.40E-04 1.22E-03 0.00E +00 5.98E-03 Teen 2.05E-04 1.30E-04 1.22E-04 1.37E-04 .24E-03 0.00E+00 4.11 E-03 Child 3.15E-04 1.39E-04 1.69E-04 2.03 E-04 1.29E-03 0.00E + 00 1.40E-03 Infant 1.48E-04 7.32E-05 6.83E-05 1.08E-04 4.58E44 0.00E + 00 2.71E-04 O

wJ Page 47 of 136

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996

,a U Table 5.1-1 (continued)

Dose factor - liquid release pathway (mrem /Ci released) 1-131 Bone- Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 2.09E-04 2.99E-04 1.71 E-04 9.78E-02 5.12E-04 0.00E + 00 7.88 E-05 Teen 2.41E-04 3.37E-04 1.81 E-04 9.83 E-02 5.80E-04 0.00E + 00 6.66E-05 Child - 4.90E 04 4.93E-04 2.80E-04 1.63 E-01 8.09E-04 0.00E+ 00 4.39E-05 infant 5.71 E-04 6.73E-04 2.%E-04 2.21E-01 7.86E-04 0.00E+00 2.40E-05 Dose factor - liquid release pathway (mrem /Ci released) 1-132 Bone ~ Liver T. Body H yroid Kidney Lungs GI-LLI _

Adult 1.43 E-07 3.81 E-07 1.34E-07 1.33E-05 6.07E-07 0.00E+ 00 7.16E-08 Teen 1.49E-07 3.90E-07 1.41E-07 1.32E-05 6.15E-07 0.00E +00 1.70E-07 Child 1.85E-07 3.39E-07 1.56E-07 1.57E-05 5.19E-07 0.00E +00 3.99E-07 Infant 1.64E-I l 3.32E-11 1.18E-11 1.56E-09 3.71E-11 0.00E+ 00 2.69E-11 Dose factor - liquid release pathway (mrem /Ci released) 1-133 l Bone Liver T. Body  %'yroid ' Kidney Lungs GI-LLI I Adult 3.33E 05 5.80E-05 1.77E-05 8.52E-03 1.01 E-04 0.00E + 00 5.21E-05 Teen 3.74 E-05 6.34E-05 1.94E45 8.85E-03 1. I I E-04 0.00E+00 4.80E-05 l Child 6.27E-05 7.75 E-05 2.94E45 1.44E-02 1.29E-04 0.00E+ 00 3.13E-05 Infant 4.77E-05 6.95E-05 2.04 E-05 1.26E-02 8.17E-05 0.00E + 00 1.18E-05 O

Page 48 of 136

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 (3

O Table 5.1-1 (continued)

Dose factor - liquid release pathway (mrem /Ci released) 1-134 Bone Liver T. Body . 'Ihyroid . Kidney Lungs GI-LLI 2.09E-10 5.69E-10 2.04E-10 9.85E-09 9.04E-10 0.00E+ 00 4.%E-13

_ Adult Teen 2.20E-10 5.82E-10 2.10E-10 9.70E-09 9.18E-10 0.00E+00 7.67E-12 Child 2.72E-10 5.05E-10 2.33E-10 1.16E-08 7.72E-10 0.00E +00 3.35E-10 Infant 5.37E-22 1.10E-21 3.91E-22 2.56E-20 1.23E-21 0.00E+00 1.14E-21 Dose factor - liquid release pathway (mrem /Ci released)

I-135 Bone Liver T. Body Thyroid - Kidney Lungs GI-LLI Adult 3.37E-06 8.83 E-06 3.26E-06 5.82E-04 1.42E-05 0.00E+00 9.97E-06  :

Teen 3.55E-06 9.14E-06 3.41 E-06 5.88E-04 1.44E-05 0.00E+ 00 1.01E-05 Child 4.54E-06 8.17E-06 3.87E-06 7.24E-04 1.25E-05 0.00E+ 00 6.23 E-06 Infant 4.48E-07 8.92E-07 3.25E-07 7.99E-05 9.94E-07 0.00E +00 3.23E-07 Dose factor - liquid release pathway (mrem /Ci released)

Cs-134 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 2.19E-01 5.21E-01 4.26E-01 0.00E + 00 1.69E-01 5.60E42 9.12E-03 Teen 2.25E-01 5.30E-01 2.46E-01 0.00E+00 1.68E-01 6.43E-02 6.59E-03 Child 2.76E-01 4.52E-01 9.55E-02 0.00E +00 1.40E-01 5.03 E-02 2.44E-03 Infa:e 1.07E-02 2.00E-02 2.02E43 0.00E + 00 5.16E-03 2. l l E-03 l 5.44E-05 O

Page 49 of 136

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 Table 5.1-1 (continued)

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

Cs-134m 5

Bone Live- T. Body - Thyroid Kidney Lungs GI-LLI Adult 4.21E-06 8.85 E-06 4.52E-06 0.00E+00 4.80E-06 7.56E-07 3.12E-06 Teen 4.42E-06 9.16E-06 4.71 E-06 0.00E+00 5.10E46 8.95E-07 6.0E-06 Child 5.48E-06 8. l l E-06 5.29E-06 0.00E+00 4.28E-06 7.07E-07 1.03 E-05 Infant 5.19E-11 8.64E-Il 4.37E-Il 0.00E+00 3.33E-Il 7.67E-12 6.84E-11 Dose factor - liquid release pathway (mrem /Ci released)

Cs-136 Bone Liver T. Body  % yroid Kidney Lungs GILLI Adult 2.23 E-02 8.81 E-02 6.34E-02 0.00E +00 4.90E-02 6.72E-03 1.00E-02 Teen 2.25E-02 8.85E-02 5.95E-02 0.00E+00 4.82E-02 /.59E-93 7.12E-03 Child 2.69E-02 7.40E-02 4.79E-02 0.00E+00 3.94E-02 5.87E-03 2.60E-03 Infant 1.18 E-03 3.47E 03 1.29E-03 0.00E + 00 1.38E-03 2.83E-04 , 5.27E-05 l

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

Cs-137 Bone IJver T. Body H yroid Kidney Lungs GI-LLI Adult 2.81E Ol 3.84E-01 2.52E-01 0.00E+ 00 1.30E-01 4.33E-02 7.43E-03 Teen 3.02E-01 4.01 E-01 1.40E-01 0.00E+00 1.36E-01 5.30E-02 5.71E43 Child 3.85E-01 3.69E-01 5.45E-02 0.00E+00 1.20E-01 4.33E-02 2.31E-03 Infant 1.49E-02 1.74E-02 1.24E43 0.00E+ 00 4.68E43 1.89E-03 5.45E-05

)

Page 50 of 136

POINT BEACII NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 t,,

Table 5.1-1 (continued)

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

. Cs-138 I Bone- Liver T. Body Thyroid Kidney 'I r gs GI-LLI Adult 3.57E-11 7.04E-11 3.49E-I l 0.00E+00 5.18E-11 5.11 E-i!. 3.00E-16 Teen 3.82E-11 7.34E-11 3.67E-11 0.00E+00 5.42E-11 6.30E-12 3.33E-14 Child 4.84E-11 6.73E-11 4.27E-11 0.00E+ 00 4.73E-11 5.10E-12 3.10E-11 Infant 1.63E-32 2.65E-32 1.28E-32 0.00E + 00 1.32E-32 2.06E-33 4.23E-32 l

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

Ba-139 Bone Liver T. Body' Thyroid Kidney Lungs GI-LLI Adult 1.67E-09 1,g9-12 4.93E-11 0.00E + 00 1.12E-12 6.77E-13 2.97E-09 Teen 1.83E49 1.2 5 12 5.50E-11 0.00E +00 1.21E-12 8.87E-13 1.63E-08 V(~'% Child 2.35E-09 1.25E-12 6.84E-11 0.00E+00 1.09E-12 7.37E-13 1.36E-07 Infant 3.30E-16 2.19E-19 9.55E-18 0.00E+ 00 1.31E-19 1.33E-19 2.09E-14 Dose factor - liquid release pathway (mrem /Ci released)

Ha-140 Bone Liver T. Body 'Ihyroid Kidney Lungs GI-LLI Adult 5.34E-04 6.71 E-07 3.51 E-05 0.00E+00 2.28E-07 3,84E-07 1.10E-03 Teen 5.41 E-04 6.63E-07 3.56E-05 0.00E + 00 2.25E-07 4.46E-07 8.35E-04 Child 1.32E-03 1.16E-06 7.72E-05 0.00E + 00 3.76E47 6.89E-07 6.69E-04 Infant 1.52E-03 1.52E-06 7.84E-05 0.00E + 00 3.61E-07 9.34E-07 3.74E 04 O

Page 51 of 136

i POINT BEACH NUCLEAR PLANT ODCM OFF5ITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 r)

Table 5.1-1 (continued)

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

Ba-141 Bone Liver T. Body - Thyroid ' Kidney Lungs GI-Lil -

Adult 4.57E-19 3.45E-22 1.63E-20 0.00E + 00 3.21E-22 1.%E-22 2.15E-28 Teen 4.96E-19 3.70E-22 2.14E-20 0.00E+00 3.44E-22 2.53E-22 1.06E-24 Child - 6.37E-19 3.57E-22 l 2.18E-20 0.00E+00 3.09E-22 ,j 2.10E-21 3.63E-19 Infant 1.58E-53 1.08E-56 4.99E-55 0.00E+00 6.52E-57 6.60E-57 1.93E-52 Dose factor - liquid release pathway (mrem /Ci released)

La-140 Bone Liver T. Body 'Ihyroid Kidney- Lungs G1-LLI Adult 3.66E-08 1.84 E-08 1.03 E-07 0.00E + 00 0.00E +00 0.00E+00 1.35E-03 Teen 3.68E-08 1.81 E-08 5.51E-07 0.00E+ 00 0.00E+ 00 0.00E+ 00 1.04E-03 i%

() Child 8.21 E-08 2.875-08 1.24E-07 0.00E+ 00 0.00E+00 0.00E+00 8.00E-04 Infant 8.56E-08 3.38E-08 8.69E-09 0.00E+00 0.00E+00 0.00E + 00 3.97E-04 Dose factor - liquid release pathway (mrem /Ci released)12-142 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 2.92E-11 1.33E-11 4.94E-11 0.00E +00 0.00E + 00 0.00E + 00 9.71E-08 Teen 3.12E-I l 1.38E-11 2.61E-10 0.00E + 00 0.00E+00 0.00E+ 00 4.21E-07 Child 3.93 E-11 1.25E-11 5.77E-11 0.00E + 00 0.00E + 00 0.00E + 00 2.48E-06 Infant 7.74E-18 2.84E-18 6.81E-19 0.00E+ 00 0.00E+ 00 0.00E + 00 4.83E-13 O

Page 52 of 136

r POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 (3

V Table 5.1-1 (continued)

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

Ce-141 Bone - Liver T. Body Thyroid Kidney Lungs GI-LLI )

Adult 2.05E-07 1.39E-07 2.42E-07 0.00E+00 6.45E-08 0.00E+ 00 5.31 E-04 Teen 2.06E-07 1.37E-07 4.88E-07 0.00E+00 6.47E-08 0.00E+ 00 3.93 E-04 i Child 5.80E-07 2.89E-07 1.42E-07 0.00E+ 00 1.27E-07 0.00E+00 3.61E44 Infant 7.11E-07 4.34E-07 5.11E-08 0.00E+ 00 1.34E-07 0.00E+00 2.24E-04 Dose factor - liquid release pathway (mrem /Ci released)

Ce-143 Bone Liver T. Body  % yroid . Kidney Lungs ~ GI-LL1

- Adult 1.47E-08 1.09E-05 1.78E-08 0.00E+00 4.78E-09 0.00E+00 4.06E-04 ,

Teen 1.49E-08 1.08E-05 9.40E-08 0.00E+00 4.86E-09 0.00E+00 3.26E-04 Child 4.01 E-08 2.17E-05 2.25E-08 0.00E+00 9.12E-09 0.00E +00 3.18E-04 Infant 5.10E-08 3.38E-05 3.86E-09 0.00E+00 9.85E-09 0.00E+00 1.97E-04 Dose factor -liquid release pathway (mrem /Ci released)

Ce-144

. Bone Liver T. Body R yroid Kidney Lungs GI-LLI Adult 1.12E-05 4.67E-06 1.04E-06 0.00E+00 2.77E-06 0.00E+00 3.78E-03 Teen 1.12E-05 4.65E-06 3.03 E-06 0.00E +00 2.78 E-06 0.00E + 00 2.82E-03 Child 3.17E-05 9.92E-06 2.20E-06 0.00E + 00 5.50E-06 0.00E + 00 2.59E-03 Infant 2.80E-05 1.15E-05 1.57E-06 0.00E+00 4.63E46 0.00E+00 1.61E-03 Page 53 of 136

l POINT BEACH NUCLEAR PLANT ODCM l OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 p l

\ Table 5.1-1 (continued)

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

Pr-143 j Bone Liver T. Body Thyroid Kidney Lungs GI-111 '

Adult 5.69E-07 2.28E-07 2.82E-08 0.00E +00 1.32E-07 0.00E+00 2.49E-03 Teen 6.00E-07 2.40E-07 2.99E48 0.00E+ 00 1.39E-07 0.00E+00 1.97E43 Child 1.07E-06 3.21E-07 5.31 E-08 0.00E+00 1.74E-07 0.00E +00 1.15E-03 Infant 6.81 E-07 2.55E-07 3.38E-08 0.00E+00 9.47E-08 0.00E+00 3.60E-04 I

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

1 Pr-144 i i

Bone- Liver T. Body Thyroid Kidney Lungs GI-LLI l l

Adult 3.76E-22 1.56E-22 2.24E-23 0.00E + 00 8.80E-23 0.00E+ 00 5.41 E-29 Teen 4.09E-22 1.67E-22 3.91E-23 0.00E + 00 9.61 E-23 0.00E+00 4.51E-25 Child 5.29E-22 1.64E-22 3.05E-23 0.00E+00 8.66E-23 0.00E + 00 3.52E-19 Q(%

Infart 1.72E-59 6.66E-60 8.67E-61 0.00E+00 2.41 E-60 0.00E + 00 3.10E-55 Dose factor - liquid release pathway (mrem /Ci released) .

I Nd-147 Bone Liver T. Body Thyroid Kidney Lungs GI-LU Adult 3.82E-07 4.42E-07 1.13 E-07 0.00E+00 2.58E-07 0.00E+00 2.12E-03 Teen 4.23 E-07 4.60E-07 5.09E-07 0.00E+00 2.70E-07 0.00E+00 1.66E-03 Child 7.45 E-07 6.03 E-07 1.47E-07 0.00E+ 00 3.31 E-07 0.00E+ 00 9.55E-04 Infant 4.53E-07 4.65E-07 2.85E-08 0.00E+00 1.79E-07 0.00E + 00 2.95E-04 Page 54 of 136

l POINT BEACH NUCLEAR PLANT ODCM l OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 O Table 5.1-1 (continued) :

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

Eu-152 Bone Liver T. Body %yroid Kidney Lungs GI-LLI Adult 1.31 E-05 2.99E-04 1.63 E-04 0.00E+00 1.85E-05 0.00E+00 1.72E-03 Teen 1.21 E-05 2.92E-06 9.00E-04 0.00E+00 1.35E-05 0.00E+ 00 1.07E-03 Child 1.84E-05 3.34E-06 1.91E-04 0.00E+00 1.41E-05 0.00E + 00 5.49E-04 Infant - 6.27E46 1.67E-06 1.40E-06 0.00E+00 4.67E-06 0.00E + 00 1.48E-04 Dose factor - liquid release pathway (mrem /Ci released) i i

W-187 Bone Liver T. Body Thyroid - Kidney Lungs GI-LLI Adult 1.52E-04 1.27E44 4.45E-05 0.00E+00 0.00E +00 0.00E+00 4.17E-02 Teen- 1.65E-04 1.34E-04 4.71E-05 0.00E +00 0.00E +00 0.00E+00 3.63 E-02 Child 2.09E-04 1.24E-04 5.57E-05 0.00E +00 0.00E+ 00 0.00E+00 1.74E-02 Infant ' 2.25E-06 1.57E-06 5.41E-07 0.00E + 00 0.00E + 00 0.00E+00 9.21 E-05 Dose factor - liquid release pathway (mrem /Ci released)  !

l Np-239 Bone liver T. Body n yroid - Kidney Lungs GI LLI Adult 3.15E-08 3.09E-09 2.30E-08 0.00E+00 9.65E-09 0.00E+00 6.34E-04 Teen 3.42E-08 3.22E-09 1.21 E-07 0.00E + 00 1.01E-08 0.00E + 00 5.19E-04 Child 6.77E-08 4.86E-09 2.83E-08 0.00E + 00 1.41 E-08 0.00E + 00 3.60E-04 Infant 5.72E-08 5.12E-09 2.89E-09 0.00E+ 00 1.02E-08 0.00E + 00 1.48E-04 IO

\J Page 55 of 136

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 i O

Table 5.1-1 (continued)

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

1 U-235 Bone Uver T. Body Thyroid Kidney Lungs . GI-LLI Adult 3.05 E-02 0.00E + 00 1.89E-03 0.00E + 00 7.13E-03 0.00E+00 2.98E-03 Teen 3.17E-02 0.00E+00 2.13E-03 0.00E+00 7.43 E-03 0.00E+00 2.30E-03 Child 6.92E42 0.00E+00 4.23 E-03 0.00E+ 00 1.14E-02 0.00E + 00 1.63E-03 Infant 4.42E-02 0.00E+00 3.37E-03 0.00E+00 9.40E-03 0.00E+ 00 7.67 E-04 4

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

U-238 Bone Liver T. Body' ' Thyroid ~ Kidney Lungs- GI-LLI l l

Adult 2.92E-02 0.00E+00 1.73 E-03 0.00E+ 00 6.67E-03 0.00E+ 00 2.10E-03 '

Teen 3.03E-02 0.00E+00 1.81 E-03 0.00E + 00 6.%E-03 0.00E+00 1.62E-03 i O

V Child 6.62E-02 0.00E +00 3.93 E-03 0.00E +00 1.06E-02 0.00E+ 00 1.15E-03  ;

Infant 4.23 E-02 0.00E+00 3.15E-03 0.00E + 00 8.78E-03 0.00E+00 5.41 E-04 Dose factor - liquid release pathway (mrem /Ci released)

Am-241 Bone Liver T. Body H yroid Kidney Lungs- GI-LLI l Adult 5.25 E-02 1.85E-02 3.47E-03 0.00E+00 2.61 E-02 0.00E+ 00 4.75E-03 Teen 4.10E-02 1.56E-02 2.77E-03 0.00E+00 2.05E-02 0.00E+00 3.74E-03 Child 4.10E-02 1.83 E-02 2.93E-03 0.00E+00 1.79E-02 0.00E + 00 2.19E-03 Infant 1.42E-02 6.68E-03 1.01E-03 0.00E+00 6.10E-03 0.00E + 00 7.17E-04 O

V Page 56 of 136

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR ,

Revision 10 DRAFT j OIFSITE DOSE CALCULATION MANUAL January 26,1996 5.1.2 Atmospheric Release Mode: Radiciodine, Tritium, and Particulates 4

The dose calculations for demonstration of compliance with the 10 CFR 50, Appendix I dose limits for radiciodines, tritium, and particulate radionuclides released to the atmosphere will be done in the ,

manner similar to the liquid release dose calculations described in l Section 5.1.1. The total dose is compared to the corresponding atmospheric release mode Appendix I dose limit for the organ in question.

i The doses are calculated using the following formula:

API = E Dose om; = E (TDF,om; X C;) s Kom mrem Where API = the Appendix I dose for compliance evaluations in mrem Dose omi = the dose to the specific age group (a) and organ (o) via release mode (m) from radionuclide (i)

TDF,om; = 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 Ci =

curies of radionuclide (i) released K om = 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 TDF,omi values are given in Appendix C.

It is mcognized 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 cormctions 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.

O O

Page 57 of 136

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 10 V 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 (mrem /Ci released)

H-3 Bone' Liver T. Body ' Thyroid Kidney ' Lungs GI-L1l Skin Adult. 0.00E + 00 9.78E-05 9.78E-05 9.78E-05 9.78E-05 9.78E-05 9.78E-05 0.00E+ 00 Teen 0.00E+ 00 1.03 E-04 1.03 E-04 1.03 E-04 1.03 E-04 1.03 E-04 1.03 E-04 0.00E+ 00 Child 0.00E + 00 1.32E-04 1.32E-04 1.32E-04 1.32E-04 1.32E-04 1.32E-04 0.00E + 00 Infant 0.00E +00 2.03 E-05 2.03 E-05 2.03 E-05 2.03 E-05 2.03E-05 2.03 E-05 0.00E +00 1

lbse factor - airborne release pathway (mrem /Ci released) p

,] F-18 Bone Liver- T. Body Thyroid Kidney Lungs GI-Lil Skin Adult 1.12E-04 0.00E + 00 9.61E-04 0.00E +00 0.00E+00 0.00E+ 00 2.19E-06 2.23E-03 Teen 1.55E-04 0.00E + 00 9.65E-04 0.00E+00 0.00E+00 0.00E+ 00 9.23 E-06 2.23E-03 Child 2.06E-04 0.00E+00 9.69E-04 0.00E+00 0.00E +00 0.00E+00 3.70E-05 2.23E-03 Infant 1.63E-04 0.00E+ 00 9.62E-04 0.00E + 00 0.00E + 00 0.00E + 00 2.53E-05 2.23 E-03 Dose factor - airborne release pathway (mrem /Ci released)

Na-22 Bone Liver T. Body Thyroid Kidney Lungs GI-Lil Skin Adult 4.83 E + 00 4.83 E + 00 2.89E + 01 4.83 E + 00 4.83 E + 00 4.83 E + 00 4.83 E + 00 3.79E+01 Teen 7.41 E + 00 7.41E + 00 3.15E+01 7.41 E + 00 7.41E+ 00 7.41 E+ 00 7.41E + 00 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 1.81 E+ 01 1.81 E+01 4.21E+01 1.81E+01 1.81 E + 01 1.81 E+ 01 1.81 E + 01 3.79E+01 Page 58 of 136

a POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR i Revision 10 DRAFT l OFFSITE DOSE CALCULATION MANUAL January 26,1996 l Table 5.1-2 (continued)

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

Na-24 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin -

Adult 9.48E-04 9.48E-04 1.77E-02 9.48E-04 9.48 E-04 9.48E-04 9.48 E-04 7.64E-02 3

Teen 1.36E-03 1.36E-03 1.81 E-02 1.36E-03 1.36E-03 1.36E43 1.36E-03 7.64E-02 Child 2.37E-03 2.37E-03 1.9:E-02 2.37E-03 2.37E-03 2.37E-03 2.37E-03 7.64E-02 Infant 3.14E-03 3.14E-03 1.99E42 3.14E-03 3.14E-03 3.14E-03 3.14E-03 7.64E-02 Dose factor - airborne release pathway (mrem /Ci released)

Sc-46 Bone Liver- T. Body Thyroid Kidney- Lungs GI-LLI Skin Adult 1.33E-02 2.59E-02 2.00E+00 0.00E+00 2.42E-02 0.00E+ 00 2.40E+00 2.69E+00 Teen 1.75E-02 3.41E42 2.00E + 00 0.00E+00 3.26E-02 0.00E + 00 2.09E + 00 2.69E+00 Child 2.23E-02 3.05E-02 2.00E+ 00 0.00E+00 2.70E-02 0.00E+00 1.32E + 00 2.69E+00 Infant 1.56E-02 2.25E-02 2.00E+ 00 0.00E +00 1.48E-02 0.00E+00 1.35E-03 2.69E + 00 Dose factor - airbome release pathway (mrem /Ci released)

Mn-54 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult - 0.00E+00 2.32E-01 1.99E+00 0.00E + 00 6.89E-02 4.15E-02 7.08E-01 2.28E+00 Teen 0.00E + 00 3.34E-01 2.01E+00 0.00E + 00 9.95E-02 5.89E-02 6.83E-01 2.28E+00 Child 0.00E + 00 4.86E-01 2.07E+00 0.00E + 00 1.36E-01 4.68E-02 4.08E-01 2.28E+00 Infant 0.00E+00 2.03 E-02 1.95E + 00 0.00E + 00 4.47E-03 2.97E-02 7.38E-03 2.28E+ 00 0

Page 59 of 136

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 O

V Table 5.1-2 (continued)

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

Cr-51 -

1 Bone Liver T. Body Thyroid' Kidney Lungs GI-LLI Skin Adult 0.00E+00 0.00E+00 6.59E-03 2.68E-05 9.86E-06 4.83E-04 1.07E-02 7.73 E-03 Teen 0.00E +00 0.00E + 00 6.60E-03 3.39E-05 1.34E-05 7.03 E-04 9.66E-03 7.73 E-03 i

Child 0.00E+ 00 0.00E + 00 6.66E-03 6.30E-05 1.72E-05 6.14E-04 5.81E-03 7.73E-03  !

Infant 0.00E+ 00 0.00E + 00 6.58E-03 2.42E-05 5.31 E-06 4.25E-04 1.02E-03 7.73 E-03 Dose factor - airbome release pathway (mrem /Ci released)

Mn-56 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 0.00E +00 4.81E48 1.27E-03 0.00E+00 5.31E-08 2.80E-04 6.01E-04 1.50E-03 Teen 0.00E+00 6.05E-08 1.27E-03 0.00E+00 6.61 E-08 4.51E-04 1.70E-03 1.50E-03 I Child 0.00E+ 00 6.26E-08 1.27E-03 0.00E + 00 6.58E-08 3.90E-04 3.66E-03 1.50E-03 Infant 0.00E+00 4.57E-08 1.27E-03 0.00E+ 00 3.27E-08 3.72E-04 2.13 E-03 1.50E-03 Dose factor - airborne release pathway (mrem /Ci released)

Fe-55 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 3.20E41 2.21 E-01 5.15E-02 0.00E + 00 0.00E+00 1.25E-01 1.27E-01 0.00E + 00 Teen 3.80E-01 2.70E-01 6.29E-02 0.00E+00 0.00E+00 1.74E-01 1.17E-01 0.00E +00 Child 8.65E41 4.59E-01 1.42E-01 0.00E + 00 0.00E+ 00 2.62E-01 8.49E-02 0.00E+00 Infant 7.36E-02 4.75E-02 1.27E-02 0.00E + 00 0.00E+00 2.56E-02 6.02E-03 0.00E + 00 Page 60 of 136

POINT BEACH NUCLEAR PLANT ODCM l OFFSITE DOSE CALCULATION MANUAL l MAJOR l Revision 10 DRAFT l

OFFSITE DOSE CALCULATION MANUAL January 26,1996

,r~,

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

Fe-59 Bone Liver T. Body Thyroid - ' Kidney Lungs GI-LLI Skiu Adult 2.01 E-01 4.73 E-01 5.65E-01 0.00E+00 0.00E+00 1.62E-01 1.58 E+ 00 4.50E-01 Teen 2.25E-01 5.24E-01 5.86E-01 0.00E+00 0.00E+ 00 2.10E-01 1.24E +00 4.50E-01 Child 4.62 E-01 7.48E-01 7.56E-01 0.00E+00 0.00E+00 2.54E-01 7.80E-01 4.50E-01 Infant 6.14E-02 1.07E-01 4.26E-01 0.00E+00 0.00E + 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 I Adult 0.00E+00 1.17E-02 4.93E-01 0.00E+ 00 0.00E + 00 1.10E-02 2.97E-01 6.13 E-01 Teen 0.00E + 00 1.59E-02 5.00E-01 0.00E + 00 0.00E + 00 1.74E-02 2.97E-01 6.13E-01 O

V Child 0.00E + 00 2.57E-02 5.26E-01 0.00E +00 0.00E+00 1.50E42 2.11E-01 6.13E-01  ;

Infant 0.00E + 00 4.38E-03 4.81E-01 0.00E+00 0.00E +00 1.13 E-02 1.50E-02 6.13E41 Dose factor - airborne release pathway (mrem /Ci released) l J

Co-58 Bone 1.iver T. Body Thyroid Kidney Lungs GI-LLI Skin

]

Adult - 0.00E + 00 3.14 E-02 6.02E-01 0.00E + 00 0.00E + 00 2.75E-02 6.38 E-01 6.23 E-01 Teen 0.00E + 00 4.00E42 6.24E-01 0.00E+00 0.00E + 00 3.99E-02 5.53E-01 6.23E-01 Child 0.00E + 00 5.73 E-02 7.07E-01 0.00E +00 0.00E+00 3.28E-02 3.35E-01 6.23E-01 Infant 0.00E + 00 9.90E-03 5.57E-01 0.00E+00 0.00E+00 2.31E-02 2.49E-02 6.23E-01 l

1

\

O Page 61 of 136

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 G

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

Co-60 1 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 0.00E + 00 1.68E-01 3.06E+01 0.00E + 00 0.00E+ 00 1.77E41 3.16E+00 3.56E+01 Teen 0.00E +00 2.23E41 3.07E+01 0.00E+ 00 0.00E+ 00 2.59E-01 2.90E+00 3.56E+01 Child 0.00E+00 3.28E-01 3.12E+ 01 0.00E + 00 0.00E +00 2.10E-01 1.82E+00 3.56E+01 Infant 0.00E + 00 5.86 E-02 3.04E + 01 0.00E+00 0.00E+00 1.34E-01 1.40E41 3.56E+01 Dose factor - airborne release pathway (mrem /Ci released)

Ni-63 Bone Liver T. Body Thyroid Kidney Lungs- GI-LLI ' Skin Adult 2.39E+01 1.65E+00 8.00E-01 0.00E + 00 0.00E + 00 5.29E-03 3.45E-01 0.00E+00 Teen 2.93 E+ 01 2.07E+ 00 9.92E-01 0.00E+00 0.00E+00 9.11E-03 3.29E-01 0.00E+00 Child 6.73E+01 3.60E+00 2.29E+00 0.00E+00 0.00E + 00 8.16E-03 2.43E-01 0.00E+00 Infant 2. l l E + 01 1.30E+00 7.32E-01 0.00E+00 0.00E + 00 6.19E-03 6.49E-02 0.00E+00 Dose factor - airborne release pathway (mrem /Ci released)

Ni-65 Bone Liver T. Body Thyroid - Kidney Lungs GI-LLI Skin Adult 8.95 E-08 1.19E-08 4.17E-04 0.00E +00 0.00E +00 1.66E-04 3.66E-04 4.85E-04 Teen 1.06E-07 1.39E-08 4.17E-04 0.00E + 00 0.00E + 00 2.78E-04 1.09E-03 4.85E-04 Child 1.64E-07 1.58E-08 4.17E-04 0.00E + 00 0.00E+ 00 2.43 E-04 2.49E-03 4.85E-04 Infant 7.17E-08 8.51 E-09 4.17E-04 0.00E+00 0.00E+00 2.41E-04 1.49E-03 4.85E-04 Page 62 of 136

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T V Table 5.1-2 (continued) .

l l

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

Cu-64 Bone Liver T. Body Thyroid Kidney- Lungs' GI-111 Skin Adult 0.00E + 00 1.12E-05 8.57E-04 0.00E+00 2.82E-05 2.01E-04 2.40E-03 9.65E-04

, Teen 0.00E+00 1.40E-05 8.58 E-04 0.00E+00 3.54E-05 3.30E-04 2.90E-03 9.65E-04 Child 0.00E+ 00 2.19E-05 8.65E-04 0.00E + 00 5.28E-05 2.84E-04 2.11E-03 9.65E-04 l Infant 0.00E + 00 3.42E-05 8.68E-04 0.00E+00 5.79E-05 2.76E-04 1.15E-03 9.65 E-04 Dose factor - airbome release pathway (mrem /Ci released)

Zn-65

)

Bone Liver- T. Body Thyroid Kidney Lungs- GI-Lil Skin

, Adult 1.21 E+ 00 3.85E+00 2.79E + 00 0.00E + 00 2.57E+00 2.56E-02 2.42E + 00 1.21E +00 l Teen 1.63E+00 5.67E+ 00 3.69E+00 0.00E+00 3.63E+00 3.68E-02 2.40E+00 1.21E + 00

(,

y) Child 3.12E+00 8.31E + 00 6.22E+00 0.00E+00 5.24E+00 2.95E-02 1.46E +00 1.21E+00 Infant 2.95E+00 1.01 E + 01 5.71 E +00 0.00E+00 4.91E+00 1.92E-02 8.54E+00 1.21 E + 00 Dose factor - airborne release pathway (mrem /Ci released)

Zn-69 Bone Liver T. Body Thyroid Kidney - Lungs GI-Lil Skin - i l

Adult 3.01E-06 5.76E-06 4.01 E-07 0.00E+00 3.74E-06 2.73E 05 1.35E-06 0.00E+ 00 Teen 4.64E-06 8.83 E-06 6.18E-07 0.00E+ 00 5.77E-06 4.70E-05 2.47E-05 0.00E + 00 Child. 1.08E-05 1.56E-05 1.45E-06 0.00E + 00 9.49E-06 4.22E-05 1.29E-03 0.00E + 00 Infant 1.93 E-05 3.48E-05 2.59E-06 0.00E + 00 1.45E-05 4.36E-05 3.23E-03 0.00E+ 00 p.

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t V Table 5.1-2 (continued)

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

Zn-69m I Liver T. Body Thyroid . Kidney Lungs GI-LLI Skin Bone Adult 4.99E-05 1.20E-04 3.07E-03 0.00E+00 7.26E-05 5.65E-04 1.13E-02 5.74E-03 Teen 7.60E-05 1.79E-04 3.07E-03 0.00E+00 1.09E-04 9.30E-04 1.49E-02 5.74E-03 Child 1.76E-04 3.00E-04 3.09E-03 0.00E+00 1.74E-04 8.08E-04 1.27E-02 5.74E-03 I Infant 3. l l E-04 6.35E-04 3.12E-03 0.00E+00 . 2.57E-04 7.93 E-04 1.00E-02 5.74E43 Dose factor - airborne release pathway (mrem /Ci released)

Br-82 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 0.00E+ 00 0.00E +00 5.44E-02 0.00E + 00 0.00E+00 0.00E+00 8.47E-03 6.41 E-02 Teen 0.00E+ 00 0.00E+00 5.89E-02 0.00E+ 00 0.00E +00 0.00E + 00 0.00E+00 6.41E-02 rm h Child 0.00E + 00 0.00E+00 7.04E-02 0.00E + 00 0.00E+ 00 0.00E + 00 0.00E + 00 6.41E42 Infant 0.00E + 00 0.00E + 00 S.32E-02 0.00E + 00 0.00E+00 0.00E + 00 0.00E + 00 6.41 E-02 Dose factor - airborne release pathway (mrem /Ci released)

Br-83 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 0.00E +00 0.00E + 00 1.65 E-05 0.00E + 00 0.00E+ 00 0.00E + 00 6.89E-06 2.84E-03 Teen 0.00E+ 00 0.00E + 00 1.%E-05 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 2.84E-03 l

Child 0.00E + 00 0.00E+ 00 2.34E-05 0.00E + 00 0.00E + 00 0.00E + 00 0.00E + 00 2.84E-03 Infant 0.00E+00 0.00E+00 2.07E-05 0.00E + 00 0.00E+00 0.00E + 00 0.00E + 00 2.84E-03 Page 64 of 136

POINT BEACH NUCLEAR PLANT ODCM I OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 O

(O Table 5.1-2 (continued) 1 i

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

Br-84 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 0.00E +00 0.00E + 00 2.59E42 0.00E+00 0.00E + 00 0.00E+00 1.11 E-09 2.49E-01 Teen 0.00E+00 0.00E+00 2.60E-02 0.00E+ 00 0.00E+00 0.00E+ 00 0.00E+00 2.49E-01 Child 0.00E+ 00 0.00E+00 2.63E-02 0.00E+ 00 0.00E+ 00 0.00E+00 0.00E + 00 2.49E-01 Infant 0.00E+ 00 0.00E + 00 2.66E-02 0.00E+ 00 0.00E +00 0.00E + 00 0.00E+00 2.49E-01 )

l I

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

Br-85 Bone Liver T. Body - H yroid Kidney ' Lungs; 'GI-LLI Skin

_Adah 0.00E+ 00 0.00E+00 4.95E-06 0.00E + 00 0.00E+ 00 0.00E+ 00 0.00E+00 2.63E-04 Teen 0.00E+00 0.00E + 00 7.06E-06 0.00E+ 00 0.00E+00 0.00E+00 0.00E+00 2.63E-04

()

O Child Infant 0.00E+00 0.00E+ 00 0.00E+00 0.00E+ 00 2.02E-05 4.21E 05 0.00E+ 00 0.00E+ 00 0.00E+ 00 0.00E+ 00 0.00E +00 0.00E +00 0.00E+00 0.00E+ 00 2.63 E-04 2.63 E-04 i

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

Rb-86 Bone Liver T. Body n yroid Kidney Lungs GI-Lil Skin Adult 0.00'.I+ 00 8.21 E-01 3.95E-01 0.00E+00 0.00E+ 00 0.00E + 00 1.61E-01 1.44 E-02 Teen 0.00E + 00 1.23 E + 00 5.92E-01 0.00E + 00 0.00E + 00 0.00E+ 00 1.82E-01 1.44E-02 Child 0.00E+00 2.18E+ 00 1.35E+00 0.00E+ 00 0.00E + 00 0.00E + 00 1.40E-01 1.44E-02 Infant J.00E+ 00 4.17E + 00 2.07E+ 00 0.00E+00 0.00E+ 00 0.00E + 00 1.07E-01 1.44 E-02 O

O Page 65 of 136

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 n

Table 5.1-2 (continued)

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

Rb-88 Bone Liver T. Body H yroid Kidney Lungs GI-LLI Skin Adult 0.00E+00 1.15E-05 5.22E45 0.00E+00 0.00E+00 0.00E+00 9.92E-17 5.31E-05 Teen 0.00E + 00 1.62E-05 5.45E-05 0.00E+00 0.00E+00 0.00E+ 00 8.66E-13 5.31E-05 Child 0.00E + 00 1.67E-05 5.73 E-05 0.00E+ 00 0.00E +00 0.00E + 00 5.12E-07 5.31 E-05 Infant 0.00E+00 1.65 E-05 5.50E-05 0.00E + 00 0.00E +00 0.00E + 00 1.01 E-05 5.31E-05 Dose factor - airbome release pathway (mrem /Ci released)

Rb-89 Bone Liver T. Body  % yroid' Kidney Lungs GI-LLI Skin Adult . 0.00E + 00 7.60E-06 1.78E-04 0.00E + 00 0.00E+00 0.00E+00 2.75E-19 2.07E-04 Teen 0.00E + 00 1.04E-05 1.80E-04 0.00E+ 00 0.00E+00 0.00E+ 00 1.00E-14 2.07E-04 Child 0.00E+ 00 1.02E-05 1.81E-04 0.00E+ 00 0.00E + 00 0.00E+00 5.61 E-08 ' 2.07E-04 Infant 0.00E +00 9.51 E-06 1.79E-04 0.00E+00 0.00E + 00 0.00E + 00 2.02E-06 2.07E-04 Dose factor - airborne release pathway (mrem /Ci released)

Sr-89 Bone Liver T. Body D yrcid Kidney Lungs GI-LIJ Skin Adult 7.63 E+ 00 0.00E+ 00 2.19E-01 0.00E+00 0.00E+ 00 4.15E-02 1.23 E+ 00 3.53E-05 Teen 1.16E + 01 0.00E+ 00 3.34E-01 0.00E + 00 0.00E+ 00 7.17E-02 1.40E+00 3.53 E-05 Child 2.77E+01 0.00E + 00 7.90E-01 0.00E + 00 0.00E + 00 6.40E-02 1.08E+00 3.53E-05 Infant 3.66E+00 0.00E + 00 1.05 E-01 0.00E + 00 0.00E+ 00 6.02E-02 7.69E 02 3.53E-05 O

Page 66 of 136

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996

'v Table 5.1-2 (continued)

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

Sr-90 Bone Uver T. Body Thyroid ' Kidney- Lungs GI-Lil Skin i Adult 5.10E+02 0.00E+00 1.25E+ 02 0.00E+00 0.00E + 00 2.85 E-01 1.47E+01 0.00E+ 00 Teen 6.33 E + 02 0.00E+00 1.56E+ 02 0.00E+00 0.00E+ 00 4.89E-01 1.77E+ 01 0.00E + 00 Child 1.05E + 03 0.00E+ 00 2.65E+02 0.00E +00 0.00E+00 4.38E-01 1.41 E+ 01 0.00E+ 00 Infant 7.33 E+ 01 0.00E+ 00 1.84E+01 0.00E+ 00 0.00E +00 3.34E-01 9.04E-01 0.00E+ 00 Dose factor - airborne release pathway (mrem /Ci released)

Sr-91 Bone Uver' T. Body Thyroid Kidney Lungs' GI.LLI Skin Adult 2.29E-04 0.00E + 00 3.03E-03 0.00E +00 0.00E+ 00 1.08E-03 6.76E-03 3.53 E-03 Teen 2.20E-04 0.00E+00 3.03 E-03 0.00E +00 0.00E+ 00 1.80E-03 8.68E-03 3.53E-03 l Child 4.09E-04 0.00E+00 3.03 E-03 0.00E + 00 0.00E+ 00 1.58E-03 6.06E-03 3.53E-03 Infant 5.29E-05 0.00E + 00 3.02E-03 0.00E +00 0.00E+00 1.56E-03 2.24E-03 3.53E-03 Il Dose factor - airborne release pathway (mrem /Ci released)

_S -92 Bone Liver T. Body 'Ihyroid Kidney' Lungs GI-LLI Skin Adult - 5.04E-07 0.00E + 00 1.65E-03 0.00E+00 0.00E+00 4.89E-04 1.28E-03 3.15E-03_

Teen 5.66E-07 0.00E+00 1.65E-03 0.00E+00 0.00E+00 8.14E-04 3.54E-03 3.15 E-03 Child 9.08E-07 0.00E + 00 1.65E-03 0.00E+00 0.00E+00 7.12E-04 7.20E-03 3.15E-03 Infant 3.12E-07 0.00E+00 1.65E-03 0.00E+ 00 0.00E + 00 7.06E-04 4.15E-03 3.15E-03 Page 67 of 136

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,m b Table 5.1-2 (continued) 1 Dose factor - airborne release pathway (mrem /Ci released) i 1

Y-90 Bone Liver T. Body - Thyroid Kidney Lungs GI-LLI Skin Adult 7.17E-05 0.00E+00 8.23 E-06 0.00E +00 0.00E+00 5.03E-03 1.19E-01 7.45E-06 Teen- 9.77E-05 0.00E+ 00 8.93E-06 0.00E + 00 0.00E+00 8.69E-03 9.20E-02 7.45E-06 Child 1.39E-04 0.00E+ 00 1.00E-05 0.00E+00 0.00E+00 7.76E-03 5.63E-02 7.45E-06 Infant 9.77E-05 0.00E + 00 8.93E-06 0.00E+00 0.00E+00 7.98E-03 3.26E-03 7.45E-06 Dose factor - airborne release pathway (mrem /Ci released)

Y-91 Bone ~ Liver T. Body - ' Thyroid - Kidney Lungs GI-LLI - Skin :

Adult 1.78E-02 0.00E+00 1.98E-03 0.00E+00 0.00E + 00 5.06E-02 2.26E+00 1.70E-03 j Teen 2.55E-02 0.00E+00 2.19E-03 0.00E + 00 0.00E+ 00 8.71E-02 2.44E+ 00 1.70E-03 Child 4.10E-02 0.00E + 00 2.60E-03 0.00E+00 0.00E + 00 7.79E-02 1.86E+00 1.70E-03 Infant 1.75E-02 0.00E+00 1.97E-03 0.00E+00 0.00E+00 7.27E-02 3.72E-03 1.70E-03 1

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

Y-91m Bone Liver T. Body 'Ihyrcid Kidney ' Lungs' GI-LLI Skin )

Adult 3.58E-06 0.00E + 00 2.31 E-04 0.00E + 00 0.00E+ 00 5.70E-05 1.05E-05 4.33E-04 Teen 6.15E-06 0.00E+00 2.31 E-04 0.00E+00 0.00E + 00 9.49E45 2.91E-04 4.33E-04 Child 1.50E-05 0.00E+00 2.31E-04 0.00E+ 00 0.00E+00 8.34E-05 2.94E-02 4.33 E-04 Infant 1.21 E-08 0.00E+00 2.31 E-04 0.00E + 00 0.00E + 00 8.27E-05 6.98E-05 4.33E-04 O

Page 68 of 136

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996

~~\

(d Table 5.1-2 (continued)

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

Y-92 Bone Liver T. Body Thyroid Kidney Lungs- GI-LLI Skin Adult 3.35E-05 0.00E+00 4.38E-04 0.00E + 00 0.00E+ 00 4.65E-04 5.83E-01 2.90E-02 l Teen 5.80E-05 0.00E + 00 4.39E-04 0.00E + 00 0.00E+ 00 7.95E-04 1.58E + 00 2.90E-02 Child 1.42E44 0.00E+ 00 4.41 E-04 0.00E+00 0.00E+ 00 7.09E-04 4.09E+00 2.90E-02 1 Infant 4.86E-07 0.00E + 00 4.37E-04 0.00E + 00 0.00E + 00 7.27E-04 3.76E-03 2.90E-02 Dose factor - airborne release pathway (mrem /Ci released)

Y-93 Bone Liver T. Body Thyroid Kidney ' Lungs GI-LLI - ' Skin Adult 1.08E-04 0.00E + 00 4.43 E-04 0.00E + 00 0.00E + 00 1.44E-03 3.35E+00 6.58E-02 Teen 1.86E-04 0.00E+00 4.45E-04 0.00E+ 00 0.00E +00 2.47E-03 5.59E+00 6.58E-02 Child 4.53E44 0.00E+ 00 4.52E-04 0.00E+00 0.00E +00 2.21E 03 6.69E+ 00 6.58E-02 l

Infant 4.45E-06 0.00E+00 4.40E-04 0.00E+00 0.00E+ 00 2.27E-03 4.95E-03 6.58E-02 l

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

Zr-95 Bone liver T. Body 'Ihyroid - Kidney Lungs GI-LLI Skin Adult 4.79E-03 1.54E-03 3.45E-01 0.00E+00 2.42E-03 5.25E-02 1.64E+ 00 3.98 E-01 Teen 6.16E-03 1.94E-03 3.45E-01 0.00E + 00 2.85E-03 7.98 E-02 1.35E +00 3.98E-01 Child 9.47E-03 2.08E-03 3.45E-01 0.00E + 00 2.97E-03 6.62E-02 8.81E-01 3.98E-01 Infant 3.43E-03 8.27E-04 3.44E-01 0.00E+ 00 9.23 E-04 5.19E-02 9.12E-04 3.98E-01 P

d Page 69 of 136

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 O Table 5.1-2 (continued)

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

Zr-97 Bone -Liver T. Body H yroid Kidney ' Lungs GI-LLI Skin Adult 3.12E-06 6.31E-07 4.16E-03 0.00E+ 00 9.56E-07 2.34E-03 3.09E-02 4.84E-03 Teen 4.31 E-06 8.52E-07 4.16E-03 0.00E+00 1.29E-06 3.85 E-03 3.09E-02 4.84E-03 Child 5.98E-06 8.66E-07 4.16E-03 0.00E+00 1.24E-06 3.36E-03 1.95E-02 4.84E-03 Infant 4.45E-06 7.60E-07 4.16E-03 0.00E +00 7.69E-07 3.27E-03 4.16E-03 4.84E-03 Dose factor - airborne release pathway (mrem /Ci released)

Nb-95 Bone- Liver T. Body - ' Thyroid Kidney Lungs GI-LLI Skin Adult 1.39E-03 7.75 E-04 1.92E-01 0.00E+00 7.67E-04 1.50E42 3.30E+00 2.26E-01 Teen 1.39E-03 7.72E-04 1.92E-01 0.00E+ 00 7.48E-04 2.23 E-02 1.99E +00 2.26E-01 Child 2.22E-03 8.65E-04 1.93 E-01 0.00E+00 8.13 E-04 1.82E-02 1.10E+ 00 2.26E-01 Infant 6.08E-04 2.49E-04 1.92E-01 0.00E+ 00 1.82E-04 1.42E-02 4.99E-02 2.26E-01 Dose factor - airborne release pathway (mrem /Ci released)

Nb-97 Bone- Liver T. Body  % yroid Kidney Lungs GI-LLI Skin Adult 2.05 E-06 5.17E-07 4.17E-04 0.00E + 00 6.03 E-07 7.12E-05 1.91 E-03 3.20E-03 Teen 3.50E-06 8.68 E-07 4.17E-04 0.00E+ 00 1.02E-06 1.17E-04 2.07E-02 3.20E-03 Child 8.49E-06 1.53E-06 4.17E44 0.00E+00 1.70E-06 1.01E44 4.73E-01 3.20E-03 Infant . 1.0l E-08 2.16E-09 4.17E-04 0.00E+ 00 1.69E-09 9.84E-05 7.98E-04 3.20E-03 Page 70 of 136

1 1

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 (3

V Table 5.1-2 (continued)

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

Mo-99 Bone Liver T. Body 'Ihyroid - Kidney ' Lungs GI-LLI Skin Adult 0.00E + 00 9.10E-03 7.34E-03 0.00E + 00 2.06E-02 2.71 E-03 2.85E-02 6.50E-03 I

Teen 0.00E + 00 1.24E-02 7.97E-03 0.00E+00 2. 84E-02 4.56E-03 3.02E-02 6.50E-03 l Child ' O.00E+00 2.06E-02 1.07E-02 0.00E + 00 4.41E-02 4.02E-03 2.08E-02 6.50E-03 Infant 0.00E+ 00 3.82E-02 1.31 E-02 0.00E+00 5.70E-02 4.00E-03 1.40E-02 6.50E-03 l l

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

Tc-99m Bone Liver T. Body Thyroid -Kidney Lungs GI-LLI Skin Adult 2.92E-09 8.24E-09 2.59E-04 0.00E + 00 1.25E-07 2.27E-05 1.28E-04 2.%E-04 i Teen 3.11 E-09 8.68E-09 2.59E-04 0.00E + 00 1.29E-07 3.42E-05 1.87E-04 2.%E-04 Child 5.95E-09 1.17E-08 2.59E-04 0.00E+00 1.69E-07 2.82E-05 1.49E-04 2.96E-04 Infant 5.14E-09 1.06E-08 2.59E-04 0.00E + 00 1.14E-07 2.41E-05 6.33E-05 2.%E-04 l

1 Dose factor - airbome 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 0.00E+00 3.01 E-04 2.04E-05 5.06E-17 5.80E-04 Teen 1.99E-05 2.83E-05 3.23 E-04 0.00E + 00 5.12E-04 3.71E-05 4.87E-12 5.80E-04 Child 4.89E-05 5.12E-05 6.93 E-04 0.00E + 00 8.72E-04 4.44E-05 1.63E-04 5.80E-04 Infant 1.93 E-12 2.44E-12 4.44E-05 0.00E + 00 2.90E-11 1.73 E-05 2.50E-05 5.80E-04 O

y Page 71 of 136

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 Table 5.1-2 (continued)

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

Ru-103 Bone Liver T. Body Thyroid Kidney Lungs GI-111 - Skin Adult 4.36E-02 0.00E+00 1.71E-01 0.00E+00 1.66E-01 1.50E-02 5.08E+00 1.77E-01 Teen 3.76E-02 0.00E+ 00 1.68E-01 0.00E+00 1.33E-01 2.32E42 3.14E + 00 1.77E-01 Child 7.01E-02 0.00E+00 1.79E-01 0.00E+00 1.77E-01 1.97E-02 1.81E+00 1.77E-01 Infant 6.20E-05 0.00E+00 1.52E-01 0.00E+ 00 1.30E-04 1.64E-02 5.05E-04 1.77E-01 Dose factor - airborne release pathway (mrem /Ci released)

Ru-105 Bone Liver T. Body Thyroid Kidney' Lungs GI-Ill Skin Adult 6.19E-04 0.00E+00 2.07E-03 0.00E+ 00 7.99E-03 3.25E-04 3.80E-01 1.02E-02 I Teen 1.06E-03 0.00E+00 2.23 E-03 0.00E+00 1.34E-02 5.39E-04 8.59E-01 1.02E-02 Child 2.59E-03 0.00E +00 2.76E-03 0.00E+00 2.28E-02 4.72E-04 1.69E+00 1.02E-02 Infant 3.63E-08 0.00E +00 1.82E-03 0.00E+00 2.67E-08 4.65E-04 1.44 E-03 1.02E-02 Dose factor - airborne release pathway (mrem /Ci released)

Ru-106 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 1.65E +00 0.00E+00 8.01 E-01 0.00E+00 3.18 E+ 00 2.78E-01 1.06E + 02 7.11E-01 ,

I' Teen 1.49E+00 0.00E + 00 7.81E-01 0.00E + 00 2.88E+00 4.77E-01 7.16 E +01 7.11E-01 Child 2.93 E + 00 0.00E + 00 9.58E-01 0.00E+00 3.%E + 00 4.25E-01 4.55E+01 7.11E-01 Infant . 2.67E-03 0.00E + 00 5.93E-01 0.00E + 00 3.28E-03 3.43E-01 5.60E-03 7.11 E-01 I

O l V  :

i Page 72 of 136  !

l POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR l Revision 10 DRAFT l OFFSITE DOSE CALCULATION MANUAL January 26,1996 O

O Table 5.1-2 (continued)

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

Rh-105 Bone ~ ' Liver T. Body Thyroid -Kidney Lungs GI-LLI Skin Adult - 4.81 E-02 3.52E-02 2.47E 02 0.00E+ 00 1.50E-01 5.72E-04 5.61E+ 00 7.74E-03 Teen 8.33E-02 6.02E-02 4.10E-02 0.00E +00 2.56 E-01 9.71 E-04 7.66E+00 7.74E-03 Child 2.04E-01 1.10E-01 9.53E-02 0.00E + 00 4.37E-01 8.59E-04 6.80E+00 7.74E-03 Infant 7.15E-04 4.68E-04 1.83E-03 0.00E + 00 1.30E-03 8.64E-04 1.22E-02 7.74E-03 Dose factor - airborne release pathway (mrem /Ci released)

Ag-110m Bone Liver- T. Body Thyroid Kidney : Lungs GI-LLI Skin Adult 4.10E-02 3.80E-02 4.85E+00 0.00E+00 7.47E 02 1.37E-01 1.54E+01 5.63E+00 Teen 6.28E-02 5.94E-02 4.86E+00 0.00E + 00 1.13 E-01 2.00E-01 1.66E+ 01 5.63 E +00 g

Q Child 1.34E-01 9.04E-02 4.90E + 00 0.00E+00 1.68E-01 1.62E-01 1.07E+ 01 5.63E+00 Infant 1.93E-01 1.41 E-01 4.92E + 00 0.00E +00 2.02E-01 1.09E-01 7.31E+00 5.63E+00 q Dose factor - airborne release pathway (mrem /Ci released)

Sb-124 Bone Liver T. Body Thyroid Kidney- Lungs' GI-LLI Skin Adult 1.44E-01 2.73E-03 1.36E+00 3.50E-04 0.00E+00 1.85E-01 4.09E +00 4.02E + 00 Teen 2.22E-01 4.09E-03 1.39E+00 5.03 E-04 0.00E+00 3.07E-01 4.46E+ 00 4.02E + 00 Child 5. l lE-01 6.63 E-03 1.48E+00 1.13 E-03 0.00E + 00 3.79E-01 3.19E+00 4.02E + 00 Infant 6.723-02 9.90E-04 1.32E+00 1.78E-04 0.00E+00 1.20E-01 2.06E-01 4.02E + 00 0

Page 73 of 136

i l

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT

! OFFSITE DOSE CALCULATION MANUAL January 26,1996 m

Table 5.1-2 (continued)

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

Sb-125 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 1.07E-01 1.20E-03 5.38E+ 00 1.09E-04 0.00E+00 1.33E 01 1.17E+ 00 9.11E+00 Teen 1.61 E-01 1.76E-03 5.39E+00 1.54E-04 0.00E+ 00 2.21E-01 1.24E+ 00 9. l l E+ 00 Child 3.69E-01 2.84E-03 5.43 E + 00 3.42E-04 0.00E + 00 2.73 E-01 8.75E-01 9.11E+ 00 Infant 8.33E-02 8.05E-04 5.37E+ 00 1.04E-04 0.00E+00 9.99E-02 1.09E-01 9.11 E+ 00 l

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+00 3.96E-02 Teen 5.11 E-01 1.84E-01 8.32E-02 1.43 E-01 0.00E+ 00 1.59E-02 1.51 E+ 00 3.%E-02 O

(j Child 1.17E + 00 3.16E-01 1.70E-01 3.27E-01 0.00E + 00 1.42E-02 1.13E+00 3.96E-02 Infant 5.10E-02 1.71E-02 2.18E-02 1.72E-02 0.00E+00 1.33E-02 2.46E-02 3.96E-02 Dose factor - airborne release pathway (mrem /Ci released)

Te-127 l Bone Liver T. Body Thyroid Kidney Lungs GI-Ill Skin Adult 4.47E-06 1.61E-06 5.15E-06 3.31 E-06 1.82E-05 1.93E-04 2.05E-03 4.60E-06 Teen 4.34E46 1.55E-06 5.12E-06 3.00E-06 1.76E-05 3.32E44 2.73E-03 4.60E-06 Child 8.13 E-06 2.20E-06 5.93 E-06 5.63 E-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 l

,O l

Page 74 of 136

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 Table 5.1-2 (continued)

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

Te-127m Bone Uver T. Body Thyroid Kidney Lungs . GI-LU Skin ,

Adult 1.19E+00 4.26E-01 1.54E-01 3.05E-01 4.84 E +00 2.85E-02 4.00E + 00 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 6.16E42 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.%E-01 6.50E-02 3.26E-02 5.66E 02 4.82E-01 3.89E-02 7.%E-02 6.16E-02 i

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

Te-129 Bone Liver T. Body - Thyroid Kidney Lungs GI-LU Skin Adult 1.48E-09 7.10E-10 3.68E-05 1.16E-09 5.56E-09 5.74E-05 4.65E-06 4.36E-05 Teen 2. l l E-09 1.00E-09 3.68E-05 1.54E-09 7.88E-09 9.78E-05 4.79E-05 4.36E-05 Child 2.90E-09 1.04E-09 3.68E-05 2.12E49 7.62E-09 8.71 E-05 7.56E-04 4.36E-05 Infant 2.34E-09 1.03 E-09 3.68E-05 2.00E-09 5.19E-09 8.89E-05 7.81E-04 4.36E-05 l

Dose factor - airborne release pathway (mrem /Ci released) 1 Tt-129m Bone Liver T. Body Thyroid Kidney Lungs ' GI-LU Skin Adult 1.39E + 00 5.19E41 2.35E-01 4.78E-01 5.80E+00 3.44E-02 7.01E + 00 9.07E-01 Teen 1.94E + 00 7.20E-01 3.22E-01 6.26E-01 8.12E+ 00 5.86E-02 7.30E + 00 9.07E41 Child 4.53E+00 1.26E+00 7.18E-01 1.46E+00 1.33E+01 5.23E-02 5.53E+00 9.07E-01 Infant 1.39E-01 4.77E-02 3.66E-02 5.34E-02 3.48E-01 4.98E-02 8.46E-02 9.07E-01 O

Page 75 of 136

POINT BEACH NUCLEAR PLANT ODChi OFFSITE DOSE CALCULATION hIANUAL l AfAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION hfANUAL January 26,1996 d Table 5.1-2 (continued)

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

Te-131 i Bone Liver T. Body Thyroid Kidney Lungs GI-LIJ Skin Adult 1.47E-03 6.14E-04 5.56E-04 1.21 E-03 6.43E-03 4.13E-05 2.09E-04 1.63 E-03 Teen 2.52E-03 1.04E-03 8.80E-04 1.94E-03 1.10E-02 6.93E-05 2.07E-04 1.63E-03 Child 6.19E-03 1.89E-03 1.93E-03 4.73 E-03 1.87E-02 6.09E45 3.25 E-02 1.63E-03 Infant 5.15E-10 2.44E-10 9.27E-05 4.69E-10 1.18E-09 6.11E-05 2.44E-04 1.63 E-03 1

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

Te-131m Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 1.30E-01 6.34E-02 7.45E-02 1.00E-01 6.43E-01 4.32E-03 6.32E+ 00 3.77E-02 ,

l Teen 2.21E-01 1.06E-01 1.10E-01 1.60E-01 1.11 E+ 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 2.18E-02 5.18E-04 1.76E-03 5.90E-03 7.81E-03 3.77E-02 I l

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

Te-132 Bone Liver T. Body Thyroid Kidney Lungs ' GI-Lil Skin Adult 1.92E-01 1.24E-01 1.27E-01 1.37E-01 1.20E+00 8.55E-03 5.89E+00 1.32E-02 l

Teen 3.19E-01 2.02E-01 2.00E-01 2.13 E-01 1.94E + 00 1.33E-02 6.42E+00 1.32E-02 Child 7.61 E-01 3.37E-01 4.17E-01 4.91 E-01 3.13 E+00 1.12E-02 3.39E+00 1.32E-02 Infant 3.94E-03 1.95E-03 1.17E-02 2.88E-03 1.22E-02 1.01 E-02 8.50E-03 1.32E-02 O

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POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MMOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 Table 5.1-2 (continued)

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

I-131 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 7.16E42 1.02E-01 8.29E-02 3.36E+01 1.76E-01 0.00E+00 2.69E-02 2.93E-02 Toen 6.57E-02 9.19E-02 7.35E-02 2.68E+01 1.58E-01 0.00E +00 1.81 E-02 2.93 E-02 Child 1.44 E-01 1.45E-01 1.07E-01 4.80E + 01 2.38E-01 0.00E +00 1.29E-02 2.93 E-02 Infant 2.04E-01 2.40E-01 1.30E-01 7.89E+01 2.805-01 0.00E + 00 8.56E-03 2.93E 02 Dose factor - airborne release pathway (mrem /Ci released) 1-132 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin

, Adult 3.44 E-05 9.67E-05 1.78E-03 3.40E-03 1.54E-04 0.00E+ 00 1.21 E-05 2.06E-03 Teen 4.73 E-05 1.30E-04 1.80E-03 4.49E-03 2.05E-04 0.00E+ 00 3.78E-05 2.06E-03 O

C/ Child 6.28E-05 1.21 E-04 1.80E-03 5.74E-03 1.86E-04 0.00E+ 00 9.50E-05 2.06E-03 Infant - 5.03E-05 1.05E-04 1.79E-03 5.03 E-03 1.17E-04 0.00E+ 00 5.65 E-05 2.06E-03 Dose factor - airborne release pathway (mrem /Ci released) l-133 Bone Liver T. Body - Thyroid Kidney Lungs GI-LLI Skin -

Adult 1.46E-03 2.53E-03 4.21 E-03 3.71 E-01 4.41E-03 0.00E+00 2.14E-03 4.19E-03

. Teen 1.49E-03 2.52E-03 4 21E-03 3.53 E-01 4.42E-03 0.00E+00 1.75E-03 4.19E-03 Child 2.87E-03 3.55E-03 4.78E-03 6.61 E-01 5.91 E-03 0.00E+00 1.35E-03 4.19E-03 Infant 3.16E-03 4.59E-03 4.79E-03 8.37E 01 5.40E-03 0.00E+ 00 7.45E-04 4.19E-03 4

L' Page 77 of 136

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Table 5.1-2 (continued)

Dose factor - airborne release pathway (mrem /Ci released) 1-134 Bone Liver T. Body Thyroid Kidney Lungs GI-111 Skin Adult 1.91 E-05 5.13E-05 6 45E-04 8.85E-04 8.17E-05 0.00E + 00 2.99E-08 7.45E-04 Teen 2.63 E-05 6.88E45 6.52E44 1.17E-03 1.09E-04 0.00E+ 00 6.05E-07 7.45E-04

, Child 3.48E-05 6.41 E-05 6.57E-04 1.50E-03 9.79E-05 0.00E+ 00 2.83 E-05 7.45E-04 Infant 2.73E-05 5.57E-05 6.47E-04 1.32E-03 6.19E-05 0.00E +00 3.83E-05 7.45E-04 Dose factor - airborne release pathway (mrem /Ci released) 1-135 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 9.31E-05 2.43E-04 3.64E43 1.56E-02 3.87E-04 0.00E+00 1.96E-04 4.14E-03 Teen 1.22E-04 3.12E-04 3.66E-03 2.05E 02 4.92E-04 0.00E+00 2.41E-04 4.14E-03 f Child 1.69E 04 3.00E-04 3.69E-03 2.72E-02 4.61 E-04 0.00E+00 1.63E-04 4.14E-03 Infant . 1.23 E-04 2.43 E-04 3.64E-03 2.22E-02 2.70E-04 [ 0.00E+00 6.06E-05 4.14E43 Dose factor - airborne release pathway (mrem /Ci released)  ;

Cs-134 Bone ~ Liver T. Body Thyroid Kidney - Lungs GI-LLI Skin Adult 6.68E+00 1.59E+01 2.26E+01 0.00E +00 5.15 E+ 00 1.71 E+00 2.78E-01 1.12E+ 01 Teen 1.06E+01 2.49E+01 2.12E+01 0.00E+00 7.90E+00 3.02E+ 00 3.09E-01 1.12E + 01 j Child 2.39E+01 3.93E+01 1.79E+01 0.00E+00 1.22E+ 01 4.37E+00 2.12E-01 1.12E + 01 j Infant 1.96E+ 01 3.66E+01 1 33E+01 0.00E+ 00 9.42E+00 3.86E+00 9.94E-02 1.12E+01 l

l 2

O v

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I POINT BEACH NUCLEAR PLANT ODCM l OFFSITE DOSE CALCULATION MANUAL l MAJOR l Revision 10 DRAFT l OFFSITE DOSE CALCULATION MANUAL January 26,1996 O

V Table 5.1-2 (continued)

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

Cs-134m Bone Liver T. Body Thyroid Kidney Ixngs GI-111 Skin Adult 8.36E-04 1.76E-03 9.41 E-04 0.00E + 00 9.54E44 1.50E-04 6.19E-04 6.90E-05 Teen 1.40E-03 2.89E-03 1.53E-03 0.00E+00 1.61E43 2.83E-04 1.92E-03 6.90E-05 Child 3.30E-03 4.89E-03 3.24E-03 0.00E +00 2.58E-03 4.27E-04 6.18E-03 6.90E-05 Infant 5.48E-06 8.72E-06 A.70E-05 0.00E+00 3.53E-06 8.31E-07 4.82E-06 6.90E-05 I

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

Cs-136 Bone Liver T. Body Thyroid Kidney Ixngs GI-LLI Skin l Adult 3.31 E-01 1.31E + 00 1.28E+00 0.00E + 00 7.27E-01 9.97E-02 1.48E-01 4.73 E-01 Teen 5.12E-01 2.02E + 00 1.70E + 00 0.00E+00 1.10E + 00 1.73E-01 1.62E-01 4.73E-01

(

'O) Child 1.14E +00 3.14 E + 00 2.38E + 00 0.00E+00 1.67E + 00 2.49E-01 1.10E-01 4.73 E-01 Infant 3.54E-01 1.04E+ 00 7.33E-01 0.00E +00 4.15E41 8.48E-02 1.58E-02 4.73E-01 l Dose factor - airborne release pathway (mrem /Ci released)

Cs-137 Bone Liver T. Body Thyroid - Kidney Lungs GI-LLI Skin Adult 9.52E+00 1.30E+01 2.30E+01 0.00E+ 00 4.42E+00 1.47E+ 00 2.52E-01 1.69E+01 Teen 1.57E+01 2.09E +01 2.18E+ 01 0.00E+ 00 7.12E+00 2.77E+00 2.97E-01 1.69E+01 Child 3.73E+01 3.57E+ 01 1.97E + 01 0.00E+00 1.16E+01 4.18E+00 2.23E-01 1.69E+01 Infant 2.99E+01 3.49E + 01 1.70E+ 01 0.00E+00 9.38E+ 00 3.80E + 00 1.09E-01 1.69E+01 O

V Page 79 of 136

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 TaNe 5.1-2 (continued)

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

Cs-138 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI - Skin Adult 2.17E-03 4.28 E-03 2.70E-03 0.00E+ 00 3.14E-03 3.10E-04 1.82E-08 4.39E-03 Teen 3.69E-03 7.08E-03 4.13 E-03 0.00E+ 00 5.23E-03 6.08E-04 3.21 E-06 4.39E-03 Child 8.93 E-03 1.24E-02 8.46E-03 0.00E+00 8.73E-03 9.40E-04 5.71E-03 4.39E-03 Infant 1.50E-05 2.32E-05 5.97E-04 0.00E+00 1.22E45 1.94E-06 2.60E-05 4.39E-03 l Dose factor - airborne release pathway (mrem /Ci released)

Ba-139 Bone I iver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 3.7SE-03 2.69E-06 1.38E-04 0.00E + 00 2.52E-06 4.62E-05 6.71E-03 6.76E-03 Teen 6.56E-03 4.61E-06 2.18E-04 0.00E+ 00 4.35E-06 8.00E-05 5.86E-02 6.76E-03 m)

( Child 1.61 E-02 8.60E-06 4.95E-04 0.00E+00 7.51E-06 7.37E-05 9.31E-01 6.76E-03 Infant 1.76E-08 1.17E-11 2.75E-05 0.00E+ 00 7.04 E-12 7.07E-05 6.06E-04 6.76E-03 Dose factor - airborne release pathway (mrem /Ci released)

Ba-140 Bone Liver T. Body Thyroid - Kidney Lungs GI-LLI Skin Adult 1.09E-01 1.37E-04 3.60E-02 0.00E+00 4.67E-05 3.78E-02 2.29E-01 3.29E-02 Teen 1.19E-01 1.46E-04 3.65 E-02 0.00E+00 4.94E-05 6.04E-02 1.88E-01 3.29E-02 Child 2.39E-01 2.10E-04 4.28E-02 0.00E+ 00 6.83E-05 5.18E-02 1.23Eol 3.29E-02 Infant 4.46E-02 4.46E-05 3.llE-02 0.00E+ 00 1.06E-05 4.74E-02 1.17E-02 3.29E-02

'd Page 80 of 136

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996

'O

\

Table 5.1-2 (continued) j l

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

Ba-141 l l

Bone Liver T. Body Thyroid Kidney Lungs GI-LIJ Skin l Adult 1.83E-03 1.39E-06 2.01 E-04 0.00E+ 00 1.29E-06 2.38E-05 8.66E-13 1.55E-03 Teen 3.16E-03 2.36E46 2.45E-04 0.00E +00 2.19E46 4.07E-05 6.75E-09 1.55E-03 1

Child 7.79E-03 4.36E-06 3.92E-04 0.00E+00 3.77E-06 6.03E-05 4.44E-03 1.55E-03 l Infant 1.86 E-09 1.28E-12 1.39E44 0.00E+00 7.72E-13 3.53E-05 5.64E-05 1.55E-03 l

l Dose factor - airborne release pathway (mrem /Ci released)12-140 Bone Liver T. Body 'Ihyroid Kidney Lungs GI-LLI Skin Adult 1.17E-05 5.91 E-06 2.70E-02 0.00E + 00 0.00E + 00 4.04E-03 6 96E-02 3.06E-02 Teen 1.57E-05 7.71 E-06 2.70E-02 0.00E + 00 0.00E +00 6.36E-03 5.51 E-02 3.06E-02 l Child 2.18E-05 7.60E-06 2.70E-02 0.00E + 00 0.00E+00 5.42E-03 3.26E42 3.06E-02 Infant 1.56E-05 6.17E-06 2.70E-02 0.00E+00 0.00E+00 4.98E-03 5.27E-03 3.06E-02 Dose factor - airborne release pathway (mrem /Ci released)

La-142 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 4.98E-06 2.27E-06 1.97E-03 0.00E+00 0.00E+00 7.52E-05 1.65E-02 9.71 E-03 Teen 8.44 E-06 3.75E-06 1.97E-03 0.00E + 00 0.00E+00 1.21 E-04 1.14E-01 9.71 E-03 Child 2.04E-05 6.50E-06 1.97 E-03 0.00E+00 0.00E+00 1.03E-04 1.29E+00 9.71 E-03 Infant 1.22E-08 4.48E-09 1.97E-03 OgE+00 0.00E+00 9.77E-05 7.07E-04 9.71 E-03 l

i l

(h L)

Page 81 of 136 1

POINT BEACH NUCLEAR PLANT ODCM l OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT ,

l OFFSITE DOSE CALCULATION MANUAL January 26,1996 l O 1 U Table 5.1-2 (continued)

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

1 Ce-141 Bone Liver T. Body Thyraid Kidney Lungs GI-LLI Skin Adult 7.38E-04 5.01 E-04 1.93 E-02 0.00E + 00 2.32E-04 1.07E-02 3.84E-01 2.16E-02 Teen 1.05E-03 7.02E-04 1.93 E-02 0.00E+ 00 3.29E-04 1.82E-02 4.02E-01 2.16 E-02 Child 1.65E-03 8.20E-04 1.93 E-02 0.00E+ 00 3.59E-04 1.61 E-02 3.02E-01 2.16E-02 ll !afant 8.32E44 5.00E-04 1.92E-02 0.00E + 00 1.58E-04 1.53 E-02 3.79E-03 2.16E-02 l

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

Ce-143 Bone Liver T. Body Thyroid Kidney Lungs' GI-LLI Skin Adult 6.71 E-05 4.80E-02 4.80E-03 0.00E+ 00 2.18E-05 9.48E-04 1.80E+00 6.60E-02 Teen 1.15E-04 8.10E42 4.81E-03 0.00E+ 00 3.'14E-05 1.55E-03 2.44E+00 6.60E-02 Child 2.77E-04 1.48E-01 4.82E-03 0.00E + 00 6.31 E-05 1.37E-03 2.17E+ 00 6.60E-02 Infant 3.55E-06 5.06E-05 4.80E-03 0.00E +00 6.85E-07 1.38E-03 8.73 E-04 6.60E-02 Dose factor - airborne release pathway (mrem /Ci released)

Cc-144 Bone Liver 1 - T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 1.26E-01 5.24E-02 1.04E-01 0.00E +00 3.10E-02 2.31E-01 8.05E + 00 1.13E-01 Teen 1.83E-01 7.56E-02 1.07E-01 0.00E+00 4.51E-02 3.96E-01 9.46E+00 1.13E-01 Child 2.91 E-01 9.10E-02 1.13E-01 0.00E + 00 5.04E-02 3.55E-01 7.37E+00 1.13E-01 Infant 9.58E-02 3.64E-02 1.03 E-01 0.00E + 00 1.61 E-02 2.92E-01 6.97E-02 1.13E-01 O

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POINT BEACH NUCLEAR. PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 L) Table 5.1-2 (continued) l Dose factor - airborne release pathway (mrem /Ci released) I Pr-143 Bone Liver T. Body n yroid Kidney Lungs GI-Lil Skin Adult 5.11 E-04 2.05 E-04 2.53E-05 0.00E+00 1.18E-04 3.34E-03 1.75E+00 3.77E-01 Teen 8.14E-04 3.25E-04 4.05 E-05 0.00E+00 1.89E44 5.74E-03 2.16E+ 00 3.77E-01  !

Child 1.82E-03 5.46E-04 9.02E-05 0.00E+00 2.%E-04 5.15E-03 1.73 E+ 00 3.77E-01 Infant 1.67E-04 6.23 E-05 8.32E-06 0.00E+00 2.35E-05 5.14E-03 5.83 E-04 3.77E-01  ;

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

Pr-144 Bone Liver T. Body Thyroid Kidney Lungs GI-LIl Skin Adult 8.93E-10 3.70E-10 2.58E-06 0.00E + 00 2.09E-10 3.01E-05 6.39E-16 2.%E-06 Teen 1.27E-09 5.22E-10 2.58 E-06 0.00E+ 00 2.99E-10 5.20E-05 6.98E-12 2.%E46 Child 1.77E-09 5.48E-10 2.58E-06 0.00E +00 2.90E-10 4.64E-05 5.84E-06 2.%E-06 Infant 1.42E-09 5.48E-10 2.58 E-06 0.00E+00 1.99E-10 4.78E-05 1.27E-04 2.%E-06 Dose factor - airborne release pathway (mrem /Ci released)

Nd-147 Bone Liver - T. Body H yroid Kidney Lungs GI-Lil Skin Adult 8.95E-05 1.03E-04 2.00E-02 0.00E+ 00 6.04 E-05 2.62E-03 1.51E-01 2.00E-01 Teen- 1.22E-04 1.33 E-04 2.00E-02 0.00E+00 7.80E-05 4.42E-03 1.15E-01 2.00E-01 Child 1.85E-04 1.49E-04 2.00E-02 0.00E+00 8.22E-05 3.90E-03 7.33E-02 2.00E-01 Infant 9.45E-05 9.69E-05 2.00E-02 0.00E+00 3.75E-05 3.83 E-03 4.73E-04 2.00E41 r

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POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 0

D 1

Table 5.1-2 (continued)

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

Eu-152 l

Bone Liver T. Body 'Ihyroid Kidney Lungs GI-Lil Skin i 1

Adult 3.32E-02 2.45E-01 3.62E+01 0.00E + 00 4.67E-02 3.26E-02 1.38E + 00 6.86E +01 Teen 4.20E-02 1.02E-02 3.62E+ 01 0.00E+00 4.73E-02 4.76E-02 1.23 E + 00 6.86E+01 l

Child 6.02E42 1.10E-02 3.62E+01 0.00E+ 00 4.64E-02 3.%E-02 8.25E-01 6.86E +01 Infant 1.30E-02 2.95E-03 3.62E+01 0.00E + 00 9.90E-03 2.46E-02 5.31E-04 6.86E+GI 1 Dose factor - airborne release pathway (mrem /Ci released) l W-187 Bone Liver T. Body Thyroid Kidney Lungs GI-Lil Skin l Adult 4.08E-03 3.41 E-03 7.22E-03 0.00E+00 0.00E +00 3.45E-04 1.12 E + 00 2.79E-02 Teen 6.98E-03 5.69E-03 8.03 E-03 0.00E+ 00 0.00E+00 5.63E44 1.54E+00 2.79E-02 l l

(O) Child 1.69E-02 1.00E-02 1.05E-02 0.00E+00 0.00E+ 00 4.88E-04 1.41 E+ 00 2.79E-02 '

Infant 1.13 E-05 7.88E-06 6.04E-03 0.00E + 00 0.00E+00 4.71 E-04 8.79E-04 2.79E-02 Dose factor - airborne release pathway (mrem /Ci released)

U-235 Bone Liver T. Body Thyroid Kidney-  : Lungs GI LIl Skin Adult 4.06E + 01 0.00E+ 00 1.04E+ 01 0.00E+00 9.47E+00 4.66E+00 3.87E + 00 1.06E+01 Teen 6.45E+01 0.00E +00 1.19E+ 01 0.00E+00 1.51 E+ 01 8.03 E +00 4.59E+00 1.06E +01 Child 1.54E+02 0.00E + 00 1.73 E+01 0.00E+00 2.53E+01 7.17E+00 3.58E+00 1.06E+01  ;

Infant 1.17E+ 01 0.00E + 00 8.84E + 00 0.00E+00 2.49E+00 5.46E +00 1.90E-01 1.06E+01 l

i Page 84 of 136

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR l Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 O#

Table 5.1-2 (continued)

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

U-238 Bone Liver T. Body Thyroid Kidney Lungs - GI-LLI Skin Adult 3.88E + 01 0.00E+00 2.33 E+00 0.00E + 00 8.86E+00 4.36E+00 2.72E + 00 2.47E-01 Teen 6.17E + 01 0.00E + 00 3.70E+00 0.00E+00 1.41E+01 7.50E+00 3.23 E +00 2.47E-01 Child 1.48E+02 0.00E+00 8.79E+00 0.00E+ 00 2.37E+01 6.73 E+00 2.53E+00 2.47E-01 Infant 1.12E+01 0.00E + 00 8.63E-01 0.00E + 00 2.33 E + 00 5.09E+00 1.34E-01 2.47E-01 Dose factor - airborne release pathway (mrem /Ci released)

Np-239 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 5.00E-05 4.92E-06 5.54E-03 0.00E +00 1.53E-05 4.47E-04 9.55E-01 9.52E4)3 Teen 8.79E-05 8.29E-06 5.55E-03 0.00E+ 00 2.60E-05 7.71E-04 1.27E+00 9.52E-03 O

Q Child 2.11 E-04 1.52E-05 5.55E-03 0.00E+00 4.39E-05 6.91 E-04 1.10E + 00 9.52E-03 Infant 4.42E-06 3.95E-07 5.54E-03 0.00E+00 7.88E-07 7.07E-04 3.14E-04 9.52E-03 Dose factor - airbome release pathway (mrem /Ci released) l Am-241 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 1.34E+02 4.76E+01 1.03E+01 0.00E + 00 6.10E+ 01 5.76E+00 3.48E+00 2.94E+00 Teen 1.46E+02 5.59E+01 1.11E+01 0.00E + 00 7.31E+01 9.99E+00 4.12E +00 2.94E+ 00 Child 1.37E+02 6.14E+ 01 1.11 E+ 01 0.00E+00 5.98E+01 8.88E+00 3.22E+00 2.94E+00 Infant 3.07E+01 1.41 E+ 01 3.56E + 00 0.00E+00 1.32E+01 6.76E+00 2.58E-03 2.94E + 00 Page 85 of 136

1 POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR l Revision 10 DRAFT l OFFSITE DOSE CALCULATION MANUAL Januanf 26,1996 '

l O l O 5.1.3 Atmospheric Release Mode: Noble Gases The dose calculations for demonstration of compliance with the 10 CFR 50, Appendix I dose limits for noble gases released to the atmosphere will be done in the manner similar to the liquid release dose i 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 = E Dose,i = E ( TDF,i X Ci ) s; K, mrem where ,

API = the Appendix I dose for compliance evaluation in mrem Dosei i

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

TDF,; = total dose factor from Table 5.1-3 in mn:m/Ci for the specific target (t) from radionuclide (i) based on the maximum annual average x/Q at the site boundary Ci= curies of mdionuclide (i) released K, = 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 x/Q values during the release using the methodology of Appendix C.

l lO Page 86 of 136

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR  !

Revision 10 DRAFT ,

OFFSITE DOSE CALCULATION MANUAL January 26,1996 1 l

l I

Table 5.1-3  !

l Activity to Dose Conversion Factors for Noble Gases (Highest Annual Average x/Q)

Beta Air . Gamma Air Skin Whole Body l Nuclide '

(mrad /Ci) (mrad /Ci) (mrem /Ci) (mrem /Ci)

AR-41 1.56E-04 4.42E-04 2.94E-04 4.72E-04 KR-83M 1.37E-05 9.18E-07 2.52E-09 7.13E-07 KR-85M 9.37E-05 5.85E-05 3.89E-05 1.15E-04 KR-85 9.27E-05 8.18E-07 5.36E-07 6.44E-05 KR-87 4.90E-04 2.93E-04 1.97E-04 6.91E-04 KR-88 1.39E-04 7.23E-04 4.89E-04 6.74E-04 q KR-89 5.04E-04 8.23E-04 5.53E-04 1.12E-03 KR-90 3.72E-04 7.75E-04 5.19E-04 9.49E-04 XE-131M 5.28E-05 7.42E-06 3.05E-06 2.84E-05 XE-133M 7.04E-05 1.55E-05 8.35E-06 5.93E-05 XE-133 4.99E-05 1.68E-05 9.79E-06 2.76E-05 XE-135M 3.51E-05 1.60E-04 1.04E-04 1.58E-04 XE-135 1.17E-04 9.13E-05 6.02E-05 1.59E-04 XE-137 6.04E-04 7.18E-05 4.73E-05 6.36E-04 XE-138 2.26E-04 4.38E-04 2.94E-04 5.37E-04 I

Page 87 of 136

POINT BEACH NUCLEAR PLANT ODCM l OFFSITE DOSE CALCULATION MANUAL l MAJOR l Revision 10 DRAFT )

OFFSITE DOSE CALCULATION MANUAL January 26,1996  ;

A U 6.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM A complete description of the PBNP radiological environmental monitoring program, l including procedures and responsibilities, is contained in the PBNP Environmental Manual.

7.0 RADIOLOGICAL IMPACT EVALUATION OF SEWAGE TREATMENT SLUDGE '

DISPOSAL The methodology for determining the radiological impact of sewage treatment sludge disposal is presented in this section. The radiological impact evaluation must be performed  !

for each sewage treatment sludge disposal prior to land application.  ;

7.1 Basis Wisconsin Electric's commitment with the United States Nuclear Regulatory .

Commission in a letter dated October 8,1987 (VPNPD-87-430, NRC-87-104) requires Wisconsin Electric to measure the concentrations of radionuclides in the sewage treatment sludge and compare them to concentration limits prior to disposal.

In addition, the appropriate exposure pathways will be evaluated prior to each application of sludge to insure that the dose to the maximally exposed member of the general public is maintained less than 1 mmm/ year and the dose to the inadvertent intruder is maintained less than 5 mrem / year.

p The exposure pathways evaluated for the maximally exposed individual are the V followmg:

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.

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 I2ke 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 intmder are the same as items 1, 4, 5, and 6 identified above for the maximally exposed individual.

Page 88 of 136

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 7.2 Procedure The following steps are to be performed by the Responsible Engineer - IRSS for each sewage treatment sludge disposal:

7.2.1 Obtain from PBNP - Chemistry 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 concentation determinations will be utilized in determining the sludge storage tank concentration values.

7.2.2 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 Appendix E.

7.2.3 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 aA Ni cations. The activity  :

from these prior disposals will be corrected for raui&gical decay prior to performing dose calculations for the meat, milk, and vepble ingestion pathways, the inhalation of resuspended radionuclides, and ali Pthways associated with a potential release to Lake Michigan. The residuai

- radioactivity will be corrected, if applicable, for the mixing of radionuclides in the soil prior to performing external exposure  ;

calculations. l Wisconsin Electric utilizes QAD, a nationally recognized computer code, to perform shielding and dose rate analyses. QAD 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 i 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 Appendix E.

7.2.4 Inform PBNP - Chemistry that the sewage treatment sludge disposal may proceed after verifying that the sewage treatment sludge meets the concentration, activity, and dose limits.

7.2.5 Forward all calculations to PBNP - Chemistry to be included with the sewage treatment sludge disposal record.

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POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 O

U 7.3 Administrative Requirements 7.3.1 Complete records of each 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.

7.3.2 Modifications to the October 8,1987, NRC submittal

a. Modification 1 - Appendix F 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 propeities am now determined annually instead of per application. The frequency for radiological characterization did not change,

b. Modification 2 - Appendix G 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 pmvided the WDNR and NRC constraiats are met.

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POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 l O

i l

l l

l APPENDIX A I

1 DERIVATION OF LIQUID RELEASE PATHWAY EFFECTIVE MAXIMUM EFFLUENT CONCENTRATION O

(

l lO I

l Page 91 of 136 l

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL March 13,1996

( A1.0 DERIVATION OF LIOUID RELEASE EFFECTIVE MAXIMUM EFFLUENT CONCENTRATION A1.1 Source Term The effective maximum effluent concentration is calculated from the annual 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.

A1.2 Effective Maximum Effluent Concentration The effective maximum effluent concentration (EMEC) was calculated using the formula given in Section 3.6 EMEC = ECi / E (C/MEC) i i or EC i* 1/SOF where:

SOF = E C/MEC i is i the summation of fractions for the annual effluent isotopic release b

v C=

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

MECi = maximum effluent conce.ntration for unrestricted areas from Appendix B, Table 2, Column 2 of 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 l (Table A-2). The average EMEC without H-3 is 4.29E-06 pCi/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 ECi / E (C i/MEC)i or EC i* 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

(]

U (10 CFR 20, Appendix B, Table 2). They are I-131 (IE-06), Cs-134 (9E-07), and Cs-137 (IE-06).

Page 92 of 136 d

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 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 3.00E-04 pCi/cc without I exceeding the SOF criterion of 10 CFR 20, Appendix B for the total liquid effluent j isotopic mixture.

I i

4 1

a l

l i

1 j

I O

I Page 93 of 136

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 O '

TABLE A l CITRIFS RFI EASED IN LlOUfDS I10UID LELEASES l NUCLIDE $ 1985 1986 1987- 1988 1989 1990 1991 11-3 1.00503 8 05E4 02 8.11 E + 02 7.09E + 02 3.57E + 02 5.59E + 02 8.72 E + 02 7.87E +02 I-131 1.00FA6 1.02FAI 3.74FA2 1.04E42 1.40FA3 1.77FA3 1.53 E44 1.83 E-03 I-132 1.00FA4 6.15E42 7.25FA2 5.82E-02 1.03 E@ 8.15 E44 4.45FA5 9.41 E@

1133 7.00FA6 1.27E-01 1.49E-Ol 1.04 E-Ol 1.21 E-02 8.11 E-03 3.01 E-03 1.01 E-02 1 134 4 00:1-04 3.18E02 4 39E-02 3.97E-02 2.29FA4 6.83 E44 1 135 3.00E45 1.04FAI 1.34FAI 1.23 E-01 4.48E-04 8.21 E-04 AG-110M 6.00E46 2.55E-05 2.84E-04 3.09FA3 9.85FA4 4.70E-04 1.7l FA4 4.06504 BA 133 2.00&OS

_R A-139 2 00E-04 8 63E-06 2.47E44 BA 140 8.00E-06 6.90E-06 4.45 E-05 6.13 E-05 CD-109 6.00F46 6.33 E-05 1.31 E-04 CE-139 7.00E-05 C D141 3.00E-05 1.3 t E-03 7.50E-04 CE-144 3.00E-06 1.37E@ 2.08E-03 4.76E-04 1.59E44 9.47FA6 9.64E-06 CO-56 600506 CO-57 6.00FA5 2.52 E-03 1.33E-04 3.21 E44 5.07E-05 6.90E-07 4.08 E-06 0 0-58 2.00E-05 4 05E-01 9.02E@ 3.36E-02 6.81 E@ 3.12E43 3.25E44 2.93 E-03 0 0-60 3.00E-06 2.88E01 2 85E-02 6.34E-02 2.04E-02 1.540 42 1.4 t E-03 5 53E-03 CR-51 5.00E-04 2.71502 3.16E44 1.58E-02 5.3 t E-05 4.44FA4 8.71 E-05 CS-134 9.00E47 4.76E-02 6.92E@ 1.18 E@ 4.96E-04 1.49E-03 CS-134M 2.00E-03 3.59E-04 5.97E-06 4.67E-04

[ CS-136 6 00E46 [

CS-137 1.00E-06 9.60E-02 2.11 E42 7.54E@ 8.63 E@ 2.80E@ 1.94E-03 8.93 E@

CS-138 4.00E-04 1.11 E-03 5.48E-03 3.24E-03 F-18 7.00E-04 1.00FA2 1.67E-02 7.56E-04 1.66E-03 2.26E-03 4.06E-04 FE-59 1.00E-05 2.76E-04 LA-140 9.00E-06 MN-54 3.00E-05 7.46E-03 1.18EG 4.68E4 1.54 504 2.68 E-04 3.10E-05 1.96FA4 MO-99 2.00E-05 3.70E-05 N B-95 3.00E05 6.28 E-03 6.65 E-04 3.21 E.03 1.6 t FA4 2.33 E-06 8.68E05 )

N B-97 3.00E-04 1.35E43 5.22E-04 6.16E-05 1.06E-05 3.90E-06 8.80E-06 5.30E-06 R B-88 4.00E-04 8.46FA5 1.11 E-02 3.33 E-03 RB-89 9.00E-04 7.98 E-04 2.34E-04 RU-103 3.00E-05 3.59E@ 1.68E46 8.41 E-04 5.86FA5 R U-106 3.00E-06 8.07E-04 2.88E@ 7.33 Ee 1.04E-04 SB-124 7.00E-06 3.86E-02 2.96E-04 1.42 E-04 2.34FA4 S E125 3.00E-05 1.12 E-02 1.20E-03 1.95E-03 1.00E@ 2.12E-02 1.28 E-05 1.08E42 SN-113 3.00E-05 1.07Em 4.20E@ 5.13 E-04 3.21 FA4 3 07E-06 SR-89 8.00E-06 2.27E-04 3.46E-05 3.89E43 2.68E03 8.69E-06 S R-90 5.00E-07 1.29E-03 2.28E44 2.80E-04 3.50E-04 2.55 E-04 TC-99M 1.00E-03 1.75E-05 3.75E-06 3.30E-05 TC-101 2.00E-03 110E @

TE-131 8.00E-05 7.98 E-05 TE-132 9.00 E.06 5 83Ee 6.94E-05 2.74E45 7.19E-06 1.74FA4 W-187 3.00E45 3.41 FA5 Y-91 M 2.00E-03 ZN-65 5.00E-06 5.15FA5 ZR-95 2.00E-05 7 95E05 2 61E44 2.45E@ 1.58E05 ZR-97 9 00E46 1.49E-06 3 09E-06 1.74E-05

\O TOTAL CI 8.06E + 02 8.12 E + 02 7.10E + 02 3.57E + 02 5.59E + 02 8 72E + 02 7.87E + 02 TOTAL W/O H-3 1.37E + 00 5.39E-01 5.1? E 41 5 09E4' 5.65 E.02 9.57E-03 5.42E-O' Page 94 of 136

li POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 1 O -

k/ TABLE A-2 FRACTIONAL MEC IN LIQUID EFFLUEffT l

NUCLIDE MEC 1985 1986 1987 1988 1989 1990 1991 ucl/cc if-3 t .00E-03 1.27E-03 125E-03 1.04E-03 5.17E44 8.36E-04 1.26E43 1.22E43 I-131 1.00E-06 16] E-04 5.75E-05 1.52 E-05 2.03 E-06 2 65E-06 2.21 FA7 2.84E46 1-132 1.00E-04 9.70E47 1.12E46 8 53E-07 1.49E-08 1.22E-08 6.43 E-10 1.46E-07  ;

I-133 7.00Fe06 2 86E-05 3.27E-05 2.18E-05 2 SlE-06 1.73 E-06 6.21 E47 2.24E-06 j 1-134 4 00E44 1.25E-07 1.69E-07 1,46E47 8.30E-10 2 65E-09 I-135 3 00E-05 5 47E46 6 87E-06 6 ole-06 2.16FA8 4.24E48 AG-110M 6 00E46 6.70E-09 7.28E-08 7.55E 47 2.38E-07 1.17E-07 412E48 1.05 E-07 B A-133 2.00E-05 B A-139 2 00E44 6 33E-11 1.79E-09 i B A-140 8 00E46 136E-00 0 00E +00 8.16E-09 1.11 E-08 CD-109 6 00E-06 1.62E-08 3.16E-08 ,

CE- 139 7 00E-05 CE-141 3.00E.05 6 89E-08 3.67E-08 CE-144 3 00E-06 7 03E-07 1.02 E-06 2.30E-07 7 92EQ 4 56E-09 4.98E-09 CO-56 6 00E-06 C0-57 6 00E-05 6 62E-08 3.41 E-09 7.84E-09 1.22E-09 1.72 E-11 9.83 E-11 C0-58 2 00E45 3.19E-05 6 94E-07 2.46E-06 4 93E-07 2.33 E-07 2.35 E-08 2.27E-07 CO 60 3.00E-06 1 51 E-04 1.46E-05 3.10E-05 9 86FA6 7.67E-06 6.79E-07 2 86E-06 CR-51 5.00E-04 8 55E-08 9.72E-10 4 63E-08 1.54E-10 f .33 E-09 2.52E-10 CS-134 9.00E-07 8 34E-05 1.18E-05 1.92 E-06 7.99E-07 2.57E-06 CS-134M 2.00E43 2.60E-10 4.46E-12 3 62E-10 CS-136 6 00E-06 w CS-137 1.00E46 1.51 E-04 3.25E-05 1. l l E-05 1.25E-05 4.19E-06 2.80E-06 1.38E-05 4 38E-09 U) CS-138 F-18 4.00E-04 7.00E44 2.11 E-08 2.20E-08 1.19E-08 3.50E-08 1.57E49 3.54E49 4 67E-09 8.99E-10 FE-59 1.00E-05 4.05E-08 L A-140 9.00E-06 M N-54 3.00E45 3.92 E-07 6 05E-08 2 29E-07 7.44E-09 1.34E-08 1.49E-09 1.01 E-08 MO 99 2 00E-05 2 68E-09 NB-95 3 00E-05 3.30E-07 3.41 E-08 1.57E-07 7.78E-09 1.16E-10 418E-09 NB-97 3 00E-04 7.10E-09 2 68E-09 3.01 E-10 512 E-11 1.94E-11 4.24E-11 2.74E-11 RR-88 4 00E-04 3.34E-10 4.27E-08 1.22E-08 RB-89 9.00E-04 1.36E-09 3 8IE-10 R U-103 3.00E-05 1.89E-07 8 62E-11 4.11 E-08 2.83E-09 RU-106 3.00F46 4.24E-07 1.48 E-06 3.58E-06 5 02E-08 SB-124 7 00EA6 8 70E-06 6 5t E-08 2.97E48 4 84E 08 S B-125 3 00E-05 5 89E-07 615E-08 9 53E-08 4 83E-08 1.06E-06 6.17E-10 5.58E-07 SN-113 3 00E-05 5 63F-08 2.15E 09 2 51E48 1.55E-08 1.59E-10 SR-89 8 00E-06 4 48E-08 6 65E-09 7.13 F-07 4.86E-07 1.62E-09 SR40 5 00E-07 4 07E-06 7.02E-07 8 21E-07 101 E-06 7.62 E-07 TC 99M 100E-03 2.76E-11 5.77E-12 4 78E-11 TC-101 2 00E-03 8 06E-12 TE-131 8 00E-05 1.45E-09 TE-132 9.00E-06 1.02 E-10 1.19F-08 4.46E-09 1.16E-09 3.00E-08 W-187 3.00E-05 165E-09 Y 9tM 2 00E-03 ZN-65 5 00E-06 1.51 E48 ZR-95 2 00E-05 6 27E-09 2.0l E-08 1.80E-07 1.14 E-09 ZR-97 9.00E-06 2 61E-10 5.28E-10 2 80E-09 bi V

Page 95 of 136

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 FRACTIONAL MEC IN LIQUID EFFLUENT 1995 1986 1987 1988 1989 1990 1991 1 ANNU AL VOt/COs) 6 34E+ f 4 6.50E + 14 6 82E+14 6.90E + 14 6 69E+ 14 6 92E + 14 6 45E+14 l TOT FR AcrION 190E-03 1.41 E-03 1.14E43 5 48E44 8 54E44 1.26E-03 1.25E-03 I FR ACT W/O 11-3 6 29E44 161E44 9.83 E45 3 04E45 1.85 E45 4 41E-06 2 55E45 TOTALCI 8 06E + 02 8.12E + 02 7.10E + 02 3.57E + 02 5 59E+02 8.72 E + 02 7.87E + 02 TOTAI, W/O H-3 1 37E + 00 5 39E41 512E41 5 99E42 5 65E42 9 57E43 5 42E-02 TOT CONC (uci/CC) 1.27E-06 1.25E06 104E46 5.17E47 8.36E47 1.26E-06 1.22 E-06 TCON W/O H 3 216E49 8.30E 10 7.51 E-10 8.69E-Il 8.44E-11 1.38E-11 8.40E-11 EMEC 6.70E-04 2'6E44 9.14 E-04 9.45 E44 9.78 E44 9.97E-04 9.80E44  ;

EMEC W/O H-3 3 43E46 5.14E4m 7.64FA)6 2.85 FA)6 4 56E46 3.14E-06 3.30E46 '

i 1

I

/\

(u-)

Page 96 of 136

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR l Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996  !

O 1

APPENDIX B 1

i DERIVATION OF ATMOSPHERIC RELEASE MODE >

EFFECTIVE MAXIMUM EFFLUENT CONCENTRATION 1

J 4

i 1

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POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL March 13,1996 p

d Bl.0 DERIVATION OF ATMOSPHERIC RELEASE EFFECTIVE MAXIMUM EFFLUENT CONCENTRATION Bl .1 Source Tenn The effective maximum effluent concentration (EMEC) for atmospheric effluents is calculated from the annual releases for the years 1985 - 1991 (Table B-1). 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 efnuent.

Bl.2 Effective Maximum Effluent Concentration The maximum concentration of a radionuclide mixture that is allowable at the site boundary is called the effective maximum efnuent concentration (EMEC). The EMEC for an effluent mixture is defined by the equation EMEC = EC / E(Ci / MEC)i 3

where Ci = concentration of radionuclide "i" m MECi = maximum effluent concentration for radionuclide "i" from (j 10 CFR 20, Appendix B, Table 2, Column 1 ,

l E (C i/ MEC) = summation of fractions (SOF), as discussed in Section 3.6, applied 3 i to atmospheric releases The EMEC is calculated from the reference radionuclide mixture which is the radionuclidcs 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 l (Table B-2). The average total EMEC is 8.04E-08 1.31E-08 pCi/cc with a range '

i of 5.84E-08 to 9.50E-08 pCi/cc. Next, the annual EMEC was modified for the presence of H-3, which is not detected by the atmospheric RMS, by multiplyire 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 i 1.23E-08 Ci/cc with a range of 5.02E-09 to 3.70E-08 Ci/cc.

l 0

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1 POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 TABLE B-1 CURIES IN ATMOSP11ERIC EFFLUENT NUCLIDE MEC 1985 1986 1987 1988. 1989 1990. 1991 uCi/mi 11 3 1,00E47 6.71 E + 01 1.20E + 02 1.18 E + 02 1.26E + 02 1.42 E + 02 1.28 E + 02 1,13 E + 02 l

AR-41 100E-08 1.27E + 00 6 81E-01 2.17E + 00 1.96 E + 00 1. 57E + 00 1.11 E + 00 107E + 00 KR-85M i 00E47 1.84 E + 01 6.77E-01 1.18 E + 00 7.31 E41 2.24F 01 1.85 E-01 103E-01 KR-85 7.00E47 1.67E + 01 1.32 E + 00 7.11 E-01 9.84E-01 3.58 E-01 1.78E-01 2.74E-01 KR-87 2.00E48 4.78 E + 00 1.01 E + 00 2.37E + 00 1.48 E + 00 4 94E-01 4.05 E-01 2.31 E4L, KR-88 9 00E-09 5.73 E + 00 1.30E + 00 2.72 E + 00 1.69E + 00 5.64E41 4.49E-01 2 56E-01 XE-131M 2 00E-06 8 54E-02 XE-133M 6 00E-07 3.30E-01 1.38E-01 2.12 E-O f 3 35E-01 4.94E-03 2.06E-02 3.97E-02 XE-133 5 00E-07 3,45 E + 01 1 53 E + 01 2 06E + 01 6 04E +01 7.54 E + 00 196E + 00 1.60E + 01 XE-135M 4 00E-08 5.76E + 00 1.27E + 00 3 68E+00 2.54 E + 00 7.37E-01 6 49E-01 3.44E-01 XE-135 7.00E48 1.19E + 0! 3 21 E + 00 5.64 E + 00 3.53 E + 00 1.08 E + 00 1.09E + 00 6 03E-01 i I

XE-138 2.00E48 1.65E+0! 2 9 t E + 00 8 87E+00 7.19E + 00 2.45 E +00 1 99E + 00 1.06E + 00 AG 110M 1.00E-10 2 31E-07 B A 133 9 00E-10 B A-139 4.00E-08 1.17E-07  ;

H A-140 2 00E49 3.41EM CD-109 2.00E-10 8.92 E-06 1.26E-06 2.28 E44 CE-139 9.00E-10 CE-141 8 00E-10 8.43E-09 CE-144 2.00E-11 2 04E-06 3.92EM 3 94E-09 CO-57 9 00E-10 2.10E-07 2.52 E-11 1.13 E-08 1.23 E46 4.80E-07 CO-58 1.00E-09 1.57E 04 133E-05 1,01 E44 3.59F-05 1.69E44 2.74E-05 3.85E-06 C0-60 5 00E-11 7.94E45 1.11 E-04 1.18 E-05 3.64E44 1.63 E-04 3.56E46 1.06E-04 CR-51 3 00E-08 5 28E-04 7.58 E-09 1

(

\ CS-134 2 00E-10 1.18 E-03 9.49E-04 5.86E-05 7.27E-05 1.10E-03 I CS-136 9 00E-10 i CS-137 2.00E-10 4 02E-03 2.94E-04 3 08E44 6.74E-04 2.10E-03 1.91 E-04 1.90E-03 CS-138 8.00E-08 9 64E-07 1.92 E-06 1.85E-03 1.26EM 3.44E-06 1.92Ee02 F-18 1.00EM 1.08E-05 2.52 E-04 3.87E-05 3.31E04 1.10E-05 6 60E-04 FE-59 7.00E-10 4.87E-09 M N-54 1.00E-09 199E-06 1.70E-06 4.86E-05 MO-99 2 00E-09 7.27E-09 2.71 E-08 N A-24 7 00E-09 1.39E44 4.32E-04 4.29E-04 I NB-95 2 00E-09 2 52E-06 7.70E-07 5.97E-07 6.25E-08 9.56E-10 NB-97 1.00E-07 1.60E-08 1.65E-09 R B-88 9 00E-08 4 63E-05 3.46E45 103 E-02 4.00F,06 1.81 E OS 1.62E41 )

R B-89 2 00E-07 4.30E-09 l R U-103 9.00E-10 191 E-08 1 89E-05 SB-125 7.00E-10 1.25 E-07 3 68E46 9.39E48 SN-113 8 00E-10 216E-08 4.80E-10 SR-89 2 00E-10 4 87E-08 1.54 E-06 7.70E-07 3.71 E-06 SR-90 6 00E-12 168E-10 4.30E-06 SR-91 5.00E-09 TC-99M 3.00E-07 6 43E-08 2.20E-07 9.24 E-07 TC-101 5.00EM TE-132 9 00F-10 3.07E-06 7.33E-08 2.34E-06 Y-88 3.00E-10 1.28E-10 ZN-65 4 00E-10 9.27E-06 ZR-95 4.00E-10 1.31 E-06 3.56E-09 7.43E-10 ZR97 2 00E-09 2 97E-10 i

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1 POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSB CALCULATION MANUAL January 26, IP96 l m s TABLE B-1 (continued)

CURIES IN ATMOSPHERIC EFFLUENT NUCLIDE MEC 1985 1986 1987 1988 1989 1990 1991 uci/mi I-131 2 00E-10 3 44E43 1.11 E43 3.08E43 5.43 E44 3.18E44 7.85E-05 3 46E44 l-132 2.00E-08 3.75E43 1.79FA3 2 42E43 4.78E44 4 20E-05 1.09E45 2 95E45 I-133 1.00E49 1.37E43 6 80E44 3.04 E-03 1 53 E-03 1.19E-03 1.13 E-04 1.13E44 I f 34 6 00E-08 133 E-05 9.32E44 L. !-;35 6 00E49 5.79E-04 1.09E-04 2.19E43 918E45 1.26E45 3.15E-08 1.58E45 O

l

O Page 100 of 136

1 POINT BEACH NUCLEAR PLANT ODCM l l OFFSITE DOSE CALCULATION MANUAL l MAJOR l Revision 10 DRAFT  !

l OFFSITE DOSE CALCULATION MANUAL January 26,1996 l n t t l  % ./

TABLE B-2 FRACTIONAL MEC FOR ATMOSPHERIC EFFLUENT IICI.IDE 1985 1986 1987 l1988 1989 1990 1991  ;

H-3 3.10E45 5.7] E-05 562605 1900E-05 6.76E-05 6.10E45 5.38E45 AR-41 6 05E46 3 24E06 103E45 9 33E-06 7.48E46 5.29E-06 510E 06 KR-85M 8.76E06 3.22E47 5 62E47 3.48 E-07 1.07E-07 8.81 E08 4 90E08 KR-85 1.14E06 8.98E48 4.84E08 669508 2.44E08 1.21 E-08 1.86E-08 KR-87 1.14E-05 2 40E-06 5 64E46 3.52E-06 1.18E-06 9.64E07 5.50E-07 KR-88 3 03E05 6 88E46 f .44E45 8 94E-06 2.98E-06 2 38E46 1.35E-06 XE-131 M 2 03E09 l XE133M 2 62E48 1.10E08 1.68E48 2.66E-08 3.92 E-10 1.63 E-09 3.15E 09 X E-133 3.29E46 1.46E-06 1.96E46 5 75E-06 7.18 E-07 1.87E47 1.52 E-06 XE135M 6 86E-06 1.51 E06 4.38E46 3.02 E-06 8.77E-07 7.73 E-07 410E-07 XE-135 8.10E46 2.18E46 3 84E46 2.40E-06 7.35E07 7.41 E-07 4.10E-07 XE-l38 3.93 E-05 6.93E06 2. I 1 E-05 5.83 E-06 4.74E-06 2.52E-06 1.71 E-05 AG-Il0M 1.10 E10 B A-139 1.39E-13 B A-140 8.12E-12 CD-109 2.12E49 3.00E-10 5.43 E-08 CE141 5 05E-13 C E144 4.86EO9 9 33E-10 9.38E-12 CO-57 1.11 E-f l 1.33 E-15 5.98 E-13 6.51 E-11 2.54 E-f l CO-58 7.48 E49 6.33 E-10 4.8 t E-09 1.71 E-09 8.05E-09 1.30E49 f .83 E-10 CO-60 7.56E-08 1.06E07 1.12E08 3.47E-07 1.55E-07 3.39E-09 101 E-07 CR-51 8.38 E-10 1.20E-14

[(/ CS 134 CS-136 CS-137 2.81 E07 9.57E 07 2.26E-07 7.00E-08 1.40E-08 7.33E-08 1.73 E-08 1.60E-07 5.00E47 4 55E08 2.62E-07 4.52 E-07 CS-138 5.74E-13 1.14E-12 1.10E-09 7.50E-14 2.05E-12 1.14E-08 F-18 5.14 E-12 1.20E-10 1.84 & 11 1.58E-10 5.24E-12 3.14 E-10 FE-59 3.31 E-13 MN-54 9 48E-11 8.10E-11 2.31 E-09 M0 09 1.73 E-13 6.45E-13 N A-24 9.46E-10 2.94E-09 2.92E-09 N B-95 6 00E-11 1.83 E-I l 1.42E-11 1.49E-12 2.28E-14 NB-97 7.62E-15 7.86E-16 R B-88 2.45 E-11 1.83 E-11 5 45E09 2.12 E-12 9.585-12 8.57508 R B-89 1.02 E-15 RU-103 1.0lE-12 1.00E49 SB-125 8.50E-12 2.M)E-10 6.39E-12 SNII3 1.29E-12 2.86E-14 SR-89 1.16El l 3 67E-10 1.83 E-10 8.83 E-10 SR-90 1.33 E-12 3.41 E-08 SR-91 TC-99M 1.02 E-14 3.49E-14 1.47E-13 TC-101 TE-132 1.62E-10 3.88 E-12 1.24E-10 Y-88 2.03E-14 ZN-65 1.10E09 ZR-95 1.56E-10 4.24513 8.85E-14 ZR-97 7.07E-15 l ("

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POINT BEACH NUCLEAR PLAlfI' ODCM 3 OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 O

b TABLE B-2 (continued)

FRACTIONAL MEC FOR ATMOSPHERIC EFFLUENT Nf3CLIDE 1985 1986 1987 1988 1989 1990 1991 I-13 i 819E-07 2 64E-07 7.33 E-07 1.29E-07 7.57E-08 1.87E48 8.24E-08 I-132 8 93FA9 4.26E-09 5.76E O9 1.14E-09 1.00E-10 2.60E-11 7.02 E-1 !

I-133 6 52E-08 3.24E-08 1.45E-07 7.29E-08 5.67E-08 5 38E-09 5.38 E-09 I-134 1.06E-11 7 40E-10 1 135 4 60E-09 8 65E-10 1.74E48 7.29E-10 1.00E-10 2.50E-13 1.25E-10 TOTALFRAC 1.49E-04 8.29E45 1.20E-04 1.11 E-04 8.83 E-05 7.62E-05 6 67F 05 TorTA! H3 1.17E44 2.57E45 6.34E45 5.13E-05 2.07E-05 1.52E-05 1.29E45 FFF MEC 5 84E-08 8 49E-08 6.62E-08 8.85E-08 8.46E-08 8.50F 08 9.50E-08 W/O H-3 3.70E-08 1.60E48 1.92E48 3.46E-08 8.10E-09 5.n2 E-09 1.44E-08 CO v

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POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 O

APPENDIX C CALCULATION OF TOTAL DOSE FACTORS USING REGULATORY GUIDE 1.109, REV.1 A

V l Page 103 of 136  %

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 C1.0 CALCULATION OF TOTAL DOSE FACTORS USING REGULATORY GUIDE 1.109 l METHODOLOGY C1.1 Liauid 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. l 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.  ;

C1.1.1 Aquatic Foods l

, The dose from the eating of fresh fish caught at the edge of the initial  !

I mixing zone was calculated using the equation:

P 'P Dose,g = 1100 Qi B,D, ige "'k b where:

)

Dose.g = 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-ft3 to pCdliter; j M, = the mixing ratio (reciprocal of the dilution factor) at the point of harvest of aquatic food, dimensionless; )

U,p = 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 ft 3/sec; Qi = the release rate of nuclide i, in Ci/ year; B ip = 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/l), in liters /kg; D,;g = the dose factor, specific to a given age group a, nuclide i, p pathway p, and organ j, which is used to calculate the U radiation dose from an intake of a nuclide, in mrem /pCi; A; = the radioactive decay constant of nuclide i, in dayd ;

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POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT

, OFFSITE DOSE CALCULATION MANUAL January 26,1996

^

l 4

t, = 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 l the water, in days.

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

"M - 1100 '

• P B;pD,;ge

~ *'k The values used in the equation above are:

l

, M, = 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 l allowed for current reversals was not used.); )

i U,p = Infant - 0, Child - 6.9, Teen - 16, and Adult - 21 kg/ year;  !

F = 1507 ft3/sec. (677000 gpm); i B;p = Values used are taken from Table A-1 of RG 1.109;

, D,;g = Values used are taken from Tables E-11 through E-14 of j j RG 1.109; l i i t, = 0.5 days. 1

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:

Aw

, Dose,g = 1100 P

QF i Dg e ~ * ' ' '

where:

Dose g = 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-ft3 to pCi/ liter; l n M, = the mixing ratio (reciptucal of the dilution factor) at the point fy of exposure, /s. :ns,onless; i

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POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 '

T l j U,, = a usage factor that specifies the intake rate for an individual of age group a associated with pathway p, in kg/ year; Q3, = consumption rate of contaminated water by an animal, in liters / day; F = the flow rate of the liquid effluent, in ft 3/sec; Qi = the release rate of nuclide i, in Ci/ year; Fx i

= 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 meat per pCi/ day; D,ig = the dose factor, specific to a given age gmup 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; 1; = the radioactive decay constant of nuclide i, in day-1;  ;

t, = the average time from slaughter to consumption, in days. j To calculate the dose per curie released, the equation above was .

i rearranged and the calculation performed for each nuclide. The

!> rearranged equation is shown below:

Dose,;g _ M,U,pQx _g Qi F ,

1 j The values used in the equation above are:

1 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.);

U,p = Infant - 0, Child - 41, Teen - 65, and Adult - 110 kg/ year; Q3, = 60 liters / day; F = 1507 ft3/sec. (677000 gpm);

4 Fx i

= Values u:;ed are taken from Table E-1 of RG 1.109; D,;g = Values used are taken from Tables E-11 through E-14 of RG 1.109; A t' = 20 days.

1 V

, Page 106 of 136

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 (J C1.1.3 Irricated 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:

A" QFaD,ige ~M P

Dose,g = 1100 where:

Dose g = 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 conven from Ci-sec/yr-ft3 to pCilliter; M, = the mixing ratio (reciprocal of the dilution factor) at the point of exposure, dimensionless; U,, = a usage factor that specifies tne intake rate for an individual of age group a associated with pathway p, in liters / year; QAw = Consumption rate of contaminated water by an animal, in liters / day; F = the flow rate of the liquid effluent, in ft 3/sec; Q, = the release rate of nuclide i, in Ci/ year; Fa = the stal;le element transfer coefficient that relates the daily intake rue by an animal to the concentration in an edible portion of animal product, in pCi/ liter of milk per pCi/ day; D,ig = 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; Ai = the radioactive decay constant of nuclide i, in day-!;

tr = the average transpon time of the activity from the feed into the milk and to the receptor, in days.

i i

f-)

L.) l l

Page 107 of 136 i

,. ~-. _

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l M/JOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 To calculate the dose per curie released, the equation above was 1

rearranged and the calculation performed for each nuclide. The i rearranged equation is shown below:

4 dd = 1100 8'

^"Fg Dgge "'4 1

The values used in the equation above are:

1 M, =

0.1111 (Point at which water is taken from the lake is taken as plume centerline 1 mile downstream. The plume centerline s

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.);

U,, = Infant - 330, Child - 330, Teen - 400, and Adult - 310 liters / year; Q3, = 60 liters / day; F = 1507 ft3/sec. (677000 gpm);

G O Fa = Values used are taken from Table B-1 of RG 1.109; Dgg = Values used are taken from Tables E-11 through E-14 of

RG 1.109; tr = 2 days.

i J

d O

Page 108 of 136

POINT BEACH NUCLEAR PLANT ODCM i OFFSITE DOSE CALCULATION MANUAL l MAJOR j Revision 10 DRAFT l OFFSITE DOSE CALCULATION MANUAL January 26,1996 C1.1.4 Potable Water The dose from ingestion of water was calculated using the equation:

Dose,g = 1100

• P QDig e **

where:

Dose g = 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-ft3 to pCi/ liter; Mp = the mixing ratio (reciprocal of the dilution factor) at the point of withdrawal of drinking water, dimensionless; U,p = a usage factor that specifies the intake rate for an individual of age ginup a associated with pathway p, in 1/ year; F = the flow rate of the liquid effluent, in ft 3/sec; Q3

= the release rate of nuclide i, in Ci/ year; I D,ig = the dose factor, specific to a given age group a, nuclide i, l pathway p, and organ j, which is used to calculate the radiation dose from an intake of a nuclide, in mrem /pCi; A; = the radioactive decay constant of nuclide i, in day-3; t, = 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.

f E

A U

3 Page 109 of 136

1 l POINT BEACH NUCLEAR PLANT ODCM l

l OFFSITE DOSE CALCULATION MANUAL l MAJOR  !

Revision 10 DRAFT

! OFFSITE DOSE CALCULATION MANUAL January 26,1996 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: '

l Dose M,U,, _g gg _

Q, F The values used in the equation above are: l M, = 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.);

U,, = Infant - 330, Child - 510, Teen - 510, and Adult - 730 liters / year; F = 1507 ft3/sec. (677000 gpm);

Dog = Values used are taken from Tables E-11 through E-14 of RG 1.109 t, = 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.)

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POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 b

b Cl.l.5 Shoreline Deposits 1

The dose from exposure to radioactive materials deposited on the shoreline i of the lake was calculated usi;g the equation:

P ap Dose,g = 110000 ig e h(1 - eM)

Q:TD where:

Dose.g = 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; i 110000 = a factor to convert from Ci-sec/yr-ft' to pCi/ liter and to

account for the proportionality constant used in the sediment radioactivity model; My = the mixing ratio (reciprocal of the dilution factor) at the point of exposure, dimensionless; U,, = a usage factor that specifies the exposure time for an individual of age group a associated with pathway p, in hours / year;

/ 'N O W = shoreline width factor, dimensionless; F = the flow rate of the liquid effluent, in ft 3/sec; Qi = the release rate of nuclide i, in Ci/ year; Ti = the radioactive half life of nuclide i, in days; D,ig = the dose factor, specific to a given age group a, nuclide i, pathway p, and argan j, which is used to calculate the radiation dose from an intake of a nuclide, in mrem /pCi; A; = 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, tp is the total time elapsed between release of the nuclides and the ingestion of the water, in days; t3 = the period of time for which the sediment or soil is exposed to the contaminated water, in days.

O Page 111 of 136

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 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:

• - 110000 P

BipT3D,ig e -16(1_ e-2A)

The values used in the equation above are:

Mp = 0.01821 (Point cf exposure is taken as the Point Beach State Park beach which is kcated 8000 meters downstream. The plume shoreline diluticn 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.);

U,, = Infant - 0, Child - 14, Teen - 67, and Adult - 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> / year; l

W = 0.3; B;p = Values used are taken from Table A-1 of RG 1.109; F = 1507 ft3/sec. (677000 gpm);

O v D,;p; = Values used are taken from Table E-6 of RG 1.109; tg = 0.5 day; 13 = 5458 days.

l Page 112 of 136

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT

, OFFSITE DOSE CALCULATION MANUAL January 26,1996 m

C1.2 Atmosoberic Release Dose Factors: Non-Galequs i

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 mrem /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 pmsented 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.

C1.2.1 Inhalation of Nuclides In Air The dose from the inhalation of nuclides in the air was calculated using the equation:

Dosep = 3.17E +04R, Y { Q DFI i g, rQ, ,

where:

Dosep = the annual dose to organ j of an individual of age group a due to inhalation, in mmm/ year; 3.17E+04 = the number of pCi/Ci divided by the number of sec/ year; R, = the annual air intake for individuals in the age group a, in m3/ year; x/Q = the annual average atmosphere dispersion factor, in sec/m3 (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; DFI;3 = the inhalation dose factor for radionuclide i, organ j, and age group a, mrem /pCi.

Page 113 of 136 1

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 To calculate the dose per curie released, the equation above was I rearranged and the calculation performed for each nuclide. The rearranged equation is shown below:

t i Dose"..

- 3.17E + 04 R* 1 Qi (Q, DFI'"

The values used in the equation above are:

R, = Infant - 1400, Child - 3700, Teen - 8000, and Adult - 8000 m 3/ year;

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

DFIg, = Values used are taken fmm Tables E-7 through E-10 of RG 1.109.

C1.2.2 Annual Organ Dose From External Irradiation From Nuclides Deoosited On the Ground The organ dose from external irradiation from nuclides deposited on the ground was calculated using the equation:

O Dosej = IE+12 (8760) 6iSp Q(1 i

- e"h)DFG y where:

Dosej = the annual dose to the organ j, in mrem / year; 1E+12 = the number of pCi per Ci; 4 8760 = the number of hours in a year; 6i = 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 site boundary in the south sector - a distance of 1300 meters.);

Sp = 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; Ai = the radioactive decay constant of nuclide i, in day-3; tg = the time period over which the accumulation is evaluated, in days; Page 114 of 136

POINT BEACH NUCLEAR PLANT ODCM

, OFFSITE DOSE CALCULATION MANUAL l MAJOR j' Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 DFG g = the open field ground plane dose conversion factor for organ j from nuclide i, in mrem-m2/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:

Dose,i = 1E+12 (8760)gopS (1 - e"h)DFGy Qi At The values used in the equation above are:

l

6i = 31E-09 m-2 (This value taken from Table I.4-2 of the FSAR, release mode 1B, annual average, site boundary.);

i Sp = 1 (No stmetural shielding is assumed.);

ts = 5479 days (15 years);

DFG y = Values used are taken fmm Table E-6 of RG 1.109.

1 0

i i

I

i i

Page 115 of 136

1 l

1 l POINT BEACH NUCLEAR PLANT ODCM I OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 C1.2.3 Annual Orean Dose From Atmospherically Released Nuclides In Milk 1

The organ dose from atmospherically released nuclides in milk was '

calculated using the equation:

~

Dosep = 2.7E+09 U,Qp6 , { Q F,,DFI,e i ~*'4 {f,f, + e *'(1 - f,f,)}

i

, r(1-e-Ad.) B;,(1 - e *'\) l YA y gi Pl i where:

Dosej = the annual dose to the organ j of an individual in age group a j from a dietary intake of atmospherically released nuclides, in l mn:m/ year; 2.7E+ 09* = the number of pCi per Ci divided by the number of days per year; U, = the ingestion rate of milk for individuals in age gmup a, in liters / year; Qp = the amount of feed consumed by a cow per, in kg/ day; 6; = 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 animal location in the south-southeast sector - a distance of 1300 meters.);

Qi = the release rate of nuclide i, in Ci/ year; 1; = the radioactive decay constant of nuclide i, in dayd ;

t3 = the time period over which the accumulation is evaluated, in days; DFI ip = the dose conversion factor for the ingestion of nuclide i, organ j, and age group a, in mrem /pCi; F, i

= the average fraction of the animal's daily intake of nuclide i which appears in each liter of milk, in days / liter; tr = the average transpo;t time of the activity from the feed into the milk and to the receptor, in days; f, = the fraction of the year that the animals graze on pasture, dimensionless; f, = the fraction of the daily feed that is pasture grass when the animal gmzes on pasture, dimensionless; Page 116 of 136

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 r = the fraction of the deposited activity retained on crops, dimensionless; Ari = the effective removal rate constant for nuclide i from crops, in days-1, where Asi = Ai + A., and A, is the removal rate constant for physical loss by weathering; A. = 0.0504 day ;

t, = the time period that crops are exposed to contamination during the growing season, in days; Yv = the agricultural productivity, in kg (wet weight)/m2 ;

B;, = 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)/m2, For iodines, this factor is changed to 1.4E+09.

O l

l e

?

Page 117 of 136

. . _. .- - - _ ~ . - - . .. =_. ..

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 To calculate the dose per curie released, the equation above was rearranged and the calculation performed for each miclide. The rearranged equation is shown below: ,

~

U' = 2.7E+9 U,Qp6, FgDFl ije ***' {f,f, + e ~*'(1 - f pf,)}

~

n x r(1 - e -A '.)

B (1 - e **)

iy YA y g PA, The values used in the equation above are:

U, = Infant - 330, Child - 330, Teen - 400, and Adult - 310 liters / year; Qp = 50 kg/ day;

=

Si 18.8E-09 m-2 (This value taken from Table I.4-2 of the FSAR, release mode IB, grazing season, site boundary.);

Fim = Values used are taken from Table E-1 of RG 1.109; DFl ip = Values used are taken from Tables E-11 through E-14 of RG 1.109; tr = 2 days; f, = 0.5; f, = 0.5; r = 0.25,1.0 for iodines, and 0.20 for noble gases, tritium, and carbon-14; t, = 30 days; Yv = 0.7 kg/m2; B iy = Values used are taken from Table E-1 of RG 1.109; P = 240 kg/m2 ;

t3 = 5458 days (15 years).

Page 118 of 136

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL March 13,1996 C1.2.4 Annual Orean Dose From Atmospherically Released Nuclides In Meat The organ dose from atmospherically released nuclides in meat was calculated using the equation:

~

Dosep = 2.7E+9 U,Q,6, { QiuF DFIij e **** p{f f, + e *'(1 - f pf,)}

i x<

' (l - * $ ) + B ,(1 i - e'*A)

YAys PA, where:

Dosej, = 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; l U, = the ingestion rate of meat for individuals in age group a, in liters / year; j 1

Qg = the amount of feed consumed by a cow per, in kg/ day;

\-- Si = 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 animal location in the south-southeast sector - a distance of 1300 meters.);

Qi = the release rate of nuclide i, in Ci/ year; Ai = the radioactive decay constant of nuclide i, in day-!;

t3 = the time period over which the accumulation is evaluated, in days; DFl),i

= the dose conversion factor for the ingestion of nuclide i, ,

organ j, and age group a, in mrem /pCi; l Fg = the average fraction of the animal's daily intake of nuclide i which appears in each kilogram of flesh, in days /kg; t, = the average time from slaughter to consumption, in days; fp = the fraction of the year that the animals graze on pasture, dimensionless; f

\

f, = the fraction of the daily feed that is pasture grass when the animal grazes on pasture, dimensionless; Page 119 of 136 g qggg

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 r = the fraction of the deposited activity retained on crops, dimensionless; i

Asi = the effective removal rate constant for nuclide i from crops, in days , where Ag; = A; + .2 .,7 and 1, is the removal rate 4

constant for physical loss by wwhering; t, = the time period that crops are exposxl to contamination during the growing season, in days; Yv = the agricultural productivity, in kg (wet weight)/m2; B iy = the concentration factor for the uptake of nuclide i in

pathway p, expressed as the ratio of the concentration in biota 2 (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.

(h v

i O

Page 120 of 136

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 A

V 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:

C' = 2.7E+9 U,Q,6 3 PpFI,je ~* {f,f, + e #*8(1 - fpf,)f

~

X*

r(1 - e -^a'.) + B;,(1 - e *) "

t YAy ni PA, The values used in the equation above are:

U, = Infant - 0, Child - 41, Teen - 65, and Adult - 110 kg/ year; I l

! Qg = 50 kg/ day; j 6; =

18.8E-09 m-2 (This value taken from Table I.4-2 of the l FSAR, release mode IB, grazing season, site boundary.); l l Fri = Values used are taken from Table E-1 of RG 1.109; DFI;3, = Values used are taken from Tables E-11 through E-14 of RG 1.109; n l 4

U t, = 20 days; fp = 0.5; f, = 1.0; r = 0.25,1.0 for iodines, and 0.20 for noble gases, tritium, and 1

carbon-14; t, = 30 days; B, 3

= Values used are taken from Table E-1 of RG 1.109; 0.7 kg/m2;

=

Yv l 1

2 P = 240 kg/m ;

1, = 0.0504 day-!;

ts

= 5458 days (15 years).  !

O Page 121 of 136

POINT BEACH NUCLEAR PLANT ODCM  !

OFFSITE DOSE CALCULATION MANUAL l MAJOR l Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 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:

~

e -A'4 <

'(1 - e -Aa k) + B,,(1 - e *'4)'

Dosej - 2.7E+9 U,f,6, Qi DFI;3 -

where:

Dosej = the annual dose to the organ j of an individual in age group a from a dietary intake of atmospherically released nuclides, in i mrem / year;  !

2.7E+9* = the number of pCi per Ci divided by the number of days per year; 1

U, = the ingestion rate of produce for individuals in age group a, in j kg/ year; f, = fraction of produce ingested grown in garden of interest, dimensionless; I

6; = 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; A; = the radicactive decay constant of nuclide i, in day-1; 13 = the time period over which the accumulation is evaluated, in days; DFI;3 = the dose conversion factor for the ingestion of nuclide i, organ j, and age group a, in mrem /pCi;

, 1 3

= the holdup time that represents the time interval between haivest and consumption of the food, in days; r = the fraction of the deposited activity retained on crops, dimensionless; Agi = the effective removal rate constant for nuclide i from crops, in days-3, where Agi = A; + A., and A, is the removal rate constant for physical loss by weathering; t, = the time period that crops are exposed to contamination during the growing season, in days; Page 122 of 136

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 m

Yy = the agricultural productivity, in kg (wet weight)/m2 ;

B iy = 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)/m2, 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:

~

a l Dose"..

- 2.7E +9 U,f,6i { DFl e-2Aij < r(1-e -A k) + Bi ,(1 - e *h) - 1 Q, i Y yA .1 r PA i The values used in the equation above are: l l

U, = Infant - 0, Child - 520, Teen - 630, and Adult - 520 kg/ year; f, = 0.76; Si =

18.8E-09 m-2 (This value taken from Table I.4-2 of the FSAR, release mode IB, growing season, site boundary.);

j DFI;;, = Values used are taken from Tables E-11 through E-14 of RG 1.109;

13 = 60 days; r = 0.25,1.0 for iodines, and 0.20 for noble gases, tritium, and carbon-14;

A, = 0.0504 day-i; t, = 60 days; Yy = 0.7 kg/m2; B;, = Values used are taken from Table E-1 of RG 1.109; P = 240 kg/m2; ts

= 5458 days (15 years).

O Page 123 of 136

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 O

.V C1.2.6 Annual Organ Dose From Atmospherically Released Nuclides In Ieafy i Vegetables The organ dose from atmospherically released nuclides in leafy vegetables was calculated using the equation:

1 e B 3,, e Dosej - 2.7E+9 U,f i5, Qi DFIij eq,, r1 .

where. l l

Dosej = 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 ays per year; U, = the ingestion rate of produce for individuals in age group a, in l i year; j fi = fraction of leafy vegetables ingested grown in garden of 4

interest, dimensionless; i

6i = 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; Ai = the radioactive decay constant of nuclide i, in day ;

t3 = the time period over which the accumulation is evaluated, in days; )

DFIg, = the dose conversion factor for the ingestion of nuclide i, organ j, and age group a, in mrem /pCi; 13 = the holdup time that represents the time interval between harvest and consumption of the food, in days; r = the fraction of the deposited activity retained on crops, dimensionless; Ani = the effective removal rate constant for nuclide i from crops, in days , where Asi = Ai + A., and A, is the removal rate constant for physical loss by weathering; Page 124 of 136

I POINT BEACH NUCLEAR PLANT ODCM l OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT  ;

OFFSITE DOSE CALCULATION MANUAL January 26,1996  !

O l d t, = the time period that emps am exposed to contamination during ,

the growing season, in days;  !

l Yv = the agricultural productivity, in kg (wet weight)/m2 ; i B;, = the concentration factor for the uptake of nuclide i in pathway p, expressed as the ratio of the concentration in biota l (in pCi/kg) to the nuclide concentration in water (in pCi/ liter),

in liters /kg; i P = the effective surface density for soil, in kg (dry soil)/m2, )

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:

i Dose".-*

- 2.7E + 9 U,f i6, { DFI,j,e- AA < r(1-e -As h) + B,,(1 - e *h)' -

Q, i YA y g PA, The values used in the equation above are: ,

i U, = Infant - 0, Child - 26, Teen - 42, and Adult - 64 kg/ year; I I

fi = 1; 6i =

18.8E-09 m-2 (This value taken from Table I.4-2 of the FSAR, release mode 1B, growing season, site boundary.); ,

i DFI;;, = Values used are taken from Tables E-11 through E-14 of l RG 1.109; tn

= 1 day; r = 0.25,1.0 for iodines, and 0.20 for noble gases, tritium, and carbon-14; A, = 0.0504 day-3; t, = 60 days;

Yv = 0.7 kg/m2; B iy = Values used are taken from Table E-1 of RG 1.109; P = 240 kg/m2; ts

= 5458 days (15 years). l l

Page 125 of 136

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR ,

Revision 10 DRAFT )

OFFSITE DOSE CALCULATION MANUAL January 26,1996 )

4 G

' b C1.3 Atmospheric Release Dose Factors: Noble Gases The equations and values used to calculate the total dose factors for noble gases i 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 radionoclide is presented in Section 5, Table 5-1.

C1.3.1 Annual Gamma and Beta Air Dose From All Noble Gas Releases 1

The dose from the submersion of individuals in air containing noble gases was calculated using the equation:

DoseY or DoseP = 3.17E +04 1

<Q,[s Qi (DF[ or DF[)

1 1

i where:

DoseY or Dose 8 = the annual gamma and beta air dose, in mrad / year; l 3.17E+04 = the number of pCi/Ci divided by the number of sec/ year; x/Q = t.he annual average atmosphere dispersion factor, in sec/m3 (The location at which the dose was calculated was the site boundary in the south sector - a distance of 1270 meters.);

O d = the n: lease rate of nuclide i, in Ci/ year; Q3 DFT or DFf = the gamma and beta air dose factors for a uniform semi-infinite cloud of radionuclide i, in mrad-m 3/pCi-year.

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

Dose [ or Dose [ 'i

= 3.17E + 04 1

Qi (Qj (DF[ or DF[)

The values used in the equation above are:

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

I DFT or DFf = Values used are taken from Table B-1 of RG 1.109.

O Page 126 of 136

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 p

d 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:

r 3r 3 7

Dose = 3.17E +04 1.11S, [ Qi DF[ + [ Q,DFS, rQ>r n s ,

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 1 coefficients; j 1

Sp = the attenuation factor that accounts for the dose reduction due to shielding provided by residential stmetures, dimensionless; XQ/ = the annual average atmosphem 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; DFJ = the annual gamma air dose factor for a uniform semi-infinite cloud of nuclide i, in mrad-m3/pCi-year; DFS; = the beta skin dose factor for a semi-infinite cloud of nuclide i, 2

which includes the attenuation by 7 mg/cm of skin, in 3

mrem-m /pCi-year.

O a

Page 127 of 136

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 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:

r Dose' - 3.17E +04 1> (1.11 Sp DF[ + DFS,)

Qn <Qi The values used in the equation above are:

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

x/Q = 9.36E-07 seconds /m3 (This value taken from Table I.4-2 of the FSAR, release mode 1B, annual average, site boundary.);

DFT = Values used are taken from Table B-1 of RG 1.109; DFS; = Values used are taken from Table B-1 of RG 1.109.

C1.3.3 Annual Total Body Dose From All Noble Gas Releases The total body dose from the submersion of individuals in air containing noble gases was calculated using the equation:

o b Dose = 3.17E +04 S y 1 { Q DFB,

( Qs i i

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; )

Sg = the attenuation factor that accounts for the dose reduction due to shielding provided by residential stmetures, dimensionless; XQ/ = the annual average atmosphem dispersion factor, in sec/m3 (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; DFB3 = the total body dose factor for a uniform semi-infinite cloud of nuclide i, which includes the attenuation of 5 g/cm2 of tissue, in mrem-m3/pCi-year.

O Page 128 of 136 1

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT i

OFFSITE DOSE CALCULATION MANUAL January 26,1996 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:

r Dose' = 3.17E +04 S,1> DFB' Qn <Qs The values used in the equation above are:

Sp = 1 (No stmetural shielding is assumed.);

= 9.36E-07 seconds /m3 (This value taken fmm Table I.4-2 of x/Q the FSAR, release mode 1B, annual average, site boundary.);

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

O i l

O Page 129 of 136 l

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 O

APPENDIX D DERIVATION OF DILUTION FACTORS USING REGULATORY GUIDE 1.113 O

Page 136 of 136

1 POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 (3

V D1.0 LIOUID EFFLUENT DILUTION FACTOR CALCULATIONS Dl .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 ofImplementing 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. l 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 l l

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.

l l

(D U

I O

Page 131 of 136

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 i TABLE D-1 SURFACE DILUTION FACTORS LIQUID EFFLUENTS IN A LARGE LAKE Downstream Distance (meters) Plume Centerline Shoreline 10 8.81 20 8.81 s 30 8.81 4

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 1 700 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 C) 20000 30000 40000 14.0 16.1 17.7 24 20.1 18.7 50000 18.8 18.3

l. 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 500000 35.2 33.3 600000 37.8 36.0 700000 40.2 38.6 l 800000 42.6 41.0 4

900000 44.8 43.3 1000000 46.9 45.5 NOTE: These mlues mere calculated maing 6e equaaon descritalbe Secel n 5.2 of he PBNP FS4R and 6efrdtonsing ndues:

e, = 900 cal /sec z, = 0 meters e, = 2 cmVsec d = 10 mesers a = 12.2 cm/see h = 10 mesers y, = 152.3 mesers b = 3M meters and a discharge race of 42.2 mElsec.

Page 132 of 136

o o o Dilution Factor at Surface l@'r! l Liquid Effluents in a Large Lake  ! dm5!

m o e9 DF per Unit Release Rate k $0 1.0E+0 6 g ng s 5P 1.0E+05 h 'e"/s'e$ 2 cm 2ieec 2 u

• 12.2 c m / s e c . dT

~ Y ( s ) = 15 2.5 m m - Z(s) = 0 m i 1.0E+0 4 g l ; ll = 3. @

[ 2 b = 305 m $

_ Disc h stg e t i.. = 42.2 m"3/sec 3 1.0E+03 a a

m g

1.0E+0 2 g y= o

=7 o .

[ Plume Centerline _

1.0E+01 g .Sb 5

5*

a 1.0E+00 1.0E+01 1.0E+02 1.0E+03 1.0E+04 1.0E+ 05 1.0E+06  :

Downstream Distance (in meters)

Area source, width 305 m and height 10 m

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996  ;

Y DI.2 Dilution Factor Twelve Miles Downstream: Two Rivers Water Intake The dilution factor used at the Two Rivers water intake twelve miles downstrezm from PBNP included the factor of two described in Section DI.l. However, insead 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 '.o reach the Two Rivers water intake is not straight. In order to reach Two River , the water must flow southeast around Point Beach State Park, which juts into I2ke Michigan, and then curves back 90 degmes towards Two Rivers. As a result of this deviation from straight line flow, any part of the plume or possibly none of the l plume would impinge upon the intake structure. )

1 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 fiumes, one directed north and one directed south, and is modeled as a source that extends 1000 feet out into the lake from the shoreline.

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

2 x c, x x "y " h u where ey = lateral turbulent diffusion coefficient in cm 2/sec x = the downstream distance in cm u = current in cm/sec Substituting the values for cy , x, and u of 900 cm2 /sec,19308 m, and 12.2 cm/sec, respectively, into the equation yields O

(V Page 134 of 136

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 cm 2 2 x 900 19308 m x 100 '"

sec m i

12.2 **

o = = 168.8 meters 100 E m

2. At distances of 0.lo,0.20, etc., off the plume centerline, the dilution factor was calculated using the equation shown in Section 5.2 of the PBNP FSAR. The distar.ces 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 i 1

Fraction of Total Fraction of Equivalent Area Under the i t

Standard Distance Curve for

, Deviation (m) Interval Dilution Factor

0. I o 16.9 0.080 13.8 0.2o 33.8 0.080 14.0 0.3o 50.6 0.078 14.3 p/

s.. 0.4o 67.5 0.075 14.7 84.4 O.5o 0.072 15.2 0.60 101.3 0.068 15.8 0.70 118.1 0.065 16.6 0.8o 135.0 0.060 17.6 0.90 151.9 0.056 18.8 1.00 168.8 0.051 20.2 1.1o 185.6 0.046 21.9 1.20 202.5 0.042 23.9 1.30 219.4 0.037 26.3 1.40 236.3 0.032 29.2 1.50 253.2 0.028 32.6 1.75o 295.4 0.053 44.7 2.00 337.6 0.035 64.7 2.25o 379.8 0.021 98.4 2.5a 421.9 0.012 158.4 3.0a 506.3 0.010 482 Totals 1.00 O

Page 135 of 136

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996

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• It is assumed that the standard deviation of the radionuclide concentrations across the plume can be represented by a nonnal 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.la and 0.2o which  ;

also includes the area of the curve in the interval -0.1o and -0.20 1 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.

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POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 l

APPENDIX E Wisconsin Electric submittal to the United States Nuclear Regulatory Commission, dated October 8,1987 (VPNPD-87-430, NRC-87-104)

The submittal consists of the letter and two Attachments. Attachment II contains Appendices A - G.

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O wisconsin Electnc poe coumr 231 W MICHIGAN P o BOX 2046. MILWAUKEE.W153201 (414)277 2345

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VPNPD-87-430 NRC-87-104 October 8, 1987 U.S. NUCLEAR REGULATORY COMMISSION Document Control Desk Washington, D.C. 20555 Gentlemen: '

DOCKET NOS. 50-266 AND 50-301 '

RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION FOR 10 CFR 20.302 APPLICATION POINT BEACH NUCLEAR PLANT On July 14, 1987, Wisconsin Electric Power Company submitted an application, under the provisions of 10 CFR 20.302, for approval of a proposed procedure to dispose of sewage treatment sludge containing minute quantities of radioactive materials. Sub-sequent to the application, Mr. Ted Quay of the NRC staff requested additional information regarding the environmental characteristics of the area surrounding the Point Beach Nuclear Plant. The responses to this request were furnished in our submittal dated August 6, 1987.

By letter dated September 9, 1987, the NRC has requested Wisconsin Electric' supply additional information in order to complete the review of our application. This Request for Additional Information (RAI) contains ten specific items which require responses or commitments from Wisconsin Electric. In addition, the NRC requests the previously submitted information and the information supplied in response to the RAI be compiled into "one complete, extensive, and self-contained package".

To facilitate your review, Attachment I is included to provide direct responses to the ten items contained in the RAI.

Attachment II is provided as the complete application, including the information from our letters dated July 14, 1987, and August 6, 1987, and information supplied in response to the r NRC RAI.

, ( -

We request that you complete your review of this complete, self-contained package and issue an approval of our application E-2

NRC Document Control Desk

() October 8, 1987 Page 2 as soon as possible. In order to facilitate your review and to expedite processing, we would be pleased to discuss these matters or provide additional information by telephone. Please feel free to contact us.

Very truly yours, l

." 17 '

O;." 'N\

l-C. W. Fay Vice President Nuclear Power bjm j Attachments i Copies to NRC Resident Inspector NRC Regional Administrator, Region III Burstein, Charnoff, ,

,() BlindcopiestoBritt/Gorske/FinkeINewton,Zach Fay, Krieser, LbpKe o

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- ATTACHHENT I 4

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RESPONSES TO QUESTIONS CONTAINED IN THE REQUEST FOR ADDITIONAL INFORMATION (RAl) 4 ON POINT BEACH 1 AND 2 REQUEST FOR DISPOSAL OF LOW LEVEL RADIOACTIVITY I

CONTAMINATED SEWAGE SLUDGE BY LAND APPLICATION

' WISCONSIN ELECTRIC POWER COMPANY l 4 UNDER 10 CFR 20.302(a) l i

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I The ~ numbering system used in these responses corresponds directly to numbering used in the NRC RAI, dated September 9, 1987.

1. a. This request is for multiple applications, approximately 2 to 4 per year.

b. This request is for multiple years, . expiration to coincide with conclusion of decommissioning activities associated with retirement of PBNP Units 1 & 2.

c. Please refer to the response to question number 10.

2. The pathways used to determine doses to both the maximally exposed individual and the inadvertent intruder are documented in Attachment II, Appendices D and E.

Due to the extremely low concentrations of radionuclides in the sewage sludge and the associate low doses, Wisconsin Electric will control access to the disposal sites by conditions of use defined in lease agreements with the lease. Use of the land is not controlled beyond the conditions of the lease, thereby not restraining a casual visitor from the disposal site. However continuous occupancy would be readily observed, and remedial action would be taken. -

3. Information contained in previous submittals has been included in Attachment II with modifications to provide specific commitments to the NRC.

4. Please refer to the response to question number 10.

O 5. Site maps have been updated and are included in Attachment II, i V Appendix C. j l

6. The direct grazing of cattle on the proposed disposal sites is controlled by restrictions contained in the lease agreement.

There vill be no restrictions placed on fishermen on Lake Michigan. l Calculations of doses due to all pathways associated with a release '

to Lake Michigan (Attachment II, Appendix E) do not indicate a need

. to apply restrictions to fishermen.

7. Please refer to revised site maps included in Attachment II, Appendix C. Site number 5 is located on company owned land beyond the PBNP site boundary. All other sites are within the PBNP site boundary area.

8. a. Please refer to Attachment II, Section 3.2, Disposal Procedure.

b. Please refer to Attachment II, Section 3.2, Disposal Procedure.

c. Please refer to Attachment II, Section 3.2, Disposal Procedure.

d. Please refer to Attachment II, Appendix A.

9. Please refer to Attachment II, including Appendix D and Appendix E for additional pathways analyzed for this submittal. These identified pathways will be analyzed prior to all subsequent disposals to insure doses are maintained within prescribed limits, i.e. ,1 arem/ year to the

{ maximally exposed individual and 5 arem/ year to the inadvertent A intruder.

V

10. A limiting concentration level for the sludge contained in the storage tank is discussed, in Attachment II, Appendix F. Since this application is for multiple applications over multiple years, Attachment II, Appendix F also addresses an activity limit.

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3 ATTACHMENT II l

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COMPLETE ANALYSIS AND EVALUATION l -

I POINT BEACH NUCLEAR PLANT i

! 10 CFR 20.302(a) APPLICATION i

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, 1.0 Purpose By this submittal Wisconsin Electric Power Company requests approval of the U.S. Nuclear Regulatory Commission for a proposed procedure to dispose of sewage treatment sludge containing trace quantities of radionuclides generated at the Point Beach Nuclear Plant. This request is submitted in accordance with the provisions of 10 CFR 20.302(a).

2.0 Waste Description The waste involved in this disposal process consists of the residual solids remaining in solution upon completion of the aerobic digestion sewage treat-

ment process utilized at PBNP. The PBNP sewage treatment plant is used to i

process waste water from the plant sanitary and potable water systems.

These systems produce non radioactive waste streams with the possible

' exception of wash basins located in the radiologically controlled area of the plant. These wash basins are believed to be the primary source of the t

extremely small quantities of radionuclides in the sludge.

j The sewage sludge generated at PBNP is allowed to accumulate in the sewage 1

plant riigestor and aeration basin. Two to four times annually, depending .

l on work activities and corresponding work force at PBNP, the volume of

• l the sludge in the digestor and aeration basin needs to be reduced to allow continued efficient operation of the treatment facility. The total volume i of sludge removed'during each disposal operation is typically on the order

} 'y .

of 15,000 gallons. The maximum capacity for the entire PBNP treatment  !

facility and hence the maximum disposal volume is about 30,000 gallons.  !

I l In the case of a maximum capacity disposal, doses would not necessarily '

i increase in proportion to the volume, since more than one disposal site may be used.

Trace amounts of radionuclides have been identified in PBNP sludge currently being stored awaiting disposal. The radionuclides identified and their concentrations in the sludge are summarized below:  !

Nuclide Concentration (pCi/cc)

Co-60 2.33E-07 Cs-137 1.50E-07 The total activity of the radionuclides in the stored sludge, based on the identified concentrations and a total volume of 15,000 gallons of sewage sludge, are as follows:

Nuclide Activity (pCi)

Co-60 13.2 Cs-137 8.5 These concentrations and activities are consistent with expected values

,O based on prior analyses of sewage sludge. The radionuclide concentration in the sewage sludge has remained relatively constant during sampling conducted since December 30, 1983.' A detailed summary of the results of this sampling program are contained in Appendix A for your review.

E-7

l O In addition to monitoring for the radionuclide content of the sludge, the WDNR requires several other physical and chemical properties of the sludge to be determined. These properties are the percent total solids, percent total nitrogen, percent ammonium nitrogen, pH, percent total phosphorus, percent total potassium, cadmium, copper, lead, nickel, mercury, zinc, and boron. An example of a typical sludge sample analysis is included in Appendix B.

3.0 Disposal Method In the context of this application, Wisconsin Electric commits to the following methodology. No distinction is made or intended between "shall" or "will", as used in the descriptions contained in this section.

3.1 Transport of Sludge The method used to dispose of the sludge shall utilize a technique approved by the WDNR. ' The process of transporting the rewage sludge for disposal involves pumping the sludge from the PBNP sewage treatment plant storage tanks into a truck mounted tank. The truck mounted tank shall be required to be maintained tightly closed to prevent spillage while in transit to the disposal site. The sludge shall be transported to one or more of the six sites approved by the WDNR for land application of the sewage sludge from PBNP.

( 3.2 Disposal Procedure The radionuclide concentrations in the sludge shall be determined prior to each disposal by obtaining three representative samples from each of_the sludge storage tanks. The sludge contained in the sludge tanks is prevented from going septic by a process known as complete mix and continuous aeration. This process completely mixes the sludge allowing for representative samples to be obtained.

The samples shall be counted utilizing a GeLi detector and multi-channel analyzer with appropriate geometry. The detection system is routinely calibrated and checked to ensure the lower limits of detection are within values specified in the Radiological Effluent Technical Specifications (RETS).

To insure t'he samples are representative of the overall concentration in the storage tanks, the radionuclide concentration determination for each of the three samples shall be analyzed to insure each sample is within two standard deviations of the average value of the three samples. If this criteria is not met, additional samples will be obtained and analyzed to insure a truly representative radionuclide concentration is utilized for dose calculations and concentration limit determinations. The average of all statistically valid concentration determinations will be utilized in determining the storage tank concentration values.

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Prior to disposal the waste stream will be monitored to determine the physical and chemical properties of the sludge, as discussed in the last paragraph of Section 2.0, Waste Description. The results will be compared to State of Wisconsin limits to insure the sludge does not pose a chemical hazard to people or to the environment.

The radionuclides identified in the sludge, along with their respective concentrations, will be compared to concentration limits prior to disposal. The methodology discussed in Appendix F will be used in determining compliance with the proposed concentration limit. The total activity of the proposed disposal will be compared to the proposed activity limit as described in Appendix F.

If the concentration and activity limit criteria are met, .the appropriate exposure pathways (as described in Appendix D) will be evaluated prior to each application of sludge. These exposures will be evaluated to insure the dose to the maximally exposed individual will be maintained less than 1 mrem / year and the dose to the inadvertent intruder is maintained less than 5 mrem / year. The exposures will be calculated utilizing the meth-odology used in Appendix E, including the current activity to be landspread along with the activity from all prior disposal. The remaining radio-activity from 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 release to Lake Michigan. The residual radio-activity will be corrected for radiological decay and, if appropriate, the mixing of the radionuclides in the soil by plowing prior to performing O external exposure calculations.

The sewage sludge is applied on the designated area of land utilizing the WDNR approved technique and adhering to the following requirements of WPDES Permit Number WI-0000957-3.

• Discharge to the land disposal system shall be limited so that during surface spreading all of the sludge and any precipitation falling onto or flowing onto the disposal field shall not overflow the peri-meter of the system.

• Sludge shall not be land spread on land with a slope greater than 12%. !

During the period from December 15 through March 31 sludge shall not be land spread on land with a slope greater than 6% unless the wastes are injected ismediately into the soil. l

• Sludge shall not be surface spread closer than 500 feet from the nearest inhabited dwelling except that this distance may be reduced with the dwelling owner's written consent.

• Sludge shall not be spread closer than 1,000 feet from a public water supply well or 250 feet from a private water supply well.

• Sludge shall not be land spread within 200 feet of any surface water unless a vegetative buffer strip is maintained between the surface watercourse and the land spreading system, in which case a minimum separation distance of at least 100 feet is required between the system and the surface watercourse.

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Depth to groundwater and bedrock shall be greater than 3 feet f rom the land surface elevation during use of any site.

i Sludge shall not be land spread in a floodway.

l Sludge shall not be land spread within 50 feet of e property line road l or ditch unless the sludge is incorporated with the soil, in which i case a minimum separation distance of at least 25 feet is required.  !

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The pH of the sludge-soil mixture shall be maintained at 6.5 or higher. l i

Low areas of the approved fields, subject to seasonally high ground-

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i water levels, are excluded from the sludge application.

Crops for human consumption shall not be grown on the land for up to j j one year following the application of the sludge. 4

{ The sludge shall be plowed, disked, injected or otherwise incorporated

, into the surface soil layer at appropriate intervals. l l

The flexibility implied in the latter provision for soil incorporation is i intended to allow for crops which require more than a one year cycle.

For the Point Beach disposal sites, alfalfa is a common crop which is harvested for several years after a single. planting. Sludge disposal on an alfalfa plot constitutes good fertilization, but the plot cannot be plowed without destroying the crop. The alfalfa in this case aids in binding the layer of sluoge on the surface of the plot. At a minimum, l 7'

however, plowing (or disking or other method of injection and mixing to  ;

a nominal depth of 6 inches) shall be done prior to planting any new crop, regardless of the crop.

3.3 Administrative Procedures Complete records of each disposal will be maintained. These records will include the concentration of radionuclides in the sludge, the total volume of sludge disposed, the total activity, the plot on which the sludge was applied, the results of the chemical composition detenninations, and all dose calculations.

The annual disposal rate for each of the approved land spread sites will be limited to 4,000 gallons / acre, provided WDNR chemical composi-tion, NRC dose guidelines, and concentration and activity limits are maintained within the appropriate values.

The farmer leasing the site used for the disposal will be notified of the applicable restrictions placed on the site due to the land spreading of sewage sludge.

4.0 Evaluation of Environmental Impact 4.1 Site Characteristics 4.1.1 Site Topography The disposal sites are located in the Town of Two Creeks in the northeast corner of Manitowoc County, Wisconsin, on the E-10

de=t so ii #t8 t er the t aer er ' * "ichis O center of the city of Green Bay, and 90 miles NNE of Milwaukee.

This site is located at longitude 87* 32.5'W and latitude 44*

17.0'N. The six sites are on property owned and controlled by Wisconsin Electric and are within or directly adjacent to the Point Beach site soundary. The sites are described below and are outlined on the map contained in Appendix C as Figure 3.

Site No. PB The approximately 15 acres located in the NE 4

1/4 of the NE 1/4 of Section 23, T. 21N - R. 24E.

Site No. PB The approximately 20 acres located in the SE 1/4 of the SE 1/4 of Section 14, T. 21N - R. 24E.

1 i Site No. PB The approximately 5 acres located in the NW

1/4 of Section 24, T. 21N - R. 24E.

Site No. PB The approximately 5 acres located in the NW -

1/4 of the SW 1/4 of Section 24, T. 21N - R. 24E.

l i Site No. PB The approximately 5 acres located in the NE i

1/4 of the NW 1/4 of Section 25, T. 21N - R. 24E.

Site No. PB The approximately 5 acres located in the NE 1/4 of the SW 1/4 of Section 14, T. 21N - R. 24E.

The overall ground surface at the site of the Point Beach Nuclear Plant is gently rolling to flat with elevations varying from Subdued knob 5 to 60 feet above the level of Lake Michigan. The and kettle topography is visible from aerial photographs.

land surface slopes gradually toward the lake from the higher glacial moraine areas west of the site. Higher ground adjacent to the lake, however, diverts the drainage to the north and south.

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The major surface drainage features are two small creeks which One creek discharges into the drain to the north and south.

' lake about 1500 feet above the northern corner During of theponds the spring, site and the other near the center of the site.

of water may occupy the shallow depressions. As mentioned in Section 3.2, Disposal Procedure, these low areas are excluded I i

4 from the sludge application.

A site topographic map covering details out'to a 5 mile radius 4

may be found in the FSAR at Figure 2.2-3 and is included in Appendix C as Figure 2.

The disposal of sewage sludge at these six sites will have no impact on the topography of this area.

4.1.2 Site Geoloqy p

! :( Prior to construction of the Point Beach Nuclear Plant, an

' evaluation of the geological characteristics of the area in and surrounding the site was made. The geologic structure of the region is essentially simple. Gently dipping sedimentary rock E-11

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l lO strata of Paleozoic age outcrop in a horseshoe pattern around a shield of Precambrian crystalline rock which occupies theThe s I western part of the region. flank of the Michigan The Basin, whic J

by discontinuous outcrops The of rocks more resistant forl form a '

sandstones with subordinate shale layers. succession o

' The bedrock strata dip very gently towards Lake thickness.

Michigan at rates from 15 to 35 feet per mile.

l The uppermost bedreck under the site is Niagara The soils contain expansive clay l till and lake deposits.

j minerals and have moderately high base exchange capacity.

In the area of the site, the Although overburden soils areofapproximately the character the .

l 70 to 100 feet.in thickness.

glacial deposits may vary greatly within relatively short i

distances, a generalized section through th

! sequence:

1. An upper layer of brown clay silt topsoil underlain with' several feet of brown silty clay with layers of silty sand;

2. A layer of 20 feet of reddish-brown silty clay with some j , sanct and gravel and occasional lenses of silt; j

I 3. A layer of 25 feet of reddish-brown silty clay with layers

of silty sand and lenses of silt; l

j 4. A layer of 50 feet of reddish-brown silty clay with some

[ sand and gravel, the lower portion of which contains

[ gravels, cobbles, and boulders resting on a glacial eroded

! surface of Niagara dolomite bedrock.

l i Site drainage is poor due to the high clay content of the soilA l combined with the pock-marked surface.on site geolog The use of these sites for disposal of sewage sludge will not impact the geology of the area.

4.2 Area Characteristics _

4.2.1 Meteorology The climate of the site region is influenced States and by those which move northeastward from the south-This conti-O western part of the country to the Great Lakes.

nental type of climate is modified by Lake Michigan.

During spring, summer, and fall months the lake temperature differs markedly from the air temperature.to easterly directions p E-12

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!* t temperatures in spring and summer. In autumn the relatively

' warm water to the lake prevents night-time temperatures from falling as low as they do a few miles inland from the shoreline.

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Summer time temperatures exceed 90'F for six days on the

average. Freezing temperatures occur 147 days and below zero j on 14 days of the winter on the average. Rainfall averages t about 28 inches per year with 55 percent falling in the months

of May through September. Snowfall averages about 45 inches per year. Sludge spreading shall be managed such that the l surface spreading together with any precipitation falling on j the field shall not overflow the perimeter of the field.

Additional information on site meteorology may be found in Section 2.6 of the FSAR.

l Th2re will be no impact on the meteorology of the area due to the disposal of the sewage sludge.

i j 4.2.2 Hydroloqy ,

l The dominant hydrological feature of this site is Lake Michigan, l one of the largest of the Great Lakes. The normal water level 1 in Lake Michigan is approximately 580 feet above mean sea level.

In the general vicinity of the site, the 30 foot depth contour is between 1 and 1-1/2 miles offshore and the 60 foot contour is 3 to 3-1/2 miles off shore. The disposal sites are twenty or more feet above the normal lake level. There is no record

.O that the sites have been flooded by the lake during modern

' times. There are no rivers or large streams which could create a flood hazard at or near the sites.

The subsurface water table at the Point Beach site has a definite slope eastward toward the lake. The gradient indi-cated by test drilling on the site is approximately 30 feet per mile. It is therefore extremely unlikely that any release of radioactivity on the site could spread inland. Furthermore, the rate of subsurface flow is small due to the relative impervious nature of the soil and will not promote the spread af releases. Further information on site hydrology is detailed in the PBNP FSAR Section 2.5.

There will be no adverse impact on hydrology of the area due to disposal of sewage sludge by land spreading.

l 4.3 Water Usage i I

4.3.1 Surface Water i Lake Michigan is used as the source of potable water supplies in the vicinity of the site for the cities of Two Rivers (12 miles south), Manitowoc (16 miles sourth), Sheboygan (40 miles south), and Green Bay (intake at Rostok 1 mile north of Kewaunee, 13 miles north). No other potable water uses are recorded O within 50 miles of the site along the lake shore. All public j

i water supplies drawn from Lake Michigan are treated in puri- i fication plants. The nearest surface water used for drinking other than Lake Michigan are the Fox River 30 miles NW and E-13

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Lake Winnebago 40 miles W of the site.

iO Lake Michigan is also utilized by various recreational activities, including fishing, swimming and boating.

1 j There will be no impact on surface water usage due to the j disposal of sewage sludge.

4.3.2 Ground Water i

l Ground water provides the remaining population with potable

! supplies. Public ground water supplies within a 20 mile radius

of the site are listed 'in Table 2.5-3 of the FSAR. Additional j wells for private use are in existence throughout'the region. .

j The location of private wells within a two mile radius of PBNP l are indicated on Figure 3, Appendix C.  !

l The potable water for use at the Point Beach Nuclear Plant is .

drawn from a 257 feet deep well located at the southwest corner i

of the plant yard. Water from this well is routinely sampled

! as part of the environmental monitoring program.

i l There will be no adverse impact on ground water usage due to

( the disposal of sewage sludge.

i i 4.4 Land Usage ji Manitowoc County, in which the site is located, and the adjacent 1 i counties of Kewaunee, Brown, Calumet, and Sheboygan are predominantly l rural. Agricultural pursuits account for approximately 90% of the

total county acreage. With the exception of the Kewaunee Nuclear l Plant located 4.5 miles north, the region within a radius of five l

l. miles of the site is presently devoted exclusively to agriculture.

. Dairy products and livestock account for 85% of the counties' farm

production, with field crops and vegetables accounting for most of

! the remainder. The principal crops are grain corn, silage corn, j oats, barley, hay, potatoes, green peas, lima beans, snap beans, '

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beets, cabbage, sweet corn, cucumbers, and cranberries. Within the

township of Two Creeks surrounding the site (15 sq. miles), there

are about 800 producing cows on about 40 dairy farms. Some beef

! cattle are raised 2.5 miles north of the site. Cows are on pasture from the first of June to late September or early October. During j the winter, cows are fed on locally produced hay and silage. Of the

milk produced in this area, about 25 percent is consumed as fluid l milk and 50 percent is converted to cheese, with the remainder being i used -in butter. making and other by products.

It has been the policy of Wisconsin Electric to permit the controlled i use of crop land and pasture land on company owned property. No

direct grazing of dairy or beef cattle or other animals is permitted 4 on these company owned properties. Crops inter.ded for human consump-tion shall not be grown on the dispo' sal sites for at least one year

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following the application of the sludge.

'The proposed land application of sewage sludge will not have any

! direct effect on the adjacent facilities. Additional land use l E-14 j T

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7 information may be found in Section 2.4 of the FSAR.

(V 4.5 Radiolocical Impact The rate of sewage sludge application on each of the six proposed sites will be monitored to insure doses are maintained within applic-able limits. These limits are based on NRC Nuclear Reactor Regulation (NRR) staff proposed guidance (described in AIF/NESP-037, August, 1986). These limits require doses to the maximally exposed member of the general public to be maintained less than 1 mrem / year due to the disposal material. In addition, NRR guidance requires doses of less than 5 mrem / year to an inadvertent intruder.

To assess the doses received by the maximally exposed individual and i the inadvertent intruder, six credible pathways have been identified l for the maximally exposed individual and four credible pathways for i the inadvertent intruder. The identified credible pathways are described in Appendix D. l Calculations detailed in Appendix E demonstrate the disposal of the l currently stored PBNP sewage sludge would remain below these limits. l The total annual exposure to the maximally exposed individual based on the identified exposure pathways is equal to 0.072 arem. The dose to a hypothetical intruder assuming an overly conservative  ;

occupancy factor of 100% is calculated to be 0.115 arem/ year. By )

definition, the inadvertent intruder would not be exposed to the l O

processed food pathways (meat and milk).

l The calculational methodology used in determining doses for the i proposed disposal of sludge stored at PBNP shall be utilized prior to

< each additional land application to insure doses are maintained less i than those proposed by NRR. This calculation will include radio-nuclides 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 radio-i nuclides, and all pathways associated with a potential release to Lake Michigan. The residual radioactivity will be corrected for radio-logical decay and, if applicable, the mixing of radionuclides in the soil prior to performing external exposure calculations. In addition, the dose to a farmer potentially leasing more than one application site will be addressed by summing the doses received from the external j exposure from a ground plane source and resuspension inhalation pathways for each leased site. In addition, the maximum site specific dose due to the other pathways identified in Appendix D, will be utilized in the total exposure estimation.

i j 5.0 Radiation Protection The disposal operation will follow the applicable PBNP procedures to maintain doses as low as reasonably achievable. Technical review and guidance will be provided by the PBNP Superintendent - Health Physics.

E-15

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! APPENDIX A i

i 1

i d

1

SUMMARY

OF RADIOLOGICAL ANALYSES i

0F SEWAGE SLUDGE SINCE DECEMBER 30, 1983 I

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Sample Tank Tank Radionuclide Concentration Date Volume (Gallons) (pCi/cc)

12-30-83 Digester 8400 Co-58 5.58E-07 Co-60 1.87E-06 Cr-51 4.88E-07 i Cs-134 1.59E-07 j Cs-137 3.57E-07 4-06-84 Digester 7560 Co-60 7.89E-07 Aeration 6667 Co-60 1.87E-07

$ 12-05-84 Digester 7560 Co-58 1.75E-07

Aeration 6667 Co-60 8.29E.07 l 6-03-85' Digester 7560 Co-60 8.29E-07

Cs-137 2.46E-07 i Aeration 6700 Co-60 3.27E-07 i Cs-137 1.33E-07 1

4-10-86 Digester 7560 Co-60 6.79E-07 l P.

i L

Cs-137 1.72E-07 .

Mn-54 4.91E-08

! Co-60 1.65E-07

! l

11-04-86 Digester 7560 Co-58 8.04E-08 j . Aeration &

. Clarifier 25100 Co-58 1.37E-07

Co-60 2.18E-07 l Cs-137 1.64E-07 l .

1 O

E-17

>* 4 s

a O

APPENDIX B 1

CHEMICAL COMPOSITION ANALYSIS OF SEWAGE SLUDGE ,

O O

E-18

l' - 'T^TE 8' * * " * ' "

ospaatuawT or mAv'**aAa. v asson cas SLUDGE CHARACTERISTIC

f Wisconsin Statute 147.02(1) and

- Wisconsin Administrative Code NR 110.77(6) g comu adeo.as may,so4o i

twage Treatment Plant Sludge 4

! . sense complete this forra and send tg the Department of Notwel Resources appropriate District / Area office. Keep one copy for

} vow records. *

& additional forms, pteene sentaca vow appropriste Distries/ Area office.

l .

wroEs pumm T mwmeEm 1 esmuiTTEx

! Wisconsin Electric Power Co=pany WI 00 L .E 2 .L I.

j' ETREETOAAOUTE COWPfT Y 231 W. .vichican Street Milwaukee l

CITY,eTATE. ElP CODE TELZPMONE MvueEm OMCA.uDE AREA CODEJ j

, 511vnuh.'c. YT 53203 .na-277-2153 i

l f ' 1. Pleses report laboratory meting results for the following parameters:

3 1

I i *Peremeter Abbreviation Result *Peremeter Abbreviation Result Total Solids, % - I0' Owomium, ppm Cr TOT N I0 Cu 2200 Total Nitrogen, % Cbpper, ppm NH - N 0.34 190

{ ,

Ammonium Nitrogen, E Land, , Pb i

' O 01 3*0 l

Toast Phosphorow,% 'P Wrewy, , Hg Totel Potassium,% . K 0.25 Ni 32 l

Nickel, ppm 1*0 D 2300 Arsenic. ppm A8 M8 p Cd I2* pH -

IO Cedmium. ppm

• Suppested erstysis procedures for the abow parameters een he found in NR 219, onetytieel sets and prosedwes, Wisconsin

• Administrative Code. AE parameters other then percent solids and pH she!! be reported on a dry weight besla.

2. what is the nome of we laboremry that did the analysis end when ws: it performed? .

Lahoremry Name Wisconsin Electric Power Co. Dem serit e April 12, 1933 Laboratory Services Division ,

where et the treatment plant was the empts sken? re ". 310 :S hCiding'tSnh prfor to h:U1in2

- .when was the semple uken? Avril 12, 1953 DATE

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APPENDIX C 4

SITE MAPS

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APPENDIX D EXPOSURE PATHWAYS ,

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E-24

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l I. EXPOSURE PATHWAYS - MAXIMALLY EXPOSED INDIVIDUAL

, 1. External whole body ex;iosure due to a ground plane source of l

radionuclides.

i

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

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

4. Vegetable ingestion pathway from vegetables grown on plot.

5. Inhalation of radioactivity resuspended in air above application j site.

~

6. Pathways associated with a release to Lake Michigan. Ingestion of

' potable water at Two Rivers, Wisconsin municipal water supply, i

ingestion of fish from edge of initial mixing zone of radionuclide release, ingestion of fresh and stored vegetables irrigated with

water source as Lake Michigan, ingestion of milk and meat from l cows utilizing Lake Michigan as drinking water source, swimming i and boating activities at edge of initial mixing zone, and shoreline

, deposits. .

~

i II. EXPOSURE PATHWAYS - INADVERTENT INTRUDER

1. External whole body exposure due to a ground plane source of rad,ionuclides.

2. Vegetable ingestion pathway from vegetables grown ca plot.

3. Inhalation of radioactivity resuspen'ed d in air above application l site.

4. Pathways associated with a release to Lake Michigan. Ingestion of potable water at 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 source as Lake Michigan, ingestion of milk and meat from cows utilizing Lake Michigan as drinking water source, swimming and boating activities at edge of initial mixing zone, and shoreline deposits.

The milk and meat pathways are not included in calculating the dose to the inadvertent intruder. The doses due to these pathways are calculated based on feeding the cows alfalfa grown on the sludge applied land. Since direct grazing on these lands is prohibited, the alfalfa sust be cropped prior to being used as feed. This effectively removes the availability of Oc these pathways to the inadvertent intruder, who by definition occupies the sludge applied land continuously.

E-25

III. GROUNO WATER PATHWAY O The ingestion of groundwater is not a credible exposure pathway. The two factors contributing to this determination are as follows:

1. The site map in Appendix C, Figure 3 details the spatial relation-ship between the proposed disposal sites and the local ground water wells. The flow gradient of ground water was determined for the ,

PBNP FSAR to be towards Lake Michigan. Reviewing the sitas and local wells shows no private well located in the path of radionuclide migration towards Lake Michigan.

l The PBNP site well is located.on the plant site, po'tentially in a l path of radionuclide migration. The PBNP well is routinely sampled as a requirement of the PBNP environmental sonitoring program.

l

2. The cation exchange capacity (CEC) of the soils at each site has been determined.

l Site ' Cation Exchange Capacity (MEQ/100a) 1 16 2 11 3 11 4 10 5 8 i

6 9 . I The cation exchange capacity of. soil is dependent on the valance of the radionuclides and is determined by the relation:

MEQ = ATOMIC VALANCE N

• 1.0E-03 Radionuclide Valance CEC (MEQ/1000) i I

3.00E-02 Co-60 +2 Co-58 +2 2.90E-02  !

Cs-137 +1 1.37E-01 Mn-54 +2 2.70E-02 Cr-51 +3 1.70E-02 Cs-134 +1 1.34E-01 Using the values for Cs-137 and site 5 which has the lowest CEC, the ,

total exchange capacity of the soil is

~

1.10 grams of Cs-137 100 grams of soil Calculating the specific activity of Cs-137, Specific Activity =

3.578E+05 ,3.578E+05 30 137 kO ,

T1/2(yrs.) ATOMIC MASS

= 87.1 Ci/ gram E-26

j The cation exchange capacity of the soil expressed in the number

of Curies of radionuclide per 100 grams of soil is 95.8 C1 Cs-137 i

100 grams of soil Since the proposed disposal of sewage sludge contains quantities of radionuclides on the order of 10-100 pCi the soil at each site has the capacity to effectively eliminate the migration of the radionuclide to ground water.

i

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l 4

\O E-27

1 l

l i

l O

APPENDIX E 1

EXPOSURE ANALYSIS a

1 4

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4 6

O E-28

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d 2

O GENERAL ASSUMPTIONS i

1. Sewage sludge is uniformly applied over plot acreage.

i

2. Sewage sludge is applied to one of the 5 acre plots, site PB-03, PB-04, PB-05, or PB-06. (Assuming the smallest site size is 1 conservative for the calculation methodology herein.)

3. Based on the sawage sludge currently stored at PSNP, the following i, data is used in the calculations.

Ground Plane Studge Volume Activity Concentration Concentration j

s Radionuclide (Gallons) (cm3) (uti) (pCi/cm3) (pCi/cm2)

Co-60 15,000 5.68E+07 11.2 2.33E-07 6'53E-08 q Cs-137 15,000 5.68E+07 E.5 1.50E-07 4.21E-08

! 1. CALCULATION OF EXTERNAL EXPOSURES 1

A. Specific Assumptions

O 1. Conser tiveix asse e r eio et4 ity re ains on surface of iand 9,et.

Calculation ignores any plowing or mixing of radioactivity within j' soil. Calculations for the proposed disposal will therefore ignore

! self absorption or shielding from soil.

The external exposure at the application site due to prior disposals

will be calculated utilizing the methodology in Appendix G and added to that calculated for the proposed disposal.

2. The plots are owned by Wisconsin Electric and have been approved by the Wisconsin Department of Natural Resources (ONR) as disposal sites. The land is leased and potentially farved. Occupancy of the land can be realistically expected only during plowing, planting and harvesting. Occupancy has been astimated to be 64 hours7.407407e-4 days <br />0.0178 hours <br />1.058201e-4 weeks <br />2.4352e-5 months <br /> per year.

B. Summary of Calculational Methodology '

. 1. Caiculate ground plane radionuclide concentrations in pCi/cm2,

2. The dose from a plane of uniformly deposited radionuclides is calculated using Regulatory Guide f.'IO9, Revision 1, Appendi.* C, Formula C-2. ,

3. Dose rates were calculated assuming continuous occupancy then adjusted for realistic occupancy factors.

E-29 -

l

. l a

O l C. External Exposure Rate Calculations The dose from a plane of uniformly deposited radionuclides is calculated using Regulatory Guide 1.109, Revision 1, Appendix C, formula C-2

! Dj(r,6)=8760Sp}Cf(r,6)DFG) y

where 4

l D (r,0) = yearly dose 8760 = hours per year Sp = 1.0, since no dose reduction due to residential j

shielding is applicable.

C (r,0) = ground plane radionuclide concentration (pCi/s.2)

DFG(i,j) = external dose factor for standing on contaminated ground

as given in Table E-6 of Regulatory Guide 1.109, i Revision 1.

Ground Plane Ground Plane y Dose 4 y Dose Factor Concentration Concentration Rate .

Radionuclide (ares /hr per pCi/m2) (pCi/cm2) (DCi/m2) (arem/yr) l Co-60 1.70E-08 6.53E-08 6.53E+02 9.72E-02

Cs-137 4.20E-09 4.21E-08 4.21E+02 1.55E-02 l TOTAL: 1.13E-01 ares / year I These calculated dose rates assume continuous occupancy. In reality, these sites will be occupied only during plowing, planting, and harvesting.

Assuming an occupancy of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> per day, I day per week, and 32 weeks (8 l

month growing season) per year, the occupancy factor becomes l 2 hr/ day

• 1 day / week

• 32 weeks /yr

• 1/8760 hours /yr = 7.3E-03.

EXTERNAL EXPOSURE DOSE RATE (arem/ year) 4 Radionuclide Continuous Occupancy Realistic Occupancy

. Co-60 9.72E-02 7.10E-04 1

Cs-137 1.55E-02 1.13E-04 TOTAL: 1.13E-01 8.23E-04

!o l E-30

i

O

, II. CALCULATION OF MEAT AND MILK INGESTION PATHWAY EXPOSURES l A. Specific Assumptions

. 1. All feed consumed by cow is grown on sludge applied acreage.  !

2. All meat and milk consumed by human is from cattle exclusively fed feed from sludge applied land.

3. are utilized fr m Stable Regulatoryelement transfer Guide 1.109 coefficients to estimate the f (B,fa)ction of radioactivity which is transferred from the soil to the feed.

I

, Radionuclide iv Co-60 9.4E-03 l Cs-137 1.0E-02

4. Alfalfa has typically been grown on the plots. Soil tests have indi-cated a minimum alfalfa yield of 4.1 tons per acre can be expected.

B. Summary of Calculational Methodology

1. The concentration of radionuclides in feed grown on the disposal )

. plot- is estimated. Transfer coefficients (B from Table E-1 of 1 l s Regulatory Guide 1.109 were used to estimate tN) fraction of radio-l l nuclide which may be expected to transfer to the feed from the soil. j i 2. Concentrations of radionuclides in milk and meat were estimated i psing Formula A-11 from Regulatory Guide 1.109.

1 j 3. Ingestion dose rates were estimated using Formula A-12 from

Regulatory Guide 1.109.

i C. Milk and Meat Ingestion Pathway Dose Rate Calculation

1. Concentration in feedc *

! Activity in Feed = B gy

• Activity in Soil Concentration in Feed = Activity in Feed /(kg of Feed

• 5 Acres)

I Radionuclide Activity in Activity in Concentration in l Radionuclide Soil (uti) Feed (uti) Feed (pCi/kg)

L Co-60 13.2 1.24E-01 6.67E+00 Cs-137 8.5 8.50E-02 4.57E+00

2. Concentration in Milk and Heat Calculate concentrations of radionuclides in milk and meat using E-31

i

~

l 1

!O '

1 Formula A-11 in Regulatory Guide 1.109, Revision 1 which is

! C94 ,FiA *C gp Qp j where Cgg = radionuclide concentration of i in component A F stable element transfer coefficient whose values are in gg = Table E-1 of the Regulatory Guide C

gp == radionuclide concentration in feed Qp consumption rate of feed = 50 kg/d (wet weight) from Regulatory Guide 1.109 l Use the following Regulatory Guide 1.109 values for F iA Element F94=, (d/1) for milk F 3 cf (d/kg) for meat

Co 1.0E-03 1.3E-02

Cs 1.2E-02 4.0E-03 Concentration in Concentration in I Radionuclide Milk (pCi/1) Meat (pCi/ko) ,

Co-60 3.34E-01 4.34E+00 Cs-137 2.74E+00 9.14E-01

3. Calculated Dose rates 1

i The fo mula for total dose from eating animal products fed vegeta-tion (alfalfa) grown on PBNP sludge applied land is given by i

Regulatory Guide 1.109, Revision 1, Fornula A-12, page 1.109-16.

. But, as noted following equation A-13, it is necessary to compute

separately the milk and meat portions of the dose. '

i DOSE = I(U,p*D g ,pg*exp(-A gst ))

where U = consumption rate of animal product i

' C $ ==conc of radionuclide i in animal product A dose factor D *P9 = average time between milking or slaughtering and tf consumption U,, by Age Group

, Infant Child Teenager Adult Milk (1/yr) 330 330 400 310 Heat (kg/yr) -

41 65 110 C gg = concentration calculated above Og *P9 = DF whole body dose factors, Regulatory Guide 1.109,

,O, Revision 1.

E-32

i lO Whole Body Dose Factors (arem/pci Incested) i

. Infant Child Teenager Adult Ingestion Ingestion Ingestion Ingestion i

Nuclide i Co-60 2.55E-05 1.56E-05 6.33E-06 4.72E-06 Cs-137 4.33E-05 4. 62E-05 5.19E-05 7.14E-05 T = 0 for milk (assume consumption on fars)  !

J s = 20 days for meat (Regulatory Guide 1.109, Revision 1, Table E-15) 1 MILK INGESTION DOSE RATE (mrem / year) 1 Radionuclice Infant Child Teenacer Adult l Co-60 2.81E-03 1.72E-03 8.46E-04 4.89E-04 , i Cs-137 3.92E-02 4.18E-02 5.69E-02 6.06E-02 4.20E-02 4.35E-02 5.77E-02 6.11E-02 )

! TOTALS:

i MEAT INGESTION DOSE RATE (ares / year)

' \ -

Radionuclide Infant Child Teenager Adult Co-60 -

2.76E-03 1.77E-03 2.24E-03 4

Cs-137 -

1.73E-03 3.08E-03 7.18E-03 j

4.49E-03 4.85E-03 9.42E-03

)

TOTALS:

2 MEAT AND MILK INGESTION PATHWAY DOSE RATES (arem/ year)

Infant - 4.20E-02

! Child - 4.'80E-02 i l 1 Teenager - 6.26E-02 1

Adult - 7.05E-02 I

4 III. CALCULATION OF VEGETABLE INGESTION PATHWAY EXPOSURES A. Soecific Assumptions

1. The WPDES permit issued to PBNP'for the disposal of sewage 4 sludge prohibits the growing of crops for human consumption for one year following the application of the sewage sludge.

" Therefore, prior to planting vegetables on the application site, the soil would be plowed. ~ Plowing is assumed to uni-formly six the top 6 inches of soil.

i E-33

. _ - . - . - . - . - - - - . . . . . . ~ .- . - - - - . - . . _ - - _ - _ _

i

? 2. The soil density is assumed to be 1.3 grams /cm2

! 3. All vegetables consumed by the individual of interest are l I grown on the sludge applied acreage.

' 4. Stable 1.109areusedtoestimatethefra,l)ionofradio-from Guide element transfer coefficients (B Regulatory t

activity transfered from the soil to the vegetables.

O Radionuclide iv Co-60 9.4E-03 Cs-137 1. 0E-02

5. The consumption factors of food medium (U 8 and the mass basis distributions from Regulatory Guide 1.109,P)able T E-5 are used to determine annual consumption of vegetables. ,,

I U,,by Age Group

• Infant Child Teen Adult l l

280 kg/yr 340 kg/yr 280 kg/yr ,

• Based on 54% vegetable consumption by mass of fruit, vegetable, and grain.

6. The Ingestion Dose Factors by age group are from Regulatory Guide 1.109, Tables E-11, E-12. E-13, and E-14.

Whole Body Incestion Oose Factors (arem/pti incested)

Radionuclide Infant Child Teen Adult Co-60 2.55E-05 1.56E-05 6.'33 E-06 4.72E-06 Cs-137 4.33E-05 4.62E-05 5.19E-05 7.14E-05

7. Radiological decay of the radionuclides applied tu the plot is not taken into account in these calculations. ,

B. Suwnary of Calculational Methodology

1. The radionuclide concentration in t'he soil is calculated in units of pCi/kg based on uniform application ove:r 5 acre plot, plowing to a depth of 6 inches, and a soil density of 1.3 g/cm3

2. values are applied to the soil concentration values to O The obtain B4 ,the radionuclide concentration in the vegetables.

3. The consumption factors (U for each age group are then used . I todeterminetheannualra$i)nuclideintakebyagegroupdue o l to eating these vegetables. l E-34

I v 4. Finally, the age dependent ingestion dose factors are used to obtain annual doses by age group.

C. Vegetable Pathway Ingestion Dose Rate Calculations

1. Concentration in soil

)

Concentration Activity Soil Volume Soil Mass In Soil Radionuclide Applied (uci) (cm3) (kg) ,

(pCi/kg)

Co-60 13.2 3.08E+09 4.00E+06' 3.30E+00 Cs-137 8.5 3.08E+09 4.00E+06 2.13E+00

2. Concentration in vegetables Concentration Concentration In In Vegetables Radionuclide Soil (pCi/kg) B iv (DCi/kg)

Co-60 3.30E+00 9.4E-03 3.10E-02 Cs-137 2.13E+00 1.0E-02 2.13E-02

3. Calculated Dose Rates The dose rate for direct ingestion of vegetables grown on the sludge applied land is given by the equation. l OOSE RATE = I U,p *gO ,p)

• EXP (-A g t)

• C g  !

where U = consumption ate of food medium D*E Al"P3==dosefactorforradionuclide,i radiological decay constant t = time between harvest and consumption Cy = concentration of radionuclide, i, in food medium.

t, the time between harvest and ingestion, is assumed to be zero for this calculation.

VEGETABLE INGESTION DOSE RATE (arem/ year)

Radionuclide Infant Child Teen Adult Co-60 -

1.35E-04 6.67E-05 4.10E-05 l

Cs-137 -

2.76E-04 3.76E-04 4.26E-04 TOTAL -

4.11E-04 4.43E-04 4.67E-04 E-35

O IV. CALCULATION OF INHALATION OF RESUSPENDED RADIONUCLIOES PATHWAY EXPOSURE A. Specific Assumptions

1. The model used to determine the radionuclide concentration in air above the sludge applied land is taken from WASH-1400, USNRC, Reactor Safety Study - An Assessment of Accident Risks in Commercial Nuclear Power Plants, Appendix VI.

2. The radionuclide concentration in air remains constant for year of interest, i.e., radiological decay and decrease in resuspension factor are not taken into account for this calculation. ,

{ 3. The maximally exposed member of the general public is assumed -

to be the farmer using the plot of land with an occupancy of l 64 hours7.407407e-4 days <br />0.0178 hours <br />1.058201e-4 weeks <br />2.4352e-5 months <br /> per year.

4. The inadvertent intruder is assumed to occupy the plot of j land for the entire year.

! 5. The Inhalation Dose Factors by age group are from Regulatory I

Guide 1.109. Tables E-7, E-8, E-9, and E-10.

1 -O f1 wu0tr 800v IasAtATIO oosE rAct0as <mreme Ci in*aied)

, ~

Radionuclide Infant Child Teen Adult

~

! Cc60 8.41E-06 6.12E-06 2. 48E-06 1.85E-06 l Cs-137 3.25E-05 3.47E-05 3.89E-05 5.35E-05 i

b LUNG INHALATION DOSE FACTORS (arem/pci inhaled) i' i Radionuclide Infant _ Child Teen Adult Co-60 3.22E-03 1.91E-03 1.09E-03 7.46E-04 l Cs-137 5.09E-05 2.81E-05 1.51E-05 9.40E-06 i

6. The age dependent inhalation rates are obtained from Regulatory Guide 1.109, Table E-5. l Inhalation Rates (m3/yr) ,

Infant Child Teen Adult

1. -

1400 3700 8000 8000 1 .

E-36

i B. Summary of Calculational Methodology

1. The ground plane radionuclide concentrations in pCi/m2

2. Calculate the resuspension factor utilizing equation given

in WASH-1400.

3. Obtain the radionuclide concentration in air (pCi/m3) above 3

plot utilizing methodology in WASH-1400.

1 4. Using parameters contained in Regulatory Guide 1.109, calculate annual dose for continuous occupancy and'for realistic, occupancy.

C. Inhalation of Resuspended Radionuclides in Air Pathway Dose Rate l Calculations - Resuspension of Radionuclide in Air

1. Ground plane radionuclide concentration Ground Plane . Ground Plane .

Radionuclide Concentration (uCi/cm2) Concentration (pCi/m2)

Co-60 6.53E-08 6.53E+02 Cs-137 4.21E-08 4.21E+02 ,

2. Calculation of resuspension factor, K (m )

From WASH-1400, K(t) = 1.0E-09 + 1.0E-05

• EXP [-0.6769

• t]

where t = time since radionuclides were deposited on ground surface.

t is assumed to be 0 for these calculations, thereby maximizing the resuspension factor.

Therefore, K = 1.0E-05 m'

3. Calculate radionuclide concentration (pCi/m3) in air.

From WASH-1400, l

.2

(" )

• airsurface concentration (DCi/ 2) deposit (pCi/m2) or '

.2  ;

Air Concentration (pCi/m3) = surface deposit (pCi/m2)

• K(m )

AIR CONCENTRATIONS Radionuclide Air Concentrations (pCi/m3)

Co-60 6.53E-03 Cs-137 4.21E-03 E-37

!q d

4. Oose Rate Calculations i

Dose Rate (ares /yr) = Inhalation Rate (m3/yr)

• Air Conc. (pCi/m2)

• i Dose Conversion Factor (ares /pCf) 4 J

WHOLE BODY INHALATION DOSE RATE (arem/ year) i f

Radionuclide Infant Child Teen Adult i Co-60 7.69E-05 1.48E-04 1. 30E-04 9.66E-05 Cs-137 1.92E-04 5.41E-04 1.31E-03 1.80E-03 4

TOTAL 2.69E-04 6.89E-04 1.44E-03 1.90E-03 LUNG INHALATION DOSE RATE (ares / year)

Radionuclide Infant Child Teen Adul t Co-60 2.94E-02 4. 61E-02 5.69E-02 3.90E-02

! . Cs-137 3.00E-04 4.38E-04 5.09E-04 3.17E-04 TOTAL 2.97E-02 4.65E-02 5.74E-02 3.93E-02 i

l' 1 INHALATION OF RESUSPENDED RADIONUCLIDES IN AIR DOSE RATES WHOLE BODY DOSE RATE (ares / year) 4 i Octupancy Infant Child Teen Adult '

Continuous 2. 69E-04 6.89E-04 1.44E-03 1.90E-03 -

! Realistic 1.96E-06 5.03E-06 1.05E-05 ' 1.39E-05

LUNG DOSE RATE (area / year)

Occupancy Infant Child Teen ' Adult f

continuous 2.97E-02 4.65E-02 5.74E-02 3.93E-02 Realistic 2.17E-04 3.39E-04 4.19E-04 2.87E-04 V. CALCULATION OF WHOLE BODY EXPOSURES DUE TO RELEASE TO L XE MICHIGAN A. Specific Assumptions

1. The methodology contained in the PBNP Offsite Dose Calculation Manual (00CM) is used to perform this calculation.

E-38 l

I l

/

4 o 2. The entire activity contained in the sludge is released into i-Late Michigan.

l The exposure pathways addressed by the ODCM methodology are

3. )

ingestion of potable water from Two Rivers, WI water supply, ,

I ingestion of fish at edge of initial mixing zone, ingestion of fresh and stored vegetables, irrigated with Lake Michigan as source of water, ingestion of milk and meat from cows utilizing

Lake Michigan as drinking water source, swining and boating  !

' - activities at edge of initial mixing zone, and shoreline deposits.

, B. Summary of Calculational Methodology

! 1. The activity released in the sludge is converted into -

Co-60 dose equivalent Curies.

The annual design release limit from the 00CM is 94.7 Co-60 l 2.

equivalent curies.

J

$ 3. The annual design release limit is based on a limiting dose

• of 6 mres adult whole body. The annual dose due to sewage

• sludge is calculated by a ratio of calculated release compared l to release limit.

,O C. w~oie seev E esure Caicuiations

1. Co-60 equivalent Curies Activity Co-60'eq.

DFi /DF Co-60 J Radionuclide (pCi) Activity (uci) 1.00E+00 13.2 l l Co-60 13.2 Cs-137 8.5 1.51E+01 128.4 3

TOTAL 141.6pCi Co-60 l

4 equivalent i 2. Ratio of dose limit to annual design release limit 6 mres

.1

- 94.7 Co-60 equivalent curies ,

^

3. Whole Body Dose Calculation Dose = 6 mrem 141.6pci 94.7x10*pCi Dose = 8.97E-06 mres

!O ~

WHOLE B00Y DOSE RATE (mrem / year)

E-39

DOSE St#HARY ,

Maximally Exposed Individual The identified credible exposure pathways for the maximally exposed individual are:

1.) External exposure froe ground plane source (realistic occupancy) 2.) Milk ingestion pathway 3.) Meat ingestion pathway 4.) Vegetable ingestion pathway 5.) Resuspension inhalation pathway (realistic occupancy)

6. ) Pathways identified due to release to Lake Michigan.

AGE GROUP Pathway Infant Child Teen Adult External 8.23E-04 8.23E-04 8.23E-04 8.23E-04 Milk 4.20E-02 4.35E-02 5.77E-02 6.11E-02 Meat -

4.49E-03 4.85E-03 9.42E-03 Vegetable -

4.11E-04 4.43E-04 4.67E-04 Inhalation 1.96E-06 5.03E-06 1.05E-05 1.39E-05 Water ,

8.97E-06 8.97E-06 8.97E-06 8.97E-06 TOTAL: 0.043 0.049 0.064 0.072 (area / year) ,

I_nadvertent Intruder The identified credible exposure pathways for the inadvertent intruder are:

9 1.) External exposure from ground plane source (continuous occupancy) 2.) Vegetable ingestion pathway 3.) Resuspension inhalation pathway (continuous occupancy) 4.) Pathways identified due to release to Lake Michigan.

AGE GROUP ,

Pathway Infant Child Teen Adult External 1.13E-01 1.13E-01 1.13E-01 1.13E-01 Vegetable -

4.11E-04 4.43E-04 4.67E-04 Inhalation 2.96E-04 6.89E-04 1.44E-03 1.90E-03

. Water 8.97E-06 8.97E-06 8.97E-06 8.97E-06 TOTAL: 0.113 0.114 0.115 0.115 (area / year)

Reviewing these tables, the calculated limiting doses for both the maximally exposed individual and the inadvertent intruder occur for the adult age group.

These doses are:

Maximally Exposed Individual: 0.072 arem/ year Inadvertent Intruder: 0.115 ares / year E-40

~a. . --..-#..m......, _ .. . . . , ,. _.

i

• i *. ,

i l

lO i APPENDIX F i -

i i

BASIS FOR SETTING CONCENTRATION LIMITS AND ACTIVITY LIMIT

FOR DISPOSAL OF SLUDGE i

i j

O -

9 4

-O E-41

i

!O Analyses of previously disposed sewage sludge have identified six different radionuclides in the sludge. All six radionuclides did not occur in each disposal. Therefore, it is difficult to determine a single concentration limit for regulating the disposal of the sludge from the storage tanks.

1

) To provide a basis to regulate the disposal of the sewage sludge based on

}

identified radionuclide concentrations, the following relation is proposed.

l N C, l j[1 01 ^ mpg 1 1 where N = number of different radionuclides identified in the sewage sludge.

! C 9

= concentration of the ith radionuclide in the sewage sludge. -

! MPC, = the MPC value of the ith radionuclide in the sewage sludge, as listed in 10 CFR Part 20 Appendix B Table II, Column 2.

If this criteria is net, the sewage sludge say be disposed of by land spread-l ing provided the dose calculations (as identified in Appendix E) indicate .

dose rates within the prescribed limits.

j

' The attachment to this Appendix details calculations performed to determine

~

doses from four radionuclides identified in the sludge. The calculations are based on an identified concentration equal to 10% of the 10 CFR Part 20,

. The calculations use the methodology

' Appendix B, Table II, Column 2 valves.

in Appendix E along with the exposure pathways identified in Appendix D to

- determine the dose rates. These calculations indicate the use of this l methedology will maintain radiation doses within the appropriate limits.

l The maximum allowable activity disposed of per year per acre is calculated

' utilizing 10% of the MPC value,10 CFR Part 20, Appendix B, Table II, Column 2, for Co-58. Volume limit per acre has been proposed at 4,000 gallons / acre / year.

Then, l

1.0E-05 pCi/cc

• 4,000 gallons / acre / year x 3.785.43 cc/ gallon

! = 151.4 pC1/ acre / year ,

e o -

l 1

l E-42

i 4

!O

U Cs-134

! Concentration in Sludge: 9.0E-07 aci/ml a

Sludge Volume Concentration Activity Ground Plane l (cm2) (pCi/cm3) (uct) Concentration (uci/cm2)

! (Gallons) 15000 5.68E+07 9.00E-07 5.11E+01 2.53E-07 i

j External Exposure y Dose Factor Ground Plane Concentratien y Dose Rate (mrem /hr. per pCi/m2) (pci/m2) (arem/ year) 1.20E-08 2.53E+03 2.66E-01 Continuous Occupancy: 2.66E-01 ares / year Realistic Occupancy: 1.94E-03 aren/ year Meat & Milk Pathway ,

Activity in Activity in Concentration in Concentration in Concentration.in

' e cac*a) ai'* cac>> a t cac4'*a)

O seii <=ci) '

• cuci) 2.75E+01 1.65E+01 5.50E+00

.. b.22E+01 5.11E-01 Milk Dose Rates (arem/ year)

Infant Child Teenager Adult 3.87E-01 4.41E-01 6.03E-01 6.19E-01 Meat Dosa Rate (ares / year) -

Infant Child Teenager Adult

- 1.83E-02 3. 27E-02 7.32E-02 Vegetable Pathway Ac.tivity Soil Volume Soil Mass Concentration Concentration (Kg) in Soil (pci/Kg) in Vegetables (pCi/Kg)

(pci) (Cm2) 3.08E+09 4.00E+06 1.28E+01 1.28E-01 5.11E+01

O E-43

. . - . . - - - . . - - - - . . . . . - . - _ - - - - - ~ _ _ . . _ . . _ _ _ . . -

i i

\

.v Vecetable Pathway Dose Rates (ares / year)

}

l Infant Child Teenager Adult 2.90E-03 3.98E-03 4.34E-03 i

Inhalation Pathway

i. Ground Plane K Air Concentration >

! Concentration (DCi/m2) (m"i) (pci/m3)

)

4 2.53E+03 1. 0E-05 2.53E-02 -

I Inhalation Pathway Dose Rates (area / year)

! Infant Child Teenacer Aoult Continuous occupancy 1.88E-03 5.68E-03 1.39E-02 1.84E-02 l Realistic Occupancy 1.38E-05 4.15E-05 1.01E-04 1.35E-04 l

Release to Lake Michican i

Activity DFjj0FCo-60 Co-60 eq. activity (uci) (uci) ,

5.11E+01 2.56E+01 1.31E+03 b<.

6 mrem , 1.31E+03 1 Ci = 8.29E-05 ares

, 94.7 C1 1.0E+06 pC).

i l Maximally Exposed Individual Infant Child Teenacer Adult i

i External 1.94E-03 1.94E-03 1.94E.-03 1.94E-03

Milk 3.87E-01 4.41E-01 6.03E-01 6.19E-01 i Meat -

1.83E-02 3.27E-02 7.32E-02 Vegetable -

2.90E-03 3.98E-03 4.34E-03

Inhalation 1.38E-05 4.15E-05 1.01E-04 1.35E-04

~

Water 8.29E-05 8.29E-05 8J9E-05 8.29E-05 i Totals: 3.89E-01 4.64E-01 6.42E-01 6.99E-01 0 .

Inadvertent Intruder Infant Child Teenager Adult

External 2.66E-01 2.66E-01 2.66E 01 2.66E-01 l '

) Vegetable Inhalation

1. 88E-03 2.90E-03 5.68E-03

3. 98E-03 1.39E-02 4.34E-03 1.84E-02

' Water 8.29E-05 8.29E-05 8.29E-05 8.29E-05 i .

j Totals: 2.68E-01 2.75E-01 2.84E-01 2.89E-01 E-44

l 1

l 1

~O i Cs-137 l

Concentration in Sludge: 2.0E-06 pCi/m1  !

Sludge Volume Concentration Activity Ground Plane (Gallons) (cm3) (uci/cm3) (pC1) Concentration (pCi/cm2) 15000 5.68E+07 2.00E-06 1.14E+02 5.62E-07 4

External Exposure y Dose Factor -

Ground Plane Concentration y Dose Rate (mrem /hr. per pCi/m2) (pC1/m2) (ares / year) 4.20E-09 5.62E+03 2.07E-01 Continuous occupancy: 2.07E-01 area / year Realistic Occupancy: 1.51E-03 area / year 1

Heat & Milk Pathway Activity in Activity in Concentration in Concentration in Concentration in O.: Soil (pci) Feed (pCi) Feed (pCi/Ko) Milk (pCi/1) Meat (pci/ko) l 1.14E+02 1.14E+00 6.13E+01 3.68E+01 1.23E+01 Milk Dose Rates (mren/ year)

Infant Child Teenacer Adult 5.26E-00 5.61E-01' 7.64E-01 8.15E-01 Meat Dese Rate (ares / year)

Infant Child Teenacer _Adul t 2.33E-02 4.15E-02 f.56E-02 Vegetable Pathwey Activity Soil Volume Soil Mass Concentration Concentration (pCi) (Cm3) (Ko) in Soil (pCi/Ko) in Vegetables (pCi/Kg)

I 1.14E+02 3.08E+09 4.00E+06 2.85E+01 2.85E-01 E-45

[ Vegetable Pathway Dose Rates (arem/ year) i Infant _ Child Teenager Adult l -

3.69E-03 5.03E-03 5.70E-03

i I Inhalation Pathway Ground Plane K -

Air Concentration j Concentration (pCi/m2) (m" ) (pCi/m3) -

! 5.62E+03 1.0E-05 5.62E-02 i

Irihalation Pathway Dose Rates (ares / year) j i

Infant Child Teenager Adult i Continuous occupancy 2.56E-03 7.22E-03 1.75E-02 2.41E-02 j Realistic Occupancy 1.87E-05 5.27E-05 1.28E-04 1.76E-04~

Release to Lake Michigan i

Activity DFj /0F Co-60 eq. activity Co-60 3 (uci) (uti) .

! 1.14E+02 1.51E+01 1.72E+03 l

O 6 arem 1.72E+03 I Ci j 94.7 C1 1.0E+06 pC1 = 1.09E-04 mrem l ,

Maximally Exposed Individual i

Infant Child Teenacer -

Adult External 1.51E-03 1.51E-03 1.51E-03 1.51E-03 Milk 5.26E-01 5.61E-01 7. 64E-01 8.15E-01 Meat -

2.33E-02 4.15E-02 5.70E-03

Vegetable -

3.69E-03 5.03E-03 5.70E-03

Innalation .1.87E-05 5.27E-05 1. 28E-04 1.76E-04 Water 1.09E-04 1. 09E-04 1.09E-04 1.09E-04  !

f Totals: 5. 28E-01 5.90E-01 8.12E-01 9.19E-01 l Inadvertent Intruder

{ Infant Child Teenager Adult 4

External 2.07E-01 2.07E-01 2.07E-01 2.07E-01 Vegetable -

3.69E-03 5.03E-03 iO

)

l; i

2=a i ti #

Water 2 55s-o3 1.09E-04 7 22s-o3 1.09E-04 1 75t-o2 1.09E-04 5.70E-03 2 415-o2 1.09E-04 Totals: 2.10E-01 2.18E-01 2.30E 2.37E-01 j E-46

l l 1

0 Co-58 Concentration in Sludge: 1.00E-05 pCi/ml Sludge Volume Concentration Activity Ground Plane (Gallons) (em3) (pCi/cm3) (pCi) Concentration (uci/cm2) 15000 5.68E+07 1.00E-05 5.68E+02 2.81E-06 External Exposure y Oose Factor Ground Plane Concentration y Dose Rate (arem/hr. per pCi/m2) (pCi/m2) (mrem / year) 7.00E-09 2.81E+C4 1.72E+00 Continuous Occupancy: '1.72E+00 aren/ year Realistic Occupancy: 1.26E-02 aren/ year Meat & Milk Pathway Activity in Activity in Concentration in Concentration in Concentration Meat (pCi/kg) in O Soil (pci) Feed (pci) Feed (pCi/Kg) Milk (pCi/1) 1.44E+01 1.87E+02

. 5.68E+02 5.34E+00 2.87E+02 Milk Dose Rates (ares / year) 1 Infant Child Teenager Adult 4.27E-02 2.62E-02 1.29E-02 7.45E-03 Meat Oose Rate (aree/ year) -

Infant Child Teenager Adult 4.22E-02 2.72E-02 3.44E-02 Vegetable Pathway Activity Soil Volume Soil Mass Concentration Concentration (Kg) in Soil (pCi/Kp) in Vegetables (pCi/Kg)

(uti) (Cm3) 5.68E+02 3.08E+09 4.0rE+06 1.42E-04 1.33E+00 E-47

-_. . . - ~ . -- .- . --._ _ . .- . -- . . . . - . - . - - - .

1 i

Yeaetable Pathway Dose Rates (arem/ year)

Infant Child Teenacer Adult

$:O 2.05E-03 1.01E-03 6.22E-04

! i l Inhalation Pathway Ground Plane K j Air Concentration i

Concentration (DCi/m2) (m' ) , (DCi/m3) 2.81E+04 1.0E-05 2.81E-01 4

Inhalation Pathway Dose Rates (ares / year) 4 Infant Child Teenacer Adult' 4

i Continuous Occupancy 5.11E-04 8.89E-04 '

7.80E-04 5.82E-04

! Realistic Occupancy- 3.74E-06 6.49E-06 i

5.70E-06 4.25E-06 t

i Release to Lake Michican j Activity 0Fj /DF Co-60 eq. activity (uci) Co-60 (uci) 1 j

5.68E+02 3.54E-01 2.01E+02 t j

6 mrem, a 2.01E+02 pCi . 1 Ci 94.7 C1 1.0E+06 pC1. = 1.27E-05 arem i

i Maximally Exposed Individual Infant Child Teenager Adult i

1 External 1.26E-02 1.26E-02 Milk 1.26E-02 1.26E-02 4.27E-02 2.62E-02 1.29E-02 7.45E-03 Heat -

4.22E-02

! Vegetable -

2.72E-02 3.44E-02 i

2.05E-03 1.01E-03 6.22E-04 Inhalation.~ 3.74E-06 6.49E-06 5.70E-06 4.25E-06 j Water 1.27E-05 i 1.27E-05 1.27E-05 1.27E-05 i

Totals: 5.53E-02 8.31E-02 5.37E-02 5.51E-02  !

Inadvertent Intruder -

~

i Infant _ Child Teenager Adult i

External 1.72E+00 1.72E+00

Vegetable -

1.72E+00 1.72E+00 2.05E-03 1.01E-03 6.22E-04 Inbalation 5.11E-04 8. 89E-04 7.80E-04 5.82E-04 Water 1.27E-05 1.27E-05 1.27E-05 1.27E-05 4

Totals: 1.72E+00 1.72E+00 1.72E+00 1.72E+00 E-48

Co-60 .

Concentration in Sludge: 5.0E-06 pCi/ml i

Sludge Volume Concentration Activity Ground Plane

(Gallons) (cm2) (uct/cm2) (pC1)

Concentration (uci/cm2) 15000 5.68E+07 5.00E-06 '2.84E402 1.41E-06

{ External Exposure y Dose Factor Ground Plane Concentration y Dose Rate (mrem /hr. per pCi/m2) (cCi/m2) (ares / year) 1.70E-08 1.41E+04 2.09E+00 Continuous Occupancy: 2.09E+00 aren/ year Realistic Occupancy: 1.53E-02 aren/ year i

Meat & Milk Pathway . .

3 Activity in Activity in Concentration in Concentration in Concentration in j Soil (pC1) Feed (pC1) _ Feed (pCi/Ko) Milk (pC1/1) Meat (pCi/ko) i 2. 84 E+02 2.67E+00 1.44E+02 7.18E+00 9.33E+01 4

Milk Oose Rates (ares / year)

Infant Child Teenager Adult 6.04E-02 3.70E-02 1.82E-02 1.05E-02 Meat Oose Rate (area / year)

Infant Child Teenagar Adult 5.97E-02 3.84E-02 4.84E-02 Vegetable Pathway l Activity Sofi Volume Soil Mass Concentration Concentration (uti) (Cm2) (Ka) in Soil (pci/Ko) in Vegetables (pci/Ko) 2.84E+02 3.08E+09 4.00E+06 7.10E+01 6.67E-01 1 E-49

f

, ]

Vecetable Pathway Oose Rates (arem/ year)

C Infant Child Teenager Adult 2.91E-03 1.44E-03 8.82E-04 Inhalation Pathway Ground Plane K Air Concentration Concentration (pci/m2) (m" ) (pci/m3) 1.41E+04 1.0E-05 1.41E-01 Inhalation Pathway Dose Rates (ares / year) l Infant Child Teenager Adult Continuous Occupancy 1.66E-03 3.19E-03 2. 80E-03 2.09E-03  :

Realistic Occupancy 1.21E-05 2.33E-05 2.05E-05 1.53E-05 )

Release to Lake Michican  !

Activity DFg /DF Co-60 o-60 eq. acd y ny (pC1) (pC1)

O ~ ,

l 6 mrem , 2.84E+02pti .. 1 Ci 94.7 C1 1.0E+06 pC1

. = 1.80E-05 arem Maximally Exposed Individual Infant Child Teenacer Adult External 1.53E-02 1.53E-02 1.53E-02 1.53E-O' Milk 6.04E-02 3.70E-02 1.82E-02 1.05E-02 Meat -

5.97E-02 3.84E-02 4.84E-02 Vegetable -

2.91E-03. 1.44E-03 8. 82E-04 Inhalation 1.21E-05 2.33E-05 2.05E-05 1.53E-05 Water 1.80E-05 1.80E-05 1.80E-05 1.80E-05 Totals: 7.57E-02 1.15E-01 7.34E-02 7.51E-02 Inadverteni ntruder Infant Child Teenager Acult Extcrnal 2.09E+00 2.09E+00 2.09E+00 2.09E+00 O

v a t i- -

2.915-o' 1.445-o> a azt-o*

Inhalation 1.66E-03 3.19E-03 2.80E-03 2.09E-03 Water 1.80E-05 1.80E-05 1.80E-03 1.80E-03 Totals: 2.09E+00 2.10E+00 2.10E+00 2.'09E+00 E-50

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APPENDIX G CALCULATIONAL METHODOLOGY FOR DETERMINING EXTERNAL DOSE RATES FROM RADIONUCLIOES AFTER INCORPORATION INTO SOIL O

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lO Wisconsin Electric utilizes QAD, a nationally recognized computer code, to

! perform shielding and dose rate analyses. The QAD computer code utilizes a

point kernel methodology to calculat.e the dose rate at a specified point

! due to a given source of radiation.

! QAD will be used to calculate the dose rate due to standing on a plot of land

^

utilized for sludge disposal after the radionuclides have been incorporated

into the plot by plowing. The following parameters will be used in the calculation

The total activity from all previous disposals will be corrected for radiological decay and used as the radio-

nuclide source term, t

Appropriate values will be used to represent the surface

! area of the plot. '

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• The radionuclides will be assumed to be incorporated uniformly into the top six inches of soil.

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• The dose rate will be calculated at a height of 1 meter 4 above the ground plane at a depth of 5 centimeters in  !

! tissue. (Regulatory Guide 1.109 values).

• The density of the soil vill be assumed to be 1.3 grams /

. cubic centimeter.

l This calculated dose rate will be used to assess the radiological consequences

of past disposals in conjunction with the consequences of proposed future i i disposals. The total radiological dose consequence of the past and the pro- i i posed disposal will be compared to the applicable limits to insure the dose l j is maintained at or below the limits.

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l POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT l OFFSITE DOSE CALCULATION MANUAL January 26,1996 l O l O l

APPENDIX F l

Modifications to the Wisconsin Electric submittal to the United States Nuclear Regulatory Commission dated October 8,1987 (VPNPD-87-430, NRC-87-104), Disposal by Land l Application of Sewage Sludge Containing Minute Quantities of Radioactive Material.

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O l F-1 CONTINUOUS USE l __

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- POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR Revision 10 DRAFT

OFFSITE DOSE CALCULATION MANUAL January 26,1996 MODIFICATION #1 CHANGE TO ORIGINAL SUBMITTAL Section 3.2, Disposal Procedure (page.3)

Section 3.3, Administrative Procedure (page 4)

The requirements for sludge characterization (the determination of the i chemical and physical properties of the sludge) contained in the sections

{ referenced above are modified to allow characterization of the sludge on an

annual basis. -

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BASIS / EXPLANATION The October 8,1987 submittal to the USNRC for permission to dispose of sewage treatment sludge containing minute quantities of radioactive material requires that, " prior to disposal the waste stream will be monitored to determine the physical and chemical properties of the sludge. ...

Subsequent to the sub-mittal and the approval by the NRC, a new Wisconsin Pollutant Discharge Elimination System (W1 DES) permit was issued to the Point Beach Nuclear Plant oy the Wisconsin Department of Natural Resources on November 30, 1988. Both )

the new WPDES permit and the Point Beach Nuclear Plant Sludge Management Plan specify an annual required frequency for the evaluation of the sludge characteristics.

b The original requirement to perfonn the characterization of the chemical and physical properties of the sewage sludge prior to each disposal has proven time consuming and costly for Wisconsin Electric Lab Services. Preparation -

of special analytical standards are required to complete the characteriza' tion study. The preparation of these standards, sample preparation, and the actual analyses are all manpower intensive and difficult to perform on a timely basis. This has led to requiring overtime for Lab Services personnel and I apport from outside companies. In order to better utilize the resources of Lab Services while maintaining the requirements of the WPDES permit, the frequency of sludge characterization in the October 8, 1987 submittal to the NRC should be changed to an annual requirement. -

This change in the required frequency for determination of the sludge characteristics does not change the requirement to analyze the sewage sludge for radionuclide content or perform dose evaluations ' prior to each disposal.

O l F-2 CONTINUOUS USE

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POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l N 00R Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 O

v APPENDIX G Modifications to the Wisconsin Electric submittal to the United States Nuclear Regulatory Commission dated October 8,1987 (VPNPD-87-430, NRC-87-104), Disposal by Land Application of Sewage Sludge Containing Minute Quantities of Radioactive Material.

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O l G-1 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULA90N MANUAL l MAJOR Revision 10 DRAFT OFFSITE DOSE CALCULATION MANUAL January 26,1996 O

V MODIFICATION #2 CHANGE TO ORIGINAL SUBMITTAL Section 3.3, Administrative Procedures (Page E-10)

The limitation on the annual volume of sludge disposal per acre contained in the section referenced above is modified to allow unlimited disposal provided the other requirements of this submittal are met.

BASIS / EXPLANATION The October 8,1987, submittal to the USNRC for permission to dispose of sewage treatment sludge containing minute quantities of radioactive material requires that "the annual disposal rate for each of the approved land spread sites will be limited to 4,000 gallons / acre, provided WDNR chemical composition, NRC dose guidelines, and concentration and activity limits are maintained within the appropriate values."

The original mquirement to limit sewage sludge disposal to 4,000 gallons per acre is based on the assumption that the sewage sludge is contaminated with Co-58 at a concentration that is ten percent of the 10 CFR Part 20 Appendix B Table 2 Column 2 value. Past sewage sludge disposal experience has shown that the sludge may or may not be contaminated and, if it is, at concentrations far below ten percent of the performed prior to each sewage sludge disposal. With the removal of some of the land spread sites due to their use as a storage site for dry storage of spent fuel, this requirement is limiting our ability to dispose of the sewage sludge on the remaining approved land spread sites.

This removal of the annual volume of sewage sludge that may be disposed of per acre on approved land spmad sites does not change the requirement to analyze the sewage sludge for radionuclide content or perform dose evaluations prior to each disposal.

This change was evaluated under SER 95-057, " Removal of licensee Commitment Involved With Sewage Sludge Disposal," 4/20/95.

I l G-2 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL l MAJOR ,

Revision 10 DRAFT l OFFSITE DOSE CALCULATION MANUAL January 26,1996 I Q

L MODIFICATION #2 y

• Depth to groundwater and bedrock shall be greater than 3 feet from

. the land surface elevation during use of any site.

• Sludge shall not be land spread in a floodway.

• Sludge shall not be land spread within 50 feet of a property line road or ditch unless the sludge is incorporated with the. soil, in which case a minimum separation distance of at least 25 feet is required.

• The pH of the sludge-soll mixture shall be maintained at 6.5 or higher.

Low areas of the approved fields, subject to seasonally high ground-d water levels, are excluded from the sludge application. l i

• Crops for human consumption shall not be grown on the land for up to one year following the application of the sludge.

The sludge shall be plowed, disked, injected or otherwise incorporated into the surface soil layer at appropriate intervals. .

The flexibility implied in the latter provision for soil incorporation is intended to allow for crops which require more than a one year cycle, ,

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For the Point Beach disposal sites, alfalfa is a coemon crop which is l harvested for several years after a single planting. Sludge disposal on l

, an alfalfa plot constitutes good fertilization, but the plot cannot be plowed without destroying the crop. The alfalfa in this case aids in binding the layer of sludge on the surface of the plot. At a minimum, 4 4

however, plowing (or disking or other method of injection and mixing to l s nominal depth of 6 inches) shall be done prior to planting any new crop, l regardless of the crop. -

3.3 Administrative Procedures lO

, y> Complete records of each disposal will be maintained. These recordt.

will include the concentration of radionuclides in the sludge, the total volume of sludge disposed, the total activity, the plot on which the sludge was applied, the results of the chemical composition j determinations, and all dose calculations. ,

e 4 c.'leh . l' The annqal disposal rate for each of the approved land spread sites i will be HeMed t: t,000 ; lkn/:m, provided WDNR chemical compos 1- l tion MRC dose guidelines, and concentration and activity limits are maintained within the appropriate values.

The farmer leasing the site used for the disposal wi11 be notified of the applicable restrictions placed on the site due to the land spreading of sewage sludge.

4.0 Evaluation of Environmental Impact 4.1 Site Characteristics 4.1.1 Site Topeereoby The disposal sites are located in the Town of Two Creeks in the northeast corner of Manitowoc Countyr Wisconsin, on the E-10 l G-3 CONTINUOUS USE