Text

Rev 9 to Point Beach Nuclear Plant Unit 1 & 2 Odcm
	ML20107L670
Person / Time
Site:	Point Beach
Issue date:	07/06/1995
From:	; WISCONSIN ELECTRIC POWER CO.
To:	;
Shared Package
ML20107L575	List: ML20107L609; ML20107L660; ML20107L670; NPL-96-0149, Forwards Annual Monitoring Rept Jan-Dec 1995, Containing Info Re Plant Releases,Solid Waste Shipments,New & Spent Fuel Shipments,Leak Testing of Sources & Other Miscellaneous Reportable Items.Revised Environ Manual & ODCM Also Encl;
References
	PROC-950706, NUDOCS 9604290395
	Download: ML20107L670 (146)
	v • d • e

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O POINT BEACH NUCLEAR PLANT l UNITS 1 AND 2 1

OFFSITE DOSE CALCULATION MANUAL WISCONSIN ELECTRIC POWER COMPANY O l July 6,1995 Revision 9 l

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I 9604290395 960422

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POINT BEACH NUCLEAR PLANT ODCM I OFFSITE DOSE CALCULATION MANUAL Revision 9 l July 6,1995 l OFFSITE DOSE CALCULATION MANUAL TABLE OF CONTENTS Page 1.0 OFFSITE DOSE CALCULATION MANUAL ADMINISTRATION . . . . . ... .. 1 t

Pu rpo se . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

1.1 .............. 1 1

1.2 General Responsibilities . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . I 1.3 Manual Revisions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 l 2.0 RADIATION MONITORING SYSTEM AND RELEASE ACCOUNTING . . . ....2 3.0 METHODOLOGY FOR DETERMINING ALARM SET POINTS ...... ......7 l 3.1 Introduction . .............................. ... . . . 7 l

3.2 Obj ec tive . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .... ........ 7 3.3 Alert Set Point Guidelines . . . . . . . .. .......................7 Ol v 3.4 Alarm or Trip Set Point Guidelines . . . . . . . . . . . . . . .............7 3.5 Monitor Calibration and Calibration Constant Determination . ..........8 l 3.6 Determination of the Effective Maximum Effluent Concentration (EMEC) for Liquid Releases . . . . . . . . . . . . . . . . . . . . . . . . .......9 3.7 Determination of Liquid Effluent Monitor Alarm Set Points .. . . ..... 11 3.8 Detennination of EMEC for Atmospheric Releases ... .............. 15 l

3.9 Determination of Gaseous Effluent Monitor Alarm Set Points . . . . . . . . . . . . 15 4.0 DEMONSTRATING COMPLIANCE WITH 10 CFR 50. APPENDIX I . . . ...... 19 4.1 Introduction ....... ...... ................. . . . . . . . 19 l 4.2 Dose Limits .............. ..........................19 4.3 Release Limits . . . . . . ................................20 4.4 EPA Regulations ... . . . . .................. . 21 i

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POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 OFFSITE DOSE CALCULATION MANUAL O

TABLE OF CONTENTS, cont. ,

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Page 1 5.0 CALCULATION AND COMPARISON OF EFFLUENT RELEASES TO RELEASE LIMITS .................................... . . . . . . . . . . . 21 5.1 Appendix I Dose Calculations ... ........................... 21 5.1.1 Liquid Release Mode . . . . . . . . . .................21 l 5.1.2 Atmospheric Release Mode: Radiciodine, Tritium, and l Particulates . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 51 5.1.3 Atmospheric Release Mode: Noble Gases ...... ......... 80 6.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ........... 82 7.0 RADIOLOGICAL IMPACT EVALUATIONS OF SEWAGE TREATMENT q SLUDGE DISPOS AL . . . . . . . . . . . . .. ........... ............82 V

7.1 B asis . . . . . . . . . . . . . . . . . . . . . ............... . . . . . . . 82 7.2 Proced u re . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 83 7.3 Administrative Requirements . .............................. 84 A nne nd i x A . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ....... . . . . . . . . 86 A1.0 Derivation of Liquid Release Effective Maximum Effluent Concentration .. ...... 87 A1.1 Source Term . . . . . . . . . . . . . . . .... ....................87 A1.2 Effective Maximum Effluent Concentration . . . . . . . . . . . . . . . . . . . . . . 87 l

A ppe nd i x B . . . . . . . . . . . . . . . . . . . . . .......... ........... . . . . . 92 Bl.0 Derivation of Atmospheric Release Effective Maximum Effluent Concentration . . . . . . 93 Bl.1 Source Term . . . . . . . . . . . . . . . ........................93 O

O Bl.2 Effective . Maximum Effluent Concentration ......................93 l

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TABLE OF CONTENTS, cont.

Pace A n ne nd i x C . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ...........98 C1.0 Calculation of Total Dose Factors Using Regulatory Guide 1.109 Methodology . . . . . . 99 C1.1 Liquid Release Dose Factors . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 99 C1.1.1 Aquatic Foods ................. ...... . . . . . . . . 99 C1.1.2 Irrigated Foods (Meat from Watered Cattle) . . . . . . . . . . . . .. 101 C1.1.3 Irrigated Foods (Milk from Watered Cattle) ............... 103 C1.1.4 Potable Water .................................105 C1.1.5 Shoreline Deposits . . . . . . . . . . . . . . .............. . 107 O ci.2 ^tm e89aeric a eie e n eee e cters: s e e-o eeees . . . . . . . . . . . . . . . . . 109 C1.2.1 Inhalation of Nuclides in Air ....... . . . . . . . . . . . . . . . . 109 C1.2.2 Annual Organ Dose from External Irradiation From i Nuclides Deposited on the Ground . . . . . . . . . . . . . . . . . . . . .110 l C1.2.3 Annual Organ Dose from Atmospherically Released Nuclides in Milk . . . . . . . . . . . . . . ................ .112 1

C1.2.4 Annual Organ Dose from Atmospherically Released Nuclides in Meat . . . . . . . . . ......................115 C1.2.5 Annual Organ Dose from Atmospherically Released Nuclides in Produce . . ........................... 118 l

C1.2.6 Annual Organ Dose from Atmospherically Released Nuclides in Leafy Vegetables . . . . . . . . . . ............. 121 C1.3 Atmospheric Release Dose Factors: Noble Gases . . . . . . . . . . . ....... 124 C1.3.1 Annual Gamma and Beta Dose from All Noble Gas (q) Releases . ................ ............. .. . 124 C1.3.2 Annual Skin Dose from All Noble Gas Releases ...... ... . 125

i l POINT BEACH NUCLEAR PLANT ODCM l OFFSITE DOSE CALCULATION MANUAL Revision 9 i July 6,1995 l OFFSITE DOSE CALCULATION MANUAL l

l TABLE OF CONTENTS, cont.

i 1

l Pace l

C1.3.3 Annual Total Body Dose from All Noble Gas Releases ........ 126 1 1

i .

Appendix D

................................. ........ ... .. 128 i

l D1.0 Liquid Effluent Dilution Factor Calculations . . . . . . . . . . . . . . . . . . . . . . . . 12 9 l

D1.1 Me thod ology . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .129 D1.2 Dilution Factor Twelve Miles Downstream: Two Rivers Water Intake ..... 132 l

l 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

l Appendix G Modification #2 to NRC Submittal ......... ............... . G-1 l

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POINT BEACH NUCLEAR PLANT ODCM l

OFFSITE DOSE CALCULATION MANUAL Revision 9 l July 6,1995 l OFFSITE DOSE CALCULATION MANUAL o

d LIST OF TABLES AND FIGURES I Page l SECTION 2.0 Table 2-1 Radioactive Liquid Waste Effluent Monitors . ................. ..3 Table 2-2 Radioactive Gaseous Waste Effluent Monitors ...... .............4

, Figure 2-1 Radioactive Liquid Waste Effluent Monitors ............... ......4 Figure 2-2 Radioactive Gaseous Waste Effluent Monitors .....................6 l

l SECTION 3.0 I

Table 3.7-1 Summary of Liquid Dilution and Effluent Pathway Flow Rates ....... .. 12 Table 3.7-2 Liquid Pathway Monitor Calculated Default Set Points . . . . . . . . . . . . . . . . 14 Table 3.9-1 Summary of Gaseous Effluent Pathway Discharge Flow Rates . . . . . . . . . . . . 16 I

Table 3.9-2 Atmospheric Pathway Monitor Default RMS Set Points ....... ....... 18 SECTION 5.0 l Table 5.1-1 Liquid Effluent Dose Factors . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . 23 p Table 5.1-2 Airborne Effluent Dose Factors ......... ...................52 V Table 5.1-3 Activity to Dose Conversion Factors for Noble Gases . . . . . . . . . . . . . . . . 81 l

l APPENDIX A 1

Table A-1 Curies Released in Liquids . . . . . . . ............... . . . . . . . . 89 Table A-2 Fractional MEC in Liquid Effluent .. ......... . . . . . . . . . . . . . . 90 l

l l APPENDIX B Table B-1 Curies in Atmospheric Effluent ......... . . .... . . . . . . . . 94 !

Table B-2 Fractional MEC for Atmospheric Effluent . .......... .. . . . . . . 96 l l

l I APPENDIX D l l

Table D-1 Surface Dilution Factors, Liquid Effluent in a Large Lake . . . . . ...... 130 Figure D-1 Dilution Factor at Surface . . . . . ................ ... .... 131 O

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POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 l OFFSITE DOSE CALCULATION MANUAL n l

'V 1.0 OFFSITE DOSE CALCULATION MANUAL ADMINISTRATION 1.1 Purpose The PBNP Offsite Dose Calculation Manual contains the current methodology and i parameters for the calculation of offsite doses due to radioactive gaseous and liquid l effluents. This manual describes a methodology for demonstrating compliance with l 10 CFR 50, Appendix I dose limits. Compliance with Appendix I is demonstrated by l 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 l effluent monitor alarm set points. The PBNP Radiation Monitoring System (RMS) l effluent monitor alarm set points are established to ensure that controlled releases of l liquid and gaseous radioactive effluents are maintained as low as is reasonably achievable and to ensure releases result in concentrations to unrestricted areas within limits specified in 10 CFR 20.

l The manual also details the methodology for evaluating the radiological impact of l sewage treatment sludge disposal. This methodology addresses the commitments made to the United States Nuclear Regulatory Commission in our application dated 3 October 8,1987 (NRC-87-104) and accepted by the USNRC in a letter dated (V 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 contained in Appendices E and F. Dose limits are established in the application to ensure the health and safety of the maximally exposed member of the general public l and the inadvertent intruder. 10 CFR 50, Appendix I dose limits do not apply to sewage treatment sludge disposal.

1.2 General Responsibilities 1

The primary responsibility for the implementation of the PBNP offsite dose i calculation program and for any actions required by the program resides with the l

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, j The Manager, PBNP is responsible for assuring that Radiation Monitoring System

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

(M O

Page 1 of 134

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 OFFSITE DOSE CALCULATION MANUAL 1.3 Manual Revisions This manual describes the current scope of the PBNP offsite dose calculation program. The program and the manual are maintained by IRSS. Program items or procedures may be periodically updated or changed, either to reflect new parameters or to improve program effectiveness. This manual may be revised at the discretion of IRSS with the concurrence of the PBNP Manager's Supervisory Staff (MSS).

2.0 RADIATION MONITORING SYSTEM AND RELEASE ACCOUNTING l

A computerized Radiation Monitoring System (RMS) is installed at Point Beach Nuclear !

Plant (PBNP). The RMS includes area, process, and effluent monitors. A description of those monitors used for liquid and gaseous effluents is presented in Tables 2-1 and 2-2. The liquid and gaseous waste processing flow paths, equipment, and monitoring systems are depicted in Figures 2-1 and 2-2. Calibration of the RMS detectors is accomplished in 1 accordance with procedures contained in the PBNP Health Physics Calibration Manual. The l 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 e released in liquid and gaseous effluents is accomplished with the RMS together with the characterization of nuclide distributions by laboratory analysis of grab samples. Sampling frequencies and analysis requirements are described in Tables 15.7.6-1 and 15.7.6-2 of the PBNP Technical Specifications. The various aspects of grab sampling and release accountability are described in the PBNP Release Accountability Manual.

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POINT BEACII NUCLEAR PLANT /O ODCM

(~~N OFFSITE DOSE CALCULATION MANUAL Revision 9 -

July 6,1995 OFFSITE DOSE CALCULATION MANUAL TABLE 2-1 RADIOACTIVE LIQUID WASTE EFFLUENT MONITORS CIIANNEL 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 3 of 134

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POINT BEACH NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL

/~ \ ODCM Revision 9 fT d

July 6,1995 OFFSITE DOSE CALCULATION MANUAL TABLE 2-2 RADIOACTIVE GASEOUS WASTE EFFLUENT MONITORS CHANNEL NUMBER NAME CONTROL FUNCTION DETECTOR TYPE 1 (2) RE-212 Containment Noble Gas Monitor Actuates containment ventilation isolation Scintillation RE-214 Auxiliary Building Exhaust Ventilation Shuts gas release valve and shifts auxiliary Scintillation Noble Gas Monitor building exhaust through carbon filters 1 (2) RE-215 Condenser Air Ejector Noble Gas None Scintillation Monitors RE-225 Combined Air Ejector Low-Range None Scintillation Noble Gas Monitor RE-221 Drummmg Area Vent Noble Gas None Scintillation Monitor RE-224 Gas Stripper Building Exhaust Noble None Scintillation Gas Monitor 1 (2) RE-305 Unit 1 and 2 Purge Exhaust Noble 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 4 of 134

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 OFFSITE DOSE CALCULATION MANUAL s

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POINT BEACH NUCLEAR PLANT ODCM l OFFSITE DOSE CALCULATION MANUAL Revision 9 I

July 6,1995 OFFSITE DOSE CALCULATION MANUAL l

i (V3 l 3.0 METHODOLOGY FOR DETERMINING ALARM SET POINTS l 3.1 Introduction The selection and maintenance of alert and alarm set points for each effluent monitor of the PBNP radiation monitoring system will be accomplished within the guidelines of this section. The computerized PBNP radiation monitoring system permits each effluent radiation monitor to be programmed to alarm at two distinct set points. The alert set peint, typically twice the steady-state reading, is intended to delineate a changing plant condition which may warrant corrective action. The high alann or l trip set point either will actuate a control function as applicable or will require corrective action to be initiated.

l

! 3.2 Obiective The effluent monitor set points are established to ensure that controlled releases of l liquid and gaseous radioactive effluents are maintained as low as is reasonably i achievable, to ensure releases result in concentrations to unrestricted areas with.in limits specified in 10 CFR 20, and to ensure that the dose limits of 10 CFR 50, '

l Appendix I are not exceeded.

,V p 3.3 Alert Set Point Guidelines l The alert set point of each effluent monitor generally will be set to alarm at two times the established steady-state reading. The alert set point is normally set at concentrations well below the alarm set point value and is never to be set in excess of I the alarm set point. In the course of plant operations, certain situations may require a deviation from the two times steady-state guideline. The intent of the alert set point is to warn of changing plant conditions which may warrant an evaluation of the cause of the increased radiation. If the increased reading is actually due to an increased radiation inventory within the system being monitored, as opposed to an increased background radiation field in the vicinity of the detector, an evaluation should be made to determine the impact of the release. The alert set point may be adjusted with the approval of the Duty Shift Superintendent. Alert set point adjustments are to be made in accordance with the PBNP RMS Alarm Set Point and Response Book.

3.4 Alarm or Trio Set Point Guidelines In accordance with the requirements of Technical Specifications 15.7.5.A.2 and 15.7.5.C.2, the alarm or trip set point for effluent monitors shall be established to amlunciate at radiation levels which would result in an unrestricted area concentration equal to or less than the applicable maximum effluent

~'s concentration (MEC) specified in 10 CFR 20, Appendix B, Table 2 for a single (d radionuclide. However, for a mixture of radionuclides, the set point shall be Page 7 of 134

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 OFFSITE DOSE CALCULATION MANUAL

(~

()) 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 formulae:

l I

Cal. Constant =

Sensitivity and l

nit r esponse

~ Sensitivity =

l E (microCi/cc) i 1

where:

Monitor response = the calculate ' counts per minute registered by monitor exposed to th 1985-1991 average noble gas isotopic distribution E(pCi/cci) = total concentration of isotopes in the 1985-1991 average noble l gas isotopic distribution l

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

O Page 8 of 134 l

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 OFFSITE DOSE CALCULATION MANUAL Liquid effluent monitor calibration constants are derived from the following formulae:

I Cal. Constant -

Sensitivity and Monitor Response Sensitivity =

E (pCi/cc)i where:

Monitor Response = the counts per minute registered by monitor exposed to calibration source E(pCi/cc)i = total concentration on radionuclides in the 1985-1991 average liquid effluent isotopic distribution The QAD computer program may be utilized to predict or determine monitor calibration constants. Application of the QAD program may be appropriate for O aetermiete8 meeite< <espee e rer ecciaeet seerce terms er other ie teeces ae# <ae use of a calibration source is impracticable. The methodology for determination of l calibration constants using the QAD program is maintained by the staff of the IRSS.

l 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 l which will alarm when a liquid effluent would contain enough radionuclides to cause the effluent concentration limit of 10 CFR 20, Appendix B, Table 2, Column 2 for a single radionuclide to be exceeded, or for a mixture of radionuclides, the summation of fractions (SOF), as defined in Appendix B, to exceed one (1). Dividing the average isotopic concentrations for the years 1985-1991 by the SOF scales the total of individual concentrations up to the value where the SOF equals one. This total concentration is called the effective maximum effluent concentration (EMEC) and its calculation is described below. (For a complete discussion of the EMEC derivation, see Appendix A.)

n U

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i l l POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 OFFSITE DOSE CALCULATION MANUAL The SOF is calculated using the formula found in the revised 10 CFR 20, Appendix B, Note 4:

l SOF = E C /MEC i i where:

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

discharge / total volume of discharge) l MEC i = maximum effluent concentration for unrestricted areas from l Appendix B, Table 2, Column 2 of the revised 10 CFR 20. l I

The SOF for radionuclides in liquid effluent for the years 1985 through 1991 were l 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 i or EC i* 1/SOF g where the variables are the same as defined above.

t l

The average EMEC, based on 1985-1991 data is 4.29E-06 Ci/cc. This is the I maximum non H-3 radionuclide mixture concentration that could be released in liquid effluent without the SOF exceeding one (1). I However, the 10 CFR 20, Appendix B criterion is that the SOF for all radionuclides,

( including H-3 which cannot be measured by the liquid effluent Nal RMS monitors, l be less than or equal to one (1). Therefore, the above equation modified by a factor j of 0.70 (see Appendix A) to account for H-3 becomes l

l EMEC = 0.70 EC i / E (C/MEC) i i or EC,

0.70/SOF.

The EMEC becomes EMEC = 0.70

4.29E-06 = 3.00E-06 Ci/cc.

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

Cs-137 (IE-06).

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l POINT BEACH NUCLEAR PLANT ODCM OFFSITE D9SE CALCULATION MANUAL Revision 9 July 6,1995 OFFSITE DOSE CALCULATION MANUAL 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 Ci/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 s1.

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

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

1 Set points are calculated using the formula l Cire water flow rate (gpm)

SP = EMEC

Waste Discharge Flow Rate (gpm) '

where SP = RMS alarm set point in Ci/cc EMEC = effective maximum effluent concentration Circ water flow rate = total flow from Unit 1 + Unit 2 Waste discharge flow rate = flow rate for effluent line on which the monitor is located Maximum waste discharge flow rates and monitors associated 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 defcult 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.

Page 11 of 134

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, July 6,1995 l OFFSITE DOSE CALCULATION MANUAL TABLE 3.7-1

SUMMARY

OF LIOUID DILUTION AND EFFLUENT PATHWAY FLOW RATES i

LIQUID EFFLUENT DISCHARGE FLOW RATE PATHWAY PATHWAY MONITOR (GPM)

RECIRCULATION WATER 1 pump, either unit 206,000 None 2 pumps, either unit 350,000 1 pump, each unit 392,000 1 pump, one unit & 2 530,000 pumps, other unit i 2 pumps, each unit 680,000 SERVICE WATER RETURN 1 (2) RE-229 (normal cooldown per pump 2 pumps @ 7500 gpm 15,900

]

l 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 RE-230 Max Flow Rate (2 pumps) 360 (sliding gate open) 1670 G

O i

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POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 l July 6,1995 l OFFSITE DOSE CALCULATION MANUAL

(

TABLE 3.7-1, cont.

l

SUMMARY

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

SPENT FUEL POOL RE-220 Max Flow Rate 700 WASTE DISTILLATE & RE-218 & RE-223 CONDENSATE TANK

DISCHARGE Max Flow Rate 100 CONTAINMENT FAN 1 (2) RE-216 COOLER RETURN Max Flow Rate per 4000 l Containment O

i i

}

O l

l Page 13 of 134

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 OFFSITE DOSE CALCULATION MANUAL TABLE 3.7-2 LIQUID PATIIWAY MONITOR CALCUL.'aTED DEFAULT SET POINTS j MONITOR FLOWRATE (com) SET POINT (uCi/cc) 1 (2) RE-229 6 @ 3700' 2.78E-05 1 (2) RE-219 & 200 3.09E-3 1 (2) RE-222 RE-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 i

O 1

'six service water pumps at normal cooldown flow rates O

Page 14 of 134

POINT BEACH NUCLEAR PLANT ODCM l OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 OFFSITE DOSE CALCULATION MANUAL 3.8 Determination of EMEC for Atmospheric Releases The maximum concentration of the mixture of radionuclides that is allowable at the site boundary is called the effective maximum effluent concentration (EMEC). The EMEC for an effluent mixture is defined by the equation

! EMEC = ECi / E(Ci / MEC)i

! where C= i concentration of radionuclide "i" MECi = maximum effluent concentration for radionuclide i from 10 CFR 20, Appendix B, Table 2 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 tnixture. This mixture is i 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 p used in the set point calculations.

'u) 3.9 Determination of Gaseous Effluent Monitor Alarm Set noints 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 Ci/cc XQ=

/ highest site boundary annual average 1.5E-M sec/m3 FR = the flow rate in ft /3 min of the effluent pathway being monitored.

Combining the above numerical values yields SP( Ci/cc) = 2.71E+01/ FR O

V Gaseous effluent pathway discharge flow rates and monitors associated with each l

pathway are summarized in Table 3.9-1.

Page 15 of 134

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

I POINT BEACH NUCLEAR PLANT OCCM OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 OFFSITE DOSE CALCULATION MANUAL TABLE 3.9-1 i

SUMMARY

OF GASEOUS EFFLUENT PATHWAY DISCHARGE FLOW RATES DISCHAPGE FLOW RATE MONITOR (S)

GASEOUS EFFLUENT PATHWAY CFM IN EFFLUENT PATHWAY

! a. Auxiliary Building Vent 66,400 RE-214 & SPING 23 j b. Combined Air Ejector 20 RE-225

c. Unit Air Ejector 10 1 (2) RE-215 i d. Containment Purge Vent

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

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

e. Gas Stripper Building 13,000 RE-224

f. Drumming Area Vent 43,100 RE-221 & SPING 24 I

I lO l

Page 16 of 134

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 OFFSITE DOSE CALCULATION MANUAL O

V 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 xtual 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 i the event simultaneous releases from these points occur. Lower set point values may be used l 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 RE-221 (SPING 24).

l (v9 '

.O Page 17 of 134 l

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 l July 6,1995 OFFSITE DOSE CALCULATION MANUAL TABLE 3.9-2 ATMOSPHERIC PATHWAY MONITOR DEFAULT RMS SET POINTS FLOW RATE SET POINT MONITOR (ft 3/ min) (uCi/cc) l RE-214 66,400 1.02E-04 l RE-225 20 1.36E+00 l 1RE-215 10 2.71E +00 l 2RE-215 10 2.71E+00 1RE-212 25,000' 2.73E-04 2RE-212 38,0002 1.78E-04 RE-224 13,000 2.09E-03 RE-221 43,000 1.58E-04 O

V

' 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 l

l lO Page 18 of 134

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 OFFSITE DOSE CALCULATION MANUAL

/N d 4.0 DEMONSTRATING COMPLIANCE WITH 10 CFR 50. APPENDIX I 4.1 Introduction Maintaining effluents within the dose objectives of Appendix I is demonstrated at PBNP by periodic calculations. Compliance with Appendix I limits is demonstrated by periodically calculating doses to the maximum exposed individual using the methodology set forth in Regulatory Guide 1.109, Rev.1, October 1977 and in other recognized sources such as ICRP publications.

In order to aid in the dose calculations, the formulae in Reg Guide 1.109 were rearranged to calculate the dose per curie released (mrem /Ci) to the environment. '

For each pathway given in Reg Guide 1.109, a radionuclide's mrem /Ci values for the I 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 consideration were summed to obtain the radionuclide's total mrem /Ci j 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 _D_ose Limits O

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

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

B. The annual total quantity of all radioactive material above background that may be teleased from each light-water-cooled nuclear power reactor to the atmosphere should not result in an annual air dose from gaseous effluents at any location near ground level which could be occupied by individuals

('] in unrestricted areas in excess of 10 millirads for gamma radiation or v 20 millir- 4 for beta radiation, or that this quantity should not result in an Page 19 of 134

POINT BEACH NUCLEAR PLANT ODCM ;

OFFSITE DOSE CALCULATION MANUAL Revision 9 I July 6,1995 OFFSITE DOSE CALCULATION MANUAL l annual external dose frora gaseous effluents to any individual in i unrestricted areas in excess of 5 millirems to the total body or 15 millirems to the skin.

C. The annual total quantity of all radioactive iodine and radioactive material in particulate form above background that may be released from each l light-water-cooled nuclear power reactor in effluents to the atmosphere should not result in an annual dose or dose commitment from such radioactive iodine and radioactive material in particulate form for any individual in an unrestricted area from all pathways of exposure n excess of 15 millirems to any organ. I 4.3 Release Limits Based on the Appendix I dose limits, Point Beach, being a two (2) unit nuclear plant, may release into the environment the quantities of radionuclides above background that fulfill the criteria listed below.

A. Pursuant to Section 4.2.A, the doses from radionuclides in the unrestricted area in liquids shall not exceed p, 1. Six (6) millirem to the whole body, or O

2. Twenty (20) millirem to any organ.

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

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

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

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

4. Thirty (30) millirem to the skin.

C. Pursuant to Section 4.2.C, the dose from radiciodine and radioactive material in particulate form released to the atmosphere in the unrestricted area shall not exceed thirty (30) millirem to any organ, i

O Page 20 of 134

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 l OFFSITE DOSE CALCULATION MANUAL l O l

d 4.4 EPA Regulations ;

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

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

c 5.0 CALCULATION AND COMPARISON OF EFFLUENT RELEASES TO RELEASE 5

LIMITS Technical Specifications 15.7.5.B.3 and 15.7.5.D.3 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 mrem /Ci released which were obtained using Regulatory Guide 1.109 and other documented methodologies.

5.1 Annendix I Dose Calculations 5.1.1 Liquid Release Mode The dose calculations for demonstration of compliance with the 10 CFR 50, Appendix I dose limits will be accomplished by the Radiological Engineering Group of IRSS. These calculations will be done monthly, within fifteen (15) days of receipt of the final effluent curie

! values from the PBNP Chemistry Section. The doses from each radionuclide will be calculated for each age group and for each organ, l

t including the whole body, and summed over all the identified radionuclides released. The total dose is compared to the corresponding liquid release mode Appendix I dose limit for the organ in question. Noble gases l

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

Page 21 of 134

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 OFFSITE DOSE CALCULATION MANUAL

( The doses are calculated using the following formula:

API = E Dose,om; = E (TDF,om; x C i ) sKom mrem where API = the Appendix I dose for compliance evaluation in mrem l

= the dose to the specific age group a) and organ (o) via Dose omi release mode (m) from radionuclide (i)

TDF,omi = total dose factor for the specific age group (a) and l organ (o) via release mode (m) from radionuclide (i) from l Table 5.1-1 in mrem /Ci j Ci =

curies of radionuclide (i) released Kom = the Appendix I dose limit for organ (o) and release mode (m) for which the calculation is being made.

1 The methodology and the values used to obtain the TDF,omi values are l

p given in Appendix C. I b

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

Instead of using the precalculated total dose factors, the Appendix I dose calculation may be modified to reflect the actual liquid discharge volume during the release period using the methodology in Appendix C.

l O

Page 22 of 134

I l

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 OFFSITE DOSE CALCULATION MANUAL Table 5.1-1 Liquid Effluent Dose Factor Summation of dose per curie released factor calculations over the pathways: potable water, aquatic l food, shoreline deposit, irrigated foods (milk), and irrigated foods (meat). !

Dose factor - liquid release pathway (mrem /Ci released) j 11-3 Bone Liver T. Body Thyroid Kidney Lungs GI.LLI i l

l Adult 0.00E +00 4.57E-06 4.57E-06 4.57E-06 4.57E-06 4.57E-06 4.57E-06 i Teen 0.00E +00 4. I 1 E-06 4.I1E-06 4. I 1E-06 4. I1E-06 4. I1E-06 4.I1E-06 l Child 0.00E +00 6.76E-06 6.76E-06 6.76E-06 6.76E-06 6.76E-06 6.76E-06 Infant 0.00E +00 7.80E-06 7.80E-06 7.80E-06 7.80E-06 7.80E-06 7.80E-06 l l

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

"~'"

lO Bone Liver T. Body Thyroid Kidney Lungs GI-LLI 1

1 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 i

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

Na-22 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 4.71E-03 4.71E-03 4.82E-03 4.71 E-03 4.71 E-03 4.71E-03 4.71E-03 l 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 8.45E-03 8.32E-03 8.32E-03 8.32E-03 8.32E-03 Infant 7.21E-03 7.21E-03 7.21E-03 7.21E-03 7.21E-03 7.21E-03 7.21E-03 l I

O Page 23 of 134

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 OFFSITE DOSE CALCULATION MANUAL

( \

Q) Table 5.1-1, cont.

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

Na-24 l Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 1.85E-04 1.85 E-N 1.85E-04 1.85 E-N 1.85 E-N 1.85E-04 1.85E-04 Teen 1.98E-04 1.98E-04 1.98E-04 1.98E-N 1.98E-04 1.98E-N 1.98E-04 Child 2.40E-04 2.40E-04 2.40E-04 2.40E-04 2.40E-04 2.40E4)4 2.40E-N Infant 8.06E-05 8.06E-05 8.06E-05 8.06E-05 8.06E-05 8.06E4)5 8.06E-05 Dose factor - liquid release pathway (mrem /Ci released)

Sc-46 Bone Liver T. Body ~ Thyroid Kidney ' Lungs GILLI I Adult 1.70E-07 3.31E-07 8.92E-06 0.00E+00 3.09E-07 0.00E+00 1.61E-03

/7 Teen 1.52E-07 2.97E-07 4.94E-05 0.00E +00 2.84E-07 0.00E+00 1.01E-03 V 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 4.94E-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 Thyroid Kidney Lungs GI-LLI I 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-N 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 Page 24 of 134

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 OFFSITE DOSE CALCUIATION MANUAL n

() Table 5.1-1, cont.

l l

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

Cr-51 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 0.00E +00 0.00E+00 1.01 E-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 2.21E-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 5.01 E-06 l

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

Mn-56 l

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

Adult 0.00E+00 3.18E-06 5.65E-07 0.00E+00 4.04E-06 0.00E+00 1.02E-04

)

O Teen 0.00E +00 3.33E-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-Il 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 Thyroid Kidney Lungs GI-LLI Adult 5.98E-04 4.13E-04 9.63E-05 0.00E +00 0.00E + 00 2.31E-04 2.37E-04 Teen 6. l l E-04 4.33E-04 1.01E-04 0.00E+00 0.00E +00 2.75E-04 1.88E-04 Child 9.35E-N 4.96E-04 1.54E-04 0.00E+00 0.00E +00 2.80E-04 9.19E-05 Infant 1.55E-04 1.00E-N 2.68E-05 0.00E+00 0.00E+00 4.91E-05 1.28E-05 O

i Page 25 of 134 '

l POINT BEACH NUCLEAR PLANT ODCM '

! OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 l OFFSITE DOSE CALCULATION MANUAL 1

O l C Table 5.1-1, cont.

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

Bone Liver T. Body Thyroid Kidney Lungs GI-LLI l Adult 9.12E-04 2.14E-03 8.23E-04 0.00E+00 0.00E +00 5.99E-04 7.14E-03 Teen 9.22E-04 2.15E4)3 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 l

Adult . 0.00E +00 2.02E-05 3.57E-05 0.00E+00 0.00E +00 0.00E+00 5.13E-04

[]

\J Teen 0.00E + 00 2.06E-05 4.62E-05 0.00E +00 0.00E + 00 0.00E +00 3.83E-04 Child 0.00E +00 2.31E-05 4.93E-05 0.00E+00 0.00E+00 0.00E +00 1.89E-04 Infant 0.00E +00 1.24E-05 2.02E-05 0.00E +00 0.00E+00 0.00E+00 4.24E-05 1

Dose factor - liquid release pathway (mrem /Ci released) l Co-58 l l Bone Liver T. Body Thyroid Kidney Lungs GI-LLI

! Adult 0.00E +00 8.49E-05 1.93E-04 0.00E +00 0.00E +00 0.00E +00 1.72E-03 Teen 0.00E +00 8.30E-05 2.04 E-04 0.00E +00 0.00E+00 0.00E+00 1.14E-03 i l I 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 l

\

l

^\ !

(V !

1 i !

l l

Page 26 of 134 l

l

POINT BEACII NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 OFFSITE DOSE CALCULATION MANUAL Table 5.1-1, cont.

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

Co-60 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI i 1

Adult 0.00E+00 2.18E-04 6.82E-04 0.00E +00 0.00E+00 0.00E +00 4.66E-03 I Teen 0.00E +00 2.44 E-04 1.30E-03 0.00E+00 0.00E+00 0.00E+00 3.17E-03 I

Child 0.00E +00 2.49E-04 8.92E-N 0.00E +00 0.00E+00 0.00E +00 1.38E-03 l Infant 0.00E +00 1.17E-04 2.77E-04 0.00E+00 0.00E +00 0.00E +00 2.79E-N l

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

Ni-63 l Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 3.03E-02 2.10E-03 1.02E-03 0.00E+00 0.00E +00 0.00E+00 4.38E-04

( Teen 3.13E42 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 7.85E44 4.41E-04 0.00E+00 0.00E+00 0.00E +00 3.91E-05 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 2.01E-07 0.00E +00 0.00E +00 0.00E+00 1.12E-05 Teen 3.66E-06 4.68E-07 2.13E-07 0.00E +00 0.00E +00 0.00E+00 2.54E-05 Child 4.68E-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-Il 8.95E-12 0.00E +00 0.00E +00 0.00E+00 1.50E-09 O

Page 27 of 134

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 OFFSITE DOSE CALCULATION MANUAL O T eeie 5.1-1. co et.

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

Cu-64 Bone Liver T. Body Thyroid 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 Infant 0.00E+00 1.41E-06 6.52E-07 0.00E+00 2.38E-06 0.00E +00 2.89E-05 j Dose factor - liquid release pathway (mrem /Ci released)

Zn-65 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI l Adult 1.73E-02 5.50E-02 2.49E-02 0.00E+00 3.68E-02 0.00E+00 3.46E-02 Teen 1.58E-02 5.50E-02 2.57E-02 0.00E +00 3.52E-02 0.00E +00 2.33E-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 4.51E-03 2.08E-03 0.00E+00 2.19E-03 0.00E +00 3.81E43 Dose factor - liquid release pathway (mrem /Ci released)

Zn-69 Bone Liver T. Body Thyroid 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 2.14E-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 2.43E-05 0.00E+00 2.52E-03 Infant 5.98E-07 1.08E-06 8.01 E-08 0.00E +00 4.47E-07 0.00E+00 8.78E-05 l

l l

O Page 28 of 134 i

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POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 OFFSITE DOSE CALCULATION MANUAL Table 5.1-1, cont.

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 5.01E-04 0.00E+00 4.53E-02 Child 4.49E-04 7.65E-04 9.04E-05 0.00E+00 4.44 E-N 0.00E+00 2.49E-02 i Infant 9.61E-06 1.96E-05 1.79E-06 0.00E+00 7.94E-06 0.00E +00 2.72E-04 l

l 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 1.47E-03 0.00E +00 0.00E +00 0.00E +00 0.00E+00 Child 0.00E +00 0.00E +00 1.71E-03 0.00E+00 0.00E +00 0.00E +00 0.00E +00 i

l Infant 0.00E +00 0.00E +00 4.43E-M 0.00E+00 0.00E +00 0.00E+00 0.00E +00 Dose factor - liquid release pathway (mrem /Ci released)

Br-83 Bone Liver T. Sody Thyroid Kidney Lungs GI-LLI l

Adult 0.00E+00 0.00E+00 9.06E-07 0.00E +00 0.00E+00 0.00E +00 1.30E-06 i

Teen 0.00E +00 0.00E+00 9.85 E-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 Infant 0.00E+00 0.00E+00 2.93E-11 0.00E+00 0.00E +00 0.00E +00 0.00E+00 l

J Page 29 of 134

i POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 OFFSITE DOSE CALCULATION MANUAL

'N (V Table 5.1-1, cont.

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

Br-84 Bone Liver T. Body Thyroid Kidney Lungs 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 l

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

Br-85 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI l Adult 0.00E +00 0.00E+00 4.24E 82 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l Teen 0.00E +00 0.00E +00 4.60E-82 0.00E +00 0.00E +00 0.00E+00 0.00E +00 Child 0.00E +00 0.00E +00 5.94E-82 0.00E+00 0.00E +00 0.00E +00 0.00E +00 l Infant 0.00E + 00 0.00E +00 9.35E-309 0.00E +00 0.00E+00 0.00E +00 0.00E+00 l

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

Rb-86 l Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 0.00E +00 7.36E-02 3.43E-02 0.00E +00 0.00E+00 0.00E+00 1.45E-02 Teen 0.00E +00 7.98E-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 l

O Page 30 of 134

l POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 I July 6,1995 i OFFSITE DOSE CALCULATION MANUAL l Table 5.1-1, cont.

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

Bone Liver T. Body Thyroid Kidney Lungs GI-LLI

Adult 0.00E +00 1.41E-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 1.0iE-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 l

Bone Liver T. Body Thyroid Kidney Lungs GI-LLI

Adult 0.00E +00 1.28E-18 8.99E-19 0.00E+00 0.00E +00 0.00E +00 7.42E-32 I(O

- j 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 Infant 0.00E+00 1.15E-61 7.93E-62 0.00E +00 0.00E +00 0.00E+00 3.92E-62 i

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

Sr-89 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 2.26E-02 0.00E +00 6.48E-04 0.00E+00 0.00E +00 0.00E +00 3.62E-03 l

Teen 2.43E-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

G V

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POINT BEACII NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 OFFSITE DOSE CALCULATION MANUAL

,e

! Table 5.1-1, cont.

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

Sr-90 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 5.63E-01 0.00E+00 1.38E-01 0.00E +00 0.00E+00 0.00E +00 1.63E-02 Teen 4.64E-01 0.00E +00 1.15E-01 0.00E+00 0.00E+00 0.00E+00 1.30E-02 Child 5.59E41 0.00E +00 1.42E-01 0.00E +00 0.00E +00 0.00E+00 7.53E-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-LLI Adult 1.27E-04 0.00E+00 5.14E-06 0.00E +00 0.00E +00 0.00E+00 6.05E-04 Teen 1.38E-01 0.00E +00 5.51E-06 0.00E+00 0.00E+00 0.00E +00 6.24E-04 Child 1.83E-04 0.00E + 00 6.91E-06 0.00E +00 0.00E+00 0.00E+00 4.04E-04 Infant 1.59E-05 0.00E+00 5.76E47 0.00E +00 0.00E +00 0.00E+00 1.88E-05 Dose factor - liquid release pathway (mrem /Ci released)

Sr-92 Bone Liver 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 1.03E-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 9.41E-10 0.00E +00 3.50E-Il 0.00E+00 0.00E+00 0.00E +00 1.01E-08 O

Page 32 of 134 l

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 OFFSITE DOSE CALCULATION MANUAL Table 5.1-1, cont, l

Dose factor - liquid release pathway (mrem /Ci released) j Y-90 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 4.85E-07 0.00E +00 1.30b-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 4.80E-07 0.00E +00 1.29E-08 0.00E +00 0.00E +00 0.00E +00 6.63E-04 Dose factor - liquid release pathway (mrem /Ci released)

Y-91 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI ,

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

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

Y-91m Bone Liver T. Body Thyroid Kidney Lungs 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 l n

v Page 33 of 134

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 OFFSITE DOSE CALCULATION MANUAL Table 5.1-1, cont.

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

Y-92 Bone Liver T. Body Thyroid 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 1.05E44 Child 4.92E-09 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 2.33 E-09 0.00E+00 0.00E +00 0.00E+00 1.69E-03 O Teen 5.77E-08 0.00E +00 6.38E-09 0.00E +00 0.00E + 00 0.00E +00 1.76E-03

'w) 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 Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 1.23E-06 3.94E-07 1.79E-06 0.00E +00 6.19E-07 0.00E+00 1.25E-03 Teen 1.llE-06 3.52E-07 8.74E-06 0.00E+00 5.17E-07 0.00E +00 8.11E-04 Child 2.48E-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 4.91E-07 0.00E +00 2.27E-04 O

Page 34 of 134

POINT BEACII NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 OFFSITE DOSE CALCULATION MANUAL G

V Table 5.1-1, cont.

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

Zr-97 Bone Liver T. Body Thyroid Kidney Lungs GILLI Adult 1.07E-08 2.16E-09 1.23E-08 0.00E+00 3.27E-09 0.00E +00 6.70E-04 Teen 1. llE-08 2.19E-09 6.42E-08 0.00E +00 3.33E-09 0.00E +00 5.94E-04 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 Dose factor - liquid release pathway (mrem /Ci released)

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 l Teen 3.25E-04 1.80E-04 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 Infant 5.36E-07 2.21 E-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 Thyroid Kidney Lungs GI-LLI Adult 2.69E-09 6.81 E-10 2.51 E-10 0.00E +00 7.95E-10 0.00E +00 2.51E-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 O

l Page 35 of 134 l

POINT BEACil NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 l OFFSITE DOSE CALCULATION MANUAL I n

()

Table 5.1-1, cont.

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

Mo-99

]

Bone Liver T. Body Thyroid Kidney Lungs GI LLI 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 4.03E-04 0.00E+00 3.15E-04 Child 0.00E +00 2.79E-04 6.91 E-05 0.00E+00 5.96E-04 0.00E+00 2.31E-04 Infant 0.00E +00 4.38E-04 8.54 E-05 0.00E +00 6.54E-04 0.00E + 00 1.44 E-04 I

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

Tc-99m l

Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 1.68E-09 4.74E-09 6.07E-08 0.00E +00 7.20E-08 2.32E-09 2.81 E-06

/Q QJ Teen 1.74 E-09 4.86E-09 6.46E-08 0.00E+00 7.24E-08 2.70E-09 3.19E46 Child 2.19E-09 4.29E-09 7.15E48 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 Child 4.98E-24 5.22E-24 6.63E-23 0.00E+00 8.90E-23 2.76E-24 1.66E-23 Infant 9.73E-69 1.23E-68 1.21 E-67 0.00E +00 1.46E-67 6.69E-69 2.08E-66 Page 36 of 134

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 OFFSITE DOSE CALCULATION MANUAL Table 5.1-1, cont.

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 4.0$E-03 Teen 2.96E-05 0.00E +00 1.64 E-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) l Ru-105 l

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 2.53E-05 Il C/

Teen 4.45E-08 0.00E + 00 2.42E-08 0.00E+00 5.62E-07 0.00E +00 3.59E-05 Child 5.71E-08 0.00E +00 2.22E-08 0.00E +00 5.02E-07 0.00E +00 3.73E-05 Infant 6.98E-10 0.00E+00 2.35E-10 0.00E +00 5.13E-09 0.00E+00 2.78E-07 Doce factor - liquid release pathway (mrem /Ci released)

Ru-106 Bone Liver T. Body Thyroid Kidney Lungs GI LLI Adult 6.71 E-04 0.00E+00 8.76E-05 0.00E +00 1.30E-03 0.00E +00 4.34E-02 Teen 5.86E-04 0.00E+00 8.85E-05 0.00E +00 1.13E-03 0.00E +00 2.81 E-02 Child 1.13 E-03 0.00E +00 1.44E-04 0.00E + 00 1.53E-03 0.00E +00 1.76E-02 Infant 2.23E-04 0.00E +00 2.78E-05 0.00E +00 2.63E-04 0.00E +00 1.69E-03 O

Page 37 of 134

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 l July 6,1995 l j OFFSITE DOSE CALCULATION MANUAL '

Table 5.1-1, cont.

Dose factor liquid release pathway (mrem /Ci released)

Rh 105 l

Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 3.35 E-06 2.45E-06 1.62E-06 0.00E +00 1.04E-05 0.00E+00 3.90E-04

Teen 4.10E-06 2.96E-06 1.97E-06 0.00E +00 1.26E-05 0.00E +00 3.77E-04 Child 8.43 E-06 4.52E-06 3.88E-06 0.00E +00 1.80E-05 0.00E +00 2.80E-04 l

Infant 1.08E-05 7.05 E-06 4.74 E-06 0.00E +00 1.96E-05 0.00E +00 1.75E-04 Dose factor - liquid release pathway (mrem /Ci released)

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 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 5.42 E-N 1.02E-05 2.21 E-N 1.32E-06 0.00E+ 00 4.22E-04 1.54E-02 Teen 5.66E-04 1.04E-05 2.53E-N 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 l

l (y~

Page 38 of 134 l

POINT BEACII NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 OFFSITE DOSE CALCULATION MANUAL Table 5.1-1, cont.

Dose factor - liquid release pathway (mrem /Ci released) 1 Sb-125 Bone Liver T. Body Thyroid Kidney Lungs GILLI Adult 3.49E-04 3.90E-06 1.07E-04 3.55E-07 0.00E +00 2.69E-N 3.85E-03 Teen 3.65 E-04 3.99E-06 2.19E-04 3.49E-07 0.00E+00 3.21E-M 2.84E-03 Child 5.14E-04 3.96E-06 1.35E-04 4.76E-07 0.00E +00 2.86E-04 1.23E-03 Infant 1.14E-04 1.ll E-06 2.35 E-05 1.43E-07 0.00E+00 7.17E-05 1.52E-04 Dose factor - liquid release pathway (mrem /Ci released)

Te-125m .

i Bone Liver T. Body Thyroid Kidney Lungs GILLI Adult 3.30E-04 1.20E-04 4.43E-05 9.93E-05 1.34E-03 0.00E +00 1.32E-03 1 1

G Teen 3.36E-04 1.21E44 4.53E-05 9.39E-05 0.00E +00 0.00E +00 9.92E-04 i U

Child 5.74E-04 1.56E-04 7.67E-05 1.61E-04 0.00E +00 0.00E +00 5.54E-04 Infant 2.47E-04 8.27E-05 3.35E-05 8.33E-05 0.00E +00 0.00E +00 1.18E-04 Dose factor - liquid release pathway (mrem /Ci released) .

1 Te-127 I Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 3.15E-05 1.13E-05 6.83E-06 2.34 E-05 1.28E44 0.00E +00 2.49E-03 Teen 3.45E-05 1.22E-05 7.43E-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 1.74 E-03 Infant 3.10E-07 1.04E-07 6.67E-08 2.52E-07 7.56E-07 0.00E +00 6.51E-06 O ,

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V Table 5.1-1, cont.

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

Te-127m l

Bone Liver T. Body Thyroid Kidney Lungs GILLI Adult 8.63E-04 3.08E-N 1.05E-04 2.21 E-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 4.05 E-N 1.79E-04 3.60E-04 4.29E-03 0.00E +00 1.22E-03 Infant 6.28E-N 2.08E-04 7.61E-05 1.82E-04 1.55E-03 0.00E +00 2.54E-04 I

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

Te-129 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI 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 1.31E-08 7.68E-08 0.00E+00 1.00E4)7 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 Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 1.35E-03 5.04E-04 2.14 E-04 4.64E-04 5.63E-03 0.00E +00 6.80E-03 Teen 1.37E-03 5.10E-04 2.18 E-N 4.43E-04 5.75E-03 0.00E +00 5.16E-03 Child 2.34E-03 6.54E-04 3.64 E-04 7.55E-04 6.88E-03 0.00E +00 2.86E-03 Infant 1.04E-03 3.58E-04 1.61E-04 4.01 E-04 2.61E-03 0.00E+00 6.23E-04 m

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, l l () Table 5.1-1, cont.

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

Te-131m j l Bone Liver T. Body Thyroid Kidney Lungs GI-LLI l

Adult 1.04E-04 5.08E-05 4.24E-05 8.05E-05 5.15E-04 0.00E+00 5.05E-03 j Teen 1.11 E-04 5.34E-05 4.49E-05 8.03E-05 5.56E-04 0.00E+00 4.28E-03 l Child 1.63E-04 5.63E-05 6.00E-05 1.16E-04 5.45E-04 0.00E+00 2.28E-03 Infant 5.46E-05 2 '.0E-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-LLI Adult 2.97E-15 1.24E-15 9.40E-16 2.44E-15 1.30E-14 0.00E +00 4.21 E-16 ,

O Teen 3.21E-15 1.32E-15 1.0lE-15 2.47E-15 1.40E-14 0.00E +00 2.63E-16 b Child l 4.12E-15 1.25 E-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 3.77E-41 1.08E-40 0.00E+00 1.71E-39 Dose factor - liquid release pathway (mrem /Ci released)

Te-132 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 1.96E-04 1.26E-04 1.19E-04 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 1.24E-03 0.00E +00 4.l lE-03 l Child 3.15E-04 1.39E-04 1.69E-04 2.03E-04 1.29E-03 0.00E+00 1.40E-03 l Infant 1.48E-04 7.32E-05 6.83E-05 1.08E-04 4.58E-04 0.00E +00 2.71E-04 l

O V

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l POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 OFFSITE DOSE CALCULATION MANUAL q

b Table 5.1-1, cont. l Dose factor - liquid release pathway (mrem /Ci released) I I-131

. Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 2.09E-04 2.99E-04 1.71E-04 9.78E-02 5.12E-04 0.00E+00 7.88E-05 Teen 2.41E-04 3.37E-04 1.81E-04 9.83 E-02 5.80E-04 0.00E+00 6.66E-05 Child 4.90E-04 4.93E-04 2.80E-04 1.63E-01 8.09E-04 0.00E +00 4.39E-05 Infant 5.71E-04 6.73E-04 2.96E-04 2.21 E.01 7.86E-04 0.00E +00 2.40E-05 Dose factor - liquid release pathway (mrem /Ci released) 1-132 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 1.43E-07 3.81E-07 1.34E-07 1.33E-05 6.07E-07 0.00E +00 7.16E-08 l

Teen 1.49E-07 3.90E-07 1.41 E-07 1.32E-05 6.15E-07 0.00E +00 1.70E-07 l

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-11 3.32E-11 1.I8E-11 1.56E-09 3.71E-11 0.00E +00 2.69E-11 I Dose factor - liquid release pathway (mrem /Ci released)

I-133 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 3.33E-05 5.80E-05 1.77E-05 8.52E-03 1.01 E-04 0.00E +00 5.21E-05 Teen 3.74E-05 6.34 E-05 1.94E-05 8.85E-03 1. llE-04 0.00E +00 4.80E-05 Child 6.27E-05 7.75E-05 2.94E-05 1.44 E-02 1.29E-04 0.00E+00 3.13E-05 Infant 4.77E-05 6.95E-05 2.04E-05 1.26E-02 8.17E-05 0.00E +00 1.18E-05 i

4 l

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- ()

l l Dose factor - liquid release pathway (mrem /Ci released) 1-134 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 2.09E-10 5.69E-10 2.04E-10 9.85E-09 9.04E-10 0.00E +00 4.96E-13

Teen 2.20E-10 5.82E-10 2.10E-10 9.70E-09 9.18E-10 0.00E +00 7.67E-12 i

Child 2.72E-10 5.05E-10 2.33E-10 1.16E-08 7.72E-10 0.00E+00 3.35E-10 l l Infant 5.37E-22 1.10E-21 3.91E-22 2.56E-20 1.23E-21 0.00E +00 1.14E-21 l

l Dose factor - liquid release pathway (mrem /Ci released) l I-135 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI i Adult 3.37E-06 8.83E-06 3.26E-06 5.82E-04 1.42E-05 0.00E +00 9.97E-06 Teen 3.55E-06 9.14 E-06 3.41E-06 5.88E-04 1.44E-05 0.00E +00 1.01E-05 l Child 4.54E-06 8.17E-06 3.87E-06 7.24E-04 1.25E-05 0.00E+00 6.23E-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 5.60E-02 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 5.03E-02 2.44E-03 Infant 1.07E-02 2.00E-02 2.02E-03 0.00E+00 5.16E-03 2.l lE-03 5.44E-05

, ,a N

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'\_) Table 5.1-1, cont.

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

Cs-134m Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 4.21E-06 8.85E-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 5.10E-06 8.95E-07 6.0E-06 Child 5.48E-06 8.llE-06 5.29E-06 0.00E +00 4.28E-06 7.07E-07 1.03E-05 Infant 5.19E-11 8.64E-11 4.37E-11 0.00E +00 3.33E-11 7.67E-12 6.84E-11 Dose factor - liquid release pathway (mrem /Ci released)

Cs-136 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 2.23E-02 8.81E-02 6.34 E-02 0.00E +00 4.90E-02 6.72E-03 1.00E-02 Teen 2.25E-02 8.85 E-02 5.95E-02 0.00E +00 4.82E-02 7.59E-03 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 I Infant 1.18E4)3 3.47E-03 1.29E-03 0.00E +00 1.38E-03 2.83E-04 5.27E-05 Dose factor - liquid release pathway (mrem /Ci released)

Cs-137 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 2.81E-01 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 5.71E-03 Child 3.85E-01 3.69E-01 5.45E-02 0.00E +00 1.20E-01 4.33E-02 2.31 E-03 Infant 1.49E-02 1.74E-02 1.24E-03 0.00E+00 4.68E-03 1.89E-03 5.45E-05 A

U Page 44 of 134

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l V Table 5.1-1, cont.

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

Cs-138 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 3.57E-11 7.04E-11 3.49E-11 0.00E+00 5.I8E-11 5.I1E-12 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 Infam 1.63E-32 2.65E-32 1.28E-32 0.00E +00 1.32E-32 2.06E-33 4.23E-32 1

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

Ba-139 Bone Liver T. Body Thyroid Kidney . Lungs GI-LLI Adult 1.67E-09 1.19E-12 4.93E-11 0.00E + 00 1.12E-12 6.77E-13 2.97E-09 Teen 1.83E-09 1.29E-12 5.50E-I l 0.00E + 00 1.21E-12 8.87E-13 1.63E-08 Child 2.35E-09 1.25E-12 6.84 E-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 1.31 E-19 1.33E-19 2.09E-14 Dose factor - liquid release pathway (mrem /Ci released)

Ba-140 )

Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 5.34E-04 6.71E-07 3.51E-05 0.00E+00 2.28E-07 3.84E-07 1.10E-03 l

Teen 5.41E-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 3.76E-07 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 __

i

(~)

O r

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o, l

I V Table 5.1-1, cont.

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

Ba-141 l Bone Liver T. Body Thyroid Kidney Lungs GI-LLI l

l Adult 4.57E-19 3.45E-22 1.63 E-20 0.00E+00 3.21E-22 1.96E-22 2.15E-28 l l

l Teen 4.96E-19 3.70E-22 2.14E-20 0.00E+00 3.44E-22 2.53E-22 1.06E-24 ]

l Child 6.37E-19 3.57E-22 2.18E-20 0.00E +00 3.09E-22 2.10E-21 3.63E-19 i 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) )

l l La-140 I

! 1 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 3.66E-08 1.84E-08 1.03E-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

(]

L Child 8.21E-08 2.87E-08 1.24E-07 0.00E +00 0.00E +00 0.00E +00 8.00E-04 1

Infant 8.56E-08 3.38E-08 8.69E-09 0.00E +00 0.00E +00 0.00E+00 3.97E-04 l Dose factor - liquid release pathway (mrem /Ci released)

La-142 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 2.92E-Il 1.33E-I l 4.94E-I l 0.00E +00 0.00E+00 0.00E + 00 9.71E-08 Teen 3.12E-Il 1.38E-11 2.61E-10 0.00E +00 0.00E+00 0.00E +00 4.21E-07 Child 3.93E-11 1.25 E-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 1

1 i

,Q i V Page 46 of 134

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! q V Table 5.1-1, cont.

i 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 5.31E-04 Teen 2.06E-07 1.37E-07 4.88E-07 0.00E +00 6.47E-08 0.00E +00 3.93E-04 Child - 5.80E-07 2.89E-07 1.42E-07 0.00E +00 1.27E-07 0.00E+00 3.61E-04 Infant 7.l lE-07 4.34E-07 5.llE-08 0.00E +00 1.34E-07 0.00E+00 2.24E-04 l

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

Ce-143 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 1.47E-08 1.09E-C5 1.78E-08 0.00E +00 4.78E-09 0.00E+00 4.06E-04 O

LJ Teen [ 1.49E-08 g

1.08E-05 9.40E-08 0.00E+00 4.86E-09 0.00E +00 3.26E-04 l l Child 4.01 E-08 2.17E-05 2.25E-08 0.00E +00 9.12E-09 0.00E +00 3.18E-04 l 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 Thyroid 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 2.78E-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 4.63E-06 0.00E +00 1.61E-03 l

O Page 47 of 134

l

~

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 l

July 6,1995 OFFSITE DOSE CALCULATION MANUAL in

(.) Table 5.1-1, cont.

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

Pr-143 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI 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 2.99E-08 0.00E+00 1.39E-07 0.00E +00 1.97E-03 l Child 1.07E-06 3.21E-07 5.31E4)8 0.00E +00 1.74E-07 0.00E +00 1.15 E-03 l

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

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

Pr-144 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI j Adult 3.76E-22 1.56E-22 2.24E-23 0.00E + 00 8.80E-23 0.00E + 00 5.41 E-29 l 1

O Teen 4.09E-22 1.67E-22 3.91E-23 0.00E+00 9.61E-23 0.00E +00 4.51E-25 N) Child 5.29E-22 1.64E-22 3.05E-23 0.00E+00 8.66E-23 0.00E +00 i

i 3.52E-19 infant 1.72E-59 6.66E-60 8.67E-61 0.00E+00 2.41E-60 0.00E+00 3.10E-55 Dose factor - liquid release pathway (mrem /Ci released)

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

(

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I POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 OFFSITE DOSE CALCULATION MANUAL Ci v Table 5.1-1, cont.

Dose factor - liquid release pathway (mrem /Ci released) l Eu-152 l

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

l Adult 1.31E-05 2.99E-04 1.63E-04 0.00E4 00 1.85E-05 0.00E +00 1.72E-03 l Teen 1.21E-05 2.92E-06 9.00E-04 0.00E +00 1.35E-05 0.00E+00 1.07E-03 i

l l Child - 1.84E-05 3.34E-06 1.91E-04 0.00E +00 1.41E-05 0.00E +00 5.49E-04 Infant 6.27E-06 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)

W-187 i

Bone Liver T. Body Thyroid Kidney Lungs GI-LLI J Adult 1.52E-04 1.27E-04 4.45E-05 0.00E +00 0.00E +00 0.00E +00 4.17E-02 f3 l %)

Teen 1.65E-04 1.34E-04 4.71 E-05 0.00E +00 0.00E +00 0.00E +00 3.63E-02 Child 2.09E-04 1.24 E-04 5.57E-05 0.00E+00 0.00E+00 0.00E +00 1.74E-02 Infant 2.25E-06 1.57E-06 5.41 E-07 0.00E +00 0.00E +00 0.00E+00 9.21 E-05 l Dose factor - liquid release pathway (mrem /Ci released)

Np-239 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 3.15E-08 3.09E-09 2.30E-08 0.00E +00 9.65E49 0.00E+00 6.34E-04 Teen 3.42E-08 3.22E-09 1.21E47 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 1.41E-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 i

I I

3 (O

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/l Table 5.1-1, cont.

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

U-235 Bone Liver T. Body 'Ihyroid Kidney Lungs GI-LLI Adult 3.05E-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 7.43E-03 0.00E+00 2.30E-03 Child 6.92E-02 0.00E +00 4.23E-03 0.00E+00 1.14E-02 0.00E+00 1.63E-03 l

Infant 4.42E-02 0.00E +00 3.37E-03 0.00E+00 9.40E-03 0.00E+00 7.67E-04 l

Dose factor - liquid release pathway (mrem /Ci released) l U-238 Bone Liver T. Body '1hyroid Kidney Lungs- GI-LLI Adult 2.92E-02 0.00E + 00 1.73E-03 0.00E +00 6.67E-03 0.00E+00 2.10E-03

! O Teen 3.03 E-02 0.00E +00 1.81E-03 0.00E+00 6.96E-03 0.00E +00 1.62E-03 V

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

Infant 4.23E-02 0.00E +00 3.15E-03 0.00E+00 8.78E-03 0.00E +00 5.41 E-04 i

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

Am-241 l Bone Liver T. Body - Thyroid Kidney Lungs GI-LLI l

Adult 5.25E-02 1.85E-02 3.47E-03 0.00E +00 2.61E42 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 l Child 4.10E-02 1.83E-02 2.93E-03 0.00E +00 1.79E-02 0.00E +D0 2.19E-03 Infant 1.42E-02 6.68E-03 1.01E-03 l 0.00E+00 6.10E-03 0.00E+00 7.17E-04

/T V

Page 50 of 134 l

i

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 OFFSITE DOSE CALCULATION MANUAL 5.1.2 Atmospheric Release Mode: Radiciodine, Tritium, and Particulates l

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 Section 5.1.1. The total dose is compared to the corresponding atmospheric release mode Appendix I dose limit for the organ in question.

l The doses are calculated using the following formula:

API = E Dose omi = E (TDF,omi x C) i s K om 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,omi = total dose factor for the specific age group (a) and l n organ (o) via release mode (m) from radionuclide (i) from U Table 5.1-2 in mrem /Ci l Ci =

curies of radionuclide (i) released i

Kom = the Appendix I dose limit for organ (o) and release l 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 recognized that some of the release quantities may not be available at the end of the month because the samples from these release paths are sent l 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.

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

Page 51 of 134 l

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 OFFSITE DOSE CALCULATION MANUAL g

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 airbome radionuclides, and direct exposure to deposited radioactivity.

Dose factor - airborne release pathway (mrem /Ci releas ed) 11-3 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin l 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 1.03E-04 1.03E-04 1.03E-04 1.03E-04 1.03E-04 1.03E-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 2.03E-05 2.03E-05 2.03E-05 2.03E-05 2.03E-05 2.03E-05 0.00E +00 m

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

F-18 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI 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 9.23E-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 2.23E-03 Dose factor - airborne release pathway (mrem /Ci released)

Na-22 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin l Adult 4.83E +00 4.83E+00 2.89E+01 4.83E+00 4.83E +00 4.83E +00 4.83E +00 3.79E+01 l

l Teen 7.41 E+00 7.41E +00 3.15E+01 7.41E+00 7.41E +00 7.41E +00 7.41 E +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

f. m Infant 1.81E+01 1.81E+01 4.21 E +01 1.81E+01 1.81 E +01 1.81E+01 1.81 E +01 3.79E +01 b

Page 52 of 134 i

1 POINT BEACH NUCLEAR PLANT ODCM i OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 OFFSITE DOSE CALCULATION MANUAL (3

v Table 5.1-2, cont.

1 i

Dose factor - airborne release pathway (mrem /Ci released) l l Na-24 l Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin 1

Adult 9.48E-M 9.48E-04 1.77E-02 9.48 E-04 9.48E-04 9.48E-N 9.48 E-04 7.64E-02 l l

Teen 1.36E-03 1.36E-03 1.81E-02 1.36E-03 1.36E-03 1.36E-03 1.36E-03 7.64E-02 i l

Child 2.37E43 2.37E-03 1.91 E-02 2.37E-03 2.37E-03 2.37E-03 2.37E-03 7.64E-02 infant 3.14E-03 3.14E-03 1.99E-02 3.14E-03 3.14E-03 3.14E-03 3.14E-03 7.64 E-02 l Dose factor - airborne release pathway (mrem /Ci released)

Sc-46 l

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 3.41 E-02 2.00E +00 0.00E+00 3.26E-02 0.00E + 00 2.09E +00 2.69E+00 v

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 - airborne 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 2.01 E +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 2.03E-02 1.95E +00 0.00E +00 4.47E-03 2.97E-02 7.38E-03 2.28E+00 i

f O

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i POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 I OFFSITE DOSE CALCULATION MANUAL tm C Table 5.1-2, cont.

)

l 1

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

Cr-51 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin l

Adult 0.00E +00 0.00E +00 6.59E-03 2.68E-05 9.86E-06 4.83E-04 1.07E-02 7.73E-03 l Teen 0.00E +00 0.00E+00 6.60E-03 3.39E-05 1.34E-05 7.03E-04 9.66E-03 7.73E-03 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 l Infant 0.00E+00 0.00E +00 6.58E-03 2.42 E-05 5.31E-06 4.25E-04 1.02E-03 7.73E-03 Dose factor - airborne release pathway (mre:n/Ci released)

Mn-56 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 0.00E+00 4.81E-08 1.27E-03 0.00E +00 5.31 E-08 2.80E-04 6.01 E-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 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 2.13E-03 1.50E-03 l Dose factor - airborne release pathway (mrem /Ci released)

Fe-55 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 3.20E-01 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 8.65E-01 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 A

Page 54 of 134

POINT BEACII NUCLEAR PLANT ODCM J OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 )

OFFSITE DOSE CALCULATION MANUAL (3

y/ Tab'e 5.1-2, cont.

?

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

Fe-59 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin l Adult 2.01E-01 4.73E-01 5.65E-01 0.00E +00 0.00E+00 1.62E-01 1.58E+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 l Child 4.62E-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 l

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

Co-57 l

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

Child 0.00E +00 2.57E-02 5.26E-01 0.00E +00 0.00E +00 1.50E-02 2.ll E-01 6.13 E-01 Infant 0.00E+00 4.38E-03 4.81E-01 0.00E+00 0.00E +00 1.13E-02 1.50E-02 6.13E-01 Dose factor - airborne release pathway (mrem /Ci released)

Co-58 Bone Liver 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 6.38E-01 6.23E-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 5.73E-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 2.31 E-02 2.49E-02 6.23E-01 l

l l

O i

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POINT BEACII NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 OFFSITE DOSE CALCULATION MANUAL n

U Table 5.1-2, cont.

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

Co-60 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 1.77E-01 3.16E +00 3.56E+01 Teen 0.00E+00 2.23E-01 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 5.86E-02 3.04E +01 0.00E +00 0.00E +00 1.34E-01 1.40E-01 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 19

\ /

Teen 2.93 E +01 2.07E+00 9.92E-01 0.00E+00 0.00E+00 9.ll E-03 3.29E-01 0.00E + 00 Child 6.73 E +01 3.60E +00 2.29E +00 0.00E +00 0.00E +00 8.16E-03 2.43E-01 0.00E+00 Infant 2. llE +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 8.95E-08 1.19E-08 4.17E-04 0.00E +00 0.00E+00 1.66E-04 3.66E-04 4.85 E-04 Teen 1.06E4)7 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 2.43E-04 2.49E-03 4.85E-04 Infant 7.17E-08 8.51 E-09 4.17E-04 0.00E +00 0.00E +00 2.41 E-04 1.49E-03 4.85E-04 l

Page 56 of 134

POINT BEACH th TCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 OFFSITE DOSE CALCULATION MANUAL Table 5.1-2, cont.

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

Cu-64 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 0.00E +00 1.12E-05 8.57E-04 0.00E +00 2.82E-05 2.01 E-04 2.40E-03 9.65E-04 Teen 0.00E +00 1.40E-05 8.58E-04 0.00E +00 3.54E-05 3.30E-04 2.90E-03 9.65E44 Child 0.00E+00 2.19E-05 8.65E-04 0.00E+00 5.28E-05 2.84E-04 2.llE-03 9.65E-04 ;

Infant 0.00E+00 3.42E-05 8.68E-04 0.00E+00 5.79E-05 2.76E-04 1.15E-03 9.65E-04 l

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

Zn-65 1

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

Adult 1.21E +00 3.85E +00 2.79E +00 0.00E +00 2.57E +00 2.56E-02 2.42E+00 1.21E+00 l

/9 V

Teen 1.63 E + 00 5.67E +00 3.69E +00 0.00E + 00 3.63E+00 3.68E-02 2.40E +00 1.21E +00 Child 3.12E+ 00 8.31 E +00 6.22E +00 0.00E + 00 5.24E+00 2.95E-02 1.46E +00 1.21E +00 Infant 2.95E +00 1.01E +01 5.71 E+00 0.00E +00 4.91 E +00 1.92E-02 8.54 E +00 1.21E + 00 l

J Dose factor - airborne release pathway (mrem /Ci released) l Zn-69 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 3.01E-06 5.76E-06 4.01E-07 0.00E +00 3.74E-06 2.73E-05 1.35E-06 0.00E +00 Teen 4.64E-06 8.83E-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 l

Infant 1.93E-05 3.48E-05 2.59E-06 0.00E +00 1.45E-05 4.36E-05 3.23E-03 0.00E+00 j 1

1 I

I gm L) l Page 57 of 134 l l

i POINT BEACH NUCLEAR PLANT ODCM l OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 OFFSITE DOSE CALCULATION MANUAL

,r h ;

V Table 5.1-2, cont. l I

Dose factor - airborne release pathway (mrem /Ci released) l i Zn-69m I l

Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 4.99E-05 1.20E-04 3.07E-03 0.00E+00 7.26E-05 5.65E-04 1.13 E-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 5.74E4)3 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 Infant 3. ll E-04 6.35E-04 3.12E-03 0.00E+00 2.57E-04 7.93E-04 1.00E-02 5.74E-03 l

I 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 6.41E-02 O

iN)

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 Child 0.00E +00 0.00E +00 7.04E-02 0.00E+00 0.00E+00 0.00E+00 0.00E +00 6.41 E-02 l Infant 0.00E +00 0.00E + 00 8.32E-02 0.00E +00 0.00E + 00 0.00E+00 0.00E+00 6.41E-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 1.65E-05 0.00E+00 0.00E +00 0.00E +00 6.89E-06 2.84E-03 l Teen 0.00E +00 0.00E +00 1.96E-05 0.00E+00 0.00E +00 0.00E +00 0.00E + 00 2.84E-03 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 2.84 E-03 em l Page 58 of 134 i

POINT BEACll NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 OFFSITE DOSE CALCULATION MANUAL r

b) Table 5.1-2, cont.

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 2.59E-02 0.00E+00 0.00E +00 0.00E +00 1. llE-09 2.49E-01 I 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 Dose factor - airborne release pathway (mrem /Ci released)

Br-85 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 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 Child 0.00E +00 0.00E+00 2.02E-05 0.00E + 00 0.00E+00 0.00E +00 0.00E +00 2.63E-04 l

0.00E+00 0.00E+00 Infant 4.2 Fd-05 0.00E +00 0.00E+00 0.00E+00 0.00E+00 2.63E-04 Dose factor - airborne release pathway (mrem /Ci released)

Rb-86 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 0.00E +00 8.21E-01 3.95E-01 0.00E +00 0.00E+00 0.00E +00 1.61 E-01 1.44E-02 Teen 0.00E +00 1.23E +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 0.00E +00 4.17E +00 2.07E +00 0.00E+00 0.00E +00 0.00E +00 1.07E-01 1.44E-02 0's N.s Page 59 of 134

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()

P Table 5.1-2, cont.

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

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

Rb-89 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin l 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 C Teen 0.00E +00 1.04 E-05 1.80E-04 0.00E+00 0.00E +00 0.00E +00 1.00E-14 2.07E-04 i

( Child 0.00E+00 1.02E-05 1.81 E-04 0.00E +00 0.00E +00 0.00E + 00 5.61 E-08 2.07E-04 j Infant 0.00E +00 9.51E-06 1.79E-04 0.00E +00 0.00E +00 0.00E+00 2.02E-06 2.07E-04 l

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

Sr-89 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 7.63E +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 3.53E-05 Child 2.77E+0! 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 1.05E-01 0.00E +00 0.00E+00 6.02E-02 7.69E-02 3.53E-05 I

O Page 60 of 134

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 OFFSITE DOSE CALCULATION MANUAL m

k_) Table 5.1-2, cont.

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

( Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 5.10E +02 0.00E +00 1.25E +02 0.00E+00 0.00E +00 2.85E-01 1.47E+01 0.00E+00 l Teen 6.33E +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 7.33E+01 0.00E+00 1.84 E + 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 Liver 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 3.53E-03

! () Teen 2.20E 04 0.00E +00 3.03E-03 0.00E +00 0.00E + 00 1.80E-03 8.68E-03 3.53E-03 l Q) l Child 4.09E-04 0.00E +00 3.03E4)3 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 l

Dose factor - airborne release pathway (mrem /Ci released) i Sr-92 l

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

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 3.15E-03 l

l 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 1

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 i

l l

/^;

L) l

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/~s, V Table 5.1-2, cont.

l l

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

Y-90 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin !

Adult 7.17E-05 0.00E +00 8.23E-06 0.00E +00 0.00E +00 5.03E-03 1.19E-01 7.45E-06 )

l 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-N 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 1

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

/O 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 l

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

Y-91m Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 3.58E-06 0.00E +00 2.31E-04 0.00E +00 0.00E+00 5.70E-05 1.05E-05 4.33E-04 Teen 6.15E-06 0.00E +00 2.31E-04 0.00E + 00 0.00E +00 9.49E-05 2.91E-04 4.33E-04 Child 1.50E-C5 0.00E +00 2.31E-04 0.00E + 00 0.00E+00 8.34E-05 2.94E-02 4.33E-04 Infant 1.21E-08 0.00E +00 2.31E-04 0.00E+00 0.00E +00 8.27E-05 6.98E-05 4.33 E-N t

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

Y-92 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 3.35 E-05 0.00E +00 4.38E-04 0.00E +00 0.00E +00 4.65E-04 5.83E-01 2.90E-02 )

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 1.42E-04 0.00E +00 4.41E-04 0.00E +00 0.00E+00 7.09E-04 4.09E+00 2.90E-02 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 1

l 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 4.43E-04 0.00E +00 0.00E+00 1.44E-03 3.35E +00 6.58E-02 1

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 )

V I Child 4.53E-04 0.00E+00 4.52 E-04 0.00E +00 0.00E +00 2.21 E-03 6.69E+00 6.58E-02 Infant 4.45 E-06 0.00E +00 4.40E-04 0.00E+00 0.00E+00 2.27E-03 4.95E-03 6.58E-02 Dose factor - airborne release pathway (mrem /Ci released) 3 Zr-95 i

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

f Adult 4.79E-03 1.54E-03 3.45E-01 0.00E +00 2.42E-03 5.25E-02 1.64 E +00 3.98E-01 !

i Teen 6.16E4)3 1.94E-03 3.45E-01 0.00E +00 2.85E-03 7.98E-02 1.35 E +00 3.98E-01 !

l 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 !

l Infant 3.43E-03 8.27E-04 3.44E-01 0.00E +00 9.23E-04 5.19E-02 9.12E-04 3.98E-01 !

i i

O d ,

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

Zr-97 Bone Liver T. Body Thyroid 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 l

Teen 4.31E-06 8.52E-07 4.16E-03 0.00E +00 1.29E-06 3.85E-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 l Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin l Adult 1.39E-03 7.75E-04 1.92E-01 0.00E+00 7.67E-04 1.50E-02 3.30E +00 2.26E-01 1

! [3 Teen 1.39E-03 7.72E-04 1.92E-01 0.00E+00 7.48E-04 2.23E-02 1.99E +00 2.26E-01 j L.)

Child 2.22E-03 8.65E-04 1.93E-01 0.00E +00 8.13E-04 1 32E-02 1.10E +00 2.26E-01 Infant 6.08E44 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 t

i Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 2.05E-06 5.17E-07 4.17E-04 0.00E +00 6.03E-07 7.12E-05 1.91E-03 3.20E-03 Teen 3.50E-06 8.68E-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 4.17E-04 0.00E +00 1.70E-06 1.01E-04 4.73E-01 3.20E-03 Infant 1.01E-08 2.16E-09 4.17E-04 0.00E +00 1.69E-09 9.84E-05 7.98E-04 3.20E-03 (3

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

Mo-99 l Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skm Adult 0.00E+00 9.10E-03 7.34 E-03 0.00E +00 2.06E-02 2.71E-03 2.85E-02 6.50E-03 Teen 0.00E+00 1.24E-02 7.97E-03 0.00E +00 2.84 E-02 4.56E-03 3.02E-02 6.50E-03 Child 0.00E +00 2.06E-02 1.07E-02 0.00E +00 4.41 E-02 4.02E-03 2.08E-02 6.50E-03 Infant 0.00E + 00 3.82E-02 1.31E-02 0.00E +00 5.70E-02 4.00E-03 1.40E-02 6.50E-03 Dose factor - airborne release pathway (mrem /Ci released)

Tc-99m Bone Liver T. Body Thyroid Kidney Lungs GILLI Skin Adult 2.92E-09 8.24E-09 2.59E-04 0.00E +00 1.25E-07 2.27E-05 1.28E-04 2.96E-04 O Teen 3.llE-09 8.68E-09 2.59E-04 0.00E +00 1.29E-07 3.42E-05 1.87E-04 2.96E-04 O

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 2.41 E-05 6.33E-05 2.96E-04 Dose factor - airborne release pathway (mrem /Ci released)

Tc-101 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 1.16E-05 1.67E-05 2.08E-04 0.00E +00 3.01E-04 2.04E-05 5.06E-17 5.80E-04 Teen 1.99E-05 2.83E-05 3.23E-04 0.00E +00 5.12E-04 3.71E-05 4.87E-12 5.80E-04 Child 4.89E-05 5.12E-05 6.93E-04 0.00E +00 8.72E-04 4.44 E-05 1.63E-04 5.80E-04 Infant 1.93E-12 2.44E-12 4.44E-05 0.00E+00 2.90E-11 1.73E-05 2.50E-05 5.80E-04 Page 65 of 134

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V Table 5.1-2, cont.

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

Ru-103 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 4.36E-02 0.00E+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 2.32E-02 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 5.05 E-04 1.77E-01 l

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

Ru-105 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 6.19E44 0.00E+00 2.07E-03 0.00E +00 7.99E-03 3.2SE-04 3.80E-01 1.02E-02 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 4.72E44 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 1.44E-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 3.18E +00 2.78E-01 1.06E +02 7. ll E-01 Teen 1.49E +00 0.00E +00 7.81E-01 0.00E+00 2.88E +00 4.77E-01 7.16E +01 7. ll E-01 Child 2.93E +00 0.00E +00 9.58E-01 0.00E+00 3.96E +00 4.25E-01 4.55E +01 7. llE-01 Infant 2.67E-03 0.00E +00 5.93E-01 0.00E +00 3.28E4)3 3.43E-01 5.60E-03 7. llE-01 O

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

Rh-105 l l l Bone Liver T. Body Thyroid Kidney Lungs GI LLI Skin Adult 4.81E42 3.52E-02 2.47E-02 0.00E +00 1.50E-01 5.72E-04 5.61E +00 7.74E-03 Teen 8.33 E-02 6.02E-02 4.10E-02 0.00E +00 2.56E-01 9.71 E-04 7.66E +00 7.74E-03 l

Child 2.04 E-01 1.10E-01 9.53E-02 0.00E +00 4.37E-01 8.59E-04 6.80E +00 7.74E-03 i

Infant 7.15E-04 4.68E-04 1.83E-03 0.00E +00 1.30E-03 8.64E-04 1.22E42 7.74E-03 i

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 l

O Teen 6.28E-02 5.94E-02 4.86E +00 0.00E +00 1.13E-01 2.00E-01 1.66E +01 5.63 E +00 kJ Child l 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 7.31 E + 00 5.63E +00 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 5.03E-04 0.00E +00 3.07E-01 4.46E+00 4.02E+00 Child 5. l l E-01 6.63E-03 1.48 E + 00 1.13E-03 0.00E +00 3.79E-01 3.19E +00 4.02E +00

, Infant 6.72E-02 9.90E-04 1.32E+00 1.78E-04 0.00E +00 1.20E-01 2.06E-01 4.02E +00 1

i

()3

Page 67 of 134 l

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POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL, Revision 9 July 6,1995 l

OFFSITE DOSE CALCULATION MANUAL (3 i V Table 5.1-2, cont.

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

Sb-125 I Bone Liver T, Body Thyroid Kidney Lungs GI-LLI Skin Adult 1.07E-01 1.20E43 5.38E +00 1.09E-04 0.00E +00 1.33E-01 1.17E+00 9. llE +00 Teen 1.61E-01 1.76E-03 5.39E +00 1.54E-04 0.00E +00 2.21E-01 1.24 E +00 9.ll E +00 Child 3.69E-01 2.84 E-03 5.43E +00 3.42E-04 0.00E +00 2.73E-01 8.75 E-01 9. l l E +00 Infant 8.33E-02 8.05E-04 5.37E +00 1.04E-04 0.00E+00 9.99E-02 1.09E-01 9.l l E+00 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 5.11E-01 1.84 E-01 8.32E-02 1.43E-01 0.00E +00 1.59E-02 1.51 E+00 3.96E-02 l 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 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 4.47E-06 1.61E-06 5.15E-06 3.31E-06 1.82E-05 1.93E 04 2.05E-03 4.60E-06 Teen 4.34E-06 1.55E-06 5.12E-06 3.00E-06 1.76E-05 3.32E-04 2.73E-03 4.60E-06 Child 8.13E-06 2.20E-06 5.93E46 5.63E-06 2.31E-05 2.98E-04 1.98E-03 4.60E-06 l 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

l p

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July 6,1995 OFFSITE DOSE CALCULATION MANUAL Table 5.1-2, cont.

Dose factor - airborne release p thway (mrem /Ci released)

Te-127m Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 1.19E+00 4.26E-01 1.54E-01 3.05E-01 4.84E +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 6.16E-02 Child 3.32E+00 8.94E-01 4.03E-01 7.94E-01 9.47E+00 4.39E-02 2.69E+00 6.16E-02 Infant 1.96E-01 6.50E-02 3.26E-02 5.66E-02 4.82E-01 3.89E-02 7.96E-02 6.16E-02 Dose factor - airborne release pathway (mrem /Ci released)

Te-129 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI 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. llE-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 2.12E-09 7.62E-09 8.71E-05 7.56E44 4.36E-05 Infant 2.34E-09 1.03E-09 3.68E-05 2.00E-09 5.19E-09 8.89E-05 7.81E-04 4.36E-05 Dose factor - airborne release pathway (mrem /Ci released)

Te-129m Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Aduli 1.39E+00 5.19E-01 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 9.07E-01 Child 4.53E+00 1.26E+00 7.18E-01 1.46E +00 1.33E+01 5.23E-02 5.53E +00 9.07E-01 Infant 1.39E-01 4.77E-02 3.66E-02 5.34 E-02 3.48E-01 4.98E-02 8.46E-02 9.07E-01 O

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/

b} Table 5.1-2, cont, t

I l

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

Te-131 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin

{ Adult 1.47E-03 6.14E-04 5.56E-04 1.21E-03 6.43E-03 4.13E-05 2.09E4% 1.63E-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 4.73E-03 1.87E-02 6.09E-05 3.25E-02 1.63E-03 l Infant 5.15E-10 2.44E-10 9.27E-05 4.69E-10 1.18E-09 6.llE-05 2.44E-04 1.63E-03 1 1

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

Te-131m l 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 Teen 2.21E-01 1.06E-01 1.10E-01 1.60E-01 1.l lE +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 Dose factor - airborne release pathway (mrem /Ci released)

Te-132 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI 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 Teen 3.19E-01 2.02E-01 2.00E-01 2.13E-01 1.94E+00 1.33E-02 6.42E+00 1.32E-02 Child 7.61E-01 3.37E-01 4.17E-01 4.91E-01 3.13E +00 1.12E-02 3.39E+00 1.32E-02 Infant 3.94E-03 1.95E-03 i 1.17E-02 2.88E-03 1.22E-02 1.01 E-02 8.50E-03 1.32E-02 l

l l

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POINT BEACH NUCLEAR PLANT ODCM l

OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 OFFSITE DOSE CALCULATION MANUAL Table 5.1-2, cont.

Dose factor - airborne release pathway (mrem /Ci released) l I-131 Bone Liver T. Body Thyroid Kidney Lungs GI LLI Skin Adult 7.16E-02 1.02E-01 8.29E-02 3.36E+01 1.76E-01 0.00E+00 2.69E-02 2.93E-02

Teen 6.57E-02 9.19E-02 7.35E-02 2.68E +01 1.58E4)1 0.00E+00 1.81E-02 2.93E-02 Child 1.44 E-01 1.45E-01 1.07E-01 4.80E +01 2.38E-01 0.00E +00 1.29E-02 2.93E-02 Infant 2.04E-01 2.40E-01 1.30E-01 7.89E+01 2.80E-01 0.00E +00 8.56E-03 2.93E-02 l

l Dose factor - airborne release pathway (mrem /Ci released) l I-132 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 3.44E-05 9.67E-05 1.78E-03 3.40E-03 1.54E-04 0.00E + 00 1.21E-05 2.06E-03 l

Teen 4.73E-05 1.30E-04 1.80E-03 4.49E-03 2.05E-04 0.00E +00 3.78E-05 2.06E-03 l 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 1.05E44 1.79E-03 5.03E-03 1.17E-04 0.00E +00 5.65E-05 2.06E-03 Dose factor - airborne release pathway (mrem /Ci released) 1-133 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 1.46E-03 2.53E-03 4.21E-03 3.71E-01 4.41E-03 0.00E+00 2.14E-03 4.19E-03 Teen 1.49E-03 2.52E-03 4.21 E-03 3.53E-01 4.42E43 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 j Infant 3.16E-03 4.59E-03 4.79E-03 , 8.37E-01 5.40E-03 0.00E+00 7.45E-04 1.19E-03 1

l

[

Page 71 of 134

l POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 l OFFSITE DOSE CALCULATION MANUAL O t V Table 5.1-2, cont. l Dose factor - airborne release pathway (mrem /Ci released)

I-134 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 1.91E-05 5.13E-05 6.45E-04 8.85E-04 8.17E-05 0.00E +00 2.99E-08 7.45E-04 Teen 2.63E-05 6.88E-05 6.52E-04 1.17E-03 1.09E-04 0.00E +00 6.05E-07 7.45E-04 j Child 3.48E-05 6.41 E-05 6.57E-04 1.50E-03 9.79E-05 0.00E +00 2.83E-05 7.45 E-04 Infant 2.73E-05 5.57E-05 6.47E-04 1.32E-03 6.19E-05 0.00E +00 3.83E-05 7.45 E-04

=

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

I-135 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 9.31E-05 2.43E-04 3.64E-03 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 4.92 E-04 0.00E +00 2.41E-04 4.14E-03 I f'

u _

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 1.23E-04 2.43E-04 3.64E-03 2.22E-02 2.70E-04 0.00E +00 6.06E-05 4.14E-03 l 1

l l

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 5.15E +00 1.71E +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 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 I l

Infant 1.96E+01 3.66E +01 1.33E +01 0.00E +00 9.42 E+00 3.86E +00 9.94E-02 1.12E +01 l l

l l

I Page 72 of 134 i

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Dose factor airborne release pathway (mrem /Ci released)

Cs-134m Bone Liver T. Body Thyroid Kidney Lungs GI-LL ' Skin Adult 8.36E 04 1.76E-03 9.41E-04 0.00E +00 9.54E-04 1.50E-04 6.19E-04 6.90E-05 Teen 1.40E-03 2.89E-03 1.53E-03 0.00E +00 1.61 E-03 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 4.70E-05 0.00E+00 3.53E-06 8.31 E-07 4.82E-06 6.90E-05 Dose factor - airborne release pathway (mrem /Ci released)

Cs-136 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult - 3.31E-01 1.31E +00 1.28E +00 0.00E +00 7.27E-01 9.97E-02 1.48E-01 4.73E-01 O

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 l

Child 1.14E +00 3.14E +00 2.38E +00 0.00E +00 1.67E +00 2.49E-01 1.10E-01 4.73E-01 Infant 3.54E-01 1.04E +00 7.33 E-01 0.00E+00 4.15E-01 8.48E-02 1.58E-02 4.73E-01 Dose factor - airborne release pathway (mrem /Ci released) l 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 4.42 E +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 1

O l

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/

( Table 5.1-2, cont.

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

Cs-138 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin ,

l Adult 2.17E-03 4.28E-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 4.13E-03 0.00E+00 5.23E-03 6.08E-04 3.21E-06 4.39E-03 Child 8.93E-03 1.24E-02 8.46E-03 0.00E +00 8.73E-03 9.40E-04 5.71E-03 4.39E-03 jInfant 1.50E-05 2.32E-05 5.97E-04 0.00E+00 1.22E-05 1.94E-06 2.60E-05 4.39E-03 Dose factor - airborne release pathway (mrem /Ci released)

Ba-139 Bone Liver T. Body Thyroid Kidney Lungs Gl-LLI Skin Adult 3.78E-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 Child 1.61E-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-I l 2.75E-05 0.00E+00 7.04E-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 3.65E-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 1.23E-01 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

\

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i l

U Table 5.1-2, cont.

l Dose factor - airborne release pathway (mrem /Ci released) i Ba 141 l Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin i l

Adult 1.83E-03 1.39E-06 2.01 E-N 0.00E+00 1.29E-06 2.38E-05 8.66E-13 1.55E-03 l Teen 3.16E-03 2.36E-06 2.45E-04 0.00E +00 2.19E-06 4.07E-05 6.75 E-09 1.55E-03 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 1.86E-09 1.28E-12 1.39E-04 0.00E +00 7.72E-13 3.53E-05 5.64 E-05 1.55E-03 l

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

La-140 l

Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 1.17E-05 5.91E-06 2.70E-02 0.00E +00 0.00E +00 4.04E-03 6.96E-02 3.06E-02 Teen 1.57E-05 7.71E-06 2.70E-02 0.00E +00 0.00E +00 6.36E-03 5.51E-02 3.06E-02 i Child . 2.18E-05 7.60E-06 2.70E-02 0.00E +00 0.00E +00 5.42E 03 3.26E-02 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

.T Dose factor - airborne releaw 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 9.71E-03 Teen 8.44E-06 3.75E-06 1.97E-03 0.00E +00 0.00E+00 1.21 E-04 1.14 E-01 9.71E-03 Child 2.04E-05 6.50E-06 1.97E-03 0.00E +00 0.00E+00 1.03 E-N 1.29E +00 9.71E-03 Infant 1.22E-08 4.48E-09 1.97E-03 0.00E +00 0.00E+00 9.77E-05 7.07E-04 9.71 E-03 O

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i POINT BEACH NUCLEAR PLANT ODCM l OFFSITE DOSE CALCULATION MANUAL Revision 9 )

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1 I

V Table 5.1-2, cont.

1 Dose factor airborne release pathway (mrem /Ci released) 1 Ce-141 J l

Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin i Adult 7.38E-04 5.01E-04 1.93E-02 0.00E +00 2.32E-04 1.07E-02 3.84E-01 2.16E-02 i Teen 1.05 E-03 7.02E-04 1.93E-02 0.00E+00 3.29E-04 1.82E-02 4.02E-01 2.16E-02 l

Cbild 1.65E-03 8.20E-04 1.93E-02 0.00E +00 3.59E-04 1.61E-02 3.02E-01 2.16E-02 l Infant 8.32E-04 5.00E-N 1.92E-02 0.00E +00 1.58E-N 1.53E-02 3.79E-03 2.16E-02 i

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

Ce-143 l Bone Liver T. Body Thyroid Kidney Lungs GI LLI Skin l 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 O Teen 1.15E-04 8.10E-02 4.81 E-03 0.00E+00 3.74E-05 1.55E-03 2.44 E +00 6.60E-02 LJ Child 2.77E-N 1.48E-01 4.82E-03 0.00E +00 6.31 E-05 1.37E-03 2.17E +00 6.60E-02 l

infant 3.55E-06 5.06E-05 4.80E-03 0.00E+00 6.85E-07 1.38E-03 8.73E-04 6.60E-02 Dose factor - airborne release pathway (mrem /Ci released)

Ce-144 Bone Liver 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 l

l Teen 1.83 E-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

~

l 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]

i

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/^%

V Table 5.1-2, cont.

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

Pr-143 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 5.11E-04 2.05E-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 4.05E-05 0.00E +00 1.89E-04 5.74E-03 2.16E+00 3.77E-01 Child 1.82E-03 5.46E-04 9.02E-05 0.00E +00 2.96E-04 5.15E-03 1.73E + 00 3.77E-01 Infant 1.67E-04 6.23E-05 8.32E-06 0.00E+00 2.35E-05 5.14E-03 i 5.83E-04 3.77E-01 Dose factor - airborne release pathway (mrem /Ci released)

Pr-144 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 8.93E-10 3.70E-10 2.58E-06 0.00E +00 2.09E-10 3.01 E-05 6.39E-16 2.96E-06 3 Teen 1.27E-09 5.22E-10 2.58E-06 0.00E +00 2.99E-10 5.20E-05 6.98E-12 2.96E-06

[O Child 1.77E-09 5.48E-10 2.58E-06 0.00E +00 2.90E-10 4.64 E-05 5.84 E-06 2.96 E-06 Infant 1.42E-09 5.48E-10 2.58E-06 0.00E +00 1.99E-10 4.78E-05 1.27E-04 2.96E-06 Dose factor - airborne release pathway (mrem /Ci released)

Nd-147 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 8.95E-05 1.03E-04 2.00E-02 0.00E +00 6.04E-05 2.62E-03 1.51E-01 2.00E-01 Teen 1.22E-04 1.33E-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 3.75 E-05 3.83E-03 4.73E-04 2.00E-01 b3 Page 77 of 134

i POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 l i

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Table 5.1-2, cont.

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

Eu-152 1

Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 3.32E-07 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+0! 0.00E +00 4.73E-02 4.76E-02 1.23E+00 6.86E +01 Child 6.02E-02 1.10E-02 3.62E+01 0.00E+00 4.64E-02 3.96E-02 8.25E-01 6.86E+01 j Infant 1.30E-02 2.95E-03 3.62E +01 0.00E +00 9.90E-03 2.46E-02 5.31E-04 6.86E +01 Dose factor - airborne release pathway (mrem /Ci released) ;

W-187 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 4.08E-03 3.41 E-03 7.22E-03 0.00E+00 0.00E +00 3.45E-04 1.12E +00 2.79E-02 O Teen 6.98E-03 5.69E-03 8.03E-03 0.00E +00 0.00E +00 5.63E-04 1.54E +00 2.79E-02 i O Child I

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 I infant 1.13E-05 7.88E-06 6.04E-03 0.00E+00 0.00E +00 4.71E-04 8.79E-01 2.79E-02 i l

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

! U-235 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 4.06E +01 0.00E+00 1.04 E + 01 0.00E+00 9.47E+00 4.66E +00 3.87E+00 1.06E +01 l Teen 6.45E +01 0.00E+00 1.19E +01 0.00E +00 1.51E +01 8.03E +00 4.59E +00 1.06E +01 l Child 1.54E +02 0.00E+00 1.73E +01 0.00E+00 2.53E+0! 7.17E +00 3.58E +00 1.06E +01 l t

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 l

l Page 78 of 134 l

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 l OFFSITE DOSE CALCULATION MANUAL l Table 5.1-2, cont.

Dose factcr airborne release pathway (mrem /Ci released)

U-238 Bone Liver T. Body Thyroid Kidney Lungs GI-LLl ' Skin Adult 3.88E+01 0.00E +00 2.33E +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 3.23E +00 2.47E-01 l

Child 1.48E +02 0.00E+00 8.79E+00 0.00E+00 2.37E+01 6.73E+00 2.53E+00 2.47E-01 '

l Infant 1.12E +01 0.00E+00 8.63E-01 0.00E +00 2.33E+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 9.55 E-01 9.52E-03 Teen 8.79E-05 8.29E-06 5.55E-03 0.00E +00 2.60E4)5 7.71E-04 1.27E +00 9.52E-03 Child 2.llE-04 1.52E-05 5.55E-03 0.00E+00 4.39E-05 6.91E-04 1.10E +00 9.52E-03 l

Infant 4.42 E-06 3.95E-07 5.54E-03 0.00E+00 7.88E-07 7.07E-04 3.14E-04 9.52E-03 )

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

Am-241 i Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 1.34E +02 4.76E+01 1.03E+01 0.00E +00 6.70E +01 5.76E +00 3.48E +00 2.94E +00 i

0.00E+00 Teen 1.46E +02 5.59E +01 1.11 E+01 7.31E +01 9.99E+00 4.12E+00 2.94E+ 00 l Child 1.37E+02 6.14E+01 1.ll E+01 0.00E+00 5.98E +01 8.88E+00 3.22E+00 2.94E +00 l

l 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 l

O V

l Page 79 of 134

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 OFFSITE DOSE CALCULATION MANUAL 5.1.3 Atmospheric Release Mode: Noble Gases The dose calculations for demonstration of compliance with the 10 CFR 50, Appendix 1 dose limits for noble gases released to the atmosphere will be done in the manner similar to the liquid release dose calculations described in Section 5.1.1. The total 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 Doseg = E ( TDF,i x C i ) s K, mrem where API = the Appendix I dose for compliance evaluation in mrem Dosei t = the dose to the applicable target (t) from radionuclide (i)

TDFri = total dose factor from Table 5.1-3 in mrem /Ci for the specific (gf target (t) from radionuclide (i) based on the maximum annual average x/Q at the site boundary Ci= curies of radionuclide (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.

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OFFSITE DOSE CALCULATION MANUAL O i 1

I Table 5.1-3 l

Activity to Dose Con,ersion Factors for Noble Gases ;

(Highest Annual Average X/Q) l Beta Air Gamma Air Skin Whole Body I Nuclide (mrad /Ci) - (mrad /Ci) (mrem /Ci) (mrem /Ci)

AR-41 1.56E-04 4.42E-04 2.94E-M 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 KR-89 5.04E-04 8.23E-04 5.53E-N 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-M 4.38E-04 2.94E-M 5.37E-04

,Q V

Page 81 of 134

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! POINT BEACH NUCLEAR PLANT ODCM l OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 OFFSITE DOSE CALCULATION MANUAL l

iO

V 6.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Requirements for the PBNP environmental monitoring program are detailed in Technical Specification 15.7.7. A complete description of the PBNP radiological environmental monitoring program, including procedures and responsibilities, is contained in the PBNP Environmental Manual. The latter is hereby incorporated into the Offsite Dose Calculation Manual (ODCM) by reference. ,

l l l 7.0 P.ADIOLOGICAL IMPACT EVALUATION OF SEWAGE TREATMENT SLUDGE I

. 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.

l 7.1 Basis ,

l 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 l sewage treatment sludge and compare them to concentration limits prior to disposal.

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

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

l 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.

l

4. Vegetable ingestion pathway from vegetables grown on plot.

I

5. Inhalation of radioactivity resuspended in air above plot.

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6. Pathways associated with a release to Lake Michigan. These pathways are ingestion of potable water at the Two Rivers, Wisconsin municipal water supply, ingestion of fish from edge of initial mixing zone of radionuclide !

release, ingestion of fresh and stored vegetables irrigated with water from Lake Michigan, ingestion of milk and meat from cows utilizing Lake l Michigan as drinking water source, swimming and boating activities at the edge of the initial mixing zone, and shoreline deposits.

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

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 l

representative samples required is three from each sludge storage tank.

The average of all statistically valid concentration determinations will be utilized in determining the sludge storage tank concentration values.

3 l (V 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 applications. The activity from these prior disposals will be corrected for radiological decay prior to performing dose calculations for the meat, milk, and vegetable ingestion pathways, the inhalation of resuspended radionuclides, and all pathways associated with a potential release to Lake Michigan. The residual radioactivity will be corrected, if applicable, for the mixing of radionuclides in the soil prior to performing external exposure calculations.

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POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 l OFFSITE DOSE CALCULATION MANUAL Wisconsin Electric utilizes QAD, a nationally recognized computer code,

, to perform shielding and dose rate analyses. QAD will be used to calculate l the dose rate due to standing on a plot of land utilized for sludge disposal in which the radionuclides from prior disposals have been incorporated into the plot by plowing. This calculated dose rate will be used to assess the radiological consequences from prior disposals with the consequences I

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.

l The methodology for calculating the radiological impact of the sewage

! treatment sludge disposal is contained in Appendix E.

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

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

l 7.3 Administrative Reauirements I l

(~T l V l 7.3.1 Complete records of each disposal shall be kept as follows:

l l l a. Radionuclide concentration of the sludge.

l l b. Total volume of sludge disposed.

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

l l d. Dose calculation results.

l l e. Results of annual chemical composition determination.

l l 7.3.2 Modifications to the October 8,1987, NRC submittal l

l a. Modification 1 - Appendix F l

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

l change.

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( l b. Modification 2 - Appendix G l

l In Section 3.3 of Attaciunent II of the submittal letter, the annual l disposal rate was "... limited to 4,000 gallons / acre, provided WDNR l chemical composition, NRC dose guidelines and activity limits are l maintained...." Modification 2 removes the 4,000 gallon limit and l makes the application unlimited provided the WDNR and NRC l constraints are met.

v)

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I POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 OFFSITE DOSE CALCULATION MANUAL O

APPENDIX A i

DERIVATION OF LIQUID RELEASE PATHWAY EFFECTIVE MAXIMUM EFFLUENT CONCENTRATION O

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! OFFSITE DOSE CALCULATION MANUAL Revision 9 l July 6,1995 OFFSITE DOSE CALCULATION MANUAL G

V A1.0 DERIVATION OF LIOUID RELEASE EFFECTIVE MAXIMUM EFFLUENT l CONCENTRATION l l l t 1 A1.1 Source Term 1 1

l l The effective maximum efnuent 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 efuuent i l because it was used for tests run on the steam system. Tritium also was omitted i from the initial calculation because its production is largely independent from the l appearance of the fission products in the effluent.

l l A1.2 Effective Maximum Effluent Concentration l

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 l where:

SOF = E C,/MEC iis the summation of fractions for the annual effluent isotopic release l C=

i concentration of radionuclide "i" ( Ci/ml) in effluent (annual l discharge / total volume of discharge) 1 MEC i = maximum effluent concentration for unrestricted areas from Appendix B, Table 2, Column 2 of the revised l 10 CFR 20.

The SOF for radionuclides in liquid effluent for the years 1985 through 1991 were calculated with and without H-3 and used to calculate the EMEC for the same years (Table B-2). The average EMEC without H-3 is 4.29E-06 pCi/cc. This is the maximum concentration of non H-3 radionuclides in a mixture that could be released l

in liquid effluent without the SOF exceeding one (1).

l 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 NaI 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/MEC) i i or EC i* 0.70/SOF.

1 Page 87 of 134

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 l OFFSITE DOSE CALCULATION MANUAL The EMEC becomes EMEC = 0.70

4.29E-06 = 3.00E-06 pCi/cc.

I Only three radionuclides identified in PBNP liquid effluent have a lower MEC ;

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

By restricting the non-tritium radionuclides to 70% of their calculated EMEC, the H-3 concentration can be discharged at 30% ofits MEC or 3.00E-04 pCi/cc without exceeding the SOF criterion of 10 CFR 20, Appendix B for the total liquid effluent isotopic mixture.

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July 6,1995 l

OFFSITE DOSE CALCULATION MANUAL p

( TABLE A-1 CURIES RELEASED IN LIQUIDS j

LIOUID F ELEASES NUCLIDE 1985 1986 1987 1988 1989 1990 1991 11-3 1.00E-03 8.05 E + 02 8. ll E + 02 7.09E + 02 3.57E + 02 5.59E + 02 8.72 E + 02 7.87E + 02 I-131 1.00E4)6 1.02 E-01 3.74E-02 1.34E-02 1.40E-03 1.77E 03 1.53 E4M 1.83E-03 j 1-132 1.00E-04 6.15 E-02 7.25 E-02 5.82E-02 1.03E43 815E4)4 4.45E-05 9.41 E-03 l I-133 7.00E4M 1.27E-01 1.49E-01 1.04E4)1 1.21E4)2 8. l l E-03 3.0l E4)3 1.0l E-02 l l-134 4.00E44 3.18E4)2 4.39E-02 3.97E-02 2.29E4M 6.83E4)4 1 1-135 3.00E-05 1.(M E-01 1.34E4)1 1.23E-01 4.48E-04 8.21 E-04 AG-110M 6.00E-06 2.55E4)5 2.84E4M 3.09E-03 9.85E4)4 4.70E4M l.71E4M 4.06E-04 BA-133 2.00E-05 BA 139 2.00E-04 8.63E-06 2.47E4M BA-140 8.00E4M 6.90E-06 4.45E-05 6.13E4)5 CD-109 6.00E4M 6.33 E-05 1.31 E-04 CE-139 7.00E-05 CE-141 3.00E4)5 1.3 t E-03 7.50E4M C E-144 3.00E4)6 1.37E-03 2.08 E-03 4.76E4)4 1.59E414 9.47 E-06 9.64E4M CO-56 6.00E-06 CO-57 6.00E4)5 2.52E4)3 1.33E-04 3.21 E-04 5.07E-05 6.90E-07 4.08 E-06 l CO-58 2.00E-05 4.05E-01 9.02 E-03 3.36E-02 6.81E4)3 3.12E-03 3.25E4M 2.93E-03 CO-60 3.00E-06 2.88E-01 2.85E-02 6.34E4)2 2.04E-02 1.54E4)2 1.41 E-03 5.53E413 CR-51 5.00E4M 2.7] E-02 3.16E-04 1.58E 02 5.31 E4)5 4.44E44 8.71E4)5 l CS-134 9.00E-07 4.76E-02 6.92E 03 1.18E-03 4.%E4M 1.49E4)3 CS-134M 2.00E-03 3.59E-04 5.97E4)6 4.67E-04 CS-136 6.00E4M CS-137 1.00E4)6 9.60E-02 2. ll E4)2 7.54E-03 8.63 E-03 2.80E-03 1.94E-03 8.93E-03 l

! CS-138 4.00E4M 1. l l E4)3 5.48 E-03 3.24E4)3 F-18 7.00E4M 1.00E 02 1.67E-02 7.56E-04 1.66E43 2.26E-03 4.06E4M FE-59 1.00E-05 2.76E4M LA-140 9.00E-06 MN-54 3.00E-05 7.46E-03 1.18E 03 4.68E4)3 1.54E-04 2.68E4M 3.10E-05 1.%E4)4 MO-99 2.00E-05 3.70E-05 N B-95 3.00E-05 6.28 E-03 6.65E44 3.21 E4)3 1.61 E4)4 2.33E4)6 8.68E-05 NB-97 3.00E4M 1.35E-03 5.22E-04 6.16E-05 1.06E 05 3.90E-06 8.80E-06 5.30E4)6 RB-88 4.00E4M 8.46E-05 1. l l E-02 3.33E-03 j R B.89 9.00E4M 7.98E4M 2.34E-04 RU-103 3.00E4)5 3.59E-03 1.68E4)6 8.41 E-04 5.86E4)5 RU-106 3.00E4M 8.07E4M 2.88E-03 7.33E4)3 1.(ME4)4 j

SB-124 7.00E4)6 3.86E-02 2.%E44 1.42E4M 2.34E-04 l SB 125 3.00E-05 1.12 E-02 1.20E-03 1.95E4)3 1.00E 03 2.12 E-02 1.28E-05 1.08 E-02 SNil3 3.00E4)5 1.07E-03 4.20E-05 513E4M 3.2 t E-04 3.07E-06 SR-89 8.00E-06 2.27E-04 3.46E 05 3.89E4)3 2.68E-03 8.69E-06 SR-90 5.00E-07 1.29E-03 2.28E-04 2.80E-04 3.50E-04 2.55E4M TC-99M 1.00E-03 1.75E4)5 3.75E-06 3.30E-05 TC 101 2.00E-03 1.10E-05 TE-131 8.00E-05 7.98E4)5 TE-132 9.00E4)6 5.83E4)7 6.94 E-05 2.74E-05 7.19E-06 1.74E4M l

l W-187 3.00E4)5 3.4 t E-05 Y-91 M 2.00E4)3 ZN-65 5.00E-06 5.15E4)5 ZR-95 2.00E-05 7.95E-05 2.61E4)4 2.45E-03 1.58E-05

, O ZR-97 9.00E4)6 1.49E-06 3.09E-06 1.74E-05 TOTAL CI 8.06E + 02 8.12E + 02 7.10E + 02 3.57 E + 02 5.59E + 02 8.72 E + 02 7.87E + 02 TOTAI. W/O 11-3 1.37 E + 00 5.39E4)1 5.12 E.01 5 99E-02 5.65 E-02 9 57E4)3 5.42E-02 Page 89 of 134

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 OFFSITE DOSE CALCULATION MANUAL r

TABLE A 2 FRACTIONAL MEC IN LIQUID EFFLUENT NUCLIDE MEC 1985 1986 1987 1988 1989 1990 1991 uCi/cc 11-3 1.00E413 1.27E-03 1.25E4)3 1.04F 43 5.17E4M 8.36E4M 1.26E4)3 1.22 E-03 I 131 1.00E-06 1.6l E-04 5.75E4)5 1.52 E-05 2.03E4M 2.65E4M 2.21 E-07 2.84E4)6 l-132 1.00E4M 9.70E4)7 1.12 E-06 8.53E-07 1.49E48 1.22E-08 6.43E-10 1.46E4)7 I 133 7.00E4)6 2.86E-05 3.27E-05 2.18E4)5 2.51E4M 1.73E4M 6.21 E-07 2.24E-06 1-134 4.00E4M 1.25E-07 1.69E4)7 1.46E417 8.30E-10 2.65E-09 I 135 3 00E-05 5.47E4)6 6.87E46 6.01E46 2.16E-08 4.24E4)8 AG-110M 6.(X)E-06 6.70E-09 7.28E-08 7.55E-07 2.38E4)7 1.17E 07 4.12E-08 1.05E4)7 BA 133 2.00E-05 BA-139 2.00E4M 6.33E-l l 1.79E4)9 BA-140 8.00E-06 1.36E4)9 0.00E + 00 8.16E4)9 1. l l E-08 CD-109 6.00E4)6 1.62 E4)8 3.16E-08 CE-139 7.00E4)5 CE-141 3.00E-05 6.89E-08 3.67E4)8 CE-144 3.00E-06 7.03 E-07 1.02E46 2.30E-07 7 92E-08 4.56E-09 4.98E4)9 CO-56 6.00E-06 CO-57 6.00E-05 6.62 E-08 3.41 E4)9 7.84E-09 1.22 E-09 1.72E-11 9.83E-Il CO-58 2.00E-05 3.19E-05 6.94 E-07 2.46E-06 4.93E-07 2.33E-07 2.35E-08 2.27E-07 CO-60 3.00E4)6 1.51E4M 1.46E-05 3.10E-05 9.86E-06 7.67E4M 6.79E4)7 2.86E-06 CR-51 5.00E4M 8.55 E-08 9.72 E-10 4.63E-08 1.54E-10 1.33E-09 2.52E-10 CS-134 9.00E-07 8.34E 05 1.18 E-05 1.92 E-06 7.99E417 2.57E-06 CS 134M 2.00E4)3 2.60E-10 4.46E-12 3.62E-10 CS-136 6.00E-06 CS-137 1.00E4V l .51 E-04 3.25E-05 1. l l E-05 1.25E4)5 4.19E4)6 2.80E-06 1.38 E-05 CS-138 4.00E4M 4.38E-09 2. l l E-08 1.19E4)8 F-18 7.00E-04 2.20E-08 3.50E-08 1.57E-09 3.54E-09 4.67E-09 8.99E-10 FE-59 1.00E-05 4.05E48 LA 140 9.00E-06 M N-54 3.00E4)5 3.92 E-07 6.05 E-08 2.29E47 7.44E-09 1.34 E-08 1.49E49 1.0lE4)8 MO-99 2.00E-05 2.68 E-09 NB 95 3.00E4)5 3.30E-07 3.4 t E 08 1.57E-07 7.78E-09 1.16E-10 4.18E49 NB-97 3.00E4M 7.10E-09 2.68 E-09 3.01 E-10 5.12E-Il 1.94 E-I l 4.24 E-I l 2.74E 11 RB-88 4.00E 04 3.34E-10 4.27E 08 1.22 E-08 RB-89 9.00E44 1.36E-09 3.81 E-10 RU-103 3.00E4)5 1.89E-07 8.62 E-i l 4.11 E-08 2.83E-09 RU-106 3.00E-06 4.24E-07 1.48E-06 3.58E4)6 5.02 E-08 SB-124 7.00E4M 8.70E-06 6.51 E-08 2.97E-08 4.84E-08 SB 125 3.00E-05 5.89E-07 6.15 E-08 9.53E-08 4.83 E-08 1.06E-06 6.17 E-10 5.58E4)7 SNll3 3.00E-05 5.63E-08 2.15E-09 2.5 t E-08 1.55E4)8 1.59E-10 SR 89 8.00E-06 4.48E-08 6.65E-09 7.13E-07 4.86E-07 1.62 E-09 S R-90 5.00E417 4.07E-06 7.02 E-07 8.21 E-07 1.01 E-06 7.62E-07 TC-99M l .00E-03 2.76E-Il 5.77E-12 4.78E 11 TC-101 2.00E-03 8.06E-12 TE 131 81)0E-05 1.45E-09 TE 132 9.00E-06 1.02 E-10 1.19E-08 4.46E-09 1.16E-09 3.00E-08 l W-187 3.00E-05 1.65E49 Y-91M 2.00E-03 ZN-65 51X)E4M 1.5 I E-08 ZR-95 2.00E-05 6.27E-09 2.0lE4)8 1.80E-07 1.14 E-09 O ZR-97 9.00E-06 2.61 E-10 5.28E 10 2.80E-09 d I Page 90 of 134

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 OFFSITE DOSE CALCULATION MANUAL TABLE A 2, (cont.)

FRACTIONAL MEC IN LIQUID EFFLUENT 1985 1986 1987 1988 1989 1990 1991 l ANNUAL VOL(CCs) 6.34 E + 14 6.50E + 14 6.82E + 14 6.90E + 14 6.69E + 14 6.92E + 14 6.45E + 14 TOT FRACTION 1.90E4)3 1.4 t E 03 1.14E4)3 5.48E4M 8.54E4M l .26E4)3 1.25E43 FRAct W/O H 3 6.29E4M 1.61E44 9.83 E45 3.(M E415 1.85E4)5 4.41 E4M 2.55E4)5 TOTAL Cl 8.06E + 02 8.12 E + 02 7.10E + 02 3.57 E + 02 5.59E + 02 8.72 E + 02 7.87 E + 02 TOTAL W/O 113 1.37 E + 00 5.39E4)1 5.12E411 5.99E4)2 5.65E-02 9.57E4)3 5.42E-02 TOT CONC (uCi/CC) 1.27E4M 1.25E.06 1.04E4M 5.17E-07 8.36E417 1.26E-06 1.22E4M TCON W/O li.3 2.16E-09 8.30E 10 7.51 E-10 8.69E Il 8.44E-Il I .38 E-I l 8.40E-I l EMEC 6.70E4)4 R.86E4M 9.14E4)4 9.45E-04 9.78E4M 9.97E4M 9.80E4M EMEC W/O 113 3.43E4M 5.14E4m 7.64E4M 2.85 E-06 4.56E4M 3.14E4M 3.30E4M l

l

^\

! (Q

?

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l I

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POINT BEACll NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 OFFSITE DOSE CALCULATION MANUAL O

I APPENDIX B DERIVATION OF ATMOSPHERIC RELEASE MODE EFFECTIVE MAXIMUM EFFLUENT CONCENTRATION l

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f POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 OFFSITE DOSE CALCULATION MANUAL Bl.0 DERIVATION OF ATMOSPHERIC RELEASE EFFECTIVE MAXIMUM EFFLUENT CONCENTRATION Bl.1 Source Term l

l The effective maximum effluent concentration (EMEC) for atmospheric effluents is calculated from the annual releases for the years 1985 - 1991 (Table B-1). Unlike l liquid releases, tritium was not omitted from the EMEC calculation. Instead, the EMEC was calculated with H-3 and then modified by the fraction of non-tritium radionuclides in the effluent.

Bl.2 Effective Maximum Effluent Concentration l 1

The maximum concentration of a radionuclide mixture that is allowable at the site !

boundary is called the effective maximum effluent concentration (EMEC). The l EMEC for an effluent mixture is defined by the equation l EMEC = ECi / E(Ci / MEC)i where l

lq Ci = concentration of radionuclide "i" l 19 MECi = maximum effluent concentration for radionuclide "i" from 10 CFR 20, Appendix B, Table 2, Column 1 E (C i/ 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 which is the radionuclides released during the years 1985 - 1991. The average annual site boundary concentration for each year was calculated using the highest annual average x/Q of 1.56E-06 sec/m3 . Then the total EMEC was calculated for each year (Table C-2). The average total EMEC is 8.04E-08 i 1.31E-08 pCi/cc with a range of 5.84E-08 to 9.50E-08 Ci/cc. Next, the annual EMEC was modified for the l presence of H-3, which is not detected by the atmospheric RMS, by multiplying each EMEC by the ratio of the non H-3 concentration to the total concentration. The annual H-3 corrected EMECs were averaged to obtain a value of 1.92E-08 i 1.23E-08 pCi/cc with a range of 5.02E-09 to 3.70E-08 Ci/cc.

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POINT BEACH NUCLEAR PLANT ODCM I OFFSITE DOSE CALCULATION MANUAL Revision 9 ,

1 July 6,1995 l OFFSITE DOSE CALCULATION MANUAL j O

V TABLE B 1 CURIES IN ATMOSPilERIC EFFLUENT NUCLIDE MEC 1985 1986 1987 1988 1989 1990 1991 uCi/mi I 11-3 1.00E-07 6.71 E + 01 1.20E + 02 1.18E + 02 1.26E + 02 1.42 E + 02 1.28 E + 02 1.13 E + 02 l AR-41 1.00E-08 1.27 E + 00 6.8 t E-01 2.17E + 00 1.%E + 00 1.57 E + 00 1. l l E + 00 1.07 E + 00 KR-85M 1.00E-07 1.84 E + 0i 6.77E41 1.18E + 00 7.31E4)I 2.24E-01 1.85E-01 1.03E-01

)

KR-85 7.00E417 1.67E + 01 1.32 E + 00 7. llE4)1 9.84E4)I 3.58E-01 1.78E411 2.74E-01 l KR 87 2.00E-08 4.78 E + 00 1.0l E + 00 2.37E + 00 1.48 E + 00 4.94E4)1 4.05E-01 2.3 t E-01 l KR-88 9 00E-09 5.73 E + 00 1.30E + 00 2.72 E + 00 1.69E + 00 5.64 E-01 4.49E-01 2.56E4)1 l XE-131M 2.00E 06 8.54E-02 l XE 133M 6.00E 07 3.30E-01 1.38 E-01 2.12 E4)1 3.35 E-01 4.94E-03 2.06E-02 3.97E-02 l XE 133 5.00E-07 3.45 E + 01 1.53 E + 01 2.06E + 01 6.04E + 0i 7.54 E + 00 1.%E + 00 1.60E + 01 XE-135M 4.00E418 5.76E + 00 1.27E + 00 3.68E + 00 2.54E + 00 7.37E-01 6.49E-01 3.44E-01 XE 135 7.00E-08 1.19E + 01 3.21 E + 00 ShlE + 00 3.53 E + 00 1.08 E + 00 1.09E + 00 6.03E4)1 XE-138 2.00E4)8 1.65 E + 0! 2.91 E + 00 8.87E + 00 7.19E + 00 2.45 E + 00 1.99E + 00 1.06E + 00 AG110M l .00E-10 2.31 E-07 BA 133 9.00E-10 BA-139 4.00E-08 1.17E47 BA 140 2.00E4)9 3.41 E-07 CD-109 2.00E-10 8.92 E-06 1.26E4M 2.28E4M CE 139 9.00E-10 CE-141 8.00E 10 8.48E-09 CE-144 2.00E-I l 2.04E-06 3.92E477 3.94 E-09 i CO-57 9.00E-10 2.10E-07 2.52 E-l l 1.13E4)8 1.23E4M 4.80E-07 )

, i CO.-58 1.00E4)9 1.57E4M 1.33 E-05 1.01E4M 3.59E4)$ 1.69E4M 2.74E4)5 3.85E4M l CO-60 5.00E-I l 7.94E4)5 1.llE-04 1.18E-05 3.64E44 1.63E4M 3.56E4m 1.06E4M CR51 3.00E-08 5.28E4M 7.58E4)9 CS-134 2.00E-10 1.18E4)3 9.49E4M 5.86E-05 7.27E-05 1.10E-03 )

CS-136 9.00E-10 CS 137 2.00E-10 4.02E-03 2.94E4M 3.08E4M 6.74E4M 2.10E-03 1.91E4M 1.90E 03 i CS-138 8.00E4)8 9.ME-07 1.92 E4M 1.85E4)3 1.26E-07 3.44E-06 1.92 E-02 F 18 1.00E4)7 1.08E4)$ 2.52E4M 3.87E 05 3.31 E4M 1.10E-05 6.60E4M l FE-59 7.00E-10 4.87E4)9 MN-54 1.00E-09 l .99E-06 1.70E4M 4.86E4)5 MO-99 2.00E4)9 7.27E4)9 2.71 E-08 l NA-24 7.00E4)9 1.39E-04 4.32 E4M 4.29E-04 I

__ N B-95 2.00E4)9 2.52E4M 7.70E4)7 5.97E-07 6.25 E-08 9.56E 10 NB-97 1.00E-07 1.60E-08 1.65E4)9 RB-88 9.00E-08 4.63E4)$ 3.46E-05 1.03 E-02 4.00E4M I .81 E 05 1.62E-01 RB-89 2.00E-07 _

4.30E4)9 RU-103 9.00E-10 1.91 E-08 1.89E-05 SB 125 7.00E 10 1.25 E-07 3.68 E4M 9.39E-08 l SN 113 8.00E-10 2.16E4)8 4.80E-10 l SR-89 2.00E 10 4.87E-08 1.54 E4M 7.70E4)7 3.7 l E-06 SR-90 6.00E 12 1.68 E-10 4.30E4M SR-91 5.00E-09 TC-99M 3.00E417 6.43E4)8 2.20E4)7 9.24E4)7 TC-101 5.00E4)7 TE-132 9.00E-10 3.07E4M 7.33E-08 2.34E4M Y-88 3.00E-10 1.28E-10 ZN-65 4.00E-10 9.27E-06 O ZR-95 4.00E-10 1.31 E-06 3.56E-09 7.43 E-10 Z R-97 2.00E4)9 2.97E-10 l

Page 94 of 134 !

l

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 OFFSITE DOSE CALCULATION MANUAL

>D l Cl TABLE B 1,(cont.)

CURIES IN ATMOSPIIERIC EFFLUENT NUCLIDE MEC 1985 1986 1987 1988 1989 1990 1991 l uCi/ml i 1 131 2.00E-10 3.44E4)3 1. I I E-03 3.08 E4)3 5.43 E4M 3.18E44 7.85E4)5 3.46E4M l 1 132 2.00E4)8 3.75E4)3 1.79E413 2.42E4)3 4.78E-04 4.20E4)5 1.09E4)$ 2.95 E-05 1-133 1.00E-09 1.37E4)3 6.80E4M 3.lM E4)3 1.53 E-03 1.19E-03 1.13E4M l.13E4M l134 6.00E-08 1.33E4)5 9.32 E4M j

I.135 6.00E4)9 5.79EIM 1.09E4M 2.19E4)3 9.18 E415 1.20E-05 3.15E-08 1.58E-05 l O

Page 95 of 134

l l POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 l July 6,1995 l

OFFSITE DOSE CALCULATION MANUAL l

Q TABLEB2 FRACTIONAL MEC FOR ATMOSPilERIC EFFLUENT NUCLIDE 1985 1986 1987 1988 1989 1990 1991 11 3 3.20E-05 5.71E4)$ 5.62 E-05 6 (X)E4)5 6.76E-05 6.10E-05 5.38E.05 AR41 6 05E44 3.24E4M l .03 E-05 9.33E4M 7.48E4M 5.29E4M 5.10E4M KR 85M 8.76E4M 3.22E4)7 5.62 E4)7 3.48E-07 1.07 E-07 8.81 E-08 4.90E4)8 KR 85 1.14E4M 8.98 E-08 4.84E4)8 6.69E-08 2.44 E-08 1.2 l E4)8 1.86E418 j KR-87 1.14E4)$ 2.40E4M 5.64E 4M 3.52E4M l.18E44 9.64E47 5.50E4)7 ~

KR 88 3 03E45 6 88E4M l .44E4)5 8.94E4M 2.98E4M 2.38E4M 1.35 E4M XE-131M 2.03E4)9 XE-133M 2.62E 08 1.10E4)8 1.68 E4)8 2.66E4)8 3.92E 10 1.63 E4)9 3.15E4)9 X E-133 3.29E-06 1.46E4)6 1.%E4)6 5.75E4M 7.18 E-07 1.87E-07 1.52 E4M l XE-135M 6.86E-06 1.5 t E-06 4.38E4M 3.02E4M 8.77E417 7.73E4)7 4.10E-07 XE-135 8.10E4M 2.18E4M 3 84E4M 2.40E4M 7.35E417 7.4 t E4)7 4.10E417 XE-138 3.93E-05 6.93E4)6 2. l l E-05 5.83E4M 4.74E-06 2.52 E-06 1.7 t E-05 AGIl0M l.10E 10 BA 139 1.39E-13 B A-140 8.12E 12 l CD-109 2.12 E4)9 3.00E-10 5.43E 08 CE-141 5.05E-13 CE 144 4.86E419 9.33E 10 9 38E-12 CO-57 1.llE Il I .33 E-15 5.98E-13 6.51E 11 2.54 E-I l CO-58 7.48E4)9 6 33E-10 4.8t E 09 1.7 l E4)9 8.05 E4)9 1.30E-09 l.83E 10 i i CO 60 7.56E-08 1.06 E-07 1.12 E-08 3.47E-07 1.55 E-07 3.39E4)9 1.01E 07 I CR 51 8.38E-10 1.20E 14 CS 134 2.8 t E-07 2.26E-07 1.40E-08 1.73E418 2.62 E417 CS-136 CS 137 9.57E417 7.00E4)8 7.33 E-08 I R)E-07 5.00E.07 4. 55 E-08 4.52 E-07 CS-138 5.74E-13 1.14E 12 1.10E4)9 7.50E-14 2.05 E-12 1.14 E-08 F-18 5.14E-12 1.20E-10 1.84E Il 1.58E-10 5.24E 12 3.14 E-10 FE 59 3.3 t E-13 MN 54 9.48 E-I l 8.10E Il 2.3 l E419 MD-99 1.73E-13 6.45E 13 NA 24 9.46E 10 2.94E4)9 2.92E-09 NB-95 6.00E Il 1.83 E-l l I .42 E-I l 1.49E-12 2.28E 14 NB 97 7.62 E-15 7.86E 16 RB-88 2.45E Il 1.83 E-I l 5.45E-09 2.12E 12 9.58E 12 8.57E4)8 RB.89 1.02E 15 RU 103 1.01 E-12 1.00E-09 58 125 8.50E-12 2.50E 10 6 39E 12 l SNll3 1.29E 12 2.86E 14 SR 89 1.16E-l l 3.67 E-10 1.83 E-10 8.83E 10 SR 90 1.33 E-12 3.4 t E-08 l SR-91 TC-99M 1.02E 14 3.49E-14 1.47E-13 TC-101 TE 132 1.62 E-10 3.88E-12 1.24E 10 Y-88 2.03E 14 ZN-65 1.10E-09 ZR 95 1.56E 10 4.24E 13 8.85E-14 p ZR 97 7.07E-15 O

Page 96 of 134

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 OFFSITE DOSE CALCULATION MANUAL V TABLE B-2, (cont.)

FRACTIONAL MEC FOR ATMOSPilERIC EFFLUENT SUCLIDE 1985 1986 1987 1988 1989 1990 1991 1-131 8.19E4)7 2.64E-07 7.33E-07 1.29E-07 7.57E-08 1.87E418 8.24E4)8 l132 8.93E4)9 4.26E-09 5.76E-09 1.14E-09 1.00E-10 2.60E-Il 7.02E-11 1-133 6.52E-08 3.24E-08 1.45 E-07 7.29E-08 5.67E4)8 5.38E4)9 5.38E-09 l-134 1.06E Il 7.40E-10 1-135 4.60E-09 8.65E-10 1.74E418 7.29E-10 1.00E 10 2.50E-13 1.25E-10 TOTALFRAC 1.49E4)4 8.29E-05 1.20E-04 1. ll E4)4 8.83E4)$ 7.6? E4)5 6.67E-05 TOTAL-H3 1.17E4)4 2.57E-05 6.34 E-05 5.13E-05 2.07E-05 1.52E4)5 1.29E 05 EFF MEC 5.84E-08 8.49E-08 6.62 E-08 8.85E4)8 8.46E-08 8.50E-08 9.50E4)8 W/O 11-3 3.70E-08 1.60E-08 l .92 E-08 3.46E-08 8.10E4)9 5.02E-09 1.44E1 l

l l

l

.O V

l l

t l

l l

Page 97 of 134

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 OFFSITE DOSE CALCULATION MANUAL

O i

a I

i i

i APPENDIX C CALCULATION OF 'f0TAL DOSE FACTORS USING REGULATORY GUIDE 1.109, REV.1 O

Page 98 of 134

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 I July 6,1995 ;

OFFSITE DOSE CALCULATION MANUAL I C1.0 CALCULATION OF TOTAL DOSE FACTORS USING REGULATORY GUIDE 1.109 l METHODOLOGY l

l C1.1 Liauid Release Dose Factors l

The equations and values used to calculate the total dose to the maximum exposed l 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 l and target organ in a matrix format for each radionuclide in Section 5, Table 5.1.1.

i The derivation of dilution factors used in the calculations is presented in Appendix D.

The highest dose in each matrix is used as the dose tracking factor to be used for the monthly tracking of release doses. These values are found in Section 5, Table 5.2.

C1.1.1 Aauatic Foods The dose from the eating of fresh fish caught at the edge of the initial mixing zone was calculated using the equation:

i l O M PU'P

() Dose,g = 1100 Qi Bip D,igeM l

where:

l Dose g = the dose to the organ j of an individual of age group a from l all of the nuclides i in pathway p, in mrem / year; l 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 harvest of aquatic food, dimensionless; r U,p = a usage factor that specifies the intake rate for an individual of I 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,p = the equilibrium bioaccumulation factor for nuclide i in n pathway p, expressed as the ratio of the concentration in biota

!] (in pCi/kg) to the radionuclide concentration in water (in pCi/1), in liters /kg; l

Page 99 of 134

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 OFFSITE EOSE CALCULATION MANUAL D,ip; = 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-3; tg = the average transit time required for nuclides to reach the point of exposure. For internal dose, tpis the total time elapsed between release of the nuclides and the ingestion of the water, in days.

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

P

id = 1100 ap B,pD,;ge%

The values used in the equation above are:

M' = 0.1136 (Point of harvest of the fresh fish is taken at a point O tooo - o stre Thevi"=ece terii"eoii" tie"rectret this location is 8.8 using RG 1.111 methodology. The dilution factor calculations are attached. The factor of 2 allowed for current reversals was not used.);

U,p = Infant - 0, Child - 6.9, Teen - 16, and Adult - 21 kg/ year; F = 1507 ft3/sec. (677000 gpm);

B, 3

= Values used are taken from Table A-1 of RG 1.109; D,ip; = Values used are taken from Tables E-11 through E-14 of RG 1.109; tp = 0.5 days.

'.\

Page 100 of 134

l POINT BEACH NUCLEAR PLANT ODCM l OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 OFFSITE DOSE CALCULATION MANUAL C1.1.2 Irricated 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:

l l

Dose,g = 1100 P ** -4 QigF D,ige where:

Dose,g = the dose to the organ j of an individual of age group a from l all of the nuclides i in pathway p, in mrem / year; 1100 = factor to convert from Ci-sec/yr-ft3 to pCi/ liter; Mp = the mixing ratio (reciprocal of the dilution factor) at the point j of exposure, dimensionless; i

U,p = a usage factor that specifies the intake rate for an individual of j age group a associated with pathway p, in kg/ year; I

QAw = 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;

= the stable element transfer coefficient that relates the daily Fx i intake rate by es animal to the concentration in an edible portion of animal product, in pCi/ liter of meat per pCi/ day; l 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 ~ ;

I t, = the average time from slaughter to consumption, in days.

n

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POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 l

OFFSITE DOSE CALCULATION MANUAL l

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

Dow,;g _ MpU,,Qx,p .g The values used in the equation above are:

l 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.);

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

Fx i

= Values used are taken from Table E-1 of RG 1.109;

) D,ip; = Values used are taken from Tables E-11 through E-14 of l

l RG 1.109; l t, = 20 days.

I l

l l

I O

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POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 r

OFFSITE DOSE CALCULATION MANUAL n

i U C1.1.3 Irricated Foods (Milk 1 rom Watered Cattle)

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

P Qw A

F Dg **

~

Dose,g = 1100 where:

Dose g = the dose to the organ j of an individual of age group a from l all of the nuclides i in pathway p, in mrem / year; 1100 = factor to convert from Ci-sec/yr-ft3 to pCi/ liter; Mp = the mixing ratio (reciprocal of the dilution factor) at the point l

of exposure, dimensionless; l

U,p = a usage factor that specifies the intake rate for an individual of age group a associated with pathway p, in liters / 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; 1

Fri = the stable element transfer coefficient that relates the daily l intake rate by an animal to the concentration in an edible l 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; l Ai = the radioactive decay constant of nuclide i, in day ;

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

Page 103 of 134 i

, POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 OFFSITE DOSE CALCULATION MANUAL

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

,;PI = 100MP P ^"Fg D,;p3e ~4 Do The values used in the equation above are:

Mp =

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

! dilution factor at this location is 9 using RG 1.111 methodology, the dilution factor calculations are attached.

The factor of 2 allowed for current reversals was not used.

This is a conservative assumption.); j

, U,p = Infant - 330, Child - 330, Teen - 400, and Adult - 310

' i liters / year; I 1

Q4, = 60 liters / day; F = 1507 ft3 hec. (677000 gpm);

l Fa = Values used are taken from Table E-1 of RG 1.109; D,ip; = Values used are taken from Tables E-11 through E-14 of '

i RG 1.109; tr = 2 days. l l

l l

O Page 104 of 134

POINT BEACH NUCLEAR PLANT ODCM

! OFFSITE DOSE CALCULATION MANUAL Revision 9 ;

July 6,1995 OFFSITE DOSE CALCULATION MANUAL C1.1.4 Potable Water i

The dose from ingestion of water was calculated using the equasn:

! MU P ap Dose,g = 1100 Qi D,ge %

where:

Dose,p; = 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; ,

?

1 3

1100 = a factor to convert from Ci-sec/yr-ft to pCi/ liter; l l l M, = the mixing ratio (reciprocal of the dilution factor) at the point of withdrawal of drinking water, dimensionless; ;

1 U,p = a usage factor that specifies the intake rate for an individual of age group a associated with pathway p, in 1/ year; l F = the flow rate of the liquid effluent, in ft 3/sec; b" Qi = the release rate of nuclide i, in Ci/ year; D,ip; = 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-1; tp = the average transit time required for nuclides to reach the point of exposure. For internal dose, tp is the total time elapsed between release of the nuclides and the ingestion of the water, in days.

1 i

l 2

G i V Page 105 of 134

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 OFFSITE DOSE CALCULATION MANUAL 1

! O(~% 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:

= 1100 P SPDge "Er Qi F The values used in the equation above are:

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

l U,p = Infant - 330, Child - 510, Teen - 510, and Adult - 730 l liters / year; l

! F = 1507 ft3/sec. (677000 gpm);

O D,ip; = Values used are taken from Tables E-11 through E-14 of RG 1.109 1 t, = 2 days (This was calculated using a current speed of 12.2 cm/s plus 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months to reflect the transport of the water through the water purification plant and distribution system.)

l l

1 i

Page 106 of 134

i l l

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 OFFSITE DOSE CALCULATION MANUAL .

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

1 P a Dosend = 110000 i i gge %1 QTD - e"'%

where:

l Dose g = the dose to the organ j of an individual of age group a from ,

l all of the nuclides i in pathway p, in mrem / year; I l 110000 = a factor to convert from Ci-sec/yr-ft 3to pCi/ liter and to l account for the proportionality constant used in the sediment radioactivity model; Mp = the mixing ratio (reciprocal of the dilution factor) at the point l of exposure, dimensionless; l

U,p = a usage factor that specifies the exposure time for an individual of age group a associated with pathway p, in hours / year; W = shoreline width factor, dimensionless; F = the flow rate of the liquid effluent, in ft 3/sec; Qi = the release rate of nuclide i, in Ci/ year;

! Ti = the radioactive half life of nuclide i, in days; 1

l D,ig = the dose factor, specific to a given age group a, nuclide i, j pathway p, and organ j, which is used to calculate the I

radiation dose from an intake of a nuclide, in mrem /pCi; Ai = the radioactive decay constant of nuclide i, in day-1; l tp = the average transit time required for nuclides to reach the point of exposure. For internal dose, tp is the total time elapsed between release of the nuclides and the ingestion of the water, in days; D) t t3 = the period of time for which the sediment or soil is exposed to the contaminated water, in days.

Page 107 of 134

POINT BEACII NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 OFFSITE DOSE CALCULATION MANUAL A 1 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:

Dose I d = 110000M,UW B ipT iD,;pj e -x6(1 - e '*'**)

The values used in the equation above are:

Mp = 0.01821 (Point of exposure is taken as the Point Beach State Park beach which is located 8000 meters downstream. The plume shoreline dilution factor at this location is 54.9 using RG 1.111 methodology. The dilution factor calculations are attached. The factor of 2 allowed for current reversals was not used.);

U,p = Infant - 0, Child - 14, Teen - 67, and Adult - 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months / year; W = 0.3; B in - Values used are taken from Table A-1 of RG 1.109; F = 1507 ft3/sec. (677000 gpm);

D,ip; = Values used are taken from Table E-6 of RG 1.109; t, = 0.5 day; t3 = 5458 days.

O Page 108 of 134

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 OFFSITE DOSE CALCULATION MANUAL C1.2 Atmospheric Release Dose Factors: Non-Gaseous The equations and values used to calculate the total dose to the maximum exposed l 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 l 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 presented by age group and target organ in matrix format for each radionuclide in Section 5, Table 5-1. The highest dose in each matrix is used as the dose tracking factor to be used for the monthly tracking of release doses. These values are found in Section 5, Table 5-2.

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

/ 3 Dosep = 3.17E + 04R, -

<Q,

[Q DFl s

i ip j where:

O V Dosep = the annual dose to organ j of an individual of age group a due to inhalation, in mrem / year; 3.17E+04 = the number of pCi/Ci divided by the number of sec/ year:

R, = the annual air intake for individuals in the age group a, in m 3/ year, j x/Q = the annual average atmosphere dispersion factor, in sec/m 3 l (The location at which the dose was calculated was the site j boundary in the south sector - a distance of 1270 meters.); ;

Qi = the release rate of nuclide i, in Ci/ year; DFl ij = the inhalation dose factor for radionuclid,e i, organ j, and age group a, mrem /pCi. I Page 109 of 134

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 OFFSITE DOSE CALCULATION MANUAL To calculate the dose per curie released, the equation above was rearranged and the calculation performed for each nuclide. The rearranged equation is shown below:

Dose *.. = 3.17E sQ, 1>04

+ R*

DFI..

un Q i The values used in the equation above are:

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

x/Q = 9.36E-07 seconds /m3 (This value taken from Table I.4-2 of

the FSAR, release mode IB, annual average, site boundary.);

l DFI),

i

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

i C1.2.2 Annual Organ Dose From External Irradiation From Nuclides Denosited On the Ground i

O rae or8e" o 8e rr m exter >> irreaietto" rrom ##ciide devoeited o the ground was calculated using the equation:

Dosej - 1E+12 (8760) 6, S p Q(1 i

- e%)DFG ij i

where:

Dosej = the annual dose to the organ j, in mrem / year; 1E+ 12 = the number of pCi per Ci; 8760 = the number of hours in a year; Si = the annual average relative deposition of nuclide i, considering depletion of the plume during transport, 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; (q/

l Qi = the release rate of nuclide i, in Ci/ year; Page 110 of 134

l POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 1 July 6,1995 i

OFFSITE DOSE CALCULATION MANUAL Ai = the radioactive decay constant of nuclide i, in day-1; i

Ib = the time period over which the accumulation is evaluated, in days; DFGij = the open field ground plane dose conversion factor for organ j l

l from nuclide i, in mrem-m2/pCi-hour.

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

Dose;I = 1E+12 (8760)iSp S (1 - e46)DFG,;

Qi Ai l

The values used in the equation above are:

63 = 31E-09 m-2 (This value taken from Table I.4-2 of the FSAR, l release mode IB, annual average, site boundary.);

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

O t3 = 5479 days (15 years);

DFG ij = Values used are taken from Table E-6 of RG 1.109.

I l

O Page 111 of 134

l POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 l OFFSITE DOSE CALCULATION MANUAL C1.2.3 Annual Orean Dose From Atmospherically Released Nuclides In Milk l

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

~

Dose 3 - 2.7E+09 U,Qp6, { ig Q F DFl ip e *h {f,f, + e **'(1 - f pf,)}

i

^

r(1-e - Am '.) Bi ,(1 - e ^)

YA y ra 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 + 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 group a, in q liters / year; V

Qg = the amount of feed consumed by a cow per, in kg/ day; 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 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-1; t3 = the tirne 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; l F% = the average fraction of the animal's daily intake of nuclide i l which appears in each liter of milk, in days / liter;

0 tr = the average transport time of the activity from the feed into j V the milk and to ihe receptor, in days; Page 112 of 134

i POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 l July 6,1995 l OFFSITE DOSE CALCULATION MANUAL fp = the fraction of the year that the animals graze on pasture, dimensionless; j f, = the fraction of the daily feed that is pasture grass when the animal grazes on pasture, dimensionless; r = the fraction of the deposited activity retained on crops, i

dimensionless; l

the effective removal rate constant for nuclide i from crops, in Ag; =

days ~ , where Asi = Ai + A., and A, is the removal rate l constant for physical loss by weathering; 1

A, = 0.0504 day-1; 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,y = the concentration factor for the uptake of nuclide i in q pathway p, expressed as the ratio of the concentration in biota ih (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.

i l

Page 113 of 134

l POINT BEACH NUCLEAR PLANT ODCM

! OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 l OFFSITE DOSE CALCULATION MANUAL

(\

l Q 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 1

~

il' = 2 7E+9 U ,p, Q5 FgDFIije */' {f f, p + e ~*5(1 - f,f,)f

~

i I

X1 r(1 - e ^d.) + B (1 - e */*)

iy l

Yy31, PA 3 l

The values used in the equation above are:

( U, = Infant - 330, Child - 330, Teen - 400, and Adult - 310 liters / year; Qg = 50 kg/ day; 6 =

18.8E-09 m-2 (This value taken from Table I.4-2 of the l

l FSAR, release mode IB, grazing season, site boundary.);

F im = Values used are taken from Table E-1 of RG 1.109; DFlij, = Values used are taken from Tables E-11 through E-14 of RG 1.109; i

tr = 2 days; f, = 0.5; f, = 0.5; r = 0.25,1.0 for iodines, and 0.20 for noble gases, tritium, and i carbon-14; t, = 30 days; Yv = 0.7 kg/m2; B iy = Values used are taken from Table E-1 of RG 1.109; l P = 240 kg/m2; t3 = 5458 days (15 years).

v Page 114 of 134 l

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 OFFSITE DOSE CALCULATION MANUAL 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:

i

~

l Dosej = 2.7E+9 U,Qp 6 , { QiiFpFIge *'k {f f, + e *'(1 - f,f,)}

p ,

i l

~

l X<

'r (1 - e-Ad.) + Bi ,(1 - e *'4) r YA y ra PA, where: ,

1 Dosej = the annual dose to the organ j of an individual in age group a l l

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; U, = the ingestion rate of milk for individuals in age group a, in (q_./

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

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

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

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

1 l t3 = the time period over which the accumulation is evaluated, in I days; l

DFl ij = the dose conversion factor for the ingestion of nuclide i, organ j, and age group a, in mrem /pCi; Fri = the average fraction of the animal's daily intake of nuclide i which appears in each kilogram of flesh, in days /kg;

, p t, = the average time from slaughter to consumption, in days; V

Page 115 of 134

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 OFFSITE DOSE CALCULATION MANUAL he 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 grazes on pasture, dimensionless; r = the fraction of the deposited activity retained on crops, dimensionless; Agi = the effective removal rate constant for nuclide i from crops, in days-', where Agi = l i+ 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; Yv = the agricultural productivity, in kg (wet weight)/m2 ;

By = 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),

q in liters /kg; V

P = the effective surface density for soil, in kg (dry soil)/m2, For iodines, this factor is changed to 1.4E+09.

O Page 116 of 134

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 OFFSITE DOSE CALCULATION MANUAL To calculate the dose per curie released, the equation above was rearranged and the calculation performed for each nuclide. The rearranged equation is shown below:

~

4' = 2.7E+9 U,Qp5, PpFl i ige *#' {f,f, + e **'(1 - f pf,)f Xd r(1-e -As '.) + iyB (1 - e '*E*)'

YA, y 3 PA, l

The values used in the equation above are:

! l U, = Infant - 0, Child - 41, Teen - 65, and Adult - 110 kg/ year; Qp = 50 kg/ day; 6; =

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

l Fri = Values used are taken from Table E-1 of RG 1.109; DFl),i

= Values used are taken from Tables E-11 through E-14 of RG 1.109; 1

t, = 20 days; i fp = 0.5; f, = 1.0; r = 0.25,1.0 for iodines, and 0.20 for noble gases, tritium, and carbon-14; t, = 30 days; B,y = Values used are taken from Table E-1 of RG 1.109; Yv = 0.7 kg/m2; P = 240 kg/m2; A, = 0.0504 day-1; 1

i O t. =

5458 aev8cis e><s).

s Page 117 of 134

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 l July 6,1995 OFFSITE DOSE CALCULATION MANUAL C1.2.5 Annual Orean Dose From Atmospherically Released Nuclides In Produce The organ dose from atmospherically released nuclides in produce was calculated using the equation:

~

Dose 3 - 2.7E+9 U,f,6, Q,DFI,je _1A <

'(1_ e -Am '.) + B,y(1 - e *h)'-

p where:

Dosep = 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; U, = the ingestion rate of produce for individuals in age group a, in l kg/ year; q f, = fraction of produce ingested grown in garden of interest, Q dimensionless; i

5i = the annual average relative deposition of nuclide i, considering l

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 day4 ;

l t3 = the time period over which the accumulation is evaluated, in l

days;

\

DFI ip = the dose conversion factor for the ingestion of nuclide i, organ j, and age group a, in mrem /pCi; I

ta

= the holdup time that represents the time interval between i

harvest and consumption of the food, in days; r = the fraction of the deposited activity retained on crops, G dimensionless; V

Page 118 of 134

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 i July 6,1995 OFFSITE DOSE CALCULATION MANUAL l

l !

Agi = the effective removal rate constant for nuclide i from crops, in days-1, where Agi = Aj + A., and A, is the removal rate ;

constant for physical loss by weathering; I l t, = the time period that crops are exposed to contamination during the growing season, in days; i

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

1

\

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

l l

O Page 119 of 134 I

POINT BEACII NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 OFFSITE DOSE CALCULATION MANUAL To calculate the dose per curie released, the equation above was rearranged and the calculation performed for each nuclide. The rearranged equation is shown below:

a

= 2.7E + 9 U,f,5 { DFI ije-1'\ < r(1-e -A '.) + B ,(1 - e ~*6)

Doseil ' 3 Qi 3

i YA y 73 PA i The values used in the equation above are:

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

=

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

l DFI 33 = Values used are taken from Tables E-11 through E-14 of RG 1.109; tn

= 60 days; O

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

t3 = 5458 days (15 years).

Page 120 of 134 L __ _ _ _

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 OFFSITE DOSE CALCUIATION MANUAL C1.2.6 Annual Orean Dose From Atmospherically Released Nuclides In Leafy Vecetables The organ dose from atmospherically released nuclides in leafy vegetables was calculated using the equation:

~

Dose, r(1-e - Am '.) + Bi ,(1 - e **)'

j - 2.7E+9 U,f ia; Qi DFl),e - A < +

i where: I l

Dose), = the annual dose to the organ j of an individual in age group a j 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 l year; U, = the ingestion rate of produce for individuals in age group a, in kg/ year; fi = fraction of leafy vegetables ingested grown in garden of interest, dimensionless; 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 garden location in the south-southwest sector - a distance of 1460 meters.);

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

= the holdup time that represents the time interval between I harvest and consumption of the food, in days; l

l O r = the fraction of the deposited activity retained on crops, l O dimensionless; l

Page 121 of 134

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

POINT BEACH NUCLEAR PLANT ODCM !

l OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 OFFSITE DOSE CALCULATION MANUAL

( Aci =

the effective removal rate constant for nticlide i from crops, in days-1, where Ati = Ai + 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; Yv = the agricultural productivity, in kg (wet weight)/m2 ;

i B,, = the concentration factor for the uptake of nuclide i in l pathway p, expressed as the ratio of the concentration in biota l l

(in pCi/kg) to the nuclide concentration in water (in pCi/ liter), l 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.

l l

l t

t l

t Page 122 of 134

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 OFFSITE DOSE CALCULATION MANUAL To calculate the dose per curie released, the equation above was

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

- 2.7E + 9 U,f 6, { DFI e -x/* 4 '(1_ e -l '.) + B (1 - e****)'

a l Dose"..

iy 3 ij Qi i Yy 1, 3 PA, l The values used in the equation above are:

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

l fi = 1; l 6, =

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

l DFl ip = Values used are taken from Tables E-11 through E-14 of RG 1.109; tn

= 1 day; t

b v r = 0.25,1.0 for iodines, and 0.20 for noble gases, tritium, and carbon-14; A, = 0.0504 day-1; t, = 60 days; Yv = 0.7 kg/m2; B,y = Values used are taken from Table E-1 of RG 1.109; P = 240 kg/m2 ;

te

= 5458 days (15 years).

l O

Page 123 of 134

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 OFFSITE DOSE CALCULATION MANUAL C1.3 Atmospheric Release Dose Factors: Noble Gases The equations and values used to calculate the total dose factors for noble gases released to the atmosphere using Regulatory Guide 1.109, Rev.1,1977 is shown below. The dose factor in mrem /Ci and mrad /Ci released for each radionuclide is presented in Section 5, Table 5-1. I C1.3.1 Annual Gamma and Beta Air Dcse From All Noble Gas Releases The dose from the submersion of individuals in air containing noble gases was calculated using the equation:

DoseY or DoseP = 3.17E +04 1 Y E

<Q, {Q(DF i

i ior DFi )

where:

DoseY or l Dosed = the annual gamma and beta air dose, in mrad / year; 3.17E +04 = the number of pCi/Ci divided by the number of sec/ year; x/Q = the annual average atmosphere dispersion factor, in sec/m 3 O (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; DFT or DFi = the gamma and beta air dose factors for a uniform semi-infinite cloud of radionuclide i, in mrad-m3/pCi-year.

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

Y "

Dosei or Dosei

- 3.17E + 04 <1> (DFi Y or DF")

i Qi s Q, The values used in the equation above are:

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

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

Page 124 of 134

l l POINT BEACH NUCLEAR PLANT ODCM l

OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 OFFSITE DOSE CALCULATION MANUAL o

V C1.3.2 Annual Skin Dose From All Noble Gas Releases The skin dose from the submersion of individuals in air cor.taining noble l gases was calculated using the equation:

Dose = 3.17E + 04 x ' '1.11Sp { Q DF' + { Q DFS,'

i i i rQ>r s n ,

where: l 1

Dose =

the annual skin dose due to immersion in a semi-infinite cloud, in mrem / year; 3.17E +04 = the number of pCi/Ci divided by the number of sec/ year; 1.11 = the average ratio of tissue to air energy absorption coefficients; Sp = the attenuation factor that accounts for the dose reduction due to shielding provided by residential stmetures, dimensionless; C) x/Q = the annual average atmosphere dispersion factor, in sec/m3 (The location at which the dose was calculated was the site boundary in 'he south sector - a d: stance of 1270 meters.);

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

= the annual gamma air dose factor for a uniform semi-infinite cloud of nuclide i, in mrad-m 3/pCi-year; DFS i = 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 mrem-m3/pCi-year.

Page 125 of 134

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 OFFSITE DOSE CALCULATION MANUAL i

(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:

r Dose'

= 3.17E + 04 1>(1.11 S p DF[ + DFS;)

Qi (Qs 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 IB, annual average, site boundary.);

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

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

Dose = 3.17E +04 S p 1

-( { Q DFB, i

n 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; Sr = the attenuation factor that accounts for the dose reduction due to shielding provided by residential structures, dimensionless; XQ / = 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.);

i l Qi = the release rate of nuclide i, in Ci/ year; 1

DFB i = 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.

Page 126 of 134

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 OFFSITE DOSE CALCULATION MANUAL To calculate the dose per curie released, the equation above was rearranged and the celculation performed for each nuclide. The rearranged equation is shown below:

I r

Dose' = 3.17E + 04 S,1> DFB'.

l Qs rQi The values used in the equation above are:

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

=

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

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

O l

i o

LJ l

l Page 127 of 134 i

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 OFFSITE DOSE CALCULATION MANUAL O

l l

l 1

1 l

l APPENDIX D l

DERIVATION OF DILUTION FACTORS USING REGULATORY GUIDE 1.113 O

Page 128 of 134

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 OFFSITE DOSE CALCULATION MANUAL O

V D1.0 LIOUID EFFLUENT DILUTION FACTOR CALCULATIONS D1.1 Methodolony The dilution factors used for calculating the doses from liquid effluent released to Lake Michigan were calculated using the methodology of Regulatory Guide 1.113,

" Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I." The parameters used in the calculation and the results of the calculation are given in Table D-1. The results are presented graphically in Figure D-1.

The centerline and shoreline values w'ere calculated using Reg Guide 1.113 formulae 17 and 18 which apply to discharges to the Great Lakes. (The formulae are not presented here. See Section 5 of the PBNP FSAR for the formulae and origin of values used.) These results are applied as calculated for fish caught near PBNP.

But for other pathways, an extra factor of two (2) is applied to account for current reversals which occur in Lake Michigan as described in the Appendix I, Section 5, of the PBNP FSAR.

O O

Nge 129 of 134

.. . ._ = _ =.

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 OFFSITE DOSE CALCULATION MANUAL TABLE D-1 SURFACE DILUTION FACTORS LIQUID EFFLUENTS IN A LARGE LAKE Downstream Distance (meters) Plume Centerline Shoreline 10 8.81 20 8.81 30 8.81 40 8.81 50 8.81 60 8.81 70 8.81 80 8.8I i 90 8.81 100 8.81

(

200 8.81 300 8.81 1 400 8.81 500 8.81 600 8.81 700 8.81 800 8.81 900 8.81 1000 8.81 122000 '

2000 8.86 1758 l 3000 9.01 401 4000 9.25 186 5000 9.53 116 6000 9.85 83.8 7000 10.2 65.9 O-4 8000 9000 10.5 10.8 54.9 47.4 10000 11.I 42.I 20000 14.0 24 30000 16.1 20.1 40000 17.7 18.7 50000 18.8 18.3 60000 19.6 18.2 7(XXX) 20.3 18.3 80000 20.9 18.6 90000 21.4 I8.9 ItXXX)0 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 800000 42.6 41.0 900000 44.8 43.3 1000000 46.9 45.5 NOTE: Tha* walues were cakulated using ne equarum described in Section 5.2 of ne PBNP F54R and defollowing walnes:

e, = 900 cd/sec r., = 0 meters e, = 2 cdhec d = 10 meters a = 12.2 cm/see h = 10 meters y, = 152.5 meters b = 305 meters and a discharge rate of 42.2 dhec.

O Page 130 of 134

o o o Dilution Factor at Surface !@a Liquid Effluents in a Large Lake lll 0 Ek DF per Unit Release Rate R Mj=

1.0E+06 = C o2 E 5 >R

d Er

"~*"

1.0E+05 *.",'s'($ l c m 2 / . . o : 8"'"*

- u = 12.2 c m / s e c

- Y(s) = 152.5 m

gy g>

- Z(s) = 0 m "Z

"C y

g 1.0E+04 a :g= m r >

[ b lb = 305 m a-a - Dischargs rate - 4 2.2 m* 3 / s.c G

0 O F a

] 1.0E+03 -

1.OE+0 2 a c yg

! eiom. c.ni.riin. . _

h0 1.0E+01 ;

!5 5

1.0E+00 1.0E+01 1.0E+02 1.0E+03 1.0E+ 04 1.0 E+ 05 1.0E+06 Downstream Distance (in meters)

Area source, width 305 m and height 10 m

l

! POINT BEACH NUCLEAR PLANT ODCM l OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 OFFSITE DOSE CALCULATION MANUAL l r-~

l D1.2 Dilution Factor Twelve Miles Downstream: Two Rivers Water Intake l The dilution factor used at the Two Rivers water intake twelve miles downstream from PBNP included the factor of two described in Section D1.1. However, instead of using the straight centerline dilution factor shown in Table 1, the weighted average l dilution factor calculated over the width of the plume was used.

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

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 1 I

1000 feet out into the lake from the shoreline.

Based on these two considerations, it was concluded that the weighted average {

dilution across the width of the plume as it diverges while flowing south would p)

( constitute a better estima'e of the dilution factor instead of the calculated for the

)

centerline of an area soure as is assumed for the FSAR calculation. The calculation and the values used are shown below.

The average dilution factor at 12 miles downstream was calculated in the following manner: 1

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 e, x x "y " h u where ey = lateral turbulent diffusion coefficient in cm 2/sec l

x = the downstream distance in cm u = current in cm/sec l

p Substituting the values for cy , x, and u of 900 cm2 /sec,19308 m, and

( 12.2 cm/sec, respectively, into the equation yields Page 132 of 134

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCUIATION MANUAL Revision 9 July 6,1995 OFFSITE DOSE CALCULATION MANUAL cm 2 C" 2 x 900 19308 m x 100 sec m 12.2 E sec l

oy = = 168.8 meters i 100 E '

m I 1 l 2. At distances of 0.10,0.20, etc., off the plume centerline, the dilution factor was calculated using the equation shown in Section 5.2 of the PBNP ;

FSAR. The distances off the plume centerline, the calculated dilution l l factor, and the fraction of the area under the normal distribution curve is listed below. l l

Distance Off Plume Centerlme Fraction of Total Fraction of Equivalent Area Under the Standard Distance Curve for Deviation (m) Interval Dilution Factor

' f')

V 0.1 o 0.20 16.9 33.8 0.080 0.080 13.8 14.0 0.30 50.6 0.078 14.3 0.4o 67.5 0.075 14.7 l 0.50 84.4 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 l 1.1 o 185.6 0.046 21.9 1.20 202.5 0.042 23.9 1.30 219.4 0.037 26.3 l 1.40 236.3 0.032 29.2

! 1.50 253.2 0.028 32.6 l 1.75o 295.4 0.05'3 44.7 l 2.0a 337.6 0.035 64.7 l 2.25o 379.8 0.021 98.4 l 2.5 a 421.9 0.012 158.4 3.00 506.3 0.010 482

, Totals 1.00 O

V l

t Page 133 of 134

1 POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 OFFSITE DOSE CALCULATION MANUAL O

V

It is assumed that the standard deviation of the radionuclide concentrations across the plume can be represented by a normal distribution curve. The fraction of the total area under the curve is that fraction of the area under the curve that lies between, for example, the interval 0.1o and 0.2o which also includes the area of the curve in the interval -0.1o and -0.20.

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.

O O

Page 134 of 134

. _ _ _ __ . - - _ _ . . _ . . _ _ - _ - - . . = - . . - _ _ - - - -

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 OFFSITE DOSE CALCULATION MANUAL n

v i l

i APPENDIX E I l

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

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

l l

1 1

i l

l l

lO l E-1 CONTINUOUS USE

r 1 POINT BEACll NUCLEAR PLANT ODCM !

OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 i OFFSITE DOSE CALCULATION MANUAL t

APPENDIX F 1

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, j

O I

.O l

l F-1 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT ODCM l OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 OFFSITE DOSE CALCULATION MANUAL O uODirIC^rION I CHANGE TO ORIGINAL SUBMITTAL Section 3.2, Disposal Procedure (page 3)

Section 3.3, Administrative Procedure (page 4) l The requirements for sludge characterization (the determination of the chemical and physical properties of the sludge) contained in the sections referenced above are modified to allow characterization of the sludge on an j annual basis. '

BASIS / EXPLANATION

l i

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-j mittal and the approval by the NRC, a new Wisconsin Pollutant Discharge j Elimination System (WPDES) permit was issued to the Point Beach Nuclear Plant by the Wisconsin Department of Natural Resources on November 30, 1988. Both the new WPDES permit and the Point Beach Nuclear Plant Sludge Nanagement Plan ;

{ specify an annual required frequency for the evaluation of the sludge characteristics. I I

The original requirement to perform 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 3

of special analytical standards are required to complete the characterization j

study. The preparation of these standards, sample preparation, and the actual l analyses are all manpower intensive and difficult to perform on a timely basis. This has led to requiring overtime for Lab Services personnel and j support from outside companies. In order to better utilize the resources of Lab Services while maintaining the requirements of the WPDES permit, the j

frequency of sludge characterization in the October 8, 1987 submittal to the i NRC should be changed to an annual requireh. at. -

1 j This change in the required frequency for determination of tu udge

! characteristics does not change the requirement to analyze the b wage sludge 4

for radionuclide content or perform dose evaluations ' prior to each disposal.

O i l F-2 CONTINUOUS USE )

POINT BEACil NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 OFFSITE DOSE CALCULATION MANUAL O

l APPENDIX G I

I l Modifications to the Wisconsin Electric submittal to the United States Nuclear Regulatory l 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, I

4 l

l l

i l

l l

O l G-1 CONTINUOUS USE

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 OFFSITE DOSE CALCULATION MANUAL l MODIFICATION #2 l l l

l CIIANGE TO ORIGINAL SUBMITTAL t l l l Section 3.3, Administrative Procedures (Page E-10) l l The limitation on the annual volume of sludge disposal per acre contained in the section referenced l above is modified to allow unlimited disposal provided the other requirements of this submittal are met.

l l BASIS / EXPLANATION I

l The October 8,1987, submittal to the USNRC for permission to dispose of sewage treatment sludge l containing minute quantities of radioactive material requires that "the annual disposal rate for each of l the approved land spread sites will be limited to 4,000 gallons / acre, provided WDNR chemical l composition, NRC dose guidelines, and concentration and activity limits are maintained within the l appropriate values."

l l The original requirement to limit sewage sludge disposal to 4,000 gallons per acre is based on the l assumption that the sewage sludge is contaminated with Co-58 at a concentration that is ten percent of l the 10 CFR Part 20 Appendix B Table 2 Column 2 value. Past sewage sludge disposal experience has l shown that the sludge may or may not be contaminated and, if it is, at concentrations far below ten p l percent of the performed prior to each sewage sludge disposal. With the removal of some of the land i i

( l spread sites due to their use as a storage site for dry storage of spent fuel, this requirement is limitmg i l our ability to dispose of the sewage sludge on the remaining approved land spread sites. {

I l l This removal of the annual volume of sewage sludge that may be disposed of per acre on approved land j l spread sites does not change the requirement to analyze the sewage sludge for radionuclide content or '

l perform dose evaluations prior to each disposal.

l l This change was evaluated under SER 95-057, " Removal of licensee Commitment Involved With i

l Sewage Sludge Disposal," 4/20/95, i i

O l G-2 CONTINUOUS USE l

POINT BEACH NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 9 July 6,1995 ,

OFFSITE DOSE CALCULATION MANUAL l l MODIFICATION #2 I

Depth to groundwater and bedrock shall be greater than 3 feet from the land surface elevation during use of any site.

l

Sludge shall not be land spread in a floodway.

l 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 i case a minimum separation distance of at least 25 feet is requirsd. l The pH of the sludge-soil mixture shall be maintained at 6.5 or higher.

i Low areas of the approved fields, subject to seasonally high ground-water levels, are excluded from the sludge application.

l Crops for human consumption shall not be grown on the land for up to one year following the appilcation of the sludge.

l l 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 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 l an alfalfa plot constitutes good fertilization, but the plot cannot be plowed without destroying the crop. The alfalfa in this case sids in binding the layer of sludge on the surface of the plot. At a minimum, i however, plowing (or disking or other method of injection and mixing to l

Q('N 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 I total volume of sludge disposed, the total activity, the plot on which the sludge was applied, the results of the chemical composition determinations, and all dose calculations.

The enn i osal rate for each of the approved land spread sites will be 14eMed tc t,^^^ ;m=/na, provided WDNR chemical compost- l l 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 l

of the applicable restrictions placed on the site due to the land spreading of sewage sludge.

4.0 Evtluation of Envirormental Imoset 4.1 $lte Characteristics 4.1.1 Site Tooocraphy l The disposal sites are located in the Town of Two Creeks in the northeast corner of Manitowoc CountycWisconsin, on the l E-10 lV i

l G-3 CONTINUOUS USE

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ML20107L670

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