Text

Rev 10 to Point Beach Nuclear Plant,Units 1 & 2 Odcm
	ML20217P285
Person / Time
Site:	Point Beach
Issue date:	04/03/1997
From:	; WISCONSIN ELECTRIC POWER CO.
To:	;
Shared Package
ML20217P274	List: ML20217P276; ML20217P285; NPL-98-0311, Forwards Annual Monitoring Rept for 1997, for Point Beach Nuclear Plant, & Rev 10 to Point Beach Nuclear Plant,Units 1 & 2 Odcm. Annual Monitoring Rept Contains Info Re Plant Releases,Solid Waste Shipments & New & Spent Fuel Shipments;
References
	PROC-970403, NUDOCS 9805060192
	Download: ML20217P285 (202)
	v • d • e

NUCLENR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 OFFSITE DOSE CALCULATION MANUAL POINT BEACH NUCLEAR PLANT UNITS 1 AND 2 OFFSITE DOSE CALCULATION MANUAL WISCONSIN ELECTRIC POWER COMPANY l

April 3,1997 4

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t l NUCLEAR POWER BUSINESS UNIT ODCM j OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 OFFSITE DOSE CALCULATION MANUAL 1 l

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i TABLE OF CONTENTS I

1 Pace 1.0 OFFSITE DOSE CALCULATION MANUAL ADMINISTRATION..... ..... .... ... .. .. . . . . .....I 1.1 Purpose.... ... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. ........I 1.2 General Responsibilities.. ... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. 1 1.3 Manual Revisions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. 2 2.0 RADIATION MONITORING SYSTEM AND RELEASE ACCOUNTING. . . . ..........2 3.0 METHODOLOGY FOR DETERMINING ALARM SET POINTS . . . . . . . . . . . . . . . .............7 3.1 Introduction.... . ... . . . . . . . . . . . . .. .. . . . . . . . . . . . . . . . ....7 3.2 Objective. . . . . . . . . . ... . . . . . . . . . . . . . . . . . . . . . . .. . ...7 3.3 Alert Set Point Guidelines. . . . . . .. . . . . . . . ...... . . . . . . . .............7 3.4 Alarm or Trip Set Point Guidelines. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ....8 3.5 Monitor Calibration and Calibration Constant Determination . . . . . . . . . . . . . . . . . . . . ..........8 3.6 Determination of the Effective Maximum Effluent Concentration (EMEC) for Liquid Releases. . 9 3.7 Determination of Liquid Effluent Monitor Alarm Set Point . . . . . . . . . . . . . . . . . . . . . . . 11 3.8 Determination of EMEC for Atmospheric Releases.. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .15 3.9 Determination of Gaseous Effluent Monitor Alann Set points. . . . . . . . . . . . . . . . . . . . . . . . . . . . .16 4.0 DEMONSTRATING COMPLI ANCE WITH 10 CFR 50. APPENDIX I.. . . .. .. . .............20 4.1 Introduction... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ..................................20 4.2 Dose Limits... . . . . . . .. .. ... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ..... 20 4.3 Release Limits........ . ... ....... ..... . .. .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . 21 i

4.4 EPA Regulations... .. .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 22

NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 OFFSITE DOSE CALCULATION MANUAL Paue 5.0 CALCULATION AND COMPARISON OF EFFLUENT RELEASES TO RELEASE (IMITS.. . 22 5.1 Appendix I Dose Calculations.... . . . .. . . . . . . . . . . . . . .

...........................22 5.1.1 Liquid Release Mode ....... . . . ... . .. .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. ..22 5.1.2 Atmospheric Relcase Mode: Radiciodine, Tritium, and Particulates. . . . . . . . . . ..........52 5.1.3 Atmospheric Release Mode: Noble Gases.... .. . . . . . . . . . . . . . . . . . . . . . ...................82 i 6.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ..... . . . . . . . . . . . 84 7.0 RADIOLOGICAL IMPACT EVALUATION OF SEWAGE TREATMENT SLUDGE DISPOSAL.. .... .. .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 84 7.1 Basis, Commitments, and Actions. .. .. ... . ... . . . . . . . . . . . . . . . . . . . . .. .84 7.1.1 Basis. . . . . . . . . . . . . . . . . . . .. .. . . . . . . . . . . . . . . . . . . .. .. ... 84 7.1.2 Basis for NRC Commitment Modification. . . . . . . . . . . . . . . . .. 84 7.1.3 Modification.. . . .. . . .. .. . . . . . . . . . . . . . . . . . . . . . . . . . . . 85

)

7.1.4 Exposure Evaluations.. . . .. .. .. . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . .. 8 5 7.2 Procedure . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . .. .. .86 7.3 Administrative Requirements. . . . . . . . . . . . . . . . . . . . . . . . .. .........87 l

l 7.3.1 Complete records of each con'aminated disposal shall be kept as follows: . .. ..........87 I 7.3.2 Modifications to the October 8,1987, NRC submittal .. .. . . . . .88 l

APPENDIX A ..... .... .. . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . .. 89 A.I.0 Derivation of Liquid Release Effective Maxirrum Effluent Concentration. . . . . . . . . . .. 90 A.1.1 Source Term ..... . .. ...... . . .... . .. . . . . . . . . ... .. . . . . . . . . . ............90 A.I.2 Effective Maximam Effluent Concentration.. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ... . . . . . 90 1

I L .)

NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 OFFSITE DOSE CALCULATION MANUAL Pace

. . . . ... . . . . . . . . . . . . . . . . . . ..........95 A P P EN DI X B . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

B.I.0 Derivation of Atmospheric Release Effective Maximum Effluent Concentration . . . . .96

. 96 Bl.1 Source Term .... ... .

.. . 96 Bl.2 Effective Maximum Effluent Concentration.. . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

.101 APPENDIX C . . . . .... .... ... . . . . . .

C.I.0 Calculation of Total Dose Factors Using Regulatory Guide 1.109 Methodology.. . .. .. .. 102 C.l.1 Liquid Release Dose Fectors.. . . . . . . . ... . . . . . . . . . . . . . . . . . . . . . .102 C1.1.1 Aquatic Foods ..... .. ..... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .102 Cl.l.2 Irrigated Foods (Meat From Watered Cattle)... . . . . . . . . . . . . . . . . . . . . . . . . . . . .104 C1.1.3 Irrigated Foods (Milk From Watered Cattle) . ... .. . . . . . . . . . . . . . . . . . . . . .106 Cl.l.4 Potable Water. . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . ... . 108 C1.1.5 Shoreline Deposits.. . . . . . . . . . . . . . . . . . . . . . . . 110 Cl.2 Atmospheric Release Dose Factors: Non-Gaseous . . .. .. . . .. . ....... . . . . . . . . . . .. .. ! 12 Cl.2.1 Inhalation of Nuclides In Air . .. . . . .. . .. . . . . . . . . . . . . ..I12 Cl.2.2 Annual Organ Dose From Extemal Irradiation From Nuclides Deposited On the Ground.. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . .113 Cl.2.3 Annual Organ Dose From Atmospherically Released Nuclides In Milk.... .. .. ... ...115 Cl.2.4 Annual Organ Dose From Atmospherically Released Nuclides In Meat . ... . . . . . I 18 C1.2.5 Annual Organ Dose From Atmospheriently Released Nuclides In Produce... . . .121 Cl.2.6 Annual Organ Dose From Atmospherically Released Nuclides In Leafy Vegetables.. 124 Cl .3 Atmospheric Release Dose Factors: Noble Gases... . ... ... . ..... ....... .... . .. ... . . . . ..127 Cl.3.1 Annual Gamma and Beta Air Dose From All Noble Gas Releases.... ..... ...... . . . . .127 Cl.3.2 Annual Skin Dose From All Noble Gas Releases. . . . . . . . . . . . . . . . . . . . ..128 Cl.3.3 Annual Total Body Dose From All Noble Gas Releases... .... .. . . . . . . .130 s

NUCLEAR POWER BUSINESS UNIT ODCM

OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 OFFSITE DOSE CALCULATION MANUAL Pace APPENDIX D... . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13 2

Dl.0 Liquid Effluent Dilution Factor Calculations . ...... . . . . . . . . . . . . . . . . . . . . . . .

.....................133 Dl.1 Methodology ..... . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . ..... 133 DI.2 Dilution Factor Twelve Miles Downstream: Two Rivers Water Intake. .. ... . ........ . .. . 136 APPENDIX E NRC Submittal: Radiological Impact j Evaluation of Sewage Treatment Sludge... .. .. . . ...... . ... . . ... ... . .. ...... .. . . . . . . E- 1 APPENDIX F.. . . . . . . . . . . . . . . ..... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . F- 1 Modification #1 to NRC Submittal... .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ... . F-2 APPENDIX G. .... .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. ... . . . . . . . . . . . . . . . . . . . . .........G-1 Modification #2 to NRC Submittal... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . G -2 APPENDIX 1I. .. . . .. . . . .. .... . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . H- 1 Modification #3.. . . . .... . . . . . . . . . . .. . . . . . . . . . . . ... .. . . . . . . .11-2 Change to Original Submittal ... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . H-2 Basis / Explanation .. . .... . . . . . . . . . . . . . . . . . . . . . ........... .. .... ..Il-2 l

1

NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 OFFSITE DOSE CALCULATION MANUAL )

LIST OF TABLES AND FIGURES Pace 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... ....... . .. .. .. .. 5 FIGURE 2-2 RADIOACTIVE GASEOUS WASTE EFFLUENT MONITORS. . . .... ........6 SECTION 3.0 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.. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ...... . . . . .. 17 TABLE 3.9-2 ATMOSPHERIC PATHWAY MONITOR DEFAULT RMS SET POINTS. . .. 19 SECTION 5.0 TABLE 5.1-1 LIQUID EFFLUENT DOSE FACTOR.... ..... . . . . . . . . . . . . . . . . . . . 24 TABLE 5.1-2 AIRBORNE EFFLUENT DOSE FACTOR .. .. . . . . . . . . . . . . . . . . . . . . . . . . . .54 TABLE 5.1-3 ACTIVITY TO DOSE CONVERSION FACTORS FOR NOBLE GASES .. ... 83 APPENDIX A TABLE A-1 CURIES RELEASED IN LIQUIDS.... . . .. . . . . . . . . . .........92 TABLE A-2 FRACTIONAL MEC IN LIQUID EFFLUENT. . . . . . . . . . . . . . . ... . . . . . 93 APPENDIX B TABLE B-1 CURIES IN ATMOSPHERIC EFFLUENT........... . ...............................97 TABLE B-2 FRACTIONAL MEC FOR ATMOSPHERIC EFFLUENT .... ...... .. ... .. ..... . 99 APPENDIX D TABLE D-1 SURFACE DILUTION FACTORS LIQUID EFFLUENTS IN A LARGE LAKE . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. .. .134 FIGURE D-1 DILUTION FACTOR AT SURFACE. . . . . . .. . . . . . . . . . . . . . ....... . 135 t ______________ _.

L' NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 4 April 3,1997 !

OFFSITE DOSE CALCULATION MANUAL l

1.0 OFFSITE DOSE CALCULATION MANUAL ADMINISTRATION l

1.1 Pumose I

l The PBNP Offsite Dose Calculation Manual contains the current methodology and l

parameters for the calculation of offsite doses due to radioactive gaseous and liquid effluents. This manual describes a methodology for demonstrating compliance with 10 CFR 50, Appendix I dose limits. Compliance with Appendix I is demonstrated by periodic calculation of offsite doses based on actual plant releases a nd comparison to Appendix I dose limits The manual also details the methodology for the determination of gaseous and liquid effluent monitor alarm set points. The PBNP Radiation Monitoring System (RMS) j effluent monitor alarm set points are established to ensure that controlled releases of l liquid and gaseous radioactive effluen.s are maintained as low as is reasonably achievable l

l and to ensure releases result in concentrations to umestricted areas within limits specified l l m 10 CFR 20.

l The manual also details the methodology for evaluating the radiological impact of sewage l treatment sludge disposal. This methodology addresses the commitments made to the l

United States Nuclear Regulatory Commission in our application dated October 8,1987 (NRC-87-104) and accepted by the USNRC in a letter dated January 13,1988. This application was submitted in accordance with the provisions of 10 CFR 20.302(a). A copy of the submittal and subsequent modifications is contained in Appendices E and F. i Dose limits are established in the application to ensure the health and safety of the maximally exposed member of the general public and the inadvertent intruder.

10 CFR 50, Appendix I dose limits do not apply to sewage treatment sludge disposal.

l 1.2 General Responsibilities The primary responsibility for the implementation of the PBNP offsite dose calculation program and for any actions required by the program resides with the Manager and the staff of the Nuclear Industry and Regulatory Services Section (IRSS). IRSS will provide the technical, regulatory, licensing, and administrative support necessary to fulfill the requirements of this manual. The calcu;ation of offsite doses and analysis of data are IRSS responsibilities.

The Manager, PBNP is responsible for assuring that Radiation Monitoring System alarm set points are established and maintained in accordance with the methodologies outlined I

, in this manual. The Manager, PBNP is also responsible for assuring the performance of l

periodic release summaries for the purpose. of demonstrating compliance with PBNP effluent release limits.

l Page1of138

NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 OFFSITE DOSE CALCULATION MANUAL l 1.3 Manual Revisions l

This manual describes the current scope of the PBNP offsite dose calculation program.

The program and the manual are maintained by 1RSS. Program items or procedures may j

be periodically updated or changed, either to reflect new parameters or to improve l progran effectiveness. This manual may be revised at the discretion ofIRSS with the concurrence of the PBNP Manager's Supervisory Staff (MSS).

2.0 RADIATION MONITORING SYSTEM AND RELEASE ACCOUNTING A computerized Radiation Monitoring System (RMS)is installed at Point Beach Nuclear 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 accordance with procedures contained in the PBNP Health Physics Calibration Manual. The set point methodology is described in Section 3 of this manual.,

The RMS is designed to detect and measure liquid and gaseous releases from the plant effluent pathways. The RMS will initiate isolation and control functions en certain effluent strcams

{ identified in Tables 2-1 and 2-2. Complete monitoring and accounting of nuclides released in liquid and gaseous effluents is accomplished with the RMS together with the characterization of nuclide distributions by laboratory analysis of grab samples. Sampling frequencies and analysis requirements are described in Tables 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.

1 Page 2 of 138 L

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NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997

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NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 l OFFSITE DOSE CALCULATION MANUAL {

3.0 METHODOLOGY FOR DETERMINING ALARM SET POINTS 3.1 Introduction i i

The selection and maintenance of. alert and alarm set points for each effluent monitor of f the PBNP radiation monitoring system will be accomplished within the guidelines of this section. The computerized PBNP radiation monitoring system permits each effluent radiation monitor to be programmed to alarm at two distinct set-points. The alert set

point, typically twice the steady-state reading, is intended to delineate a changing plant condition which may warrant corrective action. The high alarm or trip set point either will actuate a control function as applicable or will require corrective action to be initiated.

I 3.2 Obiective The effluent monitor set points are established to ensure that controlled releases ofliquid and gaseous radioactive effluents are maintained as low as is reasonably achievable, to ensure releases result in concentrations to unrestricted areas within limits specified in 10 CFR 20, and to ensure that the dose limits of 10 CFR 50, Appendix I are not exceeded.

l 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 the alarm set point. In j l

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 a!ert 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.

l l

Page 7 of 138

NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revisicn 10 April 3,1997 OFFSITE DOSE CALCULATION MANUAL 3.4 Alarm or Trin 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 annunciate at radiation levels which would result in an unrestricted area concentration equal to or less than the applicable maximum effluent concentration (MEC) specified in 10 CFR 20, Appendix B, Table 2 for a single radionuclide. However, for a mixture of radionuclides, the set point shall be estabhshed 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:

1 Cal. Constant =

Sensitivity and

=

Monitor Response Sens.. .itivity E (microCi/ cc.)

l where:

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

noble gas isotopic distribution 1

I Page 8 of 138 L

NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 OFFSITE DOSE CALCULATION MANUAL ,

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

Each liquid monitor channel displays the effluent concentration in terms of a total release concentration.

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

1 Cal. Constant =

Sensitivity and n r hsponse Sensitivity =

I(pCi / cci) where:

Monitor Response =

the counts per minute registered by monitor exposed to calibration source I(pCi/cci) =

total concentration on radionuclides in the 1985-1991 average liquid effluent isotopic distribution The QAD computer program may be utilized to predict or determine monitor calibration constants. Application of the QAD program may be appropriate for detemiining monitor response for accident source terms or other instances when the use of a calibration source j is impracticable. TLe methodology for determination of calibration constants using the ;

QAD program is maintained by the staff of the IRSS.

3.6 Detemiination of the Effective Maximum Effluent Concentration (EMEC) for Liauid Releases in order to fulfill the requirements of 10 CFR 20, the RMS set point must be a value which will alarm when a liquid effluen, 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 ofindividual concentrations up to the value where the SOF equals one. This total concentration is 4 called the effective maximum effluent concentration (EMEC) and its calculation is described below. (For a complete discussion of the EMEC derivation, see Appendix A.)

Page 9 of 138 s

ODCM NUCLEAR POWER BUSINESS UNIT Revision 10 OFFSITE DOSE CALCULATION MANUAL April 3,1997 OFFSITE DOSE CALCULATION MANUAL The SOF is calculated using the formula found in the revised 10 CFR 20, Appendix B, Note 4:

SOF = I C;/MECi where:

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

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

The SOF for radionuclides in liquid effluent for the years 1985 through 1991 were averaged and applied to the average of the isotopic concentrations for the same years.

Na-24 and H-3 were not used in the calculations (see Appendix A for details).

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

EMEC =

IC i/ I(C /MEC i i)or IC *i 1/SOF where the variables are the same as defined above.

The average EMEC, based on 1985-1991 data is 4.29E-06 Ci/cc. This is the maximum non H-3 radionuclide mixture concentration that could be rcleased in liquid effluent without the SOF exceeding one (1).

However, the 10 CFR 20, Appendix B criterion is that the SOF for all radionuclides, including H-3 which cannot be measured by the liquid effluent Nal RMS monitors, be less than or equal to one (1). Therefore, the above equation mc dified by a factor of 0.70 (see Appendix A) to account for H-3 becomes EMEC = 0.70 IC; / I(C;/MEC i) or IC i* 0.70/SOF.

The EMEC becomes l EMEC = 0.70

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

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

Page 10 of 138

NUCLEAR POWER BUSINESS UNIT ODCM i OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 OFFSITE DOSE CALCULATION MANUAL Note that the use of the 0.7 modifying factor sets the SOF for non-tritium radionuclides to l

0.7 and allows an SOF of 0.3 for H-3. A SOF of 0.3 limits the discharge concentration of l

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 5;1.

3.7 Determination of Liauid 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 discha ged to the unrestricted area. The radionuclide concentration in the release is calculated assuming a minimum circulating fj water flow rate of 206,000 gpm and the maximum flow rate of the individual liquid l effluent waste stream. The isotopic distribution of the ".aste 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.

l l Set points are calculated using the formula ,

l Cire water flow rate (gpm)

SP = EMEC

Waste Discharge Flow Rate (gpm)

I where SP = RMS alarm set point in pCi/cc 1

EMEC = effective maximum effluent concentration I Cire water flow rate = total flow from Unit 1 + Unit 2 Waste discharge flow rate = - flow rate for effluent line on which the l

monitor is located Maximum waste discharge flow rates and monitors associated with each liquid effluent pathway are described in Table 3.7-1.

j Default alarm set points normally are established based upon the maximum waste i discharge flow rate and the minimum circulation water flow rate. The liquid release l monitor default set points are listed in Table 3.7-2. Alarm set points may be adjusted for I

batch releases, when actual flow rates are known. Alarm set point adjustments which are higher than default values, are to be made in accordance with the provisions and methodologies of this section and requires approval of the MSS. Lower alarm set point values maybe used without MSS approval if the default values lie outside the upper range of the monitor or if compliance with applicable limits will not be compromised.

Page !I of 138

ODCM NUCLEAR POWER BUSINESS UNIT Revision 10 OFFSITE DOSE CALCULATION MANUAL April 3,1907 OFFSITE DOSE CALCULATION MANUAL TABLE 3.7-1

SUMMARY

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

PATHWAY (GPM)

RECIRCULATION WATER 1 pump, either unit 206,000 None 2 pumps, either unit 350,000 1 pump, each unit 392,000 1 pump, one unit & 530,000 2 pumps, other unit 2 pumps, each unit 680,000 SERVICE WATER RETURN 1 (2) RE-229 (noimal cooldown per pump 2 pumps @ 7500 gpm 15,900 3 pumps @ 6300 gpm 18,900 4 pumps @ 5100 gpm 20,400 5 pumps @ 4300 gpm 21,500 6 pumps @ 3700 gpm 22,200 STEAM GENERATOR 1 (2) RE-219 & I (2) RE-222 BLOWDOWN Max flow 200 RE-230 RETENTION POND Max Flow Rate 360 (2 pumps)

(sliding gate open) 1670 Page 12 of 138

NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 i April 3,1997 I OFFSITE DOSE CALCULATION MANUAL TABLE 3.7-1, cont i

SUMMARY

OF LIOUID DILUT!ON AND EFFLUENT PATHWAY FLOW RATES 1

LIQUID EFFLUENT DISCHARGE FLOW RATE PATHWAY MONITOR PATHWAY (GPM) l SPENT FUEL POOL IE-220 Max Flow Rate 700 I 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 Containment i f

Page 13 of 138

0 D n 98 NUCLEAR POWER BUSINESS UNIT Revision 10 OFFSITE DOSE CALCULATION MANUAL April 3,1997 OFFSITE DOSE CALCULATION MANUAL TABLE 3.7-2 LIQUID PATHWAY MONITOR CALCULATED DEFAULT SET POINTS FLOWRATE (com) SET POINT (ttCi/cc)

MONITOR 2.78E-05 1 (2) RE-229 6@3700' 200 3.09E-3 1 (2) RE-219 &

1 (2) RE-222 1670 3.70E-04 RE-230 700 8.83E-04 RE-220 100 6.18E-03 RE-218 &

RE-223 4000 1.55E-04 1 (2) RE-216

'six service water pumps at normal cooldown flow rates 4

Page 14 of 138

NUCLEAR POWER BUSINESS UNIT ODCM l OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 OFFSITE DOSE CALCULATION MANUAL 3.8 Determination of EMEC fbr 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 = IC; / I(C; / MEC;)

where C; =

concentration of radionuclide "i" MEC i = maximum effluent concentration for radionuclide i from 10 CFR 20 Appendix B, Table 2 I(C; / MEC;) = summation of fractions (SOF), as discussed in Section 3.6, applied to atmospheric releases The EMEC is calculated from the reference radionuclide mixture. This mixture is obtained from the 1985 - 1991 average annual atmospheric releases and the corresponding concentrations detennined from the highest annual average yfQ. (Details of the EMEC calculation are found in Appendix B.)

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

l l

4 Page 15 of 138

GUbW NUCLEAR POWER BUSINESS UNIT Revision 10 OFFSITE DOSE CALCULATION MANUAL April 3, I997 OFFSITE DOSE CALCULATION MANUAL _

3.9 Determination of Gaseous Effluent Monitor Alum Set points The alarm set point for each monitor is based upon maintaining the concentration of the reference radionuclide mixture at or below the EMEC. The set point is calculated using the formula SP = 2.12E+03

EMEC / (x/Q

FR) where SP = set point in pCi/cc 3 3 2.12E + 03 = conversion factor for ft / min to m /sec EMEC = 1.92E-08 pCi/cc 3

x/Q = highest site boundary annual average 1.5E-06 sec/m 3

FR = the flow rate in ft / min of the efTluent pathway being monitored.

Combining the above numerical values yields SP(pCi/cc) = 2.71E + 01/ FR Gaseous effluent pathway discharge flow rates and monitors associated wi:h each pathway are summarized in Table 3.9-1.

l Page 16 of 138

NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 OFFSITE DOSE CALCULATION MANUAL TABLE 3.9-1

SUMMARY

OF GASEOUS EFFLUENT PATIIWAY DISCIIARGE FLOW RATES DISCHARGE FLOW RATE MONITOR (S)

GASEOUS EFFLUENT PATHWAY CFM IN EFFLUENT PATHWAY

a. Auxiliary Building Vent 66,400 RE-214 & SPING 23

b. Combined Air Ejector 20 RE-225

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

d. Containment Purge Vent

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

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

c. Gas Stripper Building 13,000 RE-224

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

Page 17 of 138

NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 OFFSITE DOSE CALCULATION MANUAL Alarm set points are to be normally established based upon maximum waste discharge flow rates and the highest annual average x/Q value at the site boundary. The alarm set points may be adjusted for release periods if actual flow rates are reduced to less than maximum values or actual x/Q values are calculated.

Alarm set point adjustments to higher values are to be made in accordance with the provisions and methodologies of this section and require MSS approval. Default set point values obtained using the flow rates in Table 3.9-1 are presented in Table 3.9-2. An additional reduction factor of 1/4 has been applied to the four release point monitors so that the maximum allowable site boundary concentrations will not be exceeded in the event simultaneous releases from these points occur. Lower set point values may be used for any of the monitors without MSS approval if the default value is outside the upper range of the monitor or if compliance with applicable release limits will not be compromised. The set point values for the SPINGs will be the same as the corresponding release point monitor; RE-214 (SPING 23),1(2)RE-212 (SPINGS 21 and 22) or RE-221 (SPING 24).

l l

l Page 18 of 138

NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 l OFFSITE DOSE CALCULATION MANUAL TABLE 3.9-2 ATMOSPHERIC PATHWAY MONITOR l

l i HEFAULT RMS SET POINTS 1

MONITOR FLOW RATE SET POINT (fthmin) htCi/cc) l RE-214 66,400 1.02E-04 RE-225 20 1.36E+00 1RE-215 10 2.71 E+00 2RE-215 10 2.71 E+00 1RE-212 25,000' 2.73E-04 2RE-212 38,000 2 1.78E-04 RE-224 13,000 2.09E-03 RE-221 43,000 1.58E-04

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

)

l l

l l I l

i Page 19 of 138

NUCLEAR POWER BUSINESS UNIT ODCM l OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 OFFSITE DOSE CALCULATION MANUAL 4.0 DEMONSTRATING COMPLIANCE WITH 10 CFR 50. APPENDIX I 4.1 Introduction Maintaining effluents within the dose objectives of Appendix I is demonstrated at PBNP ,

by periodic calculations. Compliance with Appendix I limits is demonstrated by ;

periodically calculating doses to the maximum exposed individual using the methodology I set forth in Regulatory Guide 1.109, Rev.1, October 1977 and in other recognized I sources such as ICRP publications.

In order to aid in the dose calculations, the formulae in Reg Guide 1.109 were rearranged to calculate the dose per curie released (mrem /Ci) to the environment. For each pathway given in Reg Guide 1.109, a radionuclide's mrem /Ci values for the whole body and the organs were calculated for each of the two release modes, liquid and atmospheric. All of

, the pathway doses for a radionuclide vi_a i the release mode under consideration were !

summed to obtain the radionuclide's total mrem /Ci released. These values, called total dose factors (TDFs), are listed in Tables 5.1.1 and 5.1.2. The application of TDFs are given in Section 5; the calculations used to obtain them,in Appendix C.

4.2 Dose Limits To define the limits and conditions for the controlled release of radioactive materials in liquid and gaseous effluents to the environment, to ensure that these releases are as low as is reasonably achievable in conformance with 10 CFR Parts 50.34a and 50.36a, to ensure that these releases result in concentrations of radioactive materials in liquid and gaseous effluents released to unrestricted areas that are within the limits specified in 10 CFR 20, and to ensure that the releases of radioactive material above background to unrestricted areas are as low as is reasonably achievable, the following design release limits as defined in Appendix 1 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 comm;tment

from liquid effluents for any individual in an unrestricted area from all pathways of exposure in excess of 3 millirems to the total body or 10 millirems to any organ.

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

Page 20 of 138 e

NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 OFFSITE DOSE CALCULATION MANUAL C. The annual total quantity of all radioactive iodine and radioactive material in particulate form above background that may be released from each light-water-cooled nuclear power reactor in effluents to the atmosphere should not result in an annual dose or dose commitment from such radioactive iodine and radioactive material in particulate form for any individual in an unrestricted area from all pathways of exposure in excess of 15 millirems to any organ.

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 quantiues of radionuclides above background that fulfill the criteria listed below.

A. Pursuar.t to Section 4.2. A, .he doses from radionuclides in the unrestricted area in liquids shall not exceed i

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

2. Twenty (20) millirem to any organ.

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

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

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

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

4. Thirty (30) millirem to the skin.

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

4 Page 21 of 138

NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 ;

April 3,1997 l OFFSITE DOSE CALCULATION MANUAL 4.4 EPA Renulations Compliance with the provisions of Appendix I to 10 CFR 50 is adequate demonstration ofconformance to the standards set forth in 40 CFR 190 regarding the dose commitment to individuals from the uranium fuel cycle. For 40 CFR 190 compliance, quarterly dose calculations shall include exposures from effluent pathways and direct radiation contributions from the reactor units and from any outside storage tanks.

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

5.0 CALCULATION AND COMPARISON OF EFFLUENT RELEASES TO RELEASE LIMITS Technical 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 ofIRSS. These calculations will bm!one monthly, within fifteen (15) days of receipt of the final effluent curie values from the PBNP Chemistrj Section. The doses from each radionuclide will be calculated for each age group and for each organ, including the whole body, and summed over all the j identified radionuclides released. The total dose is compared to the corresponding liquid release mode Appendix I dose limit for the organ in question. Noble gases released in liquids are added to the atmospherically released noble gases for Appendix I dose compliance calculations.

t Page 22 of 138 l

NUCLEAR POWER BUSINESS UNIT OL)CM OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 OFFSITE DOSE CALCULATION MANUAL The doses are calculated using the following formula:

API =

I Doseaomi = I(TDFaomi x C;) s K om mrem where API =

the Appendix I dose for compliance evaluation in mrem Dose aomi =

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

TDFaomi =

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

curies of radionuclide (i) released K om =

the Appendix I dose limit for organ (o) and release mode (m) for which the calculation is being made.

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

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

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

Page 23 of 138

NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 OFFSITE DOSE CALCULATION MANUAL l

l TABLE 5.1-1 LIQUID EFFLUENT DOSE FACTOR Summation of dose per curie released factor calculations over the pathways: potable water, aquatic food, shoreline deposit, irrigated foods (milk), and irrigated foods (meat).

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

H-3 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 0.00E+00 4.57E-06 4.57E-06 4.57E-06 4.57E-06 4.57E-06 4.57E-06 Teen 0.00E+00 4.llE-06 4.llE-06 4.llE-06 4.llE-06 4. l l E-06 4. I I E-06 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 7.80 E-06 7.80E-06 7.80E-06 7.80E-06 7.80E-06 7.80E-06 Dose factor - liquid release pathway (mrem /Ci released)

F-18 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 1.15 E-07 9.12E-89 1.28E-08 0.00 E+00 5.14E-89 0.00 E+00 3.40E-09 Teen 1.21 E-07 7.59E-89 1.35 E-08 0.00E+00 4.35 E-89 0.00E+00 1.09 E-08 Child 1.51 E-07 1.08 E-88 1.50E-08 0.00E+00 5.74E-89 0.00 E+ 00 4.08 E-08 Infant 2.05 E- 12 0.00E+00 1.75 E- 13 0.00E+00 0.00E+00 0.00E+00 4.83 E- 13 Dose factor liquid release pathway (mrem /Ci released)

Na-22 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 4.71 E-03 4.71 E-03 4.82E-03 4.7 I E-03 4.7 i E-03 4.71 E-03 4.7 I E-03 Teen 5.48E-03 5.48E-03 6.07E-03 5.48E-03 5.48 E-03 5.48E-03 5.48 E-03 Child 8.32E-03 8.32 E-03 8.45E-03 8.32E-03 8.32 E-03 8.32E-03 8.32E-03 Infant 7.21 E-03 7.21 E-03 7.21 E-0 7.21 E-03 7.21 E-03 7.21 E-03 7.21 E-03 I

l Page 24 of 138 w .

l NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 OFFSITE DOSE CALCULATION MANUAL Table 5.1-1, cont.

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

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

Sc-46 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 1.70E-07 3.31 E-07 8.92E-06 0.00 E+00 3.09E-07 0.00E+00 1.6 l E-03 Teen 1.52E-07 2.97 E-07 4.94 E-05 0.00 E+00 2.84E-07 0.00E+00 1.01 E-03 Child 3.54 E-07 4.85 E-07 1.05 E-05 0.00E+00 4.29E-07 0.00 E+00 7.09E-04 Infant 3.42 E-07 4.94 E-07 1.54E-07 0.00E+00 3.25E-07 _' 70E+00 3.22E-04 Dose factor - liquid release pathway (mrenvCi released)

Mn-54 Bone Liver T. Body Thyroid Kidney Lungs GI-Lt.!

Adult 0.00E+00 3.28 E-03 6.34E-04 0.00 E+00 9.75E-04 0.00E+00 1.00E-02 Teen 0.00E+00 3.22 E-03 6.86E-04 0.00E+00 9.59E-04 0.00E +00 6.60E-03 Child 0.00E+00 2.60E-03 7.04 E-04 0.00 E+00 7.30E-04 0.00E+00 2.19E-03 Infant 0.00E +00 1.92 E-04 4.34 E-05 0.00 E+00 4.25 E-05 0.00E+00 7.04 E-05 i

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NUCLEAR POWER BUSINESS UNIT -ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 OFFSITE DOSE CALCULATION MANUAL Table 5.1-1, cont.

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 5.84 E-07 2.15E-07 1.30E-06 2.46E-04 Teen 0.00E+00 0.00E+00 1.17E-06 5.60E-07 2.21 E-07 1.44 E-06 1.70E-04 Child 0.00E+00 0.00E+00 1.19E-06 6.44 E-07 1.76E-07 1.18E-06 6.15 E-05 Infant 0.00E+00 0.00E+00 1.72E-07 1.12E-07 2.45 E-08 2.18E-07 5.01 E-06 Dose factor - liquid release pathway (mrem /Ci released)

Mn-56 ~

Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 0.00E+00 3.18E-06 5.65E-07 0.00E+00 4.04 E-06 0.00E+00 1.02 E-04 Teen 0.00E+00 3.33 E-06 5.94 E-07 0.00E+00 4.22 E-06 0.00E+00 2.19E-04 Child 0.00E+00 3.04 E-06 6.86E-07 0.00E+00 3.67E-06 0.00E+00 4.40E-04 Infant 0.00E+00 1.97 E-I l 3.39E- 12 0.00E+00 1.69 E-I l 0.00E+00 1.79E-09 Dose factor - liquid release pathway (mrem /Ci released)

Fe 55 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 5.98 E-04 4.13 E-04 9.63 E-05 0.00E+00 0.00E+00 2.31 E-04 2.37E-04 Teen 6.llE-04 4.33 E-04 1.0lE-04 0.00E+00 0.00E+00 2.75 E-04 1.88 E-04 Child 9.35 E-04 4.96 E-04 1.54 E-04 0.00E+00 0.00E+00 2.80E-04 9.19E-05 Infant 1.55 E-04 1.00E-04 2.68E-05 0.00E+00 0.00E+00 4.91 E-05 1.28 E-05 I

1 Page 26 of 138

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

Fe-59 Bone Liver T. Body Thyroid Kidney Lungs Adult 9. ' 2 E-04 2.14E 03 GI-LL']

8.23 E-04 0.00E+00 0.00E+00 5.99E-04 7.14E-03 Teen 9.22 E-04 2.15 E-03 8.40E-04 0.00E+00 0.00E+00 6.79E-04 5.09E-03 Child 1.29E-03 2.09E-03 1.04E-03 0.00E+00 0.00E+00 6.07E-04 2.18E-03 Infant 3.34 E-04 5.84 E-04 2.30E-04 0.00E+00 0.00E+00 1.73 E-04 2.79E-04 Dose factor - liquid release pathway (mrem /Ci released)

Co 57 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 0.00E+00 2.02E-05 3.57E-05 0.00E+00 0.00E+00 0.00E+00 5.13 E-04 Teen 0.00 E+00 2.06E-05 4.62E-05 0.00E+00 0.00E+00 0.00E+00 3.83E-04 Child 0.00E+00 2.31 E-05 4.93 E-05 0.00E+00 0.00E+00 0.00E+00 1.89E-04 Infant 0.00E+00 1.24 E-05 2.02 E-05 0.00E+00 0.00E+00 0.00E+00 4.24E-05 Dose factor - liquid release pathway (mrem /Ci released)

Co-58 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 0.00E+00 8.49E-05 1.93 E-04 0.00E+00 0.00E+00 0.00E+00 1.72E-03 i Teen 0.00E+00 8.30E-05 2.04E-04 0.00E+00 0.00E+00 0.00E+00 1.14E-03 )

I Child 0.00E+00 8.32E-05 2.57 E-04 0.00E+00 0.00E+00 0.00E+00 4.85 E-04 Infant 0.00E+00 3.84E-05 9.58E-05 0.00E+00 0.00E+00 0.00E+ 00 9.57E-05 l

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NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 OFFSITE DOSE CALCULATION MANUAL Table 5.1-1, cont.

Dose factor - liquid release pathway (mrenvCi released)

Co-60 Bone Liver T. Body Thyroid Kidney Lungs

GI-LLI Adult 0.00 E+00 2.48E-04 6.82E-01 0.00 E+00 0.00E+00 0.00E+00 4.66E-03 Teen 0.00E+00 2.44E-04 1.30E-03 0.00E+ 00 0.00E+00 0.00E+00 3.17E-03 Child 0.00E+00 2.49E-04 8.92 E-04 0.00E+00 0.00E+00 0.00E+00 1.38E 03 Infant 0.00E +00 1.17E-04 2.77E-04 0.00E+00 0.00E+00 0.00E+00 2.79E-04 Dose factor - liquid release pathway (mrem /Ci released)

Ni-63 Bone Liver T, Body Thyroid Kidney Lungs GI-LLI Adult 3.03E-02 2.10 E-03 1.02E-03 0.00 E+00 0.00 E+00 0.00E+00 4.38 E-04 Teen 3.13 E-02 2.21E-03 1.06E-03 0.00E+00 0.00E+00 0.00E+00 3.52E-04 Child 5.00E-02 2.67 E-03 1.70E 03 0.00E+00 0.00 E+00 0.00E+00 1.80E-04 Infant 1.27E-02 7.85 E-04 4.41 E-04 0.00E+00 0.00E+00 0.00E+00 3.91 E-05 Dose factor - liquid release pathway (mrem /Ci released)

Ni-65 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 3.39 E-06 4.40E 07 2.01 E-07 0.00E+00 0.00E+00 0.00E+00 1.12E-05 Teen 3.66E-06 4.68 E-07 2.13 E-07 0.00 E+00 0.00E+00 0.00E+00 2.54E-05 Child 4.68 E-06 4.41 E-07 2.57E-07 0.00E+00 0.00E+00 0.00E+00 5.40 E-05 Infant 1.74 E-10 1.97E-I l 8.95E 12 0.00E+00 0.00 E+00 0.00E+00 1.50E-09 Page 28 of 138

NUCLEAR POWER BUSINESS UNIT ODCM CFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 OFFSITE DOSE CALCULATION MANUAL Table 5.1-1, cont.

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 1.01 E-05 0.00E+00 3.43E-04 Teen 0.00E+00 4.31 E-06 2.04 E-06 0.00E+00 1.09E-05 0.00E+00 3.34 E-04

~ Child 0.00E+00 4.30E-06 2.60E-06 0.00E+00 1.04 E-05 0.00E+00 2.02E-04 Infant 0.00E+00 1.41 E-06 6.52E-07 0.00E+00 2.3 8 E-06 0.00E+00 2.89E-05 Dose fr.ctor - liquid release pathway ' nrem/Ci released)

Zn-65 1

1 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 1.73 E-02 5.50E-02 2.4 9E-02 0.00E+00 3.68 E-02 0.00 E+00 3.46E-02 Teen 1.58 E-02 5.50E-02 2.57E-02 0.00E+00 3.52 E-02 0.00E+00 2.33 E-02 Child 1.68E-02 4.47 E-02 2.78E-02 0.00E+00 2.82E-02 0.00E+00 7.85E-03 l Infant 1.32E-03 4.51 E-03 2.08E-03 0.00E+00 2.19E-03 0.00E+00 3.81 E-03 Dose factor - liquid release pathway (mrem /Ci released) l 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 2.43 E-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

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

Zn-69m Bone Liver T. Body Thyroid Kidney L mgs l GI-LLI Adult 3.25E-04 7.79E-04 7.12E-05 0.00E+00 4.72E-04 0.00E+00 4.761-02 Teen 3.50E-04 8.25E-04 7.57E-05 0.00E+00 5.0lE-04 0.00E+00 4.53E-02 Child 4.49E-04 7.65E-04 9.04 E-05 0.00E+00 4.44 E-04 0.00E+00 2.49E-02 Infant 9.61 E-06 1.96E-05 1.79E-06 ; 0.00E+00 7.94E-06 0.00E+00 2.72E-04 Dose factor - liquid release pathway (mrem /Ci released)

Br-82 Bone Liver T. Body '

B yroid Kidney Lungs GI-LLI Adult 0.00 E+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 1.71 E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Infant 0.00E+00 0.00E+00 4.43 E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Dose factor liquid] lease pathway (mrem /Ci released)

Br-83 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 0.00E+00 0.00E+00 9.06E-07 0.00E+00 0.00E+00 0.00E+00 1.30E-06 Teen 0.00E+00 0.00E+00 9.85 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 2.93 E-I l 0.00E +00 0.00E+00 0.00E+00 0.00E400 Page 30 of 138

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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 2.44 E-10 Teen 0.00E+00 0.00E+00 3.43 E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Child 0.00E+00 0.00E+00 4.33 E-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 0.00 E+00 0.00E+00 0.00E+00 l

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

Br-85 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 0.00E+00 0.00 E+00 4.24E-82 0.00E+00 0.00E+00 0.00E+00 0.00E400 Teen 0.00E+00 0.00E+00 4.60E-82 0.00 E+00 0.00E+00 0.00E+00 0.00E+00 Child 0.00E+00 0.00 E+00 5.94 E-82 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Infant 0.00E+00 0.00E+00 9.35 E-309 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Dose factor - liquid release pathway (mrem /Ci released)

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

]

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

Rb-88 Bone Liver T. Body Thyroid Kidney Lungs GILLI Adult 0.00E+00 1.41 E-16 7.46E-17 0.00E+00 0.00E+00 0.00E+00 1.94 E-27 Teen 0.00E+00 1.51 E-16 8.04E 17 0.00E+00 0.00E+00 0.00E+00 1.29E-23 Child 0.00E+00 1.45 E- 16 1.01 E- 16 0.00E+00 0.00E+00 0.00E+00 7.12 E- 18 Infant 0.00E+00 5.68E-54 3.12E-54 0.00E+00 0.00E+00 0.00E+00 5.54E-54 Dase factor - liquid release pathway (mrem /Ci released)

Rb-89 Bone Liver T. Body Thyroid Kidney- Lungs GI-LLI Adult 0.00E+00 1.28 E-18 8.99E- 19 0.00E+00 0.00E+00 0.00E+00 7.42E-32 Teen 0.00E+00 1.34 E- 18 9.4 5 E- 19 0.00Et00 0.00E+00 0.00E+00 2.05 E-27 Child 0.00E+00 1.23 E- 18 1.09E-18 0.00E+00 0.00E+00 0.00E+00 1.07E-20 Infant 0.00 E+00 1.15E-61 7.93 E-62 0.00E+00 0.00E+00 0.00E+ 00 3.92E-62 Dose factor liquid release pathway (mrem /Ci released)

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 Teen 2.43 E-02 0.00E+00 6.95 E-04 0.00E+00 0.00E+00 0.00E+00 2.89E-03 Child 4.27 E-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 l

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NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 OFFSITE DOSE CALCULATION MANUAL Table 5.1-1, cont.

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i Dose factor - liquid release pathway (mrem /Ci released) l 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 1.63 E-02 Teen 4.64 E-01 0.00E+00 1.15 E-01 0.00E+00 0.00E+00 0.00E+00 1.30E-02 Child 5.59E-01 0.00E+00 1.42E-01 0.00E+00 0.00E+00 0.00E+00 7.53 E-03 Infant 1.95 E-01 0.00E+00 4.97E-02 0.00E+00 0.00E+00 0.00E+00 2.44 E-03 _

4 l

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

Sr-91 i 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 6.05 E-04 l

Teen 1.38 E-04 0.00E+00 5.51 E-06 0.00E+00 0.00E+00 0.00E+00 6.24 E-04 Child 1.83E-04 0.00E+00 6.91 E-06 0.00E+00 0.00E+00 0.00E+00 4.04 E-04 Infant 1.59E-05 l 0.00E+00 5.76E-07 0.00 E+00 0.00E+00 0.00E+00 1.88 E-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 1.03 E-04 Teen 5.64 E-06 0.00E+00 2.42E-07 0.00E+00 0.00E+00 0.00E+00 1.44 E-04 !

Child 7.20E-06 0.00E+00 2.89E-07 0.00E+00 0.00E+00 0.00E+00 1.36E-04 Infant 9.41 E- 10 0.00E+00 3.50E-I l 0.00E+00 0.00E+00 0.00E+00 1.01 E-08 6

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NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 OFFSITE DOSE CALCULATION MANUAL Table 5.1-1, cont.

-Dose factor - liquid release pathway (mrem /Ci released) l Y-90 Bone Liver T. Body Thyroid Kidney Lungs- GI-LLI f

l Adult 4.85E-07 0.00E+00 1.30E-08 0.00E+00 0.00E+00 0.00E+00 5.15 E-03 Teen 5.16E-07 0.00E+00 1.40E-08 0.00E+00 0.00E+00 0.00E+00 4.26 E-03 Child 8.67E-07 0.00E+00 2.32 E-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 6.63 E-04 Dose factor liquid release pathway (mrem /Ci released)

Y-91 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI f 0.00E+00 0.00E+00 5.06E-03 Adult 9.20E-06 0.0CE+00 2.53 E-07 0.00E+00 Teen 9.68 E-06 0.00E+00 2.97E-07 0.00E+00 0.00E+00 0.00E+00 3.97E-03 Child 1.74 E-05 0.00 E+00 4.74E-07 0.00 E+00 0.00E+00 0.00E+00 2.32E-03 Infant 1.03 E-05 0.00E+00 2.73 E-07 0.00E+00 0.00 E+00 0.00E+00 7.35 E-04 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 2.55 E- 13 0.00E+00 0.00E+00 0.00E+00 8.72E-12 Child 2.36E-13 0.00E+00 6.04 E-14 0.00E+00 0.00 E+00 0.00E+00 4.62 E-10 Infant 2.62 E-26 0.00E+00 8.92E-28 0.00E+00 0.00 E+00 0.00E+00 8.72E-23 i

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l 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 3.51 E-09 0.00E+00 2.88E 10 0.00E+00 0.00E+00 0.00E+00 6.15 E-05 Teen 3.83 E-09 0.00E+00 1.15E-09 0.00E+00 0.00E+00 0.00E+00 1.05 E-04 Child 4.92E-09 0.00E+00 3.57E-10 0.00E+00 0.00E+00 0.00E+00 1.42 E-04 Infant 5.88E-12 0.00E+00 1.65 E-13 0.00E+00 0.00E+00 0.00E+00 1.12 E-07 i

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 0.30E+00 0.00E+00 1.69E-03 j Teen 5.77E-08 0.00 E+00 6.38 E-09 0.00E+00 0.00E+00 0.00E+00 1.76 E-03 j Child 7.75 E-08 0.00E+00 3.13 E-09 0.00E+00 0.00E+00 0.00E+00 1.16E-03 l 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 1.23 E-06 3.94 E-07 1.79E-06 0.00E+00 6.19E-07 0.00 E+00 1.25E-03 Teen 1.llE-06 3.52E-07 8.74 E-06 0.00E+00 5.17 E-07 0.00E+00 8.llE-04 Child 2.48 E-06 5.45E-07 2.26E-06 0.00E+00 7.80E-07 0.00E+00 5.69E-04 Infant 1.87E-06 4.56E-07 3.23 E-07 0.00E+00 4.91 E-07 0.00 E+00 2.27E-04 1

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1 NUCLEAR POWER BUSINESS UNIT ODCM I OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 OFFSITE DOSE CALCULATION MANUAL Table.5.1-1, cont.

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

Zr-97 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 1.07E-08 2.16E-09 1.23 E-08 0.00E+00 3.27E-09 0.00E+00 6.70E-04 Teen 1. l l E-08 2.19E-09 6.42 E-08 0.00E+00 3.33E-09 0.00E+00 5.94E-04 Child 2.21 E-08 3.19E-09 1.51E-08 0.00E+00 4.58E-09 0.00E+00 4.83 E-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 . 3.23 E-04 1.79E-04 9.73 E-05 0.00E+00 1.77E-04 0.00E+00 1.09 E+00 Teen 3.25E-04 1.80E-04 1.04 E-04 0.00E+00 1.75E-04 0.00E+00 7.70E-01 Child 3.84E-04 1.49E-04 1.08 E-04 0.00E+00 1.40E-04 0.00E+00 2.76E-01 Infant 5.36E-07 2.21 E-07 1.28 E-07 0.00E+00 1.58 E-07 0.00 E+00 1.86E-04 Dose factor - liquid release pathway (mrenvCi released)

Nb-97 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 2.69E-09 6.81 E-10 2.51 E-10 0.00 E+00 7.95 E-10 0.00E+00 2.51 E-06 Teen 2.90E-09 7.20E-10 2.73 E- 10 0.00E+00 8.41 E-10 0.00E+00 1.72 E-05 Child 3.68 E-09 6.65E-10 3.12E-10 0.00E+00 7.38E 10 0.00 E+00 2.05 E-04 Infant 5.81 E-21 1.24 E- 10 4.47 E-22 0,00 E+00 9.68E-22 0.00E+00 3.91 E-16 Page 36 of 138

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l Table 5.1-1, cont.

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

Mo-99 Bone Liver T. Body Thvroid 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 4.03 E-04 0.00E+00 3.15E-04 Child 0.00E+00 2.79 E-04 6.9 ] E-05 0.00 E+00 5.96E-04 0.00E+00 2.31 E-04 Infant 0.00E+00 4.38 E-04 8.54 E-05 0.00E+00 6.54 E-04 0.00E+00 1.44E-04 Dose factor - liquid r: lease pathway (mrem /Ci released)

Tc.99m Bone Liver T. Body Thyroid Kidney Lungs GILLI Adult 1.68 E-09 4.74 E-09 6.07E-08 0.00 E+00 7.20E-08 2.32E-09 2.81 E-06 Teen 1.74E-09 4.86E-09 6.46E-08 0.00E+00 7.24 E-08 2.70E-09 3.19E-06 Child 2.19E-09 4.29E-09 7.15 E-08 0.00 E+00 6.24 E-08 2.18E-09 2.44E-06 Infant 3.78 E- 10 7.79 E-10 1.00E-08 0.00E+00 8.38 E-09 4.07E-10 2.26E-07 Dose factor - liquid release pathway (mrem /Ci released)

Tc-101 T. Body Thyroid Kidney Lungs GILLI l Bone Liver 5.19E-24 5.10E 23 0.00E+00 9.34 E-23 2.65 E-24 1.56E-35 Adult 3.60E-24 3.89E-24 5.53E-24 5.49E-23 0.00E+00 1.00E-22 3.37E-24 9.45 E-31 Teen 5.22E 24 6.63 E-23 0.00 E+ 00 8.90E-23 2.76E-24 1.66E-23 Child 4.98E-24 1.23 E-68 1.21 E-67 0.00E+00 1.46E-67 6.69E-69 2.08E-66 Infant 9.73 E-69 Page 37 of 138

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l l

5.'5)ose 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 4.05 E-03 Teen 2.96E-05 0.00E+00 1.64E-05 0.00E+00 1.04 E-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 1.43 E-03 Infant 1.33 E-05 0.00E+00 4.43 E-06 6.00E+00 2.76E-05 0 00E+00 1.61 E-04 Dose factor - liquid release pathwey (mrem /Ci released)

Ru-105 Bone Liver ~ T. Body Thyroid Kidney Lungs GI-LLI Adult 4.13 E-08 0.00E+00 1.75 E-08 0.00E+00 5.34E-07 0.00E+00 2.53E-05 Teen 4.45 E-08 0.00E+00 2.42E-08 0.00 E+00 5.62E-07 0.00E+00 3.5'. i-05 Child 5.71 E-08 0.00E+00 2.22E-08 0.00E+00 5.02E-07 0.00E+00 3.73E-05 Infant 6.98 E-10 0.00E+00 2.35 E-10 0.00E+00 5.13E-09 0.00E+00 2.78E-07 Dose factor - liquid release pathway (mrem /Ci released)

Ru-106 Bone Liver T. Body Thyroid Kidney Lungs GILLI Adult 6.71 E-04 0.00E+00 8.76E-05 0.00E+00 1.30E-03 0.00E+00 4.34 E-02 Teen 5.86E-04 0.00E+00 8.85E-05 0.00E+00 1.13 E-03 0.00E+00 2.81 E-02 Child 1.13E-03 0.00E+00 1.44 E-04 0.00E+00 1.53 E-03 0.00E+00 1.76E-02 Infant 2.23 E-04 0.00E+00 2.78E-05 0.00E+00 2.63E-04 0.00E+00 1.69E-03 Page 38 of 138

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l t

l Table 5.1-1, cont.

i l

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

Rh-105 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 3.35 E-06 2.45 E-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 l 3.88E-06 0.00E+00 1.80E-05 0.00E+00 2.80E-04 Infant 1.08E-05 7.0$E-06 l 4.74E-06 0.00E400 1.96E-05 0.00E+00 1.75 E-04 Dose factor - liquid release pathway (mrem /Ci released)

Ag-l 10m Bone Liver T. Body Thyroid Kidney- Lungs GI-LLI Adult 3.06 E-05 2.83 E-05 3.83E-05 0.00E+00 5.56E-05 0.00E+00 1.15 E-02 l Teen 3.74E-05 3.54E-05 1.41 E-04 0.00E+00 6.75 E-05 0.00E+ 00 9.94E-03 Child 6.78 E-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 4.28 E-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 5.42E-04 1.02 E-05 2.21 E-04 1.32E-06 0.00E+00 4.22E-04 1.54 E-02 Teen 5.66E-04 1.04 E-05 2.53E-04 1.28 E-06 0.00E+00 4.94 E-04 1.14E-02 Child 7.89E-04 1.02E-05 2.83 E-04 1.74E-06 0.00E+00 4.38E-04 4.94 E-03 l

Infant 1.95 E-04 2.86E-06 6.03 E-05 5.17E-07 0.00E+00 1.22E-04 6.00E-04 6

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NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 i April 3,1997 OFFSITE DOSE CALCULATION MANUAL Table 5.1-1, cont.

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

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

Te-125m Bone Liver T. Body Thyroid Kidney : Lungs GI-LLI Adult 3.30E-04 1.20E-04 4.43 E-05 9.93E-05 1.34E-03 0.00E+00 1.32 E-03

~~

Teen 3.36E-04 1.21 E-04 4.53 E-05 9.39E-05 0.00E+00 0.00E+00 9.92E-04 Child 5.74E-04 1.56 E-04 7.67E-05 1.61 E-04 0.00E+00 0.00E+00 5.54 E-04 Infant 2.47E-04 8.27E-05 3.35 E-05 8.33 E-05 0.00E+00 0.00E+00 1.18 E-04 l Dose factor - liquid release pathway (mrem /Ci released)

Te-127 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 3.15 E-05 1.13E-05 6.83E-06 2.34E-05 1.28 E-04 0.00E+00 2.49E-03 Teen 3.45E-05 1.22E-05 7.43 E-06 2.38E-05 1.40E-04 0.00E+00 2.67E-03 Child 4.45 E-05 1.20E-05 9.54 E-06 3.08E-05 1.27E-04 0.00E+00 1.74 E-03 Infant 3.10E-07 1.04 E-07 6.67E-08 2.52E-07 7.56F-07 0.00E+00 6.5 ] E-06 l Page 40 of 138

NUCLEAR POWER BUSINESS UNIT ODCM CFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 OFFSITE DOSE CALCULATION MANUAL Table 5.1-1, cont.

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

Te 127m

~

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

Adult 8.63 E-04 3.08E-04 1.05E-04 2.21 E-04 3.51 E-03 0.00E+00 2.89E-03 Teen 8.74 E-04 3.10E-04 1.04 E-04 2.08E-04 3.54E-03 0.00E+00 2.18E-03 Child 1.50E-03 4.0$E-04 1.79E-04 3.60E-04 4.29E-03 0.00E+00 1.22E-03

, Infant 6.28E-04 2.08E-04 7.6 t E-05 1.82E-04 1.55 E-03 0.00E+00 2.54 E-04 l

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

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

Te-129m Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 1.35 E-03 5.04 E-04 2.14 E-04 4.64 E-04 5.63 E-03 0.00E+00 6.80E-03 Teen 1.37E-03 5.10E-04 2.18 E-04 4.43 E-04 5.75 E-03 0.00E+00 5.16E-03 l Child 2.34 E-03 6.54 E-04 3.64 E-04 7.55 E-04 6.88E-03 0.00E+00 2.86E-03

! Infant 1.04 E-03 3.58E-04 1.61 E-04 4.01 E-04 2.61 E-03 0.00E+00 6.23 E-04 i

l l

Page 41 of 138 I

i

NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 OFFSITE DOSE CALCULATION MANUAL Table 5.1-1, cont.

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

Te-131 m Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 1.04 E-04 5.08E-05 4.24 E-05 8.05 E-05 5.15E-04 0.00E+00 5.05 E-03 Teen 1.llE-04 5.34E-05 4.49E-05 8.03E-05 5.56E-04 0.00E+00 4.28E-03 Child 1.63 E-04 5.63 E-05 6.00E-05 1.16E-04 5.45 E-04 0.00E+00 2.28E-03 Infant > 5.46E-05 2.20E-05 1.8 l E-05 4.45 E-05 1.51 E-04 0.00E+00 3.70E-04 Dose factor - liquid release pathway (mrem /Ci released) )

Te-13I l Bone Liver T. Body Thyroid Kidney Lungs GI-LLI !

Adult 2.97 E- 15 1.24 E- 15 9.40E- 16 2.44 E-15 1.30E-14 0.00E+00 4.21 E-16 Teen 3.21 E-15 1.32E-15 1.01 E-15 2.47E- 15 1.40E-14 0.00E+00 2.63 E-16 Child 4.12 E- 15 1.25 E- 15 1.23 E- 15 3.15 E- 15 1.24 E-14 0.00E+00 2.16E-14 l 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 GILLI Adult 1.96E-04 1.26E-04 1.19E-04 1.40E-04 1.22 E-03 0.00E+00 5.98E-03 Teen 2.05 E-04 1.30E-04 1.22E-04 1.37E-04 1.24 E-03 0.00E+00 4.llE-03 i Child 3.15 E-04 1.39E-04 1.69E-04 2.03 E-04 1.29E-03 0.00E+00 1.40E-03 i Infant 1.48 E-04 7.32 E-05 6.83E-05 1.08E-04 4.58 E-04 0.00E+00 2.71 E-04 Page 42 of 138

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Table 5.1-1, cont.

Dose factor - liquid release pathway (mrem /Ci released) 1 131 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 2.09E-04 2.99E-04 1.71 E-04 9.78E-02 5.12E-04 0.00E+00 7.88E-05 Teen 2.41 E-04 3.37E-04 1.81 E-04 9.83 E-02 5.80E-04 0.00E+00 6.66E-05 Child 4.90E-04 4.93E-04 2.80E-04 1.63E-01 8.09E-04 0.00E+00 4.39E-05 Infant 5.71 E-04 6.73 E-04 2.96E-04 2.21 E-01 7.86E-04 0.00E+00 2.40E-05 Dose factor - liquid release pathway (mrem /Ci r:- --. sed) 1-132 l

Bone Liver T. Body Thyroid ( Kidney Lungs GI-LLI Adult 1.43 E-07 3.81 E-07 1.34 E-07 1.33E-05 6.07 E-07 0.00E+00 7.16 E-08 Teen 1.49E-07 3.90E-07 1.41 E-07 1.32E-05 6.15 E-07 0.00E+00 1.70E-07 Child 1.85 E-07 3.39E-07 1.56E-07 1.57E-05 5.19E-07 0.00E+00 3.99E-07 Infant 1.64 E-I l 3.32 E-I l 1.18E-I l 1.56E-09 3.71 E-I l 0.00E+00 2.69E-I l Dose factor - liquid release pathway (mrem /Ci released) 1-133 Bone Liver T. Body Thyroid Kidney Lungs GILLI Adult 3.33E-05 5.80E-05 1.77E-05 8.52E-03 1.01 E-04 0.00E+00 5.21 E-05 Teen 3.74 E-05 6.34 E-05 1.94 E-05 8.85E-03 1.llE-04 0.00E+00 4.80E-05 Child 6.27E-05 7.75 E-05 2.94 E-05 1.44E-02 1.29E-04 0.00E+00 3.13E-05 l Infant 4.77E-05 6.95E-05 2.04E-05 1.26E-02 8.17E-05 0.00E+00 1.18E-05 l

l i

i i I

1 I

r Page 43 of 138 l

NUCLEAR POWER BUSINESS UNIT ODCM -

OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 i OFFSITE DOSE CALCULATION MANUAL Table 5.1-1, cont.

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 2.04 E-10 9.85 E-09 9.04E-10 0.00E+00 4.96E-13 Teen 2.20E-10 5.82E-10 2.10 E-10 9.70E-09 9.18E-10 0.00 E+00 7.67E-12 Child 2.72 E- 10 5.05 E-10 2.33 E-10 1.16E-08 7.72E-10 0.00 E+ 00 3.35 E- 10 Infant 5.37E-22 1.10E-21 3.91 E-22 2.56E-20 1.23 E-21 0.00E+00 1.14 E-21 Dose factor - liquid release pathway (mrem /Ci released) 1-135 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 3.37E-06 8.83 E-06 3.26E-06 5.82E-04 1.42E-05 0.00E+00 9.97E-06 Teen 3.55 E-06 9.14 E-06 3.41 E-06 5.88 E-04 1.44E-05 0.00E+00 1.01 E-05 Child 4.54 E-06 8.17E-06 3.87E-06 7.24 E-04 1.25 E-05 0.00E+00 6.23 E-06 Infant 4.48E-07 8.92E-07 3.25 E-07 7.99E-05 9.94 E-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 5.21 E-01 4.26E-01 0.00E+00 1.69E-01 5.60 E-02 9.12 E-03 Teen 2.25 E-01 5.30E-01 2.46E-01 0.00E+00 1.68E-01 6.43 E-02 6.59E-03 Child 2.76E-01 4.52E-01 9.55 E-02 0.00E+00 1.40E-01 5.03 E-02 2.44 E-03 Infant 1.07 E-02 2.00E-02 2.02E-03 0.00E+00 5.16E-03 2.llE-03 5.44 E-05 Page 44 of 138

NUCLEAR POWER BUSINESS UNIT ODCM l OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 OFFSITE DOSE CALCULATION MANUAL 1 Table 5.1-1, cont.

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

Cs-134m Bone Liver T. Body Thyroid Kidney Lungs GILLI Adult 4.21 E-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 5.48 E-06 8. l l E-06 5.29E-06 0.00E400 4.28E-06 7.07E-07 1.03 E-05 infant 5.19E-11 8.64 E-l I 4.37E-11 l0.00E+00 3.33 E- 11 7.67E- 12 6.84 E- 1 I Dose f actor - liquid release pathway (mrem /Ci released)

Cs-136 Bone Liver T. Body Thyroid Kidney Lungs GILLI Adult 2.23 E-02 8.8 ] E-02 6.34 E-02 0.00E+00 4.90E-02 6.72 E-03 1.00E-02 Teen 2.25E-02 8.85E-02 5.95E-02 0.00E+00 4.82 E-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 infant 1.18E-03 3.47E-03 1.29E-03 0.00 E+00 1.38E-03 j.83E-04 5.27E-J5 Dose factor - liquid release pathway (mrem /Ci released)

Cs-137 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 2.81E 01 3.84 E-01 2.52E-01 0.00E+00 1.30E-01 4.33 E-02 7.43 E-03 Teen 3.02E-01 4.01 E-01 1.40E-01 0.00E+00 1.36 E-01 5.30E-02 5.71 E-03 Child 3.85E-01 3.69E-01 5.45 E-02 0.00E+00 1.20E-01 4.33 E-02 2.31 E-03 Infant 1.49E-02 1.74 E-02 1.24E ';3 0.00E+00 4.68E-03 1.89E-03 5.45 E-05 a

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NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 OFFSITE DOSE CALCULATION MANUAL 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-l 1 7.04 E-11 3 49E-11 0.00E+00 5.18E-11 5.11E-12 3.00E-16 Teen 3.82E-11 7.34 E-l 1 3.67E-1 1 0.00E+00 5.42E-11 6.30E-12 3.33 E- 14 Child 4.84 E- 11 6.73 E-11 4.27E-l 1 0.00E+00 4.73 E-l I 5.10E- 12 3.10E- 1 1 Infant 1.63E-32 2.65E-32 1.28E-32 , 0.00E+00 1.32E-32 , 2.06E-33 4.23 E-32 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 4.93 E-1 1 0.00E+00 1.12 E-12 6.77E 13 2.97E-09 Teen 1.83 E-09 1.29E-12 5.50E-l 1 0.00E+00 1.21 E-12 8.87 E-13 1.63E-08 Child 2.35E-09 1.25 E-12 6.84E- 11 0.00E+00 1.09E- 12 7.37 E- 13 1.36 E-07 Infant 3.30E-16 2.19E-19 9.55 E- 18 0.00E+00 1.3 ] E- 19 1.33 E- 19 2.09E- 14 Dose factor - liquid release pathway (mrem /Ci released)

Ba-140 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 5.34 E-04 6.71 E-07 3.51 E-05 0.00E+00 2.28E-07 3.84E-07 1.10E-03 Teen 5.41 E-04 6.63 E-07 3.56E-05 0.00E+00 2.25 E-07 4.46E-07 8.35 E-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 3.61 E-07 9.34E-07 3.74E-04 g Page 46 of 138

l NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 OFFSITE DOSE CALCULATION MANUAL Table 5.1-1, cont.

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

Ba-14 i Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 4.57E- 19 3.45 E-22 1.63E-20 0.00E+00 3.21 E-22 1.96E-22 2.15 E-28 Teen 4.96E- 19 3.70E-22 2.14 E-20 0.00E+00 3.44E-22 2.53E-22 1.06 E-24 Child 6.37E 19 3.57E-22 2.18 E-20 0.00E+ 00 3.09E-22 2.10E-21 3.63 E- 19 Infant 1.58E 53 1.08E 56 4.99E-55 0.00E+00 6.52E-57 6.60E-57 1.93E-52 Dose factor - liquid release pathway (mrem /Ci released)

La-140 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 3.66E-08 1.84 E-08 1.03 E-07 0.00E+00 0.00E+00 0.00E+00 1.35 E-03 Teen 3.68E-08 1.81 E-08 5.51 E-07 0.00E+00 0.00E+00 0.00E+00 1.04 E-03 Child 8.21 E-08 2.87E-08 1.24 E-07 0.00E+00 0.00E+00 0.00E+00 8.00E-04 Infant 8.56E-08 3.38E-08 8.69E-09 0.00E+00 0.00E+00 0.00E+00 3.97E-04 l Dose factor - liquid release pathway (mrem /Ci released)

La-142 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 2.92 E-I l 1.33 E-I l 4.94 E-I l 0.00E+00 0.00E+00 0.00E+00 9.71 E-08 Teen 3.12 E-I l 1.38 E- 11 2.61E 10 0.00E+00 0.00E+00 0.00E+00 4.21 E-07 Child 3.93 E-1 I 1.25 E- 1 i 5.77E-11 0.00E+00 0.00E+00 0.00E+00 2.48E-06 Infant 7.74 E- 18 2.84 E- 18 6.8 ] E- 19 0.00 E+00 0.00E+00 0.00E+00 4.83 E-13 l

l Page 47 of 138 l

NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 OFFSITE DOSE CALCULATION MANUAL Table 5.1-1, cont.

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

Ce-14i Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 2.05 E-07 1.39E-07 2.42E-07 0.00E+00 6.45 E-08 0.00E+00 5.31 E-04 Teen 2.06E-07 1.37E-07 4.88 E-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 3.6 ] E-04 Infant 7.llE-07 4.34E-07 5.llE-08 0.00E+00 1.34 E-07 0.00E+00 2.24E-04 Dose factor - liquid release pathway (mrem /Ci released)

Cc-143 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 1.47E-08 1.09E-05 1.78E-08 0.00E+00 4.78E-09 0.00E+00 4.06E-04 Teen 1.49E-08 1.08E-05 9.40E-08 0.00E+00 4.86E-09 0.00E+00 3.26 E-04 Child 4.0lE-08 2.17E-05 2.25 E-08 0.00E+00 9.12 E-09 0.00E+00 3.18 E-04 Infant 5.10E-08 3.38E-05 3.86E-09 0.00E+ 00 9.85 E-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 1.04 E-06 0.00E+00 2.77E-06 0.00E+00 3.78E-03 Teen 1.12E-05 4.65 E-06 3.03 E-06 0.00E+00 2.78E-06 0.00E+00 2.82 E-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 1.61 E-03 l

l l

1 Page 48 of 138

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NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 OFFSITE DOSE CALCULATION MANUAL Table 5.1-1, cont.

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

Pr-143 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 5.69E-07 2.28 E-07 2 r b-08 0.00E+00 1.32E-07 0.00E+00 2.49E-03 Teen 6.00E-07 2.40E-07 759E-08 0.00E+00 1.39E-07 0.00E+00 1.97E-03 Child 1.07E-06 3.21 E-07 5.31 E-08 0.00E+00 1.74 E-07 0.00E+00 1.15 E-03 Infant 6.81 E-07 2.55 E-07 3.38E-08 0.00E+00 9.47E-08 0.00E+00 3.60E-04 Dose factor - liquid release pathway (mrem /Ci released)

Pr-144 Thyroid Kidney Lungs GILLI )

Bone Liver T. Body Adult 3.76E-22 1.56E-22 2.24E-23 0.00E+00 8.80E-23 0.00E+00 5.41 E-29 Teen 4.09E-22 1.67E-22 3.91 E-23 0.00E+ 00 9.61 E-23 0.00E+00 4.51 E-25 Child 5.29E-22 1.64 E-22 3.05 E-23 0.00E+00 8.66E-23 0.00E+00 3.52E-19 infant 1.72E-59 6.66E-60 8.67E-61 0.00 E+ 00 2.41 E-60 0.00E+00 3.10E-55 Dose factor - liquid release pathway (mrem /Ci released)

Nd-147 Bone Liver T. Body ThyToid Kidney Lungs GI-LLI Adult 3.82E-07 4.42E-07 1.13 E-07 0.00E+00 2.58 E-07 0.00E400 2.12 E-03 Teen 4.23 E-07 4.60E-07 5.09E-07 0.00E+00 2.70E-07 0.00E+00 1.66E-03 Child 7.45 E-07 6.03 E-07 1.47 E-07 0.00E+00 3.31 E-07 0.00E+00 9.55 E-04 Infant 4.53 E-07 4.65 E-07 2.85 E-08 0.00 E+ 00 1.79E-07 0.00E+00 2.95E-04 l

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NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 OFFSITE DOSE CALCULATION MANUAL Table 5.1-1, cont.

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

Eu 152 Bone Liver T. Body Thyroid Kidney Lungs GILLI Adult 1.31 E-05 2.99E-04 1.63 E-04 0.00E+00 1.85E-05 0.00E+00 1.72E-03 Teen 1.21 E-05 2.92E-06 9.00E-04 0.00E+00 1.35E-05 0.00E+00 1.07E-03 Child 1.84 E-05 3.34 E-06 1.91 E-04 0.00E+00 1.41 E-05 0.00E+00 5.49E-04 Infant 6.27E-06 1.67E-06 1.40E-06 0.30E+00 4.67E-06 0.00E+ 00 1.48 E-04 i

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

W-187 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 1.52E-04 1.27E-04 4.45E-05 0.00E+00 0.00E+00 0.00E+00 4.17E-02 Teen 1.65 E-04 1.34 E-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 0.00 E+00 0.00E+00 1.74 E-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 Dose factor - liquid release pathway (mrem /Ci released)

Np-239 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Adult 3.15 E-08 3.09E-09 2.30E-08 0.00 E+00 9.65E-09 0.00E+00 6.34 E-04 Teen 3.42 E-08 3.22E-09 1.21 E-07 0.00E+00 1.01 E-08 0.00E+00 5.19E-04 Child 6.77E-08 4.86E-09 2.83 E-08 0.00E+00 1.41 E-08 0.00E+00 3.60E-04 Infant 5.72E-08 5.12E-09 2.89E-09 0.00E+00 1.02E-08 0.00E+00 1.48E-04 Page 50 of 138

1 NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 1 April 3,1997 OFFSITE DOSE CALCULATION MANUAL ;

Table 5.1-1, cont.

)

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

U-235 Bone Liver T. Body Thyroid Kidney Lungs GILLI Adult 3.0$E-02 0.00E+00 1.89E-03 0.00E+00 7.13 E-03 0.00E+00 2.98E-03 Teen 3.17E-02 0.00E+00 2.13 E-03 0.00E+00 7.43 E-03 0.00E+00 2.30E-03 Child 6.92E-02 0.00E+00 4.23E-03 0.00E+00 1.14 E-02 0.00E+00 1.63 E-03 Infant 4.42E-02 0.00E+ 00 3.37E-03 0.00 E+00 9.40E-03 0.00E+00 7.67E-04 Dose factor - liquid release pathway (mrem /Ci released)

U-238 l

Bone Liver T. Body Thyroid 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 Teen 3.03 E-02 0.00E +00 1.81 E-03 0.00 E+00 6.96E-03 0.00E+00 1.62E-03 j Child 6.62E-02 0.00E+00 3.93 E-03 0.00E+00 1.06E-02 0.00 E+00 1.15 E-03 Infant 4.23 E-02 0.00E+00 3.15 E-03 0.00E+00 8.78E-03 0.00E+00 5.41 E-04 Dose factor - liquid release pathway (mrem /Ci released)

Am-241 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI I Adult 5.25 E-02 1.85 E-02 3.47E-03 0.00E+00 2.61 E-02 0.00 E+00 4.75 E-03 I Teen 4.10E-02 1.56E-02 2.77E-03 0.00E+00 2.05E-02 0.00E400 3.74E-03 Child 4.10E-02 1.83 E-02 2.93E-03 0.00E+00 1.79E-02 0.00E+00 2.19E-03 Infant 1.42E-02 6.68 E-03 1.01 E-03 0.00E+00 6.10E-03 0.00E+00 7.17E-04 1 k

Page 51 of 138

NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 l April 3,1997 l OFFSITE DOSE CALCULATION MANUAL 5.1.2 Atmospheric Release Mode: Radiciodine, Tritium, and Particulates The dose calculations for demonstration of compliance with the 10 CFR 50.

Appendix I dose limits for radioiodines, tritium, and particulate radionuclides released to the atmosphere will be done in the manner similar to the liquid release dose calculations described in Section 5.1.1. The total dose is compared to the corresponding atmospheric release mode Appendix I dose limit for the organ in question.

The doses are calculated using the following formula:

API = I Dose aomi =

I (TDFaomi x C;) s Kom mrem Where API = the Appendix 1 dose for compliance evaluations in mrem Dose aomi =

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

TDF aomi =

total dose factor for the specific age group (a) and organ (o) via release mode (m) from radionuclide (i) from Table 5.1-2 in mrem /Ci C; = curies of radionuclide (i) released K om =

the Appendix I dose limit for organ (o) and release mode (m) for which the calculation is being made.

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

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NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 q April 3,1997 OFFSITE DOSE CALCULATION MANUAL I

)

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 j to a vendor for analysis. Usually, the only radionuclides affected by these i 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 f

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. j I

Instead of using the precalculated total dose factors, the Appendix I dose !

calculation may be modified to reflect the actual x/Q during the release ]

l period using the methodology of Appendix C.

1 Page 53 of 138

NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 OFFSITE DOSE CALCULATION MANUAL TABLE 5.1-2 ;

AIRBORNE EFFLUENT DOSE FACTOR Summations of dose per curie released were made for calculations over the pathways: ingestion of produce, leafy vegetables, milk, meat; inhalation of airborne radionuclides, and direct exposure to deposited radioactivity.

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

H-3 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 0.00E+00 9.78E-05 9.78E-05 9.78 E-05 9.78E-05 9.78 E-05 9.78E-05 0.00E4 00 Teen 0.00E+00 1.03 E-04 1.03 E-04 1.03 E-04 1.03 E-04 1.03 E-04 1.03 E-04 0.00E+00 Child 0.00E+00 1.32E 04 1.32 E-04 1.32E-04 1.32 E-04 1.32 E-04 1.32E-04 0.00E+00 Infant 0.00E+00 2.03 E-05 2.03 E-05 2.03E-05 2.03 E-05 2.03 E-05 2.03E-05 0.00E+00 Dose factor - airborne release pathway (mrem /Ci released)

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

Na-22 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 4.83 E+00 4.83 E+00 2.89 E+0 ! 4.83E+00 4.83 E+00 4.83E+00 4.83 E+00 3.79E+01 Teen 7.41 E+00 7.41 E+00 3.15 E+01 7.41 E+00 7.41 E+00 7.41 E+00 7.41E+00 3.79E+01 Child 1.50E+01 1.50E+01 3.90E+01 1.50E+01 1.50E+01 1.50E+0 ! 1.50E+01 3.79E+01 Infant 1.81E+01 1.8IE+01 4.21 E+01 1.81E+0l 1.8IE+01 1.81E+01 1.8IE+01 3.79E+01 1

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NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 OFFSITE DOSE CALCULATION MANUAL Table 5.1-2, cont.

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

Na-24 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 9.48E-04 9.48 E-04 1.77E-02 9.48 E-04 9.48 E-04 9.48 E-04 9.48 E-04 7.64E-02 Teen 1.36E-03 1.36E-03 1.8 ] E-02 1.36 E-03 1.36E-03 1.36E-03 1.36E-03 7.64 E-02 Child 2.37E-03 2.37E-03 1.91 E-02 2.37E-03 2.37E-03 2.37E-03 2.37E-03 7.64E-02 infant 3. I4 E-03 3. I4 E-03 1.99E-02 3. I4 E-03 3. I4E-03 3. I 4 E-03 3. I4E-03 7.64 E-02 Dose factor - airborne release pathway (mrem /Ci released)

Sc-46 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 1.33E 02 2.59 E-02 2.00E+00 0.00E+00 2.42 E-02 0.00E+00 2.40E+00 2.69E+00 Teen 1.75 E-02 3.41 E-02 2.00E+00 0.00E+00 3.26E-02 0.00E+00 2.09E+00 2.69E+00 Child 2.23E 02 3.0$E-02 2.00E+00 0.00E+00 2.70E-02 0.00E+00 1.32E+00 2.69E+00 Infant 1.56E-02 2.25 E-02 2.00E+00 0.00E+00 1.48 E-02 0.00E+00 1.35 E-03 2.69E+00 l

Dose factor - airborne release pathway (mrem /Ci released) l Mn-54 l 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 2.28 E+00 Teen 0.00E+00 3.34E-01 2.01 E+00 0.00E+00 9.95 E-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 4.68 E-02 4.08E-01 2.28 E+00 Infant 0.00E+00 2.03 E-02 1.95E+00 0.00E+00 4.47E-03 2.97E-02 7.38E-03 2.28 E+00 l

l l

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NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,199 / j OFFSITE DOSE CALCULATION MANUAL j Table 5.1-2, cont.

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

Cr-51 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 0.00E+00 0.00E+00 6.59E-03 2.68 E-05 9.86E-06 4.83 E-04 1.07E-02 7.73E-03 Teen 0.00E+00 0.00E+00 6.60E-03 3.39E-05 1.34 E-05 7.03 E-04 9.66 E-03 7.73 E-03 Child 0.00E+00 0.00E+00 6.66E-03 6.30E-05 1.72E-05 6.14 E-04 5.81 E-03 7.73E-03 Infant 0.00E+00 0.00E+00 6.58 E-03 2.42 E-05 5.31 E-06 4.25E-04 1.02E-03 7.73 E-03 Dose factor airborne release pathway (mrem /Ci released)

Mn-56 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 0.00 E+00 4.8 ] E-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 6.05 E-08 1.27E-03 0.00E+00 6.61 E-08 4.51 E-04 1.70E-03 1.50E-03 Child 0.00E+00 6.26E-08 l.27E-03 0.00E+00 6.58 E-08 3.90E-04 3.66E 03 1.50E-03 Infant 0.00E+00 4.57E-08 1.27E-03 0.00 E+00 3.27E-08 3.72E-04 2.13 E-03 1.50E-03 Dose factor - airborne release pathway (mrem /Ci released)

Fe-55 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 3.20E-01 2.21 E-01 5.15E-02 0.00 E+00 0.00E+00 1.25 E-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. I 7E-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 1nfant 7.36E-02 4.75 E-02 1.27E-02 0.00E+00 0.00E+00 2.56E-02 6.02 E-03 0.00E+00 Page 56 of 138

NUCLEAR POWER BUSINESS UNIT ODrM OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 OFFSITE DOSE CALCULATION MANUAL l

Table 5.1-2, cont.

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

Fe-59 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 2.01 E-01 4.73 E-01 5.65E-01 0.00E+00 0.00E+00 1.62E-01 1.58E+00 4.50E-01 Teen 2.25 E-01 5.24E-01 5.86E-01 0.00E+00 0.00E+00 2.10E-01 1.24E+00 4.50E-01 Child 4.62E-01 7.48 E-01 7.56E-01 0.00E+00 0.00E+00 2.54E-01 7.80E-01 4.50E-01 Infant 6.14 E-02 1.07E-01 4.26E-01 0.00E+00 0.00E+00 6.16E-02 5.16E-02 4.50E-01 Dose factor - airborne release pathway (mrem /Ci released)

Co-57 Bone Liver T, Body Thyroid Kidney Lungs GI-LLI Skin Adult 0.00E+00 1. I 7E-02 4.93 E-01 0.00E+00 0.00E+00 1.1OE-02 2.97E-01 6.13E-01 Teen 0.00E+00 1.50E-02 5.00E-01 0.00E+00 0.00E+00 1.74E-02 2.97E-01 6.13E-01 Child 0.00E+00 2.57E-02 5.26E-O l 0.00E+00 0.00E+00 1.50E-02 2.llE-01 6.13E-01 Infant 0.00E+ 00 4.38 E-03 4.81 E-01 0.00E+00 0.00E+00 1.13 E-02 1.50E-02 6.13 E-01 l 1

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

I Co-58 Done Liver T. Body Thyroid Kidney Lungs GILLI 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 4.00E-02 6.24E-01 0.00E+00 0.00E+00 3.99E-02 5.53 E-01 6.23E-01 Child 0.00E+00 5.73 E-02 7.07E-01 0.00E+00 0.00E+00 3.28 E-02 3.35E-01 6.23E-01 Infant 0.00E+00 9.90 E-03 5.57E-01 0.00E+00 0.00E+00 2.31 E-02 2.49E-02 6.23 E-01 4

Page 57 of 138

I NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 OFFSITE DOSE CALCULATION MANUAL j I

Table 5.1-2, cont. I l

l 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+0! 0.00E+00 0.00E+00 1.77E-01 3.16E+00 3.56E+01 Teen 0.00E+00 2.23 E-01 3.07E+01 0.00E+00 0.00E+00 2.59E-01 2.90E+00 3.56E+0 !

Child 0.00E+00 3.28 E-01 3.12E+01 0.00E+00 0.00E+00 2.10E-Ol 1.82E+00 3.56E+01

[Ini'ont 0.00E+00 5.86E-02 3.04 E+01 0.00E+00 0.00E400 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 Teen 2.93 E+01 2.07E+00 9.92E-01 0.00E+00 0.00E+00 9.llE-03 3.29E-01 0.00E+00 Child 6.73 E+01 3.60E+00 2.29E*00 0.00E+00 0.00 E+00 8.16E-03 2.43 E-01 0.00E+00 Infant 2.1 I E+01 1.30E+00 7.32 E-01 0.00E+00 0.00E+00 6.19E-03 6.49E-02 0.00E+00 Dose factor - airborne release pathway (mrem /Ci released) l Ni-65 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 8.95 E-08 1.19E-08 4.17E-04 0.00E+00 0.00E+00 1.66E-04 3.66E-04 4.85 E-04 Teen 1.06E-07 1.39E-08 4.17E-04 0.00E+00 0.00E+00 2.78E-04 1.09E-03 4.85 E-04 l Child 1.64 E-07 1.58 E-08 4.17 E-04 0.00E+00 0.00E+00 2.43 E-04 2.49E-03 4.85E-04 l Infant 7.17E-08 8.51 E-09 4.17 E-04 0.00E+00 0.00E+00 2.41 E-04 1.49E-03 4.85E-04 i

I t

i Page 58 of138

NUCLEAR POWER BUSINESS UNIT ODCM l OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 OFFSITE DOSE CALCULATION MANUAL l

i-l Table 5.1-2, cont.

Dose factor - airbome 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 9.65 E-04 Teen 0.00E+00 1.40E-05 8.58 E-04 0.00E+00 3.54 E-05 3.30E-04 2.90E-03 9.65 E-04 Child 0.00E+00 2.19E-05 8.65 E-04 0.00E+00 5.28 E-05 2.84 E-04 2.llE-03 9.65 E-04 Infant 0.00E+00 3.42E-05 8.68 E-04 0.00 E+00 5.79E-05 2.76 E-04 1.15E-03 9.65 E-04 Dose factor - r.irborne release pathway (mrem /Ci released)

Zn-65 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 1.21E+00 3.85 E+00 2.79E+00 0.00E+00 2.57E+00 2.56E-02 2.42E t00 1.21 E+00 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 5.24 E+00 2.95 E-02 1.46E+00 1.21E+00 Infant 2.95 E+00 1.01E+01 5.7 I E+00 0.00E+00 4.91 E+00 1.92 E-02 8.54E+00 1.21 E+00 Dose factor - airborne release pathway (mrem /Ci released)

Zn-69 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 3.01 E-06 5.76E-06 4.01 E-07 0.00E+00 3.74 E-06 2.73E-05 1.35 E-06 0.00E+00 Teen 4.64 E-06 8.83E-06 6.18E-07 0.00 E+00 5.77E-06 4.70E-05 2.47E-05 0.00E+00 Child 1.08E-05 1.56E-05 1.45 E-06 0.00E+00 9.49E-06 4.22E-05 1.29E-03 0.00E+00 Infant 1.93 E-05 3.48E-05 2.59E-06 0.00E+00 1.45 E-05 4.36E-05 3.23E-03 0.00E+00 l

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! OFFSITE DOSE CALCULATION MANUAL

(

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l Table 5.1-2, cont.

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

Zn-69m 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 5.74 E-03 Child 1.76E-04 3.00E-04 3.09E-03 0.00E+00 1.74 E-04 8.08E-04 1.27E-02 5.74 E-03 Infant 3.IIE-04 6.35 E-04 3.12E-03 0.00E+00 2.57E-04 7.93E-04 1.00E-02 5.74 E-03 i

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

Br-82 Bone Liver T. Body ThyToid Kidney Lungs GI-LLI Skin Adult 0.00E+00 0.00E+00 5.44E-02 0.00E+00 0.00E+00 0.00E+00 8.47E-03 6.41 E-02 Teen 0.00E+00 0.00E+00 ' 5.89E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 6.41 E-02 Child 0.00Et00 0.00E+00 7.04 E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 6.41 E-02 Infant 0.00E+00 0.00E+00 8.32E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 6.41 E-02 Dose factor - airborne release pathway (mrern/Ci released)

Br-83 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 0.00 E+00 0.00E+00 1.65 E-05 0.00E+00 0.00E+00 0.00E+00 6.89E-06 2.84E-03 Teen 0.00E+00 0.00E+00 1.96E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.84 E-03 Child 0.00E+00 0.00E+00 2.34 E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.84E-03 Infant 0.00E+00 0.00E+00 2.07E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.84E-03 Page 60 of 138

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Tab!c 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 Teen 0.00E+00 0.00E+00 2.60E-02 0.00E+0') 0.00E+00 0.00E+00 0.00E+00 2.49h 01 Child 0.00E+00 0.00E+00 2.63 E-02 0.00 E+00 0.00E+00 0.00E+00 0.00E+00 2.495-0!

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 4.95 E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.63 E-04 Teen 0.00 E+00 0.00E+00 7.06 E-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.63 E-04 Child 0.00E+ 00 0.00E+00 2.02 E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.63 E-04 Infant 0.00 E+00 0.00E+00 4.21 E-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.63 E-04 Dose factor - airborne release pathway (mrem /Ci released)

Rb-86 Bone Liver T. Body i Thyroid Kidney Lungs GI-Lil Skin Adult 0.00E+00 8.21 E-01 3.95 E-01 0.00E+00 0.00E+ 00 0.00E+00 1.61 E-01 1.44 E-02 Teen 0.00E+00 1.23 E+00 5.92E-01 0.00 E+00 0.00E+00 0.00E+00 1.82E-01 1.44 E-02 Child 0.00E+00 2.18 E+00 1.35E+00 0.00E+00 0.00E+00 0.00E+00 1.40E-01 1.44 E-02 Infant 0.00E+00 4.17E+00 2.07E+00 0.00E+00 0.00E+00 0.00E+00 1.07E-01 1.44 E-02 i

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Dose factor - airborne release pathway (mrem /Ci released) I l 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 5.73 E-05 0.00E+00 0.00E+00 0.00E+00 5.12E-07 5.3 ] E-05 Infant 0.00E+00 1.65 E-05 5.50E-05 0.00E+00 0.00E+00 0.00E+00 1.0lE-05 5.3 ] 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 1.78 E-04 0.00E+00 0 00E+00 0.00E+00 2.75 E-19 2.07E-04 l Teen 0.00E+00 1.04E-05 1.80E-04 0.00E+00 0.00E+00 0.00 E+00 1.00E-14 2.07E-04 l

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 Infant 0.00E+00 9.51 E-06 1.79 E-04 0.00E+00 0.00E+00 0.00E+00 2.02E-06 2.07E-04 l

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

Sr-89 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 7.63 E+00 0.00E+00 2.19E-01 0.00E +00 0.00E+00 4.15E-02 1.23 E+00 3.53 E-05 Teen 1.16E+01 0.00E+00 3.34 E-01 0.00E+00 0.00E+00 7.17E-02 1.40E+00 3.53 E-05 Child 2.77E+01 0.00E+00 7.90E-01 0.00E+00 0.00E+00 6.40E-02 1.08 E+00 3.53 E-05 Infant 3.66E+00 0.00E+00 1.05E-01 0.00E+00 0.00E+00 6.02E-02 7.69E-02 3.53 E-05 Page 62 of 138

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l l Table 5.1-2, cont.

l l

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

Sr-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+0! 0.00E+00 Teen 6.33 E+02 0.00E+00 1.56 E+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 4.38 E-01 1.41E+01 0.00 E +00 Infant 7.33E+01 0.00E+00 1.84 E+0 ! 0.00E+00 0.00E+00 3.34E-01 9.04 E-01 0.00E+00 i

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

Sr-91 Bone Liver T. Body Thyroid Kidney . Lungs GI-LLI Skin Adult 2.29 E-04 0.00E+00 3.03 E-03 0.00 E+00 0.00 E+00 1.08 E-03 6.76E-03 3.53 E-03 Teen 2.20E-04 0.00E+00 3.03 E-03 0.00E+00 0.00E+00 1.80E-03 8.68 E-03 3.53E-03 Child 4.09E-04 0.00E+00 3.03 E-03 0.00E+00 0.00E+00 1.58 E-03 6066-03 3.53 E-03 Infant 5.29 E-05 0.00E+00 3.02E-03 0.00E+00 0.00E+00 1.56E-03 2.24 E-03 3.53 E-03

~

Dose factor - airborne release pathway (mrem /Ci released) l Sr-92 l Bone Liver T. Body Thyroid Kidney Lungs GILLI Skin l Adult 5.04 E-07 0.00E+00 1.65 E-03 0.00E+00 0.00E+00 4.89E-04 1.28 E-03 3.15E-03 Teen 5.66E-07 0.00E+00 1.65 E-03 0.00E+00 0.00E+00 8.14 E-04 3.54 E-03 3.15E-03 Child 9.08E-07 0.00E+00 1.65 E-0?, 0.00E+00 0.00E+00 7.12E-04 7.20E-03 3.15 E-03 Infant 3. I 2E-07 0.00E+00 1.65 E-03 0.00E+00 0.00E+00 7.06E-04 4.15E-03 3.15 E-03 l

4 \

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NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 OFFSITE DOSE CALCULATION MANUAL Table 5.1-2, cont.

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

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

Y-91 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 1.78 E-02 0.00E+00 1.98E-03 0.00E+00 0.00 E+00 5.06E-02 2.26E+00 1.70 E-03 Teen 2.55 E-02 0.00E+00 2.19 E-03 0.00E+00 0.00E+00 8.71 E-02 2.44 E+00 1.70E-03 Child 4.10E-02 0.00E+00 2.60E-03 0.00 E+00 0.00E+00 7.79E-02 1.86E+00 1.70E-03 Infant 1.75E-02 0.00E+00 1.97E-0? 0.00E+00 0.00E+00 7.27E-02 3.72 E-03 1.70E-03 I

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

Y-91m Bone Liver T. Body Thyroid Kidney Lungs GILLI Skin Adult 3.58E-06 0.00E+00 2.31 E-04 0.00E+ 00 0.00E+ 00 5.70E-05 1.05 E-05 4.33 E-0 4 Teen 6.15 E-06 0.00E+00 2.31 E-04 0.00E+00 0.00E+00 9.49E-35 2.91 E-04 4.33 E-Or.

Child 1.50E-05 0.00E+00 2.31 E-04 0.00E+00 0.00E+00 8.34E-05 2 94E-02 4.33 E-On infant 1.21 E-08 0.00E+00 2.31 E-04 0.00E+00 0.00E+00 8.27E-05 6.98 E-05 4.33E-0 4 l

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NUCLEAR POWER BUSINESS UNIT ODC.'1 OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 OFFSITE DOSE CALCULATION MANUAL Table 5.1-2, cont.

Dose factor airborne release pathway (mrem /Ci released)

Y-92 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin l Adult 3.35 E-05 0.00E+00 4.38 E-04 0.00E+00 0.00E+00 4.65E-04 5.83E-01 2.90E-02 I Teen 5.80E-05 0.00E+00 4.39E-04 0.00E+00 0.00E+00 7.95 E-04 1.58E+00 2.90E-02 Child 1.42E-04 0.00E+00 4.41 E-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 l

l Dose factor - airborne release pathway (mrern/Ci reieased)

Y-93

~

Bone Liver T. Body Thyroid Kidney Lungs GILLI Skin Adult 1.08 E-04 0.00E+00 4.43 E-04 0.00E+00 0.00E+00 1.44 E-03 3.35E+00 6.58 E-02 l Teen 1.86E-04 0.00E+ 00 4.45 E-04 0.00E+00 0.00 E+00 2.47E-03 5.59 E+00 6.58E-02 Child 4.53 E-04 0.00E+00 4.52E-01 0.00E+00 0.00E+00 2.21 E-03 6.69E+00 6.58E-02 Infant 4.45 E-06 0.00 E+00 4.40E-04 0.00E+00 0.00E+00 2.27E-03 4.95E-03 6.58 E-02 l

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

Zr-95 Bone Liver T. Body Thyroid Kidney Lungs GI LLI Skin Adult 4.79E-03 1.54 E-03 3.45E-01 0.00E+00 2.42E-03 5.25E-02 1.64 E+00 3.98 E-01 Teen 6.16E-03 1.94E-03 3.45E-01 0.00E+00 2.85 E-03 7.98 E-02 1.35E+00 3.98E-01 Child 9.47E-03 2.08E-03 3.45 E-01 0.00E+00 2.97E-03 6.62E-02 8.81 E-01 3.98E-01 Infant 3.43 E-03 8.27E-04 3.44E-01 0.00E+00 9.23 E-04 5.19E-02 9.12E-04 3.98E-01 Page 65 of 138

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

Zr-97 l Bone Liver T. Body l Thyroid Kidney Lungs GI-LLI Skin Adult 3.12E-06 6.31 E-07 4.16E-03 0.00E+00 9.56E-07 2.34E-03 3.09E-02 4.84E-03 Teen 4.3 t E-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 1.24 E-06 3.36E-03 1.95E-02 4.84E-03 Infant 4.45 E-06 7.60E-07 4 16E-03 0.00E+00 7.69E-07 3.27E-03 4.16E-03 4.84E-03 Dose factor - airborne release pathway (mrem /Ci released)

Nb-95 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin 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 Teen 1.39 E-03 7.72 E-04 1.92 E-01 0.00E +00 7.48 E-04 2.23 E-02 1.99E+00 2.26 E-01 Child 2.22E-03 8.65E-04 1.93E-01 0.00E+00 8.13 E-04 1.82E-02 1.10E+00 2.26E-01 Infant 6.08E-04 2.49E-04 1.92E-01 0.00E+00 1.82 E-04 1.42E-02 4.99E-02 2.26E-01 Dose f actor - airborne release pattw ay (mrenVCi released)

Nb-97 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 2.0$ E-06 5.17E-07 4.17E-04 0.00E+00 6.03 E-07 7.12E-05 1.91 E-03 3.20E-03 Teen 3.50E-06 8.68E-07 4.17 E-04 0.00E+00 1.02 E-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 1.01 E-04 4.73 E-01 3.20E-03 J lnfant 1.01 E-08 2. I 6 E-09 4. I 7E-04 0.00E+00 1.69E-09 9.84 E-05 7.98 E-04 3.20E-03 Page 66 of 138

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l l

Table 5.1-2, cont.

i l

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

Mo-99 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 0.00E+00 9.IOE-03 7.34E-03 0.00E+00 2.06E 02 2.71 E-03 2.85E-02 6.50E-03 Teen. 0.00E+00 1.24 E-02 7.97E-03 0.00E+00 2.84E-02 4.56E-03 3.02E-02 6.50E-03 Child 0.00E+00 2.06E-02 1.07E-02 0.00E*00 4.4 ] E-02 4.02E-03 2.08E-02 6.50E-03 Infant 0.00E+00 3.82E-02 1.31 E-02 0.00E+00 5.70E-02 4.00E-03 1.40E-02 6.50E-03 Dose factor - airborne release pathway (mrem /Ci released)

Tc-99m l Bone Liver T. Body l Thyroid Kidney Lungs GI-LLI Skin Adult 2.92 E-09 8.24 E-09 2.59E-04 0.00E+00 1.25 E-07 2.27E-05 1.28E-04 2.96E-04 Teen 3.1IE-09 8.68E-09 2.59 E-04 0.00E+00 1.29E-07 3.42E-05 1.87E-04 't.96 E-04 Child 5.95E-09 1.17E-08 2.59E-04 0.00E+00 1.69E-07 2.82E-05 1.49E-04 2.96E-04 Infant 5.14E-09 1.06E-08 2.59E-04 0.00E+00 1.14 E-07 2.41 E-05 6.33 E-05 2.96E-04 i

l Dose factor - airborne release pathway (mrent Ci released)

Tc-101 Bone Liver T. Body Thyroid Kidney Lungs GILLI Skin Adult 1.16E-05 1.67E-05 2.08E-04 0.00E+00 3.01 E-04 2.04E-05 5.06 E-17 5.80E-04 Teen I .99E-05 2.83 E-05 3.23 E-04 0.00E+00 5.12E-04 3.71 E-05 4.87E-12 5.80E-04 l Child 4.89E-05 5.12E-05 6.93E-04 0.00E+00 8.72E-04 4.44E-05 1.63B-64 liUE44' infant 1.93 E- 12 2.44 E- 12 4.44 E-05 0.00E+00 2.90E- 11 1.73E-05 2.50E-05 5.80E-04 Page 67 of 138

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Table 5.1-2, cont.

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

I Ru-103 i

l Bone Liver T. Body n yroid Kidney Lungs GI-LLI Skin Adult 4.36E-02 0.00E +00 1.71 E-01 0.00E+00 1.66E-01 1.50E-02 5.08 E+00 1.77E-01 l Teen 3.76E-02 0.00E+00 1.68E-01 0.00E r00

' 1.33 E-01 2.32E-02 3.14 E+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 1.64 E-02 5.05 E-04 1.77E-01 l

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

! Ru-105 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin

! Adult 6.19 E-04 900E-00 2.07E-03 0.00 E+00 7.99E-03 3.25 E-04 3.80E-O i 1.02E-02 Teen 1.06E-03 0.00E+00 2.23 E-03 0.00E+00

1.34 E-02 5.39E-04 8.59E-O L 1.02E-02 Child 2.59E-03 0.00E+00 2.76E-03 0.00E+00 2.28E-02 4.72 E-04 1.69E+00 1.02E-02 Infant 3.63 E-08 0.00E+00 1.82E-03 0.00E+00 2.67E-08 4.65 E-04 1.44E-03 1.02 E-02 l

Dose factor - airborne release pathway (mretrvCi released) l Ru- 106 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 1.65E+00 0.00b+00 8.01 E-01 0.00E+ 00 l 3.18E+00 2.78E-01 1.06E+02 7.llE-01 Teen 1A9E+00 0.00E+00 7.8 I E-01 0.00E+00 2.88E+00 4.77E-01 7. I 6E+01 7.IIE-01 Child 2.93 E+00 0.00E+00 9.58E-01 0.00E+00 3.96E+00 4.25E 01 4.55E+01 7.1IE-01 Infant 2.67E-03 0.00E+00 5.93E-01 0.00E+00 3.28 E-03 3.43 E-01 5.60E-03 7.1lE-01 l

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

Rh-105 Bone Liver T. Body n yroid Kidney Lungs GI-LLI Skin Adult 4.81 E-02 3.52E-02 2.47E-02 0.00E+00 1.50E-01 5.72E-04 5.61 E+00 7.74 E-03 I

Teen 8.33 E-02 6.02E-02 4.10E-02 0.00E+00 2.56E-01 9.71 E-04 7.66E+00 7.74 E-03 l Child 2.04E-01 1.10E-01 9.53E-02 0.00E+00 4.37E-01 8.59E-04 6.80E+00 7.74 E-03 Infant 7.15E-04 4.68E-04 1.83 E-03 0.00E+00 1.30E-03 8.64E-04 1.22E-02 7.74 E-03 Dose factor airborne release pathway (mrem /Ci released)

Ag-l 10m Bone Liver T. Body n yroid Kidney Lungs GILLI Skin Adult 4.10E-02 3.80E-02 4.85E+00 0.00E+00 7.47E-02 1.37E-01 1.54 E+01 5.63 E+00 l Teen 6.28E-02 5.94 E-02 4.86E+00 0.00 E+ 00 1.13 E-01 2.00E-01 1.66E+0 ) 5.63 E+00 Child 1.34 E-01 9.04 E-02 4.90 E+ 00 0 00E+00 1.68E-01 1.62E-01 ,1.07E+01 5.63 E+00 Infant 1.93 E-O l 1.41 E-01 4.92E+00 0.00E+00 2.02E-01 1.09E-01 l 7.31E+00 5.63 E+00 Dose factor - airborne release pathway (mrem.Ci released)

Sb-124 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 1.44 E-01 2.73 E-03 1.36E+00 3.50E-04 0.00E +00 1.85 E-01 4.09E+00 4.02 E+00 Teen 2.22 E-O i 4.09E-03 1.39E+00 5.03 E-04 0.00E+00 3.07E-01 4.46E+00 4.02 E+00 Child 5.IIE-Ol 6.63E-03 1.48E+00 1.13 E-03 0.00E+00 3.79E-01 3.19E+00 4.02E+00 l 1nfant 6.72E-02 9.90E-04 1.32E+00 1.78 E-04 0.00E+00 1.20E-01 2.06E-01 4.02E+00 1 -

l l

l 4

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Dose factor - airt,orne release pathway (mre[n/Ci released)

Sb-125 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 1.07E-01 1.20E-03 5.38E+00 1.09E-04 0.00E+00 1.33 E-O l 1.17E+00 9. l l E+00 Teen 1.61 E-01 1.76E-03 5.39E+00 1.54E-04 0.00E+00 2.2 ] E-01 1.24 E+00 9. l l E+00 Child 3.69E-01 2.84E-03 5.43 E+00 3.42E-04 0.00E+00 2.73E-01 8.75E-01 9. l l E+00 Infant 8.33 E-02 8.05 E-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 Thyrt .J l 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. I I E-01 1.84 E-01 8.32E-02 1.43 E-01 0.00E+00 1.59E-02 1.51E400 3.96E-02 Child 1.17E+00 3.16E-01 1.70E-01 3.27E-01 0.00E+00 1.42E-02 1.13 E+00 3.96E-02 Infant 5.10E-02 1.71 E-02 2.18E-02 1.72 E-02 0.00E+00 1.33 E-02 2.46 E-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 4.47 E-06 1.61 E-06 5.15E-06 3.3 ] E-06 1.82E-05 1.93 E-04 2.05 E-03 4.60 E-06 Teen 4.34E-06 1.55 E-06 5.12 E-06 3.00E-06 1.76E-05 3.32E-04 2.73 E-03 4.60E-06 Child 8. I 3 E-06 2.20 E-06 5.93 E. 06 5.63 E-06 2.31 E-05 2.98E-04 1.98 E-03 4.60E-06 Infant I.25E-06 4.25 E-07 4.45 E-06 1.02 E-06 3.03 E-06 3.07E-04 7.48 E-04 4.60E-06 i

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

Te-127m j j Bone Liver T. Body n yroid Kidney Lungs GI-LLI Skin Adult 1.19E+00 4.26E-01 1.54 E-01 3.05E-01 4.84 E+00 2.85 E-02 4.00E +00 6.16 E-02 Teen 1.48E400 5.26E-01 1.85 E-01 3.52E-01 6.01 E+00 4.9 I E-02 3.70E+00 6. I 6E-02 Child 3.32E+00 8.94 E-01 4.03 E-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 7.96 E-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 1.48 E-09 7.10E-10 3.68 E-05 1.16E-09 5.56E-09 5.74E-05 4.65 E-06 4.36E-05 Teen 2. l l E-09 1.00E-09 3.68 E-05 1.54E 09 7.88E-09 9.78 E-05 4.79E-05 4.36E-05 Child 2.90E-09 1.04 E-09 3.68E-05 2.12 E-09 7.62E-09 8.71 E-05 7.56E-04 4.36E-05 Infant 2.34 E-09 1.03 E-09 3.68E-05 2.00E-09 5.19E-09 8.89E-05 7.81 E-04 4.36E-05 Dose factor - airborne release pathway (mrem /Ci released)

Te-129m Bone Liver .. Body Thyroid Kidney Lungs GI-LLI Skin Adult 1.39 E+00 5.19E-01 2.35 E-01 4.78E-01 5.80E+00 3.44 E-02 7.01 E+00 9.07E-01 Teen 1.94 E+00 7.20E-01 3 22E-01 6.26E-01 8.12E+00 5.86E-02 7.30E+00 9.07E-01 Child 4.53 E+00 1.26E+00 7.18 E-01 1.46E+ 00 1.33E+01 5.23E-02 5.53E+00 9.07E-01 Infant 1.39E-01 4.77 E-02 3.66E-02 5.34E-02 3.48E-01 4.98 E-02 8.46E-02 9.07E-01 Page 71 of 138

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l 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 6.14 E-04 5.56E-04 1.21 E-03 6.43 E-03 4.13E-05 2.09E-04 1.63 E-03 Teen 2.52E-03 1.04 E-03 8.80E-04 1.94 E-03 1.10E-02 6.93 E-05 2.07E-04 1.63 E-03 l Child 6.19E-03 1.89E-03 1.93E-03 4.73 F-03 1.87E-02 6.09E-05 3.25E-02 1.63 E-03 l Infant 5.15 E- 10 2.44 E- 10 9.27E-05 4.69 E- 10 1.18E 09 6.llE-05 2.44E-04 1.63 E-03 Dose factor - airborne release pathway (mrem /Ci released) l Te-131m Bone Liver T. Body Thyroid Kidney Lungs GILLI Skin Adult 1.30E-01 6.34 E-02 7.45 E-02 1.00E-01 6.43 E-01 4.32 E-03 6.32E+00 3.77E-02 Teen 2.21 E-01 1.06E-01 1.10E 01 1.60E-01 1.llE+00 7.05E-03 8.53E+00 3.77E-02 l Child 5.38E-01 1.86E-01 2.20E-01 3.83 E-01 1.80E400 6.10E-03 7.56E+00 3.77E-02 Infant 6.34 E-04 2.56E-04 2.18E-02 5.18E-04 1.76E-03 5.90E-03 7.81 E-03 3.77E-02 'j Dose factor - airborne release pathw ay (mrem /Ci released)

Te-132 Bone Liver T. Body 'lhyroid Kidney Lungs GI-LLI Skin Adult 1.92E-01 1.24 E-01 1.27E-01 1.37E-01 1.20E+00 8.55 E-03 5.89E+00 1.32E-02 Teen 3.19E-01 2.02E-01 2.00E-01 2.13E 01 1.94E+00 1.33 E-02 6.42E+00 1.32E-02 Child 7.61E-01 3.37E-01 4. I 7E-01 4.9IE 01 3. I 3 E+00 1. I 2 E-02 3.39E+00 1.32 E-02 Infant 3.94 E-03 1.95E-03 1.17E-02 2.8W-03 1.22E-02 1.0lE-02 8.50E-03 1.32E-02 5

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NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 OFFSITE DOSE CALCULATION MANUAL Table 5.1-2, conL Dose factor - airborne release pathway (mrem /Ci released) 1 13i 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 2.93 E-02 Teen 6.57E-02 9.19E-02 7.35 E-02 2.68E+01 1.58 E-0! 0.00E+00 1.8 ] E-02 2.93E-02 Child 1.44 E-01 1.45 E-01 1.07E-01 4.80E+01 2.38E-01 0.00E+00 1.29E-02 2.93 E-02 Infant 2.04 E-01 2.40E-01 1.30E-01 7.89E+01 2.80E-01 0.00E+00 8.56E-03 2.93 E-02 Dose factor - airborne release pathway (mrem /Ci released) 1-132 Bone Liver T Body Thyroid Kidney Lungs GI-LLI Skin Adult 3.44 E-05 9.67E-05 1.78 E-03 3.40E-03 1.54 E-04 0.00E+00 1.21 E-05 2.06E-03 Teen 4.73 E-05 1.30 E-04 1. DOE-03 4.49E-03 2.05 E-04 0.00E+00 3.78E-05 2.06E-03 Child 6.28E-05 1.21 E-04 I.80E-03 5.74E 03 1.86E-04 0.00E+00 9.50 E-05 2.06E-03 ,

Infant 5.03 E-05 1.05 E-04 1.79E-03 5.03 E-03 1.17E-04 0.00E+00 5.65E-05 2.06E-03 l Dose factor - airborne release pathway (mrent Ci released) l l-133 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 1.46E-03 2.53 E-03 4.21 E-03 3.71 E-01 4.41 E-03 0.00E+00 2.14E-03 4.19E-03 Teen 1.49E-03 2.52E-03 4.21 E-03 3.53 E-01 4.42E-03 0.00E+00 1.75 E-03 4.19E-03 Child 2.87E-03 3.55 E-03 4.78 E-03 6.61 E-01 5.91 E-03 0.00E+00 1.35E-03 4.19E-03 Infant 3.16E-03 4.59E-03 4.79E-03 8.37E-01 5.40E-03 0.00E+00 7.45 E-04 4.19E-03 l

l 1

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i Table 5.1-2, cont.

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

' Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 1.9 l E-05 5.13E-05 6.45 E-04 8.85E-04 8.17E-05 0.00E+00 2.99E-08 7.45 E-04

! . Teen 2.63 E-05 6.88 E-05 6.52E-04 1.17E-03 1.09E-04 0.00E &OO 6.0$E-07 7.45 E-04

( Child 3.48 E-05 6.41 E-05 6.57E-04 1.50E-03 9.79E-05 0.00E+00 2.83E-05 7.45 E-04 l Infant 2.73 E-05 5.57E-05 6.47E-04 1.32E-03 6.19E-05 0.00E+00 3.83 E-05 7.45 E-04 Dose factor - airborne release pathway (mrem /Ci released) 1 135 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 9.31 E-05 2.43 E-04 3.64E-03 1.56E-02 3.87E-04 0.00E+00 1.96E-04 4.14E-03

! Teen 1.22 E-04 3. I 2 E-04 3.66E-03 2.05 E-02 4.92E-04 0.00E+00 2.41 E-04 4. I4 E-03 l

Child 1.69E-04 3.00E-04 3.69E-03 2.72E-02 4.61 E-04 0.00 E+00 1.63 E-04 4.14 E-03 l Infant 1.23 E-04 2.43 E-04 3.64 E-03 2.22E-02 2.70E-04 0.00E+00 6.06E-05 4.14 E-03 l

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

Cs- 134 Bone Liver T. Body Thyroid Kidney Lunt,s GI-LLI Skin Adult 6.68 E+00 1.59E+01 2.26E+01 0.00E+00 5.15 E+ 00 1.71 E +00 2.78 E-01 1.12E+01 Teen 1.06E+01 2.49E+01 2.12 E+01 0.00E+00 7.90E+00 3.02E+00 3.09E-01 1.12 E+0 i Child 2.39E+01 3.93 E+01 1.79E+01 0.00E+00 1.22E+01 4.37E+00 2.12E-01 1.12 E+01 Infant 1.96 E+0 i 3.66E+01 1.33 E+01 0.00E+00 9.42 E+00 3.86 E+00 9.94 E-02 1.12E+01 Page 74 of 138

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OFFSITE DOSE CALCULATION MANUAL Table 5.1-2, cont.

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

Cs-134m Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 8.36E-04 1.76E-03 9.4 l E-04 0.00E+00 9.54 E-34 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 3.24 E-03 0.00E+00 2.58 E-03 4.27E-04 6.18E-03 6.90E-05 Infant 5.48 E-06 8.72E-06 4.70E 05 0.00E+ 00 3.53 E-06 8.31E-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 3.31 E-01 1.3]E+00 1.28 E+00 0.00E+00 7.27E-01 9.97E-02 1.48 E-01 4.73 E-01 Teen 5.12E-01 2.02E+00 1.70E+00 0.00 E+00 1.10E+00 1.73E-01 1.62 E-01 4.73 E-01 Child 1.14E+00 3.14 E+00 2.38 E+00 0.00E+00 1.67E+00 2.49E-01 1.10E-01 4.73 E-01 Infant 3.54E-01 1.04 E+00 7.33 E-01 0.00E+ 00 4.15 E-01 8.48E-02 1.58 E-02 4.73 E-01 Dose factor - airbome release pathway (mrem /Ci released) l Cs- 137 Bone Liver T. Body TinToid Kidney Lungs GI-LLI Skin Adult 9.52E+00 1.30E+01 2.30E+0 ! 0.00E+00 4.42 E+00 1.47E+00 2.52E-01 1.69 E+0 !

Teen 1.57E+01 2.09E+01 2.18 E+0 ! 0.00E+00 7.12E+00 2.77E+00 2.97E-01 1.69E+01 Child 3.73 E+01 3.57E+01 1.97E+01 0.00E+00 1.16E+01 4.18 E+00 2.23 E-01 1.69E+01 Infant 2.99E+01 3.49E+01 1.70E+0 ! 0.00E+00 9.38 E+00 3.80E+00 1.09E-01 1.69E+01 1

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Dose factor airborne release pathway (mrem /Ci released)

Cs-138 Bone Liver T. Body Thyroid Kidney Lungs Gl-LLI Skin Adult 2.17E-03 4.28 E-03 2.70E-03 0.00E+00 3.14 E-03 3.10E-04 1.82E-08 4.39E-03 Teen 3.69E-03 7.08E-03 4.13E-03 0.00E+C0 5.23E 03 6.08E-04 3.2 ] E-06 4.39E-03 Child 8.93 E-03 1.24E 02 8.46E-03 0.00E+00 8.73E-03 9.40E-04 5.71 E-03 4.39E-03 Infant 1.50E-05 2.32E-05 5.97E-04 0.00E4 00 1.22E-05 1.94 E-06 2.60E-05 4.39E-03 Dose factor - airborne release pathway (mrea/Ci released)

Ba139 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 3.78E-03 2.69 E-06 1.38E-04 0.00E+00 2.52E-06 4.62E-05 6.71 E-03 6.76 E-03 Teen- 6.56E-03 4.61 E-06 2.18E-04 0.00E+ 00 4.35 E-06 8.00E-05 5.86E-02 6.76E-03 Child 1.61 E-02 8.60E-06 4.95 E-04 0.00E+00 7.51 E-06 7.37E-05 9.31 E-01 6.76E-03 Infant 1.76E-08 1.17E-I l 2.75 E-05 0.00E+00 7.04 E- 12 7.07E-05 6.06 E-04 6.76 E-03 Dose factor - airborne release pathway (mreme Ci released) l 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 4.67 E-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 2.39 E-01 2.10E-04 4.28 E-02 0.00E+00 6.83E-05 5.18E-02 1.23 E-01 3.29E-02 Infant 4.46E-02 4.46E-05 3.IIE-02 0.00E+00 1.06E-05 4.74E-02 1.17E-02 3.29E-02 l

l Page 76 of138 l

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

Ba14i Bone Liver T. Body Thyroid Kidney Lungs GI-LI I '

Skin Adult 1.83 E-03 1.39E-06 2.01 E-04 0.00E+00 1.29E-06 2.38E-05 8.66E-13 1.55 E-03 Teen 3.16E-03 2.36E-06 2.45 E-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 3.77 E-06 6.03E-05 4.44E-03 1.55E-03 Infant 1.86E-09 1.28E 12 1.39E-04 0.00E+ 00 7.72 E- 13 3.53 E-05 5.64E-05 1.55 E-03 Dose factor - airborne release pathway (mrem /Ci released)

La- 140 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 1.I7E 05 5.91 E-06 2.70E-02 0.00E+00 0.00E+00 4.04E-03 6.96E-02 3.06E-02 Teen 1.57E-05 7.71 E-06 2.70E-02 0.00E+00 0.00E +00 6.36E-03 5.5 l E-02 3.06E-02 Child 2.18E-05 7.60 E-06 2.70E-02 0.00 E+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 0.00 E+00 4.98E-03 5.27E-03 3.06E-02 Dose factor - airborne release pathway (mrem /Ci re! eased)

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

Infant 1.22E-08 4.48 E-09 1.97E-03 0.00E+00 0.00 E+00 9.77E-05 7.07E-04 9.71 E-03 Page 77 of 138 l

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

Ce-141 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 7.38 E-04 5.0lE-04 1.93 E-02 0.00E+00 2.32 E-04 1.07E-02 3.84 E-01 2.16E-02 Teen 1.0$ E-03 7.02E-04 1.93 E-02 0.00E+00 3.29E-04 1.82E-02 4.02E-01 2.16E-02 Child 1.65E-03 8.20E-04 1.93 E-02 0.00E+00 3.59E-04 1.6 I E-02 3.02E-01 2.16E-02 Infant 8.32E-04 5.00E-04 1.92E-02 0.00E+00 1.58E-04 1.53 E-02 3.79E-03 2.16E-02 Dose factor - airborne release pathway (mrem /Ci released)

Ce-143 Bone Liver T. Body 1hyroid Kidney Lungs GI-LLI Skin 4.80E-02 4.80E-03 0.00E+00 2.18E-05 9.48 E-04 1.80E+00 6.60E-02 Adult 6.71 E-05 8.10E-02 4.8 t E-03 0.00E+00 3.74E-05 1.55E-03 2.44E+00 6.60E-02 Teen 1.15 E-04 Child 2.77E-04 1.48E-01 4.82E-03 0.00 E+00 6.31 E-05 1.37E-03 2.17E+00 6.60E-02 3.55 E-06 5.06E-05 4.80E-03 0.00 E+00 6.85E-07 1.38E-03 8.73E-04 6.60E-02 Infant Dose factor - airborne release pathway (mrem /Ci released)

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

4 I

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

Pr-143 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 5.IIE-04 2.05 E-04 2.53 E-05 0.00 E+00 1.18 E-04 3.34E-03 1.75E+00 3.77E-01

. Teen 8.14E-04 3.25 E-04 4.05 E-05 0.00E+00 1.89E-04 5.74E-03 2.16E+00 3.77E-01 Child 1.82E-03 5.46 E-04 9.02E-05 0.00E400 2.96E-04 5.15E-03 1.73E+00 3.77E-01 Infant 1.67E 04 6.23 E-05 8.32E-06 0.00E+00 2.35 E-05 5.14E-03 5.83 E-04 3.77E-01 Dose factor airborne release pathway (mrem /Ci released)14-144 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 8.93 E- 10 3.70E 10 2.58E-06 0.00E +00 2.09E- 10 3.01 E-05 6.39E-16 2.96E-06 Teen 1.27E-09 5.22 E- 10 2.5 8 E-06 0.00E+00 2.99E-10 5 20E-05 6.98 E- 12 2.96E-06 Child 1.77 E-09 5.48 E- 10 2.5SE-06 0.00E+ 00 2.90E 10 4.64 E-05 5.84E-06 2.96E-06 Infant 1.42 E-09 5.4 8 E- 10 2.58 E-06 0.00E+00 1.99E 10 4.78E-05 ( 1.27E-04 2.96E-06 I

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

Nd-l47 Bone Liver T. Body ~Ihyroid Kidney Lungs GI-LLI Skin Adult 8.95 E-05 1.03 E-04 2.00E-02 0.00E+00 6.04 E-05 2.62E-03 1.51 E-01 2.00E-01 Teen 1.22 E-04 1.33 E-04 2.00E 02 0.00E+ 00 7.80E-05 4.42 E-03 1.15 E-01 2.00E-01 Child 1.85 E-04 1.49E-04 2.00E-02 0.00E+00 8.22E-05 3.90E-03 7.33 E-02 2.00E-01 Infant 9.45 E-05 9.69E-05 2.00E-02 0.00E+00 3.75E-05 3.83 E-03 4.73 E-04 2.00E-01 Page 79 of 138

NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 OFFSITE DOSE CALCULATION MANUAL Table 5.1-2, cont.

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

Eu-152 Bone Liver T. Body Thyroid Kidney Lungs- GI-LLI Skin Adult 3.32 E-02 2.45 E-01 3.62E+ 0 ! 0.00E+00 4.67E-02 3.26E-02 1.38 E+00 6.86E+01 Teen 4.20E-02 1.02 E-02 3.62E+01 0.00E+00 4.73 E-02 4.76E-02 1.23 E+00 6.86E+01 Child 6.02 E-02 1.10E-02 3.62E+01 0.00E+00 4.64 E-02 3.96E-02 8.25E-01 6.86E+01 Infant 1.30E-02 2.95 E-03 3.62E+ 01 0.00E+00 9.90E-03 2.46E-02 5.31 E-04 6.86E+0!

Dose factor airborne release pathway (mrem /Ci released)

W.187 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 4.08 E-03 3.4 ] E-03 7.22E-03 0.00E+00 0.00E+00 3.45 E-04 1.12 E+00 2.79E-02 Teen 6.98 E-03 5.69E-03 8.03 E-03 0.00 E+00 0.00E+00 5.63 E-04 1.54 E+00 2.79E-02 Child 1.69E-02 1.00E-02 1.05E-02 0.00E+00 0.00E+00 4.88E-04 1.41 E+00 2.79E 02 Infant 1.13 E-05 7.88 E-06 6.04 E-03 0.00E+00 0.00E+00 4.71 E-04 8.79E-04 2.79E-02 Dose factor - airborne release pathway (mrem " released)

U-235 Bone Liver T. Body Thyroid Kidney Lungs GILLI Skin Adult 4.06 E+0 ! 0.00E+00 1.04 E+01 0.00E+00 9.47E+00 4.66E+00 3.87E+00 1.06E+01 Teen 6.45 E+01 0.00E+00 1.19E+01 0.00E+00 1.51 E+01 8.03 E+00 4.59E+00 1.06E+01 Child 1.54 E+ 02 0.00E+00 1.73 E+01 0.00E+00 2.53 E+01 7.17E+00 3.58E+00 1.06E+01 Infant 1.17E + 01 0.00E+00 8.84E+00 0.00E+00 2.49E+00 5.46E+00 1.90E-01 1.06E+01 j t

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NUCLEAR POWER BUSINESS UNIT ODC:.1 OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 OFFSITE DOSE CALCULATION MANUAL Table 5.1-2, cont.

l Dose factor - airborne release pathway (mrem /Ci released) l U-238 Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin 4

Adult 3.88E+0! 0.00E+00 2.33 E+00 0.00E+00 8.86E+00 4.36E+00 2.72E+ 00 2.47E-01 Teen - 6.17E+ 0! 0.00E+00 3.70E+00 0.00E+00 l

1.41 E+01 7.50E+00 3.23 E+00 2.47E-01 Child 1.48E+02 0.00E+00 8.79E +00 0.00E+00 2.37E+01 6.73E+00

]

2.53 E+00 2.47E-01 j infant 1.12E+01 0.00E+00 8.63 E-01 0.00E+00 2.33 E+00 5.09E+00 1.34 E-01 2.47E-01 Dose factor - airbome 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 2.60E-05 7.71 E-04 1.27E400 9.52 E-03 Child 2.1IE-04 1.52 E-05 5.55 E-03 0.00E+00 4.39E-05 6.91 E-04 1.10E+00 9.52 E-03 i Infant 4.42E-06 3.95 E-07 5.54 E-03 0.00E+00 7.88 E-07 7.07E-04 3.14 E-04 9.52 E-03 j Dose factor - airborne release pathway (mrem /Ci released)

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

Teen 1.46 E+02 5.59E+0 ! 1.llE+01 0.00E+ 00 7.3 ] E+01 9.99E+00 4.12E+00 2.94 E+00 j Child 1.37E+02 6.14 E+01 1.llE+0i 0.00E+00 5.98E+01 8.83E+00 3.22E+00 2.94 E+00 1 Infant 3.07E+01 1.41 E+01 3.56E+00 0.00E+00 1.32 E+01 6.76E+00 2.58E-03 2.94 E+00 Page 81 of 138

NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 OFFSITE DOSE CALCULATION MANUAL 5.1.3 Atmospheric Rele,'e Mode: Noble Gases The dose calculations for demonstration of compliance with the 10 CFR 50, Appendix I dose limits for noble gases released to the atmosphere will be done in the manner similar to the liquid release dose 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 = I Dose,; = I( TDF; x C i) s K mrem where API = the Appendix I dose for compliance evaluation in mrem Dose t; = the dose to the applicable target (t) from radionuclide (i)

TDF ri = total dose factor from Table 5.1-3 in mrem /Ci for the specific target (t) from radionuclide (i) based on the maximum annual average 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.

l Instead of using the precalculated total dose factors, the Appendix 1 dose calculation may be modified to reflect actual X/Q values during the release <

using the methodology of Appendix C. l Page 82 of138

NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 OFFSITE DOSE CALCULATION MANUAL TABLE 5.1-3 ACTIVITY TO DOSE CONVERSION FACTORS FOR NOBLE GASES (Highest Annual Average x/Q)

Nuclide Beta Air Gamma Air Skin Whole Body (mrad /Ci) (mrad /Ci) (mrem /Ci) (mrem /Ci)

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

NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 i OFFSITE DOSE CALCULATION MANUAL

)

6.0 RADIOLOCICAL 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.

7.0 RADIOLOGICAL IMPACT EVALUATION OF SEWAGE TREATMENT SLUDGE DISPOSAL l 1

The methodology for determining the radiological impact of contaminated sewage treatment sludge is presented in this section. The evaluation must be made prior to every land application of sewage treatment plant (STP) sludge that contains licensed material. Sludge and other STP material which does not contain licensed matorials may be disposed of by any legal method without l'rior radiological analysis.

7.1 Basis. Commitments, and Actions 7.1.1 Basis With the discovery that the PBNP STP sludge contained licensed material, Wisconsin Electric applied for NRC approval to dispose of the sludge by land application on land within the PBNP site boundary pursuant to 10 CFR 20.302(a). Wisconsin Electric committed to gamma isotopic analysis (GIA) of the sludge to measure the concentrations oflicensed material in the STP sludge and to compare the results to concentration limits prior to each disposal [ letter dated October 8,1987 (VPNPD-87-430, NRC-87-104)]. In addition, the dose to the maximally exposed individual of the general public and to the inadvertent intruder would be evaluated for the appropriate exposure pathways.

7.1.2 Basis for NRC Commitment Modification Pursuant to NRC guidance, 'he sludge is clean if no licensed materials are found when analyzed under conditions necessary to achieve the environmental LLDs (NRC HPPOS 221). Clean sludge is not under NRCjurisdiction and may be disposed of by any legal method without prior radioanalyses.

Therefore, if the sludge is clean and there is no pathway to the STP from the RCA, or pathways are administratively controlled to prevent the transfer of licensed materials to the STP, there is no need to analyze the sludge prior to 4 any disposal.

Page 84 of 138

NUCLEAR POWER BUSINESS UNIT ODC'1 OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 OFFSITE DOSE CALCULATION MANUAL Since the 1987 commitment, engineering modifications and administrative controls have eliminated the pathways from the RCA to the STP. Three subsequent sludge GIAs (a total of eight STP samples) utilizing the analytical parameters required to achieve environrnental lower limit of detection (LLD) found only naturally occurring radionuclides. In each analysis, the licensed materials were below the minimum detectable activity for the particular measurement and below the required LLDs. These results verify the efficiency of the modifications and administrative controls in eliminating pathways from the RCA to the STP. Therefore, because there is no longer any reason to believe that the PBNP STP sewage contains licensed material and there are no pathways from the RCA to the STP, the sewage may be disposed of by any legal method without GIA prior to each disposal.

7.1.3 Modification Periodic gamma isotopic analyses (GIA) of the STP sludge shall occur at a frequency set forth in the Environmental Standing Orders (ESO). This may include analyses prior to disposal depending on the results from the periodic analyses. The GIA of the STP sludge shall meet the LLD criteria of normal liquid effluents. The detection of any licensed material in the sludge during the periodic GIA shall necessitate retuming to the GIA prior to disposal in order to evaluate the radiological consequences of the disposal. The GIA prior to each disposal shall continue until such time that the sludge can be shown, using environmental LLD cri'eria,t not to contain licensed material.

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

7.1 A Exposure Evaluations If the sludge contains licensed material, the 1987 commitment requires that the appropriate exposure pathways be evaluated prior to each application of sludge to insure that the dose to the maximally exposed member of the general public is maintained at less than 1 mrem / year and that to the inadvertent intruder, at less than 5 mrem / year. Also, the measured concentration shall be compared to the liquid ; maximum efiluent concentrations of Appendix B to 10 CFR 20.

Page 85 of 138

I ODCM j NUCLEAR POWER BUSINESS UNIT /

Revision 10 OFFSITE DOSE CALCULATION MANUAL April 3,1997 OFFSITE DOSE CALCULATION MANUAL The exposure pathways evaluated for the maximally exposed individual are the.

following:

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

i

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

l

3. Meat ingestion pathwa,3 from cows fed alfalfa grown on plot.

4. Vegetable ingestion pathway from vegetables grown on plot.

)

l l

5. Inhalation of radioactivity resuspended in air above plot.

6. Pathways associated with a relcase to Lake Michigan. These pathways are ingestion of potable water at the Two Rivers, Wisconsin municipal water supply, ingestion of fish from edge ofinitial mixing zone of radionuclide release, ingestion of fresh and stored vegetables irrigated with water from Lake Michigan,

! ingestion of milk and meat from cows utilizing Lake Michigan as drinking water source, swimming and boating activities at the edge of the initial mixing zone, and I

shoreline deposits.

The exposure pathways evaluated for the inadvertent intruder are the same as items I,4,

! 5, and 6 identified above for the maximally exposed individual.

7.2 Procedure The following steps are to be performed by the responsible Radiological Engineer for each contaminated sewage treatment sludge disposal:

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

l 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 enteria are contained in Appendix E.

Page 86 of 138

NUCLEAR POWER BUSINESS UNIT ODCM l OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 OFFSITE DOSE CALCULATION MANUAL 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 ofin 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.

Wisconsin Electric utilizes QAD, a nationally recognized computer code, to perform shielding and dose rate analyses. QAD will be used to calculate the dose rate due to standing on a plot ofland utilized for sludge disposal in which the radionuclides from prior disposals have been incorporated into the plot by

! plowing. This calculated dose rate will be used to assess the radiological consequences from prior disposals with the consequences of proposed future disposals. The total radiological dose consequence of the past and the proposed disposal will be compared to the applicable limits to insure the dose is maintained at or below the limits.

The methodology for calculating the radiological impact of the sewage f treatment sludge disposal is contained in Appendix E.

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

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

l l

l 7.3 Admin. strative Reauirements l 7.3.1 Complete records of each contaminated disposal shall be kept as follows:

l

a. Radionuclide concentration of the sludge.

l

b. Total volume of sludge disposed.

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

d. Dose calculation results. l l

e. Results of annual chemical composition determination.

Page 87 of 138 L

NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 OFFSITE DOSE CALCULATION MANUAL 7.3.2 Modifications to the October 8,1987, NRC submittal

a. Modification 1 - Appendix F I

1 Section 3.2 of Attachment II of the submittal states that physical and chemical properties of the sludge would be determined prior the each land I application. Pursuant to a change in the PBNP WPDES Permit, i

non-radiological properties are now determined annually instead of per application. The frequency for radiological characterization did not change.

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

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

c. Modification 3 - Appendix H in Section 3.2 of Attachment II of NRC submittal letter dated October 8,1987, Wisconsin Electric committed to gamma isotopic analysis (GIA) to determine the concentration oflicensed material in sewage treatment plant (STP) sludge prior to each disposal. Pursuant to NRC HPPOS-221 guidance, the sludge has been shown to be clean on three different occasions after pathways from the RCA to the STP were eliminated by plant modifications and administrative controls. Pursuant to HPPOS, the sludge analyses were done under the conditions necessary to achieve the environmental LLDs. Only naturally occurring radionuclides were found and licensed material was below the minimum detectable concentration. This indicates that the fomier pathways from the RCA to the STP had been eliminated. Therefore, there is not need to continue the analyses because there is no RCA to STP pathway and there is no reason ,

to believe that the sewage contains licensed material. Hence, the commitment to analyze STP sludge prior to every disposal is modified and replaced with periodic analyses at a frequency set by ESO-104. However, if plant conditions change in a manner which places the STP sewage outside the guidance parameters which allowed for the discontinuance of ,

analyses, the sewage must be analyzed prior to each disposal until it again is shown not to contain licensed material.

Page 88 of 138

NUCLEAR POWER BUSINESS UNIT ODCM OFFS!TE DOSE CALC:JLATION MANUAL Revision 10 OFFSITE DOSE CALCULATION MANUAL APPENDIX A DERIVATION OF LIQUID RELEASE PATilWAY EFFECTIVE MAXIMUM EFFLUENT CONCENTRATION I

l l

I l

l l

Page 89 of 138

I NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 OFFSITE DOSE CALCULATION MANUAL ,

l A.I.0 Derivation of Liquid Release Effective Maximum Effluent Concentration A.l.1 Source Term i

The effective maximum effluent concentration is calculated from the annual l

releases via liquids for the years 1985-1991 (Table A-1). Although Na-24 was i discharged in 1985, it was excluded from the isotopic mixture because it is not a radionuclide which would be normally found in PBNP effluent. Na-24 appears in the effluent because it was used for tests run on the steam system.

Tritium also was omitted from the initial calculation because its production is largely independent from the appearance of the fission products in the effluent.

A.I.2 Effective Maximum Eftluent Concentration The efTective maximum effluent concentration (EMEC) was calculated using the formula given in Section 3.6 EMEC = IC; / I(C /MEC;)

i or IC;

1/SOF where:

SOF = I C;/MEC is i the summation of fractions for the annual effluent isotopic release Ci =

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

MEC i =

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

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

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

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

Page 90 of 138

NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 i OFFSITE DOSE CALCULATION MANUAL i l

The EMEC becomes EMEC = 0.70

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

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

and Cs-137 (lE-06).

l By restricting the non tritium radionuclides to 70% of their calculated EMEC, l

the II-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 efIluent isotopic mixture.

i

\

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Page 91 of 138

ODCM NUCLEAR POWER BUSINESS UNIT Revision 10 OFFSITE DOSE CALCULATION MANUAL April 3,1997 OFFSITE DOSE CALCULATION MANUAL TABLE A 1 CURIES RELEASED IN LIQUIDS LIQUID RELEASES 1989 1990 1991 1986 1987 1988 NUCLlDE MEC 1985 uCi/cc 7.09 E+02 3 57E+02 5 59E+02 8. 72 E+02 7.87 E +02 11-3 1.00E-03 8.0$E+02 8. l l L+02 3.74E-02 1.W E-02 1.40E-03 1.77E-03 ! l.53E-04 1.83E-03 11J1 1.00E-06 1.02E-01 5 82E-02 103 E-03 8.15E44 4.45E-05 9.41 E-03 1132 1.00 E-04 6.15E-02 7.25E 02 l.27E-01 1.49E-Oi 1.04L-01 1.21E 02 8.llE-03 3 0!E-03 1.01 E-02 1 133 7.00E-06 4.39E-02 3.97E-02 2.29E-04 6.83E44 1 134 4.00E-04 3.181i-02 1.34E-01 1.23E 01 4 48E-A 8.21E-04 1135 3 006-05 1.04 E-O L 3.09E-03 9 85E-04 4.70E-04 1.71E-04 4.06E-04 AO-110M 6 00E-06 2.55E-05 2.84EM UA 133 2.00E-05 8.63 E-06 2.47 E-04 11A 139 2.00E-04 8 00E 06 6.90E-06 4ASE-05 6.13E-05 UA 146 C D-109 6 00E-06 6.33E-05 f.3fE-04 CE-139 7.00E-05 EL141 3 00E 05 1.3 t E 03 7.50L-04 2.08E-03 4.76E-04 1.59E-04 9.4 7E-06 9 64E-06 CE-144 3 00E-06 1.37 E-03 CO-56 6 00E-06 3 21E 04 5.07E-05 6 90E-07 4.08 E-06 C0-57 6 00E-05 2.52E 03 1.33 E-04 3.36E-02 6 81E-03 3.12E-03 3.25 E-04 2.93 E-03 C 0-58 2.00E-05 4.05L-01 9 02E-03 6.34L-02 2.04E-02 1.54E 02 1.41 E-03 5.53 E-03 L O-t>0 3 00E-06 2.88E 01 2.85 E-02 3.16E-04 1.58E-02 5.31 E-05 4.44E 04 8.7 t E-05 CR 51 5 00E-04 2.71 E-02 1.18L-03 4 96E-04 1.49E-03 CS-134 9 00E-07 4.76E-02 6 92 E-03 3.59E-04 5.97E 06 4 670-04 CS 134NI 2 00E-03 CS 136 6 00L 06 8 63E-d3 2.80E-03 1.94 E-03 8 93 E-63 CS 137 1.00E 06 9.60E 02 2.llL-02 7.54E-03 CS 138 4 00E 04 1.1 I E-03 5 43E-03 3 24D03 1.67 E-02 7.56L 04 166L-03 2.26 E-03 4 06E-04 l l8 7 00E 04 100E 02 i E 59 1.00L-05 2.76E-04 LA l40 9 00E-06 4 68L-03 154E-04 2.68E44 3.10E 05 1.96E-04 MN54 3 00E-05 7.46E-03 1.18 E-03 2 00E-03 3.70E-05 M0-99 6 65L44 3.2 i E-03 1.6tE-04 2 33E-06 8 68E 05 NH 95 3 00E-05 6 28E-03 6.16E-05 1.06E-05 3.90E-06 8 80E 06 5.30E-06 N B-9 7 3 00E-04 1.3 5 E-03 5 22E-04 4 00L44 8 46E 05 1.1 I E-02 3.33 E-03 RB 88 RD 89 9 00E 04 7.98E-04 2.34E-04 3.59E-03 1.68E-06 8 41E-04 5 86E-05 RU103 3 00E-05 8 07E-04 2.88L-03 7.33L-03 1.04 E-04 RU 106 3 00E-06 3 86E-02 2 96E-04 1.42E44 2.34E 04 Sil l24 7 00L-06 1.95E-03 100E-03 2.12 E-02 1.28E-05 1.08 E-02 S0 125 3 00E-05 1.12E-02 L .20E-03 5.13 L44 3.21 E-04 3.07E-06 SN ll) 3 00E-05 1.07E-03 4.20E-05 3.46E-05 3 89E-03 2.68E-03 8 69F 06 SR 89 8 00E 06 2.27E 04 2.28E44 2.80E-04 3.50E-04 2.55E 04 S R-90 5 00E-07 1.29E-03 1.75 E-05 3.75E-06 3 30E-05 1 C-99M 1.00E-03 TC 101 2.00E-03 1.10E-05 7.98E-05 TE131 8.00E-05 7.19E-06 1.74 E-04 IE 132 9 00E 06 5 83E 07 6 94E 05 2.74E-05 3 4 t E-05 W 187 3.00E-05 Y-9 t M 2.00E-03 IN-65 5 00E 06 5.15E-05 7.95E-05 2.61 E-04 2.45E-03 1.58E-05 IR 95 2.00E-05 9 00E-06 1.49E-06 3 09E-06 1.74E-05 2R-97

7. L OE +02 3.5 7 E +02 5 59E+02 8.72E+02 7.87E+02 l'O l' AL Cl 8 06L+02 8.12 E+02 5.12E-01 5 99E-02 5 65E 02 9 57E-03 5 42E 02

'lOl'AL W/O H-3 1.37E+00 5.39E 01 Page 92 of 138

NUCLEAR POWER BUSINESS UNIT ODCM l

( OFFSITE DOSE CALCULATION MANUAL Revision 10 c

April 3,1997 OFFSITE DOSE CALCULATION MANUAL TAllLE A-2 FRACTIONAL MEC IN LIQUID EFFLUENT i

l NUCLIDE MEC 1985 1986 1987 1988 1989 1990 1991 uCi/cc 14-3 100E-03 1.27E-03 1.25E-03 1.04 E-03 5.17E-04 8.36E-04 1.26E-03 1.22E 03 1 131 1.00E 06 1.61 E-04 5.75E-05 1.52E 05 2 03E-06 2.65L-06 2.2iE 07 2.84E-06 1-132 1.00E-04 9.70E-07 1.12E-06 8.53E-07 1.49L-08 1.22E 08 6.43E-10 1.46L-07 l 133 7.00E 06 2.86E 05 3.27E-05 2.18L-05 2.51 E-06 1.73 E-06 a.21 E-07 2.24E-06 l 134 4 00E 04 1.2S E-07 1.69E-07 1.46E-07 8.30E 10 2.65 E-09 l 135 3 00E-05 5.47E 06 6 87E-06 6 0l E-06 2.16L-08 4.24 E-08 AG-!!OM 6.00E-06 6.70E-09 7.28E 08 7.55E-07 2.38E-07 1.17 E-07 4.12L-08 1.0$ E-07 11A-133 2.00E 05 llA 139 2.00E 04 6.33E Il I.79E-09 ,

!!A 140 8 00E-06 1.36E-09 0.00E+00 8.16E-09 1. l l E-08 C D-109 6 00E-06 1.62E-08 316L-08 CL.I39 7 00L-05 CE-141 3.00E-05 6.89E 08 3 67E-s8 C E 144 3 00E-06 7 03L 07 102E-06 2.30E-07 7.92E 08 4 56E-09 4 98L-09 CO-56 6 00E 06 j CO-57 6 00L-05 6 62L 08 7 84E49 1.72L-i l 9 83L-i l 3 4 t E-09 1.22 E-09 CO 58 2.00E-05 3.19E-05 6.94 L-07 2.46E-06 4 93E-07 2.33E-07 2.3 5 E-08 2 27E-07 C060 3 00E-06 1.51 E-04 1.46 E-05 310E-05 9 86L-06 7.67 E-06 6. 79E-0 7 2.86E-06 CR 51 5 00E-04 8 55E-08 9 72E 10 4 63E-08 1.54L 10 1.33 E-09 2.52E 19 C5 134 9 00E-07 8 34E 0$ l .18 L-05 192E-06 7 99E 07 2.57L-06 CS-134M 2 00E-03 2 60E 10 4 46E 12 3.62L 10 CS 136 6 00E-06 CS 137 100E-06 1.5 l E 04 3 25E 05 1.11 L-05 1.25 E-US 4,19L-06 2.80E-06 1.38 L-05 CS-138 4 00L48 .. 5 8 L-09 2.llL 08 1.19E-08 bl8 7 00E-04 2.20E-08 3 50L-08 1.57 E-09 3 54L-09 4.67E-09 8 99E-10 FE 59 1.00E-05 4 0$E-08 LA-140 9 00E-06 MN54 3 00E-05 3.92L 07 6 05L-08 2 2VE 07 7.44E-09 1.34E-08 l .49L-01 1.01 E-08 M O-99 2 00L 05 2 68E-09 N D-95 3 00E-05 3.30E-07 3 41E-08 1.5 7 L-07 7.7d L-09 1.16E 10 4.18L-09 NL197 3 00L 04 7.10E-09 2.68E-09 3.0!E 10 5 12L ll 1.94 L-i l 4 24L il 2.74 E-l l Ril-88 4 00E-N 3.34 E-10 4 27E-08 122E-08 R1189 9 00E-04 1.36L-09 3 81E-10 RU-103 3 00E-05 189E-07 8 62E Il 4 Ill-08 2 83E-09 RU-106 3 00E-06 4 24E-07 1.48E-06 3.58E-06 5 02E-08 Sll124 7 00E-06 8.70E 06 6.S t E-08 2.97E 08 4 84E-08 S11 125 3 00L-05 5 89E 07 6.15E-08 9.53 E-08 4 83E 08 l .06E-06 6.17 E-10 5 58E-07 SN il) 3 00E-05 5 63E-08 2.15E-09 2.51 E-08 1.5 5 E-08 1.59L 10 l SR 89 8 00E-06 4.48E-08 6 65L-09 7.13E-07 4 86E 07 1.62E-09 SR-90 5 00E-07 4.07E 06 7.02 E-07 8.21 E-07 1.0lE-06 7 62E-07 i TC 99M 1.00E-03 2.76E Il 5.77E 12 4.78 E-I l

'lC-101 2 00E 03 8.06E 12 1E 131 8 00E-05 1.45 E-09 ,

IE 132 9 00E 06 l.02 E-10 1.19E-08 4.46E-09 1.16E-09 3 00E-08 W-187 3.00E 05 1.65 E-09 Y-91M 2.00E-03 IN-65 5.00E-06 1.5lE-08

/R-95 2.00E-05 6.27E-09 2.0! E-08 i 80E-07 1.14 E-09 l ZR 97 9 00E-06 2 61E-10 5.28E 10 2 80L-09 Page 93 of 138

NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 OFFSITE DOSE CALCULATION MANUAL TABLE A 2,(cont) f RACTIONAL MEC IN LIQUID EFFLUENT 1985 1986 1987 1988 1989 1990 1991 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 LOT f RACTION 1.90E 03 141 E-03 8.14 E-03 5 48E-04 8.54E-04 1.26E-03 1.25E-03 FRACT W/Oli 3 i 6 29E44 1.61E 04 9 83E 05 3 64E-05 1.85E-05 i 4 41E 06 2.55E45 101 AL Cl 8 06E+02 8.12E+02 ' 7.10E+0' 3 57E+02 '559E+02 8.72E+02 Ii.87E+02

'lOTAL W/O ll 3 1.37E+00 $ 39E-01 5.12E-01 5 99E-02 5.65E 02 9 57E-03 5.42E-02 IOl' CONC (uCvCC) ' l.27E-06 ' l.25E-06 1.04E-06 517E-07 8.36E 07 1.26E-06 1.22E-06 TCON W/O11-3 216E 09 8.30E-10 7.51E-10 869E-Il 844E-Il 1.38E il 8 40E-11

~

EMEC 6. 70E-04 8.86E-04 9.14E-04 9 45E-04 9.78E 04 9.97E-04 9 80E-04 EMLC W/O ll-3 3.43E-Of 5.14E-06 7.64 E-06 2.85E-06 4.56E-06 3.14E-06 3.30E-06 Page 94 of 138

i NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 OFFSffE DOSE CALCULATION MANUAL l

l APP"NDIX B l

DERIVATION OF ATMOSPHERIC RELEASE MODE EFFECTIVE MAXIMUM EFFLUENT CONCENTRATION l

Page 95 of 138

NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 OFFSITE DOSE CALCULATION MANUAL i

B.I.0 Derivation of Atmospheric Release Effective Maximum Effluent Concentration Bl.1 Source Term The effective maximum effluent concentration (EMEC) for atmospheric effluents is calculated from the annual releases for the years 1985-1991 (Table B-1). Unlike liquid releases, tritium was not omitted from the EMEC calculation. Instead, the EMEC was calculated with H-3 and then modified by the fraction of non-tritium radionuclides in the effluent.

Bl.2 Effective Maximum Effluent Concentration The maximum concentration of a radionuclide mixture that is allowable at the site boundary is called the effective maximum efiluent concentration (EMEC).

The EMEC for an efiluent mixture is defined by the equation EMEC = IC i / E(C; / MEC;)

where Cj = concentration of radionuclide "i" MECi

= maximum effluent concentration for radionuclide "i" from 10 CFR 20, Appendix B. Table 2, Column 1 I(C i/ MEC;) = 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 3

average x/Q of 1.56E-06 sec/m Then the total EMEC was calculated for each year (Table C-2). The average tota! CMEC is 8.04E-08tl.31E-08 Ci/cc with a range of 5.84E-08 to 9.50E-08 Ci/cc. Next, the annual EMEC was modified for the presence of H-3, which is not detected by the atmospheric RMS, by multiplying each EMEC by the ratio of the non H-3 concentration to the total concentration. The annual H-3 corrected EMECs were averaged to obtain a value of 1.92E-0821.23E-08 pCi/cc with a range of 5.02E-09 to -

3.70E-08 Ci/cc.

Page 96 of 138

NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 I OFFSITE DOSE CALCULATION MANUAL l 4

TAllEE 11 1 CURIES IN ATMOSPilERIC EFFLUENT NUCLIDE MEC 1985 1986 1987 1988 1989 1990 1991 uCi/mi 11 3 100E 07 : 6 7tE+0! l.20E+02 il8E+02 1.26E+02 1.42E+02 1.28E+02 113L+02 j l

AR 41 1.00E-08 lf.17L+00 6 81E-01 2.17E+00 196L+00 1.57t+00 1. l l E+00 1.07E +00 KR 85M l .00E-07 El84E+0! 6 77E-01 1.18E +00 7.31 E-01 2.24 E-01 115E-01 1.03E-01 ,

KR 85 7.00E-07 167t+0! l.32E+00 7. l l E-01 9 84E Oi 3.58E-01 1.78E-01 2.74E-01 )

K R-87 2.00E-08 4. 78E+00 1.UIE+00 2J 7E+00 1.48E+00 4 94E 01 4 0$E-01 2.3 t h-01 I KR-88 9 00li-09 5.73 E +00 IJOL+00 2.72E+00 1.69E+00 5 64E-01 4.49E-01 2.56E-01 l XL 131M 2.00E-06 8 54E-02 XL 133M 6 00E-07 3 30E-01 1.3 8E-Ul 2.12E 01 3 3$E-01 4 94L-03 2 06E-02 3 97L-02 XE 133 5.00E-07 3.4 5 E+01 1.53t+01 2.06L+01 6 04E+01 7.54E+00 1.96E+00 1.60E +01 XL 135M 4 00E-08 5. 76E +00 1.27E+00 3 68E+00 2.54 E+00 7.37E-01 6 49E-U l 3.44 E-01 XE 135 7.00E-08 119L+0! 3.21 E +00 5 64L+00 3 53E+00 108E+00 1.09E+00 6 03E-01 XE 138 2.00E-08 1.65E+0i 2 91L+00 8 87L+00 7.19E+00 2 45L+00 1.vvE+00 1.06L+00 i

AG-i l0M l .00E-10 2 3 l E-07 l IIA-133 9.00E 10 LIA 139 4 00E-08 1.172-07 IIA 140 2.0'0E-09 3 41E 07 CD-109 2.00E 10 8 92E 06 1.26L-06 2.28L-04 CE 139 9 00E 10

~

CE-141 8 00E 10 8 481:-09 Li-144 .?. 00L 11 2.04 E-06 3 92E-07 3 44L-09 C 0-57 9 001.10 2.10E-0 7 2 52E Il 1.13E-08 1.23E-06 4 80L-07 CO-58 100L 09 1.57E-04 1.33 E-05 i Olt-04 3 $9E US 1.69E-04 2.74E-05 3 85E-06 C0-60 5 00E Il 7.94 L-05 l lil-N 1.18 E-05 3 64E-04 1.63E-04 3.56L-06 l ueE-04 )

CR Si 3 00E 08 5.28E-04 7.58E-09 I E S-134 2.00L-10 1.18E-03 9.49E-04 5.86E-05 7.27E-05 1.10E-03 j CS 136 9 00E 10 I CS-137 2 00E 10 4 02L-0) 2.9 L-04 3.08E 04 6 74E-04 2.10L-03 1,911d-04 1.90E-03 C56 38 8 00E-08 9 64L 07 1 92L 06 1.85 E-03 1.26E-0 7 3 44E-06 1.92L-02 i l I8 100E 07 108E-05 2.52E 04 3 37E-05 3.31 E-04 1.10E-05 6 60E-04 j l E 59 7.00E 10 4.67E-09 MN-54 1.001-09 l 99E-06 1.70E-06 4 86E-05 MD 99 2 00E-09 7.27E-09 2.71E-08 NA 24 7 00E-09 1.39E-04 4 32E46 4 29li-04 Nil 95 2.00E 09 2 52E-06 7.70E-07 5.97E-07 6.25 E-08 9.56E-10 Nil-97 100E-07 160E-08 1.65E-09 Ril.88 9 00E-08 4 63E-05 3.46L-05 1.03 E-02 4 00E-06 1.81 E-05 1.62E-01 Ril-89 2.00E-07 4.30E-09 RU103 9 00E-40 19 t E-08 1.89E-05 Sil l25 7.00E-10 1.2SE-07 3.68E-06 9 39E-08 SN-il3 8 00E 10 2.16E-08 4 80E-l0 SR-89 2.00E-10 4.87 E-08 1.54 E-06 7.70E-07 3.7 t E-06 SR-90 6.00E-12 1.68E-10 4.30E-06 SR-91 5.00E-09 1C-99M J.00E-07 6 43E-08 2.20E 07 9.24E-07 IC-101 5 00E-07 TE-132 9 00E 10 3.07E 06 7.33 E-08 2.34 E-06 Y-88 3 00E 10 1.28E 10 ZN-65 4 00E-10 9,27 E-06

/R-95 4 00E-10 IJ1E-06 3.56E-09 7.43E-10

/R 97 2.00E-09 2.97E 10 Page 97 of 138

NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATDN MANUAL Revision 10 April 3,1997 OFFSITE DOSE CALCULATION MANUAL TABLE D 1,(cont )

CURIES IN ATMOSPHERIC EFFLUENT 1986 1987 i968 1989 1990 1991 NUCLlDE M t.C 1985 uCi/mi

1. l i t-03 3 08L-03 5 43E4)4 3,18E-04 7.8 5 E-05 3.46E-04 1 131 2 00L 10 3 44E-03 3.75 L-03 1.79L-03 2 42L-03 4 78E-04 4.20E 05 1.09E-05 2.95E-05 l 132 2.00L-08 1.3 7 L-03 6 80L 04 3 04F-03 1.53 E-03 1.19L-03 1.13L44 1.13 E-04 l 133 1 00E-09 1-134 6 00L-08 1.33 L-05 9.320 04 1.09F-04 2 lvt-0) 918 L-05 1.26E 05 3.15E-08 1.58L-05 1 135 6 00L-09 5. 79E-04 Page 98 of 138

NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 OFFSITE DOSE CALCULATION MANUAL TAllLE 11-2 Fractional MEC for Atmospheric Effluent NbCLIDE 1985 1986 1987 1988 1989 1990 1991 11-3 120E-05 5.71 E-05 5 62L-05 6.00E 05 6 76E-05 6.10L 05 5.38 E-05 AR41 6 05E 06 3.24L 06 1.03E-05 9 33L-06 7.48E 06 5 29E 06 5.10E-06 RR 85M 8 76E 06 3 22L-07 5.62L-07 3.48E 07 107bO7 8.81 E-08 4 90E-08 K R-85 1.14 E-06 8.98E-08 4 84E-08 6 69E-08 2 44E-08 1.21 E-08 1.86E 08 RR-87 1.14 L-05 2.40b06 5.64E-06 3.52E-06 1.18 E-06 9.64 E-07 5.50E-07 1(R-88 3 03E-05 6 88E 06 1.44 L-05 8 94L 06 2.98L 06 ',.38606 1.35 E-06 XL 131M 2.03609 Xbl33M 2.62E-04 1.10bO8 168L 08 2.66L-08 3.92b10 l .63 E-09 3.15L-09 Xbl33 3.29L 06 1.46L-06 1.96E 06 5.75E-06 7.18E-07 1.87607 1.52E-06 Xbl35M 6 86E-06 1.51 b06 4 38E-06 302606 877607 7.73 bO7 410E-07 X b!35 810E-06 2.18E-06 3 84E-06 2.40E-06 7.35 E-07 7.41 E-07 410L-07 l Xbl38 l 3 93L-05 6 93 E-06 l 2. l l L-05 j $ 83L-06 l 4 74E-06 ! 252606 l .71 E-05 AG-110M l.10E 10 1 ilA 139 1.39 b13 IIA 140 812E 12 CD-109 212609 3 00E 10 5 43E-08 CL-141 5 05bl3 CE 144 4 86L-09 9 33L lO 9 38L-12 EO 57 1 llE il 1.3)L 15 5 98E 13 6 51bil 2.54 L-i l C0 58 7.4 8 E-09 6 33E 10 4 8 tlj-09 1.71 E-09 805609 l .30E-09 183L-10 C0 60 7 Set 08 1.06L 07 1.12E u8 3 47E-07 1.5 5 L-07 3.39E-09 1.01 L-07 CR SI 8 38E 10 1.20E-14 CS-134 2 8IE-07 2.26E-07 140b08 1.73L 2 621407 CS-136 CS-13 7 9 57E-07 7 00E-08 7.33E 08 1.60E-07 5 00bO7 4 55L-08 452607 j CS-138 5 74L-13 1.14E 12 1 10E 09 7.50E-14 2.05 E-12 1.14 L-08 l 18 514bl2 1.20E-10 184 E-I l 1.5 8 E-10 $ 24E-12 114L 10 lL-59 3 31E-13 l MN-54 9.48E Il 8 IOL-il 2.3 l t-09 MO-99 l.73L 13 6 45L 13 NA 24 9 46L-10 2.94 L-09 2.92E-09 blb95 6 00E-11 183btI l.42L 11 149E-12 2.28bl4 N13-97 7 62L 15 7.86bl6 RB-88 2.4 5 L-l i 1.83 bl I 5.45609 2.12 E-12 9.58b12 8 57bO8 RB 89 1.02bl 5 RU803 1.01 L-12 100E-09 Sll 125 8 50E 12 2.50b10 6.39L-12 SN-i l) 1.29 b12 2.86bl4 SR-89 1.16E-I l 3.67L-10 1.83E 10 8.83E-10 SR 90 1.33L 12 3.41b08 SR-91 1C-99M i02bl4 349614 1.47E-13 1C-101 T bl32 1.62b10 3.88E-12 1.24blo Y-88 2.03bl4 4N-65 1.10E-09 ZR 95 1.56 blo 4 24E 13 8.85 E-14

/R 97 7 07E-15 Page 99 of 138

NUCLEAR POWER BUSINESS UNIT ODCa!

OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 OFFSITE DOSE CALCULATION MANUAL TABLE H 2.(cont )

FRACTIONAL MEC TOR ATMOSPifERIC FFFLUENT 1985 1986 1987 1988 1989 1990 1991 NUCLIDL 1-131 8.19E 07 2 64L-07 7.33E 07 1.29E 07 7.5 7E-08 1.87L-08 8 24E-08 1 132 8 931-09 4.26L-09 5.76E-09 1.14 L-09 1.00E 10 2 60L lI 7 02L-li 1 133 652L48 3 24L-08 145 E-07 7 29E-08 5.67L-08 5 38E-(N 5 38E-09 l 134 106E ll 7AUL 10 1 135 460lMN 8 65L-10 1.74E-08 7 29L 10 1.00E-10 2.50E 13 1.2SE 10 IOIAllRAC 1.49L-04 5 29L-05 1.20L-04 1.llE-04 8 83L-05 7 62L-05 6 671-05 IOI AL-lO l . ! ? L-04 2.5 7 E-05 6.34 E-05 5.13 E-05 2.07L 05 1.52E-05 1.29L-05 Lif Mt.C 5 84f.-08 8 49E-08 6 621. 08 8.85E-08 8 46L-08 8.50L-08 9 50E-08

%/0 ll 3 3 70L-08 f.60L 08 1.92 E-08 3 46E-08 8.10L-09 5 02L-09 I44i-08 Page 100 of 138

NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 OFFSITE DOSE CALCULATION MANUAL l -

1 i

APPENDIX C CAI.CULATION OF TOTAL DOSE FACTORS USING REGULATORY GUIDE 1.109, REV.1 I

Page 101 of 138

ODCM NUCLEAR POWER BUSINESS UNIT Revision 10 OFFSITE DOSE CALCULATION MANUAL April 3,1997 OFFSITE DOSE CALCULATION MANUAL C.I.0 Calculation ofTotal Dose Factors Usine Reculatorv Guide 1.109 MethoJolony C.l.1 Liauid Release Dose Factors The equations and values used to calculate the total dose to the rnaximum exposed individual for each of the liquid revase mode pathways evaluated according to Regulatory Guide 1.109, Rev.1,1977 methodology is shown below. The total dose factor in mrem /Ci released is the sum of all pathway doses in mrem /Ci for the following pathways: milk, meat, fish, potable water, and shoreline deposits. The results for an organ is summed for each pathway and the total presented by age group and target organ in a matrix format for each radionuclide in Section 5, Table 5.1.1. The derivation of dilution factors used in the calculations is presented in Appendix D. The highest dose in each matrix is used as the dose tracking factor to be used for the monthly tracking of release doses. These values are found in Section 5, Table 5.2.

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:

M PU"P Dose ag = 1100 Qi ipBD 3 ige

b where:

Dosea g = the dose to the organ j of an individual of age group a from all of the nuclides i in pathway p, in mrem / year; ;

3 1100 = a factor to convert from Ci-sec/yr-ft to pCi/ liter; Mp = the mixing ratio (reciprocal of the dilution factor) at the point of harvest of aquatic food, dimensionless; U,p = a usage factor that specifies the intake rate for an individual of age group a associated with pathway p, in kg/ year; e =

3 the flow rate of the liquid effluent, in ft /sec; F

= the release rate of nuclide i, in Ci/ year; Qi Page 102 of 138

) l NUCLEAR POWER BUSINESS UNIT ODCM l OFFSITE DOSE CALCULATION MANtJAL Revision 10 i April 3,1997 l OFFSITE DOSE CALCULATION MANUAL !

l i

B;p

=

the equilibrium bioaccume'ation factor for nuclide i I in pathway p, expressed as the ratio of the ,

concentration in biota (in pCi/kg) to the )

radionuclide concentration in water (in pCill), in

{

liters /kg; j D aipj = . dose factor, specific to a given age group a, ,

nuclide i, pathway p, and organ j, which is used to j calculate the radiation dose from an intake of a !

nuclide, in mrem /pCi; A; = the radioactive decay constant of nuclide i, in day ^:

tp = the average transit time required for nuclides to reach the point of exposure. For internal dose, pt is

) the total time elapsed between release of the nuclides and the ingestion of the water, in days.

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

? l I)ose.,n,

= 1100 P U." B>p D.,p, e%

Q, r l

The values used in the equation above are: l Mp =

0.1136 (Point of harvest of the fresh fish is taken at a point 1000 m downstream. The plume centerline dilution factor at this location is 8.8 using RG 1.111 methodology. The dilution factor calculations are attached. The factor of 2 allowed for current reversals was not used.);

U ap = Infant - 0. Child - 6.9, Teen - 16, and Adutt - 211.g/ year; 3

F = 1507 ft /sec. (677000 gpm);

B;p

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

i Page 103 of 138

NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 OFFSITE DOSE CALCULATION MANUAL D,;p;

= Values used are taken from Tables E-11 through E-14 of RG 1.109; tg = 0.5 days.

C l . l .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:

" ' ^*

Dose.g3 = 1100 Q, Fa Depie*

where:

Doseapj = the dose to the organj of an individual of age group a from all of the nuclides i in pathway p, in mrem / year; 3

1100 = factor to convert from Ci-sec/yr-ft to pCi/ liter; U ap = a usage factor that specifies the intake rate for an individual of age grcup a associated with pathway p, in kg/ year:

Mp = the mixing ratio (reciprocal of the dilution factor) at the point of exposure, dimensionless; Q3, = consumption rate of contaminated water by an animal, in liters / day; 3

F = the flow rate of the liquid effluent,in ft /sec; Q; = the release rate of nuclide i, in Ci/ year; Fgi

= the stable element transfer coefficient that relates the daily intake rate by an animal to the concentration in an edible portion of animal product, in pCi/ liter of meat per pCi/ day; Page 104 of 138

NUCLEAR POWER BUSINESS UNIT - ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 OFFSITE DOSE CALCULATION MANUAL

\

D; aip

= the dose factor, specific to a given age group a, nuclide i, pathway p, and organj, which is used to calculate the radiation dose from an intake of a nuclide,

, in mrem /pCi; A = the radioactive decay constant of nuclide i, in day;

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

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

Dose.up, , ;g M, U.p Q^* Fa De n e*

i Q, F The values used in the equation abose are: ,

I Mp =

0.1111 (Point at which water is taken from the lake is l

! taken as plume centerline I mile downstream. The plume centerline dilution factor at this lo' cation is 9 using RG 1,11,1 methodology.);

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

= 60 liters / day; 3

F = 1507 ft /sec. (677000 gpm);

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

Daipj

= Values used are taken from Tables E-11 through E-14 of RG 1.109; t, = 20 days.

Page 105 of 138

NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 OFFSITE DOSE CALCULATION MANUAL C l .l .3 Irricated Foods (Milk From Watered Cattle)

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

= 1100 M' ' ^*

Q, Fa D ne *"

Dos n where:

Doseap; = the dose to the organ j of an individual of age group a from all of the nuclides i in pathway p, in mrem / year; 3

1100 = factor to convert from Ci-sec/yr-ft to pCi/ liter; Mp = the mixing ratio (reciprocal of the dilution factor) at the point of exposure, dimensionless; U,p = a usage factor that specifies the intake rate for an individual of age group a associated with pathway p, in liters / year; Q3w

= consumption rate of contaminated water by an animal, in liters / day; 3

F = the flow rate of the liquid effluent, in ft /sec; Qi

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

= the stable element transfer coefficient that relates the daily intake rate by an animal to the concentration in an edible portion of animal product, in pCi/ liter of milk per pCi/ day; -

D,;p; = the dose factor, specific to a given age group a, nuclide i, pathway p, and organj, which is used to calculate the radiation dose from an intake of a nuclide,in mrem /pCi; A; = the adioactive 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 106 of 138

NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 OFFSITE DOSE CALCUI.A TION MANUAL To alculate the dose per curie released, the equation above was rearranged and the calculation performed for each nuclide. The rearranged equation is shown below:

Dose.g, _

1100 M, U., Q4. Fa D.p,e.w Q F The values used in the equation above are:

Mp =

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

U ap = Infant - 330, Child - 330, Teen - 400, and i Adult - 310 liters / year;

=

Q,gw 60 liters / day; 3

F =

1507 ft /sec. (677000 gpm);

=

F;,1 Values used are taken from Table E-1 of RG 1.109:

D aipj = Values used are taken from Tables E-11 through E-14 of RG 1.109; tr = 2 days.

i Page 107 of138

NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 OFFSITE DOSE CALCULATION MANUAL C1.lA Potable Water The dose from ingestion of water was calculated using the equation:

Dose,i = i100 bb

Q,D,ne *4 p

where:

Doseapj = the dose to the organ j of an individual of age group a from all of the nuclides i in pathway p, in mrem / year; 3

1100 = a factor to convert from Ci-sec/yr-ft to pCi/ liter; i

Mp = the mixing ratio (reciprocal of the dilution factor) at the point of withdrawal of drinking water, dimensionless; U np = a usage factor that specifies the intake rate for an individual of age group a associated with pathway p, in 1/ year:

3 F = the flow rate of the liquid effluent,in ft /sec; Q; = the release rate of nuclide i, in Ci/ year; Daipj

= the dose factor, specific to a given age group a, nuclide i, pathway p, and organ j, which is used to calculate the radiation dose from an intake of a nuclide, in mrem /pCi; Ai = the radioactive decav enstant of nuclide i, in day ^;

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

4 l

Page 108 of 138

NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 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" = 1100 ' ' "'" D,inc' * '*

Q, 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 fhetor of 2 allowed for current reversals. The dilution factor calculations are attached.);

U ap = Infant - 330, Child - 510. Teen - 510, and Adult - 730 liters / year; 3

F = 1507 ft /sec. (677000 gpm);

D aip; " Values used are taken from Tables E-l I through E-14 of RG 1.109 tp = 2 days (This was calculated using a current speed of 12.2 cm/s plus 12 hours1.388889e-4 days 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.)

Page 109 of 138

ODCM NUCLEAR POWER BUSINESS UNIT Revision 10 OFFSITE DOSE CALCULATION MANUAL April 3,1997 OFFSITE DOSE CALCULATION MANUAL C l .l .5 Shoreline Denosits l

The dose from exposure to radioactive materials deposited on the f shoreline of the lake was calculated using the equation:

M" '"

Q,Ti D.,pj e%I - ed Dose,y, = 110000 1

where:

Dose,p;

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

F = the flow rate of the liquid effluent, in ft /sec;

= the release rate of nuclide i, in Ci/ year; Qi T; = the radioactive half life of nuclide i, in days; Daipj

= the dose factor, specific to a given age group a, nuclide i, pathway p, and organ j, which is used to calculate the radiation dose from an intake of a nuclide,in mrem /pCi; A; = the radioactive decay constant of nuclide i, in day ^;

Page 110 of 138

NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 OFFSITE DOSE CALCULATION MANUAL tg = the average transit time required for nuclides to reach the point of exposure. For internal dose, tp is the total time elapsed between release of the nuclides and the ingestion of the water, in days; tb

= the period of time for which the sediment or soil is exposed to the contaminated water, in days.

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.,,j ;;gg M,U,W .y , ,

Q, F 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 j this location is 54.9 using RG 1.111 methodology. l The dilution factor calculations are attached. The factor of 2 allowed for current reversals was not used.);

U ap = 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;p

= Values used are taken from Table A-1 of RG 1.109; 3

F = 1507 ft /sec. (677000 gpm);

D,;p)

= Values used are taken from Table E-6 of RG 1.109; i

tp = 0.5 day; tb

= 5458 days.

Page 111 of 138

NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 OFFSITE DOSE CALCULATION MANUAL Cl.2 Atmospherie Release Dose Factors: Non-Gaseous The equations and values used to calculate the total dose to the maximum exposed individual factors for non-gaseous radionuclides released to the atmosphere using Regulatory Guide 1.109, Rev.1,1977 is shown below. The total dose factor in 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 presen:ed 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.

C l .2.1 Inhalation of Nuclides In Air l

The dose from the inhalation of nuclides in the air was calculated using the equation:

/ 3 Dosej., =

3.17 E+ 04 R. 1 Q, DF'.3

where:

Doseja

=

the annual dose to organj of an individual of age group ;

a due to inhalation, in mrem / year; 3.17E+04 =

the number of pCi/Ci divided by the number of sec/ year; Ra =

the annual air intake for individuals in the age group a, 3

in m / year;

=

x/Q the annual average atmosphere dispersion factor, in f 3

I sec/m (The locatim. at which the dose was calculated was tha site boundary in the south sector - a distance of 1270 meters.);

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

the inhalation dose factor for radionuclide i, organ j, and age group a, mrem /pCi. ;

Page 112 of 138

NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 OFFSITE DOSE CALCULATION MANUAL To calculate the dose per curie released, the equation above was rearranged and the calculation performed for each nuclide. The marranged equation is shown below:

3""' =

3.17 E+ 04 R. DFI,,.

Q, sQ)

The values used in the equation above are:

Ra =

Infant - 1400, Child - 3700, Teen - 8000, and 3

Adult - 8000 m / year; y/Q =

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

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

C l .2.2 Annual Orean Dose From External Irradiation From Nuclides Denosited on the Ground The organ dose from external irradiation from nuclides deposited on the ground was calculated using the equation: .

I Dosej =

1E+ 12 (8760) 5, Sr [ [ DFG,3 i Ai l 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; l'

S; =

the annual average relative deposition of nuclide i, considering depletion of the plume during transport, in

-2 m , (The location at which the dose is calculated is the site boundary in the south sector - a distance of 1300 meters.); ,

Page 113 of 138

NUCLEAR POWER BUSINESS UNIT ODCM l OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 OFFSITE DOSE CALCULATION MANUAL l

Sp = the attenuation factor that accounts for the dose reduction due to shielding provided by residential structures, dimensionless; Qi

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

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

tb

= the time period over which the accumulation is evaluated, in days; DFG;j = the open field ground plane dose conversion factor for 2

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

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

Dose 4

= 1 E+ 12 (8760) 6. Sr DFG,j Q, Ai The values used in the equation above are:

Si =

31E-09 m'2 (This value taken from Table 1.4-2 of the FSAR, release mode IB, annual average, site boundary.);

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

tb

= 5479 days (15 years);

DFG;j = Values used are taken from Table E-6 ef RG 1.109.

4 Page 114 of 138

NUCLEAR POWER 13USINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 OFFSITE DOSE CALCULATION MANUAL I

C l .2.3 Annual Orean Dose From Atmospherically Released Nuclides in Milk The organ dose from atmospherically released nuclides in milk was calculated using the equation:

Doseg = 2.7 E+ 09 U.Qr S, Q. Em DFI,;.e*" { f, f. + e-"*'(1 - f, f.)}

fr(1-e'^o') IL(1 - e*'*)

[

Yv Ar; PL J where:

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

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 m age group a, m I liters / year; Qg = the amount of feed consumed by a cow per, in kg/ day; Si = the annual average relative deposition of nuclide i, considering depletion of the plume during transport, in m '. (The location at which the dose is calculated is the nearest animal location in the south-southeast sector - a distance of 1300 meters.); j

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

A.;

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

tb

= the time period over which the accumulation is evaluated, in days; DFI;j, = the dose conversion factor for the ingestion of nuclide i, organ j, and age group a, in mrem /pCi; Page 115 of 138

NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 OFFSITE DOSE CALCULATION MANUAL F im = the average fraction of the animal's daily intake of nuclide i which appears in each liter of milk, in days / liter; tr

= the average transport time of the activity from the feed into the milk and to the receptor, in days; fp = the fraction of the year that the animals graze on pasture, dimensionless; f 3

= 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, dimension less; A Ei = the effective removal rate constant for nuclide i from crops, in days ^, where Ag; = A; + (, and (is the removal rate constant for physical loss by weathering:

( = 0.0504 day ^:

te = the time period that crops are exposed to contamination during the growing season, in days; 2

Yv = the agricultural poductivity, in kg (wet weight)/m :

B, = the concentration factor for the uptake of nuclide i in pathway p, expressed as the ratio of the concentration in biota (in pCi/kg) to the nuclide concentration in water (in pCi/ lit.er),

in liters /kg; 2

j P = the effective surface density for soil, in kg (dry soil)/m ,

! For iodines, this factor is changed to 1.4E+09.

1 Page 116 of 138 l

NUCLEAR POWER BUSINESS UNIT ODC:d OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 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:

l l

Dose"' = 2.7 E+ 9 U.Qr6, Fim DFI,,,e*" f fp f, + e*'(1 - f, f,N Q.

x <( r(1e**) + B,,(1 - e*)' -

YvAr; Pli j The values used in the equation above are:

U, = Infant - 330, Child - 330. Teen - 400, and Adult - 310 liters / year; QF

= 50 kg/ day; Si = 18.8E-09 m# (This value taken from Table I.4-2 of the FSAR, release mode 1 B, grazing season, site boundary.);

F;n, = Values used are taken from Table E-1 of RG 1.109; DFI;ja = Values used are taken from Tables E-11 through E-14 of RG 1.109; tr

= 2 days; fp = 0.5; fs = 0.5; r = 0.25,1.0 for iodines, and 0.20 for noble gases, tritium, and carbon-14; l te = 30 days; l l

2 Yv = 0.7 kg/m ;

B iy = Values used are taken from Table E-1 of RG 1.109; P = 240 kg/m' ;

tb

= 5458 days (15 years).

Page 117 of 138

NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 OFFSITE DOSE CALCULATION MANUAL C l .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:

Dose,. = 2.7 E+ 9 U. Or 6, Q, Fir DFlip e 4d' f fp f. + e91 - f,f.y x

r(1 - e*d*} + B,v(1 - e4d') ' -

YvAr, P A, j where:

Doseja

= the annual dose to the organ j of an individual in age group a from a dietary intake of atmospherically released nuclides, in mrem / year; 2.7E+9 = the number of pCi per Ci divided by the number of days per year; Ua = the ingestion rate of meat for individuals in age group a, in liters / year; Qp = the amount of feed consumed by a cow per, in kg/ day; Si = the annual average relative deposition of nuclide i, considering depletion of the plurne during transport. in m# ,

(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; li = the radioactive decay constant of nuclide i, in day";

tb

= the time period over which the accumulation is evaluated, in days; DFI;;, = the dose conversion factor for the ingestion of nuclide i, organ j, and age group a, in mrem /pCi; Page 118 of 138

NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 OFFSITE DOSE CALCULATION MANUAL

=

Fri the average fraction of the attimal's daily intake of nuclide i which appears in each kilogram of flesh, in days /kg;

=

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

=

fp the fraction of the year that the animals graze on pasture, dimensionless; f3 =

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; A Ei =

the effective removal rate constant for nuclide i from crops, in days ^, where Agi = 1; + A w , and Awis the removal rate j constant for physical loss by weathering; j 1

t, = the time period that crops are exposed to contamination during the growing season, in days; 2

Yv = the agricultural productivity, in kg (wet weight)/m ;

1 Biy = the concentration factor for the uptake of nuclide i in pathway p, expressed as the ratio of the concentration in biota (in pCi/kg) to the nuclide concentration in water (in pCi/ liter),in liters /kg; 2

P = the efTective surface density for soil, in kg (dry soll)/m ,

For iodines, this factor is changed to 1.4E+09.

Page 119 of 138

NUCLEAR POWER BUSINESS UNIT l'

ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 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:

S*

o, "* = 2.7 E+ 9 U. Qr S. Er DFI,;. e'^d' ff, f, + e*h - f, f,y x<[r(i . c.1..) + a (i . e.ia.)- .

Yv Ati P A, J

The values used in the equation above are:

Ua =

Infant - 0, Chilu - 41, Teen - 65, and Adult - 110 kg/ year;

50 kg/ day; QF Si

.1S.8E-09 m'2 (This value taken from Table 1.4-2 of the FSAR, release mode 1B, grazing season, site boundary.);

Fri =

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

Values used are taken from Tables E-lI through E-14 of RG 1.109; t3 = 20 days; fp = 0.5; f3 = 1.0; r =

0.25,1.0 for iodines, and 0.20 for noble gases, tritium, and carbon-14; te = 30 days; B;y =

Values used are taken from Table E-1 of RG 1.109; 2

Yy =

0.7 kg/m ;

2 P = 240 kg/m ;

4

( = 0.0504 day;

=

tb 5458 days (15 years).

Page 120 of 138

NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 OFFSITE DOSE CALCULATION MANUAL Cl.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:

4 4 r(1 e '*) + IL(I - e ^) '

Doseg = 2.7 E+ 9 U, f,5i Q, DFlig e4 ^

YvAn PAi 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 mrenVyear; 2.7E+9 = the number of pCi per Ci divided by the number of days per year:

U3 = the ingestion rate of produce for individuals in age group a, in kg/ year; fg = fraction of produce ingested grown in garden ofinterest, )

l dimensionless; Si = the annual average relative deposition of nuclide i, considering s

depletion c f the plume during transport, in m ~, (The location at which the dose is calculated is the nearest garden location in the south-southwest sector - a distance of 1460 meters.);

= the release rate of nuclide i, in Ci/ year; Qi A; = the radioactive decay constant of nuclide i, in day ^;

tb

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

= the dose conversion factor for the ingestion of nuclide i, DFI;;3 organj, and age group a, in mrenVpCi; Page 121 of 138

NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 OFFSITE DOSE CALCULATION MANUAL th

= the holdup time that represents the time interval between harvest and consumption of the food, in days; r = the fraction of the deposited activity retained on crops, dimensionless; Ag; = the effective removal rate constant for nuclide i from crops, in days ^, where Ag; = Ai + Aw, and Awis 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; 2

Yv = the agricultural productivity, in kg (wet weight)/m ;

B;y = the concentration factor for the uptake of nuclide i in pathway p, expressed as the ratio of the concentration in biota (in pCi/kg) to the nuclide concentration in water (in pCi/ liter),

in liters /kg; 2

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

I I

I l

Page 122 of 138

NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 l

OFFSITE DOSE CALCULATION MANUAL To calculate the dose per curie released, the equation above was rearranged l

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

' 4 Doseig 4d' r(1-e46) + B,,(1 - e '-) '

= 2.7 E+ 9 U. f,64 [ DFlip e -

Q i Yv Ar.i PAi j The values used in the equation above are:

U, = Infant - 0, Child - 520, Teen 630, and Adult - 520 kg/ year; fg = 0.76; Si = 18.8E-09 m-2 (This value taken from Table I.4-2 of the FSAR, release mode IB, growing season, site boundary.);

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

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

( = 0.0504 day'I ;

te = 60 days; Y = 0.7 kg/m~;

B iy = Values used are taken from Table E-1 of RG 1.109; 2

P = 240 kg/m ;

l tb

= 5458 days (15 years).

Page 123 of 138

NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 OFFSITE DOSE CALCULATION MANUAL C 1.2.6 Annual Orean Dose From Atmospherically Released Nuclides in Leafv Vecetables The organ dose from atmospherically released nuclides in leafy vegetables was calculated using the equation:

Q, DFI9 . e*

r(1 - e* '*) + B,,(1 - e*)

Dosej. = 2.7 E+ 9 U. fiSi YvAa PAi f ,

l where:

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

S; = the annual average relative deposition of nuclide i, considering depletion of the plume during transport, in m.,, (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 wnstant of nuelide i, in day ^;

tb

= the time period over which the accumulation is evaluated, in~

days; DFlij , = the dose conversion factor for the ingestion of nuclide i, organ j, and age group a, in mrem /pCi; Page 124 of 138

1

[

NUCLEAR POWER BUSINESS UNIT ODCM l OFFSITE DOSE CALCULATION MANUAL Revision 10 I April 3,1997 OFFSITE DOSE CALCULATION MANUAL th

= the holdup time that represents the time interval between harvest and cons,.mption of the food, in days; r = the fraction of the deposited activity retained on crops, j dimensionless;

).Ei

= the effective removal rate constant for nuclide i from crops, in days where ).gi = ).; + 4, and ( is the removal rate constant for physical loss by weathering; te = the time period that crops are exposed to contamination during the growing season, in days; f

2 Yy = the agriculural productivity,in kg (wet weight)/m ; l B;y = the concentration factor for the uptake of nuclide i in pathway p, expressed as the ratio of the concentration in biota (in pCi/kg) to the nuclide concentration in water (in pCi/ liter),

in liters /ke:

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

i l

! O Page 125 of 138

ODCM NUCLEAR POWER BUSINESS UNIT l Revision 10 1 OFFSITE DOSE CALCULATION MANUAL I April 3,1997 l 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,,.-

=

2.7 E+ 9 U, fi 6. DFlo.e'*^ -[r(1 - e**) + B, (1 - e'*^)

Q, YvAti P Ai l

r The values used in the equation above are:

t l

Ua = Infant - O. Child - 26, Teen - 42, and Adult - 64 kg/ year; fi =

1:

Si = 18.8E-09 m'2 (This value taken from Table L4-2 of the FSAR, release mode 1 B, growing season, site boundary.);

DFI;;3

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

= 1 day; r = 0.25,1.0 for iodines, and 0.20 for noble gases, tritium, and carbon-14; i Aw = 0.0504 day ^;

l te = 60 days; l

Yy = 0.7 kg/m ;

B iy = Values used are taken from Table E-1 of RG 1.109; 2

I P = 240 kg/m ;

tb

= 5458 days (15 years).

Page 126 of 138

NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE COSE CALCULATION MANUAL Revision 10 April 3,1997

, OFFSITE DOSE CALCULATION MANUAL

! l C1.3 Atmosoberic Release Dose Factors: Noble Gases The equations and values used to calculate the total dose factors for noble l gases released to the atmosphere using Regulatory Guide 1.109, Rev.1,1977 l is shown below. The dose factor in mrem /Ci and mrad /Ci released for each radionuclide is presented in Section 5, Table 5-1.

Cl.3.1 Annual Gamma and Beta Air Dose From All Noble Gas Releases The dose from the submersion ofindividuals in air containing noble gases was calculated using the equation:

r >

r Dose or Dose D = 3.17 E+ 04 1 [Q, DFT Or DFf

<Q) ,

t where:

DoseY or 0

Dose = 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; yjQ = the annual average atmosphere dispersion factor, j 3

in sec/m (The location at which the dose was calculated was the site boundary in the south sector-a distance of 1270 meters.);

Q = the release rate of nuclide i, in Ci/ year; DFiYorDF;P = the gamma and beta air dose factors for a uniform semi-infinite cloud of radionuclide i, in 3

mrad-m /pCi-year.

I Page 127 of 138

NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 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:

f Dose [ or DoseE

' = 3.17 E+ 04 -x DF;Y or DF; Q; <Q).

The values used in the equation above are:

x/Q

=

9.36E-07 seconds /m3 (This value taken from Table 1.4-2 of the FSAR, release mode 1B, intermittent, annual average, site boundary.);

B DE[ or DFi

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

C1.3.2 Annual Skin Dose From All Noble Gas Releases The skin dose from the submersion ofindividuals in air containing noble gases was calculated using the equation:

< 3< s Dose = 3.17 E+ 04 1 1.11 Sr Q, DFl + [Q, DFS,

< s >

where:

Dose = the annual skin dose due to immersion in a semi-infmite 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 structures, dimensionless; Page 128 of 138

NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 OFFSITE DOSE CALCULATION MANUAL y/Q =

the annual average atmosphere dispersion factor, in 3

sec/m (The location at which the dose was calculated was the site boundary in the south sector - a distance of 1270 meters.);

Q; =

the release rate of nuclide i, in Ci/ year; i l DF;Y = the annual gamma air dose factor for a uniform 3

semi-infinite cloud of nuclide i, in mrad-m /pCi-year; DFSi = the beta skin dose factor for a semi-infinite cloud of 2

nuclide i, which includes the attenuation by 7 mg/cm of 3

skin,in mrem-m /pCi-year.

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

< 3 Dose' 1

= 3.17 E+ 04 (1.11 Sr DFT + DFS,)

Q, rQ) l The values used in the equation above are: <

SF =

1 (No structural shielding is assumed.).

y/Q =

9.36E-07 seconds /m3 (This value taken from l Table 1.4-2 of the FSAR, release mode 1B, annual l average, site boundary.);

1 l

DF,Y = 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.

l l

l Page 129 of 138

NUCLEAR POWER BUSINESS UNIT ODCM l

OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 l

OFFSITE DOSE CALCULATION MANUAL C l .3.3 Annual Total Body Dose From All Noble Gas Releases -

j The total body dose from the submersion ofindividuals in air i

containing noble gases was calculated using the equation:

l l

I ( %

l Dose = 3.17 E+ 04 S, 1 Q, DFB,

<Q) where:

Dose = the annual total body dose due to immersion in a l

semi-infinite cloud, in mrem / year; 3.17E+04 = the number of pCi/Ci divided by the number of sec/ year; l

SF = the attenuation factor that accounts for the dose reduction due to shielding provided by residential structures, dimensionless; yjQ = the annual average atmosphere dispersion factor, in 3

sec/m (The location at which the dose was calculated was the site boundary in the south sector - a distance of 1170 meters.);

Qi

= the release rate of nuclide i, in Ci/ year; DFB i = the total body dose factor for a uniform semi-infinite cloud of nuclide i, which includes the attenuation of 2 3 5 g/cm of tissue,in mrem-m /pCi-year.

Page 130 of 138

3 1

NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 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:

( 8 Dose' 1

= 3.17 E+ 04 S, DFB, Q, < Q)

The values osed in the equation above are:

=

Se 1 (No structural shielding is assumed.);

=

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

DFB, =

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

I l

4 I

Page 131 of 138

NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 OFFSITE DOSE CALCULATION MANUAL l

i l APPENDIX D l

DERIVATION OF DILUTION FACTORS USING REGULATORY GUIDE 1.113 Page 132 of 138

NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 OFFSITE DOSE CALCULATION MANUAL ,

~

! ]

Dl.0 Liould Effluent Dilution Factor Calculations

Dl .1 Methodoloey The dilution factors used for calculating the doses from liquid effluent released to Lake Michigan were calculated using the methodology of Regulatory Guide 1.113, " Estimating Aquatic Dispersion of Effluents from

' Accidental and Routine Reactor Releases for the Purpose ofImplementing Appendix I." The parameters used in the calculation and the results of the calculation are given in Table D-1. The results are presented graphically in Figure D-1.

The centerline and shoreline values were calculated using Reg Guide 1.113 formulae 17 and 18 which apply to discharges to the Great Lakes. (The formulae are not presented here. See Section 5 of the PBNP FSAR for the formulae and origin of values used.) These results are applied as calculated for fish caught near PBNP. But for other pathways, an extra factor of two (2) is applied to account for current reversals which occur in Lake Michigan as described in the Appendix I, Section 5, of the PBNP FSAR.

1 l

l l

l Page 133 of 138

NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 OFFSITE DOSE CALCULATION MANUAL l

i TABLE D-1 SURFACE DILUTION FACTC ~~ZC I ;E~~

~~$ - 5" O;a5aann5hsZ y >ZC>~~

~~gC 9 6~~

0

+

E

~~' 0 e~~

~~1 __~~

~~e .~~

~~ck f~~

=

~~faa 5~~

~~L 0)~~

+

~~r " E sr _~~

~~u ge 0 te 1~~

~~e Sr a .~~

~~m t L "~~
4 n 0+ (i
=
aa
~~" E e 0 c _~~
1 n
rn '
a _
t oi s '
t i
s _
3D ct n ' 0
+
Em ae Fu f R t
e a
0 a 1
e1 r
0 m
nE l
f e
s a
e o e
/
3 o
s m
e N
2 wh t
s n
t h
ig e
i o d l
R e
s .
/ .
2 mro i 2
2 4
nr 0
E
+ od n a
ti t c- o m e c '
~~0. D m u u q~~
i U
n 0 0
s
./ 5 m.
9 2e 25 m meg ta r
i m
s 1
5 0
l * - 2 1 O " 6 r e ii r ) 0 a 3
e ym2 )= ). ;3 DL h
f 1 c h p e .
p .*(
s s :
(
= is '
1 t o .uyZlbD 0 d F +
D a5- _ =Z - gig :: g : - 12 iw E
6 5 4 3 2 1 00 e 0 0 0 0 0 0 01 c
+ + + + + + + r E E E E E u E E o 0 0 0 0 0 0 0 s 1 1 1 1 1 1 1 a
e r
A bu A M
NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 OFFSITE DOSE CALCULATION MANUAL DI.2 Dilution Factor Twelve Miles Downstream: Two Rivers Water Intake The dilution factor used at the Two Rivers water intake twelve miles downstream from PBNP included the factor of two described in Section D1.1.
However, instead of using the straight centerline dilution factor shown in Table 1, the weighted average dilution factor calculated over the width of the plume was used.
This approach was used for the following reasons. First, the path that the current takes to reach the Two Rivers water intake is not straight. In order to reach Two Rivers, the water must flow southeast around Point Beach State Park, which juts into Lake Michigan, and then curves back 90 degrees towards Two RD,ers As a result of this deviation from straight line flow, any part of the plume or r.ossibly none of the plume would impinge upon the intake structure.
Second, there is a difference in the distance offshore of the PBNP discharge and the Two Rivers water intake. The Two Rivers water intake is located 5080 feet offshore. By contrast, PBNP discharges close to the shoreline through two flumes, one directed north and one directed south, and is modeled as a source that extends 1000 feet out into the lake from the shoreline.
Based on these two considerations, it was concluded that the weighted average dilution across the width of the plume as it diverges while flowing south would constitute a better estimate of the dilution factor instead of the calculated for the centerline of an area source as is assumed for the FSAR calculation. The calculation and the values used are shown below.
The average dilution factor at 12 miles downstream was calculated in the following manner:
~~1. The standard deviation of the radionuclide concentration in the y direction at 12 miles downstream on the surface of the lake was calculated. This calculation used the following formula:~~
=
2 x cy xx l oy u
where 2
ey =
latercl turbulent diffusion coefficient in cm /sec x =
the downstream distance in cm u =
current in cm/sec Page 136 of 138
NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 OFFSITE DOSE CALCULATION MANUAL 2
Substituting the values for ey, x, and u of 900 cm /sec,19308 m, and 12.2 cm/sec, respectively, into the equation yicids 2
cn1 2x 900 19308 m x 100 '*
see m "I
i 2.2 sec oy = = 168.8 meters
~~"I 100 m~~
2. At distances of 0.1o,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 factor, and the fraction of the area under the normal distribution curve is listed below.
Distance Off Plume Centerline Fraction of Equivalent Fraction of Total Standard Distance Area Under the De iation (m) Curve for Interval Dilution Factor 0.1 a 16.9 0.080 13.8 0.2a 33.8 0.080 14.0 0.3a 50.6 0.078 14.3 0.4a 67.5 0.075 14.7 0.5o 84.4 0.072 15.2 0.6o 101.3 0.068 15.8 0.7a 118.1 0.065 16.6 0.8o 135.0 0.060 17.6 0.9a 151.9 0.056 18.8 1.0c 168.8 0.051 20.2 1.1a 185.6 0.046 21.9 1.2a 202.5 0.042 23.9 1.3o 219.4 0.037 26.3 1.4a 236.3 0.032 29.2 1.5a 253.2 0.028 32.6 1.75o 295.4 0.053 44.7 2.0a 337.6 0.035 64.7 2.25o 379.8 0.021 98.4 2.50 421.9 0.012 158.4 3.0c 506.3 0.010 482 1.00 4 tals 1
Page 137 of 138
NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 OFFSITE DOSE CALCULATION MANUAL
It is assumed that the standard deviation of the radionuclide concentrations across the plume can be represented by a normal distribution curve. The fraction of the total area under the curve is that fraction of the area under the curve that lies between, for example, the interval 0.la and 0.2a which also includes the area of the curve in the interval -0.la and -0.2a.
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.
)
4 Page 138 of 138
NUCLEAR POWER BUSINESS UNIT ODCM Revision 10
)
OFFSITE DOSE CALCULATION MANUAL l April 3,1997 OFFSITE DOSE CALCULATION MANUAL i
1 APPENDIX E Wisconsin Electric submittal to the United States Nuclear Regulatory Commission, dated 1 J
October 8,1987 (VPNPD-87-430, NRC-87-104)
The submittal consists of the letter and two Attachments. Attachment II contains Appendices A-G. ,
i I
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I 1
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e WISCONSIN Electnc poe coume 231 W wCHIG AN.P o 80X2046. MILWAUKEE.WI53201 (414)277 2345 VPNPD 4 30 NRC-87-104 October 8, 1987 U.S. NUCLEAR REGULATORY COMMISSION Document Control Desk Washington, D.C. 20555 Gentlemen:
DOCKET NOS. 50-266 AND 50-301 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION FOR 10 CFR 20.302 APPLICATION POINT BEACH NUCLEAR PLANT on July 14, 1987, Wisconsin Electric Power Company submitted an application, under the provisions of 10 CFR 20.302, for approval of a proposed procedure to dispose of sewage treatment sludge containing minute quantities of radioactive materials. Sub-sequent to the application, Mr. Ted Quay of the NRC staff requested additional information regarding the environmental characteristics of the area surrounding the Point Beach Nuclear Plant. The responses to this request were furnished in our submittal dated August 6, 1987.
By letter dated September 9, 1987, the NRC has requested Wisconsin Electric supply additional information in order to complete the review of our application. This Request for Additional Information (RAI) contains ten specific items which require responses or commitments from Wisconsin Electric. In I addition, the NRC requests the previously submitted information and the information supplied in response to the RAI be compiled into "one complete, extensive, and self-contained package".
To facilitate your review, Attachment I is included to provide direct responses to the ten items contained in the RAI.
Attachment II is provided as the complete application, including the information from our letters dated July 14, 1987, and August 6, 1987, and information supplied in respense to the NRC RAI. '
We request that you complete your review of this complete, self-contained package and issue an approval of our application E-2
c 1 l l l ,
. . i NRC Document Control Desk October 8, 1987 Page 2 as soon as possible. In arder to facilitate your review and to expedite processing, we would be pleased to discuss these matters or provide additional information by telephone. Please I feel free to contact us.
l Very truly yours, l .
s v.
Ll" ?dt
( ;
! C.*W. Fay Vice President Nuclear Power bjm 1
Attachments
! Copies to.NRC Resident Inspector NRC Regional Administrator, Region III i
! Blind copies to Britt/Gorske/Finke, urstein, Charnoff, Fay, Krieser, e, Newton, Zach l I
)
l.
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'E-3
6 T 4 9 ATTACHMENT I RESPONSES TO QUESTIONS CONTAINED IN THE REQUEST FOR ADDITIONAL INFORMATION (RAI)
ON POINT BEACH 1 AND 2 REQUEST FOR DISPOSAL OF LOW LEVEL RADIOACTIVITY CONTAMINATED SEWAGE SLUDGE BY LAND APPLICATION WISCONSIN ELECTRIC POWER COMPANY UNDER 10 CFR 20.302(a) m 4
e E-4
The numbering system used in these responses corresponds directly to numbering used in the NRC RAI, dated September 9, 1987.
~~1. a. This request is for multiple applications, approximately 2 to 4 per year.~~
~~b. This request is for multiple years, . expiration to coincide with conclusion of decommissioning activities associated with retirement of PBNP Units 1 & 2.~~
~~c. Please refer to the response to question number 10.~~
~~2. The pathways used to determins doses to both the maximally exposed individual and the inadvertent intruder are documented in Attachment II, Appendices D and E.~~
Due to the extremely low concentrations of radionuclides in the sewage sludge and the associate low doses, Wisconsin Electric will control access to the disposal sites by conditions of use defined in lease agreements with the lease. Use of the land is not controlled beyond the conditions of the lease, thereby not restraining a casual visitor from the disposal site. However continuous occupancy would be readily observed, and remedial action would be taken. -
~~3. Information contained in previous submittals has been included in Attachment II with modifications to provide specific commitments to the NRC.~~
~~4. Please refer to the response to question number 10.~~
~~5. Site maps have been updated and are included in Attachment II, Appendix C.~~
~~6. The direct grazing of cattle on the proposed disposal sites is controlled by restrictions contained in the lease agreement.~~
There vill be no restrictions placed on fishermen on Lake Michigan.
Calculations of doses due to all pathways associated with a release to Lake Michigan (Attachment II, Appendix E) do not indicate a need to apply restrictions to fishermen.
7. Please refer to revised site maps included in Attachment II, Appendix C. Site number 5 is located on company owned land beyond the PBNP site boundary. All other sites are within the PBNP site boundary area.
i
~~8. a. Please refer to Attachment II, Section 3.2, Disposal Procedure.~~
~~b. Please refer to Attachment II, Section 3.2, Disposal Procedure. t~~
~~c. Please refer to Attachment II, Section 3.2, Disposal Procedure.~~
~~d. Please refer to Attachment II, Appendix A.~~
9. Please refer to Attachment II, including Appendix D and Appendix E for additional pathways analyzed for this submittal. These identified pathways will be analyzed prior to all subsequent disposals to insure doses are maintained within prescribed limits, i.e., 1 arem/ year to the g aximally exposed individual and 5 arem/ year to the inadvertent
~~.ntruder.~~
10. A limiting concentration level for the sludge contained in the storage tank is discussed, in Attachment II, Appendix F. Since this application is for multiple applications over multiple years, Attachment II, Appendix F also addresses an activity limit.
E-5
ATTACHMENT II COMPLETE ANALYSIS AND EVALUATION POINT BEACH NUCLEAR PLANT 10 CFR 20.302(a) APPLICATION e
e E-6
l *
\
i 1.0 Purpose By this submittal Wisconsin Electric Power Company requests approval of the U.S. Nuclear Regulatory Commission for a proposed procedure to dispose of sewage treatment sludge containing trace quantities of radionuclides generated at the Point Beach Nuclear Plant. This request is submitted in accordance with the provisions of 10 CFR 20.302(a).
2.0 Waste Description I
The waste involved in this disposal process consists of the residual solids remainir.g in solution upon completion of the aerobic digestion sewage treat- ]
i ment process utilized at P8NP. The PBNP sewage treatment plant is used to {
j process waste water from the plant sanitary and potable water systems. J l These systems produce non-radioactive wiste streams with the possible l exception of wash basins located in the radiologically controlled area of
~~the plant. These wash basins are believed to be the primary source of the )~~
l extremely small quantities of radionuclides in the sludge, i
j The sewage sludge generated at PBNP is allowed to accumulate in the sewage i- plant digestor and aeration basin. Two to four times annually, depending l on work activities and corresponding work force at P8NP, the volume of '
i the. sludge in the digestor and aeration basin needs to be reduced to allow I
continued efficient operation of the treatment facility. . The total volume
.of sludge removed during each disposal operation is typically en the order of 15,000 gallons. The maximum capacity for the entire P8NP treatment facility and hence the maximum disposal volume is about 30,000 gallons.
In the case of a maximum capacity disposal, doses would not necessarily t
increase in proportion to the volume, since more than one disposal site may be used.
Trace amounts of radionuclides have been identified in PBNP sludge currently being stored awaiting disposal. The radionuclides identified and their concentrations in the sludge are summarized below:
Nuclide Concentration (WCi/cc)
Co-60 2.33E-07 Cs-137 1.50E-07
~~_The total activity of the radionuclides in the stored sludge, based on the i identified concentrations and a total voiume of 15,000 gallons of sewage sludge, are as follows~~

Nuclice Activity (fjl Co-60 13.2 Cs-137 8. 5 ;
These concentrations and activities are consistent with expected values based on prior analyses of sewage sludge. The radionuclide concentration in the sewage sludge has remained relatively constant during sampling
. conducted since December 30, 1983. A detailed sunnary of the results of l this sampling program are contained in Appendix A for your review.
L E-7
l .
1 l
l l
In addition to monitoring for the radionuclide content of the sludge, l the WDNR requires several other physical and chemical properties of the sludge to be determir.ed. These properties are the percent total solids, percent total nitrogen, percent ammonium nitrogen, pH, percent total phosphorus, percent total potassium, cadmium, copper, lead, nickel, mercury, zinc, and boron. An example of a typical sludge sample analysis is included in Appendix B.
3.0 Disposal Method In the context of this application, Wisconsin Electric commits to the following methodology. No distinction is made or intended between "shall" or "will", as used in the descriptions contained in this section.
! 3.1 Transport of Sludge The method used to dispose of the sludge shall utilize a technique approved by the WDNR. The process of transporti.g the sewage sludge for disposal involves pumping the sludge from the PBNP sewage treatment plant storage tanks into a truck mounted tank. The truck mounted tank shall be required to be maintained tightly closed to prevent spillage while in transit to
~~the disposal site. The sludge shall be transported to one or more of the~~
! six sites approved by the WDNR for land application of the sewage sludge from PBNP.
3.2 Disposal Procedure The radionuclide concentrations in the sludge shall be determined prior l
to each disposal by obtaining three representative samples from each of,the sludge storage tanks. The sludge c6ntained in the sludge tanks is prevented from going septic by a process known as complete mix and continuous aeration. This process completely mixes the sludge allowing for representative samples to be obtained.
l The samples shall be counted utilizing a GeLi detector and multi-channel analyzer with appropriate geometry. The detection system is routinely calibrated and checked to ensure the lower limits of detection are within values specified in the Radiological Effluent ;
Technical Specifications (RETS).
To insure t'he samples are representative of the overall concentration in the storage tanks, the radionuclide concentration determination for each of the three samples shall be analyzed to irisure each sample is within two standard deviations of the average value of the three samples. If this criteria is not met, additiona samples will be obtained and analyzed to insure a truly representative radionuclide concentration is utilized for dose calculations and concentration limit determinations. The average of all statistically valid concentration determinations will be utilized in determining the storage tank concentration values.
E-8
Prior to disposal the waste stream will be monitored to determine the physical and chemical properties of the sludge, as discussed in the last paragraph of Section 2.0, Waste Description. The results will be compared to State of Wisconsin limits to insure the sludge does not pose a chemical hazard to people or to the environment.
The radionuclides identified in the sludge, along with their respective concentrations, will be compared to concentration limits prior to disposal. The methodology discussed in Appendix F will be usedThe in determining compliance with the proposed concentration limit.
total activity of the proposed disposal will be compared to the proposed activity limit as described in Appendix F.
If the concentration and activity limit criteria are met, the appropriate exposure pathways (as described in Appendix 0) wf11 be evaluated prior to each application of sludge. These exposures will be evaluated to insure the dose to the maximally exposed individual will be maintained less than 1 mrem / year and the dose to the inadvertent intruder is maintained less than 5 aren/ year. The exposures will be calculated utilizing the meth-odology used in Appendix E, including the current activity to be landspread along with the activity from all prior disposal. The remaining radio-activity from prior disposals will be corrected for radiological decay prior to performing dose calculations for the seat, milk, and vegetable ingestion pathways, the inhalation of resuspended radionuclides, and all pathways associated with a release to Lake Michigan. The residual radio-activity will be corrected for radiological decay and, if appropriate, the mixing of the radionuclides in the soil by plowing prior to performing external exposure calculations.
The sewage sludge is applied on the designated area of land utilizing the WDNR approved technique and adhering to the following requirements of WPDES Permit Number WI-0000957-3.
Discharge to the land disposal system shall be limited so that during surface spreading all of the sludge and any precipitation falling onto or flowing onto the disposal field shall not overflow the peri-meter of the system.
~~Sludge shall not be land spread on land with a slope greater than 12%.~~
~~During the period from December 15 through March 31 sludge shall not be land spread on land with a slope greater than 6% unless the wastes are injected immediately into the soil.~~
~~Sludge shall not be surface spread closer than 500 feet from the nearest inhabited dwelling except that this dir'ance may be reduced with the dwelling owner's written consent.~~
~~Sludge shall not be spread closer than 1,000 feet from a public water supply well or 250 feet from a private water supply well.~~
Sludge shall not be lar' spread within 200 feet of any surface water unless a vegetative but,er strip is maintained between the surface watercourse and the land spreading system, in which case a minimum separation distance of at least 100 feet is required between the system and the surface watercourse.
E-9
l
~~Depth to groundwater and bedrock shall be greater than 3 feet from '~~
the land surface elevation during use of any site.
i
~~Sludge shall not be land spread in a floodway.~~
Sludge shall not be land spread within 50 feet of a property line road or ditch unless the sludge is incorporated with the soil, in which case a minimum separation distance of at least 25 feet is required.
~~The pH of the sludge-soil mixture shall be maintained at 6.5 or higher.~~
~~Low areas of the approved fields, subject to seasonally high ground-water levels, are excluded from the sludge application.~~
~~Crops for human consumption shall not be grown on the land for up to one year following the application of the sludge.~~
~~The sludge shall be plowed, disked, injected or otherwise incorporated into the surface soil layer at appropriate intervals.~~
The flexibility implied in the latter provision for soil incorporation is intended to allow for crops which require more than a one year cycle.
For the Point Beach disposal sites, alfalfa is a common crop which is harvested for several years after a single planting. Sludge disposal on an alfalfa plot constitutes good fertilization, but the plot cannot be plowed without destroying the crop. The alfalfa in this case aids in At a minimum, binding the layer of sludge on the surface of the plot.
however, plowing (or disking or other method of injection and mixing to a nominal depth of 6 inches) shall be done prior to plar.;ing any new crop, regardless of the crop.
3.3 Administrative Procedures Complete records of each disposal will be maintained. These records will include the concentration of radionuclides in the sludge, the total volume of sludge disposed, the total activity, the plot on which the sludge was applied, the results of the chemical composition determinations, and all dose calculations.
The annual disposal rate for each of the approved land spread sites will be limited to 4,000 gallons / acre, provided WDNR chemical composi-tion, NRC dose guidelines, and concentration and activity limits are maintained within the appropriate values.
The farmer leasing the site used for the disposal will be notified of the applicable restrictions placed on the site due to the land spreading of sewage sludge.
4.0 Evaluation of Environmental Impact 4.1 Site Characteristics 4.1.1 Site Topography The disposal sites are located in the Town of Two Creeks in the northeast corner of Manitowoc County, Wisconsin, on the E-10
west shore of Lake Michigan about 30 ciles southeast of the center of the city of Green Bay, and 90 miles NNE of Milwaukee.
This site is lou ted at longitude 87* 32.5'W and latitude 44' 17.0'N. The six sites are on property owned and controlled by
> Wisconsin Electr c and are within or directly adjacent to the Point Beach site boundary. The sites are described below and are outlined on the man contained in Appendix C as Figure 3.
Site No. PB The approximately 15 acres 1ccated in the NE 1/4 of the NE 1/4 of Section 23, T. 21N - R. 24E.
Site No. PB The approximately 20 acres located it: the SE 1/4 of the SE 1/4 of Section 14, T. 21N - R. 24E. i Site No. 98 The approximately 5 acres located in the t!W 1/4 of Section 24, T. 21N - R. 24E.
Site No. PB The approximately 5 acres located in the NW 1/4 of .the SW 1/4 of Section 24, T. 21N - R. 24E.
Site No. PB TI.e approximately 5 acres located in the NE 1/4 of the NW 1/4 of Section 25, T. 21N - R. 24E.
l Site No. PB The approximately 5 acres located in the NE 1/4 of the SW 1/4 of Section 14, T. 21N - R. 24E.
The overall ground surface at the site of the Point Beach Nuclear Plant is gently rolling to flat with elevations varying from 5 to 60 feet above the level of Lake Michigan. Subdued knob and kettle topography is visible from aerial photographs. The land surface slopes gradually toward the lake from the higher
~
glacial moraine areas west of the site. Higher ground adjacent to the lake, however, diverts the drainage to the north and f south, The major surface drainage features are two small creeks which drain to the north and south. One creek discharges into the lake about 1500 feet above the northern cornertheof the site ponds and the other near the center of the site. DuringAs spring, mentioned in of water may occupy the shallow depressions.
Section 3.2, Disposal Procedure, these low areas are excluded from the sludge application.
A site topographic map covering details out to a 5 mile radius may be found in the FSAR at Figure 2.2-3 and is included in Appendix C as Figure 2.
The disposal of sewage sludge at these six sites will have no .
impact on the topography of this area.
4 4.1.2 Site Geology Prior to construction of the Point Beach Nuclear Plant, an evaluation of the geological characteristics of the area in and surrounding the sue was made. The geologic structure of the region is essentially simple. Gently dipping sedimentary rock E-11
f l
strata of Paleozoic age outcrop in a horseshoe pattern around a '
shield of Precambrian crystalline rock which occupies the western part of the region. The site is. located on the western flank of the Michigan Basin, which is a broad downwarp ringed The by discontinuous out:rops of more resistant formations.
bedrock formations are principally limestones, dolomites, and' sandstones with subordinate shale layers. The rocks form a succession of extensive layers that are relatively uniform in thickness. The bedrock strata dip very gently towards Lake Michigan at rates from 15 to 35 feet per mile.
The uppermost bedrock under the site is Niagara Dolomite.
Bedrock does not outcrop on the site but is covered by glacial till and lake deposits. The soils contain expansive clay minerals and have et.ierately high base exchange capacity.
In the area of the site, tne overburden soils are approximately 70 to 100 feet in thickness. Although the character of-the glacial deposits may vary greatly within relatively short distances, a generalized section through the overburden soils adjacent to Lake Michigan at the site consists of the following sequence:
~~1. An upper layer of brown clay silt topsoil underlain with several feet of brown silty clay with layers of silty sand;~~
~~2. A layer of 20 feet of reddish-brown silty clay with some sand and gravel and occasional lenses of silt;~~
~~3. A layer of 25 feet of reddish-brown silty clay with layers of silty sand and lenses of silt;~~
4. A layer of 50 feet of reddish-brown silty clay with some sand and gravel, the lower portion of which contains gravels, cobbles, and boulders, resting on a glacial eroded surface of Niagara dolomite bedrock.
Site drainage is poor due to the high clay content of the soil combined with the pock-marked surface. Additional information on site geology may be found in Section 2.8 of the FSAR.
The use of these sites for disposal of sewage sludge will not impact the geology of the area.
4.2 Area Characteristics 4.2.1 Meteorology The climate of the site region is influenced by the general storms which move eastward along the northern tier of the United States and by those which move northeastward from the south-western part of the country to the Great Lakes. This During conti-nental type of climate is modified by Lake Michigan.
spring, summer, and fall months the Wind lake temperature shifts from differs westerly
- markedly frw:a the air temperature.
to easterly directions produce marked cooling of day-time E-12
i
. \
I i
! temperatures in spring and summer. In autumn the relatively l warm water to the lake prevents night-time temperatures from falling as low as they do a few miles inland from the shoreline, '
i Summer time temperatures exceed 90*F for six days on the l average. Freezing temperaturas occur 147 days and below zero j on 14 days of the winter on the average. Rainfall averages about 28 inches per year with 55 percent falling in the months of May through September. Snowfall averages about 45 inches l
per year. Sludge spreading shall be managed such that the l
surface spreading together with any precipitation falling on I
the field shall not overflow the perimeter of the field.
Additional information on site meteorology may be found in Section 2.6 of the FSAR.
There will be no impact on the meteorology of the area due to the disposal of the sewage sludge.
4.2.2 Hydrology The dominant hydrological f.ature of this site is Lake Michigan, one of the largest of the Great Lakes. The normal water level in Lake Michigan is approximately 580 feet above mean sea level.
In the general vicinity of the site, the 30 foot depth contour .
is between 1 and 1-1/2 miles offshore and the 60 foot contour l is 3 to 3-1/2 miles off shore. The disposal sites are twenty or more feet above the normal lake level. There is no record that the sites have been flooded by the lake during modern times. There are no rivers or large streams which could create a flood hazard at or near the sites.
The subsurface water table at the Point Beach site has a definite slope eastward toward the lake. The gradient indi-cated by test drilling on the site is approximately 30 feet per mile. It is therefore extremely unlikely that any release of radioactivity on the site could spread inland. Furthermore, the rate of subsurface flow is small due to the relative impervious nature of the scil and will not promote the spread of releases. Further information on site hydrology is detailed in the PBNP FSAR Section 2.5.
There will be no adverse impact on hydrology of the area due to disposal of sewage sludge by land spreading.
4.3 Water Usage 4.3.1 Surface Water
! Lake Michigan is used as the source of potable water supplies in the vicinity of the site for the cities of Two Rivers (12 miles south), Manitowoc (16 miles sourth), Sheboygan (40 miles south), and Green Bay (intake at Rostok 1 mile north of Kewaunee, 13 miles north). No other potable water uses are recorded within 50 miles of the site along the lake shore. All public water supplies drawn from Lake Michigan are treated in puri-fication plants. The nearest surface water used for drinking other than Lake Michigan are the Fox River 30 miles NW and i
E-13
i i
.*
~~i Lake Winnebago 40 miles W of the site.~~
Lake Michigan is also utilized by various recreational activities, including fishing, swimming and boating.
There will be no impact on surface water usage due to the disposal of sewage sludge.
4.3.2 Ground Water 1
I Ground water provides the remaining population with potable supplies. Public ground water supplies within a 20 mile radius of the site are listed in Table 2.5-3 of the FSAR. Additional wells for private use are in existence throughout'the region. f The location of private wells within a two mile radius of PBNP are indicated on Figure 3. Appendix C.
l The potable water for use at the Point Beach Nuclear Plant is l drawn from a 257 feet deep well located at the southwest corner of the plant yard. Water from this well is routinely sampled as part of the environmental monitor *ng program.
There will be no adverse impact on ground water usage due to the disposal of sewage sludge.
4.4 Land Usage Manitowoc County, in which the site is 1ccated, and the adjacent counties of Kewaunee, Brown, Calumet, and Sheboygan are predominantly rural. Agricultural pursuits account for approximately 90% of the total county acreage. With the exception of the Kewaunee Nuclear Plar>t located 4.5 miles north, the region within a radius of five miles of the site is presently devoted exclusively to agriculture.
Dairy products and livestock account for 85% of the counties' farm production, with field crops and vegetables accounting for most of the remainder. The principal crops are grain corn, silage corn, cats, barley, hay, potatoes, green peas, lima beans, snap beans, beets, cabbage, sweet corn, cucumbers, and cranberries. Within the township of Two Creeks surrounding the site (15 sq. miles), there are about 800 producing cows on about 40 dairy farms. Some beef cattle are raised 2.5 miles north of the site. Cows are on Duringpasture from the first of June to late September or early October.
the winter, cows are fed on locally produced hay and silage. Of the milk produced in this area, about 25 percent is consumed as fluid milk and 50 percent is converted to cheese, with the remainder being used in. butter. making and other by products.
It has been the policy of Wisconsin Electric to permit the co. trolled use of crop land and pasture land on company owned property. No direct grazing of dairy or beef cattle or other anima 13 is permitted on these company owned properties. Crops intended for human consump-
~~tion shall not be grown on the disposal sites for at least one year following the application of the sludge.~~
~ The proposed 1cnd application of sewage sludge will not h0ve any direct effect on the adjacent facilities. Additional land use E-14
i information may be found in Section 7.4 of the FSAR.
4.5 Radiological Impact The rate of sewage sludge application on each of the six proposed sites will be monitored to insure doses are maintained within applic-able limits. These limits are based on NRC Nuclear Reactor Regulation (NRR) staff proposed guidance (described in AIF/NESP-037, August, 1986). These limits require doses to the maximally exposed member of the general public to be maintained less tnan 1 area / year due to the disposal material. In addition, NRR guidance requires doses of less than 5 mrem / year to an inadvertent intruder.
f To assess the doses received by the maximally exposed individual and the inadvertent intruder, six credible pathways have been identified l for the maximally exposed individual and four credible pathways for the inadvertent intruder. The identified credible pathways are described in Appendix D.
l Calculations detailed in Appendix E demonstrate the disposal of the currently stored PBNP sewage sludge would remain below these limits.
The total annual exposure to the maximally exposed individual based on the identified exposure pathways is equal to 0.072 arem. The dose to a hypothetical intruder assuming an overly conservative occupancy frctor of 100% is calculated to be 0.115 arem/ year. By definition, the inadvertent intruder would not be exposed to the processed food pathways (meat and milk).
1 The calculational methodology used in determining doses for the proposed disposal of sludge stored at PSNP shall be utilized prior to each additional land application to insure doses are maintained less than those proposed by NRR. This calculation will include radio-nuclides disposed of in previous sludge. applications. The activity i om these prior disposals will be corrected for radiological decay l-prior to performing dose calculations for the meat, milk, and vegetable ingestion pathways, the inhalation of resuspended radio-nuclides, and all pathways associated with a potential release to Lake Michigan. The residual radioactivity will be corrected for radio-logical decay and, if applicable, the mixing of radionuclides in the In addition, soil prior to performing external exposure calculations.
the dose to a farmer potentially leasing more than one application site will be addressed by summing the doses received from the external '
exposure from a ground plane source and resuspension inhalation pathways for each leased site. In addition, the aximum site specific dose due to the other pathways identified in Appendix 0, will be utilized in the' total exposure estimation.
5.0 Radiation Protection The disposal operation will follow the applicable PBNp procedures to maintain doses as low as reasonably achievable. Tect.5. cal review and guidance will be provided by the PBNP Superintendent - Health Physics.
E-15 l
O APPENDIX A
~~SUMMARY~~
OF RADIOLOGICAL ANALYSES OF SEWAGE SLUDGE SINCE DECEMBER 30, 1983 e
E-16
l l ."
t 1
Sample Tank Tank Radionuclide Date Concentration l volume (Gallons) (uci/cc) )
I 12-30-83 Digester 8400 Co-58 5.58E-07 l Co-60 1.87E-06 Cr-51 4.88E-07 Cs-134 1.59E-07 !
Cs-137 3.57E-07 1 4-06-84 Digester 7560 Co-60 7.89E-07 Aeration 6667 Co-60 1.87E-07 l
12-05-84 Digester 7560 Co-58 1.75E-07 1
Aeration 6667 i Co-60 8.29E-07 6-03-85' Digester 7560 Co-60 8.29E-07 Cs-137 2.46E-07 Aeration 6700 Co-60 3.27E-07 Cs-137 1.33E-07 4-10-86 Digester 7560 Co-60 6. 79E-07 Cs-137 1.72E-07 Mn-54 4.91E-08 Co-60 1.65E-07 11-04-86 Digester 7560 . Co-58 8.04E-08
. Aeration &
Clarifier 25100 Co-58 1.37E-07 i Co-60 2.18E-07 l Cs-137 1.64E-07 l l
l l
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E-17
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t APPENDIX 8 CHEMICAL COMPOSITION ANALYSIS OF SEWAGE SLUDGE l
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E-18
etATs or wiscoee8" SLUDGE CHARACTERISTIC
,e. oCACTMsNT CF Mt.TV2Ab RESOWCES Wisconsin Statwie 147.02(1) and Wisconsin F;sW&asode Administratiw Code NR 110.27(3) arv.j sag wage Treatment Plant Sludge l . seese complete this form araf send q the Departmem of Netwel Resowces appropriate District / Ares Offles. Keep one copy for your records. ~
For additsonal forms, pleene sensect yow approonste Dietrict/ Ares Office.
~
! esam TTaz w ,ossnm==iTav esa Wisconsin Electric Power Company WI 00 L 1 L 5 .J.
I JTREET Om ROUTE COWNTY l 231 W. .vichigan Street M11waukee i
CIT Y 5T ATE. 24, CODE RLEPMOME MvueER OMCLUDE AREA CODE)
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~~1. Pleses report laboratory testing results for the following parameters~~

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~~Parameter Abbreviation Result *Persmeter Abbreviation Result I 0* '~~
j* Total Solids, % -
Owomium, p Cr -
Total Nitrogen, % TOT N I" Cu 2200 Copper, ppm Ammonium Nitrogen,% NHj-4i 0.34 Land, ,,, Pb 190 Total Phosphorous,5 P 40.01 mre,y, g, 3.6 Total Potassium,% . K 0.25 Nickal, ,,, Ni 12 As 1.O Zn 2 5 'M Arsenic. ,,, Zin c, ,,m i 12* pH I*O cadmium. , Cd -
$essgested erotyeis procedwes for the ahem parameters een he found in NR 219, oneW tests and procedwes, Wisconsin Adminietraties code. AE parameters oemt then persent seeds and pH shell be repersed on a dry weight hesis. -
~~2. what is ow nome of the lehermory that afd the analysis and when was it performed? ,~~
tasserstory Neme Wisconsin Electric Power Co. Detseerst e April 12, 1933 Laboratory Services Division , .
I where et om v.amem pasnt wm en empie den?
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e e o APPENDIX 0 EXPOSURE PATINAYS e t e O 9 E-24
I. EXPOSURE PATHWAYS - MAXIMALLY EXPOSED INDIVIOUAL
~~1. External whole body ex;iosure due to a ground plane source of radionuclides.~~
2. Milk ingestion pathway froe cows fed alfalfa grown on plot. 3. Heat ingestion pathway from cows fed alfalfa grown on plot. 4. Vegetable ingestion pathway from vegetables grown on plot. 5. Inhalation of radioactivity resuspanded in air above application site. 6. Pathways associated with a releast to Lake Michigan. Ingestion of potable water at Two Rivers, Wisconsin municipal water supply, ingestion of fish from edge of initial mixing zone of radionuclide release, ingestion of fresh and stored vegetables irrigated with water source as Lake Michigan, ingestion of afik and meat from cows utilizing Lake Michigan as drinking water source swinning and boating activities at edge of initial mixing zone,, and shoreline deposits. II. EXPOSURE PATHWAYS - INADVERTENT INTRUDER
~~1. External whole body exposure due to a ground plane source of rad,ionuclides.~~
~~2. Vegetable ingestion pathway from vegetables grown on plot. 3. Inhalation of radioactivity resuspended in air above application site.~~
4. Pathways associated with a release to Lake Michigan. Ingestion of potable water at Two Rivers Wisconsin municipal water supply, ingestion of fish from edge of initial mixing zone of radionuclide release, ingestion of fresh and stored vegetables irrigated with water source as Lake Michigan, ingestion of afik and meat from cows utilizing Lake Michigan as drinking water source, swimming and boating activities at edge of initial mixity, zone, and shoreline deposits.
The milk and meat pathways are not included in calculating the dose to the inadvertent intruder. The doses due to these pathways are calculated based on feeding the cows alfalfa grown on the sludge applied land. Since direct grazing on these lands is prohibited, the alfalfa aust be cropped prior to being used as feed. This effectively removes the availability of 4 these pathways to the inadvertent intruder, who by definition occupies the sludge applied land continuously. E-25
1 III. GROUND WATER PATHWAY The two The ingestion of groundwater is not a credible exposure pathway. factors contributing to this determination are as follows:
1. The site sap in Appendix C, Figure 3 details the spatial relation-ship between the proposed disposal sites and the local ground water wells. The flow gradient of ground water was determined for the P84P FSAR to be towards Lake Michigan. Reviewing the sites and i lot:a1 wells shows no private well located in the path of radionuclide mJgration towards Lake Michigan.
~~I The PBNP site well is located on the plant site, potentially in a path of radionuclide migration. The PBNP well is routinely sampled as a requirement of the P8HP environmental monitoring program.~~
~~2. The cation exchange capacity (CEC) of the soils at each site has been determined.~~
Site Cation Exchance; Capacity (MEQ/100g) 1 16 l 2 11 3 11 - 4 10 5 8 6 9 . The cation exchange capacity of soil is dependent on the valance of the radionuclides and is determined by the relation: MEQ = ATOMIC VALANCE E G U
~~1.0E-03 Radionuclide Valance CEC (MEQ/100a)~~
Co-60 +2 3.00E-02 Co-58 +2 2.90E-02 Cs-137 +1 1.37E-01 Mn-54 +2 2.70E-02 Cr-51 +3 1.70E-02 Cs-134 +1 1.34E-01 Using the values for Cs-137 and site 5 which has the lowest CEC, the total exchange capacity of the soil is 1.10 grams of Cs-137 100 grass of soil Calculating the specific activity of Cs-137, 3.578E+0S ,3.578E+05 4 Specific Activity = T1/2(yrs.)
~~ATOMIC MASS 30 137~~
~~= 87.1 Ci/ gram l~~
l E-26
The cation exchange capacity of the soil expressed in the number of Curies of radionuclide per 100 gras: of soil is 95.8 Ci Cs-137
' 100 grams of soil Since the proposed disposal of sewage sludge contains quantities of radionuclides on the order of 10-100 pCf the soil at each site has the capacity to effectively eliminate the migration of the radionuclide to ground water.
t 9 O E-27
6 8 i APPENDIX E' EXPOSURE ANALYSIS E-28
[. GENERAL ASSUMPTIONS
1. Sewage sludge is uniformly applied over plot acreage.

2. Sewage sludge is applied to one of the 5 acre plots, site P8-03, P8-04, P8-05, or P8-06. (Assuming the smallest site size is conservative for the calculation methodology herein.)

3. Based on the sewage sludge currently stored at P8NP, the following data is used in the calculations.
Ground Plane Studge Volume Activity Concentration Concentration Radionuclide (Gallons) (cm3) (uCf) (uci/cas ) (uci/cm2) Co-60 15,000 5.68E+07 11.2 2.33E-07 6:53E-08 Cs-137 15,000 5.68E+07 E.5 1.50E-07 4.21E-08 I. CALCULATION OF EXTERNAL EXPOSURES A. Specific Assumptions
~~1. Conservatively assume radioactivity remains on surface of land plot ~.~~
Calculation ignores any plowing or mixing of radioactivity within soil. Calculations for the proposed disposal will therefore ignore self absorption or shielding from soil. The external exposure at the application site due to prior disposals will be calculated utilizing the methodology in Appendix G and added to that calculated for the proposed disposal.
2. The plots are owned by Wisconsin Electric and have been approved by the Wisconsin Department of Natural Resources (DNR) as disposal sites. The land is leased and potentially farmed. Occupancy of the land can be realistically expected only during plowing, planting and harvesting. Occupancy has been astimated to be 64 hours per year.
~
~~8. Summary of Calculational Methodology~~
~~. 1. Caiculate ground plane radionuclide concentrations in pCi/cm2~~
2. The dose from a plane of uniformly deposited radionuclides is esiculated using Regulatory Guide f.109, Revision 1. Appendi.~ C, Formula C-2. ,

3. Dose rates were calculated assuming continuous occupancy then adjusted for realistic occupancy factors.
E-29
C. External Exposure Rate Calculations l The dose from a plane of uniformly deposited radionuclides is calculated using Regulatory Guide 1.109, Revision 1, Appendix C, formula C-2 0 (r,6) = 8760 Sp{C(r,6)DFGg where Dj(r,8) = yearly' dose 8760 = hours per year Sp = 1.0, since no dose reduction due to residential shielding is applicable. l C (r,8) = ground plane radionuclide concentration (pCi/m2) DFG(i,j) = external dose factor for standing on contaminated ground as given in Table E-6 of Regulatory Guide 1.109, Revision 1. i Ground Plane Ground Plane y Dose Concentration Concentration Rate . Y Dose Factor (mrem /yr) (ares /hr per pCi/m ) 2 (uCi/cm2) (DCi/m2) Radionuclide 1.70E-08 6.53E-08 6.53E+02 9.72E-02 Co-60 1.5SE-02 4.20E-09 4.21E-08 4.21E+02 Cs-137 TOTAL: 1.13E-01 aren/ year In reality, these These calculated dose rates assume continuous occupancy. l sites will be occupied only during plowing, planting, and harvesting. l Assuming an occupancy of 2 hours per day, 1 day p:r week, and 32 weeks (8 month growing season) per year, the occupancy factor becomes 2 hr/ day a 1 day / week
32 weeks /yr

1/8760 hours /yr = 7.3E-03.
EXTERNAL EXPOSURE DOSE, RATE (aren/ year) Continuous Occupancy Realistic Occupancy Radionuclide Co-60 9.72E-02 7.10E-04 Cs-137 1.55E-02 1.13E-04 TOTAL: 1.13E-01 8.23E-04 i l E-30
r I l l l II. CALCULATION OF MEAT AND MILK INGESTION PATHWAY EXPOSURES A. Specific Assumptions I
~~1. All feed consumed by cow is grown on sludge applied acreage. {~~
2. All meat and milk consumed by human is from cattle exclusively fed feed from sludge applied land. i i 3. Stable element transfer coefficients (6 4 are utilized from j Regulatory Guide 1.109 to estierte the ffa)ction of radioactivity which is transferred from the soil to the feed, a O i Radionuclide iv Co-60 9.4E-03 ! Cs-137-
1. 0E-02

4. Alfalfa has typically been grown on the plots. Soil tests have indi-cated a minimum alfalfa yield of 4.1 tons per acre can be expected.
~~F Summary of Calculational Methodology l~~
~~1. The concentration of radionuclides in feed grown on the disposal i plot: is estimated.~~
Transfer coefficients (B. from Table E-1 of RegulatoryGuide1.109wereusedtoestimatet$l)fractionofradio- - i nuclide which may be expected to transfer to the feed from the soll. 2. Concentrations of radionuclides in milk and meat were estimated using Formula A-11 from Regulatory Guide 1.109.
~~3. Ingestion dose rates were estimated using Formula A-12 from l Regulatory Guide 1.109.~~
~~C. Milk and Meat Incestion Pathway Dese Rate Calculation ,~~
~~1. Concentration in feed.~~
~~l l Activity in Feed = B yy.~~
Activity in Soil Concentration in Feed = Activity in Feed /(ko of Feed

5 Acres) i Aadionuclide Activity in Activity in Concentration in Radionuclide Soil (uci) Feed (uci) Feed (DCi/ka) j Co-60 13.2 1.24E-01 6.67E+00 Cs-137 8.5 8.50E-02 4.C7E+00
~~2. Concentration in Milk and Meat Calculate concentrations of radionuclides in milk and meat using E-31 C__~~
l Formula A-11 in Regulatory Guide 1.109, Revision I which is 1 C34 , F93*Cgy*Qp where C radionuclide concentration of 1 in component A F IA = stable element transfer coefficient whose values are in gg = Table E-1 of the Regulai.ory Guide C radionuclide concentration in feed Qpif == consumption rate of feed = 50 kg/d (wet weight) from Regulatory Guide 1.109 . Use the following Regulatory Guide 1.109 values for F94 Element F,3=, (d/1) for allk F94=Ff (d/kg) for meat Co 1.0E-03 1.3E-02 Cs 1.2E-02 4. 0E-03 Concentration in Concentration in Radionuclide Milk (pCi/1) Meat (pCi/ko) Co-60 3.34E-01 4.34E+00 Cs-137 2.74E+00 9.14E-01
3. Calculated Dose rates The fo-sula for total dose from eating animal products fed vegeta-tion (alfalfa) grown on P8HP sludge applied land is given by Regulatory Guide 1.109, Revision 1, Formula A-12, page 1.109-16.
But, as noted following equation A-13, it is necessary to compute separately the milk and seat portions of the dose. DOSE = I(U,p*D 9 ,pg*exp(-Ajst )) where U = conc of radionuclide i in animal product A C $ == consumption rate of animal product D *EE =average dose factor time between allking or slaughtering and tf consumption U,p by Age Group Infant Child Teenager Adult Milk (1/yr) 330 330 400 310 Meat (kg/yr) - 41 65 110 C 93
~~= concentration calculated above 4~~
04,p9 = OF whole body dose factors, Regulatory Guide 1.109, Revision 1. E-32
l Whole Body Dose Factors (arem/pC' Incested) Child Teenager Adult Infant Incestion Nuclide Ingestion Incestion Incestion 1.56E-05 6.33E-06 4.72E-06 Co-60 2.55E-05 4.33E-05 4.62E-05 5.19E-05 7.14E-05 Cs-137 T = 0 for milk (assume consumption on fare) s = 20 days for meat (Regulatory Guide 1.109, Revision 1, Table E-15) MILK INGESTION DOSE RATE (arem/ year) Radionucline Infant Child , Teenager Adult 1.72E-O' 8.46E-04 4.89E-04 , Co-60 2.81E-03 3.02E-02 4.18E-02 5.69E-02 6.06E-02 Cs-137 4.20E-02 4.35E-02 5.77E-02 6.11E-02 TOTALS: MEAT INGESTION DOSE RATE (ares / year) Infant Child Teenager Adult Radionuclide
- 2.76E-03 1.77E-03 2.24E-03 Co-60 7.18E-03 Cs-137 - 1.73E-03 3.08E-03 - 4.49E-03 4.85E-03 9.42E-03 - TOTALS:
~~1 l MEAT AND MILK INGESTION PATNWAY 005c RATES (arem/ year)~~
~~. Infant - 4.20E-02 Child - 4.'80E-02 Teenager - 6.26E-02 Adult - 7.05E-02 III. CALCULATION OF VEGETABLE INGESTION PATHWAY EXPOSURES l~~
A. Soecific Assumptions I. The WPDES pemit issued to PBNP for the disposal of sewage l sludge prohibits the growing of crops for human consumption for one year following the application of the sewage sludge. Therefore, prior to planting veget. ables on the application site, the soil would.be plowed. Plowing is assumed to uni-formly six the top 6 inches of soil. E-3
2. The soil density is assumed,to be 1.3 grams /cm3

3. All vegetables consumed by the individual of interest are crown on the sludge applied acreage.

4. Stable element transfer coefficients (84 ) from Regulatory Guide 1.109areusedtoestimatethefraltionofradio-activity transfered from the soil to the vegetables.
~~O Radionuclide iv Co-60 9.4E-03 Cs-137 1.0E-02~~
~~) and the mass basis~~
~~5. The consumption factors of food medium (U,pTable E-5 are used distributions from Regulatory Guide 1.109, to determine annual consumption of vegetables.~~
~~U,,by Age Group" Infant Child Teen Adult~~
~~- 280 kg/yr 340 kg/yr 280 kg/yr .~~
~~Based on 54% vegetable consumption by mass of fruit, vegetable, and grain.~~
~~6. The Ingestion Dose Factors by age group are from Regulatory Guide 1.109, Tables E-11, E-12 E-13, and E-14.~~
Whole Body Ingestion Oose Factors (arem/pci incested) i Infant _ thile, Teen Adult Radionuclide 2.55E-05 1.56E-05 6. '33 E-06 4.72E-06 Co-60 7.14E-05 Cs-137 4.33E-05 4.62E-05 5.19E-05
~~7. Radiological decay of the radionuclides applied to the plot is not taken into account in these calculation:.~~
~~B. ' Summary of Calculational Methodology~~
1. The radionuclide concentration in the soil is calculated in units of pC1/kg based on uniform applicatiori over 5 acre plot, plowing to a depth of 6 inches, and a soil density of 1.3 g/cm3

2. values are applied to the soil concentration values to The obtain84
~~,the radionuclide conce.% ration in the vegetables.~~
~~for each age group are then used . 3. The consumption factors (UtodeterminetheannualraMo)nuclideintakebyage to eating these vegetables. 9 E-34~~
~~4. Finally, the age dependent ingestion dose factors are used to obtain annual doses by age group.~~
~~C. Vegetable Pathway Ingestion Dose Rate Calculations~~
~~1. Concentration in soil Concentration Activity Soil Volume Soil Mass In Soil Radionuclide Appifed (pCf) (cm3) J) (pCi/kg)~~
~~Co-60 13.2 3.08E+09 4.00E+06 3.30E+00 Cs-137 8.5 3.08E+09 4.00E+06 2.13E+00~~
~~2. Concentration in vegetables Concentration !~~
Concentration In B In Vegetables ! Radionuclide Soil (pC1/kg) iv (pCi/kg) Co-60 3.30E+00 9.4E-03 3.10E-02 Cs-137 2.13E+00 1. 0E-02 2.13E-02
~~3. Calculated Dose Rates .~~
~~7 The dose rate for direct ingestion of vegetables grown on the l sludge applied land is given by the equation. 00SE RATE = I U,p~~
~~gO ,p) a EXP (-A g t).* C 9 where~~
= consumption ate of food medium U*E D i A *Ed ==radiological dose factordecay for radionuclide, constant i !
~~t = time between harvest and consumption l Cg = concentration of radionuclide, i, in food~~
]
medium. t, the time between harvest and ingestion, is assumed to be zero for this calculation. VEGETABLE INGESTION DOSE RATE (ares / year) Radionuclide Infant Child Teen Adult Co-60 - 1.356-04 6.67E-05 4.10E-05 l Cs-137 - 2.75E-04 3.76E-04 4.26E-04 i TOTAL - 4.11E-04 4.43E-04 4.67E-04 E-35 l
IV. CALCULATION OF INHALATION OF RESUSPENDED RADIONUCLIOES PATHWAY EXPOSURE I
)
~~A. Specific Assumptions 1~~
1. The model used to determine the radionuclide concentration l in air above the sludge applied land is taken from WASN-1400, USNRC, Reactor Safety Study - An Assessment of Accident Risks in Conmercial Nuclear Power Plants, Appendix VI.

2. The radionuclide concentration in air remains constant for year of interest, i.e., radiological decay and decrease in resuspension factor are not.taken into account for this calculation.

3. The maximally exposed member of the general public is assumed to be the farmer using the plot of land with an occupancy of 64 hours per year.

4. The inadvertent intruder is assumed to occupy the plot of land for the entire year.

5. The Inhalation Dose Factors by age group are from Regulatory Guide 1.109, Tables E-7, E-8, E-9, and E-10.
~~WHOLE BODY INHALATION DOSE FACTORS (arem/oCi inhaled) Radinnuclide Infant Child Teen Adult~~
~~' Co-60 8.41E-06 6.12E-06 2.48E-06 1.85E-06 Cs-137 3.25E-05 3.47E-05 3.89E-05 5.35E-05 LUNG INHALAT7'NJ DOSE FACTORS (ares /pci inhaled)~~
~~Radionuclide Infant _ Child Teen Adult Co-60 3.22E-03 1.91E-03 1. 09E-03 7.46E-04 Cs-137 5.09E-05 2.81E-05 1.51E-05 9.40E-06~~
~~6. The age dependent inhalation rates are obtained from Regulatory Guide 1.109, Table E-5.~~
Inhalation Rates (m3/yr) Infant Child Teen Adult 1400 3700 8000 8000 E-36
B. Summary of Calculational Methodology . 1. The ground plane radionuclide concentrations in pCi/m2
2. Calculate the resuspension factor utilizing equation given in WASH-1400.

3. Obtain the radionuclide concentration in air (pCf/m3) above plot utilizing methodology in WASH-1400.

4. Using parameters contained in Regulatory Guide 1.109, calculate annual dose for continuous occupancy and for realistic, occupancy.
~~C. Inhalation of Resuspended Radionuclides in Air Pathway Dose Rate Calculations - Resuspension of Radionuclide in Air~~
~~1. Ground plane radionuclide concentration Ground Plane .~~
Ground Plane Radionuclide Concentration (pCi/cm2) Concentration (DCi/m2) Co-60 6.53E-08 '6.53E+02 Cs-137 4.21E-08 4.21E+02 ,
~~2. Calculation of resuspension factor, K (s' )~~
~~From WASH-1400, K(t) = 1.0E-09 + 1.0E-05~~
EXP (-0.6769

t) wh'ere t = time since radionuclides were deposited on ground surface.
~~t is assumed to be 0 for these calculations, thereby maximizing the resuspension factor. Therefore,~~
~
~~K = 1.0E-05 m~~
~~3. Calculate radionuclide concentration (pC1/m3) in air.~~
~~From WASM-1400 3~~
~~"I" )~~
~~airsurface concentration dt. posit (DCi/m2)~~
~~(pCi/m3) or _1 Air Concentration (pC1/m3) = surface deposit (pCi/m2)~~
~~K(a )~~
~~AIR CONCENTRATIONS Radionuclide Air Concentrations (pCi/m3) Co-60 6.53E-03 Cs-137 4.21E-03 E-37~~
~~4. Dose Rate Calculations Dose Rate (ares /yr) = Inhalation. Rate (s3/yr)~~
Air Conc. (pCi/m3)

Dose Conversion factor (area /pci)
WHOLE BODY INHALATION DOSE RATE (arem/ year) Radionuclide Infant Child Teen Adult Co-60 7.69E-05 1.48E-04 1.30E-04 9.66E-05 Cs-137 3.92E-04 5.41E-04 1.31E-03 1.80E-03 TOTAL 2.69E-04 6.89E-04 1.44Lco3 1.90E-03 LUNG INHALATION DOSE RATE (area / year) Radionuclide Infant Child Teen Adult Co-60 2.94E-02 4.61E-02 5.69E-02 3.90E-02 Cs-137 3.00E-04 4.38E-04 5.09E-04 3.17E-04 TOTAL 2.97E-02 4.65E-02 5.74E-02 3.93E-02 INHALATION OF RESUSPENDED RADIONUCLIDES IN AIR DOSE RATES l VHOLE BODY DOSE RATE (ares / year) Occupancy Infant Child Teen Adult Continuous 2. 69E-04 6.89E-04 1.48-03 1.90E-03 Realistic 1.96E-06 5.03E-06 1.05E-05 1.39E-05 LUNG DOSE RATE (eram/ year) Occupancy Infant Child Teen Adult Continmus 7. 97E-02 4.65E-02 5.74E-02 3.93E-02 Realistic 2.17E-04 3.39E-04 4.19E-04 2.87E-04 V. CALCULATION OF WHOLE BODY EXPOSURES OUE TO RELEASE TO LAKE MICHIGAN A. 4 ?ecific Assumptions
~~1. The methodology contained in the PBNP Offsite Dose Calculation Manual (ODCM). is used to perfore this calculation.~~
E-38
t
2. The entire activity contained in the sludge is released into Lake Michigan.

3. The exposure pathways addressed by the 00CM methof: , y are ingestion of potable water from Two Rivers, WI wat eupply, hgestion of fish at edge of initial mixing zone, ; ,gestion of f~esh and stored vegetables, irrigated with Lake Michigan as source of water, ingestion of allk and meat from cows utilizing Lake Michigan as drinking water source, swimming and boating activities at edge of initial mixing zone, and shoreline deposits.
~~B. Summary of Calculational Methodology~~
1. The activity released in the sludge is converted into Co-60 dose equivale." Curies.

2. The annual design release limit from the 00CM is 94.7 Co-60 equivalent curies.

3. The annual design release limit is based on a limiting dose of 6 ares adult whole body. The annual dose due to sewage sludge is calculated by a ratio of calculated release compared to release limit.
~~C. Whole Body Exposure Calculations~~
~~1. Co-60 equivaler; Curies Activity Co-60 eq. ,~~
~~DFi /DF Co-60 Activity (pci) Radionuclide (pCl) Co-60 13.2 1.00E+00 13.2 Cs-137 8.5 1.51E+01 128.4 TOTAL 141.5pci Co-60 equivalent~~
~~2. Ratio of dose limit to annual design release limit 6 area~~
~~- 94.7 Co-60 equivalent curies~~
~~3. Whole Body Dose Calculation Dose = 6 mres 141.6pci 94.7x10*pCi Dose = 8.97E-06 area WHOLE BODY 005E RATE (arem/ year)~~
E-39
00sE StMiARY , Maximally Exposed Individual The identified credible exposure pathways for the maximally exposed individual are: 1.) External exposure from ground plane source (realistic occupancy) 2.) Milk ingestion pathway 3.) Heat ingestion pathway 4.) Vegetable ingestion pathway 5.) Resuspension inhalation pathway (realistic occupancy)
~~6. ) Pathways identified due to release to Lake Michigan.~~
AGE GROUP Pathway Infant Child Teen Adult External 8. 23E-04 8.23E-04 8.23E-04 8.23E-04 Milk 4.20E-02 4.35E-02 5.77E-02 6.11E-02 Heat - 4.49E-03 4.85E-03 9.42E-03 Vegetable - 4.11E-04 4.43E-04 4.67E-04 Inhalation 1.96E-06 5.0!E-06 1.05E-05 1.39E-05 Water , 8.97E-06 8.97E-06 8.97E-06 8.97E-06 TOTAL: 0. 043 0.049 0.064 0.072 (area / year) , Inadvertent Intruder The identified crefible exposure pathways for the inadvertent intruder are: 1.) External exposire from ground plane source (continuous occupancy) 2.) Vegetable ingestion pathway 3.) Resuspension inhalation pathway (continuous occupancy)
~~4. ). Pathways identified due to release to Lake Michigan.~~
AGE GROUP Pathway Infant Child Teen Adult External 1.13E-01 1.13E-01 1.13E-01 1.13E-01 Vegetable - 4.11E-04 4.43E-04 4.67E-04 Inhalation 2.96E-04 6.89E-04 1. 44 E-03 1.90E-03
~~. Water 8.97E-06 8.97E-06 8.97E-06 8. 97E-06 TOTAL: 0.113 0.114 0.115 0.115 (area / year)~~
Reviewing these tables, the calculated limiting doses for both the maximally exposed individual and the inadvertent intruder occur for the adult age group. These doses are: Maximally Exposed Individu!1: 0.072 ares / year Inadvertent Intruder: 0.115 ares / year E-40
0 i APPENDIX F BASIS FOR SETTING CONCENTRATION LIMITS AND ACTIVITY LIMIT FOR DISPOSAL OF SLUDGE i , e e 9 4 4 E-41
Analyses of previously disposed sewage sludge have identified six different All six radionuclides did not occur in each radionuclides in the sludge.Therefore, it is difficult to determina a single concentrati disposal. limit for regulating the disposal of the sludge from the storage tanks. To provide a basis to regulate the disposal of the sewage slu N Cg
~~$f0 3 1 ^ mpy I I where N = number of different radionuclides identified in the sewage sludge.~~
C = concentration of the ith radionuclide in the 9 sewage sludge. HPC 9 =sewage the NPC value sludge, ofinthe as listed ith radionuclide 10 CFR Part 20 in the Appendix B Table II, Column 2. If this criteria is set, the sewage sludge say be disposed of by land spread-ing provided the dose calculations (as identified in Appendix E) indicate dose rates within the prescribed limits. The attachment to this Appendix details calculations Theperformed calculationstoare determine
~~~ doses from four radionuclides identified in the sludge.~~
based on an identified concentration equal to 10% of the 10 CFR Part 20,The ca Appendix B, Table II, Coluen 2 valves. in Appendix E along with the exposure pathways identified f a Appendix 0 to determine the dose rates. These calculations indicate the use of this methodology will maintain radiation doses within the appropriate limits. The maximum allowable activity disposed of per year per acre is calculated utilizing 10% of the MPC value,10 CFR Part 20, Appendix B, Table II, Column 2, Volume Ifait per acre has been proposed at 4,000 gallons / acre / year. for Co-58. Then, 3.785.43 cc/ gallon 1.0E-05 pCi/cc
~~4,000 gallons / acre / year x~~
~~= 151.4 pC1/ acre / year 9~~
E-42
Cs-134 Concentration in Sludge: 9.0E-07 sci /m1 Concentration Activity Ground Plane Sludge Volume Concentration (pCf/cm2) (pCf/cm3) (pC1) Hallons) (cm3) __
~
5.68E+07 9.00E-07 5.1AE+01 2.53E-07 15000 External Exposure y Dose Factor Ground Plane Concentration y Dose Rate (mres/hr. per pCi/m2) (pci/m2) (arem/ year) i 1.20E-08 2.53E+03 2.66E-01 2.66E-01 ares / year j Continuous Occupancy: Realistic Occupancy: 1.94E-03 ares / year l
)
Meat & Milk Pathway , Activity in Activity in Concentration in Concentration in Concentration Meat (pCi/kg) in Soil (pCi)_ Feed (pCl) Feed (pCi/Ka) Milk (pCi/1) 5.11E-01 2.75E+01 1.65E+01 5.50E+00
~~.. 5.22E+01 Milk Dose Rates (arem/ year)~~
~~Infant Child Teenacer Adult 3.87E-01 4.41E-01 6.03E-01 6.19E-01 Meat Oose Rate (aree/ year) Infant Child Teenacer Adult~~
- 1.83E-02 3.27E-02 7.32E-02 Vecetable Pativvay soil Volume Soil Mass Concentration Concentration Ac.tivity in Vecetables (oci/Ka)
(pci) (cm3) (Ko) in Soil (oci/Kc) 4.00E+06 1.28E+01 1.28E-01 l5.11E+01 3.08E+09 E-43
Vegetable Pathway Dose Rates (arem/ygar) Child Teenacer Adult Infant
- 2.90E-03 3.98E-03 4.34E-03 Inhalation Pathway Air Concentration Ground Plane K Concentration (pCi/m2) (m~s) (pCi/m3) 2.53E+03 1. 0E-05 2.53E-02 Inhalation Pathway Dose Rates (area / year)
Infant _ Child Teenacer Aoult Continuous occupancy 1.88E-03 5.68E-03 1.39E-02 1.84E-02 1.38E-05 4.15E-05 1.01E-04 1. 35E-04 Realistic Occupancy Release to Lake Michigan , Activity DFjj DFCo-60 Co-60 eq. activity (pCi) (pCi) 5.11E+01 2.56E+01 1.31E+03 6 mrem, 1.31E+03 1 Ci . = 8.29E-05 aren 94.7 C1 1.0E+06 pC1 Maximally Exposed Individual Infant Child Teenacer Adult ,
1. 94E-03 1.94E-03 1.94E-03 1.94E-03 External 6.19E-01 Milk 3.87E-01 4.41E-01 6.03E-01
- 1.83E-02 3.27E-02 7.32E-02 Meat 4.34E-03 Vegetable - 2.90E-03 3.98E-03 1.38E-05 4.15E-05 1. 01E-04 1.35E-04 Inhalation 8.29E 8.29E-05 i
Water 8.29E-05 8.29E-05 3.89E-01 4.64E-01 6.42E-01 6.99E-01 Totals: Inadvertent Intruder Infant Child Teenacer Adult 2.66E-01 2.66E-01 2.66E-01 2.66E-01 External 4.34E-03 Vegetable - 2.90E-03 3. 98E-03 5.68E-03 1.39E-02 1.84E-02 Inhalation 1. 88E-03 8.29E-05 8.29E-05 Water 8.29E-05 8.29E-05 Totals: 2.68E-01 2.75E-01 2.84E-01 2.89E-01 E-44
l Cs-137 , Concentration in Sludge: 2.0E-06 pci/s1 Sludge Volume- Concentration Activity Ground Plane (Gallons) (cm3) (pCi/cm3) (pC1) Concentration (pC1/cm2) 15000 5.68E+07 2.00E-06 1.14E+02 5.62E-07 i l External Exposure y Dose-Factor Ground Plane Concentration y Dose Rate (ares /hr. Der pCi/st) (pci/m2) (ares / year)- l 4.20E-09 5.62E+03 2.07E-01 l I Continuous occupancy: 2.07E-01 area / year l Realistic Occupancy: 1.51E-03 area / year Meat & Milk Pathway ! Activity in Activity in Concentration in Concentration.in Concentration fn soil (pCi) Feed (pci) Feed (pCi/Kg) Milk (pCi/1) Meat (pCi/ko) l . 1.14E+02 1.14E+00 6.'13E+01 3.68E+01 1.23E+01 Milk Dose Rates (aren/ year) Infant Child Teenaaer Adult l l 5.26E-00 5.61E-01' 7. 64E-01 8.15E-01 i I MeatOoseRate(area /yead Infant Child Teenager , Adult 2.33E-02 4.15E-02 9.56E-02 Vegetable Pathway Activity soil Volume Soil Mass Concentration Concentration (uti) (Cm3) (Ko) in Soil (DCi/Ka) in Vegetables (pCi/Kg) 1.14E+02 3.08E+09 4.00E+06 2.85E+01 2.85E-01 l t . E-45
Vegetable Pathway Dose Rates (arem/ year) Infant _, Child Teenager Adult
~~- 3.69E-03 5.03E-03 5.70E-03 w~~
Inhalation Pathway Ground Plane K - Air Concentration Concentration (pci/m2) (m'2) (pCf/m3) - 5.62E+03 1.0E-05 5.62E-02 Inhalation Pathway Dose Rates (arem/ year) Infant Child Teenager Adult Continuous Occupancy 2.56E-03 7.22E-03 1.75E-02 2.41E-02 Realistic Ocevaancy 1.87E-05 5.27E-05 1.28E-04 1.76E-04 Release to Lake Michigan Activity DF9 /0F Co-60 Co-60 eq. activity (pCi) (pCi) . 1.14E+02 1.51E+01 1.72E+03 6 mrem, . 1.72E+03 , 1 Ci . = 1.09E-04 mrem 94.7 C1 1.0E+06 pCi
.llaximally Exposed Individual Infant Child Teenager Adult External 1.51E-03 1.51E-03 1.51E-03 1.51E-03 Milk 5.26E-01 5.61E-01 7. 64E-01 8.15E-01 Meat -
~~2. 33E-02 *.15E-02 5.70E-03 Vegetable -~~
3.69E-03 5.03E-03 5.70E-03 Inhalation 1.87E-05 5.27E-05 1. 28E-04 1.76E-04 Water 1.09E-04 1.09E-04 1. 09E-04 1.09E-04 Totals: 5.2EE-01 5.90E-01 8.12E-01 9.19E-01 Inadvertent Intruder Infant Child Teenager Adult External 2.07E-01 2.07E-01 2.07E-01 2.07E-01 Vegetable - 3.69E-03 5. 03 E-03 5.70E-03 Inhalation 2.56E-03 7.22E-03 1.75E-02 2.41E-02 Water 1.09E-04 1.09E-04 1.09E-04 1.09E-04 Totals: 2.10E-01 2.18E-01 2.30E 2.37E-01 I E-46
Co-58 concentration in Sludge: 1.00E-05 pCi/ml Sludge Volume Concentration Activity Ground Plane (Gallons) (em3) (uct/cm3) (pC1) Concentration (pCi/cm2) 15000 5.68E+07 1.00E-05 5.68E+02 2.81E-06 External Exposure y Dose Factor Ground Plane Concentration y Dose Rate (ares /hr. per pCi/m2) (pCf/m a ) (aree/ year) 7.00E-09 2.81E+04 1.72E+00 Continuous occupancy: ' 1.72E+00 ares / year Realistic Occupancy: 1.26E-02 aren/ year Meat & Milk Pathway Activity in Activity in Concentration in Concentration in Concentration in Soil (pci) Feed (pCi) Feed (pci/Ka) Milk (pci/1) iteat (pCi/ko)- 5.68E+02 5.34E+00 2.87E+02 1.44E+01 1.87E+02 Milk Dose Rates (eres/ year) Infant Child Teenacer Adult 4.27E-02 2.62E-02 1.29E-02 7.45E-03 Meat Dose Rate (aree/ year) Infant Child Teenacer Adult 4.22E-02 2.72E-02 3.44E-02 Vegetable Pathway Activity soil Volume Soil Mass Concentration Concentration (uct) (Cm3) (Ko) in Soil (DCi/Ko) in Vegetables (pCi/Ka) 5.68E+02 3.08E+09 4.00E+06 1.42E-04 1.33E+00
~.
E-47 n
1 Vecetable Pathway Dose Rates (crem/ year) l ( Infant Child Teenacer Adult 2.05E-03 1.01E-03 6. 22E-04 Inhalation Pathway Ground Plane X Air Concentration Concentration (pci/m2) (m'2 ) (pCI/m3) 2.81E+04 1.0E-05 2.81E-01 _ Inhalation Pathway Dose Rates (aree/ year) Infant Child Teenacer Adult' Continuous Occupancy 5.11E-04 8.E9E-04 7. 80E-04 5.82E-04 Realistic Occupancy 3.74E-06 6.49E-06 5.70E-06 4.25E-06 Release to Lake Michigan Activity DF9 /DF Co-60 eg. activity (pC1) Co-60 (pCi) , 5.68E+02 3.54E-01 2.01E+02 6 arem 1 Ci 94.7 C1, , 2.01E+02 pCi , 1.0E+06 pCi. = 1.27E-05 arem Maximally Exposed Individual Infant Child Teenager Adult External 1.26E-02 1.26E-02 1.26E-02 1.26E-02 Milk 4.27E-02 2.62E-02 1.29E-02 7. 45E-03 Meat - 4.22E-02 2.72E-02 3.44E-02 Vegetable - 2.0$E-03 1.01E-03 6.22E-04 Inhalation 3.74E-06 6.49E-06 5.70E-06 4.25E-06 Water 1.27E-05 1.27E-05 1.27E-05 1.27E-05 Totals: 5.53E-02 8.31E-02 5.07E-02 5.51E-02 Inadvertent Intruder Infant Child Teenager Adult External 1.72E+00 1.72E+00 1.72E+00 1.72E+00 Vegetable - 2.05E-03 1.01E-03 6.22E-04 Inhalation 5.11E-04 8.89E-04 7.80E-04 5.82E-04 Water 1.27E-05 1.27E-05 1.27E-05 1.27E-05 Totals: 1.72E+00 1.72E+00 1.72E+00 1.72E+00 E-48
Co-60 . Concentration in Sludge: 5.0E-06 pCi/mi Sludge Volume Concentration Activity Ground Plane , (Gallons)- (cm3) (pCf/cm3) (pC1) Concentration (uct/cm2) 15000 5.68E+07 5.00E-06 '2.84E+02 1.41E-06 External Exposure y Dose Factor Ground Plane Concentration y Dose Rate (mres/hr. per pC1/ma ) (oCi/s2) (ares / year) 1.70E-08 1.41E+GJ 2.09E+00 Continuous occupancy: 2.05d+00 area / year Realistic Occupancy: 1.53E-02 area / year Meat & Milk Pathway . . . Activity in Activity in Concentration in Concentration in Concentration in Soil (pC1) Feed (pC1) Feed (pCi/Kg) Milk (pCf/1) Meat (pCi/kg) 2.84E+02 2.67E+00 1.44E+02 7.18E+00 9.33E+01 Milk Dose Rates (area / year) Infant Child Teenacer Adult 6.04E-02 3.70E-02 1.82E-02 1.05E-02 Heat Dose Rate (area / year) Infant Child Teenacer Adult 5.97E-02 3.84E-02 4.84E-02 Vegetable Pathway Activity Soil Volume Soil Mass Concentration Concentration i (uci) (Cm3) . (Ko) in Soil (oci/Ko) in Vegetables (pCi/Ka) 2.84E+02 3.08E+09 4.00E+06 7.10E+01 6.67E-01 E-49
)
~~Vegetable Pathway Dose Rates (arem/ year) I Infant Child Teenager Adult ,~~
- 2.91E-03 1.44E-03 8.82E-04 Inhalation Pathway Ground Plane X Air Concentration Concentration (oci/m2) (m~2) (pci/m3) 1.41E+04 1.0E-05 1.41E-01 Inhalation Pathway Dose Rates (ares / year)
Infant Child Teenager Adult Continuous Occupancy 1.66E-03 3.19E-03 2.80E-03 2.09E-03 Realistic Occupancy 1.21E-05 2.33E-05 2.05E-05 1.53E-05 Release to Lake Michioan Activity 0F9/DF Co-60 Co-60 eq. activity (uti) (uct) 6 mrem 2.84E+02pCi , 1 Ci . = 1.80E-05 arem 94.7 Ci 1.0E+06 pC1 l Maximally Exposed Individual Infant Child Teenager Adult External 1. 53 E-02 1.53E-02 1.53E-02 1.53E-0? Milk 6.04E-02 3.70E-02 1.82E-02 1.05E-02 Heat - 5.97E-02 3.84E-02 4.84E-02 Vegetable - 2.91E-03. 1.44E-03 8.82E-04 Inhalation 1.21E-05 2.33E-05 2.05E-05 1.53E-05 Water 1.80E-05 1.80E-05 1.80E-05 1.80E-05 Totals: 7.57E-02 1.15E-01 7. 34 E-02 7.51E-02 Inadvertent Intruder Infant Child Teenager Adult i 4 External 2.09E+00 2.09E+00 2.09E+00 2.09E+00 i Vegetable - 2.91E-03 1.44E-03 8.82E-04 Inhalation 1.66E-03 3.1SE-03 2.80E-03 2.09E-03 Water 1.80E-05 1.80E-05 1.80E-03 1.80E-03 Totals: 2.09E+00 2.10E+00 2.10E+00 2.'09E+00 E-50 l '-- --- - - - - - - _ _ - _ _ _ _ _ - - _ - - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __________________________A
4 h APPENDIX G CALCULATIONAL METHODOLOGY FOR DETERMINING EXTERNAL DOSE RATES FROM RADIONUCLIOES AFTER INCORPORATION INTO SOIL 1
~~'I E-51~~
Wisconsin Electric utilizes QAD, a nationally The recognized computer QAD computer code, code utilizes a to perform shielding and cose rate analyses. point kernel methodology to calculate the dose rate at a specified point due to a given source of radiation. QAD will be used to calculate the dose rate due to standing on a plot of land utilized for sludge disposal after the radionuclides have been incorporated into the plot by plowing. The following parameters will be used in the calculation:
The total Activity from all previous disposals will be corrected for radiological decay and used as the radio-nuclide source term.

Appropriate values will be used ta represent the surface area of the plot.

The radionuclides will be assumed to be incorporated uniformly into the top six inches of soil. .

The dose rate will be calculated at a height of I seter above the ground plane at a depth of 5 centimeters in tissue. (Regulatory Guide 1.109 values).

The density of the soil will be assumed to be 1.3 grams /
cubic centimet6r. This calculated dose rate will be used to assess the radiological consequences of past disposals in conjunction with the consequences of proposed future disposals. The total radiological dose consequence of the past and the pro-posed disposal will be compared to the applicable limits to insure the dose is maintained at or below the limits. \ l \ E-52
i NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 OFFSITE DOSE CALCULATION MANUAL 1 i APPENDIX F l Modifications to the Wisconsin Electric submittal to the United States Nuclear Regulatory Commission dated October 8,1987 (VPNPD-87-430, NRC-87-104), Disposal by Land Application of Sewage Sludge Containing Minute Quantities of Radioactive Material Page F-1 ___W
I ODCM NUCLEAR POWER BUSINESS UNIT OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 OFFSITE DOSE CALCULATION MANUAL Modification #1 to NRC Submittal CHANGE TO ORIGINAL StJBMITTA'. Section 3.2, Disposal Procedure (page 3) Section 3.3, Ackninistrative Procedure (page 4) The requirements for sludge cheracterization (the determination of the chemical and physical propertier of the sludge) contained in the sections referenced above are modified to sllow characterization of the sludge on an annual basis. BASIS / EXPLANATION The October 8, 1987 submittel to the USNRC for permission to dispose of sewage treatment sludge containing minute quantities of radioactive material requires that, " prior to disposal the waste stream will be monitored to determine the physical and chemical properties of the sludge. ... Subsequent to the sub-mittal and the approval by the NRC, a new Wisconsin Pollutant Discharge Elimination System (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 Management Plan specify an annual required frequency for the evaluation of the sludge characteristics. 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 of special analytical standards are required to complete the characterization study. The preparation of these standards, sample preparation, and the actual analyses are all manpower intensive and difficult to perform on a timely basis. This has led to requiring overtime for Lab Services personnel and support from outside companies. In order to better utilize the resources of Lab Services while maintaining the requirements of the WPDES pe mit, the frequency of sludge characterization in the October 8,1987 submittal to the NRC should be changed to an annual requirement. This change in the required frequency for detemination of the sludge characteristics does not change the requirement to analyze the sewage sludge for radionuclide content or perform dose evaluations ' prior to each disposal. Page F-2
NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 OFFSITE DOSE CALCULATION MANUAL APPENDIX G Modifications to the Wisconsin Electric submittal to the United States Nuclear Regulatory Commission dated October 8,1987 (VPNPD-87-430, NRC-87-104), Disposal by Land Application of Sewage Sludge Containing Minute Quantities of Radioactive Material. 1 l Page G-1
NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 OFFSITE DOSE CALCULATION MANUAL Modification #2 CHANGE TO ORIGINAL SUBMITTAL Section 3.3, Administrative Procedures (Page E-10) The limitation on the annual volume of sludge disposal per acre contained in the section referenced above is modified to allow unlimited disposal provided the other requirements of this submittal are met. BASIS / EXPLANATION The October 8,1987, submittal to the USNRC for permission to dispose of sewage treatment sludge containing minute quantities of radioactive material requires that "the annual disposal rate for each of the approved land spread sites will be limited to 4,000 gallons / acre, provided WDNR chemSal composition, NRC dose guidelines, and concentration and activity limits are maintained within the appropriate values." The original requirement to limit sewage sludge disposal to 4,000 gallons per acre is based on the assumption that the sewage sludge is contaminated with Co-58 at a concentration that is ten percent of the 10 CFR Part 20 Appendix B Table 2 Column 2 value. Past sewage sludge disposal I experience has shown that the sludge may or may not be contaminated and, ifit is, at concentrations far below ten percent of the perfonned prior to each sewage sludge disposal. With the removal of some of the land spread sites due to their use as a storage site for dry storage of spent fuel, this requirement is limiting our ability to dispose of the sewage sludge on the remaining approved land spread sites. This removal of the annual volume of sewage sludge that may be disposed of per acre on approved land spread sites does not change the requirement to analyze the sewage sludge for radionuclide content or perform dose evaluations prior to each disposal. This change was evaluated under SER 95-057, " Removal oflicensee Commitment Involved With Sewage Sludge Disposal," 4/20/95. 4 I Page G-2
NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 OFFSITE DOSE CALCULATION MANUAL APPENDIX H I Modifications to the Wisconsin Electric submittal to the US Nuclear Regulatory Commission dated October 8,1987 (VPNPD-87-430, NRC-87-104), Disposal by Land Application of Sewage Sludge Containing Minute Quantities of Radioactive Material. l l Page H-1
NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 OFFSITE DOSE CALCULATION MANUAL MODIFICATION #2
~~Depth to groundwater and bedrock shall be greater than 3 feet from the land surface elevation during use of any site.~~
~~Sludge shall not be land spread in a floodway.~~
Sludge shall not be land spread within 50 feet of a property line road or ditch unless the sludge is incorporated with the soil, in which case a minimum separation distance of at least 25 feet is required.
~~The pH of the sludge-soil mixture shall be maintained at 6.5 or higher.~~
Low areas of the approved fields, subject to seasonally high ground-water levels, are excluded from the sludge application.

Crops for human consumption shall not be grown on the land for up to one year following the application of the sludge.
The sludge shall be plowed, disked, injected or otherwise incorporated inco the surface soil layer at appropriate intervals. The flexibility implied in the latter provision for soil incorporation is intended to allow for crops which require more than a one year cycle. For the Point Beach disposal sites, alfalfa is a common crop which is harvested for several years af ter a single planting. Sludge disposal on an alf alfa 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, however, plowing (or disking or other method of . injection and mixing to a nominal depth of 6 inches) shall be done prior to planting any new crop, regardless of the crop. 3.3 Administrative Procedures Complete records of each disposal will be maintained. These records will include the concentration of radionuclides in the sludge, the total volume of sludge disposed, the total activity, the plot on which the sludge was applied, the results of the chemical composition determinations, and all dose calculations. v.4 m' feb . The annjal will be Metteddisposal rate te ',000 for each g:Hent/ tere,ofprovided the approved WDHR land chemical spreadcomposi-sites tion MRC dose guidelines, and concentration and activity limits are l maintained within the appropriate values. The farmer leasing the site used for the disposal wiY be notified of the applicable restrictions placed on the site due to the land spreading of sewage sludge. 4.0 Evaluation of Envirormental Impact 4.1 Site Characteristics 4.1.1 Site Topography The disposal sites are located in the Town of Two Creeks in the northeast corner of Manitowoc County, Wisconsin, on the E-10 Page G-3
NUCLEAR POWER BUSINESS UNIT ODCM OFFSITE DOSE CALCULATION MANUAL Revision 10 April 3,1997 OFFSITE DOSE CALCULATION MANUAL l Modilication #3 to NRC Submittal l Chance to Oricinal Submittal l Section 3.2 of Attachment II of the October 8,1987 letter to the NRC contains the conunitment to perform a gamma isotopic analysis of sewage sludge samples prior to every sludge disposal on land surrounding PBNP. The analytical results are to be used to evaluate the dose consequences of the l radionuclides entering the environment via this disposal pathway. As described in ODCM Section 7, the requirement for a radioisotopic analysis of the sewage sludge prior to every disposal on land surrounding PBNP is modified if the sludge has been snown to be clean and there is no reason to believe that the sludge is contaminated. Basis / Explanation Small pCi quantities of PBNP licensed materials (Co-58/60, Cs-134/137, Cr-51, and Mn-54) were found in PBNP sewage treatment plant (STP) sludge. Pursuant to of 10 CFR 20.302(a), Wisconsin Electric applied to the NRC for permission to dispose of the licensed material by applying the sludge to Wisconsin Electric land surrounding PBNP. In the October 8,1987 application letter, Wisconsin Electric committed to gamma isotopic analysis of the sludge prior to every disposal in order to evahtate the dose consequences of this disposal and to compare radionuclide concentrations to the 10 CFR 20, Appendix B, maximum effluent conce-trations. However, such analyses are not required if the sludge does not contain licensed material. If there is no reason to believe that the sludge is contaminated and if there is no pathway from the RCA to the STP, then there is no reason to analyze the sludge for 3 radionuclides once it has been shown to be clean. Administrative controls and engineering modifications to PBNP have removed the pathway from the RCA to the STP as verified by subsequent
~~analyses of the sludge under conditions required to obtain the environmental LLDs. These analyses have not revealed radionuclides attributable to PBNP. Pursuant to NRC HPPOS-221, a substance is l~~
clean if analyses under analytical parameters necessary to achieve the environmental LLDs does not reveal any licensed material. These LLDs define how hard you have to look. Below this detection level,
". . .the probability of undetected radioactivity is negligible and can be disregarded when considering the j practicality of detecting such potential radioactivity from natural background. ." (Docket No. 50-206, i
letter to J. E. Dyer from L. J. Cunningham dated September 6,1991). Therefore the NRC criteria are ! met and there is no longer any reason to believe that the STP sludge is contaminated. However if plant i 1 conditions should change in a mannec compromising the NRC criteria, radiological analysis must be j l made prior to each STP sludge land application until such time that the clean criteria are satisfied l pursuant to subsequent NRC guidance. l r l Page H-2}}

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

50 kg/ day; QF Si

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

50 kg/ day; QF Si

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